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General Information or Other | Event Number: | 39404 | |
REP ORG: | SPECTRUM TECHNOLOGIES | NOTIFICATION DATE: | 11/25/2002 |
LICENSEE: | CUTLER-HAMMER | NOTIFICATION TIME: | 16:25[EST] |
CITY: SCHENECTADY | REGION: 1 | EVENT DATE: | 11/25/2002 |
COUNTY: | STATE: MN | EVENT TIME: | [EST] |
LICENSE#: | AGREEMENT: Yes | LAST UPDATE DATE: | 11/25/2002 |
DOCKET: | PERSON | ORGANIZATION | |
JOHN ROGGE | R1 | ||
NRC NOTIFIED BY: | BILL WILLIS | ||
HQ OPS OFFICER: | HOWIE CROUCH | ||
EMERGENCY CLASS: | NON EMERGENCY | ||
10 CFR SECTION: | |||
CCCC 21.21 | UNSPECIFIED PARAGRAPH |
EVENT TEXT
PART 21 INITIAL NOTIFICATION - CUTLER-HAMMER A200 NEMA SIZE 1 STARTERS
"Equipment Identification: Starter, Non-Reversing, Size 1, 6OOVAC, 3 Pole,
W/125VDC coil, Westinghouse/Cutler-
Hammer P/N A2OOM1CS, Type B Thermal Overloads, Ambient Compensated, Manual Reset
Only
"In March 2002, Spectrum Technologies provided 20 Class 1E safety related
Cutler-Hammer A200 NEMA
Size 1 starters to Rochester Gas & Electric Company - Ginna Station. We
had purchased the starters as
commercial grade items from Cutler-Hammer, and dedicated them per EPRI NP5652,
method 1, Special
Tests and Inspections. This dedication successfully verified the following critical
characteristics:
Markings
Dimensions and Configuration
Electrical Functional Attributes, Including:
Insulation Resistance
Current Carrying Capacity
Minimum Pickup and Drop Out Voltage
Time Current Characteristics of Overload Relay
"Ginna Station recently advised us that one of the starters had experienced
an open phasing failure. They reported that they noted no current flow on one
phase when measured with a clamp-on ammeter, and that current started to flow
when the hand pressure was applied to the moving plunger extension that protrudes
out the top of the starter. They also noted that the overall travel of the plunger
appeared to be less than that noted on a similar older vintage starter. They
provided the failed starter and the older vintage starter to us for our investigation.
The continuity of all phases was successfully verified, along with the magnetic
pull force of the coil, which was comparable to the older vintage starter. We
then mounted the failed starter on a vertical plate in a horizontal (worst case)
orientation, energized the coil and loaded the main contacts to 27 amps. This
condition was maintained until the temperature stabilized with the highest temperature
recorded on the terminals (i.e., 59 degrees C to 63 degrees with ambient at
20.3 degrees C). None of this testing performed could duplicate the single phasing
condition observed by Ginna Station. We verified that the total stroke of the
failed starter was less than that of the earlier vintage starter by as much
as 0.059" by our
11/25/2002 U.S. Nuclear Regulatory Commission Operations Center Event Report
Page 2
General Information or Other (PAR) Event# 39404
measurement.
"The failed starter and the earlier vintage starter were provided to Cutler-Hammer
for an OEM evaluation. The results of the OEM evaluation was e-mailed to our
Cutler-Hammer distributor and provided to us on November 21, 2002, a copy is
attached. This information has been provided to Ginna Station, and they advised
us today (November 25, 2002) that the starters have been installed in 11 safety
related locations, as follows:
MOV-857A, Residual Heat Removal Pump A Discharge
MOV-4616, Service Water Isolation in Auxiliary Building (Open & Close Circuit)
MOV-860C, Containment Spray Pump B Discharge
MOV-813, Component Cooling Water Isolation to Reactor Support Coolers (Open
& Close Circuit)
MOV-700, Residual Heal Removal Pump Suction from Loop A Holt Leg
MOV-878A, Safety Injection Discharge to Loop B
MOV-856, Residual Heat Removal Suction from Refueling Water Storage Tank
MOV-4780, Service Water Isolation in Screenhouse (Open & Close Circuit)
"We are currently expediting Cutler-Hammer to complete an audit at their
manufacturing facility to identify the magnitude of this condition and specify
the date codes effected. We are also expediting Cutler-Hammer to obtain acceptable
replacements for the starters provided to Gin na Station."
SPECTRUM TECHNOLOGIES
112 Erie Blvd., Schenectady, New York 12305
Tel:(518)382-0056
Fax: (518)382-0283
FAX CONTROL SHEET
DATE: November 25 2002
Number of pages including this sheet 4
TO. Name: NRC Operations Center
Phone#: (301)816-5100
Fax#: (301)816-5151
FROM: Name: Bill Willis Tel:(518)382-0056
Fax: (518) 382-0283
COMMENTS: Part 21 Initial Notification - Cutler-Hammer A200 NEMA Size 1 Starters
Equipment Identification: Starter, Non-Reversing, Size 1, 6OOVAC, 3 Pole, W/125VDC
coil,
Westinghouse/Cutler-Harnmer P/N A2OOM1CS, Type B Thermal
Overloads, Ambient Compensated, Manual Reset Only
In March 2002, Spectrum Technologies provided 2o Class 1E safety related Cutler-Hammer
A200 NEMA
Size 1 starters to Rochester Gas & Electric Company - Ginna Station. We
had purchased the starters as
commercial grade items from Cutler-Hammer, and dedicated them per EPRI NP5652,
method 1, Special
Tests and Inspections. This dedication successfully verified the following critical
characteristics:
Markings
Dimensions and Configuration
Electrical Functional Attributes, Including:
Insulation Resistance
Current Carrying Capacity
Minimum Pickup and Drop Out Voltage
Time Current Characteristics of Overload Relay
Ginna Station recently advised us that one of the starters had experienced an
open phasing failure. They reported that they noted no current flow on one phase
when measured with a clamp-on ammeter, and that current started to flow when
the hand pressure was applied to the moving plunger extension that protrudes
out the top ofthe starter. They also noted that the overall travel ofthe plunger
appeared to be less than that noted on a similar older vintage starter. They
provided the failed starter and the older vintage starter to us for our investigation.
The continuity of all phases was successfully verified, along with the magnetic
pull force of the coil, which was comparable to the older vintage starter. We
then mounted the failed starter on a vertical plate in a horizontal (worst case)
orientation, energized the coil and loaded the main contacts to 27 amps. This
condition was maintained until the temperature stabilized with the highest temperature
recorded on the terminals (i.e., 59 to 63 degrees C with ambient at 20.3 degrees
C). None of this testing performed could duplicate the single phasing condition
observed by Ginna Station. We verified that the total stroke of the failed starter
was less than that of the earlier vintage starter by as much as 0.059"
by our measurement.
The failed starter and the earlier vintage starter were provided to Cutler-Hammer
for an OEM evaluation. The results of the OEM evaluation was e-mailed to our
Cutler-Hammer distributor and provided to us on November 21, 2002, a copy is
attached. This information has been provided to Ginna Station, and they advised
us today (November 25, 2002) that the starters have been installed in 11 safety
related locations, as follows:
MOV-857A, Residual Heat Removal Pump A Discharge
MOV-4616, Service Water Isolation in Auxiliary Building (Open & Close Circuit)
MOV-860C, Containment Spray Pump B Discharge
MOV-813, Component Cooling Water Isolation to Reactor Support Coolers (Open
& Close
Circuit)
MOV-700, Residual Heat Removal Pump Suction from Loop A Holt Leg
MOV-878A, Safety Injection Discharge to Loop B
MOV-856, Residual Heat Removal Suction from Refueling Water Storage ~alll(
MOV-4780, Service Water Isolation in Screenhouse (Open & Close Circuit)
We are currently expediting Cutler-Hammer to complete an audit at their manufacturing
facility to identify
the magnitude of this condition and specify the date codes effected. We are
also expediting Cutler-
Hammer to obtain acceptable replacements for the starters provided to Ginna
Station.
If you have any questions, please don't hesitate to call, fax, or e-mail us.
Assuring you of our best intentions.
William R. Willis
Vice President, QA
Spectrum Technologies Utilities Services USA, Inc.
112 Erie Blvd., Suite 3
Schenectady, NY 12305
Tel: (518) 382-0056
Fax: (518) 3~2-0283
cc: Gerald Bishoping, Ginna Station
(585) 771-3304
GE Nuclear Energy
November 18,2002
02-O9NRC.DOC
MFN 02-089
Document Control Desk
United States Nuclear Regulatory Commission
One White Flint North
11555 Rockville Pike
Rockville, Maryland 20852-2738
Subject: Final Report, Stabillty Option III: Possible Successive Confirmation
Count Resets Not Reportable
Reference: MFNO2-063, Stability Option III: Possible Successive Confirmation
Count
Resets, lOCFR Part 21 60 Day Interim Report, October 1, 2002
This letter provides closure of the reference §21.21(a)(2) 60 Day Interim
Report
notification for plants that have selected stability long-term solution Option
III. The
closure is that GE Nuclear Energy (GE) has determined that this is not a reportable
condition, however, GE recomtnends that the BWR Owners' Group Detect & Suppress
Committee evaluate the need to change the minimum allowable value for period
tolerance
used in the Oscillation Power Range Monitor (OPRM).
As described in the reference notification, the potential problem was associated
with the
algorithm that provides the licensing basis Minimum Critical Power Ratio (MCPR)
Safety Limit protection for stability Option III. The algorithm determines Successive
Confirmation Count (SCC) of an oscillating power signal. A reactor trip is generated
when SCC and osciUation amplitude reach their trip setpoints in accordance with
the
Option III and reactor protection system. configuration. The concern was that
the
oscillation period could change for an oscillation that initiates while reactor
state
conditions are changing towards eqrnlibrium state (e.g., following a two-recirculation
pump (2RPT) trip event) and cause the SCC to prematurely reset, thus delaying
the
reactor scram.
A reactor trip signal is generated when the OPRM SCC setpoint and the amplitude
setpoint are reached or exceeded for at least one OPRM cell in each trip system
channel
required to generate the trip signal (e.g., one-out-of two taken twice). The
Period Based
Detection Algorithm (PBDA) determines the SCC for each OPRM cell. When an
oscillation in an OPRM cell signal is detected by the PBDA it sets the base
period for that
cell. The period tolerance is used to determine if the period of each subsequent
oscillation is within an acceptable difference from the base period. The acceptable
range
November l8,2002
02-O9NRC.DOC
MFN 02-089
for period tolerance specified in stability Option Ill licensing topical reports
is 100 to 300
msec. A period tolerance of 50 msec has been approved for OPRM systems that
have a
25 msec sampling frequency.
GE evaluated this concern with TRACG simulations of a 2RPT event for typical
Option
III plants for reasonably limiting Extended Power Uprate (EPU) and Maximum Extended
Load Line Limit Analysis MELLLA) conditions. TRACG calculates channel power,
which can be evaluated as representative of an OPRM cell signal through the
hot channel
oscillation reload licensing methodology, and evaluated by the PBDA for successive
confirmation counts.
PBDA resets occur when the difference between the current period and the base
period
exceeds the period tolerance. The worst case would be if a spurious SCC reset
occurred
immediately before the amplitude trip setpoint was reached. For this case, that
cell would
not generate a trip signal until SCC had again counted up to the trip setpoint,
which could
be a delay of 10 to 12 seconds.
GE evaluated the potential for SCC spurious resets for period tolerance values
of 50, 100
and 150 msec. In general, more frequent spurious resets occur with shorter period
tolerance. However, the spurious SCC reset does not occur at the same time for
all the
OPRM cells in an OPRM channel. Some OPRM cell resets delay the trip generated
by
that cell, while others reset at sufficiently early times that they have again
counted up to
exceed the count setpoint when the amplitude setpoint is reached and others
do not reset
at all. Only one OPRM cell trip in an OPRM channel is sufficient to cause an
OPRM
channel trip, and each OPRM channel typically has 18 to 33 OPRM cells. In addition,
typical core loading schemes ensure that multiple OPRM cells respond very near
the peak
oscillation magnitude. The analysis concluded that even though spurious resets
occur,
these resets are not expected to significantly delay reactor scram. Therefore,
the currently
licensed PBDA provides adequate protection against a MCPR Safety Limit violation
for
instabilities initiated during a fast transient such as a 2RPT event. Therefore,
this does
not represent a Reportable Condition under l0CFR21.2l.
Even though this is not a reportable condition, the potential for some OPRM
cells to
prematurely reset SCC for an instability initiated during a 2RPT is not consistent
with the
original design basis of the PBDA. The original design basis was that continuous
confirmation counts would occur for fully coupled neutronic/thermal-hydraulic
reactor
instability. Since this may not occur for a 2RPT with period tolerance values
of 50 and
100 msec, it is recommended that Option III plants evaluate the need to change
the minimum allowable value for period tolerance.
2
November18, 2002
02-O9NRC.DOC
MFN02-089
If you have any questions, please call me at (408) 925-5362
Sincerely,
Jason S. Post, Manager
Engineering Quality and Safety Evaluations
cc: S.D. Alexander (NRC-NRRIDISPIPSIB) Mail Stop 6 F2
J. W. Foster NRC-NRR/DlSP/PSIB) Mail Stop 12 H2
J. F, Klapproth (GE-NE)
H. J. Neems (GE-NE)
PRC File
Attachments:
1. Closure of 60 Day Interim Report per §21.21 (a)(2)
2. Previously Identified Potentially Affected Plants
3
November 18, 2002
02-09NRC.DOC
MFN 02-089
Attachment 1 Closure of 60 Day Interim Report per §21.21(a)(2)
(i) Name and address of the individual informing the Commission:
Jason S. Post, Manager, Engineering Quality & Safety Evaluation, GE Nuclear
Energy, 175 Cuntier Avenue, San Jose, CA 95125
(ii) Identification of the facility, the activity, or the basic component supplied
for such
facility or such activity within the United States which fails to comply or
contains
a defect:
Stability Solution Option III plants were previously identified as potentially
affected. These plants are listed in Attachment 2.
(iii) Identification of the firm constructing the facility or supplying the
basic
component which fails to comply or contains a defect:
GE Nuclear Energy, San Jose, California
(iv) Nature of the defect or failure to comply and safety hazard which is created
or
could be created by such defect or failure to comply:
It was determined that the defect or failure to comply is not associated with
a
safety hazard and does not lead to violation of the MCPR Safety Limit
(v) The date on which the information of such defect or failure to comply was
obtained:
August 2, 2002
(vi) In the case of a basic component which contains a defect or failure to
comply, the
number and locations of all such components in use at, supplied for, or being
supplied for one or more facilities or activities subject to the regulations
in this
part:
The previously identified potentially affected plants are listed in Attachment
2.
(vii) The corrective action which has been, is being, or will be taken; the
name of the
individual or organization responsible for the action; and the length of time
that
has been or will be taken to complete the action (note, these are actions
specifically associated with the identified Reportable Condition):
GE has communicated this concern to the BWR Owners' Group Potential Issues
Resolution Team (PIRT) and to the Stability Detect & Suppress Committee.
Even
though this does not represent a reportable condition, the potential for some
OPRM cells to prematurely reset SCC for an instability initiated during a 2RPT
is
not consistent with the original design basis of the PBDA. Since continuous
4
November l8,2002
02-09NRC.DOC
MFN 02-089
confirmations counts may not occur for an oscillation initiated following a
2RPT with period tolerance values of 50 and 100 msec, it is recommended that
Option III plants and the D&S Committee evaluate the need to change the
minimum allowable value for period tolerance.
(viii) Any advice related to the defect or failure to comply about the facility,
activity, or basic component that has been, is being, or will be given to purchasers
or licensees:
It is recommended that this issue be addressed by the BWROG D&S Committee
in their overall consideration of stability solution Option III performance
and reload licensing methodology revisions.
5
November 18, 2002
02-O9NRC.DOC
MFN 02-089
Attachment 2 - Previously Identified Potentially Affected Plants
Utility Plant
x AmerGen Energy Co. Clinton
AmerGen Energy Co. Oyster Creek
x Carolina Power & Light Co. Brunswick 1
x Carolina Power & Light Co. Brunswick 2
Constellation Nuclear Nine Mile Point 1
x Constellation Nuclear. Nine Mile Point 2
x Detroit Edison Co. Fenni 2
Dominion Generation Millstone 1
x Energy Northwest Columbia
Entergy Nuclear Northoast Fitzatrick
Entergy Nuclear Northeast Pilgrim
Entergy Operations, Inc. Grand Gulf
Entergy Operations, Inc. River Bend
Entergy Nuclear Northoast Vermont Yankee
Exelon Generation Co. CRIT Facility
x Exelon Generation Co. Dresden 2
x Exelon Generation Co. Dresden 3
x Exelon Generation Co. LaSalle 1
x Exelon Generation Co. LaSalle 2
x Exelon Generation Co. Limerick 1
x Exelon Generation Co Limerick 2
x Exclon Genetation Co. Poach Bottom 2
x Exelon Generation Co. Peach Bottom 3
x Exelon Generation Co. Quad Cities 1
x Exelon Generation Co. Quad Cities 2
x FirstEnergy Nuclear Operating Co. Perry 1
Nebraska Public Power District Cooper
Nuclear Management Co. Duane Arnold
Nuclear Management Co. Monticello
Pooled Equipment Inventory Co. PIM
x PPL Susquehanna LLC. Susquehanna 1
x PPL Susquohanna LLC Susquehanna 2
x Public Service Electric & Gas Co. Hope Creek
x Soutliern Nuclear Operating Co. Hatch 1
x Soutliern Nuclear Operating Co. Hatch 2
x Tennessee Valley Authority Browns Forry l
x Tennessee Valley Authority Browns Ferry 2
x Tennessee Valley Authority Browns Ferry 3
6