ML20210F422
| ML20210F422 | |
| Person / Time | |
|---|---|
| Issue date: | 07/27/1999 |
| From: | Stephen Dembek NRC (Affiliation Not Assigned) |
| To: | Richards S NRC (Affiliation Not Assigned) |
| References | |
| REF-GTECI-023, REF-GTECI-NI, TASK-023, TASK-OR TAC-MA4519, NUDOCS 9907300134 | |
| Download: ML20210F422 (30) | |
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!.Cf.iORANDUM TO: Stuart A. Richards, Director l
Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM:
Stephen Dembok, Chief Section 2 l
Project Directorate IV & Decommissio ing,
J.A Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
MEETING WITH THE PRESSURIZED WATER REACTOR OWNERS GROUPS TO DISCUSS GENERIC ISbuE 23, " REACTOR COOLANT -
PUMP SEAL FAILURE"(TAC NO. MA4519)
The Nuclear Regulatory Commission (NRC) held a meeting with the three pressurized water reactor (PWR) owners groups (i.e., Westinghouse Owners Group (WOG), Combustion Engineering Owners Group (CEOG) and Babcock and Wilcox Owners Group (B&WOG)) on July 14,1999, to discuss Generic issue 23 (GSI-23), " Reactor Coolant Pump Seal Failure."
The purpose of the meeting was to allow the owners groups an opportunity to provide any new information they have on reactor coolant pump (RCP) seal performance and for the NRC's Office of Nuclear Regulatory Research (REC) staff to provide information to the owners groups on the path being pursued to resolve GSI 23. A list of attendees is attached (Attachment 1).
Each of the three owners groups made a presentation on the RCP seal leakage issue. The slides from each of the presentations are attached (Attachments 2,3, and 4). The information presented was primarily a review of past work, with the exception of the results of a test performed on a Westinghouse type seal that was performed in conjunction with the licensing of Sizewell nuclear power plant several years ago. The test results showed low seal leakage with loss of cooling for approximately 15 minutes, which is consistent with the Westinghouse seal leakage predictions. The WOG agreed to provide more information on this test. The owners groups' position was fundamentally the same as it has been for the past 15 years. Specifically, the owners groups continue to believe the loss of RCP seal cooling is not risk significant because seal failure is not likely and failure will not result in gross leakage. Westinghouse assumes that the use of high temperature o-rings is all that is necessary to assure the RCP seals will not fail.
The RES staff brought the owners groups up-to-date on their GSI-23 resolution path. They used risk analysis techniques to assess the affect of RCP seal failure on station blackout (SBO) coping capability and the core damage frequency resulting from loss of component cooling water (CCW) and service water (SW) scenarios. They analyzed the 4m with 8-hour coping times and assessed the incremental risk from SBO ssquences involving RCP seal loss-of-1/ ;
coolant accidents (LOCA). The staff also noted that plants which can now cope with a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
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SBO will continue to do so. For loss of CCW and SW, they u:>ed information from the Individual Plant Evaluations to assess the frequency of losses of CCW and SW, and combined this with an NRC-developed model of RCP seal LOCA behavior on loss of seal cooling, to assess the core damage frequency from the sequences involving loss of CCW or SW, and RCP LOCA. This was done for select plants. The owners groups were interested in this approach and expressed a desire to meet with the staff to discuss the approach. The staff agreed to hold such a meeting in the near term and noted that GSI-23 is scheduled to be closed by December 1999. The RES staff's preliminary determination is that assuming the available seal failure model and the resulting "!arge" leak rate, most plants will show acceptable risk from loss of RCP seal cooling and will, therefore, require no additional actions as a result of GSI-23 resolution.
The following actions resulted from the meeting:
1.
The owners groups willinform individuallicensees of the staff's pa'h to resolution of GSI-23. In the process of doing this, if any licensee believes there is additional plant specific information that would be useful to the staff in performing the risk assessment (e.g., design improvements to the component cooling water system, improved attemate ac power capability that are not captured in the individual plant examination) that the staff may not be aware of, they should provide that information via their project manager.
2.
The WOG agreed to provide more information on the Sizewall test results and consider whether to provide a list of those plants that have or are planning to use the newer high temperature O-rings in the RCP seals in ordar to improve the seal performance.
3.
RES staff will work through the owners group project manager to establish a date for a future meeting in the near term to discuss (a) the initial results of their RCP seal leakage risk assessment grouping of plants with the owners groups, and (b) the plant specific infomistion discussed in item 1, above.
This completes staff action on TAC No. MA4519.
Attachments: 1. Attendance List
- 2. WOG Presentation
- 3. CEOG Presentation
- 4. B&WOG Presentation cc w/att 1: See next page
F t
h 1
. PWR Owners Groups cc w/att 1:
Mr. Charles B. Brinkman, Dis ector Mr. Nicholas Liparulo, Manager l
Washington Operations Equipment Design and Regulatory l
ABB-Combustion Engineering, Inc.
Engineering
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12300 Twinbrook Parkway, Suite 330 Westinghouse Electric Corporation Ruav;ile, Maryland 20852 Mail Stop ECE 4-15 l
P.O. Box 355 l
Mr. Gordon C. Bischoff, Project Director Pittsburgh, PA 15230-0355 CE Owners Group ABB Combustion Engineering Nuclear Mr. Andrew Drake, Project Manager Power Westinghouse Owners Group l
M.S. 9615-1932 Westinghouse Electric Corporation 2000 Day Hill Road Mail Stop ECE 5-16 Post Office Box 500 P.O. Box 355 i
Windsor, CT 06095 Pittsburgh, PA 15230-0355 Mr. Ralph Phelps, Chairman Mr. Jack Bastin, Director CE Owners Group Regulatory Affairs Omaha Public Power District Westinghouse Electric Corporation P.O. Box 399 11921 Rockville Pike Ft. Calhoun, NE 68023-0399 Suite 107 Rockville, MD 20852 Randy Hutchinson, Chairman B&WOG Executive Committee Mr. Hank Sepp, Manager Vice President Operations Regulatory and Licensing Engineering Arkansas Nuclear One Westinghouse Electric Corporation Entergy Operations, Inc.
PO Box 355 1448 S.R. 333 Pittsburgh, PA 15230-0355 Russellville, Arkansas 72801-0967 Mr. W. W. Foster, Chairman B&WOG Steering Committee Director of Safety Assurance Duke Power Company Oconee Nuclear Station PO Box 1439 Seneca, SC 29679 Mr. J. J. Kelly, Manager B&W Owners Group Services Framatome Technologies, Inc.
P.O. Box 10935 Lynchburg, VA 24506-0935 i
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NRC/PWR OWNERS GROUPS MEETING ON GSI 23 LIST OF ATTENDEES l
July 14,1999 NAME ORGANIZATION Jared Wermlel Office of Nuclear Reactor Regulation / Reactor Systems Branch (NRR/SRXB)
Eric Weiss NRR/SRXB Christopher Jackson NRR/SRXB Stephen Dembek NRR/ Division of Licensing Project Management Tim Collins NRR/ Division of Systems Safety and Analysis John Craig Office of Nuclear Regulatory Research/ Division of Engineering Technology (RES/DET)
Frank Cherny RES/DET Sher Bahadur RES/DET Jerry Jackson RES/DET Arthur Buslik RES/DRAA/PRAB Walt Rogers NRC/ Region 11 Cindy Pezze Westinghouse l
Tom Timmons Westinghouse Paul Pyle Westinghouse /WOG l
Louis Liberatori Consolidated Edison /WOG David Lounsbury PSE&G/WOG Maurice Dingler WCNOC/WOG Bob Jaquith ABB F.P. Ferraraccio ABB Paul Hijeck ABB/CEOG Ralph L. Phelps OPPD/CEOG John Link GPUN/B&WOG Karl Jacobs New York Power Authority Steve Mays Duke Energy / Catawba Dave Modetn NEl Bob Schomaker Framatome Tech.
Bob Coward MPR Associates Altheia Wyche SERCH Licensing /Bechtel Lynn Connor DSA Christer Dahlgren NUSIS l
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CEOG PRESENTATION USNRC and Joint Owners Group Meeting GenericIssue 23, "RCPSealFailure" July 14,1999 US Nuclear Regulatory Commission Rockville, MD
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l AGENDA INTRODUCTORY REMARKS P. Hijeck, CEOG Omce, ABB Combustion Engineering Nuclear Power REVEW OF RCP SEAL DESIGN, TESTING, & EXPERIENCE F. P. Ferraraccio, ABB Combustion Engineering Nuclear Power PRA CONSIDERATIONS R.Jaquith, ABB Combustion Engineering Nuclear Power CLOSING REMARKS P. Hijeck, CEOG Office, ABB Combustion Engineering Nuclear Power
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PURPOSE Provide a summary ofinformation to the NRCthatfurthers the informationpresentedin May,1994, that wail continue to demonstrateIhat:
(1) the RCP seal design in CEOGplants has a history ofsuperior performance with no failures.
and (2) the RCP seal-relatedoperationallimits andprocedures currently in-place at CEOGplants willassure continued superiorperformance."
)($$ Combustion Engineering Owners Group 3
i DEFINITION OF FAILURE "RCP sealfailure occurs when allstares ofthe seals have degraded to a point where excessive leakare
- occurs."
- Excessive leakage is defined to be at least 25 gpm j($$ Combustion Engineering Owners Group
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CEOG RCP SEAL FAILURE HISTORY l
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/kllll Combustion Engineering Owners Group DEFINITION OF DEGRADATION "RCP sealdegradation occurs when its operating conditions deviate sienificantiv from " normal" values, as defined by the seal vendor, which could eventually require seal replacement or repair topreclude sealfailure."
)(ljll Combustion Engineering Owners Group
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RCP SEAL DESIGN Seal Cartridge Vendors Byron Jackson (BJ)
- SU 3 plants p going to N-9000]
- N-9000 4 plants Bingham
- Balanced Stator 7 plants KSB p plants historically)
Alli combustion ensineerins owners aroup RCP SEAL DESIGN General Features Hydrodynamic seals 4 stages, including vapor seal (3 stages on KSB)
Equal pressure reduction / stage - each stage capable of full system pressure Normal Controlled Bleed-Ofi(CBO) flow,1-1.5 gpm Seal iajection not required (some plants have injection)
Stringent vendor QA programs Instrumented to monitor seal performance / leakage:
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- Individual stage pressure
- CBO flow
- CBO temperature
- First stage temperature
- Alarms on CBO temperature (some plants)
Alli! combustion ensineerins owners aroup
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RCP SEAL DESIGN Comparison Data Design Feature CEOG Westinghouse Number of Stages 4 (except KSB) 3 Type of Seals All hydrodynamic First stage hydrostatic All others hydrodynamic Pressure Breakdown Equal press./ stage
- Pressure reduction
. primarily by 1st stage SealInjection Not Required Required (Used by KSB)
Design CBO Flow 1 1.5 gpm 3 gpm (KSB,3 gpm)
- All stages espable of withstandieg full system pressure -including vapor seal
)($$ Combustion Engineering Owners Group RCP SEAL DESIGN TESTING j
Summarized from 1994 presentation.
j BJ, SUDesign SONGS, BASU seal nwatain integrity under loss dcov 1978
- 88*
BJ, SU Design St Lucie, ILI4U seal neuntaim integrity under loss or coy
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IM MM KSB Design 1983 3GB==s amiintain integrity under loss of ccwa foe orsealinjecdce conditions.
Bingham
- SCE, Imchem seals maintain integrity rollowing loss ors l
f Design 1986
""H'E BJ& Biagbam AECL, BLSU and Bingham seals maintain integrity under Designs 1986 extreme imperatun and pnasure coedm BJ, N-9000 1988 ILI N-9000 seals maintain integrity under SBO Design
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RCP SEAL EXPERIENCE All Designs 1995-1999 Seal Degradations Instances
- SU Design 5 Instances
- N-9000 Design 4 Instances
- Bingham 2 Instances
- KSB 2 Instances n Each was instance of single stage failure that was either monitored and run to next outage or was associated with an outage.
Loss of Seal Cooling
- No loss of CCW events
- 1 Loss of Seal Injection w/KSB design - No seal performance consequence
)($$ Combustion Engineering Owners Group n
RCP SEAL EXPERIENCE Sample of Operational Limits and Procedures ll RCP not operated when:
- More than one failed stage
- More than 5 minutes without CCW
- CBO temperature greater than 180'F
- Plant specific set oflimits defined
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RCP SEAL EXPERIENCE Summary of all Data 1975 -1999 No instance of seal failure Decreased instances of seal degradation (in all cases, leakage below SBO coping value of 25 gpm)
Absence of RCP seal failures indicates:
- Robust seal designs
- Strict adherence to operationallimits and procedures
- Sensitive instrumentation to small deviations s
"Minorproblems identified before they become major"
)(llll Combustion Engineering Owners Group u
PRA CONSIDERATIONS Seal Failure Probability CDF (Due to loss of RCP seal cooling) - given Loss of CCW CDF (Due to loss of RCP seal cooling)-given LOOP
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RCP Seal Failure is a Very Small Contributor to Risk f
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- 4 23 104 0
104 CDF +
4 CDF from RCP Seal Failure Acceptance Guidelines for Core Damage Frequency (CDF)
)(llll Combustion Engineering Owners Group a
SEAL FAILURE EVALUATION General Assumptions All four stages must fail to have a seal LOCA Stage failures subject to common cause failure and can be modeled by the Multiple Greek Letter Technique CEOG generic analysis performed for a 4-pump plant with a 4-stage seal l
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SEAL FAILURE PROBABILITY Multiple Greek Letter Technique Q = p
- T
- A
- P.,,
Q=
probability per demand of total seal failure given loss of cooling p=
conditional probability that the common event that causes components to fail will be shared by the second or more compcnents in addition to the first T=
conditional probability that the common event that causes the failure of two or more components will be shared by three or more components A=
conditional probability that the common event that causes the component if three or more components will be shared by four or more components P.,, = total failure probability of a stage due to all independent and common cause events
)(jjll Combustion Engineering Owners Group SEAL FAILURE EVALUATION Actual Experience l
20 Events Involving Loss of CCW To 1 or more RCPs at a CE Plant
- 85% CCW lsolation
- 15% Partial LOOP STau l
I Total Numbo. of pumps:
61 Total number of stages:
232 Number of stages failed:
4 P,, = 4 stage failures /232 stage exposures = 1.72E-2/ demand I
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SEAL FAILURE PROBABILITY (Given Loss of CCW) l Q = S
- T
- 6
- P, Values Estimated from CE RCP Operating Experience (1/74-1/98) p = 2.05E-1 r = 5.56E-1 A = 4.55E-2 for four stages P, = 1.72E-2/ demand For a Single Pump:
Q4,,,, = 8.91E-5/dc mand I
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CORE DAMAGE FREQUENCY (CDF)
(Given Loss of CCW)
Loss of CCW to RCPs Frequency 48 events / 780 pump-yr
= 6.15E-2/ pump yr Seal Failure Rate
= 8.91E 5/ demand Plant Seal LOCA Frequency 4
- 6.15E-2
- 8.91E-5
= 2.19E-5/>T Conditional Core Damage Probability, Given a Small LOCA CDF (Small LOCA)/LOCA Frequency = 2.11E-3/ demand CDF (CCW Induced Seal LOCA) 2.19E-5
- 2.11E-3
= 4.62E-8/yr jyjll Combustion Engineering Owners Group 3
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l CORE DAMAGE FREQUENCY (CDF)
(DUE TO Seal Failure Given LOOP)
FREQUENCY OF LOOP
= 2.4E 2/yr(1)
FAILURE OF 2 DIESELS
= 1.0$E-2/ demand (2)(3)
= 2.51E-4/yr l
RCP SEAL FAILURE (any I of 4)
= 3.56E-4/ demand SEAL LOCA FREQUENCY
= 8.95E-8/yr No RESTORATION OF AC
= 0.24 (4 hrs)
(
Reference:
SBO COPING SRJD*.',11/1991)
= 2.15E-8/yr (1)INEEIEXT-94 00401, Table 31, Apnl.1998 (2) Does not credit AAC (3)EPRI ALWR URD
/kllll Combustion Engineering Owners Group LOOP ANALYSIS SBO Thermal-Hydraulic Evaluation Results Analysis performed for average CEOG plant (size and configuration)
Analysis showed plant can cope with 4-br SBO 4
Analysis also showed that core would not be uncovered for at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with a 248 gpm LOCA
)(llll Combustion Engineering Owners Group l
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tt=l TOTAL RISK FROM LOSS OF COOLING TO RCP SEALS Elp.g.1 CDF (oer vr)
LOSS OF CCW 4.62E-8 SBO 2.15E-8 TOTAL 6.77E-8
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CLOSING REMARKS Key Points History of superior performance - NO FAILURES Operational limits and procedures assure continued superior
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performance Testing indicates RCP seals will maintain integrity under SBO conditions RCP Seal Failure is a Very Small Contributor to Risk
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e GSI-23 B&W Designed Plant Status l
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Oconee (" Evaluation of the Oconee Units 1,2, and 3 Generic Safety Issue Resolution (TAC NOS. M74440, M74441, and M74442)", March 24,1995)
RCP & Seal Types ANO-1, CR3, DB Byron Jackson (BJ)
N9000 TMI-l Westinghouse
- 1 Seal-Controlled leakage film riding face seal
- 2 & 3 Seal-Cartridge seals (rubbing face)
- 2 Seal converts to controlled leakage film riding face seal Seal Cooling SealInjection (SI)
Makeup \\HPI System Closed Cooling Water (CCW) Thermal Barrier Seal Cooling Power Sources All plants provide power for SI and CCW from Class IE Emergency power.
All plants except CR3 provide power for SI and CCW from a SBO source.
A four (4) hour coping analysis (by BWOG, covers CR3) performed to demonstrate lack of core uncovering (25 gpm/RCP).
peC USI-23 B&W Designed Plant Status (continued)
RCP Instrumentation All plants have adequate instmmentation to monitor RCP seal cooling and performance (e.g., seal injection flow, seal return flow and temperature, etc.).
Procedures All plants have operating and emergency / abnormal procedures that address loss of seal cooling.
Expected Seal Replacement Frequency BJ N9000 Seals Performance based (6 - 8 years)
Westinghouse 20 - 40 years, Inspected and refurbished every four (4) years Test Data BJ N9000 Seal Users Group Plant test data (DB - post rebuild)
Westinghouse Test / Analysis Loss of SI Events ANO-1 30 minutes CR3 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
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GSI-23 Issue Conclusions Pump Seal failure is not a significant contributor to core damage.
There are 4 additional years of excellent seal I
operating experience since IN 95-42.
Procedures are in place at all plants to respond to loss of seal cooling events.
j The Owners Groups collectively believe that this issue can be closed without further regulatory action.
F S. Rich rds SBO will continue to do so. For loss of CCW and SW, they used information from the individual Plant Evaluations to assess the frequency of losses of CCW and SW, and combined this with an NRC-developed model of RCP seal LOCA behavior on loss of seal cooling, to
. assess the core damage frequm~y from the sequences involving loss of CCW or SW, and RCP LOCA. This was done fcv select plants. The owners groups were interested in this approach ard expressed a desire to meet with the staff to discuss the approach. The staff agreed to hold such a meeting in the near term and noted that GSI-23 it scheduled to be closed by December 1999. The RES staff's p;eliminary determination is that ersuming the available seal failure model and the resulting "large" leak rate, most plants will show acceptable risk from loss of RCP seal cooling and will, therefore, require no additional actions as a result of j
' GSI-23 resolution.
I The following actions resulted from the meeting:
1.
The owners groups will inform individual licensees of the staff's path to resolution of GSI-23. In the process of doing this, if any licensee believes there is additional plant specific information that would be useful to the staff in performing the risk assessment (e.g., design improvements to the component cooling water system, improved attemate ac power capability that are not captured in the individual plant examination) that the staff may not be aware of, they should provide that information via their project manager.
2.-
The WOG agreed to provide more information on the Sizewell test results and consider whether to pmvide a list of those plants that have or are planning to use the newer high temperature O-rings in the RCP seals in order to improve the seal performance.
3.
RES staff will work through the owners group project manager to establish a date for a future meeting in the near term to discuss (a) the initial results of their RCP seal leakage risk assessment grouping of plants with the owners groups, and (b) the plant specific information discussed in item 1, above.
This completes staff action on TAC No. MA4519.
Attachments: 1. Attendance List
- 2. WOG Presentation
- 3. CEOG Prcsontation
- 4. B&WOG Presentation original signed by S. Dembek cc w/att 1:' See next page DISTRIBUTION Hard Copy
.JWermiel EWeiss Docket File JCraig PUBLIC CJackson EPeyton PDIV-2 R/F FChemy-OGC SBahadur ACRS JJackson WRogers, Region ll fMail DMatthews/SNewberry SCollins/RZimmerman' GHolahan/TCollins -
BSheron/WKane GTracey, EDO Document Name: a:\\PDIV-2\\ Woc\\msum0714.wod
- see previous concurrence OFFICE PDIV-2/SC PDIV-2/LA
'SRXB/BC
- RES/DET SDembek:sh EP[ytonE JWermiel JCraig
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NAME DATE 7/24 /99
' 7 Ek3/ 99 7 /20/99 7 /23/99 OFFICIAL OFFICE COPY
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