ML20236V593
| ML20236V593 | |
| Person / Time | |
|---|---|
| Issue date: | 07/28/1998 |
| From: | Stewart Magruder NRC (Affiliation Not Assigned) |
| To: | Essig T NRC (Affiliation Not Assigned) |
| References | |
| PROJECT-692 NUDOCS 9808040066 | |
| Download: ML20236V593 (55) | |
Text
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t UNITED STATES y
,j NUCLEAR REGULATORY COMMISSIONS WASHINGTON, D.c. 20555-0001 July 28, 1998 MEMORANDUM TO: Thomas H. Essig, Acting Chief Generic issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM:
Stewart L. Magruder, Project Manager M M-Generic issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF MEETINGS WITH THE COMBUSTION ENGINEERING OWNERS GROUP PROBABILISTIC SAFETY ASSESSMENT WORKING GROUP Three meetings between the Combustion Engineering Owners Group (CEOG)
Probabilistic Safety Assessment Working Group (PSAWG) and the NRC staff were held on December 4-5,1997, March 25-26,1998, and May 21,1998, to discuss the status of the risk-informed technical specifications (TS) pilot program. The attendees are listed in Attachments 1-3.
The main topic discussed at these meetings was the status of the staff's review of pilot plant risk-informed TS amendments, including amendments to extend allowed outage times (AOTs) for the safety injection tanks, low pressure safety injection systems, and emergency diesel generators (EDGs). The discussions focused mainly on the inclusion of a configuration risk management program (CRMP)in the administrative controls section of the TS as part of risk-informed TS amendments and on technicalissues associated with the requests for extension of the AOT for the EDGs. Attachment 4 contains the TS program description for the CRMP which was jointly developed bv the staff and the CEOG PSAWG. contains supplementalinformation related to the EDG submittals requested by the staff and provided by the CEOG PSAWG at the December 1997 meeting. is a request for additional information (RAI) for the lead pilot plant, San Onofre Nuclear Generating Station (SONGS) that the staff provided to the SONGS representative at the May 1998 meeting. Many of the staff's RAI questions were pertinent to EDG submittals for all of the CE plants and, therefore, were discussed with h[
the CEOG PSAWG as a whole.
qs o 9008040066 980728 lN f
TOPRP EMVCgE DR Tm m
T. Essig 2-July 28, 1998 The staff also discussed other issues related to the risk-informed TS pilot program, including the status of the risk-informed regulatory guidance documents being prepared by the staff and the status of the staff's proposed revision to the maintenance rule (10 CFR 50.65). In Mdition, the CEOG PSAWG informed the staff of their plans for futuro risk-informed TS sumbittals. The CEOG PSAWG and the staff agreed to continue meeting on a periodic basis.
Project No. 692 Attachments: As stated cc w/att: See next page I
(
T. Essig 2-July 28,1998 l
The staff also discussed other issues related to the risk-informed TS pilot program, l
including the status of the risk-informed regulatory guidance documents being prepared by the staff and the status of the staffs proposed revision to the maintenance rule (10 l
CFR 50.65), in addition, the CEOG PSAWG informed the staff of their plans for future l
risk-informed TS sumbittals. The CEOG PSAWG and the staff agreed to continue meeting on a periodic basis.
Project No. 692 Attachments: As stated l
l cc w/att: See next page l
l DISTRIBUTION: See attached page Document Name:\\g\\simi\\ceogmtgm. doc
/
SC:PGEhY OFFICE PM:PGEB SC:TSB SMagrudef?sN MReinhart fffFAkstkcz NAME DATE 7/l7 /98 7/ J;f/98 0 7/M98 OFFICIAL OFFICE COPY 1
l l
9 l
l Distribution: Mtg. Summary w/ CEOG Re Risk-informed TS Dated _. July 28._.1998..
Hard Copy Docket File l
PUBLIC -
SMagruder MReinhart JClifford -
EMail SCollins/FMiraglia BSheron BBoger -
JRoe DMatthews TEssig WBeckner MRubin MReinhart SMagruder L
1
Meeting Attendees December 4-5,1997 Name Affiliation Gerald Sowers Arizona Public Service Biff Bradley Nuclear Energy Institute Bob Lindquist Arizona Public Service Alan Hackerott Omaha Public Power District Ray Schneider ABB-CE Bruce Mrowca Baltimore Gas & Electric Edward J. Weinkam Florida Power & Light David Finnicum.
ABB-CE Paul Hijeck ABB-CE LaMonte Aeynolds Consumers Energy Ching Guey Florida Power & Light Jim Powers NUSCO Frank Rahn EPRI Bob Jaquith ABB-CE Sue Jaquith ABB-CE Gary Chung Southern California Edison Mark Reinhart NRC Millard Wohl NRC John Flack NRC Richard Correia NRC Adel El-Bassioni NRC Stewart Magruder NRC Nanette Gilles NRC
l l
L Meeting Attendees March 25-26,1998 Name Affiliation Gerald Sowers Arizona Public Service j
Biff Bradley Nuclear Enegy n?stitute Bob Lindquist Arizona Public Seivice Alan Hackerott Omaha Public Powar District Ray Schneider ABB-CE l
Bruce Mrowca Baltimore Gas & Electric, David Finnicum
' ABB-CE Paul Hijeck ABB-CE
)
LaMonte Reynolds Consumers Energy
{
Ching Guey Florida Power & Light i
Jim Powers NUSCO Bob Jaquith ABB-CE Sue Jaquith ABB-CE Tom Hook Southern California Edison Mike Lloyd Entergy Operations Mark Reinhart NRC i
)
Millard Wohl NRC Nanette Gilles NRC l
)
I f
i
Meeting Attendees May 21,1998 Name Affiliation Alan Hackcrott Omaha Public Power District Ray Schneider ABB-CE Paul Hijeck ABB-CE Tom Hook Southern California Edison Jack Rainsberry Southern California Edison Doug Stickney Southern California Edison Jerry Dozier NUS Information Services Theresa Sutter Bechtel Eric Weiss NRC Om Chopra NRC Jose Calvo NRC Jim Clifford NRC lan Jung NRC Paul Gill NRC Frank Orr NRC Stewart Magruder NRC Mark Reinhart NRC Millard Wohl NRC Nanette Gilles NRC
CONFIGURATION RISK MANAGEMENT PROGRAM l
The Configuration Risk Management Program (CRMP) provides a proceduralized risk-informed assessment to manage the risk associated with equipment inoperability. The program applies to technical specification structures, systems, or components for which a j
risk-informed allowed outage time has been granted. The program l
shall include the following elements:
L 4
l a.
Provisions for the control and implementation of a Level 1 at l
power internal events PRA-informed methodology. The assessment shall be capable of evaluating the applicable plant configuration.
b.
Provisions for performing an assessment prior to entering the LCO Action Statement for preplanned activities.
Provisions for performing an assessment after entering the LCO c.
i Action Statement for unplanned entry into the LCO Action Statement.
l d.
Provisions for assessing the need for additional actions after the discovery of additional equipment out of service conditions while In the LCO Action Statement.
l l
e.
Provisions for considering other applicable risk significant contributors such as Level 2 issues and external events, qualitatively or quantitatively.
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AdditionalInformation Needed for Review of the San Onofre Emergency Diesel Generator Allowed Outage Time Extension Request 1.
Consistent with the Draft Regulatory Regulatory Guide 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-informed Decisions on Plant-Specific Changes to the Current Licensing Basis," the staff expects that the scope and quality of the analysis conducted to justify the proposed changes be appropriate for the nature and scope of the change, and be based on the as-built and as-operated and maintained plant. Further, the current plant-specific PRA supporting the licensee proposal has been subjected to quality controls. The staff finds that your current PRA is different from the originalIndividual Plant Examination (IPE). Extensive review of the Joint Application Report for Emergency Diesel Generators (EDGs), responses to the staff requests for additional information, your plant-specific submittal, and your IPE has been performed to examine your PRA. The review resulted in the need for the following additional information for the staff evaluation of your plant-specific submittal.
a.
Describe any independent peer reviews performed on your most updated PRA What quality control process do you have in order to maintain your current PRA representing the as-built and as-operated plant?
b.
Provide the following for staff review of your current PRA:
(a) a copy of the LOOP /SBO event tree, (b) a list of dominant SBO sequences.
(c) major modeling assumptions for LOOP /SBO events, and (d) major differences from your original IPE.
c.
Both the Joint Application Report (CE NPSD-996) and your plant-specific submittal qualitatively addressed the Level 2 risk associated with the proposed extended EDG AOT. However, quantitative Level 2 risk information is also an important consideration when evaluating the risk associated with your proposed EDG AOT extension request. The conditional containment failure probabilities (CCFPs) and large early release frequency (LERF) for both the current and proposed cases calculated from your updated PRA should be submitted for staff review, in addition, incremental conditional large early release probability (ICLERP) for a single 14-day AOT should also be submitted for staff evaluation of the risk associated with a single EDG outage.
d.
No RCP seal loss of coolant accident (LOCA) was assumed during an SBO in your IPE. Provide your engineering basis for making that assumption. Provide a discussion of how your PRA modeled the potential RCP LOCA during an SBO in your most updated PRA, if modeled differently from the IPE. If you have
E performed any sensitivity studies on potential seal failures during an SBO, provide the results. Explain why the potential RCP seal LOCA during an SBO is a negligible risk contributor for the proposed changes.
e.
For multiple unit sites, potential dual-unit initiators, single-unit initiators that propagate to the other unit, and shared systems can be important in PRA.
Explain how your current PRA addresses these issues and provide a quantitative or qualitative discussion that these issues either have been adequately taken into account in your analysis or have a negligible risk impact due to the proposed changes.
2.
Your IPEEE analysis shows that the average CDF contributed by external events exceeds that contributed by internal events. Discuss the impact on external event risk due to the proposed changes either quantitatively or qualitatively, and justify that the impact on the external event risk would not result in a different overall risk perspective.
3.
According to your submittal, the cross-tie capability, recently installed at your site and modeled in your current PRA, significantly reduces the SBO risk contribution from 1.8x104/yr to 5.91x104/yr. The cross-tie was worth over 1.7x104/yr for the SBO CDF.
You have also indicated that the cross-tie reduced the total CDF by 3.4x104/yr (11%
reduction in total CDF). The staff expects that the cross-tie capability would dominantly contribute to the reduction in the SBO risk; however, your submittal indicates that the SBO CDF reduction due to cross-tie accounts for only 50% of the total CDF reduction.
Please explain how the cross-tie contributes to the remaining non-SBO risk.
2
l CE OWNERS GROUP Project No. 692 cc:
Mr. Gordon C. Bischoff CEOG Project Manager ABB Combustion Engineering l
M.S. 9615-1932 2000 Day Hill Road Windsor, CT 06095 Mr. David Pilmer, Chairman CE Owners Group l
San Onofre Nuclear Generating Station I.
14300 Mesa Road San Clemente, CA 92672 Mr. Ian C. Rickard, Director l-Nuclear Licensing l-ABB-Combustion Engineering, Inc.
Post Office Box 500 2000 Day Hill Road Windsor, CT 06095 l
Mr. Charles B. Brinkman, Manager i
Washington Operations L
ABB-Combustion Engineering, Inc.
12300 Twinbrook Parkway, Suite 330 l-Rockville, MD 20852 l
l L
L
purrogk UNITED STATES g
g
,j NUCLEAR REGULATORY COMMISSION o
't WASHINGTON, D.C. 20666 4 001
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July 28, 1998 MEMORANDUM TO: Thomas H. Essig, Acting Chief Generic issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM:
Stewart L. Magruder, Project Manager M% -
Generic issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF MEETINGS WITH THE COMBUSTION i
ENGINEERING OWNERS GROUP PROBABILISTIC SAFETY ASSESSMENT WORKING GROUP Three meetings between the Combustion Engineering Owners Group (CEOG)
Probabilistic Safety Assessment Working Group (PSAWG) and the NRC staff were held on December 4-5,1997, March 25-26,1998, and May 21,1998, to discuss the status of the risk-informed technical specifications (TS) pilot program. The attendees are listed in Attachments 1-3.
The main topic discussed at these meetings was the status of the staffs review of pilot plant risk-informed TS amendments, including amendments to extend allowed outage times (AOTs) for the safety injection tanks, low pressure safety injection systems, and emergency diesel generators (EDGs). The discussions focused mainly on the inclusion of a configuration risk management program (CRMP)in the administrative controls section of the TS as part of risk-informed TS amendments and on technical issues associated with the requests for extension of the AOT for the EDGs. Attachment 4 contains the TS program description for the CRMP which was jointly developed by the staff and the CEOG PSAWG. contains supplemental information related to the EDG submittals requested by the staff and provided by the CEOG PSAWG at the December 1997 l
meeting.
l is a request for additional information (RAI) for the lead pilot plant, San Onofre Nuclear Generating Station (SONGS) that the staff provided to the SONGS representative at the May 1998 meeting. Many of the staffs RAI questions were pertinent to EDG submittats for all of the CE plants and, therefore, were discussed with the CEOG PSAWG as a whole.
i l
l 1
]
l l
l.
l T. Essig 2
July 28, 1998
~
i The staff also discussed other issues related to the risk-informed TS pilot program, l
including the status of the risk-informed regulatory guidance documents being prepared by the staff and the status of the staffs proposed revision to the maintenance rule (10 CFR 50,65). In addition, the CEOG PSAWG informed the staff of their plans for future risk-informed TS sumbittals. The CEOG PSAWG and the staff agreed to continue l
meeting on a periodic basis.
l Project No. 692 Attachments: As stated 1
cc w/att: See next page l
1 l
l l
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T. Essig July 28, 1998 The staff also discussed other issues related to the risk-informed TS pilot program, including the status of the risk-informed regulatory guidance documents being prepared by the staff and the status of the staff's proposed revision to the maintenance rule (10 CFR 50.65). In addition, the CEOG PSAWG informed the staff of their plans for future risk-informed TS sumbittals. The CEOG PSAWG and the staff agreed to continue meeting on a periodic basis.
Project No. 692 Attachments: As stated cc w/att: See next page DISTRIBUTION: See attached page Document Name:\\g\\simi\\ceogmtgm. doc
/[
OFFICE PM:PGEB SC:TSB SC:PGEB NAME SMagrudefi$$
MReinhart [f FAkstkcz f
DATE 7/ll /98 7/ Jtf/98 0 7/M98 OFFICIAL OFFICE COPY
Distribution: Mtg. Summary w/ CEOG Re Risk-informed TS Dated _ July _28.J 998._
Hard Copy Docket File PUBLIC PGEB R/F OGC ACRS SMagruder MReinhart JClifford EMail SCollins/FMirag!ia BSheron BBoger JRoe DMatthews TEssig WBeckner MRubin MReinhart SMagrude:
1 i
(
Meeting Attendees December 4-5,1997 l
Name Affiliation
';4rald Sowers Arizona Public Service Biff Bradley Nuclear Energy Institute l
l Bob Lindquist Arizona Public Service l
Alan Hackerott Omaha Public Power District Ray Schneider ABB-CE 1
l Bruce Mrowca Baltimore Gas & Electnc Edward J. Weinkam Florida Power & Light l
David Finnicum ABB-CE Paul Hijeck ABB-CE LaMonte Reynolds Consumers Energy l
Ching Guey Florida Power & Light Jim Powers NUSCO Frank Rahn EPRI Bob Jaquith ABB-CE l
Sue Jaquith ABB-CE Gary Chung Southern California Edison Mark Reinhart NRC Millard Wohl NRC John Flack NRC I
Richard Correia NRC l
Adel El-Bassioni NRC Stewart Magruder NRC Nanette Gilles NRC 1
i l
[-
Attachment i
1 Meeting Attendees March 25-26,1998 l
Name Affiliation Gerald Sowers Arizona Public Service Biff Bradley Nuclear Energy Institute Boi anJquist Arizona Public Service Alan Hackerott Omaha Public Power District Ray Schneider ABB-CE Bruce Mrowca Baltimore Gas & Electric David Finnicum ABB-CE Paul Hijeck ABB-CE LaMonte Reynolds Consumers Energy Ching Guey Florida Power & Light Jim Powers NUSCO Bob Jaquith ABB-CE Sue Jaquith ABB-CE Tom Hook Southern Califomia Edison Mike Lloyd Entergy Operations Mark Reinhart NRC Millard Wohl NRC Nanette Gilles NRC I
(
Meeting Attendees May 21,1998 Name Affiliation Alan Hackerott Omaha Public Power District Ray Schneider ABB-CE Paul Hijeck ABB-CE Tom Hook Southern Califomia Edison Jack Rainsberry Southem California Edison Doug Stickney Southern California Edison Jerry Dozier NUS Information Services Theresa Sutter Bechtel Eric Weiss NRC Om Chopra NRC Jose Calvo NRC Jim Clifford NRC lan Jung NRC Paul Gill NRC Frank Orr NRC Stewart Magruder NRC Mark Reinhart NRC Millard Wohl NRC Nanette Gilles NRC j
CONFIGURATION RISK MANAGEMENT PROGRAM The Configuration Risk Management Program (CRMP) provides a proceduralized risk-informed assessment to manage the risk associated with equipment inoperability. The program applies to technical specification structures, systems, or components for which a risk-informed allowed outage time has been granted. The program shall include the following elements:
a.
Provisions for the control and implementation of a Level 1 at power internal events PRA-informed methodology. The assessment shall be capable of evaluating the applicable plant configuration.
b.
Provisions for performing an assessment prior to entering the LCO Action Statement for preplanned activities.
c.
Provisions for pelforming an assessment after entering the LCO Action Statement for unplanned entry into the LCO Action Statement.
d.
Provisions for assessing tne need for additional actions after the discovery of additional equipment out of service conditions while in the LCO Action Statement.
e.
Provisions for considering other applicable risk significant contributors such as Level 2 issues and external events, qualitatively or quantitatively.
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Additional Information Needed for Review of the San Onofre Emergency Die w Generator Allowed Outage Time Extension Request 1.
Consistent with the Draft Regulatory Regulatory Guide 1.174,"An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Current Licensing Basis," the staff expects that the scope and quality of the analysis conducted to justify the proposed changes be appropriate for the nature and scope of the change, and be based on the as-built end as-operated and maintained plant. Further, the current plant-specific PRA supporting the licensee proposal has been subjected to quality controls. The staff finds that your current PRA is different from the original Individual Plant Examination (IPE). Extensive review of the Joint Application Report for Emergency Diesel Generators (EDGs), responses to the staff requests for additional information, your plant-specific submittal, and your IPE has been performed to examine your PRA. The review resulted in the need for the following additional information for the staff evaluation of your plant-specific submittal.
a.
Describe any independent peer reviews performed on your most updated PRA What quality control process do you have in order to maintain your current PRA representing the as-built and as-operated plant?
b.
Provide the following for staff review of your current PRA:
(a) a copy of the LOOP /SBO event tree, (b) a list of dominant SBO sequences, (c) major modeling assumptions for LOOP /SBO events, and t
(d) major differences from your original IPE.
c.
Both the Joint Application Report (CE NPSr)-996) and your plant specific submittal qualitatively addressed the Leve: 2 risk associated with the proposed extended EDG AOT. However, quantita(ve Level 2 risk ~information is also an
~
important consideration when evaluatinij the risk associated with your proposed EDG AOT extension request. The conditional containment failure probabilities (CCFPs) and large early release frequency (LERF) for both the current and proposed cases calculated from your updated PRA should be submitted for staff review. In addition, incremer,tal conditional large early release probability (ICLERP) for a single 14-day AOT should also be submitted for staff evaluation of the risk associated with a single EDG outage.
d.
No RCP sealloss of coolant accident (LOCA) was assumed during an SBO in your IPE. Provide your engineering basis for making that assumption. Provide a discussion of how your PRA modeled the potential RCP LOCA during an SBO in your most updated PRA, if modeled differently from the IPE. If you have l
I
performed any sensitivity studies on potential seal failures during an SBO, provide the results. Explain why the potential RCP seal LOCA during an SBO is a negligible risk contributor for the proposed changes.
e.
For multiple unit sites, potential dual-unit initiators, single-unit initiators that propagate to the other unit, and shared systems can be important in PRA.
Explain how your current PRA addresses these issues and provide a quantitative or quahtative discussion that these issues either have been adequately taken into account in your analysis or have a negligible risk impact due to the proposed changes.
2.
Your IPEEE analysis shows that the average CDF contributed by extemal events l
exceeds that contributed by intemal events. Discuss the impact on extemal event risk i
due to the proposed changes either quantitatively or qualitatively, and justify that the impact on the extemal event risk would not result in a different overall risk perspective.
3.
According to your submittal, the cross-tie capability, recently installed at your site and modeled in your current PRA, significantly reduces the SBO risk contribution from 1.8x104 4
/yr to 5.91x10 /yr. The cross-tie was worth over 1.7x104/yr for the SBO CDF.
You have also indicated that the cross-tie reduced the total CDF by 3.4x104/yr (11%
reduction in total CDF). The staff expects that the cross-tie capability would dominantly contribute to the reduction in the SBO risk; however, your submittal indicates that the i
SBO CDF reduction due to cross-tie accounts for only 50% of the total CDF reduction.
Please explain how the cross-tie contributes to the remaining non-SBO risk.
l 2
I IE
CE OWNERS GROUP Project No. 692 l
cc:
Mr. Gordon C. Bischoff CEOG Project Manager ABB Combustion Engineering M.S. 9615-1932 2000 Day Hill Road Windsor, CT 06095 Mr. David Pilmer, Chairman CE Owners Group San Onofre Nuclear Generating Station 14300 Mesa Road San Clemente, CA 92672 Mr. Ian C. Rickard, Director Nuclear Licensing ABB-Combustion Engineering, Inc.
Post Office Box 500 2000 Day Hill Road Windsor, CT 06095 Mr. Charles B. Brinkman, Manager Washington Operations ABB-Combustion Engineering, Inc.
12300 Twinbrook Parkway, Suite 330 Rockville, MD 20852 j
)
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