ML20056G071
| ML20056G071 | |
| Person / Time | |
|---|---|
| Site: | 05200002 |
| Issue date: | 08/26/1993 |
| From: | Mike Franovich Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9309010276 | |
| Download: ML20056G071 (12) | |
Text
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7 yy UNITED STATES
[ .h[ctj I NUCLEAR REGULATORY COMMISSION WASHINGTON. D C. 20555-0001
- August 26, 1993 Docket No.52-002 APPLICANT: ABB-Combustion Engineering, Inc. (ABB-CE)
PROJECT: CE System 80+
SUBJECT:
PUBLIC MEETING OF AUGUST 9, 1993, TO DISCUSS OPEN ISSUES RELATED TO THE PROBABILISTIC RISK ASSESSMENT (PRA) FOR THE SYSTEM 80+
STANDARD PLANT DESIGN P On August 9,1993, a public meeting was held at the U.S. Nuclear Regulatory '
Commission (NRC) in Rockville, Maryland, between representatives of the NRC and ACB-CE. The purpose of the meeting was to discuss open issues from the staff's review of the System 80+ PRA. Enclosure 1 provides a list of attendees. Enclosure 2 contains the material presented by the NRC. ,
The staff provided ABB-CE with an update on the status of the Probabilistic Safety Assessment Branch review of the System 80+ PRA. Enclosure 2 contains a summary list on the status of CE System 80+ draft safety evaluation report (DSER) PRA issues. Each item was briefly discussed, and NRC and ABB-CE actions were identified. The staff indicated that several actions need to occur by August 30, 1993. As a result of the discussion, the following commitments were made- i (1) The staff will provide ABB-CE additional comments and questions on several ABB-CE responses to DSER open items by August 16, 1993, including ;
issues on hydrogen, internal fires, and floods.
(2) The staff will provide ABB-CE with remaining comments and questions on low-power operations and shutdown risk by August 23, 1993.
(3) By August 30, 1993, the staff will provide ABB-CE with comments and f questions on ABB-CE's severe accident mitigation design alternatives submittal and the recently received seismic margins assessment.
(4) ABB-CE will provide a compiled list of PRA-related insights for Tier 1 treatment by August 23, 1993.
The staff characterized the review as proceeding according to schedule, and ,
that the only significant unresolved issue was DSER Open Item 19.1.2.4-1 on i the PRA information for Tier 1 and the reliability assurance program. It appeared that ABB-CE may need to update the PRA insights list in the standard safety analysis report to capture progress in ABB-CE's PRA evaluation of issues, such as seismic margins, fire, and flood. ABB-CE and the staff agreed , l
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l August 26, 1993 l
l to conduct a meeting in Windsor, Connecticut, to resolve the remaining open issues and discuss follow-on questions. In addition, ABB-CE and the staff will discuss "roadmaps" for PRA and severe accidents insights and assumptions ;
during the meeting which has been tentatively scheduled for September 2,1993. i i
(Original signed by)
Michael X. Franovich, Project Manager Standardization Project Directorate -
Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation ;
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Enclosures:
As stated l cc w/ enclosures:
See next page DISTRIBUTION w/ enclosures: l Docket File PDST R/F DCrutchfield ,
PDR MFranovich RPerch, BH7 P5hea DISTRIBUTION w/o enclosures: 3 TMurley/FMiraglia JMoore, 15B18 WTravers RBorchardt EJordan, MNBB3701 AThadani, 8E2 AEl-Bassioni, 10E4 WBeckner, 10E4 NSaltos, 10E4 RPalla, 10E4 TVWambach ,
ACRS (11) SMagruder TEssig 0FC: LA:PDST:ADAR PM:PDST:ADAR SC:PDST:ADAR NAME: PShea MXFra'ndvilch:sg TEssig g/ (i(ib-l DATE: 08f2(/9 08/V/93 08/y,/93 l .
OFFICIAL RECORD COPY: DOCUMENT HAME: MSUM0809.MXF i
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ABB-Combustion Engineering, Inc. Docket No.52-002 i i
cc: Mr. C. B. Brinkman, Acting Director .
Nuclear Systems Licensing !
ABB-Combustion Engineering, Inc.
1000 Prospect Hill Road Windsor, Connecticut 06095-0500 Mr. C. B. Brinkman, Manager Washington Nuclear Operations ;
ABB-Combustion Engineering, Inc. j 12300 Twinbrook Parkway, Suite 330 :
Rockville, Maryland 20852 ,
Mr. Stan Ritterbusch ;
Nuclear Systems Licensing ABB-Combustion Engineering, Inc. !
1000 Prospect Hill Road Post Office Box 500 l Windsor, Connecticut 06095-0500 Mr. Sterling Franks )
U.S. Department of Energy :
NE-42 !
Washington, D.C. 205B5 j Mr. Steve Goldberg l
' Budget Examiner 725 17th Street, N.W. i Washington, D.C. 20503 Mr. Raymond Ng 1776 Eye Street, N.W.
Suite 300 i Washington, D.C. 20006 Joseph R. Egan, Esquire ;
Shaw, Pittman, Potts & Trowbridge :
2300 N Street, N.W.
Washington, D.C. 20037-1128 ,
i Mr. Regis A. Matzie, Vice President z Nuclear Systems Development
. ABB-Combustion Engineering, Inc.
1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500 i
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' t MEETING ATTENDEES I i
AUGUST 9, 1993 NAME ORGANIZATION k
Mike Franovich NRR/PDST :
Eric Siegmann ABB-CE f William Beckner NRR/SPSB !
Nick Saltos NRR/SPSB i Syed Ali NRR/ECGB ;
Bob Palla NRR/SPSB Adel El-Bassioni NRR/SPSB .l Rupert Weston ABB-CE :
Stan Ritterbusch ABB-CE !
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i Enclosure 1 i 1
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STATUS OF RESOI.11 TION OF SYSTEM 80+ DSER i OPEN ITEMS (AS OF 8/4/93)
- 1. CLOSED: Items that are either no longer applicable or for which completed SSAR and FSER sections are available.
NUMilER TITLE ACTION REMARKS 19.1.2.2.3-2 The applicant must clarify the low-acceleration N/A No longer applicable. Applicant is preparing cutoffs in the fragility functions used in the a PRA-based scismic margins analysis.
quantification of seismic sequences.
19.1.2.2.3-3 The applicant must confirm that recovery N/A No longer applicable. Applicant is preparing actions reverse all of the effects of scismically- a PRA-based scismic margins analysis.
induced failurcs.
19.1.2.2.6-3 The applicant should clarify the role of N/A No longer applicable. Applicant is preparing different scismically-induced failures at a PRA-based scismic margins analysis, different acccicration levels.
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- 2. CONFIRMATORY: Items for which submittal has been reviewed and is considered acceptable.
NUMilER TITLE ACTION REMARKS 19.1.1.1-1 The applicant is currently updating its IRWST NRC FSER section must be completed design and will revisc its PRA. The staf f will reevaluate the possibility of an unisolable IRWST leak.
19.1.2.1.1.2-1 The applicant must con 0rm the success NRC FSER section must be completed 3
criterion regarding the number of PSVs that must open.
19.1.2.1.1.2-2 The applicant must justify the success criterion NRC FSER section must be completed for cooling the IRWST following an ATWS with a consequential steam generator tube rupture.
19.1.2.1.1.2-3 The applicant needs to provide documentation NRC FSER section must be completed to confirm success criterion of only one train
! of containment spray for cooling the IRWST following an ATWS with a stuck open PSV.
19.1.2.1.1.3-3 The applicant must provide justi0 cation for NRC FSER section must be completed i modeling an unisolable leak in a ruptured stcam generator.
19.1.2.1.1.3-4 The applicant did not include the potential for NRC FSER section must be completed.
a reactor coolant pun;p seal LOCA during an SBO scenario.
19.1.2.1.1.3-5 The applicant must estimate the uncertainty of NRC FSER section must be completed an adverse moderator temperature coefficient.
1 19.1.2.1.1.5-1 The applicant must provide common cause NRC FSER section must be completed.
l failures (CCFs) which address staff concerns.
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1 I NUS111ER TITLE ACTION RE31 ARKS 19.1.2.1.1.7 1 The applicant must perform additional NRC FSER section must be completed sensitivity, uncertainty and importance analyses.
19.1.2.1.1.8 1 The applicant must provide additional NRC/CE FSER section must be completed. CE will information regarding the demand failure providejustification of approach and error probability of rapid depressurization MOVs. factor as agreed.
l 19.1.2.1.1.8-2 The applicant must demonstrate that new and NRC FSER section must be completed . c C M ..
significant failure modes are not introduced. @ Ar c u % of .d vt t. . Ei y a d % < - ((n9"'-
' J 19.1.2.1.2.1-1 Applicant must incorporate the details of final NRC FSER section must be completed cavity flood system design into an updated PRA.
19.1.2.1.2.1-2 The applicant must justify the very low NRC FSER section must be completed probability of the dry cavity and core-concrete interaction occurrence assumed in the PRA.
19.1.2.1.2.2-1 The applicant must modify / clarify the plant NRC FSER section must be completed damage state deletion rules to address staff concerns.
19.1.2.1.2.3-1 The applicant must modify its release class NRC FSER.section must be completed definition 19.1.2.1.2.3-2 The applicant has committed to correct the NRC FSER section must be completed CEF in a revision to the System 80+ PRA.
19.1.2.1.2.4-1 The applicant must provide a more mechanistic NRC FSER section must be completed assessment of the containment isolation failure.
19.1.2.1.2.4-2 The applicant must provide justification for the NRC FSER section must be completed data used to assess various probabilitics.
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l NUMITER TITLE ACTION REMARKS 19.1.2.1.2.4-4 The applicant must justify not addressing NRC FSER section must be completed hydrogen detonation in its PRA.
19.1.2.1.2.4-5 The applicant must correct an error in the NRC FSER section must be completed assumption of the probability of high RCS pressure at the time of core damage.
19.1.2.1.2.4-6 The applicant must provide an assessment of 1) NRC FSER section must be completed the ability of the design to accommodate alpha and rocket failure loads and 2) the impact of these challenges on the risk profile.
19.1.2.1.2.4-9 The applicant must justify not explicitly NRC FSER section must be completed considering in the PRA containment overpressure by non-condensable gas generation.
19.1.2.1.2.4-10 The applicant must assess the potential for late NRC FSER section must be completed containment failure due to temp / pressure loads.
19.1.2.1.2.4-11 The applicant must justify not explicitly NRC FSER section must be completed considering a localized containment failure due to the degradation of containment penetration materials at cicvaicd temperatures.
19.1.2.1.2.4-13 The applicant must evaluate the basemat melt- NRC FSER section must be completed l through releases and the possible establishment of an additional release class.
j 19.1.2.1.2.5-1 The applicant must evaluate the potential for NRC FSER section must be completed. Minor
- revaporization releases. problems to be discussed with CE.
19.1.2.1.2.5-2 The applicant must evaluate the significance of NRC FSER section must be completed late release of iodine and modify the PRA accordingly.
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NUMilER TITI E ACTION REMARKS 19.1.2.1.3.3-1 The applicant must assess the fission product NRC FSER section must be completed release location following its re-evaluation of containment pressure capability.
19.1.2.1.4.2-1 The applicant should use additional meaurcs NRC FSER section must be completed (beyond CCDF) and compare them with the staff's proposed large release goal.
- 3. UNDER REVIEW: Issue has been technically resolved and submittal has been received. Additional RAls possible if submittal is not adequate.
NUMBER TITLE ACTION REMARKS 19.1.2.1.1.3-1 The applicant must document the time it takes to mCE- Waiting-for-CE's responses to staff RAls .;
(g 7 / 71[of y reach SCS cntry conditions following a failurc .,6 c d , --(
of safety injection during a small LOCA. ,
i 19.1.2. i . l .3-2 The applicant must demonstrate the feasibility CE Waiting for CE's responses to staff RAls i and practicality of the aggressive secondary cooldown modeled in the PRA.
19.1.2.1.1.5-2 The applicant must correct / clarify a number of NRC Responses to RAls under review. g/g human reliability analysis items. Responses received 7/16/93.
19.1.2.1.2.4-3 The applicant must provide further evaluation of NRC Staff preparing RAI regarding treatment of the effectiveness of the hydrogen mitigation dependencies in Boolean expressions YM system.
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r i NUMilER TITLE ACTION ' REMARKS 19.1.2:1.2.4-7 t The applicant must provide further justincation NRC Staff preparing RAI regarding apparent f for the values used for non-recovery probability inconsistencies 9M of containment heat removal.
-m, l 19.1.2.1.2.4-8 The applicant must correct the late hydrogen NRC Staff preparing RAI regarding treatment of g burn model's supporting logic to address staff dependencies M concerns.
19.1.2.1.2.4- The applicant must evaluate core debris NRC Staff working on verincation via MELCOR m tv -c 4 rr 12 coolability and CCI termination failure even calculation SM j after adding water to the reactor cavity. ,
19.1.2.1.2.7-1 Further analyses and justification of the NRC Structural calculations under review by containment ultimate pressure capability ECGB distribution is required.
19.1.2.1.2.8-1 The applicant must provide analyses that NRC Generally OK, but staff has investigate the influence of key issues and parameters on risk results.
recommendations re: source term sensitivity analyses. See Issue 19.1.2.1.2.8-1 8[d 19.1.2.1.3.2-1 The applicant must improve the process of NRC Generally OK, but some inconsistencies selecting representative sequences for estimating noted. Staff preparing RAI source terms for cach release class. F((4 19.1.2.1.3.4-1 The applicant must justify its decontamination NRC Generally OK, but some additional g i
factors for the various mitigation systems. clarification needed. Staff preparing RAI 19.1.2.1.3.5-1 The applicant must assess the source term NRC Staff preparing RAI uncertainty in key issues on risk estimates. g// g 19.1.2.1.5-1 The applicant must provide a more thorough NRC Staff reviewing [ submittal l treatment of the loads associated with potentially gg 88 significant containment challenges.
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NUS111ER TITLE ACTION RENTARKS 19.1.2.1.6-1 The severe accident mitigation design NRC Staff reviewing recently submitted revised M-M alternatives are still under staff review. 406 SAMDAs ## #'
19.1.2.2.6-1 The applicant should submit a risk analysis of NRC Staff reviewing CE's response to RAls .g 4 internal fires. ** ,3 19.1.2.2.6-2 The applicant should submit a risk analysis of NRC Staff reviewing CE's response to RAls ~
internal flooding. hrer 19.1.2.3-1 The applicant should provide related risk NRC/CE Item technically resolved. Staff reviewing analyses for shutdown and low power operation. fcc CE's revised analysis. CE working to a provide agreed-upon information that was missing from responses to staff RAls (risk achievement).
g 19.1.2.4-1 The applicant should provide a list of items that NRC/CE Resolution path identified. Staff reviewing could be included under DAC, ITAAC or RAP N/cx submittals. CE still working on ITAACs f requirements, and PRA input to RAP. Additional RAis g/
likely.
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- 4. RESOLVED: Technical approach has been agreed to, but we are still awaiting a submittal. Additional RAls likely since the staff has not yet seen the stibmittal.
NUMilER TITLE ACTION REMARKS 19.1.2.2.3-1 The app 1; . 7t should assess the plant fragility NRC Staff reviewing CE's analysis (received '
i curves a..u - erall plant IICLPF. 7/26/93).
- 5. OPEN: Items not ._ greed to. ,
- There are no open items.
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