ML20235J380
| ML20235J380 | |
| Person / Time | |
|---|---|
| Issue date: | 09/25/1987 |
| From: | Vissing G Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| PROJECT-675A NUDOCS 8710010418 | |
| Download: ML20235J380 (62) | |
Text
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UNITED STATES k
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WASHINGTON, D. C,20655 I
September 25, 1987
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Project No. 675 MEMORANDUM FOR:
The Record FROM:
Guy S. Vissing, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects
SUBJECT:
SUMMARY
OF MEETING WITH COMBUSTION ENGINEERING DISCUSSING UNPESOLVED SAFETY ISSUES AND GENERIC ISSUES FOR CE SYSTEM-f,0+ DESIGN, SEPTEMBER 17, 1987 INTRODUCTION A meeting of the staff with representatives of Combustion Engineering (CE) was held at the NRC offices in Bethesda, Maryland, on September 17, 1987. The purpcse of the meeting was to discuss the program for handling and resolvirig Unresolved Safety Issues (USI) and Generic Safety Issues (GSI) for the CE System 80+ design. This meeting was one of a series to keep the staff informed regarding the development of the System 80+ design. Enclosure 1 provides the list of those who were in attendance. Enclosure 2 provides the CE viewgraphs. provides a list of those applicable USI and GSI that are remaining to be resolved in the EPRI program.
DISCUSSION Initially CE was advised that the best approach to the resolution of an issue was to make it a non-issue through the design of the system. However, CE emphasized that their approach to the resolution of these issues would be through designs which would satisfy stated criteria. The criteria would be presented along with the applicable CESSAR-DC chapters which present the design that implement the criteria. They believe that the staff can review the designs along with the criteria and ultimately accept the criteria as they apply to the System 80+ design. They see this as an approach which would reduce the amount of uncertainty in acceptance before ACRS and others.
The' general approach to addressing the USIs and GSIs is by first identifying the issues through the Generic Issue Management Control System (GIMCS).
Acceptance criteria will be established through the EPRI Advance Light Water Reactor (ALWR) program,theAdvancedReactorSevereAccidentProgram(ARSAP),
CE where necessary and the NRC through programs for developing positions, reviewing and accepting proposed resolutions. However, the EPRI ALWR program will be the prime vehicle for developing topic papers which will address USIs
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and GSIs for staff review and acceptance. These topic papers will be
[b submitted with the EPRI chapters of the Requirements Document and will identify the criterie for implementation by the advanced designs. Seven topic goo 04s370925 f
6754 PDR
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. September 25, 1987
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papers have been submitted with Chapter 1 and have had comments by the staff.
However, the staff has not yet given formal acceptance through SERs. The total number of issues which EPRI has identified is 69.
identifies the issues which EPRI plans to address through topic papers.
The staff expressed a concern that it may be optimistic to expect the staff to have acceptance criteria in the manner explained. CE will propose designs which will implement the criteria which can be reference by some EPRI or NRC documentation. Through the review and acceptance of the designs there may be acceptance of the criteria.
If there is no acceptance criteria CE will still go ahead with their designs to implement a proposed resolution. CE indicated that the resolutions through the designs may be more conservative than the NRC ultimate resolutions.
Original signed by Guy S. Vissing, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects
Enclosures:
As stated DISTRIBUTION Docket-File" JPartlow DScaletti NRC & Local PDRs EJordan GVissing NRC Participants LRubenstein ACRS (10)
EHylton TKenyon OGC-Beth Pleech PDSh/
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/87 09/f7/87 09/27198
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1 2_
September 25, 1987 papers have been submitted with Chapter 1 and have had comments by the staff.
However, the staff has not yet given formal acceptance through SERs. The total number of issues which EPRI has identified is 69. Enclosure 3 identifies the issues which EPRI plans to address through topic papers.
The staff expressed a concern that it may be optimistic to expect the staff to have acceptance criteria in the manner explained. CE will propose designs f_-
which will implement the criteria which can be reference by some EPRI or NRC documentation. Through the review and acceptance of the designs there may be acceptance of the criteria.
If there is no acceptance criteria CE will still
-2 go ahead with their designs to implement a proposed resolution. CE indicated that the resolutions through the designs may be more conservative than the NRC ultimate resolutions.
Guy S. Vissing, oject Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects
Enclosures:
As stated b
Attendance List for Meeting with Combustion Engineering Concerning USIs & GSIs for System 80+ Design September 17, 1987 NAMES
-ORGANIZATION j
Robert Paer RES/DE/EIB ilerry Mazetis
'RES/DRPS/RPSIB Amira Gill NRR/ DEST /LPSB Mark P. Rubin NRR/ DEST / SAD Regis A. Matzie C-E George A. Davis C-E Stan Ritterbusch C-E Mike Green C-E Charles Brinkman C-E Bethesda Barry Mendelsohn NRR/DRIS/RSGB Charles R. Nichols NRR/ DEST /SPLB Steve Long NRR/DRSP/PDSNP Brad Herdin RES/ARB Bob Fitzpatrick Brookhaven Lab Hans Rennet NUS Corporation Guy S. Vissing NRC/NRR
CESSAR DESIGN CERTIFICATION PROGRAM 1
-A MEETING WITH THE NUCLEAR REGULATORY COMMISSION -
" RESOLUTION OF USI'S AND Gl'S" l
l DATE: SEPTEMBER 17, 1987 COMBUSTION ENGINEERING, INC.
l
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LEGAL NOTICE THl3 REPORT WAS PREPARED AS AN ACCOUNT OF WORK SPONSCRED EY CCMSUSTICN ENGINEERING, INC. NEITHER COMSUSTION ENGINEERING NCR ANY PER$0N ACTING ON ITS BEHALF:
A.
MAKE3 ANY WARRANTY CR REPRESENTATION, EXPRESS CR IMPUED INCLUDING THE WARRANTIES OF FITNESS PCR A PARTICULAR PURPOSE CR MERCHANTABluTY, WITH RESPECT TC TNE ACCURACY, COMPLETENESS, OR USEFULNESS OF THE INFORMATION CONTAINED IN THIS REPORT, OR THAT THE USE OF ANY INFORMATION, APPARATUS, METHCC, OR PRCCESS DISCLCSED IN THIS REPORT MAY NOT INFRINGE PRIVATELY CWNED RIGHTS; OR L ASSUMES ANY UASIUTIES WITH RESPECT TO THE USE OF, OR FOR CAMAGE3 RESULTING PROM THE USE OF, ANY INFORMAT1CN, APPARATUS, METHCD CR PRCCESS DISCLCSED IN THIS REPORT.
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PURPOSE o
APPRISE NRC STAFF 0F C-E's PLAN FOR CLOSING OUT THE USI's and GI's REQUIRED FOR COMPLIANCE WITH THE SEVERE ACCIDENT POLICY STATEMENT I
0 OBTAIN NRC FEEDBACK l
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AGENDA CESSAR-DC Meeting with NRC
- Resolution of USI's and GI's September 17, 1987 9:30 am
==
Introduction:==
Overview of M. D. Green Design Certification Program 10:00 am Plans for Resolution S. E. Ritterbusch of USI's and GI's i
11:15 am NRC's Approach to G. Vissing (NRC)
USI's and GI's 11:45 om Summary M. D. Green 1
consmusTion)EstCINEERIM
INTRODUCTION OVERVIEW 0F CESSAR DESIGN CERTIFICATION l
(CESSAR-DC) PROGRAM l
DR. M. D. GREEN MANAGER, STANDARD PLANT LICENSING comaW5 TION) ENGINEERING -
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OVERVIEW o
PROGRAM OBJECTIVES o
LICENSING APPROACH o
SEVERE ACCIDENT POLICY REQUIREMENTS I
o SCHEDULE l
b consustion)sucimanninc
C-E ALWR PROGRAM OBJECTIVES o
TO DEVELOP AN ADVANCED PWR
--SYSTEM 80+-- WITH ENHANCED SAFETY IMPROVED PERFORMANCE REDUCED TOTAL COST PROVEN TECHNOLOGY o
OBTAIN NRC CERTIFICATION OF THE ADVANCED PWR DESIGN
--CESSAR-DC-- TO REDUCE LICENSING RISK:
RETAIN NUCLEAR POWER AS A VIABLE FUTURE ENERGY OPTION l
COMBU5T10NhENGINEER10Hi
SEVERE ACCIDENT POLICY REQUIREMENTS FOR FUTURE PLANTS 1.
MEET CURRENT REGULATIONS, INCLUDING CP/ML RULE 2.
RESOLVE USI's and MEDIUM-AND HIGH-PRIORITY GI's 3.
COMPLETE PROBABILISTIC RISK ASSESSMENT 4.
COMPLETE NRC STAFF REVIEW (INCLUDING PRA AND DEGRADED CORE ISSUES) l l
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OVERVIEW 0F C-E's PLAN FOR RESOLUTION OF USI's AND GI's o
OBJECTIVE o
GENERAL APPROACH o
USI's and GI's TO BE ADDRESSED o
ACCEPTANCE CRITERIA o
IMPLEMENTATION o
SUMMARY
COMSU5 TION ENGINEERING
OBJECTIVE o
COMPLETELY CLOSE OUT APPLICABLE USI's AND GI's DURING NRC REVIEW 0F SYSTEM 80+
INTEGRATE INPUT FROM CONTRIBUTING ORGANIZATIONS i
AND OBTAIN NRC AGREEMENT VIA INFORMAL MEETINGS I
AND RULEMAKING RESOLUTIONS WILL BE BASED ON DOCUMENTED CRITERIA l
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GENERAL APPROACH 0
IDENTIFICATION OF ISSUES GENERIC ISSUE MANAGEMENT CONTROL SYSTEM (GIMCS)
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i COMBUSTION ENGINEER 1NC
fdHERAL APPROACH (CONT'D) o ESTABLISHMENT OF ACCEPTANCE CRITERIA SOURCES INCLUDE EPRI, ARSAP, C-E AND NRC UTILIZE EPRI REGULATORY STABILIZATION PROGRAM TO MAXIMUM EXTENT PRACTICAL
-- TOPIC PAPERS FOR " REMAINING" ISSUES
-- REFERENCED DOCUMENTS FOR " RESOLVED" ISSUES EPRI REGULATORY STABILIZATION PROGRAM IS DESCRIBED IN:
-- NUREG-1197
-- EPRI SUBCONTRACTOR REPORT SLI-8410 i
l consusTion) ENGINEERING
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GENERAL APPROACH (CONT'D) 0 IMPLEMENTATION INTO SYSTEM 80+
0 APPROVAL AND CERTIFICATION OF CESSAR-DC BY NRC (ALL ISSUES CLOSED OUT) i N com usuon).u mesm a
s APPROACH TO RESOLUTION OF SAPS USI's/GI's IDENTIFY ISSUE (GIMCS) y Rfhff0N ARSAP E FF.
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USI's AND GI's TO BE ADDRESSED HISTORY l
1970's:
CONCERNS AND SAFETY ISSUES IDENTIFIED AND ADDRESSED ON A CASE-BY-CASE BASIS 1974:
CONGRESS REQUIRED NRC TO DEVELOP A PLAN AND TO REPORT ANNUALLY ON STATUS OF
" UNRESOLVED SAFET( ISSUES" 1977:
NUREG-0410 IDENTIFIED " GENERIC" ISSUES AND DEFINED CATEGORIES OF IMPORTANCE commuffl0NhENGINEER1NG
USI s AND GI s TO BE ADDRESSED (CONT.)
NUREG-0410 CATEGORIES CATEGORY A:
RESOLUTION COULD RESULT IN SIGNIFICANT INCREASE IN SAFETY OR HAVE SIGNIFICANT IMPACT ON LICENSING CATEGORY B:
IMPORTANT TO CONTINUED SAFETY, BUT EARLY RESOLUTION NOT REQUIRED CATEGORY C:
NOT EXPECTED TO HAVE SIGNIFICANT IMPACT ON SAFETY, BUT COULD PROVIDE NRC WITH INCREASED UNDERSTANDING CATEGORY D:
NOT IMPORTANT EN0 UGH TO SAFETY TO JUSTIFY EXPENDITURE OF FUNDS consaufT10NhENGINEERil6G
s USI's AND GI's TO BE ADDRESSED (CONT.)
HISTORY I
1977:
- CATEGORY A ACTION PLANS PUBLISHED IN NUREG-0371
- CATEGORY B, C, D ISSUES DESCRIBED IN NUREG-0471
- SUBSET OF CATEGORY A ITEMS IDENTIFIED AS USI's TO BE REPORTED TO CONGRESS 1979:
STATUS REPORTING ON USI's INITIATED (NUREG-0606) 1980:
ALL TMI ISSUES PUBLISHED IN NUREG-0660 AND REQUIREMENTS ON LICENSEES PUBLISHED IN NUREG-0737 I
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USI's and GI's TO BE ADDRESSED (CONT.)
HISTORY 1982:
NRC INITIATED A PRIORITY RANKING SYSTEM (NUREG-0933) FOR ISSUES OTHER THAN USI's and TMI REQUIREMENTS comsUSTIONhENCINEEINNG
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USI's AND GI's TO BE ADDRESSED (CONT.)
GENERIC ISSUE PRIORITY LEVEL (NUREG-0933)
ELGB:
STRONG EFFORT TO ACHIEVE EARLIEST SOLUTION IS JUSTIFIED: SIGNIFICANT SAFETY IMPROVEMENT
(
MEDIUM:
POTENTIAL FOR SAFETY IMPROVEMENT MAY BE SUBSTANTIAL, BUT N0 SIGNIFICANT DEFICIENCY EXISTS.
LOM:
LITTLE OR NO PROSPECT OF SAFETY IMPROVEMENT, BUT NOT ENOUGH INFORMATION EXISTS TO JUSTIFY DROPPING DR0f:
NO MERIT TO ISSUE OR NEGLIGIBLE SAFETY SIGNIFICANCE COMBUSTIONh ENCIMEERf NG
USI's AND GI's TO BE ADDRESSED (CONT.)
LEVEL OF RESOLUTION (NUREG-0933)
POTENTIALLY RESOLVED:
ISSUES FOR WHICH TECHNICAL RESOLUTION IS IDENTIFIED AND EVALUATION NEARING COMPLETION RESOLVED:
ISSUES FOR WHICH RECOMMENDED REQUIREMENTS OR GUIDANCE ARE DOCUMENTED IN AN NRC REPORT OR MEMORANDUM E.0MPLETED:
ISSUES FOR WHICH THE REQUIREMENTS OR GUIDANCE HAVE BEEN PJBLISHED AS A REGULATION OR AS GUIDANCE IN Tile SRP SUPERSEDED:
SPECIFICALLY IDENTIFIED AS HAVING BEEN SUBSUMED OR SUPERSEDED BY ANOTHER ISSUE consNusTioNhENGINEERipH;
i USI's AND GI's TO BE ADDPfiSED (CONT.)
l ISSUE TRACKING I
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NUREG-0606 (AQUA BOOK) FOR USI's o
SAFETY ISSUE MANAGEMENT SYSTEM (SIMS) 1 o
- TMI ISSUES OTHER THAN THOSE IN NUREG-0737
- GENERIC ISSUES OTHER THAN USI's
- HUMAN FACTORS ISSUES o
GIMCS FOR MEDIUM-AND HIGH-PRIORITY GENERIC ISSUES AND USI's b.....no.).
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LIST OF USI's AND GI's TO BE ADDRESSED (FROM GIMCS) l coasmusTion)ENCimEERING
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0 C-E WILL INTEGRATE INPUT FROM OTHER ORGA.NIZATIONS:
EPRI, ARSAP, NRC o
C-E WILL UTILIZE THE EPRI REGULATORY STABILIZATION PROGRAM TO THE MAXIMUM EXTENT PRACTICAL o
C-E WILL UTILIZE ARSAP INPUT comsUSTIONh ENCIMEERING
M 8
EPRI REGULATORY STABILIZATION PROGRAM l
\\ coassusTioN) Enc NEEMNC
scoj TREND OF ISSUES (727)
FIGURE 2-1 C700) 700 -
(
(649)
(703)
(67c) 600 (584)
(629)(63e)
(606)
(588) m W
(549) 500 -
c3,g) (320) 52 w
O 400 -
2 u
c h
300 Z
200 -
i l}-
l 100 - (133)
(137) l f
l
.}
{
0 1978 1979 1960 1981 1982 1983 1984 1985 1955
'I YEAR j
COMBUSTIONhENGINEERING
)
\\
CATEGORIZATION OF ISSUES 0
NOT APPLICABLE TO ALWR DESIGN o
APPLICABLE
- DROP
- RESOLVED
- REMAINING l
l l
l l
COMBU5 TION) ENGINEERING
a DEFINITION OF CATEGORIES o
NOT APPLICABLE:
NO IMPACT ON PLANT DESIGN OR j
CONSTRUCTION CODE 1 - SUPERSEDED CODE 2 - LICENSING ISSUE CODE 3 - NOT AN ISSUE FOR STANDARDIZED DESIGN CODE 4 - OPERATING PLANT ISSUE CODE 5 - NOT A PLANT DESIGN ISSUE (I.E.,
OPERATIONAL ISSUE)
CODE 6 - REGULATORY IMPACT ISSUE comausTion)sMCINEERING
DEFINITION OF CATEGORIES (CONT.)
O DROP ISSUES:
APPLICABLE TO PLANT DESIGN, BUT OF SUCH LOW SIGNIFICANCE THAT FURTHER CONSIDERATION IS NOT JUSTIFIED o
RESOLVED ISSUES:
APPLICABLE ISSUES WHOSE RESOLUTION IS AVAILABLE CODE R - RESOLVED VIA " INFORMAL" DOCUMENTATION (E.G., MEMORANDUM, NUREG)
CODE C - COMPLETED VIA FORMAL DOCUMENTATION (E.G., RULE, SRP) comnumoN)ENCINEER1MG
DEFINITION OF CATEGORIES (CONT.)
0 REMAINING ISSUES:
APPLICABLE ISSUES WHOSE ELEMENTS OF RESOLUTION WILL BE DEFINED VIA DEVELOPMENT OF TOPIC PAPERS l
l 2
i L.........,3.......
.1 1
I l
l ALWR PROCESS FOR TREATING CURRENT ISSUES FIGUPI 6-2
/
CURRENTiS3LT l
\\
ICENTIFifD ISSUE DEFINITION
!! SUE
...IC..{.A..T.I.F.I.C. A..'..i O..N.......................................... j ISSUE i
APPLICABILITY l
ISSUE PRIORITIZATION ISSUE
. [V..A. (,y A..T..! Q.N............................................. ;
I l
l GENERIC TOPIC ISSUE PAPERS RESOLUTION I
p ELEMENTS OF RESOLUTION ISSUE l
....R.LM'F..'.Q.N.........................................
\\
DEVELO? MENT or
/ RANT RECulqMENTS COMBUSTION ENGINEERING
1 l
EPRI/NRC CATEGORIZATION OF USI's AND GI's ISSUES IDENTIFIED (727)
I I
)
v 3,
NOT APPLICAELE APPLICABLE (3ES)
(339) v v
v CROP RESOLVED REMAINING
'6')
(213)
(62)
COMBU5 TION UtCIDLEERING
USE OF EPRI RESULTS O
DOCUMENTS REFERENCED FOR " RESOLVED" ISSUES 0
TOPIC PAPERS DEVELOPED FOR " REMAINING" ISSUES l
coassusTion) mcinematmc
l EXAMPLE:
RESOLVED ISSUES A)
ISSUE:
A-3 TYPE:
UNRESOLVED SAFETY ISSUE TITLE:
WESTINGHOUSE STEAM GENERATOR INTEGRITY IMPACT ON CERTIFICATION:
RESOLVED
REFERENCE:
SECY 84-13B C-E APPLICABILITY:
NOT APPLICABLE B)
ISSUE:
A-4 TYPE:
UNRESOLVED SAFETY ISSUE TITLE:
C-E STEAM GENERATOR TUBE INTEGRITY IMPACT ON CERTIFICATION:
RESOLVED
REFERENCE:
SECY 84-13B C-E APPLICABILITY:
YES comausTion)ENCINEERfMG
EXAMPLE:
REMAINING A)
ISSUE:
A-45 TYPE:
UNRESOLVED SAFETY ISSUE TITLE:
SHUTDOWN DECAY HEAT REMOVAL IMPACT ON CERTIFICATION:
HIGH POTENTIAL C-E APPLICABILITY:
APPLICABLE TO CESSAR-DC
REFERENCES:
EPRI TOPIC PAPER C-E IMPLEMENTATION:
REVISE CESSAR-DC TO INCLUDE SHUTDOWN DEPRESSURIZATION -
MARCH 1988 c
COMBU5T10Mh ENGINEERf MG
i ARSAP PROGRAM INTERFACE o
RESOLUTION OF SOME USI's AND GI's ARE RELATED TO SEVERE ACCIDENT ANALYSIS o
FOR THESE SPECIFIC USI's AND GI's ARSAP TOPIC PAPERS MAY BE WILL BE USED o
C-E's PROGRAM FOR ADDRESSING DEGRADED CORE ISSUES (COMPLIANCE THE SEVERE ACCIDENT POLICY STATEMENT)
WILL USE ARSAP RESULTS AS DESCRIBED TO NRC STAFF ON AUGUST 12, 1987 COMBUSTION)ENCINEER1BHi
1 l
IMPLEMENTATION OF USI AND GI ACCEPTANCE CRITERIA 0
DOCUMENTED ACCEPTANCE CRITERIA WILL BE ADDRESSED DURING THE SYSTEM 80+ DESIGN PROCESS 0
C-E WILL DEVELOP RESOLUTIONS IF ACCEPTANCE CRITERIA ARE NOT ALREADY DOCUMENTED 0
DESIGN DESCRIPTION IN CESSAR-DC WILL BE MODIFIED ACCORDINGLY 0
NRC CLOSE OUT WILL BE PURSUED DURING REVIEW AND CERTIFICATION coassusTIONhENCINEERING
IMPLEMENTATION SCHEDULE o
USI's AND GI's WILL BE ASSIGNED TO CESSAR-DC CHAPTERS AND RESOLUTIONS WILL BE IMPLEMENTED ACCORDINGLY o
THE SCHEDULE FOR RESOLUTION OF THE USI's AND GI's IS THE SAME, THEREFORE, AS THE CESSAR-DC SUBMITTAL SCHEDULE COMBUSTl0Nh ENGINEER 1NC
SUMMARY
l o
GIMCS IDENTIFIES USI's AND GI's FOR SATISFYING THE SEVERE ACCIDENT POLICY STATEMENT 4
o DOCUMENTED ACCEPTANCE CRITERIA FROM EPRI AND ARSAP PROGRAMS WILL BE USED TO MAXIMUM EXTENT PRACTICAL i
o SYSTEM 80+ DESIGN AND CESSAR-DC WILL BE MODIFIED ACCORDINGLY 0
USI's AND GI's WILL BE CLOSED OUT DURING NRC REVIEW AND DESIGN CERTIFICATION consausTiomhfMCINEERING ummmmmmmmmmy
U.uiv.l }u m i g,
i
.~.n..:
9/2/66
' REMAINING ISSUES lasue Short list Requirements Number Number Document Title
~
A-29 SL-1.11 Ch.6 Nuclear Power Plant 6esign for Reduction of
, Vulnerability to Industrial Sabotage A-44 SL-1.6 Ch.d:5.C Station Blockout A-45 SL-1.5 Ch.S Shutdown Decay Heat Removal Requirements A-47 SL-1.13 Ch.10 Safety implications of Control Systems A-48 SL-1.7 Ch.5 Hydrogen Control Measures and Effect of Hydrogen Burns on Safety Equipment B-17 SL-1.16 Ch.10 Criteria for Safety-Related Operator Action B-22 S L-3.1 Ch.4 LWR f uel B-29 SL-3.6 Ch.8 Effectiveness of Ultimate Heat Sinks B-32 SI - 3.6 Ch.8 Ice Effects on Safety-Releted Water Supplies D-2 SL-4.1 Ch.S Emergency Core Cooling System Capability for
(
future Plants ll.E.4.3 SL-1.8 Ch.5 Containment Design--Integrity Check l
2 SL-3.8 Ch.10 failure of Protective Devices on Essential Equipment i
23 SL-1.1 Ch.3 Reeetor Coolant Pump Seels 29 SL-1.2 Ch.3 Bolting Degedation or failure in Nuclear Pover 4
Plants S1 SL-3.7 Ch. 8 Proposed Requirements for improving Reliability of Open Cycle Service Water Systems 67.7,0 SL-1.3 Ch. 3 Steam Generator Staff Actions--Improved Eddy Current Tests 70 SL-1.S Ch/5 PORY and Block Yelve Reliability 7S SL-1.14 Ch.10-Generic Implications of ATWS Events et Setem Nuclear Plant 76 SL-1.13 Ch.10 instrumentation and Control Pover Interactions
.t.
I ret 1AINING ISSUES (Continued)
Issue Short List Requirements Number Number __
Document Title 122.le SL-1.9 Ch. 5 Devis-Besse Loss of All feedveter Event--Common Mode Feilure of Auxiliary feedveter Pump Discharge isoletion Yelves in Closed Position 122 l b SL - 1.9 Ch.5 Devis-Besse Loss of All Feedveter Event--Excessive Delay in Recovery of Auxiliary Feedveter 122It SL-1.9 Ch.5 Davis-Besse Loss of All Feedveter Event--
interruption of Auxiliary feedveter flov C:
SL 1.9 Ch 5 Davis-Besse Loss of All Feedveter Event--Adequa:V of Emergency Procedures,0perator Training and Available Plant Monitoring Systems 1
123 SL-312 Ch.tll Deficiencies in the Regulations Governing DBA and Single failure Criterion Suggested By the Davis Besse incident of June 9,1955 124 SL-1.9 C h. 5 Auxiliary feedveter System Reliability 125.13 SL-1 16 Ch.10 Long-Term Generic Actions es e Result of the Devis-Besse Event of 6/9/85--SPDS Availability 1251.4 S L-1.16 Ch.10 Long-Term Generic Actions es e Result of the Devis-Besse Event of 6/9/B5--Plant Specific Simulator 125.1.5 St-1.16 Ch.10 Long-Te m Generic Actions es a Result of the Devis-%se Event of 6/9/05--Safety Systems Testedin All Conditions Required by Design Basis Analysis 125.1.6 SL - 1.16 Ch.10 Long-Term Generic Actions es e Result of the Devis-Besse Event of 6/9/85--Yelve Torque Limit and Bypass Svitch Settings 12511.7 SL-1.9 Ch.5 Long-Term Generic Actions es e Result of the Devis-Besse Event of 6/9/B5--Reeveluete Provisions to Automatically isolete feedveter from Steem Generator During Line Break
~3~
ret 1AINING ISSUES (continued)
Issue Short List Requirements Number Number Document Title 122.16 SL-1.9 Ch.5 Davis-Besse loss of All feedvster Event--Common Mode failure of Auxiliary feedveter Pump Discherge Isoletion Yelves in Closed Position 122 lb SL - 1.9 Ch 5 Devis-Besse Loss of All feedveter Event--Excessive Delay in Recovery of Auxiliary feedveter 122tc SL-1.9 Ch.5 Devis-Besse Loss of All feedveter Event--
Interruption of Auv111ery feedvater flow ll!
il-1.9 Ch 5 Davis-Bette loss of All feedveter Event-- Adequa;g of Emergency Procedures,0perator Treining and Aveilable Plant Monitoring Systems 123 SL-3.12 Ch.N I Deficiencies in the Regulations Governing DBA and Single failure Criterion Suggested By the Davis Besse Incident of June 9,1965 124 SL-1.9 Ch.5 Auxiliary feedveter System Reliability 125I 3 S L - 1.16 Cn.10 Long-Term Generic Actions as e Result of the Davis-Besse Event of 6/9/85--SPDS Availability 12514 SL - 1.16 Ch.10 Long-Term Generic Actions as a Result of the Devis-Besse Event of 6/9/65--Plant Specific Simuletor 1251.5 SL-1.16 Ch.10 Long-Term Generic Actions as e Result of the Davis-Besse Event of 6/9/05--Sofety Systems Tested in All Conditions Required by Design S$515 Anslysis 125.l.6 SL - 1.16 Ch.10 Long-Term Generie Actions as a Result of the Davis-Besse Event of 6/9/85--Velve Torque Limit and Bypass Svitch Settings 125 Il 'l SL - 1.9 Ch 5 Long-Term Generic Actions as e Result of the Davis-Besse Event of 6/9/65--Reevaluate Provisions to Automatically isolete feedvster from Steam Generator During Line Breal -
O
~
1, l-l REMAINING ISSUES (continued)
Issue Short List Requirements Number
- Numt.er Docume tii Title 125.11.11 SL-1.9 Ch.S Long-TermGeneric Actions es a Result of the Devis-Besse Event of 6/9/85--Recovery of Mein feedveter as Alternative to AfW 12S11.13 SL - 1.16 Ch.10 Long-Term Generic Actions as a Result of the Devis-Besse Event of 6/9/65--Operator Job Aidt 126 SL-313 Ch.3 Reliability of PWR Main Steam Safety Yelves 127 S L - 1.16 Ch 10 Testing and Maintenance of Menuel Velvet in Safet -
9 Related Systems 128 SL-16 Chg/l Electrical Pover Reliability 130 S L-3.6 Ch.8 Essentiel Service Water Pump failures et Multiplent Sites 131' SL-3.14 Ch.3 Potentiel Seismic Interaction involving the Moveble In-Core flux Mapping System in Westinghouse Plants 132 SL-1.S Ch.5 RHR Pumps inside Containment HT.01.3 At. SL-1 16 Ch.10 Human factors Program Plen--Local Control Stetions Hf.01.3.4b SL-1.16 Ch.10 Human factors Program Plan--Annunciators Hf.01.3 4c SL-1.16 Ch.10 Human factors Program Plen--Operational Aids HF.01.3 4d SL - 1.16 Ch 10 Human f actors Program Plen--Automation end Artificial Intelligence HF.01.3 A SL-1 16-Ch.10 Humen f actors Program Plen--Computers and Computer Displays 4
s-.
... - - -, w.r a.s
....._..._m.w..
)
A Ll/* c-ls sis 6 i.(
/
I I
MAJOR ISSUES IN A13fR REVIEW i
~
l j
82 GENERIC SAFETY ISSUES AS OF 7/1/86; PLUS ANY APPLICABLE ONES IDENTIFIED SINCE THEN I
REGULATORY OPTIMIZATION PROPOSALS BY EPRI:
1 LEAK-BEFORE-BREAK METHODOLOGY
- OPERATING BASIS EARTHQUAKES AND DYNAMIC ANALYSIS METHODE SOURCE TERM j
EQUlPMENT SEISMIC QUALIFICATION BY EXPERIENCE
- TORNADO DESIGN l
i BFR MAIN STEAM llNE AND LEAKAGE CONTROL i
1 IIYDROGEN CONTROL IN BTRS BWR STANDBY GAS TREATMENT SYSTEM
]
ELIMINATION OF MISSILE SHIELDS FOR R0D EJECTION j
10 DINE RELEASE CHEMICAL FORM CONTAINMENT IS0lATION
]
APPENDIX R HYDROGEN GENERATION DURING SEVERE ACCIDENTS i
(NOTE: THE ABOVE ITEMS PERTAIN TO CHAPTERS 1. 3 & 5; MORE WILL BE SUBMITTED WITH FUTURE CHAPTERS)
MARGIN TRAI>E-OFFS IN DESIGN IMPROVEMENTS A___________.___