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                '                                                                                                  d p..<.m p              A                                           UNITED STATES s*                              NUCLEAR REGULATORY COMMIS810N WASHINGTON, D.C. 30eeH001 January 7, 1998 APPLICANT: Westinghouse Electric Corporation FACILITY:     AP600
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UNITED STATES p
s NUCLEAR REGULATORY COMMIS810N WASHINGTON, D.C. 30eeH001 January 7, 1998 APPLICANT: Westinghouse Electric Corporation FACILITY:
AP600


==SUBJECT:==
==SUBJECT:==
==SUMMARY==
==SUMMARY==
OF DECEMBER 18,1997, MANAGEMENT MEETING WITH WESTINGHOUSE TO DISCUSS DESIGN CERTIFICATION SCHEDULE FOR THE AP600 The subject meeting was held la the Rockville, Maryland, office of the Nuclear Regulatory Commission between representatives of Westinghouse anct the Nuclear Regulatory Commission staff. Attachment 1 is a list of meeting attendees. Attachments 2 and 3 are the handouts provided during the meeting by the staff and Westinghouse respectively.
OF DECEMBER 18,1997, MANAGEMENT MEETING WITH WESTINGHOUSE TO DISCUSS DESIGN CERTIFICATION SCHEDULE FOR THE AP600 The subject meeting was held la the Rockville, Maryland, office of the Nuclear Regulatory Commission between representatives of Westinghouse anct the Nuclear Regulatory Commission staff. Attachment 1 is a list of meeting attendees. Attachments 2 and 3 are the handouts provided during the meeting by the staff and Westinghouse respectively.
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The meeting began with a discussion of the status of the review. The staff provided a status of the review by Chapter (See attachment 2) and also a breakdown of the final safety evaluation report (FSER) open items by Chapter. The staff's total count of FSER open items to date was 365 while Westinghouse acknowledged receipt of 301 FSER open items. The discrepancy between the counts was partly explained by recently issued items that had not yet been counted in the Westinghouse total.
The meeting began with a discussion of the status of the review. The staff provided a status of the review by Chapter (See attachment 2) and also a breakdown of the final safety evaluation report (FSER) open items by Chapter. The staff's total count of FSER open items to date was 365 while Westinghouse acknowledged receipt of 301 FSER open items. The discrepancy between the counts was partly explained by recently issued items that had not yet been counted in the Westinghouse total.
Westinghouse indicated that it had responded to 162 of the staff's FSER open items. There was a concem expressed about the resolution process for the items. Westinghouse proposed meetings with individual branches to discuss the status of the FSER open items that had been submitted by Westinghouse. Westinghouse believed that this procest was working well in the inspections, tests, analyses, and acceptance criteria, review and that a similar process could be used to elevata issues that the staff and Westinghouse did not agree on to management's attention. The staff and Westinghouse took an action to determine the best approach for resolving FSER open items. Westinghouse and the staff also agreed to have weekly senior manager phone calls and a management meeting in January to discuss the sistus of the review, t
Westinghouse indicated that it had responded to 162 of the staff's FSER open items. There was a concem expressed about the resolution process for the items. Westinghouse proposed meetings with individual branches to discuss the status of the FSER open items that had been submitted by Westinghouse. Westinghouse believed that this procest was working well in the inspections, tests, analyses, and acceptance criteria, review and that a similar process could be used to elevata issues that the staff and Westinghouse did not agree on to management's attention. The staff and Westinghouse took an action to determine the best approach for resolving FSER open items. Westinghouse and the staff also agreed to have weekly senior manager phone calls and a management meeting in January to discuss the sistus of the review, t
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2                   January 7, 1998 Westinghouse also expressed concem over some of the FSER cpen items they had received.
2 January 7, 1998 Westinghouse also expressed concem over some of the FSER cpen items they had received.
Specifically, they were concemed that some issues did not appear to meet the threshold of FSER open items. They also expressed concem with the timeliness of an FSER open item on                     4 WCOBRA/ TRAC for long term cooling concoming a time gap in the code from the end of quenching to the beginning of IRWST injection. Westinghouse bellaved that this question should have been addressed earlier in the review. Westinghouse also expressed concem that they had not yet received comments from the containment systems branch on the shutdown evaluation report and shutdown technicas specifications. Westinghouse was concemed the individual involved with developing questhns may ask questions that were more relevant to the proposed shutdown rule, and not to the curresit regulations.
Specifically, they were concemed that some issues did not appear to meet the threshold of FSER open items. They also expressed concem with the timeliness of an FSER open item on 4
WCOBRA/ TRAC for long term cooling concoming a time gap in the code from the end of quenching to the beginning of IRWST injection. Westinghouse bellaved that this question should have been addressed earlier in the review. Westinghouse also expressed concem that they had not yet received comments from the containment systems branch on the shutdown evaluation report and shutdown technicas specifications. Westinghouse was concemed the individual involved with developing questhns may ask questions that were more relevant to the proposed shutdown rule, and not to the curresit regulations.
The stati and Westinghouse discussed some of the key issues in the review. The staff took an action te provide Westinghouse a position on the time allowed to take a post accident sample, and indicated that the staff's position would be different than the position taken for the evolutionary designs. Westinghouse believed the nurce term issue needed management attention for resolution. The staff and Westinghouse also agreed that several other items may require management attention in order to be resolved. Attachment 4 contains the list of items and a brief explanation of the issue.
The stati and Westinghouse discussed some of the key issues in the review. The staff took an action te provide Westinghouse a position on the time allowed to take a post accident sample, and indicated that the staff's position would be different than the position taken for the evolutionary designs. Westinghouse believed the nurce term issue needed management attention for resolution. The staff and Westinghouse also agreed that several other items may require management attention in order to be resolved. Attachment 4 contains the list of items and a brief explanation of the issue.
The staff informed Westinghouse that the schedule paper for the AP600 final design approval was in concurrence and was expected to be issued to the Commission in the near future. The staff and Westinghouse also discussed the ACRS concems with the code development program that resulted from the ACRS meeting of December 9,1997, through December 12,1997. The staff indicated that their FSER open items in this area had incorporated some of the ACRS concems where it was possible. Westinghouse indicated that it would coontinate with the ACRS the resolution of the commitments it had rnade during the ACRS meeting.
The staff informed Westinghouse that the schedule paper for the AP600 final design approval was in concurrence and was expected to be issued to the Commission in the near future. The staff and Westinghouse also discussed the ACRS concems with the code development program that resulted from the ACRS meeting of December 9,1997, through December 12,1997. The staff indicated that their FSER open items in this area had incorporated some of the ACRS concems where it was possible. Westinghouse indicated that it would coontinate with the ACRS the resolution of the commitments it had rnade during the ACRS meeting.
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==Enclosure:==
==Enclosure:==
As stated cc wlenci: See next page DISTRIBUTION:
As stated cc wlenci: See next page DISTRIBUTION:
See next page DOCUMENT NAME: A:\12_18_MM. SUM To receive a copy of this document, Indicate in the box: "C" = Copy without attachment / enclosure *E" = Copy with attachment! enclosure "N" = No copy _
See next page DOCUMENT NAME: A:\\12_18_MM. SUM To receive a copy of this document, Indicate in the box: "C" = Copy without attachment / enclosure
OFNCE       PM:PDST:DRPM               D:PDST:DRP4]                                 l               l NAME         JMSebrosky:sg j AW 'TROuay_M DATE         01/ 'J/98       V-         01/7 /98 V %-
*E" = Copy with attachment! enclosure "N" = No copy _
OFNCE PM:PDST:DRPM D:PDST:DRP4]
l l
NAME JMSebrosky:sg j AW 'TROuay_M DATE 01/ 'J/98 V-01/7 /98 V %-
OFFICIAL RECORD COPY
OFFICIAL RECORD COPY


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Westinghouse Electric Corporation             Docket No. 52-003 cc:   Mr.- Nicholas J. Liperuto, Manager       Mr. Frank A. Ross
Westinghouse Electric Corporation Docket No. 52-003 cc:
,                  Nuclear Safety and Regulatory Analysis   U.S. Department of Energy, NE 42 Nuclear and Advanced Technology Division Office of LWR Safety and Technology Westinghouse Electric Corporation       19901 Germantown Road P.O. Box 355                             Germantown, MD 20874 Pittsburgh, PA 15230 Mr. Russ Bell Mr. B. A. McIntyre                       Senior Project M'anager, Programs f                 Advanced Plant Safety & Licensing       Nuclear Energy .nstitute Westi.1ghouse Electric corporation       17761 Street. NW Energy Syntems Business Unit             Suite 300 Box 355                                 Washington, DC 20006-3706 Pittsburgh, PA 15230 Ms. Lynn Connor Ms. Cindy L. Haag                       Doc-Search Associates Advanced Plant Safety & Licensing       Post Office Box 34 Westinghouse Electric Corporation       Cabin John, MD 20818 Energy Systems Business Unit Box 355                                 Dr, Craig D. Sawyer. Manager Pittsburgh, PA 15230                     Advanced Reactor Programs GE Nuclear Energy Mr. M. D. Beaumont                       175 Curtner Avenue, MC-754 Nuclear and Advanced Technology Division San Jose, CA 95125 Westinghouse Electric Corporation One Montrose Metro                       Mr. Robert H. Buchholz 11921 Rockville Pik3                     GE Nuclear Energy                   $
Mr.- Nicholas J. Liperuto, Manager Mr. Frank A. Ross Nuclear Safety and Regulatory Analysis U.S. Department of Energy, NE 42 Nuclear and Advanced Technology Division Office of LWR Safety and Technology Westinghouse Electric Corporation 19901 Germantown Road P.O. Box 355 Germantown, MD 20874 Pittsburgh, PA 15230 Mr. Russ Bell Mr. B. A. McIntyre Senior Project M'anager, Programs f
Suite 350                               175 Curtner Avenue, MC-781 Rockville, MD 20852                     San Jose, CA 95125 Mr. Sterling Franks                     Barton Z. Cowan, Esq.
Advanced Plant Safety & Licensing Nuclear Energy.nstitute Westi.1ghouse Electric corporation 17761 Street. NW Energy Syntems Business Unit Suite 300 Box 355 Washington, DC 20006-3706 Pittsburgh, PA 15230 Ms. Lynn Connor Ms. Cindy L. Haag Doc-Search Associates Advanced Plant Safety & Licensing Post Office Box 34 Westinghouse Electric Corporation Cabin John, MD 20818 Energy Systems Business Unit Box 355 Dr, Craig D. Sawyer. Manager Pittsburgh, PA 15230 Advanced Reactor Programs GE Nuclear Energy Mr. M. D. Beaumont 175 Curtner Avenue, MC-754 Nuclear and Advanced Technology Division San Jose, CA 95125 Westinghouse Electric Corporation One Montrose Metro Mr. Robert H. Buchholz 11921 Rockville Pik3 GE Nuclear Energy Suite 350 175 Curtner Avenue, MC-781 Rockville, MD 20852 San Jose, CA 95125 Mr. Sterling Franks Barton Z. Cowan, Esq.
U.S. Department of Energy               Eckert S2amans Cherin & Mellott NE 50                                   600 Grant Street 42nd Floor 19901 Germantown Road                   Pittsburgh, PA 15219 Germantown, MD 20874 Mr. Ed Rodwell, Managar Mr. Charles Thompson, Nuclear Engineer   PWR Design Certification AP600 Certification                     Electric Power Research Institute NE 50                                   3412 Hillview Avenue 19901 Germantown Road                   Palo Alto, CA 94303 Germantown, MD 20874 Mr. Robert Malcrs, P.E.
U.S. Department of Energy Eckert S2amans Cherin & Mellott NE 50 600 Grant Street 42nd Floor 19901 Germantown Road Pittsburgh, PA 15219 Germantown, MD 20874 Mr. Ed Rodwell, Managar Mr. Charles Thompson, Nuclear Engineer PWR Design Certification AP600 Certification Electric Power Research Institute NE 50 3412 Hillview Avenue 19901 Germantown Road Palo Alto, CA 94303 Germantown, MD 20874 Mr. Robert Malcrs, P.E.
Pennsylvania Department of Environmental Protection Bureau of Radiation Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469
Pennsylvania Department of Environmental Protection Bureau of Radiation Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469
* ll WESTINGHOUSE AP400 MANAGEMENT MEETING ATTENDEES DECEMBER 18,1997 NAME                                            ORGANIZATION -                                            ,
            - BOB VIJUK                                        WESTINGHOUSE BRIAN MCINTYRE                                  WESTINGHOUSE CHARLE9 THOMPSON                                  DEPARTMENT OF ENERGY ED RODWELL                                      EPRI DAVID STELLFOX*                                  MCGRAW. HILL BOB MAlERS*                                      PA DEPT OF ENVIRONMENTAL PROTECTION NOEL DUDLEY                                      ACRS JACK ROE
* NRR/DRPM DAVE MATTHEWS*                                  NRR/DRPM TED QUAY                                          NRR/DRPWPDST DINO SCALETTl*                                  NRR/C"PWPDST THOMAS KENYON                                    NRR/DRPWPDST DILL HUFFMAN                                    NRR/DRPWPDST JOE SEBROSKY                                      NRR/DRPWPDST
* PART TIME Attachment 1
                                    .~ , . -                ,


AGENDA FOR DECEMBER 18,1997 SMM
ll WESTINGHOUSE AP400 MANAGEMENT MEETING ATTENDEES DECEMBER 18,1997 NAME ORGANIZATION -
: l. Status of Revow II. Status of Schedule Papst lil. ACRS Cormams with Code Development Program IV. Westinghouse Commants                 .
- BOB VIJUK WESTINGHOUSE BRIAN MCINTYRE WESTINGHOUSE CHARLE9 THOMPSON DEPARTMENT OF ENERGY ED RODWELL EPRI DAVID STELLFOX*
V. Keyissues VI. Reso?vtion Process 4
MCGRAW. HILL BOB MAlERS*
PA DEPT OF ENVIRONMENTAL PROTECTION NOEL DUDLEY ACRS JACK ROE
* NRR/DRPM DAVE MATTHEWS*
NRR/DRPM TED QUAY NRR/DRPWPDST DINO SCALETTl*
NRR/C"PWPDST THOMAS KENYON NRR/DRPWPDST DILL HUFFMAN NRR/DRPWPDST JOE SEBROSKY NRR/DRPWPDST
* PART TIME
.~,. -
 
AGENDA FOR DECEMBER 18,1997 SMM l.
Status of Revow II.
Status of Schedule Papst lil.
ACRS Cormams with Code Development Program IV.
Westinghouse Commants V.
Keyissues VI.
Reso?vtion Process 4
a 4
a 4
Attachment 2-M . . . .
M


    ..              :                                                                                                                                                    i 2       .
i 2
4                                                                                  - STATU3 OF AP400 REVIEW DECEMBER 17,1997 Est.
- STATU3 OF AP400 REVIEW 4
                                                                                                                      % Complete                             Compl.
DECEMBER 17,1997 Est.
* Chapter -                                                 Branch         wr0% w/ools Ols                   Cis   Date I -- 1, intro. & General Discuss.                                 PDST                                 -    !-      -              02/13/98 2, Site Characteristics                                     ECGB,PERB                     10C         92     6             01/30/98 3, Structures, Ce.ip.,                                     ECOB,SPLB                     100         72   42             8 01/30198     '
% Complete Compl.
Equip., & Systems 4, Reactor                                                 SRXB,ECGB                     100         100     0                 -
Chapter -
5, RCS & Components                                         SPLB, SRXB, ECGS               100         91       8             01/30/98 1
Branch wr0% w/ools Ols Cis Date I -- 1, intro. & General Discuss.
4,ESFs                                                     SRXB,SCSB,                         85     80   3 08             12/31/97 ECGB, SPLB, P, SRB 7, IAC                                                     HlCB                           100         98       1             01130/98 l                             S. Electric Power                                           EELS                           100       100     0                 -
PDST 02/13/98 2, Site Characteristics ECGB,PERB 10C 92 6
9, Aux. Systems-                                           SPLB, SRXB, HICB,                   98     87   78'               12/31/97 ECGB 10, Steam & Power Converen                                   SPLB,ECGB                       100         85     4             01/30/98
01/30/98 3, Structures, Ce.ip.,
: 11. RadWaste Mangmnt                                         SPL8                           100         93     1           2 01/30/98 12, Radiation Protection                                     PERB                           100       100     0                 -
ECOB,SPLB 100 72 42 8
13, Conduct of Operations                                   PSGB, HHFB,                     100         a2   24               01/30/98 PERB, TQMB
01/30198 Equip., & Systems 4, Reactor SRXB,ECGB 100 100 0
.                            14, ITP/ ITAAC                                               TQMB,                               19     1[     1'             01130/98 ADT (ITAAC)
5, RCS & Components SPLB, SRXB, ECGS 100 91 8
L 15, Accident Analysis                                       SRXB,PERB,SCSB                 100         88     11             01/30198
01/30/98 1
: 18. Tech. Specs.                                             OTSB, TQMB -                       50     50   33*               12/11/97
4,ESFs SRXB,SCSB, 85 80 3 08 12/31/97 ECGB, SPLB, P, SRB 7, IAC HlCB 100 98 1
.                            17, QA                                                       TQMB                                   0     0                   12/31/97 18 Human Factors                                             HHFB-                           100         91     2             01/30/98 19, Severe Acc.                                             PpSB,SCSB                           89     47   578               12/19/97 20, USIs, GSis, & Oper. Exp.                                 ADT                                 59     49   348               12i31/97 r                            21, Testing & Codes                                         SRXB,SCSB                               5     0 13*               12/31/97 Overall-                                                                                         79     67   385             7
01130/98 l
S. Electric Power EELS 100 100 0
9, Aux. Systems-SPLB, SRXB, HICB, 98 87 78' 12/31/97 ECGB 10, Steam & Power Converen SPLB,ECGB 100 85 4
01/30/98
: 11. RadWaste Mangmnt SPL8 100 93 1
2 01/30/98 12, Radiation Protection PERB 100 100 0
13, Conduct of Operations PSGB, HHFB, 100 a2 24 01/30/98 PERB, TQMB 14, ITP/ ITAAC
: TQMB, 19 1[
1' 01130/98 ADT (ITAAC) 15, Accident Analysis SRXB,PERB,SCSB 100 88 11 01/30198 L
: 18. Tech. Specs.
OTSB, TQMB -
50 50 33*
12/11/97 17, QA TQMB 0
0 12/31/97 18 Human Factors HHFB-100 91 2
01/30/98 19, Severe Acc.
PpSB,SCSB 89 47 578 12/19/97 20, USIs, GSis, & Oper. Exp.
ADT 59 49 348 12i31/97 21, Testing & Codes SRXB,SCSB 5
0 13*
12/31/97 r
Overall-79 67 385 7
* SRXB open issues identified
* SRXB open issues identified
                        ' Fire protection issues identifed
' Fire protection issues identifed
* ITP open issues identifed
* ITP open issues identifed
* Review ongoing -
* Review ongoing -
* Codes issues identifed i-
* Codes issues identifed i-
_.u.-,_,...__.,.                 . . . - . .      -        _ _ , . -    .    -  , .-
_.u.-,_,...__.,.


  ~
Date af
Date af Section(s)     RAls           RAI#                   No.         Comments 2.3         10/07/97 Q470.41F                       01 2.3.6       07/23/97 Position Letter on             01 atm dispersion re:
~
MCR habitability 2.5.1       12/08/97 Q230.141F                       01 2.5.4       12/08/97 Q220.142F-144F                 03 3.2.1       12/04/97 Q210.234F                       01 3.2.2       17104/97 Q210.235F                       01 3.4.1       12/09/97 Q410.381F-395F                 015 3.5         12/12/97 Q410.412F                       01   General Q for 3.5 3.5.1.1     12/12/97 Q410A04F-405F                   02 3.5.1.2     12/12/97 Q410.406F-407F                 02 3.5.1.4     12/12/97 Q410.408F-409F                 02 3.5.2       12/12/97 Q410.410F-411F                 02 3.6.1       12/17/97 Q410.396F-403F,                 09 Q410.413F 3.7.2       12/09/97 Q220.112F-118F                 07 3.8.2       12/09/97 Q220.119F-120F ,               02 3.8.3       12/09/97 Q220.121F-123F                 03
Section(s)
;                        3.8.4       12/09/97 Q220.124F-128F                 G5 3.8.5                 Q220.129F-130F                 O2 3.9.3       11/17/97 Q210.232F-233F                 C2 3.9.6       05/29/97 Position Ltr on ADS             03   See Section 5.2.5 for RAls 07/29/97 Position Ltr on ADS             C2   on PlV concerns 3.11.3-     10/09/97 Q270.15F                       04 Q270.16-270.18F 5.2.1       10/16/97 Q230.140F                       01 5.2.5       10/16/97 Q250.30F-33F                   04 5.4.3       12/10/97 Q440.758F-759F,                 03 Q230.140F                                                     -
RAls RAI#
No.
Comments 2.3 10/07/97 Q470.41F 01 2.3.6 07/23/97 Position Letter on 01 atm dispersion re:
MCR habitability 2.5.1 12/08/97 Q230.141F 01 2.5.4 12/08/97 Q220.142F-144F 03 3.2.1 12/04/97 Q210.234F 01 3.2.2 17104/97 Q210.235F 01 3.4.1 12/09/97 Q410.381F-395F 015 3.5 12/12/97 Q410.412F 01 General Q for 3.5 3.5.1.1 12/12/97 Q410A04F-405F 02 3.5.1.2 12/12/97 Q410.406F-407F 02 3.5.1.4 12/12/97 Q410.408F-409F 02 3.5.2 12/12/97 Q410.410F-411F 02 3.6.1 12/17/97 Q410.396F-403F, 09 Q410.413F 3.7.2 12/09/97 Q220.112F-118F 07 3.8.2 12/09/97 Q220.119F-120F,
02 3.8.3 12/09/97 Q220.121F-123F 03 3.8.4 12/09/97 Q220.124F-128F G5 3.8.5 Q220.129F-130F O2 3.9.3 11/17/97 Q210.232F-233F C2 3.9.6 05/29/97 Position Ltr on ADS 03 See Section 5.2.5 for RAls 07/29/97 Position Ltr on ADS C2 on PlV concerns 3.11.3-10/09/97 Q270.15F 04 Q270.16-270.18F 5.2.1 10/16/97 Q230.140F 01 5.2.5 10/16/97 Q250.30F-33F 04 5.4.3 12/10/97 Q440.758F-759F, 03 Q230.140F


    .    :                                                                                                              l i
6.1.2 07/30/97 Position Letter on-01
6.1.2     07/30/97           Position Letter on-         01                                 )
)
contmnt coatings                                                 !
contmnt coatings 6.2.1 10/16/97 Q480.1081F -
6.2.1     10/16/97           Q480.1081F -                 01 6.2.5     10/22/97           Q480.1082F 1083F             O2; 6.2.8     12/08/97           Q480.1104F 1111F           08 6.3                           Q440.793F-794F             O2 6.4       12/02/97           Q470.46F                   01 12/08/97-           Q410.366F-380F             015 7.3.6     12/02/97           Q420,127F                   01 9.1.3                         Q410.436F                   01
01 6.2.5 10/22/97 Q480.1082F 1083F O2; 6.2.8 12/08/97 Q480.1104F 1111F 08 6.3 Q440.793F-794F O2 6.4 12/02/97 Q470.46F 01 12/08/97-Q410.366F-380F 015 7.3.6 12/02/97 Q420,127F 01 9.1.3 Q410.436F 01
                            ~? 3,1   10/20/97           Q410.308F409F               O2 9.3.2     10/20/97           Q410.310F                   01 6.3.5     10/20/97           0410.311F-312F             O2 9.4                           Q410.415F-418F             04 9.4.1                         Q410.41LF-435F             0 17 9.4.2     12/09/97           Q410.339F-341F             03 9.4.3     12/09/97           Q410.342F-347F             06 9.4.6     12/09/97           Q410.348F-351F             04 9.4.7     12/09/97           Q410.352F-355F '           04 9.4.8     12/C9/97           Q410.356F                   01 9.4.9     12/09/97           Q410.357F-358F             O2 9.4.10   12/09/97           Q410.359F-361F             03 9.4.11   12/09/97           Q410.362F-365F             04 l
~? 3,1 10/20/97 Q410.308F409F O2 9.3.2 10/20/97 Q410.310F 01 6.3.5 10/20/97 0410.311F-312F O2 9.4 Q410.415F-418F 04 9.4.1 Q410.41LF-435F 0 17 9.4.2 12/09/97 Q410.339F-341F 03 9.4.3 12/09/97 Q410.342F-347F 06 9.4.6 12/09/97 Q410.348F-351F 04 9.4.7 12/09/97 Q410.352F-355F '
9.5.1                         Q280.3?F-37F               06 9.5,4     10/30/97             Q410.321F-324F             04 9.5.5     10/30/97             Q410.325F-328F             04 i-                         9.5.6     10/30/97             Q410.329F-331F             03 9.5.7     10/30/97             Q410.332F-334F             03
04 9.4.8 12/C9/97 Q410.356F 01 9.4.9 12/09/97 Q410.357F-358F O2 9.4.10 12/09/97 Q410.359F-361F 03 l
9.4.11 12/09/97 Q410.362F-365F 04 9.5.1 Q280.3?F-37F 06 9.5,4 10/30/97 Q410.321F-324F 04 9.5.5 10/30/97 Q410.325F-328F 04 i-9.5.6 10/30/97 Q410.329F-331F 03 9.5.7 10/30/97 Q410.332F-334F 03
?
?
9.5.8     10/30/97             Q410.535F-338F             04 10.4.1-   10/10/97             0410.304F                 01'
9.5.8 10/30/97 Q410.535F-338F 04 10.4.1-10/10/97 0410.304F 01'
    -.L ,  + - _ _ . _ ,                         , - ,        ,      - - ._ , , -      . . - - . - _ - - .
-.L
+ - _ _. _,


I 10.4.3                     10/10/97                     Q410.305F                 01 10.4.5                     10/10/97                     Q410.306F                 01 10.4.7                     10/10/97                     Q410.307F                 01 11.4.1                     10/20/97                     Q460.28F                   01 13.3                       11/04/97                     100.32F-33F               O2 13.6                         12/15/97                   0920.6F-27F               O22 14.1                                                                                           issues sent 06/25/97; Update to be issued shortly.
I 10.4.3 10/10/97 Q410.305F 01 10.4.5 10/10/97 Q410.306F 01 10.4.7 10/10/97 Q410.307F 01 11.4.1 10/20/97 Q460.28F 01 13.3 11/04/97 100.32F-33F O2 13.6 12/15/97 0920.6F-27F O22 14.1 issues sent 06/25/97; Update to be issued shortly.
14.3                         11/06/97                   Q640.165                   01 15.2                         12/04/97                   Q440.740F-745F             06 12/09/97                 Q440.748F                 01 15.3                           11/06/97                 Q470.42F-44F               O2 15.3.7                         10/27/97                 Q410.320F                 01 16.1                           11/26/97                 Q470.45F .                 01 11/26/97                 Q480.1088F-1103F           016 11/26/97                 Q420.126F                   01 12/16/97               Q440.776F-786F,             013 Q440.191F-192F 12/17/97               0480.1115F                 01 12/17/97               Q410.414F                   01 16.L7                           10/17/97               Q630.15F                 ,  L1 18.13                           06/13/97               .cosition Ltr - Com-puterized Proc.
14.3 11/06/97 Q640.165 01 15.2 12/04/97 Q440.740F-745F 06 12/09/97 Q440.748F 01 15.3 11/06/97 Q470.42F-44F O2 15.3.7 10/27/97 Q410.320F 01 16.1 11/26/97 Q470.45F.
08/28/97                 Telecon summaries 09/16/97                 Computerized Proc.
01 11/26/97 Q480.1088F-1103F 016 11/26/97 Q420.126F 01 12/16/97 Q440.776F-786F, 013 Q440.191F-192F 12/17/97 0480.1115F 01 12/17/97 Q410.414F 01 16.L7 10/17/97 Q630.15F L1 18.13 06/13/97
09/16/97                 0 640.98-99               02 T O 1.3                           11/07/97               0720.430F-434F             05           Except 9.1.3.2-9.1.3.4 11/19/97             Q720.435F-438F             04 19.1.7                             10/22/97             0720.423F                 01 19.1.8                             11/19/97             Q720.439F-444F             06 19.2.3                           09/11/97             Q720.414 417               04 10/22/97             Q720.418F-420F             03 12/08/97           Q720.454F-455F             O2 11/04/97           Q720.424F-429F             05 12/08/97           Q720.456F-457F             O2 19.2.5                               10/22/97           Q720.421F-422F             O2 3
.cosition Ltr - Com-puterized Proc.
08/28/97 Telecon summaries 09/16/97 Computerized Proc.
09/16/97 0 640.98-99 02 T O 1.3 11/07/97 0720.430F-434F 05 Except 9.1.3.2-9.1.3.4 11/19/97 Q720.435F-438F 04 19.1.7 10/22/97 0720.423F 01 19.1.8 11/19/97 Q720.439F-444F 06 19.2.3 09/11/97 Q720.414 417 04 10/22/97 Q720.418F-420F 03 12/08/97 Q720.454F-455F O2 11/04/97 Q720.424F-429F 05 12/08/97 Q720.456F-457F O2 19.2.5 10/22/97 Q720.421F-422F O2 3


                                                    , ,              .y y.;
.y y.;
                                                                              . u _,. 7, ._, _ ... ,  . . _ _ . . . ,    . .        _ __
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            .                                                                                                                                          8 19.2.6         09/18/97             Position Letter on     01 ult capcty. of cont.
8 19.2.6 09/18/97 Position Letter on 01 ult capcty. of cont.
19.3           12/11/97             Q440.763F-775F --       013-' Shutdown risk 19.4           12/11/97             Q720.445F-453F         09       Seismic margina A-43           10/06/97             0650.10F               01 B-36           12/12/97             Q650.15F               01                                                                   :
19.3 12/11/97 Q440.763F-775F --
846             12/12/97             Q650.16F               01 --
013-'
C-10           10/06/97             Q650.11F               01 43             12/12/97             Q650.17F               01 82             12/12/97             Q650.18F                 01 83             12/12/97             Q650.19F                 01 124             12/12/97             Q650.20F                 01 II.B.8         10/06/97             Q650.12F                 01 II.D.1         06/11/97             Q650.1                   01
Shutdown risk 19.4 12/11/97 Q720.445F-453F 09 Seismic margina A-43 10/06/97 0650.10F 01 B-36 12/12/97 Q650.15F 01 846 12/12/97 Q650.16F 01 --
                                                                                        .y II.E.1.3       12!'2/97             Q650.21F                 01 Ill.D.3.3       10/07/97             Q650.9F                 01 Ill.D.3.4       12/12/97             Q650.22F                 01 20.7           11/07/97             Q650.13F-14F             O2 BlAO-10         12/12/97             Q650.30F                 01 BL-80-24       12/12/97             0650.23F                 01 BL-61-02       06/11/97             Q650.5                   01 BL-84-03       12/12/97             Q650.24F                 01 BL-96-02       12/12/97             Q650.31F-               01 GL80-009       12/12/97- Q650.25F                           01
C-10 10/06/97 Q650.11F 01 43 12/12/97 Q650.17F 01 82 12/12/97 Q650.18F 01 83 12/12/97 Q650.19F 01 124 12/12/97 Q650.20F 01 II.B.8 10/06/97 Q650.12F 01 II.D.1 06/11/97 Q650.1 01
.                    GL80-077       12/12/97:           Q650.32F                 01 GL80-088       06/11/97             Q650.6                   01 GL81-038         12/12/97           Qt$50.33F               01                                   _.
.y II.E.1.3 12!'2/97 Q650.21F 01 Ill.D.3.3 10/07/97 Q650.9F 01 Ill.D.3.4 12/12/97 Q650.22F 01 20.7 11/07/97 Q650.13F-14F O2 BlAO-10 12/12/97 Q650.30F 01 BL-80-24 12/12/97 0650.23F 01 BL-61-02 06/11/97 Q650.5 01 BL-84-03 12/12/97 Q650.24F 01 BL-96-02 12/12/97 Q650.31F-01 GL80-009 12/12/97-Q650.25F 01 GL80-077 12/12/97:
GL81-039         12/12/97           Q650.26F                 01 GL84-12         12/12/97             Q650.27F               01 d
Q650.32F 01 GL80-088 06/11/97 Q650.6 01 GL81-038 12/12/97 Qt$50.33F 01 GL81-039 12/12/97 Q650.26F 01 GL84-12 12/12/97 Q650.27F 01 d
                                                                                                                                . _ .-     . . ,,.r. y
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I GL85-13                           .12/12/97               0650.34F -                             01 GL87-06                           06/11/97               0650.2                                 01 l
-AJJ--iii4444-.A-a++
GL88-14                           12/12/97               Q650.28F -                             01                                                                                                         !
4
GL89-04                           06/11/97               Q650.7                                 01 GL89-10                           06/11/97               Q650.8                                 01 GL89-13                           12/12/97               Q650.29F                               01 GL95-07                           06/11/97               Q650.3                                 01 GL96-05                           06/11/97               Q650.4 01 21.2                                                     Q440.788F-790F                         03 21.6.1                             10/16/97               Q440.735F-737F                         03         LOFTRAN.
.2
21.6.2                           08/13/97               Q440.721                               01         NOTRUMP 21.6.3                                                   0440.738F-739F                         O2         WCOBRATTRAC - LBLOCA 21.6.4                             12/09/97               Q440.760F-761F                         O2         WCOBRA/ TRAC - LTC 12/10/97               0440.762F                             01 21.6.5                             11/18/97               Q480.1084F -                           01         WGOTHIC RAIS Abbreviations:
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01 GL89-04 06/11/97 Q650.7 01 GL89-10 06/11/97 Q650.8 01 GL89-13 12/12/97 Q650.29F 01 GL95-07 06/11/97 Q650.3 01 GL96-05 06/11/97 Q650.4 01 21.2 Q440.788F-790F 03 21.6.1 10/16/97 Q440.735F-737F 03 LOFTRAN.
21.6.2 08/13/97 Q440.721 01 NOTRUMP 21.6.3 0440.738F-739F O2 WCOBRATTRAC - LBLOCA 21.6.4 12/09/97 Q440.760F-761F O2 WCOBRA/ TRAC - LTC 12/10/97 0440.762F 01 21.6.5 11/18/97 Q480.1084F -
01 WGOTHIC RAIS Abbreviations:
0 - Open item C - Confirmatory item L - COL Action item 4
0 - Open item C - Confirmatory item L - COL Action item 4
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FSER OPENITEM RESPONSE RECORD FOR 12/1787 I Tott.1 number of FSER Total number of FSER ltems Received Items with a Response Returned to NRC Count cs of 12/187 125 25 Count as of 12/15S7 244 135
244                                        135 Count as of 12/1767                                                 301                                       162 I
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  +
+
lasues that may resulm mananoment attention for resolution:
lasues that may resulm mananoment attention for resolution:
: ASME Classification of the CVCS System Piping .
: ASME Classification of the CVCS System Piping.
                - The CVCS for the AP600 consists of reactor coolant pressure boundary piping that Westinghouse wants an exemption from classifying under ASME Section Ill. The staff is considering the Westinghouse proposal.
- The CVCS for the AP600 consists of reactor coolant pressure boundary piping that Westinghouse wants an exemption from classifying under ASME Section Ill. The staff is considering the Westinghouse proposal.
Treatment of Pressure Isolation Valves Tha staff believes that several system valves in reactor coolant piping penetrating the containment should be treated as PlVs even though the valves do not meet the conventional definitions of PlVs. - Westinghouse has not agreed to incorporate the valves requested by the staff. The staff is reconsidering its position Safety Classification of Containment Coatings in a {{letter dated|date=November 21, 1997|text=November 21,1997, letter}}, Westinghouse stated that the coatings uted in the vicinity of the containment recirculation screens will be classified as safety related & all other coatings inside containment are classified as nonsafety-related.
Treatment of Pressure Isolation Valves Tha staff believes that several system valves in reactor coolant piping penetrating the containment should be treated as PlVs even though the valves do not meet the conventional definitions of PlVs. - Westinghouse has not agreed to incorporate the valves requested by the staff. The staff is reconsidering its position Safety Classification of Containment Coatings in a {{letter dated|date=November 21, 1997|text=November 21,1997, letter}}, Westinghouse stated that the coatings uted in the vicinity of the containment recirculation screens will be classified as safety related & all other coatings inside containment are classified as nonsafety-related.
Based on a preliminary review of Westinghouse's response, the division of engineering does not agree with Westinghouse and believes that all coatings inside containment need to be classified as safety related.
Based on a preliminary review of Westinghouse's response, the division of engineering does not agree with Westinghouse and believes that all coatings inside containment need to be classified as safety related.
Concems about Westinghouse QA controls The staff and ACRS have found errors in documentation and submittals related to the AP600 project which reflects on the overall quality of the Westinghouse application. The staff has not yet d2cided what action is necessary in this regard.
Concems about Westinghouse QA controls The staff and ACRS have found errors in documentation and submittals related to the AP600 project which reflects on the overall quality of the Westinghouse application. The staff has not yet d2cided what action is necessary in this regard.
ITAAC Westinghouse has not provided sufficient information for many ITAAC despite repeated requests by the staff.
ITAAC Westinghouse has not provided sufficient information for many ITAAC despite repeated requests by the staff.
The ITAAC cannot be completed until all of the open items that affect the design are resolved e            Source Term
The ITAAC cannot be completed until all of the open items that affect the design are resolved Source Term e
                    . Westinghouse has pcoposed an attemative to using NURr                           s values for EQ, shleiding, vital area Lccess, and equipment survivability, i,,e proposal is under staff consideration.
. Westinghouse has pcoposed an attemative to using NURr s values for EQ, shleiding, vital area Lccess, and equipment survivability, i,,e proposal is under staff consideration.
NOTRUMP
NOTRUMP
                  ' The staff has only reviewed the AP600 verQn of the NOTRUMP code relative to changes from tne approved 1985 version of the pode. The ACRS has recently questioned whether this approach was 6dequate in consideration of changes made to the 1985 code numerics.
' The staff has only reviewed the AP600 verQn of the NOTRUMP code relative to changes from tne approved 1985 version of the pode. The ACRS has recently questioned whether this approach was 6dequate in consideration of changes made to the 1985 code numerics.
The staff is formulating its posit;on en this concem.
The staff is formulating its posit;on en this concem.  
Attachment 4


      ~       .      -.        -                  _ . _ _ _ _ - . -        -              .  .    . . .  .. ,
~
2-WCCBRNTRAC
2-WCCBRNTRAC
                    - The staff is concemed that it cannot approve the use of WCOBRA/ TRAC for AP600 when the docst>nentation of the code for operating plants has not yet been completed.
- The staff is concemed that it cannot approve the use of WCOBRA/ TRAC for AP600 when the docst>nentation of the code for operating plants has not yet been completed.
WGOTHIC
WGOTHIC The open issues identified to Westinghouse in late November 1997. The FSER input is due on December 31,1997.
                    -    The open issues identified to Westinghouse in late November 1997. The FSER input is       '
due on December 31,1997.
Fire Protection
Fire Protection
                    - The open issues were identified to Westinghouse on 11/26/97. The FSER input is due December 31,1997 i
- The open issues were identified to Westinghouse on 11/26/97. The FSER input is due December 31,1997 i
4}}
4}}

Latest revision as of 10:51, 10 December 2024

Summary of 971218 Meeting W/Westinghouse in Rockville,Md to Discuss Design Certification Schedule for AP600 Review
ML20198H562
Person / Time
Site: 05200003
Issue date: 01/07/1998
From: Joseph Sebrosky
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
NUDOCS 9801130339
Download: ML20198H562 (17)
v • d • e


Text

. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - -

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p..<.m A

UNITED STATES p

s NUCLEAR REGULATORY COMMIS810N WASHINGTON, D.C. 30eeH001 January 7, 1998 APPLICANT: Westinghouse Electric Corporation FACILITY:

AP600

SUBJECT:

SUMMARY

OF DECEMBER 18,1997, MANAGEMENT MEETING WITH WESTINGHOUSE TO DISCUSS DESIGN CERTIFICATION SCHEDULE FOR THE AP600 The subject meeting was held la the Rockville, Maryland, office of the Nuclear Regulatory Commission between representatives of Westinghouse anct the Nuclear Regulatory Commission staff. Attachment 1 is a list of meeting attendees. Attachments 2 and 3 are the handouts provided during the meeting by the staff and Westinghouse respectively.

The purposs of the meeting was to discuss the schedule for the AP600 review. The meeting was one in a series of meetings scheduled in the October through December time frame to discuss the progress of the review, and to elevate schedule impact issues to management's attention as soon as possible.

The meeting began with a discussion of the status of the review. The staff provided a status of the review by Chapter (See attachment 2) and also a breakdown of the final safety evaluation report (FSER) open items by Chapter. The staff's total count of FSER open items to date was 365 while Westinghouse acknowledged receipt of 301 FSER open items. The discrepancy between the counts was partly explained by recently issued items that had not yet been counted in the Westinghouse total.

Westinghouse indicated that it had responded to 162 of the staff's FSER open items. There was a concem expressed about the resolution process for the items. Westinghouse proposed meetings with individual branches to discuss the status of the FSER open items that had been submitted by Westinghouse. Westinghouse believed that this procest was working well in the inspections, tests, analyses, and acceptance criteria, review and that a similar process could be used to elevata issues that the staff and Westinghouse did not agree on to management's attention. The staff and Westinghouse took an action to determine the best approach for resolving FSER open items. Westinghouse and the staff also agreed to have weekly senior manager phone calls and a management meeting in January to discuss the sistus of the review, t

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9901130339 990107 PDR ADOCK 05200003 A

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2 January 7, 1998 Westinghouse also expressed concem over some of the FSER cpen items they had received.

Specifically, they were concemed that some issues did not appear to meet the threshold of FSER open items. They also expressed concem with the timeliness of an FSER open item on 4

WCOBRA/ TRAC for long term cooling concoming a time gap in the code from the end of quenching to the beginning of IRWST injection. Westinghouse bellaved that this question should have been addressed earlier in the review. Westinghouse also expressed concem that they had not yet received comments from the containment systems branch on the shutdown evaluation report and shutdown technicas specifications. Westinghouse was concemed the individual involved with developing questhns may ask questions that were more relevant to the proposed shutdown rule, and not to the curresit regulations.

The stati and Westinghouse discussed some of the key issues in the review. The staff took an action te provide Westinghouse a position on the time allowed to take a post accident sample, and indicated that the staff's position would be different than the position taken for the evolutionary designs. Westinghouse believed the nurce term issue needed management attention for resolution. The staff and Westinghouse also agreed that several other items may require management attention in order to be resolved. Attachment 4 contains the list of items and a brief explanation of the issue.

The staff informed Westinghouse that the schedule paper for the AP600 final design approval was in concurrence and was expected to be issued to the Commission in the near future. The staff and Westinghouse also discussed the ACRS concems with the code development program that resulted from the ACRS meeting of December 9,1997, through December 12,1997. The staff indicated that their FSER open items in this area had incorporated some of the ACRS concems where it was possible. Westinghouse indicated that it would coontinate with the ACRS the resolution of the commitments it had rnade during the ACRS meeting.

A draft of this meeting summary was provided to Westinghouse to allow them the opportunity to comment on the summary prior to issuance, original signed by:

Joseph M. Sebrosky, Project Manager Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No. 52 003

Enclosure:

As stated cc wlenci: See next page DISTRIBUTION:

See next page DOCUMENT NAME: A:\\12_18_MM. SUM To receive a copy of this document, Indicate in the box: "C" = Copy without attachment / enclosure

  • E" = Copy with attachment! enclosure "N" = No copy _

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NAME JMSebrosky:sg j AW 'TROuay_M DATE 01/ 'J/98 V-01/7 /98 V %-

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Westinghouse Electric Corporation Docket No.52-003 cc:

Mr.- Nicholas J. Liperuto, Manager Mr. Frank A. Ross Nuclear Safety and Regulatory Analysis U.S. Department of Energy, NE 42 Nuclear and Advanced Technology Division Office of LWR Safety and Technology Westinghouse Electric Corporation 19901 Germantown Road P.O. Box 355 Germantown, MD 20874 Pittsburgh, PA 15230 Mr. Russ Bell Mr. B. A. McIntyre Senior Project M'anager, Programs f

Advanced Plant Safety & Licensing Nuclear Energy.nstitute Westi.1ghouse Electric corporation 17761 Street. NW Energy Syntems Business Unit Suite 300 Box 355 Washington, DC 20006-3706 Pittsburgh, PA 15230 Ms. Lynn Connor Ms. Cindy L. Haag Doc-Search Associates Advanced Plant Safety & Licensing Post Office Box 34 Westinghouse Electric Corporation Cabin John, MD 20818 Energy Systems Business Unit Box 355 Dr, Craig D. Sawyer. Manager Pittsburgh, PA 15230 Advanced Reactor Programs GE Nuclear Energy Mr. M. D. Beaumont 175 Curtner Avenue, MC-754 Nuclear and Advanced Technology Division San Jose, CA 95125 Westinghouse Electric Corporation One Montrose Metro Mr. Robert H. Buchholz 11921 Rockville Pik3 GE Nuclear Energy Suite 350 175 Curtner Avenue, MC-781 Rockville, MD 20852 San Jose, CA 95125 Mr. Sterling Franks Barton Z. Cowan, Esq.

U.S. Department of Energy Eckert S2amans Cherin & Mellott NE 50 600 Grant Street 42nd Floor 19901 Germantown Road Pittsburgh, PA 15219 Germantown, MD 20874 Mr. Ed Rodwell, Managar Mr. Charles Thompson, Nuclear Engineer PWR Design Certification AP600 Certification Electric Power Research Institute NE 50 3412 Hillview Avenue 19901 Germantown Road Palo Alto, CA 94303 Germantown, MD 20874 Mr. Robert Malcrs, P.E.

Pennsylvania Department of Environmental Protection Bureau of Radiation Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469

ll WESTINGHOUSE AP400 MANAGEMENT MEETING ATTENDEES DECEMBER 18,1997 NAME ORGANIZATION -

- BOB VIJUK WESTINGHOUSE BRIAN MCINTYRE WESTINGHOUSE CHARLE9 THOMPSON DEPARTMENT OF ENERGY ED RODWELL EPRI DAVID STELLFOX*

MCGRAW. HILL BOB MAlERS*

PA DEPT OF ENVIRONMENTAL PROTECTION NOEL DUDLEY ACRS JACK ROE

  • NRR/DRPM DAVE MATTHEWS*

NRR/DRPM TED QUAY NRR/DRPWPDST DINO SCALETTl*

NRR/C"PWPDST THOMAS KENYON NRR/DRPWPDST DILL HUFFMAN NRR/DRPWPDST JOE SEBROSKY NRR/DRPWPDST

  • PART TIME

.~,. -

AGENDA FOR DECEMBER 18,1997 SMM l.

Status of Revow II.

Status of Schedule Papst lil.

ACRS Cormams with Code Development Program IV.

Westinghouse Commants V.

Keyissues VI.

Reso?vtion Process 4

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- STATU3 OF AP400 REVIEW 4

DECEMBER 17,1997 Est.

% Complete Compl.

Chapter -

Branch wr0% w/ools Ols Cis Date I -- 1, intro. & General Discuss.

PDST 02/13/98 2, Site Characteristics ECGB,PERB 10C 92 6

01/30/98 3, Structures, Ce.ip.,

ECOB,SPLB 100 72 42 8

01/30198 Equip., & Systems 4, Reactor SRXB,ECGB 100 100 0

5, RCS & Components SPLB, SRXB, ECGS 100 91 8

01/30/98 1

4,ESFs SRXB,SCSB, 85 80 3 08 12/31/97 ECGB, SPLB, P, SRB 7, IAC HlCB 100 98 1

01130/98 l

S. Electric Power EELS 100 100 0

9, Aux. Systems-SPLB, SRXB, HICB, 98 87 78' 12/31/97 ECGB 10, Steam & Power Converen SPLB,ECGB 100 85 4

01/30/98

11. RadWaste Mangmnt SPL8 100 93 1

2 01/30/98 12, Radiation Protection PERB 100 100 0

13, Conduct of Operations PSGB, HHFB, 100 a2 24 01/30/98 PERB, TQMB 14, ITP/ ITAAC

TQMB, 19 1[

1' 01130/98 ADT (ITAAC) 15, Accident Analysis SRXB,PERB,SCSB 100 88 11 01/30198 L

18. Tech. Specs.

OTSB, TQMB -

50 50 33*

12/11/97 17, QA TQMB 0

0 12/31/97 18 Human Factors HHFB-100 91 2

01/30/98 19, Severe Acc.

PpSB,SCSB 89 47 578 12/19/97 20, USIs, GSis, & Oper. Exp.

ADT 59 49 348 12i31/97 21, Testing & Codes SRXB,SCSB 5

0 13*

12/31/97 r

Overall-79 67 385 7

  • SRXB open issues identified

' Fire protection issues identifed

  • ITP open issues identifed
  • Review ongoing -
  • Codes issues identifed i-

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Date af

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Section(s)

RAls RAI#

No.

Comments 2.3 10/07/97 Q470.41F 01 2.3.6 07/23/97 Position Letter on 01 atm dispersion re:

MCR habitability 2.5.1 12/08/97 Q230.141F 01 2.5.4 12/08/97 Q220.142F-144F 03 3.2.1 12/04/97 Q210.234F 01 3.2.2 17104/97 Q210.235F 01 3.4.1 12/09/97 Q410.381F-395F 015 3.5 12/12/97 Q410.412F 01 General Q for 3.5 3.5.1.1 12/12/97 Q410A04F-405F 02 3.5.1.2 12/12/97 Q410.406F-407F 02 3.5.1.4 12/12/97 Q410.408F-409F 02 3.5.2 12/12/97 Q410.410F-411F 02 3.6.1 12/17/97 Q410.396F-403F, 09 Q410.413F 3.7.2 12/09/97 Q220.112F-118F 07 3.8.2 12/09/97 Q220.119F-120F,

02 3.8.3 12/09/97 Q220.121F-123F 03 3.8.4 12/09/97 Q220.124F-128F G5 3.8.5 Q220.129F-130F O2 3.9.3 11/17/97 Q210.232F-233F C2 3.9.6 05/29/97 Position Ltr on ADS 03 See Section 5.2.5 for RAls 07/29/97 Position Ltr on ADS C2 on PlV concerns 3.11.3-10/09/97 Q270.15F 04 Q270.16-270.18F 5.2.1 10/16/97 Q230.140F 01 5.2.5 10/16/97 Q250.30F-33F 04 5.4.3 12/10/97 Q440.758F-759F, 03 Q230.140F

6.1.2 07/30/97 Position Letter on-01

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contmnt coatings 6.2.1 10/16/97 Q480.1081F -

01 6.2.5 10/22/97 Q480.1082F 1083F O2; 6.2.8 12/08/97 Q480.1104F 1111F 08 6.3 Q440.793F-794F O2 6.4 12/02/97 Q470.46F 01 12/08/97-Q410.366F-380F 015 7.3.6 12/02/97 Q420,127F 01 9.1.3 Q410.436F 01

~? 3,1 10/20/97 Q410.308F409F O2 9.3.2 10/20/97 Q410.310F 01 6.3.5 10/20/97 0410.311F-312F O2 9.4 Q410.415F-418F 04 9.4.1 Q410.41LF-435F 0 17 9.4.2 12/09/97 Q410.339F-341F 03 9.4.3 12/09/97 Q410.342F-347F 06 9.4.6 12/09/97 Q410.348F-351F 04 9.4.7 12/09/97 Q410.352F-355F '

04 9.4.8 12/C9/97 Q410.356F 01 9.4.9 12/09/97 Q410.357F-358F O2 9.4.10 12/09/97 Q410.359F-361F 03 l

9.4.11 12/09/97 Q410.362F-365F 04 9.5.1 Q280.3?F-37F 06 9.5,4 10/30/97 Q410.321F-324F 04 9.5.5 10/30/97 Q410.325F-328F 04 i-9.5.6 10/30/97 Q410.329F-331F 03 9.5.7 10/30/97 Q410.332F-334F 03

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9.5.8 10/30/97 Q410.535F-338F 04 10.4.1-10/10/97 0410.304F 01'

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I 10.4.3 10/10/97 Q410.305F 01 10.4.5 10/10/97 Q410.306F 01 10.4.7 10/10/97 Q410.307F 01 11.4.1 10/20/97 Q460.28F 01 13.3 11/04/97 100.32F-33F O2 13.6 12/15/97 0920.6F-27F O22 14.1 issues sent 06/25/97; Update to be issued shortly.

14.3 11/06/97 Q640.165 01 15.2 12/04/97 Q440.740F-745F 06 12/09/97 Q440.748F 01 15.3 11/06/97 Q470.42F-44F O2 15.3.7 10/27/97 Q410.320F 01 16.1 11/26/97 Q470.45F.

01 11/26/97 Q480.1088F-1103F 016 11/26/97 Q420.126F 01 12/16/97 Q440.776F-786F, 013 Q440.191F-192F 12/17/97 0480.1115F 01 12/17/97 Q410.414F 01 16.L7 10/17/97 Q630.15F L1 18.13 06/13/97

.cosition Ltr - Com-puterized Proc.

08/28/97 Telecon summaries 09/16/97 Computerized Proc.

09/16/97 0 640.98-99 02 T O 1.3 11/07/97 0720.430F-434F 05 Except 9.1.3.2-9.1.3.4 11/19/97 Q720.435F-438F 04 19.1.7 10/22/97 0720.423F 01 19.1.8 11/19/97 Q720.439F-444F 06 19.2.3 09/11/97 Q720.414 417 04 10/22/97 Q720.418F-420F 03 12/08/97 Q720.454F-455F O2 11/04/97 Q720.424F-429F 05 12/08/97 Q720.456F-457F O2 19.2.5 10/22/97 Q720.421F-422F O2 3

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19.3 12/11/97 Q440.763F-775F --

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Shutdown risk 19.4 12/11/97 Q720.445F-453F 09 Seismic margina A-43 10/06/97 0650.10F 01 B-36 12/12/97 Q650.15F 01 846 12/12/97 Q650.16F 01 --

C-10 10/06/97 Q650.11F 01 43 12/12/97 Q650.17F 01 82 12/12/97 Q650.18F 01 83 12/12/97 Q650.19F 01 124 12/12/97 Q650.20F 01 II.B.8 10/06/97 Q650.12F 01 II.D.1 06/11/97 Q650.1 01

.y II.E.1.3 12!'2/97 Q650.21F 01 Ill.D.3.3 10/07/97 Q650.9F 01 Ill.D.3.4 12/12/97 Q650.22F 01 20.7 11/07/97 Q650.13F-14F O2 BlAO-10 12/12/97 Q650.30F 01 BL-80-24 12/12/97 0650.23F 01 BL-61-02 06/11/97 Q650.5 01 BL-84-03 12/12/97 Q650.24F 01 BL-96-02 12/12/97 Q650.31F-01 GL80-009 12/12/97-Q650.25F 01 GL80-077 12/12/97:

Q650.32F 01 GL80-088 06/11/97 Q650.6 01 GL81-038 12/12/97 Qt$50.33F 01 GL81-039 12/12/97 Q650.26F 01 GL84-12 12/12/97 Q650.27F 01 d

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01 GL87-06 06/11/97 0650.2 01 GL88-14 12/12/97 Q650.28F -

01 GL89-04 06/11/97 Q650.7 01 GL89-10 06/11/97 Q650.8 01 GL89-13 12/12/97 Q650.29F 01 GL95-07 06/11/97 Q650.3 01 GL96-05 06/11/97 Q650.4 01 21.2 Q440.788F-790F 03 21.6.1 10/16/97 Q440.735F-737F 03 LOFTRAN.

21.6.2 08/13/97 Q440.721 01 NOTRUMP 21.6.3 0440.738F-739F O2 WCOBRATTRAC - LBLOCA 21.6.4 12/09/97 Q440.760F-761F O2 WCOBRA/ TRAC - LTC 12/10/97 0440.762F 01 21.6.5 11/18/97 Q480.1084F -

01 WGOTHIC RAIS Abbreviations:

0 - Open item C - Confirmatory item L - COL Action item 4

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FSER OPENITEM RESPONSE RECORD FOR 12/1787 I Tott.1 number of FSER Total number of FSER ltems Received Items with a Response Returned to NRC Count cs of 12/187 125 25 Count as of 12/15S7 244 135

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Count as of 12/1767 301 162 I

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10-Nov 17-Nov 24-Nov 1-Dec 8-Dec 15-Dec 22-C,)c 29-Dec 54an 124an 194an 26-Jan 2-Feb 9-Feb

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lasues that may resulm mananoment attention for resolution:

ASME Classification of the CVCS System Piping.

- The CVCS for the AP600 consists of reactor coolant pressure boundary piping that Westinghouse wants an exemption from classifying under ASME Section Ill. The staff is considering the Westinghouse proposal.

Treatment of Pressure Isolation Valves Tha staff believes that several system valves in reactor coolant piping penetrating the containment should be treated as PlVs even though the valves do not meet the conventional definitions of PlVs. - Westinghouse has not agreed to incorporate the valves requested by the staff. The staff is reconsidering its position Safety Classification of Containment Coatings in a November 21,1997, letter, Westinghouse stated that the coatings uted in the vicinity of the containment recirculation screens will be classified as safety related & all other coatings inside containment are classified as nonsafety-related.

Based on a preliminary review of Westinghouse's response, the division of engineering does not agree with Westinghouse and believes that all coatings inside containment need to be classified as safety related.

Concems about Westinghouse QA controls The staff and ACRS have found errors in documentation and submittals related to the AP600 project which reflects on the overall quality of the Westinghouse application. The staff has not yet d2cided what action is necessary in this regard.

ITAAC Westinghouse has not provided sufficient information for many ITAAC despite repeated requests by the staff.

The ITAAC cannot be completed until all of the open items that affect the design are resolved Source Term e

. Westinghouse has pcoposed an attemative to using NURr s values for EQ, shleiding, vital area Lccess, and equipment survivability, i,,e proposal is under staff consideration.

NOTRUMP

' The staff has only reviewed the AP600 verQn of the NOTRUMP code relative to changes from tne approved 1985 version of the pode. The ACRS has recently questioned whether this approach was 6dequate in consideration of changes made to the 1985 code numerics.

The staff is formulating its posit;on en this concem.

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2-WCCBRNTRAC

- The staff is concemed that it cannot approve the use of WCOBRA/ TRAC for AP600 when the docst>nentation of the code for operating plants has not yet been completed.

WGOTHIC The open issues identified to Westinghouse in late November 1997. The FSER input is due on December 31,1997.

Fire Protection

- The open issues were identified to Westinghouse on 11/26/97. The FSER input is due December 31,1997 i

4

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