ML20198A186

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Summary of 971117 Meeting W/Westinghouse in Rockville,Md Re Design Certification Schedule for AP600.List of Attendees & Handouts Provided During Meeting Encl
ML20198A186
Person / Time
Site: 05200003
Issue date: 12/18/1997
From: Joseph Sebrosky
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
NUDOCS 9801050305
Download: ML20198A186 (27)
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UNITED STATES ((i[M3 s* P; NUCLEAR REGULATORY COMMISSION WAsHlWGTON, D.C. 3000H001

\..,,,)* December 18, 1997 APPLICANT: Westinghouse Electric Corporation FACILITY: AP600

SUBJECT:

SUMMARY

OF NOVEMBER 17,1997, MANAGEMENT MEETING WITH WESTINGHOUSE TO D:3 CUSS DESIGN CERTIFICATION SCHEDULE FOR THE AP600 The subject meeting was held in the Rockville, Maryland, office of the Nuclear Regulatory Comrnission (NRC) between representatives of Westinghorsa and the NRC 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 purpose 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 recent reorganization announced by Westinghouse and the affect it would have on the AP600 project. In a November 14,1997, letter, Westinghouso informed the staff that it would sellits Power Generation business to Sismens and that it would divest itself of the remaining industrial businesses. Westinghouse maintained that it was fully committed to the AP60t1 and that h continued to remain a high priority for the Company.

The status of Westinghouse commitmerits were then discussed. Westinghouse provided a l status of the items which were listed in a letter of October 23,1997. The letter provided a response to the staff's request for scheduler information, in general Westinghouse believed that they were meeting the commitments that were made in .,a October 23,1997 letter. Several of the items that were identified in this letter were discussed. Highlights of the discussion are as f.'llows:

Westinghouse stated that they would like to have a meeting on the anticipated translent without bN scram (ATWS) requests for additional information (RAI) with the staff in the eariy December time 1 frame. The purpose of the meeting would be to reach agreement on the approach to developing l the responses to these questions. The staff and Westinghouse took an action to arrange the meeting, ,

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4 Deceuber 18, 1997 in a previous meeting, the staff had requested Westinghouse to determine if the regulatory treatt.1ent of notesafety systems (RTNSS) schedule could be improved. The staffs request was documented in a November 6,1997, meeting summary. Westinghouse stated that they would not be able to improve on the RTNSS schedule from the previously identified date of December 12,1997.

Westinghouse stated that they had responded to all, but approximately 30 RAls, excluding inspections, tests, analyses, and acceptance criteria open items, and final safety evaluation report open items. Westinghouse stated that with the exception of the ATWS RAls discussed above, the remaining RAI responses should be to the staff by the end of November.

Westinghouse also stated that they were %:ticularly concemed with the need to resolve two key technical issues: the basemat design, and tne design basis accident (DBA) radiological consequences. Westinghouse believed that they were on a path to resolution for other key technicalissues. (Attachment 3 provides the Westinghouse status for those items identified in December 1996 as key technicalissues). For the basemat design, the staff and Westinghouse sgreed that the high level discussions that were taking place to resolve the issue would continue.

Conceming the DBA for radiological consequences, the staff and Westinghouse agreed to arrange a meeting to discuss the problem.

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 Staridardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003 Attachments: As stated cc w/atts: See next page DISTRIBUTION wlatt:

Docket File PDST R/F TKenyon PUBLIC BHuffman JNWilson JSebrosky DScaletti DISTRIBUTION w/o att:

SCollins/FMiraglia,012 GiB BSheron,0-12 G18 RZimmerr, tan,0-12 G18 JRoe DMatthews TQuay WDean,0-5 E23 ACRS (11) JMoore,015 B18 NDudley, T-2 E26 DOCUMENT NAME: A:\11,.17_MM. SUM To receive s copy of this document, indicate in the box: "C" = Copy without attachmentienclosure "E" = Copy with attachment / enclosure "N" = No copy OFFICE PM:PDST:DRPM _

DPDST:DRPM l l NAME JSebrosky:sg 7N.4 TRQuay 94 DATE 12/ f f]97 // 12/h/97 v OFFICIAL RECORD COPY

n . . . .. .. .. . . - -

Westinghouse Electric Corporation Docket No. 52 003 cc: Mr. Nicholas J. Liparuto, 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 Projed Manager, Programs Advanced Plant Safety & Licensing Nuclear Energy institute Westinghouse Electric Corporation 1776 i Street, NW Energy Systems Business Unit Suite 300 Box 355 Washington, DC 20006 3706 Pittsburgh, PA 15230 Ms. Lynn Connor Ms. Cindy L. Haag Doc-Search Associates Advanced Piant 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 Pike 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 Seamans Cherin & Mellott NE 50 600 Grant Street 42nd Floor 19901 Germantown Road Pittsburgh, PA 15219 Germantown, MD 20874 Mr. Ed Rodwell, Manager Mr. Char'es 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 Malers, P.E.

Pennsylvania Department of Environmental Protection Bureau of Radiation Protection Rachel Carson State Office Building P.O. Box B469 Harrisburg, PA 17105-8469

WESTINGHOUSE AP600 MANAGEMENT MEETING ATTENDEES NOVEMBER 17,1997

((AMg ORGANIZATION BOB VlJUK WESTINGHOUSE BRIAN MCINTYRE WESTINGHOUSE JACK ROE (PART TIME) NRR/DRPM TED QUAY NRR/DRPWPDST DINO SCALETTI NRR/DRPWPDST THOMAS KENYON NRR/DRPWPDST JERRY WILSON NRR/DRPWPDST JOE SEBROSKY NRR/DRPWPDST 4

Attachment 1

. .. .= - _ - _ _ - - . ~ . . _. -_ _ - - - - - -

1 i

l AGENDA FOR NOVEMBER 17,1SN SMM l

1. Status on list of Westinghouse commitments W  !
11. SSAR update process W lil, Status of Schedule Commission paper / discussion of

- Ol resolution process in December / January. NRC i

IV. Discussion of OITS W V. Status of major issue resolution (ATWS, seismic margins, l basemat, PlVs, containment coatings, QA controls, source 1 term, WGOTHIC, fire protection) W/NRC VI. Status of FSER inputs NRC Vll. Date of next meeting (currently scheduled for December 18,1997) All 4

i Attachment 2 .i

-._--_..l.._-,.2._ . . , _ . , . - ._.._-. _

l STATUS OF AP600 REVIEW NOVEMBER 17,1997 ,

% comnieta Chapter With Open items W/O Open items Open items Confirmatory items 1 0 0 -

2 100 95 2 3 S4 64 83 20 4 100 100 0 5 52 45 6 8 80 38 4 7 100 83 9 8 100 update exp. 0 wino issues 9 87 44 51 10 100 85 4 11 100 93 1 2 12 100 100 0 13 17 11 2 14 19 13 1 16 12 64 4 16 50 60 1 17 0 0 -

18 100 91 2 il 76 47 17

  • 20 46 39 17 21 2 0 4 Overall 65 51 207 22 Abbreviations:

0 - Open item C - Confirmatory item

1. - COL Action item NC - No Change nceded to SER (May be no input, brief introduction, or written by PDST)

_. - _ .. . ._ _ . . , _ . _ . - . _ ~ . _ . _ . _ _ , -. . .

Date of W Section(s) RAls RAI# Response Comments l 2.3 10/17/97 Q470.41F  !

2.3.6 07/23/97 Position letter on '

atm. dispersion re:

MCR habitability l 3.2.1 Q260.83, 87, 88, & No open issues sent to W 89 still under review 3.6.3 04/11/96 Status Letter Update resolved open issues 3.7 04/05/96 Status Letter 3.7.1 04/05/96 Status Letter 3.7.2 04/05/96 Status Letter, Q230.96 09/25/96 3.7.3 04/05/96 Status Letter 3.8.2 04/05/96 Status Letter, Q230.97 addressed during Q230.97 December 9-13,1996 mig (see summary dated March 4, 1997. No formal submittel made by W 58.3 04/05/96 Status Letter, Q230.98 addressed during Q230.98 January 14-16,1997 mtg (see summary dated March 18, 1997. No formal submittal made by W 3.8.4 04/05/96 Status Letter; Q230.99100 addressed Q230.99-100 during December 9-13,1996 mig (see summary dated March 4,1997. No formal submittal made by W 3.8.5 04/05/96 Status Letter; Q230.101 105 addressed Q230.101 105 during December 913,1996 mig (see sun. mary dated March 4,1997. No formal submittal made by W 3.9.6 05/29/97 Position Ltr on ADS See Section 5.2.5 for RAls on 07/29/97 Position Ltr on ADS PlV concems 3.11.3 10/09/97 Q270.15F -

Q270.16-270.18F 10/14/97 3.12.3 04/11/96 Status Letter

. . ~ _ _ ._ _ . _ _ . .

3.12.4 04/11/96 Status Letter l

3.12.5 04/11/06 Status Letter 3.12.6 04/11/96 Status Letter l

5.2.1 10/16/97 Q230.140F 1 5.2.5 10/16/97 Q250.30F 33F i

6.1.2 07/30/97 Position Letter on contnmnt coatings -I 6.2.1 10/16/97 Q480.1081F 6.2.5 10/22/97 Q480.1082F-1083F 7.0 03/04/97 064C.37-640.45 06/16/97 9.3.1 10/20/97 Q410.308F-309F 9.3.2 10/20/97 Q410.310F 9.3.5 10/20/97 Q410.311F-312F 9.5.4 10/30/97 Q410.321F 324F 9.5.5 10/30/97 Q410.325F-328F 9.5.6 10/30/97 Q410.329F-331F 9.5.7 10/30/97 Q410.332F-334F 9.5.8 10/30/97 Q410.335F-338F 10.4.1 10/10/97 Q410.404F 10.4.3 10/10/97 Q410.305F 10.4.5 10/10/97 Q410.306F 10.4.7 10/10/97 Q410.307F i

11.4.1 10/20/97 Q460.28F -

l 13.3 11/04/97 100.32F-33F

! 14.3 11/06/97 0640.165 15.3 11/06/97 Q470.42F-44F 15.3.7 10/27/97 Q410.320F 16.2.7 10/17/97 0630.15F r

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18.13 06/13/97 Position Ltr - Com. 06/24/97 puterized Proc.

08/28/97 Telecon summaries 09/16/97 Computerized Proc. 10/27/97 09/16/97 0640.08-99 19.1.3 11/07/97 Q720.430F-434F 19.1.7 10/22/97 Q720.423F 19.2 11/04/97 Q720.424F 426F IVSE questions based on draft SER (per W request for early identification of issues) 19.2.3 09/11/97 Q720.414 417 10/22/97 Q720.418F-420F 19.2.6 10/22/97 Q720.421F 422F 19.2.6 09/18/97 Position Letter A-43 10/06/97 0650.10F C-10 10/06/97 Q650.11F I!.B.8 10/06/97 0650.12F ll.D.1 06/11/97 b650.1 10/02/97 Ill.D.3.3 10/07/97 0650.9 10/29/97 20.7 11/07/97 Q650.13F-14F BL-81-02 06/11/97 0650.5 10/02/91 GL80-088 06/11/97 0650.6 10/02/97 GL87-06 06/11/97 0650.2 10/02/97 GL89-04 06/11/97 Q650.7 10/02/97 GL8910 06/11/97 Q650.8 10/02/97 GL95-07 06/11/97 0850.3 10/02/97 GL96-05 06/11/97 0650.4 10/02/97 21.6.1 10/16/97 Q440.735F-737F l

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21.6.2 08/13/97 Q440.721 09/12/97 09/17/97

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09/22/97 i

10/01/97  !

10/13/97 10/17/97  !

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f 11/17/97 CHAPTER 2

. 2.1 Closed when commitments made in 8/4-7 meeting confirmed (Rev.17) 2.2 2.3 01 10/7/97 PGEB (470.41F) 2.3.2.1  ;

2.4 Closed when commitments made in 8/4-7 meeting confirmed (Rev.17) 2.5-2.6 CHAPTER 3 3.1 3.2.1 01' 3.2.2 3.3.1 3.3.2 3.4.2 i 3.5.1.3 3.5.1.5 .

3.5.1.6 3.5.3 3.6.2 DSER 013.6.2.3-5 confirmatory pending acceptable rev. of WCAP-13054 3.6.3 3.7.4 Closed when commitments made in 8/4-7 meeting confirmed (Rev.17) 3.8.1 NOT APPLICABLE TO THE AP600 3.9.1 ECGB 11/10/97 3.9.2.1 ECGB 11/10/97 3.9.2.2 ECGB 11/10/97 i

3.9.2.3 .

3.9.2.4 .

3.9.3 01 ECGB 11/10/97 (confirmatory pending revision to WCAP-13054) 3.9.4 3.9.5 3.9.6 01 3.9.7 3.10 3.11- 01 SPSB 10/9/97 (270.15F,270.16F,270.17F and 270.18F) 3.12 ECGB 11/10/97 CHAPTER 4 4.1

'4.2 ,

4.3 4.4 4.5.1 4.5.2 4.6

. CHAPTER 5 e-+ se r--+w.,-- . , -s w v yu os y e ir*-g-e-e v,9 * - - - , - - - t.,: y q -e + e y- e + *. v +

5.2.1 01 ECGB 10/16/97 (230.140F) 5.2.3 5.2.4 5.2.5 01 SPLB 10/16/97 (250.30F,250.31F,250.32F,250.23F) 5.3.1 5.3.2 5.3.3 5.3.4 5.3.5 5.4.1.1 5.4.1.4 5.4.2.1 5.4.8 5.4.10 5.4.11 01 SPLB 9/26/97 CHAPTER 6 6.1 01 6.1.2 6.2.1.1.4 01 SCSB 10/16/97 (480.1081F) 6.2.1.2 6.2.1.5 6.2.1.7 6.2.3 6.2.4 6.2.5 01 SCSB 10/22/97 (480.1082F,480.1083F) 6.2.6 SCSB 11/7/97 6.2.7 6.2.8 01 SCSB 6.5.1 (NOT APPLICABLE TO THE AP600) ,

6.5.3 (BUT SPRAY MAY IMPACT) 6.6 CHAPTER 7 All CHAPTER 8

' All CHAPTER 9 9.1.1 9.1.2 Ol 9.1.4 Gi 9.i.5 9.2.1 (Possible 01) 9.2.2 ( " ")

9.2.3 9.2.4 9.2.5

_.__.__m._m_...m_.____.m.____.._.__.___mm____m_.i_.-_._______._________.______-_.m_______.___.___m_ .._ e

9.2.6 9.2.7 9.2.8 .

9.2.9 9.2.10 9.3.1 01 SPLB 10/20/97 (410.308F,410.309F) 9.3.2 01 SPLB 10/20/97 (410.310F) 9.3.3 9.3.4 9.3.5 01 SPLB 10/20/97 (410.311F,410.312F) 9.3.6 9.4.2 01 SPLB 11/6/97 9.4.3 01 SPLB 11/0/97 9.4.6 01 SPLB 11/6/97 9.4.7 01 SPLB 11/6/97 9.4.8 01 BPLB 11/6/97 9.4.9 01 SPLB 11/6/97 9.4.10 01 SPLB 11/6/97 9.4.1101 SPLB 11/6/97 9.5.2 9.5.3 9.5.4 01 SPLB 10/30/97 (410.321F-410.338F) 9.5.5 SPLB 9.5.6 SPLB 9.5.7 SPLB 9.5.8 SPLB CHAPTER 10 10.1 SPLB 9/19/97 10.2 SPLB 9/19/97 10.2.9 10.3.1 10.3 SPLB 9/19/97 10.4.1 Ol SPSB 10/10/97 (410.304F) 10.4.2 SPLB 9/19/97 10.4.3 01 SPSB 10/10/97 (410.305F) 10.4.4 SPLB 9/19/97 10.4.5 01 SPSB 10/10/97 (410.306F) 10.4.6 ECGB 10.4.7 01 SPSB 10/10/97 (410.307F) 10.4.8 ECGB 10.4.9 SPLB 9/18/97 10.4.10 SPLB 9/19/97 CHAPTER 11 1101 SPLB 10/20/97 (460.28F)

CHAPTER 12 All 1

i CHAPTER 13 13.1 HHFB 13.1.1 HHFB 13.1.2 HHFB j 13.2 HHFB 13.3 01 PGEB 11/4/97 (100.32F,100.33F) 13.4 HHFB 9/16/97 13.5 HHFB CHAPTER 14 14.1 HQMB  :

14.2 HQMB '

3.4 01 HQMB 10/6/97 CHAPTER 15 15.3 01 PERB 10/22/97 (470.42F,470.43F,470.44F) 15.3.7 Ol SPLB 10/27/97 (410.320F)

CHAPTER 16 16.1, Section 5.0 Parts 5.15.4 HHFB 10'28/97 '

16.2 SER COL ACTION ITEM HQMB 10.17/97 (630.15F)

CHAPTER 17 17.3 (RAP) COL ACTION ITEM HQMB t

Chapter 18 All Chapter 19 .

19.1 (Level 1 PRA) 01 SPSB 11/7/97 (720.430434F) 19.1.2.2 (Special Design Features for Core Dam. Conseq. Mit.) SCSB 11/7/97 19.1.3.1.4 (Insights from the Risk Importance Studies) SCSB 11/7/97 19.1.3.2 (Results and insights from Level 2 PRA-Cont. Anal.) 01 SCSB 11/7/fr/

19.1.3.3 (Results and !nsights from the Level 3 PRA Offsite conse.) SCSB 11//7/97 19.1.6 (Use of PRAin the Design Process) SCSB 11/7/97 19.1.7 '(RTNSS Input) 01 SCSB 10/23/97 (720.423F) 19.1.8 (PRA input to the Design Certification Process) 01 SCSB 111/7/97 19.2.2.1 (Severe Accident Preventive Features) SCSB 10/22/97 19.2.3.3.2 (Hydrogen Generation and Control) SCSB 11/7/97 19.2.3.3.3 (Core Debris Coolability) 01 SCSB 10/23/W7 (720.418F,720.419F) 19.2.3.3.4 (High-Pressure Core Melt Ejection) 01 SCSB 10/23/97 (720.420F) 19.2.3.3.6 (Containment Bypasa) SCSB 10/20/97 -

19.2.3.3.7 (Equipment Survivability) 01 19.2.3.3.8 (Containment Vent Penetration) SCSB 10/20/97 19.2.3.3.9 (Nonsafety-Related Containment Spray) 01 SCSB 11/7/97 -

19.2.4 (Containment Performance Goal). Confirmatory issues SCSB 10/20/97 19.2.5. -(Accident Management) 01 SCSB 10/23/97 (720.421F,720,422F) .

19.A.1 ~ (Resolution of DSER Open items) 01 SCSB 11/7/97

20 GENERIC ISSUES HQMB 01 11/7/97 (650.13F,650.14F) 20.2 Task Action Plan items A1 A2 A-3  ;

A 11 A 12 A 13 A 25 9/25/97  ;

A 35 9/25/97 .  !

A 40 9/29/97 ECGB A-43 01 10/6/97 SCSB (650.10F)

  • i A 44 9/25/97  ;

A 46 A 47 A-48 SCSB (/29/97 A 49 B-5 B 17 9/18/97 B 53 9/25/97 ,

B 56 9/25/97 i

843 (subsumed by GSI 105) ,

C 10 01 10/7/97 SCSB (650.11F) .

20.3 New Generic lasues '

issue 14 -

lasue 15 ,

Issue 24 SCSB 9/29/97 Issue 29 lasue 45 issue 67.3.3 lesue 70 issue 73 Issue 75 9/25/37 lasue 79

' Issue 87 9/29/97 ECOB losue 94-Issue 103 issue 113.

Issue 120 lasue 121 SCSB 9/29/97 lasue 128 i lasue 135 issue 142 9- -+-M-w -*/*w _ - sq vs e -re _ -','_,7 '

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i 20.4 TMl Action Plan items 1.A.1.4 9/18 1.A.2.6(1) 9/18 1.A.4.1(2) 9/18 II.B.2 ,

ll.B.8 01 10/7/97 SCSB (650.12F) 1.C.1 9/18

1.C.5 9/18 1.C.9 9/18 1.D.1 9/18 1.D.2 9/18 1.D.3 1.D.5(2) 1.F.1 9/24 1.F.2 9/24 1.G.2 9/24 ll.D.1 01 11.D.3 fl.E.1.2 ,

ll.E.3.1 9/25 ll.E.4.1 SCSB 9/29/97 II.E.4.2 SCSB 9/29/97 ll.E.4.4 SCSB 9/29/97 II.E.6.1 '

II.F.1 il.F.3 II.G.1 9/25 ll.J.4.1 9/18 II.K.1(5) 9/18 .

II.K.1(10) 9/18 '

II.K.1(26) 9/18 ll K 2(10)

II.K.3(9) ll.K.3(18) lil.A.1.2 lil.A.3.3 .

Ill D.3.3 Ol PGEB 10/7/97 (650.9F) 20.5 Shift Staffing -

HF1.1 - 9/18 HF4.1 9/18 l HF4.4 9/18 i

HF5.1 9/18 HF5.2 9/18 20.7 incorporation of Operating Experience BL 80-04 - SCSB 9/29/97 l

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80 06  ;

8048 -

80-11 80-20 ,

81-01 8102 Closed if WCAP 13559 revised 82-02 82 04 (By COL applicent) 9/25/97 83-03 85-02 87-01 87-02 9/24/97 01 (Action item for COL) 88-01 (By COL applicant) 9/25/97 ,

88-02 88-08 88-09 -

88-11 88-35 89-01 90-01 GL 80-14 80-35 9/25/97 80-88 Closed if WCAP-13559 revised 80-99 80-109 81-14 81-19 81-28 83-13 9/18/97 ,

83-15 83-41 9/25/97 ,

84-04 84-13 84 15 9/25/97 85-02 85-06 9/24/97 (Action item COL) 86-04 86-07 01 (Tied to A-1) 87-03 87-06 (under ISLOCA (issue 105))

87-11 ,

88-05 88-11 i 88 15 9/25/97 l' 89-02 9/24/97 (Action item COL) l 89-04 Closed if WCAP-13559 revised '

L 89-08 .

!- 89-10 90 . ._, . . . _ _ , . . . _. __ .__ . . _ - _ _ - , .- ._.

. ._. . . _ . . .. - .--...- --. _ . . . . .. - .- _ ~ - --

91-05 9/24/97 (Action item COL) 91 17 92 01 92-02 95-03 95-07 C6 sed if discussion added to SSAR 96-01 l 96-05 Open-still under staff review J Chapter 21 LOFTRAN 01 SRXS 10/16/97 (440.735F,440.736F,440,737F) 4

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..1 KEY ISSUE STATUS N

  • Complete 3
  • OK 9
  • Problem -

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8 r0 toa 13 06538AM.WPFMovember 16,1997

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L KEY ISSUE STATUS 1

COMPLETE _.-

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! 1. Content of SSAR i

  • Material added to SSAR on a selected basis l

I 4. LBB for feedwater piping system  !

  • Not included in design certification
27. Quality classification of systems 1

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  • Additional systems made safety class D l t  !

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i f 06538AM.WPF/ November 16, 4997 4 f

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KEY ISSUE STATUS COMPLETE PENDING NRC REVIEW - .

N 2e,19 Safe shutdown endstate

  • Mode 5 -

2d,9. Post-72 hour support actions l

  • NRC position letter - July 7 SSAR markup submitted to NRC - October 10

'

  • Included in Revision 17 .

2c,25 Adverse systems interactions

  • Report submitted to NRC - May 9
  • Revised report submitted - November 7
5. Soil / structure / seismic interactions
  • Agreement reached on atceptable soil variability and site parameters
  • Included in Revision 17 ossasAw.wrvmovember 16,1997 5 I

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KEY ISSUE STATUS COMPLETE PENDING NRC REVIEW N

8. Prevention and mitigation of severe accidents ,

Noncafety related containment spray included in design

10. Containment isolation ,
  • Diverse isolation signal included in RNS design .
11. Hydrogen control

- Igniters ]

- Passive autocatalytic recombiners (PAR) l

  • Four more igniters included in design (64 total)
  • Additional information provided concerning locations
4 l 13. Spent fuel pool cooling system
  • Additional safety-related makeup provided
14. Overspeed protection

6 0653BAM.WPF/ November 16,1997

f KEY ISSUE STATUS j COMPLETE PENDING NRC REVIEW l

16. Initial test program
  • Responses provided to all NRC RAls
19. Proposed LCO 3.0.3
  • Mode 5 is endstate
  • Standard completion times
20. Integrated use of PRA insights
  • Additional insights. identified by NRC will be included if technically correct .

2a,21. Passive system T&H performance reliability

. Report submitted - June 20

  • Resolution assisted by addition on short term availability controls
23. External cooling of reactor vessel / severe accidents
  • Limited deterministic analyses of ex-vessel phenomena provided
  • Suppoded by DOE ARSAP repons
24. Containment bypass / SGTR
  • Revised report submitted - November 11 06538AM.WPF/ November 16,1997 7

i-A' .

g

KEY ISSUE STATUS OK l- 2b. Acceptability of baseline and focused PRA
  • NRC reviewing revision 10.of PRA report
  • 4 ATWS RAls outstanding

- Protection of RTNSS and DID systems f_s. missiles, flood j 2f.

j - Regulatory oversight determination

  • Proposed systems and oversight submitted to NRC - July 15
  • NRC feedback letter - October 2
  • Clarification phonecall- Novem' "4
  • Response will be provided by L =m .er 12 ,

l-l

3. ITAAC
  • Revision 3 submitted to NRC - Ma, *'
  • NRC branch task team review in progress
  • Review slightly behind schedule E

06538AM.WPF/ November 16, ifr97 I

l KEY ISSUE STATUS OK l 12. Fire protection

  • NRC has accepted safe shutdown as endstate based on capabilities of l

design

  • Most information included in revision 15 l
  • Appendix 9A in revision 17
15. Security pian j

3

  • Revision 4 to security report submitted - September 12

- Review comments have been discussed informally 1

17. Computer code documentation and V&'

-ECCS

- Containment

  • All documentation provided to NRC

= NRC RAls being resolved .

  • ACRS review in progress 9

0653BAid.WPF/Novemtier 16,1997

\ _

~

.j .

l KEY ISSUE STATUS l

[ O K-

~

E

18. Safety analysis

- Chapter 6

- Chapter 15 -

l 1

  • Requiree resolution of Israa 17
  • RAls being resolved

?

22. Shutdown and low powet operations
  • Report submitted to NRC - June 9 RAI responses provided
  • Report revision - November 21
26. Technical specification review

' a NRC RAls being resolved a

10 0653BAM.WPF/ November 16.1997 l

1 e

t KEY ISSUE STATUS PROBLEM

6. Cite-soit variability (Basemat) )
  • Responses provided to latest NRC technical concerns - October 17
  • Resolution path may be identified 1
7. DBA radiological consequences
  • NRC has changed approach
  • input from Sandia national laboratory required f
  • Specifics are open items in FSER (November 6 letter)

{

i i

1 i

j 11 06538AM.WPF/ November 16.1997

_ _ _ _ __

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