ML20198R926

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Summary of 971009 Meeting W/Westinghouse in Rockville,Md Re Design Certification Schedule for AP600.List of Attendees & Handouts Encl
ML20198R926
Person / Time
Site: 05200003
Issue date: 10/30/1997
From: Joseph Sebrosky
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
NUDOCS 9711130399
Download: ML20198R926 (17)


Text

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  • E " NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30M64001 k..i>p...

October 30, 1997 APPLICANT: Westinghouse Electric Corporation FACILITY: AP600

SUBJECT:

SUMMARY

OF OCTOBER 5, 1997, MANAGEMENT MEETING WITH WESTINGHOUSE TO DISCUSS DESIGN CERTIFICATION SCHEDULE FOR THE AP600 The subject meeting was held on October 9,1997, in the Rockville, Maryland, office of the Nuclear Regulatory Commission (NRC) between representatives of Westinghouse 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 Decemt,er time frame to discuss the progress of the review, and to elevate schedule impact issues to management's attention as soon as possible.

During the meeting, the staff stated that the new schedule for the AP600 review would be forwarded to the Commission. In a September 10, 1997, meeting, Westinghouse was provided a draft copy of the schedule and had provided comments to the staff in a September 26, 1997, letter NRC-97-5349) on where they believed the sch6dule could be furthe(NSD- r improved.

The staff discussed these ccaments with Westinghouse and indicated that further improvem nt on the schedule would be difficult. However, the staff agreed to look fca potential methods to improve the schedule such as perform-ing activities in parallel in some areas, identifying issues as rapidly as possible, and examining potential ways to improve the schedule for the Advisory Committee on Reactor Safeguards (ACRS) review.

During the meeting, a scheduling problem was identified. While estimating the review schedule, the staff assumed that the ACRS could meet in the August 1998 time frame to discuss the final safety evaluation report. However, the ACRS does not have a full committee meeting scheduled for the month of August. The )/

staff of the office of Nuclear Reactor Regulation and Westinghouse agreed to discuss schedule alternatives with the ACRS to address this problem and to potentially improve the schedule as noted above.

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in addition, house agreed th:.tthere theywere wouldseveral forward acommitments madesafety revision to the standard during the meeting. 3 Westin analysis report (SSAR) as soon as possible instead of waiting to try to combine most changes to the SSAR in one revision. Westinghouse aad the staff agreed to schedule a meeting in the near Teture to discuss the SSAR Chapter 15 analysis of anticipated transients without scram. The staff also agreed to evaluate if it was feasible to forward a sensitivity anhiysis that the staff performed systems.

as part of its review on the regulatory treatment of non-safety A

9711130399 971030 PDR ADOCK 05200003 A PDR I

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October 30, 1997 t 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 Attachments: As stated cc w/atts: Set next page DISTRIBUTION w/atts:

. Docket File PDST R/F TKenyon PUBLIC BHuffman JNWilson JSebrosky DScaletti D1SIRIBEUDN w/o atts:

Scollins/FMiraglia, 0-12 G18 BSheron, 0-7 D25 RZimmerman, 0-12 G18 JRoe DM4tthews TQuay WDean, 0-5 E23 ACRS (11) JMoore. 0-15 818 NDudley, T-2 E26 DOCUMENI NAME: A:\l0 9 MM. SUM Ts ecsive a copy of this document,In3ceTo in the ben: 'C' s Copy without ettechment/encloswo *E' s Copy with attechmentlenclosure *N* = No copy 0FFICE PM:PDST:DRPM D:PDST:DRPM , 1 NAME JSebrosky d4AT TRQuay M ,.

DATE 10/1//97 V 10#/9F/ /F OFFICIAL RECORD COPY

Westinghouse Electric Corporation Docket No.52-003 cc. Mr. Nicholas J. Liparulo, Mancger 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 Manager, Programs Advanced Plant Safety & Licensing Nuclear Enorgy 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 Conner 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 Divisien 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. 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

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WEST 'nGHOUSE AP600 NANAGEMENT MEETING ATTENDEES DCTOBER 9, 1997 l

Hag [ ORGANIZATION BOB V!JUK WESTINGHOUSE BRIAN MCINTYRE WESTINGHOUSE CHARLES THOMPSON DOE NOEL DVDLEY ACRS JACK ROE (PART TIME) NRR/DRPM TED QUAY NRR/DRPM/PDST DINO SCALETTI NRR/DRPM/PDST BILL HUFFMAN NRR/DRPM/PDST JOE SEBROSKY NRR/DRPM/PDST f

Attachment 1

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10/9/97 2.1 Closed when commitments made in 8/4 7 meeting confirmed (Rev.17) 2.2 " "

2.3 Ol 10/7/97 PGEB (470.41F) 2.4 Closed when commitments made in 8/4 7 meeting confirmed (Rev.17) 2.5 " " " " "

2.6 3.1 3.2.1 01 3.2.2 3.3.1 3.3.2 3.4.2 3.5.1.3 3.5.3 ???

3.6.2 DSER 013.6.2.3 5 confirmatory pending acceptable rev of WCAP 13354 3.6.3 3.7.4 Closed when commitments made in 8/4 7 meeting confirmed (Rev.17) 3.9.1 3.9.2 3.9.3 01 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 01 4 COMPLETE 4.2 4.3 4.4 4.5.1 4.5.2 5.2.1 Ol ECGB 10/6/97 5.2.3 5.2.4 5.2.5 Ol 9/19/97 5.3.1 5.3.2 5.3.3 5.4.1.1 5,4.2.1 .

5.4.11 9/26/" -

-6.1 01 Attachment 2

6.1.2 6.2.1.1.4 01 6.2.1.2 6.2.1.5 6.2.3 6.2.4 6.2.6 6.2.7 6.5.3 (BUT SPRAY MAY IMPACT) 6.6 CHAPTER 7 All CHAPTER 8 All 9.1.1 9.1.2 Ol 9.1.4 01 9.1.5 9.2.1 (Possible 01) 9.2.2 ( " ")

9.2.3 9.2.4 9.2.5 9.2.6 9.2.7 9.2.8 9.2.9 9.2.10 9.3.3 9.3,4 9.3.6 9.5.2 9.5,3 10.1 9/19/97 10.2 9/19/97 10.3 9/19/97 10.4.1 Ol 9/19/97 10.4.2 9/19/97 10.4.3 01 9/19/97 10.4.4 9/19/97 10.4.5 01 9/18/97 10.4.6 10.4.7 OI 9/18/97

~t0.4.8 .

10.4.9 9/18/97

l l 10.4.10 9/19/97 Chapter 11 -

11.5 (partiti)

Chapter 12 All Chapter 13 13.1 -

13.1.1 13.1.2 13.2 13.4 (9/16/97) 13.5 Chapter 14 3.4 01 HQMB 10/6/97 >

Chapter 16 16.2 Chapter 18 All Chapter 19 19.2.3.3.7 (Equipment Survivability) 01 20 GENERIC ISSUES 20.2 Task Actior, Plan items A1 A2 A3 A 11 A 12 A-13 A-25 9/25/97 A 35 9/25/97 A40 9/29/97 ECGB A 43 01 10/6/97 SCSB (650.10F)

- A-44 9/25/97 A-46 A 47 A-48 SCSB (/29/97 A-49

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B5 B 17 9/18/97

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B 53 9/25/97 B 56 9/25/97 B 63 (subsumed by GSl+105)

C-10 Ol 10/7/97 SCSB (650.11F) 20.3 New Generic istues issue 14 lasue 15 issue 24 SCSB 9/29/97 -

lasue 29 -

Issue 45 lasue 67.3.3 lasue 70 lasue 73 lasue 75 0'25/97 lasue 79 issue 87 9/29/97 ECGB lasue 94 lspue 103 issue 113 issue 120 lasue 121 SCSB 9/29/97 lesue 12C lasue 135 lasue 142 20.4 TMI 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

'l.C.5 9/18 l.C.9 9/18 l.D.1 9/18 L l.D.2 9/18 l -1.D.3 l

1.D.5(2) 1.F.1 9/24 1.F.2 9/24 l 1.G.2 9/24 ll.D.1 Ol

ll.D.3 II.E.1.2 II.E.3.1 9/25 .

II.E.4.1 SCSB 9/29/97 11.E,4.2 SCSB 9/29/97

il.E.4.4 SCSB 9/29/97 ll.E.6.1 II.F.1 -

ll.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 II.K.2(10) ll.K.3(9)

II.K 3(18) lll.A.1.2 Ill.A.3.3 -

lll.D.3.3 01 PGEB 10/7/97 @50.9F) 20.5 Shift Staffing HF1.1 9/18 HF4.1 9/18 HF4.4 9/18 HF5.1 9/18 HFS.2 9/18 20.7 incorporation of Operating Experience BL 80 04 SCSB 9/29/97 80-06 80-08 80-11 80-20 81-01 81-02 Closed if WCAP 13559 revised 82-02 82-04 (By COL applicant) 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 8014 80-35 9/25/97

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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 88 15 9/25/97 89-02 9/24/97 (Action item COL) 89 04 Closed if WCAP 13559 revised 89-08 89-10 90-09 91-05 9/24/97 (Action item COL)

> 91 17 92-01 92-02 95-03 95-07 Closed if discussion added to SSAR 96-01 96-05 Open-still under staff review

AP600 KEY ISSUE STATUS k.

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SUMMARY

  • OK 19
  • Complete 3 -
  • Potential problem 0
  • Problem 2 N

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a 06318AMWPF/ October 8,1997 16 g

- o KEY ISSUE STATUS COMPLETE ~h.=e

1. Content of SSAR
4. LBE for feedwater piping system
27. Quality classification of systems osaisAu.wpr/ October s.1997 6

i 2 KEY ISSUE STATUS =

COMPLETE PENDING NRC REVIEW 8=.  !

2e,19 Safe shutdown endstate i i

10. Containment isolation
11. Hydrogen control  !

- Igniters  ;

- Passive autocatalytic recombmers
13. Spent fuel pool cooling system i
14. Overspeed protection '

j 19. Proposed LCO 3.0.3

! 20. Integrated use of PRA insights 3

21. Passive system T&H performance reliability  !

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23. Externe.1 cooling c1 reactor vessel / severe accidents 0631BAM.WPF/Ockber 8.1997 7 l l

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KEY ISSUE STATUS -

OK b-i l 2a. Passive system T&H performance reliability  !

2b. Acceptability of baseline and focused PRA

2d. Post-72 hour support actions l 2c,25 Adverse systems interactions l f

1 2f. - Protection of RTNSS and DID systems from missiles, ficod

- Regulatory oversight determination ,

3. ITAAC ,

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5. Soil / structure / seismic intoractions i  ;

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8. Prevention and mitigation of severe accidents l

0631BAM.WPF/ October 8.1997 8 i

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KEY ISSUE STATUS ..

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i i OK . ....

9. Post-72 hocr support actions
12. Fire protection  ;
15. Security plan i
16. Initial test program 4
17. Computer code documentation and V&V l

- ECCS  !

- Containment j i

18. Safety analysis

- Chapter 6

- Chapter 15 l r

22. Shutdown and low power operations  !

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0631BAM.WPF/ October 8.1997 9

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KEY ISSUE STATUS ,

OK he

24. Containment bypass / SGTR
25. Adverse systems interactions 23 Technical specification review 9

0631BAM.WPF/ October 8.1997 10

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KEY ISSUE STATUS =ge PROBLEM E!Di t I

f j 6. Site-soil variability l ll 7. DBA radiological consequences f

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osa:BAMWPF! October 8.1997 - 11 I

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