ML20236Y118

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Summary of 871112 Meeting W/Westinghouse Re Design Certification Program for RESAR SP/90 & AP-600.Related Info Encl
ML20236Y118
Person / Time
Site: 05000601
Issue date: 12/01/1987
From: Kenyon T
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8712110109
Download: ML20236Y118 (19)


Text

,

, December 1, 1987 Docket No. 50-60lz.

APPLICANT: Westinghouse Electric Corporation FACILITY: RESAR SP-90

SUBJECT:

SUMMARY

OF MEETING TO DISCUSS WESTINGHOUSE'S DESIGN CERTIFICATION PROGRAM On November 12, 1987, representatives of the NRC and Westinghouse Electric Corporation met to discuss the applicant's design certification program for the RESAR SP/90 design and the AP-600 design. Enclosure 1 is a list of attendees. Enclosure 2 is a copy of the slides used during the presentation.

Westinghouse began their presentation with a discussion of their overall licensing strategy for the RESAR SP/90 and AP-600. The applicant stated they expected completion of the PDA review for the RESAR SP/90 design in 1988, after which they planned to submit the FDA and design certification application. The applicant estimated completion of the design certification review by the end of 1992. The staff indicated that design certification could take longer than Westinghouse estimated if the project was highly contested.

Westinghouse then discussed the history of the review of RESAR SP/90, the scope of the design, and the unique safety features of the 31 ant. The meeting concluded with a discussion of the current review status, tie applicant's approach to completing the ACRS review, and the applicant's intent to develop a Licensing Review Basis document.

During the meeting, Westinghouse also indicated its intent to submit an FDA and design certification application for its AP-600 reactor design.

The applicant intends to submit preliminary conceptual design information in mid-1988, and the FDA and design certification application in early 1990. The staff acknowledged Westinghouse's intentions and indicated that there would be a need to allocate resources in its project resource schedules. Westinghouse l indicated it would present a briefing on the AP-600 at a later time. l l

original signed by l Thomas J. Kenyon, Project Manager '

Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects l

Enclosure:

DISTRIBUTION:

As stated Central File OGC-BETH Local PDR EJordan PDSNP Reading JPartlow LRubenstein NRC Participants TKenyon ACRS (10)

EHylton HBClayton, RI

( TKing P$N fP [p' n:pj UV n LRubenstein 8712110109 e71201 1 11N/87 14 / / /8 7 PDR ADOCK 0500 g0 A

December 1, 1987 b

Docket No. 50-601 APPLICANT: Westinghouse Electric Corporation ,

FACILITY: RESAR SP-90

SUBJECT:

SUMMARY

OF MEETING TO DISCUSS WESTINGHOUSE'S DESIGN CERTIFICATION PROGRAM On November 12, 1987, representatives of the NRC and Westinghouse Electric Corporation met to discuss the applicant's design certification program for the RESAR SP/90 design and the AP-600 design. Enclosure 1 is a list of attendees. Enclosure 2 is a copy of the slides used during the presentation.

Westinghouse began their presentation with a discussion of their overall licensing strategy for the RESAR SP/90 and AP-600. The applicant stated they expected completion of the PDA review for the RESAR SP/90 design in 1988, after which they planned to submit the FDA and design certification application. The applicant estimated completion of the design certification review by the end of 1992. The staff indicated that design certification could take longer than Westinghouse estimated if the project was highly contested.

. Westinghouse then discussed the history of the review of RESAR SP/90, the scope of the design, and the unique safety features of the slant. The meeting concluded with a discussion of the current review status, t1e applicant's approach to completing the ACRS review, and the applicant's intent to develop a Licensing Review Basis document.

During the meeting, Westinghouse also indicated its intent to submit an FDA and design certification application for its AP-600 reactor design.

The applicant intends to submit preliminary conceptual design information in mid-1988, and the FDA and design certification application in early 1990. The staff acknowledged Westinghouse's intentions and indicated that there would be a need to allocate resources in its project resource schedules. Westinghouse indicated it would present a briefing on the AP-600 at a later time.

original signed by Thomas J. Kenyon, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects

Enclosure:

DISTRIBUTION:

As stated Central File OGC-BETH Local PDR EJordan PDSNP Reading JPartlow LRubenstein NRC Participants TKenyon ACRS (10)

EHylton HBClayton, RI TKing P P n:pj LRubenstein 11 /87 14 / / /87

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p Cro

/ 'o g-UNITED STATES

!" n NUCLEAR REGULATORY COMMISSION h <

WASHINGTON, D. C. 20555 December 1, 1987 k *...+ / ,

L Docket No. 50-601 L

t l

APPLICANT: Westinghouse Electric Corporation FACILITY: RESAR SP-90

SUBJECT:

SUMARY OF MEETING TO DISCUSS WESTINGHOUSE'S DESIGN CERTIFICATION PROGRAM On November 12, 1987, representatives of the NRC and Westinghouse Electric Corporation met to discuss the applicant's design certification program for the RESAR SP/90 design and the AP-600 design. Enclosure 1 is a

-list.of attendees. Enclosure 2 is a copy of the slides used during the presentation.

Westinghouse began their presentation with a discussion of their overall licensing strategy for the RESAR SP/90 and AP-600. The spp11 cant stated they expected completion of the PDA review for the RESAR SP/90 design in 1988, after which they planned to' submit the FDA and design certification application. The applicant estimated completion of the design Certification review by the end of 1992. The staff indicated that design certification could take longer than Westinghouse estimated if the project was highly contested.

Westinghouse then discussed the history of the review of RESAR SP/90, the scope of the design, and the unique safety features of the plant. The meeting concluded with a discussion of the current review status, the applicant's approach to completing the ACRS review, and the applicant's intent to develop a Licensing Review Basis document.

During the meeting, Westinghouse also indicated its intent to submit an FDA and design certification application for its AP-600 reactor design.

The applicant intends to submit preliminary conceptual design.information in mid-1988, and the FDA and design certification application in early 1990. The staff acknowledged Westinghouse's intentions and indicated that there would be a need to allocate resources in its project resource schedules. Westinghouse indicated it would present a briefing on the AP-600 at a later time.

T asJ.Khn,ProjectManager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects

Enclosure:

As stated 1 . .. _ _ _ _ _ _ - . _ _ _b

I 1

Enclosure 1 )

l Meeting Attendees , j November 12, 1987 Name Organization W. Johnson , Westinghouse, Manager, Nuclear Safety Department l B. McIntire Westinghouse, Manager, Product L Licensing L M. Shannon Westinghouse, Licensing i

(. T. van de Venne Westinghouse, Engineering Manager. l'

! Advanced PWR Development f M.-Beaumont Westinghouse, Bethesda Office l T. Murley NRC . NRR  !

J. Snieaek NRC, NRR R. Starostecki NRC, NRR L. She.o NRC, NRR, DEST l

F.'Miraglia NRC, NRR, ADP l A. Thadani NRC, NRR, SAD D. Crutchfield NRC, NRR, DRSP L. Rubenstein NRC, NRR, PDSNP T. Kenyon NRC, NRR, PDSNP I

C i 8 m__________ ___ _a __ __  ;

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Enclosure 2 5

4 WEST hG-0JSE ELEC"R C CCP.

JES GN C~RT CA"Ci PROGRAM e

B. E.. .d S ..A._

NOVEMBER 12,1987 W. J. J0-NSON, MANAGIR NJC_IAR SA rY

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  • SCO)E ANJ S"RA"EGY C W JES GX lCA":n 3ROGRAM CER"
  • J ES GA Ah :) SAFE"Y TEATURIS l
  • CJRRINT L CihSIXG REVIW S"A"US l
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W D:ESIGN CERTIFICATION PROGRAM l

W STRATEGY-

  • COMP ETE PDA IN 1988
  • CONFIRM UCENSABluTY PRIOR TO FINAL DESIGN
  • IDENTIFY REGUl.ATORY HARD SPOTS
  • PROVIDE CERTAINTY FOR FINAL DESIGN ACTMTY
  • NUCLEAR POWER BLOCK SCOPE
  • PDA SUBMITTAL BASED.0N W/M- PROGRAM
  • INCLUDES.UP TO PREUMINARY DESIGN
  • $150 W TOTAL COST .'
  • INCLUDE 0 W/U.S. UTluTY INTERACT 10NS ]

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  • ADDm0NAL FEATURES TO MEET /f.XCEED U.S. NRC REQUIREMENTS J
  • FDA PROGRAM BASED ON JAPANESE PROJECT
  • W/WHI INmATED FINAL DESIGN ACTMilES WARCH 1987 TO BE COMPLETED ~1990
  • NUCLEAR POWER BLOCK SCOPE j!

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RESARSP/90FDASCOPE

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EQUIPMENT AND SYSTEMS IN SElSWIC CATEGORY 1 STRUCTURES .

i e " FINAL DESIGN" DEFINITION OF NUCLEAR POWER BLOCK SCOPE WILL PROVIDE COMPLETE

SET OF INFORMATION NEEDED TO SUPPORT STAFF SAFETY REVIEW FOR DESIGN CERTIFl-CATION l

e SPECIFIC SCOPE OF SUPPLY PROVIDES INPUTS AND ASSUMPTIONS NEEDED FOR PRA EXCEPT FOR SITE SPECIFIC EXTERNAL EVENTS

  • WILL PROVIDE ALL SAFETY RELATED BALANCE OF PLANT DESIGN INFORMATION [ SITE-SPECIFIC j ULTlWATE HEAT SINK) i*** i e _ ___ _

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  • A" TF E T0 ) LEVEL "F ERE IS EXCELLENT AGREEMENT BETWEEN A')WR MA,0R DIS GN OBJECTIVES AND EPR REQU REMENTS
  • A" THI MORE DETA _ED LEVEL, "HI EPRI

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SP/90 DESIGN & SAFETY FEATURES l

DBJECTNES OF DESIGN e ENHANCED PLANT SAFETY

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  • LDWER PCT: -BLDWD0WN ~1850* F

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  • IWPROVED PLANT PERFORMANCE

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  • EASE OF OPERABlUTY l 1

. o LESS OPERATOR ACTION o NO ECCS SWITCHOVER o OCCUPATIONAL RADlAITON EXPOSURE e LESSONS EARNED FROW EXISTING DESIGNS i

  • FRESH APPR0ACH TO PLANT LAYOUT TO WINIMIZE

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EFFECT OF C0WWON W0DE FA!!#RE DUE TO F1000 FIRE, SABOTAGE

  • N0 SHARING 0F SAFETY & NORMAL OPERATING SYSTEMS
  • DHR DNERSITf - B1IED & FEED e RESPONSWE TO CURRENT & EXPECTED FUTURE REGULATORY REQUIREMENTS
  • LOWER GENERATING COST
  • PLANT CAPITAL COST
  • FUEL CYCLI COST ham e '

____t-__-_----.

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W DESIGN CERTRICATION PROGRAM SP-90 DESIGN & SAFETY FEATURES SEVERE ACCIDEN" CONSIDERATIONS e CORE MELT FREQUENCY- 1 x 10-6 FOR INTERNA'. EVENTS i

  • CONTAINMEN" DESIGN SUCH THA" C00' ABLE G'EOMETRY IS MAINTA NED.

~

  • KEY D'ES'GN FEATURES TO S GNIrlCANTLY REDUCE CM7 .
  • 4 HIGH HEAD SAFETY INJECTION PUMPS
  • DEDICATED RCP SEAL INJECTION PUMP e EX"ERNAL EVENTS BOUNDING FOR MOST U.S. SITES

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W DESLGN CERTIFICATION PROGRAM CURRENT UCENSING REVIEW STATUS

  • ALL PDA MODJLES SUBMITTED
  • STAF REVIEW EFFORT INCREASING
  • FOCUSED PROJECT WANAGEMENT EFFORT SINCE

. NRR REORGANIZATION

  • REVIEW BRANCH ASSIGNMENTS WADE
  • W ADDRESS NG STAFF RAl's
  • RAl's BY BRANCH, NOT WODULE
  • W TURNAROUND < 60 DAYS
  • ACRS INTERACTION NEEDED

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  • REV EW SCiEDULE ESTAB lSHED

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. W DESIGN CERTIFICATION PROGRAW.

CURRENT PDA UCENSING REVIEW STATUS ACRS REVIEW STRATEGY l

l e GOAL IS TO KEEP ACRS FUI.LY INVOLVED )

1 e HAVE HAD 4 ACRS BRIEFINGS 1983-+1986

  • FULL COMMITTEE BRIEFING 11/6/87 g e SEPARATE DESIGN INTO RELATED SYSTEMS
  • PMNT SYSEWS - WODULES 1, 2, 4, 5 & 10
  • PMNT OPERATION & CONTROL. - WODUlIS 6/8, 9, 13 & 15
  • SIE & STRUCTURES - WODULIS 3,7,11,12 & 16
  • PRESENT AT 3 WEETINGS

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i W DESIGN CERTIFICATION PROGRAM.

CURRENT PDA UCENSING REVIEW STATUS e ESTABUSHED STAFF PDA REVIEW SCHEDULE (PER LETTER CRUTCHFIELD TO JOHNSON 6/19/87)

RAl's TO WESTINGHOUSE 8/87g WESTINGHOUSE RESPONSE TO ALL RAl's 12/87 DRAFT SER ISSUE 4/88\,

i WESTINGHOUSE C0WWENTS ON DRAFT SER 7/88

~

FINAL SDt ISSUE 10/88 PDA DECISION DATE 12/88 e PROPOSED ACRS SCHEDULE .

~

WODULES 1,2,4,5 & 10 (PLANT SYSTEWS) 3/88 WODULES 8/8,9,13 & 15 (PLANT OPERATION 4/88

& CONTROL)

. WODUlIS 3,7,11,12 & 18 (SITE & 5/88  :

STRUCTURES)

Full C0WWITTEE 8/88 L_A_ __

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i W JES Gs CER" FICK 10N PROGRAM FJ"JRE AC"lV"lES/COMMITMEN"S
  • UCENSING REVIEW BASIS DOCUMENT
  • C0XS S"EN" WIT- S"AOARD ZA"l0N PO_lCY i

e AP-600 SATE'Y REV EW l

.j brief11-9 1

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N ** e e a e dee W DESIGN CERTIFICATION PROGRAM.

FDA-UCENSING REVIEW BASIS DOCUMENT e ESTABUSH/ DOCUMENT UCENSING REVIEW PROCESS

  • WETHOD/TlWING 0F SEVERE ACCIDENT POUCY RULES /GUIDEUNES
  • WETHOD/TlWING OF STANDARDIZATION POUCY _

RUES /GUIDEUNES

  • PERIODIC TOP WANAGEMENT REVIEW e ESTABUSH/ DOCUMENT UCENSING REVIEW
REQUIREMENTS
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  • BRIDGE PDA OPEN ITEMS TO FDA
  • INCORPORATE WODULE 2 kwis r _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

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W DES GA CER"l CA"0N PROGRAM SJMMARY

  • RESAR S'/90 PJA RIV EW REV"A ZED

. j e B. _D MGMEN"JM TO FliS- PDA

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  • ESTAB S'-: FRAMIWORX FOR FDA a

e v " A"I A)-600 SATITY RIVIIW

  • C0X"lNJI PIR 0) C T0' LEVE_ MIET NGS brief14- 9

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