ML20045G384

Summary of 930603 Meeting w/GE,Westinghouse,ABB-C-E & D0E in Rockville,Md Re Status of Design Review Schedules Set Forth in SECY-93-097, Integrated Review Schedules for Evolutionary & Advanced Light Water Reactor Projects

ML20045G384
Person / Time
Site:	05200001, 05200002, 05200003, 05200004
Issue date:	07/01/1993
From:	Stephen Koenick Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9307130284
Download: ML20045G384 (79)

Text

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/t UNITED STATES j

,j NUCLEAR REGULATORY COMMISSION'

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WASHINGTON D.C. 20556 0001

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July 1, 1993 c

Docket Nos.52-001, 52-002,52-003, and 52-004 i

APPLICANTS:

GE Nuclear Energy (CE), Westinghouse, and ABB-Combustion Engineering (ABB-CE)

PROJECTS:

GE Advanced Boiling Water Reactor (ABWR) and Simplified Boiling j

Water Reactor (SBWR), Westinghouse AP600, and the CE System 80+

SUMMARY

OF MEETING HELD ON JUNE 3, 19:3, ON DESIGN CERTIFICATION j

REVIEWS i

A public meeting was held with representatives of the Nuclear Regulatory Commission (NRC), GE, Westinghouse, ABB-CE, and the Department of Energy (DOE), on June 3, 1993, in the White Flint offices of the NRC in Rockville, Maryl at d.

The meeting was held to discuss the status of the design review schedules set forth in SECY-93-097, " Integrated Review Schedules for the Evolutionary and Advanced Light Water Reactor Projects." There are six enclosures to this memorandum. The first enclosure contains the meeting attendees. The second enclosure reflects the NRC's introductory remarks. The third, fourth, and fifth enclosures contain the respective vendors' l

presentatioiis. The sixth enclosure was handed out at the meeting and is a memorandum that details the inspections, tests, analyses, and acceptance criteria (ITAAC) task groups for review of the GE and ABB-CE ITAAC submittals.

Opening remarks were made by the staff, followed by DOE.

The staff summarized its schedules for review of the four design certification applications and emphasized the importance of timely, high-quality submittals from the applicants.

Furthermore, the staff stated that all its reviews are proceeding based on the assumption that the Commission will approve the positions proposed by the staff in SECY-93-087, " Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor Designs." The staff is concerned that additional interaction on these issues could impact schedules significantly.

DOE expressed concern that design certification reviews are not moving forward quickly enough, and funding could be affected during the next fiscal year. DOE has proposed that periodic management review meetings such as this one be held to review progress of certification reviews.

GE gave the presentation on the ABWR (Enclosure 3). There were twb main issues raised by GE:

(1) the requirement for review of the design control document prior to final design approval issuance, and (2) the lack of feedback from the staff on the three ITAAC submittals. On the last issue, the staff responded that all outstanding design issue:; need to be resolved prior to starting the ITAAC review.

(The formal ITAAC review was subsequently started on June 21,1993.)

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i July 1, 1993 The second presentation was given by ABB-CE on the System 80+ (Enclosure 4).

Three principal issues were raised:

(1) the need for a consistent tracking system for the remaining open items, (2) the competition for NRC resources, and (3) strong endorsement of EPRI's opposition to the staff position in i

SECY-93-087 on the post-accident sampling system.

Westir.ghouse followed with a presentation on the AP600 (Enclosure 5).

Westinghouse raised the issue of limited NRC resources available to review its design and the resulting impact on the AP600 review schedule.

The staff reiterated that the Electric Power Research Institute's Passive Utility Requirements Document and the evolutionary plant designs have priority.

Westinghouse emphasized that feedback from the NRC was important, and that early identification of problem areas would help both sides meet the schedule.

l Westinghouse requested a letter on the acceptability of their AP600 test matrix.

GE concluded the presentations with the simplified boiling water reactor (Enclosure 3), and emphasized that they were planning on capitalizing on lessons learned from the ABWR review.

A follow-up meeting is tentatively scheduled for August 2, 1993.

(Original signed by)

Stephen S. Koenick, Project Engineer Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal l

Office of Nuclear Reactor Regulation

Enclosures:

As stated cc w/ enclosures:

See next pages DISTRIBUTION w/ enclosures:

Docket Files PDST R/Fs DCrutchfield PDR PShea (1)

SKoenick DISTRIBUTION w/o enclosures:

WRussell,12G18 JNWilson TWambach TEssig l

MCase CPosiusny MFinkelstein, OGC TBoyce MMalloy SNinh SMagruder FHasselberg CMcCracken, 801 RBorchardt TKenyon NMarkisohn JHWilson JMoore, 15B18 GGrant, 17G21 ACRS (11)

J0'Brien, RES BHardin, RES EJordan, MNBB3701 LShao PShea (3) n 3

f 0FC LA:PDST PE:PDST SNI SC DST (A)D:[ST A R NRR #

NAME PShea an? SKoenick d Jtdidson TEk[ig RBobrdt D[rubcNeld DATE 06/80[93 06/cra/93 06Sa/93 06/3D/93 06A0/93 (TF/ / /93 0FFICIAL RECORD COPY:

MIG 63.SSK 1

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cc:

Mr. Patrick W. Marriott, Manager Mr. Joseph Quirk Licensing & Consulting Services GE Nuclear Energy

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GE Nuclear Energy General Electric Company 175 Curtner Avenue 175 Curtner Avenue, Mail Code 782 i

San Jose, California 95125 San Jose, California 95125 s

I Mr. Robert Mitchell General Electric Company 175 Curtner Avenue i

San Jose, California 95125 1

j Mr. L. Gifford, Program Manager l

Regulatory Programs GE Nuclear Energy 4

12300 Twinbrook Parkway Suite 315 i

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Rockville, Maryland 20852

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Director, Criteria & Standards Division.

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Office of Radiation Programs U. S. Environmental Protection Agency 3

401 M Street, S.W.

Washington, D.C.

20460 Mr. Frank A. Ross 2

l U.S. Department of Energy, NE-42 Office of LWR Safety and Technology 19901 Germantown Road Germantown, Maryland 20874 1

thrcus.A. Rowden, Esq.

Fried, Frank, Harris, Shriver & Jacobson 1001 Pennsylvania Avenue, N.W.

Suite 800 Washington, D.C.

20004 Jay M. Gutierrez, Esq.

Newman & Holtzinger, P.C.

1615 L Street, N.W.

Suite 1000 Washington, D.C.

20036 Mr. Jeffrey C. Baechler GE Nuclear Energy 175 Curtner Avenue, MC-782 San Jose, California 95125

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cc:

Mr. C. B. Brinkman, Acting Director Mr. S. M. Modro Nuclear Systems Licensing EG&G Idaho Inc.

ABB-Combustion Engineering, Inc.

. Post Office Box 1625 1000 Prospect Hill Road Idaho Falls, Idaho 83415 Windsor, Connecticut 06095-0500 Mr. C. B. Brinkman, Manager Mr. Nicholas J. Liparulo Washington Nuclear Operations Nuclear Safety and Regulatory Analysis ABB-Combustion Engineering, Inc.

Nuclear and Advanced Technology Division 12300 Twinbrook Parkway, Suite 330 Westinghouse Electric Corporation Rockville, Maryland 20B52 P.O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. Stan Ritterbusch Nuclear Systems Licensing Mr. B. A. McIntyre ABB-Combustion Engineering, Inc.

Advanced Plant Safety & Licensing 1000 Prospect Hill Road Westinghouse Electric Corporation Post Office Box 500 P.O. Box 355 Windsor, Connecticut 06095-0500

-Pittsburgh, Pennsylvania 15230 Mr. Sterling Franks Mr. John C. Butler U. S. Department of Energy Advanced. Plant Safety & Licensing NE-42 Westinghouse Electric Corporation Washington, D.C.

20585 P.O. Box 355 Pittsburgh, Pennsylvania 15230

-l Mr. Steve Goldberg i

Budget Examiner Mr. M. D. Beaumont 725 17th Street, N.W.

Nuclear and Advanced Technology Division 1'

Washington, D.C.

20503 Westinghouse Electric Corporation One Montrose Metro Mr. Raymond Ng Il921'Rockville Pike 1776 Eye Street, N.W.

Suite 350 Suite 300 Rockville, Maryland 20B52 Washington, D.C.

20006 Joseph R. Egan, Esquire Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W.

Washington, D.C.

20037-1128 Mr. Regis A. Matzie, Vice President Nuclear Systems Development ABB-Combustion Engineering, Inc.

1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500

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MEETING ATTENDEES JUNE 3. 1993 3

i NAME AFFILIATION L

I Sterling Franks DOE E. Brolin DOE D. McGorr DOE Regis Matzie ABB-CE j

Dennis Crutchfield NRR/ADAR W. T. Russell NRR/ADT Bill Borchardt NRR/ADAR Jerry N. Wilson NRR/ADAR Bob Berglund GE Howard Bruschi WESTINGHOUSE Brian A. McIntyre WESTINGHOUSE Tom Wambach NRR/ADAR Tom Essig NRR/ADAR Michael Case NRR/ADAR I

Steve Frantz NEWMAN & HOLTZINGER Joe Quirk GE 2

Charles Thompson DOE Norman D. Fletcher DOE /ALWR Frank Ross DOE Pat Marriott GE Alan Beard GE Mike Finkelstein OGC/ ADVANCED REACTORS Chet Poslusny NRR/ADAR i

Tom Boyce NRR/ADAR Joe Longo ABB-CE Charlie Brinkman ABB-CE George A. Davis ABB-CE Peter M. Lang DOE Melinda Malloy NRR/ADAR Trevor Cook DOE Gary Vine EPRI Stephen Koenick NRR/ADAR Son Ninh NRR/ADAR Stewart Magruder NRR/ADAR Rick Hasselberg NRR/ADAR Conrad McCracken NRR/DSSA

DESIGN CERTIFICATION REVIEW SCHEDULES

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JUNE 3,1993

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4 INTEGRATED REVIEW SCHEDULES 4

SECY-93-097 provides very aggressive schedule dates for completing e

evolutionary and advanced LWR reviews e

SECY-93-097 schedule dates assume timely, high-quality submittals by the vendors availability of review resources resolution of policy issues at an early enough stage to be integrated into the review process l

SECY-93-097 did not provide additional schedule margin for e

uncertainties such as resource impact of conducting five major review activities simultaneously i

' reiterative interaction with vendors necessary to implement resolution of key policy issues such as severe accidents and ITAAC identification of new policy / technical issues on evolutionary reviews t

Progress towards schedule. milestones

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SECY-93-097 SCHEDULE MILESTONES PROJECT MILESTONE Applicant's RAI DSER issued FSERissued Design Responses Certification EPRI Passive URD Complete Complete November NA 1993 ABWR Complete Complete March November 1994 1995 System 80+

Complete Complete June February 1994 1996 AP600 September May November July 1993 1994 1995 1997 SBWR January September March November 1994 1994 1996 1997 l

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STAFF RESOURCE PRIORITIES Completion of the FSER on the EPRI passive Utility Requirements e

Document Closure of open design issues and ITAAC issues for both the ABWR and e

System 80+ designs Resolution of remaining passive plant policy issues e

Regulatory treatment of non-safety systems (RTNSS) source term issues Simplification of emergency planning Review of vendor test programs in support of passive plant designs l

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Developing requests for additional information (RAls) on passive plant e

designs 9

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MAJOR REMAINING ACTIVITIES FOR FSER COMPLETION Resolution of Draft Safety Evaluation Report (DSER) open items Task group review of phased ITAAC submittals l

Applicant internal validation of SAR, ITAAC, and design information Applicant submittal of certified SAR and ITAACs Staff verification of issue resolution including independent quality review ACRS subcommittee and full committee meetings FSER completion

MAJOR IMPLEMENTATION ISSUES FOR COMPLETION OF EVOLUTIONARY DESIGNS o

PRA Severe accident closure i

Technical Specifications ITAAC i

Vendor specific design issues l

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Tier 1 design description 1

Quality of certified SSAR, tier design description, and ITAAC i

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STAFF APPROACH FOR IMPLEMENTATION OF i

ITAAC REVIEW I

Seven task groups formed and ITAAC systems assigned e

t Multi-disciplined approach - several review branches represented on e

each task group Simultaneous, parallel review of ABWR and System 80+ phased e

submittals for consistency of reviews h

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Short turnaround reviews I

Staff goal of 2-3 weeks for comments-l Expect vendor incorporation within 2 weeks t

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4 Approximately 100 ITAAC systems for each design e

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MAJOR ISSUES AFFECTING REVIEW PROGRESS FOR PASSIVE LWRs Completion of review of EPRI passive utility requirements document Resolution of remaining passive plant policy issues RTNSS issues Source term issues Vendor test programs (expected completion - early 1994)

Integrated ITAAC/ design review 4

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DESIGN CERTIFICATION RULEMAKING ACTIVITIES Commission guidance on rulemaking proceedings for design certification e

(SECY-92-381) issued April 1993 1

A Federal Register Notice inviting public comment on the proposed e

design certification rule for the evolutionary LWR designs to be prepared after receiving Commission guidance on design certification rule form and content (SECY-92-287A)

Staff preparing guidance to vendors on the form and content of a Design e

Control Document (DCD) discussed in SECY-92-287 i

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LICENSING CERTIFICATION i

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STANDARDIZED CERTIFIED DESIGNS KEY TO SUCCESSFUL IMPLEMENTATION OF NPOC STRATEGY I

o PART52 IMPLEMENTATION REQUIREMENTS

- QUALITY j

-- WITHSTAND TEST OF TIME (LEGAL CHALLENGES)

-- AGREEMENTS FOCUSED ON FORM, CONTENT, AND TECHNICAL DETAILS 4

- TIMELINESS

--lMPORTANT FOR INDUSTRY CREDIBILITY AND CONFIDENCE

--ESSENTIAL FOR US. INDUSTRY PARTICIPATION INTERNATIONALLY f

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6/3/93 l

ABWR FDA Schedule 1993 1994 Finish Activity Date Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul DFSER issue Resolution 5/14/93 MB SSAR/ Tier i Verification 6/14/93 E

SSAR (Reissued) 7/31/93 Tier 1 Document 7/31/93 M

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NRC SSAR andTier 1 8/31/93 Verification E

Conforming Changes to SSAR 11/12/93 FSER (SSAR) 12/17/93 E

ACRS Reviaw 1/29/94 E

FDA Preparation & Issuance 5/31/94 Initiate Certification Process A

6/1/94 (including DCD) 1

ABWR DESIGN CERTIFICATION - ITAAC SCHEDULE JULY AUG MAY JUNE l

ACTIVITY l

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• GE PRELIMINARY A

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• GE FINAL SUBMITTAL 7/9

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INTERNAL SCHEDtJLE t_EADING TO REISStJED VERII IED SSAR ANO GEFINAL VIER 1 (INCLUDING ITAAC) DOCUr1ENT Jan Feb Mar Apr Nau Jun Jul Huo

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l ABWR CERTIFICATION PROGRAM STATUS / SCHEDULE o

DFSER issued by NRC 10/20/92 10/20/92

- 754 design-related issues

- 174 ITAAC-related issues All design-related issues addressed by GE 4/30/93 o

All design-related issues closed by NRC 5/28/93 o

- 41 Open items Remain

- Management Meeting to Confirm Closure - 6/10/93 o

Final SSAR and Tier 1 submitted to NRC 7/31/93 t

6/3/93

i ABWR DESIGN C ERTIFICATION TIER 1/ITAAC STATUS o PHASED SUBMITTAL OF REVISE 0 TIER 1 i

SCHEDULED PACKAGE ENTRIES SUBMITTAL STATUS PHASE A 21 4/23/93 SUBMII I ED 4/26/93

' PHASE B 33 5/221/93-SUBMITTED 5/21/93 PHASE C 29 6/4/93 AT LEAST 2,7 WILL BE SUBMITTED PHASE D 18 6/18/93 ON SCHEDULE FINAL 101 7/30/93 PHASES A, B, C, D BEING SUBMITTED IN PARALLEL WITH RESOLUTION OF SSAR ISSUES. RECONCILIATION PLANNED IN JUNE / JULY I

o NRC REVIEW SCHEDULE REVIEW TEAMS IN PLACE NRC UNDERSTANDS THE 7/30/93 DATE BUT IS NOT COMMITTED TO TIER 1 WRAP-UP ON THIS SCHEDULE 6/3/93

ABWR DESIGN CERTIFICATION TIER ' /ITAAC STATUS (continued) o VERIFICATION (OA COMPLIANCE)

SCHEDULED FOR COMPLETION BY 7/9/93 PROCESS IN PLACE AND LEAD SYSTEMS COMPLETE; DEPENDENT ON SSAR CLOSURE AND VERIFICATION 4

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1 ABWR FDA Schedule Assumptions t

GE would provide amendments to the Standard Safety Analysis Report (SSAR) to i

o enable the staff to close out the Draft Final Safety Evaluation Report (DFSER) j i

outstanding items y

f Marked-up SSAR submittals would be statused within two weeks following their o

submittals to confirm that the submittal adequately resolves the issue t

i SSAR amendments would be statused within two weeks following their submittals to o

confirm that the issues addressed in the amendment are closed I

i SSAR changes resulting from the development of the Tier 1 documentation would not o

" undo" the agreed-on resolution of DFSER non-Tier 1 issues. These changes; would f

be made available 1-1/2 months prior to issuance of the final SSAR r

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i ABWR FDA Schedule Assumptions (continued)

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The final amended SSAR would serve as the base document for the verification l

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process. The verification process to be done by GE would involve checking (I) the final amended SSAR against itself to assure technical accuracy and consistency and (2) the Tier 1 documents against the verified SSAR To improve upon the readability of the verified SSAR, a new, reformatted SSAR would 4

o be developed using a new format. Upon completion, the reformatted SSAR would be verified by GE against the verified SSAR. The verification would assure the reformatted SSAR content is identical to the content of the verified SSAR t

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i NRC verification of the reformatted SSAR would be a OA/QC conformance check o

against the amended SSAR. GE assumes that no technical issues would result from i

the verification i

6/3/93

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ABWR FDA Schedule Assum ations (continued)

The final Tier 1 documentation would be statused within one month of its s o

NRC. Completion of the review would be targeted within this time frame l

The combination of metric and English units would not required for the SSAR and Tier o

1 document No additional redirections pertaining to the Tier 1 format.and content are deemed o

necessary i

1 Submittal of the Design Control Document is not required prior to issuance of the o

Final Design Approval

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1 T-iFiEATS TO ABWR SCHEDULE TIMELY FEEDBACK:

I Closure of issues Quality-related issues Delayed initiation of Review of Tier 1 Submittals -

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Key Discussion Points (SBWR Schedu.e) i SECY-93-097 shows receipt of application on 3/93, GE assumes this has been o

. completed (GE notified 5/27/93) i t

Total review time is 37 months for AP-600,38 months for SBWR, SBWR should at i

o least maintain parity with AP-600 i

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RECENT SBWR in :erac': ions The Design Certification (DC) Application was submitted on o

August 27,1992 A supplement was submitted on Febivary 25,1993 which included the Tier 1 Design-Certification Document, and three TRACG Topical Reports GE received an application acceptance letter on May 27,1993 formally docketing the i

SBWR DC Application Round Zero Requests for Additional Information (RAls) were received on o

January 28,1993. 44 of 213 have been submitted the remainder will be submitted by June 30,1993.

Testing discussions have been held with ACRS/NRC since April 1992, the i

o most recent interaction was an NRC visit to the SIET facility in Italy during April 1993. A summary of all testing was submitted on May 7,1993.

I 6/3/93

SBWR FDA Schsdule History

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Reference 1992 1993 1994 1995 1996 (months)

Original Contract Date 22 8/31 i I

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SECY-91-161 Schedule 29 8/3 1/12 d

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May 91 NPOC Strategic Plan 25 8/31 8/30

'~d Sept.93 FSER to PM SECY-93-097 Schedule 38 3/31 7eai s/31

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SYSTEM 80+ AGENDA MILESTONE / SCHEDULE FOR SYSTEM 80+

(CONSISTENT WITH SECY-93-097)

J ASSUMPTIONS REQUIRED FOR SCHEDULE TO BE MET POTENTIAL THREATS TO SCHEDULE OPPORTUNITIES FOR IMPROVEMENT DESIRED NEAR-TERM ACTIONS i

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ABB-CE PLANNING SCHEDULE FOR COMPLETION OF NRC REVIEW OF SYSTEM 80+

1994 1993 Jun l Jul l Aug l Sep l Oct l Nov l Dec Jan l Feb l Mer l Apr l May l Jun l Jul l Aug l Sep l Oct l Nov l Dao ID Action Party ActMty 1

ABB-CE&NRC Complete negotistion on DSER lesues y

2 ABB-CE Complete ITAACs & Tier 1 DD y

3 ABB-CE Complete COL Action Iteme in CESS AR-DC g

4 ABB-CE Complete inittelIntegrated Review of CESSAR-DC

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6 NRC Complete DSER Stetus Trocking System y

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t CRITICAL ASSUMPTIONS REQUIRED TO MEET SCHEDULE i

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I NRC AND ABB-CE MUTUALLY DEVELOP DETAILED DSER STATUS AND TRACKING i

~$YSTEM JUNE 22, 1993 ABB-CE COMPLETES INITIAL INTEGRATED c

REVIEW OF CESSAR-DC JUNE 22, 1993

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l ABB-CE COMPLETES TIER 1 DESIGN DESCRIPTION AND ITAACS JUNE 22, 1993 ABB-CE SusMITS CESSAR-DC AMENDMENT P WITH DSER ITEMS INCORPORATED JUNE 30, 1993 (INCLUDES RESULTS OF INTEGRATED REVIEW, 4

TIER 1 DD AND ITAACS)

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CRITICAL ASSUMPTIONS REQUIRED TO MEET SCHEDULE (CONT.)

ABB-CE & NRC MUTUALLY ESTABLISH SCHEDULE FOR RESOLUTION OF EACH REMAINING DSER ITEM JUNE 30, 1993 FUTURE NRC RESOLUTIONS OF REMAINING SECY-93-087 ISSUES ARE CONSISTENT WITH NRC & ABB-CE AGREEMENTS ON l

SYSTEM 80+

JUNE 30, 1993 e

NRC REVIEWER PROMPTLY CONFIRMS THAT EACH ABB-CE SUBMITTAL (MARKED-UP SAR i

SECTIONS)

CLOSES EACH REMAINING ITEM (WITHIN TWO WEEKS OF EACH SUBMITTAL) e NRC REVIEWER PROVIDES FSER INPUT PROMPTLY (WITHIN TWO WEEKS)

AFTER CONFIRMATION THAT ISSUE IS CLOSED l

A IE HR i Combustion Engineering P%EDED

CRITICAL ASSUMPTIONS REQUIRED TO MEET SCHEDULE (CONT.)

l ABB-CE SusMITS LAST MARK-UP OF SAR SECTION TO CLOSE OUT FINAL SET OF DSER ISSUES OCT. 1, 1993 IF NRC PERFORMS INDEPENDENT CONFORMANCE VERIFICATION OF CESSAR-DC AND TIER 1 INFORMATION, IT WILL NOT IMPACT SCHEDULE NOv. 30, 1993 NRC ISSUES FSER TO COMMISSION FEB.

1, 1994 ABB-CE SUsMITS DCD TO NRC JULY 15, 1994 NRC REVIEW OF DCD DOES NOT INCLUDE A " TECHNICAL" REVIEW A ER RE Combustion Engineering.

P}EDED

1 POTENTIAL TilREATS To SCHEDULE:

COMPETITION FOR NRC RESOURCES LAST MINUTE REQUEST (S)

FOR ADDITIONAL LEVEL-OF-DETAIL IN SELECTED AREAS 1

e UNTIMELY IDENTIFICATION OF NEW INFORMATION REQUESTS BY NRC AND SUBCONTRACTORS NRC REVIEWER PRESSURE To PROVIDE COL INFORMATION (OPERATIONAL SUPPORT INFORMATION)

TIER 1 DD AND ITAAC REVIEW NEGATES RESOLUTION OF DSER ITEMS A ER ER Combustion Engineering 7%EFEp

POTENTIAL THREATS TO SCHEDULE (CONT.)

l FAILURE TO DEVELOP AND HOLD TO INTEGRATED SCHEDULE FOR CLOSURE OF ISSUES (WHICH COULD IMPACT ABB-CE AND NRC RESOURCES) e GENERIC RULEMAKING FOR SEVERE ACCIDENTS ON PASSIVE I

PLANTS POSSIBLY RE-OPENING EVOLUTIONARY PLANT RESOLUTIONS TIER 1 DESIGN DESCRIPTION AND ITAAC FORM AND CONTENT AGREEMENTS BEING RE-0PENED i

i a

NEW TECHNICAL ISSUES RAISED DURING DCD REVIEW BY NRC i

i I

i l

JL ER ER i

l Combustion Engineering f}EfEp

OPPORTUNITIES FOR IMPROVEMENT:

1 EARLY START OF ACRS REVIEW, PRIOR TO FSER TRANSMITTAL TO COMMISSION (1 TO 1-1/2 MONTH SAVINGS) e CONTINUOUS, HIGH QUALITY FSER INPUTS FROM NRC REVIEWERS TO PROJECT MANAGER AS ISSUES ARE CLOSED (1 TO 2 MONTHS SAVINGS) i NRC PROJECT MANAGER REDUCES TIME NEEDED FOR FSER e

ISSUANCE, BECAUSE OF EARLIER, CONTINUOUS INPUTS FROM l

REVIEWERS (1 TO 1-1/2 MONTH SAVINGS) i NRC REVIEW OF DCD SEPARATED FROM FDA, SO THAT FDA CAN

)

e BE ISSUED 1 MONTH AFTER COMMISSION DECISION (1 TO 1-3/4 MONTH SAVINGS) i AE fSEgEt EF i Combustion Engineering

DESIRED NEAR-TERM ACTIONS:

MUTUALLY DEVELOP DETAILED STATUS AND TRACKING SYSTEM OF ISSUE CLOSURE JUNE 22, 1993 MUTUALLY DEVELOP D_ ETA _I_LE_D_ SCHEDULE FOR CLOSURE OF REMAINING ITEMS JUNE 30, 1993 DEVELOP RESOURCE PLAN CONSISTENT WITH DETAILED SCHEDULE FOR CLOSURE OF REMAINING ITEMS TO MEET SECY-93-097 MILESTONES JULY 7, 1993 SHARE WEEKLY STATUS OF ISSUE CLOSURE JUNE 22, 1993 e

e AGREEMENT To HAVE EARLY FEEDBACK (WITHIN 2 WEEKS)

AND FSER INPUT (WITHIN NExT 2 WEEKS)

FOR REMAINING ITEMS JUNE 3, 1993 AGREEMENT THAT ADDITIONAL LEVEL OF e

i DETAIL REQUESTS AND/OR NEW INFORMATION REQUESTS ARE ISSUED THROUGH JOINT SENIOR MANAGEMENT JUNE 3, 1993 A It It Combustion Engineering 7% EDEN

4 i

-AP600 DESIGN CERTIFICATION PROGRAM DOE /NRC/ INDUSTRY DESIGN CERTIFICATION PROGRAM STATUS JUNE 3,1993 H. J. BRUSCHI, GENERAL MANAGER ADVANCED TECHNOLOGY l

i WESTINGHOUSE ELECTRIC CORPORATION T2

=

LTt I

PURPOSE To work with the NRC staff to improve the process of AP600 Design Certification through a mutally agreed-upon schedule.

In particular:

o Develop a schedule incorporating a status tracking system ~to which we commit ourselves.

o Work together to identify areas of schedular improvement and incorporate into the schedule.

o Establish a series of AP600 project review meetings in which we manage the process of design certification.

1

PREVIOUS NRC/W ACTIONS TO MAINTAIN SCHEDULE

- PLANT DESCRIPTION REPORT

- FEBRUARY 22,1989

- TESTING AGREEMENT

- JUNE 26,1992 SUBMITTAL

-SSAR

- PRA

- RAl'S FROM STAFF

- DECEMBER 14,1992 SUBMITTAL

- ITAAC

- DECEMBER 31,1992 ACCEPTANCE OF APPLICATION

- UTILITY REQUIREMENTS DOCUMENT

- REGULATORY TREATMENT OF NON SAFETY SYSTEMS (RTNSS) AGREEMENT

- IDENTIFICATION OF TECHNICAL ISSUES (SECY-93-087) i

b REQUESTS FOR ADDITIONAL INFORMATION

~

- 846 RECEIVED

- 774 RESPONSES

-INPUT NOT RECEIVED IN SEVERAL AREAS

- PRA

- PASSIVE-SAFETY SYSTEMS l

RAI RESPONSIVENESS 900

/

['

/

RECEIVED s~

/

J

/

a.o 500 m:

m 400 RESPONSES mY 300 200 100 0

23 Sep92 0*as 92 28 & s 92 in Nov 92 08 Jan 91 2&Jan93 23 Feh 91 18 Mar 93 29 Ape 93 la May 93 Olas-92 14-as 92 I A No. -92 22.I.A -92 22 Jaw 93 08-h tF9) 21 hb 9)

ROApe9) 03-May 93 28 May 93 DATE

,--,,-,-__----__--_,--,-----,.______,-._-,-_-.___---._,_,_,.------,---_.,_._-------.,_--,-_--,,,--,-,,---__n-,---

g 4

CRITICAL ISSUES

- REMAINING RAl'S DUE JUNE 30,1993

- FEEDBACK ON W RESPONSES

- TESTING MATRIX AGREEMENT NEEDED

- ITAAC UPDATE

- AP600 RTNSS RESOLUTION IMPLEMENTATION TO NRC IN AUGUST 1993 d

4

_,_.___,__._--__v.-_

OTHERISSUES

- TECHNICAL ISSUE RESOLUTION

- COMMISSION GUIDANCE NEEDED (SECY-93-087)

- W COMMENTS FORTHCOMING

- NRC STAFF RESOURCES

- INTERACTION AMONG PROJECTS e

ACTibNS TO IMPROVE SCHEDULE

- DETAILED SCHEDULE WITH STATUS TRACKING SYSTEM

- FEEDBACK ON QUALITY OF RAI RESPONSES

- AP600 SSAR AND PRA IN WORDPERFECT FORMAT

- EXAMINE WHAT CAN BE ACCOMPLISHED SIMULTANEOUSLY

- WESTINGHOUSE TIME TO RESPOND TO DSER

- USE LESSONS LEARNED FROM EVOLUTIONARY PLANT PROGRAMS

- REGULAR PROJECT REVIEW MEETINGS

- MUTUAL COMMITMENT TO MEET SCHEDULE

CONCLUSIONS

- PROGRESS HAS BEEN MADE

- NEED A BETTER PROCESS TO SURFACE ISSUES AND FOCUS ON RESOLUTION

- DETERMINATION OF CRITICAL ACTIONS, WHO IS RESPONSIBLE, AND DATE FOR RESOLUTION

- AP600 IS OBJECTIVE EXPRESSION OF URD

- WITH AGREED - UPON SCHEDULE, PERFORMANCE WILL ULTIMATELY DETERMINE ACHIEVEMENT

- WESTINGHOUSE IS COMMITTED TO AP600 4

9 4

i

i l

/

e UNIT E D STATES Ig NUCLEAR REGULATORY COMMISSION j

j,g["ge g

W ASHINGTON, D. C. 2o555

%.v /

l May 21, 1993 MEMORANDUM FOR: Those on Attached List FROM:

William T. Russell, Associate Director for Inspection and Technical Assessment Office of Nuclear Reactor Regulation

SUBJECT:

ESTABLISHMENT OF INSPECTIONS, TESTS, ANALYSES, AND ACCEPTANCE CRITERIA (ITAAC) TASK GROUPS FOR GE ABWR AND ABB-CE SYSTEM 80+

The initiation of interdisciplinary ITAAC reviews will _ commence upon a management determination that the remaining open items from each evolutionary l

plant design reviews either will not impact the ITAAC review or are few in number such that their impact on ITAAC can be effectively managed on a case-by-case basis. A senior management meeting with GE is set for June 9-10, 1993, to review the remaining open items in the ABWR review, and to make a decision on initiating the ITAAC task group reviews for the ABWR.' A similar senior management meeting is planned with CE in mid-July for the System 80+.

Until management direction is given to commence these ITAAC reviews, staff review effort should focus on closing open design review items and drafting SER inputs and transmitting such SER inputs to Projects.

The vendor schedules for ITAAC submittals is contained in Enclosure 1 and the overall Commission schedule for these reviews is in Enclosure 2.

Guidance for the reviews of the Westinghouse AP600 and GE simplified boiling water reactor ITAAC will be contained in a separate memorandum.

The pilot ITAAC reviews conducted in January through March 1993, demonstrated the need for an interdisciplinary review of subsequent ITAAC submittals. The branch chiefs and section leaders involved in these pilot reviews have i

reviewed the lessons learned and recommended the establishment of seven ITAAC task groups. These ITAAC task groups will have primary responsibility for the review of specific assigned ITAAC. The responsible branch chief and task group leaders are specified in Enclosure 3.

Team members for each task group will be made up from staff members who performed the ABWR and CE System 80+

design reviews. Selected issues that impact many ITAAC reviews, such as treatment of motor-operated valves, probabilistic risk assessment, severe accidents insights, and pre-operational testing issues, will.be reviewed by the individuals identified in Enclosure 3.

Task group leaders are authorized to assign portions of ITAAC reviewed as necessary to these special area reviewers. The ITAAC assigned to each task group for review is contained in Enclosures 4 (GE ABWR) and 5 (CE System 80+).

[

2 The leader of each task group is responsible for preparing the evaluation of In order to the assigned ITAAC for input to the safety evaluation report.

complete the review in a timely manner, each task group leader is responsible for coordinating team members' comments, meetings, teleconferences, and correspondence with the vendors through Projects. Task group leaders have the authority to call on reviewers in other branches in order to complete the review. Task group leaders should coordinate reviewer assignments at the branch chief level, and resolve conflicts at the division director level.

Task group leaders are to make progress reports to Projects for both the GE ABWR and the CE System 80+ by Friday of each week.

Projects will summarize the information in a weekly report to the Executive Team. A sample format is contained in Enclosure 6.

The overall schedule of this review will be based 4

upon the following milestones:

(1) task group leaders will generate comments within two weeks of the start of the ITff,C review, (2) Projects will transmit the team comments to the applicant within one week of receiving the comments, j

4 (3) an ITAAC will be reported as status " yellow" if not resolved within two weeks of receipt of the vendors' reply to team comments, and (4) an ITAAC will be reported as status " red" if not resolved within one month of receipt of the vendors reply to team comments. An ITAAC is considered resolved (i.e.,

becomes confirmatory) when the ITAAC team has a satisfactory markup of the i

ITAAC submitted by the vendors. These milestones will be reported to the NRR Executive Team weekly.

1 4

Task group leaders should notify the responsible branch chief and Projects immediately of any problems in timely completion of their assigned reviews.

ITAAC which are status " red" will be individually briefed by the responsible branch chief at the Thursday ADT staff meeting.

Guidance for the conduct of the reviews based on lessons learned from the pilot ITAAC reviews will be issued to task group leaders.

This guidance includes checklists for design descriptions and ITAAC (Tier 1) and boilerplate ITAAC entries for selected issues.

Each task group leader is responsible for implementing the ITAAC review guidance, as well as for updating ITAAC review 4

J. Lyons guidance as experience is gained during the course of the reviews.

is the manager responsible for coordinating and updating ITAAC review guidance.

The following approach is recommended for use by each ITAAC review team:

individual team members should conduct an individual review of the assigned ITAAC; task group meets to prepare comments and questions; comments and questions are formally transmitted to the vendor; the vendor initiates phone calls to discuss and clarify issues; meeting is held with the vendor if needed to resolve comments (only after comments have gone to vendor); vendor submits revised ITAAC (may be pen and ink markup); staff reviews changes (closeout should only be when written markup is agreed upon).

i

3 1

Reviewers assigned to task groups are responsible for timely comments and aggressive participation in the task group.

Reviewers are also responsible for knowledge of the ITAAC review guidelines for their a >propriate area of review responsibility, and updates of those guidelines tirough the appropriate task group leader. Specialists are responsible for developing guidance on their issues for task group leaders,.and for inputs to the task groups, as needed.

Assuming timely vendor submittals and closeout of open design review issues, I expect task groups to perform parallel reviews of the vendor submittals to allow for maximum exchange of lessons learned and consistency of review. The reviews may be conducted offsite and in conjunction with other task groups. A project manager will be assigned as part of the review team for continuity between teams and for interface coordination with the vendors.

I have scheduled a training session on June 1,1993, Room 1F7/9, from 8:30 a.m. to 11:30 a.m. to discuss this memorandum and to issue lessons learned from the earlier pilot ITAAC reviews.

Orisital ti;md By v:u, m 7. IwWM William T. Russell, Associate Director for Inspection and Technical Assessment Office of Nuclear Reactor Regulation

Enclosures:

1.

Vendor Submittals Schedule for ITAAC 2.

Evolutionary ALWR Review Schedules 3.

Task Group Membership 4.

Task Group Assignments for GE ABWR l

5.

Task Group Assignments for CE System 80+

6.

Sample format for Task Group Progress Reports DISTRIBUTION:

Central File WRussell TMurley FMiraglia JNWilson

- RBorchardt TBoyce TEssig MFranovich FHasselberg TKenyon SMagruder MMalloy NMarkisohn SNinh CPoslusny l

TWambach MCase RPerch, BE5 JLyons, 801 WBurton, 8D1 MChiramal, BH7 JStewart. 8H7 MRubin, BE23 GThomas, BE23 JWigginton, 10D4 RPederson, 10D4 JLee, 1004 REckenrode, 10D24 l

CGoodman, 10D24 GGalletti,10D24 JKudrick, BD7 -

JMonninger, 807 l

DThatcher, 7E4 JKnox, 7E4 DTerao, 7H15 Tcheng, 7H15 RGramm, 9Al TPolich,10A19 RPall a,10E4 GKelly, 10E4 1 0 V, 9H15 EFox AEl-Bassioni, 10E4 0FC: PM:PDST:AD ADI:NRR NAME: TBoyce:tz/ J WRussell DATE: 05/B//93 05/q/93 0FFICIAL DOCUMENT COPY: WTRRVWGD.THB 1

Addressees - Memorandum dated May 21, 1993 Dennis M. Crutchfield, Associate Director Conrad E. McCracken, Chief for Advanced Reactors and License Renewal Plant Systems Branch

' Dffice of Nuclear Reactor Regulation Division of Systems Safety and Analysis, NRR James E. Richardson, Director

Division of Engineering Robert C. Jones, Chief l Office of Nuclear Reactor Regulation Reactor Systems Branch Division of Systems Safety

Ashok C. Thadani, Director and Analysis, NRR Division of Systems Safety i

and Analysis LeMoine J. Cunningham, Chief

' Office of Nuclear Reactor Regulation Radiation Protection Branch Division of Radiation Safety l Frank J. Congel, Director and Safeguards, NRR

' Division of Radiation Safety-and Safeguards

-Gary G. Zech, Chief Dffice of Nuclear Reactor Regulation Performance and Quality Evaluation Branch Division of Reactor Inspection

, Charles E. Rossi, Director and Licensee Performance, NRR l Division of Reactor Inspection and Licensee Performance William D. Beckner, Chief l Office of Nuclear Reactor Regulation Probabilistic Safety Assessment Branch l

Division of Systems Safety Bruce A. Boger, Director and Analysis, NRR-l Division of Reactor Controls aad Human Factors Office of Nuclear Reactor Regulation l

lWarrenH.Swenson,ActingChief

! Human factors Assessment Branch Division of Reactor Controls

and Human facters, NRR Gout _am Bagchi, Chief Civil Engineering and Geosciences Branch

' Division of Engineering, NRR Richard J. Barrett, Chief Containment Systems and Severe Accident Branch Division of Systems Safety and Analysis, NRR

-Jared S. Wermiel, Chief Instrumentation and Controls Branch Division of Reactor Controls and Human factors, NRR Carl H. Berlinger, Chief Electrical Engineering Branch Division of Engineering, NRR

,.v-,

,y,

5/12/93 VENDOR SUBMITTAL SCHEDULE FOR ITAAC l

PROJECTED SUEMITTAL DATES QESIGN APRIL MAY JUNE JULY GE AGWR ITAAC 23 Templates 4/27 (23) 86 Partial 5/21 (37) 6/4 (30) 6/18 P4) 209 Full set (certified) 7/31 CE System 80+ ITAAC 11 Prototypes 4/30 (11) 69 Partial 4/30 (14) 5/28 (24) 6/18 (20) 80 full set (certified) 7/31 Westinghouse AP600 ITAAC 40 Application (12/92) Complete 40 Partial X

40 full set (certified)

X GE'SBWR ITAAC 50 Application (3/93) Complete

ALWR REVIEW SCHEDULES EPRI Passive GE ABWR CE System 80+

W AP600 GE SBWR SECY-l SECY-SECY-l SECY-l SECY-l Milestone 91-161 ; Revised 91-161 ; Revised 91-161 l Revised 91-161 ; Revised 91-161 : Revised _

Receipt of Appl.

9/90 l

9/90C 3/89 3/89C 4/91 4/91C 6/92

! 12/92C 8/92 f

3/93 RAIs to PM 6/91 l10/91C 12/90 l12/90C 10/91 10/91C 10/92

!!.6/93i 12/92 10/93 I

I RAIs Issued to l

l 12/90C 10/91

! 10/91C 10/92

!i'6/93 12/92

? 10/93 Applicant 6/91

' 10/91C 12/90 Policy Paper to Comission/ACRS 9/91 6/93 3/91 4/93C 3/91 4/93C 9/92 "6/93-11/92 6/93

';,9/93>

4/93

!.* -1/94 a Applicant Responds to RAIs 10/91 l

1/92C 7/91

!. 10/91C 2/92 2/92C 2/93 i

8/93

!~~6/94 $

DSER to PM 2/92 3/92C 8/91

! 10/91C 6/92 9/92C 6/93 2/94 fi9/94-f?45/9'44 f

9/92C f10/91C f4/92C 11/93 8/93 8/92 9/91 DSER to Com/ACRS 4/92 DFSER to Com/ACRS*

! 10/92C i

i i

Lw-i..

Applicant Responds lL.

E~.%

! t.

7/93(

1/94 l412/941 3/94 j,J3/95W to DSER (DFSER -

9/92 l

9/92C 2/92 ji; 7/93i 1/93 p

C ABWR only) fn FSER to PM 4/93 iL4/93 6/92 l-9/93' 5/93 fl11/932 5/94 fi4/95 8/94 fL'7/95 0 I

8/94 f O/953 10/94

!h10/95J FSER to Com/ACRS 6/93 fi7/93 8/92 f ~ -' 12/93 : 7/93 f;?2/94 FSER Issued for h!

h.

h ^....

I; T9 b

"U e

Publication 9/93

~ 11/93-12/92 t' 2-'3/94 :

11/93

!b 6/941 11/94 F>11/954 1/95 t' '3/962 h'5/96' b'

FDA/FR Notice l

12/92

- 5/94' 11/93 8/94 11/94 i01/96 1/95 Issued

.~

Rule /FR Notice l

l' D

2/961 I: 6/96~

Issued" l

l-6/94 l

9/94 Interim step for ABVR review only - this step not included in the SECY-91-161 schedule assumptions.

~

This step not included in the SECY-91-161 schedule assumptions.

Shaded dates - milestones to be completed

l I

TASK GROUPS:

l Structural Systems (DE/ECGB - G. Bagchi/D. Terao) l e

Plant Systems (DSSA/SPLB - C. McCracken/J. Lyons)

Reactor Systems (DSSA/SRXB - R. Jones /M. Rubin) e Electrical Systems (DE/EELB - C. Berlinger/D. Thatcher) e Human Factors Systems (DRCH/HHFB - W. Swenson/D. Eckenrode) e I & C Systems (DRCH/HICB - J. Wermiel/M. Chiramal) e RAD Protection Systems (DRSS/PRPB - L. Cunningham/

e J. Wigginton)

TASK GROUP MEMBE_ SHIP:

R Task Group Manager (Branch Chief /Section Chief)

Principle Reviewer ABWR Principle Reviewer System 80+

e Secondary Reviewers (other branches) e Project Manager (continuity and vendor interface)

Specialists (selected generic areas)

AP600 & SBWR reviewers (as observers (gain insights) during e

Projects / Task Force meeting) - Generate comments /RAls and DSER input for respective designs Specialisti:

Pro.iect Managiti:

EQ:

Harold Walker ITAAC Coordinator: Tom Boyce-MOV's:

Tom Scarbrough ABWR:

Chet Poslusny ISLOCA:

George Thomas CE System 80+:

Mike Franovich Testing:

Tim Polich AP600:

Rick Hasselberg PRA:

Glenn Kelly / Robert Palla SBWR:

Helinda Malloy Sev.Acc.: John Monninger s

Part 52:

Jerry Wilson / Tom Boyce Enclosse 3

l GE NUCLEAR ENERGY ABWR TIER 1 TASK GROUP /*SSIGNMENTS l

Structural Tier i Task Group Secondary Submittal Review Reply Resolved Comments No.

Title Branches Date Date Date Date 2.1.1 Reactor Pressure Vessel System SRXB 5/21 2.6.1 Reactor Water Cicanup System SPLB 4/23 2.8.4 Loose Parts Monitoring SRXB 5/21 2.10.4 Condensate Purification System SPLB 5/21 2.11.1 Makeup Water (Purified) System SPLB 6/18 2.11.20 Sampling System SPLB/PRPB 6/4 2.12.10 Electrical Wiring Penetrations EELB 6/4 2.14.1 Primary Containment System SPLB/SCSB/

6/18 PRPB 2.15.10 Reactor Building PRPB/SPLB/

4/23 PSGB 2.15.11 Turbine Building PRPB/SPLB 4/23 2.15.12 Control Building SPLB/PRPB/

5/21 PSGB 2.15.13 Radwaste Building SPLB/PRPB 5/21 2.15.14 Service Building SPLB/PRPB 5/21 PEPB 3.3 Piping DAC 4/23 5

Site Parameters PRPB/SPLB 4/23 Projects APP.A legend for Figures EELB/SPLB 4/23 TOTAL COMPLETED Page 2 f i

Plant Systems Tier i Task Group Secondary Submittal Review Reply Resolved Comments No.

Title Branches Date Date Date Date 2.3.1 Process Radiation Monitoring System PRPil/HICB 6/4 2.4.3 Leak Detection & Isolation System HICB 4/23 2.5.5 Refueling Equipment SRXB 5/21 l

2.5.6 Fuel Storage Facility DE/SRXB 5/21 4

2.6.2 Fuel Pool Cooling & Cleanup System DE 6/4 2.6.3 Suppression Pool Cleanup System DE 6/4 2.9.1 Radwaste System PRPB 6/18 2.9.2 Radioactive Drain Transfer System PRPB 6/18 2.10.1 Turbine Main Steam System DE/PRPB 4/23 2.10.2 Condensate Feedwater & Condensate DE 5/21 Air Extraction System 2.10.7 Main Turbine DE 5/21 l

2.10.9 Turbine Gland Steam System 5/21 5/21 2.10.13 Turbine Bypass 2.10.16 Generator 5/21 2.10.21 Main Condensor DE 4/23 i

2.10.22 Off-Gas System PRPB 6/4 2.10.23 Circulating Water System 5/21 2.11.2 Makeup Water (Condensate) System 6/18 2.11.3 Reactor Building Cooling System 4/23 Page 3

2 11.4 Turbine Building Cooling Water 6/4 0

System i

2.11.5 IIVAC Normal Cooling Water System 6/18 2.11.6 HVAC. Emergency Cooling Water 6/18 System-2.11.8 Ultimate Heat Sink DE 5/21 2.11.9 Reactor Service Water System DE 4/23 2.11.10 Turbine Service Water System 6/4 2.11.11 Station Service Air System DE 5/21 2.11.12 Instrument Air System DE 5/21 2.11.13 High Pressure Nitrogen Gas Supply DE 5/21 System 2.14.4 Standby Gas Treatment System PRPB 6/4 2.14.6 Atmospheric Control System 5/21 2.14.7 Drywell Cooling System 5/21 2.14.8 Flammability Control DE/HICB 5/21 2.15.3 Cranes & Hoists DE 5/21 2.15.5a Control Building HVAC Systems DE 6/18 2.15.5b Control Room Habitability Area DE/PRPB 6/18 HVAC System 2.15.5c Reactor Building HVAC System DE/PRPB 6/18 2.15.6 Fire Protection System HICB 5/21 2.16.2 Oil Storage & Transfer System DE 6/4 4.1 Ultimate Heat Sink DE/

6/4 Projects 4.3 Potable & Sanitary Water System 6/18 Page 4 i

i

4.4 Turbine Service Water System Projects 6/4 4.5 Reactor Service Water Interface Projects 4/23 r

4.6 Makeup Water Preparation System Projects 6/18 r-TOTAL COMPLETED s

s D

i Page5 r

.. ~..

m

.m.

Reactor Systems Tier 1 Task Group B

Secondary Submittal Review Reply Resolved Comments No.

Title Branches Date Date Date Date 2.1.2 Nuclear Boiler System DFlSPLB 4/23 2.1.3 Reactor Recirculation System DE 5/21 2.2.2 Control Rod Drive System DE 5/21 2.2.4 Standby Liquid Control System HICB 4/23 2.4.1 Residual Heat Removal System DE/HICB 4/23 2.4.2 High Pressure Core Flooder System DE/HICB 6/4 2.4.4 Reactor Core Isolation Cooling System DE/HICB 5/21 2.8.1 Nuclear Fuel 5/21 2.8.2 Fuel Channel 5/21 l

2.8.3 Control Blade 5/21 I

TOTAL COMPLETED t

(

i Page @

Electrical Systems Tier i Task Group l

Secondary Submit i Review Reply Resolved Comments No.

Title Branches Date Date Date Date 2.12.1 Electrical Power Distribution System 4/23 2.12.11 Combustion Turbine Generagor SPLB 6/4 6/4 2.12.12 DC Power Supply 2.12.13 Emergency Diesel Generator System SPLB 5/21 2.12.14 Vital AC Power Supply & AC Instru-HICB 6/4 ment & Control Power Supply Sys-tems 2.12.15 Instrument & Control Power Supply HICB TBD 2.12.17 Lighting & Service HHFB 6/4

~

4.2 Offsite Power Interface Projects 4/23 TOTAL COMPLETED O

t 1

4 Page

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Instrumentauon & tontros systems s ier a n asA vioup Secondary Submittal Review Reply Resolved Comments No.

Title liranches Date Date Date Date 2.2.1 Rod Control & Information System SRXB 6/4 2.2.3 Feedwater Control System SRXB 4/23 2.2.5 Neutron Monitoring SRXB 5/21 2.2.6 Remote Shutdown System SRXB 6/4 l 4/23 2.2.7 Reactor Protection System SRXB 2.2.8 Recirculation Flow Control System SRXB 6/4 2.2.9 Automatic Power Regulatory System SRXB 6/4 2.2.10 Steam Bypass & Pressure Control SRXB/

6/4 SPLB 2.2.I1 Process Computer System 6/4 2.7.1 Main Control Room Panel DE/EELB/

6/4 HHFB 2.7.3 Local Control Panels DE/EELB 6/4 2.7.5 Multiplexing System 6/4 2.12.16 Communication System EELB 6/4 2.14.9 Suppression Pool Temperature Moni-6/18 toring System 3.4 Safety System Ixgie & Control 5/21 3.4(i)

ISP and I&C EQ 4/23 3.4(ii)

Portions of T&C.'DAC 4/23 4.7 Communication System Projects 6/4 TOTAL COMPLETED Page 9

Radiation Protection Tier i Task Group No.

Title.,

Secondary Submittal Review Reply Resolved Comments Branches Date Date Date Date 2.3.2 Area Radiation Monitoring System 5/21 2.3.3 Containment Atmospheric Monitoring 5/21 System 3.7 Radiation Protection DAC lTBD TOTAL COMPLETED 9

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l ABB-CE SYSTEM 80+

TIER 1 TASK GROUP ASSIGNMENTS l

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Structural Tier i Task Group Secondary Submittal Review Reply Resolved Comments No.

Title Branches Date Date Date Date 1.3 Site Parameters PRPB/SPLB/

6/18 Projects 1.4 Figure Legend EELB/SPLB 4/30 2.1.1 Nuclear Island Structures SCSB/PEPB/

4/30 SPLB/PRPB 2.1.2 Turbine Building SPLB/PRAB 4/30 2.1.3 Component Cooling Water 4/30 Heat Exchanger Structure 2.1.4 Diesel Fuel Storage Structure SPLB 4/30 2.1.5 Radioactive Waste Building PRPB 4/30 2.1.6 Reactor Vessel Internals SRXB 4/30 2.1.7 In-core Instrument Guide SRXB 5/27 Tubes 2.2.4 Control Element Drive SRXB 4/30 Mechanism.

l 2.3.3 Component Supports 5/27 2.7.7 Demineralized Water Makeup SPLB 5/27 Systems 2.7.16 Chemical & Volume Control SRXB/SPLB 5/27 System 2.8.7 Steam Generator Blowdown SRXB 6/18 System 3.1 Piping Design (DAC) 6/18 l

TOTAL COMPLETED Page5

Plant Systems Tier 1 Task Group l

Secondary Submittal Review Reply Resolved Comments No.

Title Branches Date Date Date Date 2.4.2 Annulus Ventilation System 5/27 2.4.3 Combustible Gas Control in 5/27 Containment 2.4.5 Containment isolation DE 5/27 2.4.6 Containment Spray 5/27 2.7.1 New Fuel Storage Racks SRXB/DE 4/30 2.7.2 Spent Fuel Storage Racks SRXB/DE 4/30 2.7.3 Pool Cooling and Purification SRXB 4/30 System 2.7.4 Fuel Handling System DE 5/27 2.7.5 Station Service Water System 4/30 2.7.6 Component Cooling Water SRXB 4/30 System 2.7.8 Condensate Storage System 4/30 2.7.9 Process Sampling Syst'em SRXB 6/18 2.7.10 Instrument Air System 4/30 2.7.11 Turbine Building Cooling 4/30 Water System 2.7.12 Essential Chilled Water Sys-5/27 tem 2.7.13 Normal Chilled Water System 5/27 2.7.14 Turbine Building Service 4/30 Water System Page 9

2.7.15 Equipment & Floor Drainage' 5/27 System 2.7.17 Control Building Ventilation PRFB 5/27 System 2.7.18 Fuel Building Ventilation PRPB 5/27 System 2.7.19 Diesel Building Ventilation 5/27 System 2.7.20 Subsphere Building 5/27 Ventilation System 2.7.21 Containment Purge Ventila-SCSB/PRPB 5/27 tion System 2.7.22 Containment Cooling &

5/27 Ventilation System 2.7.23 Nuclear Annex Ventilation 5/27 System 2.7.24 Fire Protection System 6/18 2.7.27 Compressed Gas Systems 4/30 2.7.28 Potable & Sanitary Water 4/30 System 2.7.29 Radwaste Building Ventilation PRPB 6/18 System 2.8.1 Turbine Generator EELB/DE 5/27 2.8.2 Main Steam Supply System 5/27

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2.8.3 Main Condenser 5/27 2.8.4 Main Condenser Evacuation 5/27 System 2.8.5 Turbine Bypass System 5/27 Page 4

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Reactor Systems Tier i Task Group

-i 7

Secondary Submittal Review Reply Resolved Comments No.

Title Branches Date Date Date Date 2.2.1 Nuclear Design 6/18 6/18 2.2.2 Fuct Systems 2.2.3 Thermal and Hydraulic De-6/18 sign 2.3.1 Reactor Coolant System DE 5/27 2.3.2 Shutdown Cooling System DE/SPLB 5/27 2.4.1 Safety Depressurization Sys-SPLB/HICB 5/27 tem 2.4.4 Safety injection System HICB 5/27 TOTAL COMPLETED j

4 9

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iluman Factors Tier 1 Task Group Secondary Submittal Review Reply Resolved Comments No.

Title Branches Date Date Date Date 2.10 Technical Support Center PEPB 5/27 2.12.1 Main Control Room 4/30 2.12.2 Remote Shutdown Room HICB/SRXB 4/30 2.12.3 Control Pancis HICB 4/30 TOTAL COMPLETED 0

1 L

Page 8

Instrumentation & Control Systems Tier i Task Group Secondary Submittal Review Reply Resolved Comments No.

Title Branches Date Date Date Date 2.5.1 Plant Protection System 5/27 2.5.2 Engineered Safety Features-5/27 Component Control System 6/18 2.5.3 Safety Related Display Instru-mentation 2.5.4 Protection System Interfaces 6/18 to Non-Safety Systems 2.7.25 Communication System 6/18 TOTAL COMPLETED l

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Radiation Protection Tier i Task Group Secondary Submittal Review Reply Resolved Comments No.

Title Branches Date Date Date Date 2.9.1 Condensate & Feedwater SPLB 6/18 System 2.9.2 Gaseous Waste Management SPLB 6/18 System 2.9.3 Solid Waste Management SPLB 6/18 System 2.9.4 Process & Effluent SPLB 6/18 Radiological Monitoring &

Samplying System 3.2 Radiation Protection (DAC)

ECGB 6/18 TOTAL COMPLETED b

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$_ ample Format for Task Group Proar_ess Reporti a

(Use separate reports for GE ABWR and CE System 80+)

June 15, 1993 FROM:

Conrad McCracken, Plant Systems Task Group Leader TO:

R. W. Borchardt, Acting Director, PDST

SUBJECT:

PLA. SYSTEMS ITAAC TASK GROUP PROGRESS REPORT FOR JUNE'1993 -

E ABWR CE SYSTEM 80+

Number of ITAAC.

l ASSIGNED:

9 itECEIVED:

2 REVIEWED:

2 REPLIED:

O RESOLVED:

O Comments /Sionificant Unresolved Issues:

0ffCIff 90VJfX INnO?f4C JfMG-lN'7%Thh'f A2FGn f0R GC>

Q ELthf tLIT Y l

I cc:

Section Chief T. Boyce, 11-H-3 C. Poslusny (GE), 11-H-3 H. Franovich (CE), 11-H-3 7

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e Electrical Systen;s Tier 1 Task Group Secondary Submittal Review Reply Resolved Comments No.

Title Branches Date Date Date Date 2.12.1 Electrical Power Distribution System 4/23 c-f[V d.

6[JP P ff func.Vl_I5r' /Trfng l 6/4 f

(,[2f f 2.12.11 Combustion Turbine Generator SPLB 2.12.12 DC Power Supply 6/4 6'

(,[25 f 2.12.13 Emergency Diesel Generator System SPLB 5/21 f (o[t/ lc 2.12.14 Vital AC Power Supply & AC Instru-HICB 6/4 P

(,[2rP ment & Control Power Supply Sys-tems 2.12.17 Lighting & Service HHFB 6/4 f

[o[2f f sweemr sue: marna.

4.2 Offsite Power Interface Pro.jects 4/23 C f[/4 C.

([J8 (#

Ramr are sa:D entrasu_erY TOTAL COMPLETED c2 c2 O

O 4

TOTAL ASSIGNED:

Y INSTRUCTIONS:

P - means planned C - means completed C - In review date -is the date ofletter sent by projects to vendor

?

C - In resolved date - is the date of letter sent by vendor responding to comments

-