ML20210A802

Summary of 860828 Meeting W/Util & S&W in Bethesda,Md to Discuss Facility FSAR Updates for S&W Piping Requalification Program.List of Attendees & Viewgraphs Encl.Transcript Also Encl

ML20210A802
Person / Time
Site:	Comanche Peak
Issue date:	09/09/1986
From:	Trammell C Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20210A807	List: ML20210A802 ML20210A814
References
NUDOCS 8609170345
Download: ML20210A802 (23)

Text

- ,

0 9 SEP 1986 Docket Nos'.: 50-445 and 50-446 FACILITY: Comanche Peak Steam Electric Station, Units 1 and 2 APPLICANT: Texas Utilities Electric Company et al.

SUMMARY

OF MEETING PELD ON AUGUST 28, 1986 TO DISCUSS COMANCPE PEAK FSAR UPDATES FOR STONE & WEBSTER PIPING REQUAI.IFICATION PROGRAM On August 28, 1986, the NRC staff and consultants met with Texas Utilitios personnel to discuss proposed FSAR revisions resulting from the Stone &

Webster piping requalification program. Persons attending the meeting are identified in Attachment 1. Viewgraphs used for the presentation are attached as Attachment 2 and serve as a concise summary of the highlights of the meeting. The meeting was also transcribed (Attachment 3).

The changes to the FSAR would assure that it accurately reflects the Stone &

Webster design methodology, and would update the FSAR for the piping system requalification program to meet the intent of NRC Standard Review Plan. More details are presented in the viewgraphs.

TUGC0 will submit a formal proposed FSAR change for staff review by September 12, 1986, and requested that staff review be completed as soon as possible since staff acceptance would be a critical path item for Unit 1 pipe design.

Charles M. Trammell, Project Manager PWR Project Directorate No. 5 Division of PWR I.icensing-A

^

Attachments: Distribution:

1.. Attendees ' Docket Files ? NRC PDR

2. Viewgraphs PD#5 Rdg. Files Local PDR

3. Transcript C. J. Partlow M, Irammell Rushbrook E. Jordan Cc: See.neXt page V . # oonaN 3. Grimes A .Va<fk ,6 ok Acks (10)

WRC. PGtrNC@On/ 80. Novak Servu& LM

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+ f UNITED STATES

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, f,. g NUCLEAR REGULATORY COMMISSION 5 'O j W ASHINGTON, D. C. 20555

%,...../ 0 9 SEP 1996 Docket Nos.: 50-445 and 50-446 FACILITY: Comanche Peak Steam Electric Station, Units I and 2 APPL.ICANT: Texas Utilities Electric Company et al.

SUMMARY

OF MEETING PELD ON AUGUST 28, 1986 TO DISCUSS COMANCHE PEAK FSAR UPDATES FOR STONE & WEBSTER PIPING REQUALIFICATION PROGRAM On August 28, 19P6, the NRC staff and consultants met with Texas Utilities personnel to discuss proposed FSAR revisions resulting from the Stone &

Webster piping requalification program. Persons attending the meeting are identified in Attachment 1. Viewgraphs used for the presentation are attached as Attachment 2 and serve as a concise summary of the highlights of the meeting. The meeting was also transcribed (Attachment 3).

The changes to the FSAR would assure that it accurately reflects the Stone &

Webster design methodology, and would update the FSAR for the piping system requalification progran to meet the intent of NRC Standand Review Plan. More details are presented in the viewgraphs. ,

TUGC0 will submit a formal proposed FSAR change for staff review by September 12, 1986, and requested that staff review be completed as soon as possible since staff acceptance would be a critical path item for Unit 1 pipe design.

/W / th Charles M. Trammell, Pro.iect Manager PWR Pro. ject Directorate No. 5 l Division of PWR I.icensing-A l

Attachments:

1. Attendees

2. Viewgraphs i 3. Transcript l

cc

See next page i

- , , , , , - - - - ,--,7--~-e p

i W. G. Counsil Comanche Peak Steam Electric Station Texas Utilities Generating Company Units 1 and 2 cc:

Nicholas S. Reynolds, Esq. Resident Inspector / Comanche Peak Bishop, Liberman, Cook, Steam Electric Station Purcell & Reynolds c/o U.S. Nuclear Regulatory Commission 1200 Seventeenth Street, NW P. O. Box 38 Washington, D.C. 20036 Glen Rose, Texas 76043 Robert A. Wooldridge, Esq. Regional Administrator, Region IV Worsham, Forsythe, Sampels & U.S. Nuclear Regulatory Commission Wooldridge 611 Ryan Plaza Drive, Suite 1000 2001 Bryan Tower, Suite 2500 Arlington, Texas 76011 Dallas, Texas 75201 t.anny A. Sinkin Mr. Homer C. Schmidt Christic Institute Manager - Nuclear Services 1324 North Capitol Street Texas Utilities Generating Company Washington, D.C. 20002 Skyway Tower 400 North Olive Street, L.B. 81 Ms. Billie Pirner Garde Dallas, Texas 75201 Citizens Clinic Director Government Accountability Project Mr. Robert E. Ballard, Jr. 1555 Connecticut Avenue, N.W.

Director of Projects Suite 202 Gibbs and Hill, Inc. Washington, D.C. 20009 11 Pen Plaza New York, New York 10001 David R. Pigott, Esq.

Orrick, Herrington & Sutcliffe 600 Montgomery Street Mr. R. S. Howard San Francisco, California 94111 Westinghouse Electric Corporation P. O. Box 355 Anthony Z. Roisman, Esq.

Pittsburgh, Pennsylvania 15230 Trial t.awyers for Public Justice 2000 P. Street, NW Renea Hicks, Esq. Suite 611 Assistant Attorney General Washington, D.C. 20036 Environmental Protection Division P. O. Box 12548, Capitol Station Nancy E. Wiegers Austin, Texas 78711 Spiegel & McDiarmed 1350 New York Avenue, NW Mrs. Juanita Ellis, President Washington, D.C. 20005-4798 Citizens Association for Sound Energy 1426 South Polk Roy P. l.essy, Jr.

Dallas, Texas 75224 Wright & Talisman, P. C.

1050 Seventeenth Street, NW Ms. Nancy H. Williams Suite 600 CYGNA Washington, D.C. 20036-5566 101 California Street San Francisco, California 94111

Texas Utilities Electric Company Comanche Peak Electric Station <

Units 1 and 2 cc:

Resident Inspector - Comanche Peak

. c/o U.S. Nuclear Regulatory Commission ,

P. O. Box 1029 .

Granbury, Texas 76048 J

Mr.. John W. Beck Vice President 1 Texas Utilities Generating Company -

Skyway Tower 400 N. Olive Street, LB#81 ,

Dallas, Texas 75201 a

2 Mr. Jack Redding Licensing i Texas Utilities Generating Company l 4901 Fairmont Avenue l Bethesda, Maryland 20814 William A. Burchette, Esq. ,

Counsel for Tex-1.a Electric Cooperative -

of Texas

Feron, Burchette, Ruckert & Rothwell -

2 Suite 700 1025 Thomas Jefferson Street, NW '

! Washington, D.C. 20307 .

. GDS Associates, Inc. .

l 2525 Cumberland Parkway l Suite 45C

)

Atlanta, Georgia 30339 Administrative Judge Peter Bloch ,

U.S. Nuclear Regulatory Ccmmission 5 Washington, D.C. 20555 ,

i Elizabeth B. Johnson Administrative Judge Oak Ridge National laboratcry P. O. Box X, Building 3500 Oak Ridge Tennessee 37830 0 . Kenneth A. McCollom

, 1107 West Knapp p Stillwater, Oklahoma 74075 ,

Dr. Walter H. Jordan '

881 Outer Drive '

Oak Ridge, Tennessee 37830

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l AGENDA l .

l l

TUGCO PRESENTATION TO THE NRC -

AUGUST 28,1986 l

l A. INTRODUCTION L.D. NACE, TUGCO  :

B. SWEC OVERVIEW E.J. SISKIN, SWEC C. SWEC PRESENTATION R,P. KLAUSE, SWEC

1. FSAR UPDATES FOR PIPING REQUALIFICATION PROGRAM ll. ASME CODE EDITIONS, ADDENDA, AND CODE b CASES USED FOR THE PIPING REQUALIFICATION [I PROGRAM - ,,,, 'LIp

~

l ~!

l i .

SWEC PRESENTATION l 1 i

l

! l. FSAR UPDATES FOR PIPING REQUALIFICATION PROGRAM II. ASME CODE EDITIONS, ADDENDA, AND CODE CASES USED FOR THE PIPING REQUALIFICATION PROGRAM _ .. ....

l 1

l. UPDATING COMANCHE PEAK (CPSES)  ;

i UNITS 1 AND 2 FSAR

! PIPING SYSTEM REQUALIFICATION

! PROGRAM l

! OBJECTIVES:

• TO ASSURE FSAR ACCURATELY REFLECTS THE SWEC DESIGN METHODOLOGY l e TO INCLUDE THE SWEC COMPUTER PROGRAMS USED 1

FOR PIPING SYSTEM REQUALIFICATION PROGRAM IN THE FSAR e TO UPDATE THE FSAR FOR THE PIPING SYSTEM REQUALIFICATION PROGRAM TO MEET THE INTENT OF USNRC STANDARD REVIEW PLAN NUREG-0800. C H86 1136

., , . - _ - . n- . . . , . - . , _ . . . _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _

i

! TOPICS INCLUDED IN THE UPDATE ,

CURRENT

! SWEC REGULATORY CLARIFICATION TOPICS METHODOLOGY POSITIONS OR ADDITION

1. COMPUTER PROGRAMS X t

2. SSE LOADING IN EMERGENCY X X .

PLANT CONDITION

3. SEISMIC RESPONSE IN ZPA X X

! REGION

! 4. COMBINATION OF PEAK X X I DYNAMIC RESPONSES

! 5. PLASTIC ANALYSIS X X I 6. FUNCTIONAL CAPABILITY X X '

i 7. SPECTRAL BROADENING & X DAMPING VALUES

8. STRESS CYCLES X X

9. MISCELLANEOUS UPDATES X X

10. ASME CODE OF RECORD X

1 i 1. COMPUTER PROGRAMS UTILIZED PROPOSED CHANGE:

TO SPECIFY IN THE FSAR THOSE COMPUTER PROGRAMS WITH THEIR

VERIFICATION THAT ARE UTILIZED BY SWEC IN THE PIPING SYSTEM l REQUALIFICATION PROGRAM.

l

REASON FOR CHANGE

UPDATE THE LIST OF COMPUTER PROGRAMS USED FOR ANALYSIS OF i

PIPING SYSTEMS. ,

l

! BASIS FOR CHANGE:

! TO CONFORM TO GUIDANCE IN NUREG-0800, SECTION 3.9.1, SUBSECTION 11.2.

APPLICATIONS:

I ASME CODE CLASS 2 AND 3 PIPING SYSTEMS INCLUDING SUPPORTS FOR ASME CODE CLASS 1,2, AND 3 PIPING (APPENDIX 3B OF FSAR).

i

i .

! COMPUTER PROGRAMS PREVIOUSLY UTILIZED l ON OTHER DOCKETS )( = usr ov oo ccer (m@

l e -- V5tp Bar 867 RQP P EE RIVER NINE MILE BEAVER MILLSTONE COMPUTER PROGRAM BEND 2 VALLEY 2 3 SHOREHAM

NUPIPE-SW X X X X X

BAP X X e j BSPLT

• e i

STARDYNE X X e X e PITRUST X X X X X PlLUG X X X X X

! PITRIFE *

• X X X l STEHAM X X X X X -

i WATHAM X X X X X l WATSLUG X X ELBOW X e

! PSPECTRA X X X X STRUDL-SW X X X X X STRUDAT AND SANDUL e e l BASEPLATE-Il e o X e e BIP X

• APE X *

CHPLOT *

• X X

• RELAP e e o e e t

l DLL QMutfts 8Y S W "'

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2. SSE LOADING COMBINATIONS PROPOSED CHANGE:

DELETE SSE FROM LOADING COMBINATIONS IN EMERGENCY PLANT CONDITIONS (SERVICE LEVEL C).

REASONS FOR CHANGE: -

e TO CONFORM WITH TABLE 1, APPENDIX A, NUREG-0800,(JULY,1981)

{

• TO BE CONSISTENT WITH NSSS (CLASS 1) LOADING COMBINATIONS l e TO BE CONSISTENT WITH SWEC METHODOLOGY ON MORE THAN 8 OTHER DOCKETS

{

l BASIS FOR CHANGE:

i PRESENT VERSION OF FSAR CONSIDERED SSE IN PLANT EMERGENCY l CONDITION FOR BOP SYSTEMS. IT WAS BASED UPON REGULATORY.

l ' GUIDE 1.48 (MAY,1973) POSITION FOR CLASS 2 AND 3 PIPING.

! NUREG-0800, SECTION 3.9.3, APPENDIX A, SUBSECTION 4.2 STATED " APPENDIX A REQUIREMENTS SUPERSEDE THOSE IN THE

MAY 1973 VERSION OF REGULATORY GUIDE 1.48".

! APLICATIONS:

4 ASME SECTION 111 CLASS 2 AND 3 PIPING SYSTEMS AND CLASS 1, l 2, AND 3 PIPE SUPPORTS (SECTION 3.98.1.1, 3.9B.3.1, TABLES i

3.98-1B AND 3.9B-1C OF FSAR). CH86 0170-e

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3. SEISMIC RESPONSE IN ZPA REGION PROPOSED CHANGE:

ADD THE METHOD IN NUREG/CR-1161 (DECEMBER,1979) TO RESPONSE SPECTRUM ANALYSIS OF PIPING SYSTEMS TO ADDRESS HIGH FREQUENCY SEISMIC RESPONSES IN THE ZERO PERIOD ACCELERATION (ZPA) REGION OF THE SPECTRA (ARS).

REASON FOR C'dANGE:

• THE EXISTING FSAR IS SILENT ON THIS ISSOE.

BASIS FOR CHANGF_:

i e TO ASSURE PARTICIPATION OF ALL SIGNIFICANT MODES IN -

RESPONSE SPECTRUM ANALYSIS OF PIPING SYSTEMS.

APPLICATIONS:

ASME CODE CLASS 2 AND 3 PIPING SYSTEMS,(SECTION 3.78.3.1 OF FSAR). ,,,,,,,

4. COMBINATION OF PEAK DYNAMIC RESPONSES I PROPOSED CHANGE:

PEAK DYNAMIC RESPONSES OF PIPING SYSTEMS DUE TO SEISMIC, LOCA, AND/OR OCCASIONAL LOADS ARE COMBINED BY THE SQUARE ROOT OF THE SUM OF SQUARES (SRSS) TECHNIQUE.

REASONS FOR CHANGE:

e UPDATE TO BE CONSISTENT WITH SWEC METHODOLOGY ON MORE THAN 8 OTHER DOCKETS

! e MINIMlZE PLANT MAINTENANCE THEREBY REDUCING PERSONNEL EXPOSURES (ALARA) e TO BE CONSISTENT WITH NSSS (CLASS 1) METHODOLOGY BASIS FOR CHANGE:

e SRSS COMBINATION OF SSE AND LOCA RESPONSES IS IN CONFORMANCE WITH NUREG-0484 (MAY 1980).

e SRSS PROCEDURE OF COMBINING WATER HAMMER EVENTS i

(OCCASIONAL LOADS) WITH EARTHQUAKES AND PLANT i

DYNAMIC EVENTS IS AN ACCEPTABLE METHOD IN NUREG-1061 (VOLUME 4, JANUARY 1985).

l APPLICATIONS:

i ASME CODE CLASS 2 AND 3 PIPING SYSTEMS AND CLASS 1,2, AND 3 PIPE SUPPORTS (SECTION 3.98.3.1 OF FSAR). , , , , ,

5. PLASTIC ANALYSIS l PROPOSED CHANGE:

REVISE PARAGRAPH 3.9B.1.4.1 TO INCLUDE THE OPTION PERMITTED BY

! THE CODE TO USE PLASTIC ANALYSIS FOR ASME CODE CLASS 2 l AND 3 COMPONENTS.

REASON FOR CHANGE:

TO PROVIDE A BASIS FOR THE QUALIFICATION OF CLASS 2 AND 3 PIPING FOR LOCAL EFFECTS BASIS FOR CHANGE:

IT IS APPROPRIATE TO USE THE CODE CLASS 1 APPROACH IN NB-3228 TO EVALUATE THESE LOCALIZED EFFECTS.

APPLICATION:

ASME CODE CLASS 2 AND 3 PIPING SYSTEMS FOR LOCAL STRESS EVALUATION BETWEEN PIPE AND SUPPORT MEMBERS. c ...,>,

l 6. FUNCTIONAL CAPABILITY PROPOSED CHANGE:

ADD FUNCTIONAL CAPABILITY ASSURANCE REQUIREMENTS FOR l

PIPING SYSTEMS BY THE ANALYTICAL CRITERIA IN NEDO-21985 l (SEPTEMBER,1978) AND RELATED DOCUMENTS. IN ADDITION, THE STRESS LIMITS FOR ESSENTIAL SYSTEMS (FSAR TABLE 3.9B-1B) HAVE BEEN REVISED.

REASONS FOR CHANGE:

l

• TO ASSURE OPERABILITY OF ESSENTIAL PIPING SYSTEMS DURING AND AFTER A POSTULATED PLANT ACCIDENT CONDITION.

e TO CONFORM WITH THE REGULATORY POSITION C.2.3 IN APPENDIX-A, SECTION 3.9.3, OF NUREG-0800 (APRIL,1984).

l l BASIS FOR CHANGE:

! THE PROPOSED ANALYTICAL CRITERIA TO ASSURE THE FUNCTIONAL CAPABILITY REQUIREMENTS MEET THE OBJECTIVES OF NUREG-0800.

APPLICATIONS

ASME CLASS 2 AND 3 PIPING SYSTEMS TO BE OPERATIONAL DURING j

AND AFTER A POSTULATED PLANT ACCIDENT CONDITION (SECTION 3.98.3.1.2 OF FSAR). ,,,,,,,

I

7. SPECTRAL BROADENING (CC-N-397)

AND DAMPING VALUES (CC-N-411)

PROPOSED CHANGE:

APPLY ALTERNATIVE RULES TO THE SPECTRAL BROADENING AND DAMPlNG VALUES IN ASME CODE CASES N-397 AND N-411 RESPECTIVELY.

REASON FOR CHANGE:

UPDATE TO INCLUDE APPROVED ALTERNATIVE RULES.

BASIS FOR CHANGE:

e NRC LETTER FROM V.S. NOONAN TO W.G. COUNSIL, DATED MARCH 13,1986.

e TUGCO LETTER FOR W.G. COUNSIL TO V.S. NOONAN, DATED NOVEMBER 18,1985.

e HIGHLY RESEARCHED APPROACH UTILIZED ON MORE THAN 20 PLANTS APPLICATIONS:

e ASME CODE CLASS 2 AND 3 PIPING SYSTEMS ANALYZED BY RESPONSE SPECTRUM METHODS. c ...,,,,

_____u ____.___ -__m

l

8. STRESS CYCLES FOR SEISMIC EVENT l PROPOSED CHANGE:

SPECIFY A MINIMUM OF 50 MAXIMUM AMPLITUDE LOADING CYCLES FOR THE FIVE OBE EVENTS AND 10 MAXIMUM AMPLITUDE LOADING CYCLES FOR THE SSE EVENT.

l REASON FOR CHANGE:

! TO BE CONSISTENT WITH SWEC METHODOLOGY ON OTHER DOCKETS l AND TO CONFORM WITH CURRENT REGULATORY ACCEPTANCE CRITERIA.

l BASIS FOR CHANGE:

NUREG-0800, SECTION 3.7.3, SUBSECTION ll.2.B: AND SECTION 3.9.2, SUBSECTION ll.2.B.

1 APPLICATION:

ASME CODE CLASS 2 AND 3 PIPING SYSTEMS COMPONENTS (SECTION 3.7B.3.2 OF FSAR). ,,,,,,,

i i

l 9. OTHER FSAR UPDATES

, PROPOSED CHANGES:

i

! e UPGRADE VALVE MODELING TECHNIQUE IN SECTION 3.7B.11.

e ADD CONTAINMENT DISPLACEMENT LOAD COMBINATIONS IN TABLES 3.9B-18,3.9B-1C, AND 3.9B-1E.

e ADD THERMAL AND SEISMIC ANCHOR DISPLACEMENT LOADING COMBINATIONS FOR SYSTEMS WHOSE NORMAL OPERATION IS i REQUIRED IN FAULTED CONDITION, TABLE 3.9B-1B.

e ADD STRESS LIMITS FOR SUPPORTS FOR SYSTEMS WHOSE NORMAL OPERATION IS REQUIRED IN FAULTED CONDITION, TABLE 3.98-1E.

e UPGRADE THE FLUID TRANSIENT ANALYSIS METHODS FOR PRESSURE j RELIEVlNG DEVICES IN SECTION 3.98.3.3, IN CONFORMANCE WITH APPENDIX 0 OF ASME SECTION lil CODE.

REASON FOR CHANGES:

UPGRADE THESE SECTIONS OF FSAR TO REFLECT SWEC DESIGN CRITERIA OF PIPING SYSTEM REQUALIFICATION PROGRAM.

I

! BASIS FOR CHANGES:

) THESE CHANGES ARE ADDITIONS OR UPGRADES OF THE DESIGN

! PROCEDURES FOR COMPLETENESS AND TO BE CONSISTENT WITH THE

)

i INTENT OF NUREG-0800.

l APPLICATIONS:

ASME CODE CLASS 2 AND 3 PIPING SYSTEMS AND CLASS 1,2, AND 3 PIPE SUPPORTS.

I

10. ASME CODE OF RECORD PROPOSED CHANGE: '

TO STATE THAT ASME SECTION 111,1974 EDITION INCLUDING SUMMER 1974 ADDENDA SUBSECTIONS NC, ND, AND 1974 EDITION INCLUDING WINTER 1974 ADDENDA SUBSECTION NF IS THE ASME CODE EDITION OF RECORD.

l REASON FOR CHANGE:

TO CLARIFY THE CODE OF RECORD.

BASIS FOR CHANGE:

NOT APPLICABLE APPLICATIONS:

ASME CODE CLASS 2 AND 3 PIPING SYSTEMS AND CLASS 1,2, AND 3 PIPE SUPPORTS. ..,,,,

i  :

l l ASME CODE EDITION PARAGRAPHS AND CODE CASES l

e AS PERMITTED BY PARAGRAPH NA-1140 OF THE 1974 EDITION OF THE CODE, SPECIFIC PARAGRAPHS IN MORE RECENT EDITIONS AND ADDENDA OF THE ,

ASME CODE HAVE BEEN INVOKED. THESE ARE SHOWN IN ATTACHMENT 1.

• ASME CODE CASES UTILIZED ARE SHOWN IN '

j ATTACHMENT 2. . .......

j ATTACHMENT 1 l' ASME BOILER AND PRESSURE VESSEL CODE, SECTION 111, DIVISION 1 NUCLEAR POWER PLANT COMPONENTS:

1974 EDITION - SUMMER 1974 ADDENDA SUBSECTION NB - FOR EVALUATION OF NOZZLE STIFFNESS, QUALIFICATION OF ELBOWS WITH BRANCH CONNECTIONS, AND FUNCTIONAL CAPABILITY.

1974 EDITION - WINTER 1976 ADDENDA PARAGRAPH NC-3113 - SERVICE i CONDITIONS AND PARAGRAPH NC-3649-FOR EVALUATION OF FLEXIBLE

) HOSE.

1977 EDITION - WINTER 1978 ADDENDA, APPENDIX 0 - FOR EVALUATION OF SAFETY RELIEF VALVES.

l 1977 EDITION - WINTER 1978 ADDENDA, PARAGRAPHS XVil-2211 AND l NF-3226.5, NF-3321.1, AND FIGURES NF-3226.5-1 AND XVil-2211(c)-1.

1977 EDITION - WINTER 1979 ADDENDA, PARAGRAPH XVil-2454(c).

1980 EDITION, PARAGRAPHS NF-1131.6, NF-1133, AND XVil-2462.

1980 EDITION - WINTER 1982 ADDENDA, PARAGRAPHS NF-3225.1, i

NF-3225.2, NF-3324.5(A), NF-3324.6(A), AND TABLES NF-3225.2-1 AND

NF-3324.5(D)(1)-1.

l 1983 EDITION, PARAGRAPH NC-3658.3 - FOR FLANGE QUALIFICATION, PARAGRAPH NC-3673 - FOR BRANCH CONNECTION QUALIFICATION.

1983 EDITION - SUMMER 1985 ADDENDA, PARAGRAPH NF-4721 - BOLT HOLES. , , , , , ,

l

ATTACHMENT 2 LISTED IN UTILIZATION CODE REG. GUIDES REQUIRED TO BE CASES 1.84 OR 1.85 SHOWN IN FSAR N-71-9 (1644-9) YES NO N-224 YES NO N-225 YES NO '

N-247 YES NO j

N-249-3 YES NO N-253-4 (NOTE) NO -

l N-318-2 YES YES I

N-392 YES NO N-397 YES YES N-411 YES YES N-413 YES NO N-1606-1 YES NO N-1724 YES NO N-1734 YES NO NOTE: REQUEST FOR SPECIFIC NRC APPROVAL IS IN PROCESS.

.. . ..