ML20083J231

Forwards Util Which Transmitted Suppl 2 to Rept of third-party Review of Steam Generator Repair Program.Svc List Encl

ML20083J231
Person / Time
Site:	Three Mile Island
Issue date:	01/12/1984
From:	Churchill B METROPOLITAN EDISON CO., SHAW, PITTMAN, POTTS & TROWBRIDGE
To:	Hetrick D, John Lamb, Wolfe S Atomic Safety and Licensing Board Panel
References
ISSUANCES-OLA, NUDOCS 8401160256
Download: ML20083J231 (11)

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JOMN A. McCuLLouGM P.C. JE AN M. G ALLOwAY COwNSEL JUDITH A. SANDLER C. BowOOIN TRAIN J. PA'RsCR MICREY. P4 JOMN L. CARR. J R. EDWARD Q. YOUNG, Bt1 JEFF REY w. MAMPELMAN January 12, 1984 WReTE R S DenECT OtA6 NUMSEM (202) 822-1051 Sheldon J. Wolfe Dr. David L. Hetrick Administrative Judge Administrative Judge Chairman, Atomic Safety and Atomic Safety and Licensing Board Licensing Board Professor of Nuclear Engineering U.S. Nuclear Pegulatory Commission University of Arizona Washington, D.C. 20555 Tucson, Arizona 85271 Dr. James C. Lamb, III Administrative Judge Atomic Safety and Licensing Board 313 Woodhave Road Chapel Hill, North Carolina 27514 In the Matter of Metropolitan Edison Co., et al.

(Three Mile Island Nuclear Station, Unit No. 1)

Docket No. 50-299 OLA (Steam Generator Repair)

Dear Administrative Judges:

Enclosed please find a copy of a letter from Licensee to the NRC Staff dated January 3, 1984 forwarding Supplement 2 to the Report of the Third Party Review of the TMI-l Steam Generator Repair Program. The initial Third Party Review report and Supplement 1 thereto have previously been made available to the Board and the parties as Appendix 6 to the Staff's SER.

Re ectfully subm tted, t u _j ce ' . .urchill

. Counsel for Licensee Enclosure cc: Service List /

1 8401160256 840112 PDR ADOCK 05000289 g '2 g PDR ,

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board In the Matter of )

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METROPOLITAN EDISON COMPANY, ET AL. ) Docket No. 50-289-OLA

) ASLBP 83-491-04-OLA (Three Mile-Island Nuclear ) (Steam Generator Repair)

Station, Unit No. 1) )

SERVICE LIST Sheldon J. Wolfe Atomic Safety and Licensing Administrative Judge Board Panel Chairman, Atomic Safety and U.S. Nuclear Regulatory Commission Licensing Board Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Docketing and Service Section (3)

Washington, D.C. 20555 Office of the Secretary U.S. Nuclear Regulatory Commission Dr. David L. Hetrick Washington, D.C. 20555 Administrative Judge Atomic Safety and Licensing Board Joanne Doroshow, Esq.

-Professor of Nuclear Engineering Louise Bradford University of Arizona Three Mile Island Alert, Inc.

Tucson, Arizona 85271 315 Peffer Street Harrisburg, Pennsylvania 17102

, Dr. James C. Lamb, III Administrative Judge Jane Lee Atomic Safety and Licensing Board 183 Valley Road 313 Woodhaven Road Etters, Pennsylvania 17319 Chapel Hill, North Carolina 27514 Norman Aamodt Richard J. Rawson, Esq. R. D. 5, Box 428 Mary E. Wagner, Esq. Coatesville, Pennsylvania 19320 Office of Executive Legal Director U.S.. Nuclear Regulatory Commission Washington, D.C. 20555 Atomic Safety and Licensing Appeal Board Panel U.S. Nuclear Regulatory Comission Washington, D.C. 20555 L .-

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'a CEU Nuclear C:rporatlin

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en;S e reo viddletewn, Pennsylvania 17057 '.

• 717 944 7621 TELEX 84 2366 Writer's Direct Dial Number:

Jacn y 3, 1984 3211-53-3S5 Office of Nuclear Reactor Regulations Attn: John F. Stolz, Chief Operating Reactors Branch No. 4 U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Sir:

Three Mile Island Nuclear Station, Unit I (TMI-1)

Operating License No. DPR-50 Docket Nc. 50-289 TMI-l Sceam Generator Repair Review Enclosed is Supplement 2 to the report of the Third Party Review of the TMI-l Steam Generator Repair Program. This supplement was prepared to document group member's reviews of the changes between Revision 2 and Revision 3 of GPUN's Topical Report 008. It provides written confirmation of the TPR's earlier oral statement that the revision did not affect its conclusion that "the TMI-1 plant can be operated safely with the repaired steam generators".

Sin:erely m .

M H.D. Hukill Vice President - TMI-1 HDH:MJG:mle Enclosure cc: H. Silver C. McCracken GPU Nuclear Corporation is a subsidiary of the Gerera; Puotic Uti%es Corpcration fL

DEC 9 1983 s (- - ,

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J;Tr/-mLT THE CINCINNATI GAS -& ELECTRIC COMPANY g- _

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December 3, 1983 EJW-83-0048 Mr. R. F. Wilson Vice' President, Technical Functions GPU Nuclear 100 Interpace Parkway Parsippany, NJ 07054

Dear Mr. Wilson:

Attached-is Supplement 2 to the supplementary Report of the Third Party Review of the TMI-l Steam Generatcr Repair Program.

This Review was requested originally by your letter of April 12, 1982 and has been conducted in accordance with the Charter you provided. previous reports were issued on Septem-ber 27, 1982, February 18, 1983, and May 16, 1983.

In GPU Nuclear letters of August 22 and September 9, 1983, Mr. Wetmore provided a revision to the Safety Evaluation Report (SER) and requested review of the SER and related documents by the Third Party Review Group.

The revision of'the SER concerned design analysis. There-fore, a review was performed by the Review Group members with competence in this specialty. They completed their review and discussed their results with the Chairman. The review conclu-sions are provided in Supplement 2.

I provided the conclusion of the Review Group to Mr. Wetmore in a telephone conversation on October 6, 1983. I want to assure you that the lateness of this written report reflects only my new priorities, not any difficulties with the SER or with the timely cooperation of the other reviewers.

8 '

S' cerely, ..

• n

. J. Wagte EJW/kf

Attachment:

" Report of Third Party Review of Three Mile Island, Unit 1, Steam Generator Repair", Supplement 2, dated December 3, 1983 cc: P. R. Clark, GPU Nuclear J. Wetmore, GPU Nuclear Third Party Review Members ,

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.a REPORT OF THE THIRD PARTY REVIEW OF THREE MILE ISLAND, UNIT 1, STEAM GENEPATOR REPAIR SUPPLEMENT 2

^

5 To R. F. Wilson - Vice President, Technical Functions s GPU Nuclear

'i Prepared by THIRD PARTY REVIEW GROUP:

Stephen D. Brown Stanley A. Holland Arturs Kalnins William H. Layman David J Morgan Richard W. Weeks

Edwin J. Wagner - Chairman

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Submitted for the Review Group By: [

.}:agned Date:

'. 3!df-l

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PURPOSE

- This report is Supplement 2 of the report of the Third Party

Review of the TMI-l steam generator repair dated February 18, 1983. It evaluates a. revision to the Safety Evaluati6n Report

(SER) made since the Review Group issued its conclusions in Sup-

plement 1 of May 16, 1983.

BACKGROUND l The establishment and operation of the Third Party Review Group of the TMI-1. steam generator repair was previously dis-cussed in the Review Group's Report of February 18, 1983. The report contained a conclusion concerning the adequacy of the steam generator' repairs for safe operation of the TMI plant and

~ findings, comments, and recommendations about the steam genera-

tor repair and return of.the plant.to operation.

In Supplement 1, of May 16, 1983, the Review Group evalu-ated the GPU Nuclear responses to the Review Group's Report and concluded that

"...upon satisfactory completion of the entire program as defined in the safety evaluations and as augmented by GPU Nuclear comments during and subse-

.quent.to the April 12 and 13 meeting, the TMI-l plant can be operated safely with the repaired steam generators."

GPU Nuclear subsequently revised their SER and issued " Assess-ment of TMI-l Plant Safety for Return to Service After Steam Gen-erator Repair, Topical Report 008, Revision 3, August 19, 1983."

The Review Group was requested by GPU Nuclear letters of

' August 22 and September 9, 1983, to review the revised SER. The GPU Nuclear letters are attached as Appendix A and B to provide

explicit identity to those documents supplied for review.

Revision 3 of the SER and related documents were distributed ,

to the specialist members of the Review Group who had interest in design analysis, which was the principal content of the revision.

The reviewers were Mr. Layman, Mr. Kalnins, and Mr. Wagner. They performed the review and discussed the conclusion by telephone.

The conclusion was provided to Mr. Wetmore, of GPU Nuclear, Inr the Chairman on October 6, 1983. This Supplement 2 reports the: Review Group's conclusion.

k

i d CONCLUSION

.The Review Group reiterates the conclusion of our Supplement

.; 1:as quoted above.

Revision 3 of the SER included actions to p

resolve prior Review Group comments as GPU Nuclear indicated i would be taken. No new or open safety questions were found in our review of the revisions of the SER.

3 i -COMMENTS

' The Review Group was specifically interested in the revised t actions taken by GPU Nuclear on topics upon which the Review

.: Group commented in Supplement 1. Those topics follow and are *

.[ '

referred to the same numbered section of Supplement 1.

E. Stress Analysis of Steam Generators f.

The Review Group had commented:

"For this reason, the Review Group recom-mended that a detailed stress analysis of the i- transition zone be made including the loading

of the main steam line break.

.; Subsequent to the Review Group meeting, GPU Nuclear advised that they had completed l ~ the stress analysis of the transition zone,

, and the revising the stress report to include i this analysis and that the analysis shows an i acceptable stress condition. This resolves the Review Group's comment. "

The Review Group found Revision 3 of the SER to reflect the revised stress analysis of the transition and that the

~s tresses are acceptable.

.. F. Steam Generator Leak Tightness After Repair The Review Group.had commented:

i *

"...Because of these uncertainties in the analyses, the Review Group questioned whether ,,

the results of the GPU Nuclear analysis of leak before break had sufficient margin for

5 the limiting case of a main steam line break.

Subsequent to the meeting GPU Nuclear has pursued this issue and advised they have come to the following conclusions:

- The GPU Nuclear study on crack preparation and their interpretation of the draft analy-sis done by others suggests that cracks will

t

.not grow or not grow rapidly as a result of flow induced vibration. Although growth rate i is a function of the assumed threshold stress

intensity, even the extreme case of no thres-

hold revealed long time _ periods for crack I _ growth to a critical size and therefore ample i time for operator action to shut down the re-

' actor.. prior to a tube failure either at power

or during shutdown. *

"- The tube loads associated with the steam main line break case were calculated using a gener-

ic analysis for B&W plants. The assumptions E: used in this analysis are very conservative j with respect to the particular plant para-meters for TMI-l and results in calculated j tube loads substantially greater than would When more realistic tube

': actually' occur.

loads are taken into account, the critical

! crack size is estimated to be significantly i

1 larger and the corresponding leak rate is in-

creased by approximately a factor _of two.

3 Thus GPU Nuclear concludes that because sig-i ~nificant margin exists in the tube loading used to determine critical crack size, ro

~

further conservatisms need be added in desig-3_ nating administrative limits which take f2 credit for leak before break...

? In addition, in response to Review Group

9. suggestions, GPU Nuclear will record the conden-5 ser offgas activity data during cooldown and 7-evaluate the feasibility of using this data for

determining primary-to secondary leak rates dur-ing conditions of higher tube-to-shell delta T.

I GPU Nuclear also plans to use secondary-to-

-i primary bubble testing tube as one technique for

locating leaking tubes whenever the plant is s

shut down in response to an increase to a leak

?

rate 0.1 gpm or more. The high sensitivity of j - this measurement technique provides additional

':: assurance that flaws that could become unstable '

f before the next eddy current inspection will be ,

detected."

}i -

k T'te Review Group found Revision 3 of the SER contains E

the following items which respond satisfactorily to our pre-

? vious comments:

~:

i a) The leak before break critical crack analysis was per-

% formed for the TMI-l specific main steam line break in J addition to the generic analysis. The leak before break analysis was also further supported by improved J; analysis of leakage rates through cracks.

f' b) Monitoring primary-to-secondary leakage rate indications

. during operational cooldowns was included.

'i c) Secondary-to-primary bubble testing for tube leak detec-

s tion was included whenever the plant is shutdown in response to an increase in leak rate of 6 gph (0.1 gpm) or more.

. APPENDIX 1 - GPU Nuclear letter dated August 22, 1983'to Mr. Edward E Wagner from Mr. J.S. Wetmore, Manager, PWR Licens-ing.

APPENDIX 2 - GPU~ Nuclear letter dated September 9, 1983 to

Mr. Edward Wagner from Mr. J.S. Wetmore, Manager, i PWR Licensing.

4 2

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s APPE:; DIX 1 I

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.- GPU Nuclear Corporation y-( g gg{ 100 lnterpac+ Parr say Parsiccany,'.e., ;ersey 07054 l

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TELEX 136 482 l

Writer's Direct Cia. f;umter:  ;

August 22, 1983  ;

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i Mr. Edward Wagner  %

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Cincinnati Gas & Electric  %

Zimer Nuclear Power Station EUC 2.4 G33.

RR#1 Box 2023 l

U.S. Route 52 Fit - - l' Mos:ow, CH 45153 y ]

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Dear Ed:

Per our telephone conversation today, I am forwarding the below E listed du'=nts for review by the Third Party Revi,ew Group for M-1 OTSG ,

E Bepair:

i

! 1. An SER entitled " Assessment of M-1 Plant Safety for Paturn to 2- Service After Steam Generator Repair,"

i 2. TDR-417 Rev.1 entitled "'IMI-l OTSG Tube Axial Icads and Leakage M3ntoring."

3. 'IDR-417 Rev. O entitled "OTSG Leakage and Operating Limits," and

4. Report entitled "The Residual Crack Opening Displacements in 2 Tubes arx3 Pipes."

Item 1 consists of changes made to Topical Report 008 (changes indicated by marginal change bars) to reflect results of OTSG cold testing 2 arxi updated assessment of tube axial loads and their effects on leakage rate

monitoring. Items 2 through 4 provide additional information to sdpport the

changes reflected in Item 1.

3 We expect to have further data to support the validity of estirates of residual crack opening displacements in the near future. A final

?

revision to Topical Report 008 will be congleted at that time. ..

h Per your request, I have forwarded copies of the enclosed to i, A. Kalnins and W. Laylaan.

Sincerely,,

h l [!

)

. S. Wetmore

Fanager PWR Licensing

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dis:0079f Enclosures GPU :uclear Ccrporat:cn s a sutsic 2 y c' me Gr e  ;: :?

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GPU Nucl:cr Ccrp: ration

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.01 203 6500 TELEX 136-4E0 writer's Direct D a *.umter-E&L: 50M September 9,1953 crn ! R E C EI V E D l_ _ E. J. WAONER n

Mr. Edward Wagner SEP 141983 Cincinnati Gas 6 Electric Zimmer Nuclear Power Station rac-R.R. #1 Box 2023 Triuan ro:

U.S. Route 52 Moscow, OH. 45153

Dear Ed:

Enclosed for Third Party Review Group review is Revision 3 to Topical

.i Report 008, " Assessment of BfI-1 Plant Safety for Return to Serv' ice After i Steam Generator Repair."

To minimize unnecessary delays, I have also forwarded copies directly to A. Kalnins and W. Layman.

'i Very t urs, j

/ ^pS J S. Wetmore

.anager, PNR Licensing 1r Enclosure GoU t:acrear Corpcration is a sucscary of me Ger. era' Fu:, ; U:i -: es CC'c: rat:C" l

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