ML20206J700

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Forwards Addl Info Supporting 881026 Proposed Amend to Tech Spec 4.8.1.1.2f Re Diesel Generator Testing Requirement. Acceptance of Amend Will Allow Unit 1 Surveillance Outage to Be Cancelled
ML20206J700
Person / Time
Site: Braidwood Constellation icon.png
Issue date: 11/22/1988
From: Hunsader S
COMMONWEALTH EDISON CO.
To: Murley T
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation
References
5243K, NUDOCS 8811290081
Download: ML20206J700 (55)


Text

- _ _ _ _

a m} Commonwealth Edison One Fd National Plaza Chicago, linos Address Repy M: Post Offc2 Box 76,7 Chicago, Enos 60690 0767 November 22, 1988 Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory' Commission Washington, DC 20555 Attnt Document Control Desk Subjects Braldwood Station Unit 1 Application for Amendment to I

racility Operating License NPF-72 Appendix A, Technical Specifications tiRC_ Docket No.__50-456 Referencet (a) October 26, 1988 S. C. Hunsader letter to T. E. Murley Dear Mr. Murleys

(.

In reference (a), pursuant to 10CFR 50.90, Commonwealth Edison

. Edison) proposed to amend Appendix A, Technical Specifications, of racility Operating Licenr.e NPT-72.

The proposed amendn;ent requests a change to fechnical Specification 4.8.1.1.2f to extend, on a one-time basis, the previously accepted 31 month surveillance testing requirement for Diesel Generators 1DG01KA and 1DG01KB, for an additional 7 months, until the first refueling outage for Braidwood Station Unit 1, currently scheduled for September, 1989.

The purpose of this letter is to provide additional information that supports what was provided to you in reference (a).

Specifically, you will find attached the folicvingt Attachment "A" is the September 285, 1988 Cooper Energy Services Group letter that provides their approval of a one time extension up to 38 months for the 'init 1 Diesei Janerator Technical Specification surveillance.

Attachment "L" is the October 20, 1988 Westinghouse letter that transmitted thelv risked based evaluation performed to support the extension of the Diesel Generator Technical Specification survelliance (teardown inspgetion) from 31 months to 38 months.

Attachment "C" is the November 17, 1988 Cooper Energy Service = Group letter that provides the results of the ENSPEC 3000 Engine Analyser operated on Diesel Generators, 1DG01KA and ID01KB on November 14, and 17, 1988.

As stated in the letter, all operating parametets were wit.hin manuf acturer's specifications.

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In the Safety Evaluation and Evaluation of Significant Hazards Considerations provided with Reference (a) Edison Indicated that the failure histories of 50th diesel generators had been reviewed and trends of abnormal failures had not been identifled. The information provide 3 in Attachment "C" supports that conclusion.

As indicated in reference (a), an expedited NRC review is requested so that the revised Technical Specification can be in piece ptfor to the Braldwood Unit 1 surveillance outage, scheduled to start in early February, i

1989. Associated work packages will need to begin to be prepared soon, prior to the start of the outage.

In addition, with Unit 2 surveillances becoming due at the same time, a February, 1909 Unit 1 outage would result in a December, 1988 surveillance outage start for Unit 2.

Acceptance of this snendment will allow the Unit 1 surveillance outage to be cancelled and allow for these Technical Specification surveillances to be accomplished during the Braldwood Unit 1 Refueling outage, scheduled to start in early Septenber, i

1999.

Also, the extension will allow the Unit 2 surveillance outage to begin in early January, 1989 instead of December, 1988.

Please direct any questions you may have concerning this matter to this office.

Very truly yours, S. C. Huns 6 der Nuclear Licensing Administrator l

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Attachments (A):

September 26, 1988 Cooper Energy Services Group Letter (B): October 20, 1988 Westinghouse Letter (C): November 17, 1988 Cooper Energy Services Group Letter cc Resident Inspector - Braidwood l

S. P. Sands - NRR Regional Office KIII M. C. Parker - State of Ill.

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d ENEMY SEm4CES QW 9E961 Sepember 26, 1988 Comonwes1th Edison Braidwood Nuclear Station Rt. 1 Box 84 Bracev111e. Illinois 60407 Attention: Mr. Randall, Smith

Dear Mr. Smith:

Referring to Mr. Querio's September 16 1988 letter to G. L. Miller of Energy Services Group requesting an app,roximate thirty-eight (33) month elapsed time since the last full maintenance / inspection surveillance of your 1A and 18 diesal generator sets, which is two (2) months longer than previously agreed to.

On July 31, 1987 Energy Services Group approved a 36 month extension for the 1A and 18 diesel with a mutual agreement that thirteen (13) items of inspection be perfomed and in your September 16, 1988 letter y(Thecheck-listisattachedforyourreview.)ou state that this inspection wa It is my understanding you do trend monitoring of diesel generator operating parameters.

I suggest you continue to do so and any significant change is cause to perfor* any or all the thirteen (13) points of inspection again.

Energy Services Group grants approval of a one tirne extension (36 to 38 months) for the 1A and 18 diesels to allow Braidwood to schedule diesel generator inspection with reactor full outage.

Sincerely, hh Glenn L. Miller Service Manager Eastern Regiun

/m Attachment (ThirteenPointInspectionList)

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ATTACHMENT g./#

The following items will be perfomed during the Preventative Maintenance Program.

1) A review of the Diesel Generator's starting times. operating logs and maintenance history to identify any significant trends of degradation.

2)

Perfom engine analyzer to monitor peak firing pressures, compression pressures and cyltader vibration.

3)

Record Turbocharger spindown time.

4)

Inspect crosshead clearances by verifying freedom of movement.

(Until rocker am issue resolution.)

5)

Inspect rocker am assemblies for each cylinder without disassembly.

6) Adjust intake and exhaust valve tappets for each cylinder.

7)

Review operating logs for the following filter's differential pressure readings.

If differential pressures are rising, inspect and clean filters as necessary.

a Fuel 011 $ trainers l

b Fuel Oil Filters l

c Full Flow Lube Oil Filter d

Turbocharger Lube Oil Fitlers 8)

Inspect and clean as necessary the following filters and strainers:

i a

Luba 011 Strainers b

Crankcase Breather Filter e

Cylinder Head treather Filters d

Ate Intake Filtors e

Air Start Header Filters f

Air Intake Manifolds 9)

Inspect the fuel contro* linkage.

10)

Inspect and clean as necessary fuel injector pump metering

rods, tl)

Inspect and clean as necessary the governer control "bimba" cylinder.

12)

Inspect local control panel for cleanlinns.

13)

Perfom engine analyzer to monitor peak firing pressures and cylinder vibration.

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',/ J CCE-88-502 Westinghouse Energy Systems Pener Systems Omsv Electric Corporation e ns Pittsburp Pevsytvoa 15230 0355 NS-OPLS-OPL-I-88-422 October 20, 1988 Mr. C. A. Moerke General Design Engineer Byron and Braidwood Stations Corrconwealth Edison Company P.O. Box 767 Chicago, IL 60690 C0f00hVEALTH EDISON COMPANY BRAIIkDOD - UNITS 1 AND 2 DIESEL GENERATOR SURVEILLANCE EXTDJSION

Dear Mr. Moerke:

This letter transmits the risk based evaluation which has been perforned to support extension of the diesel generator teardown inspection from a 31 month interval to a 38 month interval. The effort was perforved at the request of Mr. E. Swartz with the cooperation of Mr. R. &ith at the Braidwood site, who received an advanced copy of the report via telex on 10/14/88.

The attachment includes a safety evaluatioa checklist (SECL-88-562) and a "no significant hazards" determination in support of the tecnnical specification change. This evaluation has as it's basis a recent evaluation which extended the surveillance interval to 31 months and was transmitted to Commonwealth Edison v.ia CAh'-10557/CE'a'-6021 dated 6/4/87.

Should you have any questions, please do not hesitate to call.

Very truly yours, rl x,-l,..l, j

h G.P. Toth, Manager pf, 4%ws L

Ccenonwealth Edison Projects smd/

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o CCE-68-502 NS-OPLS-OPL-I-88-422 cc:

R.E. Querio, Braidwood

<S.C;? Hunsader =.. s D. Swartz

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R. Sraith, Braidwood I

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nu NS-RH01-!G-10 5

SEC L-8 8 - 5(o 2.

ATTACHMENT 1 Customer Reference No(s).

WestinghouseReferenceNo(s).

(Change, Control or RFQ As Applicable)

WESTINGHOUSE NUCLEAR SAFETY EVALVATION CHECK LIST PAGE 1 0F 3

/

-/

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(1) NUCLEAR PLANT (S) u (2) CHECK LIST APPLICABLE TO:

- I[ A'c-4 # wen (SubjectofChange) y (3) The written safety evaluation of the revised procedure, design change or modification required by 10CFR50.59 has been prepaied to the extent required and is attached.

If a safety evaluation is not required or is incomplete for any reason, explain on Page 3.

Parts A and B of this Safety Evaluation Check List are to be ecmpleted only on the basis of the safety evaluation performed.

CHECK LIST - PART A (3.1) Yes No X

A change to the plant r, described in the FSAR?

(3.2) Yes No X

A change to the procedsrcs as described in the FSAR?

(3.3) Yes No X

A test or experiment.iot described in the FSAR?

(3.4) its g_ No A change to the piart technical specifications W',- htn C CW (Appen x A to the Orerating License)?

on CHECK LIST - PART B (J tificat on for Fart B answers must be included on Page 3.

(4.1) Yes No X

Will the probability of an accident previously evaluated in the FSAR be increased?

(4.2) Yes No k

Wili the consequences of an accident previously evaluated in the FSAR be increased?

(4.3) Yes_.

No A Way the possibility of an accident which is different than any already evaluated in the FSAR be created?

(4.4) Yes No k May the probability of a malfunction of equipment important to safety previously evaluated in the FSAR be increased?

(4.5) Yes No X

W111 the consequences of a La1 function of equipment important to safety previously evaluated in the FSAR bs increased?

y (4.6) Yes No n Nay the possibility of a malfunction of equipment important to safety different than any already evaluated in the FSAR be created?

j 4

(4.7) Yes No N Will the margin of safety as defined in the g

bases to any technical specification be reduced?

me.io m m

RiY NS-RM0!-IG-10 5

SEC4 F61

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ATTACHMENT 1(Continued) i Customer Reference No(s).

Westinghouse Reference No(s).

(Change Control or RFQ As Applicable)

WESTINGHOUSE NUCLEAR SAFETY EVALUATION CHECK LIST PAGE 2 0F 3 If the answers to any of the p.*., ceding questions are unknown, indicate under (5) REMARKS and explain on page 3.

If the answer to any of the above questions in (4) cannot be answered in the negative, based on written safety evaluation, the change cannot be approved without an application for license amendment submitted to NRC pursuant to 10CFR50.90.

(5) REMARKS:

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Re (enu e 2. : Byen Geneedinj 5 + w % Z ;,,i 6 in g C o n d h,s f e r-Opeation Rdo otion Prepa m,Wc 6 P-lo s 2 6 Apr,1 19 64.

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(6) APPROVAL LADDER (Signatures):

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d ate: /#/7/88 (6.1)Preparedby(NuclearSafety):

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I (6.2)CoordinatedwithEngineer(s):

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Date:

(6.3) Coordinating Group Manager (s):

Date:

(6.4) Nuclear Safety Group Manager: 8 M /, / h _ Date: /M/FN f

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NS-RM01-IC-10 5

SECL-68.g&L ATTACHMENT 1 (Continued)

Customer Reference No(s).

Westinghouse Reference No(s).

(Change Control or RFQ As Applicable)

WESTINGHOUSE NUCLEAR SAFETY EVALUATION CHECK LIST PAGE 3 0F 3 The following sumarizes the justification upon the written safety evaluation,II) for answers given in Part B of the Safety Evaluation Check List:

' G.Ct W

?.N h Af IIIReference to document (s) containing written safety evaluation:

,>s PREPARED BY:

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