ML20002C489

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Responds to Recommendations in 760419 Comments by Director,Nuclear Reactor Regulation Re Request for Exemption from 10CFR50.46. Submits Table Re Exams Performed on Class I Items
ML20002C489
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 05/11/1976
From: Sewell R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8101100365
Download: ML20002C489 (4)


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]C Consumcis Regulatory Docket Ella Power

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j Company General Offices: 212 West M cNgan Avenue. Jackson, MecNgan 49201

  • Area Code 517 788-0550 May 11,.1976 og, e

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US Nuclear Regulatory Commission

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DOCKET 50-155, LICENSE DPR 'm 8

BIG ROCK POINT PIANT 9-On April 19, 1976 you recommended to the commission in your " Comments by the Director, Nuclear Reactor Regulation, Relating to the Request for Exemption of the Big Rock Point Nuclear Power Plant From the Requirements of 10 CFR Section 50.46" that five items (Page 25) be completed by Consur. rs Power Company prior to the return of the Big Rock Point Plant to service from the present outage. The purpose of this letter is to address our actions I

with respect to these items.

Three of these items (la, lb and ld) were addressed in our proposed Technical Specifications dated May 10,197h. A fourth item (le) is discussed in this letter and additional information is provided on one item discussed in the May 10, 1976 submittal. Information regarding the fifth and remaining item (le) vill be submitted by the end of this week.

Item le states:

" Modify the emergency procedures to assure a second emergency diesel vill be obtained and operational within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after a LOCA."

The emergency procedures will be modified prior to start-up to require that, following a LOCA, a chain of events be initiated that will result in delivery of a diesel generator to the site such that it can be made fully operational within 2h hours after a IDCA.

A suitable trailer-mounted diesel generator is located at our Marysville Plant and arrangements have been made for Big Rock Point priority use in the event of a LOCA. Arrangements have also been made through a nearby Division off' for the use of a Consumers Power Company tractor to deliver the diesel s t,-

e erator to the Big Rock Point Plant. A test vill be conducted prior to start-up to ensure that the diesel generator can be operacional within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

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following a LOCA.

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2 Item lb recommended that augmented surveillance be provided for the core ring spray system. Our May 10, 1976 proposed Technical Specifications in-cluded enhanced component operability surveillance.

In addition, since April 19, 1976, we have examined all accessible welds in the Class I portion of the core ring spray system.

The' examination of the Class I portion was performed following the require-ments of Sections III and XI of the ASME B8 PV Code,1971 Edition with Addenda through winter 1972. The following table shows the items examined and method of examination:

(See attached isometric for item locations.)

Section XI Exams Item Class 6 Req Exams Performed Remarks Weld #1 II None UT Weld #2 II None UT Weld #3 II None UT Weld #4 I

UT UT Weld #5 I

UT UT Weld #6 I

UT UT Weld #7 I

UT UT Weld #8 I

UT UT Support Lug CSH-8 I

UT, VT UT, VT Weld #9 I

UT UT Hanger CSH-7A I

VT VT Hanger CSH-7 I

VT VT Weld #10 I

UT UT Weld #11 I

UT UT Weld #12 I

UT UT Weld #13 I

UT UT Hanger CSH-6 I

VT VT Weld #14 I

UT UT Weld #1kA I

UT UT-Weld #15 I

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Weld #16 I

UT UT Hanger CSH-5 I

VT VT Weld #17 I

UT UT Weld #17A I

UT UT Weld #18 I

UT, PT, VT UT, PT, VT Dissimilar Metal Weld Weld #19 I

UT None Not Accessible Weld #20 I

UT None Not Accessible Weld #21 I

UT None Not Accessible Weld #22 I

UT None Not Accessible The above examinations have been performed by Southwest Research Institute and Consumers Power Laboratory Services. The appropriate documentation shall be included in the respective 1976 Inservice Inspection reports for these groups.

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No indications were found volumetrically. One indication was found with pene-trant when examining Weld #18. 'This indication was an arc-strike and was.

subsequently ground out and reexamined and found to be acceptable.

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(kh LutL Ralph B. Sewell Nuclear Licensing Administrator CC: JGKeppler, USNRC

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'NitC r onM 105 U.S. NUCLL AH HEOULATOH V p M tGSION DOCKE T NUMDE H 82 m

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50-155 NRC DISTRIBUTION rOn PART 50 DOCKET MATERIAL TO:

NRC FROM: Consumers Rover Company DATE OF DOCUMENT Jackson, Mcih. 49201 5-11-76 j

Ralph B. Sewell DATE HECEl/EO

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5-12-76

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