ML20009C902

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Application for Amend of License DPR-6 Submitted as Tech Spec Change Request to Formalize Snubber Operability & Surveillance Requirements
ML20009C902
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 07/20/1981
From: Dewitt R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20009C901 List:
References
NUDOCS 8107220117
Download: ML20009C902 (3)


Text

t CONSUMERS POWER COMPANY Docket 50-155 Request for Change to the Technical Specifications License DPR-6 For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Facility Operating License DPR-6, Docket 50-155, issued to Consumers Power Company on May 1, 1964, for the Big Rock Point Plant be changed as described in Section I below:

I.

Changes Section 3.1.5 REACTOR DEPRESSURIZATION SYSTEM Change the " Applicability:" statement to read:

" Applies to the operating status of the Reactor Depressurization System (RDS) and the attached mechanical snubbers."

Add a new " Action:" statement which reads:

"4.

If the RDS is declared inoperable because of a snubber defect and l

1s not-returned to an operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the plant shall be brought in a normal and orderly manner to a cold shutdown condition until the RDS can be declared operable.

If the plant is already in a cold shutdown conditim, it shall not be started up until all snubbers are operable

  • Sectio a 4.1.5 REACTOR DEPRESSURIZATION SYSTEM i

Change the " Applicability:" statement to read:

" Applies to periodic testing requirements for the RDS and the attached mechanical snubbers."

Add two new " Specification:" statements which read:

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"H.

A visual inspection of 10* (2) of the thirteen mechanical snubbers on the RDS shall be performed at each refueling outage but not to I

exceed 18 months. Visual inspections shall be used to verify that I

there are no virible indications of damage or impaired operability to the snubbers or their attachments.

"I.

A functional test of 10*. (2) of the thirteen mechanical snubbers on the RDS shall be performed at each refueling outage but not to exceed 18 months. Fdnctional tests shall be used to verify that the force that initiates free movement of the snubber rod, in tension and compression, is less than the vendor specified maximum l

drag forec. Acrivation restraining action shall be achievel within l

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the vendor specificd range of velocity or acceleration in both tension and compression."

Bases:

REACTOR DEPRESSURIZATION SYSTEM Add a new paragraph at'che end of the existing " Bases:"

"All snubbers are required OPERABLE to ensure that the structural integrity of the RDS is maintained during and following a seismic or other event initiating dynamic loads. There are thirteen mechanical snubbers on the RDS that are subject to required visual and functional testing. The snubbers have a 40-year service life and no maintenance requirements as the snubbers do not contain any fluid, seals, etc."

II Discussion The above proposed Technical Specifications changes are requested in response to NRC letter dated March 23, 1981, entitled, " Technical Speci-fication Revisions for Snubber Surveillance." The purpose of incor-porating operability and surveillance criteria into the Technical Specifications is to address operability problems experienced with mechanical snubbers as identified in IE Bulletin No 81-01, dated

-January 27, 1981, entitled, " Surveillance of Mechanical Snubbers."

Consumers Power Company letter dated March 13, 1981 provided our response to IE Bulletin No 81-01.

There are only thirteen snubbers currently in use in the safety-related systems at Big Rock Point. All of these snubbers are of a mechanical design (ie, no hydraulic snubbers are used) and were manufactured by Pacific Scientific. The Reactor Depressurization System (RDS) is the only system that contains snubbers. Therefore, this change request only affects those sections of the Big Rock Point Plant Technical Speci-fications that pertain to RDS.

It will be noted that this change is not in the Standard Technical Specifications format because the Big Rock Point Plant Technical Specifications are not written in the STS format.

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3 III. Conclusion Based on the foregoing, both the Big Rock Point Plant Review Committee and the Safety and Audit Review Board have ::eviewed these changes and find them acceptable.

CONSUMERS POWER COMPANT N

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By R B DeWitt, Vice President Nuclear Operations Sworn and subscribed to before me this 20th day of July 1981.

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Helen I Dempski, Notary p6blic Jackson County,~ Michigan My commission expires December 14, 1983.

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