IR 05000219/1987020

Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-219/87-20

ML20238B224
Person / Time
Site:	Oyster Creek
Issue date:	08/25/1987
From:	Johnston W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
References
NUDOCS 8709010124
Download: ML20238B224 (3)

Text

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AUG 2 5 1987  ;

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Docket No. 50-219

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License No. DPR-16 j GFU Nuclear Corporation ATTN: Mr. P. B. Fiedler Vice President and Director Oyster Creek Nuclear Generating Station P. O. Box 388 Forked River, NJ 08731 Gentlemen:

Subject: Inspection No. 50-219/87-20 This refers to your letter dated August 10, 1987, in response to our letter dated July 8, 1987.

Thank you for informing us of the corrective and preventive actions documented in your letter. These actions will be examined during a future inspection of your licensed program.

Your cooperation with us is appreciated.

Sincerely,

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 ? Die;nagg*.

' % eang William V. Johnston, Acting Director Division of Reactor Safety cc:

M. Laggart, BWR Licensing Manager Licensing Manager, Oyster Creek Public Document Room (PDR) j Local Public Document Room (LPDR) {

Nuclear Safety Information Center (NSIC) l NRC Resident Inspector State of New Jersey ]

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OFFICIAL RECORD COPY RL OC 87-20 - 0001.0.0 08/24/87

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Region I Docket Room (with concurrences)

Management Assistant, DRMA Section Chief, DRP Robert J. Bores, DRSS h

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GPU Nuclear Corporation u Nuclear =sa:8r388 Forked River, New Jersey 08731-0388 609 971-4000

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Writer's Direct Dial Number:

August 10, 1987 Mr. William V. Johnston, Acting Director i Division of Reactor Safety U.S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406

Dear Mr. Johnston:

Subject: Oyster Creek Nuclear Generating Station Docket No. 50-219 IE Inspection Report 50-219/87-20 Response to Notice of Violation ,

i Enclosed is GPU Nuclear's response to Appendix A of your letter dated July 8.,

1987. This response is submitted in accordance with 10 CFR 2.201.

l If you should have any questions, please contact Mr. John Rogers at (609)971-4893.

Very truly yours,

_4 Pt . Fiedler Vice President and Director Oyster Creek PBF/JR/dmd (0360A)

Attachment cc: Mr. William T. Russell, Administrator Region I U.S. Nuclear Regulatory Comniission 631 Park Avenue King of Prussia, PA 19406 Mr. Alexander W. Dromerick, Project Manager U.S. Nuclear Regulatory Commission Division of Reactor Projects I/II 7920 Norfolk Avenue, Phillips Bldg.

Bethesda, MD 20014 NRC Resident Inspector Oyster Creek Nuclear Generating Station GPU Nuclear Corporahon is a subsidiary of the General Pubhc Utihties Corporation 0 h a

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ATTACHMENT VIOLATION 10 CFR 50.55a(g)(4) requires pumps and valves classified as ASME Code Class 1 to be tested for operational readiness in accordance with Section XI of the ASME Boiler and Pressure Vessel Code. Technical Specifications 4.3C requires conformance with 10 CFR50.55a(g), except where relief has been granted by the Commission.

The Emergency Service Water pumps are included as part of the _ licensee's Inservice Test Program and are thus subject to ASME Section XI, article IWP-4000, " Methods of Measurement". Subarticle IWP-4111 states that "the full range of each instrument shall not be greater than four times the reference value."

Contrary to the above, on June 2,1987, a flow measurement test was performed on System II of the ESW System utilizing a gage (ESW-1) with a range of greater than four times the established value.

RESPONSE TO VIOLATION GPU Nuclear concurs with the cited violation. Original baseline readings for the Emergency Service Water (ESW) system were approximately 4250 gpm, ,

however, on December 12, 1986, system flow rate was rebaselined due to !

throttling of the discharge valve to maintain a positive differential pressure between the ESW System and the Containment Spray System (to assure potential leakage is into the Containment Spray System). ESW system flow rate was rebaselined to approximately 3600 gpm, however, the existing gauge range was not reviewed for compliance with ASME Section XI Article IWP-4000 " Methods of Measurement".

ESW System gauges have been replaced with gauges which meet the ASME Code j requirements. The full range of these gauges does not exceed four (4) I times the reference value. All other gauges utilized in the IST program were reviewed for compliance with ASME criteria and no other exceptions were noted. Full compliance was achieved on August 7,1987.

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