ML20238B746
| ML20238B746 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/10/1987 |
| From: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | Johnston W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8708210435 | |
| Download: ML20238B746 (2) | |
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GPU Nuclear Corporation
. a-Q gf Post Office Box 388 Route 9 South Forked River.New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:
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August 10, 1987 Mr. William V. Johnston, Acting Director
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Division of Reactor Safety
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U.S. Nuclear Regulatory Commission i
Region I l
631 Park Avenue 1
l King of Prussia, PA 19406 l
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Dear Mr. Johnston:
Subject:
Oyster Creek Nuclear Generating Station j
Docket No. 50-219
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IE Inspection Report 50-219/87-20 Response to Notice of Violation j
Enclosed is GPU Nuclear's response to Appendix A of your letter dated July 8, j
i 1987.
This response is submitted in accordance with 10 CFR 2.201.
j If you should have any questions, please contact Mr. John Rogers at (609)971-4693.
Very truly yours, t
Pt
. Fiedler l
Vice President and Director l
Oyster Creek PBF/JR/dmd (0360A) 8708210435 070810 DR ADOCK 0500 9
i Attachment o
cc: Mr. William T. Russell, Administrator Region I U.S. Nuclear Regu'latory Commission 631 Park Avenue King of Prussia, PA 19406 Mr. Alexander f. 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 Corporation is a subsidiary of the General Puohc Utilities Corporation
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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 confermance witn 10 CFR50.55a(g), except where relief has been gra,1ted by the Commission.
The Emergency Service Water pumps are included as part of the licensee's l
Inservice Test Program and ue thus subject to ASME Section XI, article 1WP-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.
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RESPONSE TO VIOLATION i
GPU Nuclear concurs with the cited violation.
Original baseline readings for the Emergency Service Water (ESW) system were approximately 4250 gpm, i
however, on December 12, 1986, system flow rate was rebaselined due to I
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 Soray 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 l
Article IWP-4000 " Methods of Measurement".
ESW System gauges have been replaced with gauges which meet the ASME Code requi rements.
The full range of these gauges does not exceed four (4) 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.