ML20052G195

Informs of No Relief or Safety Valve Failures or Challenges During Apr-Dec 1980 in Response to 820423 Request for Documentation & Commitment to NUREG-0737,Item II.K.3.3, Reporting Relief & Safety Valve Failures & Challenges

ML20052G195
Person / Time
Site:	Crystal River
Issue date:	05/10/1982
From:	Mardis D FLORIDA POWER CORP.
To:	Stolz J Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.03, TASK-TM 3F-0582-08, 3F-582-8, TAC-45333, NUDOCS 8205140395
Download: ML20052G195 (2)

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Power C O A P O e a f e O se May 10,1982

1. 3F-0582-08 File: 3-0-26 m

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O Mr. John F. Stolz, Chief N

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U.S. Nuclear Regulatory Cammission Sq M i.',

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Washington, D.C. 20555 L

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Subject:

Crystal River Unit 3 Docket No. 50-302 q

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Operating License No. DPR-72 g

g NUREG-0737; Item II.K.3.3 Reporting Relief Valve and Safety Valve Failures and Challenges

Dear Mr. Stolz:

Florida Power Corporation (FPC) has received your letter dated April 23,1982, requesting documentation and commitment on Reporting Relief Valve and Safety Valve Failures and Challenges. In response to the subject item, FPC did not provide a report documenting relief valve and safety valve failures and challenges that occurred during the period of April 1,1980 through December 31,1980, because there were neither relief valve nor safety valve failures nor challenges during that period.

At Crystal River Unit 3, the requirements for the pressurizer code safety valves are given in Technical Specifications 3.4.2 and 3.4.3.

Therefore, any operation of these valves outside of the limiting conditions for operation is promptly reportable as required by Technical Specification 6.9.1.8.b.

The requirements for the pressurizer Power Operated Relief Valve (PORV) were proposed in Technical Specification Change Request Number (TSCRN) 47, dated July 13,1979, as Technical Specification 3.4.11 and TSCRN 64, Rev.1, dated August 15,1980, as Technical Specification 3.4.3.2. Upon issuance of these Technical Specifications, operation of these valves outside of the limiting conditions for operation will be promptly reportable as required by Technical Specification 6.9.1.8.b.

/ 6 8205140395 020510 PDR ADOCK 05000 P

General Office 3201 Thirty fourth street soutn. P O Box 14042. St Petersburg. Florida 33733 813-866-5151

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i Mr. John F. Stolz 4

May 10,1982 Page 2 If there are any further questions on this item, please contact this office.

k Very truly yours, Mb nee David G. Mardis Acting Manager i

Nuclear Licensing GF:mm cc:

Mr. 3. P. O'Reilly, Regional Administrator Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 3100 Atlanta, GA 30303 i.

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