ML17241A383
| ML17241A383 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 06/24/1999 |
| From: | Peterson S NRC (Affiliation Not Assigned) |
| To: | Plunkett T FLORIDA POWER & LIGHT CO. |
| Shared Package | |
| ML17241A384 | List: |
| References | |
| TAC-MA5165, NUDOCS 9907010089 | |
| Download: ML17241A383 (2) | |
Text
June 24, 1999 Mr. T. F. Plunkett President - Nuclear Division Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
RELIEF FROM ASME CODE REQUIREMENTS RELATED TO THE INTERIM RELIEF REQUEST NO. 26 FOR THE EMERGENCY CORE COOLING SYSTEM PIPING FOR ST. LUCIE PLANT, UNIT2 (TAC NO. MA5165)
Dear Mr. Plunkett:
In a letter dated April7, 1999, the licensee submitted, pursuant to 10 CFR 50.55a(g)(5)(iii) a request for relief from the repair and/or replacement requirements of the American Society of Mechanical Engineers (ASME) Code,Section XI, Articles IWNIWC-'4000 and IWNIWC-7000.
The relief request documented the conditions as committed to during the April6, 1999, telephone conference with the NRC staff. The St. Lucie Unit 2 plant is currently in the second ten year inservice inspection interval and the code of record for inservice inspection for the interval is ASME Code,Section XI 1989.
The granting of relief is based upon the fulfillmentof any commitments made by the licensee in the basis for each relief request and the alternatives proposed.
Where interim relief has been granted, the licensee should resolve the issues before expiration of the interim period. The ASME Code repairs were completed on April 10, 1999 for train A, and April 16, 1999 for header B. Therefore, as of the date of this letter, the interim period has expired.
The NRC staff finds that the Code requirements resulted in a hardship or unusual difficulty without a compensating increase in the level of quality and safety and hereby authorizes the proposed alternative contained in relief request No. 26, pursuant to 10 CFR 50.55a(a)(3)(ii)
~
Sincerely, Ori~paal signed by:
Sheri R. Peterson, Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-389
Enclosure:
Safety Evaluation cc w/encls: See next page.
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0 Cy UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 2I;555 June 24, 1999 Mr. T. F. Plunkett President - Nuclear Division Florida Power and Light Company, P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
RELIEF FROM ASME CODE REQUIREMENTS RELATEDTO THE INTERIM RELIEF REQUEST NO. 26 FOR THE EMERGENCY CORE COOLING SYSTEM PIPING FOR ST. LUCIE PLANT, UNIT2 (TAC NO. MA5165)
Dear Mr. Plunkett:
In a letter dated April7, 1999, the licensee submitted, pursuant to 10 CFR 50.55a(g)(5)(iii), a request for relief from the repair and/or replacement requirements of the American Society of Mechanical Engineers (ASME) Code,Section XI, Articles IWA/IWC-4000 and IWA/IWC-7000.
The relief request documented the conditions as committed to during the April6, 1999, telephone conference with the U.S. Nuclear Regulatory Commission (NRC) staff. The St. Lucie Unit 2 plant is currently in the second 10-year inservice inspection interval and the code of record for inservice inspection for the interval is ASME Code,Section XI 1989.
The granting of relief is based upon the fulfillmentof any commitments made by the licensee in the basis for each relief request and the alternatives proposed.
Where interim relief has been granted, the licensee should resolve the issues before expiration of the interim period. The ASME Code repairs were completed on April 10, 1999, for train "A", and April 16, 1999, for header B. Therefore, as of the date of this letter, the interim period has expired.
The NRC staff finds that the Code requirements resulted in a hardship or unusual difficulty without a compensating increase in the level of quality and safety and hereby authorizes the proposed alternative contained in Relief Request No. 26, pursuant to 10 CFR 50.55a(a)(3}(ii).
Sincerely, Docket No. 50-389
Enclosure:
Safety Evaluation cc w/encls: See next page.
Sheri R. Peterson, Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation