ML20066B400

Notice of Issuance & Availability of Amends 58 & 52 to Licenses DPR-42 & DPR-60,respectively

ML20066B400
Person / Time
Site:	Prairie Island
Issue date:	10/18/1982
From:	Clark R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20066B396	List: ML20066B394 ML20066B400
References
NUDOCS 8211060625
Download: ML20066B400 (2)

Text

{{#Wiki_filter:. 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NOS. 50-282 AND 50-306 NORTHERN STATES POWER COMPANY NOTICE OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES The U. S. Nuclear Regulatory Commission (the Commission) has issued Amendment No. 58 to Facility Operating License No. DPR-42, and Amendment No. 52 to Facility Operating License No. DPR-60 issued to Northern States Power Company (the licensee), which revised Tech-nical Specifications for operation of Prairie Island Nuclear Generating Plant, Unit Nos.1 and 2 (the fac,ilities) located in Goodhue County, Minnesota. The amendmeats are effective as of the date of issuance. The amendments revise the Appendix A Technical Specifications concerned with the peak burnup limits shown in Figure TS.3.10-7. The peak burnup linit is increased from 47,000 to 51,000 MWD /MTV. The application for the amendments complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Commission has made. appropriate findings as required by the Act and the Commission's rules and r'egulations in 10 CFR Chapter I, which are set forth in the license amendments. Prior public notice of these amendments was e not required since the amendments do not involve a significant hazards consideration. 8211060625 821018 PDR ADOCK 05000282 P PDR

7590-01 The Commission has determined that the issuance of these amendments will not result in any significant environmental impact and that pursuant to 10 CFR 51.5(d)(4) an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with issuance of these amendments. For further details with respect to this action, see (1) the application for amendments dated June 14, 1982 as revised July 7 and September 24,1982,(2) Amendment Nos. 58 and 52 to License Nos. DPR-42 and DPR-60, and (3) the Commission's related Safety Evaluation. All of these items are available for public inspection at the Commission's Public Cocument Room, 1717 H Street, N.W., Washington, D.C. and at the Environ 7: ental Conservatico Library, 300 Nicollet Mall, Minneapolis, Minnesota 55401. A copy of items (2) and (3) nay be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: Director, Division of I.f censing. Dated at Bethesda, Maryland, this 18th day of October,1982. FOR THE NUCLEAR REGULATORY COMMISSION Om Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing

e b REGULATURf INFORMATION DISTRIBUTION SYSTEM (RIDS) ACCESSION NbR:8210190717 00C.DATE: 82/10/14 NOTARIZEC: NO DOCKET

• FACIL:STN-50-528 Palo verde nuclear Station, Unit 1,

Arizona Publi 05000528 STN-50-529 Palo verde nuclear Station, Unit 2, Arizona Publi 05000529 STN-50-530 Palo Verce Auclear Station, Unit 3, Arizona Publi 05000530 AUTH.NAME AUTHuR AFFILIATION VAN 6 RUNT,E.L. Arizcna Public Service Co. RECIP.NAME HECIFIENI AFFILIATION NCVAK,T.M. Assistant Director for Licensing SLbJECT: Recuests NRC review results of PWR cesign analyses to approve removal of pipe whip restraints.Feeting w/NRC to discuss recuest & facilitate exchange of info & questions suggestec. DISTRIBUTION CODE: 8001S COPIES FLCLIVED:LTR __ ENCL _ SIZE:__________ TI1LE: Licensing Submittal: PSAR/FSAR Amats & Helateo Corresponcence NCTES:Stancaroizec plant. 05000528 Standardized plant. 05000529 Standardizec plant. 05000530 RECIPIENT COPIES RECIPIENT COPIES ID CODE /NAFE LTIR ENCL ID CODE /NAFE LTTH ENCL NRR/DL/ADL 1 0 NRR LB3 BC 1 0 NRR LB3 LA 1 0 LICITRA,E. 01 1 1 INTERhAL: ELD /HDS3 1 0 IE FILE 1 1 IE/CEP EPDS 35 1 1 IE/uEP/EPLB 36 3 3 NRR/DE/AEA8 1 0 NRR/DE/CEB 11 1 1 NRR/DE/EGB 13 3 3 NRR/DE/GB 28 2 2 NRR/DE/HGE6 30 2 2 NRR/DE/MEB 18 1 1 NRn/DE/MTEB 17 1 1 NRR/DE/ GAB 21 1 1 NRH/DE/SAS 24 1 1 NRR/Dt/SE6 25 1 1 NRn/DNFS/MFEb40 1 1 NRR/DNFb/LGB 32 1 1 NRR/DhFS/0LB 34 1 1 NRR/DnF5/PThB20 1 1 NRn/DSI/AEB 2o 1 1 NRR/DSI/ASB 27 1 1 NRn/OSI/CPo 19 1 1 NRR/DSI/CS8 09 1 1 NRR/USI/ET58 12 1 1 NRR/DSI/ICS6 16 1 1 NRn/0SI/PSB 19 1 1 NRR/DSI/ RAS 22 1 1 NRh/DSI/RS6 23 1 1 NRR/ DST /LGB 33 1 1 REG FILE 04 1 1 RGN5 2 2 RP/DDAMI/PIB 1 0 EXTERNAL: ACHS 41 o 6 BNL(ANDTS OhlY) 1 1 DPd/ DSS (AMDTSJ 1 1 FEMA-kEP DIk 39 1 1 LPOR 03 1 1 NRC PCR 02 1 1 NSIC OS 1 1 NTIS 1 1 I TOTAL NUMBER OF COPIES HEGUIRED: LTTR 55 ENCL 49

6 h P. O. Box 21666 - PHOENIX, ARIZoN A 85o36 October 14, 1982 ANPP-22020 - WFQ/TFQ Mr. Thomas Novak Assistant Director for Licensing Division of Licensing ' Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Subj ect: Palc Verde Nuclear Generating Station (PVNGS) Units 1, 2 and 3 Docket Nos. STN-50-528/529/530 File: 82-056-026; G.I.01.10

Reference:

NUREG/CR-2189, " Probability of Pipe Fracture in the primary coolant loop of a PWR plant", dated September,1981. Ded Str. Novak: The design basis for PVNGS Units 1, 2 and 3 includes the postulation of guillotine pipe breaks in the Reactor Coolant System (RCS) main loop piping. Recent analy-ses,the referenced report, of Westinghouse PWR's have shown that: 1. The probability of guillotine tailures are extemely small ( 10-12) 2. A through-the-wall crack of detectable size will remain stable when subjected to an SSE. A probabilistic analysis of the PVNGS RCS is being conducted by Lawrence Livermore Laboratories (LLL) to define the probability of a guillotine rupture. We have furnished LLL with information related to the design and expected loads on the RCS and our seismic consultant, ERTEC, is developing a site specific seismic hazard curve. This seismic hazard curve is expected to be complete and trans-mitted to LLL by October 31, 1982. It is expected that LLL will complete their analyses on PVNGS by December, 1982. Favorable results from this analysis is expected, similar to the results of the referenced report. This may justify the elimination of the double-ended guillotine break of RCS piping from the PVNGS design basis, which would dismiss the need for RCS pipe whip restraints. These restraints require substantial maintenance, surveillance and adjustment efforts during the in-service inspection program, which creates a substantial radiation exposure hazard to personnel performing these tasks. These restraints are also extensive and expensive to manufacture and install. If justified by the LLL analysis, we would very much consider removing them from the PVNGS design. gog{[o A

ss Mr. T. Novak October 14, 1982 ANPP-22020 - WFQ/TFQ Page 2 The construction status of the restraints is shown below: UNITS STATUS 1 Installed, Unadjusted 2 Machining of saddles to start November,1982 3 Machining of saddles to start January,1,985_ We feel, from results of previous analyses on other PWR designs, the LLL analysis for PVNGS will justify elimination of these restraints from the design basis. We request that the NRC review the results of LLL analyses as soon as they are available, so that you can approve the removal of the restraints from the PVNGS design. We request a meeting with the appropriate members of the NRC staff, as discussed with R. Bosnak, Chief, Mechanical Engineering Branch, on October 20, 1982, to discuss this request and to facili-tate an exchange of information, and any additional questions the NRC staff may have on this matter. Ver/ truly yours, N -{ \\ r k. c,\\. ~/ t t U_a. V, ts s { E. S. Van Brunt, Jr. APS Vice President, Nuclear Projects ANPP Project Director W, u ,j EEVBJr/TFQ/sp cc: E. Licitra k. R. Bosnak f L. Bernabei "l{'a P. L. Hourihan h A. C. Gehr w; V}

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