ML19340B183
| ML19340B183 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/14/1980 |
| From: | Burstein S WISCONSIN ELECTRIC POWER CO. |
| To: | Clark R, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8010210625 | |
| Download: ML19340B183 (2) | |
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Wisconsin Electnc mia couesnr 231 W. MICHIGAN. P.O. BOX 2046. MILWAUKEE. WI 53201 October 14, 1980 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION dashington, D. C.
20555 Attention:
Mr.
R. L.
Clark, Chief Operating Reactors Branch 3 Gentlemen:
DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT, UNIT 1 CYCLE 9 RELOAD The refueling shutdown at the end of Unit 1, Cycle 8, is planned to commence in mid-November 1980 at a cycle burnup of about 7,000 MND/T, within a range of -500 to +500 MWD /T.
Startup of Cycle 9 is expected to occur in mid-December 1980.
This letter is to advise you of our plans regarding the Unit 1, Cycle 9, reload core.
The Unit 1, Cycle 9 reload core will be designed to operate under current nominal design parameters, Technical Speci-fications and related bases, and current setpoints such that:
1.
Core characteristics will be less limiting than previously reviewed and accepted; or 2.
For those postulated accidents presented in the Final Facility Description and Safety Analysis Report (FFDS AR) which could be affected by the reload core, re-evaluation will demonstrate that the results of the postulated events will be within allowable limits.
Based on the Westinghouse Reload Safety Evaluation Report (RSER) for Unit 1, Cycle 9 and discussions with Westinghouse, safety evaluations will be performed b" our Nuclear Engineering Section 'nd our Point Beach Nuclear
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a Plant Supervisory Staff pursuant to the require-q7 Q ments of 10 CFR 50.59(a) and 10 CFR 50.59(b).
g The reload fuel mechanical and thermal-hydraulic design for the Cycle 9 reload core will be unchanged from that of previously reviewed and accepted relcad designs.
The reload core will meet 80102icnGldi 1
y s.
Mr. Harold-R. Denton October 14, 1980 reloa[dn:cleardesigns.
the F xP limit of-less than 2.32 which is consistent with previous The current F9H limit of less than 1.58 and penalties for rod bow will ensure that the DNB ratio will be greater than 1.30.
In accordance with past practice, the reload safety evaluation will rely on previously reviewed and accepted analyses reported in the FFDSAR and in earlier reload cycle RSER's.
A review will be made of the core characteristics to determine those parameters affecting the: postulated accident analyses reported in the FFDSAR.
The parametcr value will be verified to be within the conservatism of the initial assumptions used in the previous applicable safety analyses and, thus, the conclusions presented in the FFDSAR will remain valid.
The reload safety evaluation will demonstrate that Technical Specification changes will not be required for opera-tion of Unit 1 at full rated power during Cycle 9.
It will also demonstrate that unreviewed safety questions, as defined by 10 CFR-50.59, will not be involved and, therefore, application for an amendment to the Unit 1 operating license will not be required.
Consistent with the Confirmatory Orders of November 30, 1979, and January 3, 1980, and related correspondence, Unit 1 will continue to operate during Cycle 9 at reduced reactor coolant
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. pressure (2,000 psia).
We also expect to continue to operate at l
reduced. primary coolant system hot leg temperature.
Unit l'will not be o' 2ted with greater than 18% of the steam generator tubes piogged consistent with the latest ECCS analysis.
Verification of the core design will, of course, be performed by means of the standard startup physics tests normally performed at the start of each cycle.
The rod bank exchange method of performing rod worth measurements will be used for the Unit 1, Cycle 9 startup phyr'.cs tests.
Very truly yours,
o i
KAK-Sol Burstein Executive Vice Presid9nt Copy to: NRC Resident-Inspector.
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Point Beach Nuclear Plant