ML20127G871
| ML20127G871 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/17/1985 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | Harold Denton, John Miller Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20127G875 | List: |
| References | |
| CON-NRC-85-1 TAC-59060, TAC-59061, VPNP-85-2, NUDOCS 8506260116 | |
| Download: ML20127G871 (3) | |
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WlSCORSin Electnc mm came 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 June 17, 1985 NRC-85-1 VPNP-85-2 CERTIFIED MAIL Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C.
20555 Attention:
Mr. J. R. Miller, Chief Operating Reactors, Branch 3 Gentlemen:
DOCKET NOS. 50-266 AND 50-301 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 105 REACTOR VESSEL SURVEILLANCE CAPSULE REMOVAL SCHEDULE POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 In accordance with Sections 50.59 and 50.90 of 10 CFR 50, Wisconsin Electric Power Company (Licensee) hereby requests amend-ments to Facility Operating Licenses DPR-24 and DPR-27 for the Point Beach Nuclear Plant, Units 1 and 2, respectively.
These amendments would change the removal schedule for the reactor vessel surveillance capsules of both units and are in accordance with the regulations set forth in 10 CFR 50 Appendix H and the guidance of ASTM E185-82.
Proposed Technical Specification pages, with the changes identified by margin bars, are enclosed with this application.
The current surveillance capsule removal schedules for Units 1 and 2 are contained in Tables 15.3.1-1 and 15.3.1-2, re-spectively.
The approximate removal dates of Capsules T and P for
. Unit 1 and of Capsules P and S for Unit 2 currently correspond to 70% and 90% of the maximum integrated fast neutron fluence on the inside surface of the reactor vessel at end-of-life, i.e.,
40 operating years.
That schedule conforms to 10 CFR 50 Appendix H as it was in 1981.
On May 31, 1983, a revision to 10 CFR 50 Appendix H deleted the surveillance capsule withdrawal schedules previously prescribed therein, and incorporated by reference ASTM E185-82,
" Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels".
ASTM 185-82 states that "... The withdrawal schedule of the final two capsules is adjusted by the lead factor so the exposure of the second to last E
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Mr. H. R. Denton June 17, 1985 capsule does not exceed the peak end-of-life (EOL) fluence on the inside surface of the vessel, and so the exposure of the final capsule does not exceed twice the EOL vessel inside surface peak fluence.
The decision on when to test specimens from the final capsule need not be made until the results from the preceding capsules are known."
The change we are requesting would extend the approxi-mate removal dates for the final capsule in Unit 1 to a period corresponding to 110% of the peak EOL fluence on the inside surface of the vessel.
The change would extend the approximate removal dates for the last two capsules in Unit 2 to the periods corresponding to 90% and 110% of the peak EOL fluence on the inside of the vessel.
It should be noted that with the implementation of low leakage cores in both units in 1979 the lead factors originally used in determining the reactor vessel surveillance capsule removal schedules are no longer applicable.
Additionally, the reduced operating temperature and consequent reduced power operation of Unit 1 for four cycles have also invalidated the present Unit 1 capsule withdrawal schedule.
Furthermore, due to extended outages for steam generator maintenance on both units, the capsule withdrawal schedule no longer corresponds with the outage schedule.
Following the schedule as is would result in the capsules being withdrawn earlier than necessary.
Extending the schedules as requested would enable data to be obtained at greater specimen exposures thereby providing more useful infor-mation later in plant life.
We have also included a revised technical specification basis page which changes the maximum integrated fast neutron exposure of the vessel.
This change is based upon calculations performed by Westinghouse and reported in WCAP-10638, " Adjoint Flux Program for Point Beach Nuclear Plant, Units 1 and 2".
As required by 10 CFR 50.91(a) (1), we have prepared the following discussion concerning the issue of whether or not these proposed changes involve any significant hazards considera-tions.
Such a determination is made using the standards and cri-teria specified in 10 CFR 50.92.
The Nuclear Regulatory Commission has provided guidelines concerning the application of these stan-dards_in 48 Federal Register 14870.
Among the examples cited that are considered as very likely not to involve any significant hazards considerations is "a change to make a license conform to changes in the regulations, where the license change results in very minor changes to facility operations clearly in keeping with the regulations."
The requested change to the reactor vessel surveillance capsule withdrawal schedule is similar to this example.
This change was prompted by the change to Appendix H of 10 CFR 50.
Additionally, these requested changes obviously involve no significant hazards considerations as set forth in
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Mr. H. R. Denton June 17, 1985 10 CFR 50.92 (c).
The proposed amendment would not:
(1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety.
Enclosed are three signed originals and, under separate cover, forty copies of this amendments application.
Also en-closed is a check in the amount of $150 for the application fee specified in 10 CFR 170.12.
Additionally, since the current schedule requires that the next surveillance capsule for Unit 2 be removed during the next outage, we request that this amendment be approved prior to Unit 2's next refueling outage currently scheduled to begin on September 20, 1985.
Please contact us if you have any questions concerning these proposed changes.
Very truly yours, Vice President - Nuclear Power C. W. Fay 4
Enclosures (Check No. 852129 )
Copies to NRC Resident Inspector R.
S. Cullen, PSCW Subscribed and sworn to before me this 2ct4 day of June 1985.
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