ML20091Q459
| ML20091Q459 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/07/1984 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | Harold Denton, John Miller Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20091Q462 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 TAC-54559, TAC-54560, NUDOCS 8406140038 | |
| Download: ML20091Q459 (2) | |
Text
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e' Msconsm Electnc mwww 231 W. MICHIGAN, P.O. BOX 2046. MILWAUKEE, WI 53201 June 7, 1984 Mr. H.
R. Denton, Director 1
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 MODIFICATION TO TECHNICAL SPECIFICATION CHANGE REQUEST 96 TMI BACKFIT SPECIFICATIONS POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 In a letter dated February 29, 1984, Wisconsin Electric Power Company', licensee for the Point Beach Nuclear Plant Units 1 and 2, applied for amendments to Facility Operating Licenses DPR-24 and DPR-27 to incorporate changes into the Point Beach Nuclear' Plant Technical Specifications.
These changes were prinarily concerned with accident monitoring instrumentation which is being installed'in response to NUREG-0737.
Proposed Technical Specification page changes were included with that letter.
Subsequent to our transmittal of that request, we have determined that the proposed specification regarding-the reactor coolant gas vent system, specification 15.3.1.A.7, is not as clear as it could be and should be modified.
We have also determined that an error was made in the surveillance specification for the containment hydrogen monitor, Item 41 of Table 15.4.1-1, and a correction should be made.
Specifically, the sample gas for calibration of the hydrogen monitor has concentrations of 2%
and 6% hydrogen, not 1% and 4% as originally proposed; and the
~
calibration frequency should be listed as "R/Q", with the electronic calibration completed each refueling interval, and the gas calibration done quarterly.
We have reviewed the 10 CFR 50.91 significant hazards consideration determination provided with our February 29 application.
The modifications to our change request provided with this letter do not change the basis or conclusion of that determination.
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'Mr.' H.
R.'Denton, Director 2-June'7, 1984
. We.have: enclosed three signed originals and 40 copies of~this modification to Technical Specification Change a
- Requests 96; the revised Technical Specification pages supersede -
' those; corresponding-pages provided-with our February 29 letter.
Please contact me if you have7any' questions concerning these
- changes.-
s Very truly.yours, lh Vice President-Nuclear Power C. W. Fay
[ Attachment' Copie's1 to 'NRC Resident Inspector
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-c C.-F.-Riederer, PSCW
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. Subscribed aiid sworn'to before me
~:this2// % day"of June"1984.
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