ML20203F621
| ML20203F621 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 04/23/1986 |
| From: | Agosti F DETROIT EDISON CO. |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| VP-86-0048, VP-86-48, NUDOCS 8604250198 | |
| Download: ML20203F621 (3) | |
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April 23, 1986 VP-86-0048 Director of Nuclear Reactor Regulation Ms. Elinor G. Adensam, Director Project Directorate No. 3 Division of BWR Licensing U. S. Nuclear-Regulatory Commission Washington, D.C.
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Dear Ms. Adensam:
Reference:
1)
Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43 2)
Detroit Edison to NRC Letter, " Request for Amendment to Fermi 2 Technical Specifications regarding the Source Range Monitor Downscale Rod Block Setpoint", VP-85-0236, dated December 23, 2985 3)
Detroit Edison to NRC Letter,
" Supplemental Information for Requested SRM Setpoint Technical Specification Amendment", VP-86-0007, dated February 4,
1986
Subject:
Modification of Requested SRM Setpoint Technical Snecification Amendment Detroit Edison has submitted a request for an amendment to Fermi 2 Technical Specifications 3/4.3.6, 3/4.3.7.6, and 3/4.9.2 (Reference 2), as well as, a supplemental information letter (Reference 3).
Detroit Edison has elected to replace the antimony-beryllium sources.
Consequently, the proposed change to Technical Specification 3/4.3.7.6 is not required.
However, as two of.the four Source Range Monitors (S RMs) are currently below the 0.7 cps.setpoint, and only one SRM can be bypassed, the proposed changes to Technical Speciffications 3/4.3.6 and 3/4.9.2 are required.
The change to specification 3/4.3.6 will allow performance of the required SRM functional tests without altering circuitry.
Also, this change is required to avoid a continual downscale alarm which could impair the operators ability to detect an anomolus condition.
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s Ms. Elinor G. Adensam April 23, 1986 VP-86-0048 Page 2 The change to Technical Specification 3/4.9.2 is required to permit the core alterations required to change sources.
Detroit Edison is therefore withdrawing the proposed Technical Specification change for 3/4.3.7.6.
Withdrawal of this proposed Technical Specification change does not alter the conclusions reached in the original amendment concerning plant safety or the lack of significant hazard considerations.
If you have further questions regarding this matter, please contact Mr. R. L. Woolley (313) 586-4211.
Sincerely, n -
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Mr. M. D. Lynch Resident NRC Inspector USNRC Document Control Desk Washington, D.C.
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e MS. Elinor G. Adensam April 23, 1986 VP-86-0048051 Page 3 I, FRANK E. AGOSTI, do hereby af firm that the foregoing statements are based on facts and circumstances which are true and accurate to the best of my knowledge and belief.
'ME FRANK E. AGOSTI Vice President Nuclear Operations On this M 3^d day of Ok
, 1986, befo e me personally appeared FRANK E. AGO$TI, being first duly sw<rn and says that he executed the foregoing as his free act scd deed.
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