ML20247Q000
| ML20247Q000 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/31/1989 |
| From: | Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20247Q005 | List: |
| References | |
| B12814, NUDOCS 8908070023 | |
| Download: ML20247Q000 (3) | |
Text
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- Selden Street, Berkn, Connecticut P.O. BOX 270 Um7((uZE.',,
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July 31, 1989 4
Docket No. 50-245 B12814 Re:
.U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:
Millstone Nuclear Power Station, Unit No. 1 Proposed Revision to Technical Specifications Auxiliary Electrical System Pursuant to 10CFR50.90, Northeast Nuclear Energy Company (NNECO) hereby proposes to amend its Operating License DPR-21 by incorporating the changes identified in Attachment 1 into the Technical Specifications of Millstone Unit No. 1.
Backaround In processing a previous license amendment request, an apparent oversight ras id2ntified by the NRC Staff.
In 1974 the distribution voltage on the primar, side of the Emergency Station Services Transformer (ESST) was changed from 27.6 kV to 23 kV. There exists no supporting correspondence to establish that NNEC0 requested a license amendment at that time to reflect this voltage conversion into the Technical Specifications.
The purpose of this proposed change is to reconcile the Technical Specifications to existing conditions.
_D_eS g_iption of Chanael All instance:; in the Technical Specifications which mention the voltage of the transmission line involved (the Flanders line) are proposed to be changed from 27.6 k'l to 23 kV. Specific pages affected are listed below:
o Page 3/4 7-12, Section 3.7.B.4 o
Page 3/4 9-1, Section 3.9.A.3 o
Page 3/4 9-3, Section 1.9.B.4 o
Pege B 3/4 7-5, Section 3.7.B o
Page B 3/4 9-1, Section 3.9.A Safety Assessment The purpose of this proposed change is to revise the Millstone Unit No.1 Technical Specifications to reflect the correct voltage for the prinry side Aii 8908070023 890731
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U.S. Nuclear Regulatory Commission B12814/Page 2 July 31,1989 of the ESST as indicated.
The ESST serves as the alternate off-site power i
supply for Millstone Unit No.1.
The ESST high side is connected to the Flanders substatien.
In 1974 the distribution voltage was changed from 27.6 kV to 23 kV.
The change was brought about by the construction of the Flanders 115-kV substation (S/S) which was built in the early 1970s to meet an increase in area load demand. When the Flanders S/S was put into service, the original 27.6-kV feeder from Bokum S/S was retired and replaced with a 23-kV supply from the new Flanders 115-kV S/S.
This change did not affect the low-side voltage rating. The ESST continues to perform its intended function with the lower voltage and has done so for 13 years with no adverse effects.
The change has had, and will have, no impact on the plant or its safety systems nor does the new supply, although somewhat lower in voltage, impact the power rating of the feeder line (Flanders line).
Low-side voltage on the ESST, which can supply safety system loads, remains at 4.16 kV.
Significant Hazards Consideration NNECO has reviewed the proposed change in accordance with 10CFR50.92 and has concluded that it does not involve a significant hazards consideration in that the change would not:
1.
Involve a significant increase in the probability or consequences of an accident previously analyzed.
Since the capacity and low-side voltage ratings remain the same and only the high-side voltage has been reduced, the ESST still serves its intended function.
The change is administra-tive in nature and corrects an oversight from the tirne when physical changes were made to the ESST supply line.
2.
Create the possibility of a new or different kind of accident from those previously analyzed, in that the proposed change corrects the Technical Specifications to reflect the actual voltage of the ESST supply, and does not affect the ESST purpose of providing alternate off-site power to Millstone Unit No. 1.
The change does not modify plant response nor does it have any new failure modes associated with it.
3.
Invulve a significant nduction in the margin of safety.
The margin of safety is not affected by this proposed change in that the change is only in the wording of the Technical Specifications and has no effect on plant operatiom The Commission has provided guidance concerning the 3.pplication of standards in 20CFR50.92 by providing certain examples (51FR7751, March 6,1986).
The proposed amendment is enveloped by Example (i),
"a purely administrative change to Technical Specifications; for example, a change to achieve consis-tency throughout the technical specifications, correction of an error, or a change in nomenclature." The proposed change conforms the Technical Specifi-catior.s to existing conditions and is being proposed to correct an oversight
I U.S. Nuclear Regulatory Commission B12814/Page 3 l
July 31,1989 in notification of the NRC Staff of a change which has been made, but has no adverse effect on plant safety.
Although the Staff has not been formally notified of this change prior to this letter, no adverse effects on plant safety or the public have resulted.
Moreover, the current FSAR for Millstone Unit No. I correctly reflects the 23-kV distribution voltage.
The Millstone Unit No.1 Nuclear Review Board has reviewed and approved the proposed change and has concurred with the above determinations.
A comparison of this proposed change to other units at the Millstone Nuclear Power Station is not applicable as this condition is specific to Millstone Unit No. 1.
This change is being proposed to correct the Millstone Unit No.1 Technical Specifications and has no effect on plant operation.
As such, no specific schedule for approval and issuance is requested.
Due to the nature of these proposed changes, they can be effective upon issuance.
In accordance with 10CFR50.91(b), we are providing the State of Connecticut with a copy of this proposed amendment.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY GW Senior Vice Pres //
E. T.,Mroczke ident cc:
W. T, Russell, Region I Administrator M. L, Boyle, NRC Project Manager, Millstone Unit No.1 W. J. Raymond, Senior Resident Inspector, Millr,touc Unit Nos. 1, 2, and 3 STATE OF CONNECTICUT)
) ss. Berlin COUNTY OF HARTFORD )
Then personally appeared befere me, E. J. Mroczka, who being duly sworn, did state that he is Srnior Vice President of Nort! wast Nuclear Energy Company, a Licensee herein, that he is authorized to execute and file the foregoing information in the nama and on behalf of the Licensees herein, and that the statements contained in said information are true and correct to the best of his knowledge and belief.
/MmNo b
72 Notary Publ
My Commission
'res March 31,1993
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