ML20080J945
| ML20080J945 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/09/1983 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| Shared Package | |
| ML20080J948 | List: |
| References | |
| NUDOCS 8309280469 | |
| Download: ML20080J945 (5) | |
Text
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7590-01 UNITED S'ATES OF AMERICA T
NUCLEAR REGULATORY C0fiMISSION In the Matter of
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VIRGINIA ELECTRIC & POWER
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Docket No. 50-281 COMPANY
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(Surry Power Station,
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Unit No. 2)
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EXEMPTION I.
The Virginia Electric and Power Company (the licensee) is the holder of Facility Operating License No. DPR-37 which authorizes operation of the Surry Power Station, Unit No. 2 (the facility).
This license provides, among other things, that the licensee is subject to all rules, regulations and Orders of the Conunission now or hereafter in effect.
The facility is a pressurized water reactor at the licensee's site located in Surry County, Virginia.
II.
On November 19, 1980, the Commission published a revised Section 10 CFR 50.48 and a new Appendix R to 10 CFR 50 regarding fire protection features of nuclear power plants (45 F.R. 76602).
The revised Section 50.48 and Appendix R became effective on February 17, 1981.
Section 50.48(c) established the schedules for satisfying the provisions of Appendix R.
This section is the subject of this exemption request.
Section 10 CFR 50.48(c)(4) requires that modifications requiring plant shutdown be completed before startup after the earliest of F
7590-01 the following events commencing 180 days or more after NRC approval:
1.
The first refueling outage.
2.
Another planned outage that lasts for at least 60 days; or 3.
An unplanned outage that lasts for at least 120 days.
By letter dated May 3,1983, as supplemented June 27, 1983, the licensee requested exemption from 10 CFR 10.48(c)(4) to allow Appendix R modification for Surry Unit 2 to be completed during the second refueling outage after May 17, 1983.
III.
By letter dated December 31, 1982, the licensee provided a schedule for completing Appendix R modifications for Surry Units 1 and 2.
These modifications were scheduled to be completed at the second refueling outage after January 1,1983, which would have been the same as the first refueling commencing 180 days after NRC approval of the modifications.
These would be the first refuelings after May 17, 1983, which were 1
anticipated to be September 22, 1984 for Unit 1 and October 19, 1984 for Unit 2.
The licensee's engineering and procurement dates were based on these schedules.
The modifications in the December 31, 1982, letter for which the exemption is requested are:
1.
Add circuits to the remote monitoring panel for instrumentation for steam generator pressure, reactor coolant cold leg temperature, and source range neutron flux, A-
7590-01.
2.
Install diesel generator control circuit to local panel, 3.
Replace main breakers on Vital Bus Panels with molded case switches, and 4.
Replace Class lE Motor Control Center 480/120(v) control with encapsulated transformers or fuses.
Unit 2 was scheduled to be refueled on May 1, 1983, which would have put the date before May 17, 1983, (180 days after flRC approval) and made the first refueling after May 17, 1983, occur in October 1984.
However, because Unit I was shutdown for an extended period of time, the refueling shutdown of Unit 2 was delayed past flay 17,1983, in order to not have both units shut down at one time.
The licensee's letter dated June 27, 1983, specified the need for Unit 2 to operate past the May 17, 1983 date. This schedule put the refueling of Unit 2 in June 1983 and makes it the first refueling after May 17, 1983.
This delay resulted in the licensee requesting the exemption.
The licensee's letter dated June 27, 1983 stated that the refueling outage scheduled for October 1984 is now scheduled for March 1985.
We have considered the request by the licensee to be exempted from the schedular requirement of 10 CFR 50.48(c)(4) and the basis for the exemption. Since the modifications were scheduled for Unit 2 in late 1984 (now early 1985), we conclude that granting this exemption does not essentially change the schedule for the modifications but only changes the number of the refueling at which the modifications are to be completed.
Granting this exemption does not change any interim or backup fire protection measures in place. Therefore, we conclude that this exemption should be granted.
7590-01 IV.
Accordingly, the Commission has determined that, pursuant to 10 CFR 5012, an exemption is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest and hereby grants the following exemption with respect to 50 CFR 48(c)(4):
Change the implementation date for the modifications delineated in Section III of this Exemption to the second refueling commencing after May 17, 1983.
The NRC staff has determined that the granting of this Exemption will not result in any significant environmental impact and pursuant to 10 CFR 51.5(d)(4) an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with this action.
FOR THE NUCLEAR REGULATORY COMMISSION
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Harold R. Denton, Director
! Office of Nuclear Reactor Regulation Dated at Bethesda, Maryland this 9th day of September,1983
IV.
Accordingly, the Comission has determined that, pursuant to 10 CFR 50.12. an exemption is authorized by law and will not endanger life I
or property or the common defense and security and is otherwise in the public interest and hereby grants the following exemption with respect I
to 50 CFR 48(c)(4):
Change the implementation date for the modifications delineated l
in Section III of this Exemption to the second refueling commencing after May 17, 1983.
The NRC staff has determined that the granting of this Exemption will not result in any significant environmental impact and pursuant to 10 CFR 51.5(d)(4) an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with this action.
FOR THE NUCLEAR REGULATORY COMMISSION 0fe m
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Harold R. Denton, Dibector
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Office of Nuclear Reactor Regulation i
Dated at Bethesda, Maryland I
this 9th day of September,1983 I
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