ML17250B244
| ML17250B244 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/28/1991 |
| From: | Shankman S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17250B245 | List: |
| References | |
| NUDOCS 9109060194 | |
| Download: ML17250B244 (5) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R. E.
GINNA NUCLEAR PO>IER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 45 License No.
DPR-18 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
The application for amendment filed by the Rochester Gas and Electric Corporation (the licensee) dated October 16, 1985, as supplemented on January 14, 1991 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility wil.l operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been sati sf ied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Faci lity Operating License No, DPR-18 is hereby amended to read as follows:
(2)
Technical S ecifications
=The Technical Specifications contained in Appendix A, as revised through Amendment No. 45, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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3.
This license amendment is effective immediately and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Lfc~1 Susan F.
- Shankman, Acting Director Pro'ect Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance August 28, 1991
ATTACHMENT TO LICENSE AMENDMENT NO. 45
, FACILITY OPERATING LICENSE NO: DPR-18 DOCKET NO. 50-244 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove
- 3. 6-1 3.6-3 Insert 3.6-1 3.6-3
t s s a
3.6 Containment S stem ll. alii H
Applies to the'ntegrity of reactor containment.
Ob ective:
To define the operating status of the
- reactor containment for plant operation.
S cification:
3.6.1 Containment Inte rit a ~
Except as allowed by 3'. 6. 3 containment integrity shall not be violated unless the reactor is in the cold shutdown condition.
b.
c ~
The containment integrity shall not be violated when the reactor vessel head is removed unless the boron concentration is greater than 2000 ppms'ositive reactivity changes shall not be made by rod drive motion or boron dilution whenever the containment integrity is not intact unless the boron concentration is greater than 2000 ppm.
3.6.2 Internal Pressure If the internal pressure exceeds I psig or the
)
internal vacuum exceeds 2.0 psig, the condition shall'e corrected within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the reactor rendered subcritical.
Amendment No.
45 3.6-1
a'e r'asis:
The reactor coolant system conditions of cold shutdown assure that no steam wilX be formed and hence there would be no buildup in the containment if the reactor coolant system ruptures.
The shutdown margins are selected based on the type of activities that are being carried out.
The (2000 ppm) boron concentration provides shutdown margin which precludes criticality under any circumstances.
When the reactor head is not to be removed, a cold shutdown margin of 1%~k/k precludes criticality in any occurrence.
Regarding internal pressure limitations, the containment design pressure o2 60 psig would not be exceeded if the internal pressure before a ma)or steam break accident were as much as 1 psig.~~>
The,f containment is designed to withstand an internal.
vacuum of 2.5
'sig.'
The 2.0 psig vacuum is specified as an operating limit to avoid any difficulties with motor cooling.
References:
(1)
Westinghouse Analysis, "Report for the BAST Concentration Reduction for R. E. Ginna," August 1985.
('2)
UPSAR - Section 6.2.1.4.
Amendment No.
45 3.6-3