ML19323C739
| ML19323C739 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/23/1980 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19323C740 | List: |
| References | |
| NUDOCS 8005190105 | |
| Download: ML19323C739 (5) | |
Text
i 8 0051 g o loS Sa rergjo UNITED STATES g
g NUCLEAR REGULATORY COMMISSION e E WASHINGTON, D. C. 20555 L
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JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO PROVISIONAL OnERATING LICENSE Amendment No. 46 License No. DPR-16 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Jersey Central Power & Light Company (the licensee) dated January 29, 1980, complies with the standards and requirements of the-Atomic Energy Act of 1954,.as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; 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 Comission's regulations and all applicable requirements have been satisfied.
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated.in the attachment to this license amendment and paragraph 3.B. of Provisional Operating License No.
DPR-16 is hereby amended to read as follows:
3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through. Amendment No. 46,.are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION g
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Dennis L. Ziemann Chief Operating Reactors Branch #2 Division of Operating Reactors Attachment-Changes t
.chnical Specif'.
aons Date of Issuance:
April 23, 1980 l
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I ATTACHMENT TO LICENSE AMENDMENT NO. 46 PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The. revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.
PAGES 3.5-7 3.5-14 O
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3.5-7 containment is required during fuel handling operations and whenewr work is being performed on the reactor or its connected systems in the reactor building'since their operation could result in inadvertent release of radioactive material.
The standby gas treatment system (6) filters and exhausts the reactor building attosphere to the stack during secondary containment isolation conditions, with a minimum release of radioactive materials from the reactor building to the environs.
capacity.g filter trains are provided each having 100%
Twm separe If one filter train becomes inoperable, there is no immediate threat to secondary containment and reactor operation may continue while repairs are being made.
Since the test interval for this system is one month (Specification 4.5), the time out-of-service allowance of 7 days is based on considerations presented in the Bases in Specification 3.2 for a one-out-of-two system.
References:
(1) FDSAR, Volume I, Section V-1 (2) FDSAR, Volume I, Section V-1.4.1 (3) FDSAR, Volume I, Section V-1.7 (4) Licensing Application, Amendment 11, Question III-25 (S) FDSAR, Volume I, Section V-2 (6) FDSAR, Volume I, Section V-2.4*
(7) Licensing Application, Amendment 42 (8) Licensing Application, Amendment 32, Question 3 (9) Robbins, C. H., " Tests on a Full Scale 1/48 Segment' of the Humboldt Bay Pressure Suppression Containment,"
GEAP-3596, November 17, 1960.
(10) Bodega Bay Preliminary Ha:ards Summary Report, Appendix 1, Docket 50-205, December 28, 1962.
(11) Report H. R. Erickson, Bergen-Paterson to K. R.
Goller, NRC, October 7, 1974.
Subject:
Hydraulic Shock Sway Arrestors..
In conjunction with the Mark I Containment Short Term Program, a plant unique analysis was performed on August 2, 1976, which demonstrated a factor of safety of at least two for the weakest element in the suppression chamber support system. The maintenance of a drywell-suppression chamber l
differential pressure within the range shown on Figure 3.5-1 with a -
suppression chamber water level corresponding to a downcomer submergence range of 3.0 to S.3 feet will assure the integrity of the suppression chamber when subjected to post-LOCA suppression pool hydrodynamic forces.
Amendment No. U,18,32,46
AS-14 I
I REQUIRED DRYWELL TO TORJS DIFFERENTIAL PRESSURE i
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ACCEPTABLE OPERATING RANGE m.
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0.9 3.0 3.4 3.8 4.2 4.8 S.0 S.4 DOWNCOMER SUBMERGENCE, FT.
FIGURE 3.5-l
- The actual acceptable range of downcomer submergence is governed by the Technical Specifications limit on maximum and minimum water volume in the torus (see section 3.5.A.1).
This actual acceptable range of downcomer submergence will not encompass the full range of downcomer submergence indicated in the figure above.
AMENOMENT NO. 46
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