ML19331E024
| ML19331E024 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/14/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19331E025 | List: |
| References | |
| NUDOCS 8009050217 | |
| Download: ML19331E024 (4) | |
Text
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UNITED STATES y
',g NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20555 k*...../
PHILADELPHIA ELECTRIC COWANY PUBLIC SERVICE ELECTRIC AND GAS COWANY_
DELI %RVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COWANY DOCKET NO. 50-218 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 71 License No. DPR-56 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated July 22, 1980 (telecopy dated July 18, 1980),
complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Consnission's rules and regu-lations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application,
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the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) 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; D.
The issuance of this amendment will not be inimical to the common defense and security o-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 satisfied.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicatad in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows:
(2) Technical Specifications j
l The Technical Specifications contained in Appendices A and l
B, as revised tnrough Amendment No. 71, are hereby incorporated in the license.
PEC0 shall operate the facility in accordance with the Technical Specifications.
l esososo 2.\\7
3.
This license amendment is effective July 19, 1980.
FOR THE NUCLEAR REGULATORY COPfilSSION
.Ro ert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 14, 1980 i
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ATTACHMENT TO LICENSE AMENDMENT N0.
71 FACILITY OPERATING LICENSE'NO. DPR-56 DOCKET NO. 50-278 j_
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1 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page.
The revised page is identified by amendment number and contains vertical lines indicating the area of change.
Remove Page Insert'Page i
234a 234a i
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PBAPS O
LIMITING CONDITIONS FOR OPERATIONS SURVEILLANCE REQUIREMENTS 3.ll.D Shock Suppressors (Snubbers) 4.11.D Shock Suppressors (Snubbers)
'on Safety Related Systems on Safety Related Systems 3.ll.D.1 During all modes of operation, The following surveillance except Cold Shutdowns and Re-reonirements apply to hydraulic fuel, snubbers listed in Table snubbers described in 3.11.D.1.
3.11.D.1 shall be operable ex-cept as noted in 3.ll.D.2 4.11.D.1 All hydraulic snubbers whose through 3.ll.D.4 below.
seal material has been demon-strated by operating experience, 3.ll.D.2 From and after the time that lab testing or analysis to be a snubber is determined to be compatible with the operating inoperable, continued reactor environment shall be visually operation is permissible only inspected.
The inspection shall during the-succeeding 72* hours l include, but not necessarily unless the snubber is sooner be limited to, inspection of the made operable or replaced.
hydraulic fluid reservoir, fluid During this period a detennined connections, and linkage connec-effort shall be made to repair tions to the piping and anchor or replace the snubber as soon to verify snubber operability in as possible.
accordance with the following schedule:
3.ll.D.3 If the requirements of 3.ll.D.1 and 3.11.D.2 cannot be met, an orderly shutdown shai: be init-iated which would bring the re-Number of Snubbers actor to the cold shutdown con-Found Inoperable dition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> unless During Inspection the snubber is made operable or During Next Required j
during this period.
Inspection Interval Inspection Interval 3.11.D.4 If a snubber (as defined in 0
18 Months + 5 months 4.ll.D.1) is determined to 1
12 Months T 3 Months be inoperable while the reactor 2
6 lbnths T 2 Months is in the shutdown or refuel 3, 4 4 Months T 1 Month mode, the snubber shall be made 5,6,7 2 Months T 2 Weeks operable prior to reactor
>8 1 Month - 1 Week startup.
3.ll.D.5 Snubbers may be added to safety
- During the period July 17 to July 26, related systems without prior 1980, Snubber #10-GB-S-44 is permitted License Amendment to Table to be inoperable for 10 days.
3.ll.D.1 provided that a re-vision to Table 3.ll.D.1 is include /. with the next License Amendment request.
Amendment No.
71
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