ML20070D975
| ML20070D975 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 12/07/1982 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Atlantic City Electric Co, Delmarva Power & Light Co, Philadelphia Electric Co, Public Service Electric & Gas Co |
| Shared Package | |
| ML20070D977 | List: |
| References | |
| DPR-56-A-086 NUDOCS 8212160544 | |
| Download: ML20070D975 (4) | |
Text
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[%'g UNITED STATES NUCLEAR REGULATORY COMMISSION 0. \\ "( #
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WASHINGTON, D. C. 20555 PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 86 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 October 19, 1982, as supplemented December 3, 1982, 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 will operate in confomity 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; 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; i
and l
E.
The issuance of this amendment is in accordance with 10 CFR Part l
51 of the Commission's regulations and all applicable requirements have been satisfied.
l 2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-5G is:
I hereby amended to read as follows:
l l
8212160544 021207 PDR ADOCK 05000278 P
PDR atfDBeCME
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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 86. are hereby incorporated in the license.
PECO 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 J
F. Stolz, Chief
,/ oOperating Reactors Bran#4 HDivision of Licensing.
Attachment:
Chanaes to the Technical Specifications Date of Issuance: December 7,1982 G
S
ATTACHMENT TO LICENSE AMENDMENT NO.36 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
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Remove Insert 234a 234a e
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PBAPS LIMITING CONDITIONS FOR OPERATIONS SURVEILLANCE REQUIREMENTS 3.11. 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-requirements apply to hydraulic fuel, snubbers listed in Table snubbers described in 3.11.D.l.
3.ll.D.1 shall be operable ex-cept as noted in 3.ll.D.2
- 4. l l. 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 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 detemined connections, and linkage connec-effort shall be made to repair tions to the piping and anchor or replate the snubber as soon to verify snubber operability in as possible.
accordance with the following schedule:
3.11.D.3 If the requirements of 3.ll.D.1 and 3.11.D.2 cannot be met, an orderly shutdown shall 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 during this period.
Inspection Interval Inspection Interval
- l 3.ll.D.4 If a snubber (as defined in 0
18 Months + 5 months 4.ll.D.1) is detemined to 1
12 Months T 3 Months be inoperable while the reactor 2
6 Nonths 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
,L operable prior to reactor
>8 1 Month i1 Week startup.
3.11 S.5 Snubbers may be added to safety related systems without prior Through February 12, 1983, continued power License Amendment to Table 3.ll.D.1 provided that a're-operation without perfoming the visual vision to Table 3.ll.D.1 is snubber inspection on snubbers categorized included with the next as " inaccessible for inspection during License Amendment request.
reactor operation", is permitted on Unit 3, except in the event Unit 3 reactor exoer.i-ences a shutdown requiring containment entry prior to February 12, 1983, in which case, the inspection shall be performed during the outage.
Amendment No. N, 77, 86
-234a N
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