ML20043C063
| ML20043C063 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 05/25/1990 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20043C064 | List: |
| References | |
| NUDOCS 9006010263 | |
| Download: ML20043C063 (5) | |
Text
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION a
WASHING TON, D. C. 20666
's,.....,e PHIL ADELPHI A EL ECTRIC COMPANY PUBl1C 5ERVICE ELECTRIC AND GA5 COMPANY DELMARVA POWER AND L15HT COMPANY ATL ANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERAT1HG LICENSE Amendment No.156 License No. DPR-56 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated April 12, 1990..as supplemented on May 18, 1990, 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 Comissinn; 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 comon 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated 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:
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2 (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.156. 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Walter R. Butler. Director j
Project Directorate 1-2 Division of Reactor Projects. 1/II
Attachment:
Changes to the Technical Specifications Date of issuance: May 23, 1990 a
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8 (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.156, are hereby incorporated in the license.
PECO shall operate the facility in accordance with the.
i Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/S/
Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects 1/11
Attachment:
Changes to the Technical Specifications Date of issuance: May 25, 1990
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', 7 ATTAtl! PENT,TO LICENSE AMENDMENT N0.156 j
QCILITYOPERATINGLICENSENO.'DPR-56:
DOCKET NO. 50-278 Peplace the following page of the Appendix A Technical Specifications with the enclosed page. The revised areas are indicated by marginal lines..
Page 234a L
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PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.11.D.
Shock Suppressors 4.11.D.
Shock Suppressors,
u (Snubbers) on Safety Related (Snubbers) on Safety Related i
l Systems Systems l
3.11.D.1 During all modes of 4.11.D.1 operation all snubbers on safety related systems shall be operable except Snubbers required to be j
as noted in 3.11.D.2 and 3.11.D.3 operable under the provisions below.
Snubbers on non-safety related.
of 3.11.D.1 shall be demonstrated systems are excluded from this requirement 0PERABLE by performance of the if-their failure or failure of the system
- following. augmented inservica on which installed has no adverse effect inspection program and the on a safety-related system.
requirements of: Specification i
4.6.G.
q 3.11.D.2 During operation in the cold _
L4.11.D.2 shutdo@ or refueling modes, snubbers locateo on systems required to be operable Snubbers required to be.
shall be operable except-as noted in operable under the provisions' 3.11.D.3.
of 3.11.D.1 chall be visually-
. inspected according to the.
3.11.D.3 With one or more snubbers following schedule.
l inoperable under the requirements of 3.11.D.1, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, replace No. of Snubbers Next Visual or restore the inoperable snubber to-iFound~ Inoperable
. Inspection the operable status and perform an During Inspection -Period *
[
j engineering evaluation per specification'.
Period l
4.11-D.6.
If these requirements cannot be met, declare the supported system 0
18 mo. i 25%.
inoperable and follow the applicable 1
12.mo. i 25%
l
'.imiting Condition for Operation for 2
6~mo. t 25%
that System.
3,4
.4 mo,.11 25%
5,6,7 2 mo. t 25%
8 or more
'l mo.
- 25%-
The required inspection interval shall:not be. lengthened morefthan one step at 'a time.
Tne provi-sions-for extending surveillance-frequency included in action 1.0 Definitions do not 6ppij.
Snub-bers may be categorized in two l
groups, " accessible" or !'inacces-i sible",. based on their~ accessibility for inspection during reactor operation. These two groups may be inspected independently-according to the above schedule.
- Those surveillances on in-accessible snubbers which must be performed on or before May'26, 1990.and are re gired by TS 4.11.D.2 may be delayed for a period not to exceed December 31, 1990.
-234a-Amendment No 7/, 77, ##, fG1, fff,156
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