ML20078G802
| ML20078G802 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 09/30/1983 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078G804 | List: |
| References | |
| TAC-51308, NUDOCS 8310130191 | |
| Download: ML20078G802 (5) | |
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[ga dcw#'o UNITED STATES
[ *,., [,j NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20555
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s, DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 72 License No. OPR-66 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application fdr amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated April 12; 1983, 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 encangering 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 amenament is in accorcance with lu CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
8310130191 830930 PDR ADOCK 05000334 P
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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. OPR-66 is herehy amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 72, are herehy 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 1
L v
rg Operating Reacto anch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 30, 1983 l
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a ATTACHMENT TO LICENSE AMENOMENT AMENOMENT NO. 72 TO FACILIiY OPERATING LICENSE NO. OPR-66 00CKET NO. 50-334 Revise Appendix A as follows:
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Insert Pages 3/4 7-26 3/4 7-26 3/4 7-29 3/4 7-29
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PLANT SYSTEMS 3/4.7.12 SNUBBERS LIMITING CONDITICN FOR OPERATION 3.7.12 All snubbers listed in' Tables 3.7-4a and 3.7-4b shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
(MODES 5 and 6 for snubbers located on systems ** required OPERABLE in those MODES).
ACTION:
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.12.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.12 Each enubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
a.
Visual Inspections The first inservice visual inspection of snubbers shall be perfor=ed af tar four months but within 10 months of commencing POWER OPERATION and shall include all snubbers listed in Tables 3.7-4a and 3.7-4b.
If less than two (2) snubbers are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months j; 25% from the date of the first inspection.
Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule:
No. Inoperable Snubbers Subsequent Visual per Inspection Period Inspection Period
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18 months j; 25%
1 12 months + 25%
2 6 months 125%
3,4 124 days j; 25%
5,6,7 62 days f; 25%
8 or more 31 days f; 25%
The snubbers may be categorized into two groups:
those accessible and those inaccessible during reactor operation.
Each group may be inspected independently in accordance with the above schedule.
- The inspection interval shall not be lengthened more than one step at a time.
- The provisions of Specification 4.0.2 are not applicable.
- These systems are defined as those portions or subsystems required to prevent releases in excess of 10 CFR 100 ' limits.
BEAVER VALLEY - UNIT 1 3/4 7-26 Amendment No. 72
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e PLANT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)
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e.
Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:
1.
The force that initiates free covecent of the snubber rod in either tension or compression is less than the specified
=ax1=um drag force.
2.
Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
3.
Snubber release rate, where required, is within the specified range in compression or tension.
For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without dispisce=ent shall be verified.
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Snubber Service Life Monitoring
- l A record of the service life of each snubber, the date at which
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the designated service life coc=ences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.m.
Concurrent with the first inservice visual inspect' ion and at least once per 18 enths thereafter, the installation and =aintenance records for each snubber listed in Tables 3.7-4a and 3.7-4b shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review.
If the indicated service life will be exceeded prior to the next scheduled snubber service life review, the snubber s6rvice life shall be reevaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review.
This reevaluation, replace =ent or reconditioning shall be indicated in the records.
For purposes of establishing a baseline for the determinatica cf service life mcnitoring, this program will be implemented over 3 successive refueling periods.
Amendment No. 72 REAVER VALLEY - UNRT 1 3/4 7-29
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