ML20214T820
| ML20214T820 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 05/29/1987 |
| From: | Virgilio M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214T823 | List: |
| References | |
| NUDOCS 8706100442 | |
| Download: ML20214T820 (5) | |
Text
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NUCLEAR REGULATORY COMMISSION t
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.....p CLEVELAND ELECTRIC ILLUMINATING COMPANY, ET AL DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 5 License No. NPF-56 1.
The Nuclear Regulatory Commission (the Commission) has found that A.
The application for amendment by Cleveland Electric Illuminating Company, Duquesne Light Company, Ohio Edison Company, Pennsylvania Power Company, and Toledo Edison Company (the licensees) dated May 4,1987, 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; 8.
The facility will operate in conformity 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; 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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-58 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A and the Environ-mental Protection Plan contained in Appendix B, as revised through Amendment No. 5 are hereby incorporated into this license.
Cleveland Electric Illuminating Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8706100442 870529 PDR ADOCK 05000440 p
. 3.
This license amendment is effective as of May 31, 1987.
FOR THE NUCLEAR REGULATORY ColeilSSION op Mart n J. Virgilio, Acting Director Project Directorate III-1 Division of Reactor Projects - III, IV, V
& Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 29,1987
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ATTACf94ENT TO LICENSE AMENDMENT NO. 5 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 Replace the following page of the Appendix "A" Technical Specifications with the attached page.
The revised page is identified by Amendment number and contains vertical lines indicating the areas of change.
Overleaf page provided to maintain document completeness.
Remove Insert 3/4 6-5 3/4 6-5 v
V CONTAINMENT SYSTEM 5 SURVEILLANCE REQUIREMENTS (Continued) 1.
Confirms the accuracy of the test by verifying that the differ-t ence between the supplemental data and the Type A test data is I
within 0.25 L,.
The formula to be used is:
[L, + L, - D.25 L,] 1 Lc I El
+l
+ 0.25 L,] dere L
=
o as c
supplemental test result; L, = superimposed leakage; L,, =
measured Type A leakage.
2.
Has duration sufficier.t to establish accurately the change in leakage rate between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the primary contain-ment or bled from the primary containment during the supple-mental test to be between 0.75 L, and 1.25 L,.
d.
Type B and C tests shall be conducted with gas at P, 11.31 psig*,
at intervals no greater than 24 months except for t$sts involving:
1.
Air locks, 2.
Main steam line isolation valves, j
3.
Valves pressurized with fluid from a seal system, i
4.
All containment isolation valves in hydrostatically tested lines per Table 3.6.4-1 which penetrate the primary containment, and 5.
Purge supply and exhaust isolation valves with resilient material seals.
e.
Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.
f.
Main steam line isolation valves shall be leak tested at least once per 18 months.**
g.
Leakage from isolation valves that are sealed with fluid from a seal system may be excluded, subject to the provisions of Appendix J of 10 CFR 50 Section III.C.3, when determining the_ combined leakage rate provided the seal system and valves are pressurized to at 13ast 1.10 P maintain,12.44psig,andthesealsystemcapacityisadequateto system pressure for at least 30 days.
h.
All containment isolation valves in hydrostatically tested lines per Table 3.6.4-1 which penetrate the primary containment shall be leak l
tested at least once per 18 months.
i.
Purge supply and exhaust isolation valves with resilient material-seals shall be tested and demonstrated OPERABLE per Surveillance Requirements 4.6.1.8.3.~and 4.6.1.8.4.
j.
The provisions of Specification 4.0.2 are not applicable to Specifications 4.6.1.2.a. 4.6.1.2.b, 4.6.1.2.c, and 4.6.1.2.d.
"Unless a hydrostatic test is. required per Table 3.6.4-1.
- Except for valves 1821-F022A and 1821-F028A, which shall Le leak tested prior to July 12, 1987. This exception expires on July 12, 1987.
PERRY - UNIT 1 3/4 6-5 Amendment No. 5
i l
CONTAlletENT SYSTEMS PRIMARY CONTAlfetENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each primary co'ntainment air lock shall be OPERABLE with:
a.
Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and b.
An overall air lock leakage rate of less than or equal to 2.5 scf per hour at P,, 11.31 psig.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, and f.
ACTION:
a.
With one primary containment air lock door in one or both air locks inoperable:
1.
Maintain at least the OPERABLE air lock door closed
- and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door closed.
2.
Operation may then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed
- at least once per 31 days.-
3.
Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and r
in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.
Otherwise, in OPERATIONAL CONDITION #, suspend all operation f
involving handling of irradiated fuel in the primary containment, i
CORE ALTERATIONS, and operations with a potential for draining the reactor vessel.
5.
The provisions of Specification 3.0.4 are not applicable.
b.
With a primary containment air lock inoperable in OPERATIONAL CONDITIONS 1, 2, or 3, except as a result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPER-ABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHL'TDOWN within the i
next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
With a primary containment air lock inoperable, in OPERATIONAL CONDITION f, except as a result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or suspend all operations involving handling of irradiated fuel in the primary containment, CORE ALTERATIONS, and operations with a potential for draining the reactor vessel.
- When handling irradiated fuel in the primary containment, during CORE ALTERATIONS, and operations with a potential for drainir.g the reactor vessel.
- Except during entry to repair an inoperable inner door, for a cumulative time not to exceed I hour per year.
PERRY - UNIT 1 3/4 6-6
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