ML20055G508
| ML20055G508 | |
| Person / Time | |
|---|---|
| Site: | Perry  (NPF-58-A-032, NPF-58-A-32) |
| Issue date: | 07/18/1990 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20055G509 | List: |
| References | |
| NUDOCS 9007230263 | |
| Download: ML20055G508 (5) | |
Text
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THE CLEVELAND ELECTRIC ILLUMINATING COMPANY, ET AL, DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 32-License No. NPF-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.-
The application for amendment by The Cleveland Electric 111uminating Company, Duquesne Light Company, Ohio Edison Company, Pennsylvania Power Company, and Toledo Edison Company (the licensees) dated May 20, 1988 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 conformity with the application, the provisions of the Act, and the rules and regulations of the Comis-sion.
C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and i'
safety of the public, and (ii) that such activities'will be conducted t
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 1
i L
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 l,
of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Tc:nnical Specifications as indicated in the attachment to this license amendment, I
and paragraph 2.C.(2) of Facility Operating License No. NPF-58 is hereby amended to read as follows:
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(2) Technica1' Specifications The Technical Specifications contained in Appendix A and the Environ-mental Protection Plan contained in Appendix B, as revised through Amendment No. 32 are hereby incorporated into this license. The Cleveland Electric 111uminating Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
=~
John N. Hannon, Director i
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Project Directorate III-3 l
Division of Reactor Projects - III,
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IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 18, 1990 m
i
ATTACHMENT TO LICENSE AMENDMENT NO. 32 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 the amendment number and contains vertical lines' indicating the area cf change. The overleaf page is provided to maintain document completeness.
Remove Insert 3/4 1-9 3/4 1 9 4
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REACTIVITY CONTROL SYSTEMS i9 l
LIMITING CONDITION FOR OPERATION (Continued) 2.
With more than one withdrawn control rod with the associated scram accumulator inoperable and with no control rod drive pump operating, immediately place-the reactor mode switch in the Shutdown position.
1 The provisions of Specification 3.0.4 are not applicable.
c.
SURVEILLANCE REQUIREMENTS e
4.1.3.3 Each control rod scram accumulator shall be determined OPERABLE:
At least once per 7 days by verifying that the pressure is greater a.
than or equal to 1520 psig unless the control rod is inserted and disarmed or scrammed.
b.
At least once per 18 months by performance of a:
1.
' CHANNEL FUNCTIONAL TEST of the leak detectors, and 2.
CHANNEL CALIBRATION of the pressure detectors, and verifying an alarm setpoint of > 1520 psig on decreasing pressure.
l I
a PERRY - UNIT 1 3/4 1-9 Amendment No. 32
.O e.
REACTIVITY CONTROL' SYSTEMS C'ONTROL ROD ORIVE COUPLING LIMITING CONDITION FOR OPERATION l
3.1.3.4 All control rods shall be coupled to their drive mechanisms.
1 APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2 and 5*.
' ACTION:
a.
In OPERATIONAL CONDITION 1 and 2 with one control rod not coupled to its
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associated drive mechanism, within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
t 1.
If permitted by the RPCS, insert the control rod drive mechanism to accomplish recoupling and verify recoupling by withdrawing the control rod, and:
a)
Observing any indicated response of the nuclear instrumentation, and b)
Demonstrating that the control rod drive will not go to the overtravel position.
l 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 />.
2.
If recoupling is not accomplished on the first attempt or, if not permitted by the RPCS, then until permitted by the RPCS, declare the control rod inoperable, insert the control rod and disarm the asacciated directional control valves ** either:
a)-
Electrically, or b)
Hydraulically by closing the drive water and exhaust water isolation valves.
l
- 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 />.
b.
In OPERATIONAL CONDITION 5* with a withdrawn control rod not coupled to its associated drive mechanism, within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, either:
l 1.
Insert the control rod to accomplish recoupling and verify recoupling by withdrawing the control rod and demonstrating that the control
. rod will not go to the overtravel position,-or 2.
If recoupling is not accomplished, insert the control rod and disarm the associated directional control valves ** either:
a)
Electrically, or b)
Hydraulically by closing the drive water and exhaust water isolation valves, c.
The provisions of Specification 3.0.4 are not applicable.
"At-least each withdrawn control rod.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
- May be rearmed intermittently, under administrative control, to permit testing associated with restoring the control rod to OPERABLE status.
PERRY - UNIT 1 3/4 1-10
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