ML20067A481
| ML20067A481 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 02/14/1994 |
| From: | Hopkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20067A484 | List: |
| References | |
| NUDOCS 9402180056 | |
| Download: ML20067A481 (5) | |
Text
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WASHINGTON, D.C. N0001 yv.....f THE CLEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL.
DOCKET NO. 50-440
_ PERRY NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LIC MSX Amendment No. 55 License No. NPF-58 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by The Cleveland Electric Illuminating Company, Centerior Service Company, Duquesne Light Company, Ohio Edison Company, Pennsylvania Power Company, and Toledo Edison Company (the licensees) dated September 23, 1991, 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 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 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations 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:
9402180056 940214 PDR ADOCh 05000440 p
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Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 55 are hereby incorporated into.this license. The Cleveland Electric Illuminating Company shall operate the facility in accordance.with the Technical Specifi-cations and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented not later than 90 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f
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Jon B. Hopkins, S nior Project Manager Project Directorate III-3 Division of Reactor Projects III/IV/V
-i Office of Nuclear Reactor Regulation' t
Attachment:
Changes to the Technical Specifications Date of issuance:
Februa ry 14, 1994 l
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l ATTACHMENT TO LICENSE AMENDMENT NO. 55 FACILITY OPERATING LICENSE NO. NPF-58 f
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 area of change. The overleaf page is provided to maintain document completeness.
Reaove Insert 3/4 1-8 3/4 1-8 P
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l REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)
ACTION:With(Continued) a " slow" control rod (s) not satisfying ACTION a.), above:
b.
1.
Declare the " slow" control rod (s) inoperable, and 2.
Perform the Surveillance Requirements of Specification 4.1.3.2.c at least once or more " slow"per 60 days when operation is continued with three control rods declared inoperable.
Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c.
With the maximum scram insertion time of one or more control rods exceeding the maximum scram insertion time limits of Specification 3.1.3.2 as determined by Specification 4.1.3.2.c, operation may continue provided that:
1.
" Slow" control rods, i.e., those which exceed the limits of Specification 3.1.3.2, do not make up more than 20% of the 10%
sample of control rods tested.
j 2.
Each of these " slow" control rods satisfies ACTION a.l.
l 3.
The eight adjacent control rods surrounding each " slow" control rod are:
a) Demonstrated through measurement within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to satisfy the maximum scram insertion time limits of Specification 3.1.3.2, and b) OPERABLE 4.
The total number of " slow" control rods {he total number of ACT l
as determined by Specification 4.1.3.2.c, when added to a.3, as determined by Specification 4.1.3.2.a and b, does not exceed 7.
Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
d.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE RE0VIREMENTS 4.1.3.2 The maximum scram insertion time of the control rods shall be demonstrated through measurement with reactor coolant pressure greater than or equal to 950 psig and during single control rod scram time tests, the control rod drive pumps isolaled from the accumulators:
For all control rods prior to THERMAL POWER exceeding 40% of RATED a.
THERMAL POWER following CORE ALTERATIONS or after a reactor shutdown that is greater than 120 days, b.
For specifically affected individual control rods
- following maintenance on or modification to the control rod or control rod drive system which could affect the scram insertion time of those specific control rods, and c.
For at least 10% of the control rods on a rotating basis, at least once per 120 days of POWER OPEkATION.
- The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 2 provided this surveillance is completed prior to entry into OPERATIONAL CONDITION 1.
PERRY - UNIT 1 3/4 1-7 AMENDMENT No. 54