ML20151X476
| ML20151X476 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 08/18/1988 |
| From: | Perkins K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151X479 | List: |
| References | |
| NUDOCS 8808250375 | |
| Download: ML20151X476 (5) | |
Text
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UNITED $TATES NUCLEAR REGULATORY COMMISS!ON n
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WWMNGTON. D. C. 20665
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THE CLEVELAND ELECTRIC ILLliMINATING COMPANY, ET AL.
DOCKET N0. 50-440 PERRY NUCLEAR POWER PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.16 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, Duquesne Light Company, Ohio Edison Company, Pennsylvania Power Company, and Toledo Edison Company (the licensees) dated February 12 as amended May 20, 1988 complies with the standards and recuirements of the Atomic Energy Act of 1954, as amended (the Act),
anc 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 e.ompliance 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 lictnse amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-58 is hereby amended to read as follows:
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(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environ-mental Protection Plan contained in Appendix B, as revised through Amendment No.16 are hereby incorporated into this license. The Cleveland Electric Illuminating Company shall operato the facility in accordance with the Technical Specifications and the Environmutal Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION hk Lb_$m Kenneth E. Perkins, Director Project Directorate III-3 Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: August 18, 1988 i
m.
ATTACHMENT TO LICENSE AMENDMENT NO.16 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 area of change. The overleaf page is provided to maintain document completeness.
Remove Insert 3/4 4-9 3/4 4-9 b
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_ REACTOR. COOLANT SYSTEM 3/4.4.3 kr. ACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.3.1 The following reactor coolant system leakage detection systems shall be OPERABLE:
a.
The drywell floor drain sump and equipment drain sump flow monitoring system.
b.
Any 2 of the following:
1.
Drywell atmosphere particulate radioactivity monitoring system.
2.
Drywell atmosphere gaseous radioactivity monitoring system.
3.
Upper drywell air coolers condensate flow rate monitoring system.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION:
a.
With the drywell floor drain sump or equipment drain sump flow monitor-ing system inoperable, operation may continue for up to 30 days provided that the upper drywell coolers condensate flow rate monitoring system is one of the two systems OPERABLE per 3.4.3.1.b.
b.
With only one of the systems required by 3.4.3.1.b OPERABLE operations may continue for up to 30 days provided:
1.
The drywell floor drain samp and equipment drain sump flow monitoring system is OPERABLE.
2.
Grab samples of the drywell atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, c.
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 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 />.
SURVEILLANCE REQUIREMENTS l
4.4.3.1 The reactor coolant system leakage detection systems shall be demonstrated OPERABLE by:
a.
Drywell atmosphere particulate and gaseous monitoring systems-I performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a CHANNEL FUNCTIONAL T ST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months, b.
Drywell floor drain and equipment drain sump flow monitoring system-perfomance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.
c.
Upper drywell air coolers condensate flow rate monitoring system-performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days 1
and a CHANNEL CALIBRATION at least once per 18 months.
PERRY - UNIT 1 3/4 4-9 Amendment No. 16
REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:
a.
b.
5 gpm UNIDENTIFIED LEAKAGE.
c.
25 gpm IDENTIFIED LEAKAGE averaged over any 24-hour period.
d.
0.5 gpm leakage per nominal inch of valve size up to a maximum of l
5 gpm from any reactor coolant system pressure isolation valve speci-I fled in Table 3.4.3.2-1, at rated pressure.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION:
a.
With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTOOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
With any reactor coolant system leakage greater than the limits in b and/or c, above, redece the leakage rate to within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the fo' lowing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, c.
With any reactor coolant system pressure isolation valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one other closed manual or deactivated automatic or check
- valve, or 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 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 />.
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- Which have been verified not to exceed the allowable leakage limit at the last refueling outage or after the last time the valve was disturbed, whichever is more recent.
PERRY - UNIT 1 3/4 4-10
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