ML20213A530

Amend 4 to License NPF-58,revising Tech Specs to Require Operable RCIC Sys

ML20213A530
Person / Time
Site:	Perry
Issue date:	04/20/1987
From:	Holahan G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20213A509	List: ML20213A507 ML20213A530 ML20213A566
References
NUDOCS 8704280062
Download: ML20213A530 (6)

Text

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CLEVELAND ELECTRIC ILLUMINATING COMPANY, ET AL DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 4 License No. NPF-58

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 March 9, 1987, as supplemented on March, 19, 20, 31 and April 1, 7 and 10, 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;

• B. 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.  ;

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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. 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. l 8704280062 870420 PDR ADOCK0500gO P

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3. .This license amendment is effective as of April 10, 1987.

FOR THE NUCLEAR REGULATORY COMMISSION

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1 Gary. M. Hol an, Assistant Director for Regions III.& V Reactors i Division of Reactor Projects - III, IV, "

& Special Projects

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. Office.of Nuclear Reactor Regulation

Attachment:

i Changes to the Technical Specifications

Date of Issuance: April 20,1987 t

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4 ATTACHMENT TO LICENSE AMENDMENT NO. 4 FACILITY OPERATING LICENSE N0. NPF-58 DOCKET NO. 50-440 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Overleaf page(s) provided to maintain document completeness.*

Remove Insert 3/4 7-5* 3/4 7-5*

3/4 7-6 3/4 7-6 3/4 7-6a o

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l PLANT SYSTEMS i

SURVEILLANCE REQUIREMENTS (Continued)

3. Verifying that the heaters dissipate 100 Kw i 10% when tested in accordance with ANSI N510-1980.

4. Verifying that leakage through the outside air intake dampers (M25-F010A and M25-F020B for one train and M25-F0108 and M25-F020A for the other train) is limited to less than 20 scfm.

5. Verify that leakage through the exhaust dampers M25-F130A and M25-F1308 is limited to less than 20 scf.m.

f. After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter bank satisfies the inplace penetration

, testing acceptance criteria of less thin 0.05% in accordance with Regulatory Positions C.5.a and C.5.c of Regulatory Guide 1.52 Revi-L sion 2, March 1978, while operating the system at a flow rate of 30000 scfm i 10%.

g. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorber bank satisfies the in-place penetration and testing acceptance criteria of less than 0.05%

in accordance with Regulatory Positions C.5.a and C.5.d of Regulatory Guide 1.52 Revision 2, March 1978, for a halogenated hydrocarbon re-frigerant test gas while operating the system at a flow rate of 30000 scfm i 10%.

PERRY - UNIT 1 3/4 7-5

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PLANT SYSTEMS ,

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3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM LIMITING CONDITION FOR OPERATION i 3.7.3 The reactor core isolation cooling (RCIC) system shall be OPERABLE with an OPERABLE flow path capable of automatically taking suction from the sup-pression pool and transferring the water to the reactor pressure vessel.

APPL.ICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3* with reactor steam dome pressure greater than 150 psig.

ACTION:

With the RCIC system inoperable, operation may continue provided the HPCS system is OPEPABLE; restore the RCIC system to OPERABLE status within 14 days 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 reduce reactor steam dome pressure to less than or equal to 150 psig 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 -

[ 4.7.3 The RCIC system shall be demonstrated OPERABLE:

a. At least once per 31 days by:

I 1. Verifying by venting at the high point vents that the system piping from the pump discharge valve to the system isolation valve is filled with water.

2. Verifying that each valve, manual, power operated or automatic

. in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.

3. Verifying that the pump flow controller is in the correct position.

b. When tested pursuant to Specification 4.0.5 by verifying that the RCIC pump develops a flow of greater than or equal to 700 gpm in the test flow path with a system head corresponding to reactor vessel operating pressure when steam is being supplied to the turbine at 1020 + 25 - 100 psig (steam dome pressure).*

• The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.

1. The RCIC system shall be operable for the period April 10, 1987 through May 31, 1987 with the following provisions:

1. The RCIC injection valve shall not be capable of automatic opening.

2. The operational procedures shall be modified and the operators shall be trained such that the RCIC system is not operated (except as necessary for testing) unless all other high pressure systems fail to maintain an adequate reactor water level.

(Continued on page 3/4 7-6a)

PERRY - UNIT 1 3/4 7-6 AMENDMENT NO. 7, 4

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. PLANT SYSTEMS REACTOR CORE ISOLATION COOLING SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

3. Plant operation' subsequent to the reactor water level instrumentation 4

tests shall depend on the results as follows:

Channel Success Criteria A No anomalies over entire range of test conditions C No anomalies over entire range of test conditions D No anomalies over entire range of test conditions B No anomalies at pressure 1 400 psig Successful Channels Permissible Power Length of Time With RCIC Operating Lesel at Power Level i A+B+C 75% until 5/31/87 8+C+D 75% until 5/31/87 A+B+C+D 75% until 5/31/87 A + C + D + explanation 75% until 5/31/87 of B anomalies 2 400 psig All other combinations 50% 2 weeks, then shutdown

. 4. If reactor water level instrumentation shows significant deviations related to thermal hydraulic conditions unrelated to the RCIC tests, declare all reactor water level instrumentation inoperable and take whatever actions are required by Technical Specifications.

The provisions of Specification 3.0.4 are not applicable during this period.

PERRY - UNIT 1 3/4 7-6a Amendment No. 4

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