PY-CEI-NRR-0970, Annual Rept for 1988

Annual Rept for 1988

ML20235U473
Person / Time
Site:	Perry
Issue date:	12/31/1988
From:	Kaplan A CLEVELAND ELECTRIC ILLUMINATING CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
PY-CEI-NRR-0970, PY-CEI-NRR-970, NUDOCS 8903090214
Download: ML20235U473 (9)

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' CLEVELAND' ELECTRIC ILLUMINATING COMPANY PERRY NUCLEAR POWER PLANT i'

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JANUARY 1 - DECEMBER 31, 1988 ANNUAL REPORT

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DOCKET NUMBER: 50-440 l LICENSE NUMBER: .NPF-58 Submitted By: Bthera / .

Plant Techn16al/ Director ,

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Gettaral Manager p Operations I

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1 8903090214 881231 DR ADOCK 05000440 .

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. TABLE OF CONTENTS Page I. Introduction 3

11. Occupational Radiation Summary Report 4 III. Safety Relief Valve History 6 IV. Reactor Coolant System Specific Activity Analysis 8 2

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I. Introductig This information comprises the 1988 Annual Report, which is submitted in accordance with Technical Specifications 6.9.1.4 and 6.9.1.3 of Appendix A to Perry Nuclear Power Plant Operating License NPF-58. The report covers the period from January 1, 1988 until December 31, 1988.

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l II.- Occupational Radiation Summary Report Enclosed in this section is the 1988 Annual Occupational Exposure Summary Report required by Technical Specification 6.9.1.5.a of Appendix A to the Perry Unit 1 Operating License. The following-work categories were grouped as indicated below:

STATION - Operations Department and Technical Department UTILITY - Engineering Department, Plant Support Department, Quality Assurance Department and Perry Services Department OTHER - Contractor, Consultant, Centerior, Davis-Besse, Eastern District and other support personnel 4

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III.- Safety / Relief Valve Challenges The attached report lists all challenges made to the Safety / Relief Valves (SRVs) in 1988 ct Perry Nuclear Power Plant. This information is submitted in accordance with Technical Specification 6.9.1.5.b of Appendix A to Operating License NPF-58 for Perry Nuclear Power Plant Unit 1.

Included as a SRV " challenge" are the following actions / events:

the SRV being physically operated by the manual control switches in the control room.

the SRV automatically lifts per design pressure-limit when installed in the plant.

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.SRV ACTUATION EVENTS SAFETY / RELIEF VALVES'ACTUATIONS DURING 1988

. VALVE' DATE- TIME

'1B21-F041A '9-29-88 0208 i- IB21-F041E 9-29-88 0203 IB21-F041F 9-29-88 0205 1B21-F047D 9-29-88 0155 1B21-F047H: 9-29-88 0212-r-

1B21-F051C' '9-29-88 0211 1B21-F051G 9-29-88 0201-

1. All. challenges to these SRVs during the reporting period

.were in. support of a surveillance test instruction.

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p Two SRVs-(IB21-F041B and-1B21-F051B) were stroked twice for initial-operability in accordance with-Technical Specifications following valve replacement on January 28, 1988 at 1412.

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3 IV. Reactor Coolant System Specific Activity Analysis During 1988 there were no occurrences in which Technical Specification 3.4.5, " Specific Activity," Limiting Condition for Operation was exceeded. This information is submitted in accordance with Technical Specification 6.9.1.5.c.

As specified by Technical Specification 6.9.1.4 and 6.9.1.5 of Appendix A to Perry Nuclear Power Plant Unit 1 Operating License No. NPF-58, no further information is required or enclosed.

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THE CLEVELA,ND ELECTRIC ILLUMINATING COMPANY j P.O. BOX 97 5 PERRY, OHIO 44081 W TELEPHONE (216) 2594737 5 ADDRESS-10 CE.NTER ROAD FROM CLEVELAND: 241 1650 Serving The Best location in the Natien Al Kaplan ' PERRY NUCLEAR POWER PLANT VICE PRESIDENT NUCLEAR GROUP 1

February 27, 1989 PY-CE1/NRR-0970 L U.S. Nuclear Regulatory Commission I Document Control Desk Washington D.C. 20555 Perry Nuclear Power Plant Docket No. 50-440 1988 Annual Report

Dear Sir:

Attached is the 1988 Annual Report for Perry Unit 1. This report is submitted in accordance with Technical Specifications 6.9.1.4 and 6.9.1.5.

If there are any questions, please feel free to call.

Very truly y u.s, f

, /,1/A 90 Al Kaplan Vice President Nuclear Group Enclosure AK:nj c cc: T. Colburn Resident Inspector L. Hiller (Office of Management 6 Program Analysis)

USNRC, Region III 1 1 N m

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