ML20090B873

Annual Rept Jan-Dec 1991 Perry Nuclear Power Plant

ML20090B873
Person / Time
Site:	Perry
Issue date:	12/31/1991
From:	Lyster M CENTERIOR ENERGY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
PY-CEI-NRR-1464, NUDOCS 9203040105
Download: ML20090B873 (9)

Text

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,- CENTE  ;

E RGY

' PERRY NUCLEAR POWER PLANT- i Md ess:

Michael D. Lyster 10 CENTER ROAD ' PERRY, OHIO 44081

! PERRY, OHIO- 44001 VICE PRESIDENT. NUCLEAR l (216) 259 3737 l

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February 28, 1992 l PY-CEI/NRR-1464 L

, U.S. Nuclear Regulatory Commission

! Document Control Desk ,

l :Vashington, D.C. 20555 l

Perry Nuclear Power Plant Docket No. 50-440 1991 Annual Report I

Gentlemen Attached is~the 1991 Annual Report.for Perry Unit 1. This report is submitted in accordance with Technical Specifications 6.9.1.4 and 6.9.1.5 and fulfills

- ongoing commitments associated with Licensing Commitment-17 of USAR l Appendix 1B.

Since re,1y ,

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l Michael D. Lyster

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! cc NRC Project Manager

!~ NRC Resident Inspector Office NRC Region:III' 0300SG 9203040105 911231 PDR ADOCK 05000440 .

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, . Attachm:nt PY-CEI/NRR-1464 L Page 1 of 8 Tile CLEVELAND ELECTRIC ILLUMINATING COMPANY PERRY NUCl2AR POVF2 PLANT JANUARY 1 - DECEMBER 31, 1991 ANNUAL REPORT DOCKET NUMBER: 50-440 LICENSE NUMBER: NPF-58

Attachment PY-CEI/NRR-1464 L Page 2 of 8 TABLE OF CONTFKfS Page 7.. Occupational Exposure Summary Report 3 II. Safety Relief Valve Challenges 5 III. Reactor Coolant System Specific Activity Analysis 7 IV. Silicone Sealant Inspections 8

A t t achroen t PY-CE1/14RR-1464 L Page 3 of 8 I. OCCUI'ATIO!4AL_RADIAT10!J EXPOSURE

SUMMARY

REPORT Enclosed in this section is the 1991 Annual occupational Exposute Summary Report tequired by Technical Speclilcation 6.9.1.5.a of Appendix A to the Perty Unit 1 Operating License. The dose assignments to various duty functions provided herein vere obtained from pocket dosimeter tocasurements recorded in Radiation Voik Petmit (RVP) documents.

Thermoluminescent dosimeter (TLD) measurements fot 1991 are provided under a separate report in accordance vith 10 CTR 20.407. Vork categories vete grouped as indicated belov:

57ATIO!1 Perry !Juclear 'over Plant Depar tment , Petty !4uclear Support Department, resiarmance Enginecting Section and Systems Engineering Section of the Petty !Jucleat Engineering Department UTILIJJ Perry liucleat Assutance Departwent and all other Sections of the Perry 14uclear Engineering Department OTilQ Contractor, Consultant, Centerior, Davis-Besse, Eastern District, and other suppott personnel

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. . Attachmont pY-CEI/NRR-1464 L j Page 5 of 8 l

II. SAFETY' RELIEF VALVE CHALLENGES i

The attached report includes all actuations during the 1991 year. Two safety relief valves were cycled on January 13, 1991 per the surveillance test program in attempt to reset them. These valves had just been installed in the plant during refuel outage #2 vhirh ended January 6, 1991. The cycling of these valves to reset them vas unsuccessful. The tailpipe temperatures remained at approximately 225'F. The next time any SRV's vere cycled was on December 22, 1991, following a manual reactor scram. The cycling of the SRV's was to doctease the pressure in the [

reactor. The attached sheet lists the valves actuated and the times. .

l There vere a total of $0 actuations. All valves vere cycled by sne manual mode in the control Room. This information is submitted in i accordance with Technical Specification 6.9.1.$.b of Appendix A 10 Operating License NPF-$8 for the Perry Nuclear Pover Plant, Unit 1.

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

1. The SRV being physically operated by the manual conttol switch in the control room.

2. The SRV automatically lifts per design pressure limit when .nstalled '

-in the plant.

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. Attachment

. . FY-CE1/NRR-1464 L Tage 6 of 8 14FETY REl.IEF VALVH_CilAllI.NGES DURING 1991 VALVE NUMBER TIMH VALVE NUMBER TIME DATE-01/13/91 DATE-01/13/91 1B21-F051D 0330 IB21-F047G 0518 DATE-12/22/91 DATE-12/22/91 1821-F041A 0315 1821-F041B 0311 0345 0338 l 0508 1 IB21-F041C 0302 0332 1B21-F041D 0241 0453 0326 .

0358 I 1B21-F041E 0340- 0415 l 0520 l 1821-F041G 0233 1821-F041F 0313 0323 0341 0353 0530 1B21-F0478 0225 1B21-F041K 0254 0321 0330 0351 0430 IB210F047C 0251 IB21-F047D 0305 0334 IB21-F047G 0250 0454 0331 0353 IB21-F047F 0228 0433 0322 0353 1821-F051A 0246 ,

1B21-F051B 0237 IB21-F0510 0318 0325 .0347 0355 0630 IB21-F051D 0221 IB21-F051G 0309 0319 0335 0337 0455

Attachnient PY-CE1/NRR-1464 L l Page 7 of 8 III. REACTOR COOLANT SYSTEM SPECir1C ACTIVITY ANALYSIS During 1991 thete vere no occutrences in which the Technical Specification 3.4.5, " Specific Activity," Limiting condition for Operation was exceeded. This inf o:niation is submit ted in accotdance with Technical Specification 6.9.1.5.c.

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, , Attachment  :

• PY-CEI/NRR-1464 L  !

Page 8 of 8  !

IV. SILICONE SEALANT INSPECTIONS During 1991, no ref ueling outages vete per ferined. thetefore no silicone sealant inspections vete performed. This information is provided in accordance with the response to License Commitment 17 of USAR Appendix 2B

, (reference letter PY-CE1/NRR-0703 L. da -d August 27 1987 from Hutray R.

Edelman).

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