PY-CEI-NRR-1918, NPP,940101-1231 Annual Rept

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NPP,940101-1231 Annual Rept
ML20080Q656
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 12/31/1994
From: Shelton D
CENTERIOR ENERGY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
PY-CEI-NRR-1918, NUDOCS 9503090001
Download: ML20080Q656 (8)
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. ENERGY

. PERRY NUCLEAR POWER PLANT : Mail Address: Donald C. Shelton j

SENIOR VICE PRESIDENT 9O CENTER ROAD RRY,O 10 44081 NUCLEAR i

PIRRY, OHIO 44061 1

-(216) 259-3737 February 28, 1995.

- PY-CEI/NRR-1918L United States Nuclear ReFulatory Commission Document Control Desk Washington, D.C. 20555 Perry Nuclear Power Plant Docket No. 50-440 1994 Annual Report Gentlemen Attached is the 1994 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 Appendix 1B.

If you have questions or require additional information, please contact Mr. James D. Kloosterman, Manager - Regulatory Affairs at (216) 280-5833.

Very t yours,

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GMN:sc Attachment ces NRC Project Manager NRC Resident Inspector Office NRC Region III REIRS Project Manager 080026 1 9503090001 941231 PDR ADOCK 05000440 R PDR Operotng Compomes l[ g i

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')- CLEVELAND ELECTRIC ILLUMINATING COMPANY-

' t PERRY NUCLEAR POVER PLANT  ;

9 JANUARY 1 - DECEMBER 31, 1994 .

e ABBIUAL REPORT ,

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DOCKET NUMBER: 50-440- I LICENSE NUMBER: NPF-58 l t t

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Atts'chment PY-CEI/NER-1918L . ,

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' TABLE OF CONTENTS

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I. Occupational Exposure Summary Report. 3

'II. Safety / Relief Valve Challenges 5  ;

III. Reactor Coolant System Specific A'etivity Analysis '7 IV. Silicone Sealant Inspections- 7 6

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.I.; Occupational Radiation Exposure Summary Report. .

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t.p c Enclosed in this section is the-1994 Annual Occupational. Exposure Summary - ~

grouped ~as' indicated below: s i

' STATION: Perry' Nuclear Power l Plant Department, Site Protection Section-of the Perry Nuclear Services Department' UTILITY Perry Nuclear' Assurance' Department, Perry Nuclear Engineering ,

Department, other Sections of the Perry Nuclear. Services l Department, and CEI support personnel-  ;  ;

'l OTHER Contractor, Consultant,~Centerior, Davis-Besse, and other  !

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1994 A ZUAL EXPOSU23 REP 3RT' QBSULAT32T SUIDE 1.16 APP 20912 A

SUMMARY

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CO2K CAT 3202T JOB CATESCRT 'l 4 PE2SOCS >= 0 NLEM . '[. .

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l STATION UTILITY OTNER l _ STATION WTILITY

.OTNER .

REACTOR OPER. & SURVEILLANCE' MAINTENANCE 132 63~ 502 1.090' O.045- 9.111 r OPERATIONS 278 39 10 '23.211 1.026 '0.771' '

NEALTN PNYSICS 58 23 213 7.618 1.184 26.650' SUPERVISORY 3 2 34 0.034 0 0072 0.279 ENGINEERING 8 141 66 0.269 1.272 0.722' ROUTINE MAINTENANCE MAINTENANCE 179- 127 1510 23.544 6.716' 255.244-OPERATIONS ~ 308 47 32 8.832' O.330 1.089 NEALTN PNYSICS 61 26 246 4.633 0.710 .18.144 SUPERVISORY 4 3 64 0.005 0.000 0.483 ENGINEERING 19 226 211- 0.275 7.356 18.593 INSERVICE INSPECTION ' MAINTENANCE 59 10 701 0.400 0.271 46.431 OPERATIONS 62 6 7 1.199 '0.140 0.160 NEALTN PHYSICS 15 4 68 0.267 0.058 1.092 SUPERVISORY 0 0 7 0.000 0.000 0.102 ENGINEERING 4 60 73 0.157 2.412 9.608

-SPECIAL MAINTENANCE MAINTENANCE 110 46 785 '5.385 0.120 67.185-OPERATIONS 103 4 5 1.860 0.027 0.096 NEALTN PNYSICS 30 8 97 1.290 0.084 -2.745 SUPERVISORY 1 0 2 0.000 0.000 0.004 ENGINEERING 5 61 59 0.024 '1.911 1.938 WASTE PROCESSING MAINTENANCE 105 58 370 0.068 4.563 4.749-OPERATIONS 70 9 3 3.325 0.009 0.010 NEALTN PNTSICS 48 19 166 2.491 1.791 3.554-SUPERVISORT 0 1 '2 0.000 0.000 0.000 ENGINEERING 2 24 4 0.005 0.085- 0.015' REFUELING MAINTENANCE 96 51 690 19.386 1.204 68.225 OPERATIONS 133 9 8 21.369 2.540 0.604 NEALTN PNTSICS 29 19- 144 -1.201 0.377 6.893 SUPERVISORY 1 0 2 0.002 0.000 0.032 ENGINEERING 6 76 35 0'647

. 4.655 1.238 TOTALS MAINTENANCE 681 355 4558 49.873 12.959 450.949-OPERATIONS 954 114 65 59.796 -4.112 '2.730 NEALTH PHYSICS 241 '99 934 17.500 4.204 59.078 SUPERVISORY 9 6 111 0.041 0.007- 0.900

. ENGINEERING 44. 544 448 1.377 17.691 32.114-GRAND TOTALS 1929 1162 6116 128.587 38.973 545.771 Wete:

MAN-REM is based on Direct Reading Domineter Readings.

4 Persons is based on number of unique individuals signing in on any RWP in corresponding categories:

regardless of exposure received. . gf )l f _

' 88 I a work Category is based on RWP Individual signed in on.

Job Category and Station / Utility /Other is based on personnel record of individual signing in on corresponding RWP.

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'II.. SAFETT/ RELIEF VALVE CHALLENGES The attached report; includes all actuations during the 1994 year.

-During Refuel Outage #4 alllthe SRVs were removed and replaced with

-refurbished valves. Prior to declaring the newly installed valves operable, per Technical Specifications 4.0.5, each valve was tested asi required by SVI B21-T2005, "SRV Exercise Test."

On February 25 and 26, two SRVs, 1B21-F051C and 1821-F051D, were' unexpectedly opened. Each valve was actuated four times._ The plant was shutdown for Refuel' Outage #4.. Licensee' Event Report (LER)'94-008'rev. O was submitted to the NRC_as a voluntary report.

This information is submitted :ba accordance with Technical Specification .

6.9.1.5.b of Appendix A to Operating License NPF-58 for the Perry Nuclear Power Plant, Unit 1.

1 Included as an SRV " challenge" are the following actions / events. ,

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1. .The SRV being physically' operated by the manual control switch in the Control room.
2. The SRV automatically: lifts per design pressure limit when installed '

in the plant.

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SAFETY / RELIEF ACTUATIONS DURING'1994=

DATE-2/25/94 & 2/26/94 DATE-7/25/94 & 7/26/3 if VALVE NUMBER. VALVE NUMBER 1B21-F041A 1B21-F041B 1B21-F041C* 1B21-F041D:

1B21-F041E 1821-F041F 1B21-F041G 1B21-F041K.

1B21-F047B 1B21-F047D 1B21-F047F* IB21-F047G

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1B21-F047Hs 1B21-F051A 1 21-F051B 1B21-F051C**

IB21-F051D** IB21-F051G 1B21-F047C

'*These two' valves were actuated three times during the test,~all'other' valves were actuated twice.

    • These two valves were both actuated unexpectedly cni 2/25 for11B21-F051C and.

1 2/26 for IB21-r051D. .The number of actuations for each. valve ~vas four,;

-a total of eight actuations.

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..III(Reactor Coolant System Specific Activity JAnalysis-I d :During 1994 there were no' occurrences:in which Technical Specificath n 3.4.5,." Specific Activity",, Limiting Condition for Operation was.,...

exceeded. This information is' submitted in accordance with1 Technical

, -Specification 6.9.1.5.c.:

IV. Silicone Sealant I'nspections-In~accordance.vith' commitments made in response.to License Commitment 17 of the USAR' Appendix 1B (reference letter.PY-CEI/NRR-0703L dated August 27, 1987 from Murray R. Edelman)lthe following summary report lis provided. -During the Perry Unit 1, fourth refueling outage.(February 5,.

1994 - August 14, 1994)-duct specimens that were previously placed inian-environmentally representative horizontal pipe chase-in the Intermediate

. Building, 585'. elevation vere inspected. The du't e specimens'. vere. leak tested at rated pressure, with acceptable-results.- Thelresults of the duct specimen-leak test showed.that no additional air leakage'vastpresent' than previously identified in the original; test.

A valkdown of representative ~ portions:of Engineered' Safety Feature (ESP).

ventilation systems [ Annulus: Exhaust Gas Treatment (M15) . Control ~ Room-HVAC (M25) and Fuel Handling Building. Ventilation-(M40)]'was conducted and the exposed exterior silicone sealants were inspected, also with-acceptable results- .

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