ML20034F776

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1992 Annual Rept
ML20034F776
Person / Time
Site: Perry 
Issue date: 12/31/1992
From:
CENTERIOR ENERGY
To:
Shared Package
ML20034F773 List:
References
NUDOCS 9303040273
Download: ML20034F776 (8)
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Text

Attachment PY-CEI/NRR-1613 L Page 1 of 8 f

i CLEVELAND ELECTRIC ILLUMINATING COMPANY PERRY NUCLEAR POWER PLANT JANUARY 1 - DECEMBER 31, 1992 ANNUAL REPORT DOCKET F MBER: 50-440 1

LICENSE NUMBER: NPF-58 r

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1 9303040273 930301 PDR ADDCK 05000440 R

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i Attachment PY-CEI/NRR-1613 L Page 2 of 8 i

i'l TABLE OF CONTENTS l

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Occupational Exposure Summary Report 3

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II.

Safety / Relief Valve Challenges 5

III.

Reactor Coolant System Specific Activity Analysis 7

f IV.

Silicone Sealant Inspections 8

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Attachment i

PY-CEI/NPR-1613 L l

Page 3 of 8 l

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Occupational Radiation Exposure Summary Report i

Enclosed in this section is the 1992 Annual-Occupational Exposure l

Summary Report required by Technical Specification 6.9.1.5.a of Appendix A to the Perry Unit 1 Operating License. The following vork Categories vere grouped as indicated-below:

STATION Perry Nuclear Power Plant Department, Site Protection l

Section of the Perry Nuclear Support Department i

I UTILITY Perry Administrative Support Department, Perry Nuclear Assurance Department, Perry Nuclear

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Engineering Department, other Sections of the Perry Nuclear Support Department, and CEI support personnel J

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i OTHER Contractor, Consultant, Centerior, Davis-Besse, and other support personnel 1

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FILE 4: N/A RR 8: N/A 1992 ANNUAL EXPOSURE REPORT DATE:

01/28/93

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REGULATORY GUIDE' 1.16 APPENDIX A

SUMMARY

PAGE:

1 WORK CATEGCRY JOB CATEGORY

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  1. OF PERSONS > 0100 MREM l

TOTAL MAN-REM l

STATION UTILITY OTHER l

STATION UTILITY OTHER t

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REACTOR OPER. E SURVEILLANCE MAINTENANCE 44 8

31 0.904 0.000 2.938 OPERATIONS 119 9

17.671

'0.082 HEALTH PHYSICS 43 91 4.522 1.875 SUPERVISORY 1

0.000 ENGINEERING 3

27 6

0.040 0.825 0.020 ROUTINE MAINTENANCE MAINTENANCE 100 20 344 4.616 0.415 10.067 OPERATIONS 97 12 5.670 0.218 HEALTH Pit ? S I CS 37 112 0.710 4.961 SUPERVISORY 2

0.097 ENGINEERING 1

37 19 0.023 1.042 0.055 INSERVICE INSPECTION MAINTENANCE 42 327 0.435 69.904 OPERATIONS 14 5

0.220 0.155 HEALTH PHYSICS 17 48 0.640 3.515 SUPERVISORY ENGINEERING 2

24 23 0.090 0.959 6.335 SPECIAL MAINTENAMCC MAINTENANCE 102 20 570 38.460 2.620 230.015 OPERATIONS 122 14 16.323 2.600 HEALTit PHYSICS 43 143 8.583 41.762 SUPERVISORY 2

0.130 ENGINEERING 3

41 28 0.795 8.189 6.407 i

WASTE PROCESSING MAINTENANCE 62 7

47 1.021 0.580 2.080 OPERATIONS 34 1

1.815

.0.000 HEALTH PHYSICS 35 47 2.202 0.980 SUPERVISORY ENGINEERING 6

0.051 REFUELING MAINTENANCE 88 8

342 6.637 0.030 53.575 g]g OPERATION 3 123 13 4.305 0.355 HEALTH PHYSICS 34 121 2.535 12.443 ga ' p SUPERVISORY Q

W ENGINEERING 2

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0.045 1.900 0.255

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W rt TOTALS MAINTENANCE 438 63 1661 52.073 3.645 368.579

00j, OPERATIONS 509 54 46.004 3.410 os.

HEALTH PHYSICS 209' 562 19.192 65.536 b^ -

SUPERVISORY 5

0.227 ENGINEERING 12 158 85 0.993 12.966 13.072 b'

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GRAND TOTALS 1168 221

.2367 118.262 16.611 450.824

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Attachment PY-CEI/NRR-1613 L 1

Page 5 of 8 f

f II.

Safety / Relief Valve Challenges i

The attached report includes all actuations during the 1992 year.

Included as SRV " challenges" are the following actions / events.

1.

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

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

This information is submitted in accordance with Technical Specification 6.9.1.5.b of Appendix A to Operating License NPF-58 l

for the Perry Nuclear Power Plant, Unit 1.

I During Refuel Outage #3 (March 21 - June 13, 1992), Perry Unit 1

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changed out all nineteen of tha safety / relief valves.

Prior to l

declaring the newly installed valves operable, per Technical Specifications 4.0.5, they were all actuated twice. The actuations vere performed in accordance with surveillance test instruction SVI-B21-T2005, "SRV Exercise Test."

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r On November 21, 1992 during the performance of a maintenance f

surveillance SVI-B21-T0369B, "SRV Pressure Actuation Channel B Functional," two SRV's unexpectedly opened. The valves that opened were 1B21-F051C & D.

The specific equipment malfunction which caused the event could not be determined. This event was reported to the NRC in LER 92-024, dated December 18, 1992.

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Attachment PY-CEI/IER-1613 L Page 6 of 8 l

SAFETY / RELIEF VALVE CHALLENGES DURING 1992 VALVE NUMBER TIME VALVE NUMBER TIME DATE 06/10/92 l

1B21-F041A 1838 1B21-F047C 1811 IB21-F041A 1839 1B21-F047C 1812 IB21-F041B 1831 IB21-F047D 1825

.l 1B21-F041B 1833 1B21-F047D 1827 J

1B21-F041C 1819 1B21-F047F 1759 IB21-F041C 1821 1B21-F047F 1759 IB21-F041D 1807 IB21-F047G 1817 1B21-F041D 1807 IB21-F047G 1817 1B21-F041E 1834 1B21-F047H 1843 1B21-F041E 1834 IB21-F047H 1844 IB21-F041F 1836 IB21-F051A 1809 1B21-F041F 1837 IB21-F051A 1810 1B21-F041G 1801 1B21-F051B 1803 1B21-F041G 1802 IB21-F051B 1804 1B21-F041K 1814 1B21-F051C 1841 IB21-F041K 1815 IB21-F051C 1841 1B21-F047B 1756 1B21-F051D 1752 IB21-F047B 1757 1B21-F051D 1754 IB21-F051G 1828 1B21-F051G 1829 DATE 11/21/92 IB21-F051C 0357 1B21-F051D 0357 p

Attachment

_PY-CEI/NRR-1613 L l

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III.

Reactor Coolant System Specific Activity Analysis l

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During 1992 there vere no occurrences in which Technical l

Specification 3.4.5, " Specific Activity," Limiting Condition for j

Operation was exceeded. This information is submitted in accordance with Technical Specification 6.9.1.5.c.

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Attachment PY-CEI/NRR-1613 L Page 8 of 8 l

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IV.

Silicone Sealant Inspections l

In accordance with commitments made in response to License Commitment 17 of USAR Appendix 1B (reference 4etter PY-CEI/NRR-0703L, dated August 27, 1987 from Murray R. Edelman) l the following summary report is provided. During the Perry Unit 1 third refueling outage (March. 21, 1992 - June 13, 1992) duct specimens that were previously placed in an environmentally l

representative horizontal pipe chase in the Intermediate Building, 585' elevation vere inspected. The duct specimens were leak tested at rated pressure, with acceptable results. The results of the duct specimen leak test showed that no additional air leakage I

j was present than previously identified in the original test. A t

walkdown of representative portions of Engineered Safety Feature

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(ESP) ventilation systems [ Annulus Exhaust Gas Treatment (MIS),

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Control Room HVAC (H25) and Fuel Handling Building Ventilation j

(M40)] vas conducted and the exposed exterior silicone sealants l

vere inspected, also with as eptable results.

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