ML20217P662
| ML20217P662 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 12/31/1997 |
| From: | Swailes J NEBRASKA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLS980052, NUDOCS 9804100147 | |
| Download: ML20217P662 (10) | |
Text
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P.O. BOX L NEB 68321 i
Nebraska Public Power District "EME""
NLS980052 April 1,1998 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 Gentlemen:
Subject:
Annual Operating Report Cooper Nuclear Station l
NRC Docket No. 50-298, DPR-46 In accordance with Paragraph 6.5.1.C of the Cooper Nuclear Station Technical Specifications, the Nebraska Public Power District hereby submits the Cooper Nuclear Station Annual Operating Report for the period from January 1,1997, through December 31,1997.
Should you have any questions or comments regarding this report, please contact me.
l Sincerely, A
i A
l ohn H. S
'ce Presi ent o el r Energy
/lb Enclosure 2
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.cc:
Regional Administrator l
USNRC - Region IV l
Senior Resident Inspector i
USNRC - Cooper Nuclear Station Senior Project Manager USNRC - NRR Project Directorate IV-1 L
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REIRS Project Manager (w/ Personnel Man-Rem Report only)
Office of Nuclear Regulatory Research - USNRC
,t 9804100147 971231
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ll-l U.S. Nuclear Regulatory Commission April 1,'1998 Page 2 Plant Manager Cooper Nuclear Station f
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i COOPER NUCLEAR STATION BROWNVILLE, NEBRASKA ANNUAL OPERATING REPORT 1
JANUARY 1,1997, TIIROUGli DECEMBER 31,1997
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USNRC DOCKET 50-298
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TABLE OF CONTENTS SECTION PAGE 1.
PERFORMANCE CHARACTERISTICS.
1 Fuel Performance.
2 Main Steam Safety Valve and Safety Relief Valve Failures and Challenges.
3 11.
PERSONNEL AND MAN-REM EXPOSURE..
4 By Work and Job Function..
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I.
PERFORMANCE CIIARACTERISTICS I
1 FUEL PERFORMANCE For January, February, and most of March 1997, the plant operated at normal full power. The end of cycle coastdown began in late March with a shutdown for the 1997 Refueling Outage on March 29,1997. Approximately one-third of the fuel was replaced with new fuel and several reinserted fuel bundles. The reinserted fuel bundles had been removed from the reactor in 1996 as part of a fuelleaker shutdown. The fuelleaker was repaired and reinserted in the core along with its three companion bundles during the 1997 Refueling Outage.
Startup from the outage began on May 20,1997, with reactor criticality, and the generator was brought online on May 22,1997. Full power operation was achieved on May 26,1997. Normal plant power operation continued throughout the remainder of the year. A shutdown for repair of i
. plant equipment occurred in late July.
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Throughout the year, off gas activities indicated no fuel leakers. The activity levels were elevated l
above the levels experienced during 1996 prior to the fuel leaker event of that year. This is due to the memory effect of the prior fuel leak. Reactor coolant dose equivalent 1-131 and offgas release rates are well within the limits specified by the CNS Technical Specifications.
Comparisons of actual control rod densities predicted for the cycle against actual cycle operation at various core exposures indicate reactivity anomalies ofless than 1%
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MAIN STEAM SAFETY VALVE AND SAFETY RELIEF VALVE FAII URES ANL.
CHALLENGES (Ref.: NUREG-0737, Action Item II.K.3.3)
During 1997, the Safety Valves and Safety Relief Valves performed as expected. The valves showed no signs ofleakage during 1997. The Safety Valves and Safety Relief Valves were not required to operate in the automatic or manual mode.
During Refueling Outage 17, all three Safety Valves failed as-found testing requirements during surveillance testing. Two valves were out ofspecification low and one valve was out of specification high. The valves were subsequently refurbished, satisfactorily tested, and reinstalled in the plant.
During Refueling Outage 17, all eight Safety Relief Valves failed as-found testing requirements during surveillance testing. The failures were attributed to hydrogen induced corrosion bonding of the pilot disc to the pilot seat resulting in setpoint drift As an interim corrective action, CNS implemented Modification Package 93-107 which replaced the existing stellite pilot discs with stellite / platinum pilot discs. CNS committed to a mid-cycle outage to implement long term corrective action for the setpoint drift problem. During the March 1998 mid-cycle outage, all eight pilot discs were subsequently replaced with Stellite 21 discs per Modification Package 97-070.
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i II.
PERSONNEL AND MAN-REM EXPOSURE i
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COOPER NUCLEAR STATION / NESRASKA PUBLIC POWER DISTRICT 03-17-1998 P:pe 1 ANNUAL REPORT Year of 1997 NUNSER OF PER$0hWEL AND MAN REM SY WORK AND JOS FUNCTION l
l All Personnel ll Total Mon-Rem l
l l Station l Utility l Contractors ll Station l Utility l Contractors l
l Work & Job Function l E slovees l Eeloyees I and Others ll E eloyees l Eeloyees I and Others l
REACTOR OPERATION & SURVEIL MAINTENANCE 80 5
75 0.713 0.005 0.204
-OPERATIONS PERSONNEL 88 0
1 9.441 0.000 0.006 NEALTH PHYSICS 61 2
68 6.649 0.010 2.483 SUPERVISORY PERSONNEL 181 8
55 1.665 0.021 0.153 ENGINEERING PERSONNEL 130 6
134 1.760 0.D98 0.713 ROUTINE MAINTENANCE
- MAINTENANCE 144 5
419 35.015 0.053 47.047
-OPERATIONS PERSONNEL 64 0
0 5.975 0.000 0.000 NEALTH PHYSICS 42 1
76 6.189 0.001 9.266
-SUPERVISORY PERSONNEL 89 4
14 3.658 0.163 0.407
-ENGlWEERING PERSONNEL 70 3
208 5.530 0.955 17.571 INSERVICE INSPECTION MAINTENANCE 14 0
113 1.637 0.000 11.466 OPERAfl0NS PERSONNEL 7
0 0
0.026 0.000 0.000 NEALTH PHYSICS 6
0 11 0.120 0.000 0.155
-SUPERVISORY PERSONNEL 0
0 2
0.000 0.000 0.051 ENGINEERING PERSONNEL 11 0
75 0.382 0.000 7.214 SPECIAL MAINTENANCE
-MAINTENANCE 51 0
1 1.035 0.000 0.048
-OPERATIONS PERSONNEL 10 0
0 0.094 0.000 0.000 NEALTN PHYSICS 23 1
4 0.891 0.001 0.084 SUPERVISORY PERSONNEL 5
0 2
0.1 95 0.000 0.030 ENGINEERING PERSONNEL 7
0 1
0.017 0.000 0.002 WASTE PROCESSING
-MAINTENANCE 1
0 0
0.000 0.000 0.000
-OPERATIONS PERSONNEL 3
0 0
0.262 0.000 0.000 HEALTH PHYSICS 8
0 2
0.199 0.000 0.022 SUPERVISORY PERSONNEL 1
0 0
0.054 0.000 0.000
-ENGINEERING FERSONNEL 0
0 0
0.000 0.000 0.000 REFUELING
-MAINTENANCE 45 0
41 0.786 0.000 3.148
-OPERATIONS PERSONNEL 23 0
0 0.582 0.000 0.000 NEALTH PHYSICS 20 0
32 1.114 0.000 1.442
-SUPERVISORY PERSONNEL 15 0
4 0.206 0.000 0.077
-ENGINEERING PERSONNEL 16 2
46 0.282 0.002 4.137 TOTALS MAINTENANCE 335 10 649 39.186 0.058 61.912
-OPERATIONS PERSONNEL 1 95 0
1 16.381 0.000 0.006
-HEALTH PHYSICS 160 4
193 15.161 0.011 13.452
-SUPERVISORY PERSONNEL 291 12 77 5.778 0.184 0.718 ENGINEERING PERSONNEL 234 11 464 7.971 1.055 29.637 o.,or..........
GRAND TOTALS 1215 37 1384 84.477 1.308 105.726 oc..uco....................................................................................................................
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ATTACHMENT 3 LIST OF NRC COMMITMENTS l
Correspondence No: NLS980052 The following table identifies those actions committed to by the District in this document. Any other actions discussed in the submittal represent intended or planned actions by the District.
They are described to the NRC for the NRC's information and are not regulatory commitments.
Please notify the Licensing Manager dt Cooper Nuclear Station of any questions regarding this document or any associated
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j COMMITTED DATE i
COMMITMENT OR OUTAGE None
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PROCEDURE NUMBER 0.42 l
REVISION NUMBER S l
PAGE 9 OF 13 l
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