ML20207A830

1998 Annual Operating Rept for Ggns,Unit 1

ML20207A830
Person / Time
Site:	Grand Gulf
Issue date:	12/31/1998
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20207A820	List: ML20207A816 ML20207A830
References
NUDOCS 9903050263
Download: ML20207A830 (8)

Text

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Attachment I to GNRO-99/00011 Page 1 of 2 9

SUMMARY

OF OPERATING EA.PERIENCE 1998 The following is a summary of Grand Gulf Nuclear Station (GGNS) Unit 1 operating experience for the 1998 calendar year. During 1998, the reactor was critical for 7,784.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> with the generator on line for 7,642.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

On 1/28/98, the reactor manually scrammed at 1650 hours0.0191 days <br />0.458 hours <br />0.00273 weeks <br />6.27825e-4 months <br /> when the difference between the inlet temperatures on the two sides of the LP turbines reached 25 *F following closure of the heating-steam control and isolation valves for MSR 2"'-Stage Reheaters upon failure ofBOP invener lY98. Duration time - 68.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

On 3/05/98, @ 1511 reactor Feedpump 'B' tripped when the digital control system sensed a sticky control valve poppet and the core thermal power dropped to approximately 70%. As an interim measure, the 'B' feedpump governor valve was positioned off where it was sticking by biasing the control system in distributing the two pump loads. Then the 'B' feedpump was placed back in service. The 'B' control valve will be inspected und repaired in the upcoming refueling outage. Duration time - 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

On 4/09/98, @l411 Reactor Feedpump (RPF) 'B' shutdown for RFP turbine overspeed test before shutdown for refueling. Duration - 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

Os 4/11/98, @ 0000 Reactor manually scrammed for Refueling Outage #9. RF09 was scheduled to end on 5/13/98, but was extended to 5/21/98 and ended @ 1857. Duration - l 978.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />.

l On 5/22/98, generator was taken off grid @ 2341 for turbine overspeed testing Duration -

3.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. l On 5/23/98, tripped turbine @ 1718 to repair instrument tubing for reactor trip unit Cll-l N654B. Duration- 17.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.

On 5/24/98, tripped turbine @ 2232 when temperature difference between two sides of LP turbine inlet steam exceeded 25 F while taking MSR out-of-service because of stuck open temperature control valves. Duration - 11.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

On 9/12/98, power reduced for control rod sequence exchange. Circulating Water Pump 'B' seal repacked at low power. Duration - 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

- On 9/14/98, power reduced in preparation for repairing ruptured instrument air tubing in drywell at low power. Duration - 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

9903050263 990224 PDR ADOCK 05000416 R PDR

I Attachment I to GNRO-99M0011

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l On 9/15/98, turbine tripped by operator when temperature difference between two sides of d

LP turbine inlet exceeded 25 *F because of partially open MSR 'B' 2 Stage temperature control valves while taking MSR out of service at reduced power in preparation for drywell entry. Duration-38.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

On'10/21/93, power reduced to approximately 50% when Circulating Water Pump 'A'

. tripped because of burned electrical lead. Duration - 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

On 11/20/98, power reduced to approximately 50% to take Circulating Water Pump *B' out of service in order to repair a hole on main condenser waterbox transition piece. ,

Duration - 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.  !

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1 Attachment 11 to GNRO-99/00011  ;

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MAIN STEAM SAFETY RELIEF VALVE CHALLENGES 1998 .i l

i l There were no main steam line safety relief valve challenges occurring in 1998. i l.

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Attachment III to GNRO-99/00011 Page 1 of 4 GGNS UNIT 1 ANNUAL REPORT MAN-REM EXPOSURE - 1998 This section contains a tabulation of the number of station, utility and other personnel receiving exposures greater than 100 mrem / year and their associated man-rem exposure I

according to work and job function. Also included is a tabulation of the number of persor,nel by exposure range.

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Grand Gulf Nuclacr Stttion Date: 09-FEB-1919 08:19 P.O. Box 754 Port Gibson MS 39150 , .

LICENSE: NPF-2 Regulatory Guide 1.16 Information End of Year Report 1998 Number of Personnel

> 100 mrem Total man-rem

• Nork and Job Function Station Utility Contractor Station Utility Contractor 6 ROUTINE OPERATIONS AND SURVEILLANCE MAllfrENANCE AND CVNSTRUCTION 3 0 23 1.321 0.136 8.795 OPERATIONS 51 3 1 17.590 0.701 2.774 HEALTH PHYSICS 19 2 20 6.225 0.935 9.000 SUPERVISORY 5 1 2 1.679 0.343 0.926 ENGINEERING 3 0 0 1.786 0.045 0.017 ROUTINE PLANT MAINTENANCE MAINTENANCE AND CONSTRUCTION 108 25 231 40.128 9.570 96.074 OPERATIONS 12 0 0 5.320 0.018 0.003 HEALTH PHYSICE' 14 2 18 6,332 0,298 3.975 SUPERVISORY 6 0 9 1.530 0.224 3.794 ENGINEERING 8 0 32 2.016 0.073 15.619 INSERVICE INSPECTION MAINTENANCE AND CONSTRUCTION 0 0 17 0.060 0.002 5.824 OPERATIONS 0 0 0 0.000 0.000 0.000 HEALTH PHYSICS 0 0 0 0.000 0.000 0.046 SUPERVISORY 1 5 15 0.425 0.701 5.189 ENGINEERING 0 0 0 0.153 0.022 0.050 SPECIAL PLANT MAINTENM MAINTENANCE AND CONSTRUCTION 22 2 43 9.270 1.070 20.541 OPERATIONS O O O 1.077 0.007 0.340 HEALTH PHYSICS S 0 4 1.471 0.000 1.049 SUPERVISORY 2 0 0 0.691 0.079 0.072 ENGINEERING 1 0 8 0.335 0.003 1.491

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s Regulttory Guide 1.16 Information End of Yesr Report 19?S Number of Personnel

> 100 mrem Total stan-rem

• Work and Job Function Station Utility Contractor Station Utility . Contractor WASTE PROCESSING MAINTENANCE AND CONSTP.UCTION O O O 0.185 0.002 0.265 OPERATIONS 8 0 1 1.717 0.000 0.390

• HEALTH ?HYSICS 2 0 0 0.837 0.000 1.229 SUPEVISORY 0 0 'O 0.031 0.000 0.000 ENGINEERING 0 0 0 0.035 0.000 0.232 c REFUELING MAINTENANCE AND CDNSTRUCTION 0 0 15 0.026 0.061 3.C65 OPERATIONS 4 1 0 0.695 0.306 0.000 NEALTH PHYSICS O O O 0.016 0.000 0.001 SUPERVISORY 3 2 0 0.526 0.666 0.001 -

ENGINEERING 2 1 0 0.531 0.197 0.086 Totals MAINTENANCE AND CONSTRUC"f1ON 133. 27 329 50.990 10.841 134.564 OPERATIONS 75 4 2 26.399 1.032 3.507 HEALTH PHYSICS 40 4 42 14.881 1.233 15 300 SUPERVISORY 17 8 ?6' 4.882 2.013 9.982 ENGINEERING 14 1 40 4.856 0.340 17 495 Grand Totals 279 44 439 102.008 15.459 180.848

• The total radiation exposure of the above personnel constitutes 100% of the site's exposure for the year.

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Attachment III to GNRO-99/00011 Page 4 of 4 SPECIAL MAINTENANCE ACTIVITIES The following is a description of all special Plant Maintenance activities for 1998 and the total dose for each category:

Description Dose (Rem)

Remove contamination from concrete located west of .086 the condensate storage tank.

Fire watch rounds due to problems with conduit fire 1.864 seals.

Emergent work activities during RF09. 2.872 Inspection and repair ofpenetration fire seals in all .817 elevations in Auxiliary Building.

Minor MCP and DCP work activities. 3.583 Steam affected area work. 9.279 Emergent work activities. .051 Replacement of L&N oxygen analyzers with .720 Orbistere analyzers on Panel 1G33Z020.

Sand blast and NDT the strongback head (F13-E009) .025 dryer sept. strongback rad shield (F15-E020).

Hydrogen injection testing. .305 Repair flange leak on RWCU Hx A (G33-B001 A). 1.568 Modify ventilation duct in the drywell. .423 Repair broken / damaged grating, studs and hold- 1.003 down plates in the drywell.

Cut out/ replace valves G33-F052B, B21-F143B, 4.860 B21-F143C, and B21-F079B per disposition ofER 96-0944 and modify inspection ports.

RWCU heat exchanger bottom head modification 9.758 and shielding installation.

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Attachment IV to GNRO-99/00011 1 l Page1of1 i

L FAILED FUEL INDICATIONS / INSPECTIONS - 1998 Cycle 10 startup and steady-state data indicate there are no fuel failures in the Grand Gulf j l core.-

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