GNRO-2003/00009, Annual Operating Report

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Annual Operating Report
ML030860200
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 03/20/2003
From: Bottemiller C
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2003/00009
Download: ML030860200 (9)
v • d • e


Text

c.

Waterloo Road P.0. Box 756 Port Gibson, MS 39150 lei 601 437 6299 Manager Plant Licensing March 20, 2003 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk

Subject:

2002 Annual Operating Report Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 GNRO-2003l00009 Ladies and Gentlemen:

Entergy Operations, Inc. is transmitting the Grand Gulf Nuclear Station (GGNS) Unit 'I Annual Operating Report for 2002. This report is in accordance with the reporting program described in Regulatory Guide 1.16, Revision 4, Part 6.1.b as modified by the NRC letter to GGNS dated May 25, 1987 (MAEC-87/0131).

Provided as attachments are:

1. A narrative summary of operating experience during the year 2002,
2. Main Steam Line Safety Relief Valve challenges,
3. A tabulated annual report of personnel exposure greater than I 0 0 mremlyr, and
4. A summary of failed fuel indicationslinspections.

This letter does not contain any commitments.

GO30009

March 20, 2003 GNRO-2003/00009 Page 2 of 2 If you have any questions, please contact Charles A. Bottemiller at (601) 437-6299 or Ann M. Townsend at (601) 437-6486.

Yours truly, CA BIAMT:amt attachments: 1. Summary Of Operating Experience - 2002

2. Main Steam Safety Relief Valve Challenges - 2002
3. Person-rem Exposure - 2002
4. Failed Fuel Indications/lnspections- 2002 cc:

Hoeg T. L. (GGNS Senior Resident) (w/a)

Levanway D. E. (Wise Carter) (w/a)

Reynol ds N. S. (w/a)

Smith L. J. (Wise Carter) (w/a)

Thomas H. L. (w/o)

U.S. Nuclear Regulatory Commission ATTN: Mr. E. W. Merschoff (w/2)

Regional Administrator, Region IV 61 1 Ryan Plaza Drive, Suite 400 Arlington, TX 7601 1-4005 U.S. Nuclear Regulatory Commission ATTN: Mr. David H. Jaffe NRR/DLPM (w/2)

ATTN: FOR ADDRESSEE ONLY ATTN: U.S. Postal Delivery Address Only Mail Stop OWFN/7D-1 Washington, D.C. 20555-0001 GO30009

Attachment I to GNRO-2003/00009 2002

SUMMARY

OF OPERATING EXPERIENCE The following is a summary of Grand Gulf Nuclear Station (GGNS) Unit 1 operating experience for the 2002 calendar year. During 2002, the reactor was critical for 8,197.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> with the generator on line for 8,140.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Date Cause & Corrective Action Duration Time 06/22/02 Automatic reactor scram after a partial loss of offsite power 73.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when a raccoon caused a ground fault in Service Transformer 21 resulting in a Turbine Trip.

09113/02. Manually scrammed reactor at reduced power @ 2001 hour0.0232 days <br />0.556 hours <br />0.00331 weeks <br />7.613805e-4 months <br /> for 412.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Refueling # I 2.

09113/02 Refueling # I 2 continued until 1408 hour0.0163 days <br />0.391 hours <br />0.00233 weeks <br />5.35744e-4 months <br /> on 10/6/02 when 134.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> synchronized to grid.

11115/02 Core thermal power was reduced when Circulating Water Pump 0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> BJJtripped following failure of load center trip device.

GO30009

Attachment I I to GNRO-2003/00009 Page 1 of 2 2002 MAIN STEAM SAFETY RELIEF VALVE CHALLENGES This section contains a summary of Main Steam Safety Relief Valve Challenges which occurred during 2002.

GO30009

Attachment I I to GNRO-2003/00009 Page 2 of 2 DOCKET NO. 50-416 DATE 3118/03 COMPLETED BY A. M. Townsend TELEPHONE 437-6486 MAIN STEAM SAFETY RELIEF VALVE CHALLENGES Date of Occurrence: June 22,2002 Plant Operating Condition :

Rx Thermal Power: 100%

Rx Power (MWE): 1157 Rx Pressure (psig): 1025 Rx Temperatures: 549 F O

Rx MODE: 1 Number of main steam line SRVs: 20 Number of SRVs affected by event: 11 Narrative:

On June 22, 2002, GGNS experienced and opening of eleven Main Steam Safety ReliefNalves (SRV). The reactor automatic scrammed after a partial loss of offsite power when a raccoon caused a ground fault in Service Transformer 21 resulting in a Turbine Trip. The following SRVs actuated:

821F051A 821F047A B21F047L B21F051B B21F047C B21F051D B21F047D B21F051F B21F047G B21F051K 821F047H GO30009

A t t a c h m e n t I11 T o GNRO-2003/00009 P a g e 1 of 3 GGNS UNIT 1 ANNUAL RIEP0R.T MAN-REM EXPOSURE: - 2002 This section contains a tabulation of the number of station, utility and other personnel receiving exposures greater than 100 rnremjyear and their associated man-rem esposure according to work and job function.

Also included is a tabulation of the number of personnel by exposure range.

A t t a c h m e n t I11 T o GNRO-2003/00009 Page 2 of 3 The following is a break down of dose received due to Special Plant Maintenance.

Person-rem RHR A recovery & repair 11* O I 1 B33F067 B repair 3.098 E l2 piping replacement 1.498 E51F066 mod 1.472 RHR B recovery & repair 1.166 Furmanite Repair various components I.020 Forced outage 0.933 N64F020a flange repair 0.583 G33F267 reliev valve 0.529 U N sump pump repair 0.466 B33F028C solenoid repair 0.290 Minor Mods 0.376 Platform mod 0.220 Diving HFTS repair 0.206 Jet pump repair 0.146 He leak check of cond 0.155 Tip C replacement 0.1 10 TOTAL 23.279

A t t a c h m e n t I11 To GNRO-2003/00009 Page 3 of 3 Entergy Operations, Inc. Date: 18-FEB-2003 15:Ol Grand Gulf Nuclear Station P.O. Box 756 Port Gibson, M S .

39150 LICENSE: NPF-29 Regulatory Guide 1.16 Information End of Year Report 2002 Number of Personnel

> 100 mrem Total man-rem

  • Work and Job Function Station Utility Contractor station Utility Contractor ROUTINE OPERATIONS AND SURVEILLANCE MAINTENANCE AND CONSTRUCTION 0 0 0 0.121 0.001 0.051 OPERATIONS 32 0 0 8.573 0.153 0.161 HEALTH PHYSICS 12 3 7 3.308 1.154 2.605 SUPERVISORY 1 0 1 0.753 0.037 0.460 ENGINEERING 0 0 0 0.398 0.025 0.000 ROUTINE PLANT MAINTENANCE MAINTENANCE AND CONSTRUCTION 72 20 173 22.141 6.119 74.452 OPERATIONS 7 1 0 3.241 0.275 0.036 HEALTH PHYSICS 18 4 9 5.490 1.929 2.851 SUPERVISORY 5 5 16 2.265 1.306 5.738 ENGINEERING 0 0 5 1.114 0.018 5.019 INSERVICE INSPECTION MAINTENANCE AND CONSTRUCTION 0 0 0 0.002 0.000 0.797 OPERATIONS 0 0 0 0.000 0.000 0.000 HEALTH PHYSICS 0 0 0 0.004 0.000 0.008 SUPERVISORY 0 0 0 0.098 0.146 0.302 ENGINEERING 0 0 0 0.000 0.000 0.000 SPECIAL PLANT MAINTENANCE MAINTENANCE AND CONSTRUCTION 20 0 35 4.828 0.886 14.042 OPERATIONS 0 0 0 0.315 0.034 0.032 HEALTH PHYSICS 1 0 2 0.626 0.076 0.699 SUPERVISORY 0 1 0 0.173 0.524 0.717 ENGINEERING 0 0 0 0.300 0.022 0.005 WASTE PROCESSING MAINTENANCE AND CONSTRUCTION 1 0 1 0.452 0.004 0.321 OPERATIONS 0 0 1 0.010 0.000 0.294 HEALTH PHYSICS 1 0 0 0.435 0.037 0.016 SUPERVISORY 0 0 0 0.076 0.000 0.000 ENGINEERING 0 0 0 0.000 0.000 0.000 REFUELING MAINTENANCE AND CONSTRUCTION 4 0 39 1.442 0.371 11.735 OPERATIONS 2 0 0 1.005 0.000 0.046 HEALTH PHYSICS 4 0 2 1.128 0.339 1.734 SUPERVISORY 1 0 0 0.461 0.094 0.043 ENGINEERING 0 0 0 0.152 0.000 0.000 Totals MAINTENANCE AND CONSTRUCTION 97 20 248 28.986 7.381 101.398 OPERATIONS 41 1 1 13.144 0.462 0.569 HEALTH PHYSICS 36 7 20 10.991 3.535 7.913 SUPERVISORY 7 6 17 3.826 2.107 7.260 ENGINEERING 0 0 5 1.964 0.065 5.024 Grand Totals 181 34 291 58.911 13.550 122.164
  • The total radiation exposure of the above personnel constitutes 100% of the site's exposure for the year

Attachment IV to GNRO-2003/00009 Page Iof 1 FAILED FUEL INDICATIONS/INSPECTlONS - 2002 Failed fuel assessments performed during the current cycle (Cycle 13) indicate a single, large-sized fuel failure exists in the Grand Gulf core.

The failure occurred on 11/21/2002. Fuel Reliability Index peaked at 9015 pCi/sec and after failure suppression, leveled out at about 400 pCi/sec. Power Suppression Testing was conducted to determine the location of the failure.

Two rods were inserted (in cells 36-45 and 40-45) for suppression of the failure.

Power suppression test data indicates that the failure is located in cell 40-45.

Using cesium data collected during the down power for the suppression testing, it was determined that the failure is most likely located in a fresh Atrium-I 0 bundle.

Cell 40-45 contains two fresh bundles. If warranted, a mid-cycle outage will be performed to remove the fuel failure from the core. Either during this mid-cycle outage or during RFI 3, fuel sipping will be performed to determine where the failure is located. Subsequent inspections will be conducted on this bundle or bundles if it is determined from sipping results that there is more than 1 failure.

No known bundles where failures are located will be reinserted, unless the fuel rod containing the failure is removed and replaced via reconstitution.

GO30009

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