GNRO-2004/00016, Annual Operating Report

Annual Operating Report

ML040970468
Person / Time
Site:	Grand Gulf
Issue date:	03/29/2004
From:	Bottemiller C Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2004/00016, RG-1-016, Rev 4
Download: ML040970468 (9)

Text

Entergy Operations, Inc.

Entergy Waterloo Road PO. Box 756 Port Gibson, MS 39150 Tel 601 437 6299 Charles A. Bottemiller Manager Plant Ucensing GNRO-2004/00016 March 29, 2004 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

Subject:

2003 Annual Operating Report Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29

Dear Sir or Madam:

Entergy Operations, Inc. is transmitting the Grand Gulf Nuclear Station (GGNS)

Unit 1 Annual Operating Report for 2003. This report is in accordance with the reporting program described in Regulatory Guide 1.16, Revision 4, Part C.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 2003,

2. Main Steam Line Safety Relief Valve Challenges,

3. A tabulated annual report of personnel exposure greater than 100 mrem/yr, and

4. A summary of failed fuel indications/inspections.

This letter does not contain any commitments.

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GNRO-2004/00016 Page 2 of 2 If you have any questions or require additional information, please contact William B. Abraham at (601) 437-2319.

Yours truly, CABIWBA:amt attachments: 1. Summary of Operating Experience - 2003

2. Main Steam Safety Relief Valve Challenges - 2003

3. Per-rem Exposure - 2003

4. Failed Fuel Indications/Inspections - 2003 cc:

U.S. Nuclear Regulatory Commission ATTN: Mr. Bruce S. Mallett (w/2)

Regional Administrator, Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 U.S. Nuclear Regulatory Commission ATTN: Mr. Bhalchandra Vaidya, NRR/DLPM (w/2)

ATTN: ADDRESSEE ONLY ATTN: U.S. Postal Delivery Address Only Mail Stop OWFNI7D-1 Washington, D.C. 20555-0001 NRC Senior Resident Inspector (w/o)

Grand Gulf Nuclear Station Port Gibson, MS 39150 Levanway D. E. (Wise Carter) (wia)

Reynolds N. S. (wia)

Smith L. J. (Wise Carter) (wia)

Thomas H. L. (w/o)

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Attachment I to GNRO-2004/00016 2003

SUMMARY

OF OPERATING EXPERIENCE The following is a summary of Grand Gulf Nuclear Station (GGNS) Unit 1 Operating Experience for the 2003 calendar year. During 2003, the reactor was critical for 8,641.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> with the generator on line for 8,575.1 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 1/30/03 Reactor manually scrammed at 1054 hour0.0122 days <br />0.293 hours <br />0.00174 weeks <br />4.01047e-4 months <br /> when apparently a failed 37.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> wiring created a short-circuit while performing work on condensate demineralizer system, resulting in isolation of inlet and outlet isolation valves, which caused loss of Condensate Booster Pumps and Condensate Pumps, and subsequently the Reactor Feedpumps. A CR has been generated to determine the root cause and corrective actions.

1/30/03 Outage continued until synchronization to grid at 0001 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> on 0.02 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 02/01/03. Startup followed.

4/24/03 Reactor scram @0948 following partial loss of offsite power when high 147.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />

.wind caused failure of disconnect and loss of 500 KV line.

9/12/03 Sequence Exchange 40.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 9/27/03 FW heater leak 9.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 10/11/03 Reduced load 1.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> 11/08/03 C11 Surveillance 17.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 12/06/03 Reduced load (Maintenance) 11.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> G040016

Attachment II to GNRO-2004/00016 DOCKET NO. 50-416 DATE 3/24104 COMPLETED BY William B. Abraham TELEPHONE 437-2319 2003 MAIN STEAM SAFETY RELIEF VALVE CHALLENGES This section contains a summary of Main Steam Safety Relief Valve Challenges which occurred during 2003.

Date of Occurrence: April 24, 2003 Plant Operating Condition:

Rx Thermal Power: 100%

Rx Power (MWE): 1344 Rx Pressure (psig): 1032

'Rx Temperatures: 5400 F Rx MODE: 1 Number of main steam line SRVs: 20 Number of SRVs affected by event: 16 Narrative:

On April 24, 2003, GGNS experienced an opening of sixteen Main Steam Safety ReliefNalves (SRV). The reactor automatically scrammed due to a partial loss of offsite power. The scram occurred as a result of a locking collar breaking on disconnect J5205, allowing the disconnect to close and the 500KV going to ground through the grounding straps installed for breaker maintenance. The following SRVs actuated:

B21FO41A B21F047A B21 F051 B B21 F041B B21F047C B21 F051 C B21 F041 C B21F047D B21 F051 D B21F041 E B21F047G B21 F051 F B21 F041G B21F047H B21 F051 K B21F041K G040016

Attachment III to GNRO-2004/00016 Page 1 of 3 GGNS UNIT 1 ANNUAL REPORT MAN-REM EXPOSURE - 2003 This section contains a tabulation of the number of station, utility and other personnel receiving exposures greater than 100 mremlyear and their associated man-rem exposure according to work and job function. Also included is a tabulation of the number of personnel by exposure range.

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Attachment IlIl to GNRO-2004/00016 Page 2 of 3 The following is a break down of dose received due to Special Plant Maintenance.

Description Person-rem Furmanite 1.163 E12FO03A Mod 1.082 Kaowool 0.439 G17F106A Valve Replace 0.323 Reverse Osmosis Modification 0.767 D Tip Replace 0.100 G41 Mechanical Seal 0.146 LPFW 4B/4A 1.145 DW Entry 0.376 IRM C Repair 0.102 DW Sump Repair 1.407 TOTAL 7.050 G040016

Attachment III to GNRO-2004/00016 Page 3 of 3 Entergy Operations, Inc. Dates 01-MAR-2004 08s15 Grand Gulf Nuclear Station P.O. Box 756 Port Gibson, MS.

39150 LICENSE: NPP-29 Regulatory Guide 1.16 Information End of Year Report 2003 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 0.066 0.001 0.037 OPERATIONS 26 0 0 6.501 0.001 0.194 HEALTH PHYSICS 13 0 0 2.960 0.000 0.015 SUPERVISORY 1 0 0 0.464 0.006 0.115 ENGINEERING 0 0 0 0.415 0.000 0.005 ROUTINE PLANT MAINTENANCE MAINTENANCE AND CONSTRUCTION 27 0 6 8.640 0.007 2.337 OPERATIONS 0 0 0 0.688 0.000 0.026 HEALTH PHYSICS 2 0 2 1.135 0.000 0.415 SUPERVISORY 1 0 0 0.217 0.001 0.011 ENGINEERING 0 0 0 0.139 0.000 0.038 INSERVICE INSPECTION MAINTENANCE AND CONSTRUCTION 0 0 0 0.010 0.000 0.041 OPERATIONS 0 0 0 0.000 0.000 0.000 HEALTH PHYSICS 0 0 0 0.000 0.000 0.000 SUPERVISORY 0 0 0 0.005 0.000 0.000 ENGINEERING 0 0 0 0.000 0.000 0.000 SPECIAL PLANT MAINTENANCE MAINTENANCE AND CONSTRUCTION 7 0 4 2.489 0.051 2.789 OPERATIONS 1 0 0 0.160 0.000 0.000 HEALTH PHYSICS 3 0 0 1.189 0.000 0.019 SUPERVISORY 0 0 0 0.070 0.000 0.026 ENGINEERING 0 0 0 0.083 0.002 0.000 WASTE PROCESSING MAINTENANCE AND CONSTRUCTION 0 0 0 0.204 0.000 0.016 OPERATIONS 1 0 1 0.148 0.000 0.468 HEALTH PHYSICS 1 0 3 0.540 0.000 0.918 SUPERVISORY 0 . 0 0 0.011 0.008 0.000 ENGINEERING 0 0 1 0.000 0.000 0.359 REFUELING MAINTENANCE AND CONSTRUCTION 0 0 0 0.003 0.000 0.000 OPERATIONS 0 0 0 0.038 0.000 0.000 HEALTH PHYSICS 0 0 0 0.020 0.000 0.010 SUPERVISORY 0 0 0 0.012 0.000 0.000 ENGINEERING 0 0 0 0.007 0.000 0.000 Totals MAINTENANCE AND CONSTRUCTION 34 0 10 11.412 0.059 5.220 OPERATIONS 28 0 1 7.535 0.001 0.688 HEALTH PHYSICS 19 0 5 5.844 0.000 1.377 SUPERVISORY 2 0 0 0.779 0.015 0.152 ENGINEERING 0 0 1 0.644 0.002 0.402 Grand Totals 83 0 17 26.214 0.077 7.839

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

i j. : I i 1~

Attachment IV to GNRO-2004/00016 FAILED FUEL INDICATIONSIINSPECTIONS - 2003 Grand Gulf Nuclear Station (GGNS) began cycle 13 operation on October 6, 2002. One fuel failure occurred in November, 2002. This failure had been identified as a first cycle Atrium 10, non-liner assembly and had been suppressed with control rod insertion. Sum-of-six offgas activity has been relatively stable for several months at approximat4ely 12,000-14,000 [Ci/sec with Xe-1 33 of approximately 35 pCi/sec. This indicated that the failure had essentially 'sealed' and only recoil, tramp uranium present in the coolant from washout was maintaining the increased offgas levels. Additional soft operating restrictions have also been applied to the suspect core area.

During a routine control rod sequence exchange on September 12, 2003, a spike in offgas grab sample results was noted. Xe-133 increased to approximately 124 pCi/sec, with little change in sum-of-six or Xe-1 38. This was somewhat expected for a downpower and was initially attributed to a release of built up inventory from the existing failure. Following return to full power, this value decreased over the next two weeks to approximately 55-60 pCi/sec where it has stabilized. Xe-138 and sum-of-six returned to their pre-exchange levels.

Grand Gulf reactor engineering and fuels personnel, along with fuel vendor experts, have determined that the offgas signature is most likely that of a new, tight failure in a medium powered assembly. This conclusion is drawn from the fact that the Xe-1 33 did not return quickly to the pre-exchange levels as would have been expected for a typical downpower inventory release spike. Also, Xe-138 and sum-of-six values did not show an increasing trend as should be seen from a re-opening of the existing failure such that fuel washout recurs. No increases in coolant 1-134, Np-239, Sr-91/92, or U-235 have been seen. Limited coolant cesium data is of high uncertainty and not considered reliable for use in determining the age of the new failure, especially given its apparent small size in the presence of an existing large failure.

Grand Gulf cycle 13 has a mixture of GE-11 fuel (both Process 6 and Process 7 cladding) and Atrium 10, non-liner fuel. The failure is not believed to be in one of the process 6 assemblies, which are in low power edge locations. Current plans are to perform a cost/benefit/risk evaluation of possible power suppression testing for locating the failure at this point in the cycle.

GGNS will also continue monitoring with routine offgas and coolant samples. Additional cesium ration results will be determined following any down powers. Future actions will be governed by the behavior of the failure over the next several weeks.

Although the indication of a second leak was identified on September 13, 2003, the actual leak was not confirmed until December 6, 2003.

• NOTE: Even though this report is for the year 2003, the inspection of the failed fuel occurred during Refueling Outage 13, in February and March, 2004, and the results were:

Fuel sipping during RF13 identified two failed bundles. One failure was in a once-burnt ATRIUM-10 bundle, namely SPJ096 located in cell 36-45. The location of this failure was G040016

consistent with predictions following PST performed in December, 2002. The second failure was in a thrice-burnt GE11 bundle (GEC667) and was the failure predicted following the September, 2003 sequence exchange.

An analysis of the results from pool-side visual inspections of these two failures is documented in CEO 2004-00049 [2]. This analysis concluded that the ATRIUM-10 failure was most likely due to debris or an isolated fabrication issue. This conclusion was based on the failure occurring after just a few weeks of operation, the lack of any additional ATRIUM-10 failures during Cycle 13, and industry experience.

The cause of the failure in the third cycle GE11 bundle could not be determined. The failed rod was one row in from a non-bladed edge. While numerous failure modes are possible, no definite cause could be assigned. However, considering the good performance of the previous three batches of GE11 fuel at GGNS and the overall excellent appearance of the bundle, it was concluded that the 28 GEC bundles reinserted for Cycle 14 would continue to have excellent reliability.

In addition to the two failed bundles, the RF13 inspection scope included two high-power once and twice-burnt ATRIUM-10 bundles. These bundles were in overall excellent condition. The curd level on these two bundles was typical with little or no tenacious crud and no cladding oxide spallation.

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