ML20203H974

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1997 Annual Operating Rept, for Ggns,Unit 1
ML20203H974
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 12/31/1997
From: Eaton B
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-98-00018, GNRO-98-18, NUDOCS 9803030383
Download: ML20203H974 (9)


Text

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==Enteroy O

wr""""c Port G;t> son fA5 39EO Tel(01437 2123 Tebruary 23, 1998 .i e,m4

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U.S. Nuclear Regulatory Commission Mall Station P1-137 Washington, D.C. 20555 Attention: Document Control Desk

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 1997 Annual OperatinD Report ,

GNRO-98/00018 Gentlemen:

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

Unit 1 Annual Operating Report for 1997. 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 1997,
2. Main Steam Line Safety Relief V. , challenges,
3. A tabulated annual report of personnel exposure greater than 100 mremlyr, and
4. A summary of failed fuelindications/ inspections.

Yours truly, to w WAE/CWG attachments /

cc: (See Next Page)

/

IE D 9003030383 971231 ,

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GNRO 98/00018 Page 2 of 3 ,

cc: Mr. D. C. Hintz (w/s)

Mr. N. S. Reynolds (w/a) i

' Mr. Jager Smith (w/a)

Mr. H. L Thomas (w/o)

Ms. K. D. Weaver (w/a)

Mr. Ellis W. Mershoff (w/a)

Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive Suite 400 Arlington, TX 76011 Mr. Jack Donohew, Project Manager Offics of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C. 20555 F

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' Attachment i to GNRO 98/00018 Pageiori

SUMMARY

OF OPERATING EXPERIENCE 1997 The following is a summary of Grand Gulf Nuclear Station (GGNS) Unit 1 operating experience for the 1997 calendar year. During 1997, the reactor was critical for 8,760.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> with the generator on line for 8,760.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

On 9/16/97, thermal power was reduced to approximately 68% following a Reactor Feed Pump 'B' trip when Steam Jet Air Ejector supply steam valve N62F505A was opened after drifting toward closure, with hotwelllevel Hi alarm on. Rated thermal power restored on 9/19/97. Duration time - O hours.

On 12/14/97, reactor power was reduced to approximately 55% to repair the main condenser tube leak. Turbine Stop and Control Valve operability surveillance test and control rod sequence exchange were performed ahead of the original schedule, taking advantage of the low-power operation. Duration time - O hours.

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, Attachment 11 to GNRO-98/00018 Page1ofI MAIN STEAM SAFETY RELIEF VALVE CHALLENGES 1997 l

There were no main steam line safety relief valve challenges occurring in 1997.

Anachment lit to GNRO 98/00018 Page 1 of 4 GGNS UNIT 1 ANNUAL REPORT MAN REM EXPOSURE 1997-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 according to work and job function. Also included is a tabulation of the number of personnel by exposure range.

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'.Attrchment to GNRO-98/00018': ' f.

  • Poguis. tory C> aide 1.16 Information
  • '., End of Year Report 1#37.

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  • 100 erse _ _ Total man-rom *

- Sloth and Job Function - Station ' DL111ty - Carstractor Station - t!tility Ctatractor sensTE PeterweelsIG Im!sITEBUL1CE AIID CORISTRUCTICar 0 -C. 3 0.376 0.000 0.001 OPERATICIIS 0 0 0 ,0.155 0.000 0.000 4' IIRA1ldi PHYSICS - '

1 0 1 0.312' 'O.000 0.141 SUPERVTSORY .0 0- 0 0.000 0.000 0.000 EBIGINISIG 0 0 3 0.053 0.000 1.245

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.0 0. O O.000 0.000 0.000 IMIUTERIIWCE MC CCM8TRUCTICW OPERATICIIS- 0 0 -0 0.000 0.000 0.000 0 0 0 0.030 0,000' O.000 IISALTH PilYSICS

> S"7PERVISORY -0 0 0 0.000 0.000 0.000 EIBGIIIEERIIIG 'O -0 0 0.000 0.000 0.000-Totals Mh!NTEllAIBCE AIID CDIISTRUCTICM 74 0 92 20.355 0 002 30.818 OPEllATICIIS 35 0 2 9.807 . J.002 4.132 IIEALTH Pl~"TM 39 0 5 8.299 0.004 1.404 SUPERVISOLC 0 0 3 0.640 0.011 1.968 EleGIh2EltIIIG 3 0 3 1.323 0.000 1 303 Grand Totals '* O 95 40.423 'O.019 69.625

  • The total radiation exposure of the etc.no personnel constitutes'100i of the site's exposure for the year.

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Attachment to GNRO-98/00018 .-

, Page 4 of 4 -

The following is a description of all Special Plant Maintenance activities for 1997 and the totini dose for each catagory:

Description Dose (REM)

Minor Design Plant Changes 2.566 Plant Material Upgrade in all areas of the Plant 50.039 Install alternate suction path for Spent Resin Tank 0.0 0 Refueling Water Pump Internal Modifications 0.598 Conduit Fire Seal problems 0.943 ECCS Suction Suaiaer Civil Survey for pending modification 0.348 Repairs to steam systems 8.940 Rtpair Leaking Conderser Tubes. 1.549 E_ -

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  • Attachment IV to GNRO-98/00 Page1ofI <

FAILED FUEL INDICATIONS / INSPECTIONS - 1997 .--

Cycle 9 startup and steady-state data indicate there are no fuel failures in the Grand Gulf core.

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