ML20011D990

Monthly Operating Rept for Dec 1989 for Grand Gulf Unit 1. W/900115 Ltr

ML20011D990
Person / Time
Site:	Grand Gulf
Issue date:	12/31/1989
From:	Cottle W, Zinke G SYSTEM ENERGY RESOURCES, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AECM-90-0018, AECM-90-18, NUDOCS 9001260269
Download: ML20011D990 (6)

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January 15,,1990-U.S. Nuclear Regulatory Commission

-Mail Station P1-137' Washington, D.C. 20555-Attention:' Document Control Desk ,

Gentlemen:

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Doexet No. 50-416 License No. NPF-29 ..

Monthly Operating Report AECM-90/001B In accordance with the requirements of Technical Specification 6.9.1.10.

-System Energy Resources,-Inc. (SERI) is providing the Monthly Operating Report for Grand Gulf Nuclear Station Unit 1 for December 1989.(attachment).

If you have any questions or require additional information, please contact this office. '

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Attachment cc: Mr. D. C. Hintz,(w/a)

Mr. T. H. Cloninger_(w/a) ,

Mr. R. B. McGehee-(w/a) '

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

L Mr. H. L. Thomas (w/o) h- 1 Mr H. O. Christensen (w/a)

Mr. Stewart D. Ebneter (w/a)

Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta St., N.W.,. Suite 2900 Atlanta, Georgia 30323 Mr. L. L.-Kintner, Project Manager (w/a)

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 Mall Stop 14B20 Washington, D.C. 20555 doc - 1 90o t a. co O 2 (o 9 8913 3l  ?

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DOCKET NO. 50-416 ,

DATE 01/08/90 '

COMPLETED-BY G. A. Zinke OPERATING STATUS TELEPHONE (601)437-2459

1. Unit Name: GGNS UNIT 1 Reporting Period: -l Notes: }

l2. December 1989 l

3. Licensed Thermal Power (MWt): 3833 MWt l l

4. Nameplate Rating (Gross MWe): 1372.5 MWe l

5. Design Electrical Rating (Net MWe): 1250 MWe

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6. Maximum Dependable Capacity (Gross MWe): 1190 MWe l- l 7- . Maximum Dependable Capacity (Net MWe): 1142 MWe l

, 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last l 1 Report. Give Reasons:

N/A

9. Power Level To Which Restricted, If Any (Net MWe): N/A

-10. Reasons For Restrictions, If Any: N/A This Month Yr to Date Cumulative

11. Hours'In. Reporting Period ,

744 8,760 45,[62.0

12. Number of Hours Reactor Was Critical 725.6 7,005.5 35,055.7

13. Reactor Reserve Shutdown Hours 14.' Hours Generator On-Line 714 6,818.2 33,247.8

.15. Unit Reserve Shutdown Hours -0 -

16. Gross Thermal Energy Generated (MWH) 2,697,257 25,109,163 111,565,578

17. Gross Electrical' Energy Generated (MWH) 892,060 8,169,170 35,323,960

18. Net Electrical Energy Generated (MWH) 858,276' 7,846,282 33,737,993

19. Unit Service Factor 96.0 77.8 76.5

20. Unit Availability Factor 96.0 77.8 76.5

21. Unit Capacity Factor (Using MDC Net) 101.0 78.4 71.6

22. Unit Capacity Factor (Using DER Net) 92.3 71.7 64.7

23. Unit Forced Outage Rate 4.0 4.5 5.7

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Ea'ch): '

None

25. If Shut Down At End Of Report Period. Estimated Date of Startup: N/A

26. Units In Test Status (Prior to Commercial Operation).

Forecast Achieved INITIAL CRITICALITY 08/18/82 L

INITIAL ELECTRICITY 10/20/84 COMMERCIAL OPERATION 07/01/85 i

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DOCKET NO. 50-416 UNIT 1 DATE 01/08/90 COMPLETED BY G. A. Zinke TELEPHONE 601-437-2459 MONTH December 1989-

. DAY AVERAGE DAILY POWER LEVEL DAY. AVERAGE' DAILY POWER LEVEL (MW.-Net) (MW.-Net) +

1 1216.2 17 1227.7 2 1201.9 18 1225.0 3 1220.7 19 1222.7 4 1220.5 20 1228.7 5 '1206.8 21 1232 6 1196.2 22 1226 7 1127.6 23 1175.7 8 1220.2 24 1230.2 s 9 1220.6 25 1224.5 10 1210 26 1216.6 11 1208.5 27 1209.7 12 1222.5 28 1207.3

- 13 1224.0 29 1140.9 '

14 1217.1~ 30 643.5 15 1220.6 31 0

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UNIT S!!UTDOWNS AND POWER REDUCTIONS IXX'KET NO. 50-416 -

UNIT NAME 1 DATE 01/08/90 COMPLETED BY G. A. Zinke REPORT MONTil- December 1989 l l l l l l Method of_ l Licensee l l l Cause & Corrective lNo. l Date -l Type l Duration l Reason l Shutting Downl Event l System l Component l Action To l l l (1) l Hours l (2) l Reactor l Report # l Code l Code l Prevent Recurrence l l l l l (3) l l l (4) l (5) l l l l l l l l l 1 I l89- l12/30/89[ F l 30.0 l A l 2 l 89-019 l KI l XT l A manual scram was initated l010 l l l l l l l l l following loss of Plant Service l l l l l l l l l l l l l Water (PSW) due to faulty l l l l l l l signals received from it's l l l l l l l l l l Microwave control System. PSW l l l l l l l l l l l l was restored by disconnecting l l l

l l l l l l the computer inputs to the bus l l l l l l l l l l l breaker controls and restoring l l l l l l l l power locally. The breaker l l l l l l l l l l control inputs will remain l l l l l l l l l l l l disconnected pending completion-l l l l_ l l l l of failure i'nvestigations.

l l l l l l l 1 1 I l l l 1 1 I I l l 1 l1 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A-Equipment Failure 1-Manual for Preparation of Data (Explain) 2-Manual Scram Entry Sheets for Licensee B-Maintenance or Test 3-Automatic Scram Event Report (LER)

C-Refueling 4-Continued D-Regulatory Restriction File (NUREG-0161) 5-Reduced load E-Operator Training & 6-Other Licensing Examination F-Administrative 5 G-Operational Error Exhibit ~ 1-Same Source (Explain)

Il-Other (Explain) -

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MAIN STEAM SAFETY RELIEF VALVE CHALLENGES DOCKET NO. 50-416 UNIT. 1 COMPLETED BY G. A. Zinke TELEPHONE (601) 437-2459 Date of Occurrence: December 30, 1989 Plant Operating Condition:

Rx Thermal Power 82.8% Rx Pressure (psig) 1000 Rx Mode 1 Rx Power (MWE) 1008 Rx Temperatures 540*F Number of mainsteam line SRV's: 20 Number of SEV's affected by event: 12 Narrative:

On 12/30/89, a manual reactor scram was initiated as a result of loss of Plant Service Water (PSW). The Main Steam Isolation Valves were closed in accordance with the loss of PSW Off-normal Event Procedure. A high pregsure

. reactor scram signal and ATWS/ARI initiation signal were received following the MSIV closures. Maximum reactor pressure was 1087 psig. Twelve SRV's were manually cycled one at a time to maintain reactor _ pressure-at the desired pressure range.

SRV B21F047L was cycled a total of three times. The following SRVs-were cycled-twice each: 1B21F041F , 1B21F041C, 1B21F041D , 1B21F051F , 1B21F041A, 1821F051C, 1B21F047D, 1B21F051K, 1B21F041G, 1821F047H, 1B21F051B.

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' c: - m NRC SUBMITTAL CERTIFICATION FORM (Miscellaneous).

I. Letter Number (List AECM, MAEC, LER, Violation, etc.) PEc. ONeew6 Aro#r 64 2,; Ee ' /gg '

Document Originator ' '-Datei II. Certification: Responsible Section/ Organization s e r,* E 6 c e s _5-re,e r Page/ Sentence Paragraph Number Number / Numbers , BASIS COPPENTS s Atleek,ned /J 7.- Rak o m kst L e fased oo crsns drd 1 6 McKerd L.o. - fx r,u. Fuel A -Jsha freyram - deJ' STA LG Endnes.

1. Basis: 1) Indicate when an action was or will be done (date) and how.

Responsible Supv/ Supt Date

2) If statement of fact list supporting document (s) 1.e. UFSAR, P8ID, Procedure, etc.

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3) May be a statement or conclusion which is only supported by engineering / ~

judgement which must be described under basis. Respoffsible Manager Date Signature indicates certification of the accuracy of indicated portions of the document. Document may be certified with comments.

NOTE: Use separate sheet fur each section/ organization.

I PCOM NRC SUBMITTAL CERT FORM u_____________ -__

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