ML18142B359

R.E. Ginna - Forwards Monthly Operating Status Report for Month of January 1978

ML18142B359
Person / Time
Site:	Ginna
Issue date:	02/09/1978
From:	Lang L Rochester Gas & Electric Corp
To:	Office of Nuclear Reactor Regulation
References
Download: ML18142B359 (14)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-244 REC: ORG: LANG L S DOCI3ATE: 02/09/78 NRC ROCHESTER GAS 8c ELEC DATE RCVD: 02/ 16/78 DOCTYPE: OTHER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 10 MONTHLY OPERATING REPT FQR JANUARY 1978 UNIT 1... W/ATT NARRATIVE

SUMMARY

.

PLANT NAME: RE GINNA UNIT 1 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:

+++++++++++++++++ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS +4+4<++<+<<<<<<<<+

MONTHLY OPERATING REPORT FOR GRAY BOOK PREPARATION.

(DISTRIBUTION CODE A003>

FOR ACTION: BRANCH CHIEF Z IEMANN~+W/2 ENCL INTERNAL: EG F, ++W/ENCL NRC PDR++W/ENCL OR ACTION+4W/2 ENCL EXTERNAL: LPDR S ROCHESTER'Y~I +W/ENCL T IC~~W/ENCL NSIC++W/ENCL BNL<NATLAB)44M/ENCL ACRS CAT B++W/0 ENCL DISTRIBUTION: LTR 10 ENCL 10 CONTROL NBR: 780480239 SIZE: 1P+3P+iP END

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(;/g'/~;,"" gFI gp~t I30gt(<j'3.$ tII'.II+j';;;:,',I ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649 TELEPHONE g), yg APEA cooE Tie 546.2700

+ Ginna Station PEcovEO February 9, 1978

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Director, Office of Management Information and Program Control U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555 Subject Monthly Report for January, 1978 Operating Status Information R. E. Ginna Nuclear. Power Plant Unit No. 1 Docket No. 50-244 Gentlemen:

Pursuant to our proposed Technical Specification 6.9.1 attached herewith is the monthly operating status report for Ginna Station for the month of January, 1978.

ll Very truly yours, Superintendent LSL:fah Attachments 780480239

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OPERATING DATA REPORT DOCKET NO. 50 244 DATE Fe rua 1 78 COMPI,ETED BY E. McNamara, Operations Aide

'ndrew TELEPHONE. 1-716-546-2700

~ OPERATING STATUS Ext. 291-205 at Ginna

1. Unit Name: GINNA STATIO Notes Line ll:

2. Reporting Period: The number of hours in

3. Licensed. Thermal Power (MWt):

490 Reporting Period, Cumula-

4. Nameplate Rating (Gross MWc): tive, are from date of

5. Design Electrical Rating (Net MWe)t Initial, on-line of

6. Maximum Dependable Capacity (Gross hfWe): 490 generator, not date of

7. Maximum Dependable Capacity (Net MWe):

470 commercial operation.

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

9.'ower Level to Which Restricted, If Any (Net i~fWe):

10. Reasons For Restrictions, If Any:

This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 744 744 71 736

12. Number of Hours Reactor Was Critical 587 587 54,625.62

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours 0 0 8.5

• 872,256 872,256 .69,309,298

16. Gross Thermal Energy Generated (MWH)

18. Net Electrical Energy Generated (MWH) 239,624 239 624 22 427 484 79% 79% 74%

19. Unit Service Factor

20. Unit Availability Factor 79%

Unit Capacity Factor (Using MDC Net) 72% 72% 70%

21.

72% 72% 70%

l%%d 1% 12%

23. Unit Forced Outage Rate

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

Refueling "- March 17, 1978 - 6 weeks

25. If Shut Down At End Of Report.Period, Estimated Date of Startup: February 3y 1978

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

• Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION 49 88 (RKV. I/78)

• Cumulative Data Commencing January 1, 1975

l ,q,4 A RAGE DAILY UNIT POWER UNIT DOCKET NO..

UNIT ¹I Gtnna Statio Februar . 3 1978 COMPLETED BY Andrew E. McNamara, Operations Aide TELEPHONE 1-716-546-2700, Ext. 291-205, at Ginna MONTH January 1978 DAY AVERAGE DAILY POWER LEVEL DAY. AVERAGE DAILY POWER LEVEL (M We-Net) (MWe-Net) 415 1 17 415 415 2 18 415 416 19 416 415 20

.415 415 21.

417 416 22 416 416 23 416 24 416 416 357 25 414

• 10 ll 376 367

'7

• 26 12 2B 411

• 13 2$

14 349 30 315

• 31 16

• Unit Shutdown INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.

Compute to the nearest whole megawatt.

40 47 tRKVo 1/74)

DOCKET NO. 50-244 UNIT NAhll <l Ginna Station UNIT SHUTDOWN AND POWER REDUCTIONS C:OhtPLETED ltY Andrew E. McNamara, Ope ations Aide REPORT hlONTll

• TELEPllO l: 1-716-546-2700 Ext. 291-205 At Ginna Ol ~0 c D~

0 ss c v l.icensee Ew. C Cause L Corrective 0 O e 0 Ho. Date 0 e Event N o Q c Action to P. 0 o O

lxl << IA c Report Il o ~o Prevent Recurrence 0

lJ 780125 157 78-03 CB HTEXCH "B" Steam Generator, Tuba Leak (Refer to L.E.R. 78-03 for Corrective Actions)

F: Forced Reason: hlechod: FxhibicAi - Inscruccions St Scheduled A-Equipmcnt Failure (Explain) 1-hlanual for Preparation of. Data 8-htaintenancc or Test 2-hlanual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Rcport (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) ol6l)

E-Operator Training & License Examination F-Administrative G-Operational Error (Explain) 49 dg (Ra v, t/rd) ll-Other (Explain) Exhibit~- Same Source

1 I

4 HARRATIYE

SUMMARY

OF OPERATING EXPERIENCE DOCKET NO. 0-2 UNIT DATE February 3, 1978 COMPLETED BY Andrew E. McNamara, Operations Aide TELEPHONE 1 716 546 2700'xt ~ 291 205 at Ginna NTH JAWJARY, 1978 The Reactor Power Level averaged 100% in the Report Month. The exceptions were:

Two unit power level reductions to ~ 48% to repair condenser tube leaks, on 1/11 and 1/14, respectively.

A unit shutdown on 1/25 to effect repairs on the "B" steam generator, tube leak.

The unit remained shutdown at the end of the Report Period.

iQ ~ 123 u/TS)

7 NARRATIVE

SUMMARY

OF SAFETY-RELATED MAINTENANCE I.

JANUARY 1978 Ma)or safety-related. maintenance "for the month of January included plugging of a tube leak in the 1B Steam Generator." An additi'onal seven tubes were plugged due to defect indications. During the steam generator outage, the "B" loop sample valve was repaired due to a gasket leak and. the steam general'r"snubber SG>> A-7 was inspected and.

rebuilt with new seals as preventive mannite'nance. The terminal blocks for the pressurizer pressure and level control transmitters located in the containment were replaced, with Westinghouse terminal blocks. Con-trol rod power cables were checked for proper polarity and. terminal changes were made as necessary. Additional non-shutdown work included repair of a weld leak in the 1B charging pump discharge relief piping and rebuilding of a worn 1A charging pump varidrive unit.

RECEIVEO ppCUHEH'O<

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