ML18142B354

Forwards Monthly Operating Status Report for Month of July, 1978

ML18142B354
Person / Time
Site:	Ginna
Issue date:	08/03/1978
From:	Snow B Rochester Gas & Electric Corp
To:	Office of Nuclear Reactor Regulation
References
Download: ML18142B354 (14)

Text

REGULATORY INFORMATION DISTRlBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOMING NATERIAL 50-244 REC: ORG: SNOW B DOCDATE: 08/03/78 NRC ROCHESTER GAS 8( ELEC DATE RCVD: 08/14/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 FORWARDING SUBJECT FACILITY"8 NONTHLY OPERATING REPT FOR THE NONTIR OF JULY, 1978.

PLANT NANE: RE GINNA UNIT 1 REVIEWER INITIAL. X JM DISTRIBUTOR INITIAL:

DISTRIBUTION OF TIIIS NATERIAL IS AS FOLLOWS ANNUAL, SEMI-ANNUAL S NONTISI V OPERATING RPTS (Ot STAGE)

CODE A008) 'DISTRIBUTION FOR ACTION: BR CHlEF ORBQ2 BC++W/6 ENCL INTERNAL: I - /ENCL NRC PDR~~~W/ENCL I 5 E+%W/2 ENCL NIPC+~W/2 ENCL I-IANAULR~~~W/ENCL DIRECTOR DOR++W/ENCL AD FOR SYS 0 PROJ++W/ENCL E'NGI NEER ING BR~~W/ ENCL REACTOR SAFETY BR+4~W/ENCL PLANT SYSTENS BR~~W/ENCL EEB~+W/ENCL CORE PERFORNANCE BR>~W/ENCL EFFI VENT TREAT SYS++W/ENCL EXTERNAL: LPDR S ROCI JESTER i NY< 4~W/ENCL NATL LAB ORNLN~W/ENCL TERA4~W/ENCL NSIC4+W/ENCL ACRS CAT B>~W/15 ENCL DI TRIBUTION: LTR 41 -NCL 41 CONTROL NBR: 782190087 SIZE: 1P+5P

%%%%%%%%%%%%%0M%%%%%%%%%N+5k%%%%%%% THE END  %%4%%%48%440MNM%%%4%%%%%%%%%%%%%%%%%

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I IIIIIIIIIIIII ZK'ORL 55A1t ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649

'tcLrpHoHc Asc*cooL'ia 546-2700 Ginna Station August 3, 1978 r>

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~ED r,A7 I Q7 Director, Office of Management Information and Program Control U. S. NUCLEAR REGULA'LORY COMMISSION C7 f<1 Washington, D. C. 20555 cA

Subject:

Monthly Report for July, 1978 Operating Status Information R. E. Ginna Nuclear Power Plant Unit No. 1

, Docket No. 50-244

Dear Sir:

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

I Very truly yours, Bruce Snow Superintendent Attachments 78~ 190087 Y,i

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8 OPERATING DATA REPORT DOCKET NO. 50 244 DATE COMPLETED BY Andrew E. McNamara, Operations Aide TELEPHONE 1-716- -2

~ OPERATING STATUS 205, at Ginna

l. Unit Name: GINNA STATION U Notes: The reactor power level

2. Reporting Period: averaged 100% in the reporting

3. Licensed Thermal Power (MWt): 1520 period. Exceptions to the 4490 above are detailed on Page 4.

4. Nameplate Rating (Gross hfWe):

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross hfWe)t 490

7. hfaximum Dependable Capacity (Net hfWe): 4470

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

1

9. Power Level to Which Restricted, If Any (Net hfWe):

10. Reasons For Restrictions, If Any:

This Month Yr:to-Date Cumulative

12. Number of Hours Reactor Was Critical 7744 3 524. 2 756. 4

13. Reactor Reserve Shutdown Hours 744 3 437.25 55 955.63

14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours 1,$ 071864, 5,066 160+*, 73 503 202**

16. Gross Thermal Energy Generated (MWH)

17. Gross Electrical Energy Generated (MWH) 367 466

18. Net Electrical Energy Generated (hfWH) 349 994

19. Unit Service Factor

20. Unit Availability Factor 100%

21. Unit Capacity Factor (Using MDC Net) 100% 62'a n~j

23. Unit Forced Outage Rate

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

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

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COhfMERCIAL OPERATION 40 88 (REVe 1/78)

• Cumulative total commencing January 1, 1975

• • Corrected Value to rectify error in June, 1978 calculations.

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AVERAGE DAILY UNIT POWER UNIT DOCKET NO. 50 244 UNIT Nl @iona Statio Au ust 7 .1978 COMPLETED BY Andrew E. McNamara, Operations Aide TELEPHONE 205 at Ginna MONTH DAY AVERAGE DAILY POWER LEVEL DAY. AVERAGE DAlLY POWER LEVEL (MWe-Net) (MWe-Net) 17 480 18 484 473 20 485 21 472 485 22 471 485 23 469 24 25 10 483 26 469 27 12 28 13 477 2$ 469 476 410 30 377 31 16 475 INSTRUCTIONS On this formac, list the average daily unit power level in MWe-Net for each day in the reporting month.

Compute to the nearest whole megawatt.

49.87 (RKV I/78)

DOCKET NO. 50 244 UNITNAhfE Nl Ginna Station UNIT SHUTDOWN AND POWER REDUCTIONS. <)AT> u usu lcr8 COh)PLFTED BY Anclrew E. Kc amara, perations 7d.de 205, at Ginna s

c 0I s-0 C 0 C E 0 Licensee E<- 0 Ill Cause gI Corrective 0 0 C 0 No. Date 0 Event 0 Action to 0 0 0 Vl 0 0 E 0

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-e'en C Report fI I/l 0 O

Prevent R'ecurrence 0

CL No outages or power reductions to report.

3 F: Forced Reason: hfethod: Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) I-lIfanual for Preparation of Data B-hfaintcnancc or Test 2-hfanual Scram. Entry Shccts for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Ocher (Explain) 0161)

E-Operator Training & Liccnsc Examination F-Administrative G-Operational Error (Explain) 88.89 CREVs C/78) H-Other (Explain) Exhibit 1 - Same Source

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SUMMARY

OF OPERATING EXPERIENCE DOCKET NO. 0-2 UNIT Ginna Station Unit f/1 DATE Au ust 7 1 78 COMPLETED BY Andrew E. McNamara, Operations Aide TELEPHONE 1-716-546-2 0 exts 205 at Ginna MONTH Jul 1978 The reactor power level averaged 100% intthe report month, with the following exceptions: on 7/15, the reactor power level was reduced to 46% due to a Turbine Run-back.

On 7/30, the reactor power level was reduced to ~45% to perform the Turbine Main Steam Stop Valves Test.

The above power reductions were of short duration; as a result, they are omitted from Page 3, UNIT SHUTDOWNS AND POWER REDUCTIONS.

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MAINTENANCE REPORT FOR JULY 1978 During July, normal inspection and minor maintenance was performed.

Major safety related maintenance included the following:

1. Replacement of snubbers in positions. MS146 top and bottom due to seal leakage on one of these units.

2. Replacement of a failed oscillater ontthe "B" inverter.

3. Replacement of the stuffing box assemblyoon the "C" charging pump.

4. Replacement of the hinge assembly on the personnel hatch outer due to a bent hinge pin.

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