ML18142B358

Forwards Monthly Operating Status Report for Month of February 1978

ML18142B358
Person / Time
Site:	Ginna
Issue date:	03/07/1978
From:	Lang L Rochester Gas & Electric Corp
To:	Office of Nuclear Reactor Regulation
References
Download: ML18142B358 (18)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS>

DISTRIBUTION FOR INCOMING MATERIAL 50-244 REC:

NRC ORG'.

LANG L S ROCHESTER GAS 8c ELEC DOCDATE: 03/07/78 DATE RCVD: 03/13/78 DOCTYPE:

LETTER NOTARIZED:

NO COPIES RECEIVED

SUBJECT:

LTR i ENCL i MONTHLY OPERATING STATUS REPT FOR THE MONTH OF FEBRUARY'1978.

PLANT NAME: RE GINNA UNIT i REVIEWER INITIAL'RS DISTRIBUTOR INITIAL:gg

+++++++++++++++++ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS MONTHLY OPERATING REPORT FOR GRAY BOOK PREPARATION.

<DISTRIBUTION CODE A003)

FOR ACTION:

BR CHIEF-ZIEMA

++4J/2 ENCL INTERNAL:

EXTERNAL:

REG FILE++W/ENC

++W/2 ENCL LPDR S ROCHESTER'Y++W/ENCL TIC++W/ENCL NSIC~4W/ENCL BNL(NATLAB>+4W/ENCL ACRS CAT B4~4W/0 ENCL NRC PDR<4W/ENCL DISTRIBUTION:

LTR i0 ENCL i0 SI ZE: iP+5P+2P END CONTROL NBR:

780730342

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TOKK ROCHESTER GAS AND ELECTRIC CORPORATION

~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 TELEPHONE AREA CODE Tld 546.2700 Ginna Station March 7, 197 Director, Okiice ot Management Information and P Control U. S.

NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555

Subject:

Monthly Report ior February, 1978 Operating Status Information R. E. Ginna Nuclear Power Plant Unit No.

1 Docket No. 50-244

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Cp 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 February, 1978.

Very truly yours, LSL:nh Attachments Lee S.

Lang Superintendent

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OPERATING STATUS OPERATING DATA REPORT,

. DOCKET NO.

DATE March 7

1978 COMPLETED BY Andrew E. McNamara, Operations Aide TELEPHONE 1-716-546-2700 Ext.

, at Ginna

1. Unit Name:

GINNA STATION

2. Reporting Period:

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross MWe):

490

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

7. Maximum Dependable Capacity (Net MWe):

490 470 The Reactor Power Level averaged 100% in the Reporting Period, with two exceptions, detailed under Unit Shutdowns, Page 3.

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

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

10. Reasons For Restrictions, If Any:

This Month Yr:to-Date Cumulative 242,989

11. Hours In Reporting Period

12. Number of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line

15. Unit Rcservc Shutdown Hours 0

17. Gross Electrical Energy Generated (MWH)

18. Nct Electrical Energy Gcncrated (MWH)

19. Unit Service Factor

20. Unit AvailabilityFactor 89%

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21. Unit Capacity Factor (Using MDC Net)

22. Unit Capacity Factor (Using DhR Net) 77%

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23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months (Type, Date and Duration 1,416 1 185 1 760 6

510 227 482,613 84%

73%

73%

of Each):

72 408 53 703.38 8 ~ 5 vc 22 698 087 21,464,907 74%

66%

66%

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

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

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INITIALCRITICALITY INITIALELECTRICITY COMMERCIALOPERATION Forecast Achieved

• Cumulative Data Commencing January 1,

1975 49 d8 (Reve I/78)

ik AVERAGE DAILYUNIT POWER UNIT 0

February, 1978 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net)

DOCKET NO.

50 244 UNIT ¹I @irma Stat'o March 7

1978 Andrew E. McNamara, Operations Aide PHONF 1-716-546-2700 Ext. 291-205, at Ginna DAY.AVERAGE DAILYPOWER LEVEL (MWe-Net) 10 12 13 14 15 16 240 413 413 416 418 417 418 417 416 416 416 415 415 17 18 20 21 22 23 24 25 26 27 28 2S 30 31 415 415 417 351 315 414 414 4

4 415 415 414 414 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.

49 ~ 87 (RKVo I/78)

1

DO(:KET NO.

Pl Ginna Station UNIT SHUTDOWN AND POWER REDUCTIONS

(:OhIP LETED 33Y Andrew c amara, Clpe aeons Aide TELEPHONE 1-716-546-2700 Ext. 291-205, at Ginna No.

Date c0 4

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Cl Licensee Event Report 0

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Cause L Corrective Action to Prevent Recurrence 780125 55 A

78-03 CB HTEXCH "B" Steam Generator, Tube Leak.

(Refer to L.E.R. 78-03 for Corrective Actions).

NOTE: Duration (Hours) reflect February Report Month, only.

780220 F

19 A

CA Vessel Pressurizer Spray Valve 431-B, Packing Leak.

F-Forced S:

Scheduled 49-so (REV 1/78)

Reason:

A-Equipmcnt Failure (Explain)

I3-htaintcnancc or Test C-Refueling D-Regulatory Restriction

'-Operator Training &'. License Examination F-Administrative G-Operational Error (Explain)

H-Other (Explain) 3 hlcthod:

1-hlanual 2-hlanual Scram.

3-Automatic Scram.

4-Other (Explain) 4 Exhibit

- Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG-0161) 5 Exhibit/- Same Source

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE DOCKET NO.

0-2 Ginna Station, Unit //1 DATE March 7, 1978 COMPLETED BY Andrew E. McNamara, Operation Aide MONTH

February, 1978 TELEPHONE 1-716-546-2700 Ext. 291-205, At Ginna The unit remained shutdownuuntil February 3rd, to complete repairs on the "B" Steam Generator, Tube Leak.

The Reactor Power Level averaged 100% for the remainder of the Report Month, with the following two exceptions:

On 2/15 the Reactor Power Level was reduced to 96% to perform the Auxiliary Feedwater Pump Flow Check.

The Reactor Power Level was restored to 100% after the test.

On 2/20 the unit was shutdown due to a packing leak, Pressurizer spray valve.

Unit startup commenced on 2/21, and the Reactor Power Level was restored to 100%,

same date.

40 1R3 u/78)

NARRATIVE

SUMMARY

OF SAFETY-RELATED MAINTENANCE FEBRUARY, 1978 Major Safety Related maintenance during the month of February was limited to sealing a gasket leak on the "A" Steam Generator North Handhole using Furmanite during the "B" Steam Generator shutdown and repacking pressurizer valves.

PCV-431B, pressurizer spray valve, and 516, power operated relief block valve were repacked on 2/20/78.

Both valves had exhibited packing leakage.

The pressurizer manway gasket was also replaced due to leakage during the hydro after the steam generator shutdown.

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NR EFUELING INFORMATION RE UEST Page 1 of 2 1.

Name of Facility:

Rochester Gas 6 Electric Corp.

R, E. Ginna Nuclear Station Docket No. 50-244 2.

Scheduled date for next refueling shutdown:

March 24, 1978 3.

Scheduled date for restart following refueling:

April 29, 1978 Will refueling or resumption of operation thereafter require a technical specification change or other license amendment:

Ginna Station will be refueled in March 1978.

The reload will consist of 32 new fuel assemblies supplied by Exxon Nuclear Company and 89 previously exposed Westinghouse fuel assemblies.

Detailed discussions of the safety analysis performed by Exxon Nuclear for reload (cycle VIII) operation were presented to the NRC in report "Cycle VIIIReload Safety Analysis Report" XN-NF-77-53.

The change to technical specification 3.10.2.7 was required to meet the condition of Power Distribution Control (PDC 1) as described in "Exxon Nuclear Power Distribution Control for Pressurized Water Reactors",

XN-76-40 and addendum.

I The change to the bases of the technical specifications on page 3.10-8C was required for clarity and to reflect a different methology used by Exxon Nuclear in the nuclear design.

The revised basis is consistant with the Nuclear Regulatory Commission's standard technical specifications.

5.

Scheduled date(s) for submitting proposed licensing action and supporting information:

Submitted to NRC in January 1978 6.

Important licensing considerations associated with refueling, e.g.

new or fuel design or supplier, unreviewed design or performance analysis

methods, significant changes in fuel design, new operating procedures.

See response to Item 4 above.

No new operating procedures are required.

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage:

a - 121 fuel assemblies in the core.

b - 124 fuel assemblies, in the spent fuel storage at end of February 1978.

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Page 2 bf 2 8.

The present 1'icensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is

planned, in number of fuel assemblies:

The spent fuel storage capacity was increased from 210 to 595 'fuel

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assemblies positions, the modification was terminated in March 1977.

Present licensed capacity is 595 fuel assemblies.

9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

At preliminary projected discharge rate per refueling, will have enough capacity until 1984, and still maintain full core discharge capability.

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