ML20077M252

Monthly Operating Rept for Jul 1991 for Millstone Unit 2

ML20077M252
Person / Time
Site:	Millstone
Issue date:	07/31/1991
From:	Neron G, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-91-646, NUDOCS 9108130245
Download: ML20077M252 (5)

Text

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A a.<m aa m . m . f 203) 665-5000 August 7, 1991 MP-91-646 Re: 10CFR50.71(a)

U.S. Nucicar Regulatory Comtnission Document Control Desk Washington, D. C. 20555

Reference:

Facility Operating License No. DPR-65 Docket No. 50-336 1

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Dear Sir:

This letter is forwarded to provide the report of operating and shutdown experience relating to Millstone Unit 2 for the month of July,1991, in accordance with Appendix A Technical Specifications, Section 6.9.1.6. One additional copy of the report is enclosed.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

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/

/StephenE.Scace

./J/(/ . ww Station Director Millstone Nuclear Power Station SES/GN c: T. T. Martin, Region I Adml.nistrator G. S. Vissing, NRC Project Manager, Millstone Unit No. 2 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1, 2 & 3 9108130245 91073; PDR ay ADOCK 05000306 /- >'I R PDR

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OPERATING DATA REPORT DOCKET NO. J0-336 _

DATE 08/06/91 COMPLETED BY G. Neron TELEPHONE (203) 447-1791 EXT. 4417 OPERATING STATUS Notes: Items 21 and 22

1. Unit Name: Millstone Unit 2 cumulative are weighted

2. Reporting Period: July 1991 averages. Unit operated

3. Licensed Thermal Power (MWt): 2700 ___ at 2560 MWTH prior to its

4. Nameplate Rating (Gross MWe): 909 uprating to the current

5. Design Electrical Rating (Net MWe): 870 2700 MWTH power level.

6. Maximum Dependable Capacity (Gross MWe): 893.88

7. Maximum Dependable Capacity (Net MWe): 862.88-

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last 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 744.0 5087.0 136727.0

12. Number Of Hours Reactor Was Critical 617.1 3417.2 100329.8

13. Reactor Reserve Shutdown Hours 0.0 0.0 2205.5

14. Hours Generator On-Line 560.1 3289.6 95633.4

15. Unit Reserve Shutdown Hours 0.0 0.0 468.2

16. Gross Thermal Energy Generated (MWH) 1352310.0 8544461.0 263600525.4

17. Gross Electrical Energy Generated (MWH) 444249.0 2835255.0 80274954 ,1

18. Net Electrical Energy Generated (MWH) 423931.0 2716398.0 77017447.5

19. Unit Service Factor 75.3 66.7 69.9

20. Unit Availability Factor 75.3 64.7 70.3

21. Unit Capacity Factor (Using MDC Net) 66.0 61.9 66.1

22. Unit Capacity Factor (Using DER Net) 65.5 61.4 64.9

23. Unit Forced Outage Rate 24.7 35.3 14.2

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

N/A

25. If Unit chutdown At End Of Report Period, Estimated Date of Startup: N/A

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

Forecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTPICITY N/A N/A COMMERCIAL OPERATION N/A N/A l

AVERAGE DAILY UNIT POVER LEVEL DOCKET NO. 50-336 UNIT: Millstone Unit 2 DATE: _Q3/06/91 COMPLETED BY: G. Neron TELEPHONE: (203) 447-1791 EXT: 4417 MLNTH: JULY 1991 D/ f AVG. DAILY POWER LEVEL DAY AVG. DAILY POVER LEVEL (MVe-Net) (MWe-Net) 1 0 17 864 2 0 18 864 3 0 19 853 4 0 20 47 5 0 21 247 6 0 22 836 7 167 23 863 8 394 24 865 ___

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611 25 867 10 458 26 867 11 422 27 821 12 819 28 830 13 854 29 860 14 864 30 870 15 865 31 870 16 865 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.

l DOCKrT. NO. 50-336 UNIT NAME UNIT SHUTDOWNS AND POWER REDUCTIONS Millstone L - '

DATE E 06/91 -

COMPLETLD BY G. Neron l TELEPHONE (203) 447-1791 j_ REPORT MONTH JULY 1991 EKT. 4417

$d

' No. Date Typel- Durcti~a Reason 2 Method of License Systgm Compgnent Cause & Corrective (Hours) Shutting Ev. t Code Code Action to l Down Reactor3 Report

• Prevent Recurrence 04 910525 F 147.1 H- 1 91-008 JC PS tinuation of Steam j v< rator inspection

a. repair outage from i

the previous month. The main was placed "on

! c; line" July 7, 1991. Unit proceeded s 75% power and problems with'the main turbine master trfy solenoid were discovered.

05 910710 S 9.4 A 6 N/A N/A N/A The main generator was taken "off line" on July 10, 1991, to re-

pla e the "A* Turbine master trip solenoid and the *2

Stop Valve fast actin 6 solenoid. The reactor v.as main-tained critical during this period. The main generator l' was placed "on line" July 11, 1991. Unit achieved 100%

power on July 12, 1991.

l 06 910720 S 27.4 A 6 N/A N/A N/A The main generator was j taken "aff line" on

! July 20, 1991, 'o .

l troubleshoot the '4" & *t' arbine master trip adenoids.

Both the "A" 6 "B" master irip solenoids were (*placed (the "B" solenoid did nRA require replacement). The main generator was placed "on line" July 21, 1991. Unit i

achieved 1001 power on July ??. 1991.

F: Forced 2 Reason: 3 Method

' Exhibit G - Instructiors l

S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for License i C-Re fueling 3-Automatic Scram Event Report (LER) File-l D-Regulatory Restriction .

4-Continued from (NUREG-0161) i E-Operator Training & License Examination Previous month F-Administrative 5-Power Reduction 5 Exhibit 1 -Same Source i

1 G-Operational Error (Explain) (Duration -0) l H- Other (Explain)' 6-Other (Explain) i l'

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REFUELING INFORMATLQN REQQESI

1. Name of facility: Millstone 2

3. Scheduled dace for next refueling shutdown: _Anrila 1992

3. Scheduled dete for restart following refueling: N/A

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

None at this time

5. 9ckedeled date(s) for submitting licensing action and supporting information:

None .

6. Important 1.icensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or performance analyais methods, significant changes in fuel design, new operating procedures:

Mil:. stone 2 will be replardng_the Steam Generator sub-assemblies 11 refuglina out?,ge. It is durnna antLcinatedthe uncomina this willEnd of Cycle [3ghed under 10CFR 50.59.

be accomn

7. The number of fuel assemblias (a) in the core and (b) in the spent fuel storage pools In Core: (a) 212 In Spent Fuel Pool (b) 212 HgIC11gge numbers represent the total fuel assemblles and consol-ndated fuel storace boxes in these two-(2) Item Control Areas

8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capa" i that has been requested or is planned, in number of fuoi assemblies:

Chyrently 1277

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

1994. S D e n t_ Ell e: Pool Full, core qif load capacity is reached (with

-out consoll_datnon).

1998. Core Full d pent Fuel PQol Full 2009. Soent Fuci Pool Full, core off load capacity is reached- I continuent upon fyll_ scale storage of conspildated fuel in the i SDent Fuel Pool. .

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