ML20081G384

Monthly Operating Rept for May 1991 for Millstone Unit 2.W/

ML20081G384
Person / Time
Site:	Millstone
Issue date:	05/31/1991
From:	Neron G, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-91-475, NUDOCS 9106130009
Download: ML20081G384 (5)

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L L J 4.o % :.. .. ,, .3 w ., (203) 665 5000 June 10, 1991 MP-91-475 Re: 10CFR50.71(a)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

Reference:

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

Dear Sir:

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

Very truly yours, NORTilEAST NUCLFla ENERGY COMPANY

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Step en E. Scace uC Station Director Millstone Nuclear Power Station SES/GN c: T. T. Martin, Region I Administrator G. S. Vissing, NRC Project Manager Millstone Unit No. 2 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1,2&3 910613 Odd 9 910531 FDR ADOCK 050003.;6 R PDR ,///)'

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0 OPERATING DATA REPORT DOCKET NO. 50-336 DATE _D1/06/91 COMPLETED BY G Neron TELEPil0NE (203) 447-1791 EXT, 4417 OPERATING STATUS Notes: Items 21 and 22

1. Unit Name: Millstone Unit ? cumulative are weighted

2. Reporting Period: May 1941 averages. Unit operated

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

4. Nameplate Rating (Cross MWe): 409 uprating to the current

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

6, Maximum Depencable Capacity (Cross MWe); __843.88

7. Maximum Dependable Capacity (Net MWe): 86?.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 I

This Month Yr.-To-Date cumulative 1

11. Hours in Reporting Period 744.0 3623.0 135263.0 l 12, Number Of Ilours Reactor Was Critical 335.6 ___ 1800.1 99712.7 '

13. Reactor Reserve Shutdown llours 0.0 0.D_ 2205.5 I

14. Ilours Generator On-Line 320.2 2729.5 95073.3  ;

15. Unit Reserve Shutdown llours 0.0 0.0 468.2 l

16. Gross Thermal Energy Generated (MWH) 803840.0 7192151.0 262248215.4

17. Gross Electrical Energy Generated (MWil) 266485.5 2391006.Q_ 79830705.5

18. Net Electrical Energy Generated (MWil) 251355.5 2295868.0 76596917.5

19. Unit Service Factor 43.0 75.3 70.3

20. Unit Availability Factor 43.0 75.3 70.6

21. Unit Capacity Factor (Using MDC Net) 39.2 73.4 66.5

22. Unit Capacity Factor (Using DER Net) 3 P, . 8 72.8 65.3

23. Unit Forced Outage Rate 57.0 24.7 13.6

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

N/A

25. If Unit Shutdown At End Of Report Period, Estimated Date of Startup: June 28. 1991

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

Forecast Achieved INITIAL CRITICALITY N_/6. N/A INITIAL ELECTRICITY N/A N/A l COMMERCIAL OPERATION N/A N/A l

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e AVERAGE DAILY UNIT POWER LEVEL l

DOCKET NO.10-336 );

UNIT: _ Millstone Unit 2 DATE: 06/06/91 COMPLETED BY: G. Neron TELEPHONE: (203) 447-1791 EXT: 4417 MONTH: MAY 1991 DAY AVG. DAILY POVER LEVEL DAY AVG. DAILY POWER LEVEL (MWe-Net) (MVe-Net) 1 0 17 873 2 0 18 871 3 0 19 871 4 0 20 871 5 0 21 q]j, 6 0 22 870 7 0 23 869 8 0 24 869 9 0 25 562 10 0 26 0 11 0 27 0 12 97 28 0 13 443 29 0 14 866 30 0 I

15 872 31 0 16 871 INSTRUCTIONS l 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.

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l DOCKET NO. 50-336 l UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 2 DATE 06/06/91 -

COMPLETED BY G. Neron

TELEPHONE (203) 447-1791 REPORT MONTH MAY 1991 EXT. 4417 I

No. Date Type l Duration Reason 2 Method of License Systgm Component Cause & Corrective

(Hours) Shutting Event Code Code) Action to

Down Reactor 3 Report # Prevent Recurrence l

i 03 910422 F 272.6 A 4 N/A N/A N/A Continuation of Steam Generator / Extraction Steam line repair outage from the previous month. Main Generator was placed "on line" on 05/12/91. Unit achieved 100% power on 05/14/91.

04 910525 F 151.2 H 1 91-008 *

• A decision was made on 05/25/91 to manually shutdown the unit due to a steam generator tube leak. After entrance into Mode 3 (sub-critical) during the manual shutdown, the reactor tripped on steam generator low pres-sure. Testing and repair efforts are now in progress in both steam generators. Unit 2 is currently scheduled to start-up on June 28, 1991. See LER.

• - System /Conponent Codes undetermined at this time (see LER) 2 1

F: Forced Reason: 3Method

' Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for License C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continued from (NUREG-0161)

E-Operator Training & License Examination Previous month F-Administrative 5-Power Reduction 5 Exhibit 1 -Same Source G-Operational Error (Explain) (Duration -0)

H- Other (Explain) 6-Other (Explain)

b RDFUELING _IllEQBJMTION BMUREr

1. Name of facility: 1111 stone ?

2. Scheduled date for next refueling shutdown: Marsh, 1992

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

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

1[one at this tine

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

None

6. Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unroviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

Mi1Lptone 2 wi11 bo replaging_t3e Stemn_ptqncratgr aub-asnsrphlies dur: na the ung_ojnina o Fnd of Cycle 11 refueling outane. It as ant:,cipated this will be accomplished under LO_CIll 52. 59.

7. The number of fuel assemblics (a) in the core and (b) in the spent fuel storage pool:

In Core: (a) 217 In Spent Fuel Pool: (b) 712 NOTE: These numbers represent the totatl_D1gJ_ assemblies and cnnsol-idated fuel storace boxes in these two (2) Item Control Areare

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

Currently 1277

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

1994 SneD_t Fuel Pool _ Full. core off load capacity is reached (with

-out consol iditt;1_o_rt) .

1998. Core Full m Sp_ent Fuel Pool Full _

2009a Spent Fuel Pool Full. core off load capaci_ty m is reache_d-gontinnent upon f ull_ scale storage of consol idated_Juel Jn the Spenc Fuel Pool.

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