ML20043D599

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Monthly Operating Rept for May 1990 for Millstone Unit 2. W/900605 Ltr
ML20043D599
Person / Time
Site: Millstone Dominion icon.png
Issue date: 05/31/1990
From: Neron G, Scace S
NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-90-542, NUDOCS 9006080301
Download: ML20043D599 (5)


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% 5, if90 Mp-90-542 Re.: 10CTR50.71(a)

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

Reference:

Facility Operating License No. DPR 65

  • Docket !!o, 50 336 h

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, 1990, in accordance with Appendix A Technical Specifications, Section 6.9.1.6. One additional copy of the report it enclosed.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

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St. & n E Scack Station Director Millstone Nuclear Power Station SES/GN cc: 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, i

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t OPERATING DATA REPORT DOCKEi NO. 50 336 DATE 06/04/90 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: May 1990 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): 370 2700 MWTH power level.
6. Maximum Dependable Capacity (Gross HWe): 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, 7 f any (Net NWe): N/A
10. Reasons For Restrictions, If Any: N/A This Month Yr. To Date Cumulative
11. Hours In Reporting Period .

74/2 0 3623.0 126503.0

12. Number Of Hours Reactor Was Critical 168.8 3047.8 93408.9
13. Reactor Reserve Shutdown Hours ~

0.0 0.0 2205.5

14. Hours Generator On Line 168.8 3034.1 88985.5
15. Unit Reserve Shutdown Hours 0.0 0.0_ 468.2 16.-Cross Thermal Energy Generated (KWH) 455773.0 .315.6902.0, 246292740.ti
17. Gross Electrical Energy Generated (MWH) 146352,2 2646961.5 74566131.5
18. Net Electrical Energy Generated (NWH) 136916.0 2548929.5 71545563.5
19. Unit Service Factor 22.7 83.7 70.3
20. Unit Availability Factor 22.7 83.7 70.7 21.. Unit Capacity Factor (Using MDC Net) 21.3 81.5 66.5
23. Unit Capacity Factor (Using DER Net) 21.2 80.9 65.2
23. Unit Forced Outage Rate 26.5 2.4 13.5
24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):

End of Cvele 10 Refuel Outage. Scotember 15. 1990. 40 days.

25. If Unit Shutdown At End Of Report Period. Estimated Date of Startup: June 12. 1990
26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A C0KMERCIAL OPERATION N/A N/A

r AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 336 UNIT: Millstone Unit 2 DATE: 06/04/90 COMPLETED BY: G. Neron TELEPHONE: (2031447 1791 EXT: 4417 ,

MONTH: MAY 1990 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL  !

(MWe Net) (MWe Net) 1 840 17 0 ,

2 838 18 0 s

3 836 19 0 4 836 20 0 5 836 21 0 5

6 835 22 0 I

7 833 23 0 8 2 24 0 9 0 45 0 ,,,,

10 0 26 _

0 11 0__ 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 16 0 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

s DOCKET NO. 50-336 * * '

UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME- Millstone 2 -

DATE 06/04/90 .

COMPLETED BY G. Neron TELEPHONE (203) 447-1791 REPORT MONTH May 1990 EXT. 4417 No. Date Type l Duration Reason2 Method of License Systga C nt Cause & Corrective (Hours) Shutting Event Code Code Action to Down Reactor3 Report # Prevent Recurrence 02 900508 F 61.0 A 2 90-006 SJ LGV Manual Reactor Trip from 100% power was initiated due to S/G el low level.

The valve stem of feed-water regulating valve

  1. 2-N-51A had separated from the plug, causing a reduction in feedwater flow. See LER.

03 900510 S 514.2 H 6 N/A N/A N/A During the repair main-tenance initiated by failure of feed regulating valve #2-W-51A, Plant Management believed it prudent to place the Unit in Cold Shutdown due to primary-to-secondary leak rate analysis (below Technical Specification limits); Based upon previous Steam Generator-tube performance, a Steam Generator inspection and repair (as required) outage was scheduled; Inspection and repair activities were proceeding at the end of the May,1990 Reporting Period.

2 3Method I:

F Forced Reason: ' 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-Fegulatory Restriction 4-Con *inued from (NUREG-0161)

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

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

l REFUELING INFORMATION REOUEST

1. Name of facility: Millstone 2 l
2. Scheduled date for next refueling shutdown: Seotember 15. 1990
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?

YES __

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

@lly 1. 1990

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

new or different fuel design or supplier, unreviewed design or perfonnance analysis methods, significant changes in fuel design, new operating procedures None

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pools In Core: (a) 212 In Spent Fuel Pools (b) 112
8. The present licensed 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:

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. Scent Fue: Pool Full, core off load caoacity is reached (with

-out consolidat:.on).

J198. Core Full. Soent Fuel Pool Full 2009. SDent Fuel Pool Full, core off load caDacity is reached-nontinaent uDon full scale storace of consolidated fuel in the _.

Scent Fuel Pool.