ML20086G486

Monthly Operating Rept for Nov 1983

ML20086G486
Person / Time
Site:	Millstone
Issue date:	11/30/1983
From:	Gibson J, Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC
References
MP-5606, NUDOCS 8401120196
Download: ML20086G486 (6)

Text

_ _ _ _ _ _ . . . . .

b OPERATING DATA REPORT i DOCKET NO. 50-336 1 DATE 12/14/83 i COMPLETED BY J. Gibson E TELEPHONE (203)447-1791 EXT. 4431

OPERATING STATUS

1. Unit Name

Millstone 2 .

Notes Items 21 and 22 cumulative are weighted

2. Reporting Period: November 1983 g 3. Licensed Thermal Power (MWt): 2700 Ave. unit operated at i 4. Nameplate Rating (Gross MWe): 909 2560 MW Thermal prior

5. Design Electrical Rating (Net MWe): 870 to its uprating to the E 6. Maximum Dependable Capacity (Gross MWe): 895 current 2700 MW Thermal i 7 Maximum Dependable Capacity (Net MWe): 864 Power _ Level.

[

=

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7)

Since Last Report, Give Reasons:

E N/A

=

9. Power Level To Which Restricted, If Any (Net MWe): N/A r- 10. Reasons For Restrictions, If Any: N/A r

L E

=

[ This Month Yr.-to-Date Cumulative h

11. Hours In Reporting Period 720 8016 69528

12. Number Of Hours Reactor Was Critical 0 3130.5 48365.3 E 13. Reactor Reserve Shutdown Hours 0 0 2205.5 7 14. Hours Generator On-Line 0 2994.9 46182.2 468.2

=

15. Unit Reserve Shutdown Hours 0 0

16. Gross Thermal Energy Generated (MWH) 0 7877464 1h311669 _

F 17. Gross Elec. Energy Generated (MWH) 0 2575530 37806378 U 18. Net Electrical Energy Generated (MWH) (-2507) 2457202.4 36219015 __

19. Unit Service Factor 0 37.4 66.4

20. Unit Availability Factor 0 37.4 67.1 l 21. Unit Capacity Factor (Using MDC Net) 0 35.5 62.0

22. Unit Capacity Factor (Using DER Net) 0 35.2 61.1

23. Unit Forced Outage Rate 0 13.7 19.1 l 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Continuation of Refuel / Maintenance Outage 5 25. If Shut Down At End Of Report Period, Estimated Date of Startup:

y 26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved v

[ INITIAL CRITICALITY N/A N/A s INITIAL ELECTRICITY N/A N/A L COMMERCIAL OPERATION N/A N/A 3

E i

8401120196 831130 PDR ADDCK 05000336 R PDR 9\

c\

,~_

s-

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-336 UNIT Millstone 2 DATE 12/14/83 COMPLETED BY J. Gibson TELEPHONE (203) 447-1791 EXT. 4431 MONTH November 1983

-DAY AVERAGE DAILY POWER LEVEL GAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 0

.2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0

12 0 28 0 13 0 29 0 l 14 0 30 0 15 0 31 -----

16 0 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Corapute to the nearest whole megawatt.

+ - y - . - - . . ,---,,.w-- - y-

w DOCKET NO. 50-336 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 2 -

DATE 12/14/83 '

COMPLETED BY J. Gibson REPORT MONTH November 1983 TELEPHONE (203) 447-1791 l 2 No. Date Type Duration Reason Method of Licensee Systeg Compogent Cause & Corrective (Hours) Shutting 3 Event Code Code Action to Down Reactor Report # Prevent Recurrence 5 830528 S 720 C 1 N/A N/A N/A Continuation of Refuel and Maintenance Outage from previous month.

1 2 3 4 F: Forced Reason: Method: 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 Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Other (Explain) (NUREG-0161)

E-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explain) Exihibit 1 - Same Source H-Other (Explain)

o

~

Docket ~No. 50-336 Date 12/14/83 t' F ,

Unit Name Millstone 2

. Completed By J. Gibson

. Telephone'-(203) 447-1791 j Ext. 4431 CORRECTIVE MAINTENANCE SUMARY FOR SAFETY RELATED EQUIPMENT.

1 REPORT MONTH November 1983-DATE SYSTEM COMPONENT MAINTENANCE ACTION i 11/2/83 Main. Steam 2-MS-381A and 2-MS-381B Replaced with new valves 11/14/83 Main Steam #1'S/G and #2 S/G Installed some sleeves and'some

I' ' plugs along with tube plug. repair.

11/4/83

~

Main Steam 2-MS-218 and 2-MS-219 Replaced with.new valves.

11/6/83 Main Steam S/G Blowdown Piping and Modified' piping. '

. Hangers i 11/8/83 Safety Injection 2-SI-306 Replaced manual operator and bearings.

l j 11/18/83 Safety Injection 2-SI-469 Overhaul valve and re-install.

11/1/83 Reactor Coolant Thermal Shield > Removed from Core Barrel.

4 and Vessel i

i

)

i i

.j,..

Docket No. 50-336 Date: 12/14/83 Completed By: J. Gibson Telephone: (203)447-1791:

Ext. 4431 REFUELING INFORMATION REQUEST

1. .Name of facility: Millstone 2'

2. Sche' duled'.date for next refueling shutdown:

. Currently in Refuel / Maintenance Outage which commenced May 28, 1983.

.h 3i Schedule date for. restart following refueling: Estimated date for-

' restart is reactor' critical on Jan 7,1984; Turbine On-Line Jan. 12, 1984.

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

Cycle 64 operations will require Technical Specification changes.

' Supporting information has already been submitted.

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

Reassessments.of the small &-large break LOCA analyses were submitted n on Nov.,2, 1983. This reassessment of the LOCA analyses takes into

' account-the thermal shield removal and Cycle 6 core redesign characteristics.

A supplement to the Reload Safety Evaluation (RSE) Report was sent on Nov. 17,~ 1983 to address the Cycle 6 core redesign. A draft transmittal was supplied to the NRC on November 23, 1983 addressing the thermal shield removal & Core Support Barrel repair. A final report will be transmitted on or about December 16, 1983.

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

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

Steam Generator sleeves have been installed as well as some Steam Generator Tube plugging has been performed. The Thermal Shield has been

. removed from the Core Support Barrel.

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

L'

? ..

, '(a) I'n Core: 0 (b) 505

.h 8. The present licensed spent fuel pool storage capacity and the si e

[<

V '

ofrany increase in licensed storage capacity that has been requested or.is planned, in number of fuel assemblies:

667

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

l .1985, Spent Fuel Pool, Full core off load capacity is reached.

l' '1987, Core Full, Spent Fuel Pool contains 648 bundles.

L l

t i

{ ,n, , . *

~

),

5 i '\

General Offices

• Selden Street. Berkn. Connecticut F N NORTHEAST UTILITIES w amcron oo ma w P O. BOX 270 I

N ,. 9 neria wwvuus nicmc w=

.o. we ..na wa wa'"

HARTFOnD, CONNECTICUT 06141-0270 m_ oa . .c. ., -. w (203) 666-6511

, ho .a s.c c eavaao,c- .=

r E t 4 ,

i

' ~

December 15, 1983 _

r MP-5606 L

• e g

, n t

b Director Office of Management Information and Program Control

_ U. S. Nuclear Regulatory Commission , s

{ Washington, D. C. 20555

Reference:

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

r

Dear Sir:

I-This letter is forwarded to provide the report of operating and shutdown

' experience relating to Millstone Unit 2 Monthly Operating Report 83-11

-s E ' in accordai.ce with Appendix A Technical Specifications, Section i <

6.9.1.3. One additional copy of the report is enclosed. ,

1 '

,'  ! I

Very truly yours,

• ~

% ' s. NORTHEAST NUCL AR ENERGY COMPANY J s ,

r, 8 I ,

/ s\., ,

~

\- FOR: E. J. Mroczka

.'. i S t *j Station Superintendent

-I /

Millstone Nuclear Power Station BY: .Z' b R. J .' erbert g

Station Services Superintendent ,

Millstone Nuclear Power Station

- EJM/,)G: ejz -

E

't cc: Director, Office of Inspection and Enforcement, Region I i Director, Office of Inspection and Enforcement, Washingten, D. C. (10)

E, U. S. Nuclear kegulatory Commission, c/o Document Management Branch,  ;

u Washington, D.C. 205555 - /

5 k e:

8 _ __ _ _ __ _ _ _ _

3'