ML20092D700

Monthly Operating Rept for Jan 1992 for Millstone Unit 2

ML20092D700
Person / Time
Site:	Millstone
Issue date:	01/31/1992
From:	Neron G, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-92-162, NUDOCS 9202140193
Download: ML20092D700 (5)

Text

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-4 NORTHEAST UTILITIES o.nor.i On.c... s.io.n sim.i. e.riin. conn.ciicut s cow.mu w wemiacca*w T

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..n e w.is.m m o#.w P.O BOX 270 a.o.e wom*t. w*w HARTFORD. CONNECTICUT 06141-0270 oa,*is mi n*rta ='"'

(203) 665 5000 a,.

w,,u n,.a w-February 10, 1992 MP-92-162 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 January,1992, 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

/

/

l/H (a cf.,

j/ Stephen E.

cace Station Director Millstone Nuclear Power Station SES/CN 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

N I 9202140193 920210

/

l-PDR ADOCK 05000336

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PDR

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9 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

,,,1QM 36 UNIT

,,,liillitone Unit 2 DATE:

Q24Q6/92 COMPLETED BY

,,L _Neron TELEPil0NE (203) 44 7 + 17 9L,,

EXT 1

.4417 1

MONTil JANUARY _1992 DAY AVO. DAILY POWER LEVEL DAY AVO. DAILY POWER LEVEL (MWe Nat)

(MVo Het) l 1

870 17 872 2

871 18 872 3-872 19 871 4

872' 20 872 5-872 21 872 r

6 872 22 871

[

I 7

873 23 871 8

873 24 870-9 874 25

'754 t

10 873 26.

660

{

11 871 27 598 12 872 28 0

13 874 29 0

14 874 30 0

15 873 31 0

i 16 81)

INSTRUCTIONS On this format,-list the average daily unit power lovei in Mke Net for each day in the reporting month.. Compute to the nearest whole megawatt.

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OPERATING DATA REPORT

)

i DOCKET NO.

_50 336

-l DATE _02/06/92 COMPLETED BY

0. Neron TELEPHONE (203) 447 1791 l

EXT.

4417 l

i QPERATING STATQS Notes: Items 21 and 22 l

1.

U dt Name:

Millstone Unli_2__.

cumulative are volghted 2.

Reporting Period:

January 1992 averages. Unit operated L

3.

Licensed Thermal Power (MVt):

2700 at 2560 MWTil prior to its 4

Nameplate Ratin6 (Cross MWe):

909 uprating to the current 5.-

Design Electrient Rating (Not MWe):

870 2700 MWTil power level.

6.

Maximwn Dependable Capa:Jry (Cross MWe):

893.88

7.

Maximwn Dependable. Capac.cy (Not MWe)!

862.88 8.

If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since last Report.

Give Reasons N/A j

=9c Power Level To-Which Restricted, If any-(Net MWe):

N/A

10.<keasons for Restrictions, if Any:

N/A 3

i This Month Yr. To*Date cumulative a

11. Ilours In Reporting Period 744 Q 744.0 ;

141144 3

,13. Number Of Ilours Reactor Vas Critical.

_kiQ.2 650.Z_.

102703.8 13.~ Reactor Reserve Shutdown'lloura 0 D.

0.0 2205.5'

14. Ilours Generator on.Line 648.7 648.7 97817.5

15. Unit Reserve Shutdown llours-0.0-0.0 413.2

16. Cross: Thermal. Energy Generated (HV11) 1709024.0 1709024.0; 269231488.4

17. Cross' Electrical Energy.Cenerated- (MVil) 570577.5 570577.5 82147248.5

18. Het Electrical Energy Generated (MVii) 550006.5-550006.5 78795784.5-f 19.1 Unit-Service Factor-87.2-87.2 69.3 20, Unit Availability Factor 87.2-87.2 6g h-

.31. Unit capacity Factor (Uning MDC Net)

-85.7

_85.7 65.5

.32." Unit' Capacity. Factor;(Usin5 DER Net)_

12.8 12.8 15.5 85.0 85.0 64.3-

33. Unit' Forced Outage Rate.

4 24.' Shutdowns Scheduled Over Next 6 Months (Type Date.--and Duration of Each):- E00 11

' Refuel and Steam Cenerator Roolacement Outage. May 1992i 160 days.

35,1f Unit Shutdown At' End'0f Report Period, Estimated.Date of. Startup: ~ Feb. 11. 1992

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

Forecast Achieved i

INITIAL CRITICALITY N/A N/A 1NITIAL ELECTRICITY N/A N/A

COMMERCIAL OPERATION N/A N/A i

i 4

- _ _. - _ _ - - _. -. ~ - -. - - _ _

DOCKET NO.

50-336 UNIT SHUTDO'JNS AND POb'ER REDUCTIONS 12IIT NAME Millstone ?

DATE 07/06/9?

COMPLETED BY C. Neron TELEPHONE (203) 447-l' i.

REPORT ti! NTH JANUARY l997 EXT.

4417 l

2 Zo.

Date Type Duration Reason Method of License Systta Compgnent Caus:- & Corrective (Hours)

Shutting Event Code' Code

.' Action to 3

Down Reactor Report

• Prevent Recurrence 01 920125 F

24.0 A

5 N/A N/A N/A Uhile operating at 100%

power, a Steam Jet Air Ejector (SJAE) radiation monitor alarmed. The unit was reduced to 786 power due to a suspected steam genera-tor tube leak.

02 920128 F

95.3 A

1 N/A N/A N/A On 01/27/92, whi. opera -

ting at 78% power, a decision was made to com-mence a. manual shutdown of the unit due to a steam generator tube leak. Testing and repair efforts are now in progress. The unit is currently scheduled to startup on-02/11/92.

1: Forced Reason:

3 2

7 Method

' Exhibit C'-

Instructions 5: Scheduled A-Equipment Failure (Explain) 1.hl -

for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets..for License l

C-Refueling 3-Automatic Scram Event. Report (LER). File l

D-Regulatory Restriction.

4-Continued from (NUREC-0161)

E-Operator Training & License Examination Previous month 5

F-Administrative

'5-Power Reduction Exhibit 1 :- Same Source l

C-Operational Error (Explain)

(Duration -0)

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

n w

m.

REEUELING IljPORMATION REOUEST 1.

Name of facility:

8111ntone 2 2.

Schedulod dato for next refueling chutdowns

_May3 1992 3.

Scheduled dato for restart following refueling N/A 4.

-Will refueling or resumption of oporation thoroattor require a technical. specification change or other licenso amendment?

NQDe at_this time 5.

Scheduled date(s) for submitting licensing action and supporting

-information:

Nono 6.

Important licensing considerations associated with refueling, o.g.,

-now or different fuel design or supplier, unroviewod design or performance analysis methods, significant changes in fuel design, now oporating proceduront liiL A:one 2 will bo repingjna the Steam _ Grjlerator sub-agantnblies dur-no the uncomi na Md _ of. cycle 11_ _ref ueling_ctutngo.

It in ant:.cloated this sjll be accomplished under 10CFR 50.59.

7.

The number of uol assemblies (a) in the coro and (b) in the spont-fuel storago pool:

i In Coros (a) all In Spont Fuel Pools (b) 212 NOTEt " hose _Dumbers ropt:osent the total fuel assemblies and consol-

. dated fuel storage boxes in these two (2) Item control AIDAS

8.. The present_11 conned opont fuel pool storago capacity and the sizo of any increaso.in licensed storago capacity that has boon requested or is planned'-in number of fuel assemblios currentiv 127L 9.

The projected dato of the last refueling that can be dischargod to the spent fuel pool assuming the procent licensed capacity:

1994. Soent F_ng:

Pool Fyll, core off load _ capacity is reached (with

-out consolidat:.on).

,1998. Coro Puli.' Soent Fuel Pogl_ Full 2009. Soent-Fuel Pool Full. core off load capagity_is reaghed-E2ntiDEDat_upon full scale storano of consol'ldated fuel in the Spent Fuel Pool.

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