ML20058G972

Monthly Operating Rept for Oct 1990 for Millstone Unit 3.W/

ML20058G972
Person / Time
Site:	Millstone
Issue date:	10/31/1990
From:	Elms A, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-90-1181, NUDOCS 9011140155
Download: ML20058G972 (5)

Text

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November 5, 1990 MP-90-1181 Re: 10CFR50.71(a) l 6

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

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Reference:

Facility Operating License No. NPF-49

[

Docket No. 50-423 i

Dear Sir:

f In accordance with reporting requirements of technical specifications Section 6.9.1.5, the Millstone Nuclear Power Station Unit 3 Monthly Operating Report %11 covering opera-tion for the.nonth of October is hereby forwarded.

f Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

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M f-Steph6n E cace (4c6 s

Director, Millstone Station Attachment cc: T.T. Martin, Region I Administrator W.J. Raymond, Senior Resident Inspector, Millstone Unit Nos.1,2 & 3 D.H. Jaffe, NRC Project Manager, Millstone Unit No. 3 I

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'""" NRC OPERATING $1ATUS REPORT COMPLf1ED BY REACTOR ENGINEtklNG ""*"

1 1.

DOCKET.... 50 423 OPERA 11NG STATUS 2.

REPORTING PER100.. 0Cf00ft 1990 OUT AGE

• ONLINE NOUR$... 0.0

• 745.0 = 745.0

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3. Ut illif CONT AC1................. A. L. ELMS 203 444 5388 l

4.

L I CE N SED T HE RMAL P0WE R......................................... 3411

• MILL $ TONE

• l

5. h AME PL Af t R At l NG (GRost MWE )................................... 1,253 MW

• UNil 3 6.

Dill GN E t t CTR I CAL R A11 NG ( ut i MWE )............................. 1,153. 6 7.

mat lMUM DE Pf MD AB L E CAPACI T Y ( GROS $ MWE )........................ 1,184. 2 8.

max lMUM DE PE ND ABL E CAPAtliY (NE T MWE ).......................... 1,137.0 9.

IF CHANGES OCCUR AROVE $1NCE LAST REPORT, REASONS ARE...........

l N/A

10. POWER LEVEL 10 WHICH RESTRICTED, if ANY (NET MWE)...............N/A

11. REASON FOR RESTRICTION, IF ANY....N/A MONTH YEAR 10 DATE CUMULATIVE TO DAtt reens t

12. HOUR $ IN REPORilNG P.RIOD 745.0 7,2%.0 39,672.0

13. NUMsER OF HOUR $ THE REAC10R WA$ CRiflCAL 745.0 6,452.6 32,128.5

14. REACTOR RESERVE $NUIDOWN HOUR $

0.0 797.6 1,521.5

15. HOUR $ GENERATOR ONLINE 745.0 6.343.9 31,508.9 l

16. UW11 RESERVE SHUTDOWN HOUR $

0.0 0.0 0.0

17. Gross THERMAL ENERGY GENERATED (MWH) 2,235,276.0 20,292,299.0 103567708.4

18. Gross ELECTRICAL ENERGY GENERATED (MWH) 750,978.0 6,947,716.5 35,630,356.5 l

19. N(i (LICTRICAL [NERGY GENERATED (MWH) 716,105.7 6,608,388.7 33, % 3,757.4

20. UNIT SERVICE FACTOR 100.0 87.0 79.4

01. UNil AVAILA8illfY FACTOR 100.0 87.0 79.4

22. UNIT CAPAClfY FACTOR (USING MDC NET) 84.5 79.7 75.0

23. UNIT CAPACITY FACTOR (U$ING DER NET) 83.3 78.5 74.2

24. UNIT FORCED OUTAGE Raft 0.0 12.8 10.2

25. UNif FORCED OUTAGE HOUR $

0.0 933.6 3,571.1 l

SHUIDOWNS 6CHEDULED DVER NEXT SIX MONTHS (iYPE, DATE, AND DURAtl0N OF EACN)..............

Refuel Outage February 1 1991 (stbject to CONVEX approvel) 56 days IF CURRENTLY SHUIDOWN, ESTIMATED STARTUP DAff......N/A

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

E-3,23 UNIT Mll.1 RTONE UNIT 3 DATE November 2. \\290 COMPLETED BY A. L ELMS 203-444 5388 MONTH October 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE NET)

(MWE. NET) 1 1116 16 1114 2

1113 17 1096 3

1108 18 922 4

876 19 416 5

294 20 1028 6

536 21 1119 7

959 22 1116 8

1082 23 1115 9

1094 24 1126 10 1093 25 771 11 1094 26 242 12 1098 27 460-l 13 1116 28 1127-14 1117 29 1119-15 1114 30 1124 31 1126

+

DOCKET NO. 50-423 UNIT SHUTDOWNS AND POWER ' REDUCTIONS UNIT NAME M;'.T J xwNE 3 DATE 1:.-2-90 COMPLETED BY A.

EIJES TELEPHONE (203) 444-5388 No.

Date Dura-Reason Method of Licensee

" System Componant Cause and Corrective

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tion (2)

Shut down Event Code Code Action to Prevent Hours Reactor (3)- Rept No.

Prevent Recurrence Decreased power to 85% to 93-10 10-04-90 S

O H

5 N/A KE SCM perform a condenser back-t wash. Further downpower 4

caus9d,by degraded intake conditions as the result l

of a storm.

Decreased pow 9r to 35%

90-11 10-18-90 S

O H

5 N/A KE SCN due to, degrading weather conditions.

t Administratively de-90-12 10-25-90 S

O H

5 N/A BIR SB creased p9wer due to high sulfates in the steam-gener3 tor secondary side.

1: F: Forced 2: Reasons:

3: Method 4: Exhibit G - Instructions A-Equipment FailureB-Maintenance or Test (Explain) 1-Manual for Preparation of, Data-S: Scheduled 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continued from (NUREG-0161) 5 previous monthPower Reduction 5: Exhibit 1 - Same Source E-Operator Training Er License Exam F-Administrative G-Operational Error (Explain)

(Duraticn = Q)

H-Orner 9-Other (Explain)

REFUELING INFORMATION REOUEST October 1990 1.

Name of facility: Millstone 3.

2.

Scheduled date for next refueling shutdown: February 1.1991 (awaiting CONVEX approvalt 3.

Scheduled date for restart following refueling: March 29.1991 1

4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendments?

A. As a result of t le new fuel desinn. Technical Snec fications channes to the Axial Flux Difference. I-cat 71trc Hot Channe ' Fa: tor. and Refuelina Water Storane Tank

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sections will be reouired. ;urthermore. the :

uel Storane section of Desien Features will be changed to allow continued regionalized storage of soent fuel in the spent fuel

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P0DL H. Also the Instrumentation section will be chanced to reflect a new Hinh Flux at Shutdown setooint.

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5.

Scheduled date for submitting licensing action and supporting information.

A. Submitted November 1.1990.

B. Scheduled submittal date December 1.1990.

6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design of performance analysis methods, signifi-cant changes in fuel design, new operating procedures:

Cycle 4 fuel assemblies will be of the Westinchouse Vantane SH desien. This desien includes debris filter bottom nozzles. intermelliate flow mixinc crids. intecral fuel rod aurnable absorbers. and axial blankets.

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7.

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

(a): 1%

(b): 160 8.

The present licensed spent fuel pool storage capacity and the size of any increase in l

licensed storage capacity that has been requested or is planned, in number of fuel i

assemblies:

t Present size - 756.

N'o increase reouested.

9.

The projected date of the last refueling that can be discharged to the spent fuel pool assummg the present beensed capacity:

End of cycle 5.

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