ML20125E456

Monthly Operating Rept for Nov 1992 for Millstone Nuclear Power Station,Unit 3

ML20125E456
Person / Time
Site:	Millstone
Issue date:	11/30/1992
From:	Elms A, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-92-1294, NUDOCS 9212170061
Download: ML20125E456 (7)

Text

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(203) 665-5000 Re: 10CFR50.71(a)

December 10, 1992 U.S. Nuclear Regulatory Commission MP-92-1294 Document Control Desk Washington, D.C. 20555

Reference:

Facility Operating License No. NPF-49 I

Docket No. 50-423

Dear Sir:

In recordance with reporting requirements of technical specifications Section 6.9.1.5, the Millstone Nuclear Power Station - Unit 3 Monthly Operating Report 92-12 covering opera-tion for the month of November is hereby forwarded.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY Stephen. S ace Vice President, Millstonc Station - NNECO Attachment cc: T.T. Martin, Region i Administrator P. Swetland, Senior Resident inspector, Millstone Unit Nos.1,2 & 3 V. L. Rooney, NRC Project Manager, Mi!! stone Unit No. 3 4UOO'di p$k21Jggg{ $$$

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• • • • • • • NRC OPERATING STATUS REPORT COMPLETED BY REACTOR ENGINEERING *******

1 1.

00CKET.... 50 423 OPERATING STATUS i

2.

REPORilWG PERIOD... NOVEMBER 1992 OUTAGE + ONLINE HOUR $.. 202.6

+ 517.4 720.0 s

3.

UT I L ' T Y CON T ACT................. A. L. E lse 203 444 5388 4 LICENSED THERMAL P0WER.........................................

3411

• MILLSTONE *

'.. N AME PL A T E RAT I NG ( GR OSS MWE )................................... 1,253 MW

• UNIT 3

+

f 6.

DESIGN ELECTRICAL RATING (NET MWE).............................. 1,153.6 j

7.

MAX I MUM DEPENDABLE CAPACI TY (GROSS MWE )........................ 1,184.2

)

8.

MAXIMUM DEPENDABLE CAPACITY (NET MWE)........................... 1,137.0 l

9.

IF CHANGES OCCUR ABOVE SINCE LAST REPORT, REASONS ARE...........

4 N/A i

10. PO6ER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE)...............W/A

11. REASON FOR RESTRICTION, IF ANY....N/A MONTH YEAR TO DATE CUMULATIVE 'O DATE t

sassa samassamassa massamasassesasses i

li. HOURS IN REPORTING PERIOD 720.0 J,040.0 57,936.0

13. NUMBER OF HOURS THE REACTOR WAS CRITICAL 568.7 5, 74 6.3 42,294.1 s

l

14. REACTOR RESERVE SKUTDOWN HOURS 0.0 828.1 6,466.5 l

15. HOURS GENERATOR ONLINE 517.4 5,569.2 41,387.0 I

16. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

17. GROSS THERMAL ENERGY GENERATED (MWH) 1,577,343.6 18,261,131.7 135,205,277.6

18. GROSS ELECTRICAL ENERGY GENERATED (MWH) 539,692.5 6,291,618.0 46,642,879.5

19. NET ELECTRICAL ENERGY GENERATED (MWH) 503,541.1 5,937,547.0 44,351,008.8

20. UNIT SERVICE FAC10R 71.9 69.3 71.4

21. UNIT AVAILABILITY FACTOR 71.9 69.3 71.4

22. UNIT CAPACITY FACTOR (USING MDC NET) 61.5 65.0 67.2

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23. UNIT CAPACITY FACTOR (USING DER NET) 60.6 64.0 66.4

24. UNIT FORCED OUTAGE RATE 28.1 26.5 19.0

25. UNIT FORCED OUTAGE HOURS 202.6 2,003.3 9,732.4 SHUTDOWNS SCHEDULED OVER NEXT SIX HONTHS (TYPE, DATE, AND DURATION OF EACH).

j N/A i

IF CURRENTLY SHUTDOWN, ESTIMATED STARTUP DATE.....N/A 1

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I AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.,sA323 UNIT MILLSTONE UNIT 3 DATE December 8.1992 i

COMPLETED BYA. L. Elms 203444 5388 MONTH November 1992 i

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MvvE - NET)

(MWE - NET) i 1

0 16 1128 2

0 17 1132 3

0 18 939 4

0 19 1131 5

0 20 147 6

0 21 0

7 20 22 527 i

^

8 462 23 1100 i

9 898 24 1132 10 1060 25 1131 11 1136 26 1126 12 1132 27

_ _ _ _1) 11 4

13 458 28 1133 14 897 29 1133 15 1129 30 1135 4

REFUELING INFORMATION REOUEST j

i November 1992 4

1.

Name of facility: Millstone 3.

2.

Scheduled date for next refueling shutdown: lune 5.1993 1

j 3.

Scheduled date for restart following refueling: August 14.1993 4.

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

4 j

N/A l

5.

Scheduled date for submitting licensing action and supporting information.

N/A 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:

N/A 7.

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

(a): 123 (b): Zia 8.

The present licensed spent fuel pool storage ca'pacity and the size of any increase in l

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

assemblies:

l Present size - 756.

No increase reauested.

9.

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

End of cycle 5.

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DOCKET NO. 50-423 T

UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME MILLSTONE 3

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DATE 12-08-92 COMPLETED BY A.

L.

Elms j

TELEPHONE (203) 444-5388 No.

Date Type Dura-Reason Method of Licensee System Component Cause and Corrective (1) tion (2)

Shut down Event Code Code Action to Prevent-Hours Reactor (3)

Rept No.

Prevent Recurrence t

Manually shutdown the l

92-06 11/01/92 F

112.4 H

4 3-92-022-VF CDMP reactor and turbine due to both trains 9f SLCRS being declared inoper-able. The root causes were incomplete system 4

design couplgd with several specific eelp-ment problgms, inadequate test surveillance proce-i durgs, and the dgsigr basis and operating parameters of the Auxili-ary Building Filter Sys-l tgm and its interaction with the Supplemental Leak Collection and Re-lease System was not ful-lv understood.. Design changes have been imple-l mented, surveillance ^

test procedures have been

revised,

a. system j

engineer concept is being implemented and procedures are being upgraded.

4 i

1: F: Forced 2:' Reasons:

3: Method 4: Exhibit G - Instructions S:, Scheduled

'A-Equipment Failure (Explain) 1-Manual for Preparation of, Data B-Maintenance or Test 2-Manual Scram EntU Sheets for Llegnsee

.i I

C-Refueling 3-Automatic Scram Event Re ort (LER) File j

D-Regulaton Rgstriction 4-Continued from (NUREG-O 61) 4 E-Operator Training & License Exam previous month 1-F-Administrative 5-Power Reduction 5: Exhibit 1 - Same Source i

G-Operational Error-(Explain)

(Duration = 0)

H-Other 9-Other (Explain) 6 i

i 2

UNIT SHUTDOWNS'AND POWER REDUCTIONS (CONTINUED)

No.

Date Type Dura-Reason Method of Licensee System Component Cause and Corrective (1) tion (2)

Shut down Event Code Code Action to Prevent Hours Reactor (3)

Rept No.

Prevent Recurrence 92-09 11/20/92 F

41.5 A

3 3-92-024 TG N/A Reactor and turbine trip caused by steam generator low-low level during a turbine runback. The run-back was caused by an unknown failure in the EHC system or EHC system power supply. The failure did not affect safety systems so the unit was restarted. The failed device was removed from service.

1: F: Forced 2: Reasons:

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

(Duration = 0 9-Other (Explain))

H-Other 4

. -. ~ - - - _ _..

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UNIT SHUTDOWNS AND POWER REDUCTIONS

~

i (CONTINUED) lActiontoPrevent Cause and Corrective No.

Date Type Dura-Reason Method of Licensee System Component (1) tion (2)

Shut down Event Code Code Hours Reactor (3)

Rept No.

Prevent Recurrence 92-07 11/05/92 F

48.7 A

3 3-92-027 EL RLY Unit and reactor trip caused by a spurious signal from ong of two offsite electrical sys-tem protective relays.

One of the relays was defeated.for less than 20% power where it is not needed. A design change is being implemented for the other relay to improve the design.

92-08 11/13/92 F

0.0 H

5 N/A KE SCN Power, reduction due to incoming storm.

1: F: Forced 2: Reasons:

3: Method 4: Exhibit G - Instructions-l S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data

(

B-Maintenance or Test 2-Manual Scram Ent y Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continued from (NUREG-0161)

E-Operator Training & License Exam previous month F-Administrat*.ve 5-Power Reduction 5: Exhibit 1 - Same Source G-Operational Error (Explain)

(Duration = 0 9-Other (Explain))

H-Other J

t