NRC-87-0055, Monthly Operating Rept for Apr 1987

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Monthly Operating Rept for Apr 1987
ML20214D716
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 04/30/1987
From: Lenart R, Shukla G
DETROIT EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
CON-NRC-87-0055, CON-NRC-87-55 NUDOCS 8705210440
Download: ML20214D716 (5)


Text

._

OPERATING DATA REPORT DOCKET NO. ~50-341 COMPLETED BY G. S. Shukla DATE May 12, 1987 TELEPIIONE (313)S86-1617 OPERATING STATUS 1.

UNIT NAME:

Fermi 2 l Notes 1

2.

REPORTING PERIOD: April, 1987 l

1 3.

LICENSED THERMAL POWER (MWL): 3292 l

,s l

4.

NAMEPLATE RATING (GROSS MWe):

1215 l

I 5.

DESIGN ELECT RATING (Net MWe): 1093 I

i 6.

HAX DEPENDABLE CAP (GROSS MWe):

l l

7.

MAX DEPENDABLE CAP (Net MWE):

l l

8.

IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS: None 9

POWER LEVEL TO WHICH RESTRICTED, IF ANY (MWe Net):

546.5

10. REASONS FOR RESTRICTION, IF ANY: Fermi 2 is in the startup test phase and is currently authorized to operate not in excess of 505'of rated thermal power.

(Ref. A. B. Davis letter of February 16, 1087).

/

THIS MONTH YR TO DATE CUMULATIVE

11. HRS IN REPORTING PERIOD 719 2879 5313 9
12. HRS REACTOR WAS CRITICAL 172.1 1517.2 2387
13. REACTOR RESERVE SHUTDOWN HRS 0

0 0

14. HOURS GENERATOR ON-LINE 61.5 1009.4 1138.9 71
15. UNIT RESERVE SHUTDOWN HOURS 0

0 0

\\

16. GROSS THERMAL ENERGY GEN (MWH) 76,512 999,024 1,222,272
17. GROSS ELECT ENERGY GEN (MWH) 12,783 186,091 196,541
18. NET ELECT ENERGY GEN (MWH) 3875 133,368 107,409
19. UNIT SERVICE FACTOR N/A N/A N/A
20. UNIT AVAILABILITY FACTOR N/A N/A N/A
21. UNIT CAP FACTOR (USING MDC NET)

N/A N/A N/A l

22. UNIT CAP FACTOR (USING DER NET)

N/A N/A N/A

23. UNIT FORCED OUTAGE RATE N/A N/A N/A
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION OF EACH)

None

25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 05/10/87
26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

l FORECAST ACHIEVED INITIAL CRITICALITY 06/20/85 06/21/85 INITIAL ELECTRICITY 10/01/86 09/21/86 COMMERCIAL OPERATION 08/01/87 "To Be Determined 8705210440 870430 PDR ADOCK 05000341 R

PDR

ATERAGE DAILY WIT POWER LETEL DOCKET NO.

50-341 UNIT FERMI 2 DATE May 12, 1987 COMPLETED BY G. S. Shukla TELEPHONE (313) 586-1617 MONTH April, 1987 Y

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 0

17 0

2 0

18 0

' 3 0

19 0

4 0

M 0

5 0

21 0

6 106 22 0

7 0

23 0

8 113 24 0

9 214 25 0

10 248 26 0

11 130 27 0

12 0

28 0

l 13 0

29 0

14 0

30 0

15 0

31 N/A 16 0

i l

l

UNIT SPAfTOO W S A8W POMER REDUCTIONS DOCKET NO.

50-341

-DATE

' May 12.'1987' t ri s, 7

a-y, UNIT NA'lE Fermi 2 COMPLETED GV G.

S.

Shukle' TELEPHONE (313)586-1617

+:

REPORT MONTH April. 1987 METHOD OF LER SYS COMP CAUSE & CORRECTIVE NO.

DATE TYPE OUR REASON SHUTTING DOWN NO.

CODE CODE

. ACTION TO PREVENT (1)

(HRS)

(2)

THE REACTOR (4)

(5)

PECURRENCE (3) 87-09 870316 S

127.7 8

4-N/A N/A N/A Continuation of the planned' outage between TC-2 and TC-3.

Major outage activities included mod-ifying the moisture separator re-heaters, installation of a perma-nent hatch on the torus and re-placement of RHR pump motor 8.

87-10 870406 F

42.2 G-3 87-011 IA INSTRUX Reactor scram due to personnel error while performing Average Power Range Monitor B Channel functional test.

During the per-formance of this test, half scram signals are introduced on channel' "B".

The IEC repairmen mistakenly pulled the Trip Reference Card for APRM "A".

This generated a full scram. Corrective actions in-cluded counseling the individual and revising the procedure.

Reported as LER 87-011 dated May 5 1987.

(1) F: FORCED

.(2) REASON:

(3) METHOD -

(4) EXHIBIT G - INSTRUCTIONS FOR PREPARATION OF DATA' S: SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL ENTRY SHEETS FOR LICENSEE 8 - MAINTENANCE OR TEST 2 - MANUAL SCRAM C - REFUELING 3 - AUTOMATIC SCRAM EVENT REPORT (LER) FILE D - REGULATORY RESTRICTION 4-CONTINUED (NUREG-0161)

E - OPERATOR TRAINING & LICENSE EXAMINATION 5 - REDUCED LOAD F - ADMINISTRATIVE 9 - OTHER G.- OPERATIONAL ERROR (EXPLAIN)

H - OTHER'(EXPLAIN)

(5) EXHIBIT 1 - SAME SOURCE D

e 9

_~ j UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-341 DATE' May 12.'1987 ~

UNIT NAME Form 2 COMPLETED EV G.

S.

Shukla TELEPHONE (313)586-161T REPORT MONTH April. 1987-METHOD OF LER SYS COMP CAUSE & CORRECTIVE NO.

DATE TYPE DUR REASON SHUTTING DOwN NO.

CODE CODE ACTICN TO PREVENT (1)

(HRS)

(2)

THE REACTOR (4)

(5)

RECURRENCE.

(3) 87-11 870410 F

13.4 A

9 N/A HA TURBIN Reactor was not shut down.

M61n Turbine-Generator tripped due to high vibration on 85 bearing.

Investigation revealed that a falso signal was generated due to a failed vibration sensing element. The..

failed equipment was replaced.

87-12 870411 F

474.3 A

2 N/A CC PIPEXA Turbine-generator manually tripped due to a steam leak on a weld from instrument, taps on the main steam lines.

A steam leak was reported from a pipe connection on the east bypass valve.

The leak could not be isolated so the reactor was placed in cold shutdown. Outage work includes repair of the east bypass valve, replacing instrument taps, inspecting welds, installing instrument tubing supports and repacking valves in the Turbine Building.

(1) F: FORCED (2) REASON:

(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 ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM EVENT REPORT (LER) FILE D - REGULATURV RESTRICTION 4 - CONTINUED (NUREG-0161)

E - OPERATOR TRAINING & LICENSE EXAMINATION 5 - REDUCED LOAD F - ADMINISTRATIVE 9 - OTHER G.- OPERATIONAL ERROR (EXPLAIN)

H - OTHER (EXPLAIN)

(5) EXHIBIT 1 - SAME SOURCE t

$UU$If,'"

R2g Guida 1.16 May 12, 1987

?I e gg 64m nortn o NRC-87-0055 Edison me...Hi9tvaay E:-

l U._S. Nuclear Regulatory Commission Attention:

Document Control Desk Washington, D.C.

20555

Reference:

-Fermi 2 NRC Docket No.

50-341 NRC Operating License No.

NPF-43

Subject:

Monthly Operating Status Report for Anril, 19_87 Enclosed for your information and use is the Fermi 2 Monthly Operating Status Report for April, 1987.

This report includes the Operating Data Report, Average Daily Unit Power Level, and the Summary of Unit Shutdowns and.

Power Reductions identified in NRC Regulatory Guide 1.16 and - Fermi 2 -Technical Specification 6.9.1.6.

If you have any questions, please contact us.

Sincerely, R.

S. Lenart Plant Manager Enclosure cc:

A. B. Davis J.

R. Eckert E. G. Greenman D. R. Hahn W. G. Rogers J.J.

Stefano Ih

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