ML20205A835

Monthly Operating Rept for Jan 1987

ML20205A835
Person / Time
Site:	Cooper
Issue date:	01/31/1987
From:	Horn G, Sutton K NEBRASKA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
CNSS878043, NUDOCS 8703270501
Download: ML20205A835 (6)

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OPERATING DATA REPORT

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Qj DOCKET NO. 050-0298 DATE 2-10-87 .j ';O COMPLETED BY R- E. Sutton  %

- TELEPHONE 402-825-3811?  %:

a OPERATING STATUS -

, '$ 4 Cooper Nuclear Station Notes H'

1. Unit Name.

2. Reporting Period: January. 1987 $

I, 3. Licensed Thermal Power (MWt): 2381 -

4. Nameplate Rating (Gross MWe): 836

5. Design Electrical Rating (Net MWe): 778

6. Maximum Dependable Capacity (Gross MWe): 787 764

- 7. Maximum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

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9. Power Level To Which Restricted,If Any (Net MWe):

10. Reasons For Restrictions,If Any:

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This Month Yr to-Date ' Cumulative 744.0 744:0 110,353.0

11. Hours In Reporting Period ^

609.3 609.3 82,192.5

12. Number Of Hours Reactor Was Critical * *

13. Reactor Reserve Shutdown Hours 0.0 0.0 o.o 535.1 535.I 80,787.1

14. Hours Generator On-Line 0.0 0.0 0.0 .;

15. Unit Reserve Shutdown Hours '

16. Gross Thermal E'nergy Generated (MWH) 997.983.0 997,983.0 158.465.327.0 -

17. Gross Electrical Energy Generated (MWH) 329,913.0 _,

329,913.0 50.674.921.0 '. i

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18. Net Electrical Energy Generated (MWH) 316.751.0 316.751.0 - 48.823.249.O 71.9 71:9 73:2 -

19. Unit Service Factor

20. Unit Availability Factor .71.9 71.9 73.2 j

21. Unit Capacity Factor (Using MDC Net) 55.7

• 55.7 57.9

22. Unit Capacity Factor (Using DER Net) 54.7 54.7 56.9 <

! 23. Unit Forced Outage Rate -

• 13.0> 13.0 4.7 -

24. Shutdowns Scheduled.Over Next 6 Months (Type. Date.and Duration of Each1: .

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25. If Shut Down At End Of Report Period. Estimated Date of Startup: >

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY l INITIAL ELECTRICITY i COMMERCIAL OPER ATION -..

B703270501 870131

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. AVERAGE DAILY POWER LEVEL

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the nearest whole rnegawatt. -

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Operations Narrative Cooper Nuclear Station January 1987 The 1986 Refueling and Maintenance Outage continued into January until the generator was first placed on-line at 0858 on January 6, 1987. During initial reactor startup, an improper feedwater system value.line-up caused a-feedwater transient, as the RFP was being placed in service. As a result, the reactor scrammed at 1151 on January 4, due to IRM high flux.

On January 7, at 1945 a scram on low reactor water level occurred during single RF pump operation. This was the result of an open connection in the total feed flow circuitry caused by a loose connection discovered during investigation of a feed flow recorder problem. When the lead became disconnected, the RF pump speed was rapidly increased to balance feed flow with steam flow, however, this caused the pump to trip due to low suction pressure. The reactor water level then decreased producing a scram on low water level. Leads were replaced and checked throughout the RFC system before startup. The generator was placed on line at 0453 on January 10.

At 1027 on January 10, a scram on MSIV closure occurred due to a loss of actuator pressure. The low actuator pressure was the result of low ritrogen supply pressure. CNS procedures were revised and nitrogen supply pressure readjusted to better maintain the needed supply pressure. Hot startup procedures were implemented and the generator was placed on-line at 0726 on January 11, 1987.

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a DOCKliT NU. 50-298 -

UNITSIIUTDOWNS AND l'OWElt REDUCllONS CNS UNII NAnf E .

IIATE 2/10/87 CDstlLFJiI)I K Su __-

REPORT h!ONTII Januarv. 1987 _ _

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Psevent Itceurtence Q

86-07 861004 S 129.0 C 4 N/A RC FUELXX 1986 Refueling and Maintenance Outage.

87-01 870104 F 0 G 3 87-002 IBA IXMITR While placing a RF pump in service, an improper RF system valve lineup caused a feedwater transient. This resulted in a high flux scram.

87-02 870106 S 1.8 B 1 .N/A HA TURBIN Generator off-line for overspeed tur- ,

bine trip.

87-03 870107 F 57.0 H 3 87-003 CHA INDREC During investigation of a feed flow recorder problem, a loose lead became disconnected, causing a signal of no feed flow in the circuit. To balance feed flow with steam flow, the RF pump

! rapidly increased speed. This reduced suction pressure causing the RF pump to trip. As a result the reactor wa-ter level dropped and the reactor

=crammna nn inu daror invel_

l 2 3 4 F: Forced Itesson: htethod: Exhibit G Instructions

, S: Scheduled A liquipment Failure (Explain) 1 Alanual - for l'oeparation of Dara D htaintenance of Test 2 htanual Scram. Ent:y Sheets fm 1.ieensee

• C-!(efueling 3 Autunutic Seram. Event Itermi (LEltl File INiliti:G.

D Regulatory Restriction 4 Ollier (Explain) 0161)

E-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explain) Exhibis ! Same Source l'8/77) 1101her (Explain) ~. :,

DOCKET NO. 50-298 .

UNITS!!UIDOWNS AND POWElt REDUCil0NS ' CNS U NI I N A..! E nAl p, 2-10-87 ~

K. E. Sutton

• REPORT Af 0NTig January, 1987 C05tPLETED ItY

~1ELEPilONE 402-825-3811 No.

-, .!3 'N 3Yk Licensee 5 r, 'L' Cause & Corrective Date R 5S $ .555 Event g3 o3 gu Action to H g3 5 5 <.

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Continued from 87-03:

, All leads were verified to be secure i , throughout the RFC system before startup.

87-04 870110 F 21.1- A 3 87-005 CCA VALVOP While inerting the drywell the nitro-gen supply pressure to the primary .

containment'decres's'ed fcausing1MSIV -

closure due to loss of actuator pres-sure. CNS procedures were revised and the nitrogen supply pressure was readjusted to better maintain system requirements.

l I 2 3 . 4 F: Forced Itesson: Method: Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 14!anual for Pseparation of Data .

114taintenance of Test 24tanual Scram. Entry Sheets foi 1.iecusee

• C Itefueling 3 Autunutic Scram. Event Iteptus (LI:lti File INtillt:G-D Itegulatory itestriction 4-Utlics (Explain) 0161)

E-Operator Training & License Examination  !

F.Adininistrative 5 G Operational Error (Explain) Exliibit I Same Source 08/77) Il-Other (Explain)

v-COOPER NUCLEAR ST ATION Nebraska Public Power District " * ;h"c"J*"J'tM; 0,""^,5,"^

CNSS878043 February 10, 1987 Director, Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Monthly Operation Status Report for January, 1987 Docket No. 50-298 Gentlemen Enclosed for your information and use is the Cooper Nuclear Station Monthly Operating Status Report for January, 1987. The report includes Operating Status, Average Daily Unit Power Level, Unit Shutdown Data, and a Narrative Summary of Operating Experience.

Should you have any comments or require additional information regarding this report, please contact me.

Sine rely, h

G. Horn Di ion Manager of Nuclear Operations GRH def Enclosure cc: G. D. Watson w/ enc.

A. C. Gehr w/ enc.

R. D. Martin w/ enc.

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