ML20030C448

Monthly Operating Rept for Jul 1981

ML20030C448
Person / Time
Site:	Fort Calhoun
Issue date:	08/10/1981
From:	Short R OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20030C440	List: ML20030C439 ML20030C448
References
NUDOCS 8108260117
Download: ML20030C448 (10)

Text

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-285 UNIT Fort Cal 3 #1 DATE August 10, 1981 CON 1PLETED BY R. W. Short TELEPilONE (402)S36-4543 P

st0NTII July, 1981 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (5tWe-Net)

(51We-Net) 437.3 432.4 37 2

437.8 18 432.5 3

437.7 431.9 39 4

439.2 20 431.4 5

438.9 21 433.4 6

437.0 433.2 22 434.1 434.0 7,

23 8

434.0 435.6 24 9

433.9 25 433.8 to 435.4 26 436.0 435.0 439.1 27 32 433.1 442.0 28 i3 430.7 441 9 29 14 429.5 441.4 3o 15 429.8 442.1 3

16 431.8 INSTRUCTIONS On this format. list the average daily unit power level in Nlwe Net for each oay in the reporting inonth. Compute to the nearest whole megawatt.

(9/77) l 8108260117 alogio PDR ADOCK 05000285 R

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OPERATING DATA lEPORT 50-285 DOCKET NO.

DATE August 10, 1981 CO31PLETED BY R. W. Short TELEP110NE (402)53G4543 OPERATING STATUS

1. Unit Name:

Fort Calhoun Station Unit No.1 Ncte$

2. Reporting Period:

July, 1981 1500

3. Licensed Thennal Power (31Wt):

4. Nameplate Rating (Gross 51We):

501

5. Design Electrical Rating (Net SIWE): 478

6. Stasimum Dependable Capacity (Gross SlWe):

501

7. Slasimum Dependable Capacity (Net 31We):

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

N/A

9. Power Level To which Restricted,if Any(Net SIWE):

N/A

10. Reasons For Restrictions.If Any:

N/A This Alonth Yr..to.Date Cumulative

11. Ilours In Reporting Period 744.0 5,087.0 68,808.0

2. Number Of flours Reactor Was Critical 744.0 4,954.0 54,732.3 I3. Reactor Reserve Shutdown flours 0.0 0.0 1,309.5

14. Ilours Generator On-Line 744.0 4,905.4 53,665',3

15. Unit Resene Shutdown flours 0.0 0.0

'0.0

16. Gross Thermal Energy Generated (MWII) 1,052,832.4 5,149,675.9 64,867,916.2

17. Gross Electrical Energy Generated (AlWil) 340,586.0,_,

1,687,060.0 21,475,331.6 IS. Net Electrical Energy Generated (31Wil) 323,~9DT.T 1,582,943.5 20,281,126.4

19. Unit Senice Factor 100.0 96.4 78.0 l

20. Unit Availability Factor 100.0 96.4 78.0

21. Unit Capacity Factor (Using AIDC Net) 91.1 64.6 64.5 91.1 64.6 64.1 l

22. Unit Capacity Factor (Using DER Net)

23. Unit rurced Outa::e Rate 0.0 3.6 4.0

24. Shutdowns Scheduled Oser Nest 6 alonths (Ty pe. Date, and Duration of Each t:

Refueling, September 15, 1981, 4-7 Weeks i

l

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

N/A

26. Units in Test Status tPrior to Commercial Operation):

N/A Forecast Achiesed INITIA L CRITICA LiTY I

INIT I \\L ELECTRICITY CO\\l\\lERCIA L OPER A llON 1

i.

I (4/77)

s DOCKET NO.

._5_0. -235 UNIT SIIUTDOWNS AND POWER REDUCTIONS UNIT NAME _ F_ ort Calhoun #1 DATE Auoust 10. 1981 6

COMPLETED llY R. W. Short REPORT MONTil July. 1911 TELEPilONE (402)536-4543 r.

2g 3

)Yk Licensee

,E r, Cause & Corrective No.

Date g

3g j

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Event uy o-3 Action to Report a

<2 0 Prevent Recurrence jE 3 5 =g H

u C

No outages during the month of July, 1981.

i 2

3 4

F: Forced Reason:

Method:

Exhibit G -Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data Il-Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3-Automatic Scram.

Event Report (LER) File (NUREG-D Regulatory Restriction 4-Other ( Explain) 0161i E-Operator Training & License Examination F-Administ rative 5

G-Operational Error (Explain)

Exhibit !- Same source (9/77)

Il-Other ( Explain )

Refueling Infomation Fort Calhoun - Unit No. 1 Report for the nont.h ending July 1981 1.

Scheduled date for next refueling shutdown.

Septe'mber 15, 1981 2.

Scheduled date for restart following refueling.

Nove:rber 15, 1981 3.

Will refueling or restmption of operation thereafter reqaire a technical specification change or other license amendment?

No a.

If anse r is yes, what, in general, wi]1 these be?

b.

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Connittee to deter-mine whether any unreviewed safety questions are associated with the core reload.

No c.

If no such review has taken place, when is it scheduled?

August 1, 1981 4.

Scheduled date(s) for submitting proposed licensing action and support infonration.

5.

Inportant licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis nethods, significant changes in fuel des 1gn, new operating procedures.

6.

The ntrber of fuel assenblies: a) in the core 133 assemblies b) in the spent fuel pool 197 c) spent fuel pool storage capacity an1 d) planned spent fuel pool storage capacity 4a3 7.

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

199; Prepared by

///

Myt[v)

Date August 3, 1981 y

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0:'.GA l'UBLIC PC74ER DISTRICT Fort Calhoun Station Unit No. 1 July 1981 Monthly Operations Report I.

OPERATIONS SU'afARY The unit operated at 955 Reactor Power during the month of July.

Preparations for the SRO examination continued.

The exams were airinistered by the NRC on July 29, 1981.

Surveillance Tests and Operational Tests were performed.

No Safety Va.'ve or PORV challenges occurred on the primary system.

A.

PERFOR'MNCE CHARACTERISTICS LER Number Deficiency LER 81-006 The "3" channel Nuclear Power Recorder decreased approx-mately 30% in power level (as opposed to the remaining 3 channels).

"B" channel T decreased to approximately H0T 507 F from the normal operating temperature of 588 F.

The AT power level dropped approximately 15f, from its nonnal reading (and the readings of the remaining three channels).

In addition, "B" Subcooled Margin Monitor went into alarm.

The reactor was operating at approxi-mately 9h% power at the time.

The RPS was subsequently placed in a two-out-of-three logic to trip modes (i.e.,

"B" channel was placed in bypass.

It was discovered that an inadvertent ground in the NI recorder and one in a termperature loop for that channel of the RPS had causei a current loop which provided the path for the incongrous readings.

The grounds were iso-lated and the calibrations of the temperature loop and recorder checked to verify proper operation. The RPS was returned to full operability.

LER 81-007 During routine power operations at approximately 95%

power, control room operators received several..dications that diesel generator DG-1 had tried to start. These indications included:

(1) the " engine start" light being lit, (2) the diesel air dampers going open, (3) the " engine running" computer signal, and (b) the " diesel trouble" annuciator.

Immediate inspection revealed that diesel D1 had not actually started.

Monthly Operations Report July 1981 Page Two A.

PEEFOR'4 ATE CHARACTERISTICS (Continued)

LER 81-007 Diesel generator DG-2 was satisfactorily tested for operability and along with the 3h5 kv and 161 kv feeds (which were also available) more than c.lequate power was available to mitigate the consequences of an accident if necessary.

It was discovered that the speed sensing module was defective and gave the erroneous indication.

The module j

was replaced with a calibrated module and the Diesel returned to service.

B.

CHANGES IN OPERATING METHODS NONE C.

RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS Surveillance tests as required by the Technical Specifications Section 3 0 and Appendix B, were performed in accordance with the annual surveillance test schedule. The following is a summary of the surveillance tests which results in Operations Incidents and are not reported elsewhere in the report:

Operations j

Incident Deficiency i

OI-1347 ST-RM-3 Calibration of Process Radiation Monitoring.

4 (1) Facility license change number 7801 cor-rects this technical specification discre-pancy and is still awaiting NRC Action.,

(2) Completion of calibration (3) Completion of Surveillance Test Revision.

D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Dese:'iption SP-FAUD-1 Fuel Assembly Uplift Condition Detection the two operable op channels shows greater than 99%

assurance that the 150 pound criterion is not being violated.

An unreviewed safety question as defined in 10CFR50.59 did not exist as this procedure only involves evaluating data from a surveillance test.

L

Monthly Operational Report July 1981 Page Three D.

CHAIGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (Continued)

Procedure Description EEAR FC-78-49 Battery Room Ventilation completed as designed.

This modification did not constitute an unrev.iewed safety question as defined in 10CFR50.59 since it was made to reduce the chances of fire in the rooms in which the Station batteries are contained.

EEAR FC-79-5h Water Plant Supply Pump Modification completed as designed.

This modification did not constitute an unreviewed safety question as defined in 10CRR50 59 because the work done was on a non-safety related system.

EEAR FC-80-94 Vacuum Priming Trap Replacement completed as designed.

This modification did not constitute an unreviewed safety question as defined in 10CFR50.59 because the work done was on a non-safety related system.

DCR FC-75B-T Raw Water Pressure Switches completed as designed.

This modification did not constitute an unreviewed safety question as defined in 10CFR50 59 because it only involved installing voltage suppressors across switches to prevent induced DC transients.

DCR FC-75A-6 Auxiliary Building Hot Standby / Minor Piping Modi-(

fication in piping run.

DCR 75A-6 involved piping modifications to the t

auxiliary boiler to reduce thermal shock encount-ered when the boiler is placed in operation and to improve pressure regulation.

This modification did not constitute an unreviewed safety question as defined in 10CFR50 59 because the work done was on a non-safety related system.

1 l

DCR FC-77-10h Expansion of Ccmputer Room completed as designed.

This modification did not constitute an unreviewed safety question as defined in 10CFR50 59 because it only involved expansion of the computer room.

l Necessary security plan requirements were taken during the modification.

1 i

Monthly Operational Report July 1931 Page Fcur D.

CHANGES, TESTS A'!D EXPERIMENTS CARRIED OUT WITFOU" C0FtISSION APPROVAL (Continued)

Procedure Description EEAR FC-79-218 Jockey Pump completed as desigred.

This modification did not constitute an unreviewed safety question as defined in 10CFR50.59 because Tech. Specs. limits on outage time for the fire protection system were not exceeded.

EEAR FC-78-39 Installation of drain lines and isolation valves in the plant Compressed Air System.

This modification did not constitute an unreviewed safety question as defined in 10CFR50.59 because the work done provided for better reliability of the compressed air system.

EEAR FC-78-50A HVAC for Switchgear Rooms completed as designed.

This modification did r.ot constitute an unreviewed safety question as defined in 10CFR50 59 because it only involved air conditioning the Switchgear Rooms to help improve equipment reliability.

EEAR FC-78-50 Switchgear Room Separation completed as designed.

This modification did not constitute an unreviewed safety question as defined in 10CFR50.59 because it only involved dividing the Switchgear Room with fire barriers to help ensure a fire 9ould not take out redundant safety related equipment.

DCR FC-76-82 Installation of Unions on boration system safety valves.

l This modificaion did not constitute an unreviewed safety question as defined in 10CFR50 59 because it only involved iactallation of appropriste Nuclear Class fittings to remove relief valves for inservice inspection as required by Tech. Specs.

E.

RESULTS OF LEAK RATE TESTS On 7-29-81 PAL door tested at 60 psig.

Leak rate = 0.0 seem F.

CHANGES IN PLANT OPERATING STAFF NOME

i

'donthly Operational Report July 1931 Page Five G.

TRAI ING Training for July incluaed:

General Employee training and retraining for security badges.

Maintenance training on systems and Tech. Specs.

Operator requalification training program.

SRO training for 3 candidates to sit for NRC exmn in late July.

Safety meetings for each craft.

H.

CHANGES, TESTS A'ID EXPERIME ITS REQUIRING NUCLEAR REGULATORY COEiISSION AUTHORIZATION PURSUANT TO 10CFR50 59 HONE

/

p/

Approved By Managef - Fort Calhoun Station

e

..i Monthly Operational Report July 1981 Page Six II.

MAI:ITE'IA' ICE (Significant Safety Related)

~~'

M. O.

4 Date Description Corrective Action 10093 7-lh 81 Area Monitor RM-088 spiking into Cleaned switch and contacts.

alert.

10019 7-lh 81 AI klB breaker and cable faulted.

Replaced cable.

102h1 7-lh 81 V0PT Channel C reset demand push-Replaced switch, button on CB/does not reset.

102h3 7-lh 81 Air Sampler has high flow.

Replaced filter and cartridge.

106h8 6-25 81 RPS "B" Safety Channel T un grounds at 2 points in HOT Swing.

the current loop B/122-H.

Repaired 10h0h 6-8-81 "A" Raw Water Strain 3r Breaker Freed Strainer.

stops and doesn't trip.

10h10 6 h-81 Containment Particulate Monitor Replaced Take-up Motor.

RM-050 Take-up Motor faulted.

10272 5-22-81 RM-076 Radiation Monitor Set-Cleaned switch alarm contacts.

point out of tolerance.

102h0 6-10 81 AI-137 Improper indication for Replaced fuses on power smoke damper override switch 83A supplies and rewired.

& 83B off normal.

10231 5-20-81 Charging Pump CH-1B trips free when Replaced control switch.

trying to start.

108hl 7-10-81 Aux. FW Auto Initiation LI-906Y-1 Adjusted agastat and retested.

Setpoints not within tolerance.

10595 6-3-81 Iloise in Charging Pump CH-1B Realigned and replaced broken gear Box.

line.

10871 7-lh 31 Fire Pump FP-1B running 70 RPM low.

Reset RPM at 1760.

10903 7-21 81 Charging Pump CH-1B tank hot over-Repaired per MP-CH-1.

flowing.

10903 7-16 81 Heat Tracing TAR-2 Point 12 indi-Cleaned selector relay &

cating >300 F.

contactor.

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