ML19346A405

Monthly Operating Rept for May 1981

ML19346A405
Person / Time
Site:	Fort Calhoun
Issue date:	06/12/1981
From:	Tira Patterson OMAHA PUBLIC POWER DISTRICT
To:
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ML19346A401	List: ML19346A400 ML19346A405
References
NUDOCS 8106190278
Download: ML19346A405 (9)

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(,/ . AVER AL,E DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT Fort Calhoun #1 DATE June 12, 1981 COMPLETED BY T. L. Patterson TELEPilONE (402)536-4413 MONTil May, le81 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (MWe-Net) 256.8 i7 196.0 2 273.2 18 196.5 3 277.7 39 196.9 4 280.5 20 194.6 5 287.4 21 189.5 6 296.6 22 191 4 7a _

210.8 23 189.2 g 197.3 24 188.4 9 196 0 25 188.5 10 194.7 26 188.0 ,

5: 194.8 27 187.7 12 195.6 28 188.3 33 195.2 29 187.7

.: 196.4 3o 186.7 15 195.4 3 188.0 16 195.~3 INSTRUCTIONS On this format, list the average daily unit power levelin MWe Net for each day in the reportmg month.Cmnpute to the nearest whole nwgawatt.

(9/77)

H106190.278

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OPERATING DATA REPORT DOCKET NO. 50-285 DATE June Iz, 1981 CO.\lPLETED BY T. L. Patterson TELEPilONE (402)536-4413 OPER ATING STATUS

1. Unir Name: Fort Calhoun Station Unit No. 1 Notes

2. Reporting Period; May, 1981 Power maintained at about 15U0 40% most of the month to

3. Licenwd Thermal Power (31Wt):

4. Nameplate Rating (Gross 31We): 501 conserve fuel.

5. Deugn Elev rical Rating (Net SlWe): 478

6. Alasimum Dependable Capacity (Gross Nlwe): 501

7. Stasimum Dependable Capacity (Net alwe): 470

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

Electrical ratings based upon turbine vendor calculations as a result of reactor stretch power to 1500 MWth.

(Net 31We): N/A

9. Power Lese! To hhich Restricted,if N Any/A

.10, Reasons For Restrictions.lf Any:

This Stonth Yr..to.Date Cumularise I1. Ilours in Reporting Period 744.0 3,623.0 67,344.0 744,0 3,490. F 53,268.3

12. Number Of flours Reactor Was Critical

13. Reactor Resene Shutdown flours 0.0 0.0 1,309.5

14. Ilours Generator On-Line 744.0 3,448.0 52,207.9

15. Unit Resene Shutdown llours 0.0 0.0 ' O.0

16. Grow Thermal Energy Generated (51WII) 536.107.5 3,352,089.0 63,070,329.3 .

17. Grow Electrical Energy Generated 13thil) 169.944.0 1,105,998.0 20,894,269.6

18. Net Electrical Energy Generated (31Wil) 156,048.4 1,033,447.2 19,731,630.1

19. Unit Senice Factor 100.0 95.2 77.5

20. Unit Availability Factor 100.0 95.2 77.5

21. Unit Capacity Factor (Using SIDC Net) 43.9 59.1 64.1

22. Unit Capacity Factor (Using DER Net) 43.9 59.1 63.8

23. Unit Forced Outage Rate 0.0 4.8 4.1

24. Shutdowns Scheduled Over Next 6 alonths (Type. Date.and Duration of Eacht:

Refueling Outage, September 15, 1981, 6 Weeks

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

26. Units in Test Statuu rrior to Commercial Operationi: Forecast Achiesed INITIA L CRITICA LITY -

INillA L ELECTRICI fY CollstERCIAL OPER ATION (9/77)

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• DOCKET NO. 50-285 UNIT SilUTDOWNS AND POWER REDUCTIONS UNITNAME. Fort Calhoun #1 DATE June 12, 1981 REPORT MONTH May, 1981 COMPT.ETED BY . .. L. Patters.gn TELEPHONE i 402)S36-4413 w.

, j ?. 3 .5 Licensee P, , Cause & Corrective

. No. Date r- 5g 4 2s5 Esent  :: ? n '? Actmn to

$5 5 jgg Report

• 5E U 0 Present Recurrence d

No outages during the month of May.

I 2 3 4 F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A Equipment Failure (Explain) I-Manual for Preparation of Data .

B. Maintenance of Test 2 Manual Scram. Entry Sheets for I.ieensee C Refueling 3-Automatic Scram. Event Repor (LER) FileINUREG.

D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training i License Examination F-Administralise 5 G-Operational Error (Explain) Exhibit I -Same Source 19/77) II-Other (Explain)

Refueling Information

. Fort Calhoun - Unit No. 1 i

' Report for.the month ending May 1981 . ,

1. Scheduled date for next refueling shutdown. September 15, 1981

2. -Scheduled date for restart following refueling. November 15, 1981

5. .Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? No  ;

a. If answer is yes, what, in general, will

i. these be? ,

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

l c. If no such review has taken place, when is i it scheduled? September 1, 1981

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

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l 5. Important licensing considerations associated with refueling, e.g., new or different fuel design or ,

supplier, unreviewed design or performance analysis l

' methods, significant changes in fuel design, new

! operating procedures.  ;

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6 .~ The number of fuel assemblies: a) in the core 133 assemblies b) in the spent fuel pool 197 l

c) spent fuel pool l storage capacity 483 d) planned spent fuel pool storage capacity 483

7. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present i . licensed capacity. 1985 9

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. OMAHA PUBLIC POWER DISTRICT c' ort Calhoun Station Unit No. 1 May 1981 Monthly Operations Report I. OPERATIONS

SUMMARY

Fort Calhoun Station operated at power levela of 63% and 45% for the month of 'Aay.

There were no scheduled or unscheduled outages during the month of May.

The operations department participated in the audit conducted by the Institute of Nuclear Power Operations at Fort Calhoun Station. The audit was conducted over a two week period and covered all areas of plant operation.

Training for three senior reactor license upgrades were initiated in May.

Operational Surveillance tests and normal tests were completed during May.

No safety valve or PORV challenges occurred.

A.

• PERFORMANCE CHARACTERISTICS LER Number Deficiency LER 81-003 During normal operations at approximately 45% power, all 125 volt DC power feeding bus AI-41B was lost.

The main steam isolation valves (HCV-1041A/HCV-1042A) failed closed upon this loss of control power to AI-41B. These valves failing closed initiated an EHC turbine trip, which in turn, caused a reactor trip.

The loss of DC power would not have affected the ability of the plant to safely shutdown should an accident have occurred since redundant safeguards equipment was available and operable on DC panel AI-41A.

LER 61-004 During performance of ST-CONT-2, Section F.1 (test of personnel air lock scala), the leak rate of both door seals exceeded the allowable leak rate. Con-tainment integrity requires at least one door to be i properly sealed in any mode but cold shutdown. ,

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Monthly Operations Repu.-

May_1981 Page Two E

A .' PEAFORMANCE CHARACTERISTICS (Continued)

LER Number Deficiency LER 81-005 While operating at approximately 45% power and, pertorming surveillance test ST-ESF-2, Section F.1 (the monthly DC sequencer timer test), timers AC-3A

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(Component Cooling Water Pump) and AC-10A (Raw Water Pump) failed to time out within their pres-scribed limit. During the time of the failure, the AC sequencer timers which activate AC-3A and AC-10A were operable and available if needed. In addition, all sequencer timers, both AC and DC (from both "A" and "B" safeguards' trains) feeding redundant Component Cooling Water Pumps and Raw Water Pumps were available and operable if needed.

l-B. CHANGED IN OPERATING METHODS None i

! 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 in the report:

Operations Incidents Deficiency 01-1314 ST-FW-1 Failure to get 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> signature by Plant Engineer.

01-1306 ST-ESF-2 D.C. Sequencer timers for AC-3A and AC-10A not within prescribed ILmits.

O. '319

. ST-ESF-2 While performing ST-ESF-2, step inadvertantly missed causing 480V load shed.

l D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL l

Procedure Description SP-CPTP-12 This prccedure was performed to measure the moderator

temperature coefficient of reactivity to meet the

! requirements of Tech. Spec. 3.10.2.(3) which requires

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Monthlf Operations Report May 1981-Page Three D. CHANGESi TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (Continued)

Procedure Description SP-CPTP-12 (Continu~ed) the measurement within 7 EFPD of reading a HFP RCS boron concentration of 300 ppm boron. The test required movement of the center CEA which is per-mitted by Tech. Spec. 2.10.2 under Test Exemptions.

The results of SP-CPTP-12 showed.all parameters to be within the acceptance criteria.- This procedure does not involve an unreviewed safety question per 10CFR50.59(c). All operating evolutions required for this test trere carried out in strict accordance with Technical Specification and have previously Jbeen subjected to a safety analysis.

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.

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! An unreviewed safety question as defined in 10CFR50.59 1 l did not exist as this procedure only involves evaluating

! data from a surveillance test. t 1

EEAR/DCR Pressurizer Lined Control / Completed as designed.

1. FC-81-65 An unreviewed. safety question as defined 'in 10CFR50.59 did not exist as-the operational method of operating LT-101-Y was n,,t changed.- The transmitter-was moved from one physical. loc'at, ion in containment to another.

The new-location uses .the-eeme instrument manifold as-LT-106 (cold. calibrated leve'1). The level caps for l LT-106 are at the same level as those for LT-10lY.

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.Therefore, the calibration and operation-are the same as'in the other location. No changes to. wiring was l~

! made other than to extend existing wiring. Approved i

splices were used.

I l EEAR/DCR Replacement of solenoid valves on MS-291 and MS-292/

1. FC-79-168 Completed as designed.

An unreviewed safety question as defined in 10CFR50.59 did not exist as tha solenoids on MS-291 and MS-292 L with LOCA qualified solenoids. The operation of the ,

valves MS-291 and MS-292 are not affected. i l

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Monthly Operations Report May 1981 Page Four D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (Continued) ,

1 Procedure Description SP-CTPC-1 This procedure determined the thermal power of the Nuclear Steam Supply System based on ASME Power Test Code 32.1.

This procedure does not invove an unreviewed safety question per 10CFR50.59(c). 'The procedure is analytical only and does not involve any chang; to plant conditions or alignments.

E. RESULTS OF LEAK RATE TESTS No Leak Rate Test Results for May, 1981.

F. CHANGES IN PLANT OPERATING STAFF None ,

G. TRAINLNG Training for May at the Fort Calhoun Station included general employee training for both new and plant personnel, operator training and monitor team training as per the Fort Calhoun Station Training Manual and requirements training included systems, fire brigade and NRC requalification for cperators.

H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59.

Amendment No. 59 makes several changes, clarifications and improvements in the operability and surveillance requirements for hydraulic snubbers and adds similar new requirements for mechanical snubbers.

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ApprovedByI ( L .

i haha$r"- Mrt Calhoun Station

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Monthly Operations Report May 1981 j- Pa6e Five j II. MAINTENANCE (Significant Safety Related) i l M. O. # -Cate Description Corrective Action l

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'9728 4-7-81 HCV-500B stroke time exceeds Cycled valve as per ST-ISI-WD-1, L previous value, tested okay.

! -8943 4-23-81. CH-373 leaks. Repaired line per proeddure.

10038 4-30-81 Reactor Regulating Rod 40 stuck. Repaired per procedure.

l- 9859 4-10-81 CH-1B crack in veld on the Demin. Repaired per procedure.

water to the suction side.

t l 9544 2-28-81 Replace thermostat bor on DG-2. Completed, t

! 9884 4-13-81 LT-384 - Inspect for proper Amplifier replaced and I components. calibrated.

9777 4-3-81 Repack CH-1B. Completed per MP-CH-1.

! 9701 3-27-81 FT-1109/1110 - check for possible Checked amplifiers. No problems defective componen,t. found.

9745 3-30-81 RPS "C" Channel Trip Unit #7 Trip Recalibrated.

and Pretrip setpoints drifting.

9990 4-24-81 Replace battery to Diesel air Completed, compressor for DG-2.

l 10006 4-29-81 "A" Raw Water strainer backwash Replaced timer, timer inoperable.

10044 4-30-81 Pal Doors exceeded leak rate. Fluffed inner and outer door seal 9979 4-27-81 CH-1B leaks into pa'cking cooling. Repacked pump per MP-CH-1. - #

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