ML20003C826

Monthly Operating Rept for Feb 1981

ML20003C826
Person / Time
Site:	Fort Calhoun
Issue date:	03/10/1981
From:	Tira Patterson OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20003C825	List: ML20003C824 ML20003C826
References
NUDOCS 8103180516
Download: ML20003C826 (10)

Text

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-285 UNIT Fort Calhoun #1 DATE March 10, 1981 COMPLETED BY T. L. Patterson TELEPilONE (402)536-4413 MONTli Februarv. 1981 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 352.5 256.1 37 2 356.5 18 40.5 3 367.0 39 277.6 4 404.7 20 457.2 s 405.8 21 475.8 6 408.0 22 476.1 7a 408.6 23 474.0 8 408.6 24 457.5 9 408.7 25 455.8

. 10 408.2 _ 26 447.9 II 408.8 27 316.6 12 409.0 28 307.6 13 437.2 29 34 451.4 30 15 460.9 -3 16 468.6 INSTRUCTIONS -

On this format. list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77) t 8103180516;

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OPERATING D %TA REPORT DOCKET NO. 50-285 DATE March 10, 1981 COMPLETED BY __T. L. Patterson TELEPilONE (402)536-4413 OPERATING STATUS I. Unit Name: Fort Calhoun Station Unit No. I Note 5

2. Reporting Period: February, 1981 Power level at 65% power

3. Licensed Thennal Power (MWt):

1500 at end of month due to low

4. Nameplate Rating (Gross MWe): 513 grid demand.

5. Design Electrical Rating (Net MWe): 490

6. Maximum Dependable Capacity (Gross MWe): 513

7. Masimum Dependable Capacity (Net MWe): 490

8. 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 MWe): N/A

10. Reasons For Restrictions.lf Any: N/A r

This Month Yr to.Date Cumulative .

I1. Hours In Reporting Period 672.0 1.416.0 65.137.0

12. Number Of Hours Reactor Was Critical 658.0 __L 383.1 51.161.4

13. Reactor Reserve Shutdown Hours 0.0 0.0 1.309.'5 14'. Hours Generator On.Line .

646.1 1,362.3 50.122'.2

15. Unit Reserve e,hutdown Hours 0.0 0.0 ~0.0

16. Gross Thermal Energy Generated (MWH) 835,279.1 1.616,545.3 61.334.785.6 -

17. Gross Electrical Energy Generated (MWH) 278,918.0 540, N8. 0 20,328,779.6

18. Net Electrical energy Generated (MWH) 264,169.T-,_, 509,791.3 19,207,974.2

' 19. Unit Senice Factor 96.1 96.2 76.9

' 20. Unit Asailability Factor 96.1 96.2 76.9

, 21. Unit Capacity Factor (Using MDC Net) 80.2 73.5 64.7 ,

22. Unit Capacity Factor (Using DER Net) 80.2 73.5 64.3

.23. Unit Forced Outage Rate 3.9 3.8 4.1

24. Shutdowns Scheduled Oser Next 6 Months (Type. Date,and Duration of Each):

25. If Shut Down At End Of Report Period.E timated Date of Startup: N/A >

26. Units in Test Status (Prior to Commercial Operation): Forecast Achiesed INITIA L CRITICALITY -

L INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77) ,

UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. ' 50-285 UNIT NAME Fort Calhoun #1 i.

DATE March 10, 1981 COMPLETED BY T. L. Patterson REPORT MONTil Februarv. 1981 TELEPilONE (402)S36-4413

'I "E -

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= r. 5:

~. I _e E ,E4 Licensee 5%, c ., Cause & Corrective No. Date g 3g g jg5 Event u? E.1 Action to

• 5 n0 '

$3 j di oj Report a Prevent Recurrence C

- 81-02 810217 F 25.9 A 3 HH VALV0P Failed actuator caused valve HCV-1101 (feedwatei regulating valve) to close resulting in low steam generator level auto- l matic reactor trip. Actuators on both feedwater regulating valves were replaced.

1 . 2 3 4 F: Forced Reason: Method: Exhibit G. Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee C. Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-O:her (Explain) 01611 E-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explain) Exhibit I - Same Source (9/77) li Other (Explain g

1 Pcfueling Infonrntion i-Fort Calhoun - Unit No. 1 .

i Fcport for the conth ending February 1981 . .

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i

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

Scheduled date for restart folleaing refueling. November 15, 1981

2.  !

3. Will refueling or restrrption of operation thereafter i g require a technical specification change or other No license amend

rent?

a. If anmer is yes, what, in general, will these be?

?

1-4 q .

. b. If answer is no, has the reload fuel design ,

' and coro configuration been revierd by your Plant Safety Review Conmittec to deter-

- mino whether any unreviceed safety questions No are associated with the core reload. i.

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

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

/

5. Inportant licensing considerations associated with refueling, e.g., nca or different fuel design or supplier, unreviewed design or performance analysis '

nothods, significant changes in fuel design, new

. operating procedures.

E i

,6. The number of fuc1 assemblies: a) in the core . 133 assenblies b) in the spent fuel pool- 197

[' c)--spent fucl pool "

- storage capacity- 483 d) planned spent fuel pool "

storage capacity ~ 483

-7. The projected dato of the last refueling that can bc discharged to'the spent fuel pool assunting the present licensed capacity. 1985 s

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k OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 February 1981 Monthly Operations Report I. OPERATIONS

SUMMARY

The Fort Calhoun Station was operated between 65". power to 100% power during February. Fort Calhoun had one unscheduled outage on February 17, 1981, due to a feedvater control problem. The unit was returned to service on February 18, 1981.

The full power stretch operational testing was completed during February and a measurement of the isothemal temperature coefficience was also completed.

All nomal surveillance and operational tests were completed.

No safety valve or PORV challenges occurred.

A. PERFORMANCE CHARACTERISTICS LER Number Deficiency LER 80-033 During power operation, the current loop indicating pressurizer pressure and feeding the thermal margin /

low pressure calculator of the Reactor Protective System and the Safety Injection Actuation circuitry failed lov, placing the SIAS in half trip and tripping one TM/LP channel of the RPS. The RPS "B" channel vould not have tripped on high pressurizer pressure.

The RPS vas placed in two-out-of-three logic by bypassing the TM/LP bistable. Technical Specification 2.15 applies.

LER 81-001 As required by I.E. Bulletin 79-01B, FT-236, charging header flow lacks complete information to qualify it for the harsh radiation service intended. The trans-mitter is used for long term core cooling flow to the auxiliary pressurizer spray. If the transmitter should fail in a post accident situation, charging header pressure, high pressure injection flow, and pump curves can be used to determine flow.

B. CHANGES IN OPERATING METHODS None

Monthly Op; rations Report February 1981 Page Two 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 sumnry of the surveillance tests which results in Operations Incidents and are not reported elsewhere in the report:

Operations Incident Deficienc2 0I-1090 ST-FP-7 Fuel oil analysis for diesel fire pump fuel oil lost prior to analysis being completed.

OI-1091 ST-RPS-11 Test not perfomed on time.

01-1094 ST-CEA-1 Test not performed on time.

OI-1088 ST-DG-2 Instruments found out of tolerance.

OI-1058 Quarterly Fire Drill.

0I-1069 ST-FD-2 Smoke detector out of service.

OI-1063 SI-1A Inboard bearing vibration.

01-1034 ST-SI/CS-1 96-hour signoff.

OI-1067 Fire Detection Zone 7 OI-1068 TAR-2 Point 6 reading erroneously.

OI-952 VA-66 Charcoal Filter.

OI-994 ST-FW-1 96-hour signoff.

D. CHANGES, TESTS AND EXPERIMENTS CARRIED QUT WITHOUT COMMISSION APPROVAL Procedure Description / Safety Analysis Summary SP-VA-80 Hydrogen Purge System Test /Results acceptable.

An unreviewed safety question as defined in 10CFR50.59 did not exist since this procedure only involves a functional test of the hydrogen purge system to verify operability.

Monthly Operations Report February 1981 Page Three D. CHANGES, TESTS AND EXPERIME'iTS CARRIED OUT WITHOUT COMMISSION APPROVAL (Continued)

Procedure Dese iption/ Safety Analysis Su= mary SP-RPS-5 6-26-80, Excore Detector Offset Recalibration -

no adjustment necessary.

SP-RPS-5 10-27-80, Excore Detector Offset Recalibration -

no adjustment necessary.

SP-RPS-5 11-25-80, Excore Detector Offset Recalibration -

no adjustment necessary.

SP-RPS-5 12-29-80, Excore Detector Offset Recalibration -

no adjustment necessary.

SP-RPS-5 2-6-81, Excore Detector Offset Recalibration -

no adjustment accomplished.

Monthly Surveillance accomplished in accordance with Tech. Spec. 3.10. Incore/Fxcore detector recalibration agreement was maintained. This did not constitute an unreviewed safety question as defined in 10CFR50.59, since this surveillance insures that the reactor is operr.ted within bounds of the safety analysis.

SP-FE-5 Spent Fuel Inspection Stand Installation or Removal.

Installed inspection stand in preparation for 1980 Fuel Handling and Inspection.

Procedure provides for installation or removal of fuel inspection equipment for spent fuel. This did not constitute an unreviewed safety question as defined in 10CFR50 59, since the equipment allows compliance with fuel surveillance specifications but is not safety related and has no control function.

SP-RC-2-2 Steam Generator Accident Supports This procedure provided for the checking of the hot and cold settings of the adjustment nuts on the. east-west support rods in the lover steam generator acci-dent support ring prior to tack velding the nuts in place. All nuts were found to be acceptable both hot and cold and vere subsequently tack velded into place.

This did not constitute an unreviewed safety question as defined in 10CFR50.59, since it insured no addi-tional stresses would be placed on the steam generators, because of restrained thermal growth.

Monthly Operations Report February 1981 Page Four D. CHANGES, TESTS AND EXPERIME'ITS CARRIED OUT WITHOUT C0!NISSION APPROVAL (Continued)

Procedure Description / Safety Analysis Summary SP-WDS-lh Spent Resin Disposal This procedure provided for the safe and proper transfer of radioactive spent demineralizer resin from the spent resin storage tanks to shipping casks for eventual disposal. This did not consti-tute an unreviewed safety question as defined in 10CFR50.59, since the resin was packaged for shipping as required by licensed burial sitet for the radio-active resin.

SP-RC-11 Reactor Coolant Pump Assembly This procedure provided for the proper assembly of three :of the four Reactor Coolant Pumps after gasket and case stud replacement. This did not constitute an unreviewed safety question as defined in 10CFR50.59, since it insured proper tensioning of the case studs and proper gasket sealing according to the pump manu-factures' specifications.

SP-RC-MOTOR Reactor Coolant Pump Motor Replacement This procedure provided for the proper installation of three of the four Reactor Coolant Pump motors.

This did not constitute an unreviewed safety question as defined in 10CFR50.59, since it insured proper motor alignment, viring, rotation, and auxiliary system hook-up as per manufacturers' instructions and specifications.

SP-HSS-2 Inspection of Non-Safety Related R'1raulic

Shock Suppressors This procedure provided for the inspection of fourteen non-safety related hydraulic snubbers. This did not constitute an unreviewed safety question as defined in 10CFR50.59, since these are non-safety related components.

E. RESULTS OF LEAK RATE TESTS There were no leak rate tests in February.

Monthly Operations Report February 1981 Page Five F. CHANGES IN PLANT OPERATING STAFF None G. TRAINING Training for February included refresher training for all personnel that access Fort Calhoun Station in Radiation Protection and Security, system training for all crafts and scheduled training for operators.

Operations and staff began the annual simulator training required by the NRC in the last week of February and vill continue through the first week in April, 1981.

H. CHANGES, TESTS AND EXPERDEITS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment No. 55 providing for operation through Cycle 6 with less than 75% of operabic incore detectors.

Amendment No. 56 providing additional assurance for availability of reliable decay heat removal capacity.

) ,

Approved By \. ' 1 1 2i

! Mager% Fort Od1houn Station

Menthly Operations Report February 1981 Page Six II. MAI'I""fiA.' ICE (Significant Safety Related)

M. O. 4 Cate Description Corrective Action 8713 1-26-81 RPS "B" Chancel T "* *P " * "'

COLD drifting 8523 1-10-81 RM-057 Sample Pump not pumping. Replaced vacuum pump. ,

8607 1-15-81 LI-381 SIRWT Level giving Adjusted needle valve and erroneous indication. cleaned out.

8755 2-5-81 LRC-10lY spurious charging pump Replaced electrolytic capacitor starts and stops, and diode.

8554 1-16-81 FH-12 Pre-op test for new feel Performed MP-FH-2.

receipt.

8776 2-2-81 FRC-269Y Hard Controller doesn't Replaced diode and resistor, appear to have any control.