ML20062L386

Monthly Operating Rept for Jul 1982

ML20062L386
Person / Time
Site:	Fort Calhoun
Issue date:	08/10/1982
From:	Short R OMAHA PUBLIC POWER DISTRICT
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ML20062L377	List: ML20062L373 ML20062L386
References
NUDOCS 8208190093
Download: ML20062L386 (12)

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT _ Fort Calhoun Station DATE August 10, 1982 COMPLETED BY R. W. Short TELEPHONE (402)536-4543 MONDf July, 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) i 469.5 37 342.4 2

470.2 ,3 459.3 3 467.1 i, 462.7 4 464.5 20 461.4 5 459.2 21 461.1 6 458.3 22 459.7 7 461.1 23 459.4 8 460.8 24 459.6 9 460.7 25 460.9 to 461.7 26 460.7 ii 461.5 27 459.8 12 460.3 -

28 460.9 33 458.7 29 462.0 i4 457.0 3g 461.4 Is 456.6 3, 461.2 16 ,454.6 INSTRUCTIONS On this format. list the average daily unit power levelin MWe Net for each day in the reporting inonth. Compute to the nearest whole megawatt.

(9/77) 8208190093 820810 PDR ADOCK 05000285 R PDR

OPERATING DATA REPORT DOCKET NO. 50-285 DATE August 10, 1982 COMPLETED BY _R. W. Short TELEP110NE {4021536-4543 OPER A TING STATUS

1. Unit Name: Fort Calhoun Station Notes

2. Reporting Period: 'Y'

3. Licensed Thermal Power (MWt): 1500

4. Nameplate Rating (Gross MWe): 501

5. Design Electrical Rating (Net MWe): 470

6. Maximum Dependable Capacity (Gross MWe): 501

7. Maximum Dependable Capacity (Net MWe): 0

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

None

9. Power Level To Which Restricted. lf Any (Net MWel: N/A

10. Reasons For Restrictions.If Any: ifone This Month Yr..to.Date Cumulative

11. Hours in Reporting Period 744.0 5,087.0 77,568.0

12. Number Of Hours Reactor Was Critical 744.0 5,020.9 61,2b9.9

13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5

14. Hours Generator on.Line 744.0 5,011.8 60,101.8

15. Unit Resene Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1,094,321.9 7,378,242.5 74,080,072.6 17 Gross Electrical Energy Generated IMWH) 357,514.0 2,481,297.9 24,555,243.5

18. Net Electrical Energy Generated (MWH) 340,183.1 2,366,498.3 23,214,366.8

19. Unit Senice Factor 100.0 98.5 77.5

20. Unit Availability Factor 100.0 98.5 77.5

21. Unit Capacity Factor IUsing MDC Net) 95.7 97.3 65.1

22. Unit Capacity Factor IUsing DER Net) 95.7 97.3 64.8

23. Unit Forced Outage Rate 0.0 1.5 37

24. Shutdowns Scheduled Over Next 6 MonthsIType.Date.and Duration of Eacht.

1983 Refueling Outage Scheduled to Commence January 3,1983 for Three Months.

25. If Shut Down At End of Report Period. Estimated Date of Startup: N/A

26. Units In Test Status IPrior io Commercial Operationi: None Forecast Achiesed INITIAL CRITICALITY INITIA L ELECTRICITY COMMERCIAL OPER ATION (9/77)

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DOCKET NO. 50-285 UNIT SHUTDOWNS AND POWER REDUCTIONS Fort Calhoun Station UNIT N AME DATE Auoust 10. 19R2 COMPLETED SY R.'W. Short REPORT MONHf July, 1982 TELEPHONE (402)536-4543 w.

- E c

, .5 ? 3g y .E 5 Licensee E t, $*', Cause & Corrective No. Date g 3g jg& Event p mV n- Action to H 3 ,. $ j;ji g Report a f '8 Prevent Recurrence 6

There were no unit shutdowns during the month of July,1982.

1 2 3 4 F: Forced Reason: Method: Exhibit G -Instructions 1 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 (LL R) File (NURI:G-D Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination F-Adndnistrative 5 G-Operational Error (Explain) Exhibit I- Same Source (9/77) llother (Explain)

Refueling Infonration Fort Calhoun - Unit No. 1 Peport for the nonth ending July 1982 .

1. Scheduled date for next refueling shutdown. January 3, 1983

2. Scheduled date for restart following refueling. April 1, 1983

3. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes

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

A Technical Specification Change

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

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

4. Scheduled date(s) for submitting proposed licensing action and support information. November 1. 1982

5. Imortant licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or perforTnance analysis methods, significant changes in fuel design, new operating procedures.

6. The number of fuel assemblies: a) in the core 133 asserrblies b) in the spent fuel pool 237 c) spent fuel pool storage capacity 483 d) planned spent fuel pool storage capacity 728

7. 'Ihe projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. 199; Prepared by , M Date August 2, 1982 (j 1

CMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 July, 1982 Monthly Operations Report I. OPERATIONS

SUMMARY

Fort Calhoun Station operated at a nominal 100% power for the month of July,1982. One 2h hour power reduction to about 65% occurred on July 17, 1982 for the purpose of cleaning the condensate cooler and the bearing water coolers. The power reduction and cooler cleaning went very well and power was returned to 100% on the evening of July 17, 1982.

During July, the Auxiliary Boiler Fuel Oil Tank and the Diesel Fire Pump Fuel Oil Tank were drained, cleaned and refilled.

Also during July, the QA vault was upgraded to comply with appropri-ate records storage standards. In addition, the Sigma II computer was removed in preparation for the installation of the QSPDS/ERF computer.

No safety valve or PORV challenges occurred.

A. PERFORMANCE CHARACTERISTICS LER Number Deficiency LER-Olh During normal power operation, in the process of switch-in6 component cooling water heat exchangers, the assoc-iated inlet valves HCV h89A, HCV h90A and HCV h92A did not open. The consequence of this event was that only one component cooling water heat exchanger was operation-al. Tech. Spec. 2.3(1)g. requires three of four CCW heat exchangers to be operable which may be modified to two of four CCW heat exchangers operable for not more than 2h hours under Tech. Spec. 2.3(2)c.

LER-015 During the performance of surveillance test ST-ISI-WD-1, F.1, HCV-507A (the gas vent header containment isolation valve) failed to close via the control room switch. The valve was immediately closed by failing the air to the operator. Emergency Procedure EP-25 " Loss of Containment Integrity" was implemented and a Maintenance Order was written to investigate / correct the problem. Throughout the incident, the redundant gas vent header containment isolation valve remained operable and was in the closed position.

B. CHANGES IN OPERATING METHODS NONE

[) Monthly Operations Report July, 1982 Page Two C. RESULO 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 su= mary of the surveillance tests which results in Operations Incidents and are not reported elsewhere in the report:

Operations Incident Deficiency 01-1557 ST-FP-1 FP-1B Failed to run properly D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description SP-BTUGEN-1 Control Room BTU Generation Study for air condi-tioning system requirements.

This procedure did not constitute an unreviewed safety question as defined in 10CFR50 59 This procedure was used to measure and calculate the heat generated from equipment, personnel, and structures in the control room. Approved proce-dures were prepared prior to the start of work.

SP-SS-5 This procedure did not constitute an unreviewed safety question as defined in 10CFR50 59 The procedure involved inspection and disassembly of certain spent fuel assemblies for the purpose of evaluating fuel performance. Potential accidents were enveloped by FSAR Section 1h.18, " Fuel Hand-ling Incidents". Acproved procedures were pre-pared prior to the start of work.

SP-SS-h This procedure did not constitute an unreviewed safety question as defined in 10CFR50.59 The procedure involved inspection and disassembly of certain spent fuel assemblies for the purpose of evaluating fuel performance. Potential accidents were enveloped by FSAR Section lk.18, " Fuel Hand-ling Incidents". Approved procedures were pre-pared prior to the start of work.

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• Monthly Operations Esport gL July, 1982 Page Three D. (CONTINUED)

Procedure Description SP-SS-3 This procedure did not constitute an unreviewed safety question as defined in 10CFR50.59 The procedure involved inspection and disassembly of certain spent fuel assemblies for the purpose of evaluating fuel performance. Potential accidents were enveloped by FSAR Section lh.18, " Fuel Hand-ling Incidents". Approved procedures were pre-pared prior to the start of work.

SP-SS-2 This procedure did not constitute an unreviewed safety question as defined in 10CFR50.59 The procedure involved inspection and disassembly of certain spent fuel assemblies for the purpose of evaluating fuel performance. Potential accidents were enveloped by FSAR Section 1h.18, " Fuel Hand-ling Incidents". Approved procedures were pre-pared prior to the start of work.

SP-SS-1 This procedure did not constitute an unreviewed safety question as defined in 10CFR50.59 The procedure involved inspection and disassembly of certain spent fuel assemblies for the purpose of evaluating fuel performance. Potential accidents were enveloped by FSAR Section lb.18, " Fuel Hand-ling Incidentc". Approved procedures were pre-pared prior to the start o f wo rk .

SP-FE-8 This procedure did not constitute an unreviewed safety question as defined in 10CFR50 59 The procedure involved inspection and disassembly of certain spent fuel assemblies for the purpose of e"aluating fuel performance. Potential accidents were enveloped by FSAR Section 14.18, " Fuel Hand-ling Incidente". Approved procedurec were pre-pared prior to the start of work.

37 FE-9 This procedure did not constitute an unreviewed safety quection as defined in 10CFR50.59 The procedure involved inspection and dicancembly of certain spent fuel assemblies for the purpose of evaluating fuel performance. Potential accidents were enveloped by FSAR Section 1h.18, " Fuel Hand-ling Incidents". Approved procedurec were pre-pared prior to the Start of work.

' Monthly Operations Report July, 1982 Page Four D. (CONTINUED)

Procedure Description SP-FAUD-1 Fuel Assembly Uplift Condition Detection This procedure did not constitute and unreviewed safety question as defined by 10CFR50.59 since it only involved evaluating data from a surveillance test.

DCR 73-19 Insulate Process Radiation Monitor Sampling Lines This modification did not involve an unreviewed safety question as defined by 10CFR50.59 as it only involved adding heat tracing to radiation monitor sample lines to improve the quality of the samples taken.

DCR ThA-92 Gai-tronics in Storeroom This modification did not involve an unreviewed safety question as defined by 10CFR50.59 as it only involved the installation of a gai-tronics communications station to the Storeroom.

DCR ThA-106 PC7-1912 This modification did not involve an unreviewed safety question as defined by 10CFR50.59 as it did not involve a safety related system, replaced pressure control valve in Circulating Water System.

DCR ThA-ll8 NSSS Parameters Permanent Test Rig This modification did not involve an unreviewed safety question as defined by 10CFR50.59 as it only provided a means to monitor USSS parameters.

DCR 75A-19 Waste Filters WD-17A/B This modification did not involve an unreviewed safety question as defined by 10CFR50 59 as it only involved changing the mesh sising of the filters in the waste disposal system.

j ' Monthly Operations Report July, 1982 Page Five D. (CONTINUED)

Procedure Description DCR 75A-25 Variable Overpower Trip This modification did not involve an unreviewed safety question as defined by 10CFR50 59 as it added the variable overpower trip feature to the Heactor Protective System to limit the extent of any reactor power excursions.

DCR 75A kh Instrument Air Isolation Valves This modification did not involve an unreviewed safety question as defined by 10CFR50.59 as it only provided a means to isolate portions of the instrument air system for maintenance.

DCR 75A h5 Redundant Pressure Indication System for HCV-3h8 This modification did not involve an unreviewed safety question as defined by 10CFR50 59 as it only involved added redundant pressure indication to the shutdown cooling isolation valve .

DCR 75A-h8 Shutdown Cooling Sampling System

. This modification did not involve an unreviewed safety question as defined by 10CFR50.59 as it only provided for a sample connection in the shutdown cooling system.

DCR 76-20 Remodel Health Physics Station & Locker Room This modification did not involve an unreviewed safety question as defined by 10CFR50.59 as it did not involve a safety related system.

DCR 76-27 RC Level Indication During Cold Shutdown This modification did not involve an unreviewed safety question as defined by 10CFR50.59 as it provided an alternate method to nonitor water level in the reactor during refueling outages.

• Monthly Operations Report July, 1982 Page Six D. (CONTINUED)

Procedure Description DCR 76-10h Steam Dump & Bypass Valve Position Indication This modification did not involve an unreviewed safety question as defined by 10CFR50.59 as it only added position indication lights in the control room for the steam dump and bypass valves.

DCR 77-91 Backflush Connections on Raw Water Pumps This modification did not involve an unreviewed safety question as defined by 10CFR50.59 as it only provided a means to backflush raw water pumps.

EE/AR 78-6 Heating Coils for Auxiliary Building This modifiction did not involve an unreviewed safety question as defined by 10CFR50.59 as it only added preheater coils for the auxiliary build-ing supply fans.

EEAR 79-18 Auxiliary Building Ventilation System This modification did not involve an unreviewed safety question as defined by 10CFR50 59 as it only provided air conditioning to the Radio Chemistry Counting Room.

EEAR 79 h1 Condensate to Chemical Feed Isolation This modification did not involve an unreviewed safety question as defined by 10CFR50.59 as it did not involve a safety related system.

EEAR 79-lh7 Trip Circuit Bypass for Auxiliary Building This modification did not involve an unreviewed safety question as defined by 10CFR50.59 as it provided a means to bypass the trip circuit on the auxiliary building ventilation fans actuated by smoke detectors, the freesestat, and duct pressure transmitters.

The modification will help ensure the fans can be operated in a post-accident situation.

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• Monthly Operations Report

.Tuly, 1982 -

Page Seven D. (CONTINUED)

Procedure Description EEAR 80-68 Dual Setpoints for RM-061 This modification did not involve an unreviewed safety question as defined by 10CFR50.59 as it provided a means to account for temperature inversion effects on fsM-061, Radiation Monitor on the Auxiliary Building Stack.

EEAR 81-29 Thermal Stress in Piping Between Boric Acid Pumps CH hA/B This modification did not involve an unreviewed safety question as defined by 10CFR50.59 as it was made to reduce stress due to temperature changes in the boric acid piping.

E. RESULTS OF LEAK RATE TESTS Leakage for P.A.L. Door was 4200 seem as measured per ST-CONT-2, F.2.

F. CHANGES IN PLANT OPERATING STAFF Effective August 1, 1982 two positions were approved.

A. W. Richard became Tehenical Supervisor and J. J. Tesarek became the Plant Engineer.

G. TRAINING Training was continued as scheduled for generel employee maintenance, licensed and non-operators, C/RP and Technical personnel.

In addition, several special lectures were given to monitor team members and emergency response personnel.

H. CHANGES, TESTS ANL EXPERIMENTS REQUIRING NUCLEAR REGULATORY C0fGISSION AUTHORIZATION PURSUANT TO 10CFR50. 59 NONE d& r/- .. o'%f . .

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W. G. Gates Plant Manager

g> . Monthly Operations Report July, 1982 Page Eight II. MAINTENANCE (Significant Safety Related)

M. O. # Date Description Corrective Action 15433 6-28-82 HCV-318 relay in breaker is chatter- Realigned contacts, cleaned and ing. adjusted.

15273 6-25-82 Raw Water Pump AC-10A improper read- Repaired per MP-AC-10.

ings of amps.

15173 7-16-82 CH-1A Charging Pump. Packing Coolant Repaired per MP-CH-1-1.

Packing Coolant Tank is filling up when standing in idle.

15497 7-8-82 FP-1 not running properly. Cleaned out clogged line.

15526 7-14-82 RM-050/51 stopped and won't restart. Replaced pump.

15503 7-lb-82 CH-1B charging pump is leaking into Repacked CH-1B and installed Packing Coolant Tank. new discharge valve.