ML20150C181

Monthly Operating Rept for Feb 1988

ML20150C181
Person / Time
Site:	Fort Calhoun
Issue date:	02/29/1988
From:	Andrews R, Blessie W OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LIC-88-186, NUDOCS 8803180056
Download: ML20150C181 (8)

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT Fort Calhoun Station DATE March 15. 1988 COMPLETED BY W. J. Blessie TELEPHONE 402-536-4595 MONTH February 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 490.1 17 330.9 2 490.8 18 331.5 3 490.8 19 331.5 4 491.1 20 330.7 5 490.6 21 331.2 6 490.6 22 331.6 7 491.0 23 332.2 ,

8 490.9 24 333.1 9 490.3 25 332.8 10 491.5 26 333.0 11 489.9 27 333.0 12 447.8 28 332.1 L 13 157.5 29 332.3 14 150.3 30 15 276.0 31 16 332.5

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

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8803180056 880229 [

PDR ADOCK 05000285 R DCD

OPERATING DATA REPORT DOCKET N0. _ 50-285 1 UNIT Fort Calhoun Station i DATE March 14. 1988 l COMPLETED BY W. J. Blessie TELEPHONE 402-536-4595 OPERATING STATUS

1. Unit Name: Fort Calhoun Station Notes

2. Reporting Period: February 1988

3. Licensed Thermal Power (MWt): 1500

4. Nameplate Rating (Gross MWe): 502

5. Design Electrical Rating (Net NWe): 478

6. Maximum Dependable Capacity (Gross MWe): 502

7. Maximum Dependable Capacity (Net MWe): 478

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, If Any:

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 696.0 1440.0 126.506.0

12. Number of Hours Reactor Was Critical 696.0 1440.0 98.279.8

13. Reactor Reserve Shutdown Hours 0.0 0.0 1.309.5

14. Hours Generator On-Line 696.0 1440.0 97.358.8

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) __827.925.1 1 937.280.5 126.484.905.7

17. Gross Electrical Energy Generated (MWH) 280.926.0 662.282.0 41.635.203.2

18. Net Electrical Energy Generated (MWH) 265.879.5 630.191.0 39.774.273.8

19. Unit Service Factor 100.0 100.0 77.0

20. Unit Availability Factor 100.0 100.0 77.0

21. Unit Capacity Factor (Using MDC Net) 79.9 91.6 67.9

22. Unit Capacity Factor (Using DER Net) 79.9 91.6 66.0

23. Unit Forced Outage Rate 0.0 0.0 3.0

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

N/A

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

26. Units In Test Status (Prior to Commercial Operation: Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMMERCIAL OPERATION i

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50-285 -

DOCKET NO.

UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME Fort Calhoun Scotleri DATE mrch M, N February 1988 COMPLETED BY H I BloRRio REPORT MONTil TELEPHONE 402-536-4595

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]3 3 y Litensee P. Cause & Corrective p Action to N. .. Date i 3g 4,4 2s5 Event rn v pL Prevent Recurrente j f, H y3 Report = g d

88-01 880212 S O H 4 N/A EK FAN On February 12, 1988, a power reduc-tion convienced to reoair a nuclear detector well cooling fan in contain-ment. Pomr was held at 35% while re-pairs were made and powr was then returned to 707. on February 15, 1988.

Pomr will remain at 70. for approx-imately seven weeks to extend the fuel bumup window to the desired shutdown refueling date in September.

I 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 Licertsee ',

C Refueling 3 Automatic Scram. Event Repor (LER) Fric (NUREC-D Regulatory Restriction 4-Other (Explain ) 0161)

!? Operator Training & License Examination F- Ad mimst rat n e 5 G-Operational Errur ( Explam n Eshibit I - Same Source (9/77) 11 Ot her ( E xplain )

, Refueling Information Fort Calhoun - Unit No. 1 Report for the month ending February 1988 .

1. Scheduled date for next refueling shutdown. Seotember 1988

2. Scheduled date for restart following refueling. December 1988

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?

Incorporate cycle specific requirements resulting from reload safety analysis,

b. If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee 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. July 1988

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

6. The number of fuel assemblies: a) in the core 133 assemblies b) in the spent fuel pool 393 "

c) spent fuel pool storage capacity 729 "

d) planned spent fuel pool May be increased "

storage capacity via fuel oin "

consolidation

7. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. 1996 Prepared by AM Date_ March 1. 1988

.DMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 February 1988 Monthly Operations Report I. OPERATIONS

SUMMARY

Fort Calhoun Station operated at 100% power until February 12, 1988, when power was reduced to 35% to attain permissible radiological conditions for the repair of a nuclear detector well cooling fan in containment. The

. repairs were completed and power was returned to 70% on February 15.

Power will remain at 70% for approximately seven weeks to extend the fuel burnup window to the desired shutdown date in September.

Construction continues on the training facility, warehouse, and maintenance shop. An NRC inspection was conducted on Health Physics. One new operator was hired in February.

Annual NRC requalification examinations were started in February. These exams are in the new format of having open book written sections on Operating Proficiency and Limits & Controls, a plant walkthrough portion using Job Performance Measures (JPM), and later on a plant simulator section.

Small group meetings continued on commitment to excellence.

No safety valves or PORV challenges or failures occurred.

i A. PERFORMANCE CHARACTERISTICS None l B. CHANGES IN OPERATING METHODS l None C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL l

Procedure Description SP-FAUD-1 Fuel Assembly Uplift Condition Detection.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it only involved the evaluation of data from a sur-veillance test to verify that a fuel assembly uplift condition did not exist.

-Monthly Operations Report February 1988 Page Two D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (Continued)

SP-STROKE-1 In-Service Testing of Air Operated, CQE Valves.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because it was performed as post-maintenance testing on HCV-480 per Maintenance Order 880286 and HCV-484 per Maintenance Order 880288. This special procedure is part of an overall test program to determine valve degradation due to the intrus:on of water into the instrument air system. This testing did not in any way compromise plant safety, but enhanced it by ensuring that the valve undergoing maintenance is fully operable prior to being returned to service.

SP-STR0KE-1 In-Service Testing of Air Operated, CQE Valves.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because it only allowed stroke testing on 37 air operated, CQE valves. The objective of the testing is to determine if valve operability was degraded (or is degrading) due to the intrusion of water into the instrument air system. This testing did not in any way compromise plant safety, but enhanced it by ensuring operability of safety related valves.

SP-RRC-2 Reactivity Computer Setup.

This procedure did not constitute an urreviewed safety question as defined by 10CFR50.59 because the setup of the reactivity computer and placing the reactor critical are normal activities that follow each refueling outage (procedure conducted 6/87).

E. RESULTS OF LEAK RATE TESTS None F. CHANGES IN PLANT OPERATING STAFF During February, Mr. A. Scott Pallas joined the operating staff as a Helper.

' ' Monthly Operations Report February 1988 Page Three G. TRAINING During February, Station Training continued initial auxiliary operator-nuclear and equipment operator-nuclear training, continued technical staff training, and continued licensed and non-licensed training. In addition, assistance was given to the NRC in the preparation of the pilot licensed operator requalification examination.

H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 None II. MAINTENANCE (Significant Safety Related)

Repair work was done on VA-12A, Nuclear Detector Well Cooling Unit Fan to replace in-board and out-board bearings. Although VA-12A is not safety related equipment, it did require a power reduction to allow access for repairs.

T-W. Gary Gates Manager-Fort Calhoun Station

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Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 2247 l 402/536 4000 ,

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March 15, 1988 i LIC-88-186 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

Docket No. 50-285 Gentlemen:

SUBJECT:

February Monthly Operating Report Pursuant to Technical Specification Section 5.9.1, and 10 CFR Part 50.4(b)(1),

please find enclosed, one copy of the February 1988 Monthly Operating Report for the Fort Calhoun Station Unit No. 1.

Sincere ,

$ N R. L. Andrews Division Manager Nuclear Production RLA/me Enclosures c: NRC Regional Office Office of Management & Program Analysis (2)

R. M. Caruso - Combustion Engineering R. J. Simon - Westinghouse Nuclear Safety Analysis Center INP0 Records Center American Nuclear Insurers NRC File (FCS) t l

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