ML20149G289

Monthly Operating Rept for Jan 1988

ML20149G289
Person / Time
Site:	Fort Calhoun
Issue date:	01/31/1988
From:	Blessie W OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20149G268	List: ML20149G265 ML20149G289 ML20149G298
References
NUDOCS 8802180214
Download: ML20149G289 (7)

Text

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AVERAGE DAILY UNIT POWER LEVEL DOCKET N0. 50-285 UNIT Fort Calhoun Station DATE f.phruary 9. 1988 COMPLETED BY W. J. 81essie TELEPHONE 402-536-4595 L

MONTH January 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 488.0 17 __. 490.7 2 488.0 18 . 490.5 2 487.9 19 ___ 490.6 4 487.9 20 490.8 5 487.7 21 490.4 6 487.5 22 490.5 7 487.1 23 491.2 8 487.1 24 491.2 9 487.7 25 491.1 10 487.9 26 491.1 11 488.1 27 491.0 12 488.9 28 490.5 13 490.6 29 491.2 14 490.7 30 491.1 15 490.8 31 491.0 16 490.8 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.

8802180214 880212 DR ADOCN0500gg5

OPERATING DATA REPORT DOCKET N0. 50-285 UNIT Fort Calhoun Station DATE February 9. 1988 COMPLETED BY W. J. Blessie TELEPHONE 402-536-4595 OPERATING STATUS

1. Unit Name: Fort Calhoun Station Notes

2. Reporting Period: January 1988

3. Licensed Thermal Power (MWt): 1500

4. Nameplate Rating (Gross MWe): 502

5. Design Electrical Rating (Net MWe): 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 744.0 744.0 125.810.0

12. Number of Hours Reactor Was Critical 744.0 744.0 97.583.8

13. Reactor Reserve Shutdown Hours 0.0 0.0 1.309.5

14. Hours Generator On-Line 744.0 744.0 96.662.8

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1.109.355.4 1.109.355.4 125.656.980.6

17. Gross Electrical Energy Generated (MWH) 381.356.0 381.356.0 41.354.277.2

18. Net Electrical Energy Generated (MWH) _364.311.5 364.311.5 39.508.394.3

19. Unit Service Factor 100.0 100.0 76.8

20. Unit Availability Factor 100.0 100.0 76.8

21. Unit Capacity Factor (Using MDC Net) 102.4 102.4 67.8

22. Unit Capacity Factor Using DER Net) 102.4 102.4 65.9

23. Unit Forced Outage Rate 0.0 0.0 3.1

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

N/A l

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 _

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DOCKET NO.

50-285 UNIT SilUIDOWNS AND POWER REDUCTIONS UNIT N AME Fort Qilhomwud StoLion NDruary 9, DATE COMPLETED itY U I- BleSSie REPORT MONIll T,nn:m. ic)gg TELEPIIONE 402-536-4595 l

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. Date i 3? 4 h [5 25 Event  ? gL Attlun to Psevent Returrente j_

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l There vere no unit shutdoms or re.er reductions during the mnth o' l Januarv 1988.

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l 3 4 I 2 F: Fosted Reason: Method . Exhibit G - Instructions l to: Peeparainni ol' Data S. Scheduled A-Lquipment Failure (E splain) 1 Manual B-Maintenance of Test 2 Manual Scram. Entry Sheets l'or Ixemce ',

C Refuchng 3. Autunutie Sciain. Event Repori ILE R) File INURI G-D Regulatory Restension 4 Other (Explam) 0161i L Opesator Tsaining & 1.nense INammation 5

F-Admimstralise G Oper.stional treus IE mplam ) E stubit I - Same Source 19/77) 11 Ot her ilsplaus)

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a Refueling 'nformation Fort Calhoun - Unit No.1 Report for the month ending December 1987 .

1. Scheduled date for next refueling shutdown. September 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 ansi..er is yes, what, in general, will these be?

Incorporate cycle specific requirements c esulting 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. Jul y 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 fuql 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 hdC Date January 26, 1988

l OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 January 1988 Monthly Operations Report

1. OPERATIONS

SUMMARY

Fort Calhoun Station operated at 100% power throughout January 1988.

Construction continued on the training facility, warehouse and maintenance shop.

NRC inspections were performed on Security, Design Changes, Solid Radioactive Waste and Quality Assurance.

A team was formed to conduct an assessment of 20 key functional areas relating to Fort Calhoun Station. The team is to identify the improvements necessary to achieve the desired standards of excellence in operations at the Fort Calhoun Station.

Presentations were made to 39 small groups on commitment to excellence.

No safety valves or PORV challenges or failures occurred.

A. PERFORMANCE CHARACTERIS!!CS None

8. CHANGES IN OPERATING METHODS None C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL .

t 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 January 1988 Page Two D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (Continued)

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 to be conducted on 38 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.

System Acceptance Committee Packages for January 1988:

_P_a c k aoe Descriotion/ Analysis EEAR FC-86-030 HJTC Heater Overpower Protection.

This modification provided for smaller fuses in the HJTC power supply. This modification does not have an adverse effect on the safety analysis.

l EEAR FC-86-062 Monitor Tank Vacuum Breaker System.

This modification provided for the installation of l a new vent system for the monitor tanks. This modification does not have an adverse effect on the safety analysis.

E. RESULTS OF LEAK RATE TESTS The biannual leak rate test on the containment purge valves was completed on January 18, 1988, per ST-CONT-3. The total leakage for penetrations M 87 and M-88 "as found" and "as left" was 0 secm.

In December of 1987, the purge valve leakage test was performed, and

, M-87 was found with excessive leakage. The M-87 valve operator stop was adjusted and retested per ST-CONT-3. Both M-87 and M 88 were left at 0 secm. The testing frequency of ST-CONT-3 was increased to prove reliability of the containment integrity.

3l The "as left" after "B" and "C" leak rate was 374.2 scem after the December leak rate tests. Since both sets of purge valves tested 0 leakage in January, the total leakage will not change. This leak rate is well below the allowed leakage of .6 La as specified in 10 CFR 50 Appendix J.

Monthly Operations Report January 1988 Page Three F. CHANGES IN PLANT OPERATING STAFF During January, Mr. Delvin R. Trausch was promoted to Supervisor-Operations.

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G. TRAINING During January, Station Training completed training and qualification of two shift technical advisors, began a three month technical staff class for six individuals, continued initial auxiliary operator-nuclear and equipment operator-nuclear training, continued licensed and non-licensed training, and completed training of two initial hot

, license candidates and one upgrade candidate in preparation for the examinations during the week of February 8, 1988. In addition, '

preparations are being made for the requalification examinations f using the process described in the pilot program.

Js s H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 None.

!!. MAINTENANCE (Significant Safety Related)

None

& Z$ y Nako W. Gary Gates Manager-Fort Calhoun Station 1

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