ML20237B645

Monthly Operating Rept for Nov 1987

ML20237B645
Person / Time
Site:	Fort Calhoun
Issue date:	11/30/1987
From:	Andrews R, Blessie W OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LIC-87-853, NUDOCS 8712170032
Download: ML20237B645 (10)

Text

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L , :. . i AVERAGE DAILY I? NIT POWER LEVEL

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,. DOCKET NO. 50-285 l

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UNIT Fort Calhoun Station L DATE nocomhpr 10- 1987 COMPLETED BY W. J. Blessie TELEPHONE 402-536-4595 yogn; November, 1987 DAY- AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

. (MWe-Net) (MWe-Net) 490.5 17 489.7 2 :490.3' 18 489.9 3

490.3 ,9 489.7 4 490.2 20 489.6

.5 490.0 7, 489.8 6

490.1 490.0 7 490.3- 23 490.2 8 490.0 -24 490.5 9- 489.9 25 490.3 to 489.6 26 490.5 3i 489.5 g 490.7 12 489.5 2g 490.6 13 489.2 29 490.7 34 489.3 490.0 30 15 489.5 3j 16 489.4 INSTRUCTIONS On this format. list the average daily unit power levelin MWe. Net for each day in the reportmg month. Compute to the nearest whole megawatt.

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OPERATING DATA REPORT DOCKET NO. 50-285 DATE Oecember 10, 1987 COMPLETED BY W. J. Blessie TELEPilONE 402-536-4595 OPERATING STATUS

1. Unit Name: Fort Calhoun Station Note 5

2. Reporting Period: Nnvomhnr 10R7

. 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):

470

8. If Changes Occur in Capacity Ratings titems Number 3 Through 7) Since Last Report.Give Reasons:

M/A

9. Power LeSel To which Restricted,if Any (Net MWe): N/A

10. Reasons For Restrictions.lf Any:

This Month Yr..to-Dat e Cumulative i1. Hours in Reporting Period.

720.0 8,016.0 124,322.0

12. Number Of Hours Reactor Was Critical 720.0 5,864.3 96,095.8-

13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5

14. Hours Generator On.Line 720.0 5,787.7 95,174.8

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1,0?7,041.7 8,385,548.8 123,436,050.7

17. Gross Electrical Energy Generated (MWH) 368,776 J _ ,, 2,826.617.0 40,593,343.2

18. Net Electrical Energy Generated (MWH) 352,792.0 2,697.42J.8 38,780,889.7-

' 19. Unit Service Factor 100.0 72.2 76.6

20. Unit Availability Factor 100.0 72.2 76.6

21. Unit Capacity Factor (Usiag MDC Net) 102.5 70.4 67.4

22. Unit Capacity Factor (Using DER Net) 102.5 70.4 65.5

23. Unit Forced Outage Rate 0.0 0.0 ,

3.1

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

None

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

26. Units in Test Status (Prior to Commercial Operation): Forecast Achiesed INITIA L CRITICA LITY INITI A L ELECTRICITY gjg COMMERCIA L OPER ATION (9/77)

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Refueling Information Fort Calhoun - Unit No. 1 Report for the month ending October 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 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 b

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Date November 28. 1987

l-OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 November, 1987 Monthly Operations Report I. OPERATIONS

SUMMARY

Fort Calhoun_ Station operated at 100% power throughout November,1987.

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

NRC audits were performed on Security and Emergency Preparedness including close out of old items. Enforcement conferences were held on the subject of water-in the Instrument Air System.

No safety valves or PORV challenges or failures occurred.

A. PERFORMANCE CHARACTERISTICS None B. CHANGES IN OPERATING METHODS None C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description SP-VA-80 Hydrogen Purge System Test.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because i it only involved the verification of operability of the hydrogen purge system.

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- .

i veillance test to verify that a fuel assembly uplift condition did not exist.

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Monthly Operations Report l November, 1987 Page.Two D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (Continued)

Procedure Description SP-EEQ-1 EEQ Associated Equipment Identification Check.

This procedure did not constitute an unreviewed safety question because the procedure is simply an inventory list of qualified equipment and indica-tions located on various panels and control boards  ;

in the plant. No plant operations or evolutions l are involved. '

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

This procedure did not constitute an unreviewed safety question because it only allowed stroke testing to be conducted on 38 air operated, CQE valves. The objective of the testing is to deter-mine 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 November, 1987:

Packaae Description / Analysis EEAR FC-81-121 Revised Screen Wash Seal Water Piping.

This modification provided for replacement of all the carbon steel screen wash seal water piping and valves with stainless steel components. This rodi-fication does not have an adverse effect on tha '

safety analysis. '

EEAR FC-82-110B Pressurizer Spray System Thermal Fatigue - Part 2.

This modification provided for the installation of ceramic RTD on pressurizer spray tail pipe to moni-tor temperature for metal fatigue. This modifica-l tion does not have an adverse effect on the safety

( analysis.

I

Monthly Operations Report November, 1987

-Page Three D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (Continued)

System Acceptance Committee Packages for November, 1987: (Continued)

Packaae Description / Analysis EEAR FC-83-099 Microwave Detector Relocation.

This modification provided for relocation of microwave detectors in two zones, plus replacement of microwave heads with those of a different model number in four zones. This modification does not have an adverse effect on the safety analysis.

EEAR FC-84-196 VA-43 Heating Coil Failures.

This modification provided for rerouting of the condensate drain line from the VA-43A/B auxiliary building controlled area air supply steam coils.

This involves lowering of the drain piping to enhance gravity drainage of condensate. This modification does not have an adverse effect on the safety analysis.

EEAR FC-85-038A/B Vital Area Expansion - Control Room.

This modification provided for the addition of three bullet resistant doors and one card reader in preparation to move the vital area to allow for construction. This modification does not have an adverse effect on the safety analysis.

EEAR FC-85-092A Water Plant Control Room Expansion - Civil .

This modification provided for increased space in the water treatment plant lab. This modification '

does not have an adverse effect on the safety analysis.

EEAR FC-86-081 Trailer Relocation.

This modification provided for relocation of the GSE and QA trailers outside the protected area.

Power feeds were also provided to these trailers, and some minor changes were made to power feeds for other trailers on the north side of the plant. This modification does not have an adverse effect on the safety analysis.

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Monthly'0perations Report..

November, 1987

.Page.Four D; CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION

' APPROVAL (Continued)

System Acceptance Committee Packages for November, 1987: (Continued)

Packaae Description / Analysis EEAR FC-87-004 . Intake Building Lighting.

This modification provided for installation of additional flood lights on the roof of the intake structure to achieve mini.num illumination levels.

This modification does not have an adverse effect on the safety analysis.

EEAR FC-87-033A Temporary Rearrangement to Accommodate Security Upgrades.

This modification provided for the relocation of the small warehouse to accommodate security upgrades. This modification does not have an adverse effect on the safety analysis.

EEAR FC-87-047 Control Room HVAC Control Circuit. l This modification provided for replacement of pneumatic controls with electrically actuated relays for control room HVAC. This modification does not have an adverse effect on the safety analysis.

E. RESULTS OF LEAK RATE TESTS None F. CHANGES IN PLANT OPERATING STAFF ,

l During November, a Licensed Senior Operator (Terry M. Reisdorff) was l promoted to Shift Supervisor. Also, Mr. Fred Klauzer and Mr. Harold l Barnett were promoted from Auxiliary Operator-Nuclear to Equipment Operator-Nuclear-Turbine.

G. TRAINING l During November, Station Training started auxiliary operator-nuclear training, started equipment operator-nuclear auxiliary building training and completed training and qualification of two shift technical advisors.

Monthly Operations Report November, 1987 Page Five H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 None.

II. MAINTENANCE (Significant Safety Related)

None M M W. Gary Gates Manager-Fort Calhoun Station i

l

Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 402/536-4000 December 14, 1987 LIC-87-853 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

Docket No. 50-285 Gentlemen:

SUBJECT:

November 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 November 1987 Monthly Operating Report ,

for the Fort Calhoun Station Unit No. 1. I Sincerely, R .2 $m - d . /vu 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 l l R. J. Simon - Westinghouse i Nuclear Safety Analysis Center INP0 Records Center American Nuclear Insurers NRC File (FCS)

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