ML20151G793

Monthly Operating Rept for Mar 1988

ML20151G793
Person / Time
Site:	Fort Calhoun
Issue date:	03/31/1988
From:	Andrews R, Blessie W OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LIC-88-269, NUDOCS 8804200142
Download: ML20151G793 (9)

Text

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AVERAGE DAll.Y UNIT POWER LEVEL

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DOCKET NO.

50-285 UNIT Fort Calhoun Station DATE April 12. 1988 COMPLETED BY W. J. Blessie TELEPHONE 402-536-4595 MONTH March 1988 UAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 332.4 17 330.8 2

332.1 18 331.2 3

332.3 19 331.0 4

Jgja8 20 330.4_ _

5 332.6 21 329.9 6

333.0 22 221 8 7

332.9 23 329.1 8

332.3 24 329.0 9

331.8 25 330.0 10 3312fL__

26 330.4 11 331.1 27 330.3 12 331.2 28 330.4 13 331.9 29 330.5 14 332.0 30 330.9 15 331.9 31 331.2 16 330.2 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 megawstt.

NN b

8804200142 880331 PDR ACOCK 05000285 R

DCD

OPERATING DATA REPORT DOCKET N0.

50-285 UNIT Fort Calhoun Station DATE April 12. 1988 COMPLETED BY W. J. Blessie TELEPHONE 402-536-4595 OPERATING STATUS 1.

Unit Name:

Fort Calhoun Station Notes 2.

Reporting Period: March 1988 3.

Licensed Thermal Power (MWt):

1500 4.

Ni.meplate 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 Ruporting Period 744.0 2184.0 127.250.0

12. Number of Hours Reactor Was Critical 744.0 2184.0 99.023.8 13.

Reactor Reserve Shutdown Hours 0.0 0.0 1.309.5 14.

Hours Generator On-Line 744.0 2184.0 98.102.8 15.

Unit Reserve Shutdown Hours 0.0

0. 0 -

0.0 16.

Gross Thermal Energy Generated (MWH) 782.732.2 2.720.012.7 127.267.637.9 17.

Gross Electrical Energy Generated (MWH) _ZsL560.0 924.842.0 41.897.763.2

18. Net Electrical Energy Generated (HWH) 246.382.8 876.573.8 40.020.656.6 19.

Unit Service Factor 100.0 100.0 77.1

20. Unit Availability Factor 100.0 100.0 77.1

21. Unit Capacity Factor (Using MDC Net) 69.3 84.0 67.9

22. Unit Capacity Factor (Using DER Net) 69.3_

84.0 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):

The 1988 Refuelina Shutdown is tentatively scheduled for Seotember 2.1988, with startuo tentatively scheduled for November 18. 1988.

-25.

If Shut Down at End of Report Period, Estimated Date of Startup:

N/A l

26. Units In Test Status (Prior to Commercial Operation:

Forcast Achieved INITIAL CRITICALITY l

INITIAL ELECTRICITY N/A l

COMMERCIAL OPERATION l

l

DOCKET NO. 50-265 UNIT SHUIDOWNS AND POWER REDUCTIONS UNIT NAME Fort Calhoun Station DATE Aoril 17_ 1gnR ~

COMPLETED BY W. J. Blessie REPORT MONTil fluch 1988 TELEPHONE 40?-R W 4595 a

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Cause & Corrective

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3 j $2 Action to h

Date i

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4 jj5 Event p

p' Report :

mV Psevent Recurrente y:

5 5 5 =g e-oo 88-01 880212 S

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4 t</A BK Fart On February 12, 1988, a power reduc-tion commenced to repair a nuclear detector well cooling fan in contain-ment.

Power was hekd at 35% while repairs were made and power was then returned to 70% on February 15,1988.

Power will renain at 70% for approx-inately seven weeks to extend the fuel burnup window to the desired shutdown date in September 1988.

I 2

3 4

f ForscJ Reason:

Method.

Exlubit G - Instructions S. Scheduled A-Equipment Failure (Esplain)

I Manual for Preparation of Data B Maintenance oiTest 2 Manual Scram.

Entr> Sheets for Licensee C-Refueling 3 Automatic Scram.

Event Report t LERI File tNUREG-D-Regulatory Restration 4 Other (Explain) 0161i E Operator Training & Ucense Examina mn F Admmistratswe 5

Estubit I - Same Source G-Operational Eeror iExplain t (9/77)

II Other (E xplaini

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Refueling Information Fort Calhoun - Unit No. 1 Report for the month ending March 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 CJ M Date March 25. 1988

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 March 1988 Monthly Operations Report I.

OPERATIONS SUtt!ARY Fort Calhoun Station operated at 70% power throughout March 1988 to conserve core reactivity in order to maintain 100% power through the summer and still attain the scheduled September shutdown for refueling.

Construction continued on the new training facility, warehouse and

'nainte'iance shop.

An MC inspection was performed on the surveillance test program. A SSOMI team inspected modification package preparation. A training exit was held after administration of NRC license requalification exams.

Two new R0 licenses and a SR0 upgrade license were effective March 14, 1988.

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 INSFECTIONS None D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description t

l l

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

l This procedure did not constitute an unreviewed l

safety question as defined by 10CFR50.59 because it only allowed stroke testing on HCV-805C as post-maintenance testing. The objective of the testing is to verify valve operability following blowdown of valve internals to remove moisture per m0 880745.

This testing did not in any way compromise plant safety, but enhances it by ensuring operability of HCV-805C.

Monthly Operations Report March 1988 Page Two D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT C0f911SSION APPROVAL (Continued)

SP-CTPC-1 Core Thermal Power Calculation - NSSS Calorimetric.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because this procedure is a hand calculation to check the validity of the calculations performed by the plant computer. The results of this check showed that the plant computer was performing as designed in performing the calorimetric power calculation.

System Acceptance Committee Packages for March 1988:

Packaoe Description / Analysis EEAR FC-81-092 Emergency Exits.

This modification provided for the installation of stairs and a masonary block structure between Room 20 and Room 57, and relocated wiring, conduit and halon piping as required.

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

EEAR FC-85-121 Install Eye Wash / Safety Shower - Water Plant &

Turbine Building.

This modification provided for three new eye wash stations and two new safety showers in the turbine building and water plant.

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

EEAR FC-85-195 Installation of New Environmental Air Sampler.

This modification provided for the installation of the environmental air sampler RM-038 at the Blair l

OPPD Office.

This modification does not have an l

adverse effect on the safety analysis.

EEAR FC-87-013 Alert Notification System.

i This modification provided for an upgrade of the Fort Calhoun Station siren system (3 new siren sites).

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

l N

? Monthly Operations Report harch 1988 Page Three D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT C0ffilSSION APPROVAL (Continued)

System Acceptance Committee Packages for March 1988:

Packaoe Description / Analysis EEAR FC-87-024 HCV-385 and HCV-386 Air Accumulators.

This modification provided for separate air accumulators for valves HCV-385 and HCV-386.

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

E.

RESULTS OF LEAX RATE TESTS None F.

CHANGES IN PLANT OPERATING STAFF During March, Dennis Bonsall was promoted to Licensed Senior Operator, Tony Hargan was promoted to Licensed Operator and Gene Creamer was promoted to Licensed Operator.

G.

TRAINING During March, the Ecuipment Operator-Nuclear Course was completed by five individuals anc the Technical Staff Course was completed by seven individuals. The licensed operator annual requalification examination was administered by OPPD to the majority of licensed operators. The NRC administered the licensed operator requalifica-tion examination to eight individuals as part of the requalification examination "Pilot" process. Annual simulator training was begun in l

licensed operator requalification training.

Maintenance, Chemistry, Health Physics and General Employee Training continusd. The Health Physics training is being scheduled to support l

recent violation responses in this area.

H.

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

-,,,. ~ -.,, _, _ _ _ _ _ _ _. _ _ _,. _ _. _.

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i Monthly Operations Report

March 1988 Page Four II. MAINTENANCE (Significant Safety Related)

None

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W. Gary Gatei Manager-Fort Calhoun Station t

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Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 2247 402/536 4000 April 13, 1988 LIC-88-269 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

Docket No. 50-285 Gentlemen:

SUBJECT:

March 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 March 1988 Monthly Operating Report for the Fort Calhoun Station Unit No. 1.

Sincerely,

$ [$)tdwW 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)

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