ML20207E898

Monthly Operating Rept for Jul 1988 for Fort Calhoun Unit 1

ML20207E898
Person / Time
Site:	Fort Calhoun
Issue date:	07/31/1988
From:	Blessie W, Morris K OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LIC-88-718, NUDOCS 8808180174
Download: ML20207E898 (8)

Text

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AVERAGE DAILY UNIT POWER LEVEL DOCKET N0. 50-285 ilNIT Fort Ca' houn Station DATE Auaust 8, 1988 COMPLETED BY W. J. Blessia TELEPHONE 402-536-4595 MONTH July 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 421.9 17 411.3 2 424.9 18 412.9 3 423.7 19 413.4 4 420.6 20 415.3 5 418.6 21 417.8 6 414.8 22 417.9 7 414.3 23 415.5 8 414.8 24 413.4 9 416.7 25 412.1 10 417.4 26 411.9 11 417.0 27 412.5 12 416.9 28 413.0 13 416.4 29 412.9 14 414.8 30 412.9 15 410.8 31 411.2 16 410.0 ,

INSTRUCTIONS 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 regawatt.

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OPERATING DATA REPORT DOCKET NO. 50-285 UNIT Fort Calhoun Station ,

DATE Auaust 8. 1988 I COMPLETED BY W. J. Blessie i TELEPHONE 402-536-4595 OPERATING STATUS

1. Unit Name: Fort Calhoun Station Notes

2. Reporting Period: July 1988

3. Licensed Thermal Power (MWt): 1500

4. NameplateRating(GrossMWe):- 502

5. DesignElectricalRating(NetNWe):._,_ 4 78

6. MaximumDependableCapacity(GrossMWe): 502

7. 478

8. MaximumDependableCapacity(NetMWe)(:

If changes occur in Capacity Ratings Items Number 3 Through 7) Since Last Report, Give Reasons: ,

N/A

9. PowerLeveltoWhichRestricted,IfAny(NetMWe): N/A

10. Reasons for Restrictions, If Any:

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744.0 51:,1.0 130.177.0

12. Number of Hours Reactor Was Critical 744,0 51JdL 101.950.8

13. Reactor Reserve Shutdown Hours 0.0 0.0 .,.309.5

14. Hours Generator On-Line 74t.0 511: , .0 10:,.029.8 ~

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. GrossThermalEnergyGenerated(MWH) 1.009.227.6 6.909.383.5 131.L57.008.7

17. GrossElectricalEnergyGenerated(MWH) 325.930.0 2.3L2.034.0 43.284.955.2

18. NetElectricalEnergyGenerated(MWH) - 309.051.1 2.197.649.8- 41.341.732.6

19. Unit Service Factor  :,00.0 100.0 77.6

20. Unit Availability Factor  :,00.0 100.0 77.6 21 Factor (Using MOC Net) 86.9 90.0 68.9

22. UnitCapacityFactor(UsingDERNet) 86.9 90.0 67.1

23. Unit Forced Outage Rate 0.0 0.0 2.9 2 A. . ShutdownsScheduledOverNext6 Months (Type,Date,andDurationofEach):

The 1988 Refuelina Shutdown is tentatively scheduled for September 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

26. UnitsInTestStatus(PriortoCommercialOperation): Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY N/A CO M RCIAL OPERATION

DOCKET NO.50-285 UNITSHUTDOWNS AND POWER REDUCTIONS

• D TE s 988 COMPLETED BYW. J. Blessie REPORT MONTH July 1988 TFIFPHONE(402) 536-4595 e

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Action is ent -en 88-02 880618 5 0 H 4 N/A SD COND On June 18, 1988, power was reduced to 90% because of a poor performing condenser coupled with high river water temperature caused high condenser back pressure. The increase in condenser back pressure, elevated the condenser hot well temperature and caused a re-duction in hydrogen cooling capabil-ities. This reduction in cooling cap-abilities is limiting the electrical output of the gr;nerator. The unit is remaining at 90%.

I 1 2 3 4 Fforced Reneen: Adothod Exteit G - Instructions S- - A4 e FeAweEmpisM 14denuel for Preparation of Data 34debutenanos er Test 24denuel Scresn Entry Sheets for Lloonese C4teemeene 3-Automietic Screen Event Report EER) FBe pluPEG-0181 D4teendetery Resortation 4-Other Emplebit E-Operater TreWne & Ucense Emesnbemalen 6 F-AenWotramwe Enhedt 1 - Sosno Source e-Operamenal Error H-Other IEmplaini

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Refueling Information Fort Calhoun Unit No. 1 Report for the month ending July 1988 .

1. Scheduled date for next refueling shutdown. Seotember 1988

2. Scheduled date for restart following refueling. November 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. Auaust 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 ein "

consolidation

7. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. 1994*

• Full core offload of 133 assemblies lost.

Prepared by _tM AL F Date July 25.1988

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 July 1988 Monthly Operations Report I. OPERATIONS SUMARY Fort Calhoun Station operated at 90% power during the month of July due to generator cooling and condenser efficiency problems. Several cycles of circulating water chlorination were performed in an attempt to reduce mssible condenser tube fouling. The effectiveness of the chlorination las not yet been assessed. NRC examinations were administered for four SR0 upgrade candidates and one R0 candidate on July 26-28, 1988.

Construction continues on the training and warehouse facilities. The NRC conducted an in-service test inspection and a security inspection during July. Also, an INP0 Outage Evaluation Team visited the plant.

A project was initiated to assess potential improvements for the PRC procedure review process. Activities in the maintenance department for the month of July centered around the move of crafts from various remote locations in the station to the new maintenance shop addition. The facility appearance upgrade project focused on the pointing in the lower electrical penetration room, the primary sampling room, and the upper mechanical penetration rooms. Painting began on the turbine building upper level and sandblasting and recoating of the overhead has been completed. Major equipment-related activities included the replacement of the outboard thrust bearing on AC-3C component cooling aump, erection of '

scaffolding in EE-1F diesel generator #1 room, troubles 1ooting and isolation of a test circuit in turbine generator intercept valves IV-1 and IV-2, and general overhaul of the auxiliary steam system to replace and repack valves due to system aging.

During July, the outage projects scheduling team continued preparations .

for the refueling outage. Efforts toward implementation of the chemical control program continued. A new standards verification program was implemented. Preparations continued for asbestos abatement support during the outage.

No safety valves or PORV challenges or failures occurred.

A. PERFORMANCE CHARACTERISTICS None B. CHANGES IN OPERATING METH005 None I

C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None L _ _

Monthly Operations Report July 1988 Page Two D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Descriotion 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 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 (orisdegrading)duetotheintrusionof 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 July 1988:

fLagkaag, Descriptior/ Analysis DCR 76-057 Raw Water Snubbers.

This modification provided for the installation of improved snubbers on the raw water pumps. This modification does not have an adverse effect on the safety analysis.

EEAR FC-87-027 Relocation of Site Electrical Utilities.

This modification provided for the relocation of 13.8 power supplies to tne new buildings under construction. This modification does not have an adverse effect on the safety analysis.

2. RESULTS OF LEAK RATE TESTS None F. CHANGES IN PLANT OPERATING STAFF Effective July 1, OPPD implemented nuclear organizational changes.

These changes were previously transmitted (reference Letter LIC-88-504datedJuly1,1988,fromK.J.MorristoNRC).

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Monthly Operations Report July 1988 Page Three G. TRAINING During the n.onth of July, Training supported efforts in Operations, rechnical, Maintenance Technician and General Employee Training in order to support operator licenses, engineering, national certification of radiation protection technicians, and the upcoming outage. More specifically, five individuals took the NRC exam on July 26-28 (one R0 initial license, two SRO instant licenses, and two SR0upgradelicenses). Technical staff requalification and initial training was also conducted. The first week of the training for the NRRPT(NationalRegistryforRadiationProtectionTechnicians) began in July. In the area of Chemistry training, three new hire Chemistry Technicians passed their final shift exams in July and are now qualified to maintain shift rotations. In the area of Maintenance training, 50 maintenance supervisors and craftsmen have been trained in the conduct of maintenance. In addition, the observation training program has been developed and a draft standing order to implement the conduct of observation was developed.

H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 bmendment No. Description 115 The amendment revises Section 5 of the Technical Specifications to incorporate recent organizational and job title changes and to remove the onsite and offsite organizational charts.

II. MAINTENANCE (SignificantSafetyRelated)

None W b:f' W. Gary Gates 2^

Manager-Fort Calhoun Station b- i - -

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Omaha Public Power District 1623 Herney Omaha Nebraska 68102 2247 402,536 4000 Au ust 12, 1988 LI 718 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station P1-137 Washington, DC 20555

Reference:

Docket No. 50-285 Gentlemen:

SUBJECT:

July Monthly Operating Report Pursuar.t to kehnical Specification Section 5.9.1, and 10 CFR Part 50.4(b)(1),

please find enclosed one copy of the July 1988 Honthly Operating Report for the Fort Calhoun Station Unit No. 1.

Sincerely, A . 4 orris Division Manager Nuclear Operations KJM/wjb Enclosures c: P. H. Harrell - NRC Senior Resideilt inspector NRC Regional Office OfficeofManagement&ProgramAnalysis(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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