ML20151D686

Monthly Operating Rept for June 1988 for Fort Calhoun Station

ML20151D686
Person / Time
Site:	Fort Calhoun
Issue date:	06/30/1988
From:	Blessie W, Morris K OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LIC-88-589, NUDOCS 8807250202
Download: ML20151D686 (8)

Text

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9 AVERAGE DAILY UNIT POWER LEVEL i

DOCKET NO. 50-285 UNIT Fort _,Calhoun Station DATE Jul; 8. 1988 COMPLETED BY W. J. Blessie TELEPHONE 402-536-4595 MONTH June 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-het) (MWe-Net)  !

1 470.7 17 465.8 2 470.0 __ 18 465.0 3 468.1 19 458.1 4 466.4 20 450.5 5_ 465.8 21 436.3 6 465.3 22 419.4 7 465.7 23 411.8 8 465.5 24 412.7 9 466.4 25 413.9 10 -467.0 26 416.0 11 469.4 27 415.7 .. ___

12 470.7 28 416.9 13 469.0 29 416.6 14 466.6 30 418.9 15 464.1 31 16 463.6 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.

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OPERATING DATA REPORT 1

DOCKET NO. 50-285 UNIT Fort Calhoun Station

, DATE JulvEL_19_88 COMPLETED BY W. J. Blessie TELEPHONE 4_Q2-536-4595 OPERATING STATUS

1. Unit Name: Fort Calhoun Station Notes

2. Reporting Period: June 1988

3. Licensed Thermal Power (MWt): 1500

4. NameplateRating(GrossMWe): 502

5. DesignElectricalRating(NetMWe): 478

6. MaximumDependableCapacity(GrossMWe): 502

7. 478

8. MaximumDependableCapacity(NetMWe)(:

If changes occur in Capacity Ratings ItemsNumber3Through7)SinceLastRepor G(ve Reasons:

N/A Q. 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 720.0 4367.0 129.433.0

12. Number of Hours Reactnr Was Critical 720.0 4367.0 101.206.8

13. Reactor Reserve Shutdown Hours 0.0, . 0.0 1.309.5

14. Hours Generator On-Lino 720.0 4367.0 100.285.8

15. Unit Reserve Shutdown Hours 0.0 0.0- 0.0

16. GrossThermalEnergyGenerated(MWH) 1.041.667.8 _5.900.155.9 130.447.781.1

17. GrossElectricalEnergyGenerated(MWH) 340.322.0 1.986.104.0 42.959.025.2

18. NetElectricalEnergyGenerated(MWH) 323.802.8 1.888.598.7 41.032.681.5

19. Unit Service Factor 100.0 100.0 77.5

20. Unit Availability Factor 100.0 100.0 77.5 -

21 Factor (UsingMDCNet) 94.1 90.5 68.8

22. UnitCapacityFactor(UsingDERNet) 94.1 90.5 66.9

23. Unit Forced Outage Rate 0.0 0.0 3.0

24. ShutdownsScheduledOverNext6 Months (Type,Date,andDurationofEach):

The 1988 Refuelina Shutdown is tentativelv schedyled 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. 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 UNITSHUTDOWNS AND POWER REDUCTIONS D J 8 COMPLETED BY W. J. Blessie TELEPHONE (402) 536-4595 -

REPORTMOffrH June 1968 I

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No. Date i>.

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• o le fm ucensee Event 3 l'

• cause a corrective, Action to 5E m 3 g Reporte e0 0 Prevent Recurrence 8

88-02 880618 S 0 H 4 N/A SD CONN 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 Nack pressure, elevated the condenser hot well temperature and caused a reduc-tion in hydrogen cooling capabilities.

TP.is reduction in cooling capabilities is limiting the electrical output of the generator. Unit remained at 90%

for the duration of the report period.

1 2 3 4 F-Forced Reasort Method- Exhbit G - Instructions S-Scheduled A-Equipment Fabure (Explair4 1-Manual for Preparation of Data B-Mahtenance or To-t 2-Manual Scram Entry Sheets for Ucensee C-Refusing 3-Automatic Scram Event Report (LER) FIe (NUEG-0181)

D-Regulatory Restriction 4-Other (Explair$

E-Operator Training a Ucense Examination 6 F-Administrative Exhbit 1 - Same Source G-Operational Error H-Other (Explah)

(9 m )

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' Refueling Information Fort Calhoun - Unit No.1 Report for the month ending June 1988 .-

1. Scheduled date for next refueling shutdown ~ . Sectember 1988

2. Scheduled date for restart following refueling. November 1948 -

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 relead,

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 spen. fuel poci 393 "

c) spent fuel pool storage c.pacity 729 "

d) planned rpent 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. 1994*

• Fhil core offload of 133 assemblies lost.

Prepared by _. R M Date June 29. 1988 t

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

SUMMARY

Fort Calhoun Station operated at 100% power until high river temperature, condenser efficiency, and generator cooling problems forced reduction in

. power to 90% beginning June 18, 1988. Forty-four new fuel bundles were received and inspected for use during the next refueling outage. NRC inspections were performed in the areas of confirmatory measures, correc-tive actions program, and emergency preparedness. The annual emergency drill was held on June 8, and the annual emergency exercise was held on June 22. Construction continues on the maintenance shop, warehouse, and training facility. No safety valves or PORY 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-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 39 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.

Month'ly Operations' Report-

' June 1988 Page Two D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL-(Continued)

Procedure' OescriDtion SP-SFP-FILTER-1 Spent Fuel Pool Filter Element Removal from Spent Fuel-Pool.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because it provided a safe and orderly method for the one-time job-of a filter changeout on the underwater filter unit in the-spent fuel pool. A safety analysis was performed and results showed the job would pose no unreviewed safety threat.

An ALARA package was written and a prejob briefing was completed with support personnel attending.

The job was completed with no unexpected incidents. Although manrem for the job has not been totalled, an average dose was approximately 25 mr, much less than expected.

System Acceptance Committee Packages for June 1988:

Packaae DescriDtion/ Analysis EEAR FC-85-179 Replacement of HCV-247 and HCV-248.

This modification provided for the replacement of existing Valcor solenoid valves with non-Target Rock solenoid valves. This modification does not haYe an adverse effect on the safety analysis.

EEAR FC-86-023 Discharge Tunnel Temperature Probe.

This modifica!. ion provided for the reinstallation of a temperature probe in the discharge tunnel.

The new installation will allow for easier removal for repairs and will prevent freezeout during cold temperatures. This temperature probe provides monitoring of discharge water temperature from the plant. This modification does not have an adverse effect on the safety analysis.

EEAR FC-87-064 Phase III Security Bairiers. ~

i T'lis modification is considered safeguards information and does not have at adverse effect on l the safety analysis.

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j Month'ly Operations Report L June 1988 Page Three E. RESULTS OF LEAK RATE TESTS A leak rate test on the Personnel Air Lock (PAL) was completed on June 3, 1988, per ST-CONT-3, F.2. The "as found" and "as left" leak rates for.the PAL were both 0 sccm.

The "as left" "B" and "C" leak rate was 374.2 sccm following the April 19, 1988, leak rate test. Since the PAL tested zero leakage during the June test, the total leakage remains unchanged. This leak rate is well below the allowed leakage of 0.6 La (62,951 sccm) as specified-in 10CFR50 Appendix J F. CHANGES IN PLANT OPERATING STAFF Mr. Ron Arnold began his employment with OPPD in the Helper classification of the Operations department.

G. TRAINING During June, Conduct of Maintenance training and training for Central Maintenance personnel for the upcoming refueling outage were initiated. Training for five Senior Reactor Operator candidates was completed. An Auxiliary Operator-Nuclear training program was initiated. The simulator portion of the NRC pilot requalification examination was completed for eight licensed operators.

H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment No. Description 114 The amendment updates the reactor coolant system pressure-temperature limits for heatup and cooldown to reflect the new fluence prediction developed and the more limiting chemistry factor associated with the 3-410 weld.

II. MAINTENANCE (Significant Safety Related)

None

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W. Gary Gates Manager-Fort Calhoun Station

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1 Omaha Public Power District 1623 Harnet] Omaha Nebraska 68102 2247 402/536-4000 July 14, 1988 LIC-88-589 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station P1-137 Washington, DC 20555

Reference:

Docket No. 50-285 Gentlemen:

SUBJECT:

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

Sincerely, l lM. f orris Division Manager Nuclear Operations KJM/wjb Enclosures c: P. H. Harrell - NRC Senior Resident Inspector NRC Regional Office Office of Management & Program Analysis (2)

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

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