ML20211P697

Monthly Operating Rept for Nov 1986

ML20211P697
Person / Time
Site:	Fort Calhoun
Issue date:	11/30/1986
From:	Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	Taylor J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-86-666, NUDOCS 8612190122
Download: ML20211P697 (9)

Text

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-285 Fort Calhoun Station

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UNIT DATE December 8, 1986 T. P. Matthews COMPLETED BY TELEPilONE 402-536-4733 l

MONDI Novpmher. 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)

(Mwe. Net) 486.2 17 487.0 488.2 2

486.5 is 3

486.9 489.7 i9 487.2 489.6 4

2n 5

487.0 489.5 21 486.2 6

22 489.7 7

23 489.5 8

485.9 24 489.1 486.6 9

25 489.0 10 487.2 488.9 26 487.1 11 27 489.1 487.2 488.6 12 28 487 7 488.7 13 29 I

i4 487.9 488.5 30 487.8 15 3,

487.3 16 INSTRUCTIONS On this format. list the average daily unit power level in MWe Net for each day in the reporting :nonth. Coinpute to the nearest whole megawatt.

(9/77) 8612190122 861130 t

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OPERATING DATA REPORT DOCKET NO.

50-285 DATE Oecember 8, 1986 COMPLETED BY T. P. Matthews TELEPilONE 402-536-4733 OPERATING STATUS N tes

1. Unit Name:

Fny t ralhnnn Rtatinn

2. Reporting Period:

November 1986

3. Licensed Thermal Power (MWt):

1Rnn

4. Nameplate Rating (Gross MWe):

607 S. Design Electrical Rating (Net MWe):

478

6. Maximum Dependable Capacity (Gross MWe):

502 478

7. Maximum Dependable Capacity (Net MWe):

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.lf Any (Net MWel:

N/A None

10. Reasons For Restrictions.lf Any:

This Month Yr.-to Date Cumulative

11. Hours In Reporting Period 720.0 8.016.0 115,562.0

12. Number Of Hours Reactor Was Critical 720.0 7,741.3 89,487.5

13. Reactor Reserve Shutdown llours 0.0 0.0 1,309.5 720.0 7,520.2 88,643.1

14. Hours Generator On-Line 0.0 0.0 0.0

15. Unit Reserve Shutdown llours

16. Gross Thermal Energy Generated (MWil) l.a.074. 493. 4 in;22n.742.6 113.971.787.2

17. Gross Electrical Energy Generated (MWH) 166 R40.0 3.413.783.2 37.398.352.2

18. Net Electrical Energy Generated (MWH) 351.243.1 3.253.264.6 35,731,158.0

19. Unit Service Factor 100.0 93.8 76.7

20. Unit Availability Factor 100.0 93.8 76.7 102.1 84.9 66.9

21. Unit Capacity Factor (Using MDC Net) 102.1 84.9 64.9

22. Unit Capacity Factor (Using DER Net) 0.0 1.4 3.3

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months (Type.Date,and Duration of Each1:

The 1987 Refueling Shutdown is tentatively scheduled for February 28,1987, with startup te'ntatively scheduled for May 7, 1987.

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

N/A

26. Units in Test Status IPrior to Com.nercial Operation):

Forecast Achiesed INITIA L CRITICALITY INITIAL ELECTRICITY N/A COMMERCIAL OPER ATION (4/77i

UNITSHUTDOWNS AND POWER REDUC 110NS DOCKET NO. 50-285 UNIT NAME Fort Calhouri Station DATE December 8. 1986 REPORT MONTH November, 1986 COMPLETED BY T. P. Ma t thews TELEPHONE 402-536-4733

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5, E "h

• Y5 Licensee h

{g Cause & Corrective No.

Date g

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2s5 Event g?

g3 Action to Ji i =g Report a mV O

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o Prevent Recurrence e

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There were no unit shutdowns or power reductions during the month of November, 1986.

l 2

3 4

s F: Forced Reason:

Method:

Exhibit G. Instructions S: Scheduled A Equipment Failure (Explain) 1 -Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3 Automatic Scram.

Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

(

E Operator Training & License Examination F Administrative 5

G-Operational Error (Explain)

Exhibit I - Same Source 19/77) ll-01her ( E xplain )

)

Refueling Information Fort Calhoun - Unit No.1 Report for the month ending November 1986 1.

Scheduled date for next refueling shutdown.

March. 1987 2.

Scheduled date for restart following refueling.

May, 1987 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?

Fuel supplier change from ENC to CE and possible Technical Specification change.

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.

February, 1987 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.

New fuel supplier (Combustion Engineering) but the new fuel will be essentially the same as that supplied by Combustion Engineering for Cycle 5.

6.

The number of fuel assemblies: a) in the core 133 assemblies b) in the spent fuel pool 349 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 M Date December 4. 1986

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 November, 1986 Monthly Operations Report I.

OPERATIONS

SUMMARY

The Fort Calhoun Station operated at 100% power throughout November,1986.

The NRC was onsite performing audits of the Radiological Emergency Response Plan and of Plant Security. Work was started on the control room ventilation system to correct deficiencies found during an October NRC inspection.

Fire pump FP-1B was replaced.

Condensate pump FW-2A and heater drain pump FW-5C had seals replaced.

Intake structure crosstie between B and C cells was repaired permitting repacking of circulating water pump CW-lC. One waste shipment was made during the month.

Training continued during November in the following areas:

SR0 upgrade, licensed and non-licensed operator requalification, EONT, chemistry technician initial and refresher, health physics technician initial and refresher, maintenance and general employee. Administration of the annual 0 PPD licensed operator requalification exams is in progress. NRC prepared requalification exams were administered to eignt licensed operators.

One Auxiliary Operator-Nuclear resigned during the month.

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 During the October annual inspection of emergency diesel generator DG-1, a small accumulation (18 grams) of dirt / crud was found in the fuel transfer pump suction strainer. The accumulation appears to have entered the underground fuel line through a degraded pipe union.

The line was repaired per Maintenance Order No. 864089. No indications of a similar problem exist for DG-2.

The plant is progressing with the creation of a fuel integrity committee whose goal will be to ensure clean and usable diesel fuel oil at all times.

Monthly Operations Report November, 1986 Page Two D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL 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 surveillance test to verify that a fuel assembly uplift condition did not exist.

System Acceptance Committee Packages for November, 1986 Package Descriotion/ Analysis EEAR FC-81-96 New Air Source for HCV-2861.

This modification provided for the replacement of a temporary tygon tubing air line to HCV-2861 with a permanent copper tubing line.

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

EEAR FC-84-124 Installation of Temperature Devices.

This modification provided for the installation of temperature indicators to determine check valve leakage next to the auxiliary feedwater pumps.

Check valve leakage can result in steam binding of pumps. This was an INP0 response item. This modification does not have an adverse effect on the safety analysis.

EEAR FC-85-31 Hydrazine Hazards.

This modification provided for the installation of a chemical pumping station to pump chemicals into chemical mixing tanks CF-1, CF-2, CF-3 and AS-1A.

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

EEAR FC-86-31 Microwave Shielding.

This modification provided for the replacement of existing cables to Zones 7 and 8 with. shielded cable and removed wiring not used in the applicable conduit.

Also made two temporary jumpers for grounding microwaves permanent.

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

Monthly Operations Report November, 1986 Page Three d

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL D.

(Continued)

System Acceptance Committee Packages for November, 1986 Packaae Descriotion/ Analysis EEAR FC-86-052 Ventilation Housing Security Barriers.

This modification provided for the installation of barriers in the roof ventilation housings above Room

69. 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 One Auxiliary Operator-Nuclear resigned during November.

G.

TRAINING Training continued during November in the following areas:

SR0 upgrade, licensed and non-licensed operator requalification, EONT, chemistry technician initial and refresher, health physics technician initial and refresher, maintenance and general employee. Administra-tion of the annual 0 PPD licensed operator requalification exams is in progress. NRC prepared requalification exams were administered to eight licensed operators.

H.

CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment No.

Description 101 The amendment revises Section 5 of the Technical i

l Specifications to incorporate recent organizational and job title changes.

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r Monthly Operations Report

- November, 1986 Page Four II. ' MAINTENANCE (Significant Safety Related) 1

-None 4

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Omaha Pubilt Power District 1623 Harney Omaha. Nebraska 68102 2247 402!536 4000 December 12, 1986 LIC-86-666 Mr. James M. Taylor, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Reference:

Docket No. 50-285

Dear Mr. Taylor:

November Monthly Operating Report Please find enclosed ten (10) copies of the November,1986 Monthly Operating Report for the Fort Calhoun Station Unit No. 1.

Sin re W

R. L. Andrews Division fianager Nuclear Production l

RLA/me Enclosures cc: 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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