ML20207P927

Monthly Operating Rept for Dec 1986

ML20207P927
Person / Time
Site:	Fort Calhoun
Issue date:	12/31/1986
From:	Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
LIC-87-037, LIC-87-37, NUDOCS 8701200420
Download: ML20207P927 (11)

Text

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AVEDAGE DAILY UNIT POWER LEVEL 50-285 D3CKET NO.

UNIT Fort Calhoun Station DATE January 12, 1987

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COMPLETED BY T. P. Matthews TELEPHONE 402-536-4733 MONDI -December, 1986 DAY AVERAGE DAILY POWER LEVEL liAY AVER AGE DAILY POWER LEVEL (MWe Net)

(MWe Net)

I 485 3 17 4RR 2 2

462.3 is 489.6 462.4 489.3 3

i, 62.5 4

20 488.0 5

457.7 21 487.6 456.7 22 487.8 6

7 456.0 488.0 23 475.7 488.0 g

24 483.7 9

25 488.1 10 483.9 488.2 26 I

485.7 488.3 27 479.2 12 28 488.1 277.6 488.1 13 29 461.6 14 3,

4g7,g is 478.5 3:

487.7 487.8 16 1

l INSTRUCTIONS On this format. list the average daily unit power level in MWe Net for each day in the reporting inonth. Cornpute to

{

the nearest whole nwgawatt.

I 19/77) x I

8701200420 861231 PDR ADOCK 05000285 R

PDR

OPERATING DATA REPORT DOCKET NO. 50-285 DATE

.la nna rv 12, 1987 COMPLETED BY T.P. Matthews TELEPHONE 402-536-4/33 OPERATING STATUS

1. Unit Name:

Fort Calhnun Station Notes

. 2. Reporting Period:

December 1986

3. Licensed Thennel Power (MWt).

1500 502

4. Namepiste Rating (Gross MWe):

478

5. Des.gn Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross M Ne):

W

7. Maximum Dependable Capadty (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. lf Any (Net MWe).

N/A

10. Reasons For Restrictions.lf Any.

None This Month Yr..to Date Cumulative

11. Hours in Reporting Period 744.0 8,760.0 116.306.0

12. Number Of Houn Reactor Was Critical 744.0 8.485.3 90,231.5

13. Reactor Resene Shutdown flour, 0.0 0.0 1,309.5

14. Hours Generator On Line 744.0 8,264.2 89.387.1 l$. Unit Rewrve Shutdown Hou,,

0.0 0.0 0.0

16. Grom Thermal Energy Generated (MWil) 1.078.714.7 11.299,457.3 1_15,050,501.9

_3,782,157.2 37,766,726.2

17. Gross Electrical Energy Generated (MWH) 368.374.0

18. Net Electrical Energy Generated (MWH) 352.302.9 3,605,567.5 36.083,460.9

19. Unit Service Factor 100.0 94.3 76.9

20. Unit Assilability Factor 100.0 94.3 76.9

21. Unit Capacity Factor (Using MDC Net) 99.1 86.1 67.1

22. Unit Capacity Factor (Using DER Net) 99.1 86.1 65.2

23. Unit Forced Outase Rate 0.0 1.3 3.3

24. Shutdowns Scheduled Oser Nest 6 Months (Type.Date.and Duration of Eacht:

The 1987 Refueling Shutdown is tentatively scheduled for February 28,1987 with Startup tentatively scheduled for itay 7,1987.

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

N/A

26. Units in Test Status (Prior io Commercial Operationi:

Forecast Achwsed INITIAL CRlilCALITY INITI Al. ELICTRICITY N/A COMMI.RCl%L Ort:R A T10N (9/77)

s UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKETNO. 50 M UNIT NAbeE Fort Calhoun Station DAR

.la nua ry 17_ 1987 l

m gy T. P. Ma tthews

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REPORTMONTH December.1986 TELEF900NE 402-536-4733 l

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4 Licer.see gt g"3L Cause & Corrective h

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86-07 861212 S

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N/A SG Condxx On December 12, 1986, a power re-duction commenced to determine leak-i age in "A" North Condensor. Power I

was held at 57% while the condensor was cnecked. No detectable condensor leaks were identified, and the unit returned to full power on December 13, 1986.

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P I

2 3

4 s-F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A-Equipment Failure (Emplain)

I-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.

Entry Sheets for fxensee C-Refueling 3-Automatic Scram.

Event Report (LER) File (NUREG-D-Regulatory Restriction 40her (Explain) 016I)

E-Operator Training & Ixense Examination F-Administra ise 5

G-Operatsunal Estur (Emplam)

Exhibit I - Same Source 08/77)

I13her (Explam)

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Refueling Information Fort Calhoun - Unit No. 1

)

Report for the month ending December 1986 1.

Scheduled date for next refueling shutdown.

February. 1987 i

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 1

i a.

If answer is yes, what, in general, will l

these be?

l Fuel supplier change fiom ENC to CE and l

possible Technical Spec',fication 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 relcad.

c.

If no such review has taken place, then is it scheduled?

I 4.

Scheduled date(s) for submitting proposed licensing l

action and support information.

January. 1987 l

S.

Important licensing considerations associated with l

refueling, e.g., new or different fuel design or sup)1ier, unreviewed design or performance analysis metiods, 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 fue pool 349 c spent fuel pool storage capacit 729 d)plannedspentfuefpool May be increased l

storage capacity via fuel ein consolidation 7.

The )rojected date of the last refueling that can be

(

disc 1arged to the spent fuel pool assuming the present licensed capacity.

1996 l

Prepared by '"^^^' Al b Date December 29. 1986 l

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

OPERATIONS

SUMMARY

Fort Calhoun Station reduced power to approximately 95% on December 1, 1986, for Moderator Temperature Coefficient testing as required by the operating license.

Power was reduced to approximately 56% on December 13, 1986, to perform condenser leak testing. The leak was smaller than any we have tried to find before using helium. We were not successful, but it helped provide a baseline as to what we can attempt to look for in the future.

Power was returned to 100% on December 15, 1986. The last week in December, the chemical indications of a leak have been increasing, but are still within operating limits.

Results of the NRC requalification examination given to eight NRC licensed operators were received.

The annual 0 PPD administered requalification examinations were completed. General Employee Training was certified by INP0.

Training continued for maintenance crafts, chemical and radiation protection technicians and non-licensed operators.

Twelve of the trailers used for training and office space were moved out of the protected area to allow access for the upcoming auxiliary building expansion.

There was one shipment of waste offsite containing a concentrate liner and drums of compacted waste.

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 l

l L

o Monthly Operations Report December, 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.

SP-BURNUP-1 Burnup Determination for Storage of Spent Fuel.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because this procedure verifies that burnup criteria are met for spent fuel storage as required in the NRC-approved spent fuel rack installation.

SP-UF6-1 Uranium Hexafluoride Storage Cylinder External Visual Inspection.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because this procedure only provides for an inspection of a storage area and associated items.

No plant systems are affected.

SP-NFR-1 Fuel Receipt Procedure.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because this procedure provided for receipt, inspection and storage of new unirradiated fuel.

Appropriate radiological and load handling limits were observed.

SP ECT-1 Eddy Current Test of Heat Exchanger Tubes.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it only involved eddy current testing of the condenser tubes in FW-1B. This activity did not in any way affect the safety of the plant or increase the probability of an accident

-Monthly Operations Report December, 1986 Page Three 3

D.

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

SP-CHEM-1 Reactor Cor,e Hydrogen Peroxide Flush.

This-procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 insofar s

as it complied with the system manufacturer's methods.and recommendations.

System Acceptance Committee Packages for December, 1986

'Packaae Descriotion/ Analysis EEAR FC-79-190B Wide Range Noble Gas Monitor.

This modification provided for the installation of monitors RM-063L, M, and H.

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

EEAR FC-79-190C Post Accident Main Steam Line Monitor.

This modification provided for the installation of monitor RM-064. This modification does not have an adverse effect on the safety analysis.

)

1 EEAR FC-81-103 Heater for Caustic Dilution (Reroute of DW-38 Condensate Return Line).

This modification provided for the reroute of the condensate return line from DW-38 (Caustic Dilution Water Heater).

This will now supply a gravity drain. This modification does not have an adverse effect on the safety analysis.

EEAR FC-82-154 Installation of SCADA Remote Terminal.

This modification provided for the installation of a Supervisory Control and Data Acquisition (SCADA) remote unit in the turbine room. The unit receives commands from the master unit, collects and transmits the data back to the master station.

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

f 4

g

Monthly Operations Report December, 1986

'Page Four D.

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

System Acceptance Committee Packages for December, 1986 (Continued)

Packaae Description / Analysis EEAR FC-84-177 Addition of Single Ended Microwaves.

This modification provided for additional microwaves for use around the security building.

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

EEAR FC-85-078 Laundry Room Gaitronics.

This modification provided for the installation of a speaker for the Gaitronics (plant communication) system. This modification does not have an adverse effect on the safety analysis.

EEAR FC-85-084 E-Field Replacement.

This modification provided for the instaliation of two microwave detection links to replace the E-field presently in use in Zone 13. This modification does not have an adverse effect on the safety analysis.

EEAR FC-85-090 Microwave Additions.

This modification provided for additional microwaves for the security system.

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

EEAR FC-85-191 Xerox Power Feed.

This modification provided for the installation of an AC outlet for the xerox machine in the Technical Support Center. This modification does not have an adverse effect on the safety analysis.

EEAR FC-86-19B Security Building Addition.

This modification provided for the temporary perimeter detection system to accommodate the security building expansion. This modification does not have an adverse effect on the safety analysis.

Monthly Operations Report December, 1986 Page Five D.

C4ANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (Continued)

System Acceptance Committee Packages for December, 1986 (Continued)

Package Description / Analysis EEAR FC 86-34 Control Room Ventilation Test Ports.

This modification provided for the installation of test ports in the control room HVAC. This modification does not have an adverse effect on the safety analysis.

EEAR FC-86-37 Control Room Carpeting.

This modification provided for the replacement of control room carpeting. The carpeting installed was analyzed to ensure acceptability with respect to the USAR and/or fire hazards analysis of installed Fort Calhoun Station equipment.

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

EEAR FC-86-60 Installation of Emergency Preparedness Signs.

This modification provided for the installation of 10 emergency preparedness signs along the Missouri River and the 10 mile emergency protection zone.

This was a commitment to FEMA.

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

E.

RESULTS OF LEAK RATE TESTS The Biannual Leak Rate Test on the containment purge valves was completed during the month of December per ST-CONT-3.

The total leakage for penetrationr. M-87 and M-88 was left at 4,100 SCCM.

In June of 1986, the Biannual purge valve test was performed and total leakage for both penetrations M-87 and M-88 was 0 SCCM.

During the December test, M-87 was found and left at 2,800 SCCM, and penetration M-88 was found at 5.1 SCFM.

When the penetration was discovered to be leaking at 5.1 SCFM, the LC0 on containment integrity was invoked until the penetration was repaired (see Operation Incident Report 2614). Since only one valve of the two making up penetration ti-88 was leaking, containment integrity was not violated. Therefore, no LER was issued.

Monthly Operations Report December, 1986 Page Six E.

RESULTS Of LEAK RATE TESTS (Continued)

An investigation was completed on M-88 and it was determined that PCV-742C was leaking excessively. The seal was adjusted per PRC approved procedure M0 864493. The leak rate test was again performed on M-88 and found to be 1,300 SCCM. Operations Incident 2614 was written for the incident.

The last "B" and "C" leak rate total was 4,443 SCCM after the PAL door test. M-87 and M-88 leakage of 4,100 SCCM will make the new total "B" and "C" leak rate equal to 8,543 SCCM.

Thf s total is well below the allowed leakage of.6 L (62,951 SCCM) as specified in 10 CFR 50 Appendix J.

The next scheduled test that will affect the "B" and "C" leak rate total is the Biannual PAL Door Leak Test due next month.

F.

CHANGES IN PLANT OPERATING STAFF None.

G.

TRAINING Results of the NRC requalification examination given to eight NRC licensed averators were received. The annual 0 PPD administered requalif kor. ion examinations were complei.ed.

General Employee Training was certified by INP0. Training continued for maintenance crafts, chemical and radiation protection technicians and non-licensed operators.

l l

H.

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

II. MAINTENANCE (Significant Safety Related) l None M

W. Gary G es Manager-Fort Calhoun Station

Omaha Public Power District t623 Harney Omaha Nebraska 68102 2247 402/536-4000 January 13, 1987 LIC-87-037 V. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

Docket No. 50-285

SUBJECT:

December Monthly Operating Report Gentlemen:

Pursuant to Technical Specification Section 5.9.1, and 10 CFR Part 50.4(b)(1),

please find enclosed one copy of the December,1986 Monthly Operating Report for the Fort Calhoun Station Unit No. 1.

f Sincerel,

X$ dw R. L. Andrews Division Manager Nuclear Production 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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