ML20115C892

Monthly Operating Rept for Feb 1985

ML20115C892
Person / Time
Site:	Fort Calhoun
Issue date:	02/28/1985
From:	Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	Taylor J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-85-103, NUDOCS 8504180606
Download: ML20115C892 (9)

Text

.

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-285 Fort Calhoun Statfor UNIT DATE -March 6. 1985 COMPLETED BY

_T. P. Matthews TELEPHONE (402) 536-4733 February, 1985 MONTH DAY AVERAGE DAILY POWER LEVEL DAY' AVER AGE DAILY POWER LEVEL (MWe-Net)

(MWe-Neti 1 -

486.5 17 486.9 486.5-2 18 486.6 487.1 3

39 487.1 4

486.6 20 487.4 487.7

-5 23 486.8 487.8 6

22 487.0 400*1 7

23 486.7 487.6 8

E.5 487.4 9

25 486.0 to 26 487.0

• 0 486.7 33 27 487.0 486.7 12-28 486.8 13 29 486.8 34 30 487.1 15 31 16 487.3 INSTRUCTIONS

' On this format, list the average daily unit power levelin MWe. Net for each day in the reporting month. Compute to the nearest whole megawatt.

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OPERATING DATA REPORT "50-285 DOCKET NO.

DATE March 6, 1985 s

COMPLETED BY T. P.

4atthews-

. TELEPHONE f4021 536-4733-OPERATING STATUS

^

Notes Fort Calhoun Station 1.' Unit Name:

February,1985 2.. Reporting Period:

1500

~ 3. Licensed Thermal Power (MWt):

502

4. Nameplate Rating (Gross MWe):

'478

5. Desagn Electncal Rating (Net MWe):

502

~. Maximum Dependable Capacity (Gross MWe):

6 l

470

7. Maximum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report.Give Reasons

' Items 4 and 6 changed to be consistent with actual nameplate rating.

N/A

9. Power Level To Which Restricted,if Any (g'oneet MWe):

10. Reasons For Restrictions. If Any:

This Month -

Yr to Date Cumulative 672.0 1,416.0 100,202.0

/II. Hours in Reporting Period 672.0 1,416.0 76,696.2

' 12.' Number Of Hours Reactor Was Critical.

0.0 0.0

-1.309.5'

' 13. Reactor Reserve Shutdown Hours.

672.0 1,416.0-

-76,083.4' 14c Hours Generator'On-Line -

0.0

' 0. 0 0.~ 0 ~

15. Unit Reserve Shutdcwn Hours 1,001,136.2 2,109,431.1-

%,2%,198.1

16. Cross Thermal Energy Generated (MWH) 17.- Gross Electrical Energy Generated (MWH).

342 028.0

-719.402.0

-31.489.027.0' 2

-327,217.9 687,765.7

-30.099.403.0

18. Net Electrical Energy Generated (MWH) 100.0 100.0 75.9 f.

19. Unit Service Factor 100.0 100.0 75.9 T 20. Unit Availability Factor-101.9 101.6-65.4

-21. Unit Capacity Factor (Using MDC Net)

~

101.9 101.6 63.1 122. Unit Capacity Factor (Using DER Net) 0.0 0.0 3.7 123. Unit Forced Outage Rate 124.' Shutdowns Scheduled Over Next t> Months (Type. Date.and Duration of Each t:

-None

'N/A

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

z 26. Units in Test Status (Prior to Commercial Operat on): N/A Forecast Achieved -

i INITIAL CRITICALITY

' INITIA L ELECTRICITY COMMERCIAL OPERATION (9/77)

50-285~

DOCKET NO.

Fort Calhoun Station UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME DATE March 6_

t ogs; COMPLETED 8Y T. P. Matthews February, 1985 TELEPHONE (402) M6_d7n REPORT MONTH 3

Cause & Corrective

.5 ?

3

.5k Licensee E

8.

Action to

[3 No.

Date g.

3g g

jg5 Event u?

U Prevent Recurrence 50

$E j di g Report 2:

H 6

There were no unit shutdowns or power reductions during the month of February, 1985.

I 4

3 Exhibit G Instructions I

2 Method:

for Preparation of Data F: Forced Reason:

1 Manual Entry Sheets for Licensee S: Scheduled A-Equipment Failure (Explain) 2-Manual Scram.

Event Report (LER) File (NUREG-B Maintenance of Test 3 Automatic Scram.

0161)

C-Refueling 4-Other (Explain)

D-Regulatory Restriction E-Operator Training & License Examination 5

F Administrative Exhibit I - Same Source G-Operational Error (Explain)

!I-Other (ExplainI (9/77)

Refueling Information

~Ebrt Calhoun - Unit No. 1 Report for the nonth ending February,1985 1.

Scheduled date for next refueling shutdown.

October, 1985 2.

Scheduled date for restart following refueling.

December,1985 3.

Will refueling or restmption of operation thereafter require a technical specification change or other Yes license amendment?

a.

If answer is yes, what, in general, will these.be?

Technical Specification change to accommodate increased radial peaks due to further reduction in radial leakage.

b.

If. answer is no, has the reload fuel design and core configuration been reviewed by-your Plant Safety Review Carmittee 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.

September,1985 5.

Inportant 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.

Methodology Changes June, 1985 6.

The number of fuel assemblies: a) in the core 133 assemblies b) in the spent fuel pool 305" c) spent fuel pool storage capacity 729 d) planned spent fuel pool May be increased storage capacity via fuel pin consolidation 7.

The projected date of the last refueling that can be discharged to the spent fuel pool asstating the present licensed capacity.

1996 Prepared by M

Date March 4, 1985 9

8

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 February, 1985-Monthly Operations Report I. -OPERATIONS

SUMMARY

Fort Calhoun Station operated at 100% throughout February,1985.

During the month of February, three Auxiliary Operator-Nuclear personnel reported for work at Fort Calhoun Station.

The security force will be at full authorized strength in the first week of March.-

The-Chemistry / Radiation Protection group participated with Technical Ser-vices and Licensing in responding to questions by the NRC concerning steam

-generator secondary chemistry. The primary and secondary chemistry. para-meters were maintained within limits as to require no corrective actions.

The Maintenance and Technical groups continued support functions to main-tain 100% power operation.

The Training Department. continues to implement revised training programs.

The initial course for new operators is scheduled to begin in mid-March.-

No safety-valve or PORV challenges or failures occurred.

A.

PERFORMANCE CHARACTERISTICS LER Number Deficiency 84-023 R1 VIAS Actuations -- R1 corrected typos and clarified content of certain statements.

U

, "h; '

(*,L

~

Monthly Operations-Report -

Feb'ruary,;1985 Page..Two A.

PERFORMANCE CHARACTERISTICS (continued)

LER-Number' Deficiency 021 Low Boron Concentration in' Safety Injection and-Refueling Water Tank-

- 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-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 fro'm a surveillance

. test to verify that a fuel assembly uplift condition:

'did not exist.

System Acceptance Committee Packages for February,1985:

-Package Description / Analysis

' ^

Installation of CRT Cables and Conduits..

EEAR FC-83-38 This modification provided for the installation of. cable'and conduit to. selected locations for-CRT hookup and has no adverse effect on the~

safety, analysis.

LEEAR'FC-84-208:

Condensate Sample Point Upstream of "A" Drain

Cooler.

.This modification provided for the: installation

'of a sample valve on the condensate system which already has an isolation valve. This modifica-tion has no adverse effect on the safety analysis.

i I

Monthly 0perations Report February, 1985 Page Three

.D.

CHANGES, TEST AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)

~

System Acceptance Committee Packages for February, 1985:

(continued)

Package Description / Analysis EEAR FC-83-120 Gai-tronics for Office Area.

This modification provided for the installation of two Gai-tronics stations in the office area and has no adverse effect on the safety analysis.

EEAR FC-83-24 Cutout Line Between RW-153 and RW-167.

This modification provided for the removal of some unused piping and capping of the ends. This pro-vided new drain connections, but did not change the raw water system performance or function._ This modification has no adverse effect on the safety analysis.

DCR 76-66 Hazardous Material Storage Building.

This modification provided.for the construction

~

and erection of a 20' x 30' preengineered metal building-approximately 550' west and 150' north of the reactor containment centerline. This modi-fication has no adverse effect on the safety

. analysis.

EEAR FC-84-85 Inlet Union for NG-123.

This modification provided for the installation of a union on the inlet of NG-123 for ease of maintenance on.the nitrogen gas system and has no adverse effect on the safety analysis.

E.

RESULTS OF LEAK RATE TESTS None F.

CHANGES IN PLANT OPERATING STAFF During February, Messrs. Dennis Peters, Patrick Cronin and Joe.Braun reported to the Fort Calhoun Station as Auxiliary Operators-Nuclear.

Effective February 16, 1985, Mr. ' John J. Fluehr, III was appointed as Supervisor-Station Training.

Monthly Operations' Report February, 1985 Page Four G.

TRAINING

-Training in February,.1985, included operator requalification including fire brigade leader training for licensed operators, introduction to performance-based training and evaluation, and emergency procedures guideline review and development. Non-licensed operator training included classical physics, reactor theory and initial fire brigade training. Maintenance received systems training on the reactor coolant system and the demin-~

eralized water system.

H.

CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT T0 10CFR50.59 None II. - MAINTENANCE (Significant Safety Related)

None.

W id-Y S cW. Gary Gates p

Manager Fort Calhoun Station

I.

WhMEMBE?MMNRWEIEWM@ma*=-"IIHMER^

Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 402/536 4000 March 14, 1985 LIC-85-103 Mr. James M. Taylor, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555

Reference:

Docket No. 50-285

Dear Mr. Taylor:

February Monthly Operating Report Please find enclosed ten (10) copies of the February 1985 Monthly Operating Report for the Fort Calhoun Station Unit No.1.

Please note the change to lines 4 and 6 of the Operating Data Report. The Nameplate Rating and Maximum Dependable Capacity figures were revised from 501 to 502 to reflect the correct values. This change does not affect the Monthly Operating Data that has been reported previously.

Sincerely, R. L. Andrews Division Manager Nuclear Production RLA/TPM/dao Enclosures qj,[

J cc: NRC Regional Office 6

Office of Management & Program Analysis ~(2) g Mr. R. R. Mills - Combustion Engineering

@[

p Mr. T. F. Polk - Westinghouse Nuclear Safety Analysis Center 69

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INP0 Records Center 9f American Nuclear Insurers Ti NRC File 4

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