ML20137D622

Monthly Operating Rept for Dec 1985

ML20137D622
Person / Time
Site:	Fort Calhoun
Issue date:	12/31/1985
From:	Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	Taylor J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-86-016, LIC-86-16, NUDOCS 8601170050
Download: ML20137D622 (11)

Text

.

OPERATING DATA REPORT ,

DOCKET NO. 50-285 DATE January 10, 1986 COMPLETED BY T. P. Matthews TELEPHONE R 2-536-4733 OPERATING STATUS N*5 '

1. Unit Name: Fort Calhoun Station

2. Reporting Period: December, 1985 1500 .

3.1.icensed Thermal Power (MWt):

502

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe): 478

6. Maximum Dependable Capacity (Gross MWe): 502

7. Maximum Dependable Capacity (Net MWe):

478

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

N/A

9. Power Level To Which Restricted. If Any (Net MWe): N/A

10. Reasons For Restrictions.lf Any: Nnno _

This Month Yr to-Date Cumulative 744.0 8,760.0 107,546.0

11. Ifours in Reporting Period

12. Number Of Hours Reactor Was Critical 0.0 6,466.1 81,746.3

13. Reactor Reserve Shutdown llours 0.0 0.0 1.309.5 1 14. Hours Generator On Line 0.0 6,455.5 81.122.9 '

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 0.0 9,564,277.6 103.751.044.6 .

17. Gross Electrical Energy Generated (MWH) 0.0__,_ _,3,214,944.0 33,984,569.0

18. Net Electrical Energy Generated (MWil) 0.0 3,066,256.1 32,477,893.4

19. Unit Service Factor 0.0 73.7 75.4

20. Unit Availability Factor 0.0 73.7 75.4

21. Unit Capacity Factor (Using MDC Net) 0.0 73.2 65.5

22. Unit Capacity Factor (Using DER Net) 0.0 73.2 63.4

23. Unit Forced Outage Rite 0.0 0.0 3.5

24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Duration of Each t:

The 1985 Refuelina Shutdown consnenced September 28. 1985. with startco tentatively-scheduled for week of January 13, 1986. -

See item #24 25 If Shut Down At End Of Report Period. Estimated Date of Startup:

26. Units in Test Status (Prior io Comme cial Operation): Forecast Achieved INITIAL CRITICALITY

! INITIAL ELECTRICITY COMMERCIAL OPER ATION N/A e6o117ooso e51231 l

PDR ADOCK 05o00285 #* N. (4/77)

' R PM I

t- L _ (c-

• + +Y t

AVERAGE DAILY UNIT POWER LEVEL '

.(

' DOCKET NO. 50-285 UNIT Fort Calhoun Station DATE Janua'ry 10_ 1986

. COMPLETED BY T.P. Matt, hus s TELENIONE 402-536-4i33

, 3,

. -a

( % .i MONDI December 1985 .

AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL DAY (MWe-Net!

(MWe-NetJ D. 0 _ 17 nn- .

I ts.

s. >

2 0.0 is 't 40 s 3

0.0 19 s 0.0 5

0. 0 t 20

• O.n p 4- ,

- 0. 0 21-

'\ 0.0 [f /:

5 0.0 22 0.0 .

6 .

s .

7 0.0 '

23- 0.0 g ,_

0.0 24

\ 0.0 ,

0.0 0.0 9 25 __

10 n_n 26 nn 11 0.0 27 0.0 0.0 28 0.0 12 Og .i 29 0.0 13 x

14 0.0 -- 30 __

0.0

\

0.0 31 0.0-15 16 nn ,

0.0 4

INSTRUCTIONS On this format. list the average daily unit pos-r levelin MWe Net [or each day in the reportfng month. Compute to the nearest whole megawatt. s s.

.s

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- (9/77 )

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jf a a--__________ _} } _- _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _; __ ___

DOCKET NO. 50-285 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Fort Calhoun Station DATE Januarv 10. 1986 COMPLETED BY T. P. Matthews REPORTMONTH December 1985 TELEPHONE 402-536-4733

- ,{ g 3 hY Licensee , r, E , Cause & Currective Action to N. . Date i 3g i 2gE Event g3 mo g3O H

f: $ giji g Report a g Prevent Recurrence 5

85-01 850928 s 2270.2 c 1 N/A XX XXXXX 1985 refueling outage commenced September 28, 1985 1 2 3 4 F: Forced Reason: - Method: . Exhible G -Instructions for Preparation of Data S: Scheduled A. Equipment Failure (Explain) 1-Manual B-Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report tLER1 File (NUREG.

. D-Regulatory Restnetion 4-Other (Explain) 0161)

E4)perator Training & Ucense Examination

~

F-Administrative 5

G-Operational Error (Explain) Exhibit 1 - Same Source

, (9/77) Il-Other (Explaini .

e v -

P m f < !s:

Refueling Infortation Ebrt Calhoun - Unit No. 1 ,'

l 5 Report for the month ending Decenber 1985 . .,

1. Scheduled date for next refueling shutdown. March 1987 I

2. Scheduled date for restart following refueling. ' flay 1987 f

i -3. Will refueling or resunption of operation thereafter *

,)  !

, require a technical specification change or other t -

. license amendment? Yes- r r

a. If answer is yes, what, in general, will ,, f these be? - *

<, ,; r Fuel supplier change from ENC to CD ' g s and possible Technical Specification .  ;

change.  ;

s _

b. If answer is no, has the reload fuel design y L and core configuration been reviewed by' ';

/

your Plant Safety. Review Otanittee to dcster - 'q 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 subnitting prorised licensing action and support information. , ,

February 1987

5. Inportant licensing considerations associated with '

refueling, e.g., new or different fuel designSor- i supplier, unreviewed design or performance analysis' methods, significant changes in fuel design, imi' 4

operating procedures. i e New fuel supplier..(Combustion Engineering) ^~

but the new fuel will be essentially the same as that supplied by Combustion &'sT Engineering for Cycle 5a j

v 3

6. 'Ihe number of fuel assent > lies: a)-in the core. 133 assemblies 'e b):in the spent fuel pool "

~

348 c) spent fuel pool >.. g.

? storage nanacityJ /

• l 729 "

_ d) planned spent fuel pool May be increased l- storage capacity' via fuel nin I

' . consolidation I

'Ibe projected date of the last refueling tint can be .

i-

7.

{

discharged to the-spent fuel pool asetsning the present ,

licensed capacity. , 1996 ,'s 1

e

' /

Prepared by 4+y2AY) Date January 4,1986 -

j y yy . .

.. _ .. . .:vyme. . ' . ~: : ~ - "

.: = :~- a-1 .;*,% - - -

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OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. I

\

December,1985 L

Monthly Operations Report I. OPERATIONS

SUMMARY

[

' FortCaihounStationcontinuedtherefuelingandmaintenanceoutage throughout December, 1985. As the month of December ended, the Reactor

% Coolant' System was less than 200*F. , with a bubble in the pressurizer and with one Reactor Coolant Pump running.

Major maintenance items completed during the month of December included Reactor Vessel head' installation, Control Element Assembly (CEA) -

' coupling, incore changeout, and turbine / generator checkout. . Major modifications completed during'the month of December included Low 3

' Pressure Feedwater Heater replacement, HCV-335 replacement, turbine extraction line replacement, 4160/480V transformer replacement, and i electrical. penetration subassembly replacement. Work on the delta temperature wiring modification and the battery charger / instrument inverter changeout continued.

RCS heatup will commence as soon as the System Acceptance Committee reviews the last modifications needed before leaving cold shutdown.

i - Accelerated requalification training was initiated for licensed operators who failed the annual requal exam. Two individuals passed the NRC SR0 examination administered on November 12, 1985._ The third class of auxiliary operators completed classroom instruction. Work continues toward improvement of the C/RP, maintenance and general employee training programs.

No safety valve or PORV challenges or failures occurred.

A. PERFORMANCE CHARACTERISTICS 1

None B. CHANGES IN OPERATING METHODS' None C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS

.None

Monthly Operations Report December,1985 Page Two D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT C0f1 MISSION APPROVAL Procedure Description SP-ECT-1 Eddy Current Testing of Heat Exchanger Tubes (FW-1A).

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because it only involved the integrity testing of con-denser tubes to support optimum secondary chemistry and unit thermal performance.

System Acceptance Committee Packages for December,1985:

Package Description / Analysis EEAR FC-82-15 Third Auxiliary Feedwater Pump Tie-Ins.

This modification provided for the installation of tie-ins to the auxiliary feedwater system-(suction and recirc on FW-19 storage tank) and a tie-in to-the auxiliary feedwater discharge header. All work was performed in Room 81.'

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

EEAR FC-82-141 Component Cooling Water Dechromation.

This modification provided for the installation

of three 2" valves for dechromation tie-ins.

This modification does not havean adverse effect on the safety analysis.

EEAR FC-84-51 Class 1 and 2 Dresser Hancock Model 7250/7150 Valves.

This modification provided for replacement of the stem and disc assemblies of 12 Class 1 and 2 Dresser Hancock valves. The old stems were galled and pitted and:the discs needed to be replaced. This modification does-not have'an adverse effect on the safety analysis.

EEAR FC-84-61 Union Installation on Safety Injection Tanks.-

'This modification provided for the . installation of_ safety injection relief valves to facilitate removal of relief. valves for testing. This modification does not have an adverse effect on the safety analysis.

Monthly Operations Report December,1985 Page Three D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (Continued)

System Acceptance Comit' tee Packages for December,1985: .(Continued)-

1 Package Description / Analysis EEAR FC-84-72 Penetration M-16 Test Connection Isolation Valve.

This modification provided for the installation of an isolation valve on penetration M-16 test port. .This modification does not have an adverse

~

effect on the safety analysis.

EEAR FC-84-74A Fuse Prc tection for Certain Limit Switches.

This modification'provided for the relocation of-the protective fuses between the limit switches and the control circuitry for the affected valves.

The fuses will now clear a fault due to the sub-mergence of a limit switch and the solenoid will remain operable. This modification does not have an adverse effect on the safety analysis.

EEAR FC-84-80 Charging' Pump Control Circuitry Problems.

This modification provided for the elin ination of the possibility of obtai_ning an " anti-pump" feature (simultaneous "open" and "close" signal) on the charging pump control circuitry by elimi-nating a switch contact from' each charging pump control switch. This modification does not have an adverse effect on the safety analysis.

EEAR FC-84-91, Discharge of Feedwater Heater Relief Valves.

Part A This modification provided for the separation of the feedwater relief valve discharge piping from the steam packing exhauster discharge piping. The two piping trains previously shared a comon header. This modification does not have an adverse effect on the safety analysis.

EEAR FC-84-92, Nozzle Dam Control Panel Installation and Part A- Services.

~ This modification provided for the installation of nozzle dam control panel and supplied services to.the panel. This modification does _not._have an adverse effect on the safety analysis.

4 .

Monthly Operations Report December,1985 Page Four D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMtilSSION APPROVAL.

(Continued)

System Acceptance Comittee Packages for December,1985: (Continued)

Package Description / Analysis EEAR FC-84-179 Addition of HCV-1105 and HCV-1106 to-Steam Generator Isolation.

This modification provided for_ the addition of HCV-1105 and HCV-1106 to Steam Generator Isola-tion Signal (SGIS). This modification does not have an adverse effect on the safety analysis.

EEAR FC-85-42 Replacement of Dresser Hancock Valve MS-100.

This modification provided for the replacement of -valve MS-100 with a 1" Vogt #600 globe valve ASME Class 2. This modification does not have an adverse effect on the safety. analysis.

EEAR FC-85-56 Sequencing of Camera #8.

This modification will allow all . perimeter cameras to be sequenced onto the video monitors.

This is so the as built camera sequencing system'-

will be in accordance with the existing security a

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

EEAR FC-85-160 Extension of Control Room Air Intake, VA-65.

This modification relocated.the fresh' air intake point away from containment. It-is now 38 feet

-away from containment wall. This was.a duct work change only. This modification does not have an adverse effect on the safety analysis. -

EEAR FC-85-201 YCV-1045B Junction Box Seismic Support.

This modification provided an' independent seismic-ally qualified support of the junction box and its associated conduit and also eliminated the possi-

~

bility of any load being imposed onto neighboring conduit as was the case. This modification does ,

not have an adverse effect on the safety analysis. l l

1 v i

Monthly Operations Report December,1985

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

System Acceptance Comittee Packages for December,1985: (Continued)

Package Description / Analysis EEAR FC-85-204 CEA Replacement.

This modification provided for the replacement of 10 full length CEA's due to approaching the the total strain design criteria. Two spares of the original design were available on- site; C.E. was contracted to manufacturer;eight addi-tional CEA's of an _ improved design which utilized an 8" silver-indium-cadmium tip (instead of the standard B4 C pellets). This modification does not have an adverse effect on the safety analysis.

EEAR FC-85-212 Safety Injection Tank Level Switch Test Connec-tions.

This modification provided for the installation of test connections upstream and.-downstream of the safety injection . tank level switches so they

, can now be calibrated without having to vary the 1

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

. EEAR FC-85-214 Deflector Plate for Stop Valve Drains.

This modification provided for the installation -

of a baffle plate to deflect: steam downward thereby protecting condenser tubes. - This' modi-fication:does not have an adverse effect.on the safety analysis.

E. 'RESULTS OF LEAK RATE TESTS Refueling 1eak testing is in. progress. Total leakage will be reported after testing is completed. '

F. CHANGES IN PLANT OPERATING' STAFF

, .None

,. c g - ,- ,, y# rc-- *- , * - A

.e-Monthly Operations Report December,1985 Page Six G. TRAINING

~

During December, accelerated requalification training was initiated.

for licensed operators who failed the annual requal exam. Two indi-viduals passed the NRC SR0 examination administered on November 12,

. 1985. The third class of auxiliary operators completed classroom instruction. Work continues toward improvement of_the C/RP, maintenance and general employee training programs.

J H. CHANGES,. TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT T0'10CFR50.59 Amendment No. Description No. 92 This amendment changes the technical specifica--

tions to support the operation of the. unit at '

full rated power during Cycle.10.

No. 93 This amendment changes the titles of senior. .

management officials and deletes environmental qualification of electrical equipment admini-strative requirements (deadline and records).

This amendment also changes two Table of Contents pages (ii and iii) to reflect current Technical Specification sections.

II. MAINTENANCE (Significant Safety Related)

A report of all significant safety.related maintenance ~ performed during the 1985 refueling outage will be submitted at the conclusion of-the outage.

W. O W. Gary Gates Manager Fort Calhoun Station L

l l

Omaha Public Power District i 1623 Hamey Omaha. Nebraska 68102 2247 402/536-4000 January 13, 1986 LIC-86-016 l

l 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:

December Monthly Operating Report Plec.3e find enclosed ten (10) copies of the December, 1985 Monthly Operating Report for the Fort Calhoun Station Unit No. 1.

Sinc ely, s ek Svs4&J R. L. Andrews Division Manager Nuclear Production RLA/TPM/me Enclosures cc: NRC Regional Office Office of Management & Program Analysis (2)

R. R. Mills - Combustion Engineering R. J. Simon - Westinghouse Nuclear Safety Analysis Center INPO Records Center American Nuclear Insurers NRC File g

45 Si24 Employment with Equal Opportunity MaleTemale

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