LIC-90-0718, Monthly Operating Rept for Aug 1990 for Fort Calhoun Station Unit 1

Monthly Operating Rept for Aug 1990 for Fort Calhoun Station Unit 1

ML20059J120
Person / Time
Site:	Fort Calhoun
Issue date:	08/31/1990
From:	Gates W, Stice D OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-90-0718, LIC-90-718, NUDOCS 9009190178
Download: ML20059J120 (8)

Text

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Omaha Pubuc Power District 444 South 16th Street Mall Omaha. Nebraska 68102-2247 402/636-2000 September 13, 1990 LIC-90-0718 L

U. S. Nuclear Regulatory Comission Attn: Document Control Da;k Mail Station Pl-137 Washington, DC 20555

Reference:

Docket No. 50-285 Gentlemen:

SUBJECT:

August Monthly Operating Report (MOR)

Please find enclosed the August .1990 Monthly Operating Report for the Fort Calhoun Station Unit No. I as re;cired by Tech.,ical Specification Section 5.9.1.

If you should have any questions, please contact me.

Sincerely, M 8. M W. G. Gates Division Manager Nuclear Operations WGG/sel Enclosures c: LeBoeuf, Lamb, Leiby & MacRae R. D. Martin, NRC Regional Administrator, Region IV R. P. Mullikin, NRC Senior Resident Inspector n,- .

D. K. Sentell, Combustion Engineering U OUJ R. J. Simon, Westinghouse Office of Management & Program Analysis (2)

Nuclear Safety Analysis Center INP0 Records Center American Nuclear Insurers 45-5124 Employment w,tn EquN Oppnunity We#8**

9009190178 900s31

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-AVERAGE DAILY UNIT POWER LEVEL

. DOCKET NO. 50-285 UNIT: Fort Calhoun Station.

DATE September 7, 1990 COMPLETED BY D. L. Stice

TELEPHONE (402)636-2474

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MONTH' August-1990 i

DAY 'AVERACE DAILY POWER LEVEL DAY ' AVERAGE DAILY POWER: LEVEL (MWe-Net)- . (MWe-Net) ~.

'l 472- 17 469 L 2 2473- 18- 469 3 473 19 468-4 472 20- '469  ;

5 472 J 21. -

472' 1,

,6 472- 22- 474 7 473 23' 472' i 8 473 .24 <

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474 9 25' 0 10 473 .26_ '01 11 472- '27

0- i 12 472 28 0 L

i L 13 472 291 0  :

14 473 30 0'

+y 15 '472 31 0 "

16 471 t

INSTRUCTIONS

• On th!s form, list the average daily unit power level in M W-Net for each day in the reporting month. Compute to the nearest whole mege',att. ,

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OPERATING DATA REPORT-i t

DOCKET NO.-- :50-285-UNIT. Fort Calhoun Station DATE September 7, 1990 3 COMPLETED'BY 0.-L. Stice i TELEPHONE -(402)636-2474 OPERATING STATUS <

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1. ' Unit Name: Fort Calhoun Station -

Notes P

'2. Reporting Period: August 1990 i

3. Licensed Thermal Power (MWt): 1500  ;

4. NameplateRating(GrossMWe): 502- .

5. DesignElectricalRating(NetMWe):_ 478- t

6. MaximumDependableCapacity(GrossMWe): 502 !i

7. 478- ,

MaximumDependableCapacity(NetMWe)(:'ItemNumbers3through7)SinceLast. Rep

8. If changes occur.in capacity Ratings Give Reasons' N/A ]

9. PowerLeveltoWhichRestricted,IfAny(NetMWe):' N/A

10. Reasons for Restrictions,.If Any: N/A nThis Month -Yr-to-Date: . Cumulative

11. Hours in Reporting Period . 744.0 5,831.0 '

148,441.0~ *

12. Number of Hours Reactor was Critical- ~'7ET

$ 3,328.2- 114,494.67

13. Reactor Reserve Shutdown Hours 0.0 - 'O.0 1,309.5-

14. Hours Generator On-Line 571.4 3,172.1 113,177.5 ' 't e 15. Unit Reserve Shutdown Hours .

-0.0 L 0.0 0.0 o L 16. GrossThermalEnergyGenerated(MWH) 852,677.8 4,455,654.4- 148,070,765.6:

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17. GrossElectricalEnergyGenerated(MWH) 282,084.0 1,459,232.0, 48,669,340.2-0 18. Net Electrical Energy Generated (MWH) 268,935.5 2 1,388,026.7 46,455,579.5-

19. Unit Service Factor l -76.8 54.4 1 76.2

20. Unit Availability Factor 76.6 54.4 76.2

21. UnitCaptcityFactor(UsingMDCNet) 75.6 49.8 67.9- 4

22. Unit Capacity Factor (Using DER Net) 75.6 49.8- 66.3

, 23. Unit. Force ~d Outage Rate- 23.2 5.2 3.0 ~ *

'24. ShutdownsScheduledOverNext6 Months (Type,_Date,andDurationofEach):- P NONE

25. If Shut Down at End of Report Period,-Estimated Date of Startup: September 3, 1990

26. Units In Test Status (Prior to Commercial Operation): Forcast -Achieved 't INITIAL CRITICALITY ,

INITIAL ELECTRICITY N/A i COM1ERCIAL OPERATION a

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. DOCKET NO. 50-285'- @

UNIT'lWE Fort Calhoun Station i DATE September 7.1990 -

UNIT SHUTDOWNS AND POWER REDUCTIONS C(DFLETED BY D. L. Stice TELEPHONE (402)- 636-2474~ q REPORT MONTH August 1990 l .,

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!- 90-05 900824 F 172.6 A- 1 N/A. :XX XXXXXX-  : Reactor Coolant Pump;RC-3A lower seal-

. pressure degraded. rapidly and.'a con- .

l . trolled plant-shutdown was conducted.

The reactor: system was cooled down ,

and depressurized for. RC-3A uncoupling '  :!

) _ and seal replacement.  :.

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1 2 & 4

F-Forced Researc Mothet _ .. Enfedt G - Instruc#ene '

t, ' S-Scheduled ' A-Equipment Feuure *wfd=h$ Hienuel for Preparation of Data ' .;

I Entry Slasets for h B-Meintenance or Test -  : 2-4denual Scram i- 'C-Refusing 8-Aete.neIIc Seresa -

Event neport SEf4 fee pe#EG-01815 i 2

D-Residatory Restriction .

4-Other Emplebt  ? .E E-Operator Training & License Exaniination " 5- ~

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j F-Adminletative Expedt 1 - Semo Sewee G-Operational Error

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l H-Other IExplain) 1 .- _

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Refueling Information Fort Calhoun - Unit No.1 Report for the month ending- Auaust 1990

1. Scheduled date for next refueling shutdown. September 1991 t

2. Scheduled date for restart following refueling.  !

November 1991

3. ' Will refueling or resumption of operation thereafter require a technical specification change or. other license amendment? Yes 1

(

a. If answer is yes, what, in general, aill  !

these be? I

'ncorporate specific requirements 1.resulting i from reload safety I analysis, j

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

Safety Review Committee to determine.whether 4 i

any unreviewed safety questions are associated '

with the core reload. N/A

c. If no-such review has taken place, when is q

it scheduled? N/A i

4. Scheduled date(s) for submitting proposed licensing action and support information. )

June 1991 i

5. Important-licensing considerations associated with refueling, e.g., new or'different fuel design or supplier, unreviewed design or.

i performance -analysis methods, significant changes in fuel design, new operating procedures.

New fuel supplier-New LOCAlnalysis-6.

The number of- fuel assemblies: a) in the core 133 Assemblies l b) in the' spent fuel pool 477 Assemblier c) spent fuel pool storage

. capacity-729 Assembl bs d) planned spent fuel pool Planned to be incretsed storage capacity with higher density spent t fuel racks. '

7. The projected date of the last refueling that can be discharged to the spent fuel pool ascuming the present licensed capacity. 1994*

O Capability of full core offload of 133 assemblies lost.

Prepared by MI%) //L g,, p.cd Date~ 9/ /9 o O

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10MAHA PUBLIC POWER DISTRICT -.

Fort Calhoun Station Unit No =l" '

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August 1990. 4 Monthly. Operating Report-

1. OPERATIONS SUM 4ARY' Fort Calhoun Station operated at a nominal 100% po' w er until August 24,.

1990.' On' August- 18, Reactor Coolant- Pump- RC-3A. indicated a= restriction in :

the lower seal. On August 24, the seal pressure degraded rapidly and a- i controlled plant shutdown was conducted. -The reactor. system was cooled 1 down and depressurized for RC4A uncoupling and. seal:-replacement. . On i August 31,.1990 the plant was' heating up for restart. The: cause 'of seal' failure'has not yet been determined.= ,

An NRC team was on site two' weeks' performing-'an in-depth' audit _of-thy Emergency Operating Procedures (EOPs) and Abnorr:al Operating Procebres (A0Ps). This' audit.was completed August,31,11990.

The following NRC' inspections tonk- place in August::

IR90-20 E0P Team Inspection - -

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'IR90-35 Residents" Monthly Inspection (Continued from ' July- 29,-'1990) q

' The following LER was submitted:- Date. Submitted  ;

o LER 90-07 R2 Main Feedwater and Main Steam = August-1, 1990 Piping Outside Destyn Basis 0

A. SAFETY VALVES OR PORV CHALLENGES C-R FAILURES WHICH OCCURRED None E. RESULTS OF LEAK RATE TESTS The results of the Reactor Coolant' System (RCS) Leak Rate Tests' for the month of August-indicate a continuation-~of the very low RCS.  ;

leakage trend following the 1990 refueling and maintenance outage. ~

The Fort Calhoon Station Unit No. I was taken off line- at.1923 hours0.0223 days <br />0.534 hours <br />0.00318 weeks <br />7.317015e-4 months <br /> on Friday, August 24, 1990 to replace the "A"- Reactor Coolant Pump- '3' (RCP) seal cartridge. Pressure indications between the mechanic'al seals within the' seal' cartridge indicated that the: seal breakdown device for the lower mechanical seal was becoming plugged. To ensure ,

continued seal reliability, .the plant was taken to cold shutdown and. I the seal cartridge was_ replaced. No unusual RCP-seal leakage outside of 'the< controlled seal bleed-off flow was. observed.

The known leakase to the Reactor Coolant Drain Tank and the'  :

Pressurizer Querch Tank varied throughout the month from 0.0 to 0.033 - I gpm. The total leak rate, which .is the sum of. both the known and unknown leak rates,' peaked on August 19, 1990.with 0.485 gpm. 1 calculated. j

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Monthly ~0perating. Report August _1990.-

Page Two 1

1 The highest unknown leakage was determined on August 9,-1990 with I 0.412 gpm calculated. On August 9, 15,.16,'and.17,-the~ total leak- 'l rate' exceeded 0.2 gpm. Most of the' unknown leakage on these; days can be' attributed.to the(failure of the drain valve, CH-258, for:the "B"

-charging pump. The leak rate returned to normal following -repair of the drain valve. 1 i

C.- CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY. g COMISSION AUTHORIZATION PURSUANT T0t10CFR50.59 A.

l- Amendment No_. . Description-

• None

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D. SIGNIFICANT SAFETY: RELATED MAINTENANCE FORf THE. MONTH OF AUGUST 199'0--

l Significant safety related maintenance' activities completed in thei month of. August 1990 are outlined below:

. i Two maintenance. activities occurred;on the discharge drain -valve' 4 CH-258 for charging pump CH-18.. : Thi initial: Maintenance Work Order

-was issued to disassemble:the valve, lap the seat, replace the. stem, '

L disc, and packing..' Post maintenance testing'was performed by)a- 'c leakage < check of the packing at system pressure. Additional ' '

maintanance was required ~due to excessive leakage causing t_he r charging-pump to overheat within a minute of P arting; The valve.was 1 then replaced. Post maintenance testing was Wrformed by running the pump with the downstream end open to prove the_ valve held _ tightly.  ?

Oscillation problems developed on the letdown control valves LCV-101 1 and 2. Monitoring equipment was hooked up to monitor.the-valve position, the air pressure from the Electro / Pneumatic- i positioner, the air pressure from;the positioner-to'the' actuator, and-the input and output of hand indicator controller HIC-101. The i nature of the failure was determined to be;misadjustment_of_the actuator spring which'was- subsequently readjusted; The oscillation has since been reduced'to an acceptable level.

During.the forced outage commencing August 24, 1990, many maintenance items were completed in addition to the replacement.of the reactor coolant pump "A" mechanical . seal . Some of the.more significant items -

that were accomplished during the outage included replacement of the 6

-temperature element TE-lllH which feed.; the reactor regulating system. This element .had failed earlier in'the operating cycle.

Several RCS flow instrument manifolds were' replaced. This-was.

-necessary due to leaking valves in'the old manifolds.

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'Mhnthly Operating Report

-August 1990

Page .Three -

Several other minor items were corrected, including: i t

' ~ Adjustment of position-indication for reactor coolant loop i injection valves _HCV-331,,333, and 311 i

'- Repair'of RCP seal flow indicator FIA-3155 Repair of instrumentation: associated with Control Element Assemblies; 31 and Group "B"? ,

Repair 'of the solenoid valve ~for: Main. Steam' Stop Valve ~ HCV-1041A

- Replacement Lof. Heater Drain Pump SuctionL Relief Valves Replacement of D Inverter BypassLTransformer 2

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