LIC-96-0036, Monthly Operating Rept for Feb 1996 for Calhoun Station,Unit 1

Monthly Operating Rept for Feb 1996 for Calhoun Station,Unit 1

ML20106H078
Person / Time
Site:	Fort Calhoun
Issue date:	02/29/1996
From:	Lippy D, Tira Patterson OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-96-0036, LIC-96-36, NUDOCS 9603200158
Download: ML20106H078 (8)

Text

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Omaha Public Power District 444 South 16th Street Mall Omaha, Nebraska 68102-2247 402/636-2000 March 13, 1996 LIC-96-0036 U. S. Nuclear Regulatory Commission ,

Attn: Doccment Control Desk l Mail Station P1-137 Washington, D.C. 20555 I

Reference:

Docket No. 50-285

SUBJECT:

February 1996 Monthly Operating Report (MOR)

Enclosed please find the February 1996 MOR for Fort Calhoun Station (FCS)

Unit No. I as required by FCS Technical Specification 5.9.1.

If you should have any questions, please contact me.

1 Sincerely, l h -

T. L. Patterson Division Manager Nuclear Operations TLP/dll Enclosures c: Winston & Strawn L. J. Callan, NRC Regional Administrator, Region IV L. R. Wharton, NRC Project Manager W. C. Walker, NRC Senior Resident Inspector R. J. S'..non, Westinghouse INP0 Records Center 9603200158 960229 /l PDR R

ADOCK 05000285 PDR

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c5-5125 Employment mth Equalopportunity \

LIC-96-0036 Enclosure Page 1 1

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 FEBRUARY 1996 Monthly Operating Report

1. OPERATIONS

SUMMARY

During the month of February 1996, the Fort Calhoun Station (FCS) operated at a nominal 100% power. Normal plant maintenance, surveillance, equip-ment rotation activities and scheduled on-line modifications were performed during the month.

Monitoring of the Control Element Drive Mechanism (CEDM) No.15 mechanical seal leak continued. A planned maintenance outage is scheduled to conmence at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on March 15, 1996, with a planned duration of seven days. During this mini-outage, the seal will be replaced and other work will be completed to improve station reliability for the upcoming summer.

On February 1st, a supplemental one hour non-emergency notification was made to the NRC pursuant to 10CFR50.72(b)(1)(ii)(B) and (C) to update a reportable event from November 1995 in which FCS was found to be in a condition outside its design basis. Originally, only the motor control center (MCC) 480VAC breakers were considered susceptible to ground induced tripping. Further review concluded that, as a conservative measure, the affected breakers feeding safeguards motors should be included in the group of susceptible breakers. A modification to resolve the 480V breaker  ;

issue was finalized in February. Replacement trip devices have been procured with seven of the thirteen most critical breakers scheduled to be l replaced during the March mini-outage. Six motor feeder breakers are scheduled to be replaced on-line.

)

i Eight additional incore nuclear detectors failed in February 1996, rendering five of the twenty-eight detector strings inoperable. All failures have occurred in detectors that were installed during the 1995 ,

refueling outage. These failures are under investigation with assistance j from ABB/CE and the incore detector vendor. 2

2. SAFETY VALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED During the month of February, no power operated relief valve (PORV) or primary system safety valve challenges or failures occurred.

LIC-96-0036 Enclosure Page 2

3. RESULTS OF LEAK RATE TESTS The February Reactor Coolant System (RCS) leak rate was relatively steady at approximately 0.2 to 0.3 gpm throughout the month. This leak rate continued the trend established following the reactor trip on August 26, 1995. Repacking all three charging pumps in January and early February due to packing leaks has mitigated short-term increases in the leak rate.

The major contributor of the RCS leakage is "Known" leakage which is collected in both the Reactor Coolant Drain Tank (RCDT) and the Pressurizer Quench Tank (QT). Approximately 0.1 to 0.15 gpm of the total RCS leakage has been classified as "Known" leakage. The primary leakage source for "Known" leakage continues to be CEDM No.15. In addition to CEDM No.15, several of the reactor head vent system isolation valves are also leaking through. Head vent leakage is contributing an estimated 0.06 gpm with leakage being collected both in the Containment Sump and the Pressurizer QT. Leakage to the containment sump is considered " Unknown" leakage.

4. CHANGES. TESTS AND EXPERIMENTS RE0VIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59

]

Amendment No. Description None

5. SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE MONTH OF FEBRUARY 1996 1 Performed repairs on toxic gas monitors YIT- 6288B and YIT-6286B l Replaced the ratcheting wrenches on all eight of the Raw Water (RW)/

Component Cooling Water interface valves for the Containment Cooling ,

Units '

Cleaned out the air sparging line for RW Pump AC-10C

6. OPERATING DATA REPORT Attachment I J

1

. .- , t LIC-96-0036  !

Enclosure  !

Page 3  ;

7. AVERAGE DAILY' UNIT POWER LEVEL I Attachment II ,

l

8. UNIT SHUTDOWNS AND POWER REDUCTIONS -

Attachment III

9. REFUELING INFORMATION. FORT CALHOUN STATION UNIT N0. 1 Attachment IV  ;

I i

I

ATTACHMENT I OPERATING DATA REPORT DOCKET NO. 50-285 _ _ _ _ _

UNIT FORT CALHOUN STATION DATE MARCH __07,1996 COMPLETED BY D. L. LIPPY OPERATING STATUS TELEPHONE (402) 53306843

l. Unit Name: FORT CALHOUN STATION

2. Reporting Peflod: FE5MUARY 19s F NOTES

3. Licensed Thermal Power (MWt): 1500

4. Nameplate Rating (Gross MWe): 502

5. Design Elec. Rating (Net MWe): 478 l

6. Max. Dep. Capacity (Gross MWe): 502 i

7. Max. Dep. Capacity (Net MWe): 478 l

8. If changes occur in Capacity Ratings (3 through 7) since last report, l

{

give reasons: '

N/A_ - - . _

9. Power Level to which restricted, if any (Net MWe): N/A _

10. Reasons for restrictions, if any:

N/A l

THIS MONTH YR-TO-DATE CUMULATIVE i

__________ __________ __________- I

11. Hours in Reporting Period........... 696.0 1440.0 196634.0

12. Number of Hours Reactor was Critical 696.0 1440.0 155148.0 1

13. Reactor Reserve Shutdown Hours...... .0 .0 1309.5

14. Hours Generator On-line............. 696.0 1440.0 153420.5

15. Unit Reserve Shutdown Hours......... .0 -

.0 .0

16. Gross Thermal Energy Generated (MWH) 1041395 6 ~ fit 45T9.6 104846~8TT.~s~ l

17. Gross Elec. Energy Generated (MWH).. 354312.0 733460.0 67667185.2 l

18. Net Elec. Energy Generated (MWH).... 338525.5 700783.1 64558151.9 I

19. Unit Service Factor................. 106.6 100.0 78.0 l

20. Unit Availability Factor............ 100.0 100.0_ 78.0

21. Unit Capacity Factor (using MDC Net) 101.8 101.8 71.0 l

22. Unit Capacity Factor (using DER Net) 101.8 101.8 65.4

23. Unit Forced Outage Rate............. .0 .0 4.0

24. Shutdowns scheduled over next 6 months (type, date, and duration of each):

A MAINTENANCE OUTAGE IS SCHEDULED TO OCCUR FROM MARCH 15-23, 1996 TO RE-PAIR / REPLACE _ DEGRADING CEDM MECHANICAL SEALS.

25. If shut down at end of report period, estimated date of startup:

26. Units in test status (prior to comm. oper.): Forecast Achieved INITIAL CRITICALITY ~ ~ ~

INITIAL ELECTRICITY N/A COMMERCIAL OPERATION _ _ _ _

~

ATTACHMENT II

, . AVERAGE DAILY UNIT POWER LEVEL

. DOCKET NO. .50_285 UNIT FORT CALHOUN STATION

'DATE MARCH 07,1996 COMPLETED BY D. L. LIPPY TELEPHONE (402) 53306843

-MONTH FEBRUARY 1996 I

. DAY AVERAGE DAILY. POWER LEVEL DAY AVERAGE DAILY POWER LEVEL i (MWe-Net) (MWe-Net) )

.l' 486 17 487 ,

1 2 486 18 486 )

3 487 19 487 4 487 20 487 5 487 21 487 6 487 22 487

'7 487 23 487 8 487 24 .486 9 487 25 486 10 486 26 486

' 11 486 27 486 12 486 28 486

-13 486 29 486 14 486 30 N/A 15 486 31 N/A .

1 16 486 4

INSTRUCTIONS On this form, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

4

ATTACHMENT III DOCKET NO. 50-285 .

UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Fort Calhoun St. .

DATE March 7. 1996 . -

COMPLETED BY D. L. Lipov TELEPHONE (402) 533-6843 -

REPORT MONTH February 1996

No.- 'Detej iType*

t Durationi ;iteaMj- fMethod! ltleensee? $6 stim:! SCseponenti fcsuse5Morrectives J(Nours)j; i Jofi ' l: Event) ~ JCodt:[ 1.Codd[ ~  : iAction.,tej '_ , g.7 tShutting}

Report . Prevent tecurrenceli

? Dowak.. t Nek

~ ' ~

^

bneactor*>

NONE 1 2 3 4 F: Forced Reason: Method: Exhibit F - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File (NUREG-0161)

D-Regulatory Restriction 4-Other (Explain)

E-Operator Training & License Examination F-Administrative 5 H-Other (Explain) Exhibit H - Same Source (9/77)

' '~ Attachment IV Refueling Information Fort Calhoun Station - Unit No. 1 l

l Report for the month ending February 29. 1996  !

1. Scheduled date for next refueling shutdown. September 21. 1996

2. Scheduled date for restart following refueling. November 2. 1996

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

a. If answer is yes, what, in general, will Enrichment limit of soent these be? fuel racks is to be  !

increased to at least 4.5 w/o from 4.2 w/o. This is l necessary based uoon the oreliminary Cvele 17 core pattern develoDment.

1

b. If answer is no, has the reload fuel design l

and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload. N/A

c. If no such review has taken place, when is it scheduled? N/A

4. Scheduled date(s) for submitting proposed Soent fuel rack enrichment licensing action and support information. limit chanae was submitted February 1. 1996.

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. N/A

6. The number of fuel assemblies:

a) in the core 133 Assemblies b) in the spent fuel pool 618 Assemblies c) spent fuel pool storage capacity 1083 Assemblies

! 7. The projected date of the last refueling that can i be~ discharged to the spent fuel pool assuming the present licensed capacity. 2007 Outaae l

Prepared by [4El - / ta - L Date v3 / 6 q 7,