LIC-96-0016, Monthly Operating Rept for Jan 1996 for Fort Calhoun Station Unit 1

Monthly Operating Rept for Jan 1996 for Fort Calhoun Station Unit 1

ML20100F736
Person / Time
Site:	Fort Calhoun
Issue date:	01/31/1996
From:	Lippy D, Tira Patterson OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-96-0016, LIC-96-16, NUDOCS 9602220100
Download: ML20100F736 (8)

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_ _ _ _ _ . _ . . __._.._a a u:u Omaha Public Power District 444 South 16th Street Mall Omaha, Nebraska 68102-2247 402/636-2000 February 15, 1996 LIC-96-0016 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, D.C. 20555

Reference:

Docket No. 50-285

SUBJECT:

January 1996 Monthly Operating Report (M0R)

Enclosed please find the January 1996 MOR for Fort Calh'oun Station (FCS)

Unit No. 1 as required by FCS Technical Specification 5.9.1.

If you should have any questions, please contact me.

Sincerely, t

)q g) C L_ _. m%

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. Simon, Westinghouse INP0 Records Center 9602220100 960131 PDR ADOCK 05000285 R PDR 45 5124 Employment with Equal opportunity

e LIC-96-0016 Enclosure Page 1 OMAHA PUBLIC POWER DISTRICT I Fort Calhoun Station Unit No. 1 JANUARY 1996 l Monthly Operating Report

1. OPERATIONS

SUMMARY

During the month of January 1996, the Fort Calhoun Station (FCS) operated at a nominal 100% power. Normel plant maintenance, surveillance, equipment rotation activities and scheduled on-line modifications were performed during the month. Monitoring of a minor Control Element Drive Mechanism (CEDM) mechanical seal leak continued.

On January 19th, an ice jam formed upstream of Sioux City, Iowa, causing Missouri River levels to lower approximately five feet over a 24-hour period.

Preparations were made to respond to potential icing or low river level ,

conditions. On January 19th, the low river level Abnormal Operating Procedure (A0P-01) was implemented when it was projected that the river level would drop below 983 feet above sea level. As required by the procedure, the U. S. Army Corps of Engineers was requested to increase releases from Gavins Point Dam on January 20th. The Corps could not comply because flooding would occur upstream of the ice jam. Pursuant to 10CFR50.72(b)(2)(vi), a four-hour non-emergency notification was subsequently made to the NRC to report the off-site notification made to the U.S. Army Corps of Engineers. The FCS Technical Specifications require the reactor to be placed in cold shutdown if the river level is less than 976 feet, 9 inches. The lowest actual river level observed at FCS during this event was 982 feet, 6 inches with the level returning to normal after two days.

On January 24th, approximately 50 gallons of hydrazine leaked from a hydrazine storage container into the Turbine Building. Hazardous Materials personnel responded to isolate and clean up the spill. The spill exceeded the State limit, therefore, a notification was made to the State of Nebraska.

A four-hour non-emergency report was made to the NRC pursuant to 10CFR50.72(b)(2)(vi).

Several of the incore nuclear detectors have recently failed rendering 2 of the 28 strings of detectors inoperable. These failures occurred in new detectors that were installed during the 1995 refueling outage. These failures are under investigation with assistance from ABB/CE and the detector vendor.

r LIC-96-0016 Enclosure

< Page 2 e

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

3. RESULTS OF LEAK RATE TESTS l Although above normal, the January Reactor Coolant System (RCS) leak rate was steady at approximately 0.30 gpm throughout the month. This leak rate has remained relatively steady following the reactor trip on August 26, 1995.

Several increases in the leak rate were related to charging pump packing leaks during the month. Two charging pumps were repacked during January 1996 which returned the leak rate to a nominal 0.25 - 0.30 gpm.

The major contributor of the RCS leakage is "Known" leakage which is being collected in both the Reactor Coolant Drain Tank (RCDT) and the Pressurizer Quench Tank. The primary leakage source for "Known" leakage has been attributed to CEDM #15. The "Known" leak rate has decreased over the last i several months from 0.28 gpm to approximately 0.15 gpm. In addition to CEDM

1. 15, several of the reactor head vent system isolation valves are also leaking slightly with leakage being collected both in the Containment Sump and the Pressurizer Quench Tank. Leakage to the Containment Sump is considered " Unknown" leakage.

4. CHANGES. TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment No. Description None i

I

5. SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE MONTH OF JANUARY 1996

- Due to the possibility of the piston and actuator shaft being mis-aligned, the Bettis Actuators on certain inlet / outlet isolation valves on the Component Cooling Water (CCW) Heat Exchangers were inspected and rebuilt as necessary to ensure proper alignment.

- The tubes on CCW Heat Exchanger AC-1C were cleaned and the associated Raw Water Inlet Valve HCV-2882A was rebuilt.

- Charging Pumps CH-1B and CH-1C were repacked due to excessive RCS leakage. l

- Raw Water Pump AC-10B was replaced with a rebuilt pump assembly. I 1

4 LIC-96-0016' Enclosure- ,

Page 3 .,

6. OPERATING DATA REPORT Attachment I i

7. AVERAGE DAILY UNIT POWER LEVEL Attachment II

- 8. UNIT SHUTDOWNS AND POWER REDUCTIONS t

Attachment III ,

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

a i'

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, i.

ATTACHMENT I ,

t

-OPERATING DATA REPORT DOCKET NO. 50-285 UNIT. FORT CALHOUN STATION DATE FEBRUARY _05,1996 COMPLETED BY D. L. LIPPY .,

I OPERATING STATUS TELEPHONE (402) 517!66TT-~ l

. 1. Unit Name: FORT CALHOUN STATION f 2.. Reporting Peifod: JANUARY 1996 NOTES ,

, 3. Licensed Thermal Power (MWt): 1500 [

3 '4. Nameplate Rating .(Gross MWe): 502,  ;

5. Design Elec. Rating (Net MWe):

478 i 6.~ Max..Dep. Capacity (Gross MWe): 50_2,  ;

7. Max. Dep. Capacity (Net MWe): 478 l l 8. If. changes occur in Capacity Ratings (3 through 7) since last report, give reasons:

N10% i

9. Power Level to which restricted, if any (Net MWa)

N/A 1

. 10. Reasons for restrictions, if any:

N61 THIS MONTH YR-TO-DATE. CUMULATIVE j

11. Hours in Reporting Period........... 744.0 744.0 195938.0  ;

i

12. Number of Hours Reactor was Critical 744.0 744.0 154452.0  :

^

13. Reactor Reserve Shutdown Hours...... .0 .0 __13dyIS

14. Hours Generator On-line............. 71T!0 744.0~ 152724.$[

15. Unit Reserve Shutdown Hours......... .6 .0 .d' i

16. Gross Thermal Energy Generated (MWH) fff3114.0

~

1113114.0 203799422.3 I

^

17. Gross Elec. Energy Generated (MWH).. 379148.0 379148.0 ~67312873.2~

18. Net Elec. Energy Generated (MWH).... 31Fifs~776 362T57T6~ ~64 2196Y674

19. Unit Service Factor................. 100.0 100.0 7'7.9

20. Unit Availability Factor............ 100.0 100.0

~

77.9

, 21. Unit Capacity Factor (using MDC Net) 101.9 101I9- 70.8 .

I 22. Unit Capacity Factor (using DER Net) 101.9 101.9 69.2~

23. Unit Forced Outage Rate............. .0 .0 4 . d~ 1 l

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

A MAINTENANCE OUTAGE IS SCHEDULED TO OCCUR FROM_ MARCH 16-23, 1996 TO RE-PAIR / REPLACE DEGRADING CEDM__ MECHANICAL SEALS. I 4  ;

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 i

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., .=

ATTACHMENT II AVERAGE DAILY UNIT POWER LEVEL 50-285 DOCKET NO.

UNIT FORT CALHOUN STATION DATE FEBRUARY 6$7ffi6 COMPLETED BY D. L. LIPPY TELEPHONE (402) 533-6843-L I

MONTH JANUARY 1996 4

i ' DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY PONER LEVEL (MWe-Net) (MWe-Net) 1 487 17 487 i 2 487 18 487 3 487 19 487

, -4 487 20 487 5- 486 21 487  :

~

6 486 22 487 7 486 23 487 8 487 24 487 9 487 25 487 ,

10 487 26 487 i

11 487 27 487 '

j 12 487 28 487 13 487 29 486 l 14 487 30 486 15 487 31 486 1

16 487 l

l 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.

ATTACHMENT III DOCKET NO. 50-285 '

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

• DATE February'5. 1996 -

l l COMPLETED BY D. L. Liony l TELEPHONE (402) 533-6843 ,

REPORT MONTH January 1996 liNeh iDatei Tyyd M atton-  ; Reaso6 5;Methodi OLicensee- 1 System; (Camponent ~ ' LChase & Correctlie r

' iofi.

k(Nours)f 3 Event !  ? Ce(' ^

' 7 Codd!

i Action to ? "w

1- Shutting) > Report (; Prevent. Recurrence Down4 , -; No. _

3.g ,

JReactos'; - '

~

NONE L

1 2 3 4 F: F_orced 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)

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Attachment IV Refueling Information J Fort Calhoun Station - Unit No. 1 Report for the month ending January 31. 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 spent these be? fuel racks is to be increased to at least 4.5 w/o from 4.2 w/o. This is necessary based upon the oreliminary Cycle 17 core

' pattern develooment.

b. If answer is no, has the reload fuel design 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 chance 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 i 6. The number of fuel assemblies

l 4 a) in the core 133 Assemblies b) in the spent fuel pool 618 Assemblies c) spent fuel pool storage capacity 1083 Assemblies i

7. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. 2007 Outaae Prepared b ~ CO_ [A a_ _

Date c2,!6!N, 1