LIC-96-0096, Monthly Operating Rept for June 1996 for Fort Calhoun Station Unit 1

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Monthly Operating Rept for June 1996 for Fort Calhoun Station Unit 1
ML20115F845
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 06/30/1996
From: Lippy D, Tira Patterson
OMAHA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-96-0096, LIC-96-96, NUDOCS 9607180120
Download: ML20115F845 (8)
v • d • e


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  • , I l i e a muur Omaha Public PowerDistrict 444 South 16th Street Mall Omaha NE68102-2247 July 15, 1996 LIC-96-0096 l

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U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, D.C. 20555

Reference:

Docket No. 50-285 i

SUBJCCT: June 1996 Monthly Operating Report (MOR) l l

l Enclosed please find the June 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.

Sincerely, l

l F#/

l T. L. Patterson Division Manager Nuclear Operations i

l TLP/dll Enclosures c: Winston & Strawn L. J. Callan, NRC Regional Administrator, Region IV j L. R. Wharton, NRC Project Manager W. C. Walker, NRC Senior Resident Inspector R. J. Simon, Westinghouse INP0 Records Center f

9607180120 960630 PDR ADOCK 05000285 dgM

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R PDR 45 5124 Employrrent with Equal Opportunity l

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'LIC-96-0096 .

l Enclosure Page 1 l l

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

1. OPERATIONS

SUMMARY

During the month of June 1996, the Fort Calhoun Station (FCS) operated at a nominal 100% power until 1741 hours0.0202 days <br />0.484 hours <br />0.00288 weeks <br />6.624505e-4 months <br /> on June 7th, when one of four Reactor Coolant Pumps (RCP), RC-3B, was verified to have excessive vibration. Abnormal Operating Procedure A0P-5, Emergency Shutdown, was entered to reduce power and remove RC-3B from service. At 1920 hours0.0222 days <br />0.533 hours <br />0.00317 weeks <br />7.3056e-4 months <br />, the reactor was made subcritical. The plant was taken to Cold Shutdown for repair of the RC-3B motor Anti-Reverse Rotation Device (ARD) and bearing l

disassembly, inspection and cleaning. Following completion of repairs to the RC-3B motor, the reactor was made critical on June 21, 1996. Power was returned to a nominal 100% on June 26th at 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br />. Normal plant maintenance, surveillance, equipment rotation activities and scheduled on-line modifications were performed during the month.

On June 5th at 0349 hours0.00404 days <br />0.0969 hours <br />5.770503e-4 weeks <br />1.327945e-4 months <br />, a 1-hour notification was made to the NRC pursuant to 10CFR50.72(b)(1)(v), Lost Emergency Notification System (ENS).

The notification was made using the alternate phone because the handset on the primary phone was inoperable. It was determined that a button to the headset was depressed, cutting out the handset. The FCS ENS was returned to service at 0556 hours0.00644 days <br />0.154 hours <br />9.193122e-4 weeks <br />2.11558e-4 months <br /> on June 5th.

On June 10th at 1325 hours0.0153 days <br />0.368 hours <br />0.00219 weeks <br />5.041625e-4 months <br />, a four-hour notification was made to the NRC l pursuant to 10CFR50.72(b)(2)(vi), Offsite Notification. The media was informed via a written press release that the nuclear station was shutdown on June 7th due to the vibration problem noted above on RCP RC-3B.

During a structural inspection of the Auxiliary Building using the Maintenance Ru1e procedure SE-PM-AE-1001, Auxiliary Building Structural Inspection, it was identified that three of the four pressure relief panels in the south end of the floor in Room 81 had structural steel equipment supports and braces attached to their top surfaces with .

! expansion anchor bolts. This condition made the panels incapable of I l providing sufficient vent area to limit the differential pressure in the event of a tornado. On June 15th at 2251 hours0.0261 days <br />0.625 hours <br />0.00372 weeks <br />8.565055e-4 months <br />, a four-hour notification was made to the NRC pursuant to 10CFR50.72(b)(2)(1), Degraded While Shutdown. The structural obstructions were removed and compensatory I actions implemented. Details of this condition and corrective actions 1 will be provided in Licensee Evcnt Report (LER)96-005.

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  • LIC-96-0096 i Enclosure '

Page 2

2. SAFETY VALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED On June 19th, during RCS pressurization in preparation for an inservice test, a Power Operated Relief Valve (PORV) Pre-trip Alarm was received.

, With the RCS at 439'F and 1630 psia, both PORVs opened momentarily due to i_ an anomalous Low Temperature Over-Pressurization (LTOP) signal. from l Channel 2. The PORVs closed as expected. It was determined that the l Channel 2 LTOP circuit had failed. Corrective actions were taken and the j RCS was increased to normal operating temperatures and pressures.

During the month of June, no other challenges or failures occurred for the  !

l PORVs or primary system safety valves.

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3. RESULTS OF LEAK RATE TESTS The RCS leak rate was variable during June 1996 with the forced shutdown l to repair the ARD on RCP RC-38. During periods of steady state operation, the trend of minimal RCS leakage following the March 1996 outage continued. No degrading trends were noted this month and the RCS continues to operate with minimal leakage.
4. CHANGES. TESTS AND EXPERIMENTS RE0VIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment No. Descriotion None
5. SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE MONTH OF JUNE 1996 Replaced Component Cooling Water Heat Exchanger AC-1A Raw Water
Inlet Valve Solenoid Valve HCV-2880A-20 Replaced check source mechanism and realigned Containment Noble Gas Radiation Monitor Remote Ratemeter RM-051 Adjusted oil relief valve to raise oil pressure on Charging Pump CH-IC i -

Replaced shuttle valve disc and 0-rings on Containment Purge Air

. Outlet and Inlet Inboard Isolation Valves PCV-742A and PCV-742C j

Replaced Channel 2 LTOP Module PM-105B/TM-123B

LIC-96-0096 l Enclosure Page 3

6. OPERATING DATA REPORT Attachment I
7. AVERAGE DAILY UNIT POWER LEVEL Attachment II
8. UNIT SHUTDOWNS AND POWER REDUCTIONS Attachment III 9.

REFUELING INFORMATION. FORT CALHOUN STATION UNIT NO. 1 Attachment IV

ATTACHMENT I

. OPERATING DATA REPORT DOCKET NO. 50-285 UNIT FORT CALHOUN STATION DATE JULY 09,1996 COMPLETED BY D. L. LIPPY OPERATING STATUS TELEPHONE (402) 533-6843

l. Unit Name: FORT CALHOUN STATION
2. Reporting Period: JUNE 1996 NOTES
3. Licensed Thermal Power (MWt): 1500
4. Nameplate Rating (Gross MWe): 502
5. Design Elec. Rating (Net MWe): 478
6. Max. Dep. Capacity (Gross MWe): 502
7. Max. Dep. Capacity (Net MWe): 478
8. If changes occur in Capacity Ratings (3 through 7) since last report, give reasons:

N/A _

9. Power Level to which restricted, if any (Net MWe): N/A
10. Reasons for restrictions, if any:

N/A THIS MONTH YR-TO-DATE CUMULATIVE

11. Hours in Reporting Period........... 720.0

~

4367.0 199561.0

12. Number of Hours Reactor was Critical 282.1 3794.8 157502.8
13. Reactor Reserve Shutdown Hours...... ~

.0 .0 1309.5

~

14. Hours Generator On-line............. 367.8-- 3753.9 155734.4
15. Unit Reserve Shutdown Hours......... .0 .0

.0

16. Gross Thermal Energy Generated (MWH) 489182.9 5459921.0 208146229.3
17. Gross Elec. Energy Generated (MWH).. 160172.0 1845204.0 68778929.2
18. Net Elec. Energy Generated (MWH).... 151663.8 1760310.8 65617679.6
19. Unit Service Factor................. 51.1 86.0 78.0
20. Unit Availability Factor............ 51.1 86.0 78.0
21. Unit Capacity Factor (using MDC Net) 44.1 84.3 71.0
22. Unit Capacity Factor (using DER Net) 44.1 84.3 69.4
23. Unit Forced Outage Rate............. 48.9 9.4 4.1
24. Shutdowns scheduled over next 6 months (type, date, and duration of each):

l REFUELING OUTAGE SCHEDULED TO COMMENCE ON SEPTEMBER 21, 1996, WITH A l PLANNED DURATION OF 42 DAYS.

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

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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 DOCKET NO. 50-285 UNIT FORT CALHOUN STATION DATE JULY 09,1996 COMPLETED BY D. L. LIPPY I TELEPHONE (402) 533-6843 i

l MONTH JUNE 1996 l l

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! DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL ,

l (MWe-Net) (MWe-Net) i l 1 482 17 0 I 2' 481 18 0 I 3 481 19 0 '

l 4 482 20 0 5 482 21 0 J

)

6 -

480 22 25

! 363 23 7 103 8 0 24 192 ]

1 l 9 0 25- 423 )

10 0 26 467 11 0 27 466 12 0 28 465 ~~

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! 13 0 29 464 14 0 30 463 15 0 31 n/a l l 16 0 l

INSTRUCTIONS i

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

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ATTACHMENT III DOCKET NO. 50-285 -

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

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DATE July 9.1996 COMPLETED BY D. L. Liooy .

TELEPHONE (402) 533-6843 REPORT MONTH June 1996 Typd iDurationi iReaso? iLicenseej ~

.-No.  ::Datei (Methods  ; System:- dComponent"

  • Cause & Correctivel

.foft ' iCod h "

i (Hours);f 'LEvent1' S CodeN '

': Action tos h prevent' Recurrencet y Shutting::  ; Report 1: '

g- ~ -

/ Reactor81 96-03 960607 F 352.2 A 1 N/A ZZ ZZZZZZ At 1741 hours0.0202 days <br />0.484 hours <br />0.00288 weeks <br />6.624505e-4 months <br /> on June 7,1996, the FCS coninenced power reduction due to high vibrations on reactor coolant pump (RCP) RC-38. A0P-5, Emergency Shutdown, was entered to reduce power and remove RC-3B from service. The RC-3B motor anti-reverse rotation device (ARD) was replaced and the  ;

bearings were disassembled, inspected and cleaned.

The other RCP motors were checked and found to have no discrepancies. Following completion of the repairs to RC-3B motor, the plant was placed on-line on June 22,1996 at 1116 hours0.0129 days <br />0.31 hours <br />0.00185 weeks <br />4.24638e-4 months <br />. A nominal 100% power was achieved on June 26th.

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-0perator Training & License Examination F-Administrative 5 H-0ther (Explain) Exhibit H - Same Source (9/77)

. Attachment IV Refueling Information Fort Calhoun Station Unit No. 1 Report for the month ending: June 30.1996

1. Scheduled date for next refueling shutdown. September 21,1996
2. Scheduled date for restart following refueling. November 2,1996 l 3. Will refueling or resumption of operations thereafter l require a technical specification change or other Yes j license amendment?

l a. If answer is yes, what, in general, will these be? 1) Enrichment limit of spent fuel racks is to be increased to at least 4.5 w/o from 4.2 w/o. This is necessary based upon the preliminary Cycle 17 core pattern development.

l 2) Allow use of ZIRLO' fuel cladding.

b. If answer is no, has the reload fuel design and core configuration been reviewed by your Plant N/A Safety Review Committee to determine whether any unreviewed safety questions are associated with I

the core reload?

c. If no such review has taken place, when is it scheduled? N/A l 4. Scheduled date(s) for submitting proposed licensing 1) Spent fuel rack enrichment I action and support information, limit change was submitted l

February 1,1996.

i 2) ZIRLO' change scheduled for submittal by July 15, 1996.

l 5. Important licensing considerations associated with l refueling, e.g., new or different fuel design or N/A l supplier, unreviewed design or performance analysis methods, significant. changes in fuel design, new operating procedures, j

6. The number of fuel assemblies: )

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

7. The projected date of the last refueling that can be  !

discharged to the spent fuel pool assuming the 2007 Outage i present licensed capacity.

i l 4 Prepared by: C A E_ M_ Date: 7-9-*.  ;

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