ML20046D233

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Monthly Operating Rept for Jul 1993 for Fort Calhoun Station Unit 1.W/930813 Ltr
ML20046D233
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 07/31/1993
From: Gates W, Howman M
OMAHA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-93-0221, LIC-93-221, NUDOCS 9308160377
Download: ML20046D233 (7)
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{{#Wiki_filter:_- -- e Omaha Public Power District 444 South 16th Street Mall Omaha. Nebraska 68102-2247 402/636-2000 August 13, 1993 LIC-93-0221 ,. U. S. Nuclear Regulatory Commission ATTN: Document Control Desk . Mail Station PI-137 Washington, DC 20555

Reference:

Docket No. 50-285 Gentlemen:

SUBJECT:

July 1993 Monthly Operating Report (HOR) Enclosed is the July 1993 MOR for Fort Calhoun Station (FCS) Unit No. I as , required by FCS Technical Specification Section 5.9.1. If you should have any questions, please contact me. Sincerely, 

       /A/.

W. G. Gates Vice President WGG/pjc  ; Enclosures c: LeBoeuf, Lamb, Leiby & MacRae J. L. Milhoan, NRC Regional Administrator, Region IV S. D. Bloom, NRC Project Manager R. P. Mullikin, NRC Senior Resident Inspector ' R. T. Pearce, Combustion Engineering R. J. Simon, Westinghouse Office of Management & Program Analysis (2)- INP0 Records Center l l 9308160377 930731 E PDR ADOCK 05000285 e  ! <s594 R PDR (6,ppgggg"*"a* 3 l 170014  ; I

i ' OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 July 1993 Monthly Operating Report  ;

1. OPERATIONS

SUMMARY

i Nominal full power operation continued through the month of July. The station was moderately impacted by high Missouri River level throughout ' most of the month due to abnormally high rainfall amounts. On July 9,  : 1993, river level was high enough to flow into both east and west chemical , lagoons. Portions of the parking lot were also flooded. The river receded below lagoon level on July 11. On Jul 16, the river level again  : reached that of the chemical lagoons. By Jul 19, the river receded and , _ remained below lagoon level for the rest of t e month. No nuclear safety '! related functions were threatened. l On July 8, OPPD was notified that 10 of 10 candidates passed the NRC i license examinations. This resulted in the addition of five (5) new R0  : licenses, three (3) Instant SRO Licenses and two (2) SR0 Upgrade Licenses. The start of the next refueling outage has been deferred one week because of the June 24, 1993 reactor trip. Breakers are now scheduled to open on September 25, 1993. . The following NRC inspections were completed during this reporting period: IER No, peScription e 93-05 Annual Emergency Preparedness Exercise 93-11 Monthly Resident Inspection l 93-12 Special Inspection on June 24, 1993 Plant Trip -{ 

                                                                                         -i The following LERs were submitted during this reporting period:                   l LER No. Description                                                          !

93-010 Failure to Address low Halon Tank Pressure following Surveillance Test. i 93-011 Reactor Trip on Loss of Load During Switchyard Maintenance 

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2. SAFETY VALVES OR PORY CHALLENGES OR FAILURES WHICH OCCURRED ,

1 No PORV or Safety Valve failures or challenges occurred.this month. ,

3. RESULTS OF LEAK RATE TESTS  !

RCS leak rate was less than 0.200 gpm for most of the month of July. For j the first 10 days-of July, the leak rate data was erratic because of the power increase following recovery from the June 24, 1993 reactor trip. . With the return to steady state conditions, the leak rate has remained 

           . steady throughout the remainder of the month.
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Monthly Operating Report LIC-93-0221 Page Two 1 1

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

Amendment No. Description 

                                                                                         ]

153 The amendment revises the Technical Specifications to l increase the maximum bypass pressure for the Steam Generator Low-pressure Signal (SGLS) trip setting from 550 psia to 600 psia.

5. SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE MONTH OF JULY 1993 e Repaired Battery Charger #2 ampere indication by replacing a circuit board on the QSPDS Channel B (Al-208B).

t e Replaced Circuit Breaker (MCC-381-004) on the Nuclear Detector Well Cocling Unit (VA-12A). e Replaced Raw Water Pressure Controller Isolation Valves (RW-PC-2862-B, 2863-B, 2864-B, 2865-B, 2866-B, 2867-B, 2868-B, 2869-B, 2870-B, 2871-B, 2872-B and 2873-B).

  • Replaced the air receiver drain lines with new chrome-moly lines on the Diesel Generator Secondary Starting Air Receivers (SA-3A-1, 38-1).
  • Replaced the air receiver drain lines with new chrome-moly lines on the Diesel Generator Primary Starting Air Receivers (SA-4A-1, 4A-2, 4B-1 and 4B-2).

e Preliminary work commenced on the 161kV electrical system modification , which involves ring bus work in the switchyard for the addition of a l second 161kV line.

6. OPERATING DATA REPORT Attachment I
7. AVERAGE DAILY UNIT POWER LEVEL j Attachment II
8. UNIT SHUTDOWNS AND POWER REDUCTIONS i Attachment III ,
9. REFUELING INFORMATION. FORT CALHOUN STATION UNIT NO. 1 Attachment IV s

i r 

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ATTACHMENT I OPERATING DATA REPORT DOCKET NO. 50-285 -' UNIT FORT CALHOUN STATION DATE AUGUST 0_g 1993 l COMPLETED BY M. A. HOWMAN , OPERATING STATUS TELEPHONE 4 2-533-6939

1. Unit Name: FORT CALHOUN STATION
2. Reporting Period: JULY 1993 NOTES .
3. Licensed Thermal Power (MWt): 1500
4. Nameplate Rating (Gross MWe): 50_2_
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........... 744.0 5087.0 174001.0
12. Number of Hours Reactor was Critical 744.0 4877.6 135487.9
13. Reactor Reserve Shutdown Hours...... .0 .0 1309.5
14. Hours Generator On-line............. 744.0 4847.6 133910.8-
15. Unit Reserve Shutdown Hours......... .0 .0 .0 .
16. Gross Thermal Energy Generated (MWH) 1107027.4 6726748.5~ _176292224.5
17. Gross Elec. Energy Generated (MWH).. 365190.0 2250570.0 58091370.2 18.~ Net _Elec. Energy-Generated (MWH).... 350269.6 2149660.4 55420547.3
19. Unit Service Factor................. 100.0 95.3 77.0
20. Unit Availability Factor............ '100.0 95.3 77.0
21. Unit Capacity Factor (using MDC' Net) 98.5 88.4 69.1
22. Unit Capacity Factor (using DER Net) 98.5 88.4 67.4
23. Unit Forced Outage Rate............. .0 1.4 4.3
34. Shutdowns scheduled over next 6 months (type date,.and durationtof each):

_ REFUELING OUTAGE SCHEDULED TO BEGIN SEPTEMBER 25, 1993 AND LAST APPROXIMATELY_56_ DAYS. -l '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  ! l 

   . - *-                         ATTACHMENT II AVERAGE DAILY UNIT POWER LEVEL                            <

i DOCKET NO. 50-285  ! UNIT FORT CALHOUN STATION DATE AUGUST 09,1993 COMPLETED BY M. A. HOWMAN TELEPHONE 402-533-6939 MONTH JULY 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) { 1 380 17 477 

                                                                                   'i 2               472                        18              477 3               474                        19             -475                 !

4 473 20 474 5 472 21 475 6 473 22 475 4 7 474 23 475 8 473 24 475 9 474 25 473  : 10 472 26 472 11 472 27 473 12 473 28 472  ; 13 474 29 472 14 476 30 472 ' 15 - 477 31 470 16 477 INSTRUCTIONS j Onithis form, list the average daily unit power level in MWe-Net for.each q day in the reporting month. Compute to the nearest whole megawatt. I i i 1 m gn 4

ATTACHMENT III DOCKET NO. 50-285 . UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Fort Ca houn St.- DATE bucust :,0. 1993 . COMPLETED BY M. A. Howman TELEPHONE (402) 533-0939 REPORT MotRH July 1993 No. Date Type' Durstion Reason

  • Method of 1.icensee System Component Cause & Corrective (Hours) Shutting Event Code
  • Code' Action to Down Reacter8 Report # Prevers Recurrence None During July 1993, the plant operated at a nominal 100% power.

1 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions 5: 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 (NUREG4)l61) D-Regulatory Restriction 4-Other (Explain) Froperator Training & License Examination F-Administrative 5 G-Operational Error (Explain) - Exhibit 1 - Same Source H-Other (Explain) (9/77) a - -- _ - _ __. -__ - 

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Attachment IV 

                .                          Refueling Information Fort Calhoun - Unit No. 1 Report for the month ending July 1993
1. Scheduled date for next refueling shutdown. September 25, 1993  ;
2. Scheduled date for restart following refueling. November 1993 ,
3. Will refueling or resumption of operations thereafter require a technical specification i change or other license amendment? Yes
a. If answer is yes, what, in general, will +

these be? Administrative < controls revision - l regarding reload . J analysis methodology changes.

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 i, i
c. If no such review has taken place, when is it i scheduled? N/A -
4. Scheduled date(s) for submitting proposed licensing action and support information. Auoust 1993
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 i
design, new operating procedures. None Planned ,
6. The number of fuel assemblies: a) in the core 133 Assemblies in the spent' 529 Assemblies b) fuel pool c) spent fuel pool t storage capacity 729 Assemblies  !

d) planned spent Planned to be fuel pool increased with high storage capacity density spent fuel j racks. ,

7. The )rojected date of the last refueling that can be disciarged to the spent fuel pool assuming the j present licensed capacity. 1995* l 1

0 Capability of full core offload of 133 assemblies lost. Reracking to be performed between l the 1993 and 1995 Refueling Outages. ) Prepared by 8 C b Date 8d'D 1 1  : 

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