LIC-96-0084, Monthly Operating Rept for May 1996 for Fort Calhoun Station Unit 1

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

ML20112J732
Person / Time
Site:	Fort Calhoun
Issue date:	05/31/1996
From:	Lippy D, Tira Patterson OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-96-0084, LIC-96-84, NUDOCS 9606210031
Download: ML20112J732 (7)

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Omaha Public PowerDistrict 444 South 16th Street Mall Omaha NE68102-2247 June 13, 1996 LIC-96-0084 U. S. Nuclear Regulatory Commission Attn: Document Control Desk

' Mail Station P1-137 Washington, D.C. 20555

Reference:

Docket No. 50-285

SUBJECT:

May 1996 Monthly Operating Report (MOR)

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

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

If you should have any questions, please contact me.

Sincerely, Q,{ -- - -

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 INPO Records Center 9606210031 960531 PDR ADOCK 05000205 45 5124 -

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>LIC-96-0084 Enclosure Page 1 OMAHA PUBLIC POWER DISTRICT  !

Fort Calhoun Station Unit No. 1 I i May 1996 Monthly Operating Report

1. OPERATIONS

SUMMARY

I During the month of May 1996, the Fort Calhoun Station (FCS) operated at a nominal 100% power until 2105 hours0.0244 days <br />0.585 hours <br />0.00348 weeks <br />8.009525e-4 months <br /> on May 24th, when power was reduced to 95% for the end-of-cycle Moderator Temperature Coefficient (MTC) test.

At 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> on May 27th, power was returned to a nominal 100% for the '

remainder of the month. Nonnal plant maintenance, surveillance, equipment rotation activities and scheduled on-line modifications were performed during the month.

On May 2nd at 1610 hours0.0186 days <br />0.447 hours <br />0.00266 weeks <br />6.12605e-4 months <br />, a four-hour notification was made to the NRC pursuant to 10CFR50.72(b)(2)(iii)(A) for an error in the Technical Data Book (TDB) procedure, TD3-V.9, Shutdown Margin Worksheet. An investiga-tion of previous usages of the procedure determined that during Cycle 14 7 (August 25,1992) while performing rod testing, the required 4% shutdown

! margin was not maintained. Technical Specification 2.10.2(1) states "Whenever the reactor is in hot shutdown, hot standby or power operation conditions, the shutdown margin shall be t 4.0% ak/k. With the shutdown i margin < 4% ak/k, initiate and continue boration until the required shutdown margin is achieved." The minimum value of shutdown margin was estimated to be 3.35%. An investigation revealed no other violations of

• the shutdown margin requirement.

On May 26th at 0343 hours0.00397 days <br />0.0953 hours <br />5.671296e-4 weeks <br />1.305115e-4 months <br />, the Nebraska State Patrol notified the FCS Control Room that a boating accident occurred near the plant about one-half mile downstream. The injured people were taken ashore just south of the Security Building which is outside the protected area but on the owner-controlled property. A four-hour notification was made to the NRC pursuant to 10CFR50.72(b)(2)(vi) for offsite notification.

Seventeen (17) additional incore detectors failed in May 1996, rendering fifteen (15) of the t'wenty-eight (28) detector. strings inoperable.

Because less than 75% of the total incore strings are operable, an -

increase of 1% to the total uncertainties has been applied to the planar, integrated and total radial peaking factors as a conservative measure.

The frequency for surveillance test RE-ST-RX-0001, Determination of the Total Integrated and Planar Radial Peaking Factors, has been increased from monthly to a minimum of once every 15 days. All failures have  ;

occurred in detectors that were installed during the 1995 refueling outage. Tnese failures are under investigation with assistance from  ;

ABB/CE and the incore detector vendor.

0 1 .

LIC-96-0084 Enclosure Page 2

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

3. RESULTS OF LEAK RATE TESTS The Reactor Coolant System (RCS) leak rate was relatively steady through-out the month continuing the trend of minimal RCS leakage following the March 1996 scheduled maintenance outage. The May daily leak rates were steady at a nominal rate of 0.1 gpm, with no degrading trends noted.

4. CHANGES. TESTS AND EXPERIMENTS RE0VIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment No. Qgscription None

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

- Removed insulation to identify steam leak on HCV-1042A

- Cleaned out moisture in sensing lines for Toxic Gas Monitor YIT-6288B

- Replaced Raw Water Pump AC-10D

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 J

ATTACHMENT I OPERATING DATA REPORT DOCKET NO. 50-285 1 UNIT YUMT DALHOUN STATION '

l DATE JUNE 05,1996 COMPLETED BY D. L. LIPPY i OPERATING STATUS TELEPHONE (402) 533-6843

l. Unit Name: FORT CALHOUN STATION

2. Reporting Period: MAY 1996 NOTES

3. Licensed Thermal Power (MWt): 1500  !

4. Nameplate Rating (Gross MWe): ~~5{_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 3647.0_ 198841.0_.

12. Number of Hours Reactor was Critical 744.0 3412.7 157120.7

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

14. Hours Generator On-line............. 744.0 3386.1 155366.6 '

15. Unit Reserve Shutdown Hours......... .0 .0~ .0

16. Gross Thermal Energy Generated (MWH) ~~1109309.8~ 4970738.l 207657046.4

17. Gross Elec. Energy Generated (MWH).. 375488.0 1685032.0 68618757.2

18. Net Elec. Energy Generated (MWH).... 358517.3 1608647.0 65466015.8

19. Unit Service Factor................. 100.0 92.8 78.1

20. Unit Availability Factor............ 100.0 92.8 78.1  ;

21. Unit Capacity Factor (using MDC Net) 100.8 92.3 71.1

22. Unit Capacity Factor (using DER Net) 100.8 92.3 69.5

23. Unit Forced Outage Rate............. .0 1.0 3.9 Shutdowns scheduled over next 6 months (type, date, and duration of each):

~

24.

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

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

26. Units in test status (prior to comm. oper.): Forecast Achieved j l

i INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMMERCIAL OPERATION

ATTACHMENT II AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT FORT CALHOUN STATION DATE JUNE 05,1996 .

COMPLETED BY D. L. LIPPY TELEPHONE (402) 533-6843 MONTH MAY 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL '

(MWe-Net) (MWe-Net) ,

1 487 17 482 2 486 18 481

.3 486 19 479 4 487 20 479 t

5 487 21 479 6 486 22 480 7 486 23 478 8- 486 24 478 9 485 25 458 s

10 485 26 458 11 486 27 479

12 486 28 484

$ 13 486 29 484 i'

14 484 30 484 i

15 484 31' 483

. 16 484 ,

1 l l

INSTRUCTIONS 4

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! 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.

, 1

ATTACHMENT III DOCKET NO.'50-285 .-

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

DATE June 5. 1996 -

L. COMPLETED BY D. L. Lippy .

TELEPHONE (402) 533-6843 REPORT MONTH May 1996-

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i 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)

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.. ' ' Attachment IV Refueling Information Fort Calhoun Station Unit No. 1 Report for the month ending: May 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 Yes license amendment?

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.

2) Allow use of ZIRL0* 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 the core reload?

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

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

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

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

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 be discharged to the spent fuel pool assuming the 2007 Outage present licegd capacity.

Prepared -

-- Date: /r