ML20090J012

Monthly Operating Rept for Feb 1992 for Fort Calhoun Station,Unit 1

ML20090J012
Person / Time
Site:	Fort Calhoun
Issue date:	02/29/1992
From:	Cavanaugh G, Gates W OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-92-091R, LIC-92-91R, NUDOCS 9203170028
Download: ML20090J012 (9)

Text

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e Omaha Public Power Distrtt 444 South 16th Street Mall Omaha, Nebraska 68102-2247 402/656-2000 March 13, 1992 LIC-92-091R U. S. Nuclear Regulatorv Commission ATTN: Document Control Desk Mail Station PI-137 Washington, DC 20555

Reference:

Docket No. 50-285 Gentlemen:

SUBJECT:

February 1992 Monthly Operating Report (MOR)

. Enclosed is the February 1991 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,

f. h '--

W. G.~ Gates Division Manager Nuclear Operations WGG/sel Enclosures

.c: LeBoeuf Lam S.D. Bloom,b,Leiby&MacRae NRC Project Engineer R. D. Martin, NRC Regional Administrator, Region IV R. P. Mullikin, NRC Senior Resident Inspector D. K..Sentell, Combustion Engineering R. J. Simon, Westinghouse Office of Management & Program Analysis (2)

INP0 Records Centcr American Nuclear Insurers f

45 5124 _ Employment wth Equal Opportunity l/ l.

92031700P8 920229 Mate / Female J

PDR ADOCK 05000285 s- R PDR

. . . - .- - -- . - . -- -. . r OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 FEBRUAItY 1992

, Monthly Operating Report I. OPERATIONS

SUMMARY

Fort Calhoun Station- was operational only - for the first 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> during

-February. The plant was shutdown for the renainder of the month for its  !

Thirteenth Refueling Outaoe. The turbine gener tor output breakers were opened on February .1, 1991. > 515'F and shutdown margin >-4%) the same The day. reactor entered Mode 3 (T*34SSV) ( testing

-commenced while in Mode 3 with Main fiveSteam Safetyvalves of ten Valve (found to be out-of-toleronce. Since Technical Specifications require eight of ton MSSVs to be operable, OPPD made a four hour report to the NRC pursuant to 10 CFR 50.72(b)(2)(1).

After MSSV testing 'was completed, a plant cooldown and RCS boration was initiated per 01-RC-4 being achieved on Febru(ary_2,1992.RCS

~ Mode 4Cooldown)

(T 210*F wlth and shutdown shutdowncooling margin entry conditi

> 3% was achieved on February 4, 1992. Model <(T.< 210* F and refueling boron concentration) was achieved at 11:41 hours the, same day. -

The RCS was taken water solid per 01-RC-4 to cool down the pressuriter on February 5, 1992. After the pressurizer temperature was less than 200*F, a vent path was opened and the pressurizer was drained to 50%. With the pressurizer cooled and vented, the manway was removed on February 6,1992 in preparation for going to midloop < 1010' RCS level). The RCS was taken to midloop for. three and one-half h(ours to dump steam generator tubes,- then returned.to 50%-inventory =in the pressurizer.

On February 7,1992 the RCS was drained to one foot below the Reactor Vessel (RV) flange- in preparation for RV head stud- detension6ng.- Problems were encountered during detensioning of stud #16. The stud required .nuch more torque to remove than did the other studs. Stud removal was completed on February 13 1992. An -investic ation is ongoing to determine the reason for the difficulties with RV stud #16. ' During that time, the 161 kV power source was taken out of-service,to perform a modification which included adding a ring bus. This will allow the 161 kV source to be powered from two separate-

' feeder sources after the completion of a new feeder line to the 161 kV -

substation. The new feeder line is scheduled for completion during the 1993 Refueling Outage.

On February 16, 1992 the RV head was removed and the reactor refueling cavity was filled in preparation for core off-load. Off-load operations commenced-

on - February 20, 1992 -and were completed February 22,'1992. 'During that period all-133 fuel assemblies were transferred from the reactor core to the spent fuel pool.

l On February 23, 1992 the reactor refueling cavity was drained. The RCS level E was damtaken - installation to midloop and(no fuel was in placement of theeqafreactor)for pment thefor steam RV generator nozzle thermal shield L inspection.

On' February 26, 1992 the reactor refueling cavity was refilled. The core support barrel with thermal shield e:as removed from the RV and placed on a rotating inspection stand in the lower cavity.

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i Monfhly Operating Report LIC-92-091R Page 2 During)

(SIRWT the same was time,This drained. the was Safety doneInjection to accommodate and Refueling replacement Water of Tank the SIRWT suction valves LCVa83-1 and 383-2.

On February 28, 1992, the modification to the 161 kV electrical system was com11eted and the 161 kV system was returned to service. Additionally, teding of a temporary diesel was completed. The temporary diesel was installed for the 1992 Outage for use in the event of a loss of off-site sources-and on-site AC power. The temporary diesel will be in tne standby

. mode when DG-1 is taken out of service for maintenance in March.

The following NRC inspections took place during February 1992:

IER NO. IllLE 92-03 Fuel Integrity and Reactor Subcriticality (Initial Phase) 92-06 Inservice Inspection Programs The following LERs were submitted during February 1992:

Report LER No. Date Description 92-01 02/20/92 Unmonitored Release on Loss of 13.8 kV system 92-02 02/26/92 PAL Door Seal 92-03 02/27/92 Missed Fire Watch 92-06 02/24/92 RM-041/42/43 Annunciation Problem A. SAFETY VALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED On February 2, 1992, OP-ST-RC-3004 (PORV Low Temperature, Low Pressure Exercise Test) was successfully completed. This test requires each PORV to be cycled once.

B. RESULTS OF LEAK RATE TESTS Due to the plant shutdown and subsequent cooldown and depressurization for refueling, only ole RCS leak rate test was performed. That test, performed on February 1, determined the total RCS leakrate to be 0.290 gpm. Known leakage was 0.120 gpm and unknown leakage was 0.170 gpm. ,

Repairs to be made during the refueling outage are expected to i

reduce the total RCS leakage to about 25Y. of that recorded on L February 1, 1992, i

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Month *1y Operating Report

'LIC-92-091R Page 3 C. CHANGES TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSIONAUTHORIZATIONPURSUANTTO10CFR50.59 Amendment No. Description None.

D. SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE MONTH OF FEBRUARY 1992 During February- 1992, the Fort Calhoun Station maintenance staff performed many activities to support the refueling outage. Some of the significant safety related maintenance activities performed were:

Completed repairs and post maintenance testing to the inlet valve of the storage pool demineralizer, AC-317.

Completed repairs to charging pump CH-1A Ammeter A/CH-1A.

Replaced' raw water pump AC-10B with a new assembly and adjusted the impeller lift on AC-100 and AC-10D raw water pumps.

Performed NDE Inspection and repacked the HPSI Pump SI-2A Bearing Cooler CCW Outlet Drain Valve, AC-126.

Due to 'the significant maintenance work to be completed on the diesel generators, EDG-1 and EDG-2, Temporary Modification 92-019 was installed into the respective control circuits of each diesel.

This minimizes inadvertent starts of the diesels during the refueling outage. The temporary modification will be removed prior to startup.

Performed maintenance on instrument loop power supplies FQ342, LQ2904X, LQ2944X, LQ2964X and PQ2941.

-Performed maintenance .on - SG-RC-2A Feedwater Isolation Valve HCV-1386.

Replaced Solenoid Valve to SG-RC-2A Containment Isolation Valve HCV-25068.

Performed testing and maintenance to the following MOVs:

HCV-265 (Boric Acid HCV-308 (Charging Storage Pumps Tank Outlet Discharge Valve) to HPSI Hea der Isolation

' Valve)

HCV-318 HPSI to RC Loop 2A Isolation Valve)

HCV-321 HPSI to RC Loop 2B Isolation Valve)

HCV-341 Shutdown-Cooling Heat Exchangers Temperature Control Valve)

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. Monthly Operating Report LIC-92-091R Page 4 Performed trevitest and . setpoint checks for the following main steam safety valves:

MS-275, MS-276, MS-277, MS-278, MS-279, MS-280, MS-281, MS 282, MS-291 and MS-292 Performed repairs to HCV-484, Shutdown Cooling Heat Exchanger AC-4A Outlet Valve,

-' AVERAGE DAILY UNIT POWER LEVEL

' DOCKET NO. 50-285

. UNIT FORT CALhu-'N STATION DATE MARCH 1 Q 992 COMPLETED.BY G. R. CAVANAUGH TELEPHONE ~40TT3 6--2 4 7 4 -

MONTH FEBRUARY 1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)-

, 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 __

61 0 22 0 7- 0 23 0

.8 0 24 0:

9 -- 0 25 0 10, -0 26 0 11 0 27 0 l'2 0 28 0-13- 0 29 0-

-14 0 30 15: 0 31 16- 0 INSTRUCTIONS

+

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

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OPERATING DATA REPORT DOCKET NO.- 50-285 UNIT FORT CALHOUN STATION DATE _ MARCH- ~11 1992 COMPLETED BY G. R. CAVANAUGH OPERATING STATUS TELEPHONE 402-636-2474 _

1. Unit Name:

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FORT CALHOUN STATION

2. Reporting perlod: f5FRUARY 1992 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): 5_0_2_

.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:

.Nf_A _ _

THIS MONTH YR-TO-DATE CUMULATIVE

11. Hours in Reporting Period........... 696.0 1440.0 161570.0

12. Number of Hours Recc. tor was Critical 7.0 751.0 125569.7

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

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1309.5' 746.b~ 124123.1

14.-Hours-Generator On-line............. 2.0

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

.0 .0 . 0.

-16. Gross Thermal Energy Generated (MWH) 667.1 958856.1 1625F2581.8 17.cGross Elec. Energy Generated (MWH).. .0 323236.0 53499362.2

<18. Net Elec.-Energy Generated ~(MWH).... .0 306776.6-~ 51040528.0-

19. Unit Service Factor................. .3 51.8 76.8

20. Unit Availability Factor............ .3 51.8~ 76.8 L21. Unit Capacity Factor (using MDC Net) .0 44.'6 68.8 22.-Unit Capacity Factor (using' DER Net) .0 44.6_ 66.9 23'. Unit Forced Outage Rate............. .0 .0 3.9 24.z Shutdowns scheduled over next 6 months (type, date, and duration of each):

THE PLANT IS CURRENTLY SHUTDOWN FOR THE 13TH REFUELING OUTAGE. THE OUT-ffy: IS CURRENTLY SCHEDULED TO BE COMPLETED 4/27/92.

'2 5 . Ifl shut down at end of report period, estimated date of startup: 04/27/92

26. Units in test: status (prior to comm. oper.): Forcast Achieved l -INITIRL CRITICALITY -

i: INITIAL ELECTRICITY N/A COMMERCIAL OPERATION l

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v- . Refueling' Information:

.- ' Fort Calhoun - Unit No.1 q

LReport for the month ending February 1992 I

7 1=.; Scheduled dated for next refueling shutdown.- Refuelina outaae beg n ; ~

pn_lbruary . 1992

~ 2.-; Scheduled date for- restart following refueling.

April 27.1992 Will refueling or resumption of operations

>3.

- thereafter1 require a technical-specification 1 change or other license amendment?- Yes

- a. :If answer is _yes,- what, in_ general, will-these be?

Incorporate specifici requirements resulting _

from- relota safety analysis.

bilf 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? t N/A

-4.-Scheduled date(s)ifor' submitting proposed ilicensing action-an_d support informationi- Submitted November 27.

~ 1991

5. Important licensing considerations. associated with refuelin or supplier, g, e.g., newdesign unreviewed or different fuel design or performance-analysis methods, significant changes in- fuel

, design ~,;new operating procedures.

- New fuel- sup lier -

New LOCA ana vsis--

6; sThe -~ number 'ofl fuel assemblies: - a)-in theIcore; O Assembl et b) in the spent- 662 Assemb' ies

- fuel . pool .

c) spent-fuel-pool storage-capacity 729: Assemblies d)_ planned spent: Planned to be .

fuel . pool ircreased with higher- *

-storage capacity-density spent fuel racks.

E7i?The')rojected date of the last refueling ~ that can be-

-disclarged-to the~ spent-fuel pool assuming the

, lpresentlicensedcapacity. . 1995*

• Capability of full core offload of 133 assemblies lost. Reracking to be performed between the 1993 and 1995 Refueling _0utages.

Prepared by -

Date I ~

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 285-

. UNIT NAME Fort Calhoun Stat' ion:

DATE March 13. 1992 COMPLETED BY 'G. R. Cavanauch TELEPHONE 402 - 636-2474-REPORT MONTH ' February 1992 .

h Date Type' Duration Reason2 ' ' Method of ' Licensee System Component Cause & Corrictive (Hours) ' Shutting Event Code' Code' Action to .  !

Down Reactor' Report # Prevent Recurrence 92-01 2-1-92 .S 694 'C 1 XX XXXXXX On February 1,1992, the 13th Fort Calhoun Station Refueling Outage con -i 1 2 3 4 F: Forced Reason: Method: Exhibit G - 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

. D-Regulatory Restriction ' 4-Other (Explain) (NUREG-Ol61)

E-Operator Training & License Exammation 5

F-Administrative G-Operational Error (Explain) Exhibit 1 - Same Source .

(9/77) H-Other (Explain)

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