ML20080C216

Monthly Operating Rept for Jul 1983

ML20080C216
Person / Time
Site:	Fort Calhoun
Issue date:	08/10/1983
From:	William Jones, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-83-193, NUDOCS 8308190266
Download: ML20080C216 (10)

Text

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AVER AGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT Fort Calhoun Station.

DATE August 10, 1983 COMPLETED BY T. P. Matthews TELEPHONE (402)S36-4733 MONTH July, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) IMWe-Net) 448.5 37 443.4 2 446.7 is 441.8 3 443.7 i9 440.3

.: 444.5 20 439.2 5 445.9 21 438.5 6 447.2 22 438.4 7 446.7 23 438_1 8 446.3 2, 439.4 9

445.9 443.0 23 10 444.~1 26 443.3

444.0 27 442.3 12 444 1 28 441.9 33 444.4 29 443.1 3 ., 444.0 3o 442.7 15 443.0 3 442.2 16 443.5 INSTRUCTIONS On this format, list the average daily unit power leselin MWe Net for each day in the reporting inonth. Coinpute to the nearest whole megawatt.

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8308190246 830810 PDR ADOCK 05000285 Yt R PDR l1l

OPERATING DATA REPORT DOCKET NO. _50-285 DATE August 10, 1983 COMPLETED llY T. P. Ma_tthews TELEPilONE -(402)536-4733 OPER ATING STATUS Fort Calhoun Station N"'"

1. Unit Name:

2. Reporting Period: July, 1983

3. Licensed Therm 31 Power (MWt):

1500

4. Nameplate Rating (Gross MWel: 501

5. Design Electrical Rating (Net MWe): 470

6. Masimum Dependable Capacity (Gross MWe): 501

7. Masimum Dependable Capacity INet Mbe): 478 l

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8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report. Give Reasons:

N/A

9. Power Lesel To Which Restricted,1f Any (Net MWe): N/A

10. Resums For Restrictions.lf Any: None l

This Month Yr. to-Dare Cumulatise i1. Ilours in Reporting Period 744.0 5,088.0 86,329.0

12. Number Of Houn Reactor Was Critical 744.0 2,830.9 66,220.9

13. Reactor Rewrve Shutdown llours 0.0 0.0 1,309.5

14. Ilours Generator On Line 744.0 2,732.0 65.729.5

15. Unit Rewne Shutdown Hours 0.0 0.0 0.0 '

16. Gross Thermal Energy Generated (MWH) 1,110,048.8 3,727,158.6 81,343,707.0 17 Grow Electrical Energy Generated (MWH) 346 6.92_.0 u 1,172,852.0 -26.596,331.7

18. Net Electrical Energy Generated IMWH) 329,773.5 1,111,631.3 25,441,665.T

19. Unit Senice Factor 100.0 53.7 76.1

20. Unit Availability Factor 100.0 53.7 76.1

21. Unit Capacity Factor (Using MDC Net) 92.7 45.7 63.9

22. Unit Capacity Factor (Using DER Net) 92.7 45.7 62.0

23. Unit Forced Outage Rate 0.0 1.8 3.8

24. Shutdowns Scheduled Oser Nest 6 Months tType.Date.and Duration of Eacht:

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

26. Units in Test Status iPrior to Commercial Operation): N/A Forecast Achiesed INITI AL CRITICALITY INITIAL ELECTRICITY COMMERCI \ L OPER AllON Pl/77

DOCKET NO. 50-285 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Fort Calhoun Station DATE August 10. 1983 COMPLE1ED BY T. P. Matthews REPORT MON nt Julv. 1983 1ELEPHONE (402)S36-4733 n.

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• jg 3 $Y5 Licensee [w, $*, Cause & Corrective No . Date g 3g { js5 Event g y Action to H y= $ j if5 g Report = mV g Prevent Recurrence 6.5 There were no unit shutdowns for the month of July,1983.

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I 3 4 t 2 Reason: Method: Exhibit G-Instructions F: Forced for Prepararian of Data

& Equipment Failure (Explaia) 1-Manual S: Scheduled Entry Sheets for Licensee

, 8-Maintenance of Test 2-Manual Scram.

3 Automatic Scram. Event Report (LER) File INUREG-C-Refueling 4-Other (Explain) 0161)

D Regulatory Restriction E-Operator Training & Licenw Examination 5

F. Administrative G-Operational Error (Explain) Exhibit I Same Source (9/77) II-Other (E xplain)

Refueling Infonration Fort Calhoun - Unit No.1 Pcport for the nonth ending July 1983 . .

1. Scheduled date for next refueling shutdown. March 1984

2. Scheduled date for restart follcwing refueling. May 1984

3. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes

a. If answer is yes, what, in general, will i

these be?

A Technical Specification Change

b. If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Co:Imittee to deter-mine whether any unreviewed safety questions are associated with the core reload.

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

4. Scheduled date(s) for submitting proposed licensing Methodology - October 1983 i action and support information. Tech. Specs. - February 1984

5. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis nothods, significant changes in fuel design, new operating procedures.

l 6. The number of fuel assenblies: a) in the core 133 assemblies l b) in the spent fuel pool 265 c) spent fuel pool storage capacity 483 4 d) planned spent fuel pool i

storage capacity 728

7. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. 1985 Prepared by h .

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OMAHA PUBLIC P0WER" DISTRICT gA '

Fort Calhoun St.at, ton' Unit No. I

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'. July, ?983 2 Monthly Operations Report

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1. OPERATIONS 1

SUMMARY

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' Fort Calhoun Std.i$n 'operat[.d at'dosinal 100j pcwer during. the month of

• (July. Repairs were completed on condensate pump FW-2C. The preparation

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of hot license candidates for the S.R.0.:4xamine. ~

tion early :n August -

continued.during July. The staff at Fort Calhoun . Station participated -s in two meetings with the NRC de'aling with health physics /radjochemistry and a proposed Technical Specifi.ca. ,..

tion on the Reactor .

Protective Syste.n. .

No safety valve or PORV cha)1enges occurred.

A. PERFORMANCECHARACTERISTICS None B. CHANGES IN OPERATING METHODS (, r ,

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None t-

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l C. RESULTS OF SURVEILL/1CE TESTS AND INSPECTIONS s

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• f Survelllance tests as required by the Technical Specif1 cations Section .

3.7.andMppendixBwereperfdrmedinaccordancewiththeannualsur@I ^

veillance test schedule. The following ista suninary of the surveil-

- lance tests which resulted in Opdation Incidents and' are'not~ reported elsewhere in the report:

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70peraLion~ .  :

Incide'nt Deficiency , /1

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1. i-01-1731 ST-RPS-12, F.2 9 During routi'ne plantf operation at 1l

' approximately 100% power, ;the "D"

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RFS , Channel ASI faternal' tilt ~

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"' . 1 out"of, specific.ynd 4tions. to have; drifted -

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e U D. CHANGES, TESTS AND EXPERibERTS CARRIED OUT WITHOUT. COMMISSION APPROVAL

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.SP-f0T-1 - Testing 'of Heater SA 0utlet Heat Exchanger Tubes -

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This procedure did.not constitute an 'unreviewed safety.

- A question k 'as defined by:10CFR50.59 sinco c it only involved a g # g testing of non-safety related *' equipmenth \

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Monthly 0parations Report; July,1983 Page Two D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL

, (continued)

System Acceptance Committee Packages for July,1983:

Package Description / Analysis DCR 76-88 Heater Drain / Moisture Separator Drain Valve.

This modification changed out the valve internals

to improve flow characteristics. This modification has no adverse effect on the safety analysis.

EEAR FC-80-46 Emergency Feedwater Storage Tank Backup Fill.

This modification provides redundant water supply for the emergency feedwater storage tank. This modification increases plant safety and consequently has no~ adverse effect on the safety analysis.

1 EEAR FC-80-87 "D" Inverter Output Breaker.

This modification replaced a faulty breaker with a similar breaker of comparable quality. This modi-fication has no adverse effect on the safety analysis.

EEAR FC-80-72 Immersion Heater Transformer for Dl.

This modification replaced a defective transformer.

This modification has no adverse effect on the safety analysis.

E. RESULTS OF LEAK RATE TESTS Measured leakage per surveillance test ST-CONT-2, F.2 (Personnel Air Lock Leak Rate Test) was 3100 secm. This leakage does contribute towards the

.6 La Technical Specification limit. Leakage to date (cumulative) is approximately 56,186.3 sccm which is well below the 62,951 sccm limit.

F. CHANGES IN PLANT OPERATING STAFF None G. TRAINING General employee training was conducted as scheduled. S.R.0. upgrade training was conducted for six people who are to sit for N.R.C. examina-tions in August. Training included lectures-and walkthroughs. New monitor team members were given initial training on the emergency plan and emergency plan implementing procedures.

Monthly Operations Report; '

July, 1983 Page Three H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION

' AUTHORIZATION PURSUANT T0 10CFR50.59.

None II. MAINTENANCE (Significant Safety Related)

M.0. # DATE DESCRIPTION CORRECTIVE ACTION 20282 6/2/83 CH-1B has primary leak into Installed new packing packing coolant tank 19413 3/23/83 HCV-1385 replace grease Complete 20168 5/27/83 AC-3A disassemble motor and Tightened bearings inspect for cause of increased vibration 19750 3/31/83 CEA 6 and 12 malfunctioned Repaired wire 21015 7/11/83 APD trip setpoint drifted Replaced dual amp module bistable 20517 5/31/83 "A" control channel deviation Adjusted light on 20908 7/1/83 RC-133 pressurizer mini-spray Completed per PRC approved procedure blowing around packing 20894 7/8/83 AI-31B linear power channel "B" Replaced F4,5 module and reper-negative APD limit drifting formed applicable sections of causing APD channel trip ST-RPS-12 F.2 21089 7/20/83 RM-050/51 pump discharge filter Replaced gasket leaks - gasket cracked 18888 3/3/83 Replace studs on RC-3B Completed per SP-RC-11 18881 3/1/83 HCV-327 valve seat and disc Completed per procedure machining 18483 2/9/83 RPS Channel A ll2/H loop has Replaced filter capacitor, checked bad power supply loop pegged loop per CP-A/ll2H high 19419 3/25/83 HCV-2974 replace grease Complete 19418 3/25/83 HCV-2954 replace grease Complete 19416 3/25/83 HCV-2914 replace grease Complete 19417 3/25/83 HCV-2934 replace grease Complete l

19412 3/25/83 HCV-1386 replace grease Complete

• Monthly Operations Report; '

July, 1983 Page Four II. MAINTENANCE (continued)

M.0. # DATE DESCRIPTION CORRECTIVE ACTION 19613 3-29-83 VA-3A 480V Breaker trip device Installed new trip device 19603 3/28/83 M-1-2,3,4 Inspect M-contactors per NRC Bulletin 19602 3/28/83 RPS circuit breaker inspection Check RPS circuit breakers 18176 2/25/83 HCV-315 SI loop valve Regreased and checked 18174 2/25/83 HCV-312 SI loop valve Regreased and checked 19916 4/13/83 CH-1B charging pump Repacked 19262 3/19/83 Inspect the gearcase grease in Completed per procedure Limitorque actuators HCV-218-3, 347, 308 19260 3/18/83 Inspect the gearcase grease in Completed per procedure Limitorque actuators HCV-311, 312, 314, 315, 317, 318, 321, 320, 329, 327, 331, 333, 150, 151 18116 3/7/83 CEDM #25 leaks Repaired per MP-RC-10-4-A and MP-RC-10-4-B 18117 3/7/83 CEDM #7 leaks Repaired per MP-RC-10-4-C 18118 3/7/83 CEDM #13 leaks Repaired per MP-RC-10-4-C 18948 3/13/83 RC-3A removal and replacement Completed per MP-RC-3-7 of 3 RC pump studs 19481 3/28/83 Replace the alarm relay RL2 on Replaced board V0 72 in inverter B & C 19420 3/22/83 HCV-347 replace grease Complete 18784 3/7/83 HCV-327 SI loop isolation Complete valve remove motor and repack grease in gear box 18785 3/7/83 HCV-329 SI loop isolation Complete valve remove motor and repack grease in gear box 18786 3/7/83 HCV-331 SI loop isolation Complete valve remove motor and repack grease in gear box 19357 3/25/83 HCV-1042C replace grease Replaced 19356 3/23/83 HCV-1041C replace grease Replaced

. . . . Monthly Operations Report ; - <

July, 1983 l Page Five II. MAINTENANCE (continued)

M.0 # DATE DESCRIPTION CORRECTIVE ACTION 19407 4/11/83 Diesel generator engine driven Replaced air compressor air compressor unloading air is leaking 19559 3/28/83 FW-1 A condenser tube leaking Plugged tubes per procedure circulating water into hotwell 19582 3/28/83 Sequence timer for FW-6 did not Tightened loose part on internal work contact 19342 3/19/83 LCV-218-3 change gear grease Complete 19314 3/25/83 HCV-258 will not go fully open Greased and operated correctly 19291 3/23/83 HCV-383-3 change grease Complete 19278 3/19/83 HCV-150, 151 add grease Complete 19276 3/19/83 HCV-311, 314, 317, 320 add Complete grease 19275 3/19/83 HCV-2914, 2934, 2954 add grease Complete 19265 3/17/83 Repair reactor vessel stud hole Completed per procedure

1. 21 19264 3/16/83 HCV-383-3 and 383-4 inspect Replaced grease grease 18787 3/7/83 HCV-333 SI loop isolatior. Complete valve remove motor and repack grease in gear box 46< -

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W. G. Gates Manager Fort Calhoun Station l

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l Omaha Pub!!c Power District 1623 Harney Ornaha, Nebraska 68102 402/536-4000 August 12, 1983 LIC-83-193 1

Mr. Richard C. DeYoung, Director Office of Inspection and Enforcement U. S. Nuclea r Regula tory Commission Washington, D.C. 20555

Reference:

Docket No. 50-285

Dear Mr. DeYoung:

Please find enclosed ten (10) copies of the July Monthly Operating Report for the Fort Calhoun Station Unit No. 1.

Sincerely,

, W.

gh Cs Jones l Divihion Manager Production Operations WCJ/TPM:jmm Enclosures cc: NRC Regional Office office of Management & Program Analysis (2)

Mr. R. R. Mills - Combustion Engineering Mr. T. F. Polk - Westinghouse l

Nuclear Safety Analysis Center INPO Records Center NRC File s..: , -,..

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