ML20040A502

Monthly Operating Rept for Dec 1981

ML20040A502
Person / Time
Site:	Fort Calhoun
Issue date:	01/11/1982
From:	Short R OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20040A501	List: ML20040A500 ML20040A502
References
NUDOCS 8201210191
Download: ML20040A502 (11)

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AVI.R AGE drily UNII FuhEk lei EL l l

DOCKET NO. 50-285 UNIT fort Calhoun el DATE Janua ry 11, 1982 CO\tPLETED ilY R. W. Short TELEPilONE (402)536-4543

• 10NTil December, 1981 DAY AVER AGE DAll.Y POWEit LEVEL DAY AVEll AGE DAILY POhER LEVEL

(*11We Neo n:we. Net i i 0.0 ,7 0.0 2

0.0 33 0.0 3 0.0 i9 0.0 4 0.0 ,o 0.0 5 0.0 2, 66.9 6 0.0 ,, 226.0

- 0.0 2, 130.I s 0.0 292.5 9 0.0 25 313.0 to 0.0 318.0 26 0.0 318.9 i: __

3 32 0.0 320.7 I; 0.0 29 392.3 14 0.0 3g 467.2 15 0.0 ,,

475.5 i t, 0.0 INSTRUCTIONS On this fornut. !nt the aserage d.nly unit power lesel in Ntwe. Net for each Jay in the reporting inonth. Compute to the nearest whole megawait.

(4I77) 820121Cl91 &

OPERATING DA TA REPOltI DOCKET NO. 50-285 DATE January ll, 1982 CO.\lPLETED liY R. W. Short TELEPilONE M02 ) b.io-4543 OPER \ llNG STA IUS

1. Unit Name; fort Calhoun Station Unit tio.1 Notes

2. Reportin.: Penod; December, 1981

3. Licensed t hennal Power q\lhip: 1500

4. Nameplate Rating (Grow .\1he): 501

5. Desien Electrical Rating (Net 31We):

bUI

6. 31asunum Dependable Capacity (Gross N1We):

7. .\lasimum Dependable Cap:. city (Net 31We): 470 M. If Changes Occur in Capacity Ratings IIIenn Number 3 Through 7) Since Last Report. Gise Reasons:

fione

9. Power Lesel lo which Restricted. lf Anv (Net Athe): fi/A

10. Reasons For Restrictions,if Any: None This Slonth Yr..to.Date Cumulatise

11. Ilours in Reporting Period 744.0 8,760.0 72,481.0

12. Number Of llocrs Reactor Was Critical 330.1 6,460.7 56,239.0

13. Reactor Resene Shutdown flours 0.0 0.0 1,309.5

14. Ilours Generator On-Line 249.8 t,330.1 55,090.0

15. Unit Resene Shutdown floun 0.0 0.0 0.0

16. Grow Ihermal Energy Generated I.stWil) 255,589.6 6,983,589.8 66,701,830.1 17 Geow Electrical Energy Generated istWil, 85,176.0 2,285,674.0 22,0/3,945.6

18. Net l lectrical l:nerg3 Generated as1Wil, 79,700.0 2,149,685.6 20,847,868.5

19. Unit Senice l' actor 33.6 72.3 76.0

20. Umt As.nlabdity I actor 33.6 /2.3 76.0

21. Unit Capacity I actor (Using .\lDC Net) 22.4 51.I 62.8 I 22. Unit Capacity factor (Using DER Net) 22.4 51.1 62.4

23. Unit Forced Outage Rate 3.7 2.9 3.9

24. Shutdowns Scheduled Oser Nest b .\1onths IType. Date, and Duration of Each):

fione l.

25 If Shus D..wn At End Of Report Period. Estimated Date of Startup: f4/A

26. Umts in f est Status IPrior to Commercial Operation): Il0ne forecast Achiesed i INill \ L CRillCAll f Y ,

INill \L ELI:CIRICITY I COT 1\1LRCI \ L OPER A IlON (9/77)

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e i DOCKET NO. 50-285 -

UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT N AM E Fort Calhoun el

. DATE l ? n " 3 6' 11 - 1982 December,1981 COMPI ETED BY R W- 5h0Fi REPORT MONTil IEi.EPilONE (402)5%-4543  ;

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, -,  !? 3 $ Licensee ,E -r, fg Cause & Coirectise No. Date g 3=

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jg5 Esent gg gL mtion to 5 55=!

Report : mV c L

Prevcat Recurrence ,

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L 81-06 810918 5 2238.8 C 1 ft/A ft/A f1/A Reactor shutdown for 1981 refueling and maintenance outage.

81-07 811223 F 9.5 A 3 N/A WF INSTRU The condensate storage tank level ,

indication malfunctioned, permitting a low level condition in the storage tank. The low level condition caused a loss of vacuuu and sub-sequently the turbine tripped.

The faulty level indicator was repaired.

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4 I 2 3 4 i F: Forced Reason: Method: Esl6ibit G - Instinctions S: Scheduled A Equipment Failure (Explain) I-Manual for Preparation of Data ,

, IM1aintenance of Test 2 Manual Scram. Ent:) Shech for I.icensee C Refueling 3-Automatic Scram. Eseat Repost (l.1 R) tile (NURI G-D Regulatory Restriction 4-Other (E xplain) 0161) I E. Operator Training & License Examination F-Administ rative 5 G-Operational Error (Explain) Eshiba 1 - Same Source (9/77) 11-O her(Explain) l

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Pcfueling Infortration Fort Calhoun - Unit !b.1 Peport for the rmnth ending December 1981 .

1. Scheduled date for next refueling shutdran. December 1, 1982

2. Schnduled date for restart follcuing refueling. March 1, 1983

3. Will refueling or rest:rption of operation thereafter require a technical specification change or other liennm armndment? Yes ._

a. If ancmr is yes, what, in general, will these b2?

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A Technical Specification change.

b. If answer is no, has the relcnd fuel design aryl core configuration b2en revweed by your Plant Safety Paview Corntittee 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 propx,ed licensing action and support information. September 1. 1982

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

6. The nu:ier of fuel assenblies: a) in the core 133 assemblies b) in the spent fuel pool 237 c) spent fuel pool storage capacity 483 d) planned spent fuel pool storage capacity 483

7. The projected date of the last refueling that can be discharx;cd to the spent fuel pool asst:ning the present licensed capacity. 1985

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Prepared by /

s h)) 1 Date December 31, 1981

OMAHA PUBLIC PO'ER DISTRICT Fort Calhoun Station Unit No. 1 b

December 1981 l- Monthly Operations Report 4

I. OPFRATIONS SU:G'ARY q

During the month of December Fort Calhottn Station returned to power or< ration frcm a refueling cutar,0. The station cuccessfully cceplet-ed low power physics and has initiated pcwer ascension testing. The

! unit was shutdown automatically once during December due to low con-

denser vacuum causing a turbine trip. The unit was restarted and resynchronized within twelve (12) hours.

The automatic auxiliary feedwater initiation system was placed in i service when the unit was restarted from refueling operations.

New testing and operational testing continued during December.

No safety valve or PORV challenges occurred.

i i A. PERFORMANCE CHARACTERISTICS

. LER Uumber Deficiency i LER 81-10 Dttring the performance of Surveillance Test ST-ESF-7 (F.3), (Refueling Outage Calibration Performed on Recirculation Actuation Signal (RAS) Level Switch 4

Channels), it was notleed that D/LC-383-1 left and right switches were out of setpoint tolerances. The J

plant was in a refueling shutdown condition at the time the switches were found out-of-tolerance, hence

, Technical Specificaticn 2.3(1) a is not applicable.

The engineered safeguards logic was not placed in 4 bypass (2 out of 3 logic) nor was it required to be placed in 1 out of 3 logic with the affected D channel in trip, since the reactor was in a refuel-ing shutdown condition.

B. CIIAUGES IN OPERATING METIIODS i

NONE a

Monthly Operationn Report December 1981 Page Two C. RESULTU OF CURVEILLAtlCE TESTS AIID I?!3PECTIONS Surveillance testa un required by the Technical Specifications Ceetion 3.0 and Appendix B, were performed in accordance with the annual surveillance test achedule. The following is a summary of the surveillance tests which results in Operations Incidents and are not reported elsewhere in the report:

Operationn

! Inc;3ent Defic i ency OI-lh33 ST-DC-3 Component Cooling Water System dump to Raw Water System HCV h82A/B.

OI-lh3h ST-HEATER-1 Out-of-Service alarms for Banks 3 & h (F.1) failure to actuate.

OI-lhh3 ST-lGI-SI-I SI-298 Relief 3etpoint Lift out-of-tolerance.

OI-lh39 ST-RM-3 Lost Surveillance Test.

OI-lhh6 ST-FP-9 Test not performed ac ccheduled.

OI-lhh2 GT-ilflRS-1 During performance of ST-RHRS-1 Test Gauge

1. 10h was found to be not calibrated within specified time.

0I-1437 ST-RM-b Environmental Sampler OAC found to be

( F.1 ) inoperable.

OI-lhSO ST-FP-9 Fire Barrier Surveillance not performed per i

S.0. G-17.

OI-lhS2 UT-H30 h During performance of ST-HSG-k , F.1/ SIS h8 did not meet acceptance criteria.

D. CllAllGES, TECTS A!iD EXPERIMErlTS CARRIED OUT WITliOUT COMMISSION APPROVAL Procedure Dencription GP-FAUD-1 Puel Annembly Uplift Condition Detection.

An unreviewed cafety question no defined in 10CFRSO.59 did not exist no this procedure only involves evalua-ting data from a curveillance test.

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Monthly Operations Report December 1981 Page Three D. C:!AIiGE3, TECTS A!!D EXPEMI!Ti"'3 CARRIED OUT '4ITHOUT C0!CIIS310:i API ROVAL (Continued)

Procedu re Description SP-RP-1 This procedure van nerformed immediately after plant shutdown for refueling in order to provide for an initial radiolo6i cal survey of the Containment Building.

The results of the procedure demonstrated that radi-ation levels were within design parameters and that existing station radiation protection procedures and controls were adequate to cctmence maintenance and question activities within the containment. For these reasons no unreviewed safety question van iden-tified.

E. RESULT 3 0F LEAK RATE TESTS.

The 1931 refueling outage Type B and Type C local leak rate test sum-mary report is cceplete and vill be forwarded to the liuclear Reactor Regulation Branch, per 10CFR50, Appendix J.

F. CHA!!GE3 III PLA!iT OPERATI?iG STAFF 110tlE G, TR/i1IIING l Training wan given to the operations personnel on Cycle 7, Modifications.

1 Degraded core, and the Annual Licensed Operator Exam was administered.

II . CifA?iGEG, TESTS A!iD EXPERIME?iTC REQUIRI!IG tlUCLEAR REGULATORY

, COMMISSI0ii AUTHORI"ATIGII PURSUAt!T TO 10CFR50 59 tl0:lE c

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1 Monthly Operations Report Decenber 1981 Page Four II. MAINTENANCE (3ignificant Safety Related)

M.O. # Date Description Corrective Action 12382 11-2-81 011 leaks on Reactor Coolant Famp Installed new union.

Motor RC-3C Piping.

Il53h 11-10-81 Investigate Reactor Coolant Pump Repaired.

Motor RC-3C oil leak.

12872 11-21-61 Burnt contacts & wire on 100 AMP Replaced breaker & viring.

Breaker AC-5 in MCC-3A2.

9hh6 11-18-81 Replace transfer tube blind flange. Per MP-AE-3-2.

12375 11-lb-81 Component Cooling Water Pump Dischar- Installed new seat.

charge Check Valve AC-102 does not shut off tightly.

12398 11-16-81 Raw Water Valve HCV-2882A Actuator Replaced Bolt.

bolt broken.

12739 11-14-81 Reactor Coolant Valve RC-207 Svage- Welded socket, lock downstream of RC-207 leaks.

128h6 11-20-81 Stack Particulate Monitor RM-061 Found bad connection & repaired.

Will not cal. check. Needle jumps vildly.

7651 11-16-81 Repair line-charging pump suction Completed per procedure.

header.

12077 10-9-81 Area Monitor RM-079 doesn't read on Found bad connector on switch.

102 -103 decoder.

10386 10-7-81 Area Monitor RM-080 not operable. Replaced detector.

11701 9-28-81 Bh Electrical penetration leaks Tightened fittings retested.

sligritly.

12080 10-12-81 Area Monitor RM-088 ratemeter is out Changed switch & replaced switch.

of tolerance.

12079 10-11-81 Area Monitor RM-086 doesn't read on Replaced high range board.

high range.

12700 11-11-81 Svagelock fitting on Reactor Coolant Replaced nut & flarred tubing.

Valve RC-20h has bad nut and or tub-ing does not have a flare.

12633 10-9-81 AC-5B Spent Fuel Pool Cooling Pumps Adjusted packing, packing bad.

Monthly Operationc Report j December 1981 i Page Five II. MA!:iTE*iA? ICE ( Continami)

M.D. # Date Description Correctic Action 12301 11-9-81 FP-5 Jockey pump leaks. Incalled new ceals.

3 12615 11-7-81 F4-6 Electrical emergency FW Pump Adjusted packing.

leaks.

10685 10-12-81 Cpurious alarms on Area Monitor Changed high ran6e board.

BM-071.

9351 9-26-81 Uncouple Control Element Ascemblies Completed.

per MP-RC-10-6.

4487 12-7-81 Charging Pump CH-1B auto ctart light Found bad 52xx/CH-1B relay.

, on 32-2 vill not light. Replaced coil.

Il8h6 ll h-81 Penetration M-10 leakage. Repaired per LT-CV-ES-1, retested.

Il5h7 10-3-81 Perform Steam Generator RC-2B primary Performed per MP-RC-2-3 nide vicual inspector.

9h82 10-17-81 Chnnge out. AC-12A Raw Water Performed per procedure.

Strainer.

11379 11 h-81 Rebuild Bergan-Patterson Snubber Completed per MP-HSO-BP-1.

per MP-HSS-BP-1.

1250h 10-30-81 Stack Monitor RM-052 indication is Replaced detector.

off scale low.

1097h 7-23-81 Annuciator A-31 Computer standby Replaced switch block and tested.

test alana does not annuciate.

l 9820 h-7-81 Leakn around flange of Garety Replaced gaskets.

Injection Relief Valve SI-299 12698 11-15-81 Containment Isolution Valve HCV-508B Repaired solenoid. Plant in will not close. refueling shutdown not reportable.

1309h 12-6-81 Cafety Injection Valve HCV-307 Replaced solenoid valve.

colenoid valve sticking.

12105 10-10-81 Area Monitor RM-085 is fluctuating. Replaced detector.

12571 ll h-81 Tencion studo on RC-3C Reactor Completed per bT-RC-3-7-2.

Coolant Pump.

! 12521 12-6-81 Remove / Replaced ctuda on Reactor Completed per MP-RC-3-7-1.

[ Coolant Pump RC-3C.

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Monthly Operations Report December 1981 Page Six II. MAINTE: LANCE (Continued)

M.G. # Date Deceription Corrective Action 12520 11-5-81 Remove / Replaced studs in Reactor Completed per MP-RC-3-7 h.

Ccolant Pump RC-3B.

12519 11-3-81 Remove / Replace studs in Reactor Completed per MP-RC-3-7-1.

Coolant Pump RC-3A.

12108 10-19-81 Component Cooling Pump AC-3B Seal Replaced bearing and relapped leaking. seal.

120h3 11-5-81 Replace + 10 volt power supply on Completed.

AI-31D RPS Panel.

Il9h7 10-3-31 Ferform receipt inspection test Completed.

on Incore detectors.

10958 11-18-81 Area Monitor RM-07h Spilking into Charged detector and calibrated.

alamn.

12715 11-20-81 HFA Relay #27-1/SI-2 is cracked. Replaced coil.

10391 10-31-81 RPS "B" wide range DPM meter Replaced pre-amp.

spiking full scale.

12h3h 10-26-81 Containment Vent Fan VA-3A 69 Tightened mounting screws. l Control switch needs to be tightened.

11569 9-18-81 Failure of Charging Pump CH-1B to Replaced defective "C" phase start with manual C/S-Breaker goes trip device.

to trip free condition.

12025 11-2-81 #7 CEDM leakage. Performed MP-RC-10 h-C.

9910 11-2-81 #17 CEDM leakage. Performed MP-RC-10 hA, hB.

12008 11-2-81 #13 CEDM leakage. Perfonmed bT-RC-10 hC.

12027 11-2-81 #11 CEDM leakage. Ferformed bT-RC-10 hC.

9909 11-2-81 #18 CEDM leakage. Performed bP-RC-10 hA, kB.

9901 11-2-81 #33 CEDM leakage. Performed MP-RC-10 hB.

9902 11-2-81 #32 CEDM leakage. Performed MP-RC-10 hB.

12002 11-2-81 #29 CEDM leakage. Performed MP-RC-10 hB.

Monthly Operations Report December 1981 Page Seven II. MAI:!TE:IldlCE (Continued)

M.O. # Date Description Corrective Action 990h 11-2-81 #26 CEDM leakage. Performed MP-RC-10 hB.

9906 11-2-01 #2h CEDM leakage. Performed MP-RC-10 hA, kB.

9907 11-2-81 #22 CEDM leakage. Performed MP-RC-10-hA, hB.

12021 11-2-81 #21 CEDM leakage. Performed MP-RC-10 hA, kB.

9908 11-2-81 #19 CEDM leakage. Performed MP-RC-10 hA, hB.

1202h 11-2-81 #hl CEDM leaka.*e. Performed MP-RC-10 hA, kB.

9900 11-2-81 #38 CEDM leakage. Performed MP-RC-10 hA, LB.

12023 11-2-81 #35 CEDM leakage. Performed MP-RC-10 hA, hB.

12628 11-2-81 SI-3C Annual Coupling Alignment Aligned as necessary.

Check.

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I Approved By:

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,_i. S. C. Stevens Manager-Fort Calhoun Station l

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