ML20031H459

Monthly Operating Rept for Sept 1981

ML20031H459
Person / Time
Site:	Fort Calhoun
Issue date:	10/09/1981
From:	Short R OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20031H456	List: ML20031H455 ML20031H459
References
NUDOCS 8110270501
Download: ML20031H459 (8)

Text

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AVERAGE DAILY UNIT POWER LEVEL DOCl;ET NO. 50-285

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Fort Calhoun #1 UNIT October 9, 1981 DATE COMPLETED BY R. W. Short TELEPHONE (h02) 536-h543 September, 1981 MONTil DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe. Net)

I h16. 7 37 36h.5 417.2 314.9 2

gg 417.6

0. 0 3

g, 4

h16. 3

0. 0 20 h15.0 0.0 5

21 409.7 0.0 6

22 404.3 0.0 7,

23 398.h 0.0 g

24 395.9 0.0 9

25 0.O 10 391.5 26 386.1 0.0 gi 27 382.8 0.0 12 3

13 377.3 29

0. O 373.6

0. 0 g.:

30 15 370.h 3

367.0 16 INSTRUCTIONS On this format. list the average daily unit power level in MWe Net for each day in the reporting nonth. Compute to the nearest whole megawatt.

(9/77) s 8110270501 811009

{DRADOCK 05000285 PDR

1

~4 OPERATING DATA REPORT DOCKET NO. 50-285 DATE October 9,1981 COMPLETED EY R.

W.

Short TELEPil0NE (402) 5 % k543 OPER ATING STATUR I. Unit Name:

Fort Calhoun Station Unit No. 1 Notes September, 1901

2. Reporting Period:

3. Licensed Thennal Power (MWtI:

1500

4. Nameplate Rating (Gross MWe):

501

5. Design Electrical Rating (Net MWe):

478

6. Maximum Dependc.ble Capacity (Gross MWe):

7. Slasimum Dependable Capacity (Net MWe):

NIO S. If Changes Occur in Capacity Ratings g' items Number 3 Through 7) Since Last Report.Give Reasors:

N/A

9. Power Level To which Restncted. If An (Net MWe;:

N/A

10. Reaso.as For Restrictiora,if Any:

N/A r

4 This Month Yr..to.Date Cumulative

11. liours in Reporting Period 720.0 6,551.0 70,272.0

12. Number Of flours Reactor Was Critical 4 32.6 6,130.6 55,906 9

13. Reactor Reserve Shutdown flours

0. 0

0. 0 1,309 5 I

14. Ilours Generator On-Line 430 9 6,060.3 54,o40.2

15. Unit Reserse Shutdown Hours 0.0

0. 0

~0.0

16. Gross Thermal Energy Generated (MWil) 548,011.6 6,728,000.2 66,446,240.5 17 Gross Electiscal Energy Cenerated (MWil) 178 028.0 2.200,498.0 21,988,769.6 t

18. Net Electrical Energy Generated (MWil) 168,461.1 _

2,069,985.6 20,768,168.5-

19. Unit Service Factor 59.8 92.8

78. T

20. Unit Asailability Factor 59.8 92.8 ~

70.0-

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21. Unit Capac:ty Factor (Using MDC Net) 48.9 65.7 64.6

22. Unit Capacity Factor (Using DER Net) 48.9 65.7 64.2

23. Unit Forced Outage Rate 0.0 2.9

3. 9

24. Shutdowns Scheduled Oser Next 6 Montns (Type. Date.and Duration of Each t:

None

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

November 15.-1981

26. Units in Test Status 1 Prior io Commercial Operationi: N/A Forecast Achiesed INIIIA L CRil'ICALITY INITIA L ELECTRICITY COMMERCI A L OPER A TION (9/77) 6

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50-285 i

DOCKET NO.

UNIT SilUTDOWNS AND POWER REDUCTIONS f.)rt Calnoun #1 UNIT N AME DATE october 9,

, 751 -

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COMPLETED BY H.

W.

Short REPORTMONTH Seritenber.1981 TELEPif0NE (402) 536 4543 "k

.5E "h

Ek Licensee 5%

b4 Cause & Correctise s

No.

Date g

3g g

,g i 5 Event u7 9 ?

Action to

.~. g =g Report 2 rN V Prevent Recurrence

$5 5

H e.

u C

4 s

81-06 810918 s

289.1 C

1 N/A N/A N/A Reactor shutdown for annual refueling and maintenance outage.

9 l

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 of Test 2 Manual Scrans.

Entry Sheets for Licensee C Refueling 3-Automatic Scram.

Event Report iLER) Fih (NtlREG.

D Regulatory Restriction 4-Ot her (IIxplain) 0161)

E-Operator Training & l.icense lhamination F-Administrative 5

G-Operational Error (12xplain)

Inhibit i. Same Source (9/77) ll-0thet ( E splain)

Refueling Information Fort Calhoun - Unit No. 1 Peport for the nonth endils September 1981, 1,

Scheduled date for next refueling shutdown.

December 1, 1982 2.

Scheduled date for restart foHcuing refueling.

March 1, 1983 3.

Will refueling or res"mption of operation thereafter require a technical specification change or other license amendment?

i.es a.

If answer is yas, what, in general, will these be?

- A Technical Specification change.

If answer is no, has the reload fuel design o.

and core configuration been reviewed by your Plant Safety Review Comittee 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 action and support information.

September 1, 1982 5.

Inportant licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant 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 197 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 discharged to the spent. fuel pool assuming the preser c licensed capacity.

1985 Prepared by Date October 5, 1981 V

f

x E

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 September 1981 Monthly Operations Report I.

OPERATIONS

SUMMARY

Durin;. the month of September,1981 Fort Calhoun Station operated in a power coa tdown until September 18, 1981 at which tim the unit was shu' down for a refueling outage.

No safety valve or PORV challenges oce2rred.

A.

PERFORMANCE CHARACTERISTICS LER Number De ficiency LER 81-008 With the reactor operating at approximately 95% power, engineered safeguards equipment relating to RM-062 was tested for proper operation prior to a gas release.

Subsequently, the 86B/CRHS (Containment Radiation High Signal) lockcut relay failed to actuate when RM-062 was placed it " larm". This also resulted in a fail-ure of the der 2.ved signal lockout 86B1/CRHS relay to actuate. Redundant relay ch._inels, 86A/CRHS and 86A1/CRHS vere operable and did actuate at the time of the 86B/CRHS failure.

B.

CHANGES IN OPERATING METHODS NONE C.

RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS Surveillance tests as required by the L'achnical Specifications, Section 3.0 and Appendix B, were performed in accordance with the annual surveillcnce test schedule. The following is a su miarv of the surveillance tests which resulted in Operations Incidents and are not reported elsewhere in the report:

Operations Incident Deficiency 01-1379 ST-ISI-CVCS-3/ST-SI/CS-1 l

Surveillance teet not reviewed within the 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> signcrf requirement.

Monthly Opere.tions Report Septeniber 1981 Page Two g

D.

CHA!!GES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COE!ISSICN APPRO'iAL Prcee dum Description SP-FAUD-1 Fuel Asse bly Uplift Core Detection.

An unreviewed safety question as defined in 10CFR50.59 did not exist as this procedure only involves evalua-ting data from a surveillance test.

EEAR FC-79-33 Installation of actue. tor for valve HCV-712A con:pleted as designed for a Mason-Nieler 3-way valve substituted for original trip valve.

This modification did not coastitute an unreviewed safety question as defined in 10CFR50.59 as it only involved replacen:ent of a valve actt.ator in the auxil-iary building ventilation system to ensure proper valve closure.

E.

PL:SULTS OF LEAK RATE TESTS Annual leak rate tuts are in progress.

A consolidated report vill b9 pmpared at the end of testing.

F.

CHANGES IN PLANT OPER/ TING STAFF NONE G.

TRAINING Training for September consisted of operator requalification, fire brigade, crane training and increased general employee training for the upcoming outage.

H.

CHANGES, TESTS AND EXPERIMENTS RECUIRING NUCLEAR REGULATORY C0!e11SSION AUTHORIZATIO:1 PURSUANT TO 10CFR50.59 Amend =ent No. 621:, creases the required reactor shutdown margin to > 3.0", Ak/k during cold shutdown conditions.

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r Monthly Operations Report September 1981 Page Three II.

!&INTENANCE (Significant Safety Related)

M.0.

Date Des cription Corrective Action 10813 7-7-81 Auxilian Feedwater Purp. FW-10 Replaced fuse.

D.C. oil pu=p wouldn' t run.

10746 7-2-81 Heat Trscing Recorder TAR-2 PT Repaired loose lead.

1. 12 readi.ng high off scale.

10789 7-6-81 DG-1 oil te=perature sensor Repaired faulty speed sensor-malfunction.

ing circuit interlock with oi] i==ersion heate:.

10554 4-16-81 Disasser.ble and dye penetrant Inspected and installed new test of charging pu=p CH-1B.

valve seats and packing.

10h27 6-6-31 Condense.r Off-Gas Monitor /

Installed new pu=p.

RM-057 pu=p trips.

11148 8-11-31 Liquid Waste Monitor /RM-055A Readjusted radiation back-recding off scale low.

ground subtractor potentio-rete *.

11152 6-11-81 Heat Tracing Recorder / TAR-2 Repaired loose lead.

1. 12 reading high off scale, 11373 9-3-81 RPS BC-4 Matrix Relay Drop Replaced Mereun vetted relay Light failed to extinguish.

B C-4, 10851 7-lh-81 Reset lift on AC-100.

Rav Complete. Retested per Sur-Water Pu=p.

veillance Test.

11185 8-17-81 Heat Tracing Recorder / TAR-2 Adjusted numeric indicator on would not print its scan TAR-2.

Repaired relay trans-pcints.

fer switch on TAR-1.

11151 6-18-81 HCV-2885 limit switch would hapaired switch and adjusted not alarm.

f,.,r proper operaticn.

11190 8-19-81 LI A-132 internal light burne 1 Repaired sigma '::eter.

out.

10973 8-12-81 CH-1B Charging pu=p packing Repacked pump.

leak.

11189 3-15-81 Condenser off-cas Monitor /RM-057 Replaced filter.

flow fault wouldn' t clear.

llM9 8-2 h-81 Component Cooling Water Pu=p/

Reglaced contact adder block.

AC-3A relaa 52XX 1B3B-4 Pu=p was operable.

chattering.

m

....e.

Monthly Operations Report September 1981 Page Four p

II.

MAINTENANCE (Significant Safety Related)

M.O. //

Date Description Correctis

• Action 11172 6-13-81 PR-Oh9 Process Radiation Re-Removed spring mechanism corder printed illegibly, and found broken spring.

Replaced spring.

11145 8-10-81 Fire barrier #0934 degraded.

Temporarily filled barrier

1. 0934.

11231 8-20-81 Feedwater regulating power Tightened power terminals.

line loose at terminals.

11203 8-19-81 Solenoid for HCV-h02E air leak.

Rebuilt valve.

11229 8-20-81 TAR-2 out of cynchronization.

Resynchronized recorder.

11232 8-20-81 86A-CPHS, 86A-SIAS, 86A-CIAS Replaced circuit card.

did not print out on computer when tripped.

11182 8-1 3-81 Engineered safeguards 86B-CRHS Lubricated rollers and brass failed to trip properly when bushings on trip mechanism, tested.

11h21 9-8-81 Insufficient pressure on FP-1A.

Replaced pump.

11392 9 h-81 AT Pwr "A" channel deviating.

Grounded current loop.

10334 8 81 AC-10D lost suction.

Repaired per procedure MP-AC 3 1148h 9-11-81 RM-056B reading high.

Replaced detector.

Approve By y Manager - Fort Calhoun S1(ation

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