ML19305A950

Monthly Operating Rept for Feb 1980

ML19305A950
Person / Time
Site:	Fort Calhoun
Issue date:	03/10/1980
From:	Hickle B OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML19305A946	List: ML19305A945 ML19305A950
References
NUDOCS 8003180607
Download: ML19305A950 (8)

Text

l

,, ~ x.

2

, a/

N-AVERAGE DAILY UNIT POWER LEVEL l

1 DOCKET NO. 50-285 UNIT Fort Calhoun #1 DATE March 10, 1980 COMPLET ED BY B. J. Hickle TELEPil0NE 402-536-4413 MONTil Februarv. 1980 DAY AVERAGE DAILY ' POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net) (SIWE-Net) 1 0.0 17 0.0 2 0.0 is 0.0 3 0.0 39 0.0 4 0.0 20 0.0 5 0.0 21 0.0 6 0.0 22 0.0 7j 0.0 23 0.0 8 0.0 24 0.0 9 0.0 25 0.0

-10 0.0 26 0.0 11 0.0 27 0.0 12 0.0 28 0.0 13 0.0 29 0.0 14 0.0 39 15 0.0 3, 16 0.0

. INSTRUCTIONS On this format, list the average daily unit power levelin MWe Net for each day in the reporting inonth. Coinpute o the nearest whole megawatt.

(9/77 )

. 8003180h y 9

OPERATING DATA REPORT DOCKET NO. 50-285 DATE March 10, 1980

• COMPLETED BY B. J. Hickle TELEPilONE 40Z-536-4413 OPERATING STATUS Notes

1. Unit Named Fort Calhnun Statinn linit No. 1

2. Reporting Period: February, 1980 1420

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross MWe): 502

5. Design Electrical Rating (Net MWe): 407 4 6. Mnimum Dependable Capacity (Gross MWe): 481

7. Maximum Dependable Capacity (Net MWe):

457

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

N/A

9. Power Level To Which Restricted. If Any (Net MWe):. N/A

10. Reasons For Restrictions. lf Any: N/A' This Month Yr.-to Date Cumulative

11. Ilours in Reporting Period 696.0 1.440.0 56.377.0

12. Number Of flours Reactor Was Critical 0.0 432.9 44,834.5

13. Reactor Reserve Shutdown flours 0.0 0.0 1,309.5

14. Ilours Generator On.Line 0.0 430.5 43,881.6

15. Unit Reserve Shutdown flours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWil) 0.0 574,730.9 53,809,760.2 .

17. Gross Electrical Energy Generated (MWil) 0.0 190,604.0 17,850,833.6

18. Net Electrical Energy Generated (MWil) 0.0 _ _ . _ , 180,935.1 16,868,454.1

19. Unit Senice Factor 0.0 29.9 77.8 20.~ Unit Availability Factor 0.0 29.9 77.8

. 21. Unit Capacity Factor (Using MDC Net! 0.0 27.5 66.0

22. Unit Capacity Factor (Using DER Net) 0.0 27.5 65.5

23. Unit Forced Outage Rate 0.0 0.0 4.5

24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Duration of Eacht:

None

25. If Shur Down At End Of Report Period. Estimated Date of Startup: March 15. 1980

26. Units in Test Status IPrior to Commercial Operationi: Forecast Achiesed INITIAL CRITICALil Y INillA L ELLCIRICIf Y COMMERCI \L OPER ATION -

(9/77) c r ,,

UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-285 UNIT NAME Fort Calhoun #1 DATE March 10, 1980 REPORT MONTil February, 1980 COMPLETED 8Y B. J. Hickle TELEPIIONE 402-536-4413 n.

b. C

-, .53 3y * $ Ii

. Licensee Eg j% Cause & Corrective No. Date g 3g _g 5 5 Event 3, y g3' Action to j= O H 5 3@g Report 2 mU o

o Prevent Recurrence C ,

80-01 800118 S 1009.5 C 1 N/A Reactor shutdown for annual refueling and maintenance outage.

I 2 3 4 F: Forced Reason: Method: Exhibit G Instructions S Scheduled A Equipment Failure (Explain) 141anual for Preparation of Data B41aintenance or Test 2 Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File iNUREG-D Regulatory Restriction 4-Ot her ( Explain) 0161)

E-Operator Training & License Examination F Administrative 5 G-Operational Error (Explain) Exhibit I - Same Source (9/77) 11-01he r (Explain)

~

Refueling Inforration Ibrt Calhoun - Unit No. l- - .

Report for' the nonth ending Febr. 29,' 1980 .-

l. .Schedul'cd date for'next refueling shutdown. March 15, 1981

~

2. . Scheduled date for restart following refueling. May 15, 1981

-3. Will refueling or resumption 'of operation thereafter require a technical specification change 'or other.

No license amendment?

If answer is yes, what, in general, will

^

, a..

these be? :

b. If answer is no, has the reload fuel design arrl core configuration been reviewed by your Plant Safety Review Comnittee to deter-mine whether any unrevieced safety questions

-are associated with the core reload. No

c. If no such review has taken place, when is-Febr. 1, 1981

.it scheduled?

4. Scheduled date(s) for submitting proposed licensing

. action and support infor: ration.

' 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, ncy operating procedures.

~ 6. The number of fuel assemblies: a) in the core 133 assemblics b) in the spent fuel pool 197 c) spent fuel pool storage capacity 483 d) planned spent fuel t rol * '"

storage capacity 483

7. : The projected date of the last refueling that can be 4 . discharged to the spent fuel pool assunting the present 1985 licensed capacity.  !

l- Prepared by- / -

('6xP/lb Date March 3. 1980 f

u V

=w<v > -n -,-e - + -

4 ,,.e <pya -w.-- -- , , - 'n-m-g, , r-vy - , + ,y ---c-- -e-- - --r--- g

[. <

'.6

OMAHA PUBLIC POWF3 DISTRICT Fort Calhoun Station Unit No. 1 February 1980

' Monthly Operations Report

'I. OPERATIONS SUIGfARY -

Fort Calhoun remained in a refueling operation condition for the month of_ February. The fuel shuffle was completed during February and no abnornalities were discovered.

Surveillance testing continued during the month including several major refueling tests such as the Energency Safeguards With Loss of Offsite Power test.

Several open maintenance requirements were completed during a combined rav vater / component cooling water / instrument air outage.

Operations support of refueling activities continued as normal.

A. PERFORMANCE CHARACTERISTICS 4

LER Humber Deficiency i

LER-020, Rev. 2 During continuing inspections of accessible piping being performed in accordance with IE Bulletin 79-02, two additional snubbers on the safety injection system piping vere found to be inoperable because of improper installa-tion of the anchor bolts. No significant occurrence took place. The probable consequences i vould have been the inability of the snubbers to perform their design functions during a seismic event.

LER-001 On January 2,1980, while operating- at approxi-mately 98% power, the breaker feeding the con-tainment cooling fan motor (VA-33) tripped.

i This trip was believed to have occurred due to faulty trip units in the breaker feeding VA-33.

As a result of VA-33 being tag 6ed "out", redun-dant containment cooling units were tested for gg y g - -

operability in accordance with Technical Speci-D )D fication 2.h(2) . Subsequently, HCV h033, which am'W U ' #

- upon opening allows ccmponent cooling water to flow through the cooling coil for the containment cooling unit, VA-7D would not open from the control room switch.

LER-002 During power operations at approximately 90% and while performing surveillance test ST-SI/CS-1, the containment sump safety injection recircula-tion valve HCV-383-h failed to close from the control room switch. At the time of the failure,

i

^

Monthly Operations Report February 1980 P2ge Two D my)jg g-m e

w w . .u.

LA. PERFORMANCE CHARACTERISTICS (Continued) 4 LER Number Deficiency the redundant safety injection recirculation -

valve HCV-383-3 was found to be operable.

M.O..#3669 was written to investigate the problem.

LER-003 While attempting to load the diesel generator, DG-2, during the performance of a special e- 24-hour diesel generr. tor test required in i response to IE Bulletin 79-23, the generator field vent to maximum excitation; therefore,

- the diesel was shutdown to prevent generator i ,

damage. The failure was a result of a refer-

! ence 7ener diode drift in the A-C regulator panel. The diode was replaced and the diesel generator testing was resumed. Subsequently i 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> later into the " resumed" test, a radiator tube leak was discovered. This leak

, was repaired per =aintenance order and the 24-hour diesel test was restarted and satis-

• factorily completed without further incident.

LER-00h A fire barrier inside a empty breaker cubicle was degraded to pull in new cabling. A fire watch was established and a maintenance order

, issued to temporarily fill the fire barrier.

The fire watch was not maintained in a continu-ous manner as required b'/ Technical Specification , 2.19 B. - CHANGES IN OPERATING METHODS

, . None 1

, C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS

! None

'D. CHANGES, TESTS A:iD EXPERIMENTS CARRIED CUT WITHOUT COMMISSION APPROVAL 1 ,

Proc edure, Description SP-VA-80_ Hydrogen Purge System Test: Hydrogen Purge System fans, valves, and filters operated satisfactorily.

. SP-CHEM-3 Containment Atmosphere Sampling During

- Containment Pressure Test ST-CONT-T. Samples taken and analysis. completed. .

t'J t'  % =F T' W -+**n = w 4 T- =y *"*-C *T -F 'PF##' TY+P"'T"*--~FF' - * - - M 9 ^TW ' -*

e,. .

Monthly Operations Report ^ . . ,,

Februar'/ 1980 D i Ol ^

Page Three Q kJ, j  ; 5 E. RESULTS OF LEAK RATE TESTS Leak rate testing during the Refueling Outage continued for the conth of February. After the ccmpletion of all leak tests, a detailed report vill be written.

F. CHAIIGES IN PLAliT OPERATI:lG STAFF None G. TRAINING Training in February consisted of radiation protection for OPPD and contractors personnel, requalification exams for NRC licensed personnel and training for operators en the Cycle VI changes in the plant.

H. CHANGES, TESTS AND EXPERDEITS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUAIIT TO 10CFR50.59.

None 6

i

\\\ \0,^

~

'\

Approved :r -' A l- Ma'neger-Fort Calhoun utatien I

l 1

l l

1

s

.o .- e

!  %.! W D Elk $

Menthly Operations Report February 1980 D

d gi , Jgj\u L:::

Page Four II. MAI'iTE~iA! ICE (Significant Safety Related)

M. O. # d.a Description Corree:1ve Action i i

i None ii I I,

)

t

}

,6 .

-l, I

l l

l 4

i l 1

1 r 1

. .