ML20195H216

Monthly Operating Rept for Dec 1987

ML20195H216
Person / Time
Site:	Fort Calhoun
Issue date:	12/31/1987
From:	Andrews R, Blessie W, Gates W OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LIC-88-025, LIC-88-25, NUDOCS 8801190112
Download: ML20195H216 (9)

Text

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AVERAGE DAILY UNIT PotYF.R LEVEL D0cKET NO. 50-285 3.lT Fort Calhoun Station DATE Jarumev 11. 1988 COMPLETED By W. J. Blessie TELEPHONE 402-536-4595 MONTH Lctmber,1987 DAY. AVERAGE D AILY POWER LEVEL DAY AVER AGE DAILY POWER LEVFL (MWe Net) (MWe Neti i m6 37 488.2 2 488.8 __ is 488.2 3 488.9 39 488.0 4 488.7 :o 488.4 5 488.7  :: 488.8 6 488.4 22 488.7 7 488.5 23 488.5 8 488.6 -24 488.2 9 488.4 25 488.3 to 488.1 . 26 488.3 i 488.2 - 488.3

488.2 23 488.3 13 487.8 ,, 48.2 487.8 488.4 14 3o 15 487.6 3 488.3 .

16 488 1 r

INSTRUCTIONS On this format. list the aserage daily unit power leselin MWe. Net for each day in the *epor:ing month. Corr, ute to the nearest whole nwgawatt.

i (9/77)

I 8801190112 871231 ADOCK 05000285

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PDR R DCD

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. i OPERATING DATA REPORT DOCKET NO. 50-285 DATE .Tnmmrv 11, 1988 COMPLETED BY U .T Rlassie TELEPilONE 402-536-4595 OPERATING STAT US Fort Cn1houn Station '"

1. Unit Name:

2. Reporting Period: Decerber, 1987

3. Licensed Thermal Power IMWt):

1500

4. Nameplate Rating (Gross MWe). 502

5. Design Electrical Rating (Net MWe): 478

6. Maximum Dependable Capacity (Gross MWe): 502

7. Masimum Dependable Capacity (Net MWe): 478

8. If Changes Occur in Capacity Ratings (Items Number 3 Throu;h 7) Since Last Repoit.Give Reasons:

i N/A ,

9. Power Lesel To hhie's Restricted.lf Any (Net MWe): N/A

10. Reasons For Restrictions.lf Any:

This Month Yr. to Date Cumulatise l1. Hours in Reporting Period 744.0 8,760.0 125,066.0

12. Number Of Houn Reactor Was Critical 744.0 6,608.3 96,839.S

13. Reactor Resene Shutdown Hours 0.0 0.0 1.309.5  !

14. Hours Generator On-Line 744.0 6,531.7 95,918.8

15. Unit Resene Shutdown Hours 0.0 0.0 0.0  :

16. Gross Thermal Energy Generated (MWH) 1

111.574.5 9,497,123.3 124,547,625.2

17. Gross Electrical Energy Generated iMWH) 379,578.0 3,206 195.0 40,972,921.2

18. Net Electrical Energy Generated (MWH) 161 141 1 1 060 691 Q 39 1% OR2 A

19. Unit Senice . ictor 100.0 74.6 76.7

20. Unit Asailability Factor 100.0 74.6 76.7 67.6

21. Unit Capacity factor iUsing MDC Neti 102.1 73.1

22. Unit Capacity Factor (Using DER Net) _

102.1 73.1 65.7

23. Unit Forced Outage Rate G.0 0.0 3.1

24. Shutdowns Scheduled Oser Nest 6 Months (Type.Date.and Duration of Eachi:

None

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

26. Umt In Test Status IPrior to Commercial operationi: Forecast Achiesed INITI A L CRITICA LITY INITI AL ELECTRICITY COMMERCl \ L OPER ATION N/A (4/77 )

DOCKET NO. 50-285 UNIT SHUTDOWNS AND POWER REDUCTIONS Fort Calhcsun Station UNIT NAME DATE Jemrv 11 1988 COMPu:TED BY W. J. Blessie REPORT MON Hf December.1987 TELEPHONE 402-536-4595

- "h a E ?

j E2 twensee j-r, K Cause & Currect5e No . Date { 3g 4 j g5 Event g pO Action to

• - yE 5 ~.

f3 =

Repor: = mU o v

Prevent Recurrence 6

• There were no tnit shutdowns or power reductions during the month of Deconber, 1987.

I 2 3 4 F: Forced Reasim: Method: ~

Exhibit G-Instructions S: Scheduled A-Equipment Fadure(E= plain) I-Manual for Preparation of Data B-Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee *,

C Refueling 3-Automatic Scram. Event Report tLE R) File (NUREC-D-Regulatory Reststetion 4-Other (Explain) 0161)

EOperator Training & tscense Examination F-Adrmrust ratne 5 G-Operational tiror (Emplain i . Eshibit I - Same Soerec

, (9/77) II 0:her i E splain) e s - u w ~.-

-- ~ ~._ . -. ..

Refueling Information Fort Calhoun - Unit No. 1 '

Report for the month ending December 1987 .

1. Scheduled date for next refueling shutdown. September 1988

2. Scheduled date for restart following refueling. December 1988 e

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 these be?

a Incorporate cycle specific requirements resulting from reload safety analysis,

b. If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to deter- i 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. July 1988 -

5. Important licensing considerations associated with refueling, e.g., new or different fuel design or supalier, unreviewed design or performance analysis '

met 1ods, 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 393 "

c) spent fuel pool

! storage capacity 729 "

d) planned spent fuel pool May be increased "

storage capacity via fuel ein "

)- consolidation

7. The projected date of the last refueling that can be

discharged to the spent fuel pool assuming the present licensed capacity. 1996 i

Prepared by__ C 1Likk:~-- Date December 31. 1987 i

ifl OMAHA PUBLIC POWER DISTRICT  :

Fort Calhoun Station Unit No. 1  :

December 1987 i Monthly Operations Report i I. OPERATIONS

SUMMARY

, Fort Calhoun Station operated at 100% power through December 1987, completing another year with a reactor trip. Construction continued on the training facility, warehouse and maintenance shop. An NRC inspection was performed on Radiological and Environmental Controls.

No safety valves or PORV challenges or failures occurred.

A. PERFORMANCE CHAPACTERISTICS None B. CHANGES IN OPERATING METHODS ,

l None i

.i C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL i

! Procedure Description SP-FAUD-1 Fuel Assembly Uplift Condition Detection.

. This procedure did not constitute an unreviewed i

, safety question as defined by 10CFR50.59 since it only involved the evaluation of data from a sur-veillance test to verify that a fuel assembly uplift condition did not exist.

System Acceptance Committee Packages for December 1987:

1 Packaae Descriotion/ Analysis

(

! EEAR FC-87-034 Load Shed of 480 Volt Breaker 184A-6.

This modification provided for load shed of the security building. This modification does not have an adverse effect on the safety analysis.

' Monthly Operations Report December 1987 Page Two

[ D. CHANGES, TESTS'AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (Continued) ,

System Acceptance Committee Packages for December 1987: (Continued)

Packaae Descriotion/ Analysis EEAR FC-84-135 Water Treatment Plant Alarms to Main Control Room.

This modification provided for removal of three water treatment plant generated alarms (DEMIN WATER AWAITING REGEN, DEMIN WATER REGEN COMPLETE and DEMIN WATER OUTPUT P00R QUALITY) from A21 in .

the main control room. In addition, the WATER TREATMENT PLANT MALFUNCTION annunciator on A21 was wired into a "ringback" circuit. This allows any of the eight water plant alarms that input the WATER TREATMENT PLANT MALFUNCTION annunciator to realarm it even if a previous alarm input has not been cleared. This modification does not have an adverse effect on the safety analysis.

EEAR FC-86-019C Security Building Expansion.

This modification provided for substantial increase in the size of the Security Building.

Additional security access turnstiles and were installed. Also, a feature was provided that if needed there could be three entry lanes and one exit or vice versa. Furthermore, a visitor area was proviaed. HVAC and fire protection systems were expanded. The security force work area was increased and changed to a more efficient layout.

This modification does not have an adverse effect on the safety analysis. I EEAR FC-86-057 Vital Area Barriers.

This modification provided for additional physical security barriers in the auxiliary building at various locations. This modification does not have an adverse effect on the safety analysis.

EEAR FC-86-082 Space Reallocation.

This modification provided for rearrangement of part of the first floor of the service building to provide additional office space. This modifica-tion does not have an adverse effect on the safety analysis.

-Monthly Operations Report December 1987 Page Three D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (Continued)

System Acceptance Committee Packages for December 1987: (Continued)

Packaae Descriotion/ Analysis i EEAR FC-86 084 Additional Fire Damper. ,

This modification provided for the installation of damper FD-90 in ductwork between switchgear rooms '

36A and 368. This modification does not have an adverse effect on the safety analysis.

E. RESVLTS OF LEAK RATE TESTS .

i The biannual leak rate test on the containment purge valves was i completed during the month of December ser ST-CONT 3. Penetration

, M-88 was found and left at 0 secm. Altlough penetration M-87 was found at 9.2 scfm, it was left at 0 scem after the outer valve *

(PCV-7428) was adjusted and brought to its fully closed position. i.

The previous test for the purge valves was performed at the end of the 1987 refueling outage with leakage of 700 sccm and a total "B" and "C" leak rate of 1074.2 sccm. Since the December 1987 leak rate on penetrations M-87 and M 88 was left at 0 sccm, the total accumulative "as left" "B" and "C" leak rate is now 374.2 secm.

This leak rate is well below the allowed leakage of .6 La (62951 secm) as specified in 10CFR50 Appendix J.

The personnel air lock leak rate test was also completed in December per ST-CONT-2. This leak rate was found and left at 0 secm.

, F. CHANGES IN PLANT OPERATING STAFF None.

G. TRAINING  !

t During December, Station Training completed training and '

qualification of two shift technical advisors, continued training for licensed and non licensed operators and continued initial auxiliary

operator-nuclear and equipment operator-nuclear qualification training. Work was initiated to support the "pilot" NRC requalification examinations.

i

Monthly Operations Report December 1987 Pagu Four H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZAT10tl PURSUANT TO 10CFR50.59 None.

11. MAINTENANCE (Significant Safety Related)

None

&kM W. Gary Gates Manager-Fort Calhoun Station l

l l

s .

Omaha Public Power District 1623 Harney ort 1aha, Netiraska 68102 402 536 4000 January 14, 1988 LIC-88-025 V. S. fluclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

Docket tio. 50-285 Gentlemen:

SUBJECT:

December Monthly Operating Report Pursuant to Technical Specification Section 5.9.1, and 10 CFR Part 50.4(b)(1),

please find enclosed, one copy of the December 1987 Monthly Operating Report for the Fort Calhoun Station Unit fio. 1.

Sincerely, i

R. L. Andrews Division Manager fluclear Production RLA/me Enclosures c: f1RC Regional Office Office of Management & Program Analysis (2) l R. M. Caruso - Combustion Engineering R. J. Simon - Westinghouse fluclear Safety Analysis Center l

IfiPO Records Center American fluclear Insurers f1RC File (FCS)

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