ML20140J213

Monthly Operating Rept for Sept 1985

ML20140J213
Person / Time
Site:	Fort Calhoun
Issue date:	09/30/1985
From:	Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	Taylor J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-85-456, NUDOCS 8510230313
Download: ML20140J213 (9)

Text

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT Fort Calhoun Station DATE. Oct. 4. 1985 COMPLETED BY T. P. Matthews TELEPHONE (402)S36-4733 MONTH SeDtember. 1985 .

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) . IMwe-Neti

, 469.6 -

i7 476.6 2 469.3 18 475.1 3 468.1 39 472.5 4 468.5 20 a77 1 5 466.2 21 474 3 6 465.3 22 478.4 7

463.9 23 480.0 g 462.6 2.s ann _n 9 465.0 25 481.7 to 469.1 26 481.8 11 473.8 27 478.6 12 474.9 28 97 4 13 476.3 0.0 29 14 477.5 3o 0.0 478.5 15 3, 16 477 4 INSTRUCTIONS On this formar. list the average daily ur.it power lesel in MWe Net for each day in the reporting mimth. Compute to the nearest whole megawatt.

(9/77)

{'d " E I M ' 2eag n)l

OPERATING DATA REPORT DOCKET NO. 50-285 DATE Octnhor 4 1985 COMPLETED BY .P. Mattliews TELEPilONE (402)S16-4733 OPERATING STATUP, N"

I. Unit Name: Fort Calhoun Station

2. Reporting Period: September. 1985

3. Licensed Thermal Power (MWt): 1500 .

4. Nameplate Rating (Gross MWe): 502

5. Design Electrical Rating (Net MWe):

470

6. Masimum Dependable Capacity (Gross MWe): 502 ,

7. Maximum Dependable Capacity (Net MWe):

470

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

N/A

9. Power Lesel To which Restricted.If Any (Net MWe): N/A

10. Reasons For Restrictions. If Any: None This Month Yr..to Date Cumulatise II. Ilours in Reporting Period 770 0 6 ER1_0 109;197_o

12. Number Of flours Reactor Was Critical 661.5 6.466.1 R1.746.3

13. Reactor Resene Shutdown flours 0.0 0.0 1309.5

14. Hours Generator On-Line 658.8 6,455.5 81,122.9'

15. Unit Resene Shutdown Hours 0.0 0.0 0.~0

16. Gross Thermal Energy Generated (MWil) 974,986.7 9,564,277.6 103,751,044.6 .

17. Gross Electrical Energy Generated (MWill 324.508.0 309,015.T

_ 3,214,944.0 33,984,569.0

18. Net Electrical Energy Generated (MWH) 3,066,256.1 32,477,893.4

19. Unit Senice Factor 91.b 98.5 77.0

20. Unit Availability Factor 91.5 98.5 77.0

21. Unit Capacity Factor (Using MDC Net) 89 8 97.9 67.0

22. Unit Capacity Factor (Using DER Net) 89 8 97.9 64.8

23. Unit Forced Outage Rate 0.0 0.0 3.5

24. Shutdowns Scheduled Oser Nest 6 Months (Type. Date,and Duratio.i of Each t:

The 1985 Refueling Shutdown commenced September 28, 1985, with startup tentatively scheduled for December 11, 1905

25. If Shut Down At End Of Report Period. Estimated Date of Startup: December 11_, 19RR

26. Units in Test Status (Prior to Commercial Operation): N/A Forecast Achiesed INITI A L CRITICA LITY INIII AL ELECTRICIIY COM\1ERCIA L OPER ATION (9/77)

DOCKET NO. 50-285 UNITSHUTDOWNS AND POWER REDUCTIONS UNIT NAME Fort Calhoun Station DATE .0pt 19Rri REPORT MONTil Sentemher - 1985 COMPLETED BY T P btthowc

,. TELEPHONE -(an3)53g_M733 w.

- E c jg "h jY5 Licensec E

% K Cause & Corrective No. Date g 3g j .3 s 5 Event p g '3g Action to H g 4 jg Report : mV g Prevent Recurrence d

?

85-01 850928 S 61.2 C 1 N/A xx xxxxx 1985 refueling outage. commenced September 28, 1985-

' I t I 3 4 F: Forced Reason:  !

Method:

S: Scheduled Exhibit G Instructions A Equipment Failure (Exp! sin) 1 Manual for Preparation of Data B-Maintenance of Test i 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Esent Report (LER) File (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination F-Administrative 5

. G-Operational Esror (Esplain) Exhibit ! - Same Source P3/77) Il-Other (E xplain) ,

a' t r y '

h .#4

, Refueling Information Ebrt Calhoun - Unit No. 1 Report for the roonth ending Sentombor 19RR .

1. Scheduled date for next refueling shutdown. Octobor. 14RE

2. Scheduled date for restart following refueling. nocomhor. 14RG

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

a. If answer is yes, what, in general, will these be?

. Technical Specification changed submitted  %

September 3, 1985

b. If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Ormittee to deter-mine whether any unreviewul 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 Submitted -

action and support information. Sootember 3. 1985 ,

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 y

t operating procedures.

. Submitted and approved i e I

i*

6. The number of fuel assenblies: a) in the core 133 assemblies b) in the spent fuel pool "

305 c) spent fuel pool storage capacity 729 d) planned spent fuel pool llay be increased storage capacity via fuel oin consolidation

7. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present

' i. ,_. licensed capacity. 1996 Prepared by ! M Date netnhor 1_ 10AG

1  ! '

e -, .-, _ - -

' l OMAHA PUBLIC POWER DISTRICT l Fort Calhoun Station Unit No. 1 i r

September, 1985 i Monthly Operations Report i I. '

OPERATIONS

SUMMARY

f i

Fort Calhoun Station operated at 100% power until September 27, 1985, [

when a power reduction was started in preparation for the 1985 refueling  !

outage. On September 28, after 195 days of continuous operation, the -

unit was taken off line. Turbine overspeed and other equipment tests  !

were performed. Prior to commencing plant cooldown, hot degassing of the reactor coolant system was performed for the first time with very t

favorable results. ,

i Three Auxiliary Operators-Nuclear were hired dirring September. The  ;

following training classes have been in progress through the month: }

SR0 upgrade with four candidates, Equipment Operator-Nuclear (Turbine)  !

., with seven students, Auxiliary Operator-Nuclear with four students, I l- operator requalification, C/RP technician, emergency plan and general  ;

employee training.

4

} An Unusual Event was declared on September 8,1985, due to a leaky i chlorine bottle which was quickly contained. Poison pins for use in i

, the Cycle 10 core have been loaded in the new fuel, i

{ i No safety valve or PORV challenges or failures occurred. i i

i A. PERFORMANCE CHARACTERISTICS D L t

None I i

B. CHANGES IN OPERATING METHODS  !

4 None

, [

C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS i None -

l D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL i

Procedure Description j

[

.SP-FAUD-1 Fuel Assembly Uplift Condition Detection.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it only involved the evaluation of data from a ,

surveillance test to verify that a fuel assembly l uplift condition did not exist.  :

4 ,

F

I i

. 8 i Monthly Operations Report [

JSeptember,1985  ;

4 ,

Page Two l

• )

I h CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL i

[s D.

s3 (Cor.tinued)

( . Procedure Description

{

SP-SGLVT-1 ' Steam Generator Level Test. I

[

This ~ procedure did not constitute an unreviewed e safety question as defined by 10CFR50.59 since  ;

the steam generator level was merely lowered to

~

i near its design level *64% (temporarily) in an  !

effort to document steam quality changes. Upon j completion of the sp'ecial procedure, the steam  ;

1 generator operating levels were returned to normal operating levels (i.e. , approximately 70%).  ;

i System Acceptance Comittee Packages for September,1985: i

. Package Description / Analysis f EEAR FC-70-ll New fuel Elevator / Spent Fuel Interlock.  !

This modification adds limit contacts required f o, - '

to- prevent accidental insertion of a spent fuel i assembly into the new fuel elevator and raising l it out of the water. This modification does not i have an adverse effect on the safety analysis.

EEAR FC-82-72 Chemical Lagoon Influent pH.

[

This modification was installed to ensure effluent I from the water plant to the waste lagoons is with  :

a specified pH range. This pH will be controlled  !

via a " holding basin" which has accessories to i raise or lower basin pH as necessary. Therefore,  ;

all effluent to the lagoons are of proper pH.

j This modification does not have an adverse effect  !

on the safety analysis. "

EEAR FC-83-107 Intake Structure Ventilation. i This modification provides forced air cooling to f the circulating water pumps' upper bearings. '

This modification does not have an adverse effect r on the safety analysis. ,

s , ,

s Y

W e -. ,e-,- , - , - , -,,,-.,.--c-.., - . , , , - , , --e-- - - ,+ n-,-

Monthly Operations Report September, 1985 ,

Page Three D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMISSION APPROVAL (Continued)  ;,

System Acceptance Committee Packages for September,1985: (Continued)

Package Description / Analysis EEAR FC-84-93 Undersized HGA Relays in Control Circuits for HCV-247, 248, 249 and 2988.

, r This' modification eliminated or changed control relays internal to the circuits / circuitry of valves HCV-247, 248, 249 and 2988. The changeout was warranted since, under a specific sequence of operating events, the existing relays would arc.

This modification does not have an adverse effect on the safety analysis.

EEAR FC-84-158 E-Field 14 Relocation.

This modificati'on expanded the E-field (Zone 14) l so that a previo'usly known " dead zone" would be i eliminated. This modification does not have an adverse effect on the safety analysis.

• EEAR FC-85-04 Alarm Indication for Door 989-20. l This modification eliminates or isolates wiring previously snared between Door 989-19 and 989-20.  !

Previously, the alarm for 989-19 would alarm regardless of which door (989-19 or 989-20) was i opened. This modification allows for each door to trigger a separate alarm. This modification does not have an adverse effect on the safety analysis.

EEAR FC-85-37 Replacement of . Perimeter Security Cameras.

This modification changed the perimeter security cameras to a different brand /model. The function of the cameras remained unchanged. This modifi-cation does not have an adverse effect on the i safety analysis.

EEAR FC-85-81 i Security' Fence.

This modification allowed for alteration of the existing security fence .in order to upgrade to existing security plan standards. This modifi-cation.does not have an adverse effect on the

. safety analysis.

Monthly Operations Report September, 1985 i i Page Four 1

E. ' rsulTS OF LEAK RATE TESTS Refueling leak testing is in progress. Total leakage will be reported y after testing is completed.

1 i

l F. CHANGES IN PLANT OPERATING STAFF l During September, Fred Klauzer, Bill McMillian and John Goodell

reported to work as Auxiliary Operators-Nuclear.

G. TRAINING j During September, Emergency Operating Procedure training' for licensed i

operators commenced. Training continued for auxiliary operators, 1 '

turbine room operators, SR0 candidates, chemistry technicians and health physics technicians.

H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION

• i AUTHORIZATION PURSUANT TO 10CFR50.59 None II. MAINTENANCE (Significant Safety Related)

A report of all significant safety related maintenance performed during 4

the 1985 refueling outage will be submitted at'the , conclusion of the outage.

cf' 4V. / b W. Gary Gates Manager Fort Calhoun Station i

1 1

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Omaha Public Power District 1623 Harney Omaha Nebraska 68102 402/536 4000 October 11, 1985 LIC-85-456 Mr. James M. Taylor, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D. C. 20555

Reference:

Docket No. 50-285

Dear Mr. Taylor:

September Monthly Operating Report Please find enclosed ten (10) copies of the September,1985 Monthly Operating Report for the Fort Calhoun Station Unit No. 1.

Sincerely, R. L. Andrews Division Manager '

Nuclear Production RLA/TPM/rs Enclosures cc: NRC Regional Office Office of Management & Program Analysis (2)

Mr. R. R. Mills - Combustion Engineering Mr. T. F. Polk - Westinghouse Nuclear Safety Analysis Center INP0 Records Center l American Nuclear Insurers l NRC File as st24 Employmen n al opportunity