ML20094R508

Monthly Operating Rept for Jul 1984

ML20094R508
Person / Time
Site:	Fort Calhoun
Issue date:	07/31/1984
From:	Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-84-263, NUDOCS 8408200589
Download: ML20094R508 (10)

Text

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT -. Fort Calhoun Statio:

DATE . Augmt 3,1984 COMPLETED BY .T. P. Matthews TELEPflONE (402) 536-4733 MONTH July, 1984 DAY AVER AGE DAILY POWER LEVEL ' DAY AVER AGE DAILY POWER LEVEL (MWe Net) IMWe Net) 1 0.0 37 158.3 2 0.0 gg 172.0 3 0.0 39 244.1 4 0.0 20 275.0 5 0.0 3 275.7 6 0.0 22 309.7 7 0.0 23 74 1 s 0.0 24 377.0 9 0.0 25 453.7 to 0.0 455.2 26 Ig 0.0 456.7 27

0.0 28 456.3 33 75.6 456.1 29 l4 95.9 456.8 30 I5 97 4 444.6 3

16 123.6 INSTRUCTIONS On this format.hst the a$erage daily unit power lesel in MWe Nel for exh day m the repoinng nionth. Onnpute to the nearest whole nwgawatt.

(9/771 8408200589 840731 PDR R ADOCM 05000205 pyg

OPERATING DATA REPORT DOCKET NO. 50-285 DATE August.__3, 1984 COMPLETED 11Y T. P. Matthews TELEP110NE (402) 536-4733 OPERATING STATUS

1. Unit Name: Ebrt Calhoun Station N"

2. Reporting Period: July, 1984 1500

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross MWe): 501

5. Design Electrical Rating (Net MWe): 478

6. Masimum Dependable Capacity (Gross MWe): 501

7. Masimum Dependable Capacity (Net MWe): 478

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 Cumulative i1. flours in Reporting Period -

744.0 5,111.0 95,113.0

12. Number Of flours Reactor Was Critical 543.9 2,034.1 71,928.0

13. Reactor Resene Shutdown flour, 0.0 0.0 1,309.0

14. Ilours Generator On Line 442.2 1,931.7 71.334.2

15. Unit Rewne Shutdown llours 0.0 0.0 0.0

16. Grow Thermal Energy Generated (MWil) -457,374.1 ,,2_t6_1,0._,171. 0 __89.369.884,2 17 Gross Electrical Energy Generated (Mbil, 104,784.0_ , , 831t042.0 __29,148,611,0_

18. Net Electrical Energy Generated 1Mhil) 130,985.5 787,522.0 27,867,390.7

19. Unit Senice Factor 59.4 37.8 75.0

20. Unit Asailability Facto, 59.4 37.8 75.0

21. Unit Capacity Factor (Using MDC Neti 36.8 32.2 63.9

22. Unit Capacity Factor (Using DLR Neil 36.8 32.2 61.6

23. Uni Forced Outage Rate 2.9 0.7 3.5

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

Nono

25. If Shuillown At End Of Report Period. Estimated llate of Startup: N/A

26. Units in Test Status (Prior to Commercial Operationi: N/A Iorecast Achiesed ,

IN111AL CRITICA LIIY l

INITIT L ELEC TRICITY '

CO\lMLRCl4L OPER AIlON 08/773

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DOCKET NO.

UNIT SHUTDOWNS AND POWER REDUCTIONS t a noun station UNIT NAME DATE August 3, L984 COMPLETED BY T. P. Matthews REPORT MONTH July, 1994 (402) 536-4733 TELEPHONE l _E E i

-, jg 3 j Yl Licensee P. E% Cause & Corrective N. . . Date i 3= 255 Event i? g3 Action to H

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$ jgg Report r mO g' Prevent Recurrence d '

r 84-01 840303 S 3162.5 C 4 N/A XX XXXXXX 1984 refueling outage comnenced March 3,1984. Unit returned to service July 12, 1984.

84-02 840722 F 16.3 H 3 N/A XX XXXXXX 'Ihe reactor tripped when spikes on two of the RPS channels were of sufficient magnitude to cause

'IWLP trips. Noise suppressors and administrative controls were imple-mented as corrective action.

I 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 Scram. Entry Sheets for Licensee C Refueling 3 Automatic Scram. Esent Report (LER) File (NilREG-D-Regulatory Restriction 4-Other (Explain) 0161)

F-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explam) Exhibit i . Same Source 19/77) Ilother (Explain) l

Refueling Information Ebrt Calhoun - Unit No.1 -

Report for the nonth ending July 1984 .

1. Scheduled date for next refueling shutdown. December 1985

2. Scheduled date for restart following refueling. February 1986

3. Will refueling or restmption of operation thereafter require a technical specification change or other license amendment 7 Unknown at this time

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

b. If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Conmittee 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. November 1985

5. Inportant licensing considerations associated with

! refueling, e.g. , new or different fuel design or supplier, unroviewed design or performance analysis

methods, significant changes in fuel design, new a operating procedures.

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6. The number of fuel assenblies: a) in the core 133 asserrblies b) in the spent fuel pool 305 c) spent fuel pool storage capacity 729 i d) planned spent fuel pool May be increased "

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storage capacity via fuel oin consolidation

7. 'Ihe projected date of tin last refueling that can be discharged to the spent fuci pool assuming the present licensed capacity. 1996 41//42/) Date Abgust1,1984 Preparedby_v

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 July, 1984 Monthly Operations Report I. OPERATIONS

SUMMARY

Fort Calhoun Station went critical for Cycle 9 on July 8,1984. After several days of low power physics testing the generator was put online on July 12. Power was increased until the reactor tripped at 85% on July 22. The plant was back online on July 23 and reached 97% power on July 25. Power was reduced to 93% on July 30 for more reactor physics testing.

Operator Control Room Design Review interviews were completed during July, 1984.

1 No safety valve or PORV challenges occurred.

A. PERFORMANCE CHARACTERISTICS LER Number Deficiency 84-006 VIAS Actuation.84-007 VIAS Actuation.84-009 10 CFR 50.49 Testing of Conax Electrical Penetrations.

B. CHANGES IN OPERATING METHODS None C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description SP-GT-2 Gai-Tronics and Nuclear Emergency Alarm Audibility Test for Containment.

This procedure did not constitute an unviewed safety question as defined by 10CFR50.59 as it only involved personnel performing an audibility test of the nuclear emergency horns in containment.

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Monthly Operations R:: port July, 1984 Page Two D. ' CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (Continued)

Procedure Description SP-RRC-3 Reactivity Computer and Reactor Physics Constants Adjustments.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since the procedure involved calibration of the reactivity computer used during physics testing.

SP-EEQ-1 LOCA Qualified Electrical Equipment Identification Check.

This procedure did not constitute an unreviewed safety question because the procedure is simply an inventory list of qualified equipment and indications located on various panels and control boards in the plant. No plant operations or evolutions are involved.

SP-RC-2-1 Plugging Steam Generator Tubes.

This procedure did not constitute an unreviewed safety question because the procedure only provided for the installation of plugs in tubes in "A" steem generator.

SP-WDS-18 NUPAC 14D-2.0 Cask Loading.

This procedure did not constitute an unreviewed safety question because it only provided for loading material in a cask with appropriate radiation protection measures utilized.

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 uplift condition did not exist.

SP-ECT-1 Eddy Current Testing of Heat Exchanger Tubes.

This procedure did not constitute an unreviewed safety question because it only involved eddy current testing on non safety related feedwater heater numbers 4A, 48, 5B and 6A.

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Monthly Op:raticns R: port July, 1984 Page Three System Acceptance Committee Packages for July, 1984:

Package Description / Analysis DCR 03-73 Replacement of Waste Gas Release Valves.

This modification replaced a portion of the waste gas release system with new equipment that will automatically control and record the flow of waste gas vented to the atmosphere. This modi-fication has no adverse effect on the safety analysis.

EEAR FC-79-205 Redundant Level Indication and Alarms for Auxiliary Feedwater System.

This modification installed redundant level indication taps on the strong back to the auxiliary feedwater tank. This modification has no adverse effect on the safety analysis.

EEAR FC-80-88 Addition of Air Operated Valves to HCV-2908, 2918, 2928, 2937 and 2947.

This modification provided for the addition of air operated valves on HCV-2908, 2918, 2928, 2937 and 2947 and modified the control scheme. This modification has no adverse effect on the safety analysis.

EEAR FC-81-09 Upgrading of Harsh Environment Safety Related Solenoids.

This modification provided for upgrading safety related solenoids with qualified replacements.

This modification has no adverse effect on the safety analysis.

EEAR FC-81-17B Qualification of HCV-238 and HCV-239 Solenoids.

This modification provided for raising these solenoids above flood level to ensure qualifi-cation of the valves. This modification has no adverse effect on the safety analysis.

EEAR FC-82-69 Installation of Gai-tronics.

This modification provided for the installation of a gai-tronics station in the auxiliary building near the hand and foot portal monitor.

This modification has no adverse effect on the safety analysis.

- %.. i, Monthly Operations R: port- ~

July, 1984 Page Four

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

System Acceptance Committee Packages for~ July, 1984: (Continued)

Package Description / Analysis ,

i EEAR FC-82-169 N2 Blanket on EFWST..

L This modification provided for supplying nitrogen to the emergency feedwater storage tank from another source. This modification has no adverse effect on the safety analysis.

EEAR FC-83-86 "D" RPS Channel APD Dual Potentiometer Failure.

This modification provided for a new dual potentiometer module equivalent or better

- than the existing module. This modification has no adverse effect on the safety analysis. >

EEAR FC-84-002 VA-43 A/B Heating Coils Replacement.

This modification did not effect a safety related system; therefore, has no adverse effect on the safety analysis.

EEAR FC-84-69 MOV-SV-5 Replacement.

This modification did not effect a safety i related system; therefore, has no adverse effect on the safety analysis.

E. RESULTS OF LEAK RATE TESTS Results of the B and C penentration tests will be submitted under separate cover.

F. CHANGES IN PLANT OPERATING STAFF None G. TRAINING Training for the month of July included fire brigade training for ,

operations.and security personnel, annual requalification exam '

training for operators and systems training for maintenance personnel.

The STA training program is in progress.

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-Monthly Op; rations R: port July, 1984

.Page Five

'e H. . CHANGES, TESTS AND' EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT T0 10CFR50.59 Package Description / Analysis Amendment No. 60 This amendment adds limiting conditions for l

operation and surveillance requirements for reactor coolant system vents and administrative requirements for sampling and analysis of plant effluents.

t l Amendment No. 81 This amendment adds operability and surveillance

!. requirements for the containment wide range J

radiation monitors, wide range noble gas stack j monitors and main steam line radiation monitor.

II. MAINTENANCE (Significant Safety Related)

Will be submitted in the August Monthly Operations Report.

</ &

W. Gary G tes M.h ,

Manager i

Fort Calhoun Station I

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l Omaha Public Power District 1623 Harney Omaha, Nebraska 68102 402/536 4000 August 3,1984 LIC-84-263 Mr. Richard C. DeYoung, Director Office of Inspection and Enforcertent U. S. Nuclear Ibgulatory Cmmission Washington, D.C. 20555

Reference:

Docket No. 50-285

Dear lir. DeYoung:

July bbnthly Operating Report Please find enclosed ten (10) copies of the July Fbnthly Operating Re-port for the Fort Calhoun Station Unit No. 1.

1 Sincgrely,

/ Y( ////4 R. L. Andrews Division Manager Nuclear Production I RLA/TPM:jrtm Enclosures i cc: NIC Regional Office Office of Managment & Program Analysis (2)

Mr. R. R. Mills - Conbustion Engineering Mr. T. F. Polk - Westinghouse Nuclear Safety Analysis Center INPO Records Center NPC File l

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