ML20199G052

Monthly Operating Rept for May 1986

ML20199G052
Person / Time
Site:	Fort Calhoun
Issue date:	05/31/1986
From:	Andrews R, Gates W, Matthews J OMAHA PUBLIC POWER DISTRICT
To:	Taylor J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-86-281, NUDOCS 8606250004
Download: ML20199G052 (11)

Text

i AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-285 Fort Calhoun Station UNIT DATE June 5. 1986 T. P. Matthews COMPLETED BY 402-536-4733 TELEPHONE MONTH May 1Q M DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NetI (MWe-Net) 474.7 477.9 i7 i

475.3 2

47L 2 18 474.9 3

477.5 19 4

477.5 20 474 2 474.0 21 474.8 5

474.9 472.9 22 6

4 2.4 7

23 474.9 471.8 24 474 0 8

471.2 9

25 475.1 to 468.6 26 475 3 469.3 II 27 475.3 475.3 12 470 4 28 470.5 29 475.2 13 472.9 474.4 14 30 473.7 474.0 3:

15 16 473.6 INSTRUCTIONS On this format,hst the average daily unit power level in MWe. Net for each day in the reportmg month. Compute to the nearest whole megawatt.

(9/77) f gE74 a

ll:

OPERATING DATA REPORT DOCKET NO. En ?RG DATE limo R.1986 COMPLETED BY T. P. Matthews TELEPilONE 4n2-536-4733 OPERATING STATUS N

1. Unit Name:

Fort Calhoun Station

2. Reporting Period:

May. 1986

3. Licensed Thermal Power (MWt):

1500

4. Nameplate Rating (Gross MWe):

502

5. Design Electrical Rating (Net MWe):

47R 502

6. Maximum Dependable Capacity (Gross MWe):

478

7. Maximum Dependable Capacity (Ner MWe):

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

N/A

9. Power Lesel To which Restricted.lf Any (Net MWe):

N/A

10. Reasons For Restrictions. lf Any:

None This Month Yr..to Date Cumulative

11. Hours in Reporting Period 744.0 3,621.0 111_164.n

12. Number Of flours Reactor Was Critical 744.0 3.427.6 85.173.8

13. Reactor Resene Shutdown flours 0.0 0.0 1,309.5

14. Hours Generator On-Line 744.0 3.251.7 84.374.'6

15. Unit Resene Shutdown Hours 0.0 0.0 0n

16. Gross Thermal Energy Generated (MWil) 1.109.6R2_R 4_12R_1Rn.6 In7 R70;??G.9

17. Gross Electrical Energy Generated (MWH) 369 414,0. 1.371.R55.9 1R.196 d9d_?

3

18. Net Electrical Energy Generated (MWil) 352.664.5 1.307.670.7 33.785.564.1

19. Unit Senice Factor 100.0 RQ_R 75.q

20. Unit Asailability Factor 100.0 89.8 75.9

21. Unit Capacity Factor (Using MDC Neti 99.2 75.5 65.9

22. Unit Capacity Factor (Using DER Net) 99.2 75.5 63.8

23. Unit Forced Outage Rate 0.0 0.0 3.4

24. Shutdowns Scheduled Oser Nest 6 Months IType. Date,and Duration of Each):

Nnno

25. If Shur Down At End Of Report Period. Estimated Date of Startup: N/A

26. Units in Test Status (Prior to Commercial Operation):

Forecast Achiesed INITIA L CRITICALI TY INITIAL ELECTRICITY N/A CO\\lMERCIAL OPER A'ilON (9/77)

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l UNIT SHUTDOWNS AND POWER REDUC 110NS DOCKET NO.

60- N UNIT NAME Fnrt ralhnnn Etation DATE June 5. 1986 REPORT MONTH May. 1986 COMPLETED BY T_ P_ Matthows TELEPHONE an?_c;1s; a711 r

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Action to Prevent Recurrence i

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i There were no unit shutdowns or power reductions during the month of May, 1986.

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m F: Forced Reason:

Method:

Exhibit C. Instructions S; Scheduled A-Equipment Failure (Explain)

I-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3-Automatic Scram.

Event Report (LE R) File (NUREG-D-Regularory Restriction 4-01her (Explain )

0161) fi-Operator Training & License Examination F-Administrative 5

l G-Operational Error (Explam)

Exhibit I - Same Source t

(9/77) 110 her(Explain)

Refueling Information Fort Calhoun - Unit No. 1 Report for the month ending May. 1986 1.

Scheduled date for next refueling shutdown.

March. 1987 2.

Scheduled date for restart following refueling.

May. 1987 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?

Fuel supplier change from ENC to CE and possible Technical Specification change.

b.

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

February. 1987 5.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuei design, new operating procedures.

New fuel supplier (Combustion Engineering) but the new fuel will be essentially the same as that supplied by Combustion Engineering for Cycle 5.

6.

The number of fuel assemblies: a) in the core 133 assemblies b) in the spent fuel pool 348 c) spent fuel pool storage capacity 729 d) planned spent fuel pool May be increased storage capacity via fuel oin consolidation 7.

The arojected date of the last refueling that can be disclarged to the spent fuel pool assuming the present licensed capacity.

1996 Prepared by M -

Date June 2. 1986

=

i i

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 May, 1986 Monthly Operations Report i

I.

OPERATIONS

SUMMARY

Fort Calhoun Station operated at 100% power throughout May, 1986.

Licensed-operator requalification simulator training at Combustion Engineering in Windsor, Connecticut, was completed in May. New subjects covered in the training included team skills and event diagnosis.

On May 1,1986, a Notification of Unusual Event was declared when a gas leak occurred on the sampling system. The duration of the offsite release was approximately two minutes.

l J

On May 2,1986, the Regulatory Effectiveness Review (RER) team completed a check of the security hardware systems. Also in May, a routine unannounced 4

4 audit was performed by the NRC in the areas of security records and staffing.

The R0 and SR0 who failed the March NRC requal exam successfully completed the exam and their licenses were reinstated during May.

Non-licensed i

operator refresher training and general employee training continued.

No safety valve or PORV challenges or failures occurred.

A.

PERFORMANCE CHARACTERISTICS t

None i

I l

B.

CHANGES IN OPERATING METHODS l

None 1

l C.

RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS f

None D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL i

Procedure Description SP-FE-1 Visual Inspection of Irradiated Fuel.

J This procedure did not constitute an unreviewed i

safety question as defined by 10CFR50.59 since it only provided for visual inspection of discharged fuel assemblics.

Inspections were performed with underwater video equipment in accordance with l

radiological protection requirements.

1

. - ~..

Monthly Operations Report May, 1986 Page Two D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)

Procedure Description SP-S0V-1 Periodic Cycling of Solenoid Valves Preventive Maintenance to Maintain 79-01B Qualification.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because the procedure was used to maintain qualification of HCV-2630 solenoid valve. The valve was cycled to prove operability during the 1985 outage.

SP-RRC-2 Reactivity Computer Setup.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because the procedure only provides for setup of temporary test instrumentation. Appropriate technical specification requirements in regard to operability of the reactor protective system are observed.

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

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because the procedure only provides for calibration of test equipment (the reactivity computer).

System Acceptance Committee Packages for May, 1986:

Package Description / Analysis DCR 74A-21I Steam Generator Blowdown Processing System (HELB Flooding).

This modification provided for the installation of check and control valves in the steam generator blowdown processing system to decrease the effects of a high energy line break.

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

l Monthly Operations Report May, 1986 Page Three D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)

System Acceptance Committee Packages for May, 1986:

Package Description / Analysis EEAR FC-79-200 Isolation for PCV-2612 (Hydrogen to VCT).

This modification provided for the insta}lation of an isolation valve in the hydrogen supply header to the VCT.

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

EEAR FC-79-210 Isolation of PCV-2611 (Nitrogen to VCT).

This modification provided for the installation of an isolation valve in the nitrogen supply header to the VCT.

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

EEAR FC-81-99, HJTC Pressure Boundary.

Part 8 This modification provided-for the replacement of two flanges on the reactor head. This modification does not have an adverse effect on the safety analysis.

EEAR FC-81-99, Install HJTC Probe Holder in UGS.

Part 9 This modification provided for the installation of a HJTC probe holder in the UGS. This modification does not have an adverse effect on the safety analysis.

EEAR FC-81-163 Sanding In of Condensate Cooler.

This modification provided for the fabrication and installation of a screea to fit over the mouth of the condensate cooler suction piping in "A" condenser.

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

EEAR FC-82-117 Relay Supervision of Manual Generator Synchronizing.

This modification provided for the installation of new protective relaying equipment for the generator. This modification does not have an adverse effect on the safety analysis.

l I

Monthly Operations Report May, 1986 Page Four D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)

System Acceptance Committee Packages for May, 1986:

Package Description / Analysis EEAR FC-82-146B Installation and Testing of HCV-335.

This modification provided for the replacement of valve HCV-335. This modification does not have an adverse effect on the safety analysis.

EEAR FC-82-148 Manual Test Signal for Control Room Walk-In Closet Halon System.

This modification provided for the installation of a new manual pull station for control room walk-in cabinet. This modification does not have an adverse effect on the safety analysis.

EEAR FC-82-178 HEPA Filter Delta P Indication Gauges.

This modification provided for the installation of differential pressure gauges across all HEPA and carbon filters in the plant. This modification does not have an adverse effect on the safety analysis.

EEAR FC-83-83 Containment Pressure Switches.

This modification provided for the replacement of eight containment pressure switches that initiate the containment pressure high signal. This modification does not have an adverse effect on the safety analysis.

EEAR FC-84-016 480V Load Shed Switch Replacement.

This modification provided for the replacement of key lock 480V load shed switches CS-A/LS and CS-B/LS, device numbers 174 and 474 on panels AI-30A and AI-30B, respectively. This modification does not have an adverse effect on the safety analysis.

EEAR FC-84-57 Instrument Air Isolation Valves.

This modification provided for the installation of isolation valves in the instrument air system. This modification does not have an adverse effect on the safety analysis.

Mor.thly Operations Report May, 1986 Page Five D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)

System Acceptance Committee Packages for May, 1986:

Package Description / Analysis EEAR FC-84-126 Fire Protection for FW-10.

This modification extended the fire barrier into an "L" shaped configuration. The barrier now extends along the north and west side of FW-10. A security camera was also relocated. This modification does not have an adverse effect on the safety analysis.

EEAR FC-84-152 TM/LP Trip Drawer Modifications.

This modification provided for the addition of the ASI function into the calculation of PVAR, thereby adding more operating margin.

It also deleted the flow dependent selector switch. This modification does not have an adverse effect on the safety analysis.

EEAR FC-84-205B Barrier Installation.

This modification provided for the installation of an intrusion screen over the intake structure windows and intake vent for cooling air to the circulating water pumps. This modification does not have an adverse effect on the safety analysis.

EEAR FC-85-08 Boric Acid Addition System.

This modification provided for the replacement of the phosphate tank with a new stainless steel tank and mixer to add boric acid to the secondary side.

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

EEAR FC-85-80 Redundant Fusing for Alternate Shutdown Circuits.

This modification provided for the installation of redundant fuses in alternate shutdown circuits for PORV PCV-102-2, CH-1B; pressurizer heaters bank 4, group 10, 11 and 12; and instrumentation loops T1210, T121H, L101Y, L219 and P115. This modification does not have an adverse effect on the safety analysis.

Monthly Operations Report May, 1986 Page Six D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)

System Acceptance Committee Packages for May, 1986:

Package Description / Analysis EEAR FC-85-197 Removal of AI-126.

This modification provided for the removal of AI-126 and does not have an adverse effect on the safety analysis.

E.

RESULTS OF LEAK RATE TESTS None F.

CHANGES IN PLANT OPERATING STAFF None G.

TRAINING During May, the R0 and SRO who failed the March NRC requal exam successfully completed the exam and their licenses were reinstated.

Non-licensed operator refresher training and general employee training continued.

H.

CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT T0 10CFR50.59 None II. MAINTENANCE (Significant Safety Related)

None W. Gary G es Manager Fort Calhoun Station

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l Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 402/536 4000 June 13, 1986 LIC-86-281 Mr. James M. Taylor, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Comission Washington, DC 20555

Reference:

Docket No. 50-285

Dear Mr. Taylor:

May Monthly Operating Report Please find enclosed ten (10) copies of the May, 1986 Monthly Operating Report for the Fort Calhoun Station Unit No.1.

Sincerely, R. L. Andrews Division Manager Nuclear Production RLA/TPM/jb Enclosures cc: NRC Regional Office Office of Management & Program Analysis (2)

Mr. R. R. Mills - Combustion Engineering Mr. R. J. Simon - Westingiiouse Nuclear Safety Analysis Center INP0 Records Center American Nuclear Insurers NRC File 6.

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