ML20210A809

Monthly Operating Rept for Aug 1986

ML20210A809
Person / Time
Site:	Fort Calhoun
Issue date:	08/31/1986
From:	Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	Taylor J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-86-466, NUDOCS 8609170348
Download: ML20210A809 (15)

Text

s AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50 7R4 Fort Calhoun Station UNIT September 8, 1986 DATE COMPLETED BY T. P. Matthews 402-536-4733 TELEPHONE August, 1986 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (Mwe. Net)

(MWe-Net)

I 11 R 17 375.3 376.0 0.0 is 2

0.0 19 376.8 3

377.4 111.6 20 4

375.2 293.1 21 5

358.8 376.2 22 6

15.3 377.1 23 7

109.3 377.3 24 8

277.1 378.3 25 9

449.8 378.1 26

,o 385.0 27 459.7 379.1 464.8 12 28 379.0 470.9 13 29 378.3 476.7

,4 39 377.7 476.9 15 3:

376.2 16 INS 7 RUCTIONS On this format.hst the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77 )

8609170348 860831 DR ADOCK 05000205 PDR SX'hsh

OPERATING DATA REPORT 8

DOCKET NO. 50-285 DATE SeDt. 8.1986 COMPLETED BY T. P. Matthews TELEPHONE 402-536-4733 OPERATING STATUS Fort Calhoun Station Notes

1. Unit Name:

August, 1986

. 2. Reporting Period:

3. Licensed Thermal Power (MWt):

1500 502

4. Nameplate Rating (Gross MWe):

478

5. Design Electrical Rating (Net MWe):

502

6. Maximum Dependable Capacity (Gross MWe):

470

7. Maximum Dependable Capacity (Net MWe):

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

N/A N/A

9. Power Level To Which Restricted.If An (Net MWe):

one

10. Reasons For Restrictions. lf Any:

This Month Yr. to Date Cumulative 744.0 5.831.0 113,377.0

11. Hours In Reporting Period 697.5 5,556.3 87.302.5

12. Number Of Hours Reactor Was Critical 0.0 0.0 1,309.5

13. Reactor Reserve Shutdown Hours 660.4 5,335.2 gg,agg_1

14. Hours Generator On-Line 0.0 0.0 0.0

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH) 757.556.3 6.964.366.0 110,715,410.6 255,612.0 2,308,411.2 36,292,980.2

17. Gross Electrical Energy Generated (MWH) 240,448.4 2,196,188.6 34,674,082.0

18. Net Electrical Energy Generated (MWH) 88.8 91.5 76.3

19. Unit Service Facto, 88.8 91.5 76.3

20. Unit Availability Factor 67.6 78.8 66.2

21. Unit Capacity Factor (Udng MDC Net) 67.6 78.8 64.2

22. Unit Capacity Factor (Using DER Net) 9.1 2.0 3.4

23. Un.t Forced Outage Rate

24. Shutdowns Scheduled Over Nest 6 Months (Type.Date.and Duration of Each):

None N/A

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

26. Units in Test Stalus (Prior to Commercial Operationi:

Forecast Achiesed INITI AL CRITICALITY INITIAL ELECTRICITY N/A COMMERCI AL OPER ATION (9/77)

s I,

DOCKET NO.

60 N UNIT SHUTDOWNS AND POWER REDUC 110NS UNITNAME Fort Calhoun Station DATE September 8, 1986 COMPLERD BY T. P _ Matthews REPORTMONTit Auoust. 1986 TELEPHONE an? rMA 4711 l

8 s

j3 3

Y Licensee 5%

• 1, Cause & Corrective No.

Date i

3g i

2g5 Event 13 g3 Action to y~

5 jgg Report =

mO O

Prevent Recurrence g

6 86-05 860801 F

66.4 A

2 LER-8604 EL BDUCXX On August I, 1986, at 0125, the reactor and turbine-generator were manually tripped due to bus duct in--

sulation and ground strap overheating.

The unit returned to service Aug. 3, 1986 86-06 860823 S

17.2 H

4 N/A EL BDUCXX On August 23, at 0507, the generator was taken off-line to clean'and re-insulate bus duct covers relating to the August 1 trip. The unit returned-i to service the same day at 2216.

I 2

3 4

w F: Forced Reason:

Method:

Exhibit G. 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 (LER) File (NUREG-D-Regulatory Restriction 44ther (Explain) 0161) l EOperator Training & license Examination F-Administrative 5

{

Goperational Error (Explaint Exhibit I - Same Source (9/77) llother (Explain)

Refueling Infcnnation Fort Calhoun - Unit No.1 Report for the month ending Auaust. 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 Yes license amendment?'

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.

If no such review has taken place, when is c.

it scheduled?

4.

Scheduled date(s) for submitting proposed licensing February. 1987 action and support information.

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 fuel 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 349 c) spent fuel pool storage capacity 729 d) planned spent fuel pool May 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 1996 licensed capacity.

Prepared by MJN Date Auaust 27. 1986

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

OPERATIONS

SUMMARY

Fort Calhoun Station was manually tripped off line on August 1,1986, due to break down of insulation on the generator bus duct cooling. The unit was back on line on August 3, but was limited to 80% power due to amperage restrictions on the bus duct cooling ground straps since the new insulatiori was also breaking down. On August 23, the generator was taken off line and new insulation was installed again. The unit was returned to approximately 97% power. A condensate pump was out of service for repair and overhaul.

The Blair Fire Department and the Fort Calhoun Station Fire Brigade held a joint drill during August. Training continued for licensed operator requalification, non-licensed operator refresher, chemistry / health physics refresher and general employee training.

Initial training continued for C/RP shift technicians and equipment operator nuclear-turbine building.

Diesel generator training was conducted for maintenance and operations personnel.

Safety injection tank level reference legs training was conducted for instrument and control technicians.

Electrician technicians received training on circuit breaker rack in and out (NRC IE Notice 84-38).

Mechanical maintenance personnel received training on Cycle 10 modifications and on flood control.

The NRC was on site to perform an audit of licensed, non-licensed and maintenance training.

No safety valves or PORV challenges or failures occurred.

A.

PERFORMANCE CHARACTERISTICS None B.

CHANGES IN OPERATING METHODS None C.

RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS None

. = -.-

=

l Monthly Operations Report August, 1986 Page Two g

i l

D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Descriotion SP-FAUD-1 Fuel Assembly Uplift Condition Detection.

i This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 since it only involved the evaluation of data from a 4

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

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

1 l

This procedure did not constitute an unreviewed i

safety question as defined by 10CFR50.59 because the procedure is simply an inventory list of qualified 1

equipment and indications located on various panels and control boards in the plant. No plant operations or evolutions are involved.

)

SP-VA-80 Hydrogen Purge System Test.

i This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because 1

this procedure only checks operability of fans and j

cleanliness of the filters.

1 SP-RRC-2 Reactivity Computer Setup.

l This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because this procedure only provides f or the setup of the reactivity computer, a piece of test equipment.

i Technical Specification 2.14 requirements are observed.

SP-50V-1 Periodic Cycling of Solenoid Valves Preventive Maintenance to Maintain 79 018 Qualification.

This procedure did not constitute an unreviewed safety question'as defined by 10CFR50.59 because the procedure was used to maintain qualification of 36 different valves.

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l Monthly Operations Report August, 1986 Page Three D.

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

System Acceptance Committee Packages for August, 1986:

Packacq Description / Analysis DCR 73-019 Insulate and Heat Trace Process Radiation Monitor Sample Lines to Stack.

This modification provided for the installation of insulation and heat trace process to the radiation monitor sample lines to the stack. This modifica-tion does not have an adverse effect on the safety analysis.

DCR 73-036 Manual Override Switches for Diesel Start.

This modification provided for the installation of manual override switches to prevent unnecessary diesel starts during testing of the RPS. This modification does not have an adverse effect on the safety analysis.

DCR 74A-075 Maintenance Shop Addition.

This modification provided for the construction of the maintenance shop.

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

DCR 75A-027 Turbine Bearing Metal Temperature.

This modification provided for the installation of thermocouples and a temperature recorder with an alarm for turbine bearing metal temperature. This modification does not have an adverse effect on the safety analysis.

DCR 76-087 Secondary Restraints for Feedwater Pumps.

This modification provided for the installation of secondary restraints'for the suction and discharge piping of the main feedwater pumps.

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

DCR 77-034 Containment Jib Crane.

This modification provided for installation of the containment jib crane.

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

l Monthly Operations Report August, 1986 Page Four D.

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

System Acceptance Committee Packages for August, 1986:

Packaae Descriotion/ Analysis EEAR FC-78-032 Backup Cooling to Air Compressors.

This modification provided backup cooling water piping to the air compressors fron potable water.

This potable water cooling can then be used to cool the air compressors when turbine plant cooling water is taken out of service. This modification does not have an adverse effect on the safety analysis.

EEAR FC-79-089 Deluge Valve Trim Modification.

This modification provided for the installation of pressure operated relief valves on deluge valves in the fire protection system.

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

EEAR FC-79-179 Containment Pressure Indication.

This modification provided for the installation of LOCA qualified wide and narrow range containment pressure transmitters and recorders. This modification does not have an adverse effect on the safety analysis.

EEAR FC-79-185 On-Site Technical Support Center.

This modification provided for the installation of the on-site technical support center. This modification does not have an adverse effect on the safety analysis.

EEAR FC-79-190A Containment High Range Radiation Monitors.

This modification provided for the installation of high range radiation monitors in containment. This modification does not have an adverse effect on the safety analysis.

EEAR FC-80-015 Maintenance Platform for Roll-Up Door Operator.

This modification provided for the maintenance platform to be installed to allow easy access to the auxiliary building roll-up door operator.

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

Monthly Operations Report August, 1986 i

Page Five D.

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

System Acceptance Committee Packages for August, 1986:

Packaae Descriotion/ Analysis EEAR FC-80-033 Snubbers for Compliance with IE Bulletin 79-14.

This modification provided for the removal of snubbers on some auxiliary steam lines in the intake structure (snubbers used for spare parts). This modification does not have an adverse effect on the safety analysis.

EEAR FC-81-027 Fuel Transfer Canal Net.

This modification provided for the installation of safety nets above the fuel transfer canal and the new fuel storage area.

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

EEAR FC-81-073A Fire Detector Access Platforms-Turbine Building.

This modification provided for the installation of access platforms and ladder supports for fire detector accessibility in the Turbine Building.

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

EEAR FC-81-073B Fire Detector Access Platforms-Auxiliary Building.

This modification provided for the installation of access platforms and ladder rest assemblies to provide access to fire detectors in the Auxiliary Building. This modification does not have an adverse effect on the safety analysis.

EEAR FC-81-099, Auxiliary HJTC Storage Bracket.

Part 16 This modification provided for the installation of a new storage bracket for the HJTC.

The old bracket was placed in stores.

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

EEAR FC-81-100 Main Feedwater Isolation.

This modification provided for the installation of valves HCV-1385, HCV-1386, HCV-1103 and HCV-1104 to be closed by the SGIS which is made up of CPHS or SGLS and not by CIAS.

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

Monthly Operations Report August,.1986 Page Six D.

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

System Acceptance Committee Packages for August, 1986:

Packaae Descriotion/ Analysis EEAR FC-81-127 Seismic Qualification of Auxiliary Feedwater System.

This modification upgraded the seismic qualification of.the auxiliary feedwater system to the safe shutdown earthquake level. This modification does not have an adverse effect on the safety analysis.

EEAR FC-81-133 Turbine Vibration Recorder / Monitor.

This modification changed GE recorders to L&N 250 recorders. This modification does not have an adverse effect on the' safety analysis.

EEAR FC-82-048 Redesign of MSS-9A to Allow Repair of HCV-10418.

This modification provided for the redesign of snubber support MSS-9A in order to allow repair of HCV-10418. This modification does not have an

' adverse effect on the safety analysis.

EEAR FC-82-077 Condensate Storage Tank Level Indication Revision.

This modification provided for the installation of a new GE GEMAC 556 level transmitter on the condensate storage tank. This modification does not have an adverse effect on the safety analysis.

' EEAR FC-82-149 Shower in TSC Battery Room.

This modification provided for the installation of a safety shower in the TSC battery room. This modification does not have an adverse effect on the safety analysis.

EEAR FC-83-036 On/0ff Switch for Gai-tronics Handset.

This modification provided for the installation of a switch to turn off the handset when the headset was in use on FH-1 and FH-12. This modification does not have an adverse effect on the safety analysis.

Monthly Operations Report August, 1986 Page Seven D.

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

System Acceptance Committee Packages for August, 1986:

Packaae Description / Analysis EEAR FC-83-059 Modify VA-36B Temperature Control System.

This modification provides for better temperature control of the auxiliary building HVAC system be regulating the temperature via air flow and not steam flow to the coil. This modification does not have an adverse effect on the safety analysis.

EEAR FC-83-117 Railroad Siding Bumping Post Removal.

This modification provided for the removal of the railroad bumping post from the auxiliary building railroad bay. This modification does not have an adverse effect on the safety analysis.

EEAR FC-83-122 Varistor HCV-2937 Solenoid.

This modification provided for the installation of varistors on terminals in AI-1288 for HCV-2937, 2968 and 2978. This modification does not have an adverse effect on the safety analysis.

EEAR FC-83-171 Power Supply and Phone Hookup for NRC Van.

This modification provided for the installation of three duplex receptacles on the outside northeast corner of the maintenance shop and a telephone outlet for the NRC van. This modification does not have an adverse effect on the safety analysis.

EEAR FC-83-180 Relocation of Generator Mod 5-E and 4-W.

This modification provided for the relocation of motor operating devices M00-4W and SE from DS/3451-4W and DS/3451-5E to DS/3451-4E and DS/3451-5W and relabelled controls and wiring accordingly. This modification does not have an adverse effect on the safety analysis.

EEAR FC-84-010 Relocation of PAL Alarm for Security Computer.

This modification provided for the removal of the security cage around the PAL area and relocated alarm to PAL door. This modification does not have an adverse effect on the safety analysis.

Monthly Operations Report August, 1986 Page Eight D.

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

System Acceptance Committee Packages for August, 1986:

Packaae Des ~criotion/ Analysis EEAR FC-84-013 Storeroom Window.

This modification provided for the installation of a window on the south wall of the storeroom near the roll-up door. This modification does not have an adverse effect on the safety analysis.

EEAR FC-84-014 Storeroom Walk Door.

This modification provided for the installation of a walk door in the west wall of the storeroom near the roll-up door. This nodification does not have an adverse effect on the safety analysis.

EEAR FC-84-087 Water Plant Gai-tronics.

This modification replaced a desk mounted gai-tronics with a wall mounted gai-tronics and speaker in the water plant office This modification does not have an adverse effect on the safety analysis.

EEAR FC-84-105 4160/480 Volt Transformer Replacement.

This modification provided for replacement of GE 4160/480 volt transformers with Westinghouse transformers. This modification does not have an adverse effect on the safety analysis.

EEAR FC-84-173 Temporary Trailer Installation.

This modification provided for the installation of temporary trailers No. 10, 12, 13, 14, 15, 16 & 18 inside the security fence. This modification does not have an adverse effect on the safety analysis.

EEAR FC-84-181 Steam Generator Blowdown Sodium Analyzers.

This modification provided for the installation of sodium analyzers and associated recorders for steam generators A and B blowdown.

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

j Monthly Operations Report 1

August, 1986 Page Nine

[

s D.

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

System Acceptance Committee Packages for August, 1986:

Packaae Descriotion/ Analysis 1

EEAR FC-85-054 Roll-Up Door Operator.

i This modification provided for the installation of a t

roll-up door operator switch for the turbine building on the outside of the building. This l

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

EEAR FC-85-064 Installation of Additional Lighting in Concentrate i

Pumps Room.

7 This modification provided for the installation of two fluorescent fixtures (80W) and two incandescent globe fixtures. This modification does not have an I

adverse effect on the safety analysis.

l EEAR FC-85-113 Room 7 Vent Header Drains.

t This modification piped the drain lines for the j

waste gas header to the equipment drain header.

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

EEAR FC-85-168 Electrical Power for Additional Training Trailers.

This modification installed electrical power for trailers No. 8 & 9 inside the security fence. This modification does not have an adverse effect on the i

safety analysis, i

l EEAR FC-85-218 Razor Ribbon Installation.

i j

This modification added razor ribbon to the top of the security fence surrounding the vital area of the l

(

plant. This modification does not have an adverse

(

effect on the safety analysis.

l to EFWST.

EEAR FC-86-053 Additional Drain Valve for N2 il This modification installed an additional drain i

valve at a low point in the nitrogen header which I

feeds the emergency feedwater storage tank in Room j

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

4 i

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Monthly Operations Report August, 1986 Page Ten E.

RESULTS OF LEAK RATE TESTS None F.

CHANGES IN PLANT OPERATING STAFF None.

3 G.

-TRAINING 4

The Blair Fire Department and the Fort Calhoun Station Fire Brigade held a joint drill during August. Training continued for licensed operator requalification, non-licensed operator refresher, chemistry / health physics refresher and general employee training.

Initial training continued for C/RP shift technicians and' equipment operator nuclear-turbine building. Diesel generator training was conducted for maintenance and operations personnel. Safety injection tank level reference legs training was conducted for instrument and control technicians.

Electrician technicians received training on circuit breaker rack in and out (NRC IE Notice 84-38). Mechanical maintenance personnel received training on Cycle 10 modifications and on flood control.

The NRC was on site to perform an audit of licensed, non-licensed and maintenance training.

H.

CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment No.

Descriotion 99 The amendment changes the Technical Specifications to incorporate the requirements of 10 CFR 50.72 and 10 CFR 50.73.

II. MAINTENANCE (Significant Safety Related)

None I

Wf b

W. Gary Gates Manager Fort Calhoun Station

s i

Omaha Public Power District 1623 Harneu Omaha. Nebraska 68102 2247 402/536 4000 September 12, 1986 1

LIC-86-466 Mr. James M. Taylor, Director Office of Inspection and Enforcement U.S. fluclear Regulatory Commission Washington, D.C. 20555

Reference:

Docket flo. 50-285

Dear fir. Taylor:

August Monthly Operating Report Please find enclosed ten (10) copies of the August, 1986 Monthly Operating Report for the Fort Calhoun Station Unit flo.1.

Sincerely, Il I. h. L; K R. L. Andrews Division Manager Nuclear Production RLA/IPM/me Enclosures cc: f1RC Regional Office i

Office of Management & Program Analysis (2)

R. M. Caruso - Combustion Engineering R. J. Simon - Westinghouse fluclear Safety Analysis Center INP0 Records Center American Nuclear Insurers fiRC file l

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