ML20203B844

Monthly Operating Rept for Mar 1986

ML20203B844
Person / Time
Site:	Fort Calhoun
Issue date:	03/31/1986
From:	Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	Taylor J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LIC-86-142, NUDOCS 8604180267
Download: ML20203B844 (11)

Text

C AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT Fort Calhoun Station April 3, 1986 DATE COMPLETED BY T. P. Matthews TELEPHONE 402-536-4733 MONTH March, 1986 .

DAY. AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL .

. (MWe Net) (MWe-Net)

I AAA 0 17 4A6.6 2 486.B is 485.5 486.8 39 352.1 3

4 AR7 1 20 317.4 5 487.3 21 318.5 6 487.8 22 110 1 7 486.6 23 318.3 g 486.1 24 322.2 9 485.8 25 adR A 10 485.0 26 475.2 484.7 27 397.3 404'7 28 -

110.8 12 13 484.7 29 110.4 34 483.6 30 111.3 484.1 3, 151.4 15 16 484.R INSTRUCTIONS On this format. list the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/771 8604180267 860331 '

PDR ADOCK 05000285 R PDR l fI

OPERATING DATA REPORT DOCKET NO.

50-285 _

DATE apr11 J, 1986 COMPLETED BY I. V. Matthews.

TELEPHONE 402-536-4733 OPERATING STATUS Notes -

1. Unit Name: Fort Calhoun Station .

2. Reporting Period: March,-1986

3. Licensed Thermal Power (MWt):

1500 ,

4. Nameplate Rating (Gross MWe): 502

5. Design Electrical Rating (Net MWe):

470

6. Maximum Dependable Capacity (Gross MWe):

7. Maximum Dependable Capacity (Net MWe): 478

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

N/A

9. Power Level To Which Restricted. If Any (Net MWe): N/A

10. Reasons For Restrictions.lf Any: None This Month Yr to.Date Cumulative -

I1. Hours in Reporting Period 744.0 2.160.0 'l09.706.0

12. Number Of Hours Reactor Was Critical 744.0 1,964.6 83,710.8

13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5 14.~ Hours Generator On-Line 744.0 1,788.7- 82,91I.6

15. Unit Reserve Shutdown Hours 0.0 0.0 'O.0

16. Gross Thermal Energy Generated (MWH) Q41'491 R 1_056_n1R_7 Inq_7n7_nR7 R .

17. Gross Electrical Energy Generated (MWH) 11a;11A n ,_. gas;9aq ? 1a g?q,ntn 9

18. Net Electrical Energy Generated (MWH) 749.445.1 611_R07_1 11.041.7n0.7 ,

19. Unit Service Factor inn n R9 n 74 g

20. Unit Availability Factor 100_O R2.R 75.6

21. Unit Capacity Factor (Using MDC Net) 84.3 59.4 65.4

22. Unit Capacity Factor (Using DER Net) 84.3 59.4 63.4

23. Unit Forced Outage Rate 0.0 0.0 3.4

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

NONE

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

26. Units In Test Status (Prior to Commercial Operationi: Forecast Achiesed INITIAL CRITICALITY 374 INITIA L ELECTRICITY COMMERCIA L OPER ATION (9/77)

DOCKET NO. 50-285 UNIT SHUTDOWNS AND POWER REDUCTIONS . UNIT NAME For<: Calhoun Station DATE ' April 3.1986 COMPLETED BY T.P. Matthews REPORT MONTH March, 1986 TELEPHONE 402-536-4733 No. Date

%o- .$E 3 5j 3g .5

,c g 5

. Licensee Event

,E%

ug o"

. Cause & Corrective Action to P

$E $ jgg Report *r NU j Prevent Recurrence d

86-01 860319 F 0 A 4 N/A IIH Motorx A power reduction occurred on March 19, 1986, when two heater drain pump motors were damaged. Power was held at 70% while repairs were made and then the unit returned to 100% power on March 25, 1986.

4 N/A XX xxxxxxx On March.27, 1986, a power reduction 86-02 860327 F 0 F was required due to secondary chem-istry chloride limits being out of specification for 7 days. The second-ary chemistry was brought back into specification on March 31, 1986 and a power increase to 100% was under way the same day.

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 or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3 Automatic Scram. Event Report (LER) File (NUREG-D Regulatory Restriction 4-Other (Explain) 01611 E-Operator Training & License Examinatioi F-Adrr.inistrative 5 G-Operational Error (Explain) Exhibit I - Same Source

. (9/77) llother (Explain)

Refueling Information Ebrt Calhoun - Unit No.1 Report for the month ending Mar,h. tong .

1. Scheduled date for next refueling shutdown. March. 1987 2.- Scheduled date for restart following refueling. Mav. 1987

3. Will refueling or resunption 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 Otrnmittee 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. Inportant licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performanw 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 assentlies: a) in the core 133 assablies b) in the spent fuel pool "

348 i c) spent fuel pool storage capacity 729 d) planned spent fuel pool May be increased storage capacity via fuel pin "

consolidation

7. 'Ihe projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. 1996 Prepared by g

M, Date April 3, 1986 l

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

SUMMARY

Fort Calhoun Station operated at 100% power until March 19, 1986, when two heater drain pump motors were damaged. Power was held at 70% while repairs were made and then returned to 100% on March 25, 1986.

On March 27, 1986, a power reduction to 30% was required due to secondary chemistry chloride limits'being out of specification for seven days. The secondary chemistry was brought back into specification on March 31 and a power increase to 100% was under way the same day.

During the month of March five persons took the Senior Reactor Operator exam. Of the five, four passed and the fifth failed one'section. Two persons took the Reactor Operator exam with one pass and one fail.

Inspection of spent fuel was completed with indications of possible cladding degradation on one fuel assembly (HA24).

No safety valve or PORV challenges or failures occurred.

A. PERFORMANCE CHARACTERISTICS None L. 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-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 surveil-lance test to verify that a fuel assembly uplift condition did not exist.

I Monthly Operations Report

. March, 1986 l Page Two D. CHANGES, TESTS AND EXFERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description SP-VA-80 Hydrogen Purge System Test.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because the procedure only checks operability of fans and cleanliness of the filters.

System Acceptance Committee Packages for March, 1986:

1 Packace Descrintion/ Analysis 1 DCR 74A-21D Steam Generator Blow Down HVAC in Room 20.

This modification provided for the installation of the HVAC to collect radioactive gases and eject them in the controlled area ventilation. This modification does not have an adverse effect on the safety analysis.

EEAR FC-81-99, Modified MI Cable Connector Part 15 Supports.

This modification provided for lengths of 1/4" angle to be bolted to existing MI cable seismic supports beneath the cable trays and on the head lift rig seismic skirt to provide a surface through which connectors can pass and be rigidly mounted yet still be attached to the unistrut. This modi-fication does not have an adverse effect on the safety analysis.

EEAR FC-81-107 HVAC for Unassigned Room in TSC.

This modification provided for the installation of HVAC in the non-controlled area of the TSC. This modification does not have an adverse effect on the safety analysis.

Monthly Operations Report March, 1986 Page Three D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)

System Acceptance Committee Packages for March, 1986:

Packace pescription/ Analysis EEAR FC-82-02 Screen Wash Pumps Secondary Suction.

This modification provided for the installation of a cyclone sand separa-tor for the screen wash pumps and new sump pumps in the intake structure.

This modification does not have an adverse effect on the safety analysis. j EEAR FC-82-08 Warehouse Heating. l This modification provided for the installation of new heaters in the warehouse. This modification does not l have an adverse effect on the safety analysis.

EEAR FC-82-150 Replacement of Vacuum Deaerator Pumps DW-46A and DW-46B.

This modification provided for the replacement of existing vacuum pumping stations with Leybold-Heraeus Ruvac WAU-2000 Roots Pump, S250C Varovac Rotary Vane Pump and Condenser with receiving tank. This modification does not have an adverse effect on the safety analysis.

EEAR FC-83-65 Profilter for Auxiliary Building HEPA.

This modification provided for the installation of profilters on VA-39 filters. This modification does not have an adverse effect on the safety analysis.

4

Monthly Operations Report March, 1986 Page Four-D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)

System Acceptance Committee Packages for March, 1986:

Packace Descrintion/ Analysis EEAR FC-83-147 "A" Channel Flow Transmitter A/DPT-114Y Changeout.

This modification provided for the replacement of the reactor coolant flow Barton transmitter Model 752 with a CQE Rosemount transmitter. This modifica-tion does not have an adverse effect on the safety analysis.

1 EEAR FC-84-08 Upgrade Emergency Personnel 1 Decontamination Facility.

This modification provided for the remodeling of four. rooms in the GET building for improved decontamination shower facility; installation of a lift station for liquid waste retention and disposal; and replacement of the water.

service line to the GET building. This modification does not have an adverse effect on the safety analysis.

EEAR FC-84-63/64 Improved Performance of VA-46 (Control Room Air Conditioning).

This modification provided for the installation of positioners on valves HCV-2898B and HCV-2899B. This modifi-cation does not have an adverse effect on the safety analysis.

EEAR FC-84-70 Motor Operated Drain Valves for Main l Steam Stop Valves.

This modification provided for the replacement of main steam stop valves MOS-SV-1, 3, 5 and 7. This modifica-tion does not have have an adverse effect on the safety analysis.

r-.

.' . I-Monthly Operations Report March, 1986

'Page'Five ,

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

System Acceptance Committee Packages for March, 1986:

Packaae- Description /Ap31vsis EEAR FC-84-162 Containment Ventilation Duct Supports.

This modification was installed to change existing HVAC ductwork supports to allow easier access to areas north of the PAL door in the containment building. This modification does not.

have an adverse effect on the safety analysis.

EEAR FC-85-62 Replacement of FE-498.

This modification provided for the replacement of FE-498 in the component cooling water system. This modifica-tion does not have an adverse effect on the safety analysis.

EEAR FC-85-94 Extraction Steam Elbow /Line Replacement.

This modification provided for the replacement of the elbows in~the second and fourth stage extraction lines which showed wear with chrome-molly elbows.

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

EEAR FC-85-211 Replace Level Indicator LI-10lY.

This modification provided for the replacement of LI-10lY. This modification does not have an adverse effect on the safety analysis.

E. RESULTS OF LEAK RATE TESTS None F. CHANGES IN PLANT OPERATING STAFF None

Monthly Operations Report

. March, 1986 Page Six ,

G. TRAINING A requalification examination prepared by the NRC was administered to five Senior Reactor. Operator license-holders and two Reactor Operator license holders. The 1986 simulator training was begun at Combustion Engineering.

These sessions include new material on diagnostic and team skills. Normal initial and.requalification training continued in operator, maintenance, chemistry / health physics and shift-technical advisor areas.

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

None W. Gary Gates Manager Fort Calhoun Station

l l

II I Omaha Public Power District 1623 Harney Omaha, Nebraska 68102-2247 402/536-4000 April 11, 1986 LIC-86-142 l

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:

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

Sincerely, 4J R. L. Andrews Division Manager Nuclear Production RLA/TPM/me Enclosures cc: NRC Regional Office Office of Management & Program Analysis (2)

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

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