ML20215C473

Monthly Operating Rept for May 1987

ML20215C473
Person / Time
Site:	Fort Calhoun
Issue date:	05/31/1987
From:	Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LIC-87-424, NUDOCS 8706180133
Download: ML20215C473 (11)

Text

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1 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 l

. UNIT Fort Calhoun Statio DATE June 10. 1987 T. P..Matthews l

COMPLETED 8Y TELEPHONE 402-536-4733 MONT11 May, 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL l

(MWe Net)

(MWe-Net )

0.0 17 0.0 2

0.0 0.0 ig 0.0 0.0 3

,9 0.0 4

20 0.0 5

0.0 21 0.0 6

0.0 0.0' 22

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l.

INSTRUCTIONS l

On this format. list the average daily unit power levelin MWe Net for each day in the reportmg month. Compute to the nearest whole megawatt.

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1 1

i OPERATING DATA REPORT DOCKET NO.

50-285 DATE dune IV, 1987-COMPLETED BY.

T. P. Matthews 4

TELEPHONE 402-536-4733 l

OPERATING STATUS

1. Unit Name:

Fnet Calhoun Station

. Notes 2.' Reporting Period:

May, 1987

3. Licensed Thermal Power (MWt):

unn

4. Nameplate Rating (Gross MWe):

607

5. Design Electrical Rating (Net MWe):

478 502

6. Maximum Dependable Capacity (Gross MWe):

478

7. Maximum Dependable Capacity (Net MWe):

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

N/A

9. Power Level To Which Restricted. lf Any (Net MWe):

N/A

10. Reasons For Restrictions,if Any:

None e

\\

l This Month Yr. to Dare Cumulative

11. Hours in Reporting Period 744.0 3,623.0 119,929.0

12. Number Of Hours Reactor Was Critical 0.0 1,570.8 91,802.3 0.0 0.0 1,309.b

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line nn 1.567.0 90.954.1

.i

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 0.0 2.331,386.2 117,381,888.1 17, Gross Electrical Energy Genera:-4 (MWH) 0.0 785,356.0 38,552,082.2 0.0 751,184.8 36,834,64b./

18. Net Electrical Energy Generatt,4 JdWH)

19. Unit Service Factor 0.0 54.4 76.3

20. Unit Availability Factor 0.0 54.4 76.3 0.0 54.6 66.6

21. Unit Capacity Factor (Using MDC Net)

22. Unit Capacity Factor (Using DER Net) 0.0 54.6 64.9 0.0 0.0 3.3

23. Unit Forced Outage Rate

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

The 10R7 Rnfon14nn Rhntanun enmmenega y 9 3 7, 307, Thn unit wac hrnunht back on-line June'8, 1987.

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

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

Forecast Achiesed I

INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMMERCIA L OPER ATION l

1.

(4/77 )

S I

Refueling Information Fort Calhoun - Unit No. 1 Report for the month ending May 1987 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?

(1)

Fuel ~ supplier change from ANF to CE.

(2)

Increase core inlet temperature back to 545'F from 540*F (Cycle 10)

(3) Replacement of part length CEA's with nontrippable (full length) CEA's.

1 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 Currently in Refueling Mode action and support information.

submitted January 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 fuel design, new operating procedures.

6.

The number of fuel assemblies: a) in the core 133 assemblies b) in the spent fuel pool 393 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 licensed capacity.

1996 Prepared by M.b Date May 25. 1987

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 May, 1987 Monthly Operations Report I.

OPERATIONS

SUMMARY

Fort Calhoun Station continued with its tenth refueling and maintenance outage through May, 1987. Work on the reactor vessel head, reactor coolant pump run in and coupling, and steam generator sludge lancing are complete. The reactor coolant system was heated up for the hot hydro-static test which revealed a leaky flange on a pressurizer safety valves.

The RCS was cooled down and repairs are underway.

The turbine generator is back together and system startup and testing is progressing. A condenser black light leak check was performed and the condensate system is recirculating for cleanup using the'new demineralizer tie in modification.

Emergency feedwater storage tank weld repairs and painting are complete.

Replacement of secondary system piping due to wall thinning and cracking is finished.

"C" circulating water pump and motor were reinstalled.

The annual inspection was performed on Diesel Generator 2.

M0 VATS was performed on 30 valves. Other modifications in progress include ATWS, feedwater regulating system, control room HVAC upgrade, inverter breaker installation and bypass transformer replacement, new pressurizer spray valves, equipment storage platform in containment, air accumulators on the safety injection pump recirculation valves to the SIRWT, and replacement of'the containment penetration bellows for the main steam and feedwater lines.

Radioactive waste shipped off-site during May included 83 drums of compacted waste, one liner (182 cubic feet) of evaporator concentrates and one liner (101 cubic feet) of resins.

NRC. audits were performed in the areas of chemistry, Raychem splices, welding and low temperature overpressurization.

Initial auxiliary operator-nuclear, non-licensed and licensed operator requalification and shift technical advisor requalification training continued. Training on modifications performed during the 1987 refueling outage was given to licensed operators and shift technical advisors.

No safety valves or PORV challenges or failures occurred.

1 q

A.

PERFORMANCE CHARACTERISTICS 1

None I

B.

CHANGES IN OPERATING METHODS None

Monthly. 0perations ' Report

' May, 1987

Page Two l

C.

RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS.

j None:

D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL' Procedure-Description SP EE-MEGGER Fans VA-2A/2B/3A/38/7C/7D/12A/12B Megger. Test.

This procedure did not constitute an unreviewed safety question as: defined by'10CFR50.59 as Sections 6.4-and 9.10 of-the USAR do not require the operation of all containment fans simultane-ously under normal plant ' conditions, and allow and require periodic performance testing of these units. Also, Sections 2.4 and 2.13 of the Tech-nical Specifications do not require the operation of the containment fans when-the plant is in a refueling shutdown condition.

.SP-CVAC-1 Core Support P1 ate Vacuuming and Visual Inspection.

This procedure did.not constitute an unreviewed j

safety question as defined by 10CFR50.59 as this~

procedure provided guidance.in the location, identification and removal of small foreign objects which may have been present on the core support plate. Twelve small objects were found and removed.

l D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued) l System Acceptance Committee Packages for May, 1987:

l L

Packaae Descriotion/ Analysis DCR 77-37 Reactor Coolant Pump Jib Crane Tie Backs.

This modification provided for the installation of tie backs to ensure that the reactor coolant pump i

L jib cranes are properly secured during normal operation.

This modification does not have an j

adverse effect on the safety analysis.

i 1

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.j

' Monthly Operations Report

' May, 1987 Page Three D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued) i System Acceptance. Committee Packages for May, 1987:

)

Packaae Descriotion/ Analysis j

EEAR FC-81-180 Seismic Restraint of Masonry Walls.

This modification provided for seismic supports of

' the masonry walls in the auxiliary. building. This modification does not have an adverse effect on the safety analysis. -

EEAR FC-82-132 Instrument Air. Check Valves on HCV-304, HCV-305, 1

HCV-306 and HCV-307.

This modification provided for the installation of-1 check valves in the instrument air lines upstream j

of the air accumulators for HCV-304, HCV-305, i

HCV-306 and HCV-307.

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

EEAR FC-84-056 Sockets for Underwater Lights.

j This modification replaced reactor cavity power receptacles; no new conduit was installed.

Spent fuel pool power was revised to give 20 amps and 15 amps power circuits..This modification'does not have an adverse effect on the safety analysis.

EEAR FC-85-019 Actuator for LCV-383-1.

This modification provided for the replacement of the manual actuator on valve LCV-383-1.

This modi-fication does not have an adverse effect on the safety analysis.

l EEAR FC-85-029 Portable Demineralizer Tie-Ins for Condensate System.

This modification provided for the installation of tie-ins to the condensate system for a mobile demineralizer to be used during plant startups.

This modification does not have an adverse effect 4

on the safety analysis.

l

i l

Monthly Operations Report May, 1987 Page Four D.

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

System Acceptance Committee Packages for May, 1987:

Packaae Description / Analysis EEAR FC-85-048 Transfer of Sequence of Events (SOE) to the ERF Computer System.

This modification provided for the transferring of approximately 175 SOE and associated signals from the P250 computer to the ERF computer system.

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

EEAR FC-85-190 Supports on Alternator Cooling Piping.

This modification provided for the replacement of wooden block supports with angle iron bracketed supports on the alternator cooling piping.

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

EEAR FC-86-009 New Reconstitutible CEA's.

This modification provided for the replacement of i

47 existing CEA's with new Ag-In-Cd tip recon-stitutible CEA's, including part-length CEA's.

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

EEAR FC-86-066 Replacement of Strainer Housing and Lube Oil

(

Cooler Core for Diesel Generator DG-1.

]

This modification provided for the replacement of

{

the existing strainer housing and lube oil cooler j

core with upgraded versions as recommended by the diesel manufacturer.

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

i EEAR FC-86-073 Synchronism Supervisor /DS-T Modification.

This modification provided for the installation of a line pot for the Sioux City line.

This modifica-tion does not have an adverse effect on the safety analysis.

]

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g 1

Monthly Operations. Report l

May,.1987 l

Page Five

{

l D.

CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION

' APPROVAL (continued) j System Acceptance Committee Packages for May, 1987:

Packaae Descriotion/ Analysis EEAR FC-87-017 Containment Penetration Expansion Joints M-93,

'M-94 and M-95.

This modification provided for the replacement of penetration expansion joints M-93, M-94 and M-95 located in Room 81. This modification does not have an adverse effect on the safety analysis.

EEAR FC-87-019-Deflector Plate for~ Control Valve Drain.

This modification provided for the installation of a deflector plate in front of the control valve drain header to prevent steam impingement on the tubes and baffle. This modification does not have an adverse effect on the safety analysis.

EEAR FC-87-023 FWS-41 Removal.

This modification provided for the removal of pipe support FWS-41 to reduce loads on the steam generator nozzle. This modification does not have i

an adverse effect on the safety analysis.

l

.E.

RESULTS OF LEAK RATE TESTS i

None.

l 4

F.

CHANGES IN PLANT OPERATING STAFF During May, one Equipment Operator-Nuclear (David Harrison) resigned.

G.

TRAINING j

i Initial auxiliary operator-nuclear, non-licensed and licensed l

operator requalification and shift technical advisor requalification training continued. Training on modifications performed during the 1987 refueling outage was given to licensed operators and shift technical advisors.

4-

?.:

Monthly Operations. Report L May,;.1987 Page Six

r E

H.

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

Descriotion I

109 TheLamendment modifies:the Technical Specifica--

tions to reflect changes which are necessary to q

support. Cycle 11 operation.

I-II. ^ MAINTENANCE (Significant Safety Related)

A report of > all significant. safety related maintenance performed during the 1987Jrefueling and maintenance outage will be submitted at the end of the' outage.

Y"'

. AVVl -

'g s

W. Gary Gates Manager-Fort Calhoun Station e

l i

Omaha Public Power District 1623 Harney Omaha, Nebraska 68102 2247 402/536 4000 June 12, 1987 LIC-87-424 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

Docket No. 50-285

SUBJECT:

May Monthly Operating Report Gentlemen:

Pursuant to Technical Specification Section 5.9.1, and 10 CFR Part 50.4(b)(1),

please find enclosed one copy of the May,1987 Monthly Operating Report for the Fort Calhoun Station Unit No.1.

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

R. M. Caruso - Combustion Engineering R. J. Simon - Westinghouse Nuclear Safety Analysis Center INP0 Records Center i

American Nuclear Insurers NRC File (FCS) l l

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