ML20214A100

Monthly Operating Rept for Apr 1987

ML20214A100
Person / Time
Site:	Fort Calhoun
Issue date:	04/30/1987
From:	Andrews R, Matthews T OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LIC-87-326, NUDOCS 8705190260
Download: ML20214A100 (9)

Text

r 7, y- ,

i l~ '

AVERAGE DAILY UNIT POWER LEVEL a

DOCK.iNO. 50-285 UNIT Fort Calhoun Station DATE May 11, 1987 COMPLETED BY T. P. Matthews TELEPHONE 402-536-4733 4' MONTli April, 1987 t' ,

DAY AVERAGE DAILY POWER LEVEL DAY r AVERAGE DAILY POWER LEVEL (MWe Net) (MWe-NetI ki 1 0.0 i7 o,o 2 0.0 is 0.0 3- 0.0 0.0 39 4 0.0 20' O.0

. 5 0.0 21 'O.0

-, I 0.0 0.0 p 6 '

22 I' ' '

7 0.0 0.0 23 ii :q ' 8 0.0 24 0.0 9 0.0 25 0.0

' 40 0.0 26 0.0 0.0 ,,

0,0 12 0.0 28 nin

^

13 0.0 >

29 0.0 14 0.0 '

0.0 30 is 0.0 3 0.0 16 0. 0 f

INSTRUCTIONS On this format. fist the average daily unit power levelin MWe. Net for each day in the reporting nu> nth. Compute to the nearest whole megawatt.

l .,

~~

(9/77) 8705190260 870430 -

s PDR R

ADOCK 05000285 PDR 6' 762.Y l/l p

i .-

OPERATING DATA REPORT e

DOCKET NO. 50-285 DATE May 11, 1987 COMPLETED BY T. P. Matthews TELEPHONE 402-536-4733 OPERATING STATUS Fort Calhoun Station Notes I. Unit Name: ,

2. Reporting Period: Apri1 1987

3. Licensed Thermal Power (MWt):

1500

4. Nameplate Rating (Gross MWe): 502 S. Design Electrical Rating (Net MWe): 478

6. Maximum Dependable Capacity (Gross MWe): 502

7. Maximum Dependable Capacity (Net MWe): 478

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

l N/A

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

10. Reasons Fer Restrictions. lf Any: None

)'

This Month Yr.-to Date Cumulative i1. Hours In Reporting Period 719.0 2.879.0 119,185.0

12. Number Of Hours Reactor Was Critical 00 1 570.R 91,802.3

13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5

14. Hours Generator On-Line 0.0 1,567.0 90,954.1

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 Electrierl Energy Generated (MWH) 0.0 785,356.0 38,552,082.2

18. Net Electrical Energy Generated (MWH) 0.0 751,184.8 36,834,645.7

19. Unit Ser/ ice Factor 0.0 54.4 76.3

20. Unit Availability Factor 0.0 54.4 76.3

21. Unit Capacity Factor (Using MDC Net) 0.0 54.6 66.8

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

23. Unit Forced Outage Rate 0.0 0.0 3.3

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

The 1987 Refueling Shutdown commenced on March 7,1987 with startup tentatively scheduled for May 26, 1987.

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

26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMMERCIA L OPERATION (9/77)

s DOCKET NO. 50-285 UNITSHUTDOWNS AND POWER REDUCTIONS Fort Calhoun Station UNIT NAME DATE May 11. 1987 E COMPLETED BY T. P. Matthews REPORT MONTH Acril 1987 TELEPHONE 402-536-4733 i

- 5 E

, ,{g 3 j .7Ii Licensee gg K" Cause & Corrective No. Date g 3g 5 2is Event p gg Action to H y: 5 jgg Report r m La g Prevent Recurrence 6

87-02 870307 S 1313.0 C 1 N/A xx xxxxx The 1987 Fort Calhoun Station Refuel-in9 Outage comenced March 7,1987.

i 1 2 3 4 a 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 Sh:ets for Licensee j C Refueling 3-Automatic Scram. Event Report 4,LER) File (NUREG- y D Regulatory Restriction 4-Other (E.cplain) 0161) /

E-Operator Training & Ucense Examination j F-Administrative 5 G Operational Error (Explain) Exhibit ! . Same Source L

. (9/77) llother (Explain) ji

Refu@ ling Information Fort Calhoun - Unit No.-1 r

Report-for.the month ending Aoril 1987 .

1, Scheduled date for next refueling shutdown. March 1987

2. Scheduled date for' restart following refueling. May 1987

'3. Wil1' 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.

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- 1 action and support information. submitted January 1987 l S. 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 Date April 25. 1987

~

l i

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

SUMMARY

Fort Calhoun Station continued with its tenth refueling and maintenance outage through April, 1987. Core reload and fuel integrity testing has been completed. The reactor head was installed, control element assemblies were coupled and heated junction thermocouples were installed.

Reactor coolant pumps "C" and "D" had their upper guide bearings rebuilt and oil systems flushed. ' Steam generator secondary side inspection showed very good results. Setup for annulus inspection and sludge lancing are in progress.

During repainting of the Emergency Feedwater Storage Tank, flaws were discovered in the welds. As a result, all welds have been radiographed and 139 feet of welds and 18 nozzles are being repaired.

Both low pressure turbine rotors passed ultrasonic testing. A number of bucket pins have been replaced and the rotors were reinstalled. Turbine alignment is in progress.

Ultrasonic testing of secondary side piping for wall thinning and cracking has indicated several locations requiring replacement. Raychem splice inspection and replacement _is nearly complete. M0 VATS has been completed on 13 of 25 valves.

Other modifications in progress include ATWS, new Feedwater Regulating System,. inverter breaker installation and bypass transformer replacement, installation of a pressurizer loop seal and new spray valves, Control Room HVAC upgrade and condensate demineralizer connections.

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

' Monthly Operations Report April, 1987

,Page Two D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure' Descriotion 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-FE-11 Ultrasonic Examination of Fuel.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59. The most serious event that could have happened was a fuel handling incident. This type of event has previously been analyzed and documented in USAR Section 14.18.4.2. The consequences of the USAR fuel handling event were well within the limits of 10 CFR 100.

SP-FE-ll Ultrasonic Examination of Fuel.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59. The most serious event that could have happened was a fuel handling incident. This type of event has previously been analyzed and documented in USAR Section 14.18.4.2. The consequences of the USAR fuel handling event were well within the limits of 10 CFR 100.

SP-SI-HPSI HPSI Stop Valves Special Test.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 as Section 7.3.4 of the USAR allows and requires periodic performance testing of the safeguards systems. Also, Section 2.3(3) of the Technical Specifications allows HPSI pump operation (which was required to support this test) when the reactor coolant system is adequately vented to preclude a design basis pressure transient.

l

Monthly Operations Report April, 1987 Page-Three D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL (continued)

System Acceptance Committee Packages for April,1987:

Packaae Description / Analysis l

l EEAR FC-86-74 Condenser Tube Staking.  ;

1 This modification provided for the installation of condenser tube stakes to help mitigate tube-to-tube vibrational wear. This modification does not have an adverse effect on the safety analysis.

E. RESULTS OF LEAK RATE TESTS i

None.

F. CHANGES IN PLANT OPERATING STAFF None.

G. TRAINING During the month, accelerated training was initiated for one reactor operator and seven senior reactor operator candidates who will take l

the NRC examination in June. Hot license training, auxiliary operator-nuclear training, and non-licensed and licensed operator requalification training continued.

l l

H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment No. Descriotion 108 The amendment incorporates revised Limiting Conditions for Operation and Surveillance Requirements for the steam generator isolation signal.

' Monthly Operations Report-

- April, 1987

.Page Four

II. MAINTENANCE (Significant Safety Related)

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

k. & Rs W. Gary Gates Manager-Fort Calhoun Station 1 ,

l I

l 1

l .

l l

l

> Omaha Pub!!c Power District 1623 Harney Omaha. Nebraska 58102 2247 402/536 4000 May 13, 1987 LIC-87-326 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

Docket No. 50-285

SUBJECT:

April 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 April,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 INPO Records Center American Nuclear Insurers NRC File (FCS)

,>'s?

\\

., s ,2 .

. . . . , = ,3 , g e .., _ ,,

_d