ML20154D622

Monthly Operating Rept for Apr 1988

ML20154D622
Person / Time
Site:	Fort Calhoun
Issue date:	04/30/1988
From:	Andrews R, Blessie W OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LIC-88-369, NUDOCS 8805190268
Download: ML20154D622 (9)

Text

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,- y AVERAGE DAILY UNIT POWER LEVEL DOCKET N0. 50-285 UNIT Fort Calhoun Station -

DATE May 13. 1988 COMPLETED BY W.- J. Blessie TELEPHONE 402-536-4595 MONTH Aoril 1988

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 331.0 17 486.7 l

2 330.4 18 485.7 -

4 3 316.3 19 484.9 4 390.6 20 485.1 i 5 450.0 21 484.8 l 6 470.4 _ 22 485.2 7 481.7 23 486.8 8 487.9 24 487.8 l 9 487.5 25 486.2 ,

] 10 487.2 26 485.8  :

11 488.0 27 486.1 12 487.6 28 487.2  ;

13 486.7 29 476.4 486.2 461.5 14 30 j 15 486.5 31 '

16 487.0 1

INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

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_ SLM 8905190268 800430 t/

PDR ADOCK 05000285 //

R DCD

. OPERATING DATA REPORT l

DOCKET N0. 50-285 UNIT Fort Calhoun Station DATE May 13. 1988 COMPLETED BY W. J. Blessie TELEPHONE 1Q2-536-4595 OPERATING STATUS

1. Unit Name: Fort Calhoun Station Notes

2. Reporting Period: May 1988

3. Licensed Thermal Power (MWt): 1500

4. Nameplate Rating (Gross MWe): 502

5. Design Electrical Rating (Net MWe): 478

6. Maximum Dependable Capacity (Gross NWe): 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:

N/A

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

10. Reesons for Restrictions, If Any: _

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 719.0 2903.0 127.969.0

12. Number of Hours Reactor Was Critical 719.0 2903.0 99.742.8

13. Reactor Reserve Shutdown Hours 0.0 0.0 1.309.5

14. Hours Generator On l.ine 719.0 2903.0 98.821.8 '

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (HWH) 1.030.843.3 _3.750.856.0 128.298.481.2

17. Gross Electrical Energy Generated (MWH) 350.196.0 1.275.038.0_ 421247.959.2

18. Net Electrical Energy Generated (MWH) 334.202.9 1.210.776.7 40.354.859.5

19. Unit Service factor 100.0 100.0 77.2

20. Unit Availability Factor 100.0 100.0 77.2 21 Factor (Using MDC Net) 97.t_ 87.3 68.4

22. Unit Capacity Factor (Using DER Net) 97.2 87.3 66.6 l

23. Unit Forced Outage Rate 0.0 0.0 3.0

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

The 1988 Refuelina Shutdown is tentatively scheduled for September 2. 1988 with startuo tentatively scheduled for November 18. 1983.

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

26. Units In Test Status (Prior to Commercial Operation: Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY N/A ,

COMMERCIAL OPERATION l

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I UNII SHUIDOWNS AND POWER REDUCTIONS DOCKET NO. 50-285 UNIT N AME Fort Calhoun Station DATE May 13, 1988 COMPLETED BY W. J. Blessie REPORT MON TH April 1988 TELEPHONE (402) 536-4595

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.] 3 "h j E5 Licensee ,E g K Cause & Correctise N... Date E2 4 _z s 5 Event u? o-3 Action to l @

$5 @ $ Report : E0 $' Present Recurrence l 3 5 =!

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i 88-01 880212 S 0 H 4 N/A BK FAN Fort Calhoun Station was at 70%

power until starting a power ascen- '

sion on April 4, 1988. Power was maintained at 100% from April 8 to April 29 when it was reduced to 95% in preparation for moderator temperature coefficient (MTC) testing +

I 2 3 4 F: Forced Reason: Method: Exhibit G . instauctions f: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee C Refueling 3-Automatic Scram. Event Report ILER) File (NURLG.

D-Regulatory kestriction 4-Other (Explain) 0161)

E-Operator Training & Ucense Examination F-Administrative 5 G-Operational Er ror I Explaird Exhibit 1 - Same Source (9/77) llother (Explain)

l Refueling Information Fort Calhoun - Unit No. 1 Report for the month ending Aoril 1988 .

1. Scheduled date for next refueling shutdown. September 1988

2. Scheduled date for restart following refueling. December 1988

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?

Incorporate cycle specific requirements resulting from reload safety analysis.

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. July 1988

5. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis rrethods, 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 ein "

consolidation

7. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. 1994*

• Full core offload of 133 assemblies lost.

Prepared by "" Date April 25. 1988

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 ,

April 1988 Monthly Operations Report I. OPERATIONS

SUMMARY

Fort Calhoun Station was at 70% power to conserve reactivity for end of cycle until starting a power ascension on April 4, 1988. Power was maintained at 100% from April 8 to April 29 when it was reduced to 95% in preparation for moderator temperature coefficient (MTC) testing.

An NRC inspection on licensed operator initial and requalification training was conducted during April 1988. All NRC reactor operator license annual requalification exams have been completed. Annual simulator training at Combustion Engineering in Windsor, Connecticut, started in April 1988.

An INP0 plant evaluation was conducted during April 1988.

Construction continues on the new warehouse, maintenance shop, and training facility.

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 D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure Description SP-CONT-3 Verification of Containment Penetration Configurations.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59. This one time special procedure was performed to ensure containment integrity. The procedure consisted of a walkdown of all containment penetrations with a follow-up independent verification. The results were acceptable.

Monthly Operations Report April 1988 Page Two D. CHANGES, TESTS AND EXPERIMENTS CARRIED OUT WITHOUT C0tHISSION APPROVAL (Continued)

Procedure Description SP-STR0KE-1 In Service Testing of Air Operated, CQE Valves.

This procedure did not constitute an unreviewed safety question as defined by 10CFR50.59 because it only allowed stroke testing to be conducted on 39 air operated CQE valves. The objective of the testing is to determine if valve operability was degraded (or is degrading) due to the intrusion of water into the instrument air system. This testing did not in any way compromise plant safety, but enhanced it by ensuring operability of safety related valves.

System Acceptance Committee Packages for April 1988:

Packaae Description / Analysis EEAR FC-86-020A Warehouse Relocation - Earthwork.

This modification provided for earthwork preparation prior to construction of the new warehouse. This modification does not have an adverse effect on the safety analysis.

EEAR FC-86-036 Shielding Above Room 11.

This modification provided for radiation protection for the H.P. counting room. This modification does not have an adverse effect on the safety analysis.

EEAR FC-86-100 Auxiliary Building Roof Access Ladder.

This modification provided for the addition of a platform in the fan room and modification of ladders on the auxiliary building roof. This modification does not have an adverse effect on the safety analysis.

EEAR FC-87-033B Security Fence Rearrangement - Maintenance Building.

This modification provided for temporary relocation of security barriers to accommodate facility upgrades. This modification does not have an adverse effect on the safety analysis.

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Monthly Operations Report April 1988 Page Three E. RESULTS OF LEAX RATE TESTS During April, the leak rate test on the containment purge valves (penetrations M-87 and M-88) was completed per ST-CONT-3, F.4. The "as found" and "as left" leak rates for penetrations M-87 and M-88 were 0 sccm.

In January, the "B" and "C" "as left" leak rate was 374.2 secm.

Since both sets of containment purge valves tested zero leakage during this April test, the total leakage remains unchanged. This leak rate is well below the allowed leakage of 0.6 La as specified in 10 CFR 50 Appendix J.

F. CHANGES IN PLANT OPERATING STAFF None G. TRAINING During April, the National Academy for Nuclear Training accredited the radiation protection, instrument and control, electrical, mechanical, chemistry, shift technical advisor, and technical staff training programs. OPPD is now a full member of the National Academy.

Remedial training and successful examination c,f two senior reactor operators who failed the NRC-administered walkthrough examination was completed. An EONT training class began. Simulator training at CE for the licensed operator requalification program was administered.

Initial training continued for the reactor operator and senior reactor operator training programs. Quarterly seminars for technical staff and managers continuing training were conducted. Examination scenarios for the NRC-administered simulator examinations to be administered at the end of May were forwarded to Region IV personnel for their review and approval.

H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMi!SSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment No. Description 112 The amendment revises the Technical Specifications to permit an extension to the next due date from April 30, 1988 to the refueling outage scheduled for September 1988 for performing the inspection of Diesel Generator No. 1 required by Surveillance Requirements, i

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• 5 Monthly Operations Report l April 1988 i Page Four I

II. MAINTENANCE (SignificantSafetyRelated)  !

None i

"Jb A W. Gary Gates

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l Omaha Public Power District 1623 Harney Omdha. Nebraska 68102 2247 402/536-4000 May 13, 1988 LIC-88-369 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

Docket No. 50-285 Gentlemen:

SUBJECT:

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

please find enclosed, one copy of the April 1988 Monthly Operating Report for the Fort Calhoun Station Unit No. 1.

Sincerely, si '1 )os.,u b [.u R. L. Andrews Division Manager Nuclear Production NA/me Enclosures c: 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 American Nuclear Insurers NRC File (FCS)

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