ML20129G326

Monthly Operating Rept for Apr 1985

ML20129G326
Person / Time
Site:	Davis Besse
Issue date:	04/30/1985
From:	Quennoz S, Sarsour B TOLEDO EDISON CO.
To:	Haller N NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
K85-727, NUDOCS 8507180026
Download: ML20129G326 (7)

Text

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e AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-346 UNIT Davis-Besse Unit 1 May 9, 1985 DATE COMPLETED BY Bilal Sarsour (419) 249-5000 TELEPHONE Ext. 384 April 1985 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe. Net) 1 0

17 792 2

0 gg 740 3

0 g9 827 4

0 20 834 5

0 21 720 6

0 22 770 7

0

3 819 8

0 99 24 9

0 25 121 10 0

26 672 11 0

27 679 12 0

28 553 13 0

29 753 14 251 30 790 15 639 3g 16 741 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.

(4/77) 8507180026 850430 tg PDR ADOCK 05000346 7

R PDR

l OPERATING DATA REPORT DOCKET NO. ' 50-346 DATE May 9 1985 COMPLETED BY Bilal Sarsour TELEPHONE (4191249-5000, Ext. 384 OPERATING STATUS

1. Unit Name:

Davis-Besse Unit 1 Notes

2. Reporting Period:

April 1985

3. Licensed Thermal Power (31Wt):

2772

4. Nameplate Rating (Gross MWe):

925

5. Design Electrical Rating (Net MWe):

906

6. Maximum Dependable Capacity (Gross MWe):

904

7. Maximum Dependable Capacity (Net MWe):

860

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

To obtain an acceptable offset from the Reactor Protection System (RPS) trip setpoints

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

10. Reasons For Restrictions.If Any:

This Month Yr :> Date Cumulative

11. Hours In Reporting Period 720 2.880.0 59.I85.0

12. Number Of Horry Reactor Was Critical 386.7 1,953.8 34,985.3

13. Reactor Rese:ve Shutdown Hours 0.0 0.0 4,014.1

14. Hours Generator On-Line 371.1 1,847.0 33,488.3

15. Unit P.eserve Shutdown flours 0.0 0.0

16. Gross Thermal E tergy Generated (MWH) 846.236 4,196,387 1,732.5 79,182,009

17. Gross Electrica! Energy Generated (MWH) 277.850..

1.386.654 26.232.998

18. Net Electrical Energy Generated (MWH) 253.655 1.284.068 24.574.324

19. Unit Service Factor 51.5 64.1 56.6

20. Unit Availability Factor 51.5 64.1 59.5

21. Unit Capacity Factor (Using MDC Net) 41.0 51.8 48.3

22. Unit Capacity Factor (Using DER Net) 38.9 49.2 45.8

23. Unit Forced Outage Rate 8.I 1.8 16.6

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

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

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

Forecast Achmed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION (4/77 )

DOCKET NO.

50-346 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Davis-Besse Unit 1 DATE May 9, 1985 COMPLETED BY Bilal Sarsour REPORT MONTH April 1985 TELEPHONE (419) 249-5000, Ext. 384 "u

o E -s "b

EIU Licensee ae Eus Cause & Corrective E.

U0 0

l$ II E Event 3$

E$

Action to No.

Date

$?

6E E

5$#

Report #

E,0 E' O Prevent Recurrence 56

$5$

0 8

85 03 21 S

316.2 B

4 N/A N/A N/A Maintenance outage, which began on March 21, 1985, was completed on April 14, 1985, when the unit was placed on line.

5 35 04 24 F

32.7 A

3 NP-33-85-13 JD N ?A The Reactor Protection System (RPS) tripped the reactor on flux / delta flux / flow. See Operational Summary for further details.

)

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 D-Regulatory Restriction 4-Continuation from (NUREG-0161)

E-Operator Training & License Examination Previous Month F-Administrative 5-Load Reduction 5

G-Operational Error (Explain) 9-Other (Explain)

Exhibit I - Same Source (9/77)

H-Other (Explain)

OPERATIONAL

SUMMARY

APRIL, 1985 4/1/85 - 4/13/85 The scheduled maintenance outage, which began on March 21, 1985, was completed on April 14, 1985. The outage extended longer than expected due to problems with control rod drive leaf springs being out of position.

The following are the more significant outage activities performed during the outage:

1)

Repair of Control Rod Drives 5-3 and 2-7 2)

Repair of main steam safety valve SP17B2 3)

Repair generator iso phase bus phases A, B, and C 4)

Replaced rupture disc on quench tank 5)

Auxiliary Feedwater snubber and hanger repairs 6)

Modification to the Steam and Feedwater Rupture Control System to alleviate Auxiliary Feedwater snubber problem The reactor was critical at 1903 hours0.022 days <br />0.529 hours <br />0.00315 weeks <br />7.240915e-4 months <br /> on April 13, 1985. The turbine-generator was synchronized on line at 0412 hours0.00477 days <br />0.114 hours <br />6.812169e-4 weeks <br />1.56766e-4 months <br /> on April 14, 1985.

4/15/85 - 4/22/85 Reactor power was slowly increased and attained 89% power on April 16, 1985. Reactor power was maintained at approximately 89% until 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on April 16, 1985, when power was reduced to approximately 85% to perform turbine stop valve testing. During turbine stop valve testing, Control Rod Drive Trip Breaker C tripped. Reactor power was held at 85% power to permit continued troubleshooting of the problem.

Af ter the completien of the turbine stop valve testing, reactor power was slowly increased to approximately 90% which was attained on April 17, 1985. Reactor power was maintained at 90% power until 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> on April 17, 1985, when a manual power reduction to approximately 81% was initiated due to a problem with Condensate Pump #1.

Condensate Pump #1 was taken out of service to clean its oil cooler.

Reactor power was slowly increased and attained approximately 95% power at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on April 19, 1985. Power was maintained ct this power level until 0220 hours0.00255 days <br />0.0611 hours <br />3.637566e-4 weeks <br />8.371e-5 months <br /> on April 20, 1985, when manual power reduction to 93% was initiated due to a problem with Group 38 heat balance.

Reactor power was maintained at approximately 93% power until 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on April 20, 1985, when Group 38 heat balance was declared operable.

Reactor power was then slowly increased to approximately 95% which was

• attained at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on April 20, 1985. Reactor power was maintained at approximately 95% power until 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> on April 20, 1985 when a manual power reduction to approximately 81% was initiated due to low load require-ments.

Reactor power was slowly increased and attained 95% full power on April 22, 1985.

4/23/85 - 4/25/85 Reactor power was maintained at approximately 95% power until 0353 hours0.00409 days <br />0.0981 hours <br />5.83664e-4 weeks <br />1.343165e-4 months <br /> on April 24, 1985, when a reactor trip occurred. The Reactor Protection System (RPS) tripped the reactor on flux / delta flux / flow. The root cause of the reactor trip was the tripping of all four flux / delta flux / flow RPS channels due to a low Reactor Coolant System (RCS) flow signal spike or an NI power spike in conjunction with an overly conservative setting of the flux / delta flux / flow setpoint.

The reactor was critical at 0613 hours0.00709 days <br />0.17 hours <br />0.00101 weeks <br />2.332465e-4 months <br /> on April 25, 1985. The turbine generator was synchronized on line at 1237 hours0.0143 days <br />0.344 hours <br />0.00205 weeks <br />4.706785e-4 months <br /> on April 25, 1985.

4/26/85 - 4/30/85 Reactor power was slowly increased to approximately 80%, which was achieved at 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> on April 26, 1985. Power was not increased due to feedwater heater problems causing excessive condensate flow.

Reactor power was maintained at approximately 80% until 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on April 27, 1985, when a manual power reduction to approximately 68% was initiated due to low load requirements.

Reactor power was slowly increased to approximately 90% power, which was attained an April 29, 1985, and maintained at this power level for the remainder of the month, a

l

,3*

REFUELING INFORMATION DATE: April 1985 1.

Name of facility: Davis-Besse Unit 1 2.

Scheduled date for next refueling shutdown: Spring, 1986 3.

Scheduled date for restart following refueling: Summer, 1986

'4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? If answer

-is yes, what in general will these be? If answer is no, has the reload fuel design and core tanfiguration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

Ans: Expect the Reload Report to require standard reload fuel design Technical Specification changes (3/4.1 Reactivity Control Systems and 3/4.2 Power Distribution Limits).

5.

Scheduled date(s) for submitting proposed licensing action and supporting information: Winter, 1985 6.

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.

Ans: None identified to date.

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

(a) 177 (b) 204 - Spent Fuel 4.semblies 8.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.

Present:

735 Increase size by: 0 (zero) 9.

The projected date of the last refueling that can be discharged to i

the spent fuel pool assuming the present licensed capacity.

Date:

1992 - assuming ability to unload the entire core into the spent fuel pool is maintained.

l

)

BMS/005

r-r O:.f.

TOLEDO

%mm EDISON May 9, 1985 Log No. K85-727 File: RR 2 (P-6-85-04)

Docket No. 50-346' License No. NPF-3 Mr. Norman Haller, Director Office of Management and Program Analysis U. S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Mr. Haller:

Monthly Operating Report, April 1985 Davis-Besse Nuclear Power Station Unit 1 Enclosed are ten copies of the Monthly Operating Report for Davis-Besse Nuclear Power Station Unit 1 for the month of April, 1985.

If you have any questions, please feel free to contact Bilal Sarsour at (419) 249-5000, Extension 384.

Yours truly, k-wbb Step en M. Quennos:

Plant Manager Davis-Besse Nuclear Power Station SMQ/BMS/ljk Enclosures cc:

Mr. James G. Keppler, w/l Regional Administrator, Region III Mr. James M. Taylor, Director, w/2 Office of Inspection and Enforcement Mr. Walt Rogers, w/l NRC Resident Inspector 9

LJK/002 THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43652