ML20108B145

Monthly Operating Rept for Sept 1984

ML20108B145
Person / Time
Site:	Davis Besse
Issue date:	09/30/1984
From:	Quennoz S, Sarsour B TOLEDO EDISON CO.
To:	Haller N NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
K84-1281, NUDOCS 8411150323
Download: ML20108B145 (10)

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-346 UNIT. -_ Davis-Besse #1 DATE _.10-2-84 COMPLETED BY Bilal M. Sarsour TELEPHONE (419)259-5000 Ext. 384 MONDI Ser> tember. 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

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(MWe-Net)

(MWe-Net) g 619 0-37 2

618 18 0

%,2 3

619 39 0

4 619 0

20 619 0

5 21 619 0

6 22 7

619 23 0

8 591 24 0

9 565 25 0

10 564 26 0

g3 276 0-27 a

12 0

28 0

13 0

0 29 14 0

30 0

15 0

33 16 0

INSTRUCTIONS On this forrnat. list the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole rnegawatt.

(9/77) 8411150323 840930 PDR ADOCK 05000346

h DOCKET NO.

50-346 UNIT SHUTDOWNS AND POW'!! REDUCTIONS UNIT N AME Davis-Besse #1 DATE 10-2-84 COMPLETED BY Bilal M.

Sarsour REPORT MONTII september. 1984 TELEPIIONE (4191259-5000 Ext. 384

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__E Licensee

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• l, Cause & Corrective N.i.

Date g

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.g s s Event 3g e.1 s

Action to 8-j5g Reporiar mu yO Prevent Recurrence-I S

84-09-11 F

59.4 C

3 NP-33-84-13 CD Instru The reactor tripped by the Anticipa-tory Reactor Trip System (ARTS) in response to the turbine trip.

See LER #NP-33-84-13 for further details, 84-09-14 S

408.0 C

9 The refueling outage was entered follow-ing the reactor trip on 9/11/84 to

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perform scheduled maintenance and refueling work.

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S: Schedu'ed A Equipment Failure (Explain)

~ Method:

Exhibit C Instructions j

F: Forced Reason:

I-Manual for Preparation of Data

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B-Maintenance of Test 2-Manual Scrani.

Entry Sheets for Licensee C Refueling 3-Automatic Scram.

Event ReporI(LER) File (NUREG-D-Regulatory Restriction 4-Continuation from Previous Month 0161)

E-Operator Training & Liecuse Examination 5-Load Reduction F-Administrative 9-Other (Explain) 5

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G-Operational E ror (Explain)

Exliibit I - Same Source f

(9/77)

II-Other (Explain)

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l-OPERATING DATA REPORT

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DOCKET NO. 50-346 DATE 10-2-84 COMPLETED BY Bilal M.

Sarsour TELEPHONE (419)259-5000 Ext. 384 OPERATING STATUS Notes

1. Unit Name:

Davis-Besse #1

2. Reporting Period:

September, 1984 3'. Licensed Thermal Power (MWt):

2772 915

4. Nameplate Rating (Gross MWe):

5. Design Electrial Rating (Net MWe):

906 4

" 6. Maxim'um Dependable Capacity (Gross MWe)r 918

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7. Maximim Dependable Capacity (Net MWe):

R74

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

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'9. Power Level To Which Restrictedj If Any (Net MWe).

10. Reasons For Restrictions.If Any:

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This Month Yr..to.Date Cumulative i1. Hours In Reporting Period' 720' 6.575.0 54.096.0 1

12. Number Of Hours Reactor Was Critical m _6 5.529.0 33,031.5

13. Reactor Reserve Shutdown Hours 0.0 134.8-4,014.1

14. Hours Generator On.Line 252.6 5,489.5 31,641.3

~,15. Unit Reserve Shutdown Hours 0.0 0.0 l ~,7 32. 5

16. Gross Thermal Energy Generated (MWH) 514,927 13,941,608 74,985,422

17. Gross Elcetrical Energy Generated (MWH) 163,161 4,554,151 24,846,344

18. Net Electrical Energy Generated (MWH) 148.1R1 4.291.557 23.290.256

19. Unit Service Factor 15 I 83.5 58.5

20. Unit Availability Factor 35.1 83.5 61.7

21. Unit Capacity Factor (Using MDC Net) 23.5 74.7 49.3 22.7 72.0 47.5

22. Unit Capacity Factor (Using DER Wet)

23. Unit Forced Outage Rate 19.0 11.0 17.3

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

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

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

Forecast Achiesed INITIAL CRITICA LITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)

OPERATIONAL

SUMMARY

SEPTEMBER, 1984 9/1/84 - 9/8/84 Reactor power was maintained at approximately 75% power with the generator gross load at approximately 662 1 10 MWe until 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> on September 8, 1984 when power was reduced to approximately 70% due to Cycle 4 coastdown.

9/9/84 - 9/30/84.

Reactor Power was maintained at approximately'70% until 1235 hours0.0143 days <br />0.343 hours <br />0.00204 weeks <br />4.699175e-4 months <br /> on September 11, 1984 when a reactor trip occurred. The reactor tripped by the Anticipatory Reactor Trip System (ARTS) in response to the turbine trip which was caused by the inadvertent striking of the moisture separator reheater high level switch during pre-outage activities.

A plant cooldown was initiated to perform scheduled maintenance and refueling work. Full details on the work items performed during the scheduled maintenance outage will be presented in next month's Operational Summary.

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f REFUELING INFORMATION DATE:

September.1984 1.

Name of facility: Davis-Besse Unit 1 2.

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

Scheduled date for restart following refueling: December 22 1984 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendwant? If answer is yes, what in general will these be? If answer is no, has the reload fuel design and core configuration 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: July, 1984 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) 140 - Spent Fuel Assemblies 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 the spent fuel pool assuming the present licensed capacity.

Date:

1993 - assuming ability to unload the entire core into the spent fuel pool is maintained.

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COMPLETED FACILITY CHANGE REQUEST FCR NO: 84-039 SYSTEM: Auxiliary Feedwater System COMPONENT: MV 05990 and MV 06080 CHANGE, TEST OR EXPERIMENT: This FCR was implemented to change the torque switch settings on MV 05990 and MV 06080 from 1.5 open/1.5 close to 1.5 open/1.0 closed. These values were taken from the Torrey Pines i

Technology Report. Work involved with FCR 84-039 was completed March 6, 1984.

REASON FOR CHANGE: MV 05990 torqued out while attempting to open during a recent shutdown. The new torque switch settings are taken from the Torrey Pines Technology Report in an effort to improve valve reliability.

I SAFETY EVAI.UATION: The work authorized by this FCR does not create any new adverse environmental effect and does not constitute an unreviewed safety question.

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t COMPLETED FACILITY CHANGE REQUEST FCR NO: 80-272 SYSTEM: N/A COMPONENT: Containment Barricade CHANGE, TEST OR EXPERIMENT: This FCR was implemented to install a barricade over the 3' high space around the plate of the incore monitor guide tubes on the 565' elevation in containment. Work was completed on September 8, 1983.

REASON FOR CHANGE: This change occurred due to the overexposure of personnel on April 30, 1980 as a result of inadequate barricades.

SAFETY EVALUATION: The barricade will result in a reduced possibility of inadvertent personnel radiation overexposure. Therefore, this FCR does not involve an unreviewed safety question.

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COMPLETED FACILITY CHANGE REQUEST FCR NO: 81-029 SYSTEM: N/A

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ll COMPONENT: Concrete Masonry Block Wall No. 4036 i

CHANGE, TEST OR EXPERIMENT: A steel beam was installed on each side I

along the top of wall 4036 to brace the top connection and a steel _

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angle. A beam has also been used near the top of the wall along each side to provide lateral bracing. Wall 4036 separates Electrical Penetration Room #1 (428B) from the Low Voltage Switchgear Room (428) at an elevation of 603'.

Work was completed March 9, 1984.

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REASON FOR CHANGE:

Block wall reanalysis per NRC IE-Bulletin 80-11 has shown that during a seismic event the concrete masonry, the vertical 1

reinforcing steel, and the east edge, bottom, and top connections of wall j

4036 could become overstressed.

f SAFETY EVALUATION: This modification has been reviewed and found not to i

adversely affect the ability of the wall to function as a fire barrier in l

any adverse manner. Therefore, this FCR does not involve an unreviewed safety question.

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COMPLETED FACILITY CHANGE REQUEST 2

I FCR NO: 80-047 SYSTEM: Reactor Coolant System COMPONENT: Pipe Whip Restraint' CHANGE, TEST OR EXPERIMENT: FCR 80-047 allowed the modification of the upper hot leg pipe whip restraint shown on drawings 7749-C-176. Rev. 6

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and 7749-C-600, Rev. 4 to meet the design criteria in the Final Safety i

Analysis Report. Modifications included the painting and priming of this piping, changing the bolt length to 12-3/4", and modifying the pipes installation. Work was completed February 3, 1981.

REASON FOR CHANGE: While performing the RCS pipe whip restraint verification study required by item 6.3 of the 0.I.&E Inspection Report 50-346/79-23, it was determined that the upper hot leg pipe whip restraint did not meet the acceptance criteria.

SAFETY EVALUATION: Since the modified restraint will be able to perform its design function under all postulated conditions, an unreviewed safety question is not involved.

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TOLEDO

%mm EDISON October 10, 1984 Log No. K84-1281 File:

RR 2 (P-6-84-09)

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, September, 1984 Davis-Besse Nuclear Power Station Unit 1 Enclosed are ten copies of the Monthly Operating Report for Davis-Besse Nuclear Power Station Unit I for the month of September 1984.

If you have any questions, please feel free to contact Bilal Sarsour at (419) 259-5000, Extension 384.

Yours truly, gGg CS Stephen M. Quennoz Plant Manager Davis-Besse Nuclear Power Station SMQ/BMS/bec Enclosures cc:

Mr. James G. Keppler, w/l i

Regional Administrator, Region III Mr. Richard DeYoung, Director, w/2 i

Office of Inspection and Enforcement Mr. Walt Rogers, w/l NRC Resident Inspector i

LJK/002 gfCL I

THE TOLEDO EOISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43652

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