ML20212M088

Monthly Operating Rept for Oct 1986

ML20212M088
Person / Time
Site:	Davis Besse
Issue date:	10/31/1986
From:	Khazrai M, Storz L TOLEDO EDISON CO.
To:	Haller N NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NEO-86-00024, NEO-86-24, NUDOCS 8701300002
Download: ML20212M088 (11)

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-346 UNIT Davis-Besse Unit 1 DATE November 10, 1986 COMPLETED BY Morteza Khazrai TELEPHONE (419) 249-5000, Ext. 7290 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) (Mwe.Neig 1

0

,7 0

2 n 18 0 3 0 39 0

4 0 20 0 5 0 7, 0 6 0 22 0 7 0 0 23 8 0 0 24 9 0 0 25 10 0 0 26 11 0 27 0 12 0 yg 0 13 0 29 0 14 0 0 30 _.

15 0 3 O 16 0 INSTRUCTIONS On this format. list the average daily unit power leselin MWe Net for each day in the reportina month. Compute to the nearest whole megawatt, i

(9 /77 )

070100 $NOO346 DR A PDR p l

3/)

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i OPERATING DATA REPORT DOCKET NO. 50-346 DATE November 10, 1986 COMPLETED BY Morteza Khazrai TELEPHONE (419) 249-5000, OPERATING STATUS

1. Unit Name: Davis-Besse Unit 1 Notes

2. Reporting Period: October 1986

3. Licensed Thermal Power IMW:): 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:

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

10. Reasons For Restrictions.If Any:

His Month Yr.-to.Date Cumulative II. Hours in Reporting Period 744 7.295 72.360.0

12. Number Of Hours Reactor Was Critical O 0.0 35,877.1

13. Reactor Reserve Shutdown Hours 0.0 0.0 4.058.8

14. Hours Generator On.Line 0.0 0.0 34.371.8

15. Unit Reserve Shutdown Hours 0.0 0.0 1.732.5

16. Cross Thermal Energy Generated (MWH) 0.0 0.0 81.297.600 .

17. Gross Electrical Energy Generated (MWH) 0 Q. 0.0 26.933.622

18. Net Electrical Energy Generated (MWH) 0.0 0.0 25.233.177

19. Unit Service Factor 0.0 0.0 47.5

20. Unit Availability Factor 0.0 0.0 49.9 [

21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 40.5

22. Unit Capacity Factor iUsing DER Net) 0.0 0.0 38.5

23. Unit Forced Outage Rate 100.0 100.0 35.6

24. Shutdowns Scheduled Over Ne.st 6 Months (T)pe. Date,and Duration of Each1:

25. If Shut Down At End Of Report Period. Estimated Date of Startup: November 11, 1986

26. Units in Test Status (Prior to Commercial Operation): Forecast Achiesed INITIAL CRITICA LITY INITIAL ELECTRICITY COsl%IERCI A L OPER ATION (9/77 )

DOCKET NO. 50-346 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Davis-Besse Unit 1 -

DATE November 10, 1986

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COMPLETED BY Morteza Khazrai REPORT MONTH October 1986 TELEPHONE (419) 249-5000. Ext. 7290 "u

jg } $ Licensee ag g Cause & Corrective g ag m juy Event gg gg Action to No. Date e uo o u :s Report # xv au Prevent Recurrence

$6 EMS O 8

7 85 06 09 F 744 A 4 LER 85-013 JK SC The unit remained shutdown following Cont'd the reactor trip on June 9, 1985.

See Operational Summary for further details.

I F: Forced Reason: Method:

S: Scheduled A-Equipment Failure (Explain)

Exhibit G - Instructions 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 G-Operational Error (Explain) 9-Other (Explain) Exhibit I - Same Source (9/77) H-Other (Explain) s

OPERATIONAL

SUMMARY

OCTOBER 1986 The unit remained shutdown the entire month of September following the reactor trip on June 9, 1985. Corrective actions and system upgrades continue.

Below are some of the major activities performed during this month:

1) Continued testing as part of the System Review and Test Program.

1

2) Continued Motor Operated Valves Analysis Test (MOVATS) activities.

3) Continued Raychem repairs and followup corrective actions.

4) All Reactor Coolant Pump vork completed.

REFUELING INFORMATION DATE: October 1986

1. Name of facility: Davis-Besse Unit 1

2. Scheduled date for next refueling shutdown: February 1988

3. Scheduled date for restart following refueling: April 1988

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 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: Summer, 1987

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 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: 1996 - assuming ability to unload the entire core into the spent fuel pool is maintained.

BMS/005

COMPLETED FACILITY CHANGE REQUEST FCR NO.79-324 SYSTEM Steam Generators COMPONENT OTSG Orifice Plate CHANGE, TEST OR EXPERIMENT FCR 79-324 performed an adjustment to the orifice plates from approximately 25% open to approximately 0% open.

This FCR was closed July 22, 1986.

REASON FOR CHANGE This change was incorporated due to a letter from B&W (B&W Letter DB-79-156) which had a concern on pressure oscillations.

SAFETY EVALUATION

SUMMARY

FCR 79-324 involved the adjustment of the OTSG orifice plates to an approximate closed position. B&W has provided a safety evaluation of OTSG 4

thermal hydraulic oscillations (DB-79-164 dated September 14, 1979). The B&W safety evaluation which has been reviewed by Engineering supports the conclusion that this change does not involve an unreviewed safety question.

I TEMP 2 C/335/4

COMPLETED FACILITY CHANGE REQUEST FCR NO.82-048 SYSTEM Pressurizer COMPONENT Check Valve CHANGE, TEST OR EXPERIMENT FCR 82-048 added a non-nuclear 1500 check valve upstream of valve NN-64 in the 1" line from the Nitrogen System to the pressurizer.

This FCR was closed July 11, 1985.

REASON FOR CHANGE The nitrogen piping and related equipment are rated for a maximum pressure of 120 psi and would fail when subjected to a pressure in excess of 2,000 psi.

This FCR was generated in response to Recommendation #2 of SOER 81-16.

SAFETY EVALUATION

SUMMARY

FCR 82-048 modified the Nitrogen Supply System which will prevent reactor coolant, which has a pressure in excess of 2,000 psi, from penetrating the small nitrogen supply line. The consequences would be the failure of the lower pressure rated pipe, resulting in loss of primary coolant.

The modification will not affect the safety function of the system.

Therefore, no unreviewed safety question is involved.

TEMP 2 C/335/3

COMPLETED FACILITY CHANGE REQUEST FCR NO.83-062 SYSTEM Emergency Ventilation System COMPONENT LPDY 5000A, LPDY 5000B, LPDY 5000C, and LPDC 5000 CHANGE, TEST OR EXPERIMENT FCR 83-062 relocated LPDY 5000A, LPDY 5000B, LPDY 5000C and LPDC 5000 from the Mechanical Penetration Room 303 to Roon 304 of the Auxiliary Building.

This FCR was closed April 25, 1984.

REASON FOR CHANGE This change was made due to a recommendation report from EDS Nuclear on environmental qualification of safety related electrical equipment due to radiation following a LOCA.

SAFETY EVALUATION

SUMMARY

The above equipment is required to function during a LOCA which could be exposed to a significant post accident dose. The equipment contains sensitive electronic components which have a potential radiation sensitiv-ity. This equipment was not tested for qualification. Shielding would not be feasible due to bulk and cost. Testing of this equipment would be costly. Relocation of the specified equipment is the best solution.

Equipment was relocated to an area where the radiation environment plus an accident dose of 1 x 103 rads would be maximum.

The work authorized by FCR 83-062 does not change the safety function, or create any new adverse environment, and doea not constitute an unreviewed safety question.

TEMP 2 C/335/5

COMPLETED FACILITY CHANGE REQUEST FCR NO.84-060 SYSTEM Pressurizer COMPONENT Pressurizer Heaters CHANGE, TEST OR EXPERIMENT FCR 84-060 disconnected essential heater cables for Pressurizer Essential Heater Bank #1 (upper heater bundle) and reconnected to heaters in the middle heater bundle. Heater cables disconnected from the middle bundle heater were reconnected to the heaters in the upper bundle previously used for Essential Heater Bank #1.

FCR 84-060 was closed September 12, 1984.

REASON FOR CHANGE This change minimizes the possibility of essential heater banks from becoming uncovered. A low-low level pressurizer interlock, which deenergizes pressurizer heaters, only functions when the heaters are in the automatic control mode.

SAFETY EVALUATION

SUMMARY

FCR 84-060 connected the essential heater cables to heaters in the middle bundle (rather than upper bundle). This does not affect the integrity of the pressurizer as a pressure boundary. The change enhances the heater operation by minimizing the possibility of uncovering the heaters when the low-low level pressurizer interlock is defeated. All wiring changes were done at the heater connectors. No changes were made within the pressur-izer heater junction boxes. The changes and additions do not create any new adverse environment and do not constitute an unreviewed safety question.

TEMP 2 C/335/2

. .o COMPLETED FACILITY CHANGE REQUEST FCR NO.84-073 SYSTEM Component Cooling Water COMPONENT N/A CHANGE, TEST OR EXPERIMENT FCR 84-073 demonstrated the capabilities of the leak measuring device and acoustic leak sensing equipment on the Component Cooling Water System.

This FCR was closed February 21, 1986.

REASON FOR CHANGE The test performance and data was used to develop a topical report to the NRC. This report was prepared by H. A.F. A. International for Toledo Edison. The topical report will be used to justify reducing hydro-testing and pressure testing requirements based on information gained from this test and other tests which will be performed.

SAFETY EVALUATION

SUMMARY

This FCR affected only Component Cooling Water Train #1, while Component Cooling Water Train #2 provided normal component cooling water functions.

This test resulted in entering a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action statement per Technical Specification 3.7.3. During the performance of this test, an operator and electrician were on standby to place Train #1 in service if required. The test did not prevent Component Cooling Water from providing the required cooling capacity to mitigate the consequences of an accident.

Since Component Cooling Water Train #2 was available throughout the test, and Train #1 was available with operator assistance, this test did not constitute an unreviewed safety question.

TEMP 2 C/335/1

f7 . .

M)LEDO

%su EDISON November 10, 1986 NE0-86-00024 File: RR 2 (P-6-86-10)

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, October 1986 Davis-Besse Nuclear Power Station Unit 1 Enclosed are ten copies of the Monthly Operating Report for Davis-Besse Nulcear Power Station Unit 1 for the month of October 1986.

If you have any questions, please feel free to contact Morteza Khazrai at (419) 249-5000 Extension 7290.

Yours truly, mai. .

/

Louis F. Storz Plant Manager Davis-Besse Nuc1 car Power Station LFS/MK/1j k 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. Paul Byron, w/l NRC Resident Intipector Nucicar Records Management LJK/002

>N THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43G52 l