ML19263D754

Monthly Operating Rept for March 1979

ML19263D754
Person / Time
Site:	Davis Besse
Issue date:	04/06/1979
From:	Caba E TOLEDO EDISON CO.
To:
Shared Package
ML19263D753	List: ML19263D752 ML19263D754
References
NUDOCS 7904130227
Download: ML19263D754 (10)

Text

AVERAGE D AILY UNIT POWER LEVEL t

50-346 DOCKET NO.

Davis-Besse Unit 1 gg7 April 6, 1979 DATE Erdal C. Caba COMPLETED BY 419-259-5000, Ext.

TELEPIIONE 236 F!a rch, 1979 MONT11 DAY AVERAGE DAILY PO% ER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 755 751 37 3

729 752 gg 2

737 39 756 3

760 462 20 4

694 754 21 5

487 752 22 6

544 755 23 7

754 754 2g 8

748 746 25 9

705 739 26 to 749 639 gg 27 635 748 28 12 754 631 13 29 448 756 30 14 756 o

15 3g 752 16 INSTRUCTIONS On this format,hst the nerage daily unit power leselin MWe Net for each ;ay in the reporting m'onth. Compute to the nearest whole mepwatt.

(9/77n

$3'O/1.l],}h(kf

a OPERATING DATA REPO'RT 50-346 DOCKET NO.

DATE April t>,

1979 Erdal C. Caba COMPLETED BY 419-259-5000 Ext.

TELEPl!ONE 236 OPERATING STATUS Notes Davis-Besse Unit 1

!. Unit Name:

[

.I rch, 1979

2. Reporting Period:

j 2772

3. Licensed Thennal Power IMWt):

925

4. Nameplate Rating (Gross MWel:

906

5. Design Electrical Rating (Net MWe):

to be di temined

6. Maximum Dependable Capacity (Gron MWel: to be detemined

7. Maximum Dependable Capacity (Net Mhe):

8. If Changes Occur in Capacity Ratings titems Number 3 Through 7)Since Last Report.Gise Reasons:

9. Power Level To which Restricted. If Any (Net MWe):

10. Reasons For Restrictions.If Any:

This Month Yr..to Date Cumulatise 744 2160 13,925

11. Ilours In Reporting Period 731.1 1,747.4 8.379.2

12. Number Of flours Reactor has Critical 12.9 80.7 871

13. Reactor Resene Shutdown flours 712.2 1,675.1 7,408.3

14. Ilours Generator On Line 0

0 0

15. Unit Resene Shutdown llours 1,602,76>

3,879,097 14,066,667

16. Gross Thermal Energy Generated (MWil)

17. Gross Electrical Energy Generated (Mbil) 1,293,268 4.677.023 534,407_

503,590 1,212,558 4,254,018

18. Net Electrical Energy Generated (Mull)

_ 95.7 77.6 56.2

19. Unit Senice Factor 95.7 77.6 56.2

20. Unit Asailabilitv Factor t be determined

21. Unit Capacity Factor (Using MDC Net) 74.7 61.9 38.5

22. Unit Capacity Factor (Using DER Net) 0 4.8 22.4

23. Unit Forced Outage Rate 2.f. Shutdowns Scheduled Oser Nest 6 Months (Type. Date.and Duration of Each):

APEII 0' 1979

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 CRIT!CALITY INITIAL ELECTRICITY COMMERCI A L OPER ATION (9/77)

DATE:

March, 1979 REFUELING INFORMATION L

Davis-Besse Nuclear Power Station Unit 1 1.

Name of facility:

2.

Scheduled date for next refueling shutdown:

March. 1980 1

h 3.

Scheduled date for restart following refueling:

Mav, 1980 Will refueling or resumption of operation thereafter require a technical 4.

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)?

Yes, see attached Scheduled date(s) for submitting proposed licensing action and supporting 5.

information.

Dec ember, 1979 Important licensing considerations associated with refueling, e.g., new or fuel design or supplier, unreviewed design or performance analysis l

6.

different me th od s, significant changes in fuel design, new operating procedures.

None The number of fuel assc=blics (a) in the core and (b) in the spent fuel 7.

storage pool.

(a) 177 (b) 0 (zero)

The present licensed spent fuel pool storage capacity and the size of any 8.

increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.

Present 260 Increase size by 475 (735 total)

The projected date of the last refueling that can be discharged to the spent 9.

fuel pool assuming the present licensed capacity.

Date__ March,1980 - May,1980 (assuming ability to unload the entire core into the spent fuel pool is maintained).

REFUELING INFORMATION Cont'd MARCH, 1979 PAGE 2 0F 2 The following Technical Specifications (Part A) will require revision:

4.

Reactor Core Saf ety Limits (and Bases) 2.1.1 & 2.1.2 -

2.2.1 - Reactor Protection Systen Instrumentation Setpoints (and Bases) 3.1.3.6 - Regulating Rod Insertion Limits 3.1.3.7 - Rod Program 3.2.1 - Axial Power Labalance (and Bases)

The following Technical Specifications (Part A) may also require revision:

3.1.2.8 & 3.1.2.9 - Borated Water Sources (and Bases) 3.2.4 - Quadrant Power Tilt (and Bases) 3.2.5 - DNB Parameters (and Bases)

}

50-346 DOCKET NO.

Davis-Hesse Un_it 1 UNIT S!!UIDOWNS AND POWL;l REDUCTIONS UNIT N AME DATE Anrtt 6,

1979 Char les N-Alm COMPLET ED By

1. • 19 '59-S000 Fxt. 251 March, 1979 T ELLPlf 0NE REPORT MONTil l

I

~.

Cause & Corrective

.5?

}

h.s' k E

Licensee

, r, a'b No.

Date g

32 g

.3 g &

Event a?

93 Action to Nu EV Present Recurrence Report #

$E E

3 5 =g u

O 7

79 03 14 S

5.5 B

4 NA HA INSTRU Only the turbine-generator was taken of f line to perfom further repair wor l.

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on the turbine's electro-hydraulic control system.

The checkout performeu indicated suspected failure of backup speed control circuitry. The possible defective circuitry boards were re-s placed.

The flain Feedwater Pump Turbine I had 8

79 03 21 F

0 A

4 NA CH INSTRU oscillat ing speed cont.rol problems and was shutdown at 1844 hours0.0213 days <br />0.512 hours <br />0.00305 weeks <br />7.01642e-4 months <br />..The troubleshoot 1np, and operational test-Ing revealed no problems and the pump was returned to service at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on Ilarch 23, 1979.

4 3

Exhibit G Instsuctions I

2 Method:

for Picparation of Data F: Forced Reason:

1-Manual S: Schedu!cd A 1:quipment Failnre(Explain) 2-Manual Scram.

Entry Sheets for Licensee Event Report (LER) Fife (NUREG-B.M.iintenance of Test 3-Automatic Scram.

C-Refueling 4 Other (Explain) 016I)

D. Regulatory Restriction 1:-Operator Training 1 License Examination 5

F-Adnunistiative Exhibit I-Same Source G Operational 1 irur (Explain)

(9/77)

Il-Othe r (Inplain)

t I

50-346 DOCKET NO.

Davis-Besse Unit 1 UNIT SitUTDOWNS AND POWut REDUCTIONS UNIT N AME April o, 19,y DATE Charles N. Alm COMPLETED BY 419-259-5000. Ext. 251 REPORT MONT!! March, 1979 TELEPIIONE I

Licensee

,E r, h'o 5 ?

3

)Y Cause & Corrective No.

Date g

3g i

is&

Event 3,7 e8 Action to gE y

5 ;g =2 Report a mu 8O Prevent Recurrence H

u s.

6 9

79 C3 30 S

26.3 B

1 NA NA NA A unit outage was initiated to pet-form scheduled maintenance work.

The major work items include the repair

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of Main Steam Safety SP17A2, the checi out and repair of control rod drive motor for Group 8, Rod 6, the repair of Makeup Pump 1, and the inspection of condenser tubes for leaks.

3 4

I 2

Methml:

Exhibit G Instructions F: For;ed Reason:

1 Manual for Preparation of Data S: Schedu!cd A.liquipment Failure (Explain) 2 Manual Scram.

Entry Sheets for Licensee D.M.iintenance of Test 3 Antonutic Scram.

Event Report (LElt) File (NUREG-C.Refuelmg 4.Other (Explain) 0161)

D Rcrolatory Restriction 1 Operatur Training 1 License Examination 5

F Administrative Exhibit 1 Same Source G. Operational Eiror (Explain)

PJ/77) 11 Other (Explain)

OPERATIONAL SUr!ARY FOR MARCH,1979 this entire month because the Main Steam Reactor power was limited to 92.91 percent Safety Valve SPl7A2 was inoperable.

3/1/79 - 3/3/79 The reactor power level was maintained at 86 percent with the generator gross load at 785 1 10 MWe until 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on A reactor power decreasa to 15 percent was March 3, 1979.

then initiated to enable further repair work of the turbine's electro-hydraulic control system with the turbine-generator off line.

Also, recorder instrumentation was installed on the number 3 turbine control valve to troubleshoot for the cause of oscil-lation problems.

The turbine-generator was taken off line at 0152 hours0.00176 days <br />0.0422 hours <br />2.513228e-4 weeks <br />5.7836e-5 months <br />, and the 3/4/79 electro-hydraulic control system checkout revealed that the The backup speed control circuitry may have electrical f aults.

defective backup speed control circuit boards were replaced, 0725 hours0.00839 days <br />0.201 hours <br />0.0012 weeks <br />2.758625e-4 months <br />.

and the turbine-generator was synchronized on line at Reactor power was then increased and attained 86 percent of full 1125 hours0.013 days <br />0.313 hours <br />0.00186 weeks <br />4.280625e-4 months <br /> with the generator gross load at 785 1 10 MWe.

power at 3/5/79 - 3/9/79 The generator gross load was maintained at 785 1 10 MWe with reactor power at 86 percent of f ull power.

Reactor power was decreased and maintained at 75 percent from 3/10/79 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> through 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> to isolate the high pressure feed-water heat exchanger train 2 for the inspection of feedwater heat exchanger 2-4.

The inspection was made to determine if the problems discovered in heat exchanger 1-4 were also present in 2-4 and to make the same modifications that were made to 2-4 heat exchanger.

Reactor power was increased at 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> and attained 86 percent 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> with the generator gross load at 730 of full power at 1 10 MWe.

The unit power icvel remained constant with reactor power at 86 3/11/79 percent, and the generator gross load at 780 1 10 MWe.

1125 hours0.013 days <br />0.313 hours <br />0.00186 weeks <br />4.280625e-4 months <br /> on March 3/13/79 - 3/20/79 Reactor power was increased to 87 percent at 13, 1979. The unit power level was then maintained constant with reactor power at 87 percent and the generator gross load at 790 1 10 MWe until March 18, 1979. Reactor power was then

PAGE 2 OPERATIONAL

SUMMARY

FOR MARCH, 1979 3/13/79 - 3/20/79 decreased at 0116 hours0.00134 days <br />0.0322 hours <br />1.917989e-4 weeks <br />4.4138e-5 months <br /> to 60 percent to perform turbine stop Continued valve testing. The testing was completed, and reactor power had been returned to 87 percent at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> on March 18, 1979.

An autanatic runback of reactor power to 60 percent was initiated 3/21/79 1835 hours0.0212 days <br />0.51 hours <br />0.00303 weeks <br />6.982175e-4 months <br /> due to low level in Deaerator #2.

The low level at was caused by Main Feedwater Pump 1 staying at high speed which forced Main Feedwater Pump 2 to low speed. Reactor power was 1844 hours0.0213 days <br />0.512 hours <br />0.00305 weeks <br />7.01642e-4 months <br />, and Main then manually decreased to 55 percent at Feedwater Pump 1 was shutdown to enable a troubleshooting check-out.

3/21/79 - 3/23/79 Reactor power was maintained at 60 percent from 1945 hours0.0225 days <br />0.54 hours <br />0.00322 weeks <br />7.400725e-4 months <br /> on March 21,1979, to 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on March 23, 1979, with the gen-erator gross load at 520 t 10 MWe. The control problem on Main be determined by the troubleshooting.

Feedwater Pump 1 coull not 0735 hours0.00851 days <br />0.204 hours <br />0.00122 weeks <br />2.796675e-4 months <br /> The Main Feedwater Pump 1 was returned to service at on March 23, 1979, uith operational testing until 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />.

The operational testing revealed no problems, and reactor power was returned to 07 percent.

3/24/79 - 3/26/79 Reactor power was maintained at 87 percent until 1615 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.145075e-4 months <br /> on March 26, 1979, when a power decrease to below 75 percent was initiated. The power decrease was required to shutdown the Reactor Coolant Pump 1-1 which had low oil level indication.

3/26/79 - 3/31/79 The generator gross output was held at 655 1 10 MWe, with reactor power at 73 percent until 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on March 30, 1979.

At this time, unit load was decreased to perform a scheduled The turbine generator was taken off line at maintenance outage.

2142 hours0.0248 days <br />0.595 hours <br />0.00354 weeks <br />8.15031e-4 months <br /> on March 30, 1979, and the reactor was suberitical at 1109 hours0.0128 days <br />0.308 hours <br />0.00183 weeks <br />4.219745e-4 months <br /> on March 31, 1979. The work items performed during the scheduled maintenance outage will be presented in next month's operational su. nary.

~

FACILITY CRA';GE REQUESTS COMPLETED DURING MARCH, 1979 j

~

'FCR No:

77-413 SYSTEM:

Emergency Diesel Generator (EDG) Room Ventilation COMPONENT:

EDG Room Supply Fans 1-1 through 1-4 discharge deflector vanes j

CRANGE, TEST, OR EXPERIME!.T: On March 8, 1979, the physical work was completed for FCR 77-413, which modified the design of the deflector vanes on the discharge of the EDG Room Supply Fans 1-1 through 1-4.

The 1/4" studs which held the vanes in place were removed and replaced with 3/8" rods welded along the length of each of the vanes.

The change was made with the approval of the unit architect / engineer, Bechtel Corpora-tion.

REASON FOR THE FCR: The vanes originally were held in place by means of 1/4" studs attached to each end of the vane. The vibration of the vanes due to the air flow across them was causing the original studs to break off.

_ SAFETY EVALUATION: This change, which replaces the 1/4" studs on the EDG room supply ian discharge deflectors with 3/8" diancter rods, will not affect the safety function of the fans. The change will replace a part that is breaking because of vibration, hence, reliability and availability of the fans will be enhanced.

i t

I

FACILITY CHANGE REQUESTS COMPLETED DURING MARCH, 1979 FCR NO:

78-496 SYS1EM: Final Safety Analysis Report (FSAR)

Section 14, Test Abstract of TP 800.14, " Turbine / Reactor Trip Test" COMPONENT:

CHANGE, TEST, OR EXPERIMENT: On February 22, 1979, Modification M-2697 was written as per FCR 78-496.

This modification deleted the requirement for a 100% reactor trip from Test Procedure TP 800.14.

The FCR also verified that the 100% turbine trip test need not be performed provided that the 100% load rejection test is successfully completed.

REASON FOR THE FCR: No commitments were made in the FSAR for a 100% reactor trip test.

The 100% load rejection test subjects the reactor and integrated control system (ICS) to transient conditions essentially identical to the 100% turbine trip test.

In addition, the 100% load rejection test tests the capability of the electro-1800 RPM.

hydraulic control (EHC) system to control the turbine-generator's speed at SAFETY EVALUATION: The FSAR made no commitment for the perfornance of a 100% reac-tor trip test.

The test objectives of the 100% turbine trip test are duplicated in the objectives of the 100% load rej ection test.

As the transient conditions imposed on the reactor and ICS are essentially identical and the test objectives of the 100%

turbine trip test are concurrent with those of the 100% load rej ection test, no un-reviewed safety questions are involved.