ML20106J426

Monthly Operating Rept for Dec 1984

ML20106J426
Person / Time
Site:	Beaver Valley
Issue date:	12/31/1984
From:	Carey J, Smith P DUQUESNE LIGHT CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8502150627
Download: ML20106J426 (8)

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OPERATING DATA REPORT j DOCKET NO. 50-334 l DATE 1/7/85 <

. COMPLETED BY P. Smith

. TELEPHONE. 417-64'4 ~1825

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OPERATING STATUS

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1. Unit Name: Beaver Valley Power Station, Unit #1 Notes .

2. Reporting Period: necember 1984

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3. Licensed Thermal Power (MWt): 766n O

4. Nameplate Rating (Gross MWe): -- 923 ..

5.. Design Electrical Rating (Net MWe); 835 , - -

6. Maximum Dependable Capacity (Gr'oss MWe): 860 -

7. Maximum Dependable Capacity (Net MWe): 810 -

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

9. Power Level To Which Restricted,If An'y(Net MWe): None

10. Reasons For Restrictions.If Any; N/A This Mont) .. . _.. Yr to-Date . " Cumulative

11. Hours in Reporting Period 744 3784 76,008 .

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12. Number Of Hours Reactor Was Critical 0 6476.3 37,355.7

13. Reactor Reserve Shutdown Hours 0 0 4,482.8..

14. Hours Generator On-Line 0 6304.1 36,082.9

15. Unit Reserve Shutdown Hours n 0 0

16. Gross Thermal Energy Generated (MWH) o 15,808,975 83,398,514

17. Gross Electrical Energy Generated (MWH) 0 5,065,500 26,494,400

18. Net Electrical Energy Generated (MWH) -7870 4,735',955 24,624,843

19. Unit Service Factor 0 71.8 49.7

20. Unit Availability Factor 0 71.8 49.7

21. Unit Capacity Factor (Using MDC Net) 0 66.6 43.4

22. Unit Capacity Factor (Using DER Net) 0 64.6 42.1

23. Unit Forced Outage Rate 0 3.0 27.1

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

Plant shutdown for 4th refueling began October 11 at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />.

Mcheduled duration: 86 days

25. If Shut Down At End Of Report Period. Estimated Date of Startup: January 4, 1985

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY N/A N/A INITIA L ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A _ N/A 8502150627 841231 / /

PDR ADOCK 05000334 (9/77)

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, AVERAGE DAILY UNIT ?OWER LEVEL

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. *I DOCKET NO. 50-334 UNIT 37?S Uni: #1

. . , .DATE 1/7/85 COMPLETED BY P. Smith c

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{;;TELDHONE (412) 643 1825

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MONTH December 1984

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. DAY AVERAGE DAILY POWER LEVEL DAY AYERAGE DAILY POWER LEVEL (MWe Net) .

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-- ~ - 0 2 0 gg

-0 3 0 39 0

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4 0 3 0 5 0 ~'

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3 0 . 0 24 9 0 0 3 ,

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26 Il 0 0 .

27 12 0 3

e 13 0 0 29 14 0 0 30 .

. 15 0 0 31 16 0 INSTRUCTIONS .

On this formst. list th6 average daily unit power lese!In MWe. Net for each day in the reporting month.Cmnpute su the nesrest whole rnepwsst.

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DOCKET NO. 50-334-l UNITSilUTDOWNS AND POWER REDUCTIONS UNIT NAME BVPS Unit #1 .

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- DATE. 1/7/85 I

.REPORTMONill December 1984 COMPl.ETER) RY ' P. Smith TELErtlONE (412) 643-1825

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Event be E4 5.'g Cause & Cuttectise i

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t i 11 12/1/84 S 744 C 4 N/A zz zzzzzzz'.

Stationrremained shutdown for 4th Refueling Outage..

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j i 2 3 8 l~: F.wsed Ressens: mithod: Exhiteit G. Instructhms 5: Schedu!cil A. Equipment Failure (Explain) t.4tanual f.n Peepnestiani of Dass B. Maintenance sii Test '

2-Manual scram Entr> Sheets for I.lcensee l C. Refueling 3-Automatic Scram Event Repent II.I'RI file INilREG

) D Regulatory Restrictient 4-continued From Previous Month 0161)

l'4)tweaten Training A IJcense Examinathn' 5-neduction 1 F.Adndnistrative '

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G.Operatimial 1:e rin ll7.mplaiset thhibit 1 Same,Simece i (1/77) II Other llhplain) 3 - - - _ .- . .-- -. __.

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'/. FOURTH REFUELING STEAM GENERATOR INSPECTION During the Fourth Refueling Outage, the primary side of the tubing in

'A' Steam Generator was examined by Westinghouse Electric Corporation. The M1Z-18, multi-frequency eddy current system, was utilized for the inspection of all 3388 tubes in 'A' Steam Generator. The tubes were inspected full length, that is, from the tubesheet on the hot leg side over the u-bend region to the tubesheet on the cold leg-side. Twenty-four (24)  ;

of the 3388 tubes examined contained through-wall defect indications in excess of the BVPS Technical Specifications limit of 40 percent. >

l Concurrent with the eddy current examination described above, a visual  !

examination of the secondary-side tube sheet region of all- three steam j generators was conducted. The visual examination included the assessment I of the condition of the secondary side of the tubes in the tube lane, the l flow slot, and the peripheral areas. -A weld rod (4-inch long) was found in i

'A' Steam Generator and a piece of flexitallic gasket was found in 'B' i Steam Generator each was subsequently removed. No other tube defects were noted by the contractor, Westinghouse Electric Corporation.

The following twenty-four (24)' tubes in 'A' Steam Generator were removed from service by mechanically plugging both ends of the tube. All the tubes removed from service contained a defect in excess of the 40 percent limit.

Tube Location Defect Size Row Column %TWd Defect Location 1 2 48 18 inches up from the hot leg tubesheet 1 3 61 18 inches up from the hot leg tubesheet 27 11 47 2nd Support up on the Cold Leg Side 29 12 42 3rd Support up on the Cold Leg-Side 32 17 49 1st Support up on the Cold Leg Side f

36 21 42 2nd Support up on the Cold leg side 39 25 45 3rd Support up on the Cold leg side 41 26 49 3rd Support up on the Cold Leg Side 41 28 42 2nd Support up on the Cold Leg Side 43 32 46 3rd Support up on the Cold Leg Side 1

44 34 42 3rd Support up on the Cold Leg Side ,

I 43 36 48 3rd Support up on the Cold Leg Side 1 i

. 44 36 45 2nd Support up on the Cold Leg Side .

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i 43 37 43 1st Support up on the Cold Leg Side j i i  ;

44 39 42 2nd Support up on the Cold Leg Side i

j Tuba Locction D2fcct Siza Row Column %TWd D9fect Locetien 1

45 43 43 2nd Support up on the Cold Leg Side 26 44 40- 4th Support up on the Cold Leg Side 33 44 63 4th Anti-v3bration bar 33 48 60 4th Anti-vibration bar.

24 62 45 3rd Anti-vibration bar 1 90 69 18 inches up from hot leg tubesheet 1 91 87 18 inches up from hot leg-tubesheet 1 92 77 18 inches up from hot leg tubesheet 1 93 41 18 up inches from hot leg tubesheet 4

Upon completion of all plugging and retrieval activities, the Steam Generators were returned to service.

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'Af Telephone (412) 333-6000 Nuclear Division P.O. Box 4 Shippingport, PA 15077-0004 January 7, 1985 Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Monthly Operating Report United States Nuclear Regulatory Commission Director, Office of Management Information & Program Control Washington, D.C. 20555 Gentlemen:

In accordance with Appendix A, Technical Specifications, the Monthly Operating Report is submitted for the month of December 1984.

Also, please find attached the results of the Fourth Refueling Steam Generator Tube Inspection in accordance with Surveillance Requirement 4.4.5.5, Technical Specifications.

Very truly yours, d

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()iePresient

' lear Group Enclosures cc NRC Regional Office, King of Prussia, PA

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w .4 NhrrstivaSummaryofMonthly Operating Experience - Decer.ber 1984 December 1 The station was in cold shutdown for through 4th Refueling and major modification.

December 10 December 11 At 0920 hours0.0106 days <br />0.256 hours <br />0.00152 weeks <br />3.5006e-4 months <br /> on the lith RCS heatup through to approximately 104*F was begun, while December 15 pressure was maintained at ambient conditions.

December 16 On the 16th a steam bubble was established -

through in.the pressurizer at 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br />. RCS temperature December 21 was 140'F pressure was 150 psig. Filling of the Feedwater Heaters and the Condenser began at 2045 hours0.0237 days <br />0.568 hours <br />0.00338 weeks <br />7.781225e-4 months <br /> on the 16th. At 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on the 19th' began RCS pressurization to 250 psig.

Continued RCS pressurization reaching'300 psig on the 21st.

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December 22 At 1719 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.540795e-4 months <br /> began pulling containment vacuum.

Stopped pulling containment vacuum,at 1,850 hours0.00984 days <br />0.236 hours <br />0.00141 weeks <br />3.23425e-4 months <br /> with pressure at 12.3 psia due to a required containment entry to check cable connections for rod B-8.

December 23 At0930 hours reinitiated drawing containment vacuum until 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br /> when operations were secured with pressure at 9.9 psia.

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At 1415 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br /> a spurious reactor trip occurred while trithdrawing shutdown b:nhc. !cnh "!." was at 225 steps while Bank "B" was at 5 steps. The cause was an over-temperature AT spike that occurred during reinstallation of low level temeprature loop amplifiers.

A maintenance surveillance procedure on Power Range Detector, N-41 was in progress at the time with loop I '

bistable tripped.

At 1759 hours0.0204 days <br />0.489 hours <br />0.00291 weeks <br />6.692995e-4 months <br /> began RCS heatup to approximately 250'F.

RCS pressure was 300 psig. Started Reactor Coolant Pump 1A at 1810 hours0.0209 days <br />0.503 hours <br />0.00299 weeks <br />6.88705e-4 months <br />. Entered Mode 4 at 1852 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.04686e-4 months <br />.

December 24 Began plant cooldown at Mode 5 and through repressurization of containment. On the 27th December 27 entered Mode 5 at 0634 hours0.00734 days <br />0.176 hours <br />0.00105 weeks <br />2.41237e-4 months <br />. Started drawing containment vacuum at 0915 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.481575e-4 months <br />. Began plant heatup to Mode 4 at 1307 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.973135e-4 months <br /> and entered Mode 4 at 1426 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.42593e-4 months <br />. Continued with heatup toward Mode 3.

December 28 Started IB Reactor Coolant Pump at 0115 hours0.00133 days <br />0.0319 hours <br />1.901455e-4 weeks <br />4.37575e-5 months <br />.

Entered Mode 3 at 0330.

December 29 The station was in Operational Mode 3, through hot standby. The RCS temeprature and pressure December 31 were being increased to normal operating level.

Surveillance testing was in progress.

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i Major Maintenance - December 1984

1. 10-year Inservice Inspection of welds in Containment

2. Retube of the Main Condenser

3. . Inspection of Main Unit Generator b 4. Replacement of First Point Feedwater Heaters [FN-E-1A, 1B] i

.- 5. Overhaul of Main Feedwater Pump [FW-P-1A]  :

6. Reactor Coolant Pump [RC-P-1B] Seal Inspection and Maintenance w.--....~ I' i

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