ML20214L635

Monthly Operating Rept for June 1986

ML20214L635
Person / Time
Site:	Davis Besse
Issue date:	06/30/1986
From:	Khazrai M, Storz L TOLEDO EDISON CO.
To:	Haller N NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
KB86-0661, KB86-661, NUDOCS 8609100304
Download: ML20214L635 (14)

Text

AVERACE DA!LY UNIT POWER LEVEL V 50-346 DOCKET M.

gy Davis-Besse Unit 1 DATE - July 10, 1986 C098PLETED BY Nortesa Khaarai TELEPIIONE (419) 249-5000 Ext. 7290 m June 1986 DAY AVERACE DAILY POWER LEVEL DAY AVIPAGE NAILY POWER LEVEL (htwo Met) (M We Net) 1 0 j7 0 2 0 is _

0 3 0 l, _ 0 4 . 0 20 0 __

g 0 --

21 0 4 0 g 0 7 0 0 23 S 0 u 0 9 0 gg __

0 10 -- 0 2's 0 ll 0 27 0 12 0 28 --

0 13 0 2, 0 l

14 0 3g 0 18 --

0 3, le l

l INSTRUCHONS

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On.this forma.t, list the average daily unit pour levelin WWe Net for each day la the reporting month. Compute su the nesseet whole mopwett. ,

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8609100304 860630 PDR ADOCK 05000346 ,

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y CPERATING DATA REPORT acessTNo. *-30-3R ,.., 1986 DATE CobrLETED sy r Khaarai TELIFHONE '

9-5000, pyggg mg Ext. 7290 g, y y,,,, Davie-Besee Unit 1 Neess

2. % Forteg. June 1986 . ,

3. Liseased Thanual Peeer (MWt): 2772

4. Namepiste Rating (Geens MWe): '" ,

5. Design Elseedest Ra:Ing (Net MWe): 906

4. Mashoum Dependable Caposity (Geess MWe): 904 -

7. Manimum E-; "' Caposity (Not MWe):

860

8. If Chasses Oesur is capaeley Ratings (tsens Number 3 Timeugh 7) Sines last Report. Give Reesees:

, 9. Power Level To Which Reseristed. lf Amy (%t MWe):

j 10. Reneses For Restristisse.lf Amy: ___

I y ThisMeath YrAsGess Caenulative l

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!!. tienela Reporths Peded 720 4.343 69.408

12. Neesher of House Reesser Was Critlant 0.0 - 0.0 35,877.1

13. Reseter Reserve Sheedown Hours 0.0 0.0 4.058.8

14. Hours Generever On Line ,

0.0 0.0 34,37t.s

15. Unit Resene Shutdown Heure 0.0_ - - _

0.0 1,732.5 Id. Genes ThermeI Inorgy Generated (MWH) 0.0 0.0 51,297,600 .

11. Gewes Electrient Energy Generated (MWH) _ 09. 0.0 26,933,022

18. Net Electriest Energy Genanted (MWH1 0.0 0.0 25,233,177

19. Unit Servlee Facter 0.0 0.0 49.S

20. Unit Avellability Foster 0.0 0.0 52.0

21. Unit Capacity Facter (Using WDC Net) -

--- 0.0 0.0 42.3

22. Unit Capacity Feeter (Delag DER Net) 0.0 0.0 40.I

23. Unk Forced Ousage Rate inn n 100.0 31.8

24. Shuadowns Scheduled Orar Next 6 Meaths (Type. Dese,and Duration of Each l: ,

25. If Shut Down At End Of Report . Estienesed Date of Startup: - October 18, 1986

34. Units la Test Sentes (Prior te Cesiumeretel Operesien): Forumet Achieved INtflAL CRITICALITY --

INITIAL ELECTRICITY __

COMMtRCIAL OPERAfl0N v

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IMIT SEftDOMRS AB FOMER REDE:TIONS IMIT RAIS _ Davis-Benne Unit 1 ,

{l BATE July 10, 1986

] 00BF12TED BT Morteza Ehsaral

' REFCET MINTE June 1986 TEN __(419) 249-5000. Ext. 7290 i-i i

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No. Bete E E a_g I

Report # Eo o

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Present Becurreece

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l 7 85 06 09 F 720 A 4 LEst 85-013 JE SC The unit remained shutdown follouing 1 m t'd the reactor trip on June 9.1985.

I See Operational Samusery for further

details.

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F: Forced Reason: Method: Mahabit C - Instructimes S: Scheduled A-Eaguipment Failure (Explain) I-8Isamal for Properation of Bets 5-Maintenance or Test 2-48menal Scram Entry 8h==es for Liem====

C-Refoe11aK 3 a=*a== tic Scram Event Bepart (IER) File W latory testrictica 4-Contimention from M 161)

E-Operator Training & License Examination -

Frewfous Meath

{ F-Administrative 5-Imad Bedmetion l C-eperational Error (Explain) 9-Other (Emplain) Exhibit I - Same Source i

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4 OPERATIONAL StDOW.T y JUNE 1986 .

The unit remained shutdown the entire sonth of June 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 Systes Review and Test Program.

2) Continued Motor Operated Valves Analysis Test (H0 VATS) activities.

3) Completed Raychem repaire for Decay Heat Loop No. ,2 and Energency Diesel Generator 1-2.

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CCNFLETED FACILITY CHANGE REQUEST Y l l

FCR N0 77-234 -

M Various CQNPQNINT Emergency Control Transfer Switches and Cabinets CDE12A2 CDF11A1 CDF11C. CDYE2 and CDYF2 CHANCE. TEST OR EXPERIMENT This FCR implemented round handles on all emergency control transfer switches and installed barriers near cabinets CDE12A2 CDF11A1 CDF11C.

CDYE2 and CDYF2 This FCR was closed April 14, 1982.

REA30F_101 CIAMGE The original emergency transfer switches could easily be bumped out of position and could stop in midposition. When in midposition, equipment could not be actuated from the Concrol Room.

V SAFETY EVALUATION

SUMMARY

All modifications performed to the cabinets by this FCR do not prevent a

safe shutdown of the plant. This is not an unreviewed safety question.

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• COMPLETED FACILITY CHANGE REQUEST w *

!.gR gg 11-386 M Mein Steam CONFONENT Yalves SP7A and 8775 CHANCE. TEST OR IIFERIMINT This FCR modification changed the trip logic for the Startup Feedwater Valves SP7A and 5F75 from 1/2 to 2/2 logic.

This FCR was closed January 31. 1986.

REASON FOR CHANGE Trip scheme for SF7A and SF75 was 1/2 logic to trip. 8purious SFRCS trips closed SP7A and SF73 and at low power levels, stese generator levels decreased. This caused a full SFRCS trip, which resulted in a plant shutdown.

V SAFETY EVALUATION SUMMART The modification to the startup feedwater valve logic are nuclear safety related, except for portions of the installation which require a FICA consideration due to the routing through the Auxiliary Building. Installa-tion in accordance with FICA has precluded those portions from creating

, any new adverse environment. An unreviewed safety question is not involved.

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CCHPLETED FACILITY CHANGd REQUEST ',

v FC1 50 79-348

.SYSTE Freasuriser COMPONINT Fower Operated Relief Valva (PCRV)

Pressuriser Code Safety Valves CHANCE. TEST OR IIFERIMENT This FCR implemented the following changes:

1. Adjusted the PORV setpoint (PSEL-RC2-5) to 2430 pais with tolerance of 22 pois for open and 2400 22 pois for close.

2. Adjusted the pressuriser code safety valves so they shall be operable with a lift setting of 2300 212 peig (HOT).

3. Modified Technical Specification sections 3/4.4.2 and 3/4.4.3.

1 This FCR was closed May 24, 1984.

v REASON FOR CHANCE

1. Reduce the probability of opening the FORY during any transient.

2. Reduce the probability of opening the'pressuriser code safety valves during any transient. <

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3. Modify Technical Specifications 3/4.4.2 and 3/4.4.3 to reflect revised setpointe for the PORV and pressuriser code safety valves.

SAFETT EVALUATION St4 Wtt The probability of occurrence or the consequences of an accident or malfunction of equipment important to safetye previously evaluated in the Final safety Analysis Report (F8AR), has not been increased.

The possibility of an accident or malfunction of a different type other than any evaluated previously in the FsAR has not been created.

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The margin of safety,as defined in the bases for Technical Specifications has not been reduced' .

Based on the above it is determined that an unreviewed safety question does not exist.

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COMPLETED FACILITY CHANGE REQUEST M 79-397 SYSTEN Clean Liquid Radweste CONF 0NEFT Spent Haein Transfer CHANCE. TEST OR IIPan_mmsT This FCR modified the spent Rosin Transfer systes to accomplish the following:

1. Increase effectiveness of sparsing/ sizing of the Spent Rosin 8torage Tank.

2. Ensure all piping in the system can be flushed following a resin transfer operation.

3. Provide an adequate resin-water ratio to ensure efficient transfer.

This FCR was closed February 21. 1986.

V REA501 191_CRApf,E

' During resin transfer operation. transfer lines plugged with resin. The reason was auspected to be inadequate mixing or agitation of the tank, and unreliable control of resin-water ratio.

SAFETY EVALUATION 8tMMARY

' This TCR modified piping in the Spent Resin Transfer System. These modifications Technical Position were Paper made in accordance ET85 11-1. with ASME III Claes 3. or NRC Branch These changes were aimed at improving the operability and reliability of the Spent Resin Transfer Systes, and reducing personnel radiation exposure.

The changen did not involve an unreviewed safety question.

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CCHPLETED FACILITY CRAIIGE REQUEST l v i i

ECA No 80-043 i

S__Y373! Rosetor Coolaat System 1

M C-32 Snubbers CHANCE. TR5T OR RIPERDtINT '

This FCR modified the large born RC 8" and 20" saubbers.

This FCR was closed February 21, 1986.

REASON FOR CHANGE This FCR modification upgraded our anubbers to current state-of-the-art, to permit assier rebuilding and easier testing in the future.

SAFETY IVALUATION SUIGdARY The FCR modified the large bore RC 8" and 20" onubbers. The modification

• and testing were done in accordance with Specification 12301-C-32Q Revision 0 to assure that the enubbers met their operational requirements and their intended safety function. Based on the above modification and testing, no i unreviewed safety question exists.

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CCHPLETED FACILITY CRANGE REQUESTS v

FCR No 80-183 SYSTEM Component Cooling Water System COMPONENT P36-1. P36-2, 736-3 and F36-4 CRANGE. TEST OR EXPER "T ThisFCRdeletedthefollowingvalvesfromP4IDM-0455:

CC 310 CC 312 CC 317 CC 319 CC 324 CC 326 CC 330 CC 332 This FCR also renumbered the following drain valves:

CC 311 resusbered to CC 193 CC 318 renumbered to CC 293 CC 323 renumbered to CC 393 CC 331 renumbered to CC 493 v This FCR was closed February 22, 1984.

REASON POR CRANGE This tiene.correction wse made so that P&lD M-C405 reflects actual plant condi-RAFETY EVALUATION .

The intent of these never-instelled vent and drain valvee was to vent and drain the component cooling lines at the Reactor Coolant Pumps. Valvee CC 193. CC 293 CC 393. CC 493. CC 313, CC 320. CC 327 and CC 333 have been evaluated and found adequate.

Based on the above dieeuseson, this does not tapair the draining or venting of.the component cooltag lines. This change does not result in an unreviewed safaty quespion. I '

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CtMPLETED FACILITY CRANGE REQUEST  !

, ISR 3,40-113

sYsTIN Nechanical Penetration toons 3 and 4 COMPONINT Fipe Chase i

CEANGE. TEST 01IIFERMEllT This FCR provided curbs for preventing, in the event of a main feedwater line break, large quantities of water from entering the pipe chase openings in the southeast corner of Mechanical Penetration Roos #3 and in the south side of Mechanical Finetration Room f4.

This FCR was closed February 24, 1984, i

REASON FOR '* M E This FCR was written in response to a walkdown required by II Bulletin 80-11. It was discovered that the pipe chase openings in Mechanical Penetration Roose 3 and 4 did not have curbs constructed around them.

V SAFITY EVALUATICW 80tetARY This FCR added curbs around the pipe chases in Mechanical Penetration .

Rooms 3 and 4. In the event of a main feedwater line rupture in these

' rooms the curbs will prevent water from running down the pipe chase into the Energency Core Cooling System rooms on Elevation 545'. This modifica-l tion did not result in an unreviewed safety question.

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COMPLETED FACILITY CHANGE REQUEST 8 Y

FCR wo 81-099 SYSTEM Safety Features Actuation Systes (8FAS)

COMPQN_ INT SFA8 Main Control Cabinet C-5717 CRANGE. TEST OR IIPER N mrT '

i C-5717 to reflect so-built conditione.This FCR revised the connection  !

This FCR was closed February 13. 1986.

REASON FOR #_"GE The physical coincide connectione with the diagrams. in the SFAS Main Control Cabinet C-5717 did not modifications. This change was made which will aid in future SAFITY EVALUATION SUl0(ARY v ,

electrically tions in the cabinet. correct, they did not accurately reflect the ph Teature Actuation System based on the work No new authorised adverse environments were created, and this modification did not constitute an unreviewed safety question.

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s COMPLETED FACILITY' CHANGE REQUEST V

M 82-140  !- 3 IE SYSTEN 480 Volt Subetstion CONFQlfEllT Unit Sub E2 and F2 CHANGE. TEST OR EXFERTME'T This FCR added an alternate power supply to the Folar Crane (H-005) which is installed inside Containment.

This FCR was closed February 26. 1986.

8'A*0N FOR CHANGE The addition of an alternate power supply to the Folar Cranc allows electrical maintenance work to be performed without interrupting power to the Polar Crane.

SAFETY EVALUATION SIMfARY Installation of the conduit and manual transfer switch was installed in accordar.:e with FICA requirements. PICA requirements prevented this equipment from creating an. adverse environment. Based on the above, no unreviewed safety question exists.

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• 1 f July 10, 1986

( Log No. KB86-0661 Piles RR 2 (P-6-66-06)

Docket No. 50-346 License No. NFF-3 Oh 935s\Wj 08 y Mr. Norman Haller. Director Office of Management and Program Analysis y!S1g,g6D U. S. Nuclear Regulatory Commission /'

Washington, D.C. 20535 ge aM Dear Mr. Haller Monthly Operating Report, June 1956 Davis-Besse Nuclear Power Station Unit 1 i

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

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

Yours truly, t.. v. sg /.aw a .

Louis P. Stors Plant Manager Davis-Besse Nuclear Power Station LPs/Mx/1jk bec F. Heizer, PUC0 Enclosuree Public Relations Director Nuclear Fuel Manager ec's Mr. Jamee G. Kappler, w/1 Nuclear Services Direct, c/o DB.

Regional Adatinistrator, Region III Nuclear Reliability Supervisor Nucl. Facility Eng. Director Mr. Jhmes M. Taylor. Director w/2 Nuclear Safety Manager Office of Inspe,ction and Enforcement Compliance coordinator (2)

Gen supt Possil Gen Fac Mr.PaulByronfw/1 Technical Support Manager

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NRC Resident Inspector H. W. Kohn INP0 Records Center American Nuclear Insurers R. Novgrad R. C. Schuerger V LJK/002 Operations Engineering Special Programs THE TOLt00 ECWON COMPANY E0150N PLAZA 300 MADISON AVtNutD' MMU10 a3668

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