NUREG-1066, Forwards Table of B&W Plants Comparing Selected TMI Actions from NUREG-1066.Incomplete TMI Items for Facility Listed Per NUREG-0737.NUREG-0737 & Suppl 1 Active Items Re post-implementation Reviews Also Listed

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Forwards Table of B&W Plants Comparing Selected TMI Actions from NUREG-1066.Incomplete TMI Items for Facility Listed Per NUREG-0737.NUREG-0737 & Suppl 1 Active Items Re post-implementation Reviews Also Listed
ML20132D135
Person / Time
Site: 05000000, Davis Besse
Issue date: 06/20/1985
From: Thompson H
Office of Nuclear Reactor Regulation
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML20132B273 List: ... further results
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-1.C.1, TASK-TM NUDOCS 8506270129
Download: ML20132D135 (6)


Text

__

M Docket No. 50-346 3ilii } ' 'E g* k MEMORANDUM FOR:

Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:

Hugh L. Thompson, Jr., Director Division of Licensing

SUBJECT:

DEGREE OF COMPLIANCE OF DAVI.,-BESSE 1 WITH TMI ITEMS All post TMI items (NUREG-0737) have been completed at the Davis-Besse plant except:

1.

I/.D.1 (Supplement 1 to 0737) - Implementation of the Control Room Design Review.

The licensee pet the Order regarding the submittal of the sumary report and schedules.

The licensee's schedules for implementing the changes are currently stretched out over the rext 4 years with completion by startup from the 7th refueling.

2.

II.F.2 - Inadequate Core Cooling.

All aspects of the modification rec;uired by our-December 1982 Order are installed except for the continuous vent from the reactor vessel head to the hot leg. Staff has approved the preliminary continuous vent design and the licensee still plans to complete installation during the 1986 refueling (t! inter of 1986)

The Table 2 comparison of selected TMI actions from NUREG-1066 for B&W plants, updated as noted, is enclosed (Enclosure 1).

As a matter of separate interest, the following NUREG-0737 and Supplement 1 items are still active regarding staff post-implementation reviews.

MUREG 0737 Comoletion Tarcet I.C.1 ATOG 03/30/87 II.B.3.2 Post Accident Sampling 09/30/85 II.D.1 RV and SV Testing 03/31/86 II.F.2 ICC 09/30/86 II.K.3.30 SBLOCA Methods 12/31/85 II.K.3.3.1 Compliance with 10 CFR 50.46 01/31/87 i

Supolement I to 0737 1.D.1 Detailed Control Room Design Room 09/30/85 1.D.2 SPDS (Confirmatory Review) 09/30/85 h

gsd4:n%s 29 i

i

i,.

Harold R. Denton,.

Comoletion Tarcet III.A.I.2 Tech Support Center - Regional To be reviews established Operations Support Center - Recional by Region III reviews Emergency Operations Facility - Regional reviews j

III.A.2.2.

Meteorological Data Upgrade - Regional reviews Hugh L. Thompson, Jr., Director Division of Licensing

'l

Enclosure:

As stated DISTRIBUTION Docket File ORB #4 Rdg Memo File i

i D:DL[/[ son QpfA:DL

  1. 4:DL AD: R:DL Auem9u.v,wr

?<W GL Oias HThomp 6

/85 6/ 185 6/g/85 6/7)/85 l

l l

e l

o e-

/

ENCLOSURE 1 TAllLE 2 NtlREG 0737 ITEM ANO-1 CRYSTAL RIVER DAVIS 8 ESSE OCONEE RANLil0 SECO THI g _.

l.A.I.3, Shift

] ~ ~,-

Hanning C

C C

C June 1985 C

I.C.1, ATOG C

C

-November--1984-C October 1985 Nor '::. 1904C C

I.D.1, CRDR NS NS NS NS NS May 1984 C J/,;. H / 3 C anuary 1985 - I(6' I.D.2, SPDS C

August 1985 C

/4,Q.luly 1985

. v;;.:,c. 195C. -

G ea 9~4'lirn0*f-

'S6 11.8.1, RC Vents C

C C

October 1985 C'

C II.B.2, Plant Shielding C

C C

C C

December 1984" II.B.3, Post-0 Accident Sampilng Hay--1984-b C

C Hay-1984-0 C

C II.D.1, Reifef and Safety Valves C

C C

C C

C II.E.1.1. AFW C-Evaluation JeH989 Au st 1985 C

C June 1986 Fall 1985*

9J,ygarab,f II.E.1.2, AFW Initiation G

and Flow Jam-M85-Au yst 1985 C

C C

Fall 1985,

II.E.4.1.2, Hydro-gen Penetrations C

C C

C C

C t

FOOTNOTES ARE ON NEXT PAGE 6

---.~..,--u-

~..

~+

3.-

- NUREG 0737 ITEM ANO-1 CRYSTAL RIVER DAVIS BESSE OCONEE RANC110 SECO THI II.F.1.1, Noble Gas C

C C

C C

C ll.F.1.2 Iodine /

Particulate C

C C

C C

C ll.F.1.3, Contain-ment Radiation C

C C

Janr-1985-C.

C C

II.F.1.4, Contain-ment Pressure C

C C

C C

C II.F.1.5, Contain-ment Water Level C

C C

C C

C ll.F.1.6, Contain-ment flydrogen C

C C

C C

C N=*

ll.F.2, ICC Summer 1986 August 1985 all1986@

Jarr. 1987 Oct. 1986 Fall 1985*

(e,LL sa

=

II.A.I.2, Emer-gency facilities C

C C

C Am 1994-C C

III.A.2.2, Het.

C Data June-1984 Jtriy-M24 C C

Dec---1984-C C

C lli.D.3.4, Control Room Habitability C

C C

NS "r;. 1 ^0M fall 1985*

c. 9*G',

C = Complete hl Date - Expected completion date (generally depends on refueling nutage scheduled to start or end around the approximate date indicated). For THI-! all dates shif t to next refueling outage if allowed to start-up. For Oconee, dates indicate when all three units will be complete.

NS = not scheduled yet. Physical modifications will be done afte-the human factors review is complete.

  • Estimated period o' the first refueling following restart assuming THI-I restart occurs in July 1984.
    • Estimated sched se of eddy-current inspections of Steam Generators assuming THI-l restart occurs in July 1984.

7 t + 4 Cayeilui.fitJ str2M s2v<ew-tw% g mJ ya,rrea,3,

i

~

riectar trip. He svent see esseed by estItenance personnet Imedvertestly spezing a feedertsr pump condisser ergia selve uhtch esuisd less af

/

eso at 152 whez e resetsr trip accerted on Is-Is sesse graerster level.

/

veccue end tripped the esta feed wtse pump. Upon tsturn to Power, Unit I

]* J 7

The event occurred when treneferring feedveter to the esta feeduster pumpe. Unit I le currently operating at 91E power. Routine followup.

Parley I WQ Duty Of ficer. 6/23 The unit trtyped f ree 991 power en a nogettee rate flue trip at 3:55 p.m.

DR:

30-348 Reeldent inspector 6/24 EST. on 6/23. The lleensee diec'evered two blown fuses in the rod control cabinet for shutdown rode E-Il and L-il of tank D. Creep 1.

Further evaluet ten showed the cause to be shorted etreult leede la containment penettet ton 8037, endule A.

D e licensee hee reconnected the rode to opere tereinale. All eefety eyeteos functioned se deslaned. The licensee to continutn6 the evaluetten of the shorted leeds. De unit to to restert tedey, 6/24 The reeldent loopector will observe the restert.

McCutre i NQ Duty of ficer. 6/23 On 6/23 while in Mode.3 a tese of both meta feed pumpe end inteletion of DN 50-369 Auelltery feedveter occurred when plugging in the stese generator level etely chart recorder ef ter estatenance. The stese generatere estatetned level en emelltesy feedwater supply. Evaluetten to continuf ng.

Unit I to currently in Mode 2.

Routine fellemup.

DAILY REPORT Rill DATE 06/26/85 rect itt y/Licenece Wettf tcat ten

  • Itee er Event Reglemal Actton DtvlSIOli 0F REACTUR PROJECTS CUISIONWEALTN IN!SSRS. JAMES C. EEPPIER C. E. WORELIUS.

INFORMAfl0N ONLY EDISOII N. CNRISSOTIMOS AND Sal'S FROM INE ONSIONWEALTN PLANTS EDISON COMPANT WILL ATTEND A MANACEMENT MEETING Af lASALLE TU DISCUSS THE OIICOING BECULATORT IMPROVEMENT PROGRAM POR QDOIONWEALTN EDISON PLANTS.

lASALLE I AND 2 MESSRS. JAMES C. REPPLER. C. IIORELIUS. W. SCNULTZ, S. BERSON. N. CHRISSOTIMOS. AND A. MADISOII WILL 4

CONDUCT AIB ENFORCEMENT CONFERENCE WITN MANACEMENT REPRESENTATIVES OF C01980NWEALTN EDISON COMPANT TO DISCUSS THE RECENT EVENTS INVOLVIIIC THE IA55 0F ALL 199ERCEIICT CDRE COOLIIIC STSTEMS FROM JUIIE 5 THROUCII JUNE 10. 1985 At IASALIA.

STROII IPelf I TEt2ONI PROM SRI AT 0I26 ON 6/26/05. TNE REACTOR TRIPPED FROIt 988 PER MC 2515 POWER 011 STEAM CENERATOR 14 la la 12 VEL.

TASS OF RESIDENT CEIIERATOR 1412 VEL WAS CAUSED Of AN INADVERTANT TRIP INSPECTORS ARE OF THE IC MAIN PEEDWATER PUMP DUE TO EQUIPMENT ONSITE POLIAWIIIC OPERATORS RADIO DECnMIIIC ENTANCLED WITH THE Pt#IPS LICENSEES

/

OveASPEED TEST SWITCN. LICENSEE PERSONNEL MANUALLY

ACTIOIIS, f

RAN SACE THE TUROINE AIID STARTED TIIE lA MAIN y

l' FEEDWATER PUIIP. SUT WERE INIASLE 10 MAINTAIN I2 VEL g) l IN TNE IA CENERATOR. ALL SYSTEMS PUIICTI0IIED II005 TALLY.

REACTOR STARTUP IN PROGRESS.

\\w DATIS DESSE Rill SITE TEAM (tfrDATE) TWE PLANT REMAINS III COLD SMUTDnWN AIID THE INFORMATI0ll ONLY LICENSEE IS COIITINUlIIC THEIR INVESTICATION INTO THE CAUSE OF EQUlPMENT MALPUIICTIONS TNAT (ICCURRED DURINC 5

THE 6/9/95 EVP_NT.

PRELIMINART FINDlIICS RELATING 79 THE 110, 8 MAINPEED PUMP 'Rtr IIIDICATE TNAT A PAILED CARD IN TME CONTROL CIRCUlf MAY MAVE SEP.N 4

o RESPONSIBLE POR TME PEE 3 PUMP TRIP. 1ME LICENSEE ALSO FOLCD TMAT IMPROPER MAINTE2NCE COUPLE 3 tilTM CUMBERSOME PIOCEDUIES MAY MAVE CAUSED THE FAILURE OF VALVES AP599 AND 608.

THE PACT FINDINC TEAM PROM NEADQUARTERS MAS (EFT THE SITE ON SATURDAT AND MAY REfURN NEXT WEEK TU CONTINUE WITM THEIR INVESTICAtl0NN.

t DIVISON OF RADI Atl0M SAFETT AND SAFECUARDS CENERAL MESSRS. M. SCHUMACRER AND S. ROZAR, REPRESENTATIVES INFORMATION OF STATE OF MICMICAN. DOW CMEMICAL AND OAK RIDCE ASSOCI ATED UNIVERSITIES WILL BE REVIEWINC CONTAMINATED SITES IN TME BAT CITY AREA.

MORMINC REPORT - REC 10N IV DATER JUNE 24, 1985 corrected copy b'

LICENSEE /FACILITT NOTIFICATION / SUBJECT DESCRlrfl0N OF ITEM OR EVENT Wolf Creek Telecon Free Rt At 12:43 se. CDT, jene 24, 1985 A reactor trip occurred due to 6/24/85 e 14-1m level condition in otese generator *A*.

The stese generator dat 50-482 Reactor Trip level was being estatetned by a motor delven musillery feedveter pump MQ Duty Officer (MDAFP). When the feedwater teetation velves were opened at oppros-nottfled teately 12:30 AM., The water level in otese generator *A & B" started decreestag resulting in the above reactor tely. Other engineered oefety festeres systees actuated were a feedwater systes toelation and en emettlery feedwater actuation. When the feedveter toolstion occurred, level control of the stese generators wee regelned. A Mt level in the main turbine condenser indicates that the water wee poselbly leeking back free the stese generatore to the condeneer.

The plant wee being started up with shutdown rod banks being with-drawn et the time of the trip. The licensee to evaluating the reactor trip and related evente.

Wolf Creek Telecon free RI At I:28 pe. CUT, on June 23, 1985, e reactor trip occurred. The trip 6/24/85 wee caused by en instrumentation and control technteten operating the Reactor Trip wrong trip evitch on the reacter trip breaker (RTS) "A" panel. The MQ Duty Officer techeleton wee perforetab a survellence on the bypese RTS

  • A* Breaker s

nottfled and inadverently pushed the settch which tripped the RTs "e* 3reaker and the bypees breaker. A meta feedwater tooletion and en auntliery feeduster actuation also occurred due to the reactor trip. The plant wee et 302 power with startup testing in progrese et the tIee of the trip.

MORNINC REPORT - REC 104 V DATE: JUNE 24, 1985 FACILITT NOTIFICAfl0N ITEM OR EVENT RECIONAL ACTION REClON V HAS NO MORNING REPORT FOR 06/24/85.

I tweerevan rnee fx1RRECTED COPY o