ML17213B359

From kanterella
Jump to navigation Jump to search
Summary of 830425 Meeting W/Util & C-E in Bethesda,Md Re Schedule for Resolution of Thermal Shield Damage.Thermal Shield Chronological Sequence Encl
ML17213B359
Person / Time
Site: Saint Lucie 
Issue date: 05/03/1983
From: Sells D
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8305120499
Download: ML17213B359 (10)


Text

MAY 3

1983 5V-W~>

LICEHSEE:

Florida Power and Light Company FACILITY: St. Lucie Plant, Unit No.

1 pQs A>-~!4

SUBJECT:

MEETING SUNINRY - SCHEDULE FOR RESOLUTION OF THE THERMAL SHIEQD DAINGE On April 25, 1983 a meeting was held in Bethesda, ND with Florida Power and Light Company (FPSL) to discuss the FPEL schedule for resolution of the thermal shield damage at St. Lucie Plant, Unit No. 1.

A list of attendees is attached.

The proposed submittal dates for the commitmentsmade by FPSL in its April 19, 1983 lettev (L-83-230).'are contained in the staff letter from R. A. Clark to R. Uhrig (attached).

The significant date is the submittal of FPEL's con-clusions. ahd findings on July 2, 1983 that will reqnire staff review and concurrence, Since refueling and restart pvepavations are scheduled to occur at the same time, the staff will be asked to expedite this review and con-currence.

The sequence of events cal.ls for the removal of the thermal shield by cutting it around the support lugs leaving a minimum of 2" of material around ques-tionable areas of damage, then cutting the thermal shield itself into 120o segments that will be further cut up for disposal after they are removed from the cove support barrel.

After examination with ultvaeonic and eddy current equipment of the support lugs and core suppor t barrel the lugs will be cut away and machined and the core suppovt barrel will be repaired and returned to t4e reactor pressure vessel.

In alii cutting operations, pla~I,es will be used to pvotect the core suppovt barrel.

RIE'fueling of the reactor is scheduled fo be completed in early July.

FPKL intends to pet'form a full insevvice inspection during this outage.

A request fov relief from Technical Specificationsrequivements is being sent to the staff.

The surveillance capsule that is being rettaved and analyzed (see meeting sumary for April 25 afternoon meeting) will be replaced with instrumentation to monitor fluence during future operations.

FPRL has conducted.a 10 CFR 50.59 evaluation and a Technical Specification review with negative findings to date.

Although the failure analysis is not scheduled to be completed until September

1983, FPRL indicated 'i desire to complete this analysis sooner (See attached Figure).

8305120499 830503 PDR ADOCK 05000335 P

PDR..

OFFICEI SURNAME$

DATE II NRG FORM 318 (10.80) NRCM 0240

~ ~

~ ~ 00 ~ 0 ~ 0 ~ 0 ~ 0 ~ 0 ~

\\

~ ~ ~

~ ~ ~ ~ Oiiggy ~ 0

~

~

~ ~ ~ ~ 0 ~

~

~

0 ~ 0 ~ ~ ~ ~ ~ ~ 0 ~

~ ~ ~ ~ 0 ~i~ ~ 0 ~ 0 ~ ~ 0 ~ ~ ~ 0 ~ ~ 0 ~ ~

OFFICIAL RECORD COPY USGPO: 1981~960

e<

a+

y 'I

d. a S

t

w FP&L, in response to earlier questions regarding the sequence of events, provided a chronological sequence that is attached to this summary.

Attachments:

As stated cc:

See next page Original sipped ~

Donald E. Sells, Prospect Manager Operating Reactors Branch 83 Division 'of Licensing OFFICE 1 SURNAME/

088P~PJj~

CATE 5 5!0.!%3.....

NRC FORM 318 u 0-80) NRCM 0240 0.

D ieP ao ~ ~ ~ ~

pn 5g/J83

. :.AL.......

~ ~

~

ark

~ 0 ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ I~ 0 ~ 0 ~ ~

5/

/83 FFICIAL RECORD COPY USQPO: 1081~5.960

~

g J

wp l

lt

~ 4

MEETING

SUMMARY

OISTRIBUTION Licensee:

Florida Power 5 Light Company

  • Copies also sent to those people on service (cc) list for subject plant(s).

Oocket File

. NRC POR L

POR NSIC OR883 Rdg ORB&3 Summary File JHeltemes BGrimes RAClark Project Manager PMKreutzer OQ.D ELJordan JMTaylor ACRS-10 NRC Participants

Florida Power 8 Light Company

~ ~

CC:

Harold F. Reis, Esquire Lowenstein,

Newman, Reis 8 Alexrad 1025 Connecticut
Avenue, N.W.

Washington, D. C.

20036 Norman A. Coll, Esquire McCarthy, Steel, Hector 8 Davis 14th Floor, First National Bank Building Miami Florida 33131 Mr. Jack Schreve Office of the Public Counsel Room 4, Holland Building Tal 1ahassee, Fl orida 32304 Resident Inspector c/o U.S.N.R.C.

7900 S.

A1A Jensen Beach, Florida 33457 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Mr. Weldon B. Lewis County Administrator St. Lucie County 2300 Virginia Avenue, Room 104 Fort Pierce, Florida 33450 U.S. Environmental Protection Agency Region IV Office ATTN:

Regional Radiation Representative 345 Courtland Street, N.E.

Atlanta, Georgia 30308 Mr. Charles B. Brinkman Manager - Washington Nuclear Operations C-E Power Systems Combustion Engineering, Inc.

7910 Woodmont Avenue

Bethesda, Maryland 20814 State Planning and Develpment Clearinghouse Office of Planning and Budgeting Executive Office of the Governor The Capitol Building Tallahassee, Florida 32301 Regional Administrator Nuclear Regulatory Commission, Region II Office of Executive Director for Operations 101 Marietta Street; Suite 3100 Atlanta, Georgia 30303

Attachment LIST OF ATTENDEES THERMAL SHIELD RECOVERY SCHEDULE MEETING APRIL 25, 1983 NRC R. Clark D. Sells FP&L D. Chancy T. Dillard T. Vogan J. Krumins CE T. Gates S. Ritterbusch

H ST. LUCIE 0 PLANT RECOVERY PLAN I4t22i63)

FAILURE ANALYSIS t REMOVE DEBRIS FROhl REACTOR " SSEL METALLURGICALANAL PREPARE FAILURE ANALYSIS 9-16 ISI OF REACTOR VESSEL 4-14 REMOVE CSD FROM VESSEL 6-12 THERMALSHIELD PREP METHODS 6 MOSII.IZE AT SITE 4-4 6-6 REMOVE TIIERMAI. SHIELD FROM CSB 6-16 CORE SUPPORT BARREL PREPARE REPAIR METHODS 6 MOBILIZEAT SITE REPAIR CSB II SET IN REACTOR VESSEI.

5-15 RELOAD FUEL FUEL FUEL REMOVED FROM CONTAINI4EtlT PREP FOR START-UP PLAtlT Otl LBIE 6-12 6-19 SAFETY ASSESSMENT 4-1 CONTIIIUOUS ASSESSMEtlT 6 NRC REVIEW T-I0

~

~I

~'

1

~ 11 '1%I ~

1 G

I H

FLORIDA PO'IVER & LIGHTCOMPANY PSL 1

THERMAL SHIELD CHRONOLOGICAL SE UENCE 2/ 2/78 2/

/78 6/ 1/78 3/31/79 6/ 8/79 3/15/80 Initial Loose Parts Monitor (LPM) indication Initial CE investigation of LPM Start

) Cycl e 2

End

)

Start

) Cycle 3

End

)

4/

/80 CE/TEC investigation of LPM 5/10/80 9/11/81 12/ 2/81 2/26/83 Start

) Cycl e 4

End

)

Start

) Cycle 5

End

)

9/

/82 CE - Begin continuous LPM surveillance 3/21/83 Begin Fuel Shuffle 3/24/83 First chunks of debris were seen 3/29/83 Begin off-1 oad of 1/2 of core 3/31/83 Begin ful 1 off-1oad 4/ 1/83 Complete fuel off-1 oad 4/ 4/83 Remove Core Barrel from Reactor Vessel 4/14/83 Al 1 loose parts removed from Reactor Vessel lower head oamos e SERVING PEOPLE

io