L-83-521, Forwards Rev 5 to Recovery Plan Listing post-core Support Barrel Approximate Repair Flushing Time.Remaining Info Submittal Dates Listed.Thermal Shield Failure Analysis Will Be Submitted by 831027
| ML17214A508 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 10/13/1983 |
| From: | Williams J FLORIDA POWER & LIGHT CO. |
| To: | John Miller Office of Nuclear Reactor Regulation |
| References | |
| L-83-521, NUDOCS 8310180254 | |
| Download: ML17214A508 (7) | |
Text
REGULATOR FORMATION DISTRIBUTION S EM (RIDS)
ACCEW)jSION NBR98310180250 DOC ~ DATE: 83/10/13 NOTARIZED:
NO FAOIL:50 335 St+ Lucie Plantr. Uni~t 1i Flor ida Power 5 Light Co, AUTH,NAME AUTHOR AFFILIATION I')ILLIAMSgJ<N, Flor idp Power L Light Co, RECIP,NAME RECIPIENT AFFILIATION MILLER'
~ Ri Operating Reactors Branch 3
SUBJECTS Forwards Rev 5 to recovery plan listing,post core Isupport barrel approximate repair flushing time, Remaining info submittal dates listed, Thermal shield failure *analysis will be "submitted by 831027 DISTRIBUTION COOS:
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BOX 14000, JUNO BEACH, FL,33408 FLORIDAPOWER & LIGHTCOMPANY October l3, 1983 L-83-52l Office of Nuclear Reactor Regulation Attention:
Mr. James R. Miller, Chief Operating Reactors Branch jj3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Miller:
RE:
St. Lucie Unit I
Docket No. 50-335 Reactor Vessel Internals and Thermal Shield; Plant Recover Pro ram - Recover Plan Revision In our letter of October 6, l983, (L-83-509) contingencies affecting the date for return to power of St. Lucie I, were stated to be attributable to factors, the duration and/or occurrence of which were unknown at that time.
Since the date of the above letter, post-Core Support Barrel (CSB) repair flushing time has been roughly approximated.
That period of time has been incorporated into a revised St. Lucie I Recovery Plan.
Revision 5 of that Recovery Plan is enclosed.
Remaining information submittal
- dates, updating our letter of October 6, 1983, (L-83-509) and the tentative dates of your letter of April 26, 1983, are as follows:
Items (Desi nation from our A ril l9 letter L-83-230)
B.
Thermal Shield Failure Analysis D(5)
Integrity and Stability of Internals D(6)
Conclusions and Findings Tentative Submittal October 27, I 983 December l5, l983 December I5, I 983 831Qi80254 8320iS
)
,PPR I ~~QC~0~000~~5 PEOPLE... SERVING PEOPLE
Page 2 Office of Nuclear Reactor Regulation Mr. James R. Miller,Chief Although the aforementioned Thermal Shield Failure Analyses (Item B. of our L-83-230) will now be provided on or before October 27, l983, every effort will be made to transmit this report well before that time, in order that NRC internal review may be adequate to support a Florida Power & Light presentation of this area on November 8, I 983.
Should any questions arise, please contact us immediately.
Very truly yours, J. W. Williams, Jr.
Vice President Nuclear Energy J WW/DAC/jk Enclosure cc:
Harold F. Reis, Esquire
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ST. LUCIE 1 PLANT RECOVERY PLAN
( REvlsIDH s)
FAILURE ANALYSIS t REMOVE DEBRIS FROM REACTOR VESSEL METALLURGICALANAL PREPARE FAILURE ANALYSIS REPORT TO HRC 10-27 ISI OF REACTOR VESSEL REMOVE CSB FROll VESSEL 5 26 THERMALSHIELD PREP METHODS 8 MOSUZE AT SITE 5-12 7 25 CORE SUPPORT BARREL PREPARE REPNR METHODS 8 SNHULIZE AT SITE REPASI CSS 8 SET 51 REACTOR VEBSEL RELOAD RKL 8-17 IKETNQ WITH 15IC OH FALURE MECHA15SM ANALYSISRESILTS LKETNO WITH ISIC OH PROPOSEO F51AL REPORT CONTENT 2-7 2-15 PREP FOR START~
SAFETY ASSESSMENT FINALEXXOH RELOAD SIXIMITTAL CONTVIUOUS ASSESSMENT 5 15IC REVIEW 7 27 POST~ REMOVALFNAL IIE 5ISPECTION RESIA.TS~
425 53 PRESSURE/TEMPERATURE OPERATVIG CURVE
- CCEPTABLITYREVKW TO NRC 4 I 4-12 15IC MEETSIQ-PRELISNNARY ASSESSMENT+
NRC MEETSIQ RECOVERY PLAHIPTS CONSIDERATIONS 5-3 MEETVIG WITH NRC~
ONLPMS 8 EXCORE DETECTOR DATA REVIEW EXXON RELOAD 5 GAMMAHEATSIG SUBMITTALTO NRC 8-23 8-18 MEETING WITH NRC~
ON THERMAL SHIELD ANO RV DITERNALS INSPECTION RESULTS, REPASL AND ANALYSIS 8-20 5 22 11 5 12-15 3 6 MEETVIG WITH NRC ON 5ITEGRITY~
5 STABILITYOF RV BITERNALS; POST-MACI5NING FINAL NDE INSPECTION RESULTS CQ ~ssvraais TI
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