ML17228A688

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Forwards Rev 1 to Rept EMF-92-148, St Lucie Unit 1 SBLOCA Analysis & SBLOCA Data Relevant to Review of Util 930319 Proposed License Amend Request to Change RCS Design Flowrate.Requests That NRC Issue Subj Amend by 941115
ML17228A688
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 08/18/1994
From: Sager D
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17228A689 List:
References
L-94-147, NUDOCS 9408260285
Download: ML17228A688 (7)


Text

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CCELERATED RIDE PROCESSING) y REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9408260285 DOC.DATE: 94/08/18 NOTARIZED: YES DOCKET FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power & Light Co. 05000335 AUTH. NAME AUTHOR AFFILIATION SAGER,D.A.

RECIP.NAME Florida Power & Light Co.

RECIPIENT AFFILIATION

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pgp>c=fg-P Document Control Branch (Document Control Desk)

SUBJECT:

Forwards Rev 1 to Rept EMF-92-148, "St Lucie Unit 1 SBLOCA Analysis" & SBLOCA data relevant to review of util 930319 proposed license amend request to change RCS design flowrate.Requests that NRC issue subj amend by 941115. 0' DISTRIBUTION CODE OR AOOID COPIES RECEIVED'LTR Submittal: General Distribution L ENCL + SIZE'ITLE:

NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 NORRIS,J 2 2 INTERNAL: ACRS 6 6 NRR/DE/EELB 1 1 NRR/DORS/ONDD 1 1 NRR/DRCH/HICB 1 1 NRR/DRPW 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OC/aMB 1 0 OGC/HDS3 1 0 G FIL 01 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D C

u NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACTTHE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2083 ) TO ELIMINATEYOUR NAME FROM DISTRIBUTIONLISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 20

August 18, 1994 L-94-147 10 CFR 50.90 U. S. Nuclear Regulatory Coimnission Attn: Document Control Desk Washington, D. C. 20555 RE: St. Lucie Unit 1 Docket No. 50-335 Proposed License Amendment By letter L-93-035, dated March 19, 1993, Florida Power and Light Company (FPL) requested that Facility Operating License DPR-67 for St. Lucie Unit 1 (PSL1) be amended to change the Reactor Coolant System design flowrate. Justification for this request, in part, was contingent upon approval of the analytical methods employed by the fuel vendor to evaluate the PSL1 response to small break loss of coolant accidents (SBLOCA) . The evaluation model was undergoing technical review by the NRC at the time of FPL's request.

Subsequent modifications were made to the evaluation model and. its topical report, and reanalysis of the PSL1 SBLOCA 'response was performed. 1n May, 1994. Consequently, information reported in L-93-035 (part 4-2:2 of Attachment 2, and Enclosure 3) relative to SBLOCAs 1s superseded, and should be disregarded during the staff's review of that FPL submittal.

The enclosed report, "Siemens Power Corporation-Nuclear Division, St. Lucie Unit 1 Small Break LOC'A Analys1s, EMF-92-148, Revision 1, May 1994,n and Attachment 1 to this letter provide the SBLOC'A data relevant to the review of FPL's proposed license amendment. The evaluation of no significant hazards consideration contained. in L-93-035 is not affected by this supplement.

FPL requests that NRC issue the subject amendment by November 15, 1994, to support return of PSL1 to operation following the Fall-94 refuelinq outage. Please contact us about this submittal.

if there are any questions Very truly yours,

<QA8 D. A. ger Vice sident St. Lu ie Plant 240073 oo 9408260285 940818 an FPL Group company PDR ADOCK 05000335 PDR

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St. Lucie Unit 1 L-94-147 Docket 50-335 Page 2 Proposed License Amendment DAS/RLD/kw DAS/PSL g1186-94 Attachment Enclosure cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant.

Mr. W.A. Passetti, Florida Department of Health and Rehabilitative Services.

~ )1 + e I I St. Lucie Unit 1 L-94-147 Docket No. 50-335 Page 3 Proposed License Amendment STATE OF FLORIDA )

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COUNTY OF ST. LUCRE )

D. A. Sager being first duly sworn, deposes and says:

That he is Vice President, St. Lucie Plant for the Nuclear Division of Florida Power R Light Company, the Licensee herein; That he has executed the foregoing document; that the statements made in this document are true and correct to the best of his knowledge, information and belief, and that he is authorized to execute the document on behalf of said Licensee.

.A. ager STATE OF FLORIDA COUNTY OF 5), LU&t The foregoing instrument was acknowledged before me this,F dey of 8 by D.A. ager, who is pers y own to me and who did take an oath.

KAREN W t=-~S Name o Notary a.c Ny Comnission expires 0 N 9g Commission No. CC ~ 79Z k NNEH VILEST i) I hA'OMMISSlON CC859928 BPlRES API8 18,1998 IOIEO THRU TROY YAW INSUMCE, INC.

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St. Lucie Unit 1 L-94-147 Docket No. 50-335 Attachment 1 Proposed License Amendment Page 1 of 1 St. Lucie Unit 1 Reduction of Reactor Coolant S stem Desi n Flow NOTE Section 4-4.2 of FPL Letter L-93-035 (3/19/93), Attachment 2, is superseded by the following data.

Small Break LOCA SBLOCA The SBLOCA was reanalyzed for St. Lucie Unit 1 to evaluate the impact of up to 254 (average) SGTP. The break was assumed to occur in the cold leg piping at the RCP discharge. Conservative system parameters were assumed in conjunction with the proposed design RCS flowrate of 355,000 gpm. Break spectrum calculations and sensitivity calculations were performed as part of the analysis.

Single failure criteria was satisfied by assuming that one emergency diesel generator would fail to operate and thereby cause one high pressure safety injection pump and one auxiliary feedwater pump to be inoperable.

The limiting break size was determined to be 0.1 ft . Sensitivity analyses performed for the limiting break included one to evaluate the impact of a delayed RCP tripping scheme that is consistent with plant Emergency Operating Procedures, and one to evaluate the impact of +74 SGTP asymmetry, e.g., 18% of the tubes plugged in one SG and 324 plugged in the other SG. The results of both studies are bounded by the results of the limiting break calculations.

The maximum PCT achieved in the several SBLOCA cases that were analyzed is 1846 'F. The calculated maximum local cladding oxidation is 2.254 with core wide oxidation less than 1%. The reanalysis demonstrates that acceptance criteria of 10CFR50.46(b) are satisfied for the limiting SBLOCA when considering the effects of 254 (average) SG tube plugging, +74 SGTP asymmetry, and the proposed value of RCS design flow.

The SBLOCA results are based on SPC's small break methodology, as revised by their responses to questions raised during NRC's review of the associated topical report. The maximum time-step utilized is defined in the methodology. The maximum PCT of 1846 'F represents the limiting case (three cases analyzed) of sensitivity calculations performed for the limiting break size to determine adjacent core volume cross-flow sensitivity.

Additional details of the SBLOCA reanalysis, including a summary description of the evaluation models that were employed, are contained in the report enclosed with this document: "Siemens Power Corporation-Nuclear Division, St. Lucie Unit 1, Small Break LOCA Analysis", EMF-92-148, Revision 1; May 1994.