L-95-155, Forwards Rept of Increase in Peak Clad Temp of 146 F for SBLOCA Analysis,As Identified in Westinghouse to FPL
| ML17352B190 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point |
| Issue date: | 06/07/1995 |
| From: | Plunkett T FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| L-95-155, NUDOCS 9506130290 | |
| Download: ML17352B190 (6) | |
Text
PRIQRITY ACCELERATED RIDS PROCESSING REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9506130290 DOC.DATE: 95/06/07 NOTARIZED: NO DOCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH.NAME AUTHOR AFFILIATION PLUNKETT,T.F.
Florida Power 6 Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards rept of increase in peak clad temp of 146 F for SBLOCA analysis, as identified in Westinghouse 950519 ltr to FPL.
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TITLE: OR Submittal:
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1 NOTE TO ALL"RIDS" RECIPIENTS:
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JUNO'99g L-95-155 10 CFR 50.46 U.
S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C.
20555 Re:
Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems in Li ht Water Power Reactors" Title 10 CFR 50.46 (a)(3)(ii) requires that licensees report to the Commission each change to, or error discovered in, an acceptable emergency core cooling system (ECCS) evaluation model, or in the application of such model, that affects the peak clad temperature calculation, and its effect on the limiting ECCS analysis.
If the change results in a peak clad temperature (PCT) difference of more than 50'F, the licensee is required to provide the NRC with a report within 30 days and include with the report the actions required to show compliance with 10 CFR 50.46 requirements.
By letter L-94-301, dated December 15, 1994, Florida Power and Light Company (FPL) transmitted to the NRC the annual report of the ECCS analysis for Turkey Point Units 3 and 4.
On May 19,
- 1995, Westinghouse transmitted to FPL the results of a recent reanalysis of the worst case large and small break Loss of Coolant Accident (LOCA) transients for Turkey Point.
The Westinghouse letter identified an increase in the PCT of 146'F for the small break LOCA (SBLOCA) analysis.
There is no change in the PCT for the lazge break LOCA (LBLOCA).
While the Turkey Point LBLOCA analysis remains the limiting ECCS analysis, the change in the PCT for the SBLOCA results exceeds 50'F, and although not required by the regulations, FPL is providing the attached report for your information.,
Should there be any questions, please contact us.
Very truly yours,
'///
T
~
F
~ Plunkett Vice President Turkey Point Plant OIH Attachment cc:
S.
D. Ebneter, Regional Administrator, Region II, USNRC T. P.
- Johnson, Sz.
Resident Inspector, USNRC, Turkey Point Plant 950bi302rit0 950b07 PDR ADQCK 05000250 P
~'
L-95-155 Attachment Page 1 of 3 ATTACHMENT Re:
Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 10 CFR 50.46, "Acceptance Criteria for Emergency Coze Coolin S stems In Li ht Water Nuclear Power Reactors" Small Break LOCA SBLOCA By letter L-94-301, Florida Power and Light Company (FPL) reported a
peak clad temperature (PCT) of 1817'F for the worst case SBLOCA transient analysis.
This value was based upon a Turkey Point SBLOCA analysis performed by Westinghouse in 1991 using the NOTRUMP digital computer code.
This value included a calculated PCT of 1749'F plus a 62'F benefit as reported by FPL in letter L-94-073, and a 130'F penalty as reported by FPL in letter L-94-301.
Due to incorrect entries for the cold leg and accumulator line diameters in the Input Modification Program (IMP) database, an increase in the PCT for the worst case SBLOCA of 106'F has been identified.
Since the burst and blockage/time in life effect is a function of the base PCT, the burst and blockage/time in life effect has increased from 15'F to 55'F.
The net change in PCT foz the worst case SBLOCA is 146'F for a total PCT of 1963'F.
Lar e Break LOCA LBLOCA By letter L-94-301 dated December 15,
- 1994, FPL zepozted a
PCT of 2086'F for the worst case LBLOCA tzansient analysis.
This value included a calculated PCT of 2082'F plus a 16'F penalty as reported by FPL in letter L-94-073, and a 12'F benefit as reported by FPL in letter L-94-301.
The LBLOCA analysis as described in the Updated Final Safety Analysis Report (UFSAR) was performed by Westinghouse in 1991 using the BART computer code assuming the presence of fuel assembly spacez gzids.
The LBLOCA analysis does not use the IMP database, therefore, the IMP database errors do not affect the results of the LBLOCA analysis.
~Summa r The revised peak clad temperatures of 2086'F for the worst case LBLOCA and 1968'F for the worst case SBLOCA, correcting foz the effects discussed above and summarized in the enclosed Tables 1 and 2, are below the 10 CFR 50.46 acceptance limit of 2200'F.
Turkey Point Units 3 and 4 remain in compliance with the Emergency Core Cooling System (ECCS) performance criteria specified in 10 CFR 50 '6(b).
L-95-155 Attachment Page 2 of 3 TABLE 1 TURKEY POINT UNITS 3 AND 4 PREDICTED PEAK CLAD TEMPERATURES CURRENT LBLOCA EVALUATIONS THAT HAVE ASSESSED PCT PENALTIES Analysis of Record Total LBLOCA PCT specified in FPL Letter L-94-301 2082 F 2086'F Evaluations since issuance of FPL letter L-94-301 None Total Estimated LBLOCA PCT 2086'F
L-95-155 Attachment Page 3 of 3 TABLE 2 TURKEY POINT UNITS 3 AND 4
PREDICTED PEAK CLAD TEMPERATURES CURRENT SBLOCA EVALUATIONS THAT HAVE ASSESSED PCT PENALTIES Analysis of Record Total SBZOCA PCT specified in PPL Letter L-94-301 174 9oF 1817'F Evaluations since issuance of FPL letter L-94-301 IMP Database Error Correction Burst and Blockage/Time in Life hPCT*
1P 6oF 4 0oF Total Estimated SBLOCA PCT 1963'F Burst and Blockage/Time in Life margin allocation specified in L-94-301,
+15'F
- Current SBLOCA evaluation Burst and Blockage/Time in Life margin allocation,
+55'F