ML18010B145
| ML18010B145 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 07/23/1993 |
| From: | Mccarthy D CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| HO-930128, NUDOCS 9308040084 | |
| Download: ML18010B145 (8) | |
Text
~~ACCELERAT 9 DOCUMENT DISTR BUTION SYSTEM REGULA INFORMATION DISTRIBUTIO YSTEM (RIDS)
ACCESSION NBR:9308040084 DOC.DATE: 93/07/23 NOTARIZED:
NO'ACIL,:$
0-"400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTA.NAME AUTHOR AFFILIATION MCCARTHY,D.C.
Carolina Power !'ight Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards annual rept providing margin Utilization Tables that show effects of permanent assessment of PCT margin for various issues for large !!'mall break LOCA analyses of records, for period of June 1992 to May 1993,per 10CFR50.46.
DISTRIBUTION CODE:
A001D COPIES RECEIVED:LTR ENCL
" SIZE:
TITLE: OR Submittal: General Distribution NOTES:Application for permit renewal filed.
DOCKET 05000400 05000400 RECIPIENT ID CODE/NAME PD2-1 LA LE,N INTERNAL: ACRS NRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS1 EXTERNAL: NRC PDR COPIES LTTR ENCL
'1 1'
2 6
6 1
1 1
1 1
1 1
0 1
1 RECIPIENT ID CODE/NAME PD2-1 PD NRR/DE/EELB NRR/DRPW/OTSB NRR/DSSA/SRXB OC/~C REG FILE Ol NSIC COPIES LTTR ENCL 1
1 1
1 NOTE TO ALL"RIDS" RECIPIENTS PLEASE HELP US TO REDUCE WASTE! CONTACT TFIE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-20GS) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 21 'NCL 19
0 0
@ME Carolina Power &LightCompany JuL 33 1993 SERIAL:
HNP-93-827 10 CFR 50.46 Letter Number:
HO-930128 United States Nuclear Regulatory Commission ATTENTION:
Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 EMERGENCY CORE COOLING SYSTEM EVALUATION MODEL CHANGES Gentlemen:
The purpose of this letter is to provide the annual report pursuant to 10 CFR 50.46(a)(3)(ii) for the Shearon Harris Nuclear Power Plant (SHNPP) regarding the estimated effect of changes or errors in Emergency Core Cooling System (ECCS) evaluation models or in the application of the models.
This report covers the period of June 1992 through May 1993.
The enclosures to this letter provide the Margin Utilization Tables which show the effects of permanent assessment of Peak Cladding Temperature (PCT) margin for various issues for the Large and Small Break Loss of Coolant Accident (LOCA) analyses of record.
The Small Break LOCA Peak Cladding Temperature provided herein is identical to that provided in CPGL's August 26, 1992 supplement to the last annual report dated July 23, 1992.
The Large Break LOCA Peak Cladding Temperature provided herein decreased approximately 19'F due to the combined effects of use of greater Temperature-Pressure uncertainties and changes in Structural Metal Heat Modeling.
The Margin Utilization Tables also include a
listing of current open issues which are being investigated, but for which no conclusions have yet been reached.
If any of the issues result in a significant change in the calculated
- PCT, as defined by 10 CFR 50.46, they will be report'ed to the NRC in accordance with the 30-day reporting requirement.
Ii As stated in our previous letters, CPSL plans to reanalyze both the Large and Small Break LOCA events prior to Cycle 6 for SHNPP, to coincide with a change in nuclear fuel vendors.
Accordingly, these analyses of record will be approved and in place to support Refueling Outage No. 5, currently scheduled to begin in March 1994.
Questions regarding this matter may be referred to Mr. L. S. Rowell at (919) 362-2287.
Yours very trul 8c D.
C. McCarthy Manager Regulatory Affairs SDC/sdc
Enclosures:
cc:
Mr. S.
D. Ebneter
, Mr. N. B. Le Mr. J.
E. Tedrow 9SOSOOOose,9S0723 PDR ADOCK '05000400
,.. ~PDg.
't
Re ortin of 10CFR50.46 Mar in Utilization Small-Break LOCA Plant Name:
Shearon Harris Unit 1 UtilityName:
Carolina Power
& Light Company Anal sis of Record Vantage 5 Reload Transition Safety Report, February 1989 Evaluation Model:
- NOTRUMP, FQT 2.50, FAH 1.65 SGTP - 6S, Other:
Vantage 5
PCT 1779.8'F B..
Prior LOCA Model Assessments
- 1991 (Permanent Assessment of PCT Margin - Letter ¹: CQL-91-035)
- 1. Fuel Rod Initial Condition Inconsistency 2.
NOTRUMP Solution Convergence Reliability 3.
SBLOCA Cladding Creep Model 4.
SBLOCA Rod Internal Pressure Assumption APCT
+ 37
'F APCT
+
0
'F APCT
+ 20
'F APCT
+ 33.3'F Prior LOCA Model Assessments
- 1992 (Permanent Assessment of PCT Margin - Letter ¹: NLS-92-231)
- 1. Issue: Axial offset Margin Utilization (30%
- 25%)
- 2. Issue:
Increased Pressurizer and RCS Temperature Uncertainties APCT 75
'F APCT
+ 17.2'F D.
10CFR50.59 Safet Evaluations Permanent Assessment of PCT Mar in
- l. Issue:
AFW Enthalpy Delay Time Increase Letter:
CQL-90-535
- 2. Issue:
ECCS Flow Shortfall Evaluation Letter:
90CP*-G-0080 and CQL-90-573 APCT
+ 36
'F APCT
+ 75
'F Current LOCA Model Assessments (Permanent Assessment of PCT Margin - Letter ¹: CQL-93-201)
- 1. Issue: Auxiliary Feedwater Flow Table Error
- 2. Issue:
Steam Gen.
Secondary Side Modeling Enhancements APCT 0
'F APCT 0
'F F.
Current Permanent PCT PCT 1923.3'F G.
Current LOCA Model Issues No PCT Assessments Made'till Under Investi ation Reference Letter ¹: CQL-93-201)
- 1. Limiting Time in Life for Small Break LOCA 2
~ Basis Change for Hot Assembly Rod Gap Pressure
1
Re ortin of 10CFR50.46 Mar in Utilization Lar e-Break LOCA Plant Name:
Utility Name:
Shearon Harris Unit 1 Carolina Power
& Light Company Anal sis of Record Vantage 5 Reload Transition Safety Report, February 1989 Evaluation Model: 1981 With BASH, FQT - 2.45, FAH - 1.65 SGTP 6%, Other:
Vantage 5
Fuel Margins Used: Transition Core Penalty PCT 2105.2'F APCT
+ 50
'F B.
Prior LOCA Model Assessments
- 1991 (Permanent Assessment of PCT Margin - Letter ¹: CQL-91-035) 1
~ Fuel Rod Initial Condition Inconsistency 2.
LBLOCA Burst and Blockage Assumption 3.
Steam Generator Tube Seismi.c/LOCA Assumption~
APCT
+ 10
'F APCT
+
0 F
APCT
+
0
'F C.
10CFR50.59 Safet Evaluations Permanent Assessment of PCT Mar in Issue:
SI Delay Time Increase Letter:
CQL-90-573 and 90CP<-G-0080 APCT
+
4
'F D.
1992 LOCA Model Assessments (Permanent Assessment of PCT Margin - Letter ¹: CQL-03-201)
- 1. Temperature and Pressure Uncertainties
- 2. Structural Metal Heat Modeling APCT
+
6.3'F APCT 25
'F E.
Current Permanent PCT PCT 2150.5'F F.
Current LOCA Model Issues No PCT Assessments Made'till Under Investi ation 1.
Steam Generator Tube Collapse Under Combined LOCA/Seismic Loads (partial through-wall cracking)
(Reference letter ¹: CQL-92-025, dated June 25, 1992) 2.
Power Shape Sensitivity Model (PSSM)
(Reference letter ¹: CQL-93-201)
- 3. Spacer Grid Heat Transfer Error in BART (Reference letter ¹: CQL-93-201) 4.
Rod Internal Pressure Uncertainty (Reference letter ¹: CQL-93-201) 1.8'percent steam generator tube plugging margin was assessed to account for possible steam generator tube collapse in the event of a seismic event coincident with a LOCA.
Note that this issue accounted for only full through-wall cracking.
-~w; ~