W3P88-1980, Advises That No Change Required for Analysis of Record for Pressure Temp Tech Spec Limits,Per Generic Ltr 88-11 Re Reg Guide 1.99
| ML20195D716 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 11/01/1988 |
| From: | Burski R LOUISIANA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RTR-REGGD-01.099, RTR-REGGD-1.099 GL-88-11, W3P88-1980, NUDOCS 8811070122 | |
| Download: ML20195D716 (2) | |
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LOUISI AN A / 3i7 ernoNNe sister. e.o. sox 6034o POWG R & L1GHT NEW OnLEANS, LOUISIAN A 70160 * (504) $95 3100
$*0$50NA November 1, 1988 W3P88-1980 A4.05 QA U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555
SUBJECT:
Waterford 3 SES Docket No. 50-382 License No NPF-38 Generic Letter 88-11 4
REFERENCE:
LP&L Letter W3P86-0251, dated February 20, 1986 On July 12, 1988, the NRC issued Generic Letter 88-11 which apprised Licensees of the NRC's intent to use Regulatory Guide 1.99, Revision 2, in j
reviewing submittals regarding pressure-temperature limits and for analyses of the embrittlement of reactor vessel belt line materials.
LP&L has applied l
l the methodology of Regulatory Guide 1.99, Revision 2, and LP&L has concluded I
there is no change required for the analysis of record for Waterford 3 for the pressure-temperature technical specification limits, 10 CFR Part 50, l
Appendix G, estimate of embrittlement, or pressurized thermal shock,10 CFR 50.61.
The reactor vessel belt line consists of six plates and three weld materials, reference FSAR Table 5.3-13.
The material which resulted in the maximum calculated value of the adjusted reference temperature was plate M-1004-2.
An adjusted ref rence temperature of 88'F was calculated using the methodo-logy of Regulatory Guide 1.99, Revision 2, for plate M-1004-2.
The temperature and pressure limits in technical specification 3.4.8.1 for heatup and cooldown, reference figures 3.4-2 and 3.4-3, were based on an adjusted reference temperatare of 97'F, reference FSAR section 5.3.2.1.
Thus, the temperature and pressure limits in technical specification 3.4.8.1 are limiting since a higher value of the adjusted reference temperature hpflo701228S1101 p
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W3P88-1980 was used in the development of the pressure temperature limits. Also, the Low-Temperature Overpressure Protection (LTOP) setpoints and enable tempera-tures do not have to be revised since the pressure temperature limits do not have to be revised.
The adjusted reference temperature of 88'F, calculated using the methodology of Regulatory Guide 1.99, Revision 2, also satisfies the acreening criterion of 270*F for the evaluation of Pressurized Thermal Shock (PTS) pursuant to 10CFR 10 CFR 50.61.
The adjusted reference temperature of record for Waterford 3 for PTS is 85'F, see referenced letter. The analysis of record for the PTS Rule, see referenced letter, is therefore not affected by Regu-latory Guide 1.99, Revision 2.
Please contact me or Robert J. Murillo should there be any questions concerning thir letter.
GV,1..s R. F. Burski Nuclear Safety and Regulatory Affairs Manager RFB/RJM/jk1 cc E.L. Blake, W.H. Stevenson, J.A. Calvo, D.L. Wigginton, R.D. Martin, NRC Resident Inspector's Office (W3) l NS90072E
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