W3P86-0012, Revises ,Correcting Typos.Discusses Projected Ref Temp Pressurized Thermal Shock (PTS) Value for Reactor Vessel,Per Fracture Toughness Requirements for Protection Against PTS Events
| ML20141G025 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 02/20/1986 |
| From: | Cook K LOUISIANA POWER & LIGHT CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20141F977 | List:
|
| References | |
| REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR W3P86-0012, W3P86-12, NUDOCS 8602260143 | |
| Download: ML20141G025 (2) | |
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LOUISIANA 242 De - o~Oeeraser . a eOx e00.
2 O W E R & L I G H T ! NEW OALeANS70174-6000 LousSIANA9 (504)366-2345 F#ualava February 20, 1986 W3P86-0012 (Revised) A4.05 QA George W. Knighton, Director PWR Project Directorate No. 7 Division of PWR Licensing-B Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Knighton:
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Projected Value of RT g In accordance with 10CFR50.61, " Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events," Louisiana Power and Light Company herewith submits the projected value of RT #
- PTS Waterford 3 reactor vessel.
Calculations were performed using the equations of 10CFR50.61(b)(2) and are presented in Enclosure 1. An Initial Reference Temperature of 22*F was used. ThistemperaturewasdeterminedbytestswgcharediscussedinFSAR Subsection 5.3.2.1. A maximum fluence of 3.68x10 nyt (E > 1 Mev) was i used. This value was determined by tests described in FSAR 5.3.1.4 and envelopes planned core loading patterns. The calculations depicted in Enclosure 1 represent the limiting conditions which result in the maximum RT value. The reactor vessel chemical composition presented in Enclosure 2 was used.
The calculation resulted in an RT of 85'F which is below the 270*F screeningcriteriaofthePressur$NdThermalShockfinalrule. 1 Very truly yours, 8602260143 860220 DR ADOCK 050 2 [ . [s gy J g K.W. Cook M -
,f7 Nuclear Support & Licensing Manager KWC: RAS:sms cc: R.D. Martin, NRC Region IV l J.H. Wilson, NRC-NRR l NRC Resident Inspectors Office B.W. Churchill W.M. Stevenson
.v Enclosure 1 to W3P86-0012 Adjusted Reference Temperature Calculation for Screening Criteria Used in PTS Ruling Equation 1:
RT = I + M + [-10 + 470 Cu + 350 CuNi] f* (270*F from CEN -189 Appendix I (Enclosure 2)
I = Initial RT = 22*F N
For Plate M-1004-2 19 2 f = fluence = 3.68 (10 6) 1 M = 48'F margin added per final rule
. RT = 22 + 48 + [-10 + 470 x .0'l + 350 x .03 x .58] 3.68 27
. l
= 22 + 48 + [-10 + 14.1 + 6.09] 1.4216
= 22 + 48 + [10.19] 1.4216
= 22 + 48 + 14.49
= 85'F < 270*F Equation 2 gives higher value hence it is not applicable.
t L