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: Difference between revisions
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LOUISIANA | LOUISIANA 2 O W E R & L I G H T ! NEW OALeANS LousSIANA 242 De - o~Oeeraser. | ||
2 O W E R & L I G H T ! NEW | a eOx e00. | ||
70174-6000 9 (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:== | ==Dear Mr. Knighton:== | ||
==Subject:== | ==Subject:== | ||
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Projected Value of RT | 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 | Calculations were performed using the equations of 10CFR50.61(b)(2) and are presented in Enclosure 1. | ||
The calculation resulted in an RT | 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 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 | |||
[. [s gy g | |||
DR ADOCK 050 2 | |||
J M | |||
K.W. Cook | |||
,f7 Nuclear Support & Licensing Manager KWC: RAS:sms cc: | |||
R.D. Martin, NRC Region IV l | |||
J.H. Wilson, NRC-NRR NRC Resident Inspectors Office B.W. Churchill W.M. Stevenson | |||
.v 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* | RT = I + M + [-10 + 470 Cu + 350 CuNi] f* | ||
I = Initial RT = 22*F | (270*F from CEN -189 Appendix I (Enclosure 2) | ||
For Plate M-1004-2 19 | I = Initial RT = 22*F For Plate M-1004-2 N | ||
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}} | t L}} | ||
Latest revision as of 15:08, 11 December 2024
| 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) | |
Text
v 9
LOUISIANA 2 O W E R & L I G H T ! NEW OALeANS LousSIANA 242 De - o~Oeeraser.
a eOx e00.
70174-6000 9 (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 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
[. [s gy g
DR ADOCK 050 2
J M
K.W. Cook
,f7 Nuclear Support & Licensing Manager KWC: RAS:sms cc:
R.D. Martin, NRC Region IV l
J.H. Wilson, NRC-NRR NRC Resident Inspectors Office B.W. Churchill W.M. Stevenson
.v 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 For Plate M-1004-2 N
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