ML18095A951

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Suppls 900810 Response to Request for Addl Info Re Transient Temps at End of Operating Life.Encl Tables 1 & 2 of Reactor Vessel Fluence Rept for PTS Revised
ML18095A951
Person / Time
Site: Salem  PSEG icon.png
Issue date: 05/22/1991
From: Labruna S
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLR-N91088, NUDOCS 9105310189
Download: ML18095A951 (4)


Text

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Public Service Electric and Gas Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 w*

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Vice President - Nuclear Operations NLR-N91088 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

SUPPLEMENTAL INFORMATION SALEM GENERATING STATIONS UNITS ~/ANJ? ~2 1elii1 FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 Public Service Electric and Gas (PSE&G) submitted the, "Response to Request for Additional Information" on August 10, 1990, in response to your letter dated April 10, 1990.

Based on discussions with Mr. Stephen Dembek, NRR Project Manager for Hope Creek Generating Station, PSE&G is revising Tables 1 and 2 (Item 3) of Attachment 2 of the~Aµ~u~~~~o, 1990, letter to reflect the transition temperatures of the vessel at the end of the operating license.

These numbers have been calculated as of the last vessel fluence update of March 1990, and are in accordance with Regulatory Gµ*ide

  • 1.99 Revision 2.

A correction has also been made to a typographical error in Item 3 of Table 1, concerning the vessel EFPY for the End of Operating License for Salem Unit 1. provides the revised Table 1 for Salem Unit 1 and Attachment 2 provides the revised Table 2 for Salem Unit 2.

Should you have any questions reg~ft-1\\ii'.h~ li!his transmittal, please do not hesitate to contact us.

Sincerely, Attachments

Document Control Desk NLR-N91088 C

Mr. J. C. Stone Licensing Project Manager Mr. T. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief 2

New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 J*,

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ATTACHMENT 1 TO NLR-N91088 TABLE 1 SALEM UNIT 1 REACTOR VESSEL FLUENCE REPORT FOR PRESSURIZED THERMAL SHOCK MARCH 1990 (Limiting Plate B2402-1)

ORIGINAL REPORT CURRENT FUTURE ESTIMATES NRC RULING CURRENT VESSEL STATUS Date 1/23/1986 3/31/1990 Fluence (xE19 n/cm2) 0.3900 0.4648 Vessel Age (EFPY) 4.67 7.65 FSAR PLANT DESIGN END-OF-LIFE Date 1/23/2018 4/30/2018 Fluence (xE19 n/cm2)

1. 91 1.52 Vessel Age (EFP:Y)
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32 END OF OPERATING LICENSE (No extension)

Date 9/25/2008 9/25/2008 Fluence (xE19 n/cm2) 1.48 1.15 Vessel Age (EFPY) 85% Avail 24.3 18.4 Adjusted Reference Temp(°F) 245.7 END OF VESSEL LIFE (When screening criteria is met)

Date, 85% Avail 1/1/2020 8/15/2031 9/1/2028 Fluence (xE19 n/cm2) 2.00 2.00

1. 96 Vessel Age (EFPY) 33.6 43.0 40.5
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ATTACHMENT 2 TO NLR-N91088 TABLE 2 SALEM UNIT 2 REACTOR VESSEL FLUENCE REPORT FOR PRESSURIZED THERMAL SHOCK MARCH 1990 (Limiting WELDS 2-442B/C)

ORIGINAL REPORT CURRENT FUTURE ESTIMATES NRC RULING CURRENT VESSEL STATUS Date 1/23/1986 3/31/1990 Fluence (xE19 n/ cm2) 0.13 0.20 vessel Age (EFPY) 2.25 5.00 FSAR PLANT DESIGN END-OF-LIFE Date 1/23/2018 1/10/2022 Fluence (xE19 n/cm2) 1.46 1.11 Vessel Age (EFPY) 32 32 END OF OPERATING LICENSE (No extension)

Date 9/25/2008 9/25/2008 Fluence (xE19 n/cm2) 1.20 0.74 Vessel Age (EFPY) 85% Avail

21. 9
21. 0 Adjusted Reference Temp(°F) 184.5 END OF VESSEL LIFE (When screening criteria is met)

Date, 85% Avail.

4/15/2169 8/28/2232 3/9/2086 Fluence (xE19 n/cm2) 7.10 7.10 2.93 Vessel Age (EFPY) 158.0 211.0 86.5