ML18096A797: Difference between revisions

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* Public Service Electric and Gas Company
* Public Service Electric and Gas Company Stanley LaBruna                       Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations JUN 2 3 1992 NLR-N92088 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
* Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President  
NINETY DAY REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST REPORT SALEM GENERATING STATION UNIT NO. 2 DOCKET NO. 50-311 Public Service Electric & Gas Company (PSE&G) hereby provides the enclosed report in accordance with 10CFR50, Appendix J, Section V.B.3 and Salem Generating Station Technical Specification 4.6.1.2.
-Nuclear Operations JUN 2 3 1992 NLR-N92088 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
Enclosure 1 of this submittal contains the "Reactor Containment Building Integrated Leak Rate Test." This test was performed during the Salem Unit 2 sixth refueling outage. The test period was March 221 1992 to March 24, 1992.
NINETY DAY REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST REPORT SALEM GENERATING STATION UNIT NO. 2 DOCKET NO. 50-311 Public Service Electric & Gas Company (PSE&G) hereby provides the enclosed report in accordance with 10CFR50, Appendix J, Section V.B.3 and Salem Generating Station Technical Specification 4.6.1.2. Enclosure 1 of this submittal contains the "Reactor Containment Building Integrated Leak Rate Test." This test was performed during the Salem Unit 2 sixth refueling outage. The test period was March 22 1 1992 to March 24, 1992. Should there be any questions with regard to this submittal, please do not hesitate to contact us. Enclosure ( 1) 1 (,----9206290 i 7 4 920623. ' i PDR ADOCK 05000311 p *
Should there be any questions with regard to this submittal, please do not hesitate to contact us.
* PDR
Sincerely, Enclosure ( 1)           1
* Sincerely, 
(,----9206290 i 7 4 920623. '
----a---*... . -----Document Control Desk NLR-N92088 C Mr. J. c. Stone Licensing Project Manager Mr. T. P. Johnson Senior Resident Inspector 2 Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief
i       PDR ADOCK 05000311 p *
* JUN 2 3 1992 New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 Mr. Emanuel J. Mossa New Jersey Department of Labor and Industry PO Box 1503, Labor and Industry Building Trenton, NJ 08625}}
* PDR *
 
----a---
  *... . ~
Document Control Desk           2 NLR-N92088 JUN 2 3 1992 C   Mr. J. c. Stone Licensing Project Manager Mr. T. P. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 Mr. Emanuel J. Mossa New Jersey Department of Labor and Industry PO Box 1503, Labor and Industry Building Trenton, NJ 08625}}

Latest revision as of 06:31, 3 February 2020

Forwards Reactor Containment Bldg Integrated Leak Rate Test, Performed During Unit 2 Sixth Refueling Outage from 920322-24
ML18096A797
Person / Time
Site: Salem PSEG icon.png
Issue date: 06/23/1992
From: Labruna S
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18096A798 List:
References
NLR-N92088, NUDOCS 9206290174
Download: ML18096A797 (2)


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 609-339-1200 Vice President - Nuclear Operations JUN 2 3 1992 NLR-N92088 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

NINETY DAY REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST REPORT SALEM GENERATING STATION UNIT NO. 2 DOCKET NO. 50-311 Public Service Electric & Gas Company (PSE&G) hereby provides the enclosed report in accordance with 10CFR50, Appendix J, Section V.B.3 and Salem Generating Station Technical Specification 4.6.1.2.

Enclosure 1 of this submittal contains the "Reactor Containment Building Integrated Leak Rate Test." This test was performed during the Salem Unit 2 sixth refueling outage. The test period was March 221 1992 to March 24, 1992.

Should there be any questions with regard to this submittal, please do not hesitate to contact us.

Sincerely, Enclosure ( 1) 1

(,----9206290 i 7 4 920623. '

i PDR ADOCK 05000311 p *


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  • ... . ~

Document Control Desk 2 NLR-N92088 JUN 2 3 1992 C Mr. J. c. Stone Licensing Project Manager Mr. T. P. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 Mr. Emanuel J. Mossa New Jersey Department of Labor and Industry PO Box 1503, Labor and Industry Building Trenton, NJ 08625