ML18101A420: Difference between revisions

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| issue date = 12/15/1994
| issue date = 12/15/1994
| title = Forwards Radial Peaking Factor Limit Rept,Salem Unit 2, Cycle 9. Rept Includes Radial Peaking Factor Limits for Rated Thermal Power for Core Planes Containing Bank D Control Rods & Unrodded Core Planes
| title = Forwards Radial Peaking Factor Limit Rept,Salem Unit 2, Cycle 9. Rept Includes Radial Peaking Factor Limits for Rated Thermal Power for Core Planes Containing Bank D Control Rods & Unrodded Core Planes
| author name = LABRUNA S
| author name = Labruna S
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:Public Service Electric and Gas Company I Stanley LaBruna Public Service Electric and Gas 1 Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1700 Vice President  
{{#Wiki_filter:Public Service Electric and Gas Company I
-Nuclear Engineering DEC 15 1994 NLR-N94222 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
1 Stanley LaBruna                     Public Service Electric and Gas Company     P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1700 Vice President - Nuclear Engineering                                       DEC 15 1994 NLR-N94222 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
SALEM GENERATING STATION UNIT NO. 2 CYCLE 9 RADIAL PEAKING FACTOR LIMIT REPORT FACILITY OPERATING LICENSE DPR-75 DOCKET NO. 50-311 In accordance with Salem Generating Station (SGS) Unit 2 Technical Specification 6.9.1.9, Public Service Electric and Gas Company (PSE&G) hereby submits the Radial Peaking Factor Limit Report for the ninth cycle of operation (Attachment 1). This report includes the radial peaking factor limits for rated thermal power for all core planes containing Bank "D" control rods and all unrodded core planes. It also includes the plot and limit envelope of predicted heat flux hot channel factor multiplied by relative power, vs. axial core height. Should you have any questions regarding this report, please contact us. Sincerely, Attachment (1)
SALEM GENERATING STATION UNIT NO. 2 CYCLE 9 RADIAL PEAKING FACTOR LIMIT REPORT FACILITY OPERATING LICENSE DPR-75 DOCKET NO. 50-311 In accordance with Salem Generating Station (SGS) Unit 2 Technical Specification 6.9.1.9, Public Service Electric and Gas Company (PSE&G) hereby submits the Radial Peaking Factor Limit Report for the ninth cycle of operation (Attachment 1). This report includes the radial peaking factor limits for rated thermal power for all core planes containing Bank "D" control rods and all unrodded core planes. It also includes the plot and limit envelope of predicted heat flux hot channel factor multiplied by relative power, vs. axial core height.
Document Control Desk 2 c Mr. T. T. Martin, Administrator  
Should you have any questions regarding this report, please contact us.
-Region I U. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. N. Olshan, Licensing Project Manager -Salem u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. c. Marschall (S09) USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 DEG 15 1994 95-4933}}
Sincerely, Attachment (1)
 
Document Control Desk             2                   DEG 15 1994 N~-N94222 c   Mr. T. T. Martin, Administrator - Region I U. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. N. Olshan, Licensing Project Manager - Salem
: u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. c. Marschall (S09)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 95-4933}}

Latest revision as of 10:19, 21 October 2019

Forwards Radial Peaking Factor Limit Rept,Salem Unit 2, Cycle 9. Rept Includes Radial Peaking Factor Limits for Rated Thermal Power for Core Planes Containing Bank D Control Rods & Unrodded Core Planes
ML18101A420
Person / Time
Site: Salem PSEG icon.png
Issue date: 12/15/1994
From: Labruna S
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18101A421 List:
References
NLR-N94222, NUDOCS 9412230262
Download: ML18101A420 (2)


Text

Public Service Electric and Gas Company I

1 Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1700 Vice President - Nuclear Engineering DEC 15 1994 NLR-N94222 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

SALEM GENERATING STATION UNIT NO. 2 CYCLE 9 RADIAL PEAKING FACTOR LIMIT REPORT FACILITY OPERATING LICENSE DPR-75 DOCKET NO. 50-311 In accordance with Salem Generating Station (SGS) Unit 2 Technical Specification 6.9.1.9, Public Service Electric and Gas Company (PSE&G) hereby submits the Radial Peaking Factor Limit Report for the ninth cycle of operation (Attachment 1). This report includes the radial peaking factor limits for rated thermal power for all core planes containing Bank "D" control rods and all unrodded core planes. It also includes the plot and limit envelope of predicted heat flux hot channel factor multiplied by relative power, vs. axial core height.

Should you have any questions regarding this report, please contact us.

Sincerely, Attachment (1)

Document Control Desk 2 DEG 15 1994 N~-N94222 c Mr. T. T. Martin, Administrator - Region I U. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. N. Olshan, Licensing Project Manager - Salem

u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. c. Marschall (S09)

USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 95-4933