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=Text=
=Text=
{{#Wiki_filter:SEntergy Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 Stephen J. Bethay Director, Nuclear Safety Assurance July 13, 2010 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001
{{#Wiki_filter:Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station SEntergy                                                                                                                              600 Rocky Hill Road Plymouth, MA 02360 Stephen J. Bethay Director, Nuclear Safety Assurance July 13, 2010 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001


==SUBJECT:==
==SUBJECT:==
Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power Station Docket No. 50-293 License No. DPR-35  
Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station Docket No. 50-293 License No. DPR-35 Entergy Response to NRC Request for Additional Information Related to Pilgrim Relief Request (PRR)-20, Alternative Examination Requirements for Pilgrim Nozzle-to-Vessel Shell and Inner Radii Welds Using ASME Code Case N-702 and BWRVIP-108 (TAC NO. ME3290)


==REFERENCE:==
==REFERENCE:==
: 1.      Entergy Letter No. 2.10.004, Entergy Pilgrim Relief Request (PRR)-20, Alternative Examination Requirements for Pilgrim Nozzle-to-Vessel Shell and Inner Radii Welds Using ASME Code Case N-702 and BWRVIP-108dated February 1, 2010 LETTER NUMBER:        2.10Q035 ,'


LETTER NUMBER:  
==Dear Sir or Madam,==
 
This letter dockets Entergy's response to an NRC Request for Additional Information (RAI) forwarded to Pilgrim's Licensing Staff by E-mail on May 19, 2010.
The Entergy response supports the Pilgrim Relief Request (PRR)-20, Alternative Examination Requirements for Pilgrim Nc~z~z e-to-Vessel Shell Welds and Nozzle Inner Radii using the requirements of American Society of Mechanical Engineers (ASME) Code Case N-702 and BWRVI P-108 provisions.
                                              "* .i.. -" .'*..  : : * ":.* .. , . ..    . " "-      '..    : " . : .i :      I. ' -    .
                                                      * " ;:,',*"
                                                              " "' : *""        :o',.: . :'    ,:: :* '.::  *,.,':.  *  '" ":-!,:;  '.:, ,
                                                                                        ''. ,J    .". ,  Vo 9
                                                                                                                                                          -Aew?


==Dear Sir or Madam,==
Entergy Nuclear Operations, Inc.                               Letter Number: 2.10.035 Pilgrim Nuclear Power Station                                  Page 2 The proposed alternative along with the attached prior examination's results provide an acceptable level of quality and safety because it follows the requirements of ASME Code N-702 and the NRC approved technical basis (BWRVIP -108) for the alternative examination described in Pilgrim Relief Request (PRR)-20 submitted as Reference 1.
Entergy Response to NRC Request for Additional Information Related to Pilgrim Relief Request (PRR)-20, Alternative Examination Requirements for Pilgrim Nozzle-to-Vessel Shell and Inner Radii Welds Using ASME Code Case N-702 and BWRVIP-108 (TAC NO. ME3290)1. Entergy Letter No. 2.10.004, Entergy Pilgrim Relief Request (PRR)-20, Alternative Examination Requirements for Pilgrim Nozzle-to-Vessel Shell and Inner Radii Welds Using ASME Code Case N-702 and BWRVIP-108dated February 1, 2010 2.10Q035 ,'This letter dockets Entergy's response to an NRC Request for Additional Information (RAI)forwarded to Pilgrim's Licensing Staff by E-mail on May 19, 2010.The Entergy response supports the Pilgrim Relief Request (PRR)-20, Alternative Examination Requirements for Pilgrim Nc~z~z e-to-Vessel Shell Welds and Nozzle Inner Radii using the requirements of American Society of Mechanical Engineers (ASME) Code Case N-702 and BWRVI P-108 provisions." ..-" .. : i. : ": .. , ... ." "- '.. : " .: .i : I. ' -." " "' : ;:,',*" :o',.: .:' ,:: '.:: '" ":-!,:; '.: , ,''. ,J ." ., Vo 9-Aew?
There are no commitments made in this submittal.
Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power Station Letter Number: 2.10.035 Page 2 The proposed alternative along with the attached prior examination's results provide an acceptable level of quality and safety because it follows the requirements of ASME Code N-702 and the NRC approved technical basis (BWRVIP -108) for the alternative examination described in Pilgrim Relief Request (PRR)-20 submitted as Reference 1.There are no commitments made in this submittal.
If you have any questions, please call Mr. Joseph Lynch, Pilgrim Licensing Manager at 508-830-8403.
If you have any questions, please call Mr. Joseph Lynch, Pilgrim Licensing Manager at 508-830-8403.
Sincerely, Ste eJ.ethay Director, Nuclear Safety ssurance SJB/wgl  
Sincerely, Ste eJ.ethay Director, Nuclear Safety ssurance SJB/wgl


==Attachment:==
==Attachment:==
Entergy Response to NRC Request for Additional Information Related to Pilgrim Relief Request PRR-20 (2 pages) cc:          Regional Administrator, Region I            Mr. James S. Kim, Project Manager U.S. Nuclear Regulatory Commission          Plant Licensing Branch I-1 475 Allendale Road                          Division of Operator Reactor Licensing King of Prussia, PA 19406                    Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North 0-8C2 Senior Resident Inspector                    11555 Rockville Pike Pilgrim Nuclear Power Station                Rockville, MD 20852
Attachment to Entergy Letter Number 2.10.035 ENTERGY RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION RELATED TO PILGRIM RELIEF REQUEST PRR-20 (2 pages)


Entergy Response to NRC Request for Additional Information Related to Pilgrim Relief Request PRR-20 (2 pages)cc: Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector Pilgrim Nuclear Power Station Mr. James S. Kim, Project Manager Plant Licensing Branch I-1 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North 0-8C2 11555 Rockville Pike Rockville, MD 20852 Attachment to Entergy Letter Number 2.10.035 ENTERGY RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION RELATED TO PILGRIM RELIEF REQUEST PRR-20 (2 pages)
ENTERGY RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING PILGRIM RELIEF REQUEST PRR-20
ENTERGY RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING PILGRIM RELIEF REQUEST PRR-20  


==Reference:==
==Reference:==
Pilgrim PRR-20: Alternative Examination Requirements for Nozzle-to-Shell and Inner Radii Welds Using ASME Code Case N-702 and BWRVIP-108 (TAC NO. ME3290)
Dated, May 19, 2010 (By E-mail)
NRC Request:
Please provide a synopsis of what inspections have already been performed on the components for which this alternative is requested, including all indications that were found and how these indications were dispositioned.
Enterg¥/Pilqrim Response:
The following Table provides inspections that were performed on the RPV welds during refueling outages and the indications found during inspections.
('nmnnnant    in1      DImr~ri ntinn              Vi~rQ nf InQn~tinn It ITI      Inrliratinn*
Yaars of Insnection ["In RPV-NI A-NV            28" Recirc Outlet              1977,1983,1999,2009            NRI Nozzle to Vessel Weld RPV-N1 A-NIR            28" Recirc Outlet              1977,1983,1999,2009            NRI Nozzle to Inner Radius RPV-N1 B-NV            28" Recirc Outlet              1980,1995,2005                NRI Nozzle to Vessel Weld RPV-N1 B-NIR            28" Recirc Outlet              1980,1995,2005                NRI Nozzle to Inner Radius RPV-N3A -NV            20" Main Steam                1974,1983,1997,2007            NRI Nozzle to Vessel Weld RPV-N3A-NIR            20" Main Steam                1974,1983,1997,2007            NRI Nozzle to Inner Radius RPV-N3B-NV              20" Main Steam                1981,1987,1997,2007            NRI Nozzle to Vessel Weld RPV-N3B-NIR            20" Main Steam                1987,1997, 2007                NRI Nozzle to Inner Radius RPV-N3C-NV              20" Main Steam                1981,1987,1997,2007            NRI Nozzle to Vessel Weld RPV-N3C-NIR            20" Main Steam                1987,1997,2007                NRI Nozzle to Inner Radius RPV-N3D-NV            20" Main Steam                1974,1987,1997,2007            NRI Nozzle to Vessel Weld RPV-N3D-NIR            20" Main Steam                1974,1987,1997,2007            NRI Nozzle to Inner Radius RPVN6A-NV              12" Core Spray                1981,1983,1987,1997,2007      NRI Nozzle to Vessel Weld RPV-N6A-NIR            12" Core Spray                  1983,1987,1997,2007          NRI Nozzle to Inner Radius Page 1 of 2


Pilgrim PRR-20: Alternative Examination Requirements for Nozzle-to-Shell and Inner Radii Welds Using ASME Code Case N-702 and BWRVIP-108 (TAC NO. ME3290)Dated, May 19, 2010 (By E-mail)NRC Request: Please provide a synopsis of what inspections have already been performed on the components for which this alternative is requested, including all indications that were found and how these indications were dispositioned.
ENTERGY RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING PILGRIM RELIEF REQUEST PRR-20 RPV-N6B-NV         12" Core Spray                 1974,1991,2001  NRI Nozzle to Vessel Weld RPV-N6B-NIR      12" Core Spray                 1974,1991, 2001 NRI Nozzle to Inner Radius 1974, 1995,2005 RPV-N7A-NV        9" Spare Instrumentation                       NRI Nozzle to Vessel Weld 1974,1995, 2005 RPV-N7A-NIR      9" Spare Instrumentation                       NRI Nozzle to Inner Radius 1974,1995,2005 RPV-N7B-NV        9" Spare Instrumentation                       NRI Nozzle to Vessel Weld 1974,1995,2005 RPV-N7B-NIR      9" Spare Instrumentation                       NRI Nozzle to Inner Radius RPV-N8-NV        6" Head Vent                   1993,2005      NRI Nozzle to Vessel Weld RPV-N8-NIR        6" Head Vent                   1993,2005      NRI Nozzle to Inner Radius RPV-N9A-NV        5" Jet Pump Instrumentation   1987,1999,2009  NRI Nozzle to Vessel Weld RPV-N9A-NIR        5" Jet Pump Instrumentation   1987,1999,2009  NRI Nozzle to Inner Radius RPV-N9B-NV        5',' Jet Pump Instrumentation   1974,1993,2003  NRI Nozzle to Vessel Weld RPV-N9B-NIR        5" Jet Pump Instrumentation   1974,1993,2003 NRI Nozzle to Inner Radius OUTAGE              YEAR RFO #1             1974 RFO #2             1976 RFO #3             1977 RFO #4             1980 RFO #5             1981 RFO #6             1983 RFO #7             1987 RFO #8             1991 RFO #9             1993 RFO #10             1995 RFO #11             1997 RFO #12             1999 RFO #13             2001 RFO #14             2003 RFO #15             2005 RFO #16             2007 RFO #17             2009
Enterg¥/Pilqrim Response: The following Table provides inspections that were performed on the RPV welds during refueling outages and the indications found during inspections.
* NRI = NO RECORDABLE INDICATIONS Page 2 of 2}}
('nmnnnant in1 DImr~ri ntinn Vi~rQ nf InQn~tinn It ITI Yaars of Insnection
["In RPV-NI A-NV RPV-N1 A-NIR RPV-N1 B-NV RPV-N1 B-NIR RPV-N3A -NV RPV-N3A-NIR RPV-N3B-NV RPV-N3B-NIR RPV-N3C-NV RPV-N3C-NIR RPV-N3D-NV RPV-N3D-NIR RPVN6A-NV RPV-N6A-NIR 28" Recirc Outlet Nozzle to Vessel Weld 28" Recirc Outlet Nozzle to Inner Radius 28" Recirc Outlet Nozzle to Vessel Weld 28" Recirc Outlet Nozzle to Inner Radius 20" Main Steam Nozzle to Vessel Weld 20" Main Steam Nozzle to Inner Radius 20" Main Steam Nozzle to Vessel Weld 20" Main Steam Nozzle to Inner Radius 20" Main Steam Nozzle to Vessel Weld 20" Main Steam Nozzle to Inner Radius 20" Main Steam Nozzle to Vessel Weld 20" Main Steam Nozzle to Inner Radius 12" Core Spray Nozzle to Vessel Weld 12" Core Spray Nozzle to Inner Radius 1977,1983,1999,2009 1977,1983,1999,2009 1980,1995,2005 1980,1995,2005 1974,1983,1997,2007 1974,1983,1997,2007 1981,1987,1997,2007 1987,1997, 2007 1981,1987,1997,2007 1987,1997,2007 1974,1987,1997,2007 1974,1987,1997,2007 1981,1983,1987,1997,2007 1983,1987,1997,2007 NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI Page 1 of 2 ENTERGY RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING PILGRIM RELIEF REQUEST PRR-20 RPV-N6B-NV RPV-N6B-NIR RPV-N7A-NV RPV-N7A-NIR RPV-N7B-NV RPV-N7B-NIR RPV-N8-NV RPV-N8-NIR RPV-N9A-NV RPV-N9A-NIR RPV-N9B-NV RPV-N9B-NIR OUTAGE 12" Core Spray Nozzle to Vessel Weld 12" Core Spray Nozzle to Inner Radius 9" Spare Instrumentation Nozzle to Vessel Weld 9" Spare Instrumentation Nozzle to Inner Radius 9" Spare Instrumentation Nozzle to Vessel Weld 9" Spare Instrumentation Nozzle to Inner Radius 6" Head Vent Nozzle to Vessel Weld 6" Head Vent Nozzle to Inner Radius 5" Jet Pump Instrumentation Nozzle to Vessel Weld 5" Jet Pump Instrumentation Nozzle to Inner Radius 5',' Jet Pump Instrumentation Nozzle to Vessel Weld 5" Jet Pump Instrumentation Nozzle to Inner Radius 1974,1991,2001 1974,1991, 2001 1974, 1995,2005 1974,1995, 2005 1974,1995,2005 1974,1995,2005 NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI 1993,2005 1993,2005 1987,1999,2009 1987,1999,2009 1974,1993,2003 1974,1993,2003 YEAR RFO #1 1974 RFO #2 1976 RFO #3 1977 RFO #4 1980 RFO #5 1981 RFO #6 1983 RFO #7 1987 RFO #8 1991 RFO #9 1993 RFO #10 1995 RFO #11 1997 RFO #12 1999 RFO #13 2001 RFO #14 2003 RFO #15 2005 RFO #16 2007 RFO #17 2009* NRI = NO RECORDABLE INDICATIONS Page 2 of 2}}

Revision as of 16:51, 13 November 2019

Entergy Response to NRC Request for Additional Information Related to Pilgrim Relief Request (PRR)-20, Alternative Examination Requirements for Pilgrim Nozzle-to-Vessel Shell and Inner Radii Welds Using ASME Code Case N-702 and BWRVIP-108
ML102020257
Person / Time
Site: Pilgrim
Issue date: 07/13/2010
From: Bethay S
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC ME3290
Download: ML102020257 (5)
v • d • e


Text

Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station SEntergy 600 Rocky Hill Road Plymouth, MA 02360 Stephen J. Bethay Director, Nuclear Safety Assurance July 13, 2010 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001

SUBJECT:

Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station Docket No. 50-293 License No. DPR-35 Entergy Response to NRC Request for Additional Information Related to Pilgrim Relief Request (PRR)-20, Alternative Examination Requirements for Pilgrim Nozzle-to-Vessel Shell and Inner Radii Welds Using ASME Code Case N-702 and BWRVIP-108 (TAC NO. ME3290)

REFERENCE:

1. Entergy Letter No. 2.10.004, Entergy Pilgrim Relief Request (PRR)-20, Alternative Examination Requirements for Pilgrim Nozzle-to-Vessel Shell and Inner Radii Welds Using ASME Code Case N-702 and BWRVIP-108dated February 1, 2010 LETTER NUMBER: 2.10Q035 ,'

Dear Sir or Madam,

This letter dockets Entergy's response to an NRC Request for Additional Information (RAI) forwarded to Pilgrim's Licensing Staff by E-mail on May 19, 2010.

The Entergy response supports the Pilgrim Relief Request (PRR)-20, Alternative Examination Requirements for Pilgrim Nc~z~z e-to-Vessel Shell Welds and Nozzle Inner Radii using the requirements of American Society of Mechanical Engineers (ASME) Code Case N-702 and BWRVI P-108 provisions.

"* .i.. -" .'*..  : : * ":.* .. , . .. . " "- '..  : " . : .i : I. ' - .

  • " ;:,',*"

" "' : *"" :o',.: . :' ,:: :* '.:: *,.,':. * '" ":-!,:; '.:, ,

. ,J .". , Vo 9

-Aew?

Entergy Nuclear Operations, Inc. Letter Number: 2.10.035 Pilgrim Nuclear Power Station Page 2 The proposed alternative along with the attached prior examination's results provide an acceptable level of quality and safety because it follows the requirements of ASME Code N-702 and the NRC approved technical basis (BWRVIP -108) for the alternative examination described in Pilgrim Relief Request (PRR)-20 submitted as Reference 1.

There are no commitments made in this submittal.

If you have any questions, please call Mr. Joseph Lynch, Pilgrim Licensing Manager at 508-830-8403.

Sincerely, Ste eJ.ethay Director, Nuclear Safety ssurance SJB/wgl

Attachment:

Entergy Response to NRC Request for Additional Information Related to Pilgrim Relief Request PRR-20 (2 pages) cc: Regional Administrator, Region I Mr. James S. Kim, Project Manager U.S. Nuclear Regulatory Commission Plant Licensing Branch I-1 475 Allendale Road Division of Operator Reactor Licensing King of Prussia, PA 19406 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North 0-8C2 Senior Resident Inspector 11555 Rockville Pike Pilgrim Nuclear Power Station Rockville, MD 20852

Attachment to Entergy Letter Number 2.10.035 ENTERGY RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION RELATED TO PILGRIM RELIEF REQUEST PRR-20 (2 pages)

ENTERGY RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING PILGRIM RELIEF REQUEST PRR-20

Reference:

Pilgrim PRR-20: Alternative Examination Requirements for Nozzle-to-Shell and Inner Radii Welds Using ASME Code Case N-702 and BWRVIP-108 (TAC NO. ME3290)

Dated, May 19, 2010 (By E-mail)

NRC Request:

Please provide a synopsis of what inspections have already been performed on the components for which this alternative is requested, including all indications that were found and how these indications were dispositioned.

Enterg¥/Pilqrim Response:

The following Table provides inspections that were performed on the RPV welds during refueling outages and the indications found during inspections.

('nmnnnant in1 DImr~ri ntinn Vi~rQ nf InQn~tinn It ITI Inrliratinn*

Yaars of Insnection ["In RPV-NI A-NV 28" Recirc Outlet 1977,1983,1999,2009 NRI Nozzle to Vessel Weld RPV-N1 A-NIR 28" Recirc Outlet 1977,1983,1999,2009 NRI Nozzle to Inner Radius RPV-N1 B-NV 28" Recirc Outlet 1980,1995,2005 NRI Nozzle to Vessel Weld RPV-N1 B-NIR 28" Recirc Outlet 1980,1995,2005 NRI Nozzle to Inner Radius RPV-N3A -NV 20" Main Steam 1974,1983,1997,2007 NRI Nozzle to Vessel Weld RPV-N3A-NIR 20" Main Steam 1974,1983,1997,2007 NRI Nozzle to Inner Radius RPV-N3B-NV 20" Main Steam 1981,1987,1997,2007 NRI Nozzle to Vessel Weld RPV-N3B-NIR 20" Main Steam 1987,1997, 2007 NRI Nozzle to Inner Radius RPV-N3C-NV 20" Main Steam 1981,1987,1997,2007 NRI Nozzle to Vessel Weld RPV-N3C-NIR 20" Main Steam 1987,1997,2007 NRI Nozzle to Inner Radius RPV-N3D-NV 20" Main Steam 1974,1987,1997,2007 NRI Nozzle to Vessel Weld RPV-N3D-NIR 20" Main Steam 1974,1987,1997,2007 NRI Nozzle to Inner Radius RPVN6A-NV 12" Core Spray 1981,1983,1987,1997,2007 NRI Nozzle to Vessel Weld RPV-N6A-NIR 12" Core Spray 1983,1987,1997,2007 NRI Nozzle to Inner Radius Page 1 of 2

ENTERGY RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING PILGRIM RELIEF REQUEST PRR-20 RPV-N6B-NV 12" Core Spray 1974,1991,2001 NRI Nozzle to Vessel Weld RPV-N6B-NIR 12" Core Spray 1974,1991, 2001 NRI Nozzle to Inner Radius 1974, 1995,2005 RPV-N7A-NV 9" Spare Instrumentation NRI Nozzle to Vessel Weld 1974,1995, 2005 RPV-N7A-NIR 9" Spare Instrumentation NRI Nozzle to Inner Radius 1974,1995,2005 RPV-N7B-NV 9" Spare Instrumentation NRI Nozzle to Vessel Weld 1974,1995,2005 RPV-N7B-NIR 9" Spare Instrumentation NRI Nozzle to Inner Radius RPV-N8-NV 6" Head Vent 1993,2005 NRI Nozzle to Vessel Weld RPV-N8-NIR 6" Head Vent 1993,2005 NRI Nozzle to Inner Radius RPV-N9A-NV 5" Jet Pump Instrumentation 1987,1999,2009 NRI Nozzle to Vessel Weld RPV-N9A-NIR 5" Jet Pump Instrumentation 1987,1999,2009 NRI Nozzle to Inner Radius RPV-N9B-NV 5',' Jet Pump Instrumentation 1974,1993,2003 NRI Nozzle to Vessel Weld RPV-N9B-NIR 5" Jet Pump Instrumentation 1974,1993,2003 NRI Nozzle to Inner Radius OUTAGE YEAR RFO #1 1974 RFO #2 1976 RFO #3 1977 RFO #4 1980 RFO #5 1981 RFO #6 1983 RFO #7 1987 RFO #8 1991 RFO #9 1993 RFO #10 1995 RFO #11 1997 RFO #12 1999 RFO #13 2001 RFO #14 2003 RFO #15 2005 RFO #16 2007 RFO #17 2009

  • NRI = NO RECORDABLE INDICATIONS Page 2 of 2
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