ML102020257: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (StriderTol Bot change) |
||
(3 intermediate revisions by the same user not shown) | |||
Line 3: | Line 3: | ||
| issue date = 07/13/2010 | | issue date = 07/13/2010 | ||
| title = 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 | | title = 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 | ||
| author name = Bethay S | | author name = Bethay S | ||
| author affiliation = Entergy Nuclear Operations, Inc | | author affiliation = Entergy Nuclear Operations, Inc | ||
| addressee name = | | addressee name = | ||
Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#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 ,' | |||
==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. | |||
Entergy Nuclear Operations, Inc. | |||
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 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 | |||
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}} | |||
Latest revision as of 22:01, 11 March 2020
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) | |
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