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| number = ML103400158
| number = ML103400158
| issue date = 12/20/2010
| issue date = 12/20/2010
| title = Three Mile Island Nuclear Station, Unit 1 - Request for Additional Information Regarding Fourth Inservice Inspection Interval Relief Requests l4R-02 and l4R-04 (TAC Nos. ME4519 and ME4521)
| title = Request for Additional Information Regarding Fourth Inservice Inspection Interval Relief Requests l4R-02 and l4R-04
| author name = Bamford P J
| author name = Bamford P
| author affiliation = NRC/NRR/DORL/LPLI-2
| author affiliation = NRC/NRR/DORL/LPLI-2
| addressee name = Pacilio M J
| addressee name = Pacilio M
| addressee affiliation = Exelon Nuclear
| addressee affiliation = Exelon Nuclear
| docket = 05000289
| docket = 05000289
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 December 20, 2010 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 THREE MILE ISLAND NUCLEAR STATION, UNIT 1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING FOURTH INSERV1CE INSPECTION INTERVAL RELIEF REQUESTS 14R-02 AND 14R-04 (TAC NOS. ME4519 AND ME4521)  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 20, 2010 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
 
==SUBJECT:==
THREE MILE ISLAND NUCLEAR STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING FOURTH INSERV1CE INSPECTION INTERVAL RELIEF REQUESTS 14R-02 AND 14R-04 (TAC NOS. ME4519 AND ME4521)


==Dear Mr. Pacilio:==
==Dear Mr. Pacilio:==
By letter dated August 10, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 102290162), Exelon Generation Company, LLC submitted a set of relief requests for Three Mile Island Nuclear Station, Unit 1 (TMI-1). The relief requests are all associated with the fourth Inservice Inspection (lSI) interval at TMI-1. The U.S.
 
Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that additional information is needed to complete its review. This information request relates to Relief Requests 14R-02, "Request for Relief for Alternate Risk-Informed Selection and Examination Criteria for Examination Category B-F, B-J, C-F-1, and C-F-2 Pressure Retaining Piping Welds," and 14R-04, "Request for Relief for lSI Snubbers Included in the Technical Specifications Snubber Visual Examination and Functional Testing Program." The NRC staff has been reviewing the response and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The questions were sent via electronic transmission on December 1,2010, and on December 8,2010, to Mr. Thomas Loomis, of your staff. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. The draft questions were discussed in a teleconference with your staff on December 14, 2010, and a minor edit was made to RAI number 1, regarding Relief Request 14R-02. It was agreed that a response to this RAI would be submitted by January 28, 2011. Please contact me at 301-415-2833, if you have any questions.
By letter dated August 10, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102290162), Exelon Generation Company, LLC submitted a set of relief requests for Three Mile Island Nuclear Station, Unit 1 (TMI-1). The relief requests are all associated with the fourth Inservice Inspection (lSI) interval at TMI-1. The U.S. Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that additional information is needed to complete its review. This information request relates to Relief Requests 14R-02, "Request for Relief for Alternate Risk-Informed Selection and Examination Criteria for Examination Category B-F, B-J, C-F-1, and C-F-2 Pressure Retaining Piping Welds," and 14R-04, "Request for Relief for lSI Snubbers Included in the Technical Specifications Snubber Visual Examination and Functional Testing Program."
Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-289  
The NRC staff has been reviewing the response and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The questions were sent via electronic transmission on December 1,2010, and on December 8,2010, to Mr. Thomas Loomis, of your staff. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. The draft questions were discussed in a teleconference with your staff on December 14, 2010, and a minor edit was made to RAI number 1, regarding Relief Request 14R-02. It was agreed that a response to this RAI would be submitted by January 28, 2011.
Please contact me at 301-415-2833, if you have any questions.
Sd?;k~
Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-289


==Enclosure:==
==Enclosure:==
As stated cc: Distribution via Listserv REQUEST FOR ADDITIONAL II\lFORMATION THREE MILE ISLAND NUCLEAR STATION, UNIT 1 RELIEF REQUESTS ASSOCIATED WITH THE FOURTH INSERVICE INSPECTION INTERVAL RELIEF REQUESTS 14R-02AND 14R-04 DOCKET NO. 50-289 By letter dated August 10, 2010 (Agencywide Documents Access and Management System (ADAMS)
As stated cc: Distribution via Listserv
Accession No. ML 102290162), Exelon Generation Company, LLC submitted a set of relief requests for Three Mile Island Nuclear Station, Unit 1 (TMI-1).
 
The relief requests are all associated with the fourth Inservice Inspection (lSI) interval at TMI-1. The U.S.
REQUEST FOR ADDITIONAL II\lFORMATION THREE MILE ISLAND NUCLEAR STATION, UNIT 1 RELIEF REQUESTS ASSOCIATED WITH THE FOURTH INSERVICE INSPECTION INTERVAL RELIEF REQUESTS 14R-02AND 14R-04 DOCKET NO. 50-289 By letter dated August 10, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102290162), Exelon Generation Company, LLC submitted a set of relief requests for Three Mile Island Nuclear Station, Unit 1 (TMI-1).
Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that additional information is needed to complete its review. This information request relates to Relief Requests 14R-02, "Request for Relief for Alternate Risk-Informed Selection and Examination Criteria for Examination Category B-F, B-J, C-F-1, and C-F-2 Pressure Retaining Piping Welds," and 14R-04, "Request for Relief for lSI Snubbers Included in the Technical Specifications Snubber Visual Examination and Functional Testing Program." Relief Request 14R-02 1. The relief request includes the following paragraph: The Risk Impact Assessment completed as part of the original baseline [Risk-Informed Inservice Inspection] RISI Program was an implementation/transition check on the initial impact of converting from a traditional  
The relief requests are all associated with the fourth Inservice Inspection (lSI) interval at TMI-1. The U.S. Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that additional information is needed to complete its review. This information request relates to Relief Requests 14R-02, "Request for Relief for Alternate Risk-Informed Selection and Examination Criteria for Examination Category B-F, B-J, C-F-1, and C-F-2 Pressure Retaining Piping Welds," and 14R-04, "Request for Relief for lSI Snubbers Included in the Technical Specifications Snubber Visual Examination and Functional Testing Program."
[American Society of Mechanical Engineers]
Relief Request 14R-02
ASME Section XI program to the new RISI methodology. For the fourth interval lSI update, there is no transition occurring between two different methodologies, but rather, the currently approved RISI methodology and evaluation will be maintained for the new interval.
: 1.     The relief request includes the following paragraph:
The Risk Impact Assessment completed as part of the original baseline [Risk-Informed Inservice Inspection] RISI Program was an implementation/transition check on the initial impact of converting from a traditional [American Society of Mechanical Engineers] ASME Section XI program to the new RISI methodology. For the fourth interval lSI update, there is no transition occurring between two different methodologies, but rather, the currently approved RISI methodology and evaluation will be maintained for the new interval.
The NRC staff does not agree with the implication that, if there is no change in methodology, the change in risk assessment is not part of the living process.
The NRC staff does not agree with the implication that, if there is no change in methodology, the change in risk assessment is not part of the living process.
Furthermore, the submittal is requesting relief to implement a RISI program instead of an ASME program for the fourth interval, so there is a change from the methodology that would normally be used (i.e., without a relief request). Electrical Power Research Institute Topical Report 112657, Revision B-A, which is cited in the application as the evaluation methodology for the RISI program, requires an evaluation of the change in risk (core damage frequency (CDF) and large early release frequency (LERF)) arising from the proposed change in the lSI program.
Furthermore, the submittal is requesting relief to implement a RISI program instead of an ASME program for the fourth interval, so there is a change from the methodology that would normally be used (i.e., without a relief request). Electrical Power Research Institute Topical Report 112657, Revision B-A, which is cited in the application as the evaluation methodology for the RISI program, requires an evaluation of the change in risk (core damage frequency (CDF) and large early release frequency (LERF)) arising from the proposed change in the lSI program.
Please provide an estimate of the potential change in risk between the RISI program proposed for implementation in the fourth interval and the ASME Section XI requirements which existed prior to the implementation of the RISI program.
Please provide an estimate of the potential change in risk between the RISI program proposed for implementation in the fourth interval and the ASME Section XI requirements which existed prior to the implementation of the RISI program.
Enclosure
Enclosure
-2 2. The relief request states: These portions of the RISI Program have been and will continue to be reevaluated and revised as major revisions of the site Probabilistic Risk Assessment (PRA) occur and modifications to plant configuration are made. The Consequence Evaluation, Degradation Mechanism Assessment, Risk Ranking, Element Selection, and Risk Impact Assessment steps encompass the complete living program process applied under the TMI, Unit 1 RISI Program. Please provide the date of the last PRA reevaluation and revision that is described above, and a brief description of the results of the reevaluations and revisions undertaken at that date. Specifically, please provide the baseline CDF and the baseline LERF for the most current PRA. In addition, please explain how any modifications to the plant since the date of the last reevaluation and revision may impact the RISI program. Are the inspection locations in the RISI program that have been developed for the fourth 10-year interval the same locations as those in the third interval RISI program approved in the NRC staff's November 12, 2003, safety evaluation (ADAMS Accession No. ML032930264)? If not, please summarize the changes to the program and what caused those changes. If there are changes in the inspection locations for the TMI-1 fourth 1O-year interval RISI program, please provide information for the fourth interval program regarding:
 
                                                    -2
: 2. The relief request states:
These portions of the RISI Program have been and will continue to be reevaluated and revised as major revisions of the site Probabilistic Risk Assessment (PRA) occur and modifications to plant configuration are made. The Consequence Evaluation, Degradation Mechanism Assessment, Risk Ranking, Element Selection, and Risk Impact Assessment steps encompass the complete living program process applied under the TMI, Unit 1 RISI Program.
Please provide the date of the last PRA reevaluation and revision that is described above, and a brief description of the results of the reevaluations and revisions undertaken at that date. Specifically, please provide the baseline CDF and the baseline LERF for the most current PRA. In addition, please explain how any modifications to the plant since the date of the last reevaluation and revision may impact the RISI program.
: 3. Are the inspection locations in the RISI program that have been developed for the fourth 10-year interval the same locations as those in the third interval RISI program approved in the NRC staff's November 12, 2003, safety evaluation (ADAMS Accession No. ML032930264)? If not, please summarize the changes to the program and what caused those changes.
: 4.      If there are changes in the inspection locations for the TMI-1 fourth 1O-year interval RISI program, please provide information for the fourth interval program regarding:
examinations/system/components/degradation mechanisms/class, etc. similar to that provided in Tables 2, 3 and 4 of the original submittal of the RISI program for the TMI-1 third 1O-year lSI interval dated October 1, 2002 (ADAMS Accession No. ML022830211).
examinations/system/components/degradation mechanisms/class, etc. similar to that provided in Tables 2, 3 and 4 of the original submittal of the RISI program for the TMI-1 third 1O-year lSI interval dated October 1, 2002 (ADAMS Accession No. ML022830211).
Relief Request 14R-04 TMI-1 Technical Specification (TS) 4.17.1 (e)(2) provides for an optional functional testing of snubbers in accordance with TMI-1 TS Figure 4.17-1. Please verify that (1) this plan is equivalent to the 37 or 55 testing sample plan of ASME/ANSl [American National Standards Institute] OM Code Part 4,1987 Edition with OMa-1988 Addendum (OM-4); and (2) explain whether and how the requirement of additional sampling of at least half of the size of the initial sample lot as required by OM-4, Section 3.2.3.2(b), will be met while using TMI-1 TS Figure 4.17-1. If the TS requirements do not meet the OM-4 requirements, please explain how the proposed alternative provides an acceptable level of quality and safety. The requested alternative and TMI-1 TS 4.17 do not address the requirements of OM-4, Section 2.3.4.3, "Examination Failure Mode Groups," and Section 3.2.4.2, "Test Failure Mode Groups," related to examination and functional testing of snubbers. Please explain how TMI-1 TS 4.17 meets these requirements or provides an acceptable level of quality and safety. ASME, Section XI, 2004 Edition, Article IWF-5000, Subsections IWF-5200(c) and 5300(c), clearly state that integral and non-integral attachments for snubbers (including lugs, bolting, pins, and clamps), shall be examined in accordance with the requirements of Subsection IWF. Please explain whether and how these requirements will be met. If
Relief Request 14R-04
-3they will not be met, please explain how the proposed alternative provides an acceptable level of quality and safety.  
: 1.      TMI-1 Technical Specification (TS) 4.17.1 (e)(2) provides for an optional functional testing of snubbers in accordance with TMI-1 TS Figure 4.17-1. Please verify that (1) this plan is equivalent to the 37 or 55 testing sample plan of ASME/ANSl [American National Standards Institute] OM Code Part 4,1987 Edition with OMa-1988 Addendum (OM-4);
: 4. TMI-1 TS 4.17.1(b), footnote  
and (2) explain whether and how the requirement of additional sampling of at least one half of the size of the initial sample lot as required by OM-4, Section 3.2.3.2(b), will be met while using TMI-1 TS Figure 4.17-1. If the TS requirements do not meet the OM-4 requirements, please explain how the proposed alternative provides an acceptable level of quality and safety.
"**" states: The inspection interval for each type of snubber shall not be lengthened more than one step at a time unless a generic problem has been identified and corrected; in that event the inspection interval may be lengthened one step the first time and two steps thereafter if no inoperable snubbers of that type are found. OM-4, Section 2.3.2.3, "Subsequent Examination Schedule Adjustment," states that the time to subsequent examination shall not be lengthened more than one increment at a time. Please explain why the inspection intervals described in TMI-1 TS 4.17.1(b) are acceptable in lieu of the examination schedule requirement noted in OM-4, Section 2.3.2.3.  
: 2.      The requested alternative and TMI-1 TS 4.17 do not address the requirements of OM-4, Section 2.3.4.3, "Examination Failure Mode Groups," and Section 3.2.4.2, "Test Failure Mode Groups," related to examination and functional testing of snubbers. Please explain how TMI-1 TS 4.17 meets these requirements or provides an acceptable level of quality and safety.
: 5. In TMI-1 TS 4.17.1(e), "Functional Tests", the footnote  
: 3.      ASME, Section XI, 2004 Edition, Article IWF-5000, Subsections IWF-5200(c) and IWF 5300(c), clearly state that integral and non-integral attachments for snubbers (including lugs, bolting, pins, and clamps), shall be examined in accordance with the requirements of Subsection IWF. Please explain whether and how these requirements will be met. If
"*" states: The four 555,000 Ib reactor coolant pump snubbers are not included.
 
The functional test program for reactor coolant pump snubbers is implemented in accordance with the schedule and other requirements of the snubber testing program. Please provide details on how the reactor coolant pump snubbers will be tested as compared to the OM-4 requirements.
                                              -3 they will not be met, please explain how the proposed alternative provides an acceptable level of quality and safety.
December 20,2010 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville,lL 60555 THREE MILE ISLAND NUCLEAR STATION, UNIT 1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING FOURTH INSERVICE INSPECTION INTERVAL RELIEF REQUESTS 14R-02AND 14R-04(TAC NOS.
: 4. TMI-1 TS 4.17.1 (b), footnote "**" states:
ME4519 AND ME4521)  
The inspection interval for each type of snubber shall not be lengthened more than one step at a time unless a generic problem has been identified and corrected; in that event the inspection interval may be lengthened one step the first time and two steps thereafter if no inoperable snubbers of that type are found.
OM-4, Section 2.3.2.3, "Subsequent Examination Schedule Adjustment," states that the time to subsequent examination shall not be lengthened more than one increment at a time. Please explain why the inspection intervals described in TMI-1 TS 4.17.1 (b) are acceptable in lieu of the examination schedule requirement noted in OM-4, Section 2.3.2.3.
: 5. In TMI-1 TS 4.17.1 (e), "Functional Tests", the footnote "*" states:
The four 555,000 Ib reactor coolant pump snubbers are not included.
The functional test program for reactor coolant pump snubbers is implemented in accordance with the schedule and other requirements of the snubber testing program.
Please provide details on how the reactor coolant pump snubbers will be tested as compared to the OM-4 requirements.
 
December 20,2010 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville,lL 60555
 
==SUBJECT:==
THREE MILE ISLAND NUCLEAR STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING FOURTH INSERVICE INSPECTION INTERVAL RELIEF REQUESTS 14R-02AND 14R-04 (TAC NOS. ME4519 AND ME4521)


==Dear Mr. Pacilio:==
==Dear Mr. Pacilio:==


By letter dated August 10, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 102290162), Exelon Generation Company, LLC submitted a set of relief requests for Three Mile Island Nuclear Station, Unit 1 (TMI-1). The relief requests are all associated with the fourth Inservice Inspection (lSI) interval at TMI-1. The U.S.
By letter dated August 10, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102290162), Exelon Generation Company, LLC submitted a set of relief requests for Three Mile Island Nuclear Station, Unit 1 (TMI-1). The relief requests are all associated with the fourth Inservice Inspection (lSI) interval at TMI-1. The U.S. Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that additional information is needed to complete its review. This information request relates to Relief Requests 14R-02, "Request for Relief for Alternate Risk-Informed Selection and Examination Criteria for Examination Category B-F, B-J, C-F-1, and C-F-2 Pressure Retaining Piping Welds," and 14R-04, "Request for Relief for lSI Snubbers Included in the Technical Specifications Snubber Visual Examination and Functional Testing Program."
Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that additional information is needed to complete its review. This information request relates to Relief Requests 14R-02, "Request for Relief for Alternate Risk-Informed Selection and Examination Criteria for Examination Category B-F, B-J, C-F-1, and C-F-2 Pressure Retaining Piping Welds," and 14R-04, "Request for Relief for lSI Snubbers Included in the Technical Specifications Snubber Visual Examination and Functional Testing Program." The NRC staff has been reviewing the response and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The questions were sent via electronic transmission on December 1, 2010, and on December 8, 2010, to Mr.
The NRC staff has been reviewing the response and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The questions were sent via electronic transmission on December 1, 2010, and on December 8, 2010, to Mr. Thomas Loomis, of your staff. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. The draft questions were discussed in a teleconference with your staff on December 14, 2010, and a minor edit was made to RAI number 1, regarding Relief Request 14R-02. It was agreed that a response to this RAI would be submitted by January 28, 2011.
Thomas Loomis, of your staff. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. The draft questions were discussed in a teleconference with your staff on December 14, 2010, and a minor edit was made to RAI number 1, regarding Relief Request 14R-02. It was agreed that a response to this RAI would be submitted by January 28, 2011. Please contact me at 301-415-2833, if you have any questions.
Please contact me at 301-415-2833, if you have any questions.
Sincerely, /raj Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-289  
Sincerely,
                                                /raj Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-289


==Enclosure:==
==Enclosure:==
As stated cc: Distribution via Listserv DISTRIBUTION: RidsNrrPMThreeMilelsland Resource PUBLIC LPLI-2 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrDraApla Resource RidsOgcRp Resource RidsRgn1MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl1-2 Resouce RidsNrrLAABaxter Resource MOrenak, NRR RidsNrrDciCptb Resource DChung, NRR KHoffman, NRR RidsNrrDciCpnb Resource ADAMS Accession Number' ML103400158 *concurrence via email OFFICE LPL1-2/PM LPL1-2/LA APLAlBC CPTB/BC CPNB/BC LPLI-2/BC NAME PBamford ABaxter
As stated cc: Distribution via Listserv DISTRIBUTION:
* DHarrison*
RidsNrrPMThreeMilelsland Resource     PUBLIC                           LPLI-2 R/F RidsAcrsAcnw_MailCTR Resource         RidsNrrDraApla Resource           RidsOgcRp Resource RidsRgn1MailCenter Resource           RidsNrrDorlDpr Resource         RidsNrrDorlLpl1-2 Resouce RidsNrrLAABaxter Resource             MOrenak, NRR                     RidsNrrDciCptb Resource DChung, NRR                           KHoffman, NRR                     RidsNrrDciCpnb Resource ADAMS Accession Number' ML103400158           *concurrence via email OFFICE     LPL1-2/PM     LPL1-2/LA     APLAlBC         CPTB/BC         CPNB/BC             LPLI-2/BC NAME       PBamford     ABaxter
AMcMurtray*
* DHarrison*     AMcMurtray*       TLupold*     HChernoff (REnnis for)
TLupold* HChernoff (REnnis for) DATE 12/14/2010 12/14/10 11/26/2010 11/30/2010 12/09/2010 12/20/10 OFFICIAL RECORD COpy}}
DATE       12/14/2010     12/14/10   11/26/2010     11/30/2010     12/09/2010           12/20/10 OFFICIAL RECORD COpy}}

Latest revision as of 08:43, 21 March 2020

Request for Additional Information Regarding Fourth Inservice Inspection Interval Relief Requests l4R-02 and l4R-04
ML103400158
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 12/20/2010
From: Peter Bamford
Plant Licensing Branch 1
To: Pacilio M
Exelon Nuclear
Bamford, Peter J., NRR/DORL 415-2833
References
TAC ME4519, TAC ME4521
Download: ML103400158 (5)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 20, 2010 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

THREE MILE ISLAND NUCLEAR STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING FOURTH INSERV1CE INSPECTION INTERVAL RELIEF REQUESTS 14R-02 AND 14R-04 (TAC NOS. ME4519 AND ME4521)

Dear Mr. Pacilio:

By letter dated August 10, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102290162), Exelon Generation Company, LLC submitted a set of relief requests for Three Mile Island Nuclear Station, Unit 1 (TMI-1). The relief requests are all associated with the fourth Inservice Inspection (lSI) interval at TMI-1. The U.S. Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that additional information is needed to complete its review. This information request relates to Relief Requests 14R-02, "Request for Relief for Alternate Risk-Informed Selection and Examination Criteria for Examination Category B-F, B-J, C-F-1, and C-F-2 Pressure Retaining Piping Welds," and 14R-04, "Request for Relief for lSI Snubbers Included in the Technical Specifications Snubber Visual Examination and Functional Testing Program."

The NRC staff has been reviewing the response and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The questions were sent via electronic transmission on December 1,2010, and on December 8,2010, to Mr. Thomas Loomis, of your staff. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. The draft questions were discussed in a teleconference with your staff on December 14, 2010, and a minor edit was made to RAI number 1, regarding Relief Request 14R-02. It was agreed that a response to this RAI would be submitted by January 28, 2011.

Please contact me at 301-415-2833, if you have any questions.

Sd?;k~

Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-289

Enclosure:

As stated cc: Distribution via Listserv

REQUEST FOR ADDITIONAL II\lFORMATION THREE MILE ISLAND NUCLEAR STATION, UNIT 1 RELIEF REQUESTS ASSOCIATED WITH THE FOURTH INSERVICE INSPECTION INTERVAL RELIEF REQUESTS 14R-02AND 14R-04 DOCKET NO. 50-289 By letter dated August 10, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102290162), Exelon Generation Company, LLC submitted a set of relief requests for Three Mile Island Nuclear Station, Unit 1 (TMI-1).

The relief requests are all associated with the fourth Inservice Inspection (lSI) interval at TMI-1. The U.S. Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that additional information is needed to complete its review. This information request relates to Relief Requests 14R-02, "Request for Relief for Alternate Risk-Informed Selection and Examination Criteria for Examination Category B-F, B-J, C-F-1, and C-F-2 Pressure Retaining Piping Welds," and 14R-04, "Request for Relief for lSI Snubbers Included in the Technical Specifications Snubber Visual Examination and Functional Testing Program."

Relief Request 14R-02

1. The relief request includes the following paragraph:

The Risk Impact Assessment completed as part of the original baseline [Risk-Informed Inservice Inspection] RISI Program was an implementation/transition check on the initial impact of converting from a traditional [American Society of Mechanical Engineers] ASME Section XI program to the new RISI methodology. For the fourth interval lSI update, there is no transition occurring between two different methodologies, but rather, the currently approved RISI methodology and evaluation will be maintained for the new interval.

The NRC staff does not agree with the implication that, if there is no change in methodology, the change in risk assessment is not part of the living process.

Furthermore, the submittal is requesting relief to implement a RISI program instead of an ASME program for the fourth interval, so there is a change from the methodology that would normally be used (i.e., without a relief request). Electrical Power Research Institute Topical Report 112657, Revision B-A, which is cited in the application as the evaluation methodology for the RISI program, requires an evaluation of the change in risk (core damage frequency (CDF) and large early release frequency (LERF)) arising from the proposed change in the lSI program.

Please provide an estimate of the potential change in risk between the RISI program proposed for implementation in the fourth interval and the ASME Section XI requirements which existed prior to the implementation of the RISI program.

Enclosure

-2

2. The relief request states:

These portions of the RISI Program have been and will continue to be reevaluated and revised as major revisions of the site Probabilistic Risk Assessment (PRA) occur and modifications to plant configuration are made. The Consequence Evaluation, Degradation Mechanism Assessment, Risk Ranking, Element Selection, and Risk Impact Assessment steps encompass the complete living program process applied under the TMI, Unit 1 RISI Program.

Please provide the date of the last PRA reevaluation and revision that is described above, and a brief description of the results of the reevaluations and revisions undertaken at that date. Specifically, please provide the baseline CDF and the baseline LERF for the most current PRA. In addition, please explain how any modifications to the plant since the date of the last reevaluation and revision may impact the RISI program.

3. Are the inspection locations in the RISI program that have been developed for the fourth 10-year interval the same locations as those in the third interval RISI program approved in the NRC staff's November 12, 2003, safety evaluation (ADAMS Accession No. ML032930264)? If not, please summarize the changes to the program and what caused those changes.
4. If there are changes in the inspection locations for the TMI-1 fourth 1O-year interval RISI program, please provide information for the fourth interval program regarding:

examinations/system/components/degradation mechanisms/class, etc. similar to that provided in Tables 2, 3 and 4 of the original submittal of the RISI program for the TMI-1 third 1O-year lSI interval dated October 1, 2002 (ADAMS Accession No. ML022830211).

Relief Request 14R-04

1. TMI-1 Technical Specification (TS) 4.17.1 (e)(2) provides for an optional functional testing of snubbers in accordance with TMI-1 TS Figure 4.17-1. Please verify that (1) this plan is equivalent to the 37 or 55 testing sample plan of ASME/ANSl [American National Standards Institute] OM Code Part 4,1987 Edition with OMa-1988 Addendum (OM-4);

and (2) explain whether and how the requirement of additional sampling of at least one half of the size of the initial sample lot as required by OM-4, Section 3.2.3.2(b), will be met while using TMI-1 TS Figure 4.17-1. If the TS requirements do not meet the OM-4 requirements, please explain how the proposed alternative provides an acceptable level of quality and safety.

2. The requested alternative and TMI-1 TS 4.17 do not address the requirements of OM-4, Section 2.3.4.3, "Examination Failure Mode Groups," and Section 3.2.4.2, "Test Failure Mode Groups," related to examination and functional testing of snubbers. Please explain how TMI-1 TS 4.17 meets these requirements or provides an acceptable level of quality and safety.
3. ASME,Section XI, 2004 Edition, Article IWF-5000, Subsections IWF-5200(c) and IWF 5300(c), clearly state that integral and non-integral attachments for snubbers (including lugs, bolting, pins, and clamps), shall be examined in accordance with the requirements of Subsection IWF. Please explain whether and how these requirements will be met. If

-3 they will not be met, please explain how the proposed alternative provides an acceptable level of quality and safety.

4. TMI-1 TS 4.17.1 (b), footnote "**" states:

The inspection interval for each type of snubber shall not be lengthened more than one step at a time unless a generic problem has been identified and corrected; in that event the inspection interval may be lengthened one step the first time and two steps thereafter if no inoperable snubbers of that type are found.

OM-4, Section 2.3.2.3, "Subsequent Examination Schedule Adjustment," states that the time to subsequent examination shall not be lengthened more than one increment at a time. Please explain why the inspection intervals described in TMI-1 TS 4.17.1 (b) are acceptable in lieu of the examination schedule requirement noted in OM-4, Section 2.3.2.3.

5. In TMI-1 TS 4.17.1 (e), "Functional Tests", the footnote "*" states:

The four 555,000 Ib reactor coolant pump snubbers are not included.

The functional test program for reactor coolant pump snubbers is implemented in accordance with the schedule and other requirements of the snubber testing program.

Please provide details on how the reactor coolant pump snubbers will be tested as compared to the OM-4 requirements.

December 20,2010 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville,lL 60555

SUBJECT:

THREE MILE ISLAND NUCLEAR STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING FOURTH INSERVICE INSPECTION INTERVAL RELIEF REQUESTS 14R-02AND 14R-04 (TAC NOS. ME4519 AND ME4521)

Dear Mr. Pacilio:

By letter dated August 10, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102290162), Exelon Generation Company, LLC submitted a set of relief requests for Three Mile Island Nuclear Station, Unit 1 (TMI-1). The relief requests are all associated with the fourth Inservice Inspection (lSI) interval at TMI-1. The U.S. Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that additional information is needed to complete its review. This information request relates to Relief Requests 14R-02, "Request for Relief for Alternate Risk-Informed Selection and Examination Criteria for Examination Category B-F, B-J, C-F-1, and C-F-2 Pressure Retaining Piping Welds," and 14R-04, "Request for Relief for lSI Snubbers Included in the Technical Specifications Snubber Visual Examination and Functional Testing Program."

The NRC staff has been reviewing the response and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The questions were sent via electronic transmission on December 1, 2010, and on December 8, 2010, to Mr. Thomas Loomis, of your staff. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. The draft questions were discussed in a teleconference with your staff on December 14, 2010, and a minor edit was made to RAI number 1, regarding Relief Request 14R-02. It was agreed that a response to this RAI would be submitted by January 28, 2011.

Please contact me at 301-415-2833, if you have any questions.

Sincerely,

/raj Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-289

Enclosure:

As stated cc: Distribution via Listserv DISTRIBUTION:

RidsNrrPMThreeMilelsland Resource PUBLIC LPLI-2 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrDraApla Resource RidsOgcRp Resource RidsRgn1MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl1-2 Resouce RidsNrrLAABaxter Resource MOrenak, NRR RidsNrrDciCptb Resource DChung, NRR KHoffman, NRR RidsNrrDciCpnb Resource ADAMS Accession Number' ML103400158 *concurrence via email OFFICE LPL1-2/PM LPL1-2/LA APLAlBC CPTB/BC CPNB/BC LPLI-2/BC NAME PBamford ABaxter

  • DHarrison* AMcMurtray* TLupold* HChernoff (REnnis for)

DATE 12/14/2010 12/14/10 11/26/2010 11/30/2010 12/09/2010 12/20/10 OFFICIAL RECORD COpy

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