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=Text=
=Text=
{{#Wiki_filter:February 24, 2006LICENSEE:AmerGen Energy Company, LLC FACILITY:Oyster Creek Nuclear Generating Station
{{#Wiki_filter:February 24, 2006 LICENSEE:     AmerGen Energy Company, LLC FACILITY:     Oyster Creek Nuclear Generating Station


==SUBJECT:==
==SUBJECT:==


==SUMMARY==
==SUMMARY==
OF A TELEPHONE CONFERENCE CALL HELD ON JANUARY 26, 2006, BETWEEN THE U.S. NUCLEAR REGULATORYCOMMISSION AND AMERGEN ENERGY COMPANY, LLC, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE OYSTER CREEK NUCLEAR GENERATING STATION, LICENSE RENEWALAPPLICATIONThe U.S. Nuclear Regulatory Commission staff (NRC or the staff), and representatives ofAmerGen Energy Company, LLC (AmerGen), held a telephone conference call on January 26, 2006, to discuss and clarify the staff's draft request for additional information (D-RAI) concerning the Oyster Creek Nuclear Generating Station license renewal application(LRA). The conference call was useful in clarifying the intent of the staff's D-RAI.Enclosure 1 provides a listing of the conference call participants. Enclosure 2 contains a listingof the D-RAI discussed with the applicant, including a brief description on the status of the items.The applicant had an opportunity to comment on this summary./RA LLund for/Donnie J. Ashley, Project ManagerLicense Renewal Branch A Division of License Renewal Office of Nuclear Reactor RegulationDocket No. 50-219
OF A TELEPHONE CONFERENCE CALL HELD ON JANUARY 26, 2006, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND AMERGEN ENERGY COMPANY, LLC, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE OYSTER CREEK NUCLEAR GENERATING STATION, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission staff (NRC or the staff), and representatives of AmerGen Energy Company, LLC (AmerGen), held a telephone conference call on January 26, 2006, to discuss and clarify the staffs draft request for additional information (D-RAI) concerning the Oyster Creek Nuclear Generating Station license renewal application (LRA). The conference call was useful in clarifying the intent of the staffs D-RAI. provides a listing of the conference call participants. Enclosure 2 contains a listing of the D-RAI discussed with the applicant, including a brief description on the status of the items.
The applicant had an opportunity to comment on this summary.
                                        /RA LLund for/
Donnie J. Ashley, Project Manager License Renewal Branch A Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-219


==Enclosures:==
==Enclosures:==
As statedcc w/encls:  See next page


DOCUMENT NAME:  E:\Filenet\ML060580345.wpdOFFICEPM:RLRALA:RLRABC:RLRANAMEDAshleyYEdmonds LLund DATE2/10/062/10/062/24/06 Oyster Creek Nuclear Generating Station cc:Site Vice President - Oyster Creek  Nuclear Generating Station AmerGen Energy Company, LLC
As stated cc w/encls: See next page


P.O. Box 388 Forked River, NJ  08731Senior Vice President  of  Operations AmerGen Energy Company, LLC 200 Exelon Way, KSA 3-N Kennett Square, PA  19348Kathryn M. Sutton, EsquireMorgan, Lewis, & Bockius LLP 1111 Pennsylvania Avenue, NW Washington, DC  20004Kent Tosch, ChiefNew Jersey Department of Environmental Protection Bureau of Nuclear Engineering CN 415 Trenton, NJ  08625Vice President - Licensing and  Regulatory Affairs AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555Regional Administrator, Region IU.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA  19406-1415Mayor of Lacey Township818 West Lacey Road Forked River, NJ  08731Senior Resident InspectorU.S. Nuclear Regulatory Commission
DOCUMENT NAME: E:\Filenet\ML060580345.wpd OFFICE    PM:RLRA                LA:RLRA                  BC:RLRA NAME      DAshley                YEdmonds                LLund DATE      2/10/06                2/10/06                  2/24/06


P.O. Box 445 Forked River, NJ 08731Director - Licensing and Regulatory AffairsAmerGen Energy Company, LLC Correspondence Control
Oyster Creek Nuclear Generating Station cc:
Site Vice President - Oyster Creek      Director - Licensing and Regulatory Affairs Nuclear Generating Station            AmerGen Energy Company, LLC AmerGen Energy Company, LLC            Correspondence Control P.O. Box 388                            P.O. Box 160 Forked River, NJ 08731                  Kennett Square, PA 19348 Senior Vice President of                Manager Licensing - Oyster Creek Operations                            Exelon Generation Company, LLC AmerGen Energy Company, LLC            Correspondence Control 200 Exelon Way, KSA 3-N                P.O. Box 160 Kennett Square, PA 19348                Kennett Square, PA 19348 Kathryn M. Sutton, Esquire              Regulatory Assurance Manager Morgan, Lewis, & Bockius LLP            Oyster Creek 1111 Pennsylvania Avenue, NW            AmerGen Energy Company, LLC Washington, DC 20004                    P.O. Box 388 Forked River, NJ 08731 Kent Tosch, Chief New Jersey Department of                Assistant General Counsel Environmental Protection              AmerGen Energy Company, LLC Bureau of Nuclear Engineering          200 Exelon Way CN 415                                  Kennett Square, PA 19348 Trenton, NJ 08625 Ron Bellamy, Region I Vice President - Licensing and         U.S. Nuclear Regulatory Commission Regulatory Affairs                    475 Allendale Road AmerGen Energy Company, LLC             King of Prussia, PA 19406-1415 4300 Winfield Road Warrenville, IL 60555                  Correspondence Control Desk AmerGen Energy Company, LLC Regional Administrator, Region I        200 Exelon Way, KSA 1--1 U.S. Nuclear Regulatory Commission      Kennett Square, PA 19348 475 Allendale Road King of Prussia, PA 19406-1415          Oyster Creek Nuclear Generating Station Plant Manager Mayor of Lacey Township                AmerGen Energy Company, LLC 818 West Lacey Road                    P.O. Box 388 Forked River, NJ 08731                  Forked River, NJ 08731 Senior Resident Inspector              License Renewal Manager U.S. Nuclear Regulatory Commission      Exelon Generation Company, LLC P.O. Box 445                            200 Exelon Way, Suite 210 Forked River, NJ 08731                  Kennett Square, PA 19348


P.O. Box 160 Kennett Square, PA  19348Manager Licensing - Oyster CreekExelon Generation Company, LLC Correspondence Control
Oyster Creek Nuclear Generating Station cc:
Mr. James Ross Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708


P.O. Box 160 Kennett Square, PA  19348Regulatory Assurance Manager  Oyster Creek AmerGen Energy Company, LLC
Letter to Licensee AmerGen Energy Company from Donnie Ashley dated February 24, 2006


P.O. Box 388 Forked River, NJ 08731Assistant General CounselAmerGen Energy Company, LLC 200 Exelon Way Kennett Square, PA  19348Ron Bellamy, Region IU.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA  19406-1415Correspondence Control DeskAmerGen Energy Company, LLC 200 Exelon Way, KSA 1--1 Kennett Square, PA  19348Oyster Creek Nuclear Generating StationPlant Manager AmerGen Energy Company, LLC
==SUBJECT:==


P.O. Box 388 Forked River, NJ  08731License Renewal ManagerExelon Generation Company, LLC 200 Exelon Way, Suite 210 Kennett Square, PA  19348 Oyster Creek Nuclear Generating Station        cc:
==SUMMARY==
Mr. James RossNuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC  20006-3708 Letter to Licensee AmerGen Energy Company from Donnie Ashley dated February 24, 2006
OF A TELEPHONE CONFERENCE CALL HELD ON JANUARY 26, 2006, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND AMERGEN ENERGY COMPANY, LLC, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE OYSTER CREEK NUCLEAR GENERATING STATION, LICENSE RENEWAL APPLICATION Adams accession no.: ML060580345 DISTRIBUTION:
HARD COPY DLR R/F E-MAIL:
SSmith (srs3)
RidsNrrDrip RidsNrrDe RidsNrrDss RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDci RidsNrrDnrl RidsNrrDeEeeb RidsNrrDeEqva RidsNrrDeEqvb RidsNrrDeEemb RidsOgcMailCenter RidsNrrDssSbpb RidsResDetErab RidsAcrsAcnwMailCenter DLR R/F
-------------
RLaufer GMiller RBellamy, RI RCureton, RI JLilliendahl, RI MModes, RI MSykes, RI AHodgdon OPA


==SUBJECT:==
LIST OF PARTICIPANTS FOR TELEPHONE CONFERENCE CALL TO DISCUSS THE OYSTER CREEK NUCLEAR GENERATING STATION LICENSE RENEWAL APPLICATION January 26, 2006 Participants                  Affiliations Donnie Ashley                  U.S. Nuclear Regulatory Commission (NRC)
Kenneth Chang                  NRC Roy Mathew                    NRC James Davis                    NRC Dan Hoang                      NRC Kiyoto Tanabe                  NRC Rich Morante                  NRC/Brookhaven National Laboratories Michael Gallagher              AmerGen Energy Company, LLC (AmerGen)
Fred Polaski                  AmerGen Don Warfel                    AmerGen John Hufnagel                  AmerGen Mike Guthrie                  AmerGen Peter Tamburro                AmerGen Tom Quintenz                  AmerGen Howie Ray                      AmerGen Ron Zak                        New Jersey Department of Environmental Protection Enclosure 1
 
DRAFT REQUESTS FOR ADDITIONAL INFORMATION (D-RAI)
OYSTER CREEK NUCLEAR GENERATING STATION LICENSE RENEWAL APPLICATION January 26, 2006 The U.S. Nuclear Regulatory Commission staff (NRC or the staff) and representatives of AmerGen Energy Company, LLC (AmerGen), held a telephone conference call on January 26, 2006, to discuss and clarify the staffs draft request for additional information (D-RAI) concerning the Oyster Creek Nuclear Generating Station license renewal application (LRA).
The following D-RAIs were discussed during the telephone conference call.
D-RAI 4.7.2-1 Based on the monitoring of the drywell thickness to date, the applicant is requested to provide the following information:
(a)    For the drywell corrosion existing during the late 1980s, and the new corrosion found during the subsequent inspections, provide the process used to establish confidence that the sampling done and the areas considered for identifying the areas of corrosion have been adequate.
(b)    Provide a summary of the factors considered in establishing the minimum required drywell thickness at various elevations of the drywell.
(c)    Reference 4.8-21 cited in the application discusses pros and cons of various methods of mitigating the drywell shell corrosion. Provide a summary of the actual mitigating actions taken and their effectiveness.
(d)    Provide a comparative graph (or chart) showing the drywell thickness based on the assumed corrosion rate and the actual corrosion rate found after the mitigating actions were implemented.
Discussion: Licensee understands the question and will provide a response.
D-RAI 4.7.2-2 A number of Mark I containments have experienced corrosion inside their drywells at the junction of the bottom concrete floor and the steel shell. The applicant is requested to provide information regarding corrosion of the drywell shell at this location or any other location of the drywell inside surfaces.
Discussion: Licensee understands the question and will provide a response.
D-RAI 4.7.2-3 Leakage from the refueling seal has been identified as one of the reasons for accumulation of water and contamination of the sand-pocket area. The refueling water passes through the gap Enclosure 2


==SUMMARY==
between the shield concrete and the drywell shell in the long length of inaccessible areas. As there is a potential for corrosion in this area, Subsection IWE of the ASME code would require augmented inspection of this area. The applicant is requested to provide a summary of inspections performed (visual and NDE) and mitigating actions taken to prevent water leaks from the refueling seal components.
OF A TELEPHONE CONFERENCE CALL HELD ON JANUARY 26, 2006, BETWEEN THE U.S. NUCLEAR REGULATORYCOMMISSION AND AMERGEN ENERGY COMPANY, LLC, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE OYSTER CREEK NUCLEAR GENERATING STATION, LICENSE RENEWALAPPLICATIONAdams accession no.: ML060580345DISTRIBUTION
Discussion: Licensee understands the question and will provide a response.
:HARD COPYDLR R/FE-MAIL:SSmith (srs3)RidsNrrDrip RidsNrrDe RidsNrrDss RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDci RidsNrrDnrl RidsNrrDeEeeb RidsNrrDeEqva RidsNrrDeEqvb RidsNrrDeEemb RidsOgcMailCenter RidsNrrDssSbpb RidsResDetErab RidsAcrsAcnwMailCenter DLR R/F
D-RAI 4.7.2-4 The industry-wide operating experience indicates a number of incidences of torus corrosion in Mark I containments. Neither Table 3.5.2.1.1, nor AMP B.1.27, describes operating experience related to corrosion of the Oyster Creek torus. The applicant is requested to provide a summary of the results of IWE inspections performed on the torus, and a description of the torus condition.
-------------RLauferGMiller RBellamy, RI RCureton, RI JLilliendahl, RIMModes, RI MSykes, RI AHodgdon OPA  LIST OF PARTICIPANTS FOR TELEPHONE CONFERENCE CALLTO DISCUSS THE OYSTER CREEK NUCLEAR GENERATING STATIONLICENSE RENEWAL APPLICATIONJanuary 26, 2006Participants                                      AffiliationsDonnie AshleyU.S. Nuclear Regulatory Commission (NRC)Kenneth ChangNRC Roy MathewNRC James DavisNRC Dan HoangNRC Kiyoto TanabeNRC Rich MoranteNRC/Brookhaven National LaboratoriesMichael GallagherAmerGen Energy Company, LLC (AmerGen)
Discussion: Licensee understands the question and will provide a response.
Fred PolaskiAmerGen Don WarfelAmerGen John HufnagelAmerGen Mike GuthrieAmerGen Peter TamburroAmerGen Tom QuintenzAmerGen Howie RayAmerGen Ron ZakNew Jersey Department of Environmental Protection  DRAFT REQUESTS FOR ADDITIONAL INFORMATION (D-RAI)OYSTER CREEK NUCLEAR GENERATING STATIONLICENSE RENEWAL APPLICATIONJanuary 26, 2006The U.S. Nuclear Regulatory Commission staff (NRC or the staff) and representatives ofAmerGen Energy Company, LLC (AmerGen), held a telephone conference call on January 26, 2006, to discuss and clarify the staff's draft request for additional information (D-RAI) concerning the Oyster Creek Nuclear Generating Station license renewal application (LRA). The following D-RAIs were discussed during the telephone conference call.D-RAI 4.7.2-1Based on the monitoring of the drywell thickness to date, the applicant is requested to providethe following information:(a)For the drywell corrosion existing during the late 1980s, and the new corrosionfound during the subsequent inspections, provide the process used to establish confidence that the sampling done and the areas considered for identifying the areas of corrosion have been adequate.(b)Provide a summary of the factors considered in establishing the minimumrequired drywell thickness at various elevations of the drywell.(c)Reference 4.8-21 cited in the application discusses pros and cons of variousmethods of mitigating the drywell shell corrosion. Provide a summary of the actual mitigating actions taken and their effectiveness.(d)Provide a comparative graph (or chart) showing the drywell thickness based onthe assumed corrosion rate and the actual corrosion rate found after the mitigating actions were implemented.Discussion:  Licensee understands the question and will provide a response.D-RAI 4.7.2-2A number of Mark I containments have experienced corrosion inside their drywells at thejunction of the bottom concrete floor and the steel shell. The applicant is requested to provide information regarding corrosion of the drywell shell at this location or any other location of the drywell inside surfaces.Discussion:  Licensee understands the question and will provide a response.D-RAI 4.7.2-3Leakage from the refueling seal has been identified as one of the reasons for accumulation ofwater and contamination of the sand-pocket area. The refueling water passes through the gap  between the shield concrete and the drywell shell in the long length of inaccessible areas. Asthere is a potential for corrosion in this area, Subsection IWE of the ASME code would require augmented inspection of this area. The applicant is requested to provide a summary of inspections performed (visual and NDE) and mitigating actions taken to prevent water leaks from the refueling seal components.Discussion: Licensee understands the question and will provide a response.D-RAI 4.7.2-4The industry-wide operating experience indicates a number of incidences of torus corrosion inMark I containments. Neither Table 3.5.2.1.1, nor AMP B.1.27, describes operating experiencerelated to corrosion of the Oyster Creek torus. The applicant is requested to provide a summary of the results of IWE inspections performed on the torus, and a description of the torus condition.Discussion: Licensee understands the question and will provide a response.D-RAI 4.7.2-5The staff believes that for this important issue, the updated final safety analysis report (UFSAR)Supplement, should, as a minimum, briefly describe the quantitative aspect of the drywell corrosion, and the applicant's plans to maintain it above a certain thickness to ensure that the containment could perform its intended function during the period of extended operation. Thetime-limited aging analysis (TLAA) and Subsection IWE of the ASME code are the procedures by which the licensee will maintain the containment functionality.Discussion: Licensee understands the question and will provide a response.}}
D-RAI 4.7.2-5 The staff believes that for this important issue, the updated final safety analysis report (UFSAR)
Supplement, should, as a minimum, briefly describe the quantitative aspect of the drywell corrosion, and the applicants plans to maintain it above a certain thickness to ensure that the containment could perform its intended function during the period of extended operation. The time-limited aging analysis (TLAA) and Subsection IWE of the ASME code are the procedures by which the licensee will maintain the containment functionality.
Discussion: Licensee understands the question and will provide a response.
                                                  }}

Revision as of 22:58, 23 November 2019

2006/02/24-Summary of a Telephone Conference Call Held on 01/26/2006, Between the U.S. Nuclear Regulatory Commission & Amergen Energy Company, LLC, Concerning Draft Request for Additional Information, Pertaining to the Oyster Creek Nuclear
ML060580345
Person / Time
Site: Oyster Creek
Issue date: 02/24/2006
From: Ashley D
NRC/NRR/ADRO/DLR/RLRA
To:
AmerGen Energy Co
Ashley D, NRR/DLR/RLRA, 415-3191
References
%dam200604, TAC MC7624
Download: ML060580345 (8)


Text

February 24, 2006 LICENSEE: AmerGen Energy Company, LLC FACILITY: Oyster Creek Nuclear Generating Station

SUBJECT:

SUMMARY

OF A TELEPHONE CONFERENCE CALL HELD ON JANUARY 26, 2006, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND AMERGEN ENERGY COMPANY, LLC, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE OYSTER CREEK NUCLEAR GENERATING STATION, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission staff (NRC or the staff), and representatives of AmerGen Energy Company, LLC (AmerGen), held a telephone conference call on January 26, 2006, to discuss and clarify the staffs draft request for additional information (D-RAI) concerning the Oyster Creek Nuclear Generating Station license renewal application (LRA). The conference call was useful in clarifying the intent of the staffs D-RAI. provides a listing of the conference call participants. Enclosure 2 contains a listing of the D-RAI discussed with the applicant, including a brief description on the status of the items.

The applicant had an opportunity to comment on this summary.

/RA LLund for/

Donnie J. Ashley, Project Manager License Renewal Branch A Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-219

Enclosures:

As stated cc w/encls: See next page

DOCUMENT NAME: E:\Filenet\ML060580345.wpd OFFICE PM:RLRA LA:RLRA BC:RLRA NAME DAshley YEdmonds LLund DATE 2/10/06 2/10/06 2/24/06

Oyster Creek Nuclear Generating Station cc:

Site Vice President - Oyster Creek Director - Licensing and Regulatory Affairs Nuclear Generating Station AmerGen Energy Company, LLC AmerGen Energy Company, LLC Correspondence Control P.O. Box 388 P.O. Box 160 Forked River, NJ 08731 Kennett Square, PA 19348 Senior Vice President of Manager Licensing - Oyster Creek Operations Exelon Generation Company, LLC AmerGen Energy Company, LLC Correspondence Control 200 Exelon Way, KSA 3-N P.O. Box 160 Kennett Square, PA 19348 Kennett Square, PA 19348 Kathryn M. Sutton, Esquire Regulatory Assurance Manager Morgan, Lewis, & Bockius LLP Oyster Creek 1111 Pennsylvania Avenue, NW AmerGen Energy Company, LLC Washington, DC 20004 P.O. Box 388 Forked River, NJ 08731 Kent Tosch, Chief New Jersey Department of Assistant General Counsel Environmental Protection AmerGen Energy Company, LLC Bureau of Nuclear Engineering 200 Exelon Way CN 415 Kennett Square, PA 19348 Trenton, NJ 08625 Ron Bellamy, Region I Vice President - Licensing and U.S. Nuclear Regulatory Commission Regulatory Affairs 475 Allendale Road AmerGen Energy Company, LLC King of Prussia, PA 19406-1415 4300 Winfield Road Warrenville, IL 60555 Correspondence Control Desk AmerGen Energy Company, LLC Regional Administrator, Region I 200 Exelon Way, KSA 1--1 U.S. Nuclear Regulatory Commission Kennett Square, PA 19348 475 Allendale Road King of Prussia, PA 19406-1415 Oyster Creek Nuclear Generating Station Plant Manager Mayor of Lacey Township AmerGen Energy Company, LLC 818 West Lacey Road P.O. Box 388 Forked River, NJ 08731 Forked River, NJ 08731 Senior Resident Inspector License Renewal Manager U.S. Nuclear Regulatory Commission Exelon Generation Company, LLC P.O. Box 445 200 Exelon Way, Suite 210 Forked River, NJ 08731 Kennett Square, PA 19348

Oyster Creek Nuclear Generating Station cc:

Mr. James Ross Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708

Letter to Licensee AmerGen Energy Company from Donnie Ashley dated February 24, 2006

SUBJECT:

SUMMARY

OF A TELEPHONE CONFERENCE CALL HELD ON JANUARY 26, 2006, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND AMERGEN ENERGY COMPANY, LLC, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE OYSTER CREEK NUCLEAR GENERATING STATION, LICENSE RENEWAL APPLICATION Adams accession no.: ML060580345 DISTRIBUTION:

HARD COPY DLR R/F E-MAIL:

SSmith (srs3)

RidsNrrDrip RidsNrrDe RidsNrrDss RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDci RidsNrrDnrl RidsNrrDeEeeb RidsNrrDeEqva RidsNrrDeEqvb RidsNrrDeEemb RidsOgcMailCenter RidsNrrDssSbpb RidsResDetErab RidsAcrsAcnwMailCenter DLR R/F


RLaufer GMiller RBellamy, RI RCureton, RI JLilliendahl, RI MModes, RI MSykes, RI AHodgdon OPA

LIST OF PARTICIPANTS FOR TELEPHONE CONFERENCE CALL TO DISCUSS THE OYSTER CREEK NUCLEAR GENERATING STATION LICENSE RENEWAL APPLICATION January 26, 2006 Participants Affiliations Donnie Ashley U.S. Nuclear Regulatory Commission (NRC)

Kenneth Chang NRC Roy Mathew NRC James Davis NRC Dan Hoang NRC Kiyoto Tanabe NRC Rich Morante NRC/Brookhaven National Laboratories Michael Gallagher AmerGen Energy Company, LLC (AmerGen)

Fred Polaski AmerGen Don Warfel AmerGen John Hufnagel AmerGen Mike Guthrie AmerGen Peter Tamburro AmerGen Tom Quintenz AmerGen Howie Ray AmerGen Ron Zak New Jersey Department of Environmental Protection Enclosure 1

DRAFT REQUESTS FOR ADDITIONAL INFORMATION (D-RAI)

OYSTER CREEK NUCLEAR GENERATING STATION LICENSE RENEWAL APPLICATION January 26, 2006 The U.S. Nuclear Regulatory Commission staff (NRC or the staff) and representatives of AmerGen Energy Company, LLC (AmerGen), held a telephone conference call on January 26, 2006, to discuss and clarify the staffs draft request for additional information (D-RAI) concerning the Oyster Creek Nuclear Generating Station license renewal application (LRA).

The following D-RAIs were discussed during the telephone conference call.

D-RAI 4.7.2-1 Based on the monitoring of the drywell thickness to date, the applicant is requested to provide the following information:

(a) For the drywell corrosion existing during the late 1980s, and the new corrosion found during the subsequent inspections, provide the process used to establish confidence that the sampling done and the areas considered for identifying the areas of corrosion have been adequate.

(b) Provide a summary of the factors considered in establishing the minimum required drywell thickness at various elevations of the drywell.

(c) Reference 4.8-21 cited in the application discusses pros and cons of various methods of mitigating the drywell shell corrosion. Provide a summary of the actual mitigating actions taken and their effectiveness.

(d) Provide a comparative graph (or chart) showing the drywell thickness based on the assumed corrosion rate and the actual corrosion rate found after the mitigating actions were implemented.

Discussion: Licensee understands the question and will provide a response.

D-RAI 4.7.2-2 A number of Mark I containments have experienced corrosion inside their drywells at the junction of the bottom concrete floor and the steel shell. The applicant is requested to provide information regarding corrosion of the drywell shell at this location or any other location of the drywell inside surfaces.

Discussion: Licensee understands the question and will provide a response.

D-RAI 4.7.2-3 Leakage from the refueling seal has been identified as one of the reasons for accumulation of water and contamination of the sand-pocket area. The refueling water passes through the gap Enclosure 2

between the shield concrete and the drywell shell in the long length of inaccessible areas. As there is a potential for corrosion in this area, Subsection IWE of the ASME code would require augmented inspection of this area. The applicant is requested to provide a summary of inspections performed (visual and NDE) and mitigating actions taken to prevent water leaks from the refueling seal components.

Discussion: Licensee understands the question and will provide a response.

D-RAI 4.7.2-4 The industry-wide operating experience indicates a number of incidences of torus corrosion in Mark I containments. Neither Table 3.5.2.1.1, nor AMP B.1.27, describes operating experience related to corrosion of the Oyster Creek torus. The applicant is requested to provide a summary of the results of IWE inspections performed on the torus, and a description of the torus condition.

Discussion: Licensee understands the question and will provide a response.

D-RAI 4.7.2-5 The staff believes that for this important issue, the updated final safety analysis report (UFSAR)

Supplement, should, as a minimum, briefly describe the quantitative aspect of the drywell corrosion, and the applicants plans to maintain it above a certain thickness to ensure that the containment could perform its intended function during the period of extended operation. The time-limited aging analysis (TLAA) and Subsection IWE of the ASME code are the procedures by which the licensee will maintain the containment functionality.

Discussion: Licensee understands the question and will provide a response.