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{{#Wiki_filter:June 29, 2007Richard Webster, Esq.Rutgers Environmental Law Clinic 123 Washington Street Newark, NJ 07102-3094
{{#Wiki_filter:June 29, 2007 Richard Webster, Esq.
Rutgers Environmental Law Clinic 123 Washington Street Newark, NJ 07102-3094


==Dear Mr. Webster:==
==Dear Mr. Webster:==


This letter provides a response to the concerns raised in your March 30, 2007, letter whichraises additional questions about the operability of the containment drywell shell at Oyster Creek Nuclear Generating Station (Oyster Creek). In this and previous communications (Letter dated November 7, 2006, Agencywide Documents Access and Management System (ADAMS)
This letter provides a response to the concerns raised in your March 30, 2007, letter which raises additional questions about the operability of the containment drywell shell at Oyster Creek Nuclear Generating Station (Oyster Creek). In this and previous communications (Letter dated November 7, 2006, Agencywide Documents Access and Management System (ADAMS)
Accession Number ML063120572; e-mail dated November 9, 2006, ADAMS Accession Number ML070260177), you questioned the Nuclear Regulatory Commission (NRC) staff's basis for allowing restart of Oyster Creek from its most recent refueling outage (RFO 21) and the acceptability of confirmatory calculations performed by the NRC's contractor Sandia National Laboratories (SNL). The NRC responded to these communications by letters dated November 9, 2006 (ADAMS Accession No. ML063120196), and March 16, 2007 (ADAMS Accession No. ML070660182), respectively. Paragraph 4 of our March 16, 2007, letter provided a discussion of information provided in thelicensee's calculations. As a point of clarification, the NRC staff reviewed the licensee's calculations as well as confirmatory calculations performed on the NRC's behalf by SNL. The NRC staff did not perform independent calculations regarding the structural integrity of the Oyster Creek drywell shell. Therefore, no NRC-performed calculations or associated numerical assessments of uncertainty can be provided. Prior to the restart from RFO 21, the NRC staff inspected the condition of the containmentdrywell shell as well as reviewed the AmerGen Energy Company, LLC's (AmerGen's) evaluation of the drywell shell condition. The results of these activities are documented in "NRC In-Service Inspection and License Renewal Commitment Followup Inspection Report 05000219/2006013," dated January 17, 2007 (ADAMS Accession Number ML070170396). In this inspection report, the NRC staff determined that there were no safety significant conditions with respect to the primary containment that would prohibit plant startup and there was reasonable assurance that the primary containment was capable of performing its design function throughout the upcoming operating cycle. Further, the NRC staff discusses the SNL analysis and its applicability to the Oyster Creeklicensing basis analysis in the "Safety Evaluation Report Related to the License Renewal of Oyster Creek Generating Station," dated March 2007 (ADAMS Accession Number ML070890637). In this report, the NRC staff concluded that the SNL report results support and confirm that the drywell will be able to perform its intended functions in its present condition.
Accession Number ML063120572; e-mail dated November 9, 2006, ADAMS Accession Number ML070260177), you questioned the Nuclear Regulatory Commission (NRC) staffs basis for allowing restart of Oyster Creek from its most recent refueling outage (RFO 21) and the acceptability of confirmatory calculations performed by the NRCs contractor Sandia National Laboratories (SNL). The NRC responded to these communications by letters dated November 9, 2006 (ADAMS Accession No. ML063120196), and March 16, 2007 (ADAMS Accession No. ML070660182), respectively.
Also, Section 4.7.2 of the Safety Evaluation discusses the NRC staff's review of the drywell shell corrosion rate and concludes that licensee corrective actions have been successful in reducing and arresting the corrosion in the drywell shell. Conservative projections of the shell thickness to the year 2029, indicating adequate margin to the minimum wall thickness criteria, R. Webster and the licensee's drywell shell monitoring plan, which allows timely corrective action for anyfuture degradation, provide assurance that the drywell will be able to perform its design function. Additionally, in an e-mail to Mr. Richard Conte, dated June 4, 2007, and a letter datedJune 7, 2007, you included a copy of the AmerGen Calculation C-1302-187-5320-024, Revision 2. In these communications, you asserted that several areas in the sandbed region do not meet the local thinning limits and as an example, you indicated that Figure 1-7 shows such an area. This calculation is not part of the current licensing basis for Oyster Creek and has not been submitted by AmerGen for NRC staff review in conjunction with a licensing action. The NRC staff notes, however, that while Figure 1-7 depicts a 9-square-foot thinned area, Section 7.1.3.4 of the calculation indicates that the cumulative size of the ten locally thin areas measured is significantly smaller than the analyzed 9-square-foot area. The NRC staff considers the above referenced documents to be responsive to your informationrequests. If you wish to formally request the NRC to take a specific action with respect to the condition of the Oyster Creek drywell, you may do so pursuant to Title 10 of the Code ofFederal Regulations, Part 2, Section 2.206. Additional concerns may be submitted through theNRC's allegation process. For more information on this process please refer to our website (http://www.nrc.gov/about-nrc/regulatory/allegations/safety-concern.html). Sincerely,/ra/Catherine Haney, DirectorDivision of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-219 cc:  See next page R. Webster and the licensee's drywell shell monitoring plan, which allows timely corrective action for anyfuture degradation, provide assurance that the drywell will be able to perform its design function. Additionally, in an e-mail to Mr. Richard Conte, dated June 4, 2007, and a letter datedJune 7, 2007, you included a copy of the AmerGen Calculation C-1302-187-5320-024, Revision 2. In these communications, you asserted that several areas in the sandbed region do not meet the local thinning limits and as an example, you indicated that Figure 1-7 shows such an area. This calculation is not part of the current licensing basis for Oyster Creek and has not been submitted by AmerGen for NRC staff review in conjunction with a licensing action. The NRC staff notes, however, that while Figure 1-7 depicts a 9-square-foot thinned area, Section 7.1.3.4 of the calculation indicates that the cumulative size of the ten locally thin areas measured is significantly smaller than the analyzed 9-square-foot area.    . The NRC staff considers the above referenced documents to be responsive to your informationrequests. If you wish to formally request the NRC to take a specific action with respect to the condition of the Oyster Creek drywell, you may do so pursuant to Title 10 of the Code ofFederal Regulations, Part 2, Section 2.206. Additional concerns may be submitted through theNRC's allegation process. For more information on this process please refer to our website (http://www.nrc.gov/about-nrc/regulatory/allegations/safety-concern.html). Sincerely,/ra/Catherine Haney, Director Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-219 cc:  See next pageDISTRIBUTION:  Y20070094PUBLICLPL1-2 R/FRidsNrrPMGMillerRidsNrrLACBaxter RidsNrrDorlRidsOgcRpRidsAcrsAcnwMailCenterRidsNrrDorlDpr RidsRgn1MailCenterRidsNrrOdRidsNrrAdro RidsEdoMailCenterRidsOgcMailCenterRidsNrrDpr RidsOpaMailRidsOcaMailCenterRidsRgnIMailCenter RidsNrrWpcMailRidsNrrDorlLpl1-2(HChernoff)Package Accession Number:  ML071290525  Incoming Accession Number:  ML071240498 Response Accession Number:  ML071290546*Concurrence via PhoneOFFICELPL1-2/PMLPL1-2/LAR-i/DRP/PB6/BCDE/EMCB/BCOGCLPL I-2/BCDORL/D NAMEGEMillerMO'Brien*ARosebrook forRBellamy *KManolyMYoung NLOHChernoffCHaneyDATE6/29/076/29/076/28/076/29/076/29/076/29/076/29/07 OFFICIAL RECORD COPY Oyster Creek Nuclear Generating StationSite Vice President - Oyster Creek  Nuclear Generating Station AmerGen Energy Company, LLC 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
Paragraph 4 of our March 16, 2007, letter provided a discussion of information provided in the licensees calculations. As a point of clarification, the NRC staff reviewed the licensee's calculations as well as confirmatory calculations performed on the NRC's behalf by SNL. The NRC staff did not perform independent calculations regarding the structural integrity of the Oyster Creek drywell shell. Therefore, no NRC-performed calculations or associated numerical assessments of uncertainty can be provided.
Prior to the restart from RFO 21, the NRC staff inspected the condition of the containment drywell shell as well as reviewed the AmerGen Energy Company, LLCs (AmerGens) evaluation of the drywell shell condition. The results of these activities are documented in NRC In-Service Inspection and License Renewal Commitment Followup Inspection Report 05000219/2006013, dated January 17, 2007 (ADAMS Accession Number ML070170396). In this inspection report, the NRC staff determined that there were no safety significant conditions with respect to the primary containment that would prohibit plant startup and there was reasonable assurance that the primary containment was capable of performing its design function throughout the upcoming operating cycle.
Further, the NRC staff discusses the SNL analysis and its applicability to the Oyster Creek licensing basis analysis in the Safety Evaluation Report Related to the License Renewal of Oyster Creek Generating Station, dated March 2007 (ADAMS Accession Number ML070890637). In this report, the NRC staff concluded that the SNL report results support and confirm that the drywell will be able to perform its intended functions in its present condition.
Also, Section 4.7.2 of the Safety Evaluation discusses the NRC staff's review of the drywell shell corrosion rate and concludes that licensee corrective actions have been successful in reducing and arresting the corrosion in the drywell shell. Conservative projections of the shell thickness to the year 2029, indicating adequate margin to the minimum wall thickness criteria,


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
R. Webster                                      and the licensee's drywell shell monitoring plan, which allows timely corrective action for any future degradation, provide assurance that the drywell will be able to perform its design function.
Additionally, in an e-mail to Mr. Richard Conte, dated June 4, 2007, and a letter dated June 7, 2007, you included a copy of the AmerGen Calculation C-1302-187-5320-024, Revision 2. In these communications, you asserted that several areas in the sandbed region do not meet the local thinning limits and as an example, you indicated that Figure 1-7 shows such an area. This calculation is not part of the current licensing basis for Oyster Creek and has not been submitted by AmerGen for NRC staff review in conjunction with a licensing action. The NRC staff notes, however, that while Figure 1-7 depicts a 9-square-foot thinned area, Section 7.1.3.4 of the calculation indicates that the cumulative size of the ten locally thin areas measured is significantly smaller than the analyzed 9-square-foot area.
The NRC staff considers the above referenced documents to be responsive to your information requests. If you wish to formally request the NRC to take a specific action with respect to the condition of the Oyster Creek drywell, you may do so pursuant to Title 10 of the Code of Federal Regulations, Part 2, Section 2.206. Additional concerns may be submitted through the NRCs allegation process. For more information on this process please refer to our website (http://www.nrc.gov/about-nrc/regulatory/allegations/safety-concern.html).
Sincerely,
                                              /ra/
Catherine Haney, Director Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-219 cc: See next page


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 P.O. Box 445 Forked River, NJ  08731Director - Licensing and Regulatory AffairsAmerGen Energy Company, LLC Correspondence Control P.O. Box 160 Kennett Square, PA  19348Manager Licensing - Oyster CreekExelon Generation Company, LLC Correspondence Control P.O. Box 160 Kennett Square, PA  19348Regulatory Assurance Manager  Oyster Creek AmerGen Energy Company, LLC 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
R. Webster                                              and the licensee's drywell shell monitoring plan, which allows timely corrective action for any future degradation, provide assurance that the drywell will be able to perform its design function.
Additionally, in an e-mail to Mr. Richard Conte, dated June 4, 2007, and a letter dated June 7, 2007, you included a copy of the AmerGen Calculation C-1302-187-5320-024, Revision 2. In these communications, you asserted that several areas in the sandbed region do not meet the local thinning limits and as an example, you indicated that Figure 1-7 shows such an area. This calculation is not part of the current licensing basis for Oyster Creek and has not been submitted by AmerGen for NRC staff review in conjunction with a licensing action. The NRC staff notes, however, that while Figure 1-7 depicts a 9-square-foot thinned area, Section 7.1.3.4 of the calculation indicates that the cumulative size of the ten locally thin areas measured is significantly smaller than the analyzed 9-square-foot area. .
The NRC staff considers the above referenced documents to be responsive to your information requests. If you wish to formally request the NRC to take a specific action with respect to the condition of the Oyster Creek drywell, you may do so pursuant to Title 10 of the Code of Federal Regulations, Part 2, Section 2.206. Additional concerns may be submitted through the NRCs allegation process. For more information on this process please refer to our website (http://www.nrc.gov/about-nrc/regulatory/allegations/safety-concern.html).
Sincerely,
                                                    /ra/
Catherine Haney, Director Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-219 cc: See next page DISTRIBUTION: Y20070094 PUBLIC                            LPL1-2 R/F          RidsNrrPMGMiller            RidsNrrLACBaxter RidsNrrDorl                      RidsOgcRp          RidsAcrsAcnwMailCenter RidsNrrDorlDpr RidsRgn1MailCenter                RidsNrrOd          RidsNrrAdro RidsEdoMailCenter                RidsOgcMailCenter RidsNrrDpr RidsOpaMail                      RidsOcaMailCenter RidsRgnIMailCenter RidsNrrWpcMail                    RidsNrrDorlLpl1-2(HChernoff)
Package Accession Number: ML071290525 Incoming Accession Number: ML071240498 Response Accession Number: ML071290546                *Concurrence via Phone OFFICE LPL1-2/PM LPL1-2/LA R-i/DRP/PB6/BC DE/EMCB/BC OGC                      LPL I-2/BC    DORL/D NAME GEMiller        MOBrien* ARosebrook for      KManoly        MYoung HChernoff          CHaney RBellamy
* NLO DATE    6/29/07      6/29/07      6/28/07          6/29/07        6/29/07 6/29/07          6/29/07 OFFICIAL RECORD COPY


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 P.O. Box 388 Forked River, NJ 08731}}
Oyster Creek Nuclear Generating Station 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 U.S. Nuclear Regulatory Commission P.O. Box 445 Forked River, NJ 08731}}

Revision as of 06:26, 23 November 2019

Y020070094 - Response to Concerns About the Operability of the Containment Drywell Shell at Oyster Creek
ML071290546
Person / Time
Site: Oyster Creek
Issue date: 06/29/2007
From: Catherine Haney
Plant Licensing Branch III-2
To: Webster R
Rutgers Environmental Law Clinic
Miller G, NRR/DORL, 415-2481
Shared Package
ml071290525 List:
References
Y020070094
Download: ML071290546 (4)
v • d • e


Text

June 29, 2007 Richard Webster, Esq.

Rutgers Environmental Law Clinic 123 Washington Street Newark, NJ 07102-3094

Dear Mr. Webster:

This letter provides a response to the concerns raised in your March 30, 2007, letter which raises additional questions about the operability of the containment drywell shell at Oyster Creek Nuclear Generating Station (Oyster Creek). In this and previous communications (Letter dated November 7, 2006, Agencywide Documents Access and Management System (ADAMS)

Accession Number ML063120572; e-mail dated November 9, 2006, ADAMS Accession Number ML070260177), you questioned the Nuclear Regulatory Commission (NRC) staffs basis for allowing restart of Oyster Creek from its most recent refueling outage (RFO 21) and the acceptability of confirmatory calculations performed by the NRCs contractor Sandia National Laboratories (SNL). The NRC responded to these communications by letters dated November 9, 2006 (ADAMS Accession No. ML063120196), and March 16, 2007 (ADAMS Accession No. ML070660182), respectively.

Paragraph 4 of our March 16, 2007, letter provided a discussion of information provided in the licensees calculations. As a point of clarification, the NRC staff reviewed the licensee's calculations as well as confirmatory calculations performed on the NRC's behalf by SNL. The NRC staff did not perform independent calculations regarding the structural integrity of the Oyster Creek drywell shell. Therefore, no NRC-performed calculations or associated numerical assessments of uncertainty can be provided.

Prior to the restart from RFO 21, the NRC staff inspected the condition of the containment drywell shell as well as reviewed the AmerGen Energy Company, LLCs (AmerGens) evaluation of the drywell shell condition. The results of these activities are documented in NRC In-Service Inspection and License Renewal Commitment Followup Inspection Report 05000219/2006013, dated January 17, 2007 (ADAMS Accession Number ML070170396). In this inspection report, the NRC staff determined that there were no safety significant conditions with respect to the primary containment that would prohibit plant startup and there was reasonable assurance that the primary containment was capable of performing its design function throughout the upcoming operating cycle.

Further, the NRC staff discusses the SNL analysis and its applicability to the Oyster Creek licensing basis analysis in the Safety Evaluation Report Related to the License Renewal of Oyster Creek Generating Station, dated March 2007 (ADAMS Accession Number ML070890637). In this report, the NRC staff concluded that the SNL report results support and confirm that the drywell will be able to perform its intended functions in its present condition.

Also, Section 4.7.2 of the Safety Evaluation discusses the NRC staff's review of the drywell shell corrosion rate and concludes that licensee corrective actions have been successful in reducing and arresting the corrosion in the drywell shell. Conservative projections of the shell thickness to the year 2029, indicating adequate margin to the minimum wall thickness criteria,

R. Webster and the licensee's drywell shell monitoring plan, which allows timely corrective action for any future degradation, provide assurance that the drywell will be able to perform its design function.

Additionally, in an e-mail to Mr. Richard Conte, dated June 4, 2007, and a letter dated June 7, 2007, you included a copy of the AmerGen Calculation C-1302-187-5320-024, Revision 2. In these communications, you asserted that several areas in the sandbed region do not meet the local thinning limits and as an example, you indicated that Figure 1-7 shows such an area. This calculation is not part of the current licensing basis for Oyster Creek and has not been submitted by AmerGen for NRC staff review in conjunction with a licensing action. The NRC staff notes, however, that while Figure 1-7 depicts a 9-square-foot thinned area, Section 7.1.3.4 of the calculation indicates that the cumulative size of the ten locally thin areas measured is significantly smaller than the analyzed 9-square-foot area.

The NRC staff considers the above referenced documents to be responsive to your information requests. If you wish to formally request the NRC to take a specific action with respect to the condition of the Oyster Creek drywell, you may do so pursuant to Title 10 of the Code of Federal Regulations, Part 2, Section 2.206. Additional concerns may be submitted through the NRCs allegation process. For more information on this process please refer to our website (http://www.nrc.gov/about-nrc/regulatory/allegations/safety-concern.html).

Sincerely,

/ra/

Catherine Haney, Director Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-219 cc: See next page

R. Webster and the licensee's drywell shell monitoring plan, which allows timely corrective action for any future degradation, provide assurance that the drywell will be able to perform its design function.

Additionally, in an e-mail to Mr. Richard Conte, dated June 4, 2007, and a letter dated June 7, 2007, you included a copy of the AmerGen Calculation C-1302-187-5320-024, Revision 2. In these communications, you asserted that several areas in the sandbed region do not meet the local thinning limits and as an example, you indicated that Figure 1-7 shows such an area. This calculation is not part of the current licensing basis for Oyster Creek and has not been submitted by AmerGen for NRC staff review in conjunction with a licensing action. The NRC staff notes, however, that while Figure 1-7 depicts a 9-square-foot thinned area, Section 7.1.3.4 of the calculation indicates that the cumulative size of the ten locally thin areas measured is significantly smaller than the analyzed 9-square-foot area. .

The NRC staff considers the above referenced documents to be responsive to your information requests. If you wish to formally request the NRC to take a specific action with respect to the condition of the Oyster Creek drywell, you may do so pursuant to Title 10 of the Code of Federal Regulations, Part 2, Section 2.206. Additional concerns may be submitted through the NRCs allegation process. For more information on this process please refer to our website (http://www.nrc.gov/about-nrc/regulatory/allegations/safety-concern.html).

Sincerely,

/ra/

Catherine Haney, Director Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-219 cc: See next page DISTRIBUTION: Y20070094 PUBLIC LPL1-2 R/F RidsNrrPMGMiller RidsNrrLACBaxter RidsNrrDorl RidsOgcRp RidsAcrsAcnwMailCenter RidsNrrDorlDpr RidsRgn1MailCenter RidsNrrOd RidsNrrAdro RidsEdoMailCenter RidsOgcMailCenter RidsNrrDpr RidsOpaMail RidsOcaMailCenter RidsRgnIMailCenter RidsNrrWpcMail RidsNrrDorlLpl1-2(HChernoff)

Package Accession Number: ML071290525 Incoming Accession Number: ML071240498 Response Accession Number: ML071290546 *Concurrence via Phone OFFICE LPL1-2/PM LPL1-2/LA R-i/DRP/PB6/BC DE/EMCB/BC OGC LPL I-2/BC DORL/D NAME GEMiller MOBrien* ARosebrook for KManoly MYoung HChernoff CHaney RBellamy

  • NLO DATE 6/29/07 6/29/07 6/28/07 6/29/07 6/29/07 6/29/07 6/29/07 OFFICIAL RECORD COPY

Oyster Creek Nuclear Generating Station 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 U.S. Nuclear Regulatory Commission P.O. Box 445 Forked River, NJ 08731

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