ML062720210

G20060809/LTR-06-0482 - Rep. Jim Saxton, Rep. Christopher H. Smith, Rep. Robert E. Andrews, Rep. Rush Holt, Rep. Frank Pallone, Jr., and Rep. Bill Pascrell, Jr. Ltr Oyster Creek Nuclear Generating Facility

ML062720210
Person / Time
Site:	Oyster Creek
Issue date:	10/30/2006
From:	Reyes L NRC/EDO
To:	Andrews R, Holt R, Pallone F, Pascrell B, Saxton J, Casey Smith US HR (House of Representatives)
Dudley N, NRR/DLR/RLRA, 415-1154
Shared Package
ML062720203	List: ML062720210
References
G20060809, LTR-06-0482
Download: ML062720210 (13)

Text

October 30, 2006 The Honorable Jim Saxton United States House of Representatives Washington, DC 20515-3003

Dear Congressman Saxton:

I am responding to your letter to Chairman Klein dated September 26, 2006, in which you identify concerns related to the safe operation of the Oyster Creek Nuclear Generating Station (Oyster Creek). The NRC continues to implement our Reactor Oversight Process (ROP) at Oyster Creek to ensure active components and systems function as designed. In addition, the NRC is currently reviewing Oyster Creeks license renewal application to ensure that passive long-lived components and structures will be adequately managed for an additional 20 years.

With regard to the specific concerns identified in your letter, GPU Nuclear Corporation (GPU),

the former owner of Oyster Creek, identified water leakage into the drywell sand bed region during refueling outages in the mid-1980s. GPUs corrective actions included removing sand from the sand bed region and identifying drywell shell corrosion by visual inspections and approximately 1000 ultrasonic testing (UT) measurements. Further corrective actions in the early 1990s included modeling the thickness of the drywell shell to establish criteria for shell thickness, repeating UT measurement of the most corroded areas every two years, coating the drywell shell in the sand bed region to prevent further corrosion, and implementing inspection programs. In 1996, GPU determined that the corrosion rate had been arrested and decided that UT measurements would be performed in another 10 years. The NRC reviewed and approved GPUs decision.

Amergen Energy Company, LLC (the licensee), the current owner of Oyster Creek, plans to perform UT measurements on the drywell shell in the sand bed area during the refueling outage they entered on October 15, 2006. The NRC will inspect the UT measurements and the related analysis as part of the ROP for operating reactors and take regulatory action if appropriate.

For license renewal, the drywell shell is one of the passive long-lived structures that requires an aging program. The staff focused substantial technical effort in evaluating the current condition of the drywell as well as the licensees plans for monitoring the integrity of the containment structure into the future. The drywell integrity issue has been raised before the Atomic Safety and Licensing Board (ASLB) in the license renewal proceeding.

During the NRC staff review of the license renewal application, the licensee provided eleven commitments which form an integrated aging management program to identify, evaluate, and resolve issues associated with different parts of the drywell shell. The NRCs review results and the licensees commitments are contained in the Safety Evaluation Report (SER) with Open Items that was issued on August 18, 2006.

J. Saxton In addition, the NRC staff has independently developed a model of the degraded drywell using UT measurements taken on the drywell shell. The staff analyzed the pressure boundary and structural support integrity of the drywell under different accident conditions. Preliminary results of the pressure boundary analysis indicate that the stresses in the degraded drywell shell are within the American Society of Mechanical Engineers Boiler and Pressure Vessel code service level requirements.

The NRC staff believes that corrosion in the embedded region, if any, will be less severe than any corrosion in the sand bed area, since the alkalinity in the environment reduces the potential for corrosion. On the basis of analysis results from the staff model, staff has determined that even if the embedded area is corroded the pressure retention capability of the drywell shell will be maintained.

The NRC staff met with the Advisory Committee on Reactor Safeguards (ACRS) License Renewal Subcommittee on October 3, 2006, concerning the Oyster Creek SER with Open Items in general and the drywell integrity issue specifically. Members of the public had the opportunity to address the ACRS. Staff will meet again with the ACRS to discuss the results of the licensees additional UT measurements on the NRC staffs analysis.

I appreciate your interest in the safety of the Oyster Creek plant. If you have additional questions, the NRC staff would be happy to meet with you or your staff to discuss the NRCs license renewal process. Please contact me if I can be of further assistance.

Sincerely,

/RA William F. Kane Acting for/

Luis A. Reyes Executive Director for Operations

October 30, 2006 The Honorable Christopher Smith United States House of Representatives Washington, DC 20515-3003

Dear Congressman Smith:

I am responding to your letter to Chairman Klein dated September 26, 2006, in which you identify concerns related to the safe operation of the Oyster Creek Nuclear Generating Station (Oyster Creek). The NRC continues to implement our Reactor Oversight Process (ROP) at Oyster Creek to ensure active components and systems function as designed. In addition, the NRC is currently reviewing Oyster Creeks license renewal application to ensure that passive long-lived components and structures will be adequately managed for an additional 20 years.

With regard to the specific concerns identified in your letter, GPU Nuclear Corporation (GPU),

the former owner of Oyster Creek, identified water leakage into the drywell sand bed region during refueling outages in the mid-1980s. GPUs corrective actions included removing sand from the sand bed region and identifying drywell shell corrosion by visual inspections and approximately 1000 ultrasonic testing (UT) measurements. Further corrective actions in the early 1990s included modeling the thickness of the drywell shell to establish criteria for shell thickness, repeating UT measurement of the most corroded areas every two years, coating the drywell shell in the sand bed region to prevent further corrosion, and implementing inspection programs. In 1996, GPU determined that the corrosion rate had been arrested and decided that UT measurements would be performed in another 10 years. The NRC reviewed and approved GPUs decision.

Amergen Energy Company, LLC (the licensee), the current owner of Oyster Creek, plans to perform UT measurements on the drywell shell in the sand bed area during the refueling outage they entered on October 15, 2006. The NRC will inspect the UT measurements and the related analysis as part of the ROP for operating reactors and take regulatory action if appropriate.

For license renewal, the drywell shell is one of the passive long-lived structures that requires an aging program. The staff focused substantial technical effort in evaluating the current condition of the drywell as well as the licensees plans for monitoring the integrity of the containment structure into the future. The drywell integrity issue has been raised before the Atomic Safety and Licensing Board (ASLB) in the license renewal proceeding.

During the NRC staff review of the license renewal application, the licensee provided eleven commitments which form an integrated aging management program to identify, evaluate, and resolve issues associated with different parts of the drywell shell. The NRCs review results and the licensees commitments are contained in the Safety Evaluation Report (SER) with Open Items that was issued on August 18, 2006.

C. Smith In addition, the NRC staff has independently developed a model of the degraded drywell using UT measurements taken on the drywell shell. The staff analyzed the pressure boundary and structural support integrity of the drywell under different accident conditions. Preliminary results of the pressure boundary analysis indicate that the stresses in the degraded drywell shell are within the American Society of Mechanical Engineers Boiler and Pressure Vessel code service level requirements.

The NRC staff believes that corrosion in the embedded region, if any, will be less severe than any corrosion in the sand bed area, since the alkalinity in the environment reduces the potential for corrosion. On the basis of analysis results from the staff model, staff has determined that even if the embedded area is corroded the pressure retention capability of the drywell shell will be maintained.

The NRC staff met with the Advisory Committee on Reactor Safeguards (ACRS) License Renewal Subcommittee on October 3, 2006, concerning the Oyster Creek SER with Open Items in general and the drywell integrity issue specifically. Members of the public had the opportunity to address the ACRS. Staff will meet again with the ACRS to discuss the results of the licensees additional UT measurements on the NRC staffs analysis.

I appreciate your interest in the safety of the Oyster Creek plant. If you have additional questions, the NRC staff would be happy to meet with you or your staff to discuss the NRCs license renewal process. Please contact me if I can be of further assistance.

Sincerely,

/RA William F. Kane Acting for/

Luis A. Reyes Executive Director for Operations

October 30, 2006 The Honorable Robert Andrews United States House of Representatives Washington, DC 20515-3003

Dear Congressman Andrews:

I am responding to your letter to Chairman Klein dated September 26, 2006, in which you identify concerns related to the safe operation of the Oyster Creek Nuclear Generating Station (Oyster Creek). The NRC continues to implement our Reactor Oversight Process (ROP) at Oyster Creek to ensure active components and systems function as designed. In addition, the NRC is currently reviewing Oyster Creeks license renewal application to ensure that passive long-lived components and structures will be adequately managed for an additional 20 years.

With regard to the specific concerns identified in your letter, GPU Nuclear Corporation (GPU),

the former owner of Oyster Creek, identified water leakage into the drywell sand bed region during refueling outages in the mid-1980s. GPUs corrective actions included removing sand from the sand bed region and identifying drywell shell corrosion by visual inspections and approximately 1000 ultrasonic testing (UT) measurements. Further corrective actions in the early 1990s included modeling the thickness of the drywell shell to establish criteria for shell thickness, repeating UT measurement of the most corroded areas every two years, coating the drywell shell in the sand bed region to prevent further corrosion, and implementing inspection programs. In 1996, GPU determined that the corrosion rate had been arrested and decided that UT measurements would be performed in another 10 years. The NRC reviewed and approved GPUs decision.

Amergen Energy Company, LLC (the licensee), the current owner of Oyster Creek, plans to perform UT measurements on the drywell shell in the sand bed area during the refueling outage they entered on October 15, 2006. The NRC will inspect the UT measurements and the related analysis as part of the ROP for operating reactors and take regulatory action if appropriate.

For license renewal, the drywell shell is one of the passive long-lived structures that requires an aging program. The staff focused substantial technical effort in evaluating the current condition of the drywell as well as the licensees plans for monitoring the integrity of the containment structure into the future. The drywell integrity issue has been raised before the Atomic Safety and Licensing Board (ASLB) in the license renewal proceeding.

During the NRC staff review of the license renewal application, the licensee provided eleven commitments which form an integrated aging management program to identify, evaluate, and resolve issues associated with different parts of the drywell shell. The NRCs review results and the licensees commitments are contained in the Safety Evaluation Report (SER) with Open Items that was issued on August 18, 2006.

R. Andrews In addition, the NRC staff has independently developed a model of the degraded drywell using UT measurements taken on the drywell shell. The staff analyzed the pressure boundary and structural support integrity of the drywell under different accident conditions. Preliminary results of the pressure boundary analysis indicate that the stresses in the degraded drywell shell are within the American Society of Mechanical Engineers Boiler and Pressure Vessel code service level requirements.

The NRC staff believes that corrosion in the embedded region, if any, will be less severe than any corrosion in the sand bed area, since the alkalinity in the environment reduces the potential for corrosion. On the basis of analysis results from the staff model, staff has determined that even if the embedded area is corroded the pressure retention capability of the drywell shell will be maintained.

The NRC staff met with the Advisory Committee on Reactor Safeguards (ACRS) License Renewal Subcommittee on October 3, 2006, concerning the Oyster Creek SER with Open Items in general and the drywell integrity issue specifically. Members of the public had the opportunity to address the ACRS. Staff will meet again with the ACRS to discuss the results of the licensees additional UT measurements on the NRC staffs analysis.

I appreciate your interest in the safety of the Oyster Creek plant. If you have additional questions, the NRC staff would be happy to meet with you or your staff to discuss the NRCs license renewal process. Please contact me if I can be of further assistance.

Sincerely,

/RA William F. Kane Acting for/

Luis A. Reyes Executive Director for Operations

October 30, 2006 The Honorable Rush Holt United States House of Representatives Washington, DC 20515-3003

Dear Congressman Holt:

I am responding to your letter to Chairman Klein dated September 26, 2006, in which you identify concerns related to the safe operation of the Oyster Creek Nuclear Generating Station (Oyster Creek). The NRC continues to implement our Reactor Oversight Process (ROP) at Oyster Creek to ensure active components and systems function as designed. In addition, the NRC is currently reviewing Oyster Creeks license renewal application to ensure that passive long-lived components and structures will be adequately managed for an additional 20 years.

With regard to the specific concerns identified in your letter, GPU Nuclear Corporation (GPU),

the former owner of Oyster Creek, identified water leakage into the drywell sand bed region during refueling outages in the mid-1980s. GPUs corrective actions included removing sand from the sand bed region and identifying drywell shell corrosion by visual inspections and approximately 1000 ultrasonic testing (UT) measurements. Further corrective actions in the early 1990s included modeling the thickness of the drywell shell to establish criteria for shell thickness, repeating UT measurement of the most corroded areas every two years, coating the drywell shell in the sand bed region to prevent further corrosion, and implementing inspection programs. In 1996, GPU determined that the corrosion rate had been arrested and decided that UT measurements would be performed in another 10 years. The NRC reviewed and approved GPUs decision.

Amergen Energy Company, LLC (the licensee), the current owner of Oyster Creek, plans to perform UT measurements on the drywell shell in the sand bed area during the refueling outage they entered on October 15, 2006. The NRC will inspect the UT measurements and the related analysis as part of the ROP for operating reactors and take regulatory action if appropriate.

For license renewal, the drywell shell is one of the passive long-lived structures that requires an aging program. The staff focused substantial technical effort in evaluating the current condition of the drywell as well as the licensees plans for monitoring the integrity of the containment structure into the future. The drywell integrity issue has been raised before the Atomic Safety and Licensing Board (ASLB) in the license renewal proceeding.

During the NRC staff review of the license renewal application, the licensee provided eleven commitments which form an integrated aging management program to identify, evaluate, and resolve issues associated with different parts of the drywell shell. The NRCs review results and the licensees commitments are contained in the Safety Evaluation Report (SER) with Open Items that was issued on August 18, 2006.

R. Holt In addition, the NRC staff has independently developed a model of the degraded drywell using UT measurements taken on the drywell shell. The staff analyzed the pressure boundary and structural support integrity of the drywell under different accident conditions. Preliminary results of the pressure boundary analysis indicate that the stresses in the degraded drywell shell are within the American Society of Mechanical Engineers Boiler and Pressure Vessel code service level requirements.

The NRC staff believes that corrosion in the embedded region, if any, will be less severe than any corrosion in the sand bed area, since the alkalinity in the environment reduces the potential for corrosion. On the basis of analysis results from the staff model, staff has determined that even if the embedded area is corroded the pressure retention capability of the drywell shell will be maintained.

The NRC staff met with the Advisory Committee on Reactor Safeguards (ACRS) License Renewal Subcommittee on October 3, 2006, concerning the Oyster Creek SER with Open Items in general and the drywell integrity issue specifically. Members of the public had the opportunity to address the ACRS. Staff will meet again with the ACRS to discuss the results of the licensees additional UT measurements on the NRC staffs analysis.

I appreciate your interest in the safety of the Oyster Creek plant. If you have additional questions, the NRC staff would be happy to meet with you or your staff to discuss the NRCs license renewal process. Please contact me if I can be of further assistance.

Sincerely,

/RA William F. Kane Acting for/

Luis A. Reyes Executive Director for Operations

October 30, 2006 The Honorable Frank Pallone, Jr.

United States House of Representatives Washington, DC 20515-3003

Dear Congressman Pallone:

I am responding to your letter to Chairman Klein dated September 26, 2006, in which you identify concerns related to the safe operation of the Oyster Creek Nuclear Generating Station (Oyster Creek). The NRC continues to implement our Reactor Oversight Process (ROP) at Oyster Creek to ensure active components and systems function as designed. In addition, the NRC is currently reviewing Oyster Creeks license renewal application to ensure that passive long-lived components and structures will be adequately managed for an additional 20 years.

With regard to the specific concerns identified in your letter, GPU Nuclear Corporation (GPU),

the former owner of Oyster Creek, identified water leakage into the drywell sand bed region during refueling outages in the mid-1980s. GPUs corrective actions included removing sand from the sand bed region and identifying drywell shell corrosion by visual inspections and approximately 1000 ultrasonic testing (UT) measurements. Further corrective actions in the early 1990s included modeling the thickness of the drywell shell to establish criteria for shell thickness, repeating UT measurement of the most corroded areas every two years, coating the drywell shell in the sand bed region to prevent further corrosion, and implementing inspection programs. In 1996, GPU determined that the corrosion rate had been arrested and decided that UT measurements would be performed in another 10 years. The NRC reviewed and approved GPUs decision.

Amergen Energy Company, LLC (the licensee), the current owner of Oyster Creek, plans to perform UT measurements on the drywell shell in the sand bed area during the refueling outage they entered on October 15, 2006. The NRC will inspect the UT measurements and the related analysis as part of the ROP for operating reactors and take regulatory action if appropriate.

For license renewal, the drywell shell is one of the passive long-lived structures that requires an aging program. The staff focused substantial technical effort in evaluating the current condition of the drywell as well as the licensees plans for monitoring the integrity of the containment structure into the future. The drywell integrity issue has been raised before the Atomic Safety and Licensing Board (ASLB) in the license renewal proceeding.

During the NRC staff review of the license renewal application, the licensee provided eleven commitments which form an integrated aging management program to identify, evaluate, and resolve issues associated with different parts of the drywell shell. The NRCs review results and the licensees commitments are contained in the Safety Evaluation Report (SER) with Open Items that was issued on August 18, 2006.

F. Pallone In addition, the NRC staff has independently developed a model of the degraded drywell using UT measurements taken on the drywell shell. The staff analyzed the pressure boundary and structural support integrity of the drywell under different accident conditions. Preliminary results of the pressure boundary analysis indicate that the stresses in the degraded drywell shell are within the American Society of Mechanical Engineers Boiler and Pressure Vessel code service level requirements.

The NRC staff believes that corrosion in the embedded region, if any, will be less severe than any corrosion in the sand bed area, since the alkalinity in the environment reduces the potential for corrosion. On the basis of analysis results from the staff model, staff has determined that even if the embedded area is corroded the pressure retention capability of the drywell shell will be maintained.

The NRC staff met with the Advisory Committee on Reactor Safeguards (ACRS) License Renewal Subcommittee on October 3, 2006, concerning the Oyster Creek SER with Open Items in general and the drywell integrity issue specifically. Members of the public had the opportunity to address the ACRS. Staff will meet again with the ACRS to discuss the results of the licensees additional UT measurements on the NRC staffs analysis.

I appreciate your interest in the safety of the Oyster Creek plant. If you have additional questions, the NRC staff would be happy to meet with you or your staff to discuss the NRCs license renewal process. Please contact me if I can be of further assistance.

Sincerely,

/RA William F. Kane Acting for/

Luis A. Reyes Executive Director for Operations

October 30, 2006 The Honorable Bill Pascrell, Jr.

United States House of Representatives Washington, DC 20515-3003

Dear Congressman Pascrell:

I am responding to your letter to Chairman Klein dated September 26, 2006, in which you identify concerns related to the safe operation of the Oyster Creek Nuclear Generating Station (Oyster Creek). The NRC continues to implement our Reactor Oversight Process (ROP) at Oyster Creek to ensure active components and systems function as designed. In addition, the NRC is currently reviewing Oyster Creeks license renewal application to ensure that passive long-lived components and structures will be adequately managed for an additional 20 years.

With regard to the specific concerns identified in your letter, GPU Nuclear Corporation (GPU),

the former owner of Oyster Creek, identified water leakage into the drywell sand bed region during refueling outages in the mid-1980s. GPUs corrective actions included removing sand from the sand bed region and identifying drywell shell corrosion by visual inspections and approximately 1000 ultrasonic testing (UT) measurements. Further corrective actions in the early 1990s included modeling the thickness of the drywell shell to establish criteria for shell thickness, repeating UT measurement of the most corroded areas every two years, coating the drywell shell in the sand bed region to prevent further corrosion, and implementing inspection programs. In 1996, GPU determined that the corrosion rate had been arrested and decided that UT measurements would be performed in another 10 years. The NRC reviewed and approved GPUs decision.

Amergen Energy Company, LLC (the licensee), the current owner of Oyster Creek, plans to perform UT measurements on the drywell shell in the sand bed area during the refueling outage they entered on October 15, 2006. The NRC will inspect the UT measurements and the related analysis as part of the ROP for operating reactors and take regulatory action if appropriate.

For license renewal, the drywell shell is one of the passive long-lived structures that requires an aging program. The staff focused substantial technical effort in evaluating the current condition of the drywell as well as the licensees plans for monitoring the integrity of the containment structure into the future. The drywell integrity issue has been raised before the Atomic Safety and Licensing Board (ASLB) in the license renewal proceeding.

During the NRC staff review of the license renewal application, the licensee provided eleven commitments which form an integrated aging management program to identify, evaluate, and resolve issues associated with different parts of the drywell shell. The NRCs review results and the licensees commitments are contained in the Safety Evaluation Report (SER) with Open Items that was issued on August 18, 2006.

B. Pascrell In addition, the NRC staff has independently developed a model of the degraded drywell using UT measurements taken on the drywell shell. The staff analyzed the pressure boundary and structural support integrity of the drywell under different accident conditions. Preliminary results of the pressure boundary analysis indicate that the stresses in the degraded drywell shell are within the American Society of Mechanical Engineers Boiler and Pressure Vessel code service level requirements.

The NRC staff believes that corrosion in the embedded region, if any, will be less severe than any corrosion in the sand bed area, since the alkalinity in the environment reduces the potential for corrosion. On the basis of analysis results from the staff model, staff has determined that even if the embedded area is corroded the pressure retention capability of the drywell shell will be maintained.

The NRC staff met with the Advisory Committee on Reactor Safeguards (ACRS) License Renewal Subcommittee on October 3, 2006, concerning the Oyster Creek SER with Open Items in general and the drywell integrity issue specifically. Members of the public had the opportunity to address the ACRS. Staff will meet again with the ACRS to discuss the results of the licensees additional UT measurements on the NRC staffs analysis.

I appreciate your interest in the safety of the Oyster Creek plant. If you have additional questions, the NRC staff would be happy to meet with you or your staff to discuss the NRCs license renewal process. Please contact me if I can be of further assistance.

Sincerely,

/RA William F. Kane Acting for/

Luis A. Reyes Executive Director for Operations

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DATE 10/06/06 10/06/06 10/30/06 10/30/06