ML11293A441: Difference between revisions
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{{#Wiki_filter: | {{#Wiki_filter:Davis-BesseNPEm Resource From: CuadradoDeJesus, Samuel Sent: Tuesday, September 13, 2011 11:16 AM To: 'custerc@firstenergycorp.com'; dorts@firstenergycorp.com Cc: Davis-BesseHearingFile Resource | ||
'; dorts@firstenergycorp.com Cc: Davis-BesseHearingFile Resource | |||
==Subject:== | ==Subject:== | ||
D- RAI Related to Aging Management of Letdown Coolers/Teleconference request. | D- RAI Related to Aging Management of Letdown Coolers/Teleconference request. | ||
Attachments: | Attachments: RAI 2 3 3 18-4 Letdown Cooler Replacement Frequency -R1.doc Cliff: | ||
RAI 2 3 3 18-4 Letdown Cooler Replacement Frequency -R1.doc Cliff: | Attached is the second RAI youll be receiving in our upcoming RAI letter. Well like to have a teleconference on it as well. Let me know when can we have the teleconference. | ||
Attached is the second RAI | : Regards, Samuel Cuadrado de Jesús Project Manager Projects Branch1 Division of License Renewal U.S. Nuclear Regulatory Commission Phone: 301-415-2946 Samuel.CuadradoDeJesus@nrc.gov 1 | ||
: Regards, Samuel Cuadrado de Jesús Project Manager Projects Branch1 Division of License Renewal U.S. Nuclear Regulatory Commission | |||
Hearing Identifier: Davis_BesseLicenseRenewal_Saf_NonPublic Email Number: 1479 Mail Envelope Properties (377CB97DD54F0F4FAAC7E9FD88BCA6D0804FC13BC3) | |||
Hearing Identifier: | |||
==Subject:== | ==Subject:== | ||
D- RAI Related to Aging Management of Letdown Coolers/Teleconference request. Sent Date: | D- RAI Related to Aging Management of Letdown Coolers/Teleconference request. | ||
"'custerc@firstenergycorp.com'" <custerc@firstenergycorp.com> | Sent Date: 9/13/2011 11:15:57 AM Received Date: 9/13/2011 11:15:59 AM From: CuadradoDeJesus, Samuel Created By: Samuel.CuadradoDeJesus@nrc.gov Recipients: | ||
"Davis-BesseHearingFile Resource" <Davis-BesseHearingFile.Resource@nrc.gov> | |||
Tracking Status: None | |||
"'custerc@firstenergycorp.com'" <custerc@firstenergycorp.com> | |||
Tracking Status: None "dorts@firstenergycorp.com" <dorts@firstenergycorp.com> | |||
Tracking Status: None Post Office: HQCLSTR01.nrc.gov Files Size Date & Time MESSAGE 469 9/13/2011 11:15:59 AM RAI 2 3 3 18-4 Letdown Cooler Replacement Frequency -R1.doc 35322 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: | |||
Recipients Received: | |||
RAI 2.3.3.18-4 | RAI 2.3.3.18-4 | ||
==Background:== | |||
The response to RAI 2.3.3.18-3, in part, provided the following information: | |||
: 1) The letdown coolers performed acceptably from initial startup in 1978 until 1991, when plant personnel detected contamination in the component cooling water (CCW) system, and replaced both letdown coolers in 1993. Then, in 2009, plant personnel identified a small, active reactor coolant leak, and again replaced both letdown coolers in 2010. | : 1) The letdown coolers performed acceptably from initial startup in 1978 until 1991, when plant personnel detected contamination in the component cooling water (CCW) system, and replaced both letdown coolers in 1993. Then, in 2009, plant personnel identified a small, active reactor coolant leak, and again replaced both letdown coolers in 2010. | ||
: 2) A failure analysis had not been performed on the leaking letdown coolers to determine the specific leak location or to verify the failure mechanism because of high radiation dose rates associated with that effort. | : 2) A failure analysis had not been performed on the leaking letdown coolers to determine the specific leak location or to verify the failure mechanism because of high radiation dose rates associated with that effort. | ||
SRP-LR Section A.1.2.3.4, | SRP-LR Section A.1.2.3.4, Detection of Aging Effects states that nuclear power plants are licensed using the principles of redundancy, and diversity, and that degraded components reduce the reliability of the systems, challenge safety systems, and contribute to plant risk. | ||
The SRP-LR continues by stating that the effects of aging on a component should be managed to ensure its availability to perform its intended function(s) as designed when called upon, and notes that a program based solely on detecting component failure should not be considered as an effective aging management program for license renewal. | |||
Issue: | Issue: | ||
a) The applicant established the replacement frequency based on a qualified life, which was empirically derived using two plant-specific data points of 13 and 16 years, after identifying reactor coolant leakage into the component cooling water system. | Based on the information provided in this recent response, as well as the information provided in response to RAI 2.3.3.18-2 for the same issue, the staff did not consider that the applicant has provided sufficient bases to justify the replacement frequency of every seventh refueling outage (approximately 14 years) for the letdown coolers in the makeup and purification system. The bases for the staffs position are as follows: | ||
a) The applicant established the replacement frequency based on a qualified life, which was empirically derived using two plant-specific data points of 13 and 16 years, after identifying reactor coolant leakage into the component cooling water system. | |||
b) The applicant has not determined the flaw location, performed flaw sizing, or verified flaw characteristics to allow prediction of flaw stability or growth rate. Without having this information, operation of the letdown cooler with ongoing leakage is risking a failure, which would challenge the pressure relief capability of the component cooling water system and the isolation function of the valves in the makeup and purification system. | b) The applicant has not determined the flaw location, performed flaw sizing, or verified flaw characteristics to allow prediction of flaw stability or growth rate. Without having this information, operation of the letdown cooler with ongoing leakage is risking a failure, which would challenge the pressure relief capability of the component cooling water system and the isolation function of the valves in the makeup and purification system. | ||
c) While past operating experience (although limited) may have shown that the flaw was stable for some period of time, the replacement frequency determination did not appear to consider normal operational pressure transients that the letdown coolers would be expected to experience. | c) While past operating experience (although limited) may have shown that the flaw was stable for some period of time, the replacement frequency determination did not appear to consider normal operational pressure transients that the letdown coolers would be expected to experience. | ||
d) The letdown cooler replacement frequency appears to be based on overall calendar time and not actual operational time, considering both refueling and extended outages. | d) The letdown cooler replacement frequency appears to be based on overall calendar time and not actual operational time, considering both refueling and extended outages. | ||
Request: | Request: | ||
Provide a letdown cooler replacement frequency that includes adequate margin to initiation of tube leakage and provide the basis for the margin, or propose an aging management program that will adequately manage these components that are within the scope of license renewal.}} | Provide a letdown cooler replacement frequency that includes adequate margin to initiation of tube leakage and provide the basis for the margin, or propose an aging management program that will adequately manage these components that are within the scope of license renewal.}} | ||
Revision as of 13:10, 12 November 2019
| ML11293A441 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/13/2011 |
| From: | Office of Nuclear Reactor Regulation |
| To: | Division of License Renewal |
| References | |
| Download: ML11293A441 (4) | |
Text
Davis-BesseNPEm Resource From: CuadradoDeJesus, Samuel Sent: Tuesday, September 13, 2011 11:16 AM To: 'custerc@firstenergycorp.com'; dorts@firstenergycorp.com Cc: Davis-BesseHearingFile Resource
Subject:
D- RAI Related to Aging Management of Letdown Coolers/Teleconference request.
Attachments: RAI 2 3 3 18-4 Letdown Cooler Replacement Frequency -R1.doc Cliff:
Attached is the second RAI youll be receiving in our upcoming RAI letter. Well like to have a teleconference on it as well. Let me know when can we have the teleconference.
- Regards, Samuel Cuadrado de Jesús Project Manager Projects Branch1 Division of License Renewal U.S. Nuclear Regulatory Commission Phone: 301-415-2946 Samuel.CuadradoDeJesus@nrc.gov 1
Hearing Identifier: Davis_BesseLicenseRenewal_Saf_NonPublic Email Number: 1479 Mail Envelope Properties (377CB97DD54F0F4FAAC7E9FD88BCA6D0804FC13BC3)
Subject:
D- RAI Related to Aging Management of Letdown Coolers/Teleconference request.
Sent Date: 9/13/2011 11:15:57 AM Received Date: 9/13/2011 11:15:59 AM From: CuadradoDeJesus, Samuel Created By: Samuel.CuadradoDeJesus@nrc.gov Recipients:
"Davis-BesseHearingFile Resource" <Davis-BesseHearingFile.Resource@nrc.gov>
Tracking Status: None
"'custerc@firstenergycorp.com'" <custerc@firstenergycorp.com>
Tracking Status: None "dorts@firstenergycorp.com" <dorts@firstenergycorp.com>
Tracking Status: None Post Office: HQCLSTR01.nrc.gov Files Size Date & Time MESSAGE 469 9/13/2011 11:15:59 AM RAI 2 3 3 18-4 Letdown Cooler Replacement Frequency -R1.doc 35322 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
RAI 2.3.3.18-4
Background:
The response to RAI 2.3.3.18-3, in part, provided the following information:
- 1) The letdown coolers performed acceptably from initial startup in 1978 until 1991, when plant personnel detected contamination in the component cooling water (CCW) system, and replaced both letdown coolers in 1993. Then, in 2009, plant personnel identified a small, active reactor coolant leak, and again replaced both letdown coolers in 2010.
- 2) A failure analysis had not been performed on the leaking letdown coolers to determine the specific leak location or to verify the failure mechanism because of high radiation dose rates associated with that effort.
SRP-LR Section A.1.2.3.4, Detection of Aging Effects states that nuclear power plants are licensed using the principles of redundancy, and diversity, and that degraded components reduce the reliability of the systems, challenge safety systems, and contribute to plant risk.
The SRP-LR continues by stating that the effects of aging on a component should be managed to ensure its availability to perform its intended function(s) as designed when called upon, and notes that a program based solely on detecting component failure should not be considered as an effective aging management program for license renewal.
Issue:
Based on the information provided in this recent response, as well as the information provided in response to RAI 2.3.3.18-2 for the same issue, the staff did not consider that the applicant has provided sufficient bases to justify the replacement frequency of every seventh refueling outage (approximately 14 years) for the letdown coolers in the makeup and purification system. The bases for the staffs position are as follows:
a) The applicant established the replacement frequency based on a qualified life, which was empirically derived using two plant-specific data points of 13 and 16 years, after identifying reactor coolant leakage into the component cooling water system.
b) The applicant has not determined the flaw location, performed flaw sizing, or verified flaw characteristics to allow prediction of flaw stability or growth rate. Without having this information, operation of the letdown cooler with ongoing leakage is risking a failure, which would challenge the pressure relief capability of the component cooling water system and the isolation function of the valves in the makeup and purification system.
c) While past operating experience (although limited) may have shown that the flaw was stable for some period of time, the replacement frequency determination did not appear to consider normal operational pressure transients that the letdown coolers would be expected to experience.
d) The letdown cooler replacement frequency appears to be based on overall calendar time and not actual operational time, considering both refueling and extended outages.
Request:
Provide a letdown cooler replacement frequency that includes adequate margin to initiation of tube leakage and provide the basis for the margin, or propose an aging management program that will adequately manage these components that are within the scope of license renewal.