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{{#Wiki_filter:Preliminary Notification DCS No.: 0500021911XX08 Date:. November 17, 2008 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE PNO-1-08-XXX Facility Licensee Emergency Classification AmerGen Energy Company, LLC __ Notification of Unusual Event Oyster Creek Alert Forked River, New Jersey __ Site Area Emergency Docket: 50-219 General Emergency,,: | {{#Wiki_filter:Preliminary Notification DCS No.: 0500021911XX08 Date:. November 17, 2008 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE PNO-1-08-XXX Facility Licensee Emergency Classification AmerGen Energy Company, LLC __ Notification of Unusual Event Oyster Creek Alert Forked River, New Jersey __ Site Area Emergency Docket: 50-219 General Emergency,,: | ||
X Not Applicable | X Not Applicable | ||
==Subject:== | ==Subject:== | ||
RESULTS OF IMPLEMENTATION OF OYSTER CREEK LICENSE RENEWAL COMMITMENTS RELATED TO THE DRYWELL PRIMARY CONTAINMENT The NRC staff is performing an inspection of AmerGen's actions related to license renewal commitments, which were implemented during the 2008 refueling outage at the Oyster Creek Nuclear Generating Station (OCNGS). The NRC staff completed its on-site portion 6f a multi-week inspection of AmerGen's three aging management programs associated with the drywell primary containment: | RESULTS OF IMPLEMENTATION OF OYSTER CREEK LICENSE RENEWAL COMMITMENTS RELATED TO THE DRYWELL PRIMARY CONTAINMENT The NRC staff is performing an inspection of AmerGen's actions related to license renewal commitments, which were implemented during the 2008 refueling outage at the Oyster Creek Nuclear Generating Station (OCNGS). The NRC staff completed its on-site portion 6f a multi-week inspection of AmerGen's three aging management programs associated with the drywell primary containment: Containment Metallic Liner Inservice.Inspection; Structures Monitoring Program; and Protective Coating Monitoring and Maintenance Program. In'accordance with the NRC's agreement with the State of New Jersey, State Engineers observed portions of the NRC staff review. Based on the results of the NRC's inspection activities to date, the NRC staff concluded there were no safety significant conditions with respect to, the drywell containment that would prohibit plant startup. | ||
Containment Metallic Liner Inservice.Inspection; Structures Monitoring Program; and Protective Coating Monitoring and Maintenance Program. In'accordance with the NRC's agreement with the State of New Jersey, State Engineers observed portions of the NRC staff review. Based on the results of the NRC's inspection activities to date, the NRC staff concluded there were no safety significant conditions with respect to, the drywell containment that would prohibit plant startup.In the mid-1980s, GPUNuclear (previous licensee) identified corrosion of the drywell containment steel shellIiin the sand bed region. Initial licensee actions were not effective in arresting the corrosi~o, In 1992, all sand was removed from the sand bed region and the accessible exterior su~fc~es of the drywellshell | In the mid-1980s, GPUNuclear (previous licensee) identified corrosion of the drywell containment steel shellIiin the sand bed region. Initial licensee actions were not effective in arresting the corrosi~o, In 1992, all sand was removed from the sand bed region and the accessible exterior su~fc~es of the drywellshell werecleaned and coated with epoxy. Ultrasonic test (UT) thickness measurements of the' drywell shell taken in 1992 and 1996 indicated the corrosion had been effectively arrested. This information was confirmed by UT measurements in 2006, during a refueling outage. | ||
This information was confirmed by UT measurements in 2006, during a refueling outage.On October 24, 2008, OCNGS shut down for a scheduled refueling and maintenance outage.Outage work included implementation'of various license renewal aging management programs.During the 2008 refueling outage, the NRC's drywell shell inspection focused on: 1. Results of drywell shell UT thickness measurements. | On October 24, 2008, OCNGS shut down for a scheduled refueling and maintenance outage. | ||
: 2. Direct observation of drywell shell conditions both inside the drywell, including the floor trenches, and outside the drywell, in the sand bed regions.3. Condition and integrity of the drywell shell epoxy coating, including AmerGen's activities to evaluate and repair one small broken blister (with a small rust stain) and three small unbroken blisters (initially described as surface bumps) found in Bay-1 1, during the outage.4. Condition and integrity of the drywell shell moisture barrier seal between the shell and the sand bed floor, including AmerGen's activities to evaluate and repair small cracks in moisture barrier seals in multiple sand bed bays, and a small seal crack in Bay-3 which also exhibited small rust stains.5. AmerGen's activities to monitor, evaluate, and mitigate water leakage from the reactor refueling cavity onto the external surface of the drywell shell and into the sand bed regions.G:\DRS\Engineering Branch 1\Richmond\_FOIA 2009-0070\to be done -Exemption 5\OC PNO Nov- i-Lt 2008_Drywell-rev-4a.doc Preliminary Notification With respect to AmerGen's implementation of license renewal commitments, the NRC staff has concluded: | Outage work included implementation'of various license renewal aging management programs. | ||
During the 2008 refueling outage, the NRC's drywell shell inspection focused on: | |||
: 1. Results of drywell shell UT thickness measurements. | |||
: 2. Direct observation of drywell shell conditions both inside the drywell, including the floor trenches, and outside the drywell, in the sand bed regions. | |||
: 3. Condition and integrity of the drywell shell epoxy coating, including AmerGen's activities to evaluate and repair one small broken blister (with a small rust stain) and three small unbroken blisters (initially described as surface bumps) found in Bay-1 1, during the outage. | |||
: 4. Condition and integrity of the drywell shell moisture barrier seal between the shell and the sand bed floor, including AmerGen's activities to evaluate and repair small cracks in moisture barrier seals in multiple sand bed bays, and a small seal crack in Bay-3 which also exhibited small rust stains. | |||
: 5. AmerGen's activities to monitor, evaluate, and mitigate water leakage from the reactor refueling cavity onto the external surface of the drywell shell and into the sand bed regions. | |||
G:\DRS\Engineering Branch 1\Richmond\_FOIA 2009-0070\to be done - Exemption 5\OC PNO Nov- i-Lt 2008_Drywell-rev-4a.doc | |||
Preliminary Notification With respect to AmerGen's implementation of license renewal commitments, the NRC staff has concluded: | |||
: 1. All drywell shell UT thickness measurements satisfied AmerGen's acceptance criteria and current licensing basis design requirements. | : 1. All drywell shell UT thickness measurements satisfied AmerGen's acceptance criteria and current licensing basis design requirements. | ||
: 2. There were no identified significant conditions affecting the drywell shell structural integrity. | : 2. There were no identified significant conditions affecting the drywell shell structural integrity. | ||
: 3. AmerGen's inspection of the as-found condition of the external drywell shell epoxy coating, in the sand bed regions, was acceptable. | : 3. AmerGen's inspection of the as-found condition of the external drywell shell epoxy coating, in the sand bed regions, was acceptable. Four small blisters (three of which were initially identified as bumps) on the coating in Bay-1 1 were identified and repaired. AmerGen reported that some blistering was expected, and would be identified;,during routine visual examinations. The NRC staff will review AmerGen's apparent cause evaluation after it is completed. | ||
Four small blisters (three of which were initially identified as bumps) on the coating in Bay-1 1 were identified and repaired. | : 4. AmerGen's inspection of the as-found condition of the external drywell shell moisture barrier seal, between the shell and the sand bed floor, was acceptable. Surface cracks, which did not appear to completely penetrate the seal, were identified in multiplebays, and were repaired. During one crack repair in Bay-3, some drywell shell surface' corrosion was also identified and repaired. | ||
AmerGen reported that some blistering was expected, and would be identified;,during routine visual examinations. | : 5. AmerGen's activities to monitor and mitigate water leakage from the reactor refueling cavity onto the external surface of the drywell shell and into the sand bed regions are still under evaluation. | ||
The NRC staff will review AmerGen's apparent cause evaluation after it is completed. | During the outage, water leakage from ithereactor refueling cavity into the cavity drain trough, as monitored in the trough's drain line, increased from less than 1 gallon per minute (gpm) to approximately 4 to 6 gpm. Some of the water in the cavity drain trough spilled into the gap between the steel shell and the concrete shield wall;,!and ultimately into the sand bed regions. | ||
: 4. AmerGen's inspection of the as-found condition of the external drywell shell moisture barrier seal, between the shell and the sand bed floor, was acceptable. | AmerGen enhanced its leakage monitoring and performed: visual inspections to detect any water entry. Small water puddles were identified in ,several sand bed bays. After the cavity was drained, AmerGen performed direýc inspections Ifthe sand bed bays, and no significant adverse conditions were identified. | ||
Surface cracks, which did not appear to completely penetrate the seal, were identified in multiplebays, and were repaired. | AmerGen identified andfixed the! problem's found isand beds Bay-3 and Bay-i 1, as part of their aging managementprbqgiaap mplementation The drywell shell epoxy coating and the moisture barrier seal, both innthe sand bed regi~ifitare barrier systems used to protect the dryweli shell from corrosion. Th*e!problems identified with these barriers had a minimal impact on the drywell steel shell and thpýipo',jected shell corrosion rate remains very small, as confirmed by NRC staff review of UT data. | ||
During one crack repair in Bay-3, some drywell shell surface' corrosion was also identified and repaired.5. AmerGen's activities to monitor and mitigate water leakage from the reactor refueling cavity onto the external surface of the drywell shell and into the sand bed regions are still under evaluation. | Based on a review of the technical information, the NRC staff determined AmerGen has provided an adequate basis to conclude the drywell primary containment will remain operable during the period until the next scheduled examination. | ||
During the outage, water leakage from ithereactor refueling cavity into the cavity drain trough, as monitored in the trough's drain line, increased from less than 1 gallon per minute (gpm) to approximately 4 to 6 gpm. Some of the water in the cavity drain trough spilled into the gap between the steel shell and the concrete shield wall;,!and ultimately into the sand bed regions.AmerGen enhanced its leakage monitoring and performed: | The information presented herein has been discussed with AmerGen and is current as of November 17, at xxx p.m. | ||
visual inspections to detect any water entry. Small water puddles | The State of New Jersey has been notified. | ||
AmerGen identified andfixed the! problem's found isand beds Bay-3 and Bay-i 1, as part of their aging managementprbqgiaap mplementation The drywell shell epoxy coating and the moisture barrier seal, both | This Preliminary Notification is being issued for information only and will not be updated. | ||
identified with these barriers had a minimal impact on the drywell steel shell and thpýipo',jected shell corrosion rate remains very small, as confirmed by NRC staff review of UT data.Based on a review of the technical information, the NRC staff determined AmerGen has provided an adequate basis to conclude the drywell primary containment will remain operable during the period until the next scheduled examination. | ADAMS Accession Number: ML ..................... | ||
The information presented herein has been discussed with AmerGen and is current as of November 17, at xxx p.m.The State of New Jersey has been notified.This Preliminary Notification is being issued for information only and will not be updated.ADAMS Accession Number: ML ..................... | CONTACT: Richard J. Conte John Richmond (anrc.gov (Dnrc.gov (610) 337-5183 (610) 337-5220 G:\DRS\Engineering Branch 1\Richmond\_FOIA 2009-0070\to be done - Exemption 5\OC PNO Nov-2008_Drywellirev-4a.doc}} | ||
CONTACT: Richard J. Conte John Richmond (anrc. gov (Dnrc.gov (610) 337-5183 (610) 337-5220 G:\DRS\Engineering Branch 1\Richmond\_FOIA 2009-0070\to be done -Exemption 5\OC PNO Nov-2008_Drywellirev-4a.doc}} | |||
Latest revision as of 05:19, 14 November 2019
| ML091480445 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/30/2008 |
| From: | Conte R, Richmond J NRC Region 1 |
| To: | |
| References | |
| FOIA/PA-2009-0070 | |
| Download: ML091480445 (2) | |
Text
Preliminary Notification DCS No.: 0500021911XX08 Date:. November 17, 2008 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE PNO-1-08-XXX Facility Licensee Emergency Classification AmerGen Energy Company, LLC __ Notification of Unusual Event Oyster Creek Alert Forked River, New Jersey __ Site Area Emergency Docket: 50-219 General Emergency,,:
X Not Applicable
Subject:
RESULTS OF IMPLEMENTATION OF OYSTER CREEK LICENSE RENEWAL COMMITMENTS RELATED TO THE DRYWELL PRIMARY CONTAINMENT The NRC staff is performing an inspection of AmerGen's actions related to license renewal commitments, which were implemented during the 2008 refueling outage at the Oyster Creek Nuclear Generating Station (OCNGS). The NRC staff completed its on-site portion 6f a multi-week inspection of AmerGen's three aging management programs associated with the drywell primary containment: Containment Metallic Liner Inservice.Inspection; Structures Monitoring Program; and Protective Coating Monitoring and Maintenance Program. In'accordance with the NRC's agreement with the State of New Jersey, State Engineers observed portions of the NRC staff review. Based on the results of the NRC's inspection activities to date, the NRC staff concluded there were no safety significant conditions with respect to, the drywell containment that would prohibit plant startup.
In the mid-1980s, GPUNuclear (previous licensee) identified corrosion of the drywell containment steel shellIiin the sand bed region. Initial licensee actions were not effective in arresting the corrosi~o, In 1992, all sand was removed from the sand bed region and the accessible exterior su~fc~es of the drywellshell werecleaned and coated with epoxy. Ultrasonic test (UT) thickness measurements of the' drywell shell taken in 1992 and 1996 indicated the corrosion had been effectively arrested. This information was confirmed by UT measurements in 2006, during a refueling outage.
On October 24, 2008, OCNGS shut down for a scheduled refueling and maintenance outage.
Outage work included implementation'of various license renewal aging management programs.
During the 2008 refueling outage, the NRC's drywell shell inspection focused on:
- 1. Results of drywell shell UT thickness measurements.
- 2. Direct observation of drywell shell conditions both inside the drywell, including the floor trenches, and outside the drywell, in the sand bed regions.
- 3. Condition and integrity of the drywell shell epoxy coating, including AmerGen's activities to evaluate and repair one small broken blister (with a small rust stain) and three small unbroken blisters (initially described as surface bumps) found in Bay-1 1, during the outage.
- 4. Condition and integrity of the drywell shell moisture barrier seal between the shell and the sand bed floor, including AmerGen's activities to evaluate and repair small cracks in moisture barrier seals in multiple sand bed bays, and a small seal crack in Bay-3 which also exhibited small rust stains.
- 5. AmerGen's activities to monitor, evaluate, and mitigate water leakage from the reactor refueling cavity onto the external surface of the drywell shell and into the sand bed regions.
G:\DRS\Engineering Branch 1\Richmond\_FOIA 2009-0070\to be done - Exemption 5\OC PNO Nov- i-Lt 2008_Drywell-rev-4a.doc
Preliminary Notification With respect to AmerGen's implementation of license renewal commitments, the NRC staff has concluded:
- 1. All drywell shell UT thickness measurements satisfied AmerGen's acceptance criteria and current licensing basis design requirements.
- 2. There were no identified significant conditions affecting the drywell shell structural integrity.
- 3. AmerGen's inspection of the as-found condition of the external drywell shell epoxy coating, in the sand bed regions, was acceptable. Four small blisters (three of which were initially identified as bumps) on the coating in Bay-1 1 were identified and repaired. AmerGen reported that some blistering was expected, and would be identified;,during routine visual examinations. The NRC staff will review AmerGen's apparent cause evaluation after it is completed.
- 4. AmerGen's inspection of the as-found condition of the external drywell shell moisture barrier seal, between the shell and the sand bed floor, was acceptable. Surface cracks, which did not appear to completely penetrate the seal, were identified in multiplebays, and were repaired. During one crack repair in Bay-3, some drywell shell surface' corrosion was also identified and repaired.
- 5. AmerGen's activities to monitor and mitigate water leakage from the reactor refueling cavity onto the external surface of the drywell shell and into the sand bed regions are still under evaluation.
During the outage, water leakage from ithereactor refueling cavity into the cavity drain trough, as monitored in the trough's drain line, increased from less than 1 gallon per minute (gpm) to approximately 4 to 6 gpm. Some of the water in the cavity drain trough spilled into the gap between the steel shell and the concrete shield wall;,!and ultimately into the sand bed regions.
AmerGen enhanced its leakage monitoring and performed: visual inspections to detect any water entry. Small water puddles were identified in ,several sand bed bays. After the cavity was drained, AmerGen performed direýc inspections Ifthe sand bed bays, and no significant adverse conditions were identified.
AmerGen identified andfixed the! problem's found isand beds Bay-3 and Bay-i 1, as part of their aging managementprbqgiaap mplementation The drywell shell epoxy coating and the moisture barrier seal, both innthe sand bed regi~ifitare barrier systems used to protect the dryweli shell from corrosion. Th*e!problems identified with these barriers had a minimal impact on the drywell steel shell and thpýipo',jected shell corrosion rate remains very small, as confirmed by NRC staff review of UT data.
Based on a review of the technical information, the NRC staff determined AmerGen has provided an adequate basis to conclude the drywell primary containment will remain operable during the period until the next scheduled examination.
The information presented herein has been discussed with AmerGen and is current as of November 17, at xxx p.m.
The State of New Jersey has been notified.
This Preliminary Notification is being issued for information only and will not be updated.
ADAMS Accession Number: ML .....................
CONTACT: Richard J. Conte John Richmond (anrc.gov (Dnrc.gov (610) 337-5183 (610) 337-5220 G:\DRS\Engineering Branch 1\Richmond\_FOIA 2009-0070\to be done - Exemption 5\OC PNO Nov-2008_Drywellirev-4a.doc