|
|
| (6 intermediate revisions by the same user not shown) |
| Line 2: |
Line 2: |
| | number = ML14100A180 | | | number = ML14100A180 |
| | issue date = 05/08/2014 | | | issue date = 05/08/2014 |
| | title = Salem Nuclear Generating Station, Unit 1 - License Renewal Commitment Implementation to Renewed Facility Operating License Condition 2.C.21 (TAC No. MF3334) | | | title = License Renewal Commitment Implementation to Renewed Facility Operating License Condition 2.C.21 |
| | author name = Lamb J G | | | author name = Lamb J |
| | author affiliation = NRC/NRR/DORL/LPLI-2 | | | author affiliation = NRC/NRR/DORL/LPLI-2 |
| | addressee name = Joyce T | | | addressee name = Joyce T |
| Line 9: |
Line 9: |
| | docket = 05000272 | | | docket = 05000272 |
| | license number = DPR-070 | | | license number = DPR-070 |
| | contact person = Lamb J G, NRR/DORL/LPLI-2, 415-3100 | | | contact person = Lamb J, NRR/DORL/LPLI-2, 415-3100 |
| | case reference number = TAC MF3334 | | | case reference number = TAC MF3334 |
| | document type = Letter | | | document type = Letter |
| Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236, N09 Hancocks Bridge, NJ 08038 May 8, 2014 SUBJECT: SALEM NUCLEAR GENERATING STATION, UNIT 1 -LICENSE RENEWAL COMMITMENT IMPLEMENTATION TO RENEWED FACILITY OPERATING LICENSE CONDITION 2.C.21 (TAC NO. MF3334) Dear Mr. Joyce: By letter dated November 12, 2013, (Agencywide Documents Access and Management System Accession No. ML 13317B684) Public Service Enterprise Group Nuclear LLC (PSEG or licensee) submitted a document in accordance with the renewed facility operating license condition 2.C.21 for Salem Nuclear Generating Station (Salem), Unit 1. Renewed facility operating license condition 2.C.21, states: PSEG Nuclear LLC shall take one core sample in the Unit 1 spent fuel pool west wall, by the end of 2013, and one core sample in the east wall where there have been indications of borated water ingress through the concrete, by the end of 2015. The core samples (east and west walls) will expose the rebar, which will be examined for signs of corrosion. Any sample showing signs of concrete degradation and/or rebar corrosion will be entered into the licensee's corrective action program for further evaluation. PSEG Nuclear LLC shall submit a report in accordance with 10 CFR 50.4 no later than three months after each sample is taken on the results, recommendations, and any additional planned actions. In its letter dated November 12, 2013, PSEG outlined the results of compressive strength tests and petrographic examination findings from the west wall concrete core bore, as well as findings from visual examinations of the reinforcement for corrosion. PSEG obtained a 26-inch long core bore approximately 20 inches below a construction joint, and constructed samples for two compressive strength tests and three petrographic examinations. The compressive strength tests were performed in accordance with the American Society for Testing Materials (ASTM) C39 and ASTM C42. One test specimen was from the end facing the sump room; the other closest to the spent fuel pool (SFP). The sample closest to the SFP, because of its radioactivity, was examined in a specialized setting. Both tests yielded concrete compressive strengths in excess of the specified design strength. The petrographic examinations were visual and in accordance with ASTM C856. The samples obtained from the top, bottom, and middle sections of the core bore, demonstrated that the extracted concrete was in good condition and the cement paste was unaffected by chemical attacks, showing no signs of discoloration, softening, degradation, or dissolution. In addition to these tests, the licensee excavated a small area of the west wall in the vicinity of the lateral construction joint to expose and assess the condition of a portion of the reinforcing steel. PSEG stated that the only visible corrosion of the T. Joyce -2-rebar was a minor surface corrosion attributed, possibly, to the original construction or to its recent exposure to the atmosphere during measures taken to repair the area following this inspection. The licensee summarized the findings for concrete and rebar examination by stating, in part, that, "[t]he removal and examination of the core sample in the Unit 1 spent fuel pool west wall did not show any indications of concrete degradation due to borated water ingress through the concrete. Also, the exposed rebar did not show signs of aging-related corrosion." The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's letter dated November 12, 2013, documenting its 2013 actions and results related to renewed facility operating license condition 2.C.21. The NRC staff noted that for assessment of concrete degradation both compressive test cylinders yielded concrete compressive strength results well above the design compressive strength of concrete for the Fuel Handling Building, which is indicative that in the area of examination, concrete exceeds the specified design compressive strength for the structure. The NRC staff also noted that the petrographic examinations of the concrete showed that it is in good condition with no signs of chemical attacks, discoloration, softening, degradation, or dissolution, which is indicative that the concrete in the core bored | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 8, 2014 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236, N09 Hancocks Bridge, NJ 08038 |
| * area is unaffected by the environment. The NRC staff further noted that the licensee's visual examination of the exposed reinforcing bar did not show signs of corrosion affecting its thickness, and hence the rebar cross sectional area required by design. Based on its review above, the NRC staff concludes that the licensee has provided the required information and completed the actions required by renewed facility operating license condition 2.C.21 for 2013. This completes the NRC staff review under TAC No. MF3334. If you have any questions concerning this matter, please contact me at (301) 415-3100 or via e-mail at John. Lamb@nrc.gov. Docket No. 50-272 cc: Distribution via Listserv . Lamb, Senior Project Manager Licensing Branch 1-2 Divi ion of Operating Reactor Licensing Office of Nuclear Reactor Regulation T. Joyce -2-rebar was a minor surface corrosion attributed, possibly, to the original construction or to its recent exposure to the atmosphere during measures taken to repair the area following this inspection. The licensee summarized the findings for concrete and rebar examination by stating, in part, that, "[t]he removal and examination of the core sample in the Unit 1 spent fuel pool west wall did not show any indications of concrete degradation due to borated water ingress through the concrete. Also, the exposed rebar did not show signs of aging-related corrosion." The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's letter dated November 12, 2013, documenting its 2013 actions and results related to renewed facility operating license condition 2.C.21. The NRC staff noted that for assessment of concrete degradation, both compressive test cylinders yielded concrete compressive strength results well above the design compressive strength of concrete for the Fuel Handling Building, which is indicative that in the area of examination, concrete exceeds the specified design compressive strength for the structure. The NRC staff also noted that the petrographic examinations of the concrete showed that it is in good condition with no signs of chemical attacks, discoloration, softening, degradation, or dissolution, which is indicative that the concrete in the core bored area is unaffected by the environment. The NRC staff further noted that the licensee's visual examination of the exposed reinforcing bar did not show signs of corrosion affecting its thickness, and hence the rebar cross sectional area required by design. Based on its review above, the NRC staff concludes that the licensee has provided the required information and completed the actions required by renewed facility operating license condition 2.C.21 for 2013. This completes the NRC staff review under TAC No. MF3334. If you have any questions concerning this matter, please contact me at (301) 415-3100 or via e-mail at John.Lamb@nrc.gov. Docket No. 50-272 cc: Distribution via Listserv DISTRIBUTION: PUBLIC LPL 1-2 R/F RidsNrrDorllpl1-2 Resource RidsNrrLAABaxter Resource ADAMS Accession No* ML 14100A180 .. OFFICE LPL 1-2/PM LPL 1-2/LA NAME Jlamb ABaxter DATE 05/07/2014 04/30/2014 Sincerely, IRA! John G. Lamb, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation JNick, EDO Region I RidsAcrsAcnw_MaiiCTR Resource RidsRgn1 MaiiCenter Resource MMarshal, NRR *via email RASB/BC* LPL 1-2/BC MMarshal MKhanna 04/10/2014 05/07/2014 LPL 1-2/PM Jlamb 05/08/2014 OFFICIAL RECORD COPY | | |
| }} | | ==SUBJECT:== |
| | SALEM NUCLEAR GENERATING STATION, UNIT 1 -LICENSE RENEWAL COMMITMENT IMPLEMENTATION TO RENEWED FACILITY OPERATING LICENSE CONDITION 2.C.21 (TAC NO. MF3334) |
| | |
| | ==Dear Mr. Joyce:== |
| | |
| | By letter dated November 12, 2013, (Agencywide Documents Access and Management System Accession No. ML13317B684) Public Service Enterprise Group Nuclear LLC (PSEG or licensee) submitted a document in accordance with the renewed facility operating license condition 2.C.21 for Salem Nuclear Generating Station (Salem), Unit 1. |
| | Renewed facility operating license condition 2.C.21, states: |
| | PSEG Nuclear LLC shall take one core sample in the Unit 1 spent fuel pool west wall, by the end of 2013, and one core sample in the east wall where there have been indications of borated water ingress through the concrete, by the end of 2015. The core samples (east and west walls) will expose the rebar, which will be examined for signs of corrosion. Any sample showing signs of concrete degradation and/or rebar corrosion will be entered into the licensee's corrective action program for further evaluation. PSEG Nuclear LLC shall submit a report in accordance with 10 CFR 50.4 no later than three months after each sample is taken on the results, recommendations, and any additional planned actions. |
| | In its letter dated November 12, 2013, PSEG outlined the results of compressive strength tests and petrographic examination findings from the west wall concrete core bore, as well as findings from visual examinations of the reinforcement for corrosion. PSEG obtained a 26-inch long core bore approximately 20 inches below a construction joint, and constructed samples for two compressive strength tests and three petrographic examinations. The compressive strength tests were performed in accordance with the American Society for Testing Materials (ASTM) |
| | C39 and ASTM C42. One test specimen was from the end facing the sump room; the other closest to the spent fuel pool (SFP). The sample closest to the SFP, because of its radioactivity, was examined in a specialized setting. Both tests yielded concrete compressive strengths in excess of the specified design strength. The petrographic examinations were visual and in accordance with ASTM C856. The samples obtained from the top, bottom, and middle sections of the core bore, demonstrated that the extracted concrete was in good condition and the cement paste was unaffected by chemical attacks, showing no signs of discoloration, softening, degradation, or dissolution. In addition to these tests, the licensee excavated a small area of the west wall in the vicinity of the lateral construction joint to expose and assess the condition of a portion of the reinforcing steel. PSEG stated that the only visible corrosion of the |
| | |
| | T. Joyce rebar was a minor surface corrosion attributed, possibly, to the original construction or to its recent exposure to the atmosphere during measures taken to repair the area following this inspection. The licensee summarized the findings for concrete and rebar examination by stating, in part, that, "[t]he removal and examination of the core sample in the Unit 1 spent fuel pool west wall did not show any indications of concrete degradation due to borated water ingress through the concrete. Also, the exposed rebar did not show signs of aging-related corrosion." |
| | The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's letter dated November 12, 2013, documenting its 2013 actions and results related to renewed facility operating license condition 2.C.21. The NRC staff noted that for assessment of concrete degradation both compressive test cylinders yielded concrete compressive strength results well above the design compressive strength of concrete for the Fuel Handling Building, which is indicative that in the area of examination, concrete exceeds the specified design compressive strength for the structure. The NRC staff also noted that the petrographic examinations of the concrete showed that it is in good condition with no signs of chemical attacks, discoloration, softening, degradation, or dissolution, which is indicative that the concrete in the core bored |
| | * area is unaffected by the environment. The NRC staff further noted that the licensee's visual examination of the exposed reinforcing bar did not show signs of corrosion affecting its thickness, and hence the rebar cross sectional area required by design. |
| | Based on its review above, the NRC staff concludes that the licensee has provided the required information and completed the actions required by renewed facility operating license condition 2.C.21 for 2013. |
| | This completes the NRC staff review under TAC No. MF3334. |
| | If you have any questions concerning this matter, please contact me at (301) 415-3100 or via e-mail at John. Lamb@nrc.gov. |
| | . Lamb, Senior Project Manager Licensing Branch 1-2 Divi ion of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-272 cc: Distribution via Listserv |
| | * ML14100A180 *via email OFFICE LPL 1-2/PM LPL 1-2/LA RASB/BC* LPL 1-2/BC LPL 1-2/PM NAME Jlamb ABaxter MMarshal MKhanna Jlamb DATE 05/07/2014 04/30/2014 04/10/2014 05/07/2014 05/08/2014}} |
Similar Documents at Salem |
|---|
Category:Letter
MONTHYEARIR 05000272/20230042024-02-0505 February 2024
Integrated Inspection Report 05000272/2023004 and 05000311/2023004
ML24009A1022024-01-26026 January 2024
Exemption from Select Requirements of 10 CF Part 73 (EPID L-2023-LLE-0045 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
IR 05000272/20234012024-01-22022 January 2024
Material Control and Accounting Program Inspection Report 05000272/2023401 and 05000311/2023401
ML24004A1542024-01-0808 January 2024
Notification of Conduct of a Fire Protection Team Inspection
LR-N23-0079, Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days2023-12-0707 December 2023
Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days
ML23270C0072023-11-29029 November 2023
Notice of Proposed Amendment to Decommissioning Trust Agreement
LR-N23-0077, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion2023-11-29029 November 2023
Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion
ML23324A3072023-11-17017 November 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
IR 05000272/20230032023-11-13013 November 2023
Integrated Inspection Report 05000272/2023003 and 05000311/2023003
LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023
Core Operating Limits Report Cycle 30
IR 05000272/20230102023-10-12012 October 2023
Biennial Problem Identification and Resolution Inspection Report O5000272/2023010 and 05000311/2023010
IR 05000272/20234022023-10-12012 October 2023
and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2023402, 05000272/2023402 and 05000311/2023402 (Cover Letter Only)
LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023
and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement
ML23249A2612023-09-0606 September 2023
License Amendment Request to Modify the Salem and Hope Creek Exclusion Area Boundary
IR 05000272/20230052023-08-31031 August 2023
Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2023005 and 05000311/2023005)
ML23233A0762023-08-21021 August 2023
Requalification Program Inspection
ML23192A8212023-08-14014 August 2023
and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location
IR 05000272/20230022023-08-0909 August 2023
Integrated Inspection Report 05000272/2023002 and 05000311/2023002
LR-N23-0055, Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days2023-08-0303 August 2023
Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days
IR 05000354/20230022023-08-0303 August 2023
Integrated Inspection Report 05000354/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200048/2023001
LR-N23-0054, In-Service Inspection Activities2023-07-26026 July 2023
In-Service Inspection Activities
LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023
Emergency Plan Document Revisions Implemented June 28, 2023
LR-N23-0005, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-06-23023 June 2023
License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
ML23139A1472023-06-0505 June 2023
Relief Request Associated with Fourth Interval In-service Inspection Limited Examinations of Weld Coverage
ML23096A1842023-05-0909 May 2023
Issuance of Amendment No. 328 Revise and Relocate Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report
IR 05000272/20230012023-05-0303 May 2023
Integrated Inspection Report 05000272/2023001 and 05000311/2023001
ML23081A4662023-05-0202 May 2023
Issuance of Amendment Nos. 346 and 327 Revise Technical Specifications to Extend Allowable Outage Time for Inoperable Emergency Diesel Generator
IR 05000272/20233012023-05-0101 May 2023
Initial Operator Licensing Examination Report 05000272/2023301 and 05000311/2023301
LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023
2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station
LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023
2022 Annual Radioactive Effluent Release Report (ARERR)
LR-N23-0033, Core Operating Limits Report Cycle 272023-04-26026 April 2023
Core Operating Limits Report Cycle 27
LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023
License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location
ML23089A0942023-04-17017 April 2023
NRC to PSEG Hope Creek, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek
ML23087A1492023-04-17017 April 2023
NRC to PSEG Salem, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek
ML23103A3232023-04-13013 April 2023
Submittal of Updated Final Safety Analysis Report, Rev. 26, Summary of Revised Regulatory Commitments for Hope Creek, Summary of Changes to PSEG Nuclear LLC, Quality Assurance Topical Report, NO-AA-10, Rev. 89
ML23095A3682023-04-12012 April 2023
and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership
LR-N23-0006, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-24024 March 2023
Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
ML23086A0912023-03-24024 March 2023
NMFS to NRC, Transmittal of Biological Opinion for Continued Operations of Salem and Hope Creek Nuclear Generating Stations
RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023
Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2023-03-21021 March 2023
and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums
ML23044A1052023-03-13013 March 2023
Issuance of Amendment Nos. 345 and 326 Relocate Technical Specifications Requirements for Reactor Head Vents to Technical Requirements Manual
ML23037A9712023-03-0909 March 2023
and Salem Nuclear, Unit Nos. 1 and 2 Issuance of Amendment Nos. 233, 344, and 325 Relocate Technical Specification Staff Qualification Requirements to the PSEG Quality Assurance Topical Report
IR 05000272/20230112023-03-0707 March 2023
Comprehensive Engineering Team Inspection Report 05000272/2023011 and 05000311/2023011
IR 05000272/20220062023-03-0101 March 2023
Annual Assessment Letter for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2022006 and 05000311/2022006)
LR-N23-0016, and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments2023-02-28028 February 2023
and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments
LR-N23-0012, Annual Property Insurance Status Report2023-02-24024 February 2023
Annual Property Insurance Status Report
LR-N23-0014, Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.7172023-02-23023 February 2023
Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.717
ML23034A1532023-02-0909 February 2023
Operator Licensing Examination Approval
ML23019A3482023-02-0202 February 2023
Issuance of Relief Request No. SC-I5R-221 for the Alternative Repair for Service Water System Piping
LR-N23-0003, Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-2112023-02-0101 February 2023
Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-211
2024-02-05
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 8, 2014 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236, N09 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT 1 -LICENSE RENEWAL COMMITMENT IMPLEMENTATION TO RENEWED FACILITY OPERATING LICENSE CONDITION 2.C.21 (TAC NO. MF3334)
Dear Mr. Joyce:
By letter dated November 12, 2013, (Agencywide Documents Access and Management System Accession No. ML13317B684) Public Service Enterprise Group Nuclear LLC (PSEG or licensee) submitted a document in accordance with the renewed facility operating license condition 2.C.21 for Salem Nuclear Generating Station (Salem), Unit 1.
Renewed facility operating license condition 2.C.21, states:
PSEG Nuclear LLC shall take one core sample in the Unit 1 spent fuel pool west wall, by the end of 2013, and one core sample in the east wall where there have been indications of borated water ingress through the concrete, by the end of 2015. The core samples (east and west walls) will expose the rebar, which will be examined for signs of corrosion. Any sample showing signs of concrete degradation and/or rebar corrosion will be entered into the licensee's corrective action program for further evaluation. PSEG Nuclear LLC shall submit a report in accordance with 10 CFR 50.4 no later than three months after each sample is taken on the results, recommendations, and any additional planned actions.
In its letter dated November 12, 2013, PSEG outlined the results of compressive strength tests and petrographic examination findings from the west wall concrete core bore, as well as findings from visual examinations of the reinforcement for corrosion. PSEG obtained a 26-inch long core bore approximately 20 inches below a construction joint, and constructed samples for two compressive strength tests and three petrographic examinations. The compressive strength tests were performed in accordance with the American Society for Testing Materials (ASTM)
C39 and ASTM C42. One test specimen was from the end facing the sump room; the other closest to the spent fuel pool (SFP). The sample closest to the SFP, because of its radioactivity, was examined in a specialized setting. Both tests yielded concrete compressive strengths in excess of the specified design strength. The petrographic examinations were visual and in accordance with ASTM C856. The samples obtained from the top, bottom, and middle sections of the core bore, demonstrated that the extracted concrete was in good condition and the cement paste was unaffected by chemical attacks, showing no signs of discoloration, softening, degradation, or dissolution. In addition to these tests, the licensee excavated a small area of the west wall in the vicinity of the lateral construction joint to expose and assess the condition of a portion of the reinforcing steel. PSEG stated that the only visible corrosion of the
T. Joyce rebar was a minor surface corrosion attributed, possibly, to the original construction or to its recent exposure to the atmosphere during measures taken to repair the area following this inspection. The licensee summarized the findings for concrete and rebar examination by stating, in part, that, "[t]he removal and examination of the core sample in the Unit 1 spent fuel pool west wall did not show any indications of concrete degradation due to borated water ingress through the concrete. Also, the exposed rebar did not show signs of aging-related corrosion."
The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's letter dated November 12, 2013, documenting its 2013 actions and results related to renewed facility operating license condition 2.C.21. The NRC staff noted that for assessment of concrete degradation both compressive test cylinders yielded concrete compressive strength results well above the design compressive strength of concrete for the Fuel Handling Building, which is indicative that in the area of examination, concrete exceeds the specified design compressive strength for the structure. The NRC staff also noted that the petrographic examinations of the concrete showed that it is in good condition with no signs of chemical attacks, discoloration, softening, degradation, or dissolution, which is indicative that the concrete in the core bored
- area is unaffected by the environment. The NRC staff further noted that the licensee's visual examination of the exposed reinforcing bar did not show signs of corrosion affecting its thickness, and hence the rebar cross sectional area required by design.
Based on its review above, the NRC staff concludes that the licensee has provided the required information and completed the actions required by renewed facility operating license condition 2.C.21 for 2013.
This completes the NRC staff review under TAC No. MF3334.
If you have any questions concerning this matter, please contact me at (301) 415-3100 or via e-mail at John. Lamb@nrc.gov.
. Lamb, Senior Project Manager Licensing Branch 1-2 Divi ion of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-272 cc: Distribution via Listserv
- ML14100A180 *via email OFFICE LPL 1-2/PM LPL 1-2/LA RASB/BC* LPL 1-2/BC LPL 1-2/PM NAME Jlamb ABaxter MMarshal MKhanna Jlamb DATE 05/07/2014 04/30/2014 04/10/2014 05/07/2014 05/08/2014
