|
|
| (6 intermediate revisions by the same user not shown) |
| Line 3: |
Line 3: |
| | issue date = 11/03/2016 | | | issue date = 11/03/2016 |
| | title = U.S. Nuclear Regulatory Commission Response to Disputed Notice of Non-Cited Violation 05000311/2016002-02 | | | title = U.S. Nuclear Regulatory Commission Response to Disputed Notice of Non-Cited Violation 05000311/2016002-02 |
| | author name = McKinley R R | | | author name = Mckinley R |
| | author affiliation = NRC/RGN-I/DRS/PSB1 | | | author affiliation = NRC/RGN-I/DRS/PSB1 |
| | addressee name = Sena P | | | addressee name = Sena P |
| Line 9: |
Line 9: |
| | docket = 05000311 | | | docket = 05000311 |
| | license number = DPR-075 | | | license number = DPR-075 |
| | contact person = McKinley R R | | | contact person = McKinley R |
| | case reference number = EA-16-244 | | | case reference number = EA-16-244 |
| | document report number = IR 2016002 | | | document report number = IR 2016002 |
| Line 15: |
Line 15: |
| | page count = 3 | | | page count = 3 |
| }} | | }} |
| See also: [[followed by::IR 05000311/2016002]] | | See also: [[see also::IR 05000311/2016002]] |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter:UNITED STATES |
| [[Issue date::November 3, 2016]]
| | NUCLEAR REGULATORY COMMISSION |
| | REGION I |
| | 2100 RENAISSANCE BLVD. |
| | KING OF PRUSSIA, PA 19406-2713 |
| | November 3, 2016 |
| | EA-16-244 |
| | Mr. Peter Sena, III |
| | President and Chief Nuclear Officer |
| | PSEG Nuclear LLC - N09 |
| | P.O. Box 236 |
| | Hancocks Bridge, NJ 08038 |
| | SUBJECT: U.S. NUCLEAR REGULATORY COMMISSION RESPONSE TO DISPUTED |
| | NOTICE OF NON-CITED VIOLATION 05000311/2016002-02 |
| | Dear Mr. Sena: |
| | I am writing to acknowledge receipt of PSEGs letter dated October 24, 2016, in response to the |
| | U.S. Nuclear Regulatory Commission (NRC) Inspection Report 05000272/2016002 and |
| | 05000311/2016002 issued on September 22, 2016. |
| | The letter requests withdrawal of the 10 CFR Part 50, Appendix B, Criterion V, Instructions, |
| | Procedures, and Drawings, Green non-cited violation (NCV 0500311/2016002-02) concerning |
| | the failure to follow the operability process as prescribed in OP-AA-108-115, Operability |
| | Determinations & Functionality Assessments. The letter stated that PSEG was in full |
| | compliance with procedure OP-AA-108-115 when evaluating the baffle former bolt condition |
| | discovered at Unit 1 as it applied to Unit 2. The NRC will review PSEGs response and provide |
| | you a letter documenting the basis for any decision within 90 days. |
| | In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRCs |
| | Rules of Practice, a copy of this letter, its enclosure, and your response (if any) will be |
| | available electronically for public inspection in the NRCs Public Document Room or from the |
| | Publicly Available Records component of the NRCs Agencywide Documents Access and |
| | Management System (ADAMS). ADAMS is accessible from the NRC website at |
| | http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Your letter |
| | has also been added to ADAMS for the information of the public, and may be found under |
| | ADAMS Accession Number ML16298A161. |
|
| |
|
| EA-16-244
| | P. Sena -2- |
| | Should you have any questions concerning this letter, please contact me at (610) 337-5150. |
| | Sincerely, |
| | /RA/ |
| | Raymond R. McKinley, Chief |
| | Plant Support Branch 1 |
| | Division of Reactor Safety |
| | Docket No. 50-311 |
| | License No. DPR-75 |
| | cc: Distribution via ListServ |
|
| |
|
| Mr. Peter Sena, III President and Chief Nuclear Officer PSEG Nuclear LLC - N09 P.O. Box 236 Hancocks Bridge, NJ 08038
| |
|
| |
|
| SUBJECT: U.S. NUCLEAR REGULATORY COMMISSION RESPONSE TO DISPUTED NOTICE OF NON-CITED VIOLATION 05000311/2016002-02
| | ML16308A328 |
| | | Non-Sensitive Publicly Available |
| ==Dear Mr. Sena:==
| | SUNSI Review |
| I am writing to acknowledge receipt of PSEG's letter dated October 24, 2016, in response to the U.S. Nuclear Regulatory Commission (NRC) Inspection Report 05000272/2016002 and 05000311/2016002 issued on September 22, 2016.
| | Sensitive Non-Publicly Available |
| | | OFFICE RI/DRP RI/DRP RI/DRP |
| The letter requests withdrawal of the 10 CFR Part 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings," Green non-cited violation (NCV 0500311/2016002-02) concerning the failure to follow the operability process as prescribed in OP-AA-108-115, "Operability Determinations & Functionality Assessments." The letter stated that PSEG was in full compliance with procedure OP-AA-108-115 when evaluating the baffle former bolt condition discovered at Unit 1 as it applied to Unit 2. The NRC will review PSEG's response and provide you a letter documenting the basis for any decision within 90 days.
| | NAME RVadella/rb for FBower/flb RMcKinley/rrm |
| | | DATE 11/3/16 11/3/16 11/3/16 |
| In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Your letter has also been added to ADAMS for the information of the public, and may be found under ADAMS Accession Number ML16298A161. Should you have any questions concerning this letter, please contact me at (610) 337-5150.
| |
| | |
| Sincerely,/RA/ Raymond R. McKinley, Chief Plant Support Branch 1 Division of Reactor Safety Docket No. 50-311 License No. DPR-75 cc: Distribution via ListServ Should you have any questions concerning this letter, please contact me at (610) 337-5150.
| |
| | |
| Sincerely,/RA/
| |
| Raymond R. McKinley, Chief Plant Support Branch 1 Division of Reactor Safety Docket No. 50-311 License No. DPR-75 cc: Distribution via ListServ
| |
| | |
| DISTRIBUTION: (via email) DDorman, RA DLew, DRA MScott, DRP DPelton, DRP RLorson, DRS JYerokun, DRS FBower, DRP RBarkley, DRP MDraxton, DRP RVadella, DRP PFinney, DRP, SRI AZiedonis, DRP, RI COtt, DRP, AA JBowen, RI OEDO RidsNrrPMSalem Resource RidsNrrDorlLpl1-2 Resource JTrapp, DNMS RMcKinley, DRP MGray, DRS JKulp, DRS
| |
| | |
| DOC NAME: G:\DRP\BRANCH3\Enforcement\PSEG BFB Violation Challenge\Salem Disputed NCV Ack Letter.docx ADAMS Accession No. ML16308A328 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRP RI/DRP RI/DRP NAME RVadella/rb for FBower/flb RMcKinley/rrm DATE 11/3/16 11/3/1611/3/16OFFICIAL RECORD COPY
| |
| }} | | }} |
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] |
See also: IR 05000311/2016002
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION I
2100 RENAISSANCE BLVD.
KING OF PRUSSIA, PA 19406-2713
November 3, 2016
EA-16-244
Mr. Peter Sena, III
President and Chief Nuclear Officer
PSEG Nuclear LLC - N09
P.O. Box 236
Hancocks Bridge, NJ 08038
SUBJECT: U.S. NUCLEAR REGULATORY COMMISSION RESPONSE TO DISPUTED
NOTICE OF NON-CITED VIOLATION 05000311/2016002-02
Dear Mr. Sena:
I am writing to acknowledge receipt of PSEGs letter dated October 24, 2016, in response to the
U.S. Nuclear Regulatory Commission (NRC) Inspection Report 05000272/2016002 and
05000311/2016002 issued on September 22, 2016.
The letter requests withdrawal of the 10 CFR Part 50, Appendix B, Criterion V, Instructions,
Procedures, and Drawings, Green non-cited violation (NCV 0500311/2016002-02) concerning
the failure to follow the operability process as prescribed in OP-AA-108-115, Operability
Determinations & Functionality Assessments. The letter stated that PSEG was in full
compliance with procedure OP-AA-108-115 when evaluating the baffle former bolt condition
discovered at Unit 1 as it applied to Unit 2. The NRC will review PSEGs response and provide
you a letter documenting the basis for any decision within 90 days.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRCs
Rules of Practice, a copy of this letter, its enclosure, and your response (if any) will be
available electronically for public inspection in the NRCs Public Document Room or from the
Publicly Available Records component of the NRCs Agencywide Documents Access and
Management System (ADAMS). ADAMS is accessible from the NRC website at
http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Your letter
has also been added to ADAMS for the information of the public, and may be found under
ADAMS Accession Number ML16298A161.
P. Sena -2-
Should you have any questions concerning this letter, please contact me at (610) 337-5150.
Sincerely,
/RA/
Raymond R. McKinley, Chief
Plant Support Branch 1
Division of Reactor Safety
Docket No. 50-311
License No. DPR-75
cc: Distribution via ListServ
ML16308A328
Non-Sensitive Publicly Available
SUNSI Review
Sensitive Non-Publicly Available
OFFICE RI/DRP RI/DRP RI/DRP
NAME RVadella/rb for FBower/flb RMcKinley/rrm
DATE 11/3/16 11/3/16 11/3/16
