Similar Documents at Salem |
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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]
Category:Written Event Report (30 or 60 day)
MONTHYEARLR-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
LR-N21-0083, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2021 & 30 Day Report for Salem Unit 2 Upflow Conversion2021-11-24024 November 2021
Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2021 & 30 Day Report for Salem Unit 2 Upflow Conversion
ML0333606682003-11-24024 November 2003
Special Report 03-002 Re Condenser Off Gas Monitor Being Inoperable for Greater than Seven Days
ML19031A9121997-02-25025 February 1997
LER 1977-009-01 for Salem Unit 1 No. 12 Containment Fan Coil Unit Inoperable
ML19031B1781977-02-25025 February 1977
LER 1977-010-01 for Salem, Unit 1 No. 12 Containment Fan Coil Unit Inoperable
ML19031B0621977-02-24024 February 1977
LER 1977-011-01 and LER 1977-013-01 for Salem Unit 1 Industrial Waste Was Discharged from the Treatment Area When the Ph Was Outside the Range of 6~5 to 8.5
ML19031B1791977-02-15015 February 1977
LER 1977-006-01 for Salem Unit 1 #12 Reactor Coolant Flow Channel 1 Inoperable
ML19031A9151977-02-15015 February 1977
LER 1977-007-01 for Salem Unit 1 No. 12 Steam Generator Steam Flow Channel II Inoperable
ML19031B0631977-02-15015 February 1977
LER 1977-008-01 for Salem Unit 1 No. 13 Steam Generator Steam Flow Channel I Inoperable
ML19031A9161977-02-0707 February 1977
LER 1977-004-01 for Salem, Unit 1, #13 Auxiliary Feed Pump Fail to Start
ML19031B5731977-02-0101 February 1977
LER 1976-029-01 for Salem Unit 1 Phase III Test Procedure
ML19031A8271977-01-31031 January 1977
LER 1977-005-01 for Salem, Unit 1, Hydraulic Line Flange on Nos. 11 and 12 Main Steam Isolation Valves and Subsequent Violation of Technical Specification 3.0.3
ML19031B0641977-01-28028 January 1977
LER 1976-031-01 for Salem, Unit 1, Boron Injection Tank Inoperable
ML19031B0651977-01-28028 January 1977
LER 1977-001-01 for Salem, Unit 1, Containment Pressure Protection, Channel II, PT-948C, Inoperable
ML19031B0671977-01-28028 January 1977
LER 1977-002-01 for Salem, Unit 1, Pipe Failure on Letdown Vent Line
ML19031B5741977-01-28028 January 1977
LER 1976-030-01 for Salem Unit 1 No. 11 and No. 12 Boric Acid Storage Tanks Inoperable
ML19031B1801977-01-19019 January 1977
LER 1976-028-42 for Salem, Unit 1 Radioactive Spill and Unauthorized Release
ML19031B0681977-01-14014 January 1977
LER 1976-026-01 for Salem, Unit 1, Boron Injection Tank Inoperable
ML19031A7621977-01-14014 January 1977
LER 1976-020-01 for Salem, Unit 1 High Reactor Coolant System Chlorides
ML19031B1811977-01-14014 January 1977
LER 1976-025-01 for Salem Unit 1 Reduction of Shutdown Margin During Special Test Exceptions
ML19031A9191977-01-0404 January 1977
LER 1976-024-01 for Salem, Unit 1, Failure of Radiation Monitoring System Channel Rlla, Containment/Plant Vent Air Particulate Monitor
ML19031A5471977-01-0404 January 1977
LER 1976-017-01 for Salem, Unit 1 Inoperable Personnel Air Lock - Elevation 100'
ML19031A9201977-01-0303 January 1977
LER 1976-016-01 for Salem Unit 1 Improper Use of Test Leads
ML19031A9181976-01-0707 January 1976
LER 1976-021-01 for Salem, Unit 1, Boron Injection Tank Inoperable
2023-08-03
[Table view] |
Text
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Frederick W. Schneider Public Service Electric and Gas Company 80 Park Place Newark. N.J. 07101 201/622-7000
. Vice President
- Production February 24, 1977 'Rlegulatory PQC~!!ill Mr. James P. O'Reilly Director of USNRC Off ice of Inspections and Enforcements Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. O'Reilly:
LICENSE DRP-70 DOCKET NO. 50-272 ENVIRONMENTAL TECHNICAL SPECIFICATIONS REPORTS 77-ll/3L AND 77-13/3L Pursuant to the requirements of Salem Generatirig Station Technical Specifications, Appendix B, Section 5.6.2.1, we are submitting two reports for non-radiological occurrences that exceeded the limit-ing conditions for operation specified in Section 2 of Appendix B*.
These occurrences were identified as the result of a station audit, the findings of which were issued to the responsible department head on February 1, 1977.
To provide assurance in the future that these events will be recog-nized as reportable events at the time they occur, the data sheets and procedures associated with operating the plant in conformance with the Appendix B Technical Specifications will be reviewed.
Modifications will be made as necessary to identify reportable out-of-specif ication conditions as they are documented. This activity will be complete by April 1, 1977. ---~~~
Sincerely, 2253
. -~
Report Number: 9-11/3L Rep6rt 'Date: 2/16/77 Occurrence Date: 1/13/77 Facility Salem Generating Station Public Service .Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
Industrial waste was discharged from the treatment area when the pH was outside the range of 6~5 to 8.5. (Environmental Technical Specification 2.2.3 pH)
DESCRIPTION OF OCCURRENCE:
The pH recorder controlling the discharge of the solution was turned off and was reading a pH of 7. The automatic valve for discharge was open, because it thought the pH was 7. The treatment basin was oper-ating and acid and/or caustic was automatically being added to attempt to neutralize the solution.
DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:
The sample line to the discharge pH cells was frozen and no sample was flowing. Consequently, the actual pH of the discharge could not be read automatically.
ANALYSIS OF OCCURRENCE:
The pH of the discharge was found to be 5. This solution discharges to the ciculating water (river water) system and is diluted by approxi-mately 370 to 1 .. The normal river water pH is 7.5 . . It was found that a dilution of pH 2.5 solution by a factor of 370 to 1 with river water changes the pH to 7.4. In this case, the change in the circulating water pH would not be measurable and no adverse effects on the environ-ment can be postulated.
CORRECTIVE ACTION:
The frozen sample line was thawed, the leaks were fixed, the heat.
tracing was repaired, a temporary heated shelter was installed, and the automatic controls were put back in service.
Prepared by D. E. Kudera
~~~~~~~~~~~~
Manager - S em Generating Station SORC Meeting No~ 17-77
~~~~~~~~~
., * ~ j-Report Number: .-13/3L Rep~rt: ¥~ate: 2/16/77 Occurrence Date: l/i3/77 Facility Salem Generating Station Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
On December 8, 12, 17, 21, 22, 23, no sample of the discharge at Non-Rad Waste was taken. Therefore, the suspended solids analysis was not done in accordance with Environmental Technical Specification 2.2.2. Condition was identified by licensee in review of data on 1/13/77.
DESCRIPTION OF OCCURRENCE:
No sample was taken during discharge of the industrial waste system on six days in December. One of these days there was. only about one minute of discharge. There were a total of 20 days of discharge in December.
DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:
Personnel error in not following sampling schedule.
ANALYSIS OF OCCURRENCE:
The specification to sample for suspe~ded solids on a daily basis when discharging. does not have a limiting condition for operation. The data gathered is to be used in an annual average calculation. No adverse effect to the environment can be postulated.
CORRECTIVE ACTION:
Chemistry personnel have been apprised* of the importance of meeting the requirements of the sampling/analysis schedule.
N. Millis Manager - Generating Station SORC Meeting No. 17-77.
~~~~~~~~~
