Similar Documents at Salem |
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Category:Letter
MONTHYEARIR 05000272/20244032024-09-25025 September 2024 and Salem Nuclear Generating Station, Units 1 and 2, Cybersecurity Inspection Report 05000354/2024403, 05000272/2024403, and 05000311/2024403 (Cover Letter Only) ML24267A1082024-09-23023 September 2024 Submittal of the Reactor Vessel Material Surveillance Program Capsule Technical Report IR 05000272/20244022024-09-23023 September 2024 and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2024402, 05000272/2024402, and 05000311/2024402 (Cover Letter Only) IR 05000272/20240052024-08-29029 August 2024 Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Report 05000272/2024005 and 05000311/2024005) IR 05000272/20240022024-07-30030 July 2024 Integrated Inspection Report 05000272/2024002 and 05000311/2024002 LR-N24-0012, Application to Revise Technical Specifications and 10 CFR 50.12 Exemption Request to Implement Optimized ZIRLO Fuel Rod Cladding2024-07-24024 July 2024 Application to Revise Technical Specifications and 10 CFR 50.12 Exemption Request to Implement Optimized ZIRLO Fuel Rod Cladding ML24145A1772024-07-15015 July 2024 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 236, 349, and 331 Modify Exclusion Area Boundary IR 05000272/20245012024-06-12012 June 2024 and Salem Nuclear Generating Station, Units 1 and 2 - Emergency Preparedness Biennial Exercise Inspection Report 05000354/2024501, 05000272/2024501 and 05000311/2024501 ML24099A1572024-05-29029 May 2024 Issuance of Amendment Nos. 348 and 330 Permanent Extension of Type a and Type C Containment Leak Rate Test Frequencies ML24150A0032024-05-28028 May 2024 Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) and Proposed Amendment to the Decommissioning Trust Agreement LR-N24-0041, Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response2024-05-22022 May 2024 Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response IR 05000272/20240102024-05-16016 May 2024 Fire Protection Team Inspection Report 05000272/2024010 and 05000311/2024010 LR-N24-0038, Pressure Boundary Leakage Through a Reactor Coolant Pump Thermal Barrier Heat Exchanger2024-05-0909 May 2024 Pressure Boundary Leakage Through a Reactor Coolant Pump Thermal Barrier Heat Exchanger IR 05000272/20240012024-05-0707 May 2024 Integrated Inspection Report 05000272/2024001 and 05000311/2024001 LR-N24-0039, Steam Generator Tube Inspection Report - Twenty-ninth Refueling Outage2024-05-0606 May 2024 Steam Generator Tube Inspection Report - Twenty-ninth Refueling Outage LR-N24-0034, 2023 Annual Radioactive Effluent Release Report (ARERR)2024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report (ARERR) LR-N24-0035, 2023 Annual Radiological Environmental Operating Report (AREOR)2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) LR-N24-0024, Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-26026 April 2024 Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary LR-N24-0011, Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-0505 April 2024 Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000272/20240112024-04-0101 April 2024 and Salem Nuclear Generating Station, Units 1 and 2 - Plant Modification and Annual Problem Identification and Resolution Inspection Report 05000354/2024011, 05000272/2024011, and 05000311/2024011 LR-N24-0028, and Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal2024-03-28028 March 2024 and Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal LR-N24-0021, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2024-03-20020 March 2024 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums ML24071A2132024-03-12012 March 2024 Senior Reactor and Reactor Operator Initial License Examinations LR-N24-0020, Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report2024-03-0707 March 2024 Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report LR-N24-0022, Spent Fuel Cask Registration2024-02-29029 February 2024 Spent Fuel Cask Registration IR 05000272/20230062024-02-28028 February 2024 Annual Assessment Letter for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2023006 and 05000311/2023006 IR 05000272/20244012024-02-26026 February 2024 and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2024401, 05000272/2024401 and 05000311/2024401 (Cover Letter Only) IR 05000272/20230042024-02-0505 February 2024 Integrated Inspection Report 05000272/2023004 and 05000311/2023004 LR-N24-0009, In-Service Inspection Activities2024-02-0505 February 2024 In-Service Inspection Activities 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 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 ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement ML23324A3072023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24250A0582023-11-14014 November 2023 PSEG to Marine Mammal Stranding Center, Salem Sea Turtle Stranding Response Services 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 2024-09-25
[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
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~gulatory Docket File
- Frederick W. Schneider Public Service Electric and Gas Company 80 Park Place Newark. N.J. 07101 201/622-7000 Vice President Production January 28, 1977 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 NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 76-30/3L Pursuant to the requirements of Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1, we are submitting
. -- / . . Licensee Event Report for Reportable Occurrence 76-30/3L. This report is required within thirty (30) days of the occurrence.
Sincerely yours, CC: Director, Office of Inspection and Enforcement (30 copies)
Director, Office of Management Information and Program Control (3 copies)
- 1111
- - p Report Date:
Occurrence Date:
Facility:
e 1/10/77 12/28/76 Salem Generating Station Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
No. 11 and No. 12 Boric Acid Storage Tanks Inoperable.
CONDITIONS PRIOR TO OCCURRENCE:
Operational Mode 5, Reactor Power 17.5%, 85 mWe, Plant Pressure 2235 psig, Plant Temperature 552°F.
DESCRIPTION OF OCCURRENCE:
On 12/28/76, the Chemistry Foreman reported that No. 11 and* No. 12 Boric Acid Storage Tank sample analysis for boron concentration to be 19,946 ppm and 19,968 ppm, respectively. These values being be-low the minimum concentration o~ 20,100 ppm as specified in Technical Specifications L.C.O. paragraph 3.1.2.8, the Shift Supervisor imple-mented Technical Specifications action statement for L.C.O. 3.1.2.8.
The Operations Department batched one batch of boric acid and had the Chemistry Department resample. The results indicated No. 11 at 20,335 ppm and No. 12 at 20,281 ppm. Technical Specifications action statement was cancelled.
DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:
The cause of this occurrence was personnel error in analyzing the boron concentration of the Boric Acid Storage Tank.
-- /
ANALYSIS OF OCCURRENCE:
_Improper sampling analytical techniques declared the Boric Acid Storage Tanks inoperable. Batching and resampling verified proper Boron concentration in No. 11 and No. 12 Boric Acid Storage Tanks.
At no time was there any hazard to the general public or site per-sonnel.
CORRECTIVE ACTION:
All Chemistry personnel were re-instructed on sample techniques and procedural instructions which requires duplicate analysis to be per-formed.
FAILURE DATE:
This is the third report of this type. Equipment indentification not applicable.
Prepared by B. Ca.of ield Salem Generating Station SORC Meeting No. 8-77
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LICENSEE EVENT REPORT *
LICENSEE 1..ICENSE EVENT NAME ~ l..ICENSE NUMBER TYPE TYPE
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. REPORT REPORT CATECORY TYl'E SOURCE COCKET NUMBER EVENT CATE *REPORT DATE fcil11 CON"TI P I 0 I lf.J ~ I 0 I 51 0 I -I 0 I 2 I 71 2J 11 I 2 I 2 I 8 17 I 6 I I 0 111 1 I 0 I 7 I 7J t-'-i ~ 59 60 61 69 74 75
@:filfDuring Hode 1, the Chemistry Foreman reported that #11 and 12 Boric Acid I 7 8 9 so
@£] Storage Tank sample analysis for boron concentration to be 19,946 ppm and 7 a9
@E] 19,968 ppm respectively. These values being below the minimum concentra-7 a
[9JiJ1tion of 20,100 ppm as specified in Tech. Spec L.C.O. paragraph 3.1.2.8, I 7 8 9
~ jThe Shift Supervisor implemented Tech Spec action statement for L.C.O*.
eo 7 8 9 PRIME so SYSTEM CAUSE COMPONENT COMPONENT
!n'h1 COCE COCE COMPONENT COCE
- SUP9l.IER MANUFACTURER VIOl..ATION
~IP IC I l.8...1. I XI XI XI XI~ l1J IZ 19 19 19 I lJ:!I 7 8 9 10 11 12 . 17 43 "" 47 48 CAUSE DESCRIPTION
~ l The cause of this occurrence was personnel error jp analyzing the boron I
~I 9
7 89 concentration of the boric acid storage tanks. j so
[ill]
7 e~g,..----------------------------------------=-so FACILITY METHOOOF STATUS "4POWER OTHE-R STATUS DISCOVERY DISCOVERY DESCRIPTION
[ill] tru. I 0 1117 I '~~~N~/~A.__~---!I UtJ I Chemistry Analysis 7 G 9 10 12 13 44 45 80 FORM OF ACTIVITY CONTENT RELEASEO OF REl..EASE AMOUNT OF ACTIVITY LOCATION OF RELEAS£ Eli]
7 8 W
9 W
10 I
11 N/A 44 II~~~~~---N~/A~~~~~~I
~ 80 PERSONNEL EXPOSURES NUMBER TYPE Of:SCRIPTION GE ' 0 I 0 I 0 I 7 8 9 11 lZ.J 12 I N/A 1!--::3:-----....;;..;.....-.;;;.-._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _--.d.&) J PERSONNEL INJURIES NUMBER DESCRIPTION
[ili] I 0 IO IO I "'21_______...;;N~/..-A;;..__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~I 7 8 g 11 1~ so
. OFFSITE CONSEQUENCES
µEl19 . . N/A LOSS OR OAMAGE TO FACILITY
. TYPE CESCRIPTION
1 a~
IZI I N/A
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J ADDITIONAL FACTORS
~I EVENT DESCRIPTION (Continued on Page 2) I 7 8 9 00 fil!]
1 a~a------.------.----------.----~------~~-~-------~eo NAME: _ _ _ _ _ _ _ B_._**_E_._c_a_n_f_i_*e_l_d____ PHONE: (609) 365-7000 Ext.Salem-52
-- . e Licensee Event Report
- EVENT DESCRIPTION (Continued) paragraph 3.1.2.8. The Operations Department batched one batch of *boric acid and had the Chemistry Department resample. The results indicated No. 11 at 20,335 ppm and No. 12 at 20,281 ppm. Technical Specifications action statement was cancelled. No redundant systems were available. This is the third occurrence of this type. (76-30/3L).