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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~iegulafory Docket *File Frederick W. Schneider Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201/622-7000 Vice President Production February 25, 1977 Mr. James P. O'Reilly Director of USNRC Of £ice of Inspections and Enforcements Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. O'~eilly:
LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 77-10/3L 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 77-10/3L. This report is required within thirty (30) days of the occurrence.
Sincerely yours,
/
CC: Director, Office of Inspection * ,.. ** **. oo:." - -
and Enforcement (30 copies)
Director, Office of Management Information and Program Control (3 copies)
' Report Number: 77-10/3L Report Date: 2/4/77 1 R'egu!alory Docket fll@
-~
Occurrence Date: 2/1/77 Facility Salem Generating Station Publi.c Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
No. 12 Containment Fan Coil Unit Inoperable CONDITIONS PRIOR TO OCCURRENCE:
Operational Mode 3, Primary Pressure: 2232 psig, Tave: 547°F DESCRIPTION OF OCCURRENCE:
On 1/30/77, flow indication on Control Room Bezel for No. 12 Contain-ment Fan Coil Unit showed 1200 gpm with the unit secured and service water isolation valve shut. A work order was submitted to Performance Department to investigate and repair. On 2/1/77 at 1610, No. 12 C.F.c.u.
- was declared inoperable and Technical Specification Action Statement for L.c.o. 3.6.2.3 was put in affect for the p_urpose of repairing valve 12SW223.
DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:
During periods when the Fan Coil Unit is shutdown, 12SW223 is the only valve which automatically shuts to secure service water flow through the unit. Investigation revealed a broken eye bolt on the clevis con-nector between the actuator rod and the valve stem linkage, leaving the 12SW223 valve approximately 20% open at all times~
ANALYSIS OF OCCURRENCE:
During normal or emergency mode of operation of the Fan Coil Unit, 12SW223 controls the service water flow rat~ through the unit. The 20% open position allowed sufficient service water flow for normal operation but restricted flow rate below necessary emergency condition requirements. Technical Specification Action Statement 3.6.2.3 states that with one group of containment cooling fans inoperable, restore the inoperable group to operate status within 72- hcirirs oi be in Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. No .. 12 C.F.C.U. was declared oper-able within four hours, therefore, Technical Specifications were not violated. At no time.was there any danger to the health and safety of the general public or site personnel.
Report No. 77-10/3L 2/4/77
.. -- --(.
CORRECTIVE ACTION:
The broken clevis eye bolt was replaced and the valve restroked in accordance with procedure l-PD-14.1.001. The valve was tested and proper operation verified. Work order #PD-1588 was initiated to Maintenance Department to have 12SW223 valve internals inspected for evidence of binding or wear.
FAILURE DATA:
This is the first occurrence of this type.
Manufacturer: Masoneilan International Model No. 3336300 10 inch ball valve Prepared by A. Kapple
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Manager ~ ~alem Generating Station SORC Meeting No. 14-77
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LICENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE*
@El!N1J1s1G1s1~1 ~50101*-10101010101-1 OI qJ k41 ll ll ll 1Jo W-UJ REPORT REPORT CATEGORY TVl'E SOURCE OOCKET NUMBER EVENT CATE REPORT CATE .
roTi1 coN'TlR..LQJ r-ili 57 58 UJ 59 L!J 60 I 0 I 51 0 I -I 0 I 2 I 71 2J 61 I 0 I 2 I 0 11 17 I 7 I I 0 I 2 I 0 I 4 I 7 I 7J 69 74. 75
- -:*.;\\\<~ * @liliv;::~~~R~~:: 1 operation, an abnormal service water flow rate was observe4
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- ~;~.- @E] I on #12 Containment Fan Coil Unit. On 2/1/77 the Unit was declared in- J 80
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SYSTEM CODE CAUSE CODE COMPONENT cooe COMPONENT SUP9LIER COMPONENT MANUFACTURER VIOLATION (77-10/3L -?(l )
> _:. ... . 7
@m I A I A I Lill 8 9 10 11 IV I A. I LI Y I E.J.X.J 12 17 llJ 43 IM 11 12 I 0 I 44 47 lliJ 48 CAUSE DESCRIPTION
~IJhe abnormally high service water flow rate was due to a broken clevis ey¢
@:fillbolt on the actuating rod for valve 12SW223. This allowed 12SW223 to remaj.n 7 89 80
[@]!approximately 20% open at all times. Examination of other components of I 7 89 80 FACILITY METMOOOF 1.1.1 STATUS 'JI.POWER OTHER STATUS OISCOVERV OISCOVERV CESCRIP'TION L!J.!..J 7 ll
[LJ .
9 I 01 01 0 I 10 12 13 N/A 44 I ~
45 I
46 N/A .
80 I
FORM OF ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE (iliJ 7 8 LU 9
L]J 10 I
11 N/A 44 I I45 80 I
PERSONNEL EXPOSURES r.r.:"I NUMBER TYPE OESCRIPTION L!.l:!JIOIOIOI 7 8 9 11 lZJ 12 l.___ _~N=/~A=--------------,..---------=1 13 J PERSONNEL INJURIES NUMBER OESCRIPTION (ili]8 I90 I 0 I 0.11 I ._I12:-------=N=/-=-A=-------------------=1 I 7 ao OFFSITE CONSEQUENCES
~1 9 .. N/A J LOSS OR DAMAGE TO FACll.ITY TV~ OESCRIPTION Eli)s"S IZ I I N/A 1 10 J PUBLICITY 7lilil8~9-~~~------~--1.:J../-.C....-------~---------------...J r * ** "':." . 80 ADDITIONAL FACTORS.
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1 GE&~i----------""'.---~~--------~----~-----------~ao NAME: _ _ _ _ _ _ A_._K_a_p=-=.p_l_e_ _ _ _ _ _ __ PHONE: ( 6 09) 365-7 0 00 Ext. Salem-62:
--Re.port No. LER 77-10/3L
- .; ilt CASUE DESCRIPTION (Continued) the valve operating linkage showed no excessive wear or mating surface clearance. - A work order has been initiated to have the valve internals inspected for possible binding or wear. Masoneilan International Inc.
Model No. 3336300 - 10 inch ball valve.