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Category:Letter
MONTHYEARIR 05000272/20240032024-10-30030 October 2024 Integrated Inspection Report 05000272/2024003 and 05000311/2024003 ML24296B1932024-10-23023 October 2024 Project Manager Assignment LR-N24-0068, Core Operating Limits Report - Cycle 282024-10-21021 October 2024 Core Operating Limits Report - Cycle 28 LR-N24-0063, Emergency Plan Document Revision Implemented September 18, 2024. Includes NC.EP-EP.ZZ-0903, Rev. 7, Opening of Emergency Operations Facility (EOF)2024-10-0707 October 2024 Emergency Plan Document Revision Implemented September 18, 2024. Includes NC.EP-EP.ZZ-0903, Rev. 7, Opening of Emergency Operations Facility (EOF) 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) ML24267A1082024-09-23023 September 2024 Submittal of the Reactor Vessel Material Surveillance Program Capsule Technical Report 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 05000272/LER-2024-001, 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 IR 05000272/20244032024-03-20020 March 2024 And Hope Creek Generating Station - Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000272/2024403, 05000311/2024403, and 05000354/2024403 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) LR-N24-0009, In-Service Inspection Activities2024-02-0505 February 2024 In-Service Inspection Activities IR 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 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 2024-09-23
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000272/LER-2024-001, 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 05000311/LER-1922-001, Invalid Safety Injection and Valid Reactor Trip Due to Inaccurate Steam Generator Pressure Indications2023-02-21021 February 2023 Invalid Safety Injection and Valid Reactor Trip Due to Inaccurate Steam Generator Pressure Indications 05000272/LER-2017-0012018-01-0808 January 2018 Containment Integrity Inoperable for Longer than Allowed by Technical Specifications, LER 17-001-00 for Salem Generating Station, Unit 1 Regarding Containment Integrity Inoperable for Longer than Allowed by Technical Specifications 05000311/LER-2016-0022017-09-0707 September 2017 Automatic Reactor Trip due to Main Turbine Trip, LER 16-002-01 for Salem, Unit 2, Regarding Automatic Reactor Trip Due to Main Turbine Trip 05000311/LER-2015-0022017-09-0707 September 2017 P.O. Box 236, Hancocks Bridge, NJ 08038-0236 PSEG Nadea, II,C OCT 0 2 2015 LR-N15-0205 10 CFR 50.73 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 LER 311/2015-002-00 Salem Nuclear Generating Station Unit 2 Renewed Facility Operating License No. DPR-75 NRC Docket No. 50-311 SUBJECT: Licensee Event Report 311/2015-002-00 In accordance with the requirements of 10 CFR 50.73(a)(2)(iv), PSEG Nuclear LLC is submitting the enclosed Licensee Event Report (LER) Number 2015-002-00, "Reactor Trip Due to Loss of 4kV Non-Vital Group Bus." There are no regulatory commitments contained in this letter. If you have any questions or require additional information, please contact Mr. David Lafleur of Salem Regulatory Assurance at 856-339-1754. Sincerely, John F. Perry Site Vice President — alem Attachment OCT 0 2 2015 10 CFR 50.73 Page 2 LR-N15-0205 CC Mr. D. Dorman, Administrator— Region 1, NRC Mr. T. Wengert, Licensing Project Manager (acting) — Salem, NRC Mr. P. Finney, USNRC Senior Resident Inspector, Salem (X24) Mr. P. Mulligan, Manager IV, NJBNE Mr. R. Braun, President and Chief Nuclear Officer — Nuclear Mr. T. Cachaza, Salem Commitment Tracking Coordinator Mr. L. Marabella, Corporate Commitment Tracking Coordinator Mr. D. Lafleur, Salem Regulatory Assurance NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION 01-2014) t, , .1 • '., LICENSEE EVENT REPORT (LER) 'S ree Page 2 or required number of digits/characters for each block) APPROVED BY OMB: NO. 3150-0104 EXPIRES: 0113112017 Estimated burden per response to comply with this mandatory collection request: 80 hours. Reported lessons learned are Incorporated Into the licensing process and fed back to Industry. Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet e-mall to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to Impose an information collection does not display a currentlyvaild OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection. 1. FACILITY NAME Salem Generating Station - Unit 2 2. DOCKET NUMBER 05000311 3. PAGE 1 OF 4 4. TrrLE Reactor Trip Due to Loss of 4 kV Non-Vital Group Bus, LER 15-002-01 for Salem, Unit 2, Regarding Reactor Trip Due to Loss of 4 kV Non-Vital Group Bus 05000311/LER-2017-0012017-06-13013 June 2017 Emergency Diesel Generator Start Due to a Loss of Power to the 2C 4160 Volt Vital Bus, LER 17-001-00 for Salem, Unit 2, Regarding Emergency Diesel Generator Start Due to a Loss of Power to the 2C 4160 Volt Vital Bus 05000272/LER-2015-0022016-11-16016 November 2016 Condition Prohibited by Technical Specification for One Channel of Steam Generator Level Indication Inoperable, LER 15-002-002 for Salem, Unit 1, Regarding Condition Prohibited by Technical Specification for One Channel of Steam Generator Level Indication Inoperable 05000311/LER-2016-0062016-10-31031 October 2016 Automatic Reactor Trip Due to Trip of the 21 Reactor Coolant Pump, LER 16-006-00 for Salem, Unit 2, Regarding Automatic Reactor Trip Due to Trip of the 21 Reactor Coolant Pump 05000311/LER-2016-0052016-08-29029 August 2016 Automatic Reactor Trip due to Main Generator Protection Trip, LER 16-005-00 for Salem Generating Station, Unit 2 Regarding Automatic Reactor Trip due to Main Generator Protection Trip 05000272/LER-2016-0012016-07-0505 July 2016 Unanalyzed Condition due to Degraded Reactor Baffle to Former Bolts, LER 16-001-00 for Salem, Unit 1, Regarding Unanalyzed Condition due to Degraded Reactor Baffle to Former Bolts 05000311/LER-2016-0032016-04-14014 April 2016 Automatic Reactor Trip due to Main Generator Protection Trip, LER 16-003-00 for Salem, Unit 2, Regarding Automatic Reactor Trip due to Main Generator Protection Trip 05000311/LER-2016-0012016-03-21021 March 2016 AFW Loop Response Time Exceeded Technical Specifications, LER 16-001-00 for Salem, Unit 2, Regarding AFW Loop Response Time Exceeded Technical Specifications 05000272/LER-2015-0072016-01-29029 January 2016 Inoperable Control Room Emergency Air Conditioning System Due to Failed Charcoal Filter Surveillance Test, LER 15-007-01 for Salem, Unit 1, Regarding Inoperable Control Room Emergency Air Conditioning System Due to Failed Charcoal Filter Surveillance Test 05000311/LER-2015-0032016-01-22022 January 2016 Both Trains of High Head Safety Injection Inoperable Due to a Relief Valve Failure, LER 15-003-00 for Salem, Unit 2, Regarding Both Trains of High Head Safety Injection Inoperable Due to a Relief Valve Failure LR-N14-0128, Special Report 311/14-04-00, Pursuant to the Requirements of Technical Specification (TS) 3.4.10.3, Action D, for Overpressure Protection System Used to Mitigate an RCS Pressure Transient2014-05-13013 May 2014 Special Report 311/14-04-00, Pursuant to the Requirements of Technical Specification (TS) 3.4.10.3, Action D, for Overpressure Protection System Used to Mitigate an RCS Pressure Transient ML1015505772010-04-0808 April 2010 Event Notification for Salem on Storm Drain System Tested Positive for Tritium ML1034404492010-04-0505 April 2010 Document: Apparent Cause Evaluation Template Document: from Robert Montgomery LR-N05-0419, LER 05-04-00 for Salem Generating Station, Unit 2 Regarding Operation in a Condition Prohibited by Technical Specification - Containment Isolation Valves2005-08-15015 August 2005 LER 05-04-00 for Salem Generating Station, Unit 2 Regarding Operation in a Condition Prohibited by Technical Specification - Containment Isolation Valves ML0435704542004-12-13013 December 2004 Special Report 311/04-010 for Salem Unit 2 Regarding the 2R45 Detector Being Inoperable on 12/01/2004 ML19030A6261980-03-0303 March 1980 Licensee Event Report Inoperability of Air Particulate Detector Pump ML19031B0801978-09-18018 September 1978 Submit Licensee Event Report for Reportable Occurrence 78-56/03L ML19031B5101978-08-24024 August 1978 LER 1978 for Reportable Occurrence 78-43/03L on Quadrant Power Tilt Ratio Greater than 1.02 ML19031B0381978-08-24024 August 1978 LER 1978-042-03 for Salem Unit 1 Excessive Trip Setpoint During Functional Test on No. 13 S/G Steam Flow Channel 1 ML19031B5091978-08-24024 August 1978 LER 1978 for Reportable Occurrence 78-45/03L on 100 Ft. Elevation Personnel Airlock Inoperable ML19031B0361978-08-24024 August 1978 LER 1978-044-03 for Salem Unit 1 Inoperability of No. 11 S/G Feedwater Flow Channel 2 ML19031A8951978-08-14014 August 1978 LER 1978-041-03 for Salem Unit 1 Excessive Quadrant Power Tilt Ratio During Power Escalation ML19031B0391978-08-0303 August 1978 LER 1978-040-03 for Salem Unit 1 Inoperability of Makeup Valve from Demineralized Water Plant ML19031B5121978-08-0202 August 1978 Licensee Event Report 1978 for Reportable Occurrence 78-39/03L Re No. 13 Containment Fan Foil Unit Inoperable ML19031B5111978-08-0202 August 1978 Licensee Event Report 1978 for Reportable Occurrence 78-38/03L Re No. 11 Steam Generator Flow Channel II Inoperable ML19031B1651978-07-20020 July 1978 LER 1978-035-03 for Salem Unit 1 Loss of Power to No. 2 Station Power Transformer ML19031B5131978-07-20020 July 1978 Licensee Event Report 1978 for Reportable Occurrence 78-36/03L Re Vital Bus Under Voltage Relay Setting Outside Technical Specification Limit ML19031C0301978-07-20020 July 1978 07/20/1978 Letter Reportable Occurrence on Non-Radwaste Sampling for Suspended Solids ML19031B1671978-07-12012 July 1978 LER 1978-026-03 for Salem Unit 1 Failure of Motor Operated Valve ML19031C0311978-07-12012 July 1978 07/12/1978 Letter Reportable Occurrence on Missed Surveillance of Monthly Functional Test of Steam Generator Blowdown Radiation Monitoring Channels ML19031B0401978-07-12012 July 1978 LER 1978-033-03 for Salem Unit 1 No. 11 Steam Generator Steam Flow Channel II ML19031B5151978-07-10010 July 1978 Licensee Event Report 1978 for Reportable Occurrence 78-30/03L Re Control Bank and Shutdown Rod Misalignment ML19031B0411978-06-30030 June 1978 LER 1978-027-03 for Salem Unit 1 Malfunctioning Exterior Door of Containment Entry Air Lock ML19031B5171978-06-30030 June 1978 No. 1 - Licensee Event Report 1978 for Reportable Occurrence 78-28/03L Re Inoperable 100 Ft. Elevation Air Lock Interior Door ML19031C0321978-06-28028 June 1978 06/28/1978 Letter Reportable Occurrence on Non-Radwaste Sampling for Suspended Solids Analysis ML19031A8191978-06-21021 June 1978 LER 1978-029-01 for Salem Unit 1 Inoperability of Two Power Range Channels During Training Startups ML19031B5191978-05-15015 May 1978 LER 1978-025-03 for Salem Generating Station Unit 1 Re Missed Tech. Specification Surveillance: 4.8.2.4.1 DC and 4.8.2.2 AC Breaker Alignment and Power Availability ML19031B5201978-05-10010 May 1978 LER Supplemental Report for Reportable Occurrence 77-43/03L Re Inoperable No 12 S/G Channel 3 Due to Failed Pressure Transmitter ML19031B5211978-04-27027 April 1978 04/27/1978 Letter Reportable Occurrence on Excessive Concentration of Iodine in Milk Sample Collected at Environmental Sampling Location ML19031B0421978-04-17017 April 1978 LER 1978-021-03 for Salem Unit 1 Missed Surveillance of Fluoride Sample ML19031A8961978-04-17017 April 1978 LER 1978-022-01 for Salem Unit 1 Seismic Test Results for NEMA 12 Enclosures ML19031B5221978-04-11011 April 1978 LER 1978-080-03 for Salem Unit 1 Inoperability of 1B Diesel ML19031C0331978-04-0606 April 1978 04/06/1978 Letter Reportable Occurrence on Non-Radwaste Sampling for Suspended Solids Analysis ML19031B5231978-04-0606 April 1978 LER 1977-042-03 for Salem Unit 1 Inoperability of Channel III Pressurizer Level ML19031A8971978-04-0606 April 1978 LER 1978-018-03 for Salem Unit 1 Excessive Trip Setpoint During Functional Test on PWR Range Channel N43 ML19031A8981978-04-0505 April 1978 LER 1978-017-03 for Salem Unit 1 Tilt Ratio During Power Escalation 2024-05-09
[Table view] |
Text
Frederick W. Schneider Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201/622-7000 Vice President Production 1*,
' February 17, 1977 Mr. James P. O'Reilly Director of USNRC Off ice of Inspections and Enforcements Region 1 631 Park Avenue King of Prussiar Pennsylvania 19406
Dear Mr. O'Reilly:
LICENSE NO. DPR-70 DOCKET NO. so~272 REPORTABLE OCCURRENCE 76-04/3L SUPPLEMENTAL REPORT Pursuant to the requirements of Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1, we are submitting.
a Supplemental Report to 76-04/3L dated 9/15/76.
Sincerely yours, 2076 CC: Director, Office of Inspectibri and Enforcement (30 copies)
Director, Office of Management Information and Program Control (3 copies)
SUPPLEMENTAL REPORT TO
- - - _a LER 76-04/3L 9/15/76 -
LICENSEE EVENT REPOA f9 _ - --- -_
CONTROL BLOCK 6
UCENSEE L.ICENSE EVENT NAME L.ICENSE NUMBER' TYPE . TYPE
@l!J!N tJt S !GI S 111 150101-10101010101-101qJ Js4lll ll ll 1Jo 10 111
~
- . ~
CATEGCRVR~~..:T :~~~~~ . CCCKET NUMBER EVENT DATE . REPORT CATI!
IOTt1 CON'Tt.RJ..Qj
~ 57 68 L9
. 59
~
60 I 0 I 51 0 I -I 0 I 21 71 2J 61 .
I 0 I 91 0 I 21 71 61 69 74 I 0 I 11 21 81 71 75 id-EVENT DESCRIPTION _
.@Ell During Mode 6 operation, RHR System-in service. the 1A Vfral 7 8 9
@1!11 Bus was being transferred to an alternate source of power to allow 7 89
@El the lA Vital Instrument Bus Inverter to be deenergized. Durin the
- j0 15j I lA Vital Instrument Bus transfer, 1RH2 closed resulting in a: loss of ,. - *.
7 8 9 so
~I rum. flow to. the RCSU. No-redundant system was available during this 1*
7 8 9 CAUSE PRIME COMPONENT COMPONENT so SYSTEM CODE* CODE COMPONENT CODE SUPf'L.IER MANUFACTURER" VIOL.ATIOH*
--@mtE 1B I - U2J IZ IZ IZ IZ IZ.IZ r LLl - I zl 919 I9 I l~. J 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION
~I The 115 VAC vital instrument busses are nomaJJy fed through their
~{associated inverters. These inverters* are eguipped with automatic 7 8-9
[ilfil I load transfer.switches which trans£ er the load to the -backup power 7 8 9 FACILITY METHOD OF
- STATUS .. ___ ;_"°'POWER-* - - - --OTHE-RSTATUS* --OISCOVER*Y* -- _-- DISCOVERY DESCRIPTlON
[fil ~. --- I O! Q 01 I NIA - . I l..aJ N&
I~46=---".!..'-"-'1---------------;......;----"----~so J*
1 a g 10 _ 12 13 44 45 FORM OF- - .
ACTIVITY CONTENT
[lfil 7- 8 w
REL.EASED OF RELEASE.
', 9 . -
LI 10 . - - 11 I
AMOUNT OF ACTIVITY N/A 44 I -1.,..,,____
45 L.OCATION OF REL.EASE N._/=A_ _ _ _ _ _ _ _ _-...:1 so -
PERSONNEL EXPOSURES
. NUMBER TYPE DESCRlllTION * - .
1010101 1..[JI~-~--~N~/~A:...----~~-~~------~-~-dJ 1 -s 11 12 13 - iiO
- ---- PERSONNEL INJURIES -
NUMBER DESCRIPTION (IE] I 0 10 I 0itI
- 7. a 9 12_
- ,.....-_ _ _ _ ....;N=/....;;;A=*-------------------=' ao OFFSITE CONSEQUENCES l'"ilsl 1 N/A 74 9.
LOSS OR DAMAGE TO FACU..ITY TYl'tt' DESCRIPTION-i ls! t;J.
1 .,,,110.-----....--~.;;;NL../:.:A~----...,.----------------------zi(J PUBUCITY Gfilt NIA r.
- -------_- 7 8c9 so AODITIONAl. FACTORS ITJ!)t Supplemental Report to 76-04/3L 1 a g
[ill] ""'__E_VE_N_T_D_E_s_c_R_I_P_T_I_ON_&_c_A_u_s_E_DE_s_c_R_I_P_T_I_o.....N...._;,(C_o_n_t_i_n_u_e_d_o_n_P_a_:g;:..e_2...:;)_ _ _ _ _.'=:!,
7 89 ~
NAME=*~----~T~*~L~**;,.......:S~p~e~n~c~e~r--_______________ PHONE: (609) 365-7000 .Ext*. Salem- 5
- __.L~cense Event Report 76-04/31 Page 2 EVENT DESCRIPTION (Continued) occurrence. Corrective action* for* this event was to establish administrative controls as follows*:
A. When operating at or below 10% reactor power:
- 1. Will not allow maintenance or calibration of the lA-lD inverters.
B. When operating above 10% reactor power:
- 1. Will not transfer lD Vital Instrument Bus as a reactor trip signal will result due to the "General Warning" trip in the* SSPS.
- c. At any reactor power level, will not transfer any vital bus if* another protective channel bistable is. in a tripped condition since the protective_... :**
logic. for the function would then be complete.
This is the first occurrence of this type. (76-04/3L).
CAUSE DESCRIPTION (Continued) source only when both the inverter output voltage and current are zero (0).
- However, due to NRC requirements, the supply breakers for the backup source for the vital. instrument busses must be tagged open.
PROBLEMS:
A. When transferring the IA vital instrument bus to back-up power, 1RH2 valve closes due to an. erroneous HIGH pressure signal caused by an 8-cycle* (approx.)
loss of voltage during .the transfer. Also, a P-7 reactor trip signB.l is generated if the reactor is below 10% power due to de-energization of turbirie
- first stage pressure bistables.
B. When transferring*the lB vital instrument* bus,* the-loss of-voltage due .to*
the switChing causes the lRHl*valve to close, also, one source range channel is lost, resulti.ng in a reactor trip signal - "HIGH neutron flux-source-range."
C. When transferring the lC vital instrument bus, the Reactor Protection Channel III trips, initiating a P-10 permissive and a resultant de-energization of both No.* 31 and 32 source range channels.
- ~~ - --- - - - - - *- - - - : - ' " . -
i: '
" - -License Event Repqrt 76-*L Page 3 CAUSE DESCRIPTION (Continued)
ANALYSIS OF PROBLEMS:
On September 23, 1976, a test was made on the lA vital instrument bus transfer switch. It was shown that there exists an 8 1/2 - 9 cycle loss of voltage from the instant the 1A inverter's output breaker was opened to the time the transfer switch's contacts closed on the backup supply. After investigation, it is apparent that modification of the transfer switch to obtain a minimal loss of voltage period is not feasible. Because of the 1-2 millisecond operating time of the.bistable comparators used in the protection racks, even the 1/4 cycle transfer time of static switches would.still trip these bistables. Therefore, administrative control is necessary to minimize the- impact of vital instrument bus transfers on the plant.