|
|
Line 71: |
Line 71: |
| I Technical Specification Surveillance 4.8.2.2 and 4.8.2.4.1 which are* | | I Technical Specification Surveillance 4.8.2.2 and 4.8.2.4.1 which are* |
| required to be performed every 7 days were not performed within the 25 percent allowed by specification 4.0.2.a. Both items were reguired | | required to be performed every 7 days were not performed within the 25 percent allowed by specification 4.0.2.a. Both items were reguired |
| []]]] to be performed on 04-17-78 and were not completed until 04-19-78. | | [)))) to be performed on 04-17-78 and were not completed until 04-19-78. |
| cmJ | | cmJ |
| [ill] | | [ill] |
| [ill] | | [ill] |
| 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VAL.VE CODE CODE suBCODE COMPONENT CODE SUBCOOE suscooE | | 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VAL.VE CODE CODE suBCODE COMPONENT CODE SUBCOOE suscooE |
| [I]]] I z IZ I@ W@ lJLl@ lzlzlzlzlz! I@~@ w@ | | [I))] I z IZ I@ W@ lJLl@ lzlzlzlzlz! I@~@ w@ |
| 7 8 9 10 11 12 13* 18 19 20 | | 7 8 9 10 11 12 13* 18 19 20 |
| *SEQUENTIAL. OCCURRENCE REPORT REVISION | | *SEQUENTIAL. OCCURRENCE REPORT REVISION |
Line 94: |
Line 94: |
| 43 l*zJ9l9l9l@1 44 | | 43 l*zJ9l9l9l@1 44 |
| * 47 I CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS @ | | * 47 I CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS @ |
| [J]]J I Failure of operations personnel to promptly review completed surveillande DID and return Inspection Orders for reissuance resulted in the required | | [J))J I Failure of operations personnel to promptly review completed surveillande DID and return Inspection Orders for reissuance resulted in the required |
| !III] surveillance being performed late. Reinstruction. of staff personnel as! | | !III] surveillance being performed late. Reinstruction. of staff personnel as! |
| [I]]] I to the reguirement for prompt document review and timely return of IO o::IIJ I cards is expected to prevent reoccurrence. | | [I))] I to the reguirement for prompt document review and timely return of IO o::IIJ I cards is expected to prevent reoccurrence. |
| 1 a 9 80 FACILITY ljQ\ METHOD OF STATUS % POWER OTHER STATUS \:::J OISCOVERY DISCOVERY DESCi'!IPTION @ | | 1 a 9 80 FACILITY ljQ\ METHOD OF STATUS % POWER OTHER STATUS \:::J OISCOVERY DISCOVERY DESCi'!IPTION @ |
| CIEi W I 0 I 0 I 0 l@i.-1---.::N:.:.,/~A-----' W@I 7 8 9 10 12 1'.l 44. 45 Document Review 46 80 ACTIVITY CONTENT t.::;\ | | CIEi W I 0 I 0 I 0 l@i.-1---.::N:.:.,/~A-----' W@I 7 8 9 10 12 1'.l 44. 45 Document Review 46 80 ACTIVITY CONTENT t.::;\ |
Line 103: |
Line 103: |
| PERSONNEL EXPOSURES ~ | | PERSONNEL EXPOSURES ~ |
| NUMBER A TYPE t.:;\ DESCRl.PTION ~ | | NUMBER A TYPE t.:;\ DESCRl.PTION ~ |
| [[IT] I o I a I o lW~'--------N...l..-A.____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -.1 7 8 9 11 12 13 80 PERSONNEL INJURIES ~
| | ((IT] I o I a I o lW~'--------N...l..-A.____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -.1 7 8 9 11 12 13 80 PERSONNEL INJURIES ~ |
| NUMBER DESCRIPTION~ | | NUMBER DESCRIPTION~ |
| o:::II] | | o:::II] |
Similar Documents at Salem |
---|
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 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-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-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-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 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 ML19031B5101978-08-24024 August 1978 LER 1978 for Reportable Occurrence 78-43/03L on Quadrant Power Tilt Ratio Greater than 1.02 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 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 ML19031B1651978-07-20020 July 1978 LER 1978-035-03 for Salem Unit 1 Loss of Power to No. 2 Station Power Transformer ML19031B0401978-07-12012 July 1978 LER 1978-033-03 for Salem Unit 1 No. 11 Steam Generator Steam Flow Channel II 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 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 ML19031B5261978-04-0404 April 1978 04/04/1978 Letter Reportable Occurrence on Monthly Water Quality Samples 2024-05-09
[Table view] Category:Technical Specifications
MONTHYEARML24145A1772024-07-15015 July 2024 And Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 236, 349, and 331 Modify Exclusion Area Boundary 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 LR-N22-0006, License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days2022-06-29029 June 2022 License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days ML21295A2292021-11-15015 November 2021 Issuance of Amendment Nos. 340 and 321 Revise Technical Specifications to Adopt TSTF 569, Revision of Response Time Testing Definitions ML20034E6172020-02-27027 February 2020 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 222, 333, and 314 Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions and License Transfer ML19275D6942019-11-18018 November 2019 Issuance of Amendment Nos. 330 and 311 Revise Technical Specifications to Adopt TSFT-547, Clarification of Rod Position Requirements LR-N18-0129, License Amendment Request to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements.2019-02-0404 February 2019 License Amendment Request to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements. ML16096A4192016-04-28028 April 2016 Issuance of Amendments Replacement of Source Range and Intermediate Range Neutron Monitoring Systems ML16054A0682016-03-28028 March 2016 Issuance of Amendments Regarding Revision to Reactor Trip System Instrumentation Technical Specifications ML16035A0872016-03-0707 March 2016 Issuance of Amendments New Technical Specifications to Isolate Unborated Water Sources in Mode 6 LR-N16-0044, Emergency License Amendment Request to Modify Technical Specification Requirements for One Inoperable Subcooling Margin Monitor Channel2016-02-11011 February 2016 Emergency License Amendment Request to Modify Technical Specification Requirements for One Inoperable Subcooling Margin Monitor Channel LR-N15-0224, Response to Request for Additional Information License Amendment Request to Isolate Unborated Water Sources and Use Gamma-Metrics Post-Accident Neutron Monitors During Mode 6 (Refueling)2015-11-25025 November 2015 Response to Request for Additional Information License Amendment Request to Isolate Unborated Water Sources and Use Gamma-Metrics Post-Accident Neutron Monitors During Mode 6 (Refueling) LR-N15-0182, License Amendment Request to Correct a Non-Conservative Technical Specification Applicability Statement and Inconsistent Action Statements2015-10-12012 October 2015 License Amendment Request to Correct a Non-Conservative Technical Specification Applicability Statement and Inconsistent Action Statements ML15245A6362015-09-0404 September 2015 Issuance of Emergency Amendment Regarding Removal of Pressurizer Power Operated Relief Valve Position Indication Instrumentation from Technical Specifications ML15153A2302015-07-30030 July 2015 Issuance of Amendments Adopting Technical Specification Task Force (TSTF)-510, Rev, 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection(Tac Nos. MF4574 & MF457 ML15141A2712015-06-17017 June 2015 and Salem Nuclear Generating Station, Unit Nos.1 and 2, Issuance of Amendments Update of Appendix B to the Renewed Facility Operating Licenses ML15063A2932015-03-30030 March 2015 Issuance of Amendments Revision to Power Distribution Limits for Axial Flux Difference and Heat Flux Hot Channel Factor LR-N14-0074, License Amendment Request to Revise Power Distribution Limits for Axial Flux Difference and Heat Flux Hot Channel Factor2014-03-24024 March 2014 License Amendment Request to Revise Power Distribution Limits for Axial Flux Difference and Heat Flux Hot Channel Factor LR-N12-0183, License Amendment Request: Revision to Technical Specification (TS) 3.7.6.1 (Unit 1) and 3.7.6 (Unit 2) Control Room Emergency Air Conditioning System2012-07-17017 July 2012 License Amendment Request: Revision to Technical Specification (TS) 3.7.6.1 (Unit 1) and 3.7.6 (Unit 2) Control Room Emergency Air Conditioning System LR-N11-0208, Revised License Condition- Salem-Hope Creek Cyber Security Plan Supplement Submittal2011-07-0606 July 2011 Revised License Condition- Salem-Hope Creek Cyber Security Plan Supplement Submittal ML11175A2072011-06-30030 June 2011 Appendices a, B and C ML11136A0642011-06-30030 June 2011 Issuance of Renewed Facility Operating License Nos. DPR-70 and DPR-75 for Salem Nuclear Generating Station, Units 1 and 2 LR-N10-0363, License Amendment Request: Changes to Snubber Surveillance Requirements2010-10-0404 October 2010 License Amendment Request: Changes to Snubber Surveillance Requirements ML1020805012010-08-20020 August 2010 License Amendment, Issuance of Amendments Surveillance Requirements for Inservice Inspection and Inservice Testing LR-N10-0098, License Amendment Request - One Time On-Line Safety-Related Battery Replacement2010-03-29029 March 2010 License Amendment Request - One Time On-Line Safety-Related Battery Replacement ML1005704522010-03-29029 March 2010 Issuance of Amendment Steam Generator Inspection Scope and Repair Requirements ML0936308182010-01-12012 January 2010 License Amendment, Revise the Definition of Fully Withdrawn for the Rod Cluster Control Assemblies ML0929605842009-10-0808 October 2009 License Amendment Request, Revision to Technical Specification 6.8.4.i, Steam Generator Program, for One-Time (Interim) Alternate Repair Criteria (H*) LR-N09-0001, License Amendment Request to Eliminate Unnecessary Reporting Requirements in the Operating License and the Administrative Controls Section of the Technical Specifications2009-01-0505 January 2009 License Amendment Request to Eliminate Unnecessary Reporting Requirements in the Operating License and the Administrative Controls Section of the Technical Specifications ML0823409962008-09-24024 September 2008 Technical Specifications, Issuance of Amendment No. 273 Refueling Operations - Decay Time ML0823409752008-09-24024 September 2008 Technical Specifications, Issuance of Amendment No. 289 Refueling Operations - Decay Time ML0806700642008-03-13013 March 2008 Tech Spec Pages for Amendment 288, Surveillance Requirements for Containment Building Penetrations ML0806700822008-03-13013 March 2008 Tech Spec Pages for Amendment 272, Surveillance Requirements for Containment Building Penetrations LR-N08-0054, License Amendment Request (LAR) S08-03, Request for Change to Technical Specifications Refueling Operations - Containment Building Penetrations2008-03-0505 March 2008 License Amendment Request (LAR) S08-03, Request for Change to Technical Specifications Refueling Operations - Containment Building Penetrations ML0803204342008-03-0505 March 2008 Tech Spec Pages for Amendment 271 Re Refueling Operations - Decay Time ML0802204242008-02-27027 February 2008 Technical Specifications, Amendment. 270, License DPR-75, Steam Generator Feedwater Pump Trip, Feedwater Isolation Valve Response Time Testing and Containment Cooling System ML0802204142008-02-27027 February 2008 Technical Specifications to Amendment 287, License DPR-70, Steam Generator Feedwater Pump Trip, Feedwater Isolation Valve Response Time Testing and Containment Cooling System ML0734705152008-01-24024 January 2008 Amd 286/License DPR-75, Technical Specifications, Established More Effective & Appropriate Action, Surveillance & Administrative Requirements Re Ensuring the Habitability of the Control Room Envelop ML0734704082008-01-24024 January 2008 Amd 286/License DPR-70, Technical Specifications, Established More Effective & Appropriate Action, Surveillance & Administrative Requirements Re Ensuring the Habitability of the Control Room Envelop ML0717101192007-06-19019 June 2007 Technical Specifications for Amendment No. 266, Issuance of Amendments Relocation of Response Time Testing Limits (TAC Nos. MD2804 & MD2805) ML0717101212007-06-19019 June 2007 Technical Specifications for Amendment No. 283, Issuance of Amendments Relocation of Response Time Testing Limits (TAC Nos. MD2804 & MD2805) ML0715901892007-06-0606 June 2007 Units, 1 and 2, Tech Spec Pages for Amendment 282 Relocation of Technical Specification Requirements for the Movable Incore Detectors and Radioactive Gaseous Effluent Oxygen Monitoring Instrumentation ML0712202912007-05-10010 May 2007 Correction to Technical Specification Pages for Amendment Nos. 276 and 258 LR-N07-0103, Units 1 & 2, Correction to Technical Specification Pages/Amendment 276 and 2582007-05-0404 May 2007 Units 1 & 2, Correction to Technical Specification Pages/Amendment 276 and 258 ML0710906192007-04-19019 April 2007 Tech Spec Pages for Amendment 263 Accident Monitoring Instrumentation and Source Check Definition ML0710906332007-04-19019 April 2007 Tech Spec Pages for Amendment 280 Accident Monitoring Instrumentation and Source Check Definition ML0711503562007-04-19019 April 2007 Technical Specifications Elimination of Requirements for Hydrogen Recombiners and Hydrogen Analyzers Using the Consolidated Line Item Improvement Process ML0711503582007-04-19019 April 2007 Technical Specifications Elimination of Requirements for Hydrogen Recombiners and Hydrogen Analyzers Using the Consolidated Line Item Improvement Process LR-N07-0058, Application to Revise Technical Specifications (LCR S07-02) Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-04-15015 April 2007 Application to Revise Technical Specifications (LCR S07-02) Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0709203782007-03-29029 March 2007 Technical Specifications, Steam Generator Tube Integrity 2024-07-15
[Table view] |
Text
Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201 /622-7000
...~.*
r.:
C*
~;]~
- o OCJ rr1~*
U)~
c::i:J
.......****~
~::a
-- -;C:
Mr. Boyce H. Grier ~-i CJ Director of USNRC P1 0
- t*~
U>
Off ice of Inspections and Enforcements Region 1 631 Park Avenue King df Prussia, Pennsylvania 19406
Dear Mr. Grier:
LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 78-25/03L Pursuant to the requirements of* Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1.9.c, we are submitting Licensee Event Report for Reportab-le Occurrence 78-25/03L. This report is required within thirty (30) days of the occurrence.
Sincerely yours*,
JvL--/b'l~
F. P. Li r1zz1 General Manager -
Electric Production CC: Director, Office of Inspection and Enforcement (30 copies)
Director, Office of Management Information and Program Control (3 copies)
The Energy People QC\.?nn1 'lnnu 1 a '7"1'
Report Number:
e78-25/03L Report Date: 5/15/78 Occurrence Date: 4/19/78 Facility: Salem Generating Station Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
Missed Technical Specification Surveillance:
4.8.2.4.1 DC Breaker Alignment and Power Availability 4.8.2.2 AC Breaker Alignment and Power Availability CONDITIONS PRIOR TO OCCURRENCE:
Cold Shutdown Mode 5 DESCRIPTION OF OCCURRENCE:
Technical Specification Surveillance 4.8.2.2 (AC Breaker Alignment and Pow~r Availability) and 4. 8. 2. 4 .1 (DC Breaker Alignment _and Power Availability) which are required to be performed every 7 days were not performed within the 25% allowed by specification 4.0.2.a.
Both items were required to be performed on 4/17/78 and were not completed until 4/19/78.
DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:
Failure of. Operations staff *personnel to promptly review completed surveillance and return Inspection Orders 100211 and 100212 to the Performance Department resulted in late receipt of the Inspection Orders on the next due date. When Inspection Orders were received, the surveillance was overdue.
ANALYSIS OF OCCURRENCE:
Failure to perform surveillance 4.8.2.2 and 4.8.2.4.l is a violation of Technical Specification 4.0.2 which states that each surveillance requirement shall be performed within the specified time interval.
CORRECTIVE ACTION:
Operations Department staff has been instructed as to the importance of promptly returning Inspection Orders after surveillance has been completed. Also, staff personnel have been instructed to track sur-veillance items that might become overdue regardless of the status of the appropriate Inspection Order.
LER 78-25/03L FAILURE DATA:
N/A Prepared by T. L. Spencer
~---~~-----=-,~~~~~--~
Manager - ~lem Generating Statiol SORC Meeting No. 28-78
---,.~~~~~~~~~
(7-77)
,_, - - ..... ~ ' LICENSEE EVENT REPORT CONTROL BLOCK:!!- _..__....i.._...__,.__..,11_-!J 0 (PL.EASE PRINT OR TY.LL REQUIRED INFORMATION)
[ill] IN IJ Is I G Is I 1 IG)I a I aI -1 a I a I aI a I a I -1 a I a l@l 4 I 1 I 1I1 I i l©l I I©
.7 8 9 l.lCENSEE CODE 14 15 L.!CENSE NUMBER 25 26 L.!CENSE TYPE :JO 57 CAT 58 CON'T
[IUJ 7 8
~~~~~ UJ© I a I s I 60 61 aI a I aI 2 I 1 I 2 101 o I 4 I 1 I 9 I 1 I a !©I DOCKET NUMBER 68 69 EVENT DATE 74 75 I I REPORT DATE I I 80 I@
EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES@
I Technical Specification Surveillance 4.8.2.2 and 4.8.2.4.1 which are*
required to be performed every 7 days were not performed within the 25 percent allowed by specification 4.0.2.a. Both items were reguired
[)))) to be performed on 04-17-78 and were not completed until 04-19-78.
cmJ
[ill]
[ill]
7 8 9 80 SYSTEM CAUSE CAUSE COMP. VAL.VE CODE CODE suBCODE COMPONENT CODE SUBCOOE suscooE
[I))] I z IZ I@ W@ lJLl@ lzlzlzlzlz! I@~@ w@
7 8 9 10 11 12 13* 18 19 20
- SEQUENTIAL. OCCURRENCE REPORT REVISION
~ L.ERIRQ LVENTYE.A.A* REPORT NO. COOE TYPE NC.
~ REPORT NUMBER 17 21 r81 22 I
23 I I 24 o 12 I s I
/
26 1.......-1 27 I
28 oI 3I 29 LiJ 30 l=1 31 w
32 ACTION FUTURE EFFECT SHUTDOWN ~ ATTACHMENT NPA0-4 PRIME COMP: COMPONENT I TAKEN ACTION ON PL.ANT METHOD HOURS @ SUBMITTED FORM:;UB. SUPPLIER MANUFACTURER I W@l.QJ@
33 34 .
W 35 W
36.
lol*ololol 37 40 l.xJ@
41 W@
42 W@
43 l*zJ9l9l9l@1 44
- 47 I CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS @
[J))J I Failure of operations personnel to promptly review completed surveillande DID and return Inspection Orders for reissuance resulted in the required
!III] surveillance being performed late. Reinstruction. of staff personnel as!
[I))] I to the reguirement for prompt document review and timely return of IO o::IIJ I cards is expected to prevent reoccurrence.
1 a 9 80 FACILITY ljQ\ METHOD OF STATUS % POWER OTHER STATUS \:::J OISCOVERY DISCOVERY DESCi'!IPTION @
CIEi W I 0 I 0 I 0 l@i.-1---.::N:.:.,/~A-----' W@I 7 8 9 10 12 1'.l 44. 45 Document Review 46 80 ACTIVITY CONTENT t.::;\
RELEASED OF RELEASE AMOUNT OF ACTIVITY l.OCA TION OF RELEASE @
ITIIl w@) WI 7 8 9 10 11 NIA 44 45 NLA so I
PERSONNEL EXPOSURES ~
NUMBER A TYPE t.:;\ DESCRl.PTION ~
((IT] I o I a I o lW~'--------N...l..-A.____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -.1 7 8 9 11 12 13 80 PERSONNEL INJURIES ~
NUMBER DESCRIPTION~
o:::II]
7 8 9 Iola I ol@).__ 11 12
___._.*~N~A--------------------------__.so l.OSS OF OR DAMAGE TO FAC! LITY f.i3' TYPE DESCRIPTION ~
[QI) LIJ@
1 8 PUBLICITY C\
N A 9 1*a~-----~-~---...----------~---------------~-~~~-------.......1so NRC USE 0 ISSUEDt,;:;\ DESCRIPTION ~ NL y .,,
.IIliJ8Lz.J6 1 91 . N/A
~o---~-----~...;.;;.:..;.;;.~--~~~~~--~--------------'6s 69I I I I I I I I I I l I I ~ 20 ;
NAMEOFPAEPARER~----T--..__ L_.--s_o_e__n~c~e~r:.,________ PHONE: (609) 365-7000 Salen Ext.~
528 \J