Similar Documents at Salem |
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Category:Letter
MONTHYEARIR 05000272/20230042024-02-0505 February 2024 Integrated Inspection Report 05000272/2023004 and 05000311/2023004 ML24009A1022024-01-26026 January 2024 Exemption from Select Requirements of 10 CF Part 73 (EPID L-2023-LLE-0045 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000272/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000272/2023401 and 05000311/2023401 ML24004A1542024-01-0808 January 2024 Notification of Conduct of a Fire Protection Team Inspection LR-N23-0079, Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days2023-12-0707 December 2023 Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement LR-N23-0077, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion2023-11-29029 November 2023 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion ML23324A3072023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000272/20230032023-11-13013 November 2023 Integrated Inspection Report 05000272/2023003 and 05000311/2023003 LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023 Core Operating Limits Report Cycle 30 IR 05000272/20230102023-10-12012 October 2023 Biennial Problem Identification and Resolution Inspection Report O5000272/2023010 and 05000311/2023010 IR 05000272/20234022023-10-12012 October 2023 and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2023402, 05000272/2023402 and 05000311/2023402 (Cover Letter Only) LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement ML23249A2612023-09-0606 September 2023 License Amendment Request to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000272/20230052023-08-31031 August 2023 Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2023005 and 05000311/2023005) ML23233A0762023-08-21021 August 2023 Requalification Program Inspection ML23192A8212023-08-14014 August 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location IR 05000272/20230022023-08-0909 August 2023 Integrated Inspection Report 05000272/2023002 and 05000311/2023002 LR-N23-0055, Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days2023-08-0303 August 2023 Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days IR 05000354/20230022023-08-0303 August 2023 Integrated Inspection Report 05000354/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200048/2023001 LR-N23-0054, In-Service Inspection Activities2023-07-26026 July 2023 In-Service Inspection Activities LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 LR-N23-0005, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-06-23023 June 2023 License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML23139A1472023-06-0505 June 2023 Relief Request Associated with Fourth Interval In-service Inspection Limited Examinations of Weld Coverage ML23096A1842023-05-0909 May 2023 Issuance of Amendment No. 328 Revise and Relocate Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report IR 05000272/20230012023-05-0303 May 2023 Integrated Inspection Report 05000272/2023001 and 05000311/2023001 ML23081A4662023-05-0202 May 2023 Issuance of Amendment Nos. 346 and 327 Revise Technical Specifications to Extend Allowable Outage Time for Inoperable Emergency Diesel Generator IR 05000272/20233012023-05-0101 May 2023 Initial Operator Licensing Examination Report 05000272/2023301 and 05000311/2023301 LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) LR-N23-0033, Core Operating Limits Report Cycle 272023-04-26026 April 2023 Core Operating Limits Report Cycle 27 LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location ML23089A0942023-04-17017 April 2023 NRC to PSEG Hope Creek, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23087A1492023-04-17017 April 2023 NRC to PSEG Salem, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23103A3232023-04-13013 April 2023 Submittal of Updated Final Safety Analysis Report, Rev. 26, Summary of Revised Regulatory Commitments for Hope Creek, Summary of Changes to PSEG Nuclear LLC, Quality Assurance Topical Report, NO-AA-10, Rev. 89 ML23095A3682023-04-12012 April 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership LR-N23-0006, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-24024 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23086A0912023-03-24024 March 2023 NMFS to NRC, Transmittal of Biological Opinion for Continued Operations of Salem and Hope Creek Nuclear Generating Stations RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2023-03-21021 March 2023 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums ML23044A1052023-03-13013 March 2023 Issuance of Amendment Nos. 345 and 326 Relocate Technical Specifications Requirements for Reactor Head Vents to Technical Requirements Manual ML23037A9712023-03-0909 March 2023 and Salem Nuclear, Unit Nos. 1 and 2 Issuance of Amendment Nos. 233, 344, and 325 Relocate Technical Specification Staff Qualification Requirements to the PSEG Quality Assurance Topical Report IR 05000272/20230112023-03-0707 March 2023 Comprehensive Engineering Team Inspection Report 05000272/2023011 and 05000311/2023011 IR 05000272/20220062023-03-0101 March 2023 Annual Assessment Letter for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2022006 and 05000311/2022006) LR-N23-0016, and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments2023-02-28028 February 2023 and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments LR-N23-0012, Annual Property Insurance Status Report2023-02-24024 February 2023 Annual Property Insurance Status Report LR-N23-0014, Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.7172023-02-23023 February 2023 Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.717 ML23034A1532023-02-0909 February 2023 Operator Licensing Examination Approval ML23019A3482023-02-0202 February 2023 Issuance of Relief Request No. SC-I5R-221 for the Alternative Repair for Service Water System Piping LR-N23-0003, Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-2112023-02-0101 February 2023 Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-211 2024-02-05
[Table view] Category:Licensee Response to Notice of Violation
[Table view] |
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Frederick W. Schneider Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201/622-7000 Vice President Production May 20, 1977 Mr. James P. O'Reilly, Director
- u. s. Nuclear Regulatory Commission Off ice of Inspection and Enforcement Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. O'Reilly:
NRC INSPECTION REPORT NO. 50~272/77-13 INSPECTION DATE APRIL 12, 1977 NO. 1 UNIT SALEM GENERATING STATION We have received and reviewed the report of your inspection conducted April 12, 1977. The report was transmitted with your letter of April 29, 1977 and received on.May 2, 1977.
Our response to the items of noncompliance is as follows:
77-13-01 "Facility Operating License No. DPR-70 Amendment No. 4 paragraph 2.C. (4), dated January 6, 1977, states in part that, nPublic Service Electric and Gas Company shall not operate the reactor at power levels above P-7 (11 per-cent) *** with less than four (4) reactor coolant loops in operation until *** approval for less than four loop operation at power levels above P-7 has been granted by the Commission by amendment of this license. 1' Contrary to the above on April 12, 1977, the plant was operated from 10:01 a.m. to 10:32 a.m. at 25 percent power with No. 14 Reactor Coolant Pump idle and the associated loop out of service ..
On April 12, 1977, at 1001 hours0.0116 days <br />0.278 hours <br />0.00166 weeks <br />3.808805e-4 months <br />, while in Mode 1 operation, an attempt was made to transfer the lG 4kV Group Bus from_ the Station Power Transformer to the Auxiliary Power Transformer.
During the transfer, the feeder breaker from the Station Power Transformer opened but the feeder breaker from the Auxiliary
Mr. J. P. O'Reilly 5-20-77 Power Transformer failed *to close. This resulted .in a loss of the lG 4kV Group Bus and a loss of No. 14 Reactor Coolant Pump.
Plant conditions were stabilized at 25% power in three (3) loop operation. Investigation revealed that the unit isolation trip had not been reset, therefore, not allowing the feeder breaker from,the_Au,xiliary Power Transformer to close. At.
approximately 1015 hour0.0117 days <br />0.282 hours <br />0.00168 weeks <br />3.862075e-4 months <br />s~ the Unit Isolation Trip had been reset and the lG-4kVGroup Bus was re-energized from the Auxiliary Power Transformer. At 1032 hoµrs, the No. 14 Reactor Coolant Pump was re-started.
There are several factors which contributed to the oversight of the license amendment prohibiting less than four loop operation above 11% *power. Cold SRO licensed supervisory personnel have been standing watch to meet the technical specifi~ -
cation requirements until the control operators are RO licensed.
This has required a certain amount of overtime and irregular shift assignments and has prevented the start of the License Operator Retraining Program. As a result, training of licensed personnel during this interim period has not been as.effective*
as we had expected. In this particular situation, the licensed operators.were originally trained and granted their SRO licenses based on the Technical Specification which.does allow three loop operation*. The license amendment which restricts this mode of operation came approximately six months after the license was issued, _and al though operating personnel were* made aware of the restriction, _the training._ emphasis was obviously insufficient to overcome_ the more rigorous earlier training.
Therefore, in addition to the corrective action listed below, we will review the license and technical specification requirements and operating. inc.:j,.dents that have taken place to date to be sure they are incorporated into the retraining program which should resume in June. * *
- 1. An on-the-spot-change was made to OI II-1.3-1 which added Step -3.11 "Do not start a Reactor Coolant Pump while reactor is critical II I on April 12, _1977.
On April 12, 1977, a night order book entry was made to re-instruct Control Room personnel of the Reactor Coolant Pump restriction.
- 2. On April 15, _1977, a plastic tag was placed on the Operating Console as a warning to Operators that three loop operation ab6ve P-7, is not allowed.
L
Mr. J. P. O'Reilly 5-20~11 77-13-02 Technical Specification 6.8.1 requires written procedures to be established, implemented, .and maintained covering opera-tion of the*reactor coolant system.
Operating Instruction*II 1.3-3, OPERATING WITH LESS THAN FOUR REACTOR COOLANT LOOPS IN* SERVICE, SECTION 5.5, "Start-ing a Reactor Coolant Pump (RCP) During Power Operation,"
requires power level to be reduced to* below 10 percent prior_ to starting a*RCP in an idle loop.
Contrary to the above, No. 14 Reactor Coolant Pump was started in the idle loop at 10:32 a.m. on April 12, 1977, with the reactor at 25 percent power. An unplanned initi-ation of safety injection occurred as a result of adverse
The following corrective action has been taken:
An on-the-spot change added a precaution to QI II-1.3-3 on April 12,. 1977, which states, "Do not start a Reactor Coolant Pump with the reactor critical."
In response to your concern about the number and frequency of operator induced safeguard actuations, station management *has instituted a system*.which requires operator written responses to variances. in operating practices*. This system is expected to stimulate operator awareness of his actions and will indicate to management those.areas where additional training or procedure modification is required.* Also, .the Nuclear Review Board will be asked to review.the Licensed Operator Retraining Program after
- it has been in effect for six months, to verify its adequacy.
If you require additional information, we will be pleased to discuss it with you.
Very truly yours,