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| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PENNSYLVANIA 19406-2713 July 2, 2013 Mr. Timothy S. Rausch Senior Vice President and Chief Nuclear Officer | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PENNSYLVANIA 19406-2713 July 2, 2013 Mr. Timothy S. Rausch Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Blvd, NUCSB3 Berwick, PA 18603-0467 |
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| PPL Susquehanna, LLC | |
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| 769 Salem Blvd, NUCSB3 Berwick, PA 18603-0467 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| INITIAL OPERATOR LICENSING OPERATING TEST AND WRITTEN EXAMINATION APPROVAL - SUSQUEHANNA STEAM ELECTRIC STATION | | INITIAL OPERATOR LICENSING OPERATING TEST AND WRITTEN EXAMINATION APPROVAL - SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 |
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| UNITS 1 AND 2 | |
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| ==Dear Mr. Rausch:== | | ==Dear Mr. Rausch:== |
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| The purpose of this letter is to confirm the final arrangements for the upcoming operator licensing examinations at Susquehanna Steam Electric Station, Units 1 and 2. | | The purpose of this letter is to confirm the final arrangements for the upcoming operator licensing examinations at Susquehanna Steam Electric Station, Units 1 and 2. |
| The U.S. Nuclear Regulatory Commission (NRC) has completed its review of the operator license applications submitted in connection with this examination and separately provided a list of approved applicants to Mr. Corey Goff, Manager, Nuclear Training. Note that any examination waivers and application denials have been addressed in separate correspondence. | | The U.S. Nuclear Regulatory Commission (NRC) has completed its review of the operator license applications submitted in connection with this examination and separately provided a list of approved applicants to Mr. Corey Goff, Manager, Nuclear Training. Note that any examination waivers and application denials have been addressed in separate correspondence. |
| The NRC has approved the subject examinations and hereby authorizes you to administer the | | The NRC has approved the subject examinations and hereby authorizes you to administer the written examinations in accordance with NUREG-1021, Operator Licensing Examinations Standards for Power Reactors, Revision 9, Supplement 1, during the week of July 15, 2013. |
| | | The NRC staff will administer the operating tests during the week of July 8, 2013. This examination has undergone extensive review by my staff and representatives responsible for licensed operator training at your facility. Based on this review I have concluded that the examination meets the guidelines of NUREG-1021 for content, operational, and discrimination validity. By administering this examination, you also agree that it meets NUREG-1021 guidelines, and is appropriate for measuring the qualifications of licensed operator applicants at your facility. |
| written examinations in accordance with NUREG-1021, Operator Licensing Examinations Standards for Power Reactors, Revision 9, Supplement 1, during the week of July 15, 2013. | | If you determine that this examination is not appropriate for licensing operators at your facility, do not administer the examination and contact me at (610) 337-5306. |
| The NRC staff will administer the operating tests during the week of July 8, 2013. This examination has undergone extensive review by my staff and representatives responsible for licensed operator training at your facility. Based on this review I have concluded that the examination meets the guidelines of NUREG-1021 for content, operational, and discrimination validity. By administering this examination, you also agree that it meets NUREG-1021 guidelines, and is appropriate for measuring the qualifications of licensed operator applicants at | |
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| your facility. | |
| If you determine that this examination is not appropriate for licensing operators at your facility, do not administer the examination and contact me at (610) 337-5306. | |
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| Mr. T.S. Rausch 2 Please contact your Chief Examiner Mr. Joseph M. D'Antonio at 610-337-5085, if you have any questions or identify any errors or changes in the license level Reactor Operator (RO) or Senior Reactor Operator (SRO), or type of examination (partial or complete written examination and/or operating test) specified for each applicant.
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| Sincerely, /RA/ Donald E. Jackson, Chief
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| Operations Branch
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| Division of Reactor Safety Docket Nos. 50-387, 50-388 License Nos. NPF-14, NPF-22
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| cc: Distribution ListServ | | Mr. T.S. Rausch 2 Please contact your Chief Examiner Mr. Joseph M. DAntonio at 610-337-5085, if you have any questions or identify any errors or changes in the license level Reactor Operator (RO) or Senior Reactor Operator (SRO), or type of examination (partial or complete written examination and/or operating test) specified for each applicant. |
| | Sincerely, |
| | /RA/ |
| | Donald E. Jackson, Chief Operations Branch Division of Reactor Safety Docket Nos. 50-387, 50-388 License Nos. NPF-14, NPF-22 cc: Distribution ListServ |
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| ML13184A189 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRS/OB RI/DRS/OB RI/DRS/OB NAME JMDAntonio CBixler/ DJackson DATE 07/02 /2013 07/02/2013 07/02/2013}} | | ML13184A189 Non-Sensitive Publicly Available SUNSI Review Sensitive Non-Publicly Available OFFICE RI/DRS/OB RI/DRS/OB RI/DRS/OB NAME JMDAntonio CBixler/ DJackson DATE 07/02 /2013 07/02/2013 07/02/2013}} |
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Category:Letter
MONTHYEARIR 05000387/20230042024-02-0707 February 2024 Integrated Inspection Report 05000387/2023004 and 05000388/2023004 PLA-8096, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2024-01-0404 January 2024 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval PLA-8077, Emergency Plan Revision 67 (PLA-8077)2023-12-27027 December 2023 Emergency Plan Revision 67 (PLA-8077) IR 05000387/20230102023-12-11011 December 2023 Fire Protection Team Inspection Report 05000387/2023010 and 05000388/2023010 PLA-8089, Submittal of Revision to Inservice Testing Program Plan2023-12-0505 December 2023 Submittal of Revision to Inservice Testing Program Plan PLA-8084, Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.22023-11-29029 November 2023 Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 ML23345A0682023-11-28028 November 2023 Technical Specification Bases, Manual PLA-8091, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091)2023-11-0808 November 2023 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091) IR 05000387/20230032023-11-0303 November 2023 Integrated Inspection Report 05000387/2023003 and 05000388/2023003 PLA-8082, Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2023-11-0202 November 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML23291A1132023-10-12012 October 2023 Submittal of Revision 71 to Updated Final Safety Analysis Report and Revision 25 to Fire Protection Review Report ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23277A0412023-10-0505 October 2023 Notification of Commercial Grade Dedication Inspection (05000387/2024011 and 05000388/2024011) and Request for Information IR 05000387/20233012023-09-20020 September 2023 Initial Operator Licensing Examination Report 05000387/2023301 and 05000388/2023301 ML23254A0242023-09-0606 September 2023 Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) IR 05000387/20230052023-08-31031 August 2023 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2023005 and 05000388/2023005) ML23228A1952023-08-21021 August 2023 Summary of August 10, 2023, Public Observation Meeting Re. Proposed Alternative PLA-8080, Proposed Relief for Valve 251130 (PLA-8080)2023-08-14014 August 2023 Proposed Relief for Valve 251130 (PLA-8080) PLA-8074, Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2023-08-0303 August 2023 Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval IR 05000387/20230022023-08-0101 August 2023 Integrated Inspection Report 05000387/2023002 and 05000388/2023002 ML23195A1852023-07-27027 July 2023 Correction to Technical Specifications Page 3.3-73 in Amendment No. 265 PLA-8076, Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076)2023-07-20020 July 2023 Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076) ML23201A0152023-07-20020 July 2023 Operator Licensing Examination Approval ML23200A1012023-07-19019 July 2023 Notification of Conduct of a Fire Protection Team Inspection ML23193A0062023-07-12012 July 2023 Requalification Program Inspection PLA-8078, Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-80782023-07-0505 July 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-8078 ML23163A1012023-06-12012 June 2023 10 CFR 50.46 Annual Report (Pla 8065) PLA-8054, Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence2023-06-0808 June 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence IR 05000387/20234012023-06-0707 June 2023 Security Baseline Inspection Report 05000387/2023401 and 05000388/2023401 PLA-8073, Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval2023-06-0101 June 2023 Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval PLA-8064, Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064)2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064) ML23132A3212023-05-17017 May 2023 Associated Independent Spent Fuel Storage Installation - Issuance of Amendment Nos. 285 and 269 Related to Order Approving Transfer of Licenses PLA-8067, Notification of Completion of Emergence from Bankruptcy (PLA-8067)2023-05-17017 May 2023 Notification of Completion of Emergence from Bankruptcy (PLA-8067) IR 05000387/20230012023-05-12012 May 2023 Integrated Inspection Report 05000387/2023001 and 05000388/2023001 PLA-8066, Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-80662023-05-0808 May 2023 Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-8066 PLA-8053, Radiation Exposure Information and Reporting System2023-04-27027 April 2023 Radiation Exposure Information and Reporting System PLA-8058, Annual Radiological Environmental Operating Report (PLA-8058)2023-04-26026 April 2023 Annual Radiological Environmental Operating Report (PLA-8058) PLA-8041, Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041)2023-04-25025 April 2023 Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041) PLA-8047, 2022 Annual Environmental Operating Report (Nonradiological), PLA-80472023-04-19019 April 2023 2022 Annual Environmental Operating Report (Nonradiological), PLA-8047 PLA-8062, Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-80622023-04-11011 April 2023 Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-8062 PLA-8061, Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-80612023-04-10010 April 2023 Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-8061 ML23090A2302023-03-31031 March 2023 NRC Decommissioning Funding Status Report PLA-8049 PLA-8060, Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060)2023-03-30030 March 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060) ML23095A0572023-03-29029 March 2023 NRC Decommissioning Funding Status Report December 31, 2022 PLA-8057, Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-80572023-03-15015 March 2023 Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-8057 ML23065A1962023-03-0202 March 2023 EN 56387 Paragon - Part 21 Report Re Defect Identified in Automatic Transfer Switch Pn: NLI-ATS480A400X1 IR 05000387/20220062023-03-0101 March 2023 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2022006 and 05000388/2022006) PLA-8052, (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums2023-02-13013 February 2023 (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums IR 05000387/20220042023-02-0808 February 2023 Integrated Inspection Report 05000387/2022004 and 05000388/2022004 ML23010A0882023-01-15015 January 2023 Summary of Regulatory Audit in Support of License Amendment Request to Revise Control Rod Technical Specifications 2024-02-07
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PENNSYLVANIA 19406-2713 July 2, 2013 Mr. Timothy S. Rausch Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Blvd, NUCSB3 Berwick, PA 18603-0467
SUBJECT:
INITIAL OPERATOR LICENSING OPERATING TEST AND WRITTEN EXAMINATION APPROVAL - SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2
Dear Mr. Rausch:
The purpose of this letter is to confirm the final arrangements for the upcoming operator licensing examinations at Susquehanna Steam Electric Station, Units 1 and 2.
The U.S. Nuclear Regulatory Commission (NRC) has completed its review of the operator license applications submitted in connection with this examination and separately provided a list of approved applicants to Mr. Corey Goff, Manager, Nuclear Training. Note that any examination waivers and application denials have been addressed in separate correspondence.
The NRC has approved the subject examinations and hereby authorizes you to administer the written examinations in accordance with NUREG-1021, Operator Licensing Examinations Standards for Power Reactors, Revision 9, Supplement 1, during the week of July 15, 2013.
The NRC staff will administer the operating tests during the week of July 8, 2013. This examination has undergone extensive review by my staff and representatives responsible for licensed operator training at your facility. Based on this review I have concluded that the examination meets the guidelines of NUREG-1021 for content, operational, and discrimination validity. By administering this examination, you also agree that it meets NUREG-1021 guidelines, and is appropriate for measuring the qualifications of licensed operator applicants at your facility.
If you determine that this examination is not appropriate for licensing operators at your facility, do not administer the examination and contact me at (610) 337-5306.
Mr. T.S. Rausch 2 Please contact your Chief Examiner Mr. Joseph M. DAntonio at 610-337-5085, if you have any questions or identify any errors or changes in the license level Reactor Operator (RO) or Senior Reactor Operator (SRO), or type of examination (partial or complete written examination and/or operating test) specified for each applicant.
Sincerely,
/RA/
Donald E. Jackson, Chief Operations Branch Division of Reactor Safety Docket Nos. 50-387, 50-388 License Nos. NPF-14, NPF-22 cc: Distribution ListServ
ML13184A189 Non-Sensitive Publicly Available SUNSI Review Sensitive Non-Publicly Available OFFICE RI/DRS/OB RI/DRS/OB RI/DRS/OB NAME JMDAntonio CBixler/ DJackson DATE 07/02 /2013 07/02/2013 07/02/2013