Letter Sequence Other |
|---|
CAC:MF5471, Use of TS 3.10.1 for SCRAM Time Testing Activities (Approved, Closed) CAC:MF5472, Use of TS 3.10.1 for SCRAM Time Testing Activities (Approved, Closed) CAC:MF5473, Use of TS 3.10.1 for SCRAM Time Testing Activities (Approved, Closed) CAC:MF5474, Use of TS 3.10.1 for SCRAM Time Testing Activities (Approved, Closed) CAC:MF5475, Use of TS 3.10.1 for SCRAM Time Testing Activities (Approved, Closed) CAC:MF5476, Use of TS 3.10.1 for SCRAM Time Testing Activities (Approved, Closed) |
|
MONTHYEARML15324A4392015-12-17017 December 2015
Issuance of Amendments (CAC Nos. MF5471-MF5476)
Project stage: Approval
ML16029A3432016-02-0303 February 2016
Recent Amendments Adding Technical Specification 3.10.8, Inservice Leak and Hydrostatic Testing Operations.
Project stage: Other
2015-12-17
[Table View] |
|
|---|
Category:Letter
MONTHYEARIR 05000254/20230042024-02-0505 February 2024
Integrated Inspection Report 05000254/2023004 and 05000265/2023004
IR 05000237/20230042024-02-0202 February 2024
Integrated Inspection Report 05000237/2023004 and 05000249/2023004
IR 05000373/20230042024-01-24024 January 2024
County Station - Integrated Inspection Report 05000373/2023004 and 05000374/2023004
ML24024A1332024-01-24024 January 2024
Confirmation of Initial License Examination
IR 05000373/20230122024-01-18018 January 2024
County Station - Biennial Problem Identification and Resolution Inspection Report 05000373/2023012 and 05000374/2023012
IR 05000010/20230012024-01-17017 January 2024
NRC Inspection Report 05000010/2023001 (Drss)
ML24004A0052024-01-17017 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0042 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ML23354A2902024-01-0505 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0028 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ML23354A2812024-01-0404 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0031 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
RS-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024
Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval
ML23360A6082023-12-27027 December 2023
County Station Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000373/2024010 and 05000374/2024010
IR 05000254/20234032023-12-22022 December 2023
Public- Quad Cities Nuclear Power Station Security Baseline Inspection Report 05000254/2023403 and 05000265/2023403
IR 05000254/20230102023-12-20020 December 2023
Comprehensive Engineering Team Inspection Report 05000254/2023010 and 05000265/2023010
ML23349A1622023-12-17017 December 2023
Issuance of Amendment Nos. 298 and 294 Increase Completion Time in Technical Specification 3.8.1.B.4 (Emergency Circumstances)
RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023
Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days
ML23278A1292023-12-14014 December 2023
Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines
ML23305A1402023-12-13013 December 2023
Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580
RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023
Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days
ML23339A1762023-12-0505 December 2023
Notification of NRC Baseline Inspection and Request for Information (05000265/2024001)
RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023
Sixth Ten-Year Interval Inservice Testing Program
SVPLTR 23-0037, Core Operating Limits Report for Cycle 292023-11-29029 November 2023
Core Operating Limits Report for Cycle 29
ML23319A3342023-11-20020 November 2023
Regulatory Audit in Support of License Amendment Requests to Adopt TSTF 505, Revision 2 and 10 CFR 50.69
RS-23-104, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-17017 November 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
RS-23-120, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023
Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information
RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023
Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information
ML23317A1192023-11-10010 November 2023
Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums
IR 05000254/20230032023-11-0909 November 2023
Integrated Inspection Report 05000254/2023003 and 05000265/2023003
IR 05000373/20230032023-11-0909 November 2023
County Station Integrated Inspection Report 05000373/2023003, 05000374/2023003, and 07200070/2023001
ML23286A2602023-11-0808 November 2023
Issuance of Amendment Nos. 260 and 245 to Renewed Facility Operating Licenses Relocation of Pressure and Temperature Limit Curves to the Pressure Temperature Report
RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023
Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval
IR 05000373/20234012023-11-0707 November 2023
County Station Security Baseline Inspection Report 05000373/2023401 and 05000374/2023401
RS-23-113, Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 262023-10-20020 October 2023
Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 26
RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23285A2342023-10-13013 October 2023
Confirmation of Initial License Examination
RS-23-103, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023
Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans
IR 05000374/20230102023-10-11011 October 2023
NRC Inspection Report 05000374/2023010
ML23279A0712023-10-0606 October 2023
Response to NRC Dresden Nuclear Power Station, Units 2 and 3 - Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011
ML23269A0662023-09-28028 September 2023
Proposed Alternative Request RV-23H Associated with the Sixth 10-Year Inservice Testing Interval
ML23265A1322023-09-27027 September 2023
Proposed Alternative Request RV-03 Associated with the Sixth 10-Year Inservice Testing Interval
ML23206A0382023-09-21021 September 2023
Proposed Alternative to the Requirements of the ASME Code
IR 05000254/20230112023-09-20020 September 2023
Safety-Conscious Work Environment Issue of Concern Team Inspection Report 05000254/2023011 and 05000265/2023011
ML23205A1362023-09-20020 September 2023
Proposed Alternative Request RV-02D Associated with the Sixth IST Interval
IR 05000373/20233012023-09-15015 September 2023
Errata to NRC Initial License Examination Report 05000373/2023301; 05000374/2023301
IR 05000237/20230112023-09-0606 September 2023
Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011
2024-02-05
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 3, 2016 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3; LASALLE COUNTY STATION, UNITS 1 AND 2; AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - RECENT AMENDMENTS ADDING TECHNICAL SPECIFICATION 3.10.8, "INSERVICE LEAK AND HYDROSTATIC TESTING OPERATIONS"
Dear Mr. Hanson:
On December 17, 2015 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML15324A439), the U.S. Nuclear Regulatory Commission (NRC) issued the following amendments:
- 1. Amendment No. 248 to Renewed Facility Operating License No. DPR-19 and Amendment No. 241 to Renewed Facility Operating License No. DPR-25 for Dresden Nuclear Power Station (DNPS), Units 2 and 3, respectively,
- 2. Amendment No. 219 to Facility Operating License No. NPF-11 and Amendment No. 205 to Facility Operating License No. NPF-18 for the LaSalle County Station (LSCS), Units 1 and 2, respectively, and
- 3. Amendment No. 261 to Renewed Facility Operating License No. DPR-29 and Amendment No. 256 to Renewed Facility Operating License No. DPR-30 for the Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2, respectively.
The amendments added a new technical specification, Section 3.10.8, "lnservice Leak and Hydrostatic Testing Operation," including a new limiting condition for operation (LCO). After issuance of the amendments, Exelon Generation Company, LLC (Exelon, the licensee) informed the NRC staff of an issue with the underlined portion of the following paragraph from page 8 of the associated safety evaluation (SE):
Prior to use of the special operation LCO 3.10.8 for the inservice leakage and hydrostatic testing of the RCS [reactor coolant system]. all main steam isolation valves and the primary containment isolation valves connected to RCS should be in their fully closed position, even though the primary containment is inoperable.
Therefore, if there is a main steam line break in the secondary containment during use of the LCO, the resulting conditions inside and outside the secondary containment are bounded by the conditions resulting from a large main steam line break inside the secondary containment in Mode 1 described in UFSAR
[updated final safety analysis report] Section 15.6.4 (for all six plants) because the SGTS [standby gas treatment system] and secondary containment are
B. Hanson operable for all six plants. Based on this, the NRC staff finds the proposed LCO 3.10.8 acceptable to the extent that GDC [general design criterion]-16 for LSCS and draft GDC-10 for DNPS and QCNPS would continue to be satisfied.
The NRC staff discussed this issue with Exelon personnel during a call on January 28, 2016.
Exelon explained that some of the isolation valves are open or bypassed during testing to maintain shutdown cooling capability or to facilitate the 10-year extended boundary test of the reactor coolant system.
As discussed in the license amendment request and reinforced by Exelon during the call, the plant conditions and conservatisms in the main steam line break analysis (UFSAR Section 15.6.4) envelope the expected conditions during testing. Exelon stated that its UFSAR Section 15.6.4 analysis assumed full power operations and did not take credit for secondary containment and the SGTS. Under the test conditions, the reactor is not operating and the RCS has a lower temperature thus any break would result in a smaller source term. Furthermore, LCO 3.10.8 requires that secondary containment and the SGTS are operable such that any radioactive release would be reduced due to holdup within secondary containment and filtration through the SGTS.
The NRC staff considered the potential for some of the isolation valves to be open or bypassed during testing and determined that this does not alter the staff's finding in the SE that the UFSAR Section 15.6.4 analysis bounds the consequences of a pipe break in the primary system under the test conditions. Therefore, the staff's conclusions in the SE are not affected.
The staff does not expect the licensee to change how it performs its testing to conform to the above statement. If you have any questions, please contact me at 301-415-1380.
Sincerely, Blake Purnell, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-237, 50-249, 50-373, 50-374, 50-254, and 50-265 cc: Distribution via Listserv
ML16029A343 *b1y e-ma1*1 OFFICE LPL3-2/PM LPL3-2/LA SCVB/BC LPL3-2/BC(A) LPL3-2/PM NAME BPurnell SRohrer RDennig* JPoole BPurnell DATE 2/03/2016 2/01/2016 2/03/2016 2/03/2016 2/03/2016
