Letter Sequence Other |
|---|
|
|
MONTHYEARML20198M4422020-07-16016 July 2020
NRR E-mail Capture - Sequoyah and Watts Bar Nuclear Plants - Acceptance of License Amendment Request Regarding Request to Adopt TSTF-569, Revision 2
Project stage: Acceptance Review
ML20350B4932021-01-25025 January 2021
Issuance of Amendment Nos. 352, 346, 141, and 47 Regarding the Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition
Project stage: Approval
ML21033B0712021-02-16016 February 2021
Correction of Amendment Nos. 352, 346, 141, and 47 Regarding the Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition
Project stage: Other
2021-01-25
[Table View] |
|
|---|
Category:Letter
MONTHYEARML24032A0202024-01-31031 January 2024
NPDES Biocide/Corrosion Treatment Plan Annual Report, Cy 2023
ML23319A2452024-01-29029 January 2024
Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues
ML24008A2462024-01-18018 January 2024
Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule
CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions
ML24018A0142024-01-17017 January 2024
Engine Systems, Inc., Report No. 10CFR21-0137, Rev. 1, 56913-EN 56913
IR 05000327/20234422024-01-11011 January 2024
95001 Supplemental Inspection Report 05000327/2023442 and 05000328/2023442 and Follow-Up Assessment Letter
ML24011A3162024-01-11011 January 2024
Submittal of Discharge Monitoring Report (Dmr), August 2023
ML24011A3172024-01-11011 January 2024
Submittal of Discharge Monitoring Report (Dmr), September 2023
ML24011A3202024-01-11011 January 2024
Submittal of Discharge Monitoring Report (Dmr), December 2023
ML24011A3192024-01-11011 January 2024
Submittal of Discharge Monitoring Report (Dmr), November 2023
ML24011A3182024-01-11011 January 2024
Submittal of Discharge Monitoring Report (Dmr), October 2023
ML24010A2132024-01-10010 January 2024
CFR 21.21 Final Report Regarding Siemens Medium Voltage Circuit Breakers
CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024
Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)
CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024
Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability
CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024
Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)
ML24018A0952024-01-0404 January 2024
Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance Report No. 10CFR21-0137, Rev. 0
ML24004A0332024-01-0303 January 2024
Interim Report of a Deviation or Failure to Comply Crompton Instruments Type 077 Ammeter
ML24004A0402024-01-0303 January 2024
Response to NRCs November 8, 2023, Request for Additional Information - Related to Independent Spent Fuel Storage Installation
ML23346A1382024-01-0303 January 2024
Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods
IR 05000390/20234412023-12-21021 December 2023
Plantfinal Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public
CNL-23-069, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
CNL-23-068, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023
Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)
IR 05000390/20234042023-12-14014 December 2023
Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404
CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023
Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)
ML23346A1222023-12-12012 December 2023
Annual Non-Radiological Environmental Operating Report - 2023
ML23293A0572023-12-0606 December 2023
Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control
IR 05000390/20230102023-11-30030 November 2023
RE-Issue Watts Bar Nuclear Plant - Biennial Problem Identification and Resolution Inspection Report 050000390/2023010 and 05000391/2023010 and Apparent Violation
IR 05000327/20234202023-11-28028 November 2023
Security Baseline Inspection Report 05000327/2023420 and 05000328/2023420
CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023
Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
IR 05000390/20230032023-11-13013 November 2023
Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation
ML23324A4362023-11-0909 November 2023
Exam Corporate Notification Letter Aka 210-day Letter
ML23307A0822023-11-0808 November 2023
Request for Additional Information August 4, 2022, Exemption Request for Deviating from the Conditions of Certificate of Compliance No. 1032, Amendment No. 3, Related to Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation
ML23312A1432023-11-0808 November 2023
Submittal of Dual Unit Updated Final Safety Analysis Report (UFSAR) Amendment 5
IR 05000327/20230032023-11-0303 November 2023
Integrated Inspection Report 05000327/2023003 and 05000328/2023003
ML23306A1592023-11-0202 November 2023
Enforcement Action EA-22-129 Inspection Readiness Notification
ML23292A0792023-10-19019 October 2023
Tennessee Valley Authority - Emergency Plan Implementing Procedure Revision, Includes EPIP-5, Revision 58, General Emergency
IR 05000327/20230112023-10-16016 October 2023
Triennial Fire Protection Inspection Report 05000327/2023011 and 05000328/2023011
ML23285A0882023-10-12012 October 2023
Submittal of Sequoyah Nuclear Plant, Units 1 and 2, Submittal of Updated Final Safety Analysis Report Amendment 31
ML23284A4252023-10-11011 October 2023
10 CFR 50.59 and 10 CFR 72.48 Changes, Tests, and Experiments Summary Report; Commitment Summary Report; and Update to the Fire Protection Report
ML23283A2792023-10-10010 October 2023
Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Requirements Manual
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)
ML23277A0462023-10-0404 October 2023
Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases
ML23275A0272023-09-29029 September 2023
Submittal of Discharge Monitoring Report (DMR) Quality Assurance Study 43 Final Report 2023
ML23271A1662023-09-28028 September 2023
Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2)
CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision
CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023
Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03
2024-01-09
[Table view] |
Text
February 16, 2021 Mr. James Barstow Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801
SUBJECT:
SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2; AND WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 - CORRECTION OF AMENDMENT NOS. 352, 346, 141, AND 47 REGARDING THE ADOPTION OF TECHNICAL SPECIFICATION TASK FORCE TRAVELER, TSTF-569, REVISION 2, REVISE RESPONSE TIME TESTING DEFINITION (EPID L-2020-LLA-0133)
Dear Mr. Barstow:
On January 25, 2021, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 352 and 346 to Renewed Facility Operating License Nos. DPR-77 and DPR-79, for the Sequoyah Nuclear Plant, Units 1 and 2, respectively; and Amendment Nos. 141 and 47 to Facility Operating License Nos. NPF-90 and NPF-96 for the Watts Bar Nuclear Plant, Units 1 and 2, respectively. The amendments revised the Technical Specifications (TSs) to adopt Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition. During issuance of the amendment, the NRC staff used a version of TS page 1.1-6 for Watts Bar Nuclear Plant, Unit 2, that inadvertently omitted the number 42 from the list of amendments in the footer of the page.
In addition, the NRC staffs safety evaluation included the following statement on page 2:
[] and for RPS [reactor protection system] RESPONSE TIME [i]n lieu of measurement, response time may be verified for selected components provided that the components have been evaluated in accordance with an NRC approved methodology.
RPS RESPONSE TIME applies only to Combustion Engineering-designed plants and is not applicable to either Sequoyah Nuclear Plant, Units 1 and 2, or Watts Bar Nuclear Plant, Units 1 and 2.
The purpose of this letter is to issue a correction to Watts Bar, Unit 2, TS page 1.1-6 to include the number 42 in the list of applicable amendments in the footer of the page. In addition, the NRC staff is issuing a revised page 2 of its safety evaluation to delete the inapplicable discussion. A copy of the Watts Bar, Unit 2, TS page 1.1-6, and page 2 of the safety evaluation for Amendment Nos. 352, 346, 141, and 47 is enclosed. The NRC staff concludes that the enclosed corrections do not change the staffs previous conclusion in the safety evaluations for Amendment Nos. 352, 346, 141, and 47, nor do they affect the no significant hazards considerations, as published in the Federal Register on August 25, 2020 (85 FR 52374).
J. Barstow If you have any questions regarding this matter, please contact me at (301) 415-6459 or by e-mail at michael.wentzel@nrc.gov.
Sincerely,
/RA/
Michael J. Wentzel, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327, 50-328, 50-390 and 50-391
Enclosures:
- 1. Corrected Technical Specification Page 1.1-6
- 2. Corrected Safety Evaluation Page 2 cc: Listserv
ENCLOSURE 1 WATTS BAR NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-391 CORRECTED TECHNICAL SPECIFICATION PAGE 1.1-6
'HILQLWLRQV
'HILQLWLRQV FRQWLQXHG
48$'5$1732:(57,/7 4375VKDOOEHWKHUDWLRRIWKHPD[LPXPXSSHUH[FRUH
5$7,2 4375 GHWHFWRUFDOLEUDWHGRXWSXWWRWKHDYHUDJHRIWKHXSSHUH[FRUH
GHWHFWRUFDOLEUDWHGRXWSXWVRUWKHUDWLRRIWKHPD[LPXPORZHU
H[FRUHGHWHFWRUFDOLEUDWHGRXWSXWWRWKHDYHUDJHRIWKHORZHU
H[FRUHGHWHFWRUFDOLEUDWHGRXWSXWVZKLFKHYHULVJUHDWHU
5$7('7+(50$/32:(5 573VKDOOEHDWRWDOUHDFWRUFRUHKHDWWUDQVIHUUDWHWRWKH
573 UHDFWRUFRRODQWRI590:W
5($&72575,36<67(0 7KH5765(63216(7,0(VKDOOEHWKDWWLPHLQWHUYDOIURP
576 5(63216(7,0( ZKHQWKHPRQLWRUHGSDUDPHWHUH[FHHGVLWV576WULSVHWSRLQW
DWWKHFKDQQHOVHQVRUXQWLOORVVRIVWDWLRQDU\JULSSHUFRLO
YROWDJH7KHUHVSRQVHWLPHPD\EHPHDVXUHGE\PHDQVRI
DQ\VHULHVRIVHTXHQWLDORYHUODSSLQJRUWRWDOVWHSVVRWKDW
WKHHQWLUHUHVSRQVHWLPHLVPHDVXUHG,QOLHXRI
PHDVXUHPHQWUHVSRQVHWLPHPD\EHYHULILHGIRUVHOHFWHG
FRPSRQHQWVSURYLGHGWKDWWKHFRPSRQHQWVDQGWKH
PHWKRGRORJ\IRUYHULILFDWLRQKDYHEHHQSUHYLRXVO\UHYLHZHG
DQGDSSURYHGE\WKH15&RUWKHFRPSRQHQWVKDYHEHHQ
HYDOXDWHGLQDFFRUGDQFHZLWKDQ15&DSSURYHG
PHWKRGRORJ\
6+87'2:10$5*,1 6'0 6'0VKDOOEHWKHLQVWDQWDQHRXVDPRXQWRIUHDFWLYLW\E\ZKLFK
WKHUHDFWRULVVXEFULWLFDORUZRXOGEHVXEFULWLFDOIURPLWV
SUHVHQWFRQGLWLRQDVVXPLQJ
D $OOURGFOXVWHUFRQWURODVVHPEOLHV 5&&$V DUHIXOO\
LQVHUWHGH[FHSWIRUWKHVLQJOH5&&$RIKLJKHVWUHDFWLYLW\
ZRUWKZKLFKLVDVVXPHGWREHIXOO\ZLWKGUDZQ:LWKDQ\
5&&$QRWFDSDEOHRIEHLQJIXOO\LQVHUWHGWKHUHDFWLYLW\
ZRUWKRIWKH5&&$PXVWEHDFFRXQWHGIRULQWKH GHWHUPLQDWLRQRI6'0 DQG E ,Q02'(6DQGWKHIXHODQGPRGHUDWRUWHPSHUDWXUHV DUHFKDQJHGWRWKHQRPLQDO]HURSRZHUGHVLJQOHYHO
6/$9(5(/$<7(67 $6/$9(5(/$<7(67VKDOOFRQVLVWRIHQHUJL]LQJHDFKVODYH
UHOD\DQGYHULI\LQJWKH23(5$%,/,7<RIHDFKVODYHUHOD\
7KH6/$9(5(/$<7(67VKDOOLQFOXGHDVDPLQLPXPD
FRQWLQXLW\FKHFNRIDVVRFLDWHGWHVWDEOHDFWXDWLRQGHYLFHV
FRQWLQXHG
- DWWV%DU8QLW $PHQGPHQW42, 47
ENCLOSURE 2 SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-327, 50-328, 50-390, AND 50-391 CORRECTED SAFETY EVALUATION PAGE 2
initiates necessary safety systems, based on the values of selected unit parameters, to protect against violating core design limits and the RCS pressure boundary and to mitigate accidents.
The RTT verifies that the individual channel or train actuation response times are less than or equal to the maximum values assumed in the accident analyses. The RTT acceptance criteria are under licensee control. Individual component response times are not modeled in the accident analyses. The analyses model the overall or total elapsed time, from the point at which the parameter exceeds the trip setpoint value at the sensor to the point at which the equipment reaches the required functional state (e.g., control and shutdown rods fully inserted in the reactor core).
2.2 Proposed Changes to the Technical Specifications Sequoyah and Watts Bar Limiting Condition for Operation (LCO) 3.3.2 requires the ESFAS instrumentation for each Function in TS Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, to be OPERABLE. To assure the LCO is met, Sequoyah SR 3.3.2.9 and Watts Bar SR 3.3.2.10 require the licensee to verify that ESFAS RESPONSE TIMES are within limits. Similarly, Sequoyah and Watts Bar LCOs 3.3.1 require the RTS instrumentation for each Function in TS Table 3.3.1-1, Reactor Trip System Instrumentation, to be OPERABLE, and Sequoyah SR 3.3.1.14 and Watts Bar SR 3.3.1.15 requires the licensee to verify that RTS RESPONSE TIMES are within limits. Section 1.1 of the TS define ESF RESPONSE TIME and RTS RESPONSE TIME, state acceptable means to measure each response time, and provide an alternative that may be used [i]n lieu of measurement.
In its application, the licensee stated that it requests adoption of NRC-approved TSTF-569. The only revision of TSTF-569 that is NRC approved is Revision 2. As described in Section 1, Summary Description, of Revision 2 of TSTF-569:
The proposed change revises the definitions to eliminate the requirement for prior NRC review and approval of the response time verification of similar components, while retaining the requirement for the verification to be performed using the methodology contained in Attachment 1, titled, Methodology to Eliminate Pressure Sensor and Protection Channel (for Westinghouse Plants only) Response Time Testing. The proposed change will permit licensees to verify the response time of similar component types using the methodology contained in Attachment 1, without obtaining prior NRC approval for each component.
Accordingly, as shown in the licensee's LAR, the proposed changes would add an additional in lieu of measurement, alternative to measuring ESF RESPONSE TIME and RTS RESPONSE TIME for Sequoyah and Watts Bar. The additional alternative for ESF RESPONSE TIME would be [i]n lieu of measurement, response time may be verified for selected components provided
... the components have been evaluated in accordance with an NRC approved methodology.
Similarly, for RTS RESPONSE TIME, [i]n lieu of measurement, response time may be verified for selected components provided that ... the components have been evaluated in accordance with an NRC approved methodology.
The application stated that the licensee concluded that the justifications presented in TSTF-569 and the safety evaluation prepared by the NRC staff are applicable to Sequoyah and Watts Bar
ML21033B071 *by e-mail OFFICE NRR/DORL/LPLII-2/PM NRR/DORL/LPLII-2/LA* NRR/DSS/STSB/BC*
NAME MWentzel BAbeywickrama VCusumano DATE 02/10/2021 02/10/2021 02/05/2021 OFFICE NRR/DORL/LPLII-2/BC* NRR/DORL/LPLII-2/PM*
NAME UShoop MWentzel DATE 02/16/2021 02/16/2021
