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MONTHYEARML1016803802010-06-17017 June 2010 License Amendment Request, Technical Specification Change to Extend the Type a Test Frequency to 15 Years Project stage: Other ML1017601262010-06-25025 June 2010 Acceptance Review Email Technical Specification Change to Extend Type a Test Frequency to 15 Years Project stage: Acceptance Review ML1032103022010-11-17017 November 2010 Request for Additional Information Email, License Amendment Request, Revise Technical Specification 6.5.16, Containment Leakage Rate Testing Program, to Extend Type a Test Frequency to 15 Years Project stage: RAI ML1032202362010-11-18018 November 2010 Request for Additional Information, Email, License Amendment Request, Revise Technical Specification 6.5.16, Containment Leakage Rate Testing Program, to Extend Type a Test Frequency to 15 Years - Revision 1 Project stage: RAI 2CAN011102, Response to the Request for Additional Information Regarding License Amendment Request Technical Specification Change to Extend Type a Test Frequency to 15 Years2011-01-17017 January 2011 Response to the Request for Additional Information Regarding License Amendment Request Technical Specification Change to Extend Type a Test Frequency to 15 Years Project stage: Request 2CAN011104, Response to the Request for Clarification Regarding License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years2011-01-20020 January 2011 Response to the Request for Clarification Regarding License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years Project stage: Request 2CAN011109, Response to Request for Additional Clarifications Regarding License Amendment Request Technical Specification Change to Extend Type a Test Frequency to 15 Years2011-01-31031 January 2011 Response to Request for Additional Clarifications Regarding License Amendment Request Technical Specification Change to Extend Type a Test Frequency to 15 Years Project stage: Request ML1104606762011-02-15015 February 2011 Request for Additional Information Email, Round 2, License Amendment Request, Revise Technical Specification 6.5.16, Containment Leakage Rate Testing Program, to Extend Type a Test Frequency to 15 Years Project stage: RAI 2CAN031101, Response to the Request for Additional Information Regarding License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years2011-03-0707 March 2011 Response to the Request for Additional Information Regarding License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years Project stage: Request ML1108000342011-04-0707 April 2011 Issuance of Amendment No. 292 to Revise Technical Specification 6.5.16, Containment Leakage Rate Testing Program, to Extend Type a Test Frequency to 15 Years Project stage: Approval 2011-01-17
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Category:Letter
MONTHYEARML23326A0392024-01-24024 January 2024 Issuance of Amendment No. 281 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24017A1582024-01-17017 January 2024 Submittal of Emergency Plan Revision 50 IR 05000313/20234202024-01-10010 January 2024 Security Baseline Inspection Report 05000313/2023420 and 05000368/2023420 IR 05000313/20234022024-01-0202 January 2024 Security Baseline Inspection Report 05000313/2023402 and 05000368/2023402 ML23354A0022023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment IR 05000313/20234052023-12-12012 December 2023 Security Baseline Inspection Report 05000313/2023405 and 05000368/2023405 ML23341A0832023-12-11011 December 2023 Material Control and Accounting Program Inspection Report 05000313/368/2023404- Cover Letter ML23305A0922023-12-0707 December 2023 Summary of Regulatory Audit Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23275A2072023-11-28028 November 2023 Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23325A1412023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000313/20230032023-11-21021 November 2023 Revised - ANO Revised Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/ 2023001 ML23243B0452023-11-13013 November 2023 Request for Withholding Information from Public Disclosure ML23313A0962023-11-13013 November 2023 Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/2023001 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000313/20230112023-10-10010 October 2023 Commercial Grade Dedication Inspection Report 05000313/2023011 and 05000368/2023011 IR 05000313/20230052023-08-21021 August 2023 Updated Inspection Plan for Arkansas Nuclear One, Units 1 and 2 (Report 05000313/2023005 and 05000368/2023005) - Mid Cycle IR 05000313/20243012023-08-14014 August 2023 Notification of NRC Initial Operator Licensing Examination 05000313/2024301 IR 05000313/20230022023-08-11011 August 2023 Integrated Inspection Report 05000313/2023002 and 05000368/2023002 and Notice of Violation ML23209A6022023-08-0909 August 2023 Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications to Adopt Risk- Informed Completion Times IR 05000416/20230022023-08-0808 August 2023 Integrated Inspection Report 05000416/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200050/2023001 ML23208A2132023-08-0303 August 2023 Regulatory Audit Summary Concerning Review of License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23188A1732023-07-12012 July 2023 Request for Withholding Information from Public Disclosure ML23142A2022023-06-29029 June 2023 Issuance of Amendment Nos. 279 and 332 Emergency Plan Staffing Requirements IR 05000313/20234032023-06-28028 June 2023 Security Baseline Inspection Report 05000313/2023403 and 05000368/2023403 ML23178A0892023-06-26026 June 2023 August 2023 Emergency Preparedness Program Inspection-Request for Information ML23166B0902023-06-21021 June 2023 Request for Relief ANO1 ISI 036 Regarding Volumetric Examination Requirements ML23180A1082023-06-20020 June 2023 ANO Unit 1 SAR Amendment 31, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report IR 05000313/20234012023-06-13013 June 2023 Cyber Security Inspection Report 05000313/2023401 and 05000368/2023401 ML23130A2972023-05-17017 May 2023 Notification of Inspection (NRC Inspection Report 05000313/2023003) and Request for Information ML23121A3012023-05-10010 May 2023 Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications to Adopt Risk - Informed Completion Times ML23114A3572023-05-10010 May 2023 Regulatory Audit Summary Concerning Review of Request for Alternative ANO-CISI-002 Regarding Containment Inservice Inspection Frequency ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000313/20230012023-05-0909 May 2023 Integrated Inspection Report 05000313/2023001 and 05000368/2023001 ML23118A3202023-05-0808 May 2023 Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000313;05000368/2023010) IR 05000368/20233012023-05-0101 May 2023 NRC Examination Report 05000368/2023301 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23108A1362023-04-24024 April 2023 Approval of Request for Half-Nozzle Repair of Reactor Vessel Closure Head Penetration No. 46 ML23110A1122023-04-20020 April 2023 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G 2024-01-24
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Text
2CAN011109
January 31, 2011
U.S. Nuclear Regulatory Commission
Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Response to the Request for Additional Clarifications Regarding License Amendment Request Technical Specification Change to Extend the Type A Test Frequency to 15 Years
Arkansas Nuclear One, Unit 2
Docket No. 50-368 License No. NPF-6
REFERENCES:
- 1. Entergy letter dated June 17, 2010, "License Amendment Request Technical Specification Change to Extend the Type A Test Frequency to 15 Years" (2CAN061003)
- 2. Entergy letter dated January 17, 2011, "Response to the Request for Additional Information Regarding License Amendment Request Technical Specification Change to Extend the Type A Test Frequency to 15 Years" (2CAN011102)
- 3. Entergy letter dated June 29, 2000, "Request for Exemption from 10 CFR 50, Appendix J" (2CAN060011)
- 4. NRC letter dated October 12, 2000, "Arkansas Nuclear One Unit 2 One-Time Exemption from the Requirements of 10 CFR Part 50, Appendix J, Option B (TAC MA9350)" (2CNA100002)
- 5. NRC email dated November 18, 2010, "Request for Additional Information (RAI) on License Amendment Request dated June 17, 2010, Technical Specification Change to Extend the Type A Test Frequency to 15 years -
REVISION 1" (TAC No. ME4090)
Dear Sir or Madam:
Entergy Operations, Inc. (Entergy) proposed a change to the Arkansas Nuclear One, Unit 2 (ANO-2) Technical Specifications (TS) via Reference 1. Specifically, the change would allow for the extension of the ten-year frequency of the ANO-2 Type A or Integrated Leak Rate Test (ILRT) required by TS 6.5.16 to 15 years on a permanent basis.
Christopher J. Schwarz Vice President - Operations Arkansas Nuclear One Entergy Operations, Inc. 1448 S.R. 333 Russellville, AR 72802 Tel 479-858-3110 2CAN011109 Page 2 of 3
In an email dated January 21, 2011, the NRC noted an apparent contradiction in the containment test pressure quoted in the Reference 1 application for the TS change and the responses to the Request for Additional Information (RAIs) provided in Reference 2.
Reference 1 states the November 30, 2000, test was "performed at the new higher design pressure of 58 psig." Note 2 of Table 2.2-1 in Reference 2 provided the ILRT test results as "percent of containment air weight per day at Structural Integrity Test pressure (68 psig)."
In addition, it was noted that the NRC email referenced in Entergy's letter dated January 17, 2011 (Reference 2 of this submittal) is dated November 23, 2010. The NRC believes it should be an email dated November 18, 2010 (Reference 5 of this submittal). The NRC requested Entergy to review these potential contradictions and submit a supplement correcting these as necessary. This submittal provides the requested supplement.
Both of these apparent discrepancies are clarified below.
Test Pressure
10 CFR 50, Appendix J, Option B,Section III.A, for Type A tests states, "Type A tests to measure the containment system overall integrated leakage rate must be conducted under conditions representing design basis loss-of-coolant accident containment peak pressure." The original design basis loss-of-coolant accident (LOCA) containment peak pressure for the ANO-2 containment was 54 psig.
The steam generators were replaced during the fall of 2000. This replacement required an access opening to be cut in the containment building structure. Upon closure of the containment structure, a Type A test was required (e.g., performed November 30, 2000). This test was performed at a higher pressure to encompass the new LOCA containment peak pressure required by the new steam generators. The new LOCA containment peak pressure was determined to be 58 psig with a design pressure of 59 psig.
As a result of this increase, a Structural Integrity Test (SIT) was performed to evaluate the ANO-2 containment structure for the change in design pressure. The purpose of this test was to verify that the containment structure could safely carry design loads and that the structural behavior was similar to that predicted by analysis. The test was performed at 68 psig
(1.15 times the revised design pressure).
Entergy desired to perform the Type A test concurrently with the SIT, at the SIT test pressure. Entergy submitted an exemption request (Reference 3) to perform the Type A test at this higher pressure. Reference 4 provided the NRC's approval of the one-time exemption to perform the Type A test at 68 psig. The results of this test are noted in Reference 2.
Based on the above, the discrepancy was that 58 psig was denoted as the new design pressure for the Type A test when it is actually the new design basis LOCA containment peak pressure at which the Type A test would normally be performed. The last Type A test performed to date was the one on November 30, 2000. It was performed at the SIT pressure of 68 psig.
2CAN011109 Page 3 of 3
Request for Additional Information
Reference 5 provided the original formal request for additional information related to the subject TS change. Based upon a review of the requests, it was believed that one of the requests (RAI 2.1(d)) should have been deleted from the formal RAIs based on previous discussions with the Staff. This was noted in Reference 2. This deletion was confirmed in a separate follow-up email. This follow-up email was the one (dated November 23, 2010) cited in Reference 2, not the original request (dated November 18, 2010), since it provided the clarification. Entergy concurs with the NRC with regard to the correct reference that should have been cited.
There are no new commitments in this letter.
If you have any questions or require additional information, please contact Stephenie Pyle at 479-858-4704.
I declare under penalty of perjury that the foregoing is true and correct. Executed on January 31, 2011.
Sincerely, Original signed by Christopher J. Schwarz CJS/rwc
cc: Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125
NRC Senior Resident Inspector Arkansas Nuclear One P. O. Box 310
London, AR 72847
U. S. Nuclear Regulatory Commission Attn: Mr. Kaly Kalyanam MS O-8B1 One White Flint North
11555 Rockville Pike
Rockville, MD 20852 Mr. Bernard R. Bevill
Arkansas Department of Health Radiation Control Section 4815 West Markham Street Slot #30 Little Rock, AR 7220