Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
Results
Other: 2CAN010401, Arkansas, Unit 2 - License Renewal Application Clarifications, 2CAN020502, License Renewal Clarification, Arkansas Nuclear One - Unit 2, 2CAN030401, License Renewal Application Clarifications, Arkansas Nuclear One - Unit 2, 2CAN070409, Unit 2, License Renewal Application Clarifications, 2CAN080401, Unit 2, License Renewal Application Clarifications, 2CAN090402, Unit 2, License Renewal Application Clarifications, 2CAN100302, License Renewal Application, Attachment a - E, ML040900270
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MONTHYEAR2CAN100302, License Renewal Application, Attachment a - E2003-10-14014 October 2003 License Renewal Application, Attachment a - E Project stage: Other ML0407706112003-12-22022 December 2003 E-Mail MSIV Leakage Pathway RAI & License Amendment Request - Attachment 3 Project stage: Request ML0407706062003-12-22022 December 2003 E-mail Draft Proposed Emergency Changes to Technical Specifications 3.8.1.1 to Support Steam Diesel Generator Inspections - Attachment 4 Project stage: Request ML0407705992003-12-22022 December 2003 Draft Information Input Configuration Risk Management Program - Attachment 5 Project stage: Request ML0407705932003-12-23023 December 2003 Draft Information Request PRA Analysis Assessment PRA-03-024, Rev. 0 - Attachment 6 Project stage: Request ML0407705842003-12-28028 December 2003 Draft Information Input Material Discussion - Attachment 8 Project stage: Request 2CAN010401, Arkansas, Unit 2 - License Renewal Application Clarifications2004-01-22022 January 2004 Arkansas, Unit 2 - License Renewal Application Clarifications Project stage: Other ML0406105422004-02-26026 February 2004 & 12/16/2003 Summary of Telephone Calls with Entergy Operations Incorporated Regarding Draft Responses to Questions Pertaining to the Arkansas Nuclear One, Unit 2 License Renewal Application Project stage: Draft Other ML0407104662004-03-0808 March 2004 Request for Additional Information for the Review of the Arkansas Nuclear One, Unit 2, License Renewal Application Project stage: RAI 2CAN030401, License Renewal Application Clarifications, Arkansas Nuclear One - Unit 22004-03-24024 March 2004 License Renewal Application Clarifications, Arkansas Nuclear One - Unit 2 Project stage: Other ML0409002702004-03-29029 March 2004 Summary of Telephone Call Between U.S. Nuclear Regulatory Commission (NRC) and Entergy Operations Incorporated Concerning Questions Pertaining to Aging Management Review for Arkansas Nuclear One, Unit 2 LRA Project stage: Other 2CAN040401, Unit 2, Request for Additional Information Responses for License Renewal Application TAC No. MB84022004-04-0606 April 2004 Unit 2, Request for Additional Information Responses for License Renewal Application TAC No. MB8402 Project stage: Request ML0409902302004-04-0808 April 2004 Request for Additional Information for the Review of the Arkansas Nuclear One, Unit 2, License Renewal Application Project stage: RAI ML0410508202004-04-13013 April 2004 Request for Additional Information for the Review of the Arkansas Nuclear One, Unit 2, License Renewal Application Project stage: RAI ML0408206822004-04-13013 April 2004 Draft Information Input, Memo from 12/2/03 to 12/28/03 Project stage: Request ML0410508582004-04-14014 April 2004 Request for Additional Information, Review of the Arkansas Nuclear One, Unit 2, License Renewal Application Project stage: RAI ML0412003842004-04-23023 April 2004 Request for Additional Information for the Review of the Arkansas Nuclear One, Unit 2, License Renewal Application Project stage: RAI ML0412805542004-05-0505 May 2004 RAI, License Renewal Application, Section 3.3 Auxiliary Systems Project stage: RAI ML0413304862004-05-11011 May 2004 Request for Additional Information for Arkansas Nuclear One-Unit 2 License Renewal Application from Plant Systems Branch Division of Systems Safety and Analysis Docket No. 50-368 Project stage: RAI 05000368/LER-2004-001, Unit 2 Operation Prohibited by Technical Specifications Due to an Inoperable Channel of Wide-Range Containment Water Level Instrumentation2004-05-17017 May 2004 Unit 2 Operation Prohibited by Technical Specifications Due to an Inoperable Channel of Wide-Range Containment Water Level Instrumentation Project stage: Request ML0413802842004-05-17017 May 2004 Request for Additional Information for the Review of the Arkansas Nuclear One, Unit 2, License Renewal Application (Tac No. MB8402) Project stage: RAI 2CAN050404, Arkansas, Unit 2, Request for Additional Information Responses for License Renewal Application2004-05-19019 May 2004 Arkansas, Unit 2, Request for Additional Information Responses for License Renewal Application Project stage: Request 2CAN050401, Arkansas, Unit 2 - Request for Additional Information Responses for License Renewal Application2004-05-19019 May 2004 Arkansas, Unit 2 - Request for Additional Information Responses for License Renewal Application Project stage: Request 2CAN050403, Arkansas, Unit 2 - Request for Additional Information Responses for License Renewal Application2004-05-19019 May 2004 Arkansas, Unit 2 - Request for Additional Information Responses for License Renewal Application Project stage: Request 2CAN050402, Arkansas, Unit 2, Request for Additional Information Response for License Renewal Application2004-05-19019 May 2004 Arkansas, Unit 2, Request for Additional Information Response for License Renewal Application Project stage: Request 2CAN050407, Unit 2, Request for Additional Information Responses for License Renewal Application TAC No. MB84022004-05-24024 May 2004 Unit 2, Request for Additional Information Responses for License Renewal Application TAC No. MB8402 Project stage: Request ML0414700212004-05-25025 May 2004 Request for Additional Information for Review of Arkansas Nuclear One, Unit 2, License Renewal Application - DE Eeib Mcconnell Knox Project stage: RAI ML0414801342004-05-26026 May 2004 Request for Additional Information for the Review of the Arkansas Nuclear One, Unit 2, License Renewal Application (Tac No. MB8402) Project stage: RAI 2CAN060401, Arkansas, Unit 2, Request for Additional Information Responses for License Renewal Application2004-06-10010 June 2004 Arkansas, Unit 2, Request for Additional Information Responses for License Renewal Application Project stage: Request ML0416202472004-06-11011 June 2004 Request for Additional Information, Arkansas Nuclear One, Unit 2, License Renewal Application Project stage: RAI 2CAN060403, Unit 2 - Request for Additional Information Responses for License Renewal Application TAC No. MB84022004-06-16016 June 2004 Unit 2 - Request for Additional Information Responses for License Renewal Application TAC No. MB8402 Project stage: Request ML0417305712004-06-21021 June 2004 Summary of Telephone Call with Entergy Operations, Inc., Representatives Regarding Draft Request for Additional Information Pertaining to the Arkansas Nuclear One, Unit 2 License Renewal Application Project stage: Draft RAI ML0417305262004-06-21021 June 2004 & 04/16/2004 Summary of Telephone Calls Between the U.S. NRC Staff and Entergy Operations, Inc., Representatives Concerning Draft Request for Additional Information Pertaining to the Arkansas Nuclear One Project stage: Draft RAI ML0417700372004-06-23023 June 2004 & 05/27/2004, Summary of Telephone Calls Held Between the U.S. Nuclear Regulatory Commission (NRC) Staff and Entergy Operations, Inc., Representatives Concerning Drai Pertaining to the Arkansas One, Unit 2, License Renewal Application Project stage: RAI ML0417705572004-06-24024 June 2004 Request for Additional Information, Review of the Arkansas Nuclear One, Unit 2, License Renewal Application Project stage: RAI 2CAN070404, Unit 2, Request for Additional Information Responses for License Renewal Application2004-07-0101 July 2004 Unit 2, Request for Additional Information Responses for License Renewal Application Project stage: Request ML0419602602004-07-14014 July 2004 Summary of Telephone Conference Call Held on June 30, 2004, Between NRC and Entergy Representatives Concerning Request for Additional Information Pertaining to the Arkansas Nuclear One, Unit 2, LRA Project stage: RAI ML0421603562004-07-22022 July 2004 Unit 2, Request for Additional Information Responses for License Renewal Application Project stage: Request 2CAN070409, Unit 2, License Renewal Application Clarifications2004-07-22022 July 2004 Unit 2, License Renewal Application Clarifications Project stage: Other 2CAN070406, Unit 2, Request for Additional Information Responses for License Renewal Application2004-07-22022 July 2004 Unit 2, Request for Additional Information Responses for License Renewal Application Project stage: Request 2CAN080401, Unit 2, License Renewal Application Clarifications2004-08-18018 August 2004 Unit 2, License Renewal Application Clarifications Project stage: Other ML0423703952004-08-23023 August 2004 Summary of Telephone Conference Held on July 28, 2004, Between the USNRC and Entergy Operations, Inc., Concerning a Request for Additional Information Pertaining to the Arkansas Nuclear Station, Unit 2, License Renewal Application Project stage: RAI ML0423806322004-08-25025 August 2004 Summary of Telephone Call Held on July 7 and 8, 2004, Between the U.S. Nuclear Regulatory Commission (NRC) Staff and Entergy Operations Inc., Representatives Concerning Request for Additional Information Pertaining to the Arkansas Nuclear O Project stage: RAI 2CAN090402, Unit 2, License Renewal Application Clarifications2004-09-10010 September 2004 Unit 2, License Renewal Application Clarifications Project stage: Other ML0427406512004-09-30030 September 2004 Summary of Telephone Calls Held on August 26 and September 1, 2004, Between the U.S. NRC Staff and Entergy Operations Inc., Representatives Concerning RAI Pertaining to the Arkansas Nuclear One, Unit 2 LRA Project stage: RAI ML0427406292004-09-30030 September 2004 Summary of Telephone Call Held on August 24, 2004, Between the U.S. Nuclear Regulatory Commission (NRC) Staff and Entergy Operations Inc., Representatives Concerning Request for Additional Information Pertaining to the Arkansas Nuclear One, Project stage: RAI 2CAN120403, License Renewal Application Draft Safety Evaluation Report Comments2004-12-0909 December 2004 License Renewal Application Draft Safety Evaluation Report Comments Project stage: Draft Other 2CAN020502, License Renewal Clarification, Arkansas Nuclear One - Unit 22005-02-28028 February 2005 License Renewal Clarification, Arkansas Nuclear One - Unit 2 Project stage: Other 2004-05-24
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Text
En tegyRussellville, AR 72802 Tel 501 858 5000 2CAN030401 March 24, 2004 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
License Renewal Application Clarifications TAC No. MB8402 Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6
Dear Sir or Madam:
By letter dated October 14, 2003 (2CAN100302), Entergy submitted the Arkansas Nuclear One, Unit 2 (ANO-2) License Renewal Application (LRA). During the week of February 9, 2004, the NRC performed an on-site audit of the ANO-2 previously approved Staff position comparisons. As a result of this audit, the following are clarifications to the LRA:
Audit item 2621: The Inservice Inspection Program applies to the safe-ends (page 3.1-88) of Table 3.1.2-4 in addition to the Water Chemistry Program to manage cracking (other than fatigue).
Audit item 2625: Reference to Generic Aging Lessons Learned (GALL) Volume 2 IV.C2.5-s is not appropriate for the 3 inch inspection port diaphragms (page 3.1-98) of Table 3.1.2-5. Note 1 01 is the appropriate note for this item rather than notes 'C' and nEt.
Audit item 2627: Reference to the GALL item V.Dl.6-a is not appropriate for heater housing," and the correct note is 201 rather than "A' in Table 3.2.2-2 (page 3.2-29).
Audit item 2638: Reference to the GALL item VlI.H2.1-a is not appropriate for "valve,' and the correct note is 301 rather than 'E' in Table 3.3.2-2 (page 3.3-43).
Audit item 2639: The aging effects for carbon steel and cast iron are the same in all environments with the exception that gray cast iron is susceptible to the aging mechanism of selective leaching. Where selective leaching is possible, an additional program is credited unless the one specified program will manage selective leaching such as the Diesel Fuel Monitoring and Oil Analysis Programs.
JtlD
2CAN030401 Page 2 Selective leaching does not normally occur in air, lube oil, or fuel oil due to the lack of an aqueous environment. In the LRA, if cast iron components are gray cast iron and are exposed to an environment conducive to selective leaching, then they are managed by a program (Periodic Surveillance and Preventive Maintenance (PSPM)
Program, Service Water Integrity Program (SWIP), or Fire Protection Program) that includes the management of loss of material due to selective leaching.
Audit item 2643: The PSPM Program manages loss of material for the emergency diesel generator (EDG) heat exchanger bonnet in fresh raw water (page 3.3-51) in Table 3.3.2-3 through periodic internal inspections during EDG overhauls. In addition to the PSPM Program, the SWIP is conservatively included as an aging management program since it provides additional aging management of this component.
Audit item 2644: The Auxiliary Systems Water Chemistry Control Program applies to the EDG heat exchanger bonnet and shell in treated water (page 3.3-51) rather than the PSPM Program.
- Audit item 2646: In Table 3.3.2-3, reference to note "D" is not appropriate for the EDG heater housing and orifice (page 3.3-54) and the carbon and stainless steel piping (page 3.3-56) in treated water. The correct note is "E."
- Audit item 2648: In Table 3.3.2-3, reference to note 'D" is not appropriate for the EDG pump casing and tank (page 3.3-57), tubing (page 3.3-59), and valve (page 3.3-61) in treated water. The correct note is 'E."
- Audit item 2650: Section 3.3.2.2.2 states, "Elastomers are used in other systems (other than spent fuel cooling systems and ventilation systems)." For these systems, management of elastomer degradation is provided by the PSPM program and supplemented by the Fire Protection Program." The words "supplemented by" were meant to imply that for fire protection elastomers, the Fire Protection Program is used instead of the PSPM Program.
Audit item 2651: Reference to "water chemistry control" for the alternate AC diesel generator stainless steel expansion joint in treated water (page 3.3-67) in Table 3.3.2-4 means the Auxiliary Systems Water Chemistry Control Program. In addition, wherever notes 1B" or 'D" were used in Tables 3.3.2-3 and 3.3.2-4 with the Auxiliary Systems Water Chemistry Control Program as an aging management program, note "E" should have been used since the Auxiliary Systems Water Chemistry Control Program is the water chemistry control program for treated water, and it is a plant-specific program.
- Audit item 2660: Cracking-fatigue is identified as an aging effect for the chemical and volume control system pump casing (page 3.3-84) in Table 3.3.2-5 with the PSPM Program as an aging management program. Cracking-fatigue should be included as an aging effect for the chemical and volume control system charging pumps in the "Detection of Aging Effects" of Section B.1.18 of Appendix B.
2CAN030401 Page 3 Audit item 2687: In LRA Table 3.5.2-1 (page 3.5-27), reference to Table 1 item 3.5.1-15 is appropriate for tendon anchorage and tendon wires rather than to Table 1 item 3.5.1-3. Also, for item 3.5.1-15 (page 3.5-17), the appropriate reference is to the Inservice Inspection (IWL) Program rather than the Inservice Inspection (IWE)
Program.
Audit item 2690: In Table 3.5.2-4 (page 3.5-38), the correct reference to GALL Volume 2 for the heating, ventilation, and air-conditioning missile barrier is III.A3.2-a rather than III.A2.2-a.
In addition, cast iron was inadvertently included in Section 3.3.2.1.1 (page 3.3-2) and Table 3.3.2-1 (page 3.3-32) as a valve material for the spent fuel pool system. Cast iron is not a valve material in the spent fuel pool system.
Contrary to the last sentence in LRA Section 4.3.2, the ANO-2 regenerative heat exchanger requires evaluation for the effects of thermal fatigue for the period of extended operation. A fatigue evaluation showing the acceptability of the regenerative heat exchanger for the period of extended operation will be completed prior to entering the period of extended operation, or the heat exchanger will be replaced.
Also, per NRC request, enclosed is report A2-ME-2003-001, Aging Management Review of Nonsafety-Related Systems and Components Affecting Safety-Related Systems.
New commitments contained in this submittal are summarized in the attachment. Should you have any questions concerning this submittal, please contact Ms. Natalie Mosher at (479) 858-4635.
I declare under penalty of perjury that the foregoing is true and correct. Executed on March 24, 2004.
othy. Mitchell Director, Nuclear Safety Assurance TGM/nbm Attachment/Enclosure
2CAN030401 Page 4 cc:
Dr. Bruce S. Mallett Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Tom Alexion Mail Stop 0-7 D1 Washington, DC 20555-0001 U. S. Nuclear Regulatory Commission Attn: Mr. Greg Suber Mail Stop 0-11 F1 Washington, DC 20555-0001 Mr. Bernard R. Bevill Director, Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867
Attachment to 2CAN030401 List of Regulatory Commitments
Attachment to 2CAN030401 Page 1 of 2 List of Regulatory Commitments The following table identifies those actions committed to by Entergy in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.
ChPEcOe SCHEDULED ONE.
ckOne)
COMPLETION TIME CONTINUING DATE COMMITMENT ACTION COMPLIANCE (if Required)
The aging effects for carbon steel and X
July 17, 2018 cast iron are the same in all environments with the exception that gray cast iron is susceptible to the aging mechanism of selective leaching.
Where selective leaching is possible, an additional program is credited unless the one specified program will manage selective leaching such as the Diesel Fuel Monitoring and Oil Analysis Programs. Selective leaching does not normally occur in air, lube oil, or fuel oil due to the lack of an aqueous environment. In the LRA, if cast iron components are gray cast iron and are exposed to an environment conducive to selective leaching, then they are managed by a program (PSPM Program, SWIP, or Fire Protection Program) that includes the management of loss of material due to selective leaching.
Cracking-fatigue is identified as an X
July 17, 2018 aging effect for the chemical and volume control system pump casing (page 3.3-84) in Table 3.3.2-5 with the PSPM Program as an aging management program. Cracking-fatigue should be included as an aging effect for the chemical and volume control system charging pumps in the "Detection of Aging Effects' of Section B.1.18 of Appendix B.
Attachment to 2CAN030401 Page 2 of 2 Contrary to the last sentence in LRA Section 4.3.2, the ANO-2 regenerative heat exchanger requires evaluation for the effects of thermal fatigue for the period of extended operation. A fatigue evaluation showing the acceptability of the regenerative heat exchanger for the period of extended operation will be completed prior to entering the period of extended operation, or the heat exchanger will be replaced.
X July 17, 2018