Letter Sequence RAI |
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Initiation
- Request, Request, Request, Request, Request
- Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: ML15327A213, ML16133A459, ML16133A499, ML16312A270, ML17207A165, ML17250A244, ML17256A286, ML18212A032, ML18212A181, ML18212A185, ML18212A188, ML18212A190, ML18212A194, ML18212A195, ML18213A104, ML18213A114, NL-16-138, Amendment 18 to License Renewal Application, NL-17-005, Actions Concerning License Renewal Commitments 41 and 42 in Response to LR-ISG-2016-01, Changes to Aging Management Guidance for Various Steam Generator Components, NL-17-019, Amendment to License Renewal Application - Reflecting Shortened License Renewal Terms, NL-17-020, License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan, NL-17-157, Amendment 19 to License Renewal Application (LRA)
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MONTHYEARML15344A4362015-12-10010 December 2015 Lr Hearing - (External_Sender) Draft Audit Plan Edits Project stage: Request ML15327A2132015-12-21021 December 2015 Plan for the Regulatory Audit of the Service Water Integrity and Fire Water System Aging Management Programs Pertaining to the Indian Point Nuclear Generating Unit Nos. 2 and 3 LRA Project stage: Other ML15351A2032015-12-30030 December 2015 Summary of Conference Call Held on December 9, 2015, Between the NRC and Entergy Nuclear Operations, Inc. Concerning the Draft Audit Plan for the Service Water Integrity and Fire Water System Aging Management Programs Project stage: Draft Other 05000247/LER-2016-004, Re Unanalyzed Condition Due to Degraded Reactor Baffle-Former Bolts2016-05-31031 May 2016 Re Unanalyzed Condition Due to Degraded Reactor Baffle-Former Bolts Project stage: Request ML16133A4592016-06-15015 June 2016 Service Water and Fire Water Systems Aging Management Programs Audit Report for the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application Project stage: Other ML16133A4992016-06-21021 June 2016 Summary of Telephone Conference Call Held Between NRC and Entergy Concerning the Indian Point LRA Safety Review Project stage: Other ML16138A1942016-07-25025 July 2016 Request for Additional Information for the Review of License Renewal Application, Set 2016-01 Project stage: RAI ML16208A2772016-07-26026 July 2016 Lr Hearing - RAI Set 2016-01 Project stage: Request ML16312A2702016-11-0909 November 2016 Project Manager Change for the License Renewal of Indian Point Nuclear Generating Unit Nos. 2 and 3 Project stage: Other NL-16-122, Reply to Request for Additional Information for the Review of License Renewal Application, Set 2016-012016-12-0202 December 2016 Reply to Request for Additional Information for the Review of License Renewal Application, Set 2016-01 Project stage: Response to RAI NL-16-138, Amendment 18 to License Renewal Application2016-12-15015 December 2016 Amendment 18 to License Renewal Application Project stage: Other ML16350A4852016-12-15015 December 2016 Letter Enclosing Sipos Notice of Withdrawal Project stage: Request NL-17-005, Actions Concerning License Renewal Commitments 41 and 42 in Response to LR-ISG-2016-01, Changes to Aging Management Guidance for Various Steam Generator Components2017-01-17017 January 2017 Actions Concerning License Renewal Commitments 41 and 42 in Response to LR-ISG-2016-01, Changes to Aging Management Guidance for Various Steam Generator Components Project stage: Other NL-17-020, License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan2017-02-0606 February 2017 License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan Project stage: Other NL-17-019, Amendment to License Renewal Application - Reflecting Shortened License Renewal Terms2017-02-0808 February 2017 Amendment to License Renewal Application - Reflecting Shortened License Renewal Terms Project stage: Other ML17046A2312017-03-0808 March 2017 Request for Additional Information for the Review of the Indian Point License Renewal - Set 2017-01 Project stage: RAI ML17082A3112017-04-11011 April 2017 Summary of Clarification Call with Entergy Regarding Follow-Up RAIs on ISG-2012-02 Project stage: RAI ML17088A3272017-04-19019 April 2017 Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-02 Project stage: RAI ML17088A4052017-04-20020 April 2017 Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-3 Project stage: RAI ML17101A6972017-04-25025 April 2017 License Renewal Clarification Call on Baffle Bolt RAIs Project stage: Approval NL-17-052, Reply to Request for Additional Information for the Review of the License Renewal Application, Set 2017-012017-05-0808 May 2017 Reply to Request for Additional Information for the Review of the License Renewal Application, Set 2017-01 Project stage: Response to RAI NL-17-053, Reply to Request for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-032017-05-18018 May 2017 Reply to Request for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-03 Project stage: Response to RAI NL-17-060, Reply to Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-022017-05-19019 May 2017 Reply to Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-02 Project stage: Response to RAI ML17128A3352017-05-23023 May 2017 Summary of Telephone Conference Call Between the NRC and Entergy Concerning RAIs Pertaining to IP2 and IP3 Project stage: RAI NL-17-061, Reply to Requests for Additional Information for the Review of the License Renewal Application RAI Set 2017-042017-05-24024 May 2017 Reply to Requests for Additional Information for the Review of the License Renewal Application RAI Set 2017-04 Project stage: Response to RAI NL-17-069, Reply to Requests for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application RAI Set 2017-052017-06-0808 June 2017 Reply to Requests for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application RAI Set 2017-05 Project stage: Response to RAI ML17170A2862017-06-27027 June 2017 RAI Set 2017-06 Project stage: RAI NL-17-074, Supplemental Information Regarding Reply to Request for Additional Information Set 2017-01 for the Review of the License Renewal Application (LRA)2017-06-27027 June 2017 Supplemental Information Regarding Reply to Request for Additional Information Set 2017-01 for the Review of the License Renewal Application (LRA) Project stage: Supplement ML17160A1652017-06-27027 June 2017 Summary of Telephone Conference Call Held on May 31,2017, Between the NRC and Entergy Nuclear Operations Inc. Concerning Requests for Additional Information Pertaining to the Indian Point, License Renewal Application (TAC Nos. MD5407/MD5408 Project stage: RAI NL-17-084, Reply to Requests for Additional Information for the Review of the License Renewal Application. Re RAI Set 2017-062017-07-27027 July 2017 Reply to Requests for Additional Information for the Review of the License Renewal Application. Re RAI Set 2017-06 Project stage: Response to RAI NL-17-092, Amended Response to Request for Additional Information Question RAI 3.3.2-17-IP3-1 Re License Renewal Application RAI Set 2017-052017-07-27027 July 2017 Amended Response to Request for Additional Information Question RAI 3.3.2-17-IP3-1 Re License Renewal Application RAI Set 2017-05 Project stage: Response to RAI ML17207A1652017-09-0101 September 2017 License Renewal Audit Plan Regarding the Service Water Integrity Program Project stage: Other ML17191A4562017-09-20020 September 2017 Telecon Summary Related to Indian Point License Renewal RAIs Associated with ISG-2016-01 Project stage: RAI ML17250A2442017-09-20020 September 2017 Audit Report for IP Swi - Aug 2017 Project stage: Other ML17180A5032017-09-21021 September 2017 Summary of Teleconference with Entergy Nuclear Operations, Inc., Concerning Request for Additional Information Pertaining to the Indian Point Unit Nos. 2 and 3 License Renewal Application Project stage: RAI ML17256A2862017-09-25025 September 2017 Summary of Telephone Call on 09/06/17, Between NRC and Entergy Concerning Next Steps from the Site Audit on 08/1-3/17 Project stage: Other NL-17-127, Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application (LRA)2017-11-0808 November 2017 Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application (LRA) Project stage: Supplement ML17298A5442017-11-13013 November 2017 Summary of Meeting with the National Marine Fisheries Service Related to Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Project stage: Meeting NL-17-155, Re-Submittal of Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application (LRA)2017-12-14014 December 2017 Re-Submittal of Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application (LRA) Project stage: Supplement NL-17-157, Amendment 19 to License Renewal Application (LRA)2017-12-14014 December 2017 Amendment 19 to License Renewal Application (LRA) Project stage: Other NL-17-161, Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Units 2 and 3 License Renewal Application (LRA)2017-12-21021 December 2017 Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Units 2 and 3 License Renewal Application (LRA) Project stage: Supplement NL-18-010, Supplemental Information Regarding the Review of the License Renewal Application2018-02-26026 February 2018 Supplemental Information Regarding the Review of the License Renewal Application Project stage: Supplement ML18107A7592018-04-30030 April 2018 NUREG-1437, Suppl. 38, Vol. 5, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 38 Regarding Indian Port Nuclear Generating Unit Nos. 2 and 3 Final. Project stage: Acceptance Review NL-18-030, Supplemental Information Associated with Amendment 19 to the License Renewal Application (LRA)2018-05-0808 May 2018 Supplemental Information Associated with Amendment 19 to the License Renewal Application (LRA) Project stage: Supplement NL-18-044, Supplemental Information Regarding the Review of the License Renewal Application2018-06-25025 June 2018 Supplemental Information Regarding the Review of the License Renewal Application Project stage: Supplement ML18200A3332018-08-0101 August 2018 NUREG-1930, Supp 3, Safety Evaluation Report Related to the License Renewal of Indian Point Nuclear Generating Plant, Units 2 and 3. Project stage: Approval ML18211A5842018-09-17017 September 2018 Issuance of Renewed Facility Operating License Nos. DPR 26 and DPR-64 for Indian Point Nuclear Generating Unit Nos. 2 and 3 (CAC Nos. MD5407 and MD5408) Project stage: Request ML18212A0322018-09-17017 September 2018 Records of Decision for the Indian Point Renewed Licenses Project stage: Other ML18211A5962018-09-17017 September 2018 Transmittal Letter - Issuance of Renewed Facility Operating License Nos. DPR-26 and DPR-64 for Indian Point Nuclear Generating Unit Nos. 2 and 3 Project stage: Approval ML18211A5782018-09-17017 September 2018 Federal Register Notice - Announcing the Issuance of the Indian Point Renewed Licenses Project stage: Approval 2017-04-19
[Table View] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 27, 2017 Mr. Anthony Vitale Site Vice-President, IPEC Entergy Nuclear Operations, Inc.
450 Broadway, GSB PO Box 249 Buchanan, NY 10511-0249
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT LICENSE RENEWAL APPLICATION RAI SET 2017-06 (CAC NOS. MD5407 AND MD5408)
Dear Mr. Vitale:
By "05000247/LER-2007-004, Regarding Manual Reactor Trip Due to Decreasing Steam Generator Levels Caused by Loss of Feedwater Flow as a Result of [[system" contains a listed "[" character as part of the property label and has therefore been classified as invalid. Pump Suction Pressure Transmitter Power Supply Failure|letter dated April 30, 2007]], Entergy Nuclear Operations, Inc. submitted an application pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 54, to renew the operating license Nos. DPR-26 and DPR-64 for Indian Point Nuclear Generating, Unit Nos. 2 and 3, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review to ensure compliance with 10 CFR Part 54.
These requests for additional information were discussed with Richard Louie, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-6332 by e-mail at william.burton@nrc.gov.
Sincerely,
/RA/
William Burton, Senior Project Manager License Renewal Project Branch Division of Materials and License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286
Enclosure:
Requests for Additional Information cc w/encl: Listserv
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT LICENSE RENEWAL APPLICATION RAI SET 2017-06 (CAC NOS. MD5407 AND MD5408 DISTRIBUTION:
HARD COPY:
E-MAIL:
PUBLIC RidsNrrDlr Resource RidsNrrDlrRarb Resource RidsNrrDlrMccb Resource RidsNrrDlrRerp Resource RidsNrrDlrMrpb Resource RidsOgcMailCenter Resource RidsNrrPMIndianPoint Resource SStuchell BBeasley WBurton WHolston BAllik RGuzman STurk, OGC DRoth, OGC BHarris, OGC SBurnell, OPA DMcIntyre, OPA JWeil, OPA MGray, RI GDentel, RI DJackson, RI MModes, RI NSheehan, RI OPA DScrenci, RI OPA DTifft, RI NMcnamara, RI BHaagensen, RI GNewman, RI SRich, RI rlouie@entergy.com rburron@entergy.com avitale@entergy.com rwalpol@entergy.com ADAMS ACCESSION NO. ML17170A286 OFFICE LA:DLR*
PM:MRPB:DLR BC:MRPB:DLR PM:MRPB:DLR NAME YEdmonds WBurton SStruchell WBurton DATE 6/26/2017 6/26/2017 6/27/2017 6/27/2017 OFFICIAL RECORD
Enclosure INDIAN POINT LICENSE RENEWAL APPLICATION (LRA)
REQUESTS FOR ADDITIONAL INFORMATION (RAI)
RAI 3.0.3.1.2-1
Background:
GALL Report AMP XI.M41, Buried and Underground Piping and Tanks, as modified by LR-ISG-2015-01, Changes to Buried and Underground Piping and Tank Recommendations, includes the following recommendations:
- 1. The preventive actions program element recommends that coatings are provided for buried stainless steel or the applicant provides justification when coatings are not provided.
- 2. Table XI.M41-2, Inspection of Buried and Underground Piping and Tanks, recommends one inspection of buried stainless steel piping during each 10-year period, commencing 10 years prior to the period of extended operation.
Issue:
The number of recommended inspections for buried stainless steel in GALL Report AMP XI.M41, as modified by LR-ISG-2015-01, is based on coatings being provided or adequate justification when coatings are not provided. It is unclear to the staff if buried stainless steel piping is coated, and if it is not coated, the justification for why coatings do not need to be provided.
Request:
State if buried stainless steel piping is coated. If buried stainless steel piping is not coated, provide justification (e.g., increased extent or frequency of inspections, soil parameters) for why coatings do not need to be provided.
RAI 3.0.3.1.2-2
Background:
of letter dated April 28, 2017, states that polyvinyl chloride (PVC) piping exposed to soil has no aging effects due to the lack of stressors in a soil environment and non-aggressive soil as confirmed by soil samples.
GALL Report AMP XI.M41, as modified by LR-ISG-2015-01, includes the following recommendations:
- 1. The parameters monitored or inspected program element recommends visual inspections of the external surface condition of polymeric materials to detect loss of material due to wear.
- 2. Table XI.M41-2, Inspection of Buried and Underground Piping and Tanks, recommends one inspection of buried polymeric piping when backfill is in accordance with the preventive actions program element, and the smaller of one percent of the length of the pipe or two inspections when backfill is not in accordance with the preventive actions program element.
Issue:
As noted above, GALL Report AMP XI.M41, as modified by LR-ISG-2015-01, recommends reducing the number of inspections for polymeric piping based on backfill quality, but does not recommend eliminating inspections based on soil aggressiveness. It is unclear to the staff how lack of stressors in a soil environment and non-aggressive soil as confirmed by soil samples precludes the need to perform visual inspections to detect loss of material due to wear.
Request:
State the basis for why loss of material due to wear is not an aging effect requiring management for PVC piping exposed to soil. Alternatively, revise the program to address loss of material due to wear for buried PVC piping.
RAI 3.0.3.1.2-3
Background:
of letter dated April 28, 2017, states [c]athodic protection levels are maintained as described in NL-13-132 [response to RAI 3.0.3.1.2-4a dated October 3, 2013] and soil conditions are not aggressive such that cracking is not an aging effect requiring management. In addition, the stainless steel piping in the program operates at temperatures below 140°F, which is the threshold for stress corrosion cracking in stainless steel.
GALL Report AMP XI.M41, as modified by LR-ISG-2015-01, provides the following recommendations:
- 1. Stainless steel components can experience stress corrosion cracking when exposed to soil due to the potential presence of halides.
- 2. Steel components can experience stress corrosion cracking when exposed to a carbonate/bicarbonate environment depending on cathodic polarization level, temperature, and pH. See NACE SP0169-2013, Control of External Corrosion on Underground or Submerged Metallic Piping Systems, Figure 2, SCC [stress corrosion cracking] Range of Pipe Steel in Carbonate/Bicarbonate Environments.
Issue:
- 1. The threshold temperature for stress corrosion cracking of stainless steel in a treated water environment (i.e. water whose chemistry has been altered and is maintained) is 140°F; however, due to the potential presence of halides, stress corrosion cracking is an applicable aging effect for stainless steel piping exposed to soil.
- 2. The subject letter does not address cracking of steel exposed to soil, which can occur in a carbonate/bicarbonate environment depending on cathodic polarization level, temperature, and pH. It is unclear to the staff if steel piping is exposed to a carbonate/bicarbonate environment, and if it is, how factors such as cathodic polarization level, temperature, and pH preclude the need to manage steel piping for cracking.
Request:
- 1. For buried stainless steel components, state the specific soil parameters (e.g., bacteria, presence of halogens) and results that demonstrate that cracking will not occur.
Alternatively, revise the program to address cracking of buried stainless steel piping.
- 2. State the basis for why cracking is not an aging effect requiring management for steel piping exposed to soil. Alternatively, revise the program to address cracking of buried steel piping.
RAI 3.0.3.1.2-4
Background:
As amended by letter dated April 28, 2017, LRA Section B.1.6, Buried Piping and Tanks Inspection, states [i]f future inspections reveal significant coating damage caused by non-conforming backfill, then Entergy will double the inspection sample size up to an increase of five (5) inspections.
GALL Report AMP XI.M41, as modified by LR-ISG-2015-01, states that where the coatings, backfill or the condition of exposed piping does not meet acceptance criteria such that the depth or extent of degradation of the base metal could have resulted in a loss of pressure boundary function when the loss of material rate is extrapolated to the end of the period of extended operation, an increase in the sample size is conducted.
Issue:
The staff noted that degradation of the base metal could occur for reasons besides significant coating damage caused by non-conforming backfill (e.g., coating degradation based on coating service life). Significant coating damage caused by non-conforming backfill is only an example of how degradation of the base metal could occur. In addition, in contrast to AMP XI.M41, which defines the degree of degradation (i.e., loss of pressure boundary function), significant coating damage is not defined.
Request:
State the basis for why an increase in inspection sample size will only occur when significant coating damage caused by non-conforming backfill is revealed. Alternatively, revise the program to be consistent with LR-ISG-2015-01 regarding criteria for increasing inspection sample size.
RAI 3.0.3.1.2-5
Background:
As amended by letter dated April 28, 2017, LRA Sections A.2.1.5 and A.3.1.5 (Buried Piping and Tanks Inspection program UFSAR summary descriptions for Units 2 and 3, respectively) were revised in response to the issuance of LR-ISG-2015-01.
The UFSAR summary description issued in LR-ISG-2015-01 includes the following recommendations:
This program manages the aging effects of cracking.
Inspections are conducted by qualified individuals.
Where the coatings, backfill or the condition of exposed piping does not meet acceptance criteria such that the depth or extent of degradation of the base metal could have resulted in a loss of pressure boundary function when the loss of material rate is extrapolated to the end of the period of extended operation, an increase in the sample size is conducted.
Issue:
The staff noted that aspects of the UFSAR summary description issued in LR-ISG-2015-01 (bulletized above) were not included in the revised LRA Sections A.2.1.5 and A.3.1.5. The licensing basis for this program for the period of extended operation may not be adequate if the applicant does not incorporate this information in its UFSAR supplement.
Request:
State the basis for not including aspects of the UFSAR Summary Description issued in LR-ISG-2015-01 (bulletized above) in the revised LRA Sections A.2.1.5 and A.3.1.5.
Alternatively, revise LRA Sections A.2.1.5 and A.3.1.5 to be consistent with LR-ISG-2015-01.