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EPID:L-2019-LLR-0102, Implementation of BWRVIP-38 and -76 in Lieu of B-N-2 Examinations for Core Support Structures (Open) |
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Category:Code Relief or Alternative
MONTHYEARML20143A2332020-06-0303 June 2020 Relief Request for Deferral of ASME Boiler and Pressure Vessel Code, Section XI, Required Summary Report Submittal (EPID L-2020-LLR-0074 (COVID-19)) ML20034E8942020-02-11011 February 2020 Relief Request Gen-ISI-ALT-2019-01 for Proposed Alternative to Use of ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 ML19361A0562020-01-0909 January 2020 Proposed Alternative HNP-ISI-ALT-05-10 for the Implementation of BWRVIP 38 and -76 in Lieu of B-N-2 Examinations for Core Support Structures NL-19-1336, Implementation of BWRVIP-38 and -76 in Lieu of B-N-2 Examinations for Core Support Structures2019-11-0404 November 2019 Implementation of BWRVIP-38 and -76 in Lieu of B-N-2 Examinations for Core Support Structures ML18320A0572018-11-30030 November 2018 Plant, Units 1 and 2 - Proposed Inservice Inspection Alternative GEN-ISI-ALT-2017-03, Code Case N-513-4 for Moderate Pressure NL-18-0713, Request for Alternative HNP-ISI-ALT-05-08 to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping for Hatch Unit 1 Plant Service Water2018-05-17017 May 2018 Request for Alternative HNP-ISI-ALT-05-08 to Implement Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping for Hatch Unit 1 Plant Service Water NL-18-0408, Proposed Alternative RR-V-12 Regarding Main Steam Safety Relief Valve Testing2018-04-0909 April 2018 Proposed Alternative RR-V-12 Regarding Main Steam Safety Relief Valve Testing NL-18-0428, Withdrawal of Proposed Alternative GEN-ISI-ALT-2017-001 Implementation of Code Case N-786-12018-04-0909 April 2018 Withdrawal of Proposed Alternative GEN-ISI-ALT-2017-001 Implementation of Code Case N-786-1 ML17279A0452017-10-26026 October 2017 Relief Requests ISI-RR-13, -14, -18, -19, -23, and -24 for Relief from Inservice Inspection Requirements ML17268A0442017-10-20020 October 2017 Relief Requests ISI RR 16, ISI-RR-17, ISI-44-21, and ISI-RR-22 for Relief from Inservice Inspection Requirements ML17205A3452017-08-10010 August 2017 Relief Request HNP-ISI-RR- 05-01 Regarding Reactor Pressure Vessel Head Stud Inservice Inspection Requirements ML17062A8322017-03-29029 March 2017 Relief Request ISI RR-15 Regarding Control Rod Drive Housing Welds Inservice Inspection Requirements ML16314A1322016-11-23023 November 2016 Request for Alternative HNP-ISI-ALT-05-03, Version 1.0, Regarding Reactor Pressure Vessel Flange Leak-Off Piping ML15310A4062015-12-30030 December 2015 Inservice Testing Program Relief Requests and Alternatives for Pumps and Valves - Fifth Ten-Year Interval ML15352A2942015-12-28028 December 2015 Relief from the Requirements of the ASME Code ML15349A9732015-12-18018 December 2015 Relief from the Requirements of the ASME Code NL-15-1221, Withdrawal of RR-V-2 and Response to Request for Additional Information on RR-V-12015-07-16016 July 2015 Withdrawal of RR-V-2 and Response to Request for Additional Information on RR-V-1 NL-15-1265, E.I Hatch, Units 1 and 2 - 10CFR 50.55a Request No. HNP-ISI-ALT-5-01, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Maintaining Isi/Cii Related Activities on the 2001 E/2003A ASME Section XI Code2015-07-16016 July 2015 E.I Hatch, Units 1 and 2 - 10CFR 50.55a Request No. HNP-ISI-ALT-5-01, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Maintaining Isi/Cii Related Activities on the 2001 E/2003A ASME Section XI Code NL-15-1096, Provides Follow-up Letter Regarding Submittal of the Inservice Testing Program Relief Requests and Alternatives for Pumps and Valves - Fifth Ten-Year Interval2015-06-18018 June 2015 Provides Follow-up Letter Regarding Submittal of the Inservice Testing Program Relief Requests and Alternatives for Pumps and Valves - Fifth Ten-Year Interval NL-11-0162, Submittal of Revision to Relief Request RR-V-4 Fourth 10-Year Interval Inservice Testing Program2011-01-26026 January 2011 Submittal of Revision to Relief Request RR-V-4 Fourth 10-Year Interval Inservice Testing Program ML1100504942011-01-14014 January 2011 Safety Evaluation of Relief Request HNP-ISI-ALT-10, Version 1, for the Fourth 10-Year Inservice Inspection Interval Temporary Non-Code Repair of Service Water Piping, TAC ME4253 ML1020304442010-07-22022 July 2010 E-mail from Robert Martin, Regarding Verbal Authorixation of Relief - Note to File ML1020304522010-07-21021 July 2010 Verbal Authorization for Relief Request HNP-ISI-ALT-10 Temporary Non-code Repair of Service Water Piping ML1009802142010-04-0808 April 2010 Safety Evaluation of Relief Request HNP-ISI-ALT-09, Version 2.0, for the Fourth 10-year Inservice Inspection Interval ML0731301882007-12-0606 December 2007 Safety Evaluation for Alternative ISI-ALT-08 ML0713602972007-06-0505 June 2007 Relief, Evaluation of Third 10-Year Interval Inservice Inspection Program Plan Request to Relief Nos. RR-42 Through RR-45, RR- 51, RR-58, RR-59, RR-60, & RR-62 ML0604502862006-02-14014 February 2006 Request for Relief from the Requirements of the American Society of Mechanical Engineered Boiler and Vessel Code (ASME Code) ML0534700912006-01-0303 January 2006 Relief, Boiler and Pressure Vessel Code, MC6528 and MC6529 ML0533303392005-12-22022 December 2005 Request for Relief from the Requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) ML0529700082005-11-0909 November 2005 Relief, Proposed Alternative RR-41 for Third and Fourth 10-Year Inservice Inspection Interval NL-05-1372, Third and Fourth 10-Year Interval Inservice Inspection Programs, Submittal of Revised Exemption Request2005-08-0202 August 2005 Third and Fourth 10-Year Interval Inservice Inspection Programs, Submittal of Revised Exemption Request ML0510301992005-04-25025 April 2005 RR, ISI Program Intervals for Alternative Alignment of Iwe/Iwl Inspection Program (Tac No. MC4870, MC4871, MC4872, MC4873, MC4874, MC4875) NL-05-0726, Fourth 10-Year Interval IST Program Update2005-04-20020 April 2005 Fourth 10-Year Interval IST Program Update ML0501303172005-01-28028 January 2005 Ltr, RR No. 38 NL-04-1764, Third 10-Year Interval Inservice Inspection Program Submittal of Revised Relief Request RR-382004-09-13013 September 2004 Third 10-Year Interval Inservice Inspection Program Submittal of Revised Relief Request RR-38 ML0332800372003-11-21021 November 2003 Safety Evaluation Re. Request to Use ASME Code Case N-661 NL-03-1744, Third 10-Year Interval Inservice Testing Program Submittal of Revised Relief Request RR-V-18 and Response to Request for Additional Information (RAI)2003-09-12012 September 2003 Third 10-Year Interval Inservice Testing Program Submittal of Revised Relief Request RR-V-18 and Response to Request for Additional Information (RAI) ML0304100732003-02-10010 February 2003 Relief Request, Third 10-year Inservice Inspection Program ML0301404462003-01-14014 January 2003 Relief Request, Third 10-Year Inservice Inspection Program ML0230903232002-10-30030 October 2002 Third 10-Year Interval Inservice Testing Program, Revision to Existing Relief Request RR-V-11 ML0218305772002-07-0202 July 2002 Relief Requests for the Second 10-Year Inservice Inspection (ISI) Interval 2020-06-03
[Table view] Category:Letter type:NL
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~ Southern Nuclear Cheryl A. Gayheart Regulatory Affairs Director 3535 Colonnnde Parkway flirmingham . r\L 35143 205 991 .-316 NOV 0 4 2019 cagnyhea @sou thc:rnco.c(llll Docket Nos.: 50-321 NL-19-1336 50-366 U.S. Nuclear Regulatory Commission ATTN : Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant Units 1 and 2 Implementation of BWRVIP-38 and -76 in lieu of B-N-2 Examinations for Core Support Structures Ladies and Gentlemen:
Pursuant to 10 CFR 50.55a(z)(1 ), Southern Nuclear Operating Company (SNC) requests Nuclear Regulatory Commission (NRC) authorization of proposed Alternative HNP-ISI-ALT 10. This Alternative corrects specific inconsistencies between the required examinations per HNP-ISI-ALT-05-04, and those examinations required per the applicable Boiling Water Reactor Vessel and Internals Project (BWRVIP) guidelines.
By letter dated January 22, 2019, the NRC authorized the use of proposed Alternative HNP-ISI-AL T-05-04 for Edwin I. Hatch Nuclear Plant (HNP), Units 1 and 2. This authorization allowed use of BWRVIP guidelines as an alternative to certain requirements of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV Code) for the inservice inspection (lSI) of reactor pressure vessel interior surfaces, attachments, and core support structures.
Subsequent to the NRC authorization of HNP-ISI-ALT-05-04, SNC identified that certain examinations pursuant to the HNP Units 1 and 2 shroud and shroud repair were not clearly identified, and that the relationship between the ASME Code, BWRVIP, and previous HNP submittals regarding the shroud repair modification were not sufficiently delineated. This Alternative will provide the necessary clarity of HNP Unit 1 and Unit 2 specific design characteristics of the shroud support structure, and its relationship with the applicable BWRVIP guidance and previous HNP correspondence.
This letter contains no NRC commitments. If you have any questions, please contact Jamie Coleman at 205.992.6611.
Respectfully submitted, CAG/RMJ
U. S. Nuclear Regulatory Commission NL-19-1336 Page 2
Enclosure:
Alternative HNP-ISI-ALT-05-10 Cc: Regional Administrator, Region II NRR Project Manager- Hatch Senior Resident Inspector- Hatch RTYPE: CHA02.004
Edwin I. Hatch Nuclear Plant Units 1 and 2 Implementation of BWRVIP-38 and -76 in lieu of B-N-2 Examinations for Core Support Structures Enclosure Alternative HNP-ISI-ALT-05-10
Enclosure to N L-19-1336 Alternative HNP-ISI-ALT-05-1 0
- 1. ASME Code Component(s) Affected Code Class: ASME Section XI Code Class 1 Component Numbers: None Code
References:
ASME Section XI, 2007 Edition with 2008 Addenda Examination Category: B-N-2 Item Number(s): B13.30, and B13.40
- 2. Requested Approval Date Approval is requested by January 1, 2021
- 3. Applicable ASME Code Requirements Per the NRC Approval of HNP-ISI-ALT-05-04 (Reference H.), the following BWRVIP requirements apply to the items listed below for Hatch Nuclear Plant (HNP) Units 1 and 2:
ASME Item Applicable BWRVIP BWRVIP BWRVIP No. Table Component BWRVIP Exam Scope Exam Type Frequency IWB-2500-1 Document B13.30 Shroud BWRVIP-38, Weld H9 EVT-1 or UT Maximum of 6 Support 3.1 .3.2, including years for EVT -1, (Weld H9) Figures 3-2 gussets Maximum of 10 including and 3-5 years for UT gussets Note: Hatch Unit 2 configuration does not have gussets.
B13.40 Integrally BWRVIP-38, Shroud EVT-1 or UT Based on as-found Welded 3.1.3.2, support conditions, to a Core Figures 3-2 welds H8 maximum 6 years Support and 3-5 and H9 for EVT-1, 10 years Structure including for UT where gussets accessible
4. Reason for Request
In accordance with 10 CFR 50.55a(z)(1 ), HNP Units 1 and 2 previously submitted a request for NRC approval of alternative HNP-ISI-ALT-05-04 (ML18172A281) to use of the Boiling Water Reactor Vessel Internals Project (BWRVIP) guidelines in lieu of ASME Code Section XI B-N requirements. The NRC authorized this alternative January 22, 2019 (ML19011A010). Upon review of particular details in that alternative, SNC identified that E-1
Enclosure to NL-19-1336 Alternative HNP-ISI-ALT-05-1 0 certain examinations pursuant to the HNP Units 1 and 2 shroud and shroud repair were not clearly identified, and that the relationship between the ASME Code, BWRVIP, and previous HNP submittals regarding the shroud repair modification were not sufficiently delineated.
This alternative is therefore being submitted to provide the necessary clarity of HNP-specific design characteristics of the shroud support structure and its relationship with BWRVIP guidance and previous HNP correspondence. This will allow staff review of these specific details to ensure future misinterpretation is avoided.
The BWRVIP Inspection and Evaluation (I&E) Guidelines recommend specific inspection by BWR owners to identify material degradation with BWR components. The BWRVIP I&E Guidelines focus on specific and susceptible components, specify appropriate inspection methods capable of identifying known or potential degradation mechanisms, and require re-examination at appropriate intervals. The scope of the I&E Guidelines exceeds that of ASME Section XI and, in most instances, include components that are not part of the ASME Section XI jurisdiction.
Use of this proposed alternative will maintain an adequate level of quality and safety and avoid duplicate or unnecessary inspections, while conserving radiological dose.
- 5. Proposed Alternative and Basis for Use Proposed Alternative SNC requests to modify the examination requirements for HNP Unit 1 and Unit 2 welds H8 and H9 as approved in Reference H. The modified examination requirements are shown in Table 1.
Basis for Use B13.30 - Interior Attachments Beyond the Beltline Region BWRVIP-38 governs the industry requirements for H9. BWRVIP-38 clearly states in Section 2.1.2 that the Unit 2 H9 weld is not addressed since it is a low alloy steel weld that is not susceptible to IGSCC and concludes that the ASME Code Section IWB-2500 B-N-2 core support structure examinations (813.40) are sufficient for degradation monitoring.
B13.40 - Core Support Structure The previously approved alternative, ISI-ALT-05-04, did not include the H8 weld as structurally replaced by the shroud tie rod repair. References C. and E. and NRC authorizations D. and F. establish that the shroud repair also includes the H8 weld for HNP Units 1 and 2.
E-2
Enclosure to NL-19-1336 Alternative HNP-ISI-ALT 10 For HNP Unit 2, no augmented examinations are required per BWRVIP-38 for the H9 weld as it is not susceptible to IGSCC. In SNC's response to the staff's request for information regarding the absence of any reference to gusset inspections in the HNP-2 shroud stabilizer modification submittal by stating in reference G.:
"Plant Hatch Unit 2 was constructed with a 8.8" thick shroud support plate fabricated from low alloy steel and clad with Type 304 stainless steel on the bottom (lower plenum side) and alloy 82/182 on the top (annulus side). This thick plate design is unique to Plant Hatch Unit 2 and structurally takes the place of the thinner support plate/gussets or thinner support plate/support leg configurations found in other BWRs. For this reason no gusset plate examinations are specified. The Unit 2 shroud support is exempted from the inspection criteria of BWRVIP-38. Section 2.1.2 of BWRVIP-38 clearly states this and that Code examinations are adequate since the shroud support is low alloy steel and thus not susceptible to IGSCC. A collet/clevis pin assembly was installed in 1995 to provide a lower attachment for each tie rod assembly. These assemblies have no welded components."
Therefore, for Hatch Unit 2, the ASME Code Section XI B-N-2 item B 13.40 visual (VT -3) examination will continue to be performed for the accessible shroud support plate surfaces from the H8 weld up to and including the H9 weld.
- 6. Duration of Proposed Alternative This proposed alternative will be used for the Fifth Ten -Year Interval of the lnservice Inspection Program for HNP Units 1 and 2.
- 7. Precedents Precedents from HNP-ISI-ALT-05-04 are still applicable.
- 8. References A. US NRC Letter to BWRVIP, dated July 24, 2000, "Final Safety Evaluation of the "BWR Vessel and Internals Project, BWR Shroud Support Inspection and Flaw Evaluation Guidelines (BWRVIP-38), "EPRI Report TR-108823 (TAC NO. M99638).
B. BWRVIP-76NP, Revision 1: "BWR Vessel and Internals Project BWR Core Shroud Inspection and Flaw Evaluation Guidelines," May 2011 (ML11195A182).
C. SNC Letter NL-07-1155; Edwin I. Hatch Unit 1 Proposed Modification of the Unit 1 Core Shroud Stabilizer Assemblies, dated August 14, 2007 (ML072280298)
D. US NRC letter to Mr. Dennis R. Madison: "Edwin I. Hatch Nuclear Plant, Unit No. 1 (Hatch-1), Safety Evaluation for Reactor Core Shroud Relief Request, dated March 26, 2008 (ML080570109)
E. SNC Letter NL-08-1301; Edwin I. Hatch- Unit 2 Request for Authorization Under Provision of 10 CFR 50.55a(a)(3)(i) for Modification of the Unit 2 Core Shroud Stabilizer Assemblies, dated September 3, 2008 E-3
Enclosure to NL-19-1336 Alternative HNP-ISI-ALT-05-10 F. US NRC letter to Mr. Dennis R. Madison: "Edwin I. Hatch Nuclear Plant ,Unit No. 2 (Hatch-2), Safety Evaluation and Request for Additional Information for Reactor Core Shroud Relief Request, dated February 13, 2009 (ML090330216)
G. SNC letter NL-08-1897, Edwin I. Hatch- Unit 2 Response to NRC Request for Additional Information Regarding Modification of the Core Shroud Stabilizer Assemblies, dated December 19, 2008 (TAG No. MD9579)
H. US NRC letter to Ms. Cheryl A. Gayheart: "Edwin I. Hatch Nuclear Plant, Unit Nos 1 and 2- Proposed Alternative HNP-ISI-ALT-05-04 for the Implementation of BWRVIP Guidelines (EPID L-2018-LLR-0099)", dated January 22, 2019 (ML19011A010)
E-4
Enclosure to NL-19-1336 Alternative HNP-ISI-ALT 1 0 Table 1 HNP Units 1 and 2 ASME Item Applicable BWRVIP BWRVIP No. Table Component BWRVIP BWRVIP Frequency Exam Scope Exam Type IWB-2500-1 Document 813.30 Interior BWRVIP-38, Weld H-9 EVT-1 or UT Maximum of 6 years for EVT -1, Maximum of Attachments 3.1.3.2, 10 years for UT beyond Beltline - Figures 2-5, 3-Shroud Support 2 and 3-5 (HNP-1) 813.30 Interior BWRVIP-38, Weld H-9 None Per BWRVI P-38, H9 is not susceptible to Attachments 2.1.2 IGSCC, continuation of 813.40 visual (VT-3) beyond Beltline - Figures 2-2 each ten-year interval is sufficient for Shroud Support degradation monitoring (HNP-2) 813.40 Integrally BWRVIP-38, Shroud EVT-1 or UT Based on as-found conditions, to a maximum Welded Core 3.1.3.2, support weld of H9 and 6 years for EVT-1 , 10 years for UT where Support Figures 2-5, H8 and H9 gussets accessible Structures 3-2, 3-5 and gussets (HNP-1) BWRVIP-76 Shroud None for H8 Shroud hardware examination scope and R1-A, 3.5 hardware EVT -1 of four frequency is in accordance with references C (repair and gussets and D; performed in lieu of shroud horizontal components), anchorages serving as welds H1-H8.
3.6 anchorages.
(anchorages)
E-5
Enclosure to NL-19-1336 Alternative HNP-ISI-ALT-05-10 Table 1 HNP Units 1 and 2 ASME Item Applicable BWRVIP BWRVIP No. Table Component BWRVIP BWRVIP Frequency Exam Scope Exam Type IWB-2500-1 Document 813.40 Integrally BWRVIP-38, Shroud VT-3 of Each 10-year interval Welded Core 2.1.2, Figure 2- support from accessible Support 2 weld H8 up surfaces Structures to and (HNP-2) including H9 BWRVIP-76 Shroud None Shroud hardware examination scope and R1-A, hardware frequency is in accordance with references E Section 3.5 and F; performed in lieu of shroud horizontal (repair welds H1-H8. HNP-2 has no "highly stressed" components), anchorages.
Section 3.6 (anchorages)
E-6