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| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 January 9, 2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO.2 -REQUEST FOR ADDITIONAL INFORMATION (RAJ), HNP-ISI-RR-12, RESIDUAL HEAT REMOVAL SERVICE WATER PIPING (TAC NO. ME7726) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 January 9, 2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. |
| | 40 Inverness Center Parkway Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295 |
| | |
| | ==SUBJECT:== |
| | EDWIN I. HATCH NUCLEAR PLANT, UNIT NO.2 - REQUEST FOR ADDITIONAL INFORMATION (RAJ), HNP-ISI-RR-12, RESIDUAL HEAT REMOVAL SERVICE WATER PIPING (TAC NO. ME7726) |
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| ==Dear Mr. Ajluni:== | | ==Dear Mr. Ajluni:== |
| By letter dated December 22, 2011 (Agencywide Documents Access and Management System Accession No. ML113570234), Southern Nuclear Operating Company, Inc., submitted relief request for the HNP-ISI-RR-12, Version 1 for Edwin I. Hatch Nuclear Plant Unit No.2. The proposed relief request will be applicable to wall thinning in the Residual Heat Removal Service Water piping using American Society of Mechanical Engineers (ASME) Code Case N-597 -2. Responses to the enclosed RAI are needed for us to continue our review. Please provide a response within thirty (30) calendar days of the date of this letter. Sincerely, Patrick G. Boyle, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-366 | | |
| | By letter dated December 22, 2011 (Agencywide Documents Access and Management System Accession No. ML113570234), Southern Nuclear Operating Company, Inc., submitted relief request for the HNP-ISI-RR-12, Version 1 for Edwin I. Hatch Nuclear Plant Unit No.2. The proposed relief request will be applicable to wall thinning in the Residual Heat Removal Service Water piping using American Society of Mechanical Engineers (ASME) Code Case N-597 -2. |
| | Responses to the enclosed RAI are needed for us to continue our review. Please provide a response within thirty (30) calendar days of the date of this letter. |
| | Sincerely, Patrick G. Boyle, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-366 |
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| ==Enclosure:== | | ==Enclosure:== |
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| RAI cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST (RR) HNP-ISI-RR-12. | | RAI cc w/encl: Distribution via Listserv |
| VERSION 1 RESIDUAL HEAT REMOVAL SERVICE WATER PIPING EDWIN I. HATCH NUCLEAR PLANT. UNIT NO.2 DOCKET NO. 50-366 TAC NO. ME7726 By letter dated December 22, 2011 (Agencywide Documents Access And Management System (ADAMS) Accession Number ML113570234), Southern Nuclear Operating Company, Inc. (SNC, the licensee) requested Nuclear Regulatory Commission (NRC) review and approval of RR HNP-ISI-RR-12, Version 1, for Edwin I. Hatch Nuclear Plant Unit 2. The proposed relief request will be applicable to wall thinning in the Residual Heat Removal Service Water (RHRSW) piping using American Society of Mechanical Engineers (ASME) Code Case 2. To complete its review, the NRC staff requests the following additional information:
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| : 1. Clarify from which subarticles in the ASME Code Section XI the relief is requested.
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| Discuss whether the RR will deviate from Code Case N-597 -2, excluding the deviations from the five NRC Conditions imposed in Regulatory Guide 1.147, Revision 16, which are discussed in the proposed RR. If yes, list the deviation(s) and provide justification.
| |
| : 2. As shown on page E1-3 of the RR, in response to NRC Condition 1, the licensee stated that u *** [t]he EPRI Report 202L-R2 is not applicable in this case because RHRSW has oxygen content significantly higher than F AC [flow-accelerated corrosion]
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| components.
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| Similar to the FAC program at the SNC plants, SNC has implemented a Fleet Service Water Program which includes the development of inspection requirements, determining the rate of wall thickness loss plus the calculation of values for the predicted remaining life ... " (1) Discuss how the inspection requirements, the rate of wall thickness loss, the value of the predicted remaining wall thickness and the predicted remaining life for the pipe are determined in the SNC Fleet Service Water Program and discuss how these methods differ from the EPRI Report 202L-R2. (2) Page E1-5 of the relief request states that analytical evaluations will be performed based on each set of UT thickness measurements using ASME Code Case N-597 -2. However, the above quoted statement states that the Fleet Service Water Program provides analytical evaluations and will be used. Clarify whether the analytical evaluations to project (predict) wall thinning in the subject piping will be based on N-597-2 or the Fleet Service Water Program. If the analytical method in the Fleet Service Water Program will be used, discuss whether the analytical evaluation method in the Fleet Service Water Program is consistent with the analytical evaluation requirements of Code Case N-597-2. If not, justify why the analytical method in the Fleet Service Water Program is acceptable for use. 3. (1) Discuss whether the RHR Service Water piping in the proposed relief request is located above ground or buried. If some portion of the pipe is buried underground, discuss how the buried portion of the pipe will be inspected.
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| (2) Page E1-1 of the relief request states that the supply header can be cross-connected to heat exchanger 2E 11 B001 B. Discuss the exact piping boundary (from end to end) that is covered under the proposed relief request and provide Enclosure
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| -2 an isometric drawing showing the affected piping. (3) Confirm that the entire length of the pipe is accessible for ultrasonic examinations of pipe wall thickness.
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| If not, discuss how the pipe wall thickness can be determined for the inaccessible portion of the pipe. (4) Discuss the pressures and temperatures that the subject piping system will be exposed to for various design conditions.
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| : 4. On page E1-4 of the relief request, in response to NRC Condition 5, the licensee mentioned a generic calculated acceptable minimum wall thickness of 0.311 inches. The licensee also discussed a detailed evaluation per ASME Code Case N-597-2 that resulted in a calculated minimum wall of 0.183 inches. Submit both calculations and discuss the differences in wall thickness calculation that resulted in two significant different allowable wall thickness values. 5. Page E1-5 (top of the page) of the relief request states that"... [a] permanent Code-compliant repair will be performed during the next refueling outage currently scheduled to begin in February 2013 or during a system outage of sufficient length to effect repairs ... " Page E 1-5, Alternative Duration Section, states that " ... [t]his relief request will remain in effect until an ASME Section XI Code repair/replacement is performed prior to reaching the allowable minimum wall thickness based on the ongoing ultrasonic thickness measurements
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| ... " These statements appear to provide different criterion for the ASME Code repair. The first statement states that the Code repair will be performed in the next refueling outage whereas the second statement states that the subject pipe will be repaired prior to reaching the allowable minimum wall thickness.
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| (1) Discuss which statement above represents the intent of the relief request (I.e., when will the Code repair be performed).
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| (2) Discuss the criterion by which the immediate ASME Code repair of the subject piping will be performed.
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| : 6. (1) Discuss whether the subject piping system is insulated.
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| If insulated, discuss how leakage would be timely observed before the functionality and structural integrity of the piping is challenged.
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| (2) Discuss whether periodic walkdowns will be performed in addition to the UT examinations.
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| If not, discuss how leakage can be timely detected to minimize the potential of a pipe rupture. 7. Page E 1-5 of the relief request states that"... [t]he affected area will be ultrasonically examined on a frequency until SNC establishes a wear rate ... Analytical evaluation will be performed based on each set of UT [ultrasonic testing] thickness measurements using ASME Code Case N-597-2 as discussed in this relief request. .. " (1) Confirm that the UT examinations and analytical evaluations will be continuously performed until the pipe is ASME Code-repaired.
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| (2) Discuss the administrative controls and measures if the wall thinning rate increases.
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| (3) Page E1-5 states that the degradation mechanism is indeterminate and that additional areas of the subject piping were examined and no locations found below minimum wall thickness.
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| Discuss how many areas have been examined for wall thinning (pipe segments other than the areas shown in Enclosure 2 of the relief request), which minimum wall was used for acceptance (0.311 inches generic or 0.183 inches per N-597 -2 evaluation) and would the total number of examined areas provide a reasonable assurance that the RHR Service Water system piping is structurally sound (i.e., the extent of condition).
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| (4) Discuss whether the UT examinations will include inspection of areas other than the affected area of the subject piping. If not, provide justification.
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| January 9,2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO.2 -REQUEST FOR ADDITIONAL INFORMATION (RAI), HNP-ISI-RR-12, RESIDUAL HEAT REMOVAL SERVICE WATER PIPING (TAC NO. ME7726)
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| ==Dear Mr. Ajluni:==
| | REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST (RR) HNP-ISI-RR-12. VERSION 1 RESIDUAL HEAT REMOVAL SERVICE WATER PIPING EDWIN I. HATCH NUCLEAR PLANT. UNIT NO.2 DOCKET NO. 50-366 TAC NO. ME7726 By letter dated December 22, 2011 (Agencywide Documents Access And Management System (ADAMS) Accession Number ML113570234), Southern Nuclear Operating Company, Inc. |
| By letter dated December 22, 2011 (Agencywide Documents Access and Management System Accession No. ML113570234), Southern Nuclear Operating Company, Inc., submitted relief request for the HNP-ISI-RR-12, Version 1 for Edwin I. Hatch Nuclear Plant Unit NO.2. The proposed relief request will be applicable to wall thinning in the Residual Heat Removal Service Water piping using American Society of Mechanical Engineers (ASME) Code Case N-597-2. Responses to the enclosed RAI are needed for us to continue our review. Please provide a response within thirty (30) calendar days of the date of this letter. Sincerely, IRA! Patrick G. Boyle, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-366 | | (SNC, the licensee) requested Nuclear Regulatory Commission (NRC) review and approval of RR HNP-ISI-RR-12, Version 1, for Edwin I. Hatch Nuclear Plant Unit 2. The proposed relief request will be applicable to wall thinning in the Residual Heat Removal Service Water (RHRSW) piping using American Society of Mechanical Engineers (ASME) Code Case N-597 |
| | : 2. To complete its review, the NRC staff requests the following additional information: |
| | : 1. Clarify from which subarticles in the ASME Code Section XI the relief is requested. Discuss whether the RR will deviate from Code Case N-597 -2, excluding the deviations from the five NRC Conditions imposed in Regulatory Guide 1.147, Revision 16, which are discussed in the proposed RR. If yes, list the deviation(s) and provide justification. |
| | : 2. As shown on page E1-3 of the RR, in response to NRC Condition 1, the licensee stated that u *** [t]he EPRI Report 202L-R2 is not applicable in this case because RHRSW has oxygen content significantly higher than FAC [flow-accelerated corrosion] components. Similar to the FAC program at the SNC plants, SNC has implemented a Fleet Service Water Program which includes the development of inspection requirements, determining the rate of wall thickness loss plus the calculation of values for the predicted remaining life ... " (1) Discuss how the inspection requirements, the rate of wall thickness loss, the value of the predicted remaining wall thickness and the predicted remaining life for the pipe are determined in the SNC Fleet Service Water Program and discuss how these methods differ from the EPRI Report 202L-R2. (2) Page E1-5 of the relief request states that analytical evaluations will be performed based on each set of UT thickness measurements using ASME Code Case N-597 -2. However, the above quoted statement states that the Fleet Service Water Program provides analytical evaluations and will be used. Clarify whether the analytical evaluations to project (predict) wall thinning in the subject piping will be based on N-597-2 or the Fleet Service Water Program. If the analytical method in the Fleet Service Water Program will be used, discuss whether the analytical evaluation method in the Fleet Service Water Program is consistent with the analytical evaluation requirements of Code Case N-597-2. If not, justify why the analytical method in the Fleet Service Water Program is acceptable for use. |
| | : 3. (1) Discuss whether the RHR Service Water piping in the proposed relief request is located above ground or buried. If some portion of the pipe is buried underground, discuss how the buried portion of the pipe will be inspected. (2) Page E1-1 of the relief request states that the supply header can be cross-connected to heat exchanger 2E 11 B001 B. Discuss the exact piping boundary (from end to end) that is covered under the proposed relief request and provide Enclosure |
|
| |
|
| ==Enclosure:==
| | -2 an isometric drawing showing the affected piping. (3) Confirm that the entire length of the pipe is accessible for ultrasonic examinations of pipe wall thickness. If not, discuss how the pipe wall thickness can be determined for the inaccessible portion of the pipe. (4) Discuss the pressures and temperatures that the subject piping system will be exposed to for various design conditions. |
| | : 4. On page E1-4 of the relief request, in response to NRC Condition 5, the licensee mentioned a generic calculated acceptable minimum wall thickness of 0.311 inches. The licensee also discussed a detailed evaluation per ASME Code Case N-597-2 that resulted in a calculated minimum wall of 0.183 inches. Submit both calculations and discuss the differences in wall thickness calculation that resulted in two significant different allowable wall thickness values. |
| | : 5. Page E1-5 (top of the page) of the relief request states that" ... [a] permanent Code-compliant repair will be performed during the next refueling outage currently scheduled to begin in February 2013 or during a system outage of sufficient length to effect repairs ... " Page E 1-5, Alternative Duration Section, states that " ... [t]his relief request will remain in effect until an ASME Section XI Code repair/replacement is performed prior to reaching the allowable minimum wall thickness based on the ongoing ultrasonic thickness measurements ... " These statements appear to provide different criterion for the ASME Code repair. The first statement states that the Code repair will be performed in the next refueling outage whereas the second statement states that the subject pipe will be repaired prior to reaching the allowable minimum wall thickness. (1) Discuss which statement above represents the intent of the relief request (I.e., when will the Code repair be performed). (2) Discuss the criterion by which the immediate ASME Code repair of the subject piping will be performed. |
| | : 6. (1) Discuss whether the subject piping system is insulated. If insulated, discuss how leakage would be timely observed before the functionality and structural integrity of the piping is challenged. (2) Discuss whether periodic walkdowns will be performed in addition to the 3~-day UT examinations. If not, discuss how leakage can be timely detected to minimize the potential of a pipe rupture. |
| | : 7. Page E 1-5 of the relief request states that" ... [t]he affected area will be ultrasonically examined on a 3~-day frequency until SNC establishes a wear rate ... Analytical evaluation will be performed based on each set of UT [ultrasonic testing] thickness measurements using ASME Code Case N-597-2 as discussed in this relief request. .. " (1) Confirm that the 3~-day UT examinations and analytical evaluations will be continuously performed until the pipe is ASME Code-repaired. (2) Discuss the administrative controls and measures if the wall thinning rate increases. (3) Page E1-5 states that the degradation mechanism is indeterminate and that additional areas of the subject piping were examined and no locations found below minimum wall thickness. Discuss how many areas have been examined for wall thinning (pipe segments other than the areas shown in Enclosure 2 of the relief request), which minimum wall was used for acceptance (0.311 inches generic or 0.183 inches per N-597-2 evaluation) and would the total number of examined areas provide a reasonable assurance that the RHR Service Water system piping is structurally sound (i.e., the extent of condition). (4) Discuss whether the 3~-day UT examinations will include inspection of areas other than the affected area of the subject piping. If not, provide justification. |
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| RAI cc w/encl: Distribution via Listserv DISTRIBUTION:
| | '.. ML12004A062 *via e-mail ML113640210 OFFICE NRRlLPL2 -1/PM NRRlLPL2-lILA NRRlEPNB/BC NRRlLPL2-1/BC NRRlLPL2-1/PM NAME SFigueroa TLupold* GKulesa PBoyle |
| Public RidsOgcRp Resource RidsRgn2MailCenter Resource LPL2-1 RlF RidsAcrsAcnw_MailCTR RidsNrrPMHatch Resource RidsNrrDorlLpl2-1 Resource RidsNrrLASFigueroa Resource RidsNrrDeEpnb Resource JTsao, NRR ADAMS Accession No' ML12004A062
| | " (VSreenivas for) |
| .. *via e-mail ML113640210 OFFICE N RRlLPL2 -1/PM NRRlLPL2-lILA NRRlEPNB/BC NRRlLPL2-1/BC NRRlLPL2-1/PM NAME " SFigueroa TLupold* GKulesa (VSreenivas for) PBoyle DATE 01/5/12 01/5/12 12131/11 01/6/12 01/9/12 OFFICIAL RECORD COPY}} | | DATE 01/5/12 01/5/12 12131/11 01/6/12 01/9/12}} |
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Hatch Nuclear Plant Units 1 and 2 - Nrc Inspection Report 05000321/2023006 and 05000366/2023006 NL-24-0067, 10 CFR 72.48(d)(2) Biennial Report2024-02-26026 February 2024 10 CFR 72.48(d)(2) Biennial Report 2024-09-09
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24290A1552024-10-16016 October 2024 NRR E-mail Capture - for Your Action - RAI - Farley, Hatch, and Vogtle 1 and 2 - Proposed Alternative Request for Code Case N-572 ML24278A0052024-10-0303 October 2024 Document Request for Hatch Nuclear Plant - IP 92702 Follow-Up Radiation Protection Inspection - Inspection Report 2024-04 ML24211A0162024-07-26026 July 2024 NRR E-mail Capture - Request for Additional Information - Hatch, Units 1 and 2, Revise TS SRs (3.4.3.1 & 3.1.7.7) to Increase SRV Setpoints LAR ML24208A1742024-07-26026 July 2024 Request for Additional Information Regarding License Amendment Request to Revise TS SRs (3.4.3.1 & 3.1.7.7) to Increase S/Rv Setpoints ML24193A1182024-07-10010 July 2024 Email to SNC with RAI for Hatch Exemption Request ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) ML23354A2032023-12-18018 December 2023 Document Request for Hatch Nuclear Plant - Radiation Protection Inspection - Inspection Report 2024-01 ML23250A0472023-09-20020 September 2023 Request for Additional Information Regarding License Amendment Request to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts in Technical Specifications Table 1.1-1, Modes ML23264A0142023-09-14014 September 2023 NRR E-mail Capture - (External_Sender) Draft Round-2 RAI - Hatch, Units 1 and 2, Revise TS 1.1-1 Modes LAR ML23198A1552023-07-17017 July 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Hatch, Farley, and Vogtle, Units 1 and 2 Quality Assurance Topical Report (QATR) Submittal Dated June 15, 2023 ML23018A1872023-01-17017 January 2023 2023 HNP CGD Inspection Information Request ML22355A2082022-12-21021 December 2022 NRR E-mail Capture - RAI - Hatch, Units 1 and 2, Reactor Pressure Vessel 'Rpv Head Studs' LAR ML23026A2372022-11-16016 November 2022 2023001 Hatch RP RFI Final ML22208A1332022-07-26026 July 2022 NRR E-mail Capture - RAI - Hatch, Units 1 and 2, TSTF-208 LAR ML22157A3542022-06-0606 June 2022 NRR E-mail Capture - RAI - Hatch, Units 1 and 2, TSTF-505 LAR ML22140A1192022-05-20020 May 2022 NRR E-mail Capture - RAIs - Hatch, Units 1 and 2, TSTF-505 LAR ML22073A0842022-03-21021 March 2022 an NRC Fire Protection Team Inspection (NRC Inspection Report Nos. 05000321/2022011 and 05000366/2022011) and Request for Information ML22025A2142022-01-21021 January 2022 Plant Hatch 2022001 RP Baseline Inspection Information Request ML21265A3402021-09-22022 September 2021 NRR E-mail Capture - Request for Additional Information - Hatch, Unit 1, Emergency TS 3.7.2 LAR ML21111A3032021-04-21021 April 2021 NRR E-mail Capture - RAI - Hatch Unit 2 - One-Time Emergency RHR LAR (L-2020-LRO-0068) ML21110A6842021-04-20020 April 2021 NRR E-mail Capture - RAI - Hatch Unit 2 - One-Time Emergency RHR LAR (L-2020-LRO-0068) ML21013A4112021-01-13013 January 2021 Notification of Edwin I. Hatch Nuclear Plant Design Bases Assurance Inspection U.S. Nuclear Regulatory Commission Inspection Report 05000321/2021010 and 05000366/2021010 ML20293A0752020-10-14014 October 2020 NRR E-mail Capture - RAIs for SNC Fleet EP LAR (L-2020-LLA-0150 and L-2020-LLA-0151) ML20253A2732020-09-0909 September 2020 Requalification Program Inspection Hatch Nuclear Station ML20149K6252020-05-27027 May 2020 NRR E-mail Capture - RAIs for SNC Fleet Fire Protection Exemption Requests NL-19-1532, Units 1 and 2 - Response to Requests for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures. Systems and Components for Nuclear Power Reactors2019-12-18018 December 2019 Units 1 and 2 - Response to Requests for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures. Systems and Components for Nuclear Power Reactors ML19336A0142019-12-0101 December 2019 NRR E-mail Capture - RAI: Hatch Emergency TS 3.7.1 Residual Heat Removal Service Water (RHRSW) System LAR ML19280A0082019-10-0404 October 2019 NRR E-mail Capture - Request for Additional Information (RAI) - Hatch TSTF-51 LAR (L-2019-LLA-0091) ML19224C0552019-08-12012 August 2019 NRR E-mail Capture - RAI - Edwin I. Hatch Nuclear Plant, LAR Regarding Degraded Voltage (L-2019-LLA-0108) ML19220A0362019-08-0808 August 2019 NRR E-mail Capture - RAI - Edwin I. Hatch Nuclear Plant, LAR Regarding Adoption of NFPA 805, Request for Additional Information, EPID L-2018-LLA-0107 ML19164A2582019-06-13013 June 2019 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML19107A4962019-04-17017 April 2019 NRR E-mail Capture - Request for Additional Information - Hatch 1 & 2 Application to Adopt Title 10 of Code of Federal Regulations 50.69 RISK-INFORMED Categorization and Treatment of Structures, Systems and Components for Power Reactors ML19088A0092019-03-29029 March 2019 NRR E-mail Capture - Hatch 1 and 2 - LAR to Adopt NFPA 805 Fire Protection Standard, EPID L-2018-LLA-0107, Request for Additional Information ML19029B3402019-01-23023 January 2019 Southern Nuclear Operating Company, Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 Draft Request for Additional Information for the License Amendment Requests to Adopt the Risk-Informed Provisions of Title 10 of the Code of Federal Regulat ML19016A3422019-01-10010 January 2019 U2 ISI 2019001 RFI - Bcc ML18355A4772019-01-0404 January 2019 Request for Additional Information Revise TS 5.2.2.g and Update Emergency Plan Minimum On-Shift Staff Tables ML18337A4032018-12-0606 December 2018 Request for Additional Information Revise Technical Specification 5.2.2.G and Updating Emergency Plan Minimum On-Shift Staff Tables ML18085A0132018-03-0808 March 2018 Draft Request for Additional Information on Alternative RR-V-11, Proposed Extension to Main Steam Safety Relief Valve Testing Requirements ML18058A0812018-02-27027 February 2018 Enclosurequest for Additional Information(Rai for Review of Southern Nuclear Operating Company'S Decommissioning Funding Plan Updates for Joseph M. Farley,Unit 1 and 2;Edwin I. Hatch,Units 1 and 2; and Vogtle Electric Generating Plant, Unit ML17306A0872017-11-0808 November 2017 Request for Additional Information Regarding the Decommissioning Funding Status Reports (EPID L-LRO-2017-0008) ML17284A3542017-11-0707 November 2017 Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools ML17270A1402017-09-27027 September 2017 PIR Notification Letter 2017 ML17290A3172017-09-19019 September 2017 NRR E-mail Capture - Hatch 1 and 2 - Draft Request for Additional Information Request for Alternative No. HNP-ISI-ALT-05-05 ML17111A5792017-04-26026 April 2017 Request for Additional Information, Fourth 10-Year ISI Interval Relief Requests ML17110A2112017-04-24024 April 2017 Request for Additional Information ML16330A1282016-12-0505 December 2016 Request for Additional Information ML16307A1842016-11-0202 November 2016 Request for Additional Information (Non-Proprietary) ML16271A1692016-10-17017 October 2016 Request for Additional Information ML16222A2952016-08-29029 August 2016 Request for Additional Information ML16205A0012016-07-22022 July 2016 Requalification Program Inspection - Plant Hatch 2024-07-26
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 January 9, 2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT, UNIT NO.2 - REQUEST FOR ADDITIONAL INFORMATION (RAJ), HNP-ISI-RR-12, RESIDUAL HEAT REMOVAL SERVICE WATER PIPING (TAC NO. ME7726)
Dear Mr. Ajluni:
By letter dated December 22, 2011 (Agencywide Documents Access and Management System Accession No. ML113570234), Southern Nuclear Operating Company, Inc., submitted relief request for the HNP-ISI-RR-12, Version 1 for Edwin I. Hatch Nuclear Plant Unit No.2. The proposed relief request will be applicable to wall thinning in the Residual Heat Removal Service Water piping using American Society of Mechanical Engineers (ASME) Code Case N-597 -2.
Responses to the enclosed RAI are needed for us to continue our review. Please provide a response within thirty (30) calendar days of the date of this letter.
Sincerely, Patrick G. Boyle, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-366
Enclosure:
RAI cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST (RR) HNP-ISI-RR-12. VERSION 1 RESIDUAL HEAT REMOVAL SERVICE WATER PIPING EDWIN I. HATCH NUCLEAR PLANT. UNIT NO.2 DOCKET NO. 50-366 TAC NO. ME7726 By letter dated December 22, 2011 (Agencywide Documents Access And Management System (ADAMS) Accession Number ML113570234), Southern Nuclear Operating Company, Inc.
(SNC, the licensee) requested Nuclear Regulatory Commission (NRC) review and approval of RR HNP-ISI-RR-12, Version 1, for Edwin I. Hatch Nuclear Plant Unit 2. The proposed relief request will be applicable to wall thinning in the Residual Heat Removal Service Water (RHRSW) piping using American Society of Mechanical Engineers (ASME) Code Case N-597
- 2. To complete its review, the NRC staff requests the following additional information:
- 1. Clarify from which subarticles in the ASME Code Section XI the relief is requested. Discuss whether the RR will deviate from Code Case N-597 -2, excluding the deviations from the five NRC Conditions imposed in Regulatory Guide 1.147, Revision 16, which are discussed in the proposed RR. If yes, list the deviation(s) and provide justification.
- 2. As shown on page E1-3 of the RR, in response to NRC Condition 1, the licensee stated that u *** [t]he EPRI Report 202L-R2 is not applicable in this case because RHRSW has oxygen content significantly higher than FAC [flow-accelerated corrosion] components. Similar to the FAC program at the SNC plants, SNC has implemented a Fleet Service Water Program which includes the development of inspection requirements, determining the rate of wall thickness loss plus the calculation of values for the predicted remaining life ... " (1) Discuss how the inspection requirements, the rate of wall thickness loss, the value of the predicted remaining wall thickness and the predicted remaining life for the pipe are determined in the SNC Fleet Service Water Program and discuss how these methods differ from the EPRI Report 202L-R2. (2) Page E1-5 of the relief request states that analytical evaluations will be performed based on each set of UT thickness measurements using ASME Code Case N-597 -2. However, the above quoted statement states that the Fleet Service Water Program provides analytical evaluations and will be used. Clarify whether the analytical evaluations to project (predict) wall thinning in the subject piping will be based on N-597-2 or the Fleet Service Water Program. If the analytical method in the Fleet Service Water Program will be used, discuss whether the analytical evaluation method in the Fleet Service Water Program is consistent with the analytical evaluation requirements of Code Case N-597-2. If not, justify why the analytical method in the Fleet Service Water Program is acceptable for use.
- 3. (1) Discuss whether the RHR Service Water piping in the proposed relief request is located above ground or buried. If some portion of the pipe is buried underground, discuss how the buried portion of the pipe will be inspected. (2) Page E1-1 of the relief request states that the supply header can be cross-connected to heat exchanger 2E 11 B001 B. Discuss the exact piping boundary (from end to end) that is covered under the proposed relief request and provide Enclosure
-2 an isometric drawing showing the affected piping. (3) Confirm that the entire length of the pipe is accessible for ultrasonic examinations of pipe wall thickness. If not, discuss how the pipe wall thickness can be determined for the inaccessible portion of the pipe. (4) Discuss the pressures and temperatures that the subject piping system will be exposed to for various design conditions.
- 4. On page E1-4 of the relief request, in response to NRC Condition 5, the licensee mentioned a generic calculated acceptable minimum wall thickness of 0.311 inches. The licensee also discussed a detailed evaluation per ASME Code Case N-597-2 that resulted in a calculated minimum wall of 0.183 inches. Submit both calculations and discuss the differences in wall thickness calculation that resulted in two significant different allowable wall thickness values.
- 5. Page E1-5 (top of the page) of the relief request states that" ... [a] permanent Code-compliant repair will be performed during the next refueling outage currently scheduled to begin in February 2013 or during a system outage of sufficient length to effect repairs ... " Page E 1-5, Alternative Duration Section, states that " ... [t]his relief request will remain in effect until an ASME Section XI Code repair/replacement is performed prior to reaching the allowable minimum wall thickness based on the ongoing ultrasonic thickness measurements ... " These statements appear to provide different criterion for the ASME Code repair. The first statement states that the Code repair will be performed in the next refueling outage whereas the second statement states that the subject pipe will be repaired prior to reaching the allowable minimum wall thickness. (1) Discuss which statement above represents the intent of the relief request (I.e., when will the Code repair be performed). (2) Discuss the criterion by which the immediate ASME Code repair of the subject piping will be performed.
- 6. (1) Discuss whether the subject piping system is insulated. If insulated, discuss how leakage would be timely observed before the functionality and structural integrity of the piping is challenged. (2) Discuss whether periodic walkdowns will be performed in addition to the 3~-day UT examinations. If not, discuss how leakage can be timely detected to minimize the potential of a pipe rupture.
- 7. Page E 1-5 of the relief request states that" ... [t]he affected area will be ultrasonically examined on a 3~-day frequency until SNC establishes a wear rate ... Analytical evaluation will be performed based on each set of UT [ultrasonic testing] thickness measurements using ASME Code Case N-597-2 as discussed in this relief request. .. " (1) Confirm that the 3~-day UT examinations and analytical evaluations will be continuously performed until the pipe is ASME Code-repaired. (2) Discuss the administrative controls and measures if the wall thinning rate increases. (3) Page E1-5 states that the degradation mechanism is indeterminate and that additional areas of the subject piping were examined and no locations found below minimum wall thickness. Discuss how many areas have been examined for wall thinning (pipe segments other than the areas shown in Enclosure 2 of the relief request), which minimum wall was used for acceptance (0.311 inches generic or 0.183 inches per N-597-2 evaluation) and would the total number of examined areas provide a reasonable assurance that the RHR Service Water system piping is structurally sound (i.e., the extent of condition). (4) Discuss whether the 3~-day UT examinations will include inspection of areas other than the affected area of the subject piping. If not, provide justification.
'.. ML12004A062 *via e-mail ML113640210 OFFICE NRRlLPL2 -1/PM NRRlLPL2-lILA NRRlEPNB/BC NRRlLPL2-1/BC NRRlLPL2-1/PM NAME SFigueroa TLupold* GKulesa PBoyle
" (VSreenivas for)
DATE 01/5/12 01/5/12 12131/11 01/6/12 01/9/12