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Category:E-Mail
MONTHYEARML24025A1592024-01-25025 January 2024 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 - Request for Additional Information - Rvi AMP and Inspection Plan (L-2023-LLL-0016) ML23177A1992023-06-26026 June 2023 NRR E-mail Capture - Acceptance Review - Shearon Harris Nuclear Power Plant, Unit 1 - RA-23-0005 - LAR to Align Certain TSs with ISTS (L-2023-LLA-0078) ML23172A0132023-06-20020 June 2023 Duke Fleet - Correction to June 2, 2023, Request for Additional Information Proposed License Amendment Request to Revise Restrictive Surveillance Requirement Frequencies ML23153A1892023-06-0202 June 2023 Duke Fleet - Request for Additional Information Proposed License Amendment Request to Revise Restrictive Surveillance Requirement Frequencies ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML23124A1212023-05-0404 May 2023 Acceptance of Requested Licensing Action Duke Fleet Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23082A0432023-03-23023 March 2023 002 Radiation Safety Baseline Inspection Information Request Final ML23073A2282023-03-13013 March 2023 Duke Fleet- Adoption of TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements - Acceptance Review ML23065A0942023-03-0606 March 2023 NRR E-mail Capture - Acceptance Review - Shearon Harris Nuclear Power Plant, Unit 1 - RA-22-0081 - LAR to Address Administrative Changes to the Operating License and Technical Specifications (L-2023-LLA-0020) ML23058A0562023-02-27027 February 2023 Acceptance of Amendment to Revise Surveillance Frequencies for RCS Pressure Isolation Valve Operational Leakage Testing and Reactor Trip System Instrumentation ML23048A1512023-02-16016 February 2023 Acceptance Review - Proposed Alternative for Steam Generator Welds (L-2023-LLR-0003) ML22237A1632022-08-25025 August 2022 004 Radiation Safety Baseline Inspection Information Request ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22108A0182022-04-15015 April 2022 NRR E-mail Capture - Accepted for Review - Duke Energy Relief Request for Harris Nuclear Plant Inservice Testing Program Plan - Fourth Ten-Year Interval to Extend Type C Test to 75 Months ML22083A0702022-03-24024 March 2022 NRR E-mail Capture - Catawba Nuclear Station, Units 1 and 2, Shearon Harris Nuclear Power Plant, Unit 1, and McGuire Nuclear Station, Units 1 and 2 - Acceptance Review for TSTF-569 LAR ML22083A0282022-03-23023 March 2022 Email Snsb Safety Evaluation for Harris LAR to Revise Reactor Protection System TS ML22038A1572022-02-0707 February 2022 NRR E-mail Capture - Duke Energy Fleet - Acceptance of License Amendment Request Regarding Adoption of TSTF-541, Revision 2 ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML21361A0122021-12-23023 December 2021 NRR E-mail Capture - Accepted for Review - Duke Energy Fleet License Amendment Request to Relocate Emergency Operations Facility ML21354A8612021-12-15015 December 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet Request RA-19-0352 - Alternative for RPV Closure Stud Exams (L-2020-LLR-0156) ML21321A3782021-11-16016 November 2021 NRR E-mail Capture - Energy Harbor Fleet, Beaver Valley Units 1 and 2 and DAVIS-BESSEL Unit 1 - Acceptance of License Amendment Request Adoption of TSTF-554 EPID-L-2021-LLA-0193 ML21288A0802021-10-15015 October 2021 NRR E-mail Capture - Acceptance Review - Shearon Harris Nuclear Power Plant, Unit 1 - RA-21-0213 - Remove Limitations to Perform Certain SRs During Shutdown (L-2021-LLA-0167) ML21295A0372021-10-0505 October 2021 NRR E-mail Capture - Accepted for Review - Duke Energy Fleet License Amendment Request to Adopt TSTF-577 Revised Frequencies for Steam Generator Tube Inspections ML21252A0112021-08-30030 August 2021 NRR E-mail Capture - Acceptance Review - Shearon Harris Nuclear Power Plant, Unit 1- RA-21-0191 - Revised TS Related to Reactor Trip System Instrumentation (L-2021-LLA-0149) ML21189A0282021-07-0101 July 2021 NRR E-mail Capture - Acceptance Review - Shearon Harris Nuclear Power Plant, Unit 1 - RA-21-0112 - Revise TS to Reflect Development of TRM (L-2021-LLA-0108) ML21172A2432021-06-21021 June 2021 NRR E-mail Capture - Request for Additional Information - Harris RA-20-0252 - LAR to Remove Extraneous Requirements from OL and TS (L-2021-LLA-0027) ML21106A0112021-04-15015 April 2021 NRR E-mail Capture - Acceptance Review - Shearon Harris Nuclear Power Plant, Unit 1 - RA-21-0052 - Revise Containment Spray Nozzle Surveillance Frequency (L-2021-LLA-0058) ML21084A2492021-03-24024 March 2021 Notification of Inspection and Request for Information ML21084A2512021-03-22022 March 2021 NRR E-mail Capture - Acceptance Review - Shearon Harris Nuclear Power Plant, Unit 1 - RA-20-0252 - LAR to Remove Extraneous Content and Requirements from the OL and TS (L-2021-LLA-0027) ML21039A6382021-02-0808 February 2021 NRR E-mail Capture - Acceptance Review - Shearon Harris Nuclear Power Plant, Unit 1-RA-20-0311 - 10 CFR 50.69 Categorization Process to Reflect an Alternative Seismic Approach (L-2021-LLA-0003) ML21036A1142021-02-0505 February 2021 NRR E-mail Capture - Request for Additional Information - Harris - Relief Request RA-20-0312 - SW Pinhole Leak (L-2020-LLR-0143) ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML21033A8452021-02-0202 February 2021 NRR E-mail Capture - State Notification of Amendments to Shearon Harris Nuclear Power Plant, Unit 1 - Revision Minimum RCS Flow Rate and Update COLR References ML21033B1062021-02-0202 February 2021 NRR E-mail Capture - (External_Sender) (External) State Notification of Amendments to Shearon Harris Nuclear Power Plant, Unit 1 - Revision Minimum RCS Flow Rate and Update COLR References ML21032A0492021-02-0101 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet RA-20-0263 - Use of Later ASME B&Pv, XI for Repair - Replacement (L-2020-LLR-0124) ML21025A2922021-01-25025 January 2021 NRR E-mail Capture - (External_Sender) State Notification of Amendment to Shearon Harris Nuclear Power Plant, Unit 1 - Revise TS 3/4.4.9, Pressure/Temperature Limits - Reactor Coolant System ML21007A3722021-01-0707 January 2021 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-19-0352 - Proposed Alternative for Reactor Vessel Close Stud Examinations (L-2020-LLR-0156) ML21006A4302021-01-0606 January 2021 Acceptance Review - Duke Fleet RA-20-0207 Request to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML21006A4042021-01-0606 January 2021 NRR E-mail Capture - State Notification of Amendment to Shearon Harris Nuclear Power Plant, Unit 1 - Revise TS 3/4.4.9, Pressure/Temperature Limits - Reactor Coolant System ML20345A3052020-12-10010 December 2020 NRR E-mail Capture - (External_Sender) (External) State Notification of Amendments to Shearon Harris Nuclear Power Plant, Unit 1 - Revise TS 3.3.3.6 and TS 3.9.2 ML20344A4192020-12-0909 December 2020 NRR E-mail Capture - State Notification of Amendments to Shearon Harris Nuclear Power Plant, Unit 1 - Revise TS 3.3.3.6 and TS 3.9.2 ML20328A0802020-11-23023 November 2020 NRR E-mail Capture - Acceptance Review - Shearon Harris Nuclear Power Plant, Unit 1 - RA-20-0312-Relief Request, Service Water Pinhole Leak in a Socket Weld, Inservice Inspection (L-2020-LLR-0143) ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) ML20297A3102020-10-13013 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0191 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI - IWA-5120, IWA-5213, IWA-5241, IWA-5242, and IWA-5250 (L-2020-LLR-0126) ML20297A3072020-10-13013 October 2020 NRR E-mail Capture - Request for Additional Information - Shearon Harris Nuclear Power Plant, Unit 1 - RCS Flowrate Reduction/Lbloca LAR ML20297A3082020-10-0707 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0263 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI for Repair/Replacement (L-2020-LLR-0124) ML20297A3092020-10-0606 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0262 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI - IWA-4540(b) (L-2020-LLR-0125) ML20274A0462020-09-29029 September 2020 Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Revision 2 ML20247J3822020-09-0303 September 2020 Request for Additional Information - Shearon Harris Nuclear Power Plant, Unit 1 - Revise TS Related to Accident Monitoring and RFO Instrumentation 2024-01-25
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NRR-PMDAPEm Resource From: Mozafari, Brenda Sent: Friday, September 02, 2011 6:27 PM To: Caves, John
Subject:
RAI regarding TAC No. ME5409 (Harris-M5 cladding)
Importance: High
- John, By letter dated January 13, 2011, Carolina Power and Light Company (CP&L) submitted a request for an amendment to the Technical Specifications (TS) for Shearon Harris Nuclear Power Plant Unit 1 (HNP). The license amendment request (LAR) proposed a change to the HNP Technical Specifications (TS) 5.3.1 and adds the AREVA NP report BAW-10240(P)(A), Incorporation of M5 Properties in Framatome ANP Approved Methods," to the referenced analytical methods in administrative TS 6.9.1.6.2 to allow the use of M5 alloy for fuel rod cladding. The proposed amendment would modify the HNP TS to permit the use of the AREVA fuel cladding alloy designated as M5.
We have reviewed the license amendment request, and determined that additional information is needed in order to complete our evaluation.
The NRC requests that the licensee respond to this request for additional information (RAl) within 30 days of the date of this email. If the licensee concludes that more than 30 days are required to respond to the RAl, the licensee should request additional time, including a basis for why the extension is needed.
Contact me at the number below or by e-mail if you have any questions on this issue or if you require additional time to submit your response.
Brenda L. Mozafari Senior Project Manager, NRR/DORL U.S. Nuclear Regulatory Commission 301-415-2020 email: brenda.mozafari@nrc.gov PROPOSED LICENSE AMENDMENT REQUEST FOR REVISION TO TS 5.3.1 AND CORE OPERATING LIMITS REPORT REFERENCES FOR M5 CLADDING NRC DOCKET NO. 50-400 (TAC NO. ME5409)
- 1. Safety evaluation for Topical Report BAW-10240(P)(A) lists following four conditions which Framatome (FANP) has accepted:
(a) The corrosion limit, as predicted by the best-estimate model will remain below 100 microns for all locations of the fuel.
(b) All of the conditions listed in the SEs for all FANP methodologies used for M5 fuel analysis will continue to be met, except that the use of M5 cladding in addition to Zircaloy-4 cladding is now approved.
1
(c) All FANP methodologies will be used only within the range for which M5 data was acceptable and for which the verifications discussed in BAW-l0240(P) or Reference 2 was performed.
(d) The burnup limit for this approval is 62 GWd/MTU Explain in detail, how each of the above condition has been implemented at HNP Unit 1.
- 2. The safety evaluation for EMF-2310, Revision 0 topical report (Section 5.0) has restated one of the restrictions (Number 1) from the safety evaluation for ANF-89-151(P)(A) (Section 2.2, TER Conclusions) as stated below:
The stated application of the S-RELAP5 code is for the events listed above in Table 1. There are other computer codes and methodologies employed for evaluation of the events not listed in the table. For each licensing basis event analyzed, the applicant must, as always, justify the methodology used whether by reference to S-RELAP5 or whatever methodology has been used.
Explain how this restriction is implemented for the upcoming cycle reload analyses when the transition to M5 cladding occurs.
- 3. RODEX2 fuel deformation and conductivity models were incorporated in S-RELAP5 for transient and accident analyses. Provide details of the methodology in the fuel model to evaluate fuel thermal conductivity as a function of burnup and temperature, considering all of the effects that take in the fuel during the irradiation in the reactor core.
Provide a list of Shearon Harris Unit 1 FSAR Chapter 15 Non-LOCA events that will be either analyzed or dispositioned for the upcoming fuel cycle when the licensee is planning to use M5 cladding. Also summarize the methodologies and codes used for the analyses.
2
Hearing Identifier: NRR_PMDA Email Number: 137 Mail Envelope Properties (Brenda.Mozafari@nrc.gov20110902182600)
Subject:
RAI regarding TAC No. ME5409 (Harris-M5 cladding)
Sent Date: 9/2/2011 6:26:36 PM Received Date: 9/2/2011 6:26:00 PM From: Mozafari, Brenda Created By: Brenda.Mozafari@nrc.gov Recipients:
"Caves, John" <john.caves@pgnmail.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 3890 9/2/2011 6:26:00 PM Options Priority: High Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: