ML23228A195: Difference between revisions
StriderTol (talk | contribs) (StriderTol Bot insert) |
StriderTol (talk | contribs) (StriderTol Bot change) |
||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:August 21, 2023 Mr. Edward Casulli Site Vice President Susquehanna Nuclear, LLC 769 Salem Boulevard NUCSB3 Berwick, PA 18603-0467 | {{#Wiki_filter:August 21, 2023 | ||
Mr. Edward Casulli Site Vice President Susquehanna Nuclear, LLC 769 Salem Boulevard NUCSB3 Berwick, PA 18603-0467 | |||
==SUBJECT:== | ==SUBJECT:== | ||
| Line 27: | Line 29: | ||
==Dear Mr. Casulli:== | ==Dear Mr. Casulli:== | ||
On August 10, 2023, the U.S. Nuclear Regulatory Commission (NRC) staff held a virtual public meeting1 with Susquehanna Nuclear, LLC (the licensee). The purpose of the meeting was to discuss the licensees plans to submit proposed alternative under Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(z) regarding testing requirements for a residual heat removal system valve on Susquehanna Steam Electric Station, Unit 2. The enclosure to this summary contains a list of attendees. | |||
During the meeting, the licensee discussed its plans to submit a proposed alternative to testing requirements in the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) for the Unit 2 residual heat removal system cross-connect check valve V251130, which was installed in 2007. The valve is a 1-inch valve that assists with seating the containments 24-inch main check valve. The licensee discussed that it missed the opportunity to test V251130 during its spring 2023 refueling outage and inadvertently did not include the valve in its proposed alternative 2 submitted in 2013 for the fourth inservice testing program interval. The surveillances grace period expires in October. | |||
During the meeting, the licensee discussed its plans to submit a proposed alternative to testing requirements in the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) for the Unit 2 residual heat removal system cross-connect check valve V251130, which was installed in 2007. The valve is a 1-inch valve that assists with seating the containments 24-inch main check valve. The licensee discussed that it missed the opportunity to test V251130 during its spring 2023 refueling outage and inadvertently did not include the valve in its proposed | |||
The licensee indicated that it plans to propose alternative testing, under 10 CFR 50.55a(z)(1), to certain ASME OM Code testing requirements for the valve. The licensee indicated that its proposed alternative will also include a discussion of hardship that could be considered under 10 CFR 50.55a(z)(2). The licensees proposed alternative would be to supplement the 2013 proposed alternative by adding valve V251130 to the list of affected components. The licensee plans to submit the request in August 2023 and request NRCs review be completed by October 9, 2023. | The licensee indicated that it plans to propose alternative testing, under 10 CFR 50.55a(z)(1), to certain ASME OM Code testing requirements for the valve. The licensee indicated that its proposed alternative will also include a discussion of hardship that could be considered under 10 CFR 50.55a(z)(2). The licensees proposed alternative would be to supplement the 2013 proposed alternative by adding valve V251130 to the list of affected components. The licensee plans to submit the request in August 2023 and request NRCs review be completed by October 9, 2023. | ||
The NRC staff indicated that it might be more direct to submit a new alternative rather than supplementing the 2013 submittal. The staff also discussed that, for proposed alternatives, it typically reviews the most recent test and the testing history of the affected components, 1 | |||
The meeting notice and agenda, dated August 9, 2023, are available in NRCs Agencywide Documents Access and Management System at ML23221A161. | The NRC staff indicated that it might be more direct to submit a new alternative rather than supplementing the 2013 submittal. The staff also discussed that, for proposed alternatives, it typically reviews the most recent test and the testing history of the affected components, | ||
1 The meeting notice and agenda, dated August 9, 2023, are available in NRCs Agencywide Documents Access and Management System at ML23221A161. | |||
2 The licensees request, dated December 12, 2013, is available at ML13347B233 (Attachment 7). | 2 The licensees request, dated December 12, 2013, is available at ML13347B233 (Attachment 7). | ||
NRCs approval of the request, dated May 22, 2014, is available at ML14122A197. | NRCs approval of the request, dated May 22, 2014, is available at ML14122A197. | ||
E. Casulli | |||
relevant information about any sister valves (e.g., the Unit 1 valve), leakage test information, and any specific challenges that the licensee would encounter if it were to perform the required ASME OM Code test. The staff noted that it will consider the licensees alternative request under either 10 CFR 50.55a(z)(1) or (z)(2) depending on the specific information provided by the licensee and the results of the staffs review. | |||
The NRC staff did not make any regulatory decisions at the meeting. No members from the public attended the meeting. The NRC staff did not receive any public meeting feedback forms. | The NRC staff did not make any regulatory decisions at the meeting. No members from the public attended the meeting. The NRC staff did not receive any public meeting feedback forms. | ||
Please direct any inquiries to me at 301-415-0489 or by email to Audrey.Klett@nrc.gov. | Please direct any inquiries to me at 301-415-0489 or by email to Audrey.Klett@nrc.gov. | ||
Sincerely, | Sincerely, | ||
Audrey L. Klett, Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-388 | /RA/ | ||
Audrey L. Klett, Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | |||
Docket No. 50-388 | |||
==Enclosure:== | ==Enclosure:== | ||
List of Attendees | |||
cc: Listserv LIST OF ATTENDEES AT AUGUST 10, 2023, PUBLIC MEETING SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2 | |||
U.S. Nuclear Regulatory Commission Susquehanna Nuclear, LLC Audrey Klett Katie Brown Christopher Highley Jim Hennings Hipo Gonzalez Jerry Lubinsky Mel Gray John Waclawski Nikki Warnek Melissa Krick Sarah Elkhiamy Ron Vazquies Stewart Bailey Theo Edwards Thomas Scarbrough | |||
Enclosure | |||
ML23228A195 OFFICE | ML23228A195 OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DEX/EMIB/BC NAME AKlett KZeleznock SBailey DATE 08/15/2023 08/21/2023 08/15/2023 OFFICE NRR/DORL/LPL1/BC DORL/LPL1/PM NAME HGonzález AKlett DATE 08/21/2023 08/21/2023}} | ||
Latest revision as of 13:56, 13 November 2024
| ML23228A195 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/21/2023 |
| From: | Audrey Klett NRC/NRR/DORL/LPL1 |
| To: | Casulli E NRC/NRR/DORL/LPL1 |
| References | |
| EPID L-2023-LRM-0060 | |
| Download: ML23228A195 (1) | |
Text
August 21, 2023
Mr. Edward Casulli Site Vice President Susquehanna Nuclear, LLC 769 Salem Boulevard NUCSB3 Berwick, PA 18603-0467
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2 -
SUMMARY
OF AUGUST 10, 2023, PUBLIC OBSERVATION MEETING RE: PROPOSED ALTERNATIVE (EPID L-2023-LRM-0060)
Dear Mr. Casulli:
On August 10, 2023, the U.S. Nuclear Regulatory Commission (NRC) staff held a virtual public meeting1 with Susquehanna Nuclear, LLC (the licensee). The purpose of the meeting was to discuss the licensees plans to submit proposed alternative under Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(z) regarding testing requirements for a residual heat removal system valve on Susquehanna Steam Electric Station, Unit 2. The enclosure to this summary contains a list of attendees.
During the meeting, the licensee discussed its plans to submit a proposed alternative to testing requirements in the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) for the Unit 2 residual heat removal system cross-connect check valve V251130, which was installed in 2007. The valve is a 1-inch valve that assists with seating the containments 24-inch main check valve. The licensee discussed that it missed the opportunity to test V251130 during its spring 2023 refueling outage and inadvertently did not include the valve in its proposed alternative 2 submitted in 2013 for the fourth inservice testing program interval. The surveillances grace period expires in October.
The licensee indicated that it plans to propose alternative testing, under 10 CFR 50.55a(z)(1), to certain ASME OM Code testing requirements for the valve. The licensee indicated that its proposed alternative will also include a discussion of hardship that could be considered under 10 CFR 50.55a(z)(2). The licensees proposed alternative would be to supplement the 2013 proposed alternative by adding valve V251130 to the list of affected components. The licensee plans to submit the request in August 2023 and request NRCs review be completed by October 9, 2023.
The NRC staff indicated that it might be more direct to submit a new alternative rather than supplementing the 2013 submittal. The staff also discussed that, for proposed alternatives, it typically reviews the most recent test and the testing history of the affected components,
1 The meeting notice and agenda, dated August 9, 2023, are available in NRCs Agencywide Documents Access and Management System at ML23221A161.
2 The licensees request, dated December 12, 2013, is available at ML13347B233 (Attachment 7).
NRCs approval of the request, dated May 22, 2014, is available at ML14122A197.
E. Casulli
relevant information about any sister valves (e.g., the Unit 1 valve), leakage test information, and any specific challenges that the licensee would encounter if it were to perform the required ASME OM Code test. The staff noted that it will consider the licensees alternative request under either 10 CFR 50.55a(z)(1) or (z)(2) depending on the specific information provided by the licensee and the results of the staffs review.
The NRC staff did not make any regulatory decisions at the meeting. No members from the public attended the meeting. The NRC staff did not receive any public meeting feedback forms.
Please direct any inquiries to me at 301-415-0489 or by email to Audrey.Klett@nrc.gov.
Sincerely,
/RA/
Audrey L. Klett, Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket No. 50-388
Enclosure:
List of Attendees
cc: Listserv LIST OF ATTENDEES AT AUGUST 10, 2023, PUBLIC MEETING SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2
U.S. Nuclear Regulatory Commission Susquehanna Nuclear, LLC Audrey Klett Katie Brown Christopher Highley Jim Hennings Hipo Gonzalez Jerry Lubinsky Mel Gray John Waclawski Nikki Warnek Melissa Krick Sarah Elkhiamy Ron Vazquies Stewart Bailey Theo Edwards Thomas Scarbrough
Enclosure
ML23228A195 OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DEX/EMIB/BC NAME AKlett KZeleznock SBailey DATE 08/15/2023 08/21/2023 08/15/2023 OFFICE NRR/DORL/LPL1/BC DORL/LPL1/PM NAME HGonzález AKlett DATE 08/21/2023 08/21/2023