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| | number = ML17338A272 | | | number = ML17338A272 |
| | issue date = 12/04/2017 | | | issue date = 12/04/2017 |
| | title = 2017/12/04 NRR E-mail Capture - Exelon Fleet Request for Alternative to Revise Main Steam Isolation Valve Testing Frequency (EPID L-2017-LLR-0134) | | | title = NRR E-mail Capture - Exelon Fleet Request for Alternative to Revise Main Steam Isolation Valve Testing Frequency |
| | author name = Purnell B A | | | author name = Purnell B |
| | author affiliation = NRC/NRR/DORL/LPLIII | | | author affiliation = NRC/NRR/DORL/LPLIII |
| | addressee name = Neff D B | | | addressee name = Neff D |
| | addressee affiliation = Exelon Generation Co, LLC | | | addressee affiliation = Exelon Generation Co, LLC |
| | docket = 05000219, 05000220, 05000237, 05000249, 05000254, 05000265, 05000333, 05000373, 05000374, 05000410, 05000461 | | | docket = 05000219, 05000220, 05000237, 05000249, 05000254, 05000265, 05000333, 05000373, 05000374, 05000410, 05000461 |
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| | page count = 3 | | | page count = 3 |
| | project = EPID:L-2017-LLR-0134 | | | project = EPID:L-2017-LLR-0134 |
| | stage = Request | | | stage = Acceptance Review |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:1 NRR-DMPSPEm Resource From:Purnell, Blake Sent: Monday, December 04, 2017 9:41 AM To: Neff, David B:(GenCo-Nuc) | | {{#Wiki_filter:NRR-DMPSPEm Resource From: Purnell, Blake Sent: Monday, December 04, 2017 9:41 AM To: Neff, David B:(GenCo-Nuc) |
| Cc: david.helker@exeloncorp.com; Wrona, David | | Cc: david.helker@exeloncorp.com; Wrona, David |
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| ==Subject:== | | ==Subject:== |
| Exelon Fleet Request for Alternative to Revise Main Steam Isolation Valve Testing Frequency (EPID L-2017-LLR-0134)Mr. Neff: | | Exelon Fleet Request for Alternative to Revise Main Steam Isolation Valve Testing Frequency (EPID L-2017-LLR-0134) |
| | Mr. Neff: |
| | By application dated November 1, 2017 (ADAMS Accession No. ML17306A014), Exelon Generation Company, LLC (the licensee) submitted a request in accordance with Paragraph 50.55a(z)(1) of Title 10 of the Code of Federal Regulations (10 CFR) for a proposed alternative to the requirements of 10 CFR 50.55a and the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants at Clinton Power Station, Unit No. 1; Dresden Nuclear Power Station, Units 2 and 3; James A. FitzPatrick Nuclear Power Plant; LaSalle County Station, Units 1 and 2; Nine Mile Point Nuclear Station, Units 1 and 2; Oyster Creek Nuclear Generating Station; and Quad Cities Nuclear Power Station, Units 1 and 2. The proposed alternative would allow the licensee to eliminate the quarterly partial-stroke exercise testing of the main steam isolation valves for each of these facilities. |
| | The purpose of this email is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this proposed alternative. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. |
| | The NRC staff has reviewed your application and concluded that it provides technical information in sufficient detail to enable the staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed alternative in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review, as compared to the detailed technical review, there may be instances in which issues that impact the staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. |
| | You will be advised of any further information needed to support the staffs detailed technical review by separate correspondence. |
| | Based on the information provided in your submittal, the NRC staff estimates that review of this request will take approximately [[estimated NRC review hours::200 hours]] to complete. The staff expects to complete its review by May 31, 2018. These estimates are based on the staffs initial review of the application and they could change due to several factors, including requests for additional information. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date or significant changes to the forecasted hours, I will inform you of the reason for the change and provide the new estimates. |
| | Sincerely, Blake Purnell, Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 |
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| By application dated November 1, 2017 (ADAMS Accession No. ML17306A014), Exelon Generation Company, LLC (the licensee) submitted a request in accordance with Paragraph 50.55a(z)(1) of Title 10 of the Code of Federal Regulations (10 CFR) for a proposed alternative to the requirements of 10 CFR 50.55a and the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants
| | Docket Nos. 50-461, 50-237, 50-249, 50-333 50-373, 50-374, 50-220, 50-410, 50-219, 50-254, and 50-265 2 |
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| at Clinton Power Station, Unit No. 1; Dresden Nuclear Power Station, Units 2 and 3; James A. FitzPatrick Nuclear Power Plant; LaSalle County Station, Units 1 and 2; Nine Mile Point Nuclear Station, Units 1 and 2; Oyster Creek Nuclear Generating Station; and Quad Cities Nuclear Power Station, Units 1 and 2. The proposed alternative would allow the licensee to eliminate the quarterly partial-stroke exercise testing of the main steam isolation valves for each of these facilities.
| | Hearing Identifier: NRR_DMPS Email Number: 17 Mail Envelope Properties (Blake.Purnell@nrc.gov20171204094100) |
| | |
| The purpose of this email is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this proposed alternative. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to a llow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
| |
| The NRC staff has reviewed your application and concluded t hat it provides technical information in sufficient detail to enable the staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed alternative in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review, as compared to the detailed technical review, there may be instances in which issues that impact the staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.
| |
| | |
| Based on the information provided in your submittal, the NRC staff estimates that review of this request will take approximately 200 hours to complete. The staff expects to complete its review by May 31, 2018. These estimates are based on the staff's initial review of the application and they could change due to several factors, including requests for additional information. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date or significant changes to the forecasted hours, I will inform you of the reason for the change and provide the new estimates.
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| | |
| Sincerely, Blake Purnell, Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission
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| 2Docket Nos. 50-461, 50-237, 50-249, 50-333 50-373, 50-374, 50-220, 50-410, 50-219, 50-254, and 50-265
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| Hearing Identifier: NRR_DMPS Email Number: 17 Mail Envelope Properties (Blake.Purnell@nrc.gov20171204094100) | |
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| ==Subject:== | | ==Subject:== |
| Exelon Fleet Request for Alternative to Revise Main Steam Isolation Valve Testing Frequency (EPID L-2017-LLR-0134) Sent Date: 12/4/2017 9:41:01 AM Received Date: 12/4/2017 9:41:00 AM From: Purnell, Blake Created By: Blake.Purnell@nrc.gov Recipients: "david.helker@exeloncorp.com" <david.helker@exeloncorp.com> Tracking Status: None "Wrona, David" <David.Wrona@nrc.gov> Tracking Status: None "Neff, David B:(GenCo-Nuc)" <david.neff@exeloncorp.com> Tracking Status: None Post Office: Files Size Date & Time MESSAGE 3206 12/4/2017 9:41:00 AM | | Exelon Fleet Request for Alternative to Revise Main Steam Isolation Valve Testing Frequency (EPID L-2017-LLR-0134) |
| | | Sent Date: 12/4/2017 9:41:01 AM Received Date: 12/4/2017 9:41:00 AM From: Purnell, Blake Created By: Blake.Purnell@nrc.gov Recipients: |
| Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:}} | | "david.helker@exeloncorp.com" <david.helker@exeloncorp.com> |
| | Tracking Status: None "Wrona, David" <David.Wrona@nrc.gov> |
| | Tracking Status: None "Neff, David B:(GenCo-Nuc)" <david.neff@exeloncorp.com> |
| | Tracking Status: None Post Office: |
| | Files Size Date & Time MESSAGE 3206 12/4/2017 9:41:00 AM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: |
| | Recipients Received:}} |
Letter Sequence Acceptance Review |
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EPID:L-2017-LLR-0134, County, Nine Mile Point, Oyster Creek, Quad Cities, Submittal of Relief Request for an Alternative to the ASME Code - Revise Main Steam Isolation Valve Partial Stroke Testing Frequency (Withdrawn, Closed) |
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MONTHYEARML17306A0142017-11-0101 November 2017 County, Nine Mile Point, Oyster Creek, Quad Cities, Submittal of Relief Request for an Alternative to the ASME Code - Revise Main Steam Isolation Valve Partial Stroke Testing Frequency Project stage: Request ML17338A2722017-12-0404 December 2017 NRR E-mail Capture - Exelon Fleet Request for Alternative to Revise Main Steam Isolation Valve Testing Frequency Project stage: Acceptance Review ML18058A5232018-03-0101 March 2018 Summary of February 26, 2018, Meeting with Exelon Generation Company, LLC Regarding Proposed Alternative to the Main Steam Isolation Valve Testing Requirements Project stage: Meeting ML18086B2212018-03-27027 March 2018 Withdrawal of Submittal of Relief Request for an Alternative to the ASME Code - Revise Main Steam Isolation Valve Partial Stroke Testing Frequency Project stage: Withdrawal 2017-12-04
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Category:E-Mail
MONTHYEARML24312A1662024-11-0707 November 2024 Request for Additional Information (11/7/2024 E-mail) - LAR to Revise TSs to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3 ML24298A1382024-10-24024 October 2024 Final RAI for FitzPatrick JAFP-24-0047 (L-2024-LLA-0134) ML24271A0282024-09-26026 September 2024 E-Mail - Dresden Nuclear Power Station, Unit 1 - Site Visit Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations ML24254A2082024-09-10010 September 2024 NRR E-mail Capture - Quad Cities, Unit Nos. 1 and 2 - Alternative to RV-08, Rev 1, SRV Testing Interval - Acceptance of Requested Licensing Action Re Relief Request Associated with Safety Relief Valve Testing Interval ML24250A1062024-09-0606 September 2024 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - Proposed Alternative to Utilize Code Case OMN-32 (L-2024-LLR-0030) ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML24234A2772024-08-21021 August 2024 NRR E-mail Capture - Final RAI - Constellation Energy, LLC - Fleet Request - Proposed Alternative Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds (L-2024-LLR-0031) ML24233A2472024-08-20020 August 2024 Acceptance of Requested Licensing Action Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations ML24240A1902024-08-12012 August 2024 E-mail (8/12/2024) from R. Reynolds (CEG) to R. Guzman (NRC) - Corrected TS Pages for LAR TS Design Features Section to Remove the Nine Mile Point Unit 3 Nuclear Project, LLC ML24213A2202024-07-31031 July 2024 Updated Change in Estimated Review Schedule Revision to TS Design Features Section to Remove the Nine Mile Point Unit 3 Nuclear Project, LLC ML24197A0092024-07-15015 July 2024 Acceptance Review Determination for LAR to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling ML24197A0162024-07-12012 July 2024 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - License Amendment Request to Adopt TSTF-591 ML24197A0482024-07-12012 July 2024 Information Request for the Quad Cities Nuclear Station Biennial Problem Identification and Resolution Inspection ML24176A0232024-06-21021 June 2024 NRR E-mail Capture - Dresden Nuclear Power Station, Units 2 and 3 - Acceptance Review of the Amendment Request to Adopt 10 CFR 50.69 ML24159A0122024-06-0606 June 2024 NRR E-mail Capture - Dresden Nuclear Power Station, Units 2 and 3 - Acceptance of Licensing Amendment to Adopt TSTF-505 and TSTF-591 ML24156A1072024-06-0404 June 2024 NRR E-mail Capture - (External_Sender) Supplement for FitzPatrick TS 3.4.2-2 ML24156A0082024-05-31031 May 2024 NRR E-mail Capture - Constellation Energy, LLC - Fleet Request - Acceptance of Proposed Alternative Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds (L-2024-LLR-0031 ML24135A0182024-05-13013 May 2024 NRR E-mail Capture - Draft Request for Additional Information Quad Cities TSTF-505 Amendment ML24131A0612024-05-10010 May 2024 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Proposed Alternative to Utilize Code Case OMN-32 (L-2024-LLR-0030) ML24222A4092024-05-0303 May 2024 NRR E-mail Capture - Request for Additional Information Regarding Reactor Water Cleanup (RWCU) Pump Rooms - L-2023-LLA-0118 ML24122B5072024-05-0101 May 2024 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-591, Revision 0 ML24086A5182024-04-30030 April 2024 E-mail to Christian Williams Decision on the Exemption Request for Quad Cities ML24086A4782024-04-24024 April 2024 Email to Christian Williams Availability of Environmental Assessment for the Quad Cities Exemption ML24114A1702024-04-15015 April 2024 Request for State Review of the Quad Cities HI-STORM Exemption Request Environmental Assessment ML24102A2422024-04-10010 April 2024 NRR E-mail Capture - Draft Request for Additional Information Quad Cities TSTF-505 and 50.69 Amendments ML24066A0802024-04-0101 April 2024 Email to Christian Williams Decision on the Exemption Request for Dresden Nuclear Power Station Unit 2 and Unit 3 Independent Spent Fuel Storage Installation in Morris, Illinois ML24089A0102024-03-29029 March 2024 NRR E-mail Capture - Quad Cities Unit Nos. 1 and 2 - Alternative to Core Spray Pump Testing - Acceptance of Requested Licensing Action Relief Request Associated with the Sixth Inservice Testing Interval ML24065A4892024-03-28028 March 2024 Email to Christian Williams Availability of Environmental Assessment for the Exemption Request for Dresden Nuclear Power Station Unit 2 and Unit 3 Independent Spent Fuel Storage Installation in Morris, Illinois ML24078A3772024-03-15015 March 2024 Email to the State of Illinois Requesting Review of the Dresden Exemption Request Environmental Assessment ML24066A1532024-03-0606 March 2024 NRR E-mail Capture - Request for Additional Information TSTF-505, R2, Provide Risk-Informed Extended Completion Times, RITSTF (Risk-Informed Technical Specification Task Force) Initiative 4b and 10 CFR 50.69 License Amendments ML24066A0872024-03-0404 March 2024 NRR E-mail Capture - Dresden 2 and 3 - Request for Additional Information for Alternative Request I5R-22 ML24067A1242024-03-0101 March 2024 Email to Christian Williams: Request for Additional Information Regarding Dresden Relief Request Dated February 23, 2024 ML24065A2922024-02-28028 February 2024 2/28/24 Email from Constellation: Clarifying Information Regarding Dresden Relief Request Dated February 23, 2024 ML24060A0512024-02-28028 February 2024 NRR E-mail Capture - FitzPatrick - Final Arcb RAI Regarding Amendment to Update the Fuel Handling Accident Analysis ML24064A1222024-02-0606 February 2024 Biennial Problem and Identification Inspection Request for Information ML24033A0542024-02-0101 February 2024 NRR E-mail Capture - FitzPatrick - Final HFE RAI Regarding Amendment to Update the Fuel Handling Accident Analysis ML24024A1372024-01-24024 January 2024 NRR E-mail Capture - Final Snsb RAI Regarding FitzPatrick Amendment to Modify Safety Relief Valves Setpoint Lower Tolerance ML24017A1112024-01-17017 January 2024 NRR E-mail Capture - Acceptance of Requested Licensing Action Amendment Request to Adopt TSTF-529, Clarifyuse and Applicaion Rules, Revision 4 ML24008A0592024-01-0808 January 2024 E-mail Dated 1-8-2024 from R. Guzman to R. Reynolds Correct TS Page 204 for License Amendment No. 250 Adoption of TSTF-505 ML24008A2622024-01-0808 January 2024 Acceptance Review Determination for Relief Request I5R-12, Concerning Installation of a FSWOL on RPV Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld ML23363A0302023-12-29029 December 2023 NRR E-mail Capture - Preliminary RAIs for Clinton Partial Site Release ML23349A0362023-12-14014 December 2023 NRR E-mail Capture - Draft Request for Additional Information Re Quad Cities Emergency Amendment Related to Unit 1 Diesel Generator Inoperability ML23338A0402023-12-0404 December 2023 NRR E-mail Capture - Ready for Clean TS Pages and Updated Review Hours for Clinton Power Station, Unit 1, Request for License Amendment to Revise Technical Specifications Section 3.8.3 ML23339A0882023-12-0404 December 2023 NRR E-mail Capture - NRC Acceptance Review Re Dresden, Units 2 and 3 Request for Relief I5R-22 ML23328A0132023-11-22022 November 2023 Supplement - Security Rule Exemption Request – ISFSI Docket No. Reference (L-2023-LLE-0028) ML23328A0092023-11-22022 November 2023 Supplement - Dresden Security Rule Exemption Request – ISFSI Docket No. Reference (EPID L-2023-LLE-0031) (Email) ML23338A1192023-11-21021 November 2023 NRR E-mail Capture - Draft Request for Additional Information Quad Cities Relief Request I5R-26 ML23304A0172023-10-30030 October 2023 NRR E-mail Capture - Final RCI - Constellation Energy Generation, LLC - Dresden 1, 2 & 3 - Exemption from Security Rule (L-2023-LLE-0031) ML23304A0162023-10-30030 October 2023 NRR E-mail Capture - Final RCI - Constellation Energy Generation, LLC - LaSalle 1 & 2 - Exemption from Security Rule (L-2023-LLE-0028) ML23268A0022023-09-22022 September 2023 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-264-A, Revision 0 2024-09-06
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Text
NRR-DMPSPEm Resource From: Purnell, Blake Sent: Monday, December 04, 2017 9:41 AM To: Neff, David B:(GenCo-Nuc)
Cc: david.helker@exeloncorp.com; Wrona, David
Subject:
Exelon Fleet Request for Alternative to Revise Main Steam Isolation Valve Testing Frequency (EPID L-2017-LLR-0134)
Mr. Neff:
By application dated November 1, 2017 (ADAMS Accession No. ML17306A014), Exelon Generation Company, LLC (the licensee) submitted a request in accordance with Paragraph 50.55a(z)(1) of Title 10 of the Code of Federal Regulations (10 CFR) for a proposed alternative to the requirements of 10 CFR 50.55a and the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants at Clinton Power Station, Unit No. 1; Dresden Nuclear Power Station, Units 2 and 3; James A. FitzPatrick Nuclear Power Plant; LaSalle County Station, Units 1 and 2; Nine Mile Point Nuclear Station, Units 1 and 2; Oyster Creek Nuclear Generating Station; and Quad Cities Nuclear Power Station, Units 1 and 2. The proposed alternative would allow the licensee to eliminate the quarterly partial-stroke exercise testing of the main steam isolation valves for each of these facilities.
The purpose of this email is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this proposed alternative. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
The NRC staff has reviewed your application and concluded that it provides technical information in sufficient detail to enable the staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed alternative in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review, as compared to the detailed technical review, there may be instances in which issues that impact the staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review.
You will be advised of any further information needed to support the staffs detailed technical review by separate correspondence.
Based on the information provided in your submittal, the NRC staff estimates that review of this request will take approximately 200 hours8.333 days <br />1.19 weeks <br />0.274 months <br /> to complete. The staff expects to complete its review by May 31, 2018. These estimates are based on the staffs initial review of the application and they could change due to several factors, including requests for additional information. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date or significant changes to the forecasted hours, I will inform you of the reason for the change and provide the new estimates.
Sincerely, Blake Purnell, Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1
Docket Nos. 50-461, 50-237, 50-249, 50-333 50-373, 50-374, 50-220, 50-410, 50-219, 50-254, and 50-265 2
Hearing Identifier: NRR_DMPS Email Number: 17 Mail Envelope Properties (Blake.Purnell@nrc.gov20171204094100)
Subject:
Exelon Fleet Request for Alternative to Revise Main Steam Isolation Valve Testing Frequency (EPID L-2017-LLR-0134)
Sent Date: 12/4/2017 9:41:01 AM Received Date: 12/4/2017 9:41:00 AM From: Purnell, Blake Created By: Blake.Purnell@nrc.gov Recipients:
"david.helker@exeloncorp.com" <david.helker@exeloncorp.com>
Tracking Status: None "Wrona, David" <David.Wrona@nrc.gov>
Tracking Status: None "Neff, David B:(GenCo-Nuc)" <david.neff@exeloncorp.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 3206 12/4/2017 9:41:00 AM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: