ML14318A830: Difference between revisions
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| number = ML14318A830 | | number = ML14318A830 | ||
| issue date = 11/18/2014 | | issue date = 11/18/2014 | ||
| title = | | title = Acceptance of Requested Licensing Action License Amendment Request to Modify Reactor Coolant System Pressure Isolation Check Valve Technical Specification Maximum Allowable Leakage Limits | ||
| author name = Lamb J | | author name = Lamb J | ||
| author affiliation = NRC/NRR/DORL/LPLI-2 | | author affiliation = NRC/NRR/DORL/LPLI-2 | ||
| addressee name = Pacilio M | | addressee name = Pacilio M | ||
| addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear | | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear | ||
| docket = 05000289 | | docket = 05000289 | ||
| Line 14: | Line 14: | ||
| page count = 3 | | page count = 3 | ||
| project = TAC:MF5108 | | project = TAC:MF5108 | ||
| stage = Acceptance Review | |||
}} | }} | ||
=Text= | =Text= | ||
{{#Wiki_filter:Michael J. Pacilio Senior Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 18, 2014 Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO) Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUBJECT: THREE MILE ISLAND NUCLEAR STATION, UNIT 1 -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: LICENSE AMENDMENT REQUEST TO MODIFY REACTOR COOLANT SYSTEM PRESSURE ISOLATION CHECK VALVE TECHNICAL SPECIFICATION MAXIMUM ALLOWABLE LEAKAGE LIMITS (TAC NO. MF5108) Dear Mr. Pacilio: By letter dated October 30, 2014, (Agencywide Documents Access and Management System Accession No. | {{#Wiki_filter:Michael J. Pacilio Senior Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 18, 2014 Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO) | ||
}} | Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 | ||
==SUBJECT:== | |||
THREE MILE ISLAND NUCLEAR STATION, UNIT 1 -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: LICENSE AMENDMENT REQUEST TO MODIFY REACTOR COOLANT SYSTEM PRESSURE ISOLATION CHECK VALVE TECHNICAL SPECIFICATION MAXIMUM ALLOWABLE LEAKAGE LIMITS (TAC NO. MF5108) | |||
==Dear Mr. Pacilio:== | |||
By {{letter dated|date=October 30, 2014|text=letter dated October 30, 2014}}, (Agencywide Documents Access and Management System Accession No. ML14304A083), Exelon Generation Company, LLC requested an amendment to Renewed Facility Operating License No. DPR-50 for Three Mile Island Nuclear Station (TMI), | |||
Unit 1. The proposed amendment would modify the Technical Specification (TS) Table 3.1.6.1, "PRESSURE ISOLATION CHECK VALVES BETWEEN THE PRIMARY COOLANT SYSTEM | |||
& LPIS [Low Pressure Injection System]," maximum allowable leakage limits. | |||
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. 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. | |||
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (1 0 CFR), an amendment to the license (including the TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. | |||
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment 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 NRC 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 NRC staff's detailed technical review by separate correspondence. | |||
If you have any questions, please contact me at (301) 415-3100 or via e-mail at John. Lamb@nrc.gov. | |||
Docket No. 50-289 cc: Distribution via Listserv | |||
~Y.~ | |||
Lamb, Senior Project Manager icensing Branch 1-2 n of Operating Reactor Licensing of Nuclear Reactor Regulation | |||
ML14318A830 OFFICE LPL 1-2/PM LPL3-1/LA NAME Jlamb A Baxter DATE 11/17/14 11/17/14 Sincerely, | |||
/RAJ John G. Lamb, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation LPL 1-2/BC LPL 1-2/PM MKhanna Jlamb 11/14/14 11/18/14}} | |||
Latest revision as of 15:49, 10 January 2025
| ML14318A830 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/18/2014 |
| From: | John Lamb Plant Licensing Branch 1 |
| To: | Pacilio M Exelon Generation Co, Exelon Nuclear |
| John Lamb, NRR/DORL 415-3100 | |
| References | |
| TAC MF5108 | |
| Download: ML14318A830 (3) | |
Text
Michael J. Pacilio Senior Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 18, 2014 Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
THREE MILE ISLAND NUCLEAR STATION, UNIT 1 -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: LICENSE AMENDMENT REQUEST TO MODIFY REACTOR COOLANT SYSTEM PRESSURE ISOLATION CHECK VALVE TECHNICAL SPECIFICATION MAXIMUM ALLOWABLE LEAKAGE LIMITS (TAC NO. MF5108)
Dear Mr. Pacilio:
By letter dated October 30, 2014, (Agencywide Documents Access and Management System Accession No. ML14304A083), Exelon Generation Company, LLC requested an amendment to Renewed Facility Operating License No. DPR-50 for Three Mile Island Nuclear Station (TMI),
Unit 1. The proposed amendment would modify the Technical Specification (TS) Table 3.1.6.1, "PRESSURE ISOLATION CHECK VALVES BETWEEN THE PRIMARY COOLANT SYSTEM
& LPIS [Low Pressure Injection System]," maximum allowable leakage limits.
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. 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.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (1 0 CFR), an amendment to the license (including the TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment 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 NRC 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 NRC staff's detailed technical review by separate correspondence.
If you have any questions, please contact me at (301) 415-3100 or via e-mail at John. Lamb@nrc.gov.
Docket No. 50-289 cc: Distribution via Listserv
~Y.~
Lamb, Senior Project Manager icensing Branch 1-2 n of Operating Reactor Licensing of Nuclear Reactor Regulation
ML14318A830 OFFICE LPL 1-2/PM LPL3-1/LA NAME Jlamb A Baxter DATE 11/17/14 11/17/14 Sincerely,
/RAJ John G. Lamb, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation LPL 1-2/BC LPL 1-2/PM MKhanna Jlamb 11/14/14 11/18/14