ML14072A348: Difference between revisions
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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078 | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 19, 2014 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078 | ||
==SUBJECT:== | ==SUBJECT:== | ||
MCGUIRE NUCLEAR STATION, UNITS 1 AND 2-ACCEPTANCE OF REQUESTED LICENSING ACTION RE: LICENSE AMENDMENT REQUEST FOR TECHNICAL SPECIFICATION 3.4.12, LOW TEMPERATURE OVERPRESSURE PROTECTION SYSTEM (TAC NOS. MF3444 AND MF3445) | MCGUIRE NUCLEAR STATION, UNITS 1 AND 2- ACCEPTANCE OF REQUESTED LICENSING ACTION RE: LICENSE AMENDMENT REQUEST FOR TECHNICAL SPECIFICATION 3.4.12, LOW TEMPERATURE OVERPRESSURE PROTECTION SYSTEM (TAC NOS. MF3444 AND MF3445) | ||
==Dear Mr. Capps:== | ==Dear Mr. Capps:== | ||
By letter dated January 28, 2014, Duke Energy Carolinas, LLC submitted a license amendment request for McGuire Nuclear Station, Units 1 and 2. The proposed amendment revises an error made during McGuire's conversion to standard technical specifications (TSs) in TS 3.4.12. Condition G incorrectly references Condition E. As currently written, TS 3.4.12 Required Actions F.2 and G.1 collectively require that an operable residual heat removal (RHR) suction relief valve be aligned within 1 hour and that a reactor coolant system vent path greater than 2. 75 square inches be established within 8 hours if one of two Power Operated Relief Valves (PORVs) is inoperable in accordance with Condition E. As such, the proposed license amendment request revises Condition G to eliminate the reference to Condition E on the basis that the alignment of an operable RHR relief valve is sufficient to compensate for the loss of one PORV. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this proposed license 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 Title 10 of the Code of Federal Regulations (1 0 CFR) 50.90, an amendment to the license (including the technical specifications) 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. | By letter dated January 28, 2014, Duke Energy Carolinas, LLC submitted a license amendment request for McGuire Nuclear Station, Units 1 and 2. The proposed amendment revises an error made during McGuire's conversion to standard technical specifications (TSs) in TS 3.4.12. | ||
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. | Condition G incorrectly references Condition E. As currently written, TS 3.4.12 Required Actions F.2 and G.1 collectively require that an operable residual heat removal (RHR) suction relief valve be aligned within 1 hour and that a reactor coolant system vent path greater than | ||
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. | : 2. 75 square inches be established within 8 hours if one of two Power Operated Relief Valves (PORVs) is inoperable in accordance with Condition E. As such, the proposed license amendment request revises Condition G to eliminate the reference to Condition E on the basis that the alignment of an operable RHR relief valve is sufficient to compensate for the loss of one PORV. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this proposed license amendment request. | ||
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 S. Capps acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. | 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 Title 10 of the Code of Federal Regulations (1 0 CFR) 50.90, an amendment to the license (including the technical specifications) 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 | |||
S. Capps 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 the McGuire Project Manager, Jason Paige, at (301) 415-5888. | If you have any questions, please contact the McGuire Project Manager, Jason Paige, at (301) 415-5888. | ||
i Si~cerely, | |||
! \ \ ' Jc:tson C. Paige, Project Manager Plant Licensing Branch 2-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | ! | ||
\ | |||
Docket Nos. 50-369 and 50-370 cc: Distribution via Listserv | \' | ||
Jc:tson C. Paige, Project Manager Plant Licensing Branch 2-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370 cc: Distribution via Listserv | |||
ML14072A348 OFFICE DORLILPL2-1/PM DORLILPL2-2/LA DORLILPL2-1/BC DORLILPL2-1/PM NAME JPaige SFigueroa RPascarelli JPaige DATE 12/18/14 3/18/14 3/19/14 3/19/14}} | |||
Revision as of 06:54, 4 November 2019
| ML14072A348 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 03/19/2014 |
| From: | Jason Paige Plant Licensing Branch II |
| To: | Capps S Duke Energy Carolinas |
| Paige J | |
| References | |
| TAC MF3444, TAC MF3445 | |
| Download: ML14072A348 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 19, 2014 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078
SUBJECT:
MCGUIRE NUCLEAR STATION, UNITS 1 AND 2- ACCEPTANCE OF REQUESTED LICENSING ACTION RE: LICENSE AMENDMENT REQUEST FOR TECHNICAL SPECIFICATION 3.4.12, LOW TEMPERATURE OVERPRESSURE PROTECTION SYSTEM (TAC NOS. MF3444 AND MF3445)
Dear Mr. Capps:
By letter dated January 28, 2014, Duke Energy Carolinas, LLC submitted a license amendment request for McGuire Nuclear Station, Units 1 and 2. The proposed amendment revises an error made during McGuire's conversion to standard technical specifications (TSs) in TS 3.4.12.
Condition G incorrectly references Condition E. As currently written, TS 3.4.12 Required Actions F.2 and G.1 collectively require that an operable residual heat removal (RHR) suction relief valve be aligned within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and that a reactor coolant system vent path greater than
- 2. 75 square inches be established within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> if one of two Power Operated Relief Valves (PORVs) is inoperable in accordance with Condition E. As such, the proposed license amendment request revises Condition G to eliminate the reference to Condition E on the basis that the alignment of an operable RHR relief valve is sufficient to compensate for the loss of one PORV. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this proposed license 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 Title 10 of the Code of Federal Regulations (1 0 CFR) 50.90, an amendment to the license (including the technical specifications) 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
S. Capps 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 the McGuire Project Manager, Jason Paige, at (301) 415-5888.
i Si~cerely,
!
\
\'
Jc:tson C. Paige, Project Manager Plant Licensing Branch 2-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370 cc: Distribution via Listserv
ML14072A348 OFFICE DORLILPL2-1/PM DORLILPL2-2/LA DORLILPL2-1/BC DORLILPL2-1/PM NAME JPaige SFigueroa RPascarelli JPaige DATE 12/18/14 3/18/14 3/19/14 3/19/14