ML15036A402: Difference between revisions
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| issue date = 03/03/2015 | | issue date = 03/03/2015 | ||
| title = DAVIS-BESSE Nuclear Power Station, Unit No. 1 - Acceptance Review Concerning Type C Test Intervals (TAC No. MF5433) (L-14-407) | | title = DAVIS-BESSE Nuclear Power Station, Unit No. 1 - Acceptance Review Concerning Type C Test Intervals (TAC No. MF5433) (L-14-407) | ||
| author name = Brown E | | author name = Brown E | ||
| author affiliation = NRC/NRR/DORL/LPLIII-2 | | author affiliation = NRC/NRR/DORL/LPLIII-2 | ||
| addressee name = Lieb R | | addressee name = Lieb R | ||
| addressee affiliation = FirstEnergy Nuclear Operating Co | | addressee affiliation = FirstEnergy Nuclear Operating Co | ||
| docket = 05000346 | | docket = 05000346 | ||
| Line 13: | Line 13: | ||
| document type = Acceptance Review Letter | | document type = Acceptance Review Letter | ||
| page count = 3 | | page count = 3 | ||
| project = TAC:MF5433 | |||
| stage = Acceptance Review | |||
}} | }} | ||
=Text= | |||
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 3, 2015 Mr. Raymond A. Lieb Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-DB-3080 5501 North State, Route 2 Oak Harbor, OH 43449-9760 | |||
==SUBJECT:== | |||
DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 -ACCEPTANCE REVIEW CONCERNING TYPE C TEST INTERVALS (TAC NO. MF5433) | |||
(L-14-407) | |||
==Dear Mr. Lieb:== | |||
By application dated December 19, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14353A349), FirstEnergy Nuclear Operating Company (FENOC, the licensee) submitted a license amendment request for the Davis-Besse Nuclear Power Station, Unit No. 1. The proposed amendment would revise the technical specifications (TS) to adopt performance-based Type C testing for the reactor containment, which would allow for extended test intervals for Type C valves up to 75 months, and corrects an editorial issue in the TS. 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 (10 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. | |||
R. Lieb If you have any questions, please contact Ms. Eva Brown, at (301) 415-2315. | |||
Sincerely, IRA/ | |||
Eva A. Brown, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-346 cc: Distribution via Listserv | |||
ML15036A402 NRR-106 OFFICE LPLll-2/PM LPLI 11-2/LA LPLI 11-2/BC NAME EBrown SRohrer TTate DATE 2/9/15 2/9/15 3/3/15}} | |||
Latest revision as of 17:07, 31 October 2019
| ML15036A402 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 03/03/2015 |
| From: | Ellen Brown Plant Licensing Branch III |
| To: | Lieb R FirstEnergy Nuclear Operating Co |
| Shirley Rohrer, NRR/DORL 415-5411 | |
| References | |
| L-14-407, TAC MF5433 | |
| Download: ML15036A402 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 3, 2015 Mr. Raymond A. Lieb Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-DB-3080 5501 North State, Route 2 Oak Harbor, OH 43449-9760
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 -ACCEPTANCE REVIEW CONCERNING TYPE C TEST INTERVALS (TAC NO. MF5433)
(L-14-407)
Dear Mr. Lieb:
By application dated December 19, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14353A349), FirstEnergy Nuclear Operating Company (FENOC, the licensee) submitted a license amendment request for the Davis-Besse Nuclear Power Station, Unit No. 1. The proposed amendment would revise the technical specifications (TS) to adopt performance-based Type C testing for the reactor containment, which would allow for extended test intervals for Type C valves up to 75 months, and corrects an editorial issue in the TS. 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 (10 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.
R. Lieb If you have any questions, please contact Ms. Eva Brown, at (301) 415-2315.
Sincerely, IRA/
Eva A. Brown, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-346 cc: Distribution via Listserv
ML15036A402 NRR-106 OFFICE LPLll-2/PM LPLI 11-2/LA LPLI 11-2/BC NAME EBrown SRohrer TTate DATE 2/9/15 2/9/15 3/3/15