ML101610025: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (StriderTol Bot change) |
||
(5 intermediate revisions by the same user not shown) | |||
Line 2: | Line 2: | ||
| number = ML101610025 | | number = ML101610025 | ||
| issue date = 06/15/2010 | | issue date = 06/15/2010 | ||
| title = | | title = Acceptance Review Regarding Emergency Diesel Generator Allowed Outage Time Extension Amendment Request | ||
| author name = Ennis R | | author name = Ennis R | ||
| author affiliation = NRC/NRR/DORL/LPLI-2 | | author affiliation = NRC/NRR/DORL/LPLI-2 | ||
| addressee name = Joyce T | | addressee name = Joyce T | ||
Line 9: | Line 9: | ||
| docket = 05000354 | | docket = 05000354 | ||
| license number = | | license number = | ||
| contact person = Ennis R | | contact person = Ennis R, NRR/DORL, 415-1420 | ||
| case reference number = TAC ME3597 | | case reference number = TAC ME3597 | ||
| document type = Letter | | document type = Letter | ||
Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 June 15, 2010 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear P.O. Box 236, 1\109 Hancocks Bridge, NJ 08038 HOPE CREEK GEI\IERATING STATION -ACCEPTANCE REVIEW REGARDING EMERGENCY DIESEL GENERATOR ALLOWED OUTAGE TIME EXTENSION AMENDMENT REQUEST (TAC NO. ME3597) | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 15, 2010 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear P.O. Box 236, 1\109 Hancocks Bridge, NJ 08038 | ||
==SUBJECT:== | |||
HOPE CREEK GEI\IERATING STATION - ACCEPTANCE REVIEW REGARDING EMERGENCY DIESEL GENERATOR ALLOWED OUTAGE TIME EXTENSION AMENDMENT REQUEST (TAC NO. ME3597) | |||
==Dear Mr. Joyce:== | ==Dear Mr. Joyce:== | ||
By letter dated March 29, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. | |||
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. | By letter dated March 29, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100900458), PSEG Nuclear LLC (PSEG) submitted a license amendment request for Hope Creek Generating Station (HCGS). The proposed amendment would revise the HCGS Technical Specifications to extend the Allowed Outage Time for the "A" and "B" Emergency Diesel Generators from [[estimated NRC review hours::72 hours]] to 14 days. 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 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. By letter dated May 4,2010 (ADAMS Accession No. | Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), 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. | ||
T. Joyce - | This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. | ||
Sincerely, Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354 cc: Distribution via Listserv T.Joyce - | By letter dated May 4,2010 (ADAMS Accession No. ML101200075), the NRC staff notified PSEG of specific supplemental information that needed to be submitted to enable the staff to begin its detailed technical review. By letter dated May 28, 2010 (ADAMS Accession No. ML101590514), PSEG provided the supplemental information. | ||
Sincerely, /raJ Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354 cc: Distribution via Listserv DISTRIBUTION PUBLIC RidsOgcRp Resource | The NRC staff has reviewed the supplemental information and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment request 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. | ||
T. Joyce -2 If you have any questions, please contact me at (301) 415-1420. | |||
Sincerely, Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354 cc: Distribution via Listserv | |||
T. Joyce -2 If you have any questions, please contact me at (301) 415-1420. | |||
Sincerely, | |||
/raJ Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354 cc: Distribution via Listserv DISTRIBUTION PUBLIC RidsOgcRp Resource LPL 1-2 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl1-2 Resource RidsNrrDeEeeb Resource RidsNrrLAABaxter Resource RidsNrrDraApla Resource RidsNrrPMHopeCreek Resource RidsNrrDorl Resource RidsNrrDorlDpr Resource RidsRgn 1MailCenter Resource VGoel, NRR/EEEB AHowe, NRR/APLA ADAM Accession No.: ML101610025 OFFICE LPL 1-2/PM LPL 1-2/LA LPL1-2/BC NAME REnnis ABaxter HChernoff DATE 6/10/10 6/11/10 6/15/10 OFFICIAL RECORD COpy}} |
Latest revision as of 16:58, 21 March 2020
ML101610025 | |
Person / Time | |
---|---|
Site: | Hope Creek ![]() |
Issue date: | 06/15/2010 |
From: | Richard Ennis Plant Licensing Branch 1 |
To: | Joyce T Public Service Enterprise Group |
Ennis R, NRR/DORL, 415-1420 | |
References | |
TAC ME3597 | |
Download: ML101610025 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 15, 2010 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear P.O. Box 236, 1\109 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK GEI\IERATING STATION - ACCEPTANCE REVIEW REGARDING EMERGENCY DIESEL GENERATOR ALLOWED OUTAGE TIME EXTENSION AMENDMENT REQUEST (TAC NO. ME3597)
Dear Mr. Joyce:
By letter dated March 29, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100900458), PSEG Nuclear LLC (PSEG) submitted a license amendment request for Hope Creek Generating Station (HCGS). The proposed amendment would revise the HCGS Technical Specifications to extend the Allowed Outage Time for the "A" and "B" Emergency Diesel Generators from 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> to 14 days. 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 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.
By letter dated May 4,2010 (ADAMS Accession No. ML101200075), the NRC staff notified PSEG of specific supplemental information that needed to be submitted to enable the staff to begin its detailed technical review. By letter dated May 28, 2010 (ADAMS Accession No. ML101590514), PSEG provided the supplemental information.
The NRC staff has reviewed the supplemental information and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment request 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.
T. Joyce -2 If you have any questions, please contact me at (301) 415-1420.
Sincerely, Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354 cc: Distribution via Listserv
T. Joyce -2 If you have any questions, please contact me at (301) 415-1420.
Sincerely,
/raJ Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354 cc: Distribution via Listserv DISTRIBUTION PUBLIC RidsOgcRp Resource LPL 1-2 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl1-2 Resource RidsNrrDeEeeb Resource RidsNrrLAABaxter Resource RidsNrrDraApla Resource RidsNrrPMHopeCreek Resource RidsNrrDorl Resource RidsNrrDorlDpr Resource RidsRgn 1MailCenter Resource VGoel, NRR/EEEB AHowe, NRR/APLA ADAM Accession No.: ML101610025 OFFICE LPL 1-2/PM LPL 1-2/LA LPL1-2/BC NAME REnnis ABaxter HChernoff DATE 6/10/10 6/11/10 6/15/10 OFFICIAL RECORD COpy