|
|
| (4 intermediate revisions by the same user not shown) |
| Line 2: |
Line 2: |
| | number = ML103400189 | | | number = ML103400189 |
| | issue date = 12/14/2010 | | | issue date = 12/14/2010 |
| | title = Fort Calhoun Station, Unit 1 - Acceptance Following Review of Supplemental Information, License Amendment Request to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications (TA | | | title = Acceptance Following Review of Supplemental Information, License Amendment Request to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications |
| | author name = Wilkins L E | | | author name = Wilkins L |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = Bannister D J | | | addressee name = Bannister D |
| | addressee affiliation = Omaha Public Power District | | | addressee affiliation = Omaha Public Power District |
| | docket = 05000285 | | | docket = 05000285 |
| Line 14: |
Line 14: |
| | page count = 3 | | | page count = 3 |
| | project = TAC:ME4542 | | | project = TAC:ME4542 |
| | stage = Supplement | | | stage = Approval |
| }} | | }} |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 December 14, 2010 Mr. David J. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 14, 2010 Mr. David J. Bannister Vice President and CNO Omaha Public Power District Fort Calhoun Station 444 South 16th St. Mall Omaha, NE 68102-2247 |
| Bannister Vice President and CNO Omaha Public Power District Fort Calhoun Station 444 South 16th St. Mall Omaha, NE 68102-2247 FORT CALHOUN STATION, UNIT 1 - | | |
| ACCEPTANCE OF REQUESTED LICENSING ACTION RE: AMENDMENT REQUEST (TAC NO. ME4542) | | ==SUBJECT:== |
| | FORT CALHOUN STATION, UNIT 1 - ACCEPTANCE OF REQUESTED LICENSING ACTION RE: AMENDMENT REQUEST (TAC NO. ME4542) |
|
| |
|
| ==Dear Mr. Bannister:== | | ==Dear Mr. Bannister:== |
| By letter dated August 16, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 102290067), Omaha Public Power District (OPPD, or the licensee) submitted a license amendment request for Fort Calhoun Station, Unit 1 (FCS). The proposed amendment would remove the Technical Specification (TS) limiting condition for operation (LCO) 2.15, "Instrumentation and Control Systems," Table 2-5, "Instrumentation Operating Requirements for Other Safety Feature Functions," Items 3, 4, and 5, and the associated Notes a, b, c, and d, for power-operated relief valve (PORV) and pressurizer safety valve (PSV) acoustic position indication and tail pipe temperature from the FCS TSs. The proposed change would also revise the surveillance requirement (SR) for TS 3.1, "Instrumentation and Control," Table 3-3, "Minimum Frequencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls," Items 21, 23, and 24 for PORV Operation and Acoustic Position Indication, Safety Valve Acoustic Position Indication, and PORVISafety Valve Tail Pipe Temperature, respectively. | | |
| By letter dated September 17,2010 (ADAMS Accession No. ML 102580129), the U.S. Nuclear Regulatory Commission (NRC) informed you that additional information was required to enable the NRC staff to 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. | | By letter dated August 16, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102290067), Omaha Public Power District (OPPD, or the licensee) submitted a license amendment request for Fort Calhoun Station, Unit 1 (FCS). The proposed amendment would remove the Technical Specification (TS) limiting condition for operation (LCO) 2.15, "Instrumentation and Control Systems," Table 2-5, "Instrumentation Operating Requirements for Other Safety Feature Functions," Items 3, 4, and 5, and the associated Notes a, b, c, and d, for power-operated relief valve (PORV) and pressurizer safety valve (PSV) acoustic position indication and tail pipe temperature from the FCS TSs. The proposed change would also revise the surveillance requirement (SR) for TS 3.1, "Instrumentation and Control," |
| OPPD supplemented its application by letter dated September 27, 2010 (ADAMS Accession No. ML 102720964). The purpose of this letter is to provide the results of the 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. | | Table 3-3, "Minimum Frequencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls," Items 21, 23, and 24 for PORV Operation and Acoustic Position Indication, Safety Valve Acoustic Position Indication, and PORVISafety Valve Tail Pipe Temperature, respectively. |
| | By letter dated September 17,2010 (ADAMS Accession No. ML102580129), the U.S. Nuclear Regulatory Commission (NRC) informed you that additional information was required to enable the NRC staff to 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. OPPD supplemented its application by letter dated September 27, 2010 (ADAMS Accession No. ML102720964). |
| | The purpose of this letter is to provide the results of the 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. | | 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. |
| D. Bannister -2This 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 as supplemented 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) 415-1377. Lynnea Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 cc: Distribution via Listserv D. Bannister -2This 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 as supplemented 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) 415-1377. | | |
| Sincerely, Ira! Lynnea Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.
| | D. Bannister -2 This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. |
| 50-285 cc: Distribution via Listserv DISTRIBUTION:
| | The NRC staff has reviewed your application as supplemented 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. |
| PUBLIC RidsNrrDssSrxb Resource LPLIV Branch Reading File RidsNrrLA..IBurkhardt Resource RidsAcrsAcnw_MailCTR Resource RidsNrrPMFortCalhoun Resource RidsNrrDirsltsb Resource RidsOgcRp Resource RidsNrrDeEicb Resource RidsRgn4MailCenter Resource RidsNrrDorl Resource PChung, NRRIDE/EICB RidsNrrDorlDpr Resource KBucholtz, NRRIITSB RidsNrrDorlLpl4 Resource ADAMS Accession No. ML 103400189 OFFICE DORULPL4/PM DORULPL4/LA DIRS/ITSB/BC DElEICB/BC DORULPL4/BC DORULPL4/PM NAME LWilkins JBurkhardt RElliott WKemper (ARosenyev for)
| | If you have any questions, please contact me at (301) 415-1377. |
| MMarkley LWilkins DATE 12/811 0 12/6/10 12/13/10 12/13/10 12/14/10 12/14/10 OFFICIAL RECORD}} | | Lynnea Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 cc: Distribution via Listserv |
| | |
| | ML103400189 OFFICE DORULPL4/PM DORULPL4/LA DIRS/ITSB/BC DElEICB/BC DORULPL4/BC DORULPL4/PM WKemper NAME LWilkins JBurkhardt RElliott (ARosenyev for) MMarkley LWilkins DATE 12/811 0 12/6/10 12/13/10 12/13/10 12/14/10 12/14/10}} |
Letter Sequence Approval |
|---|
|
|
MONTHYEARML1015201982010-05-31031 May 2010
Emergency License Amendment Request (Lar), Revision to Technical Specification (TS) 2.15, Table 2-5 Footnote (C) for Safety Valve Acoustic Position Indication
Project stage: Request
LIC-10-0043, Supplement to Emergency License Amendment Request Revision to Technical Specification 2.15, Table 2-5 Note (C) for Safety Valve Acoustic Position Indication2010-06-0101 June 2010
Supplement to Emergency License Amendment Request Revision to Technical Specification 2.15, Table 2-5 Note (C) for Safety Valve Acoustic Position Indication
Project stage: Supplement
LIC-10-0034, License Amendment Request (LAR) Revision to Technical Specification (TS) 2.15, Table 2-5, Item 1 and TS 3.1, Table 3-3, Items 1, 2 and 4 Control Element Assembly Position Indication and Correction of TS 2.10.2(7)c.2010-07-12012 July 2010
License Amendment Request (LAR) Revision to Technical Specification (TS) 2.15, Table 2-5, Item 1 and TS 3.1, Table 3-3, Items 1, 2 and 4 Control Element Assembly Position Indication and Correction of TS 2.10.2(7)c.
Project stage: Request
LIC-10-0053, License Amendment Request (LAR) 10-04, Proposed Changes to Relocate Operating and Surveillance Requirements for the Power Operated Relief Valve and Safety Valve Position and Tail Pipe Temperature Instrumentation2010-08-16016 August 2010
License Amendment Request (LAR) 10-04, Proposed Changes to Relocate Operating and Surveillance Requirements for the Power Operated Relief Valve and Safety Valve Position and Tail Pipe Temperature Instrumentation
Project stage: Request
ML1025801292010-09-17017 September 2010
Supplemental Information Needed for Acceptance of Requested Licensing Action, Amendment to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications
Project stage: Acceptance Review
LIC-10-0085, Supplement to License Amendment Request (LAR) 10-04, Proposed Changes to Relocate Operating and Surveillance Requirements for the Power Operated Relief Valve and Safety Valve Position and Tail Pipe Temperature Instrumentation2010-09-27027 September 2010
Supplement to License Amendment Request (LAR) 10-04, Proposed Changes to Relocate Operating and Surveillance Requirements for the Power Operated Relief Valve and Safety Valve Position and Tail Pipe Temperature Instrumentation
Project stage: Supplement
ML1034001892010-12-14014 December 2010
Acceptance Following Review of Supplemental Information, License Amendment Request to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications
Project stage: Approval
ML1104801342011-02-17017 February 2011
Email, Draft Request for Additional Information, Amendment Request to Revise Updated Safety Analysis Report to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications
Project stage: Draft RAI
ML1104801392011-02-17017 February 2011
Draft Request for Additional Information, Amendment Request to Revise Updated Safety Analysis Report to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications
Project stage: Draft RAI
ML1106301792011-03-0707 March 2011
Request for Additional Information, Amendment Request to Revise Updated Safety Analysis Report to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications
Project stage: RAI
ML1106703782011-03-0808 March 2011
E-mail to Correct Due Date for Response to Request for Additional Information, Amendment to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications
Project stage: RAI
LIC-11-0030, Response to Request for Additional Information License Amendment Request to Relocate Operating & Surveillance Requirements for Power Operated Relief Valve, Safety Valve Position, & Tail Pipe Temperature Instrumentation from Technical Spe2011-04-0606 April 2011
Response to Request for Additional Information License Amendment Request to Relocate Operating & Surveillance Requirements for Power Operated Relief Valve, Safety Valve Position, & Tail Pipe Temperature Instrumentation from Technical Specif
Project stage: Response to RAI
ML1113005282011-05-10010 May 2011
Email, Draft Request for Additional Information, Round 2, Request to Revise Updated Safety Analysis Report to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications
Project stage: Draft RAI
ML1113005392011-05-10010 May 2011
Draft Request for Additional Information, Round 2, Request to Revise Updated Safety Analysis Report to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications
Project stage: Draft RAI
ML1114307242011-05-26026 May 2011
Request for Additional Information, Round 2, Amendment Request to Revise Updated Safety Analysis Report to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications
Project stage: RAI
LIC-11-0067, Response to Second NRC Request for Additional Information License Amendment Request to Relocate Operating & Surveillance Requirements for Power-Operated Relief Valve, Safety Valve Position, & Tail Pipe Temperature Instrumentation from Te2011-06-30030 June 2011
Response to Second NRC Request for Additional Information License Amendment Request to Relocate Operating & Surveillance Requirements for Power-Operated Relief Valve, Safety Valve Position, & Tail Pipe Temperature Instrumentation from Techn
Project stage: Request
ML1126204022011-09-30030 September 2011
Issuance of Amendment No. 268, Revise Updated Safety Analysis Report to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications
Project stage: Approval
2011-02-17
[Table View] |
|
|---|
Category:Acceptance Review Letter
MONTHYEARML22038A6752022-02-10010 February 2022
Acceptance of Omaha Public Power District'S License Amendment Request to Add a License Condition to Include License Termination Plan Requirements
ML21350A0262021-12-16016 December 2021
Acceptance Review of License Amend Req. to Add License Condition to Include License Termination Plan Requirements, Req. for Supplemental Info
ML17041A2382017-02-15015 February 2017
Acceptance Review Letter, Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E to Allow Plant to Reduce Emergency Planning Requirements Consistent with Permanently Defueled Condition
ML16007A3852016-01-15015 January 2016
Acceptance of Requested Licensing Action Following Supplement, Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements
ML15341A2242015-12-15015 December 2015
Supplemental Information Needed for Acceptance of Requested Licensing Action Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements
ML14178B3942014-06-27027 June 2014
NRC Acceptance Review of Fort Calhoun License Amendment Request 14-03
ML13267A1772013-09-24024 September 2013
Acceptance Review Email, License Amendment Request to Revise Updated Safety Analysis Report for Controlling Raw Water Pump Operation and Safety Classification of Components During a Flood
ML13255A0072013-09-11011 September 2013
Exemption Request, Use of Less Restrictive Work Hour Limitations During First 60 Days of Outage, in Lieu of 10 CFR 26.205(d)(7)
ML13249A3182013-09-0606 September 2013
Acceptance Review Email, License Amendment Request to Revise Updated Safety Analysis Report for Westinghouse Plant-Specific Leak-Before-Break Analysis
ML12325A5782012-11-19019 November 2012
Acceptance Review Email, Request for One-Time Exemption from Requirements of 10 CFR 26.205(d)(7) to Allow Less Restrictive Working Hour Limitations to Support Activities for Plant Startup from Current Extended Outage
ML1215800432012-06-0505 June 2012
Acceptance Review Email, Amendment Request to Revise Technical Specification 2.16, River Level, and Establish EAL Classification Criteria for External Flooding Events Under Radiological Emergency Response Plan
ML1210706522012-04-16016 April 2012
Acceptance Review Email, Relocate Technical Specification Limiting Condition for Operation 2.17, Miscellaneous Radioactive Material Sources, and Surveillance Requirement 3.13 to Updated Safety Analysis Report
ML1208303282012-03-23023 March 2012
Email License Amendment Request to Revise Technical Specification 2.15 to Establish Limiting Condition for Operation Requirements for Reactor Protective System Actuation Circuits
ML1203802312012-02-0707 February 2012
Acceptance Review Email, License Amendment Request to Incorporate New Radial Peaking Factor Definition and Clarify Limiting Condition for Operation (LCO) 2.10.2(6)
ML1136300832011-12-29029 December 2011
Acceptance Review Email, License Amendment Request to Adopt National Fire Protection Standard NFPA -805 Performance-Based Standard for Fire Protection for Light-Water Reactor Electric Generation Plants,
ML1124501302011-09-0202 September 2011
Unit No.1 - Acceptance Review Email, Exemption Request from the Requirements of Appendix E, Sections IV.F.2.b and C of Section 50, Title 10 of the Code of Federal Regulations
ML1109605292011-04-0606 April 2011
Acceptance Review Email, License Amendment Request, Establish Ultimate Heat Sink LCOs in Technical Specification (TS) 2.16, River Level, and Add Surveillance Requirements to TS 3.2, Equipment and Sampling Tests.
ML1034001892010-12-14014 December 2010
Acceptance Following Review of Supplemental Information, License Amendment Request to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications
ML1026500132010-09-21021 September 2010
Acceptance Review E-mail, Relief Request RR-12, from Requirements of ASME Code Case N-722 Visual Examination of Reactor Vessel Hot-Leg Nozzle to Safe End Dissimilar Metal Welds for 4th 10-Year Inservice Inspection Interval (ME4541)
ML1023006762010-08-18018 August 2010
Acceptance Review Email, License Amendment Request to Revise License Condition and Approve Cyber Security Plan
ML1022406482010-08-12012 August 2010
Acceptance Review E-mail, LAR Regarding Revision to (1) TS LCO 2.15, Table 2-5, Item 1, (2) TS 3.1, Table 3-3, Items 1, 2, and 4 Control Element Assembly Position Indication and (3) TS LCO 2.10.2(7)c
ML1004707252010-02-16016 February 2010
Acceptance Review Email, Request for Exemption from 10 CFR Part 73 Physical Security Requirements
ML0932402402009-11-20020 November 2009
Acceptance Review Email, Request for Use of Alternate to Depth Sizing Qualification for Volumetric Examinations of Reactor Pressure Vessel Welds
ML0918308972009-07-0202 July 2009
Acceptance Review Email, License Amendment Request, Revise Technical Specification (TS) 2.0.1 and 2.7 for Inoperable System, Subsystem or Component Due to Inoperable Power Source, Deletion of Diesel Generator SR 3.7(1)e
ML0905802252009-02-27027 February 2009
Acceptance Review Email, License Amendment Request to Modify Technical Specifications to Adopt TSTF-511, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26
ML0905407952009-02-23023 February 2009
Acceptance Review Email, License Amendment Request, Modify Technical Specifications to Add Operability and Testing Requirements for Steam .Generator Blowdown Isolation on a Reactor Trip
ML0833301062008-11-26026 November 2008
Acceptance Review Email, License Amendment Request to Revise TS 3.6(3), Containment Recirculating Air Cooling and Filtering System and License Conditions Replacement of Cacf System
2022-02-10
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 14, 2010 Mr. David J. Bannister Vice President and CNO Omaha Public Power District Fort Calhoun Station 444 South 16th St. Mall Omaha, NE 68102-2247
SUBJECT:
FORT CALHOUN STATION, UNIT 1 - ACCEPTANCE OF REQUESTED LICENSING ACTION RE: AMENDMENT REQUEST (TAC NO. ME4542)
Dear Mr. Bannister:
By letter dated August 16, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102290067), Omaha Public Power District (OPPD, or the licensee) submitted a license amendment request for Fort Calhoun Station, Unit 1 (FCS). The proposed amendment would remove the Technical Specification (TS) limiting condition for operation (LCO) 2.15, "Instrumentation and Control Systems," Table 2-5, "Instrumentation Operating Requirements for Other Safety Feature Functions," Items 3, 4, and 5, and the associated Notes a, b, c, and d, for power-operated relief valve (PORV) and pressurizer safety valve (PSV) acoustic position indication and tail pipe temperature from the FCS TSs. The proposed change would also revise the surveillance requirement (SR) for TS 3.1, "Instrumentation and Control,"
Table 3-3, "Minimum Frequencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls," Items 21, 23, and 24 for PORV Operation and Acoustic Position Indication, Safety Valve Acoustic Position Indication, and PORVISafety Valve Tail Pipe Temperature, respectively.
By letter dated September 17,2010 (ADAMS Accession No. ML102580129), the U.S. Nuclear Regulatory Commission (NRC) informed you that additional information was required to enable the NRC staff to 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. OPPD supplemented its application by letter dated September 27, 2010 (ADAMS Accession No. ML102720964).
The purpose of this letter is to provide the results of the 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.
D. Bannister -2 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 as supplemented 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) 415-1377.
Lynnea Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 cc: Distribution via Listserv
ML103400189 OFFICE DORULPL4/PM DORULPL4/LA DIRS/ITSB/BC DElEICB/BC DORULPL4/BC DORULPL4/PM WKemper NAME LWilkins JBurkhardt RElliott (ARosenyev for) MMarkley LWilkins DATE 12/811 0 12/6/10 12/13/10 12/13/10 12/14/10 12/14/10
