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| {{#Wiki_filter:APPENDIX C ADDITIONAL CONDITIONS RENEWED OPERATING LICENSE NO. DPR-59 Amendment Number Additional Conditions 243 Entergy Nuclear Operations, Inc. shall describe snubber operation and surveillance requirements in the Final Safety Analysis Report such that future changes to those requirements will be subject to the provisions of 10 CFR 50.59. | | {{#Wiki_filter:APPENDIX C ADDITIONAL CONDITIONS RENEWED OPERATING LICENSE NO. DPR-59 Amendment Number Additional Conditions 243 Entergy Nuclear Operations, Inc. shall describe snubber operation and surveillance requirements in the Final Safety Analysis Report such that future changes to those requirements will be subject to the provisions of 10 CFR 50.59. |
| 250 Entergy Nuclear Operations, Inc. shall relocate operability and surveillance requirements for logic bus power monitors, core spray sparger differential pressure, and low pressure coolant injection cross-connect valve position instruments to an Entergy-controlled document where future changes to those relocated requirements are controlled under the provisions of 10 CFR 50.59. | | 250 Entergy Nuclear Operations, Inc. shall relocate operability and surveillance requirements for logic bus power monitors, core spray sparger differential pressure, and low pressure coolant injection cross-connect valve position instruments to an Entergy-controlled document where future changes to those relocated requirements are controlled under the provisions of 10 CFR 50.59. |
| 274 Entergy Nuclear Operations, Inc. shall relocate the Technical Specification requirements identified in Table LA - Removal of Details Matrix and Table R - Relocated Specifications to licensee-controlled documents, as described in the application as supplemented on June 12, 2002, and the NRC staffs Safety Evaluation enclosed with Amendment No. 274, dated July 3, 2002. Further, relocations to the updated Final Safety Analysis Report (UFSAR) shall be reflected in the next UFSAR update required by 10 CFR 50.71(e) following implementation of this amendment. | | 274 Entergy Nuclear Operations, Inc. shall relocate the Technical Specification requirements identified in Table LA - Removal of Details Matrix and Table R - Relocated Specifications to licensee-controlled documents, as described in the application as supplemented on June 12, 2002, and the NRC staffs Safety Evaluation enclosed with Amendment No. 274, dated July 3, 2002. Further, relocations to the updated Final Safety Analysis Report (UFSAR) shall be reflected in the next UFSAR update required by 10 CFR 50.71(e) following implementation of this amendment. |
| 289 Control Room Envelope Habitability Upon Implementation of Amendment No. 289, adopting TSTF-448 Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage required by SR 3.7.3.3 in accordance with TS 5.5.14.c.(i), | | 289 Control Room Envelope Habitability Upon Implementation of Amendment No. 289, adopting TSTF-448 Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage required by SR 3.7.3.3 in accordance with TS 5.5.14.c.(i), |
| the assessment of CRE habitability as required by Specification 5.5.14.c.(ii) , and the measurement of CRE pressure as required by Specification 5.5.14.d shall be considered met. Following implementation: | | the assessment of CRE habitability as required by Specification 5.5.14.c.(ii), and the measurement of CRE pressure as required by Specification 5.5.14.d shall be considered met. Following implementation: |
| (a) The first performance of SR 3.7.3.3 in accordance with specification 5.5.14.c(i) shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2 as measured from June 28, 2004, the date of the most recent successful tracer gas test, as stated in Entergy's letter "NRC Generic Letter 2003-01 Control Room Habitability Initial Action Summary Report" (JAFP-04-0159), | | (a) |
| dated September 27, 2004, or within 18 months if the time period since the most recent successful tracer gas test is greater than 6 years. | | The first performance of SR 3.7.3.3 in accordance with specification 5.5.14.c(i) shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2 as measured from June 28, 2004, the date of the most recent successful tracer gas test, as stated in Entergy's letter "NRC Generic Letter 2003-01 Control Room Habitability Initial Action Summary Report" (JAFP-04-0159), |
| | dated September 27, 2004, or within 18 months if the time period since the most recent successful tracer gas test is greater than 6 years. |
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| Appendix C (b) The first performance of the periodic assessment of CRE Habitability Specification 5.5.14.c(ii) shall be within three years, plus the 9-month allowance of SR 3.0.2 as measured from June 28, 2004, the date of the most recent successful tracer gas test, as stated in Entergys letter NRC Generic Letter 2003-01Control Room Habitability Initial Action Summary Report (JAFP-04-0159), dated September 27, 2004, or within 9 months if the time period since the most recent successful tracer gas test is greater than 3 years. | | Appendix C (b) |
| (c) The first performance of the periodic measurement of CRE pressure, Specification 5.5.14.d shall be within 18 months, plus the 138-day allowance of SR 3.0.2 as measured from the date of the most recent successful pressure measurement test or within 138 days if not performed previously.}} | | The first performance of the periodic assessment of CRE Habitability Specification 5.5.14.c(ii) shall be within three years, plus the 9-month allowance of SR 3.0.2 as measured from June 28, 2004, the date of the most recent successful tracer gas test, as stated in Entergys letter NRC Generic Letter 2003-01Control Room Habitability Initial Action Summary Report (JAFP-04-0159), dated September 27, 2004, or within 9 months if the time period since the most recent successful tracer gas test is greater than 3 years. |
| | (c) |
| | The first performance of the periodic measurement of CRE pressure, Specification 5.5.14.d shall be within 18 months, plus the 138-day allowance of SR 3.0.2 as measured from the date of the most recent successful pressure measurement test or within 138 days if not performed previously.}} |
Letter Sequence Other |
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Results
Other: JAFP-06-0109, License Renewal Application, Amendment 10, RAI Responses, JAFP-06-0110, James A.Fitzpatrick, License Renewal Application Drawing List, JAFP-07-0019, License Renewal Application, Amendment 9, JAFP-07-0021, License Renewal Application, Amendment 6, ML062160494, ML062780155, ML062780187, ML063400415, ML070380370, ML070380389, ML070520059, ML070580464, ML071060390, ML071270080, ML071270377, ML071580049, ML071970491, ML072690528, ML072690529, ML080140266, ML080140466, ML080420252, ML081010242, ML081010259, ML081010277, ML081010332
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MONTHYEARJAFP-06-0110, James A.Fitzpatrick, License Renewal Application Drawing List2006-07-31031 July 2006 James A.Fitzpatrick, License Renewal Application Drawing List Project stage: Other ML0621604942006-07-31031 July 2006 License Renewal Application, Cover Page Through Chapter 4 Project stage: Other ML0627801872006-10-23023 October 2006 Memorandum - Audit and Review Plan for Plant Aging Management Reviews and Programs, and Time-Limited Aging Analyses for the James A. Fitzpatrick Power Plant Project stage: Other ML0627801552006-10-23023 October 2006 License Renewal Audit and Review Plan Project stage: Other ML0634004152006-12-0404 December 2006 (PA-LR) AMP Audit Request and Response Items 50 - 417 Project stage: Other ML0700800142007-01-12012 January 2007 Requests for Additional Information Regarding the Review of the License Renewal Application for James A. FitzPatrick Nuclear Power Plant Project stage: RAI ML0701201962007-01-19019 January 2007 Requests for Additional Information Regarding the Review of the License Renewal Application for James A. FitzPatrick Nuclear Power Plant Project stage: RAI ML0703803892007-02-0606 February 2007 JAFNPP AMP and AMR Database Project stage: Other ML0703803702007-02-0707 February 2007 Docketing of Audit Date Base for Aging Management Programs (AMP) and Aging Management Reviews (AMR) Pertaining to License Renewal Application of the James A. Fitzpatrick Nuclear Power Plant Project stage: Other JAFP-07-0021, License Renewal Application, Amendment 62007-02-12012 February 2007 License Renewal Application, Amendment 6 Project stage: Other ML0705200592007-02-20020 February 2007 Note to File: Docketing of Email Pertaining to License Renewal Application of the James A. Fitzpatrick Nuclear Power Plant Project stage: Other ML0703700232007-02-23023 February 2007 Requests for Additional Information Regarding the Review of the License Renewal Application for James A. FitzPatrick Nuclear Power Plant Project stage: RAI ML0713504332007-04-0505 April 2007 JAF-RPT-05-AMM30, Rev 4, Draft, Aging Management Review of Nonsafety-Related Systems and Components Affecting Safety-Related Systems, (FitzPatrick) Project stage: Draft Other JAFP-07-0019, License Renewal Application, Amendment 92007-04-0606 April 2007 License Renewal Application, Amendment 9 Project stage: Other ML0710603902007-04-0606 April 2007 License Renewal Application, Amendment 9 Project stage: Other JAFP-06-0109, License Renewal Application, Amendment 10, RAI Responses2007-04-24024 April 2007 License Renewal Application, Amendment 10, RAI Responses Project stage: Other ML0712700802007-05-0404 May 2007 Docketing of E-mail Pertaining to License Renewal Application of the James A. FitzPatrick Nuclear Power Plant Project stage: Other ML0712703772007-05-0404 May 2007 License Renewal Application Amendment 10 - Added Item (4) Project stage: Other ML0705804642007-05-25025 May 2007 Audit Summary for the JAFNPP LRA Safety Site Audits Project stage: Other ML0715800492007-06-19019 June 2007 Audit Summary Report for Plant Aging Management Reviews and Programs for the James A. FitzPatrick Nuclear Power Plant on License Renewal Application Project stage: Other ML0719704912007-07-10010 July 2007 Docketing of Document Received from the Applicant Pertaining to License Renewal Application of the James A. FitzPatrick Nuclear Power Plant Project stage: Other ML0720102672007-07-25025 July 2007 Request for Additional Information Regarding the Review of the License Renewal Application for James A. FitzPatrick Nuclear Power Plant Project stage: RAI ML0715802992007-07-31031 July 2007 Transmittal of Safety Evaluation Report with Open and Confirmatory Items Related to the License Renewal of James A. FitzPatrick Nuclear Power Plant Project stage: Approval ML0726905292007-09-0505 September 2007 ACRS License Renewal Subcommittee Presentation September 5, 2007 Project stage: Other ML0726905372007-09-0505 September 2007 License Renewal Safety Evaluation Report Staff Presentation to the ACRS Project stage: Approval ML0726905282007-09-26026 September 2007 Docketing of Slides Presentation to ACRS Subcommittee Pertaining to License Renewal Application of the James A. FitzPatrick Nuclear Power Plant Project stage: Other ML0801402662008-02-0808 February 2008 Audit Q&A Database for FitzPatrick Nuclear Plant Aging Mgmt Programs, Aging Mgmt Reviews, and Time-Limited Aging Analyses - Audit Teams Evaluation of the Applicants Responses Project stage: Other ML0801404662008-02-0808 February 2008 Q & a Database - Audit Teams Evaluation Project stage: Other ML0804202522008-02-14014 February 2008 Audit Question and Answer Database for James A. FitzPatrick Nuclear Power Plant Aging Management Programs, Aging Management Reviews, and Time-Limited Aging Analyses - Audit Teams Evaluation of the Applicants Responses Project stage: Other ML0808400482008-03-0606 March 2008 ACRS NRC, Fitzpatrick Lr SER Project stage: Request ML0808400822008-03-0606 March 2008 ACRS Fitzparick Lr Presentation Project stage: Request ML0808000342008-03-24024 March 2008 Docketing of Slides Presentations to ACRS Full Committee Meeting Pertaining to License Renewal Application of the James A. Fitzpatrick Nuclear Power Plant Project stage: Meeting ML0810102592008-09-0808 September 2008 Renewed Facility Operating License No. DPR-59 Project stage: Other ML0810102772008-09-0808 September 2008 Renewed Facility Operating License No. DPR-59 / Appendix C - Additional Conditions Project stage: Other ML0810102422008-09-0808 September 2008 Renewed Facility Operating License No. DPR-59 / Appendix a - Technical Specifications Project stage: Other ML0810103322008-09-0808 September 2008 Renewed Facility Operating License No. DPR-59 / FRN Project stage: Other ML0824903692008-09-0808 September 2008 Issuance of Renewed Facility Operating License No. DPR-59 for James A. Fitzpatrick Nuclear Power Plant Project stage: Approval 2007-04-06
[Table View] |
Text
APPENDIX C ADDITIONAL CONDITIONS RENEWED OPERATING LICENSE NO. DPR-59 Amendment Number Additional Conditions 243 Entergy Nuclear Operations, Inc. shall describe snubber operation and surveillance requirements in the Final Safety Analysis Report such that future changes to those requirements will be subject to the provisions of 10 CFR 50.59.
250 Entergy Nuclear Operations, Inc. shall relocate operability and surveillance requirements for logic bus power monitors, core spray sparger differential pressure, and low pressure coolant injection cross-connect valve position instruments to an Entergy-controlled document where future changes to those relocated requirements are controlled under the provisions of 10 CFR 50.59.
274 Entergy Nuclear Operations, Inc. shall relocate the Technical Specification requirements identified in Table LA - Removal of Details Matrix and Table R - Relocated Specifications to licensee-controlled documents, as described in the application as supplemented on June 12, 2002, and the NRC staffs Safety Evaluation enclosed with Amendment No. 274, dated July 3, 2002. Further, relocations to the updated Final Safety Analysis Report (UFSAR) shall be reflected in the next UFSAR update required by 10 CFR 50.71(e) following implementation of this amendment.
289 Control Room Envelope Habitability Upon Implementation of Amendment No. 289, adopting TSTF-448 Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage required by SR 3.7.3.3 in accordance with TS 5.5.14.c.(i),
the assessment of CRE habitability as required by Specification 5.5.14.c.(ii), and the measurement of CRE pressure as required by Specification 5.5.14.d shall be considered met. Following implementation:
(a)
The first performance of SR 3.7.3.3 in accordance with specification 5.5.14.c(i) shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2 as measured from June 28, 2004, the date of the most recent successful tracer gas test, as stated in Entergy's letter "NRC Generic Letter 2003-01 Control Room Habitability Initial Action Summary Report" (JAFP-04-0159),
dated September 27, 2004, or within 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.
Appendix C (b)
The first performance of the periodic assessment of CRE Habitability Specification 5.5.14.c(ii) shall be within three years, plus the 9-month allowance of SR 3.0.2 as measured from June 28, 2004, the date of the most recent successful tracer gas test, as stated in Entergys letter NRC Generic Letter 2003-01Control Room Habitability Initial Action Summary Report (JAFP-04-0159), dated September 27, 2004, or within 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.
(c)
The first performance of the periodic measurement of CRE pressure, Specification 5.5.14.d shall be within 18 months, plus the 138-day allowance of SR 3.0.2 as measured from the date of the most recent successful pressure measurement test or within 138 days if not performed previously.