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| | number = ML061280282 | | | number = ML061280282 |
| | issue date = 05/05/2006 | | | issue date = 05/05/2006 |
| | title = Seabrook Unit 1 - Technical Specification Pages Elimination of Monthly Operating Reports and Occupational Radiation Exposure Reports - Technical Specifications Index, 6.0 Administrative Controls | | | title = Technical Specification Pages Elimination of Monthly Operating Reports and Occupational Radiation Exposure Reports - Technical Specifications Index, 6.0 Administrative Controls |
| | author name = Miller G E | | | author name = Miller G |
| | author affiliation = NRC/NRR/ADRO/DORL | | | author affiliation = NRC/NRR/ADRO/DORL |
| | addressee name = Peschel J M, St.Pierre G F | | | addressee name = Peschel J, St.Pierre G |
| | addressee affiliation = Florida Power & Light Energy Seabrook, LLC | | | addressee affiliation = Florida Power & Light Energy Seabrook, LLC |
| | docket = 05000443 | | | docket = 05000443 |
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| =Text= | | =Text= |
| {{#Wiki_filter:INDEX 6.0 ADMINISTRATIVE CONTROLS SECTION PAGE 6A (THIS SPECIFICATION NUMBER IS NOT USED) ............................ | | {{#Wiki_filter:INDEX 6.0 ADMINISTRATIVE CONTROLS SECTION PAGE 6A (THIS SPECIFICATION NUMBER IS NOT USED) . .. .4 6.5 REPORTABLE EVENT ACTION .4........................................................6 6.6 SAFETY LIMIT VIOLATION .6. |
| .. .4 6.5 REPORTABLE EVENT ACTION .4........................................................ | | 6.7 PROCEDURES AND PROGRAMS ......................................... 6-5 6.8 _ REPORTING REQUIREMENTS 6.8.1 ROUTINE REPORTS ................................................ . 11 |
| 6 6.6 SAFETY LIMIT VIOLATION | | . 6.t........ |
| .6.6.7 PROCEDURES AND PROGRAMS ......................................... | | Startup Report _. . .... . ... .......... 6-a Annual Reports... . .. ._ . ..... .*. 6-12 Annual Radiological Environmental Operating Report .6............_._ -13 Annual Radioactive Effluent Release Report . . _.. 63 CORE OPERATING LIMITS REPORT . 6-14 6.8.2 SPECIAL REPORTS .... 6-19 SEABROOK - UNrr I XXV Amendment No. 4, 67 ,r7 3;-,8 4 109 |
| 6-5 6.8 _ REPORTING REQUIREMENTS | |
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| ====6.8.1 ROUTINE====
| | ADMINISTRATIVE CONTROLS The Startup Report shall address each of the tests identified in the Final Safety Analysis Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required In license conditions based on other commitments shall be included in this report. |
| REPORTS 6.t........
| | Startup Reports shall be submitted within: (1)90 days following completion of the Startup Test Program, (2)90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and resumption or commencement of commercial operation), supplementary reports shall be submitted at least every 3 months until all three events have been completed. |
| ................................................
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| ..11 Startup Report ._ ..... .... ..........
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| 6-a Annual Reports...
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| ... ._ ...... .*. 6-12 Annual Radiological Environmental Operating Report .6............_._
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| -13 Annual Radioactive Effluent Release Report .........................................
| |
| ._.. 63 CORE OPERATING LIMITS REPORT .6-14 6.8.2 SPECIAL REPORTS .... 6-19 SEABROOK -UNrr I XXV Amendment No. 4, 6 7 ,r 7 3;-, 8 4 109 ADMINISTRATIVE CONTROLS The Startup Report shall address each of the tests identified in the Final Safety Analysis Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.
| |
| Any corrective actions that were required to obtain satisfactory operation shall also be described. | |
| Any additional specific details required In license conditions based on other commitments shall be included in this report.Startup Reports shall be submitted within: (1) 90 days following completion of the Startup Test Program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. | |
| If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and resumption or commencement of commercial operation), supplementary reports shall be submitted at least every 3 months until all three events have been completed. | |
| ANNUAL REPORTS 6.8.1.2 Annual Reports covering the activities of the station as described below for the previous calendar year shall be submitted prior to March 1 of each year. The Initial report shall be submitted prior to March 1 of the year following initial criticality. | | ANNUAL REPORTS 6.8.1.2 Annual Reports covering the activities of the station as described below for the previous calendar year shall be submitted prior to March 1 of each year. The Initial report shall be submitted prior to March 1 of the year following initial criticality. |
| Reports required on an annual basis shall Include: The results of specific acthivty analyses In which the primary coolant exceeded the limits of Specification 3.4.8. The following Information shall be Included: | | Reports required on an annual basis shall Include: |
| (1) Reactor power history starting 48 hours prior to the first sample In which the limit was exceeded (in graphic and tabular format); (2) Results of the last isotopic analysis for radiolodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radlolodine activity was reduced to less than limit. Each result should include date and time of sampling and the radiolodine concentrations; (3)Clean-up flow history starting 48 hours prior to the first sample in which the limit was exceeded; (4) Graph of the 1-131 concentration (pCVgm) and one other radio-iodine Isotope concentration (pCVgm) as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radlolodine limit.SEABROOK -UNIT 1 6-12 Amendment No. 34, 39, 55, 88, 404109 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.8.1.3 The annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May I of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.8.1.4 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year of operation shall be submitted by May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.6.8.1.5 Deleted SEAB3ROOK | | The results of specific acthivty analyses Inwhich the primary coolant exceeded the limits of Specification 3.4.8. The following Information shall be Included: (1) Reactor power history starting 48 hours prior to the first sample Inwhich the limit was exceeded (in graphic and tabular format); (2) Results of the last isotopic analysis for radiolodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radlolodine activity was reduced to less than limit. Each result should include date and time of sampling and the radiolodine concentrations; (3) |
| -UNrr I 6-13 Amendment No. 34, 404 109}} | | Clean-up flow history starting 48 hours prior to the first sample in which the limit was exceeded; (4) Graph of the 1-131 concentration (pCVgm) and one other radio-iodine Isotope concentration (pCVgm) as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radlolodine limit. |
| | SEABROOK - UNIT 1 6-12 Amendment No. 34, 39, 55, 88, 404109 |
| | |
| | ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.8.1.3 The annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May I of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1)the ODCM and (2)Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50. |
| | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.8.1.4 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year of operation shall be submitted by May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1)consistent with the objectives outlined in the ODCM and PCP and (2)in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50. |
| | 6.8.1.5 Deleted SEAB3ROOK - UNrr I 6-13 Amendment No. 34, 404 109}} |
Letter Sequence Other |
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TAC:MC9303, Changes to Section 5.0, Administrative Controls, Removal of Monthly Operating Report and Occupational Radiation Exposure Report (Open) |
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Category:Technical Specifications
MONTHYEARML24046A0512024-05-0707 May 2024 Issuance of Amendment No. 174 to Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (LTOP) Curves ML24067A2622024-03-0808 March 2024 Issuance of Amendment No. 173 Revise Technical Specification 3/4.8.1 to Allow Replacement of Reserve Auxiliary Transformer (Emergency Circumstances) SBK-L-22024, Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2022-03-0707 March 2022 Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements ML20293A1572020-12-28028 December 2020 Issuance of Amendment No. 167 Reactor Trip System Instrumentation Technical Specification Changes to Implement WCAP-14333 and WCAP-15376 ML19326C4802019-12-0505 December 2019 Issuance of Amendment No. 163 One-Time Change to the Onsite Power Distribution Requirements SBK-L-19104, License Amendment Request 19-02, One-Time Change to the Seabrook Technical Specifications Onsite Power Distribution Requirements2019-10-0303 October 2019 License Amendment Request 19-02, One-Time Change to the Seabrook Technical Specifications Onsite Power Distribution Requirements ML18228A7372018-08-31031 August 2018 Correction Letter for Amendment No. 157 Changes to the Technical Specifications Requirements for DC Batteries (CAC No. MG0046; EPID L-2017-LLA-0289) L-2018-049, Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications2018-05-29029 May 2018 Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications ML15096A2552015-11-0202 November 2015 Issuance of Amendment Regarding License Amendment Request 14-04, Revised Reactor Coolant System Pressure-Temperature Limits Applicable for 44 Effective Full Power Years ML15231A1442015-10-0606 October 2015 Issuance of Amendment No. 150 Regarding Note for Reactor Coolant System Surveillance Requirements SBK-L-15183, LER, Seabrook Station - Technical Specification Special Report Radiation Monitor Inoperable Greater than 7 Days2015-09-25025 September 2015 LER, Seabrook Station - Technical Specification Special Report Radiation Monitor Inoperable Greater than 7 Days ML15096A1312015-07-17017 July 2015 Issuance of Amendment Regarding Changes to Technical Specification 3.3.3.1, Radiation Monitoring for Plant Operations ML15118A6322015-05-18018 May 2015 Issuance of Amendment Regarding License Amendment Request Regarding New Fuel Valut ML15082A2332015-04-24024 April 2015 Issuance of Amendment Regarding Increase Voltage Limit for Diesel Generator Load Rejection Surveillance Requirement ML15058A7062015-04-22022 April 2015 Issuance of Amendment No. 146 Regarding the Cyber Security Plan Implementation Schedule ML14345A2882015-02-0606 February 2015 Issuance of Amendment Regarding Technical Specifications Task Force Traveler-523, Generic Letter 2008-01, Managing Gas Accumulation Using the Consolidated Line Item Improvement Process ML14363A2752015-02-0404 February 2015 Non-Proprietary SE for Issuance of Amendment Regarding License Amendment Request Regarding Fixed Incore Detector System Analysis ML14184A7952014-09-0303 September 2014 Issuance of Amendment Regarding License Amendment Request Regarding Fuel Storage Changes ML13212A0692014-07-24024 July 2014 Issuance of Amendment Regarding the Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program ML14029A4452014-03-0606 March 2014 Issuance of Amendment Regarding License Amendment Request 12-04, Application Regarding Cold Leg Injection Permissive SBK-L-13121, License Amendment Request 13-05, Fixed Incore Detector System Analysis Methodology2013-09-10010 September 2013 License Amendment Request 13-05, Fixed Incore Detector System Analysis Methodology ML1130000632013-04-23023 April 2013 Issuance of Amendment Addition of Action Statement to Limiting Condition for Operation 3.6.5.1, Containment Enclosure Emergency Air Cleanup System SBK-L-13061, Response to December 2012 Request for Additional Information Regarding License Amendment Request 11-04, Changes to Technical Specifications for New and Spent Fuel Storage2013-03-27027 March 2013 Response to December 2012 Request for Additional Information Regarding License Amendment Request 11-04, Changes to Technical Specifications for New and Spent Fuel Storage SBK-L-13030, LAR 13-02 - Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process2013-03-27027 March 2013 LAR 13-02 - Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process SBK-L-12266, Supplement to License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System2013-01-31031 January 2013 Supplement to License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System SBK-L-12235, License Amendment Request 12-06, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process2012-12-20020 December 2012 License Amendment Request 12-06, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process SBK-L-11130, License Amendment Request 11-03, Regarding Containment Spray Nozzles Surveillance Requirement2011-07-14014 July 2011 License Amendment Request 11-03, Regarding Containment Spray Nozzles Surveillance Requirement SBK-L-09196, License Amendment Request to Revise Technical Specification (TS) Sections 6.7.6.k, Steam Generator (SG) Program and TS 6.8.1.7, Steam Generator Tube Inspection Report for One-Time Alternate Repair Criteria2009-09-18018 September 2009 License Amendment Request to Revise Technical Specification (TS) Sections 6.7.6.k, Steam Generator (SG) Program and TS 6.8.1.7, Steam Generator Tube Inspection Report for One-Time Alternate Repair Criteria ML0819102622008-07-30030 July 2008 Technical Specifications, Issuance of Amendment Nuclear Instrumentation Surveillance Requirements ML0812000612008-04-29029 April 2008 Tec Specs to Amendment 118, License No. NPF-086, for Seabrook, Unit 1 ML0804606942008-03-27027 March 2008 Tech Spec Pages for Amendment 117 Setpoint Change for Reactor Trip System Interlock P-9 SBK-L-07142, Correction to License Amendment Request (LAR) 07-02, Application to Revise the Technical Specifications Regarding Control Room Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-10-15015 October 2007 Correction to License Amendment Request (LAR) 07-02, Application to Revise the Technical Specifications Regarding Control Room Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0723901902007-08-23023 August 2007 Tech Spec Pages for Amendment 116 Technical Specification Task Force (TSTF)-449, Steam Generator Tube Integrity. SBK-L-07112, License Amendment Request 07-02, Application to Revise the Technical Specifications Regarding Control Room Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process.2007-07-17017 July 2007 License Amendment Request 07-02, Application to Revise the Technical Specifications Regarding Control Room Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process. ML0708802862007-03-28028 March 2007 Technical Specifications, Issuance of Amendment Regarding TSTF -449 Steam Generator Tube Integrity TAC No. MD0696 ML0704704742007-02-0909 February 2007 Technical Specifications, Issuance of Amendment Mode Change Limitations ML0629902612006-10-17017 October 2006 Tech Spec Pages for Amendment 113 Removal of License Condition 2.G ML0627501812006-09-29029 September 2006 Technical Specifications, Limited Inspection of the Steam Generator Tube Portion within the Tubesheet SBK-L-06157, Response to Request for Additional Information Regarding License Amendment Request 05-08 Limited Inspection of the Steam Generator Tube Portion within the Tubesheet.2006-08-0808 August 2006 Response to Request for Additional Information Regarding License Amendment Request 05-08 Limited Inspection of the Steam Generator Tube Portion within the Tubesheet. SBK-L-06059, License Amendment Request 06-03 Application for Amendment to Technical Specifications for Miscellaneous Changes.2006-08-0707 August 2006 License Amendment Request 06-03 Application for Amendment to Technical Specifications for Miscellaneous Changes. ML0616402492006-06-12012 June 2006 Technical Specification - Correction of Amendment No. 108, Six-Month Extension for the Containment Integrated Leakage Rate Test Interval ML0616402512006-06-0909 June 2006 Tech Spec Page for Emergency Amendment 111 Allowed Outage Time Extension from 7 Days to 14 Days for Enclosure Air Handling Fan SBK-L-06127, Emergency License Amendment Request 06-07, Containment Enclosure Emergency Air Cleanup System Allowed Outage Time One Time Change2006-06-0707 June 2006 Emergency License Amendment Request 06-07, Containment Enclosure Emergency Air Cleanup System Allowed Outage Time One Time Change ML0614402592006-05-22022 May 2006 Tech Spec Pages for Amendment 110 Regarding Measurement Uncertainty Recapture Power Uprate ML0612802822006-05-0505 May 2006 Technical Specification Pages Elimination of Monthly Operating Reports and Occupational Radiation Exposure Reports - Technical Specifications Index, 6.0 Administrative Controls SBK-L-06065, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process.2006-04-28028 April 2006 Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process. ML0610203542006-04-13013 April 2006 Tech Spec Pages for Correction of Amendment No. 107, Regarding Removal of Requirement to Perform End-of-Life Moderator Temperature Coefficient Measurement (Tac No. MC6566) ML0608601162006-03-24024 March 2006 Technical Specification Page, Revises to Permit a one-time, 6-month, Addition to the currently-approved 5-year Extension to the 10-year Test Interval for the Containment Integrated Leak Rate Test L-2006-042, 30-day Response to NRC Generic Letter 2006-01, Steam Generator Tube Integrity and Associated Technical Specifications, January 20, 20062006-02-17017 February 2006 30-day Response to NRC Generic Letter 2006-01, Steam Generator Tube Integrity and Associated Technical Specifications, January 20, 2006 ML0600904762006-01-0606 January 2006 Tech Spec Page for Amendment 106 Extension of Containment Air Lock Interlock Surveillance Requirement Interval 2024-05-07
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Text
INDEX 6.0 ADMINISTRATIVE CONTROLS SECTION PAGE 6A (THIS SPECIFICATION NUMBER IS NOT USED) . .. .4 6.5 REPORTABLE EVENT ACTION .4........................................................6 6.6 SAFETY LIMIT VIOLATION .6.
6.7 PROCEDURES AND PROGRAMS ......................................... 6-5 6.8 _ REPORTING REQUIREMENTS 6.8.1 ROUTINE REPORTS ................................................ . 11
. 6.t........
Startup Report _. . .... . ... .......... 6-a Annual Reports... . .. ._ . ..... .*. 6-12 Annual Radiological Environmental Operating Report .6............_._ -13 Annual Radioactive Effluent Release Report . . _.. 63 CORE OPERATING LIMITS REPORT . 6-14 6.8.2 SPECIAL REPORTS .... 6-19 SEABROOK - UNrr I XXV Amendment No. 4, 67 ,r7 3;-,8 4 109
ADMINISTRATIVE CONTROLS The Startup Report shall address each of the tests identified in the Final Safety Analysis Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required In license conditions based on other commitments shall be included in this report.
Startup Reports shall be submitted within: (1)90 days following completion of the Startup Test Program, (2)90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and resumption or commencement of commercial operation), supplementary reports shall be submitted at least every 3 months until all three events have been completed.
ANNUAL REPORTS 6.8.1.2 Annual Reports covering the activities of the station as described below for the previous calendar year shall be submitted prior to March 1 of each year. The Initial report shall be submitted prior to March 1 of the year following initial criticality.
Reports required on an annual basis shall Include:
The results of specific acthivty analyses Inwhich the primary coolant exceeded the limits of Specification 3.4.8. The following Information shall be Included: (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample Inwhich the limit was exceeded (in graphic and tabular format); (2) Results of the last isotopic analysis for radiolodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radlolodine activity was reduced to less than limit. Each result should include date and time of sampling and the radiolodine concentrations; (3)
Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the 1-131 concentration (pCVgm) and one other radio-iodine Isotope concentration (pCVgm) as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radlolodine limit.
SEABROOK - UNIT 1 6-12 Amendment No. 34, 39, 55, 88, 404109
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.8.1.3 The annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May I of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1)the ODCM and (2)Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.8.1.4 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year of operation shall be submitted by May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1)consistent with the objectives outlined in the ODCM and PCP and (2)in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.
6.8.1.5 Deleted SEAB3ROOK - UNrr I 6-13 Amendment No. 34, 404 109