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| {{#Wiki_filter:3 ENCLOSUR TO SERIAL: NLS-93-024 Page 1 of 1 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO.50-400/LICENSE NO.NPF-63 REQUEST, FOR LICENSE AMENDMENT TRAINING PAGE CHANGE INSTRUCTIONS Removed Pa e 6-7 Inserted Pa e 6-7 9303i00250 930304 PDR ADOCK"05000400 P , PDR)(1899HHP) | | {{#Wiki_filter:3 ENCLOSUR TO SERIAL: NLS-93-024 Page 1 of 1 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST, FOR LICENSE AMENDMENT TRAINING PAGE CHANGE INSTRUCTIONS Removed Pa e Inserted Pa e 6-7 6-7 9303i00250 930304 PDR ADOCK"05000400 P , PDR ) (1899HHP) |
| ENCLOSU TO SERIAL: NLS-93-024 Page 1 of 1 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO.50-400/LICENSE NO.NPF-63 REQUEST FOR LICENSE AMENDMENT TRAINING TECHNICAL SPECIFICATION PAGES AOMINISTRATIVE CONTROLS 6.4 TRAINING REpLAC6'rTl4 A fTACHe,~ZASTA<<6.4.1 A retrain g and replacement train g program for t unit staff shall be maintained der the.dir ection of t Manager Harr i s aining Unit and sh meet or exce the requirements and commendations of he September 1979 aft of ANS 3.with the exceptions a alternatives no d on FSAR pages 1.8 (Am.20).8-9 (Am.26), 1.8-10.27), 1.8-11 (.27), 1.8-12 (Am.Z , and 1.8-1 (Am.27), and Appendix of 10 CFR Part and the suppleme I require-men specified in Sectio A and C of Enclo re 1 of the March 8, 1980 NRC I ter to all licensees and snail includ amiIiarization w relevant o erational erience.6.5 REVIEW ANO AUOIT 6.5.1 SAFETY ANO TECHNICAL REVIEWS 6.5.1.1 General Pro ram Control 6.5.1.1.1 A safety and a technical evaluation shall be prepared for each of the following: | | |
| a.All procedures and programs required by Specification 6.8, other procedures that affect nuclear safety, and changes thereto;b.All proposed tests and experiments that are not described in the Final Safety Anal'ysis Report;and c.All proposed changes or modifications to plant systems or equipment that affect nuclear safety.6.5.1.2 Technical Evaluations 6.5.1.2.1 Technical evaluations will be performed by personnel qualified in the subject matte~andaiII determine the technical adequacy and accuracy of the proposed activity.If interdisciplinary evaluations are required to cover the technical scope of an activity, they will be performed. | | ENCLOSU TO SERIAL: NLS-93-024 Page 1 of 1 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT TRAINING TECHNICAL SPECIFICATION PAGES |
| 6.5.1.2.2 Technical review personnel will be identified by the responsible Manager or his designee for a specific activity when the review process begins.6.5.1.3 uglified Safe Reviewers 6.5.1.3.1 The Plant General Manager shall designate those individuals who will be responsible f'r performing safety reviews described in Specification 6.5.1.4.SHEARON HARRIS-UNIT L 6-7 | | |
| ~4~e INSERT TO PAGE 6-7 6.4.1 A retraining and replacement training program for the unit staff shall be maintained and shall meet or exceed the requirements and recommendations of the September 1979 draft of ANS 3.1, with the exceptions and alternatives noted in Section 1.8 (Personnel Selection and Training)of the FSAR.The initial and requali,fication training for licensed personnel is through an accredited program based on the systematic approach to training, as allowed by 10 CFR 55.31, 10 CFR 55.59, and Generic Letter 87-07. | | AOMINISTRATIVE CONTROLS |
| ''','" ADMINISTRATIVE CONT 6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained and shall meet or exceed the requirements and recommendations of the September 1979 draft of ANS 3.1, with the exceptions and alternatives noted in Section 1.8 (Personnel Selection and Training)of the FSAR.The initial and requalification training for licensed personnel is through an accredited program based on the systematic approach to training, as allowed by 10 CFR 55.31, 10 CFR 55.59, and Generic Letter 87-07.6.5 REVIEW AND AUDIT 6.5.1 SAFETY AND TECHNICAL REVIEWS 6.5.1.1 General Pro ram Control 6.5.1.1.1 A safety and a technical evaluation shall be prepared for each of the following: | | : 6. 4 TRAINING REpLAC6'rTl4 A fTACHe,~ ZASTA<< |
| a.All procedures and programs required by Specification 6.8, other procedures that affect nuclear safety, and changes thereto;b.All proposed tests and experiments that are not described in the Final Safety Analysis Report;and c.All proposed changes or modifications to plant systems or equipment that affect nuclear safety.6.5.1.2 Technical Evaluations 6.5.1.2.1 Technical evaluations will be performed by personnel qualified in the subject matter and will determine the technical adequacy and accuracy of the proposed activity.If interdisciplinary evaluations are required to cover the technical scope of an activity, they will be performed. | | 6.4.1 A retrain g and replacement train g program for t unit staff shall be maintained der the. dir ection of t Manager Harr i s aining Unit and sh meet or exce the requirements and commendations of he September 1979 aft of ANS 3. with the exceptions a alternatives no d on FSAR pages 1. 8 (Am.20) .8-9 (Am.26), 1.8-10 .27), 1.8-11 ( .27), 1.8-12 (Am.Z , and 1.8-1 (Am. 27), and Appendix of 10 CFR Part and the suppleme I require-men specified in Sectio A and C of Enclo re 1 of the March 8, 1980 NRC I ter to all licensees and snail includ amiIiarization w relevant o erational erience. |
| 6.5.1.2.2 Technical review personnel will be identified by the responsible Manager or his designee for a specific activity when the review process begins.6.5.1.3 uglified Safet Reviewers 6.5.1.3.1 The Plant General Manager shall designate those individuals who will be responsible for performing safety reviews described in Specification 6.5.1.4.SHEARON HARRIS-UNIT 1 6-7 Amendment No. | | 6.5 REVIEW ANO AUOIT 6.5.1 SAFETY ANO TECHNICAL REVIEWS 6.5.1.1 General Pro ram Control 6.5.1. 1.1 A safety and a technical evaluation shall be prepared for each of the following: |
| "~'ll}} | | : a. All procedures and programs required by Specification 6.8, other procedures that affect nuclear safety, and changes thereto; |
| | : b. All proposed tests and experiments that are not described in the Final Safety Anal'ysis Report; and |
| | : c. All proposed changes or modifications to plant systems or equipment that affect nuclear safety. |
| | 6.5.1.2 Technical Evaluations 6.5.1.2.1 Technical evaluations will be performed by personnel qualified in the subject matte~ andaiII determine the technical adequacy and accuracy of the proposed activity. If interdisciplinary evaluations are required to cover the technical scope of an activity, they will be performed. |
| | 6.5.1.2.2 Technical review personnel will be identified by the responsible Manager or his designee for a specific activity when the review process begins. |
| | 6.5.1.3 uglified Safe Reviewers 6.5.1.3.1 The Plant General Manager shall designate those individuals who will be responsible f'r performing safety reviews described in Specification 6.5.1.4. |
| | SHEARON HARRIS - UNIT L 6-7 |
| | |
| | ~ 4 ~ |
| | e INSERT TO PAGE 6-7 6.4.1 A retraining and replacement training program for the unit staff shall be maintained and shall meet or exceed the requirements and recommendations of the September 1979 draft of ANS 3.1, with the exceptions and alternatives noted in Section 1.8 (Personnel Selection and Training) of the FSAR. The initial and requali,fication training for licensed personnel is through an accredited program based on the systematic approach to training, as allowed by 10 CFR 55.31, 10 CFR 55.59, and Generic Letter 87-07. |
| | |
| | '' ','" ADMINISTRATIVE CONT |
| | : 6. 4 TRAINING 6.4. 1 A retraining and replacement training program for the unit staff shall be maintained and shall meet or exceed the requirements and recommendations of the September 1979 draft of ANS 1, with the exceptions and alternatives 3. |
| | noted in Section 1.8 (Personnel Selection and Training) of the FSAR. The initial and requalification training for licensed personnel is through an accredited program based on the systematic approach to training, as allowed by 10 CFR 55.31, 10 CFR 55.59, and Generic Letter 87-07. |
| | 6.5 REVIEW AND AUDIT 6.5.1 SAFETY AND TECHNICAL REVIEWS 6.5. 1. 1 General Pro ram Control 6.5. 1. 1. 1 A safety and a technical evaluation shall be prepared for each of the following: |
| | : a. All procedures and programs required by Specification 6.8, other procedures that affect nuclear safety, and changes thereto; |
| | : b. All proposed tests and experiments that are not described in the Final Safety Analysis Report; and |
| | : c. All proposed changes or modifications to plant systems or equipment that affect nuclear safety. |
| | 6.5. 1.2 Technical Evaluations 6.5. 1.2. 1 Technical evaluations will be performed by personnel qualified in the subject matter and will determine the technical adequacy and accuracy of the proposed activity. If interdisciplinary evaluations are required to cover the technical scope of an activity, they will be performed. |
| | 6.5. 1.2.2 Technical review personnel will be identified by the responsible Manager or his designee for a specific activity when the review process begins. |
| | 6.5. 1.3 uglified Safet Reviewers 6.5. 1.3. 1 The Plant General Manager shall designate those individuals who will be responsible for performing safety reviews described in Specification 6.5. 1.4. |
| | SHEARON HARRIS - UNIT 1 6-7 Amendment No. |
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| | "~ 'll}} |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML18017A9271999-10-21021 October 1999 Proposed Tech Specs Implementing Selected Improvements as Described in GL 93-05 ML18017A8531999-08-26026 August 1999 Proposed Tech Specs Pages,Revising TS 3/4.9.4 to Allow Penetrations Which Provide Direct Access from Containment Atmosphere to Outside Atmosphere to Remain Open During Refueling Operations ML18016B0521999-08-0404 August 1999 Proposed Tech Specs,Incorporating Analytical Methodology in TS 6.9.1.6.2 Which Are Used to Determine Core Operating Limits ML18016B0451999-08-0202 August 1999 Proposed Tech Specs 6.2.2.e Re Operations Mgt License Requirements ML18016B0101999-07-0909 July 1999 Proposed Tech Specs 3/4.2.2,3/4.2.3 & 3/4.2.5,providing Clarification & Reducing Burden of Addl License Amend Process by Implementing Guidance in GL 88-16 & NUREG-1431, Rev 1, Std Ts,W Plants. ML18016B0131999-07-0909 July 1999 Proposed Tech Specs,Relocating 3/4.3.3.3,3/43.3.4,3/4.3.3.9 & 3/4.3.3.11 to Plant Procedure PLP-114, Relocated Tech Specs & Design Basis, IAW GL 95-10 ML18016A9911999-06-15015 June 1999 Proposed Tech Specs Incorporating performance-based 10CFR50,App J,Option B for Type a Tests (Containment Integrated Leakage Rate Tests) ML18016A9781999-06-0202 June 1999 Proposed Tech Specs Revising TS 6.5 & TS 6.8 ML18016A8401999-02-26026 February 1999 Proposed Tech Specs Revising Table Notations for TS Table 3.3-4, ESFAS Instrumentation Trip Setpoints, Specifically Time Constants Utilized in lead-lag Controller for Steam Line Pressure Low (Table Item 1.e.) ML18016A7701998-12-23023 December 1998 Proposed Tech Specs 5.6, Fuel Storage, Increasing Spent Fuel Storage Capacity by Adding Rack Modules to Pools 'C' & 'D.' ML18016A7591998-12-0707 December 1998 Retyped Tech Specs Pages 3/4 6-4 & 3/4 6-4a,incorporating Changes Resulting from Issuance of Amend 84 Re Containment Air Locks ML18016A7561998-12-0707 December 1998 Proposed Retyped Tech Specs Page 3/4 9-13,incorporating Changes Resulting from Issuance of Amend 84 Re SFP Water Level & Revised Fuel Handling Accident Analyses ML18016A7531998-12-0707 December 1998 Proposed Retyped Tech Specs Page 3/4 7-5,incorporating Changes Resulting from Issuance of Amend 77 Re Afs SRs ML18016A6571998-10-28028 October 1998 Corrected TS Pages 6-5 & 6-27 Re 970612 Request for Amend to License NPF-63 Re Proposed Changes to TS 6.0.Original Submittal Contained Editorial Errors ML18016A6261998-10-15015 October 1998 Proposed Tech Specs 3/4.5.1 Re Accumulators & Associated Bases ML18016A6051998-10-0101 October 1998 Proposed Tech Specs 3.0.4 Concerning Applicability of Limiting Conditions for Operation & SR to Be Consistent with GL 87-09 ML18016A5941998-09-23023 September 1998 Proposed Tech Specs 3/4.6.3, Containment Air Locks for Consistency with NUREG-1431,Rev 1 & Clarifying Requirements for Locking Air Lock Door Shut ML18016A5461998-09-0101 September 1998 Proposed Tech Specs Section 3/4.9.11,requiring 23 Feet of Water Above Top of Fuel Rods within Irradiated Fuel Assemblies Seated in Storage Racks ML18016A5381998-08-27027 August 1998 Proposed Tech Specs,Revising Section 6.0, Administrative Controls. ML18016A5411998-08-27027 August 1998 Proposed Tech Specs Re Applicability of LCO & Surveillance Requirements ML18016A5311998-08-24024 August 1998 Proposed Tech Specs Re Use of SG Sleeves Designed by ABB-CE ML18016A4301998-05-15015 May 1998 Revised Proposed TS Pages Which More Closely Reflect Generic TS Wording Contained in Std TS W Plants ML18016A4021998-04-24024 April 1998 Proposed Tech Specs 3/4.3.2,allowing Two Hour Surveillance Interval to Facilitate Testing of 6.9 Kv Emergency Bus Undervoltage Relays ML18016A3881998-04-13013 April 1998 Proposed Tech Specs Bases Section 4.0.2,clarifying Guidance Related to Safety Performing Surveillance Testing at Power ML18016A3481998-03-12012 March 1998 Proposed Tech Specs Deleting SR 4.9.12.d.4 Which Requires Verifying That Filter Cooling Bypass Valve for Fhb EES Is Locked in Balanced Position at Least Once Per 18 Months ML18016A2591997-12-16016 December 1997 Proposed Tech Specs Pages,Revising TS 4.7.1.2.1.a.2.a to Change Differential Pressure & Flow Requirements of Steam turbine-driven AFW Pump to Allow Testing of Pump at Lower Speed than Is Currently Performed ML18016A2241997-10-29029 October 1997 Proposed Tech Specs Revising TS 3/4.8.1, AC Sources - Operating & Associated Bases to Clarify Intent of TS ML18012A8121997-06-12012 June 1997 Proposed Tech Specs 6.0 Amending Administrative Controls. ML18012A7991997-05-23023 May 1997 Proposed Tech Specs,Providing Retyped TS Pages Re Revised Action & Surveillance for ECCS Accumulators ML18012A7861997-05-16016 May 1997 Proposed Tech Specs,Informing That TS 4.6.2.3 a.2 Requires Verification at Least Once Per 31 Days of Cw Flow Rate of Greater than or Equal to 1425 Gpm to Each Containment Fan Cooler ML18012A6361997-04-23023 April 1997 Proposed Tech Specs,Incorporating Enhancements to TS Identified in Plant Review Performed IAW GL 96-01.Changes Affected Specs 4.3.2.1.1.a,4.3.2.1.4.b,4.3.2.1.6.g, 4.3.2.1.10.a,4.3.2.1.10.b & 4.7.3.b.3 ML18012A5811997-03-17017 March 1997 Proposed Tech Specs Surveillances 4.1.2.2c,4.5.2.e, 4.6.2.1c,4.6.2.2.c,4.6.3.2,4.7.1.2.1.b,4.7.3.b & 4.7.4.b to Delete Specific Restrictions in Text of Surveillances ML18022B0041997-03-14014 March 1997 Proposed Tech Specs,Increasing AOT for Refueling Water Storage Tank to Twelve Hs While Performing TS Surveillance 4.4.6.2.2 ML18022B0071997-03-10010 March 1997 Proposed Tech Specs 3/4.5 Re Emergency Core Cooling Systems ML18012A5361997-02-27027 February 1997 Proposed Tech Specs,Amending TS 3/4.4.5, Sgs, & Associated Bases,To Add Sleeve Installation as Alternative to Tube Plugging for Repairing Degraded SG Tubes ML18012A5281997-02-21021 February 1997 Proposed Tech Specs 3.0.5 Re Exception to TS 3.0.1 to Permit Equipment to Be Placed Into Svc in Order to Perform Testing to Demonstrate Operability ML18012A5351997-02-21021 February 1997 Proposed Tech Specs Revising TS 3.3.2 in Action 16 of Table 3.3-3 to Add Specific Time Interval of Six H to Place an Inoperable Channel in Bypassed Condition ML18012A5311997-02-18018 February 1997 Proposed Tech Specs 3/4.7.1, Turbine Cycle Safety Valves. ML18012A5101997-02-13013 February 1997 Proposed Tech Specs 3.2.3 Re Rated Thermal Power ML18012A5011997-02-0606 February 1997 Proposed Tech Specs 3/4.0,adding New Entry 3.0.5 to Provide Specific Guidance for Returning Equipment to Svc Under Adminstrative Control for Sole Purpose of Performing Testing to Demonstrate Operability ML18012A4961997-01-29029 January 1997 Proposed Tech Specs 3/4.0 Re Applicability ML18012A4641997-01-10010 January 1997 Proposed Tech Specs 4.8.1.1.2 Re AC Sources - Operating Surveillance Requirements ML18012A4531996-12-30030 December 1996 Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits ML18012A4161996-10-31031 October 1996 Proposed Tech Specs Re Ultimate Heat Sink Level & Temp ML18012A3981996-10-0808 October 1996 Proposed Tech Specs Bases Change to 3/4.6.1.4 & 3/4.6.1.6 Changing Calculated Peak Pressure for MSLB Event ML18012A3721996-09-18018 September 1996 Proposed Tech Specs 4.8.1.1.2 Re Surveillance Requirements for Diesel Fuel Oil Sys Pressure Testing ML18012A3071996-07-19019 July 1996 Proposed Tech Specs 3/4.6.2,CSS,extending Surveillance Interval for Performance of Air or Smoke Flow Test Through CS Nozzles from Once Every 5 Years to Once Every 10 Years ML18012A2531996-05-31031 May 1996 Proposed Tech Specs,Correcting Location Described for One of Three Triaxial Peak Accelerograph Recorders ML18012A1831996-03-20020 March 1996 Proposed Relocation of TS 3.3.3.2, Movable Incore Detectors & Associated Bases,Consistent w/NUREG-1431 & GL 95-10 ML18012A1441996-02-16016 February 1996 Proposed Tech Specs 4.3.2 Re ESFAS Instrumentation 1999-08-04
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18017A9271999-10-21021 October 1999 Proposed Tech Specs Implementing Selected Improvements as Described in GL 93-05 ML18017A8531999-08-26026 August 1999 Proposed Tech Specs Pages,Revising TS 3/4.9.4 to Allow Penetrations Which Provide Direct Access from Containment Atmosphere to Outside Atmosphere to Remain Open During Refueling Operations ML18016B0521999-08-0404 August 1999 Proposed Tech Specs,Incorporating Analytical Methodology in TS 6.9.1.6.2 Which Are Used to Determine Core Operating Limits ML18016B0451999-08-0202 August 1999 Proposed Tech Specs 6.2.2.e Re Operations Mgt License Requirements ML18016B0101999-07-0909 July 1999 Proposed Tech Specs 3/4.2.2,3/4.2.3 & 3/4.2.5,providing Clarification & Reducing Burden of Addl License Amend Process by Implementing Guidance in GL 88-16 & NUREG-1431, Rev 1, Std Ts,W Plants. ML18016B0131999-07-0909 July 1999 Proposed Tech Specs,Relocating 3/4.3.3.3,3/43.3.4,3/4.3.3.9 & 3/4.3.3.11 to Plant Procedure PLP-114, Relocated Tech Specs & Design Basis, IAW GL 95-10 ML18016A9911999-06-15015 June 1999 Proposed Tech Specs Incorporating performance-based 10CFR50,App J,Option B for Type a Tests (Containment Integrated Leakage Rate Tests) ML18016A9781999-06-0202 June 1999 Proposed Tech Specs Revising TS 6.5 & TS 6.8 ML18016A8401999-02-26026 February 1999 Proposed Tech Specs Revising Table Notations for TS Table 3.3-4, ESFAS Instrumentation Trip Setpoints, Specifically Time Constants Utilized in lead-lag Controller for Steam Line Pressure Low (Table Item 1.e.) ML18016A7701998-12-23023 December 1998 Proposed Tech Specs 5.6, Fuel Storage, Increasing Spent Fuel Storage Capacity by Adding Rack Modules to Pools 'C' & 'D.' ML18016A9341998-12-15015 December 1998 Rev 11 to ODCM, for Shnpp ML18016A7531998-12-0707 December 1998 Proposed Retyped Tech Specs Page 3/4 7-5,incorporating Changes Resulting from Issuance of Amend 77 Re Afs SRs ML18016A7561998-12-0707 December 1998 Proposed Retyped Tech Specs Page 3/4 9-13,incorporating Changes Resulting from Issuance of Amend 84 Re SFP Water Level & Revised Fuel Handling Accident Analyses ML18016A7591998-12-0707 December 1998 Retyped Tech Specs Pages 3/4 6-4 & 3/4 6-4a,incorporating Changes Resulting from Issuance of Amend 84 Re Containment Air Locks ML18016A6571998-10-28028 October 1998 Corrected TS Pages 6-5 & 6-27 Re 970612 Request for Amend to License NPF-63 Re Proposed Changes to TS 6.0.Original Submittal Contained Editorial Errors ML18016A6261998-10-15015 October 1998 Proposed Tech Specs 3/4.5.1 Re Accumulators & Associated Bases ML18016A6051998-10-0101 October 1998 Proposed Tech Specs 3.0.4 Concerning Applicability of Limiting Conditions for Operation & SR to Be Consistent with GL 87-09 ML18016A5941998-09-23023 September 1998 Proposed Tech Specs 3/4.6.3, Containment Air Locks for Consistency with NUREG-1431,Rev 1 & Clarifying Requirements for Locking Air Lock Door Shut ML18016A5461998-09-0101 September 1998 Proposed Tech Specs Section 3/4.9.11,requiring 23 Feet of Water Above Top of Fuel Rods within Irradiated Fuel Assemblies Seated in Storage Racks ML18016A5411998-08-27027 August 1998 Proposed Tech Specs Re Applicability of LCO & Surveillance Requirements ML18016A5381998-08-27027 August 1998 Proposed Tech Specs,Revising Section 6.0, Administrative Controls. ML18016A5311998-08-24024 August 1998 Proposed Tech Specs Re Use of SG Sleeves Designed by ABB-CE ML18016A4301998-05-15015 May 1998 Revised Proposed TS Pages Which More Closely Reflect Generic TS Wording Contained in Std TS W Plants ML18016A4021998-04-24024 April 1998 Proposed Tech Specs 3/4.3.2,allowing Two Hour Surveillance Interval to Facilitate Testing of 6.9 Kv Emergency Bus Undervoltage Relays ML18016A3881998-04-13013 April 1998 Proposed Tech Specs Bases Section 4.0.2,clarifying Guidance Related to Safety Performing Surveillance Testing at Power ML18016A3481998-03-12012 March 1998 Proposed Tech Specs Deleting SR 4.9.12.d.4 Which Requires Verifying That Filter Cooling Bypass Valve for Fhb EES Is Locked in Balanced Position at Least Once Per 18 Months ML18016A3051998-01-29029 January 1998 Rev 0 to HNP-IST-002, Shearon Harris Nuclear Power Plant, IST Program Plan - 2nd Interval. ML18022B0351998-01-26026 January 1998 Rev 0 to Procedure HNP-ISI-002, Shearon Harris Nuclear Power Plant,Isi Program Plan,2nd Interval. ML18016A4131997-12-18018 December 1997 Rev 10 to ODCM for Shearon Harris Nuclear Power Plant. ML18016A2591997-12-16016 December 1997 Proposed Tech Specs Pages,Revising TS 4.7.1.2.1.a.2.a to Change Differential Pressure & Flow Requirements of Steam turbine-driven AFW Pump to Allow Testing of Pump at Lower Speed than Is Currently Performed ML18016A2241997-10-29029 October 1997 Proposed Tech Specs Revising TS 3/4.8.1, AC Sources - Operating & Associated Bases to Clarify Intent of TS ML18012A8121997-06-12012 June 1997 Proposed Tech Specs 6.0 Amending Administrative Controls. ML18012A7991997-05-23023 May 1997 Proposed Tech Specs,Providing Retyped TS Pages Re Revised Action & Surveillance for ECCS Accumulators ML18012A7861997-05-16016 May 1997 Proposed Tech Specs,Informing That TS 4.6.2.3 a.2 Requires Verification at Least Once Per 31 Days of Cw Flow Rate of Greater than or Equal to 1425 Gpm to Each Containment Fan Cooler ML18012A6361997-04-23023 April 1997 Proposed Tech Specs,Incorporating Enhancements to TS Identified in Plant Review Performed IAW GL 96-01.Changes Affected Specs 4.3.2.1.1.a,4.3.2.1.4.b,4.3.2.1.6.g, 4.3.2.1.10.a,4.3.2.1.10.b & 4.7.3.b.3 ML18012A5811997-03-17017 March 1997 Proposed Tech Specs Surveillances 4.1.2.2c,4.5.2.e, 4.6.2.1c,4.6.2.2.c,4.6.3.2,4.7.1.2.1.b,4.7.3.b & 4.7.4.b to Delete Specific Restrictions in Text of Surveillances ML18022B0041997-03-14014 March 1997 Proposed Tech Specs,Increasing AOT for Refueling Water Storage Tank to Twelve Hs While Performing TS Surveillance 4.4.6.2.2 ML18022B0071997-03-10010 March 1997 Proposed Tech Specs 3/4.5 Re Emergency Core Cooling Systems ML18012A5361997-02-27027 February 1997 Proposed Tech Specs,Amending TS 3/4.4.5, Sgs, & Associated Bases,To Add Sleeve Installation as Alternative to Tube Plugging for Repairing Degraded SG Tubes ML18012A5351997-02-21021 February 1997 Proposed Tech Specs Revising TS 3.3.2 in Action 16 of Table 3.3-3 to Add Specific Time Interval of Six H to Place an Inoperable Channel in Bypassed Condition ML18012A5281997-02-21021 February 1997 Proposed Tech Specs 3.0.5 Re Exception to TS 3.0.1 to Permit Equipment to Be Placed Into Svc in Order to Perform Testing to Demonstrate Operability ML18012A5311997-02-18018 February 1997 Proposed Tech Specs 3/4.7.1, Turbine Cycle Safety Valves. ML18012A5101997-02-13013 February 1997 Proposed Tech Specs 3.2.3 Re Rated Thermal Power ML18012A5011997-02-0606 February 1997 Proposed Tech Specs 3/4.0,adding New Entry 3.0.5 to Provide Specific Guidance for Returning Equipment to Svc Under Adminstrative Control for Sole Purpose of Performing Testing to Demonstrate Operability ML18012A4961997-01-29029 January 1997 Proposed Tech Specs 3/4.0 Re Applicability ML18012A4641997-01-10010 January 1997 Proposed Tech Specs 4.8.1.1.2 Re AC Sources - Operating Surveillance Requirements ML18012A4531996-12-30030 December 1996 Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits ML18012A4161996-10-31031 October 1996 Proposed Tech Specs Re Ultimate Heat Sink Level & Temp ML18012A3981996-10-0808 October 1996 Proposed Tech Specs Bases Change to 3/4.6.1.4 & 3/4.6.1.6 Changing Calculated Peak Pressure for MSLB Event ML18012A3721996-09-18018 September 1996 Proposed Tech Specs 4.8.1.1.2 Re Surveillance Requirements for Diesel Fuel Oil Sys Pressure Testing 1999-08-04
[Table view] |
Text
3 ENCLOSUR TO SERIAL: NLS-93-024 Page 1 of 1 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST, FOR LICENSE AMENDMENT TRAINING PAGE CHANGE INSTRUCTIONS Removed Pa e Inserted Pa e 6-7 6-7 9303i00250 930304 PDR ADOCK"05000400 P , PDR ) (1899HHP)
ENCLOSU TO SERIAL: NLS-93-024 Page 1 of 1 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT TRAINING TECHNICAL SPECIFICATION PAGES
AOMINISTRATIVE CONTROLS
- 6. 4 TRAINING REpLAC6'rTl4 A fTACHe,~ ZASTA<<
6.4.1 A retrain g and replacement train g program for t unit staff shall be maintained der the. dir ection of t Manager Harr i s aining Unit and sh meet or exce the requirements and commendations of he September 1979 aft of ANS 3. with the exceptions a alternatives no d on FSAR pages 1. 8 (Am.20) .8-9 (Am.26), 1.8-10 .27), 1.8-11 ( .27), 1.8-12 (Am.Z , and 1.8-1 (Am. 27), and Appendix of 10 CFR Part and the suppleme I require-men specified in Sectio A and C of Enclo re 1 of the March 8, 1980 NRC I ter to all licensees and snail includ amiIiarization w relevant o erational erience.
6.5 REVIEW ANO AUOIT 6.5.1 SAFETY ANO TECHNICAL REVIEWS 6.5.1.1 General Pro ram Control 6.5.1. 1.1 A safety and a technical evaluation shall be prepared for each of the following:
- a. All procedures and programs required by Specification 6.8, other procedures that affect nuclear safety, and changes thereto;
- b. All proposed tests and experiments that are not described in the Final Safety Anal'ysis Report; and
- c. All proposed changes or modifications to plant systems or equipment that affect nuclear safety.
6.5.1.2 Technical Evaluations 6.5.1.2.1 Technical evaluations will be performed by personnel qualified in the subject matte~ andaiII determine the technical adequacy and accuracy of the proposed activity. If interdisciplinary evaluations are required to cover the technical scope of an activity, they will be performed.
6.5.1.2.2 Technical review personnel will be identified by the responsible Manager or his designee for a specific activity when the review process begins.
6.5.1.3 uglified Safe Reviewers 6.5.1.3.1 The Plant General Manager shall designate those individuals who will be responsible f'r performing safety reviews described in Specification 6.5.1.4.
SHEARON HARRIS - UNIT L 6-7
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e INSERT TO PAGE 6-7 6.4.1 A retraining and replacement training program for the unit staff shall be maintained and shall meet or exceed the requirements and recommendations of the September 1979 draft of ANS 3.1, with the exceptions and alternatives noted in Section 1.8 (Personnel Selection and Training) of the FSAR. The initial and requali,fication training for licensed personnel is through an accredited program based on the systematic approach to training, as allowed by 10 CFR 55.31, 10 CFR 55.59, and Generic Letter 87-07.
','" ADMINISTRATIVE CONT
- 6. 4 TRAINING 6.4. 1 A retraining and replacement training program for the unit staff shall be maintained and shall meet or exceed the requirements and recommendations of the September 1979 draft of ANS 1, with the exceptions and alternatives 3.
noted in Section 1.8 (Personnel Selection and Training) of the FSAR. The initial and requalification training for licensed personnel is through an accredited program based on the systematic approach to training, as allowed by 10 CFR 55.31, 10 CFR 55.59, and Generic Letter 87-07.
6.5 REVIEW AND AUDIT 6.5.1 SAFETY AND TECHNICAL REVIEWS 6.5. 1. 1 General Pro ram Control 6.5. 1. 1. 1 A safety and a technical evaluation shall be prepared for each of the following:
- a. All procedures and programs required by Specification 6.8, other procedures that affect nuclear safety, and changes thereto;
- b. All proposed tests and experiments that are not described in the Final Safety Analysis Report; and
- c. All proposed changes or modifications to plant systems or equipment that affect nuclear safety.
6.5. 1.2 Technical Evaluations 6.5. 1.2. 1 Technical evaluations will be performed by personnel qualified in the subject matter and will determine the technical adequacy and accuracy of the proposed activity. If interdisciplinary evaluations are required to cover the technical scope of an activity, they will be performed.
6.5. 1.2.2 Technical review personnel will be identified by the responsible Manager or his designee for a specific activity when the review process begins.
6.5. 1.3 uglified Safet Reviewers 6.5. 1.3. 1 The Plant General Manager shall designate those individuals who will be responsible for performing safety reviews described in Specification 6.5. 1.4.
SHEARON HARRIS - UNIT 1 6-7 Amendment No.
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