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| ~~~~e~e~~~~e~~~~~~~~~~~~~~~~~~ORGANIZATION............................................- | | ~~~~e~e~~~~e~~~~~~~~~~~~~~~~~~ORGANIZATION............................................- |
| &i-OPUS rg C)bib/3cC(g~Proc~e~e e~e~~~~e Y(~'T I~e~~~~e~~~~~~~e e~~~~~~e~~~~6-1 6-1 6-1 6-3 6-4 TABLE 6.2-1 MINIMUM SHIFT CREM CQMPOSITIOH.................... | | &i-OPUS rg C)bib/3cC(g~Proc~e~e e~e~~~~e Y(~'T I~e~~~~e~~~~~~~e e~~~~~~e~~~~6-1 6-1 6-1 6-3 6-4 TABLE 6.2-1 MINIMUM SHIFT CREM CQMPOSITIOH.................... |
| | | 6.2.3 ONSITE NUCLEAR SAF=TY (QNS}UNIT F unc 1on..~~~e~~~e~e~~~~e~~e~~~e e e~e~e~e~~~~~e~C~O~omposs tron....'.................."...'...................... |
| ====6.2.3 ONSITE====
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| NUCLEAR SAF=TY (QNS}UNIT F unc 1on..~~~e~~~e~e~~~~e~~e~~~e e e~e~e~e~~~~~e~C~O~omposs tron....'.................."...'...................... | |
| 6-5 R L esponslbll 1 tl es....................................... | | 6-5 R L esponslbll 1 tl es....................................... |
| -..6-5 Record~~~~~~~~e~~~~e~~e~~~e~ee~e~~~~~e e 6.2.4 SHIrt TeCHHICAL AOVISOR...............,.................... | | -..6-5 Record~~~~~~~~e~~~~e~~e~~~e~ee~e~~~~~e e 6.2.4 SHIrt TeCHHICAL AOVISOR...............,.................... |
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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
IROEX 6.0 AOMIH'I STRATIVE CONTROLS SECTION PAGe.6 1 RESPONSLBIL I Ye~~~~~e e~e~~~~e~e~~e~~~e~~e~e~~~~~e~~~~~~e~e~~6-1 6.2 6.2.1 6 C RC~~2e 2 UNIT oX t AFt~e~~e~~~~~~~e~~~~e e~~~~~~~~e~~~~~e~~e~FIGURE 6.2-1:,:.,::
.:, (D.k(FH.3......FIGURE 6.2-2...,.'::..CD.GRETA.).........
~~~~e~e~~~~e~~~~~~~~~~~~~~~~~~ORGANIZATION............................................-
&i-OPUS rg C)bib/3cC(g~Proc~e~e e~e~~~~e Y(~'T I~e~~~~e~~~~~~~e e~~~~~~e~~~~6-1 6-1 6-1 6-3 6-4 TABLE 6.2-1 MINIMUM SHIFT CREM CQMPOSITIOH....................
6.2.3 ONSITE NUCLEAR SAF=TY (QNS}UNIT F unc 1on..~~~e~~~e~e~~~~e~~e~~~e e e~e~e~e~~~~~e~C~O~omposs tron....'.................."...'......................
6-5 R L esponslbll 1 tl es.......................................
-..6-5 Record~~~~~~~~e~~~~e~~e~~~e~ee~e~~~~~e e 6.2.4 SHIrt TeCHHICAL AOVISOR...............,....................
UN i t 5 I AF OUALIF~CA t i ON 6-5 6.<RAINING.~~~~~~e e~\~~~~e~~~~\~~~~6-7 6.5 REYI:"~'NO AUOi T.6.5.1 SAF~~Y AHO TECHNICAL REYIETES General Program Control..6" 7 T h I echnl ca l Eva l Uati ons~~~~~~~~e~~~~~~~~e~~~~~~~~~~~~~~~~~~~6-7 gualified Safety Reviewers..............
~~~~~~~~~~~~~~~e~~6-7 Safety Evaluations and Approval 6.5.2 PLANT NUCLEAR SAFARI Y COMMITTtEE s~~~~~~~~(PHSC}~e~e~~~~~~~~~~~~~.6"8 F unct>on...
~~~~~~~e~~~~~e~~~~~~~~~~~e~~~~~~~~~6-9 C omposltlon.......................
~~~~~~~~~~.~~~~~.~~~~.~~M eetlng Frequency.........--.......
uorum....................................................
6"9 R'L~o~~espons s hs 1 s tl es............
~~~~~~-~~~~~~~~~~~~~~~~~~~~-~~ecords e~~~~~~~~~~~~~~~~~~R e-9 e-U.esoioso~"" 5ooo4oo PDR ADOCK 050oPDR p SHEARON HARRIS-UNIT 1.xviii
'rf rb l 6;1.1 The Plan: General Hanag r shall be respcnsible for cve.aI)un.'t ace.a-tion and shall delegate in writing the suc=essian tc this respcnsibili y du-.ing his absenc.6.1.2 TheShif Foreman (cr, during his absenc f-,m the c"n mi roam, a designated individual) shall be responsible for.the c"nt-.I r"ca ca~and func ticn.A marage en direc=ive ta this eifec->signed by t.".e Vice President-HarHs Huc'.ear P.je shall be reissued tc ail st;an personnel on an annual basis.6.2 QRG~iVIZATiOH
'Rgpiam.mi4 Zmerk ((~ad~))<<~~<<0 Q<<~~ee<<<<~I lv~I I 4~vo~vl ve<<15 e~~<<1<<vv<<eev<<~<<vvv<<eC UVI7 STAFr 6.2.2, The uni crni-ation gang~+~$cOa~~g-shal I bc'-'v~'~~~~v ve ee V~Ve ae Eac.'".an-duty shif shall be composed af at, least the minimum shif c"=csi icn shown in T~Ie 6.2-:;A=Ieas one Iic n ed 0pe.a."".shall be in t".e c"n-.I r~when fuel i in".e r ac="r.In addition, wnile t.".e uni is in,".CQ=" 1, 2,"., cr'4, a-I+as-cne Iic"nsed 6enicr Opera--r shall b in"e c o~<<e<<I rc<<ca~C.An inc vid al q aIified as a Radsa-an C"nt.=i Te'".n;c ar.natl be cn si~when fuei is in t.".r ac="r;d.All C"R~AL>~Ai~QHS shall be observed and d;r ctly supervised by ei~.er a I,icansed 6en;cr Opera"".cr lian ad 6cnicr Qpera"", Liai-d t" F ei Handling whc has nc o-".er c"nc...n-r spcnsib>11ties during t.",is operaticn;
~fY)an cr-gacrah'one rnus~hold P g~r gpr~r.4'cmice.VIt c OP~~'o<s rr)osF hofd.u 9&7lor~~~i~/~V'Ll'@ms<.~~ihe Radiatian C=nt~i Tec.".nician c csi icn may be less than t",e annum~re;ui~n~for a pericd cf time nc t" ax~2 hcu~, in order tc acc"~ace date unaxpec~d absence, pr vided imedia~ac=cn fs taken ta fill the re-quired positions.
6HEARCH HARRIS-UNIT L Insert 1 6.2.1 Onsite and Offsite Or anization An onsite and operation and shall include nuclear power an offsite organization shall be established for unit corporate management.
The onsite'and offsite organization the positions for activities affecting the safety of the plant.Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions.
Those relationships shall be documented and updated, as appropriate, in the form of organizational charts.These organizational charts will be documented in the FSAR and updated in accordance with 10 CFR 50.71(e).b.There shall be an individual executive position (corporate, officer)in the offsite organization having corporate responsibility for overall plant nuclear safety.This individual shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support in the plant so that continued nuclear safety is assured.C.There shall be an individual management position in the onsite organization having responsibility for overall unit safe operation and shall have control over those onsite resources necessary for safe ooeration and maintenance of the plant.Although the individuals wno train the operating staff and those who carry out the quality assurance functions may report to the appropriate manager on site, they shall have sufficient organizational freedom to be independent from operating pressures.
e.Health physics individuals may report to the appropriate manager on site, however, for matters relating to radiological health and safety of employees and the public the health physics manager has direct access to that on site individual having responsibility for overall unit management.
Health physics personnel have the'uthority to cease any work activity when worker safety is jeopardized or in the event of unnecessary personnel radiation exposures.
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LJl oft<n RI Vl.x)ir nnnatittr r tn)t 1l ALI(~to oo~~~~~os~~o~oo h AIL(ILLLIJJL~IJJL ITCDJTl((LC 4H(l JI(I I ALLLA I MI LI III I'fli(IJllfff JI<f~Ill k JL IL~ILJClk l(QA l LAN I fll&WCL I , NIIOIIT 5 f I LVLL tg II JI LOCI A ysisaTII(u C 1 I Ol ALT J I CC4 I W 4.IL>ILJ&1 Ill~IL IIL>I l l II JILL((1 IT'LAAI ILLLL J(Th 11 LL I a JL III TOA 1 fI CLRIJCT hlJP JAIL J i l4 tl JJJI 4 fAOOR J4%IHVa(aallll J (IILOIIAI~l'I IVI14I tsla 4.1 LJI(L~ill(LLIVtl(jllllll Jl.1 II~Il Ill v ILL TILIILJIC1 ALIA'41LLTL Ll I (IA~.JA.IJLLTALIIIN I WlO LAA IM~ILIII JINNI~ooooooooo gf P gTI104AIKW t LIICSNA(llNDtTJLJIWLIK(LJL(lJI o AJACIDA QIJLAIIJIIIKINLT I I JILVA I f 1 I ILLNI Jl klVOAf ILTLAALLJL IL~AVID Jl~ot FICillAE 6.2" 2 Qualified Safe i Reviewe.s (Ccn inuedi C These individuals shall have a baccalaureate degree in an engine ring or related field or equivalent, and 2 years of related expe.ienc.uch desiana-tian shall include the disciplines or proc dur categories far which each indi-vidual is qualified.
guaIified individuals or graucs nat an the plant swf may he relied u cn ta perform safety reviews 1 f sa designated by the Plant Generai Hanager.6.5.1.<Safety Evaluations and Aper vals 6.5.3 4.1 The safety evalua ian prepared in ac""r"ance with Spec fication 6.5.1.1.1 shall include a vri~~n de4rmina icn, wi 0 basis, af whether ar no the proc dures ar chanc s thereto proposed t s4 and exper'.ments and changes the~w and mcdificzt-'ons cons<<itute an unrevised safety ques ian as defined in Paracraoh 0.59 af 19 C."-R Par 5Q, or whether they involve a change ta t".e Final Safety Analysis Repar'he Tec."'.nical Spec-'c=-ticns, ar.e Operating Ll cense>>6.5.1.4.2 The safety evalua-ion shall he pre"ared by a qualified individual.
The safety evaluation shall he reviewed by a second qualified individual..
6.5.1.4.3 A safety evaluation and subsequent review tha c nclude-t",a the s>>" le~ac=;cn may involve an unrevised safety c~esticn, a chance ta the Tec."'.-nicai Scec--cz--'cns cr a~".ance t"~e Qce~:inc License, wiII be referred.".e Plan-Nuclear Safety C"-i=~(PN i".)for~".eir r view in aces-.-'anc wi 0 Seer f-,ca=an 6.5.2.6.Ii the PHSC r c--<<dation is t."'.at an i>>~m is an unr vie~ed safe r qua~ion, a c."'.ance tc~".e Te.".n czI Scar.';ca=.cps, cr a~g ci c'rcn t, e OcnwaT,'f enate t e ac<<cn'wl Ii be ref e~~~~f>>s a ar vaI pT iar t i<<Ipen>>.cn'IKen~.cn Ay ra>>pi c un<<aI a=-r r view bv t.".e C=-.".~:a Nuclear Sa-.e.i Se=:a in ac=a-.=-nc"~--"'.ce;-I Ic<<>>~an 6r<<o<<o>>6-5.~.4.4 I a sa a~evaiua-;on ard suh eq en-r view c"rciuc that"he suc-je~ac=;on does no<<involve an unr viewed safe-y q es-;"n, a change tc t.e Technical Soec:-,cat;on, cr a c."'.area'" t",.e Qperat;ra License,".e ac=-an may be approved by the Plan-General Hanacer cr his designe cr, as appiicahle, by the Hanager of the primary func 4onai ar a affected by the a~;cn.ine individ-ual approving the ac ion shall assure that the reviewers c"Ilec-iveiy possess the background and quali icatian in all af the disciplines nacassary and important to the specific review far both sa.ety and technical aspecw-6.5.I.4.5 A safety evaluation and subsequent review that conclude that the suhjec ac ian involves a change in the Final Safety Analysis Repor>>shall be.referred to the Corporate Nuclear Safety Sec ian far review in accordance>>th Specification 6.5.3.9, hut implementation may proceed prior to the campleti<<of that revie~.6.5.XA.G Qe individual approving the proc dure, tes, or experiment or change thereto shall be other than those wha prepared tNe safety evaluation
<<performed the safety review.SHFARON HARRIS UNIT 1 6"8