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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
ATTACHMENT 2 TO NLS-89-252 REVISED TECHNICAL SPECIFICATION PAGES 89i0060186 85'1002 PDR ADOCK 05000400 P PDC
f i
IP'
~ ~
'I
';1 SAFETY LIHITS BASES 2.1.1 REACTOR CORE
~graf Qj'ITH A.ITACHFO INCAN'RT cricciona of this a ety over eating of the fue nd poa-sib ding vhich vouam'erforation t in the reLeaae of ' f prod-ucts t re actor coolant. Ove Ln he fuel cladding evanted by rescr1ctL L operation to n the nu boiLing r e re the heat tranafe ficient ' and the c L aurfa pe ra'c ure is slightly above ool uration temperatu Operation above boundary of the nucleat regime could result 1 excessive g c cures because of set aperture from nu-boy ) and ultant ahar et ion in tranafer coeffi-ci t dirac tl urabl>> te r during o 'on and there-for 1
no PS'nd a
h L ough the M-3 rea ctor corre t rtu a re and pres s u'r The M-3 NI correlati been r-oped di ct the DMS fl ocation of M for axial and nonunifo flux di at r nay oeal NI heat flux r is defined as t of lux that vould
'o cuLated particular core lo actuaL Local lux and i ative 0 the margin to DN.
The minimum vaL ue e rl'ng steady-state o normaL operationa transients, an cipated nts ia Limite ia value corre-sponds to a obability at eonfiden chat 'll not occur and is e s an appropriace ma 0 all operacin iclona ~
The of Figure 2.1-1 shov the inca of TH&MAL POMEk, toe C System pressure and avera e for vhich the minimum 's aa than 1.30, or the aver Lpy a e veaseL exit ia equal t nthaLpy of urated liquid.
l gg,@or These curves are based on an enthaLyy hot channel factor, F>~, of and a t OPAL Cual reference cosine vith ~ peak of 1.55 for~iaL paver shape. An alLovance ia VRN TAG' included for an increase in calcul.ated P>~ at reduced pover baaed on the Rail expression!
LC2
[1 + 4.3 (1-4)] gyes LOPAR +~~p ~nd Share P is the fraction of RATED TliEIL POMER.
Thea>> limiting heat flux conditions are higher than those calcuLated for the range of aL1 control rods fully vithdravn to the maxi'lLovable control rod insertion assuming the axiaL pover iabalance is within the Limits of the fl (hI) function of the Overceaperacure trip.'hen the axial pover imbalance is noc vithin che tolerance, the axial pover imbalance effect on the Over-tamyerature hT crips vill reduce che Setyoints to provide yrotection consistent with cor f t imi f
F>H -I.LS >+ o.3S t'.I-P)34r N<TA
~<u'HEARON HARRIS - UNIT 1 8 2-1 Amendment No
REACTIVITY OL SYSTEMS 3/4 ~ 1 ~ 3 MOVABLE CONTROL ASSEMBLIES CROUP HEICHT LIMITINC CONDITION FOR OPERATION 3,1.3,1 All shutdovn and concroL rods shaLL be OPERABLE and positioned vichin 12 steps (indicaced position) of their group seep councer demand position.
APPLICABILITY: MODES 1<<and 2<<.
ACTION:
a~ With oae or more rods inoperabLe due to being iassovable as a resulc of excessive friction or,. mechanical interference or knovn to be uncrippable, determine that the SHUTDOWN MARCIN requirement of Specification 3.1.1.1 is satisfied vichin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY Mithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
n
- b. Mich more than one rod misaligned from che group step counter demand position by mora than + 12 steps (indicated position), be in HOT STANDBY vithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ~
c~ With more, than one rod inoperabl.e, due co a rod control urgent failure alarm or obvious electrical problem ia the rod controL system existing for greater thaa 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, be in HOT STANDBY vithia the fol.loving 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> With one rod trippable but inoperable due to causes other than addressed by ACTION a., above, or misaligaed from ics group step counter demand heighc by more than + 12 steps (indicaced position),
POMER OPERATION may continue provided chat vithin 1 hour:
1 ~ The rod is restored to OPERABLE status vithin the above alignment requirements o oc 2m The rod ii declared iaoperable and the remainder of the rods in the group vith the iaoperable rod are aligned to vichia + 12 steps of the inoperable rod vhiLe maintaining the rod sequence on cordrpl honks shal be rescr]cted pursuant to Specificatioa 3.1.3.6 during apccif'ied tn We subsequent operatioay or g~ OplLAAQ g('mirb RePov+, 3~ The rod is declared inoperabLe and the SHUTDOWN MARCIN requirement of Specification 3.1.1.1 is sacisfied. POMER OPERATION may thea 'continue provided that:
a) A reevaluation of each accident analysis of Table 3.1"1 is performed vichin S days[ this reevaluation shaLL confirm chat th>> previously analyred results of these accidents
<<See Special. Test Ezceptions Specifications 3.10.2 and 3.10.3 ~
SHEARON HARRIS'NIT 1 3/4 1-14 Amendment Nn. g
n 3/4.2 POSER DISTRIBUTION LIMITS, 3/4.2 ' AXIAL FLUX DIFFERENCE LIMITINC CONDITION FOR OPERATION 3.2.1 The indicated AXIAL-FLUXDIFFERENCE (AFD) shaLL be maintained within:
- a. the accepcabLe operational space 0 AxiaL Offsec ControL (RAOC) operacion, o aS S~iFfed in +e &re QerW~
l.irni4s A e porI be within a about e tar t AFD during Base Los operatio aS Speci@'ed in We Core OperaHng LimiB Re ort:
APPLICABILITY! MODE 1 above 50Z of RATED THERMAL PNER+.
ACTION:
a For operation with the indicated outside of the 4l,+ 8pM il
~ RAOC AFD
- 1. Restore th>> indicated within 1S minutes, or AFD to withi e 'imits 5pcci~ied jn Qe Q0rc Qpercdj RA Qntits gapo
- 2. Reduce THERMAL POWER to Less than 50X of RATED THERMAL POWER within 30 minutes and reduce the Power Range Neutron Flux-High Trip setpoints to Less than or equal to SSX of RATED
'DERMAL POSER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
be For Base Load operation above APL with the indicated AXIAL FLUX DIFFERENCE outside of the applicable target band about the target AFD, either!
t
- 1. Restore the indicated AFD to within the target band Limits within 15 minutes, or
- 2. Reduce THERMAL POMER to less than APL of RATED THERMAL POWER and discontinue Base Load operation within 30 minutest C ~ THERMAL POSER shall not be increased above 50Z of RATED THERMAL speci/led tdtWc Core OporaHg p;rdti+S pICFIor+ for RAOC Ope,r4bort I
+See SpeciaL Test Exception 3.10.2
~APL is the minimum allowabLe power LeveL for Base Load operation and will be provided in the per Syecificacion 6.9 '.6 ~
5 ~oP~a~v 'zP p'""
SHEARON HARRIS - UNIT 1 3/4 2-1 Amendment Nn.+
REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES
. GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3.1.3.1 All shutdown and control rods shall be OPERABLE and positioned within
+ 12 steps (indicated position) of their group step counter demand position.
APPLICABILITY: MODES 1 and 2 ACTION:
a 0 With one or more rods inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours.
- b. With more than one rod misaligned from the group step counter demand position by more than + 12 steps (indicated position), be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
C ~ With more than one rod inoperable, due to a rod control urgent failure alarm or obvious electrical problem in the rod control system existing for greater than 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, be in HOT STANDBY within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- d. With one rod trippable but inoperable due to causes other than addressed by ACTION a., above, or misaligned from its group step counter demand height by more than + 12 steps (indicated position),
POWER OPERATION may continue provided that within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />'.
- 1. The rod is restored to OPERABLE status within the above alignment requirements, or
- 2. The rod is declared inoperable and the remainder of the rods in the group with the inoperable rod are aligned to within + 12 steps of the inoperable rod while maintaining the rod sequence and insertion limits on control banks specified in the Core Operating Limits Report. The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, or
- 3. The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied. POWER OPERATION may then continue provided that:
a) A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents See Special Test Exceptions Specifications 3.10.2 and 3 '0.3.
SHEARON HARRIS UNIT 1 3/4 1-14 .Amendment No.
4 2.1 SAFETY LIMITS BASES 2.1.1 REACTOR CORE (Continued)
These curves are based on an enthalpy hot channel factor, F , of 1.62 for LOPAR fuel and 1.65 for VANTAGE 5 fuel and areference cosine with a peak of 1.55 for axial power shape. An allowance is included for -an increase in calculated F<H at reduced power based on the expression:
F<H
= 1.62 [1 + 0.3 (1-P)] for LOPAR fuel, and F<H
= 1.65 [1 + 0 '5 (1-P)] for VANTAGE 5 fuel Where P is the fraction of RATED THERMAL POWER.
These limiting heat flux conditions are higher than those calculated for the range of all control rods fully withdrawn to the maximum allowable control rod insertion assuming the axial power imbalance is within the limits of the fl (AI) function of the Overtemperature trip. When the axial power imbalance is not within the tolerance, the axial power imbalance effect on the Over-temperature AT trips will reduce the Setpoints to provide protection consistent with core Safety Limits.
SHEARON HARRIS UNIT 1 B 2-la Amendment No.
3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE LIMITING CONDITION FOR OPERATION 3.2.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within'.
II
- a. the acceptable operational space as specified in the Core Operating Limits Report for Relaxed Axial. Offset Control (RAOC) operation, or
- b. within a band about the target AFD during Base Load operation as specified in the Core Operating Limits Report.
APPLICABILITY: MODE 1 above 50X of RATED THERMAL POWER>'<.
ACTION:
a ~ For RAOC operation with the indicated AFD outside of the limits specified in the Core Operating Limits Report, either:
1 ~ Restore the indicated AFD to within the limits specified in the Core Operating Limits Report within 15 minutes, or
- 2. Reduce THERMAL POWER to less than SOX of RATED THERMAL POWER within 30 minutes and reduce the Power Range Neutron Flux High Trip setpoints to less than or equal to 55%%d of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- b. For Base Load operation above APL with the indicated AXIAL FLUX DIFFERENCE outside of the applicable target band about the target AFD, either:
- 1. Restore the indicated AFD to within the target band limits within 15 minutes, or
- 2. Reduce THERMAL POWER to less than APL of RATED THERMAL POWER and discontinue Base Load operation within 30 minutes.
C ~ THERMAL POWER shall not be increased above 50X of RATED THERMAL POWER unless the indicated AFD is within the limits specified in the Core Operating Limits Report for RAOC operation.
'<See Special Test Exception 3.10.2
>'<>'<APL i's the minimum allowable power level for Base Load operation and will be provided in the Core Operating Limits Report per Specification 6.9.1.6.
SHEARON HARRIS UNIT 1 3/4 2-1 Amendment No.
DISTRUBITION CDocket F~ile, Shearon Harris Plant PAnderson DOCKET NO(S) 50-400 Hr. Lynn M. Eury Executive Vice President Power Supp1y Caro1ina Power 8 Light Company Post Office Box 1551 Ra1eigh, North Carolina 27602
'HEARON HARRIS NUCLEAR POllER PL'ANT, UNIT 1
. The following documents concerning our review of. the subject facility are transmitted for your information.
DESCRIPTION OF DOCUMENT - '.DATED Notice of Receipt of Application Draft/Final Environmental Statement Notice of Availability of Draft/Final Environmental Statement Safety Evaluation Report, or Supplement No.
Environmental Assessment and Finding of No Significant Impact.
Notice of Issuance of Environmental Assessment Notice of Consideration of Issuance of Facility Operating License or Amendment to Facility Operating License Biweekly Notice; Applications and Amendments to Operating Licenses Involvin No Si nificant Hazards Conditions See Page(s)
Exemption Construction Permit No. CPPR- , Amendment No.
Facility Operating License No. ,Amendment No.
Order Monthly Operating Report for transmitted by Letter Annual/Semi-Annual Report:
transmitted by, Letter Other Office of Nuclear Reactor Regulation
Enclosures:
As Stated cc:See next page OFFICE> PDI I-1 "
'PA'n'd'e'rso'n""
SURNAME~
OATeg 9(29/89 .
NRC FORM 3ta tto/eo) NRCM 0240 OFFICIAL RECORD COPY