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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] |
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ENCLOSURE 1 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENT REFUELING OPERATIONS - LOW WATER LEVEL TECHNICAL SPECIFICATION PAGES 8906120039 890607 PDR ADOCK 05000400 0
P
REFUELING OPERATIONS LQM MATER LEVEl.
LIMITING CONOITION FQR OPERATION 3.9.8.2 Two independent residual heat removal (RHR) loops shall be OPERABLE, and at least one RHR loop shall be fn aperatfon.~
APPLICABILITY: HQQE 6, with frradfated fuel in the vessel when the water level alcove the top of the reactor vessel flange fs less than 23 feet-ACTION:
- a. Wth less than the required RHR loops OPERABLE, fmmedfately initiate car rectfve actian to return the required RHR loops ta OPERABLE status or to establish greater than or equal to 23 feet of water above the reactor vessel flange as saon as possible.
- b. Nth na RHR loop in operation, suspend all operations involving a reduction fn bonn concentration of'he Reactor Coolant System and immediately initiate corrective actian to return the required RHk loop ta operation. Close all containment penetrations access from the containment atmosphere ta the outside providing'frect atmosphere ~ithin 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE RE UIREMENTS 4.9.8.2QAt 1eaet ane RNR 1aap nbe11 be verfrfee In aperntIon ana aironIetInp reactor coolant at a flow rate of greater than or equal to 2500.gpm at least anne per 12 bours/ 1o/1eoeven ge @ra/el /eve/ I'e n/ ar a/oave the reaerar ye~oel flange.
<q8~ g ~/ <f>ne QI/trop phd//k varifieJ in i/a~ va/e ai qlea/e/ '7/Tal7 af ojoernfion and &mulahg a//aa/ rb poOg/a/77 a/ /caw/ once per /2 i/oaa eo/'Tenever He eoa/er level is g/au Qd l-/aver yaSSel Xlanye, "The operating RHR loop may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 2-hour period during the performance of CORE ALTERATION and core loading veri ffcatfoa fn the vfcfnfty of the reactor vessel hot legs.
SHEARON HARRIS - ND 1 3/4 9 M
REFUELING OPERATIONS BASES 3/4.9. 6 REFUELING MACHINE The OPERABILITY requirements for the refueling machine ensure that: (1) refuel-ing machine will be used for movement of drive rods and fuel assenblfes, (2) each crane has sufficient load capacity to lift a drive rad or assembly, and (3) the core internals and reactor vessel are protected fram fuel, excessive lifting force in the event they are faadvertently engaged during lifting operations.
3/4.9.7 CRANE TRAVEL FUEL HANOLING BUILOING The restriction on movement of loads in excess of the nominal weight of a fuel and control rad assembly and associated handling tool over other fuel assemblies in the storage pool ensures that fn the event this load is drapped: (1) the activity release will be limited to that cantained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks wi11 not result in a critical array. This assumption is consistent with the activity reIease assumed in the safety analyses.
3/4.9.8 RESIOUAL HEAT RIVAL ANO COOLANT CIRCULATION The requirement that at least one residual heat removal (RHR) loop be in opera-tion ensures that: (1) sufficient caolfng capacity fs available to remove decay heat and maintain the water in the reactor vessel below 140oF as required during the REFUELING MOOE, and (2) sufficient coolant circulatfon fs maintained through the care to mfnfmfze the effect of a boron dilution incident and prevent boron stratification.
The requirement to have ~ RHR loops OPERABLE when there fs less than 23 feet of water above the reactor vessel flange ensures that a sfngIe failure of the operating RHR Iaap will nat result fn a complete lass of residual- heat removal capability. Wfth the reactor vessel head removed and at least 23 feet af water above the reactor pressure vessel flange, a large heat sink fs available for care cooling. Thus, in the event of a failure of the operating RHR Iaop, ade-quate time is provided ta initiate emergency pracedures to caol the care.
3/4.9.9 CONTAINMENT VENTILATION ISOLATION SY~
Thi OPERABILITY of this systaa ensures that the cantainment purge makeup and exhaust penetratfons will be automatfcally isolated upon detection of high radfatfoa levels within the containment. The OPERABILITY of this steN issJJ required -to restrict the release of radioactive material from the containment atmasphire to the environment.
M~ nc'P:
The minimum RHR flow requirement is reduced to 900 gpm when the reactor water level is below the reactor vessel flange. The 900 'gpm limit reduces the possibility of cavitation during operation of the RHR pumps and ensures sufficient mixing in the event of a MODE 6 boron dilution incident.
SHEARQN HARRIS - UNIT 1 B 3/4 S-2
REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.2 Two independent residual heat removal (RHR) loops shall be OPERABLE, and at least one RHR loop shall be in operation.*
APPLICABILITY: MODE 6, with irradiated fuel in the vessel when the water level above the top of the reactor vessel flange is less than 23 feet.
ACTION:
a~ With less than the required RHR loops OPERABLE, immediately initiate corrective action to return the required RHR loops to OPERABLE status or to establish greater than or equal to 23 feet of water above the reactor vessel flange as soon as possible.
- b. With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE RE UIREMENTS 4.9.8.2.1 At least one RHR loop shall be verified in operation and circulating reactor coolant at a flow rate of greater than or equal to 2500 gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the water level is at or above the reactor vessel flange.
4.9.8.2.2 At least one RHR loop shall be verified in operation and circulating reactor coolant at a flow rate of greater than or equal to 900 gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the water level is below the reactor vessel flange.
- The operating RHR loop may be remove'd from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />'er 2-hour period during the performance of CORE ALTERATIONS and core loading verification, in the vicinity of .the reactor vessel hot legs SHEARON HARRIS UNIT 1 3/4 9-10 Amendment No.
REFUELING OPERATIONS BASES 3/4.9.6 REFUELING MACHINE The OPERABILITY requirements for the refueling machine ensure that: (1) refuel-ing machine will be used for movement of drive rods and fuel assemblies, (2) each crane has sufficient load capacity'o lift a drive rod or fuel assembly, and (3) the core internals and reactor vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.
3/4 ~ 9 ~ 7 CRANE TRAVEL - FUEL HANDLING BUILDING The restriction on'ovement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped: (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the safety analyses.
3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residual heat removal (RHR) loop be in opera-tion ensures that: (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor vessel below 140'F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the core to minimize the effect of a boron dilution incident and prevent boron stratification.
The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal capability. With the reactor vessel head removed and at least 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core.
The minimum RHR flow requirement is reduced to 900 gpm when the reactor water level is belo~ the reactor vessel flange. The 900 gpm limit reduces the possibility of cavitation during operation of the RHR pumps and ensures sufficient mixing in the event of a MODE 6 boron dilution incident.
3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment p'urge makeup and exhaust penetrations will be automatically isolated upon detection of high radiation levels within the containment. The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.
SHEARON HARRIS - UNIT 1 B 3/4 9-2 Amendment No.