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| {{#Wiki_filter:POWER DISTRIBUTION LIMITS BASES HEAT FLUX HOT CHANNEL FACTOR AND RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR Continued limit on the hot channel factor, F~(Z), is met.V(Z)accounts for the effects of normal operation transients and was determined from expected power control maneuvers over the full range of burnup conditions in the core.The V(Z)function is specified in the COLR.The core thermal power is determined by calorimetric on a daily frequency. | | {{#Wiki_filter:POWER DISTRIBUTION LIMITS BASES HEAT FLUX HOT CHANNEL FACTOR AND RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR Continued limit on the hot channel factor, F~(Z), is met. V(Z) accounts for the effects of normal operation transients and was determined from expected power control maneuvers over the full range of burnup conditions in the core. The V(Z) function is specified in the COLR. |
| The safety analysis is performed at 102K RATED THERMAL POWER to account for calorimetric uncertainty. | | The core thermal power is determined by calorimetric on a daily frequency. |
| Thermal power is considered to be within the 100.0X RATED THERMAL POWER limit of Figure 3.2-3 provided: a)b)c)average thermal power for any shift does not exceed 100K RATED THERMAL POWER, and instantaneous thermal power does not exceed 102K RATED THERMAL POWER, and average thermal power is less than 102K RATED THERMAL POWER for a fifteen minute period.or 101K RATED THERMAL POWER for a thirty minute period.or 100.5X RATED THERMAL POWER for a sixty minute pel 1 od.When RCS flow rate is measured, no additional allowance is necessary prior to comparison with the limit of Specification 3.2.3.A normal RCS flowrate er ror of 2.1X will be included in C,, which will be modified as discussed below.The measurement error for RCS total flow rate is based upon performing a precision heat balance and using the result to calibrate the RCS flow rate indicators. | | The safety analysis is performed at 102K RATED THERMAL POWER to account for calorimetric uncertainty. Thermal power is considered to be within the 100.0X RATED THERMAL POWER limit of Figure 3.2-3 provided: |
| Potential fouling of the feedwater venturi which might not be detected could bias the result from the precision heat balance in a non-conservative manner.Therefore, a penalty of 0.1X for undetected fouling of the feedwater venturi.raises the nominal flow measurement allowance, C,.to 2.2X for no venturi fouling.Any fouling which might bias the RCS flow rate measurement greater than 0.1X can be detected by monitoring and trending various plant performance parameters. | | a) average thermal power for any shift does not exceed 100K RATED THERMAL POWER, and b) instantaneous thermal power does not exceed 102K RATED THERMAL POWER, and c) average thermal power is less than 102K RATED THERMAL POWER for a fifteen minute period. or 101K RATED THERMAL POWER for a thirty minute period. or 100.5X RATED THERMAL POWER for a sixty minute pel 1 od. |
| If detected.action shall be taken before performing subsequent precision heat balance measurements, i.e., either the effect of the fouling shall be quantified and compensated for in the RCS flow rate measurement or the venturi shall be cleaned to eliminate the fouling.The upper limit on measured RCS flow rate in Figure 3.2-3[321,300 gpm x (1.0-C,)j protects the mechanical design flow of 321,300 gpm per FSAR Table 5.1.0-1.The 12-hour periodic surveillance of indicated RCS flow is sufficient to detect only flow degradation that could lead to operation outside the acceptable region of operation. | | When RCS flow rate is measured, no additional allowance is necessary prior to comparison with the limit of Specification 3.2.3. A normal RCS flowrate er ror of 2.1X will be included in C,, which will be modified as discussed below. |
| SHEARON HARRIS-UNIT 1 vsoaisooaz | | The measurement error for RCS total flow rate is based upon performing a precision heat balance and using the result to calibrate the RCS flow rate indicators. Potential fouling of the feedwater venturi which might not be detected could bias the result from the precision heat balance in a non-conservative manner. Therefore, a penalty of 0.1X for undetected fouling of the feedwater venturi. raises the nominal flow measurement allowance, C,. to 2.2X for no venturi fouling. Any fouling which might bias the RCS flow rate measurement greater than 0. 1X can be detected by monitoring and trending various plant performance parameters. If detected. action shall be taken before performing subsequent precision heat balance measurements, i.e., either the effect of the fouling shall be quantified and compensated for in the RCS flow rate measurement or the venturi shall be cleaned to eliminate the fouling. |
| ~soaos PDR ADQCK 05000400 P PDR B 3/4 2-5 HNP-96-014 February 8, 1996 POWER DISTRIBUTION LIMITS BASES 3/4.2.4 UADRANT POWER TILT RATIO The QUADRANT POWER TILT RATIO limit assures that the radial power distribution satisfies the design values used in the power capability analysis.Radial power distribution measurements are made during STARTUP testing and periodically during power operation.
| | The upper limit on measured RCS flow rate in Figure 3.2-3 |
| The limit of 1.02, at which corrective action is required, provides DNB and linear heat generation rate protection with x-y plane power tilts.A limiting tilt of 1.025 can be tolerated before the margin for uncertainty in F is depleted.A limit of 1.02 was selected to provide an allowance for t5e uncertainty associated with the indicated power tilt.The 2-hour time allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and correction of a dropped or misaligned control rod.In the event such action does not correct the tilt.the margin for uncertainty on F, is reinstated by reducing the maximum allowed power by 3X for each percent of tilt in excess of 1.For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, the movable incore detectors are used to confirm that the normalized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO.The incore detector monitoring is done with a full incore*flux map or two sets of four symmetric thimbles.The preferred sets of four symmetric thimbles is a unique set of eight detector locations. | | [321,300 gpm x (1.0 - C,)j protects the mechanical design flow of 321,300 gpm per FSAR Table 5.1.0-1. |
| These locations are C-8, E-5.E-ll, H-3, H-13.L-5, L-11.N-8.If other locations must be used, a special report to NRC should be submitted within 30 days in accordance with 10CFR50.4. | | The 12-hour periodic surveillance of indicated RCS flow is sufficient to detect only flow degradation that could lead to operation outside the acceptable region of operation. |
| 3/4.2.5 DNB PARAMETERS The limits on the DNB-related parameters assure that each of the parameters are maintained within the normal steady-state envelope of operation assumed in the transient and accident analyses.The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to maintain a minimum DNBR that is equal to or greater than the design DNBR value throughout each analyzed transient. | | SHEARON HARRIS - UNIT 1 B 3/4 2-5 HNP-96-014 February 8, 1996 vsoaisooaz ~soaos PDR ADQCK 05000400 P PDR |
| The indicated T, value and the indicated pressurizer pressure value are compared to analyticaT limits of 586.1'F and 2185 psig, respectively, after an allowance for measurement uncertainty is included.The 12-hour periodic surveillance of these parameters through instrument read-out is sufficient to ensur e that the parameters are restored within their limits following load changes and other expected transient operation. | | |
| SHEARON HARRIS-UNIT 1 B 3/4 2-6 HNP-96-014 February 8, 1996}} | | POWER DISTRIBUTION LIMITS BASES 3/4.2.4 UADRANT POWER TILT RATIO The QUADRANT POWER TILT RATIO limit assures that the radial power distribution satisfies the design values used in the power capability analysis. Radial power distribution measurements are made during STARTUP testing and periodically during power operation. |
| | The limit of 1.02, at which corrective action is required, provides DNB and linear heat generation rate protection with x-y plane power tilts. A limiting tilt of 1.025 can be tolerated before the margin for uncertainty in F is depleted. A limit of 1.02 was selected to provide an allowance for t5e uncertainty associated with the indicated power tilt. |
| | The 2-hour time allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and correction of a dropped or misaligned control rod. In the event such action does not correct the tilt. the margin for uncertainty on F, is reinstated by reducing the maximum allowed power by 3X for each percent of tilt in excess of 1. |
| | For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, the movable incore detectors are used to confirm that the normalized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO. The incore detector monitoring is done with a full incore*flux map or two sets of four symmetric thimbles. The preferred sets of four symmetric thimbles is a unique set of eight detector locations. These locations are C-8, E-5. E-ll, H-3, H-13. L-5, L-11. N-8. If other locations must be used, a special report to NRC should be submitted within 30 days in accordance with 10CFR50.4. |
| | 3/4.2.5 DNB PARAMETERS The limits on the DNB-related parameters assure that each of the parameters are maintained within the normal steady-state envelope of operation assumed in the transient and accident analyses. The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to maintain a minimum DNBR that is equal to or greater than the design DNBR value throughout each analyzed transient. The indicated T , value and the indicated pressurizer pressure value are compared to analyticaT limits of 586. 1'F and 2185 psig, respectively, after an allowance for measurement uncertainty is included. |
| | The 12-hour periodic surveillance of these parameters through instrument read-out is sufficient to ensur e that the parameters are restored within their limits following load changes and other expected transient operation. |
| | SHEARON HARRIS - UNIT 1 B 3/4 2-6 HNP-96-014 February 8, 1996}} |
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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
POWER DISTRIBUTION LIMITS BASES HEAT FLUX HOT CHANNEL FACTOR AND RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR Continued limit on the hot channel factor, F~(Z), is met. V(Z) accounts for the effects of normal operation transients and was determined from expected power control maneuvers over the full range of burnup conditions in the core. The V(Z) function is specified in the COLR.
The core thermal power is determined by calorimetric on a daily frequency.
The safety analysis is performed at 102K RATED THERMAL POWER to account for calorimetric uncertainty. Thermal power is considered to be within the 100.0X RATED THERMAL POWER limit of Figure 3.2-3 provided:
a) average thermal power for any shift does not exceed 100K RATED THERMAL POWER, and b) instantaneous thermal power does not exceed 102K RATED THERMAL POWER, and c) average thermal power is less than 102K RATED THERMAL POWER for a fifteen minute period. or 101K RATED THERMAL POWER for a thirty minute period. or 100.5X RATED THERMAL POWER for a sixty minute pel 1 od.
When RCS flow rate is measured, no additional allowance is necessary prior to comparison with the limit of Specification 3.2.3. A normal RCS flowrate er ror of 2.1X will be included in C,, which will be modified as discussed below.
The measurement error for RCS total flow rate is based upon performing a precision heat balance and using the result to calibrate the RCS flow rate indicators. Potential fouling of the feedwater venturi which might not be detected could bias the result from the precision heat balance in a non-conservative manner. Therefore, a penalty of 0.1X for undetected fouling of the feedwater venturi. raises the nominal flow measurement allowance, C,. to 2.2X for no venturi fouling. Any fouling which might bias the RCS flow rate measurement greater than 0. 1X can be detected by monitoring and trending various plant performance parameters. If detected. action shall be taken before performing subsequent precision heat balance measurements, i.e., either the effect of the fouling shall be quantified and compensated for in the RCS flow rate measurement or the venturi shall be cleaned to eliminate the fouling.
The upper limit on measured RCS flow rate in Figure 3.2-3
[321,300 gpm x (1.0 - C,)j protects the mechanical design flow of 321,300 gpm per FSAR Table 5.1.0-1.
The 12-hour periodic surveillance of indicated RCS flow is sufficient to detect only flow degradation that could lead to operation outside the acceptable region of operation.
SHEARON HARRIS - UNIT 1 B 3/4 2-5 HNP-96-014 February 8, 1996 vsoaisooaz ~soaos PDR ADQCK 05000400 P PDR
POWER DISTRIBUTION LIMITS BASES 3/4.2.4 UADRANT POWER TILT RATIO The QUADRANT POWER TILT RATIO limit assures that the radial power distribution satisfies the design values used in the power capability analysis. Radial power distribution measurements are made during STARTUP testing and periodically during power operation.
The limit of 1.02, at which corrective action is required, provides DNB and linear heat generation rate protection with x-y plane power tilts. A limiting tilt of 1.025 can be tolerated before the margin for uncertainty in F is depleted. A limit of 1.02 was selected to provide an allowance for t5e uncertainty associated with the indicated power tilt.
The 2-hour time allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and correction of a dropped or misaligned control rod. In the event such action does not correct the tilt. the margin for uncertainty on F, is reinstated by reducing the maximum allowed power by 3X for each percent of tilt in excess of 1.
For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, the movable incore detectors are used to confirm that the normalized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO. The incore detector monitoring is done with a full incore*flux map or two sets of four symmetric thimbles. The preferred sets of four symmetric thimbles is a unique set of eight detector locations. These locations are C-8, E-5. E-ll, H-3, H-13. L-5, L-11. N-8. If other locations must be used, a special report to NRC should be submitted within 30 days in accordance with 10CFR50.4.
3/4.2.5 DNB PARAMETERS The limits on the DNB-related parameters assure that each of the parameters are maintained within the normal steady-state envelope of operation assumed in the transient and accident analyses. The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to maintain a minimum DNBR that is equal to or greater than the design DNBR value throughout each analyzed transient. The indicated T , value and the indicated pressurizer pressure value are compared to analyticaT limits of 586. 1'F and 2185 psig, respectively, after an allowance for measurement uncertainty is included.
The 12-hour periodic surveillance of these parameters through instrument read-out is sufficient to ensur e that the parameters are restored within their limits following load changes and other expected transient operation.
SHEARON HARRIS - UNIT 1 B 3/4 2-6 HNP-96-014 February 8, 1996