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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20195B4441999-05-26026 May 1999 Proposed Tech Specs Relocating pressure-temp Curves, Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS pressure-temp Limits Rept ML20205J7671999-03-31031 March 1999 Proposed Tech Specs Increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate LIC-99-0001, Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR1999-01-29029 January 1999 Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR ML20151U3871998-09-0404 September 1998 Revised Bases of TS Sections 1.3(8),2.0.1(2),2.1.6,2.3,2.4, 2.13,2.15,3.1 & 3.6 ML20217B8241998-03-18018 March 1998 Proposed Tech Specs Re Requirements for Alternate Shutdown Panel & Associated Auxiliary Feedwater Panel ML20217B8611998-03-18018 March 1998 Proposed Tech Specs 5.2 & 5.11.2,changing Title of Shift Supervisor to Shift Manager ML20217P2041998-03-0303 March 1998 Proposed Tech Specs Pages,Revising TS 2.6 & Basis by Replacing Refs to TS 3.5(4) W/Refs to TS 5.19 ML20199L8951998-01-30030 January 1998 Proposed Tech Specs,Reflecting Relocation of pressure-temp Curves,Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS PT Limits Rept ML20199L7291998-01-30030 January 1998 Proposed Tech Specs Deleting Section 3.E Re License Term ML20202B0931998-01-30030 January 1998 Proposed Tech Specs Section 2.5 Re Steam & Feedwater Sys ML20203G4311997-12-11011 December 1997 Proposed Tech Specs,Adding New LCO to TS 2.15 Pertaining to Inoperable ESF Logic Subsystem ML20199K1391997-11-21021 November 1997 Proposed Tech Specs 5.19 Re Containment Leakage Rate Testing Program ML20217G4601997-10-0303 October 1997 Proposed Tech Specs Pages Revising TS Surveillance 3.9, Auxiliary Feedwater Sys, to Clarify What Flow Paths Are Required to Be Tested & Delete Specific Discharge Pressure ML20196J0851997-07-25025 July 1997 Proposed Tech Specs Implementing Option B of 10CFR50,App J & Allowing Frequency of Conducting ILRT & Local Leak Rate Testing to Be Based on Component Performance ML20137Y1801997-04-17017 April 1997 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20137H4941997-03-26026 March 1997 Proposed Tech Specs Incorporating Addl Restrictions on Operation of MSSVs ML20138L4361997-02-20020 February 1997 Proposed Tech Specs 5.0 Re Administrative Controls LIC-96-0183, Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents1996-11-20020 November 1996 Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents ML20129E5161996-10-24024 October 1996 Proposed Tech Specs 4.3.2,regarding Reactor Core & Control to Allow Use of Either Zircaloy or ZIRLO Cladding Proposed Additional Reference to Westinghouse Topical Report, WCAP-12610-P-A, Vantage + Fuel Assembly Rept ML20129C2621996-10-22022 October 1996 Proposed Tech Specs 5.0 Re Administrative Controls & 5.9.5 Re Core Operating Limits Rept LIC-96-0125, Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core1996-08-23023 August 1996 Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core ML20115G0041996-07-15015 July 1996 Proposed Tech Specs 4.3.2 Re Reactor Core & Control ML20112D3211996-05-31031 May 1996 Proposed Tech Specs Re LCO for Trisodium Phosphate & Increasing Min Required Amount of Trisodium Phosphate Contained in Containment Sump Mesh Baskets ML20117H6981996-05-20020 May 1996 Proposed Tech Specs,Clarifying Surveillance Test Requirements Found in TS 3-1,Tables 3-1,3-2,3-3 & 3-3A ML20117H5931996-05-17017 May 1996 Proposed Tech Specs,Relocating Operability Requirements for Shock Suppressors (Snubbers) to USAR & or Plant Procedures & Incorporating Snubber Exam & Testing Requirements Into TS 3.3 ML20097C3081996-02-0101 February 1996 Proposed Tech Specs,Allowing Increase in Initial Nominal U-235 Enrichment Limit of Fuel Assemblies That May Be Stored in Spent Fuel Pool LIC-96-0008, Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition1996-01-22022 January 1996 Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition ML20094N8631995-11-16016 November 1995 Proposed Tech Specs,Adding LCO & Surveillance Test for Safety Related Inverters & Deleting Nonsafety Related Instrument Buses ML20092G0771995-09-0606 September 1995 Proposed Tech Spec 2.7,extending Allowed Outage Time from 7 Days Per Month to 7 Days W/ Addl Once Per Cycle 10 Day Allowed Outage Time ML20087E0281995-08-0404 August 1995 Proposed Tech Specs Reducing Minimum Operable Containment Radiation High Signal Channels ML20086D5341995-06-27027 June 1995 Proposed Tech Specs Re Reformation & Clarification of TS Re Chemical & Vol Control Sys ML20091G3601995-06-26026 June 1995 Proposed Tech Specs Re Extension of Allowed Outage Time for an Inoperable Low Pressure SI Pump ML20086D3851995-06-26026 June 1995 Proposed Tech Specs Re Audit Frequencies for Plant QA Program ML20084G7751995-05-31031 May 1995 Proposed Tech Specs,Requesting Amend to Provide Addl Restrictions on Operation of CCW Sys Heat Exchangers ML20083C0091995-05-0808 May 1995 Proposed Tech Specs,Incorporating Proposed Revs Per GL 93-05 to Specs 2.3,3.1,3.2,3.3 & 3.6 ML20087G9691995-04-0707 April 1995 Proposed Tech Specs Re Relocation of Axial Power Distribution Figure for License DPR-40 ML20082J0851995-04-0707 April 1995 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20080S0291995-03-0101 March 1995 Proposed Tech Specs Reflecting Administrative Revs to TS 5.5 & 5.8,per GL 93-07 & Revs Unrelated to GL 93-07 to TS 2.5, 2.8,2.11,3.2 & 3.10 ML20078P8251995-02-10010 February 1995 Proposed Tech Specs 2.10 to Relocate Requirements for Incore Instrumentation Sys ML20077S1691995-01-0909 January 1995 Proposed Tech Specs,Reflecting Deletion of Requirements for Toxic Gas Monitoring Sys ML20078G8981994-11-11011 November 1994 Proposed Tech Specs 5.2 & 5.5,reflecting Administrative Changes ML20024J3921994-10-0707 October 1994 Proposed Tech Specs,Deleting SRs in TS 3.6(3)a for Eight Raw Water Backup Valves to Containment Cooling Coils,Deleting SRs in TS 3.2,Table 3-5,item 6 for 58 Raw Water Valves & Revising Basis of TS 2.4 to Reflect Changes ML20069H9261994-06-0606 June 1994 Proposed Tech Specs Incorporating Changes to Credit Leak Before Break Methodology to Resolve USI A-2, Asymmetrical Blowdown Loads on Rcps ML20069D8451994-05-25025 May 1994 Proposed Tech Specs Requesting one-time Schedular Exemption from 10CFR50.36a(2) ML20062N4211993-12-28028 December 1993 Proposed TS Tables 3-1 & 3-2 Re Min Frequencies for Checks, Calibrs & Testing of RPS & Min Frequencies for Checks, Calibrs & Testing of ESFs & Instrumentation & Controls, Respectively LIC-93-0228, Proposed Tech Specs Incorporating Changes to Leak Before Break Methodology to Resolve Unresolved Safety Issue A-2, Asymmetrical Blowdown Loads on Reactor Primary Coolant Sys1993-08-20020 August 1993 Proposed Tech Specs Incorporating Changes to Leak Before Break Methodology to Resolve Unresolved Safety Issue A-2, Asymmetrical Blowdown Loads on Reactor Primary Coolant Sys ML20045H1791993-07-12012 July 1993 Proposed TS 2.14,Table 2-1,Item 6.b Re ESF Sys Initiation, Degraded Voltage Setting Limits LIC-93-0159, Proposed Tech Specs Incorporating Administrative Changes1993-06-17017 June 1993 Proposed Tech Specs Incorporating Administrative Changes ML20128E5341993-02-0808 February 1993 Proposed Tech Specs Deleting Section 5.9.4 Re Radioactive Effluent Release Rept.Draft Chemistry Manual Procedure Encl ML20128C0461993-02-0101 February 1993 Proposed TS Figures 2-1A & 2-1B Re pressure-temp Limits for Heatup & Cooldown,Respectively 1999-05-26
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20195B4441999-05-26026 May 1999 Proposed Tech Specs Relocating pressure-temp Curves, Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS pressure-temp Limits Rept ML20205J7671999-03-31031 March 1999 Proposed Tech Specs Increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate LIC-99-0001, Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR1999-01-29029 January 1999 Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR LIC-98-0141, SG Eddy Current Test Rept for 1998 Refueling Outage. with1998-10-27027 October 1998 SG Eddy Current Test Rept for 1998 Refueling Outage. with ML20151U3871998-09-0404 September 1998 Revised Bases of TS Sections 1.3(8),2.0.1(2),2.1.6,2.3,2.4, 2.13,2.15,3.1 & 3.6 ML20217B8611998-03-18018 March 1998 Proposed Tech Specs 5.2 & 5.11.2,changing Title of Shift Supervisor to Shift Manager ML20217B8241998-03-18018 March 1998 Proposed Tech Specs Re Requirements for Alternate Shutdown Panel & Associated Auxiliary Feedwater Panel ML20217P2041998-03-0303 March 1998 Proposed Tech Specs Pages,Revising TS 2.6 & Basis by Replacing Refs to TS 3.5(4) W/Refs to TS 5.19 ML20199L7291998-01-30030 January 1998 Proposed Tech Specs Deleting Section 3.E Re License Term ML20199L8951998-01-30030 January 1998 Proposed Tech Specs,Reflecting Relocation of pressure-temp Curves,Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS PT Limits Rept ML20202B0931998-01-30030 January 1998 Proposed Tech Specs Section 2.5 Re Steam & Feedwater Sys ML20203G4311997-12-11011 December 1997 Proposed Tech Specs,Adding New LCO to TS 2.15 Pertaining to Inoperable ESF Logic Subsystem ML20199K1391997-11-21021 November 1997 Proposed Tech Specs 5.19 Re Containment Leakage Rate Testing Program ML20217G4601997-10-0303 October 1997 Proposed Tech Specs Pages Revising TS Surveillance 3.9, Auxiliary Feedwater Sys, to Clarify What Flow Paths Are Required to Be Tested & Delete Specific Discharge Pressure ML20211N7591997-10-0202 October 1997 Rev 0 to Fort Calhoun Station Unit 1 Operating Instruction, OI-ES-3, Engineered Safeguard Controls Normal Mode 1,2 & 3 Alignment Check ML20211N7521997-09-21021 September 1997 Rev 2 to Fort Calhoun Operations Dept Policy & Directive OPD-6-04, Annunciator Marking ML20211N7471997-09-12012 September 1997 Rev 2 to Fort Calhoun Operations Dept Policy & Directive OPD-6-08, Plastic Label Usage ML20211N7661997-08-25025 August 1997 Rev 4 to Fort Calhoun Station Unit 1 Annunciator Response Procedure ARP-1, APR-1 Annunciator Response Procedure ML20211N7411997-08-24024 August 1997 Rev 0 to Fort Calhoun Operations Dept Policy & Directive OPD-5-14, Test Monitor Program ML20196J0851997-07-25025 July 1997 Proposed Tech Specs Implementing Option B of 10CFR50,App J & Allowing Frequency of Conducting ILRT & Local Leak Rate Testing to Be Based on Component Performance ML20137Y1801997-04-17017 April 1997 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20137H4941997-03-26026 March 1997 Proposed Tech Specs Incorporating Addl Restrictions on Operation of MSSVs ML20138L4361997-02-20020 February 1997 Proposed Tech Specs 5.0 Re Administrative Controls ML20134J6841997-01-20020 January 1997 Rev 5,Change a to Security Training & Qualification Program LIC-96-0183, Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents1996-11-20020 November 1996 Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents ML20129E5161996-10-24024 October 1996 Proposed Tech Specs 4.3.2,regarding Reactor Core & Control to Allow Use of Either Zircaloy or ZIRLO Cladding Proposed Additional Reference to Westinghouse Topical Report, WCAP-12610-P-A, Vantage + Fuel Assembly Rept ML20129C2621996-10-22022 October 1996 Proposed Tech Specs 5.0 Re Administrative Controls & 5.9.5 Re Core Operating Limits Rept LIC-96-0125, Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core1996-08-23023 August 1996 Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core ML20115G0041996-07-15015 July 1996 Proposed Tech Specs 4.3.2 Re Reactor Core & Control ML20112D3211996-05-31031 May 1996 Proposed Tech Specs Re LCO for Trisodium Phosphate & Increasing Min Required Amount of Trisodium Phosphate Contained in Containment Sump Mesh Baskets ML20117H6981996-05-20020 May 1996 Proposed Tech Specs,Clarifying Surveillance Test Requirements Found in TS 3-1,Tables 3-1,3-2,3-3 & 3-3A ML20117H5931996-05-17017 May 1996 Proposed Tech Specs,Relocating Operability Requirements for Shock Suppressors (Snubbers) to USAR & or Plant Procedures & Incorporating Snubber Exam & Testing Requirements Into TS 3.3 ML20129C5351996-03-0101 March 1996 Rev 0 to Incore Instrumentation Operability Requirements ML20097C3081996-02-0101 February 1996 Proposed Tech Specs,Allowing Increase in Initial Nominal U-235 Enrichment Limit of Fuel Assemblies That May Be Stored in Spent Fuel Pool LIC-96-0008, Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition1996-01-22022 January 1996 Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition ML20108A7161995-12-19019 December 1995 Rev 7 to CH-ODCM-0001, ODCM, Incorporating TS Amend 171 for Section 3.1 Update/Reflect Changing Environ ML20094N8631995-11-16016 November 1995 Proposed Tech Specs,Adding LCO & Surveillance Test for Safety Related Inverters & Deleting Nonsafety Related Instrument Buses ML20092G0771995-09-0606 September 1995 Proposed Tech Spec 2.7,extending Allowed Outage Time from 7 Days Per Month to 7 Days W/ Addl Once Per Cycle 10 Day Allowed Outage Time ML20091P4011995-09-0101 September 1995 Rev 3 to Fort Calhoun Station ISI Program Plan Third Ten-Yr Interval 1993-2003 ML20087E0281995-08-0404 August 1995 Proposed Tech Specs Reducing Minimum Operable Containment Radiation High Signal Channels ML20086D5341995-06-27027 June 1995 Proposed Tech Specs Re Reformation & Clarification of TS Re Chemical & Vol Control Sys ML20091G3601995-06-26026 June 1995 Proposed Tech Specs Re Extension of Allowed Outage Time for an Inoperable Low Pressure SI Pump ML20086D3851995-06-26026 June 1995 Proposed Tech Specs Re Audit Frequencies for Plant QA Program ML20085M0081995-06-15015 June 1995 Rev 2 to ISI Program Plan for 1993-2003 Interval ML20084G7751995-05-31031 May 1995 Proposed Tech Specs,Requesting Amend to Provide Addl Restrictions on Operation of CCW Sys Heat Exchangers ML20083C0091995-05-0808 May 1995 Proposed Tech Specs,Incorporating Proposed Revs Per GL 93-05 to Specs 2.3,3.1,3.2,3.3 & 3.6 ML20087G9691995-04-0707 April 1995 Proposed Tech Specs Re Relocation of Axial Power Distribution Figure for License DPR-40 ML20082J0851995-04-0707 April 1995 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20108A7121995-03-15015 March 1995 Rev 6 to CH-ODCM-0001, ODCM, Incorporating New TS Amend 164 ML20080S0291995-03-0101 March 1995 Proposed Tech Specs Reflecting Administrative Revs to TS 5.5 & 5.8,per GL 93-07 & Revs Unrelated to GL 93-07 to TS 2.5, 2.8,2.11,3.2 & 3.10 1999-05-26
[Table view] |
Text
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\ 6.0 INTERIM SPECIAL TECHNICAL SPECIFICATIONS 6.4 Operation With Less Than 75% of Incore Detector Strings Operable Applicability Applies to power operation during Cycle 6 and supersades Specification 2.10.3(2).
Objective To monitor kw/ft and power distribution with less than 75% of the in-core detector strings operable.
Specification (1) Theincoredetectors{stemshallbeoperabletomonitorpeak linear heat rate, F ,FRT, and the radial power distribution withlessthan75%bbtmorethan20%ofallincoredetector strings and one incore detector string per full length quadrant, where an operable string consists of three or more operable rhodium detectors, provided:
(a) The planar radial peaking factor uncertainty, Uxy, the integrated radial peaking factor uncertainty, U R, and
'
the total peaking factor uncertainty, U q, are determined every 31 EFFD, in accordance with the reference.
(b) If UR > 6% the value of FR to be used in evalcating the approach to the limits of Specification 2.10.4(2) is F =F RM (1 + UR - 0.06)
R where FRU is determined from a power distribution map with no part length CEA's inserted and all full leagth CEA's at or above the Long Term Steady State Insertion limit for the existing Reactor Coolant Pump combination, and the integrated radial peaking factor uncertainty, Rg is the latest determined value of UR at the time U
l
! F R is determined.
(c) If U > 7% the calculated value of F xy to be used in evalNEtingtheapproachtothelimitsofSpecification 2.10.4(3) is Fxy =F xyM (1 + U xy - 0.07).
I where FxyM is determined from a power distribution map with no part length CEA's inserted and all full length CEA's at or above the Long Term Steady State Insertion l limit for the existing Reactor Coolant Pump combination l ,
and the planar radial peaking factor uncertainty, x , is
! the latest determined value of U xy at the time Fxy a determined.
l 6- AT W HMENT A 8101150[,%
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x
.,
.
, ,
6.0 INTERIM SPECIAL TECHNICAL SPECIFICATIONS 6.4 Operation With Less Than 75% of Incore Detector Strings Operable (Continued)
(d) If U as (qI >+ 7%
Uq ) the total shall be peaking uncertainty used in place of thefactor defined measurement-calculation factor of 1.07 in Specification 2.10.4(1).
(e) The maximum local peak linear heat rate in the core, cmax, shall be determined and the incore detector alarms shall be adjusted to no greater than the following:
Alarm Setting = C * @ allowed Smax where C = The detector signal converted to flux units when the reactor is operating at steady-state.
Callowed = Linear Heat Rate (kw/ft) allowed by Specifi-cation 2.10.4(1) and adjusted as required by Specification 6.3(1)(d).
- max = The maximum local peak linear heat rate (kw/ft) measured at the same reactor conditions as C above.
(2) If the incore detector system is not operable within the interval specified, the peak linear heat rate shall be monitored by ex-core detectors per Specification 2.10.4(1)(c) and the surveillance requirements of Specification 3.10(5) are deleted.
Basis Operation of the incore detector system for peak linear heat rate l monitoring and surveillance of FRI and FxyT with less than 75% of the strings operable requires additional measures to compensate l for degradation of the incore instrument system. Periodic com-parisons between calculated and measured power distributions are made to confirm the core is depleting as designed. The measure-
! ment uncertainties are computed to assure the assumptions made in j the setpoint analysis are valid. The uncertainties are computed j using the methods given in the reference.
l If the determined uncertaintics exceed the uncertainties used in the setpoint and safety analysis, the measured values of FR and
! F are augmented by the appropriate uncertainty. These new values l ofFR and F x are then used to verify compliance with Specificat, ions i 2.10.4(2)and2.10.4(3). This assures that the product of the
'
radial peaking fa.ctors and their appropriate uncertainties are '
,
less than the values used in determining the setpoints.
l
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,
-
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.
4 4 6.0 INTERIM SPECIAL TECHNICAL SPECIFICATIONS 6.4 Operation With Less Than 75% of Incore Detector Strings Operable (Continued)
The minimum margin to the kw/ft limit is used to set alarms on all detectors. This imposes restraint on the power distribution as well as the peak linear heat rate and precludes the occurrence of undetected peaks larger than the limit. When incore detectors alarms are set using this method, several alarms would be re-ceived in the event of a shift in the power distribution even though the maximum local peak linear heat rate may not be exceeded.
Reference
~
INCA /CECOR Power Peaking Uncertainty - CENPD-153-P, Revision 1-P-A, May 1980.
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. .
. .
DISCUSSION OF PROPOSED CHANGES TO OPERATING LICENSE The number of incore detector failures has reached Technical Specifications operability limit during operation of Cycle 6 at Fort Calhoun Station. The current status of the incore detector system is shown in Figure 1. The figure shows seven detector strings are inoperable using the operability definition of Technical Specification 2.10.3(2).
Currently, eight detector strings have, single failurce and could become inoperable if a single additional failure occurs in that string. The failures are predominantly occurring in two detector batches. The failures in the detectors inserted during Cycle 2 and at the beginning of Cycle 3 ~
are thought to be "old age" mortality. These detectors were not replaced during the last outage because excessive rhodium depletion was not expected to occur during Cycle 6. The failures occurring in the detectors inserted at the beginning of Cycle 5 are due to an unknown cause. These detectors are from our standard replacement inventory and were manufactured 'at the same time as the batches inserted at the beginning of Cycles 4 and 6.
Failures have not occurred in these batches.
Technical Specification 2.10.3(2) prohibits the use of the incore detector system for peak linear heat rate (kw/ft) monitoring and FR T and Fx I surveillance with more than seven failed incore de-tectorstr[ngs. The proposed Technical Specification will allow continued Cycle 6 operation using the incore detector system with fewer than 75% of the strings operable. To compensate for the system's degradation, several additional requirements are used to assure the core is operating within the limits of the safety analysis.
The existing limits on incore detector operability are imposed to insure the measurement uncertainties are no higher than the uncer-tainties assumed in the safety analysis and setpoint generation and to insure the incore detector system can monitor the peak linear heat rate using a level dependent alarm limit. The pro-posed Technical Specification requires determination of the planar radial peaking factor uncertainty, the integrated radial peaking factor uncertainty, and the total peaking factor uncertainty using the method described in the reference on a periodic basis. These measurement uncertainties are compared to the values assumed in the setpoint analysis and, if they exceed the assumed value, veri-fication is then made to assure the core is operating within the boundary of the setpoint analysis.
'
The safety and setpoint analyses used the products of the peaking factors and the peaking factor uncertainties to define the bounds of the core power distribution. The Technical Specification limits on FR and F assure the core power distribution is within the bounds ofthesafe!yy and setpoint analysis. These limits on FR and Fxy and the measured values of FR and F do not contain any uncertainty becausethesameuncertaintyisuseNyin both the setpoint and safety analysis and the measurement. However, if the measurement uncer-tainties increase, the assurance that the core power distribution is within the bounds of the setpoint and safety analysis is obtained ATTACHMENT B
>
,
. .
. .
by multiplying the peaking factor by the increased uncertainty and comparing it to the limit. The proposed method of calculating F R and Fx increase these values to compensate for the increased un-certainty such that the inequalities yxyLimit > p Measured
-- y (1 + Uxy - 0.07)
F Limit p Measured (1 + UR - 0.06)
R are satisfied.
Figures 2 and 3 show the measured and predicted values of FR and Fxy as a function of exposure for Cycle 6. As can be seen, there is agree-ment between the measured and predicted values, and the core is de-pleting in a predictable manner. Since the Cycle 6 core contains no burnable shims, there is no mechanism to cause the core to con-tinue the depletion in an abnormal fashion. The peaking factors can be expected to follow the predicted trend and remain within the bounds assumed in the analysis, as was seen during the Cycle 5 de-pletion, Figures 4 and 5. The District has continued its core fol-low program during Cycle 6 and the measurement uncertainties are within the values assumed in the safety and setpoint analysis. Con-sidering the large margin between the currently measured values of FR and Fxy and the Technical Specification limits, it is anticipated the proposed specification will provide sufficient operating margin for the remainder of Cycle 6. The peak allowable linear heat rate is calculated using the determined total peaking factor uncertainty if this uncertainty exceeds the value used in Specification 2.10.4(1).
The incore detector alarms are to be set using the minimum margin to the peak linear heat rate as opposed to the current procedure of
'
setting the alarms based on a level dependent margin to the peak linear heat rate. This imposes a restriction en the core power distribution in addition to the existing restriction on peak linear heat rate. Setting the alarms in this fashion detects shifts in i the power distribution as well as approaches to the peak linear heat i rate limit.
I Although it is considered a remote possibility, sufficient failures could occur to prevent compliance with Specification 6.3(1). If this occurs, the peak linear heat rate is to be monitored on the excore detectors. Surveillance of the power distribution to date
- provides sufficient assurance the core power distribution will re-main within the bounds assumed in the safety analysis. Therefore, there is no need to reduce the peak allowable linear heat rate nor T
monitor FR and FxyT. This condition also requires Tq to be monitored
- by the excore detectors.
Reference *
.
INCA /CECOR Power Peaking Uncertainty - CENPD-153-P, Revision 1-P-A, i May 1980.
-
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CALLED NORTH
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CYCLE 6 OPERABLE If! CORE DETECTOR STATUS FIGURE 1
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-16 I 17 17 A B C D EFGHJKLMN P R S T f BATCil LEVEL 1 LEVEL 3 e Closed circle indicates operable detectors.
. LEVEL 2 LEVEL 4 a Open square indicates failed detectors.
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Figure 2 - FORT CALHOUN CYCLE 6 INTEGRATED RADIAL PEAKING FACTOR, FR '
VS CYCLE BURNUP 1.50 - O Predicted -
A Measured 1.49 -
Tech. Spec. Limit 1.52
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Figure 3-FORT CALH0Uti CYCLE 6 PLAtlAR RA01AL PEAKIllG FACTOR,xyF VS CYCLE BURiiUP
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i d 1.41 -
1.40 -
1.39 -
1.38 -
1.37 -
. ,
.
' - - - . .
'
1.36 '
7000 8000 9000 10,000 11.000 2000 3000 4000 5000 6000 0 1000 CYCLE BURNUP (FrdD/MTU)
- -. . - . . . . - - _
.
.
~
Figure 4 - FORT CALHOUN CYCLE 5 INTEGRATED RADIAL PEAKING FACTOR FR -
VS CYCLE BURNUP 1.50 -
O Predicted
-
A Measured 1.49 0 Tech. Spec. Limit 1.52
.
1.48 g 3 1.47 -
g
.
m 1.46 -
u-of 1.45 _
S A M
"- 1.44 -
E G 1.43 -
A b
a 1.42 - ,
5 A
$ 1.41 -
o
"
1.40 .
$
o
"
- 1.39 - A
- a t 1.38 .
A
,
1.37 - ..
~
1.36 -
1.35 -
' ' ' '
' ' ' ' ' ' '
1.04 10,000 11,000 0 1000 2000 3000 4000 5000 6000 7000 8000 9000
CYCLE BURNUP (MWD /MTU)
__
. ____ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ -_ _ _ _ _ __
..
.
.
'
Figure 5 FORT CALHOUN CYCLE 5 PLANAR RADIAL PEAKING FAC10R, Fxy VS CYCLE BURNUP 1.50 - A C) Predicted
-
2k A Measured 1.49 ~ A Tech. Spec. Limit 1.57 1.48 -
1.47 -
A A
1.46 -
u.
k
. 1.45 - g 8
h 1.44 -
u.
A T 1.43 -
k 1,42 -
A 1.41 -
a g g 1.40 -
a 2d 1.39 -
A 1.38 -
1.37 -
1.36 -
1.35 -
- ,
- - . . - .
-
1.34 > '
10,000 11,000 4000 5000 6000 7000 8000 9000 0 1000 2000 3000 CYCLEBURNUP(MWD /NTU)
.
3
. .
JUSTIFICATION FOR FEE CLASSIFICATION The proposed amendment is deemed to be Class III within the meaning of 10 CFR 170.22 since it addresses a single safety issue and does not involve a significant hazard consideration.
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