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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217N3001999-10-21021 October 1999 Proposed Tech Specs,Correcting Two Textual Errors & Changing Designation of Referenced Figure ML20217K8731999-10-18018 October 1999 Proposed Tech Specs Revising Activated Charcoal Testing Methodology IAW Guidance Provided in GL 99-02 ML20212F6941999-09-21021 September 1999 Proposed Tech Specs,Increasing Required Vol of Stored Fuel in Diesel Fuel Oil Storage Tank ML20211J0211999-08-31031 August 1999 Proposed Tech Specs Bases Page 91,allowing Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line (Predicted) Uncorrected Solution & on-line (Measured) 3D-Monicore Exposure Corrected Solution ML20211B7051999-08-18018 August 1999 Proposed Tech Specs Revising Reactor Core Spiral Reloading Pattern to Begin Around SRM ML20211B6781999-08-18018 August 1999 Proposed Tech Specs Revising Definition of Surveillance Frequency to Incorporate Provisions That Apply Upon Discovery of Missed TS Surveillance ML20210D2481999-07-20020 July 1999 Proposed Tech Specs Revising & Clarifying Operability & SRs of High Pressure Core Cooling Systems ML20210D3371999-07-20020 July 1999 Proposed Tech Specs Re Enhancements to Support Implementation of Increased Core Flow ML20209G1671999-07-12012 July 1999 Proposed Tech Specs Revising Value for SLMCPR & Deleting Wording Which Specifies These as Cycle 20 Values ML20196K2951999-06-29029 June 1999 Proposed Tech Specs Pages for Proposed Change 220,revising Leak Rate Requirements of TS 3.7.A.4 & 4.7.A.4 for Main Steam Line Isolation Valves ML20196H2881999-06-24024 June 1999 Proposed Tech Specs Revising & Clarifying Terminology Re Certain RPS Scram Bypass Permissives ML20195J8691999-06-15015 June 1999 Proposed Tech Specs Increasing Stis,Adding Allowable OOS Times,Replacing Generic ECCS Actions for Inoperable Instrument Channels with function-specific Actions & Relocating Selected Trip Functions from TS ML20195F9531999-06-0909 June 1999 Proposed Tech Specs,Supplementing Proposed Change 213, Allowing Use of ASME Code Case N-560,per GL 88-01 ML20195C8841999-05-26026 May 1999 Proposed Tech Specs Clarifying Suppression Chamber Water Temp SR 4.7.A, Primary Containment & Modifying Associated TS Bases ML20206H3771999-05-0606 May 1999 Proposed Tech Specs Pages ,Eleting Specific Leak Rate Requirements of TS 3.7.A.4 & 4.7.A.4 ML20206J7231999-05-0505 May 1999 Proposed Tech Specs Pages for Proposed Change 212,modifying TS to Enhance Limiting Conditions for Operation & Surveillance Requirements Relating to SLC Sys ML20205S9431999-04-20020 April 1999 Proposed Tech Specs,Revising Reactor Core Spiral Reloading Pattern Such That It Begins Around Source Range Monitor ML20205T4721999-04-19019 April 1999 Marked-up Tech Specs Pages Re Suppl to 990201 Request for Amend to License DPR-28,revising Portions of Proposed Change 208 ML20205S4081999-04-16016 April 1999 Proposed Tech Specs Modifying Inservice Insp Requirements of Section 4.6.E to Allow NRC-approved Alternatives to GL 88-01 ML20205S3121999-04-15015 April 1999 Proposed Tech Specs Revised Bases Pages 90,227,164 & 221a, Accounting for Change in Reload Analysis,Reflecting Change in Condensation Stability Design Criteria & Accounting for More Conservative Calculation ML20202E5451999-01-25025 January 1999 Proposed Tech Specs Re Technical Requirements Manual Content ML20206S0661999-01-22022 January 1999 Proposed TS to Change Number 189,proposing Relocation of Fire Protection Requirements from TSs to TRM ML20198D5381998-12-15015 December 1998 Proposed Tech Specs Page 142,correcting Wording to Reflect Previously Approved Wording,Last Revised in Amend 160 ML20198B7421998-12-11011 December 1998 Proposed Tech Specs Changing Wording of Primary Containment Integrity Definition to State That Manual PCIVs Which Are Required to Be Closed During Accident Conditions May Be Opened Intermittently Under ACs ML20197J4631998-12-10010 December 1998 Proposed Tech Specs Section 4.9.2,revising Info Re Calibr of Augmented Offgas Sys Hydrogen Monitors ML20197H0031998-12-0707 December 1998 Proposed Tech Specs Change 209,resolving Emergency Concern Re Potential Operation Outside of LCO Contained in Current TS & Potential USQ with Respect to Opening of Manual PCIVs During Plant Operation ML20155F7421998-11-0303 November 1998 Proposed Tech Specs Incorporating Minor Corrections or Clarifications Which Enhance Clarity of TSs Without Materially Changing Meaning or Application ML20155G5061998-11-0202 November 1998 Proposed Tech Specs Re ECCS Actuation Instrumentation - LPCI A/B RHR Pump Start Time Delay Requirements & CS Sys A/B Pump Start Delay Requirements ML20151U0131998-09-0404 September 1998 Proposed Tech Specs,Increasing Spent Fuel Storage Capacity of Util Spent Fuel Pool from 2,870 to 3,355 Fuel Assemblies ML20236H4551998-06-30030 June 1998 Proposed Tech Specs Modifying Table 4.2.1 to Delete ECC Actuation Instrumentation Re Core Spray Sys & LPCI Sys Auxiliary Power Monitor Calibr Requirement ML20247E5671998-05-0808 May 1998 Proposed Tech Specs Page 270,containing Wording Inadvertently Deleted from TS Proposed Change 202 ML20247J8121998-05-0808 May 1998 Proposed Tech Specs Reducing Normal Operating Suppression Pool Water Temp Limit & Adding Time Restriction for Higher Temp Allowed During Surveillances That Add Heat to Suppression Pool ML20217P4171998-05-0101 May 1998 Proposed Tech Specs Re Administrative Controls Section ML20217G7131998-04-23023 April 1998 Proposed Tech Specs Change 200 Revising Station SW & Alternate Cooling Sys Requirements ML20217C4591998-03-20020 March 1998 Proposed Tech Specs Re Containment Purge & Vent ML20217A1271998-03-13013 March 1998 Proposed Tech Specs Bases Section 3.10.B,updated to Require That Station Battery,Eccs Instrumentation Battery,Or Uninterruptable Power Sys Battery Be Considered Inoperable If Any One Cell Is Below Specification Cell Voltage ML20202H2611998-02-0606 February 1998 Revised TS Pages Re Change 190,w/typos Corrected ML20197E8481997-12-22022 December 1997 Replacement Pages 160 & 279 & mark-up Pages to Proposed TS Change 190 Containing Editorial Changes ML20203F0131997-12-11011 December 1997 Proposed Tech Specs Revising Current Value for SLMCPR for Cycle 20,next Operating Cycle ML20199K8501997-11-21021 November 1997 Replacement Pages 147,156,157 & mark-up Pages to Proposed TS Change 190,removing Ref to Documents Outside of TS That Define Components to Which Program Applies ML20199J7661997-11-20020 November 1997 Proposed Tech Specs Pages,Revising Requirements for Main Station Batteries ML20217H6931997-10-10010 October 1997 Proposed Tech Specs Revising & Clarifying Requirements for Offsite Power Sources ML20211A6461997-09-18018 September 1997 Proposed Tech Specs,Providing marked-up Pages for Proposed Changes 192 & 193 ML20217Q3311997-08-22022 August 1997 Proposed Tech Specs Pages 245 & 252,amending App a to Modify TS to More Clearly Describe Separation of Switchgear Room Into Two Fire Areas & Incorporate Specifications for New Low Pressure CO2 Suppression Sys ML20217N4111997-08-20020 August 1997 Proposed Tech Specs Pages 270 & 270a,updating Section 6 in Order to Add & Revise Ref to NRC Approved Methodologies Which Will Be Used to Generate cycle-specific Thermal Operating Limits to COLR ML20141H1171997-07-11011 July 1997 Proposed Tech Specs,Replacing Pages 147,156 Through 161,168 & 279 of Util TS W/Corrected Pages ML20148J1861997-06-0909 June 1997 Proposed Tech Specs Change 191,updating Section 6.0 Administrative Controls ML20132B5771996-12-10010 December 1996 Proposed Tech Specs 3.13 Re Fire Protection Sys ML20129C4521996-10-17017 October 1996 Proposed Tech Specs,Revising Pages 89,89a & 90 to Incorporate Changes from Amends 148 & 149 ML20128N6031996-10-11011 October 1996 Proposed Tech Specs,Revising Existing Requirements Re Amount of Foam Concentrate Required to Support Operability of Recirculation Motor Generator Set Foam Sys in TS 3.13.G.1 & 3.13.G.2 1999-09-21
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217N3001999-10-21021 October 1999 Proposed Tech Specs,Correcting Two Textual Errors & Changing Designation of Referenced Figure ML20217K8731999-10-18018 October 1999 Proposed Tech Specs Revising Activated Charcoal Testing Methodology IAW Guidance Provided in GL 99-02 ML20212F6941999-09-21021 September 1999 Proposed Tech Specs,Increasing Required Vol of Stored Fuel in Diesel Fuel Oil Storage Tank ML20211J0211999-08-31031 August 1999 Proposed Tech Specs Bases Page 91,allowing Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line (Predicted) Uncorrected Solution & on-line (Measured) 3D-Monicore Exposure Corrected Solution ML20211B6781999-08-18018 August 1999 Proposed Tech Specs Revising Definition of Surveillance Frequency to Incorporate Provisions That Apply Upon Discovery of Missed TS Surveillance ML20211B7051999-08-18018 August 1999 Proposed Tech Specs Revising Reactor Core Spiral Reloading Pattern to Begin Around SRM ML20210D2481999-07-20020 July 1999 Proposed Tech Specs Revising & Clarifying Operability & SRs of High Pressure Core Cooling Systems ML20210D3371999-07-20020 July 1999 Proposed Tech Specs Re Enhancements to Support Implementation of Increased Core Flow ML20209G1671999-07-12012 July 1999 Proposed Tech Specs Revising Value for SLMCPR & Deleting Wording Which Specifies These as Cycle 20 Values ML20196K2951999-06-29029 June 1999 Proposed Tech Specs Pages for Proposed Change 220,revising Leak Rate Requirements of TS 3.7.A.4 & 4.7.A.4 for Main Steam Line Isolation Valves ML20196H2881999-06-24024 June 1999 Proposed Tech Specs Revising & Clarifying Terminology Re Certain RPS Scram Bypass Permissives ML20195J8691999-06-15015 June 1999 Proposed Tech Specs Increasing Stis,Adding Allowable OOS Times,Replacing Generic ECCS Actions for Inoperable Instrument Channels with function-specific Actions & Relocating Selected Trip Functions from TS ML20195F9531999-06-0909 June 1999 Proposed Tech Specs,Supplementing Proposed Change 213, Allowing Use of ASME Code Case N-560,per GL 88-01 ML20195C8841999-05-26026 May 1999 Proposed Tech Specs Clarifying Suppression Chamber Water Temp SR 4.7.A, Primary Containment & Modifying Associated TS Bases ML20206H3771999-05-0606 May 1999 Proposed Tech Specs Pages ,Eleting Specific Leak Rate Requirements of TS 3.7.A.4 & 4.7.A.4 ML20206J7231999-05-0505 May 1999 Proposed Tech Specs Pages for Proposed Change 212,modifying TS to Enhance Limiting Conditions for Operation & Surveillance Requirements Relating to SLC Sys ML20205S9431999-04-20020 April 1999 Proposed Tech Specs,Revising Reactor Core Spiral Reloading Pattern Such That It Begins Around Source Range Monitor ML20205T4721999-04-19019 April 1999 Marked-up Tech Specs Pages Re Suppl to 990201 Request for Amend to License DPR-28,revising Portions of Proposed Change 208 ML20205S4081999-04-16016 April 1999 Proposed Tech Specs Modifying Inservice Insp Requirements of Section 4.6.E to Allow NRC-approved Alternatives to GL 88-01 ML20205S3121999-04-15015 April 1999 Proposed Tech Specs Revised Bases Pages 90,227,164 & 221a, Accounting for Change in Reload Analysis,Reflecting Change in Condensation Stability Design Criteria & Accounting for More Conservative Calculation ML20202E5451999-01-25025 January 1999 Proposed Tech Specs Re Technical Requirements Manual Content ML20206S0661999-01-22022 January 1999 Proposed TS to Change Number 189,proposing Relocation of Fire Protection Requirements from TSs to TRM ML20198D5381998-12-15015 December 1998 Proposed Tech Specs Page 142,correcting Wording to Reflect Previously Approved Wording,Last Revised in Amend 160 ML20198B7421998-12-11011 December 1998 Proposed Tech Specs Changing Wording of Primary Containment Integrity Definition to State That Manual PCIVs Which Are Required to Be Closed During Accident Conditions May Be Opened Intermittently Under ACs ML20197J4631998-12-10010 December 1998 Proposed Tech Specs Section 4.9.2,revising Info Re Calibr of Augmented Offgas Sys Hydrogen Monitors ML20197H0031998-12-0707 December 1998 Proposed Tech Specs Change 209,resolving Emergency Concern Re Potential Operation Outside of LCO Contained in Current TS & Potential USQ with Respect to Opening of Manual PCIVs During Plant Operation ML20155F7421998-11-0303 November 1998 Proposed Tech Specs Incorporating Minor Corrections or Clarifications Which Enhance Clarity of TSs Without Materially Changing Meaning or Application ML20155G5061998-11-0202 November 1998 Proposed Tech Specs Re ECCS Actuation Instrumentation - LPCI A/B RHR Pump Start Time Delay Requirements & CS Sys A/B Pump Start Delay Requirements ML20196A7851998-10-0909 October 1998 Rev 19 to Vynp IST Program Plan ML20151U0131998-09-0404 September 1998 Proposed Tech Specs,Increasing Spent Fuel Storage Capacity of Util Spent Fuel Pool from 2,870 to 3,355 Fuel Assemblies ML20237E9571998-08-27027 August 1998 Start-Up Test Rept Vynp Cycle 20 ML20236H4551998-06-30030 June 1998 Proposed Tech Specs Modifying Table 4.2.1 to Delete ECC Actuation Instrumentation Re Core Spray Sys & LPCI Sys Auxiliary Power Monitor Calibr Requirement ML20247J8121998-05-0808 May 1998 Proposed Tech Specs Reducing Normal Operating Suppression Pool Water Temp Limit & Adding Time Restriction for Higher Temp Allowed During Surveillances That Add Heat to Suppression Pool ML20247E5671998-05-0808 May 1998 Proposed Tech Specs Page 270,containing Wording Inadvertently Deleted from TS Proposed Change 202 ML20217P4171998-05-0101 May 1998 Proposed Tech Specs Re Administrative Controls Section ML20217G7131998-04-23023 April 1998 Proposed Tech Specs Change 200 Revising Station SW & Alternate Cooling Sys Requirements ML20217C4591998-03-20020 March 1998 Proposed Tech Specs Re Containment Purge & Vent ML20217A1271998-03-13013 March 1998 Proposed Tech Specs Bases Section 3.10.B,updated to Require That Station Battery,Eccs Instrumentation Battery,Or Uninterruptable Power Sys Battery Be Considered Inoperable If Any One Cell Is Below Specification Cell Voltage ML20202H2611998-02-0606 February 1998 Revised TS Pages Re Change 190,w/typos Corrected ML20197E8481997-12-22022 December 1997 Replacement Pages 160 & 279 & mark-up Pages to Proposed TS Change 190 Containing Editorial Changes ML20203F0131997-12-11011 December 1997 Proposed Tech Specs Revising Current Value for SLMCPR for Cycle 20,next Operating Cycle ML20199K8501997-11-21021 November 1997 Replacement Pages 147,156,157 & mark-up Pages to Proposed TS Change 190,removing Ref to Documents Outside of TS That Define Components to Which Program Applies ML20199J7661997-11-20020 November 1997 Proposed Tech Specs Pages,Revising Requirements for Main Station Batteries ML20217H6931997-10-10010 October 1997 Proposed Tech Specs Revising & Clarifying Requirements for Offsite Power Sources ML20211A6461997-09-18018 September 1997 Proposed Tech Specs,Providing marked-up Pages for Proposed Changes 192 & 193 ML20217Q3311997-08-22022 August 1997 Proposed Tech Specs Pages 245 & 252,amending App a to Modify TS to More Clearly Describe Separation of Switchgear Room Into Two Fire Areas & Incorporate Specifications for New Low Pressure CO2 Suppression Sys ML20217N4111997-08-20020 August 1997 Proposed Tech Specs Pages 270 & 270a,updating Section 6 in Order to Add & Revise Ref to NRC Approved Methodologies Which Will Be Used to Generate cycle-specific Thermal Operating Limits to COLR ML20141H1171997-07-11011 July 1997 Proposed Tech Specs,Replacing Pages 147,156 Through 161,168 & 279 of Util TS W/Corrected Pages ML20148J1861997-06-0909 June 1997 Proposed Tech Specs Change 191,updating Section 6.0 Administrative Controls ML20149M7451997-01-24024 January 1997 Startup Test Rept,Vermont Yankee Cycle 19 1999-09-21
[Table view] |
Text
nsW:
At t ach me n t 1
'@$20 Description of Proposed Changes to Technical Specifica tior..
43 kw OO 00 Reason for Change OM S7ction/ Location Ch ange 70-g uo) gg1) Table 3.11-2, p. 180-01 Change MCPR operating limits per Per licensing analysis results using Vermont 0,o a ttached changed page. Yankee methods.
"D M O ONM m-
- 2) Bases 3.11.C.1, p. 180-h Replace current wording with the The current words refer to a GE licensing following: "The MCPR Opera ting Limit is topical report. The proposed wording is a a cycle dependent parameter which can be more general description of the basis for determined for a number of different determining the MCPR operating limit, and combina tions of operating modes, initial thus does not conflict with the use of VY conditions, and cycle exposures in order me thod s to determine the limit.
to provide reasonable assurance against exceeding the fuel cladding integrity safety limit (FCISL) for potential abnormal occurrences. The MCPR Operating Limits are presented in Appendix A of the current cycle's Core Performance Analysis report.
- 3) L.C.O. 3.3C, pp. 72, Reduce control rod scram times. To provide additional MCPR margin to limits i /2a and 73 under EOC operating condtions where the MCPR l opera ting limit is set by the limiting overpressurization transient.
- 4) Bases 3.3B.4, p. 76 Remove reference to NEDE-24011P-A and Consistent with change to Vernont Yankee replace with reference to Vermont Yankee methods and documentation of analysis results.
Core Performance Analysis report.
b
VYNPS 5.3 LIMITING CONDITIONS FOR OPERATION 4.3 SURVEILLANCE REQUIREMENTS C. Scram Insertion Times C. Scram Insertion Times 1.1 The average scram time, based on the 1. After refueling outage at.o pMor to operation de-energization of the scram pilot above 30% power with reactor pressure above valve solenoids of all operable control 800 psig all control rods shall be subject to rods in the reactor power operation scram-time measurements f rom the full.y condition shall be no greater than: withdrawn position. The scram times for single rod scram testing shall be measured without Drop-Out of %In.serted From Avg. Scram Insertion reliance on the control rod drive pumps.
Position Fully Withdrawn Time (sec)
- 2. During or following a controlled shutdown of the 46 4.51 0.358 reactor, but not more frequently than 16 weeks 36 25.34 0.912 nor less frequently than 32 weeks intervals, 26 46.18 1.468 50% control rod drives in each quadrant of 06 87.84 2.686 the reactor core shall be measured for scram times specified in Specification 3.3.C. All The average of the scram insertion times control rod drives shall have experienced for the three fastest control rods of all scram-time measurements each year. Whenever '
groups of four control rods in a two by 50% of the control rod drives scram times have two array shall be no greater than: been measured, an evaluation shall be made to provide reasonable assurance that proper Drop-Out of % Inserted From Avg. Scram Insertion control rod drives performance is being Position Fully Withdrawn Time (sec) maintained. The results of measurements per-formed on the control rod drives chall be 46 4.51 0.379 submitted in the start up test report.
36 25.34 0.967 26 46.18 1.556 06 87.84 2.848 1
i 72
- _ _. . . . . _ . _ . _ _ _ _ _ - - _ . ~ _ - - - .
VYNPS 3.3 LIMITING CONDITIONS FOR OPERATION 4.3 SURVEILLANCE REQUIREMENTS 1.2 If Specification 3.3.C.l.1 cannot be met, the average scram time, based on the de-energization of the scram pilot valve solenoids of all operable control rods in the reactor power operation condition shall be no greater than:
Drop-Out of % Inserted From Avg. Scram Insertion Position Fully Withdrawn Time (sec) 46 4.51 .358 36 25.34 1.096 26 46.18 1.860 06 87.84 3.419 The average of the scram insertion times for the three fastest control rods of all groups of four control rods in a two by
- two array shall be no greater than
Drop-Out of % Inserted From Avg. Scram Insertion
! Position Fully Withdrawn Time (sec)
- 46 4.51 .379 36 25.34 1.164 l
26 46.18 1.971 l 06 87.84 3.624 t
j 2. The maximum scram insertion time for 90%
! insertion of any operable control rod shall I
not exceed-7.00 seconds.
-72a
i s
i VYNPS l '3.3 -LIMITING CONLITIONS FOR OPERATION 4.3 SURVEILLANCE REQUIREMENTS l ]3. If ' Specification ').3.C.1.2 cannot be m:t.,
i the reactor shall not be made super-l critical; if operating, the reactor
.shall be shut down immediately upon i determination that average scram time is deficient.
- 4. If Specification 3.3.C.2 cannot be j met, the deficient' control rod shall j be considered inoperable, fully
- inserted into the core, and
- electrically disarmed.
i 1
1 I
i-4 j
j D. Control Rod Accumulators D. Control Rod Accumulators -
l At all reactor operating pressures, a rod Once a shift check the status of the pressure i accumulator. may be inoperable provided that no and level alarms for each accumulator, j other control rod in the nine-rod square array 1
around this rod has a:
1 c
]
i 4
i i '73 j.
i
VYNPS 3.3 (cont 'd)
B. Control Rods
- 1. Control rod dropout accidents as discussed in the FSAR can lead to signif cant core damage. If coupling integrity is maintained, the possiblity of a rod dropout accident is eliminated. The overtravel position feature pr vides a positive check as only uncoupled drives may reach this position. Neutron instrumentation response to rod movement provides a verification that the rod is following its drive.
- 2. The control rod housing support restricts the outward movement of a control rod to less than 3 inches in the extremely remote event of a housing failure. The amount of reactivity which could be added by this small amount of rod withdrawal, which is less than a normal single withdrawal increment, will not contribute to any damage of the primary coolant system. The design basis .ven in Subsection 3.5.2 of the FSAR, and the design evaluation is given in Subsection 3.5.4. This auE . is not required if the reactor coolant system is at atmospheric pressure since there would then be no driving force to rapidly eject a drivu housing.
- 3. In the course of performing normal startup and shutdown procedures, a pre-specified sequence for the withdrawal or insertion of control rods is followed. Control rod dropout accidents which might lead to significant core damage, ca inot occur if this sequence of rod withdrawals or insertions is followed. The Rod Worth Minimizer restric;s withdrawals and insertions to those listed in the pre-specified sequence and provides an additional check that the reactor operator is following prescribed sequence. Although beginning a rasc*or startup without having the RWM operable would entail unnecessary risk, continuing to withdra:r rods RWM fails subsequently if a second licensed operator verifies the withdrawal sequence. Continuing L... startup increases core power, reduces the rod worth and reduces tl.e consequences of dropping any rod.
Withdrawal of rods for testing is permitted with the RWM inoperable, if the reactor is subcritf. cal and all other rods are fully inserted. Above 20% power, the RWM is not needed since even with a single error an operator cannot withdraw a rod with suf ficient 'iorth, which if dec pped, would result in anything but minor cons eque nce s.
- 4. Refer to the Vermont Yankee Core Performance Analysis report.
76
s.
VYNPS Table 3.11-2 MCPR Operating Limits MCPR Operating Limit for
! Value of "N" in RBM Average Control Rod Cycle Fuel Type (2)
Equa t ion (1) Scram Time Exposure Range 8X8 8X8R P8X8R 42% Equal or better BOC to EOC-2 GWD/T 1.29 1.29 1.29 1 than L.C.O. EOC-2 GWD/T to EOC-1 GWD/T 1.29 1.29 1.29 3.3 C.1.1 EOC-1 GWD/T to EOC 1.29 1.29 1.29 Equal or better BOC to EOC-2 GWD/T 1.29 1.29 1.29
, th an L.C.O. EOC-2 GWD/T to 20C-1 GWD/T 1.30 1.30 1.30
- 3.3 C.1.2 ~
EOC-1 GWD/T to EOC 1.33 1.32 1.32 41% Equal or better BOC to EOC-2 GWD/T 1.25 1.25 1.25 than L.C.O. EOC-2 GWD/T to EOC-1 GWD/T 1.25 1.25 1.25 3.3 C.1.1 EOC-1 GWD/T to EOC 1.27 1.27 1.27
^
Equal or better BOC to EOC-2 GWD/T 1.25 1.25 1.25 th an L.C.O. EOC-2 GWD/T to EOC-1 GWD/T 1.30 1.30 1.30 j . 3.3 C.I.2 EOC-1 GWD/T to EOC 1.33 1.32 1.32 .
(40% Equal or better BOC to EOC-2 GWD/T 1.24 1.24 1.24 th an L. C . O . EOC-2 GWD/T to EOC-1 GWD/T 1.24 1.23 1.23
- 3.3 C.1.1 EOC-1 GWD/T to EOC 1.27 1.27 1.27 .
Equal or better BOC to EOC-2 GWD/T 1.24 1.24 1.24 l than L.C.O. EOC-2 GWD/T to EOC-1 GWD/T 1.30 1.30 1.30 3.3 C.1.2 EOC-1 GWD/T to EOC 1.33 1.32 1.32 4
4 75% Special Testing at Natural Circ nlation (Note 3, 4) 1.30 1.31 1.31
! (1) The Rod Block Monitor (RBM) trip setpoints are determined by the equation shown in Table 3.2.5 of the Technical' Speci fica tions.
}
! (2) The current analyses for MCPR Operating Limits do not include 7x7 fuel. On this basis further evaluation of MCPR operating limits is required before 7x7 fuel can be used in Reactor Power Operation.
-(3). For the duration of pump trip and stability testing.
(4) Kf factors are not applied during the pump trip and stability testing.
180-01 4
w
. _ _ _ _ . _ _ . . . . _ . _ _ . _ _ _ _ . . __. _. .m Bases:
l 3.11C Minimum Critical Power Ratio (MCPR) j Opera ting Limit MCPR I
l'. The MCPR Operating Limit is a cycle dependent parameter which can be determined for a number of l di fferent combina tions of opera ting modes, initial e -ditions, and cycle exposures in order to i l provede reasonable assurance agains t exceeding the ruel cladding integrit'y safety limit (FCISL) for potential abnormal occurences. The MCPR operating limits' are presented in Appendix A of the current cycle's Core Performance Analysis report.
-2. In order to counteract the postulated thermal margin degradation for the worst-casa Fuel Loading-Error accident, a higher MCPR opt. rating limit is applied to the event air ejector off gas radiation exceeds levels that could be associated with a mis-load fuel assembly.
O e
f 180-h
. . -. _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _