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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML17300B3791999-10-0808 October 1999 Proposed Tech Specs,Waiving Requirement to Perform SR 3.8.4.8 for Unit 1 Channels A,B & C on One Time Basis ML17300B3521999-09-29029 September 1999 Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7 ML17300B3321999-09-14014 September 1999 Marked-up Tech Specs Pages to TS 5.5.2 & 5.6.2,making Noted Administrative Changes ML17313B0601999-08-31031 August 1999 Rev 1 to PVNGS TS Bases Implemented Between Aug 1998 & Jul 1999 ML17313A9571999-05-26026 May 1999 Proposed Tech Specs,Reducing Spurious Reactor Trip Hazards Associated with Setpoints While Maintaining Plant Protection ML17313A4181998-06-0909 June 1998 Proposed Improved Tech Specs Sections 3.5.1 & 3.5.2,revising Safety Injection tanks-operating & Safety Injection Tanks Shutdown ML17313A1141997-11-0707 November 1997 Improved TS Pages for Section 3.0, LCO & SR Applicability, Section 3.1, Reactivity Control & Section 3.2, Power Distribution Limits. Generic Change to NUREG-1432,Rev 1 Incorporated Into Section 3.0 & 3.1 ML17312B6411997-08-28028 August 1997 Proposed Tech Specs,Allowing one-time Extension of Required Surveillance Interval for Msi Sys Portion Only of ESFAS Logic ML20217Q6801997-08-22022 August 1997 Proposed Tech Specs,Clarifying Wording in TS Bases 3/4.6.1.4, Internal Pressure ML20141H7831997-07-18018 July 1997 Proposed Improved Tech Specs Section 3.8, Electrical Power Sys ML20141H7461997-07-18018 July 1997 Proposed Tech Specs,Providing Addl Info Re Improved TS Section 3.4, Rcs ML17312B0311996-11-0606 November 1996 Proposed Tech Specs 3/4.8.1.1 Re A.C. Sources - Operating ML17300B2651996-06-17017 June 1996 Proposed Tech Specs,Changing Section 1.10 & 3.2.8 & Associated Bases for Obtaining Thyroid Dcfs Used in Definition of Dose Equivalent I-131 ML17312A6491996-04-0101 April 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Temporarily Allow Use of Hoist Instead of Refueling Machine for Movement of Fuel Assembly at Core Location A-07 ML17312A6401996-03-26026 March 1996 Proposed Tech Specs 3/4.9.6,increasing Refueling Machine Overload Cut Off Limit to 2,000 Lb,In 50 Lb Increments,For Removal of Stuck Fuel Assembly from Core Location A-06 ML17312A6321996-03-26026 March 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Relocate Refueling Machine Overload Cut Off Limit from TS 3/4.9.6 to Plant UFSAR Per Criteria in 10CFR50.36 & Rev 1 of NUREG-1432 STS for C-E Plants. ML17312A6371996-03-23023 March 1996 Proposed Tech Specs,Revising TS SR 4.8.2.1.e, DC Sources, to Suspend Provision of TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Entry Into Mode 4 Following Sixth Refueling Outage ML17312A5011996-01-17017 January 1996 Revised Page 5-1 Changing Section 5.2.2 to Include Description of Material Used for Control Element Assemblies ML17311B3221995-12-20020 December 1995 Proposed Tech Specs,Reducing Setpoint for MSIS & Rt on Low SG Pressure ML17311B0301995-07-0303 July 1995 Proposed Tech Specs Re Temp Method to Respond to Sustained Degraded Switchyard Voltage ML17311A9771995-06-21021 June 1995 Proposed Tech Specs,Modifying Tables 3.3-4 & 3.3-5 of Section 3/4.3.2 of Esfa Sys Instrumentation ML17311A8651995-05-0202 May 1995 Proposed TS 3.1.2.6,Figure 3.1-1, Min Borated Water Vols, Relocating Elevations That Correspond to Min Required Water Vols for Spent Fuel Pool Into Site Procedures ML17311A8231995-04-18018 April 1995 Proposed Tech Specs Section 3/4.4.4 Re Sleeving Process for SG Tube Repair ML17311A5631994-12-28028 December 1994 Proposed TS Sections 3.9.6 & 4.9.6.1 Re Refueling Machine ML17311A5021994-12-0707 December 1994 Proposed Tech Specs,Changing Note 5 to Table 4.3-1 of TS 3/4.3.1 to Allow Verification of Shape Annealing Matrix Elements Used in Core Protection Calculators ML17311A4341994-11-30030 November 1994 Proposed TS 3/4.4.2,changing Pressurizer Code Safety Valve Lift Setting from 2,500 Psia to 2,475 Psia in LCOs 3.4.2.1 & 3.4.2.2 ML17311A3851994-10-31031 October 1994 Proposed Tech Spec Sections 3.9.6 & 4.9.6.1, Refueling Machine. ML17311A3341994-10-0909 October 1994 Proposed Tech Specs Suspending TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Mode 4 Following Fifth Refueling Outage ML17311A2171994-08-18018 August 1994 Proposed Tech Specs Adding Analytical Method Suppl Entitled, Calculative Methods for CE Large Break LOCA Evaluation Model for Analysis of CE & W Designed Nsss. ML17310B4511994-07-12012 July 1994 Proposed Tech Specs Amend to Add One Action Statement to Table 3.3-3,entry 8 ML17310B4151994-07-0101 July 1994 Proposed Tech Specs Re Reactor Coolant Cold Leg Temperature Vs Core Power Level of TS 3.2.6 ML17310B4331994-06-20020 June 1994 Proposed Tech Specs Sections 5.3.1 & 5.6.1, & New TS Section 3/4.9.13 & Bases 3/4.9.13 ML17310B4091994-06-17017 June 1994 Proposed Tech Specs Removing Five Tables of Component Lists Per GL-91-08 ML17310B1661994-03-28028 March 1994 Proposed Tech Specs Re Min Condensate Storage Tank Indicated Level ML17310B0611994-02-18018 February 1994 Proposed Tech Specs Figure 3.2-1,Section 3/4.1.1.4 & Bases 3/4.1.1.4,establishing Min Temp for Criticality at 545 F for Facilities ML17310B0001994-01-19019 January 1994 Proposed Tech Specs of AF Automatic Actuation Logic Surveillance Frequency Extension ML17310A8361993-11-16016 November 1993 Proposed Tech Specs Table 4.2-4, Min Staffing Requirements for PVNGS Emergencies, in Support of Proposed Rev to Emergency Plan ML17310A7351993-10-26026 October 1993 Proposed Tech Specs Changing Maximum Nominal Enrichment of Fuel Allowed to Be Used in Reactor Core ML17310A6161993-09-0808 September 1993 Proposed Tech Specs Section 6.9.1.10 Re Sys 80 Inletflow Distribution to List of Methods Used to Determine Core Operating Limits ML17310A5211993-08-0505 August 1993 Proposed Tech Specs Requesting to Change Word Pressurizer to RCS for Item #4 in Both Tables 3.3-10 & 4.3-7 ML17310A5151993-08-0505 August 1993 Proposed Tech Specs Changing Surveillance Frequency from Monthly to Quarterly for Channel Functional Tests for RPS & ESFAS Instrumentation ML17310A4211993-06-30030 June 1993 Proposed Tech Specs Requesting Addl Operating Margin in Time Response of Turbine Driven AF Pump to SG Low Level Signal ML17310A2981993-05-20020 May 1993 Proposed TS 4.7.9 Re SR to Ensure Operability of Snubbers ML17306B2671993-01-25025 January 1993 Proposed Tech Specs,Reflecting Revised Train a Kw Value to Be Rejected & Load Designation & Incorporation of Provisions Discussed in 920508 Ltr Re DG Full Load Rejection Testing ML17306B1451992-11-20020 November 1992 Proposed Tech Specs Revising TS 3.2.1 Lhr, & TS 3.2.4, DNBR Margin, Increasing Action from 1 H to 4 H for COLSS Allowed Out of Svc Time Before Requirements Based on More Restrictive Core Protection Calculator Limits Apply ML17306A6491992-04-13013 April 1992 Proposed TS 3.4.8.3 Re RCS - Overpressure Protection Sys ML17306A4731992-02-14014 February 1992 Proposed Tech Specs Re Implementation of Generic Ltr 89-01, Implementation of Programmatic Controls for Radiological Effluent TS in Administrative Controls Section of TS & Relocation of Procedural Details of RETS to Odcm.... ML17306A4031992-01-16016 January 1992 Proposed Tech Specs Amend to TS Section 3.6.3,table 3.6-1 Deleting Type C Testing Requirements for Eight Valves ML17306A3701991-12-30030 December 1991 Proposed Tech Spec Table 6.2-1 Re Min Shift Crew Composition ML17306A3781991-12-30030 December 1991 Proposed Tech Spec Section 3.6.1.7 Re Containment Purge Supply & Exhaust Valves 1999-09-29
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17300B3791999-10-0808 October 1999 Proposed Tech Specs,Waiving Requirement to Perform SR 3.8.4.8 for Unit 1 Channels A,B & C on One Time Basis ML17300B3521999-09-29029 September 1999 Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7 ML17300B3321999-09-14014 September 1999 Marked-up Tech Specs Pages to TS 5.5.2 & 5.6.2,making Noted Administrative Changes ML17313B0601999-08-31031 August 1999 Rev 1 to PVNGS TS Bases Implemented Between Aug 1998 & Jul 1999 ML17313B0081999-07-14014 July 1999 Rev 2 to Inservice Insp Program Summary Manual for PVNGS Unit 1. ML17313A9571999-05-26026 May 1999 Proposed Tech Specs,Reducing Spurious Reactor Trip Hazards Associated with Setpoints While Maintaining Plant Protection ML17313A7511998-12-16016 December 1998 Rev 2 to ISI Program Summary Manual, for PVNGS Unit 3 ML17313A4181998-06-0909 June 1998 Proposed Improved Tech Specs Sections 3.5.1 & 3.5.2,revising Safety Injection tanks-operating & Safety Injection Tanks Shutdown ML17313A1141997-11-0707 November 1997 Improved TS Pages for Section 3.0, LCO & SR Applicability, Section 3.1, Reactivity Control & Section 3.2, Power Distribution Limits. Generic Change to NUREG-1432,Rev 1 Incorporated Into Section 3.0 & 3.1 ML17312B6411997-08-28028 August 1997 Proposed Tech Specs,Allowing one-time Extension of Required Surveillance Interval for Msi Sys Portion Only of ESFAS Logic ML20217Q6801997-08-22022 August 1997 Proposed Tech Specs,Clarifying Wording in TS Bases 3/4.6.1.4, Internal Pressure ML20141H7831997-07-18018 July 1997 Proposed Improved Tech Specs Section 3.8, Electrical Power Sys ML20141H7461997-07-18018 July 1997 Proposed Tech Specs,Providing Addl Info Re Improved TS Section 3.4, Rcs ML17312B0311996-11-0606 November 1996 Proposed Tech Specs 3/4.8.1.1 Re A.C. Sources - Operating ML17300B2651996-06-17017 June 1996 Proposed Tech Specs,Changing Section 1.10 & 3.2.8 & Associated Bases for Obtaining Thyroid Dcfs Used in Definition of Dose Equivalent I-131 ML17312A9451996-05-14014 May 1996 Rev 3 to Significant Condition Investigation. ML17312A6491996-04-0101 April 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Temporarily Allow Use of Hoist Instead of Refueling Machine for Movement of Fuel Assembly at Core Location A-07 ML17312A6401996-03-26026 March 1996 Proposed Tech Specs 3/4.9.6,increasing Refueling Machine Overload Cut Off Limit to 2,000 Lb,In 50 Lb Increments,For Removal of Stuck Fuel Assembly from Core Location A-06 ML17312A6321996-03-26026 March 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Relocate Refueling Machine Overload Cut Off Limit from TS 3/4.9.6 to Plant UFSAR Per Criteria in 10CFR50.36 & Rev 1 of NUREG-1432 STS for C-E Plants. ML17312A6371996-03-23023 March 1996 Proposed Tech Specs,Revising TS SR 4.8.2.1.e, DC Sources, to Suspend Provision of TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Entry Into Mode 4 Following Sixth Refueling Outage ML17312A5691996-03-0505 March 1996 Revised Pages to ISI Program Summary Manual ML17312A5011996-01-17017 January 1996 Revised Page 5-1 Changing Section 5.2.2 to Include Description of Material Used for Control Element Assemblies ML17311B3221995-12-20020 December 1995 Proposed Tech Specs,Reducing Setpoint for MSIS & Rt on Low SG Pressure ML17311B3181995-12-20020 December 1995 Revised Pages to ISI Program Summary Manual ML17311B0301995-07-0303 July 1995 Proposed Tech Specs Re Temp Method to Respond to Sustained Degraded Switchyard Voltage ML17311A9771995-06-21021 June 1995 Proposed Tech Specs,Modifying Tables 3.3-4 & 3.3-5 of Section 3/4.3.2 of Esfa Sys Instrumentation ML17311A8651995-05-0202 May 1995 Proposed TS 3.1.2.6,Figure 3.1-1, Min Borated Water Vols, Relocating Elevations That Correspond to Min Required Water Vols for Spent Fuel Pool Into Site Procedures ML17311A8231995-04-18018 April 1995 Proposed Tech Specs Section 3/4.4.4 Re Sleeving Process for SG Tube Repair ML17312A9381995-02-0303 February 1995 Corrective Action Program. ML17311A5631994-12-28028 December 1994 Proposed TS Sections 3.9.6 & 4.9.6.1 Re Refueling Machine ML17311A5021994-12-0707 December 1994 Proposed Tech Specs,Changing Note 5 to Table 4.3-1 of TS 3/4.3.1 to Allow Verification of Shape Annealing Matrix Elements Used in Core Protection Calculators ML17311A4341994-11-30030 November 1994 Proposed TS 3/4.4.2,changing Pressurizer Code Safety Valve Lift Setting from 2,500 Psia to 2,475 Psia in LCOs 3.4.2.1 & 3.4.2.2 ML17311A3851994-10-31031 October 1994 Proposed Tech Spec Sections 3.9.6 & 4.9.6.1, Refueling Machine. ML17311A3341994-10-0909 October 1994 Proposed Tech Specs Suspending TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Mode 4 Following Fifth Refueling Outage ML17311A2171994-08-18018 August 1994 Proposed Tech Specs Adding Analytical Method Suppl Entitled, Calculative Methods for CE Large Break LOCA Evaluation Model for Analysis of CE & W Designed Nsss. ML17310B4511994-07-12012 July 1994 Proposed Tech Specs Amend to Add One Action Statement to Table 3.3-3,entry 8 ML17310B4151994-07-0101 July 1994 Proposed Tech Specs Re Reactor Coolant Cold Leg Temperature Vs Core Power Level of TS 3.2.6 ML17310B4331994-06-20020 June 1994 Proposed Tech Specs Sections 5.3.1 & 5.6.1, & New TS Section 3/4.9.13 & Bases 3/4.9.13 ML17310B4091994-06-17017 June 1994 Proposed Tech Specs Removing Five Tables of Component Lists Per GL-91-08 ML17310B1661994-03-28028 March 1994 Proposed Tech Specs Re Min Condensate Storage Tank Indicated Level ML17310B0911994-03-0202 March 1994 SG Tube Insp Plan. ML17310B0771994-02-24024 February 1994 PVNGS Unit 1 Cycle 5 Startup Rept. ML17310B0611994-02-18018 February 1994 Proposed Tech Specs Figure 3.2-1,Section 3/4.1.1.4 & Bases 3/4.1.1.4,establishing Min Temp for Criticality at 545 F for Facilities ML17310B0251994-01-27027 January 1994 Unit 2 Steam Generator Tube Insp Plan Addendum. ML17310B0001994-01-19019 January 1994 Proposed Tech Specs of AF Automatic Actuation Logic Surveillance Frequency Extension ML17310A8361993-11-16016 November 1993 Proposed Tech Specs Table 4.2-4, Min Staffing Requirements for PVNGS Emergencies, in Support of Proposed Rev to Emergency Plan ML17310A7421993-10-27027 October 1993 Revised Unit 1 SG Tube Insp Plan. ML17310A7351993-10-26026 October 1993 Proposed Tech Specs Changing Maximum Nominal Enrichment of Fuel Allowed to Be Used in Reactor Core ML17310A6501993-09-17017 September 1993 Unit 1 SG Tube Insp Plan. ML17310A6161993-09-0808 September 1993 Proposed Tech Specs Section 6.9.1.10 Re Sys 80 Inletflow Distribution to List of Methods Used to Determine Core Operating Limits 1999-09-29
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ENCLOSURE PROPOSED AMENDMENT TO TECHNICAL SPECIFICATION SECTION 6.9.1.10.9309i70i76,930908 PDR ADOCK',05000528 P" PDR
A.DESCRIPTION OF AMENDMENT REQUEST The proposed amendment would add a supplement to the analytical methodology listed in PVNGS Unit 1 Technical Specifications Section 6.9.1.10, item d.Current wording: d."Modified Statistical Combination of Uncertainties," CEN-356(V)-P-A Revision 01-P-A, May 1988 (Methodology for Specification 3.2.4, DNBR Margin and 3.2.7 Axial Shape Index).Proposed wording: d."Modified Statistical Combination of Uncertainties," CEN-356(V)-P-A Revision 01-P-A, May 1988 and"System 80ŽInlet Flow Distribution," Supplement 1-P to Enclosure 1-P to LD-82-054, February 1993 (Methodology for Specification 3.2.4, DNBR Margin and 3.2.7 Axial Shape Index)., B.PURPOSE OF THE TECHNICAL SPECIFICATION I'echnical Specifications Section 6.9.1.10 lists the analytical methods used to determine the core operating limits.Plant operation is limited in accordance with the values of cycle-specific parameter limits that are established using these NRC approved methodologies.
The methodology listed in item d is used for Specifications 3.2.4, DNBR Margin and 3.2.7, Axial Shape Index.C.NEED FOR THE TECHNICAL SPECIFICATION AMENDMENT The methodology supplement,"System 80ŽInlet Flow Distribution," Supplement 1-P to Enclosure 1-P to LD-82-054, February 1993, was submitted to the NRC on March 30, 1993, for review and approval.This methodology supplement describes a revised core inlet flow distribution for use with ABB-Combustion Engineering (ABB-CE)Statistical Combination of Uncertainty methodology for assessing core thermal margin, as applied to ABB-CE System 80Žunits.The NRC Staff has been reviewing this methodology supplement, and has indicated that approval will be forthcoming.
In order to utilize this methodology supplement following NRC approval, it is necessary to add it to the list of analytical methods in Technical Specifications Section 6.9.1.10 by a Technical Specification amendment.
1of3 MueM I D.SAFETY ANALYSIS OF THE PROPOSED AMENDMENT REQUEST This proposed amendment would add a methodology supplement to the analytical methods used to determine the core operating limits.The supplement was submitted to NRC for review on March 30, 1993, and is expected to be approved by for use at PVNGS prior to issuance of this Technical Specification amendment.
Since NRC staff will have reviewed and approved the supplement, this proposed amendment to add the supplement to the list of analytical methods in Technical Specifications Section 6.9.1.10 is considered to be administrative in nature.E.NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION The Commission has provided standards for determining whether a significant hazards consideration exists as stated in 10 CFR 50.92.A proposed amendment to an operating license for a facility involves a no significant hazards consideration if operation of the facility in accordance with a proposed amendment would not: (1)Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2)Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3)Involve a significant reduction in a margin of safety.A discussion of these standards as they relate to this amendment request follows: Standard 1-Involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed change is administrative in nature and does not involve any change to the configuration or method of operation of any plant equipment that is used to mitigate the consequences of an accident.Also, the proposed change does not alter the conditions or assumptions in any of the Final Safety Analysis Report (FSAR)accident analyses.Since the FSAR accident analyses remain bounding, the radiological consequences previously evaluated are not adversely affected by the proposed change.Therefore, it can be concluded that the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
Standard 2-Create the possibility of a new or different kind of accident from any accident previously analyzed.The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed change is administrative in nature and does not involve any change to the configuration or 2of3
method of operation of any plant equipment that is used to mitigate the consequences of an accident.Accordingly, no new failure modes have been defined for any plant system or component important to safety nor has any new limiting failure been identified as a result of the proposed change.Therefore, it can be concluded that the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
Standard 3-Involve a significant reduction in a margin of safety.The proposed change does not involve a significant reduction in a margin of safety.The proposed change is administrative in nature and does not adversely impact the plant's ability to meet applicable regulatory requirements.
Therefore, it can be concluded that the proposed change does not involve a significant reduction in a margin of safety.F.ENVIRONMENTAL IMPACT CONSIDERATION DETERMINATION The proposed Technical Specification amendment is administrative in nature.The proposed amendment involves no change in the amount or type of any effluent that may be released offsite, and there is no increase in individual or cumulative radiation exposure.As such, operation of PVNGS Unit 1 in accordance with the proposed amendment does not involve an unreviewed environmental safety question., 8.MARKED-UP TECHNICAL SPECIFICATION PAGE 6-20a~3of3 fi~~P 4 4 g(q FOR INFORMATION 0 LY ADMINISTRATIVE CONTROLS 6.9.1.9'ore operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:
b.C.d.e.f.g.h.Shutdown Margin KN 1-Any CEA Withdrawn for Specification 3.1.1.2 Moderator Temperature Coefficient BOL and EOL limits for Specification 3.1.1.3 Boron Dilution Alarms for Specification 3.1.2.7 Movable Control Assemblies
-CEA Position for Specification 3.1.3.1 Regulating CEA Insertion Limits for Specification 3.1.3.6 Part Length CEA Insertion Limits for Specification 3.1.3.7 Linear Heat Rate for Specification 3.2.1 Azimuthal Power Tilt-T for Specification 3.2.3 DNBR Margin for Specification 3.2.4 Axial Shape Index for Specification 3.2.7 6.9.1.10 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in: a~b.C.d."CE Method for Control Element Assembly Ejection Analysis," CENPD-0190-A, January 1976 (Methodology for Specification 3.1.3.6, Regulating CEA Insertion Limits)."The ROCS and DIT Computer Codes for Nuclear Design," CENPD-266-P-A, April 1983 (Methodology for Specifications 3.1.1.2, Shutdown Hargin KN 1 Any CEA Wi thdrawn;3.l.l.3, Moderator Temperature Coef f i ci ent BOL and EOL limits and 3.1.3.6, Regulating CEA Insertion Limits)."Safety Evaluation Report related~the Final Design of the Standard Nuclear Steam Supply Reference Systems CESSAR System 80, Docket No.STN 50-470,"NUREG-0852 (Novenber 1981), Supplements No.1 (March 1983), No.2 (September 1983), No.3 (December 1987)(Methodology for Specifications 3.1.1.2, Shutdown Margin KN 1-Any CEA Withdrawn; 3.l.1.3, Moderator Temperature Coefficient BOL and EOL limits;3.1.2.7, Boron Dilution Alarms;3.1.3.1;Movable Control Assemblies
-CEA Position;3.1.3.6, Regulating CEA Insertion Limits;3.1.3.7, Part Length CEA Insertion Limits and 3.2.3 Azimuthal Power Tilt-T)."Hodified Statistical Combination of Uncertainties," CEN-356(V)-P-A Revision Ol-P-A, Hay 1988 (Methodology for Specification 3.2.4, DNBR Margin and 3.2.7 Axial S ape Index).and"Sys4e~go lnl<4 F(om l)is(>>ibg4ioz," S~)j(caen 4)-p+0 Enclosure I-l 4o L'b-3'2-os/, F'~p>>PALO VERDE-UNIT 1 6-20a AMENDHEHT NO 69 I l