Letter Sequence Other |
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MONTHYEARML20100H4581985-02-28028 February 1985 Analysis of Capsule U from Duke Power Co McGuire Unit 1 Reactor Vessel Radiation Surveillance Program Project stage: Other ML20100H4341985-04-0505 April 1985 Forwards WCAP-10786, Analysis of Capsule U from Duke Power Co McGuire Unit 1 Reactor Vessel Radiation Surveillance Program, Per App H to 10CFR50.Based on Rept,Rev to Tech Specs May Be Necessary.Nrc Will Be Advised If Rev Needed Project stage: Other ML20155J5671986-05-15015 May 1986 Application for Amends to Licenses NPF-9 & NPF-17,changing Tech Specs to Ensure Plant Operation Consistent W/Design & Statements in Unit 1 Cycle 4 Reload Safety Evaluation.Fee Paid Project stage: Request ML20195E2591986-05-23023 May 1986 Forwards Peaking Factor Limit Rept for Unit 1,Cycle 4 in Support of 841116 Application for Amends to Licenses NPF-9 & NPF-17.Conclusions in Reload Safety Evaluation Remain Valid Project stage: Request ML20211G1061986-06-0606 June 1986 Informs That Correct Date for Submittal of Proposed License Amends Re Cycle 4 Optimized Fuel Assembly Reload Is 860515, Not 841116 as Ref in Transmitting Peaking Factor Limit Rept Project stage: Other ML20202B3881986-06-30030 June 1986 Proposed Tech Specs Re Specific Criteria & Predicted Values of Safety Analyses & Evaluations Performed for Transients Sensitive to Positive Moderator Coefficient Project stage: Other ML20204H6551986-07-31031 July 1986 Rev 1 to Reload Safety Evaluation,Mcguire Nuclear Station, Unit 1 Cycle 4 Project stage: Other ML20204H6491986-08-0404 August 1986 Proposed Tech Specs,Reflecting Revised Design Features to Generally Allow Use of Modified Fuel Assemblies in Core Project stage: Other ML20204H6241986-08-0404 August 1986 Revised Application for Amends to License NPF-9 & NPF-17, Changing Design Features Tech Spec Section to Generally Allow Use of Modified Fuel Assemblies in Core.Cycle Specific Reload SER Revised to Reflect Core Redesign Project stage: Request ML20206M2891986-08-12012 August 1986 Advises That Rev to Peaking Factor Limit Rept Unnecessary. End of Cycle 3 Refueling Outage Schedule Provided in 860804 Submittal Revised to Reflect Unit 1 860823 Cycle 4 Startup Project stage: Other ML20214M6621986-08-28028 August 1986 Notice of Violation from Insp on 860707-11 Project stage: Other 1986-06-30
[Table View] |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217F3481999-10-15015 October 1999 Marked-up & Reprinted TS Pages,Changing TS Requirements for Insp of RCP Flywheels ML20216E6601999-09-13013 September 1999 Marked-up & Revised TS Pages,Making Permanent One Time Only Changes Incorporated Into TS 3.7.9 Allowing Up to 24 Hours to Restore Control Room Pressure Boundary to Operable Status When Two Cravs Trains Inoperable ML20211G6711999-08-27027 August 1999 Proposed Tech Specs 3.1.4 Re Rod Group Alignment Limits ML20210R0131999-08-10010 August 1999 Revised Tech Specs Bases Pages B 3.4.14-2 & B 3.4.14-6, RCS PIV Leakage ML20196H7551999-06-24024 June 1999 Proposed Tech Specs 2.0, Safety Limits, TS 3.3.1, Reactor Trip Sys Instrumentation & TS 3.4.1, RCS Pressure,Temp & Flow Departure from Nucleate Boiling (DNB) Limits ML20195F2941999-06-10010 June 1999 Proposed Tech Specs,Facilitating one-time Addition of Condition G & Administrative Controls Note to TS 3.7.9, Cravs ML20206M9391999-05-0606 May 1999 Proposed Tech Specs,Revising List of Referenced Documents in TS 5.6.5b Re COLR Requirements ML20206B0761999-04-0606 April 1999 Proposed Tech Specs Expanding Allowable Values for Interlocks P-6 (Intermediate Range Neutron Flux) & P-10 (Power Range Neutron Flux) in TS 3.3.1,Table 3.3.1-1, Function 16 ML20205L2251999-04-0505 April 1999 Proposed Tech Specs,Providing Revised SFP Storage Configuration,Revised SFP Storage Criteria & Revised Fuel Enrichment & Burnup Requirements ML20205B6231999-03-23023 March 1999 Proposed Tech Specs Pages Mark Ups for Unit 1,changing Record for FOL NPF-9 Amend Submittal ML20204F6761999-03-18018 March 1999 Marked-up Tech Spec Pages Re License Bases Record Change to License Amend Submittals ML20207C6921999-02-22022 February 1999 Proposed Tech Specs Bases,Reflecting Removal of SI Signal on Low Steamline Pressure on Page B 3.3.2-16 & Adding Clarification for Increasing Hydrogen Recombiner Power During Testing on Page B 3.6.7-4 ML20198B9671998-12-0909 December 1998 Revised TS 3.7.11 LCO Bases to Specify That AB Filtered Ventilation Exhaust Sys Is Considered Operable When Associated Two Fans,Filters,Ductwork,Valves & Dampers Are Operable ML20155B2111998-10-22022 October 1998 Proposed Revs to Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009 & DPC-NE-2009P ML20151Y2461998-09-15015 September 1998 Proposed Improved Tss,Resolving Items Identified by Util During Review ML20151U3521998-09-0808 September 1998 Proposed Tech Specs & Bases Converting to Improved Tech Specs ML20237B6241998-08-14014 August 1998 Proposed Tech Specs 4.6.5.1.b.2 & 4.6.5.1b.3 Relating to Ice Condenser Ice Bed Changing Portion of Surveillances Pertaining to Lower Inlet Plenum Support Structures & Turning Vanes from 9-month Frequency to 18-month Frequency ML20237B5721998-08-12012 August 1998 Proposed Tech Specs 4.6.5.1b.3 Re Ice Condenser Sys Components W/Respect to Accumulation of Frost or Ice ML20237A0411998-08-0505 August 1998 Suppl 8 to Improved TS Noting Differences Between Two Units. Proposed Changes Require That Specs & Surveillances Apply to Each Unit Individually,Unless Otherwise Noted,Consistent W/Version of Current TS Prior to Amends 166 & 148 ML20236U1531998-07-22022 July 1998 Proposed Revised Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009P & DPC-NE-2009 ML20236G5301998-06-29029 June 1998 Rev to Bases of TS 3/4.6/3,correcting Editorial Errors ML20247E3891998-05-0808 May 1998 Proposed Tech Specs,Revising Power Range Neutron Flux High Trip Setpoints in Event of Inoperable MSSVs & Deleting References to 3-loop Operation in Current TS Section 3.7.1.1(b) & Table 3.7-2 ML20217E6531998-04-20020 April 1998 Proposed Improved Tech Specs Re Section 1.0,2.0,3.0 & 4.0 ML20217B7871998-03-20020 March 1998 Marked-up Proposed Improved TS 3.6 & 5.5.2 ML20217N9311998-03-0303 March 1998 Proposed Tech Specs 5.5 Re Meteorological Tower Location ML20216B9851998-03-0202 March 1998 Proposed Tech Specs Responding to 980116 RAI Re Improved TS Sections 3.1 & 3.2.Suppl Changes to Improved TS Encl ML20197G4391997-12-17017 December 1997 Proposed Tech Specs Referencing Updated or Recently Approved Methodologies Used to Calculate cycle-specific Limits Contained in COLR ML20198H5361997-12-17017 December 1997 Tech Spec Pages for TS 3/4.7.8 for Use in Lieu of ASME Section XI Requirements ML20217H5541997-10-13013 October 1997 Proposed Tech Specs Supporting Replacement of Three Safety Related Narrow Range Refueling Water Storage Tank Level Instruments W/Three Safety Related Wide Range Level Instruments ML20212A2511997-10-0606 October 1997 Proposed Tech Specs Deleting All References to Steam Line Low Pressure Safety Injection Function ML20133M5541997-01-13013 January 1997 Proposed Tech Specs Implementing performance-based Containment Leak Rate Testing Requirements of 10CFR50, App J,Option B ML20133D3991997-01-0606 January 1997 Proposed Tech Specs 3/4.6 Re Containment Systems ML20132F0001996-12-17017 December 1996 Proposed Tech Specs,Supplementing Amend Request to Change Surveillance 4.8.2.1.2.e Which Will Achieve Alignment W/ Improved STS SR 3.8.4.8 ML20135B0381996-11-26026 November 1996 Proposed Tech Specs 3.8.2 Re DC Sources ML20134M1541996-11-0101 November 1996 Proposed Tech Specs 3.8.2 Allowing Use of Low Specific Gravity Cells in Vital 125 Volt Dc Sys When Desired ML20129F7591996-10-22022 October 1996 Proposed Tech Specs 3.6.1.5 Re Containment Systems & Air Temp ML20117K1011996-08-29029 August 1996 Proposed Tech Specs,Replacing 960516 Response to Concerns Re Proposed Changes for Diesel Starting Air Sys Surveillance Testing ML20113C7201996-06-21021 June 1996 Proposed Tech Specs 3.9.6,revising Term Lifting Loads to Lifting Force Used in Manipulator Crane TS 3.9.6b.2 & Redefining Auxiliary Hoist Min Capacities ML20112A7571996-05-16016 May 1996 Proposed Tech Specs 3/4.8 Re Surveillance Requirements ML20101H6101996-03-15015 March 1996 Proposed Tech Specs Re Replacement of SGs ML20101C8281996-03-0808 March 1996 Proposed Tech Specs Reflecting Separate Vols for Unit 1 & Unit 2 ML20100R4601996-03-0404 March 1996 Proposed Tech Specs,Deleting Flow Monitoring Sys from TS 3.4.6.1 & Associated SRs ML20097G3911996-02-13013 February 1996 Proposed Tech Specs Re Listing of Core Operating Limit Methodologies for Editorial Correction ML20095E9571995-12-14014 December 1995 Proposed Tech Specs Action Statements & SRs for Dgs, Incorporating Guidance & Recommendations in NUREG-1366,GL 93-05,GL 94-01 & NUREG-1431 ML20095E8081995-12-12012 December 1995 Proposed Tech Specs,Making McGuire Afd Limit Equations Identical to Previously Approved by NRC for Catawba Nuclear Station ML20095B6221995-12-0505 December 1995 Proposed TS SR 4.8.2.1.2.e Re 60-month Battery Testing ML20093L2861995-10-17017 October 1995 Proposed Tech Specs Listings of Core Operating Limit Methodologies ML20098A4631995-09-18018 September 1995 Proposed Tech Specs,Providing Revised Record Pages for LTOP Protection in TS Amend ML20092K4481995-09-18018 September 1995 Proposed Tech Spec Table 2.2-1, Reactor Trip Sys Instrumentation Trip Setpoints ML20092B1571995-09-0101 September 1995 Proposed Tech Specs,Revising TS 3/4.6.5 to Reduce Required Ice Weight in Containment Ice Condenser of Each Unit from 2,099,790 Lbs to 1,516,800 Lbs 1999-09-13
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F3481999-10-15015 October 1999 Marked-up & Reprinted TS Pages,Changing TS Requirements for Insp of RCP Flywheels ML20217J6401999-10-0606 October 1999 Revised Pages to McGuire Nuclear Station Selected Licensee Commitments Manual ML20216E6601999-09-13013 September 1999 Marked-up & Revised TS Pages,Making Permanent One Time Only Changes Incorporated Into TS 3.7.9 Allowing Up to 24 Hours to Restore Control Room Pressure Boundary to Operable Status When Two Cravs Trains Inoperable ML20211G6711999-08-27027 August 1999 Proposed Tech Specs 3.1.4 Re Rod Group Alignment Limits ML20211A9881999-08-18018 August 1999 Rev 5 to DPC Nuclear Security Training & Qualification Plan ML20210R0131999-08-10010 August 1999 Revised Tech Specs Bases Pages B 3.4.14-2 & B 3.4.14-6, RCS PIV Leakage ML20196H7551999-06-24024 June 1999 Proposed Tech Specs 2.0, Safety Limits, TS 3.3.1, Reactor Trip Sys Instrumentation & TS 3.4.1, RCS Pressure,Temp & Flow Departure from Nucleate Boiling (DNB) Limits ML20195F2941999-06-10010 June 1999 Proposed Tech Specs,Facilitating one-time Addition of Condition G & Administrative Controls Note to TS 3.7.9, Cravs ML20212A2701999-05-28028 May 1999 Rev 25 to McGuire Nuclear Station,Units 1 & 2 Pump & Valves Inservice Testing Program ML20206M9391999-05-0606 May 1999 Proposed Tech Specs,Revising List of Referenced Documents in TS 5.6.5b Re COLR Requirements ML20206Q9311999-05-0404 May 1999 Rev 29 to List of Effective Pages for Chapter 16 & Page 16.11-66 to McGuire Selected Licensee Commitment Manual. with ML20206S9401999-04-30030 April 1999 Rev 29 to McGuire Nuclear Station Selected Licensee Commitments. with List of Effective Pages ML20206K3621999-04-30030 April 1999 Revised McGuire Nuclear Station Selected Licensee Commitments (SLC) Manual ML20206B0761999-04-0606 April 1999 Proposed Tech Specs Expanding Allowable Values for Interlocks P-6 (Intermediate Range Neutron Flux) & P-10 (Power Range Neutron Flux) in TS 3.3.1,Table 3.3.1-1, Function 16 ML20205L2251999-04-0505 April 1999 Proposed Tech Specs,Providing Revised SFP Storage Configuration,Revised SFP Storage Criteria & Revised Fuel Enrichment & Burnup Requirements ML20205L2431999-04-0505 April 1999 SFP Soluble Boron Credit Dilution Analysis (Summary of Applicable Portions) ML20205L2531999-04-0505 April 1999 Boraflex Degradation Analysis ML20205B6231999-03-23023 March 1999 Proposed Tech Specs Pages Mark Ups for Unit 1,changing Record for FOL NPF-9 Amend Submittal ML20204F6761999-03-18018 March 1999 Marked-up Tech Spec Pages Re License Bases Record Change to License Amend Submittals ML20207C6921999-02-22022 February 1999 Proposed Tech Specs Bases,Reflecting Removal of SI Signal on Low Steamline Pressure on Page B 3.3.2-16 & Adding Clarification for Increasing Hydrogen Recombiner Power During Testing on Page B 3.6.7-4 ML20198B9671998-12-0909 December 1998 Revised TS 3.7.11 LCO Bases to Specify That AB Filtered Ventilation Exhaust Sys Is Considered Operable When Associated Two Fans,Filters,Ductwork,Valves & Dampers Are Operable ML20198A4691998-12-0909 December 1998 Rev 14 to DPC McGuire Nuclear Station Process Control Program ML20196G6891998-11-23023 November 1998 Rev 26 to Selected Licensee Commitments (SLC) Manual ML20196C9211998-11-14014 November 1998 Rev 26 to Selected Licensee Commitments Manual. with Update Instructions ML20155B2111998-10-22022 October 1998 Proposed Revs to Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009 & DPC-NE-2009P ML20154L7191998-10-0505 October 1998 Rev 8 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20151Y2461998-09-15015 September 1998 Proposed Improved Tss,Resolving Items Identified by Util During Review ML20151U3521998-09-0808 September 1998 Proposed Tech Specs & Bases Converting to Improved Tech Specs ML20151Z7751998-09-0808 September 1998 Rev 25 to McGuire Selected Licensee Commitment Manual, Consisting of Revised Pages 16.7-9 & 16.7-10 ML20237B6241998-08-14014 August 1998 Proposed Tech Specs 4.6.5.1.b.2 & 4.6.5.1b.3 Relating to Ice Condenser Ice Bed Changing Portion of Surveillances Pertaining to Lower Inlet Plenum Support Structures & Turning Vanes from 9-month Frequency to 18-month Frequency ML20237B5721998-08-12012 August 1998 Proposed Tech Specs 4.6.5.1b.3 Re Ice Condenser Sys Components W/Respect to Accumulation of Frost or Ice ML20237A0411998-08-0505 August 1998 Suppl 8 to Improved TS Noting Differences Between Two Units. Proposed Changes Require That Specs & Surveillances Apply to Each Unit Individually,Unless Otherwise Noted,Consistent W/Version of Current TS Prior to Amends 166 & 148 ML20236U1531998-07-22022 July 1998 Proposed Revised Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009P & DPC-NE-2009 ML20236G5301998-06-29029 June 1998 Rev to Bases of TS 3/4.6/3,correcting Editorial Errors ML20249C2081998-06-0909 June 1998 Rev 24 to Selected License Commitments (SLC) Manual & SLC 16.10.1,dtd June 1998 ML20247E3891998-05-0808 May 1998 Proposed Tech Specs,Revising Power Range Neutron Flux High Trip Setpoints in Event of Inoperable MSSVs & Deleting References to 3-loop Operation in Current TS Section 3.7.1.1(b) & Table 3.7-2 ML20217F2841998-04-20020 April 1998 Rev 7 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20217E6531998-04-20020 April 1998 Proposed Improved Tech Specs Re Section 1.0,2.0,3.0 & 4.0 ML20217B7871998-03-20020 March 1998 Marked-up Proposed Improved TS 3.6 & 5.5.2 ML20217N9311998-03-0303 March 1998 Proposed Tech Specs 5.5 Re Meteorological Tower Location ML20216B9851998-03-0202 March 1998 Proposed Tech Specs Responding to 980116 RAI Re Improved TS Sections 3.1 & 3.2.Suppl Changes to Improved TS Encl ML20203J9391998-02-19019 February 1998 Revised McGuire Nuclear Station Selected Licensee Commitments, List of Effective Pages ML20198H5361997-12-17017 December 1997 Tech Spec Pages for TS 3/4.7.8 for Use in Lieu of ASME Section XI Requirements ML20197G4391997-12-17017 December 1997 Proposed Tech Specs Referencing Updated or Recently Approved Methodologies Used to Calculate cycle-specific Limits Contained in COLR ML20203E1911997-12-0101 December 1997 Revised McGuire Nuclear Station Selected Licensee Commitments, List of Effective Pages ML20217H5541997-10-13013 October 1997 Proposed Tech Specs Supporting Replacement of Three Safety Related Narrow Range Refueling Water Storage Tank Level Instruments W/Three Safety Related Wide Range Level Instruments ML20212A2511997-10-0606 October 1997 Proposed Tech Specs Deleting All References to Steam Line Low Pressure Safety Injection Function ML20216A8691997-09-0101 September 1997 Rev 0 to QAM-2.0, Order Entry ML20210K9281997-08-31031 August 1997 Cycle 12 Startup Rept ML20216B8171997-08-25025 August 1997 Rev 0 to PE-9778-1, Test Rept-Grinnell Hydraulic Snubber Freedom of Motion Test Under Duke Powers McGuire Nuclear Station MSLB Accident Temp Condition 1999-09-13
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ATTACHMENT 1 ADDITIONAL PROPOSED McGUIRE UNIT 1 AND 2 TECHNICAL SPECIFICATION CHANGES l
l l
l 8608080170 860304 PDR ADOCK 05000369 PDR P
l DESIGN FEATURES
)
5.2.1.2 REACTORBUJJOING
- a. Nominal annular spece = 5 feet.
- b. Annulus nominal volume = 427,000 cubic feet. !
- c. Nominal outside height (measured from top of foundation base to the top of the done) = 177 feet.
- d. Nominal inside diameter = 125 feet.
- e. Cylinder wall minimum thickness = 3 feet,
- f. Dome minimum thickness = 2.25 feet.
- g. Dome inside radius = 87 feet. '
DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment is designed and shall be maintained for a -
maximum internal pressure of 15.0 psig and a temperature of 250*F.
R00 LOLATICH5 Psatl ROO LOLAfrows hay AT Any reht OsentA 5.3 REACTOR CORE d"
n'ur co*,"e>~n ri.~ oe :**;
8Y "'# " *** d"d'Y's a) ;. d 5 8"'d*",e"s.'"n o wornaos zinces.y 'c*u'd ss,1)pos.sg4 ,
Roos FAgnscA rts FAan zincasey.'t en IthfuLiss jrtgy, og 3)ygg4,,g,g3 5.3.1 The core shal contain 193 fuel assemblies with each fuel assembly containing 264 fuel ced. : :d with Ifr::le, ?. Each fuel rod shall have a l nominal active fuel length of 144 inches and contain a maximum total weight of l 1766 grams uranium. Th: '-ft 4' ::r: 10: ding :h:11 ran e xb_ ;;rkt .;nt
.c' O. 2 r ight ;:r::nt U-? E Reload fuel shall be aimilar in physical design to the initial core loading and shall have a maximum enrichment of 3.5 weight percent U-235.
CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 53 full-length and no part-length control rod assemblies. .The full-length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material for Unit I control rods shall be 80% silver,15% indium, and 5% cadmium. The nominal values of absorber material for Unit 2 control rods shall be 100%
boron carbide (B.C) for 102 inches and 80% silver, 15% indium, and 5% cadmium for the 40-inch tip. All control rods shall be clad with stainless steel tubing.
McGUIRE - UNITS 1 and 2 5-6 A s s u o m e u r reo. 6.~Ir o AMGWOM6MTWo n l wor 1)
4 ,
ATTACHMENT 2 JUSTIFICATION AND SAFETY ANALYSIS
, Mr. H.B. Tucker's (DPC) May 15, 1986 letter (as supplemented via letters dated May 23, June 6, June 30, and July 10, 1986) presented a justification and safety analysis for a proposed McGuire Unit 1/ Cycle 4 Core Reload and attendant RAOC and positive moderator temperature coefficient technical specification changes,
- concluding that the proposed Cycle 4 design did not cause the previously acceptable safety limits to be exceeded and that the technical specification 1 changes ensured plant operation consistent with the design and safety evaluation conclusion statements made in the Cycle 4 Reload Safety Evaluation (RSE).and that i
these conclusions remain valid. However, inspections during Cycle 3/4 refueling operations revealed damage to a fuel assembly. It was postulated that a contributing factor to this damage may have been flow through baffle joints impinging on rods resulting in induced vibration and subsequent damage to several fuel rods. As a result, it was decided to redesign the core without the damaged assembly. The core loading pattern was altered and two partially irradiated fuel assemblies were modified for insertion in the location previously occupied by the damaged fuel assembly and another location where baffle gap measurements approximate those in the damaged assembly's location. The modifications increase
- the assemblies resistance to flow impingement through baffle joints and thereby 4
reduce the potential for fuel damage. The modified assemblies contain solid stainless steel rods and open water channels in place of certain fuel rods (note that one of the two assemblies modified is a demonstration assembly that has been in the Unit 1 core since Cycle 2 and already contained 1 open water channel as documented in previous RSE's). A meeting between the NRC, Duke Power Company, and-
! Westinghouse was held on August 1,1986 in which this situation was discussed in detail.
i Attachment 2A is Revision 1 of the cycle-specific reload safety evaluation for McGuire Unit 1/ Cycle 4. This RSE has been updated to include all changes and additions (denoted by bars in the right margin) necessitated by the core redesign.
The revised RSE presents an evaluation for McGuire Unit 1, Cycle 4, which demonstrates that the redesigned core reload will not adversely affect the safety
). of the plant. All of the accidents analyzed and presented in the FSAR which could
! potentially be affected by this change have been reviewed for the Cycle 4 design j to determine the impact on the Cycle 4 core performance and it is concluded that j the operation of the core containing the modified fuel assemblies does not cause
- the previously acceptable safety limits for Cycle 4 to be exceeded. (Note that the NRC has previously reviewed and approved similar type modifications on Trojan Nuclear Plant (amendment No. 45 to NPF-1), and is currently reviewing a request on Beaver Valley Power Station Unit No. 1 (ref. Duquesne Light letter to NRC/0NRR dated July 11, 1986). In addition, McGuire Unit I has been operated with a water hole in an assembly during the 2 previous cycles). Consequently the previously proposed RAOC and positive MTC Technical Specification changes remain acceptable
! (note that the proposed application of the positive MTC Technical Specification l change to McGuire Unit 2 is unaffected by this Unit 1/ Cycle 4 core redesign and
- consequently its justification and safety analysis remains valid). However, since j the two modified fuel assemblies now contain 255 and 256 fuel rods respectively 2
instead of 264 as described in the design features section of the technical i specifications, an additional technical specification change is needed.
i I
~ . . - , , - , - _ _ - . , _ . _._ m - . _ _ _ _ _ _ .- -. _ .._ -. _ _ -. _ ..., _ _ _ . _ _ _- _ ,. -,.__- -
Attachment 2 Page 2 Accordingly, Technical Specification 5.3.1 is reworded to generally allow certain modifications to fuel assemblies involving the fuel rod locations providing they are determined acceptable by cycle-specific reload analysis. This enables the specification to better describe the various potential fuel assemblies that could be shown acceptable for utilization in the reactor core (note that this rewording is also being proposed for McGuire Unit 2 since the McGuire Unit 1 and 2 Technical Specifications are combined - this would allow for similar modifications to be made on McGuire Unit 2 as necessary). The relaxing of the 264 fuel rods per assembly requirement is justificable in that 264 fuel rods is the " normal" complement in an assembly, although certain differing configurations can be shown to be acceptable through safety analyses. The specific fuel assembly modifications performed for McGuire 1/ Cycle 4 have been determined acceptable by the attached revised McGuire 1/ Cycle 4 RSE in accordance with the provisions of this proposed specification. In addition to the above mentioned rewording, a sentence in the specification addressing the maximum enrichment of the initial core loading is being deleted in view of its obsolescence since Unit 1 is currently on its fourth core loading (again, this is also being proposed for McGuire Unit 2 since the McGuire Unit 1 and 2 Technical Specifications are combined and Unit 2 is currently operating with its third core loading).
In conclusion, the safety of the plant remains unadversely affected by the
- redesigned core reload, and the proposed technical specification changes ensure that plant operation remains consistent with the design and safety evaluation conclusions and that these conclusions remain valid.
i 1
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l 1
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