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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 ML20212E7851999-09-16016 September 1999 Proposed Tech Specs Pages,Modifying Surveillance Requirements 3.8.4.8,3.8.4.9 & 3.8.4.8 Bases to Allow Testing of DC Channel Batteries with Units on Line ML20210N3151999-08-0404 August 1999 Proposed Tech Specs Changing TSs 3.3.2, ESFAS Instrumentation, 3.3.3, Post Accident Monitoring Instrumentation, 3.4.14, RCS Loops - Test & 5.3, Unit Staff Qualifications 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 ML20206M9391999-05-0606 May 1999 Proposed Tech Specs,Revising List of Referenced Documents in TS 5.6.5b Re COLR Requirements ML20205C6901999-03-25025 March 1999 Proposed TS Facilitating Treatment of RTS Instrumentation, ESFAS Instrumentation,Lop DG Start Instrumentation,Cp & Exhaust Isolation Instrumentation & LTOP PORV TS Trip Setpoints as Nominal Values ML20204E5281999-03-15015 March 1999 Proposed Tech Specs Deleting TS for Cravs & Auxiliary Bldg Filtered Ventilation Exhaust Sys Actuation Instrumentation & Adding Note to TS for Cravs Re Chlorine Protection Function ML20204F6931999-03-11011 March 1999 Proposed Tech Specs 3.3.7 & 3.3.8 Re CR Area Ventilation Sys & Auxiliary Bldg Filtered Ventilation,Exhaust Sys Actuation Instrumentation ML20203A3331999-01-28028 January 1999 Proposed Tech Specs Modifying Flowrate Specified for SR 3.7.13.4 from Value Representative of One Filter Unit/Fan to Value Representative of Entire Fhves Train ML20197G8991998-12-0707 December 1998 Proposed ITS 3.8.3,modifying Inventory Requirements for DG Lube Oil Sys ML20195D6481998-11-11011 November 1998 Proposed Tech Specs,Modifying Details of SRs 3.6.11.6 & 3.6.11.7 to Be Consistent with Design of Containment Pressure Control Sys at Plant ML20155B2111998-10-22022 October 1998 Proposed Revs to Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009 & DPC-NE-2009P ML20151Y1821998-09-15015 September 1998 Proposed Improved TSs Providing Changes Necessary to Resolve Items Identified by Util During Review ML20151T9491998-09-0808 September 1998 Proposed Tech Specs & Bases Re Relocation from Current TS & Scheduling of New More Restrictive Surveillance Requirements 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 ML20237B5751998-08-12012 August 1998 Proposed Tech Specs 4.6.5.1b.2 Re Ice Condenser Sys Components W/Respect to Accumulation of Frost or Ice ML20237A6571998-08-0606 August 1998 TS Page 3/4 8-9 Re Notice of Enforcement Discretion Request from Enforcing TS Surveillance Requirement 4.8.1.1.2i.2 ML20237A9341998-08-0606 August 1998 Proposed Tech Specs,Deleting SR 4.8.1.1.2i.2 for Pressure Test of DG Fuel Oil Sys ML20237A0361998-08-0505 August 1998 Suppl 8 to Improved TS (Its),Combining Units ITS Pages to Facilitate Ease of Use & Significantly Reduce Vol of Paper That Must Be Processed & Controlled ML20236U1531998-07-22022 July 1998 Proposed Revised Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009P & DPC-NE-2009 ML20249B3961998-06-15015 June 1998 Proposed Tech Specs Affecting Requirements for low-temp Overpressure Protection ML20248B5741998-05-22022 May 1998 Proposed Tech Specs Modifying SR 4.4.3.3 for Pressurizer Heaters to Be Consistent W/Plant Design & W/Ts Requirement as Delineated in Improved Tech Specs ML20217E9831998-04-20020 April 1998 Proposed Improved Tech Specs Sections 1.0,2.0,3.0 & 4.0 ML20217E9521998-04-20020 April 1998 Proposed Tech Specs Revising Requirements for Automatic Actuation Logic & Actuation Relays Associated W/Cravs Operation Function,Which Is Part of ESFAS ML20216B9721998-04-0808 April 1998 Proposed Tech Specs 3/4.6.5 Re Ice Condenser Reduction of Required Ice Weight ML20217C7121998-03-20020 March 1998 Proposed Improved TS Section 3.6 Re Containment Sys ML20216B7691998-03-0909 March 1998 Proposed Tech Specs Pages Responding to 980116 RAI Re Improved TS Sections 3.1 & 3.2.Suppl Changes to Improved TS Also Included ML20217Q3741998-03-0303 March 1998 Proposed Tech Specs Re Catawba Safety Review Group ML20197G4391997-12-17017 December 1997 Proposed Tech Specs Referencing Updated or Recently Approved Methodologies Used to Calculate cycle-specific Limits Contained in COLR ML20203H9241997-12-11011 December 1997 Proposed Tech Specs Re ESFAS Instrumentation ML20210U6401997-09-15015 September 1997 Proposed Tech Specs Revising Pressure/Temp Limits, Overpressure Protection & Reactor Vessel Matl ML20140A6201997-05-27027 May 1997 Proposed Tech Specs Deleting References to Steam Generator Tube Sleeving & Repair That Will Not Be Used for Westinghouse Model D5 Steam Generators in Use at Catawba Unit 2 ML20140A6681997-05-27027 May 1997 Proposed Tech Specs,Removing Surveillance Requirement 4.7.13.3a.2 Which Specifies 112,320 Gallon Min Volume of Borated Water Be Available to Supply Standby Makeup Pump ML20141C2281997-05-0808 May 1997 Proposed Tech Specs Allowing Natural Circulation Testing in Mode 3 Following Steam Generator Replacement for Catawba Unit 1 ML20136G2471997-03-0707 March 1997 Proposed Tech Specs Re SGTR Evaluation ML20133E6801997-01-0303 January 1997 Proposed Tech Specs to Eliminate SI Signal on Low Steam Line Pressure.Unnecessary SI Actuation Causes Unnecessary Challenges to Plant Safety Sys,Unnecessary Thermal Transient & Increases Actuation Cycles ML20132F0631996-12-12012 December 1996 Proposed Tech Specs,Section 3/4.3.3.1,for Units 1 & 2 Clarifying Info Re Operation of Radiation Monitors for Plant Operations ML20134H3281996-11-0404 November 1996 Proposed Tech Specs to Licenses NPF-35 & NPF-52,eliminating During Shutdown Restriction for 18 Month Standby Shutdown Sys DG Insp TS Surveillance 4.7.13.1.c ML20113G4431996-09-21021 September 1996 Proposed Tech Specs 8.3 Re Onsite Power Systems ML20117K1011996-08-29029 August 1996 Proposed Tech Specs,Replacing 960516 Response to Concerns Re Proposed Changes for Diesel Starting Air Sys Surveillance Testing ML20116K4601996-08-0808 August 1996 Proposed Tech Specs 6.9.1.9 Re Listings of Core Operating Limit Methodologies 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 ML20112G9961996-06-0606 June 1996 Proposed Tech Specs,Reflecting Separate Volumes ML20112F6311996-06-0505 June 1996 Proposed Tech Specs 3/4.6 Re Containment Systems & 3/4.6.1 Re Primary Containment Integrity ML20112A7571996-05-16016 May 1996 Proposed Tech Specs 3/4.8 Re Surveillance Requirements ML20101M4741996-04-0303 April 1996 Proposed TS 3/4.6.4.3 & Bases Re Hydrogen Mitigation Sys ML20101H6101996-03-15015 March 1996 Proposed Tech Specs Re Replacement of SGs ML20100P0521996-03-0404 March 1996 Proposed Tech Specs Re Rev to 10CFR50,App J Which Provided for Reduced Test Frequency for Qualified Containment ML20096E8611996-01-19019 January 1996 Proposed Tech Specs,Providing Approved Revs to TS 6.9.1.9 to Incorporate Anticipated Revs to TRs DPC-NE-3000P-A & DPC-3002-A ML20096E5951996-01-12012 January 1996 Proposed Tech Specs Re Containment Leak Rate Testing Requirements of 10CFR50 App J,Option B 1999-09-16
[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 ML20212E7851999-09-16016 September 1999 Proposed Tech Specs Pages,Modifying Surveillance Requirements 3.8.4.8,3.8.4.9 & 3.8.4.8 Bases to Allow Testing of DC Channel Batteries with Units on Line ML20211A9881999-08-18018 August 1999 Rev 5 to DPC Nuclear Security Training & Qualification Plan ML20210N3151999-08-0404 August 1999 Proposed Tech Specs Changing TSs 3.3.2, ESFAS Instrumentation, 3.3.3, Post Accident Monitoring Instrumentation, 3.4.14, RCS Loops - Test & 5.3, Unit Staff Qualifications ML20210N9641999-07-26026 July 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual ML20211C3731999-07-26026 July 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual & List of Effective Pages 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 ML20210A5911999-06-10010 June 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual ML20216D4061999-06-10010 June 1999 Revised Catawba Nuclear Station Selected Licensee Commitment Manual, List of Effective Pages ML20211C3751999-05-19019 May 1999 5 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program. Page 1 of 15 in Section 4.1 of Incoming Submittal Not Included ML20195B4181999-05-18018 May 1999 Revised Pages to Catawba Nuclear Station Selected Licensee Commitments Manual ML20206M9391999-05-0606 May 1999 Proposed Tech Specs,Revising List of Referenced Documents in TS 5.6.5b Re COLR Requirements ML20206T0571999-05-0505 May 1999 Revised Catawba Nuclear Station Selected Licensee Commitments Manual. with List of Effective Pages ML20206J4531999-04-22022 April 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20206Q8741999-04-22022 April 1999 Revs to CNS Selected Licensee Commitments Manual,Including Page 5 of List of Effective Pages & Pages 1-11 to Chapter 16.9-13.With ML20206B1271999-04-15015 April 1999 CNS Selected Licensee Commitments Manual, List of Effective Pages ML20206C0391999-04-15015 April 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20205C6901999-03-25025 March 1999 Proposed TS Facilitating Treatment of RTS Instrumentation, ESFAS Instrumentation,Lop DG Start Instrumentation,Cp & Exhaust Isolation Instrumentation & LTOP PORV TS Trip Setpoints as Nominal Values ML20204G2541999-03-16016 March 1999 Revised Pages to Catawba Nuclear Station Licensee Commitments Manual ML20204E5281999-03-15015 March 1999 Proposed Tech Specs Deleting TS for Cravs & Auxiliary Bldg Filtered Ventilation Exhaust Sys Actuation Instrumentation & Adding Note to TS for Cravs Re Chlorine Protection Function ML20204F6931999-03-11011 March 1999 Proposed Tech Specs 3.3.7 & 3.3.8 Re CR Area Ventilation Sys & Auxiliary Bldg Filtered Ventilation,Exhaust Sys Actuation Instrumentation ML20205B1341999-03-11011 March 1999 Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20204E7271999-03-0808 March 1999 Chapter 16.5-2,page 1-3 to CNS Selected Licensee Commitments Manual. with List of Effective Pages ML20203A3331999-01-28028 January 1999 Proposed Tech Specs Modifying Flowrate Specified for SR 3.7.13.4 from Value Representative of One Filter Unit/Fan to Value Representative of Entire Fhves Train ML20199H4061999-01-16016 January 1999 Revised CNS Selected Licensee Commitments Manual ML20197G8991998-12-0707 December 1998 Proposed ITS 3.8.3,modifying Inventory Requirements for DG Lube Oil Sys ML20195D6481998-11-11011 November 1998 Proposed Tech Specs,Modifying Details of SRs 3.6.11.6 & 3.6.11.7 to Be Consistent with Design of Containment Pressure Control Sys at Plant 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 ML20151Y1821998-09-15015 September 1998 Proposed Improved TSs Providing Changes Necessary to Resolve Items Identified by Util During Review ML20151T9491998-09-0808 September 1998 Proposed Tech Specs & Bases Re Relocation from Current TS & Scheduling of New More Restrictive Surveillance Requirements 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 ML20237B5751998-08-12012 August 1998 Proposed Tech Specs 4.6.5.1b.2 Re Ice Condenser Sys Components W/Respect to Accumulation of Frost or Ice ML20237A6571998-08-0606 August 1998 TS Page 3/4 8-9 Re Notice of Enforcement Discretion Request from Enforcing TS Surveillance Requirement 4.8.1.1.2i.2 ML20237A9341998-08-0606 August 1998 Proposed Tech Specs,Deleting SR 4.8.1.1.2i.2 for Pressure Test of DG Fuel Oil Sys ML20237A0361998-08-0505 August 1998 Suppl 8 to Improved TS (Its),Combining Units ITS Pages to Facilitate Ease of Use & Significantly Reduce Vol of Paper That Must Be Processed & Controlled ML20236U1531998-07-22022 July 1998 Proposed Revised Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009P & DPC-NE-2009 ML20236P8671998-07-0606 July 1998 Updated Pages to Catawba Nuclear Station Selected License Commitments Manual ML20249B3961998-06-15015 June 1998 Proposed Tech Specs Affecting Requirements for low-temp Overpressure Protection ML20249B6221998-06-11011 June 1998 Revised Table of Contents for Chapter 16 of Selected License Commitments Manual ML20248B5741998-05-22022 May 1998 Proposed Tech Specs Modifying SR 4.4.3.3 for Pressurizer Heaters to Be Consistent W/Plant Design & W/Ts Requirement as Delineated in Improved Tech Specs ML20247Q9871998-05-11011 May 1998 Revised Chapter 16 to Selected License Commitment Manual ML20217E9521998-04-20020 April 1998 Proposed Tech Specs Revising Requirements for Automatic Actuation Logic & Actuation Relays Associated W/Cravs Operation Function,Which Is Part of ESFAS ML20217E9831998-04-20020 April 1998 Proposed Improved Tech Specs Sections 1.0,2.0,3.0 & 4.0 ML20217F2841998-04-20020 April 1998 Rev 7 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20216B9721998-04-0808 April 1998 Proposed Tech Specs 3/4.6.5 Re Ice Condenser Reduction of Required Ice Weight ML20217C7121998-03-20020 March 1998 Proposed Improved TS Section 3.6 Re Containment Sys ML20216B7691998-03-0909 March 1998 Proposed Tech Specs Pages Responding to 980116 RAI Re Improved TS Sections 3.1 & 3.2.Suppl Changes to Improved TS Also Included ML20217Q3741998-03-0303 March 1998 Proposed Tech Specs Re Catawba Safety Review Group ML20197G4391997-12-17017 December 1997 Proposed Tech Specs Referencing Updated or Recently Approved Methodologies Used to Calculate cycle-specific Limits Contained in COLR 1999-09-16
[Table view] |
Text
'
mme^
3 E"$ TABLE 2.2-1 (Continued) .
~
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n
"$ 9 REACTOR TRIP SYSTE'M INSTRUMENTATION TRIP SETPOINTS x,8 C -
s TRIP SETPOINT ALL'0WABLE VALUE gg 7 FUNCTIONAL UNIT ,
o 3l$ E 12. Steam Generator Water E.*U h u -
Level Low-Low
~
'llo.i nat row can e. 19% e narroe ran sp4n to of spcu ^Ip
~
- a. Unit 1 ' n .. ,
". 0% to 30% 0% to 30% T incret linearly increas cinearly i
.0% of span to . % of span ; y
/toom 30% to 100% RTP* m 30% to 100% RTP* i &
S-
- b. Unit 2 236.8% of narrow 235.1% of narrow jg range span range span a
- 13. Undervoltage - Reactor 277% of bus voltage 276% (5016 volts)
? Coolant. Pumps (5082 volts) with a .
- 14. Underfrequency - Reactor 156.4 Hz with a 255.9 Hz Coolant Pumps 0.2s response time
- 15. Turbine Trip ,
>2 2550 psig 2500 psig 55 a. Stop Valve EH Pressure Low
}i k$ b. Turbine Stop Valve Closure 21% open AIX open
- 16. Safety Injection Input from ESF H.A. . N.A.
2S E2 '
kb *RTP - RATED THERHAL POWER .
n '.
3- TABLE 2.2-1 (Continued) .
g TABLE NOTATIONS (Continued) 5
' NOTE 1: .
(Continued) 58l.5 F E_ T' 5^0."*? (Nn ~ al Tm allowed by Safety Analysis);
$ K3 -
Overtemperature AT reactor trip depressurization setpoint penalty coefficient as
- , presented in the Core Operating Limits Report; ,
P =
Pressurizer pressure, psig; P' = 2235 psig (Nominal RCS operating pressure);
S - Laplace transform operator, s"; t
- =
and f (AI) is a function of the indicated difference between top and bottom detectors of. the power-3 8 r range neutron ion chambers; with gains to be selected based on measured instrument response during plant STARTUP tests such that: '
- {t e
m A 4 0) For q -q between the " positive" and " negative" f 3(ol) breakpoints as presented in the i
^
Core 5pera,tingtimitsReport; , i f (oi) = 0, where q and q are percent RATED THERMAL POWER in the top and bottom halves of gg t e core respectiv y, an q, + q, is total THERMAL POWER in percent of RATED THERMAL POWER; EE (ii) -q is more negative than the f -
For each percent
" negative" breakpoint AIpresented that the in magnitude the Core of q,Oper,ating Limits Report,ipthe AT Yr(AI)
Setpoint or shall be automatically reduced by the f,(AI) " negative" slope presented in the Core gg Operating Limits Report; and
-~
(Eii) -q
, For each breakpoint
" positive" percent AIpresented that the in magnitude the Core of q,Oper,ating Limits,Reportis , theATYripSetpoint more positive than gg shall be automatically reduced by the f i(AI) " positive" slope presented in the Core 3, 3. -
Operating Limits Report.
ee )
NOTE 2: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more -
than 4.5% of Rated Thermal Power. .
~
9 TABLE 2.2-1 (Continued)
$ TABLE NOTATIONS (Continued)
S NOTE 3: (Continued) 7 E K6 =
Overpower AT reactor trip heatup setpoint penalty coefficient as presented in
] the Core Operating Limits Report for T > 590.8'F and K6 - O for T s 590.8'F. '
[ T = As defined in Note 1, T" -
Indicated T at ED ERMAL OWER (Calibration temperature for AT instrumental.y ion,<-5^0.3"f))T 5@.
S -
As defined i~n Note and f2 (AI) is a function of the indicated differences between top and bottom detectors of the power-range neutron ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that: 3 '
8 m (i) for q, - q3 between the " positive" and " negative" f 2(AI) breakpoints as presented in
.L the Core Operating ' Limits Report; f2 (AI) - 0, where q and q are percent RATED {
e THERMAL POWER in the top and bottom halves of the cor,e respe,ctively, and q, + q3 is R total THERMAL POWER in percent of RATED THERMAL POWER; -'
kk (ii) for each percent AI that the magnitude of q - q, is more negative than the f RR
" negative" breakpoint presented in the Core, Operating Limits Report, the AT fr(AI) ip 33 Setpoint shall be automatically reduced by the f 2(AI) " negative" slope presented in EE . the Core Operating Limits Report; and Ek (iii) for each percent Al that magnitude of q -q is more positive than the f (AI)
__ " positive"breakpointpresentedintheborebperatingLimitsReportthe2TTrip g; 5 Setpoint shall be automatically reduced by the f2(AI) " positive" slope presented in the Core Operating Limits Report.
CC oo ,
%; NOTE 4: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more m -- than 3.0% (Unit 1) and 3.3% (Unit 2) of Rated Thermal Power.
s
T ,
+
~
AttacNment 2' Catawba Nuclear Station -
- Technical Specification Change-
- Page 1 of 2 '
Prana-A revision to Technical Snecification Table 2 2-1 Reactor Trip System instmmentation Trip Setonints In Note 1: _
! change "T's 590.8
- F (Nominal T,yo allowed by Safety Analysis)"
to "T's 585_.1
- F, (Nominal T,yo allowed by Safety Analysis)"
" In Note 3 change "T" = Indicated T,yo at RATED THERMAL POWER (Calibration temperature for AT instrumentation,5 590.8 *F)"
to "T" = Indicated T,yo at RATED THERMAL POWER (Calibration temperaiure for AT
- instrumentation, s 585.1 *F)"
Technical Justification The values for T' and T" are defined as T 4va Allowed by Safety Analysis and Reference
.T4va at RATED THERMAL POWER respectively. In Note 1 and 3 of Table 2.2-1. When the steam generators are replaced at Catawba Unit 1, progranuned full power T,yo will be changed from 590.8 *F to 585.1
- F. This temperature was chosen based on returning the secondary side steam pressure to the original value after replacement of the steam generators.
585.1
- F was the assumed value for nominal full power T,yo in all applicable safety analyses related to replacement of the steam generators.
No Significant Harnrds Analysis The following analysis, required by 50.91, concludes that the proposed amendment will not involve significant hazards considerations as defined by 10 CFR 50.92.
10 CFR 50.92 states that a proposed amendment involves no significant hazards considerations if operation in accordance with the 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
Attachment 2 L Catawba Nuclear Station Technical Specification Change Page 2 of 2 :
(3) - Involve a significant reduction in a margin of safety.
This proposed change to the Technical Specifications does not involve a significant increase in the probability or consequences of an accident previously evaluated. Changing the value for T ava in Notes 1 and 3 of Table 2.2-1 will update the value to agree with the T,yo assumed in the applicable safety analyses for replacement of the steam generators. Acceptable results were obtained for all required reanalyses. The probability of an accident will not be significantly affected by operation with the new T,yo value, because all equipment will be operated within acceptable design limits. The consequences of previously evaluated .
accidents which are affected by this change have been evaluated, and have been determined to be within acceptable limits.
This proposed change will not create the possibility of a new or different kind of accident from any previously evaluated. This change does not change the physical configuration of -
the plant, and all analyses which are affected by replacement of the steam generators have been determined to have acceptable results assuming this value for T,yo.
This proposed change to the Technical Specifications will not involve a significant reduction in the margin of safety. All safety analyses which were affected by replacement of the steam generators assumed this value for T,yo and the results were determined to be within pn:viously acceptable limits.
O l
I I l
e Attachment 3 e
1 I
l i
1
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4