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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217B1791999-10-0404 October 1999 Revised TS Re Control Room,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation, Reflecting Agreements Reached in 990909 & 16 Discussions ML20209B8161999-06-30030 June 1999 Proposed Tech Specs Chapters 3.4,3.5,3.6,3.7,4.0 & 5.0, Converting to ITS ML20196J8731999-06-30030 June 1999 Proposed Tech Specs Correcting Errors,Per 990222 TS Amend Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation ML20207D6421999-05-31031 May 1999 Proposed Conversion to ITSs for Chapter 3.3 ML20206H0001999-04-30030 April 1999 Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI on Conversion to ITS ML20206F4421999-04-30030 April 1999 Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI Re Conversion to Its,Chapter 3.8 ML20206B4721999-04-21021 April 1999 Corrected Proposed TS Pages 5.5-6,5.5-7,5.5-8 & 5.5-9, Replacing Current W Model 51 SGs with W Model 54F ML20205G8571999-04-0202 April 1999 Proposed Ts,Increasing Dei Limit from 0.15 to Uci/Gram IAW 10CFR50.90 ML20205A2401999-03-19019 March 1999 Proposed Tech Specs Table 3.3-6,re Cr,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation ML20207C2451999-02-22022 February 1999 Proposed TS Amends to Clarify SR Refs to ANSI N510 Sections 10,12 & 13 to ASME N510-1989,with Errata Dtd Jan 1991 & to Add Footnote Which Refs FNP FSAR for Relevant Testing of Details ML20203A7711999-02-0303 February 1999 Proposed Tech Specs Pages Re Conversion to Its,Chapter 3.4 ML20196B6241998-11-20020 November 1998 Proposed Tech Specs Pages Re Conversion to Improved TS, Chapters 3.6.& 5.0 ML20155J4561998-11-0606 November 1998 Proposed Tech Specs Re Nuclear Instrumentation Sys Power Range Daily Surveillance Requirement ML20154K2521998-10-12012 October 1998 Proposed Tech Specs Section 6,providing Recognition of Addl Mgt Positions Associated with SG Replacement Project & Providing Ability to Approve Procedures Re Project Which May Affect Nuclear Safety ML20237D4111998-08-20020 August 1998 Proposed Tech Specs Reflecting Conversion to Improved TS Re Discussion of Changes & Significant Hazards Evaluations ML20217N4801998-05-0101 May 1998 Proposed Tech Specs Bases Pages Re Safety Limits,Reactivity Control Systems & Afs ML20217Q7261998-03-20020 March 1998 Proposed Tech Specs Re Power Update Implementation,Replacing Page 6-19a ML20202G1311998-02-12012 February 1998 Proposed Tech Specs Re Pressure Temp Limits Rept ML20202F1121998-02-12012 February 1998 Revised Proposed Changes to TS Page 6-19a for Power Uprate ML20198H3661998-01-0707 January 1998 Proposed Tech Specs Pages,Adding Note to Specifically Indicate Normal or Emergency Power Supply May Be Inoperable in Modes 5 or 6 Provided That Requirements of TS 3.8.1.2 Are Satisfied ML20198E6621997-12-31031 December 1997 Proposed Tech Specs Changing Nis IR Neutron Flux Reactor Trip Setpoint & Allowable Value ML20198E3141997-12-30030 December 1997 Proposed Tech Specs Re Auxiliary Bldg & Svc Water Bldg Battery Surveillances ML20197B6691997-12-18018 December 1997 Proposed Tech Specs Pages Re 970723 TS Amend Request Associated W/Pressure Temperature Limits Rept ML20211P5861997-10-16016 October 1997 Proposed Tech Specs Pages,Revising Number of Allowable Charging Pumps Capable of Injecting in RCS When Temperature of One or More of RCS Cold Leg Temperatures Is Less than 180 F ML20211J1501997-09-30030 September 1997 Proposed Tech Specs,Correcting Page 20 of 970723 TS Amend Request to Relocate RCS Pressure & Temperature Limits from TS to Pressure & Temperature Limit Rept ML20217C0341997-09-25025 September 1997 Revised Proposed Ts,Providing Addl Info Re 970630 Submittal, Titled, Jfnp TS Change Request - Credit for B for Spent Fuel Storage ML20211A6891997-09-17017 September 1997 Proposed Tech Specs Re Primary Coolant Specific Activity ML20216D0031997-09-0303 September 1997 Proposed Tech Specs Re Moveable Incore Detector Sys ML20149K1001997-07-23023 July 1997 Proposed Tech Specs,Relocating RCS P/T Limits from TS to Proposed P/T Limits Rept IAW Guidance Provided by GL 96-03, Relocation of P/T Limit Curves & LTOP Sys Limits ML20148R7521997-06-30030 June 1997 Proposed Tech Specs,Incorporating Requirements Necessary to Change Basis for Prevention of Criticality in Fuel Storage Pool.Change Eliminates Credit for Boraflex as Neutron Absorbing Matl in Fuel Storage Pool Criticality Analysis ML20148Q1041997-06-30030 June 1997 Proposed Tech Specs,Revising & Clarifying Requirements for CR Emergency & Penetration Room Filtration Sys,Required Number of Radiation Monitoring Instrumentation Channels & Deleting Containment Purge Exhaust Filter Spec ML20148K7501997-06-13013 June 1997 Proposed Tech Specs Changing TS 3/4.9.13, Storage Pool Ventilation (Fuel Movement) ML20140A3931997-05-28028 May 1997 Proposed Tech Specs,Clarifying That Testing of Each Shared EDG to Comply W/Sr 4.8.1.1.2.e Is Only Required Once Per Five Years on a Per EDG Basis,Not on Per Unit Basis ML20148E5921997-05-27027 May 1997 Proposed Tech Specs Pages Revising Applicable Modes for Source Range Nuclear Instrumentation & Providing Allowances for an Exception to Requirements for State of Power Supplies for RHR Discharge to Charging Pump Suction Valves ML20148F2381997-05-27027 May 1997 Corrected TS Bases Page B 3/4 1-3 That Incorporates Changes from COLR & Elimination of Containment Spary Additive Sys TS Amends ML20138B9251997-04-23023 April 1997 Proposed Tech Specs,Revising TS Pages to Include Footnote Concerning Filter Pressure Drop Testing & Mechanical Heater Testing ML20137H6091997-03-25025 March 1997 Proposed Tech Specs Re Primary Coolant Specific Activity ML20136F8231997-03-0707 March 1997 Proposed Tech Specs 3/4.6.3 Re Containment Isolation Valves Surveillance Requirements ML20135C6731997-02-24024 February 1997 Proposed Tech Specs Re Surveillance Requirements of Control Room,Penetration Room & Containment Purge Filtration Systems ML20135C4941997-02-24024 February 1997 Proposed Tech Specs Re SG Tube Laser Welded Sleeves.Voltage Based Alternate Repair Criteria Is Approved Prior to Laser Welded Sleeve Amend ML20135C8641997-02-14014 February 1997 Proposed Tech Specs Revising Specified Max Power Level & Definition of Rated Thermal Power ML20134J4051997-02-0606 February 1997 Proposed Tech Specs,Providing Addl Info Re voltage-based Repair Criteria for SG Tubing ML20133G5801997-01-10010 January 1997 Proposed Tech Specs Re Generic Laser Weld Sleeving & Deleting One Cycle Implementation of L* Which Expired at Last Unit 2 Outage ML20138G9581996-12-26026 December 1996 Proposed Tech Specs Reflecting Guidance Contained in GL 95-05, SG Tube Support Plate Voltage-Based Repair Criteria, Using Revised Accident Leakage Limit of 20 Gpm & Using Probability of Detection That Is Voltage Dependent ML20134N9211996-11-18018 November 1996 Proposed Tech Specs Bases B 3/4 2-5 Re RCS Total Flow Rate Surveillance ML20134K5551996-11-15015 November 1996 Proposed Tech Specs 3.6.2.2 Re Spray Additive Sys ML20134G9601996-11-11011 November 1996 Proposed Tech Specs Amending License NPF-8 to Replace Farley Specific Laser Welded Sleeve Requirements Currently in TS W/Generic Laser Welded Sleeve Process ML20149L8991996-11-0606 November 1996 Revised Technical Specification Pages for Plant Units 1 & 2 ML20128M4821996-10-0808 October 1996 Proposed Tech Specs Reflecting Deletion of Cycle Specific L* Repair Criteria Which Expires at Start of Next Unit 2 Refueling Outage ML20128F8821996-09-30030 September 1996 Proposed Tech Specs Change Request Relocating cycle-specific Core Operating Parameter Limits to Colr.Proposed Changes Based on Guidance Found in NRC GL 88-16,WOG-90-016, NUREG-1431 & COLR Approved by NRC 1999-06-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217B1791999-10-0404 October 1999 Revised TS Re Control Room,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation, Reflecting Agreements Reached in 990909 & 16 Discussions ML20209B8161999-06-30030 June 1999 Proposed Tech Specs Chapters 3.4,3.5,3.6,3.7,4.0 & 5.0, Converting to ITS ML20196J8731999-06-30030 June 1999 Proposed Tech Specs Correcting Errors,Per 990222 TS Amend Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation ML20207D6421999-05-31031 May 1999 Proposed Conversion to ITSs for Chapter 3.3 ML20206H0001999-04-30030 April 1999 Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI on Conversion to ITS ML20206F4421999-04-30030 April 1999 Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI Re Conversion to Its,Chapter 3.8 ML20206B4721999-04-21021 April 1999 Corrected Proposed TS Pages 5.5-6,5.5-7,5.5-8 & 5.5-9, Replacing Current W Model 51 SGs with W Model 54F L-99-170, Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with1999-04-20020 April 1999 Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with ML20205S9641999-04-20020 April 1999 Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with ML20205G8571999-04-0202 April 1999 Proposed Ts,Increasing Dei Limit from 0.15 to Uci/Gram IAW 10CFR50.90 ML20205A2401999-03-19019 March 1999 Proposed Tech Specs Table 3.3-6,re Cr,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation ML20205A3101999-02-28028 February 1999 Analysis of Capsule Z from Alabama Power Co Jm Farley Unit 2 Reactor Vessel Radiation Surveillance Program ML20207C2451999-02-22022 February 1999 Proposed TS Amends to Clarify SR Refs to ANSI N510 Sections 10,12 & 13 to ASME N510-1989,with Errata Dtd Jan 1991 & to Add Footnote Which Refs FNP FSAR for Relevant Testing of Details ML20203A7711999-02-0303 February 1999 Proposed Tech Specs Pages Re Conversion to Its,Chapter 3.4 ML20205T0011998-12-23023 December 1998 Rev 17 to FNP-0-M-011, Odcm ML20205T0081998-12-23023 December 1998 Rev 18 to FNP-0-M-011, Odcm ML20196B6241998-11-20020 November 1998 Proposed Tech Specs Pages Re Conversion to Improved TS, Chapters 3.6.& 5.0 ML20155J4561998-11-0606 November 1998 Proposed Tech Specs Re Nuclear Instrumentation Sys Power Range Daily Surveillance Requirement ML20154K2521998-10-12012 October 1998 Proposed Tech Specs Section 6,providing Recognition of Addl Mgt Positions Associated with SG Replacement Project & Providing Ability to Approve Procedures Re Project Which May Affect Nuclear Safety ML20151V6991998-09-11011 September 1998 Snoc Jm Farley Nuclear Plant Startup Test Rept Unit 2 Cycle 13. with ML20237D4111998-08-20020 August 1998 Proposed Tech Specs Reflecting Conversion to Improved TS Re Discussion of Changes & Significant Hazards Evaluations ML20217N4801998-05-0101 May 1998 Proposed Tech Specs Bases Pages Re Safety Limits,Reactivity Control Systems & Afs ML20205S9971998-04-19019 April 1998 Rev 16 to FNP-0-M-011, Odcm ML20217Q7261998-03-20020 March 1998 Proposed Tech Specs Re Power Update Implementation,Replacing Page 6-19a ML20202G1311998-02-12012 February 1998 Proposed Tech Specs Re Pressure Temp Limits Rept ML20202F1121998-02-12012 February 1998 Revised Proposed Changes to TS Page 6-19a for Power Uprate ML20198H3661998-01-0707 January 1998 Proposed Tech Specs Pages,Adding Note to Specifically Indicate Normal or Emergency Power Supply May Be Inoperable in Modes 5 or 6 Provided That Requirements of TS 3.8.1.2 Are Satisfied ML20198E6621997-12-31031 December 1997 Proposed Tech Specs Changing Nis IR Neutron Flux Reactor Trip Setpoint & Allowable Value ML20198E3141997-12-30030 December 1997 Proposed Tech Specs Re Auxiliary Bldg & Svc Water Bldg Battery Surveillances ML20197B6691997-12-18018 December 1997 Proposed Tech Specs Pages Re 970723 TS Amend Request Associated W/Pressure Temperature Limits Rept ML20212B1791997-10-31031 October 1997 1 SG ARC Analyses in Support of Full Cycle Operation ML20211P5861997-10-16016 October 1997 Proposed Tech Specs Pages,Revising Number of Allowable Charging Pumps Capable of Injecting in RCS When Temperature of One or More of RCS Cold Leg Temperatures Is Less than 180 F ML20211J1501997-09-30030 September 1997 Proposed Tech Specs,Correcting Page 20 of 970723 TS Amend Request to Relocate RCS Pressure & Temperature Limits from TS to Pressure & Temperature Limit Rept ML20217C0341997-09-25025 September 1997 Revised Proposed Ts,Providing Addl Info Re 970630 Submittal, Titled, Jfnp TS Change Request - Credit for B for Spent Fuel Storage ML20211A6891997-09-17017 September 1997 Proposed Tech Specs Re Primary Coolant Specific Activity ML20216D0031997-09-0303 September 1997 Proposed Tech Specs Re Moveable Incore Detector Sys ML20149K1001997-07-23023 July 1997 Proposed Tech Specs,Relocating RCS P/T Limits from TS to Proposed P/T Limits Rept IAW Guidance Provided by GL 96-03, Relocation of P/T Limit Curves & LTOP Sys Limits ML20148Q1041997-06-30030 June 1997 Proposed Tech Specs,Revising & Clarifying Requirements for CR Emergency & Penetration Room Filtration Sys,Required Number of Radiation Monitoring Instrumentation Channels & Deleting Containment Purge Exhaust Filter Spec ML20148R7521997-06-30030 June 1997 Proposed Tech Specs,Incorporating Requirements Necessary to Change Basis for Prevention of Criticality in Fuel Storage Pool.Change Eliminates Credit for Boraflex as Neutron Absorbing Matl in Fuel Storage Pool Criticality Analysis ML20148K7501997-06-13013 June 1997 Proposed Tech Specs Changing TS 3/4.9.13, Storage Pool Ventilation (Fuel Movement) ML20140A3931997-05-28028 May 1997 Proposed Tech Specs,Clarifying That Testing of Each Shared EDG to Comply W/Sr 4.8.1.1.2.e Is Only Required Once Per Five Years on a Per EDG Basis,Not on Per Unit Basis ML20148F2381997-05-27027 May 1997 Corrected TS Bases Page B 3/4 1-3 That Incorporates Changes from COLR & Elimination of Containment Spary Additive Sys TS Amends ML20148E5921997-05-27027 May 1997 Proposed Tech Specs Pages Revising Applicable Modes for Source Range Nuclear Instrumentation & Providing Allowances for an Exception to Requirements for State of Power Supplies for RHR Discharge to Charging Pump Suction Valves ML20138B9251997-04-23023 April 1997 Proposed Tech Specs,Revising TS Pages to Include Footnote Concerning Filter Pressure Drop Testing & Mechanical Heater Testing ML20198T4921997-03-31031 March 1997 Small Bobbin Probe (0.640) Qualification Test Rept ML20137H6091997-03-25025 March 1997 Proposed Tech Specs Re Primary Coolant Specific Activity ML20136F8231997-03-0707 March 1997 Proposed Tech Specs 3/4.6.3 Re Containment Isolation Valves Surveillance Requirements ML20135C4941997-02-24024 February 1997 Proposed Tech Specs Re SG Tube Laser Welded Sleeves.Voltage Based Alternate Repair Criteria Is Approved Prior to Laser Welded Sleeve Amend ML20135C6731997-02-24024 February 1997 Proposed Tech Specs Re Surveillance Requirements of Control Room,Penetration Room & Containment Purge Filtration Systems ML20135C8641997-02-14014 February 1997 Proposed Tech Specs Revising Specified Max Power Level & Definition of Rated Thermal Power 1999-06-30
[Table view] |
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I 22 Amendment No. )
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.,, TABLE 2.2-1 ,
g REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS l
FUNCTIONAL UNIT TRIP SETPOINT ALLOVABLE VALUES d'
- 1. Manual Reactor Trip Not Applicable Not Applicable w
- 2. Power Range,-Neutron Flux Low Setpoint - f 25% of RATED Low Setpoint - f 26% of RATED THERMAL POWER THERMAL POWER High Setp? int - f 109% of RATED High Setpoint - f 110% of RATED THERMAL POWER THERMAL POVER
- 3. Power Range, Neu e mn Flux, f 5% of RATED THERMAL POWER vith f 5.5% of RATED THERMAL POWER High Positive Es .
a time constant 1 2 second with a time constant 1 2 second
- 4. Power Range, Neutron Flux, f 5% of RATED THERMAL POWER vith f 5.5% of RATED THERMAL POWER High Negative Rate a time constant 1 2 second with a time constant 1 2 second
- 5. Intermediate Range, Neutron
~
f 25% of RATED THERMAL POWER $ 30% of RATED THERMAL POUER t'.
w Flux.
5
- 6. Source Range, Neutron Flux $ 10 counts per second 5 1.3 X 10' counts per second' .
- 7. Overtemperature aT See Note 1 See Note 3
- 8. Overpower AT See Note 2 See Note 3
- 9. Pressurizer Pressure-Lov 1 1865 psig 1 1855 psig
- 10. Pressurizer Pressure-High f 2385 psig 5 2395 psig
- 11. Pressurizer Vater f 92% of instrument span f 93% of instrument span Level-High
- 12. Loss of Flov .1 90% of design flow per loop
- 189% of design flow per loop
- Design flow is 87,200 gpa per loop. l E
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$ 1' E REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS
w
@ Note 1: Overtemperature aT f AT, [K 1-K 3 1+TS3 (T - T') + K3 (P - P') - fg (al)]
H 1 +T 2 8 w
where: ar, = Indicated AT at RATED THERMAL POWER T = Average temperature, "F T' f 577.2*F (Maximum Reference T,,, at RATED THERMAL POWER)
P = Pressurizer pressure, psig P' = 2235 psig (Nominal RCS operating pressure)
I+T3 1 = The function generated by the lead-lag controller for y T,,,. dynamic compensation g 1+T8 2 T1 &T 3
= Time constants . utilized in the lead-lag controller 'for T,,, T3 = . 30 secs, T 3
- 4 secs.: .
S = Laplace transform operator, sec *.
Operation with 3-loops Operation with 2 loops K1 = 1.18 K3 = (values blank pending l K2 = 0.0154 K2 = NRC approval of K3 = 0.000635 K3 = 2. loop operation) and f 1 (AI) is a function of the indicated difference between top and. bottom detectors of the power-range nuclear ion..
chambers; with gains to'be selected based on-measured instrument response during plant startup tests such that:
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, TABLE 2.2-1 (Continued) .
SE' p REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS -
" NOTATION continued i
g (i) for q - q between -35 percent and +9 percent, f (M) = 0 (where q and q are percent RATED y THERMIL P0 b in the top and bottom halves of the3 core respectively,,and q,,+ q, is total THERMAL m
POVER in percent of RATED THERMAL POVER).
(ii) ~for each percent that the magnitude of (q, - q,) exceeds -35 percent, the E trip setpoint shall' be automatically reduced by 1.37 percent of its value at RATED THERMAL POWER.
(iii) for each percent that the magnitude of (qt - q,) exceeds.+9 percent, the & trip setpoint shall be automatically reduced by 1.75 percent of its value at RATED THERMAL POWER. .. l-TS3 Note 2: Overpower E f E ,[K, - K 3 1+T3 s T - K, (T-T")-f 2( M)}
where: E ,= Indicated E at RATED THERMAL POVER T = Average temperature, "F
& T" = Reference T,,, at RATED THERMAL POWER (Calibration temperature for E instrumentation, 5 577.2*F) .
K, = 1.08 K3 = 0.02/*F for increasing average temperature and 0 for decreasing average temperature -
K, - 0.00109/*F for T > T"; K, = 0 for T f T* ,
T3 3 - The function generated by the rate lag controller for T,,, dynamic compensation 1+T3S k
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Reactor Coolant System T,,, f 581.2*F Pressurizer Pressure 1 2220 psia
Reactor Coolant System Total Flow Rate E
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- Limit not applicable during either a THERMAL POWER ramp in excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER' step in excess of 10% of RATED THERMAL POWER.
- Values blank pending NRC approval of 2. loop operation.
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5 EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION i L
Pursuant to the requirements in 10CFR50.92, each application for amendment to an operating license must be reviewed to determine if the modification involves- '
a significant hazard. The amendment as defined in WCAP;12659, describing the
" Alabama Power J. M. Farley Unit 2 Increased Steam Generator' Tube Plugging and Reduced Thermal Design Flow Licensing Report" has been reviewed and deemed not to involve a significant hazard based on the following evaluation.
-The proposed amendment involves an increase in equivalent plugging limits from the current licensed value of 10% uniform plugging to a new licensed value of 15% avera decrease ge with a 20% peak in any.one steam generator. Also included is a of- approximately'1.5% in Reactor Coolant System (RCS) total flowrate-from the current' licensed value of 265,500 gpm to a new licensed value of ,
261,600 gpm. As: discussed in WCAP-12659, a comprehensive evaluation of the effects.of the-increased tube plugging and reduced RCS flowrate has been completed, and no adverse safety implications have been identified.
Neither the increased tube plugging nor the reduced RCS flowrate involve a significant increase in-the probability or consequences.of any accident previously evaluated.
Tte LOCA and non-LOCA-accidents were reviewed in-WCAP-12659 verifying that the effects'of' increased tube plugging and reduced RCS flowrate do not invalidate the current analyses of record and-that all design basis conclusions are still met.
Several non-LOCA accidents [ main feedwater pipe rupture, uncontrolled bank withdrawal: from subcritical, partial -
loss of flow, single rea; tor coolant pump locked rotor,-' steam generator tube i rupture (doses)) were reanalyzed using the~ revised conditions associated with increased tube-plugging and reduced RCS flowrate, and acceptable _results were obtained. For those nor.-LOCA accidents for which evaluations we a performed, acceptable results were obtained by use of existing sensitivity studies, existing margins, or allocation of generic DNB margin. In all cases, current licensing criteria of r3 cord is met. -In addition, . effects of asymmetrical flow distributions have been evaluated and found acceptable. The most limiting large Break LOCA analysis (C d =0.4) was reanalyzed for the new configuration, and the analysis demonstrated a calculated PCT less.than.the Appendix K limit of 2200'F. ' Evaluations of Small Break LOCA, LOCA hydraulic forcing functions, post-LOCA long-term core cooling, and hot leg switchover to prevent boron precipitation wt_.re performed, and all current conclusions for the J. M.
Farley snit 2 remain valid.
Evaluations of MSLB tnd LOCA mass and energy releases concluded the present-mass and energy releases are-applicable and the containment responses remain valid and all licensing conclusions remain valid.
Page 1 of 2 a
Neither the increased tube plugging nor the reduction in RCS total flowrate
- creates the possibility of a new or different kind of accident from any accident previously evaluated. These effects were reviewed in detail'in WCAP 12659 for any adverse effects on RCS components. Major Nuclear Steam Supply System components (i.e., The reactor vessel, internals, loop piping, reactor coolant pump, pressurizer, and the CRDMS) were reviewed, and no adverse safety effects were found. No new single failures were found. No new accident initiators were found. Since increased tube plugging can physically alter the steam generator, the possible effects on the steam generator were evaluated in ,
detail. The results of thermal and hydraulic evaluation, U-bend tube vibration assessment, and the structural evaluation have concluded that the current components of the J. M. Farley Unit 2 steam generators satisfy the requirements of the ASME B&PV,Section III for the increased tube plugging and reduced RCS flowrate. No significant reduction in a margin of safety is involved with the increased 0.be plugging and reduced RCS flowrate since all. current acceptance criteria continue to be met.
The evaluation of the effect of these variables on non-LOCA and LOCA transients has verified that plant operation will be maintained within the bounds of safe, analyzed conditions as defined in the FSAR with the revised technical specifications, and the conclusions presented in the FSAR remain valid. Safe operation with revised core limits, a revised K1 of 1.18 and an approximate 1.5% reduction in thermal design flow has been demonstrated.The impact on K4 was small and no change to K4 was required since adequate-margin exists in the Technical Specification value. In addition, component evaluations have been performed to demonstrate compliance to current acceptance criteria. As such, no reduction in a margin of safety as defined in the basis for any technical specification is required for operation of J. M. Farley Unit 2 with' increased steam generator tube plugging and reduced RCS flowrats :
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