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| | ~ |
| | ATTACHMENT 1 i |
| | Proposed Changes to Reactor Trip Breaker |
| | , Technical Specifications Unit 1 Revision 4 |
| | Page 3/4 3-5 Replace Unit 2 Revision Page 3/4 3-5 Replace d |
| | 8608090068 DR 860801 ADOCK 05000348 PDR a |
| | J e |
| | 4 |
| | -r,------ - - - , ,,r---- , --~ -,,--- .,e |
| | -- , , , , .,,-.,,ww.n-n- , , , , .-r-- |
| | |
| | g TABLE 3.3-1 (Continued) : |
| | REACTOR TRIP SYSTEM INSTRUMENTATION i |
| | G |
| | "" MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION |
| | : 21. Reactor Trip Breakers 2 1 2 1, 2 1, 14 3*,4*,5* 13 |
| | : 22. Automatic Trip Logic 2 1 2 1, 2 1 3*,4*,5* 13 w |
| | 4b u, |
| | 9 e |
| | 9-5 |
| | |
| | I gg TABLE 3.3-1 (Continued) : |
| | REACTOR TRIP SYSTEM INSTRUMENTATION I |
| | -e b) MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION |
| | : 21. Reactor Trip Breakers 2 1 2 1, 2 1, 14 3*,4*,5* 13 |
| | : 22. . Automatic Trip Logic 2 1 2 1, 2 1 3*,4*,5* 13 R. |
| | m 9 |
| | 9 9 |
| | 5 x- - . - - - - - - |
| | |
| | ATTACHMENT 2 Significant Hazards Evaluation Pursuant To 10CFR50.92 for the Proposed Changes to the Reactor Trip and Bypass Breaker Technical Specifications in Response to Generic Letter 85-09 Proposed Changes Add Applicable Modes and Action Statements to Table 3.3-1, Items 1, 21 and 22; add Applicable Modes and Table Notation to Table 4.3-1, Items 1, 21 and 22; and add Item 23 to Table 4.3-1 for the Reactor Trip Bypass Breakers. |
| | |
| | ===Background=== |
| | Item 4.3 of Generic Letter 83-28, " Required Actions Based on Generic Implications of Salem ATWS Events," established the requirement for the automatic actuation of the shunt trip attachment for Westinghouse plants and requested licensees to submit any needed Technical Specification changes. |
| | Westinghouse developed generic design modifications for reactor trip system automatic actuation using shunt coil trip attachments. The major aspects of the Westinghouse generic design for Type DS-416 breakers are applicable to the Farley Nuclear Plant breaker modifications and have been implemented. Since some licensees had responded to Generic Letter 83-28 and had indicated that no technical specification changes were required, the NRC issued Generic Letter 85-09 to request licensees to submit proposed technical specification changes, to provide proposed changes to the Westinghouse Standard Technical Specifications (STS), and to provide guidance for licensees to use in developing their Technical Speci fications. Alabama Power Company therefore proposes changes to the reactor trip breaker technical specifications and the addition of the reactor trip bypass breaker technical specifications for the Farley Nuclear Plant Unit 1 and 2 Technical Specifications in response to Generic Letter 85-09. |
| | Analysis Alabama Power Company has reviewed the requirements of 10CFR50.92 as they relate to the proposed reactor trip and bypass breaker technical specification changes and considers the proposed changes not to involve a significant hazards consideration. In support of this conclusion, the following analysis is provided: |
| | : 1) The proposed changes will not increase the probability or consequences of an accident previously evaluated because the addition of reactor trip bypass breaker surveillance requirements will provide added assurance that diverse means of effecting a reactor trip exist and will enhance the capability to shutdown the reactor upon demand. Therefore, the probability or consequences of an accident previously evaluated have not been increased. |
| | |
| | Attachment 2 Page 2 |
| | : 2) The proposed changes will not create the possibility of a new or different kind of accident from any accident previously evaluated because the proposed changes ensure that a common mode failure will not exist and the reactor will be shutdown when required. Since the ability to shutdown the reactor has been previously analyzed, these proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated. |
| | : 3) The proposed changes will not involve a significant reduction in a margin of safety because the proposed changes enhance the ability to shutdown the reactor and therefore enhance the margin of safety associated with a reactor shutdown. The proposed changes conform to NRC accepted practice and therefore do not significantly reduce a margin of safety. |
| | Conclusion Based upon the analysis provided herewith, Alabama Power Company considers the proposed changes to the technical specifications to not involve a significant hazards consideration as defined by 10CFR50.92(c). |
| | .}} |
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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] |
Text
. - . _ _ . . .
~
ATTACHMENT 1 i
Proposed Changes to Reactor Trip Breaker
, Technical Specifications Unit 1 Revision 4
Page 3/4 3-5 Replace Unit 2 Revision Page 3/4 3-5 Replace d
8608090068 DR 860801 ADOCK 05000348 PDR a
J e
4
-r,------ - - - , ,,r---- , --~ -,,--- .,e
-- , , , , .,,-.,,ww.n-n- , , , , .-r--
g TABLE 3.3-1 (Continued) :
REACTOR TRIP SYSTEM INSTRUMENTATION i
G
"" MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION
- 21. Reactor Trip Breakers 2 1 2 1, 2 1, 14 3*,4*,5* 13
- 22. Automatic Trip Logic 2 1 2 1, 2 1 3*,4*,5* 13 w
4b u,
9 e
9-5
I gg TABLE 3.3-1 (Continued) :
REACTOR TRIP SYSTEM INSTRUMENTATION I
-e b) MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION
- 21. Reactor Trip Breakers 2 1 2 1, 2 1, 14 3*,4*,5* 13
- 22. . Automatic Trip Logic 2 1 2 1, 2 1 3*,4*,5* 13 R.
m 9
9 9
5 x- - . - - - - - -
ATTACHMENT 2 Significant Hazards Evaluation Pursuant To 10CFR50.92 for the Proposed Changes to the Reactor Trip and Bypass Breaker Technical Specifications in Response to Generic Letter 85-09 Proposed Changes Add Applicable Modes and Action Statements to Table 3.3-1, Items 1, 21 and 22; add Applicable Modes and Table Notation to Table 4.3-1, Items 1, 21 and 22; and add Item 23 to Table 4.3-1 for the Reactor Trip Bypass Breakers.
Background
Item 4.3 of Generic Letter 83-28, " Required Actions Based on Generic Implications of Salem ATWS Events," established the requirement for the automatic actuation of the shunt trip attachment for Westinghouse plants and requested licensees to submit any needed Technical Specification changes.
Westinghouse developed generic design modifications for reactor trip system automatic actuation using shunt coil trip attachments. The major aspects of the Westinghouse generic design for Type DS-416 breakers are applicable to the Farley Nuclear Plant breaker modifications and have been implemented. Since some licensees had responded to Generic Letter 83-28 and had indicated that no technical specification changes were required, the NRC issued Generic Letter 85-09 to request licensees to submit proposed technical specification changes, to provide proposed changes to the Westinghouse Standard Technical Specifications (STS), and to provide guidance for licensees to use in developing their Technical Speci fications. Alabama Power Company therefore proposes changes to the reactor trip breaker technical specifications and the addition of the reactor trip bypass breaker technical specifications for the Farley Nuclear Plant Unit 1 and 2 Technical Specifications in response to Generic Letter 85-09.
Analysis Alabama Power Company has reviewed the requirements of 10CFR50.92 as they relate to the proposed reactor trip and bypass breaker technical specification changes and considers the proposed changes not to involve a significant hazards consideration. In support of this conclusion, the following analysis is provided:
- 1) The proposed changes will not increase the probability or consequences of an accident previously evaluated because the addition of reactor trip bypass breaker surveillance requirements will provide added assurance that diverse means of effecting a reactor trip exist and will enhance the capability to shutdown the reactor upon demand. Therefore, the probability or consequences of an accident previously evaluated have not been increased.
Attachment 2 Page 2
- 2) The proposed changes will not create the possibility of a new or different kind of accident from any accident previously evaluated because the proposed changes ensure that a common mode failure will not exist and the reactor will be shutdown when required. Since the ability to shutdown the reactor has been previously analyzed, these proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3) The proposed changes will not involve a significant reduction in a margin of safety because the proposed changes enhance the ability to shutdown the reactor and therefore enhance the margin of safety associated with a reactor shutdown. The proposed changes conform to NRC accepted practice and therefore do not significantly reduce a margin of safety.
Conclusion Based upon the analysis provided herewith, Alabama Power Company considers the proposed changes to the technical specifications to not involve a significant hazards consideration as defined by 10CFR50.92(c).
.