|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML18039A8811999-09-28028 September 1999 Proposed Tech Specs Re Increased MSIV Leakage Rate Limits & Exemption from 10CFR50,App J ML18039A8241999-07-28028 July 1999 Proposed Tech Specs Providing TS for Operation of Oscillation PRM Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys ML18039A8001999-06-0303 June 1999 Proposed Tech Specs,Reducing Allowable Value Used for Reactor Vessel Water Level - Low,Level 3 for Several Instrument Functions ML18039A6991999-02-22022 February 1999 Proposed Tech Specs & Bases Pages Incorporating NRC Approved TS Change 354,requiring Oscillation PRM to Be Integrated Into Approved Power uprate,24-month Operating Cycle & Single Recirculation Loop Operation ML18039A6601998-12-15015 December 1998 Proposed Tech Specs,Revising pressure-temp Curves to Extend Validity of Curves to 32 EFPY ML18039A5041998-09-0808 September 1998 Proposed Tech Specs Providing TS for Operation of Oscillation Power Range Monitor Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys ML18039A5001998-09-0404 September 1998 Proposed Tech Specs Re Use of Containment Overpressure for ECCS Pump Net Positive Suction Head Analyses ML18039A4791998-08-14014 August 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-33, DPR-52 & DPR-68 to Change Ts.Proposed Changes Decrease Frequency of once-per-cycle Instrument Calibrations by Substituting 24 Months for 18 Months ML18039A4611998-07-31031 July 1998 Proposed Tech Specs B 3.6-2,B 3.6-7 & B 3 3.7-2 for Power Uprate Operation Omitted Pages ML18039A4481998-07-17017 July 1998 Proposed Tech Specs,Adding LCO 3.4.10 & Accompanying TS Bases Provisions from Improved TS-362 Conversion Package as Adapted for Power Uprate Conditions ML18039A4091998-06-26026 June 1998 Proposed Tech Specs Section 3.4,allowing Units 2 & 3 to Operate at Uprated Power Level of 3458 Mwt ML18039A4021998-06-19019 June 1998 Proposed Tech Specs (TS) Converting from Existing Custom TS to Improved TS ML18039A3921998-06-12012 June 1998 Proposed Tech Specs Change 390,decreasing Frequency of once-per-cycle SRs by Substituting 24 Months for 18 Months in Affected TS SRs ML20249A5661998-06-10010 June 1998 Proposed Tech Specs Section 5.0,revising Administrative Controls ML20248C5151998-05-27027 May 1998 Proposed Tech Specs Section 3.8.1,revising AC Sources- Operating ML18039A3181998-04-16016 April 1998 Proposed Rev 2 to Tech Specs Section 3.6, Containment Systems, Converting from Current TS to Improved TS ML18039A2711998-03-16016 March 1998 Proposed Tech Specs Re Power Uprate Operation ML18039A2671998-03-13013 March 1998 Proposed Tech Specs,Converting to Improved Std Ts,Per NUREG- 1433,rev 1, Std TS for GE BWRs (BWR/4). ML18039A2641998-03-12012 March 1998 Proposed Tech Specs ITS Section 3.8 Re Electrical Power Sys. ML18039A2611998-03-0303 March 1998 Proposed Tech Spec Changes TS 393 Re Reactor Vessel Pressure Temperature Curves ML20199E8051998-01-23023 January 1998 Proposed Tech Specs Section 5.0 Re Administrative Controls ML18039A2221997-12-30030 December 1997 Proposed Tech Specs Re RHR SW Pumps Required for multi-unit Operation & Cold Shutdown ML18039A2151997-12-23023 December 1997 Proposed Tech Specs Section 3.7 Re Plant Sys ML18039A2181997-12-22022 December 1997 Proposed Tech Specs Section 3.8 Re Electrical Power Sys ML18039A2101997-12-0404 December 1997 Proposed Tech Specs Pages Re TS Change 362,suppl 7 Re ITS Section 3.1, Reactivity Control Sys. ML18039A2071997-12-0404 December 1997 Proposed Tech Specs Pages Re Suppl 9 to TS Change 362, Including Rev Pages to Improved TS Section 3.5 ML18039A2011997-12-0303 December 1997 Proposed Tech Specs Section 3.9 Re Refueling Operations & Section 3.10, Special Operations. ML18039A1981997-12-0303 December 1997 Improved Tech Specs Pages Re Section 5, Administrative Controls. ML20199D5471997-11-14014 November 1997 Proposed Tech Specs Section 3.0, Limiting Condition for Operation (LCO) Operability & Section 4.0, Design Changes ML20199E1361997-11-14014 November 1997 Proposed Tech Specs Section 3.4 Re Reactor Coolant Sys ML20198Q4521997-11-0505 November 1997 Proposed Tech Specs,Incorporating Improved TS (ITS) Bases Revs & Changes to Supporting Documentation Resulting from Responding to NRC Questions ML18038B9611997-10-0101 October 1997 Proposed Tech Specs,Allowing Bfn,Units 2 & 3,to Operate at Uprated Power Level of 3458 Mwt ML18038B9361997-08-15015 August 1997 Proposed Tech Specs,Extending Existing 7-day EDG Allowed Outage Time to Fourteen Days ML18038B9061997-06-19019 June 1997 Proposed Tech Specs Supporting one-time 14-day Limiting Condition for Operation for Each EDG to Accommodate Pending Vendor Recommended Maint Activities ML20138J3781997-05-0101 May 1997 Proposed Tech Specs,Revising TS-362 Amend for Section 3.8, Electrical Power Sys Which Addresses NRC Review Comments ML18038B8651997-04-24024 April 1997 Proposed Tech Specs,Submitting Revised BFN TS Bases Section 3.5.N, References, Reflecting Updated LOCA Analyses for Units 2 & 3 ML20137U1691997-04-11011 April 1997 Proposed Tech Specs Re Pr Neutron Monitor Upgrade W/ Implementation of Average Pr Monitor & Rod Block Monitor TS (ARTS) Improvements & Max Extended Load Line Limit Analyses ML18038B8341997-03-12012 March 1997 Proposed Tech Specs Re Extended EDG Allowed Outage Time ML20136F7851997-03-0606 March 1997 Proposed TS Supporting Planned Replacement of Current Power Range Monitoring Portion of Existing Nms W/Ge Digital Nuclear Measurement Analysis & Control Power Range Neutron Monitor Retrofit Design ML20134G5401997-02-0505 February 1997 Proposed Tech Specs Revising Bases Section 3.7.A/4.7.A, Primary Containment, to Delete Wording Re Maintaining Drywell to Suppression Chamber Differential Pressure Constant for Duration of Drywell to Suppression Chamber ML20132B7401996-12-11011 December 1996 Proposed Tech Specs 2.2.A Re Safety/Relief Valve Setpoint Requirements for Reactor Coolant Sys Integrity ML20117P3341996-09-15015 September 1996 Proposed Tech Specs to Change Unit 3 TS LCO 3.6.F.1 in Order to Perform Repairs & Maint Necessary to Return RCS Recirculation Loop a to Operations ML18038B7541996-09-0606 September 1996 Proposed Conversion from Current TSs to Improved STS Consistent w/NUREG-1433,rev 1 ML20117G7121996-08-30030 August 1996 Proposed Tech Specs Re License Condition on Compliance W/Thermal Water Quality Stds ML20113B1951996-06-21021 June 1996 Proposed Tech Specs,Revising Change in SLMCPR & Bases Description of RHR Suppl Fuel Pool Cooling Mode ML20112G3891996-06-0606 June 1996 Proposed Tech Specs,Revising Section 6, Administrative Controls, to Be More Closely Aligned W/Requirements of Improved Std TSs ML20117H5231996-05-20020 May 1996 Proposed Tech Specs Implementing Guidance of GL 87-09 & NUREG-1433,Rev 1 ML20108D9021996-05-0303 May 1996 Proposed Tech Specs,Withdrawing Amend 219,temporary TS 343T, Rv Water Level Instrumentation & Amend 228,temporary TS 347T,250 Volt DC Control Power Supply Sys AOT for Unit 2 ML20107F9721996-04-14014 April 1996 Proposed Tech Specs,Revising Minimum Required Number of Operable Rv Water Level Trip Sys During Period That RCS Instrument Line Excess Flow Check Valve Surveillance Tests Being Performed ML20096C4401996-01-10010 January 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B,Performance Based Testing 1999-09-28
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18039A8811999-09-28028 September 1999 Proposed Tech Specs Re Increased MSIV Leakage Rate Limits & Exemption from 10CFR50,App J ML18039A8241999-07-28028 July 1999 Proposed Tech Specs Providing TS for Operation of Oscillation PRM Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys ML18039A8001999-06-0303 June 1999 Proposed Tech Specs,Reducing Allowable Value Used for Reactor Vessel Water Level - Low,Level 3 for Several Instrument Functions ML18039A6991999-02-22022 February 1999 Proposed Tech Specs & Bases Pages Incorporating NRC Approved TS Change 354,requiring Oscillation PRM to Be Integrated Into Approved Power uprate,24-month Operating Cycle & Single Recirculation Loop Operation ML18039A6601998-12-15015 December 1998 Proposed Tech Specs,Revising pressure-temp Curves to Extend Validity of Curves to 32 EFPY ML20206F8131998-12-0303 December 1998 Rev 12 to ODCM, for BFN ML18039A5041998-09-0808 September 1998 Proposed Tech Specs Providing TS for Operation of Oscillation Power Range Monitor Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys ML18039A5001998-09-0404 September 1998 Proposed Tech Specs Re Use of Containment Overpressure for ECCS Pump Net Positive Suction Head Analyses ML18039A4791998-08-14014 August 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-33, DPR-52 & DPR-68 to Change Ts.Proposed Changes Decrease Frequency of once-per-cycle Instrument Calibrations by Substituting 24 Months for 18 Months ML18039A4611998-07-31031 July 1998 Proposed Tech Specs B 3.6-2,B 3.6-7 & B 3 3.7-2 for Power Uprate Operation Omitted Pages ML18039A4481998-07-17017 July 1998 Proposed Tech Specs,Adding LCO 3.4.10 & Accompanying TS Bases Provisions from Improved TS-362 Conversion Package as Adapted for Power Uprate Conditions ML18039A4091998-06-26026 June 1998 Proposed Tech Specs Section 3.4,allowing Units 2 & 3 to Operate at Uprated Power Level of 3458 Mwt ML18039A4021998-06-19019 June 1998 Proposed Tech Specs (TS) Converting from Existing Custom TS to Improved TS ML18039A3921998-06-12012 June 1998 Proposed Tech Specs Change 390,decreasing Frequency of once-per-cycle SRs by Substituting 24 Months for 18 Months in Affected TS SRs ML20249A5661998-06-10010 June 1998 Proposed Tech Specs Section 5.0,revising Administrative Controls ML20248C5151998-05-27027 May 1998 Proposed Tech Specs Section 3.8.1,revising AC Sources- Operating ML18039A3181998-04-16016 April 1998 Proposed Rev 2 to Tech Specs Section 3.6, Containment Systems, Converting from Current TS to Improved TS ML18039A2711998-03-16016 March 1998 Proposed Tech Specs Re Power Uprate Operation ML18039A2671998-03-13013 March 1998 Proposed Tech Specs,Converting to Improved Std Ts,Per NUREG- 1433,rev 1, Std TS for GE BWRs (BWR/4). ML18039A2641998-03-12012 March 1998 Proposed Tech Specs ITS Section 3.8 Re Electrical Power Sys. ML18039A2611998-03-0303 March 1998 Proposed Tech Spec Changes TS 393 Re Reactor Vessel Pressure Temperature Curves ML20199E8051998-01-23023 January 1998 Proposed Tech Specs Section 5.0 Re Administrative Controls ML18039A2401998-01-15015 January 1998 Bfnp Unit 2 Cycle 10 Power Ascension Test Program Start-Up Rept, for Period 970929-1105 ML18039A2221997-12-30030 December 1997 Proposed Tech Specs Re RHR SW Pumps Required for multi-unit Operation & Cold Shutdown ML18039A2151997-12-23023 December 1997 Proposed Tech Specs Section 3.7 Re Plant Sys ML18039A2181997-12-22022 December 1997 Proposed Tech Specs Section 3.8 Re Electrical Power Sys ML20217P5051997-12-0808 December 1997 Rev 10 to ODCM, Containing Markups to Rev 9 & 10 ML18039A2101997-12-0404 December 1997 Proposed Tech Specs Pages Re TS Change 362,suppl 7 Re ITS Section 3.1, Reactivity Control Sys. ML18039A2071997-12-0404 December 1997 Proposed Tech Specs Pages Re Suppl 9 to TS Change 362, Including Rev Pages to Improved TS Section 3.5 ML18039A2011997-12-0303 December 1997 Proposed Tech Specs Section 3.9 Re Refueling Operations & Section 3.10, Special Operations. ML18039A1981997-12-0303 December 1997 Improved Tech Specs Pages Re Section 5, Administrative Controls. ML20199D5471997-11-14014 November 1997 Proposed Tech Specs Section 3.0, Limiting Condition for Operation (LCO) Operability & Section 4.0, Design Changes ML20199E1361997-11-14014 November 1997 Proposed Tech Specs Section 3.4 Re Reactor Coolant Sys ML20198Q4521997-11-0505 November 1997 Proposed Tech Specs,Incorporating Improved TS (ITS) Bases Revs & Changes to Supporting Documentation Resulting from Responding to NRC Questions ML18038B9611997-10-0101 October 1997 Proposed Tech Specs,Allowing Bfn,Units 2 & 3,to Operate at Uprated Power Level of 3458 Mwt ML18038B9361997-08-15015 August 1997 Proposed Tech Specs,Extending Existing 7-day EDG Allowed Outage Time to Fourteen Days ML20210V1171997-07-29029 July 1997 Qualification Plan & Rept MIL-STD-462D,CS114,Conducted Susceptibility,Bulk Cable Injection Numac Reactor Bldg Vents Radiation Monitor TVA Bfn,Units 1,2 & 3 ML18038B9061997-06-19019 June 1997 Proposed Tech Specs Supporting one-time 14-day Limiting Condition for Operation for Each EDG to Accommodate Pending Vendor Recommended Maint Activities ML20138J3781997-05-0101 May 1997 Proposed Tech Specs,Revising TS-362 Amend for Section 3.8, Electrical Power Sys Which Addresses NRC Review Comments ML18038B8651997-04-24024 April 1997 Proposed Tech Specs,Submitting Revised BFN TS Bases Section 3.5.N, References, Reflecting Updated LOCA Analyses for Units 2 & 3 ML20137U1691997-04-11011 April 1997 Proposed Tech Specs Re Pr Neutron Monitor Upgrade W/ Implementation of Average Pr Monitor & Rod Block Monitor TS (ARTS) Improvements & Max Extended Load Line Limit Analyses ML18038B8341997-03-12012 March 1997 Proposed Tech Specs Re Extended EDG Allowed Outage Time ML20136F7851997-03-0606 March 1997 Proposed TS Supporting Planned Replacement of Current Power Range Monitoring Portion of Existing Nms W/Ge Digital Nuclear Measurement Analysis & Control Power Range Neutron Monitor Retrofit Design ML20134G5401997-02-0505 February 1997 Proposed Tech Specs Revising Bases Section 3.7.A/4.7.A, Primary Containment, to Delete Wording Re Maintaining Drywell to Suppression Chamber Differential Pressure Constant for Duration of Drywell to Suppression Chamber ML18038B8281997-01-31031 January 1997 Rev 1 to GE-NE-B13-01805-22, Internal Core Spray Line Flaw Evaluation Handbook for Browns Ferry Units 2 & 3. ML18038B8111997-01-22022 January 1997 Rev 0 to Browns Ferry Nuclear Plant,Surveillance Instruction,Inservice Insp Program,Unit 3. ML20132B7401996-12-11011 December 1996 Proposed Tech Specs 2.2.A Re Safety/Relief Valve Setpoint Requirements for Reactor Coolant Sys Integrity ML20117P3341996-09-15015 September 1996 Proposed Tech Specs to Change Unit 3 TS LCO 3.6.F.1 in Order to Perform Repairs & Maint Necessary to Return RCS Recirculation Loop a to Operations ML18038B7541996-09-0606 September 1996 Proposed Conversion from Current TSs to Improved STS Consistent w/NUREG-1433,rev 1 ML20117G7121996-08-30030 August 1996 Proposed Tech Specs Re License Condition on Compliance W/Thermal Water Quality Stds 1999-09-28
[Table view] |
Text
TABLE 3. 11.A FIRE PROTECTION SYSTEt1 HYDRAULIC REQUIREMENTS Floe Re uired Residual Pressure Station Dm DS1 Reactor Build'ng Roof Valve 26-849 200 65 D. Valve 26-889 200 65 Rc.ue'loor I'L ~ Valve 26-835 75 70 Valve 26-843 70 Valve 26-870 7c, 70 t a lice 26 "c 75 70 Valve )6 7~
~ ~ V~ vc v--a~
~ A s
rJ 73 Valve 26-898 75 70 Cable 'ray Fixed Vater Spray Systems(I) 2QQ 70 A. Unit 1 - A, B, C, & D 65 B.'nit I - E &F 180 300 55 C. Unit - G & i!
I 70 65 D. \hit 1 - K&L 115 75 E. Unit 1 - N, P, & Q 200 70 F. Unit 2 - A & B 200 70 G. tbit 2 - C, D, E, & F 85 65 Unit 2 - J, K, & L F
H. 120 60 I. Unit2-t>>, P, Q, &R 200 70 J. Unit 3 - A & B 265 75 K. Unit 3 - C, D, E, & F 135 75 L. Unit 3 - J, K, L, & N 100 40 H. Unit 3 - N, P, & Q 30 55 N. Turbine Building 55 50
- 0. Unit 3 - DieseI Generator Building Diesel Generator Buildings 75 70 A. Valve 26-1032 %5051~449 850508 75 70 B. Va lve 26-1069 PDR ADOCK 05000259 P PDR Pump Intake Station 70 A. Valve 26-57&-
TABLE 3ell.A F RE PROTECTION SYSTE!1 HYORAULIC REQUIREMENTS Flora Re uired Residual Pressure Station s1
- 6. Control Bay 75 70 A. Valve 26-1076 Yard Loop (2) na Rydrant at valve 0-26-526 500 65 B. !(ydrant at valve 0-26-530 500 65
- 8. Cooling To~er Loop A. flydrant at valve 0-26-1023-6 500 65 I Note (0 Cable tray fixed water spray systess are to be tested sisoltaneously with ooe ]b-iarb bose stat(~
Hot (2) Yard hydra. ts and the cooling tower hydrant are to be tested using the longest
! i .it t l Yir Flnu.
PROPOSED CHANGES UNIT 2
TABIZ 3.11.A FIRE PROTECTION SYSTEH HYDRAULIC R QUIRE4 NTS Station 1 Flow Required Residual pm S1 Reactor Building Roof A. Valve 26-849 B. Valve 26-889 200 65 200 65 Re.uel Floor gl ~ Valve 26-835 Va'e 26-843 75 70 Va'e 26-870 75 75 70 I ra ~,e 25-865 s<
70 Valve 26-876 75 70
~ ~ Va've 6 88 7'0 G. Valve 26-899 75 73 70 Cable Tray Fixed ~Hater Spray Systems')
A. Lait 1 - A, B, C, & D 200 70 B. Unit 1 - E &F 180 65 C. Unitl-G&H 300 55 D. Lait 1 - K&L 70 65 E. Unit 1 - N, P, & Q 115 75 F. Unit2-A&B 200 70 G. Unit 2 - C, D, E, & F 200 70 H. L'nit 2 - J, K, & L 85 65 I. Unit '2 - N, P, Q, & R 120 60 J. Unit3-A&B 200 70 K. Lait 3 - C, D, E, & F 265 75 L. Unit 3 - J, K, L, & M 135 75 M. Unit 3 - N, P, & Q 100 40 N. Turbine Building 30 55
- 0. Unit 3 - Diesel Generator Building 55 50 Diesel Generator Buildings A. Va 1ve 26-1032 75 70 B. Valve 26-1069 75 70 Pump In take S ta tion A. Valve 26-578 75 70
TABLE 3. 11. A F RE PROTECTION SYSTEM HYDRAULIC REQUIREMENTS Flow Re uired Residual Pressure Station 9P-. Ps1
- 6. Control Bay 75 70 A. Valve 26-1076 t's ~ H;d ant at valve 0-26-526 500 65
- ., 8"an a= valve 0-"6->30 SQQ 65 3 ~ 3'31K..o T war Looo
- '.-ant a valve 0-25-'0')3-5 590 65 Oe I
Note (1) Cable Not (2) tray axed water spray systeas are to Yard hydra..ts and the be tasted s~]taaeoos]y w(tb cooling tower hydrant are to be ooe yb-~ob bose stat(oo tested using the longest
PROPOSED CHANGES UNIT 3
FIRE PROTECTION SYSTEM HYDRAULIC REQUIREMENTS Flo~ Required Residual Pressure Station Slg Reactor Building Roof Valve 26-849 200 65 Valve 26-889 200 65
- 2. Refuel Floor Valve 26-835 73 70 iz3 1 ve 26-843 73 70
'4 ~ Valve 26-870 l5 70 Va >ve 26-865 75 70 Va lve 26-876 7+
~ ~ V~ 've "6-888 75 ?3 V~ VJlvc 26-89S 75 70
- 3. Cable Tray Fixed Mater Spray Systems(l) 200 70 A. lhit 1 - A, B, C, &D 180 65 B. Unitl-E&F 300 55 C. Unitl-G&H 70 65 D. V'nitI-K&L 115 75 E. Unit 1 - N, P, & Q 70
- 200 F. Unit 2 A&B 200 70 G. Unit 2 - C, D, E, & F 65
- J, K, & L 85 H. Unit 2 120 60 E. Unit 2 - N, P, Q, & R 70
- A&B 200 J. Unit 3 265 75 K. i%it - C, D, E, & F 3 135 75 L. Unit 3 - J, K, L, & M 100 N N. Unit 3 - N, P, & Q 30 55 N. Turbine Building 55 50
- 0. Unit 3 - Diesel Generator Buildiag 4 ~ Diesel Generator Buildings 75 70 A. Valve 26-1032 75 70 B. Valve 26-1069
- 5. Pump Intake Station 70 75 Valve 26-578
TABLE 3.11.A F RE PROTECTION SYSTEM'1 HYDRAULIC REQUIREMENTS Flolv Required Residual Pressure Station Psl Control Bay 70 Valve 26-1076
- 7. Yard Loop (2)
I
!!vdra"" a" valve 0-26-~26 500 65 a ~ :!yd "a."." at valve 0-26-539 500 65 S. C"oling Tv~er Looo s !!vc-- "t a" valv~ 0-25-'" '-< 500 65 I Note (l) Cable ~ay fixed water spray systems are to be tested sinultmeously witb ~a jb-j~ b,se stat j~
Not.e (2) Yard hydra..ts and the cooling tower hydrant are to be tested using the longest
! far f 1 nay.
HRh
ENCLOSURE 2 Description and Justification (TVA BFNP TS 209)
Description The proposed change would list additional cable tray fixed water spray systems in Section 3 of Table 3.11.A "Fire Protection System Hyd li Reequ i rements, and clarify that each cable tray fixed water spray system is 11 to be tested simultaneously with one 1-1/2 inch hose station. The change also clat ifies which zones are in each system and changes the number of the existing note for Table 3.'11.A.
Pages 324 and 325 f'r units 1 and 2, Pages 355a and 355b for unit 3.
Justification he proposed The change is to satisfy a commitment made in "Plan for Evaluation, Repair, and Return to Service of Browns Ferry Units 1 and 2 (March 22, 1975 Fire)" and in response to NRC Inspection Report 84-15, Item 5.
Safety Analysis The current technical specification requires hydraulic performance verification of f'ixed fire protection systems specified in Table 3,11.A.
Tests are conducted in accordance with an approved plant procedure. The proposed revision increases the number of systems too bee t es t e d an d es requ rements to conduct certain tests simultaneously, but does not alter the approved test configuration. All additional tests were conducted in April 1984 as a part of ST 8409 R1. Therefore, the change does not affect operation, safety margins, or accident analyses, and it improves overall plant safety through additional verification of'ire protection hydraulic performance.
ENCLOSURE 3 (TVA BFlTP TS 209)
Proposed Wo Significant Hazards Consideration Determination Description of Amendment Bequest The amendments would modify the technical specifications to include additional cable tray fixed water spray systems to section 3 of Table 3.11:A "Fire Protection System Hydraulic Requirements"; and clarify that each cable tray fixed water spray system is to be tested simultaneously with one 1-1l2 inch hose station. The amendment also clarifies which zones are in each system and changes'he number for the existing note for Table 3.11.A.
Basis for Pro osed No Si nificant Hazards Consideration Determination The Commission has provided guidance for the application of criteria for no significant hazards consideration determination by providing examples of amendments that are considered not likely to involve significant hazards considerations (48 FR 14870). These examples include : "(i) a purely administrative change to technical specifications for example, a change to achieve consistency throughout the technical specifications, correction of an error, or a change in nomenclature. (ii) A change that constitutes an additional limitation, restriction, or control not presently included in the technical specifications; for example, a more stringent surveillance requirement.>>
The addition of fixed water spray systems to Table 3.11.A and the requirement to simultaneously test with one hose station are clearly encompassed by example (ii). The clarification of zones and renumbering of the notes neither add, delete or modify any requirements. The revised nomenclature serves only to provide clarification of existing requirements.
They are, therefore, administrative changes encompassed by example (i).
Since the application for amendment involves proposed changes that are encompassed by an example for which no significant hazards consideration exists, TYA proposes to determine that the proposed amendment does not involve a significant hazards consideration.