|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20216J4111999-09-28028 September 1999 Proposed Tech Specs,Removing cycle-specific Min Critical Power Ratio Safety Limit Restriction ML20206R7931999-05-17017 May 1999 Revs Made to BSEP TS Bases Between 980605 & 990507,IAW TS 5.5.10.d ML20204G5991999-03-19019 March 1999 Proposed Tech Specs Re Balance of Plant/Emergency Bus AOT Extension ML20153D8791998-09-14014 September 1998 Proposed Tech Specs 3.8.1 & 3.8.7 Re Balance of Plant/ Emergency Bus Allowable Outage Time Extension ML20237C0251998-08-17017 August 1998 Proposed Tech Specs 5.2.2.f Requiring Operations Manager or Assistant Operations Manager to Hold SRO License ML20249B1161998-06-12012 June 1998 Proposed Tech Specs Page 3.3-56 for Issued Amends 203 & 233, Correcting Erroneous Inequality Sign for Allowable Value ML20248A4681998-05-22022 May 1998 Proposed Tech Specs Pages to Rev E of Proposed License Amend for Conversion to Improved TS ML20247H9481998-05-15015 May 1998 Revised TS Pages for Administrative Rev to Proposed Surveillance Requirements 4.7.2.b.2 & 4.7.2.c,to State That Charcoal Absorber Samples Will Be Tested IAW Methodology Provided by ASTM D3803-1989 at 30 C ML20217J9171998-04-24024 April 1998 Proposed Rev D to Improved Ts,Incorporates New ITS 3.6.3.2, Containment Atmospheric Dilution Sys ML20216G7961998-04-0909 April 1998 Proposed Tech Specs,Revising Basis for Removing Suppression Chamber Temp Water Temp Monitoring Instrumentation Requirements ML20217Q1041998-04-0303 April 1998 Proposed Tech Specs Pages to Modify TS 3.5.3.1 & Associated Bases Section 3/4.5.3.1,to Revise Specified Total Volume of Condensate Storage Tank from 150,000 Gallons to 228,200 Gallons ML20217F9101998-03-27027 March 1998 Proposed Tech Specs Re Safety Limit Min Critical Power Ratio ML20217D5451998-03-24024 March 1998 Proposed Tech Specs 3.0 & 4.0 Re Applicability & Surveillance Requirements ML20216J8571998-03-13013 March 1998 Proposed Rev C to Improved Ts,Incorporating NRC Comments on Improved TS Submittal Resulting from Internal Reviews ML20203H0481998-02-23023 February 1998 Proposed Tech Specs,Revising SLMCPR from 1.10 to 1.09 & Deleting Document Reference ML20199K7041998-01-27027 January 1998 Proposed Tech Specs 3/4.8 Re Electrical Power Sys ML20197B8741997-12-18018 December 1997 Proposed Tech Specs Pages Revising Proposed Amends in 971101 Request by Expanding Note in LCO 3.3.1.1,Table 3.3.1.1-1,to Allow 12 Hours to Adjust Allowable Value,Specified in COLR, After Sufficient Reduction in Feedwater Temperature ML20198P7091997-11-0606 November 1997 Proposed Tech Specs 3/4.7.2 & 3/4.3.5.5 Revising Design Basis Qualification Requirements for CREVS & CREVS Instrumentation ML20199A3011997-11-0606 November 1997 Proposed Tech Specs,Adding Footnote to SR 4.8.1.1.2.d to Allow Performance of SR 4.8.1.1.2.d.1,SR 4.8.1.1.2.d.4 & SR 4.8.1.1.2.d.5 in Operational Condition 1 Through 5 ML20198Q3011997-11-0404 November 1997 Proposed Tech Specs 3.0 & 4.0,revising Specific Terms in Proposed TSs 4.0.1 & 4.0.3 to Reflect Existing TS Terminology ML20198P2681997-10-29029 October 1997 Proposed Tech Specs,Revising Description of Control Rod Assemblies ML20212F1991997-10-28028 October 1997 Proposed Tech Specs Revising Proposed SRs to Remove Allowable Humidity & Temperature Testing Ranges for Charcoal Adsorber ML20212F2241997-10-28028 October 1997 Proposed Tech Specs Revising Certain Instrumentation Allowable Values ML20217Q5131997-08-27027 August 1997 Proposed Tech Specs,Revising Labels for Coordinates of TS Figures 3.4.6.1-1,3.4.6.1-2,3.4.6.1-3a & 3.4.6.1-3b as Pressure (Psig) & Temp (F) Rather than Pressure Limit in Rv Top Head (Psig) ML20210P4651997-08-22022 August 1997 Proposed Tech Specs,Incorporating Power up-rate Amend 183 Provided as Replacement & Addressing Administrative Error W/Typed Bases Page Submitted w/970115 Amend Request ML20210P3601997-08-22022 August 1997 Proposed Tech Specs Bases Pages Incorporating 961101 Power up-rate Amendments ML20196J0701997-07-25025 July 1997 Proposed Tech Specs Clarifying Use of NRC Staff Approved Alternatives to Recommendations of NRC GL 88-01, NRC Staff Position of IGSCC in BWR Austenitic Stainless Steel Piping ML20149J3641997-07-18018 July 1997 Proposed Tech Specs 5.2.2.b & 5.4.2 Re Containment & RCS Design Features ML20148D3171997-05-23023 May 1997 Proposed Tech Specs 3/4.4.5 Re Reactor Coolant Sys Specific Activity ML20148E6911997-05-16016 May 1997 Corrected TS Page 3/4 5-2 to Amend 215 of License DPR-62 ML20140H1041997-05-0909 May 1997 Proposed Tech Specs Incorporating Administrative Update Resulting from Issuance on 970418 of Amends 184 & 215 to Units 1 & 2,respectively ML20138G1171997-04-30030 April 1997 Proposed Tech Specs 4.7.2.b & 4.7.2.c Revising Surveillance Requirements to Require Testing of Control Room Emergency Ventilation Sys Charcoal & Revising Acceptance Criteria for Subject Charcoal Testing ML20137Y7941997-04-14014 April 1997 Proposed Tech Specs 3.0 & 4.0 Re Applicability of LCO & Surveillance Requirements,Per GL 87-09 ML20137Y6911997-04-11011 April 1997 Proposed Tech Specs,Revising Requirements for Instrumentation Response Time Testing Associated W/Rps, Isolation Actuation Sys & ECCS ML20137N3081997-04-0202 April 1997 Corrected Page of TS 4.0.1 Re Applicability Surveillance Requirements ML20137N1011997-03-31031 March 1997 Proposed Tech Specs Rev 4.0.1 to Include Stipulation That Failure to Meet SR Constitutes Failure to Meet LCO ML20137M6541997-03-27027 March 1997 Proposed Tech Specs,Revising Definitions for Eccs,Isolation Sys & Reactor Protection Sys Response Times ML20137K9021997-03-24024 March 1997 Proposed Tech Specs Revising Definitions for ECCS Response Time,Isolation Sys Response Time, & Reactor Protection Response Time ML20137D8711997-03-22022 March 1997 Proposed Tech Specs Permitting Continued Operation W/O Completion of Instrumentation Response Time Testing,As Currently Defined in TS for Rps,Eccs & Isolation Actuation Instrumentation ML20137D8891997-03-21021 March 1997 Proposed Tech Specs Permitting Continued Operation W/O Completion of Instrumentation Response Time Testing,As Currently Defined in Ts,For Rps,Eccs & Isolation Actuation Instrumentation ML20136E7841997-03-0505 March 1997 Proposed Tech Specs Incorporating New TS Which Applies to Condenser Vacuum Pump Isolation Instrumentation ML20138K6731997-01-15015 January 1997 Proposed Tech Specs,Revising Minimum & Maximum Values of Pressure Suppression Pool Water Vols Contained in TS 3.6.2.1.a.1 & Corresponding Bases ML20133F4311997-01-0707 January 1997 Proposed Tech Specs Exchanging P-T Limits Curves Currently Located in Unit 1 & 2 TSs & Deleting Current 8,10 & 12 Effective Full Power Yr Hydrostatic Test P-T Limits Curves & Adding New Ones ML20133G2901996-12-23023 December 1996 Proposed Tech Specs 3/4.5 Re Emergency Core Cooling Sys ML20135D6301996-12-0404 December 1996 Proposed Tech Specs 3.1.2 & SR 4.1.2 Changing Method of Detecting Reactivity Anomalies & Editorial Changes to Bases for TS 3/4.1.2 ML20134K9381996-11-0101 November 1996 Proposed Tech Specs Re Full Implementation of BWROG Enhanced Option 1-A Reactor Stability Long Term Solution ML20129F5361996-10-16016 October 1996 Proposed Tech Specs,Revising Minumum Critical Power Ratio Safety Limit Ref in TS 2.1.2 from 1.07 to 1.10 for Unit 1 Cycle 11 Operation & Revises TS 5.3.1 to Reflect New Fuel Type Being Added to Unit 1 Reactor Core ML20128H2031996-10-0101 October 1996 Proposed Tech Specs,Allowing Uprate of Units to 105% of Rated Thermal Power ML20116E5451996-07-30030 July 1996 Proposed Tech Specs Revising MCPR Safety Limits in TS 2.1.2 from 1.07 to 1.09 for Cycle 11 Operation & Revising TS 5.3.1 to Reflect New Fuel Type GE13 to Be Inserted During Refueling Outage 10 ML20101R1851996-04-0808 April 1996 Proposed Tech Specs 2.1.2 Revising MCPR Safety Limits from 1.07 to 1.09 for Cycle 11 Operation,Ts 5.3.1 to Reflect GE13 Fuel & Figure 3.1.5-1 to Reflect Changes to Poison Matl Concentration Needed to Achieve Reactor Shutdown 1999-09-28
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216J4111999-09-28028 September 1999 Proposed Tech Specs,Removing cycle-specific Min Critical Power Ratio Safety Limit Restriction ML20211G0501999-08-31031 August 1999 Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept ML20206R7931999-05-17017 May 1999 Revs Made to BSEP TS Bases Between 980605 & 990507,IAW TS 5.5.10.d ML20204D5241999-03-31031 March 1999 Rev 0 to Brunswick Steam Electric Plant,Unit 2 Simulator Certification Quadrennial Rept ML20204D4961999-03-31031 March 1999 Rev 0 to Brunswick Steam Electric Plant,Unit 1 Simulator Certification Rept ML20204G5991999-03-19019 March 1999 Proposed Tech Specs Re Balance of Plant/Emergency Bus AOT Extension ML20198K0411998-12-21021 December 1998 Rev 1 to Core Shroud Insp Plan Unit 2 B214R1 Outage Apr 1999 ML20153D8791998-09-14014 September 1998 Proposed Tech Specs 3.8.1 & 3.8.7 Re Balance of Plant/ Emergency Bus Allowable Outage Time Extension ML20238F6671998-08-28028 August 1998 Core Shroud Insp Plan Unit 2 B214R1 Outage Apr 1999 ML20237C0251998-08-17017 August 1998 Proposed Tech Specs 5.2.2.f Requiring Operations Manager or Assistant Operations Manager to Hold SRO License ML20237A5711998-07-16016 July 1998 Rev 10 to OENP-16.7, Administrative Control of Check Valve Disassembly Program ML20249B1161998-06-12012 June 1998 Proposed Tech Specs Page 3.3-56 for Issued Amends 203 & 233, Correcting Erroneous Inequality Sign for Allowable Value ML20249C0131998-06-11011 June 1998 Rev 0 to TR-ECCS-GEN-011, ECCS Suction Strainer Hydrodynamic Test Summary Rept ML20248A4681998-05-22022 May 1998 Proposed Tech Specs Pages to Rev E of Proposed License Amend for Conversion to Improved TS ML20247H9481998-05-15015 May 1998 Revised TS Pages for Administrative Rev to Proposed Surveillance Requirements 4.7.2.b.2 & 4.7.2.c,to State That Charcoal Absorber Samples Will Be Tested IAW Methodology Provided by ASTM D3803-1989 at 30 C ML20217J9171998-04-24024 April 1998 Proposed Rev D to Improved Ts,Incorporates New ITS 3.6.3.2, Containment Atmospheric Dilution Sys ML20217H3061998-04-16016 April 1998 Rev 0 to ISI Program for Class 1,2 & 3 Components & Supports ML20216G7961998-04-0909 April 1998 Proposed Tech Specs,Revising Basis for Removing Suppression Chamber Temp Water Temp Monitoring Instrumentation Requirements ML20217Q1041998-04-0303 April 1998 Proposed Tech Specs Pages to Modify TS 3.5.3.1 & Associated Bases Section 3/4.5.3.1,to Revise Specified Total Volume of Condensate Storage Tank from 150,000 Gallons to 228,200 Gallons ML20217F9101998-03-27027 March 1998 Proposed Tech Specs Re Safety Limit Min Critical Power Ratio ML20217D5451998-03-24024 March 1998 Proposed Tech Specs 3.0 & 4.0 Re Applicability & Surveillance Requirements ML20216J8571998-03-13013 March 1998 Proposed Rev C to Improved Ts,Incorporating NRC Comments on Improved TS Submittal Resulting from Internal Reviews ML20197A9371998-02-25025 February 1998 Rev 4 to 0AP-025, Bnp Integrated Scheduling ML20203H0481998-02-23023 February 1998 Proposed Tech Specs,Revising SLMCPR from 1.10 to 1.09 & Deleting Document Reference ML20203M4031998-02-18018 February 1998 Rev 0 to Pump & Valve IST Program Plan Third Interval for Cp&L,Units 1 & 2 ML20197A9281998-02-12012 February 1998 Rev 22 to 0A0P-13.0, Operation During Hurricane,Flood Conditions,Tornado or Earthquake ML20204A7551998-02-0202 February 1998 Rev 0 to ESR 97-00706, Benchmark of Dll Computer Program ML20199K7041998-01-27027 January 1998 Proposed Tech Specs 3/4.8 Re Electrical Power Sys ML20199A9291998-01-22022 January 1998 Core Shroud Insp Plan Unit 1 B112R1 Outage April 1998 ML20197B8741997-12-18018 December 1997 Proposed Tech Specs Pages Revising Proposed Amends in 971101 Request by Expanding Note in LCO 3.3.1.1,Table 3.3.1.1-1,to Allow 12 Hours to Adjust Allowable Value,Specified in COLR, After Sufficient Reduction in Feedwater Temperature ML20202D9151997-12-0202 December 1997 Rev 11 to 0AOP-34.0, Chlorine Emergencies ML20198T2961997-11-24024 November 1997 Rev 0 to B2C13, Brunswick Unit 2,Cycle 13 Neutronics Startup Rept ML20199J5711997-11-14014 November 1997 Rev 3 to 0AP-025, Bnp Integrated Scheduling ML20198T3131997-11-0707 November 1997 BSEP Unit 2 Power Uprate Startup Test Rept for Cycle 13 ML20198P7091997-11-0606 November 1997 Proposed Tech Specs 3/4.7.2 & 3/4.3.5.5 Revising Design Basis Qualification Requirements for CREVS & CREVS Instrumentation ML20199A3011997-11-0606 November 1997 Proposed Tech Specs,Adding Footnote to SR 4.8.1.1.2.d to Allow Performance of SR 4.8.1.1.2.d.1,SR 4.8.1.1.2.d.4 & SR 4.8.1.1.2.d.5 in Operational Condition 1 Through 5 ML20198Q3011997-11-0404 November 1997 Proposed Tech Specs 3.0 & 4.0,revising Specific Terms in Proposed TSs 4.0.1 & 4.0.3 to Reflect Existing TS Terminology ML20198P2681997-10-29029 October 1997 Proposed Tech Specs,Revising Description of Control Rod Assemblies ML20212F1991997-10-28028 October 1997 Proposed Tech Specs Revising Proposed SRs to Remove Allowable Humidity & Temperature Testing Ranges for Charcoal Adsorber ML20212F2241997-10-28028 October 1997 Proposed Tech Specs Revising Certain Instrumentation Allowable Values ML20199J5601997-10-13013 October 1997 Rev 2 to 0AP-022, Bnp Outage Risk Mgt ML20198P4841997-10-0808 October 1997 Rev 1 to BSEP Unit 2 Core Shroud Insp Plan Outage B213R1 ML20249C0041997-09-30030 September 1997 Rev 2 to TR-ECCS-GEN-01-NP, Hydrodynamic Inertial Mass Testing of ECCS Suction Strainers ML20249C0091997-09-30030 September 1997 Rev 1 to TR-ECCS-GEN-05-NP, Hydrodynamic Inertial Mass Testing of ECCS Suction Strainers Suppl 1 - Free Vibration Data Analysis ML20217E2791997-09-17017 September 1997 Tensil Testing & Charpy Impact Testing of Reactor Archive Matl ML20217Q5131997-08-27027 August 1997 Proposed Tech Specs,Revising Labels for Coordinates of TS Figures 3.4.6.1-1,3.4.6.1-2,3.4.6.1-3a & 3.4.6.1-3b as Pressure (Psig) & Temp (F) Rather than Pressure Limit in Rv Top Head (Psig) ML20210P4651997-08-22022 August 1997 Proposed Tech Specs,Incorporating Power up-rate Amend 183 Provided as Replacement & Addressing Administrative Error W/Typed Bases Page Submitted w/970115 Amend Request ML20210P3601997-08-22022 August 1997 Proposed Tech Specs Bases Pages Incorporating 961101 Power up-rate Amendments ML20196J0701997-07-25025 July 1997 Proposed Tech Specs Clarifying Use of NRC Staff Approved Alternatives to Recommendations of NRC GL 88-01, NRC Staff Position of IGSCC in BWR Austenitic Stainless Steel Piping ML20149J3641997-07-18018 July 1997 Proposed Tech Specs 5.2.2.b & 5.4.2 Re Containment & RCS Design Features 1999-09-28
[Table view] |
Text
. - . . . _ _ .- . ._
1 < i i
r ENCLOSURE 3
't BRUNSWICK STEAM ELECTRIC PIANT,. UNIT 1 NRC DOCKET 50 325 OPERATIN3 LICENSE DPR-71' ,
REQUEST FOR LICENSE AMENDMENT. /
INSTRUCTIONS FOR INCORPORATION The proposed changes to the Technical Specifications-(Appendix A to Operating License DPR-71) would be incorporated as follows:
UNIT 1 f
) Rernove Page Insert Page 3/4 3-11 3/4 3-11 3/4 3 3/4 3-12 i 3/4 3 13 3/4 3 13 3/4 3-17 .3/4 3 17 3/4 3-18 3/4 3-18 3/4 3 19 3/4 3-19 3/4 3 22 3/4 3-22 t 3/4 3 23 3/4 3-23 3/4 3 25 3/4 3-25 3/4 3-26 3/4 3 26 3/4 3 27 3/4 2-27 I
l l
l l l l
l l
1 1
4 i'
j 1
E3 1 8806010266 DR 880527 -
ADOCK 05000325 DCD
ry
- 1. , 4 .
ENCLOSURE 4 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 -
NRC DOCKET 50 325 OPERATING LICENSE DPR-71 REQUEST FOR LICENSE AMENDMENT ~
SUMMARY
' LIST OF REVISIONS UNIT 1 Pages Descriotion of Changes, 3/4 3-11 Deleted reference to Valve Group 1 in Item 1.a.2, revised instrument tag numbers in Item 1.a.2, and added referenes to low level 3 setpoint under Item 1.a.
3/4 3-12 Reprinted to accommodate inserts.
, 3/4 3 13 Deleted reference to Valve Group 1 in
, Items 2.c and 3.e, revised instrument .
tag numbers in Items 2.c and 3.e. !
3/4 3-17 Revised instrument tag numbers in .;
Item 1.a.2, and added reference to low level 3 setpoint under Ite ,l.a. -
3/4 3-18 Revised instrument tag numbers in j Item 2.c. ]
3/4 3-19 Revised instrument tag numbers in Item 3.e. ;
3/4 3 22 Revised instrument tag numbers in Item 1.a.2, ano added reference to low 4
level 3 setpoint under Item 1.a. ,
1 i 5
3/4 3-23 Revised instrument tag numbers in Items !
i 2.c and 3.e. l 3/4 3 25 Revised instrument tag numbers in
- Item 1.a.2, and added reference to low level 3 setpoint under Item 1.a.
' I 3/4 3-26 Reprinted to accommodate insertions. l 1
i 3/4 3-27 Revised instrument tag numbers in Items 2.c and 3.e.
i l
1
{ E4-1 l l
- z. .
ENCLOSURE 5 BRUNSWICK STEAM ELECTRIC PIANT, UNIT 1 NRC DOCKET 50-325 OPERATING LICENSE DPR-71 REQUEST FOR LICENSE AMENDMENT IECHNICAL SPECIFICATION PAGES
'~
(BSEP-1-128) 24BLE 3.3.2-1 ,,
g ISOLATION ACTUATION INSTRUMENTATION E
y VALVE CROUPS MINIMUM NUMBER APPLICABLE -
g OPERATED BY OPERABLE CHANNELS OPERATIONAL X TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a) PER TRIP SYSTEM (b)(c) CONDITION ACTION I
Q l. PRIMARY CorfAINMENT ISOLATION
, s. Reactor Vcasel Water Level -
- 1. Low, Level 1 2,6,7,8 2 1,2,3 20 (B21-LT-N017A-1,B-1,C-1,D-1) -
(B21-LTM-NOl7A-1,B-1,C-1,D-1)
- 2. Low, Level 2 3 2 1,2,3 20 !
(B21-LT-N024A-1,B-1, and B21-LT-NO25A-1,B-1)
(B21-LTM-NO24A-1-1,B-1-1 and t', B21-LTM-NO25A-1-1,B-1-1) e u, 3. Low, Level 3
- j. (B21-LT-N024A-1,B-1; 1 2 1,2,3 20 8 B21-LT-N025A-1,B-1);
(B21-LTS-N024A-1-2,B-1-2; B21-LTS-N025A-1-2,B-1-2)
- b. Drywell Pressure - High 2,6,7 2 1,2,3 20 (C71-PT-N002A,B,C,D)
(C71-PTM-N002A-1,B-1,C-1,D-1)
- c. Main Steam Line g 1. Radiation - High 1 2 1,2,3 21
. (D12-RM-K603A,B,C,D) o
@ 2. Pressure - Lov 1 2 1 22
$ (B21-PT-NO15A,B,C,D)
" (B21-PTM-NO15A-1,B-1,C-1,D-1)
(BSEP-1-128) ll TABLE 3.3.2-1 (Continued)
E .
y ISOLATION ACTUATION INSTRUMENTATION N
M VALVE CROUPS MINIMUM NUMBER APPLICABLE 8 OPERATED BY OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER SIGNAL (a) PER *11tIP SYSTEM (b)(c) CONDITION ACTION U
y PRIMARY CONTAINMENT ISOLATION (Continued)
- 3. Flow - High 1 2/line 1 22 (B21-PDT-NOO6A,B,C,D; B21-PDT-NOO7A,B,C,D;
- B21-PDT-NOO8A,B,C,D; .
B21-PDT-NOO9A,B,C,D)
(B21-PDTM-NOO6A-1,B-1,C-1,D-1; -
R B21-PDTM-NOO7A-1,B-1,C-1,D-1;
- B21-PDTM-NOO8A-1,B-1,C-1,D-1; Y B21-PDTM-NOO9A-1,B-1,C-1,D-1)
C
- d. Main Steam Line Tunnel Temperature - High 1 2(d) 1, 2, 3 21 (B21-TS-N010A,B,C,D; B21-TS-N0llA,B,C,D; B21-TS-N012A,B,C,D; B21-TS-N013A,B,C,D)
- e. Condenser Vacuum - Low 1 2 1, 2 I* ) 21 (B21-PT-N056A,B,C,D)
(B21-PTM-N056A-1,B-1,C-1,D-1)
- f. Turbine Building Area S Temperature - High 1 4(d) 1 2, 3 21 2 (B21-TS-3225A,B,C,D; 3 B21-TS-3226A,B,C,D; me B21-TS-3227A,B,C,D; P B21-TS-3228A,B,C,D; B21-TS-3229A,B,C,D; B21-TS-3230A,B,C,D; B21-TS-3231A,B,C,D; B21-TS-3232A,B,C,D)
(BSEP-1-128) ,
TABLE 3.3.2-1 (Continued) -
E
@ ISOLATION ACTUATION INSTRLMENTATION
~
E g VALVE CROUPS MINIMUM NUMBER APPLICABLE M OPERATED BY OPERABLE CHANNELS OPERATIONAL 8
TRIP FUNCTION AND INSTRUMENT NUMBER SICNAL(a) PER TRIP SYSTEM (b)(c) CONDITION ACTION E
y 2. SECONDARY COrrAINMENT ISOLATION
- a. Reactor Building Exhaust Radiation - High 6 1 1, 2, 3, 5, and* 23 (D12-RM-N010A,B) .
- b. Drywell Pressure - High 2,6,7 2 1,2,3 23 (C71-PT-N002A,B,C,D) ~
(C71-PTM-N002A-1,B-1,C-1,D-1)
- c. Reactor Vessel Water Level -
Low, Level 2 3 2 1,2,3 23 l -
t (B21-LT-NO24A-1,B-1 and
.' (B21-LTM-NO24A-1-1,B-1-1 and
" B21-LTM-NO25A-1-1,B-1-1)
- 3. REACTOR WATER CLEANUP SYSTEM ISOLATION
- a. A Flow - High 3 1 1,2,3 24 (C31-dFS-N603-1A,lB)
- b. Area Temperature - High 3 2 1, 2, 3 24 (C31-TS-W600A,B.C,D,E,F)
- c. Area Ventilation A Temp. - High 3 2 1,2,3 24
{ (C31-TS-N602A,B,C,D,E,F) 3 II}
- 5. d. SLCS Initiation NA 1, 2, 3 24
,a (C41A-SI)
- e. Reactor Vessel Water Level -
E Low, Level 2 3 2 1, 2, 3 24 l (B21-LT-NO24 A-1,B-1 and B21-LT-NO25 A-1,B-1)
(B21-LTM-NO24A-1-1,B-1-1 and B21-LTM-NO25A-1-1,B-1-1)
=
(BSES 1-128) .
TABLE 3.3.2-2 (Continued)
E g ISOLATION ACTUATION INSTRUMENTATION SETPOINTS .
E ALLOWABLE M
M TRIP FUNCTION AND INSTRUMENT NUMBFR TRIP SETPOINT VALUE e
@ PRIMARY CONTAI M ENT ISOLATION G
~ 1. PRIMARY CONTAIW ENT ISOLATION
- a. Reactor Vessel Water Level -
- 1. Low, Level 1 3 + 162.5 inches
(B21-L7M-N017A-1,8-1,C-1,D-1)
- 2. Iow, Level 2 3 + 112 inches
(B21-LTM-N024A-1-1,B-1-1 and B21-LTM-M025A-1-1,B-1-1) -
- 3. Low, Level 3 3 +2.5 inches
- Y (B21-LTS-N024A-1-2,B-1-2; O B21-LTS-N025A-1-2,B-1-2)
- b. Drywell Pressure - High $ 2 psig < 2 psig (C71-PTM-N002A-1,B-1,C-1,D-1)
- c. Main Steam Line
- 1. Radiation - High $ 3 x full power background 1 3.5 x full power (D12-RM-K603A,B,C,D) background
- 2. Pressure - Low 3 825 psig 1 825 psig (821-PTM-N015A-1,B-1,C-1,D-1)
E. 3. Flow - High $ 140% of rated flow $ 14CZ of rated flow 5 (B21-PDTM-N006A-1,B-1,C-1,D-1;
?, B21-PDTM-N007A-1,B-1,C-1,D-1; z B21-PDTM-N008A-1,B-1,C-1,D-1;
? B21-PDTM-N009A-1,B-1,C-1,D-1)
(BSEP-1-128)
TABLE 3.3.2-2 (Continued) -
E Q ISOIATION ACTUATION INSTRIMENTATION SETPOINTS E
~ ALLOWABLE O TRIP FUNCTION AND INSTRUMENT NIMBER TRIP SETPOINT VALUE e
@ PRIMARY COrfAIM ENT ISOLATION (Continued)
U .
y d. Main Steam Line Tunnel Temperature - High < 200*F < 200*F (B21-TS-N010A,B,C,Di B21-TS-N0llA,B,C,D; B21-TS N012A,B,C,D;
{
B21-TS-N013A,B,C,D) ,
- e. Condenser Vacuum + Low 3 7 inches Hg vacuum 3 7 inches Hg vacuum (B21-PIM-N056A-1,B-1,C-1,D-1) ,
t f. Turbine Building Area Temp - High $ 200*F < 200*F
' * (B21-TS-3225A,B,C,D; Y B21-TS-3226A,B,C,D; 5 B21-TS-3227A,B,C,D; B21-TS-3228A,B,C,D; B21-TS-3229A,B,C,D; B21-TS-3230A,B,C,D; B21-TS-3231A,B,C,D; B21-TS-3232A,B,C,D)
- 2. SECONDARY CONTAIM EN ISOLATION
- a. Reactor Building Exhaust Radiation - High ~< 11 mr/hr < 11 mr/hr
~
(D12-RM-N010A,B) h b. Drywell Pressure - High < 2 psig < 2 psig
$ (C71-PTM-N002A-1,B-1,C-1,D-1) z c. Reactor Vessel Water Level -
? iiw,I,evel 2 3 + 112 inches * > + 112 inches *
(B21-LTM-NO24A-1-1,B-1-1 and
]-
821-LIN-NO25A-1-1,B-1-1)
~
1 ,- s
- ' - +
[
______..___.-_.___.m_ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ _ _ _ . _ - _ _ m_m.___ _ _ _ _ . _ _ __ - _ _ _ _ - - - _ _ _. _ _ _ _ _ _ _ _ - _ _ _ . ____- _ - .'
(CSEP-1-128) f
- ...- W '
TABLE 3.3.2-2 (dontinuec) ,-
, 03 ~
h ,
ISOLATION ACTUATION IMSTRUMENTATION Sf*FOIU*S g ,_
_~
g ALLOWABLE _
T2IP FUNCTION _ AND INSTRUMENT NUMBER TRIP SETPCIhT'~ VALUE
~
@ 3. REACTOR WATER CLEANUP SYSTEM ISOLATION ,
y a. A Flow - High $ 53 gal /miu < 53 gal / min
,, (G31-dFS-N603-1 A,lB)
- b. Ares, Temperature - High $ 150*F < 150*F (G31-TS-N600A,B,C,D,E,F)
- c. Area Ventilation Temperature A Temp - High $ 50*F < 50*F (C31-TS-N602A,B,C,D,E,F) .
- d. SLCS ~~ itiation NA NA (C41A-SI) ti c. Reactor Vessel
'
- Low, Level 2 3 + 112 inches
- Y (B21-LTM-NO24A-1-1,B-1-1 and G B21-LTM-N025A-1-1,B-1-1) ._
- 4. CORE STANDBY COOLING SYSTEMS ISOLATION
- s. High Pressure Coolant Injection System Isolation
- 1. HPCI Steam Line Flow - High < 300% of rated flow < 300% of rated flow (E41-PDTS-N004-2; E41-PDTS-N005-2)
- 2. HPCI Steam Line High Flow s.
3 < t < 7 second3'.
g.
Time Delay Relay 3<t< 12 secoads
.. (E41-TDR-K33; -
E. E41-TDR-K43) 2 a 3. HPCs Steam Supply Pressure - Low 3 100 psig 3 100 psig (E41-PSL-NOOlA,B,C,D)
.N -
J , (BSEP-1-128)
TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONCE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIMd (Seconds)#
- 1. PRIMARY CONTAINMENT ISOLATION
- a. Reactor Vessel Water Level -
- 1. Low, Level 1 -<13 (521-LT-N017A-1,B-1,C-1,D-1)
(B21-LTM-NOl7A-1,B-1,C-1,D-1)
- 2. Low, Level 2 <l.0*
(B21-LT-N024A-1,B-1 and B21-LT-N025A-1,B-1)
(B21-LTM-N024A-1-1,B-1-1 and l B21-LTM-N025A-1-1,B-1-1)
- 3. Low, Level 3 < l.0*
(B21-LT-N024A-1,B-1; B21-LT-N025A-1,B-1)
(B21-LTS-N024A-1-2,B-1-2; 3 821-LTS-N025A-1-2,B-1-2) I
- b. Drywell Pressure - High <13 (C71-PT-N002A,B,C,D)
(C71-PTM-NOO2A-1,B-1,C-1,D-1)
- c. Main Steam Line -<l.0*
- 1. Radiation - High(b)
(D12-RM-K603A,B,C,D)
- 2. Pressure - Low -<13 (B21-PT-N015A,B,C,D)
(B21-PTM-N015A-1,B-1,C-1,D-1) t
- 3. Flow - High <0.5* -I
~ i (B21-PDT-N006A,B,C,D; B21-PDT-N007A,B,C,D; B21-PDT-NOO8A,B,C,D; B21-PDT-NOO9A,B,C,D)
(B21-PDTM-NOO6A-1,B-1,C-1,D-1; B21-PDTM-NOO7A-1,B-1,C-1,D-1; B21-PDTM-N008A-1,B-1,C-1,D-1; B21-PDTM-N009A-1,B-1,C-1,D-1)
- d. Main Steam Line Tunnel Temperature - High <13 (B21-TS-N010A,B,C,D; B21-TS-N011A,B,C,D; B21-TS-N012A,B,C,D; B21-TS-N013A,B,C,D)
- e. Condenser Vacuum - Low <13
~
(B21-PT-N056A,B,C,D)
(B21-PTM-N056A-1,B-1,0-1,D-1)
.q BRUNSWICK - UNIT 1 3/4 3-22 Amendment No.
k
. . l r -
(BSEP-1-128)
I TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUME:IT NUMBER RESPONSE TIME (Seconds)f PRIMARY CONTAINMENT ISOLATION (Continued)
- f. Turbine Building Area Temperature - High NA (B21-TS-3225A,B,C,D; B21-TS-3226A,B,C,D; B21-TS-3227A,B,C,D; B21-TS-3228A,B,C,D; B21-TS-3229A,B,C,D; B21-TS-3230A,B,C,D; B21-TS-3231A,B,C,D; B21-TS-3232A,B,C,D)
- 2. SECONDARY CONTAIRMENT ISOLATION
- a. Reactor Building Exhaust Radiation - High(b) , 513 (D21-CM-N010A,B)
- b. Drywell Pressure - High '
$13 (C71-PT-N002A,B,C,D)
(C71-PTM-N002A-1,B-1,C-1,D-1)
- c. Reactor Vessel Water Level - Low, Level 2 ~<l.0*
(B21-LT-N024A-1,B-1 and ,
B21-LT-N025A-1,B-1) ,
l (8:1-LTM-N024A-1-1,B-1-1 and B21-LTM-N025A-1-1,B-1-1)
- 3. REACTOR WATER CLEANUP SYSTEM ISOLATION
- a. A Flow - High -<13 (C31-dFS-N603-1A,1B)
- b. Area Temperature - High ~<13 (C31-TS-N600A,B,0,D,E,F)
- c. Area Ventilation Temperature AT - High ~<13 i (G31-TS-N602A,B,C,D,E,F)
- d. SLCS Initiation NA (C41A-S1)
- e. Reactor Vessel Water Level - Low, Level 2 -<l.0w (B21-LT-N024 A-1,B-1 and Bel-LT-N025 A-1,B-1)
(B21-LTM-N024A-1-1,B-1-1 and B21-LTM-NO25A-1-1,B-1-1)
BRUNSWICK - UNIT 1 3/4 3-23 Amendment No.
e
. (BSEP-1-128)
$ TABLE 4.3.2-1 E
y ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E
M CHANNEL OPERATIONAL
' CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH
@ TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED Cl
~ 1. PRIMARY CONTAINMENT ISOLATION
- a. Reactor Vessel Water Level - ,
- 1. Low, Level 1 (B21-LT-NOl7A-1,B-1,C-1,D-1) NA(a) NA R(b) 1, 2, 3 (B21-LTM-NOl7A-1,B-1,C-1,D-1) D M M 1, 2, 3
- 2. Low, Level 2 (B21-LT-N024A-1,B-1 and '
u B21-LT-NO25A-1,B-1) NA(a) NA R(b) 1, 2, 3 I #'
(B21-LTM-NO24A-1-1,B-1-1 and B21-LTM-NO25A-1-1,B-1-1) D M M 1, 2, 3
- 3. Low, Level 3 ,
(B21-LT-N024A-1,B-1; NA', a) NA R(b) 1, 2, 3 B21-LT-N025A-1,B-1)
(B21-LTS-N024A-1-2,B-1-2; D M M 1, 2, 3 B21-LTS-N025A-1-2,B-1-2)
- b. Drywell Pressure - High (C71-PT-N002A,B,C,D) NA(a) NA R(b) y , 2, 3 (C71-PTM-N002A-1,B-1,C-1,D-1) D M M 1, 2, 3 g c. Main Steam Line '
w 1. Radiation - High D W R(d) 1 2, 3 5 (D12-RM-K603A,B,C,D)
B
$ 2. Pressure - Low
" (B21-PT-NO15A,B,C,D) NA(a) NA R(b) y f (B21-PTM-NO15A-1,B-1,C-1,D-1) D M M 1 4
(BSEP-1-128)
$ TABLE 4.3.2-1 (Continued)
E E ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS
- M X CHANNEL OPERATIONAL 8 CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH
@ TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST _ CALIBRATION SURVEILLANCE REQUIRED U
PRIMARY CONTAINMENT ISOLATION (Continued)
- 3. Flow - High (B21-PDT-NOO6A,B,C,D; NA(a) NA R(b) y B21<PDT-NOO7A,B,C,D; B21-PDT-NOO8A,B,C,D; B21-PDT-NOO9A,B,C,D)
(B21-PDTM-NOO6A-1,B-1,C-1,D-1; D M M 1 ,
w B21-PDTM-NOO7A-1,B-1,C-1,D-1; 2 B21-PDTM-NOO8A-1,B-1,C-1,D-1; w B21-PDTM-NOO9A-1,B-1,C-1,D-1)
$ d. Main Steam Line Tunnel Temperature - High NA M R 1, 2, 3 (B21-TS-N010A,,,C,D; B21-TS-N0llA,B,C,D; B21-TS-N012A,B,C,D; B21-TS-N013A,B,C,D) i
- e. Condenser Vacuum - Low
$ (B21-PT-N056A,B,C,D) NA(*) NA R(b) 1, 2f U (B21-PTM-N056A-1,B-1,C-1,D-1) D M M 1, 2f o.
3 f. Turbine Building Area Temp-High NA M R 1, 2, 3 .
5 (B21-TS-3225A,B,C,D; z B21-TS-3226A,B,C,D;
. B21-TS-3227A,B,C,D; B21-TS-3228A,B,C,D; B21-TS-3229A,B,C,D; B21-TS-3230A,B,C,D; B21-TS-3231A,B,C,D; 4 B21-TS-3232A,B,C,D)
_--._____--_-----__-_____--__----___----_-___-______-----_-_--_--_a- _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - . . _ - - _ _ _
(BSEP-1-128) g TABLE 4.3.2-1 (Continued)
E ,
y ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS n"
X CHANNEL OPERATIONAL 8 CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH
@ TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED a
- 2. cECONDARY CONTAINMENT ISOLATION
- a. Reactor Building Exhaust Radiation - High D M R 1,2,3,5, and *
(D12-RM-N010A,B)
- b. Drywell Pressure - High (C71-PT-N002A,B,C,D) NA(a) NA R ID) 1, 2, 3
( C71-PTM-N002 A-1, B-1, C-1, D-1 ) D M M 1, 2, 3 Reactor Vessel Water Level -
c.
ti Low, Level 2 (B21-LT-NO24A-1;B-1 and NA(a) NA R(b) 1 2, 3 Y B21-LT-NO25a-1,B-1) n (B21-LTM-NO24A-1-1,B-1-1 and D M M 1,2,3 B21-LTM-NO25A-1-1,B-1-1)
- 3. REACTOR WATER CLEANUP SYSTEM ISOLATION
- a. A Flow - High D M R 1,2,3 (C31-dFS-N603-1A,lB)
- b. Area Temperature - High NA M R 1, 2, 3 (C31-TS-N600A,B,C,D,E,F)
Area Ventilation A Temp - High NA M R 1, 2, 3 g c.
(C31-TS-N602A,B,C,D,E,F) m
- d. SLCS Initiation NA R NA 1, 2, 3
$ (C41A-SI) n z e. Reactor Vessel Water Level -
. Low, Level 2 (B21-LT-NO24A-1,B-1 and NA(a) NA R(b) 1, 2, 3 B21-LT-NO25A-1,B-1)
( B21-LTM-NO24 A-1-1, B-1-1 and D M M 1,2,3 821-LTM-NO25A-1-1,B-1-1)
- __ _ _ _ _ _ _ . _ _ _ _ _