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)ML20217Q513 |
Person / Time |
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Site: |
Brunswick |
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Issue date: |
08/27/1997 |
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From: |
CAROLINA POWER & LIGHT CO. |
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To: |
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Shared Package |
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ML20217Q512 |
List: |
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References |
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NUDOCS 9709030163 |
Download: ML20217Q513 (10) |
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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
_ _ _ _ - _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _
ENCLOSURE 1 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 NRC DOCKET NOS. 50 325 AND 50-324 OPERATING LICENSE NOS. DPR 71 AND DPR-02 SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENTS PRESSURE-TEMPERATURE LIMITS CURVES TYPED TECHNICAL SPECIFICATION PAGES - UNIT 1 p
[ $Doh 05 24 m
FIGURE 3.4.6.1-1 PRESSURE-TEMPERATURE LIMITS REACTOR VESSEL NORMAL OPERATION WITH CORE NOT CRITICAL
{
4200 ._ _ _ _ _ _ _ o _ _ _ _ ___.. _ _ _ ___ _ . . _._ __ _ _
_J^ ::: :E: :::1::::E ::: ::11
~
. : : :11:
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~
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- 1' :::::::::: _____._ _ _
~~ ~~
900 _ _ i _ _ _ .
f
- : ~ ~
)(
800 _ . _ _ __ _ ___
j __ ____ ._
4_ __ _..- :::::: :::: _ ___ .
T 700 e __..
- T :
~~ ~ ~~~
_ _ _ :1 NORMAL OPERATION a: ._ _ - _.._ __
p . --
CORE NOT CRITICAL - UNIT 1 600 4 --
M - _-_.-
HEATUP / COOLDOWN
$ 550 psig -
~-
-~ -
- 77;;7 ,7
-g._
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- l_ T
~~~~
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_.____ _._ll ___... _ _ ...__ _ ll- OPERATE TO RIGHT AND/OR BELOW
{
400 LIMITING LINE
~~~
.__ $:: : = BASES: i 300 ~
~~-~
,_ 7 ] 1. FUEL IN REACTOR
- 2. s 16 EFPY 200 f 3. 7.1 x $o" N/CM2> 1MEV r~ ~
- 4. RTNOT = 93*F (1/4 T)
/ 5.15 PSIINSTRUMENT LOCATION 100 ___ _.
CORRECTION INCLUDED BOLTUP' 6. REG. GUIDE 1.99 REV. 2 70*F ___ ____
0 . gn . .
0 100 200 300 400 500 600 TEMPERATURE (*F)
BRUNSWICK - UNIT 1 3/4 4-15 Amendment No.
I i
FIGURE 3.4.6.1-2 PRESSURE-TEMPERATURE LIMITS REACTOR VESSEL NORMAL OPERATION WITH CORE CRITICAL 1200 _ _ ____ __ _ ___._ ._ , .._ _ _
. ____ .l. ::: ._ _ _ _l :::E: :
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- J:: Ef: i::1 1:1Z ~1 :T:: : T~_T. 1:~T~ ZiTZ Z :Z
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y ~ ~ ~ ~
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p _
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Po : : T:1 1Z- uumNG CURVE g _ _.___ __ _
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._ -^
i OPERATE TO RIGHT AND/OR BELOW g 500 .____._._ _ _._ _ _ _ _. . . _ __._.__
q_. tiuiriNo tine
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____._____ _, OPERATION IN CROSS-HATCHED AREA 400 PERMITTED ONLY WHEN WATER LEVEL igp WI L ORMAL RANGE FOR POWER
- ~] -7
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- s. 7.1 x to" mcu2 > iMEV
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l 4. RTNDT = 93*F (114 T)
///s /s 5.15 PSI INSTRUMENT LOCATION 100 , ;
CORRECTION INCLUDED
$ f g [E _ -_.. __ __.
- 6. REG. GUIDE 1.99 REV. 2
) /, _ ,
/
/AT i
~~
0 2o sa 2to- > '
0 100 200 300 400 500 600 TEMPERATURE ('F)
BRUNSWICK . UNIT 1 3/4 4-16 Amendment No.
FIGURE 3,4,6.1-3a PRESSURE-TEMPERATURE LIMITS REACTOR VESSEL HYDROSTATIC AND LEAK TESTS 1200 ., g. 1.
1100
) y
/
pl..'
1000 _
/ .
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, L 800 _ _ j _ _
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" 500 HYD ROSTATIC '
PRESSURE TEST - UNIT 1 400 _ _
LIMmNG CURVE OPERATE TO RIGHT AND/OR BELOW
. 313 psig . - LIMmNG LINE 300 _
bases:
- 1. FUEL IN REACTOR
~ ~ ~ ~~ ^
- 2. s 14 EFPY 200 2
- 3. 2.39 x to" N/CM > 1MEV(N16 Nozzle)
- 4. N18 NOZZLE RTNDT = 86.3*F (1/4 T) ga _ __ _
- 5. BOTTOM HEAD REGION RTNOT = 10*F (1/4 T) 100 ~ ~
- 6. BELTLINE REGION RTNDT = 85.4*F (114 T)
-BOL 7
EE dSId" Efuh0^'#"
- g f,F ,,g _ _ [" _ 8. REACTOR NOT CRmCAL 0 . ..- + + . . . . . .. . .' .
60 70 80 90 100 110 120 130 140 150 160 170 180 190 200 210 220 230 240 TEMPERATURE (*F)
BRUNSWICK - UNIT 1 3/4 4-17 Amendment No.
FIGURE 3.4.6.1-3b PRESSURE-TEMPERATURE LIMITS REACTOR VESSEL HYDROSTATIC AND LEAK TESTS 1200 _ _ _
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6 1100 _
~
f d t
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~~
~
- 3. 2.73 x 10" wCu2 > iMEV(N16 Nozzle)
~
~ ~ ~
- 4. N16 NOZZLE RTNOT = 89.7'F (1/4 T)
_ _~ _ [ _
- 5. BOTTOM HEAD REGION RTNDT = 10*F (1!4 T) 100 ~ ~
6, BELTUNE REGION RTNOT = 85.4*F (1/4 T)
TION p -- 2~ 7- [5 Sg Z:
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' 70*F
_ ::_ _ _ 8. REACTOR NOT CRITICAL 0 :'T" ... . ., .. . . ;. ;
+ ...
60 70 80 90 100 110 120 130 140 150 160 170 180 190 200 210 220 230 240 TEMPERATURE ('F)
BRUNSWICK - UNIT 1 3/4 4-18 Amendment No.
. _. _ _ - . ._ . _ _ , _ . . _ . . _ . _ , . _ . . _ _ . _ . m . .- ._ > _ . _ . . _ . _ _
-3 . ..
x.:
ENCLOSURE 2-T I
- BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 NRC DOCKET NOS. 50-325 AND 50-324 o OPERATING LICENSE NOS DPR-71 AND DPR-62' F SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENTS .
PRESSURE-TEMPERATURE LIMITS CURVES a
D J
l~
i.
k j.,
r TYPED TECHNICAL SPECIFICATION PAGES - UNIT 2 i
i i
h c' a
i i
f i
F F
I 4
--, , . , . - , - , d. -
~ ~
FIGURE 3.4.6.1-1 PRESSURE-TEMPERATURE LIMITS REACTOR VESSEL NORMAL OPERATION WITH CORE NOT CRITICAL 1200 ___ _.__ _. _ _ ___ ._. _._
- ~_:_1~~'~" 1 .::
~
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1100 _ _ _ _ ___ ___.
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1:-
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900 __ __ __ ._ __.._ _ __ _
y 800 _ _. ________
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700 r 3 ____ _ _ __ . _
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, _.. - - -~ - - - -- ---
CORE NOT CRITICAL - UNIT 2 h :~:::1:::T :: .1:~ I_ : HEATUP / COOLDOWN u) ___._ __... ___ .. . __ . __ __,_ _ _
LIMITING CURVE i
~ ~
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. OPERATE TO RIGHT AND/OR BELOW 400 _ ___ ___ ____
LIMITING LINE
~
- ~~ ~~ ~~
BASES-300 r --~-- ~~'
- 7 1. FUEL IN REACTOR
- 2. s 16 EFPY 200 r - -
- 3. 7.1 x to'7 N/CM2 > 1MEV 2
- 4. RTNDT = 81.4*F (1/4 T)
_____.__[_-
l 2-- CORRECTION INCLUDED
-- ~
BOLTUP 6. REG. GUIDE 1.99 REV. 2 70-F : 1 0 373 .
0 100 200 300 400 500 600 TEMPERATURE (*F) t BRUNSWICK - UNIT 2 3/4 4-15 Amendment No.
' FIGURE 3.4.6.1-2 PRESSURE-TEMPERATURE LIMITS REACTOR VESSEL NORMAL OPERATION WITH CORE CRITICAL
- : Z
~ ~
1:::1
~
1::E_ EE .i_ : :1
~
_ .: :::T:1 1100 _ ___ __ . _ . . _ ____ _ __ __ __ __ __. _
____ _ 5 -.. ._.
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1 Z E _Z Z ::E
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Z:1ZZ 1 ZZ ZZ
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ZZ
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- _ 1. .._ _ .
~T1 900 _
_j__ . _.. -_..
800 _ .__ _ _ ___.. _ _ _ _ _ _ _
~ ~'
~
._ - . _ --: ~L_ .
700
,i 4 __
_4___ _ _ _._ . ._
i i g _ _. . ._ -
NORMAL OPERATION t 4 - - - - -
CORE CRITICAL - UNIT 2
@ 600 . . - _. . .
HEATUP / COOLDOWN g __ .. __ _-__-_. . . . _
g .
LIMITING CURVE g _ _ _ _ __ . _-..
p a 500 _
_ . _ _ . _ _____._ . tiui7ina ting
_. -_~
---.-_..~-~
. CPERATION IN CROSS-HATCHED AREA 400 . _ ____ __ _
IS WITHIN NORMAL RANGE FOR POWER OPERATION.
ZI ZZ_i . --
BASES:
300 -- -
- 1. FUEL IN REACTOR
-~
- 1]E k_ 2. 5 16 EFPY 200 __p r __ _. _
- 3. 7.1 x to" N/CM2 > iMEV ZZ /,/[
~~
- 4. RTNOT = 81.4*F (1/4 T)
~~ ~
/~
5.15 PSIINSTRUMENT LOCATION 100 ___ _ .
r, ; ,; CORRECTION INCLUDED
/ g 6. REG. GUIDE 1.99 REV. 2 f ..
/ ;7 li' / /h~~ ~t 0 70- 185 2io a >
0 100 200 300 400 500 600 TEMPERATURE (*F)
BRUNSWICK - UNIT 2 3/4 4-16 Amendment No.
FIGURE 3.4.6.1 3a PRESSURE-TEMPERATURE LIMITS REACTOR VESSEL HYDR 0 STATIC AND LEAK TESTS 1200 1100
}[
(
1000 _ _ _
.. /
f 900
- f. . -- -
l -
./. .
800 /
J - .
700 l
/ _ _
s / '-
',.M -
p g 600 y {g/ _
541 psg E
' 500 t
[I HYDROSTAflC PRESSURE TEST - UNIT 2 p
400 uumNG curve 313 psg T E 300 '
Bases-
~
- 1. FUEL IN REACTOR
- 2. s 14 EFPY 200 - - 2
~
- 3. 2.39 X 10" N/CM > 1MEV (N16 Nozzk)
__ _ _.:. 4. N16 NOZZLE RTNDT = 78.6*F (1/4 T)
[-} - - -
- 5. BOTTOM HEAD REGION RTNOT = 40*F (1/4 T) 100 4 _ _ _ _
- 6. BELTUNE REGION RTNDT = 81.8*F (114 T)
- by -
_ :- : :- 7C05"af8&"eSis^ "
70*F -- - -- - -
- 8. REACTOR NOT CRmCAL 0 .. .
60 70 80 90 100 110 120 130 140 150 160 170 180 190 200 210 220 230 240 TEMPERATURE ('F)
BRUNSWICK - UNIT 2 3/4 4-17 Amendment No.
REACTOR VESSEL HYDROSTATIC AND LEAX TESTS 1200 - -
- j -j 1 F
1100 l
/ -
1000 .
p /
/
900 - -
j /
t
, . -_- - . L _ _
800 _ _.
/,
,L 700 4
j' a s A
tu 600 -
N -
t
/ .:
% ~
.541 psg D) y ettt tt f-} h 7 .y.. .g a: 500 o- k HYDROSTATIC PRESSURE TEST - UNIT 2 I
400 y uumNG CURVE gEgRIGHT AND/OR BELOW 313 psg - -
300
- _ bases:
- 1. FUEL IN REACTOR "1
It' ~
- 2. s 16 EFPY 200 .L 2
- 3. 2.7s x 10" N/CM > 1MEV (N16 Nozzle)
- 4. N16 NOZZLE RTNDT = 82.0*F (1/4 T)
- 5. BOTTOM HEAD REGION RTNDT = 40*F (114 T) 100 ----
- 6. BELTLINE REGION RTNOT = 81.8'F (1/4 T) dowp; --
} 7' c'o"RR O NC UOko^ ' "
[{.
70*F - - - - __ _ 8. REACTOR NOT CRmCAL 7-_
0 o .
r .
60 70 80 90 100 110 120 130 140 150 160 170 180 190 200 210 220 230 240 TEMPERATURE ('F)
BRUNSWICK - UNIT 2 3/4 4-18 Amendment No.