|
---|
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
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
f3 3/";2 POWER DISTRIEUTION LIMITS ,
L-) -
3/*.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITI':S CONDITION FOR OPERATION 3.2.1. All AVERAGE PLANAR LINEAR HEAT GENERATION RATES ( APLHGR's) for eacn type of fuel as a function of AVERAGE PLANAR EXPOSURE snell not exceed the limits shown in Figures 3.2.1-1, 3.2.1-2, 3.2.1-3, 3.2.1-4, 3.2.1-5, or 3.2.1-6.
APPLICA3ILITY: CONDITION 1, wnen THERMAL POWER > 25% of RATED THERMAL POWER.
ACTION:
With an APLHGR exceeding the limits of Figure 3.2.1-1, 3.2.1-2, 3.2-1-3, 3.2.1-4, 3.2.1-5, or 3.2.1-6, initiate corrective action within 15 minutes l
and continue corrective action so that APLHGR is within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or reduce THERMAL POWER to less than 25% of RATED THERMAL POL'ER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE REOUIREMENTS 4.2.1 All APLHGR's shall be verified to be equal to or less than the applicable limit determined frem Figure 3. 2'.1 -1, 3. 2 .1 - 2 , 3. 2.1 - 3,
- 3. 2.1-4, 3. 2.1-5, or 3. 2.1-6 : t
- a. At least once per 24 hcurs,
- b. Whenever THERMAL POWER has been increased by at least 15% of RATED THERMAL POWER and steady state operating conditions have been established, and
- c. Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is operating with a LIMITING CONTROL ROD PATTERN for APLHGR.
BRUNSWICK-UNIT 1 3/4 2-1 !
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l n i i i i c-0 5000 10000 15000 20000 25000 30000 PLANAR AVERAGE EXPOSURE (mwd /t)
FUEL TYPE P8DRB285 (P8x8R)
MAXIMUM AVERAGE PLANAR LINEAR llEAT GENERATION RATE (MAPLilGR)
VERSUS AVERAGE PLANAR EXPOSURE 3
FIGURE 3.2.1-5
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i 0 5000 10000 15000 20000 25000 30000 PLANAR AVERAGE EXPOSURE (mwd /t)
FUEL TYPE P8DRB26511 (P8x8R)
MAXIMUM AVERAGE PLANAR IiNEAR HEAT GENERATION RATE sMAPLilGR)
VERSUS AVERAGE Pl_aAR EXPOSURE FIGURE 3.2.1-6
POWER O!STRIBUTION LIMITS 3 /4. 2. 2 APRM SETPOINTS LIMIT!NG CONDITION FOR OPERATION
. 3.2.2 The flew biased APRM scram trip setpoint (S) and red block trip set-point (Sgg) shall be established according to the following relationships:
S 1 (0.66W + 54%) T Sgg 1 (0.66W + 42%) T where: 5 and 5,0 are in percent of RATED THERMAL POWER, W = Loop recirculation flow in percent of rated flow, T = Lowest value of the ratio of design TPF divided by the MTPF obtained for any class of fuel in the core (T 1 1.0),and Design TPF for 8x8 fuel = 2.45.
Design TPF for 8x8R fuel = 2.48.
Design TPF for P8x8R fuel = 2.48. l APPLICABILITY: CONDITION 1, when THERMAL POWER > 25% of RATED' THERMAL POWER.
ACTION:
With S or S g exceeding the allowable value, initiate corrective action within15m1$utesandcontinuecorrectiveactionsothat5and5 are within the required limits withip. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or reduce THERMAL POWEk0to less than 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />'.
SURVEILLANCE REOUIREMENTS 4.2.2 The MTPF for each class of fuel shall be determined, the value of T calculated, and the flow biased APRM trip setpoint adjusted, as required:
- a. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
- b. Whenever THERMAL POWER has been increased by at least 15% of
, RATED THERMAL POWER and steady state operating conditions
. have been established, and
. Initially anc at least once per 12 hcurs when re react:r is cperating with a LIMITING CONTROL ROC PATTEP." #:r 'iTPF.
BRUNSWICK-L' NIT 1 3/4 2-6
POWER DISTRTBUTTON LIMfTS -
3/4.2.3 MINIMUM CRITICAL POWER RATIO LIMITING CONDITION FOR OPERATION 3.2.3 The MINIMUM CRITICAL POWER RATIO (MCPR), as a function of core flow, shall be eaual to or greater than MCPR x the Kfshown in Figure 3.2.3-1 where MCPR values are: l
- ._ BOC3* to EOC3** E0C3-2000 M!iD/t
- 2000 MWD /t to EOC3 (8x8 fuel) 1.24 1.30 (8x8R fuel) 1.24 1.30 (P8x8R fuel) 1.30 1.32 APPLICABILITY: CONDITION 1, when THERMAL POWER > 25% RATED THERMAL POWER ACTION:
With MCPR less than the applicable limit determined from Figure 3.2.3-1 ,
initiate corrective action within 15 minutes and continue corrective action so that MCPR is equal to or greater than the applicable limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or reduce THERMAL POWER TO LESS THAN 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE REOUIREMENTS 4.2.3 MCPR shall be determined to be equal to or greater than the applicable limit determined from Figure 3.2.3-1 :
- a. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
- b. Whenever THERMAL POWER has been increased by at least 15%
of RATED THERMAL POWER and steady state operating conditions have been established, and
- c. Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is Operating with a LIMITING CONTROL ROD PATTERN for MCPR.
- End of Cycle 3 BRUNSWICK - UNIT 1 3/42-7
TABLE 3.3.4-2
$ C0tlTROL R00 WITilDRAWAL BLOCK IllSTRUMEtlTATION SETP0 lilts k U
-.t.i.l'. FullCTION AND INSTRUllENT TRHtBER TRIP SETP0 lilt ALL0llABLE VALUE
- 1. APRf1(C51-APRM-Cll.A,B,C,0,E,F) _
- a. Upscale (Flow Biased) 1 (0.66 W + 42%) T* s (0.66 41 + 42%) T*
- b. Inoperative NA MIPF flA MIFF
- c. Downscale > 3/125 of full scale > 3/125 of full scale
- d. Upscale-(Fixed) < 12% of RATED TilERf1AL P0 lier < 12% of RATED TilERMAL POWER
- 2. R00 BLOCK M0tilTOR (C51-RBM-Cll.A,0)
- a. Upscale < (0.66W + 41%) T* < (0.66 W t 41%) T* l
- h. Inoperative NA MIPF flA MIPF
- c. Downscale > 3/125 of full scale > 3/125 of full scale
- 3. S0lldCE RANGE MONITORS (C51-SRM-K600A,B,C,0) y
- a. Detector not full in NA 5
NA 6
- b. Upscale 1 1 x 10 cps s 1 x 10 cps
- c. Inoperative NA NA
- d. Downscale > 3 cps
> 3 cps .
- 4. IllTElti1EDI ATE RANGE MONITORS (C51-IRM-K601 A,8,C,D,E,F ,G,II)
- a. Detector not full in NA HA
- h. Upscale . < 100/125 of full scale < 108/125 of full scale
- c. Inoperative NA NA
- d. Downscale > 3/125 of full scale > 3/125 of full scale
T=2.48 for~8x8R fuel.
T=2.48 for P8x8R fuel. l 0
3/4.2 POWER DISTRIBUT10ft LIf1ITS B'ASES ti The specifications of this section assure that the peak cladding temoerature following the postulated design basis loss-of-coolant accident will not exceed the 2200'F limit specified in the Final Acceptance Criteria (FAC) issued in June 1971 considering the postulated effects of fuel pellet densification.
3/4.2.1 AVERAGE PLAilAR LIf1 EAR HEAT GEi1EPATI0t1 RATE This specifi:ation assures that the peak cladding tempera'.ure following the postulated design basis loss-of-coolant accidenn will not exceed the limit specified in 10 CFR 50, Appendix K.
The peak cladding temperature (PCT) following a postulated loss-of-coolant accident is primarily a function of the average heat genera-tion rate of all the rocs of a fuel assembly at any axial location and is dependent only seconcarily on the rod to rod power distribution within a assembly. The peak clad temperature is calculated assuming a LHGR for the highest powered rod which is equal to or.less than the design LHGR corrected for densification. This LHGR times 1.02 is used in the heatup code along with the exposure dependent steady state gap conductance and rod-to-rod local peaking factor. The Technical Specifica-tion APHGR is this LHGR of the highest powered rod divided by its local peaking factor. The limiting value for APLHGR is shown in Figures 3.2.1-1, 3.2.1-2, 3.2.1-3, 3.2.1-4, 3.2.1-5, and 3.2.1-6. l The calculational procedure used to establish the APLHGR shown'en Figura 3.2.1-1 thru 3.2.1-6 is based on a loss-of-coolant accident analysis.l The analysis was performed using General Electric (GE) calculational models which are consistent with the requirements of Appendix K to 10 CFR 50. A complete discussion of each code employed in the analysis is prcsented in Reference 1. Differences in this analysis ccmpared to previous analyses perfomed with Reference 1 are: (1) The analyses assumes a fuel assembly planar power consistent with 10h of the MAPLHGR shown in Figures 3.2.1-1, and 3.2.1-2; (2) Fission product decay is computed assuming an energy release rate of 200 MEV/ Fission; (3) Pool boiling is assumed after nucleate boiling is lost during the flow stagna-tion period; (4) The effects of core spray entrainment and counter-current flow limitation as described in Reference 2, are included in the reflooding calculations.
A list of the significant plant inout carameters to the loss-of-cociant accident analysis is presented in Bases Table 5 3.2.1-1.
BRUNSWICK-UNIT 1 B 3/4 2-1
~
. POWER DISTRIBUTIOil LIMITS .'
BASES 3/4.2.2 APRM SETPOIrlTS .
The fuel cladding integrity safety limits of Specification 2.1 were based on a TOTAL PEAKTNG FACTOR of 2.45 for 8x8 fuel and 2.48 for 8x8R and P8x8R fuel. The scram setting and rod block functions of the APRM instruments must be adjustad to ensure that the MCPR does not become less than 1.0 in the degraded situation. The scram settings and rod block settings are adjusted in accordance with the formula in this specification when the combination of THEREM. POWER and peak flux indi-cates a TOTAL PEAKING FACTOR greater than 2.45 for 8x8 fuel and 2.48 for 8x8R and P8x8R fuel. The method used to determine the design TPF shall be consistent with the method used to determine the MTPF.
3 /4. 2. 3 MIftIMUM-CRfU CAL POWER RATIO The required operating limit MCPR's at steady state operating conditions as specified'.in Specification 3.2.3 are derived from the Established
~ '
fuel cladding; integrity' Safety t MCPR of 1.07, and an analysis of abnormal operational transients For any abnent.a1 operating tran-sient analy, sis evaluation with the initial condition of the reactor being at the steady state operating limit, it is required that the resulting MCPR does not decr. ease below the Safety Limit.MCPR at any time during the transient assuming instrument trip. setting as given in Specification 2.2.1. .
To assure that the fuel cladding integrity Safety Limit is not exceeded during any anticipated abnormal operational transient, the most limiting transients have been analyzed to determine which result in the largest reduction in CRITICAL POWER RATIO (CPP). The type of transients evaluated were loss of flow, increase in pressure and power, positive reactivity insertion, and coolant temperature decrease.
The limiting transient which determines the required steady state MCPR limit is the turbine trip with failure of the turbine by pass. This transient yields the largest a MCPR. When added to the Safety Limit MCPR of 1.07 the required minimum operating limit MCPR of Specification 3.2.3 is obtained. Prior to the analysis of abnonnal o erational tran-sients an initial fuel bundle MCPR was determined. This carar.eter is based on the. bundle flow calculated by a GE multi-channel steady sjate flow districution medel as described in Secticn 4.a of itECO-20360' I and On core parameters snown in Reference 3, respense to Iters 2 and 9.
BRUNSWICK-UNIT 1 S 3/4 2-3 i l
l
_ _