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| It I 3. A dedicated qualified person will be assigned to initiate the service | | It I 3. A dedicated qualified person will be assigned to initiate the service |
| !, water conventional header should any of the following occur: | | !, water conventional header should any of the following occur: |
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| {{ a. Any event occurs which requires ECCS actuation. | | {{ a. Any event occurs which requires ECCS actuation. |
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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
{{#Wiki_filter:..
PLANT SYSTEMS SERVICE WATER SYSTEM
, LIMITING CONDITION FOR OPER', TION 3.7.1.2 The service water system nuclear header shall be OPERABLE with at least three OPERABLE service water pumps.
APPLICA3ILITY: CONDITIONS 1, 2, 3, 4 and 5.
ACTION:
- a. In CONDITION 1, 2, or 3:
- 1. With only two service water pumps OPEPJSLE, restore at least three pumps to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN
. within the following 24 hours. p*
- 2. With only one service water pump OPERABLE, restore at least two pumps to OPERGLE status within 72 hours and restore at least three pu=ps to OPERGLE status within 7 days from the time of the initial loss or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.
- b. In Condition 4 or 5:
- 1. With only one service water pump OPERABLE, restore at least two service water pumps to OPERABLE status within 14 days or declare the Core Spray System, the LPCI System, and the diesel generators inoperable and take the ACTION required by Specifications 3.5.3.1, 3.5.3.2, and 3.8.1.2.
- 2. With the Service Water System nuclear header inoperable, maintain the Unit No.2 Service Water nuclear header OPERABLE with at least three Unit No . 2 Service water pumps OPERABLE and restore the Service Water System nuclear header to OPERABLE status within 14 days or declare the diesel generators inoperable and take the ACTION required by Specification 3.8.1.2.
- 3. With the Service Water System nuclear header inoperabl(,
maintain the Service Water System conventional header OPERABLE with at least two service water pumps OPERABLE and restore the Service Water System nuclear header to OPERABLE status within 14 days or declare the Core Spray System and LPCI Syst2= inoperable and take the- ACTION required by Specif1 ations 3.5.3.1 and 3.5.3.2 er comS y with the re wirements of Special Test Exceptior 3.In.6 BRU"5'. ICE-UNIT 1 3/4 7-2 8103160464
FLANT SYSTEMS 1
SUR'/EILLA.'!CE P.EOUIREMENTS (continued) 4 . 7.1. 2 The service water system shall be denenstrated OPERABLE:
- a. At least once per 31 days by verifying that each valve (manual.,
power operated or automatic) servicing safety related equip-ment that is not locked, sealed, or otherwise secured in position, is in its correct position.
- b. At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on the appropriate ECCS actuation test signals. -
BRUNSk'ICK - UNIT 1 3/4 7-2a P00RORIG"NAL
Il
'I5TETIAL _ JEST EXCEFTIONS 3 b 106 PIANT SERVICE WATER
' LIMITING CONDITION FOR OPERATION 3.10.6 The provisions of Specification 3.7.1.2b3 may be suspended to permit isolating and draining the service water nuclear header for maintenance provided that:
'l. The service water conventional header is lined up to supply cooling water
!, to the required ECCS loads.
[; 2. The draining / maintenance on the service water nuclear header will not affect the service water conventional system or lineup described in 1 above.
It I 3. A dedicated qualified person will be assigned to initiate the service
!, water conventional header should any of the following occur:
{{ a. Any event occurs which requires ECCS actuation.
ii
-b. Primary coolant temperature exceeds 180 0F.
\ ;.
!l SURVEILLANCE REQUIREMENTS l
i:
, 4.10.6.1 Prior to removing the service water nuclear header from service, verify that the service water conventional header is lined up to l supply cooling water for ECCS by verifying that each valve servicing l safety related equipment that is not locked is administratively
-; controlled in its proper position.
i h 4.10.6.2 Every four hours, verify that the primary coolant temperature is f 180 F.
BRUNSWICK UNIT 1 3/4 10-S
- L ANT SYSTEMS SIR'! ICE W'TER SYSTEM j.:vdTING CONDITION FOR OPEDATION 3.7.1.2 The service water system nuclear header shall be OPEPASLE with at least three OPERABLE service water pumps.
A.::LIC AB ILITY : CONDITIONS 1, 2, 3, 4 and 5.
ACTION:
- a. In CONDITION 1, 2, or 3:
- 1. With only two service water pumos OPEFABLE, restore at least three pu=ps to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SH'JTDOWN
.' within the following 24 hours. p
- 2. With only one service water pump OPERABLE, restore at least two pumps to OPERABLE status within 72 hours and restore at least three pu=ps to OPERABLE status within 7 days from the time of the initial loss or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.
- b. In Condition 4 or 5:
- 1. With only one service water pump OPERABLE, restore at least two service water pumps to OPERABLE status within 14 da: s or declare the Core Spray System, the LPCI System, and the diesel ;;enera!. ors inoperable and take the ACTION required by Specifications 3.5.3.1, 3.5.3.2, and 3.8.1.2.
l l 2. With the Service Water Syste= nuclear header inoperable, saintain the Unit No. 1 Service Water nuclear header l
OPERABLE wid at least three Unit No. 1 Service water pumps OPE..AB.E and restore tne Service Water Syst em nuclear '.c ader to JPERABLE status within 14 day., or declare the d'.esel pnerators inoperable and take the ACTION l re:;ui . ed y 3pec ificat ion 3. 3.1. 2.
l 3. With the service Water Syste nuclear header ineperable,
- maintain the Service Water Syste
- conventional header l OPERABLE with at least two service water purps OPEPABLE and restore the Service Water Systet nuclear header to OPERABLE status within 14 days or declare the Core Stray System and LPCI System inoperable and take S AC~i%
required by Specifications 3.5.3.1 and 3.5.:.2 or .o :ly with the requirements of Special Test Except ion 3.10. 5.
BRUNSWICK-UNIT 2 -2
PLW SYS dis JUR'/E!LLA.':CE REOUTREMENTS (continued) 4 . 7.1. 2 Tne service water system shall be demonstrated OPERABLE:
- a. At least once per 31 days by verifying that each valve (manual, power cperated or automatic) se-vicing safety related equip-ment that is not locked, sealed, or otherwise secured in position, is in its correct position,
- b. At least once per 18 months during shutdown, by verifying that each auto:r.atic valve servicing safety related equipment actuates to its corre:: position on the approp-iate ECOS actuation test sigr.als.
BRUNSWICK - UNIT 2 3/4 7-2a ,,
2 ;<+
P00R ORIGNAL
4 SPECIAL TEST EXCEPTIONS 3/; 10.5 PLANT SERVICE WATER LIMITING CONDITION FOR OPERATION 3.10.5 The provisions of Specification 3.7.1.2b3 may be suspended to per=it isolating and draining the service water nuclear header for maintenance provided that:
- 1. The service water conventional header is lined up to supply cooling water to the required ECCS loads.
- 2. The draining /caintenance on the service water nuclear header will not affect the service water conventional system or lineup described in 1 above.
- 3. A dedicated qualified person will be assigned to initiate the service water conventional header should any of the following occur:
- a. Any event occurs which requires ECCS actuation.
- b. Primary coolant te=perature exceeds 180 F.
SURVEILLANCE REQUIREMENTS 4.10.5.1 Prior to removing the service water nuclear header from service, verify that the service water conventional header is lined up to supply cooling water for ECCS by verifying that each valve servicing safety related equipment that is not locked is administrative 1y controlled in its proper position.
4.10.5.2 Every four hours, verify that the primary coolant temperature is n 180 F.
BRUNSWILE UNIT 2 3/4 10-3
.}}