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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] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20198K0411998-12-21021 December 1998 Rev 1 to Core Shroud Insp Plan Unit 2 B214R1 Outage Apr 1999 ML20238F6671998-08-28028 August 1998 Core Shroud Insp Plan Unit 2 B214R1 Outage Apr 1999 ML20237A5711998-07-16016 July 1998 Rev 10 to OENP-16.7, Administrative Control of Check Valve Disassembly Program ML20217H3061998-04-16016 April 1998 Rev 0 to ISI Program for Class 1,2 & 3 Components & Supports ML20197A9371998-02-25025 February 1998 Rev 4 to 0AP-025, Bnp Integrated Scheduling 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 ML20199A9291998-01-22022 January 1998 Core Shroud Insp Plan Unit 1 B112R1 Outage April 1998 ML20202D9151997-12-0202 December 1997 Rev 11 to 0AOP-34.0, Chlorine Emergencies ML20199J5711997-11-14014 November 1997 Rev 3 to 0AP-025, Bnp Integrated Scheduling 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 ML20196J5681997-07-17017 July 1997 1 to 2ASSD-05 Plant Operating Manual,Alternative Safe Shutdown Procedure Unit 2, Reactor Bldg North ML20148L7611997-06-12012 June 1997 Core Shroud Insp Plan Unit 2 B213R1 Outage,Sept 1997 ML20202D9331997-04-23023 April 1997 Rev 1 to 0FPP-038, Operation of SCBA Refill Sys ML20202D9371997-03-18018 March 1997 Rev 2 to Fire Protection Procedure OFPP-039, SCBA Use & Maint ML20115C6901996-06-30030 June 1996 Core Shroud Reinspection Plan for Unit 1 B111R1 Outage Oct 1996 ML20094E0861995-11-0202 November 1995 Core Shroud Reinspection Plan Unit 2 B2121R1 Outage for Feb 1996 ML20078P6731995-02-0909 February 1995 Core Shroud Reinsp Plan Unit 1 B110R1 Outage,Apr 1995 ML20079B0811994-12-14014 December 1994 Three-Yr Business Plan Performance Improvement Initiatives & Projects ML20073K8991994-10-0303 October 1994 Rev 47C to Plant Emergency Procedure (Pep) 0PEP-APPENDIX a, Emergency Response Resources ML20071P1491994-08-0202 August 1994 Three-Yr Business Plan Performance Improvement Initiatives & Projects ML20029E2471994-05-0404 May 1994 Three Yr Business Plan Performance Improvement Initiatives & Projects. ML20072M8571994-03-29029 March 1994 Rev 0 to Plan Mod 94-0077, Unit 2 Core Shroud Mod ML20217D4911993-07-30030 July 1993 Rev 0 to B-SP-93-06 Assessment Plan Outline, Program or Area:BNP-1 Startup & Power Ascension Readiness Assessment ML20045E0971993-05-16016 May 1993 Mod 91-038 to Field Rev 3 to Steam Leak Detection Sys Upgrade for Hpci,Rcic,Rwcu & RHR Procedure ML20044G6131993-05-11011 May 1993 Rev 5 to Design Guide DG-II.20, Design Guide for Civil/Structural Operability Reviews. ML20044C6191993-03-0101 March 1993 Rev 4 to Design Guide DG-II.20, Civil/Structural Operability Reviews. ML20116D2961992-08-31031 August 1992 Rev 2 to Nuclear Generation Group Manual 305-05, Prioritization Process ML20044G6141992-07-31031 July 1992 Rev 0 to 92C1737A, Recommended Operability Review Criteria for Piping Sys Subj to Level D Svc Loadings for Carolina Power & Light Nuclear Stations. ML20099G3101992-07-17017 July 1992 Rev 1 to Procedure WDP-002, Phase II Walkdown Procedure for Reactor Building Miscellaneous Steel & Drywell Platform Steel PM-91-038, Rev 0 to PM 91-038, Steam Leak Detection Sys Upgrade for Hpci,Rcic,Rwcu & Rhr1992-05-21021 May 1992 Rev 0 to PM 91-038, Steam Leak Detection Sys Upgrade for Hpci,Rcic,Rwcu & Rhr ML20056D6011991-11-19019 November 1991 Rev 2 to Performance Test Procedure 2-PT-24.6.4, SWS Hydraulic Performance Test for Bsep,Unit 2 ML20082H7521991-08-21021 August 1991 Rev 11 to ODCM ML20082H7501991-08-21021 August 1991 Rev 3 to Process Control Program ML20083A6541991-08-19019 August 1991 Rev 1 to Design Guide DG-VIII.50, Instrument Setpoints ML20056D6001991-01-25025 January 1991 Rev 1 to Performance Test Procedure 1-PT-24.6.4, SWS Hydraulic Performance Test for Bsep,Unit 1 ML20062C3931990-10-15015 October 1990 Rev 28 to Plant Emergency Procedure PEP-02.1, Initial Emergency Actions ML20062C3991990-10-11011 October 1990 Rev 5 to Plant Emergency Procedure PEP-02.6.10, Emergency Security Team Leader ML20081E7391990-04-20020 April 1990 Rev 6 to 25-2F, Operator Training Student Study Matl. Related Matl Encl ML20205S7011988-04-22022 April 1988 Rev 4 to Emergency Operating Procedure EOP-01-LEP-02, Alternate Control Rod Insertion:LEP-02 ML20205K9071988-04-13013 April 1988 Rev 0 to Alternative Safe Shutdown Procedure ASSD-00, User Guide ML20205S7661988-04-0808 April 1988 Rev 5 to Emergency Operating Procedure EOP-01-UG, Users Guide ML20205S6891988-04-0808 April 1988 Rev 4 to Emergency Operating Procedure EOP-01-EPP-2B, End Path Procedure 2B ML20205S6981988-04-0808 April 1988 Rev 4 to Emergency Operating Procedure EOP-01-LEP-01, Alternate Coolant Injection ML20205S7091988-04-0808 April 1988 Rev 3 to Emergency Operating Procedure EOP-01-LEP-03, Alternate Boron Injection ML20205S7721988-04-0808 April 1988 Rev 6 to Emergency Operating Procedure EOP-01-ACCP, ATWS - Containment Control Procedure ML20205S7441988-04-0808 April 1988 Rev 3 to Emergency Operating Procedure EOP-01-SRP-NSW, Nuclear Svc Water Sys Recovery ML20205S7991988-04-0808 April 1988 Rev 4 to Emergency Operating Procedure EOP-01-EPP-1M, End Path Procedure 1M 1998-08-28
[Table view] |
Text
F' h
CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UtilT 2 PROCEDURE TYPE: ALTERNATIVE SAFE SHUT 00Wii PROCEDURE NUMBER: ASS 0-18 ,,
PROCEDURE TITLE: DIESEL GENERATOR BUILDING 23' ELEVATION E6 SWITCHGEAR ROOM R B.1 Rev. 0 4/4/88 4 #
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- Approved By
- e ~1 Date: ), { {'_ _
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BSEP-2/AS$0-18 Page 2 of 12 Rev. O I
A. TITLE _
Diesel Generator Building 23' Elevation E6 Switchgear Room
- 8. REFERENCES _
- 1. Per 10 CFR 50 Append;x "P." Sections llt.G & L.
- 2. Per 10 CFR 50 Appendix "R" Section Ill.J.
C. ENTRY CONDITION This procedure is entered from Alternative Safe Shutdown Index ASSD-01.
- 1. A fire has occurred in an area containing Alternative Safe Shutdown Train B equipment, AND
- 2. The Shift Foreman has determined that the reactor is to be brought to Cold Shutdown using Alternative Safe Shutdown Train A.
l The purpose of this procedure is to provide supplemental actions to be used concurrently with E0Ps and other operations procedures to achieve 4nd l R B.I maintain Cold Shutdown coincident with or without a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> loss of off-l sita power.
D. OPERATOR ACT10fis
- 1. IF while executing this procedu're, the fire is extinguished AND tTieShiftForemandeterminesthhtnoactionwithinthis procedure is required, THEN EXIT this procedure.
- 2. OBSERVE the following parameters on instruments indicated while performing actions to achieve and maintain cold shutdown.
Location Instrument 1 2-CAC-TR-44:6-1 Suppression Pool Temp. (Pt.1) Control Room Panel Ccr.irol Room Panel 2-CAC.LR-2602 Torus Level Control Room Panci 2-C32 PI-R605 Reactor Pressure Control Room Panel 2-C32-L1-R606 A Reactor Water Level
- 3. IF reactor building entry is required to restore OR,R monitor equipment, THEf(
- a. DISPATCH the following minimum manpower for performance of this procedure:
Reactor Building - 1 Auxiliary Operator BSEP-2/ASSD-18 Page 3 of 12 Rev. O
- b. OBTAIN the following keys from the Shift Foreman's Key Locker
- /
(1) ASSD Equipment Cabinet Key #148 (1) ASSD Flashlight Tool Box Key #160
~ ~~
- c. OBTAIN Security Access Keys from SAS Security Officer located in the Control Room
- AND PROCURE the following equipment from the ASSD Tqiiipment Cabinet:
For Reactor Buildh
- 1) Sound powered phone
~((1) Flashlight (1) Copy of this procedure (3) Remote Shutdown Keys, Serial T112
_ (1) Security Access Key (1) Twenty-five foot sound powered phone extension cord
- d. USE appropriate figures in this procedure to provide access / egress routes, equipinent and comunication'"
locations.
3.
NOTE
! Implementation of ASSD-18 for Unit 1 l
will requjre Diesel Generator No. 4 to be crons-tied to 4KV Bus El via 1 4KV Bus EU. When 4KV Bus El and
. Substation E5 are re-energized by Unit 1, Suppression Pool Cooling and Shutdown Cooling for Unit 2 can then be established using Train A safe shutdown equipment.
- 4. IF Nuclear Service Water to Vital .eaoer Valve, 2-SW-V117 UNNOT be operated from the RTG8, THEN Manually OPERATE F5V-T117.
- 5. IF Nuclear Service Water Supply Valve, 2-SW-V105 CANNOT be operated from the RTGB, THEN Manually OPERATE 2-SVWfDT.
- 6. IF Conventional-Nuclear Header Cross-tie Valve, 2-SW-V102 UNNOT be operated from the RTGB, ~THEN Manually OPERATE F5W-7102. j
- 7. IF operation of RHR; Service Water System is required AND RHR Tervice Water Booster Pumps are jiOT, T available, THEN RUER to 09-43.
BSEP-2/ASSD-18 Page 4 of 12 Rev. O
e
- 8. IF operation of HPCI Steam Supply Inboard Isolation Valve, FE41-F002 is required AND power is NOT available from MCC 2XD, THEN
- a. PLACE the circuit breaker control switch in the OFF position for HPCI Steam Supply Inboard Isolation Valve, 2-E41 F002, at MCC 2XD compartment OW1.
- b. PLACE the circuit breaker control switch in the ON position for HPCI Steam Supply Line Isolation YaTve,
. E41-F002, (ASSO FEED) at MCC 2XC compartment 0S1,
- c. IF 2-E41-F002 is required to be Open, THEN PLACE the E SO Keylock Control Switch in che OPEN position, at MCC 2XC compartment 0S1.
- d. IF 2-E41-F002 is required to be Closed, THEN PLACE tiie ASSD Keylock Control Switch in the Cl05T position, at MCC 2XC compartment 051,
- 9. IF operation of HPCI Turbine Exhaust Vacuum Breaker Valve, FE41-F079, is required AND power is NOT available from MCC 2XB, THEN
- a. PLACE the circuit breaker' control switch in the OFF position for HPCI Turbine Exhaust Vacuum Breakir~
Valve, 2-E41-F079, at MCC !XB compartment 0Q0. R B.
- b. PLACE the circuit breaker control switch in the ON~
position for HPCI Turbine Exhaust Vacuum Breaker Valve, 2-E41-F079, ( ASSO FEED) at MCC 2XC compartment DT2.
j
- c. IF 2-E41-F079 is required to be Open, THEN PLACE the ESO Keylock Control Switch in the OPEN position, at MCC 2XC compartment OT2.
- d. IF 2-E41-F079 is required to be Open, THEN PLACE the I!iSD Keylock Control Switch ir, the CLOIf position, at MCC 2XC compartmcnt OT2.
- 10. IF operation of Shutdown Cooling Outboard Suction Throttle Vilve 2-E11-F008 is required AND power is NOT_ available from HCC 2X08, THEN
- a. VERIFY OFF OR PLACE the circuit breaker control -
switch in tFi 0FF position for Shutdown Cooling Suction ThrottTe Valve, 2-E11-F008, at MCC 2XDB compartment 850.
- b. PLACE the cire.utt breaker control switch in the ON position for RHR Suction Isolation Valve, 2-E11-TUO8, (ASSO FEED) at MCC 2XDA compartment C?'.
BSEP-2/ ASS 0-18 Page 5 of 12 Rev. O
/l
- c. IF 2-E11-F008 is required to be Open, THEN PLACE Tfie Close/Off/Open Keylock Switch in tiie UPEN position, at PCC 2XOA compartment B26.
- d. IF 2-E11-F008 is required to be Closed, ~THEN PLACE tfie Close/Off/Open Keylock Switch in theTESE position, at MCC 2XDA compartment 826.
- 11. WHEN Shift Foreman determines:
- a. Power is available from MCC 2XD for operation of HPCI Steam Supply Inboard Isolation Valve, 2-E41-F002 THEN (1) PLACE the circuit breaker control switch in the ON position for HPCI Steam Supply Inboar(Tsolation Valve, 2-E41-F002, at MCC 2XD compartment INi.
/
Ind/Ver
~(2) PLACE the circuit breaker control switch
!s in the _OFF position for HPCI Steam Supply I Line Inboard Isolation Valve, 2-E41-F002, (ASSD FEED) at MCC 2XC compartment 051.
RBl
/
Ind/Ver (3) PLACE the ASSO Keylock Control Switch in the 0FF position, for HPCI Steam Supply Line Isolation Valve, 2-E41-F002, at MCC 2XC compartment 051.
/ ~
Ind/Ver
~
- b. Power is available from MCC 2XB for operation of HPCI Turbine Exhaust Vacuum Breaker Valve, 2-E41-F079, THEN (1) PLACE the circuit breaker control switch in the ON position for HPCI Turbine Exhatist'acuum Breaker Valve, 2-E41-F079, at MCC 2 i compartment DQO.
/
Ind/Ver BSEP-2/ ASS 0-18 Page 6 of 12 Rev. O
(2l- PLACE the circuit breaker control switch in the OFF position for HPCI Turbine Vacuum Tr'Eaker Valve, 2-E41. F079, (ASSO FEEO) at MCC 2XC comi.irtment DT2.
/
Ind/Ver (3) PLACE the ASSD Keylock Control Switch in l the OFF position for HPCI brbine Vacuum Breaker Valve, 2-E41-F079, at MCC 2XC (
coepartment DT2. ,
l
/ t Ind/Ver .
- c. Power is available from MCC 2XDB for operation of I Shutdown Cooling Outboard Suction Throttle Valve, !
2-E11-F008, THEN j (1) PLACE the circuit breaker control switch !
in the ON position for Shutdown Cooling OutboarTSuction Throttle Valve, l 2-E11-F008, at.MCC 2XDB compartment B50. ;
~~
/
Ind/Ver i (2) PLACE the circuit breaker control switch R.S.1 in the OFF position for RHR Suction
- Isolation Valve 2-E11-F008,(ASSDFEEDl r at MCC 2XOA cc etment B26.
/ .
Ind/Ver .
~ (3) PLACE the Close/Off/Open Keylock Switch in ;
the OFF position for RHR Suction Isolation !
Valve, 2-E11-F008, at MCC 2XDA compartment i B26, i
/ [
Ind/Ver !
i t
i i i l l
BSEP-2/ ASS 0-18 Page 7 of 12 Rev. O
- 12. WHEN:
- a. Tiit fire has been extinguished AND b, All breakers, AND/OR switches operated in this procedure are restored to their normal position AND
- c. No actions within this procedure are required to achieve or maintain Cold Shutdown, THEN
- d. EXIT this procedure.
Date/ Time Completed Performed By (Print) Initials Reviewed By:
Shift Foreman K B.L BSEP-2/ASSD-18 Page 8 of 12 Rev. O
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FIGURE 4 Unit 2 Reactor Building -17' -0" Elevation Access / Egress BSEP-2/ ASS 0-18 Page 12 of 12 Rev. O o -