|
---|
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
. .
CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UNIT 2 PROCEDURE TYPE: ALTERNATIVE SAFE SHUT 00WN PROCEDURE NUMSER: AS50-14 .
PROCEDURE TITLE: DIESEL GENERATOR BUILD'NG 23' ELEVAT 01ESEL GENERATOR CELL 2 Rev. O
- A B:
l 4/4/88 Y
ONL .mh**48f
/ INF0uw.tt5tt.a dx t
umefitat ?#Jr%
FOR e mr Mete tit nd or fvh'sdJptet t
,A f
{ft. l r tras p %Li bi Nato o> u 4 4 c;erveor15.;IM
/ wi de l 1 ,
l l
Date: fff"!W Approved By: ~ General Riiiigli7Ranage he~ rations l
l Page 1 of 11 Rev. O BSEP-2/A550-14 8811110065 001025 i
PDR ADOCA ObOOO324
- D T0lal .--__-_ _ ___ - _ - -
LIST OF EFFECTIVE PAGES ASSD-14 Page(s)_ Revision 1-11 0 R S.:
l l
l Page 2 of 11 Rev. O l
BSEP-2/ASSD-14
l A. TITLE Diesel Generator Building 23' Elevation Diesci Generator Cell 2 l B. _RE FEREti_CES
- 1. Per 10 CFR 50 Appendix "R" Sections Ill.G & L.
- 2. Per 10 CFR 50 Appendix H"Section I!!.J.
l l C. Et4TRY CONDITION l
l inis procedure is entered frora 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 l The purpose of this procedure is to provide supplemental actions to be used concurrently with E0Ps and other operations procedures to achieve 7nd
, 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- R B.I l site power.
l D. OPERATOR ACT!0fiS
- 1. IF while executing this procedure, the fire is extinguished AND tKe Shif t Foreman determines that no action within this j procedure is required T_ HEN Exli this procedure.
l ~~
- 2. OBSERVE the following parameters on instruments indicated while l
performing actions to achieve and maintain cold shutdown.
Instrunent Location 2-CAC TR-4426-1 Suppression Pool Temp. (Pt.1) Control Room Panel 2-CAC-LR-2602 Torus Level Control Room Panel 2-C32-P!-R605 Reactor Pressure Control Room Panel 2-C32 L1-R606A Reactor Water Level Control Room Panel i 3. IF re ntor building entry is required to restore g monitor l equipraent THEN i a. DISPATCH the following minimum manpower for
! performance of this procedure:
Reactor Building - 1 Auxiliary Operator BSEP-2/ASSD-1A Page 3 of 11 Rev. O L
.V
_ b. OBTAIN the following keys from the Shift Foremm's Key Locker (1) ASSD Equipment Cabinet Key #148 (1) ASSD Flashlight Tool Box Key #160 j
_ c. OBTAIN Security Access Keys from SAS Security Officer f located in the Control Room ;
AND PROCURE the following equipment from the ASSO f liiuipmentCabinet i
_F_or Reactor _ Building
_(1) Flashlight Sound powerer' phone
~~~ ((1) 1) Twenty-five teot sound powered phone :
extension cord (1) Copy of this procedure (3) Remote Shutdown Keys Serial T112 ,
,_ _ (1) Security Access Key l L
- d. USE appropriate figures in this procedure to nrovide '
access / egress routes, equipment and comuntutJon I locations. -
- 4. IF Nuclear Service Water to Vital lleader Valve, 2-SW-V117 I U NNOT be operated from the RTGB, THEN Manually OPERAir !
M W V117. i I
S. IF ' Nuclear Service Water Supply Valve, 2-SW 1105 CANNOT be Werated from the RTGB, THEN Manually OPERATE 2-57-VfDT. l
- 6. IF Conventional-Nuclear Header Cross-tie Valve, 2 SW-V102 i UNNOT be operated from the PTGB, THEN Manually OPL3 ATE' I R W V102.
~
- 7. IF operation of RHR Service Water System is required AND RHR !
Te~rvice Water Booster Pumps are NOT_ available. THEN RUTR to i 0P-43. [
- 8. IF operation of HPCI Steam Supply Inboard Isolation Valve, f Y~E41-F002 is required AND power is NOT available from MCC 2XD, !
THEN l t
l '
- a. PLACE the circuit breaker control switch in the OFF ,
l position for HPCI Steam Supply Inboard Isolation {
Valve, 2-E41-F002, at MCC 2XD compartment DW1. l l t
- b. PLACE the circuit breaker control switch in the ON !
position for HPCI Steam Supply Line Isolation YaTve, }
2-E41-F002, ( ASSD FEED) at MCC 2XC compartment 051. !
j B5EP-2/ ASSD-14 Page 4 of 11 Rev. 0 [
I l
- i
+
__c. IF 2-E41-F002 is required to be Open THEN PLACE the MSD Keylock Control Switch in the OPEN
~
position, at MCC 2XC compartment DS1.
- d. IF 2-E41-F002 is requised to be Closed. THEN PLACE We ASSD Keylock Control Switch in the CT05T ~
position, at MCC 2XC compartment 051.
- 9. IF operation of HPCI Turbine Exhaust Vacuum Breaker Valvs.
TE41-F079 is required _AND_ power is NOT available from hCC 2XB,
.TH E N_
- a. PLACE the circuit breaker control switch in the OFF position for HPCI Turbine Exhaust Vacuum Breaker Valve, 2-E41-F079, et MCC 2XB compartment 9Q0.
~~
- b. PLACE the circuit breaker control switch in the ON position for HPCI Turbine Exhaust .Vacuur. Breaker 7alve, 2-E41-F079, ( ASSD FEED) at MCC 2XC compartment DT2.
- c. IF 2-E41-F079 is required to be Open. THEN PLACE the ESD Keylock Control Switch in the OPEW po'sition, at
~~
MCC 2XC compartment DT2. ,
- d. IF 2-E41-F079 is required to be Open, THEN PLACE'tSe E SD Keylock Control Switch in the CLOTE position, at MCC 2XC compartment DT2. A S ..
- 10. IF operation of Shutdown Cooling Outboard Suction Throttle Tilve, 2-E11-F008 is required AND power is NOT availabl,e f rom MCC 2XDB,_THEN
- a. VERIFY OFF OR PLACE the circuit breaker control switch in tTie OFF position for Shutdown Cooling Suction ThrottTe7alve, 2-E11-F008, at MCC 2XDB compartment B50.
- b. PLACE the circuit breaker control switch in the ON position for RHR Suction Isolation Valve, 2-E11-T608.
(ASSD FEED) at MCC 2XDA compartment B26.
- c. IF 2-E11-F008 is required to be Open. THEN PLACE We Close/Off/Open Keylock Switch in the OPEN position, at MCC 2XDA compartment B26.
I d. IF 2-E11-F008 is required to be Closed. THEN' PLACE We Close/Of f/Open Keylock Switch in the E5sE_
position, at WC 2X0A compartment B26. g
- 11. KN Shift Foreman determines:
- a. Power is available from MCC 2XD for operation of HPCI Steam Supply Inboard Isolation Valve, 2-E41-F002, THEN BSEP-2/ ASSD-14 Page 5 of 11 Rev. O
(1) PLACF. the circuit breaker control switch in the ON position for HPCI Steam Supply Inboard Tsolation valve. 2-E41-F002, at MCC 2XD compartment DW1.
/
Ind/ Ver (2) PLACE the circuit breaker control switch in the _OFF position for HPCI Steam Supply Line Inboard Isolation Valve. 2-E41-F002
( A550 FEED) at MCC 2XC compartment 051.
/
Ind/Ver (3) PLACE the ASSD Keylock Control Switch in the OFF position, for HPCI Steam Supply Line Isolation Valve. 2-E41-F002, at MCC 2XC compartment 051.
/
Ind/yer
- b. Power is available from MCC 2XB for operation of HPCI Turbine Exhaust vacuum Breaker valve 2-E41-F0797 THEN R d.
(1) PLACE the circuit breaker control switch in the ON position for HPCI Turbine Exhaust 7acuum Breaker valve 2-E41-F079, at MCC 2XB compartmerit DQO.
l
~~
l Ind/Ver (2) PLACE the circuit breaker control switch in the OFF position for HPCI Turbine Vacuum Trifaker Valve. 2-E41-F079. ( ASSD FEED) at MCC ?IC compartment DT2.
/
Ind/Ver j (3) PLACE the ASSD Keylock Control Switch in the OFF position for,HPCI Turbine Vacuum Breaker Valve. 2 E41-F079, at MCC 2XC compartment DT2.
4 Ind/Ver BSE P-2/ AS50- 14 Page 6 of 11 Rev. O
\
i
l
' ~
- c. Power is available from MCC 2XDB for operation of ,
Shutdown Cooling Outboard Suction Throttle Valve. [
- 2. Ell-F008,_THEN i
(
(1) PLACE the circuit breaker control switch i
[_ in the ON position- for Shutdown Cooling
, OutboarTsuction Throttle Valve,
- 2-E11-F008, at MCC 2XDB compartment 850. !
w j l Ind/ Ver (2) PLACE the circuit breaker control switch !
in the 0FF position for RHR Suction ;
e Isolation Valve, 2-E11.F008, ( ASSD FF.ED)
- at MCC 2XDA compartment 826. '
i -
l / !
Ind/Ver j l (3) PLACE the Close/Off/Open Keylock Switch in i l' the _OFF position for RHR Suction Isolation i Valve, 2-E11-F008, at MCC 2XDA compartment l B26. L l L
/ i Ind/Ver AS
- 12. WHEN:
! a. The fire has been extinguished AND !
l l b. All breakers. AND/0R switches operated in this i i procedure are restored to their normal position AND !
I
- c. No actions within this procedure are required to t achieve or maintain Cold Shutdown, THEN j L
- d. EXIT this procedure. I f'
Date/ Time Completed Performed By (Print)- Initials t
i l.
Reviewed By:
Shif t Foreman
(
BSEP-2/ ASSD-14 page 7 of 11 gey, g L
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- ~ ~ ACCtss/t0MEs$ f enCht JACK,inAIN A CR 8 FIGURE 1 Control Building 23'0" and 49'0" Elevations Access / Egress and Sound Powered Phone Comunications BSEP-2/ASSD-14 Page 8 of 11 Rey, O
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~ ~ ~ ~ ACCESS /EGMESS f PHONE JACK, TRAIM A OR 8 e /SQL AT! SWITCH FIGURE 2 Unit 2 Reactor Building 20' -0* Elevation Access / Egress and Sound Powered Phone ComJnic8tions BSEP-2/ ASS 0-14 Page 9 of 11 Rey, 0
s UNIT 2 REACTOR BUILDING --
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~ ~ ~ ACCESS /tentst a vnvts i FIGURE 3 Unit 2 Reactor Building 50' -0* Elevation Access / Egress BSE P-2/ AS50 14 Page 10 of 11 Rev. O t I
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UNIT 2 QEACTCM BUILOING !
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/ s CMYWELL
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ELEVATION 20'-0" Ra
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NLA00ER l 2-S W- V/17 2 SW Vitt l EL. (A PPR OX) + 2'- 0" EL. (AFPROX)-t' 0" EL. 9'- 0"_
l l F1GURE 4 U11t 2 Reactor Building -17' -0" Elevation Access / Egress BSEP-2/A550-14 Page 11 of 11 Rev. O l