|
---|
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
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
(y .
CAROLINA POWER & LIGHT COMPANY BRUtiSWICK STEAM ELECTRIC PLANT Utili 2 PROCEDURE TYPE: ALTERf4ATIVE SAFE SHUT 00Wrt PROCEDURE NUMBER: ASS 0-22 ,,
PROCEDURE TITLE: DIESEL GENERATOR BUILDING 50' ELEVATION E2 SWITCHGEAR ROOM Rev. O Ra,1 4/4/88
$ e#,1 9og%f ,gy[
f,pfp f d , m'd * '., ,* *
&*le#U},F s .,
t Approved By: f[ t [L.
General ~tEnaF/ an'agtT perations Date: j lih-[-
BS't P-2 / AS50-?? Page 1 of 11 Rev. 0 0011110100 001025 PDR ADOCK 05000324 p PDR
LIST OF EFFECTIVE PAGES ASS 0-22 Page(s) Revision 1-11 0
. _ . R B.1 f
s BSEP-2/ASSO 22 Page 2 of 11 Rev. 0
A. TITLE Diesel Generator Building 50' Elevat:on E2 Switchgear Room B. REF_ERENCES
>er 10CFRS0 Appendix 'R' Sections ll;.G & L.
1.
- 2. Per 10CFR60 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,
.A,,ED,
=~
- 2. The Shift Foreman has determined that u1e tor is to bc brought to Cold Shutdown using Altcrnative : Lie Shutdown Train A.
The purpose of this procedure is to providc supplemental actions to be_,
used concurrer,tly with E0Ps and other operations proceoires to acnieve and RB.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-site power.
D. OPERATOR ACTIONS
~~~~
- 1. IF while executing this procedure, the fire is extinguished AND ~~~
l tee Shift Foreman determines that no action within this procedure is required, THEN EXII this procedure.
- 2. OBSERVE the following parameters on instruments indicated whilJ performing actions to achieve and maint61n cold shutdown.
Instrument Location 2-CAC-TP 4426-1 Suppression Pool Temp. (Pt.1) Control Room Panel 2-CAC-LR-2602 Torus Level Control Room Panel 2-C32-PI-R605 keactor Pressure Contrcl Room Panel 2-C32-LI-R606A Reactor Water L,ve. Conte r i Room Panel
- 3. J_F. reactor building entry is required to restore OR, monitor equipment , JHEh
- a. DISPATCH the following minimum 'anpower for performance of this procedure:
Reactor Building - ; Auxiliary Operator l
's BSEP-2/ASSD-22 Page 3 of 11 Rev. 0
_ _ = _ _ _ _ _ _ . _ - _ _ _ _ _ . _ _ _ _ _ _ ________ _ _ _ ____ __ -__-___________ _ - _ _ - _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _
. r f?
t
- b. OBTAIN the following keys from the Shift Foreman's F Key Locker (1) ASSD Equipment Cabinet Key #148 f
,(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 ASSO TiiiIipment Cahinet: [
For Reactor Building .
_(1) Sound powered phone i (1) Flashlight ;
(1) Copy of this procedure ;
_ __ (3) Remote Shatdown Keys Serial T112 .
(1) Security Access Key (
(1) Twenty-five foot sound powered phone i extension cord. !
- d. USr. appropriate figures in this procedure to provfde f access / egress routes, equipment and communicatios. '
locations.
- 4. IF Nuclear Service Water to Vital Header Valve, 2-SW ' 117 !
UNN_0T be operated from the RTGB, THEN Manually OPERATE l
2-SW-V117. g g,t t
- 5. IF Nuclear Service Water Supply Valve, 2-SW-V105 CANNOT be f operated f rom the RTGB, ,T_ti,Eri Manually OPl' ATE 2-SIT-W63i.
- 6. IF Conventional-Nuclear Header Cross-tie Valve, 2-SW-V102 !
UNNOT be operated from the RTGB, THEN Manually OPERATE !
Y 5WV102. .l
- 7. IF operation of RHR Service Water System is required AND RHR f Wrvice Water Booster Pumps are NOT_ avaGable THEN RTFTR to ~
I OP-43. f
- 8. IF operation of HPCI Steam Supply Inboard Isolation Valve, -
l FE41-F002 is required AND power is NOT availabic from MCC 2XD, !
THEN :
- a. PLACE the cir;uit breaker control switch in the OFF l l position for HPCI Steam Supply Inboard Isolation ~ ;
h Valve, 2-E41-F002, at MCC 2XD compartment DW1. j l b. PLACE the circuit breaker control switch in the ON !
i position for HPCI Steam Supply Line Isolation VaWe, [
j 2-E41-F002 ( ASSD FEED) at MCC 2XC compartment 051. !
i i
I BSEP-2/ASSD-22 Page 4 of 11 Rev. O r
,e..-=_a_--.-~-,---_. ..-r---.-m . . . - . - , - - - - - - _-.-
v l
l
- c. IF 2-E41-F002 is required to be Open, THEN PLACE the
'ATSD Keylock Control Switch in the _0 PEN position, at -
MCC 2XC compartment DSI.
l
- d. IF 2-E41-F002 is required to be Closed, THEN PLACE We ASSD Keylock Control Switch in the CT03T ;
position, at MCC 2XC compartment DSI. ,
- 9. IF operation of HPCI Turbine Exhaust Vacuum Breaker Valve, :
T'E41-F079'is required _A!JD_ power is NOT available- from MCC 2XB. l THEN i
- a. PLACE the circuit breaker control switch in the OFF position for HPCI Turbine Exhaust Vacuum Breaker i Valve, 2-E41-F079, at MCC 2XB compartment DQ0. l
- b. PLACE the circuit breaker control switch in the ON !
position for HPCI TurM1e Exhaust Yacuum Breaker- [
Valve, 2-E41-F079, ( ASSD FEED) at MCC 2XC compartment i DT2.
t
- c. IF 2-E41-F079 is required'to be Open,_THEN PLACE the {
ATSD Keylock Control Switch. in the OPEN position, at c MCC 2XC compartment DT2. .
l
- d. IF 2-E41-F079 is required to be Closed, THEN PLACE We ASSD Keylock Control Switch in the CE65T i position, at MCC 2XC compartment DT2. i R B.L t
- 10. IF operation of Shutdown Coolin9 Outboard Suction Throttle !
Ya'Ive, 2-E11-F008 is required At4D power is NOT available from MCC 2XDB,_THEN
- a. VERIFY OFF OR PLACE the circuit breaker control t switch in tW 0FF position for Shutdown Cooling I Suction ThrottTe7alve, 2-E11-F008, at MCC 2XDB [
compartment B50.
- b. PLACE the circuit breaker control switch in the ON i position for RHR Suction Isolation Valve, 2-E11-T608, I
( ASSD FEED) at MCC 2XDA compartment B26. [
t
- c. IF 2-E11-F000 is required to be Open, THEN PLACE the -
~CTose/Off/Open Keylock Switch in the OTUi~ position, I at MCC 2XDA compartment B26. !
t
- d. IF 2-E11-F008 is required to be Closed, THEN PLACE :
We Close/Off/Open Keylock Switch in the'TGSE_ i position, at MCC 2XDA compartment B26.
l
- 11. WHEN Shift Foreman determines: l
, a. Power is available from MCC 2XD for operation of HPCI Steam Supply Inboard Isclation Valve, 2-E41-F002, THEN ,
BSEP-2/ASSD-22 Page 5 of 11 Rev. C
I
_ (1) PLACE the circuit breaker control switch I
in the ON position for HPCI Steam Supply InboarUsolation Valve, 2-E41-F002, at MCL 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. (ASSO FEED) at MCC 2XC compartment DSI.
/
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 DSI.
I w ~
y
- b. Power is available from MCC 2XB for operation 'of'HPCI Rg Turbine Exhaust Va< o . Breaker Valve, 2-E41-F079, THEN (1) PLACE the circuit breake control switch in the ON position for HPCI Turbine Exhaust Tacuum Breaker Valve, 2-E41-F079, at MCC 2XB compartment DQO.
/
Ind/Ver (2) PLACE the circuit breaker control switch in the OFF position for HPCI Turbine Vacuum TTiaker Valve, 2-E41-F079, ( ASSD FEED) at MCC 2XC compartment DT2.
/
Ind/Ver (3) PLACE the ASSD Keylock Control Switch in the OFF position for HPCI Turbine Exhaust Vacuum Breaker Valve, 2-E41-F079, at MCC 2XC c.orrpartment OT2. ;
/ !
Ind/Ver
\ .
BSEP-2/ASSD-22 Page 6 of 11 Rev. O t -.
- c. Power is available from MCC 2XDB for operation of Shutdown Cooling Outboard Suction Throttle Valve, 2-Ell-F008, THEN, (1) PLACE the circuit breaker control switch in the ON position for Shutdown Cooling !
OutboarTSuction Throttle Valve, i 2-E11-F008, at MCC 2XDB compartment BSO.
/
Ind/ Ver (2) PLACE the circuit breaker control switch in the OFF position for RHR Suction l Isolation Valve, 2-E11-F008, ( ASSD FEED) at MCC 2XDA compartment B26. r
/
Ind/ Ve r (3) PLACE the Close/Off/Open Keylock Switch in the_OFF position for RHR Suction Isolation Valve, 2-E11-F008, at MCC 2XDA compartment B26. ,.
g'
/ .
Ind/Ver I
- 12. WHEN:
- a. The fire has been extinguished AND ; ,
i -
- b. All breakers, AND/OR switches operateq in this procedure l are restored to their normal position AND ;
~
- c. No actions within this procedure are required to achieve f or maintain Cold Shutdown, THEN
- d. EXIT this procedure.
Date/ Time Completed Performed By (Print) Initials ;
L f
-- f i
Reviewed By- !
Shif t Foreman I
\
I BSEP-2/ASSD-22 page 7 of 11 Rey, o l f
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- FIGURE 3 Unit 2 Reactor Building 50' -0" Elevation Access / Egress l
BSEP-2/ ASS 0-22 Page 10 of 11 Rev. O i -
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LLA00ER 2-SW-Vll7 l EL, (A PPR OX) +2'- 0" 2 SW-VIIS EL. (APPROX)~2' 0" EL . 9'- 0" FIGURE 4 Unit 2 Reactor Building -17' -0" Elevation Access / Egress BSEP-2/ ASS 0-22 Page 11 of 11 Rev.0l
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