|
---|
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
.___- _-__ _ ______-___ _ _________- _ - - _ _ - _ _____ ___ -__
., t t
l I
CAROLINA POWER & LibHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT i UNIT 1 I
PROCEDURE TYPE: ALTERNATIVE SAFE SHUTOOWN PROCEDURE NUMBER: ASSD-31
, PROCEDURE TITLE: UNIT 2 REACTOR BUILDlhG SOUTH i
Rev. O ;
i 4/5/88 g a,g
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Approved By: L. te2 Cate: '/fttI #
GeneralManager.Kanagirf0perations f I
l Rev. 0 BSEP 1/ ASS 0 31 Page 1 of 11 0811110131 001025' DR ADOCK 0500 4
Lisi Of EFFECTIVE PAGES AS50-31, USM . Revision 1-11 0 i
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BSEP-1/ASSD-31 Page 2 of 11 Rev. O L
A. T l_TL E_
Unit 2 Reactor Building South B. REFERENCES
- 1. Per 10CFR50 Appendix 'R' Sections Ill.G & L.
- 2. Per 10CFR50 Appendix 'R' Section Ill.J.
C. ENTRY CONDITION This procedure is entered from Alternative Safe Shutdown Index A550-01.
- 1. A fire has occurred in an area centaining 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.
The purpose of this procedure is to provide supplemental actions to be used concurrently with E0Ps and other operations procedures to achiev,e and 80.1 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 of 6 site power.
D. OPERATORACT!_03 IF while executing this procedure, the fire is extinguished AND l ~~ ll 1. Shift Foreman determines that no action within this Ec procedure is required,,THR Exli this procedure.
I 2. OBSERVE the following parameters on instruments indicated while l performing actions to achieve and maintain cold shutdown.
Instronent Location 1-CAC-TR-4426-1 Suppression Pool Temp. (Pt.1) Control Room Panci l 1-CAC-LR-2602 Torus Level Control Room Panel 1-C32-P!-R605 A Reactor Pressure Control Roor Panel 1-C32-L1-R606A Reactor Water Level Control Room Panel
- 3. IF reactor building entry is required to restore OR monitor
~
Ruipment,3E_N,
- 4. DISPATCH the following minimum :nanpower for performance of this procedure:
Reactor Building - 1 Auxiliary Operator v
BSEP-1/AS50-31 Page 3 of 11 Rev. 0 l
t
- b. 0BTAIN the following keys from the Shift Foreman's Key r t.ocker i l
' (1) ASSU Equipment Cabinet Key f148 !
(1) ASSD Flashlight Teol Box Key #160 l
- c. OBTAIN Security Access Keys from SAS Security Officer .
located in the Control Room AND PROCURE the following equipment' from the ASSD !
E51pmentCabinet, i i
^
For Reactor _ Building l
_ (1) Sound powered phone ;
(1) Flashlight !
(1) Copy of this procedure !
1 -(3) Remote Shutdown Keys Serial T112 !
(1) Security Access Key '
Twenty-five foot sound powered phone (1) !
i extension cord. [
- d. USE appropriate figures in this procedure to provide !
l access / egress routes, equipment and connunication j locations. .- !
e
' 4 ,lF, F Nuclear Service Water to Vital Header Valve,1-SW-Y117 CANN0_T_
be operated f rom the RTGB, THEN_ Manually OPERATE 1-SW-V117.
M B.2 >
- ; 5. IF Nuclear Service Water Supply Valve,1-SW V105 CANNOT be i Serated f rom the RTGB, THEN_ Manually OPERATE 1-SW-VIDT. l l
- 6. IF Conventional-Nuclear Header Cross-tie Valve.1-SW-V102 CANNOT [
Fi operated from the RTGB, THEN_ Manuall) OPERATE 1-SW-V102. l l
~ 7. IF operation of RHR Service Water Systest is required AND RHR I Tirvice Water Booster Pumps are NOT available. THEN RUTR to ,
OP-43. [
l
! 8. IF operation of HPCI Steam Supply Inboerd Isolation Yalve, !
R41-F002 is reqJired g power is NOT available f rom HCC 1X0,
~
i
, THEN l t
Pt ACE the circuit breaker control in the OFF position a.
. for HPCI Steam Supply Inboard Isolation Vilve,1-E41-l F002, at MCC IXD compartment DW1.
a t
j . b. PLACE the circuit breaker control switch in the ON j
position for HPCI Sten Supply 1.ine inboard Isolation j Valve, 1-E41-F002 (ASSO FEED) at MCC 1XC compartment
' 051.
}
i BSEP-1/ ASS 0-31 Page 4 of 11 Rev. O
]
i
- c. IF 1-E41-F002 is required to be Open, THEN PL ACE the
'ATSO Keylock Control Switch in the ole,f!, position, at MCC 1XC compartment DSI.
- d. IF 1-E41-F002 is required to be Closed. THEN PLACE XTSO Keylock Control Twitch in the CLOSE position, at MCC 1XC compartment DSI.
- 9. IF operation of HPCI Turbine Exhaust Vacuum Breaker Valve, R41-F079, is required M0_ power is NOT_ available from MCC 1XB, IMEN,
- a. Pt. ACE the circuit breaker control switch on the OFF position for HPCI Turbine Exhaust Vacuum Breaker Valve,1-E41-F079, at MCC IVB compartment DQ0.
- b. PLACE the circuit control switch in the ON position for HPCI Turbine Vacuum Breakor Yalve, l'T41-F079 (ASSD FEED) at MCC 1XC compartment DT2.
- c. IF 1-E41-F079 is required to be Open, THEN PLACE the ATSO Keylock Control Switch in the OPEN position, at MCC IXC compartment DT2.
- d. IF 1-E41-F079 is required to be Closed, THEN PL ACE-the X! ISO Keylock Control Switch in the CLOSE W ition, at MCC 1XC compartment OT2. AO1 i
- 10. IF operation of Shutdown Cooling Outboard Suction isolation i Valve,1-E11-F003 is required AND power is NOT available f rom 1 MCC 1XDB, THEN
- a. VERIFY OFF OR PLACE the circuit breaker control switch l in the 0TT polition for Shutdown Cooling Outboard l Suction Isolation Yalve,1-E11 F008, at l MCC IXOB compartment DSO.
- b. PLACE the circuit breaker control switch in the ON position for RHR Suction isolation Valve,1-E11-Tif08, (ASSO FEED) at MCC IXOA compartment B26
- c. IF 1-E11-F003 is required to be Open, THEN PLACE the tTose/Off/0 pen Keylock Switch in the OFOT~ position, at -
MCC 1XDA compartment 826
- d. IF 1-E11-F008 is required to be Closed THEN PLACE ITose/off/open Keylock Switch in the CLOUosition, at MCC 110A compartment B26
- 11. WHEN_ Shif t Foreman determines:
- a. Power is available from MCC 1XD for operation of HPC1
. Steam Supply Inboard Isolation Valve,1-E41-F002, THEN BSEP-1/AS50-31 Page 5 of 11 Rev. 0
_ (1) PLACE the circuit brettse control switch in the ON position for HPCI Steam Supply Inboard 7 solation Valve,1-E41-F002, at NCC IXD compartment DW1.
/
Tnd7fer
_ (2) PLACE tha circuit breaker control switch in the OFF position for HPCI Steam Supply Line Isl5Ta'tlon Yalve,1-E41-f 002, ( ASSO l FEED) at MCC 1XC compartment DSI.
/
Triher
_ (3) PLACE the ASSD Keylock Control Switch in ;
the OFF position, for HPCI Steam Supply LineTolation Valve,1-E41-F002, at MCC IXC compartment DSI. !
/
IndfVer t
- t. Power is available f on MCC IXB for operation of-4%CI Turbine Exhaust Yacuum Breaker Valve,1-E41-F079, _THEN ,
PLACE the circuit breaker control switch RB'
~ (1) in the ON position for HPCI Turaine -
Exhaust 7acuun Breaker Valve,1-E41-F079, at MCC IXB conpartment 000 ,
/ .
TndWer l (2) PLACE the circuit breaker control switch in the OFF_ position for HPCI Turbine Vacuun Breaker Valve,1-E41-F079, { ASSO -
FEED) at MCC IXC compartment DT2.
/
l Ind/ver (3) PLACE the ASSD Keylock Control Switch in t the OFF position for HPCI Turbine Vacuum Breaker Valve, 1 E41 F079, at MCC 1XC (,
compartment DT2.
/
Tnfl7er i I
- c. Power is available from HCC 1XDB for operation of l Shutdown Cooling Outboard Suction Isolation Valve, '
, 1-E11-F008 THEN 1 l L l BSEP-1/ASSD-31 Page '3 of 11 Rev. O {
(1) PLACE the circuit breaker control switch in the ON pos'tlon for Shutdown Cooling OutboarTsuction isolation Valve, 1-E11-F003, at MCC IXD6 compartment B50
. .l .. _
~ ~ (2) PLACE the circuit breaker control switch in the OFF position for RHR Suction isolation Valve,1-E11-F008, ( ASSD FEED) at MCC IXDA compartment B26
/ ~
Ed7Ver
~
(3) PLACE the Close/Off/Open Keylock Switch in the OFF position for RHR Suction Isolation Yalve, 1-E11-F008, at MCC 1XDA compartment B26
/
TiTdfiei
- 12. WHEN: ., g g,;
___a. The 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, ,T_ HEN
! d. EK!T this procedure.
Date/ Tine Completed ~~
Performed By (Print)~~ Initia C 1
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Reviewed By:
ThTf t Toreman BSEP-1/ASSO 31 Page 7 of il Rev. 0
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FIGUR( 2 Unit 1 Reactor Building 20'-0" Clevation - Access / Egress and Sound Powered Phone Comunications RSEP-1/A550 31 Page 9 of 11 Rev. O
UNIT 1 REACTOR BUILDING
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(ElFM 45 0")% *D \ j s l. Ell-7068A gf (ELEV. $$;0")
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LEGEND
~ ~ ~ ACCESS / EGRESS E VALVES FIGURE 3 Unit 1 Reactor Building 50'-0" Elevation - Access / Egress BSEP-1/A550-31 Page 10 of 11 Rev. 0
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-I(19!L9, FIGURE 4 Unit 1 Reactor Building 17 *,0. Elevation . Access / Egress BSiP-1/A$50-31 E89e 11 of 11 Rev. 0 1