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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 -
1 CAROLINA POWER & LIGHT COMPANY i
BRUNSWICK STE AM ELECTRIC PLANT UNIT 2 PROCEDURE TYPE: ALTERNATIVE SAFE SHUT 00WN PROCEDURE NJiBER: ASSD.21 PROCEDURE TITLE: DIESEL GENER ATOR BUILDING S0' ELEVATION El SWITCHGEAR ROOM g g Rev. 0 2/25/83 b s/{ s *
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i Approved By:
UT Cate: d' / I
~Genersl Marager/Managgr-Operations I
95EP-2/ASSD-21 Page 1 of 12 Rev. O r l
0011110097 081025 l PDR ADOCK 05000324 P PIXt ;
, :a , e LIST OF EFFECTIVE PAGES ASSD-21 Page(g Revistan 1-12 0 P
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(
i SSEP-2/ASSD-21 Page 2 of 12 Rev. O is . . _ _ _
\
A. TITLE _
Unit 1 Reactor Building North B. REFERENCES
- 1. Per 10CFR50 Appendix 'R' Sections lil.G & L.
,, 2 . Per 10CFR50 Appendix 'R' Section Ill.J.
C. ENTRY CONDITION This procedure is entered from Alternative Safe Shutdown Index AS00-01.
- 1. A fire has occurred in an area containing Alternative Safe Shutdown Train A equipment, AND
~~~~-~
- 2. The Shift Foreman has determined that the reactor is to be broughc to Cold Shutdown u',ing Alternative Safe Shutdown Train 8.
The purpose of this procedure is to provide supplemental actions to be used concurrently with E0P's and other operations' procedures to achieve R B.I and mainta n 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--
i off-site power.
O. OPERATOR ACTIONS
- 1. IF while executing this procedure, the fire is axtinguished AND tne "'ift Foreman determines that no action within this procec e is required, THEN EXIT this procedure.
- 2. OBSERVE the fcilowing parameters on instruments indicated while performing actions to achieve and maintain cold shutdown.
location
,lnstrument 2-CAC-TR-778 Suppression Pool Water Temperature Remote Shutdown Panel Remote Snutdown Panel 2-CAC-LI-3342 Torus Level Remote Shutdown Panel 2-CAC-PI-3332 Reactor Pressure Remote Shutdown Panel 2-821-LI-R604BX Reactor Water Level
- 3. IF reactor building entry is required to restore OR monitor
~
equ pment, THEN
- a. DISPATCH the following minimum manpower for performance of this procedure:
Reactor Building - 2 Auxiliary Operators PGge 3 of 12 Rev. 0 BSEP-2/ ASS 0-21 s
- e;, x
'fi y .
- b. OBTAIN the following keys from the SOS Key Locker
^
(1) ASSD Equipment Cabinet Key #148
- (1) ASSO Flashlight Tool Box Key (160 AND PROCURE the following equipment from the ASSO WipmentCabinet:
For Reactor Building (2) Sound powered phones (2) Flashlights
~~~
(2) Copies of this procedure M- '
- 4) Remote Shutduwn Keys, Serial T112
~ ((2) Security Access Keys '
(2) Twenty-five foot sound powered phone extension cords
,~ c. USE appropriate figures in this procedure to provide access / egress routes, equipment and communication ,
locations. (Normal communications may not be '
E available.) ,
- 4. PLACE Reactor Water Level "NORMAL / LOCAL" switch, 2-821-C5-3345 at the Remote Shutdown Panel, to the "L'0 CAL" position to make --
level indicator 2-821-L1-R604BX operable. R B.\
. 5. IF RBCCW Heat Exchangers Service Water Inlet Valve, 2-SW-V106 UNNOT be operated from the RTGB, THEN Manually OPERATE 2-5W-V106.
- 6. IF Vital Heaoer Cross-tle Valve, 2-SW-V118 CANNOT be operated i
TTom the RTGB, THEN Manually 0PERATE 2-SW-V118.
- 7. IF operation of RHR Service Water System is required AND RHR Te~rvice Water Booster Pumps are NOT available, THEN RIER to ,
OP-43.
- 8. IF operation of RCIC Steam Supply Inboard Isolation Valve, 7"E51-f 007 is reouired AND poder is NOT available from MCC 2XC, ,
THEN ,
- a. PLACE the circuit breaker control switch in the 0FF position for RCIC Steam Supply Inboard Isolation ,
Valve, 2-E51-F007, at MCC 2XC compartment 054 !
- b. PLACE the circuit breaker control switch in the ON position for RCIC Steam Supply Line inboard Isolation I Valve, 2-E51-F007, (ASSD FEED) at MCC 2XD compartmant -
DY1. j 4
- c. IF 2-E51-F007 is required to be Open, THEN PLACE the ;
ESD Keylock Control Switch in the OPEN position, at ;
MCC 2XD compartment DYl. ,
r BSEP-2/ASSO 21 Page 4 of 12 Rev. O i
-. _a., , - . _ _ _ . - - , _ _ _ _ _ . _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ . _ . , _ _ _ _ , - __ , _ _ _ _ _ _ , _ , _ . _ _ . _ _ . _ _ _ _ _ _ . _ _ , _ , _
e
- d. IF 2-E51-F007 is required to be Closed, THEN PLACE the E SO Keylock Control Switch in the CLOSE position, at MCC 2XD compartment OY1.
- 9. IF operation of RCIC Turbine Exhaust Vacuum Breaker Valve, M51-F062, is required AND power is NOT available from MCC 2XA, THEN
- a. PLACE the circuit breaker control switch in the OFF position for RCIC Turbine Exhaust Vacur..n Breaker Valve, 2-E51-F062, at NCC 2XA compartment DE4.
- b. PLACE the circuit breaker control switch in the ON position for RCIC Turbine Vacuum Breaker Valve, R51-F062, (AS50 FEED) at MCC 2X0 compartment OW2.
- c. IF 2-E51-F062 is required to be Open, THEN PLACE the USD Keylock Control Switch in the OPETWsition, at MCC 2X0 compartment OW2.
- d. IF 2-E51-F062 is required to be Closed, THEN PLACE the ESO Keylock Control Switch in the CLOSE position, at MCC 2X0 compartment DW2.
RS.i
- 10. IF operation of RHR Suction Isolation V'a'Ive, 2-E11-F009 is *'
Te' quired AND power is NOT available from MCC 2XA, THEN
- a. VERIFY OFF OR PLACE the circuit breaker control switch in the '0FT Wsition for RHR Shutdown Cooling Suction Isolation Valve, 2-E11-F009, at MCC 2XA compartment OH3.
- b. PLACE the circuit breaker control switch in the ON position for RHR Suction Isolation Valve, 2-E11-T609, l (AS50 FEED) at MCC 2X0 compartment OX5.
- c. IF 2-E11-F009 is required to be Open, THEN PLACE the Rose /0ff/0 pen ASSD Feed Keylock Switen in the OPEN l- position, at MCC 2X0 compartment DX5.
- d. IF 2-E11-F009 is required to be Closed, THEN PLACE the Uose/0ff/Open ASSO Feed Keylock Switch in the CLOSE c
position, at MCC 2X0 compartment OX5.
- 11. WHEN Shif t Foreman determines:
- a. Power if, available from MCC 2XC for operation of RCIC Steam Supply Inboard Isolation Valve, 2-E51-F007, 3Ej BSEP-2/ ASS 0-21 Page 5 of 12 Rev. O
~ (1) PLACE the circuit breaker c .01 switch in the ON position for RCIC S Supply InboaFd Isolation Valve, 2-t-4-F007, at MCC 2XC compartment 054.
/
Ind/Ver (2) PLACE the circuit breaker control switch in the OFF position for RCIC Steam Supply line Isolation Valve, 2 's1-F007, ( ASSO FEED) at MCC ?X0 compartment DY1.
/
Ind/Ver (3) PLACE the ASSO Keylock Control Switch in th 9FF position, for RCIC Steam Supply Li Tsolation Valve, E51-F007, at MCC 2XD compartment DY1.
/
Ind/Ver RB.I
- b. Power is available from MCC 2XA for operation of RCIC Turbine Exhaust Vacuum Breaker Valve, 2-E51-F062, TREN (1) PLACE the circuit breaker control Switch in the ON position for RCIC Turbine Exhaust Vacuum Breaker Valve, 2-E51-F062, at MCC 2XA compartment DE4
/
inU/Ver (2) PLACE the circuit breaker control switch in the 0FF position for RCIC Turbine Vacuum Breaker Valve, 2-E51-F062, (ASSO FEED) at MCC 2XD compartment DW2.
/
Ind/Ver (3) PLACE the ASSO keylock Control Switen in the OFF position for RCIC Turbine Vacuum Breaker Valve, 2-E51-F062, at MCC 2XD conpartment DW2.
/
Ind/Ver BSE P-2/ ASS 0-21 Page 6 of 12 Rev. O
- c. Power is available from MCC 2XA for operation of RHR Suction Isolation Valve, 2-E11-F009, THEN (1) PLACE the circuit breaker control switch in the ON position for RHR Suction Isolation ValvIe7 2-Ell-F009, at MCC 2XA compartment DH3.
/
Ind/Ver
_(2) PLACE the circuit breaker control switch in the 0FF position for RHR Suction Isolation Valve, 2-Ell-F009, (ASSO FEED) at MCC 2X0 compartment DX5.
/
Ind/Ver (3) PLACE the Close/0ff/Open ASSD Keylock Switch in the OFF position for RHR Suction Isolation Valve, 2-E11-F009, at MCC 2XD compartment OX5.. RB.l
/ - " ~
Ind/Ver
- d. Reactor Water Level indicator, 2-B21-LI-R604BX, is no longer required, THEN PLACE Reactor Water Level "NORMAL / LOCAL" Switcn, 2-821-CS-3345 at the Remote Shutdown Panel, to the "NORMAL" position.
/
Ind/Ver
- 12. WHEN:
- a. The fire is extinguished AND
- b. All breakers AND/0R switches operated in this procedure are restored to their normal position AND
- c. No actions within this procedure are required to achieve and maintain Cold Shutdown, THEN
- d. EXIT this procedure.
BSEP-2/ ASS 0-21 Page 7 of 12 4ev. 0
3-Date/ Time Completed Performed By (Print) Initials Reviewed By: _
Shift Foreman R 0.1 i
BSEP-2/ ASS 0-21 Page 8 of 12 Rev. O i
n.
CONTROL Bl)/L DING _
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- - - ACCT $s/ EGRESS f*M0HEack.TMAIM^OR8 FIGURE I Control Building 23'0" and 49'0" Elevations Access / Egress and SoJnd Powered Phone Comunications SSEP 2/AS50-21 49e 9 of 12 Rev, o
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~ ~ ~ ~ ACCESS / EGRESS f PHONE JACK, TRAIN A OR 8 e ISOL ATE SWITCH FIGURE 2 Unit 2 Reactor Building 20'-0" Elevation - A::ess/ Egress and Sound Powered Phone Co munications Page 10 of 12 Rev. O 3SEP-2/ASSD-21
UNIT 2 REACTOR BUILDING
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FIGURE 4 Unit 2 Reactor Building -17' -0" Elevation - Ac. cess / Egress BSEP-2/ ASS 0-21 page 12 of 12 Rey, 0l