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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
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CAROLINA POWER & LIGHT COMPANY BRUNSWICK SThAM ELECTRIC PLANT UNIT 0 END PATH PROCEDURE IN EMERGENCY OPERATING PROCEDUREt E0P-01-EPP-1N VOLtHE VI Rev. 005 Q a:;#'{ ,
U. s,9.s '#s 0 4-O k\ ...
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p$#jp*" ci 6Y h#*i'"
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.o Approved By: h h AAS Gener.$ Mahager/
Datet I /
kf Manager-Operatio]ns Page 1 of 9 8811110187 001025 4 DR ADOCK ObO
LIST OF EFFECTIVE PACES EOP-01-EPP-1N Page(s) Revision 1-2 5 3 3 4 4 5-9 5 BSEP/Vol. VI/EOP-01-EPP-1N Page 2 of 9 Rev. 5 1
A. ,T;]' E - End Path Procedure 1N B. ENTR1 CONDITIONS
- 1. All control rods did NOT fully insert following a scram initiation.
- 2. Boren injection was commenced and was terminated when all control rods were fully inserted.
C. OPERATOR ACTIONS eneesen**** ease *eme*******nenamenenene***eeeeeeee********enee**eeeneeeeeeeeeen CAUTION DO NOT SECURE or PLACE an ECCS or RCIC in manual mode UNLESS by at least two independent indicatienst
- 1. Misoperation in the automatic mode is confirmed, OR
- 2. Adequate core cooling is assured, IF an ECCS or RCIC is placed in the manual mode, it will NOT initiate automa-tically. MAKE frequent checks of the initiating or controlling parameter.
WHEN manual operation is no longer required. RESTORE the system to automatic /
standby mode if possible, e********************************************enenamenene******en**************
~~
- 1. RESTORE and MAINTAIN reactor vessel level between +170 and
+200 inches. USE one or more of the following systems in an order that will minimite high conductivity feed to the reactor:
RPV Pressure Range ,
System for System Operation i
- a. Condensate - - - - - - - - - - - - - - - - 200-0 psig
- b. Condensate / Booster - - - - - - - - - - - - 350-0 psig
- c. Feed Pumps - - - - - - - - - - - - - - - - 1250-0 psig
- d. CRD ------------------- 1490-0 psig
- e. RCIC - - - - - - - - - - - - - - - - - - - 1190-62 psig
- f. HPCI - - - - - - - - - - - - - - - - - - - 1280-120 psig
- g. RHP ------------------- 200-0 psig
- h. Core Spray - - - - - - - - - - - - - - - - 300-0 psig BSEP/Vol. V!/EOP-01-EPP-IN Page 3 of 9 Rev. 3 1
i
{
- 2. IF the CRD Drive Water Pressure Control Valve C11(C12)-F003, and I the in-service CRD Flow Control Valve C11(Cl2)-F002A(F002B). have !
l
' been opened to maintain reactor vessel level AND the CRD System is (
no longer needed to maintain reactor vessel level. THEN PERFORM the following steps to restore the CRD System to normal operationt
~
- a. SET the setpoint tape on CRDHS Remote Flow Controller. '
Cll(Cl2)-FC-R600, to 100 gpm.
[
t
~
- b. SHIFT the CRDHS Remote Flow Controller. Cil(C12)-fC-R600, to !
the "AUT0" position. I I
- c. IF both CRD pumps are running. THEN STOP one CRD pump. !
_/_ d. OPEN and LOCK OPEN CRD Pump Condensate Return Isolation Valve.
l Ind. Ver. COR-VI (located at CST).
i
/ e. IF Charging Water Header Throttle Valve. C11(Cl2)-F034. vas Ind. Ver, manipulated to maximize CRD flow. THEN CLOSE and 1HMEDIATELY i REOPEN 8 1/2 turns Charging Water Header Throttle Valve. I C11(Cl2)-F034.
I
~
- f. SET the setpoint tape on CRDHS Remote Flow Controller. !
C11(Cl2)-TC-R600, to between 30 and 80 gpm. I
- g. ESTABLISH a drive water header differential pressure between 260 and 275 psid as read on C11(C12)-PDI-R602 on RTGB Panel P603, by throttling closed Drive Water Pressure Control Valve. (
Cll(Cl2)-F003. L
/ h. IF CRD Pueps Suction Filters Bypass Valve. CO-V306. is open. 1 Ind. Ver. THEN VERIFY a CRD pump suction filter is in service and CLOSE I i the CRD Pumps Srction Filters Bypass Valve. CO-V306.
l t
- 1. IT both CRD pump suction filters are in service. THEN 150',. TE and REPLACE the filter which has the highest dP.
j.
IF both CRD drive water filters are in service. THEN ISOLATE l and RE' LACE the filter which has the highest dP. j l
l 3. IF while executing this procedure, reactor vessel level CANNOT be l determined OR reactor vessel flooding is required. TNFN i.XIT this Er.d Path Pr E edure and ENTER the "Flooding Procedur M n the j Contingency section of this End Path Manual, j '
- 4. IF reactor vessel level CANNOT be maintained above +170 inches. THEN r MAINTAIN reactor vessel level above 0 inches. I
~
- 5. IF reactor vessel level CANNOT be maintained above 0 inches. THEN IIIT this End Path ProceEre and ENTER the "Level Restoration i Procedure" in the Contingency section of this End Path Manual.
l
- 6. IF while executing this procedure, reactor depressurization is 6
required. Ti4EN PERFORM the following stepst {
t i
BSEP/Vol. VI/EOP-01-EPP-lN Page 4 of 9 Rev. 4 [
I l
f a
a i
, enaa***en** man ***ena*******aea************************************************
i CAUTION DO NOT DEPRESSURIZE below 120 psig UNLESS motor-driven pumps sufficient to maintain reactor vessel level are running and available for injection.
ee**een**nena****ene*********eneenanneeeeeee********n****enemanna*************
- a. IF the MSIVs are open THEN RAPIDLY DEPRESSURIZE the reactor ,
with the bypass valve opening jack. l
~~
- b. IF the reactor CANNOT be depressurized to the main condenser. :
YEEN manually OPEN all ADS valve,t.
(1) 1F any ADS valve CANNOT be opened, THEN OPTN SRVs UNTIL seven valves are open, j
j ,,
(2) IF less tha three SRVs are open AND reactor pressure is
, greater than 50 pais above suppression chamber pressure, l THEN ENTER the "Emergency Depressurisation Procedure" in 4
the Contingency section of this End Path Manual and
- EXECUTE it concurrently with this procedure.
(3) CONTINUE in this procedure at Step 9.
l 7. IF the MSIVs are open. THEN MAINTAIN reactor pressure below 1025 psig l with the bypass valve opening jack OR EHC pressure setpoint.
I *****enemane***eeeeanene******ee****************************************a*****
CAUTION DO NOT DEPRES$URIZE below 120 psig UNLESS sotor-driven pumps sufficient to i
maintain reactor vessel level are running and available for injection.
enneneseeseeeeeeee***aneeeeeeee**eee***eneseen***nenee**eaneeseneneesenannee**
1 f 8. IF reactor pressure CANNOT be maintained with the EH; Srstem AND q
continuous pneumatic supply is available to the SRVs, THEN OPEN SRVs as necessary to maintain reactor pressure below 1025 psfi! USE j opening sequence B. F. E. G. A C. J. H. and D.
l j
i J
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i i
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)
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Rev. 5 1
l BSEP/Vol. VI/EOP-01-EPP-1N Page 5 of 9 l
1
---r--,---wy m -- - ,_m,
l l
eeeeeeeeeee***eneeeeee***enee**********************enee**eemeneesenenneeemenen !
i CAUTION l IF fuel failure is suspected. DO NOT REJECT RWCU to hotwell. :
) !
IF an automatic isolation of a particular system has occurred. DO NOT ATTEMPT l l
Io de-isolate or restore the systen UNTIL all available indications have been i checked and are found to be normal.
I DO NOT DISPATCH personnel to an area of a suspected break without t consideration of adverse environments. l i
ee eee e * *
- e e e e e e e e e e e m e n e e * *
- e * *e e e e e e e e e e e e e e e * * *
(
- 9. Reactor pressure control say be augmented by one or more of the !
i following systesst ;
- s. NPCI {in full flow test soda) :
J l j
- b. RCIC (in full flow test mode) j t
- c. Main Steam Line Drains r I f j __
- d. RWCU (with return to vessel) L i
- e. Feed Pumps (in recirculation mode) f t
- f. SJAEs (in full load) .
- 10. IF ADS has been inhibited. THEN RESTORE ADS as followst i
/ a. PLACE the ADS LOGIC A INNIBIT. 321C-55A switch to "AUTO." }
Ind. Ver. .
)
/ b. PLACE the ADS LOGIC B INNIBIT. 321C-558, switch to "AUTO." {
Ind. Ver. J l
~~
- c. VERIFY annunciator AUTO DEPRESS TIMERS INITIATED (A-03 3-1) is i clear.
~~
- 11. IF the nitrogen instrument air backup isolation has been overridden.
IEEN PLACE the following switches to "0 PEN":
/ a. DIV I NON-INTRPT. RNA-SV-5262 Ind. Ver.
/ b. DIV II NON-INTRPT. RNA-SV-5145 Ind. Ver.
BSEP/Vol. VI/EOP-01-EPP-1N Page 6 of 9 Rev. 5
4 3
~~
- 12. IF jumpers were installed to bypass the Vessel Level Group 1 isolation, THEN REMOVE O.e following jumpers:
- a. UNIT I only
/ _
(1) In Cabinet XU-65, between Terminals 27 and 28 on Ind. Ver. Terminal Board TB-A.
' In Cabinet XU-66, between Terminals 27 and 28 on
, (2)
Ind. Ver. Terminal Board TB-A.
/ (3) In Cabinet XU-67, between Terminals 27 and 28 on Ind. Ver, Terminal Board TB-A.
/ (4) In Cabinet XU-68, between Terminals 27 and 28 on Ind. Ver. Terminal Board TB-A.
- b. UNIT 2 only
/ (1) In Cabinet XU-65, between Terminals 43 and 44 on Ind. Ver. Terminal Board TB-A.
/ (2) In Cabinet XU-66, between Terminals 43 and 44 on Ind. Ver. Terminal Board IB-A.
/ (3) In Cabinet XU-67, between Terminals 43 and 44 on Ind. Ver. Terminal Board Td-A. ,
/ (4) In Cabinet XU-08, between Terminals 43 and 44 on Ind. Ver. Terminal Board TB-A.
- 13. IF a break outside primary containeent is suspcceed, THEN PERFORM the following steps:
3 __
- a. ISOLATE the break by remote or manual operation 'a the affected ;
< valves.
- b. REFER to AOP-01.1.
- 14. IF SJAE stack, or MSL radiation monitor indicates fuel failure, THEN PERFORM the following steps
- a. NOTIFY E&RC to sample coolant.
- b. IF high radiation or high airborne conditions exist, THEN REFER to AOP-05 through AOP-06.
- c. PLAC3 the following valve control switches to "CLOSE"t (1) DW FLOOR DRAIN INBD ISOL VLV, G16-F003 (2) DW FLOOR DRAIN OTBD ISOL VLV G16-F004 BSEP/Vol. VI/EOP-01-bPP-1N Page 7 of 9 Rev. 5 l
2- .t; T (3) DW EQUIP DRAIN INBD ISOL VLV, G16-F019 (4) DW EQUIP DRAIN OTBD ISOL VLV, G16-F020
- d. NOTIFY Radraste to place Reactor Building equipment drain tank pumpr,into the recirculation mode,
- e. DO NOT OPERATE the mechanical vacuum pumpe
- 15. IF condensate booster pump suction conductivity is greater than 0.3 paho, THEN PERFORM the following steps
- a. REMOVE affected waterboxes from service.
- b. REALIGN CfDs and CDDs to provide better ion removal.
- c. IF the Condensate /Feedwater System is NOT required to maintain reactor vessel level THEN PLACE the Condensate System in long cycle cleraup. (OP-32)
- d. DO NOT REJECT the hotwell to the CST. ,
'e. REFER to AOP-26.0.
[
j 16. IF while executing this procedure, any of the following systems fall or have failed. TH2N ENTER the associated procedure in the System '
. Recovery section of this End Path Manual and EXECJTE it concur?ently
- a. Convention.nl Service Water
- b. Nuclear Service Water
- c. Reactor Building Closed Cooling Water
- d. Turbine Building Closed cooling Water
- e. Instrument Air >
- f. Auxiliary Electrical Power
- 17. NOTIFY the SOS to perform the following steps: l
- a. CONSULT PEP-02.1.
- b. NOTIFY on-call CP&L supervisor.
- c. NOTIFY NRC per RCI-06.5. ,
- d. NOTIFY E&RC to sample coolant.
- e. IMPLEKENT 0I-22. l BSEP/Vol. VI/EOP-01-EPP-1N Page 8 of 9 Rev. 5 l
- 18. IF the MSIVs are closed, THEN REESTABLISH the main condenser as a heat sink. (OP-25)
- 19. IF RWCU has isolated AND a break in the RWCU System is NOT
~
Espected, THEN RESET the Group 3 isolation and RESTART RWCU with return to reactor vescel. (OP-14)
- 20. IF the reactor recirculation pumps have tripped, THEN RESTART the reactor recirculation pumps. (OP-02)
- 21. MAXIMIZE RWCU operation to remove boron from r:racco ent.
- 22. CONTINUE performing Containment Control, Local Emergency, and System Recovery Procedures UNTIL the exit conditions for the affected procedures are met.
- 23. RECORD required scram information in the Scram Report (01-22) and Shift Logs.
24 WRITE Work Request / Job Orders /LCOs to ensure that functional testing is performed on those systems in which jumpers were installed.
- 25. WHEN systems that require independent verification for return to service are shut down, THEN PLACE the systems in standby readiness -r per their respective cps. (Refer to Table 11.7.1 in Volume I, Book 1-AP.)
- 26. IF reactor cool down and depressurization is to be coc:menced per the SOS, THEN ENTER the General Plant Operating *rocedure and EXECUTE it concurrently with this procedure.
- 27. WHEN:
- a. Reactor vessel level can be maintaincd above +170 inches AND
- b. Reactor pressure can be maintained belov 1045 psig AND
- c. Primary containment parameters are within the limits specified in the Containment Control Procedtra, THEN EXIT this procedure and ENTER the appropriate section of the General Plant Operating Procedure for hot / standby OR, cold shutdown as directed by the SOS.
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l BSEP/Vol. VI/EOP-01-EPP-1N Page 9 of 9 Rev. 5 l