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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 STEAM ELECTRIC PLANT WIT 0 EMERGT' ICY DEPRESSURIZATION PROCEDL?.E D(ERGENCY OPERATING PROCEDURE: EnP-01-CDP VOLLHE VI Rev. 003 0% -
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1 <? l Approved By $f!t.u, Date: Y Gene $1Managep I /
' Manager - Operacwons 1
I of 5 B"111110175 001025 '
PDR ADOCK 050003P4
, P PDR Q
LIST OF EFFECTIVE PAGES E0P-01-EDP Page(s) Revision 1-5 3 BSEP/'lol. VI/EOP-01-ELP 2 of 5 Rev. 3
A. TITLE - Emergency Depressurization Procedure B. ENTRY CONDITIONS
- 1. Depressurization of the reactor is required AND
- 2. Less than three SRVs can be opened AND
- 3. Reactor pressure is at least 50 psig above suppression chamber pressure.
C. OPERATOR ACTIONS
- a***e*******************************************
CAUTION DO NOT DEPRESSURIZE below 120 psig L'NLESS motor driven pumps sufficient to maintain reactor vessel level are running and available for injection.
ene*********name**********a***************************************************
I
- 1. DEPRESSURIZE the reactor with one or more of the following systemst
- a. Main Condenser
- b. Main Steam Line Drains
- c. HPCI (full flow test mode)
- d. RCIC (full flow test mode)
- 2. IF the MSIVs are closed due to a reactor vessel lov level Group 1 isolation AND the main condenser is available as a heat sink.
THEN PERFORM the following steps:
- a. PLACE all MSIV switches to "CLOSE."
- b. PLACE the following switches to "0VERRIDE RESETt" (1) DIV I NON-INTRPT. RNA-SV-5262
_ (2) DIV II NON-INTRPT. RNA-TV-5261 i c. CLOSE the followit.g valves:
i (1) Main Steam Line Drain Inboard Isolation Valve. 521-P016
___ (2) Fein Steam Line Drain Outboard Isolation Valve. 521-T019 (3) Sample Inboard Isolecion valve B32-P019 (4) Sample Outboard Isolation Valve. 532-F020 BSEP/Vol. VI/EOP-01-EDP 3 of 5 Rev. 3
1
- d. UNIT 1 only - INSTALL the following jumpers to bypass the reactor vessel low level (+112 inches) Group 1 isolation.
(1) In Cabinet XU-65, between Terminals 27 and 28 on Terminal i Board TB-A.
(2) In cabinet XU-66. between Terminals 27 and 28 on Terminal Board TB-A.
(3) In Cabinet XV-67, between Terminals 27 and 28 on Terminal Board TB-A.
___ (4) In Cabinet XU-68 between Terminals 27 and 28 on Terminal Board TB-A.
- e. UNIT 2 only - INSTALL the following jumpers to bypass the ,
reactor vessel low level (+45 inches) Grcup 1 isolation. ;
~~~
(1) In Cabinet XU-65, between Terminals 43 and 44 on Terminal Board TB-A.
(2) In Cabinet XU-06, between Terminals 43 and 44 on Terminal Board TB-A.
(3) In Cabinet XU-67, between Terminals 43 and 44 on Terminal Board TB-A. ,
___ (4) In Cabinet XU-68. between Terminals 43 and 44 on Terminal l Board TB-A.
- f. RESET Group 1 isolation.
- g. EQUALIZE pressure and REOPEN MSIVs.
- h. F.APIDLY DEPRESSURIZE the reactor with the bypass valve opening jack. ,
BSEP/Vol. VI/EOP-01-EDP 4 of 5 Rev. 3
o s [
o = '
e ;
- 3. WHEN three or more SRVs are open OR reactor pressure is less than 50 psig above suppression chamber pressure. THEN PERFORM the following stepst
- a. IF jumpers were installed to bypass the reactor vessel level lI 3roup 1 isolation. THEN REMOVE the following jumpers (1) UNIT 1 only
/ (a) In Cabinet XU-65, between Terminals 27 and 28 on Ind. Ver. Terminal Board TB-A.
/ (b) In Cabinet XU-66, between Terminals 27 and 28 on Ind. Ver. Terminal Board TB-A.
/ (c) In Cabinet XU-67, between Terminals 27 and 28 on Ind. Ver. Terminal Board TB-A.
/ (d) In Cabinet KU-68. between Terminals 27 and 28 on Ind. Ver. Terminal Board TB-A. l (2) UNIT 2 only f
?
/ (a) In Cabinet XU-65..between Terminals 43 and 44 on l Ind. Ver. Terminal Board TB-A.
/ (b) In Cabinet XU-66, between Terminals 43 and 44 on j Ind. Ver. Terminal Board TB-A. ;
i (c) In Cabinet XV-67, betvmen Terminals 43 and 44 on Ind. Ver. Terminal Board TB-A.
/ (d) In Cabinet XU-68, between Terminals 43 and 44 on Ind. Ver. Terminal Board TB-A.
- b. Place the following switches to "0 PEN":
/ (1) DIV I NON-INTRPT. RNA-SV-5262 Ind. Ver.
/ (2) DIV II NON-INTRPT. RNA-SV-5261 Ind. Ver.
- c. EXIT this procedure. l BSEP/Vol. VI/EOP-01-EDP 5 of 5 Rev. 3 l
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