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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
-
b Core Shroud Reinspection Plan Unit 2 B212R1 Outage February 1996 l
l I
Recommended by: Nbx Date: lo /Jo/3s Approved byh68b Date: ///2/95
!!A*1888AZiaa86 G PDR
Core Shroud Reinspection Plan Unit 2 B212R1 Outage February 1996 EXECUTIVE
SUMMARY
The scope of reinspection for the Unit 2 core shroud is based on the results of previous inspections performed on both Unit I and Unit 2, follow-up actions and commitments i established from the last inspection documented in Engineering Evaluation Report 94-0077, guidance on shroud inspections contained in NRC Generic Letter 94-03 and draft 4 of the BWRVIP " Guidelines for Reinspection of BWR Core Shrouds" dated September 15, 1995.
l The reinspection scope focuses on three objectives: re-examination of selected areas to f determine crack growth, examination of a sample of the installed clamps to verify no inservice degradation, and utilization of specifically developed tooling to examine accessible portions of certain welds that were previously inaccessible. Inspection of the core shroud in Unit 2 during May 1994 was performed prior to the issuance of Generic Letter 94-03. The inspection was also performed utilizing prototype UT tooling under development. Reliability problems arose, and use of the tooling had to be abandoned. The UT equipment commonly used for core shroud inspections will not v'ork on the Bnmswick Plant shrouds because of interference from l the installed clamps on welds H2 and 113. BNP is developing specialized UT tooling to l inspect certain welds. Specifically, UT examinations will be performed on 100% of the accessible areas of weld Hl. UT will also be performed on areas not previously inspected on welds ll6A, and H6B and H7. Additionally, UT will be repeated at selected areas on weld 114 to assess crack growth during the cycle.
Additional inspections will be performed if measurements indicate that crack growth is greater than anticipated. Predictions from crack growth models (GE PLEDGE) and plant specific data e from the Crack Arrest Verification System (CAVS), indicate that little, if any, crack growth is expected. This is consistent with predictions and actual results from Unit 1.
UT inspections will be conducted utilizing pulse echo technology Equipment and procedures for UT, and for any supplemental VT, will be qualified in accordance with the inspection guidelines of the BWRVIP. The NDE uncertainty will be determined in qualification testing by the inspection vendor. These qualifications will follow the BWRVIP inspection guidelines.
Two of the twelve clamps installed on welds H2 and H3 during the Spring 1994 outage will be VT inspected to insure that no adverse degradation has occurred during the operating cycle.
An engineering evaluation of the inspection results will be performed using the flaw evaluation i
l
guidanc'e issued by the BWRVIP in Core Shroud Inspection and Evaluation Guidelines, or other accepted industry criteria.
CP&L is working closely with the BWRVIP to evaluate field information and incorporate
" lessons learned" into the inspection program. Inspection of core shroud support legs, and other vessel attachments and internals, will be performed consistent with the guidance provided by the BWRVIP in the future.
UNIT 2 CORE SIIROUD INSPECTION PLAN The scope of this inspection plan along with previous inspections meets the intent of requested licensee action item 3 of Generic Letter 94-03. This action item requires an inspection plan for all shroud welds or justification for not inspecting certain welds, and requires use of technology and industry experience to perform inspections that will consistently detect IGSCC.
The inspection plan scope has been developed from Generic Letter 94-03, the proposed BWRVIP " Guidelines for Reinspection of Core Shroud Welds" and from knowledge gained from the previous inspections of BNP Units 1 and 2. The inspection plan for the core shroud focuses on application of improved inspection techniques for welds where internal surfaces were not accessible, and on reinspection of certain areas to determine crack growth rates. UT inspection tooling commonly used in the industry will not perform adequately on the BNP core shrouds due to interference from the clamps installed on the H2 and H3 welds. BNP is developing specialized tooling to inspect the welds that cannot be inspected with conventional tooling.
Weld H1 was VT inspected at selected outside surface locations in 1994. UT will be performed during the B212R1 outage on 100% of the accessible areas of weld H1 and its associated fillet weld. Weld 111 is a ring weld with "end grain" exposure and significant cold work. Welds H2 and H3 will not be inspected since their structural function was replaced by clamps in 1994.
Weld H4 will be reinspected in two places to determine crack grov h rates. Weld H5 is not scheduled for reinspection, since relatively little cracking was found during the previous inspection, and since conditions at weld H4 (weld geometry, ECP, fluence, etc.) closely approximate those at H5.
The accessible outside areas of welds H6A, H6B and H7 were VT inspected in 1994.
Inspection of welds H6A and H6B and their associated fillet welds will be supplemented by UT inspection at six locations between jet pump pairs. Access is limited to these six areas due to the proximity of the jet pump sensing lines. All accessible areas of weld H7 will be UT inspected.
l Weld 118 and the shroud support legs below the core plate will not be inspected this outage because equipment and techniques are still being developed for these inspections. These areas will be inspected consistent with guidance provided by the BWRVIP in the future.
Although weld 119 is not currently required to be inspected by the BWRVIP guidelines, data may be available for the H9 weld due to its proximity to a weld that is included in the vessel beltline inspection program.
Two of the twelve repair clamps will be VT inspected to assure no degradation has occurred during the last cycle of operation. <
Details of the scope of inspection for each weld and for the clamps are provided in Table 1.
INSPECTION SCOPE EXPANSION l l
Based on the results of the Brunswick Plant Unit 2 Core Shroud Reinspection Plan, additional inspections of the core shroud (including repair clamps) will be performed, if required to demonstrate core shroud integrity. CP&L will address any scope expansion in our submittal of the inspection results to the NRC Staff. No such expansion is anticipated, based on the operational history during the last cycle, and the results from Unit 1.
EVALUATION An engineering evaluation of the results of the inspection will be performed, using the flaw evaluation guidance issued by the BWRVIP in the Core Shroud Inspection and Evaluation Guidelines, or other accepted industry criteria. CP&.L will submit the inspection results in accordance with the guidance of NRC Generic Letter 94-03.
l l
1
TABLE 1 Unit 2 Outage - Core Shroud Reinspection REINSPECTION WELD METHOD
- COMMENTS 11i UT 100% of accessible areas.
112 N/A None.
(Weld is structurally replaced by installed clamps).
H3 N/A None.
(Weld is structurally replaced by installed clamps).
H4 UT Two locations to assess crack growth (100% of accessible areas were inspected during the B211R1 Outage).
115 None planned Conditions at weld H4 (weld geometry, ECP, fluence, etc.) closely approximate weld H5.
Il6A UT Six (6) areas between jet pump pairs.
H6B UT Six (6) areas between jet pump pairs.
117 UT 100% of accessible areas between jet pump pairs.
l 118 None planned BWRVIP developing inspection tools / techniques.
119 UT Data may be available as a by-product of the vessel beltline inspection program.
(from OD as part of vessel beltline inspection)
Shroud None planned BWRVIP developing inspection tools / techniques.
support legs
^
Two VT VT-3 clamps & hardware for general appearance and Clamps missing parts. -
VT-1 integrity of tack welds.
-S-L-- _ _ -- _ _----- _ ----------------------------------------------.-----.-------- ------------- ------- _ _-----. --------------------.------------------------ _ - _
ENCLOSURE 2 BRIJNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 NRC DOCKET NO. 50-324 OPERATING LICENSE NO. DPR-62 SUBMITTAL OF UNIT 2 CORE SHROUD REINSPECTION PLANS LIST OF REGULATORY COMMITMENTS The following table identifies those actions committed to by Carolina Power & Light Coinpany in th!s document. Any other actions discussed in the submittal represent intended or planned actions by Carolina Power & Light Company. They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify the Manager-Regulatory Affairs at the Brunswick Nuclear Plant of any questions regarding this document or any associated i
regulatory commitments.
Committed Commitment date or outape
?/. *_
- 1. Submit the B212R1 core shroud reinspection results. 30 days after completion of inspections
+
F,_
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1 i
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