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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
- __ _ .- .-
l
- Core Shroud Inspection Plan Unit 2 B213R1 Outage SEPTEMBER,1997 Prepared by:
Phil Gore John Langdon Blane Wilton June 12,1997 Recommended by:
((02.9 % Date: Ir, i2 97 Approved by:
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Y Date: 6 -/ 2 "? '7 l
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D A CK 05 0 24 .,
P PDR
l Core Shroud Inspection Plan Brunswick Steam Electric Plant, Unit No 2 B213R1 Outage September,1997
SUMMARY
OF PREVIOUS INSPECTIONS The scope of reinspection for the Brunswick Steam Electric Plant (BSEP), Unit No. 2 Core Shroud is based on the results of previous inspections performed on both BSEP Unit No. I and Unit No. 2, follow-up actions and commitments established from the last inspection and guidance on shroud inspections and flaw evaluation obtained in the " Core Shroud Inspection and Evaluation Guidelines", issued by the Boiling Water Reactor Vessel Internals Program (BWRVIP).
Inspection of the BSEP Unit No. 2 core shroud during the B211R1 refueling outage (May 1994) was prior to the issuance of Generic Letter 94-03. This inspection was also performed while development of some of the ultrasonic tooling currently being used was ongoing. Reliability problems arose and use of the tooling was abandoned. Automated ultrasonic testing (UT) scanners commonly used for shroud inspections will not work on the BSEP shrouds because of interference from the clamps on the H2 and H3 welds. Specialized tooling has since been developed to inspect the inside diameter (ID) and outside diameter (OD) surfaces of welds H1, H4,115, core support ring welds H6A and 116B and associated fillet welds, and weld H7. These welds were previously inspected from the OD only using VT. The H9 weld was previously inspected as part of the vessel beltline inspections because it is located directly behind one of the vessel beltline welds. Additionally, UT measurements were repeated at selected areas on the H4 during the B212R1 outage in order to assess crack growth during that cycle.
UNIT 2 CORE SHROUD REINSPECTION PLAN The reinspection plan for the core shroud focuses on the application ofimproved inspection techniques for welds where internal surfaces were not accessible, and on reinspecting are.as inspected last outage to determine crack growth rates. Tooling commonly used in the industry will not work on the BSEP shrouds due to interference from the H2/H3 repair clamps.
Specialized tooling has been developed to inspect these welds.
Welds H1, H2 and H3 will not be inspected this outage. One hundred percent (100%) of the accessible areas of the H1 weld were inspected during the B212R1 outage. Any anticipated growth of the noted indications will not impact structural margins. Welds H2 and H3 have been structurally replaced replaced by the clamps.
Weld H4 will be UT examined at two locations for determination of crack depth growth; these two locations were previously examined during the B212R1 refueling outage. The H5 weld was visually inspected on the ID and OD during the B211R1 refueling outage with relatively little Pao,e 2
U cracking noted. Carolina Power & Light Company plans to UT inspect the 115 weld during the B213R1 outage to gain additional coverage and determine the depth of the cracking.
Welds H6A, H7, and H9 will not be inspected this outage. One hundred percent (100%) of the accessible areas ofli6A, H7, and H9 were UT examined during the B212R1 outage. Any anticipated growth of the noted indications in welds H6A and H7 will not impact structural margins. No indications were noted in weld H9 during the B212R1 inspections.
Weld H6B will be re-examined this outage to determine crack growth and achieve additional coverage in areas not previously accessible. The phased array equipment utilizes smaller inspection probes which should permit access to additional areas of the weld. Additional, the phased array techniques are being designed to reduce the error band margins for depth and length.
Weld H8, the shroud support legs and other areas below the core plate will not be inspected this outage because the BWRVIP is still developing inspection and evaluation guidelines, and equipment and techniques have not been developed for these areas. These areas will be inspected in the future consistent with BWRVIP guidance.
Although not currently required in the BWRVIP guidelines, inspection of the H9 weld has already been performed. This weld is directly behind one of the vessel beltline welds, so examination of the H9 weld was performed as part of the beltline weld examination during the B212R1 refueling outage.
Three of the twelve repair clamps will be visually inspected in accordance with BWRVIP Inspection and Evaluation Guidelines to assure no degradation during the last cycle of operation.
Details of the scope ofinspection for each weld, and for the clamps, are described in Table 1.
During the course of the inspections, unanticipated interferences may be encountered that will require changes to this plan. These situations will be evaluated as they arise.
INSPECTION SCOPE EXPANSION Additional areas of the shroud welds will be inspected if crack growths are unusually higher than predicted crack growth and NDE measurement uncertainty. The NDE uncertainty will be determined in quali6 cation testing by the inspection vendor. These qualifications will be in accordance with the BWRVIP inspection guidelines.
If any unusual findings are confirmed upon inspection of the three clamps, the remaining clamps will be inspected to determine the extent of any changes.
Page 3
EVALUATION An engineering evaluation will be performed on the inspection results, using the flaw evaluation guidance of the BWRVIP " Core Shroud Inspection and Evaluation Guidelines." No significant changes from the last inspection results are expected.
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TABLE 1 ,
Unit 2 Refueling Outage 12 (B213RI) Core Shroud Reinspection i WELD PREVIOUS INSPECTION RESULTS REINSPECTION COMMENTS METIIOD*
111 1994 - VT of OD between 4 lug sets with no indications None planned Not scheduled for examination this outage. Sufikient structural !
noted. margins exist. Any anticipated growth of indications will not impact i E '
1996 - UT of ~ M)% of the accessible ID and OD areas.
112 VT at 2 locatbns with circumferential cracking. N/A Replaced by clamps. l t
113 None N/A Same as 112.
114 1994 - UT of 100% of accessible area (78.8%) from OD. UT UT at 2 - 20" areas for crack depth growth determination. ;
Found 110.6" of random ID circumferential cracking. No .
OD cracking found. Depths from 0.10" to 0.86".
1996 - UT at 2 - 20" areas for crack depth growth t determination. No significant growth detected. i 115 1994 - VT of 100% ofID and 30.5% of OD. 59.3" of UT Relatively little cracking found during 1994 (B211RI) outage circumferential cracking found on ID and 11" of inspections. Will UT this outage to obtain additional coverage. ,
circumferential cracking found on the OD -
1996 - None performed.
Il6A 1994 - VT 6% of OD with a 1.5" circumferential crack. None planned Not scheduled for examination this outage. Sufficient structural
.?.argins exist. Any anticipated growth of indications will not impact '
1996 - UT 100% of accessible areas. 79% of weld length structural margins.
examined with 5.3% of examined weld length flawed. ,
II6B 1994 - VT 6% of OD with no circumferential cracking. UT UT with phased array techniques to improve coverage and refine length and depth sizing capabilities..
1996 - UT 100% of accessible areas. 78.4% of weld length examined with 69.6% of examined weld length flawed.
i
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_ . ~ . - . . . . - _ - _ _ - _ _ - _ - _ _ - _ - - _ _ _ - - _ _ . _ _ _ - _ _ _ _ _ _ _
+
. o WELD PREVIOUS INSPECTION RESULTS REINSPECTION COMMENTS METHOD
- 117 1994 - VT of 6% of the OD with no circumferential None planned Not scheduled for examination this outage. Sufficient structural cracking. margins exist. Any anticipated growth of indications will not impact 1996 - UT 100% of accessible areas. 75.6% of weld length examined with 10.9% of examined weld length flawed.
118 None None planned BWRVIP developing inspection tools / techniques.
119 1996 - UT 100% of accessible areas. 99% of weld length None planned Not scheduled for examination this outage. Sufficient structural examined with no flaws noted. margins exist. Any anticipated growth of indications will not impact structural margins.
r Shroud Not inspected. None planned BWRVIP developing inspection tools / techniques.
support legs Shroud 1994 -VT of 2 installed clamps. VT Inspect 3 clamps for general appearance, missing parts, and integrity clamps of tack welds. Will bring the total clamps inspected to 8 of the 12 1996 - VT of 3 different installed clamps. total installed.
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. )
ENCLOSURE 2 )
l BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 :
NRC DOCKET NO. 50-324 OPERATING LICENSE NO. DPR-62 l SUBMITTAL OF UNIT 2 CORE SHROUD RE-INSPECTION PLANS !
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LIST OF REGULATORY COMMITMENTS !
l The following table identifies those actions committed to by Carolina Power & Light (CP&L) I Company in this document. Any other actions discussed in the submittal represent intended or l planned actions by CP&L. They are described to NRC for the NRC's information and are not l regulatory commitments. Please notify the Manager- Regulatory Affairs at the Brunswick l Steam Electric Plant of any questions regarding this document or any associated regulatory commitments.
Commitment Committed date or outage
- 1. Perform reinspections of the BSEP Unit No. 2 core shroud in B213R1 accordance with the Core Shroud Reinspection Plan dated June 12, !
1997.
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- 2. Submit the results of BSEP Unit No. 2 core shroud re-inspections. Within 30 days following completion of the inspections.
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E2-1 t
