|
---|
Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20210P9181999-08-10010 August 1999 Safety Evaluation Authorizing Request for Reliefs CIP-01,02, 06,07,08,09,10 & 11 (with Certain Exceptions) & 12-18,for Second 10-year ISI Interval.Request CIP-04 & 05 Would Result in hardship,CIP-03 Not Required & CIP-11 Denied in Part ML20210P9441999-08-10010 August 1999 Safety Evaluation Accepting Licensee Assessment of Impact on Operation of Plant,Unit 1,with Crack Indications of 2.11, 6.36 & 1.74 Inches in Three Separate Jet Pump Risers ML20210N2341999-08-0505 August 1999 SER Accepting Response to NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issues (USI) A-46 ML20206G1871999-05-0404 May 1999 Safety Evaluation Approving Third 10-year ISI Program Requests for Relief (RR) RR-08,RR-15 & RR-17 ML20205F9031999-03-30030 March 1999 Safety Evaluation Supporting Proposed Rev to BSEP RERP to Licenses DPR-62 & DPR-71,respectively ML20203D7061999-02-0909 February 1999 SER Accepting Proposed Alternatives Contained in Relief Requests PRR-04,VRR-04,VRR-13,PRR-01,PRR-03,VRR-01.VRR-07, VRR-08 & VRR-09 Denied ML20154P8151998-10-16016 October 1998 SER Accepting Revised Safety Analysis of Operational Transient of 920117,for Plant,Unit 1 ML20154P8591998-10-16016 October 1998 SER Accepting Equivalent Margins Analysis for N-16A/B Instrument Nozzles for Plant,Units 1 & 2 ML20217K8461998-04-24024 April 1998 Safety Evaluation Approving Proposed Use of Code Case N-535 at Brunswick Unit 1 During Second 10-yr Interval,Pursuant to 10CFR50.55a(a)(3)(i).Authorizes Use of Code Case N-535 Until Code Case Included in Future Rev of RG 1.147 ML20217K3941998-04-24024 April 1998 SER Approving Relief Request for Pump Vibration Monitoring, Brunswick Steam Electric Plant,Units 1 & 2 ML20217E6841998-04-23023 April 1998 Safety Evaluation Accepting Code Case N-547, Alternative Exam Requirements for Pressure Retaining Bolting of CRD Housings ML20217E7471998-04-21021 April 1998 Safety Evaluation Accepting Alternative to Insp of Reactor Pressure Vessel Circumferential Welds ML20217B5241998-04-20020 April 1998 SE Accepting Licensee Request for Approval to Use Alternative Exam Requirement for Brunswick,Unit 1,reactor Vessel Stud & Bushing During Second 10-yr ISI Interval Per 10CFR50.55a(a)(3)(ii) ML20216B1041998-03-0404 March 1998 SER Approving Alternative to Insp of Reactor Pressure Vessel Circumferential Welds for Brunswick Steam Electric Plant, Unit 1 ML20198J0921997-09-18018 September 1997 Safety Evaluation Authorizing Licensee & Suppls & 16 Request for Approval of Alternative Reactor Vessel Weld Exam,Per 10CFR50.55a(g)(6)(ii)(A)(5) for Plant, Unit 2 for Next 2 Operating Cycles ML20198H2351997-09-0808 September 1997 Safety Evaluation Approving Licensee 970311 Request for Use of ASME Code Case N-509 & Relief from ASME Code Section IX Requirements for Exam of Hpcip Studs for Plant,Units 1 & 2 ML20137A4831997-03-18018 March 1997 SER Re CP&L Review of Power Uprate Process & Commitment Preventing Operation at Uprated Power Levels for Plant, Units 1 & 2 ML20129E0821996-09-26026 September 1996 Safety Evaluation Supporting Request to Use Certain Portions of Later Edition of ASME Code for Inservice Leakage Testing Valves for Brunswick Steam Electric Plant Units 1 & 2 ML20056D6761993-07-28028 July 1993 Safety Evaluation Concluding That Interior Masonry Walls May Be Downgraded to non-fire Related ML20128K7711993-02-11011 February 1993 Safety Evaluation Granting Relief from Certain Inservice Testing Program Requirements for Several Pumps & Valves ML20198E5081992-11-23023 November 1992 Safety Evaluation Accepting Licensee 120-day Response to Suppl 1 to GL 87-02 ML20246D6811989-08-18018 August 1989 Safety Evaluation Supporting Installation & Design of Nitrogen Pneumatic Sys,Per Generic Ltr 84-09,by Adding New Check Valves to Existing Drywell Noninterruptible Instrument Air Lines ML20246C4201989-06-27027 June 1989 SER Accepting Util Response to Generic Ltr 83-28,Item 4.5.3 Re Reactor Trip Sys Reliability for All Operating Reactors ML20247P6201989-06-0101 June 1989 Safety Evaluation Supporting Util SAFER/GESTR-LOCA Analysis ML20247M1911989-05-25025 May 1989 Safety Evaluation Re Denial of Amend Request to Licenses DPR-71 & DPR-62 ML20246P9401989-05-10010 May 1989 Safety Evaluation Accepting Plant Second 10-yr Interval Inservice Insp Program ML20246J5531989-05-0909 May 1989 Safety Evaluation Concluding That Plant Can Be Safely Operated for Another 18-month Fuel Cycle in Configuration Following Reload 5,per Improvements,Insps & Repairs to Plant IGSCC ML20245D3761989-04-25025 April 1989 Safety Evaluation Supporting Licensee IGSCC Program for Refuel 7 Outage ML20236D5481989-03-17017 March 1989 Safety Evaluation Accepting Util Response to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys Reliability ML20236D5381989-03-17017 March 1989 Safety Evaluation Accepting Util 831107 Response to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for safety-related Components ML20236D4641989-03-15015 March 1989 Safety Evaluation Re Generic Ltr 83-28,Item 2.1 (Parts 1 & 2) Concerning Equipment Classification & Vendor Interface for Reactor Trip Sys Components ML20235Z2841989-03-0808 March 1989 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Items 3.2.1 & 3.2.2 ML20235Z3451989-03-0808 March 1989 Safety Evaluation Supporting Util Compliance W/Atws Rule, 10CFR50.62 Re Power Testability Features of Alternate Rod Insertion Sys & Recirculating Pump Trip Design ML20235M5771989-02-16016 February 1989 Safety Evaluation Supporting Control Room Habitability Sys of Plant & Acceptability of Existing Tech Spec Re Control Room Pressurization Requirement ML20147G0661988-03-0202 March 1988 Safety Evaluation Supporting Proposed Functional Testing Plan for Snubbers ML20236D1311987-10-22022 October 1987 Safety Evaluation Re Util Request for Relief from Schedular Requirements for Performance of Visual Insp & Hydrostatic Test of CRD Withdrawal & Insert Lines.Granting of Request Recommended ML20235A7331987-09-18018 September 1987 Safety Evaluation Re Installation of Alternate Rod Injection (ARI) Sys & Adequacy of Plant Reactor Coolant Recirculating Pump Trip (RPT) Sys,In Compliance W/Atws Rule 10CFR50.62. ARI & RPT Acceptable NUREG-0661, Safety Evaluation Re Util 840831 Submittal of Addendum to Plant Unique Analysis Rept on Mark I Containment Mod Program.Safety/Relief Valve Load Cases C3.2 & C3.3 Adequately Addressed & Resolved1987-05-0707 May 1987 Safety Evaluation Re Util 840831 Submittal of Addendum to Plant Unique Analysis Rept on Mark I Containment Mod Program.Safety/Relief Valve Load Cases C3.2 & C3.3 Adequately Addressed & Resolved ML20212H5671987-01-16016 January 1987 Safety Evaluation Supporting Util Response to Generic Ltr 83-08 Re Restoring Safety Margins of Vacuum Breakers by Replacing Critical Parts W/Adequate Matls ML20207A8531986-11-0505 November 1986 Safety Evaluation Supporting Operation for Full Fuel Cycle W/O mid-cycle Insp for Crack Growth ML20215N3771986-10-30030 October 1986 Safety Evaluation Re Util 860320 Response to Generic Ltr 84-09, Recombiner Capability Requirements of 10CFR50.44(c)(3)(ii). Licensee Should Remove All Potential Oxygen Sources from Containments ML20203N0081986-09-17017 September 1986 Safety Evaluation Supporting Util 850919 Request for Relief from Installing Excess Flow Switch & Automatic Shutoff Valve in Diesel Fire Pump Fuel Line to Provide Protection in Event of Fuel Line Rupture ML20212N0201986-08-22022 August 1986 Safety Evaluation Denying Util 860325 Request for Relief from Inservice Insp Requirements of ASME Code Section XI, Table IWC-2500-1 for Volumetric Exam of HPCI Pump Studs ML20211G6081986-06-12012 June 1986 Safety Evaluation Supporting IGSCC Insp,Repair & Replacement Program During Dec 1985 Refueling Outage ML20205S2541986-06-0404 June 1986 Safety Evaluation Accepting Rev 2 to Nuclear Const Issues Group Spec 1, Visual Weld Acceptance Criteria for Structural Welding at Nuclear Power Plants, for non-ASME Code Welds ML20211A8281986-06-0303 June 1986 Safety Evaluation Re Rev 4 to Offsite Dose Calculation Manual.Rev Acceptable ML20198S7281986-05-29029 May 1986 Safety Evaluation Supporting 851203 Proposal to Modify Tech Spec 3/4.5.3 to Clarify Min Amount of Condensate Storage Tank Water Required to Ensure Operability of Core Spray Sys During Operating Conditions 4 or 5.Rev to Tech Specs Encl ML20133N4141985-10-23023 October 1985 Safety Evaluation Re Util 831107 & 850828 Responses to Generic Ltr 83-28,Items 3.1.2 & 3.2.1 & 850701 Request for Addl Info.Responses Re Vendor & Engineering Test Guidance & Testing Requirements After Maint Acceptable ML20134P5211985-08-28028 August 1985 Safety Evaluation Approving Use of ASME Code Case N-411 for Damping Curves ML20128M2911985-07-16016 July 1985 Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28, Salem ATWS Event, Items 3.1.3 & 3.2.3 Re post-maint Testing 1999-08-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N3271999-10-21021 October 1999 Part 21 Rept Re non-linear Oxygen Readings with Two (2) Model 225 CMA-X Containment Monitoring Sys at Bsep.Caused by High Gain Produced by 10K Resistor Across Second Stage Amplifier.Engineering Drawings Will Be Revised BSEP-99-0168, Monthly Operating Repts for Sept 1999 for Bsep,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Bsep,Units 1 & 2. with ML20212D0431999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Brunswick Steam Electric Plant,Units 1 & 2 ML20210P9441999-08-10010 August 1999 Safety Evaluation Accepting Licensee Assessment of Impact on Operation of Plant,Unit 1,with Crack Indications of 2.11, 6.36 & 1.74 Inches in Three Separate Jet Pump Risers ML20210P9181999-08-10010 August 1999 Safety Evaluation Authorizing Request for Reliefs CIP-01,02, 06,07,08,09,10 & 11 (with Certain Exceptions) & 12-18,for Second 10-year ISI Interval.Request CIP-04 & 05 Would Result in hardship,CIP-03 Not Required & CIP-11 Denied in Part ML20210N2341999-08-0505 August 1999 SER Accepting Response to NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issues (USI) A-46 ML20210R1191999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Bsep,Units 1 & 2 ML20210R1311999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Bsep,Unit 2 BSEP-99-0118, Monthly Operating Repts for June 1999 for Bsep,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Bsep,Units 1 & 2. with BSEP-99-0095, Monthly Operating Repts for May 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20210M8581999-05-14014 May 1999 B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, Rev 0 ML20211L3711999-05-10010 May 1999 Rev 0 to ESR 98-00333, Unit 2 Invessel Feedwater Sparger Evaluation ML20206G1871999-05-0404 May 1999 Safety Evaluation Approving Third 10-year ISI Program Requests for Relief (RR) RR-08,RR-15 & RR-17 BSEP-99-0075, Monthly Operating Repts for Apr 1999 for Brunswick Steam Electric Plant,Unit 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Brunswick Steam Electric Plant,Unit 1 & 2.With ML20206N1791999-04-23023 April 1999 Rev 0 to 2B21-0554, Brunswick Unit 2,Cycle 14 Colr BSEP-99-0059, Monthly Operating Repts for Mar 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20205F9031999-03-30030 March 1999 Safety Evaluation Supporting Proposed Rev to BSEP RERP to Licenses DPR-62 & DPR-71,respectively ML20206N1831999-02-28028 February 1999 Rev 0 to Suppl Reload Licensing Rept for Bsep,Unit 2 Reload 13 Cycle 14 BSEP-99-0043, Monthly Operating Repts for Feb 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20203D7061999-02-0909 February 1999 SER Accepting Proposed Alternatives Contained in Relief Requests PRR-04,VRR-04,VRR-13,PRR-01,PRR-03,VRR-01.VRR-07, VRR-08 & VRR-09 Denied BSEP-99-0005, Monthly Operating Repts for Dec 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With BSEP-98-0231, Monthly Operating Repts for Nov 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With BSEP-98-0218, Monthly Operating Repts for Oct 1998 for Bsep,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Bsep,Units 1 & 2. with BSEP-98-0210, Special Rept:On 980824,temp Element 2-CAC-TE-1258-22 Failed. Cause of Failed Temp Element Cannot Be Conclusively Determined.Temp Element Will Be Replaced & Cable Connections Repaired1998-10-30030 October 1998 Special Rept:On 980824,temp Element 2-CAC-TE-1258-22 Failed. Cause of Failed Temp Element Cannot Be Conclusively Determined.Temp Element Will Be Replaced & Cable Connections Repaired ML20154P8151998-10-16016 October 1998 SER Accepting Revised Safety Analysis of Operational Transient of 920117,for Plant,Unit 1 ML20154P8591998-10-16016 October 1998 SER Accepting Equivalent Margins Analysis for N-16A/B Instrument Nozzles for Plant,Units 1 & 2 BSEP-98-0202, Monthly Operating Repts for Sept 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20151Y6211998-09-14014 September 1998 BSEP Rept Describing Changes,Tests & Experiments, for Bsep,Units 1 & 2 ML20151Y6371998-09-14014 September 1998 Changes to QA Program, for Bsep,Units 1 & 2 BSEP-98-0185, Monthly Operating Repts for Aug 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20151T5021998-08-0505 August 1998 Project Implementation Plan, Ngg Yr 2000 Readiness Program, Rev 2 BSEP-98-0164, Monthly Operating Repts for July 1998 for BSEP Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for BSEP Units 1 & 2 ML20236T1961998-07-0101 July 1998 Rev 1 to 2B21-0088, Brunswick Unit 2,Cycle 13 Colr ML20236T1921998-07-0101 July 1998 Rev 1 to 1B21-0537, Brunswick Unit 1,Cycle 12 Colr BSEP-98-0142, Monthly Operating Repts for June 1998 for BSEP Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for BSEP Units 1 & 2 ML20236T1971998-06-30030 June 1998 Rev 2 to 24A5412, Supplemental Reload Licensing Rept for Brunswick Steam Electric Plant Unit 2 Reload 12 Cycle 13 ML20249B9691998-06-11011 June 1998 Rev 1 to VC44.F02, Brunswick Steam Electric Plant,Units 1 & 2,ECCS Suction Strainers Replacement Project,Nrc Bulletin 96-003 Final Rept BSEP-98-0129, Monthly Operating Repts for May 1998 for Bsep,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Bsep,Units 1 & 2 ML20151S9041998-05-31031 May 1998 Revised Pages to Monthly Operating Rept for May 1998 for Brunswick Steam Electric Plant,Unit 1 BSEP-98-0104, Monthly Operating Repts for Apr 1998 for Brunswick Steam Electric Plant,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Brunswick Steam Electric Plant,Units 1 & 2 ML20151S8991998-04-30030 April 1998 Revised Pages to Monthly Operating Rept for Apr 1998 for Brunswick Steam Electric Plant,Unit 1 ML20247N7501998-04-30030 April 1998 Rev 0 to BSEP Unit 1,Cycle 12 Colr ML20247N7721998-04-30030 April 1998 Rev 0 to J1103244SRLR, Supplemental Reload Licensing Rept for BSEP Unit 1,Reload 11,Cycle 12 ML20217K8461998-04-24024 April 1998 Safety Evaluation Approving Proposed Use of Code Case N-535 at Brunswick Unit 1 During Second 10-yr Interval,Pursuant to 10CFR50.55a(a)(3)(i).Authorizes Use of Code Case N-535 Until Code Case Included in Future Rev of RG 1.147 ML20217K3941998-04-24024 April 1998 SER Approving Relief Request for Pump Vibration Monitoring, Brunswick Steam Electric Plant,Units 1 & 2 ML20217E6841998-04-23023 April 1998 Safety Evaluation Accepting Code Case N-547, Alternative Exam Requirements for Pressure Retaining Bolting of CRD Housings ML20217E7471998-04-21021 April 1998 Safety Evaluation Accepting Alternative to Insp of Reactor Pressure Vessel Circumferential Welds ML20217B5241998-04-20020 April 1998 SE Accepting Licensee Request for Approval to Use Alternative Exam Requirement for Brunswick,Unit 1,reactor Vessel Stud & Bushing During Second 10-yr ISI Interval Per 10CFR50.55a(a)(3)(ii) BSEP-98-0080, Monthly Operating Repts for Mar 1998 for Bsep,Units 1 & 21998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Bsep,Units 1 & 2 ML20216B1041998-03-0404 March 1998 SER Approving Alternative to Insp of Reactor Pressure Vessel Circumferential Welds for Brunswick Steam Electric Plant, Unit 1 1999-09-30
[Table view] |
Text
_ _ _ _ _ _ _ - _ - - . _ . - _ _ - . _ _ - . __ - _ . - - _ - _ _ - - - . , _ -
3 o UNITED STATES
, g l[-
3 g
E NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 '
A...../
U SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO INSPECTIONS AND REPAIRS OF INTERGRANULAR STRESS CORROSION CRACKING (IGSCC)
CAROLINA POWER & LIGHT COMPANY, et al.
BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 DOCKET NO. 50-324
1.0 INTRODUCTION
The. staff has reviewed the licensee's submittals dated October 2 and December 30 1987 and March 25, 1988, including the inspection results, IGSCC mitigation, flaw evaluations and overlay repairs to support the con-tinued operation of Brunswick Steam Electric Plant, Unit 2, (Unit 2) in its present configuration for one 18-month fuel cycle. During the Unit 2 refuel 7 outage, 81 Class 1 piping welds, including 16 Inconel 182 buttered' nozzle welds and 10 recirculation inlet safe-end thermal. sleeve attachment welds,;were ultrasonically examined.
The results of the inspection showed that flaw indications were observed in a pipe to elbow weld (12ARD2) and a safe-end to nozzle weld (12ARE5) in the recirculation riser piping system. These two welds were reinforced with standard designed weld overlay. Three previously overlay repaired welds (28A4, 2883 and 2884) were upgraded to meet the standard design-requirements, and their surface finishes were improved to facilitate ultra-sonic inspection. For the two previously unrepaired suction safe end-to- I nozzle welds (28A1 and 2881) in the recirculation piping system, the existing flaws were reported to have no change in sizes; however, a new i small axial indication was found in weld 2881. Mechanical stress improve-ment process (MSIP) was applied to these two welds and 13 other Inconel 182 buttered nozzle welds as a mitigation for IGSCC.
A through wall leak was found in one of the jet pump instrumentation (JPI) penetration seal connection welds. This weld was reinforced with addit-ional weld metal. All other 23 JPI penetration welds were examined, and no flaws were found.
I 2.0 . DISCUSSION j Inspection The licensee reported that there are 180 Class 1 piping welds in Unit 2 l subject to IGSCC inspection. 44 of these welds are made of IGSCC resistant l material and no sample was selected from these welds for inspection. 81 l
C P
9:
J i : -
welds were inspected during refuel 7 outage of Unit 2, which included ,
j 16 Inconel 182 buttered nnzle welds,10 riser thermal sleeve-to-safe end attachment walds and 21 overlay repaired welds. The original sample size of 72 welds was detemined in accordance with the guidelines in NUREG-0313 Revision 2, and was expanded to 80 welds after flaws were found in the original-samples.
The staff concludes that the inspection scope for Class 1 piping meets the staff requirements and the guidelines in Generic Letter 88-01 since more than 50% of the IGSCC susceptible welds were insp0cted during this outage.
The staff also concludes that the limited sacale npansion is acceptable because all the welds with configuration or stas imilar to the two welds found flawed during this outage were inspected.
Ultrasonic Examination The Centerlicensee qualified reported personnel that thethe from IGSCC inspection General was perfomed Electric Company by)EPRI NDE (GE . These examiners also passed the latest requalification program. The fully auto-mated GE " SMART" ultrasonic testing (UT) system was used for examination, where geometrically feasible. The automatic system utilizes the Ultra Image III computer-driven data acquisition system with the ALARA remote scanning device. Manual examinations were perfonned where automatic UT could not be performed. The sizing of IGSCC indications was performed using 2 to 5 MHz refracted longitudinal transducers. The sizing methods used included satellite pulse observation technique (SPOT), pulse arrival time technique (PATT) ID and OD creeping wave technique, and tip diffraction techniques, as applicable.
During this outage, flaw indications were found its tw recirculation riser welds (12ARD2 and 12 ARES). Both flawed welds were overlay repaired. An axial flaw with 0.8 inch in length and a maximum depth of 605 through-wall was reported in weld 12ARD2 (pipe to elbow). Since weld 12AR02 was previous-ly treated with induction heating stress improvement (IHSI), the reported cracking of this weld after IHSI has raised some concern regarding the ef-festiveness of INSI in mitigating IGSCC. Therefore, the staff recommends that the licensee should inspect these IHSI treated welds with increased sampling during the next few refueling outages to ensure the structural integrity of these piping aids. In the safe end-to-nozzle weld 12 ARES, the major extent of the reported flat; wh located in the Inconel 182 butter adjacent to the nozzle. The length of the flaw was 4.8 inches with a maxi-mum throughwall depth of 85%. The UT data have shown that the flaw appeared to be initiated from the Inconel 182 butter and may have penetrated the
" nose" of the low alloy steel nozzle while growing toward the safe end-to-nozzle weld. Limited examinations were performed on weld 12 ARES in 1984 and 1986;.a portion of the flaw was detected in 1984 but was characterized as an embedded defect.
Two unrepaired suction safe end-to-nozzle welds (28A1 and 2881) were re-examined during this outage. The inspection results showed that the exist-ing flaws (one axial flaw in each weld) did not change in size (about 0.3
inch in length and a maximum deptn of 0.25 inch) after operation of one fuel cycle. However, a new axial flaw (0.2 inch 'in length and 0.2 inch in maxi-mum depth) was found in weld 2881. Both welds were treated with mechanical J stress improvement process (MSIP) during this outage for IGSCC mitigation. l NRC Region II inspector selectively reviewed the ultrasonic examination procedures and data, and held discussions with the examiners regarding the non-destructive examinations performed during the refuel 7 outage. The inspector concluded in his report numbered 50-325/88-02 and 50-324/88-02, dated March 11, 1988, that nondestructive examinations were performed by qualified personnel and that no violations of NRC requirements were identi -
fied.
Flaw Evaluation Two 28-inch safe end-to-nozzle welds (28A1 and 2881) were found to contain a small axial flaw during the last refuel outage. The flaws were located in the Inconel 182 butters with a maximum depth of 0.25 inch and a length of 0.25 and 0.3 inch in welds 28A1 and 2881, respectively. Fracture mechanics and crack growth evaluations performed during the last outage had shown that these flaws were acceptable without repair for at least an 18-month fuel cycle of operation. As stated above, the results of current inspections have shown that these axial flaws did not grow in size after operation of one fuel cycle. However, a new axial flaw with a length of 0.2 inch and a maximum depth of 0.2 inch was found in weld 2881. The new flaw was. located about 16 inches azimuthally from the original flaw. Since the new flaw was smaller than the original flaws.. its potential growth is bounded by the previous calculations per-formed for the original flaws. Mechanical Stress Improvement Process (MSIP) was appled to these two welds 'during this outage to mitigate the IGSCC. Therefore, we conclude that welds 28A1 and 2881 are acceptable for operation of at least an 18-month fuel cycle in its present configuration.
Tn embedded circumferential flaws were found in the weld overlay of weld 2883 after completion of overlay upgrade and surface finish improvement.
One flaw is 7.2 inches long and 0.1 inch wide and has the characteristics of lack of bonding of overlay to the base metal.. The other flaw is 0.3 inch long and 0.1 inch in through-wall dimension and has the characteristics of lack of fusion of interbead. The Ifcensee performed flaw evaluation in accordance with the requirements of ASNE Code Section XI, IWB-3500. The results of the evaluation have shown that these flaws are acceptable without repair.
The staff concludes that these flaw evaluations are acceptable.
Weld Overlay Repair During this outage, two new weld overlays with standard design were applied to welds 12ARD2 and 12ARE5; and three previously overlay repaired welds 28A4, 28B3 and 2884 were upgraded to meet the requirements of standard
n !
< ( l overlay design and improved in the surface finish to facilitate ultrasonic examination. Structrual Integrity Associates, Inc., (SIA) performed the overlay design for the licensee. The designed minimum overlay thickness does not include the first overlay layer that passed the dye penetrant exam-ination. The licensee reported that the as-built overlay thickness in these welds exceeds the minimum designed dimensions. SIA has evaluated the weld overlay shrinkage induced stresses in the recirculation piping system, as a result of 41 weld overlay repairs. The largest shrinkage stress on un-flawed welds was reported to be 8743 psi on weld 12AREl, which is within the ASME Code allowable.
A composite Inconel weld overlay was designed for weld 12ARE5 (safe end-to-nozzle). The downstream side of the overlay was extended into the nozzle for covering the flaw in the butter and the nozzle. At the nozzle side of the overlay, the first three layers were deposited by a qualified Inconel temper bead technique. The piping was running dry while depositing the temper bead layers. The temper bead technique has been demonstrated to provide adequate tempering of the heat affected areas of the low alloy steel materials. The designed overlay thickness did not include the intial three temper bead layers. After depositing the temper bead layers, the normal overlay repair technique with water running in the pipe was used for fabri-cating the rest of the overlay. The Inconel temper bead-technique was deve-loped by EPRI for weld overlay repair of P-3 components to preclude the post-weld heat treatment. The repair procedures were established in accor-dance with the requirements in AS4E Code Section XI and Code Case N-432.
Mechanical testing including tensile, bending, hardness and toughness tests were performed on a 12-inch nozzle mock-up to confirm that the simulated Inconel overlay repair met the Code requirements.
Because extensive cracking was recently reported in the recirculation riser nozzles and the thermal sleeve to safe-end attachment welds at Brunswick Unit 1, the staff recomunends that this weld overlay repaired weld (12 ARES) and the associated thermal sleeve attachment weld should be inspected dort.g next refueling outage to ensure that the integrity of the safe-end and nozzle is maintained.
Weld reinforcement was applied to the fillet socket weld of a 3/4-inch JPI penetration seal connection joint. This weld joint was found leaking during this outage. The repair consisted of applying a minimum of 0.17 inch weld metal on the penetration fitting side and 0.375 inch on the tube side. The reported thickness of the repair weld exceeded that of the original fillet weld. The liquid penetrant examination was performed after repair and no surface defect was found.
The staff concludes that the weld overlay repairs performed during this out-age are acceptable for at least an 18-month fuel cycle. The staff also concludes that the repair of a leaking JPI penetration seal weld is accept-able for continued service.
~
.c
>4
-S-Mechancial Stress Improvement Process (MSIP)
O'Donnel and Associates, Inc. (00AI) performed MSIP for the licensee on 15 Inconel buttered nozzle-to-safe end welds which consist of two 28-inch re-circulation outlet nozzle welds, nine 12-inch recirculation inlet nozzle welds, two 10-inch core spray nozzle welds and two 4-inch JPI nozzle welds.
MSIP is a mechanical process that replaces tensile residual stresses on the inside surface of the piping in the vicinity of welds with a zone of compres-sive residual stresses. The MSIP processes applied to different sizes of riozzle welds were analytically verified by 00AI using a nonlinear finite element analysis of the processes to show that the permanent strain induced i by MSIP in the range of 0.5% to 1.195 is adequate and would produce the de-sired redistribution of the residual stresses. The ultrasonic examination was performed on each weld before and after MSIP, No additional flaws were observed other than those already reported in two 28-inch nozzle welds.
Based on the licensee's submittals, the staff notes that the MSIP process applied to the nozzle-to-safe end welds was only analytically verified with-out being validated by a confirmation test on a mock-up with similar safe end-to-nozzle configuration. Because of limited field experience, the staff .
has.some reservation regarding the effectiveness of this particular applica- )
tion. Furthermore, the recent Unit 1 inspection results have shown that extensive cracking was found in 7 recirculation riser nozzles and 10 thermal sleeve-to-safe end attachment welds. Therefore, the staff recomends that these MSIP treated nozzle welds and the associated thermal sleeve-to-safe end. attachment welds be int,pected with increased sampling during the next several refueling outages to ensure that the integrity of the nozzles and safe-ends is maintained.
In NUREG 0313, Revision 2, the stress improvement (SI) process including MSIP is considered effective in mitigating IGSCC for welds with no flaws or with only minor circumferential flaws. SI credit for inspection is not allowed for welds with axial flaws because there are uncertainties in the sizing of the axial flaws. Therefore, MSIP treated welds 28A1 and 2881 containing axial flaws should be inspected in accordance with the IGSCC Category F schedule. After successful completion of four consecutive inspections, these welds may be moved up to Category E.
Special Surveillance Measures The licensee indicated that the following special surveillance measures for unidentified leakage will continue to be implemented at Unit 2:
(1) Plant shutdown shall be initiated when, within any period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, an increase in the rate of unidentified leakage in excess of 2 gpm is identified.
(2) The leakage shall be monitored at 4-hour intervals or less.
(3) The outage time for inoserable instruments for leakage measurements shall be limited to 24 tours. Otherwise, an orderly shutdown will be !
ionediately initiated.
i
i i,.'
The staff finds that these special surveillance measures are consistent with the guidelines in Generic Letter 88-01.
3.0 Conclusion Based upon the staff's review of the licensee's submittals, the staff con-cludes that the licensee has adequately addressed IGSCC in Class 1 piping with respect to inspections, repairs and litigations performed during the Unit 2 refuel 7 outage, and that these activities were performed in accordance with the guidelines in Generic Letter 88-01. In addition, the staff also concludes that Unit 2 can be safely operated for another 18-month fuel cycle in the present configuration.
Principal Contributor: W. Koo I
l l
- _ _ _ _ _ - - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ l