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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20210K4721999-08-0303 August 1999 SER Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20206A2111999-04-21021 April 1999 Safety Evaluation Authorizing Pump Relief Request PRR-001 & Valve Relief Request VRR-001 & Denying Valve Relief Request VRR-002 ML20205D5481999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Exam Weld AA with Weld Volume Coverage of 62 Percent for First 10-year Insp Interval Pursuant to 10CFR50.55a(a)(3)(ii) & 10CFR50.55a(g)(6)(ii)(A)(5) ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program ML20155H3491998-11-0303 November 1998 Safety Evaluation Granting Requests for Relief RR2-0001, RR2-0002 & RR2-0003 ML20151S5421998-09-0303 September 1998 Safety Evaluation Opposing Licensee Thermal Model as Currently Implemented.Evaluation Recommended to Be Used in Any follow-up Site Insp ML20249A6431998-06-12012 June 1998 SER Accepting 980427 Request for Change to River Bend QA Manual Program Description,Per 10CFR50.54(a)(3) ML20217P8281998-04-0707 April 1998 Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i) ML20202F0191997-11-28028 November 1997 Safety Evaluation Approving Transfer of License NPF-47 for River Bend Station,Unit 1 ML20199H3711997-11-19019 November 1997 SER Accepting Approving Request Relief from Requirements of Section XI, Rule for Inservice Insp of NPP Components, of ASME for Current or New 10-year Inservice Insp Interval IAW 50.55(a)(3)(i) of 10CFR50 ML20216E9921997-09-0404 September 1997 Safety Evaluation Accepting 970623 Request for Relief Re Authorization for Use of ASME Code Case N-416-1 & N-532,ISI Program for Listed Plants ML20141H8411997-07-30030 July 1997 Safety Evaluation Accepting Use of Code Case N-508-1 for All Four Plants for Rotation of Serviced Snubbers & Pressure Relief Valves for Purpose of Testing in Lieu of ASME Code ML20138C8501997-04-28028 April 1997 Safety Evaluation Authorizing Proposed Alternative to Vibration Measurement Requirements of OM-6,paragraph 4.6.4 (B),For Standby Svc Water Pumps & Diesel Fuel Oil Transfer Pumps,Per 10CFR50.55a(a)(3)(ii) ML20147H4371997-03-31031 March 1997 Safety Evaluation Accepting Proposed P-T Limits for Heatup, Cooldown,Inservice Leak & Hydrostatic Testing & Core Criticality ML20149M4221996-12-12012 December 1996 Safety Evaluation Supporting Update Insvc Insp Programs to 1992 & Portions of 1993 ASME Boiler & Pressure Vessel Code, Sect XI for Licenses DPR-51,NPF-6,NPF-38,NPF-29 & NPF-47. Technical Ltr Rept Encl ML20107F5611996-04-17017 April 1996 Safety Evaluation Providing Guidance on Submitting plant- Specific Info W/Respect to IST Program Alternatives Request ML20149E8831994-08-0202 August 1994 Safety Evaluation Accepting Interim Relief Request IRR-03 Re Drywell Isolation Check Valves in Equipment Drain Lines & Reactor Equipment Closed Cooling Water Sys ML20058H0221993-11-30030 November 1993 Safety Evaluation Accepting Licensee Proposed Alternative to ASME Code Requirements in PRR 15,per 10CFR50.55(a)(3)(i). Denies Pump Relief Request 14 ML20059B2771993-10-22022 October 1993 Safety Evaluation Accepting IST Program Relief Requests ML20056G2001993-08-19019 August 1993 Safety Evaluation Denying 930419 Request for Relief from Requirements for Hydrostatic Testing of ASME Class 3 Pressure Retaining Components ML20126A2971992-12-16016 December 1992 Safety Evaluation Accepting Design for Drywell Hydrogen Concentration & Suppression Pool Water Level,W/Respect to Reg Guide 1.97 ML20128D2251992-12-0202 December 1992 Safety Evaluation Accepting Methodology Described in Topical Rept EA-CA-91-0001-M, Steady State Core Physics Methods for BWR Designs & Analysis ML20055F1891990-06-27027 June 1990 Safety Evaluation Supporting Util Tech Spec Change Request Re Scram Accumulator Check Valves ML20245A1051989-06-15015 June 1989 Safety Evaluation Accepting Util 890515 & 19 Submittals Re Results of Augmented IGSCC Insp & Flaw Evaluation of Feedwater Inlet Nozzle N4-A to Safe End Weld ML20247J7411989-05-25025 May 1989 Safety Evaluation Accepting Existing Intervals for on-line Functional Testing for Achieving High Reactor Trip Sys Reliability at All Operating Reactors,Per Generic Ltr 83-28, Item 4.5.3 ML20235N6031989-02-21021 February 1989 Safety Evaluation Approving Alternate Method for Complying w/10CFR50.55a for Main Steam Positive Leakage Control Sys Valve ML20195H1511988-11-23023 November 1988 Safety Evaluation Accepting Responses Re Item 4.5.2 of Generic Ltr 83-28 Re Reactor Trip Sys Reliability on-line Testing ML20196A6611988-11-18018 November 1988 SER Accepting Util Response to Generic Ltr 83-28,Item 2.1, Part 2 Re Vendor Interface Programs for Reactor Trip Sys Components ML20195G8861988-11-18018 November 1988 SER Accepting Util Responses to Generic Ltr 83-28,Item 2.1, Part 1 Re Reactor Trip Sys Components ML20154M6561988-09-22022 September 1988 Safety Evaluation Supporting Licensee post-trip Review Program & Procedures Per Generic Ltr 83-28,Item 1.1 Re Generic Implications for Salem ATWS Events ML20151Q4701988-08-0101 August 1988 Supplemental Safety Evaluation Re First 10-yr Inservice Insp Program.Nrc Concurs W/Determination Made by Licensee That Section XI of ASME Code Exam Requirements for Category B-A Welds in Reactor Pressure Vessel Are Impractical to Perform ML20150F9501988-07-12012 July 1988 Safety Evaluation Supporting Util 840803 & 870922 Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1 & 3.2.2 Re post-maint Testing of All safety-related Components ML20148D4391988-01-14014 January 1988 Safety Evaluation Supporting Util 870731 & 1030 Submittals on Facility Compliance Re Alternate Rod Injection & Recirculation Pump Trip Sys,Per ATWS Rule 10CFR50.62 ML20236D1851987-10-20020 October 1987 Safety Evaluation Accepting Util 870602 Rev 2 to First 10-yr Interval Inservice Insp Program ML20235K6871987-09-28028 September 1987 Safety Evaluation Accepting Util Monitoring Sys for UHS as Proposed in NUREG-0989, Safety Evaluation Supporting Proposed Turbine Maint Program. Proposal Satisfies Licensee Commitment Prescribed in Sser 5. Commitment Acceptable Resolution of Turbine Maint Issue1987-08-26026 August 1987 Safety Evaluation Supporting Proposed Turbine Maint Program. Proposal Satisfies Licensee Commitment Prescribed in Sser 5. Commitment Acceptable Resolution of Turbine Maint Issue ML20209B4291987-04-22022 April 1987 Safety Evaluation Supporting Util Proposed Rev to Tech Specs Re Drywell Leakage Test Interval ML20234E0491987-03-26026 March 1987 SER Accepting Response to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing of Reactor Trip Sys & All Other safety-related Components ML20205M3691987-03-26026 March 1987 Sser Re Mark III Containment Related Issues ML20212L2351987-01-21021 January 1987 Sser Re Util 860512 & 1119 Rev 4 to Preservice Insp Program & Relief Request R 0012 (a to E) from Certain ASME Code Requirements.Relief Granted.Preservice Insp Program in Compliance w/10CFR50.55a(g)(3) ML20203N7061986-10-0909 October 1986 Safety Evaluation Supporting Amend 2 to License NPF-47 ML20214P2061986-09-19019 September 1986 SER Supporting 860917 & 19 Requests for Amend to License NPF-40,changing Tech Spec Table 3.6.4-1 to Allow Inoperability of Inboard Isolation Valve MOVFO76 Through 861004 ML20207H4151986-07-16016 July 1986 Safety Evaluation Supporting Technical Solution to Address Operability & Reliability of Tdi Emergency Diesel Generators ML20133F8241985-08-0505 August 1985 Marked-up Draft Sser 2 Re Application for Ol,Reporting Status of Certain Items Not Resolved at Time of SER Publication 1999-08-03
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARRBG-45144, Monthly Operating Rept for Sept 1999 for River Bend Station. with1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for River Bend Station. with ML20216G1201999-09-0909 September 1999 Rev 3 to Rbs,Cycle 9 Colr RBG-45110, Monthly Operating Rept for Aug 1999 for River Bend Station, Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for River Bend Station, Unit 1.With RBG-45087, Special Rept:On 990510,LPCI a & LPCS Injected Into Rv for Less than Two Minutes.Caused by Electrical Transient in One of ECCS Power Supplies.Operators Verified Reactor Cavity Level & Closed Injection Valves to Stop Injection1999-08-0606 August 1999 Special Rept:On 990510,LPCI a & LPCS Injected Into Rv for Less than Two Minutes.Caused by Electrical Transient in One of ECCS Power Supplies.Operators Verified Reactor Cavity Level & Closed Injection Valves to Stop Injection ML20210K4721999-08-0303 August 1999 SER Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves RBG-45091, Monthly Operating Rept for July 1999 for River Bend Station, Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for River Bend Station, Unit 1.With ML20210C6391999-07-0202 July 1999 Rev 2 to River Bend Station,Cycle 9 Colr RBG-45055, Monthly Operating Rept for June 1999 for River Bend Station, Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for River Bend Station, Unit 1.With ML20196J8031999-06-24024 June 1999 Rev 1 to Rbs,Cycle 9 Colr RBG-45028, Monthly Operating Rept for May 1999 for River Bend Station, Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for River Bend Station, Unit 1.With RBG-45016, Monthly Operating Rept for Apr 1999 for River Bend Station, Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for River Bend Station, Unit 1.With ML20206A2111999-04-21021 April 1999 Safety Evaluation Authorizing Pump Relief Request PRR-001 & Valve Relief Request VRR-001 & Denying Valve Relief Request VRR-002 RBG-44969, Monthly Operating Rept for Mar 1999 for River Bend Station, Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for River Bend Station, Unit 1.With ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20205D5481999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Exam Weld AA with Weld Volume Coverage of 62 Percent for First 10-year Insp Interval Pursuant to 10CFR50.55a(a)(3)(ii) & 10CFR50.55a(g)(6)(ii)(A)(5) RBG-44930, Monthly Operating Rept for Feb 1999 for River Bend Station, Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for River Bend Station, Unit 1.With RBG-44826, Monthly Operating Rept for Dec 1998 for River Bend Station Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for River Bend Station Unit 1.With ML20198K2701998-12-22022 December 1998 Rev 1 to RBS Cycle 8 Colr RBG-44773, Monthly Operating Rept for Nov 1998 for River Bend Station, Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for River Bend Station, Unit 1.With RBG-44727, LER 98-S01-00:on 981021,identified That Contract Employee with Temporary Access Authorization Failed to Disclose Complete Criminal & Employment History.Individual Denied Access to Plants for Five Years.With1998-11-17017 November 1998 LER 98-S01-00:on 981021,identified That Contract Employee with Temporary Access Authorization Failed to Disclose Complete Criminal & Employment History.Individual Denied Access to Plants for Five Years.With ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program ML20155H3491998-11-0303 November 1998 Safety Evaluation Granting Requests for Relief RR2-0001, RR2-0002 & RR2-0003 RBG-44719, Monthly Operating Rept for Oct 1998 for River Bend Station, Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for River Bend Station, Unit 1.With ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual RBG-44677, Monthly Operating Rept for Sept 1998 for River Bend Station, Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for River Bend Station, Unit 1.With ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods ML20151S5421998-09-0303 September 1998 Safety Evaluation Opposing Licensee Thermal Model as Currently Implemented.Evaluation Recommended to Be Used in Any follow-up Site Insp RBG-44629, Monthly Operating Rept for Aug 1998 for River Bend Station, Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for River Bend Station, Unit 1.With ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed RBG-44600, Monthly Operating Rept for July 1998 for River Bend Station1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for River Bend Station RBG-44564, Monthly Operating Rept for June 1998 for River Bend Station, Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for River Bend Station, Unit 1 ML20249A6431998-06-12012 June 1998 SER Accepting 980427 Request for Change to River Bend QA Manual Program Description,Per 10CFR50.54(a)(3) RBG-44539, Monthly Operating Rept for May 1998 for River Bend Station, Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for River Bend Station, Unit 1 RBG-44501, Monthly Operating Rept for Apr 1998 for River Bend Station, Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for River Bend Station, Unit 1 ML20217M8951998-04-30030 April 1998 QA Program Manual ML20217P8281998-04-0707 April 1998 Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i) RBG-44458, Monthly Operating Rept for Mar 1998 for River Bend Station, Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for River Bend Station, Unit 1 RBG-44423, Monthly Operating Rept for Feb 1998 for River Bend Station Unit 11998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for River Bend Station Unit 1 ML20203L6631998-02-11011 February 1998 Rev 0 to River Bend Station,1998 Emergency Preparedness Exercise RBG-44385, Monthly Operating Rept for Jan 1998 for River Bend Station, Unit 11998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for River Bend Station, Unit 1 RBG-44353, Monthly Operating Rept for Dec 1997 for River Bend Station, Unit 11997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for River Bend Station, Unit 1 RBG-44460, Forwards Annual Radiological Environmental Operating Rept, for Period Jan-Dec 19971997-12-31031 December 1997 Forwards Annual Radiological Environmental Operating Rept, for Period Jan-Dec 1997 ML20203H9891997-12-12012 December 1997 Part 21 Rept Re Potential Manufacturing Defect of Enterprise DSR-4 & DSRV-4 Edgs.Cooper Energy Svcs Supplied 1A-7840 Adjusting Screw to Affected Utils & Sites.River Bend Station Replaced W/Acceptable Assemblies ML20202E9941997-12-0101 December 1997 ISI Plan Second Ten-Yr Interval (Dec 1,1997-Nov 30,2007) ML20199K9741997-11-30030 November 1997 Brief Aerial Photography Analysis of RBS at St Francisville,LA:1996-1997 RBG-44337, Monthly Operating Rept for Nov 1997 for River Bend Station, Unit 11997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for River Bend Station, Unit 1 ML20202F0191997-11-28028 November 1997 Safety Evaluation Approving Transfer of License NPF-47 for River Bend Station,Unit 1 ML20199H3711997-11-19019 November 1997 SER Accepting Approving Request Relief from Requirements of Section XI, Rule for Inservice Insp of NPP Components, of ASME for Current or New 10-year Inservice Insp Interval IAW 50.55(a)(3)(i) of 10CFR50 RBG-44295, Monthly Operating Rept for Oct 1997 for River Bend Station Unit 11997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for River Bend Station Unit 1 RBG-44243, LER 97-S03-00:on 970911,contract Employee Was Granted Temporary Access After Failing to List Prior Employment Termination & Access Denial.Caused by Employee Failure to Provide Accurate Info.Updated Info Re Employee1997-10-13013 October 1997 LER 97-S03-00:on 970911,contract Employee Was Granted Temporary Access After Failing to List Prior Employment Termination & Access Denial.Caused by Employee Failure to Provide Accurate Info.Updated Info Re Employee 1999-09-09
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'o UNITED STATES
!' o NUCLEAR REGULATORY COMMISSION l
( WASHINGTON, D. C 20655 I
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SUPPLEMENTALSAFETYEVALUATIONBY_THEOFFICE_0FNUg. EAR __REACTORREGULATION ON THE FIRST TEN-YLAR INSERVICE INSPECTION PROGRAM GULFSTAJESUTILITIESCOMPANY l RIV_ER_ REND STATION, UNIT _1 DOCKET NO. 50-458 INTRODUCTION Gulf States Utilities Company, the licensee, prepared the first Ten-Year Interval Inservice Inspection (ISI) Program for the River Bend Station, Unit 1, Revision 2, to meet the requirements of the 1980 Edition, Winter 1981 Addenda of Section XI of the ASME Boiler and Pressure Vessel Code except that the extent of exami-nation for Class 2 piping welds in the Residual Heat. Removal (RHR) and Emergency Core Cooling (ECC) Systems was determined by the requirements of the 1974 Edition, Sumrer 1975 Addenda of Section XI of the ASME Boiler and Pressure Vessel Code. The first inspection interval began on June 16, 1586 and ends June 16, 1996.
The information in the River Bend Station, Unit 1 first Ten-Year Interval ISI Progran, through Revision 1, submitted July 16, 1986 was reviewed including the requests for relief from the ASME Code Section XI requirements which the licensee has determined to be impractical. The review was perforned using the Standard Review Plan, NUREG-0800, Section 5.2.4, "Reactor Coolant Boundary Inservice Inspections and Testing," and Section 6.6, "Inservice Inspection of Class 2 and 3 Components." In a letter dated January 21, 1987, the staff .
requested additional information that was required in order to complete the review of the ISI Program. The requested information was provided and Revision 2 of the ISI Program was submitted by the licensee in letters dated Febuary 27, 1987, March 10, 1987, and June 2, 1987.
The NRC staff, with technical assistance from its contractor, Idaho National Engineering Laboratory (INEL), evaluated the ISI program and found it acceptable and in compliance with 10 CFR 50.55a(g)(4). The staff's evalutation was issued on October 20, 1987. The ISI program was evaluated for (a) compliance with the appropriateASMECodeeditionandaddenda,(b)acceptabilityoftheexamina-tion sample, (c) exclusion criteria, and (d) compliance with ISI related conmitments identified during the review for the Operating License. The request for relief from the requirements of Section XI of the ASME Code was reviewed and evaluated by our contractor. The staff concurred with the contrac-tor's evaluation except that relief was not granted for Category B-A welds in the examination of the reactor pressure vessel because the procedure for the examination of these welds was under review by the staff.
On February 17-18, 1988, the staff and INEL personnel met with representatives of Gulf States Utilities Company to discuss the relief requests not granted on o169 esoeo1 h81jDOCK03000458 P
PDC
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.. Category B-A reactor pressure vessel welds in our Safety Evaluation of October 20, 1987, and the procedures used for inspecting the reactor pressure vessel at the River Bend Station, Unit 1. Gulf States Utilities Company re-quested that the NRC recensider the requests for relief from the requirements of Section XI in view of the additional information discussed at the February 17-18, 1988 meeting.
EVALUATION l The licensee's submittals were evaluated as follows:
RELIEF REQUEST RR0012A COMPONENT -
Reactor pressure vessel longitudinal shell weld BG, i Category B-A CODE -
Weld was fabricated in accordance with ASME Section III Class I requirement. Inservice inspection will be in i accordance with ASME Section XI 1980 Edition, including l Winter 1981 Addenda '
I REQUIREMENT -
Longitudinal shell welds will be 100% volumetrically examined in accordance with IWB-2500-1, Category B-A, ,
Item Bl.1? l l
BASIS FOR REQUEST -
Inservice volumetric inspection coverage of longitudinal '
shell weld BG will be reduced at an adjacent nozzle due to interference with the automated ultrasonic inspection equipment. Complete preservice ultrasonic examination coverage was achieved for transverse reflectors for longitudinal shell weld BG. Coverage for parallel re-flectors included 100% of the weld and was approximately 95% for adjacent metal in the 1/2 t zone due to inter-ference with the automatic examination equipment caused by adjacent nozzle. The inservice inspection coverage for weld BG will be the same as that cbtained during the preservice ultrasonic examination of the weld.
Completion of the remaining portion of the required examination is impractical and would result in undue hardship without a compensating increase in safety.
CONCLUSION -
The volumetric examination of the subject weld is impractical because of the interference caused by a nozzle adjacent to the weld. A significant percentage of the inservice volumetric examination will be performed.
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Therefore, the limited Section XI ultrasonic examination l provides an acceptable level of inservice structural l integrity and compliance with the specific require- l ments of Section XI would result in hardship or unusual ;
difficulties without a compensating increase in the l 1evel of quality and safety. !
RELIEF REQUEST RR0012C COMPONENT -
Reactor pressure vessel circumferential shell weld AB, Category B-A CODE -
The reactor vessel shell weld AB was fabricated in !
accordance with ASME Section III Class 1 requirements. I Inservice inspections will be performed in accordance l with ASME Section XI 1980 Edition, including Winter 1981 Addenda.
REQUIREMENT -
Reactor vessel shell weld AB will be 100% volumetric examined for inservice inspection in accordance with ASME Section XI, IWB-2500-1, Category B-A, Item B1.11.
BASIS FOR REQUEST -
The reactor vessel circumferential shell weld AB is located in a beveled area, i.e., a transition in wall thickness. Due to the physical geometry of the weld, it is not possible to pass an automated examination head over the weld and maintain couplant and transducer orientation.
During the preservice ultrasonic examination of weld AB, the automated coverage was supplemented by manual ultrasonic inspection and full coverage of weld AB was obtair,ed.
During inservice ultrasonic examination of weld AB, high radiation levels will prohibit manual UT examina- ,
tion, and coverage will be limited to that which can be obtained by automated UT examination. It is estimated that for parallel reflectors, the root of the weld and l approximately 67% of the remaining weld metal will be ;
examined by both 45' and 60 angle beams from both sides of weld AB. For transverse reflectors, virtually no coverage of the weld metal will be obtained, and approximately 90% of the adjacent metal will be examined.
Completion of the remaining portion of the required examination is impractical and would result in undue hardship without a compensating increase in safety, i
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l CONCLUSION -
Based on the weld geometry, an acceptable percentage of the Code-required volumetric examination will be per-I formed on weld AB. Supplementing the autcmated ultra-sonic examination with a manual ultrasonic examination in order to obtain full coverage of weld AB would result in radiation exposure to personnel. )
It is concluded that the automated ultrasonic examina- l tion to be conducted by the licensee provides an accep- i table level of inservice structural integrity and that l compliance with specific requirements of Section XI would result in ha-dship or unusual difficulties without a compensating increase in the level of quality and safety.
RELIEF REQUEST RR0012D COMPONENT -
Reactor pressure vessel bottom head to reactor vessel circumferential weld AA, Category B-A.
CODE -
The botton head to reactor vessel weld AA was fabricated in accordance with ASME Section III Class 1 requirements.
Inservice inspections will be perfonned in accordance with ASME Section XI 1980 Edition, including Winter 1981 Addanda.
REQUIREMENT -
Bottom head to reactor vessel weld AA will be volumetric examined for inservice inspection in accordance with ASME Section XI, IWB-2500-1, Category B-A, Item Bl.2.
BASIS FOR REQUEST -
The bottom head to reactor vessel circumferential weld AA is located at the edge of a bevel or transition in vessel diameter. The geometry is such that it can be l examined from only the vessel side of the weld. All of I the required adjacent base metal on the shell side of the weld and essentially 100% of the weld itself was ,
examined by 45 and 60' angle beams nonnal to the weld during preservice inspection. Approximately 50% of the adjacent base metal on the bottom head side of the l
weld was examined using 45* and 60' angle beams nomal to the weld from the shell side of the weld. The weld was examir id 100% for transverse reflectors in both directions on the shell side of weld AA. There was !
essentially no coverage for transverse reflectors from I the bottom head side of the weld and there was no cover-age using 45 and 60' angle beams from the bottom head l
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1 side of the weld. During inservice ultrasonic inspection of weld AA, the examination coverage will be similar to that obtained during the preservice inspection.
During inservice inspection, automated ultrasonic examination will be performed from one side, (vessel shell side). This is required because of surface irregularity (handgrinding causing pitch and roll profile) in the it. mediate weld area and the material transition area below the weld. The weld centerline location (measurement from tangent of transition) on the vessel shell may vary up to 2 inches along the vessel circumference, (C = 730.42 in.). The pitch and roll profile along the slope transition supplements the insufficient surface measurement to provide a meaningful ultrasonic (45' and 60 ) examination.
Additional manual ultrasonic examination in this area will increase the total exposurt rate for personnel at River Bend Station. Additional examination will also increase man-hour requirements which directly impacts cutage cost and duration.
CONCLUSION -
It was concluded from the licensee's submittal and review by the staff that the volumetric examination of weld AA, to the extent required by the Code, is imprac-tical because of the component and/or weld geometry. A significant percentage of the inservice volumetric examination will be performed. To obtain information from the bottom head side of weld AA, a transducer would need to be placed between weld AA and the vessel skirt.
This is a relatively small area, the surface of which is irregular due to hand grinding and presents a pitch and roll profile along the slope transition. The distance between the weld AA and the top of the skirt weld can also vary so that there would be insufficient space to place a transducer for a meaningful examination from the bottom head side of weld AA.
Therefore, it is concluded that the limited Section XI ultrasonic examination provides an acceptable level of inservice structural integrity and that compliance with the specific requirements of Section XI would result in hardship or unusual difficulties without a compensating increase in the level of quality and safety.
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l RELIEF REQUEST RR0012E COMPONENT -
Reactor pressure vessel top head flange seam weld AG, l Category B-A l
CODE -
Weld was fabricated in accordance with ASME Section III Class I requirements. Inservice inspections will be performed in accordance with ASME Section XI 1980 Edition, Winter 1981 Addenda.
REQUIREMENT -
The head to flange weld will be surface and 100%
volumetric examined for inservice inspection in accordance with ASME Section XI, IWB-2500-1, Category 8-A, Item Bl.40.
BASIS FOR REQUEST -
Due to the configuration, there is sufficient area to perform a meaningful ultrasonic examination from the top head side only.
The weld was examined volumetrically (manual ultrasonic) l l
from the AH side of the weld. There was no ultrasonic examination coverage from the flange side. Full ultra-sonic examination coverage was obtained from transverse ,
and parallel reflectors from the AH side of the weld. I During inservice ultrasonic examination of weld AG, the examination coverage should be similar to that obtained ;
during the preservice inspection. i The weld will be surface examined in accordance with ASME XI, Class 2 requirements.
CONCLUSION -
We conclude from our review of this request that the volumetric examination of weld AG, to the extent required by the Code, is impractical because of the position of the weld in relation to the flange. The licensee pro-poses to perform a significant percentage of the Code-required inservice volumetric examination.
The limited Section XI ultrasonic examination along with the full surface examir ation, provides verification of an acceptable level of structural integrity. Compliance with the specific requirements of Section XI would result in hardship or unusual difficulties without a compensating increase in the level of quality and safety.
RELIEF REQUEST RR0012H COMPONENT -
Reactor pressure vessel bottom head meridional seam welds DG and DH, Category B-A.
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.. CODE -
Welds were fabricated in accordance with ASME Section III Class I requirements. Inservice inspections will be performed in accordance with ASME Section XI 1980 Edition, including Winter 1981 Addenda.
REQUIREMENT -
Reactor vessel head weld (s) DG and DH will be volumetric examined for inservice inspection in accordance with ASME Section XI, IWB-2500-1, category B-A, Item Bl.22.
BASIS FOR REQUEST -
Inservicevolumetric(ultrasonic) examination coverage of meridional welds DG and DH cannot be achieved due to installed control rod drive (CRD) assemblies penetrating through the bottom vessel head.
Preservice inspection was performed by manual ultrasonic examination with full weld coverage and no recordable indications. This inspec-tion was performed prior to CRD installation.
Inspection of the weld (s) from beneath the bottom head will require removal of portions of the control rod drive (CRD). Perfoming the required examinations is impractical and would result in undue hardship (increase ALARA consideration and extended outage duration) without a compensating increase in safety.
CONCLUSION -
The staff evaluated the information submitted by the licensee and concluded that the Section XI volumetric examination of welds DG and DH is impractical and that compliance with the specific requirement of Section XI would result in hardship or unusual difficulties without a compensating increase in the level of quality and safety.
CONCLUSION The NRC Staff concurs with the determination made by the licensee that Section XI ASME Code examination requirements for Category B-A welds in the reactor pressure vessel are impractical to perform at the River Bend Unit I facility.
Therefore, relief is granted as requested for requests RR0012A, RR0012C, RR0012D, RR0012E, and RR0012H. The staff further concludes that reliefs granted from the examination and testing requirements and alternate methods imposed through this document give reasonable assurance of the reactor
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l pressure vessel integrity, that granting relief because of ASME Code requirement impracticality is authorized by law and will not endanger life or property, or the connon defense and security, and is otherwise in the public interest considering the burden that could result if they were imposed on the River Bend Station, Unit 1.
Principal Contributor: F. Litton I
Dated: August 1,1988 '
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