Safety Evaluation Authorizing Proposed Alternative Exam Methods Proposed in Alternative Exam 99-0-002 to Perform General Visual Exam of Accessible Areas & Detailed Visual Exam of Areas Determined to Be SuspectML20207E723 |
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Arkansas Nuclear |
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06/02/1999 |
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NRC (Affiliation Not Assigned) |
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ML20207E718 |
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NUDOCS 9906070120 |
Download: ML20207E723 (6) |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212L1141999-10-0101 October 1999 Safety Evaluation Granting Request for Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c ML20212F5261999-09-22022 September 1999 SER Approving Request Reliefs 1-98-001 & 1-98-200,parts 1,2 & 3 for Second 10-year ISI Interval at Arkansas Nuclear One, Unit 1 ML20211F4281999-08-25025 August 1999 Safety Evaluation Concluding That Licensee Provided Acceptable Alternative to Requirements of ASME Code Section XI & That Authorization of Proposed Alternative Would Provide Acceptable Level of Quality & Safety ML20207E7231999-06-0202 June 1999 Safety Evaluation Authorizing Proposed Alternative Exam Methods Proposed in Alternative Exam 99-0-002 to Perform General Visual Exam of Accessible Areas & Detailed Visual Exam of Areas Determined to Be Suspect ML20206M7711999-05-11011 May 1999 SER Accepting Relief Request from ASME Code Section XI Requirements for Plant,Units 1 & 2 ML20206F0691999-04-29029 April 1999 Safety Evaluation Accepting Licensee Re ISI Plan for Third 10-year Interval & Associated Requests for Alternatives for Plant,Unit 1 ML20205M6941999-04-12012 April 1999 Safety Evaluation Granting Relief for Second 10-yr Inservice Inspection Interval for Plant,Unit 1 ML20205D6061999-03-31031 March 1999 Safety Evaluation Supporting Licensee Proposed Approach Acceptable to Perform Future Structural Integrity & Operability Assessments of Carbon Steel ML20205D4711999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Employ Alternative Welding Matls of Code Cases 2142-1 & 2143-1 for Reactor Coolant System to Facilitate Replacement of Steam Generators at Arkansas Nuclear One,Unit 2 ML20204B1861999-03-15015 March 1999 Safety Evaluation Authorizing Licensee Request for Alternative to Augmented Exam of Certain Reactor Vessel Shell Welds,Per Provisions of 10CFR50.55a(g)(6)(ii)(A)(5) ML20198M7841998-12-29029 December 1998 SER Accepting Util Proposal to Use ASME Code Case N-578 as Alternative to ASME Code Section Xi,Table IWX-2500 for Arkansas Nuclear One,Unit 2 ML20196F4911998-12-0101 December 1998 SER Accepting Request for Relief ISI2-09 for Waterford Steam Electric Station,Unit 3 & Arkansas Nuclear One,Unit 2 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 ML20154J2471998-10-0909 October 1998 SER Accepting Inservice Testing Program,Third ten-year Interval for License DPR-51,Arkansas Nuclear One,Unit 1 ML20248D7491998-05-28028 May 1998 Safety Evaluation Accepting Licensee Request for Relief from ASME Code Repair Requirements for ASME Code Class 3 Piping ML20217A7211998-04-17017 April 1998 Safety Evaluation Supporting Proposed Alternative for ANO-1 to Implement Code Case N-533 (w/4 H Hold Time at Test Conditions Prior to VT-2 Visual Exam) 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) ML20216D6111998-03-12012 March 1998 Safety Evaluation Supporting Amend 188 to License NPF-6 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 ML20138K0561997-05-0505 May 1997 SER Approving Licensees IPE Process Capable of Identifying Severe Accidents & Severe Accident Vulnerabilities,For Plant,Unit 2 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 ML20134P8411996-11-25025 November 1996 Safety Evaluation Denying Request for Relief 96-001 Re Second 10-yr Interval ISI Program Plan,Due to Failure to Provide Basis for Impracticality ML20107F5611996-04-17017 April 1996 Safety Evaluation Providing Guidance on Submitting plant- Specific Info W/Respect to IST Program Alternatives Request ML20149K9451996-02-16016 February 1996 Safety Evaluation Authorizing Relief Request for Second 10-yr Interval IST Program Plan for Pumps & Valves at Facility ML20058L6111993-12-13013 December 1993 Safety Evaluation Approving Second ten-year Interval Inservice Insp Request for Relief Re Use of IWA-5250 Requirements Listed in 1992 Edition of ASME Code ML20058F6661993-11-24024 November 1993 Safety Evaluation Accepting Licensee Proposed Use of New DG as Alternate AC Power Source for Coping W/Sbo Subject ML20056H1331993-08-23023 August 1993 Supplemental Safety Evaluation Re Conformance to Reg Guide 1.97.Plant Design in Conformance W/Guidance of Subj Reg Guide ML20056H0001993-08-19019 August 1993 Safety Evaluation Accepting Licensee 920918 Response to GL 87-02,suppl 1 ML20128C9181993-01-22022 January 1993 Safety Evaluation Supporting Inservice Testing Program Relief Requests for Pumps & Valves ML20126H8661992-12-30030 December 1992 Safety Evaluation Granting Relief from Certain Inservice Insp Requirements of Section XI of ASME Boiler & Pressure Vessel Code,Determined to Be Impractical to Perform ML20126F7571992-12-18018 December 1992 Safety Evaluation Accepting Util Conceptual Design for Proposed Alternate Ac Power Source ML20062A5751990-10-10010 October 1990 Safety Evaluation Re Station Blackout Rule.Util Response Does Not Conform W/Station Blackout Rule ML20062A5881990-10-10010 October 1990 Safety Evaluation Re Station Blackout Rule.Util Response Does Not Conform W/Station Blackout Rule ML20059A7081990-08-17017 August 1990 Sser Concluding That Rochester Instrument Sys Model SC-1302 Isolation Device Acceptable for Use at Plant for Interfacing SPDS W/Class IE Circuits ML20056A7511990-08-0707 August 1990 Safety Evaluation Accepting Licensee Fire Barrier Penetration Seal Program & Commitment to Complete 100% Review of All Tech Spec Fire Penetration Seals by 911231 ML20062C8341990-05-24024 May 1990 Safety Evaluation Granting Relief from Certain Inservice Insp Requirements of ASME Code,Section Xi,Per 881103 & 890823 Requests ML20245K3671989-08-11011 August 1989 Safety Evaluation Accepting Licensee Actions in Response to 890120 High Pressure Injection Backflow Event ML20247N7451989-07-31031 July 1989 Safety Evaluation Concluding That Isolation Devices Acceptable for Use in Spds,Contingent on Licensee Submittal of Followup Evaluation Verifying That Failure of RIC SC-1302 Was Randomly Deficient Device Prior to Testing ML20247A8371989-07-11011 July 1989 Safety Evaluation Re Generic Ltr 83-28,Item 4.5.3 Concerning Reactor Trip Sys Reliability for All Domestic Operating Reactors ML20246J5421989-07-0707 July 1989 Safety Evaluation Re NRC Audit of Util Resolution of IE Bulletin 79-27.IE Bulletin Concerns Adequately Resolved for Facility.Periodic Test Program for Devices Recommended to Be Developed by Licensee ML20245K5971989-06-21021 June 1989 Safety Evaluation Concluding That Diverse Scram Sys & Diverse Initiation of Turbine Trip Meet Requirements of ATWS Rule (10CFR50.62) ML20245F3921989-04-25025 April 1989 Safety Evaluation Granting Util Relief from ASME Section XI Insp Requirements for Reactor Coolant Pump Casing Weld Indications Due to Impractical Requirements,Per Util 881027 Request & 10CFR50.55a ML20247E0191989-03-23023 March 1989 Safety Evaluation Supporting Instrumentation for Detection of Inadequate Core Cooling for Plants ML20206F5021988-11-15015 November 1988 Safety Evaluation Supporting Transfer of Operating Responsibility to Sys Energy Resources,Inc ML20205H8751988-10-25025 October 1988 Safety Evaluation Supporting Util 861124 & 880603 Responses to Generic Ltr 86-06,TMI Action Item II.K.3.5 Re Automatic Trip of Reactor Coolant Pumps ML20151D4131988-07-12012 July 1988 Safety Evaluation Supporting Util 831105 Responses to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys Reliability Online Testing ML20236A7581987-10-15015 October 1987 Evaluation Supporting Justification for Continued Operation Re High Reactor Bldg Temps ML20235W7011987-07-15015 July 1987 Safety Evaluation Re HPI Makeup Nozzle Cracking.Util Agreement to Record HPI Flowrate & Duration of Flow During HPI Actuation When SPDS Available Acceptable 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L8931999-10-31031 October 1999 Rev 1 to BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20212L1141999-10-0101 October 1999 Safety Evaluation Granting Request for Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c 0CAN109902, Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With ML20216J6271999-09-27027 September 1999 Rev 0 to CALC-98-R-1020-04, ANO-1 Cycle 16 Colr ML20212F5261999-09-22022 September 1999 SER Approving Request Reliefs 1-98-001 & 1-98-200,parts 1,2 & 3 for Second 10-year ISI Interval at Arkansas Nuclear One, Unit 1 0CAN099907, Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with ML20211F4281999-08-25025 August 1999 Safety Evaluation Concluding That Licensee Provided Acceptable Alternative to Requirements of ASME Code Section XI & That Authorization of Proposed Alternative Would Provide Acceptable Level of Quality & Safety 0CAN089904, Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with ML20210K8831999-07-29029 July 1999 Non-proprietary Addendum B to BAW-2346P,Rev 0 Re ANO-1 Specific MSLB Leak Rates 0CAN079903, Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with ML20207E7231999-06-0202 June 1999 Safety Evaluation Authorizing Proposed Alternative Exam Methods Proposed in Alternative Exam 99-0-002 to Perform General Visual Exam of Accessible Areas & Detailed Visual Exam of Areas Determined to Be Suspect ML20196A0191999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Arkansas Nuclear One,Units 1 & 2.With ML20196A6251999-05-31031 May 1999 Non-proprietary Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20195D1991999-05-28028 May 1999 Probabilistic Operational Assessment of ANO-2 SG Tubing for Cycle 14 ML20206M7711999-05-11011 May 1999 SER Accepting Relief Request from ASME Code Section XI Requirements for Plant,Units 1 & 2 0CAN059903, Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with ML20206F0691999-04-29029 April 1999 Safety Evaluation Accepting Licensee Re ISI Plan for Third 10-year Interval & Associated Requests for Alternatives for Plant,Unit 1 ML20205M6941999-04-12012 April 1999 Safety Evaluation Granting Relief for Second 10-yr Inservice Inspection Interval for Plant,Unit 1 ML20205D6061999-03-31031 March 1999 Safety Evaluation Supporting Licensee Proposed Approach Acceptable to Perform Future Structural Integrity & Operability Assessments of Carbon Steel ML20205R6351999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Ano,Units 1 & 2. with ML20205D4711999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Employ Alternative Welding Matls of Code Cases 2142-1 & 2143-1 for Reactor Coolant System to Facilitate Replacement of Steam Generators at Arkansas Nuclear One,Unit 2 ML20204B1861999-03-15015 March 1999 Safety Evaluation Authorizing Licensee Request for Alternative to Augmented Exam of Certain Reactor Vessel Shell Welds,Per Provisions of 10CFR50.55a(g)(6)(ii)(A)(5) 0CAN039904, Monthly Operating Repts for Feb 1999 for Ano,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Ano,Units 1 & 2. with ML20212G6381999-02-25025 February 1999 Ano,Unit 2 10CFR50.59 Rept for 980411-990225 ML20203E4891999-02-11011 February 1999 Rev 1 to 97-R-2018-03, ANO-2,COLR for Cycle 14 ML20199F0351998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Ano,Units 1 & 2 ML20198M7841998-12-29029 December 1998 SER Accepting Util Proposal to Use ASME Code Case N-578 as Alternative to ASME Code Section Xi,Table IWX-2500 for Arkansas Nuclear One,Unit 2 0CAN129805, LER 98-S02-00:on 981124,security Officer Found Not to Have Had Control of Weapon for Period of Approx 3 Minutes Due to Inadequate self-checking to Ensure That Weapon Remained Secure.All Security Officers Briefed.With1998-12-11011 December 1998 LER 98-S02-00:on 981124,security Officer Found Not to Have Had Control of Weapon for Period of Approx 3 Minutes Due to Inadequate self-checking to Ensure That Weapon Remained Secure.All Security Officers Briefed.With ML20196F4911998-12-0101 December 1998 SER Accepting Request for Relief ISI2-09 for Waterford Steam Electric Station,Unit 3 & Arkansas Nuclear One,Unit 2 ML20198D2441998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Ano,Units 1 & 2. with ML20199F7401998-11-16016 November 1998 Rev 9 to ANO-1 Simulator Operability Test,Year 9 (First Cycle) ML20195B4801998-11-0707 November 1998 Rev 20 to ANO QA Manual Operations 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 0CAN119808, Monthly Operating Repts for Oct 1998 for Ano,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Ano,Units 1 & 2. with ML20197H0741998-10-29029 October 1998 Rev 1 to Third Interval ISI Program for ANO-1 ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual ML17335A7641998-10-22022 October 1998 LER 98-004-00:on 980923,inadvertent Actuation of Efs Occurred During Surveillance Testing.Caused by Personnel Error.Personnel Involved with Event Were Counseled & Procedure Changes Were Implemented.With 981022 Ltr ML20154J2471998-10-0909 October 1998 SER Accepting Inservice Testing Program,Third ten-year Interval for License DPR-51,Arkansas Nuclear One,Unit 1 0CAN109806, Monthly Operating Repts for Sept 1998 for ANO Units 1 & 2. with1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for ANO Units 1 & 2. 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 0CAN099803, Monthly Operating Repts for Aug 1998 for ANO Units 1 & 2. with1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for ANO Units 1 & 2. with ML20237B7671998-08-19019 August 1998 ANO REX-98 Exercise for 980819 ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency 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 0CAN089804, Monthly Operating Repts for July 1998 for Ano,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Ano,Units 1 & 2 ML20196C7831998-07-30030 July 1998 Summary Rept of Results for ASME Class 1 & 2 Pressure Retaining Components & Support for ANO-1 ML20155H7161998-07-15015 July 1998 Rev 1 to 96-R-2030-02, Revised Reactor Vessel Fluence Determination ML20236R0531998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Ano,Units 1 & 2 ML20249B7791998-06-22022 June 1998 Part 21 Rept Re Findings,Resolutions & Conclusions Re Failure of Safety Related Siemens 4KV,350 MVA,1200 a Circuit Breakers to Latch Closed ML20249B5091998-06-15015 June 1998 SG ISI Results for Fourteenth Refueling Outage 1999-09-30
[Table view] |
Text
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caog p k UNITED STATES r
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- ] NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30806 4001
\ ..... j' SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST FROM SECTION XI REQUIREMENTS ENTERGY OPERATIONS. INC.
ARKANSAS NUCLEAR ONE. UNIT NOS.1 AND 2 DOCKET NOS. 50-313 AND 50-368
1.0 INTRODUCTION
Title 10 of the Code of Federal Reaulations (10 CFR), Section 50.55a, requires that inservice inspection (ISI) of certain American Society of Mechanical Engineers (ASME) Code Class 1,2, and 3 piping be performed in accordance with Section XI of the ASME Boiler and Pressure
- Vessel Code (Code, or the Code) and applicable addenda, except where altamatives have been authorized or relief has been requested by the licensee and granted by the Commission pursuant to paragraphs (a)(3)(l), (a)(3)(ii), or (g)(6)(i) of 10 CFR 50.55a. In proposing
- altomatives or requesting relief, the licensee must demonstrate that (1) the proposed altomatives provide an acceptable level of quality and safety, (2) compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety, or (3) conformance is impractical for its facility.
As published in'the Federal Register (61 FR 41303, dated August 8,1996), the NRC announced an amendment to its regulation in 10 CFR Part 50, Section 50.55a (rule). The rule I incorporated, by reference, the 1992 Edition with 1992 Addenda of Subsections IWE and IWL of Section XI of the ASME Code. Subsections IWE and IWL provide the requirements for ISI of Class CC (concrete containment components) and Class MC (metallic containment components) of light-water cooled power plants. The effective date for the amended rule was September 9,1996, and requires licensees tr> incorporate the new requirements into their ISI plans and complete the first containment ir action by September 9,2001. However, a licensee may submit a request for relief frot one or more requirements of the regulation (or the endorsed Code requirements) with proper Jt tification.
I in accordance with 10 CFR 50.55a(g)(6)(ii)(B), all licensees shall implement the inservice examinations specified for the first period of the first inspection interval in Subsection IWE,
" Requirements for Class MC and Metallic Uners of Class CC Concrete Components of I Light-Water Cooled Plants," of the 1992 Edition with the 1992 Addenda in conjunction with the
. requirements of 10 CFR 50.55a(b)(2)(ix) by September 9,2001. Licensees shall also i
. implement the inservice examinations that correspond to the number of years of operation that ;
are specified in Subsection IWL, " Requirements for Class CC Concrete Components of Light-Water Cooled Plants," of the 1992 Edition with the 1992 Addenda in conjunction with the requirements of 10 CFR 50.55a(b)(2)(ix) by September 9,2001.
Enclosure 9906070120 990602 PDR ADOCK 05000313 P PDF .
S. , ,
By letter dated April 1,1999, Entergy Operations, Inc. (the licensee), proposed an attemative to
- the requirements of IWL for Arkansas Nuclear One, Units 1 and 2. The NRC's finding with respect to authorizing the altematives or denying the proposed relief request is given below.
- 2.0 - ALTERN6 The licensee proposes attemative examination methods to those specified in ,
- Table IWL-2500-1, Examination Category L-A (ltem Nos. L1.11 and L1.12), IWL-2310, and i IWL-2510.- The attemative is to perform a general visual examination of the accessible areas
~
and a detailed visual examination of those areas determined to be suspect. The proposed examination methods will be consistent with the methods described in the 1997 Addenda of
~ Subsection lWL.
The licensee also proposes alternative examination methods to those specified in Table IWL-2500-1, Examination Category L-B litem No. L2.30), IWL-2310, and IWL-2524. The altemative is to perform a detailed visual exam. nation of both the anchorage hardware and the surrounding concrete.- The proposed examination methods will be consistent with the methods described in the 1997 Addenda of Subsection IWL.
l 2.1 Licensee's Basis for Reauestina Relief The licensee states:
In accordance with 10CFR50.55a(a)(3)(i), Arkansas Nuclear One (ANO) is requesting approval to implement altamative examination methods to those specified in Table IWL-2500-1, Examination Category L-A (Item Nos. L1.11 and L1.12), IWL-2310, and IWL-2510. ANO proposes to perform a general visual examination of the accessible areas and a detailed visual examination of those areas determined to be suspect.
In accordance with 10CFR50.55a(a)(3)(1), ANO is also requesting approval to implement alternative examination methods to those specified in Table IWL-2500-1, Examination Category L-B (item No. L2.30), IWL-2310, and IWL-2524. ANO proposes to perform a detailed visual examination of both the anchorage hardware and the surrounding concrete.
The proposed altamative examination methods have been evaluated by ANO,
' and have determined that the implementation of the attemative methods will provide an acceptable level of quality and safety for the following reasons:
- 1. ~ The visual examination methods (VT-1C & VT-3C) specified in Examination Category L-A and the visual examination methods (VT-1 and VT-10) specified in Examination Category L-B requires that the visual examination and qualification of the examiners meet the applicable requirements of IWA-2210 and IWA-2300.
The requirements specified in these ASME Code,Section XI provisions for the VT-3C and VT-1C examinations were developed for detecting flaws in metal components and for this reason, are more stringent than those that would be required for
R* . .
the detection of degradation on a concrete structure. The requirements of IWA 2210 and IWA 2300 were first introduced in Subsection IWL in the 1992 Addenda. Until the issuance of this Addenda to Subsection lWL, Examination Categories L-A & L-B only required visual examination performed by or under direction of the Responsible Engineer, who is a Registered Professional Engineer. As stated in the NRC's response to Public Comment 2.3 in Attachment 6, Part lli to SECY-96-080, issuance of Final Amendment to 10CFR50.55a to incorporate by Reference the ASME Boller and Pressure Vessel Code,Section XI, DMslon 1,
' Subsection IWE and Subsection IWL, ' Comments received from ASME members on the containment committee indicate that the newer more stringent requirements of IWA-2210 were not intended to be used for the examination of containments and were
- inadvertently included in Subsection lWL." in the 1997 Addenda, the reouirements of IWA-2210 and IWA-2300 were removed, in
{
evaluating the requirements of these ASME Code,Section XI '
provisions, ANO concluded that these requirements are not warranted for the examination of concrete surfaces nor the anchorage hardware and its surrounding concrete surfaces and would not provide a compensating increase in quality and safety. 4 2.' Degradation mechanisms for a concrete structure are differant from the degradation mechanisms of Class 1,2, and 3 !
components to which the applicable requirements of IWA 2210 and IWA-2300 were developed. Concrete deterioration and distress, as defined in ACI 201.1, Guide for Making a Condition Survey of Concrete in Service, can be effectively identified by the
_ performance of a general visual examination. As such, ANO has established controls for the performance of a general visual examination of the concrete structure. The generalvisual examination performed by ANO will be a thorough examination of the accessible areas as will the detailed visual examination of the
_ tendon anchorage hardware and its surrounding concrete and will
_ be performed by certified and properly trained examiners. If an area is determined to be suspect during the general visual examination, ANO will take additional actions to ensure the magnitude and extent of deterioration and/or distress is properly characterized for evaluation. To ensure the controls and
' techniques meet this expectation, the Responsible Engineer will periodically witness the performance of these examinations.
- 3. The general visual examination of the concrete surfaces and the
' detailed visual examination of the suspect areas detected by the general visual examination and the tendon anchorage hardware and its surrounding concrete will be performed in accordance with
- an ANO approved procedure. The examination methods outlined in this procedure will be written to be consistent with the methods approved in the rewrite of Subsection lWL (1997 Addenda) and i
L
R. , ,
.-4--
will be approved by the Responsible Engineer. These approved
. methods will delineate the necessary controls for ensuring these examinations are performed in a manner sufficient to detect evidence of degradation. When the examiner detects evidence of
' degradation, the procedure also requires a detailed visual examination to be performed and compared to established _
reporting and acceptance criteria. The reporting criteria, along with acceptance criteria, will be approved by the Responsible Engineer and will be consistent with the guidance outlined in the American Concrete Institute (ACl) Standard 349.3R-96, i Evaluation of Existing Nuclear Safety-Related Concreta Structure. i if the detailed visual examination cannot be performed for some reason (e.g., access limitation), ANO will evaluate the acceptability of the suspect area. This engineering evaluation will assume the suspect area is inaccessible and will address the ,
requirements outlined in 10CFR50.55a(b)(2)(ix)(E). The engineering evaluation will be approved by the Responsible Engineer.
- 4. The general and/or detailed visual examination will be performed by certified and properly trained personnel. Personnel performing these visual examinations will be certified in accordance with ANSI N45.2.6, Qualification ofInspection, Examination, and Testing Personnel for Nuclear Power Plants, and by ANO procedure. This level of certification will ensure the capability and visual acuity of the examiners is sufficient to detect evidence of degradation of the concrete structure or the post tensioning system. Prior to performing the examinations, the examiners will be required to successfully complete ANO approved training (i.e., training developed by the Electric Power Research Institute or equivalent) on the proper techniques for examining components subject to the requirements of Subsection lWL. In addition, the examiners will receive site specific training regarding the methods outlined in the approved plant procedure. The site-specific training will be conducted under the direction of the Responsible Engineer and will be held at the beginning of each -
subsequent inservice inspection used to satisfy the applicable requirements of IWL-2410. Successful completion of the above j training will ensure the examiners have a basic working knowledge of the components being examined and the types of degradation to be detected.
- 5. The ASME Main Committee and the Board of Nuclear Codes and Standards have also determined that Code provisions outlined in IWA-2210 and IWA-2300 were not warranted for the visual examination of concrete surfaces or post tensioning system anchorage hardware or surrounding concrete. Both organizations have approved the rewrite of Subsection lWL that eliminated the .
requirement of IWA-2210 and IWA-2300. This rewrite of
Subsection IWL was published in the 1997 Addenda of the ASME Code,Section XI. The altemative examination methods proposed
, ' by ANO is consistent with the approved rewrite of Subsection IWL
- l. and will provide an acceptable level of quality and safety.
l l- 2.2 Altemative Examination l
l The licensee proposes:
To satisfy the requirements of Examination Category L-A (Item Nos. L1.11 and -
L1.12) and Examination Category L-B (Item No. L2.30), ANO will perform the l following: ;
l l A general visual examination of the accessible concrete surfaces, and a f detailed visual examination of the suspect areas detected by the general j visual examination and the tendon anchorage hardware and its i
- surrounding concrete, as applicable, during the ANO-1 and ANO-2 first ;
containment inspection intervals [ sic). For the first containment l inspection interval, ANO will establish the beginning of the ANO-1 twenty-five year tendon surveillance and the beginning of the ANO-2 twenty year tendon surveillance as the effective start date of the first containment inspection interval for IWL-related activities. When evidence of degradation is detected by the examiners on the accessible concrete surfaces, ANO will perform a detailed visual examination. If a detailed visual examination cannot be performed, an engineering evaluation
~
approved by the Responsible Engineer will be provided which will evaluate the suspect area. To ensure the controls and techniques are adequate for detecting evidence of degradation the Responsible Engineer will periodically witness the performance of these examinations.
in addition, each examiner will successfully complete ANO approved training, including site specific, to ensure they have a basic working
( knowledge of the components being examined and the types of degradation to be detected. 1 l
3.0 EVALUATION 1
Table IWL-2500-1, Examination Category L-A (item Nos. L1.11 and L1.12), IWL-2310, and j
. IWL-2510 require a visual (VT-3C) examination of the accessible concrete susiace areas and a l visual (VT-1C) examination of suspect areas. Table IWL-2500-1, Examination Category L-B )
(item No. L2.30), IWL-2310, and IWL-2524 require the performance of a visual (VT-1) i examination of the anchorage hardware'and a visual (VT-10) examination of the surrounding j concrete. The licensee proposes an attemative to these Code requirements for all accessible
. concrete surface areas, and all tendon anchorage hardware and surrounding concrete, which
- are subject to these examinations. In its submittal, the licensee states that alternative examination methods are consistent with the methods published in the 1997 Addenda of
, Subsection IWL. !'
L
. The visual examination methods (VT-1C, VT-3C, and VT-1) required by the Code dictate that the examination, and the qualification of the examiners, meet the requirements of IWA-2210 L
P.,,,__
and IWA-2300. However, the requirements specified in these sections were developed for detecting flaws in metal components and, as a result, are more stringent than those that would be required for the detection of degradation of concrete structures. In the 1997 Addenda of Subsection lWL, the requirements of IWA-2210 and IWA-2300 were removed.
.The licensee's submittal states that the personnel performing the examinations will be certified in accordance with ANSI N45.2.6, Qualification ofInspection, Examination, and Testing
.' Personnel for Nuclear Power Plants and will have successfully completed site specific training ,
on proper examination techniques. The Responsible Engineer will periodically witness the
- performance of the examinations. For the type of examinations being performed, the staff finds this provides an acceptable level of quality and safety.
4.0 CONCLUSION
- The staff has 6 valuated the information contained in the licensee's April 1,1999, submittal for ANO-1 and ANO-2. On the basis of the preceding evaluation, the staff concludes that the proposed altemative contained in Altemative Examination 99-0-002 provides an acceptable ,
level of quality and safety and, therefore, the licensee's proposed attemative is authorized l pursuant to 10 CFR 50.55a(a)(3)(i).
Principal Reviewer: M. Kotzalas i
Date: June 2, 1999 l i
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