Similar Documents at Hatch |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217D3061999-10-13013 October 1999 SER Accepting Licensee Proposed Changes to Edwin I Hatch Nuclear Plant Emergency Classification Scheme to Add Emergency Action Levels Related to Operation of Independent Spent Fuel Storage Installation ML20212A6641999-09-13013 September 1999 Safety Evaluation Authorizing Relief Request RR-V-16 for Third 10 Yr Interval Inservice Testing Program ML20210J9631999-08-0202 August 1999 SER Finding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210J9271999-08-0202 August 1999 SER Finds That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves at Plant,Susceptible to Pressure Locking or Thermal Binding ML20207E7631999-06-0303 June 1999 Safety Evaluation Concluding That Licensee Proposed Alternative to Use Code Case N-509 Contained in RR-4 Provides Acceptable Level of Quality & Safety.Considers Rev 2 to RR-4 & RR-6 Acceptable ML20206G1691999-05-0404 May 1999 SER Approving Requirements of Istb 4.6.2(b) Pursuant to 10CFR50.55a(a)(3)(ii) ML20207M1891999-03-11011 March 1999 SER Accepting Relief Request for Authorization of Alternative Reactor Pressure Vessel Exam for Circumferential Weld ML20196J4931998-12-0707 December 1998 Safety Evaluation Accepting Proposed Alternatives in Relief Requests RR-V-12,RR-V-15,RR-P-15,RR-V-7,RR-V-12,RR-V-14 & RR-V-15 ML20153G2481998-09-24024 September 1998 SE Concluding That Licensee Implementation Program to Resolve USI A-46 at Plant Adequately Addressed Purpose of 10CFR50.54(f) Request ML20239A2531998-09-0303 September 1998 SER Accepting Licensee Request for Relief Numbers RR-17 & RR-18 for Edwin I Hatch Nuclear Plant,Units 1 & 2.Technical Ltr Rept on Third 10-year Interval ISI Request for Reliefs for Plant,Units 1 & 2 Encl ML20236W3441998-07-30030 July 1998 Safety Evaluation Accepting Relief Requests for Second 10-yr ISI for Plant,Units 1 & 2 ML20236V5191998-07-28028 July 1998 Safety Evaluation Accepting Proposed License Amend Power Uprate Review ML20236L1821998-07-0707 July 1998 Safety Evaluation Accepting 980428 Proposed Alternative to ASME Boiler & Pressure Vessel Code,Section Xi,Repair & Replacement Requirements Under 10CFR50.55a(a)(3) ML20212A1981997-10-16016 October 1997 Safety Evaluation Denying Licensee Request for Relief from Implementation of 10CFR50.55a Requirements Re Use of 1992 Edition of ASME Code Section XI for ISI of Containments ML20216J8971997-09-12012 September 1997 SER Related to General Electric Nuclear Measurement Analysis & Control Power Range Neutron Monitoring Sys Upgrade Southern Nuclear Operating Co,Units 1 & 2 ML20216E9671997-09-0505 September 1997 Safety Evaluation Accepting ,As Suppl by 970902 Request for Relief to Request RR-V-11 Re IST & S/Rv ML20210S9141997-09-0303 September 1997 Safety Evaluation Accepting Licensee Request for one-time Relief from GL 88-01 for Insp of Category E Welds at Plant, Unit 1 & 2 ML20217N9381997-08-21021 August 1997 SE Re New & Revised Relief Requests Submitted by 970130,0307 & 25 Ltrs in Relation to Third 10-yr Pump & Valve IST Program ML20217N9811997-08-21021 August 1997 Safety Evaluation for Third 10-year Pump & Valve Inservice Testing Program,Southern Nuclear Operating Co,Inc,Hatch, Units 1 & 2 ML20148U6141997-07-0707 July 1997 Safety Evaluation Accepting Licensee Proposal for Third 10-yr Interval for Pump & Valve Inservice Testing Program ML20141A1981997-06-17017 June 1997 Safety Evaluation Accepting Licensee Design Criteria for Sizing ECCS Suction Strainers ML20141A1431997-06-16016 June 1997 Safety Evaluation Accepting Third 10-yr Inservice Insp Program Plan & Associated Requests for Relief.Relief Not Required for RR-08 ML20137N1811997-04-0404 April 1997 Safety Evaluation Supporting Amends 206 & 147 to Licenses DPR-57 & NPF-5,respectively ML20134P3661997-02-21021 February 1997 SER Accepting Test & Technical Evaluations Performed for Reactor Vessel Shell Welds,Per 10CFR50.55a(g)(6)(ii)(A)(5) ML20138J5211997-02-0505 February 1997 Safety Evaluation Accepting Temporary Request for Relief from ASME Code Repair Requirements for ASME Code Class 3 Valve ML20134B3301997-01-28028 January 1997 SE Accepting Revised QA Program for Plant ML20129F8211996-10-24024 October 1996 Safety Evaluation Accepting Licensee Actions IAW Current Industry Practice & BWRVIP Guidelines for Reinspection of BWR Core Shrouds ML20059E6961993-10-21021 October 1993 Safety Evaluation Supporting Amends 190 & 129 to Licenses DPR-57 & NPF-5,respectively ML20128C1931992-11-20020 November 1992 Safety Evaluation Accepting Licensee Response to Suppl 1 to GL 87-02 ML20127L4511992-11-18018 November 1992 Safety Evaluation Accepting Justification to Cancel Commitment on Seven Human Engineering Discrepancies ML20248F9791989-09-20020 September 1989 Safety Evaluation Accepting Okonite Taped Cable Splice as Electrical Connection to Replace Terminal Blocks in Selected Low Voltage Transmitter Measuring Loops ML20247H7261989-03-16016 March 1989 Safety Evaluation Re Use of Radioiodine Protection Factor for Sorbent Canisters ML20207M0431988-10-13013 October 1988 Safety Evaluation Denying Util 880711 Request for Relief from Hydrostatic Test Requirements of Section XI of ASME Code for Class 2 Portion of Main Steam Lines Between Outboard MSIVs & Turbine Stop Valves ML20153F9941988-05-0202 May 1988 Safety Evaluation Supporting Amend 153 to License DPR-57 ML20238A6801987-09-0404 September 1987 Safety Evaluation Re Insps & Repairs of Igscc.Plant Can Be Safely Operated for Another 18-month Fuel Cycle in Present Configuration ML20236F9831987-07-29029 July 1987 Safety Evaluation Supporting Util 831107,840229 & 860821 Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1 & 3.2.2 ML20235X5271987-07-20020 July 1987 SER Supporting Util Response to Generic Ltr 83-28,Item 2.1, (Part 2) Re Vendor Interface Programs (Reactor Trip Sys Components) ML20235P8421987-07-14014 July 1987 Safety Evaluation Re Acceptance of Offsite Dose Calculation Manual as Updated & Corrected Through 861231 ML20215M3941987-06-22022 June 1987 Safety Evaluation Re Request for Relief from Inservice Insp Requirements ML20236F6151987-04-0101 April 1987 Safety Evaluation Re Analytical Method Used by Licensee to Evaluate Critical Stresses Re Mark I Containment Program Vacuum Breakers Adequate.Max Stress in Breakers Less than 30% of Code Allowable.Existing Design Structually Adequate ML20207U1441987-03-19019 March 1987 Undated Safety Evaluation Re Plant.Section 9, Radwaste Sys, of FSAR Also Encl ML20210S2731986-09-29029 September 1986 Safety Evaluation Re Inservice Insp Program & Requests for Relief ML20211F0241986-06-12012 June 1986 Safety Evaluation Supporting Util Listed Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Identification & Classification of Reactor Trip Sys Components ML20211B3201986-05-30030 May 1986 SER Accepting Licensee 831107 & 840219 Responses to Generic Ltr 83-28, Items 3.1.3 & 3.2.3 Re post-maint Testing Requirements ML20205M9461986-04-24024 April 1986 Safety Evaluation Supporting Plant Operation in Present Configuration for 18-month Fuel Cycle.Plans for Insp &/Or Mod of Svc Sensitive Austenitic Stainless Steel Piping Sys Requested 3 Months Before Start of Next Refueling Outage ML20151Y4631986-01-29029 January 1986 Safety Evaluation Supporting Amend 122 to License DPR-57 ML20137M5311986-01-21021 January 1986 SER Supporting 850718 & 1127 Requests for Reconsideration of Relief from Requirements of Section XI of ASME Code Re Exam of Supports on ASME Piping ML20141F1261985-12-26026 December 1985 Safety Evaluation Supporting Amends 120 & 59 to Licenses DPR-57 & NPF-5,respectively ML20136A8461985-12-23023 December 1985 Safety Evaluation Re Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1.Addl Info Requested on Items 3.1.1,3.1.2,3.2.1 & 3.2.2.Item 4.5.1 Acceptable ML20137E2191985-12-23023 December 1985 Safety Evaluation Re Util Response to Generic Ltr 83-28,Item 1.1, Post-Trip Review (Program Description & Procedure). Program & Procedures Acceptable 1999-09-13
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217D3061999-10-13013 October 1999 SER Accepting Licensee Proposed Changes to Edwin I Hatch Nuclear Plant Emergency Classification Scheme to Add Emergency Action Levels Related to Operation of Independent Spent Fuel Storage Installation HL-5845, Monthly Operating Repts for Sept 1999 for Ei Hatch Nuclear Plant.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Ei Hatch Nuclear Plant.With ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212A6641999-09-13013 September 1999 Safety Evaluation Authorizing Relief Request RR-V-16 for Third 10 Yr Interval Inservice Testing Program HL-5836, Monthly Operating Repts for Aug 1999 for Edwin I Hatch Nuclear Plant.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Edwin I Hatch Nuclear Plant.With ML20210J9631999-08-0202 August 1999 SER Finding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210J9271999-08-0202 August 1999 SER Finds That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves at Plant,Susceptible to Pressure Locking or Thermal Binding HL-5818, Monthly Operating Repts for July 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With HL-5805, Monthly Operating Repts for June 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20207E7631999-06-0303 June 1999 Safety Evaluation Concluding That Licensee Proposed Alternative to Use Code Case N-509 Contained in RR-4 Provides Acceptable Level of Quality & Safety.Considers Rev 2 to RR-4 & RR-6 Acceptable HL-5795, Monthly Operating Repts for May 1999 for Ehnp Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Ehnp Units 1 & 2. with ML20206G1691999-05-0404 May 1999 SER Approving Requirements of Istb 4.6.2(b) Pursuant to 10CFR50.55a(a)(3)(ii) HL-5784, Monthly Operating Repts for Apr 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With HL-5766, Monthly Operating Repts for Mar 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20207M1891999-03-11011 March 1999 SER Accepting Relief Request for Authorization of Alternative Reactor Pressure Vessel Exam for Circumferential Weld HL-5755, Monthly Operating Repts for Feb 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20206P6981999-01-0707 January 1999 Ehnp Intake Structure Licensing Rept HL-5726, Monthly Operating Repts for Dec 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20196J4931998-12-0707 December 1998 Safety Evaluation Accepting Proposed Alternatives in Relief Requests RR-V-12,RR-V-15,RR-P-15,RR-V-7,RR-V-12,RR-V-14 & RR-V-15 HL-5714, Monthly Operating Repts for Nov 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With HL-5706, Monthly Operating Repts for Oct 1998 for Hatch Nuclear Plant Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Hatch Nuclear Plant Units 1 & 2.With ML20155B6121998-10-28028 October 1998 Safety Evaluation of TR SNCH-9501, BWR Steady State & Transient Analysis Methods Benchmarking Topical Rept. Rept Acceptable HL-5691, Monthly Operating Repts for Sept 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20153G2481998-09-24024 September 1998 SE Concluding That Licensee Implementation Program to Resolve USI A-46 at Plant Adequately Addressed Purpose of 10CFR50.54(f) Request ML20239A2531998-09-0303 September 1998 SER Accepting Licensee Request for Relief Numbers RR-17 & RR-18 for Edwin I Hatch Nuclear Plant,Units 1 & 2.Technical Ltr Rept on Third 10-year Interval ISI Request for Reliefs for Plant,Units 1 & 2 Encl HL-5675, Monthly Operating Repts for Aug 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 ML20238F7131998-08-31031 August 1998 9,change 2 to QAP 1.0, Organization HL-5667, Monthly Operating Repts for July 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 HL-5657, Ro:On 980626,noted That Pami Channels Had Been Inoperable for More than Thirty Days.Cause Indeterminate.Licensee Will Replace Automatic Function W/Five Other Qualified Pamis of Like Kind in Drywell & Revised Procedures1998-07-30030 July 1998 Ro:On 980626,noted That Pami Channels Had Been Inoperable for More than Thirty Days.Cause Indeterminate.Licensee Will Replace Automatic Function W/Five Other Qualified Pamis of Like Kind in Drywell & Revised Procedures ML20236W3441998-07-30030 July 1998 Safety Evaluation Accepting Relief Requests for Second 10-yr ISI for Plant,Units 1 & 2 ML20236V5191998-07-28028 July 1998 Safety Evaluation Accepting Proposed License Amend Power Uprate Review ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps ML20236L1821998-07-0707 July 1998 Safety Evaluation Accepting 980428 Proposed Alternative to ASME Boiler & Pressure Vessel Code,Section Xi,Repair & Replacement Requirements Under 10CFR50.55a(a)(3) HL-5653, Monthly Operating Repts for June 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 HL-5640, Monthly Operating Repts for May 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 ML20248B8651998-05-15015 May 1998 Quadrennial Simulator Certification Rept HL-5628, Monthly Operating Repts for Apr 1998 for Ei Hatch Nuclear Plant1998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Ei Hatch Nuclear Plant HL-5604, Monthly Operating Repts for Mar 1998 for Edwin I Hatch Nuclear Plant,Units 1 & 21998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20216B2711998-02-28028 February 1998 Extended Power Uprate Safety Analysis Rept for Ei Hatch Plant,Units 1 & 2 HL-5585, Monthly Operating Repts for Feb 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 HL-5571, Monthly Operating Repts for Jan 1998 for Edwin I Hatch Nuclear Plant,Unit 11998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Edwin I Hatch Nuclear Plant,Unit 1 HL-5551, Monthly Operating Repts for Dec 1997 for Ei Hatch Nuclear Plant,Units 1 & 21997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Ei Hatch Nuclear Plant,Units 1 & 2 ML20199B0561997-12-31031 December 1997 Rev 0 GE-NE-B13-01869-122, Jet Pump Riser Weld Flaw Evaluation Handbook for Hatch Unit 1 HL-5581, Annual Operating Rept for 1997, for Ei Hatch Nuclear Plant Units 1 & 21997-12-31031 December 1997 Annual Operating Rept for 1997, for Ei Hatch Nuclear Plant Units 1 & 2 HL-5533, Monthly Operating Repts for Nov 1997 for Ei Hatch Nuclear Plant,Units 1 & 21997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Ei Hatch Nuclear Plant,Units 1 & 2 HL-5514, Monthly Operating Repts for Oct 1997 for Edwin I Hatch Nuclear Plant,Units 1 & 21997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20212A1981997-10-16016 October 1997 Safety Evaluation Denying Licensee Request for Relief from Implementation of 10CFR50.55a Requirements Re Use of 1992 Edition of ASME Code Section XI for ISI of Containments ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20211H5311997-10-0101 October 1997 Rev 2 to Unit 1,Cycle 17 Colr ML20211H5251997-10-0101 October 1997 Rev 3 to Unit 1,Cycle 17 Colr 1999-09-30
[Table view] |
Text
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ME:vq J k UNITED STATES ,
NUCLEAR REGULATORY COMMISSION
) WASHINGTON, D C. 300064eM l
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATiQN ALTERNATIVE TO ASME CODE SECTION XI REC"JIREMENTS TO USE CODE CASE N-516-1 FOR UNDERWATER WEl_ DING SOUTHERN NUCLEAR OPERATING COMPANY. INC.
EDWIN 1. HATCH NUCI FAR PLANT. UNIT 2 DOCKET NO. 50-366 q
1.0 INTRODUCTION
By letter dated April 28,1998, Southem Nuclear Operating Company, Inc. (SNC, the licensee) proposed an attemative to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code),Section XI repair and replacement requirements under Title 10 af the Code of Federal Raoulations (10 CFR) Section 50.55a(a)(3). SNC proposed to use Code Case N-516-1, " Underwater Welding,Section XI, Division 1," to install the Emergency Core Cooling System (ECCS) suction strainer modification at Hatch, Unit 2. The licensee's modification of the suction strainer in the suppression pool is in response to IE Bulletin 96-03,
" Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling Water Reactors," as a proactive corrective action to mitigate its potential ph._ging. The subject modification is currently planned for the upcoming fall outage at Hatch, Unit 2, scheduled to begin September 6,1998.
. ' Pursuant to 10 CFR 50.55a(a)(3), proposed attematives to the requirements of 10 CFR 50.55a(c)-(h) may be used when authorized by the NRC. The licensee must demonstrate that (1) the proposed attemative would provide an acceptable level of quality and safety [(a)(3)(i)), or (2) compi,'ance with the requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety [(a)(3)(ii)). If a licensee determines that ASME Code requirements are impractical,10 CFR 50.55a(g)(6)(i) specifies that the Commission may grant such relief and may impose such altemative requirements as it determines is authorized by law and will not endanger life or property or the common defenso and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
i 2.0 EVALUATION !
I ASME Code Section XI Raouirement The licensee indicated that the 1989 Edition of the ASME Code for Csass 1,2, or 0; and the ;
ASME Code Section XI 1992 Edition with 1992 Addenda for Class MC, are applicable to Hatch. l Subarticles IWE-4000,;" Repair Procedures," and IWA-4000, " Repair and Replacement," of the j 9007100255 900707 '
PDR ADOCK 05000366 ?
P PDR J <
___.____m _____.-_______.mm.___m.__mm.z___-__._.__ -_m __ _ m -... .
subject Section XI Code Edition and Addenda provide rules and requiremen's for the repair of pressure retaining components and their supports. lWA-4170(b)" Code Applicability," specifies that " Repairs and installation of replacement items shall be performed in accordance with the Owner's Design Specification and the original Construction Code of the component or system."
The Owner's Design Specification and the original Construction Code require repair and replacement welding in air.
Prooosed Altemative The licensee proposed to use ASME Code Case N-516-1 as an alternative to the ASME Code,Section XI, Subarticle IWE-4000 and IWA-4000 requirements for repair and replacement to install the ECCS suction strainer modification in the suppression pool at Hatch, Unit 2.
Specifically, underwater welding is needed to attach new carbon steel tees to the residual heat removel and core spray carbon steel suction stub piping inside the suppression pool. Using Code Case N-516-1 is necessary because Subarticles IWE-4000 and IWA-4000 do not contain guidance on performing underwater welding for repair and replacement.
Licensee's Basis for the Prooosed Altemative (as stated)
The licensee indicated the following to support use of Code Case N-516-1 as an alternative to the ASME Code,Section XI requirements for repair and replacement:
Code Case N-516-1 is an ASME approved code case intended to provide an acceptable level of quality and safety when applied to underwater ASME Section XI repairs and replacements which are performed underwater.
Staff Evaluation The staffis currently reviewing Revision 0 of Code Case N-516, to include it in Regulatory Guide 1.147. Revision 0 of Code Case N-516 provides guidelines for underwater welding of P-No. 8 and P-No. 4X materials. Revision 1 of Code Case N-516, N-5161, extends the application to P-No.1 materials, which are the materials SNC is using to install the ECCS suction strainer modification. The Code Case contains controls related to welding processes needed for repairs, replacements, and modifications. The results of the staffs p eliminary review of Revis!cn 0 of Code Case N-516 have shown that Revision 1 of the Cdu Case is acceptable for uce, provided that for welding of highly irradiated materials, a mockup, using material with similar fluence ievels, is used tc demonstrate that cracks do no' result. The added condition of testing irradiated materials should also be imposed upon Code Case N-516-1.
However, in the subject app lication of welding the ECCS suctmn si,ainer dfication in the suppression pool, the added condition of testing the irradiated materials is nct appheaub
' because the components in the suppression pool will not be irradiated to any degree of significance.
On the basis of its review of the licensee's submittal, the staff has determined that the u6e of Code Case N-516-1 to weld the ECCS suction strainer modification in the suppression pool at Hatch, Unit 2, is acceptable in that it will provide assursnee of weld integrity.
3.0 CONCLUSION
On the basis of its review of the licensee's submittal, the staff concludes that the licensee's proposed altemative to use Code Case N-516-1 would provide an acceptable level of quality and safety. Therefore, the proposed alternative is authorized pursuant to 10 CFR 50.55a(a)(3)(i).
Principal Contributor: L. Olshan Date: July 7, 1998 i
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