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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
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Guidance1989-06-0505 June 1989 Safety Evaluation Accepting Licensee Rev 3 to ODCM for Plant Through Temporary Change 4.Rev Meets Criteria of NUREG-0133 & Other Guidance. Guidance ML20246Q0771989-05-0909 May 1989 Safety Evaluation Supporting Proposed Mod to Delete K74B & K74D Relays from Electrical Control Circuitry of MSIV to Resolve Spurious Opening of MSIV on Loss of Reactor Protection Sys Bus a or B ML20248G2921989-03-30030 March 1989 Safety Evaluation Accepting Util 840406 Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability On-Line Testing ML20236E0141989-03-15015 March 1989 Safety Evaluation Supporting Util Implementation of 10CFR50.62 ATWS Rule ML20196D4311988-12-0606 December 1988 Safety Evaluation Documenting NRC Review of Licensee Response to Generic Ltr 83-28.Evaluation Concludes That Licensee Adequately Meets Provisions of Part 1 of Item 2.2 to Generic Ltr 83-28 ML20213A5661987-04-20020 April 1987 Safety Evaluation Supporting Amend 4 to License NPF-58 ML20205Q9771987-04-0101 April 1987 Safety Evaluation Supporting Amend 3 to License NPF-58 ML20203N6981986-10-10010 October 1986 Sser Supporting Util Request for Relief from Preservice Insp Program Requirements ML20203N6951986-10-10010 October 1986 Safety Evaluation Supporting Request for Relief from ASME Code Exam Requirements in Preservice Insp Program ML20202G4321986-07-0808 July 1986 SER Approving Tdi Diesel Generator Owners Group Program to Validate & Upgrade Design & Mfg Quality of Tdi Diesel Generators for Nuclear Emergency Standby Svc ML20198C3951985-11-0505 November 1985 Safety Evaluation Re Reliability of Tdi Standby Emergency Diesel Generators for Application at Domestic Nuclear Plants.Diesel Generators Will Provide Reliable Standby Source of Onsite Power,W/Listed License Conditions ML20138N7461985-10-28028 October 1985 SER Supporting Reliability of Tdi Standby Emergency Diesel Generators.Viewgraphs & Final Draft Tech Specs Encl 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & Pnpp QA Program ML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico PY-CEI-NRR-2437, Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With PY-CEI-NRR-2429, Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With PY-CEI-NRR-2424, Monthly Operating Rept for July 1999 for Perry Npp.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Perry Npp.With ML20210J3851999-07-28028 July 1999 Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval PY-CEI-NRR-2416, Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With ML20196A1951999-06-17017 June 1999 Instrument Drift Analysis ML20207G2741999-06-0707 June 1999 Safety Evaluation Concluding That Firstenergy Flaw Evaluation Meets Rules of ASME Code & That IGSCC & Thermal Fatigue Crack Growth Need Not Be Considered in Application PY-CEI-NRR-2409, Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2393, Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored1999-05-12012 May 1999 Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored ML20206G6451999-05-0303 May 1999 Safety Evaluation Authorizing Requests for Relief IR-032 to IR-035 & IR-037 to IR-040 Re Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp PY-CEI-NRR-2399, Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With ML20206E2261999-04-29029 April 1999 Safety Evaluation Concluding That Proposed Alternatives Will Result in Acceptable Level of Quality & Safety.Authorizes Use of Code Case N-504 for Weld Overlay Repair of FW Nozzle Weld at Pnpp & Use of Table IWB-3514 ML20206D7911999-04-23023 April 1999 Rev 6 to PDB-F0001, COLR for Pnpp Unit 1 Cycle 8,Reload 7 ML20205P4371999-04-15015 April 1999 Safety Evaluation Concluding That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking or Thermal Binding ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20206D8461999-03-31031 March 1999 Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7 Cycle 8 PY-CEI-NRR-2389, Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With ML20205G4221999-03-31031 March 1999 Safety Evaluation Accepting Second 10-yr Interval IST Program Releif Requests for Plant,Unit 1 ML20205D3101999-03-26026 March 1999 Safety Evaluation Supporting Amend 103 to License NPF-58 ML20205C3761999-03-26026 March 1999 Safety Evaluation Supporting Request for Proposed Exemption to 10CFR50,app a GDC 19 PY-CEI-NRR-2369, Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 9902271999-03-0303 March 1999 Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 990227 PY-CEI-NRR-2372, Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With ML20203A5961999-02-0202 February 1999 Safety Evaluation Accepting Licensee Proposed Revs to Responsibilities of Plant Operations Review Committee as Described in Chapter 17.2 of USAR ML20203A5211999-01-27027 January 1999 Safety Evaluation Accepting Licensee Calculations Showing That Adequate NPSH Will Be Available for HPCS Pumps ML20198R8921999-01-0707 January 1999 SER Accepting Licensee Proposed Amend to TSs to Delete Reference to NRC Policy Re Plant Staff Working Hours & Require Administrative Controls to Limit Working Hours to Be Acceptable ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20206B0101998-12-31031 December 1998 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for Fiscal Yr Ending 981231,encl PY-CEI-NRR-2356, Monthly Operating Rept for Dec 1998 for Perry Nuclear Power Plant,Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Perry Nuclear Power Plant,Unit 1.With ML20198J0031998-12-22022 December 1998 SER Accepting Licensee Response to GL 92-08,ampacity Derating Issues for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2346, Monthly Operating Rept for Nov 1998 for Perry Nuclear Power Plant,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Perry Nuclear Power Plant,Unit 1.With ML20195F6891998-11-0505 November 1998 Safety Evaluation Accepting Proposed Reduction in Commitment in Quality Assurance Program to Remove Radiological Assessor Position PY-CEI-NRR-2335, Monthly Operating Rept for Oct 1998 for Perry Nuclear Power Plant,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2329, Monthly Operating Rept for Sept 1998 for Perry Nuclear Power Plant,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Perry Nuclear Power Plant,Unit 1.With ML20153B8221998-09-16016 September 1998 Safety Evaluation Accepting Changes to USAR Section 13.4.3, 17.2.1.3.2.2,17.2.1.3.2.2.3 & App 1A PY-CEI-NRR-2323, Monthly Operating Rept for Aug 1998 for Perry Nuclear Power Plant,Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2313, Monthly Operating Rept for July 1998 for Perry Nuclear Power Plant,Unit 11998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2306, Monthly Operating Rept for June 1998 for Perry Nuclear Power Plant,Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Perry Nuclear Power Plant,Unit 1 ML20249A1891998-06-11011 June 1998 SER on Moderate Energy Line Pipe Break Criteria for Perry Nuclear Power Plant,Unit 1 & Requests Addl Info to Demonstrate That Plant & FSAR in Compliance W/Staff Position & GDC as Discussed in SER PY-CEI-NRR-2289, Monthly Operating Rept for May 1998 for Perry,Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Perry,Unit 1 ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted PY-CEI-NRR-2282, Monthly Operating Rept for Apr 1998 for Perry Nuclear Power Plant,Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Perry Nuclear Power Plant,Unit 1 ML20217D2051998-04-20020 April 1998 SER Authorizing Licensee to Use Code Case N-524 Until Such Time as Code Case Included in Future Rev of RG 1.147 PY-CEI-NRR-2277, Monthly Operating Rept for Mar 1998 for Perry Nuclear Power Plant,Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Perry Nuclear Power Plant,Unit 1 ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML20216G3901998-03-11011 March 1998 SER on Proposed Merger Between Duquesne Light Co & Allegheny Power Sys,Inc ML20216J1401998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2258, Monthly Operating Rept for Jan 1998 for Perry Nuclear Power Plant,Unit 11998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Perry Nuclear Power Plant,Unit 1 1999-09-30
[Table view] |
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, f*Ph p & UNITED STATES g j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30056-0001 o
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ALTERNATIVES TO ASME CODE REQUIREMENTS FOR REPAIR AND INSPECTION OF A FEEDWATER NOZZLE TO SAFE-END WELD FIRSTENERGY NUCLEAR POWER COMPANY PERRY NUCLEAR POWER PLANT DOCKET NO. 50-440
1.0 INTRODUCTION
By letters dated March 25 and April 1,1999, the FirstEnergy Nuclear Operating Company (the licensee), proposed an altemative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI repair requirements along with a separate attemative to the ASME Code, Section til ultrasonic examination acceptance criteria under 10 CFR 50.55a(a)(3). The proposed attematives consist of the use of Code Case N-504,
" Alternative Rules for Repair of Class 1,2 and 3 Austenitic Stainless Steel Piping," to perform a weld overlay repair on a feedwater nozzle to safe-end weld N4C-KB at the Perry Nuclear Power Plant (PNPP), and the use of ASME Section XI acceptance criteria of Table IWB-3514-3 for the laminar flaws when inspecting the overlay repaired weld in accordance with Code Case N-416-1, *Altemative Pressure Test Requirement for Welded Repairs or installation of Replacement items by Welding, Class 1,2 and 3,Section XI, Division," respectively. The subject weld was found cracked during refuel outage (RFO) 2. Mechanical stress improvement process (MSIP) was applied to mitigate the cracking during RFO 3. The safe-end was fabricated from SA-508, Class 1 (P1 Group 2) material and the nozzle was made of SA-508, Class 11 (P3 Group 3) material. Both the nozzle and the safe-end are buttered with Alloy 182 and the weld was made with Alloy 82 filter. The subject weld is a dissimilar metal weld. The flaw was reported to be initiated in the butter at the safe-end side and extended into the weld.
The licensee proposed to perform a weld overlay repair on the subject weld during the current refueling outage (RF0 7) which began on March 26,1999.
Pursuant to 10 CFR 50.55(a)(3), proposed attematives to the requirements of 10 CFR 50.55a(g) may be used when authorized by the NRC. The licensee must demonstrate that (1) the proposed altemative would provide an acceptable level of quality and safety ((a)(3)(i)), or (2) compliance with the requirements of 10 CFR 50.55a(g) would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety ((a)(3)(ii)).
ENCLOSURE 9905050057 990429 l PDR ADOCK 05000440 ;
P PDR
I 2.0 EVALUATION 2.1 ASME Section XI Code Reoair Reauirement The current applicable ASME Section XI Code to PNPP is the 1989 Edition with no addenda. Article IWB-4000, " Repair Procedures," of the subject Section XI Code Edition provides rules and requirements for repair of the pressure retaining boundary for Class 1 components and their supports. To perform the Code repair, Sub-art,icle IWB-4120 l
" Procedure" requires that defects shall be removed from the degraded components prior to performing a repair by welding.
2.1.1 Proposed Alternative The licensee proposed to use the Code Case N-504 as an alternative to the ASME Code,Section XI, IWB-4000 requirements for repair to perform weld overlay repair on the subject feedwater nozzle weld at PNPP.
2.1.2 Licensee's Basis for the Proposed Altemative The licensee's bases for the proposed alternative to the Section XI Code repair requirements are summarized below:
(1) It is not practical to perform the Code repair, which requires the removal of the defect from the degraded component as the defect was connected to the inner diameter surface of the component. Therefore, it is necessary to use the Code Case N-504 for weld overlay repair of the subject feedwater nozzle weld.
(2) The overlay is designed as a full structural overlay in accordance with the ASME Code Case E L cod the guidelines in NUREG-0313, Revision 2 to assure the structuralintegrity of the repaired weld. The designed overlay will cover the subject weld and portion of'he safe-end adjacent to the weld.
(3) The weld ovety made of Alloy 52 (ASME Code Case 2142) or Alloy 152 (ASME 2143) is resis' ant to intergranular stress corrosion cracking (IGSCC).
(4) Because of the relatively low carbon content (0.23 percent) in the safe-end material (carbon steel), a temper bead welding technique to fabricate the proposed overlay mpair is not required because the potential of hardening the safe-end material by welding is low. However, as a conservative approach, a qualified temper bead welding technique will be applied for the first three overlay layers to ensure a high quality overlay.
2.1.3 Sts*f Evaluation The licensee propo.ed attemative to Section Xi Code repair is based on the use of the Code Case N-504 to perform a weld overlay repair on the subject feedwater noz;le to i - . . . _.
k . _'
safe-end weld. The subject nozzle weld is a dissimilar metal weld (austenitic material to ferritic material) and a portion of the weld overlay will extend from the austenitic weld into the safe-end made of carbon steel material (P1 Group 2). The staff notes that, in Regulatory Guide 1.147, the approved use of the Code Case N-504 is for applying the austenitic weld over on the austenitic material. Therefore, the licensee proposed altemative will extend the application of Code Case N-504 to apply the austenitic weld overlay on the ferritic material. The licensee proposed to use either Alloy 52 or Alloy 152 for the weld overlay repair. This is acceptable because these materials have been approved by the staff and used 'successfully in the past on a similar welding application.
2.2 ASME Section 111 Code Acceptance Criteria for Ultrasonic Examination When performing pressure testing in a'ecordance with Code Case N-416-1, the Code Case requires that the acceptance criteria of the non-destructive examinations (NDE) shall be in accordance with the applicable sub-article of the ASME Section lil,1992 Edition with no addendum. For the ultrasonic examination, the acceptance criteria is provided in sub-article NB-5330.
2.2.1 Licensee Proposed Alternative The licensee proposed the acceptance criteria of ASME Code Section XI as an alternative to the Section lll requirements for the laminar flaws in the weld overlay repair, in ASME Code Section XI, the allowable laminar flaws for the dissimilar metal weld are provided in Table IWB-3514-3 for ultrasonic examination.
2.2.2 Licensee's Basis for the Proposed Alternative The licensee's bases for the proposed alternative to ASME Section 111 Code acceptance criteria for the laminar flaws are summarized below:
(1) In ASME Code Section 111 of 1992 Edition and Code Case N-504, there are no specific acceptance criteria for the laminar flaws for pre-service examination. l (2) Since the weld overlay repair is proposed to be an attemative to the ASME Section XI Code repair, it is appropriate to apoly the Code Section XI acceptance criteria for the laminar flaws when inspecting t!.: overlay repaired weld in accordance with Code Case N-416-1.
2.2.3 Staff 0 valuation The licensee proposed the use of ASME Code,Section XI, Table IWB-3514, as an alternative for the NDE acceptance criteria of the ASME Code, Section 111, for the laminar flaws in the weld overlay repair. This is acceptable because the laminar flaws j
, are not expected to impact the structural integrity of the subject overlay repaired weld. I Furthermore, if the Code repair were performed to correct such benign lamination, it might result in an adverse residual stress profile in the subject nozzle weld that could promote initiation and growth of stress corrosion cracking. The licensee proposed !
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, .s alternative has been approved by the staff in other plants for a similar weld overlay repair.
On the basis of a review of the licensee's submittal, the staff has determined that the licensee proposed alternatives as discussed above for the weld overlay repair of the subject feedwater l nozzle weld at PNPP is acceptable because it will provide assurance of weld integrity.
3.0 .Cfj 'CLUSION On the basis of a review of the licensee's submittal, the staff concludes that the proposed alternatives will result in an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the staff authorizes the use of Code Case N-504 for the weld overlay repair of the subject feedwater nozzle weld at PNPP and the use of ASME Code Section XI, Table IWB-3514, for the acceptance criteria of the laminar flaws when performing ultrasonic examination of the overlay repaired weld.
Contact:
W. Koo Date: April 29, 1999 l
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