Similar Documents at Perry |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in PNPP to Ceico ML20212A6881999-08-31031 August 1999 Safety Evaluation Supporting Amend 106 to License NPF-58 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 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 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 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 ML20205G4221999-03-31031 March 1999 Safety Evaluation Accepting Second 10-yr Interval IST Program Releif Requests for Plant,Unit 1 ML20205E0591999-03-26026 March 1999 Safety Evaluation Supporting Amend 105 to License NPF-58 ML20205D6921999-03-26026 March 1999 Safety Evaluation Supporting Amend 104 to License NPF-58 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 ML20204C0711999-03-11011 March 1999 Safety Evaluation Supporting Amend 102 to License NPF-58 ML20207F4361999-03-0303 March 1999 Safety Evaluation Supporting Amend 101 to License NPF-58 ML20207L4881999-02-24024 February 1999 Safety Evaluation Supporting Amend 100 to License NPF-58 ML20203F8381999-02-0808 February 1999 Safety Evaluation Supporting Amend 97 to License NPF-58 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 ML20198J0031998-12-22022 December 1998 SER Accepting Licensee Response to GL 92-08,ampacity Derating Issues for Perry Nuclear Power Plant,Unit 1 ML20198K9071998-12-21021 December 1998 Safety Evaluation Supporting Amend 96 to License NPF-58 ML20196J4731998-12-0202 December 1998 Safety Evaluation Supporting Amend 95 to License NPF-58 ML20196D2751998-11-23023 November 1998 Safety Evaluation Supporting Amend 94 to License NPF-58 ML20195F6891998-11-0505 November 1998 Safety Evaluation Accepting Proposed Reduction in Commitment in Quality Assurance Program to Remove Radiological Assessor Position 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 ML20153D0311998-09-15015 September 1998 Safety Evaluation Supporting Amend 93 to License NPF-58 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 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 ML20216G4711998-03-12012 March 1998 Safety Evaluation Supporting Amend 92 to License NPF-58 ML20216G3901998-03-11011 March 1998 SER on Proposed Merger Between Duquesne Light Co & Allegheny Power Sys,Inc ML20199C0471997-11-0707 November 1997 Safety Evaluation Supporting Amend 91 to License NPF-58 ML20199B2351997-11-0404 November 1997 Safety Evaluation Supporting Amend 90 to License NPF-58 ML20217E2051997-09-24024 September 1997 Safety Evaluation Supporting Amend 89 to License NPF-58 ML20211H6791997-09-18018 September 1997 Safety Evaluation Authorizing Licensees Request for Alternative from Augmented Insp of Reactor Pressure Vessel Circumferential Weld in Plant,Unit 1 ML20217B2601997-09-11011 September 1997 Safety Evaluation Supporting Amend 87 to License NPF-58 ML20211A5881997-09-11011 September 1997 Safety Evaluation Supporting Evaluation of First 10-yr Interval ISI Program Plan Requests for Relief PT-004,PT-005 & PT-006 for Plant,Unit 1 ML20217K9061997-08-12012 August 1997 Safety Evaluation Accepting Plant First 10-yr Interval ISI Program Plan Relief Request PT-007 ML20141C0081997-06-19019 June 1997 Safety Evaluation Approving Merger Agreement Between Centerior Energy Corp & Ohio Edison Co Affecting NPF-58 ML20141L9131997-05-27027 May 1997 Safety Evaluation Accepting Relief Requests for First 10-yr Interval Inservice Insp Program Plan for Plant,Unit 1 ML20147H4211997-04-0101 April 1997 Safety Evaluation Accepting Changes to USAR Sections,Which Continue to Satisfy Criteria of App B of 10CFR50 ML20134D1061997-01-27027 January 1997 Safety Evaluation on Revised EALs for Plant.Proposed EALs Changes Are Consistent W/Guidance in NUMARC/NESP-007,with One Exception,& Meets Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20114E4561996-06-18018 June 1996 Safety Evaluation Supporting Amend 85 to License NPF-58 ML20101G8351996-03-22022 March 1996 Safety Evaluation Supporting Amend 84 to License NPF-58 ML20100R1171996-02-27027 February 1996 Safety Evaluation Supporting Amend 81 to License NPF-58 ML20101G0761996-01-20020 January 1996 Corrected SE Supporting Amend 79 to License NPF-58. Inaccuracies in Description of Changes Has Been Corrected ML20100C8031996-01-19019 January 1996 Safety Evaluation Supporting Amend 78 to License NPF-58 ML20095G0201995-12-0808 December 1995 Safety Evaluation Supporting Amend 76 to License NPF-58 ML20095A5401995-11-29029 November 1995 Safety Evaluation Supporting Amend 75 to License NPF-58 ML20092N0611995-09-26026 September 1995 Safety Evaluation Supporting Amend 73 to License NPF-58 ML20092J1451995-09-15015 September 1995 Safety Evaluation Supporting Amend 72 to License NPF-58 ML20086C1551995-06-27027 June 1995 Safety Evaluation Supporting Amend 70 to License NPF-58 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000440/LER-1999-004, :on 990916,loss of Safety Function Resulted in TS 3.0.3 Entry.Caused by Design Deficiency in Control Complex Architectural Walls.Revised Storm Contingencies Instructions.With1999-10-18018 October 1999
- on 990916,loss of Safety Function Resulted in TS 3.0.3 Entry.Caused by Design Deficiency in Control Complex Architectural Walls.Revised Storm Contingencies Instructions.With
ML20217K1231999-10-14014 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 05000440/LER-1999-003-01, :on 990218,post-accident Dose Limits Were Exceeded.Caused by Relief Valve Leakage Outside of Containment.Removed Relief Valve on 990913,by Design Change Package Implemented Under 10CFR50.59.With1999-09-27027 September 1999
- on 990218,post-accident Dose Limits Were Exceeded.Caused by Relief Valve Leakage Outside of Containment.Removed Relief Valve on 990913,by Design Change Package Implemented Under 10CFR50.59.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 ML20212A6881999-08-31031 August 1999 Safety Evaluation Supporting Amend 106 to License NPF-58 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 05000440/LER-1999-002-01, :on 990327,RHR a Pump Failed to Start & LCO 3.0.3 Was Entered Due to TS Bases Misinterpretation.Caused by Failed Optical Isolator That Provided Signal to Pump Start Permissive Circuitry.Subject Circuitry Was Replaced1999-04-26026 April 1999
- on 990327,RHR a Pump Failed to Start & LCO 3.0.3 Was Entered Due to TS Bases Misinterpretation.Caused by Failed Optical Isolator That Provided Signal to Pump Start Permissive Circuitry.Subject Circuitry Was Replaced
ML20206D7911999-04-23023 April 1999 Rev 6 to PDB-F0001, COLR for Pnpp Unit 1 Cycle 8,Reload 7 05000440/LER-1999-001-01, :on 990317,discovered That Control Complex Bldg Architectural Walls Were Not Included in Tornado Dp Loading Design.Caused by Failure to Consider Tornado Dp Loads. Compensatory Measures Were Implemented.With1999-04-16016 April 1999
- on 990317,discovered That Control Complex Bldg Architectural Walls Were Not Included in Tornado Dp Loading Design.Caused by Failure to Consider Tornado Dp Loads. Compensatory Measures Were Implemented.With
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 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 ML20206D8461999-03-31031 March 1999 Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7 Cycle 8 ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20205E0591999-03-26026 March 1999 Safety Evaluation Supporting Amend 105 to License NPF-58 ML20205D3101999-03-26026 March 1999 Safety Evaluation Supporting Amend 103 to License NPF-58 ML20205D6921999-03-26026 March 1999 Safety Evaluation Supporting Amend 104 to License NPF-58 ML20205C3761999-03-26026 March 1999 Safety Evaluation Supporting Request for Proposed Exemption to 10CFR50,app a GDC 19 ML20204C0711999-03-11011 March 1999 Safety Evaluation Supporting Amend 102 to License NPF-58 ML20207F4361999-03-0303 March 1999 Safety Evaluation Supporting Amend 101 to License NPF-58 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 ML20207L4881999-02-24024 February 1999 Safety Evaluation Supporting Amend 100 to License NPF-58 ML20203F8381999-02-0808 February 1999 Safety Evaluation Supporting Amend 97 to License NPF-58 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 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 ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 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 ML20198K9071998-12-21021 December 1998 Safety Evaluation Supporting Amend 96 to License NPF-58 ML20196J4731998-12-0202 December 1998 Safety Evaluation Supporting Amend 95 to License NPF-58 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 ML20196D2751998-11-23023 November 1998 Safety Evaluation Supporting Amend 94 to License NPF-58 ML20195F6891998-11-0505 November 1998 Safety Evaluation Accepting Proposed Reduction in Commitment in Quality Assurance Program to Remove Radiological Assessor Position 05000440/LER-1998-003, :on 981001,missed TS SR on H Igniters Was Noted.Caused by Personnel Error.Missed Surveillance Was Performed on Day of Discovery of Item & Function of H Igniters Were Verified.With1998-11-0202 November 1998
- on 981001,missed TS SR on H Igniters Was Noted.Caused by Personnel Error.Missed Surveillance Was Performed on Day of Discovery of Item & Function of H Igniters Were Verified.With
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 1999-09-30
[Table view] |
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i UNITED STATES
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j NUCLEAR RE2ULATORY COMMISSION WASHINGTON, D.C. 20066 4 001
.....,o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ASME CODE CASE N-524 PERRY NUCLEAR POWER PLANT. UNIT NO.1
, CENTERIOR SERVICE COMP &liY DOCKET NO: 5048,0.
1.0 INTRODUCTION
The Technical Specifications for the Perry Nuclear Power Plant, Unit 1, state that the inservice inspection and testing of the American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i).
10 CFR 50.55a(a)(3) states that a!(ematives to the requirements of paragraph (g) may be used, when authorized by the NRC, if (i) the proposed altematives would provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1,2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, " Rules for Inservice inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) on the date 12 months prior to the start of the 120-month interval, subject to the limitations and rnodifications listed therein. The anplicable edition of Section Xi of the ASME Code for the Perry Nuclear Power Plant, Unit 1, during the first 10-year inservice inspection (ISI) intervalis the 1983 Edition through the Summer 1983 Addenda. The components (including supports) may meet the requirements set farth in subsequent editions and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein and subject to Commission approval.
Pursuant to 10 CFR 50.55a(g)(5), if the licensee determ!nes that conformance with an examination requirement of Section XI of the ASME Code is not practical for its facility, information shall be submitted to the Commission in support of that determination and a request roade for relief from the ASME Code requirement. After evaluation of the determination, pursuant to 10 CFR 50.55a(g)(6)(i), the Comminion may grant relief and may impose ENCLOSURE 9804240242 980420 PDR ADOCF. 05000440 P
PDR
1 alternative requirements that are determined to be authorized by law, will not endanger life, property, or the common defense and security, and are otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed.
By letter dated December 18,1997, Centerior Service Company, the licensee, requested approval for the implementation of the altemative criteria of ASME Sedion XI Code Case N-524 dated August 9,1993, titled " Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping,Section XI, Division 1", pursuant to 10CFR 50.55a(a)(3) to be applied to the first 10-year inservice inspection interval of Perry, Unit 1.
The staff has reviewed and evaluated the licensee's request and the supporting information to use Code Case N-524 as a proposed attemative to the ASME Code requirements for the Perry Nuclear Power Plant Unit 1.
2.0 DISCUSSION HIS FOR LONGITUDINAL WELDS IN CLASS 1 AND 2 PIPING - SECTION XI. DIVISION 1 1
Comoonent identificallDB r
Class 1, Category B-J and Class 2, Categories C-F-1 and C-F-2, longitudinal piping welds (examination items B9.12, B9.22, C5.12, C5.22 and C5.42).
Code Reouirement:
ASME Class 1 longitudinal seam welds require examination of one pipe diameter in length, but no more than 12 inches of each longitudinal wald intersecting the circumferential welds. ASME Class 2 longitudinal seam welds require examination of 2.5t (where t is the thickness of the weld) in length at the intersecting circumfemntial weld. The weld length is measured from the intersection of the circumferential weld and longitudinal weld.
Code Reauirement From Which Relief is Reauested:
Relief is requested from performing the Code required examination of Class 1 and 2 longitudinal piping seam welds for the lengths identified above.
Basis for Relief (as stated by the bcensee)
"The structural integrity of the longitudinal welds Ivas demonstrated during construction by meeting the requirements of the ASME Code Section Ill, and additionally, by meeting the requirements of ASME Section XI during preservice examination. Furthermore, through Perry's fifth refueling outage, all inservice examinations of longitudinal welds were performed to the full extent required.
There were no reportable indications during the preservice or inservice examinations.
l Industry experience in performing inservice examinations of safety class piping has demonstrated that in-service flaws are not being found in longitudinal welds.
This prompted ASME Subcommittee XI to write Code Case N-524. The conclusion of ASME Subcommittee XI was that examination of longitudinal seams beyond their intersection with a circumferential weld provides little or no benefit and, therefore, the extent of examination could be limited to the intersecting portion of the longitudinal seam without compromising the level of quality and safety.
Examination of longitudinal welds beyond their intersection with the circumferential weld involves the removal of additional insulation and, in some
]
cases, the removal of hanger clamps or other appurtenances. It is estimated that these activities are cause for at least 2 REM of exposure to workers each refueling outage. Thus, compliance with the specific requirements results in hardships without a compensating increase in the level of quality and safety.
Although Code Case N-524 is not included in Revision 11 of Regulatory Guide 1.147," Inservice inspection Code Case Acceptibility-ASME Section XI Division 1," it is listed as an accepted Code Case in DG-1050 (Revision 12 to Regulatory j
Guide 1.147), which is out for public comment."
Attemative Examination (as stated bv the licenseek 4
" Perry proposes to perform inservice examination of longitudinal welds utilizing the alternative requirements delineated in Code Case N-524. In accordance with Code Case N-524, the following shall apply:
(a)
When only a surface examination is required, examination of longitudinal piping welds is not required beyond those portions of the we!ds within the examination boundaries of the intersecting l
circumferential welds.
(b)
When both surface and volumetric examinations are required, examination of longitudinal piping welds is not required beyond those portions of the welds within the examination boundaries of the intersecting circumferential welds provided the following requirements are met.
(1)
Where longitudinal welds are specified and locations are known (as is the case within Perry's i
current inservice examination boundary),
examination requirements shall be met for both transverse and parallel flaws at the intersection of the welds and for that length of longitudinal weld within the circumferential weld volume; L
._...__w
. i (2)
Where longitudinal welds are specified and locations are unknown, or the existence of longitudinal welds is uncertain, the examination requirements shall be met for both transverse and parallel flaws within the entire examination volume of intersecting circumferential welds."
3.0 EVALUATION
The ASME Section XI Code (1983 Edition) requires one pipe diameter in length, but no more than 12 inches, be examined for Class i longitudinal piping welds. Class 2 longitudinal piping welds are required to be examined for a length of 2.5t, where t is the thickness of the weld.
l These lengths of weld are measured from the intersection of the circumferential weld and longitudinal weld. The licensee's proposed alternative, Code Case N-524, limits the volumetric and surface examination requirements of the longitudinal weld to the volume or area contained within the examination requirements of the intersecting circumferential weld.
Longitudinal welds are produced during the manufacturing process of the piping, not in the field as is the case for circumferential welds. The Code contains requirements on characteristics and performance of materials and products, and specifies the examination requirements during the manufacturing of the subject longitudinal piping welds.
In addition, there are material, chemical, and tensile strength requirements in the Code. The manufacturing process that is specified by the Code provides assurance of the structural integrity of the longitudinal welds at the time the piping is manufactured.
The preservice examination and initialinservice examinations have provided assurance of the structural integrity of the longitudinal welds. The experience in the United States has been that pipes with shop welded longitudinal seams have not experienced degradation that would warrant continued examination beyond the boundaries required to meet the circumferential weld examination requirements. No significant loading conditions or known material degradation mechanisms have become evident to date which specifically relate to longitudinal seam welds in nuclear plant piping.
If any degradation associated with a longitudinal weld were to occur, it is expected that it would be located at the intersection with a circumferential weld. This intersection is inspected in accordance with the provisions of Code Case N-524. Furthermore, the 1983 ASME Code,Section XI, Appendix ill " Ultrasonic Examination of Piping Systems" which is applicable to the j
subject plant, requires scanning for reflectors parallel and transverse to the weld seam in case l
of ferritic piping, contrary to the requirement in some older Code editions to only scan for reflectors oriented parallel to the weld seam. The transverse scan of a circumferential weld, will l
further detect reflectors oriented parallel to a longitudinal weld at the root of intersection of a longitudinal seam.
i
a.
4.0 CONCLUSION
Based on the above discussions, the staff concludes that the licensee's proposed use of Code Case N-524 as an attemative to the Code requirements, provides an acceptable level of quality and safety by providing assurance of structuralintegrity. Therefore, the licensee's proposed attemative to use Code Case N-524 is authorized for the Perry Unit 1, pursuant to 10CFR50.55a(a)(3)(i). The licensee is authorized to use Code Case N 524 until such time as the code case is included in a future revision of Regulatory Guide 1.147. At that time the licensee is to follow al1 provisions in Code Case N-524, with limitations issued in Regulatory Guide 1,147, if any, should the licensee continue to implement this relief request.
Principal Contributor: P. Patnaik Date: April 20, 1998 l
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