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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217H8991999-10-18018 October 1999 SER Approving Licensee Requests for Relief NDE-R001 (Part a & B),NDE-R027,NDE-028,NDE-R029,NDE-R030,NDE-R032 & NDE-R035. Relief Request NDE-036,denied & Relief Request NDE-R-034, Deemed Unnecessary ML20212H2381999-09-22022 September 1999 Safety Evaluation Supporting Amend 228 to License DPR-49 ML20195G9901999-06-0909 June 1999 Safety Evaluation Supporting Amend 227 to License DPR-49 ML20206N7551999-05-13013 May 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safey-Related Power-Operated Gate Valves ML20207G0251999-03-0303 March 1999 SER Concluding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety- Related MOVs at Duane Arnold & That Licensee Adequately Addressed Actions Requested in GL 96-05 ML20202B4311999-01-26026 January 1999 Safety Evaluation Accepting Request for Approval to Use ASME Code Case N-508-1 in ISI Program for Duane Arnold Energy Ctr ML20202B3851999-01-26026 January 1999 Safety Evaluation Addressing Thermo-Lag Related Ampacity Derating Issues.Ampacity Derating Analysis Results Acceptable ML20236X5321998-07-29029 July 1998 Safety Evaluation Re USI A-46 Program Implementation for Plant ML20236W0021998-07-29029 July 1998 Safety Evaluation Accepting Request for Relief NDE-R020 Re Third 10-yr ISI Interval of Plant,Per 10CFR50.55a(a)(3(i) ML20216J9171998-04-16016 April 1998 Safety Evaluation Accepting Relief Request MC-R001 for First 10-yr Interval of Containment Insp Program Per 10CFR50.55a (a)(3)(ii),per 971219 Request ML20217K7251998-04-16016 April 1998 Correction to SE of Relief Request MC-R001 Re Qualification Requirements for non-destructive Exam Personnel Performing Containment Insp ML20217H8831998-04-0101 April 1998 Safety Evaluation Supporting Request for Relief for Third ISI Program ML20217K0471998-04-0101 April 1998 Safety Evaluation Authorizing Proposed Alternative in Relief Request NDE-R004 for Plant Third 10-yr ISI Interval,Based on Finding That Compliance W/Code Would Result in Hardship W/O Compensating Increase in Level of Quality & Safety ML20217F8841998-03-23023 March 1998 Safety Evaluation Accepting Third 10-yr Inservice Insp Interval Program Plan Requests for Relief for Plant ML20199J6841997-11-21021 November 1997 SER Approving Relief Requests to Second 10-year Inservice Inspection Interval for Duane Arnold Energy Center ML20140F0121997-06-0606 June 1997 Safety Evaluation Authorizing Proposed Alternatives Contained in Relief Requests HT-014,NDE-019 & NDE-020 ML20140A7091997-05-29029 May 1997 Safety Evaluation Accepting Relief Requests & Action Item Responses for IST Program for Plant ML20141E1811997-05-19019 May 1997 Safety Evaluation Accepting Proposed EAL Changes for DAEC Consistent W/Guidance in NUMARC/NESP-007 ML20133M2921997-01-15015 January 1997 Safety Evaluation of Third Ten Year Interval Inservice Insp Program Plan Request to Use Code N-535 Ies Utilities Inc, Central Iowa Power Cooperative,Corn Belt Power Cooperative, Duane Arnold Energy Center ML20149L8741996-11-12012 November 1996 Safety Evaluation for Ies Utilities of IPE in Response to GL-88-20 & Associated Suppls for License DPR-49 ML20057D6031993-09-24024 September 1993 Safety Evaluation Granting Request for Relief from Certain Exam Requirement of Section XI of ASME Code.Request for Relief RR-001,denied ML20057C9031993-09-24024 September 1993 Safety Evaluation Granting Requested Relief from ASME Code Repair Requirements for Plant D Outboard MSIV ML20128K5231993-02-11011 February 1993 Safety Evaluation Supporting Licensee Response to Staff SE Item Numbers for Pump & Valve IST Program to License DPR-49 ML20198E3191992-11-25025 November 1992 SER Accepting Licensee Response to Suppl 1 to GL-87-02, Committing to Entire GIP-2,including Both SQUG Commitments & Implementation Guidance ML20214N8121986-09-11011 September 1986 Safety Evaluation Accepting Mods to Emergency Diesel Generator Load Sequencer Described in .Mods Assure That Loading of ECCS Pump Motors on Emergency Diesel Generators Will Be Sequenced Per Plant Design Basis 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217H8991999-10-18018 October 1999 SER Approving Licensee Requests for Relief NDE-R001 (Part a & B),NDE-R027,NDE-028,NDE-R029,NDE-R030,NDE-R032 & NDE-R035. Relief Request NDE-036,denied & Relief Request NDE-R-034, Deemed Unnecessary NG-99-1415, Monthly Operating Rept for Sept 1999 for Daec.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Daec.With ML20212H2381999-09-22022 September 1999 Safety Evaluation Supporting Amend 228 to License DPR-49 NG-99-1226, Monthly Operating Rept for Aug 1999 for Duane Arnold Energy Center.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Duane Arnold Energy Center.With NG-99-1115, Monthly Operating Rept for July 1999 for Daec.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Daec.With NG-99-0963, Monthly Operating Rept for June 1999 for Daec.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Daec.With ML20195G9901999-06-0909 June 1999 Safety Evaluation Supporting Amend 227 to License DPR-49 NG-99-0835, Monthly Operating Rept for May 1999 for Daec.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Daec.With ML20206N7551999-05-13013 May 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safey-Related Power-Operated Gate Valves NG-99-0682, Monthly Operating Rept for Apr 1999 for Duane Arnold Energy Center.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Duane Arnold Energy Center.With NG-99-0530, Monthly Operating Rept for Mar 1999 for Daec.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Daec.With ML20207G0251999-03-0303 March 1999 SER Concluding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety- Related MOVs at Duane Arnold & That Licensee Adequately Addressed Actions Requested in GL 96-05 NG-99-0330, Monthly Operating Rept for Feb 1999 for Daec.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Daec.With ML20202B4311999-01-26026 January 1999 Safety Evaluation Accepting Request for Approval to Use ASME Code Case N-508-1 in ISI Program for Duane Arnold Energy Ctr ML20202B3851999-01-26026 January 1999 Safety Evaluation Addressing Thermo-Lag Related Ampacity Derating Issues.Ampacity Derating Analysis Results Acceptable NG-99-0020, Monthly Operating Rept for Dec 1998 for Daec.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Daec.With ML20206N3211998-12-0707 December 1998 Final Part 21 Rept Re Piston Failure of MSIV Actuator at Daec.Rept Indicates That No Reportable Defect Exists,Per 10CFR21 NG-98-2010, Monthly Operating Rept for Nov 1998 for Daec.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Daec.With ML20196F9571998-11-24024 November 1998 Rev 20 to QA Program Description,Ufsar 17.2 for Daec NG-98-1875, Monthly Operating Rept for Oct 1998 for Daec.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Daec.With NG-98-1717, Monthly Operating Rept for Sept 1998 for Daec.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Daec.With NG-98-1767, Cyclic Rept of Facility Changes,Tests & Experiments,Fire Plan & Commitment Changes,For Period from 970301-980930. with1998-09-30030 September 1998 Cyclic Rept of Facility Changes,Tests & Experiments,Fire Plan & Commitment Changes,For Period from 970301-980930. with ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils ML20153B4141998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for DAEC NG-98-1389, Monthly Operating Rept for July 1998 for DAEC1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for DAEC ML20236X5321998-07-29029 July 1998 Safety Evaluation Re USI A-46 Program Implementation for Plant ML20236W0021998-07-29029 July 1998 Safety Evaluation Accepting Request for Relief NDE-R020 Re Third 10-yr ISI Interval of Plant,Per 10CFR50.55a(a)(3(i) ML20236S2541998-07-14014 July 1998 Special Rept 98-01:on 980629,diesel-driven Fire Pump Was Inoperable for Greater than Seven Days.Caused by Sheared Off Tie Rods on Accessory Drive End of Engine.Evaluated Condition,Procured Parts & Replaced Tie Rods ML20236R3251998-06-30030 June 1998 Monthly Operating Rept for June 1998 for DAEC ML20249B5171998-05-31031 May 1998 Monthly Operating Rept for May 1998 for DAEC ML20247P5651998-05-18018 May 1998 Part 21 Rept Re Model SA-A101 MSIV A' Actuator Showing Evidence of Internal Leakage,In Both Directions Past Pneumatic Piston.Situation Being Reviewed to Determine If Failure Could Pose Substantial Safety Hazard ML20247K1881998-05-0808 May 1998 Rev 0 to Cycle 16 COLR, for May 1998 ML20247H9381998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for DAEC ML20216J9171998-04-16016 April 1998 Safety Evaluation Accepting Relief Request MC-R001 for First 10-yr Interval of Containment Insp Program Per 10CFR50.55a (a)(3)(ii),per 971219 Request ML20217K7251998-04-16016 April 1998 Correction to SE of Relief Request MC-R001 Re Qualification Requirements for non-destructive Exam Personnel Performing Containment Insp ML20217K0471998-04-0101 April 1998 Safety Evaluation Authorizing Proposed Alternative in Relief Request NDE-R004 for Plant Third 10-yr ISI Interval,Based on Finding That Compliance W/Code Would Result in Hardship W/O Compensating Increase in Level of Quality & Safety ML20217H8831998-04-0101 April 1998 Safety Evaluation Supporting Request for Relief for Third ISI Program NG-98-0650, Monthly Operating Rept for Mar 1998 for Duane Arnold Energy Center1998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Duane Arnold Energy Center ML20216F6791998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for DAEC ML20217F8841998-03-23023 March 1998 Safety Evaluation Accepting Third 10-yr Inservice Insp Interval Program Plan Requests for Relief for Plant NG-98-0398, Monthly Operating Rept for Feb 1998 for DAEC1998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for DAEC NG-98-0252, Monthly Operating Rept for Jan 1998 for Duane Arnold Energy Center1998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Duane Arnold Energy Center ML20199L3481998-01-31031 January 1998 Rev 0 to Duane Arnold Energy Ctr Emergency Action Level (EAL) Technical Basis Document ML20249B3331997-12-31031 December 1997 1997 Annual Rept for Alliant Corporation ML20249B3391997-12-31031 December 1997 Central Iowa Power Coopertive 1997 Annual Rept ML20249B3351997-12-31031 December 1997 1997 Annual Rept for Corn Belt Power Cooperative NG-98-0017, Monthly Operating Rept for Dec 1997 for Duane Arnold Energy Center1997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Duane Arnold Energy Center NG-97-2118, Monthly Operating Rept for Nov 1997 for DAEC1997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for DAEC ML20199J6841997-11-21021 November 1997 SER Approving Relief Requests to Second 10-year Inservice Inspection Interval for Duane Arnold Energy Center NG-97-1959, Monthly Operating Rept for Oct 1997 for DAEC1997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for DAEC 1999-09-30
[Table view] |
Text
. . f nouq p- k UNITED STATES l .
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NUCLEAR REGULATORY COMMISSION g WASHINGTON, D.C. 20066-0001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION EOR RELIEF REQUEST MC-R001 FOR THE FIRST 10-YEAR INTERVAL OF THE CONTAINMENT INSPECTION PROGRAM E.QB IES UTILITIES INC.
DUANE ARNOLD ENERGY CENTER DOCKET NUMBER: 50-331
1.0 INTRODUCTION
The Technical Specifications for the Duane Amold Energy Center (DAEC) state that the inservice inspection of the American Society of Mechanical Engineers (ASME) Code Class 1,2, and 3 components shall be performed in accordance with Section XI of 'he ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR SU.65a(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 alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if (i) the proposed attematives would provide an acceptable level l of quality and safety, or (ii) compliance with the specified requirements would result in hardship l or unusual difficulty without a compensating increase in the level of quality and safety.
Puisuant to 10 CFR 50.55a(g)(4), ASME Code Class 1,2, and 3 components (including supports) shall meet the requirements, except the design .id access provisions and the pre-l service exar,nination 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) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The applicable ASME Code,Section XI, for the third inspection interval of the Duane Amold Energy Center, is the 1989 Edition. The components (including supports) may meet the requirements set forth in subsequent editions and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b) subject to the limitatione and modifications listed therein and subject to Commission approval.
Enclosure 9804220032 980416 PDR ADOCK 05000331 P PDR
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. l l Pursuant to 10 CFR 50.55a(g)(5), if the licensee determines 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 made for relief from the ASME Code requirement. After evaluation of the determination, pursuant to 10 CFR 50.55a(g)(6)(i), the Commission may grant relief and may impose attemative requirements that are determined to be authorized by law, will not endanger life, property, or the common defense and security, and are othenvise in the public interest, giving due consideration to the burden upon the licensee that could result if the requimments were imposed.
By letter dated December 19,1997, as supplemented on March 18,1998, IES Utilities Inc. (the licensee) submitted a request for relief from the applicable ASME Code,Section XI, requirements for the qualification and certification of non-destructive examination (NDE) personnel for containment inspections at the Duane Amold Energy Center (DAEC).
Specifically, relief is requested from the provisions of Subarticle IWA-2300, " Qualification of Nondestructive Examination Personnel," which requires NDE personnel to be qualified and certified using a written practice in accordance with CP-189, an American Society of
,fondestructive Testing (ASNT) Standard published in 1991 and endorsed in Subarticle IWA-2300.
1 2.0 DISCUSSION Component identification Code Class: MC
References:
IWE-2000 Examination Category: E-A, E-B, E-C, E-D, E-F, E-G, and E-P ltem Number: Allitem numbers
Description:
ASME Section XI Examination and Inspection Procedures for IWE l
' Components Component Numbers: All Components l Code Requirement 10 CFR 50.55a(g)(4)(v) requires that Class MC (IWE) and CC (lWL) pressure retaining components and their integral attachments meet the applicable ASME Section XI examination l and inspection requirements (1992 with the 1992 addenda). (Subsection IWL does not apply to DAEC.)
Relief is requested from the provisions of IWA-2300, " Qualification of 14ondestructive
! Examination Personnel." This requires NDE personnel to be qualified and certified using a written practice in accordance with CP-189, Standard for Quelification and Certification of Nondestructive Testing Personnel, as amended by the requirements of this Division.
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- 3-Licensee's Basis for Relief (as stated) j I
10 CFR 50.55a was amended in the Federal Register (61 FR 41303) to require the use of the 1992 Edition,1992 Addenda, of Section XI when performing containment examinations. A i
written practice based on the requirements of CP-189, as amended by the requirements of the i Subarticle IWA-2300, to implement Subsection IWE duplicates efforts already in place for all i other subsections.10 CFR 50.55a references the 1989 Edition of ASME Section XI for all other i subsections. Subarticle IWA 2300 of Me 1989 Edition requires a written practice based on i SNT-TC-1 A, as amended by the requW monts of Subarticle IWA-2300.
l Further, Subarticle IWA-2300 of the 1992 Edition,1992 Addenda, states, ' Certifications based on SNT-TC-1 A are valid until recertification is required." Visual examination is the primary
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1 nondestructive examination method required by Subsection IWE. Neither CP-189 nor SNT-TC- ;
1 A specifically includes visual examination; thus, the Code requires qualification and l certification to comparable levels as defined in CP-189 or SNT-TC-1 A, as applicable, and the l Emple"er's written practice.
Development and administration of a second program would not enhance safety or quality and ;
would serve as a burden, particularly in developing as a second written practice, tracking of !
certifications, and duplication of paperwork. This duplication would also apply to NDE vendor programs. Updating to the 1992 Edition,1992 Addenda, for Subsections IWB, IWC, etc., would require a similar request for relief.
Relief is requested in accordance with 10 CFR 50.55a(a)(3)(ii). Compliance with the specified ;
requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. )
Licensee's Pronosed Alternative Examination (as stated) i Examinations required by Subsection IWE and IWL shall be cor. ducted by personnel qualified i and certified to a written practice based on SNT-TC-1 A to the current Section XI Code of record.
Relief is requested for the first 10-year interval of the Containment inspection Program for DAEC.
3.0 EVALUATION in Federal Register Notice No.154, Volume 61, dated August 8,1996, the Nuclear Regulatory Commission amended its regulationc to incorpointe by reference the 1992 edition with 1992 addenda of Subsections lWE and IWL of Section Xi of the ASME Boiler and Pressure Vessel Code. Subsections IWF. and IWL provide the requirements for incervice inspection (ISI) of ' i Class CC (concrete containments), and Class MC (metallic containments) of the light-water cooled power plants. The effective date for the amend. ;f ;ub was September 9,1996, and it requires the licensees to incorporate the new requiren.ents into ' heir ISI plans and to complete the first containment inspection by September 0. 2001. H&cvsr, a licensee can submit a
4 -
4 request for relief from one or more requirements of the regulation (or the endorsed code requirements) with proper justification. The provision for granting relief is incorporated in the j regulation.
DAEC submitted its " Third 10-Year Inspection Interval Program Plan" for the staff review in April 1996. The program plan is based on the 1989 Edition of the ASME Section XI requirements for Class 1,2, and 3 components. The 1980 edition of the code requires the use of ASNT-TC-1A for the qualification and certification of NDE personnel. Thus, the staff recognizes that the licensee will have to develop a second program for qualifying and certifying its NDE personnel for containment inspection in acc,ordance with Subarticle IWA-2300 and its associated documentation. Moreover, as pointed out by the licensee, most of the containment examinations required by Subsection IWE are VT-3, general visual. Volumetric examination is required during the containment surface augmented inspection. Because the licensee's current procedure for qualifying and certifying the NDE personnel, based on the provisions of SNT- i TC-1 A, provides reasonable assurance of qualified examiners for Clan 1,2, and 3 I components, the use of NDE personnei qualified by the procedure for containment augmented l examination will not compromise the quality of the examination. The licensee's proposed I altemative is to continue to use CP-189 for certifying and qualifying the NDE personnel for the l next 10-year inspection interval program plan. l As the VT-3 visual examination is the basic examination technique for containment inspection, the licensee has developed procedures for qualifying the visual examination personnel for i vision tests and illumin ation requirements in accordance with IWA-2321 and IWA-2322. j Considering thm factors, the staff concludes that the alternative provides reasonable assurance of qt.daied examiners and that the imposition ~of the requirement of Subarticle IWA-2300 (1992 Edition) for containment inspection will result in hardship without a compensating increase in the level of quality and safety.
- 4. CONCLUSION Based on the review of the information provided in the relief reovest and the response to the staff's request for additional information, the staff finds that the alternative proposed by the licensee in lieu of the code requirement endorsed by the regulation will provida qualified examiners and the imposition of the code requirement would result in hardship without a compensating increase in the level of quality and safety. Accordingly, the request for relief dated December 19,1997, to allow the use of licensee's existing practice for qualifying the NDE personnel for containment inspections until the end of the current inspection interval, is authorized, pursuant to 10 CFR 50.55a(a)(3)(ii).
Principal Contributor: Hans Ashar Date: IPril 16, 1998 e