|
---|
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 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) ML20236X5321998-07-29029 July 1998 Safety Evaluation Re USI A-46 Program Implementation for Plant 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 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
-
yws p k
UNITED STATES
" NUCLEAR REGULATORY COMMISSION wASHm0 ton, D.C. 30006 0MH
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION OF REQUESTS FOR RELIEF NDE-R020 FOR ,
i IES UTILITIES INC. I DUANE ARNOLD ENERGY CENTER DOCKET NO. 50-331
1.0 INTRODUCTION
The Technical Specifications (TS) for Duane Amold Energy Center (DAEC) state that the l 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 the ASME Bojier and Pressure Vessel Code (ASME Code) and applicable addenda as required by Title 10 of the Qda of Federal Regulations (10 CFR) Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55,1(g)(6)(i). Section 50.55a(a)(3) states that attematives to the requirements of paragraph (g) may be used, when authorized by the NRC, if (i) the proposed attematives would provide an acceptable level of quality and safety or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without 3
a compensating increase in the leve! of quality and safety.
J 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 pre-service 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) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The applicable edition of Section XI of the ASME Code for the Duane Amold Energy Center, third 10-year inservice inspection (ISI) interval is the 1989 Edition.
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 j made for relief from the ASME Code requirement. After evaluation of the determination, i pursuant to 10 CFR 50.55a(g)(6)(i), the Commission may grant relief and may impose i attemative 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 l
' imposed.
i I
9808050022 980729 PDR ADOCK 05000331 G PDR
By letter dated April 26,1996, as supplemented on May 15,1998, IES Utilities Inc., the licensee of DAEC, requested relief from the requirements of the ASME Code Section XI,1989 Edition, Article IWF-5000, with regard to visual examination and functional testing of snubbers. Article IWF-5000 references the first addenda to ASME/ ANSI OM-1987, Part 4 (OM-4) for such snubber activities. The licensee requested the continued use of the current TS requirements for snubber .
visual examination and functional testing, pursuant to 10 CFR 50.55a(a)(3)(i).
2.0 DISCUSSION Component identification '
Code Classes: 1,2,3 and MC
References:
ASME,Section XI, IWF-5000 (1989 Edition)
ASME / ANSI OM-1987, Part 4, First Addenda (1988)
Code Case N-491 (TAP-1008) j Examination Category: F-A l Item Number: F1.10, F1.20, F1.30, F1.40
Description:
snubbers 1
Component numbers: All Chss 1,2,3, and MC component snubbers j I
Code Reauireme_n,_1 j l
IWF-5000 references the use of ASME / ANSI OM-1987, Part 4, First Addenda (1988) for rules l goveming visualinspection and functional testing of Class 1,2,3, and MC component snubbers. '
Licensee's Basis for Relief The licensee stated that the current DAEC technical specifications (TS) specify an adequate program for visual examination and functional testing for all safety-related snubbers. The snubber examinations and tests at DAEC are currently performed under TS Section 4.6.H, as amended in accordance with NRC Generic Letter (GL) 90-09, "Altemative Requirements for ,
Snubber Visual inspection Intervals and Corrective Actions," which was approved by the NRC in amendment 203 to the DAEC TS. The licensee stated that the current inspection program, as ]
defined by the TS, provides for a level of quality and safety equal to that of the OM-4. This is ;
based on the fact that the attemative provides the same confidence level, as supported by GL 90-09. Furthermore, the TS snubber program scope includes all safety-related snubbers, which encompasses all Code Class 1,2, and 3 snubbers required to meet the ASME Section XI requirements.
Licensee's Altemative Examination The licensee proposes to continue to use the DAEC TS requirements for visual examination and functional testing for el: ASME Class 1,2,3, and MC component snubbers.
3.0 EVALUATION The staff hac reviewed the licensee's submittal pertaining to the relief request from the l requirements of the ASME Code for visual examination and functional testing of snubbers.
- The staff finds that the licensee's basis for relief is acceptable, because it provides the same confidence level, is in accordance with GL 90-09, and provides assurance that snubbers will u___-___m_ _ _ _ _ _ - _ _ _ _ _ - _ _ - - _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - -
o .
e e
d 3
function and protect the structuralintegrity of safety-related systems and components.
Therefore, the attemative provides an acceptable level of quality and safety,
4.0 CONCLUSION
l i
Based on the information provided, the staff has determined that the licensee has presented an -
adequate justification for the requested relief from the requirements of the ASME Code,1989 i Edition,Section XI, Article IWF-5000 (which references OM-4), with regard to visual examination )
and functional testing of Code Class 1,2, and 3 snubbers. The staff has determined that the {
proposed altemative use of the TS requirement in Section 4.6.H for the Code Class snubbers ]
would provide an acceptable level of quality and safety. Therefore, the attemative in request for !
relief NDE-R020 is authorized pursuant to 10 CFR 50.55a(a)(3)(i).
Principal Contributor: Amold Lee I Date: July 29, 1998 !
l l
I e
_ ._ _ _ _ . _ _ _ _