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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212L1141999-10-0101 October 1999 Safety Evaluation Granting Request for Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c ML20212F5261999-09-22022 September 1999 SER Approving Request Reliefs 1-98-001 & 1-98-200,parts 1,2 & 3 for Second 10-year ISI Interval at Arkansas Nuclear One, Unit 1 ML20211F4281999-08-25025 August 1999 Safety Evaluation Concluding That Licensee Provided Acceptable Alternative to Requirements of ASME Code Section XI & That Authorization of Proposed Alternative Would Provide Acceptable Level of Quality & Safety ML20210K4721999-08-0303 August 1999 SER Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20210D8951999-07-23023 July 1999 Safety Evaluation Accepting First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 - ISI-020 ML20195J8951999-06-17017 June 1999 Safety Evaluation Granting Relief for Listed ISI Parts for Current Interval,Per 10CFR50.55a(g)(5)(iii) ML20207E8631999-06-0303 June 1999 Safety Evaluation Accepting Licensee 990114 Submittal of one-time Request for Relief from ASME B&PV Code IST Requirements for Pressure Safety Valves at Plant,Unit 3 ML20207E7231999-06-0202 June 1999 Safety Evaluation Authorizing Proposed Alternative Exam Methods Proposed in Alternative Exam 99-0-002 to Perform General Visual Exam of Accessible Areas & Detailed Visual Exam of Areas Determined to Be Suspect ML20206M7711999-05-11011 May 1999 SER Accepting Relief Request from ASME Code Section XI Requirements for Plant,Units 1 & 2 ML20206F0691999-04-29029 April 1999 Safety Evaluation Accepting Licensee Re ISI Plan for Third 10-year Interval & Associated Requests for Alternatives for Plant,Unit 1 ML20206A2111999-04-21021 April 1999 Safety Evaluation Authorizing Pump Relief Request PRR-001 & Valve Relief Request VRR-001 & Denying Valve Relief Request VRR-002 ML20205M6941999-04-12012 April 1999 Safety Evaluation Granting Relief for Second 10-yr Inservice Inspection Interval for Plant,Unit 1 ML20205D6061999-03-31031 March 1999 Safety Evaluation Supporting Licensee Proposed Approach Acceptable to Perform Future Structural Integrity & Operability Assessments of Carbon Steel ML20205D5481999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Exam Weld AA with Weld Volume Coverage of 62 Percent for First 10-year Insp Interval Pursuant to 10CFR50.55a(a)(3)(ii) & 10CFR50.55a(g)(6)(ii)(A)(5) ML20205D4711999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Employ Alternative Welding Matls of Code Cases 2142-1 & 2143-1 for Reactor Coolant System to Facilitate Replacement of Steam Generators at Arkansas Nuclear One,Unit 2 ML20205A6331999-03-25025 March 1999 SER Accepting Request to Use Mechanical Nozzle Seal Assemblies as an Alternative Repair Method,Per 10CFR50.55a(a)(3)(i) for Reactor Coolant Sys Applications at Plant,Unit 3 ML20204B1861999-03-15015 March 1999 Safety Evaluation Authorizing Licensee Request for Alternative to Augmented Exam of Certain Reactor Vessel Shell Welds,Per Provisions of 10CFR50.55a(g)(6)(ii)(A)(5) ML20203H8591999-02-17017 February 1999 Safety Evaluation Accepting Licensee Second Ten Year ISI Program & Associated Relief Requests for Plant,Unit 3 ML20199H6261999-01-21021 January 1999 Safety Evaluation Accepting Classification of Instrument Air Tubing & Components for Safety Related Valve Top Works.Staff Recommends That EOI Revise Licensing Basis to Permit Incorporation of Change ML20198M7841998-12-29029 December 1998 SER Accepting Util Proposal to Use ASME Code Case N-578 as Alternative to ASME Code Section Xi,Table IWX-2500 for Arkansas Nuclear One,Unit 2 ML20196F4911998-12-0101 December 1998 SER Accepting Request for Relief ISI2-09 for Waterford Steam Electric Station,Unit 3 & Arkansas Nuclear One,Unit 2 ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program ML20155H3491998-11-0303 November 1998 Safety Evaluation Granting Requests for Relief RR2-0001, RR2-0002 & RR2-0003 ML20154J2471998-10-0909 October 1998 SER Accepting Inservice Testing Program,Third ten-year Interval for License DPR-51,Arkansas Nuclear One,Unit 1 ML20151S5421998-09-0303 September 1998 Safety Evaluation Opposing Licensee Thermal Model as Currently Implemented.Evaluation Recommended to Be Used in Any follow-up Site Insp ML20237C5661998-08-17017 August 1998 Safety Evaluation Accepting Licensee Request for Exemption from Section Iii.O of Appendix R to 10CFR50 ML20236S9031998-07-22022 July 1998 SER Accepting Rev 19 to Quality Assurance Program for Waterford Steam Electric Station,Unit 3 ML20249A6431998-06-12012 June 1998 SER Accepting 980427 Request for Change to River Bend QA Manual Program Description,Per 10CFR50.54(a)(3) ML20248D7491998-05-28028 May 1998 Safety Evaluation Accepting Licensee Request for Relief from ASME Code Repair Requirements for ASME Code Class 3 Piping ML20217A7211998-04-17017 April 1998 Safety Evaluation Supporting Proposed Alternative for ANO-1 to Implement Code Case N-533 (w/4 H Hold Time at Test Conditions Prior to VT-2 Visual Exam) ML20217P8281998-04-0707 April 1998 Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i) ML20216D6111998-03-12012 March 1998 Safety Evaluation Supporting Amend 188 to License NPF-6 ML20203E9371997-12-0909 December 1997 Safety Evaluation Granting Relief Request,Per 10CFR50.55a(g) (I) ML20202F0191997-11-28028 November 1997 Safety Evaluation Approving Transfer of License NPF-47 for River Bend Station,Unit 1 ML20199H3711997-11-19019 November 1997 SER Accepting Approving Request Relief from Requirements of Section XI, Rule for Inservice Insp of NPP Components, of ASME for Current or New 10-year Inservice Insp Interval IAW 50.55(a)(3)(i) of 10CFR50 ML20216E9921997-09-0404 September 1997 Safety Evaluation Accepting 970623 Request for Relief Re Authorization for Use of ASME Code Case N-416-1 & N-532,ISI Program for Listed Plants ML20141H8411997-07-30030 July 1997 Safety Evaluation Accepting Use of Code Case N-508-1 for All Four Plants for Rotation of Serviced Snubbers & Pressure Relief Valves for Purpose of Testing in Lieu of ASME Code ML20141F3881997-06-30030 June 1997 Safety Evaluation Authorizing Licensee Request for Extension of First ISI Interval to 970924 ML20148H1271997-06-0505 June 1997 Supplemental Safety Evaluation Re Conformance to Reg Guide 1.97,Entergy Operations,Inc,Waterford Steam Electric Station Unit 3 ML20138K0561997-05-0505 May 1997 SER Approving Licensees IPE Process Capable of Identifying Severe Accidents & Severe Accident Vulnerabilities,For Plant,Unit 2 ML20138C8501997-04-28028 April 1997 Safety Evaluation Authorizing Proposed Alternative to Vibration Measurement Requirements of OM-6,paragraph 4.6.4 (B),For Standby Svc Water Pumps & Diesel Fuel Oil Transfer Pumps,Per 10CFR50.55a(a)(3)(ii) ML20147H4371997-03-31031 March 1997 Safety Evaluation Accepting Proposed P-T Limits for Heatup, Cooldown,Inservice Leak & Hydrostatic Testing & Core Criticality ML20149M4221996-12-12012 December 1996 Safety Evaluation Supporting Update Insvc Insp Programs to 1992 & Portions of 1993 ASME Boiler & Pressure Vessel Code, Sect XI for Licenses DPR-51,NPF-6,NPF-38,NPF-29 & NPF-47. Technical Ltr Rept Encl ML20134P8411996-11-25025 November 1996 Safety Evaluation Denying Request for Relief 96-001 Re Second 10-yr Interval ISI Program Plan,Due to Failure to Provide Basis for Impracticality ML20107F5611996-04-17017 April 1996 Safety Evaluation Providing Guidance on Submitting plant- Specific Info W/Respect to IST Program Alternatives Request ML20149K9451996-02-16016 February 1996 Safety Evaluation Authorizing Relief Request for Second 10-yr Interval IST Program Plan for Pumps & Valves at Facility ML20149E8831994-08-0202 August 1994 Safety Evaluation Accepting Interim Relief Request IRR-03 Re Drywell Isolation Check Valves in Equipment Drain Lines & Reactor Equipment Closed Cooling Water Sys ML20058L6111993-12-13013 December 1993 Safety Evaluation Approving Second ten-year Interval Inservice Insp Request for Relief Re Use of IWA-5250 Requirements Listed in 1992 Edition of ASME Code ML20058H0221993-11-30030 November 1993 Safety Evaluation Accepting Licensee Proposed Alternative to ASME Code Requirements in PRR 15,per 10CFR50.55(a)(3)(i). Denies Pump Relief Request 14 ML20058F6661993-11-24024 November 1993 Safety Evaluation Accepting Licensee Proposed Use of New DG as Alternate AC Power Source for Coping W/Sbo Subject 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L8931999-10-31031 October 1999 Rev 1 to BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20217F2891999-10-13013 October 1999 Drill 99-08 Emergency Preparedness Exercise on 991013 ML20212L1141999-10-0101 October 1999 Safety Evaluation Granting Request for Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c 0CAN109902, Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With RBG-45144, Monthly Operating Rept for Sept 1999 for River Bend Station. with1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for River Bend Station. with ML20217G7211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Waterford 3 Ses. with ML20216J6271999-09-27027 September 1999 Rev 0 to CALC-98-R-1020-04, ANO-1 Cycle 16 Colr ML20212F5261999-09-22022 September 1999 SER Approving Request Reliefs 1-98-001 & 1-98-200,parts 1,2 & 3 for Second 10-year ISI Interval at Arkansas Nuclear One, Unit 1 ML20216G1201999-09-0909 September 1999 Rev 3 to Rbs,Cycle 9 Colr 0CAN099907, Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with RBG-45110, Monthly Operating Rept for Aug 1999 for River Bend Station, Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for River Bend Station, Unit 1.With ML20211Q2141999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Waterord 3 Ses.With ML20211F4281999-08-25025 August 1999 Safety Evaluation Concluding That Licensee Provided Acceptable Alternative to Requirements of ASME Code Section XI & That Authorization of Proposed Alternative Would Provide Acceptable Level of Quality & Safety RBG-45087, Special Rept:On 990510,LPCI a & LPCS Injected Into Rv for Less than Two Minutes.Caused by Electrical Transient in One of ECCS Power Supplies.Operators Verified Reactor Cavity Level & Closed Injection Valves to Stop Injection1999-08-0606 August 1999 Special Rept:On 990510,LPCI a & LPCS Injected Into Rv for Less than Two Minutes.Caused by Electrical Transient in One of ECCS Power Supplies.Operators Verified Reactor Cavity Level & Closed Injection Valves to Stop Injection ML20210K4721999-08-0303 August 1999 SER Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves 0CAN089904, Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with RBG-45091, Monthly Operating Rept for July 1999 for River Bend Station, Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for River Bend Station, Unit 1.With ML20210Q6361999-07-31031 July 1999 Corrected Monthly Operating Rept for July 1999 for Waterford 3 ML20210S0581999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Waterford 3.With ML20210K8831999-07-29029 July 1999 Non-proprietary Addendum B to BAW-2346P,Rev 0 Re ANO-1 Specific MSLB Leak Rates ML20210D8951999-07-23023 July 1999 Safety Evaluation Accepting First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 - ISI-020 ML20210C6391999-07-0202 July 1999 Rev 2 to River Bend Station,Cycle 9 Colr 0CAN079903, Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with RBG-45055, Monthly Operating Rept for June 1999 for River Bend Station, Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for River Bend Station, Unit 1.With ML20209H3781999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Waterford 3 Ses. with ML20196J8031999-06-24024 June 1999 Rev 1 to Rbs,Cycle 9 Colr ML20195J8951999-06-17017 June 1999 Safety Evaluation Granting Relief for Listed ISI Parts for Current Interval,Per 10CFR50.55a(g)(5)(iii) ML20207E8631999-06-0303 June 1999 Safety Evaluation Accepting Licensee 990114 Submittal of one-time Request for Relief from ASME B&PV Code IST Requirements for Pressure Safety Valves at Plant,Unit 3 ML20207E7231999-06-0202 June 1999 Safety Evaluation Authorizing Proposed Alternative Exam Methods Proposed in Alternative Exam 99-0-002 to Perform General Visual Exam of Accessible Areas & Detailed Visual Exam of Areas Determined to Be Suspect ML20196A6251999-05-31031 May 1999 Non-proprietary Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20196A0191999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Arkansas Nuclear One,Units 1 & 2.With RBG-45028, Monthly Operating Rept for May 1999 for River Bend Station, Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for River Bend Station, Unit 1.With ML20195K3391999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Waterford 3 Ses.With ML20195C3041999-05-28028 May 1999 Annual Rept on Abb CE ECCS Performance Evaluation Models ML20195D1991999-05-28028 May 1999 Probabilistic Operational Assessment of ANO-2 SG Tubing for Cycle 14 ML20206M7711999-05-11011 May 1999 SER Accepting Relief Request from ASME Code Section XI Requirements for Plant,Units 1 & 2 0CAN059903, Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with RBG-45016, Monthly Operating Rept for Apr 1999 for River Bend Station, Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for River Bend Station, Unit 1.With ML20206S7401999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Waterford 3.With ML20206F0691999-04-29029 April 1999 Safety Evaluation Accepting Licensee Re ISI Plan for Third 10-year Interval & Associated Requests for Alternatives for Plant,Unit 1 ML20205T2621999-04-22022 April 1999 LER 99-S02-00:on 990216,contract Employee Inappropriately Granted Unescorted Access to Plant Protected Area.Caused by Personnel Error.Security Personnel Performed Review of Work & Work Area That Individual Was Involved with ML20206A2111999-04-21021 April 1999 Safety Evaluation Authorizing Pump Relief Request PRR-001 & Valve Relief Request VRR-001 & Denying Valve Relief Request VRR-002 ML20205M6941999-04-12012 April 1999 Safety Evaluation Granting Relief for Second 10-yr Inservice Inspection Interval for Plant,Unit 1 ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20205R6351999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Ano,Units 1 & 2. with ML20205D6061999-03-31031 March 1999 Safety Evaluation Supporting Licensee Proposed Approach Acceptable to Perform Future Structural Integrity & Operability Assessments of Carbon Steel RBG-44969, Monthly Operating Rept for Mar 1999 for River Bend Station, Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for River Bend Station, Unit 1.With ML20205N9671999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Waterford 3 Ses.With ML20205E8531999-03-30030 March 1999 Corrected Pages COLR 3/4 1-4 & COLR 3/4 2-6 to Rev 1, Cycle 10, Colr ML20205D4711999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Employ Alternative Welding Matls of Code Cases 2142-1 & 2143-1 for Reactor Coolant System to Facilitate Replacement of Steam Generators at Arkansas Nuclear One,Unit 2 1999-09-09
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M p T UNITED STATE 8 s
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2 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. seseMo01
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SgETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGUI,All0N 1
RELATED TO REQUESTS FOR RELIEF TO USE ASME CODE CASE N-508-1
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l ENTERGY OPERATIONS. INC.. ET AL.
l ARKANSAS NUCLEAR ONE. UNITS 1 & 2 l RIVER BEND STATION ;
! WATERFORD 3 STEAM ELECTRIC STATION l DOCKET NOS. 50-313. 50-368. 50-458. AND 50-382 i'
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1.0 INTRODUCTION
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l l The Code of Federal Regulations,10 CFR 50.55a, requires that inservice ;
inspt.ction (ISI) of certain ASME Code Class 1, 2, and 3 components be jl performed in accordance with Section XI of the American Society of mechanical ;
l
} ; Engineers (ASME) Boiler and Pressure Vassel (B&PV) Code, applicable Edition J
- and Addenda, except where specific written relief has been requested by the i licensee and granted by the Commission pursuant to paragraph 10 CFR 50.55a(g)(6)(1), or alternatives approved pursuant to 10 CFR 50.55a(a)(3). In I proposed alternatives, the licensee must demonstrate that
- (1) the proposed' .
alternatives provide an acceptable level of quality and safety; or (ii) l compliance would result in hardship or unusual difficulty without. a '
compensating increase in the level of quality and safety.- In requesting relief, the licensee must demonstrate that the requirement is impractical for their facility.
10 CFR 50.55a authorizes the Nuclear Regulatory Commission (NRC) to grant relief from ASME Code requirements upon making the necessary findings for such authorizations. The NRC staff's finding with respect to granting or not granting the relief request as part of the' licensee's ISI program is contained in this Safety Evaluation which addresses the request by Entergy Operations, Inc. (the licensee) for approval to use the ASME Code Case N-508-1 as an alternative to the ASME Code,Section XI requirements for the Arkansas Nuclear One Units 1 and 2, Waterford 3 Steam Electric Station, and River Bend Station (the four plants). The request was forwarded in the licensee's letters dated June 20, 1996, and January 14 and May 12, 1997.
The ISI program for the current interval for the Waterford 3 and River Bend Stations is based on the repair and replacement requirements of Section XI of the ASME Code, 1980 Edition through the Winter 1981 Addenda and the new interval will be based on the 1992 Edition. For Arkansas Units 1 and 2, the current interval is based on the 1986 Edition and the new interval for Unit I will.be based on the 1992 Edition.
ENCLOSURE 9700010220 970730 PDR ADOCK 05000313 P PDR
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2.0 BACKGROUND
ASME Code Section XI Reauirement:
i Article IWA-7000, Replacement, specifies the rules and requirement.s to be used when replacing, among other items, relief. valves and snubbers. In that
- article the owner's respor.sibilities are defined and require the owner to i develop a replacement program that meets the requirements of Section IWA-7130, l Replacement Program. When a component is replaced under this program, IAW-7000 requires the preparation of a replacement plan and Form NIS-2, i performance of specific Section XI reviews and evaluations, and review and i
concurrence of the Authorized Nuclear Inspector. These requirements apply even when removing and installing relief valves and snubbers solely for the <
l purpose of testing.
l Code Case N-508-1. " Rotation of Serviced Snubbers and Pressure Relief Valves i for the Purpose of Testina.Section XI. Division 1" Reauirements:
l Code Case N-508-1 provides an alternative to Article IWA-7000 when pressure i relief valves and snubbers are rotated from stock and installed on components i (including piping systems) within the Section XI boundary. Specific L requirements, that are detailed in Code Case N-508-1, must be met when ,
rotating components from stock for the purpose of testing. These requirements l include: the items must be of the same design and construction; the items '
shall have no evidence of failure at the time of removal; items being rotated shall be removed and installed only by mechanical means; items being installed shall previously have been in service; preservice inspections and pressure tests shall be performed as required by IWA-7000; traceability of inservice inspection and testing shall be maintained; the use of an NIS-2 form is not required arcept for repair or replacement of the rotated item; testing of removed snubbers and pressure relief valves, including required sample expansions, shall be in accordance with the owner's test program; and repair or replacement of removed items shall be performed in accordance with IWA-7000.
Staff Review of Code Case N-508-1:
The staff has reviewed Code Case N-508-1 for acceptability and inclusion in Regulatory Guide 1.147, " Inservice Inspection Code Case Acceptability ASME Section XI Division 1." The staff concluded that it would not approve the generic use of the Code Case. The staff's concern was the Code Case did not provide assurance that its application would net adversely impact the existing snubber service life monitoring program. Specifically, when snubbers are rotated between stock and installation, without involving the preparation of a Section XI repair / replacement plan and the subsequent submittal of a Form NIS-2, traceability of the snubbers service life could be compromised. The staff. concluded that it would review the use of the Code Case on a plant-by-plant basis.
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3.0 RELIEF RE00EST i
l The licensee requests relief from the ASME Code,Section XI, Article IWA-7000 t
- replacement requirements for snubbers and pressure relief valves. The j licensee proposed as an alternative to the ASME Code,Section XI requirements,
- to use the ASME Code Case N-508-1, titled, " Rotation of Serviced Snubber and
, Pressure Relief Valves for the Purpose of Testing" at Arkansas Units 1 and 2, Waterford 3 and River Bend. The licensee requested approval to use the Code
! Case for snubbers and relief valves that are rotated for testing as an alternative to the requirements of ASME Section XI, Article IWA-7000.
! The licensee stated that currently, when a snubber or relief valve is removed for testing, the activity is required to be treated like an ASME Code,
! l Section XI, Article IWA-7000 replacement activity. This entails the use of i replacement programs, replacement plans, suitable evaluations, ~ unique reviews within the licensee'sSection XI programs, review and concurrence by an Authorized Nuclear Inspector, and maintenance of NIS-2 or other Section XI docuantation to record the replacement. This activity requires the degraded system to remain out of service for the time that the item is removed, tested, ;
refurbished if necessary, ar.d replaced. The licensee considers these Code (
provisions appropriate when the components are replaced due to design changes, I failures or expiration of component life. However, these activities are l considered excessive for the removal and installation of snubbers and pressure relief valves solely for the purpose of testing. .
The licensee proposed to use Code Case N-508-I when a snubber or pressure relief valve is removed from a system for the purpose of testing, to rotate a i replacement component from spares into its place and to test the removed l component at a later time. The use of the code case allows the licensee to minimize the time that a degraded system remains out of service and reduces i administrative requirements and documentation. The licensee indicated that all the technical requirements for the replacement, test, and repair of l snubbers and pressure relief valves are still maintained in a manner that provides an acceptable level of safety that is consistent with the level of s'afety afforded by compliance with the ASME Section XI requirements that are currently being implemented at each of the licensee's facilities.
If the snubber or relief valve being removed requires a repair or replacement l (i.e., shows evidence of failure) then the replacement of the item will be a typical ASME Code Section XI repair or replacement and not under this Code Case, and the required Section XI documentation will be completed. The use of the Code Case only eliminates unnecessary administrative controls and documentation requirements associated with a replacement of a snubber er relief valve when the item is rotated for testing.
I 4.0 EVALUATION Code Case N-508-1 provides an alternative to the current ASME Code,Section XI, Article IWA-7000 requirement to generate a replacement program when removing snubbers or pressure relief valves from a system for testing. The
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code case allows snubbers and pressure relief valves to be rotated from stock and installed on components and piping systems within the Section XI boundary, provided all the requirements stated in the code case are met.
The code case was approved by ASME on May 11, 1994, however, its use has not been approved by the NRC for any nuclear power plants without the licensees requesting the use of the code case. The staff reviewed the code case and determined that the current text of the code case does not provide assurance that its application will not adversely impact the existing snubber ervice life monitoring program. In response to this concern, the licensee stated that its commitments and programs in effect for monitoring snubber and pressure relief valves service life at the four plants are unaffected by the alternatives of Code- Case N-508-1.
The licensee has agreed to all the Code Case requirements. Further, if the component being removed shows evidence of failure, the licensee will not use Ccde Case N-508-1, but will use ASME Code Section XI, Article IWA-7000 of the ASME B&PV Code for repair or replacement activities.
The licensee's proposed alternative to use Code Case N-508-1, with the provision that the snubber service-life monitoring program is not changed, for the purpose of testing snubbers and pressure relief valves, will eliminate unnecessary administrative and documentation requirements, minimize the time during which the affected system is out of service, and provide an acceptable level of quality and safety in.that adequate assurance of snubber reliability will be maintained.
In considering the licensee's proposed use of Code Case N-508-1, and the responte in addressing the staff's concerns with regard to an adverse impact on the existing snubber sorvice life monitoring program, the staff has determined that the application for the four plants is acceptable.
5.0 CONCLUSION
The staff concludes that the licensees' proposed alternative to use Code Case N-508-1, at the above four plants, for rotation of serviced snubbers and pressure relief valves for the purpose of testing in lieu of ASME Code,Section XI, Article IWA-7000 requirements is authorized by law, pursuant to 10 CFR 50.55a(3)(a)(1). This is based on the staff's determination that the '
use of Code Case N-508-1 at these plants provides an acceptable level of i quality and safety.
Principal Contributor: F. Grubelich Dato: July 30,1997 p -- -p ,omv n-