Safety Evaluation Accepting Licensee Proposed Alternative to Snubber Visual Inservice Exam Intervals & Sampling Rates Requirements Contained in ASME Code,Section Xi,Subsection Iwf,Article IWF-5000ML20154L659 |
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FitzPatrick |
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10/14/1998 |
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NRC (Affiliation Not Assigned) |
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ML20154L642 |
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NUDOCS 9810200023 |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20216D9541999-07-28028 July 1999 Safety Evaluation Authorizing Proposed Alternatives for Second 10-year Interval Pursuant to 10CFR50.55a(a)(3)(ii) ML20202J0891999-02-0303 February 1999 Safety Evaluation Accepting Rev 2 of Third Interval Inservice Testing Program for Pumps & Valves for James a FitzPatrick Nuclear Power Plant ML20196J3501998-12-0404 December 1998 SER Accepting License Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20196F9251998-11-25025 November 1998 Safety Evaluation Re Thrid 10-year Interval Inservice Insp Program Relief Requests for Plant ML20195K4211998-11-17017 November 1998 Safety Evaluation Authorizing Proposed Alternative in Relief Request VRR-05 Per 10CFR50.55a(a)(3)(i) & PRR-01,PRR-02R1, PRR-03,PRR-04,VRR-02,VRR-03 & VRR-04 Per 10CFR50.55a(a)(3)(ii) ML20195E1051998-11-13013 November 1998 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves, Issued 950817 ML20155H5801998-11-0303 November 1998 Safety Evaluation Authorizing Postponement of Beginning of Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) Re ASME Code,Section XI ML20155H5321998-11-0303 November 1998 Safety Evaluation Authorizing Alternative to ASME Code Requirements for CRD Bolting ML20154L6591998-10-14014 October 1998 Safety Evaluation Accepting Licensee Proposed Alternative to Snubber Visual Inservice Exam Intervals & Sampling Rates Requirements Contained in ASME Code,Section Xi,Subsection Iwf,Article IWF-5000 ML20153D2591998-09-21021 September 1998 SER Accepting Proposed Alternative Testing of Containment Following ECCS Suction Strainer Replacement ML20236V8181998-07-29029 July 1998 Safety Evaluation Accepting Request for Relief from Implementation of Requirements of 10CFR50.55a Related to Containment Repair & Replacement Activities for James a FitzPatrick Nuclear Power Plant ML20236X5881998-07-29029 July 1998 Safety Evaluation Supporting Amend 245 to License DPR-59 ML20154L9201998-07-10010 July 1998 SER Accepting Rev to Reactor Vessel Surveillance Capsule Withdrawal Schedule for James a Fitzpatrick Nuclear Power Plant ML20217A4631998-03-23023 March 1998 Safety Evaluation Accepting Use of Three Heats/Lots of Hot Rolled XM-19 Matl in Core Shroud Repair Assemblies Re Licenses DPR-16 & DPR-59,respectively ML20198S3031998-01-14014 January 1998 Supplemental SE Accepting RG 1.97,rev 2 Recommendations for Containment Isolation Valve Position Indication Instrumentation at NPP ML20128G2441993-02-0909 February 1993 Correction to NRC SE Associated W/Ts Amend 184,dtd 921217. SE Restates Portion of Section 2.0 ML20126F4771992-12-23023 December 1992 Safety Evaluation Granting Licensee Relief from ASME Code Requirements for Repair of RWCU Equalizing Line Until Next Refueling Outage ML20059K4331990-09-13013 September 1990 Safety Evaluation Accepting Util 881110,890328 & 900129 Submittals Re IGSCC Insp & Repair for Facility Reload 8/ Cycle 9 Refuel Outage ML20056B4011990-08-20020 August 1990 Safety Evaluation Approving Licensee Relief Request R14 & Denying Requests R15 & R5A Re Hydrostatic Test Requirements ML20058P4331990-08-13013 August 1990 Safety Evaluation Accepting ATWS Recirculation Pump Trip Sys Design Mod ML20206F5701988-11-18018 November 1988 Safety Evaluation Re Compliance w/10CFR50.62 ATWS Rule Re Alternate Rod Injection & Recirculating Pump Trip Sys ML20206D5231988-11-10010 November 1988 Safety Evaluation Supporting 880309 Request for Relief from Hydrostatic Test Requirement for HPCI & Rcic,Provided That Alternative Testing Performed ML20148B1001988-03-14014 March 1988 Safety Evaluation Accepting Util Justification for Deviations from Reg Guide 1.97 for post-accident Monitoring Variables ML20236G5801987-10-27027 October 1987 Safety Evaluation Supporting Util 850930,860827 & 1208 Submittals of Second 10-yr Inservice Insp Program Plan & Associated Relief Requests from ASME Code Insp Requirements ML20238E1461987-09-0808 September 1987 Safety Evaluation of Util 870415 Proposed Design for Standby Liquid Control Sys.Design Meets Requirements of 10CFR50.62 Re ATWS ML20237L5241987-09-0101 September 1987 Safety Evaluation Supporting Util 831109,840629 & 850702 Responses to Generic Ltr 83-28,Items 2.1 & 4.5.2 Re Equipment Classification & Vendor Interface & Reactor Trip Sys Reliability, Respectively ML20236J8151987-07-30030 July 1987 Safety Evaluation Re Insps for & Repairs of IGSCC During Reload 7/Cycle 8 Refueling Outage.Facility Can Be Safely Operated for One 18-month Fuel Cycle in Present Configuration ML20212F9421986-12-31031 December 1986 Safety Evaluation Supporting Amend to License DPR-59, Changing Tech Specs Re Second Level of Undervoltage Protection ML20214R5871986-11-24024 November 1986 Safety Evaluation Accepting Util Actions to Ensure Structural Integrity of Vacuum Breakers in Mark I Containments ML20210T3101986-10-0202 October 1986 Safety Evaluation Accepting Util 860228 Submittal of Rev 2 to Offsite Dose Calculation Manual on Interim Basis ML20205E3601986-08-0606 August 1986 Safety Evaluation on Util 830806,1109 & 840330 Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1. Licensee Complied W/All Items ML20210K5571986-04-18018 April 1986 Safety Evaluation Supporting Util Request for Relief from First 10-yr Inservice Insp Requirements for Class 1,2 & 3 Components ML20137S9901985-09-26026 September 1985 Safety Evaluation Accepting MSIV Leakage Control Sys,Per GDC 54, Piping Sys Penetrating Containment ML20134D2071985-08-0909 August 1985 Safety Evaluation of Util 831109 & 840629 Responses to Generic Ltr 83-28,Item 1.1, Post-Trip Review (Program Description & Procedure). Program & Procedures Acceptable ML20133F0011985-07-30030 July 1985 Safety Evaluation Accepting Util 831109 & 840629 Responses to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing ML20129E1721985-07-0101 July 1985 Safety Evaluation Re Radiological Consequences of Hypothetical LOCA While Purging Containment at Power. Radiological Consequences Acceptable ML20129E1411985-07-0101 July 1985 Safety Evaluation Supporting Demonstration of Containment Purge & Vent Valve Operability.Info Submitted Demonstrates Ability of 20-inch & 24-inch Purge & Vent Valves to Close Against Buildup of Containment Pressure During Dba/Loca ML20127E7221985-06-17017 June 1985 SER Supporting Util 840629 Response to Generic Ltr 84-09, Recombiner Capability Requirements of 10CFR50.44(c)(3)(ii) ML20127B3251985-06-10010 June 1985 Interim Safety Evaluation Approving Util 830630 Procedures Generation Package (PGP) for Emergency Operating Procedures Upon Resolution of Exceptions Noted in Section 2.PGP Submitted Per Generic Ltr 82-33 Re Suppl 1 to NUREG-0737 ML20127C7961985-06-0606 June 1985 Safety Evaluation Re Insp & Repair of RCS Piping.Plant Can Be Safely Returned to Operation in Present Configuration for Duration of Cycle 7 ML20140G5731975-07-15015 July 1975 Safety Evaluation Supporting Tech Spec Changes to License DPR-59 to Revise Suppression Pool Water Temp Limits 1999-07-28
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARJAFP-99-0277, Monthly Operating Rept for Sept 1999 Fpr Ja FitzPatrick Nuclear Power Plant.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 Fpr Ja FitzPatrick Nuclear Power Plant.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data JAFP-99-0261, Monthly Operating Rept for Aug 1999 for Jafnpp.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Jafnpp.With JAFP-99-0236, Monthly Operating Rept for July 1999 for Ja FitzPatrick Npp. with1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Ja FitzPatrick Npp. with ML20216D9541999-07-28028 July 1999 Safety Evaluation Authorizing Proposed Alternatives for Second 10-year Interval Pursuant to 10CFR50.55a(a)(3)(ii) ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept JAFP-99-0211, Monthly Operating Rept for June 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Ja FitzPatrick Nuclear Power Plant.With JAFP-99-0175, Annual Summary of Changes,Tests & Experiments for 1997/1998. with1999-06-0202 June 1999 Annual Summary of Changes,Tests & Experiments for 1997/1998. with JAFP-99-0181, Monthly Operating Rept for May 1999 for Jafnpp.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Jafnpp.With JAFP-99-0166, Monthly Operating Rept for Apr 1999 for Ja FitzPatrick Nuclear Plant.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Ja FitzPatrick Nuclear Plant.With JAFP-99-0142, Monthly Operating Rept for Mar 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Ja FitzPatrick Nuclear Power Plant.With JAFP-99-0092, Monthly Operating Rept for Feb 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Ja FitzPatrick Nuclear Power Plant.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML20202J0891999-02-0303 February 1999 Safety Evaluation Accepting Rev 2 of Third Interval Inservice Testing Program for Pumps & Valves for James a FitzPatrick Nuclear Power Plant ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc JAFP-99-0011, Monthly Operating Rept for Dec 1998 for Ja FitzPatrick Nuclear Power Plant.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Ja FitzPatrick Nuclear Power Plant.With ML20198F9991998-12-0404 December 1998 Assessment of Licensing Basis for Use of Containment Overpressure Credit for Net Positive Suction Head Analyses Power Authority of State of New York,James a Fitzpatrick Nuclear Power Plant ML20196J3501998-12-0404 December 1998 SER Accepting License Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves JAFP-98-0396, Monthly Operating Rept for Nov 1998 for Ja FitzPatrick Npp. with1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Ja FitzPatrick Npp. with ML20196F9251998-11-25025 November 1998 Safety Evaluation Re Thrid 10-year Interval Inservice Insp Program Relief Requests for Plant ML20195J7521998-11-18018 November 1998 Rev 7 to Jaf Colr ML20195K4211998-11-17017 November 1998 Safety Evaluation Authorizing Proposed Alternative in Relief Request VRR-05 Per 10CFR50.55a(a)(3)(i) & PRR-01,PRR-02R1, PRR-03,PRR-04,VRR-02,VRR-03 & VRR-04 Per 10CFR50.55a(a)(3)(ii) ML20195E1051998-11-13013 November 1998 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves, Issued 950817 ML20197G6221998-11-0606 November 1998 Non-proprietary Rev 7 to HI-971661, Licensing Rept for Reracking of Ja FitzPatrick Sfp ML20155H5321998-11-0303 November 1998 Safety Evaluation Authorizing Alternative to ASME Code Requirements for CRD Bolting ML20155H5801998-11-0303 November 1998 Safety Evaluation Authorizing Postponement of Beginning of Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) Re ASME Code,Section XI JAFP-98-0360, Monthly Operating Rept for Oct 1998 for Ja FitzPatrick Nuclear Power Plant.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Ja FitzPatrick Nuclear Power Plant.With ML20155C2821998-10-30030 October 1998 Non-proprietary Rev 0 to GENE-187-30-1598 Np, CRD Bolting Flaw Evaluation for Ja FitzPatrick Nuclear Power Plant ML20154L6591998-10-14014 October 1998 Safety Evaluation Accepting Licensee Proposed Alternative to Snubber Visual Inservice Exam Intervals & Sampling Rates Requirements Contained in ASME Code,Section Xi,Subsection Iwf,Article IWF-5000 JAFP-98-0322, Monthly Operating Rept for Sept 1998 for Ja Fitzpatrick Nuclear Power Plant.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Ja Fitzpatrick Nuclear Power Plant.With ML20153D2591998-09-21021 September 1998 SER Accepting Proposed Alternative Testing of Containment Following ECCS Suction Strainer Replacement ML20153B5611998-09-0101 September 1998 Rev 1 to JAF-SE-98-013, RHR & Core Spray Suppression Pool Suction Strainer Replacement ML20151X6891998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Ja FitzPatrick Nuclear Power Plant ML20237E8361998-08-25025 August 1998 Rev 6 to Colr ML20237E9471998-08-0808 August 1998 Rev 6 to Colr JAFP-98-0264, Monthly Operating Rept for July 1998 for Ja FitzPatrick Nuclear Plant1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Ja FitzPatrick Nuclear Plant ML20236X5881998-07-29029 July 1998 Safety Evaluation Supporting Amend 245 to License DPR-59 ML20236V8181998-07-29029 July 1998 Safety Evaluation Accepting Request for Relief from Implementation of Requirements of 10CFR50.55a Related to Containment Repair & Replacement Activities for James a FitzPatrick Nuclear Power Plant ML20153B5781998-07-28028 July 1998 Rev 0 to JAF-SE-98-025, HPCI & RCIC Suppression Pool Suction Strainer Replacement ML20236X3831998-07-14014 July 1998 Rev 2 to JAF-RPT-MULTI-02671, Summary of Detailed Evaluation for NRC Generic Ltr 96-06 ML20154L9201998-07-10010 July 1998 SER Accepting Rev to Reactor Vessel Surveillance Capsule Withdrawal Schedule for James a Fitzpatrick Nuclear Power Plant JAFP-98-0222, Monthly Operating Rept for June 1998 for Ja FitzPatrick Nuclear Power Plant1998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Ja FitzPatrick Nuclear Power Plant JAFP-98-0193, Monthly Operating Rept for May 1998 for Ja FitzPatrick Nuclear Plant1998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Ja FitzPatrick Nuclear Plant ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted JAFP-98-0168, Monthly Operating Rept for Apr 1998 for Ja FitzPatrick Nuclear Power Plant1998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Ja FitzPatrick Nuclear Power Plant JAFP-98-0128, Monthly Operating Rept for Mar 1998 for Ja FitzPatrick Nuclear Power Plant1998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Ja FitzPatrick Nuclear Power Plant ML20217A4631998-03-23023 March 1998 Safety Evaluation Accepting Use of Three Heats/Lots of Hot Rolled XM-19 Matl in Core Shroud Repair Assemblies Re Licenses DPR-16 & DPR-59,respectively JAFP-98-0091, Monthly Operating Rept for Feb 1998 for JAFNPP1998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for JAFNPP ML20202G9081998-02-0606 February 1998 Safety Evaluation Re Amend to License DPR-59 to Revise TS Tables 3.2-2 & 4.2-2 JAFP-98-0058, Monthly Operating Rept for Jan 1998 for Ja FitzPatrick Nuclear Power Plant1998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Ja FitzPatrick Nuclear Power Plant 1999-09-30
[Table view] |
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Mt4 9 p & UNITED STATES
, s* j NUCLEAR REGULATORY COMMISSION 4
WASHINGTON, D.C. 30666 4001
, \*****/ SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR RELIEF FROM SNUBBER INSPECTION REQUIREMENTS s
POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT
/ DOCKET NO. 50-333 1
4
1.0 INTRODUCTION
The Code of Federal Regulations,10 CFR 50.55a, requires that inservice inspection (ISI) of certain American Society of Mechanical Engineers (ASME Code) Class 1,2, and 3 components be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code applicable Edition and Addenda, except where specific written relief has been requested by the licensee and granted by the Commission pursuant to paragraph 10 CFR 50.55a(g)(6)(i), or attematives authorized pursuant 10 CFR 50.55a(a)(3). In proposed attematives, the licensee must demonstrate that: (i) the proposed allematives provide an acceptable level of quality and safety; or (ii) 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 its facility.
10 CFR 50.55a empowers the Commission to authorize an altemative from the ASME Code requirements upon making the necessary findings. The NRC staff's finding, with respect to authorizing the requested attemative as part of the licensee's ISI program, is contained in this Safety Evaluation (SE).
This SE addresses Relief Request No.11, submitted by the New York Power Acthority (the licensee, also known as the Pow i Authority of the State of New York) on January 26,1998, for authorization to perform the visual examination of snubbers in accordance with the guidance provided in NRC Generic Letter (GL) 90-09, Altemative Requirements for SnubberInspection Intervals and Corrective Actions, in lieu of the requirements of ASMEIANSI OMa-1988, Part 4, Sections 2.3.2.2 and 2.3.2.3 at the James A. FitzPatrick Nuclear Power Plant.
The licensee's ISI program for the third ten-year intervalis based on the requirements of the ASME Code,Section XI,1989 Edition, Subsection IWF, Article IWF-5000. Subarticle IWF-5300(a) invokes the Inservice visual examinations requirements that are to be performed in accordance with the first addenda to ASME/ ANSI OM-1987, Part 4 (published in 1988), using the VT-3 visual examination method described in IWA-2213.
2.0 DESCRIPTION
Relief is requested from the performance of visualinspections of snubbers at 18-month intervals, and the associated schedule changes if unacceptable snubbers are found, as required by ASME/ ANSI OMa-1988 Part 4, Section 2.3.2.2 Examination Schedules, invoked by Subarticle IWF-5300(a). Relief is also raquested from OMa-1988, Part 4, Section 2.3.2.3 Subsequent Examination Schedule Adjustment.
9810200023 981014 PDR ADOCK 05000333 P PDR e
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. l 2.1 LICENSEE'S PROPOSED ALTERNATIVE The licensee proposes that the visual examination of snubbers at the James A. FitzPatrick l
Nuclear Power Plant be performed at the intervals and sampling rates in accordance with the l guidance provided in NRC's GL 90-09, Altemative Requimments forSnubber VisualInspection Intervals and Corrective Actions, dated December 11,1996, as specified in Relief Request i No.11. This altemative is based upon the number of unacceptable snubbers found during the i previous inspection, the total population or category size for each snubber type, and the previous ,
interval. The licensee's proposed altemative is given below:
Examinations of snubbers will be performed at intervals and sampling rates in accordance with the requirements specified in Generic Letter 90-09, Attemative Requirements for Snubber inspection intervals and Corrective Actions, December 11,1990. This proposed attemative is based upon the number of unacceptable snubbers found during the previous inspection, the total population or category size for each snubber type, and the previous interval. Specifically, the visual inspection interval will be determined based upon the following criteria:
Population Column A Colum, B Column C Category Extended Interval Repeat Interval Reduce Interval 1 0 0 1 80 0 0 2 100 0 1 4 150 0 3 8 200 2 5 13 300 5 12 25 The next visual inspection interval for the population of a snubber category shall be determined based upon the previous inspection interval and the number of unacceptable snubbers found during that interval. Snubbers may be categorized, based on their accessability during power operation, as accessible or inaccessible.
These categories may be examined separately orjointly. This decision shall be made and documented before any inspection and used as the basis upon which to determine the next inspection interval for that category.
Interpolation between population or category sizes and the number of unacceptable snubbers is permissible. The next lower integer for the value or limit for Columns A, B, C shall be used if that integer includes a fractional value of unacceptable snubbers as determined by interpolation.
if the number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous interval but not greater than 48 months.
If the number of unacceplable snubbers is equal to or less than the number in Column B but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.
l If the number of unacceptable snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two thirds of the previous interval.
However, if the number of unacceptable snubbers is less than the number in Column C but greater than the number in Column B, the next interval shall be reduced by a factor that is one-third of the ratio of the difference between the number of unacceptable snubbers found during the previous interval a'd the number in Column B to the difference in the numbers in Columns B and C 1
2.2 LICENSEE'S BASIS FOR REQUESTED ALTERNATIVE The snubber visual inspection schedule specified in OMa-1988 assumes that the refueling intervals will not exceed 18 months. The 18-month visualinspection intervalis incompatible with the current FitzPatrick 24-month fuel operating cycle. The large number of snubbers in use at the plant make the specified OMa-1988 snubberinspection schedule and selection meihod excessively restrictive and resource intensive. Performance of the snubber inspections during power operation, as required by the OMa-1988 Part 4 inspection intervals, would result in j expenditures of significant resources, and would subject personnel to unnecessary radiological i exposure with no commensurate increase in quality or safety.
Further, the proposed altemative visual inspection schedule conforms with GL 90-09 requirements and has been previously approved for use at FitzPatrick in license amendment 180 issued on April 13,1992. Snubber inspection requirements were subsequently removed from the technical specifications and relocated to licensee-controlled documents subject to 10 CFR 50.59 in a license amendment issued on June 30,1998. No additional technical specification changes are required to implement this relief request.
3.0 EVALUATION The staff developed GL 90-09, in part, to reduce unnecessary radiological exposure to plant personnel during snubber visual inspections. To verify that a snubber can operate within specific performance limits, the licensee usually performs functional testing that typically involves removing the snubber and testing it on a specifically designed stand. Functional testing provides a 95 percent confidence level that 90 percent to 100 percent of the snubbers can operate within specific performance limits. The performance of visual examinations is a separate process that complements the functional program and provides additional confidence in snubber operability.
, GL 90-09 provides an altemate schedule for snubber visual inspections that maintains the same
- confidence level as the existing inspection intervals and allows for inspections and corrective actions during plant outages. The staff determined that the visualinspection schedule of GL 90-09 is an acceptable attemative to the ASME Code requirements, and encouraged licensees to change their Technical Specifications to be consistent with this guidance.
Based on its review of the information provided in the request for relief from the snubber visual inservice examination interval requirements of IWF-5000, the staff has determined that the licensee's proposed altemative to use intervals and sampling rates consistent with the GL 90-09
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l guidance as specified in the sobmitted relief request and provides an acceptable level of quality and safety by providing a reasonable assurance of snubber operability.
4.0 CONCLUSION
The staff concludes that the licensee's proposed attemative to snubber visualinservice examination intervals and sampling rates requirements contained in the ASME Code,Section XI, Subsection IWF, Article IWF-5000, may be authorized pursuant to 10 CFR 50.55a(a)(3)(i) based on the determination that the licensee's proposed altamatives provide an acceptable level of quality and safety.
Principal Contributor. F. Gmbolich Date: October 14, 1998 l
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