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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20211N2611999-09-0808 September 1999 Safety Evaluation Concluding That Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit & Clarification of Terminology with Respect to Reconstituted Fuel Assemblies Acceptable ML20211J2421999-08-31031 August 1999 Safety Evaluation Supporting Removal of Augmented Insp Program on RCS Bypass Lines from Licensing Basis of North Anna,Units 1 & 2 ML20211J2561999-08-31031 August 1999 Safety Evaluation Accepting Elimination of Augmented ISI Program for Pressurizer Spray Lines at North Anna Unit 2 ML20210T0791999-08-13013 August 1999 Safety Evaluation Concluding That Revised Withdrawal Schedules for North Anna Units 1 & 2 Satisfy Requirements of App H to 10CFR50 & Therefore Acceptable ML20206L4831999-05-10010 May 1999 SER Accepting Request to Delay Submitting Plant,Unit 1 Class 1 Piping ISI Program for Third Insp Interval Until 010430, to Permit Development of Risk Informed ISI Program for Class 1 Piping ML20205S0391999-04-21021 April 1999 SER Accepting Request for Relief IWE5,per 10CFR50.55a(a)(3) & Proposed Alternatives for IWE2,IWE4,IWE6 & IWL2 Authorized Per 10CFR50.55a(a)(3)(ii) ML20198H9541998-12-0303 December 1998 Safety Evaluation Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant ML20196G1381998-11-0303 November 1998 Safety Evaluation Authorizing Rev to Relief Request NDE-32 for Remainder of Second 10-yr Insp Interval for Each Unit ML20236K5531998-07-0707 July 1998 SER Accepting Request for Change in ISI Commitment on Protection Against Pipe Breaks Outside Containment ML20248C8831998-05-29029 May 1998 SER Accepting Alternatives Proposed by Licensee for Use of Code Case N-535,pursuant to 10CFRa(a)(3)(i) in ASME Section XI Inservice Insp Program ML20217B5321998-04-20020 April 1998 Safety Evaluation Supporting Proposed Alternative to ASME Code for Surface Exam of Seal Welds on Threaded Caps for Plant Reactor Vessel Head Penetrations for part-length CRDMs ML20216E8801998-03-0606 March 1998 Safety Evaluation Authorizing Licensee Request for Relief from ASME Code Requirements,Paragraph IWA-2400(c) (Summer Edition W/Summer 1983 Addenda),For Upcoming Naps,Unit 1 Outage,Per 10CFR50.55a(a)(3)(ii) ML20199J6431998-02-0202 February 1998 Safety Evaluation Approving Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 SW Piping for North Anna,Unit 1,as Submitted in ISI Relief Request NDE-46 on 971218 ML20198S7571998-01-15015 January 1998 Safety Evaluation Accepting Licensee Request for Approval to Repair Flaws IAW GL-90-05 for ASME Code Class 3 Svc Water Piping ML20198H5541997-12-29029 December 1997 SER Accepting Request for Approval of ASME Case N-498,rev 1, as an Alternative to Required Hydrostatic Pressure Test for Plant,Unit 2 ML20197K1541997-12-18018 December 1997 SER Granting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 Service Water Piping for North Anna Power Station,Per Util 970919 Submittal ML20199L0501997-11-24024 November 1997 SER Accepting Inservice Insp Program Relief Request NDE-32 ML20199E4971997-11-14014 November 1997 Safety Evaluation Authorizing Proposed Alternative of Licensee Relief Requests NDE-35 & NDE-37,for Plant,Units 1 & 2 During Second 10 Yr Interval ML20217E0701997-09-24024 September 1997 Safety Evaluation Granting Licensee ASME Section XI Relief Request NDE-33 at Plant,Unit 1 ML20217E2411997-09-24024 September 1997 SER Accepting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 Service Water Piping,Virginia Electric & Power Co,North Anna Power Station,Unit 1 ML20217E1871997-09-24024 September 1997 SER Approving Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 Service Water Piping,Virginia Electric & Power Co,North Anna Power Station,Units 1 & 2 ML20149L2001997-07-29029 July 1997 SER Granting Requests for Relief NDE-33,34 & 35 Re ISI Program,Per 10CFR50.55a(g)(6)(i) ML20149F1321997-07-17017 July 1997 Safety Evaluation Supporting Amends 205 & 186 to Licenses NPF-4 & NPF-7,respectively ML20148H1971997-06-0404 June 1997 Safety Evaluation Granting Licensee Relief Request NDE-31 Related to Inservice Insp Program ML20140F4811997-04-30030 April 1997 Safety Evaluation Accepting Licensee 951207 Proposed Alternative in Request for Relief SPT-16 Re Second 10-yr Interval Inservice Insp Program for Unit 2 ML20133G1561997-01-10010 January 1997 Safety Evaluation Accepting Second 10-year Relief Requests for Relief Numbers NDE-27,NDE-28 & NDE-29 ML20133G1911997-01-10010 January 1997 Safety Evaluation Accepting Second 10-year Interval Inservice Insp Plan Relief Request NDE-30 ML20138G1931996-10-16016 October 1996 SER Accepting Second 10-year Interval Inservice Insp Plan Request for Relief SPT-14,rev 1 Virginia Electric & Power Co North Anna Power Station,Unit 2 ML20128P1701996-10-10010 October 1996 Safety Evaluation Supporting Second 10-year Interval Inservice Insp Program Plan Requests for Relief NDE-23 Through NDE-30 for Plant Unit 2 ML20128F5981996-10-0101 October 1996 Safety Evaluation Authorizing Licensee Proposed Alternative to Examine Terminal End Welds on Lower Regenerative Heat Exchanger sub-vessels,per 10CFR50.55a(a)(3)(ii) ML20059M1181993-11-15015 November 1993 SER Accepting Category 3 Qualification in Lieu of Category 2 for Pressure Monitoring Instrumentation ML20057C0401993-09-17017 September 1993 Safety Evaluation Re Inservice Testting Program Requests for Relief ML20126C1221992-12-0404 December 1992 Safety Evaluation Authorizing Util to Continue Current Test Method for Interim Period,Based on Util Plans to Develop & Implement Use of non-intrusive Testing Techniques for Check Valves Following 1993 Unit 2 Refueling Outage ML20125B7251992-12-0303 December 1992 Safety Evaluation Granting Temporary Exemptions from Requirements of GDC-2 & 10CFR50.49 for Phase 1,stage 1 of Svc Water Sys Restoration Project ML20062C4441990-10-18018 October 1990 SER Re Station Blackout.Plant Does Not Conform W/Station Blackout Rule ML20247C2091989-09-0707 September 1989 Safety Evaluation Accepting Util 890512 Response to IE Bulletin 80-11, Masonry Wall Design ML20245J8401989-06-28028 June 1989 Safety Evaluation Supporting Restart of Unit 1 & Util 890528 Response to NRC Bulletin 89-001, Failure of Westinghouse Mechanical Steam Generator Tube Plugs ML20195J0061988-11-29029 November 1988 Safety Evaluation Supporting Licensee Responses to NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generator Tubes, Subj to Util Adopting Addl Administrative Controls ML20207F1391988-08-12012 August 1988 Safety Evaluation Supporting Util Responses to IE Bulletin 80-11, Masonry Wall Design, W/Exception of One Open Item ML20196G9081988-03-0404 March 1988 SER Re Util 831104 & 850208 Responses to Generic Ltr 83-28, Item 2.2.1, Equipment Classification (Program for All Safety-Related Components. Responses Acceptable ML20149J9301988-02-18018 February 1988 Safety Evaluation Re Relief Request 6 of Inservice Testing Program for Pumps & Valves ML20154E8221987-12-11011 December 1987 Safety Evaluation Supporting Util Identification of Major Causal Factors Leading to 870715 Tube Rupture Event & Adequacy of Diagnostic & Corrective Measures Implemented in Order to Preclude Similar Events ML20237B5981987-12-11011 December 1987 Safety Evaluation Accepting Util 870915 & 0925 Responses to Steam Generator Tube Rupture on 870715.Util Has Adequately Demonstrated That Primary Failure Mechanism Leading to Event Caused by flow-induced Vibration ML20236F4971987-10-23023 October 1987 Safety Evaluation Re Util 870925 Request for Approval of Steam Generator Downcomer Flow Resistance Plate Mods & Increase in Calculated Offsite Dose Per 10CFR50.59.Mods Acceptable ML20235U8811987-07-13013 July 1987 Safety Evaluation Supporting Request for Relief from Certain Exam & Hydrostatic Test Requirements of ASME Code ML20213G8081987-05-11011 May 1987 SER Re Util 850208 Response to Generic Ltr 83-28,Item 2.1 (Part 2), Vendor Interface Programs (Reactor Trip Sys Components. Program Acceptable ML20212K5111987-02-27027 February 1987 SER Accepting Licensee 831104 Response to Generic Ltr 83-28, Item 4.5.2, Reactor Trip Sys Reliability,On-Line Testing ML20207Q0651987-01-0909 January 1987 Safety Evaluation Denying Util 850401 Request to Reduce Number of Thimbles Required for Monthly Surveillance Flux Mapping ML20215D0811986-09-30030 September 1986 Safety Evaluation Granting Util 860613 Request for Relief from Inservice Hydrostatic Test Requirements for Svc Water Spray Sys 1999-09-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N9281999-10-20020 October 1999 Special Rept:On 991003,PZR PORV Actuation Mitigated RCS low- Temp Overpressure Transient.Caused by a RCP Facilitating Sweeping of Entrained Air Out of RCS Loops.Operating Procedure 2-OP-5.1 Will Be Revised ML20217H3631999-10-14014 October 1999 Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su ML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20217D6851999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for North Anna Power Station,Units 1 & 2.With ML20211N2611999-09-0808 September 1999 Safety Evaluation Concluding That Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit & Clarification of Terminology with Respect to Reconstituted Fuel Assemblies Acceptable ML20211J2561999-08-31031 August 1999 Safety Evaluation Accepting Elimination of Augmented ISI Program for Pressurizer Spray Lines at North Anna Unit 2 ML20216E5011999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Naps,Units 1 & 2. with ML20211J2421999-08-31031 August 1999 Safety Evaluation Supporting Removal of Augmented Insp Program on RCS Bypass Lines from Licensing Basis of North Anna,Units 1 & 2 ML20210T0791999-08-13013 August 1999 Safety Evaluation Concluding That Revised Withdrawal Schedules for North Anna Units 1 & 2 Satisfy Requirements of App H to 10CFR50 & Therefore Acceptable ML20210S1411999-07-31031 July 1999 Monthly Operating Repts for July 1999 for North Anna Power Station.With ML20210Q9931999-07-31031 July 1999 Rev 1 to COLR for North Anna Power Station,Unit 2 Cycle 13 Pattern Ud ML20209E5641999-06-30030 June 1999 Monthly Operating Repts for June 1999 for North Anna Power Stations,Units 1 & 2.With ML20195G1901999-05-31031 May 1999 Monthly Operating Rept for May 1999 for NAPS Units 1 & 2. with ML20206L4831999-05-10010 May 1999 SER Accepting Request to Delay Submitting Plant,Unit 1 Class 1 Piping ISI Program for Third Insp Interval Until 010430, to Permit Development of Risk Informed ISI Program for Class 1 Piping ML20206Q6671999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for North Anna Power Station,Units 1 & 2.With ML20205S0391999-04-21021 April 1999 SER Accepting Request for Relief IWE5,per 10CFR50.55a(a)(3) & Proposed Alternatives for IWE2,IWE4,IWE6 & IWL2 Authorized Per 10CFR50.55a(a)(3)(ii) ML20205K3041999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for North Anna Power Station,Units 1 & 2.With ML20207K5921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for North Anna Power Station,Units 1 & 2.With ML20207E1731999-02-18018 February 1999 Informs Commission of Status of Preparations of IAEA Osart Mission to North Anna Nuclear Power Plant Early Next Year ML20205A0241998-12-31031 December 1998 Summary of Facility Changes,Tests & Experiments,Including Summary of SEs Implemented at Plant During 1998,per 10CFR50.59(b)(2).With ML20199C8781998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for North Anna Power Station,Units 1 & 2.With ML20198H9541998-12-0303 December 1998 Safety Evaluation Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant ML20198J5561998-12-0303 December 1998 ISI Summary Rept for North Anna Power Station,Unit 1 1998 Refueling Outage Owner Rept for Inservice Insps ML20197G8551998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for North Anna Power Station,Units 1 & 2.With ML20196G1381998-11-0303 November 1998 Safety Evaluation Authorizing Rev to Relief Request NDE-32 for Remainder of Second 10-yr Insp Interval for Each Unit ML20195D0571998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for North Anna Power Station,Units 1 & 2.With ML20154L0691998-10-14014 October 1998 COLR for North Anna Power Station Unit 1 Cycle 14 Pattern Xy ML20155J6911998-10-0909 October 1998 Staff Response to Tasking Memorandum & Stakeholder Concerns ML20154H4001998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for North Anna Power Station,Units 1 & 2.With ML20151X8011998-09-10010 September 1998 Special Rept:On 980622,groundwater Level at Piezometer P-22 Was Again Noted to Be Above Max Water Level by 0.71 Feet. Increased Frequency of Piezometer Monitoring & Installed Addl Piezometers at Toe of Slope Along Southwest Section ML20151W4711998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for North Anna Power Station Units 1 & 2.With ML20237A4341998-07-31031 July 1998 Monthly Operating Repts for July 1998 for North Anna Power Station,Units 1 & 2 ML20236V1251998-07-14014 July 1998 ISI Summary Rept for Naps,Unit 2,1998 Refueling Outage Owners Rept of Isis ML20236K5531998-07-0707 July 1998 SER Accepting Request for Change in ISI Commitment on Protection Against Pipe Breaks Outside Containment ML20236M3381998-06-30030 June 1998 Monthly Operating Repts for June 1998 for North Anna Power Station,Units 1 & 2 ML20248M1011998-05-31031 May 1998 Monthly Operating Repts for May 1998 for North Anna Power Station,Units 1 & 2 ML20248C8831998-05-29029 May 1998 SER Accepting Alternatives Proposed by Licensee for Use of Code Case N-535,pursuant to 10CFRa(a)(3)(i) in ASME Section XI Inservice Insp Program ML20247K9281998-05-15015 May 1998 Special Rept:On 980428,letdown PCV Exhibited Slow Response When C RCP Was Started.Cause to Be Determined.Review of Operating Procedure Will Be Performed to Determine If Enhancements Are Necessary ML20216A8971998-05-0606 May 1998 Rev 0 to Cycle 13 Pattern Ud COLR for North Anna Unit 2 ML20247F4441998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for North Anna Power Station,Units 1 & 2 ML20217B5321998-04-20020 April 1998 Safety Evaluation Supporting Proposed Alternative to ASME Code for Surface Exam of Seal Welds on Threaded Caps for Plant Reactor Vessel Head Penetrations for part-length CRDMs ML20217H9611998-04-0707 April 1998 Special Rept:On 980216,groundwater Level at Piezometer P-22, Again Noted to Be Above Max Water Level by 0.41 Feet.Design Package for Installation of Addl Standpipe Piezometers at Toe of Slope Southeast Section,Developed ML20216B1891998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for North Anna Power Station,Units 1 & 2 ML20216E8801998-03-0606 March 1998 Safety Evaluation Authorizing Licensee Request for Relief from ASME Code Requirements,Paragraph IWA-2400(c) (Summer Edition W/Summer 1983 Addenda),For Upcoming Naps,Unit 1 Outage,Per 10CFR50.55a(a)(3)(ii) ML20216E2561998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for North Anna Power Station,Units 1 & 2 ML20199J6431998-02-0202 February 1998 Safety Evaluation Approving Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 SW Piping for North Anna,Unit 1,as Submitted in ISI Relief Request NDE-46 on 971218 ML20202D5811998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for North Anna Power Station,Units 1 & 2 ML20198S7571998-01-15015 January 1998 Safety Evaluation Accepting Licensee Request for Approval to Repair Flaws IAW GL-90-05 for ASME Code Class 3 Svc Water Piping ML20198P1351997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for North Anna Power Station,Units 1 & 2 1999-09-08
[Table view] |
Text
. - __ _ _ __ ~
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- $ UNITED STATES j
I' !" NUCLEAR REGULATORY COMMISSION
. g WASHINGTON. D.C. 20666-0001 ENCLOSURE SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION THE SECOND 10-YEAR INTERVAL INSERVICE INSPECTION PLAN RELIEF RE0 VEST NO. NDE-30 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION. UNIT 1 DOCKET NUMBER: 50-338
1.0 INTRODUCTION
The Technical Specifications for North Anna Power Station, Unit 1, state that the inservice inspection and testing of the American Society of Mechanical Engineers (ASME) Code Class 1, 2 and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(1). The 10 CFR 50.55a(a)(3) states that alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if (1) the proposed alternatives would provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulties without a compensating increase in the level of quality and safety.
Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2 and 3 components (including supports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests conducted during the initial 120-month interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) on the date twelve months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The applicable edition of the ASME Code,Section XI, for North Anna Power Station, Unit 1, during the second ten-year inservice inspection (ISI) interval, is the 1983 edition, including the summer 1983 addendum. 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 limitations and modifications listed therein and subject to commission approval.
Pursuant to 10 CFR 50.55a(g)(5), if the licensee determines that conformance with an examination quirement of Section XI of the ASME Code is not practical for its fat.: 'ty, information shall be submitted to the Commission 9701150211 970110 PDR ADOCK 05000338 G PDR
. _ _ _ . _ _ ~ . _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ . _ . _ _ _ _ . _ - - - -
1 2 2 in support of that determination and a request made for relief from the ASME 1
Code requirement. After evaluation of the determination, pursuant to 10 CFR 50.55a(g)(6)(i), the Commission may grant relief and may impose !
- alternative requirements that are determined to be authorized by law, will not
. endanger life, property, or the common defense and security, and are otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed.
i By letter dated July 24, 1996, Virginia Electric and Power Company submitted i to the NRC its relief request No. NDE-30 for the second inservice inspection
- interval for North Anna Unit 1.
The NRC staff has reviewed and evaluated the licensee's request and the i
supporting information on the proposed relief request No. NDE-30 for North Anna, Unit 1, pursuant to the provisions of 10 CFR 50.55a(g)(6)(1).
2.0 DISCUSSION LICENSEE'S RELIEF RE0 VEST N0.NDE-30 The volumetric and the surface examination coverages for weld No. SW-8 on line 12"-SI-69-1502-Q1, were 71 percent and 80 percent respectively due to restrictions from an integrally attached component support. North Anna Unit I has adopted ASME Code Case N-460 " Alternative Examination Coverage for Class 1 and Class 2 Welds" in the ISI Program which allows a reduction in examination coverage of less than 10 percent due to interference by another component or part geometry as being acceptable in lieu of the Code-required examination coverage of 100 percent. Pursuant to 10 CFR 50.55a(g)(5), the licensee requests relief from the examination coverage requirements of the applicable ASME Code during the second inspection interval of North Anna Unit 1.
LICENSEE'S BASIS FOR RELIEF (as stated)
"The component listed above has been examined to the extent practical as required by the Code. The Code required surface and volumetric examination coverage was reduced due to a component support which could not be removed.
The scope of volumetric examination coverage completed for the above listed weld is listed in Table NDE-30-1. Figure NDE-30-1 is provided detailing the limitations experienced. Alternative components could not be substituted for examination due to the mandatory selection requirements of the Code."
LICENSEE'S ALTERNATE PROVISIONS (as stated)
"It is proposed that the examinations already completed at the reduced coverage be counted as meeting the Code requirements."
3.0 EVALUATION The ASME Code,Section XI, 1983 edition including the summer 1983 addendum requires 100 percent volumetric and surface examinations of the subject weld. l However, the ASME Code Case N-460 allows that a reduction in examination coverage below ten percent is acceptable due to interference by another l
! 3 component or part geometry. The figure provided by the licensee depicts the
- interference caused by an integrally attached component support adjacent to the weld. Consequently, the volumetric and the surface examinations of the weld are impractical to perform even to the extent permitted by the Code Case N-460. In order to obtain the required examination coverage, design modifications would be required, causing a significant burden on the licensee.
The licensee performed the volumetric and the surface examinations to the extent practical, resulting in examination coverages of 71 percent and 80 percent respectively for the subject weld. Based on the examination coverages obtained, it can be concluded that a degradation, if present, would have been detected. As a result, reasonable assurance of structural integrity has been provided. Therefore, the staff has determined that the relief requested by the licensee be granted pursuant to 10 CFR 50.55a(g)(6)(1).
4.0 CONClyl[QH :
The staff has evaluated the licensee's submittal on the relief request NDE-30 and concludes that the Code-required examinations of the subject weld are !
impractical due to interference caused by the component support and would J impose significant burden on the licensee if the Code requirements were to be i met. The limited volumetric and surface examination performed on the weld .
provides reasonable assurance of operational readiness. The granting of this '
relief is authorized by law and will not endanger life or property or the ;
common defense and security and is otherwise in the public interest giving due '
consideration to the burden upon the licensee that could result if the l requirements vere imposed on the facility. Therefore, it is recommended that l relief be granted pursuant to the provisions of 10 CFR 50.55a(g)(6)(i). !
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