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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20206A6561999-04-21021 April 1999 Safety Evaluation Authorizing Licensee Re Rev 9 to First 10-year ISI Interval Program Plan & Associated Requests for Relief (RR) 65 from ASME Boiler & Pressure Vessel Code ML20202H9851999-01-29029 January 1999 Safety Evaluation Accepting Rev 8 to First 10-year Interval Inservice Insp Program & Associated Requests for Relief for Vogtle Electric Generating Plant,Unit 1 ML20198S1781998-12-31031 December 1998 SER Re Second 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief for Southern Nuclear Operating Co,Inc Units 1 & 2 ML20217H7181998-04-0101 April 1998 Corrected Page 5 to 980324 SER Re Relief Requests Associated W/Second 10-year Interval Insp program.RR-21 in Error in That Component,Suction Damper Inadvertently Omitted. Corrected Page 7 of Technical Ltr Rept Also Encl ML20217B8831998-03-24024 March 1998 SER Accepting Relief Request RR-5,RR-19,RR-20,RR-21,RR-23 & RR-24 for Second 10-yr Interval ISI Program Plan ML20203H9551998-02-23023 February 1998 SER Denying Quality Assurance Program Description Change for Vogtle Electric Generating Plant,Units 1 & 2 ML20203C2811997-12-0909 December 1997 Safety Evaluation Authorizing Request for Relief of Second 10 Yr Interval Inservice Insp Program ML20198T3621997-10-24024 October 1997 Safety Evaluation Authorizing Supporting Second 10-year Interval ISI Program Requests for Relief RR-17 & RR-25 as Submitted by Southern Nuclear Operating Co on 970529 ML20210R2071997-08-27027 August 1997 Safety Evaluation Accepting Relief Requests for Pump & Valve Inservice Testing Program ML20058A3041993-11-19019 November 1993 Safety Evaluation Re Accumulator Pressure & Vol Instrumentation of Reg Guide 1.97 Environ Qualification Requirements,Per Generic Ltr 82-33.Category 3 Qualification of Instrumentation Acceptable ML20062J8641993-11-10010 November 1993 Safety Evaluation Denying Licensee 920617 Request for Amends to License Changing TS 3/4.6.1.7 & 4.6.1.2f for Plant ML20059J0061993-11-0303 November 1993 Safety Evaluation Supporting Rev 15 to Emergency Plan for Plant ML20057F8291993-10-12012 October 1993 Safety Evaluation Accepting Util Submittals of Rev 7 to IST Program for Unit 1 & Rev 4 to IST Program for Unit 2 ML20057E3021993-10-0404 October 1993 Safety Evaluation Accepting Proposed Changes to EAL in Rev 15 of Plant Emergency Plan ML20056H6441993-08-26026 August 1993 Safety Evaluation Denying TS Change for Surveillance of Emergency Core Cooling Sys ML20127B7051993-01-0606 January 1993 Safety Evaluation Supporting Rev 4 to First 10-yr Interval Inservice Insp Program for Facility ML20127B6901993-01-0606 January 1993 Safety Evaluation Supporting Rev 5 to First 10-yr Interval Inservice Insp Program for Facility ML20126F3331992-12-23023 December 1992 Safety Evaluation Accepting Licensee Schedule for Completing MOV Testing Program in Response to GL 89-10 ML20059E9171990-08-31031 August 1990 SER Supporting Util 890928 Request for Exemption from 10CFR20,App a & Authorizing Use of Radioiodine Protection Factor for Sorbent Canisters ML20206L6491988-11-22022 November 1988 Supplemental Safety Evaluation Concluding That Commitment & Schedule Re 14 Open Items Concerning SPDS Acceptable. Commitment to Complete 1000 H Availability Test by 881231 Acceptable.Requirements of License Condition 2.C.7(b) Met ML20155C9901988-10-0303 October 1988 Safety Evaluation Concluding That ATWS Design Proposed by Util Meets 10CFR50.62 Requirements,Subj to Successful Completion of Certain Noted Human Factors Engineering Reviews ML20151E0421988-07-18018 July 1988 Sser Supporting Electrical Cable & Raceway Configurations for Plant ML20236S5251987-11-20020 November 1987 Safety Evaluation Supporting Util 870121,0522,0720 & 0929 Submittals Re Seismic Adequacy for Spent Fuel Pool Racks ML20236D2941987-10-28028 October 1987 Safety Evaluation Supporting Fire Suppression Sys Changes for Facility ML20236A8521987-10-15015 October 1987 Safety Evaluation Concluding That Util 870713,0930 & 1015 Submittals in Support of License Condition 2.C(8) Provide Acceptable Justification That Inorganic Zinc Coating on Fuel Oil Storage Tanks Will Not Adversely Affect Generators ML20235S8101987-10-0707 October 1987 Safety Evaluation Supporting Proposed Redesign of Steam Generator Upper Support of Reactor Coolant Loop Sys for Unit 2 & Proposed Revised FSAR ML20235G7371987-09-22022 September 1987 Safety Evaluation Supporting Rev 2 to Inservice Testing Program,Providing Cold Shutdown Valve Testing Justifications & Addl Relief Requests ML20237H3011987-08-19019 August 1987 Safety Evaluation Accepting 870601 Proposed Deletion of Electrical Penetration Filter & Exhaust Sys NUREG-1137, Safety Evaluation Supporting Util 870601 Proposal Re Pipe Break Criteria Used for Flooding Analyses & Addition of Moderate Energy non-seismic Category I Piping to Exceptions List.Nrc Does Not Entirely Agree W/Util Justification1987-08-14014 August 1987 Safety Evaluation Supporting Util 870601 Proposal Re Pipe Break Criteria Used for Flooding Analyses & Addition of Moderate Energy non-seismic Category I Piping to Exceptions List.Nrc Does Not Entirely Agree W/Util Justification ML20236H1151987-07-30030 July 1987 Safety Evaluation Supporting Util long-term Proposal for Support of Cable in Vertical Cable Trays Through Use of Stainless Steel Cable Ties ML20236F3591987-07-29029 July 1987 Safety Evaluation Re Util Response to Generic Ltr 83-28,Item 2.1 Re Identification of safety-related Reactor Trip Sys Components.Util Response Adequate ML20235J9441987-07-0707 July 1987 Safety Evaluation Supporting Supplemental Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1 Per NUREG-1000 ML20212F5381987-01-0808 January 1987 Safety Evaluation of Water Hammer Events & Corrective Actions Taken to Ensure Nuclear Svc Water Cooling Water Sys Integrity & long-term Operability.Sys Functional Integrity & long-term Operability Capability Adequate ML20214P3971986-09-15015 September 1986 SER Supporting Environ Qualification of Asco Solenoid Valves ML20205F2731986-08-0808 August 1986 Safety Evaluation Re Operability & Reliability of Tdi Emergency Diesel Generators.Submittal Concludes Technical Resolution of Generic Tdi Generator Issues ML20215A7521986-07-0707 July 1986 SER Supporting Util 860523 Proposed Changes to Tech Specs Re Reactor Trip Sys Instrumentation & Surveillance in Response to Generic Ltr 85-09.SALP Input Also Encl ML20215A9671986-05-22022 May 1986 SER Re Util 851207 Proposed Changes to Tech Specs Pertaining to Reactor Trip Sys Instrumentation & Surveillance,Per Generic Ltr 85-09.Proposed Tech Specs Should Be Submitted for Review,Per Generic Ltr.Salp Input Also Encl ML20215A7821986-05-0808 May 1986 Sser Re Util Response to Generic Ltr 83-28,Item 4.3, Reactor Trip Breaker Automatic Shunt Trip. Licensee Should Submit Proposed Tech Specs Consistent W/Generic Ltr 85-09 Guidance for NRC Review.Salp Input Also Encl ML20215G1131986-04-11011 April 1986 SER Re Util 830414,850315,0620,0906 & 860121 Responses to Reg Guide 1.97.Design Acceptable W/Respect to Conformance to Reg Guide 1.97,Rev 2,w/exception of Containment Sump Water Temp ML20127G7421985-06-13013 June 1985 Safety Evaluation Supporting Elimination of Arbitrary Intermediate Pipe Breaks in Feedwater Sys 1999-04-21
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4591999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20217K8041999-09-30030 September 1999 Rev 1 to Vegp,Unit 2 Cycle 7 Colr ML20217K7741999-09-30030 September 1999 Rev 1 to Vegp,Unit 1 Cycle 9 Colr ML20216E5061999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Vegp,Units 1 & 2. with ML20210P9841999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20209H1211999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20196F9711999-05-31031 May 1999 Owner Rept for ISI for Vogtle Electric Generating Plant, Unit 1 Eighth Maint/Refueling Outage ML20195G1731999-05-31031 May 1999 Monthly Operating Repts for May 1999 for VEGP Units 1 & 2. with ML20206N2141999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20206A6561999-04-21021 April 1999 Safety Evaluation Authorizing Licensee Re Rev 9 to First 10-year ISI Interval Program Plan & Associated Requests for Relief (RR) 65 from ASME Boiler & Pressure Vessel Code ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20206C2291999-03-31031 March 1999 Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2 ML20205Q8081999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Vegp,Units 1 & 2. with ML20205A9581999-03-31031 March 1999 Rev 0 to VEGP Unit 1 Cycle 9 Colr ML20207K6051999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20209H3951999-02-15015 February 1999 Rev 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Units 1 & 2 ML20209H4091999-02-15015 February 1999 Rev 1 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Units 1 & 2 ML20202H9851999-01-29029 January 1999 Safety Evaluation Accepting Rev 8 to First 10-year Interval Inservice Insp Program & Associated Requests for Relief for Vogtle Electric Generating Plant,Unit 1 ML20199F8041999-01-13013 January 1999 Corrected Pages to VEGP-2 ISI Summary Rept for Spring 1998 Maint/Refueling Outage ML20199E7561998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20198S1781998-12-31031 December 1998 SER Re Second 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief for Southern Nuclear Operating Co,Inc Units 1 & 2 ML20196E5221998-12-0101 December 1998 Rev 8 to ISI-P-014, ISI Program for VEGP-2 ML20198B8571998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20195H2131998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Vogtle Electric Generating Station,Units 1 & 2.With ML20154L5681998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Vegp,Units 1 & 2 ML20151W3681998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Vogtle Electric Generating Plant Units 1 & 2.With ML20154L5721998-08-31031 August 1998 Corrected Page from MOR for Aug 1998 for Vegp,Unit 2 ML20237D2051998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Vogtle Electric Generating Plant Units 1 & 2 ML20236V3121998-07-29029 July 1998 Final Part 21 Rept Re Enterprise DSR-4 & DSRV-4 Edgs.Short Term Instability Was Found During post-installation Testing & Setup as Part of Design mod/post-work Testing Process. Different Methods Were Developed to Correct Problem ML20236P6991998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20236Q3051998-06-30030 June 1998 Owner'S Rept for ISI for Sixth Maint/Refueling Outage of Vogtle Electric Generating Plant,Unit 2 ML20249A3911998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Vogtle Electric Generating Plant ML20248A1671998-05-22022 May 1998 Interim Part 21 Re Enterprise DSR-4 & DSRV-4 Emergency diesel.Post-installation Testing Revealed,High Em/Rfi Levels Affected New Controllers,Whereas Original Controllers Were unaffected.Follow-up Will Be Provided No Later than 980731 ML20249A3931998-04-30030 April 1998 Revised MOR for Apr 1998 for Vogtle Electric Generating Plant Unit 1 ML20247F3841998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20154Q9721998-04-20020 April 1998 10CFR50.59(B) Rept of Facility Changes,Tests & Experiments for Vogtle Electric Generating Plant,Units 1 & 2 ML20217H7181998-04-0101 April 1998 Corrected Page 5 to 980324 SER Re Relief Requests Associated W/Second 10-year Interval Insp program.RR-21 in Error in That Component,Suction Damper Inadvertently Omitted. Corrected Page 7 of Technical Ltr Rept Also Encl ML20216D6141998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20217Q1301998-03-31031 March 1998 Rev 0 to Vepc Unit 2 Cycle 7,COLR ML20217B8831998-03-24024 March 1998 SER Accepting Relief Request RR-5,RR-19,RR-20,RR-21,RR-23 & RR-24 for Second 10-yr Interval ISI Program Plan ML20216E2421998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20203H9551998-02-23023 February 1998 SER Denying Quality Assurance Program Description Change for Vogtle Electric Generating Plant,Units 1 & 2 ML20203E4831998-02-11011 February 1998 Rev 1 to Vogtle Electric Generating Plant,Units 1 & 2 Second Ten-Yr Interval Pump Inservice Test Program ML20198T1211998-01-31031 January 1998 Owners Rept for Inservice Inspection for Seventh Maintenance/Refueling Outage ML20202G5441998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20199E5431998-01-31031 January 1998 Rev 3 to WCAP-14720, Vogtle Units 1 & 2 Spent Fuel Rack Criticality Analysis W/Credit for Soluble Boron ML20198L6471997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Vogtle Electric Generating Plant,Units 1 & 2 ML20203C2811997-12-0909 December 1997 Safety Evaluation Authorizing Request for Relief of Second 10 Yr Interval Inservice Insp Program ML20202B7881997-12-0101 December 1997 Rev 8 to ISI-P-006, ISI Program for Gpc Vogtle Electric Generating Plant Unit 1 ML20203H0601997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Vegp,Units 1 & 2 1999-09-30
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Text
ENCLOSURE 1 l j 0* *8cg'o, UNITED STATES 3
, y ' ,g NUCLEAR REGULATORY COMMISSION t
-le WASHINGTON, D. C. 20555
%, . . . . /
SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING REVISION 5 TO THE FIRST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM F02 V0GTLE ELECTRIC GENERATING PLANT. UNIT N0, 1 DOCKET NUMBER 50-424
1.0 INTRODUCTION
Technical Specification 4.0.5 for Vogtle Electric Generating Plant, Unit 1, states that the inservice inspection and testing of the American Society of Mechanical Engineers (ASME) C ,de 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)(i). Under 10 CFR 50.55a(a)(3), alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if (i) 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 a# the components. The regulations require that inservice examination of cot,,onents and system pressure tests conducted during the first ten-year interval comply with the requirements in the latt.st edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) on the date 12 months prior to the issuance of the operating license, subject to the limitations and modifications listed therein. The applicable edition of Section XI of the ASME Code for the Vogtle Electric Generating Plant, Unit 1, first 10-year ISI interval is the 1983 Edition through Summer 1983 Addenda. 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. The first interval for Vogtle Unit 1 began June 1, 1987, and ends June 1, 1997.
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-y-Pursuant to 10 CFR 50.55a(g)(5), if a licensee determines that conformance with an examination requirement of Section XI of the ASME Code is not practi cal for its facility, informhtion shall be submitted to the Commission in support of that determination and a request made for relief from the ASME Code requirement. After evaluation of the determination, pursuant to 10 CFR-
. 50.55a(g)(6)(i), the Commission may grant relief and may impose 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.
The licensee, Georgia Power Company, submitted Revision 5 to the Vogtle Electric Generating Piant, Unit 1, First 10-Year Interval ISI Program, in 'a letter dated October 2, 1991. The ISI Program for Unit I through Revision 4 has previously been evaluated and accepted in an NRC Safety Evaluation Report (SER) dated November 26, 1991. In the SER of November 26, 1991, the NRC staff also acknowledged that by Revision 5, the licensee had withdrawn Relief Requests (RR)-1, RR-24, and RR-51. Therefore, in this review the NRC staff now evaluates the remainder of Revision 5.
The NRC staff has evaluated the Vogtle Electric Generating Plant, Unit 1, First 10-Year Interval ISI Program, Revision 5, with technical assistance from its contractor, the Idaho National Engineering Laboratory.
2.0 EVALUATIQH Most of the changes to the ISI Program found in Revision 5 consist of editorial corrections to text. The remaining changes apply to specific requests for relief. '3e information provided by the licensee in support of the requests for relief from impractical requirements has been evaluated and the bases for granting relief from those requirements are documented below.
A. RR-21. Examination Catecory B-J. Class 1 Branch Connection Welds 4 Inch' and larger Nominal Pipe Sizg In its SER of November 26, 1991, and -accompanying Technical Evaluation-Report (TER at Section 3.1.4.2), the NRC staff granted RR-21 which had requested relief from examining .100% of the Code-required volume of eleven specific Class 1 branch pipe connection welds. The licensee revised RR-21 in Revision 5 to reflect the actual examination volumes -
completed and the- receipt of new calibration blocks. Review lof the
" set-in" and " set-on" designs shows that the' branch connections cannot be examined'to the extent required by the Code. The' licensee has committed to perform the volumetric examinations .to the maximum extent practical, in addition to performing the Code-required surface examinations.
The NRC staff finds that these examinations will provide. reasonable assurance of the continued inservice structural integrity of the branch connection welds. Therefore, the NRC staff's previous basis for
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granting this relief request remains valid as reported November 26, 1991, and the request, as modified, is granted in accordance with 10 CFR 50.55a(g)(6)(1).
B. RR-26. Examination Cateaories B-J and C-F. Pressure Retainina Welds in ;
Class 1 and 2 Pioina In its SER of Novemb:r 26, 1991, the NRC staff accepted RR-26_which requested relief from examining 100% of the Code-required volume of certain welds-(see Sections 3.1.4.1 and 3.2.2.1 of the accompanying TER for Unit 1). The changes to RR-26, as modified by Revision 5,-are of an editor nature and do not change the technical content. The changes are made to be similar in content to RR-26 in the ISI Program for Unit 2 (which was accepted by the NRC staff December 17, 1991; see Sections 3.1.4.1 and 3.2.2.1 of the accompanying TER for Unit 2). Therefore, the NRC staff's previous basis for granting this relief remains valid, and the request, as modified, is granted in accordance with 10 CFR 50.55a(g)(6)(i).
C. RR-31. Use of Pioina Calioration Blocks to Examine Thin-Wall Vessels In its SER of November 26, 1991, the NRC staff granted RR-31 which had requested the modification of the Section V, Article 5 requirement to allow the use of Section XI, Appendix III for examination of certain Class 2 thin-wall vessels. RR-31 was revised in Revision 5 to add the discharge pulsation damper (Tag No. Il208-V4-002) to the list of
. affected thin-wall vessels. The " Basis For Relief" has been updated by Revision 5 to allow for the use of a flat calibration block in.
accordance with ASME Section V, Article 5, Paragraphs T-543.3.1 and
.2.
These additions are similar in content to Relief Request RR-31 in the-
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ISI Program for Vogtle Unit 2 as accepted by the NRC staff December:17, 1991 (see Section 3.2.1.3 of the accompanying TER for Unit 2 in which i the NRC staff concluded that the licensee's proposed alternative l examination method is technically justified as being equivalent or superior to the examination methods specified by the Code). The additions for Unit I do not change the technical content or the
,. justification used for the NRC staff's previous evaluation for Unit 2.-
l The thin-wall vessels (and their associated systems) within the scope of RR-31 are of identical design for Unit I and Unit 2. . Therefore, the relief request,-as modified in Revision 5 of the ISI. Program, is-authorized in accordance.with 10 CFR 50.55a(a)(3)(i).
l D. Reouests for Relief Nos. RR-17 and RR-52 l In its SER of November 26, 1991, and accompanying TER, Section 3.1.4.1, L the NRC staff granted-RR-17 which requested relief from examining 100%
L of the Code-requested volume of certain Class 1 circumferential-piping l -welds. Relief Request-RR-17 was revised in Revision 5 to correct an elbow size in the component' description from 29" to 31".
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In its SER of November 26, 1991, and accompanying TER, Section 3.1.1.6, the NRC staff granted RR-52 which requested relief from examining 100%
of the Code-required area of certain integrally welded attachments. ~~
RR-52 was revised in Revision 5 to correct a typographical error.
These corrections do not affect the basis for the NRC staff's previous approvals. Therefore, the relief requests, as corrected in Revision 5, are granted in accordance with 10 CFR 50.55a(g)(6)(1).
3.0 CONCLUSION
Most of the changes in Revisions 5 of the ISI Program for Vogtle Electric Generating Plant, Unit 1, are editorial in nature. We have determined that _
imposing the applicable provisions of Section Xi of the ASME Code would be impractical. Moreover, the requested relief, as modified, is authorized by law and will not endanger the common defense and security and is otherwise in the public interest given due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Therefore, these relief requests are granted pursuant to 10 CFR 50.55a(g)(6)(i).
In Revision 5, RR-31 is updated to reflect actual plant conditions and to configure the Unit 1 Program similar to the Unit 2 Program as accepted by the NRC staff. For RR-31, you have proposed alternative examinations and we have determined that the proposed alternatives would provide an acceptable level of quality and safety. Therefore, RR-31 is authorized pursuant to 10 CFR 50.55a(a)(3)(i).
Accordingly, the NRC staff has determined that the Vogtle Electric Generating Plant, Unit 1, First 10-Year Interval ISI Program, through Revision 5, reflects compliance with 10 CFR 50.55a(g) and Technical Specification 4.0.5 _
and, therefore, continues to be acceptable. _
Date: January 6, 1993
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