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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20211H7921999-08-13013 August 1999 Safety Evaluation Supporting Amend 126 to License DPR-54 ML20198G8271997-08-22022 August 1997 Safety Evaluation Supporting Amend 125 to License DPR-54 ML20045B9051993-06-16016 June 1993 Safety Evaluation Re Order Approving Decommissioning Plan & Authorizing Decommissioning of Rsngs,Unit 1,SMUD.Concludes That Reasonable Assurance That Health & Safety of Public Will Not Be Endangered by Decommissioning Option,Provided ML20029B6721991-02-22022 February 1991 Safety Evaluation Supporting Proposed Rev to Emergency Plan & Granting Exemption from 10CFR50-54(q) Requirements ML20059G9621990-09-10010 September 1990 Safety Evaluation Supporting Amend 115 to License DPR-54 ML19325F0311989-10-26026 October 1989 Safety Evaluation Supporting Amend 114 to License DPR-54 ML19325D0901989-10-0404 October 1989 Safety Evaluation Re Response to Generic Ltr 83-28,Item 2.2.1, Equipment Classification Program for All Safety- Related Components ML19325C9601989-09-29029 September 1989 Safety Evaluation Supporting Amend 113 to License DPR-54 ML20247B3611989-07-17017 July 1989 Safety Evaluation Supporting Amend 112 to License DPR-54 ML20245E1161989-06-20020 June 1989 Safety Evaluation Supporting Amend 111 to License DPR-54 ML20245A1991989-06-0909 June 1989 Safety Evaluation Supporting Amend 110 to License DPR-54 ML20248B6321989-06-0505 June 1989 Safety Evaluation Supporting Amend 108 to License DPR-54 ML20248B9361989-06-0505 June 1989 Safety Evaluation Supporting Amend 107 to License DPR-54 ML20248B9621989-06-0505 June 1989 Safety Evaluation Supporting Amend 109 to License DPR-54 ML20247P1761989-05-30030 May 1989 Safety Evaluation Accepting Generic Ltr 83-28,Item 4.5.2 Re on-line Testing of Reactor Trip Sys ML20247K7261989-05-23023 May 1989 Safety Evaluation Supporting Amend 105 to License DPR-54 ML20247M9231989-05-23023 May 1989 Safety Evaluation Supporting Amend 106 to License DPR-54 ML20247K6871989-05-16016 May 1989 Safety Evaluation Supporting Amend 104 to License DPR-54 ML20246F4671989-05-0404 May 1989 Safety Evaluation Re Inservice Testing Program & Requests for Relief Re ASME Class 1,2 & 3 Pumps & Valves.Program Acceptable ML20245F9041989-04-18018 April 1989 Safety Evaluation Supporting Amend 103 to License DPR-54 ML20248E9371989-03-29029 March 1989 Safety Evaluation Supporting Amend 102 to License DPR-54 ML20155D3131988-09-28028 September 1988 Safety Evaluation Supporting Amend 100 to License DPR-54 ML20151L5511988-07-14014 July 1988 Redistributed Safety Evaluation Supporting Amend 99 to License DPR-54 ML20151A2771988-07-13013 July 1988 SER Supporting Util Actions to Prevent Failure of Ammonia Tanks Which May Result in Incapacitation of Control Room & Technical Support Ctr Personnel ML20195C9311988-06-0808 June 1988 SER Accepting Util Response to Generic Ltr 83-28,Item 2.1 (Part 2) Re Vendor Interface Programs (Reactor Trip Sys) ML20195C5571988-06-0808 June 1988 SER Supporting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Equipment Classification (Reactor Trip Sys Components) ML20150F2851988-03-28028 March 1988 Safety Evaluation Supporting Resolution of Tdi Diesel Engine Vibration Problems at Facility ML20148J8611988-03-17017 March 1988 Safety Evaluation Supporting Amend 98 to License DPR-54 ML20153B2911988-03-15015 March 1988 Safety Evaluation Supporting Amend 97 to License DPR-54 ML20149L6961988-02-12012 February 1988 Safety Evaluation Supporting Amend 95 to License DPR-54 ML20055E3041988-02-12012 February 1988 Safety Evaluation Supporting Util 871223 & 880111 Proposed Changes to Tech Specs,Including Reducing Lower Limits of Detection for Liquid Radioactive Effluents ML20149L2761988-02-0909 February 1988 Safety Evaluation Supporting Amend 94 to License DPR-54 ML20148C7321988-01-0505 January 1988 Safety Evaluation Supporting Amend 93 to License DPR-54 ML20237B4141987-12-0707 December 1987 Safety Evaluation Supporting Amend 92 to License DPR-54 ML20236X1771987-12-0303 December 1987 Safety Evaluation Supporting Amend 91 to License DPR-54 ML20236X1111987-11-13013 November 1987 Safety Evaluation Supporting Amend 90 to License DPR-54 ML20236Q2461987-11-10010 November 1987 Safety Evaluation Supporting Util & Related Submittals Re Design Mods to Emergency Electrical Distribution Sys (Ref Tdi Diesel Generators) ML20236J2671987-11-0303 November 1987 Safety Evaluation Supporting Amend 89 to License DPR-54 ML20245C7051987-10-27027 October 1987 Safety Evaluation Supporting Amend 87 to License DPR-54 ML20245C7831987-10-27027 October 1987 Safety Evaluation Supporting Amend 88 to License DPR-54 ML20236G8791987-10-23023 October 1987 Safety Evaluation Supporting Amend 86 to License DPR-54 ML20236D1361987-10-23023 October 1987 Safety Evaluation Supporting Util 870826 Request to Use Repair & Replacement Program Contained in ASME Section XI 1983 Edition Including Addenda Through Summer 1983 ML20238D4151987-09-0303 September 1987 Evaluation of Engineering Rept ERPT-E0220 Re Reactor Regulation of Util Approach to Compliance W/Reg Guide 1.75 for New Diesel Generator Installation at Plant.Licensee Approach to Demonstrating Compliance Acceptable ML20238B1771987-08-27027 August 1987 Safety Evaluation Supporting Amend 85 to License DPR-54 ML20236E3731987-07-24024 July 1987 Safety Evaluation Supporting Existing & Proposed Mods to Meteorological Program & W/Planned Improvements,Facility Will Satisfy Min Meteorological Emergency Preparedness Requirements of 10CFR50.47 & 10CFR50,Apps E & F ML20205T3021987-03-31031 March 1987 Safety Evaluation Supporting Amend 84 to License DPR-54 ML20205R7871987-03-26026 March 1987 Safety Evaluation Concluding Util 831104 Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability On-Line Testing Permits on-line Functional Testing of Sys,Including Diverse Trip Features of Reactor Trip Breakers ML20205C3951987-03-13013 March 1987 Safety Evaluation Re Fracture Toughness Requirements for Protection Against PTS Events (10CFR50.61).Util 860123 Submittal Re Matl Properties & Fast Neutron Fluence of Reactor Vessel Acceptable ML20206B6561987-03-13013 March 1987 Corrected SER Re Fracture Toughness Requirements for Protection Against PTS Events (10CFR50.61).Util 860123 Submittal Re Matl Properties & Fast Neutron Fluence of Reactor Vessel Acceptable ML20205J0971987-03-11011 March 1987 Safety Evaluation Re Sys Selected for Facility Sys Review & Test Program.Sys Constitutes Adequate Scope for Sys Review & Test Program 1999-08-13
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20211H7921999-08-13013 August 1999 Safety Evaluation Supporting Amend 126 to License DPR-54 ML20195D1901999-05-0606 May 1999 Annual Rept ML20195H8571998-12-31031 December 1998 1998 Annual Rept for Smud. with ML20155D4801998-10-27027 October 1998 Amend 3 to Rancho Seco DSAR, Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode ML20248C4301998-05-0606 May 1998 Annual Rept, Covering Period 970507-980506 ML20249A7831997-12-31031 December 1997 1997 Smud Annual Rept ML20198G8271997-08-22022 August 1997 Safety Evaluation Supporting Amend 125 to License DPR-54 ML20217D3271997-07-30030 July 1997 Update of 1995 Decommissioning Evaluation for Rancho Seco Nuclear Generating Station ML20140A6371997-05-0606 May 1997 Annual Rept, Covering Period 960507-970506 ML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20137W8151997-03-20020 March 1997 Amend 1 to Post Shutdown Decommissioning Activities Rept ML20141J2711996-12-31031 December 1996 Smud 1996 Annual Rept ML20138L1231996-11-13013 November 1996 Smud Rancho Seco Incremental Decommissioning Action Plan, Rev 0,961113 ML20129E7151996-10-14014 October 1996 Defueled SAR for Rancho Seco ML20029D3561994-03-31031 March 1994 Update of 1991 Decommissioning Cost for Rancho Seco Nuclear Generating Station ML20059H6821994-01-17017 January 1994 Revised Rancho Seco Quality Manual ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20045H1071993-07-0909 July 1993 Part 21 Rept (Amend 2 to Enterprise Rept 159) Re Potential Defect in Power Cylinder Liner,Clarifying Recommended Corrective Action Delineated in .Replacement of Loose Fit Liners Will Eliminate Need for Further Insps ML20045B9051993-06-16016 June 1993 Safety Evaluation Re Order Approving Decommissioning Plan & Authorizing Decommissioning of Rsngs,Unit 1,SMUD.Concludes That Reasonable Assurance That Health & Safety of Public Will Not Be Endangered by Decommissioning Option,Provided ML20036C0081993-05-28028 May 1993 Informs Commission of Status of Open Issues & Progress of Specified Facilities Toward Decommissioning ML20059K1981993-05-0606 May 1993 Annual Rept, Covering Period from 920501- 930506,consisting of Shutdown Statistics,Narrative Summary of Shutdown Experience & Tabulations of Facility Changes, Tests & Experiments,Per 10CFR50.59(b) ML20035E4861993-04-0707 April 1993 Part 21 Rept Re K-400 Circuit Breaker Failed to Meet Certain Rating Requirements Based on ANSI C37.16.Licensees Scheduled Tests on Modified Arc Chutes in Several Different Modes at KEMA-Powertest Lab in Chalfont,Pa ML20035C1151993-03-12012 March 1993 Draft Suppl to Initial Study & Negative Declaration:Rancho Seco Nuclear Generating Station Decommissioning Plan ML20034F7031993-02-25025 February 1993 Amend 1 to Enterprise Rept 162 Re Defect on Starting Air Distributor Housing Assembly,As Followup to 930115 Final Rept.Addl Listed Part Numbers Discovered Which Are Higher Level Assemblies of Housing ML20128C9641993-02-0202 February 1993 Informs Commission of Status of Open Issues & Progress of Specified Facilities Toward Decommissioning ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20036C0601992-12-31031 December 1992 1992 Annual Rept for Smud ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML13316A1381992-11-25025 November 1992 Part 21 Rept Re Potential Problem W/Cylinder Heads Cast Prior to 840801 in Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Caused by Inadequate Casting Wall Thickness at Tapped Hole.Oil Analysis Should Be Performed Monthly ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20126E6771992-08-0303 August 1992 Rev 7 to Rancho Seco Quality Manual ML13316A0841992-01-15015 January 1992 Part 21 Rept 159 Re Potential Defect in Power Cylinder Liner in Diesel Engine of DSR-48 & DSRV-16-4 Standby Diesel Generator Sys.Investigation Continuing & Expected to Be Complete on 920301 ML13316A0791991-06-19019 June 1991 Part 21 Rept Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generator Sys Involving Intake & Exhaust Power Valve Springs Mfg by Associated Spring.Recommends That Springs Be Inspected on Periodic Basis ML20029A7511991-02-28028 February 1991 Suppl to Special Rept 90-13:on 901224,25,29 & 910113,listed Meteorological Instrumentation Inoperable for More than 7 Days.Work Request Initiated & Instrumentation Channels Declared Operable on 910116 ML20029B6721991-02-22022 February 1991 Safety Evaluation Supporting Proposed Rev to Emergency Plan & Granting Exemption from 10CFR50-54(q) Requirements NL-90-451, Monthly Operating Rept for Oct 1990 for Rancho Seco Nuclear Generating Station1990-10-31031 October 1990 Monthly Operating Rept for Oct 1990 for Rancho Seco Nuclear Generating Station ML17348B5061990-10-0909 October 1990 Part 21 Rept Re Zener Diode VR2 on Power Supply Board 9 1682 00 106 Possibly Being Installed Backwards ML20059G9621990-09-10010 September 1990 Safety Evaluation Supporting Amend 115 to License DPR-54 NL-90-443, Monthly Operating Rept for Aug 1990 for Rancho Seco1990-08-31031 August 1990 Monthly Operating Rept for Aug 1990 for Rancho Seco ML20217A5711990-08-28028 August 1990 Final Engineering Rept,Assessment of Spent Fuel Pool Liner Leakage ML20044B2071990-07-31031 July 1990 Rev 0 to Plan for Ultimate Disposition of Ranch Seco Nuclear Generating Station NL-90-439, Monthly Operating Rept for Jul 1990 for Rancho Seco Nuclear Generating Station1990-07-31031 July 1990 Monthly Operating Rept for Jul 1990 for Rancho Seco Nuclear Generating Station 05000312/LER-1990-002, :on 900614,Step 6.9.3.1 of Liquid Waste Discharge Permit Checked R-15017A as Inoperable & Two Independent Samples Not Performed.Caused by Personnel Error. Caution Will Be Added to Step 6.9.21990-07-20020 July 1990
- on 900614,Step 6.9.3.1 of Liquid Waste Discharge Permit Checked R-15017A as Inoperable & Two Independent Samples Not Performed.Caused by Personnel Error. Caution Will Be Added to Step 6.9.2
ML13316A0631990-07-19019 July 1990 Part 21 Rept Re Potential Problem W/Starting Air Admission Valve in Starting Air Sys.Caused by Air Start Piston Sticking in Air Start Valve Cap.Recommendations for Corrective Actions Forthcoming ML20055F8591990-07-16016 July 1990 Special Rept 90-11:on 900613,06,25,18,21 & 28,fire Barriers Breached More than 7 Days & Not Made Operable in 14 Days. Corrective Actions:Operability of Fire Detectors Verified on One Side of Breached Barriers NL-90-423, Monthly Operating Rept for June 1990 for Rancho Seco Nuclear Generating Station1990-06-30030 June 1990 Monthly Operating Rept for June 1990 for Rancho Seco Nuclear Generating Station ML20043H8661990-06-12012 June 1990 Special Rept 90-10 Re Fire Barriers in Auxiliary & Turbine Bldgs Which Became Inoperable & Not Returned to Svc within 7 Days as Required by Tech Spec 3.14.6.2.Operability of Fire Detectors Verified & Hourly Fire Watches Established NL-90-355, Monthly Operating Rept for May 1990 for Rancho Seco Nuclear Plant1990-05-31031 May 1990 Monthly Operating Rept for May 1990 for Rancho Seco Nuclear Plant 1999-08-13
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j NUCLEAR HEGULATORY COMMISSION 2
WASHINGTON. D.C. 3066&4001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.12sTO FACILITY OPERATING LICENSE (POSSESSION ONLY) NO. DPR-54 SACRAMENTO MUNICIPAL UTILITY DISTRICT RANCHO SECO NUCLEAR GENERATING STATION DOCKET NO. 50-312 1.0 Introduction By letter dated December 9, 1993, as superseded on December 19, 1995, and as supplemented on January 22, 1996, Sacramento Municipal Utility District (the licensee), submitted proposed changes to the Rancho Seco Nuclear Generating Station Permanently Defueled Technical Specifications (PDTS) to incorporate the revised 10 CFR Part 20.
Other changes not related to 10 CFR Part 20 were also submitted.
2.0 Evaluation The licensee has revised the TS to include wording that is consistent with the revised 10 CFR Part 20, Standards for Protection Aaainst Radiation, and will retain the same overall level of effluent control required to meet the design objectives of Appendix I to 10 CFR Part 50.
The proposed TS changes and evaluations follow:
1.
Technical Spect scation D3.6 - LIQUID HOLD-UP TANKS The licensee has proposed to change the title of the " Semi annual Radioactive Effluent Release Report" to the " Annual Radioactive Effluent Release Report."
The change is administrative in nature and is acceptable because the licensee received approval to change the frequency of submitting this report to annual in the Issuance of Amendment No. 122, 2.
Technical Specification D3/4.6 - LIQUID HOLD-UP TANKS The licensee has proposed to change the bases for the liquid holdup tanks to change a 10 CFR Part 20 reference from "10 CFR 20, Appendix B, Table II, Column 2" to "10 CFR 20 Appendix B, Table 2, Column 2."
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. The change is administrative in nature to incorporate a revised reference to 10 CFR Part 20 and is acceptable.
3.
Technical Specifications D6.6 - LICENSEE EVENT REPORT ACTION The licensee has proposed to replace the 10 CFR Part 20 reference of "20.405" with "20.2203."
This change is administrative in nature to incorporate the corresponding revised 10 CFR Part 20 section number and is acceptable.
4.
Technical Specification D6.8.3a - RADI0 ACTIVE EFFLUENT CONTROLS PROGRAM The licensee has proposed to change a 10 CFR Part 20 reference from "10 CFR Part 20, Appendix B, Table II, Column 2d to "10 CFR Part 20, Appendix B, Table 2, Column 2."
This change is administrative in nature to incorporate the corresponding revised 10 CFR Part 20 reference and is acceptable.
5.
Technical Specification D6.8.3a - RADI0 ACTIVE EFFLUENT CONTROLS PROGRAM The licensee has proposed to change the 10 CFR Part 20 reference of "20.106" to "20.1302."
This change is administrative in nature to incorporate the corresponding revised 10 CFR Part 20 section number and is acceptable.
6.
Technical Specification D6.8.3a - RADI0 ACTIVE EFFLUENT CONTROLS PROGRAM The licensee has proposed to revise this specification to read as follows:
" Limitations on the dose rate resulting from radioactive hiaterial released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY shall be limited to the following:
a)
For noble gases:
Less than or equal to a dose rate of 500 mrems/yr to the total body and less than or equal to a dose rate of 3000 mrems/yr to the skin; and, b) For tritium and for all radionuclides 'in particulate form with half-lives greater than 8 days:
Less than or equal to a dose rate of 1500 mrems/yr to any ccgan."
The change re-introduces the previously approved instantaneous gaseous effluent dose rate limits that once resided in the licensee's Radiological Effluent Technical Specifications and are now in the licensee's Off-site Dose Calculation Manual. The change is proposed in
3-order to retain operkt onal flexibility consistent with Appendix I to 10 i
CFR 50, concurrent v J.h the implementation of the revised 10 CFR Part 20.
The proposed change will retain the same overall level of effluent control required to meet the design objectives of Appendix I to 10 CFR 50.
The specification is based on NUREG-0133 and is acceptable as a dose rate limit for gaseous effluents. The limit applies at all times as an assurance that the dose design objectives in Appendix I to 10 CFR Part 50 are not likely to be exceeded. The licensee maintains that the proposed specification is not expected to have a negative impact on the ability to operate within the design objectives of Appendix I to 10 CFR Part 50 and 40 CFR Part 190.
A Based on the aoove, it is acceptable that the gaseous release rate TS for radioactive material be based on the stated dose rates.
7.
Technical Specification D6.9.1 - ROUT!NE REPORTS The licensee has proposed to change the reference to the NRC Regional Office from " Region V" to " Region IV."
The change is administrative in nature and is acceptable.
8.
Technical Specification D6.9.2.1 - ANNUAL litulVIDUAL MONITORING RESULT REPORT The licensee has proposed to replace the 10 CFR Part 20 reference of "20.407" with "20.2206."
This change is administrative in nature to incorporate the corresponding revised 10 CFR Part 20 section number and is acceptable.
9.
Technical Specificatior D6.9.5 - LICENSEE EVENT REPORT The licensee has proposed to replace the 10 CFR Part 20 reference of "20.405" with "20.2203."
This change is administratit, in nature to incorporate the corresponding revised 10 CFR Part 20 section number and is acceptable.
10.
Technical Specification D6.9.5 - LICENSEE EVENT REPORT The licensee has proposed to change the reference to the NRC Regional Office from " Region V" to " Region IV."
The change is administrative in nature and is acceptable,
- 11. Technical Specification D6.9.7 - SPECIAL REPORTS i
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The licensee has proposed to change the reference to the NRC Regional Office from " Region V" to " Region IV."
The change is administrative in nature and is acceptable
- 12. Technical Specification D6.12 - HIGH RADIATION AREAS The licensee has proposed to replace the 10 CFR Part 20 reference of "20.203" with "20.1601."
This change is administrative in nature to incorporate the corresponding revised 10 CFR Part 20 section number and is acceptable.
13.
Technical Specif"ation D6.12 - HIGH %DIATION AREAS The licensee has proposed to add an upper limit for which the TS opplies by adding the words "but less than 500 rads /hr."
The change is consistent with the revised 10 CFR Part 20 and is acceptable.
- 14. Technical Specification 06.14 - 0FF-SITE DOSE CALCULATION AND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUALS The licensee has proposed to change the 10 CFR Part 20 reference of "20.106" to "20.1302."
TMs change is administrative in nature to incorporate the corresponding revised 10 CFR Part 20 section number and is acceptable.
e
- 15. Technical Specification D6.14 - 0FF-SITE DOSE CALCULATION AND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUALS The licensee has proposed to enange the title of the " Semi annual Radioactive Effluent Release Report" to the " Annual Radioactive Effluent Release Report".
This change is administrative in nature and is acceptable because the licensee received approval to change the frequency of submitting this report to annual in the Issuance of Amendment No. 122.
3.0 STATE CONSULTATION
In accordance with the Commission's reguiations, the Caittornia State official was notified of the proposed issuance of this amendment.
The State official had no comments.
5-
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes requirements with respect to recordkeeping, reporting, or administrative procedures or requirements and changes requirements with respect to the installation or use of facility components located within the restricted area as defined by 10 CFR Part 20. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (59 FR' 10015). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and (10).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed. above, that:
(1) there is reasonable assurance that the health and safety of the public will.not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment wi not be inimical to the common defense and security or to the health ans safety of the public.
Principal Contributor: Stephen Klementowicz Date: August 22, 1997 J
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