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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217B4471999-10-0707 October 1999 Safety Evaluation Supporting Amends 159 & 150 to Licenses NPF-10 & NPF-15,respectively ML20211R0571999-09-0909 September 1999 Safety Evaluation Supporting Amends 158 & 149 to Licenses NPF-10 & NPF-15,respectively ML20212A2391999-09-0707 September 1999 Safety Evaluation Supporting Amends 157 & 148 to Licenses NPF-10 & NPF-15,respectively ML20211N0511999-09-0303 September 1999 SER Approving Exemption from Certain Requirements of 10CFR50.44 & 10CFR50 App A,General Design Criterion 41 to Remove Requirements from Hydrogen Control Systems from SONGS Units 2 & 3 Design Basis ML20211H8621999-08-23023 August 1999 Safety Evaluation Accepting Licensee Requests for Relief RR-E-2-03 - RR-E-2-08 from Exam Requirements of Applicable ASME Code,Section Xi,For First Containment ISI Interval ML20211E9441999-08-19019 August 1999 Safety Evaluation Supporting Amends 156 & 147 to Licenses NPF-10 & NPF-15,respectively ML20211F2211999-08-19019 August 1999 Safety Evaluation Supporting Amends 155 & 146 to Licenses NPF-10 & NPF-15,respectively ML20209G8991999-07-12012 July 1999 Safety Evaluation Supporting Amends 154 & 145 to Licenses NPF-10 & NPF-15,respectively ML20207A0211999-05-13013 May 1999 Safety Evaluation Supporting Amends 153 & 144 to Licenses NPF-10 & NPF-15,respectively ML20206G6561999-04-27027 April 1999 SER Accepting Proposed Exemption from 10CFR50.71(e)(4) for SONGS Units 2 & 3 ML20206D1461999-04-26026 April 1999 Safety Evaluation Supporting Amend 152 to License NPF-10 ML20205Q6221999-04-19019 April 1999 Safety Evaluation Authorizing Proposed Alternative to Use Wire Penetrameters for ISI Radiography in Place of ASME Code Requirement ML20205R0371999-04-16016 April 1999 SER Approving Proposed Deviation from Approved Fire Protection Program Incorporating Technical Requirements of 10CFR50,App R,Section III.0 That Applies to RCP Oil Fill Piping ML20205N2691999-04-0909 April 1999 Safety Evaluation Supporting Amends 151 & 143 to Licenses NPF-10 & NPF-15,respectively ML20203J1981999-02-12012 February 1999 Safety Evaluation Supporting Amends 149 & 141 to Licenses NPF-10 & NPF-15,respectively ML20203J1131999-02-12012 February 1999 Safety Evaluation Supporting Amends 150 & 142 to Licenses NPF-10 & NPF-15,respectively NUREG-0800, Safety Evaluation Supporting Amends 148 & 140 to Licenses NPF-10 & NPF-15,respectively1999-02-0909 February 1999 Safety Evaluation Supporting Amends 148 & 140 to Licenses NPF-10 & NPF-15,respectively ML20206N6281998-12-16016 December 1998 Safety Evaluation Supporting Amends 145 & 137 to Licenses NPF-10 & NPF-15,respectively ML20196A6161998-11-23023 November 1998 Safety Evaluation Supporting Amend 136 to License NPF-15 ML20154B7211998-10-0101 October 1998 Safety Evaluation Approving Licensee Request to Implement Alternatives Contained in Code Case N-546 for Current Interval at Songs,Units 2 & 3 Until Code Case Approved by Ref in Reg Guide 1.147 ML20197D0161998-09-0909 September 1998 Safety Evaluation Supporting Amends 141 & 133 to Licenses NPF-10 & NPF-15,respectively ML20239A1431998-08-26026 August 1998 Safety Evaluation Supporting Amends 140 & 132 to Licenses NPF-10 & NPF-15,respectively ML20249C7361998-06-19019 June 1998 Safety Evaluation Supporting Amends 139 & 131 to Licenses NPF-10 & NPF-15,respectively ML20203E7301998-02-17017 February 1998 SER Accepting 980105 Request to Use Mechanical Nozzle Seal Assembly as Alternate Repair Method,Per 10CFR50.55a(a)(3)(1) for Plant,Units 2 & 3 ML20202J1111997-12-0303 December 1997 Safety Evaluation Supporting Amends 137 & 129 to Licenses NPF-10 & NPF-15,respectively ML20210T0631997-08-29029 August 1997 Safety Evaluation Approving Application Re Proposed Restructuring of Enova Corp,Parent Company of San Diego Gas & Electric Co by Establishment of Holding Company W/Pacific Enterprises ML20134C9261996-10-0303 October 1996 Safety Evaluation Supporting Amends 131 & 120 to Licenses NPF-10 & NPF-15 ML20128L7231996-10-0303 October 1996 Safety Evaluation Supporting Amend 158 to License DPR-13 ML20094J5991995-11-0202 November 1995 Safety Evaluation Supporting Amends 126 & 115 to Licenses NPF-10 & NPF-15,respectively ML20091R3581995-08-23023 August 1995 Safety Evaluation Supporting Amends 124 & 113 to Licenses NPF-10 & NPF-15,respectively ML20086U0231995-07-26026 July 1995 Safety Evaluation Supporting Amends 123 & 112 to Licenses NPF-10 & NPF-15,respectively ML20086M2951995-07-14014 July 1995 Safety Evaluation Supporting Amends 120 & 109 to Licenses NPF-10 & NPF-15,respectively ML20084F6591995-05-17017 May 1995 Safety Evaluation Supporting Amends 119 & 108 to Licenses NPF-10 & NPF-15,respectively ML20081J7151995-03-17017 March 1995 Safety Evaluation Supporting Amends 118 & 107 to Licenses NPF-10 & NPF-15,respectively ML20080P3171995-02-28028 February 1995 Safety Evaluation Supporting Amends 117 & 106 to Licenses NPF-10 & NPF-15,respectively ML20078Q4101995-02-13013 February 1995 Safety Evaluation Supporting Amends 115 & 104 to Licenses NPF-10 & NPF-15,respectively ML20076M3671994-10-27027 October 1994 Safety Evaluation Supporting Amends 113 & 102 to Licenses NPF-10 & NPF-15,respectively ML20063F1671994-02-0404 February 1994 Safety Evaluation Supporting Amends 110 & 99 to Licenses NPF-10 & NPF-15,respectively ML20058B1241993-11-19019 November 1993 Safety Evaluation Accepting Proposal to Leak Rate Test SI Tank Outlet Check Valves by Using Leak Test Method Described in OM-10,Paragraph 4.2.2.3(c) ML20057G3071993-10-18018 October 1993 Safety Evaluation Granting Licensee 930616 Relief Request B-12 Re Hydrostatic Testing of Certain Welds in 4 Inch Line from Main Steam Header to Auxiliary Feedwater Pump ML20056E2441993-08-0303 August 1993 Safety Evaluation Supporting Amends 108 & 97 to Licenses NPF-10 & NPF-15,respectively ML20056E0851993-08-0202 August 1993 Safety Evaluation Accepting Licensee 890308,910301 & 911217 Responses to NRC Bulletin 88-011 Re C-E Owners Group Program for Evaluation of Pressurizer Surge Line Thermal Stratification ML20056D6421993-07-27027 July 1993 SER Approving Licensee 930305 Relief Requests B-10,B-11 & Code Case N-496 ML20128P8401993-02-17017 February 1993 Safety Evaluation Supporting Amend 153 to License DPR-13 ML20125A4341992-12-0303 December 1992 Safety Evaluation Accepting Alternative Exam Methods Per 10CFR50.55a(a)(3)(i) & Addl Info Re Auxiliary Feedwater Sys Lube Oil Cooling,Per ISI Relief Requests B-7,B-8 & B-9 & Code Case N-481 ML20085K3981991-10-0909 October 1991 Safety Evaluation Supporting Amends 100 & 89 to Licenses NPF-10 & NPF-15,respectively ML20081K1821991-06-17017 June 1991 Safety Evaluation Supporting Amends 95 & 85 to Licenses NPF-10 & NPF-15,respectively ML20081F2171991-06-0303 June 1991 Safety Evaluation Supporting Amends 94 & 84 to Licenses NPF-10 & NPF-15,respectively ML20247N3731989-08-30030 August 1989 Safety Evaluation Supporting Amends 76 & 64 to Licenses NPF-10 & NPF-15 ML20246N4321989-08-25025 August 1989 Safety Evaluation Supporting Corrected Amends 74 & 62 to Licenses NPF-10 & NPF-15,respectively 1999-09-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217B4471999-10-0707 October 1999 Safety Evaluation Supporting Amends 159 & 150 to Licenses NPF-10 & NPF-15,respectively ML20217E3381999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Songs,Units 2 & 3 05000361/LER-1999-005-01, :on 990831,loss of Physical Separation in Control Room,Occurred.Caused by Personnel Error.Creacus Train a Was Returned to Standby on 9908311999-09-23023 September 1999
- on 990831,loss of Physical Separation in Control Room,Occurred.Caused by Personnel Error.Creacus Train a Was Returned to Standby on 990831
ML20212A1471999-09-13013 September 1999 Special Rept:On 990904,condenser Monitor Was Declared Inoperable.Difficulties Encountered During Component Replacement Precluded SCE from Restoring Monitor to Service within 72 H.Alternate Method of Monitoring Was Established ML20211R0571999-09-0909 September 1999 Safety Evaluation Supporting Amends 158 & 149 to Licenses NPF-10 & NPF-15,respectively ML20212A2391999-09-0707 September 1999 Safety Evaluation Supporting Amends 157 & 148 to Licenses NPF-10 & NPF-15,respectively ML20211N0511999-09-0303 September 1999 SER Approving Exemption from Certain Requirements of 10CFR50.44 & 10CFR50 App A,General Design Criterion 41 to Remove Requirements from Hydrogen Control Systems from SONGS Units 2 & 3 Design Basis 05000206/LER-1999-001-02, :on 990808,unattended Security Weapon Was Discovered Inside Pa.Caused by Posted Security Officer Falling Asleep.Officer Was Relieved of Duties,Pa Access Was Removed & Officer Was Placed on Investigatory Suspension1999-08-31031 August 1999
- on 990808,unattended Security Weapon Was Discovered Inside Pa.Caused by Posted Security Officer Falling Asleep.Officer Was Relieved of Duties,Pa Access Was Removed & Officer Was Placed on Investigatory Suspension
ML20211Q8201999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Songs,Units 2 & 3. with ML20211H8621999-08-23023 August 1999 Safety Evaluation Accepting Licensee Requests for Relief RR-E-2-03 - RR-E-2-08 from Exam Requirements of Applicable ASME Code,Section Xi,For First Containment ISI Interval ML20211E9441999-08-19019 August 1999 Safety Evaluation Supporting Amends 156 & 147 to Licenses NPF-10 & NPF-15,respectively ML20211F2211999-08-19019 August 1999 Safety Evaluation Supporting Amends 155 & 146 to Licenses NPF-10 & NPF-15,respectively ML20210P4791999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 3 ML20210P4731999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 2 05000361/LER-1999-004-01, :on 990708,automatic Tgis Actuation Occurred. Caused by Small Leak in Suction Side of Tgis Train a Sample Pump.Small Leak Repaired1999-08-0606 August 1999
- on 990708,automatic Tgis Actuation Occurred. Caused by Small Leak in Suction Side of Tgis Train a Sample Pump.Small Leak Repaired
ML20210Q6521999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Songs,Units 2 & 3 ML20210L2771999-07-30030 July 1999 SONGS Unit 3 ISI Summary Rept 2nd Interval,2nd Period Cycle 10 Refueling Outage U3C10 Site Technical Services 05000362/LER-1999-005, :on 990630,discovered LTOP Sys Relief Valve Setpoint Was Higher than Allowed by Ts.Cause Indeterminate. Subject Valve Will Be Disassembled & Inspected to Determine Caused of High Setpoint.With1999-07-28028 July 1999
- on 990630,discovered LTOP Sys Relief Valve Setpoint Was Higher than Allowed by Ts.Cause Indeterminate. Subject Valve Will Be Disassembled & Inspected to Determine Caused of High Setpoint.With
05000362/LER-1999-006, :on 990623,EDG 3G003 Was Inadvertently Made Inoperable.Caused by Operators Aligning EDG to Inoperable Automatic Voltage Regulator.Licensee Will Revise Process of Locating Tags.With1999-07-26026 July 1999
- on 990623,EDG 3G003 Was Inadvertently Made Inoperable.Caused by Operators Aligning EDG to Inoperable Automatic Voltage Regulator.Licensee Will Revise Process of Locating Tags.With
ML20209G8991999-07-12012 July 1999 Safety Evaluation Supporting Amends 154 & 145 to Licenses NPF-10 & NPF-15,respectively ML20209C9281999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Songs,Units 2 & 3. with 05000362/LER-1999-003-01, :on 990513,reactor Manually Tripped Due to Loss of Main Feedwater.Caused by Open Relay Contact in Output of Feedwater Regulation Control Sys.Faulty Relay Was Replaced1999-06-11011 June 1999
- on 990513,reactor Manually Tripped Due to Loss of Main Feedwater.Caused by Open Relay Contact in Output of Feedwater Regulation Control Sys.Faulty Relay Was Replaced
05000362/LER-1999-004, :on 990515,reactor Manually Tripped Due to Feedwater Control Valve Opening.Caused by Faulty Valve Positioner.Faulty Positioner Was Replaced1999-06-11011 June 1999
- on 990515,reactor Manually Tripped Due to Feedwater Control Valve Opening.Caused by Faulty Valve Positioner.Faulty Positioner Was Replaced
ML20195D3061999-06-0202 June 1999 Safety Evaluation of TR SCE-9801-P, Reload Analysis Methodology for San Onofre Nuclear Generating Station,Units 2 & 3. Rept Acceptable ML20195H5491999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Songs,Units 2 & 3 05000362/LER-1999-002-01, :on 990328,RWST Outlet Isolation Valve Failed to Open After Being Closed for Testing.Caused by Degradation of Valve.Rwst Oulet Valve Was Repaired.With1999-05-20020 May 1999
- on 990328,RWST Outlet Isolation Valve Failed to Open After Being Closed for Testing.Caused by Degradation of Valve.Rwst Oulet Valve Was Repaired.With
ML20207A0211999-05-13013 May 1999 Safety Evaluation Supporting Amends 153 & 144 to Licenses NPF-10 & NPF-15,respectively ML20196L3221999-05-11011 May 1999 SONGS Unit 2 ISI Summary Rept 2nd Interval,2nd Period Cycle-10 Refueling Outage ML20206H2611999-05-0505 May 1999 Part 21 Rept Re Defect Found in Potter & Brumfield Relays. Sixteen Relays Supplied in Lot 913501 by Vendor as Commercial Grade Items.Caused by Insufficient Contact Pad Welding.Relays Replaced with New Relays ML20206S7281999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Songs,Units 2 & 3 ML20206G6561999-04-27027 April 1999 SER Accepting Proposed Exemption from 10CFR50.71(e)(4) for SONGS Units 2 & 3 ML20206D1461999-04-26026 April 1999 Safety Evaluation Supporting Amend 152 to License NPF-10 ML20205Q6221999-04-19019 April 1999 Safety Evaluation Authorizing Proposed Alternative to Use Wire Penetrameters for ISI Radiography in Place of ASME Code Requirement ML20205R0371999-04-16016 April 1999 SER Approving Proposed Deviation from Approved Fire Protection Program Incorporating Technical Requirements of 10CFR50,App R,Section III.0 That Applies to RCP Oil Fill Piping ML20205N2691999-04-0909 April 1999 Safety Evaluation Supporting Amends 151 & 143 to Licenses NPF-10 & NPF-15,respectively ML20205G2611999-04-0101 April 1999 Special Rept:On 990328,3RT-7865 Was Removed from Service. Monitor Is Scheduled to Be Returned to Service Prior to Mode 4 Entry (Early May 1999) Which Will Exceed 72 H Allowed by LCS 3.3.102.Alternate Method of Monitoring Will Be Used ML20205Q0981999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Songs,Units 2 & 3 05000362/LER-1999-001-01, :on 990211,TS 3.0.3 Entered Due to Both Chilled Water Trains Being Inoperable.Warm Main Condenser Discharged Water Diverted in Salt Water Cooling (Swc)(Bs) Intake.With1999-03-12012 March 1999
- on 990211,TS 3.0.3 Entered Due to Both Chilled Water Trains Being Inoperable.Warm Main Condenser Discharged Water Diverted in Salt Water Cooling (Swc)(Bs) Intake.With
05000361/LER-1999-002, :on 990208,pressurizer Safety Valves Were Above TS Limit.Caused by Setpoint Drift.Sce Submitted License Amend Application on 980904 Requesting Tolerence Be Changed to +3/-2%.With1999-03-10010 March 1999
- on 990208,pressurizer Safety Valves Were Above TS Limit.Caused by Setpoint Drift.Sce Submitted License Amend Application on 980904 Requesting Tolerence Be Changed to +3/-2%.With
05000361/LER-1999-001, :on 990201,automatic Start of EDG Was Noted. Caused by Workers Closing Breaker 2A0418 by Discharging Closing Springs.Operators Restored SDC in Approx 26 Minutes. with1999-03-0303 March 1999
- on 990201,automatic Start of EDG Was Noted. Caused by Workers Closing Breaker 2A0418 by Discharging Closing Springs.Operators Restored SDC in Approx 26 Minutes. with
ML20204F8101999-02-28028 February 1999 Monthly Operating Repts for Songs,Units 2 & 3.With ML20203J1131999-02-12012 February 1999 Safety Evaluation Supporting Amends 150 & 142 to Licenses NPF-10 & NPF-15,respectively ML20203J1981999-02-12012 February 1999 Safety Evaluation Supporting Amends 149 & 141 to Licenses NPF-10 & NPF-15,respectively NUREG-0800, Safety Evaluation Supporting Amends 148 & 140 to Licenses NPF-10 & NPF-15,respectively1999-02-0909 February 1999 Safety Evaluation Supporting Amends 148 & 140 to Licenses NPF-10 & NPF-15,respectively ML20202F7041999-01-21021 January 1999 Special Rept:On 990106,SCE Began to Modify 2RT-7865.2RT-7865 to Allow Monitor to Provide Input to New Radiation Monitoring Data Acquisition Sys.Monitor Found to Exceeds 72 H Allowed Bt LCS 3.3.102.Alternate Monitoring Established ML20206H2101998-12-31031 December 1998 SCE 1998 Annual Rept ML20199F0771998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Songs,Units 2 & 3 ML20206N6281998-12-16016 December 1998 Safety Evaluation Supporting Amends 145 & 137 to Licenses NPF-10 & NPF-15,respectively ML20198A6731998-12-11011 December 1998 Special Rept:On 981124,meteorological Sys Wind Direction Sensor Was Observed to Be Inoperable.Caused by Loss of Communication from Tower to Cr.Sensor Was Replaced & Sys Was Declared Operable on 981204 ML20196D8901998-11-30030 November 1998 Non-proprietary Reload Analysis Methodology for Songs,Units 2 & 3 1999-09-09
[Table view] |
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p uam gl UNITED STATES 3
S NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 2051 5 0001
/
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.151 TO FACILITY OPERATING LICENSE NO. NPF-10 AND AMENDMENT NO.143 TO FACILITY OPERATING LICENSE NO. NPF-15 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY i
THE CITY OF 31VERSIDE. CALIFORNIA THE CITY OF ANAHEIM. CALIFORNIA SAN ONOFRE NUCLEAR GENERATING STATION. UNITS 2 AND 3 DOCKET NOS. 50-361 AND 50-362
1.0 INTRODUCTION
j By application dated January 24,1997, Southern California Edison Company, et al. (SCE or the licensee) requested changes to the Technical Specifications (Appendix A to Facility Operating License Nos. NPF-10 and NPF-15) for the San Onofre Nuclear Generating Station, Unit Nos. 2 and 3. The proposed changes would revise Surveillance Requirement 3.8.1.9 to Technical t
Specification 3.8.1,'AC Sources-Operating". This would provide more limiting emergency diesel generator (EDG) voltage and frequency limits for recov'ry from the transient caused by the single largest post-accident load rejection test. The voltage and frequency limits are made tighter, to accurately reflect plant design requirements.
2.0 EVALUATION Surveillance Requirement 3.8.1.9 (SR) currently requires that the licensee:
Verify each EDG, when operating with design basis kW loading and maximum kVAR loading permitted during testing, rejects a load a 682 kW, and:
a.
Following load rejection, the frequency is s 66.75 Hz; b.
Within 4 seconds following load rejection, the voltage is a 3924 V and s 4796 V; and I
c.
Within 4 seconds f ing load rejection, the frequency is a 58.8 Hz and s 61.2 Hz.
9904160214 990409 i
PDR ADOCK 05000361 P
PDR
el 5
' The licensee has proposed to revise SR 3.8.1.9 as follows:
Verify each EDG rejects a load gmater than or equal to its associated single largest post-ac%e t load, and:
a.
Following load rejection, the frequency is s 66.75 Hz; b.
.Within 4 seconds following load rejection, the Voltage is 2 4297 V and s 4576 V; and c.
Within 4 seconds following load rejection, the frequency is a 59.7 Hz and s 61.2 Hz.
The proposed technical specification change provides more limiting voltage and frequency limits for recovery from the transient caused by the single largest post-accident load rejection test. Tne voltage and frequency limits are made tighter, to accurately reflect the assumptions made in the San Onofre accident analysis. The lower voltage is changed to 4297 V because this is the voltage that the EDG must achieve to reset the 4.16 kV engineered safety features (ESF) bus undervoltage relays to allow ESF load sequencing to proceed. Undervoltage relay reset is a permissive that must be satisfied to initiate load sequencing.
The upper limit is changed to 4576 V to be consistent with the maximum allowable steady state voltage for 4.16 kV motors (110 percent of 4160 V). The previous voltage limits were based on EDG run conditions of 4360 Vi 10 percent.
The lower frequency limit is changed from 58.8 Hz to 59.7 Hz. The lower frequency limit is equal to -0.5 percent of the 60 Hz nomina! frequency and based on maintaining acceptable high pressure safety injection system performance as assumed in the accident analyses.
In order to ensure that the EDG is tested under load conditions that are as close to design basis conditions as possible, testing is performed by rejecting an inductive load with kW and kVAR greater than or equal to the single largest post-accident load (683 kW,369 kVAR). These test conditions are consistent with the power factor requirements of Regulatory Guide 1.9 Rev. 3,
- Selection, Design, and Qualification of Diesel-Generator Units Used as Standby (Onsite)
Electric Power Systems at Nuclear Power Plants."
The ctaff concludes that the proposed voltage and frequency specified for recovery from the transient caused by the single largest post-accident load rejection are conservative in that the j
voPr.ge and frequency limits are made tighter to ensure: (1) the limits are consistent with the i
design range of the equipment powered by the EDG, and (2) the EDG continues to function as assumed in the San Onofre accident analysis. Further, rejection of an inductive load of with kW i
and kVAR greater than or equal to 683 kW and 369 kVAR make the test conditions consistent with the power factor requirements of Regulatory Guide 1.9, Rev. 3. Therefore, the proposed 3
change is acceptable.
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a l
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the California State official was notified of the proposed issuance of the amendments. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendments change a surveillance requirement. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in y
individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such hding (63 FR 6997). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmentalimpact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
1
5.0 CONCLUSION
The Commission has concluded, bLsed on the considerations discussed above, that (1) there is reasonable tissurance 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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: O. Chopra, EELB Date:
April 9, 1999 l
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