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| ==1.0 INTRODUCTION== | | ==1.0 INTRODUCTION== |
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| By letter dated May 30, 1986, the Connecticut Yankee Atomic Power Company (CYAPC0) and Northeast Nuclear Energy Company (NNECO) submitted requests for changes to the Haddam Neck Plant and Millstone Units 1, 2 and 3 technical specifications. | | By {{letter dated|date=May 30, 1986|text=letter dated May 30, 1986}}, the Connecticut Yankee Atomic Power Company (CYAPC0) and Northeast Nuclear Energy Company (NNECO) submitted requests for changes to the Haddam Neck Plant and Millstone Units 1, 2 and 3 technical specifications. |
| These amendments revise the technical specifications on fire protection and loss prevention audits to conform with the guidance of Generic Letter 82-21. More specifically, the triennial fire protection program audit for each plant will be perfonned by a qualified fire protection consultant independent of Northeast Utilities. | | These amendments revise the technical specifications on fire protection and loss prevention audits to conform with the guidance of Generic Letter 82-21. More specifically, the triennial fire protection program audit for each plant will be perfonned by a qualified fire protection consultant independent of Northeast Utilities. |
| A Notice of Consideration of Issuance of Amendments to Licenses and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing related to the requested actions was published in the Federal Register on July 16,1986(51FR25768). No comments or requests for hearing were received. | | A Notice of Consideration of Issuance of Amendments to Licenses and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing related to the requested actions was published in the Federal Register on July 16,1986(51FR25768). No comments or requests for hearing were received. |
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| > by an outside fim. | | > by an outside fim. |
| 1 By letter from T. J. Martin to W. G. Counsil dated August 1, 1984, the NRC transmitted two inspection reports which expressed concern that the relationship between the fire protection auditors and those being audited may not meet the present requirements of the technical specifications for Haddam Neck and Millstone Units 1 and 2. | | 1 By letter from T. J. Martin to W. G. Counsil dated August 1, 1984, the NRC transmitted two inspection reports which expressed concern that the relationship between the fire protection auditors and those being audited may not meet the present requirements of the technical specifications for Haddam Neck and Millstone Units 1 and 2. |
| j By letter dated May 30, 1986, CYAPC0 and NNECO requested changes to the fire protection and loss prevention audit technical specifications to remove any conflict with the guidance provided by Generic Letter 82-21. | | j By {{letter dated|date=May 30, 1986|text=letter dated May 30, 1986}}, CYAPC0 and NNECO requested changes to the fire protection and loss prevention audit technical specifications to remove any conflict with the guidance provided by Generic Letter 82-21. |
| 1 In their response letter, the lic.:nsees proposed that, beginning in November 1986, a qualified fire protection consultant, independent of Northeast Utilities, perfonn triennial fire protection program audits for each plant. | | 1 In their response letter, the lic.:nsees proposed that, beginning in November 1986, a qualified fire protection consultant, independent of Northeast Utilities, perfonn triennial fire protection program audits for each plant. |
| The staff has reviewed the proposed changes to the technical specifications i for the Haddam Neck Plant and Millstone Units 1, 2 and 3 and has concluded that the proposed changes conform to the guidance concerning triennial | | The staff has reviewed the proposed changes to the technical specifications i for the Haddam Neck Plant and Millstone Units 1, 2 and 3 and has concluded that the proposed changes conform to the guidance concerning triennial |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217K3301999-10-19019 October 1999 Safety Evaluation Supporting Amend 195 to License DPR-61 ML20211G9631999-08-30030 August 1999 SER Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20196J2191999-06-30030 June 1999 SER Concluding That Licensee USI A-46 Implementation Program,In General,Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20207G6411999-06-0303 June 1999 Safety Evaluation Supporting Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20206M4631999-05-11011 May 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Perform Ultrasonic Exam on Inner Surface of Nozzle to safe-end Weld ML20206G6221999-05-0404 May 1999 SER Accepting Util Request to Apply leak-before-break Status to Pressurizer Surge Line Piping for Millstone Nuclear Power Station,Unit 2 ML20206C8761999-04-28028 April 1999 Safety Evaluation Supporting Amend 194 to License DPR-61 ML20204H7131999-03-17017 March 1999 Safety Evaluation Concluding That NNECO Provided Adequate Justification for Deviations from RG 1.97,Rev 2, Recommendations,For Instrumentation Monitoring CST Level & Containment Area Radiation at Mnps Unit 2 ML20204C9441999-03-10010 March 1999 Safety Evaluation Denying Licensee Request for License Amend to Revise Frequency of Certain SRs for Electrical Power Sys ML20207L2631999-03-0505 March 1999 Safety Evaluation Supporting Amend 104 to License DPR-21 ML20207L5961999-02-22022 February 1999 Safety Evaluation Concluding That Code Requirements,Which Require 100 Percent Volumetric Exam of RPV flange-to-shell, Impractical to Perform to Extent Required & That Alternative Provide Reasonable Assurance of Structural Integrity ML20203D7601999-02-11011 February 1999 Safety Evaluation Supporting Millstone 1 Certified Fuel Handler Training & Retraining Program ML20196B0501998-11-24024 November 1998 Safety Evaluation Re Licensee 960213 Submittal of 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant,Unit 2 ML20155K1981998-11-0909 November 1998 Safety Evaluation Re Application of leak-before-break Status to Portions of Safety Injection & Shutdown Cooling Sys ML20195B8711998-11-0909 November 1998 Safety Evaluation Approving Revised Evaluation of Primary Cold Leg Piping leak-before-break Analysis for Plant ML20155C3781998-10-30030 October 1998 SER Denying Amend to Allow Changes to Fsar.Nrc Found That NNECO Had Not Considered Diversity Provided by Switch in Control Room That Removes Power to 1 of 2 MOV in SDC Sys Flow Path in Evaluation of High Low Pressure Design ML20155C8441998-10-29029 October 1998 Safety Evaluation Accepting Licensee Proposal to Withdraw ATWS Test Commitment ML20238F2131998-08-28028 August 1998 SER Accepting Defueled Emergency Plan for Emergency Planning for Connecticut Yankee Atomic Power Co ML20238F2781998-08-27027 August 1998 SER Related to Proposed Rev 20 to Northeast Utilities Quality Assurance Program Topical Rept for Millstone Nuclear Power Station,Units 1,2 & 3 ML20237D5001998-08-20020 August 1998 SER Approving Code Case N-389-1, Alternative Rules for Repairs,Replacements,Or Mods,Section Xi,Div 1 ML20236U7051998-07-22022 July 1998 Safety Evaluation Granting All Requests for Relief W/Exception of Requests RR-89-17 (Authorized for Class 1 Sys Only) & RR-89-21.Requests RR-13 & RR-14 Will Be Addressed in Separate Evaluation ML20236K6971998-07-0101 July 1998 SER Accepting Third 10-year Interval Inservice Insp Program Plan,Rev 2 & Associated Request for Relief & Proposed Alternatives for Plant,Unit 2 ML20236K3531998-07-0101 July 1998 Safety Evaluation Supporting Amend 218 to License DPR-65 ML20202D1621998-06-30030 June 1998 Safety Evaluation Supporting Amend 193 to License DPR-61 ML20249C2541998-06-24024 June 1998 Safety Evaluation Accepting Proposed Rev 19 to NNECO QAP Topical Rept & Amended Through 980609.Informs That NNECO Exception to Provisions in Paragraph 10.3.5 of Constitutes Temporary & Acceptable Alternative ML20248J0031998-06-0404 June 1998 Safety Evaluation Accepting Millstone Nuclear Power Station Emergency Plan ML20248M2991998-06-0202 June 1998 Safety Evaluation Approving Application Re Restructuring of Central Maine Power Co by Establishment of Holding Company ML20248C4131998-05-26026 May 1998 SER of Individual Plant Exam of External Events Submittal on Millstone Nuclear Power Station,Unit 3 ML20217M4181998-04-30030 April 1998 Suppl Safety Evaluation Accepting Licensee RCS Pressure & Heat Removal by Containment Heat Removal Sys post-accident Monitoring Instrumentation ML20217K2101998-03-27027 March 1998 Safety Evaluation Supporting Amend 192 to License DPR-61 ML20216G7921998-03-13013 March 1998 Safety Evaluation Authorizing Proposed Alternative to Check Valve Obturator Movement Requirements of OM-10 for SIL Accumulator Outlet for Listed Check Valves ML20203E8521998-02-17017 February 1998 SER Accepting Request for Relief from Requirements of 10CFR50.55a(f) for Performing Required Inservice Testing of Certain Class 2 Components IAW ASME Boiler & Pressure Vessel Code Section XI for Plant,Unit 3 ML20203E9341998-02-17017 February 1998 SER Accepting Request for Relief from Requirements of 10CFR50.55a(g) for Performing Required Exams for Certain Class 1 Components IAW ASME Boiler & Pressure Vessel Code Section XI for Plant,Unit 3 ML20203E2441998-02-0909 February 1998 Safety Evaluation Accepting Re Approval of Realistic,Median Centered Spectra Generated for Resolution of USI-A-46 ML20198R9941998-01-13013 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Millstone Nuclear Power Station,Unit 3 ML20202H7461997-12-10010 December 1997 Safety Evaluation Accepting Licensee Position That Correction of AC-11 Single Failure Vulnerability Unncessary ML20202J0911997-12-0202 December 1997 Safety Evaluation Accepting Proposed Exemption,Which Meets Special Circumstance Given in 10CFR50.12(a)(2)(ii) ML20198S2411997-10-31031 October 1997 SE Accepting Licensee Request for Deviations from Recommendations in Reg Guide 1.97,Rev 2 for Temp & Flow Monitoring Instrumentation for Cooling Water to ESF Sys Components & Containment Isolation Valve Position ML20212G5991997-10-27027 October 1997 Safety Evaluation Supporting Amend 103 to License DPR-21 ML20217K8801997-10-27027 October 1997 Correction to Safety Evaluation Supporting Amend 103 to License DPR-21.Phrase or Rod Block Protection Has Been Deleted from Listed Sentence in Staff Associated SE ML20212F1381997-10-22022 October 1997 Safety Evaluation Supporting Amend 102 to License DPR-21 ML20198M8101997-10-14014 October 1997 SER Accepting Proposed Revs to Util Quality Assurance Program at Facility ML20217M9301997-08-19019 August 1997 Safety Evaluation Accepting Continued Operation W/O High Startup Rate Trip by Nene for Millstone,Unit 2 ML20149J2661997-07-23023 July 1997 Safety Evaluation Accepting Changes & Reanalyses in ECCS Evaluation Models & Application of Models for Plant,Unit 2 ML20141L8821997-05-28028 May 1997 Safety Evaluation Supporting Amend 101 to License DPR-21 ML20141K4201997-05-22022 May 1997 Safety Evaluation Supporting Amend 191 to License DPR-61 ML20138A0111997-04-23023 April 1997 Safety Evaluation Accepting Licensee Proposal,Not to Perform Type C Leakage Rate Testing on 14 Subject CIVs ML20137V5931997-04-15015 April 1997 Safety Evaluation Supporting Amend 100 to License DPR-21 ML20137U3121997-04-10010 April 1997 Safety Evaluation Supporting Amends 99,206 & 135 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20134A0331997-01-23023 January 1997 Safety Evaluation Accepting Util Proposed Alternatives to ASME Code Requirements 1999-08-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P5391999-10-25025 October 1999 Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217K3301999-10-19019 October 1999 Safety Evaluation Supporting Amend 195 to License DPR-61 ML20217C8721999-10-0606 October 1999 Rev 21,change 3 to MP-02-OST-BAP01, Nuqap Topical Rept, App F & G Only B17896, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With B17894, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With B17898, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216J4341999-09-24024 September 1999 Mnps Unit 3 ISI Summary Rept,Cycle 6 ML20211N8401999-09-0202 September 1999 Rev 21,change 1 to Northeast Utils QA TR, Including Changes Incorporated Into Rev 20,changes 9 & 10 ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 B17878, Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With B17874, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With B17879, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With ML20211G9631999-08-30030 August 1999 SER Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves B17858, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With B17856, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With ML20211A6561999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2 ML20210J0311999-07-21021 July 1999 Rev 20,Change 10 to QAP 1.0, Organization ML20210E5931999-07-19019 July 1999 Revised Page 16 of 21,to App F of Northeast Util QA Program Plan ML20210A0411999-07-15015 July 1999 Rev 20,change 10 to Northeast Util QA Program Tr ML20210C5911999-07-15015 July 1999 Revised Rev 20,change 10 to Northeast Util QA Program TR, Replacing Summary of Changes B17814, Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start1999-07-12012 July 1999 Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start ML20209D1881999-07-0101 July 1999 Rev 20,change 9 to Northeast Util QA Program Tr ML20196J1821999-06-30030 June 1999 Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) Tr ML20209J0541999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Unit 2 B17833, Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With B17830, Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With ML20196A8451999-06-30030 June 1999 Post Shutdown Decommissioning Activities Rept ML20196J2191999-06-30030 June 1999 SER Concluding That Licensee USI A-46 Implementation Program,In General,Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20196K1791999-06-30030 June 1999 Addendum 6 to Millstone Unit 2 Annual Rept, ML20211A6751999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level & Operating Data Rept ML20195H1011999-06-11011 June 1999 Rev 20,change 8 to Northeast Utilities QAP (Nuqap) TR ML20207G6411999-06-0303 June 1999 Safety Evaluation Supporting Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively B17808, Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With ML20211B7351999-05-31031 May 1999 Cycle 7 Colr B17807, Monthly Operating Rept for May 1999 for Mnps,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 1.With B17804, Monthly Operating Rept for May 1999 for Mnps,Unit 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 2.With ML20211A6631999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level,Operating Data Rept & Unit Shutdowns & Power Reductions ML20209J0661999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 ML20206M4631999-05-11011 May 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Perform Ultrasonic Exam on Inner Surface of Nozzle to safe-end Weld ML20206J8351999-05-0707 May 1999 Rev 20,Change 7 to QAP-1.0, Northeast Utls QA Program (Nuqap) Tr ML20206G6221999-05-0404 May 1999 SER Accepting Util Request to Apply leak-before-break Status to Pressurizer Surge Line Piping for Millstone Nuclear Power Station,Unit 2 ML20206E2971999-04-30030 April 1999 Rev 1 to Millstone Nuclear Power Station,Unit 2 COLR - Cycle 13 B17782, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With ML20205K6141999-04-30030 April 1999 Non-proprietary Version of Rev 2 to Holtec Rept HI-971843, Licensing Rept for Reclassification of Discharge in Millstone Unit 3 Spent Fuel Pool B17777, Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with B17775, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With ML20205R3531999-04-30030 April 1999 Addendum 4 to Annual Rept, ML20206C8761999-04-28028 April 1999 Safety Evaluation Supporting Amend 194 to License DPR-61 ML20205R8751999-04-0909 April 1999 Provides Commission with Staff Assessment of Issues Related to Restart of Millstone Unit 2 & Staff Recommendations Re Restart Authorization for Millstone Unit 2 ML20205Q5891999-04-0909 April 1999 Rev 20,change 6 to QAP-1.0,Northeast Utils QA Program TR 1999-09-30
[Table view] |
Text
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( UNITED STATES
-[g o,$ NUCLEAR REGULATORY COMMISSION a wasHmorow.o.c.zosos
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 83 TO FACILITY OPERATING LICENSE N0. DPR-61 SUPPORTING AMENDMENT NO.111 TO PROVISIONAL OPERATING LICENSE N0. DPR-21 SUPPORTING AMENDMENT NO.112 TO FACILITY OPERATING LICENSE N0. OPR-65 SUPPORTING AMENDMENT N0. 1 TO FACILITY OPERATING LICENSE NO. NPF-49 CONNECTICUT YANKEE ATOMIC POWER COMPANY NORTHEAST NUCLEAR ENERGY COMPANY HADDAM NECK PLANT AND MILLSTONE UNITS 1, 2 AND 3 DOCKET NOS. 50-213, 50-245, 50-336 AND 50-423
1.0 INTRODUCTION
By letter dated May 30, 1986, the Connecticut Yankee Atomic Power Company (CYAPC0) and Northeast Nuclear Energy Company (NNECO) submitted requests for changes to the Haddam Neck Plant and Millstone Units 1, 2 and 3 technical specifications.
These amendments revise the technical specifications on fire protection and loss prevention audits to conform with the guidance of Generic Letter 82-21. More specifically, the triennial fire protection program audit for each plant will be perfonned by a qualified fire protection consultant independent of Northeast Utilities.
A Notice of Consideration of Issuance of Amendments to Licenses and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing related to the requested actions was published in the Federal Register on July 16,1986(51FR25768). No comments or requests for hearing were received.
8609170226 860909 3 DR ADOCK 0500
2.0 EVALUATION Generic Letter 82-21, dated October 6, 1982, from the Director, Division of Licensing, to all licensees, specified that the annual audit, in
- accordance with Standard Technical Specification-(STS) 6.5.2.8.1, may i be performed by qualified utility personnel who are not directly responsible for the site fire protection program or an outside independent fire protection consultant, but the three-year audit in accordance with STS 6.5.2.8.j must be perfomed by an outside independent fire protection consultant.
i Technical Specifications 6.5.2.8.1 for the Haddam Neck Plant and 6.5.4.7 e for Millstone Units 1, 2 and 3 require that th,e annual audit of the licensee's fire protection and loss prevention program shall be perfonned
> by an outside fim.
1 By letter from T. J. Martin to W. G. Counsil dated August 1, 1984, the NRC transmitted two inspection reports which expressed concern that the relationship between the fire protection auditors and those being audited may not meet the present requirements of the technical specifications for Haddam Neck and Millstone Units 1 and 2.
j By letter dated May 30, 1986, CYAPC0 and NNECO requested changes to the fire protection and loss prevention audit technical specifications to remove any conflict with the guidance provided by Generic Letter 82-21.
1 In their response letter, the lic.:nsees proposed that, beginning in November 1986, a qualified fire protection consultant, independent of Northeast Utilities, perfonn triennial fire protection program audits for each plant.
The staff has reviewed the proposed changes to the technical specifications i for the Haddam Neck Plant and Millstone Units 1, 2 and 3 and has concluded that the proposed changes conform to the guidance concerning triennial
! fire protection audits provided by Generic Letter 82-21. Therefore, the staff concludes that the proposed changes are acceptable. .
j
3.0 ENVIRONMENTAL CONSIDERATION
These amendments involve changes to the surveillance requirements. The 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 individual or cumulative occupational radiation exposure. The Commission '
has previously issued proposed findings that these amendments involve no significant hazards consideration and there has been no public connent on such finding. Accordingly, these 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 environmental impact , statement or environmental assessment need be prepared in connection with the issuance of these .
. amendments.
t
4.0 CONCLUSION
The staff 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.
and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the connon defense and security or to the health and safety of the public.
4 5.0 ACKNOWLEDGEMENT This Safety Evaluation has been prepared by F. Akstulewicz.
Dated: September 9,1986 4
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