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MONTHYEARML20096C9121984-08-0606 August 1984 Requests Extension to 841215 for Response to Generic Ltr 84-15 Re Diesel Generator Reliability.Extension Requested Due to Manpower Constraints,Time Needed to Collect,Verify & Analyze Data & Time Required to Formulate Future Actions Project stage: Other ML20101N6601984-12-28028 December 1984 Forwards Response to 840702 Generic Ltr 84-15 Re Reduction in Number of Cold Fast Starts Surveillance Tests for Diesel Generators & Diesel Generator Reliability Data Project stage: Other ML20101S5361985-01-28028 January 1985 Forwards Revised Pages to 841228 Response to Generic Ltr 84-15 Re Diesel Generator Reliability Data.Revised List of Failures & Causes of Failures for Each Diesel Generator for Last 20 & 100 Demands Encl Project stage: Other ML20101R8571985-01-31031 January 1985 Informs That Diesel Generator Reliability Info Submitted in in Response to Generic Ltr 84-15 Precludes Separate Response to Generic Ltr 83-41 Re Fast Cold Starts of Diesel Generators Project stage: Other ML20134A1321985-10-25025 October 1985 Advises of Review of Tech Specs & Intent to Prepare Application for Amend in Response to Generic Ltr 84-15 Re Diesel Generator Reliability.Schedule Discussed W/Nrc Project Manager on 851008 Project stage: Request ML20140F8511986-03-21021 March 1986 Proposed Tech Spec Sections 2 & 3 Incorporating Surveillance Requirements for Solid Radwaste.Discussion,Justification & Significant Hazards Consideration Encl Project stage: Other ML20140F8391986-03-21021 March 1986 Application for Amend to License DPR-40,changing Sections 2 & 3 of Tech Specs to Incorporate Surveillance Requirements for Solid Radwaste Project stage: Request ML20140F8161986-03-28028 March 1986 Forwards Application for Amend to License DPR-40,changing Sections 2 & 3 of Tech Specs to Incorporate Surveillance Requirements for Solid Radwaste.Certificate of Svc Encl. Fee Paid Project stage: Request ML20205M3801986-04-0909 April 1986 Application for Amend to License DPR-40,revising Tech Specs Re Surveillance Requirements for Emergency Diesel Generator Project stage: Request ML20205M3641986-04-0909 April 1986 Forwards Application for Amend to License DPR-40,revising Tech Specs,Re Surveillance Requirements for Emergency Diesel Generators Project stage: Request ML20207S1161987-03-13013 March 1987 Forwards Response to Questions Raised on 860321 Application for Amend to License DPR-40 Re Testing of Emergency Diesel Generators to Complete Generic Ltr 84-15 Actions Project stage: Request ML20216D0571987-06-22022 June 1987 Proposed Tech Specs Re Deletion of Requirement to Start Diesel Engine Project stage: Other ML20216D0271987-06-22022 June 1987 Update to 860321 Application for Amend to License DPR-40, Incorporating Discussion,Justification & Significant Hazards Considerations Re Deletion of Requirement to Start Diesel Engine Project stage: Request ML20235G8961987-09-24024 September 1987 Safety Evaluation Supporting Amend 111 to License DPR-40 Project stage: Approval ML20235G8881987-09-24024 September 1987 Amend 111 to License DPR-40,incorporating Revised Surveillance Requirements for Diesel Generators Into Tech Specs,Per Generic Ltr 84-15, Proposed Staff Actions to Improve & Maintain Diesel Generator Reliability Project stage: Other ML20235G8721987-09-24024 September 1987 Forwards Amend 111 to License DPR-40 & Safety Evaluation. Amend Incorporates Revised Surveillance Requirements for Diesel Generators Into Tech Specs,Per Generic Ltr 84-15, Proposed Staff Actions..., Per Util 860328 Request Project stage: Approval 1986-03-21
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217B5401999-10-0606 October 1999 Safety Evaluation Supporting Amend 193 to License DPR-40 ML20211J9321999-09-0202 September 1999 Safety Evaluation Concluding That Licensee Proposed Alternatives Provide Acceptable Level of Quality & Safety. Proposed Alternatives Authorized for Remainder of Third ten- Yr ISI Interval for Fort Calhoun Station,Unit 1 ML20210G2181999-07-27027 July 1999 Safety Evaluation Supporting Amend 192 to License DPR-40 ML20210D9951999-07-22022 July 1999 Safety Evaluation Supporting Amend 191 to License DPR-40 ML20206L4241999-05-10010 May 1999 Safety Evaluation Supporting Corrective Actions to Ensure That Valves Are Capable of Performing Intended Safety Functions & OPPD Adequately Addressed Requested Actions Discussed in GL 95-07 ML20206M2601999-05-0606 May 1999 SER Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & IPEEE Results Reasonable Given FCS Design,Operation & History ML20205Q5831999-04-15015 April 1999 Safety Evaluation Supporting Amend 190 to License DPR-40 ML20198S3771998-12-31031 December 1998 Safety Evaluation Supporting Amend 189 to License DPR-40 ML20198S4831998-12-31031 December 1998 Safety Evaluation Supporting Amend 188 to License DPR-40 ML20154M4881998-10-19019 October 1998 Safety Evaluation Supporting Amend 186 to License DPR-40 ML20154N2411998-10-19019 October 1998 Safety Evaluation Supporting Amend 187 to License DPR-40 ML20236V4891998-07-30030 July 1998 Safety Evaluation Relating to Response to GL 87-02,suppl 1 for Fort Calhoun Station,Unit 1 ML20248C0671998-05-21021 May 1998 Safety Evaluation Granting Licensee Request for Exemption from Technical Requirements of 10CFR50,App R, Fire Protection Program for Nuclear Power Facilities Operating Prior to 790101 ML20217L7201998-03-23023 March 1998 Safety Evaluation Supporting Amend 185 to License DPR-40 ML20203M4161998-02-0303 February 1998 Safety Evaluation Supporting Amend 184 to License DPR-40 ML20203A4291998-01-26026 January 1998 Safety Evaluation Supporting Amend 183 to License DPR-40 ML20199L0711997-11-24024 November 1997 Safety Evaluation Supporting Amend 182 to License DPR-40 ML20198Q4031997-10-28028 October 1997 Safety Evaluation Re Control Room Habitability Requirements ML20137L6241997-03-27027 March 1997 Safety Evaluation Supporting Amend 181 to License DPR-40 ML20134N7751997-02-13013 February 1997 Safety Evaluation Supporting Amend 180 to License DPR-40 ML20134M6171997-02-13013 February 1997 Safety Evaluation Denying Licensee Request for Approval to Use ASME Section XI Code Case N-416-1 W/Proposed Exception & Code Case N-498-2 as Alternative to Required Hydrostatic Pressure Test ML20133P9161997-01-23023 January 1997 Safety Evaluation Accepting Revised Temperature Limits for DG-1 & DG-2 ML20133C2771996-12-30030 December 1996 Safety Evaluation Supporting Amend 179 to License DPR-40 ML20132F4911996-12-0909 December 1996 Safety Evaluation Related to Individual Plant Evaluation Omaha Power District,Fort Calhoun Station,Unit 1 ML20134M0871996-11-19019 November 1996 Safety Evaluation Supporting Request for Relief from Modifying Supports SIH-3,SIS-63,SIS-65 & RCH-13 at Fort Calhoun Station ML20129H3371996-10-25025 October 1996 Safety Evaluation Supporting Amend 178 to License DPR-40 ML20128F6441996-10-0202 October 1996 Safety Evaluation Supporting Amend 177 to License DPR-40 ML20129G3131996-09-27027 September 1996 Safety Evaluation Supporting Amend 176 to License DPR-40 ML20059J1831994-01-14014 January 1994 Safety Evaluation Supporting Amend 160 to License DPR-40 ML20059J2491994-01-14014 January 1994 Safety Evaluation Supporting Amend 159 to License DPR-40 ML20058G9371993-12-0303 December 1993 Safety Evaluation Supporting Amend 158 to License DPR-40 ML20058F5951993-11-22022 November 1993 Safety Evaluation Supporting Amend 157 to License DPR-40 ML20058C7491993-11-18018 November 1993 Safety Evaluation,Authorizing Alternative,On One Time Basis Only,W/Conditions That Licensee Perform Volumetric Exam of nozzle-to-vessel Welds During First Refueling Outage of Third 10-yr Insp Interval ML20059L7081993-11-10010 November 1993 Safety Evaluation Accepting Licensee Proposed Changes to Low Power Physics Testing Program ML20059G6601993-10-29029 October 1993 Safety Evaluation Supporting Amend 156 to License DPR-40 ML20057E3471993-10-0101 October 1993 Safety Evaluation Advising That Based on Determination That Alternative Testing Consistent w/OM-10,paragraph 4.3.2.2. Requirements,No Relief Required ML20056E5411993-08-12012 August 1993 Safety Evaluation Supporting Amend 155 to License DPR-40 ML20056E5371993-08-10010 August 1993 Safety Evaluation Supporting Amend 154 to License DPR-40 ML20056D6801993-07-26026 July 1993 Safety Evaluation Supporting Amend 153 to License DPR-40 ML20128B8241993-01-26026 January 1993 Safety Evaluation Supporting Amend 149 to License DPR-40 ML20128D4511992-11-30030 November 1992 Safety Evaluation Accepting Evaluation of 120-day Response to Suppl 1 to GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors, Unresolved Safety Issue A-46 ML20062G6621990-11-19019 November 1990 Safety Evaluation Supporting Amend 134 to License DPR-40 ML20216K0661990-11-14014 November 1990 Safety Evaluation Denying Util 900221 & 0622 Requests for Exemption from App R of 10CFR50 for Fire Area 34B,upper Electrical Penetration Room.Current Level of Fire Protection Does Not Meet Section III.G.2 Requirements ML20062B6161990-10-12012 October 1990 Safety Evaluation Supporting Amend 133 to License DPR-40 ML20055G0221990-07-0606 July 1990 Safety Evaluation Supporting Amend 132 to License DPR-40 ML20246A0741989-08-17017 August 1989 Safety Evaluation Re Inservice Testing Program for Pumps & Valves ML20245H9031989-08-15015 August 1989 Safety Evaluation Re Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components). Licensee Program Meets Requirements of Item 2.1 (Part 1) of Generic Ltr 83-28 & Acceptable ML20245K3481989-08-11011 August 1989 Safety Evaluation Accepting Electrical Isolation Devices for Interfacing Safety & Nonsafety Sys Re Implementation of ATWS Rule ML20247H6421989-07-24024 July 1989 Safety Evaluation Granting 890118 Request for Relief from Hydrostatic Testing Requirements of Section XI of ASME Code ML20248C0851989-06-0202 June 1989 Safety Evaluation Supporting Amend 122 to License DPR-40 1999-09-02
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217B5401999-10-0606 October 1999 Safety Evaluation Supporting Amend 193 to License DPR-40 ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data LIC-99-0096, Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With ML20211J9321999-09-0202 September 1999 Safety Evaluation Concluding That Licensee Proposed Alternatives Provide Acceptable Level of Quality & Safety. Proposed Alternatives Authorized for Remainder of Third ten- Yr ISI Interval for Fort Calhoun Station,Unit 1 LIC-99-0084, Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With ML20216E6431999-08-26026 August 1999 Rev 19 to TDB-VI, COLR for FCS Unit 1 ML20210R1961999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Fcs,Unit 1 ML20210G2181999-07-27027 July 1999 Safety Evaluation Supporting Amend 192 to License DPR-40 ML20210D9951999-07-22022 July 1999 Safety Evaluation Supporting Amend 191 to License DPR-40 ML20216E6361999-07-21021 July 1999 Rev 18 to TDB-VI, COLR for FCS Unit 1 ML20210R2081999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Fcs,Unit 1 LIC-99-0065, Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20210P5461999-06-0808 June 1999 Rev 0,Vols 1-5 of Fort Calhoun Station 1999 Emergency Preparedness Exercise Manual, to Be Conducted on 990810. Pages 2-20 & 2-40 in Vol 2 & Page 4-1 in Vol 4 of Incoming Submittal Not Included ML20195B4581999-05-31031 May 1999 Rev 3 to CE NPSD-683, Development of RCS Pressure & Temp Limits Rept for Removal of P-T Limits & LTOP Requirements from Ts ML20207H7401999-05-31031 May 1999 Performance Indicators Rept for May 1999 LIC-99-0053, Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 11999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 1 ML20195B4521999-05-17017 May 1999 Technical Data Book TDB-IX, RCS Pressure - Temp Limits Rept (Ptlr) ML20206L4241999-05-10010 May 1999 Safety Evaluation Supporting Corrective Actions to Ensure That Valves Are Capable of Performing Intended Safety Functions & OPPD Adequately Addressed Requested Actions Discussed in GL 95-07 ML20206M2601999-05-0606 May 1999 SER Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & IPEEE Results Reasonable Given FCS Design,Operation & History LIC-99-0047, Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With ML20195E8621999-04-30030 April 1999 Performance Indicators, for Apr 1999 ML20205Q5831999-04-15015 April 1999 Safety Evaluation Supporting Amend 190 to License DPR-40 ML20210J4331999-03-31031 March 1999 Changes,Tests, & Experiments Carried Out Without Prior Commission Approval for Period 981101-990331.With USAR Changes Other than Those Resulting from 10CFR50.59 ML20206G2641999-03-31031 March 1999 Performance Indicators Rept for Mar 1999 LIC-99-0034, Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With ML20205J8181999-02-28028 February 1999 Performance Indicators, for Feb 1999 LIC-99-0025, Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With ML20207F3291999-01-31031 January 1999 FCS Performance Indicators for Jan 1999 ML20203B0991998-12-31031 December 1998 Performance Indicators for Dec 1998 LIC-99-0026, 1998 Omaha Public Power District Annual Rept. with1998-12-31031 December 1998 1998 Omaha Public Power District Annual Rept. with LIC-99-0003, Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With ML20198S3771998-12-31031 December 1998 Safety Evaluation Supporting Amend 189 to License DPR-40 ML20198S4831998-12-31031 December 1998 Safety Evaluation Supporting Amend 188 to License DPR-40 ML20196G2251998-12-18018 December 1998 Rev 2 to EA-FC-90-082, Potential Over-Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment ML20198M3141998-11-30030 November 1998 Performance Indicators Rept for Nov 1998 LIC-98-0172, Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With LIC-98-0160, Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated1998-11-25025 November 1998 Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated ML20203B0721998-11-16016 November 1998 Rev 6 to HI-92828, Licensing Rept for Spent Fuel Storage Capacity Expansion ML20196E4981998-10-31031 October 1998 Performance Indicators Rept for Oct 1998 ML20196G2441998-10-31031 October 1998 Changes,Tests & Experiments Carried Out Without Prior Commission Approval. with USAR Changes Other than Those Resulting from 10CFR50.59 LIC-98-0154, Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With ML20154M4881998-10-19019 October 1998 Safety Evaluation Supporting Amend 186 to License DPR-40 ML20154N2411998-10-19019 October 1998 Safety Evaluation Supporting Amend 187 to License DPR-40 LIC-98-0136, Monthly Operating Rept for Sept 1998 for Fort Calhoun Station,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Fort Calhoun Station,Unit 1.With ML20155G4261998-09-30030 September 1998 Performance Indicators for Sept 1998 ML20154A1251998-08-31031 August 1998 Performance Indicators, Rept for Aug 1998 LIC-98-0122, Monthly Operating Rept for Aug 1998 for Fort Calhoun Station Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Fort Calhoun Station Unit 1.With ML20238F7231998-08-17017 August 1998 Owner'S Rept for Isis ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency 1999-09-30
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< SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED T0' AMENDMENT NO.111 TO FACILITY OPERATING LICENSE N0. OPR-40 OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT NO. 1 DOCKET NO. 50-285
1.0 INTRODUCTION
By letter dated March 28, 1986, as supplemented by letters dated April 9, 1986, March 13 and June 22, 1987, Omaha Public Power District (licensee) requested changes to the Technical Specifications for Fort Calhoun Station, Unit 1.
The changes are in response to NRC's July 2, 1984 Generic Letter 84-15 entitled, " Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability." The changes are intended to reduce the number of unnecessary diesel generator cold fast starts, thus making them more reliable.
2.0 EVALUATION The proposed Technical Specifications changes and our evaluation of these proposed changes are as follows.
2.1 Action Statement 2.4 Technical Specification (TS) Section 2.4, Limiting Conditions for Operation (LCO) of the Containment Cooling System, currently allows during power operation a total of two components listed in TS Sections 2.4.1.a and 2.4.1.b to be inoperable at any one time (in addition to one raw water pump) provided that the emergency diesel generator connected to the other engineered safeguards 4.16 kV bus (1A4 or 1AS) is started to demonstrate operability. The licensee has proposed to delete the requirement of testing diesel generator ,
during the LC0 for Containment Cooling System. The staff has reviewed the above proposed TS change and finds it to be consistent with Generic Letter 84-15 to improve and maintain the diesel generator reliability by reducing excessive diesel generator testing and find it acceptable.
2.2 Action Statement 3.7(1)a Technical Specification 3.7(1)a currently requires diesel generator surveillance to be performed from ambient conditions and for the diesel generator to start and accelerate to rated speed and voltage in less than or equal to 10 seconds. The proposed change will require starting each diesel generator at least once per 184 days from ambient e709300280 ADOCK O}ppg$h PDR P
- _ _ _ _ _ _ _ _ _ _ _ _ _ _. )
s-conditions and accelerating to rated speed and voltage in less than or equal to 10 seconds. All other engine starts in this specification may be proceeded by an engine prelube period and/or other warm-up procedures as recommended by the manufacturers. We find this change to be consistent with Generic Letter 84-15 andl acceptable. Other !'
proposed changes in this TS section are as follows:
Technical Specification 3.7(1)c has been reworded for clarity. Current TS 3.7(1)e becomes 3.7(1)c(iii) and is modified to include verification that the autoconnected loads do not exceed the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating of the engine rather than continuous rating of 2500 kW, consistent with Standard Technical Specifications. The portion of current TS 3.7(1)c ,
. dealing with manual control of the diesel generators and breakers has been separated from TS 3.7(1)c and has been designated as TS 3.7(1)e.
However, the frequency of this requirement was changed from annual to refueling. The licensee also proposed an administrative change to delete the word " satisfactory" from this TS section. In addition, a note has been added to the Basis Section 3.7 to specify that Generic Letter 84-15 recommendations have been incorporated into these TSs. ;
Based on its review, the staff finds the above changes to be acceptable.
- 2. 3 Technical Specification 3.1, Instrumentation and Control In order to reduce unnecessary diesel generator starts', the licensee has also proposed a change to TS 3.1. This TS refers to the requirements for surveillance testing in terms of checks, calibration, and testing of the Engineered Safety Features found in Table 3-2. These changes are as follows:
Table 3.2, Item 11 addresses several surveillance requirements for diesel generators that are currently tested as part of the testing of Engineered Safety Feature Instrumentation and Control. Additionally, other diesel generator testing requirements are specified in TS Section 3.7. Some of the diesel generator surveillance requirements of Table 3-2 Item 11 are redundant to surveillance requirements of TS Section 3.7. The licensee has proposed to delete the redundant sur-veillance requirements and move the remaining diesel generator surveillance requirements from Table 3.2 to TS Section 3.7. Speci-fically, requirements of existing Table 3.2, Item 11a will be deleted because it is redundant to the proposed revision to Section 3.7.1.a.
The requirement of Table 3-2, Item lib regarding the start of diesel generator upon a Safety Injection Signal Actuation Test has been deleted {
from the Table because this circuitry is exercised during surveillance requirements of TS 3.7(1)c. The requirement of Table 3-2, Item lle (to perform a test of the diesel generator during refueling) is also f redundant to the proposed revision to TS Section 3.7(1)c. Therefore, the requirement of Item 11c has been deleted. The requirements of (
Table 3-2, Item 11d (to test the diesel generated auto start initiating !
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circuits prior -to startup) have been moved to the proposed revised TS Section 3.7(1)b. The staff finds the above proposed changes to be consistent with Generic Letter 84-15 and acceptable.
3.0 ENVIRONMENTAL' CONSIDERATION This amendment-involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendment involves 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 published a proposed finding that the amendment involves no significant hazards consideration and there has been no public .l comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR S51.22(c)(9).
. Pursuant to 10 CFR SSI.22(b), no environmental impact statement or environmental l assessment need be prepared in connection with the issuance of the amendment.
4.0- CONCLUSION We have 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 the amendment will not be inimical to the common defense and security or to the health and safety of the public.
4 Date: September 24, 1987 Principal Contributor: 0. Chopra 1
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