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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20211N5531999-09-0808 September 1999 Safety Evaluation Supporting Amend 121 to License NPF-57 ML20216D8331999-07-26026 July 1999 Safety Evaluation Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given HCGS Design,Operation & History ML20210F3331999-07-22022 July 1999 Safety Evaluation Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3.Finds That Proposed Alternative for RR-B3 Provides Acceptable Level of Quality & Safety & Authorizes Alternative Pursuant to 10CFR50.55a(a)(3)(i) ML20206Q4731999-05-14014 May 1999 SER Accepting Response to GL 97-05, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant ML20206C8481999-04-22022 April 1999 SER Authorizing Pse&G Proposed Relief Requests Associated with Changes Made to Repair Plan for Core Spray Nozzle Weld N5B Pursuant to 10CFR50.55a(a)(3)(i) ML20205G6051999-03-19019 March 1999 SER Accepting Relief Request Re Acme Code Case N-567, Alternate Requirements for Class 1,2 & 3 Replacement Components,Section Xi,Div 1 ML20205F8911999-03-18018 March 1999 Safety Evaluation Authorizing Licensee Requests for Second 10-year Interval for Pumps & Valves IST Program ML20247L1661998-05-0808 May 1998 Safety Evaluation Supporting Amend 111 to License NPF-57 ML20198H8121997-12-18018 December 1997 Corrected Safety Evaluation Supporting Amend 63 to License NPF-57,correcting Error Re Description of Min Core Thermal Power & Flow Conditions to Avoid Thermal Stratification ML20199C1441997-11-0606 November 1997 Safety Evaluation Supporting Amend 108 to License NPF-57 ML20199B2021997-10-31031 October 1997 Safety Evaluation Concluding That Insufficient Info Was Available for Staff to Perform Any Detailed Evaluation of Adequacy of Licensee New Strainer Design ML20198P3861997-10-31031 October 1997 Safety Evaluation Authorizing Licensee & Suppls & 1001,requesting Alternative to Perform RPV Circumferential Sheld Weld Exam Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1993 Edition ML20212C4481997-10-17017 October 1997 SER Accepting Alternative to ASME Section XI Code Requirements to Use Code N-432 & N-504-1 for Weld Overlay Repair for Hope Creek Generating Station ML20217D8341997-09-25025 September 1997 Safety Evaluation Authorizing Licensee Request for Relief RR-C2 for Plant,First 10-yr Interval Insp Program Plan ML20198F9981997-08-0404 August 1997 Safety Evaluation Accepting Proposed Changes to Rev 8 of HCGS Qap,Submitted on 970516 & 970606 by PSEG ML20133N6491996-12-24024 December 1996 Safety Evaluation Denying Amend Request Re Plant Svc Water Sys & Ultimate Heat Sink ML20134L7181996-11-12012 November 1996 Safety Evaluation Accepting Relief Request V-20 ML20128G2761996-09-26026 September 1996 SER Accepting Continuation of 18-month Test Schedule for Drywell to Suppression Chamber Vacuum Breakers ML20058G5171993-11-29029 November 1993 Safety Evaluation Supporting Amend 60 to License NPF-57 ML20058N8311990-08-13013 August 1990 Safety Evaluation Granting Relief Until Next Scheduled Outage Exceeding 30 Days & No Later than Next Scheduled Refueling Outage ML20055D3361990-06-27027 June 1990 Safety Evaluation Re Util 881128,900308 & 0417 Responses to Generic Ltr 88-11.Proposed Pressure/Temp Limits for RCS for Heatup,Cooldown,Leak Test & Criticality Acceptable & May Be Incorporated Into Plant Tech Specs,Per Reg Guide 1.99 ML20246K3361989-08-28028 August 1989 Safety Evaluation Supporting Amend 32 to License NPF-57 ML20246K5231989-08-21021 August 1989 Safety Evaluation Supporting Amend 31 to License NPF-57 ML20247D0281989-07-10010 July 1989 Safety Evaluation Supporting Amend 28 to License NPF-57 ML20244D0201989-06-0505 June 1989 Safety Evaluation Supporting Amend 26 to License NPF-57 ML20248J6731989-04-0303 April 1989 Safety Evaluation Supporting Amend 23 to License NPF-57 ML20195H6751988-11-22022 November 1988 Safety Evaluation Re Part 2 of Item 2.1 to Generic Ltr 83-28, Vendor Interface Programs - Reactor Trip Sys Components ML20151E2751988-04-11011 April 1988 SER Supporting Util Responses to Part 1,Item 2.1 of Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Events ML20148P6341988-01-19019 January 1988 Safety Evaluation Supporting Amend 14 to License NPF-57 ML20237B4611987-12-11011 December 1987 Safety Evaluation Granting Relief from Exams & Testing Requirements & Alternate Methods from First 10-yr Interval Inservice Insp Program ML20236V8151987-12-0101 December 1987 Safety Evaluation Supporting Program Existing for Identifying,Classifying & Treating Components Required for Performance of Reactor Trip Function as Safety Related. B&W Owners Group 870403 Internal Memo Also Encl ML20236U6151987-11-24024 November 1987 Safety Evaluation Supporting Amend 12 to License NPF-57 ML20236A8891987-10-14014 October 1987 Safety Evaluation Supporting Description of How Plant Alternate Rod Injection Sys,Atws Reactor Coolant Recirculation Pump Trip & Standby Liquid Control Sys Meet Requirements of ATWS Rule 10CFR50.62 ML20237L3681987-09-0101 September 1987 Safety Evaluation Supporting Amend 10 to License NPF-57 ML20206G7201987-04-0909 April 1987 Safety Evaluation Supporting Util 861125 Rev 1 to Process Control Program ML20206G4001987-04-0707 April 1987 Safety Evaluation Supporting Amend 3 to License NPF-57 ML20206R0691986-06-25025 June 1986 Safety Evaluation Supporting Util 841217 Response to Generic Ltr 83-28,Items 3.1.1,3.2.1,3.2.2 & 4.5.1 Re Required Actions Based on Generic Implications of Salem ATWS Events ML20203N2221986-06-12012 June 1986 Safety Evaluation Accepting Util Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1 ML20154S2081986-03-27027 March 1986 SER Supporting Util 860127 Request to Use Later ASME Code Editions for Design & Fabrication of Components & Supports. Proposed FSAR Changes in ASME Code Section III Requirements Acceptable ML20137R9191986-02-0404 February 1986 Safety Evaluation Accepting Applicant 850821,1004 & 17,1106 & 1209 Proposed Mods to Tests 24,28E,25,28D,3,11,16,1 & 32 of Power Ascension Test Program ML20151Z1081986-02-0303 February 1986 SER Supporting Util Response to Generic Ltr 83-28,Item 1.2 Re post-trip Review (Data & Info Capability) ML20151R2511986-01-22022 January 1986 Sser Supporting Power Ascension Test Program Acceleration. SALP Input Encl ML20137L7401986-01-22022 January 1986 SER Supporting Util 840330 Response to Generic Ltr 83-28, Items 1.1,3.1.3 & 3.2.3 Re post-trip Review (Program Description Procedure) & post-maint Testing ML20137M4001986-01-22022 January 1986 Safety Evaluation Accepting Power Ascension Program Proposed Test Mods ML20138M2421985-12-16016 December 1985 Sser Re Power Ascension Test Program Acceleration.Change Acceptable Except for Elimination of Testing at Test Condition 4.Justification for Deleting Testing at Test Condition 4 Insufficient ML20132A4481985-09-30030 September 1985 Safety Evaluation Supporting Elimination of Arbitrary Intermediate Pipe Breaks 1999-09-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217F1501999-10-12012 October 1999 Special Rept:On 990929,south Plant Vent (SPV) Range Ng Monitor Was Inoperable.Monitor Was Inoperable for More than 72 H.Caused by Electronic Noise Generated from Noise Suppression Circuit.Replaced Circuit ML20217N6531999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Hope Creek Generating Station,Unit 1.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20217M0211999-09-20020 September 1999 Part 21 Rept Re Possible Deviation of NLI Dc Power Supply Over Voltage Protection Circuit Actuation.Caused by Electrical Circuit Conditions Unique to Remote Engine Panel. Travelled to Hope Creek to Witness Startup Sequence of DG ML20211N5531999-09-0808 September 1999 Safety Evaluation Supporting Amend 121 to License NPF-57 ML20211B3781999-08-13013 August 1999 Special Rept 99-002:on 990730,NPV Radiation Monitoring Sys Was Declared Inoperable.Caused by Voltage Induced in Detector Output by Power Cable to Low Range Sample Pump. Separated Cables & Secured in Place to Prevent Recurrence ML20210U4721999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Hope Creek Generating Station,Unit 1.With ML20216D8331999-07-26026 July 1999 Safety Evaluation Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given HCGS Design,Operation & History ML20216D8721999-07-26026 July 1999 Review of Submittal in Response to USNRC GL 88-20,Suppl 4: 'Ipeees,' Fire Submittal Screening Review Technical Evaluation Rept:Hope Creek Rev 1:980518 ML20210F3331999-07-22022 July 1999 Safety Evaluation Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3.Finds That Proposed Alternative for RR-B3 Provides Acceptable Level of Quality & Safety & Authorizes Alternative Pursuant to 10CFR50.55a(a)(3)(i) ML20216D8901999-06-30030 June 1999 IPEEEs Technical Evaluation Rept High Winds,Floods & Other External Events ML20210C4731999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Hope Creek Generating Station,Unit 1.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 ML20196A1511999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Hope Creek Generating Station,Unit 1.With ML20206Q4731999-05-14014 May 1999 SER Accepting Response to GL 97-05, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant ML20206U1571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Hope Creek Generating Station,Unit 1.With ML20216D8451999-04-30030 April 1999 Rev 1, Submittal-Only Screening Review of Hope Creek Unit 1 IPEEE (Seismic Portion). Finalized April 1999 ML20206C8481999-04-22022 April 1999 SER Authorizing Pse&G Proposed Relief Requests Associated with Changes Made to Repair Plan for Core Spray Nozzle Weld N5B Pursuant to 10CFR50.55a(a)(3)(i) LR-N990157, Special Rept 99-001:on 990315, C EDG Valid Failure Occurred During Surveillance Testing.Testing Resulted in Unsuccessful Loading Attempt,Due to Failure EDG Output Breaker to Close.Faulty Card Replaced1999-04-12012 April 1999 Special Rept 99-001:on 990315, C EDG Valid Failure Occurred During Surveillance Testing.Testing Resulted in Unsuccessful Loading Attempt,Due to Failure EDG Output Breaker to Close.Faulty Card Replaced ML20205R5901999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Hope Creek Generating Station,Unit 1.With ML20205G6051999-03-19019 March 1999 SER Accepting Relief Request Re Acme Code Case N-567, Alternate Requirements for Class 1,2 & 3 Replacement Components,Section Xi,Div 1 ML20205F8911999-03-18018 March 1999 Safety Evaluation Authorizing Licensee Requests for Second 10-year Interval for Pumps & Valves IST Program ML20204F7951999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Hope Creek Generating Station,Unit 1.With ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML20202F6861999-01-26026 January 1999 Engine Sys,Inc Part 21 (10CFR21-0078) Rept Re Degradation of Synchrostat Model ESSB-4AT Speed Switches Resulting in Heat Related Damage to Power Supply Card Components.Caused by Incorrect Sized Resistor.Notification Sent to Customers ML20199E7271998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Hope Creek Generating Station,Unit 1.With ML18107A1871998-12-31031 December 1998 PSEG Annual Rept for 1998. ML18107A1881998-12-31031 December 1998 PECO 1998 Annual Rept. LR-N980580, Monthly Operating Rept for Nov 1998 for Hope Creek Generating Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Hope Creek Generating Station,Unit 1.With ML20198N4161998-11-12012 November 1998 MSIV Alternate Leakage Treatment Pathway Seismic Evaluation LR-N980544, Monthly Operating Rept for Oct 1998 for Hcgs,Unit 1. with1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Hcgs,Unit 1. with ML20155J9861998-10-31031 October 1998 Non-proprietary TR NEDO-32511, Safety Review for HCGS SRVs Tolerance Analyses LR-N980491, Monthly Operating Rept for Sept 1998 for Hope Creek Generating Station,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Hope Creek Generating Station,Unit 1.With ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils LR-N980439, Monthly Operating Rept for Aug 1998 for Hope Creek Generating Station Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Hope Creek Generating Station Unit 1.With LR-N980401, Monthly Operating Rept for July 1998 for Hope Creek Generating Station,Unit 11998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Hope Creek Generating Station,Unit 1 ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps LR-N980354, Monthly Operating Rept for June 1998 for Hope Creek Generating Station,Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Hope Creek Generating Station,Unit 1 ML20236E9491998-06-30030 June 1998 Rev 0 to non-proprietary Rept 24A5392AB, Lattice Dependent MAPLHGR Rept for Hope Creek Generating Station Reload 7 Cycle 8 ML18106A6821998-06-24024 June 1998 Revised Charting Our Future. 05000354/LER-1998-004-03, :on 980522,EDG B Declared Inoperable.Caused by Contamination W/Lubrication Oil in Delivered Fuel Oil. EDG Drained,Cleaned,Refilled & Sampled1998-06-22022 June 1998
- on 980522,EDG B Declared Inoperable.Caused by Contamination W/Lubrication Oil in Delivered Fuel Oil. EDG Drained,Cleaned,Refilled & Sampled
ML18106A6681998-06-17017 June 1998 Charting the Future. LR-N980302, Monthly Operating Rept for May 1998 for Hope Creek Generating Station,Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Hope Creek Generating Station,Unit 1 ML20248C7381998-05-22022 May 1998 Rev 0 to Safety Evaluation 98-015, Extension of Allowed Out of Service Time for B Emergency Diesel Generator ML20247L1661998-05-0808 May 1998 Safety Evaluation Supporting Amend 111 to License NPF-57 05000354/LER-1998-003-01, :on 980407,concurrent Inoperability of a & B CR Chillers Was Noted.Caused by Personnel Error. Performed IST Tests,Equipment Repairs,Training & Revised Procedures1998-05-0707 May 1998
- on 980407,concurrent Inoperability of a & B CR Chillers Was Noted.Caused by Personnel Error. Performed IST Tests,Equipment Repairs,Training & Revised Procedures
LR-N980247, Monthly Operating Rept for Apr 1998 for Hope Creek Station, Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Hope Creek Station, Unit 1 1999-09-08
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NUCLEAR REGULATORY COMMISSION
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
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RELATED TO AMENDMENT NO111TO FACILITY OPERATING LICENSE NO. NPF-57 l
PUBLIC SERVICE FI FCTRIC & GAS COMPANY I
ATLANTIC CITY Ft FCTRIC COMPANY HOPE CREEK GENERATING STATION DOCKET NO. 50-354 1
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1.0 INTRODUCTION
By letter dated December 19,1997, as supplemented March 6,1998, the Public Service Electric
& Gas Company (the licensee) submitted a request for changes to the Hope Creek Generating Station (HCGS), Environmental Protection Plan Technical Specifications (EPPTSs). The requested changes would change the wording of Section 4.2.2, " Terrestrial Ecology Monitoring,"
of the EPPTSs to include completion of the Salt Drift Monitoring Program. The March 6,1996, submittal provided clarifying information that did not change the initial proposed no significant hazards consideration determination or expand the scope of the original Federal Register notice.
2.0 EVALUATION l
The licensee has proposed changes to Section 4.2.2 of the EPPTSs that reflect the completion j
of the Salt Drift Monitoring Program. The current Environmental Protection Plan Section 4.2.2 reads as follows:
l "The applicant will implement the Salt Drift Monitoring Program to assess the impacts of cooling tower salt drift on the environment in the HCGS vicinity provided to NRC by letter dated March 28,1984 from Robert L. Mitti, Public Service Electric & Gas Co., to A. Schwencer, U.S. Nuclear Regulatory Commisson.
The monitoring program shall commence one year prior to the onset of l
commercial operation of the HCGS and inc!ude low-power testing and operational data up to three years from receipt of licelse or until such earlier time that the licensee can demonstrate that the objectives of the study have been fulfilled.
l Annual monitoring reports shall be submitted to the NRC for review.
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The licensee may make changes in the salt drift monitoring procedures withcut I
1 prior Commission approval unless the proposed change affects the program objectives described in the introduction to the Salt Drift Monitoring Program.
Changes in the procedures, for example, changes which affect sampling frequency, location, gear, or replication, shall be recorded. Records shall describe l
the changes made, the reasons for making the changes, and a statement sho'ving how continuify of the study will be affected. Any modifications or
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9805220327 980508 PDR ADOCK 05000354 p
PDR
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2-changes of the monitoring program, once initiated, shall be govemed by the need to maintain consistency with previously used procedures so that direct comparisons of data are technically valid. Such modifications or changes shall be justified and supported by adequate comparative sampling programs or studies demonstrating the comparability of j
results or which provide a basis for making adjustments that would permit direct comparisons. The annual report should describe monitoring procedures and changes in such procedures made during the report period."
The licensee proposes to replace the current text with the following statements, which describe the Salt Drift Monitoring Program final reports and terminate the licensee's commitment to study the cooling tower salt drift phenomon:
"PSE&G has completed the implementation of the Salt Drift Monitoring Program to assess the impacts of cooling tower salt drift on the environment in the HCGS l
vicinity. This study was completed by the submission of two reports: " Pre-operational Summary Report for Hope Creek Generating Station Salt Drift Monitoring Program, August 1984-December 1986" and " Operational Summary Report for Hope Creek Generating Station Salt Drift Monitoring Program, January 1987 to March 1989". The pre-operational report was submitted to the NRC on April 30,1987 (NLR-E87144) as an Appendix to the 1986 Annual Environmental Operating Report. The operational report was submitted to the NRC on October 10,1989 (NLR-N89201).
The " Operational Summary Report" contained information that fulfilled the I
requirements of a final report, and therefore will be considered the " Final Report".
This report discusses salt depositon data, native vegetation studies, comparison l
of estimated salt drift and deposition with actual data, environmental effects of salt drift and pre-and post-operational data comparison.
The study indicated that only minor, localized effects of cooling tower drift deposition are occurring. Higher deposition rates potentially attributable to the cooling tower were measured at only one location, which is on station property at a distance of 0.4 km southeast of the cooling tower. The salt deposition rate at this site is 113 mg/m / month, 2
which is well below the deposition levels that have been reported to cause vegetative 2
damage of 10,000 mg/m / year. Hope Creek Generating Station is surrounded by extensive areas of tidal salt marsh and the nearest uplands are located approximately three miles to the east, therefore no significant adverse impacts will occur as a result of l
cooling tower operation.
PSE&G has satisfied the commitments under this requirement. No further monitoring is required."
A March 28,1984 letter to Albert Schwencer, U.S. Nuclear Regulatory Commission, from Robert L. Mitti, Public Service Electric & Gas Co. delineated the requirements for the HCGS salt drift studies. The salt drift studies were required by the NRC as a condition of the HCGS construction permit in order to evaluate the effects of salt deposition from the HCGS cooling tower on the environment. The letter discussed reporting requirements for both preoperational and operational periods at HCGS. The letter also required a final report, that summarized the results of the salt drift studies for both periods. In lieu of a final report, the licensee has submitted a j
separate final report for each period. The HCGS preoperational salt drift study, performed l
f
. between August 1984 and December 1986, was submitted to NRC on April 30,1987, as an Appendix to the 1986 Annual Environmental Operating Report. The HCGS operational salt drift study, performed between January 1987 and March 1989, was submitted to NRC on October 10, 1989.
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The staff has reviewed both the preoperational and operational salt drift studies, and found that they satisfy the requirements outlined in the March 28,1984 letter.
3.0 STATE CONSULTATION
t in accordance with the Commission's regulations, the New Jersey State Official was notified of the proposed issuance of the amendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
1 The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC 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 issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (63 FR 4321). Accordingly, the amendment meets 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 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 will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: W. Gleaves Date: May 8, 1998 l
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