ML20045C314
| ML20045C314 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 06/11/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20045C297 | List: |
| References | |
| NUDOCS 9306220348 | |
| Download: ML20045C314 (10) | |
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT N0.148 TO POSSESSION ONLY LICENSE NO. DPR-3 YANKEE ATOMIC ELECTRIC COMPANY YANKEE NUCLEAR POWER STATION (ROWE)
DOCKET NO.50-029
1.0 INTRODUCTION
By letter dated December 21, 1992, Yankee Atomic Electric Company (YAEC or the licensee) proposed to amend the facility Possession Only License No. DPR-3 and the Technical Specifications -(TS) for the Yankee Nuclear Power Station (YNPS or the plant). The changes to the License and TS were proposed to reflect the permanently defueled and shutdown status of the plant. The licensee proposes to amend the TS by retaining the previous format and content, removing the no longer needed sections related to reactor operations and retaining a remainder that constitutes the proposed Defueled Technical Specifications (DTS).
Some of the remaining DTS had to be modified to remove obsolete references to reactor operation or to reflect the defueled status.
2.0 DISCUSSION i
As noted, the plant is permanently shut down and the reactor defueled. All of the active reactor core components, namely:
fuel, control rods, shim rods and neutron source vanes have been removed to the Spent Fuel Pit (SFP or spent fuel storage pool).
The plant was shut down on October 1, 1991.
By letter dated February 27, 1992, the licensee informed the NRC of its decision to permanently cease power operation at the YNPS.
Reactor defueling had been previously completed on February 15, 1992. The NRC by letter dated August 5, 1992, modified License No. DPR-3 to a Possession Only License. The license is conditioned so that the plant cannot be operated.
3.0 EVALUATION OF PROPOSED CHANGES TO POSSESSION ONLY LICENSE NO. DPR-3 YAEC requested a change to License Condition 2.C.(3) and deletion of License Conditions 2.C.(6), 2.C.(7) and 2.C.(8), and a< sequential renumbering of the remaining license conditions. The staff has determined that a renumbering of the remaining license conditions would result in confusion as the license conditions have been referred to, in many documents, in the past.
Therefore, we are retaining the existing numbering system.
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9306220348 930611 I
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i The proposed changes to 2.C.(3), Physical Security, would revise the titles of the former Security Plan and Security Training and Qualification Plan to Defueled Security Plan and Defueled Security Training and Qualification Plan.
The staff concludes that the new titles properly reflect the changes to these plans as approved in the NRC letter of November 24, 1992.
Therefore, the i
title changes in License Condition 2.C.(3) are acceptable.
License Condition 2.C.(6), Storage of Spent Fuel, restricted the SFP storage l
capacity to 391 fuel assemblies; pending NRC evaluation of the YAEC fuel pit seismic analysis. By letter dated March 30, 1984, the staff issued a Safety Evaluation that resolved the seismic issue. The license condition was written such that our 1984 letter automatically lifted the restriction. Although the license condition then became obsolete, it remained in the license. Storage capacity would now be limited by the new DTS 5.2.3 - FUEL STORAGE-CAPACITY, at 540 fuel assemblies, current number stored in the SFP plus an allowance for bundle make-up. Spent fuel generated at other reactors could not be stored at YNPS without a future license amendment requesting an increase in the storage capacity.
Based on the above, the staff concludes that deletion of obsolete License Conditior '.C.(6) is appropriate.
License Condition 2.C.(7) required the licensee to implement a leakage reduction program outside containment in systems that could contain highly radioactive fluids during and after a reactor transient or accident.
Since the reactor is permanently shut down, this program is no longer needed.
Therefore, the staff concludes that deletion of License Condition 2.C.(7) is appropriate.
License Condition 2.C.(8) required YAEC to develop a program to measure airborne concentrations of isotopes of radioactive iodine in vital areas, following a reactor accident.
Since the reactor is permanently shut down this capability is no longer needed.
In addition, isotopes of iodine have decayed to amounts that no longer pose a hazard. Monitoring of radioactivity over the fuel pool does remain a DTS requirement. Therefore, the staff concludes that deletion of License Condition 2.C.(8) is appropriate.
4.0 EVALUATION OF PROPOSED TECHNICAL SPECIFICATION CHANGES The current (original or old) TS consists of an index and six sections; the proposed new or DTS would consist of an index and only five sections, as old Section 2.0 - SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS was proposed for deletion.
However, the old sectional numbering system and titles will be retained. The DTS would skip from Section 1.0 to 3/4 as Section 2.0 would no longer appear. This safety evaluation will proceed in sequence, by section.
Section 1.0 - DEFINITIONS. The original section contains 32 definitions and two tables. The licensee proposed deletion of 22 of the definitions and both tables. The staff reviewed the 22 definitions proposed for deletion and verified that these definitions were no longer applicable due to the shutdown and defueled status of the plant. YAEC proposed minor changes to some of the remaining 10 definitions. The staff evaluated these 10 definitions and found the chcnges to be minor and appropriate to the current plant status.
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, i The tables proposed for deletion are TABLE 1.1 - OPERATIONAL MODES and TABLE L2 - FRE0VENCY NOTATION. Table 1.1 defines the six plant operating modes which are functions of core reactivity, thermal power and coolant temperature.
With the reactor permanently shut down this table is no longer pertinent and its deletion is proper. Table 1.2 provides abbreviations for frequency interval notations (such as M = at least every 31 days) for surveillance tables used in old TS Section 3/4. The DTS do not use such tables, as surveillance intervals are now spelled out in full in the text of each surveillance requirement. This change should serve to reduce confusion on surveillance intervals. Therefore, Table 1.2 is no longer relevant.
Based on the above considerations, the staff concludes that the revisions to Section 1.0 are acceptable.
Section 2.0 - SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS. The licensee proposed the deletion of this entire TS section. Section 2.0 refers only to the reactor core, main coolant system pressure and the' reactor protective system instrumentation. The reactor fuel has been removed and these components and systems are no longer operational nor needed as the plant is permanently shut down. Based on these considerations, tne staff concludes that the deletion of Section 2.0 of the TS is appropriate.
Section 3/4 - LIMITING CONDITIONS FOR OPERATION AND SVRVEILLANCE REOUIREMENTS.
The licensee proposed deletion of those TS limiting conditions for operation (LCOs) and 'surveillances related to reactor operations, and retention or modification of those TS still applicable to the defueled operations at the plant.
Each subsection of Section 3/4 is reviewed below:
Original subsection 3/4.0-APPLICABILITY. This original subsection -
defined the applicability of LCOs during various operating modes and the surveillance requirements that would be applicable during each operating mode.
In addition, inservice inspection requirements were provided where applicable. The DTS retains the same subsection number and uses the same format. The licensee proposed deletion of all references to operating modes in the DTS, as they are no longer pertinent. The staff reviewed the new Subsection 3/4.0 and determined that defueled operability requirements, defueled LCOs and out of service provisions are properly retained. The applicability of the remaining surveillance requirements were also properly considered including surveillance intervals and allowable extension times. Based on the above, we conclude that the deletions to the original Subsection 3/4.0 were appropriate and that the new subsection properly provides LCOs and surveillance reflecting the defueled status of the plant. Therefore, the new Subsection 3/4.0 is acceptable.
Original Subsections 3/4.1-REACTIVITY CONTROL SYSTEMS and 3/4.2-P0WER DISTRIBUTION LIMITS.
YAEC proposes total deletion of these two old subsections.
These TS served to prevent the reactor fuel from exceeding fuel operating limits or to mitigate the effects of a reactor accident or transient.
The staff concludes that, with the reactor permanently shut down, the total deletion of these two old subsections is acceptable.
m
. Original Subsection 3/4.3-INSTRUMENTATION. This subsection provided LCOs and surveillance requirements for instrumentation, control and protective systems needed to safely operate the reactor or for post-accident monitoring and recovery. These systems are no longer needed as the plant is shut down. However, the old Specification 3/4.3.3.1-RADIATION MONITORING INSTRUMENTATION, contains requirements for SFP area radiation monitors; this required specification is now provided in the renamed DTS Subsection 3/4.3-SPENT FUEL STORAGE AREA RADIATION MONITORS. The LCOs and surveilances of this new section remain unchanged. The staff found the new subsection 3/4.3 to be acceptable. Based on the above, we conclude that the deletions-and changes are acceptable.
Original Subsections 3/4.4-MAIN COOLANT SYSTEMS and 3/4.5-EMERGENCY CORE COOLING SYSTEM.
YAEC proposes total deletion of these two old subsections. These TS served to prevent the reactor fuel from exceeding fuel operating limits or to mitigate the effects of a reactor accident or transient. The staff concludes that, with the reactor permanently shutdown, the total deletion of these two old subsections is acceptable.
Original Subsection 3/4.6-CONTAINMENT SYSTEMS. YAEC proposes the total deletion of this subsection.
It provided LCOs and surveillance requirements for the primary containment, isolation valves, containment penetrations and the combustible gas control system.
It also provided protection against loss of containment integrity and minimization of containment leakage following a reactor accident through a required periodic pressurized containment leak testing program. With the reactor shut down, these provisions are no longer needed.
Based on these considerations, the staff concludes that deletion of the original TS subsection 3/4.6 is acceptable.
Original Subsection 3/4.7-PLANT SYSTEMS. This subsection provided LCOs and surveillance requirements for safety related plant systems which included the turbine cycle, steam generator pressure / temperature limits, snubbers and Control Room emergency air cleaning. These components are required only for reactor operation. Control Room habitability was required during plant operations and an Emergency Air Cleaning System was provided to protect the Control Room staff during a reactor design basis accident. With the current plant status, Control Room habitability could be lost for extended periods of time without affecting safe operation of the SFP. This is discussed below in subsection 3/4.8. Old subsection 3/4.7 also contains specification 3/4.7.6-SEALED SOURCE CONTAMINATION.
With the exception of the portion of the old 3/4.7.6 dealing with startup sources, this subsection is renumbered as Subsection 3/4.5 and included in the DTS. The staff found the new subsection 3/4.5 to be acceptable.
The portions of old TS 3/4.7 related to the turbine cycle, steam generators, Control Room habitability and snubbers are no longer needed due to the permanent plant shutdown.
Based on the above, we conclude that the deletions and changes are acceptable.
y Original Subsection 3/4.8-ELECTRICAL POWER SYSTEMS. YAEC proposed total deletion of this subsection.
It provided LCOs and surveillance requirements for AC electrical power sources, on-site power distribution systems and electrical system operability during reactor operating modes 1 through 6.
With the reactor shut down this operability requirement is no longer needed. However, the staff considered the need for electrical power or alternate power sources in order to maintain SFP cooling and pool level. The staff determined that if the normal electrical power systems were to become inoperable, sufficient diverse means are available to maintain SFP cooling and water level. These include an available gravity flow source of make up water and various non-electrically driven pumps that could supply make up water to the SFP. The licensee, in addition, has committed to maintain a diesel generator in operation as a "non-nuclear safety" component which could also supply AC power to the normal pump system and maintain cooling and level. Therefore, the staff concludes that adequate alternate power sources are available to maintain pool cooling and level. The rate of heat up and subsequent pool water evaporation is sufficiently slow, as demonstrated by the licensee, so that it would take at least three weeks before pool levels would fall enough to become a problem should normal power and every alternate source become unavailable.
Such a scenario is highly improbable.
Based on these considerations the staff concludes that the deletion of old TS subsection 3/4.8 is acceptable.
Original Subsection 3/4.9-REFUELING OPERATIONS. This subsection provided LCOs and surveillance requirements to ensure safety of the fuel in the reactor vessel during refueling operations.
In addition, activities such as fuel handling outside of containment and maintenance of containment integrity during fuel handling are covered by old TS 3/4.9. The licensee requested deletion of those portions of subsection 3/4.9 that address issues associated with fuel in the reactor vessel. These are 3/4.9.1 through 3/4.9.6 inclusive, 3/4.9.8 through 3/4.9.10 inclusive and 3/4.9.12. The staff evaluated the deletion of these ten subsections of old specification 3/4.9 and found that all but 3/4.9.12 dealt with protection of fuel in the reactor vessel. With the reactor permanently defueled, these TS subsections are no longer needed. TS subsection 3/4.9.12 provides LCOs and surveillance for the SFP building exhaust ventilation shutdown system and the building exit doors. The dose evaluation for a fuel handling accident in the Spent Fuel Building does not take credit for the operability of the exhaust system or the exit doors; therefore, subsection 3/4.9.12 is no longer needed. One remaining old specification, 3/4.9.7-CRANE TRAVEL - SPENT FUEL PIT, is retained as new subsection 3/4.2-CRANE TRAVEL. SPENT FUEL PIT. The other remaining old specification, 3/4.9.11-SPENT FUEL PIT WATER LEVEL, is retained as new subsection 3/4.1-SPENT FUEL PIT WATER LEVEL. The staff reviewed the new subsections 3/4.1 and 3/4.2 and noted only minor changes from the old TS. The most significant change dealt with the age of discharged spent fuel, which is no longer pertinent as there will no longer be any fuel moved to the SFP from the reactor. Based on the above, the staff concludes that the deletions made to the old subsection 3/4.9 properly reflect the shutdown status of the plant and are acceptable and that the new subsections 3/4.1 and 3/4.2 are also acceptable.
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Original Subsection 3/4.10-SPECIAL TEST EXCEPTIONS. The licensee requested total deletion of Subsection 3/4.10.
This original subsection provided LCOs and surveillance requirements to ensure safety of the fuel in the reactor vessel during physics testing and reduced coolant inventory operations. As the reactor is permanently defueled, this old TS is no longer pertinent.
Based on the above, the staff concludes that the total deletion of old TS 3/4.10 is acceptable.
Original Subsection 3/4.11-RADI0 ACTIVE EFFLUENTS. This original subsection provided LCOs and surveillance requirements for the liquid holdup tanks, which are temporary outdoor tanks, and the Gas Storage Tank.
It contained only two subsections: 3/4.11.1.4 and 3/4.11.2.6.
YAEC requested retention of old specification 3/4.11.1.4-LIOUID HOLD-UP TANKS as DTS 3/4.4 LIQUID HOLD-UP TANKS. This new DTS, except for minor changes, is unchanged from the original TS. The staff reviewed the new 3/4.4 and found it acceptable. The licensee requested deletion of old specification 3/4.11.2.6-GAS STORAGE TANK, as this tank was used only for the storage of radioactive gasses generated during reactor operation.
The entire waste gas system including the Gas Storage Tank has been purged and vented.
Based on the above, the staff concludes that the retention of old TS 3/4.11.1.4 as DTS 3/4.4 and the deletion of old section 3/4.11.2.6 are acceptable.
Bases to Section 3/4 of the DTS. The staff reviewed the underlying basis of each subsection of DTS Section 3/4. The DTS bases were adopted from the bases for the comparable original TS subsection except for new DTS 3/4.3.
For these adopted bases, the changes properly reflect the permanently defueled status of the plant.
For DTS 3/4.3-SPENT FUEL STORAGE AREA RADIATION MONITOR, a new basis section was prepared. This new basis section was found to be adequate.
Based on the above, the staff finds that the bases-to DTS Section 3/4 are acceptable.
Summary of Changes to TS Section 3/4. The new DTS Section 3/4 contains only five subsections, namely:
3/4.1 SPENT FUEL PIT WATER LEVEL 3/4.2 CRANE TRAVEL - SPENT FUEL PIT 3/4.3 SPENT FUEL STORAGE AREA RADIATION MONITOR 3/4.4 LIOUID HOLD-UP TANKS 3/4.5 SEALED SOURCE CONTAMINATION Based on the above reviews, the staff concludes that the new DTS Section 3/4-LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS is acceptable.
Section 5.0-DESIGN FEATURES. This section of the old TS provided physical site data in the form of maps and a site plot plan.
In addition, key design features of the reactor core, containment, main (primary) coolant system, and new and spent fuel storage were specified. YAEC proposed deletion of those portions of Section 5.0 that related only to reactor operations. The remainder becomes the new DTS Section 5.0, which retains needed site data, key dcsign features of spent fuel storage, and requirements for avoidance of spent
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7, fuel criticality, SFP drainage and limits on SFP capacity. The allowed storage capacity has been reduced to 540 positions, which slightly exceeds the 533 spent fuel assemblies that are currently in the SFP.
The staff verified that the portions of the old section 5.0 relating to the reactor core, main coolant system, new fuel storage and containment have been properly deleted. The staff reviewed the new Section 5.0 and determined that it properly reflects the permanently defueled status of the plant.
Based on the above, the staff concludes that the new DTS Section 5.0-DESIGN FEATURES is acceptable.
Section 6.0-ADMINISTRATIVE CONTROLS.
YAEC proposed deletion of those portions of old Section 6.0 that related to reactor operations and retained those portions still relevant to the current plant status. The new DTS Section 6.0, like the old version, defines: plant staff responsibilities, qualifications and training; facility organization, shift crew composition, safety review committees, reporting, plant procedures programs and radiation protection programs. The following review evaluates the conversion of the old subsections into the new DTS as follows:
Old Subsection 6.1-RESPONSIBILITY. This subsection was unchanged, retained its old number and was directly transferred from the old TS to the DTS and is therefore acceptable.
Old Subsection 6.2-0RGANIZATION. This subsection retains the same number and title in the DTS.
References to " refueling" and " extended shutdown periods" are deleted as they are no longer appropriate. Subsection 6.2.2.g(4) is renumbered as 6.2.2.f(4) to close a gap in TS numbering caused by a previous license amendment. The staff finds these changes acceptable.
Old Subsec:.on 6.3-FACILITY STAFF OUALIFICATIONS.
This subsection was unchanged, retained its old number and was directly transferred from the old TS to the DTS and is therefore acceptable.
Old Subsection 6.4-TRAINING. This subsection retains the same number and title in the DTS. The old TS covered only the training of the Certified Fuel Handlers. The proposed DTS version, in addition, also adds the training requirements for the balance of the plant staff. The staff finds this expansion of training at YNPS to be acceptable.
Old Subsection 6.5-REVIEW AND AUDIT.
This subsection retains the same number and title in the DTS. The proposed DTS clarifies the role of the Plant Operations. Review Committee in that they will now review "all" changes to the 1S rather than the previous wording of reviewing
" proposed" changes to the TS. The titles of the Security Plan and Emergency Plan, where they appear in this DTS subsection, are properly changed to Defueled Security Plan and Defueled Emergency Plan. Certain disciplines related only to reactor operations are removed from the composition of the Nuclear Safety Audit and Review Committee, thus reducing the size of the committee. The title, Manager of Operations, is
,e
,. made uniform throughout the subsection replacing a variety of executive titles that were previously used. The entire specification 6.5.3, which provided for an independent fire protection inspection and audit every 12 months or 36 months, using varying levels of expertise, is proposed for deletion. The purpose of these inspections and audits was to ensure that a fire could not cause core damage. With the reactor permanently defueled, these inspections and audits are no longer required. Annual audits of the Fire Protection Program for the SFP and the Spent Fuel Building will be controlled by existing procedures. These procedures are inspectable and enforceable by the NRC.
Based on the above, the staff finds the clarifications, changes and deletions to old subsection 6.5 thus forming a new DTS subsection 6.5 to be acceptable.
Old Subsection 6.6-REPORTABLE EVENT ACTION. This subsection was unchanged, retained its old number and was directly transferred from the old TS to the DTS and is therefore acceptable.
Old Subsection 6.7-SAFETY LIMIT VIOLATION. The licensee proposed a total deletion of this subsection.
Its function was to provide the necessary action to be taken if a safety limit in old TS Section 2.0-SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS was violated. The staff approved deletion of old section 2.0 elsewhere in this Safety Evaluation. As deletion of old TS section 2.0 was found acceptable by the staff, deletion of subsection 6.7 is also acceptable, as it is no longer pertinent.
Old Subsection 6.8-PROCEDURES AND PROGRAMS.
This subsection was unchanged, renumbered as DTS 6.7 and was directly transferred from the original TS to the DTS and is therefore acceptab b.
DTS 6.7 governs the use of, and changes to procedures including spent fuel pool water chemistry monitoring under plant procedure AP-9001,
" Primary Chemistry Test Frequency and Specifications." There are seven pool water chemistry parameters in the program:
pH, conductivity, chlorides, florides, tritium, gamma isotopes and boron. The pH is monitored once a week and the remainder on a twice a month frequency.
A visual inspection of water clarity is also performed.
This is the same program that was in effect during plant operations. Any future changes to this procedure would be performed under the requirements of 10 CFR 50.59 and DTS 6.7.
In addition, any such changes are inspectable by the NRC.
Based on the above, we conclude that the spent fuel pool water chemistry program remains acceptable.
Old Subsection 6.9-REPORTING RE0VIREMENTS This subsection was renumbered as DTS 6.8 but retains the same title.
YAEC proposed the deletion of those portions of old subsection 6.9 referring to Startup Reports, PORV, primary coolant specific activity, Core Operating Limits Report and other features needed to maintain primary system operability or power operations. The staff reviewed the proposed deletions and the remaining content of new DTS subsection 6.8 and found the new subsection acceptable.
of v o. Old Subsection 6.10-RECORD RETENTION. This subsection was renumbcred as DTS 6.9 with the only change being a change in wording from " Final Hazards Summary Report" to "FSAR" to reflect current terminology. The staff finds the renumbering and terminology changes acceptable.
Old Subsection 6.ll-RADIATION PROTECTION PROGRAM. This subsection was unchanged, renumbered as DTS 6.10 and was directly transferred from the old TS to the DTS and is therefore acceptable.
Old Subsection 6.12-HIGH RADIATION AREA. This subsection was renumbered as DTS 6.11 with the only change being a change in wording from " Health Physics" to " Radiation Protection" to reflect current terminology. The staff finds the renumbering and terminology changes acceptable.
Old Subsection 6.13-LNVIRONMENTAL OVALIFICATION. The licensee proposed total deletion of this subsection.
It contained otsolete references to the implementation of an environmental qualificatior program for safety related electrical equipment no longer needed at YNPS and referred to licensee actions that had to be implemented in 1980 and 1982. The staff finds the deletion of old subsection 6.13 acceptable.
Old Subsection 6.14-PROCESS CONTROL PROGRAM. This subsection was unchanged, renumbered as DTS 6.12 and was directly transferred from the old TS to the DTS and is therefore acceptable.
Old Subsection 6.15-0FF-SITE DOSE CALCULATION MANUAL. This subsection was unchanged,- renumbered as DTS 6.13 and was directly transferred from the old TS to the DTS and is therefore acceptable.
Based on the above reviews, the staff concludes that the new DTS Section 6.0-ADMINISTRATIVE CONTROLS is acceptable.
5.0 STATE CONSULTATION
In accordance with Commission regulations, the Commonwealth of Massac >usetts-State official was notified of the proposed issuance of the amendment. The State official had no comments.
6.0 ENVIRONMENTAL CONSIDERATION
The amendment changes requirements with respect to installation or use of facility components 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 (58 FR 5436). 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
m, statement or environmental assessment need be prepared in connection with the issuance of the amendment.
7.0 CONCLUSION
S 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 Commission 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: Morton B. Fairtile Date: June 11, 1993 p
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