Similar Documents at Maine Yankee |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N8371999-10-13013 October 1999 Forwards Summary of Changes Made to Maine Yankee Defueled Security Plan,Iaw 10CFR50.54(p)(2).Without Encl ML20217J0241999-10-13013 October 1999 Documents 991005 Telcon Between NRC & Util to Address All of Areas Identified in Reg Guide 1.179 & NUREG-1700 Re Final Survey Plan Except for One Area ML20212F4321999-09-24024 September 1999 Responds to 990921 e-mail to E Poteat,Requesting Waiver of Late Charges of Listed Amount for Annual Fee Invoice AR0431-99.Request Denied Because 10CFR15.37 Does Not Provide for Waiver Based on Info Provided in e-mail ML20212M2431999-09-22022 September 1999 Expresses Concern Re NRC Consideration of Adoption of Policy Based on Requests from Licensees,To Allow as Part of Decommissioning of Nuclear Power Plants & Demolition of Onsite Structures at Reactor Plant Sites ML20212E4611999-09-20020 September 1999 Responds to Concerning Possible Involvement in Weekly Telephone Calls NRC Staff Has with Maine Yankee Staff ML20212F1361999-09-20020 September 1999 Confirms That NMSS Has Received 990916 Submittal & Will Be Included as Attachment to Commission Paper Along with State of Maine Submittal ML20212F2521999-09-20020 September 1999 Confirms That NMSS Has Received 990916 Submittal & Will Be Included as Attachment to Commission Paper Along with State of Maine Submittal ML20212B7011999-09-14014 September 1999 Submits Comments & Raises Questions Re Generation of White Paper for Commission to Decide Merits of Rubberization ML20212A5911999-09-0808 September 1999 Responds to 990816 e-mail & 990901 Telcon with Respect to Comments Re Decommissioning of Maine Yankee Site.Concerns Raised with Respect to Status of Fuel at Maine Yankee Have Been Raised in Previous Ltrs to Us NRC ML20211M9371999-08-30030 August 1999 Addresses Two Issues Raised in s to Senator Collins & Governor a King That Relate to Construction of ISFSI at Maine Yankee ML20212B2181999-08-30030 August 1999 Responds to Re 990707 Message from N Allen Re Transportation Incident Involving Shipment from Maine Yankee Nuclear Power Plant ML20212E4841999-08-27027 August 1999 Informs That at 990429 Meeting of Myap Community Advisory Panel,R Shadis,Asked If Given Lack of Resident Inspectors & Limited NRC-license Review Correspondence,If Shadis Could Take Part in Weekly NRC Conference Calls with Licensee ML20216F1891999-08-26026 August 1999 Forwards Copies of Maine Yankee & Yankee Rowe Refs Listed, Supporting Industry Position That Branch Technical Position Asb 9-2 Methodology over-estimates Spent Fuel Decay Heat ML20211C0591999-08-19019 August 1999 Forwards Addl Justification for Proprietary Request Re 990809 Submittal Info on Maine Yankee License Termination Plan ML20212A5981999-08-16016 August 1999 Expresses Appreciation for with Respect to e-mail Message Re Site Release Criteria Standards Can Never Be Verified Using Existing Database ML20211D7041999-08-0909 August 1999 Forwards Rev 17 of Maine Yankee Defueled Safety Analysis Rept (Dsar), Per 10CFR50.71 & 10CFR50.4 ML20217M6501999-08-0909 August 1999 Responds to 990719 E-mail Re Cleanup Stds at MYAPC Station & Verification of Meeting Cleanup Stds.Informs That NRC Criteria for Licensing NPPs Contained in 10CFR50 & That 10CFR50.82 Addresses Requirements for License Termination ML20210Q7201999-08-0909 August 1999 Forwards non-proprietary & Proprietary Draft Documents Re Info on Myap License Termination Plan & Diskette.Proprietary Info & Diskette Withheld ML20212B2271999-08-0606 August 1999 Discusses Concerns Re Recent Incindent Involving Transport of Nuclear Matl from Maine Yankee ML20210M8171999-08-0505 August 1999 Forwards Draft License Termination Plan/Amend Plan for Maine Yankee Atomic Power Co, to Enhance Dialogue Between Various Stakeholders & Provide Springboard for Clarifying Mutual Expectations.With Three Oversize Drawings ML20210L2211999-08-0202 August 1999 Forwards Two Copies of Objectives & Sequence of Events for Maine Yankee Emergency Preparedness Exercise for 990922. Without Encl ML20210G3751999-07-28028 July 1999 Ack Receipt of June 30th Ltr That Responded to EDO Backfit Appeal Determination Re Bdba in Sfps.Staff Completed All Actions Associated with Backfit Appeal & Awaiting for New Info for Consideration Prior to Taking Addl Action ML20216D4311999-07-19019 July 1999 Informs That Util Intends to Construct ISFSI Located on Owner Controlled Property Currently Part of Maine Yankee Reactor Site ML20217M6571999-07-19019 July 1999 Expresses Concern Re Verification of Cleanup Stds at Maine Yankee Atomic Power Co Power Station ML20210C6271999-07-15015 July 1999 Forwards Draft Site Characterization Summary in Support of 10CFR50 License Termination & Copy of Latest Decommissioning Schedule with Milestones Identified.Info Submitted Per License Termination Plan ML20196K4751999-07-0606 July 1999 Informs That Confirmatory Orders ,830314,840614 & 960103 Have Been Rescinded.Staff Determined That Due to Permanently Shutdown & Defueled Status of Facility,Orders No Longer Necessary for Safe Operation & Maint.Se Encl ML20210G3981999-06-30030 June 1999 Discusses Review of Ltr Re Maine Yankee Backfit Appeal with Respect to Emergency Plan Exemptions for Decommissioning Plants ML20209C7731999-06-30030 June 1999 Responds to EDO Backfit Appeal Determination Re Emergency Plan Exemptions for Decommissioning Plants ML20209B4611999-06-29029 June 1999 Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Plant Is Y2K Ready.Contingency Plans Developed to Mitigate Potential Impact of non-plant Y2K-induced Events ML20196D9191999-06-22022 June 1999 Informs That NRC Has Completed Review of Issues Raised in of Appeal to NRC Edo.Submits List Summarizing Actions Taken Since ML20195H1741999-06-15015 June 1999 Forwards Original & Copy of Request for Approval of Certain Indirect & Direct Transfer of License & Ownership Interests of Montaup Electric Co (Montaup) with Respect to Nuclear Facilities Described as Listed ML20207H3371999-06-11011 June 1999 Expresses Appreciation for Participation at 990413 Reactor Decommissioning Public Meeting & Responds to Concern Re Absense of Timeliness on Part of NRC Replying to Letters ML20195G9411999-06-10010 June 1999 Informs That Maine Yankee Considers Backfit Claim & Appeal Request of 980716 & 990316,to Be Acceptably Resolved Based on Staff 990518 Response ML20195F7531999-06-0707 June 1999 Forwards Copy of Insurance Endorsement Dtd 990429,reflecting Change in Nuclear Energy Liability Insurance,Iaw Requirements of 10CFR140.15(e) ML20195F6721999-06-0707 June 1999 Forwards Insp Rept 50-309/99-01 on 990214-0513.No Violations Noted.Operations & Radiological Protection Programs, Including Radioactive Liquid & Gaseous Effluent Control Programs,Were Inspected During Insp ML20206U9711999-05-18018 May 1999 Responds to & Addl Info Re Appeal of NRC Determination Re Claim of Backfit Concerning Permanently Shutdown Reactor Security Plan ML20207A2851999-05-14014 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Mgt Created.Organization Chart Encl ML20206H1391999-05-0505 May 1999 Forwards Amend 164 to License DPR-36 & Safety Evaluation. Amend Consists of Changes to License in Response to 970930 Application ML20206H2311999-05-0404 May 1999 Responds to to Chairman Jackson.Forwards Copy of Recent Staff Response to Petition Submitted on Behalf of Ucs Re Fuel Cladding at Operational Reactors ML20206G5561999-05-0303 May 1999 Forwards Amend 163 to License DPR-36 & Safety Evaluation. Amend Revises Liquid & Gaseous Release Rate Limits to Reflect Revs to 10CFR20, Stds for Protection Against Radiation ML20206J2801999-04-30030 April 1999 Forwards 1998 Annual Financial Repts for CT Light & Power Co,Western Ma Electric Co,Public Svc Co of Nh,North Atlantic Energy Corp,Northeast Nuclear Energy Co & North Atlantic Energy Svc Corp,License Holders ML20206D7191999-04-29029 April 1999 Forwards Listed Radiological Repts for 1998 Submitted IAW Relevant Portions of License DPR-36 & ODCM ML20206E2911999-04-28028 April 1999 Requests NRC Review of ISFSI Licensing Submittals,As Scheduled & ISFSI Approval for Operation by Dec 2000.Util Will Support Any NRC RAI on Expedited Basis.Licensing Milestone Schedule,Encl ML20206E3101999-04-28028 April 1999 Forwards Data Diskette Containing 1998 Individual Monitoring NRC Form 5 Rept,Per 10CFR20.2206(b).Without Diskette ML20206A5521999-04-23023 April 1999 Forwards Environ Assessment & Finding of No Significant Impact Related to Util Application Dtd 980714,for Amend to License DPR-36 to Revise App a TSs to Change Liquid & Gaseous Release Rate Limits to Reflect Revs Made to 10CFR20 ML20206A6871999-04-22022 April 1999 Informs of Completion of Review of Re Nepco in Capacity as Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee Atomic Power Co ML20205N6211999-04-0707 April 1999 Ack Receipt of Which Appealed NRC Staff Determination That Util Had Not Raised Valid Backfit Claim in to Nrc.Staff Began Process of Convening Backfit Review Panel to Evaluate Appeal ML20205K6541999-04-0707 April 1999 Submits Nuclear Property Insurance Coverage Presently in Force to Protect Maine Yankee at Wiscasset,Me ML20206H2401999-03-30030 March 1999 Informs That Myap Recently Revealed That Approx 20% of Fuel Assemblies Now in SFP Are non-std & Require Special Handling & Dry Cask Packaging.Info Confirms Growing Evidence of Periodic Loss of Radiological Control ML20206A6951999-03-29029 March 1999 Request Confirmation That No NRC Action or Approval,Required Relative to Proposed Change in Upstream Economic Ownership of New England Power Co,Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee 1999-09-08
[Table view] Category:NRC TO UTILITY
MONTHYEARIR 05000309/19900181990-11-0101 November 1990 Discusses Enforcement Conference Rept 50-309/90-18 on 901018 Re fitness-for-duty Related Event.Viewgraphs Encl ML20058D3411990-10-30030 October 1990 Forwards Safety Insp Rept 50-309/90-20 on 900924-27.No Violations Noted ML20062C0731990-10-22022 October 1990 Forwards Safety Insp Rept 50-309/90-21 on 901010-11.No Violations Noted ML20058B4941990-10-18018 October 1990 Forwards Exam Rept 50-309/90-16OL on 900827-31.All Individuals Passed All Portions of Exams ML20062A2281990-10-15015 October 1990 Advises That Util 900925 Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-08,Item 2.2 Part 2, 'Vendor Interface for Safety-Related Components,' Acceptable ML20062B7091990-10-12012 October 1990 Extends Invitation to Participate in 910220 Symposium & Workshop in King of Prussia,Pa Re Engineering Role in Plant Support ML20062A3671990-10-0909 October 1990 Forwards Insp Rept 50-309/90-17 on 900731-0918.Violations of Regulatory Requirements Identified But Not Issued IR 05000309/19900011990-10-0505 October 1990 Discusses Requalification Program Evaluation Rept 50-309/90-01 (OL-RO) on 900312-15 & Forwards Notice of Violation ML20059N4631990-10-0202 October 1990 Ack Receipt of Informing NRC of Corrective & Preventive Actions Taken in Response to Violations Noted in Insp Rept 50-309/90-11 ML20059N0971990-09-26026 September 1990 Forwards Audit Trip Rept Re NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification for Plant ML20059K9911990-09-20020 September 1990 Forwards Safety Evaluation Accepting Methodology Re Statistical Combination of Uncertainties for RPS Setpoints ML20059L4081990-09-14014 September 1990 Informs That 900827 Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance, Acceptable.Nrc Considers TAC 75679 Closed ML20059H5781990-09-12012 September 1990 Forwards Safety Evaluation Re Facility Response to Station Blackout Rule.Requests Revised Response to Listed Items That Require Resolution,Within 60 Days of Ltr Date ML20059H0601990-09-0707 September 1990 Discusses Unescorted Access to Licensee Facilities & fitness-for-duty Program,Per .Nrc Regulations Do Not Prohibit Licensee from Accepting Access Authorization Program of Another Licensee,Contractor or Vendor ML20059C9831990-08-30030 August 1990 Forwards Amend 117 to License DPR-36 & Safety Evaluation. Amend Modifies Tech Spec 3.14, Primary Sys Leakage, by Deleting Current Limit of 1.0 Gpm from All Steam Generator Tubes ML20059B7181990-08-23023 August 1990 Discusses NRC Understanding of Licensee Informing of Completion of Component Cooling Water Heat Balance to Support Operation at 2,700 Mwt.Updated Heat Load Analysis Expected to Be Retained Onsite W/Design Basis Documents ML20059E2501990-08-23023 August 1990 Forwards Insp Rept 50-309/90-13 on 900620-0731.Weaknesses Noted in Procedure Quality & Adherence ML20059B9831990-08-13013 August 1990 Forwards Evaluation of Topical Rept Cen 387-P Re Pressurizer Surge Line Flow Stratification,Per NRC Bulletin 88-011,Item 1.b.Adequate Basis Not Provided to Conclude That Pressurizer Surge Line Meets All Appropriate ASME Code Limits ML20058N0501990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Encourages Initiation of Initiative Similar to Region V Establishment of Engineering Managers Forum to Share Experiences ML20056A9401990-08-0303 August 1990 Forwards Insp Rept 50-309/90-08 on 900507-11.No Violations Noted IR 05000309/19890821990-07-30030 July 1990 Advises That Util Actions to Address NRC Bulletin 88-010 Re Nonconforming molded-case Circuit Breakers Complete,Per Insp Rept 50-309/89-82 ML20055G5971990-07-19019 July 1990 Forwards Insp Rept 50-309/90-10 on 900516-0619 & Notice of Violation.Util Actions to Prevent Recurrence of Similar Personnel & Procedural Errors Be Formally Submitted in Response to Encl Notice of Violation ML20055G3211990-07-16016 July 1990 Accepts Util 900702 Response to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardeness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor/Darling Model S350W Swing Check Valves or Valves of Similar Design ML20055G7381990-07-13013 July 1990 Forwards Enforcement Conference Rept 50-309/90-11 on 900627 & Notice of Violation.Disagrees W/View Re Licensee Identified Violations.Weaknesses in Planning,Oversight & Controls of Radiological Work Resulted in Violations ML20055E6501990-07-0909 July 1990 Discusses Generic Implications & Resolutions of Control Element Assembly (CEA) Failures at Maine Yankee.Waterford Unit 3 Does Not Have Old Style CEAs Installed in Reactor Core & Does Not Plan to Use Any in Future ML20055F1471990-07-0606 July 1990 Discusses Generic Implications & Resolution of Control Element Assemblies Failure at Plant.Requests Description of Analyses Planned & Schedule for Completion of Analysis within 60 Days of Ltr Receipt ML20055G1581990-07-0505 July 1990 Advises That Changes to Plant Physical Security Plan, Acceptable,Per 890817,900116 & 0612 Ltrs ML20055C8801990-06-14014 June 1990 Forwards Radiological Controls Insp Rept 50-309/90-09 on 900507-11.No Violations Noted.Observations by Inspector Indicated Improvement in Radiological Planning & Control of Outage Work Activities ML20059M9201990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C2891990-02-20020 February 1990 Forwards Safety Evaluation Accepting Util Assessment of Asymmetric LOCA Load Problems.Reviews Included Evaluation of plant-specific Cavity Pressure,Subcooled Blowdown & Structural Analyses ML20248D3771989-09-27027 September 1989 Forwards Amend 10 to Indemnity Agreement B-51,reflecting Changes to 10CFR140,effective 890701 IR 05000309/19890111989-09-19019 September 1989 Forwards Insp Rept 50-309/89-11 on 890801-31.Instances That Need Mgt or Supervisory Attention Noted ML20247M4601989-09-18018 September 1989 Forwards Radiological Controls Insp Rept 50-309/89-15 on 890821-24.No Violations Noted.Continuing Problems Noted Re Radiation Protection Deficiency Corrective Action Program ML20247G1121989-09-0909 September 1989 Requests Detailed Design Analysis Supporting Util 890331 Proposed Design Enhancements Involving Offsite Automatic Bus Transfer Sys & Replacement of Existing X-14 Transformer W/Larger,More Capable Transformer ML20247L1471989-09-0808 September 1989 Advises That Licensee Prepare Request for Disposal of Slightly Contaminated Chemical Cleaning Solution as Licensee Prepared 881102 Request Re Technical Content, Justification & Format & Modify or Resubmit Application ML20247J7561989-09-0707 September 1989 Requests Addl Info for Closeout of IE Bulletin 79-15, Including Type & Application of Listed Pumps,Drawings, Sectional Assemblies & Parts List of Subj Pumps,Applicable P&Ids of Subj Pumps & Testing Requirements & Procedures ML20246P0701989-08-31031 August 1989 Approves Inplace Disposal of Residual Contaminated Soils at Plant Under 10CFR20.302(a),per Util .No License Amend & Environ Assessment Necessary ML20246F8591989-08-22022 August 1989 Forwards Safety Insp Rept 50-309/89-14 on 890724-28.No Violations Noted ML20246E7671989-08-21021 August 1989 Forwards Resident Insp Rept 50-309/89-13 on 890622-0731.Well Developed Controls Identified in Power Upgrade Program. Inconsistencies Noted in Implementation of Radioactively Hot Particle Controls ML20246B2691989-08-11011 August 1989 Ack Receipt of Util Informing NRC of Need for Addl Time to Prepare Response to Notice of Violation Re Insp Rept 50-309/88-20.Addl Time Granted ML20248C5401989-08-0303 August 1989 Forwards Request for Addl Info in Support of Util 890518 Response to ATWS Rule 10CFR50.62, Requirements for Reduction of Risk from ATWS Events for Light-Water-Cooled Nuclear Power Plants, Per 890628 Telcon ML20247Q7071989-07-28028 July 1989 Forwards Insp Rept 50-309/89-09 on 890518-0621.No Violations Noted ML20247H6631989-07-19019 July 1989 Forwards Safety Insp Rept 50-309/89-10 on 890612-16.No Violations Noted ML20247D0771989-07-14014 July 1989 Provides Emergency Exercise Objective & Scenario Guidelines for Emergency Exercise Schedule for Wk of 891106.List Schedule That Should Be Used for All Exercises ML20246L4201989-07-14014 July 1989 Forwards Revised Pages 3.10-16 & 3.10-17 to Amend 107 to License DPR-36,correcting Typos ML20246P5191989-07-12012 July 1989 Forwards Requalification Exam Rept 50-309/89-05OL Conducted on 890515-18.Program Rating:Satisfactory ML20246F6171989-07-10010 July 1989 Forwards Amend 113 to License DPR-36 & Safety Evaluation. Amend Modifies Tech Specs to Reflect Operating Limits for Cycle 11 Operation IR 05000309/19880231989-06-28028 June 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-309/88-23 IR 05000309/19890071989-06-26026 June 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-309/89-07 ML20245A2381989-06-14014 June 1989 Advises That Fulfills Licensee Requirement in Responding to NRC Bulletin 88-004, Potential Safety-Related Pump Loss 1990-09-07
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20212F4321999-09-24024 September 1999 Responds to 990921 e-mail to E Poteat,Requesting Waiver of Late Charges of Listed Amount for Annual Fee Invoice AR0431-99.Request Denied Because 10CFR15.37 Does Not Provide for Waiver Based on Info Provided in e-mail ML20212E4611999-09-20020 September 1999 Responds to Concerning Possible Involvement in Weekly Telephone Calls NRC Staff Has with Maine Yankee Staff ML20212F1361999-09-20020 September 1999 Confirms That NMSS Has Received 990916 Submittal & Will Be Included as Attachment to Commission Paper Along with State of Maine Submittal ML20212F2521999-09-20020 September 1999 Confirms That NMSS Has Received 990916 Submittal & Will Be Included as Attachment to Commission Paper Along with State of Maine Submittal ML20212A5911999-09-0808 September 1999 Responds to 990816 e-mail & 990901 Telcon with Respect to Comments Re Decommissioning of Maine Yankee Site.Concerns Raised with Respect to Status of Fuel at Maine Yankee Have Been Raised in Previous Ltrs to Us NRC ML20212B2181999-08-30030 August 1999 Responds to Re 990707 Message from N Allen Re Transportation Incident Involving Shipment from Maine Yankee Nuclear Power Plant ML20211M9371999-08-30030 August 1999 Addresses Two Issues Raised in s to Senator Collins & Governor a King That Relate to Construction of ISFSI at Maine Yankee ML20217M6501999-08-0909 August 1999 Responds to 990719 E-mail Re Cleanup Stds at MYAPC Station & Verification of Meeting Cleanup Stds.Informs That NRC Criteria for Licensing NPPs Contained in 10CFR50 & That 10CFR50.82 Addresses Requirements for License Termination ML20210G3751999-07-28028 July 1999 Ack Receipt of June 30th Ltr That Responded to EDO Backfit Appeal Determination Re Bdba in Sfps.Staff Completed All Actions Associated with Backfit Appeal & Awaiting for New Info for Consideration Prior to Taking Addl Action ML20196K4751999-07-0606 July 1999 Informs That Confirmatory Orders ,830314,840614 & 960103 Have Been Rescinded.Staff Determined That Due to Permanently Shutdown & Defueled Status of Facility,Orders No Longer Necessary for Safe Operation & Maint.Se Encl ML20196D9191999-06-22022 June 1999 Informs That NRC Has Completed Review of Issues Raised in of Appeal to NRC Edo.Submits List Summarizing Actions Taken Since ML20207H3371999-06-11011 June 1999 Expresses Appreciation for Participation at 990413 Reactor Decommissioning Public Meeting & Responds to Concern Re Absense of Timeliness on Part of NRC Replying to Letters ML20195F6721999-06-0707 June 1999 Forwards Insp Rept 50-309/99-01 on 990214-0513.No Violations Noted.Operations & Radiological Protection Programs, Including Radioactive Liquid & Gaseous Effluent Control Programs,Were Inspected During Insp ML20206U9711999-05-18018 May 1999 Responds to & Addl Info Re Appeal of NRC Determination Re Claim of Backfit Concerning Permanently Shutdown Reactor Security Plan ML20207A2851999-05-14014 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Mgt Created.Organization Chart Encl ML20206H1391999-05-0505 May 1999 Forwards Amend 164 to License DPR-36 & Safety Evaluation. Amend Consists of Changes to License in Response to 970930 Application ML20206H2311999-05-0404 May 1999 Responds to to Chairman Jackson.Forwards Copy of Recent Staff Response to Petition Submitted on Behalf of Ucs Re Fuel Cladding at Operational Reactors ML20206G5561999-05-0303 May 1999 Forwards Amend 163 to License DPR-36 & Safety Evaluation. Amend Revises Liquid & Gaseous Release Rate Limits to Reflect Revs to 10CFR20, Stds for Protection Against Radiation ML20206A5521999-04-23023 April 1999 Forwards Environ Assessment & Finding of No Significant Impact Related to Util Application Dtd 980714,for Amend to License DPR-36 to Revise App a TSs to Change Liquid & Gaseous Release Rate Limits to Reflect Revs Made to 10CFR20 ML20206A6871999-04-22022 April 1999 Informs of Completion of Review of Re Nepco in Capacity as Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee Atomic Power Co ML20205N6211999-04-0707 April 1999 Ack Receipt of Which Appealed NRC Staff Determination That Util Had Not Raised Valid Backfit Claim in to Nrc.Staff Began Process of Convening Backfit Review Panel to Evaluate Appeal ML20205D5141999-03-26026 March 1999 Forwards Ser,Accepting Util 980819 Request for Approval of Rev 1 to Util CFH Training & Retraining Program.Rev 1 Adds Two Provisions to CFH Training Program & Changes One Title ML20205D4011999-03-26026 March 1999 Responds to Sent to Lj Callan Re Emergency Preparedness & Financial Protection Exemption Requests Made by Util & Requests Meeting Scheduled at NRC Headquarters Be Rescheduled & Held in Vicinity of Myaps ML20196K9111999-03-26026 March 1999 Forwards Insp Rept 50-309/98-05 on 981101-0213.Determined That Two Violations Occurred Based on Insp Results & Review of 1997 LER Prior to Permanent Shutdown Determined That Addl Violation Occurred.Violations Treated as NCVs ML20205G7431999-03-26026 March 1999 Documents 990224 Telcon During Which Issues Raised in to NRC Were Discussed.Issues Discussed Re Appeal of Director'S Decision on Claim of Backfit Re Beyond DBA in SFPs ML20204C4501999-03-16016 March 1999 Forwards Amend 162 to License DPR-36.Amend Revises App a TSs of Subj License to Change Limiting Condition for Operation for Fuel Storage Pool Water Level from 23 Feet to 21 Feet ML20204F2481999-03-15015 March 1999 Responds to Expressing Concern Re 10CFR61, Licensing Requirements for Land Disposal of Radwaste & Perceptions of Insufficient Radiological Monitoring of NRC Regulated Facilities.Addresses Issues Raised ML20205G9801999-03-15015 March 1999 Responds to to Chairman Jackson of Nrc,Expressing Concerns Related to 10CFR61, Licensing Requirements for Land Disposal of Radioactive Waste ML20203H1901999-02-19019 February 1999 First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety ML20203B9001999-02-0808 February 1999 First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Already Available in PDR, Documents in App B Released in Entirety & Documents in App C Being Withheld in Part (Ref Exemption 6) ML20203D6751999-02-0303 February 1999 Responds to Requesting NRC Evaluate Two Issues Pertaining to Maintaining Isolation Zones & Vehicle Barrier Sys as Backfits Under 10CFR50.109 ML20199C9031999-01-0707 January 1999 Forwards Exemption from Certain Requirements of 10CFR50.54(w) & 10CFR140.11 for Util.Exemption Issued in Response to Licensee Application Dtd 980120,requesting Reduction in Amount of Insurance Required by Facility ML20198J9181998-12-23023 December 1998 Refers to 981109 Response to Notice of Violation Re Violations Stemming from Independent Safety Assessment Team Insp ML20198J3831998-12-21021 December 1998 Reesponds to Which Continued to Raise Several Concerns Re Belief That NRC Regulatory Action Resulted in Loss of Nuclear Generation & Put Industry Future at Risk. Assures That NRC Addressing Impact of Policies on Licensees ML20206N7481998-12-15015 December 1998 Responds to Re NRC Regulatory Oversight of Maine Yankee Atomic Power Station.Although Staff Does Not Agree with Charges That Staff Acted Inappropriately & Ineffectively,Ltr Referred to NRC OIG for Action ML20196G0291998-12-0202 December 1998 Forwards EA & Fonsi Re Util Request for Exemption from Financial Protection Requirement Limits of 10CFR50.54(w) & 10CFR140.11 for Plant,Submitted in Ltr of 980120 ML20196G2751998-11-27027 November 1998 Forwards Insp Rept 50-309/98-04 on 980803-1031.No Violations Noted.During three-month Period Covered by Insp Period, Conduct of Activities During Continued Decommissioning at Maine Yankee Facilities Was Safety Focused ML20195C3771998-11-0606 November 1998 Discusses Director'S Decision Re Maine Yankee Atomic Power Co Claim of Backfit Re beyond-design-basis Accidents in Spent Fuel Pools.Copy of Author Memo to NRR Staff Directing Them to Address Issues Encl ML20154J3421998-10-0808 October 1998 Responds to Forwarding Response of 2 Individuals to NRC DFI Issued 971219 to Yaec & Duke Engineering & Services Inc.Dfi Did Not Require Response from Individuals Identified in DFI as LOCA Group Mgr & Lead Engineer ML20154J4361998-10-0808 October 1998 Responds to Forwarding Response of Duke Engineering & Services,Inc to NRC DFI Issued 971219 to Duke Engineering & Services,Inc & Yaec ML20154J8451998-10-0808 October 1998 Responds to Which Forwarded Response to NRC Demand for Info Issued on 971219 Re OI Rept 1-95-050. Related Ltr Also Issued to Maine Yankee Identifying Apparent Violations IR 05000306/19960091998-10-0808 October 1998 Discusses Results of Several NRC Insp Repts 50-306/96-09, 50-309/96-10,50-309/96-11,50-309/96-16 & 50-309/97-01, Conducted Between 960715 & 970315,three Investigations Repts 1-95-050,1-96-025 & 1-96-043 & Forwards Notice of Violation ML20154J4511998-10-0808 October 1998 Responds to Which Replied to NRC DFI Issued 971219 to Yaec & Duke Engineering & Services,Inc.Nrc Staff Completed Review of Responses of Yaec & Duke Engineering & Services Inc & 2 Individuals ML20154D7271998-10-0202 October 1998 Forwards RAI Re Spent Fuel Pool & Fuel Assemblies.Response Requested within 30 Days of Date of Ltr ML20154A9041998-09-28028 September 1998 Forwards Insp Rept 50-309/98-03 on 980503-0801.No Violations Noted.Insp Exam of Licensed Activities as They Relate to Radiation Safety & to Compliance with Commission Regulations ML20153G0941998-09-18018 September 1998 Refers to CAL 1-96-15 Issued on 961218 & Suppl Issued 970130,confirming That Facility Will Not Restart Until Addl Actions Were Completed.Issues That Were Subj of CAL & Suppl Were Re Operation of Facility & Not Permanent Shutdown ML20153C0851998-09-16016 September 1998 Responds to 980723 e-mail to Senator SM Collins of Maine Re Several Concerns Raised About Disposal of Reactor Vessel from Maine Yankee Atomic Power Station.Nrc Made No Generic Decision,Acceptable for All Rv with Internal Components ML20197J5931998-09-16016 September 1998 Informs That on 980903 NRC Granted Exemption to Maine Yankee Atomic Power Co from Certain Sections of 10CFR50 Re Emergency Response Planning,Allowing Licensee to Discontinue Offsite Emergency Planning Activities ML20151V0461998-09-0707 September 1998 Responds to Which Raised Several Concerns Re NRC Oversight of Decommissioning of Plant ML20197C7981998-09-0303 September 1998 Forwards Exemption,Environ Assessment & SER in Response to 971106 Request to Discontinue Offsite Emergency Planning Activities & to Reduce Scope of Onsite Emergency Planning as Result of Permanently Shutdown & Defueled Status of Plant 1999-09-08
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l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION l i RELATED TO REQUEST FOR RELIEF FROM INSERVICE TESTING REQUIREMENTS FOR PUMPS AND VALVES MAINE YANKEE ATOMIC POWER COMPANY, MAINE YANKEE ATOMIC POWER STATION DOCKET NO. 50-309 Introduction By letter dated August 7, 1985, Maine Yankee Atomic Power Company (the licensee), submitted a letter to the Commission requesting changos to the Maine Yankee Inservice Testing Program for Pumps and Valves. By way of these changes, the licensee requested relief from certain requirements of the 1980 ASME Code Section XI, Subsection IWP (Pumps) and IW (Valves) as being impractical for the physical configuration of the Maine Yankee Atomic Power Station. 10 CFR 50.55 a(g)(6)(i) authorizes the Commission to grant relief from Code requirements and to impose such alternative require-ments as it determines is authorized by law upon making the necessary find-ings. This safety evaluation is for the licensee's relief request sub-l mitted in the above letter and as amended by a letter dated October 14, 1986.
Evaluation and Discussion i On May 12 and 13, 1986, the staff visited the Maine Yankee Atomic Power l Station to discuss the licensee's relief request. This visit is documented i
in the staff's Inspection Report 50-309/86-08. During this onsite visit, applicable piping and instrument drawings and IST procedures were re-viewed. The locations of the high pressure safety injection pumps suction gauges were also physically inspected. The staff informed the licensee that, as written, the relief requests submitted on August 7, 1985, did not l includesufficienttechnicaljustification,forthestafftocomplete
! its evaluation. The licensee was informed that in addition to the part-tal stroke test for check valve CS-53, a full stroke test of the check valve, even if by disassembly, must be accomplished when plant conditions permit and at a frequency consistent with plant safety.
The licensee submitted a revised relief request by a letter dated October 14, 1986, to address the staff's concerns. The licensee's relief request is evaluated below.
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- 1. Containment Spray System Suction Check Valves-Relief Request No. V-37 A. Relief Requested / Proposed Changes
' Containment spray system valves, CS-93 and CS-94, containment spray pump suction check valves (Recirculation Mode), should be exempted from the following inservice tests:
(1) Full stroke quarterly (Q)
(2) Full str, e cold shutdown (C)
(3) Partial stroke cold shutdown (Cp)
(4). Full stroke each refueling (R)
B. Code Requiren,ent 1980 ASME Code Section XI, Subsection IW.3521 requires that check valves be exercised at least once every 3 months except as provided in Subsection IW.3522.
Subsection IW.3522 requires that check valves shall be exercised to the position required to fulfill their function unless such operation is not practical during plant operation. If only limited operation is practical, during plant operation the check valve shall be part-stroke exercised during plant operation and full-stroke exercised during cold shutdowns. Valves that cannot be exercised during plant operation shall be specifically identified by the Owner and shall be full-stroke exercised during cold shutdowns. Full-stroke exercising during cold shutdowns for all valves not full-stroke exercised during plant operation shall be on a frequency determined by the intervals between shutdowns as follows: for intervals of 3 months or longer, exercise during each shutdown; for inter-vals of less than 3 months, full-stroke exercise is not required unless 3 months have passed since the last shutdown exercise.
Valves that are normally closed during plant operation and whose function is to open on reversal of pressure differential shall be tested by proving that the disk moves promptly away from the seat when the closing pressure differential is removed and flow through the valve is initiated, or when a mechanical opening force is applied to the disk. Confirmation that the disk moves away from the seat shall be by visual observation, by electrical signal initiated by a position indicating device, by observation of substan-tially free flow through the valve as indicated by appropriate pressure indications in the system, or by other positive means. This test may be made with or without flow through the valve. If it is made without flow through the valve, a mechanical exerciser shall be used to move the disk.
The force or torque delivered to the disk by the exerciser must be limited to less than 10% of the equivalent force or torque represented by the minimum emergency condition pressure differential acting on the disk, or
to 200% of the actual observed force or torque required to perform the exercise on the valve when the valve is new and in good operating condition, whichever is less, except that'for vacuum breaker valves the exerciser.
force or torque delivered to the disk may be equivalent to the desired functional pressure differential force. The disk movement shall be sufficient to prove that the disk moves freely off the seat.
C. Basis For Relief Flow testing these check valves would require operating a 5,000 gpm pump taking suction from the safeguards sump located on the
-2 ft. alevation in the containment building. The safeguards sump only holds approximately 400 gallons which is not enough to operate a 5000 gpm pump. The only way to provide enough suction through the safeguards sump would be by flooding the containment building from the -39 ft. elevation to about the 0 ft. eleva-tion. This would require an enormous amount of water and would submerge many plant components. Flow testing these check valves is considered to be impractical. An alternate test will be per-formed.
The only other practical method of ensuring that these valves operate satisfactorily is by disassembling the valve and manu-ally operating the clapper. This, however, cannot be done during normal plant operation because isolating these valves would ren-der one train of low pressure safety injection and one train of containment spray inoperable.
The primary grade borated water in these valves is very compat-ible with the valve internals. These valves are not subject to any vibration induced failures because the RAS sump is only used during an accident.
These valves have been disassembled and manually stroked in the past and have been found to be as good as new. Based on past l performance and the fact that disassembling these valves re-quires working in a highly contaminated area with respirators, disassemb'ing and exercising, alternately, one valve each refuel-ing will provide reasonable assurance that these valves will
, continue to perform their intended function. I D. Proposed Alternate Test Alternately, one valve will be disassembled and exercised every re-fueling outage. If a degraded condition is found, the valve in the other train will be disassertbled and exercised.
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4 E. Technical Evaluation / Discussion
'j The staff's review confirms that it is impracticable within the exist-ing facility design to achieve the necessary testing flow from-the containment sump. The staff agrees that a valve sampling disassembly and inspection utilizing a manuul full stroke of one disk is an acceptable method to verify check valve full stroke capability. In order to sample only one valve each refueling outage, both valves must be of the same design, manufacture, size, model number, and materials of construction and must have the t,ame service; otherwise, both valves are to be disassembled each refueling outage. Addition-ally, at each disassembly, it must be verified that the disassembled valve is capable of full stroking and that its internal parts are structurally sound (no loose or corroded parts).
Based on this review and review of the licensee's justification, the staff agrees with the licensee's basis; and, therefore, relief, sub-ject to the conditions stated above, should be granted from the re-quirements of the ASME Code Section.XI, Subsection IW, Articles 3521 and 3522 for the tsst and test frequencies listed in the relief re-quest. The licensee has demonstrated that, because of the system con-figuration, it is impractical to test the check valves in the manner specified in the Code.
F. Conclusion The staff concludes that due to system configuration, the relief re-quested should be granted and the additional sampling requirements as stated in paragraph 1.E above are imposed. The proposed alternate testing should give reasonable assurance of valve operability re-quired by the Code; therefebe, the staff concludes that the relief granted will not endanger life or property or the common defense and security of the public.
- 2. Containment Spray Systpm Recirculation Line Check Valve. Relief Request No.V-63 i 1
A. Relief Requested / Proposed Changes .
L Containment spray system valve, CS-53, minimum recirculation check valve, should be exempted from the following inservice test:
(1) Full stroke quarterly (Q),
(2) Full stroke cold shutdown (C),
< (3) Partial stroke cold shutdown (Cp), and j
(4) Full stroke each refueling (R)
- 8. Code Requirements 1980 ASME Code Section XI, Subsection IW.3521 requires that check valves be exercised at least once every 3 months except as provided in Subsection IW.3522.
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Subsection IWV.3522 requires that check valves shall be exercised to the position required to fulfill their function unless such operation is not practical during plant operation. If only limited operation is practical, ,
during. plant operation the check . valve.shall be part-stroke exercised during plant operation and full-stroke exercised.during cold shutdowns.' Valves that cannot be exercised during plant operation shall be specifically'ide'ntified ,
by the Owner and shall be full-stroke exercised during cold shutdowns.
Full-stroke exercising during cold shutdowns for all valves.not full-stroke exercised during plant operation shall be on a~ frequency. determined by.the intervals between shutdowns as follows: :for intervals of 3 months or longer, exercise during each shutdown; for intervals of-less than 3 months, full-stroke exercise is not required unless 3 months have passed since the-last shutdown exercise.
Valves that are normally closed during plant operation and whose function is to open on reversal of pressure differential shall be tested by proving.
that the, disk moves promptly away from the seat when the closing pressure differential is removed and flow through the valve is initiated, or when a '
mechanical opening force is applied to the disk. Confirmation that the disk moves away from the seat shall be by visual observation, by electrical 4
signal initiated by a position indicating device, by observation of substan-j tially free flow through the valve as indicated by appropriate pressure indications in the system, or by other positive means.. This test may be made with or without flow through the valve. If it is made without flow
! through the valve, a mechanical exerciser shall be used to move the disk.
l The force or torque delivered to the disk by the exerciser must be limited to less than 10% of the equivalent force or torque represented by the mini-mum emergency condition pressure differentia 1' acting on the disk, or to 200% of the actual. observed force or torque required to perform the exercise on the valve when'the valve is new and in good. operating condition,'which-ever is less, except that for vacuum breaker valves the exerciser force or torque delivered to the disk may be equivalent to the desired functional-pressure differential force. The disk movement shall be sufficient to
, prove that the disk moves freely off the seat.
1 C. Basis for Relief CS-53 is a 6-inch check valve which allows minimum recirculation flow
- from the low pressure safety injection (LPSI) and.three-containment j spray (CS) pumps back to the refueling water storage tank. -To be sure ,
!- that this valve goes full open and passes the maximum design flow, four-
, of these pumps would have to be run in the full recirculation mode simul-
- taneously. Operating four of these pumps in the recirculation mode simul-taneously would render both trains of LPSI and CS inoperable. The tech-nical specifications require both trains to be operable during normal plant operation. This would also render both trains of residual heat removal (RHR) inoperable during cold shutdowns. For these reasons, it is imprac -
ticable to perform a full stroke flow test on this valve during normal
- plant operation and cold shutdowns.
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. D. Proposed Alternate Test CS-53 shall be partially stroked quarterly (QP) during monthly test- l ing and shall be disassembled, inspected, and manually full stroked while disassembled during each refueling outage (Cp).
E. Technical Evaluation / Discussion The staff reviewed the licensee's technical specifications and draw-ing 11550-FM-92A, " Operating Valve No.5 Diagram RHR, Containment Spray, and Low Pressure Safety Injection Piping," for purposes of eval-uating the licensee's original relief request dated August 7,1985.
Review of the drawing confirmed to the staff that it is impractical to get full design flow through this check valve. As previously noted in section 1.E of this safety evaluation, disassembly and inspection utilizing a manual full stroke of the disk is an accept--
able method to verify full stroke capability.
Based on the above review, including the licensee's submitted just-ifications, the staff agrees with the licensee's basis and, there-fore, relief should be granted from the requirenents of ASME Code Section XI, Subsection IW, Articles 3521 and 3322 for the test and test frequencies listed in the relief request. The licensee has de-monstrated that, because of the system configurations, it is impract-ical and potentially unsafe to test this check valve in the manner specified in the Code.
F. Conclusion The staff concludes that, due to system configuration, the relief re-quested should be granted and the proposed alternate test is imposed.
The proposed alternate testing should give reasonable assurance of valve operab1;'.ty required by the Code; therefore, the staf f concludes that the relief granted will not endanger life or property or the common defense and security of the public.
- 3. Power Operated Valve Stroke Times Generic Relief Request A. Relief Requested / Proposed Change Generic relief is requested from the requirement to use the previous stroke time test results for the basis of increased test frequency.
The use of a fixed reference value determined from the stroke time results from several previous tests would be used instead.
B. Code Requirement IW-3417(a) states that, if, for power operated valves, an increase in stroke time of 25% or more from the previous test for valves with full-stroke times greater that 10 seconds or 50% or more for valves with full-stroke times less than or equal to 10 seconds is observed, test frequency shall be increased to once each month until corrective action is taken, at which time the original test frequency shall be resuared.
C. Basis for Relief Using a fixed reference value provides a more logical and stringent basis for determining increased test frequencies. Adhering to the Code as stated above, a valve's stroke time could increase during each test and still be considered acceptable, while in fact, the valve could be failing or, at least, worthy of being tested at an increased frequency. Using a fixed reference value as a standard would give rise to an increased test frequency much sooner than the standard set forth in the Code.
Having a fixed reference value would provide a means for promptly making known whether or not a valve is operating in the' normal, alert, or inoperative range. The reference values with corresponding alert and inoperative values may be incorporated into plant surveil-lance procedures which control valve testing; and, therefore, would allow one to immediately assess whether or not a valve is operating satisfactorily.
D. Proposed Alternate Basis for Increased Test Frequencies Vice IWV 3417(a)
If a fixed reference value is exceeded by either:
1.) 25% or more for those reference values greater than 10 seconds, or
- 2. ) 50% or more for those reference values less than or equal to 10 seconds, The frequency of testing shall be increased to once a month until the condition is corrected.
E. Technical Evaluation / Discussion The staff agrees with the licensee's basis; and, therefore, relief should be granted from the requirements of ASME Section XI Subsection IWV, Article 3417(a) for corrective action criteria as listed in the relief request. The licensee has demonstrated that their method for evaluating power operated stroke times is more conservative than that i
specified in the Code. By using a constant reference value, a grad-ual drift in stroke times can be precluded.
F. Conclusion The staff concludes that the relief request should be granted; and, the alternate test basis is imposed. The alternative evaluation criteria is bounded by that currently required by the Code; there-fore, the staff concludes that the relief granted will not endanger life or property or the common defense and security of the public.
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1 . 4. High Pressure Safety Injection Pumps Suction Gauges Relief Request No.P-5 L A. Relief Requested / Proposal Change Installed suction gauges of the three high pressure injection pumps P-14A, P-148 and P-145 be allowed to remain-at the current range of
' 0-120. psi or four times reference value rather that be changed to a range of 0-90 PSI or three times reference value as specified in the Code.
B. Code Requirements IWP-4120 -
The full-scale range of each instrument shall be three j times the reference value or less.
C. Basis for Relief During a normal plant operation, these pumps are aligned as charging pumps and have a suction pressure of around 30 psia. ASME Section XI requires that the gauge used to measure the suction pressure during inservice pump tests shall have a maximum range of zero to three times the reference value which, in'this case, is 0-90 psia. Also, the accuracy must be within i 2% of full scale. However, during an acci-
- dent situation, these pumps are realigned as high pressure safety in-
, jection pumps and, after a recirculation actuation signal (RAS), take 4
suction from the discharge of the containment spray pumps. In this situation, the suction pressure of the pumps would exceed 90 psia. A suction pressure in excess of 90 psia could potentially, damage a 0-90 psia gauge.
Therefore, Maine Yankee deems it necessary to use a 0-120 psia gauge
, to ensure that the gauge will be operable during an accident situa-tion. Also, this 0-120 psia gauge is calibrated to within i 1% of full scale (1.2 psi) as compared to the code required accuracy for the 0-90 psia gauge of i 2% of full-scale (1.8 psi). Therefore, the 0-120 psia gauge is more accurate than the code requires. The pumps also have a large differential pressure of about 2500 psi. This means that significant~ variations'in suction pressure will cause small percentage changes in differential pressure. For example, a 10 psi error in the suction pressure reading would give a change in dif-ferential pressure of only 0.4%. This is well within the code allow- ,
ed variation of the acceptable differential pressure range of plus 2%
to a minus 7%.
4 D. Alternate Test n For the reasons stated above, the currently installed 0-120 psia gauges will continue to be used to measure the suction pressure on the high pressure safety injection pumps duringLinservice testing.
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E. Technical Evaluation / Discussion The staff confirmed that HPSI pump measured discharge pressures were approximately 2475 psig and suction pressures approximately 40 psig.
Measured discharge pressures for the containment spray pumps were approximately 195 psig. The above test data confirm the licensee's calculations. The staff notes that the containment spray pumps-discharge would do potentially less damage to a 0-120 psi gauge than to a 0-90 psia gauge when those pumps discharge to the suction side of the high pressure injection pumps. The licensee has demonstrated that use of 0-90 psia gauge would provide no improvement in safety or inservice test results; and, in fact could create a situation potentially more damaging to those gauges. The staff also notes that IWP-4110 requires the licensee to assure instrument accuracy to with-in 12% of full scale.
Based on the above review and review of the licensee's justificat-ions, the staff agrees with the licensee's basis. Therefore, relief should be granted from the requirements of Section XI, Subsection IWP
, Article 4120 for HPSI pumps suction gauges listed in the relief re-quest.
F. Conclusion The staff concludes that the relief requested should be granted. The alternate use of higher range suction gauges will not affect eval-uations of high pressure safety injection pumps performance; there-fore, the staff concludes that the relief granted will not endanger life or property or the common defense and security of the public.
Date: April 7,1997 Principal Contributor:
N. J. Blumberg, R:I
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