ML20054C792
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| ML20054C792 | |
| Person / Time | |
|---|---|
| Site: | 05000000, 05000139 |
| Issue date: | 09/27/1977 |
| From: | Norderhaug L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Carlson D WASHINGTON, UNIV. OF, SEATTLE, WA |
| Shared Package | |
| ML19323G049 | List:
|
| References | |
| FOIA-81-339 NUDOCS 8204210659 | |
| Download: ML20054C792 (2) | |
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20196L2741999-05-20020 May 1999
[Table view]Informs That Univ of Wa Did Not Receive Project Funding from State of Wa Legislature for Upcoming Biennium,Which Is from 1999 to 2001.University Intends to Leave Reactor in Current stand-by Status Until Addl Funding Received ML20155E0941998-10-20020 October 1998 Confirms Conference Call of 981013 & 980923 Meetings Re Univ of Washington Research Reactor Decommissioning Project Budget Status.Decommissioning Plan Will Be Amended.Amend Will Be Submitted Prior to Start of First Phase ML20248M2831998-06-11011 June 1998 Forwards Insp Rept 50-139/98-201 on 980514.No Violations Noted.Various Aspects of Safety Program Were Inspected Including Selective Exams of Procedures & Representative Records,Interviews W/Personnel & Observation of Facility ML20059M3931990-09-26026 September 1990 Ack Receipt of Transmitting Change to Physical Security Plan.Nrc Considers Security Plan to Be Withdrawn. Ltr Withheld (Ref 10CFR2.790) ML20056A5371990-07-31031 July 1990 Responds to 900706 Request for Addl Info Re Decommissioning Univ of Washington Argonaut Reactor.Items Refer to Sections 1.3 & 2.1 of Razebld Decommissioning Plan ML20055E4501990-07-0606 July 1990 Forwards Second Request for Addl Info Re Razebld Decommissioning Plan ML17347B5881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits ML15217A1031990-02-28028 February 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals ML18094B3221990-02-28028 February 1990 Forwards Executed Amend 14 to Indemnity Agreement B-74 ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) ML20006G0621990-02-22022 February 1990 Forwards Revised Proprietary Pages to DPC-NE-2004, Core Thermal Hydraulic Methodology Using VIPRE-01, Reflecting Minor Methodology Changes Made During Review & Approval Process.Pages Withheld ML20006E5881990-02-20020 February 1990 Forwards Proprietary Response to NRC 890725 Questions Re Vipre Core Thermal Hydraulic Section of Topical Rept DPC-NE-3000 & Rev 2 to Pages 3-69,3-70,3-78 & 3-79 of Rept. Encls Withheld (Ref 10CFR2.790) ML20006E1441990-02-16016 February 1990 Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals ML20006E9071990-02-16016 February 1990 Discusses Plants Design Control Program.Util Adopted Concept of Design Change Implementation Package (Dcip).Dcip Will Contain or Ref Design Change Notice Prepared Per Approved Procedures ML20006E4201990-02-14014 February 1990 Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 ML18094B3291990-02-14014 February 1990 Forwards Printouts Containing RW-859 Nuclear Fuel Data for Period Ending 891231 & Diskettes ML20011E6151990-02-12012 February 1990 Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21) ML20011E5571990-02-0808 February 1990 Forwards Us Bankruptcy Court for Eastern District of Tennessee Orders & Memorandum on Debtors Motion to Alter or Amend Order & Opinion Re Status of Sales Agreement Between DOE & Alchemie.Doe Believes Agreement Expired on 890821 ML20055C3411990-02-0808 February 1990 Forwards Insp Rept 50-139/90-02 on 900111.No Violations Noted ML20011E4991990-02-0606 February 1990 Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested ML20011E5981990-02-0505 February 1990 Requests That Listed Individuals Be Deleted from Svc List for Facilities.Documents Already Sent to Dept of Environ Protection of State of Nj ML20006D6911990-02-0202 February 1990 Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle ML20006C5661990-01-31031 January 1990 Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at Plants ML18153C0951990-01-29029 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Belief in Appropriateness to Address Generic Ltr 89-13 Concerns within Context of Established Programmatic Improvements Noted ML20011E2521990-01-29029 January 1990 Forwards Proprietary Safety Analysis Physics Parameters & Multidimensional Reactor Transients Methodology. Three Repts Describing EPRI Computer Code Also Encl.Proprietary Rept Withheld (Ref 10CFR2.790) ML20006B7961990-01-29029 January 1990 Forwards Summaries of Latest ECCS Evaluation Model Changes ML20006C6711990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Plants Have Established Preventive Maint Program for Intake Structure & Routine Treatment of Svc Water Sys W/Biocide to Control Biofouling ML20006D6611990-01-29029 January 1990 Advises That 900117 License Amend Request to Remove Certain cycle-specific Parameter Limits from Tech Specs Inadvertently Utilized Outdated Tech Specs Pages.Requests That Tech Specs Changes Made Via Amends 101/83 Be Deleted ML18153C0871990-01-26026 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedures to Be Revised & Familiarization Sessions Will Be Conducted Prior to Each Refueling Outage ML20006D2431990-01-26026 January 1990 Provides Info Re Emergency Response Organization Exercises for Plants.Exercises & Callouts Would Necessitate Activation of Combined Emergency Operations Facility Approx Eight Times Per Yr,W/Some Being Performed off-hours & Unannounced ML18094B2861990-01-26026 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Aggressive Program of Monitoring,Insp & Matl Replacement Initiated in Advance of Generic Ltr 89-13 Issuance ML19354E4191990-01-25025 January 1990 Comments Re Issuance of OL Amends & Proposed NSHC Determination Re Transfer of Operational Mgt Control of Plants & Views on anti-trust Issues Re Application for Amend for Plants ML19354E6711990-01-24024 January 1990 Requests Approval to Use Alloy 690 Plugs as Alternative to Requirements of 10CFR55(a),codes & Stds for Plants Prior to 900226 ML17347B5451990-01-24024 January 1990 Informs of Plans to Apply ASME Code Case N-356 at Plants to Allow Certification Period to Be Extended to 5 Yrs.Rev to Inservice Insp Programs Will Include Use of Code Case ML19354E4451990-01-22022 January 1990 Submits Update on Status of RHR Sys Iconic Display at Facilities,Per Generic Ltr 88-17 Re Loss of Dhr.Computer Graphics Display Data in Real Time & Reflect Status of Refueling Water Level & RHR Pump Parameters ML19354E4461990-01-22022 January 1990 Forwards Proprietary Rev 1 to DPC-NE-2001, Fuel Mechanical Reload Analysis Methodology for MARK-BW Fuel, Adding Section Re ECCS Analysis Interface Criteria & Making Associated Administrative Changes.Rev Withheld ML20005G7161990-01-20020 January 1990 Forwards Rev 1 to Updated FSAR for Braidwood & Byron Units 1 & 2.Changes in Rev 1 Include Facility & Procedures Which Were in Effect as of 890610.W/o Encl ML20006A8001990-01-19019 January 1990 Forwards Response to NRC 891220 Ltr Re Violations Noted in Plant Insps.Response Withheld (Ref 10CFR73.21) ML16152A9091990-01-18018 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. W/900131 Release Memo ML18153C0771990-01-17017 January 1990 Forwards North Anna Power Station Emergency Plan Table 5.1, 'Min Staffing Requirements for Emergencies' & Surry... Table 5.1, 'Min Staffing Requirements...', for Approval,Per 10CFR50.54(q),NUREG-0654 & NUREG-0737,Suppl 1 ML20006A2011990-01-16016 January 1990 Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel in Anchor Darling Swing Check Valves.Eight Subj Valves Identified in Peach Bottom Units 1 & 2 & Will Be Returned to Mfg ML20006A6241990-01-16016 January 1990 Forwards Draft Qualified Master Trust Agreement for Decommissioning of Nuclear Plants,For Review.Licensee Will Make Contributions to Qualified & Nonqualified Trust as Appropriate ML18153C0731990-01-15015 January 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or or Valves.... Util Replaced Studs in twenty-five Valves ML20006B8821990-01-10010 January 1990 Reissued Ltr Correcting Date of Util Ltr to NRC Which Forwarded Updated FSAR for Byron/Braidwood Plants from 881214 to 891214.W/o Updated FSARs ML20006A8201990-01-10010 January 1990 Forwards Errata to Rev 3 to BAW-1543,Tables 3-20 & E-1 of Master Integrated Reactor Vessel Surveillance Program Reflecting Changes in Insertion Schedule for A5 Capsule for Davis-Besse & Crystal River ML20005G6431990-01-10010 January 1990 Responds to Generic Ltr 89-21 Re Implementation of USI Requirements,Consisting of Revised Page to 891128 Response, Moving SER Ref from USI A-10 to A-12 for Braidwood ML20005G7601990-01-0404 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Plan. Privacy Info Should Be Deleted Prior to Placement in Pdr.W/ D Grimsley 900118 Release Memo ML20005F4641990-01-0303 January 1990 Advises That Licensee Implemented 10CFR26 Rule Re fitness-for-duty Program W/One Exception.Util Has Not Completed Background Check for Some of Program Administrators.Checks Expected to Be Completed by 900105 ML18094B2331990-01-0303 January 1990 Certifies Util Implementation of fitness-for-duty Program, Per 10CFR26.Training Element Required by Rule Completed on 891215.Chemical Testing for Required Substances Performed at Min Prescribed cut-off Levels,Except for Marijuana 1999-05-20 Category:NRC TO EDUCATIONAL INSTITUTION MONTHYEARML20059M3931990-09-26026 September 1990
[Table view]Ack Receipt of Transmitting Change to Physical Security Plan.Nrc Considers Security Plan to Be Withdrawn. Ltr Withheld (Ref 10CFR2.790) ML20055E4501990-07-0606 July 1990 Forwards Second Request for Addl Info Re Razebld Decommissioning Plan ML20055C3411990-02-0808 February 1990 Forwards Insp Rept 50-139/90-02 on 900111.No Violations Noted ML20247G5671989-05-19019 May 1989 Provides Procedure Outline for Decommissioning Reactor to Convert Facility Housing to Subcritical Assembly.Application Should Include Decommissioning Plan Which Discusses Radioactivity Levels Prior to Installation of Assembly IR 05000097/19890011989-05-12012 May 1989 Forwards Safety Insp Repts 50-097/89-01 & 50-157/89-01 on 890425-26.Weakness Identified in Area of Documentation ML20195H0451988-11-18018 November 1988 Forwards Amend 14 to License R-73 & Safety Evaluation.Amend Allows Certain Surveillance Requirements Associated W/ Operation of Reactor to Be Suspended If No Fuel in Core ML20205T6921988-11-0303 November 1988 Notifies of 890110 Meeting W/Region V in San Francisco,Ca to Discuss Policies & Procedures for Operator Licensing Activity in Region V.Agenda Encl IR 05000072/19880011988-10-28028 October 1988 Ack Receipt of 880804 & 25 Ltrs Informing NRC of Steps Taken to Correct Violations & Deviations Noted in Insp Repts 50-072/88-01 & 50-407/88-01 & Order.Concludes That W/ Exception of Violation 5.c,violations Did Not Occur ML20151U7541988-08-11011 August 1988 Informs of NRC Interpretation of Section 10CFR50.74(a) Re Changes in Operator or Senior Operator Status ML20148G6761988-03-10010 March 1988 Forwards Insp Rept 50-139/88-01 on 880111.No Violations or Deviations Noted ML20147D0421988-02-29029 February 1988 Requests That Recipient Resubmit Proposal to Convert to Low Enriched U Fuel to Meet 10CFR50.64(6)(2) or (3) Requirements by 880327.Identical Ltrs Sent to Listed Dockets ML20149M3561988-02-24024 February 1988 Forwards Amend 13 to License R-73.Amend Modifies Tech Specs to Change Permissible Rod Drop Time of Shim Rod 3 to 3 s, Increases Surveillance Frequency for All Control Rods & Reduces Core Excess Reactivity to 1.9% Delta K/K IR 05000139/19870021987-12-0404 December 1987 Forwards Matl Control & Accounting Safeguards Insp Rept 50-139/87-02 on 871116 & 17.No Violations or Deviations Noted.Rept Withheld (Ref 10CFR2.790(d)) IR 05000139/19870011987-10-0606 October 1987 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-139/87-01.Periodic Measurement of Rod 3 Drop Time Following Reactor Operation Expected Based on 870930 Telcon ML20235J9721987-09-25025 September 1987 Extends Invitation to Attend 871110 Meeting W/Region V in San Francisco,Ca to Discuss Policies & Procedures for Operator Licensing Activity in Region V & NRC Policy & Developments ML20238D7511987-08-28028 August 1987 Forwards Insp Rept 50-139/87-01 on 870727-28 & Notice of Violation ML20215C6351987-06-11011 June 1987 Informs of Recent NRR Reorganization.Current Ofc Now Called Standardization & Non-Power Reactor Directorate,Under Div of Reactor Projects Iii,Iv,V & Special Projects,Nrr.T Michaels Project Manager for Facility ML20206C6061987-04-0808 April 1987 Ack Receipt of & Payment of $3,000 for Civil Penalty Imposed on 870313.Corrective Actions Described in Will Be Examined During Future Insps ML20212P1851987-03-11011 March 1987 Responds to 870309 10CFR2.206 Petition for Commission Review of Directors Decision DD-87-2.Time Period for Commission Review Expired & Decision Became Final Agency Action on 870310.Served on 870312 ML20206R6801986-06-27027 June 1986 Forwards Safeguards Insp Repts 50-139/86-01 & 50-139/86-02 on 860602-03.No Violation Noted ML20140G7111986-03-27027 March 1986 Lists Change in Telephone Number for H Bernard,Facility Project Manager,Due to NRR Reorganization.D Tondi New Nonpower Reactor & Safeguards Licensing Section Leader. Correspondence Should Be Sent to Listed Address ML20136G3791985-11-18018 November 1985 Discusses Actions Re Claims of Alleged Inadequacies in Containment Leak Rate Tests Performed at LWR Plants.Matter Will Not Be Considered Further ML20136F8091985-11-18018 November 1985 Informs That Excess Unirradiated Highly Enriched U Can Be Removed from Facility within 120 Days of Effective Date of Show Cause Order ML20136A9181985-11-14014 November 1985 Responds to 851023 Request for Guidance on Any Requirement Re Use of N Stamped Equipment in Reactor Thermal Hydraulic Circuits.No Stamping Requirements Contained in 10CFR or in Manuals or Guides ML20138A0801985-10-0404 October 1985 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp on 850717-19 ML20135F9711985-09-0404 September 1985 Forwards Insp Rept 50-139/85-01 on 850717-19 & Notice of Violation ML20127M3791985-05-0606 May 1985 Advises That 850205 & 0424 Changes to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20127P1151985-04-24024 April 1985 Forwards Exam Rept 50-139/OL-85-01 on 850325-26 ML20126E4311985-03-25025 March 1985 Responds to FOIA Request for Records Re FIN B-0489, Containment Leak Rate Testing Program & Quadrex Corp/Nrc Contracts.Forwards Documents Re FIN B-0489.Documents Also Available in Pdr.No Documents Re Quadrex Subj to Request ML20128P3091984-12-0404 December 1984 Responds to 841126 & 27 Telcon Requests for Listed Info. Diagram of Mark II Containment Encl.S&W Will Forward Correct Diagram of Surry Containment.Experimental Data for Decay Heat Curve Does Not Exist.W/O Encl ML20128P2691984-11-20020 November 1984 Forwards Diagrams Illustrating Core Concrete Interaction, Based on Corcon Calculations for Facility.Concrete Consists of Limestone ML20128P2331984-11-14014 November 1984 Forwards Microfiche of EPRI Mar 1980 Revised Rept NSAC-1, Analysis of TMI-2 Accident. Version Out of Print.W/O Encl NUREG-0850, Forwards Vol 1 to NUREG-0850, Preliminary Assessment of Core Melt Accidents at Zion & Indian Point Nuclear Power Plants & Strategies for Mitigating Effects. Vol 1 Only Vol Available at Present1984-08-14014 August 1984 Forwards Vol 1 to NUREG-0850, Preliminary Assessment of Core Melt Accidents at Zion & Indian Point Nuclear Power Plants & Strategies for Mitigating Effects. Vol 1 Only Vol Available at Present ML20128N9361984-08-14014 August 1984 Forwards Vol 1 to NUREG-0850, Preliminary Assessment of Core Melt Accidents at Zion & Indian Point Nuclear Power Plants & Strategies for Mitigating Effects. Vol 1 Only Vol Available at Present ML20197H1651984-06-12012 June 1984 Forwards IE Safeguards Insp Rept 50-139/84-01 on 840424 & Notice of Violation NUREG/CR-3028, Forwards NUREG/CR-3028, Review of Limerick Generating Station PRA & Vols 1 & 2 to NUREG/CR-0027, Proceedings of Intl Meeting on Thermal Nuclear Reactor Safety. Advises That NUREG/CR-3300 Not Published.W/O Encls1984-05-31031 May 1984 Forwards NUREG/CR-3028, Review of Limerick Generating Station PRA & Vols 1 & 2 to NUREG/CR-0027, Proceedings of Intl Meeting on Thermal Nuclear Reactor Safety. Advises That NUREG/CR-3300 Not Published.W/O Encls ML20128N3851984-05-31031 May 1984 Forwards NUREG/CR-3028, Review of Limerick Generating Station PRA & Vols 1 & 2 to NUREG/CR-0027, Proceedings of Intl Meeting on Thermal Nuclear Reactor Safety. Advises That NUREG/CR-3300 Not Published.W/O Encls ML20210E6761984-03-23023 March 1984 Forwards Region V Evaluation of Emergency Preparedness Concerns Expressed in 831104,1209 & s Included in Latest Plant Sser NUREG/CR-1250, Forwards Vols 1 & 2 to NUREG/CR-1250, TMI - Rogovin Rept1984-03-18018 March 1984 Forwards Vols 1 & 2 to NUREG/CR-1250, TMI - Rogovin Rept ML20128N2001984-03-18018 March 1984 Forwards Vols 1 & 2 to NUREG/CR-1250, TMI - Rogovin Rept ML20210E6891983-12-30030 December 1983 Ack Providing Addl Data Re Concern About Method of Notifying Population in Case of Flood.Siren Concern Being Addressed.Fema Ltr Addressing Items Identified in Initial Encl ML20128M7001983-11-0101 November 1983 Forwards Draft Vols I-III to BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls ML20128M7741983-09-12012 September 1983 Forwards Draft Vols I-III of BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls ML20128M7601983-09-12012 September 1983 Forwards Draft Vols I-III of BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls ML20128M7311983-09-12012 September 1983 Forwards Draft Vols I-III of BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls ML20128M7951983-09-0909 September 1983 Forwards Draft Vols I-III of BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls ML20128M8191983-08-12012 August 1983 Forwards Draft Vols I-III of BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls ML20128M7981983-08-12012 August 1983 Forwards Draft Vols I-III of BMI-2104 Re Ongoing Source Term Reassessment Study.W/O Encls IR 05000139/19820021982-07-29029 July 1982 Forwards IE Safeguards Insp Rept 50-139/82-02 on 820722.No Noncompliance Noted ML20054L6971982-06-23023 June 1982 Forwards IE Insp Rept 50-139/82-01 on 820608-11.No Noncompliance Noted 1990-09-26 Category:OUTGOING CORRESPONDENCE MONTHYEARML20248M2831998-06-11011 June 1998
[Table view]Forwards Insp Rept 50-139/98-201 on 980514.No Violations Noted.Various Aspects of Safety Program Were Inspected Including Selective Exams of Procedures & Representative Records,Interviews W/Personnel & Observation of Facility ML20059M3931990-09-26026 September 1990 Ack Receipt of Transmitting Change to Physical Security Plan.Nrc Considers Security Plan to Be Withdrawn. Ltr Withheld (Ref 10CFR2.790) ML20055E4501990-07-0606 July 1990 Forwards Second Request for Addl Info Re Razebld Decommissioning Plan ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) ML20055C3411990-02-0808 February 1990 Forwards Insp Rept 50-139/90-02 on 900111.No Violations Noted IA-89-409, Final Response to FOIA Request.App a & B Records Available in PDR & Encl.Portions of App B Record Withheld (Ref FOIA Exemption 6)1989-09-26026 September 1989 Final Response to FOIA Request.App a & B Records Available in PDR & Encl.Portions of App B Record Withheld (Ref FOIA Exemption 6) ML20247R3361989-09-26026 September 1989 Final Response to FOIA Request.App a & B Records Available in PDR & Encl.Portions of App B Record Withheld (Ref FOIA Exemption 6) ML20248G9731989-09-20020 September 1989 Forwards Unexecuted Amend 13 to Indemnity Agreement B-69, Reflecting Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu ML20248F0321989-09-14014 September 1989 Forwards Rept of AOs at Licensed Facilities for First Calendar Quarter 1989.Plug Failure Resulted in Steam Generator Tube Leak at North Anna Unit 1 & Steam Generator Ruptured at McGuire Unit 1.W/o Encl ML20247G2781989-09-13013 September 1989 Partial Response to FOIA Request for Records.Apps F & G Records Available in Pdr.App H Records Partially Withheld & App I Record Completely Withheld (Ref FOIA Exemption 5) ML20247L2401989-09-13013 September 1989 Responds to Re K Barnes Concerns Regarding Safety at Plants.Advises That to Date,Releases from Plants Remain Well within Accepted Stds ML20247H6411989-09-12012 September 1989 Advises That 890816 Revisions to ATWS Mitigation Sys Acceptable W/Requirements of 10CFR50.62(c)(1) ML20247K2231989-09-11011 September 1989 Forwards Amends 123 & 41 to Licenses DPR-61 & NPF-49, Respectively & Safety Evaluation.Amends Change Tech Specs 4.10.1.D.1.h & 4.4.5.4.a.8 to Allow Insp of Steam Generator Tubes by Insertion of Ultrasonic Test Probe ML20247E3371989-09-0707 September 1989 Forwards Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Change Tech Spec Sections 6.10.2.m & 6.10.3 Re Records Retention for Radiological Effluent Monitoring & ODCM ML20246Q0121989-08-31031 August 1989 Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted IR 05000029/19890141989-08-31031 August 1989 Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted ML20246K8571989-08-25025 August 1989 Discusses NRC Actions in Reponse to Constituent Concerns Re Excessive Overtime Worked by Employees of Plants ML20246B6591989-08-18018 August 1989 Forwards 40th Quarterly Status Rept on Emergency Preparedness for Nuclear Power Plants from Apr-June 1989. Lilco Shareholders Voted to Accept Terms That Provide for Sale of Plant to State of Ny ML20246C7101989-08-18018 August 1989 Forwards Order,Effective Immediately,Modifying CPs CPEP-1 & CPEP-2 to Require Notification of Commission Before Taking Possession of Any Classified Equipment & to Show Cause Why CPs Should Not Be Revoked ML20246C8161989-08-16016 August 1989 Partial Response to FOIA Request for Documents.App D & E Documents Available in Pdr.App E Documents Encl ML20246C3941989-08-15015 August 1989 Forwards Safeguards Insp Repts 50-272/89-19,50-311/89-17 & 50-354/89-15 on 890710-14.No Violations Noted ML20246C8211989-08-11011 August 1989 Confirms 890808 Telcon Re Util Participation in NRC Regulatory Impact Survey on 891023 in Berlin,Ct.Schedule & General Discussion Groups Shown in Encl ML20248D6921989-08-0404 August 1989 Advises That Rev 6b to Generating Stations Emergency Plan Transmitted by Util 890710 Form Acceptable & Does Not Decrease Effectiveness of Plan ML20248C0561989-08-0303 August 1989 Forwards Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants.Nrc Requested to Be Notified Upon Completion of Human Factors Review ML20245H5331989-08-0202 August 1989 Advises That 890519 Changes to QA Program Described in CPC-2A Acceptable.Issues Addressed Listed ML20247P9581989-08-0101 August 1989 Partial Response to FOIA Request.App a Records Available in Pdr.App B Records Encl & Available in PDR ML20247F0481989-07-25025 July 1989 Partial Response to FOIA Request for Records.App L Record Available in Pdr.App M Records Partially Withheld Ref (FOIA Exemption 7).App N Record Provided to Requestor But Not Made Publicly Available at This Time ML20247H6891989-07-25025 July 1989 Requests Proposed Design Change to Containment Hydrogen Monitoring Sys,W/Schedule for Implementing Change or Justification for Existing Configuration ML20246P0181989-07-17017 July 1989 Forwards Request for Addl Info Re 890620 Filing for Reorganization in Us Bankruptcy Court.Nrc Will Initiate Proceeding for Suspension or Revocation of CPs Should Licensee Fail to Respond by 890815 ML20246A2951989-06-29029 June 1989 Forwards Request for Addl Info Re NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs ML20246L2211989-06-26026 June 1989 Forwards Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Revise Tech Specs by Removing Tech Spec Figures 6.2-1 & 6.2-2 Re Organizations Functional Requirements ML20245J3301989-06-22022 June 1989 Provides Background Info on Regulatory Analysis Supplementing NRC Proposed Backfit,Per 890413 Request.Util Expected to Provide Schedule for Implementation of Required Improvements ML20245B4271989-06-21021 June 1989 Final Response to FOIA Request.App U Records Encl & Available in Pdr.App V Record Withheld (Ref FOIA Exemption 5) ML20245F2691989-06-16016 June 1989 Forwards SER Accepting Licensee 850612 Response to Generic Ltr 83-28,Item 4.5.3 Re Trip Reliability & on-line Functional Testing of Trip Sys ML20245B3881989-06-15015 June 1989 Responds to Re Flow & Pressure Drop Calculations for RWCU & Feedwater & Condensate Sample Panels.Util Actions Do Not Have Adverse Impact on Nuclear Reactor Safety to Extent That Protection of Safety of Environ Affected ML20245B1731989-06-15015 June 1989 Ack Receipt of Rev 55 to QA Topical Rept CE-1-A.Program Satisfies Requirements of 10CFR50,App B & Acceptable ML20245H1491989-06-15015 June 1989 Submits Correction/Clarificaton to Util 890508 Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Program on Critical Air Demand Equipment Is in Addition to Investigations Performed ML20244C2941989-06-0909 June 1989 Advises Tht Util 890329 Request for Approval to Use Fuses for Electrical Isolation of non-Class 1E Dc Power Sys Acceptable Provided That Circuit Breaker in Parallel to Two Fuses Locked Open ML20245B4531989-06-0808 June 1989 Forwards Encl Listed Info on Decommissioned & Shutdown Reactors Requested During Discussions at Saxton on 890511 ML20244C5091989-06-0101 June 1989 Advises That Bunker Ramo Penetration Assemblies Environmentally Qualified to Perform Intended Functions for Plants,Per 890224 Rept & .Concerns Expressed in Re Byron Unit 2 Satisfied ML20248C2671989-05-31031 May 1989 Forwards Insp Repts 50-321/88-37,50-366/88-37 & 50-424/88-53 on 881102-890106 & Notice of Violation.Notice of Violation Withheld (Ref 10CFR2.790(d) & 73.21) ML20247M7731989-05-26026 May 1989 Forwards Directors Decision Re Ohio Citizens for Responsible Energy 10CFR2.206 Petition Re 880309 Power Oscillation Event at Lasalle,Unit 2 ML20247G5671989-05-19019 May 1989 Provides Procedure Outline for Decommissioning Reactor to Convert Facility Housing to Subcritical Assembly.Application Should Include Decommissioning Plan Which Discusses Radioactivity Levels Prior to Installation of Assembly ML20247H3511989-05-19019 May 1989 Advises That Licensee Response to Generic Ltr 82-33 Re post-accident Monitoring Instrumentation,Per Rev 3 to Reg Guide 1.97,acceptable,except for Four Items Listed in Technical Evaluation Rept ML20247J7801989-05-19019 May 1989 Informs of Implementation Schedule for Item 1.b of NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification, Mutually Agreed Upon Between NRC & Westinghouse During 890411 Meeting ML20247C1521989-05-18018 May 1989 Informs of Implementation Schedule for Item 1.b of NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification. Understands That Westinghouse Will Provide Util W/Generic Bounding Analysis Re Seismic Loadings ML20247G5241989-05-18018 May 1989 Responds to Re Util Position on Dealing W/Dc Grounds After Discussion W/Nrc in 890301 Meeting.Continued Plant Operation Will Be Allowed Only So Long as Applicable Limiting Conditions/Or Action Statements Met ML20247B2411989-05-17017 May 1989 Comments on Expeditious Actions & Notice of Audit on Generic Ltr 88-17 Re Potential Loss of Dhr.Requests Addl Info Re Training Packages,Administrative Controls for Containment Closure & RCS Level Indications ML20246Q1511989-05-16016 May 1989 Informs of Implementation Schedule for Item 1.b of NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification, Per 890411 Meeting W/Westinghouse Owners Group.Proposed Schedule for Analysis Must Be Accelerated ML20246P8141989-05-15015 May 1989 Requests Addl Info Re 881130 Application for Amends to Licenses Per Generic Ltr 87-09.Affirmation Should Be Provided That Procedures,Mgt Directives & Onsite Reviews Limit Use of Spec 3.0.4 Exceptions 1998-06-11 |
See also: IR 05000139/1977003
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UNITED STATES
NUCLEAR REGULATORY COMMiss!ON
REGION V
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SUITE 202. WALNUT CREEK PLAZA
f , j. 4. " --* * * d ' \\
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1990 N. CALIFORNIA BOULEVARD
WALNUT C REEK. CALIFORNI A 94596
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SEP 2 71977
Docket No. 50-139
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University of Washington
College of Engineering
369 Loew Hall, FH-10
Seattle, Washington 98195
Attention:
Dr. Dale Carlson, Dean
College of Engineering
Gentlemen:
Subject: University of Washington Inspection
This letter refers to the inspection of your activities authorized under
NRC License No. R-73 conducted by Mr. M. D. Schuster of this office on
September 19-20, 1977.
It also refers to the discussion of our inspection
findings held by the inspector with Professor W. Chalk and members of
his staff on September 20, 1977.
The inspection included examination of activities related to physical
protection against industrial sabotage and against theft of special
nuclear material in accordance with applicable requirements of Title 10,
Code of Federal Regulations, Part 73, " Physical Protection of Plants and
Materials," your Security Plan, and license conditions pertaining to
physical protection as described in the enclosed inspection report.
Within these areas, the inspection consisted of selective examinations
of procedures and records, interviews with facility personnel and ob-
servations by the inspector.
,
Within the scope of this inspection, no items of noncompliance were
observed.
In accordance with Section 2.790 (d) of the NRC's " Rules of Practice,"
Part 2 Title 10, Code of Federal Regulations, documentation of the
findings of your safeguards and security measures are exempt from public
disclosure; therefore the enclosed inspection report will not be placed
in the Public Document Room.
,ptung
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8204210659 811110
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SEP 2 71977
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Should you have any questions concerning this letter, we will be glad to
discuss them with you.
Sincerely,
6.
LeRoy{ LNo de aug. Actin'g Chief
Saf
ranch -
Enclosure:
IE Inspection Report 50-139/77-03
cc(w/ enc 1)
Prof. W. Chalk, Director
Nuclear Reactor Bldg. FD-10
Univ. of Washington
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