ML20235E583
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17347B5881990-03-0101 March 1990
[Table view]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 ML18094B3221990-02-28028 February 1990 Forwards Executed Amend 14 to Indemnity Agreement B-74 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 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 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 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 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) 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 ML20006B7961990-01-29029 January 1990 Forwards Summaries of Latest ECCS Evaluation Model Changes 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 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 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 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 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 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 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 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 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 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 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 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 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 ML18153C0491990-01-0303 January 1990 Advises of Implementation of fitness-for-duty Program Which Complies w/10CFR26.Util Support Objective of Providing Assurances That Nuclear Power Plant Personnel Will Perform Tasks in Reliable & Trustworthy Manner 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 ML17347B5051990-01-0202 January 1990 Certifies That Util Has fitness-for-duty Program Which Meets Requirements of 10CFR26.Util Adopted cut-off Levels Indicated in Encl ML20042D3731990-01-0202 January 1990 Forwards Revised Crisis Mgt Implementing Procedures, Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9, Rev 1 to CMIP-14 & Rev 30 to CMIP-21 ML17347B4961989-12-28028 December 1989 Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Considering Expansion of Plants to Include Addl safety-related & Position Changeable Valves W/ Emphasis on Maint & Testing ML20042D3381989-12-28028 December 1989 Forwards Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. Util Will Comply W/Ltr Recommendations W/Noted Exceptions.Response to Be Completed When Ltr Uncertainties Cleared ML18094B2201989-12-27027 December 1989 Advises of Intent to Provide follow-up Response to Generic Ltr 89-10 by 900831 to Describe Status of Program, Recommendation Exceptions & Any Schedule Adjustments ML18094B2291989-12-27027 December 1989 Requests to Apply ASME Section XI Code Case N-460 to Facilities Re Reduction in Exam Coverage on Class 1 & 2 Welds.Fee Paid 1990-03-01 Category:NRC TO VENDOR/MANUFACTURER MONTHYEARML20246C7101989-08-18018 August 1989
[Table view]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 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 ML20246P4171989-03-23023 March 1989 Advises That 890210 Condition III.6 of CP Issued to Alchemie Re Financial Assurances for Protection of Common Defense & Security by Control of Classified Machinery Not Applicable ML20235N9801989-02-22022 February 1989 Forwards Notices of Issuance of CPs for Alchemie Centrifuge Plan Demonstration & Oliver Springs Facilities ML20205T5991988-11-0707 November 1988 Requests Survey of Proposed Oliver Spring Site to Look for Evidence of Threatened or Endangered Species ML20205R7171988-11-0303 November 1988 Requests 880912 Submittal Re Ability to Assure Funding for Decontamination Over Entire Period of License Be Revised. NRC Expects That Sale of Unneeded,Unclassified Matl Will Realize Sufficient Funds to Cover Costs of Removal of Matl ML20205T6961988-11-0303 November 1988 Notifies of 890110 Meeting W/Region V in San Francisco,Ca to Discuss NRC Reactor Operator Licensing Program in Region ML20205M9061988-10-28028 October 1988 Advises That Addendum 2 to WCAP-10988, COBRA-NC,Analysis for Main Steamline Break in Catawba Unit 1 Ice Condenser Containment, Forwarded by Will Be Withheld from Public Disclosure,Per Request ML20205L0381988-10-27027 October 1988 Informs That WCAP-11935, McGuire 2 - Evaluation for Tube Vibration-Induced Fatigue Will Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20205Q5661988-10-25025 October 1988 Forwards SERs Re Company 871117 Application for Authority to Construct & Operate Facilities to Enrich Stable Isotopes at Facility-1 Cpdf & to Construct Facility for Same Purpose at Facility-2 Oliver Springs ML20154E7171988-09-0808 September 1988 Forwards Notice of Issuance of Environ Assessment & Finding of No Significant Impact & Environ Assessments Re 871107 Application to Construct & Operate Facility for Enriching Stable Isotopes ML20148B5101988-03-15015 March 1988 Informs of Relocation of NRR to Stated Address in Rockville,Md ML20153B1541988-03-15015 March 1988 Informs of Relocation of NRR to Stated Address in Rockville, MD ML20235T2431987-09-24024 September 1987 Forwards Insp Repts 50-018/87-01,50-070/87-01,50-073/87-01 & 50-183/87-01 on 870901-03 & Notice of Violation ML20214M6631987-05-22022 May 1987 Forwards Revised NRC Form 398.Rev Reflects Changes to 10CFR55 Effective on 870526.Revised Form Requires New Applications to Complete Each Category Including Educ, Training & Experience.Changes Detailed in Encl 2 ML20205L6971987-03-27027 March 1987 Requests Further Info & Documentation Re Steam Generator Tube Vibration Problem for Generic CESSAR Sys 80 Steam Generator Design by 870410.Specific Questions Re Request Encl ML20207H6641986-07-22022 July 1986 Ack Receipt of 860508 Application for Approval of Transfer of Ga Co Control for Licenses R-38,R-67 & SNM-0696. Application Fee Required ML20199F2211986-02-19019 February 1986 Further Response to FOIA Requests for Documents Re Humboldt Bay File Up to 761231,Bodega Bay file,4x4 Test Info & Wuergassen Plant 1972 Incident.Forwards App J Documents.App J Documents Withheld Due to Proprietary Nature ML20140F3691986-01-14014 January 1986 Further Response to FOIA Request for Several Categories of Documents Re Pressure Suppression Containment.Fsar & SER for Limerick Only Documentation Re 4x4 Tests.Encl Apps D-G Documents Responsive to Item 4 Also Available in PDR ML20137C5151986-01-13013 January 1986 Forwards Summary of Changes & Revised Pages Incorporating Changes to Braidwood Draft Tech Specs.Byron Tech Specs Should Address diesel-driven Essential Svc Water Makeup Batteries.Amend Request Will Be Needed ML20239A1971985-12-17017 December 1985 Further Response to 850927 & 1106 FOIA Requests for Documents Re Pressure Suppression Containment,Including Humboldt Bay & Bodega Bay Docket Files.Bodega Bay File Being Placed in Pdr.Review of Addl Documents Continuing ML20138A7521985-10-0808 October 1985 Requests Listing of Customers Purchasing or Ordering Valve Operators Containing Magnesium Motor Rotors.Test Anomalies Have Raised Concern Re long-term Availability of Valve Operator Motors W/Magnesium Rotors ML20133B2801985-07-29029 July 1985 Approves 841219 & 21 Requests for Withholding CAW-84-117, Equipment Justification for Interim Operation - Wolf Creek Generating Station,Unit 1 & Callaway Station,Unit 1, from Public Disclosure,Per 10CFR2.790 ML20126C1121985-06-10010 June 1985 Approves Request That WCAP-10553, Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Byron Units 1 & 2 & Braidwood Units 1 & 2, Be Withheld (Ref 10CFR2.790) ML20128L5161985-05-22022 May 1985 Concludes That 1985 Financial Info,Per 850419 Submittal, Satisfies 10CFR140.21,requiring That Each Licensee Maintain Approved Guarantee of Payment of Deferred Premiums for Each Operating Reactor Over 100 Mw(E) ML20129B2161985-05-20020 May 1985 Approves 841018 & 830926 Requests for Withholding WCAP-10690 & WCAP-10691, Technical Bases for Eliminating Large Primary Loop Pipe Rupture..., from Public Disclosure Per 10CFR2.790 ML20137G9831983-12-0909 December 1983 Notifies of 840111 Meeting in Shiller Park,Il to Discuss Scheduling Problems Re Exam Process & Examiner Stds, (NUREG-1021).Attendee Names & Addl Discussion Subjs Should Be Submitted by 831219.Preliminary Agenda Encl ML20137G9721983-07-22022 July 1983 Advises That Region III Telephone Number Will Be Changed Effective 830822.New Number Listed.Notice of Change Will Appear in Fr Prior to 830822 ML20055A4331982-06-16016 June 1982 Discusses Alternative Methods for NRC to Conduct Confirmatory Analyses of Westinghouse NSSS Designed NSSS W/O Involvement of OL Applicants.Transient & Accident Evaluation Performed on Generic Basis Generally Acceptable ML20054E8951982-06-0707 June 1982 Approves Request for Withholding Info Per 10CFR2.790 Re Improved Thermal Design Procedures (CAW-82-15) ML20137G8881981-08-28028 August 1981 Forwards IE Info Notice 81-26, Compilation of Health Physics Related Info Items. Five Items of Info That Generally Have Impact on Areas Normally Under Responsibility of Health Physics Group Listed ML20137G5071981-07-31031 July 1981 Forwards IE Info Notice 81-22, Section 235 & 236 Amends to Atomic Energy Act of 1954, Which Should Be Brought to Attention of Employees & Others Involved in NRC-licensed Activities.No Response Required IR 05000264/19790031979-12-0505 December 1979 Forwards Insp Rept 50-264/79-03 on 791022-24 & Notice of Violation ML20137H0401979-11-0909 November 1979 Forwards IE Info Notice 79-12A, Attempted Damage to New Fuel Assemblies. No Response Requested ML20137H0341979-10-17017 October 1979 Submits New Telephone Number for Region Iii,Effective 791022 ML20197B0231978-10-23023 October 1978 Responds to Advising That NEDO-24048, Evaluation of Acoustic Pressure Loads on BWR/6 Internal Components Part of Gessar Docket & Fee Exempt.Concurs on Fee Exemption ML20137H0031978-08-11011 August 1978 Ack Receipt of 780727 Response to Notice of Violation ML20137H0221978-06-12012 June 1978 Forwards IE Bulletin 78-08, Radiation Levels from Fuel Element Transfer Tubes ML20137H1121978-02-0606 February 1978 Confirms 780202 Telcon Re Meeting Between NRC & Dow Chemical Co on 780207 at Facility to Discuss Results of Physical Security Insp on 780110-12 ML20137H3941977-11-21021 November 1977 Forwards Amend 3 Renewing License R-108 & Incorporating Security Plan as License Condition.Safety Evaluation,Eia Notice of Issuance & Negative Declaration Also Encl.Security Plan Withheld (Ref 10CFR2.790) ML20137G9311977-08-18018 August 1977 Forwards Insp Rept 50-264/77-02 on 770719-22,26 & 27.No Noncompliance Noted ML20137H1161977-07-22022 July 1977 Ack Receipt of Informing of Recovery of 200-mCi Cs-137 Sealed Source from Brine Well on 770621 ML20137H2171977-07-18018 July 1977 Forwards IE Circular 77-10, Vacuum Conditions Resulting in Damage to Liquid Process Tanks ML20140F5801977-06-0606 June 1977 Advises That GE 770303 Conclusions That Leaking Safety/Relief Valves Would Result in Lower Loads on Structures than First Actuation W/O Leakage Unjustified,For Listed Reasons ML20137H3901977-04-15015 April 1977 Requests That Encl Notice Re Direct Accessibility of IE to Employees Concerned About Quality of Work,Radiological Safety or Safeguards at Facility Be Posted ML20137H3511976-12-17017 December 1976 Forwards IE Circular 76-03, Radiation Exposures in Reactor Cavities. Prompt Reply Requested.Original Submittal Forwarded on 760913 Not Received as Noted on 761214 ML20137H4101976-09-0101 September 1976 Requests That Encl Form Be Completed & Submitted by 760915 & Facility Emergency Plan & Implementing Procedures by 761007 in Order for NRC to Prepare Info Packets for Use in Responding to Incidents or Emergencies IA-85-256, Requests That Encl Form Be Completed & Submitted by 760915 & Facility Emergency Plan & Implementing Procedures by 761007 in Order for NRC to Prepare Info Packets for Use in Responding to Incidents or Emergencies1976-09-0101 September 1976 Requests That Encl Form Be Completed & Submitted by 760915 & Facility Emergency Plan & Implementing Procedures by 761007 in Order for NRC to Prepare Info Packets for Use in Responding to Incidents or Emergencies ML20234E7981976-07-0808 July 1976 Forwards List of Info Required to Complete Review of LWR ECCS Performance to Verify Conformance to 10CFR50.46.Info Must Be Filed on GESSAR-238 & GESSAR-251 Dockets as Part of Std SAR & Be Reviewed Prior to Preliminary Design Approval ML20235E5831976-07-0707 July 1976 Forwards Description of NRC Position on Safety Relief Valve Discharge Piping as Result of NRC Continuing Review of Quencher Safety Relief Valve Discharge Device for Facility. Commitment to Implement NRC Position Requested by 760716 1989-08-18 Category:OUTGOING CORRESPONDENCE MONTHYEARML20055C3921990-02-26026 February 1990
[Table view]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) 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 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 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) 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 IR 05000029/19890141989-08-31031 August 1989 Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted ML20246Q0121989-08-31031 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 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 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 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 ML20247H6891989-07-25025 July 1989 Requests Proposed Design Change to Containment Hydrogen Monitoring Sys,W/Schedule for Implementing Change or Justification for Existing Configuration 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 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 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 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 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 Director'S Decision Re Ohio Citizens for Responsible Energy 10CFR2.206 Petition Re 880309 Power Oscillation Event at Lasalle,Unit 2 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 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 ML20247C0111989-05-12012 May 1989 Forwards NRC Quarterly Status Rept to Congress Covering First Quarter 1989.On 890303,NRC Dismissed Shoreham Intervenors from Licensing Proceeding for Misconduct During Proceeding.W/O Encl ML20246L2741989-05-11011 May 1989 Forwards Anl Draft Rept Re Main Steam Line Breaks in Plants Ice Condenser,Per Util 880613,0907 & 1012 Ltrs & WCAP-10988 & WCAP-10986P,for Review & Comments within 60 Days.W/O Encl ML20246Q0731989-05-0808 May 1989 Forwards Revised Tech Spec Page B 3/4 4-2,clarifying Operability Requirements for PORVs in Manual or Automatic Mode,In Response to Util 881212 Request ML20247A5941989-05-0303 May 1989 Extends Invitation to Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Meeting Agenda Encl ML20247A7781989-05-0303 May 1989 Extends Invitation to Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Meeting Agenda Encl 1990-02-26 |
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/ UNITED STATES YA '
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NUCLEAR REGULATORY COMMISSION
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p'" .r g.I y WASHINGTON, D. C. 20555 o,, .
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- 5 General Electric Company ATIN:
Mr. Ivan F. Stuart, Manager
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Safety and Licensing Section Nuclear Energy Division 175 Curtner Avenue San Jose, California 95114 Gentlemen:
As a result of our continuing review of the " quencher" safety relief valve discharge device for the GESSAR-238 Mark III containment, we have !
developed a position on safety relief valve discharge piping that is described in the enclosure to this letter.
Please provide us, by July 16, 1976, with a commitment to implement the staff position into the GESSAR-238 Nuclear Island design.
If you have further questions concerning the staff position, please contact us.
Sincerely, t -
D. B. Vassallo, Chief Light Water Reactors
- Branch No. 4 Division of Project Management
Enclosure:
As stated s 1 kD fj9870623 THOMAss7-40 PDR
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JUL 0 71970 REQUEbl FOR ADDITIONAL INFORMATION ;
i GESSAR-238 NUCLEAR ISLAND ;
Section 5.2.2.2 of the GESSAR PSAR states that a portion of the safety relief valve discharge piping (i.e., the portion from the pipe anchor inside the drywell.to.the suppression pool) will be designed to quality Group D, which is nonseismic Category I. This classification is unaccept- 3 able for that portion of discharge piping which is in the suppression pool and drywell penetrations since the integrity of this piping is required !
to mitigate the safety relief valve discharge loads and steam condensation loads. Structures, . including the containment wall, basemat and drywell wall, are ; designed based upon those loads which are developed for'a particular safety relief valve discharge device. Therefore, the intregrity of'these j
structures requires that the steam discharged from the safety relief valves I to the piping penetrating the drywell is properly channeled to the safety. l relief valve discharge device in the suppression pool.
Based on the rationale stated above, we have concluded the following: It is our position that all safety relief valve discharge piping in the i suppression pool and the drywell penetrations, all supports for this i piping, the safety relief valve discharge device and the support (s) for the safety relief valve discharge device shall be classified quality Group C ,
and designed to seismic Category.I requirements. I 9
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