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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17347B5881990-03-0101 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 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) 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 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 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 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) 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 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 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 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 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 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 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 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 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 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 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 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 1990-03-01
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20055C3921990-02-26026 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) 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) 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) 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 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 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 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 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 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 Director'S Decision Re Ohio Citizens for Responsible Energy 10CFR2.206 Petition Re 880309 Power Oscillation Event at Lasalle,Unit 2 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 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 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 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 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 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 ML20246Q3711989-05-0303 May 1989 Extends Invitation to Attend Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Agenda & Info Re Lodging Arrangements Encl ML20247A5941989-05-0303 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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. /. .g MSPONSE TYPt i RESPONSE TO FREEDOM OF \ ION ^'
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(s ee.e INFORMATION ACT (FOIA) REQUEST g ig ,
00Catt NUMBERise ut esameom KEOUISTER Ms. Ophelia G. Williams PART i.-RECORDS RELEASED OR NOT LOCATED (See checked bones)
No agency records subpect to the request have been located.
No addrtaonal agency records subpect to the request have been located Agency records subpect to the request that are identifed in Appendix A a,e ai,eady ava,iabie ,o, pubiic it.pect,on and co,ymg in tne NRC Pubi,c Documeni Room.
K 1717 H Street. N W., Washington DC-Agency records subsect to the request v' are identifed m Appendix b are being rnade avadaNe for puNic enspection and copying in the NRC Public Document X liioom,1717 H Street, N.W.. Washington. DC, in a folder under the FolA number and requester name.
The nonproprietary verson of the proposaHal that you agreed a accept m a telephone conversation with a member of my staff is now bemg made svalable for public inspection cnd coying at the NRC Pubhc Document Room,1717 H Street. N W., Washington, DC. an a folder under thia FOIA number and requester name.
Enclosed e information on how you may obtem access to and the charges for copying records placed en t4 NRC Pubiec Document Room.1717 H Street. N W, Washington. DC.
Agsney records subpoet to the request are enclosed Any applicable charge for copes of the records provided and payment procedures are noted era the cuhments secton.
l l F.ecords subsect to the request have been referred to another Federal agencytest for revew and direct response to you.
1 in von of NRC's response to the request, no further acton is being taken on appeal letter dated PART ll.A-INFORMATION WITHHELD FROM FUBLIC DISCLOSURE Ceum informaton in the requested iocords e being withheld from pubhc disclosure pursuant to the FOIA exemptions described in and for the reasons stated in Part l', sec-tarta B. C, and O. Any released portions of the documents for which only part of the record is bemg withheld are being made avadable for public enspection and copymg m
- .e NRC Public Document Room.1717 H Street, N.W.. Washington OC. in a folder under this FOlA number and requester name.
Comments Since your request involved 3814 hours0.0441 days <br />1.059 hours <br />0.00631 weeks <br />0.00145 months <br /> af search time instead of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />, you will receive a reimbursement check in the amount of $21.00.
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Appendix A
'FO!A 87-121 DOCUMEflTS ALD.EADY Ifl THE PDR Date Description
- 1. 08/16/82 Memo D. G. Eisenhut to Regional Administrators re:
Proposed Guidance for Calibration and Surveillance Requirements for Equipment Provided to Meet Item II.F.1, Attachments 1, 2 and 3 ~NUREG 0737 ACCESSION NO. 8209270140
- 2. 11/13/85 Memo R. L. Baer to'C. J. Paperiello re: Effluent Radiation Monitor Calibrations.
ACCESSION NO. 8511180296 ,
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Appendix B FOIA 87-121 DOCUMENTS BEING PLACED IN THE PDR Date Description
- 1. 04/29/77 Memo J. H. Sniezek to Multiple Aodressees re: Minimum Shif t Crew Composition w/ enclosures (4 pages)
- 2. 06/08/77 Memo F. J. Nolan to R. C. Knop re: Intent of Technical Specification (TS) Requirement Relating to APRM Flux l Trip at Quad Cities - Memorandum dated 5/25/77, Docket No. 50-294 (1 page)
- 3. 09/08/77 Memo F. J. Nolan to A. B. Davis re: Voluntary Entry l into Technical Specification Action Statements (F14482H1)
(F14529H2) w/ enclosures (7 pages) {
q
- 4. 12/12/77 Memo F. J. Nolan to Multiple Addressees re: Technical Specifications for Minimum Critical Fower Ratio (MCPR) i w/ enclosures (3 pages)
- 5. 08/14/80 Memo R. L'. Spessard to E. L. Jordan re: Testin Requirements for Standby Gas Treatment Systems SGTS) l (AITSF03096680) w/ enclosure (2'pages) '
- 6. 08/27/80 Memo R. F. Heishman to All Members - Reactor Operations and Nuclear Support Branch re: Position on " Licensed !
Power Level" w/ enclosure (3 pages)
- 7. 10/02/80 Memo J. F. Streeter to E. L. Jordan re: Possible Design Deficiency in LaSalle Emergency Diesel Generator Air Starting) w/ attachment (3 pages Systems ( AITS - F03110380)
- 8. 04/16/81 Memo E. B. Blackwood to F. Re.imann re: BWR 5/6 Control i
Rod Drive Scram Testing (AITS F03001881) (2 pages)
- 9. 08/18/81 Memo R. L. Baer to R. L. Spessard re: Testing of Standby Gas Treatment Systems at LaSalle (AITS F03096680H07) (2 pages)
- 10. 01/18/82 Memo R. L. Baer to Multiple Addressees re: Clarification of Provisions of Appendix J in 10 CFR 50 w/ enclosures (4 pages)
- 11. 05/21/82 Memo to File re: Operability of Containment Isolation Valves (2pages)
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Appendix 8 (cont'd) FOIA 87-121 DOCUtiENTS BEING PLACED IN THE PDR l
Date Description k
- 12. !
10/14/82 Memo re: TIA 82-53 Equipment Qualification Requirements for NUREG-0737 Items (2 pages)
- 13. 01/03/83 Memo D. G. Eisenhut to C. E. Norelius re: TIA 82-37, Testing of Nomally Closed Check Valves w/ attachments (4 pages) j 14 01/12/83 Memo D. G. Eisenhut to R. Spessard re: Stopwatches t
Calibration and ASME Requirements on Transients Analyses l (2pages) 1
- 15. 01/28/83 '
Memo C. E. Norelius to D. G. Eisenhut re: Request for j Technical Assistance - Clarification of LaSalle 1 i Technical Specification 3.8.1.2, Action a. (1 page) i
- 16. 01/31/83 Memo C. E. Norelius to 'D. G. Eisenhut re: Request for Technical Assistance - NRR Position on When an Action l Statement is Entered as a Consequence of Failure to i
Perform Surveillance Tests (1 page) l
- 17. 02/09/83 Memo C. E. Norelius to D. G. Eisenhut re: Request for j
i Technical Assistance - NRR Position on Shutdown Time i Allowances When an LC0 is Not Met (2 pages) l
- 18. 02/16/83 l Memo C. E. Norelius to D. G. Eisenhut re: Request j for Technical Assistance - Technical Specification i
Interpretation (AITS F03008283) w/ attachment (5 pages) 1
- 19. 03/11/83 Memo D. G. Eisenhut to C. E. Norelius re: NRR Position of When an Action Statement is Entered as a Conse of failure to Perfom Surveill& e Tests (1 page)quence
- 20. 03/22/83 Memo D. G. Eisenhut to C. E. Norelius re: Clarification of LaSalle 1 Technical Specification 3.8.1.2, Action a.
(2pages)
- 21. 03/23/83 Memo D. G. Eisenhut to C. E. Norelius re: NRR Position i on Shutdown Time Allowances When an LCO is Not Met (2pages)
- 22. 03/29/83 Memo R. L. Spessard to J. M. Taylor re: Quality Assurance Audits to Verify Conformance to Technical Specification Provisions (2 pages) 1 2
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Appendix 8 (cont'd) FOIA 87-121 l
DOCUMEllTS BEltlG PLACED IN THE PDR I Date Description
- 23. 04/01/83 Memo C. E. Norelius to D. G. Eisenhut re: Transfer of Responsibility - Containment Vessel Welds not in Strict Compliance with FSAR Commitments - Perry Nuclear i Power Plant, Units 1 and 2 (2 pages) 24 !
04/20/83 Memo D. G. Eisenhut to C. E. Norelius re: NRR Position i on Component Operability when a Diesel Generator is t Inoperable (2 pages) '
- 25. 04/22/83 Memo D. G. Eisenhut to C. E. Norelius re: Containment Cooling System Operability for the Kewaunee Nuclear Power Plant w/ enclosures (9 pages)
- 26. 05/02/83 Memo C. E. Norelius to D. G. Eisenhut re: Request for Technical Assistance to Delineate Appropriate Licensee Actions Following Failure of Certain ECCS/ Containment Isolation Valves (4 pages)
- 27. 06/29/83 Memo D. G. Eisenhut to C. E. Norelius re: Technical Assistance to Delineate Appropriate Licensee Actions Following Failure of Certain ECCS/ Containment Isolation Valves (4 pages)
- 28. 07/14/83 Memo C. E. Norelius to D. G. Eisenhut re: Zion Technical Specifications (1page) )
- 29. 10/07/83 Memo D. G. Eisenhut to C. E. Norelius re: Containment Vessel Welds not in Strict Compliance with FSAR Commitments - Perry Nuclear Power Plant (Units 1 & 2) w/ attachment (10pages)
- 30. 10/21/83 Memo C. E. Norelius to D. G. Eisenhut re: Request for Technical Assistant-NRR Position on Technical Specifications Interpretation-Primary Containment Allowable Leakage Rates w/ attachment (2pages)
- 31. 10/28/83 Me c D. G. Eisenhut to C. E. Norelius re: Clarification i of the Term " Deputy Plant Manager" as Used in Generic Letter 82-12 w/ enclosure (4 pages)
- 32. 01/30/84 Memo J. G. Partlow to R. L. Spessard re: Quality Assurance SpecificationsAudits to Verify Provisions (Conformance to Technical 1 page) 3
q Appendix B (cont'd) F0IA 87-121 DOCUMENTS BEING PLACED IN THE PDR I
Da te Description
- 33. 02/84 Memo R. L. Spessard to C. E. Norelius re: Testing Requirements of Containment Airlocks at Kewaunee - l Technical Assistance (F03067783) w/ attachment (3 pages)
- 34. 03/20/84 Memo C. E. Norelius to D. G. Eisenhut re: Request for Assistance - Correction / Clarification of a Technical Specification Discrepancy w/ enclosures (6 pages)
- 35. 03/30/84 Memo C. J. Paperiello to F. Pagano re: Interpretation of Paragraph 50.72(b)(1)(v) of 10 CFF Part 50 (F003007984) w/ enclosure (3 pages)
- 36. 04/04/84 Memo D. G. Eisenhut to C. E. Norelius re: Technical Assistance to Establish a Staff Position on a Technical Specifications Interpretations on Prinary Containment Allowable Leakage Rates (TIA-83-102) (3 pages)
- 37. 05/30/84 Memo D. G. Eisenhut to C. E. Norelius re: NRR Technical Assistance - Interpretation of Technical Specifications Applicable to Vital Buses Powered Fror Non-Class 1E Power Source (Davis-Besse) w/ enclosure (3 pages)
- 38. 06/21/84 Memo R. C. DeYoung to Multiple Addressees re: Release of IE Inspection Manual to Licensees and the Public w/ enclosure (4 pages)
- 39. 01/10/85 Memo R. C. DeYoung to Multiple Addressees re: Notifications to the NRC Operations Center and Reporting Events in Licensee Event Reports (3 pages)
- 40. 04/18/85 Memo H. L. Thompson to R. L. Spessard re: Closure Verification of Nortnally Closed Check Valves During Reoperation Testing at Callaway (TIA 83-117) w/ enclosure (3 pages)
- 41. 07/08/85 Memo D. M. Crutchfield to Distribution re: Technical Specification Operability Requirements w/ enclosure (7 pages)
- 42. 07/15/85 Memo H. R. Denton/J. M. Taylor to Multiple Addressees i
re: Relief from Technical Specification LCOs (2 pages) l
- 43. 11/22/85 Memo H. L. Thompson to Multiple Addressees re: I Technical l Specification Interpretation (2 pages)
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l Appendix B (cont'd) F0! A 87-121 DOCUMEf4TS BElitG PLACED 1:1 THE PDR Date Description e
- 44. 12/04/85 Memo E. L. Jordan to W. T. Russell re: Recommended Technical Specification Change Concerning the loss of Control Room Cooling (2 pages)
- 45. 04/28/86 Memo J. A. Hind to H. L. Thompson, Jr., re: Request for Technical Assistance Regarding Post-Accident Noble Gas Effluent Monitorin w/ attachment (2 pages)g Systems at Callaway
- 46. 05/27/86 Memo H. R. Denton to C. E. Norelius re: Technical Specification Interpretation on Snubbers (3 pages) l
- 47. 09/09/86 Memo C. E. Norelius to G. M. Holahan re': Request for Technical Assistance - Additional Clarification of Snubber Technical Specification Requirements (3 pages)
- 48. 02/10/87 Memo H. R. Denton to Multiple Addressees _re: Interim Commission Policy on Technical Specifications w/ enclosure (18 pages)
- 49. Undated l Memo D. G. Eisenhut to C. E. Norelius re: LaSalle Unit 1 - Fast Cold Starts of Diesel Generators (1 page) i 5
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[ g UNITED STATES
( t! NUCLEAR REGULATORY COMMISSION j
...../ WASHINGTON, D.C. 20555 i
July 30,1987 i e
NOTE FOR: T e DocumentJontrol System i FROM: 'at w b#bth-C rcedom of Information & Privacy i Acts Branch Division of Rules and Records
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SUBJECT:
F01A-87-121 FROM OPHELIA WILLIAMS '
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Appendix A to the 7/1/87 letter from Grimsley ' -
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to Williams -egarding the above-referenced i FOIA request erroneously indicated that two i 1 documents are already available in the Public l' .)
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' Document Room. In fact, the two documents were l j available in Central Files only. '
j I have cleared the release of the two documents with NRR and these documents can now be placed in the PDR. l-Please change the file code. fok the two documents '
from Central" Files:to PDR availability. L t
Enclosures:
- 1. 8/16/82 memo from Eisenhut to Regional l Administrators '
- 2. 11/13/85 memo from Baer to Paperiello ,
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cc: Kathleen Ruhlman, PDR l l' s
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Appendix A F0IA 87-121 00CUMEf4TS ALREADY IN THE PDR Date Description
- 1. 08/16/82 Memo D. G. Eisenhut to Regional Administrators re:
Proposed Guidance.for Calibration and Surveillance Requirements for Equipment Provided to Meet Item-II.F.1, Attachments 1, 2 and 3. NUREG 0737 ACCESSION NO. 8209270140 l 2. 11/13/85. Memo R. L. Baer to'C. J. Paperiello re: Effluent
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l Radiation Monitor Calibrations ACCESSION NO. 8511180296 I
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