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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 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
[Table view] Category:FOREIGN GOVERNMENT/AGENCY TO NRC
MONTHYEARML20135G4521984-02-21021 February 1984 Informs of 840226 FSAR Mission Arrival ML20135G6381982-07-0202 July 1982 Ack Receipt of to Bartolome & Encl Seismic Info. Info Provided by Applicant Re Vibratory Ground Motion & Comments & Findings of Reviewer Requested ML20135G6551981-07-22022 July 1981 Informs of Interest in Participating in Emergency Preparedness Exercises.Exact Dates of Exercises at Power Plants Requested ML20234B7601962-11-0505 November 1962 Informs That Margen Would Be Interested in Pressure & Suppression Principle for Bodega Bay & Whether Commission Has Requested Specific Experiments Re Program 1984-02-21
[Table view] Category:INCOMING CORRESPONDENCE
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 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 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 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 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 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) 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 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 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 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 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 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 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 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 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 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 ML20005E1911989-12-26026 December 1989 Forwards Revised Page 2 Correcting Plant Implementation Date for USI A-24 Requirements in Response to Generic Ltr 89-21 ML18153C0261989-12-26026 December 1989 Responds to Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & surveillance.Motor-operated Valve Program Structured to Allow Similar Approach to motor-operated Dampers.Results Will Be Submitted in 30 Days 1990-03-01
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- w. lands a,d . i niversits*
- '"' "I ' ' #* ** #'N '"I'P'"""d a hientific report
.i Another petitton ageinti es. be r.eid on the malict
- by a facults cornraittee u.hiph tablishment of a SCI millmr" He s aid safe radtauon- was t ritica! of the plant loca.
e ,lPac.f.
i ic . Gas & F;teetnc * *- htattims, v e e no' n!!inent . tion next in the site for a 2r.a. .t inuclear power plant on F$r, :13 uc!t kn.iwe whe n :ne l'UC rme .biutopret Tesearch~cens ' I fd rar- >
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speakers
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/& L he found "a thous.'ing committe:" to aclisit anti plant-j l
p,y DON !;NCDAnt, ,
The wirty of Pacific Cas &l day n:ght's meet!r.g before cbout%nd inaccu 'acies" in, uhat was' petitions, r!cetric Co/r pro;t,:cd nuclear'd persons said flatly Ox Bo. presentedof but v. hen pressed by "This man." Mr. Radu de.
the speakers finally l,clared, " our insults intelligence!
> reactor at Eodega ll:ad is the'de;;a plant is likely to have an nyera new butle cry cf opy.: ion to the{ atomic accident: but they wid'said he thought they were " errors'We have the tlght to dislike any.
thing we want , ."
compnny's plans for a power plant'the safety systems are untricd on i . Imcepretatioc."
there, a full scalc and that the quesdon; ht he did promise the group Mr. Crcndon apologized.
A series of >peakers n a meet. of public protection shou!d be' bat he would ask that the Atomic
'# 3
.Eacrgy Corrmission proceedings speakers and hsues e ing in Santa Rosa Saturday night;more fully explored. ,
ske:ched the haard. M ndiation: A recurring theme was that the on PG&E's construction permit a? Some of the speahcrs and issues and of reactors in gen:ral terms. ',"cxperts" should not be trusted l plication-the next big step--bc raisei Ar.d oiers oudined pads of ac. by the public, but that the public;hed locally. , Dr. Malcoln. Petersm, represen.
tha that include e,.s:ah to the'aould be fully informed of the lic predicted he would be su: jtauve of the Gccater SL Louis !
Senoma County Sul.crvi. sors and! safety and then make a decision cessful in getting the h:arings;Citiecns' Com;nktec for Nuc! cI court action to halt da udlity comJon the planL pnoved from Maryland, where they Informadon and dirxtor of the
,are customarily held. Wash:ngton U.dversity Divisien o!! l par.y's plans until farther nudics!
Mldalght Debate i And he said the AEC's proccel Gasirventerolq;y, o u t1in e d thel l can be made. l The big opposidon in the earlierj 'Ihc relative ca'.m of the 3%.lings would deal with the question battic beforc ',he Ph.he Utiliticsihour meeting was i rippled near of reactor safety, and told the!fccis in m Com: Hision--which he com:dmidnight when Alexander Gren ; crowd that "you can't in youriof life and genetic changes trand-mitted from generatim to genera von cicte rgumc/r , 0.:.t thefdon, the Governors Co.Ordir.ator;cwn doctor, you can't be your own p'.r.at would w.stroy '..: recreation.
ion. l]
sectic and xdendf;c pscatial oflofPuccilon.
Atomicentered' Energy That Development rankled -John Radu,expert."
Santa Scientists and nat ons disa;reci d
tand Radiation the Tbde;;a '..:adland.s and Bodega'the discussion. !1osa. who with Marvin E. Brown, i on(Continued what is a "2,safe" !a There as en chwrver. Mr. Gren A!:cy Ford, are to form a "st'cr c on Pa;e Cr,L 3) lir.rbor.
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un in this country zzo only esu..c i.5 Mill urknown . .
A g "Tne safe dow" "Tha ia: cat of reactor safety dc.
.t.d. don si n."
- he said. "is no don.' of said Dr. Thornton. "is of I
"ljat we mual consider the hvac 3afe devices to prevent accidentscou
,addmg Dis and risks" of atomic ancrgy, in vite nf operator crror."
that the jid;;mcat on the benclits "sholdd not b? c.:.'ie by acci. cat occurred:"Nevertheless." he said. "this l scientists, una arc only r.iuncrs .
{
in. ihe lic!d of nature. Tre &ct boiTk PGLE proposal is for a \
elon rests on you, and tauld nothjeg!Mg-water reactor at Bodega be ddepied to semitin "
i ude: a new kind of con-
- ainment
['
Dr. Tin son & r:ent. system . . . called pres-sity 4 Cahfornia ec.ie.arh Dnerocien-lTimrnton
<lsarc ouNression con s yet sald "whi h i to containmen i tiat at and the!!io Danner Physics.Lahora:nry of;he testcd a worki
! hiedical who num ng reactor." I hned the rnajnr known reac!o/ ar-esdents, including the !!v4 acci- cs
' dent involving a strall ho.l.o cwa b f4 g, hm.2the I(umboldt operau.on ter reactor~. ,
l
' thece Idaho that k!!!cd: Bay plant which PGLE is to pu t Aka '# ,)
kely cause" ofJ* ?*****'.**'*P""""
i PG \
.j' 'W#$suppr&E says it tested the pressure !
ession system in model form i
land la part of the final reactor be- i
- fore gaining AEC approval some i
- two years egs.
' k
, (Tac company says the " unique j desi;;n. which protects operating ' !
, y personne! and the public against
.har.crds resulting from an acciden- !
! tal release of radioactivity, is be- {
lieved to be a significant advance "
in the art" of reactor buf!dingt.
\
Dr. Richard C. Sill. University of NevWa physics professce, who!
outhnad the professional physi!
cisti concern over the dangers of-radir. tion, and who said it is difhcult to get "technicalinforma-tion and evaluation frorn compe-tent scientists who are free from financial or administrative re-straict."
- He saw "just one way you can proceed at this juncture and re-tain traditional democratic institu-
- tions a;id processes. You can de-mand by petition, publicity, and pos- .
albly by legal s,ction that the permit granted to PG1E he held in abey- ,
ance umil the whole subject . . . has Leen prgerly evalusted."
'Ile huct said two possible con- -
- st. hants whd would be independ-ent" are Dr. Ralph E. Lapp, of Arlington. Va., on the reactor.
health and physical hazards part -
of the problem and Dr. Harrison ,
Brown. California Institute of Tech-l l
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. titude." and urged de audience tof be skeptial "of the experts," and L to " remain skepucal of the people ,
who spcAe here tanight."
i lie saw Mr. Grendon in the rear nology geochemistry professor). of the room at the Odd Fellows Max Kortum, Petaluma rancher l hall and asked him to answer a f and a strong figure in the battle question from the floor about the before the PUC carlier this year. possibilities of "cther uses" of the i d the group that Sonoma Coun- Bodega t,ite ether than an electric -.
ervisors were "!ooled con- power plant. "thousand inaccuracies" statement . '
by the word ' steam Mr. Grendon used that as a plat. which brought a kriot of speakers f
then tne permit for the, form from which to explain the around him. He said there were! l P.a anted. official mechanisms for insuring "so many that it is impossible' 1 fn't know then that WM the 'h 4 m 611" them, but on pressure /I plar .s to be atomic. powered. j He intervenes in proceedings be.jfrom a couple of the speakers con.
he said, but now he said he hopea i
' fore the AEC, he said, on beha ;, ceded some might have been " mis. !
a " proper hearing can be heid" of state agencies "to see that noth.!ia:ctPretations.
by the county on the use permit it issued in !Y,0. Ing is overInnked in the way of; But extravagant things were about the " relative has.
Phi!!ip Berry. 0Aland lawye, safety." :said;',
ards of the plar.t. and the " tone 1 who represented the Sierra Club' A " measured risk" is a price of the meeting was not to inform, .j at the PUC hearings, told the of progress, Mr. Grendon said, but to mis-mform." 4 group he finds strength in the and "we must not stifle progress The meeting was sponsored by argument that the use permit was by not doit;; anything." the Northern California Associa.
illegal, on grounds that PG&l; Mr. Pesonen ti,ld the state offi. Lion to Preserve Bodega Head and didn't submit complete plans and cial that he presented "a very specifications on s@ plication. able esse for a very disabled sub. Harbor, the Bodega Bay Chamber of Commerce and the Santa Rosa "Gr.e of the really tragic things." jcet," and said Mr. Grendon an.
Unitarian Fellowship.
he :Jd, "is .the attitude taken by swered " glibly," working "at a the Board of Supervisors in this great tactical disadvantage."
- coun That attitude he defined, Mr, Grendon objected: he wasn't f as "ty." arrogant and presumptuous"!being glib. he said; his answers ,,
l in "not holding one public hear, were " carefully thought out and ing" on the question of the permit. honestly a,poken." ;
David,Pcsonen, organizer of the Nr. Grendon agreed-in answer!
, meeting and a leader in the Sierra to a quotion from Mr. Pesonen- l CLS battle against the plant be.
Ifore the PUC, told the crowd that that he'd heldattempt to get the AEC];
3 hearings locally.
"th:s isn't over yet." But be warned that only testi. I many of " experts" or those directq' '
" Skeptical Attitude" ly involved would be weighed by' '
"The democratic process," la the AEC.
declared, " demands a skeptical at._
_ . _After the meeting he made hisi ,
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l Pcril at Bodcga Mcad Editor-The Public Utilities J Commin:en has approved the P.G. ]
& E. kcoga Head project-virtu- ~
l ally as presented by P.G. & E. and 1 with no safeguards assured for that j scenic cnd unique crea.
The arguments by Dr. Thorn-ton 5aegent (Tbc Chronicle, November il) seemed convincing.
!y to refute the reasons presented of P.G. & E. for its choice of this, . .
location. 1 i
Specifically, the very great i possibility that a temperature in- )
version in the local waterway could -
raise temperature for as much as a few days to a level where much of .
the life would be killed alone i makes the site most incompatible 1 with the needs for producing ]
power . ~ '
ASHTON BROWN.
Kensinbton..ne 3.a u .
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- ^11/14/6 2 USE OfHER SIDE FOR ADDITIONAL REMARK $ g, g. GovtRN.8ENT PRINTlhG OFFICE :19U+22007 4
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LETTER '
f(:c4.&<. it)97%
" . Bodega Bay Reactor .
l Editor-l would like to.make a N
- few clarifying remarks with regard ' . .
- to my statements about the Bodega
- - reactor reported in The Chronicle .
- I
~ .
> i . - November 11. ,
First, t.t no time did I say the
' " plant should not be built;" l said - .
'7 only that we should " pause for a ]
+ lT ', ,
' closer look." . . . '
l
- I described the three major re.
c.'
f.
. actor accidents which are known -
to have occurred in the world since . .-
. the beginning of the atomic rge, -
only one of -which was in the United States , . . Your story said s
"there have been a number of re. ,
, actor failures in the Nation in the - !
past few years," which gives a
- . rather dif ferent impression. I also - ,
' stated that the safety' record of
- the atomic energy industry' has
- been excellent as a whole. / ,
Although both the SL-1 reactor .
at Arco and the proposed P.G.&E.
f
- reactor at Bodega are boiling water
^" +
- types, this is the end of their ,'
similarity. Your story says they
, are "of the = same . basic type," *
< which is an oversimplification. I.
- did not mean to imply that the
. potential for an accident was of a similar level in the two . . . .
I took some pains to state that reactor technology is not my field, and that because the people in
' " Sonoma county were unable to .
- find an expert on reactor safety
+ , viho was willing to talk, I was try. -
Ing to fill the gap. I thing P.G.&E.
should be willing to meet the pub. ' '
l
- lic frankly on the ~ subject of re. . ,
actor safety . . .
l
- ' . THORNTON SARGENT. ' .
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