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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: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
[Table view] |
Text
GcNE SNYDER M Dwnner. Kiwruere D'N N'
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CONGRESS OF THE UNITED STATES ,, _ w Pusuc wcnMs ANO TRANSPCATATION HOUSE OF REPRESENTATIVES W4 SHINGTON. O.C. 20515 7 """"*"' ""
- saca^a;M^agNe ^aD May 22, 1981 Mr. Joseph M. Hendrie Chairman Nuclear Regulatory Commission .
1717 H Street, N. W.
Washington, D. C. 20555 i
Dear Mr. Chairman:
Enclosed is a letter from my constituent, Max H. Schwartz of Bedford, Kentucky, relating to his concern about the confusion surrounding various reports on the quality of the construction of the Marble Hill Nuclear Power facility being built by Public Service Indiana.
I can assure you Mr. Schwartz is not the only person in the area concerned about this matter and that the app *.ehension reflected in his letter is widespread throughout much of rf District along the Ohio River.
I would appreciate it if you could ha e Mr. Schwartz's letter reviewed and provide me with a response with which to reassure not only him and the others who share his doubts and apprehension, but myself as well -- that safety is not being short-cut at Marble Hill.
Thanking you in advance, I am Sincerely yours,
, A. - ,
U Gene Snyder GS:cmy w cc: Max Schwartz f i 8108170197 810625 CF ADCCK 05000546
%f CF
! M AX H. SCHWARTZ ATTORNEY AT LAW LOUI5VILLE. KY. POST OFFICE BOX 12 B E D FO R D. K Y.
TELEPHONE' BEDFORD. KENTUCKY 40006 TELEPHONE ss2 iso 2 25Hus ARI A CODE 302 ARE A CODE 502 April 21, 1981 Mr. Gene Snyder Member of Congress
- House Office Building i Washington, D.C. 20515
Dear Representative Snyder:
This letter is written in memorandum of our conversation of this date (April 21, 1981) regarding my concerns about the recent developments relative to Public Service Indiana's receiv-ing NRC approval to resume safety-related work at the Marble Hill
, Nuclear Power Plant site.
, Enclosed are copies of two articles which appeared in the
" Madison-Courier."
' In the article dated March 28, 1981, wherein it is reported that PSI has been given approval by the NRC to resume safety-related work, it is stated that two independent consultants retained by the NRC to review existing concrete work have made ,
initial determinations that the existing concrete work is structurally sc.und; however, it is stated that the report of these two constaltants has yet to be completed. As far as I know, the NRC has yet to receive the completed reports. Nothing is said within the article regarding the findings of a third inde~ pendent consultant which was selected by Save the Valley, Dr. Michael Cassaro, of the University of Louisville. The en-closed article of March 25, 1981, seems to indicate that Dr.
Cassaro's initial determination on the matter is that existing
- concrete work is not structurally sound.
It is my understanding that when the NRC agreed to allow independent engineers to inspect the plant site and make reports 4
concerning the structural soundness of critical concrete work, the NRC agreed to not allow PSI to resume safety-related work until such reports had been reviewed. The enclosed articles seemed to indicate that the NRC allowed safety-related work to be resumed prior to reviewing the final reports of the indepen-dent inspectors. From what I can glean from these articles, it appears that the two California independent inspector's initial determination are that existing concete work is sound. On the other hand, Dr. Cassaro's initial findings are that concrete work is not sound.
e 4Y6 u b
IQQi
.s
I Mr. Gene Snyder April 21, 1981 Page Two It appears to me that the NRC has not kept its word on these matters in that it has allowed safety-related word to resume prior to reviewing the final reports by the independent inspectors and :
to add insult to injury, the NRC has allowed safety-related work to be resumed in the face of conflicting reports regarcing the construction of critical areas.
4 I would very much appreciate it if your office would contact the NRC and try to obtain an explanation regarding these matters.
I would very much like to believe that the NRC has the situation at' Marble Hill under control and that I can rest assurred that the NRC is making every effort to insure that the Marble Hill
- fac,ility will be safe. However, if the NRC continues to go back l
on its word and displays every appearance that it is trying to
" cover up" the independent inspectors' reports, I cannot help but lose faith with the NRC.
Your attention to this matter will be greatly appreciated and I'm sure that your continued interest in the matte,r is of value to all concerned.
t With warm personal regards, I am Sincerely yours,
. / -s x
?ch Max H. Schwartz MHS:js Enclosures
. - - , - me --g---- a e- -----+~-e- - -- y--
Wednesday Afternoon's l
)
l MADISON COLRIEE Volume No. 275 Medison,ladiene, Merch 25,1981 Single Cop l t ._-........_............._.,_.,,,.......~,.~,~.~..o -.
student at the junior high. Miss Sheldon and Miss Knowland were alternates for the scholarships presented by Psi loto groups Oscar, Xi and Tri Koppo sororities and the Madison Music Club. (StoH photo by Steve Wfiiter.)
. Rom +
d Marble Hill concrete tests said E
Mass tr inadequate:In epen ent eng.ineer .
Ma _
The independent engmeer selected by concrete and their echoes measured to find construction would be " fairly imminent."
Nye The Valley ta study the concrete tests air pockets.
at Public Service Indiana's nuclear power Save The Valley President Robert Gray Barton Grabow, PSI vice president-plant at Marble Hill claims the tests were said Cassaro told him that 700' concrete public relations, told The Madison Couner madequate. tests would guarantee at least 95 percent today that "the NRC has expressed full Dr. Michael Cassaro nf the University of accuracy. confidence in the reliability of the
.teuisvtlle said the tests need to be ex. Two independent California engmeers evaluation of in-place concrete at Marble wg3p panded to ensure the concrete work meets hired by the NRC to student the concrete Hill, based on findings of two independent George
, federalsaterystandards :est findings are expected to complete ' concrete specialists retained by the NRC.
secunt)
He said m two reports sent to the their reports soon. The NRC said that their Public Service Indiana shares that con- magle Nuclear Regulatory Commission that too study is expected to support test findings fidence."
Alexanc few uitrasound tests were done to assure at that the concrate is safe. In a March 20 letter to Cassaro, " genera ieast a 95 percent chance of accuracy, as Gaston Fiorelli. NRC branch chief of professor of civil engineenng at the emerge require 8 by the NRC. pro;ect inspection in Chicago, said he had University of Louisville, from James G. Bushu Sixty tests, each mvolymg about a etbac already received a verbal report that the Keppler, director of Region 3 of the NRC, chairmA yard of concrete, were done at the plant. two Califorma engineers have concluded said that based on four separate came se ne safety-related structures have about they have no problems with the quality of evaluation methods used by the con- unusual mm cubic yards of concrete, accordmg the concrete. sultants. "We NRC has concluded that the ' Hill that m Cassaro's reports. PSI is currently waiting for word from quality of in-place concrete at Marble Hill unhappt
'the NRC to begin all safety-related work. has teen adequately assessed ..to this ex- TheN Not even 500 rests, the tests said, would The utility has already received per- tent hRC requirements have been met." phatical.
l guarantee with 95 percent accuracy that missinn ta do some safety-rela ted work. The two California engmeers who -- that
. Fioretti sait thst af e.ths, Califaema examined the concrete studiss fortim NRC gg,m as NRC safety standards. In the tests. engmeers' report suprorts the concrete and Roland-C.
were Alfred L. Parme Asked cra.wund waves were beamed into the tests as expected, the resumption of all Hamm.both of San Diego. , Calif. House p 9id, "Hi Ranch Supermarket owner Haston 97 purchases Red & White Food Store g;;
l j Ernest R. Haston, founder of Ranch Haston who was the recipient of the 1981 now does supermarket consulting in over l tupermarkets. Inc., Greensburg, has pur- Greensburg Area Chamber of Commerce 30 states and Canada and owns a farm in i .hased the Red & White Food Store on Community Service Award this month. Decatur County. If then i
Madison's hilltop at 2106 Lanier Drive. founded Ranch Supermarkets. Inc., in Haston is a member of the board of it's that t
, The store, which was also formerly Pick 1965. The corporation now includes five directors of the Decatur County Bank and neglect t!-
l S Pack IGA No. 2. became the Ranch such stores as weil as Sunnycrest the Bible Baptist church. Dr. Frede s upermarketonMondayof thisweek. Distnbutors. Bo-Ka Shop. Circle Pnnting. He and his wife, the former Betty Jo the secon, Hastnn purchased the grocery from E. Ohio River Realty,and Multi-Rand. Schlabach, a nauve of Anderson, have four the Dict:
Ibernaus & Sons. Inc., Vincennes. That A native of Sparta. Tenn.. Haston was children ' - Susan, 29, principal and English.
ompany had purchased it just about a one of nine children, bemg one of a set of teacher at Indiana Christian Academy in Cassidy yearago twins. His parents. Smith and Ethel Anderson: Marc.27, pnnter at Circle Prin- the Univer Haston. now reside m Anderson. ting in Greensburg: Greg. 26. manager of day and
, He graduated from White County High the Bo Ka Fionst Shop m Greensburg and students, .
e Saturday Afternoon's w 1
MADISON COURIER E Volume 144. No. 278 .
.M Medison. Indiene, March 28,1981 single Copy 25g Js' Q
PSI 9 ets NRC aPProyal to resume P(4N e
Marble Hil safety-related work M i
Public Sernet miiman has receved ap- that all safety-related work could now proval from the Nuclear Regulator 7 Com- has concluded that the existing concrete .?
mission to resume safety-related work at progress except that which would cover workisstructurallysound. -
its nuclear power plant at Marbie Hill. concrete areas not yet adequately evaluated and repaired to the satisfaction Two i%t consultants retained PSI expects to resume verk as safety- by the NRC in July 1900 to review existing of inspectors from the NRC's Chicago related constraction at the Marble Hill site regionaloffice, concrete work have also made an initial ;
within a week. Work was halted some 18 determination the existing concrete work months ago because of quality assurance Although Shields didn't expect em- is strtraturally souncf. De report of two and construct 2cn management problems- ployment levels to make immediate, .
dramatic jumps, a gradual increase will California consultants - Rolland C.
"De resumption of safety reisted con- Hamm and Alfred L. Parme -is not ex-struction has been a deliberste pain- be noted. De company now employs 550 peeted to be completed for at leest several stakmg prpcess but we're very confident workers at the plant and will see a peak weeks.
levelof 2,000 3.000 workers.
that the nuclear experience we've added De company projects the first unit of over the last year and a half and the he safety-related areas where PSI will the 33.4 billion power plant wdl go lato changes we've made will assure safe con- re-start work are those which apply to the commercial operation in late 1908 and a struction at Marble Hill," said S.W. nuclear part of the plant such as the con- .-
second unit dueiniste1987.
Shields, semor vice prendent-nuclear for tainment building which holds the nuclear .
reactor,saidPSlofficials. Shields also said current cost estimates i PSL "None d the conditions which remain ,
for the project will result in at least a 25-shouldereste unexpecteddelays." PSI was allowed tb continue its con- percent savings over the life of the nuclear THE SKY V struction schedule for non-safety related Yesterday's authortzation for resump. plant when compared to other after- all studen tion of safety-related work at the plant areas such as a turbine generating natives, including natural gas generation, building, cooling towers and a switchyard students c provides for close scrutiny by NRC in. which was suggested in recent Save De Clark, Sric i
spectors to determme the adequacy d the after the im order. And, the NRC had per- Valleylatters to theuclitY-work. mitted some safety-related work sach as Sommes,1
, The cost of extend:ng the proposed Unrestricted authority to continue the pipmg and electrical insulation to begin in l
December 1980.
Alankan natural gas pipeline from Chicago ' Dottilo, Ar work wdl not be granted until the utility to Madison, the cost of buildmg a natural dy Rezner demonstrates its quality assurance and The. latest authorization also includes gas-fired power plant (which is not curren-construction management programs are removal and replacement of all patches tly permitted by federallaw), the potential m gv previously made to repair surface defects y being adequately implemented,'the NRC said. in the concrete.
effect of decontrol of natural gas prices p, $ e ,
p, and the cost of scrapping most the Marble
- Victor Stello Jr., director of the NRC's An NRC investigation in tm determined Hill equipment all would make the Wes in- . *-
Office of Inspection and Enforcement, said that many patches were made improperiy.
feasible and protubitively expensive, ,
An NRC review of tests and examinations Shields said.
- t. .-'
W h?
Herman Yater to retire Tuesday; W -.
has been PSImana9er since 1959 -i By STEVE WHITE n ; +
Herman Yater will end his many years said. "It was the worst disaster our elec-m the busmess of prending electricity of tric operation ever had in Madison by far " *,
chen he retites Tuesday. He said that businesses and dairies sait E food for the men to est dunrig the tune .,
Yater, manager of the Madison distnet 4 -
j they werein Madison.
1 for Public Service Indiana. bsean hi. .
" - ' ' ' , , , , , , _ , E&
- o I
i i
i CONGRESS OF THE UNITED STATES .
HOUSE OF REPRESENTATIVES WASHINGTON, D.C. 20515 OFFICIA: Bus 4 NESS M.C.
Mr. Joseph M.11endrie ,.
- Chairman Nuclear Regulatory Connaission 1717 11 Street, N. W.
Washington, D. C. 20555 I
LM.._. - .