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Category:CORRESPONDENCE-LETTERS
MONTHYEARSVP-99-181, Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 9906301999-10-20020 October 1999 Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 990630 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217K7011999-10-13013 October 1999 Provides Response to Questions Related to Request for License Amend,Per 10CFR50.90, Credit for Containment Overpressure. Supporting Calculations Encl 05000254/LER-1999-004, Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action1999-10-12012 October 1999 Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action ML20217F6321999-10-0707 October 1999 Forwards Insp Repts 50-254/99-01 & 50-265/99-01 on 990721- 0908.No Violations 05000254/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee1999-10-0707 October 1999 Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee ML20212K9421999-10-0505 October 1999 Informs That NRC Accepts 990513 Inservice Inspection Relief Request CR-31 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr SVP-99-189, Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage1999-09-22022 September 1999 Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage ML20212J0451999-09-21021 September 1999 Forwards Safety Evaluation of Licensee USI A-46 Program at Quad Cities Nuclear Power Station,Units 1 & 2,established in Response to GL 87-02 Through 10CFR50.54(f) Ltr ML20212D8231999-09-20020 September 1999 Informs That Effectieve 991101,NRC Region III Will Be Conducting Safety System Design & Performance Capability Pilot Insp at Quad Cities Nuclear Power Station.Insp Will Be Performed IAW NRC Pilot Insp Procedure 71111-21 ML20212C6961999-09-15015 September 1999 Forwards Insp Repts 50-254/99-17 & 50-265/99-17 on 990823- 0827.No Violations Noted SVP-99-190, Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys1999-09-13013 September 1999 Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys ML20211Q7961999-09-0909 September 1999 Forwards Correction to Administrative Error on Page 8 of NRC Insp Repts 50-254/99-16 & 50-265/99-16,transmitted by Ltr, ML20217H5661999-09-0909 September 1999 Discusses 990907 Pilot Plan Mgt Meeting Re Results to-date of Pilot Implementation of NRC Revised Reactor Oversight Process at Prairie Island & Quad Cities.Agenda & Handouts Provided by Utils Encl ML20211Q6511999-09-0808 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Quad Cities Operator License Applicants During Wk of 000327.Validation of Exam Will Occur at Station During Wk of 000306 ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20211F8251999-08-25025 August 1999 Forwards Insp Repts 50-254/99-15 & 50-265/99-15 on 990816-20.No Violations Noted.Insp Evaluated Effectiveness of Maint Rule Program & Review Periodic Evaluation Specifically Required for 10CFR50.65 ML20211B8691999-08-20020 August 1999 Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed ML20211D1491999-08-19019 August 1999 Forwards Insp Repts 50-254/99-16 & 50-265/99-16 on 990719-22.Staff Identified Major Discrepancy Re Accuracy of Data Submitted to NRC for Protected Area Security Equipment Performance ML20211C7601999-08-19019 August 1999 Confirms NRC Intent to Meet with NSP & Ceco on 990807 in Lisle,Il to Discuss with Region III Pilot Plants,Any Observations,Feedback,Lessons Learned & Recommendations Relative to Implementation of Pilot Program ML20210R7451999-08-13013 August 1999 Forwards Insp Repts 50-254/99-11 & 50-265/99-11 on 990601-0720.NRC Identified Several Issues Which Were Categorized as Being of Low Risk Significance.Two Issues Involved NCVs of Regulatory Requirements SVP-99-147, Notifies of Change to Bases of TS to Licenses DPR-29 & DPR- DPR-30.Change to TS Section 3/4.9 Provides Clarity & Consistency with Sys Design Description in Ufsar,Sections 8.3.2.1 & 8.3.2.2.TS Bases Page,Encl1999-08-13013 August 1999 Notifies of Change to Bases of TS to Licenses DPR-29 & DPR- DPR-30.Change to TS Section 3/4.9 Provides Clarity & Consistency with Sys Design Description in Ufsar,Sections 8.3.2.1 & 8.3.2.2.TS Bases Page,Encl SVP-99-170, Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety1999-08-13013 August 1999 Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety ML20210T9941999-08-13013 August 1999 Forwards Insp Repts 50-254/99-12 & 50-265/99-12 on 990628-0716.Violations Noted SVP-99-154, Notifies NRC That M Price,License SOP-31389,is No Longer Required to Maintain Operator License.Price Was Removed from Licensed Duty on 990729 & Comm Ed Requests License Be Terminated1999-08-13013 August 1999 Notifies NRC That M Price,License SOP-31389,is No Longer Required to Maintain Operator License.Price Was Removed from Licensed Duty on 990729 & Comm Ed Requests License Be Terminated ML20210R9541999-08-10010 August 1999 Informs That During 990804 Telcon Between J Bartlet & M Bielby,Arrangements Were Made for NRC to Insp License Operator Requalification Program at Plant.Insp Planned for Wks of 991018 & 25 ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M5461999-08-0606 August 1999 Discusses 990804 Telcon Between J Bartlet & M Bielby,Where Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant.Insp Planned for Wks of 991018 & 25 ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210L8371999-08-0202 August 1999 Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety Related Motor-Operated Valves ML20210M4691999-07-30030 July 1999 Forwards Insp Repts 50-254/99-14 & 50-265/99-14 on 990713-15.One NCV Was Identified & Discussed in Encl Insp ML20210H4661999-07-29029 July 1999 Forwards Insp Repts 50-254/99-13 & 50-265/99-13 on 990628-0702.No Violations Noted.Insp Consisted of Selective Examination of Procedures & Representative Records, Observations of Activities & Interviews with Personnel 05000254/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73(a)(2)(iv).Rev Includes Cause Codes & Energy Industry Identification Sys Identifiers Which Were Erroneously Omitted in Original Ler.Commitments Listed1999-07-29029 July 1999 Forwards LER 99-002-01,IAW 10CFR50.73(a)(2)(iv).Rev Includes Cause Codes & Energy Industry Identification Sys Identifiers Which Were Erroneously Omitted in Original Ler.Commitments Listed SVP-99-151, Responds to NRC 990701 Telcon RAI Re Licensee Amend Request Re Use of Containment Overpressure to Support NPSH Available for ECCS at Quad Cities Nuclear Power Station,Units 1 & 21999-07-23023 July 1999 Responds to NRC 990701 Telcon RAI Re Licensee Amend Request Re Use of Containment Overpressure to Support NPSH Available for ECCS at Quad Cities Nuclear Power Station,Units 1 & 2 SVP-99-150, Forwards Responses to 990520 RAI Re Annual 10CFR50.46 Rept1999-07-23023 July 1999 Forwards Responses to 990520 RAI Re Annual 10CFR50.46 Rept SVP-99-146, Informs of Termination of License SOP-31132-1,for G Green, as Required by 10CFR50.74(b).Individual Was Removed from License Duty on 9906251999-07-21021 July 1999 Informs of Termination of License SOP-31132-1,for G Green, as Required by 10CFR50.74(b).Individual Was Removed from License Duty on 990625 ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes SVP-99-139, Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage1999-06-30030 June 1999 Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage ML20209B2081999-06-29029 June 1999 Discusses Closure of Response to RAI Re GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity. Rvid,Version 2 Issued as Result of Review of Responses.Info Should Be Reviewed & Comments Submitted by 990901 05000265/LER-1999-002, Forwards LER 99-002-00 for Quad Cities Nuclear Power Station IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Commits to One Listed Action1999-06-25025 June 1999 Forwards LER 99-002-00 for Quad Cities Nuclear Power Station IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Commits to One Listed Action SVP-99-122, Forwards Regulatory Commitment Change Summary Rept, Containing Summary Info from 980601 Through 9906011999-06-25025 June 1999 Forwards Regulatory Commitment Change Summary Rept, Containing Summary Info from 980601 Through 990601 SVP-99-066, Informs That J Reed,License SOP-31034-1,was Removed from License Duty in 990618.Termination of License Is Requested1999-06-25025 June 1999 Informs That J Reed,License SOP-31034-1,was Removed from License Duty in 990618.Termination of License Is Requested SVP-99-103, Informs NRC of Results of Subject Evaluation as Committed to in .Evaluation Consisted of Analytically Demonstrating That Cfu Factor for Rv Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period1999-06-25025 June 1999 Informs NRC of Results of Subject Evaluation as Committed to in .Evaluation Consisted of Analytically Demonstrating That Cfu Factor for Rv Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period ML20196F7921999-06-24024 June 1999 Forwards Meeting Summary,Nrc Meeting Handout & Licensee Handout from 990608 Meeting ML20196E7131999-06-23023 June 1999 Forwards Insp Repts 50-254/99-09 & 50-265/99-09 on 990421-0531.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20196E4821999-06-21021 June 1999 Discusses 990617 Meeting by Region III Senior Reactor Analysts (SRA) in Cordova,Il to Meet with PRA Staff to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA Staff 1999-09-09
[Table view] Category:NRC TO U.S. CONGRESS
MONTHYEARML20058B9701990-10-22022 October 1990 Responds to 900525 Request for Updated Info Re Cracks in Reactor Vessel Head at Unit 2.Review of Fabrication History for Unit 1 Revealed Mismatches W/Manual Back Clad at Three Areas.Supporting Info Encl ML20058M0091990-08-0606 August 1990 Forwards Documents Providing Updates on Cracks in Reactor Vessel Head at Facility.W/O Encls ML20246K8571989-08-25025 August 1989 Discusses NRC Actions in Reponse to Constituent Concerns Re Excessive Overtime Worked by Employees of Plants ML20246M3831989-08-17017 August 1989 Responds to Re Constituent Jt Shaff Concern That Containment Mod to Install Hardened Vents Not Being Immediately Implemented at Plant.Concludes That NRC Need Not Immediately Require All Plants to Install Hardened Vents ML20246M3761989-08-17017 August 1989 Responds to Re Containment Mod to Install Hardened Vents Not Being Immediately Implemented at Plant. Concludes That NRC Need Not Immediately Require All Plants W/Mark I Containments to Install Hardened Vents ML20246C1151989-08-17017 August 1989 Responds to Constituent Jf Shaff Concerns That Implementation of Containment Mod to Install Hardened Vents Not Immediate.Commission Direction of Staff to Initiate Backfit Analyses for Each Mark I Containment Plant Noted ML20248C0681989-04-0606 April 1989 Forwards Responses to Questions Re Shaff Concerns Described in on Mark I Containment Sys & Evacuation Plans for Plant ML20245D6531988-09-14014 September 1988 Responds to Re Requested Response to Concerns of H Nickerson Long Work Hrs for Personnel at Various Central Illinois Nuclear Generating Plants.Related Info Encl ML20213D4301977-05-23023 May 1977 Advises That Investigation Initiated by Region 3 on 770426 Has Not Yet Been Completed ML20235E1491972-08-22022 August 1972 Informs That on 720815,Licenses DPR-29 & DPR-30 Further Amended to Authorize Continuous Operation at 90% Rated Power w/diffuser-pipe Sys in Operation & to Extend Expiration Dates of Licenses to 731030 ML20235F4761972-05-19019 May 1972 Advises That Commission Has Issued Encl Amends 3 & 1 to Licenses DPR-29 & DPR-30,respectively.Amends Authorize Steady State Power Levels & Permit Level of 2,260 Mwt Under Emergency Load.W/O Amends ML20235D7421972-03-23023 March 1972 Informs That Commission Has Filed Encl Supplementary Notice of AEC Consideration of Issuance of Facility Licenses for Both Units W/Ofc of Fr for Publication 1990-08-06
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217F6321999-10-0707 October 1999 Forwards Insp Repts 50-254/99-01 & 50-265/99-01 on 990721- 0908.No Violations ML20212K9421999-10-0505 October 1999 Informs That NRC Accepts 990513 Inservice Inspection Relief Request CR-31 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20212J0451999-09-21021 September 1999 Forwards Safety Evaluation of Licensee USI A-46 Program at Quad Cities Nuclear Power Station,Units 1 & 2,established in Response to GL 87-02 Through 10CFR50.54(f) Ltr ML20212D8231999-09-20020 September 1999 Informs That Effectieve 991101,NRC Region III Will Be Conducting Safety System Design & Performance Capability Pilot Insp at Quad Cities Nuclear Power Station.Insp Will Be Performed IAW NRC Pilot Insp Procedure 71111-21 ML20212C6961999-09-15015 September 1999 Forwards Insp Repts 50-254/99-17 & 50-265/99-17 on 990823- 0827.No Violations Noted ML20217H5661999-09-0909 September 1999 Discusses 990907 Pilot Plan Mgt Meeting Re Results to-date of Pilot Implementation of NRC Revised Reactor Oversight Process at Prairie Island & Quad Cities.Agenda & Handouts Provided by Utils Encl ML20211Q7961999-09-0909 September 1999 Forwards Correction to Administrative Error on Page 8 of NRC Insp Repts 50-254/99-16 & 50-265/99-16,transmitted by Ltr, ML20211Q6511999-09-0808 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Quad Cities Operator License Applicants During Wk of 000327.Validation of Exam Will Occur at Station During Wk of 000306 ML20211F8251999-08-25025 August 1999 Forwards Insp Repts 50-254/99-15 & 50-265/99-15 on 990816-20.No Violations Noted.Insp Evaluated Effectiveness of Maint Rule Program & Review Periodic Evaluation Specifically Required for 10CFR50.65 ML20211B8691999-08-20020 August 1999 Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed ML20211C7601999-08-19019 August 1999 Confirms NRC Intent to Meet with NSP & Ceco on 990807 in Lisle,Il to Discuss with Region III Pilot Plants,Any Observations,Feedback,Lessons Learned & Recommendations Relative to Implementation of Pilot Program ML20211D1491999-08-19019 August 1999 Forwards Insp Repts 50-254/99-16 & 50-265/99-16 on 990719-22.Staff Identified Major Discrepancy Re Accuracy of Data Submitted to NRC for Protected Area Security Equipment Performance ML20210R7451999-08-13013 August 1999 Forwards Insp Repts 50-254/99-11 & 50-265/99-11 on 990601-0720.NRC Identified Several Issues Which Were Categorized as Being of Low Risk Significance.Two Issues Involved NCVs of Regulatory Requirements ML20210T9941999-08-13013 August 1999 Forwards Insp Repts 50-254/99-12 & 50-265/99-12 on 990628-0716.Violations Noted ML20210R9541999-08-10010 August 1999 Informs That During 990804 Telcon Between J Bartlet & M Bielby,Arrangements Were Made for NRC to Insp License Operator Requalification Program at Plant.Insp Planned for Wks of 991018 & 25 ML20210M5461999-08-0606 August 1999 Discusses 990804 Telcon Between J Bartlet & M Bielby,Where Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant.Insp Planned for Wks of 991018 & 25 ML20210L8371999-08-0202 August 1999 Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety Related Motor-Operated Valves ML20210M4691999-07-30030 July 1999 Forwards Insp Repts 50-254/99-14 & 50-265/99-14 on 990713-15.One NCV Was Identified & Discussed in Encl Insp ML20210H4661999-07-29029 July 1999 Forwards Insp Repts 50-254/99-13 & 50-265/99-13 on 990628-0702.No Violations Noted.Insp Consisted of Selective Examination of Procedures & Representative Records, Observations of Activities & Interviews with Personnel ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) ML20209B2081999-06-29029 June 1999 Discusses Closure of Response to RAI Re GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity. Rvid,Version 2 Issued as Result of Review of Responses.Info Should Be Reviewed & Comments Submitted by 990901 ML20196F7921999-06-24024 June 1999 Forwards Meeting Summary,Nrc Meeting Handout & Licensee Handout from 990608 Meeting ML20196E7131999-06-23023 June 1999 Forwards Insp Repts 50-254/99-09 & 50-265/99-09 on 990421-0531.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20196E4821999-06-21021 June 1999 Discusses 990617 Meeting by Region III Senior Reactor Analysts (SRA) in Cordova,Il to Meet with PRA Staff to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA Staff ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20195K1411999-06-16016 June 1999 Forwards Safety Evaluation Authorizing Relief Request RV-23A for Duration of Current 10 Yr IST Interval on Basis That Compliance with Code Requirements Would Result in Hardship Without Compensating Increase in Level of Quality & Safety ML20195J6401999-06-14014 June 1999 Discusses Licensee 990331 Remediation Plan for Welds Susceptible to Intergranular Stress Corrosion Cracking at Quad Cities Nuclear Power Station,Unit 1 & Requests Licensee Address Concerns Discussed & Propose Plan to Implement C/A ML20207H6171999-06-14014 June 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-254/99-01 & 50-265/99-01,per 990217 & 0401 Ltrs Which Transmitted NOV Associated with Insp Repts 50-254/98-23 & 50-265/98-23 ML20206Q3111999-05-18018 May 1999 Final Response to FOIA Request for Documents.Forwards App a Records Being Released in Entirety ML20206S3981999-05-14014 May 1999 Forwards Insp Repts 50-254/99-06 & 50-265/99-06 on 990307-0420.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20206S1131999-05-13013 May 1999 Informs That on 990505 NRC Staff Held Planning Meeting for Plant to Identify Insp Activities at Facility Over Next 6 to 12 Months ML20206S1561999-05-12012 May 1999 Informs of Plans to Conduct Public Meeting on 990608 in Rock Island,Il to Present Planned Changes to NRC Regulatory Processes & Pilot Plant Program for Quad Cities Station ML20206N9621999-05-11011 May 1999 Forwards Insp Repts 50-254/99-08 & 50-265/99-08 on 990419-23.No Violations Noted.Insp Examined Efforts in Addressing Actions Requested in NRC GL 96-01, Testing of Safety Related Logic Circuits ML20206P8511999-05-11011 May 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-254/98-21 & 50-265/98-21.Corrective Actions Will Be Examined During Future Insp ML20206P6811999-05-11011 May 1999 Confirms Discussion Between Members of Staff to Have Mgt Meeting at Qcs on 990608 in Training Bldg,Meeting Open to Public.Purpose of Meeting to Discuss Qcs Performance Described in PPR ML20206F3221999-05-0404 May 1999 Second Final Response to FOIA Request for Documents.Forwards Documents Listed in App B Maintained in PDR Under Request Number 99-134.Documents in App C Being Released in Part (Ref FOIA Exemptions 6) ML20206Q5701999-05-0303 May 1999 Informs That on 990420-21 NRC Senior Managers Met to Evaluate Nuclear Safety Performance of Operation Reactors, Fuel Cycle Facilities & Other Matl Licenses ML20206E0621999-04-30030 April 1999 Refers to Ceco Which Committed to Perform Future FW Nozzle Insps in Accordance with BWROG Alternate BWR FW Nozzle Insp Requirements Rept.Informs of Misunderstanding Re Condition 6 Implications in SER Which Approved Rept ML20205T4281999-04-22022 April 1999 Informs That Encl FEMA Correspondence Was Received on 990322,transmitting FEMA Evaluation Rept for 981007 Annual Medical Drill Conducted at Rock Island County for Quad City Nuclear Power Station.No Violations Were Noted ML20205Q5191999-04-16016 April 1999 Forwards SER Concluding That Quad Cities Nuclear Power Station,Unit 1 Can Be Safely Operated for Next Fuel Cycle with Weld O2BS-F4 in Current Condition Because Structural Integrity of Weld Will Be Maintained ML20205P4641999-04-15015 April 1999 Forwards for Review & Comment Draft Info Notice That Describes Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station Unit 2,Arkansas Nuclear One Unit 2 & Ja Fitzpatrick NPP ML20205P0591999-04-14014 April 1999 Ninth Partial Response to FOIA Request for Documents.App Records Already Available in Pdr.Records in App T Encl & Being Made Available in Pdr.App U Records Being Released in Part (Ref FOIA Exemption 7).App V Records Withheld Entirely ML20205N9541999-04-0909 April 1999 Forwards Insp Repts 50-254/99-03 & 50-265/99-03 on 990308-12.No Violations Noted.Longstanding Materiel Condition Issues Continue to Be Problem,However Progress Had Been Made in Listed Areas ML20205J5691999-04-0707 April 1999 First Partial Response to FOIA Request for Documents. Documents Listed in App a Being Released in Their Entirety ML20205F8031999-04-0202 April 1999 Forwards Draft Info Notice Describing Unanticipated Reactor Water Draindown of Listed Plants ML20205J2891999-04-0101 April 1999 Forwards Insp Repts 50-254/99-01 & 50-265/99-01 on 990121-0306.Violations Identified Involving Failure to Follow Station Procedures for Use of Shutdown Cooling & Failure to Follow Station out-of-svc Tagging Procedures ML20196K9001999-03-31031 March 1999 Forwards Radiation Protection Insp Repts 50-254/99-07 & 50-265/99-07 on 990309-12.No Violations Were Identified.Insp Consisted of Review of Solid Radwaste Processing & Control Program & Radioactive Matls Shipping Program ML20205G5811999-03-26026 March 1999 Advises of Completion of Plant Performance Review on 990201 to Develop Integrated Understanding of Safety Performance. Overall Performance of Plant Acceptable.Plant Issues Matrix & Insp Plan Encl ML20204E0611999-03-18018 March 1999 Discusses Review of Rev 8Q to Portions of Plant Emergency Plan Site Annex ML20207L7511999-03-15015 March 1999 Informs That Staff Offers No Objections to Util 990121 Change to Licenses DPR-29 & DPR-30,App a TSs Bases Sections 3/4.10.K & 3/4.10.L.Changes Clearly Identifies That RHR Scs Not Designed to Be Throttled Sufficiently to Maintain Rc 1999-09-09
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' UNITED STATES '
8 6- NUCLEAR REGUL ATORY COMMISSION .
- WASHINGTON, D. C. 20555
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/ August 17, 1989 The Honorable'. Tom-Tauke United States House of Representatives
~ Washington, D.C.- 20515
Dear Congressman Tauke:
Enclosed with your July 20, 1989. letter to Chairman'Kenneth M. Carr of the Nuclear Regulatory Commission (NRC) was a letter from one of your constituents, Mr. John T. Shaff. Mr. Shaff is concerned that a containment modification to install hardened vents is' not being immediately implemented at Quad Cities Station, Units 1.and 2. The Commission has carefully evaluated this matter and has concluded that it need not immediately require all plants with Mark I containments to install hardened vents.
However, July-11,.1989, the Coinnission directed the NRC staff:
... to initiate plant-specific backfit analyses for each of the Mark I plants to evaluate the efficacy of renuiring IFinstalla-tion'of hardened vents at such plants. .This should be accomplished taking into: consideration the individual plant designs and their respective ' capabilities to withstand overpressurization events.
-Where the backfit analysis supports imposition of. such a. requirement, and after consideration of information from licensees, the staff should proceed accordingly with the imposition of. a requirement that such a plant install a reliable, hardened vent. The objective should be'to complete this process, including ir.stallation of hardened vents where justified, within three years. The staff's backfitting schedule should include consideration of the refueling outage schedule'for each plant in order to ensure that reasonable plant implementation dates are met.:
The direction )rovided by the Commission, which the NRC staff is following, is consistent wit 1 the NRC rule pertaining to backfit requirements. The purpose of the backfit rule is to assure that modifications imposed by the staff will result in a substantial increase in the overall protection of the public health and safety and that the costs of implementation for the licensee are justified in view of the increased protection. This approach protects both the health and safety of the'public and prevents unwarranted expenditures by the utilities and ultimately their rate-payers.
Sincerely,
, //-
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HUMAN RESOURCES-RANKtNG CONGRESS OF THE UNITED STATES u
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SELECT COMMITTEE ON AGING RETIREMENT INCOME AND EMPLOYMfMT-Jul"J 20, 1989~ "A"K'"G "'"0"'T"*""
TASK FORCE FOR THE RURAL ELDERLY A Mr. Kenneth M. Carr Chairman-Nuclear Regulatory Commission 1717 H Street, N.W.
Washington, D.C. 20555
Dear Mr. Chairman:
I recently received the enclosed letter from one of my constituents, Mr. John T. Sha'f f of Camanche, Iowa, regarding the Commonwealth Edison plant at Cordova, Illinois.. Any observations or comments you might care'to share with me as I-prepare a response would be greatly appreciated.
Thank you for your assistance.
Best wishes.
ince ly,
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Tom Tauke Member of Congress TT/es-Enclosure I
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COMMUNICATIONS $HOULD SE DIRs ' 3 TO THE OFFICE INDICATED.
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John T. Shaff - --- _ . ~
RR 1, Box 193
.Camanche, I owf 52730 ~-
(319) . 522-2554 "
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, -July 11, 1989 ~~~ j
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The Honorable Tom Tauke 2244 Rayburn Office Building ___
Washington, D.C. 20515 '"- --- -_..
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Dear Congressman Tauket _J.'_
~~ ~
Enclosed is a copy of an article printed in the Clinton Herald ~
' July 6, 1989. You may . remember our conversations of early th i s ye ar on this subject. Since I live t.pprox imate l y ' three mi l e s f rom the Commonwe al th Edison plant at Cordova, Illinois, I am upset that action.is'not being taken NOW to remedy what is obviously a design.
flaw in the containment system of th'is facility.
According to-the ar t i cl e .the NRC st af f recommended that;the action be taken on all such' plants as soon as 'possi bl e or, pr ac t i cal .
With this-recommendation one would wonder if the,NRC members are more:
interested in utility companies or in the-common good of the public.
There have been numerous articles that would insinuate that the NRC-members have the. utilities in mind'more than anyone else.
I have read that President Bush's nominee to the NRC thought-that people had an unreasonable. fear of atomic energy, I would suggest'that it is more a healthy, reasonable fear based.on the record of a few companies and the-inaction.of the NRC in: matters such as'the one outlined in the enclosed' article.
I am writing this letter also to Senator Grassley and to Senator Harken in the hope that the three of you can either yourselves or with other senators and representatives join in a bipartisan effort'to force the NRC into action on this matter.
As a farmer I cannot easily move to another region if this area is wiped out by a nuclear disaster, the roots of my family on this farm'date back to 1837.
Very truly yours,
% ) v y/ r John T. Sh f
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~RR-1, Box 193
- i Camanche, Iowa 52730 4- 3319).522-2554 July 11, 1989 Mr.,Cordell! Reed-L . Senior Vice President
- Commonwe al th Edison' Company.
Post Office Box 767 Chicago, Illinois 60690
Dear Mr. Reed:
E WeHbriefly met at the visitors center of the Quad Cities 4
[ Nucl ear Pl an t ' January 4, 1989 at a SALP report meeting. After the meet ing you and ' ! vi si ted about the plant in general and par t i cul arl y
. about the containment system.of.the plant. I'l'ive 3.1 miles NNW of .
I :
the plant'.
Enclosed is an article dealing with containment systems of Mark I plantsLin the United States including the Guad Cities facility. I would'like to know if any modifications of the containment system is in the works in light of this announcement and if not, why not?
I am very aware of.the fine'line that you have to tread between
. turning L a prof it for stockholders and maintaining a safe facility for the people living in'the area.
I al so am conv i nced through Ron Higgins, the onsight NRC inspector, that the facility is managed quite well and is not a prime.
candidate for a disaster. However, each year of age that is added to the facility increases the chances for something to happen
. particularly if all maintenance and inspection people 1are not on their toes. For this reason I would hope that you can look at your containment and either feel assured it is very adequate for the needs or else make it that way according to the NRC guidelines.
Again please tend some information as to your stand.on the containment 'i ssu e .
Very truly yours,
- '1 ; --
p John T. Shaff Copies: Congressman Tom Tauke Senator Charles Grassley Senator Tom Harken Governor Terry Branstad
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As a further precaution,the com-=-
% gN $[\D(g sion oroered its staff to speed up sm-plementation of an enstmg NRC re.
EdafOD/I quirement that a Mark I plant .be.
capable of withstanding a totalloss of nuke pIOnf eieanc o wn n uto,aben ,
the reactor. t O enIXed Eeme B*y, a =lwrt er the Public Citizen envu onmental -
group, said the NRC was "buyteg WASHINGTON ( AP)-The Nuclear time" for the nuclear industry by pro-Regulatory Commeon rejected a mising furtherstudy.
staff recommendation that protective Plant owners generally opposed a containment shells on 24 commercial blanket requirement for im-nuclear power reactors be modtfied to lessen the risk of rupture in the event provementsto the MarkI contnimnent system, saying sthey wo'uld not ap -
of asevereaccident. preciably reducethensk of rupture.
The commission said there was no .Of the 24 reactors with Mark I con-need for a blanket requirement for the tainments, four are not operating. '!
changes, although it ordered a plant- $
They are Philadelphia Electne Co.'s by-plrat study of whether hard pipe Peach Bo: tom No. 3, and the Ten- I vents should be added to the contain- nessee Valley Authonty's Browns 3 ment buildings, known as Mark I and :
Ferry No.1,No.2 andNo.3.
made by GeneralElectricCo. I The remainmg plants in the study, The vents would relieve severe theirlocation andownersare: I pressure that would. build up ,if the ,
Brunswick, two ~ reactors at reactor con were damaged'"A contain- i ment failure could }ead to the release ; '
Southport, N.C., Carolina Power &
Ilght Co.: Cooper, Brownsville, Neb.,
of dangerous amounts of radioactivity into the atmosphere. i J,1.1- . ' ~ ' ! Nebraska Public Power District: .
Dresden, two reactors at-Morns, Ill.,
Anti-cucleargroups have urged the -
Commonwealth Edison Co.; Quad NRC to shut down plants with Mark 1 -
containment buildings, saying theys Cities. twoleactors at Cordova!IT Commonwealth Edison and Iowa Gas pose too great a risk to public
- health & Electne Co.; , ,.
and safety. .
Duane Arnold, Palo, Iowa, Iowa' Ther NRC staff earlier tbis year '
Electric Light & Power Co.: Fermi 2i recommended requiring the changes
- Laguna Beach, Mich., Detroit Edison atall24 plants-aboutaquatterof the Co.; Nine Mlle Point It Scriba, N.Y.,
nation's nuclear power stations. - New York Power Authonty; James A.
The commmion' rejected that ap-Fitzpatick,' . Scriba, tN.YJ. Niagara proach . Wednesday, but said it would Mohawk Power Corp.; Edwin1. Hatch, require the hard pipe vents-at any two reactors at Baxley7Ga., Georgia plant deemed by NRC analysts to need them.,It said,the case-by-case ap-Power Co.; . _~~
Hope Creek, Salem,N J.' Public Ser-proach should settle the question <-
for all vice Electric & Gas Co.; Millstone 1 24plantswithinthree years. Waterford, Conn., Northeast Utilities:
The 24 plants were selected because Monticello, ..Monticello,' Minn., Nor. -
their containment buildings are believ- thern States Power Co.; Oyster Creek, ed to be more vulnerable to nipture Toms River, N.J., G PU Nuclear Corp.; -
during a seven reactor ' accident than and Vermont Yankeei Vernon, Vt.,
othereontainmentsystems, .... .
VermontYankee NuclearPo'werCorp.
BTht.comtmssion also'said it would
$pprove irents at any plants that volun- t s
- 3. ,
tarily. chose to install them. Few are expected to do it vohmtsily.'1 . ~ . . -
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} August 17, 1989
-The Honorable-_ Charles E.' Grassley United States Senate Washington, D.C. 20510
Dear Senator Grassley:
Enclosed with your July 24, 1989 letter to Chai man Kenneth M. Carr of the Nuclear Regulatory Commission (NRC) was a letter from one of your constituents,
' Mr. John T. Shaff. Mr. Shaff is concerned that a containment modification to-instal 1~ hardened vents is not being immediately implemented at Quad Cities-Station, Units-1 and 2. The Commission has carefully evaluated this matter and has concluded that it need not immediately~ require all plants with Mark I containments to install- hardened vents- .
However, July 11, 1989,- the Commission directed the NRC staff:
... to initiate plant-specific backfit analyses for each of the Mark I plants to evaluate the efficacy of requiring the installa-tion of hardened vents at such plants. This should be accomplished taking into consideration the individual plant designs and their respective capabilities to withstand overpressurization events.
Where the backfit analysis supports imposition of such a requirement, and after consideration of information from licensees, the staff should proceed accordingly with the imposition of a requirement that-such a plant install a reliable, hardened vent. The objective should be to complete this process, including installation of hardened vents where justified, within three years. The staff's backfitting schedule should include consideration of'the refueling outage schedule for each plant in order to ensure that reasonable plant implementation dates are met.
l The direction provided by the Commission, which the NRC staff is following, is consistent wit 1 the NRC rule pertaining to backfit requirements. The purpose of the backfit rule is to assure that modifications imposed by the staff will L
result in a substantial increase in the overall protection of the public health l and safety and that the costs of implementation for the licensee are justified in view of the increased protection. This approach protects both the health and safety of the public and prevents unwarranted expenditures by the utilities and ultimately their rate-payers.
Sincerely,
/ OCSA FULLTEXT ASCil SCAN g J es M. Tay r f j Acting Executive Director
- for Operations h4y19g-G' '
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- "'*iT.heYon::rable Charles E. Grassley F. Unliibd States Senate August 17, 1989 3
. ,ashington, W D.C. 20510 !
Dear Senator Grassley:
Enclosed with your July 24, 1989 letter to Chairman Kenneth M. Carr of the-Nuclear Regulatory Commission (NRC) was a letter from one of yotr constituents, Mr. John T. Shaff. Mr. Shaff is concerned that a' containment modification to install hardened vents is not being immediately implemented at Quad Cities '
Station, Units 1 and 2. The Commission has carefully evaluated this matter and has concluded that it need not immediately require all plants with Mark I containments to install hardened vents.
However, July 11, 1989, the Commission directed the NRC staff:
... to initiate plant-specific backfit analyses for each of the Mark I plants to evaluate the efficacy of requiring the installa-tion of hardened vents at such plants. This should be accomplished taking into consideration the individual plant designs and their respective capabilities to withstand overpressurization events.
Where the backfit analysis supports imposition of such a requirement, and after consideration of information from licensees, the staff should proceed accordingly with the imposition of a requirement that such a plant install a reliable, hardened vent. The objective should be to complete this process, including installation of hardened vents where justified, within three years. The staff's backfitting schedule should include consideration of the refueling outage schedule for each plant in order to ensure that reasonable plant implementation dates are met.
The direction provided by the Commission, which the NRC staff is following, is consistent with the NRC rule pertaining to backfit requirements. The purpose of the backfit rule is to assure that modifications imposed by the staff will result in a substantial increase in the overall protection of the public health and safety and that the costs of implementation for the licensee are justified in view of the increased protection. This approach protects-both the health and safety of the public and prevents unwarranted expenditures by the utilities and ultimately their rate-payers.
SincerelA@al SM D h m s M I3Y James M. Taylor Acting Executive Director for Operations Similar letters sent to:
The Honorable Tom Harkin The Honorable Tom Tauke United States Senator United States House of 131 E. 4th Street Representatives 314B Federal Building Washington, D.C. 20515
-Davenport, IA 52801 (Document Name - GT 4646)
*PREVIOUSLY CONCURRED
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' July 24, 1989 Nuclear _ Regulatory Commission-
-Congressional' Liaison- .
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' Washington, D.C.s 20555
Dear.' Director:
Enclosed please find,~a letter from John T.-Shaff regarding'the centoiment system:-at t% cordova, Illinois. nuclear plant.
I would appreciate any assistance you could. provide pertaining to this matter. Please mark.your return correspondence to the
' attention of Paul.M. Collison when-responding to my office. ,
Thank you for your attention to my request.
Sincerely, Charles E. Grassley United States Senator CEG/pc Enclosure
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\y RR 1, Box 193
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i Lg7g' (319) 522-2554
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-July 11, 1989 The Honorabl e Charles Grassl ey 6, 135 Hart: Senate Office Building
?!- Washington, D.C. 2051U
-M
Dear' Senator Grassley:
7f Enclosed is a copy of an article. printed in the Clinton Herald
;D - -
July 6, 1989. .Since 1 live approximately three miles from'the M Commonwealth Edison plant at Cordeva, Illinois, I am upset.that
$f action is not being taken NOW to remedy what is obviously a design dj flaw in the containment system of this facility, s;G ly According to the article the NRC staff recommended that the
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action be taken on all such plants as soon as possible or practical.
Ej With this recommendation one would wonder if the NRC members are more
,y interested in utility companies or in the common good of the public.
There have been numerous articles that would insinuate that the NRC
*!) members have the utilities in mind more than anyone else.
5d.
hj I have read that President Bush's nominee to the NRC thought p
that people had an unreasonable fear of atomic energy, I would suggest that it i s more a healthy, reasonable fear based on the
, ;, record of a few companies and the inaction of the NRC in matters such
;_4 as the one outilned in the enclosed article.
3 I am writing this letter also to Congressman Tauke and to
;,j Senator Harken in the hope that the.three of you can either j yourselves or with other senators and representatives Join in a bipartisan effort to force the NRC into action on this matter.
, As a farmer I cannot easily move to another region if this area
,] is wiped out by a nuclear disaster, the roots of my f amily on this fj' farm date back to 1837.
i Very truly yours,
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$ John T. Shaff 4-d 5 1-q
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. John.T. Shaff RR 1, Box 193 Camanche, Iowa 52730 j;
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(319) 522-2554 July 11, 1989 i Mr..Cordell Reed-Senior-Vice President
, Commonwealth. Edison Company Post Office Box 767 Chicago, Illinois 60690
Dear Mr. Reed:
I c We briefly met at the visitors center of the: Quad Cities i Nuclear Plant January 4, 1989 at a SALP report meeting. After the meeting you and I visited about the plant in general and particularly about the containment system of the plant. I live 3.1 miles NNW of the plant.
[ Enclosed i s an ar ti cl e deal ing wi th . con tainmen t systems of Mark
,' I plants in the United States. including the Quad Cities facility. I would l ike to know if any modifications'of the containment system is in the works in light of this announcement and if not, why not?
I am very aware of the fine line that you have to tread between turning a profit'for stockholders and maintaining a safe facility for the people living in the area.
I al so am conv i nced through Ron Hi ggi ns, the onsight NRC inspector, that the. facility is managed quite well'and is not a prime candidate for a disaster. However, each year of age that is added to the facility increases the chances for something to happen-particularly if all maintenance and inspection people are not on their toes. For this reason I would hope that you can look at your containment and either feel assured it is very adequate for the needs or else make it that way according to the NRC guidelines.
L Again please send some information as to your stand on the l' containment issue.
l Very truly yours,
$2 Vl John T. Shaff Copies: Congressman Tom Tauke Senator Charles Grassley Senator Tom Harken l Governor Terry Branstad l
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Ois a further precaution, the commis-Dg. . gb :$ (
sion. ordered its staff to speed tip im-
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0 O f'y . g" 3 P ***"'",that a . Mark..I-plant ,be .
quirement; j M.c. . , . l capable of withstanding a totalloss of tit /ke,piOnfs 1
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. electrical power.without overheating thereactor.< t t .a of.N . -
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,. h B&y, a nhr exput for O na D e n i X e d> .' the Public Citizen' environmental group, said the NRC4as'" buying
' WASRINGTON ( AP)-ThhNuclear. time" for the nuclear' Industry by pro-Regulatory . Commission.. reject,ed a staff recommendation that protective mising furtherstudy., .,, . ;..
. Plant owners generally opposed a containment shells'on 24 commercial nuclear power reactors be modified to blanket requirement k orilfim-f pro {ements to the Mark I containment -
~
the,eyent, lessen the risk ofy ruptur,ejn;4.n p .' sistem,"saying LtheyMuld fdot/aF i of aseversaccident.j c pr.eciably reduce the risk of nipture..
. The commission.said there was no seed for a blanliet requirement f or the 7,,'Of.the'24 tainments, reactors four. are . notwith Mark I con- ~I Toperating.
changes, although it ordered a plint * :
I They are Philadelphia Electric Co's by-plant study.of ,whether hard pipJ !; Peach Bottom No. 3,*and.the Ten- 1 vents should be added to,the contain!.
ment buildings, knownis Mark I and i nessee Valley : Authority's Browns 3 Ferry No. I,No.2 and No. 3. 1 madebyGeneralElectric Co. 9.,. 1 eThe~ remaining plants in the study,
' The vents .wouldirrelieve , severe I theirlocationandawnersare:
. pressure .that would build up if the . .
^
' Brunswick, two ' reactors - at ,
reactof dBre ie'fe dhiIgsd. A contain-T-Southport,' N.C..' Carolina Power & J*
ment failure could , lead to the release f '
13ght Co.; Cooper,"Brownsville, Neb.,
of dadgero~us' amounts of hdioactivity / Nebraska Public. Power District; Intotbeatmosphere.W fVl3.Q M M. Dresden, two reactors at Morris, Ill., '
t.Adti-nuclear 4;roups have urged the f d NRC to shut down plants with; Mark I p Common, wealth Edison' Co.[ ,9ua,d Citiesc twoTreactors'at Cordova,Jit, containment -buildings, . saying < theyW Commonwealth Edison uno lowa Gas pose too' great Frisk to public health z.; & Electne Co.; : ., . . '" !
andsafety. ' I ~ " . . ..M [." 7hane Arnold, Palo,' Iowa.il'owa*
J Thet NRC staff earlier. thisl year, 1j '
Electric Light & Power Co.i Fermi 2, recommended' requiring the' change 8 i IAguna Beach, Mich.; betroit Edison at all 24 plants - about a quarter of the Co.;.Nine. Mile, Point >1!.Scriba, N;Y.,
nation's nuclear power stations. DM W 'New York Power Authority; James A '.
4The' commission ' rejected that'ap'1 Fitzpatick, ~ Scriba, tN.Y.'. Niagara proach. Wednesday, but said it would 14ohawk Power Corp.; Edwin!. Hatch, require the hard pipe; vents at any. '} two reactors at,BaxleyjGa., Georgia plant deemed by NRC analysts to need' Power Co.; .
"~ ^' -
them.;It'said,the case-by. case apt.y proach should settle the question ior all (?
C Hope Creek, Salem', N.J.', Public Ser; {
vice Electric & Gas Co.; Millstone 1, 24 plants within'threc years. ' T- Waterford, Conn., Northeast Utilities; aThe 24 plants were selected because Monticello, .Monticello? Minn.? Nor- -
their containment buildings are believ f thern States Power Co.; Oyster Creek, ed to be more vulnerable to rupture {
~
Toms River, N.J., GPU Nuclear Corp.; ;
during a severe reactor accident,than,a and Vermont YankeeT Vernon,' Vt.,
othercontaintuent,sygems. .
Vermont Yankee N ucicar Power Corp.u ' '
OTheicomnussion.,also'said it would ' ,
~
z approve vents at any plants that (olun t ci' ,
tarily chos'e to install them. Few are {
expected to do it v6hssta'rilyM i s.. - .
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