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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl 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 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) ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210L1061999-08-0202 August 1999 Forwards Insp Rept 50-010/99-13 on 990702-27.No Violations Noted.Insp Examined Activities in Areas of Facility Management & Control & Radiological Safety ML20210D2961999-07-20020 July 1999 Forwards Corrected Info for DNPS Unit 3 MOR for June 1999. Year-to Date Forced Outage Hours Should Have Read 70 Hours Instead of 0 on Page 8.Error Also Affected Cumulative Forced Outage Hours Which Should Have Been 24,761 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) 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) 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 ML20196K3231999-06-30030 June 1999 Informs That Effective 990703,NRC Project Management Responsibility for Dresden,Unit 1 Station Will Be Transferred to P Ray 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 ML20196D3491999-06-18018 June 1999 Forwards Insp Repts 50-237/99-08 & 50-249/99-08 on 990408-0521.Four Non-Cited Violations Noted.Maint on safety- Related Emergency CR Not Performed Well.Low Impact Issues Re Communications Present in Operations,Maint & Security 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 ML20195E3451999-06-0707 June 1999 Forwards 3.5 Inch Computer Diskette Containing Revised File Format for Annual Dose Rept for 1998,per 990520 Telcon Request from Nrc.Each Station Data Is Preceded by Header Record,Which Provides Info Necessary to Identify Data ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20207G2571999-06-0303 June 1999 Informs That Effective 990328,NRC Ofc of NRR Underwent Reorganization.Within Framework of Reorganization,Division of Licensing Project Management Created ML20195B2301999-05-19019 May 1999 Requests Approval of Proposed Changes to QA Topical Rept CE-1-A,rev 66a.Attachment a Describes Changes,Reason for Change & Basis for Concluding That Revised QAP Incorporating Proposed Changes Continues to Satisfy 10CFR50AppB ML20206Q3111999-05-18018 May 1999 Final Response to FOIA Request for Documents.Forwards App a Records Being Released in Entirety ML20206P2431999-05-13013 May 1999 Forwards Insp Rept 50-010/99-09 on 990325-0506.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20206F5381999-04-30030 April 1999 Forwards Magnetic Tape Containing Annual Dose Repts for 1998 for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR20.2206(c).Without Magnetic Tape ML20206B1501999-04-22022 April 1999 Forwards 1998 Occupational Radiation Exposure for Dresden Nuclear Power Station,Units 1,2 & 3. Rept Was Revised to Rept Only Individual Radiation Exposures Greater than 100 Mrem ML20206B2471999-04-20020 April 1999 Informs That SE Kuczynski Has Been Transferred to Position No Longer Requiring SRO License.Cancel License SOP-31030-1, Effective 990412 ML20205K5521999-04-0202 April 1999 Forwards Partially Withheld Security Insp Repts 50-010/99-07,50-237/99-07 & 50-249/99-07 on 990308-12.Two non-cited Violations Identified Involving Failure of Security Personnel to Implement Required Measures ML20205K5841999-03-31031 March 1999 Submits Rept on Status of Decommissioning Funding for Reactors Owned by Comm Ed.Attachment 1 Contains Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) ML20196K7001999-03-31031 March 1999 Forwards Dresden Nuclear Power Station,Units 1,2 & 3 Radioactive Effluent Release Rept,Jan-Dec 1998. ODCM Was Submitted by Ltr in Accordance with Dresden TS 6.9.A.4 of Dresden Tech Specs Section 6.14.A.3 ML20205D7231999-03-26026 March 1999 Informs That Region III Emergency Preparedness Inspector Will Be Provided Copy of Comed Exercise Manual for 990526 Annual Exercise at DNPS ML20205B4241999-03-23023 March 1999 Provides Results of drive-in Drill Conducted on 990208,as Well as Augmentation Phone Drills Conducted Since 981015,as Committed to in Util ML20207L7141999-03-0808 March 1999 Discusses Transmitting Changes Identified as Rev 59 to Security Plan for Dresden Nuclear Power Station,Units 1,2 & 3.Staff Determined That No NRC Approval Required in Accordance with 10CFR50.54(p) ML20207D6831999-03-0101 March 1999 Forwards fitness-for-duty Program Performance Data for Each Comed Nuclear Power Station & Corporate Support Employees for Six Month Period Ending 981231,per 10CFR26.71(d) ML20207E0931999-02-26026 February 1999 Informs That Region III EP Inspectors Will Be Provided One Copy of Exercise Evaluation Objectives for 990526 Annual Exercise at Dresden Station as Enclosure to Ltr for Review. Proprietary Encl Withheld ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20203G3631999-02-10010 February 1999 Forwards Insp Rept 50-010/99-02 on 981218-990129.No Violations Noted.During Insp,Activities in Area of Facility Mgt & Control,Decommissioning Support Activities & Radiological Safety Were Examined ML20203C7001999-02-0202 February 1999 Informs That Mhb Technical Associates No Longer Wishes to Receive Us Region III Docket Info Re Comed Nuclear Facilities.Please Remove Following Listing from Service List ML20202G0621999-01-25025 January 1999 Forwards 1998 Revs to Commitments Rept Made in Docketed Correspondence for Dresden Nuclear Power Station ML20199F3291999-01-14014 January 1999 Ack Receipt of Ltr Dtd 981230,transmitting Changes Identified as Rev 59 to Plant Security Plan,Submitted Under Provisions of 10CFR50.54(p) ML20199E0201999-01-12012 January 1999 Forwards Change to Bases of Dnps,Unit 1 TS Section 3.10, Fuel Handling & Storage. Change Eliminates Reference to Initiation of Generating Station EP Action That Is Incorrect & Not Part of Reason for Min FSP Water Level TS ML20199C8851999-01-11011 January 1999 Forwards Monthly Operating Repts for Dec 1998 for Dnps,Units 1,2 & 3,as Required by TS 6.9.A.5.Year-to-date Generator Hours for Unit 2 for Oct 1998 & Nov 1998 Corrected in Rept ML20206P7411999-01-0707 January 1999 Informs of Delay in Implementation of Strategic Reform Initiative Action Steps.Util Mgt Now Preceeding to Implement Succession Planning Steps for Corporate Ofc & Expects Completion of Action Steps 2 & 3 by 990128 ML20198N7691998-12-30030 December 1998 Forwards Rev 59 to Security Plan for Dresden Nuclear Power Station,In Accordance with 10CFR50.4(b)(4).Rev Withheld ML20198A2531998-12-10010 December 1998 Ack Receipt of Which Transmitted Changes Identified as Rev 57 to Plant Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20198A2511998-12-10010 December 1998 Ack Receipt of ,Which Transmitted Changes Identified as Rev 58 to Plant Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20196E2371998-11-27027 November 1998 Discusses Licensee ,Requesting That Agreement in Be Changed to Reflect Latest NRC Conditions Requiring Licensees to Notify NRC of Transfer of Assets to Affiliates Imposed in Connection with Approval of Transfer ML20196B5871998-11-20020 November 1998 Requests That Svc List for All NRC Correspondence Re Any of Six Comed Nuclear Stations Be Modified Per Attached List.All Other Names Previously Listed Should Be Removed ML20196A4121998-11-19019 November 1998 Forwards Safety Evaluation Accepting Proposed Changes to QA TR CE-1-A,Rev 66,by ,As Modified by Ltrs & 1027.Proposed QA Tr,Rev 66 Continues to Comply with Criteria of 10CFR50,App B ML20195J4271998-11-13013 November 1998 Forwards Insp Repts 50-010/98-18,50-237/98-27 & 50-249/98-27 on 981013-16 & Notice of Violation.Mgt Activities Were Focused Toward Maintaining Effective Security Program ML20195E6451998-11-12012 November 1998 Provides Results of drive-in Drill Conducted on 981007,as Well as Augmentation Phone Drill Conducted on 980917 ML20195F3461998-11-10010 November 1998 Forwards Rev 58 of DNPS Security Plan,Including Listed Changes,Iaw 10CFR50.4(b)(4).Encl Withheld Ref 10CFR73.21 ML20155D2701998-10-27027 October 1998 Forwards Changed Pages from 980423 Submittal Providing Addl Info Marked with Revision Bars & Revised Pages to QA Topical Rept Section 18,for Review ML20154P9051998-10-20020 October 1998 Ack Receipt of 980821 Submittal,Per 10CFR50.54(a),requesting Review & Approval of Proposed Changes That Reduce Commitments in QA TR,CE-1-A.Util Should Refrain from Implementing Subj Changes Until Formal Notification Given 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl 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 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) ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210D2961999-07-20020 July 1999 Forwards Corrected Info for DNPS Unit 3 MOR for June 1999. Year-to Date Forced Outage Hours Should Have Read 70 Hours Instead of 0 on Page 8.Error Also Affected Cumulative Forced Outage Hours Which Should Have Been 24,761 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) 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 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 ML20195E3451999-06-0707 June 1999 Forwards 3.5 Inch Computer Diskette Containing Revised File Format for Annual Dose Rept for 1998,per 990520 Telcon Request from Nrc.Each Station Data Is Preceded by Header Record,Which Provides Info Necessary to Identify Data ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20195B2301999-05-19019 May 1999 Requests Approval of Proposed Changes to QA Topical Rept CE-1-A,rev 66a.Attachment a Describes Changes,Reason for Change & Basis for Concluding That Revised QAP Incorporating Proposed Changes Continues to Satisfy 10CFR50AppB ML20206F5381999-04-30030 April 1999 Forwards Magnetic Tape Containing Annual Dose Repts for 1998 for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR20.2206(c).Without Magnetic Tape ML20206B1501999-04-22022 April 1999 Forwards 1998 Occupational Radiation Exposure for Dresden Nuclear Power Station,Units 1,2 & 3. Rept Was Revised to Rept Only Individual Radiation Exposures Greater than 100 Mrem ML20206B2471999-04-20020 April 1999 Informs That SE Kuczynski Has Been Transferred to Position No Longer Requiring SRO License.Cancel License SOP-31030-1, Effective 990412 ML20205K5841999-03-31031 March 1999 Submits Rept on Status of Decommissioning Funding for Reactors Owned by Comm Ed.Attachment 1 Contains Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) ML20196K7001999-03-31031 March 1999 Forwards Dresden Nuclear Power Station,Units 1,2 & 3 Radioactive Effluent Release Rept,Jan-Dec 1998. ODCM Was Submitted by Ltr in Accordance with Dresden TS 6.9.A.4 of Dresden Tech Specs Section 6.14.A.3 ML20205D7231999-03-26026 March 1999 Informs That Region III Emergency Preparedness Inspector Will Be Provided Copy of Comed Exercise Manual for 990526 Annual Exercise at DNPS ML20205B4241999-03-23023 March 1999 Provides Results of drive-in Drill Conducted on 990208,as Well as Augmentation Phone Drills Conducted Since 981015,as Committed to in Util ML20207D6831999-03-0101 March 1999 Forwards fitness-for-duty Program Performance Data for Each Comed Nuclear Power Station & Corporate Support Employees for Six Month Period Ending 981231,per 10CFR26.71(d) ML20207E0931999-02-26026 February 1999 Informs That Region III EP Inspectors Will Be Provided One Copy of Exercise Evaluation Objectives for 990526 Annual Exercise at Dresden Station as Enclosure to Ltr for Review. Proprietary Encl Withheld ML20203C7001999-02-0202 February 1999 Informs That Mhb Technical Associates No Longer Wishes to Receive Us Region III Docket Info Re Comed Nuclear Facilities.Please Remove Following Listing from Service List ML20202G0621999-01-25025 January 1999 Forwards 1998 Revs to Commitments Rept Made in Docketed Correspondence for Dresden Nuclear Power Station ML20199E0201999-01-12012 January 1999 Forwards Change to Bases of Dnps,Unit 1 TS Section 3.10, Fuel Handling & Storage. Change Eliminates Reference to Initiation of Generating Station EP Action That Is Incorrect & Not Part of Reason for Min FSP Water Level TS ML20199C8851999-01-11011 January 1999 Forwards Monthly Operating Repts for Dec 1998 for Dnps,Units 1,2 & 3,as Required by TS 6.9.A.5.Year-to-date Generator Hours for Unit 2 for Oct 1998 & Nov 1998 Corrected in Rept ML20206P7411999-01-0707 January 1999 Informs of Delay in Implementation of Strategic Reform Initiative Action Steps.Util Mgt Now Preceeding to Implement Succession Planning Steps for Corporate Ofc & Expects Completion of Action Steps 2 & 3 by 990128 ML20198N7691998-12-30030 December 1998 Forwards Rev 59 to Security Plan for Dresden Nuclear Power Station,In Accordance with 10CFR50.4(b)(4).Rev Withheld ML20196B5871998-11-20020 November 1998 Requests That Svc List for All NRC Correspondence Re Any of Six Comed Nuclear Stations Be Modified Per Attached List.All Other Names Previously Listed Should Be Removed ML20195E6451998-11-12012 November 1998 Provides Results of drive-in Drill Conducted on 981007,as Well as Augmentation Phone Drill Conducted on 980917 ML20195F3461998-11-10010 November 1998 Forwards Rev 58 of DNPS Security Plan,Including Listed Changes,Iaw 10CFR50.4(b)(4).Encl Withheld Ref 10CFR73.21 ML20155D2701998-10-27027 October 1998 Forwards Changed Pages from 980423 Submittal Providing Addl Info Marked with Revision Bars & Revised Pages to QA Topical Rept Section 18,for Review ML20154M4291998-10-15015 October 1998 Forwards 1998 Third Quarter 10CFR50.59 Rept of Completed Changes,Tests & Experiments.Completed SEs Compared to Previous Quarterly Repts as Docketed ML20154J4951998-10-0707 October 1998 Forwards Revised Security Plans for CE Listed Nuclear Power Stations,Per 10CFR50.4(b)(4).Changes Do Not Decrease Effectiveness of Station Security Plans.Encl Withheld ML20151Y5101998-09-11011 September 1998 Provides Results of drive-in-drill Conducted on 980804 & Augmentation Phone Drills Conducted Between 980601 & 0831 ML20151Y2931998-09-0909 September 1998 Notifies NRC of Results of Feasiblity Study of Seismically Qualified or Verified Path to Obtain Water from Ultimate Heat Sink & Deliver It to Shell of Isolation Condenser for Each Unit ML20238F7571998-08-28028 August 1998 Forwards fitness-for-duty Program Performance Data for Each of Util Nuclear Power Stations for Six Month Period Ending 980630 ML20237D9771998-08-21021 August 1998 Forwards Proposed Changes to Quality Assurance Topical Rept (QATR) CE-1-A,rev 66,modifying Ref Submittal & Clarifying Certain Changes to QATR Proposed in Util .Page A-1, 6 of 6 of Incoming Submittal Not Included ML20237A8611998-08-0707 August 1998 Requests Approval of Enclosed Qualified Unit 1 Supervisor Initial & Continuing Training Program, Which Ensures That Qualifications of Personnel Are Commensurate W/Tasks to Be Performed & Conditions Requiring Response ML20237A8871998-08-0707 August 1998 Documents Completion of Util Action Items Discussed at 980529 Meeting W/Nrc.Updated Proposal to Consolidate Near Site Emergency Operations Facilities Into Single Central Emergency Operations Facility,Provided ML20236W1311998-07-27027 July 1998 Forwards Response to NRC Re Violations Noted in Insp Repts 50-010/98-15,50-237/98-18 & 50-249/98-18, Respectively.Encl Withheld ML20236T7241998-07-24024 July 1998 Forwards Revised Epips,Including CEPIP-2000 Series Table of Contents & Rev 7 to CEPIP-2121-01, Augmentation Caller Instructions ML20236R2531998-07-16016 July 1998 Summarizes Results of drive-in Drill as Well as Preceeding call-in Drills Conducted Between Each drive-in Drill,As Committed to in 980326 Meeting Between Util & NRC ML20236F8041998-06-29029 June 1998 Forwards Rev 0 to Defueled SAR Dresden Nuclear Power Station Unit 1 Commonwealth Edison Co, Per Requirements of 10CFR50.71(e)(4).Decommissioning Program Plan Is Being Reformatted & Revised Into Defueled SAR SVP-98-170, Advises That AL Misak,License SOP-30832-1,is No Longer Required to Maintain Operator License1998-05-0101 May 1998 Advises That AL Misak,License SOP-30832-1,is No Longer Required to Maintain Operator License ML20247B6521998-04-30030 April 1998 Forwards 1997 Repts for Braidwood,Byron,Dresden,Lasalle,Quad Cities & Zion Nuclear Power Stations.Repts Being Submitted Electronically on Magnetic Tape.W/O Encl ML20217G8841998-04-23023 April 1998 Forwards Proposed Changes to QATR CE 1-A,rev 66.Change Constitutes Major Programmatic Rev to Onsite & Offsite Review Processes as Presently Described in Rept ML20246Q1391998-04-20020 April 1998 Provides Response to Violations Noted in Insp Repts 50-010/98-08,50-237/98-08 & 50-249/98-08.Corrective Actions: Described in Attachment Which Contains Safeguards Matl.Encl Withheld ML20217N3461998-03-31031 March 1998 Provides Basis for Plant Conclusion That Dam Failure Coincident W/Loca Is Beyond Design Basis of Dresden,Units 2 & 3.Licensing Amend Is Not Necessary & Clarifications to UFSAR May Be Made Through Provisions of 10CFR50.59 ML20216H4041998-03-13013 March 1998 Forwards Revs to Byron,Dresden,Lasalle & Zion Station OCDM, Current as of 971231,ODCM Manual & Summary of Changes Included ML20203L2911998-02-27027 February 1998 Provides Revised Schedule for Hazardous Matl Response Drill Described in 971121 Response to Insp Repts 50-010/97-13,50-237/97-13,50-249/97-13 & NOV 1999-09-30
[Table view] Category:PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA TO NRC
MONTHYEARML20244B0011989-03-0808 March 1989 Lists Facts to Consider for Action to Fix or Close GE Reactors Once & for All ML20206D9451988-08-12012 August 1988 Annotated Ltr Expressing Appreciation for Reply to & Assurance in Response to Concerns Pertaining to Operation of Ref Plants ML20245D6611988-08-0808 August 1988 Submits Listed Comments in Response to Re Safety Practice to Schedule Nuclear Plant Operating & Maint Personnel for 16 H Shifts &/Or Excessive Overtime ML20207B1031988-04-18018 April 1988 Urges Cancellation of Paragraphs X & Y of 10CFR50.54 Re Tech Specs & Policy for Operating Nuclear Plants, Respectively ML20155A7431988-02-24024 February 1988 Discusses Safety Problems at Comm Ed Nuclear Power Plants Re Risking Fuel Meltdown by Turning Off Safety Sys as Directed by Util Policy in Emergency If Core Cooling Is Adequate. Vice President Instruction Encl ML20206E0431988-01-29029 January 1988 Expresses Concern Re Two Hazardous Practices at Ref Plants, Including Risking Meltdown by Authorizing Operators to Turn Off Nuclear Plant Safety Sys During Emergency ML20238B7731987-08-0707 August 1987 FOIA Request for Records Explaining Status of Listed LERs Omitted from List,Previously Received from Nrc,Of LERs Filed by Commercial Nuclear Power Plant Licensees for Operating Year 1986 ML20215K2791986-09-0404 September 1986 FOIA Request for Six Categories of Documents Re 1982 Civil Penalty & Ofcs of Investigations & Inspector & Auditor Investigations of Listed Facilities ML20210C5971986-08-14014 August 1986 FOIA Request for DE Harmer to Pw O'Connor Re Dow Nuclear Solvent 1 Used for Chemical Decontamination of Dresden Unit 1 ML20134D5881985-05-0808 May 1985 FOIA Request for Documents Re NRC Proposed Decommissioning Rule & Implementation of Rule to Decommissioned Reactors ML20077A8071983-07-15015 July 1983 Comments on Bangor Daily News & MTV Repts of NRC Order to Shut Down Five Facilities for Insp of Cooling Pipes. Subsequent Rescission Considered Under Pressure from Private Owners of Plants.Requests Stronger Enforcement ML20076M3301983-05-10010 May 1983 FOIA Request for Info Re PNO-III-83-027 Concerning Faulty Valve radiographs,PNO-III-83-026 Concerning Use of Lubricant on Valve Seats & Info on Doe/Nrc 830419-20 Meetings Concerning Geologic Repository in Salt Program ML20003F6481981-03-16016 March 1981 Opposes Facility Being Made Into Radioactive Dump ML20136A9481979-06-0101 June 1979 Comment on Proposed Transfer of 509 Spent Fuel Rods to Quad Cities Nuclear Facility in Cordova,Il.Opposes Transfer on Grounds That Radioactive Waste Cannot Be Disposed of Safely ML19268B8371979-05-0303 May 1979 Forwards Representative Matl Prepared by Citizens for Better Environ & NRDC to Disclose Interest in Issue of Nuclear Power ML19276E1151979-02-0505 February 1979 Forwards Curriculum Vitae for Tamplin & Cochran.Cites Two Precedents Bearing on Issue of Standing:Hunt Vs Wa Apple Advertising Commission,432US333 & VA Electric Power Co, ALAB-522,(1979) ML19269C2951978-12-28028 December 1978 Forwards NRDC & Citizens for a Better Environ Statement of Contentions.Previously Submitted Informally to Applicant & NRC on 781206 to Minimize Challenges ML20084R5281975-09-0909 September 1975 Requests Details of Inoperable Status of Both Diesel Generators for 23 H on 750304-05.Addl Info Re Serious Consequences of Diesel Generator Failure Coupled to Loss of Offsite Power Also Requested ML20235D4461971-06-0303 June 1971 Comments on Idaho Nuclear Safety Repts on Tests 845 - 850 of Semiscale Blowdown & Emergency Core Cooling Project. Concerns Over LOCA & Public Safety Raised.Aec Should Suspend Listed Licenses 1989-03-08
[Table view] |
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ta r', M-t 262 Sheffield Lane q e' , ') P Glen Ellyn, II. 60137 April 18, 1988 ,3 g+ \3 /hs) E' ,egd
,I s k1 Mr. Lando Zech Chairman k
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,7 6
U.S. Nuclear Regulatory Commission ;\a+ (
Washington, D.C. 20555
Dear Lando:
In May 1987, I made a formal Complaint to the Illinois the Commerce Commission against Commonwealth Edison Company, Chicago based utility. I complained that commonwealth Edison risks the health and safety of Illinois citizens when operating nuclear power plants in northern Illinois.
During proceedings 'onducted by the Illinois Commerce I
Commission, Commoni calth Edison's lawyer acknowledged that I w,e b Company officials authorize work in a reactor containment versel with the reactor producing power at Dresden and Quad __3 i Cities Stations. The lawyer also acknowledged that Company q officials authorize into a nuclear operators reactor to turn by a safety off water system being before the pumped system G( .1;W--
has finished its job during an emergency. Commonwealth Edison's lawyer moved that my Complaint be dismissed because the Nuclear Regulatory Commission resolved these issues in 1982 and nuclear saf ety is a matter under federal jurisdiction, i for The Illinois Commerce Commission dismissed my Complaint 1988, the l want of jurisdiction. In a letter dated January 13, write to Chairman of the Commerce Commission suggested that I Region III of the Nuclear Regulatory Commission.
i On January 29, 1988, I wrote to the RegionalI Administrator, cited the Nuclear Regulatory Commission, Region III.
hazardous practices at Commonwealth Edison's nuclear 1986,powerI l
plants. In a follow up letter dated February 24, wrote that employees work near a nuclear reactor producingbut power at the Company's Dresden and Quad cities Stations, risking a fuel meltdown by turning off a safety system can i
occur at any Commonwealth Edison nuclear power plant. ,
Mr. Charles H. Weil, Investigation and Compliance Specialist, acknowledged my letters. In a letter dated March 31, 1978, l Mr. Edward G. Greenman, Director Division of Reactor :
Projects, replied to my complaints.
Mr. Greenman writes that the Nuclear Regulatory Commission approves of employees working in a reactor containment vessel l
when the reactor is producing power at Commonwealth Edison's Dresden and Quad Cities Stations. Mr. Greenman writes that when workers are inside the cont.ainment vessel with the l
8909/86/19-X 1
t reactor producing power, the containment vessel is always deinerted. But Dresden Unit 2 Technical Specification 1.7.A.S.a. requires that the containment vessel be inerted -
onygen concentration reduced to less than 5% with nitrogen -
during reactor power operations. Commonwealth Edison officials therefore violate Operating Licenses and Technical Specifications when they work employees in a reactor containment vessel with the reactor producing power at Dresden and Quad Cities Stations.
Mr. Greenman also writes that the Nuclear Regulatory Commission approves of employees working in a containment vessel with the reactor producing power because Commonwealth Edison officials ensure that the radiation dose limits of 10 CTR part 20 are not exceeded. But 10 CFR part 20 reads, in cddition to complying with stipulated dose limits, officials chell make every reasonable ef f ort to maintain radiation oxposures of nuclear plant employees as low as reasonably ochievable. Because of high radiation levels, General E'eectric engineers designed the boiling water reactors at Dzesden cnd Quad Cities to operate without workers entering the containment vessel during power operations (General
~ Electric Manuals NEDO-10128 and NEDO-10260). Commonwealth Edison officials therefore violate 10 CFR part 20 and plant ,
Operating Licenses, when they expose workers to hazardous radiation by sending them into a reactor containment vessel with the reactor producing power at Dresden and Quad Cities Stations.
Mr. Greenman writes that the Nuclear Regulatory Commission censiders it reasonable to turn off a nuclear plant safety system in an emergency. But Federal Regulations require a nuclear plant safety system to pump water into a nuc1Lar reactor as long as the abnormal condition which activated the system, persists. Commonwealth Edison's policy permits operators to turn off water being pumped into a nuclear reactor during an emergency before the safety system has finished its job. Turning off water being pumped into a nuclear reactor during an emergency, can cause a nuclear fuel meltdown. Commonwealth Edison's policy can cause a nuclear fuel meltdown, release of highly radioactive fission products, and exposure of plant personnel and people nearby to hazardous radiation. Mr. Greenman writes that the Nuclear Regulatory Commission affirms this policy - a policy that can cause an accident like Three Mlle Island.
Regarding the Three Mile Island accident, Victor Stello writes:
" .. had the operators allowed the emergency core cooling L
system to perform its intended function, damage to the core i
would most likely have been prevented." (FORWARD to NUREG- ;
l 0600, fifth paragraph) '
l l -
2
k4 a
- 4 In July, 1979, Mr. Stello conmissioned a Special Review Group to review the lessons learned from the Three Mile Island Cecident. The Special Review Group found if operators had cdhered to Technical Specifications, the high pressure injection system would not have been throttled with the reactor coolant system at low pressure conditions. (NUREG-0616, pgs 87, 86)
Three official investigations confirm that operating Three Mile Island as required by the Operating License and Technical Specifications, would ha , vented danage to the nuclear reactor:
(1) The president's Commission found that reactor core damage would have been prevented if the high pressure injection '
cystem had not been throttled. (Kemeny Commission Finding #4, pg 28)
(2) Calculations by the Special Inquiry Group show that use '
of the high pressure injection system would have prevented overheating of the thel and release of radioactive material.
(Rogovin Vol II part 2, pgh D.2.b, pgs 558,561)
(3) The Special Investigntion by the Senate Subcommittee on Nuclear Regulation isund the cause of severe damage to the reactor core was the inappropriate overriding of automatic safety equipment by plant operators and managers. (Hart ,
Report Chapter 2, Findings and Conclusions, 92, pg 9)
The Nuclear Regulatory Commission issued a new Regulation on June 1, 1983. This Regulation, 10 CFR 50.54 (x) and (y),
authorizes a Senior Operator in a nuclear plant to deviate from technical specifications in an emergency. Technical specifications prescribe settings for nuclear plant safety s ys t e ms . Settings f or automatic protective systems -
emergency core cooling systems for example - are defined so that action of a saf ety system will correct an abnr.rmal condition before fuel design limits are exceeded. Technical Specifications require an automatic safety system to operate l
as long as the abnormal condition which threatens the nue. lear fuel exists in the plant. Following technical speciflcations during an emergency leads to plant safety. Safety will not require a Senior Operator to deviate from technical l
, specifications. Mr. Stello believes that following technical l specifications is the safe way to operate a nuclear plant 1.
t To protect public health and safety from the hazards of .
nuclear radiation when nuclear energy is prodJCing power, I l
j urge you to cancel Federal Hegulation 10 CFR 50.54 paragraphs g,;<
(x) and (y). Enclosed is a draft to replace these paragraphs.
l l v 5 ", ,
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' Sincerely yours, d'; 7 ~~l charles Young 3
t
F 1 On December 31, 1984, the Office of Nuclear Reactor R0gulation established a Technical Specification Improvement Project to consider the entire subject of Technical Specifications and provide recommendations for improvement.
The Group concluded that problems identified with Technical Specifications do not pose an acute safety problem for Operating power reactors. Mr. Stello sent the Report to the Ccmmissioners in a letter dated January 13, 1986. In his lotter, Mr. Stello endorsed the principal finding of the Group. The Group's principle finding is that.there are no ceute safety concerns associated with Technical Specifications which support a mar:iatory program of changes to the Technical Specifications of operating reactors.
Enclosure Copy to:
Ms. Mary Bushnell .
Cha ir ma n Illinois commerce Commission 4
Section 50.54, Title 10, DRAFT - Suggested change to part 50, Code of Federal Regulations.
850.54 conditions of Licenses.
(xi The Atomic Energy Act of 1904 stipulates that a in licensee shall operate a commercial nuclear power plant cecordence with technical specifications. Technical Opecifications define the specific characteristics of a nuclear power plant which ensure that iuel design limits are not exceeded during normal operations and emergencies. By review of a nuclear power plant's safety analysis and technical specifications, the Nuclear Regulatory Commission determines that utilization of special nuclear material will be in accord with the conson defense and security and will provide protection to the health and safety of the public. To prevent fuel damage and protect public health and safety from the hazards of nuclear radiation, a licensee shall follow technical specifications when operating a commercial nuclear power plant.
(y) The Chief Executive Officer of a public utility or other organization licensed to operate a commercial nuclear power plant shall establish pclicy for operating the plant.
The Chief Executive Officer shall direct that the nuclear power plant be operated in accordance with the Operating License and Techrical Specifications."
References:
(1) Atomic Energy Act of 1954, Section 2232 (2) Code of Federal Regulations, Tirle 10, part 50 Sections 50.34, 50.36, 50.46, 50.57, and Criterion 10, APPENDIX A.
M d 'g . . "
262 Sheffield Lane 'O Glen Ellyn, IL 60137 >
February 24, 1988 m o -, , , ,
vr r-o -
J' ~ ~ W" M Mr. Charles H. Weil , g o" ,' ,'
Investigation and compliance Specialist '
s P -
'".1 #. . ' , .st '3 U.S. Nuclear Regulatory Commission, Region III Post Office Box 2027 60138-2027 13 Olen Ellyn, Illinois vM J
Dear Mr. Well:
y My letter of January 29, 1988, describes two safety problems 9 -
ct Commonwealth Edison nuclear power plants. The first - ~~}~ TLv &
working employees near a nuclear reactor producing power -y#> 2-cccurs at Dresden and Quad Cities Stations. Risking a fuel'] -4 y-meltdown by turning of f a safety system, can occur at any Commonwealth Edison nuclear power plant.
The Energy Reorganization Act of 1974, places responsibility for safety on officers of companies operating nuclear power plants. Section 206 of the Act reads that an officer of a firm operating a nuclear plant who learns of a plant defect which could create a substantial safety hazard, r5all
- immediately notify the Nuclear Regulatory Commission.
A Commonwealth Edison Company Policy authorizes operators to turn of f a safety system in an emergency if core cooling is
- adequate. The Policy states that core cooling is adequate if reactor coolant system pressures, temperatures, and levels are stable. But stable reactor coolant system pressures, temperatures and levels do not mean that core cooling is adequate. With reactor coolant system pressure stable but low, temperature stable but high, and level stable but low, the reactor's nuclear fuel can be burning up.
An operator at any Commonwealth Edison nuclear power plant can cause serious damage by following instructions issued by Company officers. Turning off water being pumped into a nuclear reactor by a safety system bef ore the syr tem has i finished its job, can cause the meltdown of a reactor's nuclear fuel.
A copy of the defective Policy is enclosed. I have underlined one of the defects in the Policy.
Very respectfully, bi ul- 9 --n Charles Young Enclosure 1 '/pp.
N1@?6 @@S? .
I copy to:
Mary B. Bushnell, Chairman Illinois commerce Commission Illinois Department of Nuclear Safety I
Lando Zech, Chairman
- U.S. Nuclear Regulatory Commission i.
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VICE PRESIDENT'S INSTRUCTION NO.1-0-17 f SU3 JECT: Company Policy Regarding safe Operations and Adherence to
( Nuclear Procedures and Effective: August 18, 1986 Technical Specifications Cancels: V.P. Instn 1-0-17 ($-23.g3) ,
1 I
This lastruction reaffirma Company policy regarding adherence to nuclear procedures and technical specificathns.
l The prunary concern of the Company with respect to the operation of its ;
nuclear generating plants is to ensure the health and safety of the public as wellInas ;
station personnel. All personnel within the Company share this responsibility. l particular, it is the primary responsibility of the Station Shift Engineer to maintain safe plant operation since it is he who has direct control over all plant operations l during his shift. t l
In order to achieve this safety goal, plant operation is to be within the ~
t boundaries specified in our technical specifications and in adheree:e to procedures and operating orders. Systems which could affect the public health and safety >
(including energency core cooling system, red-waste, etc.) are to remain operable as prescribed in the technical specifications.
It is recognised that circumstances may arise which were not foreseen in the #
For example, a combination of events which l preparation of technical specifications.
were analyzed individually may, taken together, produce results which were not In these i
{ expected or analysed during reviews leading to the technical sp![
cause, rather than prevent, problema. If such circumetances should arise, prudence i I
may require operation outside of the technical specifications, procedures operating orders. l probles and only after careful consideration and orapprovall (1) injury to the public i
Operator immediately available in order to prevent l Company personnel (2) releases off-site above technical specification limits, or (3 j i
desage to equipment Af such damage is tied to a possible adver health and safety.
license conditions and technical specifications is immediately apparent which can provide adequate or equivalent protection.
l Further, it say bt necessary upon occasion to taanorarii, withdraw Thisa averam should_ f j
er systems f rom opey_ation by niacina it in a manual or null-to-lock mode.
r be done only when c anditions are "stable and under centro 1L or when it isThe apparent conditical that continued opet acion would aggravate or worsen the plant condition. :
of "stable and under control" are considered to exist (1) if the radiatio the pressure and temperature in the primary containment are stable, and (2) if thel ,
d is adequate core temperatures and levels.
coolina as _ indicated by stable reactor coo 1~ ant avs j
i i (
- careful consideration, and Ititismust not expected be reviewed and appro that such operations will !
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be conducted for prolonged periods. l l !
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Ill. C. C. Docket 87-0228 Exhibit A I
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VICE PRESIDEST'S 1h5IhuGI40h NO. 1-0-1/ 1
^8h 2 i /
.8418 46)
Whenever a system is withdrawn from operation as outlined, continuing surv:111&nce of ths relevant parameters must be maintained by a licensed Reactor
>peret r to assure the safe operation of the plant until the system can be restored ,
- 9 mormal operability or until it is no longer needed, as prescribed by the
- cchnical specifications.
In all cases noted above, when the technical oper.ification boundaries are raceeded or when a system is withdrawn from operation:
The Station Shift Engineer shall be notified immediately.
. The Shift Technical Advisor / Station Control Roon Enlineer shall be consulted to determine whether immediate shutdown, orderly power reduction, or other course of action is appropriate.
The Station Manager or his designate shall be notified who in turn shall notify the Nuclear Duty Officer in accordance with established procedures. ,
The NRC Operations Center shall be notified by telephone. When time permits, the notification must be made before tha protective action is taken; otherwiss, r.he notification must be made as soon as possible thereafter.
A report shall be promptly made to the Division Vice Frasident -
Nuclear Stations. .
A plant shutdown, immediate or by power reduction, shall be cemmenced unless prolcnged operation under the circumstances is concurred in by the NRC in the case of operating outside the technical specifications. In other cases the Station Manager or his designate may authorize prolonged operation if appropriate.
All station personnel shall be informed of this policy and it shall be lacluded in our training program.
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Vice President
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