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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20154N0091998-10-13013 October 1998 Forwards Notice of Docketing & Acceptance Review of License Amend Application for GE - Morris Operation ISFSI & Associated Tss.Notice Has Been Forwarded to Ofc of Fr for Publication ML20154J5311998-10-0909 October 1998 Informs That NMSS Is Updating Distribution List for Correspondence Associated with GE - Morris Operation Isfsi. Licensee Is Requested to Verify That Address Info Is Correct by 981110 ML20151R6621998-08-25025 August 1998 Informs That Pg Brochman Has Assumed Project Mgt Responsibilities for Gemo Isfsi.All Communications W/Nrc Should Be Directed to Brochman as Point of Contact for Facility ML20056F8781993-08-23023 August 1993 Acks Receipt of Transmitting Changes Identified as Rev NEDS-14507-D3 to Morris Operation Physical Plan Per 10CFR72.186(b).Changes Consistent W/Provisions of 10CFR72.186(b) & Acceptable ML20058M0361993-04-12012 April 1993 Partial Response to FOIA Request for Documents.Forwards Records in App L Which Are Being Withheld Partially for Listed Reasons,(Ref FOIA Exemptions 5) ML20126J1831992-12-30030 December 1992 Ack Receipt of in Response to NRC , Clarifying Concerns Re GE Morris Groundwater Monitoring Evaluation.Evaluation Acceptable ML20126J2151992-12-0303 December 1992 Provides Update & Requested Amplifying Info on Issues Discussed in NRC Re Description of Existing Well Functional Capabilities,Drinking Water Analysis,Aquifer Performance & Vault & Basin Leak Detection Sys ML20062C7851990-09-27027 September 1990 Responds to NRC Re Violations Noted in Insp Rept 72-0001/90-01.Corrective Actions:Procedures Reviewed W/ Personnel Re Review of Special Work Permits ML20059D8831990-08-29029 August 1990 Forwards Safety Insp Rept 72-0001/90-01 on 900212-14,0530,31 & 0601 & Notice of Violation ML20246P4731989-07-19019 July 1989 Forwards NRC Info Notice 89-045,Suppl 1, Metalclad,Low Voltage Power Circuit Breakers Refurbished W/Substandard Parts. No Action or Response Required ML20244B7331989-04-13013 April 1989 Forwards Safety Insp 72-0001/89-01 on 890227-0303 & Forwards Notice of Violation ML20246M0681989-03-17017 March 1989 Forwards GE Annual Rept for 1988 ML20246L5071989-03-0202 March 1989 Advises That 890216 Rev to Physical Security Plan Consistent W/Provisions of 10CFR72.33(e) & Acceptable ML20151S9321988-07-27027 July 1988 Responds to Violations Noted in 880720 Insp Rept.Corrective Actions:Technician Reinstructed Re Protective Clothing ML20196E1501988-02-19019 February 1988 Forwards Safety Insp Rept 72-0001/88-01 on 880111-15.No Violations Noted IR 07200001/19870011987-05-0808 May 1987 Forwards Insp Repts 72-0001/87-01 & 30-29361/87-01 During Nov 1986 Through 870424 & Notice of Violation from 861006-10 Insp.Insp on 870210-13 & 18-20 Also Discussed.No Response Required Since Corrective Actions Already Taken ML20210D2341987-01-16016 January 1987 Forwards Changes to Physical Security Plan,Correcting Reporting Requirements Found in Error During NRC Insp. Changes Withheld (Ref 10CFR73.21) ML20212E4731986-12-29029 December 1986 Forwards Safeguards Insp Rept 72-0001/86-05 on 861215-16 & Notice of Violation.Notice of Violation Withheld (Ref 10CFR73.21) ML20213G0401986-11-0505 November 1986 Forwards Insp Rept 72-0001/86-02 on 861006-10.Decision on Enforcement Action Re Violations Forthcoming in Separate Correspondence ML20197A4971986-10-21021 October 1986 Confirms 861028 Meeting at Region III Ofc in Glen Ellyn,Il to Discuss Results of Radiation Protection Insp Conducted on 861006-10,proposed Corrective Actions & NRC Enforcement Options ML20211E5261986-10-17017 October 1986 Advises That 860917 Changes to Physical Security Plan Consistent W/Provisions of 10CFR72.33(e) & Acceptable ML20209A7941986-08-29029 August 1986 Confirmatory Action Ltr Re 860828 Telcon Discussing Proposed Measures to Be Taken to Ensure That External Package Contamination Levels Do Not Exceed DOT Limits During Transport ML20212P4331986-08-27027 August 1986 Confirmatory Action Ltr Re 860827 Telcon Concerning High Levels of Removable Contamination Measured on Surface of IF-300 Casks on 860729 & 0819.NRC Understands That Casks Will Not Be Released Until Acceptable Measures Taken ML20203E2271986-07-18018 July 1986 Forwards Safety Insp Rept 72-0001/86-01 on 851119-860715.No Violations Noted ML20155F6711986-04-18018 April 1986 Advises That 860404 Rev to Physical Security Plan Consistent W/Provisions of 10CFR72.84(b) & Acceptable.Future Revs to Plan Should Be Sent to Region III at Listed Address ML20197E9081986-04-0404 April 1986 Forwards Changes to Physical Security Plan.Encl Withheld (Ref 10CFR2.790) DD-85-16, Advises That Time for Commission to Review Director'S Decision DD-85-16 Expired.Commission Declined Review. Decision Became Final Agency Action on 851210.Served on 8512131985-12-13013 December 1985 Advises That Time for Commission to Review Director'S Decision DD-85-16 Expired.Commission Declined Review. Decision Became Final Agency Action on 851210.Served on 851213 ML20138B2401985-12-0606 December 1985 Appeals NMSS 851104 Denial of Illinois Safe Energy Alliance 850829 Petition Seeking Detailed Environ Review of GE Interim Spent Fuel Storage Facility in Morris,Il.Facility Never Accorded Review Envisioned Under NEPA & 10CFR51 ML20137Z1131985-12-0404 December 1985 Requests Review of Director'S Decision Denying Request for Federal EIS for GE Morris Operation Due to Numerous Deficiencies in Decision,Including Disregard for Recent Changes in Scope & Nature of Operation ML20137L9771985-11-21021 November 1985 Requests Extension Until 860101 for NRC Review of Illinois Safe Energy Alliance Request for Petition That EIS Be Prepared for Facility Operation ML20138Q9431985-11-14014 November 1985 Requests Review of Director'S Decision Under 10CFR2.206 Denying 850829 Petition for Preparation of EIS Re GE Morris Operation.Natl Environ Groups Indicated Intention to Urge Review of Decision ML20138R1501985-11-12012 November 1985 Supports Illinois Safe Energy Alliance 850829 Petition Re License Granted to GE on 820504 for Spent Nuclear Fuel Storage Facility.Nrc Action on EIS Requested ML20138Q9181985-11-12012 November 1985 Requests Reversal of Director'S Decision 85-16 Urging Preparation of EIS Re GE Morris Operations Prior to Receipt of Addl Irradiated Fuel.Facility Location Close to Metropolitan Area Indicates Need for EIS IR 05000313/20100071985-10-17017 October 1985 Forwards Insp Rept 72-0001/85-02 on 850313-1007.No Noncompliance Noted ML20209G3271985-09-13013 September 1985 Ack Receipt of Transmitting Changes to Physical Security Plan.Changes Consistent w/10CFR72.84(b) & Acceptable.Amend Fee Will Be Returned ML20128G6091985-06-28028 June 1985 Informs of Acceptance of 840531 & 850531 Annual Updates to Consolidated SAR for Morris Operation.No Comments Offered ML20055B3321982-07-0808 July 1982 Notifies of No Change in Status of Fuel Stored at Facility in May & June.Current Status Table Encl ML20054J4491982-06-22022 June 1982 Informs That No Addl Category 1H(a) Fee Will Be Required for 790227 Renewal Application for License SNM-1265.Max Fee,Per 10CFR170.31,paid ML20151B5721981-02-0909 February 1981 Forwards DM Dawson to Ofc of Nuclear Matl Safety & Safeguards ML20151B5771981-02-0404 February 1981 Forwards Revised Pages & Addl & Updated Financial Info Re License Amend.Sec Form 10-K for 1980 & GE 1980 Annual Rept Will Be Forwarded When Available ML20148Q5291981-01-12012 January 1981 Forwards Amended Application for Renewal of License SNM-1265 ML20148H4941980-11-14014 November 1980 Forwards 801112 Fr Notice of 10CFR72 Issuance Per NRC Commitment Made in 801003 Motion to Set Aside Schedule for Summary Disposition ML20148D2291980-08-0606 August 1980 Forwards 780810 Memo Re Meeting Between Southwest Nuclear Co & Nrc,As Followup to 800804 Telcon ML20126C7371980-03-0707 March 1980 Ack Receipt of Re Changes to Physical Security Plan.Changes Acceptable.Encl to Ltr Withheld (Ref 10CFR2.790) ML20126C1861980-03-0606 March 1980 Requests to Have Name Put on Mailing List Re Morris,Il Nuclear Dumping Site ML20126B7901980-03-0303 March 1980 Notifies of Fee Refund Re 781015 Request to Amend Certain Conditions of License SNM-1265.No Licensing Action Taken on Reviewing Request.Request Has Been Considered Closed ML20126C9941980-02-20020 February 1980 Opposes Choice of Morris,Il as Dumping Site for Nuclear Waste.Suggests That Waste Disposal Be Part of Nuclear Plant Site 1998-08-25
[Table view] Category:NRC TO VENDOR/MANUFACTURER
MONTHYEARML20059D8831990-08-29029 August 1990 Forwards Safety Insp Rept 72-0001/90-01 on 900212-14,0530,31 & 0601 & Notice of Violation ML20246P4731989-07-19019 July 1989 Forwards NRC Info Notice 89-045,Suppl 1, Metalclad,Low Voltage Power Circuit Breakers Refurbished W/Substandard Parts. No Action or Response Required ML20246L5071989-03-0202 March 1989 Advises That 890216 Rev to Physical Security Plan Consistent W/Provisions of 10CFR72.33(e) & Acceptable ML20196E1501988-02-19019 February 1988 Forwards Safety Insp Rept 72-0001/88-01 on 880111-15.No Violations Noted IR 07200001/19870011987-05-0808 May 1987 Forwards Insp Repts 72-0001/87-01 & 30-29361/87-01 During Nov 1986 Through 870424 & Notice of Violation from 861006-10 Insp.Insp on 870210-13 & 18-20 Also Discussed.No Response Required Since Corrective Actions Already Taken ML20212E4731986-12-29029 December 1986 Forwards Safeguards Insp Rept 72-0001/86-05 on 861215-16 & Notice of Violation.Notice of Violation Withheld (Ref 10CFR73.21) ML20213G0401986-11-0505 November 1986 Forwards Insp Rept 72-0001/86-02 on 861006-10.Decision on Enforcement Action Re Violations Forthcoming in Separate Correspondence ML20197A4971986-10-21021 October 1986 Confirms 861028 Meeting at Region III Ofc in Glen Ellyn,Il to Discuss Results of Radiation Protection Insp Conducted on 861006-10,proposed Corrective Actions & NRC Enforcement Options ML20211E5261986-10-17017 October 1986 Advises That 860917 Changes to Physical Security Plan Consistent W/Provisions of 10CFR72.33(e) & Acceptable ML20209A7941986-08-29029 August 1986 Confirmatory Action Ltr Re 860828 Telcon Discussing Proposed Measures to Be Taken to Ensure That External Package Contamination Levels Do Not Exceed DOT Limits During Transport ML20212P4331986-08-27027 August 1986 Confirmatory Action Ltr Re 860827 Telcon Concerning High Levels of Removable Contamination Measured on Surface of IF-300 Casks on 860729 & 0819.NRC Understands That Casks Will Not Be Released Until Acceptable Measures Taken ML20203E2271986-07-18018 July 1986 Forwards Safety Insp Rept 72-0001/86-01 on 851119-860715.No Violations Noted ML20155F6711986-04-18018 April 1986 Advises That 860404 Rev to Physical Security Plan Consistent W/Provisions of 10CFR72.84(b) & Acceptable.Future Revs to Plan Should Be Sent to Region III at Listed Address IR 05000313/20100071985-10-17017 October 1985 Forwards Insp Rept 72-0001/85-02 on 850313-1007.No Noncompliance Noted ML20209G3271985-09-13013 September 1985 Ack Receipt of Transmitting Changes to Physical Security Plan.Changes Consistent w/10CFR72.84(b) & Acceptable.Amend Fee Will Be Returned ML20128G6091985-06-28028 June 1985 Informs of Acceptance of 840531 & 850531 Annual Updates to Consolidated SAR for Morris Operation.No Comments Offered ML20054J4491982-06-22022 June 1982 Informs That No Addl Category 1H(a) Fee Will Be Required for 790227 Renewal Application for License SNM-1265.Max Fee,Per 10CFR170.31,paid ML20126C7371980-03-0707 March 1980 Ack Receipt of Re Changes to Physical Security Plan.Changes Acceptable.Encl to Ltr Withheld (Ref 10CFR2.790) ML20126B7901980-03-0303 March 1980 Notifies of Fee Refund Re 781015 Request to Amend Certain Conditions of License SNM-1265.No Licensing Action Taken on Reviewing Request.Request Has Been Considered Closed ML20147E5451978-12-11011 December 1978 Forwards Working Copy of Most Recent Rev of Draft Guide 3.44 Standard Format & Content for SAR to Be Incl in a Lic Appl for Storage of Spent Fuel in an Independent Spent Fuel Storage Installation. W/O Encl ML20147B7191978-12-0101 December 1978 Follows Up 781111 Telephone Conversation.Requests Clarifying Statement to Describe Transfer of Direct Loads on Wall in Finite Element Model & Confirmation That Neither Pool Will Be Drained Intentionally During Oper ML20147C0071978-11-17017 November 1978 Responds to 780922 Appl & Grants Amend to Special Nuc Matl Lic SNM-1265,Section 6-A & Conditions 14 & 16 Re Fuel Assemblies & Stored Fuel ML20148G6691978-11-0303 November 1978 Requests Addl Payment of Fee for Processing Separate Amend to License SNM-1265 ML20197C6271978-10-18018 October 1978 Review of Amend Appl Re Lacrosse BWR Fuel assemblies,790922 Gen Elec Ltr to Nrc,Is in Progress.Questions Re Fuel Arrangement & Discrepancy in Calculations Are Propounded ML20148K7051978-10-18018 October 1978 Responds to 780920 Request by Licensee for Info Re Safety Data for Renewal Appl for Lic SNM-1266 for GE Morris Oper. Present Csar,Updated to Incl All Detailed Info Specified in Proposed Reg Guide Under Each Section,Will Suffice ML20150B9631978-09-26026 September 1978 Ack Receipt of 780918 Transmittal of Safeguards Contingency Plan.Requests Payment of $6200 Fee 1990-08-29
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20154N0091998-10-13013 October 1998 Forwards Notice of Docketing & Acceptance Review of License Amend Application for GE - Morris Operation ISFSI & Associated Tss.Notice Has Been Forwarded to Ofc of Fr for Publication ML20154J5311998-10-0909 October 1998 Informs That NMSS Is Updating Distribution List for Correspondence Associated with GE - Morris Operation Isfsi. Licensee Is Requested to Verify That Address Info Is Correct by 981110 ML20151R6621998-08-25025 August 1998 Informs That Pg Brochman Has Assumed Project Mgt Responsibilities for Gemo Isfsi.All Communications W/Nrc Should Be Directed to Brochman as Point of Contact for Facility ML20056F8781993-08-23023 August 1993 Acks Receipt of Transmitting Changes Identified as Rev NEDS-14507-D3 to Morris Operation Physical Plan Per 10CFR72.186(b).Changes Consistent W/Provisions of 10CFR72.186(b) & Acceptable ML20058M0361993-04-12012 April 1993 Partial Response to FOIA Request for Documents.Forwards Records in App L Which Are Being Withheld Partially for Listed Reasons,(Ref FOIA Exemptions 5) ML20126J1831992-12-30030 December 1992 Ack Receipt of in Response to NRC , Clarifying Concerns Re GE Morris Groundwater Monitoring Evaluation.Evaluation Acceptable ML20059D8831990-08-29029 August 1990 Forwards Safety Insp Rept 72-0001/90-01 on 900212-14,0530,31 & 0601 & Notice of Violation ML20246P4731989-07-19019 July 1989 Forwards NRC Info Notice 89-045,Suppl 1, Metalclad,Low Voltage Power Circuit Breakers Refurbished W/Substandard Parts. No Action or Response Required ML20244B7331989-04-13013 April 1989 Forwards Safety Insp 72-0001/89-01 on 890227-0303 & Forwards Notice of Violation ML20246L5071989-03-0202 March 1989 Advises That 890216 Rev to Physical Security Plan Consistent W/Provisions of 10CFR72.33(e) & Acceptable ML20196E1501988-02-19019 February 1988 Forwards Safety Insp Rept 72-0001/88-01 on 880111-15.No Violations Noted IR 07200001/19870011987-05-0808 May 1987 Forwards Insp Repts 72-0001/87-01 & 30-29361/87-01 During Nov 1986 Through 870424 & Notice of Violation from 861006-10 Insp.Insp on 870210-13 & 18-20 Also Discussed.No Response Required Since Corrective Actions Already Taken ML20212E4731986-12-29029 December 1986 Forwards Safeguards Insp Rept 72-0001/86-05 on 861215-16 & Notice of Violation.Notice of Violation Withheld (Ref 10CFR73.21) ML20213G0401986-11-0505 November 1986 Forwards Insp Rept 72-0001/86-02 on 861006-10.Decision on Enforcement Action Re Violations Forthcoming in Separate Correspondence ML20197A4971986-10-21021 October 1986 Confirms 861028 Meeting at Region III Ofc in Glen Ellyn,Il to Discuss Results of Radiation Protection Insp Conducted on 861006-10,proposed Corrective Actions & NRC Enforcement Options ML20211E5261986-10-17017 October 1986 Advises That 860917 Changes to Physical Security Plan Consistent W/Provisions of 10CFR72.33(e) & Acceptable ML20209A7941986-08-29029 August 1986 Confirmatory Action Ltr Re 860828 Telcon Discussing Proposed Measures to Be Taken to Ensure That External Package Contamination Levels Do Not Exceed DOT Limits During Transport ML20212P4331986-08-27027 August 1986 Confirmatory Action Ltr Re 860827 Telcon Concerning High Levels of Removable Contamination Measured on Surface of IF-300 Casks on 860729 & 0819.NRC Understands That Casks Will Not Be Released Until Acceptable Measures Taken ML20203E2271986-07-18018 July 1986 Forwards Safety Insp Rept 72-0001/86-01 on 851119-860715.No Violations Noted ML20155F6711986-04-18018 April 1986 Advises That 860404 Rev to Physical Security Plan Consistent W/Provisions of 10CFR72.84(b) & Acceptable.Future Revs to Plan Should Be Sent to Region III at Listed Address DD-85-16, Advises That Time for Commission to Review Director'S Decision DD-85-16 Expired.Commission Declined Review. Decision Became Final Agency Action on 851210.Served on 8512131985-12-13013 December 1985 Advises That Time for Commission to Review Director'S Decision DD-85-16 Expired.Commission Declined Review. Decision Became Final Agency Action on 851210.Served on 851213 IR 05000313/20100071985-10-17017 October 1985 Forwards Insp Rept 72-0001/85-02 on 850313-1007.No Noncompliance Noted ML20209G3271985-09-13013 September 1985 Ack Receipt of Transmitting Changes to Physical Security Plan.Changes Consistent w/10CFR72.84(b) & Acceptable.Amend Fee Will Be Returned ML20128G6091985-06-28028 June 1985 Informs of Acceptance of 840531 & 850531 Annual Updates to Consolidated SAR for Morris Operation.No Comments Offered ML20054J4491982-06-22022 June 1982 Informs That No Addl Category 1H(a) Fee Will Be Required for 790227 Renewal Application for License SNM-1265.Max Fee,Per 10CFR170.31,paid ML20148D2291980-08-0606 August 1980 Forwards 780810 Memo Re Meeting Between Southwest Nuclear Co & Nrc,As Followup to 800804 Telcon ML20126C7371980-03-0707 March 1980 Ack Receipt of Re Changes to Physical Security Plan.Changes Acceptable.Encl to Ltr Withheld (Ref 10CFR2.790) ML20126B7901980-03-0303 March 1980 Notifies of Fee Refund Re 781015 Request to Amend Certain Conditions of License SNM-1265.No Licensing Action Taken on Reviewing Request.Request Has Been Considered Closed ML20147E5451978-12-11011 December 1978 Forwards Working Copy of Most Recent Rev of Draft Guide 3.44 Standard Format & Content for SAR to Be Incl in a Lic Appl for Storage of Spent Fuel in an Independent Spent Fuel Storage Installation. W/O Encl ML20147B7191978-12-0101 December 1978 Follows Up 781111 Telephone Conversation.Requests Clarifying Statement to Describe Transfer of Direct Loads on Wall in Finite Element Model & Confirmation That Neither Pool Will Be Drained Intentionally During Oper ML20147C0071978-11-17017 November 1978 Responds to 780922 Appl & Grants Amend to Special Nuc Matl Lic SNM-1265,Section 6-A & Conditions 14 & 16 Re Fuel Assemblies & Stored Fuel ML20148G6691978-11-0303 November 1978 Requests Addl Payment of Fee for Processing Separate Amend to License SNM-1265 ML20148K7051978-10-18018 October 1978 Responds to 780920 Request by Licensee for Info Re Safety Data for Renewal Appl for Lic SNM-1266 for GE Morris Oper. Present Csar,Updated to Incl All Detailed Info Specified in Proposed Reg Guide Under Each Section,Will Suffice ML20197C6271978-10-18018 October 1978 Review of Amend Appl Re Lacrosse BWR Fuel assemblies,790922 Gen Elec Ltr to Nrc,Is in Progress.Questions Re Fuel Arrangement & Discrepancy in Calculations Are Propounded ML20150B9631978-09-26026 September 1978 Ack Receipt of 780918 Transmittal of Safeguards Contingency Plan.Requests Payment of $6200 Fee ML20141F8891977-07-29029 July 1977 Notifies of NRC 770823-25 Meetings W/Fuel Cycle Licensees & Transportation Agents Near Richmond,Va to Discuss Proposed Rules 42FR25744 Re Contingency Planning & 42FR34310 Re Upgrading Safeguards in Fuel Cycle Facilities 1998-08-25
[Table view] |
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General Electric Company G. E. Morris Operation ATTN: 'T. E. Ingels Managa ,iberis Operation 7555 East Collins Road Morris, IL 60450-9740 Gentlemen:
The enclosed NRC Information Notice No. 89-45, Supplement 1: "Metalclad, Low-Voltage Power Circuit Breakers Refurbished With Substandard Parts" is provided for your information. No specific action or written response is required.
Sincerely, Original Signed by John P. Roberts -
John P. Roberts, Section taader Irradiated Fuel Section Fuel Cycle Safety. Branch
Enclosure:
As stated
_ - ~ _ _ _
Distribution: N 03Y Docket 72-1 PDR NRC File Center ER/F '
71 - l IMSB R/F IMIF R/F JRoberts JSchneider FBrown
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......... y. 19... k NAME :J3chneider: own :JR berts :
DATE: 07//f/89 :07/ed /89:07/ /9 /89: : :
OFFICIAL RECORD COPY
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UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555 July 6, 1989 NRC INFORMATION NOTICE NO. 89-45, SUPPLEMENT 1: METALCLAD, LOW-VOLTAGE POWER CIRCUIT BREAKERS REFURBISHED WITH SUBSTANDARD PARTS Addressees:
All holders of operating licenses or construction permits for nuclear power reactors.
Purpose:
.This information notice supplement is being provided to present additional information regarding the supply of surplus or refurbished circuit breakers and related electrical equipment to nuclear power plants as discussed in NRC Information Notice No. 89-45. It is expected that recipients will review this information for applicability to their facilities and consider actions, as appropriate, to avoid similar problems. However, suggestions contained in this information notice do not constitute NRC requirements; therefore, no specific action or written response is required.
Description of Circumsta.. es:
NRC Information. Notice No. 89-45 discussed a General Electric (GE) type AKF-2-25 metalclad, low-voltage power circuit breaker (field discharge configu-ration) from the Quad Cities nuclear power plant found te ce refurbished with nonstandard and substandard parts.
In conducting followup inspections at utilities that have procured circuit i breakers of this type and other related electrical equipment from Satin Ameri-can Corporation, the NRC has l_ earned of the existence of other equipment from Satin American, refurbished with nonstandard and possibly substandard parts and fabrication methods, some of which may contain latent defects resulting from the introduction of nonstandard materials and components. These defects may not be readily detectable by means of normal inspection and testing, and the -
nature of the defects is such that they could render the equipment inoperable without warning.
Discussion:
l Recent information, received in the course of the NRC's review and inspections j of refurbished electrical equipment, indicates that GE EC-type, series i overcurrent trip devices (particularly EC-1 and EC-2A) commonly used in GE
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1 IN 89-45, Supplement 1 I July 6,1989 i Page 2 of 3 AK-type, low-voltage power circu.it breakers, and supplied by a vendor other than the original manufacturer, may have been represented as new or original
. equipment. Documentation such as " certificates of certification" stated that the trip devices were " duplicates" of " identical" equipment originally sup-plied, when in fact, they were refurbished. Many were fitted with irregular nameplates and nonstandard and substandard parts. The trip devices were supplied primarily during the period 1983 through 1987. These electro-mechanical devices are presently used in Class 1E DC electrical systems because the newer solid-state devices use current transformers as sensors which do not operate on DC. They are also used in safety-related AC_ electrical systems that may be exposed to the harsh radiation environments of design-basis accidents.
Solid state trip devices have limited capability to withstand the effects of accident radiation doses greater than 10,000 rads or to ~ unction properly under the conditions of high accident radiation dose rates.
Of particular concern is the fact that, ir addition to irregular nameplates and refurbishment nat in accordance with the manufacturer's specifications, some of the units could be considered potentially defective as a result of the use of nonstandard parts and questionable refurbishing methods. Specifically, I disassembly and detailed examination of trip units supplied to Nine Mile Point, Unit 1, by Satin American revealed that some trip units were modified, appar-ently to alter their trip characteristics, by (1) substituting series coils with nonstandard numbers of turns, (2) changing instantaneous trip springs and/or varying the numbe: of active spring turns and/or adjusting tension to ,
compensate, and (3) altering longtime trip characteristics by such practices as k' using nonstandard longtime trip calibration springs, apparently enlarging the 1 bleed orifices in the dashpot pistons and/or substituting piston; (the markings of some of which were found to be incorrect for the nameplate longtime trip I characteristic and current rating) or using other inan the original dashpots to obtain different time delays. Additionally, in some trip units examined, the samples of oil taken from the dashpots exhibited some variance from their expected color and odor, indicating that the mechanical modifications may have been. complemented by the use of nonstandard dashpot oils (of yet undetermined composition, viscosity, and compatibility) to aid in obtaining the desired longtime trip characteristics.
Aside from the issue of representation of refurbished equipment as original, such modifications constitute the introduction of potential latent defects into equipment, already of indeterminate quality, that would not be readily detected by normal field testing and inspection and which could result in oegraded trip unit performance, inability to be adjusted properly, or failure to operate entirely.
Attachment 1 identifies differences that have been observed between several characteristics of construction of refurbished series overcurrent trip devices as supplied by Satin American and original ones from GE. Some of these at-tributes, identified by an asterisk (*), can often be observed without removing an installed trip unit from its circuit breaker (although the breaker may have to be racked out) and the rest may be observed by removing only the trip unit cover. These attributes may be used to identify refurbished units, although they, in themselves, may not all represent defects.
1 IN 89-45, Supplement 1 July 6, 1989 Page 3 of 3 Attachment 2 tabulates differences between various attributes of irregular nameplates found on some refurbished series overcurrent trip devices supplied by Satin American and authentic ones from GE. These differences may also be used to identify refurbished units.
Addressees are cautioned that although the differences described in Attachments 1 and 2 may be used to identify refurbished units from one vendor, each charac-teristic should be considered, since not all refurbished units will exhibit all of the differences that have been identified. Therefore, the lack of some of the differences described, or variations on them, should not be considered sufficient evidence to conclude that a given trip unit has not been refurbished.
The NRC is particularly interested in obtaining information on circuit breakers and related electrical equipment supplied by Satin American or others in which -
l differences or deficiencies in IN 89-45 and this supplement. have been found that are similar to those described Of special interest is information on recent '
procurement. Documentation, in as much detail as practicable, of any such differences or deficiencies discovered, especially in cases in which a piece of equipment may have been improperly cerviced or refurbished, is important.
Licensees may communicate information of this type by telephone to one of the-technical contacts listed below.
No specific action or written respom e is required by this information notice supplement. If you have any questions about this matter, please contact one of the technical contacts listed below or the Regional Administrator of the appropriate regional office.
{I,)
Charles E. Rossi, Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation Technical Contacts: S. D. Alexander, NRR (301) 492-0995 j i
U. Potapovs, NRR (301) 492-0984 l 1
Attachments:
- 1. Observed Differences in Original and Refurbished Trip Device Construction 2.
Observed Differences in Authentic and Irregular Trip Device Nameplates
- 3. List of Recently Issued NRC Information Notices I
W_
Attachment 1 l IN 89-45, Supplement 1 July 6, 1989 Page 1 of 1=
t
$ OBSERVED DIFFERENCES IN ORIGINAL VICE CONSTRUCTION AND1
! This attachment identifies differences tnat have bee as supplied by Satin American and tributes, identified by an asterisk (*) .
original rrent trip devices- on Some of these at-to be racked out) and the rest may cover. be may e breaker observe have These attributes may be used to identify refurbishedremovin units.
COMPONENT
- 1. ORIGINAL GE Magnetic structure _ REFURBISHED pole piece laminations Fastened with
- 2. rivets Fastened with split pins' EC-2A ' dashpot fasteners (also called roll pins)
Riveted to frame
- 3. Longtime calibration Bolted to frame with nuts and machine screws spring (EC-2A) Half near adjusting thumbwheel is painted; Slightly larger diameter color corresp and not painted
- 4. rating range.onds to EC-2A instantaneous trip adjusting spring Usually 8 active turns and 1 inactive turn, > 9 active turns, painted
- 5. unpainted 1 includin Paint on magnetic nut or <g screw adjusting Flat black, even and 8 active turns structure and/or frame smooth Glossy, drips may be 6.
Dashpot lever arm shaft applied over r,ust rubber oil seal boots Secured with two wraps of copper wire, ends May still use old style
- 7. twisted since 1984 pinch / spring type " hose" Longtime trip dashpots clamps Caet aluminum alloy body Body may have been
Square, flat cardboard unfinished sandblasted series coil insulators Usually bears handwrit-ten instantaneous trip Often shows no marking setting marking and the or is a used insulator,
- 9. tester's rubberstamp inverted so original EC-1 trip setting or marks are hidden calibration plates Factory set for long-time and short-time Replacement plates characteristics, stamped to work on bright aluminum, coarse refurbished unit, stamped characters matte finish, finer
- 10. Series coil: condition, stamped characters numtwr of turns, lug Uniform amber " varnish" type, and position insulation number of Discolored / darkened; may turns corre,ct for cur- appear recoated overhea-rent rating 1 ted; may have wr,ong lug pattern or number of turns Noteli Consuit' functional and technical construction documentation specificationserifand/or for btthe manu specific in do u .
y
. p Attachment 2 .
IN 89-45, Supplement 1 July 6, 1989 Page 1 of 1.
OBSERVED DIFFERENCES IN AUTHENTIC AND IRREGULAR TRIP DEV This attachment tabulates differences between various attributes of irregular nameplates found on some refurbished series overcurrent trip devices supplied by Satin American and authentic ones from GE.
observed without removing an installed trip unit from its circuit breakerThese attr (although the breaker may have to be racked out). These differences may be used in conjunction with Attachment 1 to identify refurbished units.
ATTRIBUTE AUTHENTIC GE IRREGULAR NAMEPLATE
- 1. Finish on EC-1 Bright brushed aluminum nameplates White anodized / matte-finished aluminum
- 2. Finish on EC-2A nameplates White anodized finish Similar finish, often lacquered but not lacquered
- 3. "INSPECTE0" block Unique, single-line stamps (made at GE Blank or stamp figure closed figure / shape l made by reorienting Plainville, CT factory (not used on new units and/or superimposing prior to about 1984) made after 1984 at GE one standard :, tamped Atlanta, GA factory) character on another
- 4. Shop or work order (
Letters "ATL " followed Not seen on refur-number (only on trip by unique five-digit bished trip units [
units made in GE Atlan- number usually stamped {
ta factory, 1984 on) with irregular in upper left corner 1 nameplates
- 5. Date code (should not Stamped, 2-ltr code on top Present on most appear.on plates with line between catalog "NO." EC-2As, missing on shop order number)1 and type designation, year many EC-1s examined, ltr different weight from year and month let-month letter. ters same weight
- 6. "NO." block (catalog 054900497G-1 printed on May be stamped onto part or drawing number) EC-2As of this design irregular nameplates
- 7. "NO." block "NO." corresponds to type Numbers may not ind unique "NP" (nameplate) correspond correctly namber for each design 1 or be valid at all
- 8. "NO." block "8"s in "NO." block on Plain figure "8"s EC-1s appear as: " 8' "
e.g., 2380685G-1 i
- 9. Frequency symbol "CY" Printed on EC-1s Stamped
- 10. Stamped characters Darkened with paint Darkened with grease
- 11. EC-1 trip setting Coarse stamped numbers Finer numbers, gradu-calibration plates ations closer spaced
{
- 12. EC-2A type designation "EC-2A" printed "A" suffix stamped i 1
i i
l l Note 1:
Consult manufacturer for identification of valid date codes, catalog j numbers (and corresponding nameplate numbers), inspection stamps, and '
shop order numbers.
i
Attachment 3 IN 89-45, Supplement 1 July 6, 1989-Page 1 of 1 LIST OF RECENTLY ISSUED NRC INFORMATION~ NOTICES Information Date of Notice No. Subject Issuance- Issued to 89-55 Degradation of Containment 6/30/89 All holders of OLs Isolation Capchility by a or cps for nuclear High-Energy Lina Bresk power reactors.
89-54 Potential Overpressurization 6/23/89 All holders of OLs of the Component Coo',ing or cps for nuclear Water System power reactors.
89-53 Rupture of Extraction 6/13/89 All holders of OLs Steam Li ,e on High or cps for nuclear Pressure Turbine power reactors.
88-46, Licensee Report of 6/8/89 All holders of OLs Supp. 3 Defective Refurbished or cps for nuclear Circuit Breakers power reactors.
89-52 Potential Fire Damper 6/8/89 All halders of OLs Operational Problems or cps for nuclear power reactore.
89-51 Potential Loss of Required 5/31/89 All holders of OLs Shutdown Margin During or cps for nuclear Refueling Operations power reactors.
88-88, Degradation of Westinghouse 5/31/89 All holders of OLs Supp. 1 ARD Relays or cps for nuclear power reactors.
89-50 Inadequate Emergency 5/30/89 All holders of OLs Diesel Generator Fuel or cps for nuclear Supply power reactors.
89-49 Failure to Close Service 5/22/89 All holders of OLs Water Cross-Connect or cps for nuclear Isolation Valves power reactors.
C0-48 Design Deficiency in the 5/22/89 All holders of OLs Turbine-Oriven Auxiliary or cps for nuclear Feedwater Pump Cooling power reactors.
Water System OL = Operating License CP = Construction Permit L___._________________.__--_-.--_