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| number = ML20212R111 | | number = ML20212R111 | ||
| issue date = 04/15/1987 | | issue date = 04/15/1987 | ||
| title = Forwards Response to NRC | | title = Forwards Response to NRC Re Security Insp on 870316-19.W/o Encl | ||
| author name = Kerr W | | author name = Kerr W | ||
| author affiliation = MICHIGAN, UNIV. OF, ANN ARBOR, MI | | author affiliation = MICHIGAN, UNIV. OF, ANN ARBOR, MI | ||
| Line 11: | Line 11: | ||
| contact person = | | contact person = | ||
| document report number = NUDOCS 8704240287 | | document report number = NUDOCS 8704240287 | ||
| title reference date = 04-06-1987 | |||
| document type = CORRESPONDENCE-LETTERS, EDUCATIONAL INSTITUTION TO NRC, INCOMING CORRESPONDENCE | | document type = CORRESPONDENCE-LETTERS, EDUCATIONAL INSTITUTION TO NRC, INCOMING CORRESPONDENCE | ||
| page count = 1 | | page count = 1 | ||
| Line 21: | Line 22: | ||
==Dear Mr. Axelson:== | ==Dear Mr. Axelson:== | ||
The enclosed information is in response to your inspection letter dated April 6, 1987. | The enclosed information is in response to your inspection {{letter dated|date=April 6, 1987|text=letter dated April 6, 1987}}. | ||
Sincerely, W. Kerr, Director Michigan Memorial-Phoenix Project OY I | Sincerely, W. Kerr, Director Michigan Memorial-Phoenix Project OY I | ||
O B704240287 B70415 PDR ADOCK 05000002 G PDR osure Contains Saf ;.ords Infor ion. n Separation T is Decontrolled. | O B704240287 B70415 PDR ADOCK 05000002 G PDR osure Contains Saf ;.ords Infor ion. n Separation T is Decontrolled. | ||
SAFEGUARD MATION | SAFEGUARD MATION | ||
- __ _ __ _ _ _ _ _ _ _ _ _ _ -}} | - __ _ __ _ _ _ _ _ _ _ _ _ _ -}} | ||
Latest revision as of 01:47, 5 May 2021
| ML20212R111 | |
| Person / Time | |
|---|---|
| Site: | University of Michigan |
| Issue date: | 04/15/1987 |
| From: | Kerr W MICHIGAN, UNIV. OF, ANN ARBOR, MI |
| To: | Axelson W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 8704240287 | |
| Download: ML20212R111 (1) | |
Similar Documents at University of Michigan | |
|---|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N3541999-10-26026 October 1999
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[Table view]Forwards, Requalification Program Ford Nuclear Reactor, in Response to NRC 900706 Request for Addl Info ML20055G3081990-07-17017 July 1990 Submits Info Re 10CFR50.33 & 50.75 Decommissioning Funds ML20248G2411989-09-20020 September 1989 Responds to NRC Questions Re Pool Leakage at Facility. Summary of Pool Water Makeup,Surface Evaporation & Leakage for Most Recent Two Quarters of 1989 & for Preliminary Measurement Conducted from 890915-18 Provided ML20244B1251989-05-30030 May 1989 Provides Correlation Between Rev Numbers & Content & Listing of Revs on Review Sheet of Emergency Plan ML20247F3101989-05-16016 May 1989 Forwards Revised Figure 6.1, Organization Chart for Ford Nuclear Reactor, Reflecting Reorganization of Health Physics Organization.Figure Should Be Included w/890508 Rev 1 to Tech Specs ML20245F0981989-04-20020 April 1989 Forwards Rev 5 to Emergency Plan Ford Nuclear Reactor. Changes Involve Time Limit on Ltrs of Agreement W/Ann Arbor Police Dept,Fire Dept & Ambulance Svc and Definition of Emergency Staff Members ML20196E7521988-11-0404 November 1988 Requests Approval of Alternate Routing for Shipment of Spent Triga Fuel from Cheyenne,Wy to Denver,Co ML20148D7571988-03-15015 March 1988 Forwards Revised Page 17 of Emergency Plan Re Modifying Section 3.2.1,per 880309 Request ML20244B1331988-01-15015 January 1988 Requests Listed Mods to Facility Emergency Plan ML20237K9631987-08-14014 August 1987 Forwards Proposed Revs to Emergency Plan,Reflecting Reorganization of Facility Mgt.Reactor Operators Are Not Required to Be in Line of Succession for Emergency Director ML20237J1511987-08-0404 August 1987 Forwards Proposed Revs to Pages 13-15 of Emergency Plan, Reflecting Facility Mgt Reorganiztion Including Addition of Second Assistant Reactor Manager ML20212R1111987-04-15015 April 1987 Forwards Response to NRC Re Security Insp on 870316-19.W/o Encl ML20215K4671987-03-26026 March 1987 Requests Approval of Route to Be Used for Transport of Spent Reactor Fuel.Proposed Route Attached ML20210F9121987-02-0505 February 1987 Advises That 861203 Revs to Emergency Plan Implemented,Per NRC 870116 Approval ML20244B1311986-12-0303 December 1986 Provides Changes to Listed Sections of Plant Emergency Plan, for Review & Approval.Changes Result of Region III Emergency Preparedness Insp ML20211C9881986-10-16016 October 1986 Responds to Re Security Plan.Revised Plan,W/All Mods Delineated,Encl.Encl Withheld (Ref 10CFR2.790) ML20203P1101986-10-0808 October 1986 Advises That Changes to Emergency Plan Submitted on 860813 Fully Implemented ML20203F2711986-07-15015 July 1986 Forwards Security Plan,Amending License R-28,per 10CFR50.90. Revised Sections Provide Decreased Security Arrangements Due to Conversion to Low Enriched Fuel & Organization Changes. Plan Withheld (Ref 10CFR2.790) ML20214A7351986-01-28028 January 1986 Requests Approval of Route for Transporting Spent Reactor Fuel.Proposed Route Encl ML20136E6451986-01-0303 January 1986 Forwards Revised Pages 5.7 & 18 to QA Program,Reflecting Elimination of Supervisor of Reactor Operations.Assistant Reactor Manager Assumed Responsibilities Formerly Assigned to Position ML20137X0391985-12-0404 December 1985 Responds to NRC Re Noncompliance Noted in Safety Insp on 851120-22.Corrective Actions:License Amend Request Submitted on 851202 to Remove Position of Supervision of Reactor Operations from Tech Specs ML20136F5531985-11-0707 November 1985 Responds to NRC Re Violations Noted in Insp on 851002-04.Corrective Actions:Rubber Sealing Gasket on Final 5-micron Filter Replaced & Fourth Sentence in Section 5.10.3 of Retention Tank Dumping Procedure HP 115 Revised ML20138L5891985-02-28028 February 1985 Forwards Revised Tech Specs & Safety Analysis as Part of OL Renewal Request,Including Page 5 of Section 1.0 Re Establishment of Surveillance Frequencies & Page 9 of Section 3.0 Re Shutdown Margin Requirements ML20138L5531980-04-0202 April 1980 Forwards Application for Amend to License R-28 & Safety Evaluation for Low Enrichment U Fuel.Nrc Questions & Safety Analysis Satisfactorily Addressed ML20126B8451980-03-0303 March 1980 Advises That on 800301,approx 47 Mci Br-82 Released Up Facility Exhaust Stack.Caused by Broken Sample.Max Possible Release Over 24-h Less than 0.7% Max Permissible Concentration ML20197B9231978-10-24024 October 1978 Responds to 781003 NRC Ltr Re Noncompliance Noted in Inspec on 780906-08.Corrective Actions:Calibr of Gamma Spectrometry Equip & Preparation of Health Physics Procedure Req Quarterly Calibr of Gamma Spectrometry Equip by 781201 ML20138L5121978-06-12012 June 1978 Forwards Addl Info Supporting 770630 Amend Request to Utilize Aluminide & Oxide Fuels.Request to Utilize UO2 Withdrawn,As Use Not Anticipated 1990-07-18 Category:INCOMING CORRESPONDENCE MONTHYEARML20195C0551999-05-25025 May 1999
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Rev Corrects Various Minor Typos & Revised Significant Radiation Exposures to Reflect Current 10CFR20 Guidance as Listed ML20129J0281996-10-28028 October 1996 Submits Rev 15 to Ford Nuclear Reactor Emergency Plan ML20057D2321993-09-30030 September 1993 Responds to NRC Re Violations Noted During Insp of Facility.Corrective Actions:Purchased New Model MGS0500 Mixed Gamma Std to Use for Germanium Detector Calibr,Per HP-105.Contests Part of Violation Re Fnr HP Procedures ML20057C5811993-09-15015 September 1993 Forwards Rev 3 of Page 5 of Requalification Program.Rev Makes Requalification Program Consistent W/Requirements of 10CFR55.53(F)(2) Re Extended Absence from Operation ML20056G3731993-08-27027 August 1993 Informs of Plans to Conduct Series of off-line Periods to Evaluate Reactor Sys,Procedures & Drawings,Evaluate Effluent Paths from Reactor Facility,Test Upgraded Equipment & Train Operators on Equipment & to Modify Procedures & Manuals ML20126E6571992-10-29029 October 1992 Forwards Amend 38 to Ford Nuclear Reactor TS Redefining Specification 3.1,under License R-28 for Phoenix Project ML20126E7351992-10-27027 October 1992 Responds to Commitment to Evaluate Effects of Unanticipated Reactivity Insertions at Facility & to Conduct Thorough Review of Procedures & Ts.Info on Corrective Actions Planned & Completed Related Reportable Occurrence 15 Encl ML20055H1111990-07-18018 July 1990 Forwards, Requalification Program Ford Nuclear Reactor, in Response to NRC 900706 Request for Addl Info ML20055G3081990-07-17017 July 1990 Submits Info Re 10CFR50.33 & 50.75 Decommissioning Funds ML20248G2411989-09-20020 September 1989 Responds to NRC Questions Re Pool Leakage at Facility. 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Text
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DMS THE UNIVERSITY OF MICHIGAN Michigan Memorial-Phoenix Project Office of the Director Ann Arbor, Michigan 48109-2100 (313) 764-6213 April 15, 1987 W.L. Axelson, Chief Nuclear Materials Safety and Safeguards Branch United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Re: Ford Nuclear Reactor University of Michigan Docket 50-2 License R-28 Security Inspection on March 16-19, 1987
Dear Mr. Axelson:
The enclosed information is in response to your inspection letter dated April 6, 1987.
Sincerely, W. Kerr, Director Michigan Memorial-Phoenix Project OY I
O B704240287 B70415 PDR ADOCK 05000002 G PDR osure Contains Saf ;.ords Infor ion. n Separation T is Decontrolled.
SAFEGUARD MATION
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