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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P6721999-10-26026 October 1999 Informs That Effective 991026,CH Bassett Will Be NRC Inspector for Engineering Experiment Station at Ohio State Univ,Due to Retirement of Previously Assigned Inspector ML20204F3971999-03-16016 March 1999 Informs That Mj Davis,License SOP 30847-1,no Longer Employed at Osur.License May Be Terminated ML20204B2031999-03-0404 March 1999 Forwards Insp Rept 50-150/99-201 on 990208-12.No Violations Noted.Insp Consisted of Organization,Periodic & Special Repts,Operations & Maint,Procedures Requalification Training,Surveillance,Experiments & Physical Security ML20248A3501998-05-13013 May 1998 Informs That Kr Herminghuysen,SOP-70125,no Longer Requires License to Operate Reactor,Effective 980430 ML20199H9951997-11-18018 November 1997 Informs of Change in Person Serving as Director of Engineering Experiment Station as Required by TS 6.6.2(3)(C) of Oh State Univ Research Reactor ML20217P3201997-08-22022 August 1997 Informs That Responsibility for Non-Power Reactor Insp Program Has Been Transferred from Nrr.All Related Repts, Correspondence & Inquires W/Docket Number Specified Should Be Directed to Listed Address ML20136D6651997-03-0606 March 1997 Forwards Amend 17 to License R-75 & Safety Evaluation.Amend Revises License Condition 2.B to Increase Possession Limit from 10 G to 30 G of Highly Enriched U-235 in Form of Fission Chamber Linings,Foil Targets & Other Applications ML20138K8831997-02-11011 February 1997 Discusses Review of Changes to Ohio State Univ Research Reactor Emergency Plan Submitted by .Changes IAW 10CFR50.54(q) ML20133F7011996-12-19019 December 1996 Forwards Revised Emergency Plan,Per & Recent Discussion W/R Myser of Oh State Univ & Cohen of NRC ML20135B1451996-12-0202 December 1996 Advises That Proposed Changes to Operator Requalification Plan Acceptable ML20129H8281996-11-0101 November 1996 Forwards EPA Referral Form Re Effluent Releases to Ambient Air from Ohio State Univ Nuclear Reactor,Iaw 1992 MOU Between NRC & EPA ML20129H8631996-11-0101 November 1996 Forwards Insp Rept 50-150/96-01 on 961007-11.No Violations Noted ML20128P8551996-10-0707 October 1996 Forwards Rev 7 to Administrative Procedure AP-09, Ro/Sro Requalification ML20129E7061996-10-0101 October 1996 Forwards RAI Re Changes to Research Reactor Emergency Plan. Response to Be Submitted within 60 Days of Ltr Date ML20117C8201996-08-19019 August 1996 Forwards Revised Requalification Program Ro/Sro Requalification ML20094B5941995-10-10010 October 1995 Discusses Proposed Deletion of Physical Security Plan for Protection of SNM of Moderate Strategic Significance or Low Strategic Significance ML20091S1501995-08-28028 August 1995 Informs That During 950720 Meeting Reactor Operations Committee Reviewed & Approved Listed TS Changes ML20086A3571995-06-14014 June 1995 Forwards Trtr Peer Review for Oh State Univ Nuclear Reactor Lab, for 950214-15 ML20085J1781995-05-19019 May 1995 Submits Advance Notification of Listed Category III Matl,Per Requirements of 49CFR173.22(C),10CFR73.67(E)(1)(i) & 10CFR73.72(A)(3) ML20085J2361995-05-19019 May 1995 Submits Advance Notification of Shipment of Category II Matl from Ohio State Univ to Westinghouse Savannah River Co to Meet Requirements of 49CFR173.22(C),10CFR73.67(E)(1)(i) & 10CFR73.72(A)(3) ML20085J1281995-05-0303 May 1995 Requests That Shipping Window Extending from 950530-0603 Be Assigned for Licensee Category II Shipment as Per 950503 Telcon ML20083K7491995-05-0202 May 1995 Forwards Revised Emergency Preparedness Plan for Ohio State Univ Nuclear Reactor Lab ML20082Q1081995-04-24024 April 1995 Forwards Revised Security Plan Re Recent Exterior Environs Changes.Encl Withheld ML20116D8281995-01-0606 January 1995 Forwards Info Which Updates NRC on Matter Re Magnet Amplifiers for Osu Research Reactor ML20083K7581994-12-23023 December 1994 Forwards Revised Emergency Preparedness Plan for Ohio State Univ Nuclear Reactor Lab, as Result of Nuclear Reactor Lab Staff Review of Emergency Plan & Responding to Notice of Violation ML20077C7571994-09-30030 September 1994 Responds to NRC Re Violations Noted in Insp Rept 50-150/94-01.Corrective Actions:Licensee Definding Timely Manner as within Yr Being Audited & Findings Will Be Reviewed within Three Months of Completion of Audit ML20072F1061994-08-12012 August 1994 Responds to NRC 940523-26 Ltr Re Violation Noted in Insp Rept 50-150/94-01.Corrective Action:Training Supervisor Will Administer Annual Exam in 1994 ML20069G0191994-05-31031 May 1994 Informs That Jm Hatch Has Terminated Employment W/Oh State Univ Research Reactor,Therefore There Is No Longer Need for License SOP-30214-3 ML20056F7691993-08-23023 August 1993 Forwards Amend 14 to License R-75 & Se.Amend Revises TS to Allow Greater Magnet Holding Currents in Control Rod Magnet Circuit Before Rod Drops Initiated ML20056F2711993-08-11011 August 1993 Forwards Results for Operator Requalification Exam on 930628.W/o Encl ML20044H4961993-06-0404 June 1993 Discusses Telcon Between W Eresian & Rd Myser Re Performance of Requalification Exam at Pool Reactor Which Is Scheduled on 930628 to Be Performed in Accordance W/Ol Std ES-606 ML20036A2921993-05-0404 May 1993 Ack Receipt of Transmitting Changes to Oh State Univ Nuclear Reactor Lab Physical Security Plan.Changes Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20035G1751993-04-21021 April 1993 Forwards Revised Portions of Physical Security Plan for Protection of SNM of Moderate Strategic Significance or Low Strategic Significance.Encl Withheld (Ref 10CFR2.790) ML20035A7941993-03-24024 March 1993 Grants Temporary Waiver of Compliance from TS 3.2.3.13 to Allow Magnet Currents Up to 100 Ma Before Rod Drop Initiated.Waiver Effective 15 Calendar Days After Date of Ltr ML20034H9021993-03-15015 March 1993 Responds to NRC Request for Addl Info to Support 930203 Request to Test Rod Drop Performance W/Magnet Currents Up to 100 Milliamps ML20034J0121993-03-12012 March 1993 Addresses Several Issues Concerning Recent Malfunction of Shim Safety 1 Control Rod in Response to Slow Scram & Corrective Actions Taken & Proposed in Order to Restart Reactor ML20034G2241993-02-25025 February 1993 Forwards Insp Rept 50-150/93-02,70-0801/93-01 & 70-3005/93-01 on 930209-10.No Violations Noted ML20128K6781993-02-0808 February 1993 Advises That Author Replaced Weislogel as Director of Engineering Experimental Station ML20128K6671993-02-0303 February 1993 Requests Permission to Test Magnets in Reactor at Currents Up to 100 Milliamps.Licensee Will Perform Several Rod Drop Tests to Verify That Reactor Safety Sys Would Still Operate within Design Criteria,Prior to Requesting TS Change ML20044B5731992-09-16016 September 1992 Discusses Telcon Between R Myser & F Collins Re Plans to Perform Requalification Exams Scheduled for Wk of 921214 ML20118A7201992-07-21021 July 1992 Informs That Weislogel Has Replaced Rf Redmond as Acting Director of Engineering Experiment Station ML20073P9561991-05-13013 May 1991 Forwards Power Increase Plan for Increase from 10 Kw to 500 Kw ML20029B5791991-03-0404 March 1991 Forwards Insp Repts 50-150/91-01,70-0801/91-01 & 70-3005/91-01 on 910205-07.No Violations Noted ML20065K7491990-11-21021 November 1990 Forwards Rev 5 to Administrative Procedure AP-09, Reactor Operator/Senior Reactor Operator Requalification ML20062F0611990-11-14014 November 1990 Forwards Amend 13 to License R-75,SE,notice of Issuance & Environ Assessment.Amend Changes License Condition & Tech Specs to Increase Authorized Steady State Reactor Power from 10 Kw to 500 Kw & to Authorize Possession of SNM ML20056A2901990-07-30030 July 1990 Forwards Decommissioning Funding Plan for Ohio State Univ Research Reactor ML20055H9921990-07-26026 July 1990 Advises That Decommissioning Funding Plan Awaiting Signature by Univ Provost.Provost Due Back During Wk of 900730 ML20043G8781990-06-12012 June 1990 Forwards Proposed Tech Specs & Bases Re Changes to Reactor Operating Power,Per Recent Discussion W/Nrc ML20042D8021990-03-26026 March 1990 Forwards Notice of Consideration of Issuance of Amend to License R-75 and Opportunity for Hearing on 871007 Request to Increase Power Level to 500 Kw ML20033E3271990-02-28028 February 1990 Forwards Response to 891222 Request for Addl Info Re Power Increases,Consisting of Tables Listing Constants Used in Whole Body Dose Estimates & Proposed Plan for Determination of Ar-41 Concentrations 1999-03-04
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20204F3971999-03-16016 March 1999 Informs That Mj Davis,License SOP 30847-1,no Longer Employed at Osur.License May Be Terminated ML20248A3501998-05-13013 May 1998 Informs That Kr Herminghuysen,SOP-70125,no Longer Requires License to Operate Reactor,Effective 980430 ML20199H9951997-11-18018 November 1997 Informs of Change in Person Serving as Director of Engineering Experiment Station as Required by TS 6.6.2(3)(C) of Oh State Univ Research Reactor ML20133F7011996-12-19019 December 1996 Forwards Revised Emergency Plan,Per & Recent Discussion W/R Myser of Oh State Univ & Cohen of NRC ML20128P8551996-10-0707 October 1996 Forwards Rev 7 to Administrative Procedure AP-09, Ro/Sro Requalification ML20117C8201996-08-19019 August 1996 Forwards Revised Requalification Program Ro/Sro Requalification ML20094B5941995-10-10010 October 1995 Discusses Proposed Deletion of Physical Security Plan for Protection of SNM of Moderate Strategic Significance or Low Strategic Significance ML20091S1501995-08-28028 August 1995 Informs That During 950720 Meeting Reactor Operations Committee Reviewed & Approved Listed TS Changes ML20086A3571995-06-14014 June 1995 Forwards Trtr Peer Review for Oh State Univ Nuclear Reactor Lab, for 950214-15 ML20085J2361995-05-19019 May 1995 Submits Advance Notification of Shipment of Category II Matl from Ohio State Univ to Westinghouse Savannah River Co to Meet Requirements of 49CFR173.22(C),10CFR73.67(E)(1)(i) & 10CFR73.72(A)(3) ML20085J1781995-05-19019 May 1995 Submits Advance Notification of Listed Category III Matl,Per Requirements of 49CFR173.22(C),10CFR73.67(E)(1)(i) & 10CFR73.72(A)(3) ML20085J1281995-05-0303 May 1995 Requests That Shipping Window Extending from 950530-0603 Be Assigned for Licensee Category II Shipment as Per 950503 Telcon ML20083K7491995-05-0202 May 1995 Forwards Revised Emergency Preparedness Plan for Ohio State Univ Nuclear Reactor Lab ML20082Q1081995-04-24024 April 1995 Forwards Revised Security Plan Re Recent Exterior Environs Changes.Encl Withheld ML20116D8281995-01-0606 January 1995 Forwards Info Which Updates NRC on Matter Re Magnet Amplifiers for Osu Research Reactor ML20083K7581994-12-23023 December 1994 Forwards Revised Emergency Preparedness Plan for Ohio State Univ Nuclear Reactor Lab, as Result of Nuclear Reactor Lab Staff Review of Emergency Plan & Responding to Notice of Violation ML20077C7571994-09-30030 September 1994 Responds to NRC Re Violations Noted in Insp Rept 50-150/94-01.Corrective Actions:Licensee Definding Timely Manner as within Yr Being Audited & Findings Will Be Reviewed within Three Months of Completion of Audit ML20072F1061994-08-12012 August 1994 Responds to NRC 940523-26 Ltr Re Violation Noted in Insp Rept 50-150/94-01.Corrective Action:Training Supervisor Will Administer Annual Exam in 1994 ML20069G0191994-05-31031 May 1994 Informs That Jm Hatch Has Terminated Employment W/Oh State Univ Research Reactor,Therefore There Is No Longer Need for License SOP-30214-3 ML20035G1751993-04-21021 April 1993 Forwards Revised Portions of Physical Security Plan for Protection of SNM of Moderate Strategic Significance or Low Strategic Significance.Encl Withheld (Ref 10CFR2.790) ML20034H9021993-03-15015 March 1993 Responds to NRC Request for Addl Info to Support 930203 Request to Test Rod Drop Performance W/Magnet Currents Up to 100 Milliamps ML20034J0121993-03-12012 March 1993 Addresses Several Issues Concerning Recent Malfunction of Shim Safety 1 Control Rod in Response to Slow Scram & Corrective Actions Taken & Proposed in Order to Restart Reactor ML20128K6781993-02-0808 February 1993 Advises That Author Replaced Weislogel as Director of Engineering Experimental Station ML20128K6671993-02-0303 February 1993 Requests Permission to Test Magnets in Reactor at Currents Up to 100 Milliamps.Licensee Will Perform Several Rod Drop Tests to Verify That Reactor Safety Sys Would Still Operate within Design Criteria,Prior to Requesting TS Change ML20118A7201992-07-21021 July 1992 Informs That Weislogel Has Replaced Rf Redmond as Acting Director of Engineering Experiment Station ML20073P9561991-05-13013 May 1991 Forwards Power Increase Plan for Increase from 10 Kw to 500 Kw ML20065K7491990-11-21021 November 1990 Forwards Rev 5 to Administrative Procedure AP-09, Reactor Operator/Senior Reactor Operator Requalification ML20056A2901990-07-30030 July 1990 Forwards Decommissioning Funding Plan for Ohio State Univ Research Reactor ML20055H9921990-07-26026 July 1990 Advises That Decommissioning Funding Plan Awaiting Signature by Univ Provost.Provost Due Back During Wk of 900730 ML20043G8781990-06-12012 June 1990 Forwards Proposed Tech Specs & Bases Re Changes to Reactor Operating Power,Per Recent Discussion W/Nrc ML20033E3271990-02-28028 February 1990 Forwards Response to 891222 Request for Addl Info Re Power Increases,Consisting of Tables Listing Constants Used in Whole Body Dose Estimates & Proposed Plan for Determination of Ar-41 Concentrations ML20244A4541989-05-26026 May 1989 Forwards Response to NRC 890330 Communication Re Change in Operating Power & Revised Tech Specs,For Review & Approval. State of Oh Ofc of Energy Mgt Consulted W/To Formulate Answers to Questions ML20235Z3361989-03-0707 March 1989 Forwards QA Program for Ohio State Univ Nuclear Reactor Lab, Administrative Procedure AP-14, Ohio State Univ Research Reactor Mod Requests & Procedure RS-11, Routine Shipment of Radioactive Matl ML20154Q0051988-05-0606 May 1988 Forwards Responses to Questions Re Conversion to Low Enrichment U Fuel.Modified Tech Specs Which Reflect Initial Operation W/Low Enrichment U at Current 10 Kw steady-state Thermal Power Level Also Encl ML20235U5351987-10-0707 October 1987 Forwards Revised SAR & Tech Specs for Ohio State Univ Research Reactor.Facility Currently Undergoing Conversion to low-enriched U Fuel,Per Recently Passed NRC Regulations & Change in Operating Power ML20216H3891987-06-24024 June 1987 Submits Rept of Safety Sys Failure.On 870618,during Testing of New Safety Equipment,Determined That No Output Voltage from LOG-N to Period Generator.Caused by Broken Circuit Ground at Two Prong End of Cable.Diagram Encl ML20205H2311987-03-23023 March 1987 Submits Proposal for Conversion of Fuel at Reactor from Highly Enriched to Low Enriched U,Including Certification of Availability of DOE Funding & Schedule for Conversion ML20211H5331987-02-17017 February 1987 Forwards Explanations & Mods to Requalifiction Program,Per NRC 870204 Telcon.Section on Document Review Added to Section IV, Precautions ML20215F9681986-12-16016 December 1986 Forwards Revs to Administrative Procedures,Including Rev 3 to AP-03, Reactor Operator/Senior Reactor Operator Requalification & Rev 3 to AP-07, Review of Procedures ML20211G9471986-10-27027 October 1986 Forwards Rev 2 to Administrative Procedure AP-09, Reactor Operator/Senior Reactor Operator Requalification, for Review & Approval.Procedure Revised on 861020 by Ohio State Univ Subcommittee of Reactor Operations ML20197B2451986-04-30030 April 1986 Requests Deletion of Section 4 of Amend 7 to License R-75 Correcting Discrepancy in Quantity of U-235 ML20205E9461985-10-17017 October 1985 Responds to 850927 Order to Show Cause Re Removal of Excess Unirradiated Highly Enriched U.Provisions of Section III of Order Should Not Be Imposed Since Only Irradiated Fuel Elements Possessed ML20133M8051985-10-0101 October 1985 Responds to NRC Re Violations Noted in Safety Insp Rept.Corrective Actions:Requirements for Calibr of Exit Radiation Survey Instrument & Pocket Dosimeters & List of Items Requiring Notification Will Be Distributed ML20140D2671984-12-0303 December 1984 Responds to NRC Re Violations Noted in Insp Rept 50-150/84-01.Corrective Actions:Scheduling Procedures for Instrument Calibr & Control Element Tests,Requalification Exams & Reactor Operations Meetings Revised ML20093M2691984-10-12012 October 1984 Advises That Emergency Preparedness Plan Fully Implemented as of 841012.Correspondence Re Plan Should Be Directed to Author.Questions on Contact or Implementation of Plan Should Be Directed to Rd Myser or JW Talnagi ML20090J8071984-05-10010 May 1984 Forwards Addendum to Emergency Preparedness Plan for Ohio State Univ Nuclear Reactor Lab, Per ML20069M4471982-11-0202 November 1982 Forwards Public Version of Emergency Preparedness Plan ML20042B2531982-02-26026 February 1982 Forwards Info Re Security Plan.Encl Withheld (Ref 10CFR73.21) ML20031H3131981-09-22022 September 1981 Forwards Revised Pages to Security Plan for Protection of SNM of Moderate Strategic Significance.Pages Withheld (Ref 10CFR2.790) ML20002B5291980-11-17017 November 1980 Responds to NRC Re Violations Noted in IE Insp Rept 50-150/80-03.Corrective Actions:Procedure Revised to Include Methods for Personnel Accountability During Emergency Evacuation 1999-03-16
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T-HE Engineering Experiment Station 156 Hitchcock Hall j
W 2070Neil Avenue Columbus, OH 43210-1275 Phonc 614-292-4903 FAX # 614-292-9021 UNIVERSITY g_
O"O )\\
January 6,1995 G
i
\\
Roy J. Caniano, Chief r\\
Reactor Support Programs Branch US NRC Region III 801 Warrenville Rd.
l Lisle,IL 60532-43S1 l
l
Subject:
Update of Magnet Amplifiers for the OSU Research Reactor, Docket 50-150 License P.-75 i
Dear Mr. Caniano,
In March of 1993 the OSURR reported a failure of a control rod to drop _ following a slow l
scram. The status of our progress in correcting this problem was reviewed by Mr. Tim l
Reidinger during his inspection of May 23-26,1994. Subsequent to his inspection new magnet control amplifiers have been installed, tested, and approved by the OSU Reactor i
L Operations Committee at its meeting of September 22,1994. The Reactor Staff agreed i
durmg this meeting to update the NRC on this matter which is the purpose of this letter i
and attachments. The Reactor staff realizes this item may not be closed out until the next on site inspection. -If you have questions on this matter please contact Mr. Richard Myser at 614/292-6755.
Sincerely, Qbyb Csu l
Jose B. Cruz, Jr., Dean l
Enclosures
- c. Richard Myser i
Don W. Miller i
l Ted Michaels 1
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50 P
PDR l
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M IIM College of Engineering
i A
To : ROC Members From : Michael J. Davis Date : 10 August 1994 Subject : New Control Rod Magnet Amplifiers
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In response to the failure of Shim Safety Rod # 1 to drop to the bottom following a manual scram, a new magnet control system has been designed, built, and tested. Failure of the previous system was determined to be due to a short occurring between the engage limit switch assembly and the magnet coil assembly, allowing Shim Safety Rod #1 to remain energized despite the insertion of a scram signal. As a result, the NRL staff agreed to design and mstall a magnet current amplifier that " electrically floats"; and to design a system to monitor the magnet coil cable to continuously check the integrity of the lines and provide an alarm to notify the operator if a problem develops.
The new system has a floating power supply to provide the " electrical float". Current from the power supply is regulated by an LM-317 current regulator. which is adjustable via a ten turn potentiometer. Technical Specification 3.2.3 requires that current be limited to less than or equal to 100 mA. Limitation is provided by the combination of an LM-339 comparator, and a 74C74 dual flip flop. The comparator has adjustable high and low current set points, that allow a maximum magnet current of 91 mA (<= 100 mA). It checks to ensure that magnet current is between the two set points, and sends its output to the flip flop. The flip flop has two outputs, one of which goes to the " Current OK" LED, j
and the other of which goes to the fast scram FET. When current is outside of the high I
and low set points, the flip flop sends a signal to the FET, causing it to open the current path to the magnet. This is in essence the effect of any fast scram signal. The slow scram system functions independently from the fast scram system. It is comprised of a 171 DIP 25 double pole relay that opens on both sides of the magnet coil when the relay coil ground path is opened due to the receipt of any slow scram signal. The fact that the current path is broken on both sides of the magnet coil, rather than just one side, is an.
improvement in the system that precludes a failure of the type that initiated the redesign of the system.
The " Current OK" LED indicates that the FET is closed and that there is a current path through the fast scram system to the magnet coil. The " System OK" LED indicates that the slow scram relay is closed, again allowing current flow to the magnet coil. There is an inherent continuous system check to ensure the integrity of the lines, in that if a short develops across the magnet coil while it is energized, the current will bypass the coil and i
the rod will drop. The system also measures voltage drop across the magnet coil. In the event of such a short, current will stay constant, but voltage will drop to zero, to alert the j
operator that a stort has developed.
The design of the system was reviewed with Dr. Richard Bailey and Howard Dyke on 28 Feb 1994. A prototype was built and bench tested on 29 Jun 1994. Bench testing included fast and slow scram tests, high and low current drop-out tests, determination of maximum failure current and power to the magnet coil, and determination of magnet current decay time. Fast scram, slow scram, and high / low drop-out tests functioned as expected. Maximum failure current (maximum current that can be delivered by the power supply without regulation and / or limitation) was measured to be 121 mA, and j
maximum power delivered (based on the maximum failure current) to the coil was then calculated to be 4 W. Maximum magnet coil decay time was measured to be 2-3 ms.
i The prototype was then installed and tested in the control room on 5 Jul 1994. Fast and i
slow scrams were tested IAW approved procedure IM-03. High and low current drop-out tests were also performed. All test results were satisfactory.
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To : ROC Members From : Michael J. Davis Date : 21 Sep 1994 Subject : Long Term Preventive Maintenance Items In Response To Shim Safety Rod #1 Failure Subsequent to the failure of Shim Safety Rod #1 to drop following a manual scram on 5 Mar 1993, the NRL agreed to perform a number of preventive maintenance items as part of our long term plan to prevent the recurrence of this type of event.
- 1) Examine magnet coil connectors for corrosion on a quarterly basis. Following l
these inspections, a determination will be made on the necessity of providing auxiliary ventilation to remove condensation.
Inspections showed no noticeable increase in corrosion or condensation. With the new magnet control system, a build-up of corrosion leading to a short to the outer magnet assembly will not adversely affect the safety system. In the two cases in which this short develops and the outer magnet assembly is at ground, as it should be, the current source l-to the magnet will still be the current amplifier in the control room, and thus, will be l
subject to safety system designs. If the current source side develops this short under this l
condition, current will be shunted around the magnet. If the return side develops this
- short, the magnet will continue to operate as normal. If this type of short develops and l
l the outer magnet assembly is not at ground (which was the case leading to our previous
)
l failure), then one of two things happens. If the short is on the current source side of the magnet, then the current loop is blocked by the circuitry in the magnet control system. A
'1 test of the blocking capability of the system was performed by inserting a 120 VAC signal to the magnet BNC center (current source side) of the control system. As expected, the system shut down. If the short occurs on the return side, it will be shunted l
to ground through the BNC shield ground, which will have no effect on the magnet current or the control system.
In light of all of this, the NRL staff has agreed that shim safety magnets shall be inspected 4
l on an annual basis and during magnet replacement operations. Furthermore, it has been decided that it is im-=y to modify the magnet coil housings to provide auxiliary i
ventilation to remove condensation.
- 2) Create a procedure to monitor the magnet coil cable on a monthly basis to check for electrical grounds.
j 1
This item was performed as part of our Pre-Start Checkout procedure (IM-03). As part of that procedure, a scram check is performed on each of the shim safety rods. With the old magnet current control system in place, if a short similar to the one that caused the rod drop failure had occurred, causing the expected electrical ground of the system to no longer be at ground on any of the shim safety rods, then the rod would fail to drop during this test. If all of the rods dropped as expected, then this indicated that the electrical grounds were still at ground. This system check was part of Procedure IM-03 prior to the l
rod drop failure incident. As a result, no new procedure needed to be developed. This check will continue as part of the Pre-Start Checkout procedure to be performed prior to each daily reactor operation.
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