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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20211B1851999-08-16016 August 1999 Forwards Response to 990308 RAI Re Amends to License R-66 & Ts.Proposed Wording for possession-only License & Revised & New Ts,Included ML20211B9041999-08-16016 August 1999 Forwards Substitute Cavalier TS Pages 32 & 33 for NRC Copy of Cavalier TS Amend Application,Replacing Old Page 32 ML20207A4371999-05-24024 May 1999 Forwards Advance Notification of Spent Nuclear Research Reactor Fuel Shipment R66-99-2 from U VA Nuclear Reactor Facility to Savannah River,Sc.Details Concerning Shipment in Attachment.Attachment Withheld ML20217A6321999-05-24024 May 1999 Provides Advance Notification of Spent Nuclear Research Reactor Fuel Shipment R66-99-2 from Univ of Virginia Nuclear Facility to Savannah River,South Carolina.Encl Withheld ML20206K8071999-05-0606 May 1999 Forwards Insp Rept 50-062/99-201 on 990414-16.No Violations Noted.Insp Consisted of Selective Exams of Procedures & Representative Records,Interviews with Personnel & Observations of Activities in Progress ML20205J4271999-03-30030 March 1999 Submits Advanced Notification of Upcoming Spent Nuclear Reactor Fuel Shipment R66-99-1 from Univ of VA Nuclear Reactor Facility to Savannah River,Sc,Per 10CFR73.Details of Shipment,Encl.Without Encl ML20207K2501999-03-0808 March 1999 Forwards Request for Addl Info Re Amend Request for License R-66 Submitted on 980929 ML20203A1331999-02-0303 February 1999 Requests That Senior Reactor Operator License SOP-70161,on Univ of VA Reactor (License R-66) of CA Bly,Be Terminated ML20202B3421999-01-25025 January 1999 Ack Receipt of 990107 Response to Violations Noted in Insp Rept 50-062/98-202.Response Meets Requirements of 10CFR2.201 ML20206P2991999-01-0707 January 1999 Responds to NRC Re Violations Noted in Insp Rept 50-062/98-202.Corrective Actions:Correct Name for Content Matl Being Shipped Is Now Typed Onto All Shipping Forms ML20198L1161998-12-29029 December 1998 Responds to Request for Updated Version of Route Approved by .Enclosure 1 & Page 7 of Enclosure 2 to Be Incorporated with 981026 Package Encl ML20198J2221998-12-21021 December 1998 Forwards Amend 24 to License R-66 & Safety Evaluation.Amend Removes Surveillance Requirements for Rod Drop Measurements & Primary Coolant Flow Calibr ML20198F1101998-12-21021 December 1998 Requests 30-day Extension to Response to NRC Rai, ML20197H6901998-12-10010 December 1998 Submits Clarification of Request for Amend to Univ of VA Reactor TS Dtd 981203.Request Remains Active ML20197H5701998-12-0909 December 1998 Forwards Insp Rept 50-062/98-202 on 981116-19 & Notice of Violation.One Violation Identified.Various Aspects of Operations,Safety & Security Programs Inspected Including Selective Exams of Procedures & Representative Records ML20197G9721998-12-0303 December 1998 Informs That Univ of VA Is in Process of Preparing Response to NRC 981123 RAI Re Proposed Set of UVAR TS Amends Submitted on 980929.Listed Are Two UVAR TS Considerations That Are Being Brought to NRC Attention for Resolution ML20196B1081998-11-23023 November 1998 Forwards Request for Addl Info Re Amend Request for Amended FOL R-66 for University of Virginia Research Reactor, Submitted on 980929.Response Requested within 30 Days of Date of Ltr ML20155D4711998-10-30030 October 1998 Forwards Advance Notification of Spent Nuclear Research Reactor Fuel Shipment R66-98-1 from U VA Nuclear Reactor Facility to Savannah River,Sc.Details of Shipment Are Encl. Without Encl ML20198C8351998-10-30030 October 1998 Forwards Advance Notification of Spent Nuclear Research Reactor Fuel Shipment R66-98-1 from Univ of VA Nuclear Reactor to Savannah River,Sc.Details of Shipment Encl. Without Encl ML20155C1271998-10-27027 October 1998 Informs That Univ of Virginia,Cavalier & UVAR Reactor Operator Requalification Program Meets Requirements of Regulations & Therefore,Acceptable.Implementation of Approved Program Should Begin Immediately ML20155B6031998-10-26026 October 1998 Refers to Request Dtd 980922,for Approval of Route to Be Used for Transport of Spent Fuel from University of Virginia Nuclear Reactor Facility,Charlottesville,Va to Us DOE Savannah River Site,Aiken,Sc ML20154H9561998-10-0707 October 1998 Forwards Response to NRC Request for Addl Info Re Revised Reactor Operator Requalification Program ML20239A1061998-09-0303 September 1998 Forwards RAI Re Revised Reactor Operator Requalification Program,Submitted by Ltr ML20236X8071998-08-0303 August 1998 Forwards Revised Operator Requalification Program for NRC Review & Approval.New Program Takes Into Account de-facto Limitations of Licensed Ro/Sro Duties Just to Fuel Handling Activities,Given That Reactor Core Is Permanently Unloaded ML20236Q9931998-07-15015 July 1998 Withdraws 960319 Request That Revised Security Plan Become License Amend,Per 10CFR50.34 & 10CFR50.59,due to Permanent Shutdown of Univ of VA Reactor,Effective 980701 ML20236K4741998-07-0707 July 1998 Forwards Amend 8 to License R-123 & Safety Evaluation. Amend Tranfers Responsibility for Overall Mgt of CAVALIER from School of Engineering to Office of Vice Provost for Research ML20236F7091998-06-26026 June 1998 Ack Receipt of ,Informing NRC of Univ of Virginia Decision to Cease Operations at Univ of Virginia Research by 980701 & Being Process to Decontaminate & Decommission Facility ML20249C3801998-06-22022 June 1998 Submits Formal Notification to Us NRC of Intention of Univ of VA to Begin Process That Will Lead to Decontamination & Decommissioning of Univ of VA Reactor Covered by License R-66 ML20249B8641998-06-18018 June 1998 Submits Response to NRC RAI Re TS Amend Request ML20249A5921998-06-15015 June 1998 Forwards Amend 23 to License R-66 & Safety Evaluation.Amend Transfers Responsibility for Overall Mgt of University of Virginia Research Reactor from School of Engineering to Ofc of Vice Provost for Reseach IR 05000062/19982011998-05-0404 May 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-062/98-201.NRC Will Examine Implementation of Corrective Actions During Future Insp ML20217H7921998-04-23023 April 1998 Informs That Univ of VA Administration Had Made Decision to Move Toward Ceasing Operations of UVAR Reactor,As Stated in ML20217H7891998-04-15015 April 1998 Accepts Ltr as Official Notification to NRC of Univ of VA Intent to Decommission Univ of UVAR Reactor ML20216B6331998-04-0606 April 1998 Submits Answer to NRC Request for Addl Info Re Univ of VA Reactor UVAR & Univ VA Cavalier ML20217M1531998-04-0101 April 1998 Responds to NRC Re Violations Noted in Insp Repts 50-062/98-201 & 50-396/98-201 on 980126-28.Corrective Actions:Held make-up Evacuation Drill & Tested Evacuation Alarm.Greater Attention in Documenting & Filing Paperwork ML20217G6241998-03-30030 March 1998 Forwards Annual Rept of Operations of Univ of VA Reactor & Cavalier Reactor During Period 970101-1231,per Section 6.7.2 of TS ML20216G8581998-03-11011 March 1998 Forwards Request for Addl Info Re Review of Amend Request for License R-66,submitted on 980226.Responses Requested to Be Provided within 60 Days of Date of Ltr ML20197B7881998-03-0404 March 1998 Forwards Insp Rept 50-062/98-201 on 980126-28 & Notices of Violation & Deviation.Various Aspects of Radiation Protection & Safety Programs Were Inspected ML20203L9351998-02-18018 February 1998 Forwards Copy of Results of Operator Initial Exam Conducted at Univ of Virginia on 980115-16 ML20197F7171997-12-11011 December 1997 Forwards Insp Repts 50-062/97-201 & 50-396/97-201 on 971111- 13.No Violations Noted ML20197G1381997-12-11011 December 1997 Responds to Electronic Mail Message of 971201 Re Comparative Costs of Relicensing & Decommissioning non-power Reactors ML20198Q3541997-11-0303 November 1997 Confirms Arrangements P Isaac Made W/P Benneche for Administration of Operator Licensing Exams at Univ of Virginia Reactor.Exams Scheduled for Wk of 980112.Requests Ref Matl Listed in Encls ML20198F6671997-08-0101 August 1997 Informs That on 970804,non-power Reactor Insp Program Will Be Transferred from Region II Ofc to NRR ML20141K6131997-05-15015 May 1997 Forwards Insp Rept 50-062/97-01 on 970414-17.No Violations Noted ML20138H0911997-05-0707 May 1997 Forwards Scenerio for 961119 Emergency Drill IR 05000062/19960031997-04-22022 April 1997 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-062/96-03. Corrective Actions Will Be Examined During Future Insp ML20137V9121997-03-25025 March 1997 Forwards List of Phone Numbers & Directions to NRC Region II Ofc.Ofc Will Move to Atlanta Federal Center Complex on 970425.During Transition Period of 970425-27 Ofc Will Not Be Open for Business ML20137U9911997-03-18018 March 1997 Forwards Annual Rept of Operations of Univ of VA Reactor & Cavalier Reactor for Period 960101-1231.W/o Encl ML20141K4911997-02-17017 February 1997 Forwards Response to Violations Noted in Insp Rept 50-062/96-03.Corrective Actions:Reactor Staff Will Request Approval from Univ of VA Reactor Safety Committee for Changes to UVAR Emergency Plan & Implementing Procedures ML20133F8671996-12-20020 December 1996 Forwards Insp Rept 50-062/96-03 on 961118-21.No Violations or Deviations Noted 1999-08-16
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20211B1851999-08-16016 August 1999 Forwards Response to 990308 RAI Re Amends to License R-66 & Ts.Proposed Wording for possession-only License & Revised & New Ts,Included ML20211B9041999-08-16016 August 1999 Forwards Substitute Cavalier TS Pages 32 & 33 for NRC Copy of Cavalier TS Amend Application,Replacing Old Page 32 ML20217A6321999-05-24024 May 1999 Provides Advance Notification of Spent Nuclear Research Reactor Fuel Shipment R66-99-2 from Univ of Virginia Nuclear Facility to Savannah River,South Carolina.Encl Withheld ML20207A4371999-05-24024 May 1999 Forwards Advance Notification of Spent Nuclear Research Reactor Fuel Shipment R66-99-2 from U VA Nuclear Reactor Facility to Savannah River,Sc.Details Concerning Shipment in Attachment.Attachment Withheld ML20205J4271999-03-30030 March 1999 Submits Advanced Notification of Upcoming Spent Nuclear Reactor Fuel Shipment R66-99-1 from Univ of VA Nuclear Reactor Facility to Savannah River,Sc,Per 10CFR73.Details of Shipment,Encl.Without Encl ML20203A1331999-02-0303 February 1999 Requests That Senior Reactor Operator License SOP-70161,on Univ of VA Reactor (License R-66) of CA Bly,Be Terminated ML20206P2991999-01-0707 January 1999 Responds to NRC Re Violations Noted in Insp Rept 50-062/98-202.Corrective Actions:Correct Name for Content Matl Being Shipped Is Now Typed Onto All Shipping Forms ML20198F1101998-12-21021 December 1998 Requests 30-day Extension to Response to NRC Rai, ML20197H6901998-12-10010 December 1998 Submits Clarification of Request for Amend to Univ of VA Reactor TS Dtd 981203.Request Remains Active ML20197G9721998-12-0303 December 1998 Informs That Univ of VA Is in Process of Preparing Response to NRC 981123 RAI Re Proposed Set of UVAR TS Amends Submitted on 980929.Listed Are Two UVAR TS Considerations That Are Being Brought to NRC Attention for Resolution ML20198C8351998-10-30030 October 1998 Forwards Advance Notification of Spent Nuclear Research Reactor Fuel Shipment R66-98-1 from Univ of VA Nuclear Reactor to Savannah River,Sc.Details of Shipment Encl. Without Encl ML20155D4711998-10-30030 October 1998 Forwards Advance Notification of Spent Nuclear Research Reactor Fuel Shipment R66-98-1 from U VA Nuclear Reactor Facility to Savannah River,Sc.Details of Shipment Are Encl. Without Encl ML20154H9561998-10-0707 October 1998 Forwards Response to NRC Request for Addl Info Re Revised Reactor Operator Requalification Program ML20236X8071998-08-0303 August 1998 Forwards Revised Operator Requalification Program for NRC Review & Approval.New Program Takes Into Account de-facto Limitations of Licensed Ro/Sro Duties Just to Fuel Handling Activities,Given That Reactor Core Is Permanently Unloaded ML20236Q9931998-07-15015 July 1998 Withdraws 960319 Request That Revised Security Plan Become License Amend,Per 10CFR50.34 & 10CFR50.59,due to Permanent Shutdown of Univ of VA Reactor,Effective 980701 ML20249C3801998-06-22022 June 1998 Submits Formal Notification to Us NRC of Intention of Univ of VA to Begin Process That Will Lead to Decontamination & Decommissioning of Univ of VA Reactor Covered by License R-66 ML20249B8641998-06-18018 June 1998 Submits Response to NRC RAI Re TS Amend Request ML20217H7921998-04-23023 April 1998 Informs That Univ of VA Administration Had Made Decision to Move Toward Ceasing Operations of UVAR Reactor,As Stated in ML20217H7891998-04-15015 April 1998 Accepts Ltr as Official Notification to NRC of Univ of VA Intent to Decommission Univ of UVAR Reactor ML20216B6331998-04-0606 April 1998 Submits Answer to NRC Request for Addl Info Re Univ of VA Reactor UVAR & Univ VA Cavalier ML20217M1531998-04-0101 April 1998 Responds to NRC Re Violations Noted in Insp Repts 50-062/98-201 & 50-396/98-201 on 980126-28.Corrective Actions:Held make-up Evacuation Drill & Tested Evacuation Alarm.Greater Attention in Documenting & Filing Paperwork ML20217G6241998-03-30030 March 1998 Forwards Annual Rept of Operations of Univ of VA Reactor & Cavalier Reactor During Period 970101-1231,per Section 6.7.2 of TS ML20138H0911997-05-0707 May 1997 Forwards Scenerio for 961119 Emergency Drill ML20137U9911997-03-18018 March 1997 Forwards Annual Rept of Operations of Univ of VA Reactor & Cavalier Reactor for Period 960101-1231.W/o Encl ML20141K4911997-02-17017 February 1997 Forwards Response to Violations Noted in Insp Rept 50-062/96-03.Corrective Actions:Reactor Staff Will Request Approval from Univ of VA Reactor Safety Committee for Changes to UVAR Emergency Plan & Implementing Procedures ML20132F5931996-12-16016 December 1996 Responds to 960919 RAI Re TS Amend Request . Withdrawal of Proposed TS Amend,Requested ML20134L0571996-11-15015 November 1996 Requests 30 Day Extension for Response to NRC 960919 RAI Re 960528 Application for Amend to License R-66 ML20128N1421996-10-11011 October 1996 Requests Extension to 961119 Re Submittal of TS Amend RAI ML20117J2161996-05-28028 May 1996 Forwards Proposed TS Amend,Consisting of Revised (or Deleted) Definitions for Terms Reactor Secured,Reactor Shutdown,Reactor Operating,Reference Core Condition & Reactivity Limits ML20106J9561996-03-26026 March 1996 Forwards Public Version of Revised Epips,Including Rev 19 to EPIP-6 & Rev 19 to EPIP-14 ML20101N8651996-03-26026 March 1996 Forwards Rev 19 to EPIPs for Facility,Including EPIP 6,page 2,EPIP 6,Attachment 1,pages 1 & 2 & EPIP 14,Attachment 1, Page 1.Rev Reflects Changes in Personnel & Phone Numbers.W/O Encls ML20101E3891996-03-19019 March 1996 Forwards Proprietary Amendment to License R-66 Re Security Plan for Univ of VA Reactor Facility.Encl Withheld (Ref 10CFR2.790) ML20100K6001996-02-22022 February 1996 Forwards Revised Version of Reactor Facility Security Plan. Encl Withheld ML20094C4081995-10-26026 October 1995 Forwards Revised Pages to SAR & New Proposed TS 4.9, Surveillance of Activity in Secondary Coolant Sys, in Response to NRC 951025 RAI ML20093L1041995-10-19019 October 1995 Forwards NRC Questionaire & Licensee Answers Re Proposed Amend to SAR of 951010,including Proposed SAR Section 9.20.8 as Component of Response to NRC Question 6. Replacement of Proposed SAR Amend Also Encl ML20095F2681995-10-11011 October 1995 Forwards Univ of VA Nuclear Reactor Facility 1995 Annual Emergency Preparedness Drill Scenario.Requests That Encl of Ltr Be Held from NRC Public Document Room Until After Drill Event ML20093C7411995-10-10010 October 1995 Forwards SAR for Low-Enriched U Fueled Univ of VA Reactor ML20083P7031995-05-11011 May 1995 Advises That All HEU Fuel Elements Removed from Facility & Condition II.B.(4) Can Be Deleted from License R-66,in Response to NRC 950508 RAI Re Proposed Changes to License. Licensee Still Possesses HEU in Form of Fission Chambers ML20097J3921995-04-20020 April 1995 Forwards Response to NRC 950309 RAI Re Proposed Changes to Ts.Revised TS Also Encl ML20082N9141995-04-19019 April 1995 Forwards Estimated Uncertainity for Univ of VA Reactor Reactivity Measurements ML20081L9751995-03-27027 March 1995 Forwards Rev 18 to EPIPs & Rev 3 to Emergency Plan ML20078C7201994-10-26026 October 1994 Requests That NRC Take No Further Action on Review of Security Plan Proposed by Licensee on 900713,in View of Completed Conversion of Univ of VA Reactor to LEU Fuel & Upcoming Decommissioning of 100W Cavalier Reactor ML20077C3841994-10-18018 October 1994 Forwards Univ of VA Nuclear Reactor Facility 1994 Emergency Preparedness Drill Scenario for 941122 ML20076F9031994-10-13013 October 1994 Forwards HEU to LEU Fuel Conversion Rept, as Required by Attachment to Amend 20,License R-66 ML20077S3361994-07-29029 July 1994 Submits Affidavit Re NRC Request for Publication of Proprietary & Confidential Info of Protechnics Intl,Inc,In Connection W/Spill Which Took Place at Univ of VA Reactor Facility in 1992 & Reported to NRC by Univ on 920911 ML20070G2781994-07-13013 July 1994 Responds to NRC Re Violations Noted in Insp Rept 50-062/94-04.Corrective Action:Many Routine Surveys Performed ML20063F9101994-01-14014 January 1994 Forwards Rev 16 to Epips.Requests Ack Receipt & Filing of Rev by Returning Completed Cover Sheet.W/O Encl ML20062N6471994-01-10010 January 1994 Informs That Rd Flack Named Dept Chairman,Effective 931201 ML20059K0121993-11-0404 November 1993 Informs Nrc,Rd Flack,Named Acting Chair of Dept of Mechanical,Aerospace & Nuclear Engineering by Dean of School of Engineering & Applied Science ML20056F7791993-08-26026 August 1993 Responds to NRC Re Violations Noted in Insp Rept 50-062/93-01.Corrective Actions:Complete Review of Console Schematics & Electronics Performed & Improved Labelling Sys Adopted for Modules in Console 1999-08-16
[Table view] |
Text
r 5049-SCHOOL OF ENGINEERING $
April 19,1995 & APPUED SCIENCE DEPARTMENTOFMECil4NICAL, AEROSPACE (
Mr. Alexander Adams AsouvCtc4aEscisEEnzsc U.S. Nuclear Regulatory Commission Mail Stop 10-D-21 university of virginia Thornton Hall Washinbton D.C. Charlottesville, VA 22903-2442 20555 go4/924-7421 FAX: 804/982-2037 TDD: 804/982 HEAR Phone: (301) M4-1127 NRC Facsimile: (301) 415-2260 Phone then Fax: (301) 415-1032 Re: Estimated uncertainty for UVAR reactivity measurements
Dear Mr. Adams,
In reply to (INEL) Mr. James Miller's request for reactivity coefficient values and uncertainties associated with the LEU UVAR core, we have extracted pertinent information listed in the IIEU to LEU Conversion Report, UVN527367/ MANE 95/101, dated October 1994. The reactivity measurements furnished in attachment can be accepted at an estimated +- 10% uncertainty level.
I am still trying to obtain supporting information concerning the HEU-18 Expt data listed in Table 3 of the " Safety Analysis for the University of Virginia Reactor LEU Conversion" paper presented at the XII International RERTR Meeting, in September of 1989. It should be noted that an LEU fuel element has the same external dimensions, and same plate dimensions, as that of the old HEU element. However, LEU elements have 22 fuel plates, rather than 18 plates, each.
Sincerely, W'W Robert U. Mu der, Director U.VA. Reactor Facility enc: HEU and LEU reactivity parameters
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,,J SHUTDOWN MARGIN - 1.2 % delta k/k June 13. 1994
.- Date EXCESS REACTIVITY + 3.27 % delta k/k U-235 4807 GRAMS EXPERIMENT WORTH 1.63 % delta k/k I
F - Normal Fuel Element P - Grid Plate Plug
~
- v. PF - Partial Fuel Element HYD RAB - Hydraulic Rabbit
{ CR - Control Rod Fuel Element THER RAB - Thermal Pneumatic Rabbit
'a- G - Graphite Element EPI RAB - Epithermal Pneumatic Rabbit S - Graphite Source Element RB - Radiation Basket F'
REG - Control Rod Fuel Element with Regulating Rod Er Rod Vorths #1 - 2.80 % #2 - 2.63 % #3 - 1.84 % Ree - 0.401 %
r r
MINERAL IRRADIATION FACILITY
~
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F F F-REG F F
, P VS-015 VS-009 VC-001 VS-013 VS-004 C P 11 12 13 14 15 16 17 A 18 N
F F-CR1 PF F F I P VS-006 VC-002 VP-001 VS-007 VS 008 S P 27 T 21 22 23 24 25 26 28 E
F F F. F-CR2 F R G VS-001 VS-010 VS-011 VC-003 VS-012 P 31 32 33 34 35 36 37 I 38 R
F F F-CR3 F F R.
r- G VS-014 VS-003 VC-004 VS-002 VS-005 P
, _ _ 41 42 43 44 45 46 47 F 48 A
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G G HT-1 G HT-3 S P
~
51 52 53 54 55 56 57 58 EPI u G G G RAS C G G G 61 62 63 64 65 66 67 68
- THER HYD C G RAB G G RAB G G 71 72 73 74 75 76 77 78 G G G G G G G G 81 82 83 84 85 86 87 88 Figure 9. LEU-2 Core Loading Diagram W -
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16
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-_ ROD #2 - 2.63 %
-- ROD #3 - 1.84 %
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The excess reactivity of LEU-2 was measured experimentally to be + 3.27 %
Ak/k, well below the + 5.0 % Ak/k limit required by the Technical Specifications.
i-b) Experimental Facilities m-Before operating at any appreciable power, various experimental facilities were installed in the reactor and the reactivity worth of each facility was determined with the following results:
Exnerimental Facility Worth (%Ak/kT
'" Epi-Thermal Rabbit, grid position 64 - 0.01 Thermal Rabbit, grid position 73 - 0.01 Hot Thimble #1, with specimens, grid position 53 - 0.28
" Hot Thimble #3, without specimens, grid position 55 - 0.54 Canister Irradiation Facility, east side of core - 0.04 The sum of the absolute worth of the experimental facilities is 0.88 %Ak/k, well below the 2 %Ak/k limit for all experiments required by the Technical Specifications.
f*
c) Approach to Full Power The initial approach to power with the LEU-2 core was begun on the afternoon of May 12,1994. The power was leveled out at 200 kW,500 kW,1 MW, and I i.
finally 2 MW to check instrument response and to perform radiation surveys.
Full power of 2 MW was achieved at about 5:20 P.M. Radiation surveys at the reactor bridge and around experimental areas showed no increase in radiation levels as compared to the HEU core. ;
., d) Power Coefficient Measurement The reactor was taken critical at low power in a xenon-free condition and the critical rod positions were noted. Rod #2 was withdrawn about 0.5 inch to put
" the reactor on a positive period. Doubling times were measured with a stop watch using the linear instrument. The power was allowed to rise until it leveled off at 870 kW due to negative temperature effects. The average temperature rise across
" the core was noted. The doubling times were converted to reactivity and matched ahnost exactly with the reactivity worth of rod #2 when it was withdrawn as ,
i determined from the rod worth curve. The power coefficient was experimentally verified to be -0.139 %Ak/k/MW or in terms of the change in average core temperature - 0.0275 %Ak/k/F. It is noted that this measurement includes several effects such as the fuel doppler, fuel expansion, and moderator temperature i g
1 coefficients. The moderator temperature coefficient was measured separately.
)
Hl
- 19 w
7 u -
y e) Moderator Temperature Coefficient Measurement The reactor was operated all day at full power on May 13,1994 and the pool temperature was 97.9 'F when the reactor was shut down. The cooling
~ systems were secured and the reactor remained shut down for three days to allow Xenon to decay. The reactor was taken critical at low power on May 16,1994.
The pool temperature was 86.9 'F and the AT was 0.0 'F. The secondary cooling system was energized and the pool was allowed to cool down. The power level was maintained by adjusting Rod #2. The pool was cooled for 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. The Core outlet temperature changed by 11.24 *F. Rod #2 moved from 14.39 inches at the beginning of the test to a final position of 14.16 inches. The reactivity
~
associated with this change was obtained from the rod worth curves and determined to be 0.05 % Ak/k.
~~ Rod #2 was then moved back to it's original position of 14.39 and doubling times were taken to determine the reactivity associated with the rod movement as a
, check against the rod curves. The reactivity associated with the doubling times was 0.039 % Ak/k. Due to incomplete mixing from the cooldown the moderator l, ,j temperature increased 2.06 F during this measurement giving a temperature 3 differential 9.18 *F as compared with the original temperature. Ar average of
_ _l these measurements yielded a value of- 0.0044 %Ak/k/ F for the moderator temperature coefficient.
~
_ f) Experimental Facilities Between May 23,1994 and June 10,1994, several other experiments were loaded in the reactor, giving the following experiments and experimental facilities now in the reactor.
Worth (% Ak/k) l
- 1. Epi-Thermal Rabbit, grid position 64 - 0.01 7 2. Thermal Rabbit, grid position 73
- 0.01
- 3. Hot Thimble #1, with specimens, grid position 53 - 0.28
_ 4. Hot Thimble #3, without specimens, grid position 55 - 0.54
- 5. 1.2 kg of Fe samples in H.T. #3 + 0.05
- 6. Cannister Irradiation Facility (East side of core) - 0.04
- 7. MIF Stand, front of core on pool floor 0.00
~
- 8. MIF Lead Shield, front of core on MIF stand + 0.33
- 9. MIF Box, Model 3, #2 (Gas cooled), North side of core - 0.37 w
l The sum of the absolute worth of the experimental facilities is 1.63 %Ak/k, which !
. is below the Technical Specification limit of 2.0 % for all experiments.. '
20
)
1 VI. Comparison Between LEU and IIEU Cores The LEU-1 core was similar to an HEU core operated in 1975. They were both
~
4x4 configurations surrounded by graphite. Due to the increased U-235 content of the LEU fuel, with changes from 18 to 22 plates per element, partial elements were loaded in grid positions 23 and 26 in the LEU core. Comparisions of the two cores are as follows:
, HEU Core LEU-1 Core (2.73 kg U-235) (3.57 ke U-235)
Rod Worth (% Ak/k)
Rod #1 3.56 3.46
~~
Rod #2 3.75 3.86 Rod #3 2.30 2.41 Reg Rod 0.428 0.375 3 Shutdown Margin (% Ak/k)
__ ] (Rod #2 and Reg withdrawn) -2.7 - 1.21 Excess Reactivity (% Ak/k) + 3.35 + 4.66
~~~
The control rod worths that were computed for both the HEU and LEU-1 cores were in good agreement with these measured values.
A comparison of the measurements made with the LEU fuel and predictions in the LEU SAR, and HEU comparisons, where available, are presented below.
~
The " Power" temperature coefficient was measured during a core-heat-up experiment. It is expressed as the change in Ak/k per average change in core temperature. This is not
_ the same conceptually as the isothermal moderator temperature coefficient, which was measured during a pool-cool-down experiment at low power.
- moom, mese' s
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21 w
L.
LEU Core L EU-SAR HEU Core Power Coeff. (% Ak/k/MW) - 0.139 NA NA
~
" Power" Temperature
~
Coefficient (% Ak/k/'F)(LEU-2) .0275 NA .0288 Moderator Temp. Coefficient
(% Ak/k/'F) (LEU-2) .0044 .0082 NA
~
~ Void Coefficient (uniform)
(% Ak/k/% void)(LEU-1) - 0.19 - 0.22 NA The most significant observation is that the " Power" temperature coefficients for the old HEU and new LEU-2 cores are almost identical. signifying that the safety characteristics
_ of the two cores are essentially the same.
The isothermal moderator temperature coefficient value is clearly different from the
" Power" temperature coefficient value, but it was not expected to be comparable. The
~
j measured isothermal moderator temperature coefficient is about a factor of 2 smaller than the value calculated for an ideal unrodded LEU core model. Considering experimental uncertainties in the measurement, and the lack of partially inserted control
_ rods in the computational model, the agreement is judged to be acceptable.
L-- The void coefficient measurements lie in the range of the calculated void coefficients.
Local experimental differences are expected te be caused by the presence of partially inserted control rods in the core.
VII. Shipment of All IIEU Fuel Elements From Facility All HEU fuel (32 elements) was shipped to Savannah River in the BMI-1 \
l'
" shipping cask in three shipments made on May 4,1994, June 6,1994, and
"_ July 8,1994, respectively.
22 M
-