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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M3801999-10-21021 October 1999 Forwards Insp Rept 50-263/99-06 on 990813-0923.Four Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217G0711999-10-13013 October 1999 Forwards Insp Rept 50-263/99-12 on 990913-17.No Violations Noted ML20217B1421999-09-30030 September 1999 Informs That on 990902,NRC Staff Completed mid-cicle Plant Performance Review of Monticello Nuclear Generating Station. Staff Conducted Reviews for All Operating NPPs to Integrate Performance Information & to Plan for Insp Activities ML20212K9131999-09-30030 September 1999 Refers to 990920 Meeting Conducted at Monticello Nuclear Generating Station to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA ML20216J2491999-09-30030 September 1999 Ack Receipt of 980804,990626 & 0720 Ltrs in Response to GL 98-01,suppl 1, Year 2000 Readiness of Computer Sys at Npps. Staff Review Has Concluded That All Requested Info Has Been Provided ML20216G4341999-09-24024 September 1999 Forwards Exam Rept 50-263/99-301 on 990823-26.Violation Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy.Test Was Administered to Two Applicants. Both Applicants Passed All Sections of Exam ML20212G7171999-09-24024 September 1999 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Its.Conversion Package Submittal Continues to Be Targeted for Aug of 2000 ML20216J8091999-09-24024 September 1999 Informs That New Diaphragm Matl Has Corrected Sticking Problem Associated with Increased Control Rod Drive Scram Times.Augmented Testing of Valves at Monticello Has Been Discontinued ML20212G9801999-09-23023 September 1999 Refers to Resolution of Unresolved Items Identified Re Security Alarm Station Operations at Both Monitcello & Prairie Island ML20212F0901999-09-21021 September 1999 Confirms Discussion Between M Hammer & Rd Lanksbury to Have Routine Mgt Meeting on 991005 in Lisle,Il.Purpose of Meeting to Discuss Improvement Initiatives in Areas of Operations & Equipment Reliability ML20212A9761999-09-0909 September 1999 Submits 1999 Annual Rept of Any Changes or Errors Identified in ECCS Analytical Models or Applications ML20217A5751999-09-0909 September 1999 Forwards Individual Exam Results for Licensee Applicants Who Took Aug 1999 Initial License Exam.Without Encls ML20211Q6981999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Monticello Operator License Applicants During Wks of 010604 & 11.Validation of Exam Will Occur at Station During Wk of 010514 ML20211L1981999-09-0101 September 1999 Forwards Insp Rept 50-263/99-05 on 990702-0812.No Violations Noted ML20211K7971999-09-0101 September 1999 Informs That Util Reviewed Rvid as Requested in NRC .Recommended Corrections Are Listed ML20211K2591999-08-27027 August 1999 Forwards NSP Co Fitness for Duty Program Performance Data for Six Month Period Ending 990630 ML20211F9961999-08-26026 August 1999 Forwards Effluent & Waste Disposal Semi-Annual Rept for 990101-990630, Revised Effluent & Waste Disposal Semi-Annual Rept for 980701-981231 & Revs to ODCM for Monitcello Nuclear Generating Plant ML20211C9501999-08-23023 August 1999 Forwards Rev 17 to Monticello Nuclear Generating Plant USAR, Updating Info in USAR to Reflect Implementation of Increase in Licensed Core Thermal Power from 1,670 Mwt to 1,775 Mwt.Rept of Changes,Tests & Experiments Not Included ML20210T9601999-08-12012 August 1999 Provides Rept on Status of Util RPV Feedwater Nozzle Insps Performed in Response to USI A-10 Re BWR Nozzle Cracking ML20210U1831999-08-12012 August 1999 Revises 980202 Commitment Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions ML20210Q0341999-08-0404 August 1999 Forwards SE Granting Licensee 980724 Relief Request 10 Re Third 10-year Interval ISI Program Plan,Entitled, Limited Exam ML20210H0861999-07-28028 July 1999 Forwards Insp Rept 50-263/99-04 on 990521-0701.No Violations Noted.Licensee Conduct at Monticello Facility Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Appropriate Radiological Controls ML18107A7051999-07-20020 July 1999 Provides Suppl Info Which Supersedes Info in 990625 Ltr in Response to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. ML20212H3191999-07-16016 July 1999 Forwards Aug 1999 Monticello RO Exam Package,Including Revised Outlines.All Changes Are in Blue Font ML20209G5621999-07-14014 July 1999 Forwards Insp Rept 50-263/99-11 on 990621-24.No Violations Noted.Objective of Insp,To Determine Whether Monticello Nuclear Generating Station Emergency Plan Adequate & If Station Personnel Properly Implemented Emergency Plan ML20196J5351999-07-0202 July 1999 Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950515 & NSP Responses & 980917 for Monticello Npp.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 ML20196J9681999-07-0101 July 1999 Informs That in Sept 1998,Region III Received Rev 20 to Portions of Util Emergency Plan Under 10CFR50.54(q).Based on Determination That Changes Do Not Decrease Effectiveness of Licensee Emergency Plan,No NRC Approval Required ML20209B6151999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Y2K Readiness Disclosure Attached ML20196H2291999-06-24024 June 1999 Responds to Administrative Ltr 99-02,dtd 990603,requesting Licensee to Provide Estimate of Licensing Action Submittals Anticipated.Four New Submittals Per Year Are Anticipated IR 05000263/19990031999-06-18018 June 1999 Forwards Insp Rept 50-263/99-03 on 990409-0520.Four Violations Noted & Being Treated as non-cited Violations, Consistent with App C of Enforcement Policy ML20207D5851999-05-25025 May 1999 Submits Info Re Partial Fulfillment of License Conditions Placed on Amend 101,which Approved Use of Ten Exceptions for 24 Months Subject to Listed App C Conditions.Util Will Submit Second Rept to Obtain Approval for Continued Use ML20206S0911999-05-17017 May 1999 Forwards Response to NRC 990324 RAI Re Proposed Amend to pressure-temp Limits & Surveillance Capsule Withdrawal Schedule, .Supporting Calculations Also Encl ML20206N5601999-05-13013 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Cm Craig Will Be Section Chief for Monticello Npp.Organization Chart Encl ML20206G2181999-05-0505 May 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, Dtd 960110,for Plant ML20206G4901999-05-0404 May 1999 Forwards Staff Review of Licensee 960508 Response to NRC Bulletin 96-002, Movement of Heavy Loads Over Sf,Over Fuel in Rc or Over Safety-Related Equipment, .Overall, Responses Acceptable.Tac M95610 Closed ML20206G7741999-05-0303 May 1999 Forwards Insp Rept 50-263/99-02 on 990223-0408.One Violation Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20206D1651999-04-27027 April 1999 Forwards Radiation Environ Monitoring Program for MNGP for Jan-Dec 1998, Per Plant TS 6.7.C.1.Ltr Contains No New NRC Commitments or Modifies Any Prior Commitments ML20205N0821999-04-12012 April 1999 Forwards SE of NSP Response to NRC GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Licensee Adequately Addressed Actions Requested in GL ML20205N4811999-04-0909 April 1999 Forwards Licensing Requalification Insp Rept 50-263/99-10 on 990308-12.No Violations Noted.However,Inspectors Through Observation of Simulator Scenario Exams Noted Difficulties in Ability of SM to Simultaneously Implement Duties of SM ML20205N5301999-04-0909 April 1999 Discusses Arrangements Made on 990406 for Administration of Licensing Exams at Monticello Nuclear Generating Station During Wk of 990823.Requests That Exam Outlines Be Submitted by 990128 & Supporting Ref Matls by 990719 ML20196K7831999-03-31031 March 1999 Forwards Decommissioning Funding Status Rept for Monticello & Prairie Island Nuclear Generating Plants,Per Requirements of 10CFR50.75(f)(1) ML20205H5731999-03-29029 March 1999 Submits Required 1998 Actual & 1999 Projected Cash Flow Statements for Monticello Nuclear Generating Plant & PINGP, Units 1 & 2.Encl Contains Proprietary Info.Proprietary Info Withheld,Per 10CFR2.790(b)(1) ML20205C6561999-03-26026 March 1999 Submits Semiannual Update on Project Plans for USAR Review Project & Conversion to ITS ML20205C4851999-03-26026 March 1999 Informs That on 990203,NRC Staff Completed PPR of Nuclear Plant.Staff Conducts Reviews for All Operating NPPs to Develop an Integrated Understanding of Safety Performance ML20205A5881999-03-24024 March 1999 Forwards Request for Addl Info Re Submittal Requesting Rev of pressure-temperature Limits & Surveillance Capsule Withdrawal Schedule ML20204H4711999-03-18018 March 1999 Forwards SER Concluding That Util Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Monticello & Adequately Addressed Actions Requested in GL 96-05 ML20207H5161999-03-11011 March 1999 Forwards Insp Rept 50-263/99-01 on 990112-0222.No Violations Noted ML20207F4091999-02-28028 February 1999 Forwards Fitness for Duty Program Performance Data for Six Month Period from 980701-981231,IAW 10CFR26.71 ML20207F6741999-02-24024 February 1999 Forwards Summary of Nuclear Property Insurance Maintained at Monticello & Prairie Island Nuclear Generating Plants ML20207F6901999-02-23023 February 1999 Forwards Effluent & Waste Disposal Semi-Annual Rept for 980701-981231, Off-Site Radiation Dose Assessment for 980101-981231 & Revised Effluent & Waste Disposal Semi- Annual Rept for 980101-980630, for Monticello 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20216J8091999-09-24024 September 1999 Informs That New Diaphragm Matl Has Corrected Sticking Problem Associated with Increased Control Rod Drive Scram Times.Augmented Testing of Valves at Monticello Has Been Discontinued ML20212G7171999-09-24024 September 1999 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Its.Conversion Package Submittal Continues to Be Targeted for Aug of 2000 ML20212A9761999-09-0909 September 1999 Submits 1999 Annual Rept of Any Changes or Errors Identified in ECCS Analytical Models or Applications ML20211K7971999-09-0101 September 1999 Informs That Util Reviewed Rvid as Requested in NRC .Recommended Corrections Are Listed ML20211K2591999-08-27027 August 1999 Forwards NSP Co Fitness for Duty Program Performance Data for Six Month Period Ending 990630 ML20211F9961999-08-26026 August 1999 Forwards Effluent & Waste Disposal Semi-Annual Rept for 990101-990630, Revised Effluent & Waste Disposal Semi-Annual Rept for 980701-981231 & Revs to ODCM for Monitcello Nuclear Generating Plant ML20211C9501999-08-23023 August 1999 Forwards Rev 17 to Monticello Nuclear Generating Plant USAR, Updating Info in USAR to Reflect Implementation of Increase in Licensed Core Thermal Power from 1,670 Mwt to 1,775 Mwt.Rept of Changes,Tests & Experiments Not Included ML20210T9601999-08-12012 August 1999 Provides Rept on Status of Util RPV Feedwater Nozzle Insps Performed in Response to USI A-10 Re BWR Nozzle Cracking ML20210U1831999-08-12012 August 1999 Revises 980202 Commitment Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions ML18107A7051999-07-20020 July 1999 Provides Suppl Info Which Supersedes Info in 990625 Ltr in Response to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. ML20212H3191999-07-16016 July 1999 Forwards Aug 1999 Monticello RO Exam Package,Including Revised Outlines.All Changes Are in Blue Font ML20209B6151999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Y2K Readiness Disclosure Attached ML20196H2291999-06-24024 June 1999 Responds to Administrative Ltr 99-02,dtd 990603,requesting Licensee to Provide Estimate of Licensing Action Submittals Anticipated.Four New Submittals Per Year Are Anticipated ML20207D5851999-05-25025 May 1999 Submits Info Re Partial Fulfillment of License Conditions Placed on Amend 101,which Approved Use of Ten Exceptions for 24 Months Subject to Listed App C Conditions.Util Will Submit Second Rept to Obtain Approval for Continued Use ML20206S0911999-05-17017 May 1999 Forwards Response to NRC 990324 RAI Re Proposed Amend to pressure-temp Limits & Surveillance Capsule Withdrawal Schedule, .Supporting Calculations Also Encl ML20206D1651999-04-27027 April 1999 Forwards Radiation Environ Monitoring Program for MNGP for Jan-Dec 1998, Per Plant TS 6.7.C.1.Ltr Contains No New NRC Commitments or Modifies Any Prior Commitments ML20196K7831999-03-31031 March 1999 Forwards Decommissioning Funding Status Rept for Monticello & Prairie Island Nuclear Generating Plants,Per Requirements of 10CFR50.75(f)(1) ML20205H5731999-03-29029 March 1999 Submits Required 1998 Actual & 1999 Projected Cash Flow Statements for Monticello Nuclear Generating Plant & PINGP, Units 1 & 2.Encl Contains Proprietary Info.Proprietary Info Withheld,Per 10CFR2.790(b)(1) ML20205C6561999-03-26026 March 1999 Submits Semiannual Update on Project Plans for USAR Review Project & Conversion to ITS ML20207F4091999-02-28028 February 1999 Forwards Fitness for Duty Program Performance Data for Six Month Period from 980701-981231,IAW 10CFR26.71 ML20207F6741999-02-24024 February 1999 Forwards Summary of Nuclear Property Insurance Maintained at Monticello & Prairie Island Nuclear Generating Plants ML20207F6901999-02-23023 February 1999 Forwards Effluent & Waste Disposal Semi-Annual Rept for 980701-981231, Off-Site Radiation Dose Assessment for 980101-981231 & Revised Effluent & Waste Disposal Semi- Annual Rept for 980101-980630, for Monticello ML20203A3081999-01-28028 January 1999 Forwards TS Page 60d,as Supplement 3 to 971125 LAR Re CST Low Level Hpci/Rcic Suction Transfer.Page Includes NRC Approved Amend 103 Changes for Use by NRC in Issuing SER ML20202F7821999-01-27027 January 1999 Forwards 1999 Four Year Simulator Certification Rept for MNGP Simulation Facility, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(vi).Ltr Contains No New Commitments or Modifies Any Prior Commitments ML20206S0331999-01-20020 January 1999 Submits Annual Rept of Safety & Relief Valves Failure & Challenges ML20206P1221998-12-31031 December 1998 Forwards LAR for License DPR-22,revising TS pressure-temp Curves Contained in Figures 3.6.1,3.6.2,3.6.3 & 3.6.4, Deleting Completed RPV Sample SRs & Requirement to Withdraw Specimen at Next Refueling Outage & Removing Redundant SR ML20198M3271998-12-28028 December 1998 Submits Change to Commitment for Submittal of ITS Application.Util Plans to Provide ITS Conversion Package Submittal to NRC in Dec of 2000 ML20198J7511998-12-22022 December 1998 Informs of Completion of Listed Commitment Made in Re Severe Accident Mgt. Severe Accident Mgt Guidelines Have Been Assessed,Plant Procedures Have Been Modified & Training of Affected Plant Staff Has Been Completed ML20198J4311998-12-21021 December 1998 Forwards Rev 2 to SIR-97-003, Review of Test Results of Two Surveillance Capsules & Recommendations for Matls Properties & Pressure-Temp Curves to Be Used for Monticello Rpv. Under Separate Cover,Licensee Is Providing LAR to Revise Curves ML20198J7711998-12-14014 December 1998 Documents 981214 Discussion with NRC Staff Re Deviation from Emergency Procedure Guidelines ML20195C9631998-11-11011 November 1998 Forwards 120-day Response to NRC GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment ML20195C8781998-11-11011 November 1998 Forwards Supplement to 971125 License Amend Request Re Condensate Storage Tank Low Level Suction Transfer Setpoints for HPCI Sys & Reactor Core Isolation Cooling Sys ML20195E2261998-11-10010 November 1998 Submits Suppl 1 to Util Response to NRC Request for Addl Info Re 981118 Request for Deviation from Emergency Procedure Guidelines ML20155H6591998-11-0404 November 1998 Forwards Response to 980910 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20155F9091998-10-27027 October 1998 Forwards Master Table of Contents to Rev 16 of Usar.Info Was Inadvertantly Omitted at Time of 981023 Submittal ML20155A2661998-10-23023 October 1998 Forwards Rev 16 to USAR for Monticello Nuclear Generating Plant. Summary of Changes,Tests & Experiments Made Under Provisions of 10CFR50.59(b)(2) Also Encl.Rev Updates Info in USAR for Period Up to 980801 05000263/LER-1998-005, Forwards LER 98-005-00,re HPCI Being Removed from Service to Repair Steam Leak in Drain Trap Bypass.Commitments Made by Util Are Listed1998-10-21021 October 1998 Forwards LER 98-005-00,re HPCI Being Removed from Service to Repair Steam Leak in Drain Trap Bypass.Commitments Made by Util Are Listed ML20154L9321998-10-12012 October 1998 Forwards Suppl 2 to LAR & Suppl 980319,which Proposed Changes to Ts,App a of Operating License DPR-22 for Mngp.Number of Addl Typos & One Title Change on Pages Associated with Amend Request Have Been Identified 05000263/LER-1998-004, Forwards LER 98-004-00 Re Manual Scram Inserted Following Pressure Transient Closes Air Ejector Suction Isolation Valves & Trips Offgas Recombiners.Ler Contains Listed Commitment1998-10-0909 October 1998 Forwards LER 98-004-00 Re Manual Scram Inserted Following Pressure Transient Closes Air Ejector Suction Isolation Valves & Trips Offgas Recombiners.Ler Contains Listed Commitment ML20154L8671998-10-0909 October 1998 Forwards Suppl 1 to LAR for License DPR-22, Replacing Exhibits B & C of Original Submittal to Reflect Item 2 & Subsequent Changes.Request for APRM Flow Converter Calibr Interval Extension,Withdrawn ML20154J6201998-10-0505 October 1998 Forwards Rev 49 to Monticello Security Plan.Encl Withheld, Per 10CFR73.21 ML20154D7921998-10-0101 October 1998 Forwards Response to NRC RAI Re Licensee 971118 Request for Deviation from Emergency Procedures Guidelines.Proprietary Flow Charts,Including Rev 5 to C.5-110 RPV Control & Rev 6 to C.5-110 RPV Control, Encl.Proprietary Info Withheld ML20154D8031998-09-25025 September 1998 Submits Annual Rept of Any Change or Error Identified in ECCS Analytical Models or Application ML20153F0051998-09-25025 September 1998 Forwards Suppl 1 to 971031 Application for Amend to License DPR-22,replacing Exhibit C Which Contains TS Pages Incorporating Proposed Changes Described in Original 971031 Request ML20153F5351998-09-25025 September 1998 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Improved TS ML20153E0331998-09-17017 September 1998 Forwards Response to NRC 980629 RAI Re RPV Weld Chemistry Values Previously Submitted as Part of Plant Licensing Basis.Next Monticello RPV Sample Capsule Scheduled to Be Removed During 1999/2000 Refueling Outage ML20153D1441998-09-17017 September 1998 Informs NRC That Listed Commitments 1 & 3 Were Completed by End of 1998 Refueling Outage.Commitments Involved Final Disposition of Remaining Outlier Components Re All Known Outstanding Work Associated with GL 87-02,Suppl 1,USI A-46 ML20153D8561998-09-17017 September 1998 Forwards Rev 17 to EPIP A.2-414, Large Vol Liquid Sample &/ or Dissolved Gas Sample Obtained at Post Accident Sampling Sys. Superseded Procedures Should Be Destroyed.Ltr Contains No New NRC Commitments,Nor Does It Modify Prior Commitments ML20153E9011998-09-0909 September 1998 Forwards Rev 1 to MNGP Colr,Cycle 19, Incorporating Changes to power-flow Maps in Figures 6 & 7.Changes Made to Correct Errors in Stability Exclusion Region & Stability Buffer Region Shown on Rev 0 ML20151S7401998-08-28028 August 1998 Responds to NRC Re Violations Noted in Insp Rept 50-263/98-09.Corrective Actions:Procedure 4 AWI-04.04.03 Will Be Revised to Eliminate Term Urgent from Section 4.3.1.D 1999-09-09
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NORTNERN STATES POWER COMPANY MIN N E APO Li m. M t N N E SOTA B 54o1
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Dear Mr. Grier:
NONTICELI4 NUCISAR CENERATING FIANT Docket No. 50-263 Licese No. DPR-22 Response to July 26,197314tter on Shutdown Margin Testing on August 3, 4 and 5,1973, Shutdown Harnin Verification tests were ecrapieted on all 121 control rods at the Monticc11o Daelear Generating Plant as stipu-lated in the July 26, 1973 letter frena B B Grier to L J Wachter. Rese tests were perforraed in accordance with the AEC criteria prebented in our August 2,1973 telephone conversat.Lon documented in an August 3,1973 letter frema D L Etemann to L 0 Mayer. % ese criteria required dennonstrating a shutdown margin of 0.75% delta k with allowance for transient xenon and samaritus so long as no amore than two control rods were withdruun fums the fully inserted post.Lon. Testing of peripheral rods cosamenced 77 hours8.912037e-4 days <br />0.0214 hours <br />1.273148e-4 weeks <br />2.92985e-5 months <br /> after the July 31, 1973 shutdown. Subcriticality was verified for each test condition.
Attached is a tabulation of 199 shutdown margin d*=mmtrations, some rods being tasted more than once. The tests are grouped into three cat *Eories:
Tuo Rod Out testa shodthat two adjacent CODtrol Inds TED could be fully withdrawn while maintainJng subcriticality.
This was done on the periphery where indiviqutt rod worths are very anali.
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RSP Calculations taere done by NSP prior to receiving the final AEC criteria. Tests were specified to demonstrate greater than or equal to 1% delta k abutdown margin with anc rod out.
The transient zanon and samarium was less than 0.257, detta k at the time of these tests so the AEC criteria vers satisfied.
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l GE calculations were likeurise done by CE prior to receiving ABC criteria. Their tr_ats were designed to demonstrate a shutdown margin of greater than or equal to 1.27A delta k with one rod out.
This larger margin was chosen to allow testing to be done at sodar-ator temperatures op to 125'F tahich adds a naastivity reactivity of up to 0.20% detta k.
Testing aus done with moderstor temperatures between 95 and 1000F dtich involves no significanc $ange in reactivity from the cold condition. Transient =*** and samarium wa less than 0.25% delta k during these tests also such that ABC criteria were satisfied.
Should thers be any questions regarding the tabulated test results, please feel fue to contact us.
Yours very truly,
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LJ achter Vice President -
Power Production & System Operation IJU/br cc: D L Zin=*=
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15 10-43 14-39 48 110 16 14-43 18-39 14 CE/NSP 17 18-43 22-39 14 GE 18 22-43 26-39 48 GE 19 22-43 26-47 06 NSP 20 26-43 30-39 48 GE 21 26-43 22-47 06 E5P 22 30-43 26-39 48 m
23 30-43 26-47 06 NSP 24 34-43 30-39 14 CE 25 38-43 34-39 14 CE/Nsr 26 42-43 38-39 48 nto 27 06-39 10-35 08 CE 28 06-39 06-35 48 TKOf 29 10-39 14-35 14 CE/NEP 30 14-39 18-35 14 2
31 14-59 10-35 08 NSP 32 18-39 22-35 14 CE 33 18-39 14-43 06 R5P 34 22-39 26-35 14 CE 35 22-39 18-43 08 NSP 36 26-39 30-35 14 GE 37 25-39 22-35 08 NSF 38 30-39 26-35 14 GE 39 30-39 34-43 08 WSP 40 34-39 30-35 14 m
41 34-39 38-43 06 NSP 2
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54 21-35 16-39 10 ESP 55 26-35 i
30-31 44 GE 56 26-35 22-39 08 N8P r.J.
57 30-35 26-31 58 30-35 34-39 48 CE 10 B&P 59 34-35 30-31 44 GE l
60 34-35 38-39 08 NSF 61 38-35 34-31 14 GE l
62 38-35 42-39 06 R$P 63 42-35 38-31 14 GE 64 46-35 42-31 08 GE 65 02-31 06-27 08
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76 26-31 30-27 48 GE 77 26-31 22-35 12 BSP 78 30-31 26-27 48 m
79 30-31 34-35 08 BEF 80 34-31 30-27 44 m
j 81 34-31 38-35 10 NSP i
42 38-31 34-27 14 GE j
83 38-31 42-35 08 NSF g
84 42-31 38-27 48 GE 85 42-31 46-27' 06 use 86 46-31 42-35 10 R$P i
87 50-31 46-27 08 GE 88 50-31 50-27 48 Tao
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91 10-27 14-23 44 GE 92 10-27 06-23 06 NSP 4
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97 22-27 26-31 16 38P 98 26-27 30-23 48 CE 2
99 26-27 22-31 12 ESF i
100 30-27 26-23 48 m
j 101 30-27 34-23 12 NSP 1
102 34-27 30-23 48 5
i 103 34-27L 38-23 08 ESF 104 34-27 38-31 08 M8P 105 3& 27 34-23 14 GE j
106 42-27 38-23 48 CE 107 42-27 46-31 06 EEF 106 46-27 42-23 10 MSP-4 109 50-27 46-23 08 CE 110 02-23 W 27 08 CE 4
111 02-23 02-27 48 tuo 112 06-23 10-27 16 NSF 113 06-13 10-19 10 BSP 114 10-23 14-27 48 CE 115 10-23 06-27 06 MSP 116 14-23 18-27 14 GE 117 14-23 10-19 08 BEF 118 18-23.
22-27 48 m
i 119 18-23 14-27 10 NSF 120 22-23 26-27 48 GE 121 22-23 18-19 08 NSF 122 26-23 30-27 48 GK 123 26-23 30-19 12 MSP 124 30-23 26-27 48 CE 125 30-23 5 19 08 WSF 126 34-23 30-27 43 CE i
127 34-23 38-19 ic asF 128 38-23 34-27 14 GE 129 38-23 42-19 08 NSP 4
l 130 42-23 38-27 48 CE 131 42-23 46-27 06 NSP l
132 46-23 42-19 10 NSF l
133 50-23 46-27 08 CE 134 50-23 50-27 48 TRO l
135 06-19 10-23 08 GE 136 06-19 06-15 48 Tao 137 10-19 14-23 14 CE i
138 10-19 14-15 12 NSP J
139 14-19 18-23 14 CE i
140 14-19 10-13 06 nsF 141 18-19 22-23 48 CE 142 18-19 14-13 08 NSP 143 22-19 26-23 48 CE 144 22-19 18-13 to usF l
145 26-19 30-23 48 GE l
..s
. - - - - - -. -~
n Test '
Pod Pully Ad,jacent Rod No.
Withdrawn location Position _
Commwnts 1A6 26-19 22-15 08 REP 147 30-19 26-23 48 CE 148 30-19 34-15 10 BSP 149 34-19 30-23 48 GE 150 34-19 38-15 08 NSP 151 38-19 34-23 14 CE 152 38-19 42-15 06 REP 153 42-19 38-23 14 GE 154 42-19 38-1S 12 NSP 155 46-19 42-23 08 CE 156 46-19 46-15 48 TRO 157 06-15 10-19 08 GE 158 10-15 14-19 14 CE/NSP 159 14-15 18-19 14 CE 160 18-15 22-19 14 GE 161 18-15 14-11 06 RSP 162 22-15 26-19 14 GE 163 22-15 18-11 08 NSP 164 26-15 30-19 14 GE 165 30-15 26-19 14 GE 166 3 0-15 34-11 08 RSP 167 34-15 30-19 14 CE 168 34-15 38-11 06 NSP 169 38-15 34-19 14 GE 170 38-15 42-19 08 MSP 171 42-15 38-19 14 GE/SNP 172 46-15 42-19 08 GE 173 10-11 14-15 48 1R0 174 14-11 18-15 14 GE/ ESP 175 18-11 22-15 14 GE 176 22-11 26-1S 48 GE 177 22-11 26-07 06 NSP 178 26-11 30-15 48 GE 179 26-11 30-07 06 NSP l
180 30-11 26-15 48 CE l
181 30-11 26-07 06 NSP l
182 34-11 30-15 14 CE 183 34-11 38-15 08 NSP 184 38-11 34-15 14 GE 185 42-11 38-1S 48 2RO 166 14-07 18-11 08 GB 187 14-07 18-07 48 TRO 188 18-07 22-11 08 CE i
189 22-07 15-11 10 N3P 190 26-07 22-11 10 NSP 191 30-07 34-11 10 SSP l
192 34-07 30-11 08 GE 193 34-07 38-07 l.8 TRO l
194 38-07 34-11 08 CE i
195 22-03 26-07 08 GE 196 22-03 26-03 48 TRO l
197 26-03 30-07 08 GE 198 26-03 30-03 48 TRO 199 30-03 26-07 08 GE l
~
AEC DI' 7EUTION FOR PART 50 DOCKET MAT !AL (TDtPORARY FOPM)
CONTROL NO:
_ '062 FILE:
FROM:
DATE OF DOC DATE REC'D LTR MEMO RPT OTIER Northarn cretam Pn"ar Comneny Minnanpolie, Minn
$$491 l
j. J. Nnchter A-6-73 A-7-73 FACcIMILE TO:
ORIG CC OTIER SENT AEC PDR v
SENT LOCAL PDR v ur. Criar 1
CLASS UNCLASS PROP IhTO INPUT NO CIS REC'D DOCKET NO:
Xxx 1
50-263 DESCRII' TION :
ENCLOSURES:
- 1. t r t e 7-26-73 1 tr fm B H Grier to L J Wachter.
furnishing info re shutanen margin verification t e s t s on all con t rol rod s........ W/ At tache d -
ACKNOWLEDGE 6 Results of Monticello Shutdown Marg!n Verificar ton Test, dta Augm t 3-5, 1973.........
'D0 NOT REMOVE PLANT NAME : Mon t i c el l o FOR__ ACTICN/INFOPRATION m.c.71 eo BUTLER (L)
SCIMENCER(L) y ZImANN(L)
REGAN(E)
W/ Copies W/ Copies W/ 7 Copies W/ Copies CLARK (L)
STOLZ(L)
DICKER (E)
W/' Copies V/ Copies W/ Copies W/ Copies GOLLER(L)
VASSALLO(L)
KNICHION(E)
W/ Copies W/ Copies W/ Copies W/ Copies KNIEL(L)
SCHD1EL(L)
YOUNGBLOOD(E)
W/ Copies W/ Copics W/ Copics W/ Copies INTERNAL DISTRIBUTION IPFC V" 9 TECH REVIEW DENTON LIC ASST
_A / T IND WAEC PDR HENDRIE GRIMES BROWN (E)
BRAIIMAN
/ OGC, ROOM P-506A SCHROEDER CAMMILL y DIGGS (L)
SALTZMAN
/ MUNTZING/ STAFF MACCARY KASTlER GEARIN (L) g CASE Di1GHT BALLARD COULBOURNE (L)
PLANS CIAMBUSSO PAWLICKI SPANGLER LEE (L)
MCDONALD BOYD SHA0 MAIGRET (L)
DUBE MOORE (L)(BWR) y STELLO ENVIRO SERVICE (L)
DEYOUNG(L)(PWR)
HOUSTON MULLER SIIEPPARD (E)
INTO y SKOV110LT (L)
NOVAK DICKER SMITil (L)
C. MILES P. COLLINS ROSS DiIGHTON TEETS (L)
IPPOLITO YOUNGBLOOD WADE (E)
REG OPR y TEDESCO REGAN WILLIAMS (E) y1'ILE 6 REGION (3)
LONG PROJECT LDR WILSON (L)
MORRIS IAINAS v4TEELE BENAROYA HARLESS VOLINER A
EXTERNAL DISTRIBUTION fA g 1 - LOCAL PDR Minnen%n1(=, Minn.
7
/ 1 - DTIE(ABERNATHY)
(1)(2)(9)-NATIONAL LAB'S 1-PDR-SAN /LA/NY
/1 - NSIC(EUCHANAN) 1-R. S c hoonrak e r,CC, GT, D-323 1-GERALD LELLOUCHE 1 - ASLB(YORE /SAYRE/
l-R. CATLIN, E-256-GT BROOKHAVEN NAT. LAB WOODARD/"H" ST.
1-CONSULTANT' S 1-AGMED(WALTER K0 ESTER
/16 - CYS ACRS H0bOCUC 9FUT TO LIC AcRT. NEWMARK/BLUME/ACBABIAN Di-C-4 2 7-GT R. DICCc ON A A-7 3 1-CERALD ULRIKSON...ORNL
/ 1-RD.. MULLER..F-309 CT
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