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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 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 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 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 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 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 ML20210U1831999-08-12012 August 1999 Revises 980202 Commitment Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions 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 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 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) 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 ML20205C6561999-03-26026 March 1999 Submits Semiannual Update on Project Plans for USAR Review Project & Conversion to ITS 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 ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function 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 ML20210U1831999-08-12012 August 1999 Revises 980202 Commitment Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions 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 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 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 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 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 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 ML20153F5351998-09-25025 September 1998 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Improved TS 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 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 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 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 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 ML20238E8201998-08-26026 August 1998 Forwards Effluent & Waste Disposal Semi-Annual Rept for Jan-June 1998 & Revised Effluent & Waste Disposal Semi- Annual for Jul-Dec 1997. Ltr Contains No New NRC Commitments,Nor Does It Modify Any Prior Commitments ML20237E9741998-08-26026 August 1998 Forwards Rev 4 to EWI-09.04.01, Inservice Testing Program. Rev of Inservice Testing Program Reflects Valves Added as Result of Component Mods Recently Performed ML20237E6821998-08-25025 August 1998 Forwards fitness-for-duty Program Performance Data for Six Months Period Ending 980630 1999-09-09
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I Northem States Power Company Monticello Nuclear Generating Plant 2807 West Hwy 75 Monticello. Minnesota 55362-9637 May 25,1999 10 CFR Part 50 Section 50.71 (a)
U S Nuclear Regulatory Commission Attn: Document Control Desk -
Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Partial Fulfillment of License Conditions Placed on Amendment 101 l I
Reference 1. Letter from Craig A. Schibonski, NSP, to NRC Document Control Desk, !
" Revision Two To License Amendment Request Dated July 26,1996 Reactor Coolant Equivalent Radiciodine Concentration And Control' Room Habitability," dated June 19,1998.
I As an attachment to the above Reference 1 NSP submitted " Exhibit F - EFT System Commitment and ASME N510-1989 Testing Exceptions." In this exhibit NSP identified ten current requirements for filter testing which it found potentially impractical for the existing Monticello Emergency Filtration Testing (EFT) system. In response, the NRC issued Amendment 101 to the Monticello license which approved use of the ten exceptions for 24 months subject to the following Appendix C conditions:
Conduct an independent evaluation of the testing methodology and the testing configuration of the EFT [ emergency filtration testing] system by HEPA and charcoal filter testing expet1s.
This evaluation shallinclude review of the exceptions to the ASME N510-1989 testing standards listed in Exhibit F of NSP's June 19,1998, letter. The evaluation shall be reported to the NRC. (The implementation date for this condition is "Within 9 months of the date of issuance of Amendment No.101.")
Initiate appropriate modifications to the EFT system to comply with the ASME N510-1989 testing standard or obtain NRC approval for continued use of the exceptions. (The l )
implementation date for this condition is *Within 24 months of the date ofissuance of I Amendment No.101 ')
NSP engaged NUCON to perform the independent evaluation. Attached is Exhibit F of the June I
19,1998 letter, annotated with the NUCON evaluation and the NSP response, to address each u i JM.lCENSE\ License App C\ EFT I,c cond #1. doc I 9906040011 990525 PDR ADOCK 05000263 P PDR l
1 of the ten testing e.vceptions. Three of the exceptions (items 3,4, and 5 of Exhibit F) can be eliminated because NSP currently complies with these sections of N510-1989. Three of the exceptions (items 6,8, and 10 of Exhibit F) can be eliminated because compliance can be <
achieved with reasonable modifications to the Monticello EFT system. Three of the exceptions I (items 1,2, and 9 of Exhibit F)will be retained because N510 compliance would require major re-design and modification of the existing Monticello facility. A modification will be performed which may eliminate the need for one exception (item 7 of Exhibit F.) This must be re-evaluated following completion of the modification. !
l NSP considers this submittal to complete the requirements of the first licerise condition cited 1 above. We are proceeding with the modifications and testing so that they are completed within j the 24 month interval. We will submit a second report in sufficient time to obtain NRC approval i for continued use of the remaining exceptions within the 24 month interval. This report will also address the results of the injection point modification (item 7 of Exhibit F.) ,
This letter contains no new NRC commitments, nor does it modify any prior commitments. j Please direct any questions on this matter to Marcus H. Voth, Licensing Project, at (612) 271-5116.
Byron Day i Plant Manager Monticello Nuclear Generating Plant ,
c: Regional Administrator-Ill, NRC ;
~
NRR Project Manager, NRC Resident Inspector, NRC j State of Minnesota Attn: Steve Minn i l
Attachments: Affidavit to the US Nuclear Regulatory Commission Exhibit F - EFT System Commitment and ASME N510-1989 Testing Exceptions (Annotated version of Exhibit F as it originally appeared in Reference 1)
UNITED STATES NUCLEAR REGULATORY COMMISSION i .
NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 Submittal of Information Provided in Partial Fulfillment of License Conditions Placed on Amendment 101 Northern States Power Company, a Minnesota corporation, hereby submits a letter dated May 25, 1999 entitled Partial Fulfillment of License Conditions Placed on Amendment 101 intended to fulfill the requirements of the first of two license conditions issued with Amendment 101 of license DPR-22 found in Appendix C, Additional Conditions- Facility Operating License No. DPR-22.
This letter contains no restricted or other defense information.
NORTHERN STATES POWER COMPANY By J 2/m h, yron'DIfag
@lant P Manager Monticello Nuclear Generating Plant On this A 5 D day of AV / 9 99 before me a notary public in and for said County, personally appeared Byr'on D. Day, Plant Manager, Monticello Nuclear Generating Plant, and being first duty sworn acknowledged that he is authorized to execute this document on behalf of Northern States Power Company, that he knows the contents thereof, and that to the best of his knowledge, information, and belief the statements made in it are true and that it is not interposed for delay.
CAILtAA4_ ' ~
Marcus H. Voth Notary Public - Minnesota Wright County My Commission Expires January 31,2000 I MARCU8 H. VOTH l ! NOTMtYPUKIC MINNESOTA; i
... $ M _ D 1_ D 81' N .. .. .
c l
Exhibit F
. . EFT System Commitment and ASME N510-1989 Testing Exception j l'
(Annotated version of Exhibit F as it originally appeared in Reference 1)
Commitment Within 9 months of the date of the approval of this amendment, NSP will conduct an
. Independent evaluation of the testing methodology and system testing configuration of the Emergency Filtration (EFT) system by HEPA and charcoal filter testing experts. All of the exceptions to the testing standards listed below will be evaluated. The results of this review will be reported to the staff.
ASME N510-1989 Testing Exceptions
- 1. Section 5.5.1 of ASME N510-1989 Section 5.5.1 of ASME N510-1989 provides guidance for visualinspection of the air treatment system.
NSP Exception NSP performs a visual Inspection of applicable items from Section 5.5.1, NSP performs a visual inspection by procedure, but many of the standard's inspections items are not applicable to the Monticello EFT system. Examples of items that are not applicable to Monticello include:
- 1) dovetail type access gaskets with a seating surface suitable for a knife edge seal, and 2) shaft seals.
NUCON Evaluation and NSP response NUCON agrees that many of the checklist items found in N510 do not apply to the EFT l system since it is a serpentine type of design not addressed by ASME N509. In addressing the specific examples of incompatibility between the Monticello EFT installation and N510 requirements, NUCON recommends that replacement gaskets should have a dovetail design. NSP agrees that as parts are replaced, such testability Improvements should be considered. ,
l Exception #1 will be retained, since the visual checklist contains items which are not applicable to the EFT system.
i
- 2. Section 6.2.2 and Table 1 of ASME N510-1989 l Section 6.2.2 and Table 1 of ASME N510-1989 state that a housing leak test shall be performed every 10 years. ,
i 1
i
NSP Exception l ' This test is not performed at Monticello. The EFT system at Monticello was built to be tested to l . ANSI /ASME N510-1980 which does not require these tests to be performed periodically. No provisions were provided to accommodate this test. The entire EFT housing is contained within the protective envelope supplied by the system, and any leakage into the housing would be filtered air. Periodic performance of a test that verifies the ability to maintain the control room envelope at a positive pressure is an adequate demonstration of system leak integrity.
NUCON Evaluation and NSP response NUCON agrees that the housing leak test would be very difficult to perform, given the EFT system design. NUCON states an acceptable alternative would be to perform a
- smoke test on the housing upon completion of periodic in-place filter testing to detect any.Inleakage. NSP has incorporated the smoke test into EFT in-place filter testing procedures.
Exception #2 will be retained. The housing smoke test provides an acceptable alternative to detect housing inleakage.
- 3. Section 7.1 of ASME N510-1989 Section 7.1 of ASME N510-1989 recommends a mounting frame pressure leak test to verify the absence of leaks through seal welds of the HEPA filter and adsorber frames, and between the frames and housings be performed.
NSP Exception This test is not performed at Monticello. Leaks of this nature are detected by the visual inspection test or the in-place filter test, and credit is taken for these tests as allowed by the standard.
NUCON Evaluation and NSP response NUCON states that per N510-1989 the mounting frame pressure leak test is an optional test which would normally only be done during acceptance testing. NSP agrees that the l
test is optional, noting that Table 1 of N510-1989 states "It is left up to the owner to l
determine whether a mounting frame leak test is warranted based upon the visual examination."
Exception #3 will be eliminated since NSP does comply with Section 7.1 of N5101989.
1
- 4. Section 8.5.1.4 of ASME N510-1989 Section 8.5.1.4 of ASME N510-1989 requires that a housing component pressure drop airflow i test be performed which requires that maximum pressure drops across each of the components !
be simulated. The unit is run at this maximum pressure drop across the system, and adequate airflow is ensured.
2 l
l u
NSP Exception i This test is not performed at Monticello. The EFT system was designed to be tested to the ANSI /ASME N510-1980 standard which does not require that this test be performed l periodically. The system at Monticello contains a low flow trip. If airflow is too low through the l system due to debris loading of the filters, the running train will automatically trip, and the ;
standby train will start.
NUCON Evaluation and NSP response l NUCON states that per N510-1989 the pressure drop airflow test is required only during acceptance testing and after major modification. NSP agrees that periodic pressure drop airflow tests are not required by the standard.
Exception #4 will be eliminated since NSP does comply with Section 8.5.1.4 of N510-1989.
- 5. Section 8.5.2.2 of ASME N510-1989 Section 8.5.2.2 of ASME N510-1989 requires a periodic airflow distribution test through the adsorber banks.
NSP Exception This test is not performed at Monticello. Monticello's EFT system was designed to be tested to i the ANSI /ASME N510-1980 standard which does not require this test be performed periodically. No provisions were made in the design of the Monticello EFT to perform this test periodically.
NUCON Evaluation and NSP response NUCON states that per N510-1989 the airflow distribution test is required only during acceptance testing and after major modification. NSP agrees that periodic airflow distribution tests are not required by the standard.
Exception #5 will be eliminated since NSP does comply with Section 8.5.2.2 of N510-1989.
- 6. Section 10.3 of ASME N510-1989 Section 10.3 of ASME N510-1989 states that sample points for DOP sampling shall be I downstream of a fan, or downstream sample manifolds shall be qualified per ASME N509.
NSP Exception At Monticello, the downstream sampling is performed upstream of the fan using a single injection point. No shaft seals are installed on the system's fans, therefore sampling j 3 l 1
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i downstream of the fan would obtain a diluted air sample. Section 10.3 of the ANSI /ASME N510-1980 standard, which the EFT System was originally designed to, does not require the
' use of a sampling manifold. No provisions were made in the design of the Monticello EFT for l sampling manifolds. I I
l NUCON Evaluation and NSP response NUCON agrees that testing downstream of a known dilution source is not acceptable.
NUCON recommends use of temporary sample manifolds for downstream sampling, I which would be installed for testing and removed for operation. NSP agrees with )
NUCON's recommendation and will obtain and qualify manifolds for in-place testing. l Exception #6 will be eliminated following incorporation of manifolds into the testing j program.
- 7. Section 10.5.8 of ASME N510-1989 l l
Section 10.5.8 of ASME N510-1989 states that upstream and downstream DOP concentrations are repeated until readings within +/- 5 % of respective previous readings are obtained. The final set of readings is then used to calculate penetration.
NSP Exception At Monticello, the readings are taken until the concentrations are within +/- 10% and the highest penetration reading is conservatively used with a minimum of three readings taken.
Because of the injection point location for the Monticello EFT system, it is difficult to consistently achieve +/- 5% between readings.
NUCON Evaluation and NSP response ;
NUCON recommends that the injection port be relocated or that injection manifolds be evaluated to provide better mixing of the challenge agent. NSP agrees with NUCON's recommendation and will incorporate either qualified new injection ports or injection ,
manifolds into the testing program. This exception will then be reevaluated and i eliminated if the +/-5 % criterion can be met.
Exception #7 will be eliminated if the +/-5 % criterion can be met following incorporation of manifolds and/or new injection ports into the testing program.
- 8. Section 11.3 of ASME N510-1989 Section 11.3 of ASME N510-1989 states that sample points for halide challenge gas shall be downstream of a fan or downstream sample manifolds shall be qualified per ASME N509.
NSP Exception See item 6 above.
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NUCON Evaluation and NSP response See item 6 above. Exception #8 will be eliminated following incorporation of manifolds into the testing program.
- 9. Section 11.4 of ASME N510-1989 Section 11.4 of ASME N510-1989 states that R-11 is the preferred test gas with R-112 or R-112A as acceptable alternatives.
NSP Exception NSP reserves the ability to use alternate test gases that are found to be acceptable alternatives by the industry. Monticello currently employs R-11 as the test gas; however, environmental concerns regarding the use of such halide gases may result in use of these gases not being feasible in the future.
NUCON Evaluation and NSP response NUCON and NSP agree that this exception is reasonable.
Exception #9 will be retained, since use of the specified test gas (R-11) may be restricted in the future.
- 10. Section 11.5.8 of ASME N510-1989 Section 11.5.8 of ASME N510-1989 states that when a housing contains more than one bank )
of adsorbers in series, the halide gas test shall be repeated for each bank. I 1
NSP Exception 1 At Monticello, the two adsorber banks are tested as a single unit. This requirement was not present in A.NSI/ASME N510-1980, which the EFT System was designed to, and a qualified injection manifold between the two banks was not provided.
NUCON Evaluation and NSP response NUCON recommends use of temporary injection / sample manifolds to test the adsorber banks individually, which would be installed for testing and removed for operation.
NSP agrees with NUCON's recommendation and will obtain and qualify manifolds for in-place testing.
Exception #10 will be eliminated following incorporation of manifolds into the testing program.
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