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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 ML20217M3371999-10-20020 October 1999 Forwards Notice of Docketing of License SNM-2506 Amend Application.Notice Has Been Forwarded to Ofc of Fr for Publication ML20217M1111999-10-19019 October 1999 Forwards Insp Repts 50-282/99-14 & 50-306/99-14 on 990920- 22.One Violation Noted & Being Treated as Ncv.Insp Focused on Testing & Maint of Heat Exchangers in High Risk Sys ML20217F4331999-10-15015 October 1999 Forwards Rev 39 to Security Plan.Changes Do Not Decrease Effectiveness of Security Plan.Rev Withheld,Per 10CFR73.21 ML20217G0711999-10-13013 October 1999 Forwards Insp Rept 50-263/99-12 on 990913-17.No Violations Noted ML20217C2351999-10-0606 October 1999 Forwards Insp Repts 50-282/99-12 & 50-306/99-12 on 990823-0917.No Violations Noted.Insp Consisted of Selected Exam of Procedures & Representative Records,Observation of Activities & Interviews with Personnel 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 IR 05000272/19990071999-09-28028 September 1999 Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified ML20212J8811999-09-28028 September 1999 Forwards Preliminary Accident Sequence Precurson Analysis of Operational Event That Occurred at Plant,Unit 1 on 990105, for Review & Comment.Comment Requested within 30 Days of Receipt of Ltr 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 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 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 ML20212F5121999-09-20020 September 1999 Forwards Response to NRC , Preparation & Scheduling of Operator Licensing Examinations ML20212D8401999-09-16016 September 1999 Discusses 990902 Telcon Between D Wesphal & R Bailey Re Administeration of Retake Exam at Prairie Island During Wk of 991206.NRC May Make Exam Validation Visit to Facility During Wk of 991116 ML20217H2331999-09-10010 September 1999 Forwards Security Insp Repts 50-282/99-10 & 50-306/99-10 on 990809-12.Two Findings,Each of Low Risk Significance Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20212A9241999-09-0909 September 1999 Discusses Plans Made During 990902 Telephone Conversation to Inspect Licensed Operator Requalification Program at Prairie Island During Weeks of 991101 & 991108.Requests That Written Exams & Operating Tests Be Submitted by 991022 ML20212B0511999-09-0909 September 1999 Forwards Insp Repts 50-282/99-11 & 50-306/99-11 on 990816-20.One Issue of Low Safety Significance Was Identified & Being Treated as Ncb ML20217H5661999-09-0909 September 1999 Discusses 990907 Pilot Plan Mgt Meeting Re Results to-date of Pilot Implementation of NRC Revised Reactor Oversight Process at Prairie Island & Quad Cities.Agenda & Handouts Provided by Utils Encl ML20217A5751999-09-0909 September 1999 Forwards Individual Exam Results for Licensee Applicants Who Took Aug 1999 Initial License Exam.Without Encls ML20212A9761999-09-0909 September 1999 Submits 1999 Annual Rept of Any Changes or Errors Identified in ECCS Analytical Models or Applications ML20211Q7641999-09-0808 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant Operator License Applicants During Wk of 000515,in Response to D Westphal ML20211N8631999-09-0707 September 1999 Withdraws 970814 Request for Exemption from 10CFR50,App R, Section III.G.2, Fire Protection of Safe Shutdown Capabilities 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 ML20211K7971999-09-0101 September 1999 Informs That Util Reviewed Rvid as Requested in NRC .Recommended Corrections Are Listed ML20211L1981999-09-0101 September 1999 Forwards Insp Rept 50-263/99-05 on 990702-0812.No Violations Noted ML20211L0211999-09-0101 September 1999 Provides Notification That License Amends 141 & 132 & Associated License Conditions 6 & 7 Have Been Fully Implemented ML20211K5911999-09-0101 September 1999 Informs That Util Reviewed Rvid Data Base,As Requested in NRC .Summary of Proposed Changes & Observed Differences Are Included in Encl Tables ML20211Q6041999-08-31031 August 1999 Forwards Rev 19 to USAR for Pingp,Per 10CFR50.71(e).Rev Brings USAR up-to-date as of 990228,though Some Info Is More Recent.Attachment 1 Contains Descriptions & Summaries of SE for Changes,Tests & Experiments,Per 10CFR50.59 ML20211K5931999-08-31031 August 1999 Forwards License Amend Request for License SNM-2506, Proposing Change to License Conditions 6,7 & 8 & TSs App a of License by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks 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 ML20211D3541999-08-24024 August 1999 Discusses GL 95-07 Re Pressure Locking & Thermal Binding of safety-related Power Operated Gate Valves.Forwards SE Re Response to GL 95-07 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 ML20211C7601999-08-19019 August 1999 Confirms NRC Intent to Meet with NSP & Ceco on 990807 in Lisle,Il to Discuss with Region III Pilot Plants,Any Observations,Feedback,Lessons Learned & Recommendations Relative to Implementation of Pilot Program ML20211C2311999-08-19019 August 1999 Forwards Unit 1 ISI Summary Rept,Interval 3,Period 2 Refueling Outage Dates 990425-0526,Cycle 19 971212-990526. Rept Identifies Components Examined,Exam Methods Used,Exam Number & Summarizes Results ML20211B8311999-08-19019 August 1999 Forwards Request for Relief 8 Re Limited Exams Associated with Unit 1 Third ten-year Interval Inservice Insp Program. Licensee Requests Relief Due to Impractibility of Obtaining 100% Exam Coverage for Affected Items ML20211B5711999-08-19019 August 1999 Forwards Second 90-day Rept for Implementation of Voltage Based Repair Criteria at Prairie Island Unit 1.Rept Fulfills Requirements of Section 6.b of Attachment 1 to GL 95-05 ML20211B0561999-08-18018 August 1999 Provides Addl Info on Proposed Rev to Main Steam Line Break Methodology ,in Response to NRC Staff Request Made in 990416 Telcon.Nuclear Svcs Corp Rept PIO-01-06, Analysis Rept Structural Analyses of Main Steam Check... Encl ML20211C7371999-08-17017 August 1999 Discusses Closure of Staff Review Re Generic Implication of Part Length Control Rod Drive Mechanism Housing Leak on 980123.Enclosed NRC 980811 & 1223 Ltrs Responded to WOG Positions Re Corrective Actions ML20211B2621999-08-17017 August 1999 Forwards Insp Repts 50-282/99-09 & 50-306/99-09 on 990719-22.No Violations Noted.Insp Included Review & Evaluation of Current Emergency Preparedness Performance Indicators ML20210T5661999-08-12012 August 1999 Forwards RAI Re & Suppl ,which Requested Exemptions from TSs of Section III.G.2 of 10CFR50 App R,To Extent That Specifies Separation of Certain Redundant Safe Shutdown Circuits with fire-related Barriers ML20210R7021999-08-12012 August 1999 Forwards Insp Repts 50-282/99-06 & 50-306/99-06 on 990601- 0720.One NCV Occurred,Consistent with App C of Enforcement Policy 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 ML20210P5191999-08-11011 August 1999 Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950519 & NSP Responses for PINGP & 951117. Staff Reviewed Info in Rvid & Released Info as Rvid Version 2.Requests Submittal of Comments Re Revised Rvid by 990901 ML20210Q0341999-08-0404 August 1999 Forwards SE Granting Licensee 980724 Relief Request 10 Re Third 10-year Interval ISI Program Plan,Entitled, Limited Exam 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217F4331999-10-15015 October 1999 Forwards Rev 39 to Security Plan.Changes Do Not Decrease Effectiveness of Security Plan.Rev Withheld,Per 10CFR73.21 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 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 ML20212F5121999-09-20020 September 1999 Forwards Response to NRC , Preparation & Scheduling of Operator Licensing Examinations ML20212A9761999-09-0909 September 1999 Submits 1999 Annual Rept of Any Changes or Errors Identified in ECCS Analytical Models or Applications ML20211N8631999-09-0707 September 1999 Withdraws 970814 Request for Exemption from 10CFR50,App R, Section III.G.2, Fire Protection of Safe Shutdown Capabilities ML20211K7971999-09-0101 September 1999 Informs That Util Reviewed Rvid as Requested in NRC .Recommended Corrections Are Listed ML20211L0211999-09-0101 September 1999 Provides Notification That License Amends 141 & 132 & Associated License Conditions 6 & 7 Have Been Fully Implemented ML20211K5911999-09-0101 September 1999 Informs That Util Reviewed Rvid Data Base,As Requested in NRC .Summary of Proposed Changes & Observed Differences Are Included in Encl Tables ML20211Q6041999-08-31031 August 1999 Forwards Rev 19 to USAR for Pingp,Per 10CFR50.71(e).Rev Brings USAR up-to-date as of 990228,though Some Info Is More Recent.Attachment 1 Contains Descriptions & Summaries of SE for Changes,Tests & Experiments,Per 10CFR50.59 ML20211K5931999-08-31031 August 1999 Forwards License Amend Request for License SNM-2506, Proposing Change to License Conditions 6,7 & 8 & TSs App a of License by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks 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 ML20211C2311999-08-19019 August 1999 Forwards Unit 1 ISI Summary Rept,Interval 3,Period 2 Refueling Outage Dates 990425-0526,Cycle 19 971212-990526. Rept Identifies Components Examined,Exam Methods Used,Exam Number & Summarizes Results ML20211B8311999-08-19019 August 1999 Forwards Request for Relief 8 Re Limited Exams Associated with Unit 1 Third ten-year Interval Inservice Insp Program. Licensee Requests Relief Due to Impractibility of Obtaining 100% Exam Coverage for Affected Items ML20211B5711999-08-19019 August 1999 Forwards Second 90-day Rept for Implementation of Voltage Based Repair Criteria at Prairie Island Unit 1.Rept Fulfills Requirements of Section 6.b of Attachment 1 to GL 95-05 ML20211B0561999-08-18018 August 1999 Provides Addl Info on Proposed Rev to Main Steam Line Break Methodology ,in Response to NRC Staff Request Made in 990416 Telcon.Nuclear Svcs Corp Rept PIO-01-06, Analysis Rept Structural Analyses of Main Steam Check... Encl 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 ML20210G5061999-07-30030 July 1999 Responds to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates 05000282/LER-1999-007, Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics1999-07-23023 July 1999 Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics ML20210J4991999-07-22022 July 1999 Forwards Rev 18 to USAR for Pingp,Bringing USAR up-to-date as of 990228,though Some Info More Recent.Safety Evaluation Summaries Also Encl 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 ML20209H8051999-07-14014 July 1999 Forwards Summary of non-modification Safety Evaluation Number 515 Re Storage of Fuel Inserts,Per Insp Rept 72-0010/99-201 ML20209D4181999-07-0707 July 1999 Informs That Util Has Changed Listed TS Bases Pages Attached for NRC Use.Util Made No New Commitments in Ltr ML20209C3951999-07-0101 July 1999 Forwards Supplemental Response to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20209B7541999-07-0101 July 1999 Final Response to GL 98-01,Suppl 1 Re Y2K Readiness of Computer Sys.Sys Remediated as Required for Plant Operation. Contingency Plans Developed to Mitigate Impact of Y2K-induced Events at Key Rollover Dates ML20196J8941999-06-30030 June 1999 Transmits Util Comments on Draft Regulatory Guide DG-1074, Steam Generator Tube Integrity. Licensee Recommends That NRC Focus on Several Important Listed Areas Considered Principal Concerns & Contentions ML20209C3011999-06-29029 June 1999 Forwards Annual Rept of Corrections to NSP ECCS Evaluation Models,Iaw 10CFR50.46.Since All Analyses Remain in Compliance,No Reanalysis Is Required or Planned 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 ML20209B5751999-06-24024 June 1999 Submits Revised Relief Request for Limited Examinations Associated with Third 10-yr ISI Examination Plan.Attached Is Unit 1 Relief Request 7,rev 1 Which Addresses Limited Examinations 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 ML20196F3871999-06-23023 June 1999 Forwards Revised Pages 71,72 & 298 of Rev 7 to NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units, Per Discussions with Nrc.Approved Version of Rept Will Be Issued 05000282/LER-1999-006, Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics1999-06-18018 June 1999 Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics ML20195G4281999-06-0909 June 1999 Notifies That Amsac/Dss Mods Completed & TS 138/129 Has Been Fully Implemented 05000282/LER-1999-005, Forwards LER 99-005-00 Re Containment Inservice Purge Sys Not Isolated During Heavy Load Movement Over Fuel.Event Has Indicated That Level of Performance Expected by Mgt Has Not Yet Been Achieved1999-06-0707 June 1999 Forwards LER 99-005-00 Re Containment Inservice Purge Sys Not Isolated During Heavy Load Movement Over Fuel.Event Has Indicated That Level of Performance Expected by Mgt Has Not Yet Been Achieved ML20207F4301999-06-0101 June 1999 Forwards 1999 Unit 1 SG Insp Results,Per TS 4.12.E.1. Following Insp 84 Tubes Were Plugged for First Time 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 ML20195C6861999-05-21021 May 1999 Forwards Rev 17 to USAR for Prairie Island Nuclear Generating Plant.Attachment 1 Contains Descriptions & Summaries of SEs for Changes,Tests & Experiments Made Under Provisions of 10CFR50.59 During Period Since Last Update ML20196L2461999-05-21021 May 1999 Forwards Rev 0 to COLR for Pingp,Unit 1 Cycle 20, IAW TS Section 6.7.A.6 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 ML20206T2461999-05-17017 May 1999 Forwards Off-Site Radiation Dose Assessment for Jan-Dec 1998, Rev 0 to Annual Radiactive Effluent Rept for 980105- 990103 & Effluent & Waste Disposal Annual Rept Solid Waste & Irradiated Fuel Shipments,Jan-Dec 1998 ML20206U6781999-05-17017 May 1999 Forwards Revised Emergency Response Plan Implementing Procedures,Including Rev 15 to F3-3,rev 15 to F3-16,rev 14 to F3-22 & Table of Contents ML20206U7131999-05-17017 May 1999 Forwards Revised EOF Emergency Plan Implementing Procedures, Including Table of Contents & Rev 2 to F8-10, Record Keeping in Eof. with Updating Instructions ML20206R0401999-05-13013 May 1999 Forwards Application for Amends to Licenses DPR-42 & DPR-60, Removing Plant Organization Requirement,Imposed in Amend 141/132 That Plant Manager,Who Has Responsibility for Overall Safe Operation of Plant,Report to Corporate Officer ML20206Q0871999-05-13013 May 1999 Forwards Result of Evaluation Re Ultrasonic Exams of SG Number 22 Performed in Accordance with ASME Boiler & Pressure Vessel Code Section Xi.Procedure Used for Evaluation Contained in WCAP-14166,submitted for Review ML20206F9381999-05-0303 May 1999 Forwards Response to NRC 990304 RAI Re GL 96-05 Program at Pingp.Licensee Commitments Are Identified in Encl as Statements in Italics ML20206J3851999-05-0303 May 1999 Forwards 1998 Annual Radiological Environmental Monitoring Rept 1999-09-09
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_ . _ _ . _ . _ _ . _ . . _ . _ _ . _ . _ _ _ _ . _ . ..._ _ _ _ . _ _____ . _ _ _
300 Third Street,-N.E.
. Apt. 303 Washington,D.C. 20002
~
October 4,1995 Mr. na ab H. % EREEDOM OF INFORAIATION Director, Division of Freedom d ACT REQUEST Informerian and Puhlicarian, Service omoe g u,.i.i ia. .fe cA-95 4 [ g U.S. Nuclear Regulatory ('<wnmieninn g.d, jo //-t f ,
Washington, D.C. 20555 ATTN: FOIA Request
DearMr.Grimsley:
Pursuant so the Freedorn ofInformatiani Act, I would like to request the following documane=*ian be placed in the NRC's Public Dc-: -= Room:
- 1) IE Manual Chapter 2955 as referenced on pag 2 of anached SECY-86-37.
(Anachment 1)
- 2) Draft NRC Manual Chapter 0516 as referenced in hpW 15,1981 letter fmen NRC to Northern States Power. (see Attachment 2)
- 3) NRC Manual Chapter 0516 dated July 25,1986 as referenced in NRR Office l
Letter 44, Revision 1. (see Attachment 3)
Please let me know if you require any additional information. I can be reached at 202/634- -
1439.
Sincerely, l
Mic 0 % ahn
Enclosures:
as stated -
9512130196 951004 I
PDR FDIA 0,' MEAL 193-418-_PDR ,
.y_____.
Pam - Ced, Oct 4, 1995 10:30 AM Pego 1. -
ACN: 9207070133 ,
DhTE: 810915 UTC: CL/* CORRESPONDENCE-LETTERS DIC: CUT /*OUTOOING CORRESPONDENCE EST_.PAGES: 1 L1: INFORMS THAT SALP REVIEW & ASSOCIATED MGT MEETINGS WILL TAKE L2: PLACE IN NEAR FUTURE FOR PLANTS.FORMARDS DRAFT NRC E 0516 L3: WHICH WILL.BE USED AS GUIDE FOR PERFORMANCE OF SALP REVIEWS. I L4: W-0 DRAFT MC 0516. I KEY: DRAFTS REY: GUIDELINES REY: MAM4cDEC KEY: MEETINGS REY: PERFORMANCE REY: REVIENS REY: SALP -
KEY: SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE FICHE: 62248:001-62248:103 PFL: ADOCK-5000263-Q-810915 !
DKT: .50263F/#MONTICELLO NUCLEAR GENERATING PLANT, NORTHERN STATES I DKT: 50263Q/#MONTICELLO NUCLEAR GENERATING PLANT, NORTHERN STATES DKT: 50282F/# PRAIRIE ISLAND NUCLEAR STATION, UNIT 1, NORTHERN DKT: 50282Q/# PRAIRIE ISLAND NUCLEAR STATION, UNIT 1, NORMERN DKT: 50306F/# PRAIRIE ISLAND NUCLEAR STATION, UNIT 2, NORMERN DKT: 50306Q/# PRAIRIE ISLAND NUCLEAR STATION, UNIT 2, NORTHERN RN#1: GILBERTS D E AN#1: SPESSARD R L RA41: EUTNSP/9 NORTHERN STATES POWER CO. ;
AA91: NOIRS/9 REGION III, IE (720101-810228) !
PACKAGE: 810915-9207070133*
OTHER: 9207070133 4
e
Pam - Wed, Oct 4, 1995 10:33 AM Pcg3 1 ,
ACN: 8701050482 DATE: 861222 Iy!C: C3(/* MEMORANDUMS-CORRESPONDENCE Iy!C: MEBO/* INTERNAL OR EXTERNAL MEWRANDUM EST,PAGES: 4 EST_,PAGES : 46 L1: REV 1 'IO OFC LTR 44 ALERTING NRR STAFF 'IO AGENCY APPROVAL OF L2: MANUAL CHAPTER 0516 'SALP ' DTD 860725 & SUPERSEDING OFC L3: L'IR 44 DTD 840103. IMPLEMENTING PROCEDURE 'IO BE UTILIZED 'IO L4: PREPARE ALL SALPS & MANUAL CHAPTER 0516 ENCL.
KEY: APPROVALS KEY: IMPLEMENTATION REY: DODIFICATIONS REY: PROCEDURES KEY: REVISIONS KEY: SALP ,
KEY: STAFFING KEY: SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE FICHE: 46327:315-46327:318 FICHE: 68699:001-68699:047 PFL: FOIA--BOLEY 87-830-880711 FIA: 87-830 AN#1: DENION H R FNAME: BOLEY RA41: NRRC/9 OFFICE OF NUCLEAR REACTOR REGULATION, DIRECTOR (85112 AA61: NRRC/9 OFFICE OF NUCLEAR REAC70R REGULATION, DIREC'IOR (85112 PACKAGE: 880711-8808010400A OTHER: 8808010400 es l
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I rebr.ary 3. i ns (Information) stCv-u-37
(
l g: The Cennis,pfeners
)
j
{gg Victor Stelle. Jr.
Acting Esecutive Ofrector for Operations SYSTDMTIC ASSESSMENT OF LICENSEE PERF0fpIANCE (5 alp)
.M: PROCESS -
l l l 1
m: To provide the Commission with information en the SALp program and 1ts current status.
i .
l
! . Beckeroend: The SALp program was taplemented in 1g00 in response to item i j !.B.2. of NUREG-0660. Volume 1. "NRC Action plan Developed as a
- Result of the TMI-2 Accident." A description of the erfeinal 1 dated February it. 1980.
l program Ine results wasof provided in SECY-80-83, the first round evale htfons mere reported in l HUREG-0834. 'NRC Licessee Assessments.'
The Commission was briefed on the objectives of the SALp t program and the results of the first round evaluations en 8
September 22. Ig81. As a result of that briefing, the following changes were made to the SALp program at the request of the Commission: .
o The first round assessments covered periods up to two years. The staff was requested to taprove the timeliness of assessments by targeting the completten of assessments
, annually. The staff < aplemented this recommendation.
e The ffrst tsund of assessments was done in Headquarters by a based of senter headquarters managers. Responsibi-Ifty for performing the assessments was shifted from Needquarters to the Regional Offlees.
.. o For the first round assessment, plants were rated as "Above Average.' ' Average.' or "telow Average" overall as well as in each functional area. Based on the Con-mission's comment concernfag adverse taplicattens of '
renting stilities, the assessment criterta were revised
- such that they de not provide for ranking plants to determine their relative performance.
Contact:
James 4. partlow, it Ent. 24414 g/
h
\
A - k gggos h..""F6T cAnDE86-90 -
PDn v - - -- - - -
o ..
The Comissioners '
('
i
- The ffret round of assessments dfd not provide a means for takW fato censideretien 11consee input. The revised ; recess estab11shed a means for taking Ifcensee -
responses into account.
Incorporating the above changes. MC Manual Chapter 0516
- $ystematic Assessment of Licensee performance' was fssood on March 23. ,1Mt as a replacement for IE Nanual Chapter 2955.
/
SALp evaldettens were perfomed in accordance with this Iult Manuel Chapter until Neves6er 15. Ige 4 den a revision uns issued for fateria ese. That revisfon was in response to a '
staff assessment of the SALp process. In conjonctfen with the fssaance of the Nevester 15. Ige 4 rettsfon. a review group, which facluded representatives from E00. IE. MR.
AEOD.19t55 and the regional e?ficca, uns formed to further l stub the SALP process. The mvfew group finished its assfgnment and recommended several cha9 pes to the SALp Manual Chapter. The recessended changes were included in a proposed revisfon to NRC 0516 whicl(uns issued for review and cessent to the approprfate staff offices en June 27. 1M 5. Comments on the proposed revisten were l considered in the preparetton of the enciesed revisten I' to NRC 0516 which was issued for taplementatten on November 5. IM5 by the Ofrector. Office of Inspection .
and. Enforcement. I 1
App'reatmetely 325 assessments have been issued since the i! beginning of the SALP process in 1g00. -
Discussion: The objectives of the SALP program as contained in the 4 November 5. IM5 revisfon rensfa unchanged from the l original objectives. They are:
o To taprove the NRC regulatory program.
o To peralt sound decisions regarding NRC resource allocations, o To taprove licensee perforsence.
e To collect, through an fategrated NRC staff effort.
available observations on a periodic bests and evaluate licensee perforsence based on these obser-watfons.
1 O
) The Cosmissioners ,
Whfle the objectives of 5 ALP have rossined the same, several changes fa the mechanics of the process have taken place since the issusace of NRC Maneci Chapter 0516 on March 23. Ig82. The interfs revision to the SALP process issued Noveder 15. 1984, contained the following significant changes:
e Added a new functional area " Quality rams and Abfalstrative Controls Affecting Quel 1
- for evaluating 1 both operating phase reactors and constrwetion phase l reactors. 1 e Provfded instrtxtfons for the llegional Ahtnistrator to issue the 5 ALP Board Report to the Itcensee rather than issuance by the SALP Soard Chefraan, e Changed the periodicity for perforetag SALP evaluations
- from annually to a maximum of once per 18 months.
e Provided that SALP management meetings with the Itcensee be conducted as open meetings and that members of the public be treated as observers.
The enclosed revision to NRC 0516 includes the fe11owing significant changes from the lateria revision implemented on November 15, 1984 e' The addition of Trafning and Qualification Effective-ness as a functions 1 area rather than treating Training and Qualificatter tffectiveness as evaluation criterta in the assessment of other functional areas.
o A requirement that two SALP evaluations be conducted at approximately 12-month intervals when new operating
- Ifeenses are issued. -
During its recent assessment of the SALP process, the staff explored alternate means for gradi Itcensee perforsence.
However. 1t was concluded that the ission's comments made in September ig81 folloing the first round of SALP ;
evaluations are still valtd (i.e.. 'The adverse implicat1ons I
- of ranking utilities can be avoided by a ting three categories for the assessment. The first catertry 14 identify those facilttles for which more licensee and hence more INIC attention 8s needed. The second category should identify those facilities for uhtch proper balance of licensee and NRC attention has been
- achieved. The last category should identi those fact 11 ties I for which more than seequate attention by licensee is i
- apparent and hence a reduction in NRC resources for those l facilities can be realized.") Therefore, the staff has decided to continue with the current basic method of evaluating utility i performance.
( l t I
-, . . , . ~ . - . . . - - .
fhe CosefssIoners ,
~
~ " ~ ~ '
As part of our continuing effort to effective 1Vetflize SALP results, IE has recently revised IE Manual Chapter 2515 to make the rervits of SALP evaluations a primary consideration in the allocation of fnspection resources. 7The revised IE Manuel Chapter provides spec 1fIc guidance for increasing or decreasing f aspection efforts in response to the Tatest $ ALP evaluations. l As noted in the enclosed revisten to IntC 0516, Ifeensee performance 4shich results in functional amas being rated Category 3 fs acceptable only on a short tem bests. Continued perfemancs at such levels will not.be tolerated. Letters transattting 14LP lteports containing Category 3 retings require the licensee to respond and provide the licensee's planned cormctive actions to achieve impmved perferuance in the functional areas rated Category 3. The staff is developing additional guidelines on further actions to be taken when licensee performance is evaluated as Category 3. Staff is also developing a set of objective perfomance -adicators for potential use in evaluating each of the SALP functional areas and for signaling adverse perfemance trends throughout the SALP evaluation period.
The staff is continuing to monf ter the SALP process in orgler to promote consistency of 5 ALP resulte between regions and to assess improved and attemate means of evaluattap licensee performance. We are also working to further stream fne the 5 ALP process and thereby minimfre the itRC resources required to perfo m 5 ALP evaluations. .
./-
/.UW Victor Ste11cf.'Jr.
- Acting Executive rector for Operations
Enclosure:
tutC MC 0516
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