|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H5811999-10-15015 October 1999 Forwards 1999 Update to FSAR, for McGuire Nuclear Station.With Instructions,List of Effective Pages for Tables & List of Effective Pages for Figures ML20217G7861999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20217F3591999-10-13013 October 1999 Forwards Info Copy of Cycle 14 COLR for McGuire Nuclear Station,Unit 1 ML20217F3261999-10-13013 October 1999 Submits Quantity of Tubes Insp from Either Side of SGs A-D & Lists Tubes with Imperfections,Locations & Size.No Tubes Removed from Svc by Plugging.Total of Eleven Tubing Wear Indications Identified at Secondary Side Supports in SGs ML20217F8011999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of McGuire Nuclear Station.Areas That Warranted More than Core Insp Program Over Next Five Months,Not Identified.Historical Listing of Plant Issues Encl ML20217J5091999-10-0606 October 1999 Forwards Revs to Section 16.15-4.8.1.1.2.g of McGuire Selected Licensee Commitments Manual.Section Has Been Revised to Allow Testing of Portions of DG Fuel Oil Sys Every 10 Yrs ML20217C8351999-10-0505 October 1999 Communicates Correction to Info Provided During 990917 Meeting with Duke Energy & NRC Region Ii.Occupational Radiation Safety Performance Indicator Values Should Have Been Presented as 1 Instead of 0 ML20217C4471999-10-0404 October 1999 Forwards Insp Repts 50-369/99-06 & 50-370/99-06 on 990801- 0911.Determined That One Violation Occurred & Being Treated as Non-Cited Violation ML20212J2191999-10-0404 October 1999 Informs That Util 980326 Response to GL 97-06, Degradation of SG Internals Provides Reasonable Assurance That Condition of Steam Generator Internals Are in Compliance with Current Licensing Bases for Facility ML20212J7801999-10-0404 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for McGuire NPP & 990615.Informs That NRC Reviewed Responses & Concluded That All Requested Info Re Y2K Readiness Provided.Subj GL Considers to Be Closed ML20212M1651999-09-23023 September 1999 Refers to 990917 Meeting at Region II Office Re Licensee Presentation of self-assessment of McGuire Nuclear Station Performance.List of Attendees & Licensee Presentation Handouts,Encl ML20212D1671999-09-20020 September 1999 Forwards Exemption & SER from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Re Isolation of Main Steam Branch Lines Penetrating Containment.Exemption Related to Licensee Application ML20212B6491999-09-15015 September 1999 Informs That Encl Announcement Re 990913 Application for Amend to Licenses NPF-9 & NPF-7 Forwarded to C Observer in North Carolina,For Publication ML20212D5321999-09-15015 September 1999 Informs That Duke Energy Corp Agrees to Restrict Max Fuel Rod Average Burnup to 60,000 Mwd/Mtu,In Order to Support NRC Final Approval & Issuance of Requested Amend ML20212A4131999-09-14014 September 1999 Informs That TR DPC-NE-2009P Submitted in 990817 Affidavit, Marked Proprietary,Will Be Withheld from Public Disclosure, Pursuant to 10CFR2.709(b) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20216E8791999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for July 1999 for McGuire Nuclear Station ML20212A0501999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementing Code Case for Duration of Insp Interval ML20212A2631999-09-0909 September 1999 Forwards Rev 25 to McGuire Nuclear Station,Units 1 & 2 Pump & Valve Inservice Testing Program, IAW 10CFR50.55a. Section 8.0 Contains Summary of Changes & Detailed Description of Changes Associated with Rev 25 ML20212A5191999-09-0808 September 1999 Requests NRC Approval for Relief from Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,App VI,VI-2430(c) & 2440(b).Approval of 99-GO-002 Is Requested by 000301 ML20211J3671999-08-31031 August 1999 Forwards Public Notice of Application for Amend to License NPF-9 Seeking one-time Extension of Surveillance Frequency for TS SR 3.1.4.2 Beyond 25% Extension Allowed by TS SR 3.0.2 ML20211M4451999-08-30030 August 1999 Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting ML20211H1741999-08-30030 August 1999 Forwards Comments on Catawba Nuclear Station Units 1 & 2 & McGuire Nuclear Station,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid.Ltr Dtd 990107,rept ATI-98-012-T005 & Partial marked-up Rept WCAP-14995 Encl ML20211K8831999-08-26026 August 1999 Forwards Insp Repts 50-369/99-05 & 50-370/99-05 on 990620-0731.Two Violations Occurred & Being Treated as NCVs ML20211G5181999-08-24024 August 1999 Forwards SE Re second-10-yr Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211F2971999-08-17017 August 1999 Forwards non-proprietary & Proprietary Updated Pages for DPC-NE-2009,submitted 980722.Pages Modify Fuel Design & thermal-hydraulic Analysis Sections of DPC-NE-2009. Proprietary Page 2-4 Withheld,Per 10CFR2.790 ML20211B1121999-08-16016 August 1999 Forwards Topical Rept DPC-NE-2012, Dynamic Rod Worth Measurement Using Casmo/Simulate, Describing Results of Six Drwm Benchmark Cycles at Catawba & McGuire & Discusses Qualification to Use Drwm at Catawba & McGuire ML20210V0171999-08-13013 August 1999 Confirms Conversation Between M Cash & M Franovich on 990806 Re Mgt Meeting,Scheduled for 990917 to Present self- Assessment of Plant Performance.Meeting Will Be Held in Atlanta,Ga ML20210S2231999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210T4511999-08-10010 August 1999 Forwards Response to NRC RAI Re 981014 Standby Nuclear Svc Water Pond Dam Audit Conducted by FERC ML20210R4311999-08-10010 August 1999 Forwards Summary Rept of Mods,Minor Mods,Procedure Changes & Other Misc Changes Per 10CFR0.59 ML20210R0031999-08-10010 August 1999 Forwards Revised TS Bases Pages to NRC for Info & Use. Editorial Changes Were Made to Correct Incorrect UFSAR Ref Number Associated with Certain Reactor Coolant Sys Pressure Isolation Valves ML20210Q3701999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr as Listed,Thirty Days Before Exam Date in Order to Register Individuals to Take Exam ML20210H7691999-07-21021 July 1999 Submits Summary of 990715 Meeting at Facility Re Presentation of Results of Most Recent Periodic Ppr.List of Meeting Attendees Encl ML20209H1551999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for May 1999 Also Encl ML20210E1931999-07-13013 July 1999 Forwards Insp Repts 50-369/99-04 & 50-370/99-04 on 990509-0619.Four Violations of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy NUREG-1431, Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation1999-07-0909 July 1999 Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20209G5151999-07-0808 July 1999 Forwards Amended Pages to Annual Radioactive Effluent Release Repts, for 1997 & 1998 for McGuire Nuclear Station. Portion of Rept Was Inadvertently Omitted Due to Administrative Error,Which Has Been Corrected ML20196J9001999-07-0606 July 1999 Informs That 990520 Submittal of Rept DPC-NE-3004-PA,Rev 1, Mass & Energy Release & Containment Response Methodology, Marked Proprietary Will Be Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20196J4381999-06-29029 June 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1,NRC Revised Info in Rvid & Releasing Rvid Version 2 ML20196G3721999-06-24024 June 1999 Documents Verbal Info Provided to NRR During Conference Call Re Relief Requests 98-002 & 98-003 ML20196G7461999-06-22022 June 1999 Requests Exemption from Requirements of 10CFR54.17(c) That Application for Renewed Operating License Not Be Submitted to NRC Earlier than 20 Yrs Before Expiration of Operating License Currently in Effect ML20195K3601999-06-14014 June 1999 Forwards MORs for May 1999 for McGuire Nuclear Station,Units 1 & 2 & Revised MORs for Apr 1999.Line 6 Max Dependable Capacity (Gross Mwe) on Operating Data Rept Should Be Revised to 1114 from Jan 1998 to Apr 1999 ML20195D5691999-06-0303 June 1999 Submits Ltr to Facilitate Closing of Inspector Follow Up Item 50-369,370/97-15-05,re Revising Site Drawings in UFSAR Into Summary one-line Flow Diagrams,Per NRC 990327 Telcon ML20195F1851999-06-0202 June 1999 Forwards Insp Repts 50-369/99-03 & 50-370/99-03 on 990328- 0508.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20195E8771999-06-0202 June 1999 Confirms Telcon with M Cash on 990524 Re Public Meeting for 990715.Purpose of Meeting to Discuss Results of NRC Most Recent PPR ML20207D0521999-05-21021 May 1999 Informs That in Telcon on 990519 Between a Orton & Rf Aiello Arrangements Made for Administration of Initial Written Exam for McGuire Nuclear Station on 990603.Exam Will Be Administered at Catawba Simultaneously with Written Exam ML20196L1791999-05-20020 May 1999 Communicates Util Licensing Position Re Inoperable Snubbers. Licensee Has Determined That Structure of ITS Has Resulted in Certain Confusion Re Treatment of Inoperable Snubbers ML20196L1851999-05-20020 May 1999 Forwards Proprietary & non-proprietary Version of Rev 1 to TR DPC-NE-3004, Mass & Energy Release & Containment Response Methodology, Consisting of Finer Nodalization of Ice Condenser Region.Proprietary Info Withheld ML20206T4481999-05-13013 May 1999 Forwards Rev 3 to Topical Rept DPC-NE-3002-A, UFSAR Chapter 15 Sys Transient Analysis Methodology, IAW Guidance Contained in NUREG-0390 ML20206R0791999-05-13013 May 1999 Forwards Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 & Revised Monthly Operating Repts for Mar 1999 1999-09-09
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217F8011999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of McGuire Nuclear Station.Areas That Warranted More than Core Insp Program Over Next Five Months,Not Identified.Historical Listing of Plant Issues Encl ML20217C4471999-10-0404 October 1999 Forwards Insp Repts 50-369/99-06 & 50-370/99-06 on 990801- 0911.Determined That One Violation Occurred & Being Treated as Non-Cited Violation ML20212J2191999-10-0404 October 1999 Informs That Util 980326 Response to GL 97-06, Degradation of SG Internals Provides Reasonable Assurance That Condition of Steam Generator Internals Are in Compliance with Current Licensing Bases for Facility ML20212J7801999-10-0404 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for McGuire NPP & 990615.Informs That NRC Reviewed Responses & Concluded That All Requested Info Re Y2K Readiness Provided.Subj GL Considers to Be Closed ML20212M1651999-09-23023 September 1999 Refers to 990917 Meeting at Region II Office Re Licensee Presentation of self-assessment of McGuire Nuclear Station Performance.List of Attendees & Licensee Presentation Handouts,Encl ML20212D1671999-09-20020 September 1999 Forwards Exemption & SER from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Re Isolation of Main Steam Branch Lines Penetrating Containment.Exemption Related to Licensee Application ML20212B6491999-09-15015 September 1999 Informs That Encl Announcement Re 990913 Application for Amend to Licenses NPF-9 & NPF-7 Forwarded to C Observer in North Carolina,For Publication ML20212A4131999-09-14014 September 1999 Informs That TR DPC-NE-2009P Submitted in 990817 Affidavit, Marked Proprietary,Will Be Withheld from Public Disclosure, Pursuant to 10CFR2.709(b) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20212A0501999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementing Code Case for Duration of Insp Interval ML20211J3671999-08-31031 August 1999 Forwards Public Notice of Application for Amend to License NPF-9 Seeking one-time Extension of Surveillance Frequency for TS SR 3.1.4.2 Beyond 25% Extension Allowed by TS SR 3.0.2 ML20211K8831999-08-26026 August 1999 Forwards Insp Repts 50-369/99-05 & 50-370/99-05 on 990620-0731.Two Violations Occurred & Being Treated as NCVs ML20211G5181999-08-24024 August 1999 Forwards SE Re second-10-yr Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20210V0171999-08-13013 August 1999 Confirms Conversation Between M Cash & M Franovich on 990806 Re Mgt Meeting,Scheduled for 990917 to Present self- Assessment of Plant Performance.Meeting Will Be Held in Atlanta,Ga ML20210Q3701999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr as Listed,Thirty Days Before Exam Date in Order to Register Individuals to Take Exam ML20210H7691999-07-21021 July 1999 Submits Summary of 990715 Meeting at Facility Re Presentation of Results of Most Recent Periodic Ppr.List of Meeting Attendees Encl ML20210E1931999-07-13013 July 1999 Forwards Insp Repts 50-369/99-04 & 50-370/99-04 on 990509-0619.Four Violations of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy NUREG-1431, Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation1999-07-0909 July 1999 Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196J9001999-07-0606 July 1999 Informs That 990520 Submittal of Rept DPC-NE-3004-PA,Rev 1, Mass & Energy Release & Containment Response Methodology, Marked Proprietary Will Be Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20196J4381999-06-29029 June 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1,NRC Revised Info in Rvid & Releasing Rvid Version 2 ML20195E8771999-06-0202 June 1999 Confirms Telcon with M Cash on 990524 Re Public Meeting for 990715.Purpose of Meeting to Discuss Results of NRC Most Recent PPR ML20195F1851999-06-0202 June 1999 Forwards Insp Repts 50-369/99-03 & 50-370/99-03 on 990328- 0508.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20207D0521999-05-21021 May 1999 Informs That in Telcon on 990519 Between a Orton & Rf Aiello Arrangements Made for Administration of Initial Written Exam for McGuire Nuclear Station on 990603.Exam Will Be Administered at Catawba Simultaneously with Written Exam ML20206L5631999-05-11011 May 1999 Forwards Two Documents Requesting That NRC Place on Docket 50-369 & 50-370,technical Interface Agreement 97-02 & Related Staff Evaluation ML20206N3451999-05-11011 May 1999 Forwards SE of Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20206M2121999-05-11011 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Mgt Created ML20206C0451999-04-23023 April 1999 Forwards Insp Repts 50-369/99-02 & 50-370/99-02 on 990214-0327.No Violations Noted ML20205Q6641999-04-15015 April 1999 Forwards Amend 10 to Indemnity Agreement B-83 for Signature & Return to Document Control Desk ML20205M6741999-04-13013 April 1999 Discusses 980318 Telcon of Licensing Bases Record Change Re Duke Energy Corp License Amend Request, & Staff Approval in Form of TS Amends 184 & 166,dtd 980930.Forwards Revised Pp to SE of 980930 ML20205T1711999-04-0909 April 1999 Informs That on 990317 Ho Christensen & a Orton Confirmed Initial Operator Licensing Exam Schedule for Y2K.Initial Exam Dates for Wks of 000508 & 22 for Approx 13 Candidates ML20205M2601999-03-25025 March 1999 Informs That NRC Completed PPR of Plant on 990201.Plant Issues Matrix & Insp Plan for Next 8 Months Encl ML20205A9371999-03-24024 March 1999 Forwards Evaluated & Final Rept from Ferc,Related to 981014 Dam Safety Audit Conducted at McGuire Nuclear Station for Category I Standby Service Water Pond Dam.List of Actions That Should Be Taken by Util to Ensure Safety of Dam,Encl ML20205H9201999-03-18018 March 1999 Forwards Exam Repts 50-369/99-301 & 50-370/99-301 on 990125- 0205.Of Eleven SRO & RO Candidates Taking Written Exam & Operating Tests,Nine Passed & Two Failed,Representing 82% Pass Rate ML20204E3221999-03-10010 March 1999 Forwards Insp Repts 50-369/99-01 & 50-370/99-01 on 990103- 0213.Non-cited Violation Noted ML20207M9091999-03-0505 March 1999 Informs That Info Submitted by Application, Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20203J0431999-02-16016 February 1999 Discusses Review of Plant,Units 1 & 2 IPEEE Submittal.Staff Concludes That Util IPEEE Process,Capable of Identifying Most Likely Severe Accidents & Severe Accidents Vulnerabilities.Intent of Suppl 4 to GL 88-20 Met ML20203C2411999-02-0505 February 1999 Discusses Draft Operation Insp Rept for McGuire Nuclear Station Standby Nuclear Service Water Pond Dam Conducted on 981028.Draft Rept States That Dam Appeared to Be in Good Condition & Adequately Maintained ML20203G3361999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Listing of Names of Candidates for Exam ML20202E3861999-01-28028 January 1999 Refers to GL 96-05 Issued on 960918 & DPC 980331 Updated Response to GL 96-05 Indicating Intent to Implement Provisions of JOG Program on MOV Periodic Verfication at Mcguire.Rai Re JOG Program McGuire Encl ML20199L4421999-01-25025 January 1999 Informs That by Encl Ltrs & 981223,NRC Has Responded to WOG Positions Re C/As to Address Generic Aspects of part-length CRD Mechanism Housing Issue That Originated as Result of 980123 Leak at Pings ML20203A4171999-01-22022 January 1999 Refers to 990119 Meeting Conducted in Region II Ofc for Presentation of self-assessment of McGuire Nuclear Station Performance & Future Plant Initiatives.List of Attendees & Presentation Handouts Encl ML20198Q7711999-01-0505 January 1999 Informs That Staff Review of GL 97-05, SG Tube Insp Technique, Did Not Identify Any Concerns with SG Tube Insp Techniques Employed at McGuire That Would Indicate That Util Not in Compliance with Current Licensing Bases for Plant ML20198Q7551999-01-0505 January 1999 Forwards RAI Re 980722 Request for Amend to Plant,Units 1 & 2 TSs to Permit Use of Westinghouse Fuel.Response Requested on or Before 990131 ML20199F6031998-12-23023 December 1998 Submits Summary of 981105 Training Managers Conference.List of Attendees & Matl Used in Presentation Enclosed ML20198N8771998-12-18018 December 1998 Forwards Insp Repts 50-369/98-10 & 50-370/98-10 on 981004- 1121.No Violations Noted ML20198N7001998-12-14014 December 1998 Confirms 981210 Conversation Between M Cash & E Lea Concerning Meeting Scheduled for 990119.Purpose of Meeting to Present self-assessment of Plant Performance ML20198A4221998-12-11011 December 1998 Forwards SE Accepting Licensee 980115 Request for Relief from Requirements of ASME BPV Code,Section Xi,Table IWB-2500-1,for Plant ML20196F2901998-11-23023 November 1998 Advises of Planned Insp Effort Resulting from Insp Planning Meeting Held on 981102.Details of Insp Plan for Next Four Months & Historical Listing of Plant Issues Called PIM Encl ML20196B0011998-11-23023 November 1998 Forwards Emergency Response Data Sys Implementation Documents,Which Include Data Point Library Updates for Listed Plants.Changes Should Be Made to Data Base as Soon as Possible.Without Encl ML20195J5401998-11-19019 November 1998 Forwards RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations. Staff Requests Response to RAI by 990205 ML20196C7681998-11-13013 November 1998 Forwards Copy of Answer Key & Master Bwr/Pwr GFE Section of Written Operator Licensing Exam,Administered on 981007 by Nrc.Without Encl 1999-09-23
[Table view] |
Text
-
r pa ncg l n UNITED STATES 3
D .E NUCLEAR REGULATORY COMMISSION o e / WASHINGTON, D.C. 20555 s, ***+
- w f Concord Associates, Inc. JUN 101993 Attn: Paul M. Haas 725 Pellissippi Parkway Suite 101, Box 6 Knoxville, TN 37933
Dear Mr. Haas:
Subject:
Contract No. NRC-04-91-069, Task Order No.17 Entitled,
" Individual Plant Examination (IPE) Reviews, Internal Events, Human Factors Only" - Step 2 (McGuire)
This confirms the verbal authorization provided to you on May 7,1993 to commence work under the subject task order with a temporary ceiling of $3,500.
In accordance with Section G.9 entitled, " Task Order Procedures" of the subject contract, this letter definitizes Task Order No.17. This effort shall be performed in accordance with the enclosed Statement of Work.
Task Order No.17 shall be in effect From May 7,1993 through December 6, 1993, with a total cost ceiling of $19,105 which is inclusive of the $3,500 temporary ceiling authorized on May 7, 1993. The amount of $17,855 represents the total estimated reimbursable costs and the amount of $1,250 represents the fixed fee.
The obligated amount of this task order is $19,105.
Accounting Data for Task Order No.17 is as follows:
APPN No.: 31X0200.360 B&R No.: 36019202300 FIN No.: L-1934 B0C: 2542 OBLIGATED AMOUNT: $19,105 RES IDENTIFIER: RES-C933-104 The following individuals are considered to be essential to the successful performance for wor.k hereunder: Paul H. Haas and C. Randy Bovell.
The Contractor agrees that such personnel shall not be removed from the effort under the task order without compliance with Contract Clause H.1, Kev Personnel.
Issuance of this task order does not amend any terms or conditions of the subject contract.
I 9309250359 930610 7 PDR CONTR u NRC-04-91-069 PDR I
w -
= t NRC-04-91-069 ;
Task Order No. 17 Page 2 l Your contacts during the course of this task order are:
Technical Matters: John Flack l Project Officer (301) 492-3979 ;
Contractual Matters: Edna Knox-Davin [
Contract Administrator i (301) 492-4731 l Please indicate your acceptance of this Task Order No. 17 by having an official, authorized to bind your organization, execute three copies of this i document in the space provided and return two copies to the Contract -'
Administrator. You should retain the third copy for your records. i If you have any questions regarding this matter, please contact Edna Knox- l Davin, Contract Administrator, on (301) 492-4731.
Sincerely, j30 '
Mary Jo Mattia, Contracting Officer Contract Administration Branch No. 2 Division of Contracts and Property Management Office of Administration
Enclosure:
As stated ACCEPTED: .M/
NAME: Paul M. Haas TITLE: President DATE: June 15, 1993 l
l i
- ~
l l'
Contract NRC-04-91-069 Concord Associates, Inc.
STATEMENT OF WORK l
Task Order - 17 TITLE: Individual Plant Examination (IPE) Reviews, Internal Events Human Reliability Analysis Only, (McGuire)
HRC PROJECT MANAGER: John H. Flack, RES (301-492-3979)
NRC TEAM LEADER FOR MCGUIRE: Ed Chow, RES (301-492-3984) l TECHNICAL HONITOR: John H. Flack, RES (301-492-3979) i f
PERIOD OF PERFORMANCE: 8 months v BACKGROUND: 1 On November 23, 1988, the NRC issued Generic Letter 88-20, " Individual Plant Examination," which stated that licensees of existing plants should perform a- ,
systematic examination (IPE) to identify any plant-specific vulnerabilities to severe accidents, and to report the results to the Commission. The purpose of the IPE is to have each utility (1) develop an overall appreciation of severe accident behavior; (2) understand the most likely severe accident sequences at its plant; (3) gain a quantitative understanding of the overall probability of core damage and radioactive material releases; and (4) reduce the overall ;
probability of core damage and radioactive releases by modifying procedures ;
and hardware to prevent or mitigate severe accidents. All IPE submittals will be reviewed by the NRC staff to determine if licensees met the intent of Generic Letter 88-20. ,
TheNRCstaffreviewofIPEsinvolvesatwostepprocess. The first step, or t
" step 1" includes an NRC team examinatioc of the IPE submittal and subsequent ,
meetings with the licensee to understand the IPE effort. All IPE submittals will undergo a " step 1" review by the NRC staff. A second step, or " step 2" review, may be required if limitations are identified, or a better understanding of the licensee's IPE process is warranted. Contractors are expected to support the " step 2" review effort by auditing IPE documentation '
held at the site, and assessing limitations identified by the NRC review team members under " step 1."
OBJECTIVE:
The purpose of this task order is to provide support during the " step 2" review of the McGuire IPE human reliability analysis. The NRC review objective is to determine whether the licensee's IPE process met the intent of Generic letter 88-20. The " step 2" review will involve a site visit and audit 1
of " tier 2" information (e.g., fault trees, system notebooks, data, calculations). 1 WORK REOUIREMENTS AND SCHEDULE: -
Under this task order contract, an audit of the McGuire IPE human reliability analysis will be performed. The contractor will provide qualified specialists and the necessary facilities, materials, and services to the NRC staff. The contractor analyst will review the IPE submittal and associated documentation, and prepare for a site visit by developing an audit plan which will be submitted to the IPE Team Leader at least three weeks prior to the site visit.
The site visit will involve the audit of " tier 2" information, and include plant walk-throughs and meetings with licensee staff involved in the IPE analysis. The audit will focus on licensee identified vulnerabilities, especially those associated with the decay heat removal system. The contractor will bring to the immediate attention of the review team members any potential vulnerabilities that may appear to require further analysis or i evaluation, and the basis for identified concern. ,
For this task order, perform the following subtasks:
Subtask 1. Review and Identify Needed Information i Review IPE review team " step 1" findings, specifically those associated with the human reliability analysis. Review NRC questions sent to the licensee and the licensee's response. Attention should be placed on any remaining issues and their significance with respect to the IPE's ability to identify vulnerabilities. During the submittal review, key on the following aspects of the licensee's IPE process:
A. General Approach A.1 The IPE employed a viable process to confirm that the plant models represent the as-operated plant. ;
A.2 The employed HRA methodology is clearly described and justified l for selection. The methodology (including the human action 1 taxonomy) employed is capable of identifying important human actions.
B. Review the Sequences Involving Human Action B.1 The accident sequences appropriately considered human actions i consistent with NUREG-1150 and other NRC accepted PSAs (see NUREG- l 1335 Appendix B). g B.2 The accident sequences screened out because of low human error (see NUREG-1335, Section 2.1.6.6) appear appropriate, based on HRA techniques employed.
2
B.3 For multi-unit plant analyses, the IPE appropriately considered operational differences between units.
C. Quantitative Process C.1 In general, the licensee employed a reasonable process to understand and quantify human reliability. The process lead to a determination of important human failure probabilities, and considered uncertainties in human response, either qualitative or quantitative.
C.2 The employed human error probability (HEP) screening values appear capable of screening .in significant human errors.
C.3 The IPE developed human error probabilities (HEPs) for significant human actions, or provided rationale for using screening values.
C.4 Sources of generic human reliability data used in the IPE were documented and the rationale for their use provided. Generic human error probability (HEP) data were modified using plant-specific Performance Shaping Factors (PSFs) as appropriate, and the rationale for selection of employed PSFs was provided.
C.5 The recovery method is clearly described and credit for recovery actions appears justified.
D. Vulnerability Evaluation D.1 The IPE supports the licensee's definition of vulnerability with respect to human error. The licensee's definition provided a means by which the licensee could identify potential vulnerabilities (as so defined) and plant modifications (or safety enhancements) to eliminate or reduce the affect of vulnerabilities.
D.2 The identification of plant improvements include human-related plant modifications (e.g., procedures and training), and proposed modifications are reasonably expected to enhance human reliability and plant safety.
Document any identified strengths, weaknesses, obvious limitations or inconsistencies between the licensee's IPE findings and studies from similar plants. Areas needing specific attention during the site visit should be identified and forwarded to the NRC review team leader in a letter report at least three weeks prior to the site visit and audit. Identify licensee personnel that need to be contacted during the site visit and documentation needed for audit.
Schedule Completion: Three weeks prior to site visit 3
I
]
Subtask 2. Perform Site Visit The objective of the site visit is to access and review information not contained in the submittal but needed to understand the licensee's IPE process. The site visit will:
(1) audit all IPE " tier 2" information related to the human reliability, e.o.. human event trees. fault trees. notebooks. data base. etc.;
(2) obtain an overall physical perspective of the licensee's operational facility by performing walk-throughs, especially focusing on areas which require outside control room actions during accident scenarios; (3) gather information and insights on weak areas identified by the NRC under " step 1"; and (4) interview key analysts and site personnel that were responsible f,or the IPE project.
NOTE: Once at the site, but prior to the start of the on-site audit, the contractor's staff is required to meet with the NRC IPE Review Team Leader and other NRC personnel involved in the IPE review. The pre-audit meeting will focus on the audit's scope and objectives, coordination of travel logistics, and preparation of site access documentation.
Schedule Completion: The site audit is expected to involve three days including travel and will be scheduled in cognizance with the NRC plant Project Manager and the licensee. An early pre-audit meeting at the site is
~
scheduled for the first day, followed by a two-day IPE audit and closing meeting on the third day.
Subtask 3. Prepare Technical Evaluation Report l The contractor will prepare a technical evaluation report with the following outlint:
Executive Summary l l
Provide a one-page summary of the audit process, findings, conclusions, and recommendations.
I. Introduction o Provide a brief overview of the licensee's IPE process in the technical area under audit and any important insights stemming from the IPE in the technical area under review.
o Provide a brief overview of the audit process, the scope, objectives, and areas of interest.
. 4
. 1 I
o Document pre-site visit activities; include meetings, information review, and preparation for site visit.
o Document si.te activities including:
- Information audited at the site - description of " tier 2" j information audited Personnel interviewed and identification of individuals that :
provided information during the audit (include name, title and company) ;
Walk-throughs performed and general observations of facilities >
Describe how areas of interest discussed in the
" Introduction" above were addressed during the audit II. Audit Findings for each of the subtask 1 items listed above, discuss the audit's :
findings, including any strengths or shortcoming identified in the licensee's IPE and significance with respect to the overall IPE effort.
Note any inconsistencies with other PSA's. Indicate and discuss areas ,
reported in the submittal but not supported by " tier 2" information audited at the site. ,
III. Audit Conclusions and Recommendations Document the audit's conclusion. Focus on the ability of the licensee's IPE process to identify potential vulnerabilities, and the reasonableness of licensee's actions and commitments. The report should '
discuss the reasonableness of any specific licensee identified vulnerabilities and associated fixes. Characterize limitations with regard to significance.
Schedule Completion: The contractor shall provide a technical review report one month following the site audit.
REPORT RE0VIREMENTS:
Technical Reports At the completion of subtask 1, provide an audit plan. input to the IPE Team Leader. The plan shall include areas needing specific attention during the site visit, and licensee personnel that will need to be contacted.
At the completion of subtask 2, but prior to the audit team's exit meeting with the licensee, each contractor cialist shall provide a draft audit I report input to the NRC Team Leader. The format and scope of this input shall ;
5 r
l be as provided by the NRC IPE Team Leader. Typically, this input will consist of a handwritten summary of the contractor's audit findings.
1 The contractor will submit to the NRC technical monitor two copies of the J audit report one month after the completion of the Step 2 site audit. Copies will include one hard copy and one computer diskette version (Wordperfect 5.1 or other IBM PC compatible software acceptable to the NRC IPE Team Leader) to i be given to the IPE Team Leader. The report shall summarize all findings, results, and conclusions in the areas examined in the format described under Task 3. If the contractor finds that the licensee's IPE is obviously deficient in any of the areas examined, the IPE Team Leader should be notified in advance. Deficient or weak areas should be clearly documented in the audit report. In addition, if the contractor finds that there are specific areas that need additional in-depth review, the Team Leader should be notified of the areas, and provided with the rationale for subsequent review.
Business letter Report The contractor shall provide monthly progress reports in accordance wit'h the requirements of the basic contract.
HEETINGS AND TRAVEL:
One, one person, three-day trip to the plant site to conduct the IPE audit.
ESTIMATED LEVEL OF EFFORT:
For each IPE reviewed and audited:
Subtask I 60 contractor hours Subtask 2 24 contractor hours ;
Subtask 3 100 contractor hours It shall be the responsibility of the contractor to assign technical staff, employees, and subcontractors whar have the required educational background, l experience, or combination thereof, to meet both the technical and regulatory objectives of the work specified in this 50W. The NRC will rely on representation made by the contractor concerning the qualifications of the personnel proposed for assignment to this task order including assurance that all information contained in the technical and cost proposals, including resumes and qualifications of the personnel proposed for assignment to this i task order and conflict of interest disclosures, is accurate and truthful.
NRC FURNISHED MATERIAL:
(I) Licensee's IPE submittals, (2) IPE review questions and licensee's response.
I 6
l
.+ ~
l l
TECHNICAL DIRECTION: l The NRC Project Manager is:
John H. F1ack Severe Accident Issues Branch Division of Safety Issue Resolution U.S. NRC, Mail Stop NL/S 324 Washington, D.C. 20555 Telephone No. (301) FTS-492-3979 I
t b
i
. 7