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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N1931999-10-22022 October 1999 Forwards Insp Rept 50-298/99-12 on 990927-30.No Violations Noted.Insp Exam of Activities Under License as They Relate to Emergency Preparedness & to Compliance with Commission Rules & Regulations & with Conditions of License ML20217G8771999-10-14014 October 1999 Forwards Insp Rept 50-298/99-10 on 990920-24.No Violations Noted ML20217G7401999-10-14014 October 1999 Forwards MOR for Sept 1999 for Cooper Nuclear Station. Rept Includes Documentation of Challenges to Safety/Relief Valves,Iaw TS 5.6.4 ML20217C2671999-10-0808 October 1999 Forwards Insp Rept 50-298/99-03 on 990823-27 & 0907-10.No Violations Noted.Purpose of Insp to Ensure That Licensee Had Effective Programs for Identifying,Evaluating & Correcting Problems Which Could Impact Safe Plant Operations ML20212K9661999-09-30030 September 1999 Forwards Safety Evaluation Accepting plant-specific Safety Evaluation Rept for USI A-46 Program Implementation at Cooper Nuclear Station ML20216J1081999-09-28028 September 1999 Ltr Contract:Task Order 048, Cooper Safety Sys Design & Performance Capability Insp, Under Contract NRC-03-98-021 ML20212J5061999-09-27027 September 1999 Forwards Insp Rept 50-298/99-07 on 990718-0828.No Violations Noted.Inspectors Focused on Implementation of Licensee Reactor Safety & Emergency Preparedness Programs ML20212F3641999-09-22022 September 1999 Forwards Insp Rept 50-298/99-09 on 990823-26.No Violations Noted ML20216J8061999-09-20020 September 1999 Forwards Rev 37 to Safeguards Plan,Iaw Provisions of 10CFR50.(p).Rev Withheld,Per 10CFR73.21 ML20212C4921999-09-15015 September 1999 Forwards Monthly Operating Rept for Aug 1999 for Cooper Nuclear Station.Rept Includes Operating Data Rept,Unit SD Rept & Documentation of Challenges to Safety/Relief Valves ML20212A6061999-09-14014 September 1999 Forwards Insp Rept 50-298/99-08 on 9900816-20.No Violations Noted.Insp Focused on Implementation & Effective Performance of Access Authorization/Fitness-for-Duty (Behavior Observation) Program & Access Control of Personnel ML20211N5271999-09-0202 September 1999 Responds to NRC 990823 RAI Re Y2K Readiness at Cooper Nuclear Station,Per GL 98-01,Suppl 1 05000298/LER-1999-006, Forwards LER 99-006-00 for Cns.Commitments Made by Util Encl1999-08-26026 August 1999 Forwards LER 99-006-00 for Cns.Commitments Made by Util Encl ML20211F1311999-08-24024 August 1999 Forwards Rev 1 to Calculation Nedc 97-044, NPSH Margins for RHR & CS Pumps, in Support of 990615 Proposed Amend to DPR-46 Re Containment Overpressure Contribution to ECCS Pumps NPSH Requirements 05000298/LER-1999-003, Informs That Commitment Re Insp Rept 50-298/98-15 & LER 99-003,to Bound Extent of Condition & Take Appropriate C/As Is Now Complete.Addl Time Is Required to Accommodate Training of Engineering Support Personnel1999-08-23023 August 1999 Informs That Commitment Re Insp Rept 50-298/98-15 & LER 99-003,to Bound Extent of Condition & Take Appropriate C/As Is Now Complete.Addl Time Is Required to Accommodate Training of Engineering Support Personnel ML20211F4661999-08-23023 August 1999 Discusses GL 98-01 Issued by NRC on 980511 & NPPD Responses for Cooper Nuclear Station & 990628 & Results of Visit to Plant on 990811-12.Staff Determined That Integrated Contigency Plan Incomplete & CNS Not Y2K Ready ML20210R0301999-08-12012 August 1999 Forwards Monthly Operating Rept for July 1999 for Cooper Nuclear Station,Iaw Guidance Provided by GL 97-02.Rept Also Includes Documentation of Challenges to Srvs,Per TS 5.6.4 ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210P6761999-08-10010 August 1999 Requests That Following Changes Be Made to Distribution on NRC Correspondence ML20210P6861999-08-0909 August 1999 Forwards Insp Rept 50-298/99-06 on 990530-0717.No Violations Noted.During Insp,Inspectors Identified Two Issues Categorized as Being Low Risk Significance & within Licensee Response Band ML20210N1331999-08-0606 August 1999 Forwards Notice of Withdrawal of Application for Amend to FOL DPR-46.By Ltr Licensee Withdrew Amend Request Which Would Have Revised Usfar to Reflect as-built Configuration of Reactor Bldg Isolation Dampers ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210K6071999-08-0202 August 1999 Submits Withdrawal of Proposed License Amend Re Secondary Containment Isolation Description & Refueling Accident Analysis Results ML20210K3811999-08-0202 August 1999 Forwards Listed Info,Which NPPD Believes Demonstrates Ability to Obtain Funds in Amount of $10 Million for Payment of Such Premiums within Specified Three Month Period,Iaw 10CFR140.21 ML20210G5101999-07-28028 July 1999 Forwards fitness-for-duty Program semi-annual Performance Rept for Period of 990101-0630,per Provisions of 10CFR26.71(d) ML20210D2541999-07-21021 July 1999 Forwards Insp Rept 50-298/99-02 on 990628-0702.Purpose of Insp Was Primarily to Evaluate Effectiveness of Licensed Operator Requalification Program.No Violations Were Identified ML20210C2041999-07-20020 July 1999 Discusses 990715 Mgt Meeting with Midamerican Energy Co Re risk-informed Baseline Insp Program Recently Implemented at Cooper & Fort Calhoun Stations ML20209H8191999-07-15015 July 1999 Forwards Safety Evaluation on GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Cooper Nuclear Station ML20209E6951999-07-12012 July 1999 Discusses Response to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. Recommends Review of New Database Diskettes on Listed Website.Comments Due by 990901 or Data Entered Into Rvid for Plant Will Be Acceptable ML20209D8731999-07-0808 July 1999 Refers to 990707 Meeting Re Licensee Recent Maintenance Program self-assessment.Also Discussed How Licensee Incorporated Assessment Findings Into Rev of Maintenance Performance Improvement Plan.List of Attendees Encl ML20209B7851999-07-0101 July 1999 Forwards Corrected Occupational Radiation Exposure Repts, for Cys 1996 & 1997.Util Stated That Repts Did Not Properly Tabulate Number of Personnel Receiving Exposures Less than 100 Mrem by Work & Job Functions in CY96 & CY97 05000298/LER-1999-005, Forwards LER 99-005-00 for Cns.Commitments Made by Util Encl1999-07-0101 July 1999 Forwards LER 99-005-00 for Cns.Commitments Made by Util Encl ML20196J2471999-06-29029 June 1999 Discusses Completion of Licensing Action for GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps, 05000298/LER-1999-004, Forwards LER 99-004-01.Commitments Made by Util Are Encl1999-06-28028 June 1999 Forwards LER 99-004-01.Commitments Made by Util Are Encl ML20209B5451999-06-28028 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl ML20196H0331999-06-24024 June 1999 Informs NRC of Deletion of 1991 Commitment Contained in Ltr Re Feedwater Nozzle Bypass Leakage Monitoring at Plant ML20196F7511999-06-24024 June 1999 Discusses 990622 Meeting with Public at Arbor Manor, Alburn,Ne to Provide Overview of Pilot Insp Program ML20209A7221999-06-23023 June 1999 Submits Revised Pages to Proposed Change to Plant TS Previously Submitted in ,Per 990615 Telcon with NRC ML20196F5331999-06-22022 June 1999 Forwards Examination Summary Rept for FW Nozzle Examinations Performed During 1998 Fall Refueling Outage at Cooper Nuclear Station.Rept Covers Past Examinations Up to & Including 1998 Fall Refueling Outage ML20196B4681999-06-17017 June 1999 Forwards TS Bases Changes Made at Plant Subsequent to Receipt of License Amend 178,dtd 980731,for Conversion to Its,Through 990610.List of Effective Pages for TS Bases, Encl ML20196E1411999-06-16016 June 1999 Forwards Insp Rept 50-298/99-05 on 990502-29.Noncited Violations Identified ML20195H8891999-06-14014 June 1999 Forwards Response to NRC 990315 RAI Re GL 95-07, Pressure Locking & Thermal-Binding of SR Power-Operated Gate Valves, 180-day Response Submitted by District on 960213 ML20195F6171999-06-0909 June 1999 Informs That GE Rept, Matl Presented by GE 970709 Meeting at Cooper Nuclear Power Station Re Replacement of ECCS Pump Suction Strainers Between Nppd,Ge & NRC Staff, Will Be Withheld from Public Disclosure as Requested ML20207G3031999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Cooper Nuclear Station EP Implementing Procedure EPIP 5.7.1, Emergency Classification,Rev 24,under 10CFR50,App E,Section V Provisions.No Violations Identified ML20195E2351999-06-0808 June 1999 Forwards Response to NRC 990517 RAI Re Util Proposed Change to TS Re Calibr Frequency of Reactor Recirculation Flow Transmitters Associated with APRM ML20207G4481999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Cooper Nuclear Station EP Implementing Procedure,Epip 5.7.1, Emergency Classification,Rev 23 C2,under Provisions of 10CFR50,App E,Section V ML20207G3001999-06-0707 June 1999 Ack Receipt of Which Transmitted Changes to Cooper Nuclear Station Ep,Rev 33,under Provisions of 10CFR50,App E,Section V.No NRC Approval Required Based on Determination That EP Effectiveness Not Affected by Changes ML20207G4531999-06-0707 June 1999 Ack Receipt of Which Transmitted Changes to Cooper Nuclear Station EP Implementing Procedure EPIP 5.7.1, Emergency Classification,Revision 25,under Provisions of 10CFR50,App E,Section V ML20207D3811999-05-27027 May 1999 Informs That During Next 6 to 12 Months,Starting 990530,NRC Plans to Conduct Insps Shown in Attached Insp Plan.Insps Include Both Planned Baseline & Supplemental Insps (Formerly Core & Regional Initiative Insps) ML20207A5191999-05-19019 May 1999 Forwards Insp Rept 50-298/99-04 on 990321-0501.Four Violations Identified & Being Treated as non-cited Violations 1999-09-30
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217N1931999-10-22022 October 1999 Forwards Insp Rept 50-298/99-12 on 990927-30.No Violations Noted.Insp Exam of Activities Under License as They Relate to Emergency Preparedness & to Compliance with Commission Rules & Regulations & with Conditions of License ML20217G8771999-10-14014 October 1999 Forwards Insp Rept 50-298/99-10 on 990920-24.No Violations Noted ML20217C2671999-10-0808 October 1999 Forwards Insp Rept 50-298/99-03 on 990823-27 & 0907-10.No Violations Noted.Purpose of Insp to Ensure That Licensee Had Effective Programs for Identifying,Evaluating & Correcting Problems Which Could Impact Safe Plant Operations ML20212K9661999-09-30030 September 1999 Forwards Safety Evaluation Accepting plant-specific Safety Evaluation Rept for USI A-46 Program Implementation at Cooper Nuclear Station ML20216J1081999-09-28028 September 1999 Ltr Contract:Task Order 048, Cooper Safety Sys Design & Performance Capability Insp, Under Contract NRC-03-98-021 ML20212J5061999-09-27027 September 1999 Forwards Insp Rept 50-298/99-07 on 990718-0828.No Violations Noted.Inspectors Focused on Implementation of Licensee Reactor Safety & Emergency Preparedness Programs ML20212F3641999-09-22022 September 1999 Forwards Insp Rept 50-298/99-09 on 990823-26.No Violations Noted ML20212A6061999-09-14014 September 1999 Forwards Insp Rept 50-298/99-08 on 9900816-20.No Violations Noted.Insp Focused on Implementation & Effective Performance of Access Authorization/Fitness-for-Duty (Behavior Observation) Program & Access Control of Personnel ML20211F4661999-08-23023 August 1999 Discusses GL 98-01 Issued by NRC on 980511 & NPPD Responses for Cooper Nuclear Station & 990628 & Results of Visit to Plant on 990811-12.Staff Determined That Integrated Contigency Plan Incomplete & CNS Not Y2K Ready ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210P6861999-08-0909 August 1999 Forwards Insp Rept 50-298/99-06 on 990530-0717.No Violations Noted.During Insp,Inspectors Identified Two Issues Categorized as Being Low Risk Significance & within Licensee Response Band ML20210N1331999-08-0606 August 1999 Forwards Notice of Withdrawal of Application for Amend to FOL DPR-46.By Ltr Licensee Withdrew Amend Request Which Would Have Revised Usfar to Reflect as-built Configuration of Reactor Bldg Isolation Dampers ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210D2541999-07-21021 July 1999 Forwards Insp Rept 50-298/99-02 on 990628-0702.Purpose of Insp Was Primarily to Evaluate Effectiveness of Licensed Operator Requalification Program.No Violations Were Identified ML20210C2041999-07-20020 July 1999 Discusses 990715 Mgt Meeting with Midamerican Energy Co Re risk-informed Baseline Insp Program Recently Implemented at Cooper & Fort Calhoun Stations ML20209H8191999-07-15015 July 1999 Forwards Safety Evaluation on GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Cooper Nuclear Station ML20209E6951999-07-12012 July 1999 Discusses Response to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. Recommends Review of New Database Diskettes on Listed Website.Comments Due by 990901 or Data Entered Into Rvid for Plant Will Be Acceptable ML20209D8731999-07-0808 July 1999 Refers to 990707 Meeting Re Licensee Recent Maintenance Program self-assessment.Also Discussed How Licensee Incorporated Assessment Findings Into Rev of Maintenance Performance Improvement Plan.List of Attendees Encl ML20196J2471999-06-29029 June 1999 Discusses Completion of Licensing Action for GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps, ML20196F7511999-06-24024 June 1999 Discusses 990622 Meeting with Public at Arbor Manor, Alburn,Ne to Provide Overview of Pilot Insp Program ML20196E1411999-06-16016 June 1999 Forwards Insp Rept 50-298/99-05 on 990502-29.Noncited Violations Identified ML20195F6171999-06-0909 June 1999 Informs That GE Rept, Matl Presented by GE 970709 Meeting at Cooper Nuclear Power Station Re Replacement of ECCS Pump Suction Strainers Between Nppd,Ge & NRC Staff, Will Be Withheld from Public Disclosure as Requested ML20207G3031999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Cooper Nuclear Station EP Implementing Procedure EPIP 5.7.1, Emergency Classification,Rev 24,under 10CFR50,App E,Section V Provisions.No Violations Identified ML20207G4481999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Cooper Nuclear Station EP Implementing Procedure,Epip 5.7.1, Emergency Classification,Rev 23 C2,under Provisions of 10CFR50,App E,Section V ML20207G4531999-06-0707 June 1999 Ack Receipt of Which Transmitted Changes to Cooper Nuclear Station EP Implementing Procedure EPIP 5.7.1, Emergency Classification,Revision 25,under Provisions of 10CFR50,App E,Section V ML20207G3001999-06-0707 June 1999 Ack Receipt of Which Transmitted Changes to Cooper Nuclear Station Ep,Rev 33,under Provisions of 10CFR50,App E,Section V.No NRC Approval Required Based on Determination That EP Effectiveness Not Affected by Changes ML20207D3811999-05-27027 May 1999 Informs That During Next 6 to 12 Months,Starting 990530,NRC Plans to Conduct Insps Shown in Attached Insp Plan.Insps Include Both Planned Baseline & Supplemental Insps (Formerly Core & Regional Initiative Insps) ML20207A5191999-05-19019 May 1999 Forwards Insp Rept 50-298/99-04 on 990321-0501.Four Violations Identified & Being Treated as non-cited Violations ML20206Q6171999-05-17017 May 1999 Forwards RAI Re 990301 & 10 Ltrs Re Proposed TS Changes to Calibr Frequency of Recirculation Flow Transmitters from Once Every 184 Days to Once Every 18 Months.Util Responses Should Be Provided within 30 Days of Ltr Date ML20206P0171999-05-12012 May 1999 Discusses GL 96-05 Issued on 960918 & NPPD Responses Submitted on 961118,970317,980504 & 990222 for Cooper Nuclear Station.Forwards Safety Evaluation Concluding That NPPD Adequately Addressed Actions Requested in GL 96-05 IR 05000298/19980091999-05-12012 May 1999 Refers to Insp Rept 50-298/98-09 Conducted Between 981227-990130.During Insp,Apparent Violation of 10CFR50.50 Identified & Being Treated as non-cited ML20206M1791999-05-11011 May 1999 Informs That NRC Ofc of NRR Reorganized Effective 990328. Reorganization Chart Encl ML20206H4191999-05-0707 May 1999 Informs That on 990407,NRC Administered Gfes of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However,Copy of Master Exam with Answer Key,Encl for Info.Without Encl ML20206P8961999-05-0707 May 1999 Refers to Meeting Conducted at Region IV Office on 990506 Re Licensee Upcoming Rev to Strategy for Achieving Engineering Excellence & Plans to Achieve Performance Improvements.List of Attendees & Util Presentation,Encl ML20206H7541999-05-0505 May 1999 Forwards Insp Rept 50-298/99-01 on 990207-0320.Violations Being Treated as non-cited Violations ML20205R5541999-04-16016 April 1999 Submits Summary of 990330 Public Meeting in Brownville,Ne to Discuss Results of PPR Completed on 990211,which Allowed for Exchange on New Assessment Process,Current Performance Review & Upcoming Actions Taken in Response to Y2K Concerns IR 05000298/19980221999-03-19019 March 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-298/98-22 on 990107.Finds Reply Responsive to Concerns Raised in NOV ML20205E8991999-03-19019 March 1999 Advises of Completion of Plant Performance Review on 990209 to Develop Integrated Understanding of Safety Performance. Overall Performance Was Acceptable.Problems with Communication in CR Resulted in Several Minor Events ML20204D9451999-03-18018 March 1999 Forwards Insp Rept 50-298/98-09 on 981227-990206.Three Violations Identified & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy ML20207M9591999-03-15015 March 1999 Forwards Request for Addl Info Re Licensee Response to GL 95-07, Pressure-Locking & Thermal-Binding of Safety-Related Power-Operated Gate Valves, for Cooper Nuclear Station ML20204B6771999-03-15015 March 1999 Submits Withdrawal of Amend Request for Operating License DPR-46.Proposed Change Would Have Modified Facility TSs Pertaining to Neutron Monitoring Neutron Detectors ML20207M9811999-03-15015 March 1999 Advises That Which Withdrew 980415 Amend Request, Being Treated as Withdrawal.Proposed Change Would Have Modified Facility TSs Pertaining to Neutron Monitoring,Flow Biased Rod Block Monitor ML20204B3301999-03-11011 March 1999 Forwards SE Accepting Third 10-year Interval Inservice Insp Program Plan Requests for Relief Numbers RI-13,RI-17 & RI-25 for Plant ML20204B7061999-03-11011 March 1999 Requests Approval of Proposed Operability Criteria for Use in Evaluation & Interim Resolution of Degraded & Nonconforming Conditions with Piping & Pipe Supports at Facility ML20205A5811999-03-0909 March 1999 Forwards Exam Rept 50-298/99-301 for Exam Administered on 990212.Exam Included Evaluation of Four Applicants for Reactor Operator License ML20207K3231999-03-0808 March 1999 Discusses 990224 Meeting Re Staff Critique of Refueling & Equipment Outage RE-18 & Implementation Status of Improvement Strategy for Engineering.List of Attendees & Matl Used in Presentation Encl ML20202G1701999-02-0202 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam at Util Facility on 990407.Authorized Representative from Facility Must Submit Ltr Listing Names of Candidates ML20202E3121999-01-22022 January 1999 Forwards Insp Rept 50-298/98-08 on 981115-1226 & Notice of Violation.First Violation Re Staff Failure to Follow Procedures (Two in Operations,One in Maint & One in Plant Support) ML20199G6041999-01-19019 January 1999 Informs That Effective 990118,JN Donohew Has Assumed NRC Project Mgt Responsibility for Cooper Nuclear Station ML20199E1521999-01-0707 January 1999 Forwards Insp Rept 50-298/98-22 on 981116-1208 & Notice of Violation Re Lack of Effective Oversight by Plant Mgt 1999-09-30
[Table view] |
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= E UNITED STATES I
5 ! NUCLEAR REGULATORY COMMISSION l
k f
/ WASHtNGTON, D.C. 20555-0001 SEP 2 31993 Scientech, Inc.
ATTN: James Meyer, Project Manager 11821 Parklawn Drive Rockville, MD 20852
Dear Mr. Meyer:
Subject:
Contract No. NRC-04-91-068 Task Order No.19 Entitled,
" Individual Plant Examination (IPE) Reviews, Internal Events, ,
Back End Only" (Cooper)
. In accordance with Section G.5, Task Order Procedures, of the subject contract, this letter definitizes Task Order No.19. This effort shall be performed in accordance with the enclosed Statement of Work.
Task Order No.19 shall be in effect from September 30, 1993 through September 29, 1994 with a total cost ceiling of $18,390.31. The amount of
$16,805.00 represents the total estimated reimbursable costs and the amount of
$1,585.31 represents the fixed fee.
The obligated amount of this task order is $18,390.31.
Accounting Data for Task Order No. 19 is as follows:
APPN No.: 31X0200.360 B&R No.: 36019202300 JOB CODE: L1933 BOC No.: 2542 Obligated Amount: $18,390.31 RES Identifier: RES-C93-118 The following individuals are considered to be essential to the successful performance for work hereunder: James Meyer and Henry Amarasooriya.
The Contractor agrees.that such personnel shall not bc removed from the effort under the task order without compliance with Contract Clause H.1, Kel Personnel.
The issuance of this task order does not amend any terms or conditions of the subject contract.
Your contacts during the course of this task order are:
Technical Matters: John Flack, Project Officer (301) 492-3979 Contractual Matters: Paulette Smith, Contract Administrator (301) 492-7670 I
9311010258 930923 PDR CONTR NRC-04-91-068 PDR y (
NRC-04-91-068 Please indicate your acceptance of this Task Order No. 19 by having an official, authorized to bind your organization, execute three copies of this document in the space provided and return two copies to the above Contract Administrator. You should retain the third copy for your records.
As we rapidly approaching September 30, our fiscal year ending date, you should expedite the execution of and return of this document. Unless the signed documents are returned to me prior to that date, I cannot assure you of the continued availability of these funds. You also also requested to FAX a copy of the signed document as soon as possible to ensure that the NRC has adequate time to record this obligation of funds. The facsimile number is (301) 492-4994.
If you have any questions regarding the modification, please contact Paulette.
Smith, Contract Administrator, on (301) 492-7670.
Sincerely,
, db
. Fields, Contracting Officer Contract Administration Branch No.-3 Division of Contracts and Property Management.
Office of Administration
Enclosure:
Statement of Work ACCEPTED: ' -
J > ,
/l/
NAME[arshall J. T Manager BashkIh OLLLce TITLE September 27, 1993 DATE f
l .
Contract NRC-04-91-068 Scientech STATEMENT OF WORK Task Order - 19 TITLE: Individual Plant Examination (IPE) Reviews, Internal Events Back-End Only (Cooper)
DOCKET NUMBER: 50-298 NRC PROJECT MANAGER: John H. Flack, RES (301-492-3979)
' HRC TEAM LEADER FOR COOPER: John H. Flack, RES (301-492-3979)
TECHNICAL MONITOR: John H. Flack, RES (301-492-3979)
PERIOD OF PERFORMANCE: September 30, 1993 through September 29, 1994 l
BACKGROUND:
On November 23, 1988, the NRC issued Generic Letter 88-20, " Individual Plant i 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 l core damage and radioactive material releases; and (4) reduce the overall i 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 8 . 1 l
Generic Letter 88-20.
OBJECTIVE:
The purpose of this contract is to solicit contractor support in order to '
enhance the NRC review of licensees' IPE submittals. This contract includes the examination and evaluation of the Cooper IPE submittal, specifically with regard to the "back-end" analysis. The contractor review will be of limited scope and consist of a " submittal only" review and the licensee's response to questions raised by the staff. The " submittal only" review and gathering of ;
associated insights will help the NRC. staff determine whether the licensee's i IPE process met the intent of Generic Letter 88-20, or whether a more detailed review is warranted.
By identifying the IPE's strengths and weaknesses, extracting important insights and findings, and providing a comparison to staff reviewed and accepted PSAs (e.g. NUREG-1150, PSAs identified in NUREG-1335 Appendix B), it 1
~, . ,
~"
- r. ;
.'. I is expected that the NRC will be in a better position to expeditiously i evaluate the licensee's IPE process. To provide support under this contract, ;
the contractor will search for obvious errors, omissions and inconsistencies in the IPE submittal and the licensee's response to a " Request for Additional 1 Information," (RAI) as described in the work requirements listed below.
WORK RE0UIREMENTS AND SCHEDULE:
The contractor will perform a " submittal only" review of the Cooper "back-end" IPE analysis. [The review is to include only the Level II analysis. Review .
of Level III (consequence analysis) is beyond the scope.of this contract.] 1 The contractor shall provide the qualified specialists and the necessary 3 facilities,. materials, and services to carry out such a review. The
- contractor will utilize NRC review guidance documcnts for detail and . . .,
reference, as well as other interim guidance provided by the NRC Technical Monitor. The contractor is not expected to make a plant / site visit in order to perform this review.
Subtask 1. Review and Identification of IPE Insichts Perform a back-end " submittal only" review of each IPE submittal and identify important IPE insights by completing the NRC IPE Data Summary Sheets. .During .
the review, focus on the areas described below under " Work Requirement." Thel l contractor will note any: (1) inconsistencies between methodology employed in the IPE submittals and other PSA studies, and (2) inconsistencies between the .
submittal's IPE findings and findings stemming-from other.PSAs '(See NUREG-- a ~
1335, Appendix B). Respond explicitly to each work requirement by noting.
important review findings including any IPE strengths and weaknesses.
Appropriately characterize any shortcomings with respect to the impact on IPE conclusions. Identify and provide a justification for a Request for ,
Additional Information (RAI).
Word Reouirement 1.1. Perform a General Review of the Licensee's IPE' 4 Back-End Analytic Process ;
Check the following:
1.1.1 The IPE submittal is essentially complete with respect to the level of detail requested in NUREG-1335. ;
1.1.2 IPE employed methodology is clearly described and justified for selection. Approach is consistent with Generic Letter 88-20 ,
Appendix 1.
1.1.3 The IPE employed a viable process to confirm that the containment and containment systems represent-the as-built, as-operated plant.- ,
1.1.4 IPE back-end had been appropriately peer-reviewed to help assure the analytic techniques were correctly applied.
1 2 j l
l 1
Work Reouirement 1.2. Review of the Containment Analysis / Characterization Check the following:
1.2.1 The IPE analysis appropriately treated front-end and back-end dependencies, i.e., plant damage states considered reactor system / containment system availability, system mission times, inventory depletion, dual usage (spray vs. injection).
1.2.2 Classes of sequences with significant probability (those that meet the G.L. 88-20/NUREG-1335 screening criteria) were evaluated further using simplistic, but realistic, containment event trees.
1.2.3 The focus of the IPE's containment analysis was on failure modes and timing. Containment failure modes are consistent with those identified in Table 2.2 of NUREG-1335.
1.2.4 The IPE process assessed and identified contributors to containment isolation failure.
1.2.5 System / human response were integrated with the phenomenological aspects of accident progression into the containment event trees.
Allowances for recovery actions were made to allow for accident management actions.
1.2.6 The IPE submittal appropriately documented radionuclide release characterization for accident sequences exceeding the Generic Letter 88-20 (or NUREG-1335) screening criteria.
~
Work Reouirement').3. Review the Ouantitative Nature of the Accident Prooression and Containment Performance Analysis Check the following: -
1.3.1 The licensee employed a reasonable process to understand and quantify severe accident progression. The process lead to a determination of important conditional containment failure probabilities, and considered phenomenological uncertainties, either qualitative or quantitative. .
1.3.2 Dominant contributors to containment failure are consistent with insights from other PSAs of similar design.
1.3.3 The IPE appropriately characterized containment performance for each of the CET end-states.by assessing containment loading (either calculated or referenced).
1.3.4 Tha containment analysis considered the impact of severe accident ei.<ironments on equipment behavior.
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Work Reauirement 1.4. Review the IPE Anoroach to Reducina the Probability of Core Damaae or Fission Product Release Check the following:
1.4.1 The IPE analysis appears to support the licensee's definition of vulnerability, and that the definition provides a means by which the identification of potential vulnerabilities (as so defined) and plant modifications (or safety enhancements) is made-possible.
1.4.2 The identification of plant improvements and proposed modifications are reasonably expected to enhance plant safety.
Work Reauirement 1.5. Review Licensee's Response to Containment Performance Improvement Recommendations Check that the licensee appropriately responded to recommendations stemming from the Containment Performance Improvement (CPI) Program, i.e., that the licensee's assessment, findings, conclusions and actions (as appropriate) considered the following as a function of containment type:
BWRs (MARK I,II,III) o Harden vent o Alternative water supply for drywell spray / vessel injection o Enhanced reactor pressure vessel depressurization system reliability o Implementation of Revision 4 of the BWR Owners Group EPGs o Improved hydrogen igniter power supply (Mark III)
Additional for BWR (MARK III) o Evaluation of vulnerability to interrupted power supply td -
hydrogen igniters and need for improvement ,
PWR Ice Condenser Containments o Evaluation of vulnerability to interrupted power supply to hydrogen igniters and need for improvement PWR Dry Containments o Evaluation of containment and equipment vulnerabilities to hydrogen combustion (local and global) and need for improvement.. This would include consideration of gaseous pathways between the cavity and the upper containment volume to confirm adequate communication to promote natural circulation and recombination of combustible gases in the reactor cavity.
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Work Reouirement 2.0. Comolete Data Sheets A. Summarize data on the Consolidated Data Summary Sheet as described (
below.
CONSOLIDATED DATA
SUMMARY
SHEET fINTERNAL EVENTS) o Conditional containment failure probability given core damage:
o Significant PRA findings:
o Enhanced plant hardware (implemented after 1988 PRA) containment modifications:
o Potential containment improvements under consideration and not modeled:
B. Complete the NRC data summary sheets and note any lack of information, as appropriate. However, exclude those data entries marked "BNL Data Entry." These data will be collected by Brookhaven National Laboratory under a separate contract.
Subtask 2. Prepare Preliminary Technical Evaluation ReDort Prepare a preliminary Technical Evaluation Report with the outline prescribed bel ow.
I. Executive Summary Provide a brief overview of the IPE review, the scope and depth as appropriate. Place emphasis on review areas identified as being im)ortant and rationale for importance, i.e., found to be important in otler PSAs of similar design. Discuss any important or unique plant characteristics. Note plants with similar features and any important ' .
insights stemming from other relevant PSA studies.
II. Contractor Review Findings Explicitly address each work requirement element listed above under Subtask 1, " Review and Identification of IPE Insights." Discuss any ,
strength or weakness so identified and significance with respect to the overall IPE effort. Identify any additional information (in the form of questions back to the licensee) which would be important to the review effort. List these questions separately in an appendix. Indicate why the information is important for closure.
III. Overall Evaluation and Conclusion Summarize the " submittal only" review conclusions based on the information submitted and significance of IPE strengths and weaknesses. l 5
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IV. IPE Insights, Improvements, and Commitments Characterize important IPE findings and insights, including any significant containment characteristics or analytic assumptions that impact insights. Describe and characterize any significant enhancements implemented by the licensee, specifically in response to important insights which stem from the IPE process. Identify any licensee commitments and characterize the need to track commitments based on the impact on IPE conclusions. Also identify and characterize any potential improvements not forthcoming but perceived to be significant.
V. IPE Evaluation and Data Summary Sheets Attach: (a) Consolidated Data Summary Sheets using the above outline, and (b) the NRC IPE data sheets.
Appendix: Questions and Comments Provide all questions and comments which are to be discussed with the licensee. Provide rationale for comments, especially when seeking additional ,
information.
Subtask 3. PreDare Final Technical Evaluation Report Review the licensee's response to staff questions and comments. Update the preliminary TER developed under Subtask 2, as appropriate, based on the additional information received from the licensee. Emphasis should be placed on review areas identified under Subtask 2. Provide rationale as appropriate to support the need for any additional follow-on studies or recommendations.
Note: The contractor should be prepared to participate in telephone l communications with the licensee and/or discussions with NRC review team members regarding the licensee's responses to questions and issues l stemming from the preliminary TER. * .
REPORT REQUIREMENTS:
l Technical Reports The contractor will submit to the NRC Technical Monitor four copies of'the Preliminary Technical Evaluation Report (TER) six weeks after the initiation of this contract. Copies will include three hard copies and one 3.5" computer diskette version (Wordperfect 5.1 or other IBM PC compatible software acceptable to the NRC IPE Team Leader). The Preliminary TER shall summarize all findings, results, and conclusions in the areas examined in the format I described under Subtask 2. If the contractor finds that the licensee's IPE is obviously deficient in any of the areas examined, the Technical Monitor should be notified in advance. Deficient or weak areas should be clearly documented in the Technical Evaluation Report. In addition, if the contractor finds that there are specific areas that need additional in-depth review, the Team Leader 6
l should be notified of the areas, and provided with the rationale for subsequent review.
'J The contractor will submit to the NRC Technical Monitor three copies of the !
Final Technical Evaluation Report (TER) two weeks af_ter the receipt of.the licensee's response to staff questions and comments. Copies will include two hard copies and one 3.5" computer diskette version (Wordperfect 5.1 or other IBM PC compatible software acceptable to the NRC IPE Team Leader). The Final TER shall update all findings, results, and conclusions in the areas examined in the format described under Subtask 2 as appropriate.
BUSINESS LETTER REPORT: ,
The contractor shall provide monthly progress reports in accordance with the requirements of the basic contract.
MEETINGS AND TRAVQ:
One, one person trip to NRC Headquarters to present and discuss review findings and conclusions.
ESTIMATED LEVEL OF EFFORT:
For each IPE reviewed:
Subtask 1 80 contractor hours Subtask 2 80 contractor hours Subtask 3 16 contractor hours It shall be the responsibility of the contractor to assign technical staff, employees, and subcontractors who have the required educational background, . ,
experience, or combination thereof, to meet both the technical and regulatory objectives of the work specified in this S0W. 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 conflict of interest , disclosures, is accurate and truthful.
NRC FURNISHED MATERIAL:
- 1. Licensee's IPE submittal.
- 2. Licensee's response to staff generated questions and associated information.
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TECHNICAL DIRECTION:
The NRC Project Manager is:
John H. Flack 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 t
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