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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210L1061999-08-0202 August 1999 Forwards Insp Rept 50-010/99-13 on 990702-27.No Violations Noted.Insp Examined Activities in Areas of Facility Management & Control & Radiological Safety ML20210D2961999-07-20020 July 1999 Forwards Corrected Info for DNPS Unit 3 MOR for June 1999. Year-to Date Forced Outage Hours Should Have Read 70 Hours Instead of 0 on Page 8.Error Also Affected Cumulative Forced Outage Hours Which Should Have Been 24,761 ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20196K3231999-06-30030 June 1999 Informs That Effective 990703,NRC Project Management Responsibility for Dresden,Unit 1 Station Will Be Transferred to P Ray ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes ML20196D3491999-06-18018 June 1999 Forwards Insp Repts 50-237/99-08 & 50-249/99-08 on 990408-0521.Four Non-Cited Violations Noted.Maint on safety- Related Emergency CR Not Performed Well.Low Impact Issues Re Communications Present in Operations,Maint & Security ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20195E3451999-06-0707 June 1999 Forwards 3.5 Inch Computer Diskette Containing Revised File Format for Annual Dose Rept for 1998,per 990520 Telcon Request from Nrc.Each Station Data Is Preceded by Header Record,Which Provides Info Necessary to Identify Data ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20207G2571999-06-0303 June 1999 Informs That Effective 990328,NRC Ofc of NRR Underwent Reorganization.Within Framework of Reorganization,Division of Licensing Project Management Created ML20195B2301999-05-19019 May 1999 Requests Approval of Proposed Changes to QA Topical Rept CE-1-A,rev 66a.Attachment a Describes Changes,Reason for Change & Basis for Concluding That Revised QAP Incorporating Proposed Changes Continues to Satisfy 10CFR50AppB ML20206Q3111999-05-18018 May 1999 Final Response to FOIA Request for Documents.Forwards App a Records Being Released in Entirety ML20206P2431999-05-13013 May 1999 Forwards Insp Rept 50-010/99-09 on 990325-0506.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20206F5381999-04-30030 April 1999 Forwards Magnetic Tape Containing Annual Dose Repts for 1998 for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR20.2206(c).Without Magnetic Tape ML20206B1501999-04-22022 April 1999 Forwards 1998 Occupational Radiation Exposure for Dresden Nuclear Power Station,Units 1,2 & 3. Rept Was Revised to Rept Only Individual Radiation Exposures Greater than 100 Mrem ML20206B2471999-04-20020 April 1999 Informs That SE Kuczynski Has Been Transferred to Position No Longer Requiring SRO License.Cancel License SOP-31030-1, Effective 990412 ML20205K5521999-04-0202 April 1999 Forwards Partially Withheld Security Insp Repts 50-010/99-07,50-237/99-07 & 50-249/99-07 on 990308-12.Two non-cited Violations Identified Involving Failure of Security Personnel to Implement Required Measures ML20205K5841999-03-31031 March 1999 Submits Rept on Status of Decommissioning Funding for Reactors Owned by Comm Ed.Attachment 1 Contains Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) ML20196K7001999-03-31031 March 1999 Forwards Dresden Nuclear Power Station,Units 1,2 & 3 Radioactive Effluent Release Rept,Jan-Dec 1998. ODCM Was Submitted by Ltr in Accordance with Dresden TS 6.9.A.4 of Dresden Tech Specs Section 6.14.A.3 ML20205D7231999-03-26026 March 1999 Informs That Region III Emergency Preparedness Inspector Will Be Provided Copy of Comed Exercise Manual for 990526 Annual Exercise at DNPS ML20205B4241999-03-23023 March 1999 Provides Results of drive-in Drill Conducted on 990208,as Well as Augmentation Phone Drills Conducted Since 981015,as Committed to in Util ML20207L7141999-03-0808 March 1999 Discusses Transmitting Changes Identified as Rev 59 to Security Plan for Dresden Nuclear Power Station,Units 1,2 & 3.Staff Determined That No NRC Approval Required in Accordance with 10CFR50.54(p) ML20207D6831999-03-0101 March 1999 Forwards fitness-for-duty Program Performance Data for Each Comed Nuclear Power Station & Corporate Support Employees for Six Month Period Ending 981231,per 10CFR26.71(d) ML20207E0931999-02-26026 February 1999 Informs That Region III EP Inspectors Will Be Provided One Copy of Exercise Evaluation Objectives for 990526 Annual Exercise at Dresden Station as Enclosure to Ltr for Review. Proprietary Encl Withheld ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20203G3631999-02-10010 February 1999 Forwards Insp Rept 50-010/99-02 on 981218-990129.No Violations Noted.During Insp,Activities in Area of Facility Mgt & Control,Decommissioning Support Activities & Radiological Safety Were Examined ML20203C7001999-02-0202 February 1999 Informs That Mhb Technical Associates No Longer Wishes to Receive Us Region III Docket Info Re Comed Nuclear Facilities.Please Remove Following Listing from Service List ML20202G0621999-01-25025 January 1999 Forwards 1998 Revs to Commitments Rept Made in Docketed Correspondence for Dresden Nuclear Power Station ML20199F3291999-01-14014 January 1999 Ack Receipt of Ltr Dtd 981230,transmitting Changes Identified as Rev 59 to Plant Security Plan,Submitted Under Provisions of 10CFR50.54(p) ML20199E0201999-01-12012 January 1999 Forwards Change to Bases of Dnps,Unit 1 TS Section 3.10, Fuel Handling & Storage. Change Eliminates Reference to Initiation of Generating Station EP Action That Is Incorrect & Not Part of Reason for Min FSP Water Level TS ML20199C8851999-01-11011 January 1999 Forwards Monthly Operating Repts for Dec 1998 for Dnps,Units 1,2 & 3,as Required by TS 6.9.A.5.Year-to-date Generator Hours for Unit 2 for Oct 1998 & Nov 1998 Corrected in Rept ML20206P7411999-01-0707 January 1999 Informs of Delay in Implementation of Strategic Reform Initiative Action Steps.Util Mgt Now Preceeding to Implement Succession Planning Steps for Corporate Ofc & Expects Completion of Action Steps 2 & 3 by 990128 ML20198N7691998-12-30030 December 1998 Forwards Rev 59 to Security Plan for Dresden Nuclear Power Station,In Accordance with 10CFR50.4(b)(4).Rev Withheld ML20198A2531998-12-10010 December 1998 Ack Receipt of Which Transmitted Changes Identified as Rev 57 to Plant Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20198A2511998-12-10010 December 1998 Ack Receipt of ,Which Transmitted Changes Identified as Rev 58 to Plant Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20196E2371998-11-27027 November 1998 Discusses Licensee ,Requesting That Agreement in Be Changed to Reflect Latest NRC Conditions Requiring Licensees to Notify NRC of Transfer of Assets to Affiliates Imposed in Connection with Approval of Transfer ML20196B5871998-11-20020 November 1998 Requests That Svc List for All NRC Correspondence Re Any of Six Comed Nuclear Stations Be Modified Per Attached List.All Other Names Previously Listed Should Be Removed ML20196A4121998-11-19019 November 1998 Forwards Safety Evaluation Accepting Proposed Changes to QA TR CE-1-A,Rev 66,by ,As Modified by Ltrs & 1027.Proposed QA Tr,Rev 66 Continues to Comply with Criteria of 10CFR50,App B ML20195J4271998-11-13013 November 1998 Forwards Insp Repts 50-010/98-18,50-237/98-27 & 50-249/98-27 on 981013-16 & Notice of Violation.Mgt Activities Were Focused Toward Maintaining Effective Security Program ML20195E6451998-11-12012 November 1998 Provides Results of drive-in Drill Conducted on 981007,as Well as Augmentation Phone Drill Conducted on 980917 ML20195F3461998-11-10010 November 1998 Forwards Rev 58 of DNPS Security Plan,Including Listed Changes,Iaw 10CFR50.4(b)(4).Encl Withheld Ref 10CFR73.21 ML20155D2701998-10-27027 October 1998 Forwards Changed Pages from 980423 Submittal Providing Addl Info Marked with Revision Bars & Revised Pages to QA Topical Rept Section 18,for Review ML20154P9051998-10-20020 October 1998 Ack Receipt of 980821 Submittal,Per 10CFR50.54(a),requesting Review & Approval of Proposed Changes That Reduce Commitments in QA TR,CE-1-A.Util Should Refrain from Implementing Subj Changes Until Formal Notification Given 1999-09-30
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20210L1061999-08-0202 August 1999 Forwards Insp Rept 50-010/99-13 on 990702-27.No Violations Noted.Insp Examined Activities in Areas of Facility Management & Control & Radiological Safety ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) ML20196K3231999-06-30030 June 1999 Informs That Effective 990703,NRC Project Management Responsibility for Dresden,Unit 1 Station Will Be Transferred to P Ray ML20196D3491999-06-18018 June 1999 Forwards Insp Repts 50-237/99-08 & 50-249/99-08 on 990408-0521.Four Non-Cited Violations Noted.Maint on safety- Related Emergency CR Not Performed Well.Low Impact Issues Re Communications Present in Operations,Maint & Security ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20207G2571999-06-0303 June 1999 Informs That Effective 990328,NRC Ofc of NRR Underwent Reorganization.Within Framework of Reorganization,Division of Licensing Project Management Created ML20206Q3111999-05-18018 May 1999 Final Response to FOIA Request for Documents.Forwards App a Records Being Released in Entirety ML20206P2431999-05-13013 May 1999 Forwards Insp Rept 50-010/99-09 on 990325-0506.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20205K5521999-04-0202 April 1999 Forwards Partially Withheld Security Insp Repts 50-010/99-07,50-237/99-07 & 50-249/99-07 on 990308-12.Two non-cited Violations Identified Involving Failure of Security Personnel to Implement Required Measures ML20207L7141999-03-0808 March 1999 Discusses Transmitting Changes Identified as Rev 59 to Security Plan for Dresden Nuclear Power Station,Units 1,2 & 3.Staff Determined That No NRC Approval Required in Accordance with 10CFR50.54(p) ML20203G3631999-02-10010 February 1999 Forwards Insp Rept 50-010/99-02 on 981218-990129.No Violations Noted.During Insp,Activities in Area of Facility Mgt & Control,Decommissioning Support Activities & Radiological Safety Were Examined ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20199F3291999-01-14014 January 1999 Ack Receipt of Ltr Dtd 981230,transmitting Changes Identified as Rev 59 to Plant Security Plan,Submitted Under Provisions of 10CFR50.54(p) ML20198A2531998-12-10010 December 1998 Ack Receipt of Which Transmitted Changes Identified as Rev 57 to Plant Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20198A2511998-12-10010 December 1998 Ack Receipt of ,Which Transmitted Changes Identified as Rev 58 to Plant Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20196E2371998-11-27027 November 1998 Discusses Licensee ,Requesting That Agreement in Be Changed to Reflect Latest NRC Conditions Requiring Licensees to Notify NRC of Transfer of Assets to Affiliates Imposed in Connection with Approval of Transfer ML20196A4121998-11-19019 November 1998 Forwards Safety Evaluation Accepting Proposed Changes to QA TR CE-1-A,Rev 66,by ,As Modified by Ltrs & 1027.Proposed QA Tr,Rev 66 Continues to Comply with Criteria of 10CFR50,App B ML20195J4271998-11-13013 November 1998 Forwards Insp Repts 50-010/98-18,50-237/98-27 & 50-249/98-27 on 981013-16 & Notice of Violation.Mgt Activities Were Focused Toward Maintaining Effective Security Program ML20154P9051998-10-20020 October 1998 Ack Receipt of 980821 Submittal,Per 10CFR50.54(a),requesting Review & Approval of Proposed Changes That Reduce Commitments in QA TR,CE-1-A.Util Should Refrain from Implementing Subj Changes Until Formal Notification Given ML20154F6291998-10-0606 October 1998 Forwards Insp Rept 50-010/98-16 on 980723-0918.No Violations Noted.During Period Covered by Insp,Activities in Areas of Facility Mgt & Control,Spent Fuel Safety & Radiological Safety Examined ML20154B6761998-10-0101 October 1998 Informs That NRC Reviewed Comm Ed Submittals & Finds,Util Has Adequately Addressed Actions in GL 95-07,as Discussed in Encl SE ML20153C4941998-09-21021 September 1998 Forwards SER Accepting Qualified Unit 1 Supervisor Initial & Continuing Training Program for Dresden Nuclear Power Station IR 05000010/19980151998-08-13013 August 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-010/98-15, 50-237/98-18 & 50-249/98-18 Issued on 980629.Corrective Actions Will Be Examined During Future Insps ML20237B1321998-08-11011 August 1998 Forwards Corrected Copy of NOV Re Insp Repts 50-010/98-15, 50-237/98-18 & 50-249/98-18 Conducted on 980601-04.Notice Did Not Contain Safeguards Info.Administrative Error Resulted in Document Being Marked as Safeguards Info ML20236P9451998-07-15015 July 1998 Forwards Emergency Response Data Sys Implementation Documents Including Data Point Library Updates for Oconee (Number 255),Dresden (Number 257) & Susquehanna (Number 258) ML20236L1151998-07-0606 July 1998 Forwards Insp Rept 50-010/98-13 on 980319-0630.No Violations Noted.Activities in Area of Facility Mgt & Control,Sf Safety & Radiological Safety Were Examined ML20236F1471998-06-29029 June 1998 Forwards Insp Repts 50-010/98-15,50-237/98-18 & 50-249/98-18 on 980601-0604.Areas Examined within Security Program Were Identified ML20236G9961998-06-26026 June 1998 Forwards Insp Repts 50-237/98-14 & 50-249/98-14 on 980403- 0527.No Violations Noted.Unavailability of HPCI Sys Continued to Be Problem at Dresden During Insp Period ML20249C3121998-06-23023 June 1998 Inorms That Proposed Revision 66 to QA Topical Rept,CE-1-A, Not Acceptable.Requests That Licensee Refrain from Implementing Changes Until Formally Notified ML20248B9431998-05-27027 May 1998 Discusses 980520 Public Meeting Re Dresden Unit 1 Decommissioning Activities & Dry Cask Storage Project. Meeting Handouts Encl ML20247E3061998-05-0808 May 1998 Confirms Discussion W/B Snell Re Agreement to Have Meeting on 980520 at Plant,Training Bldg to Discuss Unit 1 Status & Plans,Problem Identification & Prevention & Dry Cask Storage Status IR 05000010/19980081998-05-0101 May 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-010/98-08, 50-237/98-08 & 50-249/98-08.Corrective Actions Will Be Examined During Future Insps ML20216G6311998-04-0909 April 1998 Summarizes 980312 Meeting Conducted at Region III Ofc in Lisle,Il,To Discuss Util Performance Re Action That Util Taken in Response to NRC 10CFR50.54(f) Ltr, Re Safety Performance at Facilities.List of Attendees Encl ML20217J2131998-04-0202 April 1998 Forwards Copy of Each Revised Forms 398,personal Qualifications Statement & 396,certification of Medical Exam by Facility Licensee.Due to Error on Instructions for Form 398,addendum for Completing Form Are Provided ML20217E8191998-03-26026 March 1998 Discusses Review of Dec 1997,rev 7K to Generating Stations Emergency Plan,Submitted Under Provisions 10CFR50.54(q).NRC Approval Not Required,Changes Do Not Decrease Effectiveness of Plan ML20217D5951998-03-25025 March 1998 Forwards Insp Repts 50-010/98-08,50-237/98-08 & 50-249/98-08 Conducted Between 980302 & 11.Areas within Security Program Were Examined.Nov & Insp Details Being Withheld ML20248L7911998-03-18018 March 1998 Forwards Insp Rept 50-010/98-02 on 971215-980226 & Nov.Rp Program Exhibited Number of Weaknesses.Program Declined Through Most of 1997 Until Control Informal,Personnel Not Well Informed or Disciplined & Mgt Involvement Lacking ML20216B8321998-03-0606 March 1998 Forwards Decommissioning Insp Plan for Remainder of FY98 for Plant,Unit 1,for Info.Plan Will Be Updated Approx Twice Each Yr & May Be Revised at Any Time Based on Future Insp Findings,Events & Resource Availability ML20203H9651998-02-26026 February 1998 Confirms Discussion to Have Meeting on 980312 in Lisle,Il to Discuss Comed Nuclear Operating Division Performance as Relates to Actions Comed Taken in Response to NRC Ltr ,re Safety Performance at Comed Nuclear Facilities ML20203B1651998-02-0909 February 1998 Informs That Effective 980209 R Burrows Has Been Assigned as Project Manager for Plant,Unit 1 ML20202H1701998-02-0909 February 1998 Discusses 980114 Meeting W/Listed Attendees in Lisle,Il to Discuss Commonwealth Edison Co Performance Re Actions Util Has Taken in Response to NRC 970127,10CFR50.54(f) Ltr Concerning Safety Performance at Util Facilities IR 05000010/19970241998-02-0303 February 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-010/97-24, 50-237/97-24 & 50-249/97-24.Actions Will Be Examined During Future Insp ML20202C7821998-02-0303 February 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-010/97-19, 50-237/97-19 & 50-249/97-19.Corrective Actions Will Be Examined During Future Insp ML20198T4491998-01-20020 January 1998 Advises of Planned Insp Effort Resulting from Dresden Plant Performance Review.Details of Insp Plan for Next 6 Months Encl ML20198N7181998-01-15015 January 1998 Discusses Conversation Between I Johnson & J Gavula Re Cancellation of Planned Routine Mgt Meeting on 980122 in Lisle,Il ML20197H8761997-12-23023 December 1997 Forwards Insp Repts 50-010/97-26,50-237/97-26 & 50-249/97-26 on 971029 & 1106.No Violations Noted.Noncited Violation Re Failure to Implement FFD Provisions Contained in Plant Procedure Was Identified ML20197G5641997-12-19019 December 1997 Ask Receipt of Ltr Dated 971002,which Transmitted Changes Identified as Rev 56 to Dresden Nuclear Station Security Plan,Submitted Under Provisions of 10CFR50.54(p).Changes Do Not Decrease Overall Effectiveness of Plan ML20197E9681997-12-19019 December 1997 Forwards Insp Repts 50-010/97-24,50-237/97-24 & 50-249/97-24 on 971016-1122 & Notice of Violation ML20203J6481997-12-16016 December 1997 Final Response to FOIA Request for Documents.Forwards Documents Listed in App A.Documents Will Be Available in PDR ML20203J8091997-12-15015 December 1997 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-010/97-20, 50-237/97-20 & 50-249/97-20 on 971030 1999-08-02
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l 8 E UNITED STATES l
5 i NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20S550001
,/
Scientech, Inc.
ATTN: James Meyer, Project Manager !
11821 Parklawn Drive l Rockville, MD 20852 l
Dear Mr. Meyer:
Subject:
Contract No. NRC-04-91-068, Task Order No. 20 Entitled,
" Individual Plant Examination (IPE) Reviews, Internal Events, Back End Only" (Dresden 2 & 3) l In accordance with Section G.5, Task Order Procedures, of the subject contrapt, this letter definitizes Task Order No. 20. This effort shall be performed in accordance with the enclosed Statement of Work.
Task Order No. 20 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. 20 is as follows:
APPN No.: 31X0200.360 B&R No.: 36019202300 JOB CODE: L1933 B0C No.: 2542 Obligated Amount: $18,390.31 RES Identifier: RES-C93-119 j 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 be removed from the effort ,
under the task order without compliance with Contract Clause H.1, Eey i 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 9311010256 930927 '
fY I PDR CONTR \,'
i NRC-04-91-068 PDR
3 i
NRC-04-91-068 l j
Please indicate your acceptance of this Task Order No. 20 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, ,
, h c Fields, Contracting Officer Contract Administration Branch No. 3 Division of Contracts and Property Management Office of Administration
Enclosure:
Statement of Work ACCEPTED: o .
N}
MarshallJ.Wv Manager, Rockville Office TITLE September 27, 1993 DATE t
Contract NRC-04-91-068 Scientech STATEMENT OF WORK Task Order - 20 TITLE: Individual Plant Examination (IPE) Reviews, Internal Events Back-End Only (Dresden Units 2 & 3)
DOCKET NUMBER: 50-237 NRC PROJECT MANAGER: John H. Flack, RES (301-492-3979)
NRC TEAM LEADER FOR DRESDEN UNITS 2 & 3 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 BACKGROUND:
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.
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 Dresden Units 2 & 3 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 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
is expected that the NRC will be in a better position to expeditiously 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 Additicnal Information," (RAI) as described in the work requirements listed below.
WORK RE0VIREMENTS AND SCHEDULE:
The contractor will perform a " submittal only" review of the Dresden Units 2 &
3 "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.) The contractor shall provide the qualified specialists and the necessary facilities, materials, and services to carry out such a review.
- The contractor will utilize NRC review guidance documents 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." The 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-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 -
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.
2
1 i
Work Reauirement 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.
The focus of the IPE's containment analysis was on failure modes 1.2.3 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, i 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 HUREG-1335) screening criteria. l Work Reauirement 1.3. Review the Ouantitative Nature of the Accident i Prooression and Containment Performance Analysis Check the following:
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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. _q I
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 The containment analysis considered the impact of severe accident environments on equipment behavior.
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l Work Reauirement 1.4. Review the IPE Acoroach to Reducino the Probability of Core Damaae or Fission Product l Release l
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 .
l 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 Recuirement 1.5, Review Licensee's Resoonse 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. ,
1 BWRs (MARK I,II,III) o Harden vent :
o Alternative water supply for drywell spray / vessel injection l 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 to' 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 Evaluation of containment and equipment vulnerabilities to i o J 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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Complete Data Sheets Work Reouirement 2.0.
A. Summarize data on the Consolidated Data Summary Sheet as described below.
CONSOLIDATED DATA
SUMMARY
SHEET (INTERNAL EVENTS) o Cruditional 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 Report Prepare a preliminary Technical Evaluation Report with the outline prescribed below.
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 important and rationale for importance, i.e., found to be important in other 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 I, " 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 toIndicate the review why effort. List these questions separately in an appendix.
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.
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1 IV. IPE Insights, Improvements, and Commitments Characterize important IPE findings and insights, including any ;
significant containment characteristics or analytic assumptions that l impact insights. Describe and characterize any significant enhancements i 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 characterizt 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 ,
l information.
Subtask 3. Prepare Final Technical Evaluation ReDort 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 communications with the licensee and/or discussions with NRC review team members regarding the licensee's responses to questions and issues ' -
stemming from the preliminary TER.
REPORT RE0VIRFHENTS:
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 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
V should be notified of the areas, and provided with the rationale for
The contractor will submit to the NRC Technical Monitor three copies of the Final Technical Evaluation Report (TER) two weeks after 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 The or other Final IBM PC compatible software acceptable to the NRC IPE Team Leader).
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.
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MEETINGS AND TRAVEL:
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, e 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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L 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
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