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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M3371999-10-20020 October 1999 Forwards Notice of Docketing of License SNM-2506 Amend Application.Notice Has Been Forwarded to Ofc of Fr for Publication ML20217M1111999-10-19019 October 1999 Forwards Insp Repts 50-282/99-14 & 50-306/99-14 on 990920- 22.One Violation Noted & Being Treated as Ncv.Insp Focused on Testing & Maint of Heat Exchangers in High Risk Sys ML20217F4331999-10-15015 October 1999 Forwards Rev 39 to Security Plan.Changes Do Not Decrease Effectiveness of Security Plan.Rev Withheld,Per 10CFR73.21 ML20217C2351999-10-0606 October 1999 Forwards Insp Repts 50-282/99-12 & 50-306/99-12 on 990823-0917.No Violations Noted.Insp Consisted of Selected Exam of Procedures & Representative Records,Observation of Activities & Interviews with Personnel ML20212J8811999-09-28028 September 1999 Forwards Preliminary Accident Sequence Precurson Analysis of Operational Event That Occurred at Plant,Unit 1 on 990105, for Review & Comment.Comment Requested within 30 Days of Receipt of Ltr IR 05000272/19990071999-09-28028 September 1999 Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified ML20212G7171999-09-24024 September 1999 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Its.Conversion Package Submittal Continues to Be Targeted for Aug of 2000 ML20212G9801999-09-23023 September 1999 Refers to Resolution of Unresolved Items Identified Re Security Alarm Station Operations at Both Monitcello & Prairie Island ML20212F5121999-09-20020 September 1999 Forwards Response to NRC , Preparation & Scheduling of Operator Licensing Examinations ML20212D8401999-09-16016 September 1999 Discusses 990902 Telcon Between D Wesphal & R Bailey Re Administeration of Retake Exam at Prairie Island During Wk of 991206.NRC May Make Exam Validation Visit to Facility During Wk of 991116 ML20217H2331999-09-10010 September 1999 Forwards Security Insp Repts 50-282/99-10 & 50-306/99-10 on 990809-12.Two Findings,Each of Low Risk Significance Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217H5661999-09-0909 September 1999 Discusses 990907 Pilot Plan Mgt Meeting Re Results to-date of Pilot Implementation of NRC Revised Reactor Oversight Process at Prairie Island & Quad Cities.Agenda & Handouts Provided by Utils Encl ML20212A9241999-09-0909 September 1999 Discusses Plans Made During 990902 Telephone Conversation to Inspect Licensed Operator Requalification Program at Prairie Island During Weeks of 991101 & 991108.Requests That Written Exams & Operating Tests Be Submitted by 991022 ML20212B0511999-09-0909 September 1999 Forwards Insp Repts 50-282/99-11 & 50-306/99-11 on 990816-20.One Issue of Low Safety Significance Was Identified & Being Treated as Ncb ML20211Q7641999-09-0808 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant Operator License Applicants During Wk of 000515,in Response to D Westphal ML20211N8631999-09-0707 September 1999 Withdraws 970814 Request for Exemption from 10CFR50,App R, Section III.G.2, Fire Protection of Safe Shutdown Capabilities ML20211K5911999-09-0101 September 1999 Informs That Util Reviewed Rvid Data Base,As Requested in NRC .Summary of Proposed Changes & Observed Differences Are Included in Encl Tables ML20211L0211999-09-0101 September 1999 Provides Notification That License Amends 141 & 132 & Associated License Conditions 6 & 7 Have Been Fully Implemented ML20211K5931999-08-31031 August 1999 Forwards License Amend Request for License SNM-2506, Proposing Change to License Conditions 6,7 & 8 & TSs App a of License by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks ML20211Q6041999-08-31031 August 1999 Forwards Rev 19 to USAR for Pingp,Per 10CFR50.71(e).Rev Brings USAR up-to-date as of 990228,though Some Info Is More Recent.Attachment 1 Contains Descriptions & Summaries of SE for Changes,Tests & Experiments,Per 10CFR50.59 ML20211K2591999-08-27027 August 1999 Forwards NSP Co Fitness for Duty Program Performance Data for Six Month Period Ending 990630 ML20211D3541999-08-24024 August 1999 Discusses GL 95-07 Re Pressure Locking & Thermal Binding of safety-related Power Operated Gate Valves.Forwards SE Re Response to GL 95-07 ML20211C7601999-08-19019 August 1999 Confirms NRC Intent to Meet with NSP & Ceco on 990807 in Lisle,Il to Discuss with Region III Pilot Plants,Any Observations,Feedback,Lessons Learned & Recommendations Relative to Implementation of Pilot Program ML20211B8311999-08-19019 August 1999 Forwards Request for Relief 8 Re Limited Exams Associated with Unit 1 Third ten-year Interval Inservice Insp Program. Licensee Requests Relief Due to Impractibility of Obtaining 100% Exam Coverage for Affected Items ML20211B5711999-08-19019 August 1999 Forwards Second 90-day Rept for Implementation of Voltage Based Repair Criteria at Prairie Island Unit 1.Rept Fulfills Requirements of Section 6.b of Attachment 1 to GL 95-05 ML20211C2311999-08-19019 August 1999 Forwards Unit 1 ISI Summary Rept,Interval 3,Period 2 Refueling Outage Dates 990425-0526,Cycle 19 971212-990526. Rept Identifies Components Examined,Exam Methods Used,Exam Number & Summarizes Results ML20211B0561999-08-18018 August 1999 Provides Addl Info on Proposed Rev to Main Steam Line Break Methodology ,in Response to NRC Staff Request Made in 990416 Telcon.Nuclear Svcs Corp Rept PIO-01-06, Analysis Rept Structural Analyses of Main Steam Check... Encl ML20211B2621999-08-17017 August 1999 Forwards Insp Repts 50-282/99-09 & 50-306/99-09 on 990719-22.No Violations Noted.Insp Included Review & Evaluation of Current Emergency Preparedness Performance Indicators ML20211C7371999-08-17017 August 1999 Discusses Closure of Staff Review Re Generic Implication of Part Length Control Rod Drive Mechanism Housing Leak on 980123.Enclosed NRC 980811 & 1223 Ltrs Responded to WOG Positions Re Corrective Actions ML20210T5661999-08-12012 August 1999 Forwards RAI Re & Suppl ,which Requested Exemptions from TSs of Section III.G.2 of 10CFR50 App R,To Extent That Specifies Separation of Certain Redundant Safe Shutdown Circuits with fire-related Barriers ML20210R7021999-08-12012 August 1999 Forwards Insp Repts 50-282/99-06 & 50-306/99-06 on 990601- 0720.One NCV Occurred,Consistent with App C of Enforcement Policy ML20210P5191999-08-11011 August 1999 Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950519 & NSP Responses for PINGP & 951117. Staff Reviewed Info in Rvid & Released Info as Rvid Version 2.Requests Submittal of Comments Re Revised Rvid by 990901 ML20210G5061999-07-30030 July 1999 Responds to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates 05000282/LER-1999-007, Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics1999-07-23023 July 1999 Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics ML20210J4991999-07-22022 July 1999 Forwards Rev 18 to USAR for Pingp,Bringing USAR up-to-date as of 990228,though Some Info More Recent.Safety Evaluation Summaries Also Encl ML20209J0941999-07-15015 July 1999 Forwards SER Finding Rev 7 to Topical Rept NSPNAD-8102, Reload Safety Evaluation Methods for Application to PI Units, Acceptable for Ref in Plant Licensing Actions ML20209H8051999-07-14014 July 1999 Forwards Summary of non-modification Safety Evaluation Number 515 Re Storage of Fuel Inserts,Per Insp Rept 72-0010/99-201 ML20209D4181999-07-0707 July 1999 Informs That Util Has Changed Listed TS Bases Pages Attached for NRC Use.Util Made No New Commitments in Ltr ML20209H8361999-07-0202 July 1999 Forwards Operator Licensing Exam Repts 50-282/99-301(OL) & 50-306/99-301(OL) for Tests Administered During Week of 990517-21.Two Applicants Passed All Sections of Exam & Issued Reactor Operator Licenses to Operate Pings ML20196J9681999-07-0101 July 1999 Informs That in Sept 1998,Region III Received Rev 20 to Portions of Util Emergency Plan Under 10CFR50.54(q).Based on Determination That Changes Do Not Decrease Effectiveness of Licensee Emergency Plan,No NRC Approval Required ML20209C3951999-07-0101 July 1999 Forwards Supplemental Response to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20209B7541999-07-0101 July 1999 Final Response to GL 98-01,Suppl 1 Re Y2K Readiness of Computer Sys.Sys Remediated as Required for Plant Operation. Contingency Plans Developed to Mitigate Impact of Y2K-induced Events at Key Rollover Dates ML20196J8941999-06-30030 June 1999 Transmits Util Comments on Draft Regulatory Guide DG-1074, Steam Generator Tube Integrity. Licensee Recommends That NRC Focus on Several Important Listed Areas Considered Principal Concerns & Contentions ML20209F0391999-06-30030 June 1999 Forwards Insp Repts 50-282/99-04 & 50-306/99-04 on 990407-0531.Violation Noted.Notice of Violation or Civil Penalty Will Not Be Issued,Based on NRC Listed Decision to Exercise Discretion ML20209C3011999-06-29029 June 1999 Forwards Annual Rept of Corrections to NSP ECCS Evaluation Models,Iaw 10CFR50.46.Since All Analyses Remain in Compliance,No Reanalysis Is Required or Planned ML20209B5751999-06-24024 June 1999 Submits Revised Relief Request for Limited Examinations Associated with Third 10-yr ISI Examination Plan.Attached Is Unit 1 Relief Request 7,rev 1 Which Addresses Limited Examinations ML20196F3871999-06-23023 June 1999 Forwards Revised Pages 71,72 & 298 of Rev 7 to NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units, Per Discussions with Nrc.Approved Version of Rept Will Be Issued 05000282/LER-1999-006, Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics1999-06-18018 June 1999 Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics ML20196D5501999-06-18018 June 1999 Forwards Individual Exam Results for Licensee Applicants Who Took May 1999 Initial License Exam.In Accordance with 10CFR2.790,info Considered, Proprietary. Without Encls ML20196A6741999-06-17017 June 1999 Refers to 990517-20 Meeting with Util in Welch,Minnesota Re Licensee Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee PRA Staff 1999-09-09
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M3371999-10-20020 October 1999 Forwards Notice of Docketing of License SNM-2506 Amend Application.Notice Has Been Forwarded to Ofc of Fr for Publication ML20217M1111999-10-19019 October 1999 Forwards Insp Repts 50-282/99-14 & 50-306/99-14 on 990920- 22.One Violation Noted & Being Treated as Ncv.Insp Focused on Testing & Maint of Heat Exchangers in High Risk Sys ML20217C2351999-10-0606 October 1999 Forwards Insp Repts 50-282/99-12 & 50-306/99-12 on 990823-0917.No Violations Noted.Insp Consisted of Selected Exam of Procedures & Representative Records,Observation of Activities & Interviews with Personnel IR 05000272/19990071999-09-28028 September 1999 Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified ML20212J8811999-09-28028 September 1999 Forwards Preliminary Accident Sequence Precurson Analysis of Operational Event That Occurred at Plant,Unit 1 on 990105, for Review & Comment.Comment Requested within 30 Days of Receipt of Ltr ML20212G9801999-09-23023 September 1999 Refers to Resolution of Unresolved Items Identified Re Security Alarm Station Operations at Both Monitcello & Prairie Island ML20212D8401999-09-16016 September 1999 Discusses 990902 Telcon Between D Wesphal & R Bailey Re Administeration of Retake Exam at Prairie Island During Wk of 991206.NRC May Make Exam Validation Visit to Facility During Wk of 991116 ML20217H2331999-09-10010 September 1999 Forwards Security Insp Repts 50-282/99-10 & 50-306/99-10 on 990809-12.Two Findings,Each of Low Risk Significance Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20212B0511999-09-0909 September 1999 Forwards Insp Repts 50-282/99-11 & 50-306/99-11 on 990816-20.One Issue of Low Safety Significance Was Identified & Being Treated as Ncb ML20217H5661999-09-0909 September 1999 Discusses 990907 Pilot Plan Mgt Meeting Re Results to-date of Pilot Implementation of NRC Revised Reactor Oversight Process at Prairie Island & Quad Cities.Agenda & Handouts Provided by Utils Encl ML20212A9241999-09-0909 September 1999 Discusses Plans Made During 990902 Telephone Conversation to Inspect Licensed Operator Requalification Program at Prairie Island During Weeks of 991101 & 991108.Requests That Written Exams & Operating Tests Be Submitted by 991022 ML20211Q7641999-09-0808 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant Operator License Applicants During Wk of 000515,in Response to D Westphal ML20211D3541999-08-24024 August 1999 Discusses GL 95-07 Re Pressure Locking & Thermal Binding of safety-related Power Operated Gate Valves.Forwards SE Re Response to GL 95-07 ML20211C7601999-08-19019 August 1999 Confirms NRC Intent to Meet with NSP & Ceco on 990807 in Lisle,Il to Discuss with Region III Pilot Plants,Any Observations,Feedback,Lessons Learned & Recommendations Relative to Implementation of Pilot Program ML20211B2621999-08-17017 August 1999 Forwards Insp Repts 50-282/99-09 & 50-306/99-09 on 990719-22.No Violations Noted.Insp Included Review & Evaluation of Current Emergency Preparedness Performance Indicators ML20211C7371999-08-17017 August 1999 Discusses Closure of Staff Review Re Generic Implication of Part Length Control Rod Drive Mechanism Housing Leak on 980123.Enclosed NRC 980811 & 1223 Ltrs Responded to WOG Positions Re Corrective Actions ML20210T5661999-08-12012 August 1999 Forwards RAI Re & Suppl ,which Requested Exemptions from TSs of Section III.G.2 of 10CFR50 App R,To Extent That Specifies Separation of Certain Redundant Safe Shutdown Circuits with fire-related Barriers ML20210R7021999-08-12012 August 1999 Forwards Insp Repts 50-282/99-06 & 50-306/99-06 on 990601- 0720.One NCV Occurred,Consistent with App C of Enforcement Policy ML20210P5191999-08-11011 August 1999 Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950519 & NSP Responses for PINGP & 951117. Staff Reviewed Info in Rvid & Released Info as Rvid Version 2.Requests Submittal of Comments Re Revised Rvid by 990901 ML20209J0941999-07-15015 July 1999 Forwards SER Finding Rev 7 to Topical Rept NSPNAD-8102, Reload Safety Evaluation Methods for Application to PI Units, Acceptable for Ref in Plant Licensing Actions ML20209H8361999-07-0202 July 1999 Forwards Operator Licensing Exam Repts 50-282/99-301(OL) & 50-306/99-301(OL) for Tests Administered During Week of 990517-21.Two Applicants Passed All Sections of Exam & Issued Reactor Operator Licenses to Operate Pings ML20196J9681999-07-0101 July 1999 Informs That in Sept 1998,Region III Received Rev 20 to Portions of Util Emergency Plan Under 10CFR50.54(q).Based on Determination That Changes Do Not Decrease Effectiveness of Licensee Emergency Plan,No NRC Approval Required ML20209F0391999-06-30030 June 1999 Forwards Insp Repts 50-282/99-04 & 50-306/99-04 on 990407-0531.Violation Noted.Notice of Violation or Civil Penalty Will Not Be Issued,Based on NRC Listed Decision to Exercise Discretion ML20196D5501999-06-18018 June 1999 Forwards Individual Exam Results for Licensee Applicants Who Took May 1999 Initial License Exam.In Accordance with 10CFR2.790,info Considered, Proprietary. Without Encls ML20196A6741999-06-17017 June 1999 Refers to 990517-20 Meeting with Util in Welch,Minnesota Re Licensee Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee PRA Staff ML20207B5841999-05-26026 May 1999 Forwards SER Concluding That Licensee 990412 Proposed Alternative to ASME Code for Surface Exam of Seal Welds on Threaded Caps for Reactor Vessel Head Penetrations for part-length CRDMs Will Provide Acceptable Quality & Safety ML20207D0641999-05-26026 May 1999 Informs of Plans to Conduct Meeting on 990614 in Red Wing,Mn,To Present Planned Changes to NRC Regulatory Processes & Pilot Plant Program for Prairie Island Nuclear Generating Station ML20207B7941999-05-25025 May 1999 Forwards Insp Repts 50-282/99-05 & 50-306/99-05 on 990426- 30.No Violations Noted.Overall Plant Radiological Controls Effective in Maintaining Reasonable Collective Dose for Work Being Conducted During Unit 1 Refueling Outage ML20207B3281999-05-24024 May 1999 Informs That in May 1999,Region III Received Rev 20 to Portions of Prairie Island Nuclear Generating Center Emergency Plan.Rev Submitted Under Provisions of 10CFR50.54(q) ML20207A1491999-05-20020 May 1999 Forwards Request for Addl Info Re Areas of Seismic,Fire,High Winds,Floods & Other External Events for IPEEE Submittals for PINGP Dtd Dec 1996,March 1998 & Dec 1998 ML20206S0891999-05-13013 May 1999 Informs That on 990505 NRC Staff Held Planning Meeting for Plant to Identify Insp Activities at Facility Over Next 6 to 12 Months ML20206N4581999-05-13013 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Management Created. Reorganization Chart Encl ML20206J2101999-05-0404 May 1999 Forwards Insp Repts 50-282/99-02 & 50-306/99-02 on 990226-0406.No Violations Noted.During Insp Period,Sf Casks 08 & 09 Successfully Loaded & Cask 08 Transported & Placed in ISFSI ML20206E1801999-04-29029 April 1999 Forwards Insp Rept 72-0010/99-01 on 990308-0413.No Violations Noted.Purpose of Insp Was to Observe Various Portions of Dry Fuel Cask Loading Program ML20205R4841999-04-16016 April 1999 Forwards Security Insp Repts 50-282/99-03 & 50-306/99-03 on 990322-26.No Violations Noted.Objective of Insp Effort Was to Determine Whether Activities Authorized by License Were Conducted Safely & IAW NRC Requirements ML20205R1791999-03-30030 March 1999 Responds to Issue Re Generic Implication of part-length Control Rod Drive Mechanism Housing Leak at Praire Island, Unit 2 & Beaver Valley Power Station,Units 1 & 2 IR 05000282/19980161999-03-30030 March 1999 Discusses Fpfi Repts 50-282/98-16 & 50-306/98-16 on 980810-28.Determined That Violations Occurred Involving MOVs Being Unable to Satisfy post-fire Safe Shutdown Function & Spurious Actuation of Sys Due to Fire Damage ML20205B5781999-03-26026 March 1999 Advises That NSPNAD-8102-P,rev 7, Prairie Island NPP Reload Safety Evaluation Methods for Application to PI Units Submitted in 990129 Application Will Be Withheld from Public Disclosure ML20205G9321999-03-26026 March 1999 Informs of Planned Insp Effort Resulting from Prairie Island Plant Performance Review for Period 980328-990131.Historical Listing of Plant Issues & Details of NRC Insp Plan for Next 6 Months Encl ML20205C0671999-03-26026 March 1999 Informs That Exhibit E (CEN-629-P,Rev 03-P, Repair of W Series 44 & 51 Steam Generator Tubes Using Leak Tight Sleeves Will Be Withheld from Public Disclosure,Per Util 990205 Application & C-E Affidavit,Per 10CFR2.7990 ML20205B5161999-03-26026 March 1999 Discusses Util Re Rept of Corrections to Licensee ECCS Evaluation Models.Attachments 1 & 2 from Were Withheld from Public Disclosure Due to Proprietary Markings from W.Attachments 1 & 2 Will Now Be Placed in PDR ML20204E4651999-03-18018 March 1999 Forwards Insp Repts 50-282/99-01 & 50-306/99-01 on 990115-0225.No Violations Noted ML20207E0401999-03-0404 March 1999 Forwards Request for Addl Info Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves, Program at Prairie Island Nuclear Generating Plant ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20206U1831999-02-0909 February 1999 Responds to Encl Ltrs, & 1223 Re Generic Implication of part-length CRDM Housing Leak.Review Under TAC Numbers MA1380 & MA1381 Considered Closed ML20202G2101999-01-29029 January 1999 Forwards Insp Repts 50-282/98-23 & 50-306/98-23 on 981204- 990114.No Violations Noted.Insp Characterized by Several Unexpected Operational Events,Caused by Equipment Failure, Personnel Errors & Procedure Problems 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 ML20202J1421999-01-22022 January 1999 Informs of Completion of Review of NSP Which Proposed Alternative to Surface Exam Requirements of Paragraph N-518.4 of 1968 ASME BPV Code for CRD Mechanism Canopy Seal Welds.Forwards SE Supporting Alternative ML20199F8471999-01-14014 January 1999 Forwards FEMA Evaluation Rept for 980721-22 Emergency Preparedness Exercise at Prairie Island Nuclear Generating Station ML20206U2101998-12-23023 December 1998 Provides Staff Response to Re WCAP-15126, Technical Assessment of Part Length CRDM Housing Motor Tube Cracking in WOG Plants.Nrc Agrees That Incremental Core Damage Frequency for Range of Defects Might Be 10.6 Per Ry 1999-09-09
[Table view] |
See also: IR 05000282/1997008
Text
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July 16, 1997
EA 97-290
Mr. M. D. Wadley
Vice President, Nuclear Generation
Northern States Power Company
414 Nicollet Mall
- Minneapolis, MN 55401
SUBJECT: NRC INSPECTION REPORT 50-282/97008(DRS); 50-306/97008(DRS)
AND NOTICE OF VIOLATION
1
Dear Mr. Wadley:
l
l
On June 13,1997, the NRC completed a System Operational Performance Inspection
(SOPI) at your Prairie Island Nuclear Generating Plant. The inspection team assessed the
auxiliary feedwater (AFW), and portions of the control room ventilation and safeguards
chilled water systems' operational performance by a detailed review of the design,
maintenance, operation, and surveillance testing of the systems. The enclosed report
presents the results of that inspection.
The inspectors identified that, with exceptions, maintenance and operations were being )
well performed and that your engineering staff was considered knowledgeable end
conscientious. However, the results of the SOPl raised concerns about the rigor of i
certain aspects of engineering, particularly with verification of the design basis l
performance of safety-related pumps through an effective surveillance program. Concern .
was also raised by observations that your Updated Safety Analysis Report (USAR) was not !
being maintained current. Additional concern was generated because corrective actions
for prior identification of these issues were not timely. The existing controls appeared to j
have failed to identify potentially degraded equipment (AFW Pumps) or to prompt
.
'
appropriate corrective actions.
. Based on the results of this inspection, apparent violations were identified and are being
considered for escalated enforcement action in accordance with the " General Statement of
Policy and Procedure for NRC Enforcement Actions" (Enforcement Policy), NUREG-1600.
The apparent violations include failure of your test controls to incorporate test criteria
necessary to assure verification that AFW pumps could meet design requirements.- In
addition, apparent violations of corrective actions were noted by your failure to complete
actions identified in 1991 that may likely have identified the AFW pump test criteria
problem, as well as failure to take timely corrective action on inaccurate AFW flowrates in
the USAR. Apparent violations of 10 CFR 50.71, " Maintenance of records, making of
reports," and of 10 CFR 50.9, " Completeness and accuracy of information," were also
_
g
identified for failure to correct the inaccurate USAR AFW flowrate. Further, apparent
violations of 10 CFR 50.72, "Immediate Notification Requirements for Operating 'l
Reactors," 10 CFR 50.73, " Licensee Event Report System," and 10 CFR 50.59, " Changes,
Tests and Experiments," were identified for failure to report that the plant was outside its
"
9707220135 970716
PDR ADOCK 05000282
PDR
ll lll l l
g
u. -. - _ _
e
4
K
-
M. D. Wadley 2 July 16, 1997
,
design basis when it was determined that the main feedwater line rupture analysis used a
higher AFW flow value than the pumps could deliver, and for your subsequent failure to
verify via a safety evaluation that no unreviewed safety question existed. It is of particular
concern that your staff had various opportunities to maintain the USAR current with
respect to this issue during 1993 and 1995, but this did not occur.
Accordingly, no Notice of Violation is presently being issued for these inspection findings.
In addition, please be advised that the number and characterization of apparent violations
described in the enclosed inspection report may change as a result of further NRC review.
A predecisional enforcement conference to discuss these apparent violations has been
scheduled for August 1,1997. This conference will be open to public observation. The
decision to hoU a predecisional enforcement conference does not mean that the NRC has
v 4termined that a violation has occurred or that enforcement action will be taken. This
e anference is being held to obtain information to enable the NRC to make an enforcement
decision, such as a common understanding of the facts, root causes, missed opportunities
to identify the apparent violation sooner, corrective actions, significance of the issues and
the need for lasting and effective corrective action, in particular, we expect you to
address the continued operability of the systems we reviewed and any other affected
systems and, the failures of your corrective action process.
In addition, this is an opportunity for you to point out any errors in our inspection report
and for you to provide any information concerning your perspectives on (1) the severity of
the violation (s), (2) the application of the factors that the NRC considers when it
determines the amount of a civil penalty that may be assessed in accordance with
Section VI.B.2 of the Enforcement Policy, and (3) any other application of the Enforcement
Policy to this case, including the exercise of discretion in accordance with Section Vll.
You will be advised by separate correspondence of the results of our deliberations on this
matter. No response regarding the(se) apparent violation (s) is required at this time.
In addition, the NRC has determined that violations of NRC requirements occurred. These
violations are cited in the enclosed Notice of Violation (Notice) and the circumstances
surrounding them are described in detailin the subject inspection report. The violations
are of concern because they represent a lack of rigor and controlin the calculation
verification program and, for the cable tray separation issue, represent another example of
untimely and non-comprehensive corrective action for earlier-identified design issues.
You are required to respond to this letter and should follow the instructions specified in the
enclosed Notice when preparing your response. The NRC will use your response, in part,
to determine whether further enforcement action is necessary to ensure compliance with
regulatory requirements. Additionally, please be prepared to discuss the design control
violation during the pre-decisional enforcement conference, including the reason for the
violation (or basis for disputing it), and corrective action taken or planned to avoid similar !
l
design control issues.
4
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e l
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M. D. Wadley 3 July 16, 1997
I
Finally, you are also requested to respond in writing on any planned actions, including timo
frames, for re-performing the control room habitability dose calculations and any plans to !
test the control room isolation dampers for verification of the inteakage assumption as
discussed in Section E1.4 of this report. This issue was of concern to the NRC because
l
, the existing analysis demonstrated a low margin to the thyroid dose limit and the effects '
of higher than assumed unfiltered inleakage could place the plant outside of the regulatory
limit.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, j
its enclosures, and your response will be placed in the NRC Public Document Room (PDR). l
Sincerely,
/s/ J. M. Jacobson (for)
John A. Grobe, Acting Director
Division of Reactor Safety
- Docket Nos. 50-282;50-306;72-10
Licenses No. DPR-42; DPR460
, Enclosures: 1. Notice of Violation !
! 2. Inspection Report 50-282/97008(DRS); 50-306/97008(DRS)
cc w!encis: Plant Manager, Prairie Island !
John W. Ferman, Ph.D., i
Nuclear Engineer, MPCA
State Liaison Officer, State !
of Minnesota
State Liaison Officer, State i
of Wisconsin
Tribal Council, Prairie Island
Dakota Community
Distribution:
/encls SRis, Prairie Island, TSS w/encls
Docket File w%/encls
PMBLIC.lE-01 Monticello w/encls CAA1 w/encls
OC/LFDCB w/encls LPM, NRR w/encls DOCDESK w/encls !
DRP w/encls A. B. Beach, Rlli w/encls J. Lieberman, OE w/encls
DRS w/encls J. L. Caldwell, Rlll w/encls J. Goldberg, OGC w/encls
Rlli PRR w/encls Rlli Enf. Coordinator w/encls R. Zimmerman, NRR w/encls
SEE ATTACHED CONCURRENCES
DOCUMENT NAME: G:\DRS\PRA97008.DRS
To receive a copy of thle document, Indicate in the box: "C" = Copy w/o attachment / enclosure "E" = Copy with attachment /enclostk "N" o copy
OFFICE Rill:DRS l Rill:DRS ,lE Rlll:DRP l Rlll:EICS l R$)lgjiirf \ l
NAME Guzman/lc/jp/kjc Rin N Mc-Barger Clayton JAobyn7()tobe
DATE 07/ /97 07//'//97 07/ /97 07/ /97 q7/g/R7/
OFFICIAL RECORD COPY U
m ._. -
,_ . .. _ __ _ _ .. _ _
,
.
%
M. D. Wadley 3
.
'
Finally, you are also requested to respond in writing on any planned actions, including time
frames, for re-performing the control room habitability dose calculations and any plans to
-
test the control room isolation dampers for verification of the inleakage assumption as
discussed in Section E1.4 of this report. This issue was of concern to the NRC because
the existing analysis demonstrated a low margin to the thyroid dose limit and the effects
of higher than assumed unfiltered infeakage could place the plant outside of the regulatory
limit.
I
in accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, i
its enclosures, and your response will be placed in the NRC Public Document Room (PDR). I
1
Sincerely,
l
\
,
l
l John A. Grobe, Acting Director i
Division of Roactor Safety l
Docket Nos. 50-282;50-306;72-10
Licenses No. DPR-42; DPR-60
j Enclosures: 1. Notice of Violation
2. Inspection Reports 50-282/97008(DRS); 50-306/97008(DRS)
. cc w/encis: Plant Manager, Prairie Island
John W. Ferman, Ph.D.,
Nuclear Engineer, MPCA
'
State Liaison Officer, State
of Minnesota
State Liaison Officer, State
- of Wisconsin
Tribal Council, Prairie Island
,
Dakota Community
I-
!
$ DOCUMENT NAME: G:\DRS\PRA97008.DRS
To receive a copy of this document, indicate in the box: "C" = Copy without
attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy
OFFICE Rlli 6 Rill Rlll pr Rlli Rlli
'
NAME uzyn MRing BClayt l JGrobe
pM g~ /./an:Ic/jp JMcCorm{ck-
BargerM hQ (1, l'V
DATE b O7/3/97 07/ /97 07/J /97 t7/cy/97 07/ /97
OFFICIAL RECORD COPYgat U$ pprul a
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