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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 05000282/1997012
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December 12, 199'/.
Mr.' M. D. Wadley
Vice President, Nuclear Generation
Northem States Power Company
414 Nicollet Mall
Minneapolis, MN ' 55401
SUBJECT: NOTICE OF VIOLATION (NRC INSPECTION
REPORT NO. 50-282/97012(DRS); 50 306/97012(DRS))
Dear Mr. Wadley:
- This will acknowledge receipt of your letter dated Nove.nber 13,1997, in response to
our letter dated October 14,1997, trarismitting a Notice of Violation associatad with inapection
Report No. 50-282/97012(DRS); 50-306/97012(DRS). We have reviewed your corrective
actions and have no further questions at this time. These corrective actions will be examined
during future inspections.
Sincerely, ,
Original Signed by J. Jacobson for
John A. Grobe, Director
Division of Reactor Safety
Docket No. 50-282
Docket No. 50-306
Enclosure: Ltr dtd 11/13/97, J. P. Sorensen, Northern
States Power to USNRC g
ec w/ encl: Plant Manager, Prairie Island I
State Liaison Officer, State
of Minnesota
State Liaison Officer, State
of Wisconsin
Tribal Council, Prairie Island
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Northern States Power Company
Prairie island Nuclear Generating Plant
1717 Wakontie Dr. East
Welch, Minnesota $5089
November 13,1997 10 CFR Part 2
U S Nuciear Regulatory Commission
Attn: Document Control Desk
Washington, DC 20555
PRAIRIE ISLAND NUCLEAR GENERATING PLANT
Docket Nos. 50-282 License Nos. DPR-42
50-306 DPR-60
Reply to Notice o' Violation (Inspection Report 97012),
Deficiencier in the Fire Protection Program _
Your letter of October 14,1997, which transmitted Inspection Report No. 97012,
required a response to a Notice of Violation. Our response to the notice is contained in
the attachment to this letter,
in addition, you requested responses to two Unresolved items. These responses
immediately follow.
URI 07012-01 Hot Shorts with Valve Damage:
As indicatedin the inspection report, we willperform additionalreviews of the hot
short problems following the completion of the safe shutdown analysis currently
being revised. After completion of the analysis a revised list of MOVs that are
susceptible to hot shorts will be developed and further reviews will be made for
these MOVs. Information Notice 92-18 willbe used for guidance in these
additionalreviews.
URI 97012-08 Fire Brigade Drill Requirements:
We am in the process of reviewing all of the commitments made relating to the
Fim Protection Program. After this review is completed the commitments will be
assessed against practices allowed by our administrative procedures and any
discmpancies between our fire brigade drill commitments and pmcedures will be
corrected.
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USNRC' NORTHERN STATES POWER COMPANY
November 13,1997
Page 2
In this letter and attached response we have made new Nuclear Regulatory
Commission commitments, these are indicated by italics,
Ples se contact Jack Leveille (612-388-1121, Ext. 4662) if you hate any questions
relateJ to this letter.
/
oel P Sorensen
Plant Manager
Prairie Island Nuclear Generating Plant
c: Regional Administrator- Region lil, N'RC
Senior Resident inspector, NRC
NRR Project Manager, NRC
J E Silberg
Attachment: RESPONSE TO NOTICE OF VIOLATION
i
1R97372. DOC
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RESPONSE TO NOTICE OF VIOLATION
VIOLATION 1
10 CFR 50.71(e) required that revised portions of the Fina; bafety Analysis Report
(FSAR) be submitted to the NRC.
Contrary to the above, on July 1,1994, substantial revisions were mad. to the Fire
Hazards Antlysis (FHA)(referenced as a portion of the FSAR) that were not submitted
to the NRC.
This is a Severity Level IV violation (Supplement 1).
Response to Violation 1
Reason for the ViolatiRD
Control & maintenance of the Fire Hazard Analysis (FHA)is outlined in several PINGP
site documents. The Prairie Island FHA is currently located in Operations manual
section F5 Appendix F. The USAR outlining the Fire Protection Program is located in
USAR section 10.3.1. Current practice for control and maintenance of the FHA and
USAR documents are outlined in SAWI 3.13.0," Fire Prevc..tative Practices," 5AW1
3.13.1 " Fire Protection Review of Plant Modifications," and SAWI 4.9.0 " Safety
Analysis Reports" as well as other site procedures which use processes to evalcate
and make required changes. The documents identified above use the FHA and USAR
in sepnte text and use separate processes for making changes to each.
Prict to this URC inspection, Prairie Island viewed the FHA as a separate document
than the USAR section.
Corrective Actions Taken:
During an unannounced fire protection inspection in March of 1994 the inspector
identified a violation relating to timely updates to the facilities FHA. Following the
issuance of this violation we completed a revision to the FHA that included
incorporation of all modifications completed since the previous revision where the FHA
was impacted. In addition, the facility developed an Administrative Work Instruction,
5AWI 3.13.1, " Fire Protection Review of Plant IV.odifications," that implemented
requirements for reviews of modifications that may impact the Fice Protection Program
for the facility. This Administrative Work Instruction has been in effect since the
inspection of 1994. Changes were made to the FHA as indicated in our response to
Violation 282/306/94004-1b dated May 2,1994. In this response we did not indicate
that we would or understood we were required to submit the updated FHA to the NRC
for review. NRC GL 86-10 requires all changes to the approved program be reported
annually to NRR along i.vith FSAR revisions. A major revision to the FHA could be
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i- considered u program change; however, all that was done was to updete the fire _ _
loading portion of the FHA and to_ identify the more conservative methodology used to .
complete this update.
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We are currently revising the Safe Shutdown Analysis which will require changes to the
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' FHA. - The revised FHA will be submitted during the first USAR update submittal of
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1998. .
Action to Be Taken to Prevent Recurrence '
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- A procedure change request was submitted for 5AWI 4.1.0, P! ant Operations and Site
Engineering Manuals to require that any changes made to the Fire Hazards Analysis be -
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submitted to the site Licensing Department for inclusion with the next USAR submittal
to the NRC.
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- '. Date When Full Comollance Will Be Achieved
The Prairie Island Fire Hazards Analysis will be submitted with the first USAR submittal
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of 1998.
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November 13,1997 l
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VIOLAT!ON 2.a
Prairie !sland hchnical Specification 6.5.A.7 required tilat detailed written
implementing prcadures be prepared and followed for the fire protection program,
a. Administrative Work !nstruction SAWI 3.13.0, " Fire Preventive Practices,"
Paragraph 6.9.6, stateo. " Individual Fire Brigade members SHALL actively
participate in at least one drii; per year."
Contrary to the above, during 1996, SAW13.13.0 was not followed in that 7
members of the fire brigade did not actively participate in fire brigade drills.
This is a Severity Level IV violation (Supplement 1).
Resoonse to Violation 2.a
Reason for the Violation
The reason for the violation was that we interpreted " active participation" to include
participation from the control room functions during a fire scenario. We are unaware of
the existence of clear NRC guidance on the meaning of" active participation."
Corrective Actions Taken
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Following the identification of this issue by the inspector we removed from Fire Brigade
duty those individuals that had not participated as a member of the fire brigade at the
scene of a drillin the past 12 months. In the following days, additional fire drills were
conducted and the individuals who had not previously participated in a fire drill at the
drill scene did participate as brigade members at the dr;ll scene. Following this
participation these individuals were rebrned to active Fire Brigade status, it should be
noted that these individuals had all participated in hands-on fire brigade training, during
the preceding 12 months, which includes full suit-up and full participation in fire fighting
scenarios.
Corrective Actions tq. Prevent Recurrence
We will change our administrative requirements to identify that ACTIVE participation in
a Fire Drill will require fire brigade members to respond to the location of the simulated
fire in fullprotective equipment and willinvolve participation in fire bdgade activities to
extinguish and prevent the spread of fires simulated for the drill. We will develop a
program to track this drillparticipation and fire brigade qualifications will require this
active participation in drills. The program willbe in place by March 1,1998.
Date When Full Comoliance Will Be Achieved
Full compliance has been achieved.
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Nov:mber 13,1997
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VIOLATION 2.b
Prairie Island Technical Specification 6.5.A.7 required that detailed written
implementing procedures be prepared and followed for the fire protection program.
b. Prairie Island Administrative Work Instruction SAW13.4.0,"QA Records Control,"
Revision 4, stated in paragraph 6.2.3: " Records that meet one or more of the
following criteria SHALL be classified as lifetime records: a. Would be of
significant value in demonstrating capability for safe operation of a safety related
or fire protection related item."
Contrary to the above, the December 12,1996, detector surveillance data
documented during fire protection surveillance SP 1189," Safety Related Fire
Detector Check," was not available for inspector review because it had been
discarded.
This is a Severity Level IV violation (Supplement 1).
Resoonse to Violation 2.b
Reason for the Violation
The inspection report states:
The inspector identified that detector surveillance data documented during SP
1189, " Safety Related Fire Detector Check," Revision 16, was not ava>able for
inspector review because it had been discarded. Only the cover sheets of
surveillances were saved. The licensee stated this was allowed by the licensee's
Administrative Work Instruction, SAW11.5.0, Revision 2, in Paragraph q.3.d.
It is true that we stated that the discarding of pages from the completed surveillance
procedure was allowed by Administrative Work Instruction 5AW11.5.0, which states that
pages of standing procedures may be discarded if several requirements are met,
including:
The discarded pages SHALL contain only routine, initiated steps and no data,
dates or signatures.
The discarded pages of SP-1189 contained only routine, initiated steps and did not
contain dates or signatures. We have questioned whether these routine, initiated steps
constitute " data" or provide " significant value in demonstrating capability for safe
operation of a safety related or fire protection related item." We have discovered that
we have an intemal disagreement regarding this question in general. However, in the
case of SP-1189, the procedure itself refers to the information in the table (the initials)
as test results. Test results must be maintained as quality records. Therefore, we
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November 13.1997
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acknowledge the violation but have not determir.ed that it extends beyond this particular
procedure.
Corrective Actions Taken
The discarded surveillance pages have not caused us to doubt the operability of the fire
detectors. The cover sheet, which is maintained:
e documents completion of the test by the signature of the performer (along with
the date and time),
e acceptability of the test results, documented by the signature of the fire
protection administrator,
e documents, by signature, the system engineer review of the test for
completeness
e documents necessary corrective maintenance by referring to work orders
generated
in addition, any pages with deviaticns are maintained with the coversheet. Because
revisions of surveillance procedures are maintained, it is possible to recover the
specifics that were addressed by past surveillances of the fire detectors.
The information is available from the preserved documentation to make appropriate
safety, operability, or reportability determinations. We, therefore, believe that no
repeated surveillance is deemed necessary.
! Corrective Actions Recarding Fire Protection Data Retention
We will revise SP-1189 to require the retention of allpages that contain any
documentation ofperformance (prior to the next performance of the test). As
discussed in the reason for the violation, the violation resulted from the procedure
calling out the information in the table as " test results;" we are not considering this to be
a global concern and are not currently changing our retention practice for other than fire
detector surveillance procedures. Further action is dependent on the conclusion to be
determined as discussed in the following section. We may elect to subsequently re-
retase the retention practice for SP-1189 as a result of that determination.
Corrective Actions to Preclude Recurreaca
We will determine the acceptable definition of data (in particular, as it relates to test
results) and revise the administrative workinstruction(s) as necessary. If a revised
concept of data is incorporated into the administrative work instruction (s), we will
perform an appropriate review of other surveillance procedures for conformance.
Date When Full Comoliance Will Be Achieved
Full compliance has been achieved, we are currently maintaining completed fire
detector surveillance procedures in their entirety.
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VIOLATION 2. c
Prairie Island Technical Specification 6.5.A 7 required that detailed written
implementing procedures be prepared and followed for the fire protection program.
c. Surveillance Procedure (SP) 1192," Safeguards Electrical and Mechanical
Penetrations Surveillance inspection," Revision 7, requires the verification of
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penetration seal operability through visual inspection.
Contrary to the above, on April 4,1997, SP 1192 was not followed in that 8
penetrations were not verified to be operable.
This is a Severity Level IV violation (supplement 1).
Response to violation 2.c
Reason for the Violation
There are approximately 100 sketches attached to surveillance procedure SP-1192.
The surveillance procedure outlines several steps for completing the work, it directs the
inspector to place checkmarks by the individual penetrations on the sketches; this is to
keep track of them because there are several on each drawing. The procedure also
directs the inspector to initial and date each sketch when it has been completed. A field
or working copy of the inspection procedure is used while performing the penetration
inspections. The field information is then transferred to an office copy which is used as
the master work order. The craft inspector assured us the penetrations had been
inspected although he had not properly transferred the checkmarks onto the master
copy of the work order. causing the violation.
Note that the engineering review after all the work has been done verifies by each page
signoff that all the penetrations were checked, not by looking for individual checkma-ks
on each sketch.
Corrective Actions Taken
When the question arose whether or not the inspections had been performed for the
subject penetrations, a roving fire watch was established for the penetrations noted as
being possibly inoperable and a work order issued to inspect those penetrations that
were not indicated as being inspected on the sketches. These penetrations were
inspected and found to be intact and acceptable.
Action to Preclude Recurrence
The surveillance procedure has been submitted to the Error Reduction Task Force
(ERTF) for a Human Factors review and will be modified following this mview based on
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November 13,1997
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the recommendations of the ERTF. Through improvements in the human performance
aspects of the surveillance and its logging of completion of inspections the ability to
properly determine if all penetrations were inspected will be enhanced.
Date When Full Comoliance Will Be Achieved
Full compliance has been achieved.
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