ML20215H698
ML20215H698 | |
Person / Time | |
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Site: | Peach Bottom, Arkansas Nuclear, Surry, 05000000 |
Issue date: | 01/12/1987 |
From: | Morris B NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
To: | Sommers D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
Shared Package | |
ML20215H426 | List: |
References | |
FOIA-87-20 NUDOCS 8706240190 | |
Download: ML20215H698 (1) | |
Category:CORRESPONDENCE-LETTERS
MONTHYEARML18152B3571999-10-22022 October 1999
[Table view]Requests Relief from Temporary Repair of Through Wall Leak Discovered on 30 Inch Component Cooling Heat Exchanger Discharge Pipe Associated with Service Water Sys Common to Surry Units 1 & 2 1CAN109906, Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 11999-10-19019 October 1999 Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 1 ML20217M6631999-10-19019 October 1999 Forwards Insp Rept 50-277/99-07 & 50-278/99-07 on 990920.No Violations Noted ML20217J4971999-10-18018 October 1999 Requests Addl Info Re Results of Util Most Recent Steam Generator Insp at ANO-2 & Util Methodology Used to Predict Future Performance of SG Tubes ML20217J3601999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Integranular Attack in Tubesheets of Once-Through SG, Rev 1 Marked as Proprietary Will Be Withheld from Public Disclosure ML20217J3871999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through SG, Rev 0 Marked as Proprietary Will Be Withheld from Public Disclosure 2CAN109902, Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs1999-10-15015 October 1999 Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs 2CAN109903, Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp1999-10-14014 October 1999 Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp ML20217K9241999-10-14014 October 1999 Forwards Amend 234 to License DPR-56 & Se.Amend Consists of Changes to TS in Response to Application & Suppls ,1001 & 06,which Will Support PBAPS Mod P00507,which Will Install Digital Pr Neutron Mining Sys ML20217F7391999-10-14014 October 1999 Requests Addl Info Re Peach Bottom Atomic Power Station Units 2 & 3 Appendix R Exemption Requests ML18152B3581999-10-14014 October 1999 Submits Response to Violations Noted in Insp Repts 50-280/98-201 & 50-281/98-201.Corrective Actions:Visual Insps Were Completed on Accessible Coatings Inside Containment for Both Units 1 & 2 ML20217F6841999-10-13013 October 1999 Forwards Senior Reactor Operator Initial Exam Repts 50-277/99-302(OL) & 50-278/99-302(OL) Conducted on 990913- 16.All Applicants Passed All Portions of Exam ML20217F3021999-10-12012 October 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at PBAPS Have Been Completed.Ltr Also Confirms Completion of Actions Required by Confirmatory Order Modifying Licenses, ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML20217E7451999-10-0808 October 1999 Forwards Response to NRC 990820 RAI Concerning Proposed Alternatives Associated with Third ten-yr Interval ISI Program for Pbaps,Units 2 & 3 ML20217D1721999-10-0808 October 1999 Forwards RAI Re 990729 Request for Amend to TSs Allowing Special SG Insp for Plant,Unit 2.Questions Re Proposed Insp Scope for Axial Cracking Degradation in Eggcrate Support Region Submitted.Response Requested by 991015 ML20217C4141999-10-0606 October 1999 Forwards Response to NRC 981109 RAI Re Resolution of USI A-46 for Pbaps.Proprietary Excerpts from GIP-2,Ref 25 Results of BWR Trial Plant Review Section 8 Also Encl. Proprietary Excerpts Withheld ML20217B9151999-10-0606 October 1999 Provides Clarifying Info to Enable NRC to Complete Review of License Change Request ECR 98-01802,re Changes Necessary to Support Installation of Digital Pr Neutron Monitoring & Incorporate long-term T/H Stability Solution Hardware ML20217B7701999-10-0606 October 1999 Submits Corrected Info to NRC 980528 RAI Re Util Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20217B4051999-10-0505 October 1999 Forwards Amend 233 to License DPR-56 & Safety Evaluation. Amend Changes Minimum Critical Power Ratio Safety Limit & Approved Methodologies Referenced in Core Operating Limits Report ML20217B3181999-10-0505 October 1999 Advises That Info Submitted in 990712 Application,Which Contained Attachment Entitled, Addl Info Re Cycle Spec SLMCPR for Peach Bottom 3 Cycle 13,dtd 990609, with Affidavit,Will Be Withheld from Public Disclosure 1CAN109905, Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included1999-10-0404 October 1999 Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included ML20217B8891999-10-0101 October 1999 Forwards Response to RAI Re Request to Install Digital Power Range Neutron Monitoring Sys & Incorporate long-term,thermal-hydraulic Stability Solution Hardware. Revised TS Table 3.3.2.1-1 Encl 05000278/LER-1999-004, Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv)1999-10-0101 October 1999 Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv) ML20212L0621999-10-0101 October 1999 Forwards Safety Evaluation & Exemption from Certain Requirements of 10CFR50,App R,Section III.G.2, Fire Protection of Safe Shutdown Capability 1CAN099908, Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria1999-09-30030 September 1999 Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria ML20217D5211999-09-30030 September 1999 Informs That Remediating 3D Monicore Sys at Pbaps,Units 2 & 3 & 3D Monicore/Plant Monitoring Sys at Lgs,Unit 2 Has Been Completed Ahead of Schedule ML20212J6851999-09-29029 September 1999 Informs of Completion of mid-cycle PPR of Peach Bottom Atomic Power Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl New Insps Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20216J3981999-09-29029 September 1999 Submits Comments for Lgs,Unit 1 & Pbaps,Units 2 & 3 Rvid,Rev 2,based on Review as Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity 2CAN099902, Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,20001999-09-29029 September 1999 Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,2000 ML20212J5751999-09-28028 September 1999 Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 990913-16 at Licensee Facility.Without Encls ML20216J0191999-09-27027 September 1999 Forwards Request for Addl Info Re Util 990301 Request to Support Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware,For Plant 1CAN099903, Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.31999-09-27027 September 1999 Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.3 ML18152B3401999-09-27027 September 1999 Requests That Ma Walker Be Removed from List of Individuals Scheduled to Take Exam IAW Guidance Provided in NUREG-1021, Operator Licensing Exam Stds for Power Reactors ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC 1CAN099907, Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative1999-09-26026 September 1999 Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative 1CAN099906, Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data1999-09-24024 September 1999 Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data 2CAN099901, Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 9908271999-09-24024 September 1999 Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 990827 ML20212H5431999-09-24024 September 1999 Informs of Decision to Inspect H-3 & H-4 Shroud Welds During Upcoming 3R12 Outage Scheduled to Begin Late Sept 1999 ML20212H6171999-09-24024 September 1999 Forwards Rev 2 to COLR for Pbaps,Unit 2,Reload 12,Cycle 13, IAW TS Section 5.6.5.d.Rept Incorporates Revised Single Loop Operation MAPLHGR Flow Multiplier ML20216H6751999-09-24024 September 1999 Forwards Amends 229 & 232 to Licenses DPR-44 & DPR-56, Respectively & Ser.Amends Will Delete SR Associated Only with Refueling Platform Fuel Grapple Fully Retracted Position Interlock Input,Currently Required by SR 3.9.1.1 ML20216H6451999-09-24024 September 1999 Forwards Notice of Withdrawal of Util 990806 Application for Amends to Fols DPR-44 & DPR-56.Proposed Change Would Have Involved Temporary Change to Increase Limit for Average Water Temp of Normal Heat Sink ML20216F8811999-09-23023 September 1999 Withdraws 990806 Exigent License Change Application.Tech Spec Change to Allow Continued Power Operation with Elevated Cooling Water Temps During Potentially Extreme Weather Conditions No Longer Needed Due to Favorable Weather 2CAN099904, Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR1999-09-23023 September 1999 Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR ML20212F5031999-09-22022 September 1999 Forwards SER Granting Relief Requests 1-98-001 & 1-98-002 Which Would Require Design Mods to Comply with Code Requirements,Which Would Impose Significant Burden Pursuant to 10CFR50.55a(g)(6)(i) ML20212E8661999-09-22022 September 1999 Discusses GL 98-01 Y2K Readiness of Computer Sys at NPPs & Supplement 1 & PECO Response for PBAPS Dtd 990630. Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient During Y2K Transition ML18152B3381999-09-21021 September 1999 Forwards in Triplicate,Applications for Renewal of License for Bf Jurewicz & JW Heide.Without Encls ML20212F5481999-09-20020 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing, for Pbaps,Units 2 & 3 & Lgs,Units 1 & 2 ML20212D1191999-09-17017 September 1999 Forwards SE Re Proposed Alternatives to ASME Section XI Requirements for Containment Inservice Insp Program at Plant,Units 2 & 3 1CAN099905, Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments1999-09-17017 September 1999 Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments 1999-09-30 Category:NRC TO UTILITY MONTHYEARML20062F0481990-11-19019 November 1990
[Table view]Advises That SR Peterson Replacing C Poslusny as Project Manager for Facility,Effective 901105 ML20216K0001990-11-13013 November 1990 Forwards Insp Repts 50-313/90-30 & 50-368/90-30 on 900905- 1016 & Notice of Violation ML20062F2241990-11-0909 November 1990 Forwards SSFI Repts 50-277/90-80 & 50-278/90-80 on 900917- 1003 Conducted by Corrective Action Review Team.Corrective Actions Generally Acceptable W/Some Weaknesses Noted IR 05000313/19900321990-11-0808 November 1990 Ack Receipt of Outlining Steps to Provide Addl Technical Support for Radiation Protection Manager.Planned Actions Acceptable as Documented in Insp Repts 50-313/90-32 & 50-368/90-32 ML20058G8471990-11-0808 November 1990 Forwards Insp Repts 50-313/90-32 & 50-368/90-32 on 900924-29.No Violations or Deviations Noted IR 05000277/19900191990-11-0707 November 1990 Forwards Exam Repts 50-277/90-19OL & 50-278/90-19OL Administered During Wk of 900924 ML20058G1631990-11-0707 November 1990 Forwards Summary of Current Status of Unimplemented Generic Safety Issues at Plant ML20062D5381990-11-0606 November 1990 Forwards List of Unimplemented Generic Safety Issues at Facilities,Per Generic Ltr 90-04 ML20058E2881990-11-0101 November 1990 Rejects 900302 Request for Amend to Tech Specs to Revise Power Calibr Requirements for Linear Power Level & Core Protection Calculator delta-T Power & Nuclear Power Signals ML20058G1541990-10-31031 October 1990 Requests That Util Furnish Ref Matl Listed in Encl 1, Ref Matl Requirements, for Administration of Licensing Exams & Evaluation of Requalification Program Scheduled for Wk of 910304 ML20062D5761990-10-31031 October 1990 Forwards Insp Repts 50-313/90-40 & 50-368/90-40 on 901015-19.No Violations Noted ML20062D5631990-10-31031 October 1990 Forwards Insp Repts 50-313/90-37 & 50-368/90-37 on 901015-19.No Violations Noted ML20062D5511990-10-31031 October 1990 Forwards Insp Repts 50-313/90-31 & 50-368/90-31 on 901001-04.No Violations Noted ML20062C7451990-10-26026 October 1990 Forwards Safety Evaluation Accepting Response to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow ML20058D2371990-10-26026 October 1990 Informs of Impending fitness-for-duty Program Insp & Requests 10CFR26.20 Required Policies & Procedures ML20059P0441990-10-16016 October 1990 Authorizes Use of Inconel 690 (I-690) as Alternate to I-600 in Steam Generator Tube Sleeves/Plugs Per 10CFR50.55a(a)(3) ML20058A5211990-10-16016 October 1990 Forwards Insp Repts 50-313/90-38 & 50-368/90-38 on 901001- 05.Violation Considered for Escalated Enforcement Action ML20058A0811990-10-15015 October 1990 Forwards Questions Re 900808 License Amend Request to Increase Reactor Power to 100% for Response ML20062B8211990-10-11011 October 1990 Forwards Final SALP Repts 50-277/89-99 & 50-278/89-99 for Jul 1989 to May 1990.Improvements Noted ML20062A5511990-10-10010 October 1990 Forwards SER Re Util 890403,13 & 0717 Responses to Station Blackout Rule.Issue of Conformance Still Open ML20062A0651990-10-0505 October 1990 Forwards Safety Insp Repts 50-277/90-17 & 50-278/90-17 on 900814-0924.One Violation Noted IR 05000313/19900011990-10-0404 October 1990 Ack Receipt of 900420 & 0914 Ltrs Re Validation of Nonlicensed Operator Staffing Per Insp Repts 50-313/90-01 & 50-368/90-01 ML20059N5841990-10-0303 October 1990 Informs That Issuance of Senior Reactor Operator Licenses, for Fuel Handling Only,For More than One Facility Conditionally Acceptable ML20059M0441990-09-26026 September 1990 Approves 900809 Request to Withhold 86-1179795-01, ANO-1 HPI Flow Rate Requirements (Ref 10CFR2.790(b)(5)) ML20059M6561990-09-22022 September 1990 Ack Receipt of Util Re Corrective Actions Taken in Response to Insp Repts 50-277/90-13 & 50-278/90-13 ML20059K3851990-09-14014 September 1990 Forwards Insp Repts 50-313/90-28 & 50-368/90-28 on 900827-31.No Violations or Deviations Noted.Some Weaknesses Identified in Areas of Alternate Safe Shutdown Procedure & Associated Training for Unit 2 ML20059J2431990-09-14014 September 1990 Discusses Programmed Enhancements for Generic Ltr 88-17, Loss of Dhr. Changes in Completion Schedule Should Be Submitted to NRC ML20059J1971990-09-13013 September 1990 Ack Receipt of & Payment for Civil Penalty Proposed by NRC in in Amount of $75,000 ML20059J9901990-09-13013 September 1990 Forwards Info Re Generic Fundamentals Exam of Operator Licensing Written Exam to Be Administered on 901010.W/o Encl ML20059H0701990-09-11011 September 1990 Requests Addl Info Re Audit Rept Distribution,Per 890711 & 900420 Application Request for Removal of Organization Charts from Tech Spec Per Guidance Provided in Generic Ltr 88-06 & Miscellaneous Administrative Changes ML20059K7211990-09-0606 September 1990 Forwards Safety Insp Repts 50-277/90-15 & 50-278/90-15 on 900723-27 & Notice of Violation ML20059G2951990-09-0606 September 1990 Advises That Rev 10 to Emergency Plan,Contained in ,Acceptable.Rev Consists of Changes Resulting from Reorganization,Relocation of Personnel from Little Rock Ofc & Improvements from Annual Emergency Preparedness Exercise ML20059E8621990-08-31031 August 1990 Forwards Insp Repts 50-313/90-27 & 50-368/90-27 on 900813-17.No Citations Issued for Violation ML20059D1551990-08-30030 August 1990 Forwards Request for Addl Info to Continue Review of 891019 Application for Amend Extending Insp Frequency of Spent Fuel Pool from Once Per 18 Months to Once Per 60 Months.Response Requested within 45 Days IR 05000313/19900161990-08-29029 August 1990 Discusses 900823 Meeting Re Unresolved Item Concerning Missed Surveillance Tests,Per Insp Repts 50-313/90-16 & 50-368/90-16.Violation of Tech Spec Requirements Noted But Not Cited Due to Listed Reasons ML20059D6381990-08-29029 August 1990 Ack Receipt of Re Proposed Changes to Unit 1 Tech Spec 6.12.2.6(b) & Unit 2 Tech Spec 6.9.3.1.Proposed Changes Appear to Improve Quality of Semiannual Radioactive Effluent Release Repts ML20059E5901990-08-29029 August 1990 Forwards Summary of 900823 Quarterly Performance Meeting at Plant Re NRC Authorized Activities.Meeting Provided Better Understanding of Current Implementation Status of Program Changes at Plant.List of Attendees & Viewgraphs Encl ML20059F3441990-08-29029 August 1990 Forwards Insp Repts 50-313/90-23 & 50-368/90-23 on 900716-20.No Violations or Deviations Noted ML20059C4011990-08-24024 August 1990 Forwards Insp Repts 50-280/90-23 & 50-281/90-23 on 900723-27.Violations Noted ML20056B2691990-08-23023 August 1990 Forwards Request for Addl Info Re 880126 Application for Amends to Licenses,Revising Tech Specs to Provide More Restrictive Limits on Emergency Svc Water Sys.Response Should Be Provided within 60 Days of Ltr Receipt ML20059B8461990-08-23023 August 1990 Responds to Re Violations Noted in Insp Repts 50-313/89-33 & 50-368/89-33.Violations Remain Applicable ML20056B4921990-08-22022 August 1990 Forwards Request for Addl Info Re Util 900618 Response to NRC Questions on Condensate Storage Tank Seismic Qualification.Response Should Be Provided within 45 Days to Facilitate Completion of NRC Effort ML20056B4131990-08-21021 August 1990 Forwards Summary of 900718 Meeting Re Exercise Weaknesses Noted in Insp Repts 50-313/90-08 & 50-368/90-08 ML20056B4641990-08-21021 August 1990 Ack Receipt of Advising NRC of Current Status of Security Perimeter Improvements,Per Insp Repts 50-313/87-31 & 50-368/87-31.Implementation of Design Change DCP 90-2001 for Perimeter Lighting Will Be Monitored for Adequacy Later ML20059A7011990-08-17017 August 1990 Forwards Sser Concluding That Rochester Instrument Sys Model SC-1302 Isolation Device Acceptable for Use at Plant for Interfacing SPDS W/Class IE Circuits ML20059A6581990-08-16016 August 1990 Requests Discussion of Measures Considered &/Or Taken to Reduce Amount of Time Needed to Obtain Effluent Sample Analyses Results,Per 870121 Application for License Amends to Licenses DPR-44 & DPR-56 ML20058P2601990-08-13013 August 1990 Forwards Insp Repts 50-313/90-26 & 50-368/90-26 on 900730-0803.No Violations or Deviations Noted.Rept Does Not Include Specific Insp Followup for Any Diagnostic Evaluation Team Findings ML20058N9741990-08-10010 August 1990 Forwards Insp Repts 50-313/90-19 & 50-368/90-19 on 900601- 0715 & Notice of Violation.Util Should Respond to Failure to Adequately Implement Surveillance Test Required by Tech Specs IR 05000313/19900041990-08-0909 August 1990 Ack Receipt of 900611 & 0731 Ltrs Re Steps Taken to Correct Violations Noted in Insp Repts 50-313/90-04 & 50-368/90-04 ML20056A7491990-08-0707 August 1990 Forwards Safety Evaluation Accepting Licensee Fire Barrier Penetration Seal Program & Commitment to Complete 100% Review of All Tech Spec Fire Penetration Seals by 911231 1990-09-06 Category:OUTGOING CORRESPONDENCE MONTHYEARML20217M6631999-10-19019 October 1999
[Table view]Forwards Insp Rept 50-277/99-07 & 50-278/99-07 on 990920.No Violations Noted ML20217J4971999-10-18018 October 1999 Requests Addl Info Re Results of Util Most Recent Steam Generator Insp at ANO-2 & Util Methodology Used to Predict Future Performance of SG Tubes ML20217J3601999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Integranular Attack in Tubesheets of Once-Through SG, Rev 1 Marked as Proprietary Will Be Withheld from Public Disclosure ML20217J3871999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through SG, Rev 0 Marked as Proprietary Will Be Withheld from Public Disclosure ML20217F7391999-10-14014 October 1999 Requests Addl Info Re Peach Bottom Atomic Power Station Units 2 & 3 Appendix R Exemption Requests ML20217K9241999-10-14014 October 1999 Forwards Amend 234 to License DPR-56 & Se.Amend Consists of Changes to TS in Response to Application & Suppls ,1001 & 06,which Will Support PBAPS Mod P00507,which Will Install Digital Pr Neutron Mining Sys ML20217F6841999-10-13013 October 1999 Forwards Senior Reactor Operator Initial Exam Repts 50-277/99-302(OL) & 50-278/99-302(OL) Conducted on 990913- 16.All Applicants Passed All Portions of Exam ML20217D1721999-10-0808 October 1999 Forwards RAI Re 990729 Request for Amend to TSs Allowing Special SG Insp for Plant,Unit 2.Questions Re Proposed Insp Scope for Axial Cracking Degradation in Eggcrate Support Region Submitted.Response Requested by 991015 ML20217B3181999-10-0505 October 1999 Advises That Info Submitted in 990712 Application,Which Contained Attachment Entitled, Addl Info Re Cycle Spec SLMCPR for Peach Bottom 3 Cycle 13,dtd 990609, with Affidavit,Will Be Withheld from Public Disclosure ML20217B4051999-10-0505 October 1999 Forwards Amend 233 to License DPR-56 & Safety Evaluation. Amend Changes Minimum Critical Power Ratio Safety Limit & Approved Methodologies Referenced in Core Operating Limits Report ML20212L0621999-10-0101 October 1999 Forwards Safety Evaluation & Exemption from Certain Requirements of 10CFR50,App R,Section III.G.2, Fire Protection of Safe Shutdown Capability ML20212J6851999-09-29029 September 1999 Informs of Completion of mid-cycle PPR of Peach Bottom Atomic Power Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl New Insps Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20212J5751999-09-28028 September 1999 Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 990913-16 at Licensee Facility.Without Encls ML20216J0191999-09-27027 September 1999 Forwards Request for Addl Info Re Util 990301 Request to Support Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware,For Plant ML20216H6751999-09-24024 September 1999 Forwards Amends 229 & 232 to Licenses DPR-44 & DPR-56, Respectively & Ser.Amends Will Delete SR Associated Only with Refueling Platform Fuel Grapple Fully Retracted Position Interlock Input,Currently Required by SR 3.9.1.1 ML20216H6451999-09-24024 September 1999 Forwards Notice of Withdrawal of Util 990806 Application for Amends to Fols DPR-44 & DPR-56.Proposed Change Would Have Involved Temporary Change to Increase Limit for Average Water Temp of Normal Heat Sink ML20212F5031999-09-22022 September 1999 Forwards SER Granting Relief Requests 1-98-001 & 1-98-002 Which Would Require Design Mods to Comply with Code Requirements,Which Would Impose Significant Burden Pursuant to 10CFR50.55a(g)(6)(i) ML20212E8661999-09-22022 September 1999 Discusses GL 98-01 Y2K Readiness of Computer Sys at NPPs & Supplement 1 & PECO Response for PBAPS Dtd 990630. Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient During Y2K Transition ML20212D1191999-09-17017 September 1999 Forwards SE Re Proposed Alternatives to ASME Section XI Requirements for Containment Inservice Insp Program at Plant,Units 2 & 3 ML20212D9961999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Arkansas Nuclear One.Nrc Plan to Conduct Core Insps at Facility Over Next 7 Months.Details of Insp Plan Through March 2000 Encl ML20216F1381999-09-0808 September 1999 Forwards Retake Exam Repts 50-280/99-302 & 50-281/99-302 on 990824.One SRO Applicant Who Received re-take Operating Test Passed re-take Exam ML20211P2961999-09-0707 September 1999 Provides Authorization to Administer NRC Approved Initial Written Exams to Listed Applicants on 990913 at Peach Bottom Npp,Delta,Pennsylvania ML20211L4901999-09-0101 September 1999 Forwards Insp Repts 50-313/99-12 & 50-368/99-12 on 990711- 0821.No Violations Noted ML20211J2351999-08-31031 August 1999 Forwards Request for Addl Info Re SG Outer Diameter Intergranular Attack Alternate Repair Criteria for Plant, Unit 1 ML20211E6941999-08-26026 August 1999 Forwards Request for Addl Info Re Min Critical Power Ratio. Response Should Be Submitted within 30 Days of Ltr Receipt ML20211F4181999-08-25025 August 1999 Forwards SE Accepting Licensee 980603 & 990517 Requests for Approval of risk-informed Alternative to 1992 Edition of ASME BPV Code Section Xi,Insp Requirements for Class 1, Category B-J Piping Welds ML20211Q4491999-08-25025 August 1999 Responds to Re Changes to PBAPS Physical Security Plan,Safeguards Contingency Plan & Guard Training & Qualification Plan Identified as Revs 13,11 & 9, Respectively.No NRC Approval Is Required,Per 10CFR50.54(p) ML20211D5421999-08-23023 August 1999 Forwards Amends 228 & 231 to Licenses DPR-44 & DPR-56, Respectively & Se.Amends Revise TSs to Correct Typographical & Editorial Errors Introduced in TSs by Previous Amends ML20211A9721999-08-20020 August 1999 Forwards Request for Addl Info Re Third 10-year Interval Inservice (ISI) Insp Program Plan for Plant,Units 2 & 3 ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl IR 05000368/19990111999-08-12012 August 1999 Forwards Insp Repts 50-313//99-11 & 50-368/99-11 on 990719-23.No Violations Noted.Insp Focused on Review of Licensed Operator Requalification Program & Observation of Requalification Exam Activities at Unit 1 ML20210T5451999-08-12012 August 1999 Forwards Copy of Environ Assessment & Findings of No Significant Impact Re Licensee Request for Amends to Plant. Amends Consist of Changes to TS to Correct Typos & Editorial Errors Introduced in TS by Previous Amends ML20210P1561999-08-10010 August 1999 Submits Response to Requests for Addl Info Re GL 92-01,rev 1,Suppl 1, Rv Structural Integrity, for Pbap,Units 1 & 2. NRC Will Assume That Data Entered Into Rvid Are Acceptable for Plants,If Staff Does Not Receive Comments by 990901 ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210N7831999-08-0909 August 1999 Forwards Copy of Notice of Consideration of Issuance of Amends to Fols,Proposed NSHC Determination & Opportunity for Hearing, Re 990806 Request for License Amends.Amends Incorporate Note Into PBAPS TS to Permit One Time Exemption ML20210P0801999-08-0404 August 1999 Forwards Initial Exam Repts 50-277/99-301 & 50-278/99-301 on 990702-14 (Administration) & 990715-22 (Grading).Six of Limited SRO Applicants Passed All Portion of Exam NUREG-1092, Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls1999-08-0303 August 1999 Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210J0161999-07-30030 July 1999 Forwards Copy of Notice of Consideration of Approval of Transfer of FOL & Issuance of Conforming Amends Re 990723 Application ML20210L3581999-07-29029 July 1999 Ltr Contract,Task Order 43, Arkansas Nuclear One Safety System Engineering Insp (Ssei), Under Contract NRC-03-98-021 ML20216D8131999-07-28028 July 1999 Forwards Request for Addl Info Re SG Tube End Cracking Alternate Repair Criteria for Plant,Unit 1 ML20210H5341999-07-27027 July 1999 Forwards Insp Repts 50-277/99-05 & 50-278/99-05 on 990518- 0628.NRC Determined That Two Severity Level IV Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20210C2191999-07-21021 July 1999 Forwards Insp Repts 50-313/99-08 & 50-368/99-08 on 990530-0710 at Arkansas Nuclear One,Units 1 & 2,reactor Facility.No Violations Noted.Conduct of Activities at Plant Generally Characterized by safety-conscious Operations ML20209F2461999-07-15015 July 1999 Request Addl Info Re Relief Request CRR-01 Through CRR-11 for Plant,Units 2 & 3.RAI Undtd ML20209H5251999-07-15015 July 1999 Informs That as Result of NRC Review of Licensee 980701 & 990311 Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 RAI, Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 ML20209E5551999-07-0808 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1,suppl 1,staff Revised Info in Rv Integrity Database & Releasing Database as Rvid Version 2 ML20209D8521999-07-0707 July 1999 Responds to Util 990706 Request That NRC Exercise Discretion Not to Enforce Compliance with Actions Required by TS 3.7.2, Auxiliary Electrical Sys. NOED Warranted & Approval Granted for Extension of Allowed Outage Time to 14 Days ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 ML20209A8561999-06-25025 June 1999 Refers to Investigation Rept A4-1998-042 Re Potential Falsification of Training Record by Senior Licensed Operator at Arkansas Nuclear One Facility.Nrc Concluded That Training Attendance Record Falsified ML20196D4241999-06-21021 June 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp of License SOP-43716 Issued on 990325.Believes That NRC Concerns Have Been Adequately Addressed at Present 1999-09-08 |
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,es tsevy'e UNITED STATES NUCLEAR REGULATORY COMMISSION -I
^% wAssimoTon, c. c. zosse
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'JAN 12 t on e
Virginia Electric Power Company c/o David Somers "
1 Jame:. River Plaza - 5
- 7th 8 Cary St.
Richmond Virginia 23261
Dear Mr. Somers:
As you know from your conversation with William 1.ahs of my staff, The NRC, with -
its contractor, EG&G Idaho, Inc., is in the process of developing a PRA-based interactive system for assisting NRC resident inspectors in planning their inspection activities. The system is called the Plant Risk Status Infomation A Management System, or PRISIM, and is briefly described in Enclosure 1.
version of PRISIM is currently under test and evaluation at the Arkansas Nuclear One (ANO-1) facility and, as part of an overall PRISIM evaluation process, versions are under development for Peach Bottom and Surry. A copy of the ANO-1 PRISIM user's manual-is enclosed for your infomation. . ..
Although PRISIM is based on the latest PRA infomation, we continue to try to assure that this basis is as up-to-date as possible. Since the Surry PRA has been updated as of mid-1985, we believe that the Surry design and procedures are, in general, correctly represented. However, there may have been some changes with which we should be aware and, as in both our Peach Bottcm and ANO-1 efforts, we have found that this information is best attained through direct contact with knowledgeable utility personnel. Specific infomation on surveillance test and system procedures has proven most useful in our past efforts.
We would be willing to discuss the PRISIM program and, in particular, the Surry version of PRISIM with you and other interested VEPC0 personnel. This discussion could be accomplished in a cottference call or at a meeting which could take place at your convenience. Questions on PRISIM could be answered Your assistance in arranging such a and infomation needs could be discussed. -
discussion regarding your would certainlyon preferences bethis appreciated.
matter. , ^~ '.Please - '" W conta'c4,W4ahs N' ' " ~ -j. . -(443-73632)h
. . J _M-
'Since'reh's ~
l NW Bill Morris Acting Director Division of Reactor System Safet i
Office of Nuclear Regulatory Research
,~
C. Patel, NRR cc:
S. Newberry, NRR M. Ernst, Rgn. II
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