|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M6631999-10-19019 October 1999 Forwards Insp Rept 50-277/99-07 & 50-278/99-07 on 990920.No Violations Noted 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 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, 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 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 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 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 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 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) 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 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 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 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 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 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 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 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 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 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 ML20212A0091999-09-0909 September 1999 Provides Notification That Licenses SOP-11172 & SOP-11321, for SO Muntzenberger & Rh Wright,Respectively,Are No Longer Necessary as Result of Permanent Reassignment 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 ML20211K7031999-08-30030 August 1999 Forwards Response to NRC 990826 RAI Re License Change Application ECR 99-01255,revising TSs 2.1.1.2 & 5.6.5 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 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) ML20211E9191999-08-24024 August 1999 Forwards fitness-for-duty Program Performance Data for Jan-June 1999 for PBAPS & LGS IAW 10CFR26.71(d).Data Includes Listed Info 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 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 ML20210P8321999-08-11011 August 1999 Responds to NRC 990715 Telcon Re Util 990217 Submittal of Proposed Alternatives to Requirements of 10CFR50.55a(g)(6)(ii)(B)(1) Re Containment Inservice Insp Program ML20210P8151999-08-11011 August 1999 Forwards Final Pages for Pbaps,Unit 2 & 3 OLs Re License Change Application ECR 99-01497,which Reflects Change in Corporate Structure at Pse&G ML20211B6521999-08-10010 August 1999 Informs That Dp Lewis,License SOP-11247,has Been Permanently Reassigned & No Longer Requires License,Per 10CFR50.74.Util Requests That Subject Individual Be Removed from List of License Holders 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 ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response 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 ML20210J0161999-07-30030 July 1999 Forwards Copy of Notice of Consideration of Approval of Transfer of FOL & Issuance of Conforming Amends Re 990723 Application 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 ML20210F3731999-07-23023 July 1999 Submits Confirmation That,Iaw 10CFR50.80,PSE&G Is Requesting NRC Approval of Transfer of Ownership Interests in PBAPS, Units to New Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML20210E6211999-07-22022 July 1999 Submits Rev to non-limiting Licensing Basis LOCA Peak Clad Temps (Pcts) for Limerick Generating Station (Lgs),Units 1 & 2 & Pbaps,Units 2 & 3 ML20210E5811999-07-21021 July 1999 Forwards Final Tech Specs Pages for License Change Application.Proposed Change Will Revise Tech Specs to Delete Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS ML20216D8041999-07-19019 July 1999 Submits Summary of Final PECO Nuclear Actions Taken to Resolve Scram Solenoid Pilot Valve Issues Identified in Info Notice 96-007 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217F3021999-10-12012 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, 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 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 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) 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 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 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 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 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 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 ML20212A0091999-09-0909 September 1999 Provides Notification That Licenses SOP-11172 & SOP-11321, for SO Muntzenberger & Rh Wright,Respectively,Are No Longer Necessary as Result of Permanent Reassignment ML20211K7031999-08-30030 August 1999 Forwards Response to NRC 990826 RAI Re License Change Application ECR 99-01255,revising TSs 2.1.1.2 & 5.6.5 ML20211E9191999-08-24024 August 1999 Forwards fitness-for-duty Program Performance Data for Jan-June 1999 for PBAPS & LGS IAW 10CFR26.71(d).Data Includes Listed Info ML20210P8321999-08-11011 August 1999 Responds to NRC 990715 Telcon Re Util 990217 Submittal of Proposed Alternatives to Requirements of 10CFR50.55a(g)(6)(ii)(B)(1) Re Containment Inservice Insp Program ML20210P8151999-08-11011 August 1999 Forwards Final Pages for Pbaps,Unit 2 & 3 OLs Re License Change Application ECR 99-01497,which Reflects Change in Corporate Structure at Pse&G ML20211B6521999-08-10010 August 1999 Informs That Dp Lewis,License SOP-11247,has Been Permanently Reassigned & No Longer Requires License,Per 10CFR50.74.Util Requests That Subject Individual Be Removed from List of License Holders ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML20210F3731999-07-23023 July 1999 Submits Confirmation That,Iaw 10CFR50.80,PSE&G Is Requesting NRC Approval of Transfer of Ownership Interests in PBAPS, Units to New Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML20210E6211999-07-22022 July 1999 Submits Rev to non-limiting Licensing Basis LOCA Peak Clad Temps (Pcts) for Limerick Generating Station (Lgs),Units 1 & 2 & Pbaps,Units 2 & 3 ML20210E5811999-07-21021 July 1999 Forwards Final Tech Specs Pages for License Change Application.Proposed Change Will Revise Tech Specs to Delete Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS ML20216D8041999-07-19019 July 1999 Submits Summary of Final PECO Nuclear Actions Taken to Resolve Scram Solenoid Pilot Valve Issues Identified in Info Notice 96-007 05000278/LER-1999-002, Forwards LER 99-002-01 to Correct Title Contained in Box (4) of LER Coversheet Form.Rev Does Not Change Reportability Requirements or Any Other Info Contained in Original Submittal of LER1999-07-12012 July 1999 Forwards LER 99-002-01 to Correct Title Contained in Box (4) of LER Coversheet Form.Rev Does Not Change Reportability Requirements or Any Other Info Contained in Original Submittal of LER ML20209G9121999-07-0909 July 1999 Informs That Ja Hutton Has Been Appointed Director,Licensing for PECO Nuclear,Effective 990715.Previous Correspondence Addressed to Gd Edwards Should Now Be Sent to Ja Hutton ML20209D9781999-07-0808 July 1999 Forwards Addl Info to Support EA of Proposed 990212 License Application ECR 98-01675,correcting Minor Administrative Errors in TS Figure Showing Site & Exclusion Areas Boundaries & Two TS SRs ML20209D8821999-07-0707 July 1999 Submits Estimate of Number of Licensing Actions Expected to Be Submitted in Years 2000 & 2001,as Requested by Administrative Ltr 99-02.Renewal Applications for PBAPS, Units 2 & 3,will Be Submitted in Second Half of 2001 ML20209D2671999-07-0202 July 1999 Responds to NRC 990322 & 0420 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20209E1131999-06-30030 June 1999 Forwards Proprietary NRC Form 398, Personal Qualification Statement-Licensee, for Renewal of RO Licenses for EP Angle,Md Lebrun,Jh Seitz & Zi Varga,Licenses OP-10646-1, OP-11081,OP-11082 & OP-11085,respectively.Encls Withheld ML20209B7001999-06-30030 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20209C1201999-06-30030 June 1999 Informs of Util Intent to Request Renewed License for PBAPS, Units 2 & 3,IAW 10CFR54.Licensee Anticipates That License Renewal Application Will Be Submitted in Second Half of 2001 05000277/LER-1999-004, Forwards LER 99-004-00 Re Unplanned ESF Actuations During Planned Electrical Bus Restoration Following Maint Activities1999-06-20020 June 1999 Forwards LER 99-004-00 Re Unplanned ESF Actuations During Planned Electrical Bus Restoration Following Maint Activities ML20196A5291999-06-14014 June 1999 Forwards Final Pbaps,Unit 3 TS Pages for License Change Request ECR 98-01802 Re Installation of Digital Power Range Neutron Monitoring (Prnm) Sys & Incorporation of long-term thermal-hydraulic Stability Solution Hardware ML20195E6051999-05-27027 May 1999 Requests Exemption from Requirements of 10CFR72.44(d)(3) Re Submittal Date for Annual Rept of Principal Radionuclides Released to Environ.Exemption from 10CFR72.72(d) Re Storage of Spent Fuel Records,Additionally Requested ML20195B8171999-05-25025 May 1999 Forwards Final TS Pages for License Change Application ECR 96-01511 Re Rev to Loss of Power Setpoints for 4 Kv Emergency Buses ML20195B6191999-05-19019 May 1999 Forwards PBAPS Units 2 & 3 Annual Radiological Environ Operating Rept 56 for 980101-1231, Per Section 6.9.2 of Ol. Trace Concentrations of Cs-137 Were Found in Sediment Consistent with Levels Observed in Previous Years ML20206P9171999-05-10010 May 1999 Updates Some of Transmitted Data Points Provided in Data Point Library ERDS for Pbaps,Units 2 & 3.Data Point Info Format Consistent with Guidance Specified in NUREG-1394 ML20206K6581999-05-0404 May 1999 Forwards PBAPS Bases Changes Through Unit 2 Bases Rev 25 & Units 3 Bases Rev 25.Bases Reflect Change Through Apr 1999, Thereby Satisfying Frequency Requirements of 10CFR50.71 ML20206D4651999-04-29029 April 1999 Forwards Rev 16 to UFSAR & Rev 11 to Fire Protection Program (Fpp), for Pbaps,Units 2 & 3.Page Replacement Instructions for Incorporating Rev 16 to UFSAR & Rev 11 to Fpp,Encl ML20207B8431999-04-23023 April 1999 Forwards Final Rept for 981117,plume Exposure Pathway Exercise of Offsite Radiological Emergency Response Plans site-specific for Peach Bottom Atomic Power Station.One Deficiency & 27 Areas Requiring C/A Identified ML20206C5461999-04-20020 April 1999 Forwards Radioactive Effluent Release Rept 41 for Jan-Dec 1998 for Pbaps,Units 1 & 2. Revs Made to ODCM & Station Process Control Program (PCP) During Rept Period,Encl 05000277/LER-1999-003, Forwards LER 99-003-00 Re 990318 Failure to Maintain Provisions of Fire Protection Program to Properly Address Effects of Flooding1999-04-16016 April 1999 Forwards LER 99-003-00 Re 990318 Failure to Maintain Provisions of Fire Protection Program to Properly Address Effects of Flooding ML20205K4541999-04-0808 April 1999 Forwards Revised Info Re 990330 NRC Nuclear Power Reactor Licensee Financial Qualifications & Decommissioning Funding Assurance Status Rept 05000278/LER-1999-001, Forwards LER 99-001-00 Re 990312 ESF Actuation of Rcics Due to High Steam Flow Signal During Sys Restoration.Rept Submitted Per 10CFR50.73(a)(2)(iv)1999-04-0808 April 1999 Forwards LER 99-001-00 Re 990312 ESF Actuation of Rcics Due to High Steam Flow Signal During Sys Restoration.Rept Submitted Per 10CFR50.73(a)(2)(iv) ML18106B1431999-03-31031 March 1999 Forwards Pse&G Rept on Financial Min Assurance for Period Ending 981231 for Hope Creek,Salem,Units 1 & 2 & Pbaps,Units 2 & 3,IAW 10CFR50.75 ML20205F8981999-03-31031 March 1999 Provides Info Re Status of Decommissioning Funding for LGS, Units 1 & 2,PBAPS,Units 1,2 & 3 & Sgs,Units 1 & 2,per Requirements of 10CFR50.75(f)(1) ML18106B1411999-03-30030 March 1999 Forwards Decommissioning Info on Behalf of Conectiv Nuclear Facility License Subsidiaries,Atlantic City Electric Co & Delmarva Power & Light Co,For Listed Nuclear Facilities ML20205J0831999-03-26026 March 1999 Requests Enforcement Discretion from Requirements of PBAPS, Units 2 & 3 Ts.Enforcement Discretion Pursued to Avoid Unneccessary Plant Transient Which Would Result from Compliance with TS ML20205B6421999-03-24024 March 1999 Submits 1998 Annual Decommission Rept for Pbaps,Unit 1. There Were No Reportable Events Involving Unit 1 for 1998 1999-09-09
[Table view] |
Text
__ _ _ ._ __ . _ _ . _
0:rald C. Calney Vice President
- Peach Bottom Atomic Power Station d I v :
"; 1 Ca' "*"'
PECO ENERGY Delta. PA 1/314-9739 717 456 7014 January 19, 1996 i
Docket Nos. 50-277 50-278 !
License Nos. DPR-44 l DPR-56 l U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Subject:
Peach Bottom Atomic Power Station Units 2 & 3 l Response to Notice of Violation (Combined Inspection Report No. j 50-277/95-26 & 50-278/95-26)
Gentlemen:
In response to your letter dated December 12,1995, which transmitted the Notice of ,
Violation concerning the referenced inspection report, we submit the attached vio!ation i response and revision to LER 3-95-04. The subject report concerned a Routine Residents' Integrated Inspection that was conducted October 15 through November 25, 1995. An extension to the original required date of response was requested via telephone on January 10,1996, by Ronald K. Smith, PBAPS Regulatory Group, and was granted by Walter J. Pasciak, Section Chief - Projects Branch 4, Division of Reactor Projects.
If you have any questions or desire additional information, do not hesitate to contact us. ;
C Gerald R. Raine i Vice President l Peach Bottom Atomic Power Station Attachment l
250036 s 9601250133 960119 ADOCK 05000277 PDR G PDR /y,()'
6 CCN #96-14008 h
.. .- . - -- - --. . . - . . - _ . . . - - . ~ . . -
~
l cc: B. W. Gorman, Public Service Electric & Gas !
R. R. Janati, Commonwealth of Pennsylvania i T. T. Martin, US NRC, Administrator, Region l W. L. Schmidt, US NRC, Senior Resident inspector l
H. C. Schwemm, VP - Atlantic Electric R. I. McLean, State of Maryland A. F. Kirby ill, DelMarVa Power l
RESPONSE TO NOTICE OF VIOLATION Restatement of Violation Technical Specification 3.6.C. requires, in part, that during reactor power operation with both drywell sump collection and flow monitoring systems inoperable, for longer than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the unit shall be in at least Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Contrary to the above, between October 26 and October 29,1995, during reactor power operations, both drywell sump collection systems were inoperable for longer than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and the unit was not in at least Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
This is a Severity Level IV violation (Supplement 1).
Incident Description in April 1995, the Liquid Radwaste System Manager initiated a request for the Drywell Sump Pump Level Controllers to be replaced. The existing controllers were obsolete, and more reliable solid state controllers were requested. Engineering Change Requests (ECR's) were initiated to perform the task and in May,1995, the ECRs were approved to replace controllers in the Drywell Floor Drain and Drywell Equipment Drain Systems.
In August 1995, an Administrative Guideline (AG)-123," Maintaining Configuration Control of Design Changes" review was performed by Maintenance Planning, Design Engineering and the Liquid.Radwaste System Manager. The AG-123 review was required to ensure that modification design, installation and acceptance test plan (ATP) were thoroughly evaluated to successfully implement the modification. The topic of resistor sizing was discussed and the decision was made to use a resistor value of 10K ohms. -This decision was based primarily on the resistor value sizing chart provided by the manufacturer and consideration of the process fluid (water) being monitored.
Resistance level probes found in both Drywell systems and comparative resistance circuitry initiate and stop associated drain pumps to control system level. Each Drywell system has two pumps, a lead pump and a lag pump, that will start pumping on a HI level (lead pump) or a HI-HI level (lag pump). Both pumps will automatically cease pumping when instrumentation circuity senses LOW level. Control instrumentation i initiates or ceases pumping based on resistance changes between a common probe, which is always immersed in water, and three other associated probes for HI level, HI-HI level and LOW level. The resistance between these probes is compared to a fixed resistor in the instrumentation circuitry to automatically initiate or tp pump of the Drywell Sumps.
l 4
n - ,- - - - , . - , , - -- . . . - ,i
On October 23,1995, the Drywell Floor Drain Sump Pumps were run in the manual mode, to pump the sump to its lowest level. A clearance was then applied to the Drywell Floor Drain Sump, which isolated the system and blocked the pumps from automatically starting. Work was completed by Instrumentation and Controls (l&C) personnel on October 25,1995, and the logic was tested satisfactorily under the clearances. l&C then signed off the clearance to support Operations Surveillance Test (ST)-O-020-560-3,
" Reactor Coolant Leakage Test", to verify normal floor drain pump out rates.
Operations personnel decided that the post modification test (PMT) was satisfied after 1 observing three-4 hour periods with no Drywell Floor Drain pump-outs. This pump-out rate was considered consistent with the pump out rate of the Drywell Floor Drain Sump before the system was removed from service where only one pump out had occurred in seventeen-4 hour periods. The Shift Supervisor concluded that it could take several days for the Drywell Floor Drain Sump to fill back up and signed off the PMT as satisfactory, since the I&C PMT was completed without any known discrepancies. The Drywell Floor Drain System was declared operable, which allowed application of clearances on the Drywell Equipment Drain System.
On October 26,1995, the Drywell Equipment Drain Sump Pumps were run in the manual mode, to pump the sump to its lowest level. A clearance was then applied to the Drywell Equipment Drain Sump, which isolated the system and blocked the pumps from automatically starting. Work was completed by I&C personnel on October 27,1995, and the logic was tested satisfactorily under the clearance, l&C then signed off the clearance to support the Operations PMT and Operations initiated ST-O-020-560-3 to verify normal Drywell Equipment Drain Sump pump out rates.
During the performance of ST-O-020-560-3 on October 28,1995, at approximately 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />, it was noted that no pump outs from the Drywell Equipment Drain Sump had occurred in > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and that no pump outs from the Drywell Floor Drain Sump had occurred in > 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br />. Shift Supervision was notified and the decision to manually start the sump pumps was made. It was realized at that time that a problem existed with the automatic start function of the Drywell Collection Systems and I&C was notified. The Liquid Radwaste System Manager was also notified of the situation, and Operations '
initiated a manual cump out schedule for both the Drywell Floor Drain & Drywell Equipment Drain Systems to maintain surveillance requirements.
Once the resistor sizing problem was identified, a plan was developed to replace the resistor in question and to test the system. On October 31,1995, the Drywell Equipment Drain Sump was blocked and the 10K ohm resistor was replaced with a 2.2 mega ohm resistor. Approximately 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> later the PMT was signed off satisfactoriiy based on a revised testing method which allowed the Drywell Equipment Drain Sump to fill up with the pumps in off to ' allow the HI-HI alarm to come in. Following the HI-HI alarm, the pumps were returned to the automatic mode of opWion and the sump was allowed to pump down. The system was then declared operable.
On November 1,1995, the Drywell Floor Drain Sump was blocked and the 10K ohm resistor was replaced with 2.2 mega ohm resistor. On November 3,1995, the revised PMT was completed and signed off satisfactorily. The Drywell Floor Drain System was then returned to the automatic mode of operation and the system was declared operable.
Reasons for the Violation The initial design review and AG-123 review were less than adequate in the selection '
of the proper resistor value for the Drywell Sump Pump Level Controllers. Engineering did not recognize the importance of evaluating conductivity as a critical characteristic of ,
the replacement part and therefore did not ensure that the resistor selected was proper ,
for that application. Although resistor sizing was discussed during the AG-123 review i process, it was not thoroughly evaluated by the design engineer. The design engineer based the selection of the 10 K ohm resistor on a sizing chart provided by the i manufacturer. Additional clarifying information supplied by the manufacturer was not adequately evaluated to ensure the proper resistor was selected. The primary concern of the design engineer was centered around the circuit wiring and the logic of the Drywell Sump Collection System. The wiring was very complex and the wiring documentation for the system required close scrutiny. As a result of the design engineer's concentrated focus on the wiring and not realizing the importance of resistor sizing, the walkdown performed by the designer and the design engineer.was less than adequate. The installed resistor value was not recorded on the existing system or compared to the resistor value selected.
The AG-123 review team did not adequately address the ATP. The lack of sensitivity to include and address conductivity as a critical characteristic resulted in an ATP that did not address the full spectrum of inputs to be verified. The ATP lacked sufficient detail for Operations and did not assure a positive test to verify operability. The AG-123 review team relied too heavily on an existing ST to adequately address the Drywell Sump Level Controlier replacement. In addition, management expectations were not met for the use of a routine surveillance test to satisfy AG-123 requirements of "one step beyond" operability verification. If a routine test is used for this purpose it is expected that specific modification acceptance criteria be added as appropriate to ensure positive verification of operability. The ATP in this case did not provide specific acceptance criteria for system performance or direction regarding sump capacities, expected time for pump outs, or contingency plans in case unexpected results were received.
The Liquid Radwaste System Manager's oversight of the replacement of Drywell Sump Pump Level Controllers was less than adequate. The System Manager should have exhibited a heightened awareness and ownership of the system during the controller replacement. In addition, the System Manager should have been more involved to provide system expertise to Operations personnel.
+ w +m .~, -
v e gw y w- - -- -
3 .
y l
The implementation of the AG-123 process in this event did not meet management i expectations. Overall, the AG-123 process has heightened the awareness of station personnel performing modifications and has improved the overall change process.
Additional clarification and communication of management expectations for AG-123,
- however, is required to ensure station personnel are implementing AG-123 as intended.
The AG-123 review for this ECR did not account for and address the full range of j variables or special criteria when developing the ATP. In addition, the review failed to l ensure that appropriate testing parameters were incorporated.
! Operations personnel failed to identify that the Drywell Floor Drain Sump did not pump out following the pre-maintenance pump out or after receiving overflow from the Drywell
- Equipment Drain System. Additionally, it was not identified that the Drywell Equipment i
! Drain Sump did not initiate a pump out following the return of the sump to service.
i Operations personnel were aware that the sumps had not pumped out, but were not aware of the sump capacities or the time that would be required for the sumps to fill up
- and initiate a pump out. Operations personnel did not aggressively question system data i and did not meet managements expectations for applying healthy skepticism and i
- heightened awareness when returning equipment to service.
i l
! Operations personnel failed to log the removal and return of both Drywell Collection
- Systems and to enter _ a potential limiting condition of operation (PLCO) when removing
, equipment required to be operational by Technical Specifications (TS). Personnel did not i meet management expectations or the Operations Manual requirement of OM-P-8.2 which clearly states that the removal or return to service of Technical Specifications (TS) i related systems or components are to be appropriately logged. Additionally, OM-P-12.2
! states the expectation to enter a PLCO when removing TS equipment from service. The
- OM requirements and management expectations for entering PLCOs were not met. :
j Operations personnel did not identify that the PMT was inadequate to demonstrate oparability. The PMT adequately verified the electronic configuration changes, but did not adequately address or verify the component (resistor) change, which resulted in the loss of the automatic pump out function of the Drywell Collection System Sumps. The control room Supervisor based the operability determination of the Drywell Floor Drain System on the successful completion of the I&C PMT and a passive negative test (no pump outs expected) and did not maintain a questioning attitude and heightened awareness when reviewing the PMT for operability.
l The Corrective Steos That Have Been Taken and the Results Achieved Manual pump outs were initiated every two hours on both the Drywell Floor Drain Sump and Drywell Equipment Drain Sump, after the automatic start function of the both systems pumps was determined to be-inoperable.
An ECR was implemented to in' w the properly sized resistors and the ATP was reviseo to provide a more comprehensive test to ensure system operability.
The eppropriate resistor _value was documented on station drawings.
Operations Shift personnel involved in this event. were counselled on the OM requirements and Management expectations regarding log keeping, conservative decision making and operability determinations.
The logkeeping performance indicator was also revised to monitor for entries where TS equipment is either removed or returned to service and to include PLCO and LCO entries.
The design engineer and designer were counselled on the expectations of performing an all inclusive walkdown when developing a plan to change plant equipment and the need to thoroughly review all appropriate documentation and manufacturer information regarding the planned change.
The System Manager was counselled on the expectations of system ownership and heightened oversight for any proposed change to that system and the importance of evaluating that change with a testing method "one step beyond" as required in AG-1'23.
Corrective Actions that Will be Taken to Avoid Further Violations Management expectations of the AG-123 process will be reinforced to station personnel by February 5,1996, to ensure that personnel understand the intent of AG-123. AG-123 will also be revised to include this event as an example of the degree of evaluation and questioning needed in the process to ensure success. This revision will be completed March 29,1996.
Appropriate Design Engineering procedures will be evaluated and revised to provide additional guidance on the identification and selection of critical system characteristics and how to evaluate differences in these characteristics with respect to the functions of plant systems and components. The procedures will be revised March 29,1996.
A sample of pending Document Equivalent Changes (DECs) for significant plant systems will be reviewed and evaluated for similar problems. This review will be completed by March 29,1996.
l
Enhanced ATP training will be provided to appropriate design change team members by July 1,1996.
OM-C-10.5 will be revised to verify that the control room Supervisor performs an adequate review of PMTs for operability. Specifically, when the PMT conceras a design change of a TS system. The OM will be revised to ensure that the PMT verifies positive automatic operation of the system or component utilizing actual plant parameters. This 4 revision will be completed by March 29,1996.
ST-O-020-560-3(2), " Reactor Coolant Leakage Test" will be revised to include the capacities of the Drywell Floor Drain and Drywell Equipment Drain Sumps.
This revision will be completed by March 29,1996. i i
A training package will be developed to reinforce appropriate logkeeping, PLCO entries, PMT adequacy for determining operability, healthy skepticism and overall heightened awareness. This training will be developed and implemented by March 29,1996.
l Date When Full Comoliance Was Achieved Full compliance was achieved October 29,1995, when two hour manual pump outs for the Drywell Floor Drain Sump and Drywell Equipment Drain Sump were initiated. The automatic start function of the Drywell Equipment Drain Sump was restored October 31, 1995, and the automatic start function of the Drywell Floor Drain Sump was restored November 3,1995.
I i
1 i
I w