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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:NRC TO UTILITY
MONTHYEARML20062F2241990-11-0909 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 05000277/19900191990-11-0707 November 1990 Forwards Exam Repts 50-277/90-19OL & 50-278/90-19OL Administered During Wk of 900924 ML20062D5381990-11-0606 November 1990 Forwards List of Unimplemented Generic Safety Issues at Facilities,Per Generic Ltr 90-04 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 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 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 ML20062A0651990-10-0505 October 1990 Forwards Safety Insp Repts 50-277/90-17 & 50-278/90-17 on 900814-0924.One Violation Noted ML20059N5841990-10-0303 October 1990 Informs That Issuance of Senior Reactor Operator Licenses, for Fuel Handling Only,For More than One Facility Conditionally Acceptable 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 ML20059J1971990-09-13013 September 1990 Ack Receipt of & Payment for Civil Penalty Proposed by NRC in in Amount of $75,000 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 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 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 ML20058N0531990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Encourages Initiation of Initiative Similar to Region V Licensees Establishment of Engineering Managers Forum ML20056A5011990-07-30030 July 1990 Forwards Safety Insp Repts 50-277/90-13 & 50-278/90-13 on 900516-0702 & Notice of Violation ML20055E1711990-07-0606 July 1990 Requests That Licensee Provide Data on Channel Box Bow Vs Exposure Associated W/Methods Used to Account for Effects of Channel Box Bow During Second Bundle Lifetime Channel Boxes, Per 900425 Response to Bulletin 90-002,within 30 Days ML20055E9611990-07-0505 July 1990 Requests Addl Info Re Util 891228 Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance ML20055D0721990-06-27027 June 1990 Advises That Reactor Operator & Senior Reactor Operator Licensing Exams Scheduled for Wks of 900924 & 1001.Ref Matls,Listed on Encl,Should Be Provided by 900724 ML20055C8761990-06-15015 June 1990 Forwards Safety Insp Repts 50-277/90-10 & 50-278/90-10 on 900403-0515.No Violations Noted.Increased Mgt Attention Warranted to Ensure That Instances of Failure to Complete Surveillance Testing Identified & Corrected ML20059M8671990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248H8041989-10-0505 October 1989 Grants Termination of Requirements Set Forth in Section VA of Order to Permit Operation of Both Units at Full Power ML20248H1361989-10-0303 October 1989 Forwards Unexecuted Amend 22 to Indemnity Agreement B-28, Reflecting Changes to 10CFR140 Re Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu ML20248G2291989-09-29029 September 1989 Forwards Safety Insp Repts 50-277/89-21 & 50-278/89-21 on 890901.No Violations Noted.Insp Concluded That Improvements in Radiological Controls Program Have Been Slow.Addl Mgt Attention to Program Warranted ML20248E2351989-09-27027 September 1989 Forwards Summary of Issues Re Verification of Quality of Certain Types of Activities Performed for Mods at Facility. Mods Cover Automatic Depressurization Sys/Msiv Instrument Nitrogen Accumulator & Svc Water Pipe Replacement ML20248A4111989-09-25025 September 1989 Forwards Restart Team Safety Insp Repts 50-277/89-20 & 50-278/89-20 on 890730-0902.No Violations Noted ML20248E5581989-09-21021 September 1989 Forwards SER Supporting Use of Frosstey Fuel Performance Code Described in Topical Rept PECo-FMS-003, Steady-State Fuel Performance Methods Rept. Addl Applications of Subj Code Require NRC Review & Approval ML20247L9331989-09-13013 September 1989 Advises That Written Reactor Operator Licensing Exams Scheduled on 891211 & Operating Exams on 891212-15.Ref Matl Listed on Encl Should Be Provided by 891001.Simulator Exam Scenario Should Be Retained Until Exam Process Completed ML20247E8491989-09-0707 September 1989 Forwards SALP Board Repts 50-277/88-99 & 50-278/88-99 for Aug 1988 - June 1989 ML20247B8711989-09-0101 September 1989 Forwards Restart Safety Insp Repts 50-277/89-19 & 50-278/89-19 on 890618-0729.No Violations Noted ML20246E0241989-08-21021 August 1989 Forwards Safety Evaluation Accepting Util Response to Generic Ltr 83-28,Item 2.1 (Parts 1 & 2) Re Components Required to Trip Reactor & Interface W/Nmss Vendors or Vendors of Each Component,Respectively ML20246J4571989-08-18018 August 1989 Clarifies NRC Position Re Definition of Extremity for Purpose of Setting Occupational Exposure Limits,Per Info Notice 81-26.Util Should Ensure That Procedures Incorporate Applicable Dose Limits in 10CFR20 ML20248D0261989-08-0101 August 1989 Confirms 890714 Telcon & Requests Assistance & Cooperation in Review of Allegation Involving Plant.Util Should Fully Review Allegation & Take Action in Accordance W/Encl Instructions.Encl Withheld (Ref 10CFR2.790) ML20248C0421989-07-28028 July 1989 Responds to Util in Response to NRC Re Potential Violation of 10CFR50.7.Review of Record Indicates That Violation May Have Occurred.No Further Action Warranted as Case Settled Prior to Investigation ML20247E3191989-07-21021 July 1989 Relaxes Requirements of Section V.A of 870331 Order to Permit Operation of Unit 2 to Full Power ML20246F6121989-07-0606 July 1989 Forwards NRR to Ecology Ctr of Southern California Re Petition to Fix or Close All Nuclear Power Reactors Designed by Ge.Petition Being Treated Under 10CFR2.206 ML20246C3681989-06-30030 June 1989 Forwards Safety Evaluation Supporting 871019 Response to Generic Ltr 83-28,Item 4.5.3, Reactor Trip Sys Reliability, On-Line Testing of Reactor Trip Sys. Existing Test Intervals Consistent W/High Reactor Trip Sys Availability ML20246B9561989-06-28028 June 1989 Forwards Annual Emergency Preparedness Exercise Safety Insp Repts 50-277/89-17 & 50-278/89-17 on 890614.No Violations Noted ML20246B9161989-06-28028 June 1989 Advises That Requirements of 870331 Order Relaxed to Permit Unit 2 Operation Not to Exceed 70% Full Power,In Accordance W/Section Ve of Order ML20246A0001989-06-26026 June 1989 Forwards Restart Safety Insp Repts 50-277/89-16 & 50-278/89-16 on 890507-0617 & Notice of Violation ML20245C9671989-06-16016 June 1989 Requests Addl Info on Response to Generic Ltr 88-01 on IGSCC in Matls.Response Should Be Provided within 60 Days of Receipt of Ltr ML20247M7731989-05-26026 May 1989 Forwards Director'S Decision Re Ohio Citizens for Responsible Energy 10CFR2.206 Petition Re 880309 Power Oscillation Event at Lasalle,Unit 2 ML20247N8481989-05-25025 May 1989 Forwards Safety Insp Repts 50-277/89-12 & 50-278/89-12 on 890410-13.No Violations Noted ML20247L6481989-05-24024 May 1989 Forwards Restart Safety Insp Repts 50-277/89-15 & 50-278/89-15 on 890402-0506.No Violations Noted.Two Issues Remain Unresolved,Including HPCI Sys Wiring Error That Occurred During Plant Mod Installed in Mar & Apr 1989 ML20247K9191989-05-18018 May 1989 Forwards Electrical Insp Repts 50-277/89-13 & 50-278/89-13 on 890405-07 & 13.Issues to Be Resolved Before Unit 3 Restart Listed.No Violations Noted ML20246N3401989-05-10010 May 1989 Advises That Written Senior Reactor Operator Licensing Exams Scheduled for 890814 & Operating Exams Scheduled for Wk of 890918.Ref Matls Listed on Encl Should Be Provided by 890601 ML20246Q3711989-05-0303 May 1989 Extends Invitation to Attend Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Agenda & Info Re Lodging Arrangements Encl IR 05000277/19870301989-04-26026 April 1989 Ack Receipt of Re Steps Taken to Correct Violations Noted in Insp Repts 50-277/87-30 & 50-278/87-30 ML20245F3181989-04-26026 April 1989 Requests Encl Addl Info Re Util 890310 Application for Amends to Licenses DPR-44 & DPR-56 Re Intermediate Detector Not in Startup Position for Calibr 1990-09-06
[Table view] Category:OUTGOING CORRESPONDENCE
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 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 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 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 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 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) 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 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 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 ML20209F2461999-07-15015 July 1999 Request Addl Info Re Relief Request CRR-01 Through CRR-11 for Plant,Units 2 & 3.RAI Undtd 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 ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20195K2251999-06-11011 June 1999 Forwards Insp Repts 50-277/99-04 & 50-278/99-04 on 990405- 0517.One Severity Level IV Violation of NRC Requirements Identified & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20207G2051999-06-0707 June 1999 Informs of Reorganization in NRR Ofc,Effective 990328. Reorganization Chart Encl ML20207B8381999-05-24024 May 1999 Forwards FEMA Final Exercise Rept for Peach Bottom Atomic Power Station Plume Exposure Pathway Exercise Conducted on 981117.One Deficiency & 27 Areas Requiring Corrective Actions Identified ML20207A0541999-05-17017 May 1999 Acks 990512 & 14 Telcons with Licensee Re Util Request That Rev 8 of NUREG-1021, OL Exam Stds for Power Reactors Be Followed Rather than Interim Rev 8 for Exams in Sept 1999. Request Acceptable ML20206K2231999-05-0606 May 1999 Informs That Author Authorized to Exercise Discretion & Not Issue NOV or Civil Penalty Re Violation Util Identified Involving Unit 2 Rod Block Monitoring Sys Being Inoperable for 29 of 185 Control Rods ML20206K1921999-05-0606 May 1999 Discusses 990503 Telcon Between J Williams & B Bierly Re Arrangements Made for Administration of Licensing Exam at Peach Bottom Facility During Week of 990913 ML20206A1511999-04-20020 April 1999 Forwards Request for Addl Info Re Util 980514 Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-operated Valves. Response Requested within 90 Days of Ltr Receipt ML20206A2801999-04-20020 April 1999 Discusses Proposed Changes Submitted by PECO on 980416, 981116,990122 & 990211 to Plant Emergency Action Levels (Eals).Eals Incorporate Guidance in NUMARC/NESP-007,Rev 2. SE Supporting Proposed EALs Encl ML20205N1961999-04-0909 April 1999 Informs of NRC Planned Insp Effort Resulting from Peach Bottom Atomic Power Station Plant Performance Review Conducted for Period April 1998 to 990115.Historical Listing of Plant Issues & Insp Plans Through Jan 2000 Encl ML20205K7321999-04-0707 April 1999 Forwards Amends 227 & 230 to FOLs DPR-44 & DPR-56, Respectively.Amends Consist of Changes to TS SRs Re Secondary Containment Doors,In Response to 980204 Application,As Revised by ML20205J0531999-04-0101 April 1999 Ack Receipt of 990326 Notice of Enforcement Discretion Request & Documents Resolution.Notes That E3 EDG Returned to Operable Status on 990327,within 14 Day Completion Time Required by Ts.No Enforcement Discretion Necessary ML20205B9891999-03-25025 March 1999 Forwards Insp Repts 50-277/99-01 & 50-278/99-01 on 990105-0215.Violation Noted & Being Treated as non-cited Violation.Nrc Concluded That Staff Maintained Effective Influents Controls & Effective Security Program ML20203H8101999-02-12012 February 1999 Discusses Completion of Licensing Action for Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in BWR, ML20203H7751999-02-12012 February 1999 Discusses Completion of Licensing Action for GL 92-08, Thermo-Lag 330-1 Fire Barriers, for Peach Bottom Atomic Power Station ML20202J5251999-02-0101 February 1999 Forwards Insp Repts 50-277/98-11 & 50-278/98-11 on 981110- 990104 & Notice of Violation Re Failure to Complete Facility Licensed Operator Requalification Program ML20202J8081999-02-0101 February 1999 Forwards Insp Repts 50-277/98-09 & 50-278/98-09 & Notice of Violation.Insp Focused on Reactor Core Isolation Cooling & 4kV Electrical Distribution Sys Operation Under Normal & Emergency Operation Conditions ML20203A6111999-01-22022 January 1999 Confirms 990115 Conversation Between Mj Williams & P Orphanos Re Arrangements Made for Administration of Licensing Exam at Limerrick Generating Station & Peach Bottom Atomic Power Station During Week of 990705 ML20198P1761998-12-30030 December 1998 Forwards from R Calvan Transmitting FEMA Rept for Spring 1998 Peach Bottom Atomic Power Station Ingestion Exposure Pathway Exercise.No Deficiencies Identified During Exercise Conducted on 980407-09,980506 & 980519-21 ML20198K5911998-12-24024 December 1998 Forwards Emergency Response Data Sys Implementation Documents Which Include Data Point Library Updates for Fermi (Number 268),Peach Bottom (Number 269) & Beaver Valley (Number 270).Without Encls IR 05000277/19980081998-12-21021 December 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-277/98-08 & 50-278/98-08 Issued on 981028 ML20198D4071998-12-16016 December 1998 Forwards Emergency Preparedness Insp Repts 50-277/98-12 & 50-278/98-12 on 981116-19.No Exercise Weaknesses,Safety Concerns or Violations of NRC Requirements Identified 1999-09-07
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/ ~ d el JUN 1988 Docket Nos. 50-277 50-278 Philadelphia Electric Company ATTN: Mr. Corbin A. McNeill Executive Vice President-Nuclear 2301 Market Street Philadelphia, Pennsylvania 19101 Gentlemen:
Subject:
Request For Additional Information On Plan For Restart of Peach Bottom Atomic Power Station, Revisior I On April 8,1988 we received revision 1 to your "Plan for Restart of Peach Bottom Atomic Power Station (PBAPS),Section I, Corporate Action and Section II, PBAPS Action along with a schedule for completion of the corrective action activities listed in the plan. On May 19, 1988 members of our staff met with your staff in Rockville, Maryland to discuss our questions on the plan.
Attached are requests for additional information based on our review of the subject Plan. Attachment I are questions on the Plan Section I and Attach-ment II are questions on Section II.
In order for us to proceed with cur review, please provide a schedule for your response to these questions so that we can effectively plan our review and our next meeting.
Sincerely, Original Signed 37 UILL11 ; T. LUSSELL William T. Russell Regional Administrator
Enclosures:
As stated 0FFICIAL RECORD COPY ADD INFO REQ - PB RESTART PLAN -
0001.0.0 8806090053 G80601 7
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05/27/88 h DR ADOCK 0500 p % lg
Philadelphia Electric Company 2 41 JUN 888 cc w/end :
J. W. Gallagher, Vice President, Nuclear Services E. C. Kistner, Chairman, Nuclear Review Board Dickinson M. Smith, Vice President, Peach Bottom Atomic Power Station Jack Urban, General Manager, Fuels Department, Delmarva Power & Light Co.
John F. Franz, Plant Manager, Peach Bottom Atomic Power Station Troy B. Conner, Jr. , Esquire W. H. Hirst, Director, Joint Generation Projects Department, Atlantic Electric Bryan W. Gorman, Manager, Exter nal Affairs Eugene J. Bradley, Esquire, Assistant General Counsel (Without Report)
Raymond L. Hovis, Esquire Thomas Magette, Power Plant Siting, Nuclear Evaluations W. M. Alden, Director, Licensing Section Doris Poulsen, Secretary of Harford County Council Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector Commonwealth of Pennsylvania bec w/ enc 1:
Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o encl)
Section Chief, DRP Robert J. Bores, DRSS Brent Clayton, E00 i
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R RI:RA /,lp an Russe 11F 5/g88 5/ /88 0FFICIAL RECORD COPY ADD INFO REQ - PB RESTARr PLAN -
0002.0.0 05/24/88
t ATTACHMENT 1 Section I No. .Page Question P
I-1 (ES) 6 ' Explain why the. commitment to have senior management, plant management, et. al. meet with the NRB has been deleted in Revision 1.
I-2 5 Describe the accountability of other employees and workers addressed in the last topic under, item (1) which talks about ".. . employees assigned to site work locations on a permanent bases are accountable . . ."
I-3 5 -Item 2 discusses self assessment and problem resolution however, the action items concentrate on problem resolution and third party problem identifications.
Explain what line management will do themselves to identify problems and self. assess their own organization (aside from measuring progress against performance goals).
I-4 6 NRB review of organizational and personnel performance issues has been deletad from the plan. Explain who will address these issues.
I-5 9 Identify the changes to figure 1.
1-6 11 Identify the changes to figure 2.
! I-7 12 Describe key accountabilities.and responsibilities for the Senior Vice President - Nuclear as all of the other i
Executive Vice President direct reports are given in this section.
- I-B 17 Describe the process used by the Manager, Organization and i Management Development Division to monitor progress toward l meeting objectives for culture changes and how it differs from other assessments of work management ' processes.
I-9 24 Correct the inconsistency between figure 4 which shows LGS-2 construction management reporting to a Manager under l the Vice President Nuclear Engineering and figure 1 which shows LGS-2 construction management report to the Senior Vice President Nuclear.
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ATTACHMENT 1(continued)~
Section I No. Page Question I-10 27 Explain whether nuclear maintenance in Nuclear Services is really limited to nuclear activities.
I 29 Identify the changes to figure 5.
I-12 27 Explain how the long standing weaknesses in this area are expected to improve with the limited experienca and talent in the Health Physics Group.
I-13' 31 Explain.why the Manager, Nuclear Training should not be held accountable for the effectiveness of the training conducted.
i .I-14 36 Explain why the ideas of direct observation and involvement in on going activities as a way of monito' ring performance should not be added.
I-15 40 QA audits appear to be expanded in scope to include comprehensive technical and performance based factors.
Section II, Executive' Summary, page 12, states that staffing of the new site Quality organization has resulted in the recruitment and selection of a significant number
- of new experienced personnel. These statements indicate there has been an increase in QA/QC personnel on site.
Provide more information to describe the increase in personnel and scope of audits.
1-16 43-45 Describe whether the Commitment Tracking program is '
(Sec 3.5 included in the Information Management and Reporting and 3.6) Systems Program and how these two program activities differ.
,. The function of commitment management / tracking is also included in the functional organization description for the site Support Manager, the site Superintendent-l Technical and the corporate Nuclear Services division.
r Provide a description of the Commitment Tracking program including the inputs to the program, how the progress of a commitment's various elements will be followed, including l how the three groups named above will coordinate their 1- efforts, and how completion of all of a commitment's elements will be verified and documented.
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ATTACHMENT 1.(continued)-
Section I No. Page Question I-17 53 Discuss how the wide range of independent assessment methods _ir.cluding the monitoring of the independent assessment functions will work without undermining accountabilities in the line organization and without undermining the confidence that upper management places in line management.
1-18 -54 Compare NRB technical expertise with technical specification iequirements.
1-19 55 Destribe the NCB members qualifications to be able to perform the atties described in the charter and the time they will have to devote to this activity. Explain the extent of the NCB respo sibilities relative to review of the inspection reports.
I-20 57 Explain what ;s intended by private NCB meetings with the Administrator NRC Region I.
I-21 63 Activity Number CA4-1.1.3. Explain why it is acceptable to limit staffing assignment completion to the senior engineer level.
o I-22 64 Activity Number CA4-1.3.2. Explain why each position description should not state what the incumbent will be accountable for, and why the position descrirtions are limited to senior engineer level. In addition, explain how incumbents indicate their acceptance of their responsibilities and accountabilities.
I-23 65 Activity Number CA4-1.4.1. Describe to whom employees not assigned permanently to site work will be accountable. It
, is not clear how this activity accomplished the goal stated
- at the top of the page (for all those assigned to both sites permanently).
l I-24 65 Explain how the assurance of quality philosophy will be implemented.
t I-25 65 Describe the caliber of individual who will be selected to I. fill the QA positions in terms of experience, technical l
ability and QA professional experience.
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ATTACHMENT 1 (continued)-
Section I No. Page Question I-26 68 Activity Number CA4-2.7.5. Explain why performance evaluation training for supervisors should not be conducted before restart.
I-27 68 Activity Number CA4-2.8.1. Explain why written guidelines with respect to meetings, timely communications, problem identification and analysis and followup corrective ~ action activities are limited to Nuclear Service and Nuclear Engineering personnel.
I-28 69 Activity Number CA4-2.9.1 Explain how this item addresses the corrective action of "Establish interactive communications and problem solving between line management and independent assessment organizations ....."
I-29 69 Activity Number CA4-2.9.2. Justify deleting the shif t inspectors job description and reporting.
I-30 70 Activity Number CA4-3.2.3. Explain why revision 1 changed the NRB chairman from a full time back to a part time position. Describe the changes to the NRB charter.
'I-31 71 Activity Numbers CA4-3.4.1-3. Explain why these items regarding independent assessment of review and feedback processes used by independent assessment groups were deleted. In addition, describe what aspects of the restart plan will be assessed in the scheduled Self Assessment. Who will perform the Self-Assessment? Will written audit procedures or plans be used in this Self Assessment? How will these procedures or plans be prepared, reviewed and approved? How will these documents be used in the assessment. What other inputs will be used in reaching conclusions or recommendations in the Self Assessment?
ATTACHMENT 2 Section II No. Page Question II-1 18 Explain how PECo will "capture" the knowledge and experience that was lost by the personnel changes at Peach Bottom.
II-2 20 The chain of command has been shortened in going from the operators to the Vice President. Explain how the command chain has been shortened for other workers such as HP, ISEG, QA, QC, and Maintenance.
II-3 23 Project Manager, third item - Define "minor modification" and explain what coordination / review / approval will be required from the engineering group.
II-4 29 Discuss how planned job rotation of shift operators will impact a knowledge or awareness of plant and industry hi sto ry .
II-5 32 Describe the goal regarding nominal and maximum overtime to be worked by the SR0s and R0s.
II-6 38 Describe the PECo schedule for staffing licensed positions listed.
II-7 47 Explain whether this definition means to a) emphasize or b) limit assurance of quality to the workers doing a task.
II-8 53-54 Explain why the activities in the omitted paragraphs, such as meetings in small groups with development of recommendations and feedback were deleted.
II-9 59 Describe the "underlying attitudes" that promoted unaccep-table behavior in the control room. Explain why the MAC problem root cause assessment should not be included as an appendix or by reference for completeness of response to tne Order as it was in the earlier CTE plan.
II-10 61 Provide a schedule for the followup Peach Bottom simulator shift team training.
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ATTACHMENT 2 (continued)-
Section II No. Page Question
'II-11. 63 -We understand that approximately 20% of the comments provided to "Tell it to the Manager" have.not been responded to. Provide your evaluation of the impact of this on the program effectiveness.
II-12 67 Describe the infractions that were the cause of the personnel terminations made by the Plant Manager. Explain why the action was taken at the Plant Manager level.
II-13 68 Describe the implementation of the performance evaluation system for 1987.
II-14 69 The criteria listed for procedure revision requirement all use the word "would", "would result in misoperation",
" . . .would compromise . . . safety" rather than "could "
Explain the use of "would" instead of "could."
II-15 70 Explain why the criterion of understandability was not used for procedures upgraded prior to restart II-16 71 Second paragraph. Describe what procedures are the-
"specified procedures".
.II-17 72 Explain how improvements to support procedural compliance address the subject of ease and mechanisms of making both temporary and permanent changes to procedures.
Describe the temporary procedure change process. Explain when it can be used. Describe how it is intended to be used.
11-18 74 Explain why the four work management processes being assessed for improvement should not be completed prior to restart.
II-19 75 Define what is meant by "key plant systems" and explain why the preventive maintenance system should not be completed prior to restart.
II-20 79 Provide a clearer description of "The Nuclear QA management team (s)", the team (s) composition, and the team (s) responsibilities.
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ATTACHMENT 2 (continued)
Section II No. Page Question II-21 87 Activity Number CA1-1.1.1. Explain why selection of qualified candidates is limited to superintendent level a,id up.
11-22 88 Activity Number CA1-2.2.1. Explain how the reorganization of control room work activities will provide for increased backshif t activity to further assure operator alertness.
II-23 89 Activity Number CA2-1.1.1. Explain how PECo management will determine that each operating crew is ready for plant restart. Describe whether the process will include certification on the Peach Bottom simulator and whether the certification will verify completion of training on revised procedures, the operations administration manual and the watchstanders manual. Describe the training on these procedures and manuals.
II-24 89 Activity Number CA2-1.2.1. Describe the schedule for implementing higher entry standards and appropriate compensation schedules for recruitment and hiring of future licensed operator candidates.
11-25 89 Activity Number CA2-1.2.2. Provide plans for additional operator training to provide ongoing reserve of licensed operators. Explain how and when the Peach Bottom simulator will be used to certify licensed operator candidates.
II-26 89 Activity Number CA2-1.3.1. Explain whether th:1 blocking and support group rotates with the shift crew and when this group will be staffed.
II-27 89 Activity Number CA2-1.3.2. Explain who comprises the work control group, and describe their responsibilities and qualifications. Describe the extent to which they establish work priorities and when the group will be staffed.
II-28 90 Activity Numbers CA2-2.2.1 and 2. Describe the scheduled goal for implementing selected degree and certificate programs.
J ATTACHMENT 2.(continued)
Section 2
- No. Page- Question II-29 92 Activity Number CA3-2.1.3. In addition.to training for managers / supervisors developed as a result of a "training needs assessment survey", explain how a formalized training program for managers / supervisors will address:
(1) How to coach and support subordinate levels of supervision, (2) How to evaluate training program effectiveness of subordinate staff, and (3) How to reinforce training given to subordinate staff.
Describe the schedule for developing and implementing a :
manager / supervisor training program following the training needs assessment survey.
Explain the similarities and differences between the Manager Training Program, PFE and MFE, and the reasons for them. Explain how the Manager / Supervisor Training Program will relate the Technical Staff / Manager Training area of the Accreditation Program. . Provide the Manager / Supervisor Training Program syllabus.
Describe processes in place to ensure that the nuclear training organization receives regular input from plant management about training needs and the effectiveness of training programs.
Describe the training (similar to PFE, MFE, PE and TEAM) that will be developed for new hires and for transfers from other parts of PECo.
II-30 92 Activity Number CA-3-2.2.2. In addition to a PFE for first and second line supervisory personnel, describe what similar training will be given to non-operations personnel below supervisory level and why it should not be complete prior l
to restart, t
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e ATTACHMENT 2 (continued)
Section II No. Page -Question:
'II-31' 92 Activity Number CA3-2.2.3. Explain why manage- supervisors-should not be trained on conducting face-to-face performance appraisal interviews prior to restart. In addition to training for managers / supervisors on conducting. face-to-face performance appraisal interviews, describe the training they will receive on writing performance standards and on writing effective performance evaluations.
II 92 Activity Number CA3-2.2.4. Explain why the training on disciplinary policies and work rules should not be completed prior to restart.
II-33 92 Activity' Number CA 3-3.2.1. Explain how the licensed operator traini .g program addresses a supervisory / leadership curriculum. Provide the training syllabus.
II-34 94 Activity Number CA3-3.4.1. Describe the followup PFE and MFE training. D ovida a schedule for and syllabus of this followup training.
II-35 95 Activity Number CA3-3.7.2 Describe the followup processes in place to respond to suggestions / recommendations / concerns made by the employee involvement program (P.B TEAM).
II-36 95 Activity Number CA3-3.7.3. In addition to meetings of the Plant Manager with Superintendents, Assistant Superintendents, Senior Engineers and Lead Vendor personnel to discuss work
. priorities, work progress and problem areas, describe any regularly scheduled meetings station management has with shift managers.
II-37 95 Activity Number CA3-3.7.4. Describe the organizational survey, and feedback process. Describe whether this survey focused on PECo or on Peach Bottom. Explain how the survey met the intent of the MAC recommendation.
The PBAPS Action Plan states that 15% of-PBAPS managers, first line supervisors and employees participated.
(1) Were the number of people surveyed from each group 15% of the total number of employees in that group? If not, explain how the 15% was distributed across groups.
ATTACHMENT 2 (continued)
Section II No. Page Question (2) In addition to managers and 1st line supervisors receiving the survey data and making recommendations, will employees who participated in the survey have the survey results reported to them and will they have the ability to make recommendations (i.e. , beyond discussing the manager's and first line supervisor's recommendation).
(3) Provide the results of the organizational survey and managements' response to the survey items.
II-38 95 Activity Number CA3-4.1.2. Describe the processes used to communicate the disciplinary and grievance policies to site employees, and to respond to questions / classifications.
Describe what tracking procedure has been developed to ensure that each step in the grievance process has been accomplished.
Describe the generic schedule to ensure timely resolution of grievances.
II-39 96 Activity Number CA3-4.3.1. Describe the schedule established for developing performance standards for each employee and for coaching employees on their role in the performance evaluation process. Explain why more frequent performance evaluations should not be conducted until employee performance has stabilized (e.g. every six months) as one way of monitoring / evaluating the continuation of positive av.titudes/ culture changes among the managers /
supervisors / staff.
II-40 95 Activity Number CA3-4.4.1. Describe the formal procedure change initiation process and the process for developing new procedures, and the schedule for turn-around time from operator feedback through accomplishment.
II-41 97 Activity Nutber CA3-4.4.4. Explain why all training on revised procedures should not be complete prior to restart.
Describe the tracking system for ensuring that new and revised procedures are incorporated into training programs.
ATTACHMENT 2 (continued)
Section II No. Page Question 11-42 97 Activity Number CA3-4.4.7. Explain why all procedures p should not be reviewed prior to restart.
11-43 98 Activity Number CA3-4.5.1. Identify the areas in which site quality crganizations and the site line organization have improved working relationships.
11-44 98 Activity Number CA3-4,5.2. Explain why continuous QA/QC monitoring of operating activities should not be continued during restart of both units. Indicate how the appropriate level of QA coverage for ongoing operations at PBAPS will be determined.
Provide a schedule for operations training of nuclear QA personnel.
11-45 98 Activity Number CA3-4.5.3. Clarify how developing a technically based audit program within Nuclear Operations QA has contributed to self-assessment efforts within site operations. Specify what important areas for improvement have been identified and any resulting improvements.
Describe the standards set in the 1988 Nuclear QA Goals which assure the maximization of performance based audits and surveillances.
Describe improvemer.ts which have been made in the processes and formats by which Nuclear QA reports independent assessment feedback to site and corporate management.
II-46 98 Activity Number CA3-4.5.4. Explain when improved QA reporting practices will be in place.
II-47 99 Activity Number CA3-4.6.7. Describe the schedule for development and implementation of interface agreements between site training and corporate training departments.
11-48 99 Describe the processes established for: identifying problems, developing corrective actions, tracking corrective action commitments, and evaluation of effectiveness of actions.
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ATTACHMENT 2 (continued)
Section II No. Page Question II-49 99 Describe the schedule for assessing work management processes and implementation of recommended changes in these processes.
11-50 99 Activity Number CA3-4.6.8. Explain when the Nuclear Performance Management Program will be in place.
11-51 103 Explain why shutdown issue number 9 involving a management focus on compliance rather than acknowledgement and correction of the root causes of problems is not correlated with root cause number one involving a lack of adequate personal leadership skills on the part of senior management at the plant.
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