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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: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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.. November 25, 1996 Mr.- D. M. Smith,' President PECO Nuclear Nuclear Group Headquarters-Correspondence Control Desk P. O. Box 195 Wayne, Pennsylvania 19087-0195 SUBJECT: COMBINED INSPECTION REPORT NOS. 50-277/96-04; 50-278/96-04
Dear Mr. Smith:
This. refers to your September 5,1996 correspondence, in response to our August 6,1996 letter.
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Thank you for informing us of the corrective and preventive actions documented in your letter.
These actions will be examined during a future inspection of your licensed program.
t Your cooperation with us is appreciated. ,
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Sincerely, t
ORIGINAL SIGNED BY:
Walter J. Pasciak, Chief
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Projects Branch 4 l
Division of Reactor Projects l
Do':ket Nos. 50-277; 50-278
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Mr. cc: l T. Mitchell, Vice President G. Rainey, Senior Vice President, Nuclear Operations G. Edwards, Plant Manager, Peach Bottom Atomic Power Station !
D. Fetters, Vice President, Nuclear Station Support I G. A. Hunger, Jr., Chairman, Nuclear Review Board and Director, Licensing )
J.W. Durham, Sr., Senior Vice President and General Counsel T. Neissen, Director, Nuclear Engineering Division G. Lengyel. Manager, Experience Assessment cc w/cy of licensee's ltr:
C. D. Schaefer, External Operations - Nuclear, Delmarva Power & Light Co.
B.W. Gorman, Manager-External Affairs, Public Service Electric & Gas Co. !
P. MacFarland Goelz, Manager, Joint Generation, Atlantic Electric '
R. McLean, Power Plant Siting, Nuclear Evaluations J. H. Walter, Chief Engineer, Public Service of Maryland R. Ochs, Maryland Safe Energy Coalition J. Vannoy, Acting Secretary of Harford County Council L. Jacobson, Peach Bottom Alliance TMI - Alert (TMIA)
Nuclear Safety Information Center (NSIC)
NRC Resident inspector l Commonwealth of Pennsylvania i State of Maryland
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l Mr. i Distribution w/cy of licensee's itr:
Region l Docket Room (with concurrences)
W. Dean, OEDO J. Shea, NRR J. Stolz, PDI-2, NRR Inspection Program Branch, NRR (IPAS)
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PUBLIC D. Screnci, PAO
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l DOCUMENT NAME: a: reply.pb "E" = Copy with attachment / enclosure To receive a copy of this do nt. Indicate in tl's box: "C" = Copy without attachment / enclosure
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OFFICE RI:Df)P p // lA/ RI:DRP l NAME WPe%gfak///
DATE a1/ eff 96/
OFFICIAL RECORD COPY f
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PECO NUCLEAR ni L"Tft"*"" .
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$745$jN 2 Fax 717 456 4243 September 5, 1996 ,
Docket Nos. 50-277 50-278 License Nos. DPR-44 DPR-56 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Subject: Peach Bottom Atomic Power Station Units 2 & 3 Response to Notice of Violation (Combined Inspection Report No.
50-277/96-04 & 50-278/96-04)
Gentlemen:
In response to your letter dated August 6,1996, which transmitted the Notice of Violation concerning the referenced inspection report, we submit the attached response. The subject report concerned a Routine Resident Integrated Safety inspection that was conducted May 5 through July 6,1996.
If you have any questions or desire additional information, do not hesitate to contact us.
b + $# VM Thomas N. Mitchell Vice President,
Peach Bottom Atomic Power Station Attachments I
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cc: B. W. Gorman, Public Service Electric & Gas R. R. Janati, Commonwealth of Pennsylvania
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H. J. Miller, US NRC, Administrator, Region I W. L. Schmidt, US NRC, Senior Resident inspector H. C. Schwemm, VP - Atlantic Electric
R. I. McLean, State of Maryland A. F. Kirby 111, DelMarVa Power
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CCN#96-14073 7-
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RESPONSE TO NOTICE OF VIOLATION Restatement of Violation Technical specification 5.4.1 requires, in part, that written procedures be implemented to cover technical specification required surveillance testing, operation of the reactor I protection system, and for maintaining secondary containment integrity.
Contrary to the above, PECO did not properly implement written procedures for:
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Technical specification required testing on a control room emergency ventilation system filter train. Specifically, on May 9,1996, PECO contractor technicians, under the supervision of a PECO maintenance technician, did not implement procedure ST-M-40D-905-2 properly.
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Operation of the reactor protection system. Specifically, on May 22,1996 a plant equipment operator did not properly implement procedure SO 60F.6.A-2 dunng restoration of the 2B reactor protection s loss of power and a half reactor scram. ystem motor generator set, resulting in a
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Maintaining secondary containment integrity. Specifically, on June 12, a chemistry technician did not implement procedure A-C-134 properly, resulting in an improperly controlled breach of the secondary containment.
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This is a Severity Level IV violation (Supplement 1).
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/ r Reason for the Violation (Example 1)
On May 9,1996, at approximately 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />, ST-M-40D-905-2, Control Room Emergency Ventilation Filter Train 'A' Test, was identified as being performed out of sequence. ST-M-40D-905-2 is a Level 1 procedure which requires the procedure to be in hand, and the performance and completion of steps to be documented as they are )
performed. The filter train test was being perfomled by an outside contractor with the '
support of Peach Bottom Atomic Power Station (PBAPS) maintenance. The contractor is utilized for their expertise on charcoal filter train testing, results analysis, knowledge of safety-related ventilation systems and the regulatory requirements of these systems. The vendor performs these tests with generic procedures and guidelines developed by the vendor for these tasks. PBAPS has specific surveillance tests that delineate the steps required to perform the filter testing. The result of this process was that the PBAPS
, maintenance procedure and the vendor procedure did not agree with respect to sequence and chronological order of the steps. The testing was performed on the filter train until the evolution was questioned by the NRC resident inspector. The testing was
' stopped and reviewed by the maintenance technicians, maintenance supervision and the i vendor. It was determined that the Control Room Emergency Filter Train ST was not I i being performed as written.
Corrective Steps That Have Been Taken and the Results Achieved
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- Upon discovery of the issue, the test was stopped and the procedure was revised using the Temporary Procedure Change process. Vendor personnel assisted in this process to
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ensure that the PBAPS ST was revised to the proper test methodology and sequence. l The temporary change and permanent revision to the procedure was approved and the I
- test completed satisfactorily at 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br /> on May 9,1996.
A meeting was held with the work team on August 2,1996 where management expectations and requirements of A-C-79 were communicated. The maintenance division also conducted an all-hands meeting on August 9,1996 to discuss this issue and communicate management expectations for procedure usage and compliance.
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A review of other procedures associated with vendor test performance was performed.
Several procedures were identified with similar situations of potential conflict and 1 Procedure Problem Identification Process (PPIS) action items were initiated to resolve these issues.
Corrective Steps That Will Be Taken to Avoid Further Violations i Vendor input and comment will be obtained prior to test performance to ensure station procedures are consistent with vendor and industry practices. Appropriate procedures will
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be revised prior to test performance to ensure consistency.
l Date When Full Compliance Was Achieved '
Full compliance on ST-M-40D-905-2 was achieved on May 9,1996 when the test procedure was revised to sequentially correspond to the activities required to be performed. The test was then satisfactorily performed and completed.
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Beason for the Violation (Exampic 2)
On May 22,1996, at approximately 1305 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.965525e-4 months <br />, an unexpected loss of the Unit 2 'B' RPS power supply occurred when an equipment operator mispositioned the voltage
< adjustment rheostat for the RPS Attemate feed transformer. The operator was required, per procedure SO 60F.6A-2," Transferring Reactor Protection System Power Supplies",
to adjust the 'B' RPS MG set rheostat to set-up the 'B' RPS MG set for return to service from maintenance. A pre-job briefing was conducted and the operator was instructed on the appropriate sequence of restoration. The operator proceeded to walk down the SO to ensure he was familiar with all of the locations for restoration, specific actions required, and test equipment installation points. After this evolution was complete, he returned to the 'B' RPS MG set and verified appropriate steps in the SO. The next task described in
the SO was to adjust the rheostat on the 'B' RPS MG set. Instead, the operator
! proceeded to the RPS Alternate feed and turned the rheostat for the RPS Alternate feed i
thus causing the unexpected transient. The cause of this event was the failure of the
operator to follow SO 60F.6.A-2. This resulted in an unanticipated unit half scram and an outboard Group Ill PCIS isolation which required a four hour notification to the NRC.
, Corrective Steos That Have Been Taken and the Results Achieved
Upon loss of the alternate RPS feed, the operating shift investigated the cause of the
- transient and restored the RPS feeds in accordance with station procedures.
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The equipment operator was counseed on the expectation to adhere to procedures, be l aware of his surroundings and to fully a plement self-check techniques.
j Corrective Stens That Will Be Taken to Avoid Further Violations The corrective steps that have been initiated as a result of this event will serve to avoid further violations.
Date When Full Compliance Was Achieved i
' Full compliance was achieved on May 22,1996, when the RPS feeds were returned to normal.
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, Reason for the Violation (Exampb 3)
On June 12,1996, at approximately 1005 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.824025e-4 months <br />, the hatch between the Unit #3 refuel ,
floor and the refuel floor roof was propped open to allow access to the roof for '
performance of CH-428," Main Stack and Vent Stack Sampling System Efficiency Determination". Personnel performing this test believed that the only procedural requirement to open the hatch was to have a security guard present. They were not aware that propping this door open resulted in a violation of secondary containment even though this hatch was posted as an A-C-134, " Control of Hazard Barriers" hatch. The security guard also failed to recognize the consequence of propping the hatch door open and the potential to impact secondary containment integrity. This work activity should have been controlled by A-C-134 and GP-16 " Breaching and Establishing Secondary Containment". These procedures do not allow a secondary containment door to be propped secondaryopen without specific controls put in place to ensure compliance with maintaining containment.
Corrective Steps That Have Been Taken and the Results Achieved Upon discovery, the following actions were taken. The hatch to the roof was immediately closed and shift management was notified. Personnel working on the roof were briefed on A-C-134 requirements and the need to keep the hatch closed for secondary containment operability. The security guard was also briefed to ensure the hatch remained closed for secondary containment operability, except for brief passage.
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An evaluation was performed to determine if secondary containment had been compromised during this event. The evaluation concluded there was sufficient margin to ensure the safety function of secondary containment was maintained.
An all-hands meeting was held with the chemistry staff to address the issues of A-C-134 and GP-16 ar.d the need to properly maintain hazard barriers closed except for passage and the neea to ensure secondary containment is maintained.
Nuclear security group issued a bulletin to all security personnel to ensure that designated and posted as A-C-134 doors are not propped open. In addition, the locks to the refuel floor roof hatches have been changed which require a specific key to open these hatches. This key is only issued by nuclear security and contains a tag which warns not to open these hatches without GP-16 and shift supervision's authority.
Procedure CH-428 was revised, using the temporary procedure change process, to obtain permission from shift management to temporarily breach secondary containment in accordance with GP-16 and A-C-134. CH-428 was then permanently revised to reflect the same requirements in the prerequisite section of the procedure as well as adding precautionary notes in the procedure sections that require roof access.
GP-16 was revised to render secondary containment inoperable in modes 1(Power Operation),2(Startup), and 3(Hot Shutdown) as a result of opening either the Unit #2 or
- 3 refuel floor hatch to reactor building roof.
The information and causes of this issue were provided to site-wide work groups. Action items were issued to site groups to ensure review of this issue and an understanding A-C-134 and its requirements, as well as the need to control secondary containment as it relates to the PBAPS design basis.
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Corrective Steos That Will Be Taken to Avoid Further Violations The corrective steps that have been initiated as a result of this event will serve to avoid further violations.
Date When Full Compliance Was Achieved Full compliance was reached at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on June 12,1996, when the hatch to the Unit
- 3 refuel floor roof was closed.
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