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| | number = ML20062C508 | | | number = ML20062C508 |
| | issue date = 10/24/1990 | | | issue date = 10/24/1990 |
| | title = Responds to NRC 900914 Ltr Re Violations Noted in Insp Repts 50-277/90-14 & 50-278/90-14.Corrective Action:Individual Involved W/Event Counseled Re Failure to Adhere to Tech Spec 9.12, Reactor Vessel Temp. | | | title = Responds to NRC Re Violations Noted in Insp Repts 50-277/90-14 & 50-278/90-14.Corrective Action:Individual Involved W/Event Counseled Re Failure to Adhere to Tech Spec 9.12, Reactor Vessel Temp |
| | author name = Miller D | | | author name = Miller D |
| | author affiliation = PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC | | | author affiliation = PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
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| | contact person = | | | contact person = |
| | document report number = NUDOCS 9011010001 | | | document report number = NUDOCS 9011010001 |
| | | title reference date = 09-14-1990 |
| | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE |
| | page count = 7 | | | page count = 7 |
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| ==Dear Sir:== | | ==Dear Sir:== |
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| In response to your letter dated September 14, 1990 which transmitted the subject Inspection Report and Notice of Violation, we submit the attached response. The subject Inspection report concerns a routine resident safety inspection conducted during the period July 3, 1990 through August 13, 1990. | | In response to your {{letter dated|date=September 14, 1990|text=letter dated September 14, 1990}} which transmitted the subject Inspection Report and Notice of Violation, we submit the attached response. The subject Inspection report concerns a routine resident safety inspection conducted during the period July 3, 1990 through August 13, 1990. |
| ! If you have any questions or require additional information, please do not hesitate to contact us. | | ! If you have any questions or require additional information, please do not hesitate to contact us. |
| Sincerely. | | Sincerely. |
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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: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
_ _ _ . _ __ .. . _ _ _ _ __ __ _. _ . - -- _ _ _ _ _ _ _ _ _ _ _
CCN'Co-141204 To PHILADELPHIA ELECTRIC COMPANY kh3 PIACil DCTFIIBl ATOMIC MMTR STATION R D. I, Ika 208
_in Delta, Itnmylvania 17314 rucs mornw-im rowia or a u sun ws pl?) 456 7014 D. B. Miller, Jr.
Yke President I
l October 24, 1990 10 CFR 2.201 Docket Nos. 50-277 50-278 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 i
SUBJECT:
Peach Bottom Atomic Power Station - Units 2 & 3 Response to Notice of Violation (Combined Inspection Report Nos. 50-277/90-14;50-278/90-14)
Dear Sir:
In response to your letter dated September 14, 1990 which transmitted the subject Inspection Report and Notice of Violation, we submit the attached response. The subject Inspection report concerns a routine resident safety inspection conducted during the period July 3, 1990 through August 13, 1990.
! If you have any questions or require additional information, please do not hesitate to contact us.
Sincerely.
Attachment '
f l
l cc: R. A. Burricelli, Public Service Electric & Gas T. M. Gerusky, Commonwealth of Pennsylvania J. J. Lyash, USNRC Senior Resident ^ Inspector T. T. Martin, Administrator, Region I, USNRC H. C. Schwemm. Atlantic Electric R. I. McLean, State of Maryland J. Urban, Delmarva Power
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, Dscument Control Desk 4
10/24/90 Page 2 bec: J. A. Basilio 52A-5, Chesterbrook
, J. A. Bernstein 51A-13. Chesterbrook R. N. Charles 51A-1 Chesterbrook Commitment Coordinator 52A-5, Chesterbrook 4 Correspondence Control Desk 61B-3, Chesterbrook E. J. Cullen S23-1 Main Office ,
A. D. Dycus A3-15 Peach Bottom E. P. Fogarty A4-4N, Peach Bottom J. F. Franz A4-1S, Peach Bottom A. A. Fulvio A4-15. Peach Bottom D. R. Helwig 51A-11, Chesterbrook G. A. Hunger 52A-5, Chesterbrook R. J. Lees, NRB 53A-1 Chesterbrook J. M. Madara $3A-1, Chesterbrook C. J. McDermott S13-1 Main Office D. B. Miller, Jr. SMO-1. Peach Bottom PB Nuclear Records A4-2S Peach Bottom J. M. Pratt B-2-S, Peach Bottom L. B. Pyrih 638-5, Chesterbrook J. T. Robb 51A-13. Chesterbrook D. M. Smith 52C-7, Chesterbrook 0
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l Document Control Desk 10/24/90 Page 3 l
Attachment
- Response to Notice of Violation 90-14-01 Restatement of Violation A. Technical Specification (TS) 6.8.1 ri.luires establishing and implementing written procedures that meet the requirements of Sections 5.1 and 5.3 of ANSI N18.7-1972, and Appendix A of Regulatory Guide (RG) 1.33 (November 1972). Contrary to the above, on three occasions during the inspection period operations personnel did not adhere to established procedures for equipment monitoring and operation. Specifically:
A.1 Appendix A of Regulatory Guide 1.33 Section G.4.A. requires procedures for mechanical vacuum pump operation. Abnormal .
operating procedure A0 8.2-3, "Off-Gas System Operatica During Controlled Shutdown if High Off-Gas Activity Exists," Revision 0, provides the sequence of actions needed to place the mechanical vacuum pump in service.
Contrary to the above, on July 27, 1990, licensed operators deviated from the sequence contained in the procedure, by opening the vacuum breaker prior to starting the mechanical vacuum pump, which led to a small release of radioactive gas into the turbine building and later to the environment through the reactor building ventilation stacks.
A.2 Section 5.3.3 of ANSI N18.7-1972 requires procedures for shutting down and changing modes of operation for systems related to the safety of the plant. System operating procedure I S0 400.7 A. " Restoration of Control Room Ventilation following a.
High Radiation Trip," Revision 1, requires placing the control switches for the six normal supply fans to 'off' before resetting a trip of the control room ventilation supply u radiation monitors. ,j Contrary to the above, on July 30, 1990, a. licensed operator reset the 'B' control room radiation monitor before placing the i fan control switches to the 'off' position. This action caused safety-related equipment to return to its normal mode following reset of an engineered safety feature actuation signal.
A.3 Section 5.3.4.2 of ANSI 18.7-1972 requires procedures for monitoring cooldown rates. TS 4.6.A.1 requires logging both recirculation loop temperatures during cooldown. Surveillance-test procedure ST 9.12. " Reactor Vessel Temperatures," Revision 15, requires logging recirculation loop-. temperatures every 15 minutes during cooldown until temperatures stabilize.
' Document Control Desk 10/24/90 Page 4 Contrary to the above, on July 27, 1990, licensed operators did not log the 3 'B' recirculation loop temperature during a plant cooldown for about 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. This is the second recent
, occurrence of failure to implement procedure ST 9.12 properly.
This is a Severity Level IV Violation (Supplement 1). '
Cause of the Violation (A.1) ,
Following the manual scram of Unit 3 due to a recombiner off-gas isolation, operations personnel concentrated their efforts on restoring main condenser vacuum aad resetting the isolation. At the same time operations and shift management decided to prepare the mechanical vacuum pump (MVP) for operation in case the recombiner could not be returned to service. The normal system alignment for the MVP required that the Condenser Off-Gas to MVP valves be closed. Contrary to normal alignment, the three Condenser Off-Gas to MVP valves had been opened during power operation to increase first stage Steam Jet Air Ejector (SJAE) performance. These open valves were listed on the Abnormal Equipment Status List.
The MVP was prepared for operation utilizing Abnormal Operating Procedure (AO) 8.2-3, Revision 0, "Off-Gas System Operation During Controlled Shutdown if High Off-G6s Activity Exists". During this time, the Shift Supervisor became concerned that the MVP could become damaged if the water in the vacuum breaker seal was drawn into the MVP when started.
The Shift Supervisor deviated from procedure and directed that the vacuum breakers be opened. Opening the vacuum breakers resulted in release of seal water and non-condensable gases into the MVP room and ultimately the turbine building. The vacuum breakers were then immediately closed. it was later determined that the condenser had actually been slightly pressurized, although the condenser vacuum gauge read 0" Hg. This, in connection with the open Condenser Off-Gas to MVP valves, provided a direct flowpath to the MVP room and turbine building from the pressurized condenser. This resulted in contamination of the MVP room, the turbine building becoming radioactively airborne, and the release of non-condensable gases through the roof vents.
Corrective Actions Taken and Results Achieved An event investigation was promptly initiated to' evaluate the incident. The manufacturer of the mechanical vacuum pump, Nash Engineering was contacted 1
about the Shift Supervisor's concerns. The manufacturer stated that the MVP <
utilizes seal water as a liquid compressant to draw a vacuum and that- ,
additional water from the vacuum breaker seals would not damage the MVP. 1 During the course of this investigation, the implications of this event.were '
discussed with the Shift Supervisor involved. This information and a summary of this incident with corrective action dispositions was included in a Licensed Operator Required Reading Package issued 10/22/90.
An evaluation was performed on A0 8.2-2(3) to determine if the procedure should be revised to clarify how the MVP is placed in service with the water i seals already established. After reviewing the event and the procedure.it was:
b Document Control Desk 10/24/90 Page 5 determined that a revision is not required. It was concluded that if the procedure had been properly followed, the off-gas would not have been released into the turbine building.
Cause of Violation (A.2)
- On July 30, 1990 after receiving a spurious control room ventilation high '
i radiation signal, the normal control room ventilation fans tripped and the system isolated. The emergency control room ventilation then initiated.
System Operating procedure (50) 400.7.A. " Restoration of Control Room Ventilation following a High Radiation Trip. ' Revision 1, requires that the normal control room ventilation fans be placed in the off position prior to the reset of the isolation. Contrary to 50 400.7.A. Operations personnel failed to place these fans in the off position prior to resetting the isolation. This resulted in the normal ventilation fans returning to operation after the isolation reset. Failure to use this procedure was the cause of this incident. A contributing cause was believed to have been the simplicity of the procedure ind several recent occurrences of other spurious high radiation signals that created a mindset of familiarity with the procedure.
Corrective Actions Taken and Results Achieved The importance of procedure compliance was stressed to the Operations personnel involved in this incident and expectations of job performance were reaffirmed. ,
Operations Management issued a letter on August 21, 1990 to Shift Operations personnel addressing the reset of control room ventilation isolations. This correspondence emphasized the necessity of performing operator functions in full compliance with appropriate procedures and having those procedures in hand.
Additionally, information was distributed to operations personnel on August 23, 1990 which further stressed the importance of having the procedure in hand and assuming an active self-checking role. This letter referenced incidents that would have been prevented if the appropriate procedures had been followed.
Cause of Violation (A.3)
On July 27, 1990 after the Unit 3 scram, a Reactor Operator began logging-temperature readings for the Reactor Bottom Head Drain, "A" Recirculation Loop, and "B" Recirculation Loop as required by ST 9.12. " Reactor Vessel Temperature". The temperature readings are required to be taken at least once every 15 minutes during heatup or cooldown as directed by Technical Specification 4.6.A.1 and ST 9.12. Shift Supervision verified that logging these temperatures had been appropriately initiated after the scram. On July ,
28, 1990, while attempting to equalize recirculation loop temperatures, an excessive heatup of the "B" Recirculation Loop occurred. it was discovered during the heatup investigation that the temperature of the "B" Recirculation Loop was not recorded for a period of about 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> during the plant cooldown
"D:cument Control Desk 10/24/90 Page 6 on July 27, 1990. The failure to log the "B" Recirculation loop temperature was a combination of personnel error, inadequate human factors of ST 9.12, and poor communications. Although ST 9.12 requires that the temperature readings be recorded during cooldown or heat-up conditions, Operations personnel thought it was not applicable since the "B" Recirculation Loop was not in service and they considered the temperatures to not accurately represent the coolant or vessel conditions. A note in the body of the procedure specified that temperature readings be recorded every 15 minutes during reactor heatup or cooldown, regardless of equipment status, until the temperature remains constant. This information, however was not contained on the data sheets.
Most Operations personnel were also not aware that ST 9.12 had been revised in response to a previous similar event which required recording of idle recirculation loop temperatures.
Corrective Steps Taken and Results Achieved An investigative report was immediately initiated to evaluate the causes of this incident and the corrective actions needed. These causes and corrective actions were reported in LER 3-90-09.
The individual involved with this event was counselled concerning the failure to adhere to ST 9.12. " Reactor Vessel Temperature."
The data sheets of ST 9.12 were revised on 8/30/90 to include appropriate instructions at the top of each sheet. This revision has added consistency between the procedure and the data forms and provides guidance while r performing the procedure.
The information and results of this incident have been distributed to appropriate Operations Shift personnel. Operations Support personnel and Operations Management personnel for review.
Corrective Actions Taken To Avoid Future Violations in addition to the specific corrective ac+ Mns taken for each violation, the Plant Manager designated a special commt> to initiate an investigation into the issue of inattention to detail. Thh anmittee was tasked to analyze and evaluate appropriate source documents and to interview plant personnel for added insight into the problem. A status update of the committee's progress was discussed at the Fall Supervisory Meeting held October 3, 1990. During this meeting the Plant Manager and other management personnel stressed the importance of procedure compliance and attention to deNil. The final committee report and recommendations to resolve this issue are currently under review by the Plant Manager. Corrective actions will be taken as appropriate to address these reconnendations.
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Date When Full Complia3ce Was Achieved full compliance was ac'aieved for Violation A.1 on July 27, 1990 when the vacuum breakers were reclosed. Full compliance was achieved for Violation A.2 i on July 30, 1990 w!.en the normal ventilation was appropriately restored to service. Full cc:npliance was achieved for Violation A.3 en July 28, 1990 when the temperature for the 3B recirculation loop was logged on ST_9.12-1 and continued to be recorded for the remainder of the cooldown. ;
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