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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
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PECO NUCLEAR A Unit of PECO Energy nm e. co--
%citar Group H040 Quarters ;
36 esjerggu p
March 26,1999 Docket No. 50-277 50-278 License No. DPR-44 DPR-56
. U. S. Nuclear Regulatory Commission Attn: Document Control Desk )
Washington, DC 20555
SUBJECT:
Peach Bottom Atomic Power Station, Unit UM53' 23 Request for Enforcement Discretion Conceming an Inoperable Diesel Generator
Dear Sir / Madam:
As discussed with the NRC on March 26,1999. PECO Ene.rgy Company he requests Enforcement Discretion (ED) from the recuirements of Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3 Tec1nical Specifications (TS). l This Enforcement Discretion is being pursued to avoid an unnecessary plant transient l The reque(i.e., a plant shutdown) whicl1 would result from compliance with tI sted relief is non-recurring and of short duration, '
In accordance with the guidance contained in NRC Administrative Letter 95-05, Revision 1, " Revisions to Staff Guidance for implementing NRC Policy on i Noticec of Enforcement Discretion," and Part 9900 of the NRC Inspection Manua'. ie following information is provided:
~1)
The TS or other license conditions that will be violated.
Limiting Condition for Operation 3.8.1.b ("AC Sources - Operating") for the Peach Bottom Atomic Power Station (PBAPS , Units 2 and 3 Technical Specifications requires that four diesel genera) tors be capabl the onsite Class 1 E AC electrical power distribution system while in Modes 1,2, and 3. As discussed in Condition B, with one diesel generator inoperable Required Action 8.5 requires that the diesel generator be restored to operable status within a Completion Time of 14 days from the discovery to meet 3.8.1.b. Otherwise, with this Condition not met within the specified Completion Time, Condition G requires that the Units must be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Mode 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
This Enforcement Discretion (ED) requests a one-time. 3 day extension, from Required Action B.5 which requires that the one inoperable diesel generator be restored to an operable status within the Completion Time of 14 days. i 9904090163 990401 L PDR ADOCK 05000277 P PM
)
n 1
s . l l
i -
March 26,1999 Page 2 I diesel generator, a 3 day extension is requested i
remaining testing associated with the diesel generator outage cur progress at PBAPS, Units 2 and 3. This extension is necessary in order !
to avoid an undesirable transient resulting from the shutdown of both Unns.
2)
The circumstances surroundino the situation. includino ao
! causes. the need for oromot action and identification of any relevant historical events.
! No#
! On March 14,1999, at 1AWhours, an outage to perform a 24 month planned to occur over a 7 day period working 2 ,
I actual work was planned to occur over a 5 day work window, with an additional day for testing, and an additional day for unplanned contingencies. As a part of this diesel generator outage, the govemor an
! the Jacket water bypass gaskets were to be replaced. This is the first tim that the gaskets were replaced in the life of the diesel. Previously, a was identified in a gasket in the Jacket water system, in order to preven future Jacket water leaks, it was considered a prudent action to repla the gaskets. This evolution involved the replacement of 48 gaskets. The gaskets were replaced in-kind, which one would expect would be an began on Wednesday, March 17,1999. appropriate, prudent test, a leak was identified in one gasket on Saturday, March This gasket was replaced. During the first diesel run on Sunday. Marc 21,1999, a different gasket failed. At that time it was determined that all 48 gaskets would be replaced utilizing a different installation method. All gaskets were replaced.
During the second test run on Tuesday, March 23,1999 a different
/ gasket failed. All gaskets were replaced again, however, with a different gasket material and sealant. This activity was performed in accordance ith an approved Engineering evaluation.
pp,f The gasket failures were the result of the gaskets slipping out of their connections. The root cause for the failure of the gaskets has been attributed to the gasket material which could not adequately seal the being used,In addition to the new gasket material, a permatex sealant is surfaces.
'q*@ Due to the unanticipated time necessary to correct the gasket failures, an
% additional 3 days is requested in order to complete the remaining diesel consists of govemor tuning, corrgenerator testing associated with hour fast start fullload run test, a'd a fullload reject test..aion of gov L
March 26,1999 Page 3 3)
The safety basis for the reauest. includino an evaluation of_the safety signJtcance and ootential consecuences of the orooosed course of actio
_This evaluation should include at least a cualitative risk ass derived from the licensee's PRA.
V *y in assessing the safety significance of the requested ED, two perspec D. rwere consic'ered. The first perspective was to compa
@ shutdown. In this comparison, pursuing ED is preferred due to the g increased risk associated with placing the Units through a shutdown and s
creating the possibility of a disturbance on the offsite sources due to loss of generation from the PBAPS units.
The second perspective considers the actual safety conse associated with the proposed Completion Time extension.quences These consequences are considered minimai in that the extension in the Completion Time has no impact on the capability of the remaining dies generators and offsite sources to perform their required safety functions.
The level of acceptable risk associated with the E3 diesel generatorin the of 3 days. However, the additional 3 day duration rep calculated risk increase. The increase represents a negligible contribution to the total yearly risk and is considered non-risk significant using the acceptance guidelines for Core Damage Frequency (CDF) and the Large Early Release Frequency (LERF) from Regulatory Guide 1.174.
4)
Ihe basis for the licensee's conclusion that the noncomolianc pf ootential detriment to the oublic health and safety and that no sianificant hn7ard consideration is involved.
The proposed ED will not be of potential detriment to the public health and safety, and does not involve a Significant Hazards Consideration based on the following discussion:
- 1. The oronosed chanoes do not involve a sionificant increase i probability or consecuences of an accident oreviousiv evaluated because '
the probability of a Loss of Offsite Power LOOP day extension of the Completion Time for(the one) is independent of the 3 diesel generator, and the requested extension does not introduce any failure mechanisms to the previously considered LOOP. The consequences of an accident are independent of the Completion Times Time does not effect the consequence. The increase in the Completion s because the LOOP analysis considers that one diesel generator is out-of-service. The Peach Bottom standby AC power system is designed with sufficient redunJancy such that one diesel generator may be removed from service for testing, inspection, or repairs in the time provided in the current Technical Specifications. The remaining three diesel generators are still capable of carrying sufficient loads to mitigate the coriseguences of an accident and offsite source is fully capable of supplying the pow l o
i
- March 26,1999 Page 4 mitigate an accident. Currently, the plant has three fully capable offsite lines (No. 2 startup source, No. 3 startup source, and the 343 startup source capable of supplying the power requirements to mitigate an acciden)t. During the 3 day extension, written dire limit planned on-site and offsite maintenance which would affect the availability of the offsh sources. Therefore, the probability or increased by the additional time requested. consequences of
- 2. The orooosed chsnoes do not create the possibility of a new or different kind of amident tmm any oreviousiv evaluated because the requested change is extendq a Completion Time, and this in and of itself does not create the possibility cf a new or different kind of accident.
Extending the Completion Time does not introduce any new accident initiator,
- 3. The oronosed chances do not involve a sianificant reduc 3on in maroin of safety. because the PBAPS, Units 2 and 3 standby AC system is designed with suificient redundancy such that one diesel generator be removed from service for testing, inspection or repairs with the remaining three diesel generators capable of carrying sufficient loads to satisfy the Updated Final Safety Analysis Report requirements for shutdown of both Units.
Written direction on planned maintenance will improve the likelihood that the three offsite lines will be available during the extended diesel outage period. There is no planned maintenance on the Conowingo Tie-Line (SBO)line during the extended Completion Time. Considering this fact, as well as the decrease in likelihood of a LOOP event, a 3 day extension to the Completion Time does not involve a significant reduction in a margin of safety.
5)
The basis for the licensee's conclusion that the noncomoliance wil involve adverse consecuences to the environment.
The proposed Enforcement Discretion will not have any adverse environmental impact since the Enforcement Discretion will not result in any increase in the amount or result in any change in the type of effluent which may be released offsite. The remaining diesel generators and offsite power sources will continue to peiform their intended safety functions and ensure safe plant shutdown if necessary.
- 6) Any orooosed compensatorv measure (st hg . As required by plant Technical Specifications (Required Action B.1), with 8 one diesel generator inoperable, verification is performed to ensure d' correct breaker alignment, required equipment available, and indicated power is available for the Conowingo Tie-Une. This verification is performed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Currently, the plant has three fully capable offsite lines (No. 2 startup source, No. 3 startup source, and the 343 l 1
M:rch 26,1999 Page 5 i 1
startup an source) accident. Durin capable of supplying the power requirements to m to limit planned on g the 3 day extension, written direction will oe in place availability of the offsite lines. site and offsite maintenance which would
- 7)
The iustification for the duration of the r:oncomoliance.
@ As a result of gasket failures which occurred during the testing of the E diesel generator, a 3 day extension P requested to complete the dp.remaining testing associated with a diesel generator ou 3rogress at PBAPS, Units 2 and 3. This extension is necessary in order
& "o avoid an undesirable transient resulting from the shutdown of both Units.
8)
A statement that the reauest has bp_en sooroved bv the facility l oraanization that normally reviews safety issues (Plant Onsite Review p,_ommittee. or its eouivalentt The Plant Operations Review Committee has approved this request fo Enforcement Discretion.
9)
The reauest must specifically address which of the NOED criteria for acorooriate olant conditions specified in Section B is satisfied and how it is soecified. {
i The plant conditions associated with this request satisfy Part 9900 Criterion B.1
'a), " avoid uMesirable transients as a result of forcing compliancidith the license condition and, thus, minimizing potential safety consequences and operating risks," in that this request avoids a shutdown of both Units.
Limiting Condition for Operation 3.8.1.b requires that four diesel generators be capable of supplying the onsite Class 1E AC electrical power distribution system while in Modes 1,2, arid 3. As discussed in Condition B, with one diesel generator inoperable, Required Action B.5 requires that the diesel generator be restored to operable status within a Completion Time of 14 days from the discovery to meet 3.8.1.b.
Otherwise, with this Condition not met within the specified Completion Time, Condition G requires that the Units must be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> '
and Mode 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. As discussed previously, pursuing ED is preferred due to the increased risk associated with placing the Units through a shutdown and creating the possibility of a disturbance on the offsite sourcas due to loss of generation from the PBAPS units.
3
1
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, March 26,1999 Page 6 10)
If a follow-uo license amendment is reouired the NOED reauest m include marked-uo TS oaoes showino the orooosed TS chances commitment hours. to submit the actual license amendment reauest within 4)
I This request is for a 3 day extension in the Completion Time, in Accordance with the guidance of Part 9900 of the NRC Inspection Manual, no license amendment is necessary, 11)
For NOEDs involvino severe weather or other natural events. the licentec's reauest must be sufficientiv deta!!ed for the staff to evalu likelihood that the event could affect the olant. the capability of the unimate heat sink. on-site and off-site emeroency orecaredness status.
access to and from the olant, acceptability of any increased radiolooical risk to the oublic and the overall oublic benefit.
This naturalEnforcement events. Discretion does not involve severe weather or oth I
Ve ruly yours,
,,[ h h ?
D Edwards Director- Licensing ce; H. J. Miller, Administrator, Region 1. USNRC I
A. C. McMurtray, USNRC Senior Resident inspector, PBAPS i
03/26/99 FRI 14:40 FAI 610 640 6773 DIR. LICENSING 001 PECO Nuclear Memorandum i
l FACSIMILE TRANSMITTAL SHEET DATE: M 9h TOTAL No. OF PAGES:
TO: ,
.bdb FAX: b /O- 3 37-83 Y h l
FROM: D, hh PHONE:
FAX: 610-640-6773 l
RE:
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@ i Any questions with the transmittal of this fax please contact (610) 640. C176
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