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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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July E7, 1998 Mr.' G. Rainey, President PECO Nuclear Nuclear Group Headquarters Correspondence Control Desk l P.O. Box 195 l Wayne, Pennsylvania 19087-0195
SUBJECT: COMBINED INSPECTION REPORT NOS. 50-277/98-02 AND 50-278/98-02
Dear Mr. Rainey:
This letter refers to your July 10,1998, correspondence in response to our June 9,1998 letter.
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.
Your cooperation with us is appreciated.
Sincerely, Original Signed by:
l Clifford J. Anderson, Chief )
Projects Branch 4 Division of Reactor Projects Docket Nos. 50-277;50-278 cc w/ Licensee Response Ltr:
R. Boyce, Director, Nuclear Quality Assurance j G. J. Lengyel, Manager, Experience Assessment : I J. W. Durham, Sr., Senior Vice President and General Counsel /
l T. M. Messick, Manager, Joint Generation, Atlantic Electric / !
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W. T. Henrick, Manager, External Affairs, Public Service Electric & Gas I R. McLean, Power Plant Siting, Nuclear Evaluations ;
l J. Vannoy, Acting Secretary of Harford County Council j R. Ochs, Maryland Safe Energy Coalition l l J. H. Walter, Chief Engineer, Public Service Commission of Maryland i I Mr. & Mrs. Kip Adams )
! Commonwealth of Pennsylvania ,.
State of Maryland i TMI- Alert (TMIA)
9807310352 980727 PDR l
0 ADOCK 05000277 PDR g f na;', C C b 0FFICIAL RECORD COPY IE:01 !
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l Mr. cc w/o Licensee Response Ltr:
G. Edwards, Chairman, Nuclear Review Board and Director, Licensing J. Doering, Vice President, Peach Bottom Atomic Power Station J. B. Cotton, Vice President, Nuclear Staticn Support A. F. Kirby, Ill, External Operations - Delmarva Power & Light Co.
M. Warner, Plant Manager, Peach Bottom Atomic Power Station Mr. & Mrs. Dennis Hiebert, Peach Bottom Alliance
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Mr. Distribution w/ Licensee Response Letter:
Region i Docket Room (with concurrences)
C. Anderson, DRP
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D. Florek, DRP
! R.Junod,DRP Nuclear Safety Information Center (NSIC)
NRC Resident inspector PUBLIC B. McCabe. DECO R Pr.ps, PDI-2, NRR Inspection Program Branch, NRR (IPAS)
M. Thadani, NRR B. Buckley, NRR R. Correia, NRR F. Talbot, NRR DOCDESK DOCUMENT NAME: A:\RL902.PB i To rsceive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" =
Copy with attaptgent/ enclosure "N" = No copy
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' OFFICE Rl/p% Rl/DRP
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l NAME D)6rek CAnderson t/g DATE 071]S)/98 07/p198 '
GrFICIAL RECORD COPY
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-:4~;'. Jahn Doering, Jr.
d Vice Presidern Peach Bottom Atorme Power Staton
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.PECO NUCLEAR A Unit of PECO Energy gg;g,cfm-r ga;gy73g9032 g
Fax 717 456 4243 E mat deenngineco-energycom i
July 10,1998 Docket Nos. 50-277 '
50-278 License Nos. DPR-44 DPR-56 U. S. Nuclear Regulatory ^ommission j Attn.: Document Control sesk Washington, DC 20555 {
j Subject: Peach Bottom Atomic Power Station Units 2 & 3 Response to Notice of Violations (Combined Inspection Report No. 50-277/98-02 & 50-278/98-02)-
Gentlemen:
.,
in response to your letter dated June 9,1998, which transmitted the Notice of Violation (NOV), concerning the referenced inspection report, we submit the attached response.
The subject report concerned a Residents' Integrated Safety Inspection that was i
conducted March 15,1998 through May 4,1998.
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If you have any questions or desire additional information, do not hesitate to ccvact us.
W /)'
John oering, Jr.
Vice President, Peach Bottom Atomic Power Station Attachments MT/mt -
cc; -_N.J. Sproul, Public Service Electric & Gas R. R. Janati, Commonwealth of Pennsylvania H. J. Miller, US NRC, Administrator, Region I
'A. C. McMurtray, US NRC, Senior Resident inspector
- R. I. McLean, State of Maryland A. F. Kirby lit DelMarVa Power / Atlantic Electric L
l CCN 98-14052 0 ^^
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bec: OEAP Coordinator 62A4. Chesterbrook Correspondence Control Program 618-3, Chesterbrook NCB Secretar) (11) 6?A-1 Chaeterbrook G. C 3, ChesNorook J. Doering SM34-9, Peath Sc tom ,
J. B. Cotton 62C-3, Chestettrook '
R. W. Boyce 63C-3, Chestertrook E. J. Cullen S23-1, Main Of fice T.A.Shea SMB4-6, Peach Bottom G. D. Edwards 62A-1, Chesterbrook J. G. Hufnagel 62A-1, Chesterbrook C. J. McDermott S13-1, Main Office M. E. Warner A4-1S, Peach Bottom G. L. Johnston SMB3-5, Peach Bottom
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R. L Gambone A4-1S, Peach Bottom 2 R.A.Kankus 63C-2, Chesterbrook G.J.Lengyel A4-4S, Peach Bottom M.J. Taylor A4-SS, Peach Bottom i
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RESPONSE TO NOTICE OF VIOLATION 98-02 Restatement of Violation 1. Technical Specification 5.4.1 requires, in part, that written procedures be established, l' implemented, and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, Appendix A, November 1972. The procedures listed in Regulatory Guide 1.33, Appendix A, include emergency core cooling systems.
Contrary to the above, prior to March 22,1998, PECO failed to properly maintain system operation procedure SO 23.1.18-2, "High Pressure Coolant injection (HPCI) System Manual Operation," resulting in inadequate instructions for the operation of the HPCI vibration monitoring equipment. This procedure did not allow for the vibration monitoring 5 equipment warm-up time of 30 minutes required to ensure equipment reliabihty.
Be.ason(s) For The Violations While performing surveillance procedure (ST) ST-O-023-301-2, Revision 19, "HPCI Pump, Valve, Flow and Unit Cooler Functional and in-Service Test * to verify operabikty -
of the unit 2 HPCI system on March 13,1998, NRC inspectors questioned operations shift management as to the significance of the high HPCI vibration meter and recorder readings in the control room. The control room supervisor referred to the operating
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procedure, SO 23.1.B-2, Revision 11, "HPCI System Manual Operation" for the limit on vibration. The control room meter indicated a reading of greater than 5.0 mils with spikes as high as 5.92 mils. The procedure requires the HPCI turbine be tripped immediately if greater than 3.5 mils vibration is observed. Based on the inspectors'
observaCons and information provided by operators locally monitoring the HPCI booster pump vibration, the operators questioned the rehabikty of the control room monitoring equipment and the unit 2 HPCI turbine was shutdown. The HPCI system remained inoperable until additional testing and monitorirg indicated that vibration readings were within the acceptable range.
The incident was discussed with operation and I & C personnel in addition to the system manager The discussions indicated that it was not readily recognized by the system manager nor others that a warm-up time was required due to the design of the instrument. Some station personnel who worked with this type of instrument for a number of years were aware of the warm-up period for this instrument.
This instrument utilizes a vacuum tube design which does not function properly untilit warms up to operating temperature. Although known to some personnel, this system requirement had not been annotated in operations or surveillance procedures.
Corrective Steps That Have Been Taken Anc' The Results Achieved A Temporary Change to include a precautionary 30 minute warm-up time on the recorder and indicator was initiated on March 22,1998, for five operating and four test procedures.
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Corrective Steps That Will Be Taken To Avoid Further Violations i
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Six test procedures which involve HPCI monitoring are also being revised to include a statement that if the HPCI vibration monitoring system, VBI and VBR-4(5) 06 displays ,
inaccurate information during the first 30 minutes of operation it may be due to system I warm-up time. A statement that if a vibration concern exists then the severity of the vibration should be verified in the HPCI Pump Room via local indication will e!so be added. In addition, Engineering Change Requests (ECRs) have been initiated to evaluate the removal of these recorders and indicators from service since installed local indication is more accurate than the HPCI vibration monitoring system in the control I reom.
l Date When Full Compliance Will Be Achieved Full compliance was achieved on March 22,1998, when a temporary change to SO 23.1.B-2 was implemented. The change provided the information that the HPCI '
vibration monitoring system., may display inaccurate information during the first 30 minutes of operation due to system warm-up time. It also included that if a vibration concern exists, the severity of vibration is to be verified in the HPCI Pump Room.
Revisions to the fifteen operating and test procedures that involve HPCI monitoring are expected to be revised by September 1998. In addition, information on this incident and the HPCI vibration monitoring system will be included in the July 1998, Operation's
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" Focus On Excellence" newsletter. This newsletter is required reading for all Operations personnel, i
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j Restaternent of Violation
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2. Technical Specification 5.4.1 requires, in part, that written procedures be established, implemented, and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, Appendix A, November 1972. The procedures listed in !
Regulatory Guide 1.33, Appendix A, include restrictions for activities in radiation and high radiation areas !
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PECO Health Physics procedure HP-C-215, " Establishing and Posting Radiologically l Controlled Areas," Revision 2, required each Radiation Area to be conspicuously posted {
with a sign or signs bearing the radiation symbol and the words, " CAUTION RADIATION l
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Contrary to the above, on April 24,1998, the NRC identified that the radiation area signs at the access to the North Isolation Valve Room (NIVR), a known and surveyed
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radiation area, were not visible nor conspicuous.
Reason (s) For The Violations i
On Friday April 24,1998, an operator and an operations health physicist (H.P.) went to {
the North isolation Valve Room (NIVR) to perform a draining procedure. .he area was i controlled as a high radiation area due to the potential of a HPCI actuation and the I
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subsequent potential dose rates in the room in excess of 100 millirem per hour. Actual )
survey data from the routine survey program indicated that the highest general area was i 22 millirem per hour and that the area was not a high radiation area as defined by 10 '
CFR 20.1003,10 CFR 20.1601, and Peach Bottom Technical Specification 5.7. The H.P. briefed the operator on the task arid the radiclogical conditions in the area, opened ,
the coor and let the operator in to perform the work. When it was open, the door l opened such that the radiation sign on the outside of the door posting the room as a High Radiation Area faced the wall and was no longer visible. The operator indicated to the H.P. that he saw a leak in the room. The H.P. verbally checked with the operator to ensure the operator was not wet and then proceeded around imi corner of the NIVR to acquire protective clothing. During this time the operator remained inside the NiVR and did not have sight of the door. It was at this time the NRC inspector entered the area and observed that the door to the NIVR wn left ajar and the radiation posting was no longer conspicuously posted.
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Corrective Steps That Have Been Taken And The Results Achieved Once this issue was brought to the attention of Health Physics personnel by the NRC inspector, the door to the NIVR was closed and additional postings were put in place to ensure visible and conspicuous notification. A Performance Enhancement Program (PEP) investigation (10008303) was initiated on April 26,1998, to investigate the event, determine potential causes and develop appropriate corrective actions. All controlled high radiation areas (28 areas) were monitored and reviewed for consis:ency with the posting standard and with the procedure. The locked high radiation areas were also evaluated for appropriateness of regulatory controls and human factors. In addition, Limerick'd posting program was benchmarked for the control and posting of locked high radiation areas. This benchmarking was completed by May 15,1998.
The H.P. involved in the incident was counseled regarding this incident. In addition, an
"all hands' meeting was held on May 15,1998, with all H.P. staff to stress the need to ensure continuous procedural compliance and to ensure there is a full understanding of applicable technical specifications. The meeting was also used to obtain feedback on how the Radiation Protection group could ensure that the incident does not re-occur.
Corrective Stens That Will Be Taken To Avoid Further Violations Radiological posting of various areas in the plant (e.g., units 2 and 3 RCIC turbine
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exhaust to torus line) are being evaluated to assure the plant is meeting its posting standards and create a " human factored" control of controlled high radiation areas.
Date When Full Comoliance Will Be Achieved Full compliance was achieved on April 24,1998, when the door to the NIVR was closed and the radiation posting was visible. Enhanced postif _, similar to that at Limerick, of high radiation area doors was completed by June 21, '98.
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