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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
[Table view] |
See also: IR 05000277/1997005
Text
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November * 5, 1997
,
Mr. D. M. Smith, President
PECO Nuclear
Nuclear Group Headquarters
Correspondence Control Desk '
P. O. Box 195
Wayne, Pennsylvania 19087 0195
SUBJECT: INSPECTION REPORT NOS. 50 277/97 05 AND 50 278/97 05
Dear Mr. Smith:
This letter refers to your October 13,1997, correspondence, in response to our
September 12,1997, 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,
1
Clifford J. Ander(on, Chief
Project Branch No. 4
Division of Reactor Projects
Dacket Nos. 50 277:50-278
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9711200259 971106
PDR ADOCK 05000277 t
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Mr. D. M. Smith 2
cc:
G. A. Hunger, Jr., Chairman, Nuclear Review Board and Director, Licensing
T. Mitchell, Vice President, Peach Bottom Atomic Power Station ,
G. Rainey, Senior Vice President, Nuclear Operations
J. B. Cotton, Vice President, Nuclear Station Support
T. Niessen, Director, Nuclear Quality Assurance
A. F. Kirby, Ill, External Operations Delmarva Power & Light Co.
G. Edwards, Plant Me ager, Peach Bottom Atomic Power Station
G. J. Lengyel, Mane ar, Experience Assessment
J. W. Durham, Sr ienior Vice President and General Counsel
T. M. Messick sger, Joint Generation, Atlantic Electric
W. T. Hennck, enager, External mffairs, Public Service Electric & Gas
R. McLean, Pow. Plant Siting, Nuclear Evaluations
J. Vannoy, Acting. 3ecretary of Harford County Council
- R. Ochs, Maryland Safe Energy Coalitior
J. H. Walter, Chief Engineer, Public Service Commission of Maryland
Mr. & Mrs. Dennis Hiebert, Peach Bottom Alliance
Mr. & Mrs. Kip Adams
Commonwealth of Pennsylvania
State of Maryland
TMl- Alert (TMIA)
Distribution:
Region i Docket Room (with concurrences)
W. Axelson, DRA
P. Swetland, DRP
A. Linde, DRP
Nuclear Saf aty information Center (NSIC)
NRC Re=ident inspector -
i
PUBLIC
W. Dean, OEDO
i
L. M. Padovan, PM, NRR
l
l J. Stolz, PDl 2, NRR
Inspection Program Branch, NRR (IPAS)
R. Correia, NRR
F. Talbot, NRR
DOCDESK
1
DOCUMENT NAME: P:
to receNo a copy of this document. Indicate in the bes: 'C' = Copy without attachment!onclosure 't* = Copy wrth attachment / enclosure 'N' = No copy
OFFICE Rl/D,/ l Rl/DRP / l l
NAME WSchmidt P CAnderson /l'c '
DATE 11/06/97 'i>' 11/ cu/97 11/ /97 11/ /97 11/ /97
0FFICIAL RECORD COPY
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Pe:ch (Witom Atomm Pcwer Stiton
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PEC'O NUCLEAR gogg P
$7""jjj7g4S032
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A Unit of PECO Energy
(
Fax 717 456 4243
Docket Nos. 50-277
50-278
License Nos. DPR-44
DPR-56
October 13, 1997
U. S. Nuclear ReDulatory Commission
Attn.: Document Control Desk
Washington, DC 20555
Subject: Peach Bottom Atomic Power Station Units 2 & 3
Response to Notice of Violation (Combined Inspection Report No.
50-277/97-05 & 50-278/97-05)
t
Gentlemen:
9
in response to your letter dated September 12,1997 which transmitted the Notice
- of Violation conceming the referenced inspection report, we submit the attached
response. The subject report concerned a Residents' Integrated Safety inspection
which was conducted June 8 through August 9,1997,
If you have any questions or desire additionalinformation, do not hesitate to
contact us.
Ik*k
Thomas N. Mitchell
Vice President,
Peach Bottom Atomic Power Station
Attachments
cc: W. T. Henrick, Public Service Electric & Gas
R. R. Janati, Commonwealth of Pennsylvania
H. J. Miller, US NRC, Administrator, Region i
R. S. Barkley, US NRC, Interim Senior Resident inspector
T. M. Messick, Atlantic Electric ,
R.1. McLean, State of Maryland ,
A. F. Kirby Ill, DelMarVa Power
.
CCN 97-14060
L .
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l
bec: OEAP Coordinator 62A-1, Chesterbrook !
Correspondence Control Program 61B-3, Chesterbrook
NCB Secretary (11) 62A-1, Chesterbrook
D. M. Smith 63C-3, Chesterbrook
G. R. Rainey 63C-3, Chesterbrook
T. N. Mitchell SMB4-9, Peach Bottom- i
L J. B. Cotton 62C-3, Chesterbrook
T. J. Niessen 53A-1, Chesterbrook
E. J.' Cullen . S23-1, Main Office
+ E. W. Callan SMB4-6, Peach Bottom
G. A. Hunger 62A-1, Chesterbrook '
J. G. Hufnagel 62A-1, Chesterbrof k
C. J. McDermott S13-1, Main Office -
G. D. Edwards A41S, Peach Bottom
V. Cwietniewicz PB-TC, Peach Bottom
R.A.Kankus 61C 1, Chesterbrook
G. J. Lengyel A4-4S, Peach Bottom
R. K. Smith A4 5S, Peach Bottom
.
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9
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RESPONSE TO NOTICE OF VIOLATION 97 05-02
Restatement of Violation
Technical specification 5.4.1 requires, in part, that written procedures be
established and maintained covering the bypass of safety functions.
Contrary to the above, PECO did not properly maintain written procedures for the
bypass of the main control room (MCR) ventilation system isolation when a
Division i MCR radiation monitor was inoperable. Specifically, Procedure GP-25 ,
Appendix 13, MCR Ventilation Isolation, Division 1, failed to provide complete
instructions for maintaining radiation monitor RIS-0760A in a tripped condition.
Consequently, on or about July 10,1997, a PECO technician removed the monitor
from a tripped condition, contrary to technical specifications.
This violation represents a Severity Level IV problem (Supplement 1).
Backaround Information
On July 8,1997, Maintenance Instrument and Control (l&C) technicians contacted
the instrument manufacturer of the "A" channel Main Control Room Emergency
Ventilation (MCREV) radiation monitor RIS-0760A concerning a problem where
the monitor was indicating higher than three other channels. This monitor samples
the main control room air it.itake for radiation and initiates a trip on a high radiation
signal. After discussion with the manufacturer, l&C personnel determined that the
pre-amplifier was the most probable cause of the monitor indicating high. Although
the readings were higher than the other instruments, the instrument was still within
the operating band. The higher readings actually put the monitor in a more
conservative direction with the instrument operating closer to the trip point. A
routine calibration check and quarterly functional test had also been recently
performed successfully.
Maintenance Planning created a work order to evaluate and replace the pre-
amplifier if necessary. Shift Management declared the MCREV sub-system
inoperable on July 9 at 5:30 p.m. to allow l&C to investigate and perform work
activities, Technical specifications 3.3.7.1 allowed six nours before the channel
would need to be placed in the trip condition. The pre-amplifier was replaced
within this time frame, but troubleshooting following the replacement revealed that
the higher than normalindication had not changed.
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At approximately 10:30 p.m., I&C technicians informed the control room of their
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results and that they could not continue due to working hour limitations. Since the
six hour tech spe; limit was running out, the Operations shift decided to enter GP.
25 Append * id - MCR Ventilation isolation, Division I and placed the "A" MCREV .
radawn monitor RIS-0760A in the trip condition by turning the key lock switch to
"OFF" locally at the monitor. Tags were placed on the redundant MCREV
channels as a precaution in the main control room, but were not placed on the
local monitor that was tripped. These actions were in compliance with the
procedure as it was written.
The on shift I&C technicians continued to summarize their troubleshooting
activities with the Operations shift who afterwards requested to talk with the l&C '
- subject matter expert (SME). At approxirnately 10:45 p.m., the I&C SME was
called to the control room. The shift discussed the activities with the l&C SME and
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questioned if any further troubleshooting could be performed. It was determined
that the instrument grounds were the on!y item that had not been previously
checked. The l&C SME communicated to the shift that he was going to continue
work and check the radiation monitoring instrument grounds to see if there could
be excessive noise affecting the instrument. Although the shift questioned the l&C
SME on how the grounds were to be checked, they were not aware that this
testing would involve taking the lochi radiation monitor out of the trip condition.
Following the control room briefing, the l&C SME went to the local panel for the "A"
MCREV radiation monitor RIS-0760A. The l&C SME placed the key-lock switch to
"ON" and initiated troubleshooting activities. During these activities various
grounds where checked within the monitor, but no appreciable differences in the
readings were noted. At approximately 12:45 a.m. on July 10,1997, the l&C SME
concluded troubleshooting activities. The I&C SME notified the control room that
he had completed work and that troubleshooting would resume on day-shift.
At 3:00 a.m., while resetting an unrelated alarm, a Plant Reactor Operator (PRO)
observed the MCREV radiation monitor alarm reset. The PRO immediately
recognized that the alarm should not have cleared and notified control room
supervision. An investigation was initiated and the l&C SME was called at his
home to determine why the MCREV radiation monitor had reset. At approximately
3:25 a.m. it was determined that the local key-switch for MCREV radiation monitor
RIS-0760A had been placed back in service for troubleshooting and was left in the
"ON" position. The key lock switch was then placed in the "OFF" position and the
GP-25, Appendix 13 trip was re-established. .
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Reason For the Violation
GP 25, Appendix 13, *MCR Ventilation Isolation, Division I" was not adequate to
ensure the radiation monitor would be maintained in the trip condition. The
procedure allowed the tripped unit to be either removed or placed in service by the
use of a local key-lock switch rather than a jumper or other mechanical device. As
a result, the key-lock switch was taken to the *OFF" position to implement the trip.
When the unit was returned to the "ON" position to perform troubleshooting, the
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trip was negated. The procedure did not provide a serviceable method to insert
the trip. Additionally, even though the procedure required redundant components
to be tagged in the control room as a precaution, the actual local component that
was administrative!y removed from service was not required to be tagged.
Therefore, there was no localir sication to indicate that the radiation monitor had
been placed in the tripped condition per procedure
Communications between Operations and Maintenance l&C was less than
adequate. Although Operations was aware that the l&C SME was performing
troubleshooting and work activities on the radiation monitor, they were not aware
that the instrument was required to be re energized to support this testing. Better
communication of the activities planned should have identified the procedural
inadequacy where troubleshooting could rat be performed with the radiation
monitor in the "OFF" position or in the tripped condition.
The l&C SME was so focused on troubleshooting the instrument grounds that he
did not realize at the time that by placing the local radiation monitor key-lock switch
to the "ON" position for troubleshooting that he was negating the trip implemented
per GP-25, Appendix 13.
Corrective Steos That Have Been Taken and the Results Achieved
At 03:25 a.m. on July 10,1997, the key-lock switch for Radiation Monitor RIS-
0760A was placed in the "OFF" position in accordance with GP-25, Appendix 13,
which re-established the trip for the MrT4EV Division 1 Radiation Monitoring. A
local equipment status tag was placed on MCREV radiation monitor RIS 0760A to
prever.t further manipulation of the switch. All work activities on the radiation
monitor were suspended. In addition, later that day, GP-20, Append.ix 13 was
temporarily changed to trip the channel using a jumper, which maintained power to
the radiation monitor in the trip mode to allow troubleshooting activities.
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A review of other GP 25 Appendices was conducted to ensure that no other similar 4
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conditions existed where channel trips could be removed by the single action of
positioning key lock switches.
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- A Performance Enhancement Program (PEP) was initiated on July 10 to -)
investigate this event. Results of that investigation have been used to develop
this response.
Review of this event determined that although the MCREV "A" channel was
administratively declared inoperable per GP-25, Appendix 13, the radiation monitor -
was functional and capable of monitoring the radiation levels and providing a trip
function to MCREV. The testing that l&C performed during the troubleshooting
evolution verified that the radiation monite a as able to respond to input signals i
and provide correct indications. Additionally, the instrument was tested by the ,
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equipment manufacturer and found to be within specifications. The vendor testing -
of the detector and pre-amplifier determined that the radiation monitor that had
been placed back into service for troubleshooting was in calibration and capable of i
performing its function in the event of a high radiation signal to the "A" radiation
monitor. As a result, the "A" channel of the MCREV Radiation Monitor was
functional and would have performed appropriately.
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Corrective Steos That Will Be Taken to Avoid Further Violations ,
A revision to GP-25 Appendix 13 and 14 (for channels B and D) will be
implemented to incorporate the temporary changes which have been initiated.
This revision is the next step in the progression of the temporary change process. 1
This change willincorporate the use of some type of mechanical device to provide
the capability to energize equipment for troubleshooting or testing without
removing equipment from a tripped condition. This revision will be completed by
November 21,1997.
Additional information concerning this event will be provided to appropriate
Operations and Maintenance l&C personnel by November 30,1997.
Date When Full Comoliance Was Achieved
Full compliance was achieved on July 10,1997, when a temporary change (TC)
was implemented on GP-25, Appendix 13 to trip the appropriate channel using a
jumper instead of the appropriate key-lock switch. This change enabled the '
equipment to remain energized for troubleshooting without affecting the trip.
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