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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M6631999-10-19019 October 1999 Forwards Insp Rept 50-277/99-07 & 50-278/99-07 on 990920.No Violations Noted ML20217K9241999-10-14014 October 1999 Forwards Amend 234 to License DPR-56 & Se.Amend Consists of Changes to TS in Response to Application & Suppls ,1001 & 06,which Will Support PBAPS Mod P00507,which Will Install Digital Pr Neutron Mining Sys ML20217F7391999-10-14014 October 1999 Requests Addl Info Re Peach Bottom Atomic Power Station Units 2 & 3 Appendix R Exemption Requests ML20217F6841999-10-13013 October 1999 Forwards Senior Reactor Operator Initial Exam Repts 50-277/99-302(OL) & 50-278/99-302(OL) Conducted on 990913- 16.All Applicants Passed All Portions of Exam ML20217F3021999-10-12012 October 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at PBAPS Have Been Completed.Ltr Also Confirms Completion of Actions Required by Confirmatory Order Modifying Licenses, ML20217E7451999-10-0808 October 1999 Forwards Response to NRC 990820 RAI Concerning Proposed Alternatives Associated with Third ten-yr Interval ISI Program for Pbaps,Units 2 & 3 ML20217B7701999-10-0606 October 1999 Submits Corrected Info to NRC 980528 RAI Re Util Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20217B9151999-10-0606 October 1999 Provides Clarifying Info to Enable NRC to Complete Review of License Change Request ECR 98-01802,re Changes Necessary to Support Installation of Digital Pr Neutron Monitoring & Incorporate long-term T/H Stability Solution Hardware ML20217C4141999-10-0606 October 1999 Forwards Response to NRC 981109 RAI Re Resolution of USI A-46 for Pbaps.Proprietary Excerpts from GIP-2,Ref 25 Results of BWR Trial Plant Review Section 8 Also Encl. Proprietary Excerpts Withheld ML20217B3181999-10-0505 October 1999 Advises That Info Submitted in 990712 Application,Which Contained Attachment Entitled, Addl Info Re Cycle Spec SLMCPR for Peach Bottom 3 Cycle 13,dtd 990609, with Affidavit,Will Be Withheld from Public Disclosure ML20217B4051999-10-0505 October 1999 Forwards Amend 233 to License DPR-56 & Safety Evaluation. Amend Changes Minimum Critical Power Ratio Safety Limit & Approved Methodologies Referenced in Core Operating Limits Report 05000278/LER-1999-004, Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv)1999-10-0101 October 1999 Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv) ML20217B8891999-10-0101 October 1999 Forwards Response to RAI Re Request to Install Digital Power Range Neutron Monitoring Sys & Incorporate long-term,thermal-hydraulic Stability Solution Hardware. Revised TS Table 3.3.2.1-1 Encl ML20217D5211999-09-30030 September 1999 Informs That Remediating 3D Monicore Sys at Pbaps,Units 2 & 3 & 3D Monicore/Plant Monitoring Sys at Lgs,Unit 2 Has Been Completed Ahead of Schedule ML20212J6851999-09-29029 September 1999 Informs of Completion of mid-cycle PPR of Peach Bottom Atomic Power Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl New Insps Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20216J3981999-09-29029 September 1999 Submits Comments for Lgs,Unit 1 & Pbaps,Units 2 & 3 Rvid,Rev 2,based on Review as Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20212J5751999-09-28028 September 1999 Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 990913-16 at Licensee Facility.Without Encls ML20216J0191999-09-27027 September 1999 Forwards Request for Addl Info Re Util 990301 Request to Support Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware,For Plant ML20212H6171999-09-24024 September 1999 Forwards Rev 2 to COLR for Pbaps,Unit 2,Reload 12,Cycle 13, IAW TS Section 5.6.5.d.Rept Incorporates Revised Single Loop Operation MAPLHGR Flow Multiplier ML20216H6451999-09-24024 September 1999 Forwards Notice of Withdrawal of Util 990806 Application for Amends to Fols DPR-44 & DPR-56.Proposed Change Would Have Involved Temporary Change to Increase Limit for Average Water Temp of Normal Heat Sink ML20212H5431999-09-24024 September 1999 Informs of Decision to Inspect H-3 & H-4 Shroud Welds During Upcoming 3R12 Outage Scheduled to Begin Late Sept 1999 ML20216H6751999-09-24024 September 1999 Forwards Amends 229 & 232 to Licenses DPR-44 & DPR-56, Respectively & Ser.Amends Will Delete SR Associated Only with Refueling Platform Fuel Grapple Fully Retracted Position Interlock Input,Currently Required by SR 3.9.1.1 ML20216F8811999-09-23023 September 1999 Withdraws 990806 Exigent License Change Application.Tech Spec Change to Allow Continued Power Operation with Elevated Cooling Water Temps During Potentially Extreme Weather Conditions No Longer Needed Due to Favorable Weather ML20212E8661999-09-22022 September 1999 Discusses GL 98-01 Y2K Readiness of Computer Sys at NPPs & Supplement 1 & PECO Response for PBAPS Dtd 990630. Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient During Y2K Transition ML20212F5481999-09-20020 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing, for Pbaps,Units 2 & 3 & Lgs,Units 1 & 2 ML20212D1191999-09-17017 September 1999 Forwards SE Re Proposed Alternatives to ASME Section XI Requirements for Containment Inservice Insp Program at Plant,Units 2 & 3 ML20212A0091999-09-0909 September 1999 Provides Notification That Licenses SOP-11172 & SOP-11321, for SO Muntzenberger & Rh Wright,Respectively,Are No Longer Necessary as Result of Permanent Reassignment ML20211P2961999-09-0707 September 1999 Provides Authorization to Administer NRC Approved Initial Written Exams to Listed Applicants on 990913 at Peach Bottom Npp,Delta,Pennsylvania ML20211K7031999-08-30030 August 1999 Forwards Response to NRC 990826 RAI Re License Change Application ECR 99-01255,revising TSs 2.1.1.2 & 5.6.5 ML20211E6941999-08-26026 August 1999 Forwards Request for Addl Info Re Min Critical Power Ratio. Response Should Be Submitted within 30 Days of Ltr Receipt ML20211Q4491999-08-25025 August 1999 Responds to Re Changes to PBAPS Physical Security Plan,Safeguards Contingency Plan & Guard Training & Qualification Plan Identified as Revs 13,11 & 9, Respectively.No NRC Approval Is Required,Per 10CFR50.54(p) ML20211E9191999-08-24024 August 1999 Forwards fitness-for-duty Program Performance Data for Jan-June 1999 for PBAPS & LGS IAW 10CFR26.71(d).Data Includes Listed Info ML20211D5421999-08-23023 August 1999 Forwards Amends 228 & 231 to Licenses DPR-44 & DPR-56, Respectively & Se.Amends Revise TSs to Correct Typographical & Editorial Errors Introduced in TSs by Previous Amends ML20211A9721999-08-20020 August 1999 Forwards Request for Addl Info Re Third 10-year Interval Inservice (ISI) Insp Program Plan for Plant,Units 2 & 3 ML20210T5451999-08-12012 August 1999 Forwards Copy of Environ Assessment & Findings of No Significant Impact Re Licensee Request for Amends to Plant. Amends Consist of Changes to TS to Correct Typos & Editorial Errors Introduced in TS by Previous Amends ML20210P8321999-08-11011 August 1999 Responds to NRC 990715 Telcon Re Util 990217 Submittal of Proposed Alternatives to Requirements of 10CFR50.55a(g)(6)(ii)(B)(1) Re Containment Inservice Insp Program ML20210P8151999-08-11011 August 1999 Forwards Final Pages for Pbaps,Unit 2 & 3 OLs Re License Change Application ECR 99-01497,which Reflects Change in Corporate Structure at Pse&G ML20211B6521999-08-10010 August 1999 Informs That Dp Lewis,License SOP-11247,has Been Permanently Reassigned & No Longer Requires License,Per 10CFR50.74.Util Requests That Subject Individual Be Removed from List of License Holders ML20210P1561999-08-10010 August 1999 Submits Response to Requests for Addl Info Re GL 92-01,rev 1,Suppl 1, Rv Structural Integrity, for Pbap,Units 1 & 2. NRC Will Assume That Data Entered Into Rvid Are Acceptable for Plants,If Staff Does Not Receive Comments by 990901 ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210N7831999-08-0909 August 1999 Forwards Copy of Notice of Consideration of Issuance of Amends to Fols,Proposed NSHC Determination & Opportunity for Hearing, Re 990806 Request for License Amends.Amends Incorporate Note Into PBAPS TS to Permit One Time Exemption ML20210P0801999-08-0404 August 1999 Forwards Initial Exam Repts 50-277/99-301 & 50-278/99-301 on 990702-14 (Administration) & 990715-22 (Grading).Six of Limited SRO Applicants Passed All Portion of Exam ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response NUREG-1092, Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls1999-08-0303 August 1999 Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls ML20210J0161999-07-30030 July 1999 Forwards Copy of Notice of Consideration of Approval of Transfer of FOL & Issuance of Conforming Amends Re 990723 Application ML20210H5341999-07-27027 July 1999 Forwards Insp Repts 50-277/99-05 & 50-278/99-05 on 990518- 0628.NRC Determined That Two Severity Level IV Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20210F3731999-07-23023 July 1999 Submits Confirmation That,Iaw 10CFR50.80,PSE&G Is Requesting NRC Approval of Transfer of Ownership Interests in PBAPS, Units to New Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML20210E6211999-07-22022 July 1999 Submits Rev to non-limiting Licensing Basis LOCA Peak Clad Temps (Pcts) for Limerick Generating Station (Lgs),Units 1 & 2 & Pbaps,Units 2 & 3 ML20210E5811999-07-21021 July 1999 Forwards Final Tech Specs Pages for License Change Application.Proposed Change Will Revise Tech Specs to Delete Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS ML20216D8041999-07-19019 July 1999 Submits Summary of Final PECO Nuclear Actions Taken to Resolve Scram Solenoid Pilot Valve Issues Identified in Info Notice 96-007 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217F3021999-10-12012 October 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at PBAPS Have Been Completed.Ltr Also Confirms Completion of Actions Required by Confirmatory Order Modifying Licenses, ML20217E7451999-10-0808 October 1999 Forwards Response to NRC 990820 RAI Concerning Proposed Alternatives Associated with Third ten-yr Interval ISI Program for Pbaps,Units 2 & 3 ML20217C4141999-10-0606 October 1999 Forwards Response to NRC 981109 RAI Re Resolution of USI A-46 for Pbaps.Proprietary Excerpts from GIP-2,Ref 25 Results of BWR Trial Plant Review Section 8 Also Encl. Proprietary Excerpts Withheld ML20217B9151999-10-0606 October 1999 Provides Clarifying Info to Enable NRC to Complete Review of License Change Request ECR 98-01802,re Changes Necessary to Support Installation of Digital Pr Neutron Monitoring & Incorporate long-term T/H Stability Solution Hardware ML20217B7701999-10-0606 October 1999 Submits Corrected Info to NRC 980528 RAI Re Util Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20217B8891999-10-0101 October 1999 Forwards Response to RAI Re Request to Install Digital Power Range Neutron Monitoring Sys & Incorporate long-term,thermal-hydraulic Stability Solution Hardware. Revised TS Table 3.3.2.1-1 Encl 05000278/LER-1999-004, Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv)1999-10-0101 October 1999 Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv) ML20217D5211999-09-30030 September 1999 Informs That Remediating 3D Monicore Sys at Pbaps,Units 2 & 3 & 3D Monicore/Plant Monitoring Sys at Lgs,Unit 2 Has Been Completed Ahead of Schedule ML20216J3981999-09-29029 September 1999 Submits Comments for Lgs,Unit 1 & Pbaps,Units 2 & 3 Rvid,Rev 2,based on Review as Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20212H6171999-09-24024 September 1999 Forwards Rev 2 to COLR for Pbaps,Unit 2,Reload 12,Cycle 13, IAW TS Section 5.6.5.d.Rept Incorporates Revised Single Loop Operation MAPLHGR Flow Multiplier ML20212H5431999-09-24024 September 1999 Informs of Decision to Inspect H-3 & H-4 Shroud Welds During Upcoming 3R12 Outage Scheduled to Begin Late Sept 1999 ML20216F8811999-09-23023 September 1999 Withdraws 990806 Exigent License Change Application.Tech Spec Change to Allow Continued Power Operation with Elevated Cooling Water Temps During Potentially Extreme Weather Conditions No Longer Needed Due to Favorable Weather ML20212F5481999-09-20020 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing, for Pbaps,Units 2 & 3 & Lgs,Units 1 & 2 ML20212A0091999-09-0909 September 1999 Provides Notification That Licenses SOP-11172 & SOP-11321, for SO Muntzenberger & Rh Wright,Respectively,Are No Longer Necessary as Result of Permanent Reassignment ML20211K7031999-08-30030 August 1999 Forwards Response to NRC 990826 RAI Re License Change Application ECR 99-01255,revising TSs 2.1.1.2 & 5.6.5 ML20211E9191999-08-24024 August 1999 Forwards fitness-for-duty Program Performance Data for Jan-June 1999 for PBAPS & LGS IAW 10CFR26.71(d).Data Includes Listed Info ML20210P8321999-08-11011 August 1999 Responds to NRC 990715 Telcon Re Util 990217 Submittal of Proposed Alternatives to Requirements of 10CFR50.55a(g)(6)(ii)(B)(1) Re Containment Inservice Insp Program ML20210P8151999-08-11011 August 1999 Forwards Final Pages for Pbaps,Unit 2 & 3 OLs Re License Change Application ECR 99-01497,which Reflects Change in Corporate Structure at Pse&G ML20211B6521999-08-10010 August 1999 Informs That Dp Lewis,License SOP-11247,has Been Permanently Reassigned & No Longer Requires License,Per 10CFR50.74.Util Requests That Subject Individual Be Removed from List of License Holders ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML20210F3731999-07-23023 July 1999 Submits Confirmation That,Iaw 10CFR50.80,PSE&G Is Requesting NRC Approval of Transfer of Ownership Interests in PBAPS, Units to New Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML20210E6211999-07-22022 July 1999 Submits Rev to non-limiting Licensing Basis LOCA Peak Clad Temps (Pcts) for Limerick Generating Station (Lgs),Units 1 & 2 & Pbaps,Units 2 & 3 ML20210E5811999-07-21021 July 1999 Forwards Final Tech Specs Pages for License Change Application.Proposed Change Will Revise Tech Specs to Delete Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS ML20216D8041999-07-19019 July 1999 Submits Summary of Final PECO Nuclear Actions Taken to Resolve Scram Solenoid Pilot Valve Issues Identified in Info Notice 96-007 05000278/LER-1999-002, Forwards LER 99-002-01 to Correct Title Contained in Box (4) of LER Coversheet Form.Rev Does Not Change Reportability Requirements or Any Other Info Contained in Original Submittal of LER1999-07-12012 July 1999 Forwards LER 99-002-01 to Correct Title Contained in Box (4) of LER Coversheet Form.Rev Does Not Change Reportability Requirements or Any Other Info Contained in Original Submittal of LER ML20209G9121999-07-0909 July 1999 Informs That Ja Hutton Has Been Appointed Director,Licensing for PECO Nuclear,Effective 990715.Previous Correspondence Addressed to Gd Edwards Should Now Be Sent to Ja Hutton ML20209D9781999-07-0808 July 1999 Forwards Addl Info to Support EA of Proposed 990212 License Application ECR 98-01675,correcting Minor Administrative Errors in TS Figure Showing Site & Exclusion Areas Boundaries & Two TS SRs ML20209D8821999-07-0707 July 1999 Submits Estimate of Number of Licensing Actions Expected to Be Submitted in Years 2000 & 2001,as Requested by Administrative Ltr 99-02.Renewal Applications for PBAPS, Units 2 & 3,will Be Submitted in Second Half of 2001 ML20209D2671999-07-0202 July 1999 Responds to NRC 990322 & 0420 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20209E1131999-06-30030 June 1999 Forwards Proprietary NRC Form 398, Personal Qualification Statement-Licensee, for Renewal of RO Licenses for EP Angle,Md Lebrun,Jh Seitz & Zi Varga,Licenses OP-10646-1, OP-11081,OP-11082 & OP-11085,respectively.Encls Withheld ML20209B7001999-06-30030 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20209C1201999-06-30030 June 1999 Informs of Util Intent to Request Renewed License for PBAPS, Units 2 & 3,IAW 10CFR54.Licensee Anticipates That License Renewal Application Will Be Submitted in Second Half of 2001 05000277/LER-1999-004, Forwards LER 99-004-00 Re Unplanned ESF Actuations During Planned Electrical Bus Restoration Following Maint Activities1999-06-20020 June 1999 Forwards LER 99-004-00 Re Unplanned ESF Actuations During Planned Electrical Bus Restoration Following Maint Activities ML20196A5291999-06-14014 June 1999 Forwards Final Pbaps,Unit 3 TS Pages for License Change Request ECR 98-01802 Re Installation of Digital Power Range Neutron Monitoring (Prnm) Sys & Incorporation of long-term thermal-hydraulic Stability Solution Hardware ML20195E6051999-05-27027 May 1999 Requests Exemption from Requirements of 10CFR72.44(d)(3) Re Submittal Date for Annual Rept of Principal Radionuclides Released to Environ.Exemption from 10CFR72.72(d) Re Storage of Spent Fuel Records,Additionally Requested ML20195B8171999-05-25025 May 1999 Forwards Final TS Pages for License Change Application ECR 96-01511 Re Rev to Loss of Power Setpoints for 4 Kv Emergency Buses ML20195B6191999-05-19019 May 1999 Forwards PBAPS Units 2 & 3 Annual Radiological Environ Operating Rept 56 for 980101-1231, Per Section 6.9.2 of Ol. Trace Concentrations of Cs-137 Were Found in Sediment Consistent with Levels Observed in Previous Years ML20206P9171999-05-10010 May 1999 Updates Some of Transmitted Data Points Provided in Data Point Library ERDS for Pbaps,Units 2 & 3.Data Point Info Format Consistent with Guidance Specified in NUREG-1394 ML20206K6581999-05-0404 May 1999 Forwards PBAPS Bases Changes Through Unit 2 Bases Rev 25 & Units 3 Bases Rev 25.Bases Reflect Change Through Apr 1999, Thereby Satisfying Frequency Requirements of 10CFR50.71 ML20206D4651999-04-29029 April 1999 Forwards Rev 16 to UFSAR & Rev 11 to Fire Protection Program (Fpp), for Pbaps,Units 2 & 3.Page Replacement Instructions for Incorporating Rev 16 to UFSAR & Rev 11 to Fpp,Encl ML20207B8431999-04-23023 April 1999 Forwards Final Rept for 981117,plume Exposure Pathway Exercise of Offsite Radiological Emergency Response Plans site-specific for Peach Bottom Atomic Power Station.One Deficiency & 27 Areas Requiring C/A Identified ML20206C5461999-04-20020 April 1999 Forwards Radioactive Effluent Release Rept 41 for Jan-Dec 1998 for Pbaps,Units 1 & 2. Revs Made to ODCM & Station Process Control Program (PCP) During Rept Period,Encl 05000277/LER-1999-003, Forwards LER 99-003-00 Re 990318 Failure to Maintain Provisions of Fire Protection Program to Properly Address Effects of Flooding1999-04-16016 April 1999 Forwards LER 99-003-00 Re 990318 Failure to Maintain Provisions of Fire Protection Program to Properly Address Effects of Flooding ML20205K4541999-04-0808 April 1999 Forwards Revised Info Re 990330 NRC Nuclear Power Reactor Licensee Financial Qualifications & Decommissioning Funding Assurance Status Rept 05000278/LER-1999-001, Forwards LER 99-001-00 Re 990312 ESF Actuation of Rcics Due to High Steam Flow Signal During Sys Restoration.Rept Submitted Per 10CFR50.73(a)(2)(iv)1999-04-0808 April 1999 Forwards LER 99-001-00 Re 990312 ESF Actuation of Rcics Due to High Steam Flow Signal During Sys Restoration.Rept Submitted Per 10CFR50.73(a)(2)(iv) ML18106B1431999-03-31031 March 1999 Forwards Pse&G Rept on Financial Min Assurance for Period Ending 981231 for Hope Creek,Salem,Units 1 & 2 & Pbaps,Units 2 & 3,IAW 10CFR50.75 ML20205F8981999-03-31031 March 1999 Provides Info Re Status of Decommissioning Funding for LGS, Units 1 & 2,PBAPS,Units 1,2 & 3 & Sgs,Units 1 & 2,per Requirements of 10CFR50.75(f)(1) ML18106B1411999-03-30030 March 1999 Forwards Decommissioning Info on Behalf of Conectiv Nuclear Facility License Subsidiaries,Atlantic City Electric Co & Delmarva Power & Light Co,For Listed Nuclear Facilities ML20205J0831999-03-26026 March 1999 Requests Enforcement Discretion from Requirements of PBAPS, Units 2 & 3 Ts.Enforcement Discretion Pursued to Avoid Unneccessary Plant Transient Which Would Result from Compliance with TS ML20205B6421999-03-24024 March 1999 Submits 1998 Annual Decommission Rept for Pbaps,Unit 1. There Were No Reportable Events Involving Unit 1 for 1998 1999-09-09
[Table view] |
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PIIILADELPIIIA ELECTRIC COMi%NY
- NUCLEAR GROUP HEADQUARTERS
' 955-65 CHESTERBROOK BLVD.
WAYNE, PA 19087 % 91 y., (215) 640-6000 NUCLEAR ENGINEERING A SERVICES DEPARTMENT October 8, 1991 Docket Nos. 50-277 50-278 Lteense Nos. DPR-44
, .m DPR-56 {
U.S.-Nuclear Regulatory Commission
- +. Attn Document Control Desk fyj; 7
i Washington, DC 20555 i!O - SUBJECT - Peach Bot. tom Atomic Power Station, UnJts 2 and 3 b e.: . Inservice Testing Program
- ya ~ ,
REFERENCE:
Letter from~W. R. Butler (NRC) to G. J. Beck y~ (PECo) dated January 17, 1991 f;
Dear Sir:
-The above referenced letter transmitted the-NRC's.
Safety Evaluation (SE) for the Peach--Bottom-Atomic Power Statloa
_(PBAPS),-Units 2 and'3 second 10 year interval. Inservice Testing
. ( IST) ' Program.: The purpose of this lettec is'to provide a voluntary--response to the SE, and to provide an updated,
- uncontrolled copy of Revision'2 to the IST' Program (Enclosure 1).
'This revision includes changes-recommended-by-the.NRC in-the SE, and was issued for use-within six months _of receipt--of the-SE.
Appendix C-of_the above referenced letter listed ten IST Program anomolies-Identified by the NRC during review.
Enclosure - 2 :to _ this : letter - contains a restatement -of each anomoly to11 owed-by our; response.
1 I
I 3'
9110210001 911009 PDR -ADOCK 05000277 sk
)U i
_P; PDR 'l i
O s j
. .. . . . _ . . . _ - .. _ _m._... __. ___ . _ . . . . _ _ . .
U.S. Nuclear Regulatory Commission October 8, 1991 Inservice Testing Program. Page 2-
'If you have any questions concerning-this issue, please do not' hesitate to contact us.
Very truly yours 1 $k:'
G. J. B ck, Manager Licensing Section Nuclear Engineering & Services
Enclosures:
- 1. Second 10-Year Interval Inservice Testing Program, Revision 2
- 2. Response to NRC Identified Anomollen cc: T. T. Martin,-Adminictrator, Region I, USNRC J. J. Lyash, USNRC Senior Resident Inspectcr, PB If
1 Enclosure 2 Peach Bottom Atomic Power Station, Units 2 and 3 PPCo Response to NRC Identified Anomolles in Second 10-Year Interval IST Program
- 1. The licensee shall categorize all excess flow check valves A/C instead of C.
PECo Response Relief Request GVRR-2 and the associated valve tables have boon revised in Revision 2 of the Program tc categorize excess flow check valves as A/C.
-2.- The licensee stated at the working meeting that the main steam safety / relief valve ta11pipo vacuum breakers would be included in the IST. program and a relief request would be provided proposing to manually exercise the valvo disks during cold shutdowns when the drywell is de-inerted and during refueling outages. The licensee has instead proposed to test these vacuum breaker check valves in accordance with the requirements of ANSI /ASME OM-1-1981 which states that vacuum breaker devices are to be tested at least once each ten-year interval. This-proposal is not in agreement with Section XI, Paragraph IWV-3522(b), which states, in part, "except that for vacuum breaker valves the exerciser force or torque delivered to the disk may be equivalent to the desired functional pressure differential force. The disk movement shall be sufficient to prove that the disk moves freely off the seat." This exercising test is required to be: performed at the quarterly test frequency stated in Paragraph IWV-3521 with reference to Paragraph IWV-3522.
Since the_ vacuum breakers in question are simple check valves with no external means of operation or required differential-pressure setpoint, they should be exercised in accordance with the requirements-of Section XI in order to demonstrate: valve operational readiness. These valves are inaccessible during power. operation because they are located inside the drywell and the drywell atmosphere is inerted with' nitrogen gas. They are also inaccessible during most cold _ shutdowns because the drywell is not de-Jnerted,
-therefore, they cannot be exercised each cold shutdown in
- accordance with the applicable requirements of section XI.
The licensee should provide a relief request to perform exercise testing _during those cold shutdowns when the drywell is de-inerted and during refueling outages. The valves are:
VRV-2-01-8096A VRV-2-01-8096G VRV-2-01-8096B VRV-2-01-809611 VRV-2-01-8096C VRV-2-01-8096J
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'13-VnR-1,=14-VRR-2, 23-VRR-2, and 23-VRR-3. When valve disassembly is used as an alternative to Code testing, the valve internals should be visually inspected for worn or
-corroded parts and-the valve disk should be manually exercised per Generic Letter 99-04, Attachment 1, Position
- 2. Further, the licensee should perform a partial flow test of each valve prior to returning it to service follm:ing the ,
disassembly and inspection procedure.
The NRC staff considers valve disassembly and inspection to be a maintenance procedure that is not a test and not equivalent to the exercising produced by_ fluid flow. This-procedure has some risk which may make its routine use as a substitute for testing undesirable when some method of testing is possible. Check valve disassembly is a valuable maintenance tool that can provide a great deal of information'about a valve's internal condition and as such should be. performed.under the maintenance program at a frequency commensurate with the valve type and service. The licensee should' actively pursue the use of alternate testing methods to full-stroke exercise these valves, such as using non-intrusive _ diagnostic techniques to demonstrate whether they swing fully;open during partial flow testing or closed when flow is ceased. If another method is developed to verify the full stroke capability of the listed valves, the affected relief request should be revised or withdrawn.
, PECo Responso-Relief Requests 13-VRR-2 and 23-VRR-2 have been deleted from the IST Program since'they are no longer needed. The design flow rates for the valves covered by these Relief Requests can be achieved which allow for verification of the
' full-stroke capabilities of the valves._ For the valves covered by the remaining Relief Requests 13-VRR-3, 14-VRR-2 and 23-VRR-3, maintenance procedures require visual inspection of_ valve internals for worn or corroded parts. A requirement to manually exercise the valve disk'after reassembly has been added to these procedures in accordance with Generic Letter 89-04.. Relief Requests 13-VRR-3, 14-VRR-21and 23-VRR-3 have been revised in Revision 2 of the Program to require partial flow testing of each valve following disassembly. .These three~ remaining Relief Requests address.only Unit 3 valves. -It is expected that these three Relief Requests will no_ longer be needed following completion of Modification 1498 during the Unit-3 refueling outage which began September 1991. This modification will replace the valves with valves whose operators are capable of full stroke testing. Consequently, pursuit of alternate testing methods such as non-intrusive diagnostic techniques'will not be necessary.
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- 6. .The licensee hasLidentified check valve disassembly as the 1 alternate testing to verify the reverse flow closure capability for the valves addressed in relief requests
- 10-VRR-1, 13-VRR-1, 14-VRR-1, and 23-VRR-1. When valve
' disassembly:Is used as an alternate to Code. testing, the valve _ internals should be visually inspected for worn or corroded parts and'the valve disk should be manually exercised-per Generic-Letter 89-04, Attachment 1, Position
- 2. Further, the licensee should' perform a. partial flow test _
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-of-each_ valve prior to returning it-to service following the disassembly and inspection procedure.
The NRC_ staff considers valve disassembly and inspection to be a maintenance procedure that is not a test and not equivalent-to the exercising produced by fluid flow. This procedure has some risk which may make its routine use as a substitute.for testing undesirable when some method of testing is pessible.-Check valve _ disassembly is a valuable maintenance tool that can provide a great deal of information about a valve's internal condition and as such '
should be performed under the maintenance program at a frequency commensurate with the valve type and service. The
. licensee should actively-pursue the use of alternate testing methods to verify.the reverse flow closure of these. valves, such'as using;non-intrusive diagnostic techniques to demonstrate whet.5er they swing fully closea upon cessation or reversal of-Ilow. If another: method is developed to=
verify lthe' reverse-flow closure capability of the listed valves,'the affected relief request should be revised or withdrawn.
PECo Response Maintenance procedures require visual inspection of valve internals for worn _or-corroded parts.--A requirement to
. manually exercise the valve disk after reassembly haslbeen
-added t* these procedures in accordance with Generic Letter 89-04. _ - Ralie f : Reques ts 10-VRR-1, : 13-VRR-1, 14-VRR-1 and 23-VRR-1 have been revised in Revision 2 of the Program to require partial-flow-testing of each valve following disassambly.
In response to the NRC recommendation to pursue'en alternate testing method, PECo is-active in the Nuclear Industry Check
-Valve Group (NIC) and-is reviewing'NIC Report NIC-01,
" Evaluation of Nonintrusive_ Diagnostic Technologies for
-Check Valves." - The methods-discussed-in this report will be evaluated to determine iffthey are acceptable as an-alternative to the presently approved NRC method of check valve disassembly. In the interim, PECo is pursuing a_ check valve-sample disassembly and inspection program that will reduce the number of valves being disassembled during an outage.
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- 7. The licensee's proposed alternate testing in relief request GVRR-1 for leak rate testing containment isolation valves may not be conservative and may, therefore, permit excessive leakage through certain individual valves without requiring corrective actions. Although individual leakage rates will be assigned for each containment isolation valve, it appears that the corrective actions will be based on leakage limits calculated for each local leak rato test. Each containment isolation valve should be individually leak rate tested if practicable. When valves can only practically be tested in groups, the group limit should be set such that excussive leakage through any individual valve, even the smallest, is detected and appropriate corrective actions taken.
PECo Response This issue was discussed among the NRC, EG&G-Idaho and PECo in a telecon on April 18, 1991. During the telecon, PECo described a Residual Heat Removal (RHR) penetration which-has a 24-inch and a 1-inch valve in parallel. Because of the difference in size between the two valves, we are unable to assign a maximum penetration leak rate that is low enough to detect significant leakage from the 1-inch valve and high enough to allow acceptable leakage from the 24-inch valvo.
The NRC indicated that installation of block valves, which would allow individual testing of the valves, is discouraged because of the risk of the block valves being inadvertently closed. The NRC also indicated that they would not encourage assigning a low leakage rate, suitable for the 1-inch valve, because it could result in unnecessary corrective actions on the non-degraded 24-inch valve.
Therefore, it was concluded that the provisions of the Relief Request approval had been met.
- 8. The licensee has identified check valve disassembly as the alternate testing to verify the reverse flow closure capability for the keep fill valves addressed in relief requests 14-VRR-1 and 14-VRR-3. The NRC staff considers valve disassembly and inspection to be a maintenance procedure that is not a test and not equivalent to the exercising produced by fluid flow. This procedure has some risk which may make its routine use as a substitute for testing undesirable when some method of testing is possible.
The licensee is encouraged to investigate methods of verifying the reverse flow closure of these check valves other than disassembly and inspection. For these keep fill series check valve pairs, the NRC has found acceptable verifying by positive means (such as leak testing) that at least one of the series valves is closed once every three months. No additional testing needs to be performed unless there is an indication that the closure capability of the pair of valves is questionable, then both valves must be l
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,l dec'ared inoperable and repaired or replaced before being returned.to service.
PECo Response l l
Maintenance procedures require visual-inspection-of valve internals for worn or corroded parts. A requirement to manually exercise the valve disk after reassembly has been added to these procedures in accordance with Generic Letter 89-04. -Relief Requests 14-VRR-1 and 14-VRR-3 have been revised in Revision 2 of the Prooram to require partial flow testing of each valve following 02 assembly.
As stated-previously in response to Anomoly 6, PECo is
_ pursuing alternate test methods than valvo disassembly and is pursuing options-for reducing the number of valves being ,
disassembled. PECo will also consider the potential for testing series check valves in pairs.
9.. The licensee _has proposed to tust the serJoe parallel check valves that serve as vacuum breakers fer the HPCI/RCIC turbine exhaust linos as-units by verifying a forward flow pathLthrough each group, refer to relief request GVRR-4.
TheseLvalves also perform a safety function in the closed
- position ta_ prevent steam from being directly introduced into-the torus airspace. In a telephone conversation, the licensee recognized the closed safety function of those valves; this change should be reflected in future IST program submittals. Also, the licensee should verify the reverse' flow closure of-thet., talves as a unit during quarterly HPCI/RCIC pump testing. If the forward flow -
capability or reverse flow closure capability of the' valve group'is questionable, the licensee should declare all valves in.the group' inoperable and replace, repair, or verify the operational readjness of each valve prior to placing it back into servica. :
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-PECo Response
'Ralief Request'GVRR-4 has been revised'in Revision 2 of the Program to include reverse exercising.
l: '10 . The licensee.has requested relief from exercising and measuring the stroke time of the main steam automatic depressurization valves,'-RV-2(3)-01-071A, -071B, -071C,
-071G, and -071K'. The-licensee proposed to exercise these
. valves during refueling outages which should demonstrate l their ability.to stroke to their safety function position.
However, the-proposed alternate. testing does not adequately monitor for degradation of these valves.. Therefore,-the licenseo should assign a'mcximum stroke time limit that is
' based on previous test data to these valves and verify that they stroke within that limit during testing. The measured
l Page 7 stroke times need not be trended or compared to previous values, but if the maximum limit is exceeded, the valve should be declared inoperable and corrective actions taken in accordance with IWV-3417(b).
PECo Response Relief Roquest 01-VRR-1 has been revised in Revision 2 of the Program to include stroke time requirements. No actual stroke time test history currently exists for these valves which would allow the assignment of meaningful maximum stroke time limits. Test data will be obtained for each l
unit during startup from occh unit's next refueling outage.
The resultant maximum stroke time limits will then be included in the appropriate Surveillance Tests (STs). STs for Unit 2 will be revised within 6 months from startup of Cycle 10 and STs for Unit 3 will be revised within 6 months from startup of Cycle 9. As stated by the NRC in Anomoly 10, the measured stroke times will not be trended or compared to previous values, but if the maximum limit is exceeded, the valve will be declared inoperable.
2190a. doc
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