|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N8911999-10-15015 October 1999 Forwards Rept of Changes,Tests & Experiments at Pilgrim Nuclear Power Station for Period of 970422-990621,IAW 10CFR50.59(b).List of Changes Effecting Fsar,Encl ML20217D3951999-10-13013 October 1999 Forwards Request for Addl Info Re Util 990806 Submittal on USI A-46, Implementation Methodology Used at Pilgrim Nuclear Power Station, Per GL 87-02 ML20217E1581999-10-0808 October 1999 Forwards Insp Rept 50-293/99-05 on 990726-0905.Three Violations Noted & Being Treated as Ncvs.Violations Include Failure to Assure That Design Bases Correctly Translated Into Specifications ML20217C3151999-10-0606 October 1999 Forwards Scenario Package for Pilgrim Nuclear Power Station Nrc/Fema Evaluated Exercise Scheduled for 991207.Without Encl ML20217D5591999-10-0505 October 1999 Documents Pilgrim Nuclear Power Station Five Yr Survey of Main Breakwater.Survey Has Determined That Pilgrim Main Breakwater Is Intact & Remains Adequately Constructed to Perform Designed Safety Function ML20217C8051999-10-0505 October 1999 Forwards Proprietary Results of Audiologic Evaluations for Jp Giar,License SOP-10061-3.Attachment Clearly Shows Requirements for Operator Hearing Ability Are Met. Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML20212J8301999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Pilgrim Nuclear Power Station.Staff Conducts Reviews for All Operating NPPs to Integrate Performance Info & to Plan Insp Activities at Facility Over Next Six Months ML20216J9961999-09-29029 September 1999 Forwards Resume of Person Identified as Acting RPM in Licensee to NRC Re Notification That Person Named in License Condition 11 of 20-07626-02,is No Longer Employed at Pilgrim Station.Resume Withheld,Per 10CFR2.790 ML20212F7871999-09-24024 September 1999 Advises That Util 990121 Application for Amend Being Treated as Withdrawn.Proposed Changes Would Have Modified Facility UFSAR Pertaining to Values for post-accident Containment Pressure Credited in Pilgrim Net Positive Head Analyses ML20212H1381999-09-23023 September 1999 Submits Info in Support of Request Filed on 990730 to Grant one-time Exemption from 10CFR50,App E,Authorizing Biennial Full Participation Emergency Preparedness Exercise to Be Conducted in 2002 Instead of 2001 ML20212H1441999-09-23023 September 1999 Withdraws 990121 Request for License Change Re Emergency Core Cooling Sys Net Positive Suction Head,Due to Incorrect Datum Preparation ML20212C2861999-09-16016 September 1999 Forwards SER Accepting Licensee 981123 Request for Relief RR-E1,RR-E5,RR-E6 Pursuant to 10CFR50.55a(a)(3)(i) & Request for Relief RR-E2,RR-E3 & RR-E4 Pursuant to 10CFR50.55a(a)(3)(ii) ML20216F3451999-09-16016 September 1999 Forwards Summary Rept Providing Results of ISI Conducted at PNPS on-line & Refueling Outage (RFO 12) ML20216E7111999-09-0909 September 1999 Forwards License Renewal Application Including Form NRC-398 & Form NRC-396 for Jp Giar,License SOP-10061-3.Without Encls ML20216E5891999-09-0707 September 1999 Forwards Copy of Pilgrim Station Organization Structure. Encl Refelcts Changes in Upper Mgt Level Structure.Changes Were Effective 990901 ML20211M4501999-09-0303 September 1999 Informs That Pilgrim Nuclear Power Station Plans to Conduct Full Participation Emergency Preparedness Exercise with Commonwealth of Ma on 991207,IAW 10CFR50,App E,Section IV.F.2 ML20211M9161999-08-31031 August 1999 Submits Review & Correction of Info in Reactor Vessel Integrity Database (Rvid),Version 2,re Pilgrim Station ML20211J8391999-08-30030 August 1999 Forwards Rev 1 to Provisional Decommissioning Trust Agreement for Plant,Changing Portions of Agreement to Permit Up to Two Distributions & Clarify Formula for Distribution ML20211H5701999-08-27027 August 1999 Forwards Insp Rept 50-293/99-04 on 990610-0725.Two Violations Identified Being Treated as non-cited Violations ML20211C3381999-08-19019 August 1999 Provides semi-annual LTP Update,Including Schedule, Commitment Descriptions,Progress Since Last Update & Summary of Changes.Rev Bars Indicate Changes in Status Since Last Submittal ML20210U7521999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opossing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U6691999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opposing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U5761999-08-18018 August 1999 Responds to Opposing Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts. Informs That for Sale,Nrc Responsible for Only Ensuring That Entergy Technically & Financially Qualified to Operate NPP ML20210U5151999-08-17017 August 1999 Forwards Notice of Withdrawal of Application for Approval of Indirect Transfer of FOL for Pilgrim in Response to .Approval No Longer Needed Since Beco Sold Interest in Pilgrim to EOI on 990713 ML20211B3841999-08-16016 August 1999 Forwards Response to NRC Second RAI Re Pressure Locking & Thermal Binding of SR power-operated Gate Valves ML20210U4831999-08-13013 August 1999 Forwards fitness-for-duty Program Performance Data Sheets for Period of 990101-0630,per 10CFR26.71(d) ML20210S0891999-08-0909 August 1999 Forwards Amend 11 to Indemnity Agreement B-48 Signed by Boston Edison Co & Entergy Nuclear Generation Co ML20210R6251999-08-0606 August 1999 Provides Supplementary Info on USI A-46 Implementation Methodology at Pilgrim Station,To Enable NRC to Perform Evaluation & Issuance of Plant Specific SER for Plant ML20210M9411999-08-0202 August 1999 Requests That NRC Treat Pending Actions Requested by Beco Prior to 990713,as Requests Made by Entergy.Ltr Requests That Minor Administrative Changes to License Amend 182 & Associated Ser, ,reflect 990713 Transfer ML20210H8761999-07-30030 July 1999 Requests That NRC Grant Exemption from Requirements of 10CFR50,App E,Section IV F,Which Would Authorize Rescheduling of 2001 Biennial Full Participation Emergency Preparedness Exercise for Pilgrim Station to 2002 ML20210H8661999-07-29029 July 1999 Provides Revised Response to GL 96-06 & Addresses NRC Insp Concern for Containment Penetration X-12.Info Submitted to Facilitate NRC Review & Closeout of Subject GL for Plant ML20216E2321999-07-26026 July 1999 Discusses GL 92-01,rev 1,suppl 1, Rv Structural Integrity. NRC Revised Info in Rvid & Releasing as Rvid Version 2 ML20216D4131999-07-22022 July 1999 Informs That J Conlon,License OP-11040-1,terminated Employment with Beco on 990703,per 10CFR50.74.Individual Will Not Participate in Util Licensed Operator Requalification Training Program ML20210E2231999-07-20020 July 1999 Discusses Arrangements Made by Dennis & M Santiago During 990615 Telephone Conversation for NRC to Inspect Licensed Operator Requalification Program at Pilgrim During Wk of 991004 ML20210C4151999-07-19019 July 1999 Informs That Util Intends to Submit Approx Eight Licensing Actions in FY00 & Eight in FY01,in Response to Administrative Ltr 99-02.Actions Are Not Expected to Generate Complex Reviews ML20210A9441999-07-14014 July 1999 Responds to Re Changes to Pilgrim Nuclear Power Station Physical Security Plan Identified as Issue 2,rev 14, Addendum 1,respectively.No NRC Approval Is Required IAW 10CFR54(p) ML20210F3711999-07-14014 July 1999 Informs NRC That Effective 990713,listed Pilgrim Station Security Plans Have Been Transferred from Boston Edison to Entergy & Are Still in Effect ML20209G2251999-07-0909 July 1999 Forwards Insp Rept 50-293/99-03 on 990419-0609.Five Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C. Several Individual Tagging Errors Occurred ML20209C4661999-07-0707 July 1999 Forwards SE Accepting Addendum on Proposed Change in Corporate Ownership Structure Involving Entergy Nuclear Generation Co ML20209C3851999-07-0606 July 1999 Forwards Redacted Draft of Decommissioning Trust Agreement Re Transfer of PNPS & NRC Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generating Co ML20209C7761999-07-0606 July 1999 Submits Annual Summary Rept of Changes Made to QAP Description as Described in QA Manual,Vol Ii.Rept Covers Period of Jul 1998 Through June 1999.No Changes Made During Period ML20196J7251999-07-0101 July 1999 Informs of Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, for Pilgrim Nuclear Power Station ML20209B9411999-06-30030 June 1999 Discusses Deferral of IGSCC Welds to RFO 13.Deferral of Welds to Refueling Outage 13 Does Not Impact Acceptable Level of Quality & Safety Per 10CFR50.55(a)(3)(i) Since Plant in Compliance W/Exam Percentage Requirements ML20209B9431999-06-30030 June 1999 Provides Formal Notification That Closing Date for Sale & Transfer of Pilgrim Station Scheduled to Occur on 990713. a Wang Will Be Verbally Notified of Time of Sale Closing ML20196H2381999-06-29029 June 1999 Forwards SER Denying Licensee 980820 Request for Alternative Under PRR-13,rev 2 for Use of Code Case N-522 During Pressure Testing of Containment Penetration Piping ML20209B9791999-06-29029 June 1999 Forwards Rev 13A to Pilgrims COLR for Cycle 13,IAW TS 5.6.5 Requirements.Rev 13A Provides cycle-specific Limits for Operating Pilgrim During Remainder of Cycle 13 ML20209A8761999-06-28028 June 1999 Forwards SER Authorizing Licensee 990317 Relief Request to Use ASME Code Case N-573 as Alternative to ASME Code Section XI Article IWA-4000 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20209A8701999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant,Reporting Status of Facility Y2K Readiness Encl ML20210U5901999-06-25025 June 1999 Opposes Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts.Expresses Skepticism Re Claim by Companies That Consumers Will Benefit from Proposed Consolidation & four-year Freeze in Base Rates ML20209C3431999-06-22022 June 1999 Forwards Addendum 1,Rev 14 to Pilgrim Station Security Plan,Iaw 10CFR50.54(p)(2).Changes Proposed Have Been Implemented & Constitute Increase in Plant Defense Plan Commitments.Encl Withheld,Per 10CFR73.21 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062E0071990-11-14014 November 1990 Forwards List of Unimplemented GSIs at Facility,Per Generic Ltr 90-04 ML20062D6651990-11-0808 November 1990 Ack Receipt of Forwarding Util Evaluation of NRC Inspector General Rept 90N-02 Re Offsite Emergency Planning ML20058G9761990-11-0707 November 1990 Forwards Safety Insp Rept 50-293/90-20 on 900816-1008 & Notice of Violation ML20058C5501990-10-26026 October 1990 Requests Written Policies & Procedures Needed for NRC Preparation for Planned fitness-for-duty Insp ML20062B4311990-10-17017 October 1990 Advises That 901012 Response to Generic Ltr 90-03 Re Vendor Interface for safety-related Components,Acceptable ML20062B7161990-10-12012 October 1990 Extends Invitation to Attend 910220-21 Util Symposium/ Workshop in King of Prussia,Pa Re Engineering Role in Plant Support.Interest to Participate,Intent to Attend & Approx Number of Representatives to Attend Requested by 901115 ML20062B6281990-10-12012 October 1990 Forwards Insp Rept 50-293/90-21 on 900905-07.Insp Conducted to Review Event of 900902-03 Which Involved Number of Component Malfunctions & Operational Complications Following Shutdown ML20059N7251990-10-0101 October 1990 Requests That Matls Listed in Encl Be Furnished to Assist Maint Program Team Insp Scheduled for 901105-16 ML20059K6901990-09-11011 September 1990 Forwards Transcript of 900906 Public Meeting in Plymouth,Ma W/State & Local Officials Re Emergency Planning.W/O Encl ML20059H5871990-09-0101 September 1990 Advises That Reactor Operator & Senior Reactor Operator Exams Scheduled for 901203.Encl Listed Ref Matl Requested ML20059J6521990-08-29029 August 1990 Forwards Safety Insp Rept 50-293/90-09 on 900806-10.No Violations Noted.Concludes That Engineering & Technical Support Organizations Continue to Provide Strong Station Support ML20059A1481990-08-17017 August 1990 Forwards 900816 Summary of 900807 Meeting Re Inservice Testing Program ML20058P0471990-08-0909 August 1990 Forwards Safety Insp Rept 50-293/90-18 on 900709-13.No Violations Noted ML20058N0401990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Power Reactor Licenses in Region 1 Should Initiate Similar Program to Provide Sharing of Info & Experiences Involving Engineering Initiatives & Solution to Problems Common to All ML20056A4801990-07-30030 July 1990 Forwards Safeguards Insp Rept 50-293/90-16 on 900625-29.No Violations Noted.One Unresolved Item Identified ML20058L7051990-07-27027 July 1990 Forwards Safety Insp Rept 50-293/90-17 on 900625-29.No Violations Noted ML20055F2461990-06-29029 June 1990 Forwards Safety Insp Rept 50-293/90-13 on 900501-0611.No Violations Noted.Repetitive Failures of Diesel Driven Fire Pump Noted,Requiring Increased Mgt Attention ML20059M8421990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20247R8071989-09-21021 September 1989 Forwards SALP Rept 50-293/88-99 for 880516-890630.Instances of Deviation from Approved Practices & Lack of Attention to Detail Which Led to Challenges to Plant Equipment & Personnel Noted ML20247K6661989-09-0707 September 1989 Forwards Insp Rept 50-293/89-07 on 890525-0710 & Notice of Violation ML20246K5091989-08-24024 August 1989 Accepts Summary of QA Program Description Changes for 1989, Forwarded by ML20246L7821989-08-23023 August 1989 Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000.Failures to Properly Plan, Supervise & Inspect Tagout of Circuit Breakers Directly Contributed to Event ML20246D7261989-08-18018 August 1989 Submits Response to Re Plant Power Ascension Program.Util Proposal to Defer Phase 2 of Shutdown from Outside Control Room Test to Planned Fall 1989 mid-cycle Outage Accepted IR 05000293/19890071989-08-18018 August 1989 Approves Reactor Operation Up to 75% of Full Power Per Licensee Power Ascension Test Program.Nrc Findings Docketed in Insp Repts 50-293/89-07 & 50-293/89-08 & Status of Emergency Preparedness for Communities Encl ML20246J4811989-08-18018 August 1989 Clarifies NRC Position Re Definition of Extremity for Purposes of Setting Occupational Exposure Limits.Due to Misunderstanding,No Enforcement Action Planned If Licensee Procedures Incorporated Misunderstanding ML20246G1861989-08-18018 August 1989 Approves Reactor Operation Up to 75% of Full Power Per Licensee Power Ascension Test Program.Nrc Findings Docketed in Insp Repts 50-293/89-07 & 50-293/89-08 & Status of Emergency Preparedness for Communities Encl ML20245F1781989-07-31031 July 1989 Forwards Insp Rept 50-293/89-06 on 890411-0524.No Violations Noted.Licensee Actions W/Respect to 890503 Turbine Trip/Reactor Scram Demonstrated Excellent Approach to Problem Investigation & Resolution ML20247D0181989-07-18018 July 1989 Ack Receipt of Re Response to NRC Bulletin 89-003, Inadequate Latch Engagement in Hfa Type Relays Mfg by Ge. Necessary Actions Performed to Address Issues in Bulletin ML20246N3921989-07-14014 July 1989 Forwards Safety Insp Rept 50-293/89-09 on 890619-22.No Violations Noted ML20246D4961989-07-0606 July 1989 Advises That 880713 Response to NRC Bulletin 88-004, Potential Safety-Related Pump Loss Acceptable ML20246A7561989-06-26026 June 1989 Approves Reactor Operation Up to 50% Full Power,Per Util Power Ascension Test Program & Confirmatory Action Ltr 86-10.Assessment of Licensee Readiness for Release from NRC Approval Point 3 & Related Info Encl ML20246B5961989-06-22022 June 1989 Forwards,For Info,Nrr Ack Receipt of Petition Filed by Ecology Ctr of Southern CA & Stating That Petition Being Treated Under 10CFR2.206 of Commission Regulations ML20245A5371989-06-0909 June 1989 Forwards Insp Rept 50-293/89-05 on 890311-0410.Weaknesses Noted Re Evaluation of Failure Rate & Root Causes for Failures of Airlock Doors & Interlocks ML20244C2121989-06-0707 June 1989 Responds to Util 881011 Response to Generic Ltr 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. Implementation Schedule Contingent Upon Resolution of Procedure ML20244C2751989-06-0606 June 1989 Forwards Draft Safety Evaluation Re Plant Compliance W/ 10CFR50.62, ATWS Rule. Requests Response to NRC Concerns Re Diversity & Testability of Alternate Rod Injection & Reactor Pump Trip Sys NUREG-1275, Informs That Util Fulfilled Requirements of Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety Related Sys1989-06-0202 June 1989 Informs That Util Fulfilled Requirements of Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety Related Sys ML20247P5501989-06-0101 June 1989 Forwards Request for Addl Info on Proposed Tech Specs Change Re Visual Insp of High Energy Piping.Listed Concerns Based on Review of Bechtel Calculation 17322-S5,Rev 1 ML20247M2661989-05-26026 May 1989 Forwards Director'S Decision,Ltr of Transmittal & Fr Notice in Response to Ocre 2.206 Petition Expressing Concerns Re 880309 Power Oscillation Event at LaSalle Unit 2 & Request to Reopen Rulemaking on ATWS Issue.W/O Encls ML20246P6051989-05-15015 May 1989 Forwards Notice of Withdrawal of Application for Amend to License DPR-35.Amend Would Modify Tech Specs Re ECCS Surveillance Requirements ML20247D5481989-05-0808 May 1989 Forwards Augmented Insp Team Rept 50-293/89-80 on 890413-19 & 17-26.Team Concluded That Safety Significance of 890412 Pressurization Transient Was Minor,Though Event Raised Concerns Re Proximate Human Factors & Equipment ML20246N7951989-05-0404 May 1989 Forwards Mgt Meeting Rept 50-293/89-04 on 890328-30 W/Commonwealth of Ma & Local Officials ML20247A6911989-05-0303 May 1989 Extends Invitation to Attend Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Agenda & Info Re Lodging Arrangements Encl ML20245H8371989-04-26026 April 1989 Forwards SAIC-89/1121, In-Progress Audit Rept of Dcrdr at Boston Edison Co Pilgrim Nuclear Power Station & SAIC-89-1119, In-Progress Audit Rept for Boston Edison Co Pilgrim Nuclear Poser Station Spds ML20245H9551989-04-26026 April 1989 Forwards Insp Rept 50-293/89-01 on 890206-0310 & Notice of Violation ML20245J1441989-04-25025 April 1989 Advises That 880921 & 890302 Responses to NRC Bulletin 88-007 & Suppl 1, Power Oscillations in BWRs Meet Requirements of Both Bulletins ML20244E4611989-04-14014 April 1989 Requests Prompt Review & Reporting of Status of Implementation of TMI Action Plan Items at Facility.Printout of All TMI Items Annotated Where Tracking Sys Indicates That Implementation Not Complete Encl ML20244C2771989-04-10010 April 1989 Informs of Completion of Followup on Plant Regulatory Effectiveness Review Effort & Activities Re TAC 56995. Previous Compensatory Measures Removed as Result of Implementing Corrective Action ML20244A6931989-04-0707 April 1989 Forwards Mgt Meeting Rept 50-293/89-43 on 890309 to Discuss Util Followup Actions to 890304 Reactor Scram ML20244A6281989-04-0303 April 1989 Forwards Insp Rept 50-293/88-37 on 881227-890205.Violation Noted Re Failure to Control Locked High Radiation Area Access ML20236A8451989-03-0303 March 1989 Approves Reactor Operation Up to 25% of Full Power Per Util Power Ascension Test Program & Confirmatory Action Ltr 86-10.Urges Util to Cooperate W/Commonwealth of Ma & Local Govts to Further Improve State of Emergency Preparedness 1990-09-11
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217D3951999-10-13013 October 1999 Forwards Request for Addl Info Re Util 990806 Submittal on USI A-46, Implementation Methodology Used at Pilgrim Nuclear Power Station, Per GL 87-02 ML20217E1581999-10-0808 October 1999 Forwards Insp Rept 50-293/99-05 on 990726-0905.Three Violations Noted & Being Treated as Ncvs.Violations Include Failure to Assure That Design Bases Correctly Translated Into Specifications ML20212J8301999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Pilgrim Nuclear Power Station.Staff Conducts Reviews for All Operating NPPs to Integrate Performance Info & to Plan Insp Activities at Facility Over Next Six Months ML20212F7871999-09-24024 September 1999 Advises That Util 990121 Application for Amend Being Treated as Withdrawn.Proposed Changes Would Have Modified Facility UFSAR Pertaining to Values for post-accident Containment Pressure Credited in Pilgrim Net Positive Head Analyses ML20212C2861999-09-16016 September 1999 Forwards SER Accepting Licensee 981123 Request for Relief RR-E1,RR-E5,RR-E6 Pursuant to 10CFR50.55a(a)(3)(i) & Request for Relief RR-E2,RR-E3 & RR-E4 Pursuant to 10CFR50.55a(a)(3)(ii) ML20211H5701999-08-27027 August 1999 Forwards Insp Rept 50-293/99-04 on 990610-0725.Two Violations Identified Being Treated as non-cited Violations ML20210U7521999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opossing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U5761999-08-18018 August 1999 Responds to Opposing Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts. Informs That for Sale,Nrc Responsible for Only Ensuring That Entergy Technically & Financially Qualified to Operate NPP ML20210U6691999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opposing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U5151999-08-17017 August 1999 Forwards Notice of Withdrawal of Application for Approval of Indirect Transfer of FOL for Pilgrim in Response to .Approval No Longer Needed Since Beco Sold Interest in Pilgrim to EOI on 990713 ML20216E2321999-07-26026 July 1999 Discusses GL 92-01,rev 1,suppl 1, Rv Structural Integrity. NRC Revised Info in Rvid & Releasing as Rvid Version 2 ML20210E2231999-07-20020 July 1999 Discusses Arrangements Made by Dennis & M Santiago During 990615 Telephone Conversation for NRC to Inspect Licensed Operator Requalification Program at Pilgrim During Wk of 991004 ML20210A9441999-07-14014 July 1999 Responds to Re Changes to Pilgrim Nuclear Power Station Physical Security Plan Identified as Issue 2,rev 14, Addendum 1,respectively.No NRC Approval Is Required IAW 10CFR54(p) ML20209G2251999-07-0909 July 1999 Forwards Insp Rept 50-293/99-03 on 990419-0609.Five Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C. Several Individual Tagging Errors Occurred ML20209C4661999-07-0707 July 1999 Forwards SE Accepting Addendum on Proposed Change in Corporate Ownership Structure Involving Entergy Nuclear Generation Co ML20196J7251999-07-0101 July 1999 Informs of Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, for Pilgrim Nuclear Power Station ML20196H2381999-06-29029 June 1999 Forwards SER Denying Licensee 980820 Request for Alternative Under PRR-13,rev 2 for Use of Code Case N-522 During Pressure Testing of Containment Penetration Piping ML20209A8761999-06-28028 June 1999 Forwards SER Authorizing Licensee 990317 Relief Request to Use ASME Code Case N-573 as Alternative to ASME Code Section XI Article IWA-4000 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20195K3071999-06-15015 June 1999 Forwards Safety Evaluation Granting Licensee Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water Sys Piping for Plant ML20195K3851999-06-11011 June 1999 Forwards Copy of Notice of Consideration of Approval of Application Re Proposed Corporate Merger & Opportunity for Hearing.Application Seeks Approval of Proposed Indirect Transfer of FOL for Plant ML20196K9921999-06-0404 June 1999 Informs That NRC Ofc of NRR Reorganized Effective 990328.As Part of Reorganization,Division of Licensing Project Mgt Created ML20207E7351999-05-27027 May 1999 Responds to Requesting Reduction in IGSCC Insp Frequency Per GL 88-01 to Be Performed During Upcoming RFO 12.Forwards SE Re Reduction of IGSCC Insp of Category D Welds Due to Implementation of H Water Chemistry ML20207B6341999-05-26026 May 1999 Informs That Licensee 990415 Submittal Re Financial Position of Entergy Intl Ltd,Llc Will Be Marked as Proprietary & Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act ML20207B7391999-05-24024 May 1999 Forwards from Kc Goss of FEMA to Cl Miller Forwarding FEMA Analysis of Prompt Alert & Notification Sys for Pilgrim Nuclear Power Station.Based on Review,No Significant Problems Exist with Alert & Notification Sys ML20207B0701999-05-24024 May 1999 Responds to Sent to Ofc of Congressional Affairs Requesting Info on Concerns Raised by One Constituent,J Riel Re Y2K Compliance of Pilgrim NPP in Plymouth,Ma ML20207C0321999-05-18018 May 1999 Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co ML20206U7501999-05-17017 May 1999 Forwards Insp Rept 50-293/99-02 on 990308-0418.Two Severity Level 4 Violations Occurred & Being Treated as NCVs ML20206M1891999-05-11011 May 1999 Forwards SE of 980826 Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Sys Piping for Plant ML20206E0551999-04-29029 April 1999 Discusses Bulletin 96-03 Issued on 960506 & Beco Responses ,970207,981230,990121 & 990309 for Pilgrim Npp. Determined That Actions Taken Should Minimize Potential for Clogging of ECCS Suction Strainers ML20206B3031999-04-20020 April 1999 Forwards Insp Rept 50-293/99-01 on 990125-0307.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy.Security Program Was Also Inspected ML20205Q9491999-04-0909 April 1999 Informs That on 990225 NRC Staff Completed PPR of Pilgrim Nuclear Power Station.Staff Conducts Reviews for All Operating NPPs to Develop an Integrated Understanding of Safety Performance ML20205B9391999-03-24024 March 1999 Forwards Second Request for Addl Info Re GL 95-07, Pressure-Locking & Thermal-Binding of Safety-Related Power-Operated Gate Valves ML20204C7871999-03-17017 March 1999 Informs That Application Submitting Transfer of Facility Operating License & Matls License & Proposed Amend, Will Be Marked as Proprietary & Be Withheld from Public Disclosure Pursuant to 10CFR2.709(b)(5) ML20199K8321999-01-22022 January 1999 Forwards Request for Addl Info Re Transfer of Facility Operating License for Plant ML20199H5811999-01-20020 January 1999 Submits Exemption Withdrawal of 10CFR70.24(a) Re Criticality Accident Monitoring Requirements ML20198L7781998-12-22022 December 1998 Forwards Insp Rept 50-293/98-10 on 981020-1208.No Violations Noted.Nrc Regional Specialists Reviewed EP & Fire Protection Programs.Ep Program Was Found to Be Well Implemented ML20198J0891998-12-21021 December 1998 Forwards NRC Response to Me Lampert Re Transfer of Ownership of Pilgrim Station in Response to Senator Kerry Ltr Dtd 981019.NRC Will Terminate License Only When Licensee Remediates Site to Levels Specified in Regulations ML20198J1041998-12-21021 December 1998 Forwards NRC Response to Me Lampert Re Transfer of Ownership of Pilgrim Station in Response to Congressman Markey Ltr Dtd 981019.NRC Will Terminate License Only When Licensee Remediates Site to Levels Specified in Regulations ML20137T2211998-12-17017 December 1998 Responds to to Chairman Jackson Re Concerns About Possible Sale of Pilgrim Station & Waste Disposal Issues.No Application for License Received Nor Contract of Sale Between Beco & Entergy.Record Copy ML20198J1161998-12-17017 December 1998 Responds to to Chairman Jackson in Which Recipient Expressed Concern About Possible Sale of Pilgrim Station & About Waste Disposal Issues.Nrc Has Not Received Application for Transfer of License to Date ML20198P2781998-12-17017 December 1998 Final Response to FOIA Request for Documents.Forwards App a Records Being Released in Entirety.App B Records Being Withheld in Entirety (Ref FOIA Exemption 4) ML20198B2021998-12-0909 December 1998 Advises of Planned Insp Effort Resulting from Licensee Irpm Review.Details of Insp Plan for Next 6 Months & Historical Listing of Plant Issues Encl ML20197H8521998-12-0909 December 1998 Responds to Ltr Sent to Chairman SA Jackson on 981028 Re Concern That NRC Will Not Perform Environ Assessment in Connection with Consideration of Approval of Transfer of License for Plants to Permit Sale ML20196J1201998-12-0404 December 1998 Ack Receipt of 971217 & 30 & 980112,0309,0423 & 0630 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-293/97-02,50-293/97-11,50-293/97-13, 50-293/97-80 & 50-293/98-01.Actions Found Acceptable ML20196B5421998-11-24024 November 1998 Forwards Plant SRO & RO Initial Exam Rept 50-293/98-301OL During Wk of 981016-23 ML20196F7631998-11-24024 November 1998 Forwards Insp Rept 50-293/98-203 on 980928-1023.No Violations Noted.Three Issues Identified Re Containment Flooding,Surveillance Testing Criteria & Protection for RBCCW System from High Energy Line Break Inside Drywell ML20196C1191998-11-20020 November 1998 Forwards Insp Rept 50-293/98-08 on 980907-1019.No Violations Noted.During Insp Period,Chemical Decontamination of Residual Heat Removal Sys Was Well Planned & Implemented Which Reduced Radiation Doses in Heat Removal Quadrants ML20195H7361998-11-16016 November 1998 Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 981016 & 981019-23 at Facility.Nine Applicants Were Administered Exam & Nine Passed.Licenses Issued & Individual Test Results Encl.Without Encl ML20155C4781998-10-29029 October 1998 Forwards RAI Re Resoultion to GL 96-06 Issues at Plant,Unit 1.Response Requested by 981130 ML20154J7881998-10-0808 October 1998 Authorizes Mb Santiago to Administer Initial Written Exams to Applicants Listed (Except Applicants Redlined), on 981016.NRC Region I Operator Licensing Staff Will Administer Operating Tests During Week of 981019 1999-09-30
[Table view] |
Text
P
/,//
' ,s n
, 2
. . . . #[ ATTAc-amerJf i ..
UsetTED STAT M ATOMIC ENWISY COMMISWON <j O[ ' _ ..
January 7, 1975 y Docket No. 50-293 gL 7 9 (d Boston Edison Company ATTN: ter. Maurice J. Feldesan h Vice President [v Operations and Engineering 800 Boylston Street
{
Boston, Massachusetts 02199 Gentlemen:
Our review of your Technical Specifications related to insta11d filter 43 systems indicates a need for additional Limiting These conditione are required for Operation is order to (140) and Surveillance Requirements.
O ensure high confidence that the systems will function reliably, when moeded, at a degree of efficiency equal to or better then that assumed in O the accident smalyses.
O In order to assist you in the preparation of appropriate revisises,as have prepared model Technical Specifications which include IAO's, Serve 111ance Requirements and Bases for the following Pilgria Unit 1 ovetems:
- 1) Main Control Room Environmental Control Systems N 2) Standby Gas Treatment System You are r e to submit by no later then 45 days from the date of O this 1 lication for amenement to your Ise - tuns would chemSe the Techairal Specifications related to tastalled f11ter eyetens O so as to be in comforenace with the requiremente in the amm1M model Technical Specifications, Sincerely, m .
ww' Deania L. Eiemaan ief Operating Ranctore Breech #2 Directorate of Licensing Enclosera Model Technical Specificatione f ces See mest page h
/o ao 8701300160 870127 PDR ADOCK 05000293 n P ppR
- - - }
P Y ",
- ATTAcHmeMT 2 /, /, ff,2 A UttfTED STATES ATOMIC ENUW3Y COMMISS4CN
- d
,O i , , ,,
' -o- .
January 7, 1975 h Docket No. 50-293 6% g a 9 (d Boston Edison Company
[
ATTN: Mr. Maurice J. Feldmann Vice President [g h
Operations and Engineering T 800 Boylston Street Boston, Massachusetts 02199 /
Centlement Our review of your Technical Specifications related to installed filter e systems indicates a need for additional Limiting These are Conditions required in for Operation order to (LCO) and Surveillance Requirements.
O ensure high confidence that the systems will function reliably, when needed, at a degree of efficiency equal to or better than that assumed in C the accident analyses.
O In order to assist you in the preparation of appropriate revisines, we have prepared modal Technical Specifications which include LCO's, Surveillance Requirements and Basse for the following Pilgria Dait i systems:
- 1) Main Control Room Ravironmental Control Systems CM 2) Standby Ces Treatment System You are requasted to submit by no later thes 45 days from the dat_a_of this letm == .pplication for -- t to your license tnat would O
change the Technical Specificatione related to installed filtar systeme g so as to b- in conformance with the requirensets in the maniamed model Technical Specifications.
Sincerely,
~
wvwas n-f .
Dennis L. Zie= ann, iaf Operating Reactors Branch #2 Directorate of Licensing Encloeures Model Technical Specifications f h
A ect See next page
,to
/o t 8701300160 870107 PDR ADOCK 0500009J P PDR
r'r,eus
\
] , l}( Nh] --< wm $';jf$Cf f::;; <; fi - i;5
- l% <
,.4
); gt gi,; " ,
r- .-g j '
q .
Boston Edison Company O cc w/ enclosures:
Mr. Dale G. Stoodley, Counsel Boston Edison Company 800 Boylston Street Boston, Massachusetts 021M Mr. J. Edward Howard, Superintendent Nuclear Engineering Department Boston Edison Company 800 Boylston Street Boston, Massachusetts 02199 Mr. Grant Baston, Pilgrim Division Beed Boston Edison Company EyD #1 Rocky Hill Road Plymouth, Massachusetts 02360 N Mr. Winfield M. Sides, Jr.
Quality Assurance Manager O 800 Boylston Street Boston, Maseachusetts 02199 O
O Anthony Z. Rotsman, Esquire Berlin, Roisaan and Kessler 1712 N Street, N. W.
9 Washington, D. C. 20036 g Plymouth Public Library North Street N Plymouth, Massachusetts 02360 Mr. J. E. Larson Senior Licensing Engineer o and Co-ordinator j Boeton Edison Company o EyD #1 Rocky Hill Road Plymouth, Massachusetts 02360 0
~ e v.
o0I240 ooo, O '1. a
$ C'A TECHr.!CfL SPECIFICATTCNS
+
- 4.7 SURVEILLANCE REGUIRDE'iTS 3.7 LIMIT!*i CONDITIONS FOR OPERATION
- 8. Standby Gas T-eatr.ent Systen 8. Stan6y f%s Trectment System l
- 1. At least once per operating cycle, the
- 1. Except as specified in Specification following conditions shall be de.,onstrated.
3.7.8.3 below, both circuits of the .
standby gas treate.cnt system and the e diesel ger.crators required for a. Pressure drop across the conbined operation of such circuits shall be HEPA filters and charcoal adsorber k.D ^
banks is less than inches of /
operable at all times hten secondary wateratthesysten@<esignflow containment integrity is required.
rate. *
- 2. a. The results of the in-place cold DOP d,f, b. fnlet heater input is capable of
- p.and halo enated hydrocarben tests at I4f design f ows on HEPA filters and
- freducingR.H.from100to707.R.H. .
- o wC charcoal adsorber banks shall show c. Air distribution is uniform within M
>99% 00P removal and > 99% l
- . ~ -~ ~
hydrocarbon~~removal.
~
Iy 20% across HEPA filters and charcoal l aggo7yers, results of laboratory carbon } F -
. . ( b. 2. a. e tests and sample analysis of.
sasple analysis shall show >95% Specification 3.7.8.2,sh,g,1) jy
.l _w amoaccmurethyl iodide rEnoval ,,
I at a velocity within 20 percent of > 8^ performed initially a_nd at least once.per year for standby service .
( actuglsystendesign,0.5to1.5 cr after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of .3 inlet methyl iodido concentra- '
system operation and following -
t on. >,,70% R.H. and >190*F.
j [ g
( significant painting. fire or chemical release in any ventilation
- c. Fans shall be shown to operate within / zone coemunicating with the system. .s j J
?,,10% design ficw. ~
I
- b. Cold DOP testing shall be perfenned
~~ ~
E Q;
~f pg wee.1 oNI] Ym g,4 cnooA -flow 7' -
'after each complete or partial replacement of the HEPA filter bank or after any structural <J d
em7 M '.I ' 3 N e n,, g, c p u ,a 2 maintenance on the system housing.
(evtou J b y E A (
g * ~ ~N" h009 d
O OO I24 BWR TECMMICAL 59ECIFICATIO'iS l .,,4
- ]F 4.0 St.'RVEILLA:tCE REQUIRFT.ENTS ; . _!
3.7 LIMITING CONDITIONS FCR OPERATION !
- c. 911cgenated hydrocarbon testing shall M be perforred after each complete er ~
I-s partial rcplaccecnt of the charcoal adsorber bank or after any structural Cl i ,
gp traintenar.cc on the3systers housing.
) D
- d. Each circuit shall be cperated with
- [./
the heaters ori at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every
[ ,/ ~
& gp%)
M f Test sealing of gaskets for housing
. a~
f Ll/[k doors tWnstream of the HEPA filters i
" and charcoal adsorbers shall be performed ' ;."
8 at and in confomance with each test 4 ef. h [,.< C - [/
perfonred for compliance with : 0; Specification 4.7.6.2.a and Specification 3.7.B.2.a.
r,
- M O.
System drains e.cre present shall be 1%
- 3. Frcm and after the date that one qucrterly for adequate water level in Je l circuit of the standby sas treatment loop-seals.
system is made or four.d to be At least once per operating cycle inoperable for any reason, recctor 4. 4.
operation and fuel handling is automatic initiation of each branch of the standby gas treatment system permissible only during the succeeding a seven days unless such circuit is sooner *"-* shall be demonstrated. '
made operable, provided that during j7J.At least once per operating cycle 7 1 such seven days allsactive components / b. msnual operability of the bypass valve g.
of the other standby gas treatment M g/ /g. c) /
(
- F # yc for filter cooling shall be dueenstre circuit shall be operable.
( ao
- 4. If these conditions cannot be met, c. When one circuit of the standby gas treatment system becomes inoperable ,
procedures shall be initiated t sha H k M a h W inr:ediately to establish reactor o rc
' MN conditions for which the standby not required.
$,pe,$
gas treatment ".ystcn f I m C'T R
~ _
g 00120 0010 .
B G TECH *itCAL SPCCIFICATICNS_
.L ja,,ggg, ~ I 3.7.8 Standby Gas Treatment System Ust the reactor butiding ateosphere to The star.dby gas treatrent system is designed to filter ar.d exh:Both stancy gas treatmant system fans the stack during secondary cantain: cr.t isolatien conditions.
q are destgr.ed to autcrratically start upon contairrr.ent isolationShould andonetosystem maintain the reactor b pressure to the design r.egative pressure so that all leakage should be in-leakege.Each of the two fans has 10 fail to start, the redundant system is designed to start automatically.
[percentcapacity.
High efficiency particulate absolute (HEPA) filters are installed before and after the charcoal ad to minimize potential release of particulates to the envirorcent and to prevent clogging of the iodine adsorbers.
environment.
The charcoal adsorbers are installed to reduce the potertial g release bypass leakage for the ch:rcoal *.dsorbces and a HEPA cffic:crcy of.ethv )iedide at least 99gpercent rer.- al o particulates. The laboratcry carbo.i scep'c test results sheu!d indicate a ....m uuIf the ef icier,cies rencval efficiency of at least 95 percent for expected accident conditions. be less than the of the HEPA filters and charcoal adsorbers are as specified, the resulting doses wil' 1Q. fro 100 cuidelines fs-.de,,, accidents analyzed.J Cperation of the fans significant'y different f ,
pT EN /b design flow will change the ren.,vai ctricicncy of the NEPA filters and charcoal adsorbers. !
Only one of the two standby gas treatment systems is needed to cicanup the reactor buildir.g at=os If one system is found to be inoperable there is no israediate threat to Mh upon contairment isolation.
- [. the containment system performance and reactor operation or refueling operatio'n g
repairs are being made.
standby gas treatment system is not required.
S.h .a sk . of
,g'
' E8
. u. .e 4 ~
f p g [' :al l u us-
..E Q
oas T:Cseca &%ues i i 9 -st}., ,
Standby Gas Treat.-ent Syste- less thar 6 nches of water at 4.7.3.
d b s are not c ogged by excessive Pressure the system design drop across flow rate will indicate thethatco-bined the filters andHEPA a sor er filters and ctarcoal a .ounts of foreign matter.at least once por sela op* rating cycle c red h E2ft to sPc. systen i.&.!-t-:r: ;cd eparfemarce rre u
- nrbersca;;bility, The frequency of tests and ll]
rfom as evaluat s'oro tne r plecc.crcoal ahalysis are nermw to sh adsorders uith et haloganated tht t hydrocarton refri -
ge. r orted in accordance with USAEC Report 07-1082. for the rer:vai or Standard M-16-1T/ The enarcoal adscrber ef ficiency test procedures should all:w p [#.
I g h can one acsoroer Eachtray, srple emptying should be atof at least two sccples. If test results are unccceptable, least or.e twobed idaall 1.52.
inches adsorbent fec, the in dicacter in,thetray The replacerr.cnt tray, and system for d
amixing length equal shall be repla th
.F# g y lity. Tests of the HEFA filters thickness the adsorber of the traybed.j removed with for the an testadsor'ocnt shocid meet qualified the sane adsorbent according quaAny f Regulatory to Table GuideHEPA 1 of Regul 1.52. filters found da with 00p aerosol shall be performed in acccedance to ANSI N101.1-1972.
shall be replaced with filters qualified pursuant to Regulatoryi Position the test of C.3.d heate. o i
/[ad *4 All elements of the heater should be demonstrated tm to be functional
[ ,, .
capacity.
spre externally 'cag the 'I linear ust fan in op- tion. 0 -rosol shal n of 00P the fan NSb W doo closed check the y ket scal. ny dote .st repea peri ry o ach res,. tive doorptable t re uit an be gaskets airs an '
A88f ns . ad an u. =t*e_
A=-M , h :p n :h = t b: ::d wfs e& g:'
sh:11 b
#j F :yncr. dc;ir.: ;-: p m eat *- tM "It-r/ m e A-Tevel w p, cm i. uy-pass ieaxd5e ii uo th0 5'4L _
h coal adsorber ,
could become contaminatedThefrom determinationthe fumes, of significantchemicals shall be made by or foreig
- Sall be performed as required for operational use. Knowledgeable staff members should be consulted prior the operator on duty at the time of the incident.
to making this determination. umiliv vi siit.er cco.ing i:. inc;n 7 E w o.u.m on of the automatic initiation capn iii b o %~If one standby hpas treatment s reactor operi system is ino asw er ay nem perrorrance capability.This substantiates the avnilability of the operable syste'n and t mast be i.ested daily. can continue for a limited period of time.
er refueling operation
m
~ .T G ooi24 Gboi2 O ..f.4 PWR AND 8WR TECHNICAL SPECIFICATIONS 1.:
I 4.0 SURVE!LLANCE REQUIREE NTS
,.Y
* 'a : .
3.0 LIMITING CON 0!TIONS FOR OPERATION . +m
- 8. Control Roers Air Trea*===t swstem
- 8. Control Room Air Treatment System '
At least once per operatino cycle, the R
- 1. Except as specified in Specification ,, .
pressure drop across the castined MM 3.0.8.3 below, the control room air filters and charcoal adsorter banks .
treatment system and the diesel ( g/ j A h d ' I shall be demonstrated to be less them generators required for operation 6 inches of water at system design fles '
of this system shall he ansrable Ng& y41 9 M -<at all timmt filteority "--Contjainmen is movind. 37# O[ ,, sa2.d a. TThe >_.
tests and sample amelysis of
' 4A 9
Specificat%cn 3.0.8.2 shall be ,4
- 2. a. The results of the in-place cold performed initially and at least - 4 DW and halogenated hydrocartpon I once per year servicei e tests at design ficws on'HEPA or after of ten Fx filters and charcoal adsorber banks /[. en and ft igni %
shall show >995 00P removal and >995 painting, fire er 1 release %
halogenate O ydrocartan removal.- in any ventilation zone communicattig { ;<
- 4
- b. The results of laboratory cartpon I with the systen.
Y?
sample analysis shall show >905
- b. Cold.00P testi shall be perftrum8 , y 4
radiesctive methyl iodide removal /
after each or partial at a velocity within 20% of system Q filter beak er ,
Wip. 0.05 to 0.15 mg/k3 inlet iodide Og., ment of theany structure 1 amistenance en to concentration >955 R.H. and >125'F.
~
system housieg. _j
- c. Fans shall be shown to operate within
+101 design flow.
- c. Malogensted hydrocorten MM et P
- he perferend efter eseh "
b partial repleesment of the datestaadsorb maintenance on the system hose W {
- d. Each cirentt shall be operated at leasGDboves)very-Snth.
I H JV
. m,m. m,, o.d.. _ --
*
#~
~
P'JR AND m:R TEC1"l! CAL SPECIFICATIO:!S_ .q
' I
' ^ '-
f ,
t 4.0 SURVEILLANCE REQUIREMENTS ~ 7, ;
,I 3.0 LIMITI E CONDITIO:ts FOR OPERATION a w .,
? tr f<
At least once per operating cycle 4:h 3.
automatic initiation of the control
' 3 From and after the date that the .
control room air treatment system .
room air treatment gystem shall be. J.,j((t'@
is made or found to be inoperable de:nonstrated. M4 for any reasor., reactor eceration ,ifj 3 or refueling operations is fj i per:nissible only during tha , ' crig g
l succeeding seven days unless such .
. circuit is sooner made operable. .
.' ;9)
<4 Qq
- 4. If these conditions cannot be met, -
l' reactor shutdown shall be initiated -
"~d, and the reactor shall be in cold MK ggq shutdown within 24 hours for reactor operations and refueling yqf operations shall be terminated Ol.
irmediately. * - + ,
' s g
- i1 a4 '
. ig l' ,
y l . ,
~
it
oo,ne . ..
l e oo,,
- g e
Y
~
Pk'R AftD BifR TECl%ICA!. SPECIFICATIONS _
las3, Control Room Air Treatnent System _ for intake air 3.0.8. h The control room air treatment system is designed to filter the control room atmosp ereThe con i in the control room and/or for recirculation during control roon isolation conditions.
system is designed to automatically start upon control room k isolation and to ma nta pressure to the design positive pressure so that all leakcge should l adsorbers beto out lea age.
High efficiency particulate absolute (HEPA) filters are installed before the charcoaThe charco prevent clogging of the iodine adsorbers. The in-place test results should indicate a system leakd a HETA effic intake of radio 1odine to the control room.
- tightness of less than 1 percent bypass leakage for the charcoal adsorbers anThe laboratcry carbo least 99 percent removal of CDP particulatos. least 90 percent for expacted accident ltingconditions.
doses
, a radioactive methyl todide removal efficiency of at will be less than the allowable Operation of levels the fans stated significantlyin Criterion different from the 19 of the Ge a
)
Power Plants. Appendix A to 10 CFR Part 50.
design flow will change the removal efficiency of the HEPA filtersd reactor and charcoal adsorb {
ile repairs are being made. u If the system is found to be inoperable, there is not i;rcediate threat to wr.
ld shutd the control;dj room operation or refueling operation may continue for a limited period of time wh If the system cannot be repaired within seven days, the reactor is shutdown and brough within 24 hours or refueling operations are terminated.
K w
3
.'s
[L
f PW A';D SG TECH!!ICAL $PECIFICATIONS_ ,
ki Seses n 4.0.8 Control Reca Air Treatment System _
ie L Pressure drop across the co:6tned HEPA filters and charcoal a Pressure drop should be detemined at least once per operating cycle amounts of foreign matter.
to show system performance capability.
" The frequency of tests and sample analysis Tests of the are r.ecessary charcoal adsorbers with halogenated to show that the HEPA fi hy*irocarbon adsorbers can perfom as evaluated. -1082. Iodine ,rgeval efficiency tests shall shall be perfomed in accordance with USAEC RepcrtThe charcoal cdsorber efficiency testl procedures d sh follow ROT Standard H-16-1T.
removal of one adsorber tray, ecptying of one bed from the tray, mixing the obtaining at least two sampics. If test results are unacceptable, all adsorbent in the system
. The equal to the thickness of the bcd.
shall be replaced with a adsorbe t qualified iccordir.g.to Table 1 of Regulatory Guide 1.5 replacement tray for the adsorber cray recoved for the test should meet the same a Tests of the HEPA filters with 00P aerosol shall be perfont.ed in accordance to AflSI fl1
' My HEPA filters found defective shall be replaced with filters qualified pursuant to Reg Position C.3.d of Regulatory Guide 1.52.
Operation of the system for 10 hours every month will ds..onstrate operabjlity of the adsorber system and remove excessive moisture built up on the adsorber.
at If significant painting, fire or chemical release occurs such that the HEPA filter or ch adsorber could become contaminated from the fu:es, chemicals The detemination or foreign materials, of the sa and sample analysis shall be perforred as required for operational use. Knowledgeable significant shall be made by the operator on duty at the time of the incident.
staff menbers should be consulted prior to rakf r.g this determination.
Demonstration of the automatic initiation capability is necessary to assurs, systern perfon-an
m ..
#. l '_ o 9*3800 e
-}}