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Category:CORRESPONDENCE-LETTERS
MONTHYEARL-99-035, Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld1999-10-18018 October 1999 Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld ML20217G0801999-10-0707 October 1999 Informs That on 990930,staff Conducted mid-cycle PPR of Farley & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Will Conduct Regional Insps Associated with SG Removal & Installation ML20217P0661999-10-0606 October 1999 Requests Withholding of Proprietary Rept NSD-SAE-ESI-99-389, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217B1891999-10-0404 October 1999 Submits Clarification Re Development of Basis for Determining Limiting Internal Pressure Loads Re Review of NRC SE for Cycle 16 Extension Request.Util Intends to Use Guidelines When Evaluating SG Tube Structural Integrity ML20212J8391999-09-30030 September 1999 Forwards RAI Re Request for Amends to Ts.Addl Info Needed to Complete Review to Verify That Proposed TS Are Consistent with & Validate Design Basis Analysis.Request Discussed with H Mahan on 990930.Info Needed within 10 Days of This Ltr ML20212J8801999-09-30030 September 1999 Discusses GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps. Util 980731,990607 & 03 Ltrs Provided Requested Info in Subj Gl.Nrc Considers Subj GL to Be Closed for Unit 1 L-99-032, Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 21999-09-23023 September 1999 Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 2 L-99-034, Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 21999-09-23023 September 1999 Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 2 ML20212F8861999-09-23023 September 1999 Forwards Revised Relief Request Number 32 for NRC Approval. Approval Requested by 991231 to Support Activities to Be Performed During Unit 1 Refueling Outage Scheduled for Spring of 2000 ML20212E7031999-09-23023 September 1999 Responds to GL 98-01, Year 2000 Readiness of Computer Sys at Npps. Util Requested to Submit Plans & Schedules for Resolving Y2K-related Issues ML20212F1111999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals ML20212C2351999-09-16016 September 1999 Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20212D0101999-09-15015 September 1999 Informs That Submittal of clean-typed Copy of ITS & ITS Bases Will Be Delayed.Delay Due to Need for Resolution of Two Issues Raised by NRC staff.Clean-typed Copy of ITS Will Be Submitted within 4 Wks Following Resolution of Issues ML20212C4641999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams L-99-031, Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed1999-09-13013 September 1999 Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed ML20212C8041999-09-10010 September 1999 Responds to to D Rathbun Requesting Review of J Sherman Re Y2K Compliance.Latest NRC Status Rept on Y2K Activities Encl ML20212D4581999-09-10010 September 1999 Responds to to D Rathbun,Requesting Review of J Sherman Expressing Concerns That Plant & Other Nuclear Plants Not Yet Y2K Compliant ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211N8041999-09-0808 September 1999 Informs That on 990930 NRC Issued GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Condition, to Holders of Nuclear Plant Operating Licenses ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20212C0071999-09-0202 September 1999 Forwards Insp Repts 50-348/99-05 & 50-364/99-05 on 990627- 0807.No Violations Noted.Licensee Conduct of Activities at Farley Plant Facilities Generally Characterized by safety-conscious Operations & Sound Engineering ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20211K2131999-08-31031 August 1999 Informs That Snoc Has Conducted Review of Reactor Vessel Integrity Database,Version 2 (RVID2) & Conclude That Latest Data Submitted for Farley Units Has Not Been Incorporated Into RVID2 ML20211K4101999-08-31031 August 1999 Resubmits Relief Requests Q1P16-RR-V-5 & Q2P16-RR-V-5 That Seek to Group V661 Valves from Each Unit Into Sample Disassembly & Insp Group,Per 990525 Telcon with NRC L-99-030, Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS1999-08-30030 August 1999 Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS ML20211G6851999-08-26026 August 1999 Informs That During Insp,Technical Issues Associated with Design,Installation & fire-resistive Performance of Kaowool Raceway fire-barriers Installed at Farley Nuclear Plant Were Identified L-99-029, Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 07271999-08-19019 August 1999 Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 0727 ML20211B9431999-08-17017 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 990101-990630,IAW 10CFR26.71(d).Rept Covers Employees at Jm Farley Nuclear Plant & Southern Nuclear Corporate Headquarters ML20211B9211999-08-17017 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-348/99-09 & 50-364/99-09.Corrective Actions:Security Response Plan Was Revised to Address Vulnerabilities Identified During NRC Insp ML20210R5101999-08-12012 August 1999 Forwards Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16 Only,Based on risk- Informed Approach for Evaluation of SG Tube Structural Integrity,As Result of Staff Comments ML20212C8141999-08-0909 August 1999 Forwards Correspondence Received from Jm Sherman.Requests Review of Info Re Established Policies & Procedures ML20210T2021999-08-0606 August 1999 Forwards Draft SE Accepting Licensee Proposed Conversion of Plant,Units 1 & 2 Current TSs to Its.Its Based on Listed Documents ML20210Q4641999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr to La Reyes,As Listed,With List of Individuals to Take exam,30 Days Before Exam Date ML20210J8341999-07-30030 July 1999 Forwards Second Request for Addl Info Re Util 990430 Amend Request to Allow Util to Operate Unit 1,for Cycle 16 Based on risk-informed Probability of SG Tube Rupture & Nominal accident-induced primary-to-second Leakage ML20210G4901999-07-30030 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, Issued 990603.Ltr Contains NRC License Commitment to Utilize ASTM D3803-1989 with Efficiency Acceptance Criteria Utilizing Safety Factor of 2 L-99-028, Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines1999-07-30030 July 1999 Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines L-99-027, Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.51999-07-27027 July 1999 Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.5 ML20210G8181999-07-26026 July 1999 Forwards Insp Repts 50-348/99-04 & 50-364/99-04 on 990516- 0626.One Violation Identified & Being Treated as Noncited Violation IR 05000348/19990091999-07-23023 July 1999 Discusses Insp Repts 50-348/99-09 & 50-364/99-09 on 990308- 10 & Forwards Notice of Violation Re Failure to Intercept Adversary During Drills,Contrary to 10CFR73 & Physical Security Plan Requirements ML20210E4071999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines L-99-026, Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments1999-07-19019 July 1999 Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments L-99-264, Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 20011999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20209H4721999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20196J6191999-07-0202 July 1999 Forwards Final Dam Audit Rept of 981008 of Category 1 Cooling Water Storage Pond Dam.Requests Response within 120 Days of Date of Ltr 05000364/LER-1999-001, Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed1999-07-0202 July 1999 Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed ML20196J7471999-07-0202 July 1999 Forwards RAI Re Cycle 16 Extension Request.Response Requested within 30 Days of Date of Ltr ML20196J5781999-07-0202 July 1999 Forwards RAI Re 981201 & s Requesting Amend to TS Associated with Replacing Existing Westinghouse Model 51 SG with Westinghouse Model 54F Generators.Respond within 30 Days of Ltr Date ML20196J6571999-07-0202 July 1999 Discusses Closure to TAC MA0543 & MA0544 Re GL 92-01 Rev 1, Suppl 1,RV Structural Integrity.Nrc Has Revised Rvid & Releasing It as Rvid,Version 2 as Result of Review of Responses ML20196J3591999-06-30030 June 1999 Forwards SE of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARL-99-035, Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld1999-10-18018 October 1999 Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld ML20217P0661999-10-0606 October 1999 Requests Withholding of Proprietary Rept NSD-SAE-ESI-99-389, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217B1891999-10-0404 October 1999 Submits Clarification Re Development of Basis for Determining Limiting Internal Pressure Loads Re Review of NRC SE for Cycle 16 Extension Request.Util Intends to Use Guidelines When Evaluating SG Tube Structural Integrity L-99-034, Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 21999-09-23023 September 1999 Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 2 L-99-032, Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 21999-09-23023 September 1999 Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 2 ML20212F8861999-09-23023 September 1999 Forwards Revised Relief Request Number 32 for NRC Approval. Approval Requested by 991231 to Support Activities to Be Performed During Unit 1 Refueling Outage Scheduled for Spring of 2000 ML20212C2351999-09-16016 September 1999 Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20212D0101999-09-15015 September 1999 Informs That Submittal of clean-typed Copy of ITS & ITS Bases Will Be Delayed.Delay Due to Need for Resolution of Two Issues Raised by NRC staff.Clean-typed Copy of ITS Will Be Submitted within 4 Wks Following Resolution of Issues L-99-031, Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed1999-09-13013 September 1999 Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed ML20212C4641999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20211K2131999-08-31031 August 1999 Informs That Snoc Has Conducted Review of Reactor Vessel Integrity Database,Version 2 (RVID2) & Conclude That Latest Data Submitted for Farley Units Has Not Been Incorporated Into RVID2 ML20211K4101999-08-31031 August 1999 Resubmits Relief Requests Q1P16-RR-V-5 & Q2P16-RR-V-5 That Seek to Group V661 Valves from Each Unit Into Sample Disassembly & Insp Group,Per 990525 Telcon with NRC L-99-030, Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS1999-08-30030 August 1999 Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS L-99-029, Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 07271999-08-19019 August 1999 Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 0727 ML20211B9431999-08-17017 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 990101-990630,IAW 10CFR26.71(d).Rept Covers Employees at Jm Farley Nuclear Plant & Southern Nuclear Corporate Headquarters ML20211B9211999-08-17017 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-348/99-09 & 50-364/99-09.Corrective Actions:Security Response Plan Was Revised to Address Vulnerabilities Identified During NRC Insp ML20210R5101999-08-12012 August 1999 Forwards Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16 Only,Based on risk- Informed Approach for Evaluation of SG Tube Structural Integrity,As Result of Staff Comments ML20212C8141999-08-0909 August 1999 Forwards Correspondence Received from Jm Sherman.Requests Review of Info Re Established Policies & Procedures ML20210G4901999-07-30030 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, Issued 990603.Ltr Contains NRC License Commitment to Utilize ASTM D3803-1989 with Efficiency Acceptance Criteria Utilizing Safety Factor of 2 L-99-028, Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines1999-07-30030 July 1999 Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines L-99-027, Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.51999-07-27027 July 1999 Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.5 ML20210E4071999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines L-99-026, Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments1999-07-19019 July 1999 Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments L-99-264, Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 20011999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20209H4721999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 05000364/LER-1999-001, Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed1999-07-0202 July 1999 Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed L-99-024, Responds to NRC RAI Re Conversion to ITS for Chapters 3.4, 3.5,3.6,3.7,3.9 & 5.0,per 990419-20 Meetings with NRC1999-06-30030 June 1999 Responds to NRC RAI Re Conversion to ITS for Chapters 3.4, 3.5,3.6,3.7,3.9 & 5.0,per 990419-20 Meetings with NRC L-99-025, Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.211999-06-30030 June 1999 Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.21 ML20196J8631999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA L-99-249, Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA1999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA L-99-224, Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments1999-06-0707 June 1999 Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments ML20195F1731999-06-0707 June 1999 Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld L-99-217, Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld1999-06-0707 June 1999 Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld L-99-225, Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants1999-06-0707 June 1999 Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants ML20195F0621999-06-0707 June 1999 Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments ML20195E9581999-06-0707 June 1999 Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants ML20195C6941999-05-28028 May 1999 Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program L-99-021, Forwards Response to RAI Re Conversion to ITSs for Chapter 3.3.Attachment II Includes Proposed Revs to Previously Submitted LAR Re Rais,Grouped by RAI number.Clean-typed Copies of Affected ITS Pages Not Included1999-05-28028 May 1999 Forwards Response to RAI Re Conversion to ITSs for Chapter 3.3.Attachment II Includes Proposed Revs to Previously Submitted LAR Re Rais,Grouped by RAI number.Clean-typed Copies of Affected ITS Pages Not Included L-99-203, Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program1999-05-28028 May 1999 Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program ML20195F2101999-05-24024 May 1999 Requests That Farley Nuclear Plant Proprietary Responses to NRC RAI Re W WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs, Be Withheld from Public Disclosure Per 10CFR2.790 L-99-180, Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI1999-04-30030 April 1999 Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI ML20206F4321999-04-30030 April 1999 Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI L-99-017, Forwards Responses to NRC RAI Questions for Chapters 3.1, 3.2,3.5,3.7 & 3.9 of Ts.Attached Pages Include Proposed Revs Previously Submitted LAR to Rais,Grouped by Chapters & RAI Numbers1999-04-30030 April 1999 Forwards Responses to NRC RAI Questions for Chapters 3.1, 3.2,3.5,3.7 & 3.9 of Ts.Attached Pages Include Proposed Revs Previously Submitted LAR to Rais,Grouped by Chapters & RAI Numbers ML20206C8021999-04-26026 April 1999 Forwards 1998 Annual Rept, for Alabama Power Co.Encls Contain Financial Statements for 1998,unaudited Financial Statements for Quarter Ending 990331 & Cash Flow Projections for 990101-991231 05000348/LER-1998-007, Forwards SG-99-04-001, Farley-1:Final Cycle 16 Freespan ODSCC Operational Assessment, as Committed to in Licensee & LER 98-007-00.Util Is Revising Plant Administrative SG Operating Leakage Requirements as Listed1999-04-23023 April 1999 Forwards SG-99-04-001, Farley-1:Final Cycle 16 Freespan ODSCC Operational Assessment, as Committed to in Licensee & LER 98-007-00.Util Is Revising Plant Administrative SG Operating Leakage Requirements as Listed L-99-015, Forwards Rev 1 to Jfnp Security plan,FNP-O-M-99,resulting from Implementation of Biometrics Sys.Changes Incorporate Changes Previously Submitted to NRC as Rev 28 by Licensee .Encl Withheld,Per 10CFR73.211999-04-21021 April 1999 Forwards Rev 1 to Jfnp Security plan,FNP-O-M-99,resulting from Implementation of Biometrics Sys.Changes Incorporate Changes Previously Submitted to NRC as Rev 28 by Licensee .Encl Withheld,Per 10CFR73.21 ML20206B4391999-04-21021 April 1999 Forwards Corrected ITS Markup Pages to Replace Pages in 981201 License Amend Requests for SG Replacement L-99-172, Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.21999-04-21021 April 1999 Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.2 ML20205S9501999-04-21021 April 1999 Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.2 ML20205R0431999-04-13013 April 1999 Forwards Correction to 960212 GL 95-07 180 Day Response. Level 3 Evaluation for Pressure Locking Utilized Analytical Models.Encl Page Has Been Amended to Correct Error 1999-09-23
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33 VICE PRESIDENT - NUl:L2AR Date Approved l )?]y , /D J Y'//
GENERAL MANTGER-FAR 7INTCLEAR /LANT Date Approved
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e Nucitar Plant. The Emergency Plans for Alabama, Georgia, and Florida are given in ANNEX 1. AkNEX 11, and ANNEX III, respectively.
The criteria to be used for offsite protective action recommen-detions is given below. The basis for protective action guides is " Protective Action Evaluation Part 11 Evacuation and Shel-tering, Protective Actions Against Nuclear Accidents involving Gaseous Releases", EPA-520/1-78-0018. It should be noted that these levels are quite 1cw and are used as guidelines for pro-tective acticn rather than rigid lovels of action. Recommenda-tion of sheltering in residences shall be considered when the projected time of exposure in the area of the reside.xe, is less a
than 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> or when transit time (see Appendix E for evacuation time estimates) and meteorological conditions would cause cumu-lative exposure time to be received in transit to exceed 50% of the total exposure time. Areas within a ten mile radius in which protective action is deemed necessary will be referred to by Evacuation Zone as shown in Figure 21.- The population dis-tribution "ithin this ten-mile radius has been predicted for the life of the plant and is summarized graphically in Figure 22.
- a. Classification of Offsite incidents E(g Er.p.iec t ed Oraan or Classification 0.qngs tiedia Involved I GENERAL 5.0 rem Whole Body 10.0 rem Thyroid SITE AREA 1.0 rem .Whole Body 2.5 rem Thyroid ALERT 1 mr/hr at Whole Body sito boundary Thyroid
- b. Response Classificg11gn Protectivg_ Actions to be Recommended
.tl.111te Authorities GENERAL Recommendations based on plant conditions: l
- 1) Immediate evacuation for Zone A and for five-mile downwind zones.
- 2) Shelter remainder of plume EPZ.
- 3) Control access to the affected areas.
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e e Classification Protective Actions to be Recoy *d.qd to State Authorities V Recommendations based on projected dose: l
- 1) Immeditte evacuation for Zone A and for five-uile downwind zones.
- 2) She'ter remainder of plume EPZ.
- 3) Control access to the affected ereas.
- 4) locate and evacuate hot spots.
- 5) Control of food and water supplies and possible confiscation in certain sectors.
- 6) Monitor environmental radiation levels.
SITE AREA Recommendations based on plant onditions are at the discietion of t.he ED as appropriate.
Recommendations based on projected dose:
- 1) Shelter Zone A and 5 mile downwind zones.
- 2) Monitor envirenmental radiation levels,
- c. 3) Control access.
(' 4) Consider evacuation of childrer.
and pregnant women.
ALERT Recommendations are to be made at the discretion of.the ED based on plant conditions or projected dose.
The authority for recommending initiation or relaxation of protective measures is vested solely with the Emergency Director and Recovery Manager and may not be delegated to any other member of the emergency organization.
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. nJP-0-EIP-15 l
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FARLEY NUCLEAR PLAtU l
DiERGD4CY PLAN If1PLD4DRI!G PROCEDURE 1 l
C4P-0-EIP-15 S
A P
E T
Y DiEPGD4CY DRILLS ft E
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PROCEL3JRE USAGE REQUIREMDR5 SECTIONS Pach step of the procedure is to be read
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's DDNTINU00fil55 prior to performing that step. Each step is to be performed ir, the sequence given. Where required, each step is to be signed off as cumplete before proceeuing to_the next step.
REFEED4CE USE - The precedure is to be referred to periodically to confirm that all required parts of a work FIGURE 2 activity have been performed. Where required, ctops are to be signed off to show tl." procedure requirements have been met.
INEDRMATIOR USE - An 5clivity may Fs performed f rom memory, but the procedure should be available fot use as needed and RD4AINDER for training. _ _
Approved:
fi W ny General Manager - Nug7 ear P W t~~
J3te Issued: /d -/d - 9 List-of-Effective-Pat Page Rev.
1 14 2-7 19 Figure 1 13 rigure e 20 DOCUMEN T CONTROL CONTROLLED COPY EIP-15/2 DO NOT REfHODUCE COPY NO yl
FNP-0-EIP-15 e nu2GENCY DRILLS 1.0 Purpose
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V) This procedure provides instructions and describes renponsibi1Lities for conducting emergency plan drills and testing communications networks.
2.0 References 2.1 Joseph M. F'arley Nuclear Plant Emergency Plan 2.2 IE letter (Lewis to Mcdonald) dated October 11, 1984: Submittal of Annual Emergency Exercise Objectives and Detailed Scenarios 2.3 tie-0-STP-60.0, Emergency Communications operability Tests 2.4 rWP-0-EIP-8, Emergency Communications 2.5 IWP-0-AP-27, Training Group Conduct of operations 3.0 C;eneral 3.1 Preplanned exercises simulating emergencies will be conducted to:
3.1.1 Determine the effectiveness of the FNP emergency organization in handling emergencies.
3.1.2 Evaluate communication and action support with offsite agencies.
3.1.3 Evaluate the interface with and response of the company emergency organization.
3.1.4 Test the auequacy of timing and contents of the EIP's.
3.1.5 Test emergency equipment and communications networks.
3.1.6 Test the public prompt notification system.
3.1.7 Keep affected personnel aware of their role in the plan.-
3.2 The scenarios for use in these Jrills will be written ana include the following elements:
3.2.1 The basic objective 3.2.2 The date, time, place (s) and participating organizations.
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nip-0-tIP-15 3.2.3 2he sinulateo event 3.2.4 A time schedule of real and simulated events.
3.2.5 A narrative sunnary describing conduct of the drill.
3.3 Lach emetgency alarm or announcement shall be considered valid unless an announcement is made to the contrary.
3.4 tach individual at the rarley Nucleat Plant (nip) shall participace in emerg1ncy plan drills unless specifically exer.pted by the General Manager - Nuclear Plant.
3.5 The General Manager - Nuclear Plant shall evaluate the plant operating status and ascer*.ain that the drill will not adversely affect plant operations or equipment or the health and safety of the general public.
3.6 Audit observers shall be stationed at various locations to observe the performanr2 of emergency personnel.
3.7 All drills shall be coordinated with the shif t supervisor to the extent necessary to prevent an adverse effect on plant operations.
g Normal security controls r. hall be maintained during all drills.
3.9 Required drills listed in 5.3 may be conducted in the course of the same exercise.
3.10 Post drill critique deficiencien and observations are ncrmally outlined in the following categories:
3.10.1 Findings: Items of a significant nature that could result in failure to meet an exercise objective. Items of a significant nature that are repeated from a previous drill.
3.10.2 connents: Isolated eases of petsona), ptocedural, equipment or scenario inadequacies or strengths noted during the conduct of a drill.
3.10.3 Recommendations: Observations made during the conduct of a drill that result in suggestions to enhance the various aspects of the plants emergency response.
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4.0- Responsibilities (See Figure 1) [
4.1 Ao directed by the General hanager - Nuclear Plant, the O Training Manager will coordinate the scheduling and conduct of drills, lie will be provided with technical assistance from thJ Environmental OUN) Supervisor- and a sof tware individual in the 4 Computer Services Gcoup. The Training staff, software !
individual and 12N Supervisor ate the only MfP personnel authorized to review drill scenarios without approval of the General Manager - Nuclear Plant. The Training Manager will be
-responsible for the following general elements of drillst 4.1.1 Scenario development
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4.1.2 Drill Audit Observer assignments 4.1.3 Drill execution .
4.1.4 Post drill critiques
-4.1.5
. Emergency Plan training for APCO employees 4.1.6 Scheduling of Emergency Plan training for non-APCO [
persevel.
l 4.2 The General Manager - Nuclear Plant, Assistant General Manager
- operations, or the Ascistant General Manager - Support will approve the final drill scenario. One of the above positions which_is not scheduled to participate in the drill will be the :
approval authority.
4.3- The DN Supervisor will provide the following assistance to the Training Manager as requested:-
4.3.1 Technical assistance.for scenario development 4.3.2 Drill audit observer personnel 4.3.3 Personnel as instructors for Emergency Plan training =
for APCO and non-APCO employees. '
4.4 The software _ individual will prepare an EDCM simulation of the drill and run the simulation during the conduct of the drill. ,
lie will take out an admin'LCO with the Shif t Supervisor during '
any periods in which real EDCM capability is. overridden.
'4.5 The DN Supervisor will be- responsible for tracking' corrective action items-identified in the critique of-the annual emergency ,
exercise. ihese items may include those generated by MfP personnel and/or Nuclear Engineering and Licensing (NEL) personnel.. Items identified wi.11 then be assigned to the responsible group for corrective action.
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L FNP-0-EiP-15 4.6' 'Ihe Training Manager 4111 plan.offsite agency- participation via the Manager - !Juclear Engineering and Licensing who conducts -
lia hon with such agencies. The following drill planning O milestones should be folleved for the annual emergency exercise.
Information Submittal Submittal to be Submitted to NTS to NRC Description of scope 85 days prior 75 days prior e*
of exercise and to exercise to exercise objectives to be fulfilled
, Complete exercise 55 days prior 45 days prior scenario with all to exercise to exercise
- > controller information and simulation data t.
3.0 Procedure 5.1- Jesting of the Plant Emergency Alarm shall be as follows:
5.1.1 operations will be responsibir f r scheduling and performing the weekly set. % g of the Plant Emergency Alarm.
5.1.2 All alarm tests shall be preceded by announcing over O the plant public address system that the alatm is to be sounded.
5.1.3 All alarm tests shall be conclHed when the completion
-of.the test-is-announced over ine plant public address system. ,
5.2 Communications checks shall be conducted as follows:
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5.2.1 Conmunications checks will be performed monthly in accordance with FNP-0-STP-60.0 for all locations which are part of the Emergency Notification Network, Emergency Notification System, and llealth Physics Network by the operations Group.
5.2.2 The EOF /TSC/OCC intercom system will be tested at least annually by the Operations Group.
5.2.3 Communications checks and verification of phone numbers with all other organizations listed in EIP-8 will be performed quarterly by the Environmental and Emergency P'anning Group.
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5.2.4= Radiation Monitoring Team (MT,1 communications equipment stored at the Eor will be tested at least annually by the Environmental and Emergency Planning Group.
5.2.5 The Prompt Public Notification System will be tested at least once a day by the Security Group.
5.2.6 - A quarterly test to contact On-call personnel shall be performed by the Operations Group.
5.2.6.1 This quarterly test will be scheduled by the
. DN Supervisor.
j 5.2.6.2 The DN Supervisor will obtain permission from the On-call. Emergency Director prior to J the day of the quarterly test. f
. 5.2.6.3 'Ihe on-call DN Supervisor will notify the '
Unit 2 Shitt Supervisor-to conduct the test.
. 5.2.6.4 'The Shift Supervisor will have the test performed as soon as possible follcwing notification, s.
5.2.6,5 'Ihis test will consist of contacting personnel who are o"-call for the date and time specified.
5.2.6.6 Operations will document test results by
-(. completing rigute 2 and forwarding .to the DN Supervisor.
5.2.6.7 The DN Supervisor chall review ti.e results of the test, initiate corrective action as necessary and forward a completed copy of-rigure 2 to the General Manager.
5.3- The fonowing Emergency Plan drills shall be conducted in the periodicity specified below. . Required drills may be conducted concurrently in the same exercise.
,5.3.1 Annual Radiation Emergency Exercise Exercises simulating radi_ation emergencies will be held at leasttannually. These scenarios will be varied from exercise to exercise such that all major elements of the plan and emergency organizations are exercised at least once overy 5 years.- These exercises will be preplanned and will involve the active participation of 1ccal, state and federal agencies.
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'- One (1) exercise may be started between 6 P.M. and midnight and another between midnight and 6 A.M. once -
every six(6) years. One (1) exercise my be performed O every six years which is unannounced, except as required for effective coordination with the management of the various agencies and for the evaluation of the J
health and safety of the general public.
5.3.2 Fire Drills
- a. Fire Drills will be conducted with fire brigade members as required by the plant technical specifications.
- b. Fire Drills will be conducted annually which will involve the Dothan rire Department.
5.3.3 Medical brargency Drills A medical emergency drill will be conducted annually Milch will- involve ambulance and offsite medical treatment facility participation.
5.3.4 Radio 1.ogical Monitoring Drills Radiological monitoring drills will be conducted annually which will include initiating onsite and offsite radiological monitoring of vegetation, soil, water, and air.
5.3.5 llealth Physics Drills Health Physicc drills will be conducted semi-annually
, which will involve tesponse to nimulatad elevated airborne and liquid samples and direct radiation measurements in the plant environment. Sampling and analysis of the reactor coolant system including using the post-accident sampling system will be conducted ~
annually, 5.3.6 Practice and Table Top Drills 5.3.6.1 Table top drills will be conJucted periodically as deemed necessary by FWP management. These drills will involve discussions of responsibilities and actions
-in response to the emergency conditions of.
the scenario.
5.3.6.2 Practice drills will be conducted Fe '-11cally as deemed necessary by fuP management. These drills will. involve the FNP emergency response organization-(in whole or in part) responding to emergency =
conditions of'the scenario.
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FNP-0-E!P-15 i 5.4 At the conclusion of the drill the Emergency Directnr shall announce that the drill has been terminated.
5.5 Appropriate local, state, and federal a encies will be advised of major drills in advance to allow the r observation or i
participation. All observing ot participating agencies will be requested to provide comments on drill evaluation to the 3 Training Mm ager.
turEs The critique of table top drills will be conducted during and after completion of the drill. No formal written critique is required. ,
The criti,que of practices will be conducted as specified in section 5.6; however, results of such critiques are not required to be provided in a formal manner to the Vice President - thclear.
-5.6 Upon drill termination, the Training Manager will conduct a post drill critique with the drill observers. Equipment, procedure, performance, training, drill, etc. deficiencies ^will be summarized in a written critique forcat. Comments recesved from offsite agencies will be incorporated in this critique.
The critique will be presented to the Assistant General Manager
- Plant Operations and the Assistant General Manager - riant
, Support by the Training Manager for review and fine.lization.
Upon completion of this review and finalization, the critique ;
will be forwarded to the General Manager - tMclear Plant for review. '!he General Manager - Nuclear Plant may assign improvement items from the critique to appropriate plant staff ,
for action. The General Manager - Nuclear Plant will forvard the drill critique to the Vice President _- Nuclear for review.
The Vica President - Nuclear may assign improvement items to Nuclear Generation staff for action, m 5.7 Documentation of drill scenario, drill participation and drill I critique will be forwarded to Document control in accordance with rNP-0-AP-27. -
5.8 The Training Manager will track drill participation by individuals who fill the Emergency Director, operations i Manager, Maintenance Manager, Technical-Manager and llealth Physics Manager roles. Participation in each role will be rotated.
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Dnergency Plan Drill Organization
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General tianager ,
thclear Plant F
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. Manager - lAiclear _ , _ , _ _ Training Engineering and Licensing Manager 4
1 Environmental . Software Individual-Supervisor. (Computer Services)-
b Drill Audit observers -
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k ne-0-EIP-15 ESTIMATED ESTIMATED f TIME OF MI!AfrES OF TIME TO POSITION C0tTTACTED I!OIVIDUAL COtTTACTED C0tTIACT ARRIVAL ARRIVAL * {
Emergency Director hssistant to i
. Emergency Director j Maintenance Manaaer Operations Manager Technical Manager ,_
l Mechanical Support- !
I&C Support
_ Electrical Support Reactor Engineer ,
Systems Engineer i
__ Computer Support _
, Licensing Engineer _
GPTS Support __ ,_ _ ;
lieulth Physics Manager O Chemistry Supervisor __
t Quality Control l SAER Support >
Environmental Supervisor _
t Early Co. Liaison Ilouston Co. Liaison
- This column for EP use only g
QUARTERLY TEST START DATE/ TIME ._ /
SHIFT SUPERVISOR __
ENVIRONMENTAL SUPV REVIfM / -
CORRECTIVE ACTION
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