Forwards NRC Draft Environ Protection Plan,Revised Per 800729 Meeting W/Util.Mods Reflect Site Specific Application.Requests Consideration of Encl Conductivity Study for Deletion of Certain Programs from Tech SpecsML19338C700 |
Person / Time |
---|
Site: |
Farley ![Southern Nuclear icon.png](/w/images/1/14/Southern_Nuclear_icon.png) |
---|
Issue date: |
08/07/1980 |
---|
From: |
Clayton F ALABAMA POWER CO. |
---|
To: |
Office of Nuclear Reactor Regulation |
---|
References |
---|
NUDOCS 8008180479 |
Download: ML19338C700 (30) |
|
|
---|
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
[Table view] Category:UTILITY TO NRC
MONTHYEARML20064A7131990-09-17017 September 1990 Advises That Due to Reassignment,Jj Clark No Longer Needs to Maintain Senior Reactor Operator Licenses ML20059J2811990-09-14014 September 1990 Forwards List of Key Radiation Monitors Which Will Be Used as Inputs to Top Level Radioactivity Status Bar Re Spds.List Identifies Monitors Which Would Provide Concise & Meaningful Info About Radioactivity During Accidents ML20065D5961990-09-13013 September 1990 Responds to Violations Noted in Insp Repts 50-348/90-19 & 50-364/90-19.Response Withheld ML20059J1661990-09-13013 September 1990 Forwards Monthly Operating Rept for Aug 1990 for Jm Farley Nuclear Plant & Rev 10 to ODCM ML20059L0751990-09-12012 September 1990 Forwards Revised Pages to Rev 3 to, Second 10-Yr Interval Inservice Insp Program for ASME Code Class 1,2 & 3 Components ML20059J2911990-09-12012 September 1990 Forwards Operator Licensing Natl Exam Schedules for FY91 Through FY94,per Generic Ltr 90-07.Requalification Schedules & Estimated Number of Candidates Expected to Participate in Generic Fundamental Exam,Also Encl ML20064A7111990-09-12012 September 1990 Forwards Rev 1 to Relief Request RR-1, Second 10-Yr Interval Inservice Insp Program for ASME Code Class 1,2 & 3 Components ML20059J2891990-09-12012 September 1990 Confirms Rescheduling of Response to Fitness for Duty Program Notice of Violation 90-18-02,per 900907 Telcon ML20065D6621990-09-12012 September 1990 Forwards NPDES Permit AL0024619 Effective 900901.Limits for Temp & Residual Chlorine Appealed & Stayed ML20064A3431990-08-28028 August 1990 Forwards Corrected Insertion Instructions to Rev 8 to Updated FSAR for Jm Farley Nuclear Plant ML20059D4711990-08-22022 August 1990 Forwards Fitness for Duty Performance Data for Jan-June 1990 ML20059B5101990-08-22022 August 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jan-June 1990.No Changes to Process Control Program for First Semiannual Period of 1990 Exists ML20056B2751990-08-20020 August 1990 Forwards Relief Requests from Second 10-yr Interval Inservice Testing Program for Class 1,2 & 3 Pumps & Valves. Request Incorporates Commitments in 891222 Response to Notice of Violation ML20056B2741990-08-20020 August 1990 Forwards Rev 2 to Unit Inservice Testing Program,For Review & Approval.Rev Incorporates Commitments Addressed in Util 891222 Response to Notice of Violation & Other Editorial & Technical Changes ML20058Q1481990-08-15015 August 1990 Forwards Rev 3 to FNP-1-M-043, Jm Farley Nuclear Plant Unit 1 Second 10-Yr Inservice Insp Program,Asme Code Class 1,2 & 3 Components ML20058P6201990-08-15015 August 1990 Forwards Rev 1 to FNP-2-M-068, Ten-Yr Inservice Insp Program for ASME Code Class 1,2 & 3 Components, Per 891207 & 900412 Responses to NRC Request for Addl Info ML20055G7701990-07-18018 July 1990 Updates 900713 Response to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount ML20055F7411990-07-11011 July 1990 Forwards Monthly Operating Rept for June 1990 & Corrected Monthly Operating Repts for Nov 1989 Through May 1990.Repts Revised to Correct Typo on Value of Cumulative Number of Hours Reactor Critical ML20055F3781990-07-10010 July 1990 Submits Final Response to Generic Ltr 83-28,Items 4.2.3 & 4.2.4.Util Position That Procedures Currently Utilized by Plant Constitute Acceptable Ongoing Life Testing Program for Reactor Trip Breakers & Components ML20055D4861990-07-0202 July 1990 Requests Authorization to Use Encl ASME Boiler & Pressure Vessel Code Case N-395 Re Laser Welding for Sleeving Process Described by Oct 1990,per 10CFR50.55a,footnote 6 ML20055D1001990-06-26026 June 1990 Responds to Violations Noted in Insp Repts 50-348/90-12 & 50-364/90-12 on 900411-0510.Corrective Actions:Electrolyte Level Raised in Lights Identified by Inspector to Have Low Electrolyte Level ML20044A6191990-06-26026 June 1990 Suppls 900530 Ltr Containing Results of SPDS Audit,Per Suppl 1 to NUREG-0737.One SPDS Console,Located in Control Room,Will Be Modified So That Only SPDS Info Can Be Displayed by Monitor.Console Will Be Reconfigured ML20043G4741990-06-11011 June 1990 Submits Addl Info Re 900219 Worker Respiratory Protection Apparatus Exemption Rev Request.Proposed Exemption Rev Involves Features Located Entirely within Restricted Area as Defined in 10CFR20 ML20043C1851990-05-29029 May 1990 Forwards Proposed Schedules for Submission & Requested Approval of Licensing Items ML20043B5941990-05-25025 May 1990 Provides Rept of Unsatisfactory Performance Testing,Per 10CFR26,App A.Error Caused by Olympus Analyzer Which Allowed Same Barcode to Be Assigned to Two Different Samples. Smithkline Taken Action to Prevent Recurrence of Scan Error ML20042G7461990-05-10010 May 1990 Certifies That Plant Licensed Operator Requalification Program Accredited & Based Upon Sys Approach to Training,Per Generic Ltr 87-07.Program in Effect Since 890109 ML20042F0831990-05-0101 May 1990 Forwards Rev 18 to Security Plan.Rev Withheld ML20042G3081990-04-25025 April 1990 Forwards Alabama Power Co Annual Rept 1989, Unaudited Financial Statements for Quarter Ending 900331 & Cash Flow Projections for 1990 ML20042E4121990-04-12012 April 1990 Provides Addl Info Re Review of Second 10-yr Inservice Insp Program,Per NRC 890803 Request.Relief Request RR-30 Requested Reduced Holding Time for Hydrostatically Testing Steam Generator Secondary Side ML20012E9571990-03-27027 March 1990 Forwards Annual Diesel Generator Reliability Data Rept,Per Tech Spec 6.9.1.12.Rept Provides Number of Tests (Valid or Invalid),Number of Failures for Each Diesel Generator at Plant for 1989 & Info Identified in Reg Guide 1.108 ML20012D9661990-03-22022 March 1990 Forwards Annual ECCS Evaluation Model Changes Rept,Per Revised 10CFR50.46.Info Includes Effect of ECCS Evaluation Model Mods on Peak Cladding Temp Results & Summary of Plant Change Safety Evaluations ML20012D8901990-03-20020 March 1990 Clarifies 891130 Response to Generic Ltr 83-28,Item 2.2.1 Re Use of Q-List at Plant,Per NRC Request.Fnpims Data Base Utilized as Aid for Procurement,Maint,Operations & Daily Planning ML20012C4701990-03-15015 March 1990 Responds to NRC 900201 Ltr Re Emergency Planning Weaknesses Identified in Insp Repts 50-348/89-32 & 50-364/89-21. Corrective Actions:Cited Procedures Revised.Direct Line Network Notification to State Agencies Being Implemented ML20012C6241990-03-14014 March 1990 Informs of Resolution of USI A-47,per Generic Ltr 89-19 ML20012C4651990-03-13013 March 1990 Provides Verification of Nuclear Insurance Reporting Requirements Specified in 10CFR50.54 w(2) ML20012C2051990-03-0505 March 1990 Forwards SPDS Critical Function Status Trees,Per G West Request During 900206 SPDS Audit at Plant.W/O Encl ML20012A1621990-03-0202 March 1990 Forwards Addl Info Inadvertently Omitted from Jul-Dec 1989 Semiannual Radioactive Effluent Release Rept,Including Changes to Process Control Program ML20012A1301990-03-0101 March 1990 Responds to Generic Ltr 90-01 Re Request for Voluntary Participation in NRC Regulatory Impact Survey.Completed Questionnaire Encl ML20043A7481990-02-0202 February 1990 Forwards Util Exam Rept for Licensed Operator Requalification Written Exams on 900131 ML20006D2311990-01-31031 January 1990 Responds to NRC Bulletin 89-003 Re Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedures Will Be Revised to Incorporate Guidance That Will Preclude Inadvertent Loss of Shutdown ML20006A9091990-01-23023 January 1990 Forwards Response to Generic Ltr 89-13 Re Svc Water Sys Problems Affecting safety-related Equipment.Util Has Program to Perform Visual Insps & Cleanings of Plant Svc Water Intake Structure by Means of Scuba Divers ML20005E4931989-12-28028 December 1989 Provides Certification That fitness-for-duty Program Meets 10CFR26 Requirements.Testing Panel & cut-off Levels in Program Listed in Encl ML20005E3681989-12-28028 December 1989 Responds to Violations Noted in Insp Repts 50-348/89-28 & 50-364/89-28 on 891002-06.Corrective Actions:All Piping Preparation for Inservice Insp Work in Containment Stopped & All Participants Assembled to Gather Facts on Incident ML20005E1971989-12-27027 December 1989 Responds to Violations Noted in Insp Repts 50-348/89-22 & 50-364/89-22 on 890911-1010.Corrective Actions:Steam Generator Atmospheric Relief Valve Closed & Core Operations Suspended.Shift Supervisor Involved in Event Counseled ML20011D5041989-12-22022 December 1989 Responds to Violations Noted in Insp Repts 50-348/89-26 & 50-364/89-26.Corrective Actions:Personnel Involved in Preparation of Inservice Test Procedures Counseled. Violation B Re Opening of Pressurizer PORV Denied ML19332F2111989-12-0707 December 1989 Forwards Final Response to NRC 890803 Request for Addl Info Re Review of Updated Inservice Insp Program,Summarizing Results of Addl Reviews & Providing Exam Listing Info ML19332F0791989-12-0707 December 1989 Responds to Violations Noted in Insp Repts 50-348/89-22 & 50-364/89-22.Corrective Actions:All Managers Retrained on Intent of Overtime Procedures & Sys Established to Provide Independent Check of All Time Sheets Each Pay Period ML19332F1141989-12-0707 December 1989 Forwards Description of Instrumentation Sys Selected in Response to Generic Ltr 88-17, Loss of DHR, Per Licensee 890127 Commitment.Hardware Changes Will Be Implemented During Unit 1 Tenth & Unit 2 Seventh Refueling Outages ML19332F1241989-12-0707 December 1989 Forwards Response to NRC 890803 Request for Addl Info Re Review of Second 10-yr Inservice Insp Program,Per 891005 Ltr ML19353B0071989-12-0606 December 1989 Forwards Rev 1 to Safeguards Security Contingency Plan.Rev Withheld 1990-09-17
[Table view] |
Text
-
,1 A:aca~a M*er Cercary 600'e ?8? St eet Pas:C* ce Ocs 2641 Berram A.aca a MM sewas msw THIS DOCUMENT CONTAINS POOR QUAllTY PAGES h k
" cu"
- m nav m: c asse August 7, 1980 Docket Nos. 50-348 50-364 Director .
Of fice of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Re: Environmental Protection Plan Gentlemen:
On May 19, 1980, Alabama Power Company submitted proposed changes ,
to Joseph M. Farley Nuclear Plant Operating License No. NPF-2 involving the Appendix B Non-Radiological Environmental Technical Specifications. This same submission was also to apply to Farley Unit 2.
Mr. R. L. Ballard's memo to L. L. Kintner of July 16, 1980 responded to our letter of May 19, 1980, and provided a draft Environmental Protection Plan (EPP) for Farley Unit 2. On July 29, 1980, representatives of Alabama Power Company met with your staff to discuss the draft EPP.
As a result of thac meeting, certain aspects of the draft EPP have been modified to reflect site specific application for both Farley Units 1 and
- 2. These modifications are incorporated into Attachment I, which is a rewrite of the draf t EPP forre2ded by Mr. Ballard's letter of July 16, 1980.
During tr.e July 29, 1980 meeting, certain studies were discussed relative to programs conducted pursuant to the current NPF-2 Technical Specifications. These studies included a conductivity study, a visibility I monitoring study, and the program to correct erosion conditions and provide l screening along transmission line rights-of-way. With the exception of the conductivity study, all these documents have been submitted to the NRC as part of the annual report. Pursuant to this letter, we are formally submitting as Attachment II a copy of the conductivity study. This study was not required by NPF-2 Technical Specification until Unit 2 had been in operation for two years. We request consideration of this formal submission and the other referenced studies for the deletion of certain programs from the NPF-2 Technical Specifications. These considerations also apply to the deletion of certain programs from the draft Environmental Protection Plan.
COQY S
///
8 0 08180 N b [
. _ . . . .. . . , . . . - - ~ .- _
- o
? i 1
- Director Office of Nuclear Reactor Regulation Page 2 August 7, 1980 l
i j
With the above referenced :nodifications, the draf t EPP can be l
incorporated into the license for Farley Unit 1 and the license for Farley Unit 2. Such incorporation will provide the same programs for both units of the Farley Nuclear Plant.
If you have any questions, please advise.
r l
Very truly ours, ,
1 m f d // D' jl% * ,
F. L. Clayton, Jr.
FVB:1 Attachment i
cc: Mr. R. A. Thomas l Mr. G. F. Trowbridge l
i 4
I
e 1
9
=W Attachment I n
=
I
! 4 I.
i e
1 1 - . - -- . . - - - - _ _
.7.-__._._.._7.,__ -
. i i .
i, .
APPENDIX S 1 ,
j I TO FACILITY OPERATING LICENSE NO. DPR-1 T ~
FARLEY NUCLEAR PLANT J
! UNIT 2
- r
. s "9
i 1
1 ALABAMA POWER COMPANY DOCKET No. 50-364 t
i
! l 4
eem 4
ij - -
J t
! ENVIRONMENTAL PROTECTION PLAN l
I (NCN-RADIOLCGICAL) i 4
1 l
a 9
l l
I l
+
I I
i !
l
--..- _. -.-.-.._.,_m,.-,..-_,..._~...- . . . . _ _ _ _ . - - - , _ _ . . - . . . _ . _ . _ . - . - - - -
._ ._ . -_._s _. 2 .- .. - - -4 2 - . - . . _ _ _ . . - . . - . = - . . . - , .
JOSEPH M. FARLEY 'lVCLEAR PLA?6 UtlIT 2 EtWIR0fMNTAL PROTECTION PLAtt (NON-RADIOLOGICAL)
TA3LE OF CONTEtES ,
Section Page 1.0 Objectives of the Environmental Protection Plan . . . . . . . . . . . 1-1 2 .0 Environmental Protection Issues . . . . . . . . . . . . . . . . . . . 2-1 2 .1 Aq ua t ' e I s s u e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-1 2.2 Te rre s t ri a l I s s ue s . . . . . . . . . . . . . . . . . . . . . . . . . . 2-2
~
3 .0 Cons is tency Requi reme nts . . . . . . . . . . . . . . . . . . . . $ '. . . 3-1 3.1 S ta tio n Des i gn and Ope ratio n . . . . . . . . . . . . . . . . . . . . . 3-1 3 .2 Reporting Related to the tiPCES Permits and State Certification. . . . 3-2 3 .3 Changes Required for Compliance with Other Regulatory Requirements. . 3-3 4 .0 Envi ronmen tal Co ndi tio ns . . . . . . . . . . . . . . . . . . . . . . . 4-1 4 .1 Unusual or Important Envircnmental Events . . . . . . . . . . . . . . 4-1
- . 2 Envi ronme ntal Mo ni tori ng . . . . . . . . . . . . . . . . . . . . . . . 4-1 5 .0 Admi ni s t ra ti ve Procedures . . . . . . . . . . . . . . . . . . . . . . 5-1 5 .1 Review and Audit. . . . ....................... 5-1 5.2 Reco rds Re ten tio n . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.3 Cha n ges i n Envi ronme ntal P ro tec ti o n Pl a n . . . . . . . . . . . . . . . 5-2 5 .4 Station Reporting Requi ments . . . . . . . . . . . . . . . . . . . . 5-2 s
1.0 Cbjectives of the Environm:ntal Protection Plan l
The EPP is to provide for protection of environmental values during construction and operation of the nuclear facility. The principal objectives of the EPP are as fotLows:
(1) Verify that the plant is operated in an environmentally acceptable manner, as established by the FES and other NRC environmental impact assessments. .
(2) Coordinate NRC requirements and maintain consistency with other Federal, State and Local requirements for environmental protection.
(3) Keep NRC informed of the environmental effects of f acility construction and operation and of actions taken to control those effects.
t -
a.
t .
Environmental concerns identified in the FES which relate to water quality matters are regulated by way of the Licensee's NPOES permit.
d 1
1 1
ea *%
1-1 l
l l
2.0 Environmental Protection Issu2s In :ne FES-CL dated December 1974, the staf f censidered the envircnmental iscacts associated with :he coeratien of the two uni: Farley Nuclear Plant. Certain envirenmental issues were identified whien recuired stucy er License conditiens to resolve environmental concerns and to assure adecuate are:ection of the anvi ronment.
2.1 Aquatic Issues Scecific aquatic issues raised by the staf f in the FES-CL were: .
- 1. The need for aquatic monitoring programs to confirm that thermal mixing occurs as predicted, that chlorine releases are centrolled within those i~ discharge concentrations., evaluated, and that ef fects on aquatic biota and water quality due to plant operatien are no greater than predicted.
~
- 2. The need for scecial studies to document levels of intake entrainnent and impingement.
(FES-CL: Summary and Conclusions and Sections 6.2, 6.3 and 6.6) 4 Aquatic issues are addressed by the effluen Limitations, monitoring recuirements and the Section 316(b) demonstration recuirement centained in the effective NPDES permit issued by EPA-Regicn IV and new ic=lemented by the Alaba=a Water
.s e
2-1
-,c- - . , , - . . . - - - - , , . - - . .--
Improvem:nt Ccmmissicn. The NRC uitL rely on theso agencies for regulation of 1 i
matters involving water quality and aquatic biota, 2.2 Terrestrial Issues
- 1. Potential imoacts on the terrestrial environnent associated with drift f rom the mechanical draf t cooling towers. (FES-OL Section 6.5)
- 2. Potential increase in fogging associated with operation of the mechanical draft cooling towers. (FES-OL Section 6.5)
- 3. Potential erosion and visual effects along transmission Line corridors and at highway crossings, respecti.vely. CFES-OL Sections 4. 2, 5.4.4.1, 1.2) r __ ,-
t .,
- 4. The need for controlled use of herbicides on transmission rights-of way.
(FES-OL Sections 4.2, 5.4.4.2, 11.2)
- 5. The need for documentation of the Licensee's commitment to conduct a land management program. (FES-OL Sections 5.2 and 6.5)
NRC requirretits with regard to the above terrestrial issues are specified in
! Subsection 4.2 of this EPP.
i l
(
2-2
3.0 Consistency Requirements 3.1 Station Design and Operation The Licensee may make changes in plant design or operation or perform tests o r experiments affecting the envirencent provided such changes, tests, or experiments do not involve an unreviewed environmental question, and do not
~
i nvolve a change in the Environmental Protection Plan. Changas in plant design o r operation or tests or experiments which do not affect the environment are not s ubject to the requirements of the Environmental Protection Plan. Acti vities governed by Section 3.3 are not subject to the requirements of this section.
Before engaging in additional construction or operational activities which may a ffect the environment, the licensee shall prepare and record an environmental e valuation of such activity. When the evaluation indicates that such activity i nvolves an unreviewed environmental question, the licensee shall provide a i written evaluation of such activities and obtain prior approval from the Director, Office of ibclear Reactor Regulation. When such activi ty involves a change in the Environmental Protection Plan, such activity and change to the Environmental Protection Plan may be implemented only in accordance with an
~
appropriate license amendment as set forth in Section 5.3.
A proposed change, test or experiment shall be deemed to involve an unreviewed environmental question if it concerns (1) a matter which mcy result in a s ignificant increase in any adverse environmental impact previously evaluated i n the final environmetnal statement (FES) as modified by staff's testirony to the Atomic Safety and Licensing Board, supplements to the FES, environmental
(
3-1
impact appraisals, or in any decisions of the Atomic Safety and Licensing Board; o r (2) a significant change in effluents or power level (in accordance with 10 CFR Part 51.5(b)(2)) or (3) a matter not previously reviewed and evaluated i n the documents specified in (1) of this Subsection, which may have a s ignificant adverse environmental impact.
The licensee shall maintain records of changes in facility design or operation a nd of tests and experiments carried out pursuant to this Subsaction. These records shall include a written evaluation which provide bases for the determina-tion that the change, test, or experiment does not involve an unreviewed environmental question nor constitute a decrease in the effectiveness of this EPP to meet the objectives specified in Section 1.0. The licensee shall include as part of his Annual Environmental Operating Report (per Subsection 5.4.1) biref descriptions, analyses, interpretations, and evaluations of such changes, tests and experiments.
l-3.2 Reporting Re:ated to the NPDES Perr its and State Certifications Violations of the NPDES Permit or the State certification (pursuant to
- S ection 401 of the Clean Water Act) shall be reported to the NRC by submittal o f copies of reports required by the NPDES Permit.or certification. The licensee shall also provide the NRC with copies of the following studies at the same time they are submitted to the permitting agency:
A. 316(b) Demo 1stration Study B. Chlorine minimization study
Changes and additions to the fiPCES Pemit or the State certification shall be reported to the fiRC within 30 days following the date the change is approved.
I I f a permit or certification, in part or in its entirety, is appealed and s tayed, the fiRC shall be notified within 30 days fel10 wing the date the stay i s granted.
! The fiRC shall be notified of changes to the effective NPCES Pemit proposed by the licensee by providing fiRC with a copy of the proposed change at the same ;
l time it is submitted to the pemitting agency. The notification of a licensee i nitiated change shall include a copy of the requested revision submitted to the permitting agency. The licensee shall provide the NRC a copy of the application for renewal of the fiPCES permit at the same time it is submitted to the pemitting agency.
3.3 Changes Required for Compliance with Other Regulatory Requirements
- - r Changes in Plant Cesign, Operation, or tests or experiments which are required to achieve compliance with other Federal, State or local environmental regulations i
a re not subject to the requirements of subsection 3.1.
I i
-s 3-3
.. - . , . . . . . , , . , - - . - . - . . _ . . , ~ . _ - . _ - . . - . - _ . _ , - - - , . - . _ _ ,
4.0 Environmental Conditions 4.1 Unusual or Important Environmental Events Any occurrence of an unusual or important event that indicates or could result i n significant environmental impact casually related to plant operation shall be recorded and promptly reported to the flRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone, telegraph, or facsimile transmissions followed by a written report (per Subsection 5 .4.2) . The following are examples: excessive bird impaction events, onsite plant or animal disease outbreaks, mortality or unusual occurrence of any species protected by the Endangered Species Act of 1973, fish kills, increase in nuisance organisms or conditions and unanticipated or emergency discharge of waste water or chemical substances.
No routine monitoring programs are required to implement this condition.
4.2 Environmental Fbnitoring 4 .2.1 Aerial Remote Sensing Vegetation communities of the site and vicinity whithin 1 kilometer of the cooling towers in all directions shall be aerially photographed to detect and assess the s ignificance of damage, or lack thereof, as related to cooling tower drift I
d ispersions . Photography shall be done by aerial overflight during May to June.
Monitoring shall include a program of low altitude false color aerial photography (either color infrared photography or multispectral or multiband photography).
The scale for full coverage shall be adequate to enable identification of vegetative damage over relatively small areas of terrtin. Some circumstances may warrant inspection of photographs discerning individual trees. Such scale should be in the interval between 1:1000 and 1:12,000 as appropriate to resolve i mpacted features.
4-1
Photographs shall be companed with baseline to ascertain chang::d v:getation.
Photographic interpretations shall correlate data from ground truth from ground i nspection surveys with areas of stress and nonstress as seen on the photographs for purposes of verification of results and interpretation. Ground truth s urveys shall be perfonned during the aerial photographic monitoring for two unit operation. This program shall require aerial photographic monitoring during the first May to June period after Unit 2 has been in operation for o ne year and the program shall be repeated during the same period two years t herea f ter. A report shall be submitted as part of the annual report following the last aerial photographic monitoring period. The report shall contain a descriotion of the program, results, and interpretative analyses of environmental i mpacts . Results reported shall contain information encompassing but not limited to the following: sampling data; time of day; film types; spectral bands; and o ne (1) set of resultant color transparencies encompassing an area within approx-imately a one kilometer (1 km) radius of the Unit I and 2 towers.
4 .2.2 Herbicide Application The use of herbicides within the following corridor rights-of-way shall conform to the approved use of selected herbicides as registered by the Environmental P rotection Agency and approved by State authorities and apolied as directed by said authorities: Farley to Pickard - South - 230 KV; Farley to Webb to Pickard - 230 KV; and Farley to Snowdown - 500 KV.
Herbicide use shall be summarized in the annual report. If herbicides are used, the annual report shall include the following infor-ation: name of transmission
! line corridor; commercial name of the herbicides; quantity of each herbicide; and method and frequency of applications for each herbicide. A, statement shall be 4-2
i I included that application of herbicides has confortned to the Environmental P rotection Agency and State requirements.
J 4.2.3 Land Panagement l _ There shall be a land management program instituted at the F'.P to provide for
! revegetation of site areas impacted during construction as cescribed in Section 5.2 of the FES-OL. ~his program requires landscaping of certain areas around the plant buildings and the revegetaticit and management of the remiander of the site as a wildlife refuge. There shall be no reporting requirement associated wi th this i tem.
)
i
- 3. -
i l
[
4-3
,-,e.-----._,----..-m,,.. . . . , , - . ,,,w-.--.,.,7 .,,- ,.-y _ , , , _ .,m., , , m.._-,.,w.. . . - .%,, ,e, , . _ . . ,. . , ,,.- _.,m% ,,_ . - . -- -.--,_-..- ,,,, ,
5.0 Administrative Procedures 5 .1 Review and Audit The licensee shall provide for review and audit of compliance with the E nvironmental Protection Plan, The audits shall be conducted independently o f the individual or groups responsible for perfor:.iing the s;acific activity.
A description of the organization structure utilized to achieve the independent review and audit function and results of the audit activities shall be maintained and made available for inspection.
5.2 Records Retention Records and logs relative to the environmental aspects of plant operation shall be made and retaired in a manner convenient for review and inspection.
These records and logs shall be made available to NRC on request. ,,
Records of modifica: ions to plant structures, systems and components determined to potentially affect the continued protection of the environnent shall be retained for the life of the plant. All other records, data and
~
logs relating to the Environmental Protection Plan shall be retained for five years or where applicable in accordance with the requirements of other Federal, S tate, or local agencies.
e 5-1
5.3 Changes in Environmental Protection Plan f
l Recues:
for change in the Environmental Protection Plan may be submitted to the NRC at any time. The request shall include an assessment of the environmental l
. Implementation imcact of the proposed change and a supporting justifica 'on.
accroval of ,
of such changes in the EPP shall not commence prior to NR in:ceporating the the proposed changes in the f orm of a license amendment accropriate revision to the Environmental Protection Plan. .
- 5. 4 Station Reporting Requirements 5.4.1 Routine Reports An Annual Environmental Operating Report describing implementation of this EPP for the previous year shalL be submitted to the NRC prior to May 1 of each year. The initial report shaLL be submitted prior to May 1 of the year
.. following l' ,
issuan:e of the operating License.
The period of the first report shall begin with the date of issuance of the operating License.
The report shall include summaries and analyses of the results of the environ-mental protection ac:ivities required by Subsection 4.2 of this Environmental Protection Plan for the report period, including a comparison uith preopera-tional studies, operational controls (as appropriate), and previous non-radiological environmental monitoring reports, and an assessment of the If harmful observed impacts of the station operation on the environment.
effects or evidence of trends towards irreversible damage to the environment are observed, the Licensee shall provide a detailed analysis of the data and a proposed course of action to atLeviate the problem.
The Annual Environmental Operating Report shall also include:
(a) A list of EPP noncompliances and the corrective actions taken to remedy them.
(b) A list of all changes in station design or operation, tests, and experi-ments made in accordance with Subsection 3.1 which involved a potentially s ignificant unreviewed environmental issue.
(c) A list of nonroutine reports submitted in accordance with Subsection 5.4.2.
In the event that some results are not available by the report due date, the report shall be submitted noting and explaining the missing results. The missing data shall be submitted as soon as possible in a supplementary report.
5.4.2 tbnroutine Rccarts A written report shall be submitted within 30 days in the event that an " Unusual o r Important Environmental Event", as speci fied in Subsection 4.1, occurs.
Events reportable under this Subsection which also require written reports to other Federal, State, or local agencies for ea.v1091 mental protection shall be reported in accordance with those reportief requirements'in lieu of the requirements of this Subsection. The M As y ' ', ba provided a copy of s uch reports at the same time they ait submitted to the other agency.
5-3
o
?bnroutine reports, to the extent practicable, shall (a) describe, analyze, a nd evaluate the event, including extent and magnitude of the impact and plant operating characteristics, (b) describe the probable cause of the event, (c) indicate the action taken to correct the reported event, (d) indicate the corrective action taken to preclude repetition of the event arc to prevent
- similar occurrences involving similar components or systems, and (e) indicate the agencies notified and their preliminary responses.
j-9
. 5-4 1
. _ . - . _ . _ _ _ , . _ _ _ _ ~ . . _ . , . - . _ . _ . _ _ _ _ . . _ . . _ - . . _ _ _ _ . . _ _ . . .. ._. , _ _ _ _ . _ _ . _ . - - _ _ , _ - . . . _ _ , , .
l l
{
- i Attachment II O
e da
- - - ,r- - - - - , . , ,
FARLEY NUCLEAR PLANT CONDUCTIVITY STUDY
.w-
,e. ..
G h
I.
i i
e
l l
l i
Introduction:
Section 31.1.(b)-1 of the Joseph M. Farley Nuclear Plant Non-Radiological Environmental Technical Specifications require a program to assess the impacts due to drift from the mechanical draft cooling towers at the plant. This study consisted of establishing sampling stations (see Figure ') at three locations and obtaining pre and post cceration soil conductivity data from the various sample points. The data obtained was to be statistically analyzed to determine the impact of cooling tower drift on soil conductivity. Although the study was to continue through Unit 2 operation, an interim analysis has been performed on Unit 1 operation related data.
Results:
The analysis of Unit I related data shows no statistically valid effects on soil conductivity from cooling tower crift. This is confirmed by the following statistical analyses. ,,
t ,
1 w
I J
,. - . ,- y..- ,, - -
-m,y, m 7-., -- y ,___ .,_--4.__,_ - - . - - _ - -,_.---e----_-- --,-- -- r -,<w- -. , - -
a Figure I. ,-
(Taken from Farley Environmental Technical Speci fications)
$ . . . . ._ . . . . .s . . . . .i.--
g 4, . . . . .. .s 2
) s t
- 6. (*, .
l *
- 40PjnfY UNC .
\
lp ~
l A i
I6 i
a 15
, NNW N I
'L ,
> . ,.x
,.... ._......u. . . ....NNE _ , , , . ,, , __
f N $ , NE 2 ,
/! l
\
/r 1 s
f
11is 3 i i i .
/ I,S% . . -. . .. . ..c.oco v. rows ss ENE l F04 UN:7 /2 -
I jj jl
/ / ./ \
i 1',,
'% +, /
j4
,, _ mar _i .
E
!F:-
/ arou .
_t s,
.. .. . ~ _ _ . ~ ?. ., . ,,,
l ..f . .. g . _. . . . . . f . . .. ,
Y j %
- i .r - - : , x x Aaj i
'\ ( w's'w
\\
\ /
\l ,
E!E ;
I
- ,/
'\
. . **.000 8 10 6 s SW SE
\. \A .
I - . . , 9 7 *
' SSW SSE g
8
- 8
, i.
. ..\.
- f bM . ~. .. . . . . . . .. .. ~...... . .
g .. ,,
\ _= __
7 A SAMPLING STATION ALAB&wa Pose 8t COwravy
.CSEPw u FamL E Y NUC'.E1.R Pt. AMT E N yt *Ch u t N TA L fECHmCAL 57ECar CateCa#S y
, LCCt.TICN CF SCtt S.*.MPL6NG STA 3 -18 FCR COOLING TOW E R DRIFT EFFECTS FIGURE 3. t -2
O In order t.o test for possible effects of tne cooling towers at Farley fluclear plant, the following procedure was :eveleped:
Each of three sampling stations surrounding -he cooling towers was sub-divided into sixteen grid cells. During the pm-operatiomi monitoring period, eight soil samples from each grid cell in each quadrant were collected anc analyzed. Similarly, eleven samples were taken during the post-ocerational period. From this infonnation the mean conductivity for each quadrant cell for both pre and post-operational periods was computed for use in a statistical analysis.
In testing the hypothesis that for a given quadrant, the mean conductivity during the pre-op period is equal to that of the post-op ..
period (i .e. u pre =u post), the paired t-test was applied. Tne first step in the analysis involved computing the difference between the average pre-op value and the average post-op value for each grid cell (i.e. dj =
Y pre, i - T post, i for i = 1,2, . . 16) . By forming the differences in cell observations, any effect the grid cell might have on the results is
~
cancelled. Therefore, testing the hypothesis that u -u post = 0 is equivalent to testing Ho:ud=0 H1 :ud/0 _
-0 d ,
I The test statistic, T-RATIO = Sd /6 1 n l where d = ii E_ dj l i =1 n
( Z. d$) 2 n 2 i=1 2
and d5
.E di -
n is t-distributed with n-1 n-1 degrees of freedom. If lT-RATIO J s to/2, n-1, we fail to reject Ho.
The results for each quadrant are as follows:
l FARLEY NUCLEAR PLANT STATISTICAL ANALYSIS OF SOILS CONDUCTIVITY PEASURE!!ENTS (A TEST OF HYPOTHESIS ON MEANS)
CELL # PR E-O P MEAN PO S T-O P Ff E A N DIFFERENCE 1 46.38 42.36 4.02 2 47.00 40.64 6.36 3 52.38 43.55 8.83 4 51.13 42.36 8.77 5 45.13 40.18 4.95 6 48.38 40.36 8.02 7 56.00 47.82 8.18 8 53.13 49.27 3.86 9 43.38 47.45 -4.07 10 55.25 53.82 1.43 11 45.50 48.18 -2.68 12 52.75 50.27 2.48 13 51.63 50.45 1.18 14 42.13 46.45 -4.32 15 47.25 41.36 5.89 16 44.38 42.36 2.02
, . . 48.86 45.43 3.43.
T-RATIO = 3.15329 UITH 15 DECREES OF FREEDOM FORE.=0.05, T-RATIO)2.132=T4 ,g TPEREFORE, WE REJECT Ho (U3 =0). -
w D
b 10 e
. - , . - - , - - - -. , . . . - - - - , - - - . , +, ,-.
. FARLEY NUCLEAR PLANT STATISTICAL ANALYSIS OF SOILS CONDUCTIVITY MEASl'R EMENTS (A TEST OF HYPOTHESIS ON MEANS)
CELL # PR E-OP M EAF POST-OP MEAN DIFFERFMCE 1 75.00 86.82 11.82 2 54.88 61.82 -
6.94 3 65.88 57.55 8.33 -
4 41.25 48.55 -
7.30 5 67.75 70.36 -2.61 6 79.88 58.73 21.15 7 39.50 40.36 - 0.86 8 49.88 64.73 14.85 9 82.38 64.90 17.48 10 64.75 44.18 20.57 11 46.00 45.91 0.09 12 34.75 52.00 17.25 13 46.13 38.73 7.40 14 49.13 39.27 9.86 15 43.75 58.82 15.07
- 16 51.00 40.09 10.91 55.74 54.55 1.19 T-RATIO = 0.37060 MITH 15 DECREES OF FREEDOM FORM =0.05, T-R AT IO < 2 .13 2 =To /2.. is THEREFORE, WE FAIL TO REJECT Ho (Ug=0).
amen e
k l
t l
l
-- ,,, -- , , < . - - . - , , - ,n..------- , ,- , , -
FARLEY NUCLEAR PLANT -
STATISTICAL ANALYSIS OF SOILS CONDUCTIVITY MEASUR EMENTS (A TEST OF HYPOTHESIS ON !!EANS)
CELL i PRE-OP !!EAN P O S T-O P !! E A N DIFFERENCE 1 34.13 37.18 -3.05 2 30.00 35.09 -5.09 3 35.38 36.27 -0.89 4 62.29 49.18 13.11 5 40.43 42.18 -1.75 '
6 35.38 46.55 11.17 7 58.63 50.00 8.63 8 55.00 . 61.18 -6.18 9 46.25 44.45 1.80 10 47.14 55.27 -8.13 11 62.71 46.64 16.07 12 57.50 56.55 0.95 13 55.71 42.73 12.98 14 50.63 54.64 .4 . 0
- 15 58.00 51.91 6.09 16 42.25 60.73 18.48 48.21 48.16 0.06 i -
T-RATIO = 0.02328 WITH 15 DECREES OF FREED 011
FCPN.=0.05, T-RATIO <2.132=Lf2,g TH ER E F O P. E , WE FAIL TO REJECT Ho ( Ug,= 0 ) .
e N
9 9
e 4
., .- . -, n . - - - - - .-- - - - - - -- ,-. - - -
b___ - -
Due to the rejection of Ho for the SW quadrant, an additional analysis was conducted to test the hypothesis:
H : u o d(0 H : u '
- d In the one-tailed t-test we fail to reject H if T - RATIO 6 t ,
The results from this analysis are:
j_ ..
6 M
S S
E et -
,_ Qy1 s
j
l
FARLEY NUCLEAR PLANT STATISTICAL ANALYSIS OF l
SOILS CONDUCTIVITY 11EASUR EMENTS
( .\ TEST OF HYPOTHESIS ON 11EANS)
CELL # PR E-OP MEAN POST-OP MEAN D IF F ER ENC E 1 46.38 42.36 4.02 2 47.00 40.64 6.36 3 52.38 43.55 8.83 4 51.13 42 36 8.77 5 45.13 40.18 4.95 6 48.38 40.36 8.02 7 56.00 47.82 8.18 8 53.13 49.27 3.86 9 43.38 47.45 -4.07 10 55.25 53.82 1.43 11 45.50 48.18 -2.68 12 52.,75 50.27 2.48 13 51.63 50.45 1.18 14 42.13 46.45 -4.32 15 47.25 41.36 5.89 16 44.38 42.36 2.02 48.86 45.43 3.43 T-RATIO = 3.15329 UITH 15 DECR EES OF FREEDOM
- ~
FORE,=0.05, T-R ATIO)1. 7 5 3 =Ta ,6 T!! E P.E F O R E , UE REJECT Ho (U(40).
w e
. 9 e
l l
An assumption of the paired :-test is that the two groups of data have equal variances. In order to ensurs the saccle data complied wi th this res triction, the statistic F= PEE 32 POST n n -
- 2. ( X -X )2 f_ (X -X )2 2 PRE,i PRE 2 i=1 POST,i POST where 5 ppg = i=1 and S POST "
n-1 n-1 was computed to test the hypothesis 2
Ho: U PRE
1*a PRE n POST
, We fail to redect H o if F1 4 2,n-1,n-14 F 4 F=/2,n-1, -
n-1 -
The results of the test are illustrated in the following table.
een 4
e e- , - , ,- - - - - - . . . --.-r- - . _ , . . - - - - - - . , - _ - - , , - . , - - - , a n n. , , . - , , --
1.,
m . . _ . .- . .
O s -
_g_
, F ARLEY NUCLE /.R PLANT STATISTICAL ANALYSIS OF SOILS CONDUCTIVITY P.EASURE.MENTS (A TEST OF HYPOTHESIS ON VARIANCES)
SU OUADRANT ESE OUADRANT N Nk' OUADRANT F-RATIO: 1.024 1.228 1.723 F O R e - 0 . 0 5 , E f. ,,,, .g = 2 . 8 2 .
THEREFCRE, WE FAIL TO REJECT Ho IN ALL THREE CASES.
O 4
9 e
e=" %
i t
t
-e 9
i ,
o l
I f
. s i .
t i .
- -- -. . - ... . . _ . ..__ ._ ,._- -___--.-_-_,__,,,,-__... - ..- -__ _.____ __ -- _ ,,,,,_, .. , _ ,