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| {{Adams | | {{Adams |
| | number = ML20148M951 | | | number = ML20151E887 |
| | issue date = 03/28/1988 | | | issue date = 04/07/1988 |
| | title = Insp Repts 50-348/88-07 & 50-364/88-07 on 880211-0310.No Violations or Deviations Noted.Major Areas Inspected:Review of Monthly Surveillance & Maint Observations,Radiological Protection Program & Physical Security Program | | | title = Corrected Ltr Forwarding Insp Repts 50-348/88-07 & 50-364/88-07 on 880211-0310.No Violations or Deviations Identified |
| | author name = Bradford W, Dance H, Miller W | | | author name = Verrelli D |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| | addressee name = | | | addressee name = Mcdonald R |
| | addressee affiliation = | | | addressee affiliation = ALABAMA POWER CO. |
| | docket = 05000348, 05000364 | | | docket = 05000348, 05000364 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-348-88-07, 50-348-88-7, 50-364-88-07, 50-364-88-7, NUDOCS 8804060267 | | | document report number = NUDOCS 8804150425 |
| | package number = ML20148M938 | | | package number = ML20151E867 |
| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | page count = 6 | | | page count = 2 |
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| UNITED STATES
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| NUCLEAR REGULATORY COMMISSION | | NUCLEAR REGULATORY COMMISSION |
| ,0 f o nEGloN il J*i .. j 101 MARIETTA STRE ET. '
| | [ '$ REGloN H 101 MARIETTA STREET, * { |
| * ATLANT A, GEORGI A 30323
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| Report Nos.: 50-348/88-07 and 50-364/88-07 Licensee: Alabama Power Company 600 North 18th Street Birmingham, AL 35291 Docket Nos.: 50-348/88-07 and 50-364/88-07 License Nos.: NPF-2 and NPF-8 Facility name: Farley 1 and 2 Inspection Conducted: February 11 - March 10, 1988 Inspection at Farley site near Dothan, Alabama Inspectors: ,./_ s ']
| | ..... APR 01 M8 Docket Nos. 50-348 and 50-364 License Nos. NPF-2 and NPF-8 Alabama Power Company ATTN: Mr. R. P. Mcdonald Senior Vice President P. O. Box 2641 Birmingham, AL 35291-0400 Gentlemen: |
| W! H Bradford bfv ktw "
| | SUBJECT: NRC INSPECTION REPORT NOS. 50-348/88-07 AND 50-364/88-07 This refers to the Nuclear Regulatory Commission (NRC) 'nspection conducted by W. H. Bradford on February 11 - March 10, 1988. The inspect. ion included a review of activities authorized for your Farley facility. At the conclusion of the inspection, the findings were discussed with those members of your staff identified in the enclosed inspection repor Areas examined during the inspection are identified in the report. Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observation of activities in progres Within the scope of the inspection, no violations or deviations were identifie In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Roo The responses directed by this letter and its enclosure are not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, Pub. L. No. 96-51 Should you have any questions concerning this letter, please contact u |
| *$ f7f fVY Date Signed LraL . sin /w Date Signed W.HsMille7 ,
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| Approved by: -[
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| H. C. Da~nce,'Section Chief n Y!M [
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| Dite S'igned
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| Division of Reactor Projects SUMMARY Scope: This routine on-site inspection involved a review of monthly surveillance observation, monthly maintenance observation, operational safety verification, engineered safety system inspection, radiological protection program and physical security progra Results: No violations or deviations were identified, i
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| | Sincerely, David M. Verelli, Chief Reactor Projects Branch 1 Division of Reactor Projects |
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| | Enclosure: (See page 2) |
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| | 8804150425 000407 0 PDR ADOCK 0500 |
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| REPORT DETAILS 1. Licensee Employees Contacted J. D. Woodard, General Plant Manager D. N. Morey, Assistant General Plant Manager W. D. Shipman, Assistant General Plant Manager R. D. Hill, Operations Manager C. D. Nesbitt, Technical Manager R. G. Berryhill, Systems Performance and Planning Manager J. J. Thomas, Maintenance Manager J. K. Osterholtz, Unit Supervisor, Administrative L. W. Enfinger, Administrative Manager J. E. Odom, Operations Unit Supervisor B. W. Vanlandingham, Operations Unit Supervisor T., H. Esteve, Planning Supervisor J. B. Hudspeth, Document Control Supervisor L. K. Jones, Material Supervisor R. H. Marlow, Technical Supervisor L. M. Stinson, Plant Modification Manager Scott Fulmer, Supervisor, Safety Audit Engineering Review Other licensee employees contacted included technicians, operations personnel, maintenance end I&C personnel, security force members, and office personne . Exit Interview The inspection scope and findings were summarized during management interviews throughout the report period and on March 14, 1988, with the plant manager and selected members of his staff. The inspection findings were discussed in detail. The licensee acknowledged the inspection findings and did not identify as proprietary any material reviewed by the inspection during this inspectio . Licensee Action on Previous Enforcement Matters (92702)
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| This area was not inspecte Monthly Surveillance Observation (61726)
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| The inspectors observed and reviewed Technical Specification (TS) required surveillance testing and verified that testing was performed in accordance with adequate procedures, test instrumentation was calibrated, lim' ting conditions for operation (LCO) were met, test results met acceptance criteria and were reviewed by personnel other than the individual directing the test, deficiencies identified during the testing were
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| properly reviewed and resolved by appropriate management personnel, and personnel conducting the test were qualifie Portions of the following test activities were observed or reviewed by the inspectors:
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| 2-STP-1 RHR Pump 2A Monthly Operability Chec STP-2 Penetration Room Filtration Alignment Verificatio STP-22.18 Auxiliary Feedwater Automatic Valve Position Verificatio STP-121 Incore/Excore Detector Calibratio STP-33.2A Reactor Trip Breaker "A" Operability Tes STP-4 Miscellaneous Valves Inservice Tes STP-8 Diesel Generator 1-2A Operability Tes STP-8 Diesel Generator 1C Operability Tes STP-617.0 Penetr ation Room Filtration System Heater Tes No violations or deviations were identifie . Monthly Maintenance Observation (62703)
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| Station maintenance activities of safety-related systems and components were observed / reviewed to ascertain that they were conducted in accordance with approved procedures, regulatory guides, industry codes and standards, and were in conformance with TS. Items considered during the review included: verification that limiting conditions for operations were met while components or systems were removed from service; approvals were obtained prior to initiating the work; approved procedures were used; completed work was inspected as applicable; functional testing and/or calibrations were performed prior to returning components or systems to service; quality control records we e maintained; activities were accomplished by qualified personnel; parts and materials were properly certified; and, radiological and fire prevention controls were implemented. Work requests were also reviewed to determine the status of outstanding jobs to assure that priority was assigned to safety-related equipment maintenance which may affect system performanc The following maintenance activities were observed / reviewed:
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| KdR 116046A Repair fuel pump Leak on Diesel Generator 1 KWR 119228 Terminate cable for Diesel Generator 1-2A lube oil heate KWR 138284 Replace 2" service water piping to RHR Train A MCC-2A room cooler KdR 138286 Replace 2" service water piping to MCC-2A room cooler .
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| MWR 161626 Install pressure switch for breathing air syste MWR 163515 Test reactor trip breaker 2 GM- Insulation resistance testing for rotating equipment (air compressors A and B and auxiliary jacket water pump for Diesel Generator 1-2A).
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| i 0-MP-1 Diesel Air Intake and Exhaust Valve Visual Inspection (diesel V-B) Colt Model DC-2V Diesel Engine 1B, 18 Month f Inspectio MP-1 Colt Model DC-2V Diesel Engine IB, 18 Month Inspectio MP-1 Model DC-2V Diesel Generator Engine IB, Quarterly Inspectio Mp-28.114 Inspection and Testing of Reactor Trip Breakers (breaker for 2A).
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| 2-IMP-25 P-4 Permissive Contact Verification (Unit 2 "A" train).
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| No violations or deviations were identifie . Operational Safety Verification (71707)
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| The inspectors observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the report period. 'lso, the operability of selected emergency systems was verified,
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| tagout records were reviewed and proper return to service of affected components was verifie Tours of the auxiliary building, diesel building, turbine building and service water structure were conducted to observe plant equipment conditions, including fluid leaks and excessive vibrations and general housekeeping efforts. The inspectors verified compliance with selected limiting condition for operation (LCO) and results of selected surveillance test The verifications were accomplished by direct observation of monitoring instrumentation, valve positions, switch positions, accessible hydraulic snubbers, and review of completed logs, records, and chemistry results. The licensee's compliance with LCO action statements were reviewed as events occurre The inspectors routinely attended meetings with certain licensee management and observed various shif t turnovers between shif t supervisor, shift foremen and licensed operators, These meetings and discussions provided a daily status of plant operations, maintenance, and testing activities in progress, as well as discussions of significant problem On March 3,1988, the licensee notified the NRC resident inspectors that an accumulation of gas had been discovered in the piping of the "A" trains on Units 1 and 7 in the RHR discharge to the charging pumps suction piping. This gas was analyzeo and was found to contain the same
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| | j 101 MARIETTA STREET, 't ATL ANTA, G EORGI A 3o323 |
| | %,,,,,# hpR 01 M Docket Nos. 50-348, 50-364 License Nos. NPF-2 and NPF-8 Alabama Power Company ATTN: Mr. R. P. Mcdonald Senior Vice President P. O. Box 2641 Birmingham, AL 35291-0400 Gentlemen: |
| | SUBJECT: NOTICE OF VIOLATION (NRC INSPECTION REPORT NOS. 50-348/88-07 AND 50-364/88-07) |
| | This refers to the Nuclear Regulatory Commission (NRC) inspect. ion conducted by W. H. Bradford on February 11 - March 10,1988. The inspection included a review of activities authorized for your Farley facility. At the conclusion of the inspection, the findings were discussed with those members of your staff identified in the enclosed inspection repor Areas examined during the inspection are identified in the report. Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observation of activities in progres Within the scope of the inspection, no violations or deviations were identifie In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Roo The responses directed by this letter and its enclosure are not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, Pub. L. No. 96-51 Should you have any questions concerning this letter, please contact u |
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| composition of H2 volume control tank overpressure of hydrogen. The RHR to charging pump suction is used during the recirculation phase during accident conditions. The licensee vented the gas from Unit 1 "A" train on February 26, 1988. The amount of gas vented was equivalent to 450 gallons of water. No gas was found on Unit 1 "B" train. Unit 2 "A" train was vented on February 29, 1988. The equivalent of 310 gallons of gas was removed. No gas was found on "B" train. Successive venting was conducted s:
| | Sincerely, David M. Verelli, Chief Reactor Projects Branch 1 Division of Reactor Projects Enclosure: (See page 2) |
| on March 1 and 2 with decreasing amounts of gas accumulation. The licensee went to a 8 hour venting schedule and no more accumulation of gas was found. The immediate concern was the safety significance in regard to the high pressure charging pump operation during accident conditions. The licensee contacted Westinghouse Corporation and was informed by Westinghouse and Pacific Pump (Manufacturer) that the gas volume be limited to less than 6 cubic feet. However, the licensee has initiated a program to not allow any gas build up. This program consists of regular venting and charging pump operation which will preclude the gas buildu The licensee is investigating certain modifications and alternatives as a ,
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| permanent fix to the gas accumulation. For further information refer to Inspection Report No. 348-364/88-0 No violations or deviations were identifie . Radiological Protection Program (71709)
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| Selected activities of the licensee's Radiological Protection Program were reviewed by the inspectors to verify conformance with plant procedures and NRC regulatory requirement. The areas reviewed included: organization and management of the plant's health physics staff, " A LARA" implementation, Radiation Work Permits (RWP's) for compliance to plant procedures, personnel exposure records, observation of work and personnel in radiation areas to verify compliacce to radiation protection procedures, and control of radioactive ma:erial No violations or deviations were identifie . Physical Security Program (71SSI)
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| Licensee's compliance to the approved security plan was reviewed by the inspectors. The inspectors verified by observation and interviews with security force r?mbers that measures taken to assure the physical protection of the facility met current requirement Areas inspected included: organization of the security force, establishment and maintenance of gates, doors, and isolation zones, access control, and i
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| I No violations or deviations were identified.
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| 9. Engineered Safety Systems Inspections (71710)
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| The inspectors performed inspections of portions of various safety related systems during this inspection period. Major components were checked for leakage and any general conditions that would degrade performance or prevent fulfillment of functional requirement The following Unit 2 systems were inspected in detail:
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| Auxiliary Building Ventilation Syste Penetration Rooms Filtration Syste Containment spray System Including Chemical Additive Syste Residual Heat Removal Syste Items inspected included: confirmation that licensee's system line-up procedures matched plant drawings; surveillance procedures included the surveillance requirements of the Technical specifications; system valves and electrical breakers were in correct alignment or position; instrumentation was inservice and calibration was current; hangers and supports were aligned and in service; equipment was properly labeled; and, general housekeeping and cleanliness were properly maintaine The components inspected were found inservice / operable or if not inservice were covered by applicable "Tag Out" procedures to meet the requirements
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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:NRC TO UTILITY
MONTHYEARML20062E0451990-11-13013 November 1990
Discusses 901106 Meeting Re Alternative Tube Plugging Criteria for Facility Steam Generators
ML20062D6911990-11-0909 November 1990
Forwards SER Re Response to Generic Ltr 88-11 Concerning NRC Position on Radiation Embrittlement of Reactor Vessel. Compliance w/10CFR50,Appendix G,For Min Upper Shelf Energy Could Not Be Verified.Operation for 16 EFPY Acceptable
ML20058F7931990-11-0606 November 1990
Forwards Summary of NRC Understanding of Current Status of Unimplemented Generic Safety Issues for Plant,Per Util 900627 Response to Generic Ltr 90-04
ML20058B4021990-10-19019 October 1990
Forwards Summary of 900913 Mgt Meeting Re Emergency Preparedness Program & Onsite Technical Support Ctr
ML20058B1391990-10-16016 October 1990
Forwards Insp Repts 50-348/90-28 & 50-364/90-28 on 900911-1012.No Violations or Deviations Noted
ML20062B7031990-10-12012 October 1990
Requests Completion of Analysis of Liquid Samples Spiked W/ Radionuclides within 60 Days of Receipt of Ltr
ML20058B2581990-10-12012 October 1990
Ack Receipt of 900807 & 0904 Ltrs Transmitting Objectives & Scenario Package for Exercise Scheduled on 901024
ML20059N6721990-10-0909 October 1990
Responds to Util 900702 Request for Authorization to Use ASME Boiler & Pressure Vessel Code Case N-395.Request Acceptable
IR 05000348/19900181990-10-0909 October 1990
Ack Receipt of 900926 Response Re Violations Noted in Insp Repts 50-348/90-18 & 50-364/90-18
ML20062C6601990-10-0909 October 1990
Ack Receipt of 900913 Response to Violations Noted in Insp Repts 50-348/90-19 & 50-364/90-19
ML20059N3481990-09-24024 September 1990
Forwards Insp Repts 50-348/90-24 & 50-364/90-24 on 900827-31.No Violations or Deviations Noted
ML20059K1311990-08-28028 August 1990
Confirms Mgt Meeting on 900913 to Discuss Timeliness of Activation of Emergency Response Facilities
ML20059H0921990-08-23023 August 1990
Forwards Insp Repts 50-348/90-20 & 50-364/90-20 on 900711-0810.No Violations or Deviations Noted
ML20059B3421990-08-23023 August 1990
Advises That Util 900131 Response to NRC Bulletin 89-003 Re Potential Loss of Required Shutdown Margin During Refueling Operations,Satisfactory
ML20056B3721990-08-21021 August 1990
Forwards Order Imposing Civil Monetary Penalty in Amount of $450,000 Re Violations,Per 870914-18,1102-06 & 16-21 Insps. Violations Include Failure to Demonstrate Splice Qualification & Failure to Maintain Environ Qualification
ML20058M9441990-08-0303 August 1990
Forwards Insp Repts 50-348/90-19 & 50-364/90-19 on 900711-13 & Notice of Violation.Notice of Violation Withheld (Ref 10CFR2.790 & 73.21)
ML20058P8661990-07-31031 July 1990
Forwards Insp Repts 50-348/90-21 & 50-364/90-21 on 900709-13.No Violations or Deviations Noted
ML20055H4251990-07-13013 July 1990
Forwards Insp Repts 50-348/90-16 & 50-364/90-16 on 900611-0710.Violations Noted,But Not Cited
ML20055H6501990-07-13013 July 1990
Forwards Insp Repts 50-348/90-17 & 50-364/90-17 on 900618-22.No Violations or Deviations Noted
IR 05000348/19900121990-07-10010 July 1990
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-348/90-12 & 50-364/90-12.Part (a) of Violation Agreed with Denial & Withdrew This Portion & Revised Records Accordingly
ML20059M8061990-06-13013 June 1990
Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl
ML20055C3961990-02-23023 February 1990
Forwards Insp Repts 50-348/90-04 & 50-364/90-04 on 900129-0202.No Violations or Deviations Noted
ML20248B0201989-09-18018 September 1989
Forwards Summary of 890912 Mgt Meeting in Region II Ofc Re Configuration Mgt Program & Findings of self-initiated Safety Sys Assessment of Svc Water Sys.List of Attendees & Meeting Agenda Also Encl
ML20247K0821989-09-15015 September 1989
Forwards Amend 8 to Indemnity Agreement B-81,reflecting Revs to 10CFR140, Financial Protection Requirements & Indemnity Agreements, Increasing Liability Insurance
ML20248C2061989-09-15015 September 1989
Advises of Special Emergency Operating Procedure Insp Program Being Performed at Plant on 891127-1208 to Verify That Procedures Technically Accurate & That Actions Can Be Accomplished W/Equipment,Controls & Instrumentation
ML20247G5401989-09-12012 September 1989
Forwards Insp Repts 50-348/89-19 & 50-364/89-19 on 890821-25.No Violations or Deviations Noted.Licensed Operator Performance During Simulator Training Did Not Meet Expectations
ML20247G9511989-09-12012 September 1989
Forwards Insp Repts 50-348/89-18 & 50-364/89-18 on 890731-0804 & Notice of Violation.Notice of Violation Withheld (Ref 10CFR2.790 & 73.21)
ML20247G6611989-09-0707 September 1989
Confirms 890906 Telcon W/J Garlington & D Verrelli Re Mgt Meeting Scheduled for 890912 in Region II Ofc to Discuss Results of Licensee self-initiated Safety Assessment
ML20247F4881989-09-0606 September 1989
Ack Receipt of Responding to Violations Noted in Insp Repts 50-348/89-13 & 50-364/89-13.Implementation of Corrective Actions Will Be Examined During Future Insps
ML20246N7041989-08-25025 August 1989
Forwards Insp Repts 50-348/89-17 & 50-364/89-17 on 890724-28.No Violations or Deviations Noted
ML20246P3561989-08-17017 August 1989
Forwards Insp Repts 50-348/89-16 & 50-364/89-16 on 890711-31.No Violations or Deviations Noted
ML20246G3921989-08-11011 August 1989
Confirms Util Participation in NRC Regulatory Impact Survey on 890911,per 890808 Telcon.Agenda Encl
ML20245K5571989-08-0909 August 1989
Advises That 890601 Rev 16 to Emergency Plan Consistent W/ Provisions of 10CFR50.54(p) & Acceptable
ML20245H9851989-08-0303 August 1989
Requests Responses to Encl Questions Re Requests for Relief from ASME Code Requirements of Second 10-yr Inservice Insp within 45 Days of Ltr Receipt
ML20245H1201989-08-0202 August 1989
Requests That Encl Ref Matls Be Furnished to NRC by 890825 for Requalification Program Exam Scheduled for Wk of 891023
ML20248C8061989-08-0101 August 1989
Forwards Insp Repts 50-348/89-10 & 50-364/89-10 on 890424-27 & 0508-12 & Notice of Violation.Unresolved Item Identified
ML20247R9781989-07-28028 July 1989
Forwards Final FEMA Rept on 881102 Emergency Response Exercise.Identified Deficiency Promptly Corrected.Resolution of Weaknesses,Identified by Fema,Should Be Corrected Prior to Next full-scale Emergency Preparedness Exercise
ML20245F1971989-07-26026 July 1989
Forwards Insp Repts 50-348/89-14 & 50-364/89-14 on 890611-0710.No Violations or Deviations Noted.Matter Re Apparent Excessive Work Hours for Licensed Operators Will Be Discussed W/Util at 890731 Meeting in Region II Ofc
ML20247R5141989-07-26026 July 1989
Forwards Insp Repts 50-348/89-13 & 50-364/89-13 on 890509-10 & Notice of Violation.Fact That Two Independent Actions Involving Unauthorized Use of Radioactive Matls Occurred within Short Time Indicates Disrespect for Radioactivity
ML20247E2691989-07-20020 July 1989
Forwards Exam Rept 50-348/OL-89-01 Administered During Wks of 890619 & 26.Concerns Noted Re Operator Performance & Exam Admin.Concerns Will Be Discussed at 890731 Mgt Meeting at Region II Ofc
IR 05000348/19890111989-07-18018 July 1989
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-348/89-11 & 50-364/89-11
ML20246L8101989-07-13013 July 1989
Forwards Antitrust Settlement Notice Submitted for Fr Publication
ML20246B2391989-06-27027 June 1989
Forwards Insp Repts 50-348/89-12 & 50-364/89-12 on 890511-0610.No Violations or Deviations Noted
ML20246B0051989-06-16016 June 1989
Forwards Insp Repts 50-348/89-11 & 50-364/89-11 on 890411- 0510 & Notice of Violation
ML20245A8551989-06-13013 June 1989
Forwards SER Supporting Util 831104 & 850422 Responses to Generic Ltr 83-28,Item 4.5.3, Reactor Trip Sys Reliability for All Domestic Operating Reactors
ML20245F5031989-06-13013 June 1989
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-348/89-07 & 50-364/89-07
ML20245G3171989-06-13013 June 1989
Requests Completion of Radiochemical Analyses of Liquid Samples Spiked W/Radionuclide within 60 Days of Receipt of Samples
ML20248A1751989-06-0202 June 1989
Ack Receipt of 890407 Response to Violations Noted in Insp Repts 50-348/89-03 & 50-364/89-03.Violation Occurred as Stated in Notice of Violation.Written Statement Describing Corrective Actions Requested.Encl Withheld (Ref 10CFR2.790)
ML20247L4481989-05-25025 May 1989
Comments on Licensee 881229 Response to Generic Ltr 88-17 W/Respect to Expeditious Actions for Loss of Dhr.Response Appears to Meet Intent of Ltr But Lacks Details for Listed Items
ML20247L6451989-05-25025 May 1989
Requests That Licensee Follow Instructions of 890328 Order & Either Request Hearing or Submit Payment of Civil Penalty Re Operation of Safety Injection Pump W/Gas from Crossover Piping.Hydrogen Accumulation Discovered on 880226 Not 06
1990-09-24
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217G0801999-10-0707 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
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
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
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
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
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
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
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
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
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
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
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
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
ML20196J7471999-07-0202 July 1999
Forwards RAI Re Cycle 16 Extension Request.Response Requested within 30 Days of Date of Ltr
ML20196J3591999-06-30030 June 1999
Forwards SE of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs
ML20196D1931999-06-22022 June 1999
Discusses Requesting Approval & Issuance of Plant Units 1 & 2 ITS by 990930.New Target Date Agrees with Requested Date
ML20196H9801999-06-10010 June 1999
Submits Two RAI Re ITS Section 4.0 That Were Never Sent. Reply to RAI Via e-mail
ML20196A3401999-06-10010 June 1999
Forwards Insp Repts 50-348/99-03 & 50-364/99-03 on 990404-0515.No Violations Noted
ML20206R4741999-05-13013 May 1999
Informs That Staff Reviewed Draft Operation Insp Rept for Farley Nuclear Station Cooling Water Pond Dam & Concurs with FERC Findings.Any Significant Changes Made Prior to Issuance of Final Rept Should Be Discussed with NRC
ML20206M2321999-05-11011 May 1999
Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Mgt Created
ML20206G7341999-05-0404 May 1999
Forwards Safety Evaluation Re Completion of GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves
ML20206G2411999-04-30030 April 1999
Forwards Revised RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, Program at Farley.Requests to Be Notified of Rev to Original Target Date of 990521
ML20206R2031999-04-29029 April 1999
Forwards Insp Repts 50-348/99-02 & 50-364/99-02 on 990221-0403.No Violations Noted
ML20205T1931999-04-0909 April 1999
Informs That on 990316,J Deavers & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Farley NPP for Y2K.Initial Exam Dates Are Wks of 000508 & 22 for Approx 12 Candidates.Chief Examiner Will Be C Ernstes
ML20205Q1541999-04-0606 April 1999
Forwards Insp Repts 50-348/99-09 & 50-364/99-09 on 990308-10.One non-cited Violation Identified
ML20205M2831999-04-0202 April 1999
Forwards Errata Ltr for Farley Nuclear Power Plant FEMA Exercise Rept.Page 19 of Original Rept Should Be Replaced with Encl Corrected Page 19
ML20196K4881999-03-19019 March 1999
Forwards Insp Repts 50-348/99-01 & 50-364/99-01 on 990110- 0220.One Violation of NRC Requirements Occurred.Violation Being Treated as non-cited Violation Consistent with App C of Enforcement Policy
ML20205A2611999-03-19019 March 1999
Advises of NRC Planned Insp Effort Resulting from Farley Plant Performance Review on 980202.Historical Listing of Plant Issues & Details of NRC Insp Plan for Next 8 Months Encl
ML20204C9561999-03-17017 March 1999
Forwards RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, Program at Plant,Units 1 & 2.Response Requested by 990521
ML20204E6601999-03-11011 March 1999
Discusses Ofc of Investigation Rept 2-1998-024 Re Contract Worker Terminated by General Technical Svc Supervisor for Engaging in Protected Activity.Evidence Did Not Substantiate Allegation & No Further Action Planned
ML20207M2181999-03-11011 March 1999
Advises That Info Contained in 990125 Application CAW-99-1318 & Affidavit Will Be Withheld from Public Disclosure,Per 10CFR2.790
ML20207M1991999-03-0808 March 1999
Partially Withheld Info Re Meeting Held on 990129 at Region II Ofc in Atlanta,Ga to Discuss Physical Protection Measure for Svc Water Intake Structure Located at Facility (Ref 10CFR73.21).List of Attendees Encl
ML20206U1831999-02-0909 February 1999
Responds to Encl Ltrs, & 1223 Re Generic Implication of part-length CRDM Housing Leak.Review Under TAC Numbers MA1380 & MA1381 Considered Closed
ML20203G5541999-02-0505 February 1999
Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 940407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Listing of Candidates for Exam
ML20203G3921999-02-0202 February 1999
Forwards Insp Repts 50-348/98-08 & 50-364/98-08 on 981129- 990109
ML20199L4451999-01-25025 January 1999
Forwards for Review & Comment Revised Draft Info Notice Re Inservice Testing of A-4 Multimatic Deluge Valve for Farley NPP Units 1 & 2.Informs That Comments Submitted on 981120 Were Reviewed & Incorporated Where Appropriate
ML20199K7351999-01-21021 January 1999
Responds to 981123 Request by Providing Copy of Latest Draft of Info Notice Being Prepared Which Discusses Failure of Several Preaction Sprinker Sys Deluge Valves.Requests Submittal of Comments by 981120
ML20199K7231999-01-20020 January 1999
Confirms 990119 Telcon Re Informational Meeting Scheduled for 990129 to Be Held in Atlanta,Ga to Discuss Security Related Issues at Plant.Meeting Will Be Closed to Public,Due to Sensitive Nature of Issues
ML20199K1381999-01-12012 January 1999
Informs That on 990117,Region II Implemented Staff Reorganization as Part of agency-wide Streamlining Effort, Due to Staffing Reductions in FY99 Budget.Organization Charts Encl
ML20199D8541999-01-12012 January 1999
Forwards SE Accepting Relief Request for Inservice Insp Program for Plant,Units 1 & 2
ML20199C9361999-01-0808 January 1999
Forwards Insp Repts 50-348/98-14 & 50-364/98-14 on 981207- 10.No Violations Noted
1999-09-09
[Table view] |
Inspection Report - Farley - 1988007 |
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Text
_ _ _ _ _ _ _ _ _ _ _ _ _ -
UNIT ED STATES .
'
NUCLEAR REGULATORY COMMISSION
[ '$ REGloN H 101 MARIETTA STREET, * {
t ATLANTA, GEORGI A 30323
..... APR 01 M8 Docket Nos. 50-348 and 50-364 License Nos. NPF-2 and NPF-8 Alabama Power Company ATTN: Mr. R. P. Mcdonald Senior Vice President P. O. Box 2641 Birmingham, AL 35291-0400 Gentlemen:
SUBJECT: NRC INSPECTION REPORT NOS. 50-348/88-07 AND 50-364/88-07 This refers to the Nuclear Regulatory Commission (NRC) 'nspection conducted by W. H. Bradford on February 11 - March 10, 1988. The inspect. ion included a review of activities authorized for your Farley facility. At the conclusion of the inspection, the findings were discussed with those members of your staff identified in the enclosed inspection repor Areas examined during the inspection are identified in the report. Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observation of activities in progres Within the scope of the inspection, no violations or deviations were identifie In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Roo The responses directed by this letter and its enclosure are not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, Pub. L. No. 96-51 Should you have any questions concerning this letter, please contact u
Sincerely, David M. Verelli, Chief Reactor Projects Branch 1 Division of Reactor Projects
.
Enclosure: (See page 2)
.-
8804150425 000407 0 PDR ADOCK 0500
- .- .. , . _- _ _ _
- _ _ - -_
W87g UNITED STATES .
'
Do NUCLEAR REGULATORY COMMISSION
-[ n REGloN ll
$.
j 101 MARIETTA STREET, 't ATL ANTA, G EORGI A 3o323
%,,,,,# hpR 01 M Docket Nos. 50-348, 50-364 License Nos. NPF-2 and NPF-8 Alabama Power Company ATTN: Mr. R. P. Mcdonald Senior Vice President P. O. Box 2641 Birmingham, AL 35291-0400 Gentlemen:
SUBJECT: NOTICE OF VIOLATION (NRC INSPECTION REPORT NOS. 50-348/88-07 AND 50-364/88-07)
This refers to the Nuclear Regulatory Commission (NRC) inspect. ion conducted by W. H. Bradford on February 11 - March 10,1988. The inspection included a review of activities authorized for your Farley facility. At the conclusion of the inspection, the findings were discussed with those members of your staff identified in the enclosed inspection repor Areas examined during the inspection are identified in the report. Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observation of activities in progres Within the scope of the inspection, no violations or deviations were identifie In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Roo The responses directed by this letter and its enclosure are not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, Pub. L. No. 96-51 Should you have any questions concerning this letter, please contact u
Sincerely, David M. Verelli, Chief Reactor Projects Branch 1 Division of Reactor Projects Enclosure: (See page 2)
