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| DEC l / 82
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| Docket Nos. 50-348, 50-364
| | _ |
| License Nor. NPF-2, NPF-8
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| Southern Nuclear Operating Company, Inc.
| |
| ATTN: Mr. W. G. Hairston, III
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| Executive Vice President
| |
| Nuclear Operations
| |
| P. O. Box 1295
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| Birmingham, AL 35201
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| Gentlemen: .i
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| SUBJECT: NRC INSPECTION REPORT NO. 50-348/92-30 AND 50-364/92-30
| |
| ,
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| This refers to the inspection conducted by M. D. Hunt of this office on
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| November 16-20, 1992. The inspection included a review of activities autho-
| |
| rized for your Farley facility. At the conclusion of the inspection, the
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| findings were discussed with those members of your staff identified in the
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| report. .
| |
| Areas examined during the inspection are identified in the report. Within
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| these areas, the inspection consisted of selective examinations of procedures
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| and representative records, interviews with personnel,-and observation of
| |
| ; activities in progress.
| |
| . | | . |
| Within the scope of the inspection, violations or deviations were not identi-
| | . - . |
| fled. However_, our review of your GL 89-10 Motor Operated Valve (MnV) program
| | D/J l |
| indicated that programatic issues associated with differential. pressure
| | ' |
| testing to the maximum extent possible and the acceptability of using the
| | - |
| MOVATS data base for valve setup remains open. Additional information
| | . |
| regarding NRC inspection fitdings 50-348, 364/91-201-02-and 91-201-03 is
| | . |
| necessary for the NRC to complete the evaluation of the acceptability of your-
| | DEC l / 82 |
| GL 89-10 M0V program. You are requested to provide the following information:
| | ; |
| Your ' plans for differential pressure -(d/p) testing to the maximum extent
| | Docket Nos. 50-348, 50-364 |
| practicable since the limited d/p testing that was performed during your
| | License Nor. NPF-2, NPF-8 |
| , 1992 indicated that M0 VATS data base and vendor calculations underpr-
| | Southern Nuclear Operating Company, Inc. |
| edicted the required minimum thrust approximately: 25% of the time. This-
| | ATTN: Mr. W. G. Hairston, III |
| should also include your controls for selection and screening of valves
| | Executive Vice President |
| that will or will not be d/p -tested.
| | Nuclear Operations |
| Information' that demonstrates that your M0V program will clearly document-
| | P. O. Box 1295 |
| assumptions and margins used in the thrust calcul nions to compensate for
| | Birmingham, AL 35201 |
| uncertainties in the MOVATS data base and vendor calculations.
| | Gentlemen: |
| ,- 9212290004 921217
| | .i |
| h PDR ADOCK 05000348 ,
| | SUBJECT: |
| .G. -PDR -
| | NRC INSPECTION REPORT NO. 50-348/92-30 AND 50-364/92-30 |
| .
| | , |
| XBol
| | This refers to the inspection conducted by M. D. Hunt of this office on |
| | November 16-20, 1992. |
| | The inspection included a review of activities autho- |
| | rized for your Farley facility. At the conclusion of the inspection, the |
| | findings were discussed with those members of your staff identified in the |
| | report. |
| | . |
| | 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 progress. |
| | . |
| | Within the scope of the inspection, violations or deviations were not identi- |
| | fled. However_, our review of your GL 89-10 Motor Operated Valve (MnV) program |
| | indicated that programatic issues associated with differential. pressure |
| | testing to the maximum extent possible and the acceptability of using the |
| | MOVATS data base for valve setup remains open. Additional information |
| | regarding NRC inspection fitdings 50-348, 364/91-201-02-and 91-201-03 is |
| | necessary for the NRC to complete the evaluation of the acceptability of your- |
| | GL 89-10 M0V program. |
| | You are requested to provide the following information: |
| | Your ' plans for differential pressure -(d/p) testing to the maximum extent |
| | practicable since the limited d/p testing that was performed during your |
| | 1992 indicated that M0 VATS data base and vendor calculations underpr- |
| | , |
| | edicted the required minimum thrust approximately: 25% of the time. This- |
| | should also include your controls for selection and screening of valves |
| | that will or will not be d/p -tested. |
| | Information' that demonstrates that your M0V program will clearly document- |
| | assumptions and margins used in the thrust calcul nions to compensate for |
| | uncertainties in the MOVATS data base and vendor calculations. |
| | 9212290004 921217 |
| | ,- |
| | h |
| | PDR |
| | ADOCK 05000348 |
| | , |
| | .G. |
| | -PDR |
| | - |
| | . |
| | XBol |
|
| |
|
| ,
| | , |
| i
| | i |
| .- '. *
| | * |
| Southern Nuclear Operating 2 DEC I 7 1992
| | '. |
| Company, Inc.
| | .- |
| Please respond within 30 days of receipt of this letter.
| | DEC I 7 1992 |
| The responses directed by this letter are not subject to the clearance
| | Southern Nuclear Operating |
| procedures of the Office of Management and Budget as required by the Paperwork
| | 2 |
| Reduction Act of 1980, Pub. L. No. 96-511.
| | Company, Inc. |
| In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of
| | Please respond within 30 days of receipt of this letter. |
| this letter and its enclosure will be placed in tne-NRC Public Document Room.
| | The responses directed by this letter are not subject to the clearance |
| Should you have any questions concerning this letter, pisase-contact us.
| | procedures of the Office of Management and Budget as required by the Paperwork |
| Sincer ly,
| | Reduction Act of 1980, Pub. L. No. 96-511. |
| 8
| | In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of |
| Albert F. Gibson, Director
| | this letter and its enclosure will be placed in tne-NRC Public Document Room. |
| Division of Reactor Safety
| | Should you have any questions concerning this letter, pisase-contact us. |
| | Sincer ly, |
| | 8 |
| | Albert F. Gibson, Director |
| | Division of Reactor Safety |
| 4 | | 4 |
| Enclosure:
| | Enclosure: |
| NRC Inspection Report
| | NRC Inspection Report |
| cc w/ encl:
| | cc w/ encl: |
| B. L. Moore
| | B. L. Moore |
| Manager, Licensing
| | Manager, Licensing |
| Southern Nuclear Operating
| | Southern Nuclear Operating |
| Company, Inc.
| | Company, Inc. |
| P. O. Box 1295
| | P. O. Box 1295 |
| Birmingham, AL 35201-1295
| | Birmingham, AL 35201-1295 |
| R..D. Hill, Jr.
| | R..D. Hill, Jr. |
| , | | , |
| General Manager, Farley Plant i
| | General Manager, Farley Plant |
| [ Southern Nuclear Operating 1 | | i |
| 7
| | [ |
| Company, Inc. .l
| | Southern Nuclear Operating |
| .P. O. Box 470
| | 1 |
| Ashford,'-AL 36312
| | 7 |
| W. R. Bayne, Supervisor
| | Company, Inc. |
| Safety Audit and Engineering Review
| | .l |
| Farley Nuclear' Plant ;
| | .P. O. Box 470 |
| P. O. Box 470
| | Ashford,'-AL 36312 |
| Ashford, AL 36312
| | W. R. Bayne, Supervisor |
| -State Health Officer
| | Safety Audit and Engineering Review |
| Alabama Department of Public Health
| | Farley Nuclear' Plant |
| 434 Monroe Street-
| | ; |
| -Montgomery, AL 36130-1701
| | P. O. Box 470 |
| .(cc w/ encl cont'd - See page 3)
| | Ashford, AL 36312 |
| . . . . . :- - .n.- . - - - . . . = . . . - - , _ . . , , . - , . . . - . . . -
| | -State Health Officer |
| | Alabama Department of Public Health |
| | 434 Monroe Street- |
| | -Montgomery, AL 36130-1701 |
| | .(cc w/ encl cont'd - See page 3) |
| | . . . |
| | . . :- |
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| | _ |
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| | . . - - |
| Southern Nuclear Operating 3- .
| | . |
| Company, Inc. DEC -l l G2
| | . - - |
| (cc w/ encl cont'd)
| | . _ . _ . _ |
| James H. Miller, Ill, Esq.
| | . - - |
| Balch and Bingham
| | .. - |
| P. O. Box 306
| | -. |
| 1710 Sixth Avenue North
| | * |
| Birmingham, AL 35201
| | . |
| Chairman
| | O |
| Houston County Conunission
| | i |
| !1 P. O. Box 6406
| | Southern Nuclear Operating |
| Dothan, Al 'd302
| | 3- |
| bec w/ enc 1:
| | Company, Inc. |
| Steve Hoffman, NRR
| | DEC -l l G2 |
| F. Cantrell, Ril
| | . |
| Document Control Desk
| | (cc w/ encl cont'd) |
| NRC Resident inspector
| | James H. Miller, Ill, Esq. |
| '
| | Balch and Bingham |
| U.S. Nuclear Regulatory Commission
| | P. O. Box 306 |
| Route 2, Box 24
| | 1710 Sixth Avenue North |
| Columbia, AL 36319
| | Birmingham, AL 35201 |
| FILE NAME: S:\DRS\EB\FAR9230L.MB
| | Chairman |
| -Ril:DRS- Ril:DRS Ril:DR ' Ril:DRS Ril '';
| | Houston County Conunission |
| Rll:DRP
| | P. O. Box 6406 |
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| | 'd302 |
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| | Steve Hoffman, NRR |
| 12//p/92 12//O /92 12//B/92 )12/0/92- 12/[{/92 12/gy/92
| | F. Cantrell, Ril |
| -- . _ - - , - . _ . - . - _ . . . _._- _ _ .-..- - _. -
| | Document Control Desk |
| | NRC Resident inspector |
| | ' |
| | U.S. Nuclear Regulatory Commission |
| | Route 2, Box 24 |
| | Columbia, AL 36319 |
| | FILE NAME: S:\\DRS\\EB\\FAR9230L.MB |
| | -Ril:DRS- |
| | Ril:DRS |
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| }} | | }} |
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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 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 ML20212C2351999-09-16016 September 1999 Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal L-99-031, Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams 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 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 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 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 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 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 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 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 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 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 L-99-027, 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 Guidelines1999-07-22022 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 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 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 ML20196J7471999-07-0202 July 1999 Forwards RAI Re Cycle 16 Extension Request.Response Requested within 30 Days of Date of Ltr 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 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 L-99-024, 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 ML20196J3591999-06-30030 June 1999 Forwards SE of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs 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 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 ML20196D1931999-06-22022 June 1999 Discusses Requesting Approval & Issuance of Plant Units 1 & 2 ITS by 990930.New Target Date Agrees with Requested Date ML20196A3401999-06-10010 June 1999 Forwards Insp Repts 50-348/99-03 & 50-364/99-03 on 990404-0515.No Violations Noted ML20196H9801999-06-10010 June 1999 Submits Two RAI Re ITS Section 4.0 That Were Never Sent. Reply to RAI Via e-mail L-99-021, 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-99-022, 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 1999-09-09
[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 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 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 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 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 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 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 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 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 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 ML20199D8541999-01-12012 January 1999 Forwards SE Accepting Relief Request for Inservice Insp Program for Plant,Units 1 & 2 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 ML20199C9361999-01-0808 January 1999 Forwards Insp Repts 50-348/98-14 & 50-364/98-14 on 981207- 10.No Violations Noted ML20198S2741999-01-0606 January 1999 Informs That Staff Reviewed SG 90-day Rept, Farley Unit 2 1998 Voltage Based Repair Criteria 90 Day Rept, & Found Assessment to Be Acceptable.Staff Review Encl 1999-09-09
[Table view] |
See also: IR 05000348/1992030
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DEC l / 82
Docket Nos. 50-348, 50-364
License Nor. NPF-2, NPF-8
Southern Nuclear Operating Company, Inc.
ATTN: Mr. W. G. Hairston, III
Executive Vice President
Nuclear Operations
P. O. Box 1295
Birmingham, AL 35201
Gentlemen:
.i
SUBJECT:
NRC INSPECTION REPORT NO. 50-348/92-30 AND 50-364/92-30
,
This refers to the inspection conducted by M. D. Hunt of this office on
November 16-20, 1992.
The inspection included a review of activities autho-
rized for your Farley facility. At the conclusion of the inspection, the
findings were discussed with those members of your staff identified in the
report.
.
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 progress.
.
Within the scope of the inspection, violations or deviations were not identi-
fled. However_, our review of your GL 89-10 Motor Operated Valve (MnV) program
indicated that programatic issues associated with differential. pressure
testing to the maximum extent possible and the acceptability of using the
MOVATS data base for valve setup remains open. Additional information
regarding NRC inspection fitdings 50-348, 364/91-201-02-and 91-201-03 is
necessary for the NRC to complete the evaluation of the acceptability of your-
GL 89-10 M0V program.
You are requested to provide the following information:
Your ' plans for differential pressure -(d/p) testing to the maximum extent
practicable since the limited d/p testing that was performed during your
1992 indicated that M0 VATS data base and vendor calculations underpr-
,
edicted the required minimum thrust approximately: 25% of the time. This-
should also include your controls for selection and screening of valves
that will or will not be d/p -tested.
Information' that demonstrates that your M0V program will clearly document-
assumptions and margins used in the thrust calcul nions to compensate for
uncertainties in the MOVATS data base and vendor calculations.
9212290004 921217
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PDR
ADOCK 05000348
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DEC I 7 1992
Southern Nuclear Operating
2
Company, Inc.
Please respond within 30 days of receipt of this letter.
The responses directed by this letter 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.96-511.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of
this letter and its enclosure will be placed in tne-NRC Public Document Room.
Should you have any questions concerning this letter, pisase-contact us.
Sincer ly,
8
Albert F. Gibson, Director
Division of Reactor Safety
4
Enclosure:
NRC Inspection Report
cc w/ encl:
B. L. Moore
Manager, Licensing
Southern Nuclear Operating
Company, Inc.
P. O. Box 1295
Birmingham, AL 35201-1295
R..D. Hill, Jr.
,
General Manager, Farley Plant
i
[
Southern Nuclear Operating
1
7
Company, Inc.
.l
.P. O. Box 470
Ashford,'-AL 36312
W. R. Bayne, Supervisor
Safety Audit and Engineering Review
Farley Nuclear' Plant
P. O. Box 470
Ashford, AL 36312
-State Health Officer
Alabama Department of Public Health
434 Monroe Street-
-Montgomery, AL 36130-1701
.(cc w/ encl cont'd - See page 3)
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Southern Nuclear Operating
3-
Company, Inc.
DEC -l l G2
.
(cc w/ encl cont'd)
James H. Miller, Ill, Esq.
Balch and Bingham
P. O. Box 306
1710 Sixth Avenue North
Birmingham, AL 35201
Chairman
Houston County Conunission
P. O. Box 6406
!1
Dothan, Al
'd302
bec w/ enc 1:
Steve Hoffman, NRR
F. Cantrell, Ril
Document Control Desk
NRC Resident inspector
'
U.S. Nuclear Regulatory Commission
Route 2, Box 24
Columbia, AL 36319
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