|
---|
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: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 - 1996009 |
---|
|
|
Text
. _ _ _ . . .
' '
December 24, 1997 Mr. D. Vice President - Farley Project Southern Nuclear Operating Company, Inc.
Post _ Office Box 1295 Birmingham, Alabama 35201 1295 SUBJECT: REQUEST FOR ADDITIONAL INFORMATION RELATED TO KAOWOOL FIRE BARRIERS - JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2
Dear Mr. Morey:
During a routine NRC inspection (NRC Inspection Report 50-348, 364/96-09), and a subsequent follow up inspection (NRC Inspection Report 50-348,364/97-12), the NRC identified a number of technicalissues associated with the design, installation, and fire resistive performance of the Kaowool raceway fire barriers installed at the Farley Nuclear Plant. In order
> to evaluate the ability of the Kaowool fire barriers to provide the level of fire resistive protection needed to meet the fire endurance performance objectives of NRC requirements (pre- and post-Appendix R), and the approved fire protection program, the staff requires additional information. Enclosed is the staff's request for additional information conceming the Kaowool fire barriers installed at the Farley Nuclear Plant.
In order to maintain a timely review, it is requested that the information be provided within 30 days of receipt of this letter, if you require any clarification regarding this request, please call me at (301) 415-2426.
Sincerely ORIGINAL SIGNED BY:
Jacob 1. Zimmerman, Project Manager Project Directorate 112 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation ,
Docket Nos. 50-348 and 50-364 Enclosure:- Requesi for Additional information gg g g}g g@pf
.cc w/ encl: See next page Distribution: HBerkow ACRS
' ' Docket File s - LBerry JJohnson, Rll PSkinner, Ril-b (C\
PUBLIC JZimmerman PD ll-2 Rdg. MSalley BBoger OGC *See previous concurrence g To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachmentlenclosure "N" = hgcoyy OFFICE PM:PDll-2* LA:PDil-29 lJ D:PDil-2 ( }b NAME JZIMMERMAN:cn LBERRYJLQ HBERKOWh
'
,DATE 12/23/97 Wr /97 /b/S2//97 / /97 DOCUMENT NAME: G:\FARLEY\KAOWOOL\M97701.RAI OFFICIAL RECORD COPY 9001120271 971224 PDR ADOCK 05000348 G PDR ,
.
-
h3 c c c -
+
,
' *
paano, 3- t UNITED STATES s-
p NUCLEAR REGULATORY COMMISSION 2 WASHINGTON, D.C. ma m3
%...../ December 24, 1997 Mr. D. R Morey Vice President - Farley Project Southem Nuclear Operating Company, Inc.
Post Office Box 1295 Birmingham, Alabama 35201 1295 SUBJECT: REQUEST FOR ADDITIONAL INFORMATION RELATED TO KAOWOOL FIRE BARRIERS - JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2
Dear Mr. Morey:
During a routine NRC inspection (NRC Inspection Report 50 348,364/96-09), and a subsequent follow-up inspection (NRC Inspection Report 50 348,364/97-12), the NRC identified a number of technical issues associated with the oesign, installation, and fira resistive performance of the Kaowool raceway fire barriers installed at the Farley Nuclear Plant. In order to evaluate the ability of the Kaowool fire barriers to provide the level of fire resistive protection needed to meet the fire entlurance performance objectives of NRC requirements (pre and post Appendix R), and the approved fire protection program, the staff requires additional information. Enclosed is the staff's request for additional information conceming the Kaowool fire barriers installed at the Farley Nuclear Plant.
In order to maintain a timely review, it is requested that the information be provided within 30 days of receipt of this letter, if you require any clarification regarding this request, please call me at (301) 415-2426.
Sincerely,
'
\{
% A <
a
Jacob 1. i merman, Pro et Manager Project Directorate ll-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation l
Docket Nos. 50-348 and 50-364
, Enclosure: Request for AdditionalInformation l-cc w/enci: See next page l
l
, _
. .. . . . .-- -.----- ._ .
, .
Joseph M. Farley Nuclear Plant.
cc:
Mr. R. D. Hill, Jr.
General Manager-Southem Nuclear Operating Company Post Omca Box 470 Ashford, Alabama 36312 Mr. Mark Ajiuni, Licensing Manager Southem Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201 1295 Mr. M. Stanforo Blanton Balch and Bingham Law Firm
'
Post Omco Box 306
'
1710 Sixth Avenue North Birmingham, Alabama 35201 Mr. J. D. Woodard Executive Vice President Southem Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201 State Health Officer Alabama Department of Public Health 4M Monroe Street Montgomery, Alabama 36130-1701 Chairman Houston County Commission Post Office Box 6406 Dothan, Alabama 36302 Regional Administrator, Region ll U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 Atlanta, Georgia 30303 Resident inspector
. U.S. Nuclear Regulatory Commission 7388 N. State Highway 95 Columbia, Alabama 36319
_ _
__ _ _ _ __ _ _
'. .
REQUEST FOR ADDITIONAL INFORMATION KAOWOOL RACEWAY FIRE BARRIER PERFORMANCE JOSEPH M. FARLEY NUCLEAR PLANT. UNITS 1 AND 2 1.0 BACKGROUND During a routine NRC inspection (NRC Inspection Report 50-348,364/96-09), and a subsequent follow-up inspection (NRC Inspection Report 50-348,364/9712), the NRC identified a number of technical issues associated with the design, installation, and fire resistive performance of Knowool raceway fire barriers installed at the Farley Nuclear Plant (FNP).
2.0 LICENSING BASJS On April 13,1979, the NRC issued the FNP Fire Protection Safety Evaluation Report (SER).
- This SER documented the results of the staffs evaluation of the Alcbama Power Company's (APC's, the licensee's) FNP Fire Protection Program Reevaluation Report (dated September 15,1977), and its Amendments 1-4 (dated February 23,1978; July 14,1978; October 27,1978; and January 3,1979, respectively), in 6.d4 SER, the NRC approved APC's commitments to provide (1) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> fire rated barriers for one train of Component Cooling Water (CCW) cables in the CCW Pump Area for each unit; (2) 30-minute fire rated barriers on the control and power cables to the CCW pumps and on other essential cables; and (3) either a double-thick barrier consisting of two layers of 30-minule-rated enclosure around one train, or a half hour barrier around both trains for the cables located in Fire Areas 1,4,5,6,9,13,20,21, 34,41,42,51. and 72. This is in accordance with Section 4.3.5.1 of the FNP Fire Protection Reevaluation Report.
2.1 REQUEST FOR ADDITIONAL INFORMATION Please provide the following information:
2,1.1 For each fire area, provide a list of the electrical raceways protected by a fire barrier and describe the safety related and safe shutdown functions being protected.
2.1.2 For each fire arsa, identify the type of raceway (e.g.,18-inch wide aluminum ladder back cable tray), the fire barrier material used (e.g.,1 inch of Kaowool) and provide the design details (e.g., typical design and installation drawing details), and installation instructions that were in use at the time of the August 21,1980, NRC site visit.
Enclosure
_ - . _ _ . - -- -
-..- - ,- -. ,-. _ - _ - -_ _ - - - - -
, ,
--
2-2.1.3 For each raceway fire barrier, provide the fire test reports, data,' and _ engineering _
evaluations that support the fire resistive rating of the fire barrier used to meet the fire protection technical requirements as documented in the April 13,1979, SER.'
3.0 TECHNICAL BASIS FOR APPENDIX R EXEMPTIONS By letters dated March 13 and May 31,1985, FNP requested exemotions to Appendix R, Section Ill.G. The licensee based its exemption requests on the Appendix R imorpretations made in Generic Letter (GL) 83-33 *NRC Positions on Certain Requirements of Appendix R to 10 CFR Part 50," October 19,1983, and Information Notice (lN) 84-09 " Lessons Leamed from NRC Inspections of Fire Protection Safe Shutdown Systems (10 CFR Part 50, Appendix R),"
February 13,1984. The NRC-approved exemptions, are based, in part, on the assumption that i
' the Knowool raceway fire barriers were accepted by the NRC and installed prior to the issuance ;
of Appendix R.
3.1 REQUEST FOR ADDITIONAL INFORMATION
- In support of certain exemptions, the I;censee committed to install additional 1-hour rated fire barriers. Since these were new installations and were not previously approved, their design should have considered the fire barrier performance guidance identified in IN 84-09 and later in GL 86-10 ' implementation of Fire Protection Requirements," April 24,1986: In order to e evaluate the fire resistive performance of the fire barriers installed in support of the March 13 and May 31,1985, exemption requests, provide the following additional information:
3.1.1 Identify the new raceway fire barriers (i.e., installed after the effective date of Appendix R)
. and their fire resistive rating. In addition, for each of these fire barriers, identify the fire area / room where they are located, the raceway / cable tray they are protecting , and the safe shutdown or safety-related function that is being protected.
.
__
3.1.2 For these raceway fire barriers, pmvide the design details (e.g., typical design and installation drawing details) and intJllation instructions that were developed and used to install the barriers.
3.1.3 For each fire barrier, provide the fire test reports, data, and engineering evaluations that support the fire resistive rating of the fire barriers.
3.1.4 For exemption requests 1-22,1-26, and 2-4, the licensee stated that some of the pre-existing raceway fire barrier installations were adequate based on the fact that their fire resistive rating exceeded the potential fire severity in the fire area. For these cases, provide the analysis that supports the conclusion that the protected cables would be free
- of fire damage in the event of a fire, u - . -
i
,
- - . . . - . , . - ~..
. - _ .. . - . - - . . - - . - . - . - -_.- . - _ . _ . - - . _ . _ - . - - -
i <.
.s
- 3-
'
4.0 FIRE ENDURANCE TESTING
In IN 93-40,' Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier Material," i
= May 26,1993, the 6taff identified problems with the fire endurance performance of the Thermal. j Ceramics rackasy fire barrier system (using two FiroMaster FP-60,1-inch thick, ceramic fiber )
= blankets) installed on a 36-inch wide cable tray,: At approximately 20 minutes into the test the 1
- tray developed an opening' at a butt joint which resulted in a 3-1/2-inch opening at the end of -
- the test (60 minutes). The temperature as measured on cables inside the barrier system ranged from 400 - 500 'F at the end of the test. Hosc stream tests were not performed. ,
,
in IN 9341 *One Hour Fire Endurance Test Results for Thermal Ceramics Knowool 3M Company FS-195 and 3M Company Interam E-50 Fire Banier Systems,' May 28,1993, the staff also identified conditions related to the thermal performance of the Kaowool fire barrier i system when tested in a small scale fumace. The temperature as measured on the nonfire or t unexposed side of the fire barrier material on the cables reached a maximum temperature of l 800 'F at 60 minutes. (Note: Thia test attempted to follow the ASTM E-119 standard time l temperature test fire exposure but failed to do so.) The test results in IN 93-41 are further l aiscussed in the Underwriters Laboratories, Inc. (UL), report dated September 6,1978, and are I related to the cable tray fire test; Test No. 3. UL did not perform the test, classify the fire barner 1
,
product, issue a listing, or claim that this test would predict full-scale fire test performance. !
Based on a letter dateel October 1,1993, from J. E. Love, Project Enge . Bechtel, to l
- . D. N. Morey, Vice President, Southem. Nuclear Operating Company, it appears that the fire l resistive rating / qualification of the Kaowool barriers installed at FNP between 1979 and 1980 l
'
L are based on the Kaowool receway and cable tray fire barrier system designs documented in
. Babcock and Wilcox fire test report entitled " Tests For Fire Protection for Complete Engulfinent ,
'
. . of Cable Trays and Conduits Containing grouped Electrical Conductors," dated October 24,
. 1978.' The fire barrier design tested in Test No. 3 had a cable fill of 35% and it allowed cable ;
Jacket temperatures to reach 200 - 800 'F at 60 minutes. This cable tray fire barrier system used a tight butt joint design and appeared to perform better than the design that used an ;
,
attemative butt joint design. No hcse stream test was performed. ;
'
The NRC, in Inspection Report 50-348, 364/97-12, identified that certain FNP electrical raceway or cable tray fire barrier systems do not extend through the fire barrier wall penetration, which is not representative of the tested configuration. The FNP Knowool fire barriers typically butt up -
against a fire rated wall, floor, ceiling, or silicone penetration ' seal and are bonded to,its mating surface (e.g., wall face) with a flame-mastic type coating. The staff is concemed that this fire barrier interface may not be capable of maintaining the continuity of the fire barrier, and thus prevent it from performing its intended fire resistive function.
. __ i The Underwriters Laboratories, Inc. (UL), Report dated September 6,1978, entitled " Cable
~ Raceway Protection Systems Fire Test investigation," documents the independent observations
- made by UL during the Babcock and Wilcox Knowool fire barrier test, which were documented
. : in its report dated October 24,1978.
.
.
_ _ _ _ . . . ~ _ , . , ,,,,-s- w. . - ~ - m.,# a,.,,.. , -v-,,-- - , * , , , #--.,. ,,,,- ,.- - , -, ,- ,, .r-. _ .
i
, .
l
'
?
!
, 4.1 REQUEST FOR ADDITIONAL INFORMATION l l 4.1.1 Describe the butt joint design used at FNP and discust how it meets or exceeds the design attributes used by the Babcock and Wilcox 1978 test configuration. State whether or not an analysis was performed, which evaluated the butt joint design deficiency noted ,
'
IN 93-40 and its potential applicability to the designs used at FNP. Provide the analysis.
4.1.2 Discuss the design / installation attributes of the FNP Knowool fire barriers as campered to !
'
those tested and for osch of the critical attributes (e.g., raceway siz6, raceway
orientation, air drops, cable fill, cable size, cable type, joint and seem design, fastener /
- band spacing) and summarize how deviations between the tested and installed attributes .
,
effect the fire resistive charactristics of the installed fire barriers. Provide any additional - l
, informaticn which demonstrates that the installed Knowool fire barriers meet NRC !
i requirements and licensing commitments.
[
1 4.1.3 The 1978 &abcock and Wilcox tests (4 inch diameter conduit and 18-inch wide cable tray) evaluated limited receway configurations, in addition, the raceway fire barrier I system test specimens extended through the fumaos well and terminated outside ;,w test "
'
fire's zone of influence. Sechtel, in its letter dated Octcber 1,1993, indicated that the L 1978 Babcock and Wilcox test results provided sufficient test data to justify scooptance i of nontested configurations. Provide the engineering analysis which supports the ,
4 conclusions made that the 1978 tests bound the actual installations. Specifically, ;
address the Knowool fire barrier interface with other fire barriers (e.g., fire walls). -
'
4.1.4 For the FNP Knowool fire barriers installed after the effective date of Appendix R, provide the cable functionality analysis and subsequent testing which demonstrates that the protected post fire safe shutdown cables are capable of performing their intended ;
"
functions during and after a postulated fire (Refer to GL 86-10 Interpretation 3, * Fire
'
Damage"), j c l 4.1.5 Provide the tests / analysis that technically assesses the required protection to raceway ;
supports and the required protection of intervening items into the Knowool fire barrier system. l f
5.0 GENERIC LETTER 92-08 ,
On Dooember 17,1992, the staff issued Generic Letter (GL) 92-08, "Thermo-Lag 3301 Fire [
Barriers," to all holders of operating licenses for nuclear power plants. GL 92-08 addressed
.
fire endurance and ampacity dorating issues associated with Thermo Lag 330-1 fire barrier i materials. GL 92-08, did not request specific action for other barrier materials. However, as documented in GL 92-08, the staff expected the licensees with fire barriers constructed from i other materials to review ' . 92 08 and determine if the technicalissues applied to those other barrier materials used at their facilities and to consider actions, as appropriate, to avoid similar :
problems. ,
'
,
P C _ _ _ _ _ _ . - _ _ . _ _ . . _ _ a
_ . ~ . _ _ _ _ _ _ _ _ - - _ _ _ _
-
_ - _ _ _ _ _ _ _ _ _ _ . _ - . - _ _ . _ . _ _ . . _ _ . . _ . _ __ _ _...
. . . .
5.1 REQUEST FOR ADDITIONAL INFORMATION 5.1.1 GL 92-08 identified three principal areas of concem: fire endurance capability; ampacity dorating of cables enclosed in fire barriers; and the evaluation and application of the resulte of tests conducted to determine the fire endurance ratings and the ampacity dercting factors. State whether or not an evaluation was performed to assess the Knowool fire barrier design, fire endurance performance, nr.d ampacity dorating against the insights and concems documented in GL 92-08, if an evaluation was performed, provide the results and discuss the subsequent actions taken to assess and correct any technical issues associated with the installed Knowool fire barriers.
,
.
-S. - - ,- . . - - . , - - - , . - - - . , - - , - - - , . - . . . , ,
, . . , . ., ...----m-g_. , n-a._,