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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation ML20203B9591997-09-18018 September 1997 Pressure Locking Summary & Evaluations Using Commonwealth Edison Methodology for Sqn ML20210J1761997-07-31031 July 1997 Unit 1,Cycle 9 Alternate Plugging Criteria 90 Day Rept ML20138D1991997-04-0404 April 1997 Special Project97-928S, Sequoyah Nuclear Plant Assessments ML20138C5371997-03-24024 March 1997 Rev 0 to Pressurizer Level Event ML20217G2401997-03-0303 March 1997 Non-proprietary Rev 0 to SE of Reduced Thermal Design Flow ML20117J3611996-08-0101 August 1996 SE of Safety Valve Setpoint Tolerance Relaxation ML20117K9461996-03-0505 March 1996 Reliability Study ML20117K9511996-02-29029 February 1996 Reliability Common Cause Assessment, for Feb 1996 ML20095J1891995-10-0505 October 1995 Design & Analysis of Weld Overlay Repair for Sequoyah Unit 1 CRDM Lower Canopy Seal Welds ML20081D3831995-03-12012 March 1995 Simulator Four Yr Test Rept for 950312 ML20083N9521994-11-16016 November 1994 10CFR50.59 Rept to Nrc ML20024H8491993-07-19019 July 1993 Evaluation of Ultrasonic Test Results from 1993 ISI on Underclad Flaw Indications in Sequoyah,Unit 1 Rv Nozzles. ML20118D1941992-09-21021 September 1992 Technical Rept on Hydrogen Control Measures & Effects of Hydrogen Burns on Safety Equipment ML20114A6641992-08-15015 August 1992 920619 Self-Assessment. Several Hardware & Software Enhancements to Emergency Response Ctrs Completed During Reporting Period ML20141M1341992-03-27027 March 1992 Spent Fuel Pool Mod for Increased Storage Capacity ML20029C2011991-03-12012 March 1991 Initial Simulator Certification. ML20028H8591990-09-0707 September 1990 Nuclear Quality Audit & Evaluation Review Rept, Sequoyah Nuclear Plant Look Back Review of Cable Issues. ML20136J0431990-06-30030 June 1990 Criticality Analysis of Sequoyah Units 1 & 2 Fresh Fuel Racks ML20043B6061990-05-11011 May 1990 Diesel Generator Voltage Response Improvement Rept. ML20006E5771990-02-0505 February 1990 Rev 1 to Sequoyah Units 1 & 2 Spent Fuel Storage Rack Criticality Analysis. ML20246D5351989-02-28028 February 1989 Steam Generator Tubing Insp Results ML20247H1301988-11-30030 November 1988 Rev 0 to Structural Analysis & Evaluation of Sequoyah Reactor Coolant Pump Support Columns ML20236D1951988-11-18018 November 1988 HVAC Damping Values ML20134H6801988-09-0202 September 1988 Technical Evaluation of Procurement of Matls & Svcs ML20245B4181988-08-17017 August 1988 Investigation Rept,Design & Operation of Sampling Sys for Analysis of High Purity Water ML20151Q2691988-08-0101 August 1988 Final Rept on IE Bulletin 79-14 for Tva,Sequoyah Nuclear Plant Unit 1 & Common Piping ML20155J5721988-07-31031 July 1988 Assessment of Structural Adequacy of Concrete Foundation Cells for Emergency Raw Cooling Water Pumping Station & Access Roadway ML20207F6231988-07-0505 July 1988 Evaluation of Effects of Postulated Pipe Failures Outside of Containment for Sequayah Nuclear Plant,Units 1 & 2 ML20207B6301988-06-27027 June 1988 Engineering Assurance Oversight Review Rept,Sequoyah Nuclear Plant - Unit 1,Design Baseline & Verification Program ML20147G9961988-03-31031 March 1988 Review of Operational Readiness Corrective Actions. Related Documentation Encl ML20147H6331988-02-29029 February 1988 Plant,Diesel Generator Evaluation Rept ML20147G7861988-02-25025 February 1988 Task Rept on Development of Seismic Acceleration Response Spectra for Diesel Generator Bldg of Sequoyah Nuclear Plant, Part 1:Design Basis SSE Input ML20147G8041988-02-25025 February 1988 Task Rept on Development of Seismic Acceleration Response Spectra for Diesel Generator Bldg of Sequoyah Nuclear Plant, Part 2:Site-Specific OBE & SSE Inputs ML20234F2111988-01-0505 January 1988 Rept of Sequoyah Readiness Review ML20147F0581987-12-0202 December 1987 Non-linear Time History Seismic Response Analyses for ERCW Cell, Task Rept ML20236B3481987-10-15015 October 1987 Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 207.4(B), Deviation Documentation:Caq Documentation ML20236B3511987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Sequoyah Element Rept 232.8(B), Piping & Valve Design:Criteria for Min Pipe Wall Thickness ML20236B3541987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 235.2(B), Electrical Safety:Exposed 480 Volt Bus at Panel Top ML20236B3441987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Sequoyah Element Rept 204.9(B), Use of Reverse Prints ML20236B3581987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 241.4(B), Cable Termination & Splices:Amphenol Connector ML20236Q2011987-10-0101 October 1987 Temp Measurement Rept for Long-Term Current Test on Littlefuse,Flas-5,5 Amp Fuses 1999-08-02
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20217G3721999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20210G6631999-07-28028 July 1999 Cycle 9 90-Day ISI Summary Rept ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20195K2951999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20204C3111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20203H7381999-02-18018 February 1999 Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions ML20211A2021999-01-31031 January 1999 Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199G3641998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20197J5621998-12-0303 December 1998 Unit 1 Cycle 9 90-Day ISI Summary Rept ML20197K1161998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20195F8061998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With ML20154H6091998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20154H6251998-09-17017 September 1998 Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 Colr ML20153B0881998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 ML20237B5221998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Snp ML20237A4411998-07-31031 July 1998 Blended Uranium Lead Test Assembly Design Rept ML20236P6441998-07-10010 July 1998 LER 98-S01-00:on 980610,failure of Safeguard Sys Occurred for Which Compensatory Measures Were Not Satisfied within Required Time Period.Caused by Inadequate Security Procedure.Licensee Revised Procedure MI-134 ML20236R0051998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Sequoyah Nuclear Plant ML20249A8981998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Sequoyah Nuclear Plant,Units 1 & 2 ML20247L5141998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Sequoyah Nuclear Plant ML20217K4471998-04-27027 April 1998 Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05 ML20217E2221998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sequoyah Nuclear Plant ML20248L2611998-02-28028 February 1998 Monthly Operating Repts for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20202J7911998-01-31031 January 1998 Monthly Operating Repts for Jan 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 ML20199F8531998-01-13013 January 1998 ASME Section XI Inservice Insp Summary Rept for Snp Unit 2 Refueling Outage Cycle 8 ML20199A2931997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20198M1481997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20197J1011997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199C2951997-11-13013 November 1997 LER 97-S01-00:on 971017,vandalism of Electrical Cables Was Observed.Caused by Vandalism.Repaired Damaged Cables, Interviewed Personnel Having Potential for Being in Area at Time Damage Occurred & Walkdowns ML20199C7201997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Sequoyah Nuclear Plant L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation 1999-09-30
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1 TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.6 (B)
SPECIAL PROGRAM REPORT TYPE: SEQUOYAH ELEMENT REVISION NUMBER: 0 TITLE: PIPING AND VALVE DESIGN Rubt'er Gasket Deterioration PAGE 1 0F 9 REASON FOR REVISION:
PREPARATION PREPARED B N /0//7/RS
// '
// SIGNATURE 'DATE REVIEWS M644 REVIEW COMMITTEE f
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/ DATE V
TAS:
SIGNATURE DATE CONCURRENCES V) / /0 lll CEG-H: NW / O'2 7- 14 SRP:
SIGNATURE DATE SIGNATURE DATE APPROVED BY:
ECSP MANAGER DATE MANAGER OF NUCLEAR POWER DATE 8612090459 861120 7 CONCURRENCE (FINAL REPORT ONLY)
DR ADOCK 0500
[
TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.6 (8)
SPECIAL PROGRAM REVISION NUMBER: O PAGE 2 0F 9
- 1. CHARACTERIZATION OF ISSUE (S):
Concern: Issue:
IN-85-400-002 Rubber gaskets, used in flange
" Rubber gaskets used in the ERCW, joints, installed in safety-related RCW, and other unspecified raw water piping systems such as systems, exhibit deterioration Essential Raw Cooling Water (ERCW),
over short periods of time: exhibit rapid deterioration and could which could adversely impact impact plant nuclear safety, plant nuclear safety due to '
gasket failure. No further specifics or other details are available."
- 2. HAS ISSUE BEEN IDENTIFIED IN ANOTHER SYSTEMATIC ANALYSIS? YES X NO Identified by TVA Generic Concern Task Force Report Date 05/19/86 Documentation Identifiers:
~
GOR-23-23, Rev. 1
- 3. DOCUMENT NOS.. TAG NOS.. LOCATIONS. OR OTHER SPECIFIC DESCRIPTIVE IDENTIFICATIONS STATED IN ELEMENT:
The element identifies rubber gaskets installed in flanged joints used in ERCW and Raw Cooling Water (RCW).
- 4. INTERVIEW FILES REVIEWED:
File No. IN-85-400-002
- 5. DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
See Appendix A.
1069d - 10/17/86
TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.6 (8)
SPECIAL PROGRAM REVISION NUMBER: O PAGE 3 0F 9
- 6. WHAT REGULATIONS. LICENSING COMMITMENTS. DESIGN REQQlREMENTS. OR OTHER APPLY OR CONTROL IN THIS AREA?
See Appendix A.
- 7. REQUESTS FOR INFORMATION. MEETINGS. TELEPHONE CALLS. AND OTHER DISCUSSIONS RELATED TO ELEMENT:
See Appendix A.
- 8. EVALUATION PROCESS:
- a. Reviewed with site personnel maintenance history of rubber gaskets at SQN and WBN plants.
- b. Established historical validity of the concern from a search of maintenance records.
- c. Identified material presently used for rubber gaskets and reviewed code requirements.
- d. Reviewed TVA Generic Concern Task Force Report, GOR-23-23 for this element and assess / verify findings.
- e. Determined safety impact of rubber gasket deterioration if it were presumed to occur.
- 9. DISCUSSION. FINDINGS. AND CONCLUSIONS:
Discussion:
The concern relates to short-term deterioration of rubber gaskets installed in flanged piping joints in the ERCW, the RCW and other unspecified systems at WBN plant. The CI postulates that such a condition may have a possible adverse impact on plant nuclear safety.
1069d - 10/17/86
TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.6 (8)
SPECIAL PROGRAM REVISION NUMBER: 0 PAGE 4 0F 9 Initially this concern was investigated on WBN. Interviews with WBN maintenance personnel could not establish a historical problem with rubber gaskets in either safety or non-safety related systems. One isolated instance suggested that about six years ago some unidentified rubber gasket material installed in non-safety related systems did not perform satisfactorily and required replacement. No further action was considered necessary at that time, and no further problems of this nature have been noted.
Based on the WBN concern the TVA SQN Generic Concern Task Force identified " rubber gasket deterioration" as a potential generic
~
issue. An investigation was initiated to determine if a similar problem existed at SQN plant. The Task Force interviewed responsible SQN mechanical maintenance personnel, but none were aware of any rubber gasket deterioration problem. Additionally, the Task Force examined 1555 maintenance requests (MR) on the ERCW system covering a six year period through April 17, 1986. Five of these MRs identified system leakage; however, none involved rubber gaskets. The Generic Task Force Report GOR-23-23 appropriately concluded that while rubber gaskets are used in cerisin mechanical systems in both the reactor and auxiliary buildings, there has been no verifiable adverse impact on operation.
l l
1069d - 10/17/86 I
TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.6 (8)
SPECIAL PROGRAM REVISION NUMBER: 0
/
i PAGE 5 0F 9 The economy of using a gasket in a flanged joint results from ,
avoiding the expense of grinding and lapping the joint faces to obtain fluid tight joints. The gasket in a flanged piping joint provides a seal and is not associated with the pressure retaining function of the flanges and bolting. The presence of a deteriorated or imperfectly sealing gasket may risult in a leaking joint but is not considered a failure of the system pressure boundary.
A leaking flanged joint is a plant maintenance item without impact on plant nuclear safety. The failure of a gasket is not a sudden event. The amount of system inventory that would be lost through joint leakage is not sufficient to diminish a safety system's ability to meet its intended purpose.
Leaktight integrity of the ERCW system is assured by periodic pressure tests and inspections required by SQN design criteria No.
SQN-DC-V-7.4, " Essential Raw Cooling Water System (67)." The required tests and inspections are implemented at SQN Plant by preventive maintenance program procedures PM-168'6-067 and PM-1685-067 for units 1 and 2 respectively.
1069d - 10/17/86
TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.6 (B)
SPECIAL PROGRAM REVISION NUMBER: 0
/
\ PAGE 6 0F 9 Section III of the ASME B&PV code requires only that gaskets be made of materials that are not injuriously affected by the fluid in the pipe or by temperature within the piping design temperature range. In accordance with the code, if the expected normal service pressure does not exceed 720 psi or the temperature does not exceed 750*F (which is the case for all SQN systems wher'e rubber gaskets are used), the selection of a suitable gasket material is the owner's responsibility and not an issue.
Rubber gasket material (1/16 inch thick red rubber, Garlock ring type #122) is specified on relevant SQN design drawings, as reported in App. A, 5.a. The Garlock #122 ring type rubber gasket is manufactured to meet the requirements of ASTM D 1330. This gasket material is typically used in low temperature / pressure water services. All rubber gaskets now used in both safety and non-safety related systems at SQN Plant are procured to ASTM Standard Specification for Rubber-Sheet Gaskets, D1330.
Findings:
- a. The rubber gasket material specified and installed in certain systems at SQN plant complies with Section III of the ASME B&PV code for class 2 and 3 piping systems.
1069d - 10/17/86
TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.6 (B)
SPECIAL PROGRAM REVISION NUMBER: 0 t
PAGE 7 0F 9
- b. The rubber gasket material installed at SQN plant is typical of the best industrial standard rubber gasket material commercially available.
- c. There is no evidence of rubber gasket failure (premature or otherwise) at SQN Plant.
- d. Deterioration of gasket material does not present a safety issue.
Conclusions:
- a. The concern is not valid for the rubber gasket material used at SQN Plant.
- b. There is no adverse impact on plant nuclear safety as a consequence of the rubber gasket material used at SQN Plant.
1069d - 10/17/86
TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.6 (B)
SPECIAL PROGRAM REVISION NUMBER: 0
/
PAGE 8 0F 9 APPENDIX A
- 5. DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
- a. TVA Generic Concern Task Force Report, GOR-23-23, Rev.1, (05/19/86)
- b. TVA Design Criteria SQN-DC-V-7.4, Essential Raw Cooling Water System (67) ,
- c. Drawings 47BM450,17BM302, and 47BM915; Bill of Materials for ERCW and High Pressure Fire Protection (HPFP) systems
- d. ASTM Standard Specification for Rubber-Sheet Gaskets, D 1330
- e. ASME Code,Section III, Division 1, Subsection NC-Class 2 Components, and Subsection ND-Class 3 Components
- 6. WHAT REGULATIONS. LICENSING COMMITMENTS. DESIGN REQUIREMENTS. OR OTHER APPLY OR CONTROL IN THIS AREA?
a Design Criteria }0N-DC-V-30, " Classification of Piping, 25(PIV-E*d -V 3* 0 Valves, and Vessels" Pumps,
- b. ANSI-B16.21-1978, " Nonmetallic Flat Gaskets for Pipe and Flanges"
- c. Drawings 47BM450,17BM302, and 47BM915; Bill of Materials for ERCW and HPFPS
- d. ASTM Standard Specification for Rubber-Sheet Gaskets, D 1330
- e. ASME Code,Section III, Divisinn 1, Subsection NC-Class 2 Components, and Subsection ND-Class 3 Components e
1069d - 10/17/86
TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.6 (B)
SPECIAL PROGRAM REVISION NUMBER: 0 j
[ PAGE 9 0F 9
\ l
- 7. REQUESTS FOR INFORMATION. MEETINGS. TELEPHONE CALLS. AND OTHER DISCUSSIONS RELATED TO ELEMENT:
- a. RFI #SQN-506
- b. Telephone calls from S. Presser, Bechtel, to J. Casey, TVA, SQN, and H. Mahlman, TVA, Knoxville, (09/15/86 and 09/24/86)
- c. Telephone call from S. Presser, Bechtel, to K. Lewis, TVA, WBN, and H. Mahlman, TVA, Knoxville, (09/15/86)
- d. Telephone call from S. Presser, Bechtel, to T. E. Cook, Garlock Area Representative, (09/24/86)
- e. Response to RFI SQN-508, TVA Transmittal No. 100(4) 1069d - 10/17/86
ENCLOSURE 2 l
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