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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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{{#Wiki_filter:-- _ _ - .
e, 2TVA'ENPLOYEE CONCERNS REPORT NUMBER: . 215.10(8)
SPECIAL PROGRAM
[^ REPORTcTYPE:. SEQUOYAH ELEMENT REVISION NUM8ER: 0 a
TITLE:- CIVIL / STRUCTURAL DESIGN-
'Feedwater Heater Monorail Hanger Design PAGE 1 0F 7 ,
REASON FOR REVISION:-
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ECSP MANAGER DATE MANAGER Of NUCLEAR POWER DATE l CONCt'RRENCE (FINAL REPORT ONLY)
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; TVA EMPLOYEE CONCERNS REPORT NUM8ER: 215.10(B)
SPECIAL PROGRAM
[! REVISION NUMBER: 0 l- ,
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PAGE 2 0F 7-p
_1 . - CHARACTERIZATION OF ISSUES:
Concern: s 1Ls_ue:
LDA-85-001 .
Tae structural integrity of hangers
" Structural integrity of the for the feedwater heater monorails is feedwater heater. monorail- questionable.
hangers."
- 2. HAVE ISSUES BEEN IDENTIFIED IN ANOTHER SYSTEMATIC ANALYSIS 7_ YES X NO Identified by TVA and Impe11 Corporation Date 08/13/85 and 08/16/85 Documentation Identifiers:
TVA memo f rom V. R. 'Defenderfer to SQN Project Files,
[B25,850813 019], "SQN - Design Review of Turbine Building Feedwater Heater Replacement "
Impe11 Corporation letter from S. F. Strang to R. O. Barnett (Impell/TVA-85-594), " Personal Service Contract No.*TV-65378A, SQN-Design Review of Honorail Structure "
- 3. DOCUMENT N05.. TAG NOS. LOCATIONS OR OTHER SPECIFIC DESCRIPTIVE
_ IDENTIFICATIONS STATED IN ELEMENT:
-The concern addressed hangers for the feedwater heater menorails which are located in the turbine building.
{
- 4. INTERVIEW FILES REVIEWED: f The expurgated interview file for concern LDA-85-001 was reviewed.
The file contains the K-form, SQN plant operation impact evaluation, and the generic applicability sheets. The file also has a hand written statement documenting a meeting of 08/06/85 l between the two concerned employees and the cognizant design engineer. In the meeting, the engineer explained the design approach and the details of the monorail hangers. The statement concluded that the two employees expressed their satisfaction with ,
the explanation and that the concern could be considered closed i (App. A, 7.c), 3 l
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i TVA EMPLOYEE CONCERNS REPORT NUM8ER: 215.10(B)
SPECIAL PROGRAM REVISION IRMBER: 0 )
i FAGE 3'0F 7 s .yf/
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- 5. DOCUMENTS RrVIEWED RELATED TO THE ELEMENT:
See Appendix A. l
- 6. WHAT REGULATI0t:S. LICENSING COMITMENTS. DESIGN REQUIREMENTS OR OTHER APPLY OR CONTROL IN THIS AREA?
See' Appendix A.
a
- 7. LIST RE00ESTS FOR INFORMATION. MEETINES. TELEPHONE CALLS. AND OTHER DISCUSSIONS RELATED TO ELEMENT.
See_ Appendix A.
i
- 8. EVALUATION PROCESS:
- a. Obtained and reviewed copies of monorail drawings and calculations.
- b. Performed a plant walkdown reviewing the subject components,
- c. Obtained reports of other independent structural reviews.
- d. Determined that monorails weie load-tested and obtained related documentation.
- 9. DISCUSSION. FINDINGS. AND CONCLUSIONS:
Chronolo_gy The concern was expressed orally: On or before 08/05/85 The concerned employees met with the design engineer: 08/06/85 j TVA independent review was completed: 08/13/85 t Impe11 review was completed: 08/16/85 s Monorail load-test was performed: Od/25/85 K-form was dated: 06/17/86 i
04790 - 12/01/86
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TVA EMPLOYEE CONCERNS REPORT NUMBER: 215.10(B)
SPECIAL PROGRAM c REVISION NUMBER: O . -
A q '. , . PAGE 4 0F 7 m
j Discussion: ,
TVA decided to replace a total of 12 out of 42 feedwater heater's in 1 late 1984 on both of the SQN units because of mechanical problems encountered. The feedwater heater replacement involved moving large, heavy (89,000 lb) equipment over long distances through ;
confined spaces. The replacement, therefore, required additional n.onorails at various locations in the turbine building to transport the heaters. 3 l
TheSQNturbinebuildingisnotaCatTgoryIstructure,and,in i accordance with TVA Design Standard C1.2 2, the subject monorail !
girders, hangers, and braces are non-Category I nonsafety-related !
components whose failure will not jeopardize the function of any Category I structure, system, or component ( App. A. 6.b). The governing design document for these steel components is AISC specification as stated in TVA DS-C1.6.1 ( App. A 6.c). The AISC' specification covers design, f abrication, and erection of structural steel, c The evaluation team reviewed the feedwater heater drawings i furnished by both the original supplier and the new supplier (App. A, 5.d and 5.e) and confirmed that the correct lifting weights were used in the design calculations. The design calculations and drawings were reviewed for assumptions, logic, ,
analysis, code interpretations, member selections, connections, and clarity of presentations (App. A, 5.a, 5.b, and 5.f). The evaluation team found the design documents well organized,
- complete, and meeting the AISC requirements. The monorail beams supporting the trolleys are 24" deep beams and the hangers are l 5" x 3" double angles. The hangers, being tensile members, are expectecly smaller in size than the beams, which are primarily bending members. Nevertheless, the evaluation team determined that the monorail hangers are designed with an adequate margin of -
i safety. The team also performed a field walkdown of the as-built ,
installation including connections (App. A, 7.b). The installation appeared satisfactory.
This replacement operation was also reviewed independently and in detail by a TVA structural engineer in August 1985 because of its q critical nature ( App. A. 5 9). The report, based on the review of engineering design calculations and drawings, stated, "The hoist support system consisting of monorail beams and vertical, lateral, and longitudinal load carrying members was well conceived and designed." ;
Hereover, during the same month,.another design review was performed by Impell Corporation at the request of TVA. Impell also ;
f determined that the monorail structure is adequate and safe, !
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M TVA EMPLOYEE CONCERNS REPORT; NUMBER:i 215.10(8)L SPECIAL. PROGRAM
[ ,
REVISION, NUMBER:1,0 . -
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.provided the monorai's are operated within the limitations
.specified on the design drawings:( App. . A, 5.h).' ~
q Subsequently,Lthe SQN site director requested a monorail load' test prior.to lifting tAe heaters to ascertain the soundness of the.
system design. The test was performed on 08/25/85 and in-accordance with ANSI B30.11-1980 procedure using a concrete beam-
. weighing'125,000 lb (40 percent heavier than.the largest heater).
The. test load was transported by. trolley-for-the full length of the; ,
monorail system. The test was considered successful by visual l
- observations (App A,- Cc).
Following -the test, the feedwater heaters were replaced successfully.
The subject employee concern was reporte'd during erection 'of -the.
system on or before 08/05/85-{ App. A, 7.d), and, apparently, .
because of the relatively slender appearance.of the hangers a supporting the'large monorail beams. < subsequently, as stated in .
Section 4,-the concerned employees: discussed this~ issue with the' i design engineer,: understood the design concepts, and expressed ;
'their satisfaction with the hanger design.
FinAjg:
n ,
The evaluation team found the hangers for' the feedwater heater mviorails.in the turbine building structurally adequate for the ,
rated load.- This was confirmed by other reviews, the load' test,
~
and, ultimately, by the successful heater replacement operation.-. .
Conclusion:
1 The evaluation team concluded that the issue of the. hangers for the feedwater heater inonorails being structurally' inadequate is not valid, and the as-built installation conforms to the AISC and TVA i design requirements.
- 10. CORRECTIVE ACTION:
-No Corrective action is required.
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TVA EMPLOYEE CONCERNS REPORT WUMBER: 215.10(B)
SPECIAL PROGRAM i , REVISION kWM8ER: 0-
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.J [ PAGE 7 0F 7 APPENDIX A (Cont'd) "
- 6. WHAT REGULATIONS. LICENSING COMMITMENTS. DESIGN REQUIREMENTS O'd OTHER APPLY OR CONTROL IN THIS AREA?
- a. American Institute of Steel Construction (AISC), j
" Specification for the Design,. Fabrication, and Erection of Structural Steel for Buildings," effective 11/01/78
- b. TVA Civil Design Standard 05-C1.2.2, " Classification of Structures, Quality Levels of Structural Materials, and Related Quality Assurance Responsibilities of the Design Engineer," (12/12/83) '
- c. TVA Civil Design Standard DS-C1.6.1, R1, " Structural Steel Design Scope," (06/05/81)
- d. TVA Civil Design Guide DG-C1.6.4, " Design of Structural Connections," (05/09/84)
- e. TVA Civil Design Guide DG-C1.6.7, " Design of Structural Steel
. Members (Building, Miscellaneous, and Supplemental Steel),"
(05/09/84) 8
- f. American National Standard ANSI 830.11-1980, " Monorails and. !
Underhung Cranes" i
/. LIST REQUESTS FOR INFORMATION._ MEETINGS.-TELEPHONE CALLS. AND OTHER, DISCUSSIONS RELATED TO ELEMENT.
- a. RFI SQN #539, (08/25/86)
- b. Walkdown in the Sequoyah Turbine Building, by the evaluation team on 09/18/86
- c. Review of ECTG Files, Documentation for Concern LDA-85-001, (10/31/86) .
)
- d. Telephone call from N. Shah, Bechtel, to J. Bajraszewski, TVA,10M 409 (11/17/86) i
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