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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
[Table view] |
Text
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TVA EMPLOYEE CONCERNS REPORT NUMBER: WP-17 SPECIAL PROGRAM REPORT TYPE: Welding Project REVISION NUMBER: 0 TITLE: Vendor Weld Quality REASON FOR REVISION: N/A SWEC
SUMMARY
STATEMENT: N/A PREPARATION PREPARED BY:
Original Signed By J. E. Rose 04-07-86 SIGNATURE DATE REVIEWS PEER:
Original Signed By R. M. Bateman 04-07-86 SIGNATURE DATE TAS: TECHNICAL REVIEW ON Y
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SIGNATURE DATE CONCURRENCES Original Signed By CEG-H: L. E. Martin 09-03-86 SIGNATURE DATE SRP: c 44. I //-2d -86 SIGNATURES DATE APPROVED BY-hAfA l
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$'h N/A ECSP MANMiER DATE MANAGER OF NUCLEAR POWER DATE CONCURRENCE (FINAL REPORT ONLY)
- SRP Secretary's signature denotes SRP concurrences are in files.
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}iELDING PROJECT GENERIC EMPLOYEE CONCERN s
EVALUATION REPORT REPORT NUMBER: WP-17-SON. R0 DATE 04-08-86
SUBJECT:
VENDOR WELD OUALITY CONCERNS CONSIDERED: IN-85-127-001
- IN-85-007-003 IN-85-657-001
- SPECIFICALLY INVESTIGATED BY NSRS IN REPORT I-85-753-WBN 00, WP PREPARED BY Original Signed by J. E. Rose 4/7/86 ,
OC, WP REVIEWED BY Original Signed by R. Bateman 4/7/86 ,
QA, up REVIEWED BY Original Signed by R. P. Lynskey 4/7/86 ,
REVIEWED
[ 2 , CEG-H, WELDING 77
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00360 i
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GENERIC EMPLOYEE CONCERN.
SUMMARY
SHEET Report Number: WP-17-SON. RO Report
Title:
VENDOR WELD QUALITY I. CONCERNS CONSIDERED: IN-85-127-001
- IN-85-007-003 IN-85-657-001
- Specifically investigated By NSRS in Report I-85-753-WBN Attachment 2)
II. ISSUES INVOLVED
- 1. ~ Vendor welds are not of the same quality as TVA field welds.
- 2. Vendor welds are not inspected in the field.
III. STATEMENT OF CONCERN / ISSUE VALIDITY
,. Validity: Y X ,N , Substantiated: Y X ,N .
IV. EFFECT ON HARDWARE AND/OR PROGRAM l None i
V. JUSTIFICATION Vendor welds and equipment are inspected against contract requirements.
VI . . RECOMMENDATION AND/OR CORRECTIVE ACTION NEEDED None l
VII. REINSPECTION NEEDED: Y ,N I .
VIII. ISSUE CLOSURE By this report.
IX. ATTACHMENT
- 1. Text of Employee Concerns
- 2. NSRS Investigation Report - I-85-753-WBN
}
Page 1 of 1 00360
Is GENERIC EMPLOYEE CONCERN Report Number: WP-17-SON. R0 Report
Title:
VENDOR WELD OUALITY I. SCOPE OF EVALUATION This engineering analysis covers the following WBN concerns determined to have possible generic implications at SQN:
IN-85-127-001
- IN-85-007-003 IN-85-657-001
- Specifically investigated By NSRS in Report I-85-753-WBN (Attachment 2)
II. ISSUES ADDRESSED BY CONCERNS Each concern was analyzed to determine the issues voiced by the concerned individuals. These issues are as follows:
- 1. Vendor welds are not of the same quality as TVA field welds.
_; 2. Vendor welds are not inspected in the field.
i III. CONCERN VALIDITY OR SUBSTANTIATION NSRS has investigated and substantiated the general condition of vendor welds as they relate to WBN in Report I-85-753-WBN for Employee Concern IN-85-007. The conclusions of this report which are-WBN-specific are also applicable to SQN. These conclusions are as follows:
(
l l 1. The employee concerns are substantiated as they relate to the observed general condition of vendor welds.
- 2. A similar problem had been identified, reported, documented, and dispositioned in accordance with applicable QA program requirements at WBN.
Due to the general nature of the concerns and issues voiced by these concerns, the conclusions are applicable to vendor welds in general.
Page 1 of 2 i
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l 00360 l
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WP-17-SQN, R0 TVA invokes technical and quality assurance requirements in contracts for vendor-supplied materials and equipment by reference to industry codes. These contracts are reviewed to assure that required technical standards and quality assurance requirements are included. Many times the governing. codes and standards that control vendor weld quality have requirements which are less stringent than the TVI. construction standards in Process Specifications G-29M or G-29C which contain welding quality requirements of ASME, ANSI, and AWS. Vendor-supplied materials and equipment may be source inspected by TVA prior to shipment or shipped without TVA inspection fecm vendor facilities. This program is outlined in the OC and NO QA Programs, as applicable. When source inspection is required, it is performed by TVA Vendor Surveillance ,
personnel to determine compliance with code, standard, and contract requirements. Items not required to be source inspected are inspected when they are received at the site to determine compliance with code, standard, and contract requirements.
In summary, both the field and vendor welds are required to meet applicable code requirements. TVA field welds are visually inspected to a more conservative interpretation of code requirements relating to visual weld attributes. The final appearance of TVA field welds is generally superior to vendor-supplied equipment.
The issue concerning vendor welds not being. inspected is not substantiated due to the vendor surveillance program and receipt inspection programs.
The effect on the hardware is of no consequence because the materials and equipment are inspected in acccedance with contract requirements.
Based.on the foregoing analysis, the issues considered in these concerns are closed.
3 Page 2 of 2 l 00360
Attrchment 1 03/24/86 (EMPLOYEE CONCERNS) PAGE 1 of 1 11:40:58 .
LOC STATUS RESP -OTC- PPP CFR TC ------CONCERN-------
IN.SP PROELEf1 3-- ------ ---- ----- --- --- ---- --
. ID
/ 366 ,EGEG G.O NR IN-85'-127-OO1 -U Ct1UW -
YWORDS: UENDOR CRITERIA DIFFERENCES X: W Y: C 2: N INCCNSISTENCY IN CRITERIA USED FOR WELD INSPECTIOtJ OF EERSEN-PATERSCN Arid TVA l HANGER WELDS. E.P. WELDS LODK EAD. WHILE BETTER LOOKItJG TUA WELDS ARE REJECTED FOR COST 1 ETIC REASONS. HANGER FAE SHOP. LOCATED AT SOUTH EAST CORNER OF TUREINE ELDG., HAS BINS FULL OF E.P. HANGER PARTS WHICH EXEt1PLIFIES THIS CONCERil. CI DOES EXISTS. NOT Xh0U SPECIFIC HANGER N'S OF AREAS IN THE PLANT UHERE THIS CONDITI0fl TECHNICAL COT 1MENTARY:
' ISSUE LOC CONSIDERED: UENDOR WELDS ARE NOT OF THE sat 1E QUALITY AS TVA FIELD WELDS.
STATUS RESP -OIC- PPP CFR INSP TC ------CONCERN------- PROELEM ID 753 NSRS JO SR IN-BS-007-DO3 WCMUW XEYWORDS: UENDOR UELD QUALITY NONSPECIFIC .X: W Y: C
[ 2: N
-GENERAL LOOK OVER UFNDOR WELCS SHOULD BE PERFORMED. UENDOR WELDS ARE NOT IN-SPECTED AT WENP 1 OR 2. THEY ARE EASILY DISTINGUISHABLE FROT1 FIELD WELES SECAUSE OF THE EnD OUALITY OF THE UENDOR WELDS. UENDOR WELDS WOULO NOT PASS THE JAME ACCEPTANCE NSF RPTM I-85-753-WEN)
[(NICAL COT 1MENTARY:
ISSUE CONSIDERED: - 1. UENDOR UELUS ARE NOT INSPECTED Itl THE FIELD.
LOC
- 2. UENDOR WELDS ARE NOT OF THE sat 1E QUALITY AS TUA FIELD WELDS STATUS RESP -OTC- PPP CFR INSP TC ------CONCERN------- PROELEM ID JO NR IN-85-GS7-OO1 WCMUW KEYWORDS: UENDOR CRITERIA DIFFERENCES X: W Y: C Z: N
' SEVERAL UENDOR WELDS HAVE BEEN INSTALLED IN THE VARICUS LOCATIONS OF POWER HOUSE UNIT 1 a 2 WHICH DID NOT MEET THE ACCEPTANCE CRITERIA CG-29 T1) OF TVA WELDING SPECIFICATIONS. AS AN EXAMPLE: HEATER C1 LOCATED AT T15 & G LINE ELEU.708*-O" TUREItJE BUILDING. NAr1E OF UENDOR: YUSA, HEAT TRANSFER CORP. COtJSTRUCTIDN DEPT CONCERN. CI HAS NO ADDITIONAL INFORMATION.
TECHNICAL cot 1t1ENTARY:
ISSUE CONSIDERED: UErlDDR WELDS ARE NOT OF THE SAME QUALITY AS TVA WELDS.
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TENNESSEE VALLEY AUTHOR,lTY ..
73 ,
Craven Crowell, Director of Information, E12A4 C-K Attachment 2 '
FRO 31 - : K. W. Whitt, Director of Nuclear Safety Review Staff, E3A8 C-KPage 1 of 8 DATE :
' J A N 141986 senJECT: REPORTS SUBMITTAL FOR " NUCLEAR SAFETY UPDATE" Attached is one copy'each of the fol awing final reports of investiga-tion or evaluation of employee concerns for your use, summarization, and publication in Nuclear Safety Update. All have been reviewed and accepted by NSRS. ,
Investigation Investigation Concern No. Performed by Concern No. Performed by IN'-85-001-005 NSRS IN-85-007-003 NSRS '
IN-85-278-002 NSRS
.) IN-85-955-001 NSRS IN-86-064-001 NSRS IN-86-200-003 NSRS IN-86-221-001 NSRS
IN-86-305-002 NSRS ' #
Pil-85-038-001 NSRS
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- O
't K. W. Whitt Attachments
' Please acknowledge receipt by signing, copying, and returning this transmittal form to J. T. Huffstetler at E3B37 C-K.
cc: R. P. Denise, LP6N35A-C #'"
D. R. Nichols, E10A14 C-K jf
E. K. S11ger, LP6N48A-C .y .,,'~'
LK M