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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:- - _ - _ _ _ _ _ - _ - _
- *, TVA EMPLOYEE CONCERNS REPORT NUMBER:..,232.8(B) i SPECIAL PROGRAM
. REPORT TYPE: SEQUOYAH ELEMENT REVISION NUMBER: 0
- TITLE: PIPINC~AND VALVE DESIGN 1
Criteria for Minimum Pipe Wall Thickness PAGE 1 0F 7 J I
i REASON FOR REVISION:
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PREPARATION PREPARED BY:
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e TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.8(B)
SPECIAL PROGRAM t REVISION NUMBER: 0 PAGE 2 0F 7
- 1. CHARACTERIZATION OF ISSUES:
Concern: Issue:
IN-85-545-X06 a. The ASME Section III code formula for "12-1/2% was the criteria esta- calculating required minimum wall blished by Engineer Design for thickness of stainles:; steel Class 1 minimum wall thickness since and 2 piping may be less conservative 1978. One engineer was found than the 12-1/2 percent criterion to be using the less stringent established for WBN units 1 and 2 f ormula contained in Code in 1978.
Section NB. The above applies to QA Class 2, and some Class 1, stainless steel pipe in Units 1 & 2."
- 2. HAVE ISSUES BEEN IDENTIFIED IN ANOTHER SYSTEMATIC ANALYSIS? YES N0 X Identified by Not Applicable
() Date Not Applicable Documentation Identifiers:
None.
- 3. DOCUMENT NOS., TAG NOS., LOCATIONS OR OTHER SPECIFIC DESCRIPTIVE IDENTIFICATIONS STATED IN ELEMENT:
The concern identifies the Division of Engineering Design and the ASME B&PV Code, Section III, Subsection NB.
- 4. INTERVIEW FILES REVIEWED:
File IN-85-545 reviewed on October 8, 1986, contained only the K-form.
t' 0443D(12/03/86)
1, TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.8(B)
]
SPECIAL PROGRAM L REVISION NUMBER: 0 !
PAGE 3 0F 7
)
- 5. DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
See Appendix A.
- 6. WHAT REGULATIONS, LICENSING COMMITMENTS, DESIGN REQUIREMENTS, OR OTHER APPLY OR CONTROL IN THIS AREA?
See Appendix A.
- 7. LIST RE0UESTS FOR INFORMATION, MEETINGS, TELEPHONE CALLS, AND OTHER DISCUSSIONS RELATED TO ELEMENT.
See Appendix A.
- 8. EVALUATION PROCESS:.
- a. Reviewed applicable TVA Division of Engineering design criteria-i establishcu for WBN plant and SQN plant ASME Section III Class 1 l and Class 2 stainless steel piping.
- b. Reviewed applicable ASME B&PV Code, Section III subs =tions for minimum pipe wall thickness calculation requirements,
- c. Reviewed SQN FSAR sections pertaining to piping classifications and design.
I
- d. Reviewed typical SQN pipe wall thickness design calculation to verify conformance with code methodology.
- 9. DISCUSSION, FINDINGS, AND CONCLUSIONS: l Discussion:
As stated, the concern appears related to the manufacturing tolerance allowed by ASTM Standard Specification A530 (ASME SA-530) for seamless and welded pipe purchased by schedule number or nominal wall thickness under several ASTM pipe product specifications. The ASTM standard stipulates the minimum actual wall thickness of seamless or welded pipe shall not be more than l 0443D (12/03/86) 1 m_____
,?l.
TVA EMPLOYEE CONCERNS REPORT NUMBERi 232.8(B)
.SPECIAL PROGRAM ,l W REVISION NUMBER: 0 PAGE 4 0F 7' 1
.12.5 percent under the nominal wall.thicknessLspecified. in the
-procurement document. This tolerance-is a maximum.and provides one' 1 acceptance' criterion for receiving inspection of commercially available seamless and welded pipe.
The minimum reauired pipe wall thickness is-determined by a prescribed equation in the appropriate piping design code based on the fluid. system' parameters. These design parameters include internal pressure, pipe diameter, and maximum allowable stress for. 1 the selected material at the design temperature. -After the minimum required. pipe wall thickness is determined by the design code i equation, the next heavier commercial wall thickness,is selected I taking into account the manufacturing tolerance allowed in the purchase specification. Thus the piping installed in the plant is assured of having an actual (manufactured) minimum wall thickness equal to or greater than the recuired (designed) minimum wall 1
-thickness.
In certain situa'tions where piping has been procured as a bulk commodity; it could be necessary for an engineer to determine the e adequacy of actual minimum pipe wall thickness available~by .
.) calculating the minimum required wall thickness using the design
. code' equation and the system design parameters for. comparison.
-Typical of such situations would be system modifications or ';
-additions and justification for using pipe with an actual wall 4 thickness less than the minimu.m allowed by the ASTM standard.
l Since the. concern was expressed at Watts Bar, a review was conducted' of the WBN plant design criteria document WB-DC-40-36,
" Classification of Piping, Pumps, Valves, and Vessels," Rev. O, 02/11/75, and Table 3.2-4 of the WBN FSAR. This revealed that WBN 4 committed to the ASME B&PV Code Section III for safety-related systems piping design. There is no evidence to support the allegation of the concern that TVA Engineering Design established for WBN a' piping design criteria more stringent than the ASME code i for determination of minimum required pipe wall thickness.
The SQN plant FSAR commitment to the ASME B&PV Code, Section III, applies to piping items initially procured after April 2,1973.
Prior to April 2, 1973 SON plant piping was designed to the ANSI B31.1 Power Piping Code. These piping design code constituents are ;
documented in the SON Design Criteria Document SON-DC-V-3.0,
.
- General Design Criteria for the Classification of Piping, Pumps, Valves, and Vessels." Currently ti. SON Engineering Project staff i I
h.
4 0443D (12/03/86) i
'I TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.8(B)
SPECIAL PROGRAM REVI5 ION NUMBER: 0 ,
a PAGE 5 0F 7 i
are preparing verification calculations to docJment the design basis of essential aechanical systems, reliminary versions of typical examples of these verification c.ticulatians were reviewed '
in the course of this investigation and confirm use of appropriate piping design codes identified in the design criteria.
On the basis of regulatory and other appropriate system safety criteria, TVA has systematically classified SON plant equipment for application of the ASME B&PV Code, Section III design rules (for items initially procured after April 2, 1973). Code Subsections ND and NC provide rules for the design of Code Class 1 and 2 items !
(TVA Classes A&B) respectively. Under the Code permitted optional use of Code Classes, items classified as Class 2 (TVA Class B) may i be designed and certified under the rules of Subsection NB. Thus ,
any Code Class 2 pipe wail thickness determinations made under the )'
rules of Code Subsection NB, as is implied in the concern, are acceptable and do not represent a safety issue.
Findinas:
- a. Piping design criteria established by TVA Division of 4 I
Engineering Design has consistently requirea use of Q'" appropriate piping code rules to determine the minimum ,
required pipe wall thickness of piping in safety and l nonsafety class systems.
- b. 12-1/2 percent is the maximum permissible reduction of nominal wall thickness allowed by several ASTM standard !
specifications for furnishing seamless and welded carbon steel and stainless steel piping products. l
- c. The manufacturing tolerance on nominal pipe wall thickness specified for material purchase is not an element in the !
piping code equation for determining minimum required pipe i wall thickness and, thus, has no impact on the design j conservatism. j
Conclusion:
The concern is not valid for the safety class piping systems installed at SQN Plant
- 10. CORRECTIVE ACTION:
No corrective action is required.
h I
0443D(12/03/86)
1 S-. 'TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.8(B)
SPECIAL PROGRAM REVISION NUMBER: 0 PAGE 6 0F 7 APPENDIX A
- 5. DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
- a. TVA Mechanical Design Guide DG-M5.1.3, " Steel Piping Materials, Accessories and System Design Considerations"
- b. SQN Plant Design Criteria SQN-DC-V-3.0, " General Design Criteria for the Classification of Piping, Pumps, Valves and Vessel s"
- c. SQN Final Safety Analysis Reoort, Section 3.0, " Design Criteria - Structures, Components, Equipment and Systems"
- d. Selected Sheets of Piping Bill of Material for SQN Piping Drawing No. 47W450 --Series, " Essential Raw Cooling Water"
- e. ASTM A 312 (ASME SA-312), " Specification for Seamless and Welded Austenitic Stainless Steel Pipe"
- f. ASTM A 530 (ASME SA-530), " Specification for General
.] Requirements for Specialized Carbon and Alloy Steel Pipe"
- g. ASME B&PV Code, Section III, Division 1, Subsection NB -
Class 1 Components; Subsection NC - Class 2 Components; and Subsection ND - Class 3 Components
- h. SQN Plant Pipe Wall Thickness Verification Calculations (Preliminary and Unnumbered) for Auxiliary Control Air and Steam Generator Blowdown Systems
- i. WBN Plant Design Criteria WB-DC-40-36, " Classification of Piping, Pumps, Valves and Vessels" !
- 6. WHAT REGULATIONS, LICENSING COMMITMENTS, DESIGN REQUIREMENTS, OR OTHER ;
APPLY OR CONTROL Ih THIS AREAY !
- a. SQN Final Safety Analysis Report, Section 3.0, " Design Criteria - Structures, Components, Equipment and Systems"
- b. SQN Plant Design Criteria SQN-DC-V-3.0, " General Design Criteria for the Classification of Piping, Pumps, Valves and Vessel s" i ,. c. ASTM A 530 (ASME SA-530), " Specification for General Requirements for Specialized Carbon and Stainless Steel Pipe" 4
0443D (12/03/86) l
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f-a
,. TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.8(B)
SPECIAL PROGRAM REVISION NUMBER: 0 PAGE 7 0F 7 APPENDIX A (Cont'd)
- 7. LIST REQUESTS FOR INFORMATION, MEETINGS, TELEPHONE CALLS, AND OTHER DISCUSSIONS RELATED TO ELEMEN1.
- a. RFI #5QN-562 (9/15/86)
- b. TVA Transmittal #115 (9/19/96) l c. Telecon between Mahlman, TVA, and Griffith, Bechtel, (10/17/86)
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6 04430(12/03/86)
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