Rev 0 to Piping & Valve Design:Carbon Steel Vs Stainless Steel Drainage Piping, TVA Employee Concerns Special Program Element ReptML20236E618 |
Person / Time |
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Site: |
Sequoyah |
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Issue date: |
01/05/1987 |
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From: |
Griffith J TENNESSEE VALLEY AUTHORITY |
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To: |
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Shared Package |
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ML20236E191 |
List: |
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References |
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232.2(B), 232.2(B)-R, 232.2(B)-R00, NUDOCS 8710290286 |
Download: ML20236E618 (8) |
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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. 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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
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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
_ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ . _ __
TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.2(B) I SPECIAL PROGRAM l l
i REPORT TYPE: SEQUOYAH ELEMENT REVISION NUMBER: 0 S
TITLE: PIPING AND VALVE DESIGN Carbon Steel vs. Stainless Steel Drainage Piping PAGE 1 0F 8 REASON FOR REVISION:
i l
I l
PREPARATION PREPARED BY:
i /2 -3/-86 DATE g yGNATURE REVIEWS RE C0091ITT E:
/Af 1 Th l2 - $ l' b5, i
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f v 51GNATURE DATE TAS: ,
SIGNATURE DATE CONCURRENCES 8710290286 071023 -
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/-[f7 PDR ADOCK 05000327 P PDR CEG-H: dYnd IT'77 SRP:
DATE SIGNATURE DATE SIGNATURE APPROVED BY:
ECSP MANAGER DATE MANAGER OF NUCLEAR POWER DATE CONCURRENCE (FINAL REPORT ONLY)
. x
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a
'TVAEMPLOYEE'CONCERNSL REPORT' NUMBER: 232. 2( B ). - 1 SPECIAL PROGRAM .j REVISION NtMBER: 0 ;
b ~
PAGEl2 0F 8 j l
- 1. . , CHARACTERIZATION OF ISSUES:
LConcerns: Issues: j IN-85-021 -006' _
- a. The reactor building floor drain-
"The floor drain piping is- piping design drawings may have carbon steel and:should be required the use of carbon steel .,
instead of stainless . steel piping a stainless stcel in reactor
~ building 1 ant 2." material.
- XX-85-127-002 . .
- b. Carbon steel pipe may have been "Sequoyah - floor drain piping installed in the reactor building
~
is carbon steel and it should be floor drain system instead of
. stainless steel . . Reactor. Bldg." stainless . steel as required by the design drawings. i i
- 2. HAVE ISSUES BEEN IDENTIFIED IN ANOTilER SYSTEMATIC ANALYSIS? YES X NO Identified by TVA Nuclear Safety Review Staff (NSRS) ]
Date March 6,1986 -
Documentation Identifiers:
NSRS Investigation Report No. I-85-921-SQN, Reactor Building Raceway Drains, (03/06/86)
- 3. DOCUMENT NOS., TAG NOS., LOCATIONS OR OTHER SPECIFIC DESCRIPTIVE IDENTIFICATIONS STATED IN ELEMENT:
Sequoyah Reactor Buildings 1 and 2 floor drain piping.
- 4. INTERVIEW FILES REVIEWED:
Files IN-85-021 and XX-85-127 reviewed 06/18/86, contained only K-foms.
(
L i
L 06940 - December 31, 1986 sa-a- - - - - , . _ _ ,
y
- q c
2
-fe 232.2(B)
~
^
TVk EMPLOYEE CONCERNS REPORT NUMBER':
SPECIAL PROGRAM REVISION NtMBER:. 0
'PAGE 3 0F"8 d
- 5. 'DOCIEENTS REVIEWED RELATED TO THE' ELEMENT: _
~
See Appendix A.
6 .- WHAT. REGULATIONS, LICENSING COWilTMENTS,, DESIGN REQUIREMENTS OR OTHER
, APPLY OR CONTROL IN THIS AREA?
4 See Appendix A..
.= i
~
- 7. LIST REQUESTS-FOR INFORMATION, MEETINGS, TELEPHONE CALLS, AND OTHER DISCUSSIONS RELATED TO ELEMENT.
See Appendix A. ,
P.- EVALUATION PROCESS:-
- a. Reviewed SQN FSAR Section 9.3.3 for. design. bases. and-
~ description of reactor building floor drain system and
- Section 3.2.2.6 for system safety classification.
- b. Rev'ewed SQN reactor building drainage flow diagram, piping installation drawings, and bills of material listed in App.
A, 5 d.
- c. Reviewed.SQN design criteria manual and TVA Mechanical Design Guide DG-M8.1.6, Nonradioactive Building Drainage Requirements," for basic design criteria applicable to the i reactor building drainage system.
- d. Reviewed TVA Nuclear Safety Review. Staff (NSRS) Investigation
~
Report No. I-85-921 -SQN.
e.. Reviewed TVA purchase requisitions for supply of reactor building drainage system materials specified on the piping drawings and relevant bills of material.
- f. Sumarized information developed from document reviews and i evaluated the significance and validity of issues identified in the concerns.
L l
lL i
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E 0694D - December 31, 1986
- j
e
, TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.2(B).
h SPECIAL~ PROGRAM REVISION NtMBER: 0'
~
PAGE 4 0F.8-
- 9. . DISCUSSION, FINDINGS, AND CONCLUSIONS:
Chronology:
~
12/09/86: Concerns documented on Employee Concern Assignment Request forms by Employee Response Team (ERT) 12/12/85: TVA Nuclear Safety Review Staff (NSRS) initiated investigation of perceived problem identified in concerns 03/06/86:- NSRS Investigation Report No. I-85-921-SQN issued with a Priority 2 (P2) recommendation 05/13/86: SQN plant staff responded to the NSRS recommendation Discussion:
The employee. concerns received by the Quality Technology Company 1 (QTC)/ Employee Response Team (ERT) pertain to the suitability of carbon steel piping material used in the SQN Reactor Building floor -
drain- system. The concerned individuals stated that stainless steel piping should have been used. It was unclear from their
' statement whether the perceived prebha was considered one of construction or design. Therefore, the NSRS. investigation and this ,
evaluation of the concern have addressed'both aspects.
The reactor building embedded floor drain piping is TVA nonnuclear safety class L as noted on SQN basic design drawing.47W851-1 R17,
" Mechanical Flow Diagram, Floor and' Equipment' Drains, Reactor Building Units 1 and 2." Sequoyah Nuclear Plant FSAR Table 3.2.2-3 identifies no specific code jurisdiction (" unclassified") ;
applicable to TVA class L piping system for field fabrication, examination, and testing. The piping design complies with ANSI B31.1-1967, " Power Piping Code" and, since the reactor building is a Seismic Category I structure, the nonnuclear safety piping located inside is seismically supported as necessary to prevent unacceptable interactions with safety-related components.
The SQN FSAR Section 9.3.3 design bases identify the reactor building floor drain system as a portion of an independent chemical waste collection and disposal system which prevents uncontrolled releases of hazardous materials to the environment. The floor drain piping material selection is based on the fluid to be handled being water and air as identified in FSAR Table 9.3.3. The TVA engineering practice, as documented in Division of Engineering Design, Mechanical Design Guide, DG-M8.1.6, " Nonradioactive j Building Drainage Requirements," is to use carbon steel pipe and '
fittings with cast iron drainage fittings unless there are special I
l 06940 - December 31, 1986 I i
____1__.__ _ l
.- I TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.2(B)
SPECIAL PROGRAM REVISION NUMBER: 0 l PAGE 5 0F 8 l 1
considerations. In the reactor building application the embedded
' floor drain piping has been specified on SQN drawings 47W476-1 and ,
2 as carbon steel in the annulus area (outside of containment)'and j stainless steel inside containment below elevation 738.0 ft.
Because of its superior corrosion resistance and ease of decontamination, stainless steel is used for embedded floor drainage piping inside containment in locations where there is a possibility of handling radioactive fluids. (SQN Element Report -
229.2(B) addresses a related issue pertaining to the potential for 2 spread of radioactive contamination through the reactor building floor drain system.)
The TVA Nuclear Safety Review Staff (NSRS) conducted an investigation to evaluate the validity of the concern by identifying the reactor building floor drain piping material requirements and by inspection of the installation where accessible !
~
for compliance. The NSRS investigation reviewed design drawings and bills of material to identify the reactor building drain j arrangements and material requirements.. Available relevant l installation and inspection records were also reviewed and SQN site i personnel familiar with the installation. procedures were interviewed. The NSRS investigators performed visual inspection <
and magnetic testing of the accessible embedded floor drain pipe ends in the containment raceway of both Units 1 and 2. The NSRS investigation verified the use of stainless steel embedded floor !
drainage piping in accessible containment raceway areas as called !
for on the design drawings and found no evidence that carbon steel pipe was used in these areas. The NSRS Investigation Report No.
I-85-921-SQN concluded the concern was not substantiated.
In the course of their verification inspections the NSRS ,
investigators discovered that nonstainless steel material had been used for floor drain grates where stainless steel was specified on the design drawings. The NSRS investigation report recommends correcting the condition of using nonstainless grating material ,
where stainless grates are specified on the design drawings. The )
SQN plant staff response ( App. A, 5.g) to the NSRS report recommendation committed to replacing the noncomplying grates with l stainless steel grates.
Findings:
- a. Both carbon steel and stainless steel materials have appropriate applications in the reactor building floor i drainage piping systems, and both have been used in the design and installation.
g 4
1 -- i
m.
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. , . t
& , TVA EMPLOYEE CONCERNS -REPORT NUMBER:- 232.2(B).
.a :SPECIAL PROGRAM
^ REVISION NUMBER:: 0 7
PAGE 6 0F 8-
'b.. The. superior serviceability of stainless steel piping'is; 3
/ justified in those reactor building drainage systems where-
- there is. a potential for handling radioactive.or borated
' water, and stainless steel material has been specified in 'the
- -design for.use in those systems.
c.. Stainless steel piping has been installed in the reactor -
building drainage systems where required by tho' design.
u However, some installed floor' drain gratings have been identified that are not in. compliance with the installation drawings. This discrepancy is being corrected by TVA.
- d. The-reactor building embedded drainage piping material is not a nuclear ' safety . issue.
Concl usion:--
'Neither concern is substantiated, and both issues identified are g, invalid.
- 10. CORRECTIVE ACTION:-
'No corrective action is required.
i' 1
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0694D - December 31, 1986 i L--I____
' l
.. 1 1
TVA EMPLOYEE CONCERNS- REPORT NUMBER: 232.2(B) l SPECIAL PROGRAM j REVISION NUMBER: 0 )
PAGE 7 0F 8 APPENDIX A ,
- 5. DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
- a. TVA, Sequoyah Nuclear Plant, Final Safety Analysis Report (FSAR), ( Anendment 3)
- b. TVA, Sequoyah Nuclear Plant, Design Criteria Manual
- c. TVA, Mechanical Design Guide DG-M8.1.6, " Nonradioactive Building Drainage Requirements," (08/17/82)
- d. TVA, Sequoyah Nuclear Plant Drawings 47W851-1 R17 Mechanical Flow Diagram, Reactor Building Floor and Equipment Drains 47W476-1 R9 - Reactor Building Annulus Floor Drains and Embedded Piping 47W476-2 R10 Reactor Building Containment Drains and Embedded Piping 47BM476 R1 Piping Bill of Material, Reactor Building Annulus Floor Drains and Emb. Piping 47BM476-1 R2 Piping Bill of Material, Reactor Building Containment Drains and Emb. Piping
- e. TVA NSRS Investigation Report No. 1-85-921-SQN, " Reactor Building Raceway Drains," (03/06/86) l
- f. TVA memo from K. W. Whitt to H. L. Abercrombie, " Nuclear Safety Review Staff Investigation Report Transmittal," ,
(03/07/86) !
l
- g. TVA memo from H. L. Abercrombie to R. F. Denise, "NSRS Investigation Report No. I-85-921-SQN," (05/13/86)
- h. TVA Purchase Requisition No. 92621 (03/16/70) and No. 92638 (08/05/70) for floor drain materials 0694D - December 31, 1986
Y' ll#
- 4.40- TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.2(B)-
4" . SPECIAL PROGRAM I' REVISION NUMBER: 0-PAGE 8 0F 8 3
J l
L . APPENDIX A (cont'd)
' 6. ' WHAT REGULATIONS, LICENSING COMMITMENTS, DESIGN REQUIREMENTS OR OTHER APPLY OR CONTROL IN THIS AREA? l a.- 10CFR Part 50, Appendix.B, Criterion VIII, " Identification
-and Control of Materials, Parts,' and Components" ib. SQN FSAR Sections 3.1. 2.1, 3. 2. 2. 6 and , 9. 3. 3
=
- 7. LIST REQUESTS FOR-INFORMATION, MEETINGS,- TELEPHONE CALLS, AND OTHER DISCUSSIONS RELATED TO ELEMENT.
- a. RFI SON-508 (08/25/86)
- b. RFI SON-736 (11/24/86)
- c. TVA SQN Transmittal:#100 (08/27/86)
.d. TVA SON Transmittal #153 (11/17/86)
- e. .TVA SON Transmittal- #159 (11/25/86)
'i f
I 0694D - December 31,.1986 AM ____ .________ _ _ . _ _ _ . _ _ - _ . . _ _ _ . _ _ I