ML20216D047
ML20216D047 | |
Person / Time | |
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Site: | Sequoyah |
Issue date: | 12/04/1986 |
From: | TENNESSEE VALLEY AUTHORITY |
To: | |
Shared Package | |
ML20216D020 | List: |
References | |
232.3(B), NUDOCS 8706300435 | |
Download: ML20216D047 (20) | |
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TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.3(B) t SPECIAL PROGRAM REPORT TYPE: SEQUOYAH ELEMENT REVISION NUMBER: 1 TITLE: PIPING AND VALVE DESIGN Improper Piping Insulation Material PAGE 1 0F 11 REASON FOR REVISION:
Rey, 1: Addition of concern No. I-85-106-SON to scope of element and !
incorporation of Senior Review Panel Rev. O conrnents.
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PREPARATION j PREPARED BY: ,
g IGNTURE DATE s REVIEWS
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\2-O-85 DATE S/GNATURE TAS:
SIGNATURE DATE CONCURRENCES CEG-H:
I SIGNATURE DATE SIGNATURE DATE APPROVED BY:
9706300435 8706193 PDR ADOCK 05000327 P PDR.
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TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.3 (B)
SPECIAL PROGRAM REVISION NUMBER: 1
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PAGE 2 0F 11 I
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- 1. CHARACTERIZATION OF ISSUE (S):
Concerns: Issues:
EX-85-089-002 a. The physical durability of the soft "CI'. feels that improper insulation (rock wool) type piping insulation-materials were installed in many material widely used at WBNP and at aspects of WBNP construction. SQNP may not provide as satisfactory CI expressed that most of the a service life as would a ' harder" insulation installed was 'SOF' material. q insulation (' Rock Wool'),
covered by a metal sheath. CI b. The types of nonmetallic thermal ll1]
i stated'that this type of insul- insulation being. installed at SQN.
ation is easily damaged, and is plant on austenitic stainless steel subject to deterioration due to , components in safety-related systems- ,
vibration over long periods of may be of unacceptable quality. j time. CI. expressed that a :
' Harder' type of' insulation I should have been used." 4 I-85-106-SON "The employee was concerned about the quality of nonmetallic thermal insulation being installed on '
austenitic stainless steel safety-.
related. systems. He stated that in past experience at other i nuclear plants the types of insula-tion that TVA is using at Sequoyah would not be acceptable. He stated ;
that he had questioned the use of these types of insulation about two years prior to the plant staff and had been told that everything ,
was okay. He was looking for an independent assessment."
- 2. HAVE ISSUES BEEN IDENTIFIED IN ANOTHER SYSTE'MATIC ANALYSIS? YES X !LO _,_
Identified by: N_uclear Safety Review Staff (NSRS)
Date: 12/27/85 00820 12/04/86
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TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.3 (B)
SPECIAL PROGRAM REVISION NUMBER: 1-PAGE 3 0F 11 Documentation Identifiers:
NSRS Investigation Report No. I-85-106-SON
- 3. DOCUMENT NOS., TAG N05., LOCATIONS OR OTHER SPECIFIC DESCRIPTIVE.
IDENTIFICATIONS STATED IN ELEMENT:
Piping insulation, " rock wool,"' and nonmetallic insulation
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- 4. INTERVIEW. Fli.ES REVIEWED: d j
EX-85-089-002 ' 1 1-85-106-50N Files reviewed.0ctober 8, 1986, contained only K-forms.
- 5. DOCUMENTS REVIEWED RELATED TO THE ELEMENT: 1 1
See Appendix A. .k
- 6. WHAT REGULATIONS, LICENSING COMMITMENTS,' DESIGN REQUIREMENTS OR OTHER APPLY OR CONTROL IN THIS AREA? ,l 1
See Appendix A.
- 7. LIST REQUESTS FOR INFORMATION, MEETINGS, TELEPHONE CALLS, AND .0THER ' j DISCUSSIONS RELATED TO ELEMENT.. 1 See Appendix A.
8.- EVALUATION. PROCESS:
- a. Reviewed TVA Mechanical Design Guide DG-M18.9.1 " Insulation for Piping and Equipment'in: Nuclear Power Plants."
- b. Reviewed TVA Sequoyah Design' Criteria for insulation:
requirements inside and outside containment. l i
- c. Reviewed TVA specifications for Sequoyah insulation supply and installation inside and outside containment.
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TVA' EMPLOYEE CONCERNS REPORT NUMBER: 232.3(B)
SPFCIAL PROGRAM REVISION NUMBER: 1.
PAGE 4 0F 11
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- d. Reviewed manufacturer's product data. sheets for the mineral fiber insulation materials installed at SQN and WBN Plants.
- e. ' Reviewed related ASTM Standards for' mineral fiber insulation materials.
- f. Reviewed TVA Nu' clear Safety Review Staff (NSRS) Investigation Report No.'I-85-106-SQN.
- g. Reviewed TVA SQN Plant Standard Practices and Procedures for controlling the procurement, storage and installation of.,
replacement nonmetallic' thermal insulation on austenitic stainless steel.
- 9. DISCUSSION, FINDINGS, AND CONCLUSIONS:
Discussion:
Issue "a" The first concern questions the durability.of:the soft (rock wool).
piping' insulation installed at WBNP because of its: alleged'
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j susceptibility to damage from abuse'and long-term deterioration.
when exposed to vibration. Based on discussion with'the insulation-contractor, the term "SOF" (as quoted on the K-form) does not..
identify any type or brand name-of insulatio'n used at WBN.
Therefore, it is interpreted to mean " Soft."
Rock wool is one of several mineral substances used in t' he' manuf acture of the fibrous type of mass. insulation. " Mineral-Fiber" is the ASTM Standard generic term'for ~ insulation' material'.
composed principally of fibers manufactured from molten mineral substances such as rock, slag, or; glass, with or.without.. binders.
The TVA Insulation Design Guide. (App. A, 5.a)iprovides general and specific requirementsp standards,L and: application' guidelines for.
various types of insulation to be used in nuclear power plants 1 ,
including all metal reflective types' for piping'and equipment; inside containment and massstypes for other piping, equipment"an'd:
ducts. The TVA insulation. specificati.ons-( App. A,15.dLand 5.'e) .,
' provide. specific requirements for the procurement and installation -
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of piping-insulation at WBN and'SQN Plants..
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.- l TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.3 (B)
( REVISION NUMBER: 1 l PAGE 5 0F 11 1
At SQN plant the majority of installed insulation is m.olded calcium l silicate. However, at SON (and WBN) mineral fiber insulation has j been applied to some piping outside of containment only (excluding '
the mineral fiber block used in the main piping containment ,
penetrations). Typically mineral fiber insulation is installed on j heat traced piping containing borated water, Essential Raw Cooling 1 Water (ERCW) system piping, Raw Cooling Water (RCW) system piping, ,
and some exposed drainage piping. Two forms of mineral fiber _
insulation have been used at SON: i
- a. Felted mineral fiber flexible blanket type manufactured from 4 resilient refractory fibers, bonded with organic resin and supplied as a one piece, single layer, wrap-around pipe covering.
- b. Rigid preformed mineral fiber type, manuf actured from refractory fibers and with an organic resin binder molded into hollow cylinders, supplied in sections or segments suitable for single or multiple layer pipe covering. 1 i
Both forms of mineral fiber insulation are applied to straight pipe with metal wire or bands and covered with an .016-inch thick aluminumjacket. .
These mineral fiber insulation forms can be characterized as soft Decause of their relatively low compressive strength compared to certain other types of comonly used pipe insulation such as molded calcium silicate. ASTM Standard C165, " Standard Method for .
Measuring Compressive Properties of Thermal Insulation" provides procedures for measuring thermal insulation mechanical behavior under compressive load.
Another of the several mechanical properties which needs to be considered in the selection of insulating material is hardness.
Hardness is defineo as that property which measures a material's ability to resist penetration. It affects ease of application and' is determined by ASTM Standard C569, " Standard Test Method for Indentation Hardness of Preformed Thermal Insulators." The resilience of the wrap-around blanket type is desirable in some piping applications covering small obstructions such as heat-tracing.
Insulations of all types commonly applied to piping are susceptible to some degree of damage if not handled carefully during installation and protected from abuse after installation.- Mineral fiber type piping insulation has been widely used in industrial and' power plant applications and has provided many years of 0082D 12/04/86'
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TVA EMPLOYEE. CONCERNS REPORT NUMBER: . 232.3 (B)-
SPECIAL PROGRAM .j p* REVISION NUMBER:. . 1 j t,
PAGE 6 0F 11-
- l satisfactory service. If damaged during' installation or af ter to the extent that: thermal performance is. unacceptable, the damaged-
-section of. insulation can be economica11y'and readily replaced.
During installation, a reasonable amount of' waste from. abusive'. =
damage and other causes is anticipa;ed and considered- acceptable.
4 Mechanical vibration can cause deterioration ofx piping insulation thermal performance:through wearing.away, ' settling, 'or dustingjof .
the insulation material. '1 71 The resistance to vibration' of mineral. fiber type. pipingTinsulation is good and there are applications where its mechanical- Q perfonnance can be. superior to thatof 'a harder material:'such.as. .j molded calcium silicate. - The microseismic forces resulting. f romi '
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the small' amplitude vibrations produced by fluid flow;at design a velocities in the insulated piping at SQN (and.WBN) are'not of-sufficient magnitude to cause= significant wearing'away or dusting j) of the minera11 fiber or other insulation used. . Furthermore,. -
because of the bonding of the fibers, settling is not alproblem -l with rigid or semirigid insulations. '
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Satisf actory service' experience in' widespread (applications; j' demonstrates. the acceptability of mineral fiber' as anf economic, durable!and' maintainable' piping insulation material.
- 1 Issue ab" ,
The second concern wasTreceived March!12, 1985 bylthe TVA Nuclear 3 1 Safety Review Staff (NSRS) during.as review ofTmaintenance o.
activities at the SQN plant. The'NSRSLinitiatedianHnvestigationt ) ;
to evaluate the validity of;the concern?byTidenti.fying thel l applicable insulation requirements'for SQN and'thefplant's; . _
)
compliance with these requirements. The NSRS InvestigationReportl ' 4 No. I-85-106-SQN, issued Decembe'r'.2'l', L1985, contained corrective- j action' recommendations which were completed.by,the SQN plant'stafff i May. 25,1986. The..' Employee' Concern TaskiGroup?(ECTG)~' documented ! l the concern by preparing'an Employee Concerni Assignment <-(K-form);on; September 22, 19861 L
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<The NSRS investigation revealed the concernLpertained to ther
' potent.ial for nonmetallic insulation' causing cracking of taustenitic! .
stainless' steel. This possible: promotion ~of c stress'. corrosion j cracking could ar.ise from contact! of;:austenitic; stainless? steel '
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- with insulating; materials containing excessivellevels offleachabl.e) ,
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- TVA EMPLOYEE ' CONCERNS ' -REPORT NUMBER:' 232.3 (B)- ,
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SPECIAL PROGRAM REVISION NUMBER: 1- s s
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PAGE:7 0F-11
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chloride and fluoride . ions as; defined in USNRC Regulatory Guide '
.l.36, " Nonmetallic Thermal Insulation for Austenitic Stainless Steel." Over an extended period of time the concerned individual f
- had' observed the-installation on safety-related. austenitic L . .
.stil a n ess st ee 1 1sy stems 'of insulation. types that he. believed were of unacceptable quality (noncompliance.wlth Regulatory Guide 1.36"
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req uirements) .
In conducting the investigation'the NSRS investigator' reviewed-
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relevant design drawings and procurement specifications, and-interviewed responsible Office'.of: Engineering;(0E) personnel'to-identify the-original; SQN fplant; insulation requirements.
Additionally, ' plant procurement procedures and. standard practices documents were reviewed, and responsible plant personnel were.-
' interviewed to. determine the extent :of insulation replacement.due ~
-to maintenance and modification activities. .Also, the. investigator..
evaluated the' traceability of replacement? insulation from purchase to installation.
The NSRS Investigation Report No. I-85-106-SQB found that while most of the insulating materials installed at'SQN were the'.same:as ~
those.used at other TVA plants where compliance with Regulatory l'
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Guide 1.36 is required, compliance ~ at: SQN was uncertain because ~
certification documentation was ' lacking;; and.Lfuture compliance wast not assured..fThe report appropriately recommended documenting' .
demonstration of compliance with Regulatory ' Guide 1;369equirements; for nonmetallic insulation installed in the-plant and'storedt on site _ It also recommended procedural changes to" assure compliance with the Regulatory Guide requirements of(future replacement- ~
insulation purchased by the-plant. - , ,
The S'QN' plant < staff response L( App.l A,f 5.m.'and 5;n)(toNhe NSRS -
report . recommendations; committed,to Regulatory Guide 1.~36 testing 1 '
of nonmetallic. thermal insulation: installed'on stainless /steelfin:
safety related systems and warehousedlin ~ Power Stores,%and?to 1 maintain: testing documentation. Further.:the plant response l J committed toirevising SQN plant sta"ndard practice.SQM35,L E l
"assure Nonmetallic Thermal that future insulationInsulation-Austenitic' needsiwill'be procureds Stainless Steel,")to,h stored, an w , j installedTin. documented. compliance .with Regulatory Guide 1.36- '
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i TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.3 (B)
SPECIAL PROGRAM REVISION NUMBER: 1
' PAGE 8 0F 11 l Findings:
1 a.1 . Commercially available mineral fiber type piping insulation l has appropriate and economic applications in the SON plant. i j
a.2 The general serviceability of mineral fiber piping insulations is satisfactory when installed and maintained j with reasonable care.
a.3 At SON mineral fiber piping insulations exposed to the-vibration created by fluid flow.in the insulated pipes during i normal operation will not experience a significant loss of j thermal performance over the long term when installed and j maintained in accordance with the manuf acturer's instructions.
b.1 Regulatory Guide 1.36 requirements were recognized by TVA and l all TVA nuclear plants were appropriately instructed'in 1975 '
by Division of Power Production' procedure DPM No. N75M9.
b.2 TVA SON Plant Standard Practice 50M35 (01/18/83) transcribed the Regulatory Guide 1.36 requirements from DPM No. N75M9 and i was incorporated by reference into SQN Plant Procurement i Procedure SOA 45, which governed the purchase of replacement j insulation at the time of the NSRS investigation but did not require quality certification documentation.
Subsequent to the NSRS investigation, the SQN plant staff i I b.3 completed a program of testing nonmetallic insulation i installed and in Power Stores storage areas which verified and documented compliance with Regulatory Guide l.36 req uirement s.
b.4 The SQN plant staff revised procedure SQM35 to incorporate NSRS report recommendations for documenting compliance with ,
Regulatory Guide 1.36 requirements for new nonmetallic ,
insulation purchases at SON.
Conclusion:
- a. The concern is not valid for the mineral fiber types of ~
piping insulation installed at SQN.
00820 12/04/86 A
- a. , l TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.3 (B) )
SPECIAL PROGRAM ;
i- REVISION NUMBER: 1 j PAGE 9 0F 11
- b. The concern was valid for nonmetallic insulation at the time it was raised to the NSRS since the SQN plant could not ;
document compliance with Regulatory Guide 1.36 requirements.
However, subsequent SQN plant actions to revise the !
insulation procurement procedure and-maintain appropriate i chemical test documentation now assure and demonstrate the 1 acceptable quality of nonmetallic insulation installed on 1 austenitic stainless steel in safety-related systems. Thus- l the perceived problem identified by the concern is resolved. j i
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- 10. CORRECTIVE ACTION: j l
No corrective action is required. j
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. TVA EMPLOYEE CONCERNS L REPORT NUMBER: ~232.3(B)
SPECIAL PROGRAM i 1
REVISION NUMBER:' 1 PAGE 10 0F 11 ;
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APPENDIX A'
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- 5. . DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
.a. TVA Mechanical Design Guide DG-M18.9.1, " Insulation for j Piping and Equipment in Nuclear Power Plants"' 1
'd
- b. TVA Design Criteria, SON-DC-V-2.10, " Insulation Used Within the Containment Vessel"
- c. TVA Design Criteria, SQN-DC-V-1.1.ll.4, " Pipe Insul'a tion Modifications for Pipe Rupture Protection Outside. Containment" 1
- d. TVA Specification No.1475, " Thermal Insulation Materials' for:
Piping and Equipment Inside the Containment .for Sequoyah
. Nuclear Plant ~ Units 1 and 2 and Thermal Insulation Materials-for Piping,- Equipment:and Reactor Vessel Inside the f Containment for Watts Bar Nuclear Plant Units l' and'2" -]
- e. TVA Specification No. 2093, " Insulation.for Piping- and.
Equipment Including Installation, and. Pipe and Equipmenti ;)
Insulation Installation Inside Containment and the-Main and. .1
(. Reheat Steam Piping to the Turbine Building, Sequoyah Nuclear i Plant Units 1 and 2" )
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- f. TVA SON Drawings 47W400 series, insulation installation
- g. FIBREX Inc. Technical Data Sheet for."Epitherm 1200 Molded Pipe Insulation" 1 Forty Eight Insulations Inc. Product Data' Sheet'.for h.
" Forty Eight MF Pipe Insulation"
'i. ASTM Standard Specification.C547-77-for. " Mineral Fiber-
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Preformed Pipe Insulation" ?
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- j. ASTM Standard Specification C592-80 for " Mineral Fiber Blanket Insulation and Blanket-Tppe Pipe. Insulation:
. (Metal-Mesh Covered) '(Industrial Tipe)"
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- k. Letter from L. M. Mills, TVA, to- A. Schwencer,; NRC,; 1 l
No'." A27 800721. 018,- (07/21/80)
.1. TVA' N'uclear Safety Review Staff Investigation Rep' ort-No.
I-85-106-SON,(12/27/85) 1 0082D 12/04/86 o
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TVA EMPLOYEE CONCERNS REPORT NUMBER: 232.3(B)
SPECIAL PROGRAM REVISION NUMBER: 1 q
PAGE 11 0F 11 APPENDIX A (Cont'd)
- m. TVA memorandum from H. L. Abercrombie to K. H. Whitt, (01/16/86)
- n. TVA memorandum from K. H. Whitt to H. L. Abercrombie (02/13/86)
- o. TVA SON Plant. Standard Practice SOM 35 (05/21/86),
" Nonmetallic Thermal Insulation - Austenitic Stainless Steel"
- 6. WHAT REGULATIONS, LICENSING COMMITMENTS,' DESIGN REQUIREMENTS, OR OTHER.
i APPLY OR CONTROL IN THIS AREA 7
- a. SON plant design criteria listed ~ in 5.b.above
- b. TVA insulation specifications listed in 5.d and 5.e above-
- c. TVA drawings listed in 5.f above
- d. USNRC Regulatory Guide 1.36, " Nonmetallic Thermal Insulation for Austenitic Stainless Steel"
" Nonmetallic Thermal Insulation' for Austenitic Stainless Steel"
- f. TVA SON Plant Standard Practice S0M 35.(05/21/86),
" Nonmetallic Thermal Insulation - Austenitic Stainless Steel"
- 7. LIST REQUESTS FOR INFORMATION, MEETINGS, -TELEPHONE CALLS, AND OTHER -
DISCUSSIONS RELATED TO ELEMEN1..
- a. TVA SON Transmittal #100,-(08/27/86),
- c. TVA SON Transmittal- #115, . (09/19/86)
- d. Telecon between Mahlman and Mills, TVA Knoxville, and; Griffith,BechtelSF,(09/24/86)-
.f. TVA SON Transmittal #142, (10/30/86) ,
0082DT12/04/86 ,
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ECTG.C.3 Attachment A Page 1 of 1 Revision 2 - A-ECSP CORRECTIVE Action Tracting-Document
-(CATD)
INITIATION 1'. Immediate-Corrective Action Required: .O Yes- k:No 2.
- 3. StopWortRecommended:.Odesol CATD No. 2-3 L.06 - 5 0 hi 4% No INITIATION DATE I L " YO'"Ib
- 5. . RESPONSIBLE:0RGANIZATION:
.6. PROBLEM DESCRIPTION: O QR K NQR-SPEC t Pic ATieeJ 6-13 b%EA&RAPM 5 2. DEFERS- GA i.l0 R ts o s cTI s AI - 70 o r H t. R. Doc U wL lE.r4 T5 . BuT , ~
A F TE GL ST I P U L A-T* t N 6 S d C. M D E.s:: Mr2. A L. d o (s -
nN To MAKE. Op e s c u rst. e m s u r's tM VArt M Q M M "1.1 2L . ' T'44 \ $ t #4 t' o p44 f t f'E kf t v S M au L D' O E' GECmLVgp
) O ATTACHMENTS-
- 7. PREPARED BY: NAME D . L.. D A. m oM S ))- DATE: # f -1.e - F 6 :
- 8. CONCURRENCE: CEG-H " DATE:
- 9. APPROVAL: ECTG PROGRAM MGR. -DATE:
CORRECTIVE ACTION.
- 10. . PROPOSED CORRECTIVE ACTION PLAN:
1 O ATTACHMENTS
'11. PROPOSED BY: . DIRECTOR /MGR: DATE:
- 12. CONCURRENCE: CEG-H: DATE:
SRP: DATE:
'ECTG PROGRAM MGR: 'DATE:
VERIFICATIONANDCLOS' EON
. ~
- 13. Approved. corrective actions have been verified:ss? satisfactorily 5 implemented. ,
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, SIGNATURE- TITLE. .DATE'
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Date/"II"b7 TCAB' -ON
.l Gordon L. Parkinson, Project Manager Bechtel Power Corporation Fifty Beale Street P.O. Box 3965 San Francisco, California 94119
Dear Mr. Parkinson:
EMPLOYEE CONCERN EVALUATION PROGRAM - SEQUOYAH RESTART PROGRAM'-
CORRECTIVE ACTION PLAN (CAP) 4 reoIM ~!
Attached is the linegCAP.for Element Report 29 06' CATD 23106- S Q W - I .
- Please review and concur in accordance with the Employee Concerns Task Group (ECTG) Program Manual or provide comments as soon as possible.
['
Upon receipt and approval of all CAPS required.'for each. element report, you should revise the report to indicate the corrective actions that'will f s be initiated by the appropriate line organization. 1 i
& R.W Y ?
GMrge R.:McNutt 1
I GRM CJR:
Attachments ]
cc (Attachments):
D. T. Clift, 9-162 SB-K .
'N. A. Liakonis, W9'B85 C-K- t H. A. Mahlman, W7 A52 C-K P..B. Nesbitt, W8 D199 C-K-T. C. Price, 5-212 SB-K i
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,' UNITED STATES GOVERNMENT TENNESSEE VALLEY AUTHORITY Memorandum To- :
W. R. Brown, Jr., Program Manager, Employee Concerns Tast Group, ONP, Watts Bar Nuclear Plant FROM - H. L. Abercrombie, Site Director, ONP, O&PS-4. Sequoyah Nuclear Plant DATE January 16, 1987
SUBJECT:
SEQUOYAH NUCLEAR PLANT (SQN) - EMPLOYEE CONCERNS TASK GR REPORT 231.06 SQN - ENGINEERING CATEGORY - CORRECTIVE ACTION
Reference:
My memorandum to you dated December 24, 1986 (S03 861223 805)~
I Attached is my revised CAP for Element Report 231.06 SQN for your.
review / concurrence.
This revised CAP supersedes the' CAP previously transmitted to you (see reference) and is not a restart requirement.
If you agree with the proposed CAP, please si5n the ECTG concurrence space below item 9 on the CAP tracting checklist and return the CAP tracking i checklist.
//H. $L. Abercrombie RCD:JDS:PLS:CS Attachment ec (Attachment):
RIMS, MR 4N 72A-C (B25 '870115 024)
- 7. C. Price, 5-212 SB-X RECElVED-0556T 15N 1 VS7 Impi.yse consms Task Gro@ WEN na, w.we wt
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. Standard Practice: Page 8; '9 y 1"
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- - AttachmentA. " '
' ' I Page 1+of: <
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, Corrective Action Plan of Employee Concern Envestigation '
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' Tracking Checklist ~ ,
j ECTG. Report /CATD' Number ~23 /4 N9A/ f# # 2 3/de gw 6 -
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onsible for Corrective Action Plan-
' I.ead Organization Resp /2 - f- 0f ' < f Initiation Date .
- )
CORRECTIVE ACTION PLAN (CAP)-
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.1. Does this report require corrective action?- l (If yes,' describe' corrective action to be -taken, if new provide. justification)
' E rasnr .tener ' son 6.rm.ver Couseau 23l 0V mae rs or- ework ' ruxe 's lm i e so.s rn>dPb rA riaN ef'0fue*1st' Ocusreverow bee miedrian $*7 ts '#s tstet e . .$ $
lenes ' ou r ' ru saware ' se ' wa s on :runawsrinx , avrOr coas xer Esauraaws. J '
De m.ruam ' kn ur ^'arrar ' as sswnrre e v ^ 0-X1x - arriW foM sa&, seneru ~ Mwe
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- 2. Identify any;similar item / instances and corrective action taken.., .
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- 3. Will corrective action preclude recarrance;of(findings 7f. Yes+ 1A' , :No k- - C Does this report;contain . findings thatf are conditions adverseito' auality (CAQ)?--pJ, '
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as defined by AI-12 or NEP 9.17 1 ...
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- 6. Which site,section/ organization is responsible for correctiveiaction?-
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- 7. Is corrective. action required for restart? . , .
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l l(This determination 'is to be. made .' using' Attachment C Nf SQA166. )/
'8. P2' zone numbercfor restari corrective action?'. Zone: J// 9/(& ' M l
- 9. Estimate completionLdate for correctionLaction., 'MPEnc:$$- a h I_ /@
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, , SQA166 -
1 Revision 8
- i t . A7?ACIMEET A , i Page 2 of 2 ~
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- 10. Was your cor:t ective action initiated and ecmpleted in accordance with step 1? .j Yes No l
- 11. If step 10 is no, describe the corrective action taken.
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- 12. Is the correttive action i:aplementation, complete? Yes No
- 13. Is the correctiva action documentation ~ closed? Yes No
- 14. What documente, were used to implement the corrective action?
Completed By: Date Verified Ly: , Date ECTG Clost.xe: .-
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'Attachm:nt E-
[ - ' Page 1 of 3 1 Revision 4-1 ECTG VERIFICATION CLOSE0VT CHECKLIST I:
-CATD Noc l I
This CATD wasl designated: C/A completion notification -l Memorandum RIMS No. -l' I
[] QR CAQ No. .
This ' memorandum denoted CATO: l
-[] Partial' Closure -l 4
[]NQRL
[] Complete Closure i j l
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SUMMARY
- C/A elements reviewed l: [] Procedure and/or drawing revision .
-l [] Walkdown documents
[] Training records.
.l [] Document and/or drawing reviews .. .
l
'l [] Examination or test results [] Modification'(ECN) documents I
[] Engineering analysis [] New program (s). l '#
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1 []' Repair or replacement records' f] Other' .specify l' 1
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l . DI SCUSSI0in Discuss 'veritbtion actions' taken '(including documents /.. l hardware reviewed as applicable). See verification guidance,- l ..
1 l page 3 of-3 of this attachment.- l l
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l Corrective actions were adequate::[] Yes l-
Conclusions:
[] No . .[]' N/Al 1: g -
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[] [].Deficienciesadequately,scoped 1- 1 l
l- [] [] Deficiencies' corrected. . .l j
[] .[] Actions. required to. prevent recurrence 1 complete.- l ..
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- j. Signature Date- -l
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l Attachment"E Pagec2Lof 3 1 Revision 4 ,
- - VERIFICATION CLOSE0VT CHECKLIST - ..
1
~
Date 1 E.T /CATD NO. - Initials 1
- l
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)! DISCUSSION: --(Continued) .
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ECTG C.3 3 Attachment E i Pag 2 of 3 -l Ravision 4 VERIFICATION CLOSE0VT CHECKLIST i
j
-l CATD NO.
Initials Date I
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DISCUSSION _: (Continued) i I
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Cf v ECTG C.3 3 .. .-
Attachm:nt E I Pagt 3 of 3 Revisica 4 VERIFICATION GUIDANCE .
Date i
.T Initiels _
i'
.l.CATD No. .
i stions: '
1
,l' Verification activities should answer two que i ements l 1 Were specific corrective action commitments and requ r 1-
.l-(1) completedt 1 l Vere the corrective actions taken adequatet l l'(2) ..
h rrective actions taken-- I >
l . verifier should consider whether or not t e coistent
~
with the erplicit li h t was accepted by.
ll The address the identified problem in a manner cons l-i and implied
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elements At a minimum, of the corrective the corrective actions shouldist, action correctedplan t ahave all, j identified 1-l'. ECTO.
i d to prevent *
-l
'l- similar deficiencies i ble.
if similartion defleiencies and sive the er1 ' ident 1
.1 recurrence where appl ca id in {
l found to cubstantiate verification of corrective lusions.- ac 1 I appropriate document references .
d'in the-and/or hard I
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I If the " Corrective Actions were adequate I- tive actions were *' hN/Av. block is check 1 I
i conclusion section, this indicates that no' correcJ ,l req
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. DISTRIBUTION ~FOR MEETING
SUMMARY
DATED: June 19, 1987-
, Facil.ity: Sequoyah Nuclear Plant, Units 1 and 2*1 D6thtTilQ.
.NRC PDR-
~ Local PDR JKeppler/JAxelrad
.SEbneter'
.SRichardson-JZwolinski BDLiaw.-
GZech . .
RII SRConnelly, 01A EWS-461
.BHayeso EWS-454
~CJamerson LJDonohew MFields.
.HGarg '
PHearn RAuluck-GGeorgiev
>SElrod RII
' GWal ton .. RII DSmith' ACRS-(10)
FMiraglia- P-428 EJordan. MNBB-9604 OGC-BETH EWS-360 Projects Rdg j SON Rdg. <
l JMeyer H-1149 ;!
JAustin H-1149 l JMilhoan H-1149 .
PGwynn H-1149 -
CAders . H-1149 '
Hon._M. Lloyd Hon. J. Cooper
~
l Hon. A. Gore 4 Dr. H. Myers i S. A. White l TVA-Bethesda
'l
- Copies sent to' persons on facility service 11sti -
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