Text

Forwards Response to NRC 880222 Request for Addl Info to Resolve Restart Allegations
	ML20147B371
Person / Time
Site:	Sequoyah
Issue date:	02/29/1988
From:	Gridley R; TENNESSEE VALLEY AUTHORITY
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20147B376	List: ML20147B371; ML20147E569;
References
	NUDOCS 8803020079
	Download: ML20147B371 (341)
	v • d • e

{{#Wiki_filter:~ TENNECOEE VALLEY ' AUTHORITY CH ATTANOOG A. TENNESSEE 374ot 5N 157B Lookout Place FSB 291988 U.S. Nuclear Regulatory Comission ATTN Document Control Desk k'ashington, D.C. 20555 Gentlement In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - RESPONSE TO REQUEST FOR ADDITIONAL-INFORMATION FROM TVA TO RESOLVE RESTART SQN ALLEGATIONS This is in response to your telecopy request from Mel B. Fields dated February 22, 1988, entitled, "Request for Additional Information from TVA to Resolve Restart SQN Allegations." Our response to each of the items is enclosed. The enclosure is intended to respond to NRC's request for additional information only and contains no new comitments. Please telephone M. R. Harding at SQN, (615) 870-6422, if you have any questions. Very truly yours. TENNES EE VALLEY AUTHORITY / R. G idley, Di ctor Nuclear Licens ng and Regulatory Affairs Enclosures cc (Enclosures): Mr. K. P. Barr, Acting Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Comission Region II 101 Marietta Street..W. Suite 2900 Atlanta, Georgia 30323 Mr. G. G. Zech, Assistant Director for Projects IVA Projects Division U.S. Nuclear Regulatory Comission g3o j One k'hite Flint, North 11555 Rockville Pike 8 1 Rockville, Maryland 20852 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy. Tennessee 37379 g803020079 880229 ~ I DR ADOCK 0500 7 p An Equal Opportunity Employer

O 9 ENCLOSilRES e 6 e 1 O f 1 -______s

(1) (a)."What SQN procedures / controls require reinspection of the electrical hangers that were modified after initial inspection? (b) What SQN procedures enforce such requirements of inspection of the modified electrical hangers? (c) Have there been any corrective actions implemented if reinspections were not enforced?" TVA RESPONSE: 1. (a) All modifications of safety-related structures, $ystems, and components are performed according to appropriate plant procedures that require adequate inspection of structures or equipment before it is put back in service. Administrative Instruction (AI) 19 (Part IV), "Plant Modification: After Licensing," and Modifications and Additions Instruction (M&AI) 11. "Fabrication, Installation, and Documentation of Supports, Piping Systems and Structures Attached t,o Seismic Category I Structures " are the relevant procedures. (b) see (a) above (c) Procedures are enforced without exception. It has been stressed to all employees that it is their responsibility to initiate a Condition Adverse to Quality Report (CAQR) when procedures are not adequate or are not being followed. The CAQR process ensures adequate correction of identified problems. 4 9 e O e 6

J ' (2) "When unistruts are welded to other materials much thicker than the I struts, thermal distortion of the side walls of the struts can occur, and may cause the nut-spring assembly for clamp bolts to become partially or entirely detached from one side of the strut. Was such a problem ever observed, and hence corrected, at SQN during TVA's long term bolt tightening program?" TVA RESPONSE: d Thermal distortion of the unistrut side walls was observed at SQN unit 2 as part of the Corrective Action Report (CAR) 87014 program. The condition and the repair procedure were confirmed by testing conducted by ~i Singleton Materials Engineering La,boratories. The procedure and technical 4 justification for the repair are documented by attachment 1. N-6 1 r i i e a d i s r y

9 1 (3) "What TVA procedures trace and control heat numbers of the strut materials at SQN? Provide such procedures for review." TVA RESPONSE: Traceability is "as required" by the design, fabrication, and-installation applicable codes. t Pipe hangers are to American National Standards Institute (ANSI) B31.1, 1968, and Manufacturers Standardization Society (MSS) - SP-58. l Heating, ventilating, and air conditioning (KVAC), cable trays, and 4 conduit are to American Institute of Steel Construction (AISC) - Seventh Edition. ANSI B31.1, MSS-SP-58, and AISC neither require nor specify traceability. The.unistrut clamp / configuration used at SQN does not require heat code traceability. ~ 1 4 I ~ 8 l 4 i l ^ l i 1 I i i

< (4) (a) "What is the status of TVA's corrective actions to address the deficiencies in the seismic qualification of SQN equipment, as identified in NRC's November 6, 1987 IDI report?" t TVA RESPONSE: TVA responded to the findings from NRC's Integrated Design Inspection (IDI) of SQN unit 2 Essential Raw Cooling Water by letter dated December 29, 1987. Follow-up inspections by NRC in Knoxville, Tennessee, the week of February 1, 1988, resulted in either closure of the open issues or agreement on the additional actions needed to resolve outstanding questions. Revised or supplemental TVA responses to these issues are being provided to NRC the week of February 29, 1988, by separate transmittal.

4) (b) "What is the status of TVA's corrective actions in addressing the problem of equipment vendor's seismic loads being not properly" interfaced with TVA's anchorage design and the concerns with the electrical mounting devices, as referenced in Item 24 of TVA letter to NRC, dated June 23, 1987, ' Review of March 28, 1987 from Dallas i

Hicks.'" TVA RESPONSE: The status' of the corrective actions as referenced in item 24 is as follows: Element 201.03 Corrective Action: The design criteria that are identified in SQEP-29 as requirements for restart will be reviewed, revised, i . or generated as applicable before restart. Status: Complete and closed by Employee Concern Task Group (ECTG) for unit 2. Complete but not closed by ECTG for unit 1 (refer to attachment 2). Element 204.04 - i SQN did not receive an element report on this number. No SQN j corrective action identified. l Element 220.03 - Corrective Action: Calculations will be performed for observations - noted in the element report for several supports. Status: Nonrestart corrective action. Not complete. l \\ t \\

l Element 228.00 - Corrective Action: Verify adequacy of straps (conduit) in the slip-through direction. Status: Restart action for unit 2 is complete and closed by Bechtel 4 (refer to attachment 2). Element 223.03 - i Corrective Action: Verify that all required instrumentation (FSAR Chapter 15) mounted by TVA is seismically qualified. Status: Unit 2 is restart complete--closed by Bechtel and ECTG (refer to attachment 2). W 1 f 1 i l a I l s

! i (5) "Provide ECN's L5313 and 2905 which corrected the design deficiency in the t blowout roof of the Main Steam Valve Room. What was the nature of the design defect of the blowout roof that required the ECN's for correction?" TVA RESPONSE: Engineering Change Notice (ECN) 2905 corrected the deficiency in unit 2 and ECN L5313 corrected the deficiency in unit 1 (refer to attachment 3). The ECNs were issued to correct the roof system for preventing water problems on the east and west steam valve rooms. The present roof has been subjected to high temperatures and exposure to moisture due to valve testing. Since testing, an additional exhaust fan has been added to each roof area to relieve the high temperature and moisture buildup. Additional changes to prevent recurrence are as follows: 1. Add vapor barrier and insulation to avoid moisture damage and i high temperature to the plywood. 2. Change plywood thickness and quality for durability. i i 3. Change' method of application of the roof weather coating for greater flexibility. t O I e J l

_7 (6) "The TVA response for the Watts Bar site regarding the concern that there is no material control of ASME bolts smaller that 1" (See letter dated June 5, 1985 from J. Hufman, TVA to H. Thompson, NRC, Enclosure 1 - Item 1) is acceptable to the staff. Provide a similar response, if possible, for the Sequoyah site." TVA RESPONSE: Response to NRC regarding control and issuance of bolting materisis at SQN has been made in several areas. The Safety Systems Outage Modifications Inspection (SSOMI) (Docket Nos. 50-327/86-68 and 50-328/86-68) reported unmarked bolts in the vital battery racks similar to the WBN situation. An extensive TVA study of unmarked A307 bolts included SQN stock and is reported in the TVA response to SSOMI findings Item D-2.1-8 (samples 44 1, 45-1, and 46-1). Other bolting traceability concerns identified by the SSOMI findings were satisfactorily resolved. The applicable portions of Construction Specification G-53 noted in the WBN respense concerning traceability, markings, and stock / issue. controls were also required for SQN. These requirements are now implemented by several SQN site procedures. TVA has taken several additional actions to ensure that bolting materials are controlled and installed to Criterion VIII requirements at SQN. The Contract Engineering Group was formed to specify the quality and technical requirements for procurement of spare parts. Inventory bolting that may be utilized for safety-related applications is being procured, inspected, stored, and issued as basic components. Specific requirements are for manufacturer identification, grade marking requiresents, and heat inspection. Until the evaluation of in-stock boltii.6 material is complete, a controlled release program has been implemented that provides an evaluation of the acceptability of an item for its intended use before being. issued. = a i j i 1 I

(7) "A QA Deviation Report No. D04-5-4112-D01 was written on Bellefonte. According to this report EN DES has failed to provide construction with adequate inspection requirements to ensure the structural adequacy of non-essential tubing installed in Category I structures. Documented quality control inspections are not required in EN DES documents. This inspection is required to ensure the tubing maintains structural-integrity r and will not cause damate to essential equipment by acting as a missile or by wetting. Since this observation is generic, discuss the corrective actions taken by TVA to eliminate the problem at Sequoyah. Also, discuss the measures takan to prevent the recurrence of the problem." TVA RESPONSE: The typical supports used in Category I structures for supporting "non-essential" tubing were designed, installed, and inspected to the same Quality Assurance and Quality Control requirements as Category I supports. Therefore, the nonessential tubing is supported to maintain its structural integrity after a seismic event. For the above-mentioned reasons, this problem is not applicable to SQN. t i P l 9 l i ) ~ a 1 l

-f. (8) "A QA Deviation Report No. D04-S-84-4508-D04 was written on Bellefonte. ,According to this report General Construction Specification G-60, "Tield Routing of Instrument Impulse Lines, Sample Lines and Control Air Lines," is not referenced in the instrumentation and control drawings, i Series 5GB 0925-10. These drawings are being utilfred by the field for their design and installation of instrument tubings. The omission of G-60 from the drawings could potentially result in construction i requirements including physical separation of tubing not being included 4 in the field design and installation of instrument tubings. Since this { observation is generic, discuss the corrective actions taken by TVA to 4 eliminate the problem at Sequoyah. Also, discuss the measures taken to prevent the recurrence of the problem." TVA RESPONSE: 4 Please refer to Attachment 4. "Instrument Separation Walkdown i Information," for SQN. The summary addresses the actions taken on this . issue at SQN. Those actions are fully adequate to prevent recurrence of the problem. 6 e 1 J 1 o e I l l 4

. (9) "Was the traceability of structural steci ever the subject of an investigation by TVA, QTC, ete? Please provide references and results of such investigations." TVA RESPONSE: The Employee Concerns Program (ECP) is concluding an in-depth investigation of several issues involving heat number validation / traceability for structural eteel during SQN construction. The issues are identified in ECP Element Report Nos. ECP-87-SQ-510-09 and ECP-86-Sy-253-01 and NRC's referral RII-84-A-0187. ECP-87-SQ-510-09 addresses the results of this investigation and supersedes ECP's previous report ECP-86-SQ-253-01. ECP determined that ECP-87-SQ-510-09 was a potential restart item in accordance with ECP Instruction ECP-4, attachment 1. The Plant Operationc Review Staf f concurred with ECP's determination. Accordingly, the SQN Restart Director designated a line organization responsible to perform a restart determination in accordance with SQA190, Attachment E. The Restart Determination Manager determined that ECP-87-SQ-510-09 was not required for restart (refer to attachment 5). r l O O

k 4 4 3, (10) "Was there ever an audit or Level III evaluation of NDE and/or Radiographs performed by the TVA/ISI Groups in Chattanooga covering all sites? Please provide results of any such audits or evaluations." 1 TVA RESPONSE: Under the direction of TVA's Nondestructive Test Evaluation (NDE) Inspcetion Group, independent Levs' III evaluations of radiographs were performed by Technical Service Laboratory (TSL) at Watts Bar Nuclear Plant (WBN), Browns Ferry Nuclear Plant (BFN);( and SQN in 1987. Reports submitted by TSL dated April 8, 1987, and March 31, 1987, identify the results of these evaluations (refer to attacha'nt 6). a M' A directive from S. A. White dated January 111 1987, required that all new radiographs at WBN receive Level III revipw and acceptance. This i directive was expandea on January 23, 1987, to include all of TVA's nuclear plants. Office of Nuclear Power Nondistructive Engineering ~ Branch has complied with the directives, providing Level III evaluation and finak acceptance of new radiographs completed at each of TVA's nuclear plants. The requirement for Level III overview is now included in TVA's radiographic examination procedure N-RT-1. N-RT-1 is being further revised to include ANSI-recommended measures for contro11.ing factors that prematurely age radiographic film. Such factors were the~ cause of problems identified, in TSL's reports, as those affecting archival film quality. l I d R l i I l n lH l N ,i '

l I i ATTACHMENT 1 (B25 880119 803) 1 N l r 9 e 4 O

P 03' 1G3 AL NGCord '0 TVA 10G97 (DN E 446) DNE CALCULATIONS f,,g TITLE PLANT / UNIT PR O LG odif.C FO K. i2c Po l t o r 00tsre.0 7 f, toe t o co r.ir.dc Tio R SC9 0 0 0 tr M i 8 L-PR EPARING ORG ANIZATION KEY NOUNS (Consult Rl!.tS DESCRIPTORS LIST) hcleP-em o 9 s. o cu r e u r. co e c o, s o rr ocT c BR ANCH/ PROJECT lOENTIFIERS Each time these calculatons are Iwwed, preparers rwst ensure that the original (ROI RIMS eccesseon number is filled in. O 00 WA ~0 b R ev (for RIMS'use) O RIMS accession number D C. R 't.f V5i w 870804A0010, B 2s 87 072 9 802 4 w so.zs lei a rprn'..o'$$,~.goa"'"= Rd880130E0018M B 25 880119 803 S M 1 - o - 3 6 ') - C,1 Np D C. C. ifST R SAH 5ECTION($) UNIO SYSTEMIS) R Revision 0 R1 R2 R3 Safety < elated ? Yes @ No O ECN No. (or ind.cate Not Appl.ceble) Dc.h) X ~ C 0 0 2.r A H/A Statement of Problem

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Checked l2 6 P A 1 4 i d C. -T H 6 S f r.c.A D OWtsT RO T P g.o G LC M A d D y 9Mh// Jtut t ric.s A F. L A R. 6. Sc VE ' Kpproved g ' g' V g;u 4 j g/ ggg (4 6 L,0 As AQ A C.c4 FT A & Lt: Date V y'Q p .S t-j B 3 71 T O T C 00 6. L D. 1 LN$ l* lt)-98 List all pages added )*1 by this revision, gy 7.f List all pages deleted d j y, ; by this revision. g 3, j@l List all pages changed 9: "94(V by this revision, gir Abstract hk ' I Ri BYf s(14 f 3 These calculations contain an unverified assumption (s) 2 No @ gI that must be verified later. THLS

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NEP-301 g-THIS PAGE IS ADC00 BY REV. / $*I"U'1 cA1.cubATIUM us.s Agn ve. ult Ava4 Avn 6 4nuircav6NT REVIEW) FORM "Do 4 X o o o 2,5 A.cALt. d. Calculation No. Revision Method of design verification (independent review) used (check method used): 1. Design Review 2. Alternate Calculation. 3. Qualification Test Justification (explain below): Method 1: In the design review method, justify the technical adequacy of the calculation and explain how the adequacy was verified (calculation is similar to another, based on accepted handbook methods, appropriate -sensitivity studies included for confidence, etc.). Method 2: In the alternate calculation method, identify the pages where the alternate calculation has been included in the calculation package and explain why this method is adequate. [ Method 3:' In the qualification test method, identify the QA documented ) source (s) where test!ng adequately demonstrates the adequacy of this calculation and earlain. A vraum vsnisozr> ymat A.sz o 3.1 A r ra w x m 1* fo i I I s 1 0. l !b-88 ( Design Verifier . Oste (Independent Reviewer) 9 ~

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THE FOLLOWIMG PROCEDURE IS FOR REPAIR OF SPREAD Plooo ~ UMISTRUT TO ITS ORIGIMAL SHAPE AMD REINSTALLMEMT OF UMISTRUT CLAMP, tMAMILE_THE_._ EXISTING UMlSTRUI._ CLAMP _.FROM TME_ _ _ _ _. -SPREAD UMISTRUT. ~~~~~~

2. PRESS BACK SPREAD UMISTRUT, AT AMBIEMT TEMPERATURE, TO ITS ORIGIMAL SHAPE BY USIMG C-CLAMPS OR ANY OTHER EQUIVALEMT EQUIPMENT, 3.lMSPECT THE UUl5TRUT CLAMP FOR AMY DAMAGE. IF DAMAGE EXISTS,

REPLACE UMISTRUT CLAMP WlTH MEW UMISTRUT CLAMP OF THE SAME SIZE. IIMSTALL UNISTRUT CLAMP PER REQUIREMENTS ~OF 47AOSO 51 /8" (i. '/G4") SERIES DRAWlMG. I ?/4" MAX 1 MUM %R UNTIL SPRlWGuuT f,h SETS PROPERLY y b 0 g h % J d d E tQ ~ 5 o I k ~ $ (xRgj 0 .u 0 = ) egeg SPREAD UMlSTRUT s&!3 ORIGIMAL SHAPE NOTES: ( CONTINUED FROM 47A050 NOTES)

69. STRUCTURAL TUBIMG OF THE SAME SIZE, PERPENDICULAR TO EACH oTHER WILL REQUIRE A FLARE BEVEL WELD OM TWO SIDES.

70. Plooo UMISTRUT OM 2"x2" STRUCTURAL TUBIMG WILL REQUIRE A FLARE BEVEL WELO IM LIEU OF A FILLET lAIELD, PROVIDED A MINIMUM EFFFcTive vuonAT C F '/e" IS MAIMTAINED.-

THIS PAGE IS ADDED BY REV. I COMPANION DR.AWlNGS: 47AOSO SERIE9, -~ IMITIAL ISSUE PER EXCEPTIO'M' THIS ONG 15 APPLICABLE OMLY TO "A" CW AM6E COMTROL PE R.*- SUPPORTS ON Y2AND SMALLER TUBIN4, (('s% CATAGoRY I STR AND '/2"AND SMALLER-PtPE. E MECHAMICAL AsnEsiG:TD HANGER DRAWING 07En.';rT >'.G'JNTER _ GENERAL NOTES m ti.m. E.' Np SEQUgA ,LEgR PLANT Q ve RIMS Nt 2,7.5 670907 702.. ?IUC ?h a a ~ '- ' i--a iWIGL .. Ad. @$*S @ 9/. 8 ~ w,q.y;s7;4s:.... '.....$b?

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Date 7/ WlQ Checked by hg Date 7/2 572f7 SUSJ ECT: F/y - UP O/= S73rtti,4n upsg rs v7.3 REFERENCEEl 1 O f) 4 7 2 C44cd toit!5 &llt8 /1.C f*/ro w /IV /~/4, '3 flow f d IW y u d i t/ I( /u /180v5 CdfGT / r to /1.f suo 7' 70. t/ CE FG/tr/GtG 7M 6~.Q/mc svAS/Jfft .M y?/ f Y VssO To P// r/16. S/NGt & SPAfdC b'4/ 777t v 7 So /N 7P/ESS Cd.rG S 7?? 6 f V/GO 4 P/'CCC OF IN000 /fNO.. A s'/A/71/?!CAo 7//2 Y l'ut/sto 7P1 C SPMEMD tont..f of usur s'r/ v r~ 8 7 Sof 7 a snity17764 S 77% o le G 5 7//Kn E tv4J 40 PM/71 A GG f C sitN f o A y 7>rir F#eCi!.C*.T To 7?' f w/4PJ c/ Am 7 5 7// C/l 5TN VC 7t//r/l femPC d.HCH 7;, .4FrrA F/xavc une/t 771 5 tu.u vrxwr.r,.r/rc 3"PA' tnc A'c/ r.r* toCrt E f/OPC/ by CAM rfD

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1 i 1-i i i i l t I 1 Sheet 6 '/__ 'of_l. _ __. l_L-l PIPE SUPPORT CALCULATION SbEETl Cale. l.D. 47A 050 -2 8 i i i _ s cm h.__ d mT_.k. P.._ -...-_. Project Prepared by NM Date ///J fs / i Checked by h Date ///df/g 1%EFERENCES SUEMECT: Fly-vP Of s*M EMD v p t s 77C J'T* -stucF. O N. L.l _ O M t... V M LL. OF Uhl t STil J T S C l'V 5,H 6 0 f!A Cit. To iTe o ty st m+ g,,__s ocornon,,;yy_pgmgag w,a, w,u_gg c invv1o <!Y

rattc_ A&1Mik_ /4t acnn wie.w ab u n 7n88.

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==- ._ g'.. _. cd I-m CONC L u s s on!. :_. R EPA nte s u c, P Ro css p u r G. F o rt lo l ooo.. 9 V N 1 t Til v T. P F A. . 9 % G. 4*I A O 50 ? 75 AO OO .__ _.._._'.\\. S __ t% C C A P.T A 'L.5. 6.*.. _.. -...-....._ __. .__ u._ _ :. ... _. jVOTG. 8 9. o F. 0%G._A'ih 0SO?.35... lS. n CLs PTA GG C m ~ __.f8tt.. susrtFleniton sucwa ou PG. C) of TN!r. cnte. LU .C NO TE ' 70 0 F OwG. 41AOSo 2 5 Is._ A ccs UAet.e ptr< 0. .... JusT/ft(Arton geogw ori p g,_ 7 g p _ 7717,c rp gc, $Q "E p. _7 .___L_ _...... ~ ~.. -. -.... _.......... i i ._u-.. ..~..__;_. L. l f - _. L,.. g..... i -_' I i . l.. _.... i_ _ _. i. i i f f g.. i ..._ _ _. ;... q i i i 1 4 l l l 3 I I I l l 8 i I l l p T,v a,s o n s ten D E S.3l8 3) l l l j j

QUALITY TNFORMATION REQUEST / RELEASE (QlR) DIVISION OF NUCLEAR ENGINEERING CA (hcortft"5 ^cg41 INTERNAL /SE ONtY) '88 01:.3 00? .T0 K. L. Mogg, DBOC-C34 SQN lDOCUMENTNUMBER l 101R-50P$0N-88-012 lFROM B. B. Neely, W9 C150 C-K ^ l

PACE 1 0F 1 lTYPEOFDOCUMENT

IDAIE, N,! O 1hhb o

l() REQUEST NEED DATE l ... - - l P TAN T ANO UN I T ) (X) REtEASE REF. 01R N/A l Stauoyah Nuclear Plant _1 & 2 l_ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _. _R[F{RENCEO DOCUMENT!,, _,,,,, _ _ _,, _ _ _,,,,,,,,,,,,,,,,, l Av_allable in One of the RIMS Systens l Attactrnent to This CIR l Document Identifyino Nuc6er l Doc (rent Attachment Wteter ; I I l$QMMech.HangerDWG. 47A050-25 l l47A050-25 Calc. Package 825 810902 702 l l l l l SUBJECT Repair procedure for spread P1000 channel ~ l I SYSTEMS AFFECTED l UNIO /5YSTEM10 l N/A l N/A lQUAllTYINFORMATIONREQUESTED/ RELEASED The condition to which the repair procedure shown on $QN drawing 47A050-25 applies has been observed in unistrut clag and channel specirnens assertled for testing at Singleton Materials Engineering Lab. Channel

l. which has spread due to the welding process has been repaired in similar fashion to that desc with no signs of distress. Clrp allowables need no further reduction as a result of this repair.

l l This quality infomation release was reviewed by $1ngleton Materials Engineering Laboratory. -l l l I i I s!QUoYAH W)*Ltt'i r! *.MT I THIS PAGE IS ADDED BY REV. I l d 2. ~ I r.,.r.. # *No. - 2 5.. ..llkf.b.S.--_ $ :.s. l .e ..;2SG-1)M/W-.. l l l l. l PAEPARED REYlEWED (RELEASES ONLY) CD A &s i/n/97 lAPPRO ED (BPANC CHI F/ PROJECT ENGINEER) F 'fjd J t< M TVA10929(ONEl4A-6-86) l cc(Attachments)! RIMS, SL 26 C-K R. C. Oute, 05C-E28 SQN J. P. Best, $ME-K TOTAL P.02 [ /

Jgf ~-=. y2 1 i i I -l l PIPE SUPPORT CALCULATION SHEET l l - E.* M. 10 l.. L I I i l l I l i 7' I cc

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-ddik 4 itchrofect -

.P,li - .d by de Stihif Date :bLt-4 7 ' $6) 41/ 8' Ch. - d by M Date 7/ff/n

SUBJECT:

F/ / '- g /* OF //1/o/ g,g.*M pEFERENCES -. =. Y ACO'T~ d'A t/.f 6 l'>tc 5"Ps<6M n . I.- R' M s&k4. of. ye t r/e c)r wr kr scle. - ou F4Ar "U gg ?$N7'& k.771/C/t. ?S A : / S Dl///2& #ffs J C f-4 'IA 05'O CC/2/51 D.t?) A.rt Nd.!. / 7~ 1a,4.r*

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i..

[ l I t-i i l e i j 4 l .1 i I i t t t ..d-I i i I f 4 !-(- I }I i i i i i 1 i i i i i ii i i t i i l I TvA toras (cN ots a.sa); l l l l l l l l l g g l l [ j j j.

V )o eet VL. RE FOLLOWIMG PROCEDURE IS FOR REPAIR OF SPREAD P1000 7/t.t/ f t t1MtSTRUT TO ITS ORIGIUAL SHAPE AMD REIMSTALLMENT OF WMISTRUT CLAMP. 'ecke- ,J,, DIS MAMTLE THE EXISTING UMISTRUT CLAMP FROM THE SPREAD UMISTRUT.

2. PRNPREAD'1.1MISTRUT AT AMB1EMT7EMPERATURE, T ITS ORIGIMAL SHAPE BY USIMG C-CLAMPS OR AMY OTHE EQUIVALEMT EQUlPMENT.

sr.o .4.lMSPECT THE UUl5TRUT CLAMP FOR AMY DAMAGE. IF DAM E EXISTS, REPLACE UMISTRUT CLAMP WITH MEW UMISTRUT CLA OF THE

g SAME SIZE.

o ~ tw .ffjuSTALL UNISTRUT CLAMP PER REQUIREMENTS,C) 47AOBO H 5 c,., S ERIES DRAWlMG. ._1 /s" (i./G4") OR UMTl SPRlWCuuT l yr SETS RoPERLY l b, r g 9.h .. _ _ _ _ _ _d , _ _____~ 0 RiclMAL SHAPE SPREAD UMISTRUT ,,_1 &.cw sag - IflcIW r. . NOTES:(CONTIMUED FROM 4 7 05o NOTES)

69. STRUCTURAL TUBIMG OF T SAME SIZE. PERPENolCULAR TO EACH

OTHER WILL REQUIRE FLARE BEVEL WELD OM TWO SIDES.

70. Plooo UMISTRUT o P"x 2 " STRUCTURAL TUBIMG WILL REQUIRE I

A FLARE BEVEL LO IM ' LIEU OF A FILLET WELD, PROVIDED A MINIMUM EFF CTIVE THROAT OF '/ " IS MAIMTAINED. 1 8 l E-2-XooO25A A ?*47AObO 29 Act 000 THIS DW IS ~ APPLICABLE OMLY TO SUPPORTS UMDER THE SCOPE OF SElSMIC CATAGoRY I STRUCTURES SMI-313g," 6 nueto.a rv."7 MECHAMICAL SEISHIC CATAGORYLIMSTR. 5*"7 SUPPORT DETAll t sWw SE N [ hE Ro,7LANT g _,0.. %1, ,-u o r Ib^7' I7' W DE crIcato s E Y TE ?. ...$.' WT2 i.' l... .., l l..- l.m l.... l.... l..,1 n. l l -=[" ll SEE ABOVE r... r

s//7;' Jkte T oAA l

l-- j-- l. l i i i i i { PIPE SUPPORT CALCULATION SHEET Sheet _ */ of J/O Cafe. l.D. 47AOSO J-I ' l $l I I l --- - - -- M hJ 9-e a,,, t c t Project. Prepared by ' ().' N AH Date '7 9 W4 7 Checked by ' &W ' Date 9/tf/g') l REFE'RENCES

SUBJECT:

.Pugeo c s : sucasrs rvTson or F i n e.t awsc waso /" Ptscs OF Sykers t</ 2 40 esrusso ctirevno t Sui FAcn of Ent/stl. S/Z 2 7F84 SYS543 R EF. 4*7A O S I S &.52.l l5.5 D L A k/Ir-sG C. ~ . k-I l ] l TS 2nx %. 04- ~ '_._j n 3r3xl4 g l... l f, I g g

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l-1 s ....i a SEC.T.1ON 6 S. t. .._ P A R T I A L. ELEV. VI EW. (au: oce,. so. 4 iAoJi-as tu ) EVnL. U AT~l CN.:. ON. 47AOS/ TYPICA L PMWl H 4 S. TME IJe w Beru22N Tv86 57E645.of san 16 $/25 AS S/0WN.. A40V6 /$ CNovsN. Af. SQUn#5.. tJSL D. Ym.C /.C w/ ON c. 10EtO S y m 8 0 4.. / 7~ 5;ve ut p. 13E.. F4/r*E ssvsc. ///54D Sym804. YH2 EFFECT/t/6 fM20/fr Of $9UA$6. M tD. j,s EGML 70 THE 7Mit/tA/EJ's of 7/ss.svnt /Wnr t.*. 4l?, epppt. 7 0 7?? C. w M t 171/C/tp u J". OF 7t/GE. $ T C C 4,l. T // 8 E F F 6 C 7I V C 7~H/On7 -j=ott_. fintes ec</cl. t e s t o. t.r se s s o S. n un t.- To _. P12...tr7/As/mpm.: IyM&t. TH / fit.v Gst o F 7t/G S'.'S Y2.2 L.. J SrL ) /* $ D W o. VOL.. 5.,.. C 2,. CT.r. 7 / C, _.... ..L.l. O. ; L._ / .. '... SCU AllC to St o.. SymGoL t*t)d /.!E '. /<b4ACEO.4y A s1:Ri.Q n.eep e ers s._ wnio : syxeoA..zws.cwin cinoc is anven su note 69 on ' pus.; 4740So-25 l i l I I I ede.w

m m a. cru ots....n,

i i i i g; i i j i i i i i epw

. sac R oc M lo jo. lm 4 .itzytri SEQUOYAH NUCLEAR PLANT ns mggy A a,Aoso-2s I es o g.,gg,,. o., _, SEQll0YAH ... _ 6 4,w'er/r>_ .m, N(ICLEAlt PLMT 81 ~ sv G d f 1/to/ TT gygy;j pggg,g,g < sz ime a ttritsts t% (St5tKi h tilitst3@ Tit $ CE Am, CALCS. FOR INFORp310N OHl.Y e i ee m.,. e en = * * * . p m e aume=

e i ) 1 ATTACHMENT 2 (T25 870708 869) (U10 870706 001) (S03 870420 852) ^ (T25 870817 982) (U10 870813 002) (U10 880218 001) I o e 5

,, T V A,f,4 (05-9-45) (Op wA5 45) UNITED STATES GOVEltN31E iT 25 Memorandum 8707o3 3gg TENNECSEE VALLEY AUTHORITY TO H. L. Abercrombie, Site Director, O&PS-4, ONP, Sequoyah Nuclear Plant FROM W. R. Brown, Jr., Program Manager, Employee Concerns Task Group, ONP, Watts Bar Nuclear Plant DATE gr[3.r g g

SUBJECT:

SEQUOYAlf NUCLEAR PLANT (SQN) - EMPLOYEE CONCERNS TASK GROUP CORRECTIVE ACTION TRACXING DOCUMENTS (CATD) 201.03-SQN

CLOSE0UT VERIFICATION - ENGINEERING CATEGORY

Reference:

Your memorandum to me dated April 22, 1987 (S03 870420 852) (copy. attached) We have completed our review of youu-implementation of corrective actions required to resolve the problem noted by CATD 201.03-SQN-01 (copies attached). We have found this action acceptable in resolving the problem for SQN Unit 2 restart. This is a partial closure. This CATD will remain open until all corrective action is

complete, r

C nM g.R. Brown,Jr. pp6 GRM:XDH Attachments cc (Attachnents): RIMS, MR 4N 72A-C R. C. Denney, DSC-P, Sequoyah J. L. McAnally A108 IOB, Watts Bar G. R. McNutt, ECTG Bldg., ONP, Watts Bar 5772T ... stnuorm mvaun u t .- n q-Srff OuECTG3's Outt w.;*..:

R t L'&J g

av 11?4 .-..*****'t h r1 ~ }' i I. I } $ I i g i [g. r 3 ',7 J '- P E y v pi ..q Y'b 7 >C.WTC l -I -..i. ? ( Ofb. LC' G-.{ - t l ( ( [..... ..-.-.,.a-- 9 ....... Ase ' =.b o \\ n.... t ' c c.. : n.

o. n

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$10 8.7,0706 001 Bechtel Western Powe' Corporation r ,C Engneers - Constructors Fifty Beale Street San Francisco, Cahfornia Ma# Address: PO Box 39% San Frarosca CA 94119 July 2, 1987 BLT-258 Mr. George R. McNutt Engineering CEG-H Tennessee Valley Authority Knoxville, Tennessee 37902 Subjedt: Watts Bar Nuclear Plant Emplo9ee Concerns Evaluation Program Tennessee Valley Authority Job No. 16985-026 CATD 201 03-SQN 01 ?

Dear Mr. McNutt:

In accordance with ECTG procedure ECTG C.3, Revision 4, and your memo dated 06/26/87, attached is the "ECTG Verification Closeout Checklist" for the subject CATDs. Very truly yours,

w,

=m G. L. Parkinson Project Manager GLP/gd Attachment 29930 7/ 6/87---GRM: R}N cc: RIMS, MR 4N 72A-C D. T. Clift, 9-162 SB-K R. Denny, DSC-E SQN l b 12514 (496) ,a . c.. w - + s

~ ~ ECTG C.3 Attachment E Page 1 of 4 Revision 4 l ECTG VERIFICATION CLOSE00T CHECKLIST j CATO No. 20103 SQN 01 1 This CATD was designated: C/A completion notification Memorandum RIMS No. S03 870420 852 [>l QR CAQ No. Not Required []NQR M Partial Closure ~ This memorandum denoted CATO: []CompleteClosure .. - q

SUMMARY

C/A elements reviewed i

((Walkdowndocuments - [>< Document _ and/or drawing reviews [@. Procedure and/or drawing revision Training records ~ [; Examination or test results [; Modification (ECN) documents c [. Engineering analysis y i;,Other-specify New program (s) [] Repair or replacement records DISCUSSION: C Sequoyah Engineering Procedure SQEP-29, R3, establishes the requirements for developing a Design Basis Document (080) for SQN. The Restart Design Basis Document (RDBD) is the 080 which contains design criteria for safety-related systems or portions of systems identified by SQN-0SG7-048. It contains, as a minimum, a list of . general and system design criteria for the site, plant, and structures . required to support safe shutdown. Currently, only the RDBD for SQN unit 2-has been issued. Therefore, verification of the corrective actions at this time is limited to SQN. unit 2. Corrective actions for the SQN unit 1 RDBD will be verified when they have been completed. The following verification actions have been taken for SQN unit 2: 1. Reviewed Sequoyah Engineering Procedure SQEP-29, R3 (Reference 1), and verified that it contained requirements for the preparation of the Restart Design Basis Document (RD00) and that it listed design criteria (DCs) prepared or referenced for the restart of SQN unit 2. M Discussion continued ~

== Conclusions:== Corrective actions were adequate M Yes [] No []N/A Yes No M ((1Deficienciesadequatelyscoped ( M [ Deficiencies corrected - on completion of EA action items M [] Actions required to prevent recurrence mplete $!l cs-f. - lL// 7 7 " Signature Date

ECTG C.3 Attachment E Page 2 of 4 C Revision 4 ECTG VERIFICATION CLOSE0VT CHECKLIST CATO No, y103 SQN 01 Initials 4/4-~ Date 7/4/#7 DISCUSSION: (Continued) 2. Reviewed the RDBD for' SQN unit 2, R1 (Reference 2), and verified that the DCs listed in SQEP-29,'.R3, are contained in this document. 3. Reviewed a sampling of 13 DCs and verified that each has been ~ checked, reviewed, and approved, and either a list of commitments / requirements (C/Rs) has been prepared or the branch chief has ~ reviewed C/Rs for inclusion into general design criteria for the restarr of SQN unit 2. (Proper incorporation of C/Rs into the OCs will be verified in CATO 20101 SQN 01.) The sampled DCs were: SQN-DC-V-1.0, R0 (CEB) SQN-0C-V-2.15, R0 (NEB) SQN-DC-V-10.5, R1 (EEB) SQN-DC-V-2.17, R0 (NEB SQN-0C-V-11.3, RS (EEB) SQN-0C-V-9.0, R0 (NEB)) SQN-0C-V-11.4.1, R2 (EEB) SQN-0C-V-13.9.6, R0 (NEB) C SQN-DC-V-4.1.1,R0(MEB) SQN-DC-V-26.2, R0 (NEB) SQN-0C-V-ll.8, R1 (MEB) SQN-0C-V-27.5, R0 (NEB) SQN-DC-V-13.9.9,R0(MEB) 4. The Engineering Assurance (EA) involvement in the review of DCs as part of the EA Oversight Review of the SQN Design Baseline and Verification Program was substantiated by review of the following documents. The EA Program Plan for conducting the Oversight Review (Reference 3) was reviewed. ' A summary report (Reference 4) of the results of the EA Oversight Review was also reviewed. This report ' documented 351 action items for engineering resolution. Supplemental information relating to EA review of DCs (Reference 5) was obtained, which included the list of DCs reviewed and the method used to verify tiie accuracy and completeness of C/Rs incorporated in to the DCs. Fifteen DCs, a 36.6% sampling of the DCs contained in the RDBD, were reviewed by EA. Eight action items related to design criteria problems identified by EA for engineering resolution were reviewed and the response documents for the closecut of these items were reviewed. The action items reviewed were C28, E22, E25, E28, E29, E30, E39, and N28. S. Reviewed NRC inspection reports on the Design Baseline and Verif_ication Program (DBVP) (References 6, 7, 8, and 9). Several observations on problems with the design criteria documentt.<ere identified by the NRC. These identified observations were f documented as open items which require resolution by TVA nrior to ~ (_ the restart of SQN unit 2. TVA responses to,the NRC open items -') 04 Discussion continued 23030-4

ECTG C03 Attachment E Page 3 of 4 Revision 4 ECTG VERIFICATION CLOSE0UT CHECKLIST i CATO NO. 20103 SON 01 Initials /cT Date 7/.2//7 i DISCUSSION: (Continued) (References 10 and 11-) and the draft NRC Safety Evaluation Report ~ on the DBVP (Reference 12) were ' reviewed. The DBVP for the development of the 0B0 was found to have been implemented, although several items identified by the NRC require resolution. 6. Examined a TVA memorandum (Reference 13), which delineated specific action items to'_ resolve EA and NRC concerns related to design criterie preparation. This document indicated that these acti'on items have been completed and the concerns have been resolved (Reference 14). However, the NRC has not yet completed evaluation of the responses and some items currently remain open. Summary ( On the has'is of the above verification performed, the corrective actions taken were found to be adequate to provide the 080 for restart of SQN unit 2. However, the corrective rtions have not all been closed at the present time. Some open items from NRC inspections have not been closed. These items will be evaluated by the HRC for closure prior to the restart of SQN unit 2; therefore, the corrective actions for this CATO can be considered to be completed for the restart of SQN unit 2, References

1. Sequoyah Engineering Procedure SQEP-29, R3, "Procedure for Preparing the Design Basis Document for Sequoyah Nuclear Plant,"

(02/13/87)

2. "Restart Design Basis Document, Sequoyah Nuclear Piant - Unit 2,"

R1,(03/19/87)

3. "Program Plan for the Engineering Assurance Independent Oversight Review for the Sequoyah Nuclear Plant Design Baseline and Verification Program," R1, (02/23/87)

4. Summary Report, Action Items Originated by the Engineering Assurance Independent Oversight Review Team for the Sequoyan Nuclear Plant Design Baseline and Verification Program (03/16/87).

( M Discussion continued 23030-4

ECTG C.3 Attachment E Page 4 of 4 Revision 4 ECTG VERIFICATION CLOSE0VT CHECKLIST CATO N0. 20103 SON 01 Initials AT' Date 7/2/#7 DISCUSSION: (Continued)

5. TVA memo from J. W. von Weisenstein to G. McNutt, "Information on Closeout Verification of CATO 20103 SQN 01," (04/24/87) (RFI SQN-791)

6. Letter from J. M. Taylor, NRC, to S. A. White, TVA, "Report Nos.

50-327/86-38 and 50-328/86-38," (09/15/86)

7. Letter from J. M. Taylor, NRC, to C. C. Mason, TVA, "Report Nos.

50-327/86-45 and 50-328/86-45," (10/31/86) t

8. Letter from J. M. Taylor, NRC, to S. A. White, TVA, "Report Nos.

50-327/86-55 and 50-328/86-55," (02/03/87)

9. Letter'from B. J. Youngblood, NRC, to S. A. White, TVA, "Transmittal of Oraf t Safety Evaluation Report on the Design C

Baseline Verification Program," (01/20/87)

10. Letter from J. A. Domer, TVA, to the NRC, "Sequoyah Nuclear Plant -

NRC Inspection and Enforcement Report Numbers 50-327/86-55 and 50-328/86-55," [L44 870422 802], (04/22/87)

11. Letter from J. A. Domer, TVA, to the NRC, "Sequoyah Nuclear Plant -

Response to Items from Inspection Report Nos. 50-327, -328/86-38 and 50-327, -328/86-45," [L44 870203 806], (02/03/87)

12. Letter from R. Gridley, TVA, to 8. J. Youngblood, NRC, "Sequoyah Nuclear Plant - Oraf t Safety Evaluation Report - Design Baseline and Verification Program," [L44 870227 805], (02/27/87)

13. TVA memo from J. F. Cox to Sequoyah Engineering Project File, "Sequoyah Nuclear Plant - Design Baseline and Verification Program (DB & VP) to Support Restart," [825 860911012], (09/11/86)

) )

14. TVA memo from J. F. Cox to Sequoyah Engineering Project File, "Sequoyah Nuclear Plant (SQN) - Design Baseline and Verification Program (DBVP) to Suppert Restart," [825 861203 019], (12/03/86)

~ - END - 23030-4

I?NITED STATES GOVERN 3!ENT S08 870420 85o ^# MentorancllLMt C TENNESSEE VALLEY AUTHORITY TO W. R'. Brown, Jr., Program Manager, Employee Concerns Task Group, ONP, Watts Bar Nuclear Plant I'R0li H. L. Abercrombie, Site Director, O&PS-4, Sequoyah Nuclear Plant DATE April 22, 1987 SU nJ ECT' SEQUOYAH NUCLEAR PLANT (SQN) - EMPLOYEE CONCERNS TASK GROUP (ECTG) REPORT 201.03 SQN - UNIT 2 RESTART CORRECTI,VE ACTION PLAN (CAP) IMPLEMENTATION

Reference:

Your memorandum to me dated January 12, 1987, "Sequoyah Nuclear Plant (SQN) - Employee Concerns Task Group (ECTG) Element Reports - Engineering Category - Concurrence With Corrective Action Plan (CAP)" (T25 870112 892) I acknowledge receipt. of your concurrence with my CAP on Element Report 201.03 SQN (see above reference). The unit 2 restart corrective action for this report has been completed. Attached is the site line organization corrective action completion document for your use. You may proceed with your completion verification ( of this corrective action. Please sign the ECTG closure space below item la on the CAP tracking checklist and return the CAP tracking checklist. I ^ g H. L. Abercrombie RCD:JDS:JB:EAM Attachment RECElVEG) RIMS, MR 4N 72A-C (B25 '870417 017) cc: J. L. McAnally, A108 IOB, Watts Bar (Attachment) [fg,Q L 'g 0256D Erec.,n ters:..:.Tata i amun ':.'Im. { I ik a u m n,-a Wm t

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,A x l YE ~ ['4 l H t Idh o '.. l4_ 'A5 i l l s Me t. ,lk M i / I h ! )S ggt '.,( hHa.N. 6 Lee,6.. ' i ' se 1

Standard Practice s Page 8 p SQA166 Revision 8 Attachment A Page 1 of 2 Corrective Action Plan of Employee Concern Investigatio Tracking Checklist n ECTG Report /CATD Number 'lOl# 3 SGA) Cffd Lead Organization Responsible for Corrective Action Plan 2C/-(? 3 5'ON c '. ~ Initiation Date

~27 P'4
A/ 6.

~ CORRECTIVE ACTICN PLAN (CAP)

1. Does this report require corrective action?

Yes __ ! (If yes, describe corrective action to be taken No r,J ActMasr.<et A.wr rys Dwcd Airsu re Vsonesru / An', if co, provide justificat .4Hre/Arra D///CA/ /?wr thw.as ne w s ~ A d,> fordr/nsa 3.</ '$fff-ze /?C f/Ar/xr><r#9rNr brrMM C&M#s# 7Mor A// ' _ fst//fdMh nr #nnur , AfLW/,h, w>s AL M_ //fNf/4/fh lN AP/u&fd/A $hd TO //fAM)# 2. Identify any similar item / instances and corrective action t k Al/*All a en.

4. Does this report contain findings that are conditions Yes tro _

as defined by AI-12 or NEP 9.17 adverse to cualitv (CAJ)

5. IP a CAQ con $ltion exists, what CAQ document was initiated?

~ YES _ No v AfD1// 6

. Which site" section/ organization is responsible for corrective action

~ l ~ /)A f

7. Is corrective action required for restart?.

8. P2 zone number for restart corrective action?(This determina Yes V

No ~ .)

9. Estimate completion date for correction action. Zone _ (/f6 8 Completed By h d4/ I Approved By

' [/j'/i%kl(4V Date ja - s"- g(, ECTG Concurrence (/%s A//'4f/f~ Date __ /2 ft, ^ / Date ts - /2-> 7 ~ ) / 0206S/mit s

Standard Practice Page 9 SQA166 Revision 8 ( ATTAClefDIT A Page 2 of 2 CAP CI.CSURE

10. Was your corrective action initiated and completed in accordance yit ep 17

11. If step 10 is no, describe the corrective action taken.

Yes V No JW

12. Is the corrective action implementation complete?

13. Is the corrective taction documentation closed?

Yes (44 h No

14. What documents warp used p_/p i,mplement' he corrective actio Yes / tt1 No j

Cc=gleted By: f./11 5/ /E f tM & Date 04-//f/f*7 Veci!ied By: Q ~-_ X f2(. ECTG Closure:M b<O tac-M Date Y'//'sl'y y Date 7 7-J7 f L{ n'. '2 Wa> O d h ty (Step flo.) I Description N l l I C 0206S/olt

CATD No. 201.03-SQN-01 ( ATTACHMENT 1 PAGE 1 0F 1 CLOSURE ITEM No.14 0F ATTACHMENT A The document used to implement the corrective action is the Restart Design Basis Document ( RDBD). The corrective action for each unit of SQN will be completed as the applicable RDBD is issued. The RDBD is prepared in accordance wir.h Sequoyah Engineering Procedure SQEP-29 "Procedure for Preparing the Design Basis Document for. Sequoyah Nuclear Plant" and is a listing of the upper tier design documentatJon for the safety-related systems or portions of systems identified'by Calculations SQN-OSC7-048. The RDBD contains es a minimum, a listing of those design criteria which have been reviewed, revised, or generated as required to address the commitments and requirements for restart. After restart, any existing, new, or revised design criteria required to capture the design basis shall be incorporated into the DBD prior to the use of any design document and will be maintained throughout the life of the plant. The RDBD f or unit 2 at SQN (B28 861210 006) has been issued and a general revision (revision 1) has also been issued (B25 870324 052). The RDBD for unit 1 at SQN is projected to be issued by July 1,1987. (: s DE02;JB7100.09 SQEP Apr. 13, 1987 l 1

N ,, >A TVA 44 tes-9 65) toAwAS a 5) UNWED STATES GOVERNMENT T 2 5 87 0 817 982

' Memorandum

(. TENNESSEE VALLEY AUTHORITY TO H. L. Abercrombie, Site Director, O&PS-4, ONP, Sequoyah Nuclear Plant FROM W. R. Brown, Jr., Program Manager Employee Concerns Task Group, ONP, Watts Bar Nuclear Plant DATE g617}337

SUBJECT:

SEQUOYAH NUCLEAR PLANT (SQN) - EMPLOYEE CONCERNS TASK CORRECTIVE ACTION TRACKING DOCUMENT (CATD) - CLOSEOUT VERIF ENGINEERING CATEGORY

Reference:

Your memorandum to me' dated March 16, 1987 (S03 870313 803) (copy attached) We have comrleted our review of your implementation of corrective actions required to resolve the problems noted by CATD 22800-SQN-02 and 03 (c.opies attached). We have found this action acceptable'in resolving the problem. This is a partial closecut for CATD 22800-SQN-02 and it will remain open. CATD 22800-SQN-03 is a complete closure and it will be closed. August 11, 1987 (U10 870813 002). See Bechtel letter dated MY ' f4 W.ef. Brown, Jr. ~ GRM:GB Attachments cc (Attachments): RIMS, MR AN 72A-C ' R. C. Denney, DSC-P, Sequoyah Phil Brackins, FSB, ONP, Watts har G. R. McNutt, ECTG Bldg. ONP, Watts Bar T. C. Price, 5-212 SB-K q%uovorm'gr i m O 1 9'87 i ~ V e t. h 3 $a W 6281T 4 m p m w

\\ U10 870813 002 Bechtel Western Power Corporation Enoncers - Constructors Fdty Beate Street San Frarcsco, CaMornia uu w,u: po so, as s.n r,-a c4 smo August 11, 1987 BLT-416 Mr. George R. McNutt Engineering CEG-H Tennessee Valley Authority Knoxville, Tennessee 37902

Subject:

Watts Bar Nuclear Plant Employee Concerns Evaluation Program Tennessee Valley Authority Job No. 16985-026 _CATO 228 00 SON 02, 03 Verification o

Dear Mr. McNutt:

In accordance with ECTG procedure ECTG C.3, Revision 5, attached is the "ECTG Verification Closeout Checklist" for the subject CATO. plant restart items have been closed; post-restart activities are still open.Pleas This letter and its attachment supersede BLT-378 (07/31/87) and its attachment. Very tr your h G. L P i on Proj Man er GLP/gd Attachment 3295D ? 8/13/87---GRM:RMW cc: RIMS, MR 4N 72A-C R. Denny, DSC-E SQN N. A. Liakonis W9 B85 C-K { 1M14 (E98)

t. ECTG C.3 Attachment E Page~l of 7 Revision 4 ( ECTG VERIFICATION CLOSE0VT CHECKLIST I l CATD No. 228 00 SON 02, 03 This CATD was designated: See discussion C/A completion notification Memorandum RIMS No. 503 870313 803 i " QR CAQ No. 1 NQR This memorandum denoted CATO: M Partial Closure []CompleteClosure

SUMMARY

C/A elements reviewed

'i Walkdown documents [TrainingrecordsProcedure and/or dra Document and/or drawing reviews Examination or test results J,l Modification (ECN) documents Engineering analysis i Newprogram(s) [] Repair or replacement records NOther-confirmatoryreevaluation procram 1. DISCUSSION: p ( The documents'and calculations reviewed are listed in Section 2 and the references are found in Section 3. j Unistrut P-2558 clamos (CATO 228 00 SON 02) From review of calculations / documents a., c., d., and J., the , verifier noted TVA Singleton Lab had performed new test series on Unistrut P-2558 type clamps and has established new allowable loads for Unistrut P-2558 series clamps (calculation a. and also document j.). Calculations a., c., and d. also indicate that i i based on a recent testing, the existing allowable loads for so,me of the clamps'have to be reduced. However, the calculations do not clearly indicate what actions TVA took to review the adequacy of the existing designs and installed conduit supports in the i light of the reduced clamp allowable loads. In IOM 1617 M Continued 1

== Conclusions:== ~ Corrective actions were adequate M Yes* [ No N/A

PlantrestartitemsareCLOSED,butpost-restartactiv]tiesa['r]eOPEN i

i (seediscussion) Yes No N/A ? [] Deficiencies adecuately scoped L Deficiencies corrected i {i [] Actions required to prevent recurrence complete i 1:.4 k 2-12-87 { Signature btM I'/# Date 32570 ^ d

5* ECTG C.3 Attachment E Page 2 of 7 Revision 4 ( ECTG VERIFICATION CLOSEQUT CHECKLIST CATO NO. 228 00 SON 02, 03 InitialsJh_ Date $[//[87 DISCUSSION: (C:ctinued) (08/04/87; reference h.) as noted below, TVA clarified the pre-restart criteria u' sed in evaluatin~g the effect on the acceptability of the existing installed conduit clamps. On the basis of a discussion between TVA and the verifier,on 08/04/87 (IOM 1617; reference h.), TVA indicated that new clamp allowable loads have been established for Unistrut P-2558 series clamos that are lower than the loads originally used for conduit supports utilizing these clamps. Evaluation of the effect on the acceptability of previously installed conduits could not be established on a generic basis, as such potential loads would exc' eed the nt.d allowable loads. Thus, TVA opted to determine that the existing conduit supports were "fit for service" as a plant C pre-restart criterion and would determine that they met design criteria as a post-restart activity. The "fit for service" criterion involved was be. sed on very conservative conduit span assumptions, thus maximizing loading on the clamps during seismic conditions and utilizing a conservative straight line interaction equation to demonstrate that there is an adequate factor of safety i against ultimate strength. Thus, calculation a. demonstrates that none of the clamps will actually "fail" due to a reduction in clamp capacities. ' This approach is ' acceptable to the verifier for plant restart. As a result of, or concurrent with, the long-term TVA determined that other anomalies existed in the conduit supports. Accordingly, CAQR SQT 820626 (document h.) was generated to close all remaining conduit support activities. CAQR also covers the problem stated in CAQR SQT 820606 (document This g.) that new test data on Unistrut P-2558 clamps do not support existing SQN PSDM allowables for loading in the axial direction, resulting in factors of safety lower than intended for some support designs using P-2558 clamps. 4* {. M Discussion continued 32570 e

ECTG C.3 Attachment E Page 3 of 7 Revision 4 ( ECTG VERIFICATION CLOSE0VT CHECKLIST CATD NO. 228 00 SON 02, 03 Initials M Date %fH[87 DISCUSSION: (Continued) The verifier found acceptable the new test data on Unistrut P-2558 series clamps and the established new a'llowable loads on the clamps. The verifier judged that the "fit for service" approach is adequate for plant restart because of global conservatism applied in calculation a. However, as the "fit for service" approach does not comply to design basis, the following post-restart activities are required on a long-term basis: Confirm adequacy of the Unistrut P-2558 series clamps in the o existing designs and installed conduit supports, and provide , fixes as required. Identify a minimum factor of safety of the Unistrut P-2558 o ( type clamps in tne existing designs and installed conduit supports using new allowable loads and utilizing an interaction equation. The verifier also reviewed CAQR SQT 820626, R1, and the plan for resolution of the CAQR (documents h. and 1.). The verifier reviewed in detail the portion of the description of condition in the CAQR related to the Unistrut P-2558 series, clamp, the remedial corrective action, and the proposed recurrence control actions. - The plan for resolution of CAQR SQT 820626 (document i.) was also reviewed in detail for its purpose, scope, assessment assumptions, and methodology. The verifier found that the portion of the scope of CAQR SQT 820626 related to the P-2558 series clamp, the remedial corrective action, the proposed recurrence control actions, and the resolution plan are satisfactory and acceptable. Therefore, the verifier determined that (1) the specific corrective action commitments and requireT,ents were completed. (2) the corrective actions taken for plant restart items are adequate, and (3) post. restart activities on a long-term basis are required to confirm the adequacy of, and identify a_ minimum factor of safety for, the existing and installed Unistrut P-2558 series' conduit clamps. M Discussion continued t 32570

7 3 ECTG'C.3 Attachment E Page 4 of 7 Revision;4 ( ECTG VERIFICATION CLOSE00T CHECKLIST i CATD NO. 228 00 SON 02, 03 Initials h Date lifS7 i DISCUSSION: (Continued). Double Cantilevered Conduit Hanaers -(Drawino 47A056-668 t CATO 22800 SON 03) Calculation b. evaluated the installation of double cantilevered s conduit hanger as shown on. drawing 47A056-668 (optional support detail to drawing 47A056-66). SQN FCR 2598 implemented the ~; 47A056-668 typical support on 8/13/84 and later a note was added to this drawing stooping the use of tnis typical support'on 11/22/85. SQN modification group maintained a typical support log i book and identified 355 "_47A056-66" typical conduit supports as possibly being installed.during this time frame (08/13/84 to 11/22/85). An initial walkdown was performed by an outside 1 [ 1 con, tractor to identify these supports. Out of the 355 supports l possibly being installed, the contractor determined 11 of the supports were deleted, eight supports were inaccessible due to ( high heat and high radiation, one support was not a "47A056-66" i l typical, 54 supports were not located, and of the 281 supports identified, none of them used the optional double cantilevered t The 54 supports ths.c the contractor were unable to } hanger detail. i locate were then walked down by syn modification group. Out of the 54 supports, the modification group found 3 supports could not . be located, 43 were identified as not using the hanger detail of l drawing 47A056-66B and 8 were determined by reviewing FCRs as also i not using the optional double cantilevered hanger detail. TVA concluded that the results of these walkdowns gave a high level of i confidence that the optional double cantilevered conduit hanger detail shown on drawing 47A056-663 or 2. was not used in SQN units I l i The verifier found the calculation satisfactory and acceptable ) with the one anomaly noted below. S The verifier noted that Yariance 56-66-A44 for support 2-068-10192 (FCR 2803, sheet 64 of - j calculation b.) appeared to be a double cantilevered hanger. j variance showed a cantilevered P1000 Unistrut connected The perpendicular to an existing cantilevered vertical P1000 Unistrut. This support was very similar to typical 47A056-668 I hanger. However, a rev.iew of calculation f. revealed that the 1 DQ Discussion continued 32570 _-=.

1 ECTG C.3 Attachment E Page 5 of 7 Revision, ( ECTG VERIFICATION CLOSE0VT CHECKLIST CATO N0. 228 00 SON 02, 03 Initials _ h _ Date_9fft[$') (Continued) support is not a "doubis Wastilever" as implied by Variance 56-66-A44 and SQ-FCR-2808. Based on a TVA walkdown and as stated in Section 1.0 of this calculation, the vertical Unistrut is welded at both ends to the cross-bracing of panel 2-M-4.

Thus, the support is a single cantilever.

The actions taken by TVA for this support and the double cantilever support topic are adequate. Thus, the corrective action plan implemented all required actions for CATO 228 00 SQN 03 including those to prevent recurrence for both SQN units 1 and 2. Therefore, the verifier determined that (1) the specific corrective action commitments and requirements were completed for CATD 228 00 SQN 03 and (?) the corrective actions taken are adequate. 2. DOCUMENTS AND CALCULATIONS REVIEWE0 The following documents / calculations associated with the corrective action for the subject CATDs were reviewed: Emoloyee Concern Element 228.00 P-2558 Clamps Calculation , a. Package, RO, [B25 870228 815); R1, [825 870519 802]; R2, (B25870706801] b. Employee Concern Element 228.00 Typical 47A056-663 Calculation Package, R0, (825 870303 803] TVA memo from R. C. Weir to R. O. Barnett,."Secuoyah Nuclear c. Plant - Axial load Testina of Unistrut P-2558 Clamps," 01/13/87,(846870109001. SQN Axial Load Capacity Testing of Unistrut P-2558 clamps d. DNE Calculation, "Unistrut P-2558 Test Evaluation," R1, (841 870602 001) EN DES Calculation ""Variance 47A056-66-A44," RO, e. [825850423411) L M Discussion continued 32570

ECTG C.3 Attachment E Page 6 of 7 Revision 4 ( ECTG VERIFICATION CLOSE0VT CHECKLIST CATD NO. 228 00 SON 02, 03 Initials _ M Date_%tif6'l (Continued) f. DNE Calculation "Seismic ~ Analysis of Recorder Support Structure,"R0,[825870618800] g. CAQR SQT 820606, RO,-[S13 870414 814] h. CAQR SQT 820626, RO, [S13 870414 836]; R1, [S13 870430,833] i. TVA memo from C. N. Johnson to R. O. Barnett, "Sequoyah Nuclear Plant - CAQR SQT 05/22/87,[825870605013]870626 R1 - Plan for Resolution," Sequoyah Nuclear Plant Unit 2 Conduit Restart Evaluation Program plan (05/08/87) (

j. QlR CEB-87-099 "Unistrut P-2558 Clamp Allowable Load Capacities,"[841870710250]

3. REFERENCES The following references are related to the corrective action for , the subject CATDs: Letter from G. L. Parkinson, Bechtel, to G. R. McNutt, TVA, s a. BLT-225 (05/22/87) b. Telephone ~ call from G. R. McNutt et al., TVA to C. W. Jordan et al., Bechtel, IOM 1061 (05/29/87) Telephone call from R. C. Denney et al., TVA to N. G. Shah c. et al., Bechtel, IOM 1094 (06/03/87) d. Telephone call from J. D. Swearingen et al., TVA to J. W. 8enkert, Bechtel, IOM 1329(06/24/87) Telephone call from R. C. Denney et al., TVA to J. W. Benkert, e. Bechtel IOM 1367 (06/30/87) ? L $0Discussioncontinued 32570 i

ECTG C.3 Attachment E Page 7 of 7 Revision 4 ( ECTG VERIFICATION CLOSE0VT CHECKLIST CATD NO. _228 00 SON 02, 03 Initials M DateSfil[$ t (Continued) f. Telephone call from A. M. Matayas, Bechtel, to S. K. Cook et al., TVA, IOM 1462 (07/10/87)

9. ' Telephone call from G. R. McNutt, TVA, to J. W. Benkert, Bechtel, IOM 1605 (08/03/87)

h. -Telephone call from G. R. McNutt et al., TVA, to J. W.

Benkert, Bechtel, IOM 1617 (08/04/87) - END - 1 i i i k []Discussioncontinued 1 32570 \\

PM6 /d of /7 ECTG C.3

~

Attachneet A Page 1 of 1 Revision 2 - A ECSP CottECTIVE Aetten Treetint Document (CATD) INfTIATION 1. Zariediate Corrective Action Required: % Yes O No 2. Stop Wort Reccessended: O Tes % No 3. CATD No. 2 2 600 -5G A/ - 0 2. a. IMITIATION DATE //[0/[64 5. RESPONS!!LE ORGANIZATION: TVM - b A/E 6. PROBLEM DESCRIPTION: W QR O WQR P/s CNE PAWC Y 57/f r$ BE TWEE A/ TVA RA/D f/MGLE TcA/ l)B UW/f 79u r CORP. '$ TES T bA TA P/96 5744P P2 STP -2 0 Cd UN/J TA'U T T O P 25'S"8 - 4 0 /w rHE SL/P-THRour, H DrPECr/CAF. LC4b-7ES/~ED _ RL L 3 WA8t E LonDC Fog YME UW/f 7Ruf P/PE S TRAP 7HE DM J/ coa / TA GUL A 7'ED /W SG A/ P s D /1 WARE BASED OA/ _ S/^/ A L E TON 2 7Er Y Rs s u r-- T.s. 7 PREPARED ST: NAME 4L W M

43__

MO 6\\ O_ ATTACH?!ENTS 8. CONCURRENCE: CEG-H#<V A DATE: ///o//B4 - M^e. sm 'ny fr-' DATE: i//- /r*P} 9. APPE0YAL: ECTG PROCFJ.M MGE. _ V _ DATE: _CORREC*!VE AC' TION 10. PROPCSED CORRECTIVE ACTION PLAN: 8# '7~4'E W^'6N// icd BY AffAf DJi/NDt W 6 ? 6~ W C, / 7. O ~/. 003 I 11. PROPOSED bT: iM

.* e

/ DIRECTOKn' K: /bufer r/0//M O ATTACHMENTS ~ 12. CONCUERENCE: CEC-H: _ /2,M ' / M _ _ DATE: /?/J.'r! ~ M/ SRP: _

' 4//&

DATE: /- 2/-* 7 ] l ECTG PROGRAM MGE: _ DATE: i ~ DATE: VERirtCATIcv AND CLOSEOUT 13.* Approved corrective actions have been verified as sati f t ripl ert.e n t e d. ~ s actorily SIGNATURE ~ L,) IITLE ~ DATE .g- .' ? --r

P446 / 70F/7 ECTG C.3 Attachment A

~

Page 1 of 1 Revision 2. A ECSP CotttCT M Aet t oo Tractt nt Document 15A1D.1 ,INITI& TION 1. Isenedlate Corrective Actica Required: % Yes D No 2. Stop Wort Recouriended: 0 Yes % No 3. CATD No. f EBM -f6N-03 //j /84 4 INITIATION DATE 5. RESPONSISLE QRGANIZATION: TV4-bNE /o/ 6. PROBLEM DESCRIPTION: g QR O WQR ~ CAL ful 4 7/OW OF bOU8L E CAWr/trysneb c o a.sc ur y M a gt"E R f' ORA W/M4 4 740 $~d = d6 8, 90 ) WA$ _ uMA VA /4 A 8L E SOR fyAL UA T/ OM 7ED H REv/S W a fsi O AT*1CHMENTS 7. PREPARED BY: N1.9 E 4 a W;r e L' A cb N() DATE: 5. CONCURRENCE: CEG-H #

5 em, rO* ' M C

_ e/es / 96 p / 9. APPROYAL: ICTG PROGRAM MGR. _ U ,DATE: _///A.n _,DATE: CORREC*IVE ACTION (., 10. PROPOSED CORRECT!YE ACTICN FlLN: _ M Twe** CA P ~ WHf MWot'/A/04/M 8?T g 6 pg. o g, oog // /4/ / 11. PROPCsED BY: DIRECTORfMGR:g//////Ut/(rt//w/' O ATTACHMENTS ~ i 12. CCNCURRENCE: DATE: CEG-H: _ EL+rw /2 n

C f-

~ DATE: /2/c ~7. >p.rf, ~ StP: / A//* ~ DATE: /.> 1 ' ECTG PROGRAM MGt: __ ~ VERIFfCATION AND closE0tf7 - DATE: ~ 13. Approved corrective actless have been verified as satisf actorill implemented. Ak _ hi$ $$$'Y A ,,c m m V'/ V7 --) mm Dm e , _o e b

e

' Standard Practice Page 8 ~, SQA166 Revision.8 Attachment A Page 1 of 2 Corrective Action Plan of Ex.ployee Concern Investigation Tracking Checklist ECTG Report /CATD Number 22T M S Q A./ M I O/'TD D# 0 " 'l@ N* A t'3 Cead Organization Responsible for Corrective Action Plan FN M Initiation Date

- 7 0 !'

CCRRECTIVE ACTICN PLAN (CAP) _/

1. Does this report require corrective action?

Yes V No b(If es, describe coyre,ctive action to be taken, if no, provide justification) xt n ih nuit a J rrl ed cri n f% c~rA!. 2 fl t'e P1 s~n k -4 D f n s i, b l I, e w r. ), e, r\\ ; r e is 4 s e d -rk/ r e n e 4n mnIe. t> ts t h -d w h o s.. u ; ~ a. tl u ti n n th ol 6 m. rt t b 4..v ;i 1-s..L a t;a- * -4 S er P'r5k 5 0 r n C 'h:e-tv.).Sp_ f t" %,&ie~h g y n n P W u 4, r # L' / 3 'i P D ie,1 s s8 -4i.* S n&te ro fll',1 L,, 4vate j.14. t e si il h 0 rf, L r... ., el d el 13. LJ.i,// e v n i t. a 4 r e n e, ch rqu. rl e i A 1. ft.,... 43.<J,A ik nH1i,r e L n su.-eh L e o L 4 to n,C f l h o_,M4 r' n.-

J/. h n be r I i vf i.i.,, A o a ~ ; J-sid //r' : A., /. /, 11 ri e 4 4 c,o, n 7 J. h ;

A s. 1, l' t I & 1 2. Identify any similar item /instarices' and dorrective action take'n. /\\/ FNC ~, 4 ts rei f, roi r,r 4, ri. e n vi rl n v. r J m ivi e n i A 'I a + f 6. c: 4o is e, r e 1 V i (q's n n. mi rd 1. 'l* f t n f n, t' I t. d. n t. ;o c: ri n n F L- F <'s i a n e i >'. I ?-

1. Il e e,

e 1 e r d, 2.* (R t 'h o r%~+ c ric r e n t l i s A 4-r t v.w h v. n d e h e t n)e a.

3. Will corrftetivel detion preclude rbcurrence of findings?

a s Yes y Np

4. Does this report contain findings that are conditions adverse to cualitv (C'Q)

] as defined by AI-12 or UEP 9.17 f

5. IP a CAQ condition exists, what CAQ document was initiated?YES _ _,_ Ho '_ V

6. Which site sectiqn/organisation is respqnsible/t for corrective action?

(l i u

i /

.5' y p r, p r -l-C' p fo -( ; p n I f

7. Is ci:irrective action' required for restart? i Ya*

V (This determination is-to'be made using Attachment C of N QA166.)

8. P2 zone number for restart corrective tion? Zone

/.6/4

9. Estimate completion dat for corre t' n a tion..T4 4

/. ').. /L/ V (f //, Completed By f.< / date / 7 // 2 b w 4/ Approved By sfiff/h //J,6 ' ' Date '/h 2 -- Q ct ECTG Concurrence % /2/ art'M Date A f/ F7 ~ of i (l 0206S/mit /

y,a\\ a +.u ,, MITED STATES GOVERNMENT 2V[6M10Tand MM1 $g Q Q1*5808 d TENNESSEE VALLEY AUTHORITY p To W. R. Brown, Jr., Program Manager Employee Concerns Tast Group, ONP, Sequoyah Nuclear Plant FROM H. L. Abercromble. Site Director O&PS-4 Sequoyah Nuclear Plant DATE March 16, 1937

SUBJECT:

SEQUOYAH NUCLEAR PLANT (SQN) - EMPLOYEE CONCERNS TASK G REPORT 228.00 SQN, R1 - ENGINEERING CATEGORY - CORRECTIVE ACTION PLAN l (CAP) IMPLEMENTATION

Reference:

Your memorandum to'me dated January 21, 1987, "Sequoyah Nuclear Plant (SQN) - Employee. Concerns Task Group (ECTG) Element Reports - Engineering Category - Concurrence with Corrective Action Plan (CAP)" (T25 870121955) l I acknowledge receipt of your concurrence with my CAP on Element Report 228.00 SQN, R1 (see above reference). The restart corrective action for this report has been completed. Attached is the site line organization corrective action completion document for your use. (...? ._.of.this_Jestart correction _ action.You may proceed with your completion verifica Please sign the ECTG concurrence space below item 14 on the CAP tracking checklist and return the CAP tracking checklist. hl$ $ 4 H. L. Abercrombie RCD:JDS:JB:PV Attachment RIMS, MR AN 72A C (B75 '870311 0397 ec: J. L. McAnally, ONP, A108 IOB, Watts dar (Attachment) 7,07 0740T Cme' w Cone.f.w TaA e Croup WB*d Me ar.um Rec 6, h M h W g_. t !5

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c Standard Practice Page 8 '(' N SQA166 Revision.8 Attachment A Page 1 of 2 t Corrective Action Plan of Employee Concern Investigation Tracking Checklist ECTG Report /CATD Number ~22000 SQA/ NI Iead Organization Responsible for Corrective Action Plan (PTD N ' 22f

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~ ' i CCRRECTIVE ACTICN PLAN (CAP)

1. Does this report require corrective action?

If res, describe ccyra}ctive action to be taken, if no V(r> r.,T Yes No d a h eu n s J rd n+ ret h , provide justific_ation Arr. s a+c d ~rkle d n n % >,\\ , a t.n c I, - t nP.1 c xM h '+*C Pa wd-4 0 i n sli n '.l.L un t h )~ r1 e e e + '. a> r i Cai e n a,o p 4 3 4..i. i. eF en n m A i.r e il 1. a .,c.fc; rf osL e e.... ' s. p rf n6 si fer L d.\\ ofe' e.,n isow n L e, r o 0 4' 4 L,, A m, i j o g, n (( k a f .C l., r e e t i e,4 e e. n beer m l i H e 4 ea In e l13r e i,n nu etra.ree.e,e.o e l e e y,, el e ru i f, oh frj rw 4 le n. v,.m m im 3, ) L.t. L 4, o *

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Identify any similar item / instances' and correceive action r4, 4-e r i s e. ne a l3 ; (- 4. /, i ' s 14 - take~n. /V 6Aff .- d r' nis M ti o n e o r e n n tf n.. r J rn e.a aniAofa-#nue4a h n a m. n h, f l.t a i n...le,J..)rt, c ( *,,;k 0 n*nY i~4 s~. ri., n s - e m c i a.# o u, r e L / to s rr1',.: sr 1% N S c. i.. e, # i- .1 1/ s i.~ rW r a int't e e A 4-e

3. Will corrpetived 4ction preclude rhcurrence of findings?

< v Ci:A-4.. nt'ic nseabrst.

4. Does this report contain findings that are conditions ad Yes g Np _

as defined by AI-12 or NEP 9.1? verse to cuality

5. IF a CAQ condition exists, what CAQ docum,ent was initi t d?

(CA YES No _ V _Q) ae

6. Which site secti n/ organization is responsible fo

' ll 5 ff I l /> b n t't $ S F A-f*! f M ?? corrective action? ,f

7. Is corrective action'rsquired for restart?

8. P2 sone nurr.ber for restart corrective (This determination is to Yes 1 No of,$QA166.)

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9. Estimate completion dat tion? Zone _

'f /E6 for coerect n action. _,7'A Al /S. / L/.Y (4 rj ~ Completed By rN / ' Approved By w, n/ lab /A,,6, " ' _ /!. 7. 2 / Date. 1

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Date _ A.2/ F7 Date '/2-3 O cr ~ 4 0206S/mit 8 ~ 1________-__

..i.- p y Standard' Practice I pag, 9 (~ SQA166 Revision 8 AITACHMD.'T A Page 2 of 2 CAP CLCSt.7RE

10. Was your corrective action initiated and completed in a ccordance with step 17

11. If step 10 is no, describe the corrective action taken Yes

/ No ~ 13s Is the corrective action documentation clos'ed?12. I Yes' V No

14. What documents were used to implement the, corrective actio ?Yes Completed By:

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+LW 4" "3 L 10- 880218 001 .I L Bechtel Western Power Company Ereneers - Cor*ructors Fdty Beale Street San Francisca Cahtorrva w Med Address: PO Bos 3961 Se Frvosca CA 94119 -l February 16, 1988 BLT-617 Mr'. George R. McNutt Engineering CEG-H Tennessee Valley Authority Knoxville, Tennessee 37902

Subject:

Watt's Bar Nuclear Plant Employee Concerns Evaluatt0.1 Program Tennessee Valley Authority Job No. 18968-804 CATO 223 03 SON 01 o

Reference:

.TC,CA-059 dated 01/13/88

Dear Mr. McNutt:

In accordance with ECTG procedure ECTG C.3, Revision 5, and the referenced letter, attached is the "ECTG Verification Closecut Checklist" for the subject CATD. Please note that only unit 2 plant restart items have been closed; post-restart activities are still open. This letter and its attachment supersede BLT-451 (08/26/87) and its attachment. Very truly yo'urs, W !G.L. Parkinson Project Manager GI.P/YKH ~ Attachment 02/18/88...CRM/JRB cc: RIMS, MR 4N 72A-C W.R. Brown, Jr.. ECTG Bldg.. WBNP R.C. Denney, DSC=E SQN / N.A. Liakonis. W9 B85 C-K ~ 4570e m et A utyg d e, emes pp.,r CorporaSon )

ECTG C.3 Attachment E Page 1 of 18 Revision 4 ECTG VERIFICATION CLOSE0VT CilECKLIST i CATO No. 223 03 SON 01 This CATD was designated: C/A completion notification Memorandum RIMS No. 503 871231 801 (X) QR CAQ No. See Olscussion (See Olscussion) This meinorandum denoted CATO: () NQR / (X) Partial Closure (SQN Unit 2 restart only) () Complete Closure

SUMMARY

C/A elements reviewed (X) Walkdown documents (X) Procedure and/or drawing revision (X) Document and/or drawing reviews [ ] Tral.ning records

[] Examination or test results (X) Modification (ECN) documents [X) Engineering analysis [ ] New program (s) () Repair or replacement records [X) Other - Special Maintenance Instruction OISCUSSION: Local Instrument Seismic Qualification A. DISCUSSION This verification closeout checklist supersedes the previous vertftcation checklist, dated 08/26/87, attached to BLT-451 (Reference C.3). The scope of this verification is limited to the completion of the corrective actions that were identified as unit 2 plant restart items in the subject CATO. The post-restart correc.tive actions l are not complete at present; hence, they are not addressed here. [x] Continued

== Conclusions:== Corrective actions were adequate (X) Yes* ( ) No [ ] N/A Unit 2 restart items are CLOSED, but postrestart activities are OPEN. Yes No N/A t (X) () ( ) Deficiencies adequately scoped [X) () ( ) Deficiencies corrected (X) [] [ ] Actions required to preven ~ 4 recurrence complete }. p & d Tvd ~ - 1.*l7-88 Signature Oate 4482D-R10 (02/17/88)

EdTGC.3 Attachment E Page 2 of 18 Revision 4 ECTG VERIFICATION CLOSEOUT CHECXLIST 4 CATO NO. 223 03 SON 01 Initials-M Date 2//7/#8 [ DISCUSSION: (Continued) The documents and calculations reviewed are listed in Section 8, "References," and the CATO-related correspondence are itemized in Section C. The problem description of subje t CATO was, "Installation of local field-mounted instruments need review and evaluation for seismic adequacy." TVA's Corrective Action Plan (CAP), as quoted from Element Report 223.3(8). Section 10, is as follows: "TVA will obtain a list of SQN Units 1 and 2 safety-related instruments from Sequoyah Critical Structure, Systems, and Components (CSSC) List. The list will be evaluated against TVA commitments made in Element Report 209.l(8)." "TVA will perform a drawing search and field inspection as well as a seismic qualification documentation search. This process will establish completeness of design, verify as-built installations, and ensure thFekistence~of'adequ' ate selsinTc' ~ qualification documentation of all Unit 2 safety-related instruments required for safe shutdown, to mitigate core damage, or to prevent releases in excess of 10CFR100 limits (fSAR Chapter 15 events) before Unit 2 restart. All other Unit 2 safety-related instruments and all Unit I safety-related , instruments will be subjected to the same document search and field inspection process after Unit 2 restart." "These post' Unit 2 restart activities will be performed before restart of Unit 1, as confirmed by TVA in 10M 980 (5/14/87: App. A, 7.w)." "The field inspection will be performed in accordance with procedures approved by Plant Operation Review Co'mmittee (PORC), or generic procedures that cover walkdowns, surveys, and field inspections, or procedures endorsed by Quality Assurance (QA). i A i condition adverse to quality report (CAQR) will be initiated and corrective actions will be provided for each incompletely documented or nonconforming installation. In addition. TVA indicated that other design change audits have resulted in the following actions that would preclude recurrence of the findings: M Discussion continued 44820-Ril (02/17/88) s]

EC'TG C.3 Attachment E Page 3 of 18 Revision 4 ECTG VERIFICATION CLOSEOUT CHECKLIST CATO NO. 223 03 SON 01 Initials M Date 2 h 7/88 f .g .t OISCUSSION: (Continued) r-TVA design interface document, CEB-0I 121.03, "Seismic o Design, Review and Control" (App. A, 6.e), has been recently revised (05/86) to refine and strengthen the seismic design review process to ensure adequate selsmic design qualification of instruments and their installations. SON ^ seismic review process of instruments is in accordance with CEB-DI 121.03. Revision 2 of Sequoyah Engineering Procedure SQEP-13 issued o

in 12/86 and current revision 3 (03/87; App. A. 5.11) require walkdowns before initiating an engineering change notice (ECN).

This procedure provides a mechanism to identify potential Installation problems in the design of mounting detail for future installation of instruments." This corrective action plan was submitted by TVA to the evaluation team via TCAB-094 (05/12/87). As this CAP meets the TVA's FSAR commitment for the Category lE Instrumentation at SQN, the evaluation team concluded that the stated CAP is adequate resolution of the issues. TVA notified the evaluation team of the completion of all pre-restart corrective action activities via TCCA-025 (Reference C.1; 08/18/87). The evaluation team observed that the corrective actions implemented did not address all issues as noted in BLT-451 (Reference C.3; 08/26/87) and the attached verification checklist (08/26/87) and in'BLT-559 (Reference C.17; 11/25/87). Var.tous telephone calls were made between the evaluation team and TVA to resolve open issues (e.g., Reference C.10, C. ll, C.13, and C.15). Subsequently a meeting was held at the SQN plant on 12/14-18/87 to identify remaining open issues as reported and itemized in BLT-595 (12/30/87). TCCA-059 (Reference C.2; 01/14/88) Indicated that corrective action was completed based on transmittal of the revised Calculation SQEP-C2-128, which was one of the subjects of the 12/14-18/87 meetings. The following documents were received by the evaluation team as a result of,these meetings and prov.ide the basis of the verification closecut for unit 2 prestart activities: 1. EEB Calculation SON-ISL-001. R2 (12/18/87) (Reference B.ll This calculation identifled a list of safety-related instruments associated with FSAR Chapter 15 events required for unit 2 restart. The list was prepared as an input to Special Maintenance ]. Instruction SHI-0-317-61 (Reference B.6), which initiates the J^ M Discussion continued . _}.[,, 44820-Ril (02/17/88) C N ..o~ p,- m..g g@. " f 0 ""*'(

ECTG C.3 Attachment E Page 4 of 18 Revision 4 ECTG VERIFICATION CLOSE0VT CHECKLIST CATO NO. 223 03 SQN 01 Initials 11 Date a//7/ds DISCUSSION: (Continued) first phase of corrective action required for unit 2 restart for Corrective Action Report CAR-87-014 (Reference B.12). CAR-87-014 identifies various problems with Instrumentation components, instrument sense line condition.sc and mounting support of instrumentation components and associated piping. SMI-0-317-61 provides walkdown, inspection, and rework instructions that are to be performed on a specific scope of instruments and their associated sensing Ilnes that are required for unit 2 restart. The instrument list used in this SMI was based on EEB Calculation SQH-ISL-001. This same instrument list was also used to implement the corrective action for CATO 223 03 SQN 01, A total of 271 locally mounted instruments associated with 17 systems were identified by TVA in Calculation SQN-ISL-001 as required for unit 2 restart. To develop the list, TVA reviewed the instrument tabulation drawings, control drawings, logic drawings, and system walkdown boundary identification drawings (SWBID). The SWBID drawings are current design system drawings marked with system boundaries required for unit-2 restart and are part of Calculation SQN-OSG7-048 (Reference 8.2). TVA ONE indicated that the 271 instruments identified are required for safe shutdown, to mitigate core damage or to prevent releases in excess of 10CFR100 limits (FSAR Chapter 15 events). Calculation SCG-4M-00267 (Reference B.4) states: "Chapter 15 of the Sequoyah FSAR presents the various system transients that are postulated to occur. The scope of this effort addresses the instruments required to control and monitor selected Chapter 15 events. More specifically, the j subject instruments are presented in Table 1 (of Calculation 1 SCG-4H-00267) as they were identified in the EEB calculation i (SON-ISL-001) of Reference 2. The EEB list of instrument in { Reference 2 was obtained from Reference 3, (ONE-NEB Calculation SQN-OSG7-048), the System Walkdown Boundary Identification Document (SWBID). This document, SWBIO, is an lssued DNE calc'ulation and does not include Critical l e 1 l M Discussion continued 44820-Ril (02/17/88) m (

ECTG C.3 Attachment E Page S of 18 Revision 4 ECTG VERIFICATION CLOSE00T CHECKLIST CATO NO. 223 03 SON 01 Initials }Iv; Date2[17/906 OISCUSSION: (Continued) Structures Systems and Components (CSSC) list as an input document. Although the CSSC list may be involved in other employee concerns, it has no impact on the list of instruments developed for Employee Concern 223.03." The evaluation team notes that the scoping' input to Calculation SQN-ISL-001 is Calculation SQN-OSG7-048 which is a higher order document than the CSSC List. Thus the evaluation team concludes that this scoping method is an adequate alternative to that contained in the CAP. 2. CEB Calculations SCG-4M-00267, R0 (01/16/88), and SCG-4M-00268, R0 (01/16/88) (References B.4 and 8.5) Calculation SCG-4M-00267 documents the seismic review and evaluation efforts performed for the instruments and their installations scoped in the EES Calculation SQN-ISL-001. Calculation SCG-4M-00267 also addresses the resolution of the nonconforming installation of instrumentation that were reported during the performance of SMI-0-317-61 (Reference B.6). Calculation SCG-4M-00267 replaces the original Calculatten 3 SQEP-C2-128 (Reference B.3). Calculation SCG-4H-00267 consists of more than 2,000 pages, whe'reas companion Calculation SCG-4M-00268 has more than 3,000 This companion calculation contains reference materials pages. that were used in Calculation SCG-4M-00267. The materials are primarily instrument seismic qualification documentation required for unit 2 restart. These include vendor test reports, test I procedures, and TVA approval letters. In lieu of a complete and detailed review of these calculations, the evaluation team performed an overview of the calculations, and sele ~cted ten biased samples of instruments and their installations from the ventilating system 30 contained in Calculation SCG-4M-00267 for detailed seismic review. System 30 has 54 instruments, of which j 35 were found by TVA DNE to have some type of support anomalies as i indicated in the Data Sheet 8.1 during the performance of i SHI-0-317-61 (Reference B.6). These data sheets record anomalles i and do not pass judgment on the significance of the individual 1 D( Discussion continued 44820-Ril (02/17/88) s' l

ECTG C.3 Attachment E Page 6 of 18 Revision 4 ECTG VERIFICATION CLOSE00T CHECKLIST CATO NO. 223 03 SQN 01 Initials J u'. Date 2//7/98 DISCUSSION: (Continued) anomaly. This special maintenance instruction was prepared to perform a walkdown of instrumentation and record mounting anomalies noted in CAR-87-014 As these data were judged appropriate by TVA to evaluate.lssues for element report 223.3(B), they have been so used. The evaluation team considers this TVA judgment to be adequate. The completed Data Sheet 8.1 formed part of Calculation SCG-4M-00267. The 10 instruments listed below are located in the Aux 111ary Building at or above elevation 669 feet (Reference B.30); 8 of them are duct-mounted flow switches, one is a wall-mounted temperature switch, and one is a floor panel-mounted (Instrument rack) pressure differential indicating switch. Reference Section Instruments Manufacturer /Model No. Calc. SCG-4M-00267/OO268 2-FS-30-185 Dwyer/1627-1 Category 14A/ Appendix T 2-FS-30-157 Owyer/1627-1 Category 14A/ Appendix T 2-FS-30-187 Owyer/1627-! Category ISC/ Appendix T 1-FS-30-190 Dwyer/1627-1 Category 14A/ Appendix T 1-FS-30-191 Owyer/1627-1 Category 14A/ Appendix T 2-TS-30-200 Johnson Controls / Category 15G/ Appendix S Penn A19-BBC-2 2-FS-30-200 FCI/12-64-3 Category ISG/ Appendix E '2-FS-30-201 Dwyer/1627-1 . Category 14A/ Appendix T 2-FS-30-202 ~0wyer/1627-S Category 14A/ Appendix T 0-PDIS-30-149 Dwyer/3301 Category 9J / Appendix L 'i The review of the calculations identified the following: A document search was performed by TVA to identify the seismic a. qualification documentation of the instruments req 0lred for unit 2 i restart. The document search was performed in accordance wtth SQN Project Procedure for resolution of employe.e concern 223.03 (UE&C Project Procedure SNP-PP-0020; Reference B.4). i CAQR SQP 880029 (Reference B.9) was prepared for those Instruments with missing Sqi selsmic qualification documents; they will be retrieved as post-restart activities, Instruoene o_FOIS-30-149, owyer switch k)$ 1 4 W Discussion continued 44820-Ril (02/17/88) .... 3 .t

ECTG C.3 Attachment E Page 7 of 18 Revision 4 ECTG VERIFICATION CLOSE00T CHECKLIST CATO NO. 223 03 SON 01 Initials M Gate 2/M/89 DISCUSSION: (Continued) Model 3301. mounted to a floor panel, was one of those Instruments with missing seismic test report. Interim qualification criteria (for restart only) based on Seismic Qualification Utilities Group (SQUG) seismic experience data base (Appendix A of Calculation SCG-4M-00267; Raference B.4) were used to qualify those instruments for which no seismic qualification document was identified and retrieved. The evaluation team reviewed the SQUG ~ data base and found it adequate for use as interim qualification criteria for unit 2 restart. ^ b. The TVA memo from J. B. Hosmer to R. C. Denney (Reference B.16; 01/29/88) indicates that CAQR SQP 880029 (Attachment 7 to Reference B.16) now includes retrieval or obtaining appropriate TVA approval letters. TVA DNE indicated that this is one of the 1 .5Q to post-restart activities. SQuG seismic experience data ease wiii be invoked as required as interim qualification criteria for /)( unit 2 restart. TVA approval letters, or other documented evidence of 1VA review and approval of seismic qualification 1 reports, were not always contained in Calculation SCG-4M-00268 or CAQR SQP 880029. The evaluation team considers the above approach adequate. Appendix P of Section I of the Calculation SCG-4M-00268 indicates c. prissure transmitters Foxboro E-10 series (e.g., Hodel E13DM) were seismically quallfled by Hyle Report 45592-4 (Reference B.5). The Hyle test report listed only Foxboro N-E10 series (e.g., N-E130M) as tested. The TVA memo from Hosmer to Denney (Reference B.16) indicates that the letter "N" designates nuclear grade, and that seismic qualification is the same for both Foxboro E10-series and N-E10 series pressure transmitters. This is considered adequate l by the evaluation team. d. Category 1E instruments 2-PS-047-073, -074, and -075 are located in the Turbine Building and are not seismically quallfled. The exemption from seismic qualification for Category lE instruments located in the Turbine Building is documented in Sequoyah FSAR Section 7.2 (Attachment 4 to Reference B.16). Instruments i 2-PS-047-073, -074, and -075 are used to detect a turbine trip for i i )4 Olscussion con,tinued { 44820-Rll (02/17/88)

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ECTG C.3 Attachment E Page 8 of 18 Revision A ECTG VERIFICATION CLOSE00T CHECKl.IST t CATO NO. 223 03 SON 01, Initials b Date 2/r7/#8 DISCUSSION: (Continued) reactor protection and no credit is taken for these instruments in-accident analysis. Thus seismic qualification of these instruments is not required by TVA. The evaluation team' considers this approach adequate. Table 2 of Calc'ulation SCG-4H-00267 identifies model numbers for e. instruments required for unit 2 restart. The TVA memo from Hosmer to Denney (Reference B.16) stated that the model number for i instrument 2-PS-03-164 is SBilAKR; the instrument was manufactured by ASC0a The model number was inadvertently omitted by TVA and will be added to revision 1 of Calculation SCG-4M-00267 as a post-restart item. This is considered adequate by the evaluation team. f. A drawing search and a field inspection were performed by TVA to ~ ' identify and verify as-bullt mounting installation of instruments required for unit 2 restart. The drawing search was also performed in accordance with SQN Project Procedure for resolution I of employee concern 223.03 (UE&C Project Procedure SNP-PP-0020; Appendix C of Calculation SCG-4H-00267). The field inspection was performed in accordance with SMI-0-317-61 (Reference B.6). Four CAQRs (References B.7, B.8, 8.10, and B.11) were generated for instruments with no approved mounting detall drawings or nor) conforming installation. There were approximately 370 identified discrepancies associated with about 210 instruments pertaining to instrumentation components and their mounting support installations. Many of the discrepancies were very similar in nature and were sorted into 21 discrepancy categories. Evaluations were performed to qualify the as-installed instruments with mounting discrepancies. Work requests (References B.19 to B.29) have been issued involving instruments that r,equired immediate restart modification, changes, or repairs. These work requests include: Inspect 0-FS-313-318; 0-FS-313-327; 0-FS-313-353; B274747 0-FS-313-362, 0-FS-311-020; 2-PT-068-068; 0-FT-067-209 i i J M Discussion continued II320-Rll (02/17/88)

ECTG C.3 Attachment E Page 9 of 18 Revision 4 ECTG VERIFICATION CLOSE00T CHECKLIST-CATO NO. 223 03 SON 01 Inltials Ed Date 3/t7/98 DISCUSSION: (Continued) B2R4157 Secure 1-FS-313-447 before unit 2 restart B284159 Replace missing bolts and tighten existing' bolts t 0-FS-031-492 before unit 2 restart I B284160 Replace missing bolts 0-FS-031-495'before unit 2 restart 8284161 Replace improper size bolts 2-LT-068'-320 before unit 2 restart B284162 Replace missing screw 0-FS-313-389 before unit 2 restart B2@4163 Install nuts on existing bolts 2-FS-313-497 B284164 Install missing mounting bracket (2 required: 1 i installed) 2-FS-030-157 before unit 2 restart 8284165 Install Instrument down side up 0-FE-031-495 before unit 2 restart B284166 Install Instrument down side up 0-FE-031-487 before unit 2 restart i 3 B284167 Install Instrument down side'up 0-FE-031-484 before unit 2 restart. %lb Verification of completion of these work requests is a post-restart item. The cover sheet of Calculation SCG-4M-00267 Infers'the number of g. instruments inspected were based on Special Maintenance Instruction SHI-0-317-61. Rev. O. Revision 3 of the SMI (Reference B.6) required additional instruments to be inspected. i The TVA memo from Hosmer to Denney (Reference B.16) Indicated that l hg revision 3 of SHI-0-317-61 I was used. The cover sheet of Calculation SCG-4H-00267 will be revised to indicate revision 3 of the SHI as a post-restart item. This response is considered adequate by the evaluation team. t Table 3 of Ca'lculation SCG-4H-00267 lists installation drawings of h. i associated Category IE instruments required for, unit 2 restart. Out of a total of 271 instruments required for restart, about 55 i C4 Olscussion corltinued l 44820-R11 (02/17/88) ~ -\\

ECTG C.3 Attachment E Page 10 of 18 Revision 4 ECTG VERIFICATION CLOSE00T CHECKLIST CATO NO. 223 03 SON 01 Inltlals j a; Date a//7/#6 OISCUSSION: (Continued) instruments and associated installation drawings were not tabulated. The TVA memo from Hosmer to Denney (Reference 8.16) indicated a copy of Table 3 has been marked as shown on to the meno to include installation drawings for the balance of the 271 instruments. Upon review of the marked Table 3, the evaluation team considered the marked table C6 /4 adequate. Revision to Table 3 of Calculation SCG-4H-00267 to /7pp include the marked information is a post-restart item. 1. The evaluations provided in Calculation SCG-4H-00267 has not. - properly accounted for the installation of instruments (some samples are listed below) that are mounted on the flexible parts of the ductwork (e.g., duct skin made of thin gauge sheet metal and the flexible standing seam bars, i.e., seams, pocket locks). The seismic response spectra provided in Design Input Memorandum (DIH) SQN-DC-V-13.8-3 (Reference 8.15) did not properly account for the local flexibility of the duct skin and the flexibility of the standing seam bars to which some of the instruments are attached; viz, flexibility of the supporting structures of instruments which may induce additional seismic amplification that may affect the seismic qualification of the instrument has not been properly addressed. Section of ' Instruments Calc. SCG-4H-00267 2-FS-030-201 Category 14A 2-FS-030-200 Category ISG 2-FS-030-202 Category 14A 2-FS-313-523 Category ISA 1-FS-313-473 Category 15A 2-FS-030-187 Category 15C The TVA memo from Hosmer to Denney (Reference 8.16) stated that the seismic response spectra provided in DIH SQN-0C-V-13.8-3 (Reference B.15) did not properly account for the local amplification due to the local flexibility of the duct skin and the flexibility of the standing seam bars where some of the instruments are attached. The memo outlined several options for resolution of this concern. The following are extracts from the TVA memo: pdOlscussioncontinued 44820-Ril (02/17/88) A

~ ECTG C.3 c Attachment E Page 11 of 18 Revision 4 ECTG VERIFICATION CLOSE0VT CHECXLIST CATO NO. 223 03 SON 01 Initials M Date 2/t7/88 DISCUSSION: (Continued)

Reference:

Bulletin 42 (Part 2 of 5 Parts) from The Shock and Vibration Bullettn; The Shock and Vibration Information Center; Naval Research Laboratory, Washington DC; January 1972 (Copy included with Attachment 6).

1. If the existing equipment qualification tests are used, the appropriate ampilfication factor obtained from figure 7 of the above reference will be applied to the accelerations presented in DIM SON-0C-V-13.8 for each elevation.

If any of the resulting accelerations exceed the test accelerations to ~ hich the duct mounted instruments are quallfled, one of the w following methods or a combination of the following methods shall be used to qualify the duct-mounted instrument installation: < A. If necessary, field inspections shall be performed to determine exactly where on the duct an instrument is installed (i.e., mounted near the center of sheet metal panels, near a flange or mounted to or near a stiffer element of the ductwork). B. Duct frequencies, including the span and local effects, shall be determined to justify n._ot using the peak acceleration given in O!H SQN-0C-V-13.8. C. Replace the instrument with anc,ther instrument that is quallfled to higher acceleration levels, t ' Redesign the Instrument mounting bracket and/or move the D. i existing instrument to an acceptably rigid location on the duct. 1 2. If the existing instrument seismic qualification documents are judged inadequate, the following actions are available: l A. Perform a document search to locate seismic qualification documents that quallfles the instruments to higher acceleration levels. B. Perform seismic tests on prototype instruments that qualify the instruments to higher acceleration levels. Options A through D of item I above may also be used in conjunction with the above actions, M Discuss ~lon continued 44820-Ril (02/17/88)

\\

ECTG C.3 Attachment E Page 12 of 18 Revision 4 ECTG VERIFICATION CLOSE00T CHECKl.IST i i CATO NO. 223 03 SON 01 Initials L* Date 2//7/88 OISCUSSION: (Continued) 3. When the above alternatives cannot be implemented expediently, the SQUG experience data base criteria shall be invoked as justification for restart. The instrument installation shall be 1.lsted in CAQR SQP-880029 and its ye Mb ' seismic qualification shall be resolved subsequ S9 iS ~ l\\f 50 p b Items 1 or 2, or both, may be performed either before or after n unit 2 restart; however, if they cannot be implemented before unit g puff pt 2 restatt, then item 3 will be implemented before restart. yM'pg Verification of activities actually accomplished will be performed post-restart. The above resolution is considered adequate by the evaluation team. j. The evaluation team noted that an independent review has not been performed for Calculation SCG-4H-00267 as required by Interim Order to NEP 3.1, Revision 1. Section 4.1.5 (Reference 8.32). In response to this, the TVA memo from Hosmer to Denney (Reference B.16) indicated that the requirement that the design verifter (independent reviewer) cannot be the checker or the person who performed the review in Section 4.1.4 of NEP 3.1 (technical adequacy reviewer) has been walved in a variance to Interim Order to NEP 3.1. This was documented in a letter from A. f*. Capozzi, TVA, to R. H. Bryans. United _ Engineers and Constructors. Inc. (UELC) (Attachment 2 to Refe'rence B.16). The letter also stated that Attachment 6 to NEP 3.1, "Calculation Independent Review Verification Form" will be included in the calculation. TVA or jQR UELC will ir.clude a completed "Calculation Independent Review Verification Form" in accordance with NEP 3.1 as subject to the above walver in revision I of Calculation SCG-4H-00267. This is a post-restart Item. 3. CONCLUSION Therefore, the evaluation team determined that (1) the specific corrective action commitments and requirements for unit 2 restart were completed. (2) the corrective actions taken for the unit 2 restart items are technically adequate, and (3) post-restart activities are identified to provide complete instrument seismic qualification documentation as well as confirmation of the adequacy of the existing duct-mounted instrument installation to meet FSAR commitments on a long term basis. M Discussion continued 44820-Ril (02/17/88) 1;

ECTG C.3 Attachment E Page 13 of 18 Revision 4 4 ECTG VERIFICATION CLOSE0VT CHECKLIST CATO NO. 223 03 SON 01 Initials M Date a//7/g8 DISCUSSION: (Continued) 8.

REFERENCES:

The following documents associated with the corrective action for the subject CATO were reviewed:- 1. DNE-EEB Calculation SQN-ISL-001, "SQ-CAR-87-014 Instrument Inspection List," Rev. O. (B25 870918 802), (09/17/87); Rev. 1 (B25 871202 8001, (11/17/87); Rev. 2, (B25 871223 8053,~ (12/18/87) 2. DNE-NEB. Calculation SQN-0SG7-048, "Identification of Systems ' Required for Sequoyah Restart " Rev. 4, (825 870319 801), (03/19/87); Rev. 5, (B25 870617 102), 106/!7/87) 3. DNE-CEB Calculation SQE.'-C2-128, "Seismic Qualification Local and Panel Mounted Instruments," Rev. O, (B25 870804 805), (08/04/87); Rev. 1,' (B25 871221 843), (12/11/87) 4. DNE-CEB Calculation SCG-4M-00267, "Resolution of Employee Concern 223.03 - Seismic Qualification and Installation of Instruments," Rev. O. (B25 880116 805), (01/16/88) ~ Appendix A - Appilcation of the SQUG Seismic Experience Data o i Base As Justification for Restart Criteria Appendix C - TVA SON Project Pr.ocedure for Resolution of o Employee Concern 223.03, "Seismic Qualification and Installation of Instruments" - UE&C Project Procedure SNP-PP-0020, Rev. O. (01/05/88) 5. DNE-CEB Calculation SCG-4H-00268, "Summary of Reference Material for Resolution of Employee Concern 223.3," Rev. O. [B25 880116 806), (01/16/88) Appendix P - Wyle Laboratories Qualification Plan 45352-1 o (Report No. 45592-4), "Phase II Qualification Plan for Foxboro N-E10 series Pressure Transmitters for Utility Transmitter Qualification Group for Use in Various Nuclear Power J Generating Stations," Rev. B. (06/22/81) Appendix 5 - Gaynes Engineering and Testing Laboratories, o Inc., "Johnson Controls, Inc., Milwaukee, Wisconsin; Seismic Vibration Testing of One (1) Electric Thermostat A19 ABC-36," for Watts Barr Nuclear Plant, Job No. 76634, (12/21-22/76) 1 1 M Discussion continued 44820-RI) (02/17/88)

ECVG C.3 Attachment E o Page 14 of 18 Revision 4 ECTG VERIFICATION CLOSEOUT CHECXLIST CATO fl0. 223 03 SON 01 Initials M Date 2//7/#8 DISCUSSION: (Continued) Appendix T - Equipment Qualification Report for MVT/RST/TCT o Transmitters for Watts Barr Nuclear Plant. TVA P.O. No.: 85KLO-837740, Nutherm Ref. No. TVA-1830, Rev. O, Vol6me I: Wyle Report No. 47847-1, "Seismic Simulation Test Program on Thirty-nine Electrical Components," Revision A (06/27/85) 6. TVA SQN Special Maintenance Instruction SMI-0-317-61, "Instrumentation Features Walkdown, Rework and Inspection . Instructions for CAR 87-014," Rev.1 (06/12/87); Rev. 3, (09/30/87) 7. CAQR SQP 871235 Rev. O (S13 870717 803) 8. CAQR SQP 871147. Rev. O, (S13 870630 828) 9. CAQR SQP 880029 Rev. O. (513 880115 836) I ~:

10. CAQR SQP 871099, Rev. O, (513 870618 829)

'11. CAQR SQP 871100, Rev. O. (S13 870618 830)

12. Corrective Action Report SQ-CAR-87-014 with date of approval i

04/15/87

13. TVA Design Interface Document CEB-DI 121.03, "Seismic Design, t

Review, and Control," Rev. l. (805,860516 500), (05/16/86)

14. Sequoyah Engineering Procedure SQEP-13. "Procedure for Transitional Design Change Control." Rev. 3. (03/05/87) i

15. TVA memorandum from R. O. Barnett, Chief Civil Engineer, to Civil Engineering Branch Flies, "SQN-Design Input Memorandum (DIH) on seismically qualifying round and rectangular duct

SQN-DC-V-13.8," 0!M-SQN-0C-13.8-3, (841 870319 001), (03/19/87)

16. TVA memorandum from J. 8. Hosmer, Project Engineer, to R. C.

Denney, Employee Concerns Special Project Manager, "SQN-Closure of Employee Ccncern 223.03 and Resolution of Bechtel Comments on j Calculation SCG-4H-00267." [B25 880129 001), (01/29/88) l Letter from A. P. Capozzi, TVA, to R. H. Bryans, UELC, o "SQ!! Unit I and 2 - General Design and Field Support Task Performance Contract (TPC) - United Engineers & Constructors. Incorporated (UE&C) - Personal Services Contract TV-72992 " TVUE-0035, (01/11/88) M Olscussion continued 44820-Rin (02/17/88) . :.1

EC7G C.3 'i Attachment E l Page 15 of 18 Revision 4 l i ECTG VERIFICATION CLOSEOUT CHECKLIST l CATO NO. 223 03 SON 01 Initials M W Date 3//7/88 i ) O!SCUSSION: (Continued) . Marked-up changes to Table 3 of CES Calculation SCG-4H-00267, o I Rev. 0 i l SQN FSAR Section 7.2,_"Reactor Trip System" (pages 7.2-10 o and 7.2-11) 4 1 o Marked-up changes to Table 6 and Table 7 of CEB Calculation i SCG-4H-00267. Rev. 0 The. shock and vibration Bulletin, Bulletin 42 (Part 2 of-S o Parts), January 1972 - A Publication of The Shock and i Vibration Information Center, Naval Research Laboratory, j Hashington, D.C. o Marked-up changes to CAQR SQP 880029 Rev. O. (513 880115 836) ~

17. TVA memorandum from J. B. Hosmer. Project Engineer, to L. L.

McCormick, Site Licensing, "SQN-Transmittal of NRC Commitment - Control number NC0870278002." (825 871021008] t' i i ONE Calculation SQN-ISL-001, Rev. O i o Instrument Project Status Report for Unit 2 Phase 1 o o ' Instrument Project Discrepancy, Report for Unit 2 Phase l' }

18. OCN X00020A, [825 870721 501), (07/20/87)

19. Work Request 8284164, (01/12/88) i l

20. Work Request 8284160, (01/10/88)

21. Work Request 8284159, (12/22/87)

22. Work Request 8284163, (01/11/88) i

23. Work Request 8284157, (12/16/87)

24. Work Request 8284162, (01/15/83) t

25. Work Request 8284161, (01/14/88) i

26. Work Request 8284165, (01/12/88) j j

27. Work Request 8284166, (01/12/88)

M Discussion continued 1 44820-Ril (02/l?/88f 4 ..;j

ECTG C.3 Attachment E Page 16 of 18 Revision 4 ECTG VERIFICATION CLOSEOUT CHECKLIST CATO NO. 223 03 SON 01 Initials M Date 2A g gd DISCUSSION: (Continued)

28. Work Request B284167, (01/12/88)

29. Work Request B274747, (01/15/68) 4 i

30. TVA-SQN Orawings:

1 3 47A900-4, RO "Mechanical Heating, Ventilating & Air l Conditioning Sheet Metal Detalls" 47H920,.12, R17 "Mechanical Heating, Ventilating and Air' Conditioning" i 47H920-13,'R14 "Mechanical Heating, Ventilating and Air Conditioning" 47H920il4, R15 "Mechanical Heating, Ventilating and Air i Conditioning" 1 t 47H920-15, R19 "Mechanical Heating, Ventilating and Air j Conditioning" l 47H920-23. R23 "Mechanical Heating, Ventilating and Air i Conditioning" ) 47S600-22,R7 "Mechanical Instruments and Controls" 47H600-227, R6 "Nechanical Instruments and Controls" 47H600-298, R1 "Mechanical Instruments and Controls" 1

31. EQE Recort No. 87126-01-R-001, "A review of Hainteilance Activities Involving Replacement Parts at the Sequoyah Nuclear Plant Unit 2 and Unit 0 (Common) Using the Seismic Experience Data Base,"

Rev. O, [B31 870714 801), July 1987

32. TVA memorandum from J. A. Kirkebo, Olrector of Nuclear Engineering, to Those listed, "0NE Interim Order for NEP-3.1, i

Revision 1 Calculations," [B05 871119 500), (11/19/87)

33. TVA Design Criteria 50N-DC-V13.8, "Seismically Qualifying Round and Rectangular Duct," Rev. 4 [B42 860220 500), (02/20/86)

M Discussion continued 44820.Ril (02/17/88)

i ECTG C.3 Attachmeat E Page 17 of 18 Revision 4 ECTG VERIFICATION CLOSE0VT 0HECKLIST CATO NO. 223 03 SON 01 Initials li Date a//gg8 l OISCUSSION: (Continued) C. CATD-RELATED CORRESPONDENCE: i The following references are related to the corrective action for l the subject CATO: 1. Lt.tter from G. R. McNutt. TVA, to G. L. Parkinson, Bechtel. TCCA 25 (no RIMS number), (08/18/87) 2e letter from G. R. McNutt. TVA, to G. L. Parkinson, Bechtel, TCCA 594 [no RIMS number), (01/13/87) TVA memorandum from H. L. Abercromble Site Olrector, to W. R.. o Srown, Jr., Employee Concerns Task Group Program Manager, "ECTG Element Report 223.03 SQN-Unit 2 restart corrective i act, ion plan (CAP) implementation." (503 871211 801), (01/06/88) 3. Letter from G. L. Parkinson, Bechtel, to G. R. McNutt, TVA, BLT 451 (08/26/87), CATO 22303 SQN 01 - not vertfled 4. Letter from G. L. Parkinson, Bechtel, to G. R. McNutt, TVA,. BLT-595 (12/30/87) 5. RFI SQN 877 (10/23/87) 6. RFI SQN 880 (10/26/87) 7. RFI SQN 911 (12/09/87) 8. RFI SQN 929 (01/06/88) 9. Telephone call from J. T. Hut and J. E. Staub, TVAs to J. W. Benkert, Bechtel, ION 1757, (08/25/87)

10. Telephone call from R. C. Denney et al., TVA, to J. W. Benkert and Y. K. Hul, Bechtel, ICH 1932, (09/03/87)

~

11. Telephone call from J. W. Benkert, Bechtel, to J. E. Staub, TVA, ION 1945 (10/19/87)

12. Telephone call from G. R. McNutt et al., TVA, to C. W. Jordan et al., Bechtel IDH 2262. (01/26/88) 54 Discussion continued 44820-Rin (02/17/88)

e O s ECTG C.3 Attachment E i Page 18 of 18 Revision 4 ECTG VERIFICATION CLOSE00T CHECXLIST CATO NO. 223 03 SON 01 Initials k Date 2//7/88 DISCUSSION: (Continued)

13. Telephone call from J. D. Swearingen et al., TVA, to K. Wiedner i

i et al., Bechtel, IDH 2101. (12/01/87)

14. Bechtel comments on ONE-EEB preliminary calculation SQN-ISL-001

) ION 1922. (10/07/87)

15. Bechtel comments on DNE-EES calculation SQN-ISL-001 draft revision 1 ION 1986, (11/05/87) l'6. Bechtel ccmments on DNE-EEB calculation SQN-ISL-001, revision i

and DNE-CEB preliminary calculation SQEP-SCG-4H-00227, 10H 2205, (01/08/88) 4

17. Letter from G. L. Parkinson, Bechtel, to G. P. McNutt, TVA, BLT 559. (11/25/87) i

+ 1 i i i } I i e e i 1 1 l I l () Discussion continued 44820-Ril (02/17/88) )

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NUC PR C6anat:o F"

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ly.d. or Data Sheet APPROVEDs p., aw .ca,.y. No Available fjff s TPE Electrical Br. Chi ^* Da e '- e h. 'WAs-4/5 RJ ' - F. ' Therm.al Power Engirwering Branches .., y'. ' ,...,n ( / =. .~ i [rI p/N E Mech,,c,al,, I g \\? igg g'.diNucigr' h..,l, ' 7 r ^

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I.T Electrical .de-Nonconformance Report Requlted -/ / .. ^ ~" Mech W,' .gA Vendor Backcharges involved ,.,[.-k,,f-V /o,

h.'%tjT. h,G PHYSICALWOR K MUST OC DON E BEFOR Ei

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UNREVIEWED SAFETY-QUESTION DETERMINATION .<v.. + ',[ /10551 (EN DES 7 80) l SHEET C1 ' e Dequoy.ah Nuclear Plant, Dalsy.TN i TO: Qf3R.O Froien kanager ove sq4 GB K -- ROM: MEDS ACCCSSION NO. g TR,7 Dgo SWP '81 1218 ~5 2 9 E PREPARED REVIEWED APPROVED R E o* MBA Rd%i 5kidaA .1/27h/Yu 7 .e i 4.a. a g. 2 2 R 3 3 ~ 4 R 0 l ~ 4 S R . Ifh - ' < > " + i

R08vlNITI AL ISSUE PRC;ECT % N USQ7 YES NO ' 7 I

AFFECTED UNIT (* [ -M O~ fcuJ--D CM- ,[5 l ECN NO. ECN DATE YES/NO SHEET NO MCR/DCR NO. 8[i DATE SPECIAL REQUIREMENT (S) N .s/. /8 OTHER DATE POTENTI AL TECH SPEC CHANGE f tEFERENCES, SC LC313 COVER. SHEET ~ QSQO 50P1b/27tNPcRMAr1ed sh%er fem. Ec4 IJ3t 3, It.Y FeeMd gg7,; gacg ro R tO c. 8-2.7-80 AoG Boo 82aci9, AMD Ga Ahler2. CAT 1ods tdlTH W.AA.)k" I 3:t/EAJDo<.45k /. A44h "RcGIM F4 (EETHe/P.og. AMD lee 9A-r24:s. '? - :cGlW. :%2M-- DESCRIPTION OF CHANGE _ 6A57"' AND tdES7~ ST@rM \\lA1.L/E W*0 EMS - ?OoF DES (GA), I

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YES CHIEF NUCLEAR ENGINEER,W10Cl26 C K

".,.' '**dC.;4 CHIEF. ARCHITEC7UR AL DESIGN BR ANCH.W4Cl26 C K CHIEF. MECH ANIC AL EN OCS BR ANCH.1025PT K i. .'f CHIEF. CIVIL EN OF $ SR ANCH. W3Cl26 C K

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2

.,,,g UNREVIEWED SAFETY QUESTION DETERMINATION ' NI' l 53(SR.c r.,,,6c, SQtd \\ IDENTIFIER ( Unreviewed Safety Question: "q ..,.,1. Is the probability of occurrence or the consequences of an accident or c malfunction of equipment important to safety previously evaluated in 'Idh the Safety Analysis Report increased? ............................ Ye s No V d.[h dINustification: ' b'k6 M kTEMlM IMSTAf f FO C4 4 "Tl'ftf EC/d A TD \\JPGR.AbG rM GOAti79 0FTth=- TRoep cF-TRe. EASr AMb u)EST GrE75% MLA/6 (lecM.s. TifG MEtd T2 cop (5 sElsut cALLt< GOALt F/et Ado m OPGR.AbEb TD PRINEMT MetsTURE P4cW EMS 77fM7~ Co(>LB . 225 ULT /A) ROOP- ?=Atult?E Ad $ A S 6: TO SAPe7cr RELM*~n ECO 9MEUT of4 ccMFoerprr. 90 stG4 iF<cAur CIfAA16E e/A/ m. THE RccP ScoMor)$$WEssdKE RESUL75 PitoM 72-hs bJd6e' (~72 *%Q.-THE2eFo ' THEW d Alo M)cAe~ASE JA) 7dE MA~ v~.: j(t.JW O A C C C-U 2 /2 A.JC[ CA.1~UE CbA.LSSQ.UBAJCE~ &t/du,)AI@ . /M 7HE G5' A /2. ALSO, 7H6.SPGr*tAL 2EQUttZgM EAj73 cAJ WSH2ei 3 k)/LL. EO50 AE 7?MY" SOtO P/12.2 0/2.o TV C~n sJJ r weR t ie 12iA At2e Skrispreb. jQ..:v s.

2. Is the possibility for an accident or malfunction of a different type s f.,.gthan any evaluated previously in the Safety Analysis Report created?................

Yes No- .M.N n. v. C. ' ~.iJsiiricuron TWG MATm2t ALs MsTatreo B4 TWs e CN Nze 2mv//z2o Jfin UPsttnoc,He coAuru op meacos of mc ensr aus ~d %%l.c#tdEs7 srsMu t/nLLIE R.co MS. TMIS M ATETLIAL* (s ALie.EAd4 h~ 1.e-W; M'10 USE IM st MiLAML APPu cA noA15 ELSCdHE7f-G: id 7M E R.AA)T. . r: ',.'g. "DfG dEd T2-ocE t5 G E t5 A4(C ALL}f QdAL1 FI 6-fa A A3D t5 bet % .W -IUPC> R.ACEbTD 6LJMIA)A7E Mo/SNgE 9/2c/3CEAAS 'TMMT Codu. ~ l3esOLT IAl RCOF' PAtLL)/LE Asdb PoS5I/3LE ' DANA %G 'TD '.?"SAPGTL( 3 ELATED GEDdiPMEATI. MGh]CG. do OE$ ACCtbeb ~. J .M ALFdMCT7Pd Ob ADIPf:ET2EAfi~ TV96 Tif'Ad IM 71fE- 't"-SA(2-. IS e ].- '.3. Is the margin of safety as defined in the basis for any technical specification ~ .a .3 r ed u c ed ?........................................................Y e s No / . 'T't-fF dd M DMtGO 1AjtLL. ELIMIA/A-7E M ots'70/2.E @c8CEX4 s, J lr 100 CH-A/JsE c/2._ CHMLLFAME To 7HE 7FCH SAFCS /S Ef." ( . 'PREseMTub 8'1 7>tts CH-nr)6e, 'THG7EFFo/25 7?!G M AM)M= T.. i ~ . ; SA Rn-t.1 AS DET:th]ED oN 7?h=- a Asis. Fo/2. AAJu TECH SPEC -L. .- 3

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- 'j Sh et #3 UNREVIEWED SAFETY QUESTION DETERMINATION L5.5 /5 RD 500 1 Project I ,Special R5quirement(s) or. Precaution (s).. ( b, Mark Subject to Which This Page Applies) ' dp ... ' Safety Evaluation............ ' ^ . ' ' '. '. Additional Information Preparer 7,;..:,, *, Reviewer D (1DiTaid) ~ u 9 9, W e: O ta T2.oop 'DEStC,d AMB TWE M4re=72 e4LI "M' 'PRodi be n Tb 9ePLArt= 7HE ct D TtooP-bktliiitMtJSi pSg j codpba A m 7%g Ft Re-RioTec:rved REQUtdE-AlpA) r bMOAJE47rB /A) 7NF F/#F 84 0 TE: c 77 O AJ $c[. cg/7Eb g Fo4 s (D, AJ. _. _ - = - T- _ T 7 -- -;d. M b$Ah h Md WLf_J MO til A 8 A,u a J M m M..D a & ",x w o.00.. '~ w ssA 4.- von., A U v 7 g t d.8% ' '4 = L g Ag \\ T s -f '.a- . z..: j - .c;*'*;Ts*

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V REVISION LOG USC h for Eav / p> 9 run.: DESCRIPTION OF REVISION App ved &AfN 2o . )~n. u a/ E s w e /? / / b e/e fe Spects/ fegNomMf concena3 fire fr tectim. 7Ae re f is n sOekns s lo /9pp/iy p p,/. no s,yn. N?sn/ '%rnr.cq Ae /o<d is credeA Ay this ECH. in J.' k ev4e Spec,V Ref cirmes/conews.% 3 b ON O UY f leS80/e O & h Q/t f y / b k's Y. 3 N ~ l l TVA 105 34 (EN DE S4'7 0)

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.J a gLrt.. u . q.UJ."' SBQUOYAll WCLEAR PIANT .. dec., USqD SUPEORT IIIFOR"ATIOM SHE'!P ?.; ..ECN - L 6313 Af f_ dk,.~ .r fE Description of Change: Note: This description should be complete enou6h .tifli;hto enable a reviewer familiar with the system to understand what is being 2 f.;,, '.n.,..,)i done and why. Continue on additional sheets if-necessary. Mc s. {;iN.. ' Y Kevice=* Losp Des,e. s, n r w aa:-o7-i.us,ce Pns41 w n ' ~. '. ' c ~ . M.p v. ;. .cte Od@3 . i, n. w rt.. .-T 2,. .. %9, a. ](; g .e %lv " Knowledgeable Individuals /

References:

,h fy/g pu//2 r.. qh,'I)csign Considerations-j i 3

fM.,

"~' (if["i. [11ardware - Components being added by this change comply with t ~ material, electrical, and environmental criteria: <.-y...,. .). _. WCWf - y ~ AA. ---- '~ ' ' ' ~ Design Engineer 2. Seismic - This change does not invalidate system or component scismic requirements. Details: 4)d 41e - r m n>fY $ d Design Engincei-3. Loca_ tion - Relocations specified in this chango have considered separa-tion requirements imposed by electrical or pipe break criterial, etc. Details: f % A,t;-

^.

/ ':.h t A 8 ",' Design E6gineer 4.. .... - T ..,7fc;.. c. . J:,,'5 .:5~d.k-NN I2

.a .. p" ~ u a..e., L SSI3' ttEb STATES GOVERNMENT 1g/3 0710 Mil 1M71 TENNESSEE VALLEY AUTHORIT ~ [( des '810 9 03 0 0 8 L30 810831 9 58~ M. N. Sprouse, Manager of Engineering Design, WilA9 C-K .i FROM.: H. J. Green, Director of Nuclear Power, 1750 CST 2-C I s'.'ic DATE September 2, 1981 e I .-.%p: l .' St*BJECT: SEQUOYAH NUCLEAR PLANT - DESIGN CHANGE REQUEST NO. SQ-DCR-859 ~.. . '._.] ~~7 f.. ~.L ~ Please process the attached change. request SQ-DCR-85'9 in acenrance wittt_, N-OQAM, Part II, Section 3.2. 6-f . Cateeorvtutj.,4.g."; 3 :. ' -j .y' (, m3,. ,.,.7c.:... A () NRC com=1tment, nuclear safety, or EPA requirement l,_ Z gj i B ~(X) Availability, capacity, and reliabil.ity imprev = cat M -8: ] C () ALARA sad safety (iadustrial) i; - d1.H i= - :n. E D () Improved maintenance and operationa' efficiency ~' b E (.) Convenience item 1 g ;7 jE The engineering design cost is less than $10,000 and should be charged N. directly to account num'er NO20-765-30-01. o O .y>. n J ~.- + 5 m M-b b.d M+. h h lhhl Os 5 2 s': /J. J. Grahp /j enc HttmNo ot: cN O.} _ tll[pf ' ~ \\) j MANat;M CFF1CE m<3 M l.2@.M.. TGC:JR:DEM:DJC it 'Nmf

Noted

9 '[: 'i' Attach =ent

' 5 h" 'W@" cc (Attachment): ! h T ' ',

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, ARMS, 640 CST 2-C l y[..;f J. M. Ballentine, NUC PR, Sequoyah l yih y NO R. J.' Johnson, NUC PR, Power Operations Training Cent y g""~ j 's C. C. Mason, NUC PR, Watts Bar l,/ I cn c: 5 L. M. Mills, 400 CST 2-C -~ i B. F. Roberts, 417 UBB-C (* 5 y ,G. G. Stack, CONST, Sequoyah =0E g;)

=c.}=g[. {

E ~ This was prepared' principally by M. A. Allen. D... .+ 9/3/81 - DBB:SB 8<<p cc (Attachment): .,I, Z,, l7' * ' M % [ R. W. Cantrell, 204 GB-K.- Please handle and reply to Green for my * ~ *ldl,C .,"h ( signature by _10/2/81.--MNS ek MEDS, 100 UB-K @...U mu . ac. f ..e/3/81 - RWC:DB SWP '810 90 3 115

5.c :'.... wst a l 9

c (Attachment): ... -..,, r.y[I,E. '"< -."s # 5 .' O.,: ?. R. A. ' Painter, ESC 80 C-K ' '. C'... 'cl i ? T'WE.fMf:.D@.3,$.M, A) ...,v..v .s r UJ. A.*Raulston, W10Cf26 C-K d---_ x c MEDS,[100,UB-K $ $ Q M @ h, ,,,j ; ..t. .s... ^ s,....,.

y.. AI-19'- Part III - *."/. ATTACIU S T 6 L CSis ' ~ f) ja P2ga 1 of 1 Aff p, g gr. 3 ., $.. (. c. Rev.,3' ~ -....x' . (~- DESIGN CHANGE R ST .\\ .Q,,.... v ..s ' N'"Sequoyah Nuclear Plant' DCR No. SQ-DCR- - 859 Date Februa' v 2'4. 1Q81 ~ l ..,... Originating Section Outare tOriginator Ga v N. nm hanam SAY 10h t. m.,..p,0utstanding Work Item No. 3- '417 8855 .t i "' ' Uni: System Sequence r- ..ny.. .N

7.Conponent Valve Room Roofs s.-

e Change Requested:. Modify valve roo= roof due to leakare. [Ref I.-5313) ~ '-- ~

m..

..gp . = l Reason f:r Request:. The joints between the blev-off roof and the ue:--anent va n have f developed a leak due to extansion and contraction and should be redesi ned. The same proble: vas encountered on unit two and this D0p. is need'ed to allow drawin: issue for both uni,s. Non-safe v-rela ed DC?. Safe v-related 20?. 1. CSSO non-safety related J. OSSO safety-related b 2. Non-0SSO ari does no-dire:.ly e.ffe:: 2. Non-OSSO but directly affee,s safe y-related CSSO _' x safe y-rela ed 0530 f 3.

dork can be cc pleted rrior to cffsi e 3

Te:h spe changes invclvei a provt.1 se::i:n u Mo::-safety-related reviev :en;1eted by I s d., a Accounting Data

u. .[ [.;..[ /_ _/ Pr# ""--v E' DIS s copin: vork to be done under Job Order rio.

~~ ~ p!3nC2/ / This modifica.-ic: is to be capi alized under '[i$$'2 @ This modifica:ic. is to be cht.rge$ o*7l'7,53~300- D $5 i PUL W d t 'Y Maintenance Accou.: no. p2 /3 dc<:t.-&.Nego gg. 3 o -o; .c:: ~ (-d4L[ 4m /6 5) t l 1"- ~ [ f gg Outace Section Admin. Officer .Date / / This is a non-safety-related mod..ca,ien, a safety review has been Performed, an approval is given to begin modift:stion. / '?lant Superintenden: Da e Work conple ed; transnit to E" DES for drawine revision eniv. / / Outage Director Date / This modification is safety related proces_ sing to E! DES for., o is to be transn te s ~. .. ~.. 1 Approved for transnittal to Chief, NUC PR Pl_ ant 42Derintendent Ddt t D \\i h 1 0 / 3 } \\ k i,,, _e ~ r Approved for transnittal to EN DES. nb ~? [ ( / ,fj.conlyfilledoutifunderconsiderationafter . DMor of Nuclear'I'over.14'M *3 ' D Li. closure of construefion accounts. ,,,,., *. 52 - . 7a..i.,.lN,*m-M,y ---$'gT:ff ... A s.m,. g,m.&e. gy, n. . ~... .. a.u, m... :. .w.. .u

.. w w. a.m,

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,,*.*! *.**. 1 - L.SbG ,'a Atb ? /$ s 3 J . W. DCR NUMBER p 85Q (. .( .C'.O.S..T ES - -- --.T.I.M.A T.E ~ .m $ UNIT 1 UNIT 2 $ UNIT 0 $ TOTAI; ..~...s. "'."<3..,.'. LABOR 10,000 10,000 MATERIAL h.000 k.000

FIELD ENGINEERISC 1.500

~ 1.500

DESICS ESGINEERING 5.000

~ 5.000 TOTAL 20,500 20,500' 'd. . - 97 7 ALTERSATIVES COSSIDERED: Consideration was riven to renairire the existing desien but it was feit'that the eroblem vould reoccur and a n.v desien would be c 4, tw. in e .di,*- ESEFIT ASA YSIS: . Due to the safetv--elated ecuit=er.t located in the roon s:= reo* 1e.'n ein mot b. tol -st.8 4e. H-Ge* +kat +k. a mm1

.n.4-en.'. 411 w.. ---w 4. +.s. 6 nna em 4.

wE,.#4A 'ih. c1.M.'f~ factor over the 40 year life of the clant'--w4,4.. <L. - + n no.,. n A .~r.--....- 't Y-...:i. ~: c Any ecuie=ent da-*?e resulting . z.,C. u.,I' i ?!-. from roof leakare vould increase the factor and oossibiv reduce the clant .. availability. e-em e . ! ' 3'T.9 j ? @ W ,.n-.,- . ~...,.. .z.. .. u.... ia.... w....,,: _ r. Q .,n:.. c ... v: .a,, y.m. .n. ,,~ .yg. ~.a. u.m,.v.4_.,_ ,,,3..w,. u;.. ..<wp ... ;.a,,.

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l Af, s . s,.T s. Sheet 1 <r IMPACT AND JUSTIFICATION FORM I i h 1 ~P-TVA ECN No. l.53t'% IJ No. 96[o i., Date sy[ PRCJECT SGOuoyA// A4/dAct P/Avr />An'l' / . i.' 1. Description of Proposed Change + l' A nam e Poo f 2)e st n Du huma f!e osu IUlfkast*AclbST ./ / / 4-n P. LJ. C 4^3Tet=t1 'h A rs h Ave. u< t 2 7, / rem (ADn fw29 r o/9) / A .d. - ~ N orip.nator 2. Category: / / 1. Proposed ECN essential for unit operation and r.ay not be deferred until after unit operation license. g 2. ProposedECNaffectsplantoperatingreliabilityand/oravailability. Proposed ECN i=ple=entation may be deferred until after unit operation Mccaso . : 2 3.i-I ;h;l$. Y. il f ir%'S 17 3. Proposed ECN is to improve plant operating flexibility and/or conven- ^N,D 'ience. Proposed ECN i=ple=entation may be deferred until after unit . ;.f>,' operation license. ., j;,.,..+ 3,,.] Justification for Selection of Category _ /= v tt pm f e a s'i r w m e d r a t t* cac i rnw s < n.e 4 a.. /?s,'o, do z.b~ _ A A)b //pnT /* A n A rc su 1~ e>n + o s /res) n / focopacyr s 'o _ TAs VM tit = Amms (((. 4. 25T Proceed With Further Consideration as Category 1$ or 3 (circle one) C Do Not Proceed With Further Consideration '~ J.!!-N EDN,

'nyt: :;<.hfQ?.: Qts 2 t,,

n oj L O M i /ts(tro ' 2Llh1/i&}d; ? ' Sect, ion SuDervian"

i llf S PROJECT ' arga./o t se/ A). A 6x#e/ Sheet 2 IJ Ho. _ [ [ $ ' I l q 5. Design and Procurement - Section Involve =ent - Schedule Duration f Work--Duration Bar Graph (Weeks /Nashhs) I( Branch Sup7 2 3 4 5 6 7 8 9 lo 11 12 M-H Dg.s No. m gu TT TT T T T T T T T s I I I -l l l l l l 1 m2 l l l l l 1 I l i I I I I I I I I I I I I 1 I I I l l l 1 I I I ) i I I i l I i l i I 1 I I I I I I I I I I l I I i i l i I I l l l 1 i l l l i l l I l _.. - ] I i i i i l i I I I 5* I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I i I I I I I I I I I I I r I I I I I I I I i i I ~4( I I I i i I i l i I I I I I I I I I I I I 6.)S v 'As vi 'e L d a s ,a h a n a -n/J 20 m-A.t 's , o. n.e i, '., 7.l Reemded Disposition and Re= arks pff,,,.,e / u N t +A, e d. m /,,*4 / h Avoin B e v 'p % = a r / %,s s, s / 12 FG UMtM Acoms. < / 8. Signatures dd%f2L% 2w k. Section Sup'ez riser Heyi/Pf6dect DYgineer Branch Chief Project Manag Q ' 9 Dicposition by Design Project Manager Proceed to Imple=ent Design and Construction Before Unit Initials Date Operation Licence ,..,....;., gg,,. -:..<. w,'%. d D ' Place in Control File foi Possible'I=ple=entatien;-Per ID qAPL, .s j..;. : Initials Date and EP 4.02 3. " ^ - ' "

.... s. L.53/ 3 _ * ,. n... n.s,. .9 4 88 4 %g..TV A e4 81s Ay# 9' '.a. UNITED STATES bOVERNMENT s. ENTemdrasdum TENNESSEE VALLEY AUTHORITY g::,:r:. Mi2 Kit? ADB '800827 o I._ .Q.$Togt~ R. W. Cantrell. Sequoyah and Watts Bar Design Proj ects Manager 204 C (2) jf$,<.sv..n...FR,0gs; Withers C. Adkins, Chief, Architectural Design Branch, W4C126 C .a; [ p r ~ 8 August 27, 1980 ' F,1 g,]iff.-Nff. gy.(

SUBJECT:

SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 - BLOW OUT ROOFS OF MAIN STEAM "T Sk J,." 2Rg '. '..

c,et::y.* p.

VALVE ROOMS .. &..,:. :.sh< :N y. a. y

f g Q.:ii...t L. ;; -

-h

ll >.;' f,.7......' We request that an ECN be issued in accordance with EN

.j.'nitQ. correct the roof system in order to prevent water problems on the east ., ;, ',:!j., and west ster.m valve rooms of unit 2 Sequoyah outage will issue a DCR ' i. to correct the roof damage for the eas.t and west st'eam valve rooms.p gm,,/~~/ The present roof has been subj ected to high te=peratures and exposure to moisture due to valve testing. Since testing, an additional exhaust fan s.ej; has been added to each roof area to relieve the high temperature and. moisture buildup. r Additional change to be made and to prevent reccurrence is as f.ollows: ^ o r. 1. Add vapor barrier and insulation to avoid moisture damage and high temperature to the plywood. . ;,.'t.; 2. Change plywood thickness and quality for durability. y "- ' 7 ~ 3. ' Change nethod of' application of the roof weather coating for greater ,f. flexibility. s .m v.a.;q... -..p. Drawing 46W403-3 vill b'e revised.to reflect these changes. .hypyp.t.%(.p. ~ e. co. s s,... w-kh !. '.k'.N.! f OHit551 SliFe'd Bi. I SWP g.,'.,:,3., g., c Howard A. Stucky .d.. ;+.. -,...-;-~..:. '( 9;. - Withers C. Adkins SE,, C ?,80 .i

..,~: .;' -

SKM:W N I SuDv Nrd ~ cc: ME S, E4B37 C-K l R.W.L! 4 JWCi .. r.v;. EHC j* DB '.1,. "i.;,. y,. R.B K. l GED ~ f- '.'i\\ _ / l JCK i ~ f.. p/ l-T l m ~n .w n.x,^$.- N.9$%.W. Mi.?@.4W. E..i M_g% l4'O.d.. h m h...;,n n.,.... v 4 & m u s s.$e m.MfN1$'.'@.,"..'.+ w.,.~ p, 4 T ~ ~.e. tem 6 ,' MEN 4 s M1T i',M.I ' Akk. mw.w =3E.'59.k.9*'t e~ s ~ w M 2: ' " '. ~ L ~~-

e i y' g c.. -SCOPE OF CH ANGE ESTIMATE UOYAN WCIF3.R PIAtIT ECII IiO. _L W W PR CT: 9b0 h TEi.A M ALST6 IJ IIO. ,ING: sur:4/ruwaE: b - W vAc- .I Requestad COIIST Contac 4 Unit 1 Procured B'/ PR, Regn, Deliver / For Ite:s Qty t ', (EIT DES /CC:!3T) or Contr Date Verificatio: GTkys %/4 " ExTsmoK 1 og 1 FLYW coo leolG W douGT'. WA e-rg vic.xsK4 ~ &L-h4ToHBRtc-s ca f R'c=op iM//h l(ofG H G M GT. NA-c.i r5 \\ h fE.THTLEMEi 6-%p I og VAPOR BAMRIEK IGIG k G o g G T. MA eite Fo4.M4 L.4.4:. og l k, Isl6 doNGT. N I IMULATlcM Gi-rg t ( 2h.?**.* A,'.! ' l G 6 b g e S = ._ ( i - ~ g k co=snts: . r, '. % i.*f. f *y nhQ ..=: := - -:.eA&s Red lQ 1 e

ENGINEERING CHANGE NOTICE NO. L53)A TENNESSEE VALLEY AUTHORITY c:^~c" M'D N ~' joivlSION OF ENGINEENNO DESIGN g ~ N :* Sequeyah Nuclear Plant. DaisL N PACE I . Tc: T ~ l besign Project ManagN9 m: Released By: { g gg WA Design Project Manager breparing Section MEOS Accession No. MED5 Accession No. NUCLEhQ blo. 2 R R "" * " 'd 9 WP '81 1218 530 d BY:D. M. K11 RRTHDQPE Tctal'Pages (RO): 3 R R 'la, "en'," 3 c.R R 2 6 Architect; [ WkiM U); % "w{Mk1gaw - SCOPE Project MEhllCVMM M//c1 FAR Pl_ ANT Affected Units l Systern or Feature EAAT Ah)D WE.ST ATE A AA t/A,LVE - ROO AA A Reference & Description of Change QE\\/ISE ROOF DESlGN TO PREVENT WATER PROPLEMA. EXISTIMG ROOV MA% AEEN A IniEC.TED TO MiGM TE M OFRATuF2E5 Ayb EXPDAURE TO MOlbTURE~ ~ DL1E TO VALin TE%T/ AIC,. { %= ..r-s..' ',).* s-h r:' f:; ** a .1t. h n j .p. SEE ASSOCIATED DRAWINGS LIST, REVERSE SIDE l I'EV. DATE P R E-SECT. GROUP 3 RANCH ECN O.P. N O. 155UED PA RCO SUPV. HEAD CHIEF C'.ERK MOL DESCRIPTION OF REVISION TOTAL PAG ES b ... N o. p0 f P, S Field Materials as follows: ,, g,gy i i Additionallnforrnation:,scE,9 cope of cNANCE ES DMA7E, //N/7 2 CNWCE AMEdN

____--___.-___________________J_____c@-

~tA Q l 1 Chief. Architecturat Design Branch,W4C126 C K Chief. Electrical Engineering & Design Branch,W2D224 C K . ~.~n t Chlef, Civil Engineering Branch,W9D224 C K 4 Chief, Civil Engineering & Design Branch, W3Cl26 C K Chief. Mechanical Engineering & Design Branch,102SPT K j MEDS, E403 7 C K ... 4.0 * 'd

s TENNESSEE VALLEY AUTH* ITY oivision or EN:ilNEERING Olsl:N ENGINEERING CHANGE NOTICE NO.

/'83 /3 ~ DATA SHEET NO. / PAGE Q s .,,9 l AFFECTED OWG ISSUE DATEY' I UNIT DRAWING OR B/M NUM8ER REV.,EXPECTE M CTUAL g REMARKS DAT. r REV. c.3.vg i / 4GW4&2 l2 W A2u 23 9) 'x \\ / 46WWJ-0 // MM /2*2HI l i ! ' /N *,'3 f g .s s. : I li f j;,. ' I I 3 i I l i I I f I t l 1 i I i i i f. I l (: I f I f I l I l c '.*.M is'. I l I ,I -~~ I I I l l 4 l I 1 i i I I i I l I f _ l ~ l ~ l I J. e l y

m S u s,&

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"w as h ' ' ',.

~.,rj,* .,g e 'q y e

.+ 0,,, ENGINEERING CHANGE NOTICE /

COVER SHEET SWP

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- jk (OAla Sheell Required)

No Ava.f able

I Thermal,l'nwer Engineering neanches Wb in' W u mm

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.Q)[of'. ~ ,a_./r.L,'()* f j ro.ieet nr v ._ t o ica nnainoce neanuenhc-==(yc' ..= pj(cuan supervisor ngat ntnpa:ition by Desica Per.1""L thna:'."r 9 I, I V.ccw n'. 10nir,n r.nu C,suut.ruut.lon Nrurt Unit Mu/ C. - '/ //.f.[p 1 rocci"t nate on.cni.". i,i m..in e Y iii. p a n . r nu t. pii : ille t t'..) n p t. " nl.al.liin pt, c l11 t),.\\ t'. !f. l' f,f i i l'., e pg.g. . t,,,, i ...it- .,i a g I e w

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ATTACHMENT 4 a + = i l O e y = e

INSTRUMENT SEPARATION WALKDOWN INFORMATION BY: INSTRUMENT PROJECT SQNP TABLE OF. CONTENTS I.

SUMMARY

"f' II. DNE CALCULATIONS ~ . J' A. SQN-ISL-001 B. Information on 2-LT-63-176 III. SPECIAL MAINTENANCE INSTRUCTION s A. SKI-0-317-61 IV. DATA SHEETS 8.14 WITH APPROPRIATE 8.1 DISCREPANCY SMEETS V. RESULTING CAQR'S A. SQP870478 B. SQP871099 C. SQP871148 D. SQP880122 VI. REDUNDANT INSTRUMENT LINE SLEEVE WALKDOWN A. Purpose B. Results O 4 /t 1693E 6 A 4

C I

SUMMARY

CAQR 87-014 was written February 27, 1987 and identified potential separation violations of instrument lines. However, drawing 47W600-133 provided separation requirements for instrument line installations and SNP Inspection Instruction B1 was in place during the plant construction phase to ensure the original instrument line separation acceptability. To resolve the separation concetTt, ECNs and DCNs a re reviewed to identify safety related instrument lines that have been insv iled/ reworked since plant licensing. A calculation (see Section II) that encompassed these lines was issued to document the scope and the attributes to be inspected by field walkdowns. l SMI-0-317-61 was written to provide field walkdown and inspection instructions for unit 2. From these field walkdown inspections, discrepancies were documented, restart determinations made, and dispositions provided via 8.1 data sheets (see Section IV). Resulting CAQRs are contained in Section V. s In addition, a field walkdown was conducted to verify that no redundant ( sensing lines within the scope of instruments identified in section VI were. routed through common sleeves. This walkdown identified no separation problems., Sections II thns VI of this package provide the basis for the determination of acceptability for instrument line separation for SQN unit 2. 4 e- .--a j 1693E

U$-) YSNES M 54 G. 4 l {,, rya toser tone 44el DNE CALCULATIONS g. g l

'. *l> TIT L ESo-CA R-87-6/4 TMSTRUMENT IMSPECT/od 1./ST SEQUsYAW UNI T 2.

rLANT/ UNIT f PR EP ARING QRGANIZATioN

KEY NOUNS (Consult RIMS DESCRIPTORS LIST) l DME-EEB

/STRUMENT MOUNT /NG. (UAl.XDowd, INSPECT /CM l SR ANCM/rROJECT loENTiFIER$ Eun im these ceiculet,ons are 5#wed. P'eDe'eri must ensure that she ochenes (Roj pgMS uceuion l ggj,,ISL-00l " ' RiuS un) awS acceuion nun +e ao 87o 925t.co4 l B25 870918 802 7,ruCua oEsicN ooCuuENTisi a' B712llFCOO4-B25 871202 800 a2.,.r.u., vmm um y B25 871223 805 . Aps,.)1,o~is,g,gEgs, g INFORMATION ONI.Y Revision 0 R1 R2 R3 Sa f ety< elated ? Yes @ No O ECN No. (or endeut. Not Appeecsbiel W N /A ^ Statement of Problem '""'"h.} Q & Qf f }{,LQ IDEUTIPY TMSTRUMENTS / // ? >Y> i SQ-CAR-87-0/4 TYPE fb $$H Mod-COMFORM AMCE IDWMJ2:Jh5wa.numu seroRe-w!:r-2 nesrar O F UN IT 1 AN D UNIT.2.. R2. / o a g 7g$ 2 bl7j77 ItlWld List all pages added FA,5 8, $C ( j== by this revision. E list all pages deleted }, by this revision. O I G T X A L. "' s'"# tar" 2< v o,t,s.t These alculations contain an unverified assumption (s) that must be verified later. Yes O No @ 7//E INSTRUMENT 7~48, CDMTROL. D244'utNG 5, Lostc D24w/dG6 AA/D Stu2 ZD DRAld/NGS tvERE REV/EWED To. IDENTIFY THE TMSTR UM EMT.S TD BE INSPECTED FOR Sq -CAR 0/4 7*YPE Mod-CCAlt=0RMANCE. 77/0CE JMSTRUMENTS' ARE TABul4TED /A/ 74BL.E.f AND LISTED SEPARATEg FOR UNrr i AND A RESTMT-92 3 q.ha n/a1 hrs RA OF Till3 C/\\LCMLATION CONTAIN3 18 6 HELTS, G'f CLu DItK. TMG. CO U EA SHEET

AND REtitsloN PMG Ro of TM/S CALCUL ATiod CoNTA/N3 // Si/EETS EXCLUDING THE

( COVER SWEET AWO REV/Slad P4GE. RI cf 71ll3 cat.cutArioA! CCHTAINS I4 SHEETS E<CLUD/MG ING CcVER. -SHEET AND REV/SICM PAGE O u4,.um.~o,io,. u,,,,,,,oes on Rivs se,..ee C.eier. u..,.um. .i,.v. O J v4,.u m.so,... uie.ui,0. o: Jr. ST4uB Osc-p[spN toore..: cc: RIV$.3L M C K

.. -..44-4:lWJNIde='

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REVISION LOG rine: SQ. CAR-87-of4 TMSTRUMENT TMSPECTIod LIST SGM - ISL-co l 8 'y,',' " DESCRIPTION OF REVISION 4,,N',.4 CALCOL ATIDN 15 REvl5ED To PROVIDE ADDITIOMAL TAFORMATIOM AMO CLARIFICATION.No CHANGES VIERE l MADE To 7HE LIST OF INSTRUMENTS IM TABLE 1. lifM[g7 ALSD. RI o. THIS CALC REPLACE.5 THE RO I OR I G lh Al.. 4HICH H45 BEEd MISPLACED. .. L '- 2,., CALCULATlo,9 REVISED TO CLA#.lFY TABLE 1 geausoin n vn enn m remn-o *.wr/ THAT U N17 P.3AND UNIT I INSTR.l4MENTimg,ARE57 ) gm q, /E LISTED 5E0httATELY. ALSO ADDED l-TS-20-103,lo3A i AND.1-TS 104, lo4A To TABLs 1 Dus To LEVIS)bN To N FB CMcut.ATroM SdN-OSG7-048, AND R Ebl5ED THE. REVISION NUM0ER. oF THIS CAlc NED IN *kEFGC. ENC ES"5 E0. Tion. e e O d* N? ~........ ~..... >., ....g h*5' ..k$.k O

4 REFER ENCES- @ SQ, CAR c/4 @ SYSTEW1 k/dbilDOW / BoudDARY' ZDENT/h*/CA TICA/ g D2Ak//NGS (SWBID), REV. : 6 @ SEQUDYAN CONTROL D2.gwir/GS 47Wroto tentes @ SEQuoYAH tosIC ORAw/ ass 47wtoll Septgs @ 3E9uoYhH zasrRumear 748 47840/ seetes $ SEQUOY AH cournol oggwtass 4,W367.sepigS @ (NOCLUAR, EA1614EER,lMG SRANCH 9 CALC., SQ M -056'l -048 s2ys'702.2aeis) as 4 e c ()g0ch 10/5/j,] OIP l dent _W'W~E l 7j

1. 1. L sh~2 CIO1R

<l L h (' 1 Prep W.9% 8/f/97. glp -ld entM-1SL-Mt Chk kd f/nh7-sh 2 ClO 3 R O2

.mari%;A4. %,.en%\\Q4h,
~ ~ -

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Cr AN ALYSIS - SQ-CAR-87-c(4 IDEUTIFIED VARioUS IMsTRUMENT IM6 TALL ATioM COMFl6URAT/oNS TN AT DID NOT COMFORM To DRAWINGS OR IMSTALLATION SPECIFIC ATioNS. THESE ITEMS WERE DlLCOVERED DURIMG RourIME AMD RAMCOM IMSPECTIDN S PER SMI 315-SO AMD 3 SMT.-O- $ n-S'2. EXAM PLES OF SOM E cF TH E ~ ~ M0d-C0dFCRMIM G ITEMS ADD RESSED BY CAR-87-Ol4 b ARE.: R1

l. DAMA6EB INSTRUMENTS

2. LOOSE AMD MISSIMG NOTS AND EOLTS

3. DAMA6ED IMSTRUMEMT SUPPORTS

4. LcOSE AND MIGSIMG IMSTRUMENT. UNE CLAM.PS S. DAMAGED AMD TMCOlFREGTLY stoPED IMSTRUMEMT SEMSE LIMES THIS 15 oMLY A PARTIAL LISTlM6 0F THE MOM-CodFORMl46 ITEMS, A toMPLETE LISTIM6 OF THE ATTRIsuTES pog prep 8 ellos /0!5/87 BIP l den l50Al-TSL-601.

ChkO A N' M /'/5"M' Sh 3 cio 3A ai / ."w:;yyp}.' abd$$$dSid$Iih.~.dkNNEd$

C. c, WWICH THE INSTRUMEMTS WILL BE' TNSPECTED ARE GNEM IN SMI En-61. THE NUCLEAR ENGIMEERING BRANCH PERFORMED l' A CALcu LATioM (S44- 0SG7-6+8) To DETERMIME THE MidlMUM SET OF SY'57 EMS oR PORTIONS OF SYSTEMS THAT ARE REQUIRED To MlTl6 ATE CERTAId SELECTdD EVEAJTS DESCRIB ED IM CHAPTER id ~ fME FSAR 'AND To PREVENT OFFSITE DOSAGE IM 4 r EXCESS OF TH E LIMITS PRESCRI BED BY 10CFR100. THESE SYSTEMS AND FbRTIONS OF SYSTEMS ARE IDENTIFIED OM A SET OF DRAW /NG S KNOWd AS THE SYSTEM WALkDOWM E00MD ARY IDEMTIFICAT?Od DR AWINGS (SW BID). SECrlOM 7. l. I OF THE FSAR IbENTIM.E5 THE ELECTRICAL AMD I.fC SYSTEMS REQUIRED To a FUNCTIDW To ACHIEVE THE SYSTEM RESPodses [ ASSOMED IN THE SAFETY EVALUATIDMS AMD THOSE-L Pre O B Wifur ic/S/87 ChkO A'V/E'NA-/r? BIP ident SOM-TSL-Q sh 3A C/0 % RI tbs $.. 4

MEEDED TD SHOT r,0WM THE PLANT SAFELV. THE i Ij'C SYSTEMS LtdTED ARE RCACTOR TRIP SYSTEM \\; EN6f MEEEED SAFETY FEATURES ACTUATlaN SYSTEN\\ (E?.2AS) AND SAMETY RELATED DISPLAY IMSTRUMENT-ATIOM WHick TVA REFERS ~ To AS F6ST-AcclDEMT MoulTORIN6 (PhM). i T4EREFcRE;THE IMSTRUMENTS Tb BE NSPECTE D FOR Nod-f_cWFol?M AN C E WOULD BE mosE R\\ \\ PROCESS SEMSifG TMSTRUMENTS LulTHirJ 7HE I B00dD ARY OF TME SNBID LRAWINGS KJHicH PROVIDE l AM JtJPUT To THE REACTOR PROTECTlod SYSTEM (RPS';, THE ESFAS SYSTEM OR PAM AND WERE INSTALLED i I i BV 'lVA. IOSTRU M E M T 5 IMSTA LL ED BY TH E VEN Do R i l OM HIS PACKAGE OR Skib WERE THE RESPoMslBILITY ) qi l OF TIE VeMDOR AMD ARE EgcLUDED FROM THE l l TuSPEGTlotJ LIST.. ~ Prop 5/6 (/</to. /o/5-/s7 I co-Q n WL w,in_ 8/P ident MM-ISL-Col g sh.3.L.cto 3' n I L

r i THE PROCESS SENSIM6 TMSTRUMENT.S WNic)4 MEET 714E FOLLOWIN6 CRITERI A WILL BE INSPECTED 1 FOR NOM-60tJFoRMIM6 CON DiTioNS :

1. INSTRUMENTS VJiWIM THE BouMDARY oF THE SW51D DRAWIN65 (REQUIRED To MlTIGA i ACCIDEt4TS)

2. TMSTRUMEMTS ItJSTALLED BY TVA otJ LocA L PAMELS (VEMDoR INSTALLED IMSTRUMENTS AR5 EXCLUDED) 3, IMSTROMEMTS WHICH PROVt DES ctdE OR MORE OF,T14 E FOLLONIM6 '.

gi A) AM IMPUT To THE REACTOR PROTECTION GYSTEM (RPS) OR B) AN ItJPUT FoR POST-ACCIDENT MotJITORING (PAM) oR c) PERFORMS AM EM6f MEERitJ6 SAFEGUARD ForacTrotJ ~ _ - THE IMSTRUMEMT TAB CoMTROL DRAkitrJ6 s 3 Lc6fc 3 IRAWIN6S AMD SNBI'D DRAWlMG S' WERE REVIEWED To IDEMTIFY THE PROCESS SEMSIM6 ItJSTRUMENTS t( -0 8 OdA*-/f/S/e7 8/P l dent M-ISL-M / Prop &NYlMW'M*O Chk / Sh 30 CIO A R l 3 V I- _ -f W. m.- - g

. U .r 1 4 s WdlCW M EE T T11 E CR I TE R./ A Ll' TE D ABoV E. THOSE ItJSTRUMEAJTS ARE TABULATED ltd Rl l TABLE 1. b l l i i ) J J 3 l' ~ i . =

e..

i I 4 4 i ~ 7*- J i s l l - !I a ( .c 1 2. .I. m.y... ..-j .r.. Prep OA LA'ffe" ny'v/ny W .~ BIP idenl MA-TSL -nol Chk // Y k,f/, w, l Sh 4 _C/O g _ R-f -- -q' 1 i 4 4 4 y -'.. 4f f-s.~

= s ~ v Y

w ..w

r. s.

. -..M ) '%f 1 +,-v. ...y w 5- . w .'mw-- @m = :. a 4.b e, ., - - *4% { _y i - p=, mas, ..e 'e., . m sw ** ' '=e ne

~ ~ TMW \\ y8 ai,,isci PAgo No. -F-h 12/17/87 R ESTA A7-UNIT 2AINSTRUMENTS FOR SQ-CAR-87-14 C ALCULATION SQN-ISL-001 RS-PREPARED J/R 6pQ I,2.- 17-17 CHECKED s MM.7Mk.12'17' 87 UNIT INST SYS LOOP PANEL LOCATION IN SLOPE SEPARATION WLXDN v2* PT 01 002 A L-196 UA14 690-0 Y 2 PT 01 002 B L-197 VA14 690-0 Y Y '2' FT 01 003 A L-182 Y / 2' FT 01 003 B L-183 Y / 2' PT 01 005 L-102 UA14 706-0 Y s2 PT 01 009 A L-194 Y Y ,2 PT 01 009 B L-195 Y Y /2 FT 01 010 A L-182 Y /2 FT 01 010 B L-183 Y /2' ' PT 01 012 L-106A Y $2 TS 01 017 A Y .2 TS.01 017 B Y 2' TS 01 018 A Y .2 TS 01 D18 B Y 2-PT 01 020 A L-194 Y Y Y 2' PT 01 020 B L-195 Y Y j /2 FT 01 021 A L-182 Y ~ 2 FT 01 021 B L-183 Y

2-PT 01 023 L-106A XA14 706-0 Y

/2 PT 01 027 A L-196 UA14 690-0 Y ' 2' PT 01 027 B L-197 VA14 690-0 Y 'Y / /2 FT 01 028 A L-182 Y /2 FT 01 028 B L-183 Y /2' PT 01 030 L-102 UA13 690-0 Y s 2' PT 01 072 L-109 Y i < 2' PT,01 073 L-110 Y /2 FT 03 035 A L-68 Y Y V2' FT 03 035 B L-58 Y Y ,/ 2 LT 03 038 L-183 Y /2' LT 03 039 L-184 Y /2 LT 03 042 L-185 Y '2 LT 03 043 L-185 Y v/jl FT 03 048 A L-68 Y Y /2, FT 03 048 B L-58 Y Y p' 2' LT 03 051 L-182 Y 2 LT 03 052 L-184 Y sd! LT 03 055 L-185 'Y rdt LT 03 056 L-185 Y ~ v2 FT 03 090 A L-68 Y Y /2 FT 03 090 B L-58 Y Y /2 LT 03 093 L-182 Y .<2 LT 03 094 L-184 Y ,2 LT 03 097 L-185 Y f 8 2 LT 03 098 L-185 Y j 2 FT 03 103 A L-68 Y y i .' 2 FT 03 103 B L-58 Y Y i / 2-LT 03 106 L-183 Y . ~. ..x.-. ,.ua.. ... ::.n' b.ty : .-- Y

TA3LE I ~ 4'Pcgo Ns. 4k '7 ,bf6 i h #i? REs7AKT-i 12/17/87 UNIT 2 INSTRUMENTS FOR SQ-CAR-87-14 3CALCULATION SQN-ISL-001 R2. PREPARED:./fq /164/J2 Ji//7/t/ CHECKED:#$P A

2////#7 UNIT INST SYS LOOP PANEL LOCATION IN SLOPE SEPARATION WLXDN 2

LT 03 107 L-184 Y ,2 LT 03 110 L-185 Y ,2 LT 03 111 L-185 Y 2 PS 03 121 A L-215 Y Y $2 PS 03 121 B L-215 Y Y .2 PS 03 121 D L-215 Y Y .2 PS 03 138 A L-431 Y /2 PS 03 138 B L-432 Y .2 PS 03 139 A L-214 Y Y < 2' PS 03 139 B L-214 Y Y ,2 . PS 03 139 D L-214 Y Y v2 FT 03 _1 <4 2 L-215 Y Y s2 PS 03 144 A L-222 Y Y 2 PS 03 144 B L-222 Y Y v2 PS 03 '144 D L-222 Y Y .2 FT 03 147 L-217 Y ,2 LT 03 148 L-183 Y .2 PS 03 "148 L-440 Y .2 FT 03 155 L-217 Y

,,2 LT 03 156 L-184 693-0 Y

./ 2 PS 03 156 L-439 TA13 714 Y 2 FT 03 163 L-216 Y ,'.,2 LT 03 164 L-184 693-0 Y ./ 2 PS 03 164 L-439 TA13 714-0 Y / 2 FT 03 170 L-216 Y v2 LT,03 171 L-183 Y /2 PS 03 171 L-440 Y .-2 LT 03 172 L-417 'Y .<2 LT 03 173 L-178 Y <2 LT 03 174 L-178 Y v2 LT 03 175 L-417 Y 2 PDT 30 042 L-186 AZ290 704 Y Y ,-2 PDT 30 043 L-188 Y Y 2 PDT 30 044 L-189 Y Y 2 PDT 30 045 L-133 Y Y ,. 2 PS 30 046 A L-140 Y Y ,2 PS 30 046 B L-142 'Y Y ,2 PS 30 047 A L-140 Y Y 2 PS 30 047 B L-142 Y Y 2 PS 30 048 A L-146 Y Y , 2 PS 30 048 8 L-83 Y Y 2 TS 30 104 Y [ .'2 TS 30 104 A Y -1 FS 30 146 Y 1 FS 30 147 Y 0 TS 30 147 WAS 714-0 Y .O PDIS 30 148 0-L-428 Y ,, ;,g3, ,.,. s 'e ','4[~10 iki5)'id[sNNSk'hk :. .'O e r e

TA8LE I Pcg3 No. --3 8 i 12/17/87 A4 W'7/87 RESTAfi' UNIT 2 INSTRUMENTS FOR SQ-CAR-87-14 A CALCULATION SQN-ISL-001 R A. l PREPARED 2/ gge/,,( ji//7/((/ i CHECKEDs)$g & l1//7/fy UNIT INST SYS LOOP PANEL LOCATION IN SLOPE SEPARATION WLXDN O PDIS 30 149 Y 2 _ FS 30.156 Y 0 TS 30 156 Y 2 FS 30 '157 Y 2 FS 30 184 Y 2 TS 30 184 Y 2 FS 30 185 Y 2 TS 30 185 Y 2 FS 30 186 Y 2' TS 30 186 Y 2 FS 30 _187 Y 2 TS 30 187 Y 1 FS 30 190 Y 1 TS 30' 190 Y 1 FS 30 191 Y 1 TS 30 191 Y ~ {( ,O FS 30' 192 Y 0 TS 30 192 Y k-0 FS 30 193 Y 0 TS 30 193 Y 2 FS 30 194 Y ~ 2 TS 30 194 Y 2 FS 30 195 Y .2 TS 30 195 Y 2 FS 30 196 Y 2 Ts 30 196 Y 2 FS 30 197 Y .- 2 TS 30 197 Y 2 FS 30 200 Y 2 TS 30 200 Y .2 FS 30 201 Y 2 TS 30 201 Y 2 FS 30 202 Y 2 TS 30 202 Y , 2 FS 30 207 Y l 2 TS 30 207 'Y 2 PT 30 310 L-188 Y 2 PT 30 311 L-189 Y 2 FS 300 448 Y 2 FS 300 450 Y 2 FS 300 452 Y f 2 FS 300 454 Y O FE 31 484 - LOCAL Y O FS 31 484 L-395 Y O FE 31 487 LOCAL Y 0 FS 31 487 L-395 Y 0 FE 31 492 LOCAL Y .:..:,m: a..0 ..;..: ~. 9.k*. *, p,. to g,

TABLE I l' Pago No. -+ 9 { 12/17/87 hio RESTMT 8 4 7/67 UNIT 2AINSTRUMENTS FOR SQ-CAR-87-14 CALCULATION SQN-ISL-001 R d. PREPARED: hy%, Gell.11/l?/%7 fl CHECKED s NN /2/n/47 UNIT INST SYS LOOP PANEL LOCATION IN SLOPE SEPARATION WLXDN .0 FS 31 492 L-394 Y 0 FE 31 495 LOCAL Y .O FS 31 495 L-394 Y 0 FS 311 008 Y .O FS 311'010 Y i 0 FS 311 020 Y 0 FS 311 023 Y O FS 311 027' Y O FS 311 028 Y O' FS 311 033 A Y 'O FS 311 034 Y .' O FS 311 035 A Y O FS 311 035 B Y O FS 311,~108 Y Y O FS 311 109 Y Y 0 PDIS 313 305 Y 0 FS 313 318 Y ,,O FS 313 327 Y O PDIS 313 340 Y ~ 0 FS 313 353 Y O FS 313 362 Y O FS 313 381 Y Y 0 FS 313 382 Y Y .O FS 313 389 Y Y 'O FS 313 390 Y Y j1 FS 313 425 Y Y /0 FS 313 426 Y Y 1 FS 313 439 Y 1 FS 313 446 Y 1 FS 313 447 Y /1 FS 313 450 Y Y /1 FS 313 451 Y Y ,1 FS 313 465 Y 1 FS 313 472 Y 'l FS 313 473 Y ,' 2 FS 313 475 Y Y 2 FS 313 476 y y 2 FS 313 489 Y 2 FS 313 496 y , 2 FS 313 497 Y 2 FS 313 500 y y .2 FS 313 501 Y y ( 2 FS 313 515 Y 2 FS 313 522 y 2 FS 313 523 y j 0 PS 32 062 L-221 Y j O PS 32 082 L-221 y

~..v

.:MR -:p., l).4.::.. ;.. h. '?.'.%5is. --- j

i lit 5 Lt I - + 10 Pcqo No. 12/.17/87 Gel *fM .4ESTAff" UNIT 2 INSTRUMENTS FOR SG-CAR-87-14 3CALCULATION SON-I L-001 K1 PREPARED: /2.622 /2.//747 CHECKED: gg /2//7/(7 6 S. OPE SEPARATION L UNIT INST SYS LOOP PANEL LOCATION IN l WLXDN e0 PS 32 085 L-235 Y ,O PS 32 088 L-235 Y Y 2 PS 47 073 Y l . 2 PS 47 074 Y )'2 PS 47 075 y2 LT 63 050-L-344 Y ,2 LT 63 051 L-453 Y Y 'h 2 LT 63 052 L-452 i /2 LT 63 053 L-345 Y 2-LT 63 176 L-182 Y Y f2 LT 63 177 L-183 Y Y 2 LT 63 178 Y Y ,/ 2 LT 63 179 Y Y f O FS 65 025 A Y y0 FS 65 02,5 B Y O FS 65 031 A Y O FS 65 031. B Y g 0 FS 65 044 A Y O FS 65 044 B Y ,O FS 65 055 A Y f0 FS 65 055 B Y 2 PDT 65 080 L-342 WA12 714-0.Y Y

'2 PDT 65 082 L-341 WA12 714-0 Y Y

'2 PDT 65 090 L-342 Y Y ',2 PDT 65 097 L-341 Y Y

/ 0 FS 67 206 L-198 Y

Y (/ 0 FT 6,7 206 L-198 Y Y /0 FS 67 209 L-494 Y Y /0 FT 67 209 L-494 Y. Y /0 LDT 67 470 0-L-400 Y /0 PS 67 471 0-L-400 Y <0 PS 67 475 0-L-401 Y s' O LDT 67, 477 0-L-401 Y /0 PS 67 480 0-L-402 Y ,. O LDT 67 482 0-L-402 Y O PS 67 485 0-L-403 Y I ,/ 0 LDT 67 487 0-L-403 Y 2 PDIS 67 490 A L-416 Y. 2 PDIS 67 490 C L-416 Y 2 PDIS 67 490 E L-416 Y 2 PDIS 67 491 A L-415 Y [ 2 PDIS 67 491 C L-415 Y 2 PDIS 67 491 E L-415 Y ,2 FT 68 006 A L-226 Y 2 FT 68 006 B L-227 Y ! {( 2 FT 68 006 D L-228 Y s. ,2 FT 68 029 A L-226 Y ..l .'.:.ll:g,.. hf..j 0. $i... e,:U..b 2 5%4'

1. -

,.y.g ~ -,.

4 j ~ r, POg3 Ns. 11 12/17/87 M4 88/0/" ~ ItE57 ART" UNIT 2 INSTRUMENTS FOR SQ-CAR-87-14 3 CALCULATION SQN-ISL-001 RC. PREPARED:jf 9 A St/412/l?/87 i CHECXED: gj h /2//7/f7 1 UNIT INST SYS LOOP PANEL LOCATION IN SLOPE SEPARATION l i WLKDN ) i 2 FT 68 029 B L-227 Y t 2 FT 68 029 D L-228 Y .2 FT 68 048 A L-226 Y .2 FT 68 048 B L-227 Y 2 FT 68 048 D L-228 Y j ./ 2 PT 68 066 L-340 Y Y 2 PS 68 066 A L-358 Y 2 PS 68 066 D L-358 Y .2 PT 68 068 L-360 Y Y a f 2' PS 68 068 A L-359 Y 2 - PS 68 068 D L-359 Y f>2 PT 68 469 L-388 Y Y 2 FT 68 071 A L-226 Y 2 FT 68.,071 3 L-227 Y l ,2 FT 68 071 D L-228 Y 2 LT 68-320 L-454-Y Y Y i 2 PT 68 322 L-142 Y Y Y l ,' 2 PT 68 323 Y Y Y 2 PT 68 334 Y Y 2 LT 68 335 Y Y 2 LT 68 339 L-179 Y Y i 2 PT 68 340 L-179 Y Y f1 LS 70 209 A L-429 Y 1 LA 70 209 B L-497 Y 2 LS 70 210 A L-496 Y ) j / 2 LS.70 210 B L-428 Y ] v' 2-FT 72 013 L-287 Y Y 2 FT 72 034 L-288 Y Y 2 FS 74 012 A L-5 Y Y '2 FS 74 012 B L-5 Y Y 2 FS 74 024 A L-22 Y Y ./ 2 - FS 7,4 024 B L-22 Y Y q 2 LS 87 021 L-490 Y 2 LS 87 022 L-492 Y 2 LS 87 023 L-491 Y

2 LS 87 024 L-493 Y

e e i d - l .... ;.l ; c- . t p0.g;i'..:3, . a .1 *. 4, ,,, ei ? ,, y . '.,,'i e i 3. ... w.. -. a...,,.. . ? _e. u ~ ~ >,,,

TABLE I .(,PcgoNo. 1A 12/17/87 RESTMF UNIT 1AINSTRUMENTS FOR SQ-CAR-87-14 CALCULATION SQN-ISL-001 E1 PREPARED: 49 it. /3e# 11//7 /f 7 CHECKEDs j y & 12/tTl47 UNIT INST SYS LOOP PANEL LOCATION IN SLOPE SEPARATION WLXDN 1 PT 01 002 A L-196 UA14 690-0 Y 1 PT 01 002 B L-197 VA14 690-0 Y Y 1 FT 01 003 A L-182 Y 1 FT 01 003 B L-183 Y 1 PT 01 005 L-102 UA14 706-0 Y 1 PT 01 009 A L-194 m Y Y 1 PT 01 009 B L-195 Y Y 1 FT 01 010 A L-182 Y 1 FT 01 010 B L-183 Y 1-PT 01 012 L-106A Y 1 TS 01 017 A Y 1 TS 01.017 B Y ~ 1 TS 01 018 A Y 1 TS 01 018 B Y 1 PT 01 020 A L-194 Y Y 1 PT 01 020 B L-195~ Y Y 1 FT 01 021 A L-182 Y 1 FT 01 021 B L-183 Y 1 PT 01 023 L-106A XA14 706-0 Y 1 PT 01 027 A L-196 UA14 690-0 Y 1 PT 01 027 B L-197 VA14 690-0 Y Y 1 FT 01 028 A L-182 Y 1 FT 01 028 B L-183 Y 1 PT 01 030 L-102 UA13 690-0 Y 1 PT 01 072 L-109 Y 1 PI O1 073 L-110 Y 1 FT 03 035 A L-68 Y Y 1 FT 03 035 B L-58 Y Y 1 LT 03 038 L-183 Y 1 LT 03 039 L-184 Y l 1 LT 03 042 L-185 Y 1 LT 03 043 L-185 Y 1 FT 03 048 A L-68 Y Y 1 FT 03 048 B L-58 Y Y 1 LT 03 051 L-182 Y 1 LT 03 052 L-184 Y 1 LT 03 055 L-185 'Y { 1 LT 03 056 L-185 Y 1 FT 03 090 A L-68 Y Y I 1 FT 03 090 B L-58 Y Y i 1 LT 03 093 L-182 Y 1 LT 03 094 'L-184 Y 1 LT 03 097 L-185 Y l [ 1 LT 03 098 L-185 Y N. 1 FT 03 103 A L-68 Y Y l 1 FT 03 103 B L-58 Y Y 1 LT 03 106 L-183 Y t. ~. <.. u;.. [,:(.M.k M h '.. '-?.'h L...'..4,tN;Y,dTa}. s. , - G g.,, - - - . r.b. ,w.t, <,

t TABLE I P0go No. -r 13 '12/17/87 kns salo?M RESTART' ' UNIT 1 INSTRUMENTS FOR SQ-CAR-87-14 3 . CALCULATION SQN-ISL-001 R2. PREPARED: (1 12./l? /g/ CHECKEDs y y (1pyjgj UNIT INST SYS LOOP PANEL LOCATION IN SLOPE SEPARATION WLKDN 1 LT 03 107 L-184 Y 1 LT 03 110 L-185 Y 1 "LT 03 111 L-185 Y 1 PS 03 121 A L-215 Y Y 1 PS 03 ~ 121 B L-215 Y Y 1 PS 03 121 D L-215 Y Y 1 PS 03 138 A L-431 Y 1 PS 03 138' B L-432 Y 1 PS 03 139 A L-214 Y Y t l' PS 03 139 B L-214 Y Y 1 PS 03 139 D L-214 Y Y 1 FT 03__142 L-215 Y Y r 1 PS 03 144 A L-222 Y Y 1 PS 03.144 B L-222 Y Y 1 PS 03 144 D L-222 Y Y 1 FT 03 147 L-217 Y 1 LT 03 148 L-183 Y 1 PS 03 ' 148 L-440 Y 1 FT 03 155 L-217 Y 1 LT 03 156 L-184 693-0 Y 1 'PS 03 156 L-439 TA13 714 Y 1 FT 03 163 L-216 Y 1 LT 03 164 L-184 693-0 Y 1 PS 03 164 L-439 TA13 714-0 Y 1 FT 03 170 L-216 Y 1 LT 03 171 L-183 Y 1 PS 03 171 L-440 Y 1 LT 03 172 L-417 Y 1 LT 03 173 L-178 Y 1 LT 03 174 .L-178 Y 1 LT 03 175 L-417 Y 1 PDT 30 042 L-1C6 A2290 704 Y Y 1 PDT 30 043 L-188 Y .Y 1 PDT 30 044 L-189 Y Y 1 PDT 30 045 L-133 Y Y 1 PS 30 046 A L-140 Y Y 1 PS 30 046-B L-142 Y Y 1 PS 30 047 A L-140 Y Y 1 PS 30 047 B L-142 Y Y 1 PS 30 048 A L-146 Y Y 1 PS 30 048 B L-83 Y Y 1 TS 30 103 Y j ( 1 TS 30 103 A Y j 1 FS 30 186 Y I 1 TS 30 186 Y { 1 FS 30 187 Y 1 TS 30 187 Y ..s. ..7, ..d.( # .$.h!$NP ! y" ...... -. _,.ty.. ,9 j

'*\\,Pago No. ~~3-I4 12/17/87 M6 IM4%1 RE57MRT UNIT 1A INSTRUMENTS FOR SQ-CAR-87-14 CALGULATION SGN'ISL'001 RA PREPARED: J/gy 4 M J.1//7/$'7 CHECKED: gg 12/ v/g7 UNIT INST SYS LOOP PANEL LOCATION IN SLOPE SEPARATION WLXDN 1 FS 30 194 Y 1 TS 30 194 Y 1 FS 30 195 .Y 1 TS 30 195 Y 1 FS 30 '196 Y 1 TS 30 196 Y 1 FS 30 197 Y 1 TS 30 197 -Y 1 FS 30 201 Y l' TS 30 201 Y 1 FS 30 202 Y 1 TS 30 202 Y ^ 1 PT 30 310 L-188 Y ~ 1 PT 30. 311 L-189 Y 1 PS 47 073 Y 1 PS 47 074 Y 1 PS 47 075 Y 1 LT 63' 050 L-344 Y 1 LT 63 051 L-453 Y 1 LT 63 052 L-452 Y 1 LT 63 053 L-345 Y 1 LT 63 176 L-182 Y Y 1 LT 63 177 L-183 Y Y I 1 LT 63 178 Y Y 1 LT 63 179 Y Y 1 PDT 65 080 L-342 WA12 714-0 Y Y 1 PDT 65 082 L-341 WA12 714-0.Y Y 1 PDT 65 090 L-342 Y Y 1 PDT 65 097 L-341 Y Y 1 PDIS 67 490 A L-416 Y 1 PDIS 67 490 C L-416 Y 1 PDIS 67 490 E L-416 Y 1 PDIS 67 491 A L-415 Y ) 1 PDIS 67 491 C L-415 Y 1 PDIS 67 491 E L-415 Y 1 FT 68 006 A L-226 .Y 4 1 FT 60 006 B L-227 Y ~ 1 FT 68 006 D L-228 Y ~ 1 FT 68 029 A'L-226 Y 1 FT 68 029 B L-227 Y 1 FT 68 029 D L-228 Y 1 FT 60 048 A -L-226 Y ( 1 FT 68 048 8 L-227 Y i 1 FT 68 048 D L-228 Y 1 PT 68 066 L-340 Y Y t i 1 PS 68 066 A L-358 Y

v.,

1 PS 60 066 D L-358 Y , w, 'o' $rlN, = .... m Q. % ;.' s.. :: %;r S]E Y5 m--- - 9 7..

-~ABLE ) .,..,Pcgo Na. +15 12/17/B7 )(eap1/V7 RESTA RT~ UNIT 1 INSTRUMENTS FOR SQ-CAR-87-14 ~ "lTON SON-ISL-001 R4. PREPARED: 29 R 8eil 11/17 /$7 CHECKEDs gg M l2/j7/47 UNIT INST SYS LOOP PANEL LOCATION IN SLOPE SEPARATION WLXDN 1 PT 68 068 L-360 Y Y 1 PS 68 068 A L-359 Y 1 PS 68 068 D L-359 Y 1 PT 68 069 L-388 Y Y 1 FT 68 071 A L-226 Y 1 FT 68 071 B L-227 Y 1 FT 68 071 D L-228 Y 1 LT 68 320 L-454 -Y Y Y 1 PT 68 322 L-142 Y Y Y 1* PT 68 323 Y Y Y 1 - PT 68 334 Y Y 1 LT 68 -335 Y Y 1 LT 68 339 L-179 Y Y 1 PT 68. 340 L-179 Y Y 1 FT 72. 013 L-287 Y Y 1 FT 72 034 L-288 Y Y 1 FS 74, 012 A L-5 Y Y ~ 1 FS 74 012 B L-5 Y Y 1 FS 74 024 A L-22 Y Y 1 FS 74 024 B L-22 Y Y 1 LS 87 021 L-490 Y 1 LS 87 022 L-492 Y 1 LS 87 023 L-491 Y 1 LS 87 024 L-493 Y i 4 L <( l i ~ .,...;s:.?c. -id$0.@\\; ~-...-

'. 9 SUNMN2Y cl~ RESuLTS ..,.. :. u.. :. THE LIS7~ of TNtTRUMENYS 70 25 Zd3PECTED FeR SQ - CAR o/4 7YPE A/DAl-CoWFORMa4 AscE A N D M U TT*.1 RESTAKT S*, BEFORE UNI T 2 ResrA A2 T /s US TED IN A TABLE /. . r. Codct.us w Al - NA l 1 i 6 l 1 1 ( i lad P95 '8 g %\\ pays-S .~ \\ pgp p g ()4 g/.s-/47 BlP Idant SON ISL-ool chu b. A' firk.'rRub. sh II cI o ~~ R O a ..:;3,f;.....,...,...:...., . u, ?. .sg. ..c.

t DNE CALCULATIONS ~ Information on 2-LT-63-176 This instrument was not installed during walkdown, it was i removed and being reworked, per WRf B226384. i a h l 1 a e t = r i a d 'We - h, w .g .,- [ + gfe ^ s I .,. ' (. t j - k j 4 d i i i b ,y s 4' 5 J ^ m..' j b s j .[ 6 i o i i 1 e 4 'Da i 1 ky +. .+. y i s

4 f

r';. i ( c% . a of - ~ e. Y -,' d, [ J s'$.~ e' ..W i --r; } & :.5 -~ U ,q .o v. 9t.. -,. a ..t - i {

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ML20147B371

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