IA-86-387, Package of Insp Repts & Related Info Re Const of Plant
| ML20154H643 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 12/16/1985 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20154H613 | List: |
| References | |
| FOIA-86-387 NUDOCS 8805260016 | |
| Download: ML20154H643 (129) | |
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. l howuver, it wau brought to the atteention of the f oreman to be corrected. Thtc diiscrepancy wan a signaturer in tho wrong block. All ;
other travelern revicewced indi cat ed no di screpanci er.. Work packages reviewed:
~
. 2-01-F . 2 *,:1 1:
. 2-21-1 . "'- 21 -N
. 2 21-H . 2- 21 -D ,
. 2 E . 2- ;' 1 - A.1
. 2-01-G . 2 *i' i ~ l .
Notut Work paci:agen cont ained morn than on ce tr avulwr insi de. lar -*Lni at t :. & A . . m .- m . v . --4. ' . p s. h g ga a , Q v W W;a.'! fr & p u c " d ' S taw .f n . ., <A~/
- oating field Fngi ncarn .tr e gquel i f t ed in ort.ordanco to si t e procedure P- EP-14$ 1, rtdicion O. ANSI %. 2. 6 f u lio l o n g ier applicab)c. e i n c t* the lue.l acui f i cat i on n igtj t i vo t.emt nq-j 4g,g , a hoga nn s og coat i ng ia1dgnoineet muS y*,e he falitukng qual 2 41 t.M i on t equi r oment s.:
. Minimum of ono anti one holi (1 1/2) yo,ir s. c::portonco in tho, k innpuetaon end documentstion of pr ot etti ve coat ings wort: et' A I nocinar (acality *
. Shala be phyclectly tapable of peri or mi ng the arnigned t a e. L t. .
. Shall h6ve naturel or correctt d near distance visual activtty such that thny are capable of rending .1-1 lutters on a si.endard Jeeger'n Chart. '
thcoe inspectors ar e giveen c'lattruani inste uction un all coatings rocedures, and a proficiency tent f or all instrumentatton us.ed to ! eriorm the inspectionL. lhe goatingr. [2 eld Quper va nor c.'vo l u.a t e n the i r oficiency of the inspection on the use al tiie instrumrnts. 1h? ItRC inspec m reviewed appr a m a t. ly m qht ^ .. ngu Fi bgine ing f stor do. Jr.ttng teld Eng -er b reen ds r - ewed i di ed tI ey wro sfind in ac c:e to st te prut.edut os, i w y 54~4 ~ fjor1tyoi the (cating {teld 1(nq3nne,rn quelaiicat2on cucordu ruviewed by pe NRC inspetctor nndicated t. hat they had been qualtfind or certalied to , 'er]! 45.2.6 bef or e decl awbi f i cati on of frutiecti vtt Coatinon. Ita NRC inspector ef[dnot review croi t (phl ntet v.) qualification breaut,u w1no the TR1 ' c r uvi ww, they tit at ed that t h c= r r a f t e, qual i f t c at.: on i wer er asequate.
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$f(f.$ y lhe NhC inupre:t or r@v3 tewed c.a31 br et i on r or or rit. ci two !!1et:oiwter Sdhenion i tcuterm nntt four DFT Qauge fierc or ds. n,ntis cated ttist the i nstrutnefit s. werc l l r.nl i br at at thcar propeer n t er r v a l o . No dttaccepanciou were noted. l i
Thu NRC in >cctor reviowed t protedurec. '-
!!- - a ' '- " i v c' 'N ) f In - > .- 1 m u4e,n -t x t ,, u u n .: M ! i- ~ n _ -J '- - # 1 m c ' 'M pp. l
( i I! nth instiumo,t5, wer c cal ibr,4te i 1o an arenr.cv nI a/- l iv/. . The cr.atingu 4 avid engine <<r pi etedur et f or in ol inuin inthezisin avadanos iai the til e c oi e t e r Adhas, nn Iest er 2 e mor i conwr vat i ve theto r ugut r eri. DOG . M rin g,py),gg et
+ BC..*E*M .JCC!- 7 ,
I ti t - 1 :',. "Calsbrstaon 01 DFT 044uges, r ev a t. l an D . dated 3-11-02 j 3( IEI 33, "Cielibret1on of dhip:1 on i c S. r. t e. , " rcviiaon M. dat ed 2.-27 On J L 4.c n n c >e p - (.Afib/r!?fpq., ! [t%1C H7741 [ Mbit il 4 '. M' , , t%1H st;";O 4 ) - ~ i Mt.1 (' ti ti ?? * , ' t t'.1 C 11 ','f P i'/ f% / M*. l i c 'C ' ) ; Nu vi ol.At iont or ele v 1 cit 1 c o n wuna ideni)iacd. ).ACtipn ripuiear* :f "'"J C C. s i 41 h O '? / '77 Coni.1 eme n t No. c3 f 1he NRC inspector revj eut ci t he u ist u*;. o f act ionc requir ed by illi:C rel at e.c I l to tht- 1RT f a nr11ngu a n NUREG-0 7'U , Supp) vmorit No. 4. pagu M 13. , l (3) De g3 5j'2# b1he NRC inspector r ev i emf t! tIw ilot. t 011 m.te<I i<.. t he r1( enet or cel t tirot 2 on correttaon to i her data inr aclh e*.4 nri t e M
<r. LoserAng !
mi s,i:o l l antf ou t. steu! atem. in Unit. I 1. :. 1ho t!at a at enn.pl et o ' bui h iv. not b ec ra i 4 a ri.il 1 t.el i nt u r ef or t i or m 4 or t.nbito L t al ta NkC for ruvsaw. (2) .D.f"i" Q y y ,g gr 3 (lhi u cal.stgur y detel c wi t h4 NCli' % Which provide "utw a: 1 S d i crios i t i on r. for d i :.c r ep.an t coating- materr i.12 9 With i le a derC4u a t e t er htTi c al .i ust i f a t<<t i tin f or- t her d t s. msi ti on. ; The action r equi red f or gig. cat eger y hiin tienn completed by [ the )atenceu .a n ti subm b uu3 1 o Mr . V 1 ut. n S . N u u n iii. !)1 - or if , Nuc l uar- floact or hogul .4t i enj.% rJove<R!iTr~ftT~TQ } [,9 ! (1yy.461,)h r ou i i o. t L I (3) q _ r r o u d u t. g . . . . l I r FROM US NRC RIV STP C J 2< 8 Gr B 5_ 15 2. 31_ P. O t
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. .I i The TRT f ound devie;ientitec in procuduren and instruction f or coating work anc elated ant,poction activitiesj during the construction phiis . which render ud 1. hem inappropriate or i insidequhte i rnpur t antugr a r. t. i v dotormaning itaon. 11w 1R1ratisfactory al tsu f nund atcomplishment of t hat t he pr Octrdur e review snd opptoval syht r m wow inadeuvM e to detect and c orr irc t t h e~.it d e, i i i. i un c i e,"a .
Thev NRC inhpector*t. r eview of this. category ndje 704/O 3.2.EG h e t. tuviied t+ i r e rs,4t a ng pr oc edur es qir, t hs. 8ths{ater. tructiontha phar.e t. n' U..i *,? anc rei nspection acti vt t iun .U( Unit 1 to iric1ude inspection ,itt tr i but e':, f or* dogmint hg satt uf met or y accomp!i+shment of i mpor t antYvct i vi t i ut. CP-EF-6.2 han buon er.tablinhtd tn ar,s. urn that pr ocedur et. and instructi ons, are , ruviewod and approved by technically igu.alif ied indi viduals t o act.ure cont.1 btency end c/l ar-1 t y. L ter TXX-461hk j VhN -1 . J. --t ca r.w hiEw u a m. a urr ou t l i n M. the (.o.s t i ng.6 nuevces j l nce c r ugr .<m f oi cperaticou. l W CR41095. l0 Crept 1.09 sA N Wp, ; i IRl e e qui o . l. .): 4 t ipd,0.ed t u t i nue lt ui pad d :, t i on.e l s t eamt. t o t;e " entier ed on tiiv r :u.wpt log. Unit 2 u:n mp t Jc to date. However. Unit 1' will W. have II'kq i current 4) rid up nt eri ng'#.h'e exempt log / bec # is u s.e 4+-Lau: A ust i nu M (d sf i rM; N s -+-+- w s ) l be rewor ked or r e p .<i r e d . Unit t ' at <".t* mite will h t: compl ut.e anti f t a'*.. ;J .)r. it log $dico t o t- bacitf t t est Progt 4m df a t a i compl etaj Lhee saiemg.4 a,-- si. wat u % M t nto %u ),,
/ joy td n v . t> \ a Q , n Gda.s m .% {. (, , g .
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FILE NAME : REPORT.14 i HUAC AUDIT DECEMBER 28e 1995 There are no problems with the audit t rail from hardware to documentation. More work can be performed Jn this audit in the i { -%. area of assemblye weld, and component documentation. %- < g l IMring the audite HVAC components in Unit 2 were inspected for I identsfacetton markings which were a permanent part of the component. drawing component These markings or (identification f rom a d rawi ng ) , identifications were then used to identify unique documents which t raced the component ma rk ings to test ' reports and other documentation which described how component was manufactured. that The CPSES does not have Safety Class 1. Setsmic Category I HVAC , components. The highest i classiftcation is Safety Clasr 2, Seismic Category I. The components inspected during this audit are part Peactor Containment Boundary. of the They are passive components uhtch serve to contain any ractoactive materials which can become ai rt.orne during abnormal reactor operattons. ; The following icentifies the contents and backup material in attached REPORT.101 .
- 1. Appendix A documents and scentifies .he areas in the HVAC systems where the CFRT effort and I spection Mcdwle '017*
overlappeN ?' . vve.lew *s in the it.spect ion of As Ir.st alled Equipment. Tr* equipa.etit ist i Setsmsc Support for Duc t work Ductwork '
! solation Dampers L Fans and Motors Filters
- 2. Appendix B documents the Safety Classificat;ons and Seismte Categories of the HVAC system. All components and equipment are of Safety Class 2. Setsmic Category I or less, f
- 2. Appendix C documents the field audit of the component s on !
the inside and outstde of five penetrations which are part of the Reactor Cont atraent boundarv. t 4 Appendix D documents the Auctt Trat1 from the Unit 2 Reactor : Containment to the Unnt 2 Document Cont rol Cent er. A total { of seventeen items are t raced to thei r respective documents. , The remaining audat items are pape and weld tdent ificat ion which i j was documented in the field. The Unit 2 DCC computer was down on the last day, j 12/28/DSe I was on attee so these items could not ; be traced. i n -- - - -,- , e --.,,,-~,.-,,---,-,,-r-- - - - - - , , , - - - . - , .-n,. - - - - - - - - - - , - - - - - - ,, ,, - - - -
l
. ( ,
s 1 FILE NAME: REPORT.10 HUAC AUDIT DECEMBER 28, 1985 APPENDIX A The audit began with a review + Inspect ion Module 50100, the from Inspection and Enforceme- Manual. The NRC is also performing and audit of the wo. being perforraed as a result the CPMT. A of following documentsi review of this audit was pe rf o rmed using the ERC QA/QC-RT-859 ERC QA/QC-RT-981 QI-023 Rev 1 QI-024 (This document was not available as of 12/23/85) QI-035 Rev 0 .e CI-036 Rev 0 QI-039 Rev 0 QI-040 Rev 0 The review was undertaken to determine how much or the work ps rformed by the CPRT audit could be coplied toward credit in the performance of IP module 50100. Specific
- statements of audit inst ruct ions in the module were Identified and documented. A search for similar statements in the EPC Inst ructions was then mace to determine where credit for the module audit can be taken f rom the NRC audit of the CPRT.
The following table identifies where the two monits o.erlap. I E MANUAL 50100-024c In this paragraph the following t able identifies where the procedure overlaps the NRC audit. Manual
- Parag Item Locat Config Ident CPR T Audit Items c.1 yes yes no QI-035. Rev 0, 5.1.A, 5.2 c.2 yes .< es yes QI-039, Rev O, 5.1 c.3 ves yes yes QI-023, Rev 1, 5.1, 5.2, 5.3 c.9 yes yes yes QI-023, Rev 1, 5.1, 5.2, 5.3 c.12 yes yes yes QI-023, Rev 1, 5.1, 5.2, 5.3
. ( ,
i APPENDIX A The To11owing statements are f rom the TT,AR, and are used . r1 this audit Class to establish 1 and Seismic which HVAC Category 1. items or components ar) Safety A. Control Roon HVAC and filt rat ion systems equipment rooms
- 1. pa9e 9.4-2, conditionang unats.
The system is equinped with Tour modular air-Each pair of air-conditioning units is powered from an independent Class IE bus and is physically ' Leparated by a dividing fire wall...
- 2. page 9.4-3.
All dampers are set to Tail in the safe position or are operation.provided with separate, bottled air supplies for emergency
- 3. page 9.4-3, All cont rol valves and dampers are equipped with o manual ope rat ors at accessible locations ...
4 page 9.4-3, System component s and ductwork are of seismic Cat ego ry I and ANS Safety Class 3 design ... B. Spent Fuel Pool Area Vent il at ion System 1.page 9.4-13, emergency fuel pool cooling pump room fan coil units are located in the spent
- 2. pege 9.4-13, emergency fan coil units are supplied with chilled water f rom the safety-related chillvd water system.
- 3. page 9.4-14, Each emergency fan coil unit is interconnected with 4
the page same Class IE bus as the equipment it serves. 9.4-17, The Fuel Building air exhaust duct wo rk is ANC Safety Class 3 and seismic Category 1.
- 5. page 9.4-17, The emergency fan coil units, which are located in the safety re1ated pump rooms, are seismic Category I and ANS
~
Safety Class 3. C. Auxiliary Building and Radwaste Area 1.page 9.4-1D. The ductwork lavout is arranged so that in areas
~
where ai rborne radioactivity may be present, airflow is directed from areas of lower potential rad i osct ivity toward areas of hi ghe r pot ent ia l radioactivity.
- 2. page 9.4-19 Each emercancy fan coil unit is interconnected so that it starts with the equipt ent it serves.
3.page 9.4-21, The exhaust system is seismic Category I up to the fan discharge.
- 4. page 9.4-21, The air supply system is seismic Category I except for the Vens and the dampers which are seismic Category II.
D. Engineered Safety Features Vent ilat ion System
- 1. page 9.4-27 At least one ESF exhaust Tan is automatically energized from its Class 1E bus following a LOCAI ...
- 2. page 9.4-27, ...
each of the pump compa rt ment s is equipped with emergency fan coil units ... which is powered from the same Class 1E buss as the equipment it serves. 2
f 1 i l 1
- 3. The auxiliary cooling units are supplied with chilled water from the safety-related chilled water system ...
- 4. page 9.4-29, The exhaust system, cooling units, and safety features chilled water system are of seismic Category I and ANS Safety Class 3 design.
E. Containment Ventilation Systems Containment Recirculation and Cooling System CRCS Control Rod Drive Mechanism Ventilation System CRDMVS Neutron Detector Woll Cooling System NDUCS Containment Process Filtration CPF
- 1. page 9.4A-1, CRCS Por' dea cooling is provided by the Containment Spray System.
- 2. page 9.4A-4, CRCS Containment Recirculation fans are provided with a connection to the Class 1E Buses ...
, 3. page 9.4A-4, CRCS Monitors consist of air temperature, humidity, and pressure... 4 page 9.4A-10 The systen's inside the Containment are seismic Category II. -
- 5. page 9.4A-10, Penet rat ions are ANS Safety Class 2 and Seismic l Categorv I. !
- 6. page 9.4A-10. Exhaust air is passed through iodine adsorber beds prior to its discharge.
F. Diesel Cenerator Evilding Ventilation System
- 1. page 9.4C-1, The system is seismic Category I and ANS Safety l Class 3. '
- 2. page 9.4C-1. The fans in each diesel gentretor compartment ,
start automatically on receipt of diesel generator start signal. 9.4C-2, l
- 3. page Fans are powered from the same safety-related l
electrical bus as the diesel that is being ventilated. l
. b G. Uninterruptable Power Supp2 v and Dist ribut ion Rooms Ai r Conditioning, Systems
- s. ,
- 1. page 9.4C-9, The air .onditioning system is comprised of two 100'./ capacity self-contained air-conditioning units located in adjacent s'ooms that are physically separa*ed by a dividing fire wall.
. 2. page 9.4C-9, The redundant A/C units are powered from independent Class 1E buses.
- 3. pa9e 9.4C-1, The UPS and Dist ribution Room A/C system is ANS Safety Class 3 and Seismic Category I.
H. From Appendix 17A of the FSAR, the following statements in TABLE 17A-1 are made for components of Safety Class 2 (there are no Safety Class I components listed for HVAC, however,* the HVAC panels in the cont rol room are Safety Clast 1E > t Items 0, 221, and 229. Piping and valves of all systems penet rat ing the containn.ent are Safety Class 2. Seismic Category I. The QA requirements arwi (NOTE 26) Meets quality assurance requirements as set f o rt h in Gibbs & Hill spec. 2323-GS-903. Rev
- 1. QA for Procurement of Materials and Equipment, which satisfies requirements of 10CFR50, Appendix B, and (NOTE A > an Operations QA Program will be i r pl ement ed which satisfies applicable requirements of Regulatory Guide 1.33, Rev. 2, "Quality Assurance Program Requi rement s ( Ope rat ions ). Other requirements include (NOTE 136) Generic Analysis dynamic method and (NOTE 13d> testing method will be used for seismic qualificat ion (see Section 3.7).
Item 9b, Hydrogen Purge System Exhaurt filter units are Safety Class J$. Seismic Category 1. See NOTES 26. and A. Also the , method of testing (NOTE 13c) used fro seismic qualification is the Static method or equivalent static method using dynamic load factors. Item 96, Hydrogen Purge System Exhaust ductwork, suppo rt s & dampers outside containment are Safety Class 3, Seismic Category I. Meets quality assurance provisions of Brown & Roots' Quality Assurance Program ( see FSAR Sect ion 17.1.1.3), which satisfies requirements of 10CRF50, Appendix B. Also see NOTE A and NOTES 13c and 13d. Item 17, Diesel Generator Combustion Air I nt ak e and Exhaust System Piping and Valver outside Scope of Diesel Cen Mf r. are Safety Class 3 and Seismic Category I. (NOTE 13a) Seismic qualification is by the Individual Analysis dynamic method. See NOTES 26, A, and 13c. The Supports for Class 3 piping are also S'af et y Class 3. Seismic Category I. This is to meet pertinent nortions of the QA criteria set forth in 10CFR50, Appendix B as defined by the specification. Component support s are designed in accordance with ASME BLPU Code, Section III, Class 3 but fabricated to AISC-1970. See also NOTES 13a and A. Item 23c, Control Room HVAC panels are Safety Class 1E, Seismic Category I. See NOTES 26 A, 13c, and 13d. I. NUREG-0797 NUREG-0797, tupplement No. 8. SER, Civil, Structural, and Misc, page K-137, "FSAR volume IV, Section 3.2, Classification of structures, Components and Systems, states that part of the containment ventilation system is seismic Category It however, FSAR Volume XIV. Section 17.0, Appendix 17A, list of Quality Assured Items, st ates that t he cont a3 ament ventilation system is { seismic Category II and nonsafety related with the exception of I the contalnment Purge exhaust ductwork, suppo rt s , debris screen, and isolation valves, which are seismic Category I. Only the isolation valves, which are safety and code class 2. are safety related and seismic Category I. ( The TRT determined that the entire containment ventilation system i is nonsafety related, except for the isolation valves referenced , above. None o f t hese nonsaf ety-related systems is necessary for ( the safe shutdown of the reactor or to prevent or mitigate the l consequences of accidents or malfunctions in the reactor coolant pressure boundary. 4 L
APPENDIX C Two drawings were used for the auditt 2323-M2-0301 Rev. CP-4, and 2323-M2-0502 Rev.1. Drawing number M2-0502 was used to
- locate M2-0301, the Unit 2 Containment Penetrations.
Rev CP-4, From Drawing 2323-the containment penet ration numbers for the main air ducts are as follows: PENETRATION NUMBER LINE NUMBER __________________ FUNCTION ' M III - 18 - _____________ M III - 19 12-VA-2-01-151-2 H2 PURGE SUPPLY MV-1 12-VA-2-13-151R-2 H2 PURGE EXHAUST MV-2 48-VA-2-902-152-2 CONT PURGE SUPPLY M V - 14 48-UA-2-901-152-2 CONT PURCE EXHAUST e 18-VA-2-900-152-2 CONT PRESS RELIEF These Unit 2 penet rat ions and thei r att ached valves were inspected on 12/26/85 and 12/27/85. The valves and pipes and pipes ident ified here are part the containment boundaryl i.e. they are the first barriers penetration. on the inside and outside of the The following information was containment
)\ inspection. recorded during that d y PgNETPATIUN INSIDE CONT OUTSIDE CONT M III 18 Could not reach these valves as the scaffolding had been removed.
\
From the DWG. 2HU 5543 .
\ N
'* N .
2HU 5563 N These numbers are from a valve. 9144-03-07-03 2HV 5542 f These numbers are from a pipe. [ 1 VAXAB 03 M III 18 I These numbers are from a valve. 2VA 001 t AF 074 Serial no. H 2012-1 Lot no. These numbers are from a pipe. The main pipe HT F81200 MR 31486 These numbers are from a pipe. 3/4 inch pipe HT 405447 MR 16154 These numbers are from a pipe. l Weld-o-let 12-6x3/4 3M 501 7 1F 37 BH ? M III 19 These numbers are from a valve. t
l
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9144-03-07-03 14759-1A
- These numbers are from a valve.
9144-03-97-03 14759-1B These numbers are from a Y pipe. - l HT 26278 MR 092555 These numbers are from the drawing. 2HV 5541 2HV 5562 , 12 UA-2-13-151R-2 These numbers are from a valve. 14759-1C 9144-03-07-03 This number is from the drawing.
- 2HU 5540 .
These numbers are from a valve. VA-X-AB-004A AF 083 Serial no. H2012-1 Lot no. This number is from the drawing. 2VA 002 MU 2 These numbers are from a valve. 48-9134-05-07-03 14759-3C This number is from the drawing. 2HV 5539 These numbers are from a valve. 1 14?S9-3D 1 48-9134-05-07-03 This number as from the drawing. i 2HV 5538 ,
'M V 14 These numbers are from a valve.
14759-2A 2HV 5549 These numbers are from a valve. 14759-2E 2HV 5548 These numbers are from a valve. 2VA 005 AD 213 Serial no. H1820-1 Lot no. MV 1 These numbers are from a valve. 2HV 5537 14759-3A These numbers are from a valve. 2HV 5536 14759-3B These numbers are from a valve. TB 307 AD 219 Serial no. H1826-1 Lot no. This number is from the drawing. 2VA 003 s i a-
APPENDIX D This appendix Document is the audit Control Center. paper t rail from the Const ruct ion number were entered into the computer. The valve numbers and Penetration computer identified the Receiving With these numbers, the (RIR). Inspection Report Numbers The computer also Q. identified some of these valves as non-The RIR was then retrieved from the files and inspected for content and number cross referencing. One valve number <2HV 5548) was not listed by the computer. valve 14759-2B, was The serial number for this . RIR. # entered into the computer to identify the Q PEHETRATION U ' NO. VA VE RIR P.O. y SERIAL HO. ,, M III 18 2HV 5543 12191 CP 0086 14759-1B 2HU 5563 12191 CP 0086 2HV 5542 14759-1E 12191 CP 0086 14759-1F 2VA 001 9579 CP 0020A.1 AF 074 M 111 19 H 2012-1 Lot no. 2HV 5541 12191 CP 0086 2HU 5562 14759-1A 12191 CP 0086 2HV5540 14759-1B 12191 CP 0086 2VA 002 14759-1C
- 9579 CP 0020A.1 AF 083 H2012-1 Lot no.
MV2 2HU 5539 12191 CP 0086 14759-3C 2HU 5538 12191 CP 0086 MV 14 14759-3D
'2HU 5549' 12191 CP 0086 T4759-2A 2HU 5548 12191 CP 0086 14759-2B 2VA 005 08565 CP 0020A.1 AD 213 H1826-1 Lot no.
MV 1 2HV 5537 12191 CP 0086 14759-3A 2HV 5536 12191 CP 0086 14759-3B 2VA 003 08509 CP 0020A.1 AD 219 H1826-1
=
Lot no. For selected pipest M III 18 03565 CP 0074 802252/14 The computer was down so I could not cross the Heat numbers to the RIR's for the pipes. The RIR packago contents consisted of the fo11owin95 RIR-8509. PO-CP 0020A.1, Lot Number-H1826-1 Page 1 _ Cert ified to conformance ,
- 1. Fluid flow +/- 15% of published values
- 2. No visible leakage f Page 2 - Wall t hick ness inspection Page 3 - Final acceptance plan Manufacturers data report Final acceptance plan l
.t. '~k
', g Serial nos & traceability repo rt Wall Thickness fl r, . F Page 4 Certs Reference list
- Requirements check list ?, ',' 4 1 Page 5 - Cleaning, inspection categories i
Shipping Assembly, Hyd o, Tagging, Packing, Page 6 - Code conformance Page 7 - Valve serial no. list / body, bonnet, etc. RIR-9579, PO-CP 0020A.1, Lot
- the above listing for RIR-8509 Number -H2012-1, is similar to J RIR 8565, M III le _
4 This not package looks completes the have non-conformances, receiving check-list does 70368--037 8 l % _ RIR 12191, RIR 13110, RIR 13186, RIR 13187 ~ These RIR packages contained the followinel Receiving Check-List Drawings QA check-list I Doc. Package
'} Drawings i Order Spec Sheet Material Traceabiltty List Body Mill Test Report (MTR)
Disc MTR :
'.1 Stem MTR j Disc Pin MTR g
Oask et ketainer MTR j Gasket Retainer Bolts Corts Filler Metal Test Report Manufacturers Cert Cert of Compliance Material Test Report t Liquid Penetration TR Weld Repair Report
'- Body Radiographic Report Wall FinalThickness TR Measurement Report Cleaning Cert Cycle TR ASME Data Report Assembly Shop Traveler l
p
. . . - . . . .. . . = .
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FILE hat 1E PEPOPT.16 HVAC Surarnary J ANUAP'I' 13. 1986 Referencel Report.14 IE tiodules 50100 e HVAC rytt ern at CPSES 1s not classified ar' Safetv Related The~ highest class 111 cation is Safety Clasr 2, This- clar:11) cation Seisenic Categor' I. penetration 5 ir br:19n+d to the HVAC svitene valv+r ano Boundary. a.sh i c h are otrt of the Penctor Evilding Cont tintuent I rel at i on DInspectton arnpe rr , Module war Procedure 50100 - 24c. 1 t ern 3. configuration. inspected for proper Identification.~and darrage. loention,
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. ,g " h t, UNITED STATES NvCLkAR REGULATORY COMMISSION
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$11 RYAN PLAZA ORIVE. SUITE 1004
.P ARUNQTON, TtxAs 76011 FACSIMILE. TRANSMITTAL DATE/ TIME: /~ 2 2 Tb PRIORITY _:
k Innediately 1 Hour 2-4 Hours MESSAGE TO: _ /dd /P5 MESSAGE FROM: b /7//CMMUb NUMBER OF PAGES: _ k PLUS TRANSMITTAL. SHEET , TELECOPY NUMBER: 7/7497' h//2.VERIFICAT!0N NUMBER: CONTACT:
............................................................. -- . . 2 . . . . . . ::
SPECIAL INSTRUCTIONS / ATTACHMENT (S): Transmitted & Verified by: DISPOSITION: Return to Originator ____ Place in Mail l NAME DATE Other
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( . f 1. d. ' 'd "o " ' Save o so,pueog sw y' ' Observation of Electrical Installation Activities 3 x .a # 75/2,\ Durin0 this reporting period the NRC inspector observed two cofoty-related cable termination activities. The first termination ! cctivity observed was a termination of s Train A (orange cable) in a i Junction box in containment; the second was the termination of two Train B (green cables) in a motor control center (NCC) in the green switchgear room.
,In-process work observation was performed to verify thats the latest decwings and termination cards are being used) the cables are protected from damage from nearby construction activitiest that proper separation
- 15 maintainedi segregation of power, control and instrument cables is maintained; cable identification is preservedt bending radium is maintained; cabl e ent ry point is acceptable; tools requiring calibration cro in good repair and properly calibrated; connection tightness is sul; terminstrens are of the correct type and properly located; junction boxes, MCC's and switchgear are free of debris QC activities aro performed at the times specified; nonconformances are identified and reco1ved in acccedance with procedures; and installation and inspection cctivities are being documented during the in-process work activity.
Terminations of two types were observed. One required terminal lugs, tho other did not. The attributes specific to the termination type in cddition to those attributes common to both were inspected. Cabl a l numbces and termination points were na i "" Cable No. E02199710, t e r m,e p t' 8 I"' I junction box (JB) 2C245 in containment and Cable Nos. EG213268, AG213254 t c r mAbein]
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.CP2-EPMCEB-06 in the green switchgear room. The NRC inspector verified that all pertinent requirements had been met.
I N0 vs olad el N bidd s m i ' L ('[cJ, i l 8 o w h
0 g, , , 3 . 1 ge c ayre - FILE NAMEI REPORT.13 , December 20, 1985 This file summarises the audit of the IE Information Notice and Generic Letter files that TUCCo maintains. The audits were performed to IE Manual Inspection Procedure 92717-02 and 92703-02.03. These TUGCo files are in the care of Dean Palmer, Indust ry Operating Experier.ce Coordinator. IE INFORMATION NOTICE AUDIT NOTICE REV FOR DISTRI- CORRECTIVE SEE RECEIVED APPLIC- BUTION ACTION NOTE IDENT ABILITY 85-22 yes yes yes yes A 85-04 yes yes yes none 85-56 yes yes yes yes B 85-33 yes yes yes no C 85-34 yes yes yes no D 85-35 yes yes no N/A E 85-36 yes yes yes none NOTES: A - Revision to maintenance procedures to include verification that the pinion gear is not reversed - by 9-1-85, Bill Dockey, 7-2-85. Maint. Engr. B - Chemist ry layup p rog rarn cefined in TIM - 850907, Bob Deleno, ext 5246., Data sheets use to document p rog rarri l
- RHR HEAT EXCH Tubes - Hydra:ine & LiOH Shell - Comp Cooling Water DIESEL GEN WATER JACKET Tubes - C1 Service Water Shell - Sod 1ura Hit rite SAFETY INJECTION SYS - Dry Open to Atmosphere C - An NRC CAT inspection at several sites identified that undersized no :le to shell welded Joints in tanks & heat exch existed. Or192nally sent to R. Baker '3/16/65 for actton. As of 7/19/85, no action by Baker. he questions
,, ICER's existence. Plamer sent him another copy 7/19/85.
D - Stress corrosion cracking of PASS, sent to Doug Davis on 5/21/85. reply on 8/25/85, by Maint Eng, Want more verification from Tech Support that these conditions could exist. kE-NRCauditoragreesthat the No's are appropriate.
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L L*..'.l e < GENERIC LETTER AUDIT In this audit, all (about 15) the Generic Letter folders were opened and briefly read to understand the general thru:st of the NRC letter. Two folders were reviewed for content, 83-11 and 83-
- 16. Both files contained documentation to show that the letter) was reviewed by TUCCo Engineers and was distributed to the appropriate TUGCo personnel. The other audit items identified by Inspection Procedure 92703-02.03 did not apply to these letters-%J Generic Letter 83-11 adentified an NRC concern that users of Safety Analysis Codes (RETRAN, RELAP, TRAC, etc, ...) must understand and perform code certification prior to performing site specific analysis. Randy Janne, TUCCo Nuclear Fuels, was contacted about the letter. He stated that U & EXXON will perform the Safety Analysis for the first five cycles. TUGCo intends to develop the expertise.
Generic Letter 83-16 discussed the SALEM ATW3. The engineering review included a discussion with training which identified that the SALEM scenario was part of the course work for TUGCo trainees. The NRC auditor noted that Licensing appears to be the receiver
, of correspondence from the NRC. They then distribute (unknown
. how distribution is determined) the material to Ted Jenkins group, Superintendent. Operations support. The NRC inat erial is e[ then split into two categories, responses not required < Dean !
Falmer) and responses requi red (Roy Cisneros). These groups then perform an engineering review on the material, determine its significance, determine where it snould be dist ributed and who should provide the response (11 requi red ). As a follow up, the j appropriate TUGCo personnel determine if the issues have been resolved or whether questions # are then contacted by phone to f remain. These actions are documented in the files reviewed by[ the NRC inspector. g /^ Y P
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NW cLeJo'//c. APPENDIX _b CONSTRUCTION INSPECTION REPORT U. S. NUCLEAR REGULATORY COMMISSION l REGION IV !
?
NRC Inspection Report: 50-445/85-Wlf Permit: CPPR-126 CPPR-127 ( Deckets: 50-445 50-446/85-M f{ : Category A2 50-446 . 9 ' i M Applicant: Texas Utilities p g Company (TVEC) , f Skyway Tower V
- 400 North Olive Street Lock Box 81 Dallas, Texas 75201 Facility Name: Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 In m et hn At: Glen Rose, Texas Ir- - ion Conducted: 965hr 1-31,1985 Insnectors: .___. L l
ll, O. PM111ps, senior Resident Reactor
/- ,f M Inspector ($28@), Construction, Region IV Date
/*
Q CPSES Group (paragraphs 1, 2, 3, 4, 5, 6, 9, 10) -
/ -
w 1 c.E. Jour m , W . ,v u s. h 1 u fsv M kq) Wk t ^ o lla Q W, $s u f4 T<ra SI' W 7 l ', ' y w fn . c. 8 a t , K,u c tw A v e . W / PN/ / 0-< f DC ((qf l*) j ! EL.Kelley,SRRI, Operations,RegionIV Date CPS ES Group (paragraph y) '
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Reviewed by:
- l. Barnes, Group Leader, Region IV CPSES Group Date Approved: ,
T. F. Westerman, Chief, Region IV CPSES Group v Date b { h pection Summary Inspection Conducted: kes W (f 9:t;btr 1-31, 1985 ((Report 50-445/85-9) A yas inspected: Routine, unannounced inspections of Unit I which included
- o pre f d g e O Tha inspection involved N pect
'{ #
M; *M cc - - inspector-hours onsite by NRC inspectors and & i
.tf .
e aw,aia, e 'g,y-Ra wlts: Within the four arcas inspected, e ,ne violation'ffef!ure t: ;;t:blish M r::: dure , for centrol ...d dee , -nenrae +n stnn , t ve deter g;;;eu-t ;t ab!'ity e' tb- :hipme..i vi vriginal y
' " "fed. e.<ng em.per3tte. (Sygcy,p373;r pp 4) v Q.r.u. W /S~~ '
h spect, ion Conducted: Ge44ber 1-31, 1985(Report 50-446/85-4) Area: :nspected: Routine, announced and unannounced inspections of Unit 2 u luded plant tours; applicant actions on cons , I g,hg,L h@- e' 1 ].. '
' OA 'cti^ar ec:rd ; :udit^ previous of ^A .cc:,rt;inspection weld. atert:1 centivi, .nd** 9#/ j gip, findings p-___.._.,.~ { ;stgru s .1 cable tray / equipment walkdown.
in c-hoursbyfHRCinspectorsandiconsultant/'Theg,,* inspection involved g,3, .,. - h W eg, ( 3 y g ( ), Q Re' ' -
*GM ' 9) e9 E r* e s1 p-Within
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thepf;;seven t e:1' cf:!:tiaas r;peei f:!'"aa areas aa = a inspected, a a c ea 'e -- a %s4e
- a. rape-t(!: violationsC le I' ' -::::[' ';.iia a . ore to +n conten1 4 !::: ef triga dec'-ants; n=**;-eph h ^' e<* dit:h wei+ ten crocedures for control and ac:: =t:bility of dat @n r e.. vi iv ZIC, p:rt; spF 5,5) ... . 'd::ti fed.
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- 1. Persons Contacted AaWL h Personnel Herritt, Assistant Projectg General Mana utP.Halstead, Manager,QualityControl(OC)ger lC. Velch, QC Supervisor kV.Mscidw Tuhco NJClfe b e n e e re g
y e y (TAJf) /H e c A +n . c o./ in p n ere
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The NRC inspector reviewetd protective ecatings travelcere to determine if the records were adequate, complete, legible. retrievable and documented in accordante to site procedures.eas11 Iny addition, the NRC i nspect.or compared t he compl eted and in procoas travnlers uyutem wastoaccurato. thn PFG tract:i ng system to determino af thr trackit,ig The computer printout i s uured for the tracio ng u y r.t. o m , lis. ting the travoter numbor, par.l: age numboi , unit, crea code traveler/ room number, any cutstandi ng coat tng def ici ency r eports and status. the Records accordance reviewed to si teweru legible, coatings e,m l y r etra evabl e and compl uto in pr oc.edures. record tr'ck' Heview of Unit 2 coatings system a system new, by# the NRC i ns.petr: tor indicated that the 4yutem. The tracking s)yr.t emi s h vrary reel i abl u .and tracking accurate i s updated on a daily baut n. i i The NRC inspector 61so reviewed i n proc ut.s. t ravel ers, in the fauld, There was one minor isolated di scr epant y note in traveler L'-21-0 i P*0M vt-t<RCNT C i D i6-es 4s;w F -4 i
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?r5 g t{nggg g' l Oke ~ ri CONSTRUCil0W INSPECTION REPORT f j / g fg g [
r- <l U. S. NUCLEAR RE6ULATORY COMMISSION REGION IV NRC Inspection Report 50 445/85 18 Pereit CFFR- 26 50-446/85-15 CPFR 1 7 v Decket: 50-445 Category A2 50-446 Applicant: Texas Utilities Electric Coepany (TUEC) Skyway iceer 400 horth Olive Street Lock los 81 Dallas,irias 75201 Facility kase: Cesanthe Peak Steae Electric Station (CFSES Unit 1 InspectiLn At: 61en fest, feias Ir.spettacn C:nda:ted: tecenter 1 31, 1965 ,'
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Ins?ecters: ~ 4 ,
\,
!. Ph.li.gs, wenior R m dent Re ut:r (Uv) */ Date \
l Inspector (SRRI), Construction egion IV ,CFSCS Group (paragraphs I, 2, 3, 4, 5, 6 K) It // \
/
C. E. Jchnson, Senior Resident Reactor Date Inspector (SRRil, Construction, MIV SouthTeiasProject V/ (paragraph 7) SVl P.(paragraph W. Michag,10) Reactor Inspector, Rettk!VyI Date h
. ?
'i e
. Pelt 2
,i
- 8. L. Kelley, SAR!, Operations, W IV, late i i CP$(S Grsep (parageaphs til 4
Consultant [646 - J. H. k Cleskey l Reviewedby:
- 1. Barnes, 6rcup Leader, RIV CPSES Group Bate Approved T. F. liesteraan, Chief, Reg,e(IV CPSES Group Bate ,
i i i l i I h w----- - - ,,-_y, .--r-,_m-
o . . L~ 59ho PAGE 3 T yp im O i fr.. 4 ~( f. losoection Summarv ! {, ' [ Inspection Conducted: December 1-31. 1985(Recort 50-445/05-15) 6Cfig.lOggggttd: Routine, unann ced inspections of Unit 2 which included l// 40RsOt: Mr and applicant actions on
- . . : .. c ' plant construction deficiencies;l previous inspection l findings) IE Notices; Qjns@sk & 'V -
and Generic Letterst,grotective coatings; heating ventilation and airconditioning (HVAC); pipe supports: and electrical cable tray / equipment X The inspection i nvol ved J . nnpector-hours onsite by four NRC inspectors and one consultant. Begylts: Within the seven areas inspected, no violations or deviations were identified. D_ETAIL_5
- 1. Persons Contacted Acolicant Personnel
i . . e
- PAGE 4 k
I L. Hart, Quality Assurance (OA) TUGCO Nuclear Energy (TNE) ( Electrical \ Engineer . P. Hal st ead, Manager, Quality Control (DC) F. Madden, TUGCO Nuclear Engineering (TNE) Mechanical Engineer J. Merritt, Assistant Project General Manager, TUGCO D. Palmer, Industry Operating Experience Coordinator P. Stevens, TNE Electrical Engineer C. Welch, CA Supervi sor, TUGCO The NRC i nspect or s al so i nt erviewed other applicant employees during thi s inspection period. 2. Anolicant
.s Action on Previous NRC Insoection Fi ndi na s . Unit 1 and k.
(Open) Unresolved Items 445/8514-U-02 and 03; 446/8511-U-01 and 02; and 445/0516-U-01; 446/8513-01: Procedures did not address constructiondeficiencyfilecongynt; incomplete OA record files;
% mWYV bg V and TUGCO commitment pf The NRC inspector continued th&4 g,4,., V V to revieq(s 4
- inspection,by'following up ok,athese i eps p during this inspection period. e t d' TUGCO is still working on th/s item and anticipates completing the review and taking necessary action to improve the current system by March 1, 1985.
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PAGE 5
, j i
'gkl (OPgN) Unresolved Items 445/8516-U-02 and 03; 446/8513-U-02 and !
03: IE Bulle 1 for 79-14 and 79-28 Th NRC inspectors continued thrs, inspection by f ollowing up on,th/s'ti temh TUGCO i s working on improving the IE Bulletirsystem and has named a new coordinator. They will consolidate the filF, and place OA records in the vault. The corrective action on amplicable IE
/ Bulletins requiring hardware evaluation, repair and replacement o A"M p ri fied W a will be reviewed to assure that th, cognizant construction cLd S J(,/
organization tracks these 4 tm..; to completion. v' (Closed) Violation 445/843 02: Failure to report alleged talsified records per 10 CFR 50.55te). The NRC inspector found that TUGCO had conducted an investigation of this matter to
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( validate the signatures of Or insparte-t Jad f uw.d nn oth-r similar occurrences. This problem arose when two inspectors participated in an inspection and one inspector left before the h inspection was completed and the other inspector signed for him. k> Notes added by the second inspector were misleading and he T received a reprimand. The inspection was a valid inspection of anchor bolts used to secure a stairway in Unit 1 Safeguards Building. Training was conducted to emphasi:e correct 4~ s documentationg ( Trec(u hyd N V No violations or deviations were identified.
- 3. Apolicant Action on 10 CFR 50.55(e) Deficiencies
c 1 I PAGE 6 (Closed) Construction Deficiency D-1-0181(CP-85-30): Switch gear cabinet terminations by the vendor. The NRC inspector rece ma .,.; m :< t inspect t\'is item to determine why the terminations were replaced when TUGCO letter TXX-4598 dated October 16, 1985 stated it was not reportable. The inspector svi ewed the TUGCO evaluation and found that this item was not reportable because they concluded it would not adversely affect
- hf ly d '
the safe operation of the plant. It was replaced because it did not meet TUGCO's standards (Attachment 9 of OI-OP-11.3-28) which may be more stringent than the manufacturer's standard. IV y
- 4. A J plicant At; tlon on Invy$ tj orl_amj En f orcem_en_t 44 0 Inf ormat_i on NoticeslII^l o V M' p The IE Information rv sent to the nuclear industry for.
inf ormation purposes and require no action by the Jd cen [ een nd
/ V' ayr 'rour & }
Applicants with respect to reporting to the NRC but e2,
;qu.re V A{g4gaction on applicable notice technical4eissueg pic m i p C Iar 1
- # < bie d p dW The handling of these notices are not covered by NRC regulations; however, the 4,, MgEsale : th t f NRC is interested in how the, subject notices are handled. The following noy ce files were rev'ewed to determine how TU CO LpV en v' W4M y determines applicability m distribution, and t aM ac t i or),:
85-04, 85-22, 85-33, 85-34, 85-35. 85-36, and 85-56, itw This reve of TUGCO files shows that their system es fs NIJ W is working 3 satisfactorily as re;"r=H te c h n metient
<W # 5 Ju a f+mt.
wara We 6 4<Mk No violations or devi ati ons were identi f i ed.
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PAGE 7 i, Acolicant Action on Generic Letters 5. I, 4 1 The Generic etters are also sent to the industry for information l purposes and require no response to the NRC. Again the NRC is interested in how the utility distributes, evaluates, and, if applicable, takes corrective action. The NRC inspector reviewed *' 15 files and selected Generic Letters 83-11 and 83-16'for a more ' detailed review. TUGCO Licensing receives and distributen these letters to the operations support group for their review and 1 action. Review of the files revealed that the TUGCO system does adequately consider Generic Letters and appropriate action was , talen on these generic letters. , No violations or deviations were identified. 1
- 6. General Plant Insoections of Unit 2 At various times during the inspection period. NRC inspectors conducted unplanned inspections of the reactor building, i
apd the electrical and control building. safeguards building /, Vf,"kheNRCinspector O- . , % uiu ru m . - observed ongoing construction work and discussed various subjects with personnel engaged in work activities. W Cpecif.- ylenmed inspecticn a, m c. wus ed an i I t Ne fo!!o-.ng perr; rap' . I t No violations or deviations were identified.
. l PAGE 8
- 7. Protective coatinos. Unit I and 2
- a. The NRC inspector reviewod the coating specifications and s procedures for clarity, consistepcy,, technical criteria, and W L , wi At 6(enf.- < 1 /
applicati-a instructiony. These procedures contain better criteria than the old procedures which were reviewed by the NRC Technical Review Team (TRT) in l'184. PersonnelfdP'p/ training / qualification, concrete /r.tcel reinspection and inspection, testing, documentation, and repair are well covered in specification 2323-AS-31 and in Procedures CP-EP-14.2. 14.3 14.7 14.8. 14.1. 14.4, 14.9 14.0. 14.5 14.6 6.2: CCP-30 and 40.
- b. Observation of work activity - Tha insnacter ctccr .ed nur x in progress and completed work as follows: pressurizer room 31, steam generator rooms 26 and 29 elevator shaft room 30 room 21. fabrication shop and paint storage building. Most of the work observed was surface preparation, however, a final application of the coatin f the steel liner was s h/
y, W r{ceh - p/ observed in room 21. The, preparation and application w*e )w"* ' accomplished in accordance with good commercial practices and the crafts and field engineers were knowledgable. Fi el d inspectors were present and were notified by the craft when hold points were imposed. Paint storage areas are temperature controlled and maternal shelf life was closely monitored and controlled.
7 i
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- i PAGE 9
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c. Records Review - The protective coatings paper flow group t t l (PFG). The purpose of the PFG is to establish a method of i i initiating. preparing, issuing. tracking, logging, and controlling protective coatings travelers and associated ' f i ! i supporting documentation for the verification of coatings l activities. The NRC inspector reviewed protective coatings travelers ,to ! determine if the records were adequate, complete, le ' le. easily retrievable and documented in accordance M site 1 procedures. In addition. the NRC inspector compared the completed and in process. travelers to the PFG tr acking system to determine if the t;acking system was accurate. The computer printout is used for the t r a c ki ,4 c ,a t e,,,, listing the travnler number, package number, unit, area code / room, number, any outstanding coating deficiency reports and the traveler status. Records reviewed were l e,q 1 b l e . easily retrievable and uh I'W complete in accorda 'ce site coatings procedures. Revi ew
'Q 4 W /
jW of Unit 2 coatingy records tracking system,'by the NRC ' i Vf inspectorj i ndicated that the system at the site is now a J very reliable and accurate tracking system. The tracking [ system is updated on a daily basis. ) ! The NRC inspec or 1so reviewed in process travel rs in he i J J field. 1 hm = was ne minor isolated discrepancyvu Y fo note yn ' r
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PAGE 10 . 1. Y < Th '" 3 (46 ,. g traveler 2-21-0., however, M n a kv4. u)h it ::: brought to th= we. J [g W bloL k rece d pn N f d % 1ov h atter. u?% tiong.. el the Laconinrema k to h= c;.,act;d. .. a ! g'f wsy bvou % { 4, . . fz-r fet Th mm's W iwr.r(ra'i
< % + j.
Manetur e in tha -rang M cc:, All other travel ers reviewed in N +c,H wd V L/ nn H i e r- r u n a n - p g ,/o)h.d (m ['" N k s'" p s " V V Work packages reviewed:
/ C-21-F 2
7 2-21-O'; 2-21-I I '/ 2-21-N
/ .
2-21-H I 2-21-B) 2-21-E f . 2-21-AJ j / 2-21-G " y . 2-21-L , Noter it M package b tain=d s
/ O' " 3.a.-i.r b e a:. v V_'
inside, of Y The NRC inspect m reviewed 8 training records for coating ,d v f t eld ongineers who were trained and qualified f/
&dU in accordancg D ' site procedure CP-EP-14.1 Reviston D.
A;- + iw M.n-.l ys.;)-{ (ANSI) 45.2.6 i s no longer applicable sinc /the c. (frm d EM' 6 declassification of protective coatingsj Thej majoritg 4f "Y pst & the coating f i el d engineers quali fi cati on records, reviewed ', by the NRC inspector indicated that gt.ffey had been qualifted or certified to ANSI 4 .2.6 before declassification of h/ octNM protective coatingsg Regardless, a beginning coating field engineer must still meet the following qualification requirements:
I PAGE 11
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\
. Minimum of one and one-half (1 1/2) years experience in !
\
the inspection and documentation of protective coatings ' work at a nuclear facility Shall be physically capable of performing the assigned tasks.
. Sh al,1 hav natural or corrected near distance visual ,
A,c4A.ih activity such that they are capable of reading J-1 letters on a standard Jaeger's Chart. These inspectors are gi ven classroom instruction on all coatings procedures, and a proficiency test for all instrumentation used to perform the i nsnarti on= , Tha coatings fi d supervisor evaluates the proficiency of the or ') Vp W gM inspectten tpe use of the instruments. , i s The NRC inspector did not review craft (painters) qualification because during the TRT's review, they stated that the craft adequate.
+ d* Cwae-l* -6 <W, --@g quali f ications were he NRC inspector reviewed two procedures. IEI-15, gi t , f 'I T 7 "Calibration of DFT Gauges," Revision 5, dated 3 :: 04 and IEI-35, "Qelibration of Adhesion Testers," Revision 3, dated T.WS*177894V ? "- 04 b p p M a.dM Mth .nrtre w k H4 4 8 V
.ts were calibrated to an accuracy of j
+/- 10%. The coatings field engineers procedures for l
t
4 9 i i PAGE 12 1 i minimum adhesion readings for the Eleef ometer Adhesion i Tester is more conservative than required. The NRC inspector reviewed calibration records of two > electrometer adhesion testers, (M&TE #3741 and M&TE #2904) and four DFT gauges, (M&TE #4332, M&TE #4333, M&TE #2809, and MSTE #2923). Records indicated that the instruments . were calibrated at their proper intervals' . "r disc.epens.w.
"r : .=tr^ V i
h(. V Action required of TUEC (NUREG-0797) Supplement No. 9). The NRC inspector reviewed the status of actions required by TUEC related to the TRT findings in NUREG-0797, Supplement No. 9 Dage M-13. 1). Backfit test program - The NRC inspector reviewed the Lo V data collected for the Eleefometer c al i br at i on correction to the data for adhesion tests coverinq miscellaneous steel items in Unit 1 6 2. The data is complete but has not been finalized into report form ! for submittal to NRC for review. 2). Traceability - This category deals with nonconformance i l reports (NCR's) which provide "use as is" dispositions i for discrepant coating materials with inadequate I r technical justification for the disposition.
- _.~ _ -
, I n
t PAGE 13 \ i I I The action required for this category has been completed by the licensee and submitted for review tolTa ~ p uince 9, g_ , ;_ , . / Director of Nuclear Reactor Regulation in TUGCO letter (TXX-4613) dated November i 18, 1985). 3b Coatings procedures. , The TRT found deficiencies in ' 3 / procedures and instruction for coating gwork ./ and related inspection activities, during the construction phrae, . i which rendered them inappropriate or inadequate .or t determining satisfactory accomplistment of important work activities. The TRT also found that the procedure review and approva*. system was inadequate to detect and cor ect these defi ci anci ac . Th's NRC inspector's review of this category indicates that TUGCO has revised their coating procedures for the Unit 2 construction phase and the reinspection activities for Unit 1 to include inspection attributes for determining satisf actory accomplishment of important work activities. CP-EP-6.2 has been established to assure that procedures and instructions are reviewed and approved by technically qualified ! i individuals to assure consi stency and clarity. I i
'l TUGCO letter TXX-4613 outlines the coatings '
survestlance program for operations.
, e t PAGE 14 4). Coating exempt log. The TRT requested an updated estimate of the number of additional items to be entered on the exempt log. Unit 2 exempt log is ,
f current and up-to-date. However, Unit 2 will have wery v t f-< ) l s b&t&4 e =n +e We tIV mV
='i=; into the exempt log because 3 deficient j arnJ p/
coating ( will be reworked or repaired. When the Unit 1 !
/ V Backfit e Test s Program
- data is complete, an estimate will o
be entered into the exempt log. i No violations or deviations were identified. '- t
- 8. Hoat i n_g._Venj;i 1 at i nn_ and Ai r C_ontij_t_) onj n nq_ ( HVAC) S v e.t e m e. ,_ 1]n Lt l i E. FSAR. speci f i cat i on, and drawings reviewed T;ie in. Lector l
reviewed the Comanche Peak Steam Electric Station (CPSES) Final Saf ety Anal ysis Report (FSAR) to identify the HVAC's design and quality assurance requirements. FSAR Volume IV. Section 7.2. "Classification of Structures. Components and I Systems," states that part of the containment ventilation system is seismic Category I; however, FSAR Volume XIV. 1 Section 17.0. Appendix 17A, "List of Quality Assured Items," ' states that the containment ventilation system (which contains eight subsystems / components) is seismic Category II and nonsafety related with the exception of the containment t [ purge exhautt ductwork, support, debris screen, and i sol ati on val ves, which are seismic Category I. Only the i
}
i PAGE 15 ! isolation valves, which are safety and code class 2, are safety related and seismic Category I. The Gibbs 6 Hill Inc. specification for HVAC systems is 2323-MS-85 Revision 3. Selected portions of this specification were reviewed to select the the hardware to be inspected. Isolation dampers or valves and hydrogen purge 5th b .vw systems wereg inspectpd.y
- b. Work observed. The NRC inspector used drawings numbers
/ v' 2323-M-2-0301, Revision CP-4 and 2323-M2-0502, Revision 1 to verify the equipment as-installed, t.e., identification.
location, and conf'.guration of the hydrogen supply / exhaust. and containment suppl y/purga /rel i ef svs+ams. The (011ching were inspected CDUIGIUMENT V6LVE SERI AL (JO. BIR EEGEIBBII98 001 M III 18 2HV 5543 14759-1B 12191 2HV 5563 14759-1B 12191 OHV 5542 14759-1F 12191 2VA 001 AF 074 9579 H 2012-1 Lot no.
g . .
. t PAGC 16 1
i M !!! 19 2HV 5541 14759-1A 12191 2HV 5562 14759-1B 12191 f 1 2HV 5540 14759-1C 12191 ! 2VA 002 AF 003 9579 ! I 7 Lo( no. H 2012-!
- MV2 2HV 5539 14759-3C 12191 1
2HV 5538 14759-3D 12191 }
- {
MV 14 2HV 5549 14759-2A 12191 } 2HV 5548 1 14759-2B 121'P1 j, 4 2VA 005 AD 213 08565 3 H if826-1 La no. MV 1 OHV 5537 14759-3A 12191 { OHV 5536 14759-3B 12191 2VA 007 AD ?10 03509 H 1826-1 Lot no. V
- c. Records Received - The NRC inspector reviewed Receiving v v -
, v s InspectionReporg[ packages (RIR) .which contained (}RfR ,12191.,
RIR 13110 R1R. 13186, RIR 1318j the f ol l owi ng t r Receiving check-list, drawings, OA check-list, and a
/
documentation package withidrawings, order speclfetsheet, af material traceability list, body mill test report (MTR), disc MTR, stem MTR. disc pin MTR, gasket retpiner MTR, gasket retainer bolts certification (CERT), filler metal i ! test report (TR), manufacturers material twet TA ,(t .
,y m qV certificate of compliance, liquid penetra&++e TR, weld
. l i
f PAGE 17 l V' TA repair report, body radiographics report, wall thickness
ry & V measurement eepect, final TR, cleaning Cert, cycle TR, ASME data report assembly shop traveler.
No violations or deviations were identified.
- 9. Mechanical Penetrations. Unit 2 In conjunction with the HVAC inspection, the NRC inspector observed mechanical penetration work which had been completed and reviewed selected records.
- a. Work observed - Penetration Nunters MIII-18, MIII-19, MV-2.
qNM / MV-14, and MV-1 were l ocated 4*em)drawi no nt'abar {& to 64 V 2323-M2-0502, Revision 1 and were, properl y identi f i ed and configured. These penetrations were properly protected and showed no damage.
- b. Records reviewed - The inspector reviewed RIR package f or penetration MIII-18 and found that the package contained the proper documentation.
No violations or deviations were identified.
- 10. Safety Related Pioe Suororts and Restraint Systems 4
' )
~
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PAGE 18 I 1
@, M)V i
- a. Procedures - The NRC inspector Brown & Root Inc. (B&R) CA '
manual, Section 16, Revi si on 16; Section 19, Revision 8 (i n ' part): and Appendix 1.0, Revision 3 (in part). ASME OA procedures CP-DAP-2.1, Revi si on 123 11.2, Pevision 8 11.1-28, Revi si on 341 and 19.1, Revision 2 (in part) were al so reviewed.
- b. Observation of work activity - The NRC inspector interviewed 3 craftsmen who were installing an anchor support for containment spray piping in the Safeguards building. The welding of the support and torquing of baseplate anchor bolts were witnessed. Wor} was accomplished in accordance wi th the work pac 6 ages.
f The NRC inspector inspected a total of 24 pipe supports on the Safety I injection system piping. Of these, two were large bore spring hangers, one small bore snubber, one large bore snubber, two equipment snubbers, eleven small bore restraints, and seven large bore restraints. Several discrepancies were noted on the l f allowing supports: _ _ _ _ _ _ _ _ _ ,, _ _ _ _ _ _ _ _ h_ _ _ d_{ . T $ I f._ . 1 However. OC has not performed their inspection of these supports, and hence installation can not be considered complete so*then no v v" findings cr- h= V g j 3*Ird at this time. Theg discrepancies found were i generally insufficient clearance or a departure from the desinn l I drawing. The basic design of the support systems examined appeared to be adequate. l I 1
) 1 sq ;
PAGE 19 4,h{ til t { { h4 i i i The NRC inspector reviewed seven saf ety related pipe support j i t documentation packages t ;.g- L- ) i { including records of materiale, welding, DC inspection. ! t i nonconformance reports, and rework and reinspection as follows: t [ The items of nonconformance were generally for dimensions slightly out of tolerance, (i . e. Hilti bolt minimum spacing). All NCR's appeared to be dispositioned properly. . No violations or deviations wr>re identified. i
- 11. Electrical Inspaction
- 12. F~it Interview
- An exit interview was conducted January , 1986, with the ;
applicant representatives identified in paragraph 1 of Appendix E i uf this report. During this interview, the NRC inspectors summarized the scope and findings of the inspection. The i applicant acknowledged the findings. j l h i l t h h I
1 . E - g s
- Bf i Jbf!3 '/*- g "W P88EI a 'r T .
g '8MPT 15.17 NT l ' 02M9111G CON $fRWCil0E !sIPtCTI M M PM T : U. $. NUCttAR M6itefMY C0m!$$!0s l : M6!ONIV IIRC Inspection Repwt 50445/0511 Pereit CFFR 126 50-446/0515 CFFR127 Category 42 locket: 50 445 50446 ;
. Applicants ie ai Utilities Electric Cospaty (TUCC)
$6yeayTeser 40 horth Olin Street L::t hi II
- blles,1esas 75201 '
facility Naee Creanche Feat Stese Electric Stat: p (Cittli Unit ! 6 2 Inspettien it: Glenicle,Tetal Inspution Cet. tutted: Decenter 131,1965 r laspectors. H. $. Phillips, Senicr Resident Reitter late Intentor ($RR!). Constriction, Region IV (RIV) CF5tl Group (paragraphs 1, 2, 3, 4, 5, 6, 8, 9, 121 l l. C. E. Johnson, Staior Resteent Peacter Cate lasputer ($Mll, Construction. RIV South Teial Frej n t (paragraph 71 i l P. W. 8'thavd Beatter Insenter, RIV late (peragrap'.101 l 1 l
i-g
. )
r PA6E 2 i D. L. Kelley, SRRI, Operations, RIV, late CPSES Group (paragraphs 11) Consultant: E666 - J. H. PcClesley
, Reviewed by:
- 1. Barnes, Group Leader, RIV CPSES Group Date Approved:
- T. F. Westersan, Chief, RIV CPSES Group Date I
w.emv- yy ye* ,.,,,3. ,,...y. .. . ,,,%. ,, , . ,-.,--,, , ,., ,_,,,,_-r-%, , , , , _ ,, .__r,. _.m , . . .-p, .- -, ,. - _ . _ , - - , - _.y, y y, ,
- 1. ,
1
, . I !
' i PAGE 3
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laynection Summarv k
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l i Ob_ser_vittion of Electrical Inst all a_t i on Act i vi t i es During this reporting period the NRC inspector observed two ~ saf ety-rel ated c able terminati on acti vi ti es. The first termination activity observed was a termination of a Train A (orange cable ) in a junction box in containment; the seennd was the termination of two Train B (green cable) in a motor control center (MCC) in the green , switchgear room. In-pt ocess work obwevati on was perf ormed to verify that: the latest drawings and termination cards are being used; the cables are t
. protectad from damage f rom ar r by ccr.;tructica acti vi ties; that proper separation is maintained; segregation of power, control and instrument L
cables is naintained; cable identification is preserved; bending l i radius is maintained; cable entry point is acceptable; tools requiring I. calibration are in good repair and properly calibrated; connection tightness is correct: terminations are of the correct type and properly located; junction boxes, MCC's and switchgear are free of debris: OC activities are performed at the times specified; nonconformances are identified and resolved in accordance with procedures; and installation and inspection activities are being documented during the in-process work activity. Terminations of two types were observed. One required terminal lugs, the other did not. The attributes specific to the termination type in addition to those
I
. 5.
PAGE 4 a attributes common to both were inspected. Cable numbers and termination points were; cable no. E02199710, termination point ' junction box (JB) 2C245 in containment and cable nos. EG213168,
~
AG213254 termination point. CP2-EPMCEB-06 in the green switchgear room. the NRC inspector verified that all pertinent requirements had been met. No violations or deviations were identified. . Inspection conducted: December 1-31. 1985 (Report 50-445/85-18) Areas Insoegted: Routine, unannounced inspections of Unit I which included applicant Ar+ i onc on .onstr uc t i on def i ci enci es, applicant actions on previous NRC inspection findings, IE Notices, Generic Letters, and TRY coatings. The inspection involved 59 inspector-hours onsite by two NRC inspectors and one consultant. - Results: Within the four areas inspected, no violation or deviation was identified. Insoection Conducted: December 1-31. 1985 (Report 50-446/85-15) 6C981_101Qgsted: Routine. announced and unannounced inspections of l l Unit 2 which included plant tours and applicant actions on nnstruction deficiencies; previous inspection findings IE Notices; t_
i I PAGE 5
'and Generic Letters; and inspection of protective coatings; heating ventil ation and ai r-conditioni r.g (HVAC); pipe supports; and electrical cable tray / equipment. The inspection involved 168 inspector-hours onsite by four NRC inspectors and one consultant.
Besults: Within the seven areas inspected, no violations or . deviations were identified. DETAILS
- 1. Persons Contacted Acolicant Personnel L. Hart. Quality Assurance (OA) TUGCO Nuclear Energy (TNE)
Electrical Engineer l P. Halstead, Manager, Quality Control (DC) [ F. Madden, TUGCO Nuclear Engineering (TNE) Mechanical Engineer J. Merritt, Assistant Project General Manager, TUGCO D. Palmer, Industry Operating Experience Coordinator l , P. Stevens, TNE Electrical Engineer l C. Welch, OA Supervisor, TUGCO i
i 6 PAGE 6 /
/
l The NRC inspectors also interviewed other applicant employees during this inspection period.
- 2. Acolicant Action on Previous NRC Inspection Findinos. Unit 1 and 2 (Open) Unresolved Items 445/8514-U-02 and 03; 446/8511-U-01 and 02; and 445/8516-U-01; 446/8513-01: Procedures did not address construction deficiency file content: incomplete GA record f i l e's ;
and TUGCO commitment to revi ew thi s matter. The NRC inspector continued the previous inspection by f oll ows mg up on each of these i teras during +his inspection period. TUGCO is still working on these items and anticipates completing the review and taking necessary Action to improve the current system by March 1. 1985. (Open) Unresolved Items 445/8516-U-02 and 03; 446/8513-U-02 and 03: IE Bulletin files for 79-14 and 79-28. The NRC inspectors continued the previous inspection by following up on each of these items. TUGCO is working on improving the IE Bulletin system and has named a new c oor di riat or . They will consolidate the files, and place OA records in the vault. The corrective ection on applicable IE Bulletins requiring hardware evaluation, t repair and replacement and verification will be reviewed to 6
. 1 i
4 t PAGE 7 assure that the cognizant construction organization tracks these actions to completion. No vic tions or deviations were identified.
- 3. Aoolicant Action on 10 CFR 50.55(e) Deficiencies (Closed) Construction Deficiency D-1-0181(CP-85-30): Switch gear cabinet terminations by the vendor. The NRC inspector inspected this item to determine why the terminations were replaced when TURCO letter TD -4595 dateil October 16. 1985 st at i ;
it was not reportable. The inspector reviewed the TUGCO r /clesti on and fou.id ti.al thiu tium won i .o t repu. table because they concluded it would not adversely affect the safe operation ' of the plant. It was only replaced because it did not meet TUGCO's standards (Attachment 9 of OI-OP-11.3-28) which may be more stringent than ihe manufacturer'e standord, s
- 4. Acolicant Action on Inspection and Enforcement Inf ormati on Notices (IEN)
The IE Information notices are sent to the nuclear industry for information purposes and require no action by the licensees and '
- applicants with respect to reporting to the NRC but are encouraged to take action on applicable notice technical issues 1
I
. _ , , - , - - - - - . , _ , . , , . , , - - , , - . . , , . . _ - . _._.- .-- _v-, , _ - _ , _ _ _ , . . , ~ _ , . _ _ . - - - - - _ _ - _ ~ ~ , -
I k PAGE 8 ,
\,
to prevent similar technical problems. The handling of these notices are not covered by NRC regulations; however, the~NRC is interested in how the technical issues in the subject notices are handled. The f ollowing notice files were reviewed to determine how TUGCO determined applicability; make distribution, and took action on IEN 85-04, 85-22, 85-33, 85-34, 85-35, 85-36, and 85-56. This review of TUGCO files shows that their established system is working satisfactorily as technical issues were addressed. No violations or deviations were identified.
- 5. Anolicant Action on Generic Letters The Generic letters are also sent to the industry for information purposes and require no response to the NRC. Again the NRC is interested in how the utility distributes, evaluates, and, if applicable, takes corrective action, lhe NRC inspector reviewed 15 fil es and sel ected Generic Letters 83-11 and 83-16 for a more detailed review. TUGCO Licensing receives and distributes these letters to the operations support group for their review and action. Review of the files revealed that the TUGCO system does adequately consider Generic Letters and appropriate action was taken on these generic letters.
No violations or deviatiens were identified.
l i PAGE 9 .
- 6. General Plant Insoections of Unit 2
^ At various times'during the i nspect i on per i od. NRC inspectors conducted unplanned inspections of the reactor building, safeguards building, and the electrical and control building.
The NF.C inspector observed ongoing construction work and discussed various subjects with personnel engaged in work activities. No violations or devi ati ons were identified.
- 7. Pr at art i ve coat i qqs, ..Qnj t__1 and 2
- a. The NRC inspe-tcr revicued the coating specif.cetions ano procedures for clarity, consi st enc y, technical criteria. and instructions for applying coatings. These procedures contain better criteria than the old procedures which were revi ewed by the NRC Technical Revi ew Team (TRT) in 1984 Personnel training / qualification. concrete / steel reinspection and inspection, testing, documentation. and repair are well covered in specification 2323-AS-31 and in Procedures CP-EP-14.2, 14.3, 14.7, 14.8, 14.1, 14.4, 14.9, 14.0, 14.5, 14.6, 6.2: CCP-30 and 40.
- b. Observation of work acti vi ty - The inspector observed work in progress and completed work as follows: pressurizer room
PAGE 10 31, steam generator rooms 26 and 29, elevator shaft roc.m 30, room 21, fabrication shop and paint storage building. Most of the work observed was surface preparation, however, a final application of the coating of the steel liner was observed in room 21. The surface preparation and application of coating were accomplished in accordance with good commercial practices and the crafts and field engineers were knowledgeable. Field inspectors were present and were notified by the craft when hold points were imposed. Pai,nt storage areas are temperature controlled and materi al shelf life was closelv moni t ored and cont rolled.
- c. Records Review - The protecti ve coatings paper flow group (CCA). Tha n'trroco nf the DFG is to e.t.aiido a mernon at initiating, preparing. i ssuing, tracking, logging, and ,
controlling protective coatings travelers and associated supporting documentation for the verification of coatings ac t i v i t a rs. The NRC inspector reviewed protective coatings travelers to determine if the records were adequate, complete. legible, easily retrievable and documented in accordance with site I procedures. In addition, the NRC inspector compared the completed and in process travelers to the PFG tracking system to determine if the tracking system was accurate. The computer printout is used for the tracking system.
- , - - - - ----r ,y v -
- , - - , - , ,- - -~,--we --.--g,
?
.i PAGE 11 i,
t listing the traveler number. package number, unit, area , code / room, number, any outstanding coating deficiency ' reports and the traveler status. Records reviewed were legible, easily retrievable and complete in accordance with site coatings procedures. Review of the Unit 2 coating records tracking system, by the NRC inspector, indicated that the system, at the site is now a very reliable and accurate tracking system. The tracking system is updated on a daily basis. Thr- NRC intpector al so revi ewed in proress travelers in the field. One minor isolated discrepancy was noted on traveler
.S1-^., hm mme , tb7 si0nntur: which was in i. e + we ong niouk received prompt attention when it was brought to the foreman's attention. All other travel ers reviewed were correct.
The f ollowing work packages which contained more than or.e travel er were revi ewred: 2-21-F, 2-21-0, 2-21-I. 2-21-N, 21-H, 2-21-B, 2-21-E, 2-21-AJ, 2-21-G, and 2-21-L. The NRC inspector reviewed 8 training records for coating field engineers who were trained and qualified in accordance l with site procedure CP-EP-14.1. Revi si on O. The American National Standards Institute (ANSI) 45. 2. 6 i s no l onger
. --- . - __ . - . ~ . . - . - . .- - . -
. i *
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PAGE 12 ! applicable since the approved declassification of protective ', coatings; however, the majority of the coating fiald ~ engineers qualification records that were reviewed by the i NRC inspector indicated that they had been qualified or ' certified to ANSI 45.2.6 before the deciassification of protective coatings occurred. Regardless, a beginning , coating field engineer must still meet the following qualification requirements: t Minimum of one and one-half (1 1/2) years experience in the i n sp ec ti on and documentation of protective coatings
- worl at a nuclear facility 5
C - 1 1 5P 'hy=1cally capabte of ger f orerei e g cne assigned tasks. Shall have natural or corrected near distance visual I acuity such that they are capab]e of reading J-1 ; letters on a standard Jaeger's Chart. These inspectors are given classroom instruction on all coatings procedures, and a proficiency test for all instrumentation used to perform the inspections. The coatings field supervisor eveluates the proficiency of the inspector's use of these instruments.
- 1. .
- , . - .- - _ , _ . . . . . _ . . . ~ . _ , . _ . , _ _ _ . , , . - - - - , . , , , , . . . , , , . _ _ . _ . , - _ - - . , -
_ _ . , . _ . - , . - . _ _ . y--
~ . . .
i I PAGE 13 i
-i The NRC inspector did not review craft (painters) !
qualificati on because during the TRT's revi ew, they stated that the crafts qualifications were adequate,
- d. Calibration. The NRC inspector reviewed two' procedures.
4 IEI-15, "Calibration of DFT Gauges, " Revi sion 5, dated March 11, 1982 and IEI-35. "Calibration of Adhesion Testers," Revision 3, dated February. 27, 1984. The gauges and adhesion testers were calibrated to an accuracy of +/- 10"(. . The coatings field engineers procedures for minimum adhesion readings for the Electometer Adhesion Tester is more conservative than required. Tbn NRC inapactor rc* *i thed Cal i brall ure t eCor du vi twO electometer adhesion testers. (M&TE #3741 and M&TE #2904) and four DFT gauges, (M&TE #4332, M&TE #4333, M&TE #2809, and M&TE M2923). Records indicated that the instruments were calibrated at their proper i ntervels.
- e. Action required of TUEC (NUREG-0797) Supplement No. 9). The NRC in?.pector reviewed the status of actions required by l
TUEC related to the TRT findings in NUREG-0797, Supplement [ No. 9, page M-13. . l i 1). Backfit test program - The NRC inspector reviewed the l data collected for the Electometer calibration y=.e r-m,i-m--.-rv, ,w.-- - .-r.y. .--.m,.3
- - -e, - - - -
-r - - -
l
^i l
1 I PAGE 14 . , correction to the data for adhesion tests covering miscellaneous steel items in Unit 1 & 2. The data is complete but has not been finalized into report form for submittal to NRC for review. 2). Traceability - This category deals with nonconformance reports (NCR's) which provi de "use as is" di sposi tions for discrepant coating materials with inadequate technical justification for the disposition. , j The actInn roquired for this category has been completed by the licensee and submitted f or revi ew to the, Director of Nuclear Reactor Regulation in TUGCO i st + er 'TV"-
- a 17. ) Jated t'esember la, 1980!.
3). Coatings procedures. The TRT found deficiencies in procedures and instructions for coatings work and related insprction activitten, during the construction phase, which rendered them inappropriate or inadequate for determining satisfactory accomplishment of important work activities. The TRT al so f ound that the procedure review and approval system was inadequate to detect and correct these deficiencies. The NRC 2nspector's review of thi s catagory indicates that TUGCO has revised thei r coati ng pr oceduren f'.?r the
PAGE 15 k i Unit 2 construction phase and the reinspection
- activities f or Uni t i to include inspection attributes for determining satisfactory accomplishment of important work activi ties. CP-EP-6.2 has been established to assure that procedures and instructions are reviewed and approved by technically qualified individuals to assure consistency and clarity.
TUGCO letter TXX-4613 outlines the coatings . surveill ance program for oper a t i on s. 4). Coating nuempt 104 The TRT requested an updated estimate of the number of additional items to be an t arrd an *_P 2 c. ca.p t 1-u. Ur.i l 2 Onempt lug is current and up-to-date. However. Unit 2 will have few entries into the exempt log because any deficient coating areas will be reworked or repaired. When the Unit 1 backfit test program data is complete. an estimate will be entered into the exempt log. No violations or deviations were identified. 8. Heat ino Ventilation and Air Conditionino (HVAC) Systems. Unit L_
- a. FSAR. specification. and drawings reviewed - The inspector i
reviewed the Comanche Peak Steam Electric Station (CPSES)
PAGE 16 . Final Safety Analysis Report (FSAR) to identify the HVAC's l design and quality assurance requirements. FSAR Volume IV, Section 3.2, "Classification of Structures. Components and Systems," states that part of the containment ventilation system is sei smic Category I; however, FSAR Volume XIV, Section 17.0, Appendin 17A, "List of Quality Assured Items," states that the containment ventilation system (which e contains eight subsystems / components) is seismic Category II and nonsaf ety related with the exception of the containment purge exhaust ductwork. support, debris screen. and
-isolation v al vr>s , which are seismic Category I. Only the i sol at i on vol ves, which are safety and code class 2. ar e saf ety rel ated and sei smic Category I.
The Gibbs t< Hill Inc. specification for HVAC systems i s 2323-MS-85 Revi si on 3. Selected portions of this specification were reviewed to select the the hardware to be i nspect ed. Isol ati on dampers or val ves and hydrogen purge systems were sel ect ed for inspection,
- b. Work observed. The NRC inspector used drawings numbers 2323-M-2-0301, Revision CP-4 and 2323-M2-0502. Revi si on 1 to verify the equipment as-installed, i.e., identification.
location, and configuration of the hydrogen supply / exhaust. and containment suppl y/ purge /rel i ef systems. The following were inspected:
1
+
t PAGE 17 t t C9NIAlUMENI______VeLyg______ SERIAL Ng z ___ __BI R EENEIB8110N 09v M III 18 2HV 5543 14759-15 12191 2HV 5563 14759-1B 12191 2HV 5542 14759-1F 12191 , 2VA 001 AF 074 9579 H 2012-1-Lot no. M III 19 2HV S541 14759-1A 12191 2HV 5562 14759-1B 12191 2HV 5540 147G9-iC 1/141, 2VA 00? AF.003 9579 H 2012-1 Lot no. 1: MV2 2HV 5539 14759-3C 12191 2HV 5538 14759-3D 12191 l MV 14 2HV $549 14759-2A 12191 \ 2HV 5548 14759-28 12191 2VA 005 AD 213 09565 [ H 1826-1 Lot no. l MV 1 2HV 5537 14759-3A 12191 l t 2HV 5536 14759-3B 12191 2VA 003 AD 219 08509 H 1826-1 Lot no. m , , e o..,w--,w
,,, - . - --, , - . , _ , , -- -.,--.--c.,----,,'. e ,.r,-- vy-y,-~---vamre- F- r rr--v- wr~ +-
i c t PAGE 18 c. Records Received - The NRC inspector reviewed receiving inspection report (RIR) packages (RIR 12191, RIR 13110, RIR i i 13186. and RIR 13187) whi ch contained the f ollowing: Receiving check-list, drawings, OA check-list, and a i documentation package withs drawings, order specification sheet, material traceabili ty list, body mill test report (MTR), disc M7R, stem MTR, disc pin MTR, gasket retainer MTR, gasket retainer bolts certification (Cert), filler , metal test report (TR), manufacturer's material TR, certificate of compliwnce, liquid penetrant TR. weld repair report, body rad s por sphi cs TR, wal1 thicknens measurennent report, final TR. cl eaning Cert, cycle TR, ASME data report au e mh1v ab.,p +ravm'nr No violations or deviations were identified.
- 9. Mechanical Penet rat i ong lfn t t 2 In conjunction with the HVAC inspection, the NRC inspector observed mechanical penetration work which had been completed and reviewed uel ected records.
- a. Work observed - Penetration Numbers MIII-18 MIII-19 MV-2.
MV-14, and MV-1 were located using drawing number 2323-M2-0502, Revision 1 and were fount to be properly
. l i l I
l PAGE 19 l identified and configured. f These penetrations were properly
- protected and showed no damage. '
b. Records reviewed - The inspector reviewed RIR package for penetration MIII-10 and found that the package contained the proper documentation. No viol ations or deviati ons were identified.
- 10. Safety Rel ated Pioe Supports and Restraint Systems
- a. Proceduren - The NRC i nspector r e vi ewed Brown b Root Inc.
(BLR) OA manual, Section 16, Revi si on 16; Section 19 Revi r.i on 8 Mn parti; end appe..dia 1.U, Neviilun s tin part). ASME DA procedures CP-OAP-2.1. Revision 12 11.1. Revision 0; 11.1-28, Revision 34: and 19.1, Revi si on 2 (i n part) were also revi ewed. l
- b. Observation of work activity - The NRC inspector interviewed 3 craf tsmen who were installing an anchor support for containment spray piping in the Safeguards building. The !
welding of the support and torquing of baseplate anchor bolts were wi tnessed. Work was accomplished in accordance ' t with the work packager. L
, - - - - . . - - , , , - , , - - , = , -.------,-n-,----,------n-.,- , - - - , , , - - , - . , - - - - - - - - - . - - . - - - - ~ . - -
. i PAGE 20 The NRC inspector inspected a total of 24 pipe supports on the Safety I injection system piping. Of these, two were large bore spring hangers, one small bore snubber, one laroe bore snubber, two equipment snubbers, eleven small bore restraints, and seven large bore restraints. Several discrepancies were noted on the following supports: H-SI-2-SB-020-1-2, 2, 5-2, 6-2, 8-2, 10-2, 11-2, and 12-2; H-SI-2-5B-019-1-2, 3-2, 4-2, and 5-2; SI-2-039-401-S22R, SI-2-039-404-S22R; SI-2--309-406-522R; SI-2-044-401-S22R; SI-2-070-404-S22R; SI-2-070-405-S22K; and ,
SI-2-070-406-522R. However, OC has not performed their inspection of theso supports, and hence installation can not be considered complete In there are no findings at this time. The discrepancies found were generally insuf ficient clearance or a departure from ti.e deeiga dr awin . The ba iw du,m ion of 'he support systems examined appeared to be adequate. The NRC inspector reviewed seven safety related pipe support documentati on packages including records of materials, welding. OC inspection, nonconformance reports, and rework and 4 reinspection as follows: RH-2-58-024-OO1-2, CT-2 -038-402-C52R. CS-2-RB-072-702-1, CC-2-041-713-A63R, MS-2-150-448-C52K. H-CS-2-RB-021-7120-1, and H-SI-2-RB-0580-701-2. l l The items of nonconf ormance were generally f or dimensions slightly out of tolerance, (i . e. Hilti bolt minimum spacing). All NCR's appeared to be dispositioned properly, l
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PAGE 21 No vio1'ations or deviations worse identified. '
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- 11. Electrical Inspection i f
- 12. Exit Interview t
b ! An exit interview was conducted January O, 1986, with the v'
-applicant representati ves identified in paragraph 1 of Appendix E of this report. During this interview, the NRC inspectors ;
summarized the scope and findingt of the i nspection. The appl t c ant acknowlodged the findingc. k P c l l i, f l ( e
- V
---..,,,-m...-.., , . _ , - - - - , , - , , , - - . . . . - - < .
E -
#3 '
2//2/16 i PME l
' ~BRWT 18.1, REV.2 Y Afft!IlliG i
i COWSTRUCTION INSPECTION REPORT , U. S. NUCLEAR REGULATORY COMMISSION ' REGIONIV i MC Inspection Repcrt: 50-445/0518 Persit: CFFR-126 50-446/65 15 CPPR-127 Category A2 Docket: 50-445 50-446
, Applicant: Texas Utilities Electric Coepany (TUECl Skymay Toser 400 North Olive Street Lock Bor 81 Dallas, Texas 75201
- Facility Nase: Cceanche Fran Steae Electric Station (CFSES) Unit 1 & 2 Inssection Att Glen Rese, Texas inspection Conducted: Deceeber 1-31,1995 Inspectors:
H. S. Fhillips, Senior Resident Reactor Date Inspecter (SRRI). Construction, Region IV (RIV) CPSES Group (paragraphs I, 2, 3, 4, 5, 6, 8, 9, 121 l C. E. Johnson, Senior Resident Reactor Date Inspector (SRRI), Construction, RIV l South Texas Project j fparagraph 7) 1
/
P. W. Michauf, Reactor Inspector, Riv Date 3V (paragraph 10) l L l t
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PAGE 2 i 1 I i
- 9. L. Kelley, SRRI, Operations, RIV, ' Bate 'V '
CPSES Group (paragraphs ill ; i 4 Consultant: E666 - J. H. McClesley
, , Reviewed by:
- 1. Barnes, Group leader, RIV CPSES Group Date -
t Approved:
- T. F. Westersan Chief, RIV CPSES Grcup Date -[
[ t I s I k
+
[ i 1 h i i f I i _ _ - - . . . . . , - , - - -~
' i
- t PAGE 3 :
i ( Inspection Summarv
/
s- l 1
' r u .a ..k, ,\ i ll=Obser._v,af i nn__of El ec t r i c a l InstMiet i on Activities y
a\
;6.d '
l During this reporting period the NRC inspector observed two safety-related cable termination activities. The first termination activity observed was a termination of a Train A (orange cable ) in a junction box in containment; the second was the termination of
- eo Train B (green cable) in a motor control center (MCC) in the green ,
switchgear room. in-penrev wne l- obscr stion wan perinrmnd to verify that: the latect drawings and termination cards are being usedt the cables are n q+ e-+ ed J e na d amaga . f r run nearb y r.:. 'r ue t i t. . cti..Lias; thet propea separation is maintained segregation of power, control and instrument cables is maintained cable identification is preserved; bending radius is maintained: cable ent ry poi nt is acceptable: tools requiring calibration are in good repair and properly calibrated: connecticn tightness is correct; terminations are of the correct type and properly located; junction boxes. MCC's and switchgear are free of debris; OC activities are performed at the times specified;
; nonconformances are identified and resolved in accordance with t
procedures; and installation and inspection activities are being
; documented during the in-process work activity. Terminations of two i
l types were observed. One required terminal lugs, the other did not. f i The attributes specific to the termination type in addition to those t.
1 PAGE 4 i
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attributes common to both were inspected. Cable numbers and ' termination points were; cable no. E02199710, termination point junction box (JB) 2C245 i n containment and cable nos. EG213168. AG213254 termi nati on point. , j. j.4 CP2-EPMCEB-06 in the green switchgear room. the NRC inspector j verified that all pertinent requirements had been met. I J No violations or devi ations were identi fied.
.L' -
I n qp ec t_i on conducted: December 1 -3 L 1985 (Rey.or t 50-445/85-18) Areas Inspected: Routine, unannounced inspections of Unit I which includ.H appl i. r ant e.-ti on :n wnstr u ti co deficienste,, applic.ent actions on previous NRC inspection findings, IE Notices. Generic I L Tk.Lhs. w % % s V Letters, andpRT) coatings. The innpection involved 59 inspector-hours onsite by two NRC inspectors and one consultant. Resultsi Within the four arear, inspected, no vi ol at t on or devi at i on was identified. Insoection Conducted: December 1-31, 1985 (Report 50-446/85-15)
- 6C&;ag_losaggigd
- Routine, announced and unannounced inspections of t
Unit 2 which included plant tours and applicant actions on l construction deficiencies; previous inspection findings: IE Notices: t _, . . . . - , . - _ _ . , ~ _ , _ ..~,,._,v_ v., ,,_.,--_.__...,,,,,.y..,. ,__,.-__.,_m. - _ _ _ _ , _ , , , _ _ . _ _ , . , . . . _ , . , . . , _ . . . _ . . _ _ _
'4 PAGE 5 , g and Generic Letters; and inspection of protective coatings; heating ventilation and air-conditioning (HVAC); pipe supports; and electrical cable tray / equipment.. The inspection i nvol ved 168 inspector-hours onsite by four NRC inspectors and one consultant.
Bestj },t p : Within the seven areas inspected, no violations oc deviations were identified. I DETAILS ) l
?P".TOs EQO.tertad m .
']* *3..bW
- ..'i. '!. _,. . . . d. ff_M. - -_ . . . . m#H' 9_.
l L. Hart. Quality Assurance (OA) TUGCO Nuclear Energy (lNE) Electrical /
-- ~~, .- .
i Engineer i P. Halstead, Manager, Quality Control (OC) y l l l F . _ Ma d d en . TMGCO 'b; 1 e r--Enqir. r i n g fTNE Q Mec h a n i c a l Engineer i J. Merritt, Assistant Project General Manager Ti trr9 V i i D. Palmer, Inductry Operating Euperience Coordinator i P. Stevens, TNE Electrical Engineer C. Wolch, OA Supervisor, TUGOO-
J' I t PAGE 6 i
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i The NRC inspectors also interviewed other applicant employees during this inspection period. , 2. Acolicant Action on Previous NRC Insoettien Findinos. Unit 1, and 2 (Open) Unresolved Items 445/8514-U-02 and 03; 446/8511-U-01 and 02; and 445/8516-U-01: 446/8513-01: Procedures did not addres,s construction deficiency file contents incomplete OA record files;
- d. fn
- a. 'a' n* 4 -t ' M(
d TUGCO c 'ommi I " * * *tment
- O
- Vto review this matter. The NRC inspc: tor tontinuod the pr e /s ouc i nnpect i on by following up on each of these itemn during this inspection period. TUGCO is still workino nr. + *m:-' i t .s. A.ad :.r.t i ci pe le, con.pl et i ng the ra ci c ar.d taking necessary action to improve the current system by March 1, 1985.
f (Open) Unr es.o l s ed Items 445/8516-U-02 and 03: 446/8513-U-02 and 4 03: IE Bulletin files f or 79-14 and 79-28. The NRC inspectors continued the previous inspection by following up on each of j these items. TUGC0 is working on improving the IE Dulletin l system and has named a new coordinator. They will consolidate o the files, and place OA records in the vault. The corrective action on applicable IE Bulletins requiring hardware evaluation. b/ l repai r a,n d,, r ep l a c emen t and verification will be reviewed to i i
d e 1 1 PAGE 7 5 i assure that the cognizant construction organization tracks these actions to completion, j No violations or deviations were identified. 4
- 3. Acolicant Action on 10 CFR 50.55(e) Deficiencies
- (Closed) Construction Deficiency D-1-0181(CP-85-30)
- Switch gear cabinet terminations by the vendor. The NRC inspector inspected this item to determine why the terminations were
! r ep l eiced when 1UGCO l ett er Ty F-C?S dded October 16, 198'i st ated 1/24 L i i . ..m &
iM was not reportable. The inspector reviewed the TUGCO
- v a l e * ' F i r :- r
- 3 .ur.J tk.)! thir ' t ric a at r.t:t . . p ut t..sbi a beceu,+
5- W they concluded it would not4 adversel y af f ett the safe operation W i of the plant. It was only repl aced because it did not meet TUGCO's standards (Attachment 9 of DI-OP-11.3-28) which may be more stringent than the manni acturor's st andard. l 4. Apolicant Action on Ingpection and Enfor,Sement Information l Nr,tices (IEN) s V The IE Information Motices are sent to the nuclear industry for inf ormation purposes and require no action by the licensees and tl+1 V applicants with respect to reporting to the NRC but,3are encouraged to take action on appl i cabl e not'l1ce V technical issues,v g' { li e s 4 t.a. , k
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PAGE 8 to prevent similar technical problems. The handling of these e notices are not covered by NRC regulations however. the NRC is interested in how the technical 1suues in the subiect noticee are handled. The f ollowing notice files were reviewed to determine how TUGCO determined applicability; make distribution, and took V action on IEN 85-04, 85-22, y85-33, f'5-34, 8 ,85-35, p. 85-36, and V'85-56. Tnis review of TUGCO files shows that their establi shed syste.n is working satisfactorily as technical issues were addressed. No violati ons or deviations were identified.
- 5. Aeolicant Action on Generic Letters
/ I gM t y W The Generic Tetters are also sent to the, industry for information purposes and require no response to the NRC. Again the NRC 1s interested in how the utility distributes, evaluates, and, if i applicable, takes corrective action. The NRC inspector reviewed
! 15 files and selected Generic Letters 83-11 and 93-16 for a more detailed review. TUGCO Licensing receives and distributes these letters to the operations support group for their review and action. Review of the filea revealed that the TUGCO system does 4 adequately consider Generic Letters and appropriate action was taken on these generic letters. ' t ] a d, No violations or devi ati ons were i denti f i ed. ! I i
.. . - - - . ~. . - _- . .. - - . E 2
i g e PAGE 9 .
- 6. General Plant Insoections of Unit 2 1
At vari ous timeu duri ng the inspection period. NRC inspectors ' F us y conducted unp1 nned , inspections of the reac or buiJting, , safeguards butJE ing, and the electrical a , c.on t r ol building.- The NRC inspector observed ongoing construction work and discussad various subjects with personnel engaged in work activities. No violations or deviations were identified. i
- 7. E'r nt +,r t i vr_ coa t i ng g uUnit 1 and 2 2
4 Tha NR" inspector revleued th; c ca t i c.4 upectiisatimes c.id i procedures for clarity, consistency, technical criteria. and ( instructions for applying coatings. These procedures contain better criteria than the old procedures which were ' , reviewed by the NRC Technical Revi ew Team (TRT) in 1984. Personnel training / qualification, concrete / steel f-l reinspection and inspection. testing, documentation, and i l repair are well covered in specification 2323-AS-31 and in Procedures CP-EP-14.2, 14.3, 14.7, 14.8, 14.1 14.4, 14.9, I f 14.0, 14.5, 14.6. 6.2: CCP-30 and 40. I , [
- b. Observation of work activity - The inspector observed work in progress and completed work as f ollows: pressurizer room ;
I l
- i
i 4 I l PAGE 10 . 31, steam generator rooms 26 and 29, elevator shaft room 30. room 21, fabrication shop and paint storage building. Most of the wort obnorved was surface preparation. however. 4 final application of the coating of the steel liner wac observed in room 21. The surface preparation and application of coating were accomplished in accordance with . good commercial 0 practices and the crafts and field engineers were k nowl edgeabl e. Field inspectors were present and were notified by the craft when hold points were imposed. Paint stor age areas are tono we controlled and material shelf liie wa' clot.elv moni+
- n r1 :antrolled.
- c. Recor ds Revi ew -
The protective coatings paper flow group I "'m i ne nurpose cf U.e TIC .* L o e M e b s 4 tin i.i melhua ci Initiating, preparing, issuing, tracking. logging, and cont rolling protect ) ve coatings travel ers and associ ated supporting documentation for the verification of enating?
.* t i t v t t t 0h.
The NRC inspector revi ewed protective coatings travel ers t o determine i f the records were adequate. complete. legible, easily retrievable and documented in accordance with site procedures. In addi ti on, the NRC inspector compared the completed and in process travelers to the PFG tracLang system to determine if the tracting system was accurate. The comput er printout is used for the tracking sys t ein .
s a PAGE 11 listing the traveler number, package number, unit, area ! t code / room, number, any outstanding coating deficiency ' r eport n and the traveler status. Records reviewed were legible, easily retrievable and completo in accordance with site coatings procedures. Review of the Unit 2 coating records tracking system, by the NRC inspector. indicated that the system, at the site is now a very reliable and accurate tracking system. The tracki,ng system is updat ed on r, dai 1 y basis. The NPC i nspector a l r.r r .$vi c-wed in ptocuts traveler 5'. in the field. One minor isolated discrepancy was noted on traveler v 2-71-n.. howauce the ,,: y. .a l u . (;.h i i t ew i ni tiive wr ong blork)l y V t C. ~ d4d V s I ret . c hwpromp t'at++ ota.on when it was brought to the foreman's attention. All other travelers reviewed were correct. The f ollowing worl parl:agen which contained more than one traveler were reviewed: 2-21-F. 2-21-O, 2-21-1. 2-21-N. 21-H, 2-21-B, 2-21-E. 2 AJ . 2-21-G, and 2-21-L. The NRC inspector revi ewed 8 training records f or coating field engineers who were trained and qualified in accordance with site procedure CP-EP-14.1. Revision O. The American National Standards Institute (ANS!) 45. 2. 6 i s no l onger
- . . - = = . . _. . -
i
. I e .
i PAGE 12 3_ applicable since the approved declassification protective' r coatings; however, the majority of the coating ield engineersf quali fi cat 2 cn records that were revic>wed by the NRC inspector indicated that they had been qualified or certified to ANSI 45.2.6 before the declassification of protective coatings occurred. Regardless, a beginning 6-coating field engineer must still meet the following qualification requirements: yilu+ ! '
/i sv Mi ni mum of one and one-half (1 1/2) years experiento in the inspecti on and documentat s on of protecti ve cont i nos wori at a nuclear f acilit v. s Sb Al l Sr. physicall, capabl e w T g.ar f or .7.l og eno ca s i grien tasks.
t I Shall have natural or corrected near distance visual l i acuite such that they are capable of reading J-1 letters on a standard Jaeger's Chart. i These inspectors are given classroom instruction on all coatings procedures, and a proficiency test for all i instrumentation used to perf orm the inspections. The coatings f i el d supervisor evaluat es the profi ciency of the inntector's use of these instruments.
' 1 a
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PAGE 13
- i The NRC inspector did not review craft (painters) or
$~"'*~ 'c qua l i f i c a t i onj b ec a u se 1, a . ,+ t h e TRT % r evi ewg& "they s R4 t ha-t t h e r -- 9 + n e ua LM+c " i s . - cm adequate.
- d. Calibration. The NRC inspector reviewed two procedures, IEI-15, "Calibration of DFT Gauges, " Revi si on 5, dated March 11, 1982 and IEI-35 "Calibration of Adhesion Testers,"
Revision 3, dated February, 27, 1984. The gauges and adhesio, testers were calibrated to an accuracy of +/- 10,%. L / The coatingt, 6i+1d =OmeeN3 procedures for minimum adhesion
~
. V' r aadi ngs for the E1 [:t omet er Adhesion Tenter is more c on r,er u t i v e i han requi r ed.
The NRP i nspwr tne envi =w-i "alibratinn retcrde, wT t6 0
/ /
el ib,[omet er adhesion testers, (MLTE #3741 and Mkfd #2904) v, y and foup DFT gauges. (MSTE #4332. MpTE #4333 Mb E #2809.
/
and M!pT E.42923). Records indi cated that the instruments a were cell brated at their proper intervals. yt
- t. . pv e.
Action required of TUEC (NUREG-0797) Supplement No. 9) . g The NRC inspector reviewed the status of actions required by /.It TUEC related to the TRT findings,An NUREG-0797. Supplement No. 9. . p ag e M- 10.- J' ! !). Backfit test program - The NRC inspector reviewed the f data collected for the Elect'ometer calibration [ _
i [ t PAGE 14 . !
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correction to the data for adhesion tests covering ' l miscellaneous steel items in Unit 1 & 2. The data is complete but hat not been final% %Anto'- report f Be
,/v to i
.4 V *b V l 4cr subm1 t t#1 ' to NRC f or revi ew.
2). Traceability - This category deals wi th nonconf ormance . reports (NCR's) which provide "use as is" dispositions for discrepant coating materials with inadequate technical justification for the disposition. , 4 The~ action required for thi s category has been i, aV c oirip ] o f e d b s the 11cenuce and,rubmitted for review to
. V tho/ Director of Nuclear Reactor Regulation in TUGCO i lo++o- 'TXY-4'.*75 datrd Novembcr IC, 17C3).
31 Coatings procedures. The TRT found deficiencies in - procedures and instructions for coatings work and related i nspect 3 on at t i vi t i ev.. during the construction , phase, which rendered them inappropriate c,e inadequate for determini ng sati sf actory accompli shment at ' important work activities. The TRT also t.und that the ?
< w ( de d.w procedure review and approval sysi.em was inadequate,to '
detect and correct t. ese defici encies.
/ ..
/ /
L, p.c P' f) , (.s(~ 6
+
I The NRC inspec'or's review of t h i s e 2 t y m i rtd i c a t.es-
.that TUGCO hap revised their coating procedures for the !
i L l ---. . - - . . - - - . -. - -. -
_f.
)
e 4
. PAGE 15 -
1 i n Unit 2 construction phase and the reinspection. activities for Unit 1 to include inspection attributes for determining satisfactory accomplishment of important work activi ties. CP-EP-6.2
.v a>v hat 5:r3 established to assure that procedures and instructions
, are reviewed and approved by technically qualified
) individuals to assure consistency and clarity.
, TUGCO lett.er TXX-4613 outlines the coatings ,
surva111ance program for operations. 4). Coat i no en empt 1oo. The IR1 rnouested an updat ed estimate of the number of additional items to be er.tered an the an nmn '. Icg. Ur i t ? ., u...s i ic4 ic current and up-to-date. However. Unit 2 will have few entries into the e::empt log because any deficient coating areas will b r- reworked or repaired. When the Unit 1 baci:f i t t es.t procram date is complete, an estimato will be untered into the exempt log. No violations or deviations were identified.
- 8. Heatino Ventilation aqd Air Conditionino (HVAC) Systems, Unit 21
- a. FSAR, specification, and drawings reviewed -
The inspector reviewed the Comanche Peat Steam Electric Station (CPSES)
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Final Safety Analysis Report (FSAR) to identify the HVAC's ; design and quality assurance requirements. -FSAR Volume IV, Section 3.2. "Classi fication of Structures. Components and $ 1 Systems." states that part of the containment ventilation \ system is seismic Category It however, FSAR Volume XIV. t
\
Section 17.0, Appendix 17A. "List of Quality Assured Items," i i states that the containment ventilation system (which - contains eight subsystems / components) is seismic Category II ! and nonsafety related with the exception of the containment . purge enhaust ductwork, support, debris screen. and t sol at i on val ves, which are seismic Categorv I. Only tt o i sol at i nn val vee, which are safety and code clan 2. are safety related and seismic Category I. [ The Gibbe t< Hill Inc. specification for HVAC systems is 2323-MS-85 Revision 3. Selected portions of this
- specification were revi ewed to select the the hardware to be j incpecied. Isol ation dampers or valves and hydr ogeri pur ue f
systems were selected for inspection. ! y I j b. Work observed. The NRC inspector used drawings numbers 2323-M-2-0301, Revi si on CP-4 and 2323-M2-0502. Revi si on 1 to veri f y the equipment as-installed, i.e.. i dent i f i cati on . location, and configuration of the hydrogen supp19/enhaust. i and containment supply / purge / relief s yst eias . The following were inspected
i..
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i k e , i PAGE 17 I i k.
\1 l lt i
i CQUIGIUMEUI______YGLVE______ SERIAL UQt____BIR ' ' EENEI68Il06 t NQt - M III 18 2HV 5543 14759-1B 12191 2HV 5563 14759-1B 12191 ' L 2HV 5542 14759-1F 12191 i
-2VA 001 AF 074 9579 :
i t H 2012-1 Lot no. . M III 19 2HV 5541 14759- 1 A 12191 [ ' 2HV 5562 14759-1B 12191 2HV $54^ 11757-10 12171 i i 2VA 002 AF 003 9579 , H 2012-1 Lot no. MV2 , 2HV 5539 14759-3C 12191 h 2HV 5538 14759-3D 12191 MV 14 2HV 5549 14759-2A 12191 i 2HV 5548 14759-2B '12191 , t. 2VA 005 AD 213 08565 [ H 1826-1 Lot no. 1 r, MV 1 2HV 5537 14759-3A 12191 i OHV 5536 14759-3B 12191 I 2VA 003 AD 219 00509 I H 1826-1 Lot no. I
. I k
1 PAGE 18 ! c. vi<w / Records Repe+ved - The NRC inspector reviewed receiving
- inspection report (RIR) packages (RIR 12191, RIR 13110, RIR 13186. and RIR 13187) which contai ned the following:
Receiving check-list, drawi ngs, CA check-list, and a documentation package withs drawings, order specification sheet, material traceability list, body mill test report (MTR), disc MTR, stem MTR, disc pin MTR, gasket retainer MTR. gasket retainer bolts certification (Cert), filler , metal test report (TR), manuf acturer 's materi al TR, cortificate of c ompl i ance. l i qtii d penetrant TR, weld repair report, hoov rads 00rAphict 1R. wall thtciner.c mowouremer.t report, final TR, cleaning Cert, cycle TR, ASME data report aca emi.i < .hnp + r c "r.1 c . No violations or deviations were identified.
- 9. Mnchanical Nn nt r a t inrtg uUn i t 2 In conjunction with the HVAC inspection, the NRC inspector observed mechanical penetration work which had been completed and reviewed selected records.
- a. Wor 6 observed - Penetration Numbers MIII-18, MIII-19 MV-2.
l MV-14 and MV-1 were located using drawing number d V i 2323-M2-0502, Revi si on 1 and were fount'to be properly l
l. l PAGE 19 , identified and configured. These penetrations were properly protected and showed no damage, b. Records reviewed - The inspector reviewed RIR package f or penetration MIII-18 and found that the package contained the proper documentation. No violations or deviations were identified.
- 10. Safety Related Pine Supp.orti An.d Restraint _ Systems t
4,
- a. Procedures - The NRC incpector reviewed Brown & Foot Inc.
(BtR) CA manual. Section 16. Revi si on 16; Section 19 i Ccvi::is on A fin n nr+ ) ; r. .M op n an d i :- 1.0 Davisica ! ;ini part). ASME OA procedures CP-OAP-2.1. Revision 12 11.1, Revi sion 8: 11.1-28, Revi si on 34: and 19.1, Revi sion 2 (in pert) were also reviewed,
- b. Observation of work activity - The NRC inspector interviewed 3 craftsmen who were installing an anchor nupport for containment spray piping in the Safeguards building. The welding of the support and torquing of baseplate anchor bolts were witnessed. Work was accomplished in accordance with the work packages.
PAGE 20 l l The NRC inspector inspected a total of 24 pipe supports on the ! Safety I injection system piping. Of these, two were large bore spring hangere, one small bore snubber. one large bore snubbor, i two equipment snubbers, eleven small bore restraints, and seven large bore restraints. Several discrepancies were noted on the t following supports: H-SI-2-SB-020-1-2, 2, 5-2, 6-2, 8-2, 10-2, 11-2 and 12-2: H-SI-2-5B-019-1-2, 3-2, 4-2, and 5-2: SI-2-039-401-S22R, SI-2-039-404-S22R SI-2--309-406-S20R; SI-2-044-401-S22R; SI-2-070-404-S22R; SI c a.u g . p2-070-405-S22K; and . SI-2-070-406-S22R. However. OC ha5fNot i,sperformed their ^' y V u VN V V sy' inspection.a Nthere supports,,jand hen & i,,anstal l at i ona;s r ar, not be r considerod Vt v' ' completo,so thr-re are no',Jnl , findings at this time. lhe di screpancies f ound were generally insufficient clearance or a departura 4-: 4 th- d::ign d r awi r.g . The basi c Jesign or rna support systems examined appeared to be adequate. The NRC inspector reviewed seven saf ety related -pipe nupport documentat i on pacLaqos including records of mat er i al s, weldinu. OC inspection, nonconformance reports, and rewort and reinspection as follows: RH-2-5B-024-001-2. CT-2-028-402-C52R. i l CS-2-RB-072-702-1. CC-2-041-713-A63R. MS-2-150-448-C52h. , H-CS-2-RB-021-7120-1, and H-SI-2-RB-0580-701-2. s V [Q l(, et' b '/ Ei S " f 'q The items of nonconformance,were generally f or di mensi ons Cb+ t u-'4 l slightly out of t ol er anc e. (i . e. Hilti bolt manimum spacing). i d All NCR's appeared to be dispositioned properly. ( t
-- - - - - - . _ . . - . - . , , - - , < - , - - - . , . - - - - - . - - . . . - . . , - - , ,-n- - - - - - - . ~ . . . , . . <g-- r - - -
i PAGE 21 t
\
No violations or deviations were identified.
- 11. Electrical Inspection
- 12. Exit Interview An exit intervi ew was conducted January . 1986, wi t , the applicant representatives identifi ed in paragraph 1 of Appendix E of this report. During th2s interview, the NRC inspectors stimmar i .7 nd t. h e t,c op r- and findinan of t hrt inspection. The appl i e ant zicinowl 1 god tho 4 1 n d i n ci .r .
2
. E #- :
Pb j .-- - P;,st:- FINAL DAAFT Ft6.25 r TRANSMITTED TO OPS l l RMHil G i CONSTRUCilDNIhSPECTIONREPORT i I U. S. DUCLEAR RESULATORY COMMISSION l R(610NIV
- NRCInspetticeRe:ert 50 445/85-18 Feraitt CFFR !!6
!0446/65!! CF;5-::'
Sette*: 50445 Category A7 50446 Applicants fesas Utilities Electric Compani (TVEC)
$6yeay To er 400herthOliveStreet Leck Pei 81 !
Callas,teias 75201 i Fa:1! sty SHe! C ea9the Feal Steat flettrit $ tat 3Ci (CE${$f ihitt 1 % 2 i
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fr.s;e:terst
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!rstetter (14 1), Construction. Regicn IV CF5ESGrcup trita;r e s 1, ?, 3. 4, 5, 6. 6, 9, 12)
I e a C. i. J: bas:5. 5H1. ConstNet:c . Felica. I '.' Cats SouthTesasFreject , 4 (ca'agrath 71 t I i F. W. Michaud, Reatter instetter. E(6!CN IV Cate f (taragraph 10) , 1 L
t HEE 9 ' . 1 D. L. telley, SRRI, Operations, Region IV, Date CFSES Group (paragraphs !!) f c a t e lt a'.t t (~ts J. '. 'tCletter Reite=ti by:
- 1. f arnes, Group Leager. Region IV CPSES Group Date A::reved:
- 1. F. Westersan, Chief, Frpen IV CFSES Grcup Date
- n
. . \
... PAGE 3
, \
i In_s2ec t i on Summary, i. s d t Ln_5pf g_t;i_on,, c,_qn d u c t ed :_ December 1-3 11_ 1985 (Report 50-4 45 / E15- 12), Ar n%1n opp 4 .tf nt; Fu r i t l ii.+ . unannuiir.i: E d t ospe.4c ti ons of Unit I which ineluded applicant actiens on construction def i c i enc i es, applicant actions on previous NRC i nsportion findings. IE Noticos, Generic ' Lett ers, and NRC Technical Revi ew Team (TRT) coatings. The inspection a involved 59 Inspector-hours onw t ra by two NRC inspectors and one consultant.
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() V' O [( f { fIl
- I,1 l tj f e ' j ,) f 4 ey }
p... < h re t
.hs}.16 *t' k 18 'l i C h n '.k' C i P (12 l H ' r ** ffd e P f ' l'_<1 3, I,'7?,* . j Ron_nc t 50- 4 4 6.' 9 5- I t~. )
Arras I n T 6.fc_t.q d : f< nut tne. a t r.0'n( e.' .
- o id e in r.n n ou n c e d inspection'. ni' l
Unit 2 which inc1oded plont t inn % tui -tie l i r a r.t actione on c onst ri.ac 4 ton .h 1 i - 1 : . .- ~ : . o.' 'i... .n i , to.- i r u.i - s i i r pe v ! , < .i . NPC findltsy1* j f I l ~* t i i .
- a { e i. I t ai'- * *
; ; 31 J i s t ese~ i ( si n d 1 M5 pet i 1 (iii F*
prot "(.ti v r> r nat i no : t .t > '. i nq .~e- ' t ! st i oni und a i r - t on d a t a r.u i o q ( H'hR .' : p i p t- t-tip p o r t s ,u d pl* 4r) col .ib l c t r o v s' equi > mon t . The insporttnn involved 168 i nspor i or -- h ai n on s 1 t .? by 4 otir NNC I ns pec t or i, and ont+ cnnaultant. b
. . \.
Par.g c Resultn Within the seven areas inspected, no vi olati ons or deviations were identified. DF. TA l j _S . 1. f- er son sJon t aglig! T.: ,f r j)t t. i '. t.1 e 5 Gener at i. reg _ _qsap.in f , j,gtf,r t i - - nf* l II l. k 6
- t. t 'f=iy\ f l Il %I,8 \ h9 g
. i r i: 1 i , .! . . . t no or P. Holatnad. Pia n o.wr . Quality Conteel (DCi F. M cid d t' n . TNF Mechanical Fncinenr J. Mccrritt. Mtittant Froject Grenor e] t1c o n o c-D. Polm.r. I .t'u - t r y Op er -# 1 no E :.or i er:. r- .
O r r a i nr.1 o i ~ i,..,n-
. i t ie F. ' . ir- ;) F o.3: n . re t . oc ' 1 ti. D .', c _. g . . . .
4 t r T h r. Nf- C in p.n_toru also i nt er vi oveed of he.r oppi i c . . n t. enisIc.f. % during than intpettion period.
"AGE 5
(
- i k
- 2. Apolieant Action on Provicus NRC Insnection Fif3gLn_qs. t LAi t s 1 and 2 a.
(Open) Unre=,olved i t isme (44S/0514- U- n? and O '. : 446<nStt-il 91 and 02: arut 4 6 '. . F.'s t 1; *4. Mt./P51'. 01t : h oc inio r c+ (.h a r c. ! addrer.s conttruction drficiency file content.. i ncomplet e ()A record i i 1 es. def a r 1 c nr y report corrocti ve a cti on, and TUG.CO c ommi t mrsnt ta revi ew thi o mat t er . Thri NRC inspector conti nued t he pr evi ous i nupect i on t)y fol1owing up on each of t b > e.o i tems, dur a no t h i < i nspnc t f or perand. TUGCO is 5,tt11 wor l i no nn t hen r. . t eit, and a n t i c t ri s.t ec compl et i ng tha revi+-o
.. i t s t r i, , n- . . i, , i.,
,,i,.- .... tE.. r t ir - e e i* s . ! t .-in !>
, 1
- b. (Op* n ) Unresol.ed I t . , tic 1 4 4 5 < O "..! 6 - ' E 0 9 +nd n?. 4.i o . 951 ' -I I-< C and 0-' i : IE t<ulletin +i1es for 79-14 anc 7 '/ ".'3 . The tai ~
irspector: continued t t.e prn.ious t i e..pec t i c.n hv fellnwina up or. -a r. h ni t h n e e 2 t +- cmv . Il P'C O 1= i4rI)no on i top r cr. t n o tho If f.* I i ,
- 1 + c.t i c. .). ,,.d 1. :-) A ic. ,
e...-. i i
!:e. ?
~I f ii!I c s .n : r il a ite ! v the
- 3 er . .. s i d j 1.. ~ e Die t c . .t (" ), t i-s.si t ) t . Ties r. or r eu i .<- .: t 1 ir i oli ; l .1 < ih ! o IF l'.:1 l e t i ri'.
requirinq hardoare esclua+3On. repair. r ep l acommit e n ,1 v ot ificntion wi1i b6 t* slowed to .ts>>re, i h At tbo -itot si; +nt 5 const rur: t 3 on oroana:4.t2on tracis t l i n e.e actionr *o complettari. i l l
e o Pone n l No violations or devi ations were identifi ed. 3. Ap.p l i c an t Action on_10 CFR_56.55_(e) Dofieieneina a c i m: o d ' Const rtict t uo De+ r a s nry h-- 2 -01 r!] s c i - - u'_, *a . 2 sw3e ch c e.<r cabinet terminations. by the vender. The NF C a nnpe.-t or i nt,pec t ed thi s i t em to det<>rmine why t he termi nat i er were rrplaced when TUGCO lotter TY>-4598 datori Oct ober 16, 19'35. t,t a t r d that the deficiency was not repor t abl e. The inspector r += v i ewc d tha TUGCO oval uat i nri ;.ind + oun r1 t hat t h s r. i t r ro war. not i I fBOII' E% % f} f*f [' I I } I,8 k ) 5' f ( g71' f, f (lr r}g jf W r4l . ( DQk pb\# f {
- f. %g hf fe( f i (, ,i. q ,. r a , , , ,. t .. ' '.i . it wv mril s ret ' .* . t . 3 r r i
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1
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Irii..rn .*;or.
- h. ]_J. ; ry - t ' ((j 4 Ti. it ,a 4 + 3 c.n t ! ;. t i r ,p ,r c- . r. t ! . i t. . . ia eo i
...ir. .tir piir p o st.. a n r1 r -rw t e oc. , 1r in i nc- ii- n. e.d
.y y 1 Antc wi i t. i - ;>wt i te e opor t i nr. ti.thr- f JM' hiit *ii.- . .t+-
,, r i , oi .
-m . o rt to t. a l e .c. t 3 on nn appl a e abl s. t ec hri) r .,1 ic'-cow. 14 sq .p l . .it - ) e . 4 o p r en.,es i t s 1 c. ,1,r technical p r ot.1 nios . h.indi i ric 1t.++
ot I hee s- inai i t i $' Are i.ot I o ver e-d b y NF. C r +-qui at t ont : however, ihe tJ M i . i n; or . e t ed i.. Iinw t t. . t +% h r e i c .a 1 1a 5 a ir t an t hr. c.i
- 3 + + c t nnt a i s. ar e hr rid I ed.
1he (rillew:nn nutnrA 4 s 1M w r- r ( ' e e s A eweti t c.
n i DSOE 7 determine how TUGC0 determined applicabilityt make distribution, and took action on IEN 85-04, 85-22. 85-37, 85-34, 85-35 85-36. and 85-56. Thiti review of TUGCO fil es shows t hat their p*tabli<had synt am in unriino satic,fartort!,. ne t ru *in i e n 1 ir,u v.3 imrs ..riif r r o re d . No viol..tions or d ev i a t i on e, wera i dent i f i ed. . 5. 6pp1 i c a n t__6c t ion on Ganer3e i.ett m Th at NRC Ccneric L o t i e r -- re # 1 <. e. . - s:.n t tn the r i n ,-. lear trdus.tev bor i ne .ir .i-* ie>n p cro .ut.! .. ii? .in r. i ore r 1o *he imF. Ao-ann 4 ?, !t :' . .s ; i . .d 4 *i '- ut 1
*i ) e t r i fn*Ir,!, ,I- .i' '*
.i. : , < i . *
,oi t i i J.1.. . .i .
. + - ..: T i < ir. . Thc ta<i - : n pc-c +. c.r re. i o.:eit IF. f i l eu cruf rel r.c t ed Generic f.etterc R7-11 and 8~.-16 f ne << ninr i ii. t 3 i l r>.1 r r.< i w . TUCCO Itr uiir.3 ng rec ru ws vnct di s t r a hiit ec 1. h e t;e 1 t. t t o r .- to t ni . pe r ..t 3 i sto. qupport grcup for t het < r r . i m ci r. d cu t i . ir , . h*-.t.+ ca t h.> 4 i l c-r rrwealtd that the l ucy'r. t,,, <j.- -.p. n.. '
-1 c.- :..r
- c. . ,. 3c . i 4 e. .. ymi e p.w , p, 1 . t u- t i v . .a , : s. n f n. . y s .c 3 I r . t t. c. ,
ik. v i al .i t i on- er deviation- w e r r- i d >n t i f t ed.
- 6. Gen t>r .41 P1 ani Unpcn t ore. o4 Lini t 2
\ . PAtE o !
4 At various times during the inspection period, NRC inspectors > conducted inspections of the reactor, safoguards. and thre el ec t r i c al / cont rol building. The NRC incpector obcer ved ongoinq con =.t r uc ti on wnr i- nnel di ntu is cri varinun anbjorte 6-i r i h rn > .m iel
- r e y n. i co t I. wuri m i2 ,ttte-.
No s i ol i<t 1 non or devi a t i on": wr-r e 1 dent 1fied.
. 7 Fr nigS tj ve coatinrth Unit 1 iin d 2
- 3. i hr Nor i r. ' r,rr t or r e v i n W C- d f. h e c r eat I ng ct p t r i 4' ! r 41 ' n:c :e n ti er, '
..; ( s ., l 43 3+ r... -
. .i..... , te. t i,,c - * ,
t . , . . i: ,' ' i
..4; :. ., *e, , ; t .; i. th... ; i , .. . ' ,1 .
( . o h o i- in.i.:h r .= r e .10ww1 hs the NC f orhni e n t Revi ew feato (TWii .. 9 0 % !' F ci monnel t r ni ni oq / p.M i f a cat i on. c a r. c r 4 + c < c. t . - 5 c 4 i .e. i ec t i on <nd inepret1on, tr st i og. dor t oi:ent a
- r. ,
r ap .i r .s r well c n 4er + il :n poi i 4 .'+3c:. P ? '. - ( . -
.m ..
i- r. r . . , cP- r P t M . . t>..' i 1 '
?".ti. 1 1 . '.~. . 1. 4 A L i t' 'e :ne .; i t.
T he- i nspec t or ob s ec' +d wt r i in p r r.y ree- a n ci c r. t.p l -i (+ i 6.r.i ! ce follows pr es r e ir i <-e e n oin '1. ..t < am genor M or i ron.c. ain d 09 01evat t.r nha+t c or.n, 'O. . r onen 21. fabrica.tann chnn
'i n ! paint ttorsgo bu i l d i ni.j . Mn r.t nf t h. . wi .e $ nh e r . ra t vc c.
. t r i a t: r- pr opar at i on. hnwrver. ..i iinal afirilici*ti n t t t ..
PAGP 9 coating of the steel liner wan observed in room 21. The f.urface preparation and application of coating were accomplished in accordance with good commercial practicor and +hr craftr, and 4in!d nngi rierw e eer o I nnwl edgenh 1.- i~.:-) d i n t p ec t r;r .at p .
. . . n f. n d ve . e t i f) t i erj b-ttir. tr4 *t when hal d poi n t s. wrir c4 imposed. Paint e,torago a r t.>a t. are temperature contrn)Ied and matorial shelf 1 i f c- wa'a elosoly '
nioni t or ed and c on+ rol 1 od.
- c. R$-c ord e Reviow --
The p r ot ec t 1 vr- c oat i na ci paper f1ow group T F r- . T h e P t t,r u r. .I thi.. FFG is to oste.hlish s mr?thod r ir.j i u .r,0. ; 4 i.eu i... s. t i i n o , t . i 6 i ii. i r a ;i ng. ,:. r. .-1
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- y. + o. i 1.o .>:r.4ir. t..i. 01 ccat1im:
actisitine. Tiu . iS C i n i p..t t iir r s . l e 6.ed protc".lsvt. c o a t i ria s t r (4 vel or e t c. dr t erm si. 2+ t i m- r r- c a' d " vorn i. . j a qi i e. t r; . cn np1 et c. 1 or,2t.] - a .
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4
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. ii.iq.1..t -il und iis i .r n. 96 i ' ., e l t-r - t ri t t . r. .6 2inci i
esstevi to d o t t-r ai t r i . li the trat Iinq s yst em wa9 ar . tir a r * . The. c cvtipu t er pr1eitmut i5 used ior t h r- teaciing 2. e t o i.) . I 1 E t i n t) ihe travoler riumher , pactage numb &r, untt. er na n..d e / r riom . riuinhe t . .o, o' ~ t .n d iiit) rnatino drf1e2er.r.v r r por i n and iho i r .. '. i . o r ita+un. i i _ __-w- r --
. l PAGE 10 l
Records reviewed were l egible, uant l y retri evable and complete in accordance with si te coatingt, procedures. ' l l Review of the Unit 2 coating recordu trach ng tyetem, by the NRC in'.pector. i ndi cat $d that thr .vtiem, at i tie n8e inu
< rry r e.-l 1.i b l i . .nd ..i o r a t r- t r aci 2 ng <
> 31 + ia . .
Ie s t r..c t t no system i t. U p d a t i= d on a dai1y b a s.,i v. . The NRC intspect or e4] to revi ews d in process t ravel ers in the
. fi+1d. One minor scalated di screpanc / was noted on trav++1er 2- 0. , h owcaver , t he rij gnat ure (which was in the wrong t 113 !\ war, pr.wptty e nr e on t a= d when it we '. r m iqht t r. t h v-4... !i, .i .,i, .i '. . . . . . . , i, .. ) o , - e ..1mu. .
.1 or r '
T' - f 1 : owi riq war i p a r i a oa", wht ch c nnt a s nm: nore +t.an c.r...
'1,
- t. . -
6.o r ;- r r . v. i o w. d : 2-21 -f . 2 .~ 1 - 0 2-: 1 -l . ? - ? ] -16
- p t - r , 7 - 7 ,1 r , :'- 21 -,u , 2-pt-G.
.ind 7 ;j.q .
i,
.i.:n,i+., e m . , r ,m .1 r r .. . i r . . e u. e- < . * , n .:,
i, .r i . . ,1 .
.zi.a.... w...
. .i e h r. . +r.tr.. ! .4r..: q,ay, ,-..t a r,
.. c r.r- d e n c e wi t li .1 1 * - proced rc- CP--l W 1 1.1. i,c>' 1on O Ihr-
^
. .. .a e t e. .- n N . t i . .i i + 1 :M .4ridar d s In>titute (oN51> F. , .S io no 1 ( ,n g .3 epplitablo
- i nee t he approv.2d dec 1 e tN 4 i c.a t i r..n cA lit ot rac t t ve r ca t I nin.: t inw e'v er . the me j cr a t y of the coatino f i ra l d .n.gi nor r t qi v41 t
- 1 c a t ion rercrda thet wrro re vi ewnd tiy the NRC insper t or s iid s .wt ed t hai i f.
- y h a rl bv r n qua1 *: p ri cr
t o I pn.w : certified to ANSI 45.2.6 before tho declas91fication of ; protective coatings occurt 9d. Regardlen, a beginning 1 enating finid engiierr m u t.t sti11 meet the fol1owano ! qiu l . c sentinn rrquir++.-nie: - Sh.=11 have a mi n i niuin at one and one-half (1 1/2) yn a r s. ex ture i ont e- an the i n 9 p t>c t i o n and documentat1on of t l
pr otect i ve eoatings warl at a nut l rar f .= r 1 1 i t y Shall bit phvni t i l l e c .
H Clair
- c.i -i. i r.r.in i n*:1 ri sc i itn on ali I
. r i , t T i .a ; ; i e .. ..h, , s. rp, i. ..:ct<i,. *nsi 4 c,i 1 1!
- i. ' + 4 . w r. ! .t 3 ni. i -
.ii. , , ., . . .n p..
[ .ine t,eh' .* - i. ii, i .i t 1is pi..,,c;i...r- i
.t I i .q[s f60 i f f '
- l(*24- i,i rh- i. *ine- It (t .rit r, t e .
The- f1PC i rmp or. t. " til ii niit t n, 1em cr at t ' r i A 1 i t en .'i qual 1 i i t'.;t 2 onn bt r an .o t h rs TFO r o n e w etl ? hein a n ti thes a t o t est '
t liai ihe cratt qi e.41 t t t <: a t 3 ;i u." a ri o . p i a ,
\
PAGF 12 !
t i
l d. Calibration. The NRC nspector revi ewed t wn pr oredue er..
IEl-15. "Cal i brat i on cif DFT Gaugos." Rovinson b. (la t ed March 11 1 1982 and I E I <.S . "Calibrat. ion oi tedhesien re s i. .. e, . "
F r-vi n t or t ', ri g t t d 6Jr>lic i e r ri . '" 1 9F '. Th e ,1.u ii n r- wiut
.idhl 1> I-' t ag =! 4 {, lit .i t .I . ,j d e , 4 t y , i * ., e , y' ) t
}',,,
The rontin.) prt>reduris i or ina n1 itivoi sille ca on '
t* e ti d i n a r. 6or t t i, .
Fler.inet w f.dhe* ion 7091 ar i* ew..e e n on-tc-t va t i ve ttu.r. -
r mt'i r ed .
l Tio4 imC i ns pi>c i . ir s. , owed c i l i tst s t i on c r>c i >r d t. of t w. .
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. i N. Traceability -
This catboory deal s wi t h nonc onf ormarice I t
reportc (NCR'n) wht ch provi de "oro an a v d a tiliot.: t a nris !
for discrepant coating meterials with i nadaquate !
, terhniral ju-tif$ catirm for t h.4 r+i e nir i t i. .
t ihn artion roquir"<1 for i t. 2 eatenory hn tv -ri i
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c r orr.pl =: t ed b y t be- 1 i r ern a r'e /iitti wM Lutwist*.c1 f or rew&Ow ,
t o t h.- Di r ect or .34 th er l oar Rt* u. t or Roonlation in TitGCO
, I ei t.e-r t T r X - 4 61 '*. ) drit ed November- 1G. 198":3. '
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I and approved by technically qual i f i r'd individuals to astmre const st e ncy anti clerity.
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, PAGE 15
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T Section 17.0 Appent11 $
17A. "List of Ouality Ac*urbd i t e m s. . " ;
Staten that t he et>nt Ai nitient vont 3 ) at 1 on '3yst Dru (bla ch c on t a i nas ei ght siit'snt **m' / component s ) is spirimat Cat woory 11 enti nonsafetv t ral at ott +n i h the c' r ept i on cd tio- e om :) ni ent a
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9efofv r e l .s t r.ij .nt! w 1 e c.n r- C.st ogor ./ 1.
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'?HV 556 3 14759-1B 12141 i
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l PAGE 17 '
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Recei vi no check-li st, drawings, OA check-lint, and*a ,
documentation package with: drawings, order spectiitation sheet, material traceability list, body mill test report (MTR), di st MTR. st c>m MTR. d i s t- pin MTR, gasket ret ai ne r ti t- .,.. Ii c e t .u on, ' . r.1 i - r..r'i+. +
. i n et.il I. erd r r'por t ( T li ) . manu f ar t or er 's ni..t er i ai I l< .
certi4)cate of c omp i 1 anc e.. 1 i qm d penetrant TR, wr>1 rl repair roport, body rr, h ogr apl.ir- TU. su l 1 + li t c i not s, air.mu r o ni-n i r <- por t , final TP. c i v ain i ng ia r t , cvcl e TR. c,c;ME ria t c. '
report au "mbly shop t r ,3 v e l e r .
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Records reviewed - The i n sp er-t or reviewed RIR package for f i f
penetration MITI-18 and found that the paclagr containr>d the!
a i
propor documentation.
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- n. Procedures - T h 5+ tlRC i nspec t or reviewed I<rown 6 fin ot Inc.
( N.F i DA manual , Section 16, Revision 16: uc t i on 19 .
F4- s i 51 r.n T. (1n part) : and App on t11 : j. . R r+ v i . i v r. -~ ( 1 r, -
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, PAGE 19 1
. i
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large bore restraints. Several di screpanci es were noted on the '
following supports: H-SI-2-SB-020-1-2, - 7. - 2 . 5-2. 6-2, 8-2, 10-2, 11-2. and 12--2 ; H-SI-2-58-O!9-1-2, 3-2, 4-2, and 5-2:
31 039 -401 -G2?R, SI-2-039-404-322R: S1-2--309-406-122R:
- . T . .. . . ; .:. 3 T. -
.. .. ; , i .; y,. .;
) ...i.r,
. c; , ,
Sl-: -07n to!, -G ~ ?R . .
Howtwor. ).N , i ne poct ton had not h sf on prer f ormed on c u p n c3r t. c . s b ) n t s- inotal1at2nn was not c on r i cier r.rj C 03 p l O f s'. 1 iWF 8- a r e.- 70 IJRP f 2 nrii rios at t h 1 c, time. The di ve rop m ;i on i 7.tnd were ut rierc.) I v i nmei f i ci ont c) ear ance ot- a d-t r+iire f r ism t he i t e r. : gri or awi ng. The basic de=1gn of iho ru; port s ti.= .- is- i. i noci 5.r >p o. o eri t o br> adequatr. .
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PAGE 20 11.
Observation of Electrical Work Act i vi ti es During this reporting period the NRC inspector observed two' naf et y-related cabl e t er mi nat i on act i vi ti es. The f i r 1. i
' c . r. 2 n . F :
. .q. art: ci t ni t e . .' i ! m:i 11 . a l r .. i r ..
tarange cable ) in a iunt t s on bo:. in containmenti t he toc t inr; ww the t er mi na t i on nf two Ire)n B foreen reble) i n a mntcr c on t.r cil ccntor (MCC) in t he grr-er, mnI,hqear ronm.
T r. pr oc e<= n work nhner nt i on we perintmod to /ertiv that: t he-1 Stent iir awi n ac anr1 t er ma na+ i nn r: a r d t are brinn used: the c.?biss
.r. . ' c i m t irca , i ,. m ;, , , ia f. .. . ? a r L. i' -d 5on ;- t: ,i i ii . ' F e-e i .
t , e ,. ,.t ; c. J p i ii.l i j .
r.1 . ii
!' p e:-r r /cd : bond 3 t i:. r ' c! i o '- 2- m0 2 n tai ned: c a b i ,_ Pntry point 11
.' 1. . .o n - ;i i. , cn 1: - . . ' t-- .- 3:. gnod i epair ano y op< r i v ri.1ibrated: .enor<tioi: + 1 c. h t n e s u '
orrrtt:
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. Of s t.* r +4qailr Pei iArM2OAI j i en d . i t i ,- ri t i c. . r ri l (! no t . d The sitributoq npetific to t h <- t orm) not i on t yp. in .an..: t i r ,o *O ttnse r. . t i r i hi ii .: - c noin.ori i c. lio t r, w. r < - iri. g.'. 1 .q!. I ah1- n i ' n.l i
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. . 3 PAGE 21 i
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.i and termination points were; cable no. EG2199710, termination
- t point junction box (JB) 2C245 in containment and cabl e non.
EG213168, AG713254 t ermi nat i on point. I rp- r r t o i r, - i n ato q o,,. ,oi6 .t.,,,
,, e n , ,, ,, . t he - P' i t : p t .. - or mr i f t .>.1 t h a t. alI r'o r t i n o n t r oqui rement : had been met.
'Jo vi n! at i ons nr d*>vietions wet .c dontifiad.
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