ML20238A011
| ML20238A011 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 03/14/1986 |
| From: | Phillips H NRC |
| To: | NRC |
| Shared Package | |
| ML20237F760 | List:
|
| References | |
| NUDOCS 8708200342 | |
| Download: ML20238A011 (51) | |
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U 5. NUCLEAR Rt6ULAftRY COMMISSION - ) [Ws ' ,IN W t 3 ItAM M - '
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T.F.Ifesteraan, Chief,RegicaIVCPIESGren; ble hiitti[H.IVitE! Nov e k gt,, inspecticatenducted: anage 1.M 1985 f tPnert 50 44545-w) fttil.hlit;itit Routhn, unannounced las;rctions of Unit I which:1ncluded r l rH:::';h ' ' r : A/[pilant acticas en constructico deficiencies t previous 100 inspectien IG- is findings; 9 H ** t $ ^ Y. 3j'e;) A sears'eAl h' an+
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Cate i 4 Appr0Yell T. F. Vestersan, thief, Reglen IV CPIES Group Date i l hiittilM.httEY No v"> IL Inspecticatenducted: ausse I-M 1985 I(Reecet Se 445/65 sr>
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NMcv 13 # Istbeetlen tendotted: Os6eber t-31.1995(Reeert 50 446/05 3 1 kill.lDilttlife Routtee, announced and unannounced leapections of Unit 2 ' {
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1 l DETAILE 1 i,
- 1. PEMBONS CONTACTED
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'T'UGCD PEREONNEL J. Merritt, Assistant Project, General Manager P. Halstead, Manager Quality . Control (GC) i C. Welch, QC Supervisor l 4
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- 2.
- Plent Teurs M 1 At various times during the inspection period NRC inspectors ML conducted general tours of the reacter building, safeguards building, and the electrical and control building. During the l tours, the NRC inspector ebserved ongoing construction work, and discussed various subjects with personnel engaged in werk activities. l No violations or deviations were identified.
- 3. .,Aetien en 10 CFR Part 50.55(e) DM i el enci en Identifiref bv the Aen11eant M I^ -
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PAGE 1 e l i DRAFT NO. 2 MXHs6:T , Pd h. IR APPEED11 C h !- CONSTRUtil0N INSPECTION REPORT l
!!.S.NUCLEARRE6ULATORYCOMMIS$10N REGION IV l
[ $ NRCInspectionReport 50-445/8516 Perait CPPR 126 50-446/B5-13 CPPR-127 Docket: 50-445 Cate0ery: A2 M 446 g Applicant: Tesas Utilities Electric Cospany ITUEC) . Skymay Toser - ( 400 herth Olive Street ' Lock Box 01 tallas, Texas 75201 f i 1 ' Facility Nase: Conanthe Peak Steae Electric Station (CPSES), Unitel & 2 svj Inspection Att Glen Rose, Texas j Inspection Conducted: Noveater 1-30,1985 J Inspetters: H. S. Phillips, Senior P.elident Reactor Date s Inspector (SRRI), Construction, Region IV ] CPSES Group ; (paragraphs 1. 2, 3, 4. 5, 6, and B) l i D. L. Kelley, SRR1, Operations, Region IV late CPSES Grcup (paragraph 7) 1 3 Consultants E666-J. H. McCloskey ; Parameter T H. Young
, i
( g
/,.
^\ I
~\i g
j
\
s
/,7 PAGE 2 Revie'<td ty: ,
I. !arnes, Group Leader, Region IV CPSES Group Date .s i 1 5 hproved: 1 L
- 1. F. bestersan, Chief, Region IV CPSEli Group , y Cate 1
( 4 I i i a i O l 1 3 s
\
q l N l 1 I I I h l l.
- t i
I I l
1
*e 6 I
- ... . PAGE 3 Q.
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t : T .' A
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/
.;. Insoection Summorv g x
, J,fi c'. ng. r% t;.
,f
~
hlnsoectfonConducted: P?py_ ember 1-30. 1985;,183gprt 50-445/85-16)
+ 3 v f e ..
{ 75 reaslInsp_rg_tedg Routine, unannounced inspections of Unit 1 which m if .t. g,in'cluded applicant actions on construction defici enci es, opplicant li actions on previous NRC inspection findings, IE Bulletins, OA records, and el etitri cal p ene t r at i en t, . The inspection involved inspector-hours onsite bv one t!RC inspector and two consultants. 1 Resultsg Within the seven arear., inspected, no violations or devi ations were identified. l Jns;petigrL Conoveted: Novemher 1-30u1985 (Recort 50-446/85-13) BrfJg_.I nsp_tq t ed y4/ Rout i ne, announcedandunannouncedinspection[ Unit "d which included plant tours, esplicant actions;on construction 7, , v' deficiencies, applicant actions # pre vious
/ NRC inspection findings, IE Bulletins, QA records, electrical penetrations, and review of electrical inspectionandpnstallationtestprocedures. The inspection involved 21o b M inspector-hours onsite by two NRC inspectors anr1 two consultants.
Resul ts Within the aix a 2as inspected, no viole.tions or deviations werit , i den t i f i ed .,
i PAGE 4 DETAILS
- 1. Persons Contacted Texas Utilities Generatina Comoany (TUGCO)
, .., K. Anger, Site Design Engineer
, R. Babb, TNE Engineer ar.d Site Fire Protection Leader
, H. Cheatheam, Technical Support Engineer S.df,.
- %- R. Cisneros, Special Project Group Coordinator P. Halstead, Manager, Quality Control J. Hicks, Licensing J. Marshall, Licensing
,J. Merritt, Assistant Project General Manager, Unit 2 D. Palmer, Industrial Operating Experience Coordinator C. Welch, QC Services Supervisor i
Contractor Personnel I W. Baker, Engineer, Brown & Root (BLR) D. Bal enther , Site DC Supervisor, Brand Industrial Services Inc. (BISCO) G. Fedor, Development Engineer, BISCO, Park Ridge, Illinois B. Kennedy, Site Project Manager, BISCO L. Smith, Engineer, BLR B. Wright, Engineer, B&R The NRC inspectors also interviewed other applicant employees during this inspection period. yW .< v... ...
.- .g , ,.
.c . aka.t.,,-
1 4 l PAGE 5
'Ec s8 , .
MGy ! ' '.n. i ADD 1(cant Action on Previous NRC Inspection Findinos j
) . .~
94 .- 6K ; _ a~. (Closed) Unresol ved Item (445/8119-U-02): Control of QA k,5 .b;' records for pipe supports. Procedures had not addressed or k s,*kQs
, -given instructions for retrieval of records for items that cbhad'been completed and then needed to be modified. On k
- a. October 29 and November 4, 1985, the NRC inspector reviewed j n' .y y
.jXyJ-v "; the applicable procedures that were implemented from 1982 until the present. These procedur es adequately address the retrieval of completed packages from the vault when modifications are required.
1 l I
- b. (Closed) Deviation (445/8408-D-03): Deviation f rom design i i
dr. f information for the installation of ,peismic Category I/ Seismic Category II structural steel for the bolted connections between the part designated W16x40 and the wall on platform OP-11 in the pressurizer compartment. This deviation concerned a platform that was upgraded to Category I without a corresponding change in details for bolted connections. On October 24-28, 1985, the NRC inspector followed up on this item to determine if corrective action was complete. TUGCO's response dated August 23, 1984, indicated that design change authori:ation (DCA) 19469, Revi si on 1, was issued to require a locking mechanism jon platf orm OP-11 d bolts)g and that the DCA does d addressygg locking devices. L . . 0% . e o . s _o a
t c.y PAGE 6 i
5,,,'.,*'*
. .< $ The response also incicated that a complete review of the
. 1,f(4. .R', ,
" hand-tight" instruction would be complete by October
- 1, 4
. ke . . . s . 1984.
The last DCA was issued in July 1985 to cover this
.' ~
V:l d?'-' issue. The NRC inspector took a sample of 17 DCAs and one
?# . ,
', , drawing that had been generated or revised to address the l l- .%'
,.d
~
" hand-tight" issue.
_, g.:- These all showed that locking devices
,- 4 7 ' '
t i are required where potential movement and backing off of nuts must be addressed. c.
.\
(Cl osed ) Vi ol at i on (445/84222 00): Unit i unauthorized removal of BISCO fire seal. The applicant initiated corrective action which included: (1) providing training to construction to reindoctrinate them on CPSES rules and policies, (2) performing a walkdown inspection of Unit 1, and (3) initiating programmatic controls for construction. The NRC inspector reviewed the following documentation of the ccerective actions: T-141, TUGCO CAR-038, IM No. 27535 n4*J dated August 0, 1984 and 4 the oractice of using discrete s construction packages wwe ::ch-.pacicarge contain the { necessary instruction and forms to complete the specified l work,
- d. (Closed)
Unresolved Item (445/8426-U-03): As-built i j notation on field sketch instrument number (FSI) drawings. There was a question on one "as-built" notation on FSI drawings. During November 6 and 7, 1985, the NRC inspector followed up on this item to determine if the applicant had l
PAGE 7
, .b l ,;'. :- )
i % completed the actions they agreec to complete. Sample l i
, copies of six of
> u, the drawings in question were requested at 4
^FJ the central document control center (DCC).
' w
- All had been
- l. stamped "for reference purposes only". Also, the drawings U
J ' s 'i-
. .. ? ' e.
at the central DCC and f our other distribution points are
*9 stamped "for office and engineering use only" when issued.
None of the drawings had "as-built" on them. This action 1
.' . . J '
if3:~.V r. - satisfies the NRC concerns. i o f ) / io.q.(/ j, $ Y ' u.Oe a. (Cl osed ) Unresolved Item %432-U-01 : TUGCO organization. On November 1, 1985, the NRC Inspector reviewed pc( this unresolved item. The assistant project general manager of TUGCO still reports tejtwo different vice presidents: s however, a third vice president is responsible for licensing, nuclear fuel, and quality assurance (QA). The Director of CA reports directly to this TUGCO Vice / President, Licensing, Nuclear Fuel and CA. This separation is acceptable f rom a cost and scheduling standpoint and e th reporting level i s suf fica entl y high to provide organizational freedom for organizations performing quality assuran::e f uncti ons. i This concern is reflected in the CPSES DA P1an, Section 1.1, Quali ty Assurance Division, which was revised October 18, 1985. D f. (Open) Unresol ved Item / i (445/8514-U-02t<446/0511-U-01): Procedures do not address 10 CFR Part 50.55(e) file content or provide a method f or completion /signof' f Le corrected s kM$2 *: .,
-7 .w___.2___________. __ _ _ - - - . - - - - - - - - - - -' -' - - - -- "** " '
l 1
' i
{ i PAGE B I 1- l i ..... d construction deficiencies. This item was considered by TUGCO managemont as resolving present procedure of system weaknessem-- ~ l \ 4, . . . The NRC inspector reviewed TUGCO Procedure NEO CS-1
'(,
bj
.M."/
' +<** . : ". "
enti tl ed, " Eval uati on of and Reporting of Items / Events Under J'
'n, g, , ,
10 CFR Part 21 and 10 CFR Part 50.55(e)." The review l
%j' ,'g, fj. li. . .
reveal d that the f ollowing procedures we'r i' inconsistent with ocedure NEO CS-2: CP-OP-16.1, Revision 6, dated (/
. January 16, 1985; TNE-AD-5, Revision 3, dated June 21, 1984; DOP-DA-12, Revision 2, dated September 9, 1985; and CP-OP-15.6, Revision 3, dated January 16, 1985. The inconsistencies include conflicting responsibilities, method of evaluation, deportability criteria, notification policy; and reporting instructions.
&l& .d' TUGCO has committed ypt Ore fil e tracking t-^g-du-aMs
/
12 ' .=
/
J d _ and M 'procedur)a inconsistencies cr: dbring ;..v v J 4 f ha+ $11 mttient M t hi s ,iiat-ter era i l'-ded t,b =;;,mp .s J by March 1, I 1986. l l l l J
# Y" / g c Pe n) '* Ul" '
. ' (Jy*GCOTU *~ 4RC has w A_ indicatec 4 4.s+"eW5' that =I a-+thru;;"
- g. .A 341== rim n muiW V
--~...-. N Vactions are being taken to identify all '
records necessary to close out open files. This action is to be completed by March 1, 1986.
, . D ha w a
s g j{ PAGE 9
,-- h. (Open) Unresolved Item (445/9422-U-04): Material certification for electrical penetration seals. The NRC inspector questioned M** thep*ertifli,
% 2 cation pf of the chemical and '
/
physical testing. H^TUGCO suh 4 BISCO certificate of Noo. / / M
. compliance (COC) numbeccsr 3057, 3081, 2093,and 3 BISCOfite D'o]/ V 1 receiving inspection checklist f or purchase orderg/7y, 2730 and 2773. There is a statement that the articles comply PC LI with all F 5 ,qe ,. d er- specification requirements >
(2323-MS-3BF)* fowever, no reference is made to the DOW Corning, Inc. chemical and physical testing of the subject material. This item remains open pending the receipt of a COC which certifies that this material meets such test requirements or DOW test results. During thi s inspecti on, the NRC inspector found other documentation and hardware issues which are discussed in i paragraph 6 of this report.
- 3. Aeolicent Action on 10 CFR Part 50.55(e) Deficiencies:
l The NRC inspectors evaluated corrective action taken on 1 reportable deficiencies by reviewing TUGCO deficiency reports ,[
*t ChOul d i 7.c 1 Rd c c T44&l-ysi GMM9-Ta f ur l p --i my l i C a t i CN O IM L
l corr ec T. i ve mu ii on i sa. u-r i . The inspector f ound no corrective action completion date for 74 was na M %4/ CP-84-29, "HVAC Fire Scenario. " Gorrective action f or deficiency L , ,AMAhk
I
'9-1 i PAGE 10 y_. . , .
CP-84-27, " Ventilation Exhaust Dampers," was o be completed for Unit 1 by September 1985 and for Unit 2 be ore startup testing. aa ((.9) w k sc as t i V o / However, Unit i deficiencies were not currencety corrected and it geraat.4< uM kV
, is not clear how, Unit 2 will be tracked 20- : rrJc t. -- .w U vo . v'
=f
.$.5. r. - ., Deficiencies CP-85-13 and CP-85-05, described in deficiency
- w. : ; .W
;) - ' '. reports and open items li st ,jalso give no corrective action dates.
- c. -
Several final 10 CFR Part 50.55(e) reports contained corrective action completion dates; however, work was neither completed by f' the reported date nor was a supplemental report made to the NRC to report on significant corrective action date changes. Deficiency report for CP-84-31, " Control Room Separation Wall, " stated that corrective action was scheduled for completion by 1
' December 15, 1984; however, it was not completed as of November
]1 30, 1985. Similarly, deficiency reports f or CP-85-11, I
" Instrument Fitting Locations," and CP-85-12, " Auxiliary l Feedwater Pressure Control,"Vstated that corrective action was
\
scheduled to be completed for Unit 1 by May 1985. The open items
., list indicated they were not completed on November 30, 1985.
\_ - r TUGCO management has assembled a task force consisting of four to five engineers or specialists to evaluate and take action on the matters described above. This item is unresolved (445/8516-U-01, 446/8513-U-01).
No viol ati ons or devi ati ons were identi fied.
.4
, A. ,
ac3T C 'n. e
a W' . PAGE 11 H .<-4. Acolicant Acti on on IE Bulletins (IEEd/ /
., . e i a.-
In response to discussions regarding the TUGCO program concerning IE Bulletins, culars, and Information Notices, Region IV was inf ormed that . TUGCO will perform a review of related procedures and records to determine the adequacy of procedures and the completeness of associated records. The W/ initiation
' L f- v of this offort &f, will a ff allow the task review of g10 CFR 50.55(e) program g presently in progress.
This item is uneesolved (445/8516-U-02p/ 446/8513-U-02).
/
- i. < ., Ws .
b. TUGCO Action on IEBs Two IEBs K79-14 and 79-28) were ' selected to review hardware evaluations or repair / replacements. TUGCO IDER Log Sheet, page 10, dated April 9j 1984, j W AL / was reviewed to determine the status of the IEBI. I IEB^ 79-14 was evaluated by TUGC0 in 1983 and was )* 1 1 statused as closed. The NRC inspector indicated that the closure of IEB 79-14 was premature since Stone & Webster is currentl y anal y::i ng Uni t i sei smi c analysis versus as-buil t drawings, which directly relates to this IEB. Unit 2 as-built work has also not been completed. TUGCO stated that the IEB 79-14 file will be reopened and a supplemental l report will be submitted upon completion of the ongoing project engineering work, d e
l 4.j f>.9
.,3 , PAGE 12
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The above item (IEB,79-14) status is considered an open item f.* 4: ' . (445/8516-0-03, 446/8513-0-03). l,1 :" j a-
\
N a., c 6 / Y@. f IEB 79-28 identified deficiencies with certain manuf actured I g ., . f '{ #4. . i lots of NAMCO EA 180 limit switches. The gasket material of i,, . j Yn the f aulty lots, when exposed to temperatures above 175 o
,.I degrees F, vaporized and emitted a yellow-brown crystal like
-f'i e resin that can cause these switches to fail.
_ R{ r The NRC inspector
. f ound the TUGCO documentation complete in this case for the specified corrective action of replacing these switches with switches manufactured in acceptable lots.
The NRC inspector verified the replacement of 14 switches and found the corrective action to be complete and correct, except 2 of the 14 switches could not be traced using the existing travelers. That is, the NAMCO limit switches on i residual heat removal valves 1-HCV-606 and 1-FCV-618 were ' incorrectly ident:fied. i Travelers EE 82-1415-5801 and EE B3-0 73-5801 identified the replacement switches as EA 180-32302 and EA 170-31302, while the switches actually installed in the field were identified as EA 180-31.302 and EA 180-31302, respectively. TUGCO is evaluating t.his inconsistency to determine if 'there is other documentation to account for this. Thi s i tem is unresolved (445/8516-U-04F 446/8513-U-04). h'kw. . m . O '
~ '
,4 PAGE 13 h-
. , . l
. ., 'QA' Records Retenti on l
The NRC inspectors f ound that construction deficiency and IEB files were not stored in the QA records vaults. Because such I.- Y . abbr.dshavenotbeendepositedinacentral ig location, it is very 7N9 ;, difficult to retrieve these records. TUGCO is assessing this
;re
- v ,T e -
/ ,
. record file issue.
$N This item is open pending the completion of their r,eview (445/B516-0-05,.8513-0-05).
i
- 6. Electrical Penetrations 1
p/ l 5 o - L+- In NRC Inspection Report No.A 84-22 dated October 11, 1984, the v' certification of BISCO electrical penetration seals (fire i j barriers) was questioned with respect to the testing of the l seals. During the f ollowup of this item (discussed in a previous paragraph), the NRC inspector identified related but different findings. h i
. ,,; iL' 4 \
The NRC inspector reviewed the records to determine 4 e(gNt l BISCO seal /'lwere- Oo &i- odcenr
$ amn'~ty*
tested S r= wi+hh+--+
$ Csd M er % S M & .V
- qui : _;,;;.
The eight penetrations inspected are; AB-790-174-1022A, e d EC-854-150A-1018A and-101GBP EC"B54-151 A-2003A and y2004A, 6-e / i EC-854-151B-2025A and-2026AP and TB-803-010A-100BA. g _ w . 4&d,m,.n. . , . .... *c.s%et ~
i h j,.; PAGE 14 ft;e 'b ;
,_,3 /
The following documents contain cER.::ibe conflicting h NA C SM information that .w.s we r ==J v 4 h - ggg! ,
) ..>s , ] .E b BISCO letter to Ta,<es Ui. ; . tt1nrg dated November 13, 1984,
. answered the NRC certification inquiry and stated that the '
subject fire barrier seal (test Mo{ PCA-76 ANI No. S-26, 24"x42", floor / wall, material 6548, M 9* depth, LAD or SLD , tray, all cables, 40% loaded) met all TUGCO CC W A *$ 'No. Contract l 3 i
/ \
CP-0707, Gibbs & Hi11 [ edification No. 2323-MS-38F, ASTM {
/ / /
E-119,and IEEE 634, thequi.rement io - \ l American
//
Nuclear Insurers (ANI) letter to BISCO dated August I 20,K'985, withdrew its acceptance of BISCO SF-20 (1977) .v Silicone or Dow Corning 3-6548 RTV Silicone foam without a 4 ;L w.J Fh.= ,d+ p , j damming board left in place. The NRC inspectors found that this withdrawal was based on BISCO's not having complete documentation of the test results and the recent failure of a BISCO sample tested at an independent laboratory employed l by the ANI. reason given for " -"=4s h w LtM hie rec s was
.;J& t hat they were g. ...m7m up lost in a 1976 fire o the %, mov e i
o other facilities after t.e fire. f N ANI letter dated August 20, 1985, to Ten.. 0 6 i l i n e s--/ A=m sting C=.p ,y fTUGCO{ /nformed them of the rescinded i acceptance and the test failure that occurred 2 hours and 35 minutes into the independent test performed in accordance with ASTM E-119. Further, it stated that this fire barrier _:______-____1-s__--:-----_.---- -------- #
I
# r- PAGE 15 o
i 4
.f "g
.g may not be adequate where there is a strict requirement tor
/
a 3- hour rated barrier.
/ i Comanche Peak Final Safety Analysis Report (FSARhpage I
f^len, LdSS 9.5-223 requires th penetrati se sted ! 9,6-ynk,b.t.c
,a "... m s g) %._
% , ,. g
, .j,,gg.
g,,,.,.4.,..at g :;,s, , ,u.,.,.it--on g ,,seal
,p gsp'3g n =4 .f w, l a
J corcance With ASTM E-119 and IEEE 634.g ,.-w-_7.1 L7g / (:L) /
- z. n . .
a= N d " '"-+ . requir:: t!..L qabling for redundant safety skedJ / _]- divisichbe be separated by walls having 3-hour fire rated f 4
* $sdM.[ <~.~.
barriers, 6 c:b!: pr :di ..w , w wu, ..cg ., . Li w aggi o,y'f Wpg'b.3.c. l l
?.'-17
- Ao 4-=e l '
;;- -pC . :..a requirats the 3-hour rating for barriers for cable trays that contain cold shutdown cabling.
TUGCO Design Deficiency Report (TDDR) No. FP-85-063 dated August 29, 1985, documented the deficiency. On the same report the deficiency was marked not reportable in the 10 I l CFR Part 21 and Part 50.55(e) reportable block. The corrective action was for BISCO to prove satisfactory testing of the failed seal and all other ANI accepted seals. Note: The evaluation of deportability is being reevaluated by TUGCO. BISCO letter dated September 16, 1985, states that approval had been rescinded because the hose stream test was eit er clwv 'n qor destroyed o. t % fiv 8 o r e- s dre pwi mm h 4 [lM,(le f g lost) It also stated that the ANI testing standards are much more stringent and stated that BISCO
.i
l i
"A . ,
%I PAGE 16 t '
'" - hs seals meet and surpass the test standards of ASTM E-119.
The letter further states that the ANI representative l l witnessed a test on 9-inch silicone foam using the same design configuration that failed in the ANI test. However, !
.the letter also states that the success of this BISCO test was based on applying a 3/8-inch proprietary coating on the face of the silicone foam. The letter stated that this retrofit corrective measure can be employed by those who wish to upgrade this particular seal design.
Note: It appears that the original seals that were tested had no coating. I
. TUGCO interoffice memorandum (Creamer to fennedy) dated October 16, 1985, discussed the rework of all seals a'ffected by ANI disapproval of S-26. '
\ l BISCO e.emorandum to TUGCO (Trent to Anger) dated October 24, sfylt V ;
1985, identifies yppenetrations to be reworked.
;.t g.
[:E'*WS& WDE ' Ty lef t,ers discussed above ' -t'--[de-f rf t h -- ; ,. !d }
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_c_
./
]
dp.6..u w; . ..m b : ; - ' = = . ' Iha BISCO letters dated November I 13, 1984, and September 16, 1985, 2 W: . . T i~v f _ ._ __..- M--V- the first one certifies to meeting ASTM E-119 and IEEE 634 test M requirements while the latter only mentions ASTM E-119. A4> also VITq= v states that BISCO recently retested the original design configuration and it passed l/however, in the same paragraph on O e*'thi g
t l 4 PAGE 17 7 - t
- c. ,pT . page 2 they state that they added a3/8(proprietarycoating y l fs-a.i M t m s h i d /
yJ which according to TU CD is not on their barriersg ir ple:2.
%N M' #\
m fffE l SM fHo p r thiss coating as if g'5h4.e BISCOddiscusses 4, V is a retrofit and/or a 74 u a , v' "th$i<
} design change. Seeue- me tA- - m = + 4 n c. . BISCO's claim that Wey j yt kst urL s $ ^H u eces.s rs k
& afpry t;;t:d ther. b.4, Io e. s *.sA n / i
-tert;d
-l-.e s4. *n e;M~theWi t:&:t1-bore.
+.
- S k S M s-.g f.i . V app e --- + m he l i ne rr.:i e rt Mi t e ANI letter to ----~Vdated August 20, 1985,
<J k l +L+;f % l* 4ed so s r L s t e. w e! " ,
ks ?"oM & M 9.* h ouw, V ~
] ahd. BISCOM claimedthat the ANI test exceeded ASTM E-119 '
. , . . requirements ic& $Q > . s's em eh %the im"mm='= tent w4+" seJ ::.k .s3 lIctt-r. It is also i l
unclear as to how many test failures have occurred. It appears l
- v' l that there were two recent failures, an)( ANI test and a BISCO test failure. TMGCC w ald met ;xplei.. U i = - .n e t t er-s. V i
The f ollowing items are unresolved pending clarification or 1
)
I resolution: l ua.4a k l '
- c. Reevaluation of m-- ng- 1976 test documentation and recent test failures for 10 CFR Part 21 and 10 CFR Part 50.55(e)
/ / /
reportabilityp' (445/8516-U-06p 446/8513-U-06).
- b. Inconsistent test methods and/or test results documented by BISCO and the ANI test laboratories for the specific design VV I
l - configuration PCA-76 (ANI No. S-26)4which the ANI rescinded r.h3A Ne, fP~.YC-O L3 vel s/ acceptance and the completion off corrective actiorgd;;;ribad- v m TDDE No. FP 063. whi ch ..r equ4 r-ed--eori -c t i w , wi U.- p /
"~rl:- Thim Hnt" ment also_reautrem + he--ver,J wr iv p, wvi ur'/
--um,c e...ouh_e aN r --e .< -
/
v cm r p T (445/8516-U-07f 446/8513-U-07) / O , '*
- I
I
.n
$i i f
~,
?" . 02, q%. PAGE 18 es
;N 3, .
.,c , , ,
- 7. " Review of Electrical Insoection and Installation / Test Procedures-The NRC inspector completed the review of the applicant's QA/QC program and procedures relating to the installation of electrical components and cables. In addition,a review of the electrical insta'11ation/ test procedures was conducted. The areas covered in
]
the review weret organizational structure and personnel, audits, p4/y rep voremee,4s, werk n, d' jfn 4/y MSpec/5n Mecch'MS, Cen /rol & S
-~.
sW8kk&NtBE8N6E8Pf majestal, Cedrol of atgscusEhepB6GM8biaWekgypgl4695tEBqES$MER6: pr-cerun, Cerree kve t ' Lik dat v~ *
- f" d r*l, ' htlce ,be.
i 2.l, rel e [ qual i ty r ec or d s, and on-si te design control . 1 f utp5 &d, l l In order to identif y specific criteria in the above areas, a
/
review was conducted of Sections 7, 8 3 and 17 of the applicant's FSAR to identify the commitments pertaining to the installation of electrical components and cables. The tabulation consists of j l the pertinent regulatory guides, IEEE standards, and specific ' alternative programs. The specific commitments, coupled with the requirements of of Appendix B to 10 CFR Part 50, form the criteria by which the CA/DC program is judged. A second examination was conducted to identif y the QA/DC program
- t. . !
. y, Ng.,y,. specifics and procedures which pertain to the installation of s '. .v. l electrical componer.ts and cables. The program and procedures were then compared to the FSAR commitments and 10 CFR Part 50, Appendix B criteria to determine if the program and procedures
, adequately addressed the required criteria.
-{ .
,,p u
y PAGE 19 i The following procedures were r evi ewed (a) Inspection Procedures OP-11.3-27, Revi si on 11: OP-11.3-28, Revision 28; OP-11.3-29, Revi si on 17; OP-11.2-29.1, Revi si on 18; OP-11.3-31, Revision 8; QP-11.3-38, Revision 7; OP-11.3-40, Revision 2; QP-11.3-41 Revision 5; OP-11.3-43, Revi si on 19; OP-11.3-44, Revi si on 16; (b) I Install ation/Tes.t Procedur es EEI-5, Revision 3; EEI-6, Revision 1 6; eel-7, Revisi on 5; EEI-8, Revi si on 5; EEI-13, Revision 4; i EEI-16, Revi si on 0: EEI-18, Re vi si on 3; EEI-21, Revision 0; 1 EEI-23, Revi si on 1: EEI-26. F.evi si on 0; ECP-?O. Revi si nn 0: and I j _(c) Admi ni strati ve Procedure CPM--6. 5, Revi si on 11. (
)
k
]
The NRC incpector al so det er rni ned that the "l essons l earned" on Unit i have been incor porated into the Unit 2 QA/DC inspection (' programs and procedurec. l l i No vio3 ati ons or devi at l one were .t dent 3 f i ed . l l l
- 8. Exit Interview I
An exit interview was conducted December 4, 1985, with the applicant representatives identified in paragrap 1 of Appendix D of this report. During this interview, the NRC inspectors summarized the scope and findings of the inspection. The applicant acknowledged the findings. Subsequent to this i nterview, the NRC inspector notified the applicant with respect U! ,e # W - 'A . ,
, e .. ' i , PAGE 20'
['f,'
* , Pk , to the f ailure to report the 10 CFR Part 50.55(e) deficiency 6%';< . s' . -
e described in paragraph 6 above. i
.. p,,,'
1 I n f
.?6' W- l .. . u NJ. I'
[ e. I
. i l
Q sify: eg, . O b d l 1 , *9 b , ej
- y.
'.' e s4 .
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