ML20199A618
| ML20199A618 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak, 05000000 |
| Issue date: | 06/11/1984 |
| From: | BROWN & ROOT, INC. (SUBS. OF HALLIBURTON CO.) |
| To: | |
| Shared Package | |
| ML17192A346 | List:
|
| References | |
| FOIA-85-313, FOIA-85-59, FOIA-86-A-20 CP-QAP-11.1, NUDOCS 8606120536 | |
| Download: ML20199A618 (29) | |
Text
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BROWN & RCOT, INC. ISSUE NUMBER REVISION CATE PAGE CPSES JOB 35-1195 CP-QAP-11.1 5 ggg 1 of 3 TITLE: ORIGINATOR: M d -#-8#
DATE FABRICATION AND 19 dsA41 5//[90/
INSTALLATION REVIEWED BY: /X '
/ INSPECTION OF V OATE COMP 0NENTS, COMPONENT SUPPORTS, AND PIPING APPROVED BY:
.s-T Q[.
-m 6+
j 4 e/ //N Site QA~ Manager DATE
1.0 REFERENCES
f 2.0 2.1 GENERAL PURPOSE R WMMMM MW .
This procedure delineates the responsibilities and -general requirements for Quality Control (QC) inspection / surveillance of Nuclear Safety Class 1, 2 and 3 activities affecting quality. The requirements contained herein are stipulated to ensure that QC inspection activities are accomplished and documented in accordance with applicable project design documents, codes, standa rds , regulatory requi rements, and the B&R QA Manual.
2.2 SCOPE
, The requi rements delineated herein or in subordinate l instructions apply to quality activities performed by B&R at CPSES. Procedures / instructions issued by departments other than the Quality Assurance (QA)/QC Department shall not be used to impose cons traints or requi rements upon QC surveillance / inspection activities. Simila rly, all QA/QC procedures / instructions shall delineate only QC surveillance / inspection criteria and/or attributes to be used while perfonning surveillance or inspection.
2.3. RESPONSIBILITY The Site QA Manager (SQAM) is responsible for all Safety Class 1, 2 and 3 inspection and surveillance activities. He is also responsible for ensuring adequate procedures and instructions are available for the performance of activities affecting quality.
B6061 6 860604 com 8' 5-59 y
GARDE 86-A-20 PDR b$
i SROWN & ROOT, INC. ISSUE CPSES NUMBER REVISION DATE PAGE
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CP-QAP-11.1 5 g 2 of 3 2.4 HOLD POINTS Hold points are defined as any operation in the production process that requires QA/QC/ANI inspection release before further processing. Hold point acceptance is indicated on the appropriate process control document.
Operational Traveler (OT) hold points shall be assigned by QA as deemed necessary to assure that the quality of the item being installed is in cmpliance wi th applicable requirements. j Hold points designations are as follows:
- a. Monitor (M) - conformance verification by physically ~
observing a task being pe rfo nned on a periodic or randam basis. The inspector must be notifed prior to implementing work activities,
- b. Verify (V) - confonnance verification by physically inspecting an iten after perfonnance of an operation, does not require physical observation of the work being perfonned; or, by reviewing objective evidence attesting to the fact that the operation was performed and satisfactorily comple ted . The ins pector shall be notified subsequent to the performance of an operation.
- c. Witness (W) - confonnance verification by physically observing the entire operation being performed. The inspector shall be notified prior to commencenent of work.
2.5 TRAINING AND CERTIFICATION Personnel perfo nning inspection and surveillance of activities affecting quality shall be trained and certified in accordance with CP-QAP-2.1, and subordinate instructions.
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3.0 PROCEDURE 3.1 QC INSPECTION / SURVEILLANCE INSTRUCTION PREPARATION QE, as directed by the SQAM, shall review applicable specifications, drawings and procedures. They shall prepare quality documents that delineate adequate, concise attributes, actions and acceptance criteria for accomplishing inspection activities.
43 s BROWN & ROOT, INC. ISSUE CPSES NUMBER REVISION DATE PAGE JOB 35-1195 CP-QAP-11.1 5 JUN 111984 3 of 3 3.2 PERFORMANCE OF INSPECTION / SURVEILLANCE Inspections and surveillance of activities affecting quality shall be accomplished in accordance with applicable QA procedures, and subordinate instructions.
3.2.1 Receiving Inspection Receiving inspection shall be accmplished and docmented in accordance with CP-QAP-8.1, and subordinate instructions.
3.2.2 Nondestructive Examination f Nondestructive examination shall be accepli shed and documented in accordance with CP-QAP-10.2, and subordinate '
instructions.
3.2.3 Fabrication and Installation Inspection / Surveillance The inspection and routine surveillance of fabrication and installation activities shall be accomplished and documented in accordance wi th instructions subordinate to this instruction.
3.2.4 Final Acceptance, Testing, and Verification Final acceptance, testing and verification of Safety Class 1, 2, or 3 system installation shall be accomplished and docuented in accordance with CP-QAP-12.1 and CP-QAP-12.2.
3.2.5 Storage and Maintenance Inspection Storage and maintenance inspections shall be acceplished
, and documented in accordance with CP-QAP-14.1.
3.2.6 Nonconfonnance Control The control of nonconfo nning conditions shall be accomplished and documented in accordance with CP-QAP-16.1.
3.2.7 Quality Engineering Surveillance / Review QE shall be responsible for perfonning surveillance of site ASME activities to verify compliance with the QA Manual and i QA , procedures / ins tructions.
l QE shall review results of routine surveillance perfonned by j the QCG to as sure compliance with project procedures /
j instructions in areas other than those designated as planned inspection, examination or testing holdpoints.
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, TEXAS UTILITIES GENERATING COMPANY
.a#rnNEE!'"ou"s*s'dfel"sSi$Us" ' PURCHASE ORDER SUPPLEMENT g
38,724.75 AcomoM SY THis Suppt.EMENT 0.00 S osDUCTloM SY TMis suppt.EMENT Texas Utdities Generating Co.
3 48.017.75 ',ocuocorar,u P.o. sex 1oc2. Glen Rose. Texas 76043 SUP96EMENT NUMBER TO 1 CFF 773-S 10/12/83 0-8510-000000-007 '"~'""Si B[L0W "oEN*"
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T PACIFIC SCIENTIFIC Ua!"*E'*a o"E a s"wf*"s E Ye^c'oE"*zEo 0
- KINTECH DIVISION %"ghMo%'*ss"u'E on*c"y 's"v'*TsNI.
1346 S0. STATE COLLEGE BLVD. c"^sma oseantuaNT.
LANAHEIM, CA. 92803 j R 18873A CONFIRMED TO: DIANE YOUNG 714/774-5217 ,
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raa euacwasma ocela'r"ufs"r*w'IMfEc^r"se"EI.Y."Sf^a"!L"nalsTr!.Ui!We'uC'EREo PURCHASE oRoER
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U/t ESCRIFTION fRICE ITE. FR CE
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O ANTE PROMISED SHIP APPROX. DELIVERY -
DATE: 12/7/83 DATE: 12/14/83 REFf.R TO SUBJECT ORDER AND A00 THE FOLLOWING COST OF REPAIRS: ,
f 7 2 EA MODEL PSA - 1/4 PART NUMBER 1801104-05, ','
SERIAL NUMBERS 3920, 4037, 4131, 4133, 4592,
. 4711, 4713, 3933, 5951, 5959, 6127, 6199, 6604, 10758, 10766, 11347, 11359, 11840, 12355, 12635,
- 15321, 15369, 15383, 15388, 15390, 16154, 16164.
16205, 16220, 19318, 19495, 19541, 20390, 21692, 22766, 22795, 26117, 26199, 28039, 28106, 33710, -
33647. -
MATERIALS: $258.71/EA $10,865.82 LABOR 173.00/EA 7.,266.00 8 EA MODEL PSA-1/2 PART NUMBER 1801104-07, SERIAL h'l NUMBERS. 1198, 2652, 2658, 8395, 8402, 8979, 10337, 11812, 12317, 12319, 12348, 4277, 8969 -
MATERIALS 264.23/EA 3,434.99 LABOR 179.00/EA 2,327.00 Except as hereus amend ment carries forth and preserves au Terms and Conditions of the ortpnal Purchase Order and previous Supplements.
l ^som eon 1y9.M0 COST 0F REPAIR OF SNUB 8ERS TEXAS S GENER ATING COMPANY CHANGEDStMyQ QN/ PD (0171807 4881 ExCO caouismonsiE'" ouwave. coin se7 esi expv ,,
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ao= ao'ca m TEXAS UTILITIES GENERATING COMPANY caos 2 or 3 P.O. NO. SUPPLEMENT NO. PURCHASE ORDER SUPPLEMENT CONTINUATION SHEET CPF 10873-S 1 EM
% U/g DESCRIPTION UNIT PRICE TrEM FRICE 9A 5 EA MODEL PSA-1 PART NUMBER 1801102-05, SERIAL NUMBERS, 12030, 12997, 14596, 14611, 16441 MATERIALS 63.00/EA 315.00 LABOR 185.80/EA 929.00
, 99 EA MODEL PSA-1 PART NUMBER 1801102-05, SERIAL .
C/ NUMBER 3680 -
MATERIAL 71.00/EA 71.00 LABOR 255.00/EA 255.00' 10 '17 EA MODEL PSA-3 PART NUMBER 1801106-05, SERIAL NUMBERS 3624, 3627, 5366, 6711, 6758, 8402, 12927, 12933, 12982, 13013, 16799, 16827, 16845, 21333, 26500, 12950, 14915 MATERIALS 192.88/EA 3,2h8.96 LABOR 5,285.98 310.94/EA 11 '4 EA N00EL PSA-10 PART NUMBER 1801103-07, SERIAL NUMBERS 3137, 3944, 5328, 7711 MATERIALS- 2,748.00 687.00/EA LABOR 1,516.00 379.00/EA 12 1 EA MODEL PSA-35 PART NUMBER 1801112-09, SERIAL .
NUMBER 9624 LABOR 432.00/EA 432.00 TOTAL AMOUNT THIS SUPPLEMENT NO.1 $38,724.75 l
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TEXAS UTILITIES GENERATING COMPANY cao7 3 cr 3 P.O. NO. SUPPLEM ENT NO. PURCHASE ORDER SUPPt.EMENT CONTINUATION SHEET 10873-S 1 Q QM E U/I DEsCRIrr!ON UN ICE ITEM P CE NOTE:
SNUBBER SERIAL NUMBERS 3933 AND 14915 WERE LOST AT PACIFIC SCIENTIFIC FACILITY AND WILL BE RE-PLACED AT NO CHARGE. SNUBBER SERIAL NUMBERS 4129 AND 2645 WERE FOUND TO BE OPERATIONAL AND
, WILL BE RETURNED AT NO CHARGE.
SAFETY RELATED REQUIREMENTS QA/QC Requirements listed on the original pur- ~
chase order and subsequent supplements remain in effect and apply to supplement No.l.
QUALITY RECEIVING INSPECTION REQUIRED.
APPROVED:
0rtbh c,moha \ * -
- 2" Q CPSE5 QUALITY ASSURANCE DATE THE ABOVE PRICE IS FIRM AND NOT SUBJECT TO ESCALATION.
CONFIRMING TELEPHONE ORDER PLACED ON 10/12/83 BY TOM HEARD AT WHICH TIME TERMS AND CONDITIONS WERE VERIFIED. ANY CHANGE REQUIRES APPROVAL OF PERSON PLACING ORDER. -00 NOT CUPLICATE.
Au. TERMS AND CONDITIONS OWN TH ACE AN A ER H S ONE SM QF S ROER SUMEMENT ARE VENOOR* COPY
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CPSES FIELD REQUISITION CONTINUATION SIIEET - CONSTRUCTION k$ . 'b
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THIS l$ NOT A PURCHASE ORDER FIEQUISITION k 7N/ i LEAVE BLAteK FOR l' sAmv mmAspeo om l.
l ITT M QUANTI 1 Y DESCRIFTION COST NO. WANTT D Give entnplete descriptions, ratings, catalog nos.,etc. Attach specifications,1f required. % y ,,n CODI S l
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i TEXAS UTILITIES GENERATING COMPANY PAGE 1 Op 5 oats 6-28 sw TO TEXA5 UTILITIES GENERATING COMPANY, ATTN: BROWN & ROOT, INC.
C/o COMANCHE PEAK STEAM ELECTRIC STATION PURCHASE ORDER FM 201, GLEN ROSE, TEXAS 76043 Oniciu,e M RMAMN NOMCANN SILL TO TEXAS UTILITIES GENERATING COMPANY P.O. BOX 1002. CLEN ROSE. TEXAS 76043 x 5" "' v ' ^ F o 8- SHIPPING POINT
'.: T."::" .::" .*:: MOTOR FREIGHT PREPAY AND A00 SMtPMENT PROMISED SY rERMS REQ.NQ. ACCQUNT NQ.
P.O. NO. NET 30 DAYS R 18873 1-0-8510-000000-007 N/A CPF 10873-5 P -l T PACIFIC SCIENTIFIC - ....,,..-
o KIN TECH DIVISION *".".! ,"".*.I".*"*l2 ",." "/.".O y 1346 S0. STATE COLLEGE BLVD. y PLEASE RENDER INVOICES IN ANAHEIM, CA. 92803 DUPI.lCATE CONFIRMED TO FLOYO FREDERICKSON (714) 774-5217 ~
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O AN TY U/t DESCRIPTION NTED UNI PRJCE ITEM P CE THIS PURCHASE ORDER COVERS THE RETURN OF THE FOLLOWING ITEMS FOR INSPECTION, TESTING, AND ESTIMATE OF REPAIR TO THE REQUIREMENTS OF ASME SECTION III, SUBSECTION NF, CLASS 1 AND GIB8S AND HILL SPECIFICATION 2323-MS-46A.
1 44 EA MODEL PSA-1/4 PART NUMBER 1801104-05, $82.00/EA $3,608.00 SERIAL NUMBERS, 3920,4037,_4R9,4131,4133, 4592, 4711, 4713, 5933, 5951, 5959, 6127, 6199, 6604, 10758, 10766, 11347, 11359, 11840, 12355, 12635, 15321, 15369, 15383, 15388, 15390, 16154, 16164, 16205, 16620, 19318, 19495, 19541, 20390, 21692, 22766, 22795, 26117, 26199, 28039, 28106, 3933, 33710, 33647 2 14 EA MODEL PSA-1/2 PART NUMBER 1801104-07, 84.00/EA 1,176.00 SERIAL NUMBERS, 1198, &45, 2652, 2eb8, -
8395, 8402, 8979, 10337, 11812, 12317, 12319, 12348, 4277, 8969 3 6 EA MODEL PSA-1 PART NUMBER 1801102-05, 118.00/EA 708.00 SERIAL NUMBERS, 3680, 12030, 12997, 14596, 14611, 16441
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gig,vsa pIPESUPPORTS(MATERIALCONTROL[ TEXAS UTILITIES GENERATING CO.\tPANY auvan at\T. HEARD /sr tai n asuasi ext 296 / -- -
Laculs:TIONER M. BLEDSOE (si n asuasi ext
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""""***'2-TEXAS UTILITIES GENERATING COMPANY eaa3 2 or 5 P.Q NQ PURCH ASE ORDER CONTINUATION SHEET CPF 10873-S ANTE l Ull DESCRIFTION UNI CE I CE 4 17 EA MODEL PSA-3 PART NUMBER 1801106-05, $153.00/EA $2,601.00 SERIAL NUMBERS, 3624, 3627, 5366, 6711, 6758, 8402, 12927, 12933, 12982, 13013, 16799, 16827, 16845, 21333, 26500, 12950, 14915 5 5 EA MODEL PSA-10 PART NUMBER 1801103-07, 178.00/EA 890.00 SERIAL NUMBERS, 3137, 3944, 14915, 5328, 7711 6 1 EA MODEL PSA-35 PART NUMBER 1801112-09 310.00/EA 310.00 SERIAL NUMBER, 9624
~ '
TOTAL AMOUNT FOR TESTING AND INSPECTION ONLY $9,293.00 NOTE: PACIFIC SCIENTIFIC IS TO FURNISH .
TEXAS UTILITIES GENERATING COMPANY WITH AN ESTIMATED REPAIR CHARGE AND OBTAIN APPROVAL PRIOR TO REPAIR OF PACIFIC SCIEN-TIFIC MECHANICAL SHOCK ARRESTORS (SNUBBERS).
THE REPAIR ESTIMATE SHALL BE SUBMITTED TO:
ATTN: R.D. GENTRY - PROCUREMENT MANAGER IF REPAIRS ARE TO BE MADE FOR THE ESTIMATE AMOUNTS GIVEN BY PACIFIC SCIENTIFIC, A SUPPLEMENT WILL BE ISSUED TO THIS PURCHASE ORDER TO ADD THESE COSTS TO THE TOTAL PUR-CHASE ORDER AMOUNT.
TESTING SHALL BE PERFORMED TO ONE OF THE FOLLOWING PACIFIC SCIENTIFIC TESTING " 0CE-DURES AS SUBMITTED ON 18 MAY, 1983:
IT519 REY. W, IT523 REY. T. IT524 REV. T.
IT527-OS REY. U, IT527-07 REV. U, IT 534 i REY. M, AND IT533 REY. J.
TRACEABILITY IN ORDER TO MAINTAIN TRACEABILITY, PURCHASER l
SHALL IDENTIFY MECHANICAL SHOCK ARRESTORS IN l SUCH A MANNER THAT IDENTIFICATION WILL NOT BE LOST DURING THE REPAIR PROCESS. SELLER SHALL ASSURE THAT SUCH IDENTIFICATION REMAINS INTACT l DURING ALL PROCESSING AND HANDLING WHILE IN l
HIS POSSESSION.
ALL TERus AND CONotflONS SHOWN ON E AN RE R$g e ME $ GNEO SMEET OF THIS OROER ARE EFFECTIVE COVERING VENDOR
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'"" ** r TEXAS UTILITIES GENERATING COMPANY caos 3 on 5 P.Q NQ PURCH ASE ORDER CONTINUATION SHEET CPF 10873-5 ANT U/I DESCRIPTION yphCE ITE CE CPSES RECEIVING INSPECTION INSTRUCTIONS CPSES RECEIVING INSPECTION SHALL VERIFY THAT MECHANICAL SHOCK ARREST 0RS FURNISHED FOR RE-PAIR ESTIMATE ARE PROPERLY IDENTIFIED PRIOR TO SHIPMENT. UPON RETURN OF MECHANICAL SHOCK ARRESTORS TO THE J08 SITE, CPSES RECEIVING INSPECTION SHALL RE-VERIFY THAT THE IDENTITY OF MECHANICAL SHOCK ARRESTORS HAS BEEN MAIN- -
TAINED. '
r VENDOR SERVICE QUALITY ASSURANCE REQUIREMENTS General ,
Services procured herein shall be considered Nuclear Safety Related. Strict compliance with referenced codes, specifications and re-quirements is mandatory. Services shall be in accordance with the Vendor / Subcontractor's written Quality Assurance program confonning to the applicable requirements of ANSI N45.2 antl 10CFR50, Appendix B or ASME Section III (NCA-3800 or NCA-4000), subject to verification by Purchaser's Quality Assurance Department. Seller shall extend the Right-of-Access to the Pur-chaser, his designated representative or authora ized regulatory agencies. Such access shall include all facilities and records for the pur-
. pose of surveillance and Q/A audits. Seller shall establish provisions for imposing similar Quality Assurance requirements to applicable sub-tier vendors.
gality Assurance Program Seller shall submit his Quality Assurance pro-gram to the Purchaser for approval and docu-mentation. Subsequent revision; shall be sub-mitted for approval prior to implementation (uncontrolled copy shall be submitted with pro-posal and controlled copy upon receipt of pur-chaseorder).
Seller shall agree to stop work at the request of Purchaser or his representative until reso-lution of any Quality Assurance / control discre-pancy. _
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' " " ' " '_ TEXAS UTILITIES GENERATING COMPANY l l
l 1 cAas 4 or 5 l l P.Q NQ PURCH ASE ORDER CONTINUATION SHEET l
< CPF 10873-5 i W Og&T U/1 DESCRIFTION UN CE I M CE ;
Nonconformance Reoortino l 10CFR21
- The provisions of 10CFR21 apply to this order and certain requirements must be met, e.g.:
21.6' Posting requirements 21.21 Notification of failure to comply or existence of a defect l 21.31 Procurement documents -
. 21.51 Maintenance of records 4
A copy of any report furnished to the NRC of a potential deficiency /nonconfonnance in com-pliance with 10CFR21 concerning equipment or -
services intended for use in any Texas Utilitie:s Company system nuclear power plant must be transmitted to EVP/GM Texas Utilities Generating
! Company at the same time and in the same manner 1 in which the report is furnished to the NRC.
l APPROVED FACILITY l THIS MATERIAL / EQUIPMENT MUST BE SHIPPED FROM APPROVED FACILITY AT: ANAHEIM, CALIF.
i QUALITY RECEIVING INSPECTION REQUIRED.
i APPROVED:
ajd , Ma '7is1t3_
CP5Es QUALITY AS5URANCE DATE I THE A80VE PRICE IS FIRM AND NOT SUBJECT TO ESCALATION.
SHIPPER IS REQUIRED TO REFERENCE THIS PURCHASE ORDER / SUPPLEMENT AND LINE ITEM NUMBER (INCLUD-ING DIRECT SHIPMENTS) ON ALL PACKING LISTS, INVOICES AND CORRESPONDENCE. .
1 ALL TERMS ANO CONotflONS SHOWN ON THE AN mE mst F wt S GNEO SHEET OF THIS ORDER Amt EFFECTIVE COVERINC.
I N
" " " i TEXAS UTILITIES GENERATING COMPANY (Aas 5 O. S P.Q NQ PURCH ASE ORDER CONTINUATION SH EET CPF 10873-5 E W$T Ull DESCRIPTION UN[ RICE ITEM CE EXPEDITING ALL GOODS AND SERVICES FURNISHED UNDER THIS ORDER MAY BE EXPEDITED AT ALL TIMES AND PLACES INCLUDING THE PREMISES OF THE SELLER AND HIS SUPPLIERS, REGARDLESS OF TIER, EITHER BEFORE. DURING OR AFTER MANUFACTURE BY RE-PRESENTATIVES DESIGNATED BY THE OWNER. THE EXERCISE OF OR FAILURE TO EXERCISE THIS RIGHT TO EXPEDITE SHALL NOT RELIEVE THE SELLER OF ~
HIS OBLIGATION TO FURNISH ALL GOODS AND SER-VICES IN STRICT CONFORMANCE WITH ALL OF THE TERMS OF THIS ORDER.
IF EXPEDITING IS PERFORME0 ON THE PREMISES OF THE SELLER OR HIS SUPPLIERS, SELLER SHALL FURNISH WITHOUT ADDITIONAL CHARGES ALL REA-SONABLE FACILITIES AND ASSISTANCE FOR THE SAFETY AND CONVENIENCE OF THE OWNER'S REPRE-SENTATIVES IN THE PERFORMANCE OF THEIR DUTIES.
CONFIRMINGTkLEPHONEORDERPLACEDON7-5-83 BY TOM HEARD AT WHICH TIME TERMS AND CONDITIONS WERE VERI-FIED. ANY CHANGE REQUIRES APPROVAL OF PERSON PLACING ORDER. 00 NOT DUPLICATE.
l ALL YERMS ANO CONOITIONS SHOWN ON THE PA AN mtv RSE P HE IGNEO SMEET THIS ORDER AAE EFFECTIVE CCVERING
,VENOCR* COPY
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r" TEXAS UTILITIES GENERATING COMPANY
== No. o q . A ucs '
- h 373 / g' / w m s CPSES FIELD REQUISITION - CONSTRUCI' ION
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n,.,e u..a s.r P..a s.E rw 'A/>74/.gzf 7 ' Hl318 T NOT A PORCHA$E ORDER y,yoo,u,ug /Jfcjfjc Sc/ZM7/r7c -
OEPARTMENt: Material Control. REQUISITION No. jlf ,_ - .
sTatET,Jdh6aiem 30. 3/Wi t.h ve h v.v OttE(,f givg INTENoED UsE: pine hnnnrH DATr )PRIL7 w%
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travr.st.ama rom TTEM QUANTrrY pfg DMWON .
SAM W Ha m N g [b NO. WANTED Cl.e resplete deerrlyelone, ratists, catalog nas., etc. Attaa speelflentlens. li req.irect. E ,,,, ,, a rong, CODES 4 l REQUEST TOR VENDOR SERVICES EE d ;y @ .p[( @ .
l i Request Vendor shop services for the inspection of Pacific '
~l @7 i g d Nfl$dl i Scientific flechanical Shock Arrestors (snubbers). The vendor m - __(
is to inspect snubbers which have been received on site that
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vendor should be authorized to inspect, test, ani disassembic l i
j as required to determine the exact prob 1Em or damage to the g 4 1
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l l Individual snubber. Upon completion of the inspection the jb__ _ f '
l vendor is to submit to the site their recommendation and cost ,
l for repairs of the snubber unit. .
NOTE: No repair work should be done on snubbers prinr to I "-? ' 'T - '
site review of vendor's findings and cost proposal, l '
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TEXAS y,TILITIES GENERATING COMPANY -
CPSES FIELD REQUISITI6N CONTINUATION SilEET - CONSTRUCTION I'Jlj3
' No R gg THIS IS NOT A PURCHASE ORDER REQUISITION l
- e. J' LEAVE RLANK FOR sam l mcnnsm wn 'l, g33:
ITEM OUANTTTY DFSCRIPTION ,
NO_ W ANTT D UN Give cornPl ete descriptions, rstings, catalog nos etc. Attach specincations.lf required. (yn,3 QAss p, ,9,,t l
At that time the site will address each individual j snubber unit on a case by case basis and authorize needed .
repa i rs . ?
All work shall be certified to meet the requirements ragggman_c -- _,, _3 I specified in ASME III, Sub-Section NF, Class I, and PS-46A. ter:
! Recownded Vendor - Sole Source $.
Pacific Scientific .
Q!aI! Big;;;msemRFT Kin Tech Div. na gggg;3l l 1316 S. State College 111v<f. .
ge= -.
Anaheim, Cali f. 92803 -ig_ -_ -
A-T^- E ATTH: Mr. Floyd Fredrickson J[ % f!
Tel. 711-771-5217 ).! !
The snubber units (shnck arrestors) are listed )y size, i .
vendor part number. A serial number on attached pages, that are to be returned for inspection.
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TEXAS, UTILITIES GENERATING COMPANY CPSES FIELD RkQUISm0N CONTINUATION SilEET - CONSTRUCTION No R THIS IS NOT A PURCHASE ORDER REQUISITION
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DI'.SCRIPTION SArTTY rummasmat+rt ( OST ITEM OtJANTITY ^38 NO. W AN TI D Gl,e ciwnplete descriptions, ratings, catalog nos.,etc. Attach specifications,if required. W IT Pa M TOTAI COi i's M J4 b t'odel P5A-1/4 Part !! umber 1801104-05, Serial Numbers, 3920, -D Q6 l 1 ea. f. ) ,
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) 4037, 4129, 4131, 4133, 4592, 4711, 4713, 5933, 5951, 5959,1 . kfhydf@ ! uunk ,
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6127, 6199, 6604, 10758, 10766, 11347, 11359, 11810, 12355, ; i g ,;y.c b.: ,
l 12635, 15321, 15369, 15383, 15388, 15390, 16154, 16164, ;i f l 16205, 16220, 19318, 19495, 19511, 20390, 21692, 22766, 5 l 22795, 26117, 26199, 28039, 28106. 393JJ37/0, _3%47 4 !'
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2 /4 1/ ca. Model P5A-1/2 Part flumber 1801101-07, Serial flunbers,1198, h 2615, 2652, 2658, 8395, 8102, 8979, 10337, 11812, 12317, lE
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am , w_ . _r 3 6 ca. f!odel PSA-1 Part ilumber 1801102-05, Serial fiumbers, 3680, 9 4 $N [N b f 12030, 12997, 14596, 14611, 16141. a 1 j WiiM BI B l
1 17 vib ca. !bdel PSA-3 Part Number 1801106-05, Serial Numbers, 3624, 9
3627. 5366. 6711. 6758. 8402. Iu 1. 12933. 12982. 13013. N ij W -j M.md h f .
N 16799, 16827, 16845, 21333, 26500, 1 #A .1295o 14es( m m sh a
M BRM M u
DATE f g 0,@ ROVAL IoI478.".dl Ecfc'EPTED. ,
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' TEXAS VTILITIES GENERATING COMPANY , ,
, , , CPSES FIELD REkUISITION CONTINUATION SIIEET - CONSTRUCTION No R THIS IS NOT A PURCHASE ORDER REQUISITION l l
LEAVE BLANK FUR sArtiv l, rummasm r* PT COST l ITEM QUANTTTY DESCRIFTION NO. WANTED U/I Give counplete descriptions. ratings. catalog nos.,ete. Attach speelfications.lf required. y ,,, y , coDi s l 5 5' id* ea. Model PSA-10 Part Number 1801103-07, Scrial Numbers, 3137, )
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- s i 6 1 ea. 11odel PSA-35 Part flumber 1801112-09, Serf al Number, 9624. h _..
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BROWN & ROOT, INC. q, QA RECORD Quality Assurance Department NCR N0. (Y} .590 / ,
Nonconformance Report (NCR)
CPSES-35-1195 PAGE / OF i DRAWING / IDENTIFICATION
- TAG /ID NUMBER LOCATION OR ELEVATION RIR NO.
sr.axmo osi "
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.Shb be c's se e. gP e 4-?S whs 3 Aa a s+ NlA NONCONFORMING CONDITION TREND DOCUMENT VIOLATED: MIS -C # /o A REY. 3 PARA.
CATEGORY TlIl tlitAciml Ls s 4 o A S a mb be.r's ha,vt c o ffe,r }g[de)b a s -
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REPOR,JE0 BY:- -
0 ATE: REVIEW / APPROVAL DATE:
Heae / 2. DocXsex 4-o3 93 <,,
ACTION ADDRESSEE 'N' STAMPE0 COMPONENT CAR NO.: ASME CODE ITEM: ,
V Yes X No Y Yes No
- f vvv43 OISPOSITION: '
A-REWORK 8-REPAIR C-USE AS IS 0-SCRAP E-RETURN TO VENDOR .
l i
i' ENG. REVIEW / APPROVAL: DATE: QA REVIEW: 0 ATE:
l TUGC0/QA REVIEW / APPROVAL: 0 ATE: ANI REVIEW: 0 ATE:
QC VERIFICATION: DATE: POTENTIALLY REPORTABLE Yes NO ANI CONCURRENCE: DATE: INITIAL /0 ATE:
dESTINGHOUSE CONCURRENCE: ec DATE:
QA REVIEW / CLOSURE: ; -
i I I i '
s BROWN & ROOT, INC.
0A RECORO Quality Assurance Department NCR NO. (Y)- 3'90 /
Nonconformance Report (NCR)
CPSES-35-1195 PAGE / OF i DRAWING / IDENTIFICATION TAG /ID NUMBER LOCATION OR ELEVATION RIR N0.
Sea- AHMMb uSs' "
Subbe r's % Pyes 4?r whs3' % e+ N/A NONCONFORMING CON 0! TION TREND DOCUMENT VIOLATED: #1 5 W /c A REV. 3 PARA.
CATEGORY d'/h Tl2P- (LO tc hed Ls 6 'k o A S a s6 be.r's ha.ve. e I Lhe.r ],1,[dej f a o
O 9'r a:he- p r c PL r L y o r b r v e. 6 a e , g , , ,) ,_ ) g y-we ,_, g ,,,)) C ;y d u
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- REPOR ED BY:~
- DATE: R DATL ar~/ s.bsexsex 4- 0 93 /YEIEW/
/ nis/APPROVAL DW Y-/ Y-73 ACTION ADDRESSEE 'N' STANPED COMPONENT CAR NO.: ASME CODE ITEM:
Nht/ r ao< -
f Yes
- 5* W V-P3
')( No
^/4 X_Yes No OISPOSITION:
A-REWORK 8-REPAIR C-USE AS IS D-SCRAP E-RETURN TO VENDOR g PARTIAL DISPCXSITICN:
All snubbers on attached list shall be returned to the vendor for testing and inspection to determine repair requirenents and costs. Upon receiving this information fran the vendor the site material control group will make the decision of whether to repair the snubbers or not. 'Ihis decision will be a case by case basis for each srnh. Peference field requisition 18873.
- m , - / , /
Y-/ .5 cz2W V-/
TUGC0/QA REVIEW /APPROVA#'. DATE: AfL REVIEW: DATE:
at R +N-73 WA-- 4//vh3 QC VERIFICATION: DATE: POTENJIALLY REPORTABLE Yes ' V NO ANI CONCURRENCE: DATE: I,*1ITIAL/0 ATE: - ([!h,8 WESTINGHOUSE C0ffCURRENCE:
QA REVIEW / CLOSURE: DATE: .
- FOR $FORMATM
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C RETURNED GOODS C AUTHORIZATION RGA 83/1059 PO/FR CPF10873-S /FR18873 0 MATERIADATE 6-14-83
. . . VENDOR PACIF-IC SCIENTIFIC TELE SHIP TO ANAHEIM, CALIF. 92803 TELE ADDRESS 1346 S. STATE COLLEGE BLVD.
VIA PPD x COL REASON FOR RETURN nAMACED MATERIAL QTY ITEM DESCRIPTION
, 44 ea. PSA-1/4 SNUBBERS 14 ea. PSA-1/2 SNUBBERS 6.ea. PSA-1 SNUBBERS 17 ea. PSA-3 SNUBBERS' 5 ea. PSA-10 SNUBBERS 1 ea. PSA-35 SNUBBERS TOTAL OF 87 SNUBBERS-ATTACHED IS A LIST OF SERIAL NO.
ATTN: MR FLOYD FREDRICKSON 714-774-5217
- L
, PERSO@TH0RIZIN@ RETURN DEPTMATERTAL CONTROL EXT 390
-- =
RECEIVED AT WHSE "A" SHIPOUT DATE LOC DATE AUTH TO RETURN SHIPMENT TO VENDOR PER ON DOCUMENT #
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APPROVAL DATE 8 & R EXPEDITOR MGR
' ' ' " ~
TEXAS UhLITIES GENERATING COMPANY 3 4 CPSES FIELD REQUISITION CONTINUATION SHEET - CONhUCTION No R THIS IS NOT A PURCHASE ORDER "QEQUISITION i LEAtt $1 LAME P0h t 11 tl QUANTITY I DESCRIPTION
's m reacwAsmo om. COST N
M t. WANTIU Cive complete descriptions.rstings catalog nos etc Attach specifications,tf required. I w, CODES e
~'
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1 44. S4 _Q~ ea. Model PSA-1/4 Part Number 1801104-05, Serial Numbers, 3920, 4037, 4129, 4131, 4133, 4592, 4711, 4713, 5933, 5951, 5959, ,
_ 6127, 6199, 6604, 10758, 10766, 11347, 11359, 11840, 12355,
, 12635, 15321, 15369, 15383, 15388, 15390, 16154, 16164, !
__ 16205, 16220, 19318, 19495, 19541, 20390, 21692, 22766, C 22795, 26117, 26199, 28039, 28106. 3953.337/o. 5 % 47-W A m
.4' .
_2 /4 12t4K ea. Model PSA-1/2 Part Number 1801104-07, Serial Numbers,1198, 2645, 2652, 2658, 8395, 8402, 8979, 10337, 11812, 12317, 12319, 12348. 4 2'l l,, 8 % 1
~
3_ 6 ea. Model PSA-1 Part Number 1801102-05. Serial Number $, 3680, r '
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_ 12030, 12997, 14596, 14611, 16441. '
i, o.6 4 / 7 M u18 ca. Model PSA-3 Part Number 1801106-05, Serial Numbers, 3624, i !
8 3627. 5366. 6711. 6758. 8402. 12927. 12933. 12982. 13013. 1
-l 1 16799, 1682 7, 1684 5, 21333, 26500, 12950,. 14 ers .
V.TRACTO) APPROV AL -
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TEXAS ITTILITIES GENERATING COMPANY ,,,, 4 ,, 4 CPSES FIELD HEQUISITION CONTINUATION SHEET - CONSTRUCTION NDR THISIS NOT A PURCHASE ORDER REQUISITION r e t At OUANTit i pf, DESCRIPTION SAFETY a INO Den COST st). w A NTi l> ci e co.npicte descriptions. ratinsi. cataios nos eie. Asincti specifications,ir required. CL^
m cooEs 5 5 3$k 9 ea. Model PSA-10 Part Number 1801103-07, Serial Numbers, 3137 -
3944,14915, 5326. 77/ l 4-f4# .
6 1 ea. Model PSA-35 Part Number 1801112-09, Serial Number, 9624.
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Brown & Root,Inc.
' P. O: BOX 1001 .
GLEN ROSE, TEXA5 76043 SHIPPING RECORD so. 35-1195 FREDRICKSON PACIFIC SCIENTITIC ATTR: MR. FLOYD staansIION o ,, 7-6-83 To:
1346 5. STATE E COLLEGE BLVD. Job No.
AMANEIM. CALIF. 92803 Referenc.: CPF 10873-5 R-18873 *Q"
'I dwT4 ^ /-. PREPAID, Tho Following Shipped To You Today Via: - .
O For cr. die O For R.p.ir O R.ntoi R. turn O REPAIR OF DAMAGED NATERIAL o- u= o.= w
~
1 44 EA PSA-1/4 SMf58ERS .
14' EA PSA-1/2 SMUB8ERS' .
5 EA PSA-1 SNUSSERS 17 EA PSA-3 $NUSSERS .
1 EA PSA-35 SNUSSERS .
T TOTAL OF 87 SNUB 80tS--ATTACHED IS A LIST OF SERIAL N05.
ATTE: !st. FLOYD FREDERICE305. 714-774-5217
! d6F^ .
Q.A. VERIFIED:, n, , s 7-4 ./ ?
R:morks: PER ROY W IGHT. 1390: BEN JONES Received By: b d . 7 /4 -M: L.C. VICXLtmD
~~
O RETunseo AUTHDRF2ATON.,
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s I RGA 83/1059 PO/FR CPF10873-S /FR15873 O FATERIAD' ATE 6-14-33 VENDOR FACIFIC SCIE:CIFIc TELE .
, I
, SHIP TO ATJ.HEIM, CALIF. 926C3 , - TEl.E l
- ADDRESS 1346 S. STATE COLLEGE SLVI). <
- j. VIA pro X COL !
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REASON FOR RETURN DAMAGED MATERIAL /AA) A.c.p,2 a / A -)
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- I P I i QTY ~
i ITEM DESCRIPTION
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j PSA-1/4 44 ea. SNUBBERS L <
14 ea. PSA-1/2 SNUBBERS l 6'aa. PSA-1 SNUBBEPS
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17 ea. PSA-3 SNUBBERS ,
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5 en. ' 'PSA-10' SNUBBERS . 43
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L TOTAL OF 87 SNUBBERS-ATTACHED IS A LIST OF SERIAL NO.
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t: ATTN: MR FLOYD FREDRICKSON 714-774-5217
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( wrriIrUtgre ogreeo or cesRosed NOTE-where the rote et volve of the property. desecoeat The ondoctored ogreed or volve, shepoors value ofare thereovered property to asstate heret,specit.
ys icolly stateo bt, the shipper
- to be(Aght ; or Caspier.
noe e=edine. . . .h. pe, h n a ebd Shipper /t V " Charges Advancede per Addrets BY l3 -
"THIS SHIPMENT t$ TENDE RED ANO RECEIVED SUBJECT TO THE TERMS AND CONOlTIONS OF THE CARRIERS' 88LL OF L. ACING AS FILED wtTH THE INTERSTATE COMMERCE COMMiS$10N" NOT NEGOTIABLE C* ,
SHIP CENTRAt. - IT'S CONVENIENT & SAFE I
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TEXAS UTILITIES GENERATING COMPANY 3 4 Cl*SES FIELD REQUISITION CONTINUATION SIIEET - CONkRUCTION N3R THISISNOT A PURCHASE ORDER ' REQUISITION *
- LEAvt SLA#E FOR lilAl NO.
- QUANTITY WANTED U/I DESCRitTION .
Give cornplcas descriptions. stings, catalog nos.,etc. Attach specifications,if require #, i S$'
coag N**^"*o om .
,,, ,, a ,ogg cogy CODES l
f' 1 44 31 % v ea. Model PSA-1/4 Part Number 1801104-05, Serial Nb2 ers 39h0, 4037, 4129, 4131, 4133, 4592, 4711, 4713, 5933, 5951, 5959, a: 6127, 6199, 6604, 10758, 10766, 11347, 11359, 11840, 12355,
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12635, 15321, 15369, 15383, 15388, 15390, 16154, 16164, I
16205, 16220, 19318, 19495, 19541, 20390, 21692, 22766, .
22795, 26117, 26199, 28039, 28106. 3953.337/0. 33647-D ,
0 sd ,
'2 /4 lit # ea. Model PSA-1/2 Part Number 1801104-07, Serial Numbers ,1198, P
2645, 2652,. 2658, 8395, 8402, 8979, 10337, 11812, 12317, 12319,12348, 42M , 8969_
3 6 ea. Model PSA-1 Part Number 1801102-05, Serial Numbers, 3680, 12030, 12997, 14596, 14611, 16441.
t 17 M 14 4 ea. Model PSA-3 Part Number 1801106-05 Serial Numbers, 3624,
{3627.5366.S711.6758.8402.12927.12933.12982.13013.
i p 16799,16827,16845, 21333, 26500,1295o,.14c>ss. .
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. TEXAS UTILITIES GENERATING COMPANY ,,,,, 4 ,, 4 .
Cl*SES FIELD REQUISITION CONTINUATION SIIEET - CONSTRUCTION NoR THIS IS NOT A PURCHASE ORDER REQUISITION
- LEAVC GLAseK FOS I t'l M QUANTITY DESCRIFTION "'*"^sueo u n cosy
. .NO. WANTED U/l Gius cuenptste descriptions.satings. catalog mos.,stc. Attach specifications,6f sequised. 8^'$'
a m ,,,g, yogg CODES l 5 6 3$k3 ea. Model PSA-10 Part Number 1801103-07, Serial Numbers, 3137 -
3944, 14915, 5 3 2 6 . 7711 4 4 4 8 s
4 6 1 ea. Model PSA-35 Part Number 1801112-09, Serial Number, 9624.
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{g 10 j P49lO)i h 8 y 3f [t 6M.f-Gard d
t# p stts In Reply Refer To: },",k. $\k.'
Docket: 50-445/84-12 ,., '3, {['1 i .! . ($3 50-446/84-06
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Teras Utilities Electric Company C,'
20 ATTN: M. D. Spence, President, TUGC0 Skyway Tower ,
400 North Olive Street I Lock Box 81 g
Dallas, Texas 75201 i Gentlemen: U i
This refers to the inspection conducted under the Resident Inspection Program by Mr. J. E. Cummins and others of this office during the period -
March 20, 1984, through May 18, 1984, of activities authorized by NRC
[
Construction Permits CPPR-125 and CPPR-126 for the Comanche Peak facility,
- Units 1 and 2, and to the discussion of our findings with Mr. J. T. Merritt and other members of your staff at the conclusion of the inspection.
t
> Areas examined during the inspection included plant status, action on previous findings, 10 CFR Part 50.55(e) report followup, allegation followup (Unit 1),
. Inspection and Enforcement Bulletin followup, preservice inspection (Unit 1),
j and plant tours. Within these areas, the inspection consisted of selected examination of procedures and representative records, interviews with personnel, and observations by the inspectors. The inspection findings are documented in the enclosed inspection report.
! Within the scope of the inspection, no violations or deviations were identified.
' In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure will be placed in the NRC Public Document Room unless you notify this office, f by telephone, within 10 days of the date of this letter, and submit written application to withhold information contained therein within 30 days of the date of this letter. Such application must be consistent with the requirements
- of 2.790(b)(1). -
RPSB/2h TF h TF '5b F W OS&
WFSmith/1h OMHunnicut WCSefdle TFWesterman RL angar RPDenise
[a/11/84 [r/11/84 {(/d/84 / /84 k/S(/84 h/g\/84 p i d'A'84b fr0\g-85-59 mm . - - . . ._
Ml
Texas Utilities Electric Company Should you have any questions concerning this inspection, we will be pleased to discuss them with you.
Sincerely.
. . : '. C . *
.;- . bL_,u. ;
Richard L. Bangart, Director Region IV Comanche Peak Task Force
Enclosure:
Appendix - NRC Inspection Report 50-445/84-12 -
50-446/84-06 cc w/ enclosure:
4 Texas Utilities Electric Company .
ATTN: H. C. Schmidt, Manager Nuclear Services Skyway Tower 400 North Olive Street Lock Box 81 Dallas, Texas 75201 Texas Utilities Electric Company ATTN: B. R. Clements, Vice President, Nuclear Skyway Tower 400 North Olive Street Lock Box 81
. Dallas, Texas 75201 bec to DMS (IE01) bec distrib. by RIV:
RPB1 Resident Inspector-Ops RPB2 Resident Inspector-Cons TPS R. Bangart, D/TF J. Collins, RA W. Seidle, DD/TF R. Denise 0/RRP&EP T. Ippolito, NRR S. Treby, ELD D. Hunnicutt, TF MIS SYSTEM T. Westerman, EO RIV File J, Gagitardo.(CPSES)
TEXAS STATE DEPT. OF HEALTH Juanita Ellis Renea Hicks Billie P. Garde TRT (2) (CPSES)
- _ _ m. . m .__m - , , _ _ . ~ . , - - ._ ._ . .., --
l APPENDIX U. S. NUCLEAR REGULATORY COMMISSION REGION IV NRC Inspection Report: 50-445/84-12 Construction Permits: CPPR-126 50-446/84-06 CPPR-127 Dockets: 50-445; 50-446 Licensee: Texas Utilities Electric Company (TUEC) ,
Skyway Tower .
400 North Olive Street !
Lock Box 81 Dallas, Texas 75201 .
Facility Name: Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 Inspection at: Glen Rose, Texas Inspection Conducted: March 20, 1984, through May 18, 1984 Inspeckors d!.2 /!8 f f J. E. Cummins, Senior Resident Inspector ' Datef Construction (paragraphs 1, 2, 4, 7, 8, and 9) 1 4 hr JL ='M 4A2//89 W. M. McNeill, Reactor Inspector, Dite /
Project Section A (paragraph 6) f b 9n J Q 2 W.u/8y
'Date /
D. P. Tomlinson., Senior Resident Inspector South Texas Project (paragraph 6) b 9x M +
D. M Hunnicutt, Team Leader, Region IV c/u/gy 0' ate '
Task Force (paragraphs 1, 3, 4, 5, 7, and 9)
M yrwMJWW"' '
2-Inspection Summary Inspection Conducted March 20, 1984, throuch May 18, 1984 (Report: 50-445/84-12)
Areas Inspected: Routine, announced inspection of plant status, licensee action on previous findings, 10 CFR 50.55(e) report followup, allegation followup, Inspection and Enforcement Bulletin followup, and plant tours. The inspection involved 170 inspector-hours onsite by four NRC inspectors.
Results: Within the six areas inspected, no violations or deviations were identi fied.
Inspect,fon Summary -
Inspection Conducted March 20, 1984, throuch May 18, 1984 (Report: 50-446/84-06)
Areas Inspected: Routine, announced inspection of plant status, licensee '
action on previous findings, 10 CFR 50.55(e) report followup, Inspection and Enforcement Bulletin followup, and plant tours. The inspection involved 26 inspector-hours onsite by two NRC inspectors.
Results: Within the five areas inspected, no violations or deviations were identified.
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DETAILS SECTION
- 1. Persons Contacted .
"J.T. Merritt, Assistant Project General Manager, Texas Utilities Generating Company (TUGCO)
H. Hutchinson, Project Control Manager, B&R
'. G. L. Morris, Site Mechanical Level III ASME Quality
- Engineer, B&R ~
+
- F. L. Powers, Electrical / Control Building Manager, TUGC0
.i S. Spencer, QA Auditor (Corporate Office), TUGC0 J. Marshall, Licensing Supervisor (Corporate Office), TUGC0 M. Riggs, Operations Support Engineer, TUGC0 -
- T. Taylor, Engineer, Battelle Pacific Northwest Laboratories
! K..V. Cook, Research and Development Engineer, Oakridge
! National Laboratory l
J. Enriotto, Manager, Material Technology, Westinghouse j 0. Adaomis, Senior Engineer, Westinghouse R. Dacko, Licensing Engineer, TUGC0 J. Keller, Field Engineer, TUGC0 _ _
- The NRC inspectors also contacted other plant personnel including members l
of the construction, operations, technical, quality assurance, and
! administrative staffs.
!
- Denotes those attending one or more exit interviews.
- 2. Plant Status Construction of Unit 1 is approximately 97% complete with fuel loading scheduled for the end of September 1984. The licensee continues to 4
complete and turnover systems and areas from construction to operations.
The turnover process is accomplished in two phases. The first phase takes place when construction completes a system or area and turns that .
system or area o er to the startup group. The turnover process is I
completed for a system or area when operations makes final acceptance of the system or area from the startup group. .The table below indicates the status, as of April 27, 1984, of the 423 distinct areas identified by the licensee for turnover from construction to operations:
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f Total number of areas 423 l l
Number. of areas submitted to startup 226 Number of areas accepted by startup 199 Number of areas submitted to operations 116 Numbers of areas accepted by operations 82 The table below indicates the status, as of April 27, 1984, of the 332 distinct subsystems identified by the licensee for turnover from
~
construction to operations: +
Total number of subsystems 332 Nunber of subsystems submitted to startup . 314 -
Number of subsystems accepted by startup 313 Number of subsystems submitted to 57 operations Number of subsystems accepted by operation 27 Construction of Unit 2 is approximately 65% complete with fuel loading scheduled for March 1986.
- 3. Licensee Action on Previous Inspection Findings (Closed) Severity Level V Violation 445/8324-01 and 446/8315-01:
Failure to Provide Adequate Procedures, Instructions, or Drawing for Installation of Najor Items of Equipment The NRC inspector reviewed the licensee's stated corrective actions by reviewing and evaluating the following licensee procedures:
- QI-QAP 11.1-39, " Mechanical Equipment Installation Inspection", Rev. O, dated February 2, 1983
- CP-QAP-12.1, " Inspection Criteria and Documentation Requirements Prior to System N-5 Certification," Rev. 8, dated August 3,1983 The NRC inspector's review determined that the specification and the construction installation procedures for mechanical equipment installation were revised by requiring that the engineer specify the requirement for w - c , --~-,
m---
kN-W safety-related mechanical equipment. A reinspection program has been instituted to verify mounting details on safety-related mechanical equipment by requiring an additional step in the inspection walkdown and maintaining an appropriate checklist. Licensee has completed reinspection, walked down systems, and checked "as built" conditions. The Master Data Base is up to date.
4 The NRC inspector verified that the licensee's corrective actions as stated in their response dated June 28, 1983, have been adequately implemented.
(Closed) Severity Level V Violation 445/8324-02 and 446/8315-02: Failure
' to Provide Adequate Maintenance of Materials and Equipment in Outdoor Warehouse Areas ,
The NRC inspector reviewed the licensee's stated corrective actions by reviewing and evaluating the following licensee procedures:
- QI-QAP-11.1-26, "ASME Pipe Fabrication and Installation Inspections," .
Rev. 11, dated March 18, 1983 '
.i l t ,
- QI-QAP-11-28, " Installation Inspectior.s of ASME Component Supports, Class 1, 2 and 3," Rev. 8, dated January 15, 1982
- QI-QAP-11.1-28A, " Installation Inspections of ASME Class 1, 2, and 3 4 - ' Snubbers'," Rev. 2, dated April 28, 1983
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- CP-QAP-16.1, " Control of Nonconforming Items" p
- QI-QAP-2.1-5, " Training and Certification of Mechanical Inspection Personnel" 4
[
The NRC inspector determined that QC inspection instructions have been y
revised to specifically address the verification of material conditions l
of items prior to installation and that storage conditions preclude
[
deterioration of materials and equipment. Outside storage is monitored
) on a periodic basis by QA to determine the adequacy of storage and a it preservation program has been established to clean, preserve, and/or 4 paint any items showing signs of dirt or corrosion. The licensee has
- prepared a standard warehouse procedure that addresses storage requirements and conditions.
9
[
The NRC inspector verified that the licensee's corrective actions as stated in their response dated June 28, 1983, have been adequately implemented.
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E (Closed) Unresolved Item (445/8214-02): Review of Licensee's Method of
[ Inspection of Skewed Welds, Dated November 8,1982 j
An allegation that the licensee's QC inspection procedure for welding did
[ not contain written instructions for examining skewed fillet welds was s
reviewed. (NOTE: Skewed welds are defined as those welds joining two l
structural members that are not in the same plane and are not perpendicular L '
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to each other. A typical example is two members jointed at an angle of ,
45 degrees with a weld at the joint toe of 135 degrees and another weld at the heel at a 45 degrees angle).
The NRC inspector completed a detailed review and evaluation of four procedures and the results of the licensee's reinspection efforts for skewed fillet welds. Procedures reviewed are listed below:
l'
- QI-QAP-11.1-26, Revision 15 "ASME Pipe Fabrication and Installation Inspections and Requirements Prior to System / Subsystem N-5
- Certification"
- QI-QAP-11.1-28, Revision 24, " Fabrication and Installation Inspection of Safety Class Component Supports" #
- QI-QAP-11.21-1, Revision 6, " Requirements for Visual Weld Inspection"
- CP-QAP-16.1, Revision 20 " Control of Nonconforming Items" .
The NRC inspector reviewed licensee / contractor records for 27 of the 640 supports with skewed fillet welds. The records were reviewed primar'ily i for final as-built configuration and the results of the licensee's reinspection effort. The licensee originally committed to a reinspection of randomly selected skewed fillet welds with selection based upon statistical sampling techniques (reference: Inspection Report 50-445/82-14, paragraph 4). However, the licensee performed a 100% reinspection of the 640 affected supports with skewed fillet welds, rather than a randomly selected statistical technique. The NRC inspectors reviewed the licensee's drawings to determine the extent of inspection requirements for supports with skewed fillet welds. The NRC inspector's review and evaluation determined that the licensee's reinspection did not identify any skewed fillet welds that were undersized or otherwise did not meet appropriate requirements. No nonconformance reports (NCRs) were issued by the licensee or contractor during or as a result of the reinspection effort.
The NRC inspector performed visual inspection of the following Unit 1 supports and found no undersized skewed fillet welds:
, RC-1-099-001-C86R RC-1-101-002-C86K l RC-1-115-020-C66A RC-1-115-025-C66K DD-1-109-035-C46R VO-1-148-001-C46R SF-1-022-005-C46R SF-X-135-700-A35R CA-1-028-021-C46R CH-1-005-005-C86R No violations or deviations were identified.
(Closed) Severity Level IV Violation 445/8324-03 and 446/8315-03:
Failure to Remove Obsolete Drawings from Construction Work Areas f
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I-The NRC inspector reviewed the improved process for reproducing drawings and determined that the new process results in an improved drawing, both i
! in quality and legibil.ity. The drawings reviewed are current and no out-of-date drawings were located in the work areas. The licensee's 1 " Satellite" system for Unit 1 is complete and operational. This system is composed of four separate " Satellite" areas. The licensee is approxi-mately 98% complete on a fifth " Satellite" area that is designated for Unit 2. From this review, the NRC inspector concluded that the four
" Satellite" areas meet FSAR Section 17, paragraph 17.1.6 and B&R Procedure DCP-3, "CPSES Document Control Program," requiremen,ts.
The NRC inspector verified that the licensee's corrective actions as stated in their response dated June 28, 1983, have been adequately impiesented.
+
- 4. 10 CFR 50.55(e) Report Followup and Evaluation The NRC Inspectors conducted a review of 26 licensee reported potential 10 CFR Part 50.55(e) packages. Of these 26 reports, 10 were found to not '
require a report (nonreportable) and the other 16 required the licenseeThe to submit a report in accordance with 10 CFR Part 50.55(e) requirements.
j licensee refers to 10 CFR 50.55(e) reports as "Significant Deficiency t
Analysis Reports" (SDARs). The licensee's SDARs were reviewed for content, I compliance with NRC requi'ementsr for reporting, corrective actions,-
appropriate evaluation, timeliness of reporting, and completion of documentation. The following 26 CFR Part 50.55(e) reports (SDARs) and f related licensee documentation were reviewed by the NRC inspectors, were found to meet the requirements, and were closed:
i Licensee Evaluation Licensee 50.55(e) Date or Reportable (R) or Letter Not Reportable (NR) Closed Number 50AR Subject CP-81-01 Ceilcote 658-N Epoxy NR 2/17/81 TXX3279 Testing and Calcula- ,
! tions for " Compressive Strength of Epoxy Grout"
}
) 3/18/82 TXX3495 CP-82-A Installed Borg Warner R L
Valves (Containment
' Spray Valves) 5/28/82 TXX3523 CP-82-02 Design of Horizontal R Fire Dampers CP-82-06 Unit 2 Emergency Diesel R 1/10/84 TXX4095 (EDG) Generator Auxiliary Skid
(
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Licensee Evaluation Licensee 50.55(e) Reportable (R) or Date Letter or Not Reportable (NR) Closed Number SDAR Subject R 1/30/84 TXX4101 CP-82-15 Defective Piston Skirt Castings for Unit 2 EDG R 9/7/83 TXX4043 CP-83-01 Borg Warner Valves (check valves - disen-gaged parts)
CP-83-10 Letdown Heat Exchanger R 7/7/83 TXX4001 Anchors (mounting conff- .
guration) Z R 7/12/83 TXX4005 CP-83-15 Cable Tray Clamps (mild steel bolting acceptable)
CP-83-17 Inadequate Overpressure R 8/9/63 TXX4023 Protection for Spent Fuel ,
Pool Cooling Hx Components Cooling Water (relief valves incorrectly set) 8/6/80 TXX3173
- CP-79-09 Installation of Major R Conduit Supports Without Senefit of an Approved Instruction, Procedure or Drawing R 9/26/83 TXX4054 CP-83-18 Containment Building l Cooling (neutron detector t
' well Reactor Cavity Cool-ing System)
R 12/28/83 TXX4091 CP-83-21 Transmitter Calibrations f (excessive errors due to
! calibration techniques corrected) ,
HR 2/28/83 TXX3635 CP-83-04 Potential Defect of Radiation Monitoring System I TXX4016 R 7/29/83
{ CP-83-06 Vendor Installed HVAC System l
i R 5/31/83 TXX3677 l CP-83-07 New Fuel Storage Racks l
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!io.55(e) Licensee Evaluation Licensee or Repcrtable (R) or Date Letter SDAR Subject Not Reportable (NR) Closed Number CP-83-08 Control Valve Brackets R 4/21/83 TXX3657 Unqualified Valve Attachments CP-83-12 Class 1 Material NR 6/21/83 TXX3691
. Deficiencies (NDE I specified was not performed) l CP-83-13 Strut Jamming Devices NR 6/21/83 TXX36692 ~
f (jam nuts on rigid struts)
CP-83-14 (W) Loop Power Supply NR 6/21/83 TXX3693 -
(NLP) Printed Circuit Cards - no cards of type with defects found at CP CP-83-16 Welded Attachments to NR 7/20/83 TXX4012 Piping After Hydrostatic
- Testing _
CP-83-19 Service Water System NR 10/17/83 TXX4064 Valves (safety function not adversely affected)
CP-83-22 Chlorine Detection and R 1/18/84 TXX4098 Control Room HVAC (not per NRC Regulation and
. FSAR)
CP-84-07 Deficient Lug Crimping R 3/29/84 TXX4139 CP-82-05 Concrete Void in Unit 1 R 8/24/82 TXX3561 Steam Generator Compart-ment #2 Exterior Wall CP-82-01 Material Procured by NR 2/19/82 TXX3480 AFC0 Steel CP-82-08 Defective Limitorque NR 10/12/82 TXX3580 Pinion Keys ,
The above 10 CFR Part 50.55(e) reports are closed.
No violations or deviations were identified.
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Selected NRC inspector observations of licensee reported items (10 CFR Part 50.55(e)) that the licensee is presently investigating or performing corrective a'ction on are discussed below:
- a. Rodent Damaae to Class IE Electrical and Control Cables k
The licensee verbally reported damage to electrical and control cables between the Service Water Intake Structure (SWIS) and the safeguards building to the NRC and subsequently documented the information in SDAR CR-84-10.
' The NRC inspectors observed portions of the licensee's inspection, corrective actions, and repulling of repaired cables or replacement of electrical and control cables at the SWIS and manholes MH 1A1 and f MH 1A2 locations. The licensee removed all 28 cables (24 control cables and 4 instrumentation cables) in the Orange (A) Train. The l
licensee found considerable rodent damage to the insulation on several -
of these Instrument and Control (I&C) cablas, and replaced each of the 28 I&C cables with new cable. The licensee pulled each of the nino I
480V AC electrical cables out of the conduit and raceways; visual inspection identified some minor surface damage caused by rodents on i two of these cables. The licensee repaired each surface damaged area and returned the cables to their original locations. The licensee performed visual inspections, meggered each of the 3 cables for the 6.9KV AC circuit, performed high voltage (hi pot) testing on each cable, and determined that the 649KV circuit was satisfactory.
Licensee end NRC inspectors determined that the major rodent damage occurred near the junction of conduit C-130 01711 and junction box JBIM-2070 and between manhole E1A2 and E1A1 and safeguard cable c
A4009242A. Inspections of junction box JBIM-2060 and conduits C-12005538, C-1205539, and C-12001693 in the SWIS were also performed by the licensee and NRC inspectors.
The licensee issued the following NCRs as a result of the rodent damage to electrical and control cables in the Orange (A) Train:
E-84-00954, Rev. 3 E-84-00962, Rev. 1 E-84-00974, Re'v. 2 E-84-00975, Rev. 1 E-84-01309, Rev. O Prior to reinsta11ation af the cables, each conduit was cleaned and no evidence of rodents was found. The licensee has completed replacement, repairs, repulling, and testing of the above cables.
The licensee included the following preventive measures to assure the integrity of the cables:
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< (1) All areas adjacent to manholes were baited with rat poison.
(2) All conduit openings in the manholes are covered with temporary protective covering to preclude rodent entry.
Permanent coverings are to be installed as specified in Design Change Authorization (DCA) 20397.
(3) All conduit openings at the entrance or exit of the ductwork have been sealed with elastomer caulk or firestop foam. ,
The licensee investigated the Green (B) Train cables between the SWIS and the safeguards building to assure that the integrity of this .
The Itcensee personnel pulled oversized train could be verified. The NRC inspectors observed j cloth swabs through each conduit. ~ >
portions of this swabbing from both the SWIS and the manhole l
' entrances. Possible rodent entry was identified in one conduit.
The licensee removed the 28 (24 control and 4 instrumentation) .
cables from the ductwork as required by NCR E-84-01434.
The licensee inspected these cables and determined that The two ifcensee active cables and one spare cable had sustained minor damage.
The NRC inspectors observed portions of repaired the minor damage. The licensee the inspection and repair in the Green (B) Train.
reinstalled the 28 cables and initiated the preventive measures stated above for the Orange (A) Train.
No violations or deviations were identified.
- b. Thermo-lao Installation
' On May 2,1984, the licensee verbally reported to the NRC, that contrary to CPSES construction procedures, construction debris in the form of scraps of thermo-lag material was found lying loose in electrical cable trays.
The licensee subsequently documented this Prefabricated sections of thermo-lag incident in SDAR CP-84-11.
material are being installed around electrical cable trays for fire protection. The strips of thermo-lag material had apparently been placed inside the cable trays to support the prefabricatedWhen sections the, of thermo-lag that were installed over the cable trays.
problem was discovered, the licensee stopped the installation of the thermo-lag and evaluated the problem. The licensee's corrective action included the retraining of individuals involved in the installation of thermo-lag, the reinspection of cable trays 24 inches wide and larger that had already had the thermo-lag installed, and additional quality control inspection of cable trays immediately prior to sealing the prefabricated sections of thermo-lag.
No violation or deviations were identified.
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- 5. Followup of A11ecation concerning Bolts for Steam Generator (SG) Upper Lateral Supports .
An allegation was received in the Region IV office that some bolts holding ,
the SG laterial supports to the wall plates had been cut off and, therefore, were incapable of securing the SG 1ateral supports to the imbedmont plates in accordance with design requirements.
A review by the NRC inspector of the materials, drawings, specification, purchase orders, travellers, material received records, and related records documents indicated that the licensee purchased 144 A540GT B23 Class 4 2-1/2-inch diameter bolta 9 inches in length. The licensee purchased these 144 bolts 1-1/2 inches too long and then cut each of these bolts to 7-1/2-inch length to meet delivery and scheduling requirements. The rework ~
p (cutting 1-1/2 inches off the 9-inch length of each bolt) was authorized by the licensee and is documented in work package MR8-0550-013-RB.
The licensee did cut 1-1/2 inches off each bolt; therefore, in substance, .
this allegation was substantiated. However, there is no technical merit nor safety cor.cern related to cutting 1-1/2 inches off the length of each bc1t.
The original design required hex head bolts 7-1/2 inches in length and 2-1/2 inches in diameter.
The NRC inspector reviewed the following documents related to the above information:
- G&H Drawing 2323-17. Rev. 1
- AFC0 Steel Drawing 303
- Purchase Order (PO) 35-1195-14915 C07
- Material Received Records (MRR) 060860, 61000, and 611$0
- Material Test Reports (MTRs) for Charpy Impact, Tensile Strength, -
Chemical Analysis, Heat Treatment, and Magnaflux Testing
- Receiving Inspection Reports (RIR) 6008, 6256, and 6428 No violations or deviations were identfied.
- 6. Preservice Inspection - Unit 1 ,
A previous NRC inspection (50-445/82-19) reported witnessing of preservice .
ultrasonic inspection of Unit l's reactor c:olant system piping. It was noted in the above report that: (1) adequate penetration of the longi-
- tudinal wave was not achieved as evidenced by the sporadic loss of back '
reflection and (2) a full volumetric examination was not achieved as evidenced by the saturation of the cathode ray display screen such that .
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indications in the outer half of the pipe thickness could not be identified by the refracted longitudinal wave. A demonstration by Westinghouse was requested by the NRC Division of Licensing based on recently reported successful ultrasonic inspections at the Callaway and Wolf Creek sites.
The demonstration was requested to establish if these improvements in the ultrasonic testing instrumentation could result in a successful ultrasonic inspection at CPSES, Unit 1.
On. March 20 and 21, .1984, the confirmatory demonstration ultrasonic inspection.was performed at CPSES, Unit 1 by Westinghouse. The demonstra-tion was witnessed by NRC inspectors and their consultants (Oak Ridge and Pacific Northwest Labs). The inspection was performed by Westinghouse Level II and III personnel (qualified to SNT-TC-1A) to Procedure ISI-206, Revision 0, " Manual Ultrasonic Examination of Welds." The demonstration f included a longitudinal wave and a refracted (41 degrees) longitudinal wave of weld joint numbered 13 on Isometric Drawing T8X-1-4200 of Unit 1 and several weld joints; i.e., 27 and 29 of Unit 2. .
The demonstration confirmed the previous NRC observations in regard to Unit 1. On weld number 13, only a sporadic back reflection could be achieved from the longitudinal wave. With the refracted longitudinal wave, considerable saturation was observed, approximately one-half the material thickness. On Unit 2, a consistent back reflection from the longitudinal wave was observed which indicated adequate penetration. After searching for a counter bore on the inside diameter of four different joints, one joint was found which consistently showed the counterbore by the refracted longitudinal wave. The saturation of the screen was less however, abaut 1/4 of the thickness near the outside diameter still could not be 'nspected.
It was noted that the procedure, equipment, and some of the personnel were the same as previously used in the 1982 preservice inspection.
The differences found between Units 1 and 2 could be accounted for by the observed differences in surface finish condition and preservice inspection weld preparation. The chemical composition of the heats, grain size, and other geometrical factors could not be visually determined, but could have j
been significant contributors to the ultrasonic differences observed during the demonstration.
- 7. Plant Tours -
At various times during the inspection period, the NRC inspector conducted general tours of the reactor building, fuel building, safeguards building, electrical and control building, and the turbine building. During the tours, the NRC inspector observed housekeeping practices, preventive maintenance on installed equipment, ongoing construction work, and discussed various subjects with personnel engaged in work activities.
No violations or deviations were identified.
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- 8. Inspection and Enforcement Bulletin (IEB) Followup 4
The NRC inspector reviewed the licensee's IEB files for selected IEBs to
- verify that the licensee had conducted an adequate review of each IEB to
. determine its applicability to the CPSES facility and that the licensee had taken appropriate action when the IEB was applicable. Through discussions with licensee representatives and reviewing records, the NRC l inspector was able to determine that the licensee had satisfactorily l responded to the IEBs listed below. These IEBs are closed.
Licensee Closure IEB No. Title Letter No./Date
! 78-05 Malfunctions of Circuit Breaker TXX2908/11-16-78 j l Auxiliary Contact Mechanism Model CR 105X 78-06 Defective Cutler Hammer, Type M TXX2959/02-19-79
. Relays with DC Coils TXX2869/08-04-78
~
78-10 Bergen-Patterson Hydraulic TXX2894/10-19-78
- Shock Suppressor Accumulator Spring coils
[ 79-03 Longitudinal Weld Defects in TXX2983/05-01-79 and ASME SA-312 Type 30455 TXX3204/10-07-80
(79-03A Pipe Spools Mfg. by Youngstown
- Welding and Engineering Co. .
f 79-04 Incorrect Weights for Swing TXX3000/06-14-79 Check Valves Manufactured by TXX2989/05-23-79 l Velan Engineering Co.
t 79-09 Failures of G.E. Type AK-2 TXX2988/05-22-79 j Circuit Breakers in Safety-i Related Systems 1
79-11 Faulty Overcurrent Trip TXX3013/07-16-79
- Device in Circuit Breakers for Engineered Safety Systems
[
l 79-23 Potential Failure of Emergency TXX3056/10-17-79 l DG Field Exciter Transformer .
l 79-25 Failures of Westinghouse BFD TXX3191/09-08-80 ,
i Relays in Safety Related Systems i
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4 Licensee Closure 4 IES No. Title Letter No./Date i
80-16 Potential Misapplication of TXX3172/08-08-80 Rosemount, Inc. Models 1151 and 1152 Pressure Transmitters with "A" or "D" Output Codes l
j 80-21 Valve tokes Supplied by Malcolm TXX3250/12-22-80
( Foundry Co.. Inc.
I 80-23 Failures of Solenoid Valves TXX3246/12-17-80 Manufactured by Valcor Engineering Corp. I 1 80-19 Failures of Mercury-Wetted TXX3189/09-08-80 l
Matrix Relays in Reactor Protective Systems of Operating Nuclear Power Plants Designed by CE 80-04 Deficiencies in Primary Con- TXX36687/06-14-83 i tainment Electrical Penetration Assemblies
~
NRC inspector observations of activities related to IEB 82-04 are discussed ~
4 below:
IEB 82-04 licensee action item 1.a required the licensee to inspect all supplier provided electrical penetration terminal boxes and verify that the conductor terminations were satisfactory. The licensee determined that there were 4 supplier provided penetrations (IE80 IE81, 2E80, and 2E81) with y attached terminal boxes involved each with 8 terminations for a total of 32 terminations. Due to the small number of terminations involved, the l
licensee replaced all 32 lugs in these boxes which had previously been terminated by the supplier.
IE8 82-04 licensee action item 1.b required the licensee to inspect electrical penetration conductors as they enter and exit penetration modules and verify the , integrity of the insulation around the conductors.
The licensee inspected all of the accessible conductors on safety-related e penetrations for L' nits 1 and 2. At the time of the licensee's Y inspection, the Unit 2 safety-related penetrations were stored in a warehouse and the Unit 1 safety-related penetrations were installed in j the plant. The ifcensee's inspection included all of the Unit 2
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safety-related penetration conductors and all of the Unit I safety-related penetration conductors where these penetration conductors enter / exit the penetration modules on the reactor building end of the penetrations. Tne licensee's inspection verified the integrity of the insulation around the conductors. The Unit 1 penetration conductors on the end of the penetra-
- tion located outside of the reactor building were not accessible. The licensee's inspections were documented by quality control personnel.
IE8 82-04 licensee action item 1.c required the licensee to conduct detailed examinations of all supplier provided in-line butt splices having a wire size of #2 AWG and smaller, and to ascertain acceptability of these connections. The licensee inspected a random sample of the vendor provided in-line butt splices. The sample size was a minimum of 25% of the total number of vendor supplied in-line butt splices for each size conductor. In j addition to the inspection of butt splices, the licensee selected a 10%
random sample of the in-line butt splices, inspected and performed a pull test on them. The in-line butt splices for all wire sizes except #2 AWG passed the pull test. Due to the failure of the #2 AWG conductor in-line butt splices to pass the pull test, the licensee is replacing all #2 AWG in-line butt splices on safety-related penetrations.
The NRC inspector performed the following inspection activities to verify that the licensee's response and corrective action fulfilled the requirements of IEB 82-04:
- a. Reviewed the licensee's sample size and found that it met or exceeded the minimum required by Section 2.b of IES 82-04.
- b. Reviewed licensee's documentation and connector vendor (Amp Incorporated) catalogs.
- c. Inspected a random sample of licensee installed connectors and verified that the connectors were installed properly. The connectors and crimping tool were as specified by the connector vendor. The crimping tool was calibrated (the calibration included the performance of a pull test on a similarly installed sample connection).
- d. Inspected the conductor insulation of a random sample of conductors at the point where the conductors exited / entered the epoxy of the penetration feed thru modules.
Selected portions of the accessible conductors on the safety-related i . penetrations listed below were inspected:
- Unit 1 (penetrations installed) IE6, IE9, IE10, IE11 IE12,.IE13, IE15 IE16, IE17, IE47 IE39, IE56, IE60, IE64, IE62, AND IE63.
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- Unit 2 (penetratione stored in warehouse) 2E12, 2E13, 2E18, 2E40, 2E56, 2E57, 2E58, 2E59, 2E62, 2E64, 2E76, 2E77, 2E78, 2E79, 2E80, AND 2E81.
Selected NRC inspector findings are discussed below:
- a. In attachment 2 to enclosure 1 of licensee's response letter TXX-3687 4
dated June 14, 1983, the licensee incorrectly listed penetrations 2E78 and 2E79 as the penetrations inspected for #12 AWG conductors.
The penetrations actually inspected were 2E76 and 2E77 and the licensee's documentation confirm these inspections. .
- b. During the manufacturing process, a piece of sleeving was placed over some of the conductors on the section of conductor that is embedded j in epoxy. This sleeving extends approximately 2" on either side of j the epoxy. This sleeving in some cases is cracked at the juncture of the sleeving and the epoxy. The conductor insulation inside the sleeving was intact in all except one instance observed by the NRC inspector. This instance was on conductor E3 of penetration IE10.
This conductor had insulation damage; however, this damaged conductor had been identified by the licensee, and the licensee had issued revision 4 to sheet 10A of drawing 2323-EI-0511 which class.ified this lead and two adjacent leads as damaged.
- c. During-the licensee's inspection of the in-line butt splices, the il licensee found that the vendor had failed to crimp one end of a splicing lug on lead E6 of penetration 2E-58. This condition was
!' documented on licensee's traveler No. EE83-0136-9301 and corrective
} action (splicing lug to be replaced) delineated on nonconformance i report E83-00424. This failure of the vendor to crimp the lug was i not interpreted by the cognizant licensee representative as being an y under crimped condition and, therefore, this instance was not identified in the licensee's response to IEB 82-04. The licensee inspected 424 conductor splices and tniu is the only crimp that was j identified as not being made. The Unit 1 penetrations are installed i with most of the related work being completed on them. The NRC inspector did not find any evidence of conductor deterioration or damages that would make the integrity of the Unit 1 penetrations questionable.
- The licensee is still performing work on the Unit 2 penetrations. Some of fp the work being performed is restoration from the inspection, testing, and 2 corrective action related to IEB 82-04. The NRC inspector will monitor selected portions of this work and also the installation of these penetrations.
1 .
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- 9. Exit Interviews The NRC inspectors met with meers of the TUEC staf f (denoted in paragraph 1) at various times during th* Course of the inspection.
The scope and findings of the inspection were discussed. The licensee acknowledged the NRC inspectors' statements.
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.c su avan m.AzA oRNE. SUM 1000 July 26, 1984 In Reply Refer To: -
Dockets: 50-445/84-08 50-446/84-04 Texas Utilities Electric Company ATTN: M. D. Spence, President. TUGC0 Skyway Tower 400 North Olive Street -
Lock Box 81 .
Dallas. Texas 75201 I Gentleme~: n This refers to the inspection conducted under the Resident Inspection Program by Messrs. J. E. Cumins W. F. Smith, L. E. Martin and C. R. Oberg of this office during ths period November 14,.1983, through March 31, 1984, of activities authorized by NRC Construction Permits CPPR-126 and CPPR-127 of the Comanche Peak facility, Units 1 and 2, and to the discussion of our findings with Mr. J. T. Merritt, and other members of your staff at the conclusion of the inspection.
Areas examined during the inspection included licensee action on previous findings,10 CFR Part 50.55(e) report followup,10 CFR Part 21 report follow-up, allegation followup (Un'it 1), independent inspection of coatings, tra.in-ing of protective coatings inspectors, review of safety-related systems (Unit 1), inventory of audit material in custody of NRC, and plant tours.
Within these areas, the inspection consisted of selective examination of pro-cedures and repmsentative records, interviews with personnel, and observa-tions by the inspectors. The inspection findings are documented in the enclosed inspection report.
During this inspection, it was found that certain of your activities were in violation of NRC requirements. Consequently,you are required to respond to this violation in writing, in accordance with the provisions of Section 2.201 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regula-tions. Your response should be' based on the specifics contained in the
( Notice of Violation enclosed with this letter.
During this inspection, it was found that certain of your activities appeared to deviate from a comitment made to the NRC. This item and reference to the comitment are identified in the enclosed Notice of Deviation. You are requested to respond to this deviation in writing.
Your response should be based on the specifics contained in the Notice i of Ceviation enclosed with this letter.
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! Company
! In accordance with 10 CFR 2.790(a), a copy of this letter and the i
enclosures will be placed in the NRC Public Document Room unless you notify this office, by telephone, within 10 days of the date of this letter, and submit written application to withhold infomation contained
- therein within 30 days of the data of this letter. Such application
- must be consistent with the requirements of 2.790(b)(1).
! The responses directed by this letter and the accompanying Notices are i not subject to the clearance procedures of the Office of Management and Budget as , required by the Paperwork Reduction Act of 1980 PL 96511.
l Should you have any questions concerning this inspection, we will be w l
- pleased to discuss them with you.
Sincerely.
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Richard L. Bangart, Di tor l . Region IV Task Force j
I
Enclosures:
] 1. Appendix A Notice of Violation 3
.i 2. Appendix B Notice of Deviation
- 3. Appendix C NRC Inspection Report -
li 50-445/84-08 n 50-446/84-04 cc w/ enc 1:
Texas Utilities Electric Company ~
} ATTN: H. C. Schmidt, Manager 1 Nuclear Services 3 Skyway Tower i 400 North Olive 5treet Lock Box 81 Dallas, Texas 75201 l
}
Texas Utilities Electric Company 0 ATTN: B. R. Clements, Vice President, Nuclear Skyway Tower 400 North Olive Street Lock Box 81 Dallas , Texas 75201 h
1 h - . . - _ _ _ _ _ _ _
O APPENDIX A NOTICE OF VIOLATION Texas Utilities Electric Company Docket: 50-445/84-08 Comanche Peak Steam Electric Construction Pamit: CPPR-126 Station (CPSES) Unit 1 Based on the results of an NRC inspection conducted during the period of i November 14, 1983, through March 31, 1984, and in accordance with the NRC :
Enforcement Policy (10 CFR Part 2, Appendix C), 49 FR 8583, dated March 8, 1984, i the following violations were identified: !
l A. Gaps on Unit 1 Polar Crane Bracket and Seismic Connections Exceed Desion Requirements i 10 CFR 50, Appendia 8. Criterion V requires that, " activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances ~ l and shall be accomplished in accordance with these instructions, procedures, or drawings." >
Design change Authorization 9872 required that all gaps on the Unit 1 .
polar crane bracket and seismic connections greater than 1/16 inch be shimed. .
Contrary to the above on February 13, 1984, the NRC inspector reviewed l the polar crane bracket and seismic connections listed below and I observed that there were unshimed gaps that exceeded 1/16 inch.
Connection location 1 on Girder (.looking Approximate Girder Number from inside containment) Gap 23 center 1/8" i 23 right 1/8" l 26 right 3/16" 20 center 5/32"
, 20 left 3/16" l 19 right 3/16" l 17 center 5/32" 16 right 1/8" ;
l This is a Severity Level IV Violation (Supplement 11.0) (.445/8408-01).
B. Failure to Perform Insoections of Installation Activities Related to )
Unit 1. Main Coolant System Crossover Leg Restraints Criterion X of Appendix B to 10 CFR Part 50 requires that inspections ;
of activities affecting quality shall be established and executed by or for the organizations performing the activity to verify confomance i with the documented instructions, procedures, and drawings for l accomplishing the activity. j l
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Texas Utilities Electric Company Quality Assurance Plan, in Section 10.0, requires that planned written inspection procedures be utilized. It further requires that inspection activities include the types of characteristics to be measured, the methods of examination, and the criteria.
Contrary to the above, it was determined that inspections were not made of the installations of the Unit 1 crossover leg restraints, nor were any documents requiring such an inspection issued. Specifically, the require-ments for installation, as specified in Gibbs & Hill Drawing 2323-51-0550, were not inspected and documented. The eight crossover restraints (2 per loop) are major components of the main coolant piping seismic restraints
- and support system.
L This is a Severity Level IV Violation. (Supplement II.0) (445/8408-02)
( .
Pursuant to the provisions of 10 CFR 2.201, Texas Utilities Electric Company is hereby required to submit to this office, within 30 days of the date of 1 the this Notice, corrective a written steps statement which have or explanation been taken in reply, and the results including:)
achieved; (2 c(or) rec-tive steps which will be taken to avoid further violations; and (3) the date ~
r when full compliance will be achieved. Consideration may be given to extend-ing your response time for good cause shown. _
Dated: July 26, 1984 _
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1 APPENDIX B NOTICE OF DEVIATION Texas Utilities Electric Company Docket: 50-445/84-08 Comanche Peak Steam Electric Construction Permit: CPPR-126 Station (CPSES) Unit 1 Based on the results of an NRC inspection conducted during the period of November 14, 1983, through~ March 31, 1984, and in accordance with the NRC enforce-ment Policy (10 CFR Part 2. Appendix C), 49 FR 8583, dated March 8,1984, the following deviation was identified:
Deviation from Desion Information for Installation of Seismic Category I/
Seismic Category II Structural Steel for the Bolted Connections Between i i
the W16x40 and the Wall on Platform OP-ll in the Pressurizer C-artment.
the intended objectives of ANSI N45.2.11." (Draft 2. Revision 2 -
May 1973) -
, Contrary to the above, the licensee did not incorporate the intended objectives of ANSI N45.2.11 into the design of certain personnel access platforms at CPSES. A review of the design documentation, including Gibbs and Hill Drawing 2323-51-0556, Revision 4, Design Change Authorization'(DCA) 9764, Revision 3, and DCA 1090, indicated that the above platfonn was originally i designed as nonsafety-related.
- 2. ANSI N45.2.11 (Draft 2, Revision 2 - May 1973), paragraph 3 requires that design input requirements be specified to the level of detail necessary to permit the design activity to be carried out in a correct manner and should include basic functions, loads, and physical interfaces. ANSI N45.2.11, paragraph 8, requires that design changes be subjected to design control measures comensurate with the above.
Contrary to the above, the design documentation was upgraded to Seismic Category II with the particular beams supporting safety-related instrument tubing for two channels of pressurizer level upgraded to Seismic Category I. DCA 1090 required that the bolted connections between the W16x40 and the wall be " hand tight only", but did not address any locking device or thread upset to prevent nut backoff.
I
- 3. AISC Manual for Steel Construction in the Specification for Design, Fabrication, and Erection of Structural Steel for Butiding in Section 1.23.5 addresses the need for tightening high strength bolted connections to prevent the nut from loosening and falling off.
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2 In deviation from the above, DCA 9764 upgraded the platform !
to Category I and changeout of material, but did not change the connection requirements specified in DCA 1090.
This is a deviation (445/8408-03).
Texas Utilities Electric Company is hereby requested to submit to this office within 30 days of the date' of this Notice of Deviation, a written statement or explanation in reply, including: (1) the corrective steps which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further deviation from connitments made to the Connission; and (3) the date when full compliance will be achieved. Consideratiorf may be given to extending #
your response time for good cause shown. ~
Dated: July 26, 1984 l
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APPENDIX C U. S. NUCLEAR REGULATORY COMiISSION REGION IV I
! NRC Inspection Report: 50-445/84-08 I 50-446/84-04 Dockets: 50-445; 50-446 Construction Permits: CPPR-126 CPPR-127 r
Licensee: Texas Utilities Electric Company (TUEC)
Skyway Tower 400 North Olive Street Lock Box 81 Dallas, Texas 75201 $
Facility Name: Comanlhe Peak Steam Electric Station (CPSES), Units 1 and 2 Inspection At: Glen Rose, Texas h
l Inspection Conducted: November 14, 1983 through Parch 31, 1984 k
Inspec rs:
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/ Date j (p. aragraphs E. Cummins, Senior Resident Inspector-Construction 1,2,3,5,6,7,8,9,10,13).
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W. F. Smith, Resident Inspector-Operations 4//O/Bf
/ Date
- (paragraphs 1, 4, 13) f L.1. Martin / Reactor . nspector, Engineering Section / pate -
(paragraphs 4,11,13)
- $f 3 C. R. Oberg, React g Inspector, Reactor Project Sec. A Date
! (paragraphs 1, 11, T3) i
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a4<.6v D. M; Hunnicutt', Chief, Rea or Pro 3ct Section A Date' (paragraphs 1, 3, 9, 13) 2 Approved:
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Date' fh l D. M. Aunnicutt, Chief, Reacto Frofect[Section A i
Inspection Sumary Inspection Conducted November 14. 1983 throuch March 31, 1984 (Report 50-445/84-08)-
l ~
Areas Inspected: Routine, announced inspection of licensee action on i previous f ndings,10 CFR Part 50.55(e) report followup,10 CFR Part 21 followup, allegation followup, independent inspection of coatings, training of protective coatings inspectors, review of safety-related systems, inventory of audit material in custody of NRC, plant status, and plant tours.
The inspection involved 190 inspector-hours onsite by five NRC inspectors.
Results: Within the ten areas inspected, two violations (gaps on Unit 1 1 polar crane bracket and seismic connections exceed dr. sign requirements, paragraph 3 and failure to perfom required inspections, paragraph 11) and one deviation (deviation from FSAR design requirement, paragraph 11) i were identified. .
- Inspection Sumary Inspection Conducted November 14, 1983 through March 31, 1984 (Report 50-446/84-04)
Areas Inspected: Routine, announced inspection of licensee action on previous findings, :,0 CFR Part 50.55(e) report followup,10 CFR Part 21 report follow-up, independent inspection of coatings, training of protective coatings inspectors, inventory of audit material in custody of NRC, and plant tours.
l The inspection involved 44 inspector-hours onsite by two NRC inspectors.
Results: Within the seven areas inspected, no violations or deviations were identified.
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I l 3 DETAILS
{ 1. Persons Contacted f Principal Licensee and Contractor Employees
- 8. R. Clements, Vice President, Nuclear Operations I *J. C. Kuykendall, Manager, Nuclear Operations l *J. T. Merritt Site Project Manager
- R. A. Jones, Manager, Plant Operations
- T. L. Gosdin, TUGC0 Public Infomation Coordinator
- R. T. Jenkins, Operations Support Superintendent
- M. McBay Engineering Manager, TUGCO Engineering and Construction (E&C)
- R. P. Baker Staff Engineering Manager, TUGC0 E&C $
J. Marshall, Licensing Supervisor (Corporate Office)
- D. E. Deviney, Operations QA Supervisor -
- T. P. Miller, Lead Startup Engineer. TUGC0
- C. H. Welch, QA Services Supervisor i
- H. A. Lancaster, Startup QA Specialist
- J. C. Smith, Cperations QA
- M. Riggs, Operations Support Engineer
- 8. C. Scott, QA Supervisor A.~ Vega, QA Services Supervisor R. Kissenger, Project Civil Engineer J. D. Hicks, Assistant Site QA Supervisor R. L. Moller, Westinghouse Site Prcject Mana .
G. Purdy, lite QA Manager Brown & Root (B&R)ger H. Hutchin;.on, Project Control Manager G. L. Morris Site Mech. Level III ASME Quality Engr., B&R The NRC inspectors also contacted other plant personnel including members i of the construction, operations, technical, quality assurance, and admin-istrative staffs.
- Denotes those attending one or more exit interviews.
- 2. Plant Status Construction of Unit 1 is approximately 97% canplete with fuel loading scheduled for July 1984. There is presently a great deal of effort to complete areas and then turn the completed areas over to Texas Utilities Generating Company (TUGCO) operations. The turnover process requires two phases. The first phase takes place when construction completes a specified area and turns that area over to the startup group. The second phase of the turnover process i.s when TUGC0 opera-tions completes final acceptance of the area from the startup group.
The licensee has identified 422 distinct areas which are to be turned over. As of March 9, 1984, 158 of these 422 areas had been turned 9
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over from construction to the startup group. TUGC0 operations has made final acceptance of 66 of the 422 areas. The 422 distinct areas identified by the licensee to be turned over vary greatly in J size and complexity; therefore, the number of areas turned over pro-vides an indicator that progress is being made, but to make a detemina-tion as to the degree of progress, the size and complexity of each area must be evaluated.
~
Construction of Unit 2 is approximately 65% complete. Fuel loading is scheduled for January 1986.
j 3. Licensee Action on Previous Inspection Findings
~
! a. (Closed) Violation (445/82-11): Failure to Perform Inspections of Installation Activities Related to Unit 1 Containment Polar Crane.
The licensee's Nonconfomance Report (NCR) M-82-00894 documents -
the above violation. The disposition of NCR M-82-00894 directed that the polar crane girder connection finger shims previously installed per DCA 9872 were to be remcved and inspected and any deviations from the requirements of DCA 9872 were to be identified to engineering for resolution. The licensee removed and inspected all of the finger shims associated with the Unit 1 polar crane bracket and seismic connections. During this inspection, any shim that did not meet the design requirements of OCA 9872 was replaced.
This included the replacement of ten finger shims that were found to have clipped fingers. Operational traveler CE-82-370-8104 was issued to accomplish and document the shim inspection and rework directed by NCR M-82-0094. Traveler CE-82-370-8104 also instructed that the new shims were to be installed per the requirements of DCA 9872. .
. The shim inspection and rework was inspected and documented by quality control (QC) inspectors on NCR M-82-00894. This NCR was 5 closed on January 24, 1983. The quality control inspection of
! the shim rework satisfies the requirements which were previously I
not met and which resulted in the original violation. This item is closed. However, the NRC inspector performed a random inspection of the polar crane girder connection shims and had the following two concerns:
(1) Design Change Authorization (DCA) 9872 required that all gaps greater than 1/16 inch be shimmed. In addition QC personnel verified that the gap for each polar crane girder connection was i
less than 1/16 inch and documented this on a shim documentation card which was attached to Traveler CE-82-370-8104. However, the NRC inspector observed that the following randomly selected j girder connections had gaps that exceeded 1/16 inch:
L
5 Connection Location !
on Girder (looking Approximate l Girder Number from inside containment) Gap 23 center 1/8" 23 right 1/8" 26 right 3/16" 20 center 5/32" 20 left 3/16" 19 right 3/16"
- 17. center 5/32" 16 right 1/8" This is an apparent violation (445/8408-01).
(2) CCA 9872 required that the shims be tack welded as shown on Gibbs and Hill sketch SK82032 (Sheet 3 of DCA 9872). General Note 4 of SK82032 states that shims in the seismic connection may be welded to either vertical plate; however, on the seismic connections for girders 18, 22, 26, and 27 the tack welds which welded the' shims together also tack welded the vertical plates together. This concern was discussed with licensee personnel. This is an unresolved item (445/8408-04).
- b. (Closed) Severity Level IV Violation 445/8323-02: Instructions.
The five jam nuts identified as being loose were reworked and verified by QC to be " snug tight." The inspection checklist of procedure l
CP-QAP-12.1 was revised so that jam nut tightness is verified.
( 4. 10 CFR Part 50.55(e) Report Followuo Inspection l The RRI (Operations) conducted a review of all reports made by the licensee pursuant to 10 CFR 50.55(e) since the CPSES construction pennit was issued on December 19, 1974. During the period between December 19, 1974, and February 17, 1984 NRC reading files showed that 103 reports were transmitted to the Connission. TUGC0 logs were in r
agreement. Of these, subsequent correspondence indicated that the l
licensee, upon further investigation, concluded that 57 reports did not meet the reporting criteria of 10 CFR 50.55(e) and thus were "not reportable." -
The balance of 4610 CFR 50.55(e) reports appear to be reportable except for three recent items, which were unoer investigation at the time of the inspection.
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- The RRI noted that 2610 CFR 50.55(e) reports had been closed by the '
1 licensee. However, the status report published weekly by the site QA secretary indicated that they were awaiting NRC action for closure.
, The licensee's representatives stated that the item would be closed
( and removed from the weekly report as soon as the SRRI (Construction) reviewed the records submitted to him and specifically addressed i each in an inspection report as satisfactorily closed. At the exit I
interview of March 2, 1984, the RRI pointed out that this is not a requirement of the NRC and as such the NRC should be removed from the status report as actionee for closure of each item. The records i submitted to the SRRI (Construction) should be retrieved and placed i in the appropriate licensee-controlled file, subject to future NRC
- l audits. During the exit interview the licensee stated that this ~
would be done.
- The RRI reviewed eight of the 10 CFR 50.55(e) report folders in detail. .
l The licensee refers to them as "Significant Deficiency Analysis Reports"
- (SOARS). Attributes evaluated included followup correspondence, depth -
! of investigation, and compliance with reporting requirements. The ~'
{ eight folders were numbered SDAR 81-07, 82-03,82-07, 82-09, 82-13,
- ' 82-14, 83-03, and 83-20. Half were ruled "non-reportable" by the licensee, and half were " reportable." The RRI did not observe any l deficiencies in any of the folders.
t In addition to reviewing specific SDAR records, the RRI reviewed the following applicable procedures: -
CP-EP-16.3 " Control of Reportable Deficiencies" DQP-CS-6 " Reporting of Significant Deficiencies"
' CP-QP-16.1 "Significant Construction Deficiencies" -
CP-QP-15.6 "SDAR Status Tracking" The above procedures appear to meet the requirements of 10 CFR 50.
! The condition and tracking of each of the SDAR packages substantiate this, i However, the RRI noted that the corporate office in Dallas, Texas, has one numbering system with their own log for 50AR's originated in the corporate office. The CPSES site QA office has another numbering system, with their own log, for SDAR's originated at the site. The corporate office tracks all 50AR's, but CPSES tracks only the 50AR's originated at the site. At the exit interview of March 2,1984, the RRI comented that Site status report addressees could be led into believing the site tracking system is complete when such is not necessarily the case.
( No violations or deviations were identified. I l
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- 5. Followup of Part 21 Report )
On February 3,1984, a licensee audit of one of it's suppliers, Gulfalloy.
Inc., identified an apparent falsification of inspector's eye examination records. This apparent falsification of records was reported to the NRC
, by Gulfalloy, Inc., in accordance with the reporting requirements of 10 CFR Part 21. The falsification of eye exam records occurred when the eye exam records ~from an eye exam given to three inspectors on November 13, 1980, were photocopied and the date changed so that it would appear that the three inspectors had also received eye exams on October 22, 1961. Additional eye exams were given to the inspectors on September 15, 1982, and again on January 16, 1984. The Gulfalloy, Inc., #
employee responsible for ensuring that the inspectors received the -
required eye exam was also responsible for reviewing material manufac-turers chemical and physical test results.
The NRC inspectors discussed this event with licensee personnel and were infonned that corrective action would include a review of the records of material received from Gulfalloy, Inc. The NRC inspector will continue to monitor the licensee's corrective action.
No violttions or deviations were identified.
- 6. Followup of A11ecation The following allegation was relayed from the NRC Region IV office to the
- NRC inspector for followup
- " Fork lift ran into guide rods by missile l shield. Rods were approximately 24" diameter stainless steel." Represen-tatives from the Office of Investigations interviewed the alleger in order to obtain more details regarding this allegation, but were unsuccessful in this effort.
l The NRC inspector was unable to identify an event that fit all* the specifics in the above allegation. As far as the NRC inspector could detemine from discussions with personnel familiar with work in the reactor building, fork lifts have not been used in the reactor building.
However, the following event could have been what was observed by the alleger:
l l On October 14,.1983, the refueling crane struck and bent a thermocouple l column. This incident and subsequent corrective action were documented I on Westinghouse Field Deficiency Report TBX-10285 and Brown and Root l NCR M-11438. The themocouple column that was bent is a long (approxi-i mately 17 feet) tube .that provides support for incore thermocouple i
tubing between the upper core internals and the reactor vessel head.
The lower end of the themocouple column is attacned to the upper core assembly.
- - - --.-,--,_-_n,- . . _ , - , . , . . , . , _ - _ , , , . - - - - - - , ,, ,__.-,--.,-.,-.,,..,,,.,,n._.-.,..,.,.
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8 The refueling crane is a bridge type crane that spans the refueling cavity.
At the time the incident took place, the upper core assembly was mounted i on extension legs and stored in its nonnal storage location in the re-fueling cavity. The extension legs elevated the upper end of the thermo-couple column high enough to place it in the path of the refueling crane.
The bent thermocouple was reported, evaluated, and straightened as reported in the two documents identified above. This allegation .is closed.
No violations or deviations were identified.
- 7. Independent Inspection of Coatinos -
3 Brookhaven National Laboratories (BNL) has'been contracted by the NRC to conduct an independent inspection of the CPSES protective coatings program and its implementation, and to investigate allegations of .
improprieties in the protective coatings area.
During this inspection period BNL inspectors performed three onsite inspec-tions at CPSES. -
2 The scope and findings of this ongoing inspection will be documented in a subsequent NRC report.
- 8. Trainino of Protective Coatinos Inspectors On March 8, 1984, the NRC inspector attended a training session given for i protective coatings quality control inspectors. The purpose of the training session was to review and discuss recent changes to protective coatings Procedure QI-QP-11.4-26 " Inspection of Steel Substrate, Sur- .
face Preparation, Primer Application, Primer Repair Seal and Finish i Coat Application and Repair". The lesson plan for the training session was followed and the attendees were allowed ample opportunity to discuss the topics covered.
No violations or deviations were identified.
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- 9. Inventory of Audit Material in Custody of NRC i
On March 9,1984, the NRC inspector took custody of a box containing file folders from the site quality assurance supervisor. The box of file folders had been collected by licensee personnel during an audit of quality control inspectors conducted on March 8, 1984. An NRC repre-sentative subsequently made an inventory of the contents of this box.
- 10. Plant Tours -
4 At various times during the inspection period, the NRC inspector conducted general tours of the reactor building, fuel butiding, safeguards building,
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9 electrical and control building, and the turbine building. During the tours the NRC inspector observed housekeeping practices, preventive maintenance on installed equipment, and ongoing construction work.
No violations or deviations were identified.
- 11. Review of Safety-Related Systems (Unit 1)
- a. Platfoms Inside Containment On December 14, 1983, the NRC inspector obsc ved loose bolted connections on platfom OP-11 in the pressurizer compartment. -
i Platfom OP-11 supports safety-related instrument tubing for two channels of pressurizer level on the under side of the platform. A review of the design documentation including Gibbs & Hill Drawing 2323-51-0556, Revision 4, DCA 9764, .
Revision 3, and DCA 1090 indicated that this platform was originally designed as nonsafety-related. It was upgraded .
i i to Seismic Category II with the particular beams in question l
being Seismic Category I as they were supporting safety-related i
instrument tubing for two channels of pressurizer level. OCA 1090
- required that the bolts be " hand tight only" to allow for lateral expansion of the platform, but it did not address any locking device or thread upset to prevent nut backoff. DCA 9764 upgraded the platform to Category I and changeout of material but did not change the connection requirements specified in DCA 1090. Subsequent to identification of this problem l
I by the NRC inspector, a DCA was initiated requiring the use of l jam nuts or upset threads to correct this problem with the platforms shown on G&H Drawing 2323-S1-0556. The NRC inspector advised the licensee that DCA 1090 affected more than one drawing and that engineering would have to look at all similar connections j for general application and corrective action.
1 This is a deviation (445/8408-03).
- b. Main Coolant loco Restraints l During an inspection inside containment, Unit 1, the crossover leg restraints of main coolant loop No. I were examined for con-formance to applicable drawings for materials, construction, and installation. Materials and welding were found to be as specified on the drawings.
There are two similar restraints on each main coolant loop made of ils inch ASTM A36 carbon steel. The restraints were manu-factured by AFC0 Steel Corporation in accordance with G&H 0550, l
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10 Revision 4. The restraints are massive, approximately 11 feet long. 3 feet wide and 5 feet tall. Each restraint is fastened l to the base mat by 16 prepositioned 2 inch diameter anchor bolts as specified on G&H drawing 2323-51-0551, Detail B.
3 Drawing SI-0550 required that each anchor bolt be pretensioned to "90 plus or minus 10 kips" and utilize a washer, two regular nuts and a jam nut made of ASTM A 540 material. The bottom c nut and the washer required a tack weld as noted in the drawing.
The tack welds were not found on any of the anchor bolts inspected.
In addition, no record of a QC 1rsta11ation inspection of the restraints for loop No.1 or any other loop of Unit I could be found.
Thus, pretensioning of the anchor bolts could not be confimed. j The crossover leg restraints are major components of the main 4 coolant piping seismic restraint and support system. Appendix B i
l of 10 CFR 50, Criterion X, requires that inspections of ,
l activities affecting quality shall be established and perfomed to verify confomance with documented instructions, procedures,~
and drawings for accomplishing the activity. -
TUEC QA Plan, Section 10.0 requires that planned written inspection procedures be used. No requirement for inspection of the crossover leg restraints had been issued. This is also ~~ ~-
i contrary to 10 CFR 50, Appendix B, Criterion X.
This is a violation (445/8408-02).
! 12. Unresolved items i
) Unresolved items are matters about which more information is required '
t in order to determine whether they are acceptable items, violations l or deviations. One unresolved item related to polar crane shims
{ -(Unresolved Item 8408-04) is discussed in paragraph 3.
- 13. Exit Interviews The NRC inspectors met with members of the TUEC staff (denoted in para-f 1 graph 1) at various times during the course of the inspection. The
[ scope and findings of the inspection were discussed.
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