ML20211J837
| ML20211J837 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 05/06/1983 |
| From: | Kaulfus B TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | |
| Shared Package | |
| ML20211J491 | List:
|
| References | |
| FOIA-85-59 CP-SAP-19, NUDOCS 8606270067 | |
| Download: ML20211J837 (55) | |
Text
7 CPSES STARTUP ADMINISTRATIVE PROCEDURE O-CP-SAP-19 c.w:3 Lu n.15d a " t.~ : Cd '~= + DE" %4 u "W is O%k af.,TJ1:"Mirl.;a74; :';g Revision:
s Prepared By:
B.
W.
Kaulfus 0
Reviewed By:
4214:..
/
ea Stdrup Engineer Reviewed By:
/
e, TUGC0 QA SEartup/ Turnover Surveiflance Supe: visor Reviewed By:
/Y A-
Title:
Reviewed By:
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Title:
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Approved By:
/ /A Date:
M r ger', CP S S tar t'u
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~b'O3 Effective Date 8606270067 860617 eg7_t_t PDR FOIA GARDEOS-59 PDR s
-(
Paga 2-of.11
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10.:
TABLE OF CONTENTS
'SECTION TITLE PAGE COVER SHEET 1
TABLE OF CONTENTS 2
1.0 PURPOSE 3
2.0 APPLICABILITY 3
3.0 DEFINITIONS 3
4 ~. 0 -
, PROCEDURE 3
4.1 Education'and Experience 3
4.2 Indoctrination 3.
~4.3 Training-3
_4.4 Physical Capabilities 4
4.5:
-Qualification Require =ents 5
LO 5o azrtatucts 5
6.0 ATTAcafENTS 6
e
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y" i CP-SAP-19
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Page 3'of_11-
-TPAINING/0UALIFICATION REOUIREMENTS FOR STARTU? PERSONNEL 1.0 PURPOSE The purpose of this: procedure is to-define the minimum qualifications that are required for Startup personnel assigned to perform testing and related g
activitixs and to provide a method of documenting personnel qualifications?
C'
~
~
2.0 APPLICABILITY The requirements of this procedure apply to startup personnel assigned-to perform the activities. defined in Attachment A on safety-related_
~ components, systems and structures during the startup programs for CPSES Units 1 and 2.
~
3.0 -DEFINITIONS (di "a==
4.0 PROCEDURI
- 4.1 Education and Experience i
4'.l.1 As a. minimum, startup personnel assigned to perform the duties specified by Attachment A shall meet'the education and experience require =ents specified on Attachment B for the required level' prior to the perfor=ance of those duties.
}
4.1.2 Education and experience shall be evaluated based on the individual's resume by an individual qualified as Level IV and documented on Attachment.B.
- 4.1.3 The education and experience of. individuals qualified to perform the duties specified by Attachment A shall be-verified' and documented 'y'.the individual's employer.
~4 2 INDOCTRINATION 4.2.1 As' a minimum, startup personnel assigned to perform the duties specified by Attachment A will be indoctrinated in the subject materials specified on Attach =ent C, prior to performance of those duties. The individual shall document ce=pletion of the required indoctrination, on Attach =ent C.
4.2.2 Startup clerical personnel will be indoctrinated in the b
applicable procedures, and revisions thereto, governing their job.related activities. This indoctrination will be documented on Attachment C.
4.2.3 Indectrination in revisions to Startup Administrative Procedures and Prerequisite Test -Instructions will be documented on Receipt / Acknowledgement forms transmitted to.
startup test personnel with the applicable procedure revisions.
F
R;vinisn 5L Pag 2 6 of 11 3.
,x-4 3 TRAINING 4.3.
4.3.1.1
~Megger insulation tester 4.3.1.2 Hi-Pot dielectric test set 4.3.1.3 Phase rotation. indicator 4.3.1.4 Si=pson 250 =ultimeter 4.3.1.5 Cla=p-on a==eter 4.3.1.6 Molded case breaker and ther=al overload test set 4.3.1.7-Digital volt /oh= =eter 4.3.1.8 Strobo-tac RPM indicator 4.3.1.9 IRD vibration test equip =ent (Model 306).
4.3.1.10 Surface pyro =eter-4.3.1.11
. Precision bridge 4.3.2 Credit for training received, on the ite=s specified by paragraph 4.3.1, at other facilities =ay be granted by the Lead Startup Engineer on a case-by-case basis if the subjects covered, training dates, na=e of the facility where the training was received, and na=e of individual that ad=inistered the training is docu=enced by letter or certificate.
4.3.3 Training on the ice =s specified by paragraph 4.3.1 shall be g
ad=inistered by an individual qualified as Level IV.
L-Satisfactory co=pletion of such training shall be docu=ented on Attach =ent D.
4.3.4 General E=ployee and Radiation verker training of startup personnel who vill be allowed unescorted access in the plant af ter i=ple=entation of per=anent plant security shall be ad=inistered and docu=ented in accordance with TUCCO Training Depart =ent procedures TRA-101 and TRA-102.
4.4 PHYSICAL CAPA3ILITIES 4.4.1 As a =ini=u=, startup. personnel actpigly involved in testing activities who perfor= vis d exa=1 nations';~sdh as;' flus,h cloth ~sa=ple evaluations, reading _instru=ents, etc., shall pass a color visirn and visual acuity exa=i'Eation ad=inistered and documented in accordance with QPM-001 prior to the perfor:ance of those duties. The following exceptions =ay apply to those personnel that fail the color vision exa=ination; 4.4.1.1 Require =ent for passing the color vision exa=ination f3
=ay be waived by the Lead Startup Engineer if the individual's job duties do not require acceptable color vision; or r
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Prgo 5 of'11
' 4. 4.~ 1. 2 Verification that the individual can correctly
~
-identify -and pair all colored - conductors of a 12 conductor cable. This verification shall'be =ade by j
the -Startup QA Specialist and documented by a =e=o to the individual s qualification records file.
4.4.2 Color vision and visual acuity examinations shall be j
administered annually in accordance with QPM-001.
4.5 QUALIFICATION REQUIREMENTS
~4.5.1 The qualification level of the Lead Startup Engineer shall be established by the Manager, CPSES Startup and documented on Attachment E based on his evaluation of the Lead Startup Engineers education and experience.
4.5.2 The qualification level of startup personnel shall be established by the Lead Startup Engineer or another individual qualified as Level IV and documented on Attachment E.
4.5.3 The qualification level of startup personnel shall be re-evaluated when deemed necessary by the Lead Startup Engineer.
4.5.4 4 gammFM96tf03fr;th.entagrJrm nam *w ??
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5.0 REFERENCES
w.
l 5.1 FSAR. Section 14.2.2.7 5.2 QPM-001, Color Vision and Visual Acuity Examination 5.3 CPSES Startup Quality Assurance Plan 5.4 TRA-101, General E=ployee Training
'5.5 TRA-102,; Radiation Worker Training 5.6 STA-302, Station Records l
l l
--.+....a.
- ~... _....
c CP-SAP-19 Ravision 5 Page 6 of 11 6.0. ATTACOfENTS A - Startup Activity / Minimum Qualification Requirements Matrix 3 - Startup, Personnel Minimum Education and Experience Evaluation Record J
C - Startup Personnel Indoctrination Record D - Startup Personnel Training' Record I - Startup Personnel Qualification Record 9
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CP-SAP-19 Revision 5
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f Page 7 of 11 ATTAC' MEiT A d
STARTUP ACTIVITY / MINIMUM OUALIFICATION REOUIREMENTS MATRIX h
STARTUP ACTIVITY L-I L-II
- L-III L-IV Direct or Supervise the Conduct of Prerecuisite Tests XV Review Prerequisite Test
/
Results X
Approve Prerequisite Test j
Results I
Review and Approve Preoperational l
Test Procedures and Results I
Direct or Supervise the Conduct i
of Preoperational Tests X
- Level III is not used.
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O e L. $
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~ ATTACHMENT B CP-SAP-19 STARTU? PERSONNEL MINIMUM EDUCATION Revision 5 EXPERIENCE EVALUATIONS RECORD Page 8aof 11 Name:
Compliance
- Education / Experience Recuire=ents Check-Off Co==ents
. LEVEL I d
- / a. 1. 3achelor's degree in engineering or-the physical sciences:
A
. f;
- 2. 3 mos testing / operating experience:-------
s
- 3..1 Mo. on-the-job training supervised by J.
Level I or higher:
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e]
. 'j. q.
- b. 1. H. S. Diploma or equivalent:---------
2
'h 3-
- 2. 4' years of pwr. plant testing / operation
. ' l2 (2 yrs. may be related technical training):
y
- 3. I me. on-the-job training supervised by p'
Level 1 or higher:
LE7EL II a.f. Bachelor's degree in engineering or the l
physical sciences:
l
- 2. 1 yr. pwr. plant, testing /cperation experience:
i
- 3. 3 mos f amiliari:ation of CPSES or similar design:
a
- b. 1. H. S. Diploma or equivalent:-----
- 2. 4 yrs pur. plant testing / operation _(2 yrs.
4 may be related technical training):
- 3. 3 mos familiarization of CPSES or similar design:
LEVEL III - (Not Used)
. LEVEL IV
- a. 1. Bachelor's degree in engineering or the l
physical sciences:
- 2. 2 yrs. applicable power _ plant experience:
- 3. 2 yrs. applicable Nuclear pvr plant exp erience : ----
- b. 1. H.S. dipic=a or equivalent :-------
_(t
- 2. 6 yrs, applicable plant experience'(2 yrs.
may be related techn4 cal training):------
- 3. 2 yr applic..ble Nuclear power plant experience:
Evaluated By:
Date:
Attach Detailed Resume of Education and Experience 9
e e e -o w
m-e s
omr,-t-
-ees
CP-SAP-19 Revision 5-
~
Page 9 of.11 ATTACEiENT C STARTt.*P PERSONNEI. INDOC*RINATION RECORD CPSES Scattup Quality Assurance Plan
,7inal Safety Analysis Report - Section 14.2 Startup Administrative Procedures Manual
-Prerequisite Test Instructions Manual
' Systens Su=sary of a Westinghouse Pressurized Water Reactor-Nuclear Power Plant Code of-Federal. Regulations Title 10 (1) Part 21 (2) Part 50.55 (e)
(3) Part 50 Appendix A (4) Part 50 Appendix B Other: (Lis: subject, procedures by number, e:c.) -
l I have received indoctrinacion on the above caterial.
, Date:
Name:
4-t
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m CP-SA?-19 1 '
. ~ -
Rsvision 5')~
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Paga 10 of 11 ATTACHMENT D STARTUP PERSONNEL TRAINING RECORD NAME:
Type of Training :
(Classroom, self study, vendor dee.onstration, e:c.)
INSTRUCTOR'S SUBJECT DATE RECEIVED NAME/COMPMIY AFFILIATION e
e D
D t
I A
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~
ATTAChN. ENT E CP-SAP-19 STARTU? PERSONNEL QUALIFICATION RECORD.
R1 vision 3 Page 11 of 11
'NAME:
EMPLOYED BY:
Date Assigned to Star.up Organization:
For Level I Qualification Only:
On-the-Job Training Period:
to Supervised By:
Date:
THE ABOVE INDIVIDUAL IS QUALIFIED AS:
LEVEL I II III IV (Circle One)
EVALUATED BY:
TITLE:
DATE:
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m Draft 1 8/28/84 AQ-19/CP2 COMANCHE PEAK OPEN ISSUE ACTION PLAN Task: Determine the training of prerequisite testing personnel and their support people.
Ref. No.: AQ-91 Characterization: It is alleged that the personnel performing prerequisite testing have received improper or inadequate training and these personnel receive little or no supervisor during testing.
/
Initial Assessment of Significance: The validity of prerequisite testing is suspect'if performed by untrained personnel.
l Source: QA-QC Category 4 l
I Approach to Resolutions:
l l
i I
1.
Review training records of personnel performing the prerequisite and j
startup casting and compare with requirements.
l l 2.
Review test procedures to determine if sufficient detail is provided to i l give test personnel adequate guidance for performance of test.
FO)A-85-69 l
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Refer any examples of wrongdoing or significant deficiencies to TRT manager.
4.
Evaluate allegations for generic / safety implications.
5.
Report on results at review / evaluation of allegations.
Related Open Issue Identification:
Status:
., i t
i Review Lead:
Support:
i Estimated Resources:
Estimated Completions:
i CLOSURE:
$2/f Reviewed by:
- f 77 F TRT Leader
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CONANCHE PEAK NUCLEAR POWER PLANT AltEGATIONS AND/0R INVEST! Gall 0NS SlM4ARY i
CROSS REF./OR CONPLETION ALLEGER-DATE RECEIVED f
TASK SOURCE TRACKING CATEGORY 1-7 SCHEDULE SOURCE I
ALLEGATI0?! OR CONCERN ACTION / STATUS ANON CONFID BN/0 ATE SYSTEN NO.
LEAD OPEN CONPLETE DOCUNENT PAGE
[ AQ-91 Improper inadequate train-X 1
GAP witness H #12 i
{
ing of testers (no super-TRT r
j vision of tester in the j
field)
AQ-92 Packages arriving to STE's Open X
1 GAP #15 with DCA's issued against TRT drawings. (Aux. Relay Room)
AQ-93 Print changes with no Open X
1 GAP witness H #17 DCA's in package arriving TRT at SIE AQ-94 No procedure to ensure Open X
1 GAP witness H #13 that STE has proper TRT documentation AQ-95 Possible misuse of NCR's Open X
1 GAP witness A, D #24 to cover more than one TRT
travele r" l
AQ-96 Use of open-ended Field Open X
1 CAP witness J #29 Job Order " blank check" TRT
- 40 or 04 makes work appear to have been pre-approved AQ-97 Permanent documentation Open X
1 CAP witness C #32 is being pulled out of the IRT vault and new NCR's written on old probelas because the documentation did not match the log book i
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QUALIFICATIONS OF INSPECTION, EXAMINATION AND I
TESTING PERSONNEL FOR NUCI EAR POWER Pt. ANTS ANSI /ASME Ne5.2A-1978 l
+
f (4) Four. year college graduation plus six months i
of related experience in equivalent inspection,exami.
nadon, or tesdag acdvides.
Personnel who are assigned the responsibility and 3 D W lli authority to perform functions covered by this Stan.
dard shall have, as a mmunum, the level of capability (1) Six years of satisfactory performance as a Level shown in Table 1. When a single inspection or test re.
l II in the corresponding inspection, examination or test quires implementation by a team or group, personnel category or class,or not meeting the requirements of this Standard may (2) High school graduation plus ten years ofrelated be ud in data.taking amisninents or in plant or experience in equivalent inspection, examination, or equiprnent operation provided they are supervised or testing activities; or high school graduation plus eight mrseen by a qualified individual participating in the years experience in equivalent inspection, examin laspection, examination, or test.
tion, or testing activities, with at least two years Ievel II, and with at least two years associated wi nuclear facilities-or if not, at least sufBcient traming
~
__.m f ility A file of records of personnel qualification shall be (3) Completion of college level work leading to an established and maintained by the employer. Collec.
tion, storage, and control of records required by this Associate Degree and seven years ofrelated experience Standard shall be in accordance with ANSI N45.2.9.
In equivalent inspection, aramination, or testing ac.
tivities, with at least two years of this experience as.
sociated with nuclear facilities-or if not, at least suf.
fi-lent training to be acquainted with the relevant
- 6. REVISION OF ANSI STANDARDS REFERRED TO IN THIS DOCUMENT quality assurana aspects of a nuclear facility, or (4) Four. year college graduation plus five years of When any of the Standards referred to in this docu.
f related experience in equivalent inspection, examina, rnent is superseded by a revison approved by ANSI, tion, or testing activities, with at least two years of the revision is not mandatory until it has been incor.
this experience associated with nuclear facilities-or porated as part of a contract.
if not, at least sufficient training to be acquainted Revisions to this Standard issued after the date of with the relevant quality assurance aspects ofa nuclear a specific contract involdng this Standard may be used facility.
by mutual consent of the purchaser snd the supplier.
0 70A-85-59 XM l
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5 I' G 's 4 Systems f,
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% 01 DC POWFR McDOWF8I_.,
51 PLANT CAS lil OCH EN /WOtlACK f
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AC DISTRIBUTION ticDOWElL/ JAMAR /SIEGEL 52 AUXil.IARY REl.AY ltACKS THOMSON /SK El.Tura 4)
STARTUP POWER SHPPLY S I EGEL 53 COMPUTF.R DFt.K 04 SFRVICE WATFR h
54 TURRINE Cl.AND STEAM WOOTIN 05 POT A RI.5: llATFR IITilH s a A 55 REACTOR COOLANT
/
06 FIRE PROTICTION/l)ETECTION FEl.TN ER 56 BORON RECYCLE FUHilSH illa
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07 CONTROI. 110141 HVAC CASTINEl./ PHALEN 57 SAFETY INJECTION 08 MATT RMS & HISC AREA VENT.
FilALEN/VORA 58 RESIDUAI. IREAT llEMOVAI.
/
09 VATER TREATHFUT CLARK 59 HOT USED 10 DDilN. & eEACTult HAKEUP WATER Cl. ARK 60 SOLID WASTE PROCESSING WHITEH EAD/PI ETROVICal
- il CielPON g COOLINC WATER COCKREL 61 CASEOllS WtSTE PROCESSING BU Rl* /1.OWTH ER
?
12 CteeltrKICATIONS MacLEOD 62 MAIN TUlt81NE & AUX 13.l ARIE.S WOOTEN /FAR LEY h'OHAClf l}
T.B. & NORM 5WCR llVAC VORA
- 6)
HAIN CEN. & AUXILIARIES WOOTEN/FARI.I;Y/rfULLENS 14 INSTRUMENT Alt itc KI B BIN 64 itEACTOR P80TECTION
/
IS SFRVICE AIR McKlBBIN 65 CONTAINHENT ATHOSPHERE HohlT.
Dr.lK
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16 1URR. PLT. COOI.ING WATER BERNHOFT 66 NHCLEAR INSTltDHENTATION 1.OPEZ 17 OFFICE & SERVICE AREA ltVAC PHALEN 67 llYDitOCEN RECOHulNER TUCCo OPERATIONS 18 SEWACE TREATHENT Cf.A P.K 68 ROD CONTROL CRITES 19 CONDI.PSATE McKIBBIN 69 HISC. IIVAC SYSTEMS OWEN f
20 AllXILIARY STEAM McKIRRIN 70 RADI ATION NNITOlllNG QUAH l
28 FON-SAFETY CallLLED WATER COBB 78 NUT USED 22 SAMPLING SYSTEH RollR ER / PACE 72 EE.EVATORS ROHRER 7
23 VPNTS & DNAINS IIEtellLA 73 PROT. & SURV. PKC (N-16)
LOPEZ 24 l'RIHAltY Pl.T. VENTILATION COR8 74 HOVABI.E INCORE & Fl.UX HAPflNG WI NKLE81.ECil/OF k N ER 25 CONDFNSATE POLISHING CLARK 75 STR. INTEC. & LEAK RATE TESTING DI.OCllER 26 CIRCULATitlC WATER CLAltK 76 AD. BLDC. STR. & INTEkNAl. EQUIP.
TilCCo OPEllATIOPS j.
27 COND. VAC. WTR. BOX PRIMING H ttut!!,A 77 HAINT. STR. '& INTEliNAL EQilIP.
TUCCo OPEkATIONS d
7R ERF COMPUTER OFFNER 2H STi>H CEN. FEEDWATER 29 UNIT l DIESEL. CEN. & AUX HULI. ENS /8ECKER 79 NOT llSED 30 NOT t: SED 80 SEISHIC INSTRUMENTATION WI N KI.Enl.FCil 31 SAFETY CastLLED WATER llENNESSY
~ 84 CRANES & ilOISTS VAN CULIK/illNTERSCllFR
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ROi!R ER /
- 12 AUXILIAkY Bl.DC. IIVAC HFNNESSY 82 HETEOROLOGICAL HONITORING SCHHITZ t
f 3)
CllOllCAL FEED NcKIRRIN
~ 83 ANNUNCIATOR Hact.EOD/SK ELTON i
34 MAIN STEAM 84 HEAT TRACING SIEGEL f
75 ilEATEN tilt A IN Wik)T FN 85 CATHODIC PROTECTION SIEGEL l
36 SAFLGUARO DI.DC. HVAC PH A L F N /H ENN ES S F.Y R6 NOT USED 37 AllXII.l AltY FEFI) WATER d
87 SECURITY WINTERS I
18 EXTRACTION STEAH WOOTEN 88 ANAlOC CONTHOL SANDERS 39 DIESEL CENERATOR HVAC BOOZEnt 89 STRUC1URES VANDER GRIFT a
40 FUEL HANDI.INC & VESSEL SERVICING lilNTERSCllER
- 90 SSI STRilCTURE TUCCo OPEntATIONS 48 f.ls. Wild WASTl; PROCESSINC PACE /WHITEllEAD/LOWTilER 98 I.OOSE PARTS HONITORING WINKLE 81.ECH 42 FilEL 8LDC. 16VAC COnB 92 NOT USED 41 TURR. Oll. PURIFICATION WOOTfH/FARLEY 91 CONTAINHENT BLOCliEn r
44 STtt. CtN. til OWDOWN & Cl.FANUP FEl.TNER s,
94 NOT USED 4%
(DNTAINIHNT VENTil.ATION OWtN 4
95 NOT USED 46 C64ITA INHENT HYDitOCFN PHitCE OWIN 96 NOT USED s
w 47 Fatt l. PthH. CIM)L. & CIEANifP li l,ts!'t it SCllER 97 HOT USED P( T 4 F%
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48 Cid4TAINHL!!T SPRAY
/ 9 46 TEST DEFERRALS i:su s 4 3 4 3 ~.fi f u m
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49 CilEH. & VOLUME CONTROL
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4 50 SWITCHYARD filfLTJNS XX X
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- Annex 1 Comanche Peak Allecation Work Package Allegation Number _ ;4 0 - 9 /
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Numbers of Similar Allegations f
Statement of Allegation:
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Date Received The above information prepared by _ // gap @ cp#och Name Date
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Group Leader.
NfittG lr uer nso r e.
'1 Name Date Assigned Team Members Date Assigned t
s.
Date Assignec l
Date Assigned Date Assigned
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e EIG IEECCTRINATICN As a minimum, Electrical Test Group personnel will be indoctrinated in the
- j following cubject reading materials prior to perfor: nance of these duties:
P-SAP-3 " Custody Transfer of Station Components" m
CP-SAP-4 " Custody Transfer Tagking" a
ICP-SAP-5 " Safety Tagging Procedure" Y CP-3AP-6 "Centrol of Work on Station Components After Release from Construction to TUGC0" CP-AP-13 " Temporary System Modificatiens"
' CP-SAP-14 " Design Change Processing" ICP-SAP-16 " Nonconforming Condition Reporting" 7
[ CP-SAP-20 " Guidelines for System Walkdown Inspections" CP-SAP-21 " Conduct fo Te' sting" I CP-SAP-22 " Retest Control" XCP-EE-l "Meggar and Hi Pot Testing"
_}
I XCP-EE-5 "Switchgear and Motor Control Center Testing" EI XCP-EE-7 "Pewer Transformer Testing" XC P-E-8
" Control Circuit Functional Testing"
[XCP-EE-9 " Initial Motor Rotation and Run-In" Y.CP-EE-10 " Motor Operated Valve / Damper Testing" I XCP-EE-11 " Air Operated Valve / Damper Testing" XCP-EE-12 " Annunciator / Monitor Light Box Operability Testing" YXCP-EE-18 " Power and Distribu' tion Panel Test Procedure" XCP-EE-19 " Immersion Heater Functional Tests" Y XCP-ME-1
" Initial Pump Operation" d
Z XCP-ME-3 "HVAC Gravity and Fir ~e Damper Testing" FO)A45-59 M4
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Ql WG I:iEO:TRINATION Fage 2 XCP-ME-5 ' Tan Functional Tests" d XCP-ME-13 " Unit / Duct Heater Functional Tests" The above reading list was completed as of Signed:
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QUALIFICATION REQUIREMENT FOR STE'S, ETG'S & MTG'S Appendix "B" Criteria XI, " Test Control" and ANSI N45.2-1971, " Test Control" which states:
10CFR 50 APPENDIX B XI.
TEST CONTROL A test program shall be established to assure that all testing required to demonstrate that structures, systems, and components will perform satisfactorily in service is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable design documents. The test program shall include, as appropriate, proof tests prior to installation, preoperational tests, and operational tests during nuclear power plant and fuel reprocessing plant operation, of structures, systems, and components. Test procedures shall include provisions for assuring that all prerequisites for the given test have been met, used, and the test is performed under suitable environmental conditions. Test results shall be documented and evaluated to assure that test requirements have been satisfied.
TEST CONTROL A test program shall be established to assure that all testing required to demonstrate that the item will perform satisfactorily in service is identified and documented, and that the testing is performed in accordance with written test procedures which incorporate or reference the requirements and acceptance limits contained in applicable design documents. The test program shall cover all required tests, including, as appropriate, prototype qualification tests, proof tests prior to installation, preoperational tests, and operational tests to verify continued satisfactory performance during operation. Test requirements and acceptance criteria shall be provided by the organization responsible for the design of the item under test, unless otherwise designated.
Test procedures shall include provisions for assuring that prerequisites for the given test have been met, that adequate instrumentation is available and used, and that necessary monitoring is performed. Prerequisites include such items as calibrated
)
instrumentation, appropriate equipment, trained personnel, condition of test equipment and the item to be tested, suitable environmental conditions, and provisions for data acquisition. Test results shall be documented, and evaluated by responsible authority to assure that j
test requirements have been satisfied.
90)A-85-59 l'
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' l Section 14.2.2.7 stated the original key personnel qualification for the l
Startup program. During the NRC review of Section 14, the NRC initiated
' Question Q423.1, which states:
423.0 Initial Test Program Q423.1 Provide minimum qualification requirements for members of the Joint Test Group.
It is not clear whether the JTG members will' review test procedures and results themselves, or they will delegate this responsibility to others.
If the JTG members do not personally review the preoperational and start-up test procedures and results for technical adequacy, provide minimum qualification requirements for personnel who will perform the reviews for them. Provide minimum qualification requirements for individuals who may be designated by the JTG members to review and approve modifications to preoperational and start-up tests.
TUGC0 Response to Q423.1 was:
R423.1 Review of test procedures and results may be performed by the JTG members only or delegated to staff personnel. However, the JTG member or his delegate must meet the minimum qualifications for i
these functions as stated in revised Subsection 14.2.2.7.
t I
Subsection 14.2.3.5 describes the methods for revision and e
modification of preoperational and initial start-up test procedures and identifies the job positions responsible for approval of those revisions and/or modifications. Subsection 14.2.2.7, including the change described above, provides qualification requirements for the job positions identified in subsection 14.2.3.5.
The above response was a basic commitment to the NRC request and the FSAR l
was updated to address the JTG concern.
Further review of the FSAR by the NRC in Section 14 prompted the issuance This question was issued as a staff position, j
of Question Q423.7.,have to commit to their requirements.
indicating we would The question is l
as follows:
I Q423.7 The minimum qualification requirements for System Test Engineers and members of the Joint Test Group (or personnel designated by l
them to review test procedures and results) do not appear to be i
commensurate with the importance of the tasks they perform.
It i
is the staff's position that the following categories of personnel hold the listed minimum qualification requirements.
Minimum qualifications of System Test Engineers or other I
individuals that direct or supervise the conduct of individual Preoperational Tests (at the time of assignment to the task).
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A bachelor's degree in engineering or the physical sciences l
or the equivalent and one year of applicable power plant 4
experience.
Included in the one year of experience should be at least three months of indoctrination / training in 1
nuclear power plant systems and component operation of a a
J nuclear porer plant that is substantially similar in design to the type at which the individual will perform the function, or i
2.
A high school diploma or the equivalent and four years of power plant experience. Credit for up to two years of this four year experience may be given for related technical training on a one-for-one time basis.
Included in the four years of experience should be at least three months of indoctrination / training in nuclear power plant systems and component operation of a nuclear power plant that is substantially similar in design to the type at which the individual will be employed.
l Minimum qualifications of System Test Engineers or other individuals that direct or supervise the conduct of li individual'Startup Tests.
(At the time of assignrcnt to the task).
l 1.
A bachelor's degree in engineering or the physical sciences or the equivalent and two years of applicable power plant experience of which at least oneyear shall be applicable nuclear power plant experience or, 1
i.
l 2.
A high school diploma or the equivalent and five years of applicable power plant experience of which at least i
two years shall be applicable nuclear power plant experience. Credit for up to two years of non-nuclear experience may be given for related technical training on a one-for-one time basis.
i Minimum qqalifications of Joint Test Group members or other individuals responsible for review and approval of Preoperational and Startup Test Procedures and/or review and approval of test results.
(At the time the activity is being performed).
!~
1.
Eight years of applicable power plant experience with a minimum of two years of applicable nuclear power plant i
experience. A maximum of four years of the non-nuclear
'l experience may be fuifilled by satisfactory completion of academic training at the college level.
.! j The above qualification identified by the NRC is basically a reprint of i
ANSI N45.2.6 " Qualifications of Inspection, Examination, and Testing Personnel for Nuclear Power Plants" as endorsed by Reg. Guide 1.58.
Again TUCCO committed to the staff position as indicated in the following l,:
response to Q423.7.
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'R423.7-FSAR Section.14.2.2.7 has been revised to incorporate Systems i
Test Engineer and Joint Test Group Member Qualifications to be commensurate with the staff's position.
At this point, Startup was committed to a basic N45.2.6 Type of Program, we still had not committed to Reg. Guide 1.58.
After the FSAR had been revised to reflect the commitments to Q423.7, the NRC staff position changed, as indicated in Question Q423.21 below:
Q423.21 Your response to item 423.7 is not acceptable. ANSI Standard N45.2.6 was not intended to cover personnel who direct or supervise the conduct of preoperational tests or personnel who review preoperational or startup test procedures or results. Our current position is that these individuals should hold the qualifications stated in regulatory position 3 of proposed Revision 2 to Regulatory Guide 1.8, February 1979 (issued for comment). State that your minimum qualification requirements will be in accordance with this regulatory position or provide justification for requiring any lesser qualifications.
Again TUGC0 Consmitted:
R423.21., Response to item 423.7 has been revised.
The followips is the Regulatory Position 3 of Proposed Revision 2 to Regulatorf Guide 1.8, February 1979, which Startup has committed:
Regulatory Position 3:
3.
Section 1. " Scope " of ANSI /ANS 3.1-1978 states, "(The Standard) addresses itself to the qualifications, responsibilities, and training of personnel in operating and support organizations appropriate for the safe and efficient operation of nuclear power plants." In addition, the following minimum qualifications for personnel responsible for preoperational'and startup testing i
programs should be used:
a.
Minimum qualifications for individuals that direct or supervise the conduct of individual preoperational tests -
at the time the test is conducted, the individual should
~
i have a bachelor's degree in engineering or the physical j
sciences or the equivalent and one' year of applicable power plant experience. Included in the one year of experience l
should be at least 3 months of indoctrination / training in nuclear power plant systems and component operation in a nuclear power plant that is substantially similar in design j
to the type at which the individual will perform the j
function.
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b.
Minimum qualifications for individuals that direct or supervise the conduct of individual startup tests - at the time the test is conducted, the individual should have a bachelor's degree in engineering or the physical sciences or
+
the equivalent and two years of applicable power plant experience, at least one year of which should be applicable nuclear power plant experience.
c.
Minimum qualifications for individuals assigned to groups responsible for review and approval of preoperational and startup test procedures or results - at the time the activity is being performed, individuals that perform these activities should have a minimum of eight years of applicable power plant experience with a minimum of two years of applicable nuclear power plant experience. A maximum of four years of non-nuclear experience may be fulfilled by satisfactory completion of academic training in engineer or the physical sciences at the college level.
d.
Qualifications for other inspection, examination, and j.
testing personnel are contained in Regulatory Guide 1.58
- {~
" Qualification of Nuclear Power Plant Inspection.
Examination, and Testing Personnel."
In the above qualification, the term " Bachelor's Degree or equivalent" is
~
used. Regulatory Position 2 of Regulatory Guide 1.8 February 1979 defines t
this term as:
!l i ;'
Regulatory Position 2 s
2.
For the purpose of this regulatory guide, when the phrase " bachelor's degree or equivalent" is used, the qualifications considered as minimum acceptable substitutes for a bachelor's degree are a hiah
},
school diploma or its equivalent and one of the followins:
1 l'
a.
Four years of formal schooling in science or engineeringi l!
b.
Four year of applied experience at a nuclear facility in the are for which qualification is sought;
.j
) t, c.
Four years of operatiotial or technical experience or training in nuclear power; or i
d.
Any combination of the above totaling four years.
!l For comparison the following is Startup's Commitment on qualifications as
!I indicated in the FSAR Section 14.2.2.7.
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14.2.2.7 Qualifications ~of Key Personnel The minimum qualifications of individuals responsible for review and approval of preoperational test procedures and results shall be; (1) Bachelor's degree in engineering or the physical sciences and four years of applicable power plant experience; or (2) high school diploma or equivalent and eight years of applicable power plant experience. Credit for up to two years for related technical training may be substituted on a one-for-one time basis. A minimum of two years shall be applicable nuclear power plant experience.
The minimum qualifications of individuals responsible for review and approval of initial startup test procedures and results shall be the same as required for regular members of the Station Operations Review Committee (SORC).as described in Section 13.4.1.1.2, SORC Membership Qualifications.
~
The minimum qualifications of individual that direct or supervise the conduct of preoperational test at the time of performance of the duties, shall be; (1) Bachelor's degree in engineering or the physical sciences and one year of experience in power plant testing or operation. Included in the one year shall be three months of familiarization of system and component l
operation unique to the design of similar nuclear power plants at which the individual will be employed, or (2) a high school diploma or equivalent and four years of experience in power plant testing or operation or credit for up to two years for related technical training may be substituted on a one-for-one time basis.
Included in the four years shall be three months of familiarization of system and component operation unique to the design of similar nuclear power plants at which the individual i..
will be employed.
f The minimum qualifications of individuals that direct or supervise the conduct of initial startup test at the time of l
performance of the duties, shall be; (1)
Bachelor's degree in engineering or the physical sciences and two years of experience in power plant testing or operation.
Included in the two years 3
l shall be a minimum of one year of nuclear power plant testing, operation or training on a nuclear facility, or (2) a high i.
school diploma or equivalent and five years of experience in l
power plant experience. Credit for up to two years for related j
technical training may be substituted on a one-for-one basis.
c i
All test personnel will be indoctrinated in the use of startup l;
and applicable station administrative control procedures, test procedures and familiarized with all applicable quality assurance l$
requirements.
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'i The value/ impact statement for Proposed Revision 2 to Regulatory Guide 1.8 on Personnel Selection and Training for Nuclear Power Plants issued with the Proposed Revision 2, indicated the NRC's intentions for imposing Staff
-[
Position 3, it states:
"Value/ Impact Statement" Regulatory Position 3 has been added to clarify the
.c.
j qualifications of personnel who direct or supervise individual j
preoperational and startup tests and for individuals assigned to i'
groups who are responsible for review and approval of preoperational and startup tests.
Value -
There has been some confusion as to whether the qualifications for inspection and test personnel described in Regulatory Guide 1.58 apply to preoperational and startup test personnel.
The additional regulatory position eliminates this confusion and 1
clearly identifies the qualifications that the staff considers acceptable. This will benefit both applicants and the staff in selection and review of personnel.
Impact - There should be little impact. The staff has been recommending j.
and approving the qualifications included in the position for some time.
Additional larification can be obtained by a review of the FSAR j
commitment to Regulatory Guide 1.58.
FSAR TABLE-1AB PAGE 1A(B)-24 4
Regulatory' Guide 1.58 l
Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel Discussion With reference to the subject Regulatory Guide as it applies to activities during the construction phase:
~
1.
For inspection activities within the scope of the ASME Code, inspectors are qualified in compliance with the requirements of Regulatory Guide 1.58. Revision 1.
2.
For inspection activities outside the scope of the ASME Code, inspection personne1'are qualified in general compliance'with the requirements of Regulatory Guide 1.58, Revision 1 except as follows:
a.
Some inspection personnel qualifications are documented on a TUGC0 form and not on the Constructor's form.
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b.
Some of the qualification forms are signed by a TUGC0 I
representativa and not by a Constructor representative.
3..
Qualification records are collected, stored and controlled in compliance with ANSI N45.2.9 Draft 11, Revision 0, dated January 17, 1973, as included in the " Gray Book".
For Operational Phase activities, CPSES TUGC0 Operations will comply with j
the provisions of Regulatory Guide 1.58, Revision 1, for the qualification of quality control inspection personnel.
i Also refer to Appendix 1A(N) and Section 17.2.
As indicated in the above FSAR Regulatory Guide "1.58 Revision 1" is committed to for " inspection personnel only".
Upon review of the 4
Regulatory Guide 1.58 Revision 1. under Section C Regulatory Position, 1.
)
Section 1.2, " Applicability" of N45.2.6 states as follows:
1.
Section 1.2, " Applicability " of ANSI N45.2.6-1978 states that the standard applies "to personnel who perform inspections, i ~
examinations, and tests... during preoperational and startup testing, and during operational phases of nuclear power plants."
l, However, for qualification of personnel (1) who approve i
preoperational, startup, and operation test procedures and test results and (2) who direct or supervise the conduct of individual i
preoperational, startup, and operational tests, the guidelines i
j; contained in Regulatory Guide 1.8, " Personnel Selection and Training," should be followed in lieu of the guidelines of ANSI l
N45.2.6-1978.
ETG's QUALIFICATION REQUIREMENTS REI.ATIVE TO STARTUP SUPPORT
,i, As identified in FSAR Table 1A3, Construction has committed to Regulatory Guide 1.58 Revision 1 for inspection personnel. As stated within l;
Regulatory Guide 1.58 Revision 1. ANSI N45.6-1978 is endorsed as the j.
implementing instruction. Section 4. " Performance" of ANSI N45.6-1978 states:
j j-4.
PERFORMANCE j.,
Personnel who are assigned the responsibility and authority to perform functions covered by this Standard shall have, as a minimum, the level i
of capability shown in Table 1.
When a single inspection or test requires implementation by a team or group, personnel not meeting the l
requirements of this Standard may be used in data-taking assignments or in plant or equipment operation provided they are supervised or
!f overseen by a qualified individual participating in the inspection, examination, or test.
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l 7.
Section 4, " Performance," of ANSI N45.2.6-1978 states:
"When a single inspection or test requires implementation by a team or group, personnel not meeting the requirements of this Standard may be used in data-taking assignments or in plant or equipment operation provided they are supervised or overseen by a qualified i
individual participating in the inspection, examination, or test."
These personnel should have sufficient training to ensure l
an acceptable level of competence in the performance of their i
activities.
As indicated in Section 4 ANSI N45.2.6 allows the use of personnel who do f
not meet the requirements of ANSI N45.2 ed they are su ervised or i
i oversee a
lified individual.
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ETG EMPLOYEES AND BADGE NUMBERS Adams, Niles S802 /
Malone, Dan 1551 /
An, Sang 0777 /
Marsh, Jim W356 /
4646/j Meier, Dave S313 /
4 41, " v.h Z461 Milford, Terry W595/
Baxter, Ben UO87f s4forris, Richard Q591
.' CNW T L $ennett, Lee B
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cisco, Larry L260 Nickels, Robert 1946 /
8r6'" Cartee, Ed '
S986 Obenhaus, Otto 1460/
E759f Orfield, Gary N469/
Foster, John F249 cm./ g, DasarM Ef #
Fuston, Pat
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Peterson, Keith 9434/
Gonsalves, Doug S276 Grant, John U203 Piper, James Z899 C*ey, Deeg Utt@ /
Quick, Joe C123p 02 - -4 2;, L.. m..
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t Reed, Don Q899
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Halbert, Jodie 1331 Hall, Billy E546/
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Salph, David S803'/
liarper, S teed FA57 /j gC ehew, Beog 4466 Hedgepeth, Bill T314 Shorter, Bill S270' llendrix, Fred 1357/
Sims, Clint Z437' Hill, Al Z306
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Slyder, James 1057v
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Sulzener, Greg Q075 /
Iloit, Dennis S593 Totten, Eric X448 #
Iludgins, Mike W534
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gp,,,3 J&eamnen, Jeff g.gp fgG[,4d*ang=casald WGypg ?J Underwood, Jerry T964 j
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/ "A ll/* f illiams, Rocky Y8479 J J '/
MJ LaCas, liarvey S317 Williams, Warren F567 /
Lowery, Roger YO43 Luck, Paul W760/
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CERTIFICATION OF DESIGN Westinahouse Electro-Mechanical Division ouisa 1.rons,io o. sie a Westinahouse Electro-Mechanical Division stena a. lysis repara on it!. u James C. DiPerna (i) p,or. g.g.s sie_ PA a,s.go.153 72-E Daisa sPetifications certified by_
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REGION IV Report No. 50-445/79-22; 50-446/79-21
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Docket No. 50-445; 50-446 6,
Category A2 Licensee: Texas Utilities Generating Company 2001 Bryan Tower Dallas, Texas 75201 Facility Name: Comanche Peak, Units 1 and 2 Investigation at: Comanche Peak Steam Electric Station, Glen Rose, Texas Investigat'ionConducted: September 7 and 12; Octob r 11, 16, 18 and 20, 1979 n
Inspectors:
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R.f C. Stewart, Reuttor Inspector
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Projects Section W
II '?A ~ Y J. I. Tapia,Meictor nspector, Engineering Date Support Section N/26//f L. D. Gilbert, Reactor Inspector, Engineering
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R.' G. Taylor %3esident Reactor Inspector
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Investigation during the periods September 7 and 12: October 11, 16, 18 l
and 20. 1979 (Report No. 50-445/79-22: 50-446/79-21) l Areas Investigated: Special investigation of allegations concerning the quality of construction at the Comanche Peak facility, Units 1 and 2, by a j
former Quality Assurance inspector, whose connents are contained in the University of Texas at Arlington " Shorthorn" newspaper, dated July 18, 1979.
The investigation involved thirty-eight inspector-hours by four NRC inspec-tors.
Results: The allegations either have no merit, or could not be substantiated.
No items of noncompliance or deviations were identified.
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a INTRODUCTION Comanche Peak Steam Electric Station (CPSES), Units I and 2, are under construction in Somervell County, Texas, near the town of Glen Rose, Texas. Texas Utilities Generating Company is the Construction Permit t
holder with Brown and Root, Inc. as the Constructor and Gibbs and Hill, Inc.
as the Architect / Engineer.
REASON FOR INVESTIGATION As a result of allegations in regard to the quality of construction at the CPSES facility by a former Quality Assurance inspector, whose comments are contained in the University of Texas at Arlington (UTA) " Shorthorn" newspaper dated July 18, 1979, an investigation was initiated in order to assess their validity and impact on safety-related components and systems.
SUMMARY
OF FACTS l.
Allenation No.1 1
On Wednesday, July 18, 1979, the UTA " Shorthorn" contained a front page article entitled, " Peak Construction called ' Sloppy,' Former Inspector Cites Defects." -The article, by Mike Hinshaw, a UTA staff writer, contained the results of an interview held by the writer with a former Brown and Root employee and currently a student at UTA. In the article, the former employee alluded to examples of the lack of job site coordination, shoddy workmanship, poor supervision, and a waste of construction materials. In addition, he indicated that hundreds of defects have not been identified during construction of the facility.
Alleaation No. 2:
t
.l During the course of an interview by the IE inspectors with the former employee, he alleged that he was told by an individual (unidentified) that a radioactive material / source (nondescript) was dumped into the
,,j Comanche Peak cooling lake.
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s Allegation No.' 3:
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or. Primary Coolant System, Field Welds W-19 and W-20.
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Allenation No. 4:
aeg' pwd In addition, he stated that he was told that a 6" check valve weld
~ ^ - 29 deficiency had been repaired without correct procedural instructions.
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' CONCLUSIONS 4
1.
Allesation No. 1:
Matters Identified in Newspaper Article
. i Although the alleger related to instances of what he termed " shoddy" workmanship, poor supervision and poor job site coordination, he could not provide any additional information, beyond conjecture and hearsay, that would support his allegations of undetected defects.in the con-struction activities at the Comanche Peak facilities.
2.
Allegation No. 2: -Alleastion that Radioactive Material / Source was Dumped into the Comanche Peak Lake Although the alleger was requested to have his unidentified source contact the NRC Regional office, no such person has done so.
Sources whose partial identity met the descriptions given by the alleger were j
interviewed. They had no knowledge of such an event, nor could they imagine such an event happening without their being aware of it.
This allegation appears to have no merit.
3.
Allesation No. 3: Allened Improper Welds on Primary Coolant System The reference made to Field Welds FW-19 and 20 by the alleger regarding improper repair appears to be hearsay. The allegation has no merit in that witnesses and records of the repairs do not substantiate improper repair.
i 4.
Allesation No. 4: Four or Sir Inch Check Valves - Disassembly Without t
Proper Procedure The witness identified by the alleger was interviewed. The witness stated 'that the valve in question was a 6" check valve and that pro-j371 per repair and resolution of the initial discrepancy was complete and 1
%45 documented. Furthermore, there is no evidence that would suggest that the procedure discrepancy cited by the alleger would have a
-d potential detrimental impact on the health and safety of the public.
y, Since the witness, who had first hand knowledge of the valve repair,
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refuted the allegation, the IE inspector concluded that the allegation could not be substantiated.
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i DETAILS I
1.
Persons Contacted Principal Licensee Employees
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R. G. Tolson, Site QA Supervisor J. V. Hawkins, Product Assurance QA Supervisor R. V. Fleck, Startup QA Supervisor i
Former Brown & Root /TUGC0 Employee The Alleger, Former Brown and Root (B&R)
Brown & Root Employees Individuals "A" through "C"
- Other Personnel Two members of Citizens for Fair Utility Rates 2.
Investination a.
Allesation No. 1: Matters Identified in Newspaper Article On September 7, 1979, two IE inspectors met with the alleger at his apartment on the campus at the University of Texas (UTA),
Arlington, Texas. The interview was prearranged through a tele-phone conversation with the alleger on September 5, 1979 l ~
In attendance during the interview were guests of the alleger 1
?
who were introduced as members of an organization known as Citizens for Fair Utility Rates.
The alleger and his guests requested that the interview be tape
.l recorded, utilizing a cassette tape recorder and operated by the guests. There were no objections to the request as presented.
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The IE inspectors identified the " Shorthorn" article as the specific area of concern to the IE Regional Staff. Particular reference was made to the last few paragraphs which state:
" Asked if.there's a possibility defects in Comanche Peak construction have not been caught, the alleger said yes.
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s, How likely is that possibility?
"'How likely? It's a 100 per cent.'
" Asked if hs knew for sure that there are defects that will go into the plant, he again said yes. The dialogue went:
"Do you know how many such cases there are like that?
n,No.'
"More than 107
"'Yes.'
"More than 100?
"'Sure.'
l "More than 500?
"Long pause. 'Possibly.'
"Would they be in critical areas? Could it be in the cooling system?
"'It goes all the way across the board,' he said, 'from piping systems to electrical systems to electronic systems.'"
Findings The IE inspectors asked the alleger if he could be more specific in identifying the defects he was alluding to in the article. He responded with an affirmative statement and proceeded in relating, quite emphat-ically, numerous incidents that involved, in his opinion, work activi-
.l ties being done by unqualified and unconcerned workmen. Subjects a
alluded to by the alleger included rigging, protection of installed
, j equipment, setting of diesel generator components, control room panel discrepancies, etc. However, aside from material wastes in each of the incidents related by the alleger he acknowledged that, in every a
case involvine enfatv-ra1=+-d -^-aananta
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metinn~=ad/nF gli measures were taken to his satisfactinn and that what he may have I
.p conslucceu as oezects" did not go uncorrected. He further acknow-j ledged, that despite his frustrations in accomplishing his assign-ments, he was functioning as the job description dictates as a
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Allegation No. 2: Radioactive Material / Source
' '_i':S N was Dumped into the Comanche Peak Lake Reservoir
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In addition to the matter identified in paragraph 3 above, the
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but refused to identify) told him that, sometime between the period September 1978 and November 1978, the dispatcher had received an urgent telephone call from the warehouse area,
.l possibly Westinghouse, "to dispatch a truck and cherry picker ASAP."
The dispatcher responded accordingly. After some unspecified time lapse, the equipment operators returned and told the dispatcher that they had just dumped nondescript containers or objects marked j
" Radioactive" into the lake.
l The alleger could be no more specific than that stated above. He insisted on not identifying his source of information, but he did agree to contacting the person and attempting to encourage the person to contact the NRC Regional office.
Findings
~
(1) Interview with Individual "B" - Equipment Dispatcher h
Individual "B" was interviewed by telephone September 18, 1979.
l Individual "B" acknowledged being one of the Equipment Dis-t patchers during the period September 1978 through November 1978.
t Individual "B" stated that the incident, related to by the f
alleger was unidentifiable to Individual "B",
however, Indivi-l dual "C", also an Equipment Dispatcher during the same time j
span, may have some knowledge concerning the alleged event.
f (2) Interview with Individual "C" - Equipment Dispatcher i
j On September 20, 1979, through information provided by Individual "B", Individual "C" was interviewed telephonically.
ij Individual "C" acknowledged employment a's an Equipment Dispatcher during the time frame indicated by the alleger.
Individual "C" could not recall such an incident or event alluded to by the alleger. Individual "C" indicated that I
such an incident would be remembered and would have been s
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known to Individuals "B" and "C".
Furthermore, given the situation described co other individuals would be dispatching the equipment involved other than individuals "B" and "C".
.j The allegation appears to have no merit.
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Allenstion No. 3: Improper Welding / Repair Process
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TheallegetjwasaskedbytheIEinspectorsifhehadknowledge g"@
pf any "deig: cts" in other areas that he was aware of that went D
ancorrectet-He stated that a welder (whom he would not identify)
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itold him ttht he, the welder, improperly repaired a Steam Genera-
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- he alleger stated that the field weld was either FW-19 or FW-20.
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Intervie gg j
s.f DuringtheinterviewwithIn)1dduabE"In'SIpt'e'abeE1271979','~he~
stated that with reference to field welds W-19 and W-20, he had monitored the repair activities of the specific welds on a daily basis. To his knowledge, there was no area of repairs that would have penetrated into the carbon steel material. The work was completely controlled by the on-site Westinghouse Representatives who worked closely with each repair. Repair procedstres were developed by the Westinghouse, Pittsburgh office.. All work was done properly and all defects were properly removed and properly documented. Individual "A" stated that he could not agree with the alleger.
In addition, during a routine on-site inspection conducted October 11, 1979,1/ the IE Resident inspector reviewed the record documents and radiographs of the two field welds,
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W-19 and W-20 during his review of the piping installation activities. There were no discrepancies observed.
This allegation could not be substantiated.
d.
Allegation No. 4: Disassembly of 4" (or 6") Check Valve Without i
a Procedure l
An additional matter, specifically idcutified by the alleger, involved a repair to a weld that required, as he stated, "The valve body disassembly in order to accomplish the proper repair."
He related that a 4" tr a 6" stainless steel check valve, located in the borated water system, in the area of the component cooling 3d p ) q system, had a Nonconformance Report (NCR) written against the q
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not been properly purged during welding and there was evidence W
p d-of oxide on the inside surface. The alleger further stated that, j
A although the i jnde surface of the weld was_ correctly repaired,
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only have bein'~a 6omplished by dismantling the valve body. The
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with first hand knowledge of the specific uncorrected " defect."
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Findings f
Interview with Individual "A" On September 12, 1979, by a prior arrangement made by the IE I
Resident Reactor inspector, Individual "A" was interviewed at his home by two IE inspectors. Individual "A" acknowledged his 4
inspection involvement during the repair of the 6" stainless
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steel check valve identified by the alleger. Individual "A" stated that, "although there was no evidence to assume that the valve was disassembled, the repair was correctly made and I personally closed out the NCR, which received the proper engineering approval."
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QA RECORD Quality Assurance Depar M "'
, NCR NO. M-2869 Monconfomance Report (ICR)
CPSES-35-1195 PAGE /
OF 7
i DRAWING / IDENTIFICATION TAG /ID NLMIER LOCATION OR ELEVATION RIR NO.
BRP-CS-1-AB-002 FW-1 & FW-3 Amr. Ride.
810' N/A WNCONFORMING CONDITION T 0 4901 QI-QAP-11.1-26 5
2.1 END DOCINEAT VIOLATED:
CP-OAP-16_1 REY.
6 PARA. 2.1 CATEGORY M-12 1.
Hold points E & F on the above field welds have been by-passed.
RPS attached.
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DISPOSITION RESPON5IBILITY:
DISPOSIpHASSIGNEDTO:
CAR NO.f AliME CODE ITEM:
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REWG LK REPAIR USE AS IS XX SCRAP RETURN TO VEND 0R l
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The by-passed hold points have been indirectly verified per FDR-13,751 l
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No rework or repair is required.
j QA RECORD
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