Text

Insp Rept 50-344/89-12 on 890522-0601.Violations Noted.Major Areas Inspected:Review of Licensee NDE Procedures,Nde Records,Radiographs & QA Documentation & NRC NDE Personnel Reperformed Sample NDE on Safety Related Sys & Components
	ML20245L147
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	08/03/1989
From:	Mendonca M; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
Shared Package
ML20245L135	List: ML20245L130; ML20245L143; ML20245L147;
References
	50-344-89-12, NUDOCS 8908220007
	Download: ML20245L147 (16)
	v • d • e

'

p ]&Vif ,

>

a ,,

3 ]

.

a

pp

lb ;N.c '

-'

'

,

. .

h.w W

,

c - U.S.' NUCLEAR REGULATORI COMMISSION- 7

>

, , ,

,

1 i

' .'

'

i w

la ,, .

-

' REGION I

'

q , a

.g i ,i-

^

~

Report No. . 89-12 .y -

?g#L Q <%x. ,. .

.

3*' ,5 4 ,' ' - ( y

'

_ M sf. Docket No. 50-344- ,

.n -

-

jp

%gm[plicenseNo.

y,

- NPF'-li '

, y .

s-

'

, l > > l k.

'

.n

,

a% . ,

,

'

'- i 1,>

p y Licensee: <'121

y;.j% -

Portland General Electric

S.W. Salmon Street ".

,

',

-

i,-

f 1 ja

t4m

Portland, C.egon' 97204 j.

_ ,

l

>

,

}

V(,i

'

f i.{ ^ , Facility Name: ' Trojan. Nuclear Power Station i > d

- 4

a# ,

~

,

'

J' $ Inspection At: Oregon' _

%

,

%j ' Inspection Conducted: -May 22 through June 1, 1989 * N

- , Inspectors:- H.~W. Kerch, Senior Reactor, Engineer

'

.

.R.nH.' Harris, NDE. Technician

M. A. Oliveri, NDE Technician _ _

R.'C. Barr,. Senior.. Resident. Inspector, Trojan

.

~% % # g/3 /M

(Approvedby: cm < A

M. M. Mendonca, Chief Date Signed

. Reactor ProjectsSection I

'

h

'

Inspection Summary and Conclusions:- A routine, announced inspection was-

conducted- at Trojan Nuclear Power Station on May_22 through June 1,.1989.

,(ReportNo. 50-344/89-12).

" Areas Inspected: = The: inspection. included independent review of licensee-

nondestructive examination (NDE) procedures, NDE-records, radiographs and

, -_ quality assurance documentation. Qualified NRC NDE personnel also reperformed

a sample of_ nondestructive examinations on safety related systems and

components.

Results:= Based on this inspection,,significant weaknesses in Trojan's ISI

contractor performance and oversight of ISI contractor's activities such as

work performance, procedures, training of examiners and specific testing of

examinees. to site specific procedure requirements were identified. Five

violations and one unresolved item were identified during this inspection.

, . .

)

l

7

9908220007 890304

hDR ADOCK 05000344

-

PDC

t

4

'

' .- ' ._ .. _

_ _ _ _ _ - _ _ _ _

-

.

,

y -

.

'

DETAILS

I.0 PERSONS CONTACTED (30703)

PORTLAND GENERAL ELECTRIC (PGE)

'

Greg Kent " Supervisor Engineers

Mike Schwartz Branch Manager

, Bill Williams Nuclear Services

-

'

' Don Williams- Quality Services Supervisor

'*. ' Dan'Nordstrom Quality Assurance flanager

.'. , ,

D. W. Swan. Manager' Technical Services

'

' B. L. Baker Quality Services NDE Level III

Rick Neiman Inservice Inspection Level III

J 4 *; ' Carl'Shaw Staff Engineer ^

Norm Dyer Health Physicist Supervisor

Scott Bauer' Manager Nuclear Regulations

~

- * .

Paul Yundt General Manager

'

E * D. W. Cockfield ' Vice President.

- * J. D..Guberski Compliance Engineer

FACTORY MUTUAL INSURANCE

-Jerry Smoot Authorized Nuclear Inspector ANII

Denotes those attending the exit meeting.

The inspectors also. contacted other administrative and technical

personnel during this inspection.

2.0 INDEPENDENT MEASUREMENTS - NRC NONDESTRUCTIVE EXAMINATION AND QUALITY

RECORDS REVIEW OF SAFETY RELATED SYSTEMS

During the period of May 22 through June 1, 1989, an onsite independent

-inspection was conducted at the Trojan Nuclear Power Station. The

inspection was conducted by NRC Region I based inspectors, contracted

nondestructive examination (NDE) personnel and the Senior Resident

. Inspector. The purpose of this inspection was to verify the adequacy of

the. licensee's nondestructive examination and welding quality control

program. This was accomplished by duplicating, as nearly as possible,

the licensee performed examinations rcquired by codes and regulations and

comparing the results. The NRC examinations were performed on randomly

selected components from varirus safety related systems and were

performed in accordance with the ASME Boiler and Pressure Vessel Code,

Section XI,1983 Edition, ar,d to USAS B31.7,1969 through summer 1971.

Included in this examination were welds and pipe supports selected from

the Safety Injection (SI), Component Cooling (CC), Feedwater (FW),

Service Water (SW), Pressurizer Surge Line (PZR), Residual Heat Removal

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ __

W~ f '

~ ~

^

fx

^

'

L ( .i ., ', '- -

(

.

,

Q?

v.

l ?.h ,7 r- L' ' ' ' a r

w

'

L

_ n .p:

~

. -

eyu

. .

. g]J-

3

t ,

,

, y _

. c -

b ,

'

4

'

,j + ! < .

p r

> , ! Miscellaneous Vents:and Drains Systems. The items, selected were.

^n^ 3 .

-

previously inspected and accepted by the licensee as indicated by onsitei .

'

" " -

,

-

QA/QC documents. , ,

'

x . .

. ,.

.

+

, ,

, LIQUID PENETRANT' EXAMINATION (57070) ,

+

?- , .. . '

. , _

.. ,

',

Twenty-four safety related pipe weldments and adjacent base' material (i

-inch on either side of the weld) were examined on the outside surface of-

LL ;the pipe using the. visible dye penetrant method per NRC procedu.e NDE-9,

9 Rev. O in' conjunction with the licensee's procedure TNP-QAP-PT-ItA , Rev

m :2. Included in this~ examination were ASME Class 1 and 2 stainless steel

'

pipe weldments/solected from the Safety Injection (SI) and Residual Heat

- Removal (RHR)'syttems.

x

+ Results: No-violations were identified.

'

MAGNETIC PARTICLE EXAMINATION (57070)

-Fourteen 1 safety'relatedp'ipeweldmentsandadjacentcbasematerial(iinch

on each' side'of.the weld) were examined'using the dry magnetic particle

~

method per NRC procedure;NDE-6 Rev. O in conjunction with the. licensee's

procedure TNP-QAP-MT-100 Rev. 2. Included in this examination were ASME-

Class 2 carbon steel' pipe'weldments selected from the Feedwater (FW)

. system.

'

Results: No violations-were identified.

RADIOGR'APHIC EXAMINATION (57090)

u

Eight' safety related pipe.weldments were radiographer using an Iridium

192 source. The technique and procedure used were in'accordance with NRC

procedure NDE-5, Rev. 0.in conjunction with the licensee's procedures

QIP-17 Rev. O. A013-7.and associated drawings / isometrics and -

radiographic data reports. Included in this sample were ASME Class 1 and

'

2 pipe weldments selected from the Pressurizer (PZR) Surge Line and Feed-

< water (FW)' Systems. The. resulting radiographs were evaluated, and

,

compared with the licensee's radiographs.

. Result: Feedwater weld P25881R4 was rejected. (see next paragraph on

,

-radiographic review)

RADIOGRAPHIC REVIEW (73753)

A sample of the licensee's radiographs was reviewed. The inspector

reviewed twelve (12) feedwater modification and pressurizer surge line

,

J

,

.c field welds to verify compliance with USAS B31.7fcode requirements, ,

-accuracy of radiographic film interpretation, and adequacy"of the

licensee's radiographic examination program Additionally, the same

twelve 1(12) welds were re-radiographer by the NRC during this inspection s

and the resulting films were compared to licensee file film to - ,

independently verify that correct radiographic file film was on hand. a'

Attachment No. 1 identifies the specific welds that were radiographer by

,

the NRC.

-

i

"1

f-' *

. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

. _ _

_,

e 3 ,

,

'

.

) iJ _

Results: NRC radiographic film for feedwater weld P25881R4 disclosed an

elongated indication 3/8 inch in length that exceeded USAS.B31.7 Code

criteria.. A review of the licensee's code approved radiographic films

revealed the same indication in radiographic film area 22-34.- This

. indication had not.been recorded or dispositioned by the licensee,

although the weld did have final licensee acceptance. This is a

violation of USAS B31.7. (50-344/89-12-01) Subsequent to NRC

identifying the subject indication, the licensee performed a thorough

evaluation which included contour grinding; additional radiography, using

more sensitive radiographic film; ultrasonic examination; and flaw

evaluation in accordance with Section XI. The licensee's evaluation

(June 6, 1989 memorandum from M. H. Schwartz to D. W. Swan) states that

the indication in the original radiograph measure 0.365 inch in length

.but that evaluation in accordance with IWA-3360 and 3370 of Section XI

shows the indication is an acceptable laminar flaw. In addition, the

licensee's reradiography and ultrasonic inspections indicate that the

indication is most likely a result of surface conditions in the root area

of the weld which was subject to several repair welds.

<

' EROSION / CORROSION (57080) ,

'

b Eight safety and non-safety related pipe components were examined for

"; Ci erosion / corrosion using a Nova D-100 digital thickness gauge. The method

and procedures used were in accordance with NRC procedure NDE-11, Rev; O 's

in. conjunction with the licensee's procedure PEP-30-9 Rev. I and >

1

associated quality assurance records. Based on information supplied by-

,.

the licensee, the erosion / corrosion examination was performed on selected- '

,

- pipe components to determine if pipe wall thinning is present. The

'

thickness measurements were taken at predetermined locations. on the

- systems selected for inspection, especially on geometries most

susceptible.'to erosion / corrosion, such as elbows, tees =and reducers. The

. points inspected were on a 2 inch by 2 inch grid pattern. In some cases,

where more detailed information was required, a 1 inch by 1 inch square

grid was used. Included in this inspection were various size pipe

components selected from the following systems: Feedwater(FW),

Extraction Steam (EX), and Miscellaneous Vents and Drains (MVD).

Results: Based on the inspections performed, the licensee's inspections

for erosion / corrosion appeared to be performed effectively. No violations

were identified.

ULTRASONIC EXAMINATION (73753)

Six safety related pipe weldments were ultrasonic 1y examined using a ,

Sonic Mark 1 ultrasonic flaw detector per NRC procedure NDE-1, Rev. O, 1

Memphis Testing Services procedure QAP-UT-101 Rev. 1, and associated j

drawings / isometrics and ultrasonic test data reports. The instrument

calibration (linear verification) was performed per NRC procedure NDE-2,

Rev. O. A distance amplitude correction curve (DAC) was constructed

using the licensee's calibration standard PDR-7-RI. To ensure repeat-

ability of the ultrasonic examination, instrument settings and search l

units (transducers) were matched, as nearly as possible, to those !

indicated by the licensee's ultrasonic data reports. )

l

_ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _

_.

r

. 4

,., *

.

Results: No violations were identified. 4

'

l VISUAL EXAMINATION (57050)

?

Fifty safety related pipe weldments and adjacent. base material (i inch on

each side of the weld) were visually examined per.NRC procedure NDE-10,

Rev. O, Appendix A, in conjunction with the licensee's procedure

OAP-VT-108 Rev. O and associated drawings and quality. control documents. _

The examination was performed specifically to identify any visible cracks

or linear indications, gouges, leakage, or arc strikes with. craters or

corrosion which infringed upon the pipe serviceability during plant

operation. Mirrors,. lights and weld gauges were used to aid in the, ..

inspection and evaluation of;these weldments. ' Included in this' sample

were ASME Class 1 and 2 carbon and stainless steel weldments selected

from the Pressurizer (PZR) Surge Line, Safety Injection (SI), Feedwater

(FW), and Residual Heat Removal (RHR) Systems.

Results: No~ violations were identified.

VISUAL INSPECTION HANGER / SUPPORTS (57050)

During this inspection eighteen safety related hanger / supports were

visually examined per NRC procedure NDE-10, Rev. O, Appendix A and B in

.

conjunction with the licensee's procedure OAP-VT-108. Rev. 0; and,

associated site OC documents, isometrics, and drawings. Included in this

inspection were hangers / supports selected from the Service Water (SW) and

Component Cooling (CC)' systems. In the area of welding, the accessible

surface area and adjacent base material for a distarae of one-half inch

on each side of the weld was examined. In the area of component

integrity, specific ~ attributes looked for were proper installation;

configuration or modification of the component; evidence of mechanical or

structural damage; and corroded, bent, missing, loose or broken members.

Results: No violations were identified.

VISUAL INSPECTION GENERAL (73753)

During a walkdown inspection it was noted that anchor bolts for

structural steel members shown on drawing C-379, section "B", were skewed

at an angle and the nuts for these bolts did not appear to be in 100

percent contact with the baseplate or washers. The presence of fresh

grout was evident around the base of the supports and cracks were found

in the concrete wall under many of the support plates. Cracks also were

found urider the base plate shown on drawing C-379 detail 2. This

condition was common to all four steam generators.

These possible discrepancies were discovered late in the inspection and

turned over to the resident inspector for follow-up (0 pen item 89-12-07).

(See attachment No. 4 for sketch.)

The weld surface condition of feedwater piping modification welds that

fall outside the ISI program was considered marginal for examinations by

~

. - - - _ _ _ _ . _ . _ _ _ - - _ _ . _ _ - - - - - _ - _ .

-

un

g. ,. ;+

-

n -,. ,

,,.s

n x:- ms

_2 .

,y w'.%em.b

.

.6C

i g@,g ' .~

J p '

5,.

'

e

L

M'

r

1'; * '

,

v; y

,g wr . . .. .

x. , .

G M, ,4% , ,

'

, 't n

,

. ..[

w ,

, w <

'

,

. ,,

M

M# .all:four.NDE methods. Site-ISI' arid welding cognizant engihee sl

recognized the problem and were planning to change? appropriate; procedures

,

^

e

' % 'l

s

M. "to state NDE surface requirements.for all! future, class 2 weldments. '

s

N N ., "

' '

'

,

7, 3

B- 3.0 INSERVICE INSPECTION PROGRAM AND DATA REVIEW'(7N55)

D '

$ :The Trojan ISI l program is 1its second' ten' year interval. Trojan's ISI

, ,

sprogram'was prepared.by' Westinghouse:and is; implemented by the licensee.

The current ten year interval incorporates the requirements of the ASME-

Boiler and Pressure Vessel Code,Section XI 1983' edition and addenda

,

- through the summer of 1983. This was updated from the first 10 year-

'

Inspection plan which previously conformed to the' requirements of the

1974 Edition, Summer 75 Addenda.

'

'The inspector reviewed the following to ascertain compliance with

> '

applicable ASME code; requirements, lice...c w............, und regulatory

,

requirements.

'1The inservice inspection program.-

-

The. inspection plan .for the second. ten year interval.

t

. r

' Personnel certification: records for qualification of manual

y ,

..

ultrasonic' contractor, personnel.

L g' '

-

NDE records.,

ISI NDE procedures.

U ' '"

-Ultrasonic data for a Reactor Vessel Norrle indication on:the "A"

J hot leg.,

L' The' licensee's close out of the first 10/ year ISI interval.

.ISI action plan 88-035'.-

.The NRCLinspector also witnessed one ultrasonic examination and one

liquid penetrant examination of weldsLperformed by the licensee's

. contractor.

"

ilSI DATA REVIEW-

' A review of ~ISI ultrasonic' data for systems 330010, 010030, 011570,

035030 and 301120 reveaied the following deficiencies.

' '

The volume of weld examined was not properly documented,- ,

, Examination limitations were not properly documented,

No plots existed to assure proper ultrasonic coverage, g'

Characterization of detected ultrasonic indications were not

,

'

documented to indicate defects l verses geometric conditions,' .

~

-

Ultrasonic examination reports of record did not (have dis' position's

g,

v

as to acceptability of examination results.

QM This is a violation of Quality Assurance Procedure'0AP-UT-101 *

,

."

"C . requirements (50-344/89-12-04). "

, a

j ,k

< . ,-

@ Dur'in'g review of the. contractor's ultrasonic calibration data' sheets,it'he

h inspector noticed that changes were made by technicians ,that 'would .,'

N

.

s

'

require recalibrations; i.e., change of transducers (probes) from 0 to

>lg 45 and adjustment of controls other than the gain or attenuation. The _

s

y

w

.' ?> .s

$5y-

'

- = _ _ _ _ _ - _ _ _ _x.- - _ _ _ - - __ .-. _-- --

-. _- _ . - _ - - _ - -- . -_ _ - _ _

'

Y ' -

',

, .- ..

,

following welds 89-011580, 011620, and 011630 were identified by the NRC

,

.

,as: requiring recalibration~. Other discrepancies found were-the lack of

the use of simulator blocks to check for any change in calibration during

J. _the examination. It was determine that the technicians did not carry a

, simulator block to check! the system for the verification of the

instrament sensitivity and sweep range calibration at the start of the

examinations.

'

U This is a violation of Quality Assurance Procedure 0AP-UT-101

requirements. (50-344/89-12-03)

INSERVICE (ISI) EVALUATION OF CALIBRATION BLOCKS (73755)

-

During this inspection, the inspector reviewed documentation for

Ultrasonic Calibration Standards and Quality Control Data used at the

-Trojan Nuclear Power Plant. The review consisted of quality assurance

procedures and as-built drawings ~to determine calibration block size,.

' thickness,Eand configuration; notch dimension and location; and Certified

Mill Test Reports (CMTRs) to determine material specifications. In

addition to the above,'e sample of test blocks was physically evaluated

. by the inspector by taking dimensions and evaluating notch reflectors to-

determine if modifying. the calibration blocks would interfere with the -

'

establishment of. a primary reference point. A Sonic Mark i ultrasonic

flaw detector and scale (6 inch scale with divisions of 1/64th) were use

in this evaluation.

As'a result 'of the above review and evaluation, it was found that the-

-as-built' drawings of the calibration blocks-provided by the. contractor

1(Memphis-Testing Services, Inc.) were poorly drawn and did not delineate-

the actual type of notches as shown on the original drawings. Although

no changes had been made, all of the Memphis Testing Services drawings.

as close as could be, determined, indicated a buttress'crdss section notch-

configuration whereas the original drawings indicated a sawtooth cross

section configuration. A dimensional check of notch location found that

calibration blocks PDR-7-R1 and PDR-28 had notches whose' dimensions were

less than "T" from the edge (T being the thickness.of the ' material) of

.the calibration block. ASME Section V articl'e 5, Fig.'T-542.8.1.1 .

specific notch dimensions, indicates that the location:of. notches be no-

closer than "T" from any block edge. An examination of these calibration'

blocks using an ultrasonic flaw detector determined, how' e ver, that the '

notches "as-built" did not interfere with the primary referenc'e or

distance. amplitude correction curv'el(DAC). The'l.icensee.has committed to- 4

making better as-built drawings andiis continuing' the re-examination of

2

,

all the ISI blocks. "

1 -

ISI REFERENCE MARKING SYSTEM gi

During this inspection it was determined that the ASME Section XI andL~

site procedure QC-RT-1 required marking: systems were not being adhered:to >

for weld center lines and the reference 2ero. points with direction of .

inspections. Welds P-28372 and P-25893 each had two zero reference ,

- -- _

nj m .

- - -

.

-- -- - -

'*

a'

.,

-7

1

,

7 , ,

,

1 _

starting' points with opposing directions of examination. stamped. Welds

-P-25894, P-25897 and P-25876 had no zero' reference starting points

indicated. Weld P-25875.had no weld identification marking. Some of

these welds-are Class 2 and the licensee indicated they may not be

' -

included intthe sample identified for inspection under the ISI

program. .Nonetheless, the requirements of the Code must be followed.in

, . performing baseline inspections. Lack'of, or inadequate marking on these

."

welds could hinder future ~ISI data evaluation if.the sample of Class 2

welds is required to be expanded in accordance with the Code.

This.is a violation of NRC requirements. (50-344/89-12-02)

ISI QUALIFICATION / CERTIFICATION OF CONTRACTOR PERSONNEL

. lTheinspectorreviewedthetraining,qualificationandcertificationof

ISI contractor personnel as stated in procedure MTS-QAM-300 Revision 0.

The, certification 'and~ qualification process includes general theory,

specific and practical examinations. The specific examination covers

-

plant- specific assignments, codes, standards and procedures. Paragraph

.

8.1.3 of the procedure states: " Specific examination shall cover equip-

ment operating procedures,; test techniques and codes that the examiner

may encounter in specific assignments. The examination may be

administered as an op'en book test (emphasis added)." SUT-TC-1A(1980)

paragraph 8.3 states "The written examination should be administered

without access to~ reference material (closed book) except thatlnecessary

data, such as graphics', tables, specifications, procedures, and codes,

may be~provided. ASNT. Inquiry '77-5 clarifies the ASNT position with

regard to what is~ meant by." closed book".for the specific examinations.

-

It. states that'for sections of the spec.ific examinations reference

material may be supplied, provided the reference' material cannot. answer

. questions related to other closed book portions of,the specific

-

. examinations. .The review of the NDE' contractor's specific examinations

a' by the.NRC revealed that the examinations included questions related to

ASME Section V. However, the NDE methods. article of Section V was '

e

% provided.to the examinees during the examination; consequently, providing

[ the answers to the examination questions.- In addition, the specific

examination did not include any questions related to site ' specific ,

requirements. The NDE technicians working.for this contractor do;not ' )

necessarily have,any previous' site specific procedure training for this'

, facility. .

^,

The procedures for personnel qualification, training, and examination and. -

' certification'of NDE personnel at the site are inadequate to assure i

complete compliance to code requirements. This is b violation.

(50-344/89-12-05) This deficiency in the certification and qualification

program contributed to the other ISI deficiencies identified during this

inspection.

A

ISI OBSERVATION OF WORK / ACTIVITIES (73753)

During this inspection the inspector witnessed non-destructive examina- i

tions performed by Memphis Testing Services's NDE level II technicians. I

1 Specific activities observed were ultrasonic and liquid penetrant exami-

nations. . Activities observed during the ultrasonic examination are as

1

!

. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ !

_ ,. .

.

. .. .s .g7

- -

, , .

s

t-

, follows; instrument calibration, construction of a distance amplitude

correction curve (DAC) and subsequent examination of pipe weld 89-00104.

, Theiultrasonic examination' observed was performed in accordance to

", Memphis Testing Service procedure QAP-UT-101, Rev. 1. The activities

-observed giuring the liquid penetrant examination were as follows; visual

examinations of the test surface for anything that may interfere with the

inspection, a. temperature check of the material, cleanliness check,

a3 penetrant application,' dwell time, removal of penetrant, application of

' 5 the developer;and an evaluation of the results. The liquid penetrant

,

examinations observed were performed in accordance with Memphis Testing

Service l procedure QAP-PT-100 Rev. O.

No violation were identified; however, at the start of the ultrasonic

examination it was found that the ultrasonic instrument in use did not

maintain screen height linearity. Due to.the instrument problems

mentioned above the technician had to replace and recalibrates a new

instrument.

ISI CLOSE OUT

l

4

The inspector reviewed the licensee's actions to assure that Trojan's

f_irst ten year interval ISI was accomplished in compliance with the FSAR

and ASME boiler and pressure vessel code section XI, 1974 edition through

summer 1975 addenda. The following were reviewed:

,

-

PGE's' letter to Westinghouse, RLS-273-86PW1803, dated March 6, 1986.

1.

-

Memorandum SAM-5-86m dated August 28, 1986. (Summary of the first

ten year program close out.)

-

Westinghouse letter POR-28-527 dated September 19, 1986 (Reference

PGE letter RLS-273-86 PW1803 dated March 6, 1986).

'

PGE's March 6, 1986 letter to Westinghouse documented their review of the

first ten year inspection interval and identified several inconsistencies

and missed inspection items. The missed inspections were scheduled to be

performed during the 1986 outage. However, NRC review of the 1986 outage

. ISI records revealed that support SR 122 (RH-250IR-19-2), identified in

l the March 6 letter, had not been inspected as required. The licensee had

not identified this overdue inspection and no nonconformance report had

'

been issued. Subsequent to the NRC identifying the missed inspection,

the licensee performed visual examinations of support SR-122

(examinations 308440 and 308445) and issued nonconformance report 84-214

, requiring rework of the support. NRC did not perform a complete review

of all the ISI records to determine if additional inspection items from

the first ten year inspection interval have not been completed. This j

item remains unresolved pending licensee review of the ISI program j

records to determine if any additional first interval inspections were l

missed (50-344/89-12-06). j

I

l

1

l

I

'

_ _ _ _ _ _ _

y. .

-

g

, ,

. w . m .

-

'

. 2n 9 . _

[: 4; C *

[M

F

y. . ,

3

I , ,

,

'

,

ys

~ '

y r v , .

'

gu , y- '4.0$ REVIEW 0FSITENDEPROCEDURES'AND.MA'UALS N s . ,

' '

The procedures' listed in Attachment 5.0 werel reviewed in the-reg'ional

.~ office during this inspection period for Lcompliance to the licensee's ~

FSAR commitments and applicable. codes, standards and, specifications.

i . . . .

.. t

!

Results: .. No violations were identified.:. However, procedure 0AP-UT-101

Rev. 1, which was in compliance.did not give adequate guidance to the

.

, technician during -instrument calibration, consequently procedure

OAP-UT-101 Rev.1, was. revised to insure a; standard guidance for the

instrument. calibration. The inspector.has no other concerns about this

issue.-

, 5.0 ATTACHMENTS- >

Attachment. No.1 is a . tabulation of' specific pipe weldments and

'

components examined with results.

Attachment No. 2 is a. tabulation of specific pipe components examined for

erosion / corrosion'with results.

Attachment No. 3 is'a -tabulation of specific hanger / supports examined

with results. .

= Attachment No. ~4 is a section of Bechtel drawing (C-379) of the Main

-

Steam Line. Supports.

'

Attachment.No. 5 is a list of the ND$ procedures reviewed by the NRC

inspectors.

'6.0 UNRESOLVED ITEMS

Unresolved items.are matters about which more information is' required in

Lorder to ascertain whether they are acceptable items or violations.

Section.3'.0 ISI CLOSE0VT contains an unresolved item.

'7.0 Management Meetings (30703)

The licensee's management was informed of the scope and purpose of the

'

inspection at the entrance interview.on May 23, 1989. The findings of

the inspection were discussed with the licensee's representatives during

the course of the inspection and presented to the licensee's management

at the' exit interview on June 1,1989 (see paragraph!1.0 for attendees). 1

. At no time during the inspection was written material provided to the

licensee by the inspector. =The licensee did not indicate,that

proprietary information was involved within the scope of this inspection.

'

~

% s

.

'

.

i

. . l,

4

, I

-

.

1

. _ - . .

. c: , _. . y

L l ATTACHMENT'01 INDEPENDENT MEASUREMENTS : INSPECTION SHEET 1.OF 2

LSITELTROJAN NDE PIPING /WELDMENTS DATE: 5/22-6/2/89-

ISO /DWG WELD ID SYS CL. RT MT' PT UT VT ACC REJ COMMENTS

EBB-3 P-25889. FW 2 X X X X

i

EBB-3 NO-02226-C FW 2 X X X

EBB-3 P-25919 FW 2. X X X X

EBB 3-1 P-2597R4 'FW 2 X X X

~ EBB 3-1 P-25971. FW. 2 X X X

.

DBD3-3 P-28626 FW 2 X X X

2501R-31-5" 89-011620 SI 2 X X X

2501R-31-5 89-011630 SI 2 X X X

z2501R-31-5- 89-011570- SI 2 X X X

~2501R-31-5 89-011580 SI. 2 X X X

RC2501R20-1' P28371 PZR 1 X X X

RC2501R20-1 P28372 PZR 1 X- X X TWO"O" MARKED

2501R19-1-1--' FW4987 SI- 2 X X X

2501R19-1-1 SW-A- SI 2 X X X

2501R19-1-1 SW-B_ SI 2 X X X-

.

2501R19-1-1 SW-DL SI 2 X X X

2501R19-2-1' SW-D' RHR 2 X X X

SW-C RHR 2 X X X

2501R19-2-1

RH-2501R19-3 FW4994 SI 2 X~ X X

SW-B SI 2 X X X

5

2501R19-3-1

SW-C SI 2 X X X

2501R19-3-1

2501R19-3-1 SW-D SI 2 X X X

2501R19-3-1 SW-E' SI 2 X X X ;

i

SW-G SI 2 X X X

2501R19-3-1-

EBB-3-1 P-25893- FW 2 X X X TWO"O" MARKED 1

l

2501R22-653 FW-20444 SI 2 X X X NRC/ WITNESS

-[i i d

u

- _ _ _ _ _ _ _

< vs

w , r. ;

'

t <1

4TTACHMENT 4f1- INDEPENDENT MEASUREMENTS INSPECTION SHEET 2 OF 2

[

P SITE: TROJAN NDE PIPING /WELDMENTS DATE: 5/22-6/2/09

. ISO \DWG WELD ID SYS CL RT MT PT UT VT ACC REJ COMMENTS

601R-1-1-1 SWB SI 2 X X X

~

l

601R-1-1-1 SWC SI 2 X X X

601R-1-1-1 SWD SI 2- X X X

601R-1-1-1 SWE SI 2 X X X

l .

l 601R-1-1-2 SWC SI 2 X X- X

L

\

601R-1-1-2 SWE SI 2 X X X

l

601R-1-1-2 SWF SI 2 X X X

601R-1-1-2 SWA SI 2 X X X

601R-1-1-2 SWB SI . 2 X X X

601R-1-1-2 SWC SI 2 X X X

601R-16-2 FW-1480 SI 2 X X X

EBB-3-2 P-25881 FW 2 X X X SEE PARA.

3.4.4-45 010130 SI 1 X X X

3.4.4-45' 010140 SI 1 X X X

EBB-3-1 P-25892 FW 1 X X X

EBB-3-1 P-25893 FW 1 X X X

EBB-3-1 P-25894 FW 1 X X X NO"O" STAMP

EBB-3-1 P-25897 FW 1 X X X NO"O" STAMP

EBB-3-1 P-25898 FW 1 X X X

EBB-3-1 P-25875 FN- 1 X X X NO WELD ID

EBB-3-1 P-25876 FW 1 X X X NO"O" STAMP

EBB-3-1 P-25877 FW 1 X X X

EBB-3-1 P-25976 FW 1 X X X

-

EBB-3-1 P-25914R-1 FW 1 X X X

_J

l

TOTAL 8 14 24 6 50 49 1

.

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _

_ . _ _ . -- _ .- . _ _ _ _ - . _ -

,i *

, . .

"

@ TTACHMENT. 462 INDEPENDENT MEASUREMENTS.. INSPECTION E

. SITE: TROJAN EROSION / CORROSION DATE: 5/22-6/2/89-

ISO \DWG WELD ID UT VT ACC REJ SYS CL. COMMENTS l

l

FIG-HBD9-1 MVD-28-7 X X' X MVD BOP MISC. VENTS AND DRAINS (MVD)

FIG-HBD9-1 MVD-28-6 X X X MVD BOP

FIG-HDD9-1 MVD-28-5 X X X MVD BOP

FIGGCD12-1 XS-1-4 X X X EX BOP EXTRACTION STEAM (EX)

FIGGCD12-1 XS-1-3 X X X EX DOP ,

FIGEBD6-2 FW-33-2 X X X FW BOP FEEDWATER CFW)

l' FIGEBD6-2 FW-33-3 X X X FW BOP

FIGEBD6-2 FW-33-4D/S X X X FW BOP

TOTAL (8) PIPE COMPONENTS

PLANT ENGINEERING PROCEDURE

FEP-30-9

1'

l

_

l

,

j

___ . - . . ~ , . - . ~

~

J

l

- . _ _ _ _ ._ - - - - - - _ _ _ _ _

.

-)

( .- _ _ _

,

-

...,'

'

0 ATTACHMENT #3 INDEPENDENT MEASUREMENTS INSPECTION

SITE: ' TROJAN. HANGER / SUPPORT INSPECTION DATE: 5/22-6/2/89

PGE/ ISO HANGER / SUPPORT SYSTEM CLASS ACC REJ COMMENTS l

, .HDD-30-1 H8A CC 3 X AUX. BDLG,

y

l;iHBD-30-2 H4 CC 3 X AUX. BDLG.

I HDD-30-2 SR7 CC 3 X AUX. BDLG.

'HBD-30-2 SR220 CC 3 X AUX. BDLG.

.HBD-28-1 H2 CC 3 X AUX. BDLG. .

1HFD-3-4 SR18 SW 3 X AUX. BDLG.

HFD-3-4- SR19 SW 3 X AUX. BDLG.

l

HFD-4-4 SR35 SW 3 X AUX. BDLG.

HFD-5-4 SR46 SW 3 X AUX. BDLG.

HFD-5-4 SR47 SW 3 X AUX. BDLG.

HFD-5-4 SR48. SW 3 X AUX. BDLG.

HBD-28-1 H2A CC 3 X AUX. BDLG.

HBD-28-1 H2A (WELD) CC 3 N/A AUX. BDLG.

HBD-28-2 SR5 CC 3 X AUX. BDLG.

HBD-28-2 SR6 CC 3 X AUX. BDLG.

'

HBD-28-2 SR238 CC 3 X AUX. BDLG.

HBD-28-1 H12 CC 3 X AUX. BDLG.

>

HBD-30-2 SR220 CC 3 X AUX. BLDG.

I

,

.I

i

l

l'

TOTAL ,

!

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

, - - - _ - , . - - . _ - -

,ls*f

. .(_ op o-

. .

I

,

"

$enil @vs$ 1n

L{ ?$ h 6M [.

'

l $*; -

$ N

.

,

2n . t*a sl*

h b

l w

3

L

- 5a ;w

- - ,_ se = --

u{ a s p.

'g !wE

-

e

-

,

-

0 :W

5 A

m

M.g 3

5j $ 24

4 .

< -

9

.

A.. .

~*p:

';[, .t t-

\ . ..... n . % %r ~ ~;

, $. < .

.D % ,.e ' {g f l

,

6i .'

) ; , ;

IU !

NIM

6

. ~

1l'*

1

7

-

l .

.

-

4( 8

Np. ,

(

.

'

..

& ,1 N> % 3

O

.

.$,.

s

-

.n U

Q wt to

,

-

& Y *

w b.

,

-

o Q

xg

. , '

' ' .~t -

,,,.- s .J

_ . . _ .h wu .I s

. \ . _.

c. .; :

, eq '

t

{

j'

M

.

3

,- -. -

. .

-.

'

.k ~[.... .

'....,

. . ,

.g.: .mr-) - - - -l- , - - - --) ue ) - , -

.. j. k ., e. n

-

, ,

. ,

1 e .b .

i

1 ,

'

- - .

'

- '

'z , 1:

i

..

\ v 2

i. -

-

.,

'

[ .'

h

-

- .

Y . .

(g I \'

& t ...

N

j

l'

l !

.!

t

.

I, 'k / I

{ \s \ '

.. . .:

,/ :

<

.

-

I

\ .

.i w m i

l \ * D )'

. ,I- M L

'

J c-

-

.%- s er

.

s\ C. .

. _ _ _

N 0

lq 'N- 4~ /~ \ . , ,

. \.I

x

,

-

o <

e w ,

. 9

il { *

'N

\ Q Oy

Q

-

c 3, -).' -

f

, 3,< v

[

-

\ o

s

g-

s

.

,

.[.

.

i.._V. .Y .......__.l 1 oy

O-

'

\'

, .s,t.

,

~ , , . .. .. ..

g %, ,

%' 'f

Q.

t

j' .

. . . ,

-

to '

.s

. . :* . '

.

. O! .'. * .:

- - '-

=J:

9

e

'

O

. .

4

.

. .~. . ' 4. .

_- _ _.

- ' . . , *

"

, - + * *

..

.

"

ATTACHMENT 5

, , PORTLAND GENERAL ELECTRIC (PGE)

PROCEDURE TITLE REVISION /NO. <

t

RADIOGRAPHIC EXAMINATION QIP-17 REV. 0

CONTROLS AND INTERFACES .FOR CONTRACTORS QCP26 REV. 1 ..

PERFORMING RADIOGRAPHY ONSITE INSPECTION ;

FIELD '

CONTROL OF SITE RADIOGRAPHY AD13-7 '

ULTRASONIC THICKNESS MEASUREMENTS QIP-9 REV. 1

PLANT ENGINEERING PROCEDURE PEP-30-9 REV. 1

EROSION / CORROSION

.PITTSBURGH TESTING LABORATORY

RADIOGRAPHIC EXAMINATION -

QC-RT-1 REV. 16

MEMPHIS TESTING SERVICES, INC.

TRAINING, QUALIFICATION AND CERTIFICATION MTS-QAM-300 REV 0

JF PERSONNEL

"

VISUAL EXAMINATION QAP-VT-108 REV. O

,

NONDESTRUCTIVE EXAMINATION TNP-QAP-UT-109 REV.0

PROCEDURE ULTRASONIC

{

MANUAL EXAMINATION OF FULL QAP-UT-101 REV. 1 !

PENETRATION BUTT WELDS

'

QAP-UT-101 REV. 2

TOWNSEND AND BOTTUM-SERVICE GROUP INC.

L

ULTRASONIC INSTRUMENT LINEARITY TNP-QAP-CP100 REV. I j

PERFORMANCE CHECK !

LIQUID PENETRANT EXAMINATION TNP-QAP-PT-100 REV. 2 )

MAGNETIC PARTICLE TNP-QAP-MT-100 REV. 2 j

i

MANUAL ULTRASONIC ZERO DEGREE QAP-UT-102 REV. O I

EXAMINATION

ULTRASONIC EXAMINATION OF BOLTING QAP-UT-103 REV. O

ULTRASONIC EXAMINATION OF QAP-UT-104 REV. O

STAINLESS STEEL MATERIAL

ULTRASONIC PLANAR FLAW SIZING QAP-UT-107 REV. 0

]

ML20245L147

Text

Navigation menu

Search