ML19257D278

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IE Insp Rept 50-338/79-43 on 791030-1101.No Noncompliance Noted.Major Areas Inspected:Inservice Insp Activity & Response to IE Bulletin 79-17
ML19257D278
Person / Time
Site: North Anna Dominion icon.png
Issue date: 11/29/1979
From: Economos N, Herdt A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML19257D276 List:
References
50-338-79-43, IEB-79-17, NUDOCS 8002040016
Download: ML19257D278 (7)


See also: IR 05000338/1979043

Text

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION

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101 MARIETTA ST., N.W., SulTE 3100

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AT* \\NTA, GEORGIA 30303

DEC -41979

Report No. 50-338/79-43

Licensee: Virginia Electric and Power Company

Richmond, Virginia

23261

Facility Name: North Anna 1

Docket No. 50-338

License No. NPF-4

Inspection at Noryt. Anna Site near Mineral, Virginia

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Approved by:

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A. R. Herdt, Section Chief, RC&ES Branch

Da'te Signed

SUMMARY

Inspection on October 30 - November 1, 1979

Areas Inspected

This routine, unannounced inspection involved 24 inspector-hours onsite in the

areas of inservice inspection activity and IE Bulletin 79-17.

Results

Of the two areas inspected, no items of noncompliance or deviations were

identified.

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DETAILS

1.

Persons Contacted

Licensee Employees

  • W. R. Cartwright, Station Manager
  • J. W. Martin, Supervisor, Quality Arsurance
  • E. W. Harrell, Superintendent of Maintenance
  • H. L. Travis, Mechanical Foreman - NDT
  • C. B. Swope, Senior QC Inspector
  • W. R. Madison, NRC Coordinator

Other licensee employees contacted included technicians, security force

members, and office personnel.

Other Organizations

Westinghouse (W) - NSD

E. Conrad, Site Coordinator

Nuclear Energy Services, Inc. (Conam Division)

M. Dobson, Level II Examiner

R. Lofgren, Level II EC-Interpreter

NRC Resident Inspector

M. Kidd

  • Attended exit interview

2.

Exit Interview

The inspection scope and findings were summarized on November 1, 1979 with

those persons indicated in Paragraph 1 above. The inspector identified the

areas inspected which included procedure review work observation and record

review relative to ISI activities under way in Unit 1.

3.

Licensee Action on Previous Inspection Findings

Not inspected.

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4.

Unresolved Items

Unresolved items are matters about which more information is required to

determine whether they are acceptable or may involve noncompliance or

deviations. New urresolved items identified during this inspection are

discussed in paragrpah 7.

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5.

Inservice I.,spection - Review of Procedures

a.

Procedure Technical Content

Procedures governing the inservice inspection (ISI) of components

listed in ASME Section XI, IWB-2000/IWC-2000 were prepared by W and

approved by VEPC0 for use during this ISI interval. A review of

selected procedures was performed on a previous inspection documented

in IE RII: report 50-338/79-40. This procedure review was a followup

effort, performed to conclude work in this area.

The inspector reviewed

magnetic particle inspection procedure ISI-70 Rev. O in order to

ascertain whether it was consistent with applicable code requirements.

The code governing ISI procedures and activities is ASME Section XI

(74S75). The aforementioned procedure was revicwed in the areas of

surface preparation and temperature at the time of testing, type and

color of particles used, extent of exe ination and direction, prod

spacing, magnetizing current levels a 2 ut asity, lif ting power and

pole spacing requirements when the Joke method is employed and accep-

tance criteria.

VEPCO's eddy current procedure NDT 14.1 Rev. 7.3 has been written to

comply with RG 1.83 (RG) and has been approved for the examination of

Steam Generator (S/G) tubes. This procedure was reviewed in order to

ascertain whether it specified the equipment to be used, test parameter,

examination method, calibration, acceptance criteria.

Within this

area the inspector noted that the procedure did not specifically

address / require re-test of tubes examimed during an interval wherein

calibratioa had drifted. This matter was discussed with the licensee

representatives who agreed to address this area in the forthcoming

procedure revision. This matter was identified as inspector followup

item 338/79-43-01, "Calitration Drift-tube Reexamination".

b.

Procedure Scope

The inspector selected four (4) areas subject to examination during

this outage as specified in IWB-2500 and IWC-2500. The selected areas

were as follow:

IWB-2500

AREAS

CATEGORY

ITEM

Closure llead Weld

B-C

1.3

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Reactor Vessel Outlet

Nozzle

B-F

2.1

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IWB-2500 (Continued)

AREAS

CATEGORY

ITEM

Pressurizer

Long. and

Circumferential

B-B

2.1

Pressurizer Support

Skirt

B-F

2.8

IWC-2500

Steam Generator

Circumf. Welds

C-A

1.1

Steam Generator

Nozzle Welds

C-L

1.2

Integrally Welded

Supports

C-E-1

2.5

Piping

C-F

2.1

For the above items the Inspectior Program Plan was reviewed to ascer-

tain whether the specified category, method of examination and extent

were delineated and consistent with applicable code requirements.

Within the areas examined, no items of noncompliance or deviations were

identified.

6.

Eddy Current Examination of Steam Generator (S/G) Tubes

Eddy current (EC) examination of the tubes in S/G "C" was underway at the

time of this inspection. The examination is being performed with procedure

NDT-14.1 Rev 7.3 discussed earlier in this report.

Selection of steam

generator and tube sample per steam generator is controlled by Technical

Specifications (TS) paragraphs 4.4.5.1 and .2.

Discussions with the licensee's representative disclosed the finding of two

" leakers", located in row I columns 51 and 60 in steam generator "C".

The

rupture / defect was believed te be located in the U bend region of both

tubes.

In addition the licensee representative stated that the EC examina-

tion showed extensive tube denting existed in cost of the tubes examined in

S/G "C".

This condition was demonstrated by reviewing examination of

randomly selected tubes recorded on magnetic tape. These tubes were identi-

fied as follows: RIC1, R3C1, R6C1, R7C1, R46C41. Discussions with operators

and those involved with the examination disclosed that because of the

denting a 0.650" diameter probe had been substituted for the 0.700 diameter

probe normally used. Examination of tubes in S/G "A" was scheduled to

start later in the month. The licensee representative stated that SG "B"

would probably be examined during this outage.

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The inspector uitnessed the EC examination of SG "C" tubes R43C32, R44C33,

R42C33, R3C33, RIC33 and R42C34, revieweo: examination results, equipment

and personnel certifications; system calibration and calibration standard

quality records.

Within the areas inspected no items of noncompliance or deviations were

identified.

7.

Inservice Inspection - Data Review and Evaluation

Selected NDE records generated during this ISI period were reviewed in

order to ascertain whether the reported extent of on going examinations

rela.tive to class 1 and 2 components were consistent with T. S. commitments

and met minimum percentage examination requirements as specified in the

applicable code.

Records from several areas examined during this outage were reviewed to

ascertain whether they contained reference to examination results and data

sheets; examination equipment data, calibration data sheets; evaluation of

data, extent of exaraination, deviations from programatic requirements,

disposition of findings and identification of NDE material. Records selected

for the above work effort were as follows:

,

CLASS 1

Area

Weld #

Sketch #

Branch Connection and

1,4,5,7,8,9

VRA-1-4100

Long/Circumfer. Welds

VRA-1-4102

Integr. Welded

WS-1, WS-2

VRA-1-4102

Supports

Dissimilar Welds

16, 17, 21

VRA-1-4101

CLASS 2

Area

Weld #

Sketch #

Circumf. Butt Welds

1,4,7,10

VRA-2-2540

In addition records from pressure retaining pipe welds in various Class 1

and 2 systems were reviewed to ascertain whether unacceptable deviatione

existed between initial and final system calibrations; documentation of

examination data and recordable indications was complete and accurate; data

evaluation was performed by qualified personnel and that it was consistent

with code / procedure requirements and, whether incomplete examinations and

results were ' repeated to permit full evaluation as applicable.

Within these areas tile inspector noted that in cases where full examination

of a weld was not possible because of configuration inaccessibliity, welded

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attachments etc.

the record described the examination only as " partial"

without quantifying the extent of the limitation.

The inspector stated

that limited examinations needed to be more fully delined in order to

provide an accurate record of examinations performed on these welds. The

licensee representative agreed to look into this matter and the inspector

stated that it would be identified as unresolved item number 338/79-43-02

" Description of partial examination of welds".

Within the areas examined, no items of noncompliance or deviations were

noted.

8.

Inservice Inspection - Observation of Work and Work Activities

The licensee ISI program plan for this outage, (I-II,1979), was reviewed to

ascertain whether nondestructive examinations met T. S. and ASME Section XI

(74,S75) requirements relative te number of items to be inspected; methods

and extent of examination.

In addition the inspector witnessed the following:

1.

Volumetric examination (UT) of weld 12DM, sketch VRA-1-4301,

Pressurizer Surge Line.

2.

Surface examination of weld 12DM, sketch and line same as above.

3.

Eddy current of S/G "B" tubes listed below:

R0W

COLUMN

43

32

44

33

42

33

03

33

01

33

42

34

The above examinations were performed in accordance with applicable code

and/or R.G. requirements and the approved NDE procedures as applicable.

Within the area inspected no items of noncompliance or deviations were

identified.

9.

IE Bulletins (IEB)

IEB 79-17, Pipe Cracks in Stagnant Borated Water Systems at PWR Plants

(Unit 1).

The inspector discussed the Bulletin with responsible licensee personnel.

The licensee has identified the affected systems, responded to Part 1 of

the Bulletin, and is in the process of establishing a sampling plan for the

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inspections required by Part 2 of the Bulletin.

'EPC0 has requested an

extension for the time allowed to perform the inspections required by Part

2 of the Bulletin.

Within the areas inspected, no items of noncompliance or deviation were

identified.

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