ML20150B637

Insp Rept 50-364/78-12 on 780905-08.No Noncompliance Noted. Major Areas Inspected:Independent Insp Effort & Review of Reactor Coolant Piping,Quality Records & Welding

ML20150B637
Person / Time
Site:	Farley
Issue date:	10/20/1978
From:	Conlon T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20150B640	List: IR 05000364/1978012 ML20150B637 ML20204B821
References
50-364-78-12, NUDOCS 7811020360
Download: ML20150B637 (5)

See also: IR 05000364/1978012

Text

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UNITED STATES

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h [ga aEGoq'cq NUCLE AR REGULATORY COMMISSION

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101 M AHIE TT A ST R E E T, N.W.

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Rem rt No.: 50-364/78-12

' Docket No.: 50-364

l License No.: CPPR-86

l

l Category: A-2

Licensee: Alabama Power Company

Post Office Box 2641

Birmingham, Alabama 35291

Facility Name- Joseph M. Farley Plant, Unit 2

Inspection at: Ashford, Alabama

Inspection conducted: September 5-8, 1978

Inspector: P. K. VanDoorn

Reviewed try:- _ -( c;r et/ ,r /.'

T. E. Conlon, Chief Date

Engineering Support Section No. 2

Reactor Construction and Engineering

Support Branch

Inspection Summary

Inspect ion on September 5-8, 1978 (Report No. 50-364/78-12)

Areas inspected: Routine unannounced inspection of safety related piping

work activities and quality records; reactor coolant pressure boundary piping

quality records; safety related structures quality records. The inspection

involved 25 inspector-hours on site by one NRC inspector.

Results: No items of noncompliance or deviations were identified.

781102o36o

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R11 Report No. 50-364/78-12 I-1

DETAILS I Prepared hy: '/ ,_

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P. K. VanDoorn, tietallurgical Engineer

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Engineering Support Section No. 2

Reactor Construction and Engineering

Support Branch

Dates of Inspection: September 5-8, 1978

Reviewed by _ -8 n m v<- //Da (e &

T. E. Conlon, Chief

Engineering Support Section No. 2

Reactor Construction and Engineering

Support Branch

1. Persons Contacted

a. Alabama Power Company (APCO)

• J. A. Mooney, Project rianager, Const ruction

• R. E. Hollands , QA Supervisor

• J. C. Payson, QA Staff Engineer

• R. S. Fucich, QA Engineer

• J. G. llegi, Project QC Engineer

hD. B. Hartline, QA Engineer

b. Cont.ractor Orjaniztion

Dainel Construction Company (DCC)

kl. F. Warrick, Construction Manager

hL, C. Easterwood, QC Manager

kF. L. Thomas, QA Engineer

B. B. Marchman, QCDS Supervisor

S. King, QCDS Engineer

L. T. Chandler, QCDS Engineer

hDenotes those present at the exit interview.

2. Licensee Action on Previous Inspe_ction Findi_ngs

(0 pen) Unresolved Item (364/78-09-01): Verification of Anchor Bolt

Lengths. This item was originally iaentified en June 23, 1978. It

concerned establishment of a measurement based system to provide

verification of the proper length of anchor bolts. The inspector

reviewed actions which had been completed to date DCC has randomly

ultrasoncially tested 104 previously installed anchor bolts and has

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Rll Report No. 50-364/78-12 1-2

identified four bolts of improper length, all associated with large

hangers. Statistical analysis is sti]] in progress to determine the

number of additional bolts to be tested.

In addition to the above a program for testing of all newly installed

anchor holts was initiated on July 17, 1978. No lengt h deviations

have been identified to date as a result of this program. This item

will be reviewed in detail at a later date.

3. Unresloved items

No unresolved items were identi fied during this inspection.

4. Independent inspection Effort

a. The inspector conducted a general walk-through inspection of the

containment and auxiliary buildings to observe construction pro-

gress and general construction activities such as welding, material

handling, housekeeping and storage,

b. The applicable code for installation of safety related piping is

the ASME Boiler and Pressure Vessel Code, 1971 Edition plus

addenda through the summer of 1971. The inspector observed

safety related piping installation activities to determine if

Code, NRC and SAR requirements were being met. Activities observed

included weld preparation of steam generator No. 2 outlet, heat

treatment of main steam system weld numbers FW 50571 and FW

50572, and fit up of auxiliary feedwater syster weld number 2F

and 7F.

No items of noncompliance or deviations were identified.

5. Re actor Coolant Pressure Boundarv Pip _ing,_ Review of Quality Records

The applicable Code for reactor coolant pressure boundary piping is

the ASME Boiler and Pressure Vessel Code, Section 111, 1971 Edition

plus addenda thrcugh the summer of 1971 for installation, and various

editions and addenda for the purchase of material dependent upon the

purchase date The inspector re"iewed quality records to determine if

Code, NRC and SAR requirements were met. Installatica records were

reviewed for the following spools:

Spool No. Size System

E21-CCA-27-4 6" Safety injection

E21-CCA-27-6 6" Safety injection

E21-CCA-27-9 6" Safety injection

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Ril Report No. 50-364/78-12 1-3 -

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Ell-CC-22-5R 8" Residual Heat Removal

B13-CCA-10 27.5" Reactor Coolant

B13-CCA-12 31" Reactor Coolant

B13-CCA-11 29" Reactor Coolant

E11-CCA-22-5 8" Residual Heat Removal . . .

E21-CCA-26 3/4" and 2" Safety injection

Additional records were reviewed for the first six spools listed above

and included, as applicable, material test reports / certification

records, vendor shop manufacturing and NDE records NSSS quality release

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forms, and receiving inspection reports. General Class 1 piping ,

storage recerds were reviewed for January through July of 1978. APCO

QA audits of October 14, 1977 concerning piping storage and November 11,

1977 concerning; pipe cleaning were also reviewed.

No items of noncompliance or deviations were identified.

6. Reactor Coolant Pressure Boundary Piping (Welding) - Review of Quality

Records

^

The applicable Code for installation of reactor coolant pressure ..

boundary piping is delineated in paragraph 5. The inspector reviewed

welding quality records to determine if Code, NRC and SAR requirements

were met. Records were reviewed for the following welds:

Weld No. Size '

FW-5 6" .

FW-6 6"

FW-10 8"

FW-11 8"

7F 27.5"

8F 27.5"

Areas reviewed included inspection records covering visual and dimen-

sional inspections, weld hist.cy records, NDE records, weld repair

records, welding material cont rol records, welder qualification records,

and inspector qualification records. The inspector also reviewed six

noncomformance reports relative to reactor coolant pipe

No items of noncompliance or deviations were identified.

7. Safety Related St ructures (Welding) - Review Of _quali_ty_ Rec.ords , ,

The inspector reviewed QA audits and nonconformance report s (NCR'S) in

the area of welding of saf et y related st ructures to determine if

records were complete, legible, retrievable, properly closed out and

that adequate and timely corrective actions had been taken. Specifscally

.

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Rll Report No. 50-364/78-12 1-4

reviewed were the APC0 audit of April 21, 1978 concerning modifications

to the Reactor Makeup Water Tank and Condensate Storage Tank, the APCO

audit of June 30, 1978 concerning MT inspection of whip restraint

welds, and 12 NCR's numbered Q2W-14, 16, 31, 33-35, 39-43, and 70.

No items of noncompiance or deviations were identified.

8. Safety Related Piping - Review of Quality Records

The applicable Code is delineated in paragraph 4.b. Installation

records such as checklists, isometrics, inspection, records cleanliness

records, and records of qualification of inspection personnel were

reviewed for 10 pipe spools to determine if Code, NRC and SAR requirements

were met. Specific pipe spools reviewed were E11-ECB-28-1, -2M1, -3,

and -4; E13-HCB-53-4, -5, -6, and -7; and E13-HCB-78-1 and -2.

No items of noncompiance or deviations were identfied.

9. Safety Related Piping - Observation of Work and Work Activities

The applicable Code is delineated in paragraph 4.b. The inspector

observed handling of feedwater system spool No. N21-DBB-1-1 for confor-

mance with work performance procedures and construction specifications.

No items of noncompliance or deviations were identified.

10. Exit Interview

The inspector met with license representatives (denoted in paragraph 1)

at the conclusion of the inspection. The inspector summarized the

scope and findings of the inspection.

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