IR 05000324/1973014

From kanterella
Jump to navigation Jump to search
RO Insp Repts 50-324/73-14 & 50-325/73-07 on 731015 & 17.No Violations Noted.Major Areas Inspected:Redundant Channel Cable Separation,Redundant Channel Conflict,Radiography of Field Welds & NDT Requirements
ML20044C496
Person / Time
Site: Brunswick  
Issue date: 10/29/1973
From: Crossman W, Mcfarland C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20044C467 List:
References
FOIA-92-569 50-324-73-14, 50-325-73-07, 50-325-73-7, NUDOCS 9303230137
Download: ML20044C496 (8)


Text

.

'

' [f '%g UNITED STATES g' '

ATOMIC ENERGY COMMISSION q

!.7p -

DIRECTORATE OF R%WTORY OPERATIONS c

..y acciou n - suit e ets

%, aus c5 ;p 2n we ac t me t st ac ci. wont.csv

-

r

,,,,,

.,,,,,, y,,,

at ca T a. cronc a Exs RO Inspe.ction Report Nos. 50-324/73-14 and 50-325/73-7 Licensee: Carolina Power and Light Company 336 Fayetteville Street Raleigh, North Carolina 27602 Facility Name: Brunswick 1 and 2 Docket Nos. :

50-325 and 324 License Nos. :

CPPR-68 and CPPR-67 Category:

A2 and A3 Location:

Southport, North Carolina Type of License: 821 the, BWR, G-E Type of Inspection: Routine, Announced, Quality Assurance Dates of Inspection: October 15-17, 1973 Dates of Previous Inspection: October 2-5, 1973 (Brunswick 1)

October 1-5, 1973 (Brunswick 2)

Principal Inspector: i L.[ C FNi

/f-;

/0/1'i'73 C. R. McFarland, Reactor Inspector Date Facilities Section Facilities Construction Branch Accompanying Inspectors: None Other Acconpanying Perscnnel: None

-

Reviewed by: i ' I /.- u >'l o

!

'

/P 2f/77

/

W. A. Crossman, Senior Inspector Date Facil1 ties Section Facilities Construction Branch

.

.

-

9303230137 930202

'

PDR FOIA 0'MEALI92-569 PDR

.,

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

_ _.

.

. -

,

RO Rpt. Nos. 50-324/73-14-2-and 50-325/73-7 SUMMARY OF FINDINGS 1.

Enforcement Action A.

Violations None i

B.

Safety Items None II.

Licensee Action on Previously Identified Enforcement Matters A.

Violations certain items appeared to be in violation with 10 CFR 50, Appendix B, " Quality Assurance Criteria for Nuclear Power Plants," as indicated below. These apparent violations were considered to be of Category II severity.

73-ll-Al(II)

Redundant. Channel Cable Separation Criteria for the separation of redundant system cables within wiring enclosures are needed.

This item remains open.

73-ll-A2 (II)

Redundant Channel Conflicts Redundant channel cables are not separated, i. e.,

laced into a bundle in cabinets XU-13 and XU-25.

This item remains open.

73-7-A2(II)

Radiography of Field Welds Radiographic deficiencies are being reviewed.

This item remains open.

B.

Safety Items None

.

-__-_-~_

__

.

. -

.

.

RO Rpt. Nos. 50-324/73-14-3-and 50-325/73-7 III. New Unresolved Items None IV.

Status of Previously Reported Unresolved Items At the conclusion of this inspection, six items remain unresolved.

73-13/1 NDT Requirements The FSAR and the United Engineers and Constructors, Inc. (UE&C)

specifications need to be revised to reflect the actual practice

'

used for the NDT requirements for class IIA piping. This item remains open.

i

!

73-13/2 QA/QC of Mancers, Snubbers and Restraints

'

f Carolina Power and Light Company needs to review their erection, inspection, and QA/QC programs related to hangers, snubbers and restraints. This item remains open.

73-11/1 Redundant System Equipment

!

,

The licensee will review and provide justification for-the design of the control modes for the redundant nuclear service water header pumps and the associated shut off valves. Th1s item remains open.

73-3/2 Piping Documentation The licensee and Brown and Root, Inc. (B&R) are correcting

{

the documentation for each. weld joint.

Implementation of the revised procedures needs to be evaluated. This item remains open.

73-1/1 Verification of Nuclear Valves to Design Specifications (RO:II Letters Dated June 30, 1972 and February 16, 1973)

,

!

The licensee has not completed his program of measurement

'

of all valves. This item remains open.

!

,

t

.

. -

k

. -

p

.

.

r RO Rpt. Nos. 50-324/73-14-4-

'

.

and 50-325/73-7 I

!

T 73-1/2 Limitorque Valve Operator Failure (RO:II Letter Dated

!

December 4,1972, CP&L Letter Dated July 2,1973)

i Site corrective work by Limitorque and CP&L continues.

!

This item remains open.

i V.

Design Changes l

None

'

i VI.

Unusual Occurrences z

!

!

None

i VII. Other Significant Findines

'

,

None

,

VIII. Management Interview i

-

i The inspector met with Messrs. M. F. Thompson, Jr. and H. R. Banks of

[

CP&L to appraise them of the general areas of inspection and the l

findings as noted in this report.

<

,

!

~

f

i i

f I

~

.

,

I

,

I

' I

.

I f

?

-

f r

.

..,.. - _.. -

-

.-

, _

-

.

.

RO Report Nos. 50-325/73-7 and 1-1

?

50-324/73-14 DETAILS I Prepared by:

[

h-I '77 C. R. McFa'rland, Reactor Inspector Date

,

Facilities Section, Facilities

'

'

Construction Branch Dates of Inspection: October 15-17, 1973 i

Reviewed by:

b N.

8/#!73

'

un-W. A. Crossman, Senior Inspector Date Facilities Section, Facilities

Construction Branch

'

All information in Details I applies equally to Brunswick 1 and 2 except where information is identified with a specific reactor.

I

1.

Persons Contacted l

W. B. Kincaid - Vice President, Power Plant Engineering M. F. Thompson, Jr. - Manager, QA Engineering and Vendor Surveillance R. Hanford - Principal QC Specialist D. N. Allen - Senior Quality Surveillance Specialist, Engineering

[

D. A. McGaw - Principal Quality Surveillance Specialist

J. V. Gailey - Senior Quality Surveillance Specialist, Vendor Surveillance H. R. Banks - Manager, QA and Training Audit Section,Special Services Department l

D. Locklear - Principal QA Specialist, Special Services Department i

M. A. McDuffie - Manager, Power Plant Construction

-

N. J. Chiangi - Manager, QA Construction i

G. M. Simpson - QC Specialist, Construction 2.

Proj ect Status Ihe overall percent completion of civil. and architectural engineering features as of September 30, 1973, was reported to be 75% for Unit 2 and 49% for Unit 1.

.

.

3.

Personnel and/or Organization Status A recent reorganization of the Engineering, Construction and

~

^[

Operation Groups has separated the construction work from the

engineering and vendor surveillance work.

W. B. Kincaid, Vice President, Power Plant Engineering, has a QA section to survey and

[

audit the engineering and vendor surveillance work.

'M. A. McDuffie, i

-

l

- :

,

..

..

.

-.

.-

. -.

,

!

!

-

.

.

i RO Report Nos. 50-325/73-7 and I-2

.

50-324/73-14 i

,

!

i

!

Manager, Power Plant Construction, has a QA section to survey and

.!

audit the construction activities.

D. V. Menscer, Vice President, t

Special Services Department, has a QA section that conducts corporate audits of these activities.

All of the above applies to

[

all of the present (Brunswick 1 and 2, Harris 1, 2, 3 and 4) and proposed plants.

N. J. Chiangi has recently been employed by CP&L

-;

to be the QA Manager of Construction. The site QC specialists will i

report to Mr. Chiangi. CP&L plans to revise Appendix D of the FSAR

,

to report these, and other, changes in organizations and responsibilities i

-

for CP&L and their contractors.

.i t

4.

Status of Outstanding Enforcement Matters and Outstanding

'

Unresolved Items j

r Discussions of specific matters did not develop any significant

information about any of the 1tems listed in the prior reports and i

noted in the summary section of this report.

!

5.

QA/QC Program Activities

+

s t

a.

General f

i.

j The inspector's review of the licensee's files indicate that

!

reasonable and effective followup is.being conducted on the

!

j items noted in the RO inspection reports, in the surveys

i conducted by the power plant engineering QA section, and in the l

audits conducted by the special services department QA section.

'

The licensee has increased the number of planned and actual QA surveys and audits of contractors and of CP&L groups from J

that planned at the time of our audit in July. The surveys j

.

and audits are conducted to meet the requirements of the current

'

draf ts of ANSI 45.2.12, " Requirements for Auditing of Quality

[

'

Assurance Programs for Nuclear Power Plants."

!

b.

QA Audit Status Reports

" Quality Assurance Audit Status Reports" are written each month

,

by the QA manager to the vice president, Power Plant Engineering

.

and Construction (PPE&C).

These monthly reports for February

}

through September 1973 were reviewed by the inspector.

c.

Audits of Construction Activities

.

,

~

The Quality Assurance Audit (QAA) files for audits of the constructor Brown and Root, Inc. (B&R) QAA 80-1,

}

,

April 18-20, 1972 and June 28-29, 1972; QAA 80-2,

!

,

i.

,

December 13-15, 1972; QAA 80-3, April 10-12, 1973; and QAA 80-4,

<

l

-

I l

',

,

-

.. -

_

.._. _..

... -..

_ _.

-_

_.-

. _

-

-

!

-

.

. -

i

,

RO Report Nos. 50-325/73-7 and I-3 f

50-324/73-14 l

!

August 7-9, 1973), includes correspondence by the vice president

'

PPE&C expressing concern that the audit findings be implemented.

!

and that the outstanding deficiencies and problems be resolved.

Direct involvement by upper management is evident throughout the file and corrective actions by CP&L and B&R are documented.

l Their concerns have often overlapped items reported in the RO i

inspection reports. CP&L on site personnel have recently assumed a role of direct involvement (rather than auditing only) with

,

'

the constructor QA work to eliminate many problems. There has

{

been a continuing concern for better procedures for administrative

{

controls and craf twork as well as for better implementation of j

existing procedures.

l d.

QA Surveys of United Encineers and Constructors (UE&C)

i

,

QA audits and surveys of the architect engineer, UE&C, have l

been conducted since February 1970 and the surveys have been

!

reviewed by CP&L management. The inspector reviewed in detail the files for survey No. 10 conducted September 6 and 7, 1973,

!

and survey No. 9 conducted. March 6, 1973. The purpose of

!

survey No. 10 was to ascertain the. compliance with the UE&C QA procedure for " Drawing, Specification, Purchase Order, and

.

Procedure Review," and to check for the corrective actions l

taken by UE&C. The purpose of Survey No. 9 was to review the vendor submittals that we are required by the equipment specifications l

and the operation of the UE&C Reliability and QA Department.

A cursory review was made of audits 1 (February 24, 1970),

,

2 (April 7, 1970), 3 (June 16, 1970), 4 (October 6, 1970) and 5 (October 1,1971), and surveys (name change and organization change), 6 (May 19,1972), 7 (July 19,1972), and 8 (October 31, 1972).

The files show reasonable survey questions, investigations, followup, verification effectiveness, corrective actions,

.l observation of processes, and inspections for co=pleteness l

and adequacy to assure conformance to specifications or

procedures.

The audits indicate periodic actions were taken to

examine adherence to approved procedures and to verify the effectiveness of a quality system.

l The inspector reviewed the UE6C QA procedures related to vendor surveillance, audit actions on NSSS supplier, field QA engineer activities, and the special conditions for purchases of materials and equipment. The inspector reviewed the UE&C weekly activity report No. 101 dated September 28, 1973. The inspector reviewed the UE&C status of specifications for BSEP Units 1 and 2 dated. August 24, 1973.

.

.

FEF. DER INSPECTION EEPORT IDENTIF1 CATION SHEET

.'

l

' REPORT N0s. 50-324/73-14

,

.-

50-325/73-7

-

!

..

..

TO:

W. A. Crossman, Senior Inspector. Facilities Section. Facilities Construction Branch

!

Licensee:

Inspection Dates,n f, g_,7 f 7, i

c,v,34,2 p,.,,, a 3 4 s.

c m,,,,,,

f s n,3+h nnre - wnrr h r,rn14nn Brunswick 1 and 2 Other Inspectors None Feeder Report Prepared By:

-

10/21/73

-

C. R. McFarland, Reactor Inspector Date Facilities Section, Facilities Construction Branch Inspector's Evaluation (continue on attached sheet, if necessary)

No items of direct safety concern were identified. No unusual information itens were identified. No information was identified that should be included in the letter to the licensee of items other than those in the Summary of Findings.

-

,

Management participaJion in the QA program is documented in their files.

CP&L [d57:fn d B&R is documented.

It's effectiveness is not too evident. Our concerns are shared by CP&L management.

f

.

l

.

,

'

Signaturc

.

.

1 TO:

,

The attached Feeder Inspection Documentation is transmitted in reviewed and approved form.

.

'

Co=ments:

.

b m

4