ML20002C325

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IE Insp Repts 50-445/80-23 & 50-446/80-23 on 801001-1031. Noncompliance Noted:Failure to Follow Procedures for Making Full Penetration Welds
ML20002C325
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 11/19/1980
From: Crossman W, Renee Taylor
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20002C324 List:
References
50-445-80-23, 50-446-80-23, NUDOCS 8101100063
Download: ML20002C325 (7)


See also: IR 05000445/1980023

Text

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U. S. NUCLEAR REGULATORY COMMISSION

O

OFFICE OF INSPECTION AND ENFORCEMENT

REGION IV

Report No. 50-445/S0-23; 50-446/80-23

Docket No. 50-445; 50-446

Category A2

Licensee:

Texas Utilities Generating Company

2001 Bryan Tower

Dallas, Texas 75201

Facility Name:

Comanche Peak, Units 1 and 2

Inspection at:

Comanche Peak Steam Electric Station, Glen Rose, Texas

Inscection Conducted:

October 1980

Inspector:p

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M . G.' Taylor, Resicent Reactor Inspector

Date

Projects Section

// 8%

Aoproved:

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W. A. Crossman, Cnief, Projects Section

Bate

Insoection Summary:

Insoection During October 1980 (9ecort No. 50-445/80-23: 50-446/80-23)

Areas Insoected:

Routine, announced inspection by tne Resident Reactor Inspector

(RRI) including general site tours; piping, electrical and instrument instal-

lation activities; protection of installed equipment; and pipe supports and

restraints.

The inspection involved seventy-five inspector-hours by the RRI.

Resuits:

No items of noncompliance or deviations were identified in fice of

tne areas.

One item of noncompliance (infraction - failure to follow porcedures

for making full penetration welds

paragrapn 6) was identified in one area.

8202 20006,3,

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DETAILS

1.

Persons Contacted

Princioal Licensee Emoloyees

  • D. N. Chapman, TUGCO, Quality Assurance Manager

"R. G. Tolson, TUGCO, Site Quality Assurance Supervisor

  • J. R. Ainsworth, TUGCO, Quality Engineering Supervisor

Otner Persons

J. V. Hawkins, Brown & Root, Project Quality Assurance Manager

The RRI also interviewed other licensee and Brown & Root employees during

the inspection period including both craft labor and QA/QC personnel.

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  • Denotes those persons with whom the RRI held on-site management meetings

during the inspection period.

2.

Action on Previous Insoection Findings

(Closed) Unresolved Item (50-445/79-18; 50-446/79-18):

Preinstallation

Handling of Hot Shutdown Panel.

The RRI reviewed a letter from the

panel fabricator dated July 10, 1980, which was accompanied by the data

runs of a computer analysis of the panel structure and the lifting

eyebolts.

The vendor, Reliance Electric Company, states that the

analysis indicated that the stresses imposed on the panel during the

lift were approximately an order of magnitude less than the material

yield strength and that in their opinion there has been no compromise

to either the safety or performance of the panel under design con-

diticas.

The licensee's Architect / Engineer concurred with the

analysis of the vendor by letter dated August 15, 1980.

The RRI had no further questions regarding this matter.

(Closed) Infraction (50-445/80-20; 50-446/80-20):

Unsuitable Weld

Surface Condition as Required by Magnetic Particle Test Procedures.

The licensee notified RIV by letter dated October 20, 1980, that all

of the components involved in tha noncompliance item had been reinspected

and that components requiring rework to acnieve compliance had been

completed or were being processed.

The licensee also stated that he

would assure that in process and release inspections would be accomplished

in the vendor's shops to assure ccmpliance on future production efforts.

The RRI observed a portion of the reinspection and rework effort in regard

to the components and was satisfied that it was being accomplished in a

sound manner.

The RRI also interviewed the Brown & Root employee who

was the basis for an allegation made to RIV 'in regard to these components

and found that he had been assigned to close monitoring of the vendor's

on-site activities involving the reinspection and rework effort.

The

interviewee indicated that he was satisfied with the effort.

The RRI had

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no further questions regarding the components themselves.

The licensee's

commitment in regard to future inspections in the vendor's facilities

will be evaluated during future routine inspections.

This item of noncompliance is therefore considered closed.

(Closed) Unresolved Item (50-445/80-08; 50-446/80-08):

Qualification

of Rockbestos Electrical Cable.

The RRI was provided with documentary

evidence that flame tests had been accomplished on both the cable

and the individual wires of multicanductor cable.

The test data

furnished indicated that the cable met the requirements of IEEE-383-74.

The RRI had no further questions on this matter.

3.

Site Tours

The RRI toured the safety-related plant areas several times weekly during

the inspection period to observe the general progress of construction and

the practices involved.

Three of the tours were accomplished during

portions of the second shift where the main activity continues to be the

installation of electrical cables and the application of protective coatings.

No items of noncompliance were identified.

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4.

Protection of Major Installed Ecuipment

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The RRI observed that the Reactor Vessel Internals (core support structure)

continued to be partially installed within the Unit 1 Reactor Vessel.

The

vessel head and the lifting rig structure were fully covered with heavy

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plastic as a dust cover.

The Unit 2 Reactor Vessel was found to be well

protected during the period with a full floor cover over the refueling

pool cavity and with a prefabricated cover on the vessel itself.

The Unit

2 Reactor Vessel Internals remained in their storage enclosure during the

period.

The RRI observed that randomly selected electric prime movers for pumps

had their space heaters energized as did the motors associated with motor

operated valves.

Relative to the status condition of the Reactor Vessel Internals, the RRI

reviewed documentation relative to an incident which occurred on September

12, 1980, and was reported to RIV as a potential Significant Construction

Deficiency on September 13, 1980.

The incident involv7d what appeared to

be the inadvertent application of weld metal to one of three Roto-lock

inserts during the process of welding in an anti-rctotion locking tab.

The incident was initally documented by the licensee on Nonconformance

Report 80-00072 which has now been finalized by requiring that the insert

be removed and returned to Westinghouse for examination for possible internal

cracking as a result of the welding or for replacement.

The licensee

informed RIV by a letter dated October 10, 1980, that their final review

of the incident indicated the matter was not reportable under the criteria

of 10 CFR 50.55(e).

The RRI has reviewed the engineering analysis upon

which this decision was based and had no further questions.

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No items of noncompliance were identified.

5.

Safety-Related Pioing Installation and Welding

The RRI made several observations of the handling practice, relative to

piping components during the inspection period both in the on-site fabrica-

tion shop and within the main plant buildings.

The practices observed were

consistent with the construction practices outlined in Construction Pro-

cedure 35-1195-CPM 6.9, Project Specification MS-100, and good industry

practice.

The RRI observed the following welds being made during the inspection

period:

Weld No.

Isometric

Filler Ht.

Welder (s)

Procedure

Process

W-1

CS-2-AB-013

464176

ABN

88025

GTAW

FW-2

SI-2-SB-005

464074

BBI-AHS

99028

GTAW

The RRI verified that the weld filler metals being utilized in the above

welds were certified by the suppliers via Certified Material Test Reports

as meeting the applicable requirements of ASME Section II.

The welders and

weld procedures noted above were verified to have been properly qualified

in accordance with ASME Section IX.

The RRI also examined the radiographs of the following welds for compliance

with the requirements of ASME Section III for weld quality and Section V for

the quality of the radiographs themselves.

Weld No.

Isometric

Line No.

W-16

RC-2-RB-072

6-RC-2-100-2501R1

FW-6-2

RC-1-RB-020

6-RC-1-161-2501R1

FW-16

SI-1-RB-022

3-SI-1-202-2501R1

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FW-5

CS-1-RB-028

2-CS-1112-2501R1

W-7 & W-4

RC-2-RB-072

6-RC-2-098-2501R1

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W-9

SI-2-RB-018

6-SI-2-102-2501R1

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W-15A

CS-1-RB-001

2-CS-1-107-2501R1

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W-3 & W-2

RC-2-RB-073

6-RC-2-147-2501R1

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W-7-1

SI-1-Y0-03

12-SI-1-031-151R2

FW-2

CT-1-RB-017

8-CT-1-076-301R2

No items of noncompliance were identified.

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6.

Pioino System Succorts and Restraints

a.

Pioe Whio Restraints

During the inspection of this gentral class of components as discussed

in Inspection Report 50-445/80-20; 50 1?6/80-20, the RRI became aware

of yet another substantial group of large weldments that nad been

fabricated by Chicago Bridge and Iron (CB&I) in their Salt Lake City,

Utah, facility.

This group of weldments has been designated as pipe

whip restraints rather than pipe mount restraints involved in the above

referenced report but are fabricated of essentially the same materials

and are similar in appearance.

It was found that the components had

been procured by Brown & Root for the licensee under sub-contract

35-1195-0578 which in turn references a series of design drawings

beginning with 2323-SI-0581.

Drawing 2323-SI-0578 :ontains the general

and specific technical requirements for the componants while the balance

of the cawings contain design details for each component.

The RRI located several of the components in an on-site storage area

and examined them as well as possible for weld quality, considering

that each had been painted.

Of necessity, the inspection had to be

limited to one of general appearance.

Most of the welds on the

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components presented a good appearance since they were of good confi-

guration and were reasonably smooth, which would be typical of good

welding practice.

Most of the welds were noted to be on both sides

of the "T" member connections and appeared to be full penetration

double welded joints.

The RRI found several connections, however,

that had been welded only from one side and showed no weld metal on

the other side.

The RRI was also able to slip the point of a pocket

knife blade under the edge of the unwelded side in a few locations.

Reference to the design drawings and the welding notes indicated

that these connections were to have been full penetration, which they

were not.

Review of the fabricator's shop drawings, as approved by

the engineer, revealed a joint design that would not provide full

penetration.

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This item of noncompliance was identified to the licensee by an offi-

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cial notification on October 16, 1980.

b.

Sway Struts

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On September 19, 1980, the licensee informed the RRI that a potential

Significant Construction Deficiency had been identified in regard to

devices generally known as sway struts.

A sway strut is usually a

length of small pipe with threaded pieces welded on the ends.

Threaded

eye bolts are then installed to form a turnbuckle with the assembly

being used to support or restrain the motion of a pipe system at a

particular location in primarily one direction.

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The ASME Code requires that the eye bolts have full thread engagement

in the end pieces and tnat there be a means to provide assurance that

full thread engagement is achieved after installation.

It had been

found during the installation of three struts manufactured by NPS

Ir%stries, that the eye bolts could be completely removed from the

assembly even though tne end threads were to have been upset as a

measure to assure full engagement.

The licensee subsequently notified RIV by a letter dated October 15,

1980, that, after evaluation, it had been concluded that the deficiency

was not formally reportable under 10 CFR 50.55(e).

The evaluation

contenas that since each strut is designed to a custom length for a

specific location. there is no reasonable probability that the eye

bolts would not have the necessary full thread engagement and, there-

fore, would not present any safety hazard.

After review of the

evaluation, the RRI had no further questions on this matter since the

contention was found to be factual.

In order to satisfy a specific Code requirement, the licensee and/or

the vendor are in the process of identifying those struts which do

not have the upset thread feature and are making minor modifications

to allow for thread upsetting and thereby achieve full compliance with

the ASME code.

No items of noncompliance were identified.

7.

Electrical Installation Activities

The RRI made a number of observations of electrical cable pulling operations

during the period.

The RRI was able to observe each of three cable pulling

crews one or more times during the period in order to ascertain whether they

were working within the parameters of the site installation procedures and

good practices.

The RRI also observed the activities of the QA/QC personnel

assigned to monitor the pulling crews.

The RRI found that both the craft

labor and QA/QC forces were working consistently to the requirements of

their respective procedures, EEI-7 and QE-QP-11.3-26.

No items of noncompliance were identified.

8.

Instrument Installation Activities

The RRI observed two different pipefitter instrument crews installing

im W se tubing during the reporting period.

The workmanship which involves

cutting, deburring and bending small diameter stainless steel tubing was

being done in accordance with standard practices.

The tubing runs were

properly sloped and properly fastened to the support devices.

The RRI

observed that the Swage-lock fittings were being tightened in accordance

with the manufacturer's recommended procedures.

The R?I did not verify

whether the tubing runs and instruments were located as required by design

drawings.

This function will be accomplished during future inspections.

No items of noncompliance were identified.

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Manacement Meetincs

The RRI met with one or more of the persons identified in paragrapn 1 on

October 3, 9, 14, 16, 29 and 31, 1980, to discuss inscection finaings and

the licensee's actions and positions.

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