ML19344F289

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IE Insp Repts 50-445/76-01 & 50-446/76-01 on 760107-09. Noncompliance Noted:Qc/Qa Surveillance Conducted W/O Prescribed Procedures
ML19344F289
Person / Time
Site: Comanche Peak  
Issue date: 01/29/1976
From: Crossman W, Dickerson M, Stewart R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML19344F268 List:
References
50-445-76-01, 50-445-76-1, 50-446-76-01, 50-446-76-1, NUDOCS 8009150080
Download: ML19344F289 (14)


See also: IR 05000445/1976001

Text

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U. S. NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFCRCEMEtrf

REGION IV

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IE Inspection Report Nos. 50-445/76-01

Docket Nos. 50-445

50-446/76-01

50-446

Applicant:

Texas Utilities Generating Conpany

Category A2

2001 Bryan Tower

Dallas, Texas 75201

Facility:

Comanche Peak Steam Electric Station

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Units 1 & 2

Location:

Glen Rose, Texas

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Type of Licensee:

W, PWR, ' 1161 HW(e)

Type of Inspection: Routine, Unannounced

Dates of Inspection: January 7-9, 1976

Dates of Previous Inspection: November 18-21 and December 1, 1975

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Principal Inspector:

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R. C. Ste % Reactor Inspector

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Accompanying

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Inspector:

M. 'W. Dickers'ETttrTleactor inspedtor /

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Reviewed By:

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W. A. Crossman, Senior Reactor Inspector

Date

Projects Section, Reactor Construction &

Engineering Support Branch

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SU1DVuur OF FINDINGS

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' Enforcement Action

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A.

Items of Noncompliance

1.

' Violations

'None

2.

Infractions

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-a. . 10 CFR 50, Appendix B, Criterion V,-states in part,

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" Activities affecting quality shall be prescribed by

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documented instructions, procedures, or drawings, of a

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type appropriate to the circumstances and shall be

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accomplished in accordance with these instructions,

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procedures, or drawings ."

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(1)

Lack of Procedures

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Contrary to the above, the licensee's contractor is

installing containment building seismic category class I

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pipe restraint embeds without prescribed documented

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instructions or work procedures.

(DETAILS, paragraph 4.a)

(2) Lack of QC Surveillance Procedures - Embeds

Contrary to the above, the licensee's contractor is

conducting QC surveillance of the containment building

seismic category class I embeds installations without

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prescribed documented instructions or procedures.

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(DETAILS, paragraph 4.b)

(3)' Lack of QC Surveillance Procedures - Containment Liner

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Contrary to the above, the licensee's contractor is

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conducting QC surveillance of the containment building

steel liner installation without prescribed documented

instructions or procedures.

(DETAILS, paragraph 3.b)

b.

10 CFR f,0, Appendix B, Criterion'V, states in'part,

- "Activicies affecting quality shall be prescribed by

documented instructions, procedures, or drawings, of a

-type appropriate to the circumstances and shall be

accomplished in accordance with these instructions, pro-

cedures, or drawings."

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-CPSES QA Plan Manual, paragraph 2.3 states in part,

"The system assures drawings, specifications, procedures

and instructions accurately . . . meet stipulations of

related codes and standards . . . ."

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B&R QA Manual,. paragraph 5.5 states in part, "B&R Procedures

Jshall provide the requirements for standard formats and

shall establish review, approval, issuance, and control

methods for procedures, instructions, end drawings."

.

(1) Design Change control'- Procedural Deficiency'

Contrary to the above, the licensee's A&E and contractor's

subcontractor have not incorporated approved design

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changes into the applicable design specification and

work procedures, respectively, as prescribed by the

CPSES QA Plan, Section 2.3.

(DETAILS, paragraph 3.c)

(2) Examination & Repair - Procedural Deficiency

Contrary to the above, the licensee's contractor is

conducting examination and repair activities on seismic

category class I components without documented

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instructions or procedures developed and issued in a

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manner prescribed by the B&R QA Program Manual, paragraph

5.5.

(DETAILS, paragraph 4.c)

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3.

' Deficiencies

None

B.

Deviations

None

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II.

. Licensee Action on Previously Identified Enforcement Matters

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(75-13/I.A.2) Corrective Action - Concrete Aggregates

The licensee is currently in the process of preparing a reply to this

infraction pursuant =to the provisions of Section 2.201, Part 2, 10 CFR.

The ;eply is to be submitted-January 19.

This matter remains unresolved.

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.III.

New Unresolved Items

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Pipe Restraint' Embeds - Examinations and Repairs

The licensee's_ contractor is implementing examinations, repairs and

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acceptance standards on seismic category class I pipe restraints in

accordance with a G&H letter / procedure that appears to be in

conflict with C&H Specification No. 2323-SS-17 and ASME Section III,

Division 1, Subsection NE, paragraph NE-4642.

(DETAILS, paragraph 4.d)

IV.

Status of Previously Reported Unresolved Items

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A.

CDR'- H00507F4

-Reactor' Building Over-Excavation

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The licensee submitted a final report on this matter, dated

December 12, 1975.

During previous on-site inspections the IE

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inspector had observed portions of the rock recoval activities as

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described in the report, and there are no further questions in

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that regard; however, final corrective measures involve pressure

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grouting of vertical. fractures in the areas of the containment

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building and safeguards building of each unit. This matter will

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remain unresolved.pending the review and observallon by IE of

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the grouting activity,

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B.

75-12/III.2

Method of Identification and Control of Nonconformances

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During this inspection the inspector was informed that the revised

B&R Procedure CP-QAP-15.1 was still in the final internal review

phase and not issued for use.

This matter remains unresolved pending

IE review of the revised procedure.

V.

Design Changes

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None

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VI.

Unusual Occurrences

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None

VII.

Other Significant Items

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VIII.

Management Interview

1.

Site Meeting

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On January 9, at the conclusion of the inspection, a meeting was

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held with the following licensee representatives in attendance:

Texas Utilities' Services Inc. (TUSI)

R. W. Caudle, Project Manager - Nuclear Plants

H. C. Schmidt, QA Manager

C. H. Gatchell, Resident Manager

P. M. Milam, Site QA Supervisor

R. Murray, Civil Engineer

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R. M. Kissinger, Civil Engineer

Brown & Root, Inc. (B&R)

H. C. Dodd, Proj ect Manager

C. E. Bonin, Assistant Proj ect Manager

P. L. Bussolini, Project QA Manager

D. L. Hansford, Senior QC Engineer

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W. E. Childress, Jr., Project Engineer

J. B. Loth, QA Coordinator

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G. W. McGee, Site Civil Engineer

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Gibbs & Hill (G6H)

J. J. Moorhead, Resident Engineer

R. V. Fleck, QA Supervisor

J. V. Hawkins, Site QA Representative

R. C. Barber, Welding Engineer

T. R. Fleig, Electrical Engineer

F. L. McAllister, Hechanical Engineer

D. J. Fellinger, Civil Engineer

The inspection findings, as contained in the Sunmary and Details

Sections of the report, were discussed.

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DETAILS

Persons Contacted

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Texas Utilities Services, Inc.'(TUSI)

H. C. Schmidt, QA Manager

C. H. Gatchell, Resident Manager

P. M. Fulam, Site QA Supervisor

Brown & Root, 'Inc. '(B&R)

P. L. Bussolini, Project QA Manager

D. L. Hansford, Senior QC Engineer

G. H. Fisher, QC Inspector, Civil

W. E. Childress, Jr. , Project Engineer

J. B. Loth, QA/QC Coordinator

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R. Crosno, QC Inspector, Mechanical

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L. E. Hancock, Subcontract Administrator

Gibbs & Hill (C6H)

J. J. Moorhead, Resident Engineer

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R. V. Fleck, QA Supervisor

J. V. Hawkins, Site QA Representative

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Chicago Bridge & Iron'(CB&I)

M. Jeffers, Welding & QA Supervisor

W. E. Nelson, Project QA Engineer

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Report of Subjects Inspected

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1.

Scope of Inspection

The inspection was limited to a follow-on .eview of QA/QC records and

obs.'rvation of the on-site construction activities related to the

containment building steel liner and seismic category class I embed

installations for Units 1 and 2.

In addition, a review of previously

identified items of noncompliance and unresolved matters was conducted.

2.

, Plant Progress

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The overall plant progress, as of January 9, is reported by the licensee

as 12% complete (10% Unit 1 and 2% Unit 2).

(continued)

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Installation of reinforcing. steel and erbeds is continuing on Unit 1

containment building foundation in preparation for concrete place-

ment to the 805'-6" elevation.

CB&I construction crews are currently installing the Unit 2 reactor

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cavity liner plate (vertical) to the 805'-6" elevation.

Work is continuing on the safeguards and turbine building foundations.

Foundation preparation for the SSI Dam is continuing.

Backfill is now

scheduled to start in mid-January.

3.

Containment (Structural' Steel Welding) - Liner

a.

Observation of Work and Work Activities

The inspector observed the fit-up of sections of the Unit 2 cavity

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plate liner, plates 20-4 No. 4 and 20-4 No. 5, prior to welding of

joint Nos. C19, C21 and C22.

The welds are identified and located

on drawings utilized to record information relative to each weld

joint. Preparation of the joints and their alignment appeared to be

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satisfactory.

Each is inspected prior to velding to assure proper

alignment. The tack welding on joints C19 and C21, relative to

plate 20-4 No. 5, was observed to be in progress.

Welding in

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progress was also observed on joint No. CS (the circunferential weld

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joining the bottom of the cavity liner to the cavity liner, wall).

Chicago Bridge & Iron Company welding procedure WPS-E8018-01/74-2427/8,

Submerged Arc Process, in use by the welders, utilizes E8018-Cl weld

rod s, and requires no preheat unless the base metal tenperatures are

below 500F for the thickness of plate being welded. Welders were

currently qualified for the positions being welded and the specified

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NDE (Magnetic Particle Inspection) examination procedure.

FEP-13B,

Revision 8, was observed to be in use.

Additionally, the welds

are examined by vacuum box procedure, VTP-4B, Revision 2, prior to

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acceptance of the final weld.

Checks are also made to assure that

applicable welding variables are within specified limits.

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One welding material issue location is utilized for this welding.

Observance of the issue control, amount withdrawn . identity of

welder, date and identification of weld, and the handling of returned

material appeared satisfactory.

Materials are stored in a locked

storage trailer in unopened containers or in ovens which are

maintained at the. proper tenperature, 250 F.

During observation of

the welding activities no uncontrolled filler material was

observed to be in use.

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The stud welding operation on plate 20-4 No.1 to CB&I procedure

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WPS-Stud Welding / 74-2427/8 was also observed and appeared to be

in accordance with the procedural requirements for velding and

for visual inspection in accordance with procedure VEP-1B,

Revision 1

Level II inspectors were observed to be in the cavity liner and

at the site of the stud welding operation.

The inspector also examined weld joint numbers C12, C8, C2

(cavity bottom welds) and C18. (the vertical weld joining plate

20-3 No. 1 to 20-3 No. 2).

However, final acceptance of these

welds had not been completed at the time of the inspection.

b.

Review of Quality Records

The inspector selected six field welds in the Unit 1 cavity liner

and reviewed the quality records required to be established by

Gibbs & Hill Specification No. 2323-14, Containment, Steel Liner,

Revision 3, dated November 17, 1975 and by the CB&I Nuclear

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Quality Assurance Manual for ASME Section III Products, dated

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April 3, 1975.

The welds selected were for joint numbers C1, C5,

C7, C16, C26, and C19.

The records reviewed appeared to conform

to the requirements.

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Weld history records are recorded on checklist R2, Revision 1 and

R3, Revision 1.

Included were the joint number, identification r

welders, fit-up, weld procedure utilized, finished joint check,

NDE Reports (MT and VB), and final acceptance of the weld.

Also

note 4 if applicablg are weld repairs.

Records of preheat or

interpass temperatures is not required.

Individual history records

of weld repairs, if required, are also maintained on these same check-

lists.

Weld C16 required weld repair in conformance with repair procedure

GRP-10B, Revision 2 (are gouging to remove defect) as a result of

examination by NDE procedure MTP-13B, Revision S.

NDE report

No. 9, dated August 7, 1975, disclosed unacceptable porosity in

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the weld and was recorded as nonconformity number 5.

NDE report

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No. 10, dated August 7, 1975, indicated acceptance of the repaired

weld by MT.

The repaired weld was subsequently vacuum box tested

on August 8, 1975, and final acceptance was completed on August 13,

1975.

A burn through on piece 20-5 No. 2, reported as nonconformance No. 15,

was recorded as repaired by weld procedure SRP (74-2427)A and

assigned weld number C33.

The weld was examined by NDE procedure

MTP-13B, Revision 8 and VTP-4B, Revision 2, and noted as acceptable

on September 6, 1975.

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(continued)

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Resolution of Unresolved Item 75-12/III.2, Method of Identification

and Control of Nonconformances, is pending a revision to B&R

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procedure CP-QAP-15.1 and remains open.

Welding material verification of identify and conformance with

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specifications is made upon receipt at the site and the material

is then stored in the sealed containers as received.

Prior to

issuance the rods are baked in an oven maintained at a minimum

temperature of 2500F.

The rod is kept in the ovens until issue.

Weld rod is issued to the individual welder. by the supervisor of

welding and QA or by the welding supervisor.

Records of the

issuance is maintained (welder, joint, oven minimum temperatures,

date, time issued and time returned).

Unused, rod returned to the

supervisor of welding and QA or to the welding supervisor is logged

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as returned, and destroyed or returned to the oven for rebaking

for the required rebaking period.

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A review of welder qualification and inspector qualification records

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indicated that the welders were qualified for the welding being

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performed and that the inspectors were level II qualified to perform

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the required inspections.

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The inspector was informed that no audits of the CB&I work at the site

had been performed by B&R. Surveillance had apparently been provided

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by B&R but at the time of the inspection no approved procedure

relative to the surveillance was in use or available for review,

as required by 10 CFR Part 50, Appendix B, Criterion V.

In addition,

the G&H Specification No. 2323-SS-14, Section 11.0, Quality

Assurance, states in part, "The contractor shall establish and

implement a Quality Assurance Program which rigidly conforms to

the applicable rules and standards as imposed by the AEC; 10 CFR 50

Appendix B, ANSI N45.2 1971, . . . the program shall include

pertinent aspects of_ procurement, fabrication, site erection,

inspection . . . the contractor shall submit all fabrication,

installation and testing procedures to TUSI for review and comment

prior to their use."

In discussing this matter with the licensee, the inspector

acknowledged that TUSI had approved a revision to the review

.

requirements; however, the inspector pointed out that the relaxation

of the review function did not relieve the contractor from the

requirements of 10 CFR 50, Appendix B, Criterion V, which states

in part, " Activities affecting quality shall be prescribed by

documented instructions, procedures, or drawings, of a type

appropriate to the circumstances and shall be accomplished in

accordance with these instructions, precedures, or drawings."

(continued)

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It was also acknowledged by the inspector that the contractor

provided a procedure schedule which indicates that procedure,

for the B&R QA surveillance activities during installation of

the containment liner, is in preparation; however, as emphasized

by the inspector, the installation of the containment liner

plate has v een in progress since early August.

This matter has been identified as an item of noncompliance.

Surveillance of the activities of CB&I relative to Unit I were

provided by the TUSI on site QA organization.

Report No. C-

040-75, dated August 19, 1975, indicated four areas found to be

deficient. The deficiencies were subsequently resolved.

Corre-

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spondence relating to the resolution of a deficiency regarding

the method utilized for NDE was reviewed by the inspector. Work

on the containment liner was suspended on August 29, 1975, and

resumed on September 4, 1975, after the deficiency had been

corrected and accepted by TUSI.

c.

Design Change Control - Procedural Deficiency

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During the QA/QC documentation and record review, the inspector

observed that an approved ACI-ASME code change, involving contain-

ment liner plate welding requirements, was transmitted to B&R,

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CB&I, and G&ll from TUSI by letter (TUS-437) dated July 14, 1975.

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The design change authorized specific changes to the April 1973

draft addition ACI-ASME code entitled, ' Proposed Standard Code

For Concrete Reactor Vessels And Containment," sections CC-5521.1.1

(c), CC-5521.1.l(d), CC-5521.1.1(f) and radiography of Appendix IX.

The inspectofs review of the G&H specification No. 2323-SS-14 and

the CB&I QA program manual, Division 4, revealed that the above

changes had not been incot.> rated in these documents as required by

the CPSES QA Plan, Section 2.3, " Design Review" paragraph 2.3.1,

which states in part ".... the system assures that drawings, speci-

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fications, procedures and instructions accurately reflect the design

bases, conform to the representations in the license application,

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meet stipulations of related codes and standards, ...." Paragraph

2.3.4.1 incorporates ANSI 45.2.11, draft 2, revision 2, and paragraphs

2.3.4.4 and 2.3.5 prescribes the responsible discipline and procedure

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for review and control of changes, respectively.

In discussing this matter with the cognizant licensee representatives,

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the IE inspector identified this matter as an item of noncomplitnce

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in that procedural requirements were not coupletely followed in con-

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trolling the above code changes which would assure changes are dis-

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tributed to and used at the location where the prescribed activity is

perfo rmed.

10CFR 50, Appendix B, Criterion V, states in part, " Activities

affecting quality shall be prescribed by documented, instructions,

procedures, or drawings, of a type appropriate to the circumstances

and shall be accomplished in accordance with these instructions,

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procedures or drawings."

(continued)

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'4.

Containment Building Embeds - Seismic Category Class I Components

During the inspector's review of Quality Assurance activities associated

with the installation of the containment building embeds, it was observed

by the inspector that during installation of the (12) containment build-

.;;;

ing sump pipe restraints, welding of temporary support attachments were

conducted by unqualified welders and without qualified weld procedures.

This matter was identified by the B&R QC surveillance inspector and

documented by B&R deficiency disposition report (DDR) No. C-172 dated

November 22, 1975,and a chronological history contained in G&H letter

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GHF-352 dated December 5, 1975. Howe.ver, further review of this matter

by the IE Inspector revealed the following:

a.

Lack of Work Procedures

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In addition to the procedural deficiency identified in DDR-C-172,

the IE. inspector found that installation of the containment building

drain sump pipe restraints, (G6H drawing 2323-SI-0503, Detail 14A,

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Revision 3, Dated September 26, 1975) were being installed without

benefit of installation procedures which is contrary to 10CFR 50,

Appendix B, Criterion V and contrary to the G6H specification No.

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2323-SS-17, entitled, " Miscellaneous Steel," dated February 28, 1975.

Section 10.0 of the G&H specification entitled, "QA Program for the

Supply Fabrication and Erection of Miscellaneous Steel in Category

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I Structures", states in part, "The contractor shall establish and

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impicment a QA program which rigidly conforms to the applicable rules

and standards as imposed by the A.E.C.,

10CFR 50, Appendix B, ANSI

N45.2-1971Property "ANSI code" (as page type) with input value "ANSI</br></br>N45.2-1971" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process., .......

The contractor shall submit all fabrication, installation and testing

procedures to TUSI for review and cc= ment prior to their use."

This matter is identified as an item of noncompliance.

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b.

Lack of QA/QC Surveillance Procedure - Embeds

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As identified in items 3.b and 4.a above, the G&H specifications

Nos. 2323-SS-14 and 2323-SS-17, Sections 11 and 10, respectively,

prescribe the requirements for establishing and implementing proce-

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dures for fabrication, installation, testing and inspection. It is

evident by the B&R DDR-C-172, that QC surveillance activities were

being conducted; however, this function was being conducted without

benefit of a required procedure.

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This matter is identified as an item of noncompliance.

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c.

Examination and Repair - Procedural __Eeficiency

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During the IE inspector's review of the B&R DDR-C-172, regarding the

unqualified welding of temporary attachments to the reactor sump pipe

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restraints, it was observed that the DDR did not address to the

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apparent lack of installation procedures (Item 4.a above) nor was

it apparent that examination and repair procedures, within the

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meaning of 10CFR 50, Appendix B, Criterion V and G6H specification

No. 2323-SS-17, Section 10.0, were developed and implemented for

this activity.

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G6H letter CHF-352, dated December 5, 1975, contains a chronological

summary of events in the process of disposition of the DDR-C-172.

The summary of events addresses to the period November 22 through

December 5, 1975.

The letter responses a G6H letter (GHF-342)

which is purported to contain recommended procedural development

and observation of all other requirements such as preheat and

post-weld heat treatment that may be applicable; however, an

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attachment to G&H letter (GTN-5981) dated December 5,1975,

contained detailed instructions for the repair and inspection of

the pipe restraint " unqualified" welds.

The procedure / instruction

is in the form of a memorandum; without evidence of standard format

or review and approval signatures as prescribed by the B&R QA

program manual, paragraph 5.5 and B&R QAP-5.1, dated July 14, 1975.

It was further revealed by the IE inspector that during the removal

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of the unqualified welds in accordance with the G6H instruction

referenced above, approximately 43 linear indications were found in

the base metal of 4 of the 12 assemblies.

These defects were found

during the PT examination conducted af ter grinding out of the "un-

"""""

qualified" welds.

The linear indications were in the 2 " plate edge;

indicative of plate laminations extending to 4" in length and running

parallel to the plate surface.

As a result of this finding, B&R

DDR-C-192, dated December 21, 1975, was issued.

In response to the

DDR-C-192, G6H engineering conducted an on-site investigation and

provided an additional letter / memorandum (GTN-6294) dated January

17, with an attachment entitled, " Procedure for Examination and

Repair of Edge Defects in Frames Per Drawing G&H 2323-SI-0503."

The " procedure" is in narrative form; without standard format or

review and approval signatures as prescribed by the B&R QA program

manual.

B&R QA program manual dated July 14, 1975, paragraph 5.5 states in

part, "B&R procedures shall provide the requirements for standard

formats and shall establish review, approval, issuance and control

methods for procedures, instructions and drawings. All activities

affecting quality shall be accomplished in accordance with instruc-

tions, procedures and drawings. The B&R QA/QC procedure.s shall

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reflect and define specifications, drawings and other document re-

quirements for quality activities. These quality activities shall

be inspections, reviews and monitoring functions."

In discussing this matter with the licensee representatives, the

inspector stated that B&R, as the constructor, has no provisions

within their QA/QC program that permits the implementation of un-

reviewed and unapproved procedures or instructions of the type provid-

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ed by G&H.

(continued)

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This matter is identified by the IE inspector as an item of

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noncompliance in that contrary to 10CFR 50, Appendix B, Criterion

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V, the constructor did not develop or establish examination and

repair procedures / instructions as prescribed by the B&R QA program

manual.

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d.

Pipe Restraint Embeds - Examination and Repair - Unresolved Matters

The G&H drawing, No. 2323-SI-0503, Revision 3, dated September 26,

1975, Detail 14A, delineates the fabrication and installation re-

quirements for the reactor sump pipe. restraints. Note 5 states,

" Post-weld' heat treatment shall conform to the requirements of the

ASME Boiler and Pressure Vessel Code, Section 111, Division 1, Sub-

section NE."

..

,

During the IE inspector's review of the G6H letter, GTN-6294, dated

January 7, and the attached repair procedure for examination and

.

repair of the linear indications, it was observed that this procedure

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included grind-out of the subject linear indications, that would permit

welding of a remaining crack (or indication) of a width equal to or

.

less than .002".

I

1

The prescribed repair is contrary to the ASME Code Section III, Division

'

1, Subsection NE, paragraph NE-4642 entitled, " Weld Repairs Without

Required Post-Weld Heat Treatment", and the referenced Subsection NB,

p===-

paragraph NB-5352 entitled, " Acceptance Standards." In addition, the

.

G6H specification 2323-SS-17, Section 4.0 material, states.in part,

"All materials shall be the best of their respective kinds, obtained

from well finished shapes, bars or plates as required and shall be

free from any imperfections, laminations, pitting, slag inclusions,

......" The G&H repair procedure confines the area of PT examination

to a selected area and permits detectable laminations or indications

to remain in the plate.

In discussing these items with the licensee, the inspector was informed

'

that these items will be reviewed with the cognizant G6H engineer.

1

These items remain unresolved.

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INSPECTION PLAN-

.kE In pection Report No.

50-445-446/76-01

.: .

s

~ Licensee:

Texas Utilities Generating Co.

Location:

Dallas, Texas

Comanche Peak Steam Electric Station (CPSES) - Units 1 & 2

Facility:

Type of Licensee:

W, PWR, 1159, MWe

Type of Inspection:

Routine, Unannounced

Dates of Inspection:

January 7-9,~1976

. Dates of Previous Inspection:

November 18-21 and December 1, 1975

INSPECTORS:

R. C. Stewart & M. W. Dickerson

SCOPE OF INSPECTION

,

-1.

This inspection is limited to a follow-on review of the on-site construction

activities related to concrete placement, containment linear plate installation,

and backfill (SSI Dam).

-

2.

Individual on-site inspection effort:

A.

Stewart

-

(1) Review Project Status

(2) Review previous infraction, Item 75-13/I. A.2, Concrete Aggregates

- (3) Review CDR's (10 CFR 50.55(e)) Items 75-12/IV.1 & 4

(4) Conduct inspection per procedures:

~45063B (Backfill SSI Dam)(no

P.. . : . - u - v c

-)

-

e-

480533 (Containment (Steel Structures & Supports) Containment Structures

only)

~

48055B (Containment (Steel Structures & Supports) Containment Structures

only)

.

B.

Dickerson

(1) Conduct inspection per procedure:

55053B (Containment- (Structural Steel Welding) Containment Structure only.

55055B (Containment (Structural Steel Welding) Containment Structure only.

1

Approve / Disapprove:

-

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,

d. C. Stewart

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Dati:

W. A. Crossman

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