ML19320D084

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IE Insp Repts 50-456/80-05 & 50-457/80-05 on 800429 & 0520. Noncompliance Noted:Failure to Perform Surveillance on Valves in Storage & Failure to Meet Welding or Storage Procedure Requirements
ML19320D084
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 06/03/1980
From: Danielson D, Eric Lee
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML19320D077 List:
References
50-456-80-05, 50-456-80-5, 50-457-80-05, 50-457-80-5, NUDOCS 8007180519
Download: ML19320D084 (5)


See also: IR 05000456/1980005

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U.S. NUCLEAR REGULATORY COMMISSION

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OFFICE OF INSPECTION AND ENFORCEMENT

REGION III

Report No. 50-456/80-05; 50-457/80-05

Docket No. 50-456; 50-457

License No. CPPR-132; CPPR-133

Licensee:

Commonwealth Edison Company

P. O. Box 767

Chicago, IL 60690

Facility Name:

Braidwood Station, Units 1 and 2

Inspection At: Braidwood Site, Braidwood, IL

Inspection Conducted: April 29, and May 20, 1980

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Inspector:

E. W. K. Lee

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Approved By:

ielson, Chief

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Engineering Support Section 2

Inspection Summary

Inspection on April 29 and May 20, 1980 (Report No. 50-456/80-05;

50-457/80-05)

Areas Inspected: Reactor Coolant Pressure Boundary and Safety Related

Piping work activities, welding, procedures and records; previously identi-

fied noncompliance item. The inspection involved 13 inspector-hours

onsite by one NRC inspector.

Results: Of the nine areas inspected, no apparent items of noncompliance

or deviations were identified in 6 areas; 3 apparent items of noncompliance

were identified in three areas (infraction - failure to perform surveil-

lance on valves in storage - licensee action previous inspection findings;

infraction - failure to meet welding procedure requirements, paragraphs 2

and 4; infraction - failure to meet storage requirements, paragraph 3).

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DETAILS

Persons contacted

Principal Licensee Personnel

  • W. Carlson, Construction Supervisor
  • R. Cosaro, Station Superintendent
  • M. A. Gorski, Quality Assurance Engineer
  • S. M. Jaquez, Quality Assurance Engineer
  • R. Redinger, Station Constructian
  • T. R. Sommerfield, Quality Asserance Supervisor

Phillips, Getschow Company

  • R. Meyers, Site Manager
  • Denotes those present at the exit interview.

Licensee Action on Previous Inspection Findings

(Closed) Noncompliance Item (457/78-80-01) Failure to perform surveillance

of valves: The inspector toured warehouses No. 1, 2, and 3 where valves

are stored and established that the ends of four 6" check valves stored in

Warehouse No. 3 with I.D. No. 2SI-012B, No. ISI-012A, No. ISI-012B and

No. 2SI-012A were not covered. Review of surveillance records indicated

valves were inspected quarterly from September 1978 to June 1979 for

warehouses No. I and 2 and September 1979 for warehouse No. 3.

This

condition represents an item of noncompliance identified in Appendix A

(456/80-05-01; 457/80-05-01).

During inspection on May 20, 1980 the inspector determined that action had

been taken to correct the identified noncompliance and to prevent recurrence.

Consequently, no reply to this noncompliance is required.

Functional or Program Areas Inspected

1.

Reactor Coolant Pressure Boundary Piping - Observation of Work and.

Work Activities (Unit 1)

The inspector ovserved weld end preparation of the Reactor Coolant

System weld No. M-196-LP2-FW12.

It was determined that work activi-

ties were performed in accordance with applicable procedures and

good construction practices were adhered to.

No items of noncompliance or deviations were identified.

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2.

Reactor Coolant Pressure Boundary Piping - Observation of Welding

Activities (Unit 1)

The inspector observed welding of the Reactor Coolant System welds

No. M-196-LP3-FW12 and No. H-196-LP1-FW1.

It was determined that

(1) work was conducted in accordance with the traveller; (2) proper

welding materials were used; (3) work areas were free of weld rod

stubs; (4) welding procedure requirements were met; (5) physical

appearance was acceptable and (6) weld bead width of weld No.

M-196-LP3-FW12 was between 5/8" to 1".

This condition repr sents

an item of noncompliance as identified in Appendix A (456/80-05-02).

Except as noted, no items of noncompliance or deviations were identified.

3.

Reactor Coolant Pressure Boundary and Safety Related Piping - Welding

Material Control (Units 1 and 2)

a.

Review of Documents

The inspector reviewed the following documents:

(1) Phillips, Getschow Company (PG) Procedure No. QCP-B3,

Revision 2, " Control of Material Requisitions and Purchase

Orders".

(2) PG Procedure No. QCP-B8, Revision 4, " Issuance and Control

of Welding Material".

(3) PG Procedure No. QCP-B9, Revision 1, " Receiving Inspection

of Items, Material or Equipment".

(4) Purchase Order, receiving inspection report, and material

test reports for ER308L wire with heat Nos. 462327, 743575,

742774, and 744424; ER309 wire with heat Nos. C18095 and

lot No. 29617; ER316 wire with heat No. 74781 and lot No.

32606 and ER308 wire with heat No. 01556 and lot No. 30605.

It was determined that the above documents met the PSAR,

10 CFR 50, Appendix B and the applicable code requirements.

b.

Control of Materials

The inspector toured Phillips, Getschow Company welding material

issuing station located at the Turbine Building.

It was deter-

mined that (1) the welding materials are properly identified and

segregated; (2) records are properly kept; (3) issuance and

return of welding materials are controlled in accordance with

approved procedures and (4) the temperature of the rod ovens

is maintained except weld rod oven No. 12.

The temperature of

this oven is 150 F instead of 275 F as required by the procedure.

This condition represents an item of noncompliance identified in

Appendix A (456/80-05-03 and 457/80-05-02).

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Except as noted, no items of noncompliance or deviations were identified.

4.

Reactor Coolant Pressure Boundary and Safety Related Piping - Visual

Examination of Welds (Unit 1)

The inspector visually inspected the partially completed Reactor

Coolant System weld No. M-196-LP1-FW2 and the completed Safety Injec-

tion System weld No. SI-6-FW7B.

It was determined that the weld bead

width e)ceeded the procedure requirements. This condition represents

an item of noncompliance as identified in Appendix A (456/80-05-02).

5.

Reactor Coolant Pressure Boundary and Safety Related Piping - Weld

Heat Treatment (Unit 1)

a.

Review of Procedure

The inspector reviewed the applicable welding procedures used in

welds stated in paragraphs 2 and 7 of this report and determined

that preheating and monitoring methods are specified and acceptable.

b.

Observation of Preheating

While observing welding activities for items stated in para-

graphs 2 and 7 of this report, the inspector determined that

preheat met the welding procedure requirements.

No items of noncompliance or devitions were identified.

6.

Reactor Coolant Pressure Boundary and Safety Related Piping - Welder

Qualification (Unit I and 2)

The inspector reviewed the following documents:

a.

Phillips, Getschow Company Procedure No. QAP-13, Revision 0,

including Supplement 1, " Qualification of Welders and Welding

Procedure".

b.

Randomly selected the qualification record of eight welders who

performed welding on welds stated in paragraphs 2 and 7 of this

report.

The inspector determined that the above documents met the require-

ments of ASME B&PV Code Section IX.

No items of noncompliance or deviations were identified.

7.

Safety Related Piping - Observation of Welding Activities (Unit 1)

The inspector observed welding of the Residual Heat System welds

No. RH-2-FW13 and No. RH-2-FW1.

It was determined that (1) work was

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conducted in accordance with traveller; (2) proper welding materials

were used; (3) welding procedure requirements were met; (4) work

area was free of weld rod-stubs; and (5) physical appearance was

acceptable.

No items of noncompliance or deviations were identified.

8.

Safety Related Piping - Observation of Work and Work Activities

(Unit 1)

The inspector observed the handling and protection of the Safety

Injection System spool No. SI-6-5.

It was determined that work

activities were performed in accordance with applicable procedures

and good construction practices were adhered to.

No items of noncompliance or deviations were identified.

Exit Interview

The inspector met with licensee representatives (denoted under Persons

Contacted) at the conclusion of the inspection on May 20, 1980. The

inspector summarized the purpose and findings of the inspection. The

licensee ackncwledged the findings reported herein.

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