ML20209C217

Forwards Specific Instructions Re Independent NDE of RCS & Other safety-related Piping,Per W Laudan Request.Any Exceptions Should Be Identified & Documented in Contractor Final Rept

ML20209C217
Person / Time
Site:	Diablo Canyon
Issue date:	06/30/1983
From:	Morrill P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:	Bishop T, Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20209C222	List: ML20209C217 ML20210E460 ML20210E486 ML20210E515 ML20210E525 ML20210E538 ML20210E544 ML20210E562 ML20210E583 ML20210E602 ML20210E632 ML20210E649 ML20210E657 ML20210E671 ML20210E686 ML20210E697 ML20210E731 ML20210E749
References
FOIA-86-151 NUDOCS 8307060038
Download: ML20209C217 (5)

Text

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UNITED STATES {

! 'a NUCLEAR REGULATORY COMMISSION

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0, 145o MARIA LANE.SulTE 210 g * * ,e WALNUT CREEK CALIFORNIA 94596 JUN 3 01983 MEMORANDUM FOR: T. Bishop, Chief, Reactor Projects Branch No. 2 D. Kirsch, Chief, Reactor Projects Section No. 3 FROM: P. Morrill, Reactor Inspector Non-destructive Examination (NDE) Activities to be Performed

SUBJECT:

! at Diablo Canyon Related to Reactor Coolant System (RCS)

{ piping Minimum Wall Problem Thepurposeofthismemoistodocumentthedecisiontoconducthndependent_.

EDE of RCS and other safety related piping at the Diablo Canyon plant and to

, ' forward the specitic 2.nstructions related to this work which TTrave prepared. These instructions are enclosed and were requested by Mr. W. .

Enudan of IE HQ. I have telecopied a copy to Mr. Laudan at Headquarters and j ro Mr. M. Mendonca at the Diablo Canyon site on June 29, 1983. A copy was

' also telecopied to our contractor, Par,ameter Inc., on June 30, 1983. The j scope, methodology, and purpose of the subject examinations were developed

> based on discussions between Messrs. J. Martin, B. Faulkenberry, J. Crews, D. Kirsch, and myself. The instructions are intended to be used as input to i any scope o'f work document developed by *ir. Laudan and to assist the NDE contractor as well as our staff,,to prepare for this work. The document is

, intended to be general in nature and used for guidance. However, any exceptions should be identified when they are observed and documented in the

. contractor's final report. .

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P. J. Morrill Reactor Inspector f

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J. Martin, RV

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l B. Faulkenberry, RV .

l J. Crews, RV W. Laudan, IE HQ -(4^.]'{'

! H. Schierling, NRR HQ ,k k f'

, J. Carlson, RV M. Mendonca, RV

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1 29 June 1983 OUTLINE OF NON-DESTRUCTIVE EXAMINATION WORK TO BE PERFORMED AT DIABLO CANTON, JULY 5-8, 1983, BY NRC CONTRACT PERSONNEL ,

, GENERAL INFORMATION: , .

! Location: Diablo Canyon Nuclear Plant, Unit No. 1

.! San Luis Obispo, California

! Licensee Pacific Gas and Electric Company j Docket No. 50-275 Purposes (1) To obtain data to verify safety related piping systems minimum wall thickness

- measurements recently taken by the licensee (2) To determidtthe adequacy of radiography performed on the subject welds and identify non-conformance with.the piping codes P

.; Site

Contact:

Mr. John Carlson, NRC Senior Resident Inspector, 805-595-2353 R Y contact: Mr. Phil Morrill, NRC Reactor. Inspector, 415-943-3740 t

Work Hours: 0730-1630, July 5 through 8, 1983 i -

i i REQUIREMENTS:

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To be Furnished at the Diablo Canyon Site by the licensee Hard hats & safety glasses Insulation removal

Seafolding erection Escorts to locate welds in the plant Calibration blocks Assi, stance to assemble docume9tation (radiographs)

Electrical power and extensiop cords for portable

. test equipment j Working space for one or two persons to examine radiography records

! Viewer to examine radiographs

! Use of lunchroom and sanitary facilities Use of Zerox machine as back-up

! To be Furnished at the Diablo Canyon Site by the NRC:

Assistance as required by the Senior Resident Inspector Telephones in the NRC* trailer Zerox machine for copying To be Furnished by the Contractors

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Certified level II or III examiners to conduct (1)  !

ultrasonic wall thickness measurements and (2) an examination of radiographs for adequacy .

I Certified and calibrated ultrasonic test equipment '

Two copies of certifications & qualifications of all l contractor personnel, and dosumentation verifying j certification & Qualification of equipment used shall be given to the NRC contact upon arrival at i the Diablo Canyon Site.

j Calibration of. equipment and measurements performed

. shall be in accordance with the latest editions

of the ASME code. Two copies of all calibration i records and data sheets will be furnished to the NRC contact at the conclusion of the work.

[ A letter report including a description of the work performed, the data obtained or examined, and j

g evaluation of the adequacy of licensee's

. documentation shall be prepared and delivered to the NRC Region Y office by July 13, 1983. An f exit meeting will be held with the URC contact i at the conclusion of the work to discuss the scope and findings.

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EXAMINATIONS REQUIRED:

! (1) The welds and adjacent piping described below are to be examined to measure and record minimum wall thickness. It is required that measu'rements be t u ,w u

at 3 inch intervals around the circumference of the

.i welds. At each interval, the weld area, and adjacent area for 3 inches on each side of the weld shall be ultrasonically examined to determin the~ piping minimum

- wall thickness. This data shall be recorded on data sheets similiar to the attached sheet. Calibrations and measurements shall be in accordance with the latest

!' editions of the ASME code. The examinations should be j in pipe to pipe joints and not adjacent to valves.

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i Reactor Coolant System (RCS) Welds---2.2 to 2.5 inch wall Extruded stainless steel pipe, 27 5, 29, & 31 inches

! I.D.

! 1-16 1-11 2-17 1-1 2-1 i

3-9 2-9 2-10 2-13 2-19 4-17 (total of 11)

-l pressurizer surge line---estimated 1.0 to 1.5 inch wall

', stainless steel pipe estimated to be 14 inches I.D.

RCS to surge line weld (1)

Surge line to pressurizer weld (1) two randomly selected welds in between (2)

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Main steam and feedwhter lines---estimated 1.5 inch

• wall t carbon steel estimated to be 28 and 16 inches I.D.

respectively - '

steam generator feedwater nozzlea to pipe (4) steam generator steam line nozzles to pipe (4)

, first adjacent we.1ds in piping outboard of the welds described above (8) )

[ Emergency Core Cooling System welds---estimated 1.0 to 2.0 inch thickness, stainless steel pipe 6 and 10 inch

. 0.D. All welds selected should be inside containment.

1 four (4) welds in the discharge lines from the

' safety injection tanks four (4) welds in the safety injection pump

+ injection lines four (4) welds in the residual heat removal system J

four (4) welds where the above piping ties into

, the RCS TOTAL 47 WELDS l

~! (2) For the welds described above, certified and qualified personnel shall examine the licensee <a radiographs used to meet original code requirements to determin wheather the radiographs are acceptable and to verify the adequacy of the subject welds. In some cases there are additional radiographs which generally were taken after grinding was performed upon 'the piping.

These radiographs shall also be examined for adequacy and to verify the intergity of the RCS and associated piping.

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