ML20151U569

Forwards Revised Pages of Preservice Insp Program,Reflecting Requested Insps of 20 Welds of Containment Spray Sys,Per Sser 2 (Confirmatory Issue 11)

ML20151U569
Person / Time
Site:	Catawba
Issue date:	02/06/1986
From:	Tucker H DUKE POWER CO.
To:	Harold Denton, Youngblood B Office of Nuclear Reactor Regulation
References
NUDOCS 8602110053
Download: ML20151U569 (8)

Text

F D

A L

r DUKE POWER GOMPAhT P.O. BOK 33180 CHARL(FFTE, N.C. 28242 HAL H.':UCKER

-- tutzenown

= =cas (704) aya.4sas wwAmmaraamarrion February 6, 1986 Mr. Harold R. Denton, Director Office of Nuclear' Reactor Regulation U.

S.

Nuclear Regulatory Commission Washington, D.

C.

20555 Attention:

Mr.

B.

J. Youngblood, Project Director PWR Project Directorate No. 4 Re:

Catawba Nuclear Station, Unit 2 Docket No. 50-414

Dear Sir:

On April 16, 1984, Duke Power Company (Duke) submitted Revision 3 to the Preservice Inspection (PSI) Program for Catawba Units 1 and 2.

The PSI program for Catawba Unit 1 was approved'by the Staff in Supplement 2 to the Catawba Safety Evaluation Report.

Approval of the Unit 2 program was left open by SSER-2 (Confirmatory Issue 11).

On January 8, 1986, the Staff requested that 20 welds in the Catawba Unit 2 Containment Spray (NS) System be inspected, even though Catawba Unit 2 is essentially identical to Unit I and falls under the same edition and addenda of Section XI of the ASME Code.

Although clearly a backfit under 10 CFR 50.109, Duke declined to pursue the backfit appeal process due to the potential impact on the-licensing schedule for Unit 2 and the relatively low cost of the requested inspections.

As a result, the PSI program for Unit 2 has been revised to include the requested inspections of the NS System.

The attached pages reflect these changes.

Very truly yours, O

R Hal B. Tucker ROS: sib B602ik$0b 4

PDR O

s~

Mr. Harold R. Danton, Director February 6,.1986 Page Two cc: ' Dr. J. Nelson Grace, Regional Administration i -

U. S. Nuclear Regulatory Commission-Region II 101 Marietta' Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Catawba Nuclear Station e

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7.0 Augmented Preservice Inspection Plan Augmented preservice inspection shall be performed as required in Section 1 of - this Plan.

Specific examinations are listed in Section 8 of this Plan.

7.1 _ Examination Categories and Requirements Items requiring augmented preservice inspection are described in the following paragraphs.

Each inspection will be assigned a unique Item Number.

' 7.1.1 Reactor Coolant Pump Flywheels Two inspections are required by USNRC Regulatory Guide 1.14, Revision 1.

The entire volume of the flywheel must be examined by the ultrasonic method, and the bore and keyway areas must be examined by the magnetic particle method.

However, a magnetic partical inspection is required on all exposed surfaces for inservice inspection, so the preservice inspection will be extended to. included all exposed surfaces of the flywheel.

7.1. 2 Steam Generator Tubing USNRC Regulatory Guide 1.83, Revision 1, allows the shop examina-tion of steam generator tubing to serve as the preservice inspection.

All Unit 1 and Unit 2 steam generator tubing will be examined to assure that no tube degradation has occurred during shipping, storage, or installation of the steam generator.

7.1.3 Steam Generator Feedwater Modification After completion of the Feedwater Modification multifrequency Eddy Current Testing was performed to assure no damage was incurred during the modification and to establish baseline wear data in the preheater portion of all four (4) steam generators in Unit I and Unit 2.

A remote visual inspection was also performed on all four (4) steam generators in Unit 1 to assure no damage to the secondary side during the modification.

The possibility of wear degradation will be monitored by eddy current inspection as part of the inservice inspection program.

7.1. 4 Class 2 Valve Body Welds Liquid Penetrant testing was performed on Class 2 valve body welds to reference as baseline data for future inservice inspection.

7.1. 5 Containment Spray System - NS Ultrasonic inspection was performed on selected Class 2 piping welds.

Boundaries of the affected piping are shown on Flow Diagram CN-2563-1.0, included in this section.

PRESERVICE INSPECTION PLAN REV. 5 CATAWBA NUCLEAR STATION PAGE 1 C/6550015

8.0 Detailed Listing of Examinations for Catawba Units 1 and 2 All ASME Class 1, 2, and 3 systems and-components have been reviewed to determine the preservice examination requirements for Catawba Units 1 and 2.

The Examination Listings contained in this section were written in accordance with the criteria found in Sections 3, 4, 5, and 7 of this Plan.

8.1 Examination-Information The following information is listed for each examination where applicable:

8.1.1 Item Number The Item Number'for each examination is composed of three sections.

'The first two sections of the item number for ASME Class 1 or Class 2 items are the same as the Item Numbers assigned in Table IW8-2500 or IWC-2500 of ASME Section XI.

The first two sections of the item number for Augmented Inspections will be chosen as follows:

j E1.01 Reactor Coolant Pump Flywheel Examinations.

E2.01 Steam Generator Tube Examinations E3.01 Class 2 Valve Body Welds i

E4.01 Class 2. Piping Welds The last section of the Item Number is a three or four character sequence to uniquely identify that inspection.

i 8.1.2 10 Number The ID Number is chosen so that, by using the specified Reference i

Drawing (s) and any applicable comments, the area to be examined can be accurately identified.

Several different weld identification systems were used by various equipment vendors.

A consistent system of weld or component identification has been developed and is described below:

8.1. 2.1 The first character of each ID Number indicates the Unit to which the examination applies.

8.1. 2. 2 The Unit Number is followed by two or three letters to indicate the component or system to be examined.

The abbreviations used are:

RPV Reactor Pressure Vessel PZR Pressurizer SGA Steam Generator A SGB Steam Generator 8 SGC Steam Generator C SGD Steam Generator D RCP Reactor Coolant Pump ACC Safety Injection Accumulator Tank WAC Upper Head Injection Water Accumulator 1

Tank l

PRESERVICE INSPECTION PLAN REV. 6 i

CATAWBA NUCLEAR STATION PAGE 1 C/6550015

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- ' = - - - -

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RHR HX Residual Heat Removal Heat Exchanger RHRP Residual Heat Removal Pump NAC Upper Head Injection Nitrogen Accumulator Tank CA Auxiliary Feedwater System CF Main Feedwater System FW Refueling Water System NC Reactor Coolant System ND Residual Heat Removal System NI Safety Injection System l

NS Containment Spray System NV Chemical and Volume Control System SA Auxiliary Steam System SM Main Steam System SV Main Steam Vent to Atmosphere 8.1.2.3 The remainder of the ID Number will indicate the exact weld or component to be examined, as shown on the Reference Drawings.

Additional information will be included in the comments space when necessary to positively identify the area to be examined.

Abbreviations were used to indicate the following types of welds:

Safe-End Welds - ID Number ends with "SE" Longitudinal Seam in Fitting - ID Number ends with "L"

Westinghoase Butt Weld - ID Number containing "W" Westinghouse Branch Pipe Weld - ID Number containing "WN" 8.1. 3 Drawing Numbers At least one Duke Drsin, dumber is listed for each examination.

Drawing numbers bes nning with "CNM" are vendor's component drawings.

Drawing r.mbers beginning with "CN " followed by a four digit number are </ stem flow diagrams, and those beginning "CN "

followed by a one-digit number and a two-letter system designation (see par.

8.1.2.2) are system piping isometrics.

All listed drawings are available at the Document Control Office at Catawba.

8.1. 4 Inspection Required The followin'g abbreviations are used to describe ti ", type of inspection required for each item:

PT Liquid Penetrant Inspection MT Magnetic Particle Inspection RT Radiographic Inspection UT Ultrasonic Inspection ET Eddy Current Inspection VIS Visual Inspection 8.1.5 Procedure t

The inspection procedure is listed for each item to be inspected.

The procedures are chosen from those in Paragraph 3.4 of this Plan.

PRESERVICE INSPECTION PLAN REV. 6 CATAWBA NUCLEAR STATION PAGE 2 C/6550015

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1

r PROGRAN: RLRe7179-GAISIO2 DUKE PtMER CtMPANY PAGE 193 FILE:

C007133 PLANT:

CATA>eA LMIT 2 -

GUALITY ASSURANCE DEPARTM NT 02/03/86 PRE-SERVICE A8G IN-SERVICE INSPECTICM SYSTEN KEY:

ITEM DARSER -

CATAteA LMIT 2 PRESERVICE INSPECTIth LISTING R INS

P. PROCEDURE

NATERIA'. DIAN. THICKMSS CALIS.

ITEM 94RSER ID DAMBER ORANING DARSERS REQ. MASER TYPE SIZE ILENGTH)

SLOCK ********* CS9ENTS ***********

E4.01.016 2NS53-10 CN-2NS-053 UT ISI-120 SS 10.00 C.365 50321 CN-2563-1.0 E4.01.017 2NS53-14 CN-2NS-053 UT

~ ISI-120 SS 10.00 0.250 50320 CN-2563-1.0

-~

E4.01.018 2NS53-19 CN-2 Pts-053 UT ISI-120 SS 10.00 0.250 50320 CN-2563-1.0 E4.01.019 2NS72-04 CN-2NS-072 UT ISI-120 SS 10.00 0.250 50320 CN-2563-1.0 E4.01.020 2NS72-21 CN-2NS-072 UT ISI-120 SS 10.00 0.250

-50320 CN-2563-1.0 onnen*********e*

FOR LMIT 2 ***************um

• • • THERE MFRE 21 RECOROS SELECTED *n*

• • • NHOSE IleM DARSERS SEGIN HITH E4.

• • • THERE NERE 2,927 TOTAL RECORDS C**

SELECTED FOR LMIT 2 C*************** men **************::::::::::**

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