ML20134L914

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Forwards Revised Relief Request from Weld Exam Coverage Requirements of ASME Section XI for Welds in Reactor Coolant Sys,Per ISI Requirements
ML20134L914
Person / Time
Site: North Anna Dominion icon.png
Issue date: 01/28/1997
From: Saunders R
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
97-033, 97-33, NUDOCS 9702200008
Download: ML20134L914 (20)
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VIHOINIA ELECTHIC AND POWEH COMI*ANY Hicnwonn,VIHOINIA 2026]

January 28, 1997 United States Nuclear Regulatory Commission Serial No.97-033 Attention: Document Control Desk NL&OS/ETS Washington, D.C. 20555 Docket No. 50-339 License No. NPF-7 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 2 REVISED ASME SECTION XI RELIEF REQUESTS North Anna Unit 2 is currently in the second period of the second ten year interval.

North Anna Unit 2 inservice inspections and examinations are conducted to the requirements of the 1986 Edition of ASME Section XI. Several examinations pedormed during the recent refueling outage did not meet the ASME Code required weld examination coverage. Therefore, pursuant to 10 CFR 50.55a (g)(5)(iii), relief is requested from the weld examination coverage requirements of ASME Section XI for welds in the Reactor Coolant System. Relief Requests NDE-33,34, and 35 detail the )

weld examination coverage obtained and are provided as Attachments to this letter.

These relief requests have been reviewed and approved by the Station Nuclear Safety and Operating Committee.

This letter is not intended to establish any additional commitments. If you have any additional questions concerning these relief requests, please contact us.

Very truly yours, 02/ 2 A R. F. Saunders l

Vice President - Nuclear Engineering and Services Attachments \

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9702200000 970128 PDR ADOCK 05000339 h . . ,

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1 i cc: U. S. Nuclear Regulatory Commission

. Region ll 101 Marietta Street, N. W.

5 Suite 2900 Atlanta, Georgia 30323 Mr. R. D. McWhorter NRC Senior Resident inspector 1

North Anna Power Station 1

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1 ASME Section XI Relief Requests l NDE-33,34, and 35 l 1

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i Virginia Electric and Power Company North Anna Power Station Unit 2 4

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i Virginia Electric & Power Company North Anna Power Station Unit 2 Second 10 Year Interval Request for Relief Number NDE-33 I. IDENTIFICATION OF COMPONENTS Mark / Weld # Line# Drawina# Class l

9 27M"-RC-403-2501R-Q1 12050-WMKS-109E-1 1 20 31"-RC-405-2501R-01 12050-WMKS-109F-1 1 j II. IMPRACTICABLE CODE REQUIREMENTS l The 1986 edition of ASME Section XI Table IWB-2500-1, examination category B-J, item number B9.11 does not allow any limitations to the required volumetric or surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10%.

III. CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED Relief is requested from examining the Code required volume for the identified pipe-to-pump welds.

IV. BASIS FOR RELIEF The components listed above have been examined to the extent practical as required by the Code. The Code required volumetric examination coverage was reduced due to weld joint geometry, and the material type from which the components are constructed. The scope of volumetric examination coverage completed for the above listed welds is listed in Table NDE-33-1. Figures NDE-33-1 and NDE-33-2 are provided detailing the limitations experienced. These welds are classified as terminal ends and are required to be examined by the ISI Program.

V. ALTERNATE PROVISIONS It is proposed that the examinations already completed at the reduced coverage be counted as meeting the Code requirements. In addition:

1. A visual (VT-2) examination will be performed during the normally scheduled system leakage test each refueling outage;
2. Technical Specifications requires that the reactor coolant system leak rate be limited to one gallon per minute unidentified leakage. This value is calculated at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; and
3. The containment atmosphere particulate radioactivity is monitored every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

_ _ . _ _ . . _ . _ . . . _ _ _ _ . . - . _ _ . - . . _ . _ . _ . _ - _ . - . . ~ . - -

The proposed alternative examinations stated above will ensure that  ;

the overall' level of plant quality and. safety will not be  !

compromised. .

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Table NDE-33-1 North Anna Unit 2 Examination Coverage Estimates Category B-J, Item B9.11 UT Coverage % Surface Examination %

Mark / Weld # 2 5 7 8 Coveraae % Reason for Partial Examination 9 97 0 50 50 100 Nozzle and weld joint configuration and material type (ASTM A-351 austenitic steel casting) timit the use of an extended V-path examination. The weld was examined to the maxiaua extent practical using 45* and 60* RTD search units from the loop pipe side. Approximately 97% of the tower 1/3 of the weld was covered in the 2 direction.

L 20 0 100 100 100 100 Nozzle and weld joint configuration and materlat type (ASTM A-351 austenitic steel casting) timit the use of an extended V-path examination. The weld was examined to the manlaua extent practical using 45* and 60* RTD search units from the loop pipe side. Approximately 100% of the tower 1/3 of the weld was covered in the 5 direction.

UT Scan Direction Definitions 2 - Axiat scan, 180 degrees from isometric flew direction (weld count).

5 - Axist scan, the same direction as the isometric flow (weld count).

7 - Ciretaferential scan, clockwise rotation when viewing in the direction of isometric flow.

8 - Circumferential scan, counterctockwise rotation when viewing in the direction of isometric flow.

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North Anna Power Station Unit 2 i Second 10 Year Interval Request for Relief Number NDE-35 I. IDENTIFICATION OF COMPONENT Mark /Weldt Drawino# Class >

l 1 12050-WMKS-RC-R-1.2 1 (

II. IMPRACTICABLE CODE REQUIREMENTS The 1986 edition of ASME Section XI Table IWB-2500-1, examination [

category B-A, item number Bl.40 does not allow any limitations to i the required volumetric or surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10%.

III. CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED Relief is requested from examining the Code required volume for the identified head-to-flange weld.

IV. BASIS FOR RELIEF  !

The component listed above has been examined to the extent practical as required by the Code. Due to the joint configuration l and a lifting lug the required volume could not be examined. The

! reduction in coverage is detailed in Table NDE-35-1. Figures NDE-35-1 and NDE-35-2 are provided detailing the limitations  :

l experienced. .

V. ALTERNATE PROVISIONS l

It is proposed that the examinations already completed at the t reduced coverage be counted as meeting the Code requirements. In l addition:

1. A visual (VT-2) examination will be performed during the j normally scheduled system leakage test each refueling outage;
2. Technical Specifications requires that the reactor coolant system leak rate be limited to one gallon per minute unidentified leakage. This value is calculated at least once i per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; and i

L

3. The containment atmosphere particulate radioactivity is monitored every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4 The proposed alternative examinations stated above will ensure that the overall level of plant quality and safety will not be compromised, l

L l

Table NDE-35-1 ,

North Anna Unit 2 Examination Coverage Estimates (Reactor Vessel)

Category B-A, Item Bl.40 .

Mark /Wetdf Beam Annie Exam Area scan Direction  % Exam Reason For Partial 1 (120* - 240*) 0 Weld & Base -

% Joint configuration and seterial tyoe (ASTM SA-533 GR. 8 45 Weld 2 48 with stainless steel cladding) Limit the use of an 45 Weld 5  % V-path examination. Lift lug restricts UT scans in att 45 Weld 7 95 directions.

45 Weld 8 95 60 Weld 2 15 60 Weid 5 96 60 Weld 7 95 60 WeId 8 95 45 & 60 Base 2 56 45 & 60 Base 5  %

45 & 60 Base 7 95 45 & 60 Base 8 95 Surface coverage %%

UT scan Direction Definitions 2 - Axist scan flange side of weld 5 - Axist scan head side of weld ,

7 - Cire mferential scan, clockwise (tooking down on head) 8 - Cire mferential scan, counterctockwise (tooking down en head)

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