AECM-86-0224, Requests NRC Approval of Proposed Change to Inservice Insp Program to Allow Use of Figure Iwb 2500-7(b) from 1983 Edition,Summer 1983 Addenda of ASME Code,Section XI Re Exam Category B-D Weldments.Fee Paid

Requests NRC Approval of Proposed Change to Inservice Insp Program to Allow Use of Figure Iwb 2500-7(b) from 1983 Edition,Summer 1983 Addenda of ASME Code,Section XI Re Exam Category B-D Weldments.Fee Paid

ML20203F575
Person / Time
Site:	Grand Gulf
Issue date:	07/23/1986
From:	Kingsley O MISSISSIPPI POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
AECM-86-0224, AECM-86-224, TAC-61929, TAC-62047, NUDOCS 8607310119
Download: ML20203F575 (5)

Text

r MISSISSIPPI POWER & LIGHT COMPANY

] Helping Build Mississippi EidlanddiddB P. O. BO X 164 0, J AC K SO N, MIS SISSIP PI 39215-1640 July 23, 1986 O. D. KINGSLE Y, J R.

YlCE PRESIDENT NUCLE AR OPERATIONS U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C. 20555 Attention: Mr. Harold R. Denton, Director

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 ASME Section XI Code and the Inservice Inspection Program AECM-86/0224 In accordance with 10CFR50.55a(g)(4)(iv), Mississippi Power and Light (MP&L) requests NRC approval of a proposed change to the Grand Gulf Nuclear Station (GGNS) Inservice Inspection (ISI) Program to allow the use of figure IWB 2500-7(b) from the 1983 Edition, Summer 1983 Addenda (Attachment 3) of ASME Section XI for determining the Code required examination coverage for Examination Category B-D weldments.

Currently the GGNS ISI program is in accordance with ASME Section XI, 1977 edition through and including 1979 Summer Addenda with requested portions of the 1980 Edition through and including the Winter 1980 Addenda as submitted in MP&L letter dated July 25, 1984 (AECM-84/0371).

Since MP&L is requesting adoption of a portion of the 1983 Edition, Summer 1983 Adder.da to the ASME Section XI Code, paragraph IWB 3512 and its referenced paragraphs must also be adopted in order to ensure that all related require-ments of the respective edition and addenda are met.

l Attachment 1 provides MP&L's justification for requesting adoption of the above described portions of the 1983 Edition, Summer 1983 addenda.

l 8607310119 860723 PDR ADOCK 05000416 O PDR B

,\t J16AECM86071501 - 1 Member Middle South Utilities System , f

[ 2ec cl wfC&cn W/dd oC)

c .--

AECM-86/0224 Page 2 MP&L requests NRC review and approval of the subsequent edition and addenda change to the GGNS ISI program described above by August 21, 1986 in order to identify final scheduling and manpower constraints for the upcoming September 1986 refueling outage.

In accordance with the requirements of 10CFR170.21, an application fee of

$150 is attached to this letter. If additional information is required to support your review, please contact this office.

Your truly,

^

ODK:bms

, Attachment cc: Mr. T. H. Cloninger (w/a)

Mr. R. B. McGehee (w/a)

Mr. N. S. Reynolds (w/a)

Mr. H. L. Thomas (w/o)

Mr. R. C. Butcher (w/a)

Mr. James M. Taylor, Director (w/a)

Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission 4

Washington, D. C. 20555 Dr. J. Nelson Grace, Regional Administrator (w/a)

O. S. Nuclear Regulatory Commission Region II 101 Marietta St., N. W., Suite 2900 Atlanta, Georgia 30323 i

J16AECM86071501 - 2

Attachment 1 Justification for Requesting Adoption of Portions of ASME Section XI Code, 1983 Edition Through Summer 1983 Addenda The present GGNS adopted ASME Section XI Code requires vessel nozzle examination to consist of a full thickness examination of the attaching weld, inner radius, and a portion of the nozzle bore (see Attachment 2). These examinations were performed during preservice utilizing manual techniques with a combination of procedures. There are 35 Category B-D nozzle to vessel welds that are required to be examined during the ten year inspection interval.

Since the performance of preservice, automated systems for RPV examinations have been developed by General Electric and are currently scheduled to be used during RF01 on 9 nozzles. The use of automated ultrasonic examination systems for reactor inspections helps to minimize man-rem exposure and provide for better data collection and analysis. With the present technology and equipment available for automated nozzle examinations, a limitation of volume coverage exists. Due to nozzle geometry, thicknesses and multiple angles associated with the examination, manual scans are required to supplement the automated examination in order to obtain full coverage. It is anticipated that the supplemental examinations would require an average of 6 man-hours per nozzle (2 men x 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />); this includes calibration and examination.

The examinations would require working from a skip box lowered into the annulus between the RPV and biological shield for nozzles in the No. 2 and No.

4 ring regions and from a ladder for nozzles in the No. I ring region. In addition, each inner radius examination requires the changing of transducer wedges to facilitate a clockwise and counterclockwise scan. The 9 nozzles scheduled for RF01 will utilize approximately 54 man-hours in examination time not including support personnel. Based on dose rates experienced by the ISI contractor in a recent outage at the Susquehanna Nuclear Power Plant, a minimum of 10 examiners may be required to complete full volume examinations.

Later editions of ASME Section XI minimized the difficulties of performing a full thickness examination by reducing the required examination volume (see ). The newly defined examination area includes the potential crack initiation sites and minimizes the difficulties associated with examining a full nozzle thickness. Performance of volumetric examinations to the volume specified by IWB 2500-7(b) of the 1983 Edition, Summer 1983 Addenda of ASME Section XI will eliminate the need for supplementing the automated ultrasonic examinations with manual scans.

In conclusion, MP&L is requesting NRC approval of the adoption of figure IWB 2500-7(b) from the 1983 Edition, Summer 1983 Addenda of ASME Section XI into the ISI Program for GGNS. In order to incorporate all related requirements into the above request it will also be necessary to adopt IWB 3512 and its referenced paragraphs.

J16AECM86071501 - 4

ATTACILMENT 2 Fig. IWB 2500 7 SECTION XI- DIVISION I r

l a

I 3

I l I NOZZLE

! t"I  :

WALL THICKNESS I

h

\

g ia s-A [ s 8 n x

~f W n 6 0 1

M s y

, sr . _4 Y c E h y

X a ljE n W 3 o

• a ~ /

i

} .r$5

, e. 1 x

g ~

5" -

y w E \ 0 CLA00 LNG M E 4- tn2 >

NOTE: ALL FLAWS ARE EXAGGERATED IN SIZE AND SCALE S78 FIG. IWB-2500-7 N0ZZLE TO-SHELL OR HEAD WELD JOINTS (Applies to Nozzles With or Without Internal Reinforcement) 30 L

ATTACHMENT 3 Mg. IM15-1500 7(b) SECTION XI - DIVISION 1 1983 Edition D

!!11 I fI i s i(J I

+ 'n 1 m:

tn1 'n2 * "022'* **ll thick"*58 t, = shell (or head) thickness rj = nozzle insice radius l

l I

t,I2 t,12 A I N O 8 Cl 0

1. ~% . a. n r- ,

.., g

• h g N o '

'h% N f l 1 - I

/

a l

N 50 l -

ft l N \ l t t'

/ '

i

• i21P / sa i 4 l i

g i1 11P if

/' l g - -

l .

M / H G F _El f I N~/ l C! adding k rj - 1/2 in. "2 re ent

\ s / i i

-4 P * /

N'

\

N -

t

--f.

jr

=

E x arn. vol.

r N M /

%  % # A-8-C-O-E-F-G-H c*orner flaw EXAMINATION REGION (Note (111 EXAMINATION VOLUME (Note (2)!

Sheet for head) ad ioerung region C-D E-F Attachment weld region 8CFG.

Nozzle cylinder region A 8-C H Nozzle inside comer region M-N 0 P NOTES:

(1) Emamination regions are identified for the purpose of differentiating the acceptance standards in IW8 3512.

(2) Examination volumes may be determined either by direct measurements on the component or by treasurements based on design drawings.

FIG. IW8 2500-7(b) N0ZZLE IN SHELL OR HEAD (Examination Zones in Flange Type Notzles Joineh by Full Penetration Butt Welds) 76 L __ ___ ___ _ _ - .