AECM-86-0248, Forwards Relief Request I-00013 Seeking NRC Approval for Use of Summer 1983 Addenda of ASME Section Xi,Based on Interpretation of 10CFR50.55(a)(g)(4)(iv), Re Inservice Insp Requirements for Reactor Pressure Vessel Nozzles

Forwards Relief Request I-00013 Seeking NRC Approval for Use of Summer 1983 Addenda of ASME Section Xi,Based on Interpretation of 10CFR50.55(a)(g)(4)(iv), Re Inservice Insp Requirements for Reactor Pressure Vessel Nozzles

ML20214K862
Person / Time
Site:	Grand Gulf
Issue date:	08/15/1986
From:	Kingsley O MISSISSIPPI POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
AECM-86-0248, AECM-86-248, TAC-61929, TAC-62047, NUDOCS 8608220141
Download: ML20214K862 (8)

Text

__ - - -

t, D

MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi EulMII6lidd5 P. O. B O X 164 0, J A C K S O N. MIS SIS SIP PI 39215-1640 August 15, 1986 O. D. KINGSLEY, J R.

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

Dear Mr. Denton:

c

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 Inservice Inspection AECM-86/0248 By letter dated July 23, 1986 (AECM-86/0224), Mississippi Power and Light (MP&L) requested NRC approval of the use of a portion of the 1983 Edition, Summer 1983 Addenda of ASME Section XI based on an interpretation of 10CFR50.55a(g)(4)(iv). However, by letter dated July 30, 1986 (MAEC-86/0242),

the staff requested that MP&L resubmit in the format of a relief request.

The purpose of this submittal'is to provide the subject request as a relief request in accordance with 10CFR50.55a(g)5.

Attachment 1 provides relief request number I-00013 which includes specific components, applicable code requirements, information to support the determination that the code requirements are impractical, the specific relief requested, and reasons why relief should be granted.

If additional information is required to support your review, please contact this office.

Yours uly,

. / ,

ODK:vog Attachment cc: (See Next Page) 86092:'0141 860815 d

q PDR ADOCK 0U000416 G PDR , h I \

J13AECM86081101 - 1 Member Middle South Utilities System

r ~

~ -

AECM-86/0248' Paga 2 Mr..T. H. Cloninger (w/a)

~

cc:

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

U. S. Nuclear Regulatory Commission Region II

-101 Marietta St., N. W., Suite 2900-Atlanta, Georgia 30323 i

s i

L I

l l

l l

i J13AECM86081101 - 2 l

r f, GRAND GULF NUCLEAR STATM INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUEST PAGE 1 of 3

- GRAND GULF NUCLEAR STATION

- UNIT 1 REQUEST FOR RELIEF NO. I-00013 INSERVICE INSPECTION RPV N0ZZLE INNER RADII I. Component: Reactor Pressure Vessel Nozzles As Listed in Table I.

II. Code The Unit I reactor pressure vessel was. designed and fabricated to ASNE Section III, Class I Requirements.

Applicable inservice inspections are to be performed to ,

ASME Section XI, 1977 Edition with Addenda through and including Sununer 1979 Addenda.

III. Code Requirements: Table IWB 2500-1, Examination Category B-D, Full

' Penetration Welds of Nozzles in Vessels, items B 3.90 and B 3.100 requires a full thickness volumetric examination of the attaching weld, inner radius, and a portion of the nozzle bore (see Figure 1).

IV. Information to The volumetric examinations were performed during support the deter- ' preservice utilizing manual techniques with a combination mination that of procedures. There are 35 category B-D nozzle to vessel the code welds that are required to be examined during the ten year requirements are inspection interval. Since the p'erformance of preservice, impractical automated systems for RPV examinations have been developed and are scheduled to be used at GGNS when conditions permit. 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.

The supplemental (manual) examinations are estimated to require an average of 6 additional 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 does not include support personnel.

The examinations would require working from a skip box (man lif t) lowered into the ann'alus 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 thus requiring an additional calibration.

t l_ NWPREP RELIEF NO. I-00013

[ f, GRANO GULF NUCLEAR STATWJ INSERVICE INSPECTION REQUIREMENTS FA.i *' INSEiWICE INSPECT 10N SECTION 4

"" TEN YEAR PFCGRAM RELIEF REQUEST PAGE 2 of 3 Of the 35 nozzles, 29 are to be examined using automated techniques, and the remaining 6 are to be examined using manual techniques because of their small diameter. The 29 nozzles utilizing automated examinations will require supplemental manual examinations totaling approximately 174 additional man-hours excluding personnel support time.

Examination time for the 6 smaller diameter nozzles would be ceduced from approximately 6 man hours to 5 man hours for each nozzle. The total savings in man-hours for all nozzles would total approximately 180 hours0.00208 days <br />0.05 hours <br />2.97619e-4 weeks <br />6.849e-5 months <br />.

Examinations performed to the 1977 edition, suuner 1979 addenda of ASME Section II requires extensive manhours to be spent inside the annulus area between the reactor pressure vessel and the biological shield. Fixtures and rigging for lifting and maneuvering the examination personnel are complex and require additional personnel to be located within the drywell to monitor and operate the equipment.

Later editions of ASME Section II minimized the difficulties of performing a full thickness examination by reducing th'e required examination volume (see figure 2) .

The newly defined examination area includes the potential crack initiation sites and' minimizes the difficulties associated with examining a full nozzle thicknees.

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 and reduce the total time required for performing examinations on those nozzles examined manually, thus reducing man-rem exposure significantly.

V. Specific Permission is requested to allow the use of Figure IWB Relief Requested: 2500-7(b) from the 1983 Edition, Summer 1983 Addenda of ASME Section Il for determining code required ermehmeion coverage for exavination Category B-D weldments.

l Since the request is for a portion of the 1983 edition.

Summer 1983 Addenda of the ASME Section II Code, Paragraph IWB 3512 and its referenced paragraphs must also be adopted in order to ensure that all related requirements of the respect 1ve edition and addenda are met.

VI. Reasons Why Relief from Figure IWB 2500-7 of the 1977 Edition through Relief Should 1979 Summer Addenda of ASME Section XI is requested for Be Granted: the following reasons:

1. The area of examination that is omitted by the 1983 Edition, Summer 1983 Addenda of ASME Section XI did not have.any recordable indications identified during preservice.

W99p RET.IEF NO. T-OOOl3

r GRANO GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS Fr[,lI y g" INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUEST PAGE 3 of 3

2. The newly defined examination crea (see Figure. 2) includes those areas that by industry experience have the potential for crack initiation.

3. The Code of Federal Regulations, Title 10, Part 50.55a(g)(4)(iv) allows for the use of subsequent editions and addenda that are incorporated by reference in 10CFR50.55a(b)(2) and subject to the Commission's approval.

As used in 10CFR50.55a(b)(2), references to Section II of the ASME Boiler and Pressure Vessel Code Refer to Section XI, Division 1, and include editions through the 1983 edition and addenda through the Summer 1983 Addenda, subject to limitations not applicable to this request.

VII. Alternate Since the requested relief meets the requirements Testing: contained in an Edition and Addenda of ASME Section XI that is accepted by the Commission, no alternate testing is proposed.

NWPREP RELIEF NO. I-00013 'w

i

'l mm w mm mm INSERVICE INSPECTION REQUIREMENTS l

[if' F I r INSERVICE INSPECTION SECTION 4 E TEN YEAR PROGRAM RELIEF REQUEST l

TABLE 1 RELIEF REQUEST - I-00013

~ Nozzle Cutout Diameter Notes No. Service Inches N1-A Recirculation Outlet 50.80 N1-B Recirculation Outlet 50.80 N2-A Recirculation Inlet 35.37 N2-B Recirculation Inlet 35.37 N2-C Recirculation Inlet 35.37 N2-D Recirculation Inlet 35.37 N2-E Recirculation Inlet 35.37 N2-F Recirculation Inlet 35.37 N2-G Recirculation Inlet 35.37 N2-H Recirculation Inlet 35.37 N2-J Recirculation Inlet 35.37 N2-K Recirculation Inlet 35.37 N2-M Recirculation Inlet 35.37 N2-N Recirculation Inlet 35.37 N3-A Steam Outlet '

'52.87 N3-B Steam Outlet 52.87 N3-C Steam Outlet 52.87 32.87 '

N3-D Steam Outlet N4-A Feedwater 35.12 To Be Supplemented by NUREG 0619 N4-B Feedwater 35.12 To Be Supplemented by NUREG 0619 N4-C Feedwater 35.12 To Be Supplemented by NUREG 0619 N4-D Feedwater 35.12 To Be Supplemented by NUREG 0619 N4-E Feedwater 35.12 To Be Supplemented by NUREG 0619 N4-F Feedwater 35.12 To Be Supplemented by NUREG 0619 NS-A Corespray 35.37 NS-B Corespray 35.37 N6-A RHR/LPCI 35.37 N6-B RER/LPCI 35.37 N6-C RHR/LPCI 35.37 N7 RCIC Head Spray 20.50 N8 Spare 20.50 N9A Jet Pump Instr. 17.00 N9B Jet Pump Instr. 17.00

N10 CRD Hyd. Sys. 19.88 j N16 Instr. Vib. 23.94 l

l l

NWPTEL REQUEST I-00013 TBL

Fig. IWB.2500-7 SECTION XI- DIVISION I r- 7 '

I I

I g ,

I I .

<  ! t "I -

NOZZLE WALL THICKNESS I N h

i

-i a 4--

A[ s B f  ;\

a,

• i m

Y d \ 'C m ***

k , @ , i w M a f [$$

$ a l

ou I

}:5 5

, a, ~

w E \ D CLADDING e I--> '

E

(--- t n2 > \

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)

FIGURE 1 RELIE7 REQUEST NO. I-00013

^

NWPFIG REQUEST NO. I-00013

e

. e Fig. IWB-2500 7(b) SECTION XI - DIVISION I 1983 Edition

!!il I i

I

'I ,

I l

4 nt M

=

fa g,f a g nettle wall thickness t,

a shell (or head) thickness tj

= nott's inside radius y

I l

t,/2 t,/2 e->

A I N O SC D

~ _ . , u -t--- ,

1 ,

o y' g N i' '

\ ". 3

'kw \  !

1 I

I l .

g q ( I u .

o(

/ I \ -

, ~ ,

l M- H G F EO

[ ,

I s/ cad ng ,

f ej - 1/2 in. n2 * ,,,,

1 s / i ,

g - a /

\  ! = = -

f. Exam. vol.

N M /

'~

A-B-C-D-E-F-G-H Comer fiam EXAMINATION HEGION [ Note (1)1 EXAMINATICN VOLUME INote (2))

Shets (or headt adpoining repon C-D-E F Attachment weed repen 8-C-F<a Notree cytinder repon A-8.G-H Norste insede comer region M-N-0 P NOTES:

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

(2) Exam.nanon votumes may be determined eether by direct measurements on the component or by measurements beeed on design drawings.

FIG. IWB-2500 7(b) N0ZZLE IN SHELL OR HEAD (Examination Zones in Flange Type Nozzles Joined by Full Penetration Butt Welds)

FIGURE 2 RELIEF REQUEST NO. I-00013 NWPFIG REQUEST NO. I-00013 *

.