AECM-87-0198, Provides Rev to 10-yr Inservice Insp Plan Relief Request I-00015 Submitted by .Rev Provides New Figure for Reactor Pressure Vessel Seam Ba,Demonstrating Geometric Limitation of Performing Required Volumetric Insp

Provides Rev to 10-yr Inservice Insp Plan Relief Request I-00015 Submitted by .Rev Provides New Figure for Reactor Pressure Vessel Seam Ba,Demonstrating Geometric Limitation of Performing Required Volumetric Insp

ML20236E684
Person / Time
Site:	Grand Gulf
Issue date:	10/26/1987
From:	Kingsley O SYSTEM ENERGY RESOURCES, INC.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
AECM-87-0198, AECM-87-198, NUDOCS 8710290313
Download: ML20236E684 (34)

Text

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icEl GCI 29 A 9 51 -

RE90tMCEE, INC.

OLM9 D. KtcsuY JR October 26, 1987 vce nese t u na cre mens y

U.lS. Nuclear Regulatory Commission Washington, D. C.

20555 Attention:

Document Control Desk 4

' Gentlemen:

.o

SUBJECT:

Grand Gulf Nuclear Station Unit 1

(

Docket No. 50-416 License No.-NPF-29 l

Ten-Year Inservice Inspection Plan

/

Relief Request I-00015 i

AECM-87/0198 The purpose of this submittal is to provide a revision to Relief Request I-00015-submitted by AECM-87/0112 dated June 12 1987. The relief request (attached)issubmitteiinaccordancewith1CFR50.55a(g)5(111).

The revision consists'of providing a new figure for Reactor Pressure Vessel (RPV) seam BA demonstrating the geometric limitation of performing the

-l required volumetric inspection. Additionally, System Energy Resources, Inc.

l (SERI)-withdraws the request for relief for seams AG, DH, DK, DJ, DM, DN and DP l

on the top head of the RPV from Relief Request I-00015. The top head seams will be inspected at Refueling' Outage 2 from the inside surface. The revision to Relief Request I-00015 was discussed with members of the NRC staff on 2

4 October 15, 1987 in Bethesda, Marylar,d.

Your expeditious review and approval of the subject relief request is requested.

SERI is scheduling a rafueling outage for November 6, 1987 and requests-NRC approval by December 15, 1987.

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

Your

uly, 8710290313 e71026 PDR ADOCK 05000416 1

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s Mr..N.lS.Reynolds~(w/a LMr.H.'LOThomas-(w/o) 1

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

.Dr.-J. Nelson-Grace, Regional Administrator $/a)

.U. S. Nuclear Regulatory Commission Region ~II.

j, 101 Marietta St...N. W., Suite 2900-Atlanta,- Georgiai 30323 l

Mr;'L.,L..Kintner,ProjectManager(w/a)-

V Office'of Nuclear Reactor Regulation q

l U. S. Nuclear Regulatory. Commission.

-7920 Norfolk Avenue iBethesda', Maryland 20814' l

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J16AECM87101901' 1 1;

GRAND GULF NUCLEAR STATION INS N CE ES N ON N INSERVICE INSPECTION SECTION 4 3l87gy",%

TEN YEAR PROGRAM Rvr m RIQUEST GRAND GUIF NUCLEAR STATION UNIT 1 RELIEF REQUEST NO. I-00015 l

l PAGE 1 of 3 l

t INSERVlCE INSPECI' ION OF REACIOR PRESSURE VESSEL WEIDS I.

Component:

Reactor pressure vessel (RPV) components, welds ard associated base material identified in table 1 of this relief request.

II.

Code:

'Ihe unit 1 reactor pressure vessel was designed aM fabricatM to ASME Section III, class 1 requirements. Applicable inservice inspections are to be performed in accordance with Regulatory Guide 1.150 Revision 1 and ASME Section XI, 1977 Edition with AddeMa through and including Summer 197.9. Also, Relief Request No. I-00013 permits the use of ASME Section XI,1983 Edition with the Summer 1993 Addenda, Figure INB-2500-7(b) for identifying the Code required examination volum.

III.

Code Requirements:

Table IWB 2500-1, Examination Category B-D, B-A and B-F, requires specified volunes to be examined volumetrically at specified periods during the ten year interval. Included in this volumo is varying degrees of base mate rial adjacent to each weld that also requires examination.

IV.

Information to Due to geometric configurations of the GGNS Unit 1 support the reactor, certain code required examination determination that volumes, as depicted in ASME Section XI, cannot be the code examined to the extent of obtaining full code requirements are coverage. Table 1 provides a listing of the impractical:

affected components and reactor pressure vessel welds with a detailed description of the cause and degree of the limitation.

Relief Request Number I-00014 prwides engineering rational addressing the limitations associated with the nozzle to vessel welds. 7he discussions provided prior operating plant experience to justify that no further examinations were necessary and additionally this was justified by recognizing that the feedwater nozzles are the limiting case. Although 100% of the code volumes vre not examined for the nozzle to vessel welds, t~fficient examination cmerage was obtained to det et any potential crac,:ing.

GRAND GULF NUCLEM STATiGN INSERtJICE INSPECI' ION REQUIREMENT'S INSERVICE INSPECTION SECTION 4 srsrEu (*'""

TEN YEAR PROGRAM RELIEF REQUEST RESOURCES, INC.

l anwo auw NuCtEm SrmON UNIT 1 RETM REQUEST 10. I-00015 PAGE 2 of 3 IV.

Information to A study of the welds listed in table 1 has support the shown that these weld locations are also determination that bounded by the feedwater nozzle discussions.

the code The stresses due to any expected loadings ard requirements are conditions at these locations are' bounded by impractical:

those at the feedwater nozzle locations.

(continued)

Supportirg the concept of the bounding is the fact that no indications have been found at any of the partially examined locations. In addition, it should be noted that a partial examination of each weld was obtained which included either all or a portion.of the f

reactor pressure vessel inner surface.

V.

Specific relief Permission is requested to perform ultrasonic requested:

examinations within the limitations described in table 1 of this relief request.

VI.

Reasons why relief Relief as described within should be granted should be granted:

for the following reasons.

1.

The entire reactor pressure vessel was I

subjected to an ASME Section III hydrostatic test after fabrication.

2.

The entire reactor pressure vessel will be subjected to system leakage test at each refueling outage and a system hydrostatic test each inspection interval in accordance with the requirements of ASME Section XI.

1 3.

The subject welds were volumetrically examined in accordance with ASME Section l

III during fabrication.

{

l i

1 e-41 t_______

s f.,

GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIRDIENTS I -

INSERVICE INSPECTION SECTION 4 l.

srsru Zuur TEN YEAR PROGRAM pri m REQUEST V

RCSovRCES, INC.

GRAND GUIF NUCEAR SIATION

)

UNIT 1 i

RET M REQUEST NO. I-00015 PAGE 3 of 3 VI.

Reascas why relief 4.

W re is no history of service induced should be granted; flaws in these areau of the reactor pressure vessel other than those of the feedwater nozzles M a' m ed in Relief Request Number I-00014.

5.

The areas of the reactor pressure vessel I

beirg examined are the limiting areas.

6.

The potential for initiation and propagation of cracking has been discussed assuming both fatigue and stress corrosion cracking mechanisms. It was concluded by the use of limiting analyses results performed for the feedwater nozzle blend radii, that

. crackirg is unlikely at Grand Gulf nozzle / vessel weld locations In fact, even if it was hypothesized that thess postulated cracks went undetected, a crack length of 58 inches was required before rapid crack growth were to occur i

I during normal operation. It is unlikely that cracks of this size would go undetected. Therefore, a significant leak before break margin exists.

VII.

Alternate testing:

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j GRAND GULF NUCLEAR STATION INSERVICE INSPEC' FIN RByum INSERVICE INSPECTION sEcrION 4 l

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TEN YEAR PROGRAM pn m REQUEST GRAND GUIF NUCIEAR STATION UNIT 1 1

FM N REguESP No. I-00015 i

s N1 RECIRCUIATICH CUfIEf N0ZZIE 'IO SAFE DID WEID IlMITATIONS i

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Automated techniques utilizing a 45' shear wave obtains two directional 2

coverage of an area equal to.17 in,

Also, a 45' and 60' refracted longitudinal (RL) wave is utilized that o

obtains one directional coverage of the entire code volum scanning from the nozzle side.

o The cross hatched area received the one directional coverage from the nozzle side, the remaining area was examined from two directions utilizing the shear wave.

o Manual examinations will provide two directional coverage of the weld and nozzle base material, the available "W" dimension on the safe end side of the weld is insufficient to obtain full coverage of the safe end material.

FIGURE 14

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60*RL 45 f.

Total code volume at a cross sectional view is.846 in2 o

Automated techniques utilized a 45' and 60' RL wave for the examination of the N2F and N2H to obtain complete code volume coverage from one direction with both angles.

1

'Ihe remainirq N2 nozzles (A,B,C,D,E,G,J,K,M,N) were examined o

completely from one direction with only the 60' due to excessive noise received with the 45' traneAo m rs Manual examinations can provide two directiond coverage of the o

area represented by the y hatching, this would improye total l

code coverage to.271 in or 32% for the 60' and.642 in or 75.6% for the 45'.

o If the presently available 45' transducers are improved to reduce noise levels, future examinations will include the 45' for improved coverage.

l FIGURE 15

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GRAND GUIE NUCIEAR STATION l

UNIT 1 PM N REQUEST NO. I-00015 2

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of the total code volume.

FIGURE 16 I

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FIGURE 17 I

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TEN YEAR PROGRAM FM N REQUEST ll GRAND GUIE NUCIEAR STATION UNIT 1 l

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tions will increase two directional coverage by 9.7%

FIGURE 18

GRAND GULF NUCLEAR STATION INSERVICE INSPECTIN N INSERVICE INSPECTION SECTION 4 i

3" $ j,""'d, TEN YEAR PROGRAM-RMN REQUEST GRAND GUIE NUCIEAR SIATION UNIT 1 Pn m REQUEST No. I-00015

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of the total code volume.

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