ML20117H133
| ML20117H133 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 05/21/1996 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20117H125 | List: |
| References | |
| NUDOCS 9605280042 | |
| Download: ML20117H133 (69) | |
Text
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GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREhENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS PAGE 1 OF 3 l GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00002, REVISION 3 l
INSERVICE INSPECTION
)
OF PRESSURE RETAINING WELD IN SCRAM DISCHARGE VOLUME PIPING I.
Comoonent:
An inaccessible portion ofweld No. 91 on the scram discharge volume piping (12" EBB line) is located in the Control Rod Drive Hydraulic (C11) System. (See the attached sketch.)
II.
Cpic The subject pressure retaining piping weld was designed and fabricated to ASME Section III, Class 2 requirements. Applicable inservice inspections are to be performed in accordance with AShE Section XI,1977 Edition through and including Summer 1979 Addenda.
.III, Code reauirements:
Class 2 pressure retaining piping welds are required to be volumetrically and surface examined once ever ten-year interval in accordance with ASME Section XI, Table IWC-2500-1, Category C-F.
IV.
Information to suonort the determination that the code reauirements are imoractical:
The installation of a bracket directly above the circumferential weld No. 91 has limited the accessibility to the weld for unitrasonic examination. The inaccessible portion of the weld is approximately 5.5 inches of the circumference of the 12 inch NPS pipe, or 14 percent of the weld length.
V.
Soecific relief reauested:
Permission is requested to delete the requirement to volumetrically examine the portion of weld No. 91 inaccessible due to the installed bracket.
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GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS PAGE 3 OF 3 l BR ACKET
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GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREhENTS l
l INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS l
PAGE 1 OF 1 GRAND GULF NUCLEAR STATION UNIT 1 j
RELIEF REQUEST I-0004, REVISION 3 R9RVICE INSPECTION RPV LOWER JEAD-TO-SHELL WELD A-A i)ELETED 1
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GRANb GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS l
PAGE 1 OF 1 GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-0005, REVISION 2 INSERVICE INSPECTION l
RPV SEAM WELD A-B LOWER HALF 1
DELETED i
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a GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIRENENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS j
PAGE 1 OF 1 l GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-0006, REVISION 3 l
INSERVICE INSPECTION RPV SEAM WELD A-C DELETED
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GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4
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TEN YEAR PROGRAM RELIEF REQUESTS PAGE 1 OF 3 l l
GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-0007, REVISION 2 l
)
INSERVICE INSPECTION OF j
PIPING WELDS WITHIN GUARD PIPES I.
Comoonent:
ASME Section III, Class 1 pressure retaining circumferential welds located in Feedwater Loops A and B (B21), Main Steam (B21), Reactor Core Isolation Cooling (E51), Residual Heat Removal (E12), and Reactor Water Clean-up (G33) piping. These welds are located on system piping inside guard pipes, which extend beyond the containment. The applicable welds are listed in Table 1.
II.
Cads These welds were designed and fabricated to ASME Section III, Class 1 requirements. Applicable inservice inspection is to be performed in accordance with ASME Section XI,1977 Edition through and including Summer of 1979 Addenda.
IIL Code reauirements:
Class 1 pressure retaining piping welds are required to be volumetrically and surface examined once each ten year inspection interval in accordance with ASME Section XI, Table IWB-2500-1, Examination Category B-J.
IV.
Information to succort the determination that the code reauirements are imoractical:
The circumferential welds joining the flued head and the process pipe are encapsulated by the portion of the guard pipe which protrudes beyond the containment. To comply with the inservice inspection requirements of ASME Section XI, two 4" x 6" elliptical access ports spaced 180' apart l
l are provided for access to the welds. During the development of the access port design, the l
inservice contractor had indicated that the ports were adequate to permit performance of surface and ultrasonic examination of the entire weld.
After fabrication and installation of the process pipe, guard pipe, and flued head, it was determined that the entire length of the weld is not accessible through the two access ports.
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GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS PAGE 2 OF 3 l l
GRAND GULF NUCLEAR STATION UNIT 1 l
RELIEF REQUEST I-00002, REVISION 3 l
l INSERVICE INSPECTION OF PRESSURE RETAINING WELD IN SCRAM DISCHARGE VOLUME PIPING VI.
Reasons why relief should be cranted:
Request for exemption from inservice volumetric (ultrasonics) examination of the inaccessible portion of this weld should be granted for the following reasons:
1.
This weld was examined by radiography and passed in accordance with ASME Section III, Class 2 requirements.
2.
This weld was surface examined (liquid penetrant) and pa; sed in accordance with ASME Section,XI, Table IWC-2500-1, Category C-F requirements.
3..
The accessible portion of this weld was volumetrically examined using ultrasonic techniques and passed in accordance with ASME Section XI, Table IWC-2500-1 requirements.
4.
This weld has been hydrostatically tested in accordance with AShE Section III, Class 2 requirements.
5.
This weld will be subject to pressure testing in accordance with the requirements of AShE Section XI, Table IWC-2500-1 and ASME Section XI Code Case N-498-1.
6.
The portion of this weld inaccessible for volumetric examination will be surface examined each inspection interval in accordance with ASME Section XI, Table IWC-2500-1, Category C-F requirements.
VII.
Alternative testing:
The accessible portion of the weld will be volumetrically and surface examined each inspection interval in accordance with ASME Section XI, Table IWC-2500-1. Should indications be l
l found, an engineering evaluation will be made to determine if the inaccessible portion of the l
weld has been affected. The inaccessible portion of this weld represents approximately 14 percent of the total weld length.
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GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS PAGE 2 OF 3 l GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-0007, REVISION 2 l
i INSERVICE INSPECTION OF PIPING WELDS WITHIN GUARD PIPES V.
Soecific relief reauested:
Permission is requested to perform ultrasonic examination of the welds listed in Table 1 to the extent possible through the 4" x 6" access ports. Also, permission is ~ requested to perform the code-required surface examinations on the same welds to the extent possible through the access ports. The percentage of each weld examined will be recorded during the inservice examination.
VI.
Reasons whv relief should be eranted:
Exemption is requested for the inservice inspection ofinaccessible portions of welds located inside guard pipes for the following reasons:
'l.
All but one of these lines were designed to high energy pipe break criteria. The exception is QlE12G012W47 which is classified as moderate energy pipe.
2.
These welds were designed and fabricated in accordance with ASME Section III, Class I requirements and were examined by radiographic and liquid penetrant techniques.
3.
These welds have satisfactorily passed both liquid penetrant and ultrasonic examinations in accordance with ASME Section XI, Class 1 requirements (preservice relief request no.
00001).
4.
Class 1 isolation valves in the process pipe on both sides of the guard pipes are capable of completely isolating each pipe in the event of a pipe failure.
5.
The guard pipes have been designed and constmeted in accordance with ASME Section III, Class 2 requirements and were hydrostatically tested in accordance with ASME Section III, Class 2 requirements.
6.
The guard pipes are open to the drywell environment; thus, any leakage due to weld failure will be contained within the drywell. The guard pipes will prevent any leakage from escaping to the Containment Building.
7.
The process pipes inside the guard pipes were hydrostatically tested in accordance with ASME Section III, Class I requirements.
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GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIIEMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS j
PAGE 3 OF 3 l GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-0007, REVISION 2 l
INSERVICE INSPECTION OF PIPING WELDS WITHIN GUARD PIPES 8.
The process piping inside each guard pipe assembly will be subject to pressure testing in accordance with AShE Section XI, Table IWB-2500-1 and AShE Section XI Code Case N-498-1.
Vll.
Alternative testing:
The accessible length of each weld will be ultrasonically and surface examined in accordance with ASME Section XI, Table IWB-2500-1, Examination Category B-J.
Should signs of weld deterioration or discrepancies be noted during regular inspections, evaluation of the conditions will i
be made.
. Note: In addition, a relief request (No. 00001) based on the above logic for four-(4) welds on
' main steam pipes was submitted earlier with the Unit 1 preservice inspection. The Nuclear
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Regulatory Commision accepted this request for reliefin GGNS Safety Evaluation Report, l
Supplement #2.
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GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 -
TEN YEAR PROGRAM RELIEF REQUESTS GRAND GULF NUCLEAR STATION UNIT I RELIEF REQUEST I-0007, REVISION 2 l
TABLE 1 EXAMINABLE EXAMINABLE FIEM SYSTEM WELD ISO PIPE VOLUMETRIC TYPE SURFACE ~
WELD REASON FOR NO.
NO.
NO.
NO.
SIZE COMPONENT AREA SCAN AREA CLASS TYPE IJMrrAT10NS I
B21 Gl2-CI-A MS 81-9 28" PIPE TO PIPE 2P4 T
NOTEI I
CIRC GUARD PIPE 2
B21 Gl2-Al-A MS-I I-3 28" PIPE TO PIPE 27 %
T NOTEI I
CIRC GUARD PIPE 3
B21 G12-DI-A MS-II-12 28" PIPE 10 PIPE 27 %
T NOTEI I
CIRC GUARD PIPE l
4 B21 Gl2-BI-A MS-11-6 28" PIPE TO PIPE 27 %
T NOTEI 1
CIRC GUARD PIPE 5
B2I W2 FW-11-1 24" PIPE TO PIPE 24 %
T NOTEI I
CIRC GUARD PIPE 6
B21 W18 FW-11-7 24" PIPE TO PIPE 24 %
T NOTEI 1
CIRC GUARD PIPE 7
DELETED
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8 E12 W47 RH-11-1 20" PIPE 10 PIPE 19 %
T NO1E I I
CIRC GUARD PIPE 9
DELETED l
10 E51 W7 RI-l1-3 10" PIPE TO PIPE 100 %
T NOTEI 1
CIRC GUARD PIPE II G33 WIS CU-l 1-3 6"
PIPE TO PIPE 50 %
T NO1E 1 1
CIRC GUARD PIPE NOTE 1:
The percentage of each wcid that is accessible for surface examination will be recorded during the inservice examination.
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-0007, REVISION 2 l
FIGURE 1 J
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1 GRAND GULF NUCLEAR STATION INSERVICEINSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 l
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TEN YEAR PROGRAM RELIEF REQUESTS PAGE 1 OF 3 l GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00008, REVISION 3 l
INSERVICE INSPECTION OF CONTROL ROD DRIVE AND INCORE HOUSING WELDS & FLANGE BOLTING L
Comoonent:
Peripheral control rod drive housing welds (tube-to-tube, tube-to-flange) and bolting located on CRD housings.
]
II.
Cgdg:
These portions of the CRD and in-core housing were designed and fabricated to the ASME Section III, Class 1 requirements. Applicable inservice inspections are to be performed in accordance with ASME Section XI,1977 Edition through and including Summer 1979 Addenda.
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III.
Code reauirements:
1.
Welds located in 10% of the peripheral CRD housings require surface examination (dye penetrant) during each ten-year inservice inspection interval in accordance with ASME Section XI, Table IWB-2500-1, Examination Category B-0.
l 2.
Pressure retaining bolting for the flange-to-flange joints, located on the CRD and incore housings, are required to be visually examined (VT-1) once every ten-year inspection interval in accordance with ASME Section XI, Table IWB-2500-1, Examination Category B-G-2.
l IV.
Information to support the determination that the code reauirements are imoractical:
l The weld areas and bolting are not accessible for inspection unless the control rod drive (CRD) support structures are removed. A 360' surface examination cannot be accurately accomplished from the outside, due to interference from the adjacent CRD housings InWon of the weld from the inside of the CRD housing would require that the CRD mechanism be removed, which could result in damage to the drive. With removal of the drive, a small amount of reactor water would escape to the CRD L
cavity area, possibly causing contamination of personnel and equipment. The time frame associated with the CRD support stmeture removal and CRD mechanism would be approximately six (6) man hours per l
drive. Dosage received by personnel in this interval cannot justify the inspection process to possibly find a fault which could be discovered by excessive leakage in the drywell sump monitored per Operating License Manual (Technical Specification) limits in effect.
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GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS PAGE 2 OF 3 l GRAND GULF NUCLEAR STATION UNIT 1 l
RELIEF REQUEST I-00008, REVISION 3 l
l t
INSERVICE INSPECTION i
OF CONTROL ROD DRIVE AND INCORE HOUSING WELDS & FLANGE BOLTING l
V. '
Soecific reliefreauested:
Permission is requested to exempt from inservice inspection, the peripheral CRD housing welds (tube-to-tube, tube-to-flange), the eight (8) bolts associated with each flange of 193 CRD housings and the l
four bolts associated with each flange of 58 incore housings.
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- VI.
Reasons why relief should be eranted:
Request for exemption from inservice inspection should be granted for the following reasons:
1.
The peripheral CRD housing welds have been exi$i.ed by radiography and liquid penetrant methods and have been hydrostatic tested in accordance with ASME Section III code requirements.
2.
All incore and CRD housing bolting has been examined in accordance with the requirements of l
ASME Section III, which exceed the Section XI (VT-1) visual examination requirements.
3.
The welds and bolted connections will be subject to pressure testmg in accordance with the requirements of ASME Section XI, Table IWB-2500-1 and ASME Section XI Code Case N-498-1.
4.
If the welds and/or the bolts fail while in operation, the maximum leakage rate, by calculation, will occur at at the peripheral CRD housing tube-to-flange weld. 'the maximum calmlatad leak rate is to 681 gpm. By entena established in Subarticle IWB-1200, " exemptions by make up capacity," the normal make up capability for GGNS is 878 gpm, which exceeds the calculated maximumleakage.
5.
I.eak detection is provided with the leakage detection system, with continuous monitoring in the control room.
6.
The CRD housing supports would prevent ejection of the housings in case of total failure of the l
welds or bolts.-
I 7.
Removal of the CRD support structure would result in hardships with no compensatory increase in the level ofquality and safety.
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GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREhENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM i
RELIEF REQUESTS PAGE 3 OF 3 l GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00008, REVISION 3 l
INSERVICE INSPECTION OF CONTROL ROD DRIVE AND INCORE HOUSING WELDS & FLANGE BOLTING VII.
Alternate testina:
None NOTE A similar request for relief from preservice inspection requirements was accepted by NRC in GGNS Safety Evaluation Report, Supplement #2.
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GRAND GULF NUCLEAR STATION INSERVICEINSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS PAGE 1 OF 3 l GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00009, REVISION 3 l
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INSERVICE INSPECTION OF PUMP CASING AND ATTACHMENT WELDS i
1.
Comoonent:
Pump casing and attachment welds located within the surrounding concrete pump suppon i
encasement for the following pumps (see attached list and sketches):
PUMP PUMP NO.
SKETCH NO.
Residual Heat Removal 1E12C002B RH-8-12 Low Pressure Core Spray lE21C001 LP-9-4 High Pressure Core Spray IE22C001 HP-8-10 11.
Cads l
, The three pumps listed above were designed and fabricated to the ASME Section III, class 2 l
requiremen'ts. Applicable Inservice Inspection is to be preformed in acco'rdance with ASME Section XI,1977 Edition through and including Summer 1979 Addenda and Code Case N 343.
III.
Code Reauirements:
j Pressure retaining welds, and attachment welds that provide a support function are required to l
receive a surface examination once every ten-year interval in accordance with ASME Section XI, Table IWC-2500-1 category C-C and C-G.
IV.
Information to supoort the determination that the Code requirements are impractical:
Inaccessible pump casing welds are located where the concrete pump support encasement only allows a 3 inch clearance between the pump casing and the concrete encasement wall (see figure 1 for details of the design). Due to the limited accessibility, it is impractical to surface examine those ponions of the welds located within the surrounding concrete pump support encasement. The IE12C002B and IE21C001 pumps also have a support integrally welded to the bottom exterior of the pump barrel that rests against the sump floor. The clearance between the floor and the bottom of the barrel is approximately 1 inch preventing sufficient access to perform the surface examination i
of the 1/2 inch of base material on each side of the attaching weld (see figure 2).
i e
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 i~
TEN YEAR PROGRAM RELIEF REQUESTS PAGE 2 OF 3 l GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00009, REVISION 3 l
INSERVICE INSPECTION OF PUMP CASING AND ATTACHMENT WELDS I
V.
Soecific reliefReauested:
Permission is requested to exempt from inservice inspection the inaccessible portions of the pump j
casing welds listed on Table 1. Also permission is requested to exempt the base material associated
].
with the support attachment welds from the surface examinations as shown in figure 2.
I VI.
Reasons why relief should be granted:
Request for exemption should be granted for the following reasons:
j 1.
The pump casing welds have been volumetrically examined by radiography and passed in accordance with the ASME Section III, Class 2 requirements.
i 1
2.
The attachment welds were surface examined and accepted in accordance with the i
requirements of ASME Section III, Class 2 requirements.
i 3.
The accessible length of each applicable casing weld will be surface examined in accordance with ASME Class 2 requirements.
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4.
The entire weld volume of each support attachment weld will be surface examined in accordance with ASME Class 2 requirements.
5.
The failure of these welds, thus leading to failure of the pump, would have no adverse effect on plant safety, as redundant emergency core cooling systems are provided.
I 2
6.
Annunciators (i.e. Iow suction pressure, discharge pressure abnormal, etc.) are provided in the control room, along with other system indicators, to alert the oparators to abnormal l
operating conditions.
4 7.
The systems, including the pumps, are tested per the GGNS Operating License Manual
)
(Technical Specifications) requirements to ensure operability.
J 8.
Pumps will be subject to pressure testing in accordance with ASME Section XI, Table IWC-2500-1 and ASME Section XI Code Case N-498-1.
4
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS PAGE 2 OF 3 l GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00010, REVISION 6 l
INSERVICE EXAMINATION OF PRESSURE RETAINING WELDS VI.
Rehsons why relief should be granted:
Request for permission to limit the code required examination to the accessible areas should be granted for the following reasons:
1.
The inaccessible portions oflisted pressure retaining welds were examined by radiography, passed in accordance with ASME Section III, Class 1 and 2 requirements.
2.
The inaccessible portions of the pressure retaining and integral attachment welds were surface examined (magnetic particle or liquid penetrant), passed in accordance with ASME III and/or XI, Class 1 and Class 2 requirements.
3.
The piping welds with limited examinations will be subject to pressure testing in accordance with ASME Section XI, Table IWB-2500-1 or IWC-2500-1, as applicable, and ASME Section XI Code Case N-498-I.
4[
Deleted l
S.
Acc:ssible portions of listed welds will be volumetrically and surface examined each insp;ction interval in accordance with ASME Section XI. Should indications be found, an eng'neering evaluation will be made to determine if the inaccessible portions of the listed wdds have been affected.
6.
Leak detection is provided, by way of the leakage detection system with continuous monitoring, for the RHR, RCIC, MS, RWCU, RECIRC and FW systems.
7.
The failure of any one of these pressure retaining piping welds would have no adverse effect on plant safety as there is isolation capability and/or shut down capability as part of the plant design. The design analysis bounds the limiting fault conditions for line breads in and outside of containment.
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS PAGE 3 OF 3 l GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00010, REVISION 6 l
INSERVICE EXAMINATION OF PRESSi/RE RETAINING WELDS 8.
The calculated maximum piping stresses and usage factor at the integral attachments on the piping, including consideration of the local pipe wall stresses, have been determined in the j
Class 1 Stress Report and are equal to the following.
)
Item No. 45,46,47, and 48 (System No. B21) a)
Primary plus secondary (equation 10); 32,775 psi (1.72 S.),
b)
Usage factor is 0.0442.
Item No. 78 and 79 (System No. B33) a)
Primary plus secondary (equation 10); 22,792 psi (1.37 S m),
b)
Usage Factor is 0.0071 Circumferential and longitudinal welds in piping with stress levels below 2.4 S and usage factors below 0.4 are excluded from ISI examinations, in accordance with Table IWB-2500-1 Category B-J.
9.
Examinations at GGNS of category B-J, B-K-1 and C-F welds have not identified any flaws or evidence of service induced degradation.
VII.
Alternate testing:
The applicable welds will be examined to the maximum extent practical as determined by the extent of the specific limitation. Each weld will be subjected to a volumetric or surface examination as required by Talbes IWB and IWC 2500-1.
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GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUtREhENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS 4l GRAND GULF NUCLEAR STATION UNIT 1
)
RELIEF REQUEST I-00009, REVISION 3 l
TABLE 1 l
LIST OF PUMP'WELOS '
E12 - RHR PUMP "B" CASING Welds Surfaces ht Shall Be Examined DH-1 DH-4 DH-7 SB-4 SB-7 DH-2 DH-5 DH-25 SB-5 DH-3 DH-6 SB-3 SB-6 Welds That Can Be Partially Examined Welds that cannot be examined SB 2 (18" accessible 54" inaccessible)
SB-1 (inaccessible)
Attachment welds that can be canially examined SB-12 (see figure 2 for details oflimitation)
E21 - LPCS PUMP CASING Welds Surfaces That Shall Be Exwined DH 1 DH-4 DH-7 SB-4 SB-7 D' -2 DH-5 DH-27 SB-5 H
DH-3 DH-6 SB 3 SB-6 Welds That Can Be Partially Examined Welds hat Cannot Be Examined SB-2 (3" accessible, 69" inaccessible)
SB 1 (inaccessible)
Attachment Welds ht Can Be Partially Examined SB-12 (see figure 2 for details oflimitation)
E22 - HPCS PUMP CASING Welds Surfaces That Shall Be Examined DH-1 DH-4 DH-7 SB-4 SB-7 l
DH-2 DH-5 DH-19 SB-5 l
DH-3 DH-6 DH-28 SB-6 l
Welds That Can Be Partially Examined Welds That Cannot Be Examined l
Deleted SB-1 (inaccessible) l SB-2 (inaccessible)
SB-3 (inaccessible)
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS RELIEF REQUbST I-00009, REVISION 3 l
FIGURE 1 DH-5
>25 V
24"-G88-73 o
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onkh l-CH-4 60H-2
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$1490LTse OH-G EOUF E NT SLFPGlis flM-t uEy.sr t-? '
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,i T* CLEARANCE BETWEEW Ptte i
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REler0RCING BAND
$8-3d Sg,4 58-5 NOTE:
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LONGITUDINAL WEtDDENTS ARE:
DH-7. 58-2. SB-4. 0H-25 & 58-6 58 4 flEINFbRCING SADO g SB-7
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58-12 eATTACHMENT WELDS MPL No. lEt2GOIO susrps totarum w cor, e r ser, espec aun.
u.. 52 tEOUIP9(NT SUPPORin Real B AUK. SLOC.
M-13408 P-e005a
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INSERVICE INSPECTION REQUIREMENTS GRAND GULF NUCLEAR STATION INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS RELIEF REQUEST I-00009, REVISION 3 l
FIGURE 1
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es
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GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS RELIEF REQUEST I-00009, REVISION 3 l
FIGURE I I
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13 RAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RET TEF REQUESTS RELIEF REQUEST I-00009, REVISION 3 l
FIGURE 2 1
I
~
j t
i
~
l i
BOTTOM OF PUMP COLUMN g
S<
PUMP j
BARREL u
y SUPPORT 3,o ATTACHMENT WELD
/
I K5?.'[},.' h
.. j;Cy '
p* *j.g.7.$'.:.
..b:..
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CONCRETE FLOOR IN BOTTOM OF PUMP SUMP ATTACHMEF r WELD LIMITATIONS PUMPS lE'2 COO 28 ANO IE21COOI
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS j,
INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS i
PAGE 10F 3 l 4
f GRAND GULF NUCLEAR STATION 3
UNIT 1 RELIEF REQUEST I-00010, REVISION 6 l
INSERVICE EXAMINATION 4
j OF PRESSURE RETAINING WELDS
[
I.
Comoonent:
Inaccessible portions of ASME Section III, Class I and 2 pressure retaining and integral attachment i
piping welds listed in Table 1 (see attached).
j II.
Cads i
These portions of the pressure retaining and integral attachment piping welds were designed and i
fabricated to ASME Section III, Class 1 and Class 2 requirements. Applicable inservice inspections are to be performed in accordance with the ASME Section XI,1977 Edition, through and including 4
th'e Summer 1979 Addenda.
I III.
Code Reauirements:
Class 1 and Class 2 pressure retaining piping welds are required to be volumetrically and surface examined, essentially 100% of the weld, once every ten year interval in accordance with ASME Section XI, Table IWB-2500-1, Category B-J, Table IWC-2500-1, Category C-F. The Class 1 l
integral attachment welds depicted in table 1 are required to be surface examined once each ten j
year intervalin accordance with ASME Section XI, Table IWB-2500-1, Category B-K-1.
IV.
Information to sunoort the determination that the Code reauirements are imoractical:
Portions ofwelds that were preservice examined have physical obstructions due to design. Due to this limited accessibility, it is impractical to perform the surface and volumetric examination for
}
100% of the required examination volume as indicated for the welds listed in Table 1.
1 l
V.
Soecific Relief Reauested:
I Permission is requested to perform the Code required examinations to the extent described in Table t
l.
i i
i
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS PAGE 3 OF 3 l 1
i GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00009, REVISION 3 l
INSERVICE INSPECTION OF PUMP CASING AND ATTACHMENT WELDS 9.
Approximately 82 percent of the welds on the subject pump, which require surface examination, are accessible. Performance of the required examinations on these accessible welds should ensure that generic degradation is not occurring in these pump casing welds.
NOTE-A similar request for relief from preservice inspection of the pump casing welds has been accepted by the NRC in GGNS Safety Evaluation Report, Supplement No. 2.
VII.
Alternate Testina:
None e
t i
a 8
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST l-00010, REVISION 6 l
l TABLEI l
EXAMINABLE EXAMINABLE ITEM SYSTEM WELD ISO PIPE VOLUMETRIC T/PE SURFACE WELD REASON FOR NO NO NO NO SIZE COMPONENT AREA SCAN AREA CLASS TYPE LIMITATIONS I
E12 Gol4-FW-44 RII44 6"
VALVE TO ELBOW 55 %
T 100 %
1 CIRC ELBOW RAlWUS 2
B21 G9-CI-B-11B MS-114 28" ELBOW SEAM 38 %
T 38 %
I LONG P!PE RESTRAINT 3
E51 G0044-8-1 RI-8-2 6"
ELBOW TO ELBOW 70 % -
T 100 %
2 CIRC ELBOW RADIUS l
4 B21 Gil-DI-B-11B MS-I l-ll 28" ELBOW SEAM 38 %
T 38 %
1 IDNG PIPE RF51RAINT 5
B21 G8-Al-B-11B MS-I l-2 28" ELBOW SEAM 38%
T 38 %
1 LONG PIPE RES1RAINT 6
B21 G030-FW-23 FW-8-2 24" VALVE TO PIPE 93%
T 100 %
1 CIRC SOCK-O-LET 7
B21 G030-FW-36 FW-8-4 24" VALVE TO PIPE 93%
T 100 %
I CIRC SOCK-O-LET 8
B21 G026-FW-17 FW-11-7 24*
PIPE TO TEE 93%
T 100 %
1 CIRC SOCK-O-LET 9
B2I G001-W4 MS-l 1-3 28" VALVE TO PIPE 82 %
T 100 %
1 CIRC PIPE RE:5 I KAINT 10 B21 G001-W4 MS-1 I-9 28' VALVE TO ELBOW 82 %
T 100 % -
1 CIRC PIPE RESTRAINT 11 B21 G9-CI-B-11A MS-Il4 28' ELBOW SEAM 38%
T 38 %
I LONG PIPE RESTRAINT DELETED j
13 E51 G004-7-8-4 RI4-1 10*
REDUCER TO TEE 71 %
T 100 %
2 CIRC TEE 14 E51 G004-74-9 RI4-1 10' REDUCER TO1EE 71%
T 100 %
2 CIRC TEE j
15 ESI G004-744 RI-8-1 10" REDUCER ~ID TEE 71 %
T 100 %
2 CIRC TEE l
16 B33 G024.W2 RR-ll-19 4"
ELBOW TO TEE 62 %
T 100 %
I CIRC TEE DELETED 18 B21 G11-DI-B-11A MS-11-11 28" ELBOW SEAM 38% -
T 38 %
1 LONG PIPE RESTRAINT 19 B2i G001-W9 MS-I l-12 28" VALVE TO PIPE 82 %
T 100 %
I CIRC PIPE RESTRAINT 20 B2I G8-Al-B-lJA MS-11-2 28" ELBOW SEAM 38%
T 38 %
1 LONG PIPE RESTRAINT 21 E51 G001-WI RI-8-12 6"
VALVE TO ELICW 73%
T 100 %
2 CIRC ELBOW RAINIIS 22 E51 G001-W40 RI-I l-4 6"
VALVE TO ELBOW 51.5 %
T 100 %
1 CIRC ELBOW RADRJS 23 B33 G001-W5 RR-11-2 24" ELBOW TO PUMP 73% see note I T
100 %
I CIRC PUMP l
24 B33 G001-W6 RR-11-2 24" PIPE TO PUMP 58% see note I T
100 %
1 CIRC PUMP 25 B33 G001-W8 RR-II-3 24" VALVE TO PIPE 50% see note 2 T
100 %
I CIRC VALVE 26 B33 G001-W28 RR-11-9 24" ELBOW TO PUMP.
62% sae note I T
100 %
1 CIRC PUMP 27 B33 G001-W29 RR-11-9 24*
PIRAP TO PIPE 61% see note i T
100 %
1 CIRC PUMP 1
l
i GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00010, REVISION 6 l
TABLEI EXAMINABLE EXAMINABLE I1EM SYSTEM WELD ISO PIPE VOLUMETRIC TYPE SURFACE WELD REASON FOR NO NO NO NO SIZE COMPONENT AREA SCAN AREA CLASS TYPE LIMITAllONS 28 B33 G001-W31 RR-lI-10 24" VALVE TO PIPE 50% see note I&2 T
100 %
1 CIRC VALVE 29 B33 GS-BI-B RR-II-9 4*/24*
SWEEP TO PIPE 59% see note I T
100 %
1 BRANCH SWEEP-O-ET 30 B33 GS-Bi-E RR-II-9 4*/24*
SWEEP TO PIPE 63% see note I T
100 %
i BRANCH SWEEPoLET 31 B33 G023-W37 RR-11-15 20*
TEE TO PIPE 65% see note 1 T
100 %
1 CIRC TEE 32 B33 G024.W8 RR-II-16 4*
PIPE TO SWEEP 50% see note 2 T
100 %
1 CIRC SWEEPoLET 33 B33 G024-W27 RR-Il-17 4"
PIPE TO SWEEP 50% see note 2 T
100 %
1 CIRC SWEEP &LET 34 B33 GIO-BI-L RR-II-Il 12*/16" SWEEP TO PIPE 50% see note 3 P
100 %
1 BRANCH SWEEP-O-ET 35 B33 GIO-BI-K RR-11-Il 12*/I6' SWEEPTO PIPE 50% see note 3 P
100 %
1 BRANCil SWEEP-O-ET 36 B33 G10-BI-3 RR-II-Il 12*/16*
SWEEP TO PIPE 50% see note 3 P
100 %
1 BRANCH SWEEP-O-ET 37 B33 GIO-Bi-H RR-II-Il 12*/16*
SWEEP TO PIPE 50% see note 3 P
100 %
1 BRANCH SWEEP-O-MT 38 B33 GIO-BI-G RR-II-Il 12*/16*
SWEEP TO PIPE 50% see note 3 P
100 %
1 BRANCH SWEEP O-ET 39 B33 GIO-BI-F RR-II-Il 12*/16*
SWEEP TO PIPE 50% see note 3 P
100 %
I BRANCH SWEEP-O-ET 40 B33 G001-W34 RR-11-11 24*
PIPE TO CROSS 50% see note 3 P
100 %
1 CRC CROSS 41 B33 GIG-BI-A RR-11-11 16' PIPE TO CROSS 50% see note 3 P
100 %
1 CRC CROSS 42 B33 G10-BI-B RR-11-11 16* -
PIPETO CROSS 50% see note 3 P
100 %
1 CRC CROSS 43 B21 G8-Al-C MS-11-2 8*/28' SWEEPTO PIPE 100 %
T 98 %
1 BRANCH PIPE SUPPORT 44 B21 0026-W36 FW-il-1 24' PIPE TO VALVE 95 %
T 100 %
1 CIRC PIPE SUPPORT 45 B21 G8-Al-L,M,N,P MS-11-2 28' LUGS TO PIPE N/A N/A 49%
1 INT ATT PIPE RESTRADff 46 B21 GIO-Bi-L,M,N,P MS-II-5 28*
LUGS TO PIPE N/A N/A 49%
1 INTATT PIPE RESTRAINT 47 B2I G9-Cl-L,M,N,P MS-11-8 28" LUGS TO PIPE N/A N/A 49%
1 INT ATT PIPE RESTRADir 48 B21 GI l-DI-L,M,,N,P MS-11-11 28*
LUGS TO PIPE N/A N/A 49%
1 INT ATT PIPE RESTRAINT 49 B33 G001W27 RR-l1-9 24" PIPE TO VALVE 50% see note 1 T
100 %
1 CRC VALVE 50 B33 G001W33 RR-11-10 24' VALVE TO PIPE 50% see note 1 T
100 %
1 CIRC VALVE St B33 G10-Al-A RR-1l-4 16*
CROSS TO PIPE 50% see note 3 P
100 %
I CIRC CROSS 52 B33 G10-Al-B RR-11-4 16" CROSS TO PIPE 50% see note 3 P
100 %
I CIRC CROSS 53 B33 G6-BI-C RR-II-9 4*/24" PIPE TO SWEEP 50% see note I T
100 %
1 BRANCH SWEFP 54 B33 Glo-Al-F RR-I I-4 16*/12" PIPE TO SWEEP 50% see note 3 P
100 %
I BRANCH SWEFP I
.._. _.-_. _._ _. _._ - _.. _ _.- _. _ _. _.-. - - m _ _ _. _ _ _.. _....... _
t
.i GRAND GULF NUCLEAR STATION
-INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS i
i GRAND GULF NUCLEAR STATION l
UNIT 1 l
RELIEF REQUEST I-00010, REVISION 6
. l' t
I l
TABLEI l
i I
EXAMINABLE EXAMINABLE TEM SYSTEM WELD ISO PIPE VOLUMETRIC 1YPE SURFACE WELD REASON FOR NO NO NO NO SIZE COMPONENT AREA SCAN AREA CLASS TYPE LIMITATIONS 55 B33 GIO-Al-G RR-il-4 16*/12" PIPE TO SWEEP 50% see note 3 P
100 %
I BRANCH SWEEP 56 B33 G10-A1-H RR-11-4 16*/I2" PIPE TO SWEEP 50% see note 3 P
100 %
1 BRANCH SWEEP l
57 B33 GIO-Al-J RR-11-4 16*/12" PIPE TO SWEEP 50% see note 3 P
100 %
1 BRANCH SWEEP f
f 58 B33 G10-Al-K RR-ll-4 16"/12" PIPETO SWEEP 50% see note 3 P
100 %
I BRANCH SWEEP i
59 B33 GIO-Al-L RR-11-4 16*/12" PIPETO SWEEP 50% see note 3 P
100 %
1 BRANCH SWEEP i
60 B33 G00lW4 RR-I I-2 24" VALVE TO PIPE 50% see note l T
100 %
1 CRC VALVE
[
61 B33 G001W9 RR-11-3 24" PIPETO VALVE 50% see note I T
100 %
I CIRC VALVE 62 B33 G00lW10 RR-11-3 24*
VALVE TO PIPE 50% see note i T
100 %
I CIRC VALVE f
i 63 B33 G6-Al-C RR-11-2 4*/24*
PIPE TO SWEEP 50% see note I T
100 %
1 BRANCH SWEEP 64 B33 G5-Al-E RR-il-2 4*/24" PIPE TO SWEEP 50% see note i T
100 %
I BRANCH SWEEP 65 B33 GS-Al-B RR-11-2 4"/24*
PIPE TO SWEEP 50% see note 1 T
100 %
I BRANCH SWEEP l
66 B21 G11-DI C MS-11-11 28*/10" PIPE TO SWEEP 57 %
T 97 %
I BRANCH liANGER
[
67 B21 GIO-BI C MS-11 5 28"/10" PIPE TO SWEEP 71 %
T 100 %
1 BRANCH llANGER l
68 B21 Glo-BI-E MS-I l-5 28"/10" PIPE 10 SWEEP 71 %
T 85 %
I BRANCII IIANGER 69 B21 GIO-BI-F MS-11-5 28"/10" PIPETO SWEEP 78%
T 100 %
I BRANCH HANGER 70 B21 GIO-BI-H MS-11-5 28"/10" PIPE TO SWEEP 78 %
T 100 %
I BRANCH HANGER 71 B21 G10-BI O MS-11 5 28*/10" PIPETO SWEEP 78 %
T 100 %
I BRANCH HANGER 72 E51 0004Wl8 RI-8-21 6'
VALVE TO PIPE 83.18 %
T 100 %
2 CRC PIPE RESTRAINT l
73 G33 0012W54 CU-il-13 6"
VALVE TO ELBOW 85.59 %
T 100 %
1 CIRC ELBOW RADIUS 74 B21 G001W5 MS-l1-9 28" VALVETO PIPE 62.8%
T 100 %
1 CIRC VALVE I
75 B21 G00lW10 MS-I I-12 28" VALVE TO PIPE 80.8 %
T 100 %
1 CIRC VALVE-f 3
76 B33 G00lW3 RR-11-1 24" ELBOW TO VALVE 30.0 %
T 100 %
1 CIRC VALVE 77 B33 G00lW26 RR-il-8 24" ELBOW TO VALVE 50.0 %
T 100 %
1 CIRC VALVE I
78 B33 G3*Al-F,G H I RR-11-1 24" LUGS TO PIPE N/A N/A 75 %
1 INT ATT PIPE RESlRANT
(
79 B33 G4-BI.H,LK,L RR-11-8 24" LUGSTO PIPE N/A N/A 75%
I INT ATT PIPE RESTRAINT i
80 E32 Gil9W32 IV-8-3 1.5*
TEE TO ELBOW N/A N/A 83 %
I CIRC PIPE SUFPORT I
J 81 E51 G00lW39 RI-il 4 6"
PIPE TO VALVE 79.0 %
T 100 %
I CIRC VALVE
[
lI
- 2..1--...
.--_-,_---___.-,.-_.a_--_,_,._--_-...--_-.--_-_--_-__-
.w,<--
,e me
\\
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS GRkND GULF NUCLEAR STATION i
UNIT 1 RELIEF REQUESTI-00010, REVISION 6 ll TABLEI LEGEND t
P = SCAN PARALLEL TO THE WELD T = SCAN TANGENT (PERPENDICULAR) TO THE WELD NOTES:
1
- 1. In addition to the "T" scan limitation, these welds are augmented by the requirements of NUREG 0313 and therefore are examined with a parallel j
scan that is not required by ASME Section XI. The parallel scan is limited to one side of the weld (50%) due to the fittings being joined by the weld.
2.
100% coverage was obtained in one direction only, using refracted longitudinal wave.
- 3. The "P" scan is performed for compliance with NUREG 0313,100% of ASME Section XI coverage is obtained without limitation.
l i
f 4
- - ~
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIlULMENTS INSERVICEINSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS PAGE 1 OF 1 l i
i l
GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00011, REVISION 2 l
INSERVICE INSPECTION OF THERMAL TEE SLEEVE WELDS DELETED l
l r
4 i
i
1 GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS PAGE 1 OF 2 l GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00012, REVISION 2 l
INSERVICE INSPECTION OF PRESSURE RETAINING WELDS l
l l
I.
Comoonent:
i Inaccessible portion of Class 1 pressure retaining piping weld located on reactor core isolation l
cooling (RCIC, E51). (See Table 1 for details.)
II.
Cads This portion of the pressure retaining piping weld was designed and fabricated to the ASME Section III, Class I requirements.
Applicable inservice inspections are to be performed in accordance with the ASME Section XI,1977 Edition through and including Summer 1979 i
Addenda.
l III.*
Code reouirements-Class 1 pressure retaining piping welds that are required to be volumetrically and surface examined essentially 100% of the weld, once every ten-year interval in accordance with ASME Section XI, Table IWB-2500-1, Category B-J.
r l
1 IV.
Information to suonort the determination that the code reauirements are imoractical:
l A portion oflisted weld that was preservice examined has a physical obstruction due to design.
Due to the limited accessibility, it is impractical to volumetrically examine 100% of the weld listed in Table 1.
l V.
Specific reliefreauested:
Permission is requested to exempt from volumetric examination the inaccessible portions of the Class I weld listed in Table 1.
l l
VI.
Reasons why relief should be aranted:
Request for and exemption should be granted for the following reasons:
1.
The entire listed weld was examined by radiography and passed in accordance with ASME l
Section III, Class 1 requirements.
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS PAGE 2 OF 2 l GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00012, REVISION 2 l
INSERVICE INSPECTION OF PRESSURE RETAINING WELDS 2.
The entire listed weld was surface examined (liquid penetrant) and passed in accordance
. ith ASME Section III and/or XI, Class I requirements.
w 3.
The listed weld was subject to a hydrostatic test and VT-2 examination in accordance with ASME Section XI, Class requirements and no leaks were found.
4.
The listed piping weld will be subject to a system leakage test after each refueling outage for Class 1 in accordance with ASME Section XI requirements.
5.
The listed weld will be subject to pressare testing in accordance with ASME Section XI,.
Table IWB-2500-1 and ASME Section XI Code Case N-498-1.
- 6..
The entire listed weld, including that portion inaccessible for volumetric examination, will be surface examined each inspection interval, in accordance with ASME Section XI.
7.
Accessible portion oflisted weld will be volumetrically examined each inspection interval in accordance with ASME Section XI. Should indications be found, an engineering evaluation will be made to determine if the inaccessible portion oflisted welds has been affected.
8.
Leak detection is provided, by way ofleakage detection system with continuous monitoring for the RCIC system.
9.
The failure of this weld would have no adverse effect on plant safety as there is isolation capability as part of the plant design.
VII.
Alternative testina:
The accessible portion of the weld identified in Table I will be inspected twice by volumetric examination during the ten-year interval.
o GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS l
INSERVICE INSPECTION SECTION 4 l
TEN YEAR PROGRAM RELIEF REQUESTS 3l l
I GRAND GULF NUCLEAR STATION l
UNIT 1 RELIEF REQUEST I-00012, REVISION 2 l
l TABLEI ITEM SYSTEM WELD ISO PIPE LIMITED TYPE REASON FOR NO HQ ILQ R
S]ZE COMPONENT AREA SCAN CLASS LIMITATIONS Om 1
E51 502 RI-I l-7 6"
VALVE TO ELBOW 25 %
T 1
RADIUS OF ELBOW o
O
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS PAGE 1 OF 3 l GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00015, REVISION 2 l
i INSERVICE INSPECTION OF REACTOR PRESSURE VESSEL WELDS I.
Comoonent:
Reactor pressure vessel (RPV) components, welds and associated base material identified in Table 1 of this relief request.
II.
Cads 1
The Unit 1 RPV was designed and fabricated to ASME Section III, Class I requirements.
Applicable inservice inspections are to be performed in accordance with Regulatory Guide 1.150, Revision 1, and ASME Section XI,1977 Edition with Addenda through and including Summer
' 1979. Also, Relief Request No. I-00013 permits the use of ASME Section XI,1983 Edition with the Summer 1983 Addenda, Figure IWB-2500-7(b) for identifying the Code-required examinati6n volume.
9 IIL Code reauirements:
Table IWB-2500-1, Examination Category.B-D, B-A, and B-F, requires specified volumes to be examined volumetrically at specified periods during the ten-year interval. Included in this volume is varying degrees of base material adjacent to each weld that also requires examination.
IV.
Information to sunoort the determination that the code reauirements are imoractical:
Due to geometric configurations of the GGNS Unit I reactor, certain code-required examination volumes, as depicted in ASME Section XI, cannot be examined to the extent of obtaining full code coverage. Table I provides a listing of the affected components and RPV welds with a detailed description of the cause and degree of the limitation.
l Relief Request No. I-00014 provides engineering rational addressing the limitations associated with l
the nozzle to vessel welds. The discussions provided prior operating plant experience to justify that no funher examinations were necessary and additionally this was justified by recognizing that the feedwater nozzles are the limiting case. Although 100% of the code volumes were not examined for the nozzle to vessel welds, sufficient examination coverage was obtained to detect any potential l
cracking.
)
l I
- - ~
~ - - -
f GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS l,
INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS PAGE 2 OF 3 l l
l GRAND GULF NUCLEAR STATION l
UNIT 1 RELIEF REQUEST I-00015 REVISION 2 l
INSERVICE INSPECTION OF REACTOR PRESSURE VESSEL WELDS A study of the welds listed in Table I has shown that these weld locations are also bounded by the feedwater nozzle discussions. The stresses due to any expected loadings and conditions at these locations are bounded by those at the feedwater nozzle locations. Supporting 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 RPV inner surface.
l V.
Soccific relief reauested:
Permission is requeaed to perform ultrasonic examination within the limitations described in Table 1 of this relief request.
VI.
Reasons why relief should be granted:
Relief as described within should be granted for the following reasons:
1.
The entire RPV was subjected to an ASME Section III hydrostatic test after fabrication.
2.
The entire RPV will be subjected to pressure testing in accordance with ASME Section XI, Table IWB-2500-1 and ASME Section XI Code Case N-498-1.
3.
The subject welds were volumetrically examined in accordance with ASME Section III during fabrication.
4.
There is no history of service-induced flaws in these areas of the RPV other than those of the feedwater nozzles discussed in Relied Request No. I-00014.
5.
The areas of the RPV being examined are the limiting areas.
l
1 e
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS PAGE2OF2 GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I 00024, REVISION 0 INSERVICE INSPECTION OF CLASS 1 PUMP AND VALVE INTERNAL SURFACES VI.
Reasons why relief should be eranted:
Alternate examination requirements for Class 1 pumps and valves should be granted for the following reasons:
1.
All components are designed, fabricated, installed, and tested in accordance with the requirements of ASME Section III, Class 1.
2.
The alternate examination requirements eliminate unnecessary man-Rem exposure and man-hours expenditure that provide no compensating increase in quality or safety.
3.
The alternate examination requirements eliminate unnecessary component disassembly that j
would contribute to degrading component life and increase risks associated with potential reassembly errors.
l i
4.
The alternate requirements are in accordance with an edition of ASME Section XI endorsed in 10CFR50.
l VII.
Alternative testina:
l None l
I l
i J
l 1
rl-GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REOUESTS l
PAGE 3 OF 3 l l
GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00015, REVISION 2 l
INSERVICE INSPECTION OF REACTOR PRESSURE VESSEL WELDS l
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 oflimiting analyses results performed for the feedwater nozzle blend radii, that cracking is unlikely at l
Grand Gulf nozzle / vessel weld locations. In fact, even if it was hypothesized that these l
postulated cracks went undetected, a crack length of 58 inches was required before rapid crack growth was to occur during normal operation. It is unlikely that cracks of this size would go undetected. Therefore, a significant leak before break margin exists.
VII.
Alternative testing:
None i
l l
I
GRAND GUI.F NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS Page i of4 l GRAND GULF NUCLEAR STATION UNIT I RELIEF REQUEST I-00015, REVISION 2 l
TABLEI CODE WELD I.D.
CATEGORY ITEM NO.
DESCRIPTION OF EXAMINATION LIMITATION Nozzle N7 B-D B3.100 The N7 nozzle contains 121 'h" diameter holes drilled and tapped 3 %" deep into the nozzle face.
These holes prevent primary ultrasonic waves from reaching the bore region of the nozzle inner radius (see Figure 1).
Nozzle N8 B-D B3.100 Same as the N7 nozzle.
Seams; B-A Bl.22 The RPV bottom head is constructed of four side plates and one center plate which are joined by four DA,DB, welds. Following preservice examinations, a total of 255 holes were bored into the bottom head DC, DD assembly into which the following components were installed: 193 control rod drives, 58 incore tubes,2 NIS drain lines,1 Nil and 1 N18 core differential pressure lines. In addition to these, the RPV skirt is welded approximately 6" below the seam that attaches the shell to the head and an
- insulation bracket is mounted approximately 4" to 6" below the support skirt to bottom head weld that further restricts access to the four welds. The following portions of each weld are accessible for examination: DA - 44.4%, DB - 44.4%, DC - 17.2%, DD - 17.2%.
I
GRAND GULF NUCLEAR STATION
- INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS Page 2 of4 l GRAND GULF NUCLEAR STATION UNIT I RELIEF REQUEST I-00015, REVISION 2 l
TABLE 1 CODE WELD 1.D.
CATEGORY ITEM NO.
DESCRIPTION OF EXAMINATION LIMITATION Scam; B-A Bl.30 The "AE" weld seam joins the no. 4 shell ring to the RPV flange. The physical configuration of the AE flange precludes complete examination coverage of the code-required volume. The code volume is examined with limitations from the shell side only, access from the flange side of the weld is totally progibited (see: Figures 3 & 4). The following provides the details of the volumes examined compared to the code-required volume.
2 Code Volume: 84.35 in 2
Weld Volume. 15.06 in Examination Coverage Obtained:
Code Volume
% Examined Weld Volume
% Examined (in )
(in')
2 0
42.47 50.3 12.58 83.5 45* - T 66.56 78.9 14.04 93.2 60 - T 71.48 84.7 14.09 93.5 45 - P 42.47 50.3 12.58 83.5 60 - P 42.47 50.3 12.58 83.5
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS.
INSERVICE INSPECTION
. SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS Page 3 of4 l.
GRAND GULF NUCLEAR STATION Unit i RELIEF REQUEST l-00015, REVISION 2 l
.TABLEI t
CODE WELD 1.D.
CATEGORY ITEM NO.
DESCRIPTION OF EXAMINATION LIMITATION Nonles; B-D B3.90 The N4 nonles are located on shell ring no. 3,17" from the N13 nonles. The close proximity of the l
N4A,N4C, N13 nozzles limits the automated examination to a "W" dimension of 14" for approximately 44* of the l
N4D,N4F N4 nozzles circumference. This limitati6n prevents the 60 T-Scan from examining all of the required code volume (see Figure 5). Supplemental manual 60* examinations would obtain coverage of the limited area; however, due to the radiation levels encountered at the first refuel outage (3 R/hr) and the fact that the volume not examined by the 60 scan is examined by the 45* T-Scan,45 and 60 P-Scan and the o scan, it is not practical to perform the supplemental examinations.
Nozzles; B-D B3.90 Examination of 4 recirculation ihiet nozzles is limited due to enterferences from the two N9 Jet Pump N2D,N2C, instmment nozzles located approximately 14" from the affected N2's This portion of the circumference that is not accessible to the automated scanner is examined manually, but the 14" N2J, N2K limitation prevents complete coverage with the 60 T-Scan (see Figure 6).
i Nozzles; B-D B3.90 The two N9 nozzles are located between and just below four of the N2 nozzles creating the same N9A,N9B limitations for the N9 nozzles as discussed above for the N2's (see Figure 7).
..m m.
u m
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS Page 4 of 4 l GRAND GULF NUCLEAR STATION UNIT I RELIEF REQUEST l-00015, REVISION 2 l
TABLEI 1
CODE WELD 1.D.
CATEGORY ITEM NO.
DESCRIPTION OF EXAMINATION LIMITATION Nozzle to B-F
.B5.10 Due to the geometric configuration of the nozzle to safe end assembly, full code coverage cannot be safe welds:
obtained from two directions.
Examinations are performed with either shear wave, refracted NI A&B, longitudinal wave, orboth due to the complex bi-and trimatellic structurers of the nozzle to safe end N2A thru assembly. Currently, examinations are performed utilizing automated systems, the coverage of an automated examination is more limiting than that of a manual examination. The coverage report N2N,N4A thru N4F, provided in Figures 14 through 19 indicates the additional coverage that can be obtained in the event NSA&B, future examinations are performed with manual techniques.
N6A,B&C,
~
N9A&B l!
O
P GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS I
~
r i
NOZZLE g
.t BORE REGION 1
~
r R
~
m y SOUND BEAM
<\\
h VESSEL i/
t N7 AND N8 NOZZLE RESTRICTED j
BORE EXAMINATION FI G U R E 1.
SC ALE.4'=LO"
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS I
J l
I
.i i
so-l I
{
l 45*
I l
I J
l SHELL RING 4 I
i l
ff I
T-SC AN FIGURE 3
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS l'
I l'
u____a l
l l
l i
I k
I I
I I
I l
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I I
o,45,60-SHELL RING #4 i -
P-SCAN FIGURE 4.
INSERVICE INSPECTION REQUIREMENTS GRAND GULF NUCLEAR STATION SECTION 4 INSERVICE INSPECTION TEN YEAR PROGRAM RELIEF REQUESTS i
t N13 y
P, t NOZZLE d
N4 NOZZLE j
THIS AREA IS LIMITED TOM"OF 14" APPROX. 44* DUE TO THE LOCATION
_i OF THE N13 NOZZLES l
i4" o
r i
FIGURE 5 SCALE: I /10 PAGE I OF 2
GRAND GUI F NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE ii45PECTION SECTION 4
[
TEN YEAR PROGRAM RELIEF REQUESTS I
i N4 l
NOZZLE LIMITED TO"W"OF 14" FROM APPROX. 44'-
1
't DUE TO LOCATION OF NI3 NOZZLES.
i, e
l Nf3 l[
60 i,
i j
e 45*
] d VESSEL q
I/2T g I
WELD F ! G U R E 5.-
AREA NOT EFFECTIVELY SCALE 1/4 EXAMINED BY 60* T-SCAN PAGE 2 OF 2
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREhENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS I
N ZZLE NOZZLE h
THESE AREAS OF THE EXAMINATION VOLUME
)
WERE SUPPLEMENTED BY A MANUAL EXAMINATION t
g
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f
\\
N s
f
\\
, \\
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/
N2 s
LIMITED SCAN FOR APPROX.40 g
N2 DUE TO LOCATION OF N9 NOZZLE I
LIMITED SCAN FOR APPROX.40' DUE TO LOCATION OF N9 NOZZLE N9 N0ZZLE FIGURE 6 SCALE:l/lO PAGE I,OF 2
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS N
I AREA NOT EFFECTIVELY EXAMINED WITH 60* T-SCAN
( 6.55 SQ.IN.)
N2 LIMITED"w" a
f 1 N9 60* DEG.
/
45'DEG A
~
FIGURE 6.
PAGE 2 OF 2
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,--,---,-----------,----.--.,,n-8 4
GRAND GULF NUCLEAR STATION -
INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEA.R PROGRAM RELIEF REQUESTS l
l N2-NOZZLE N2-NOZZLE Y
+
[
AFFECTED AREA
\\
[
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\\
h'
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FIGURE 7.
SCALE.'l/lO PAGE I OF 2
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GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS GRAND GULF NUCLEAR STATION UNIT 1 l
RELIEF REQUEST NO. I-00015, REVISION 2 l
l l
N1 l
RECIRCULATION OUTLET NOZZLE TO SAFE END WELD LIMITATIONS l
i Q
1 l
l FLOW i
45'SW l
NOZZLE i
SAFE END INCONEL l
BUTTER j
NI Total code volume at a cross-sectional view is 0.95 in'.
Automated techniques utilizing a 45' shear wave obtains two-directional coverage of an area equal 2
to 0.17 in,
l e
Also, a 45' and 60* refracted longitudinal (RL) wave is utilized that obtains one-directional coverage of the entire code volume scanning from the nozzle side.
l 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.
t 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 r.afe end material.
FIGURE 14
-w-------_
7 w?=py-igr y.7.y,.<
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELEF REQUESTS GRAND GULF NUCLEAR STATION UNIT I RELIEF REQUEST NO. I-00015, REVISION 2 l
N2 RECIRCULATION INLET NOZZLE TO SAFE END WELD LIMITATIONS f
I
/
FLOW
=
SAFE END NOZZLE INCONEL BUTTER f INCONEL BUTTER 60*RL
/
745'RL N2 Total code volume at a cross-sectional view is 0.846 in'.
Automated techniques utilized a 45' and 60* RL wave for the examination of the N2F and N2H to obtain co code volume coverage from one direction with both angles.
u The rema' N2 nozzles (A, B, C, D, E, G, J, K, M, N) were examined completely from one e
direction with only the 60* due to excessive noise received with the 45* transducers.
Manual examinations can provide two-directional coverage of the area represented by the cross-2 2
hatching, this would improve total code coverage to 0.271 in or 32% for the 60* and 0.642 in or 75.6% for the 45*.
If the presently available 45* transducers are improved to reduce noise levels, future examinations will include the 45* for. improved coverage.
FIGURE 15
. = -
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS GRAND GULF NUCLEAR STATION UNIT I RELIEF REQUEST NO. I-00015, REVISION 2 l
N4 FEEWATER INLET NOZZLE TO SAFE END WELD l
LIMITATIONS l
l t
l
\\
l SAFE END NOZZLE l
FLOW
=
INCONEL BUTTER INCONEL BUTM l'
'60*RL N45'RL l
N4 t
4 2
Total code volume at a cross-sectional view is 0.70 in,
Automated techniques utilizing a 45* and 60 RL wave obtain'xi coverage of the code volume from o
one direction only (safe end side).
Manual examinations will provide coverage from two directions for the area identified above by the o
2 cross-hatching,0.36 in or 51.4% of the total code volume.
FIGURE 16 l
v GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS GRAND GULF NUCLEAR STATION UNIT I RELIEF REQUEST NO. I-00015, REVISION 2 l
N5 CORE SPRAY TO SAFE END WELD LIMITATIONS l
SAFE END NOZZLE FLOW INCONEL BUTTER
=
MA 60*RL 45*RL N5 SCALE
- 1" = I" 2
i Total code volume at a cross-sectional view is 0.72 in,
Automated techniques provide a 45' shear wave from the safe end side, obtaining two-directional 2
coverage of an area equal to 0.33 in or 46.6% of the total code volume.
r:
Also, a 45' and 60* RL wave examination from the safe end side is performed, obtaining one-IE directional coverage of the total code volume. Area receiving exammation from one direction only is 53.4% of the code volume.
Manual examinations with RL wave will increase two-directional cover by 18%.
FIGURE 17
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELEF REOUESTS GRAND GULF NUCLEAR STATION UNIT 1 RELEF REQUEST NO. I-00015, REVISION 2 l
l N6 RESIDUAL HEAT REMOVAL / LOW PRESSURE CORE INJECTION SAFE END TO NOZZLE WELD LIMITATIONS SAFE-END NOZZLE FLOW l
I N
l l INCONEL BUTTER l
l
- 60*RL
/45'RL l
l N6 1
2 Total code volume at a cross-sectional view is 0.93 in,
Automated techniques provide a 45' shear wave examination from the safe end side, obtaining 2
l two-directional coverage of 0.34 in or 36.6% of the total code volume.
Also,45' aInd 60 RL wave examinations performed from the safe end side obtain one-directional coverage allhe total code volume; area receiving one-directional coverage only is 0.59 in or 2
l 63.4% of tfie code volume.
2 Manual examinations will increase two-directional coverage by 9.7% or 0.09 in,
l FIGURE 18 I
T.
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREhENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELEF REQUESTS l
GRAND GULF NUCLEAR STATION l
UNIT 1 RELIEF REQUEST NO. I-00015, REVISION 2 l
l N9 ET PUMP INSTRUhENTATION NOZZLE TO SAFE END WELD l
.w FLOW NOZZLE SAFE-END lNCONEL BUTTER [~
\\ 45*RL N9 i
z Total code volume at a cross-sectional view is 0.29 in,
Automated techniques provide a 45' shear wave examination from the safe end side, obtaining 2
two-directional coverage of 0.10 in or 34.5% of the total code volume.
M8 Also,45*and 60* RL wave examinations performed from the safe end side obtain one-directional 2
coverage of the total code volume; area receiving one-directional coverage ordy is 0.19 in or 65.5% of the total code volume.
2 t 1.
Manual examinations will increase two-directional coverage by 27.5% or 0.08 in,
>1 l
l FIGURE 19 i
I
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREhENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELEF REQUESTS i
PAGE 1 OF 1 l GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00017, REVISION 1 l
PRESSURE TESTING OF CATEGORY CH PRESSURE RETAINING COMPONENTS l
l DELETED l
l t
i l
i l
l l
)
i 1
l L
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREhENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS i
Page 1 of 4 l GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00018, REVISION 2 l
PRESSURE TESTING i
OF CATEGORY B-P PRESSURE RETAINING COMPONENTS l
I.
Comoonent:
Class I pressure retaining components, Examination Category B-P (see table 1).
II.
Cads The pressure retaining components within this category are designed and fabricated to AShE Section III, class I requirements. Applicable inservice inspections are performed in accordance with AShE Section XI,1977 Edition through and including the Summer 1979 Addenda.
III.
Code Reauirements:
Class 1 pressure retaining components, category B-P, are required to receive a system leakage test (IWB-5221) each refueling outage, and a system hydrostatic test (IWB-5222) or a leakage test (ASME Code Case N-498-1) each inspection interval.
IV Information to succort the determination that the code reauirements are imoractical:
AShE Section XI,1977 Edition, Summer 1979 Addenda, Table IWB-2500-1, category B-P, note 1, requires the test boundary for both the system leakage and the hydrostatic test to include the entire reactor coolant system. This boundary, as defmed, requires poruons of piping to be pressure tested that are isolated by normally closed valves. To accomplish testing of the isolated piping, extensive efforts are required that may include the installation of mechanical jumpers, initiation of false signals to open valves or the erection of independent water and pressure sources. Later editions of ASME Section XI have redefined the test boundary for the system leakage test.
Note 1 ofIWB-2500-1, Category B-P has been revised to address only the system leakage test and to redefine the test boundary as:
'The pressure retaining boundary during the system leakage test shall correspond to the reactor j
coolant system, with all valves in the normal position, which is required for normal reactor l
operation startup. The VT-2 examination shall, however, extend to and include the second closed
(
valve at the boundary extremity."
l l
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS l
INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS Page 2 of 4 l GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00018, REVISION 2 l
PRESSURE TESTING OF CATEGORY B-P PRESSURE RETAINING COMPONENTS l
V.
Soecific Relief Reauested:
With the use of ASME Section XI Code Case N-498-1, there are two distinct leakage tests. The system leakage test performed at each refuel outage (Category B-P. Items B15.50, B15.60,'and i
l B15.70), and the system leakage test (Code Case N-498-1) performed as an alternative to the hydrostatic test performed at the end of the interval.
For those system leakage tests performed at each refuel outage, permission is requested to establish the Class I pressure test boundary to the requirements of ASME Section XI,1983 Edition, Summer 1983 Addenda, Table IWB-2500-1, Category B-P, Note 1.
System leakage tests performed to the requirements of Code Case N-498-1 as an alternate to the interval hydrostatic test l
will be performed using the test boundaries as described by the Code Case. Table I lists the portions o~f systems that are examined by the VT-2 method, but excluded from pressurization during the refuel outage system leakage test.
VI.
Reasons why relief should be eranted:
Request for altering the Class I refuel outage system leakage test pressurizati.on boundaries should l be granted for the following reasons:
1.
All components excluded from pressurization during the system leakage test are designed, l fabricated, installed and tested to the requirements of ASME Section III, Subsection NB (Class 1).
l 2.
The components excluded from pressurization during the refueling outage system leakage test are subjected to pressurization during the interval system leakage test with hold times meeting those required for a hydrostatic test.
i 3.
DELETED l
4.
This request for relief, if approved, would be consistent with the current NRC approved i
edition of ASME Section XI(1983 Edition, Summer 1983 Addenda).
VII.
Alternate Testina:
None l
\\
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS 3 of 4 GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00018, REVISION 2 l
PRESSURE TESTING
)
OF CATEGORY B-P PRESSURE RETAINING COMPONENTS TABLE._1 l
IHM SYSTEM LINE CLASS DESCRIPTION l
1 B21 1" DBA-87 LINE DOWNSTREAM OF QIB21-F136B 2
B21 1" DBA-87 LINE DOWNSTREAM OF QIB21-F136A 3
B33 2" DCA-24 LINE DOWNSTREAM OF QIB33-F051 A 4
B33 2" DBA-42 LINE DOWNSTREAM OF QlB33-F029 5
B33 2" DCA-24 LINE DOWNSTREAM OF QlB33-F051B 6
C41 1 1/2" DCA-3 LINE D,0WNSTREAM OF QlC41-F219 i
7 C41 3/4" DCA-33 LINE DOWNSTREAM OF QlC41-F219 8
C41 1" DCA-31 LINE DOWNSTREAM OF QlC41-F210
~
'9' C41 1 1/2" DCA-2 LINE UPSTREAM OF QlC41-F222 10 C41 1" DCA-34 LINE UPSTREAM OF QlC41-F222 j
11 C41 3/4" DCA-4 LINE UPSTREAM OF QlC41-F222 12 C41 1" DCA-34 LINE DOWNSTREAM OF QIC41-F218 13 C41 3/4" DCA-4 LINE DOWNSTREAM OF QlC41-F026 14 E12 6" DBA-32 LINE UPSTREAM OF QlE51-F066 15 E12 1" DBA-80 LINE UPSTREAM OF QIE51-F066 16 E12 1" DB A-80 LINE DOWNSTREAM OF QlE12-F344 17 E12 14" DB A-28 LINE UPSTREAM OF QlE12-F041B 18 E12 1" DBA-81 LINE UPSTREAM OF QIE12-F041B 19 E12 1" DBA-81 LINE DOWNSTREAM OF QIE12-F236 20 E12 20" DBA-64 LINE DOWNSTREAM OF QlE12-F009 21 E12 14" DB A-29 LINE UPSTREAM OF QIE12-F041 A 22 E12 1" DBA-4 LINE DOWNSTREAM OF QlE12-F223 23 E12 12" DBA-38 LINE UPSTREAM OF QlE12-F041C 24 E12 1" DBA-79 LINE UPSTREAM OF QlE12-F041C l
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS 4 of 4 GRAND GULF NUCLEAR STATION UNIT 1 l
j RELIEF REQUEST I-00018, REVISION 2 j.
PRESSURE TESTING OF CATEGORY B-P PRESSURE RETAINING COMPONENTS T6BLE1 l
lIEM SYSTEM LINE CLASS DESCRIPTION 25 E12 1" DBA-79 LINE DOWNSTREAM OF QlE12-F234 26 E21 14" DBA-1 LINE UPSTREAM OF QIE21-F006 27 E21 1" DBA-31 LINE UPSTREAM OF QIE21-F006 28 E21 1" DB A-31 LINE DOWNSTREAM OF QlE21-F207 29 E22 12" DBA-5 LINE DOWNSTREAM OF QlE22-F005 30 E22 14" DBA-5 LINE UPSTREAM OF QlE22-F005 l
31 E22 1" DBA-78 LINE UPSTREAM OF QlE22-F005
~
l 32 E22 1" DBA-78 LINE DOWNSTREAM OF QlE22-F218
'33 E38 1 1/2" DBA-87 LINE UPSTREAM OF QlE38-F002A l
34 E38 1 1/2" DBA-87 LINE UPSTREAM OF QlE38-F002B 35 E51 10" DBA-24 LINE DOWNSTREAM OF QlE51-F063 36 ESI 1" DBA-34 LINE DOWNSTREAM OF QlE51-F076 l
37 G33 6" DBA-86 LINE DOWNSTREAM OF Q1G33-F250 38 G33 1" DBA-86 LINE DOWNSTREAM OF QlG33-F241 39 G33 3/4" DBA-82 LINE DOWNSTREAM OF QIG33-F002 l
l l
l I
i 1
l
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIRENENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS PAGE 1 OF 5 l GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00019, REVISION 1 l
INSERVICE EXAMINATION OF REACTOR PRESSURE VESSEL ITEMS l
I.
Comoonent:
Inaccessible ponions of the Reactor Pressure Vessel (RPV) as listed below.
1.
Jet Pump Instrument Nozzles (N9 A&B), safe end to penetration seal welds (see Figure 1).
2.
RPV flange stud hole ligament areas (see Figure 2).
II.
Qdr 1.
The Jet Pump Instrument Nozzle assemblies were designed and fabricated to ASME Section III, Class I requirements. Applicable inservice inspections are to be performed in accordance wi.th the ASME Section XI,1977 Edition through and including the Summer 1979 Addenda, Table IWB-2500, Category B-J.
2.
The RPV flange assembly is designed and fabricated to ASME Section III, Class I requirements. Applicable inservice inspections are to be performed in accordance with the ASME Section XI,1977 Edition through and including the Summer 1979 Addenda, Table IWB-2500, Category B-G-1.
III.
Code reauirements:
1.
ASME Section XI, Table IWB-2500, Category B-J, requires the safe end to penetration seal weld to be volumetrically and surface examined. The examinations are to be performed once each inspection interval.
2.
ASME Section XI, Table IWB-2500, Category B-G-1, requires the threads in the RPV flange stud hole, and one inch of base material around the stud hole, to be volumetrically i
examined for a depth equal to the diameter of the stud. The examinations are to be performed once each inspection interval.
1
I GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREhENTS INSERVICE INSPECTION SECTION 4 TEN YELDROGRAM RELIEF REQUESTS PAGE 2 OF 5 l L
GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00019, REVISION 1 l
INSERVICE EXAMINATION OF REACTOR PRESSURE VESSEL ITEMS IV.
Information to suonort the determination that the code reauirements are imoractical:
1.
The welds requiring relief attach the penetration seal to the safe end. The penetration seal is a forged item allowing 14 socket-welded connections for each of the two N9 nozzles. The configuration of the penetration seal and the installing weld limits the access required for obtaining full code coverage of the weld and associated base material.
The weld is volumetrically examined from the safe end, obtaining 44.7% coverage of the code volume. Examination from the weld and from the penetration seal side of the weld is prohibited due to component configuration and weld geometry (see Figure 1).
2.
The area of the RPV flange requiring reliefis located between the stud hole and the RPV inside diameter (ligament area). The ligament area also contains the sealing surface that makes contact with the RPV head flange. The seal surface is comprised of deposited weld l
material, and raised approximately %" above the flange face creating a geometrical obstruction.
A code volume of 96% is volumetrically examined without interference with the seal surface. The remaining 4% is contained within the restricted area associated with the seal surface (see Figure 2).
V.
Soecific relief reauested:
Permission is requested to perform the code-required volumetric examinations to the extent described above and shown in Figures I and 2.
l l
I
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS 1
INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS I
PAGE 3 OF 5 l GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00019, REVISION 1 l
l INSERVICE EXAMINATION OF REACTOR PRESSURE VESSEL ITEMS l
VI.
Reasons why relief should be granted:
I Request for permission to limit the code-required examination to the accessible areas should be j
granted for the following reasons:
l l.
N9 NOZZLE TO PENETRATION SEAL a.
The subject welds were installed, radiographed, surface examined, and hydrostatically tested to the requirements of ASME Section III, Class 1.
l b.
The subject welds are completely surface examined during inservice activities once each inspection interval.
c.
The welds are subject to a pressare test in accordance with ASME Section XI, Table IWB-2500-1, and ASME Section XI Code Case N-498-1.
i d.
The safe end material is SA 336-F8 (304) stainless steel, and the penetration seal is l
304L stainless steel. Due to the geometric configuration of the weld joint, the examination can only be conducted from the safe end side of thejoint, and therefore, l
does not obtain full coverage. The examination is able to obtain 44.7% of the code-l required volume. The examineable area includes the inside surface of the safe end l
(304 stainless steel material) including the heat-affected zone.
The primary degradation mechanism at this location is intergranular stress corrosion cracking (IGSCC). Fatigue is not a significant factor due to the limited fatigue l
loading at this location. Therefore, the potential for cracking at this location should consider IGSCC only. The occurrence of IGSCC is caused by the simultaneous l
presence of three factors:
1) high stress, 2) aggressive environment, and i
3) susceptible material.
l l
l GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS PAGE 4 0F 5 l l
GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00019. REVISION 1 l
INSERVICE EXAMINATION OF REACTOR PRESSURE VESSEL ITEMS The safe end and penetration seal side of the weld both see essentially the same stress and environmental conditions. However, there is a significant difference in material susceptibility between the 304 SS safe end and the 304L penetration seal.
Generic Letter 88-01, NUREG 0313, Revision 2, recognizes 304L type materials as being IGSCC resistant. The 304 portion of the assembly including that side of the i
weld root is examined from one direction utilizing IGSCC techniques and qualified personnel. In addition, Generic Letter 88-01 excludes all piping smaller than 4" in i
nominal diameter. The N9 A&B safe ends are less than 4" in nominal diameter; therefore, under the rules of the generic letter, the safe ends are not susceptible to IGSCC.
- e. -
The accessible portions of the subject welds will be volumetrically examined and the complete weld and adjacent base material will be surface examined in accoidance with ASME Section XI. Should indications be found, an engineering evaluation will be made to determine if the inaccessible portions of the subject welds have been affected.
f.
Any leakage occurring from the N9 nozzles would be detected by the existing leakage detection system.
g.
Mechanical preparation of the weld would allow additional coverage to be obtained by facilitating transducer placement on top of the weld. The efforts necessary for obtaining the improved coverage would require a man rem expenditure of approximately 21.2 whole body and 37.2 for the extremities. The total man rem exposure required to obtain the additional examination coverage is not justified based on the low probability ofIGSCC occurrence and the limited fatigue loading at the subject welds.
h.
Examination history at GGNS has not recorded any flaws or evidence of service induced degradation in category B-J welds.
i.
The limited examination of the two N9 nozzles (A&B) is considered to be sufficient to determine the structural integrity of welded assemblies.
l
i GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4
~
TEN YEAR PROGRAM RELIEF REQUESTS PAGE 5 OF 5 l GRAND GULF NUCLEAR STATION i
i UNIT 1 l
RELIEF REQUEST I-00019, REVISION 1 l
INSERVICE EXAMINATION OF REACTOR PRESSURE VESSEL ITEMS 2.
a.
The RPV flange was fabricated as part of the RPV assembly and tested to the 1
requirements of ASME Section III, Class 1.
l b.
The RPV, inciuding the flange assembly, is subject to a pressure test in accordance with ASME Section XI, Table IWB-2500-1, and ASME Section XI Code Case N-498-1.
c.
The entire code volume around the stud, hole is examined except for the area associated with the sealing surface. This area is examined for a distance of %" from the stud hole before interference from the seal surface is encountered. With the RPV head in place and fastened with the studs to the.RPV shell flange, the seal surface and underlying material is subjected to compressional loads. The material in the vicinity of the threads or adjacent to the stud hole is subjected to sheer loading with the head in place. Therefore, the limiting location with respect to applied stress is the material nearest the stud hole threads. Since this limited area is examined, any anticipated flaw initiation will be detected.
d.
The amount of obtained volumetric coverage that includes the bounded area is adequate to ensure structural integrity of the stud hole regions of the RPV flange.
VII.
Alternative testing:
None l
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS l
N9 A S B SAFE END TO PENETRATION SEAL 44.7% EXAMINED IN ONE DIRECTION HUMP AT ( OF WELD PREVENTS SCANNING COMPLETELY ACROSS WELD MACHINED EDGE
.68" 10' SLOPE
/
PENETRATION SEAL SAFE END F
I V
[
l 2
[,[,',] CODE VOLUME FOR VOLUMETRIC EX AMINATION =.2281N o
4
((/2 EX AMINABLE VOLUME FOR VOLUMETRIC EXAMIN ATION.i02 IN or 44.7 %
FIGURE I
..d
INSERVICE INSPECTION REQUIREMENTS GRAND GULF NUCLEAR STATION INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS CODE EXAMIN ATION VOLUME FOR 360*
OF STUD x\\
RPV CLOSURE STUD 5
2 STAINLESS STEEL n
I VESSEL I D OVERLAY WELD METAL d
c SEALING SURFACE fg o[ ((j-
" I 5)
SEALING p
SURFACE
{
f@, '
r
?
?
5
.5"
)
l" CODE EXAMINATION VOLUME g
{
RP V STU D If
/
\\
RPV FLANGE TOP VIEW OF SHELL FLANGE FIGURE 2 CROSS SECTION VIEW OF RPV FLANGE UNABLE TO SCAN FULL I"QRCLE AROUND STUD HOLE
GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREhENTS J
INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELEF REQUESTS PAGE 1 OF 2 GRAND GULF NUCLEAR STATION UNIT 1 RELEF REQUEST I-00024, REVISION 0 INSERVICE INSPECTION OF CLASS 1 PUMP AND VALVE INTERNAL SURFACES I.
Component:
Class I pumps and valves, examination Category B-L-2 and B-M-2.
II.
C.qde:
The pumps and valves addressed by these examination categories are designed and fabricated asSection III, Class I pressure retaining components.
III.
Code reauirements:
AShE Section XI,1977 Edition through the Summer 1979 Addenda, IWB-2500 requires examination of the internal surfaces of one pump and one valve from each group of pumps / valves performing similar functions in the system.
IV.
Information to suooort the determination that the code reauirements are imoractical:
Affected compoaents have shown good reliability in service. Significant man-hours are required to perform disassembly of pumps / valves.
Additionally the expenditure of man-Rem is high.
Disassembly of pumps and valves solely for the purpose of visual examination is inconsistent with ALARA concerns and poses an excessive burden with no compensating increase in quality or safety. Later editions of ASME Section XI incorporate provisions requiring examination only if components are disassembled for maintenance, repair, or volumetric examination. These Code j
requirements are contained in Code Year and addenda that have been endorsed for use in 10CFR50.
V.
Specific relief reauested:
Permission is requested to allow performance of pump / valve internal examination in accordance with the requirements of Table IWB-2500-1, Examination Categories B-L-2 and B-M-2 contained in the 1989 Edition of the AShE Code. Note 2 to this table states: " Examination is required only when a pump or valve is disassembled for maintenance, repair, or volumetric examination.
Examination of the intemal pressure boundary shall be performed to the extent practicable.
Examination is required only once during the inspection interval."
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