ML20079D357
| ML20079D357 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf |
| Issue date: | 07/03/1991 |
| From: | Cottle W ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GNRO-91-00113, GNRO-91-113, NUDOCS 9107110252 | |
| Download: ML20079D357 (13) | |
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~===~ ENTERGY W. T. Cottle July 3,199' U.S. Nuclear Regulatory Commission Mail Station F1-137 Washington, D.C.
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Attention:
Document Cr rol Desk Subjects Grand Gu!
ucicar Station Unit 1 Docket No. 50-416 License No. NPF-29 ASME Section XI Relief Request Number 1-00009 Revision 2 GNRO-91/00113 Gentlemen This.:ubmittal requests relief from the requirements of ASME Section XI, in accordance with 10CFR50.55a(g)(5)(iv) and 10CFR50.55c(g)(6)(1).
A revision to the previously approved relief request is attached.
4 Relief Request I-00009 Revision 2 addresses three welds that have been deleted. These welds are in 3/4" ccmponent connections.
It has been determined that these welds sre exempt from inservice inspection under provisions of ASME Section XI, subparagraph IWC-1220 (c).
Deletion of these welds reduces the percentage of accessible welds requiring surface examination to 82% (from 87%).
Certain welds were also added.
These welds were included in Relief Request 1-00009. Revision 0 and relief from examination was granted by the NRC.
The welds were inadvertently omitted from Revision 1 of the relief request.
Relief from examination is still required.
Section VI, Item 7 of the relief request is revised to delete specific reference to frequency of testing.
It was not the intent of the relief request to define a test frequency. Technical Specifications specify the frequency of tests required to assure systa cparsbility.
Deletion of test frequency does not change the basis for relief.
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I ' July 3, 1991 GNRO-91/00113 Page 2.of 3 I Your review and approval of these requests is requested prior to January 1, 1992, in order to allow planning for the upcoming refueling outage, which is scheduled for April 1992. If additional information is required to support your review, pisano adtino. Yours truly, exp r-~ C-- - _. WTC/JE0/mte attachments: 1. Summary of Revision 2 Changes 2. Rollef Roquest Numbrr 1-00009 Revision 2 cc: Mr. D. C. Ilintz (w/o) .Hr. J. L. Mathis (w/a) Mr. R. B. McGohee (w/o) Mr. N. S. Reynolds (w/o) Mr.11. L. Thomas (w/o) Mr. F. W. Titus (w/a) Mr. Stewart D. Ebneter (w/a) Regional Administrator U.S. Nuc1 car Regulatory Commission Region II 101 Harlotta St., N.W., Suite 2900 Atlant.a, Georgia 30323 Mr. L. l.. Kintner, project Manager (w/a) Office of Nucinar Reactor Regulation U.S. Nuclea r Regulatory.Commiasion Hall Stop llD21 Washington, D.C. 20555 G9106263/SNLICFLR-- 2 =. -...
t ' to GNRO-91/00113 Page 1 of 1 l = Summary of Revision 1 Chnngos - Relief Request 1-00009 i '"Inservico inspect.ipn pf.,1l ump _Cas f.pg and.. Attachment Wolds" Rollof Roquest f Revision 2 Change item No. Requestod Reason _for Chango/ Comments 1 E12 RilR pump ll" Delete Itams These itoms are in 3/4" ( welds Dil-11 and-component. connections and aro Dil-12 ; exempt from inservice - E21 hPCS pump inspection under ASHE wnhin Dil-11 and Section XI, subparagraph Dil-12 ; - IWC-1220(c). E22 -liPCS pump Thir. would reduce tho wolds Dil-11 and percentage of accessible wolds l D!l-12. roquiring surfaco oxamination f om 87% to 82%. Section 1Y, l Item 9. Section VI. Dolotn Technical Specifications - i ' Item 7. specify the frequency of tests required to assure system operability. E22 ilPCS pump Add items Those wolds worn included in wolds SB-2 and Revision 0 and relief was 5D-3. granted. Thn wolds worn inadvortently omitted from Revision 1 of the rollof req ues t... Relief from examination is still required. i f G9106263/SNh1CFLR - 4 a wie .r-e e,,m>- .-r w ,s-~~ ,,,,,.~-e,,x--- c,,,7u,,_,ww .w --n,-, ,.-4r.-,w.ae,-,e n. ow,,~e.m,, s-p-rww-.,,
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Roller Roqunst Number 1-00009 Revision 2 "Inse_r,visy1_Inspectjon of _ l' ump _C3 sing and Attachment _ yells" 3 Ppges Following: 5 Pages Rollof Request - Revision 2 -4 Pages Drawlngs - 09106263/SNLICFLRl-5 z.
GRAND GULF NUCLEAR STATION In00rvico IncpOction R0 guiro 2Onto INSERVICE INSPECTION U Cf U TEN YEAR PROGRAM GRAND GULF NUCLEAR STATION UNIT 1 RELIEP REQUEST I-00009, REVISION 2 PAGE 1 OF 5 JflSERVICE INSPECTION OF PUMP CASING AND ATTA0NENT WELQJi 1. Component: Pump casing and attachment welds located within the surrounding concrete pump support encasement for the following pumps (see attached list and sketches): Fjd1E PUMP NO. SKEJCH N01 Residual He:t Removal IE120002B RH-8-12 Low Pressure Core Spray lE210001 LP-9 4 High Pressure Core Spray lE220001 HP-8 10 II. Code: The three pumps listed above were designed and fabricated to the ASME Section 111, class 2 requirements. Applicable Inservice inspection is to be preformed in accordance with ASME Section XI,1977 Edition through and including Summer 1979 Addenda and Code Case N 343. 111. Code Requirements: Pressure retaining welds, and attachment welds that provide a support function are required to 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 support inaccessible pump casing welds are located where the determination that the concrete pump support encasement only allows a the Code requirements 3 inch clearance between the pump casing and the are impractical: concrete encasement wall (see figure 1 for details of the design). Due to the limited accessibility, it is impractical to surface examine those portions of the welds located within the surrounding concrete pump support encasement. The IE120002B and IE210001 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 of the 1/2 inch of base material on each side of the attaching weld (see figure 2). M:\\ MECH \\MUNTER\\ RELIEFS \\RR09R2Tx 009
GRAND GULF NUCLEAR STATION In00rvico InCPOction ROquircmOnto INSERVICE It'SPECTION 8 CfI " TEN YEAR PROGRAM GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00009, REVISION 2 l PAGE 2 OF 5 INSERVICE INSPECTION OF PUMP CASING AND ATTACHMENT WELDS V. Specific relief Permission is requested to exempt from inservice Requested: inspection the inaccessible portions of the pump 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 Request for exemption should be granted for the should be granted: following reasons: 1. The pump casing welds have been volumetrically examined by radiography and passed in accordance with the ASME Section 111, Class 2 requirements. 2. The attachment welds were surface examined and accepted in accordance with the requirements of ASME Section 111, Class 2 requirements. 3. The accessible length of each applicable casing weld will be surface examined in accordance with ASME Class 2 requirements. 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.
6. Annunciators (i.e. low suction pressure, discharge pressure
- abnormal, etc.)
are provided in the control room, along with other system indicators, to alert the operators to abnormal operating conditions. 7. The systems, including the pumps, are tested per the GGNS Operating License Manual (Technical Specifications) requirements to ensure operability. M \\ MECH \\HUW1ER\\ RELIEFS \\RR09R2tx 009
l GRAND GuLr NUCLEAR STATION Incorvico Incp,ction R0guirc20nto Scotion 4 INSERVICE INSPECTION Relief Request TEN YEAR PROGRAM GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00009, REVISION 2 PAGE 3 OF 5 INSERVICE INSPECTION OF PUMP CASING AND ATTACHMENT WELDS VI. Reasons why relief 8. Pumps will be subject to a system pressure should be granted test in accordance with ASME Section XI, (continued): Class 2 requirements. 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 Testing: None Vill. NRC discussion The following statements, conclusions, statement recommendations, etc. have been adopted by the NRC (Revision 1): and are to be considered part of this request-for-relief's approval. Since tne surface examinations can be conducted from either the external or internal surface of the pump casing, an attempt should be made to examine the portions of the casing
- welds, inaccessible on the external
- surface, on an internal surface if the pumps are disassembled for maintenance.
Therefore, relief is recommended as requested provided: (a) The surface examinations are performed to the maximum extent practical, (b) the code-required system pressure tests are performed, and (c) the surface examitiations are completed from the internal surface if a pump is disassembled for maintenance. Mi\\ MECH \\ HUNTER \\RELIEft\\RRD9R2TX.009
GRAND Gutr' NUCLEAR STATION Inecryioo Insp00 tion RGquircasnto INSERVICE-INSPECTION 80ction 4 TEN YEAR PnoGRAM Reliet Request GRAND GULF NUCLEAR STATION UNIT 1 RELIEP REQUEST I-00009, REVISION 2 PAGE 4 OP 5 INSERVICE INSPECTION OF PUMP CASING AND A11Atllti[N1..WELES Vill. NRC discussion NRC additional discussion for revision 1 to the statement (Revision 1, relief request: continued): The staff concludes that the limited surface examination of the support-to casing welds for the residual heat removal sump and the low pressure core spray pump wil' provide the necessary assurance of structural reliability because although 1/2 inch of base metal on each side of the weld cannot be examined, 100% of the weld metal.will be examined. In addition, if the pumps are disassembled for maintenance, surface examinations will be completed from the internal surface. The staff also concludes that compliance with the soccific requirements of Section XI would result in hardship or unusual difficulties without a compensating-increase in the level of quality and safety. Therefore, relief is granted as requested. i L l I-in i [ l M t \\ME CH\\NE,f ER \\REll t f S\\RR09R2TX.009
_. - - ~ _,_ ~ _ -.. - _w GRAND GULF NUCLEAR STATION Incorvico Inspootion Rcquircacnts INSERVICE INSPECTION Scotion 4 TEN YEAR PROGRAM GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST NO. I-00009 REVISION 2 TABLE 1 LIST OF PUMP WELDS PAGE 5 OF 5 E12 - RHR PtMP 'B' C ASING Velds Surfaces That Shall Be framined DH 1 DH-4 DH-7 $B 4 $B-7 DH-2 DH-$ DH 2$ SB $ DH-3 DH-6 SB-3 $B-6 i Velds That Can Be Partially Examined Velds that cannot be examined SB-2(18' accessible.54' inaccessible) $81(inaccessiblo) Attachment welds that can be partially examined $B-12 (see figure 2 for details of limitation) f21 - LPCS PUMP CASING Velds Surfaces That Shall Be Imamined DH 1 DH-4 DH 7 SB-4 SB 7 DH-2 DH-5 DH 27 $B-5 DH DH-6 58-3 SB-6 Welds That Can Be Partially f uamined ' Welds That Cannot Be Examined $82(3' accessible.69' inaccessible) $8-1 (inaccessible)- AttacWnt Velds Thot Can Be Partially Eramined $812(seefigure2forretailsoflimitation) {JP-HPCS PLMP CASING Velds Surfaces That Shall Be Eramined DH-1 DH-4 - DH 7 58 5 DH-2 DH DH-19 58 6 DH-3 DH-6 $H-28 $B ? Velds That Can Be Partially framined Velds That Cannot Be Examined SB-4 (68' accessible, d' inaccessible) SB-1 (inaccessible) SB-2(inaccessible) $b-3 (inaccessible) . Mi\\ MECH \\ HUNTER \\ RELIEF $\\RR09R2fx.009 w m-U v w s n---+r =----s e-r .-----m -e w, e-w.,ww--=--wr..- .E-m,w e =
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GRAND GuLr NUCLEAR STATroN IG C ryi c InspOctica RCquir"COnts INSERVICE INSPECTION 800tica 4 Ten YEAn PaoGRAM Relief Roquest NO. I-00009 FIGURE 2 ] I l BOTTOM OF PUMP COLUMN i< PUMP w BARREL ,d suPeoaf /,. y ATTACHMENT WELD . t e*.[,4$ ) d ,. j;d p gi,4*.V.'.{L' .'.llb..I CONCRETE FLOOM IN BOTTOM y/ OF PUMP SUMP ATTACHMENT WELD LIMITATIONS PUMPS IE12 COO 28 AND tE2lC006 ---n. - - - -}}