ML20113B576
| ML20113B576 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf, Arkansas Nuclear, River Bend, Waterford  |
| Issue date: | 06/20/1996 |
| From: | Hutchinson C ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GNRO-96-00071, GNRO-96-71, NUDOCS 9606270217 | |
| Download: ML20113B576 (5) | |
Text
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Enttrgy Op:rstirnz,Inc.
~- ENTERGY aO so 7se Port Gbson, MS 39150 Tel 60107 2800 C. R. Hutchinson voc Provient ofMa%CS Grana Gtd Ndar Statm June 20, 1996 Document Control Desk U.S.
Nuclear Regulatory Commission Mail Static.. Pl-37 Washington, D.C.
20555
Subject:
Approval of ASME Code Cases N-508-1
" Rotation of Serviced Snubbers and Relief Valves for the Purpose of Testing" Arkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29 River Bend Station Docket No. 50-458 License No. NPF-47 Waterford 3 Steam Electric Station Docket No. 50-382 License No. NPF-38 GNRO-96/00071 Gentlemen:
The purpose of this submittal is to request approval pursuant to 10CFR50. 55a (a) (3), for the use of American Society of Mechanical Engineers (ASME) Code Case N-508-1 as an alternative to existing ASME Section XI Code requirements which are currently in ef fect at all Entergy's nuclear
- stations, i.e.,
Arkansas Nuclear 1 and 2, Grand Gulf, Waterford 3 and River Bend. Approval of this code case will allow its usage in this and future intervals at each respective facility.
1 Code Case N-508-1 is contained in the 1995 Edition of Nuclear Code Cases but has not been included in Regulatory Guide 1.147, " Inservice Inspection j
Code Cases Acceptability - ASME Section XI Division 1."
Currently, snubbers and relief valves that are rotated for the purpose of j
testing are being governed by our Repair / Replacement Programs. Code Case N-4 508-1 provides alternative rules that eliminate the rotation of snubbers and relief valves, for testing purposes, from the scope of each facility's
)
Repair / Replacement Program.
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1 June 20, 1996 GNRO-96/ 00071 Page 2 of 5 l
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This change reduces documentation, evaluations, and personnel review time j
which is typically associated with ASME Section XI Repair / Replacement work activities. The requirements established by this code case are adequate to i
ensure that the rotation of the serviced equipment is appropriately tracked and limited to mechanical removal and installation.
I Aditionally, current plans at Grand Gulf are to utilize the alternatives j
allowed in the subject code case during its upcoming refueling outage in Fall 1996. Approval of this code case will allow its use during the current and upcoming intervals at each respective site.
Approval for the use of this code case is requested by August 31, 1996.
Should you have any questions regarding this request, please contact Riley Ruffin at Grand Gulf Nuclear ctation 601-437-2167.
Yours truly
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CRH/R /
l attachment:
Code Case h 508-1 i
cc:
Mr.
R. B. McGehee (w/a) l Mr.
N.
S. Reynolds (w/a) i l
Mr.
H. L. Thomas (w/o)
Mr.
J.
W. Yelverton (w/a)
Mr. L. J. Callan (w/a)
Regional Administrator l
U.S.
Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 1
Arlington, TX 76011 Mr. J.
N.
Donohew, Project Manager (w/2) l Office of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C.
20555 NRC Senior Resident Inspector (w/a)
Grand Gulf Nuclear Station P. O.
Box 756 Bald Hill Road Port Gibson, MS 39150
June 20, 1996 GNRO-96/ 00071 Page 3 of 5 cc:
NRC Senior Resident Inspector (w/a)
Arkansas Nuclear One 1448 S. R.
333 Russellville, AR 72801 NRC Resident Inspector (w/a)
Waterford 3 Steam Electric Stati 1 Trailer 426 P. O. Box B Killona, LA 70066 NRC Resident Inspector (w/a)
River Bend Station P. O. Box 1051 St. Francisville, LA 70775 Mr. George Kalman, Project Manager (w/a)
Office of Nuclear Reactor Regulation U.
S.
Nuclear Regulatory Commission Region IV/ANO-1 Mail Stop 13H3 Washington, D.C.
20555 Mr. T. W. Alexion, Project Manager (w/a)
Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Region IV/ANO-2 Mail Stop 13H3 Washington, D.C.
20555 Mr. C.
P.
Patel, Project Manager (w/a)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Region IV/W3 Mail Stop 13H3 Washington, D.C.
20555 Mr. David Wiggington, Project Manager (w/a)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission l
Region IV/RB Mail Stop 13H3 Washington, D.C.
20555
June 20, 1996 GNRO-96/ 00071 Page 4 of 5 cc: (cont'd)
Mr. Eugene Inbro (w/a)
CBLA Task Force U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Mail Stop 9Al Washington, D.C.
20555
2 CASE N-508-1 cus orous.on.a.oo==.-m.m. coo.
Approval Date: May 11,1994 See NumericalIndex tbr auparadon and any reeMirmation datoe.
Case N.5081 (b) Items being removed shall have no evidence of Rotation of Servicati Snubbers and Pressure Relief failure at the time of removal; Valva for the Purrese of Testing (c) Items being rotated shall be removed and Sr.: tion XI, Division 1 installed only by M="! means; (4) Items being installed shall prenously have Inquuy What alternative rules to those stated in been in setvice; d
IWA-4000 (IWA-7000 for Editions and Addenda (e) Preservice inetweiana and pressure tests shall J
prior to the 19'61 Addenda) may be used when, for be performed as required by IWA 4000 (IWA-7000 the purpose of testing, snubbers and pressure relief for Editions and Addenda prior to the 1991 Adden-valves are rotated from stock and installed on com-da);
ponents (including piping systems) within the Section XI boundary?
(f) The Owner shall maintain a method of tracking the items to ensure traceability of insernce inspec-tion and testing records; Reply: It is the opinion of the 'ammittee thai, as
. (g) Use of an NIS-2 form is not required except as r
an alternative to the provisions of IWA-4000 (IWA.
provided in (i) below; 7000 for Editions and Addenda prior ta the 1991 (h) Testing of removed snubbers and pressure re-Addenda) and for the purpose of testirg, snubbers lief valves, including 1s93.4 sample expansions, and relief valves may be rotated from stock and in-shall be performed in accordance with the Owner's stalled on components (includmg piping systems) test program; within the Section XI boundary provided the follow-(i) Repair or seylh, t of removed items,when ing requirements are met:
required, shall be y..f=
d in accordance with (a) Items being removed and installed shall be of IWA-4000 (IWA-4000 or IWA-7000 for Editions and the same design and construction; Addenda prior to the 1991 Addenda).
e 983
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