ML18085A329
| ML18085A329 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/17/1980 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Mittl R Public Service Enterprise Group |
| References | |
| NUDOCS 8012040156 | |
| Download: ML18085A329 (2) | |
Text
NOV I 7 1980 -
Docket No. 50-311 Mr. -R. L. Mittl, General.Manager -
Licensing and Environment Engineering and Construction Department Public Service Electric and Gas Company 80 Park Plaza, Tl7A Newark, Mew Jersey 07101
Dear Mr. Mitt1:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON SALEM, UNIT 2 -
CONTAINMENT BOUNDARY FRACTURE TOUGHNESS As a result-of our continuing review of Salem"2 for a full power license, we find that we need additional information to complete our evaluation. This information is needed to assess the degree cif compliance of Salem 2 with GDC 51, "Fracture Prevention of Containment-Pressure Boundary".
To demonstrate compliance with GOC.51,-you are-requested to provide fracture toughness data for the A 106 Grade C piping used in the steam generator feedwater system from the connection to the process pipe of feedwater penetrations of pipe lihe numbets 5, 6, 7, 8 (PSEG Dwg. 207496 A*BB08~7) and the stop-check isolation
- valves. These data must confirni that at the lowest service temperature of the piping, 60 -F, the material meets either the Charpy V notch lateral expansion criterion or the nil ductility transitiort temperature criterion contained in the Summer 1977-Addenda, ASME Code Section III for Class 2 components.
These data must. be derived from pipe material fn the same metallurgical condition and fr0m the 'Same heat and comparable wall thickness as the installed pipe.
Shou-ld these fr-acture toughness data be unavailable, or if they do not meet the criteria specified by the Summer 1977 Addenda, ASME Code Section III for Cl ass 2 components, _you are requested to either: 1 ) show through ana 1 ys is or materials tests that the integrity of the containment boundary with respect to brittle fracture and rapidly* propagating fracture will be maintained for the normal operating, maintenance, testing, and postulated accident conditions as demanded by GDC 51; or 2) request ah exemption from GDC 51 and provide the
- justification for this exemption.
If you have any questions on this request, please do not hesitate to contact us.
Sinc.erely,_
'fy.,v.~ Is/
Robert L. Tedesco, A'ss i st ant Director for Licensing
..4-J}_
Division of Licensing
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NRC FORM 3-18 (S.*7*i' "-;;..ic~.-; *JZ-;-0 1ENT PRINTiNG OFFICE: 1979-289-369
cc:
Richard Fryling, Jr., Esq.
Assistant General Counsel f'ublic Service Electric & Gas Compa11y 80 Park Place Newark, New Jersey 07100
~ark Wetterhahn, Esq.
Conner, Moore & Cober Suite 1050 1747 Pennsylvania Avenue, N. W.
lfashington, O. C.
20006 Mr. Leif J. Norrholm c/o U. S. Nuclear Regulatory Cc1:.'11ission Drav,*er I Hancocks Bridge, New Jersey 08038