ML20117F761
| ML20117F761 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 05/09/1985 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Butler W Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8505130314 | |
| Download: ML20117F761 (2) | |
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Pubfic Service Electnc and Gas Company 80 Park Plaza, !# war k, NJ 07101/ 201430-8217 MAILING ADDRESS / P.O. Box 570, Newark, NJ 07101 Robert L. Mitti = General Manager Nuclear Assurance and Regulation L
May 9, 1985 f
Director of Nucl' ear Reactor Regulation L
U.S. Nuclear Re'gulatory Commission 7920 Norfolk Avenue.
Bethesda, MD 20814 l
Attention:
Mr. Walter Butler, Chief Licensing Branch 2 Division of Licensing g
Gentlemen:
CODE CASE N-411 AND ASME SECTION III; REOUEST FOR APPLICATIONS TO PIPING SYSTEMS HOPE CREEK GENERATING STATION DOCKET NO. 50-354 Public Service Electric and Gas Company requests approval to apply Code Case N-411 to the Hope Creek piping as-built reconciliation.
By applying Code Case N-411 for damping, revisions to the piping systems that could ultimately produce stiffer piping systems and overly conservative pipe support loads, will be minimized.
s The Hope Creek initial design did not utilize this code case.
Code Case N-411 will not be invoked unless allowable stress limits or excessive pipe support loads resulting from the Hope Creek as-built reconciliation are encountered.
If applied, N-411 will be utilized on an entire piping stress calculation.
i At the completion of the Hope Creek reconciliation effort, a list of systems where Code Case N-411 has been applied will be available.
I Consistent with the use of the above code case, we request tolapply selected portions of the 1981 Winter Addenda to ASME III for piping stress analysis and portions of the 1983 I
P.dition of ASME III for pipe support evaluations.
Utiliza-
' tion of these later codes will allow higher allowable stresses and possibly preclude modifications to the piping system and/or supports'.
As with Code Case N-411, this later code will.only be utilized on calculations that require modifications due to application of the code of record.
The use of these codes will apply to an entire calculation.
The r
specific paragraphs requented for use are:
' 8505130314 850509 The Energy Peopk)
PDR ADOCK 05000354 p
PDR 95 4912 (4W 7 M 1
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Director.of Nuclear Reactor Regulation-2 5/9/85 f
Pipe. Stress Analysis; 1981 Winter Addenda to ASME III, Subsection NC/ND-3652, 3653, 3654, ~ and 3655.
Pipe. Support Evaluations; 1983 Edition of ASME III, Subsections NF-3226, 3256, 3266, 3300, 3426, 3456, 3526, 3556, 3626, 3656, and tables NF-3623(b)-1, 3622(b)-1, 3652(b)-1, 3522(b)-1, 3523(b)-1, 3552(b)-1.
Should you have any questions in this regard, do not hesitate to contact.us.
N.-:
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Very truly yours, k
L
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C' D.
H. Wagner a;
USNRC Licensing Project Manager
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A.' R.
Blough USNRC. Senior Resident Inspector ft
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