ML20134E292
| ML20134E292 | |
| Person / Time | |
|---|---|
| Issue date: | 10/29/1996 |
| From: | Collins T NRC (Affiliation Not Assigned) |
| To: | Sheron B NRC (Affiliation Not Assigned) |
| Shared Package | |
| ML20134E293 | List: |
| References | |
| TAC-M95745, NUDOCS 9611010100 | |
| Download: ML20134E292 (2) | |
Text
. . . . . _ . _ _ _ _ _ _ _ _ . _ _ . . . __ ._- _ _ _ _ . _ _ _ _ _ _ . - . _
October 29, 1996 i
i MEMORANDUM TO: Brian Sheron Acting Associate Director i for Technical Review
- Office of Nuclear Reactor Regulation .
~
THROUGH Gary Holahan. Director Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation ,
,- 4 FROM: Timothy E. Collins. Acting Chief.
Reactor Systems Branch 4 Division of Systems Safety and Analysis )
} Office of Nuclear Reactor Regulation
SUBJECT:
WAIVER OF CRGR REVIEW FOR EMF-96-029(P) 1- (TAC N0. M95745) i
REFERENCES:
Memorandum from E. L. Jordan to T. E. Murley "CRGR i Consideration of Topical Reports." September 29, 1989.
! Attached is the safety evaluation report prepared by the Division of Systems 1
. Safety and Analysis in which the staff acce)ts Topical Report EMF-96-029(P) l for referencing in license applications. T1e staff proposes that the CRGR ,
j review be waived in accordance with the ooggested revised procedures in the l memorandum referenced above. I
]
EMF-96-029(P) describes a revised PWR neutronic code system. SAV-95. This i code system consists of CASMO-3G as the cross section generator and PRISM as l the core simulator. These codes replace the current approved CASMO version '
used as the cross section generator and XTGPWR as the core simulator.
I The CRGR charter states that the CRGR should review each of the staff's approvals of topical re) orts. However, the staff believes that CRGR review is not necessary because t1e methodology is essentially an update of the current ;
code packages used by Siemens and does not represent a new staff position. If you agree that a CRGR review is not necessary, please indicate by signing on the line below. Otherwise. the staff will prepare an appropriate CRGR l package. !
Attachment:
As stated l Brian Sheron DISTRIBUT ION Approved: CRGR review is not necessary. ;CentralIFiles? SRXB R/F PDR LKopp TCollins LKopp R/F
Contact:
L. Kopp. SRXB/DSSA EWeiss GHolahan -
Ext 415-2879
'*See previous concurrence OFFICIAL RECORD COPY Document Name: G:\ EMF 96029 ,
OFC DSSA:SRXB DSSA:SRXB DSSA:SRXB TECH ED D:DSSA d em " DFOS / 6; NAME LK0PP* -EWEIS$* TCOLLINS* NITA*
GMh l DATE 9/26/96 9/28/96 10/19/96 8/22/96 h/geh OFFICIAL RECORD COPY 0 r.0001 p,o r'x 10- M-%9- 2 s
9611010100 961029 6/f h)(IT)
/ -
3 PDR .TOPRP EMVEXXN 2
,C ,; PDR $
p uay y- & UNITED STATES NUCLEAR REGULATORY COMMISSION E
f WASHINGTON. D.C. 20555-0001
% +o October 29, 1996 MEMORANDUM TO: Brian Sheron, Acting Associate Director for Technical Review j Office of Nuclear Reactor Regulation i THROUGH Gary Holahan. Director Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation FROM: Timothy E, Collins. Acting Chief Reactor Systems Branch /
Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation
SUBJECT:
WAIVER OF CRGR REVIEW FOR EMF-96-029(P)
REFERENCES:
Memorandum from E. L. Jordan to T. E. Murley "CRGR Consideration of Topical Reports." September 29., 1989.
Attached is the safety evaluation report prepared by the Division of Systems Safety and Analysis in which the staff acce]ts Topical Report EMF-96-029(P) for referencing in license applications. T1e staff proposes that the CRGR 1 review be waived in accordance with the suggested revised procedures in the ;
memorandum referenced above. !
EMF-96-029(P) describes a revised PWR neutronic code system. SAV-95. This code system consists of CASMO-3G as the cross section generator and PRISM as the core simulator. These codes replace the current approved CASMO version used as the cross section generator and XTGPWR as the core simulator.
The CRGR charter states that the CRGR should review each of the staff's approvals of topical re> orts. However, the staff believes that CRGR review is not necessary because tie methodology is essentially an update of the current j code packages used by Siemens and does not represent a new staff position. If l you agree that a CRGR review is not necessary. please indicate by signing on '
the line below. Otherwise, the staff will prepare an appropriate CRGR j package.
Attachment:
As stated Brian Sheron f4 Approved: CRGR review is not necessary.
Contact:
L. Kopp Ext. 415-2879