ML20147C703
| ML20147C703 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee, Point Beach, Prairie Island, Ginna, 05000000 |
| Issue date: | 03/01/1988 |
| From: | Di Ianni D, Diianni D Office of Nuclear Reactor Regulation |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8803030139 | |
| Download: ML20147C703 (3) | |
Text
.
y N NAR 1 1988 9 ;ox o
. MEMORANE"i FOR:
Steven A.,Varga, Director Division of Reactor Projects I/II Office of Nuclear Reactor Regulation THRU:
Martin Virgilio, Director Project Directorate III-1 Division of Reactor Projects - III, IV, V
& Special Projects i
Wayne Hodges, Chief Reactor Systems Branch-FROM:
Dominic C. 01 Ianni, Project Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V
& Special Projects
SUBJECT:
MPA 005, UPPER PLENUM INJECTION STATUS
SUMMARY
REPORT
The corrections indicated have been communicated to both the plant specific project manager (s) and plant specific reviewer (s) for proper updating of the data base tracking system.
2.
Recommendations concerning the MPA generic priority (i.e., should it change and why) and should the MPA continue:
(A "none" in this section means the generic' priority is acceptable and the MPA should continue as is.)
None 3.
Item for Senior Management Attention (Only list items which truly require senior management attention to resolve.)
None
%galsi;m, Dominic C. Di Ianni, Project Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V
& Special Projects cc:
Joe Gitter DISTRIBUTION David Wagner DOCKET OR CENTRAL FILE Carl Stahl NRC & LOCAL PDRs l'
P031 READING FILE
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GHOLAHAN PDR p
DIIANNI RINGRAM CONTACT:
D. Di Ianni, NRR 49-21324 See previous concurrence
- SRXB*
PM/P031: DRSP*
C:SRXB*
D/P031: DRSP*
P YHHsii DDilanni:cr MWHodges MVirgilio GHolahan 4
02/22/88 02/22/88 02/22/88 02/24/88 02/g6/88 0FFICIAL RECORD COPY F
MEMORANDUM,FOR:
Steven A. Varga, Director Division of Reactor Projects I/II Office of Nuclear Reactor Regulation THRU:
Martin Virgilio, Director 9,roject Directorate III-1 Division of Reactor Projects - III, IV, V
& Special Projects Wayne \\ odges, Chief H
Reacto'r Systems Branch s
\\
FROM:
Dominic 03 Di Ianni, Project Manager Project Directorate III-1 Division ofxReactor Projects - III, IV, V
& Special Projects N
SUBJECT:
MPA 005, UPPER PLENUM INJECTION STATUS
SUMMARY
REPORT
\\
The corrections indicated has i be'en communicated to both the plant specificprojectmanager(;)and}plantspecificreviewer(s)forproper updating of the data bast track ng system.
2.
Recommendations concerning he MP generic priority (i.e., should it change and why) and should t..
40A continue:
(A "none" in this section means the generic priority
=cceptable and the MPA should continue as is.)
None 3.
Rem for Senior Management Attention (Only l_ist ites ~hich truly require senior management attention to resolve.)
Nons Dominic C. 01 Ianni, Project Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V
& Special Projects cc:
see Gitter David Wagner l
Carl Stahl I
CONTACT-D. Di Ianni, NRR gh
{
gp 49-21324 Rb D/PD31:DRSP AD:DRSP SRXB PM/PD31:DRSP C
YHHsii DDilanni:ct WHodges MVirgilio GHolahan 02/A2/88 02/tA/88 02 $ /88 02/B/88 02/ /88 0FFICIAL RECORD COPY
~
~
SUMMARY
REPORT
~
MPA 005 Upper Plenum Injection for Westinghouse two-loop plants February 1, 1988 1
Westinghouse (W) two-loop plants have a low pressure safety injection system i
(LPSI) which injects water directly into the upper plenum of the reactor vessel (UPI).
However, the approved ECCS evaluation models for two-loop plants are based on an ECCS system in which safety injection flow is injected directly into the cold leg of the reactor system.
Because of the difference in the water injection between ECCS evaluation models and the actual UPI in the reactor vessels, the requirement of 10 CFR Appendix K Section II 5 may not be met.
Six plants owned by four utilities are affected.
These plants are j
presently operating on the basis of a number of interim approaches for determining allowable peaking factors.
The Westinghouse Owners Group consisting of Northern States Power Company and Wisconsin Electric Company i
submitted a best estimate ECCS evaluation model using the SECY 83-472 approach to analyze the UPI for Prairie Island Nuclear Generation Plant and Point Beach I!uclear Generating station.
The other plants (i.e. RE Ginna and Kewaunee) will be analyzed with a best estimate ECCS evaluation model developed by the Combustion Engineering (CE) Owners Group (Rochester Gas Electric and Wisconsin Public Service Corporation).
j Status a
(A) Prairie Island / Point Beach 1
The staff review for the generic model is scheduled for completion on
]
(both Prairie Island & Point Beach) August 15, 1988 and plant specific analyses should be completed on January 15, 1989.
(B) RE Ginna/Kewaunee l
A preliminary review of the CE evaluation model by the staff indicates i
the model is deficient in several areas that will require further work.
Because of these anomalies, a realistic schedule cannot be determined without further negotiation with CE Owners Group.
There is a single reviewer assigned for the Westinghouse and CE evaluation models in which effort is being devoted in series.
Currently, the major effort is beir placed on the review of the Westinghouse evaluation model.
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