ML20040A166
| ML20040A166 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 03/24/1975 |
| From: | Desiree Davis Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201200441 | |
| Download: ML20040A166 (5) | |
Text
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e UNITED STATES NUCLEAR REGULATORY COMMISSION f
W ASHING TON, D.
C. 20555
- M 2 4 WS Project No. 566 VENNR: BABC0CK & WILCOX COMPANY (B&W)
PLANT : B-SAR-205 PREAPPLICATION MEETING ON B-SAR-205 On March 20, 1975, members of the NRC staff met with representatives from B&W to discuss the future submission of a standard safety analysis report on the B-SAR-205 plant. A list of attendees is attached.
Significant points discussed are summarized below:
1.
Source Term B&W indicated that they planned to include a description of the analytical methods used to compute primary system activity levels and the results for 1% failed fuel in B-SAR-205.
Since previous B&W customers requested
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source terms for their individual plants, B&W asked for guidance in what to present in B-SAR-205 for normal operational releases (Appendix I).
The staff indicated that a bounding case for different plant operational modes and fuel cycles or several alternatives for various modes and cycles would be acceptable. However, the alternatives should be kept to a minicum.
2.
Comparison of B-SAR-205 NSS Parameters B&W presented a hand out comparing the B-SAR-205 plant with their standard 205 fuel assembly design plant such as Bellefonte. A copy of this hand out is attached.
Basically, there are no hard ware difference. The increased RC flow is anticipated as a result of previously oventesign.
The OTSG superheat has been reduced slightly with a corresponding reduction in p' ant heat rate. B&W will perform the accident analysis at 3800 MWt plus 2% per Regulatory Guide 1.52.
3.
NSSS Definition B&W requested clarification of several items in Amendment 1 to WAsil-1341 and stated that their current plants were to comply with that document.
?.ny options to their base NSSS would be submitted in topical reports af ter the B-SAR-205 is submitted.
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Interface Information The staff requested a table in Section 1 indicating the location of all interface information for the various NSSS systems. Also, the staff noted that the P&ID's should note interfaces with a unique symbol which ja an aid to people referencing B-SAR in the future. The staff requested a draf t of the cross reference table prior to submission of B-SAR-205.
l 5.
Seismic Design of Components B&W indicated that their present plans were to design for a SSE of 0.3g, i
and that this design would not be changed for low seismic sites.
6.
Regulatory Guides 1.70-XX B&W questioned how to treat the new series of Regulatory Guides that are revising the standard format. The staff indicated that the most important aspect was the content of the PSAR and that all information indicated in the Regulatory Guides must be submitted.
In this regard, our current scheduling requires all acceptance review questions (such as Regulatory Guide 1.70-XX requests) be supplied within five weeks of acceptance. In regard ti format, a receat inquiry from AIF has f'
been received and the curren feeling is that any one or combinations of three methods would be act optable (1) use the Standard Format Revision 1, (2) use the Standard Format Revision 1 with the extra material in special section for each chapter or (3) a mixture of the Revision 1 and Revision 2 of the Standard Forisst. The staff indicated that the last method would be best in terms of our review since the i
standard review plans are geared to the Revision 2 format.
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Don K. Dp'vis, P o ect Manager Light Watet Reactors Branch 2-3 Division of Reactor Licensing Attachments:
(1) List of Attendees l
(2) B&W Hand Out i
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.o ATTACHMENT 1 ATTENDANCE LIST PREAPPI.ICATION MEf, TING ON B-SAR-205 I
MARCH 20, 1975 i
4 P
J DRL-l D. K. Davis J. Giannelli H. Schierling W. Haass DTR i
C. G. Long (APCSB)
M.' Bell (ETSB) l J. L. Minns (ETSB)
L. Riani (APCSB)
A, R. Ungaro (APCSB) i B&W R. E. Schaffstall J. Hamilton G. J. Brazill W. J. Keyworth
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ATTACHMENE2 Comparison of 205 Fuel Assembly NSS Parameters L
B SAR-205 Standard 3600 MWt 3600 3800 CORE POWER, MWt 3618 3821 NSS POWER, MWt LINEAR POWER, kw/ft 5.43 5.73 PEAX, kv/ft 14.40 15.2 1060 1060 STEAM PRESSURE, psia 50 35 minimum SUPERHEAT, F NET PLANT OUTPUT, MWe*
1240 1297 NET PLANT HEAT RATE, Btu /kwh*
9909 10,000 FUEL ASSEMBLIES 205 205 ACTIVE FUEL LENGTH, in.
143 143 CONTROL ROD DIRVES, U CORE 72 72 P CORE 77 77 MAXIMUM 89 89 RCS FLOW, lo LB/HR 150.5 158.6+
s RV INLET TEMPERATURE, F 572.3 569 RV OUTLET TEMPERATURE, F 628.8 626 FEEDWATER TEMPERATURE, (MAX.), F 465 465 REACTOR VESSEL ID, in.
182 182 RC HOT LEG ID, in.
38 38 RC COLD LFG ID, in.
28 28 PUMP SUCTION ID, in.
32 32 STEAM CENERATOR TUBES 16,016 16,016 l
STEAM CF.NERATOR HEIGHT, ft.
75.4 75.4 RV-SG b SPACING, f t.
34.0 34.0 RCS VOLUME, f t 13,900 13,900 3
i CORE FLOODING TANKS NUMBER 2
2 3
1800 1800 VOLUME, ea. f t LOW PRESSURE INJECTION PUMPS NUMBER 2
2 FLOW per pump, gym 5000 5000 HICH PRESSURE INJECTION / MAKEUP PUMPS NUMBER 3
3 FLOW per pump, gym 700 700
- Estimated at 2" Hg backpressure 7 F.W. heaters.
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DISTRIBUTION OF MEETING SL'MMART_
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'Ii SVarga r.Leag NRC PDR MWilliams MBell LPDR FSchroeder JLMinns L Reading (M. Groff)
RMaccary LRiani LWR 2-3 Reading File HDenton AUngaro VAMoore RTedesco RCDeYoung VStello j
DMuller JKnight i
KColler SPawlicki DSkovholt LShao RDenise BCrimes j
JStolz WGacmill KKniel MSpangler
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ASchwencer JKastner DVassallo RBallard OParr CLong WButler GLainas BYoungblood VBenaroya r
VRegan TNovak GDicher TIppolito GKnighton Dross GLear OELD RPurple 15E (3)
DZiemann RS (3)
PCollins TCoulbourne i
WHouston ACRS (16)
RVollmer DDavis 3
l RIreland JGiannelli j
. RClark HSchierling WHaass
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