GO2-93-258, Forwards Nonproprietary Table 4-1, Containment Performance Results, Per JW Clifford Request.Table Reflects Deletion of Header, GE Proprietary Info, as Included in 930709 Request for Amend Re Power Uprate
| ML17290A733 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 10/25/1993 |
| From: | Parrish J WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GO2-93-258A, NUDOCS 9311120259 | |
| Download: ML17290A733 (5) | |
Text
~ecEI.ERAr aoCUMXm Msr mrox svSxEM REGULA INFORMATION DISTRIBUTIO YSTEM (RIDS)
ACCESS~ON NBR:9311120259 DOC.DATE: 93/10/25 NOTARIZED: NO DOCKET I FPCIL".50;, 397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH.NAME AUTHOR AFFILIATION PARRISH,J.V.
Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards nonproprietary Table 4-1, "Containment Performance Results,"
per JW Clifford request. Table reflects deletion of
- header, "GE Proprietary Info," as included in 930709 request for amend re power uprate.
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NOTE TO ALL"RIDS" RECIPIENTS:
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c WASHINGTONPUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Wasbtngton Way ~ Rtcbland, 1Pasbtngton 99352<968
~ (509) 372-5000 G02-93-258A October 25, 1993 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.
20555 Gentlemen:
Subject:
WNP-2, OPERATING LICENSE NPF-21 POWER UPRATE
Reference:
Letter G02-93-180, dated July 9, 1993, JV Parrish (SS) to NRC, "Request for Amendment to the Facility Operating License and Technical Specifications to Increase Licensed Power Level from 3323 MWt to 3486 MWt with Extended Load Line Limitand a Change in Safety Relief Valve Setpoint Tolerance" The reference included Table 4-1, "Containment Performance Results,"
with a header containing, "GE Proprietary Information." Per a request made by J. W. Clifford, Senior Project Manager, a non proprietary version of this table is provided.
This table only differs from that provided in the reference in that the header has been deleted as we have determined that the table contains no information proprietary to General Electric or the Supply System.
Sincerely
. V. Parrish (Mail Drop 1023)
Assistant Managing Director, Operations AGH/bk Attachments CC:
BH Faulkenberry - NRC RV NS Reynolds - Winston & Strawn JW Clifford - NRC DL Williams - BPA/399 NRC Site Inspector - 927N 93lii20259 93i025 PDR ADOCK 05000397 P
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Table 4-1 CONTAIN1VQATPERFORMANCE RESULTS
~Parame er Current FSAR
~aseo)
Updated Final at Updated Methods at Uprated Methods Uprated Power With
~FSAR e
~pwertare ELLLtarn Limit Peak Drywell Pressure (psig) 34.7 Peak Wetwell Pressure (psig) 27.3 34.5 30.2 34.8 30.2 35.1 45 (4) 45 Peak Drywell-to-Wetwell Pressure Difference (psid)
Peak Bulk Pool Temperature ('F)
LOCA Alternate Shutdown 19.4 220 215 21.7 199 21.5 210 (4)
(4) 25 212 212 (1)
Analysis performed at 3462 MWt (104.2% oforiginal rated power), dome pressure 1040 pslg.
(2)
Analysis, performed at 3702 MWt (1.02 x 110% of original rated steam flow), dome pressure. 1040 psig.
(3)
Updated (current) methods (References 2, 3 and 4).
(4)
Bounded by Power Uprate Case.
Note:
The value of Pa to be used for 10CFR50 App. J testing must be > the peak calculated containment pressure resulting from any design basis accident.
To bound a potential future power uprate (110% of original rated steam flow) and possible unforeseen future plant changes, the value of Pa is conservatively chosen to be 38 psig.
4-11
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