ML20207D926
| ML20207D926 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/19/1986 |
| From: | Conway R GEORGIA POWER CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20207D929 | List: |
| References | |
| 0826V, 826V, GN-1239, NUDOCS 8701020001 | |
| Download: ML20207D926 (2) | |
Text
_;.
. Georg1 Power Corrgcry:
. 333 PedmosO Avenue '
Atlanta., Georgia 3o308 Tefephone 404 52&6F24 '
h-f Mading Address.
Post Office Box 4545 -
At!anta, Georg'a 30302 -
t l
R.E.Conwat the southem e4ntre system Senior Vice President December 19, 1986 g
' Director of Nuclear Reactor Regulation File: X7N00-32 Attention: Mr. B. J. - Youngblood Log:
GN-1239
[
-PWR Project Directorate #4 fm Division of PWR Licensing A I
U..S. Nuclear Regulatory Commission
)..
Washington,-D.C.
20555 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PIANT - UNITS 1 AND 2 FSAR AMENDMENT NUMBER 32 Dear Mr. Denton Georgia Power Company, acting on its own behalf and as agent for Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and the City of Dalton, Georgia, hereby submits Amendment 32 to the Vo8tle Electric Generating Plant (VEGP) Final Safety Analysis Report (FSAR).
This amendment consists of revisions to the FSAR which dociunents changes to
. reflect design and Technical Specification consistency. These changes are itemized on Attachment 1.
Also included are instructions for inserting the Amendment 32 FSAR changes.
In accordance with the requirements of 10 CFR 54.30(b) and (c), three (3) signed originals and sixty (60) copies of Amendment 32 are submitted for your use.
Should you have any questions on the enclosed submittals, do not hesitate to contact me.
Yours truly, R. E. Conway 8701020001 861219 4 PCR ADOCK 0500
/
DA 0 1986 w Yg-u k E
Notarf Publig/
0826y Notary Pu'.He, Rkhmond County, Georgio My Ccmceden emires June I6,1970.
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i 7-Attachment 7
- FSAR Section.
Reason for Change Table 3.2.2-1 Clarifications requested by NRC staff 3.6.1 Clarification requested by NRC staff; jet impingement
- 3.6.2 Clarification requested by NRC staff; intermediate break locations 3.9.B.1.2 GN-1228, 12/10/86; FAPPS computer program description 5.3.1 Reflect use of ASTM E-185-82 vice E-185-79 Table 6.2.1-1.
Correction to containment design temperature from
'400*F to 381*F Table 6.3.2-1 Reflect nominal boron concentration in accumulators 7.2.1.1, Table 7.2.1-1 Addition of SSPS general warning alarm to reactor trip listing; consistent with 7.2.2.2.3 7.2.1 Clarification of overtemperature and overpressure T trip 9.4.8.1.2 GN-1227, 12/10/86; clarify temperature of AFW pumphouse 13.4.1 CN-1232, 12/11/86; PRB membership qualification Table 15.0.6-1 Clarify response time associated with SG water level Table 15.6.5-4 Revised response times to reflect analysis with Table 15.6.5-6 respect to containment isolation Table 16.3-3 Addition of " Capsule Fluence" column; consistent with Q251.1 Table 16.3-4 Addition of GDC-57 valves 17.2 Clarification requested by NRC staff; Opns QA Pmg Q420.47 Reflect design modification for slave relay testing 0826V
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