ML20199C379

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Forwards Amend 24 to FSAR for Vogtle Electric Generating Plant,Units 1 & 2.Justification for Revs Also Encl
ML20199C379
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 06/13/1986
From: Conway R
GEORGIA POWER CO.
To: Youngblood B
Office of Nuclear Reactor Regulation
Shared Package
ML20199C383 List:
References
0362V, 362V, GN-929, NUDOCS 8606180112
Download: ML20199C379 (8)


Text

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Garga Power Company 333 %ec:rnor.t Averve A!iar.m. Georg a 30308 Tctent se 404 5:6 EI?4 MaAr:g Aciress Post ON e Den 4545 A!!anta Gx;ra.a 20302 9

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R.E.Conway Sen.or vice Pres &rt June 13, 1986 Director of Nuclear Reactor Regulation File: X7N00-24 Attention:

Mr. B. J. Youngblood Log:

GN-929 PWR Project Directorate #4 Division of PWR Licensing A 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 24

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 24 to the Vogtle Electric Generating Plant (VEGP) Final Safety Analysis Report (FSAR).

This amendment consists of revised pages for the FSAR as documented in previous correspondence with the NRC, design and/or operational updates, and closure of SER items. A listing of the letters and updates are itemized in.

Please note that some of the revisions may require changes to the SER. Also included are instructions for inserting the Amendment 23 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 24 are submitted for your use.

Should you have any questions on the enclosed submittals, do not hesitate to contact me.

Yours truly, 8606180112 860613-4 PDR ADOCK 0000 K

R. E. Conway SWORN AND SUBSCRIBED EFORE ME, THIS h

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Director of Nuclear Reactor Regulation File: X7N00-24' June 13, 1986 Log:

GN-929 Page 2 xc:

M. A. Miller R. A. Thomas G. Bockhold, Jr.

L. T. Gucwa J. E. Joiner, Esquire B. W. Churchill, Esquire B. Jones, Esquire H. H. Gregory, III D. C. Teper W. C. Ramsey Vogtle Project File 0362V 1

ATTACHMENT 1 FSAR Section Reason for Change 1.9.26, 3.1' Clarification, Walker to Kelley, 3/15/86 1.9.68, Q640.25 Update to agree with NSSS standard start-up procedures 1.9.88 Clarification to reflect incorporation of -

WCAP-8370/7800 in Section 17.1 1.9.133 Reflect Technical Specifications 1.9.150, 5.2.3.4 Clarification to RV weld inspection T1.9-1, 2, & 3 Update to reflect use of NRC approval code cases 2.4, 2.5 Revised to reflect latest information and analysis for groundwater hydrology 3.6.1, 3. 6.2 Revised criteria. to reflect actual' rather than mechanistic breaks 3.7.B.3 Reflect use of multiple response spectra methodology (1) 3.8.1 Reflect current design, wedge material in containment post-tensioning system 3.9.B.1 Reflect use of additional computer program 3.9.B.3, Q210.54 Amplification of deflection criteria for supports 3.11.N.1 Reflect EQ updates 3F Reflect flood level analysis 4A CI-15; update to reflect use of RTDs in place of thermocouples

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FSAR Section Reason for Change 6.2.5 Reflect Technical Specifications - 7.1.1' Clarify " Phase B" isolation; human factor HED implementation 7.2.1, 7.3.5, 7.3.6, CI-26; update logic diagrams to 7.3.7 reflect override of control-room isolation signals T7.5.2-1 Update instrument ranges 8.2.2 Documentation of use of ASTM-B189

-8.3.1, Q430.62 Reflect Technical Specifications 8.3.1.4_

Clarification of cable tray fill at transition points 8.3.2.1 Reflect current design, upgraded minimum inverter operating voltage (2) 8.3.2 Reflect current design; resolve NRC finding 424/85-21-02 9.2.6 Reflect current analysis and Technical Specifications; minimum CST capacity (3) 9.2.10, 9.2.11 Reflect current design, turbine plant cooling load 9.5.1, 9A, 9B OI-7 & 8; reflect safe shutdown analysis 10.3.5 Consistency with Q281.6 commitment to -use EPRI-NP-2704 for chemistry control 10.4.9 Reflect current design; check valves in AFW system, and location of CST level alarm (3)'

T12.3.4-2 Instrument setpoint change to reflect actual testing Chapter 13 01-11; reflect new corporate structure, Bailey to Denton, GN-878, 4/21/86; training, Bailey to Denton, GN-862, 4/4/86, and 5/26/86 NRC teleconference 14.2.8 Reflect current test procedures

FSAR Section Reason for Change

.Q210.47 Clarification from NRC during teleconference,1/15/86

-Q271.1-CI-14; Bailey to Denton, GN-903, 5/7/86; P&V operability Q430.2 CI-35; Bailey to Denton, GN-877, 4/21/86; diesel load test (1) SER impacted, pages 3-28 & 29, by the additional use of multiple response spectra methodology rather than the exclusive use of the envelope method.

(2) SER impacted, page 8-7, vital AC buses will operate at a minimum of 105 rather than 104 volts.

(3) SER impacted, pages 9-22 & 10-19, by requirement for 340,000 rather than 330,000 gallons in the CST.-

t 0362V

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ATTACHMENT 1 FSAR Section Reason for Change 1.9.26, 3.1 Clarification, Walker to Kelley, 3/15/86 1.9.68, Q640.25 Update to agree with NSSS standard start-up procedures 1.9.88 Clarification to reflect incorporation of WCAP-8370/7800 in Section 17.1 1.9.133 Reflect Technical Specifications 1.9.150, 5.2.3.4 Clarification to RV weld inspection T1.9-1, 2, & 3 Update to reflect use of NRC approval code cases 2.4, 2.5 Revised to reflect latest information and analysis for groundwater hydrology 3.6.1, 3. 6.2 Revised criteria to reflect actual rather than mechanistic breaks 3.7.B.3 Reflect use of multiple response spectra methodology (1) 3.8.1 Reflect current design, wedge material in containment post-tensioning system 3.9.B.1 Reflect use of additional computer program 3.9.B.3, Q210.54 Amplification of deflection criteria for supports 3.11.N.1 Reflect EQ updates 3F Reflect flood level analysis 4A CI-15; update to reflect use of RTDs in place of thermocouples O

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FSAR Section Reason for Change O

Q210.47 Clarification from NRC during teleconference, 1/15/86 Q271.1 CI-14; Bailey to Denton, GN-903, 5/7/86; P&V operability Q430.2 CI-35; Bailey to Denton, GN-877, 4/21/86; diesel load test O

(1) SER impacted, pages 3-28 & 29, by the additional use of multiple response spectra methodology rather than the exclusive use of the envelope method.

(2) SER impacted, page 8-7, vital AC buses will operate at a minimum of 105 rather than 104 volts.

(3) SER impacted, pages 9-22 & 10-19, by requirement for 340,. 00 rather than 0

330,000 gallons in the CST.

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0362V

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"SAR Section Reason for Change 6.2.5 Reflect Technical Specifications 7.1.1 Clarify " Phase B" isolation; human factor HED implementation 7.2.1, 7.3.5, 7.3.6, CI-26; update logic diagrams to 7.3.7 reflect override of control room isolation signals T7.5.2-1 Update instrument ranges 8.2.2 Documentation of use of ASTM-B189 8.3.1, Q430.62 Reflect Technical Specifications 8.3.1.4 Clarification of cable tray fill at transition points 8.3.2.1 Reflect current design, upgraded minimum inverter operating voltage (2) 8.3.2 Reflect current design; resolve NRC finding 424/85-21-02 9.2.6 Reflect current analysis and Technical Specifications; minimum CST capacity (3)

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9.2.10, 9.2.11 Reflect current design, turbine plant cooling load 9.5.1, 9A, 9B OI-7 & 8; reflect safe shutdown analysis 10.3.5 Consistency with Q281.6 commitment to use EPRI-NP-2704 for chemistry control 10.4.9 Reflect current design; check valves in AFW system, and location of CST level alarm (3)

T12.3.4-2 Instrument setpoint change to reflect actual testing Chapter 13 01-11; reflect new corporate structure, Bailey to Denton, GN-878, 4/21/86; training, Bailey to Denton, GN-862, 4/4/86, and 5/26/86 NRC teleconference 14.2.8 Reflect current test procedures O

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