ML20247M729
| ML20247M729 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/27/1989 |
| From: | Bradham O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20247M733 | List: |
| References | |
| NUDOCS 8908020206 | |
| Download: ML20247M729 (5) | |
Text
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South reroHna ElIctric & G:s CompIny 01 S.
radhIm Jenkinsv$e SC 29065 Nuclear Operations (803) 3454 040 SCE&G
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. July 27, 1989 U. S. Nuclear Regulatory Commission q
Document Control Desk j
Washington, DC 20555
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Amendment 5 to Updated Final Safety AnalysisReport(FSAR) i Gentlemen:
-i In accordance with 10CFR50.71(e), South Carolina Electric & Gas Company (SCE&G), acting for itself and as agent.for South Carolina Public Service Authority, herewith files eleven (11) sets of Amendment 5 to the updated Final Safety Analysis Report (FSAR) for the Virgil C. Summer Nuclear Sthtion.
This FSAR Amendment is updated.as of March 1,1989, and includes the effects of: all changes made in the facility or procedures as described.in the FSAR i
since the last amendment; all' safety evaluations performed by.the Licensee, either in support of requested license amendments or in support of-conclusions that changes did not involve an unreviewed safety question; and-4 all analyses of new safety issues performed by or on behalf of the Licensee 1
at Commission request. The undersigned affirms that the statements ~and matters set forth herein are true and correct to the best'of his knowledge, information and belief.
If there are any questions, please contact us at your convenience.
l Very truly yours, I
l
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8 l
- 0. S. Bradham 1
EPM /0SB: led Attachments j
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Page 2 l
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dd 8908020206 890831
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PDR ADOCK 05000395 L
h-PDC
Document Control Desk
' ~ July 27, 1989 Pdge 2 c:
D. A. Nauman/0. W. Dixon, Jr./T. C. Nichols, Jr.
E. C. Roberts W. A. Williams, Jr.
S. D. Ebneter (w/ Attachment)
J. J. Payes, Jr.
General Managers C. A. Price /R. M. Campbell, Jr.
R. B. Clary K. E. Nodland J. C. Snelson G. O. Percival R. L. Prevatte (w/ Attachment)
J. B. Knotts, Jr.
H. G. Shealy NSRC RTS (RG 890001)
NPCF File (813.12) i i
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I ERRATA SHEET l
The Instruction Sheet contains one error--it directs removal of, and replacement with, pages 7.5-48/7.5-49. Pages 7.5-48/7.5-49 are also in the Amendment Package. These two pages should be discarded. The I
actual pages to be replaced are 7.5-47/7.5-48, which are included with this Errata.
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1 Therefore, holders should remove existing pages 7. 5-47/7.5-48 and replace I
them with the attached.
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g TABLE 7.5-1 (Continu:d)
~
RECULATORY CUIDE 1.97 VARIABLES NOTES 9
A.
Pressurizer Pressure (1700 to 2500~ psi) is used to resolve ambiguities above 1700 psi.
Below 1700 psi, Safety Injection Flow versus Associated Pump Curve is used.
B.
Design pressure is 57 psig. Wide Range Pressure provides indication when pressure exceeds 15 psig.
C.
This variable is Category 2 since protection grade auto switch over to Service Water is available.
D.
Recording of one narrow range and one wide range level for each steam generator provides trending information required for verification of secondary heat sink function.
E.
Virgil C. Summer Radiation Monitoring Syste'ms meet the intent of Regulatory Guide 1.97 (Revision 3) based on the pre-licensing modifications performed to meet IJuclear Regulatory Commission requirements under NUREC 0578.
(Reference SER Items 1.8.30 and 7.5.2).
Equipment is seismically mounted, designed and tested to operate in its normal and post accident environment.
F.
Trending capability is provided using the Technical Support Center (TSC) Computer System for 30 minute trending.
C.
RCS Sampling is used to address this variable.
V. C. Summer's Nuclear Sampling System meets the requirements of NUREC-0737. The points of extraction are:
RHR Loop A and Loop B, Pressurizer Liquid and Steam Spaces, RCS Loop B Hot Leg, and RCS Loop C Hot Leg.
Sampling Valves 9350A, 9350B, 9356A, 9356B, 9357, 9364C, 9365B, and 9365C.
are:
Portable Samplin: can be used to address sampling requirements from Reactor Building. amp, ECCS Pump Room Sumps, and Auxiliary Building Sumps.
H.
Rate meters are seismically qualified and located in the Control Room panel XCP6200. All control room equipment is in a mild environment.
Hi range detectors are seismically supported.
l i
I.
Main steamline flow instrumentation with a range of approximately 0-15%
g of nominal loop steam flow is used to detect the position of the steam generator safety valves.
i J.
This variable covered by RHR Flow.
l K.
Each fan has a green light and an alarm on the Main Control Board (MCB) g to indicate tripped condition, a red light on the MCB to indicate fan running, and an Emergency Support Facility (ESF) status light on the ESF MCB to indicate fan running.
L.
Existing Area Camma Monitors (1.0E-04 to 1.OE-1 R/HR) are augmented by high range portable survey instrumentation to meet range requirements.
i AMENDMENT 5 7.5-48 AUGUST, 1989
TABLE 7.5-1-(Continued)
RECULATORY CUIDE 1.97 VARIABLES NOTES A.
Pressurizer Pressure (1700 to 2500 psi) is used to resolve ambiguities above 1700 psi.
Below 1700 psi, Safety Injection Flow versus Associated Pump Curve is used.
B.
Design pressure is 57 psig. Wide Range Pressure provider indication when pressure exceeds 15 psig.
C.
This variable is Category 2 since protection grade auto switch over to Service Water is available.
D.
Recording of one narrow range and one wide range level for each steam generator provides trending information required for verification of secondary _ heat sink function.
E.
Virgil C. Summer Radiation Monitoring Syste'ms meet the intent of Regulatory Guide 1.97 (Revision 3) based on the pre-licensing modifications performed to meet Nuclear Regulatory Commission requirements under NUREC 0578.
(Reference SER Items 1.8.30.and 7.5.2).
Equipment is seismically mounted, designed and tested to operate in its normal and post accident environment.
F.
Trending capability is provided using the Technical Support Center (TSC) Computer System for 30 minute trending.
l C.
RCS Sampling is used to address this variable.
V. C. Summer's Nuclear Sampling System meets the requirements of NUREC-0737. The points of extraction are:
RHR Loop A and Loop B. Pressurizer Liquid and Steam Spaces, RCS Loop B Hot Leg, and RCS Loop C Hot Leg.
Sampling Valves 9350A, 9350B, 9356A, 9356B, 9357, 9364C, 9365B, and 9365C.
are:
Portable Samplin: can be used to address sampling requirements from Reactor Building 2mp, ECCS Pump Room Sumps, and Auxiliary Building Sumps.
H.
Rate meters are seismically qualified and located in the Control Room panel XCP6200. All control room equipment is in a mild environment.
i Hi range detectors are seismically supported.
l l
I.
Main steamline flow instrumentation with a range of approximately 0-150-of nominal loop steam flow is used to detect the position of the steam i
generator safety valves.
1 J.
This variable covered by RHR Flow.
K.
Each fan has a green light and an alarm on the Main Control Board (MCB) to indicate tripped condition, a red light on the MCB to i7dicate fan running, and an Emergency Support Facility (ESP) status light on the ESF MCB to indicate fan running.
L.
Existing Area Camma Monitors (1.0E-04 to 1.0E-1 R/HR) are augmented by high range portable survey instrumentation to meet-range requirements.
AMENDMENT 5 7.5-48 AUCUST, 1989 l
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