ML20236X927
| ML20236X927 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/04/1987 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| SL-3696, NUDOCS 8712100382 | |
| Download: ML20236X927 (6) | |
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[ Georgia Power Company 333 Piedmont Aanue Atlanta, Georgia 30308
- Telephone 404 526-6526 Mailing Address
Pbst Office Box 4545 Atlanta. Geogia 30302 b
Georgia Power L T. Gucwa the southern electr system '
. Manager Nrclear Safety-
- and Ucensrng SL-3696 0647m X7GJ17-V720 X7GJ10-V100 December 4, 1987
-U. S. N'uclear Regulatory Commission ATTN: Document Contro'i Desk Hashington, D.C.
20555
' PLANT V0GTLE - UNITS-1 AND 2 NRC DOCKETS 50-424, 50-425 OPERATING LICENSE NPF-68, CONSTRUCTION PERMIT CPPR-109
[CCS SURVEILLANCE TESTING - PROPOSED FSAR REVISIQN_S Gentlemen:
Please find attacFed the proposed.FSAR changes describing ECCS surveillance testing requested by M.
A.
Miller in a
letter to J; P. O'Reilly dated November 5, 1987. - Following your - review, the FSAR will be revised to reflect these changes.
If you.should have any questions or require additional information, please contact the undersigned.
Sincerely,
.l W% 1.L-/n L. T. Gucwa
-TVR/1m Enclosure c:
(see next page) 8712100382 871204
'E PDR ADOCK 05000424 i
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Georgia Power L q
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U. S. Nuclear Regulatory Commission December 4, 1987 Page Two i
I c: Georaia Power Company Mr. P. D. Rice l
Mr. J. P. O'Reilly 1
Mr. G. Bockhold, Jr.
Mr. J. E. Gwartzwelder Mr. C. H. Hayes GO-NORMS l
1 Southern Comoany Servicn l
Mr. R. A. Thomas Mr. J. A. Bailey Shaw. Pittman. Potts & Trowbridge Mr. B. H. Churchill, Attorney-at-Law Troutman. Sanders. Lockerman & Ashmore Mr. A. H. Domby, Attorney-at-Law U. S. Nuclear Regulatory Commission l
Dr. J. N. Grace, Regional Administrator i
Mr. J. B. Hopkins, Licensing Project Manager, NRR (2 copies) i Mr. J. F. Rogge, Senior Resident Inspector-0perations, Vogtle e
0647m "5
k Georgia Power h ENCLO5URE PLTNT V0GTLE - UNITS 1 AND 2 NRC DOCKETS 50-424, 50-425 OPERATING LICENSE NPF-68, CONSTRUCTION PERMIT CPPR-109 ffCS SURVEILLANCE TESTING - PROPOSED FSAR REVISIONS l
l 0647m E-1 11/18/87 SL-3696 700775
, _ = _
i p
s i
'VEGP-FSAR-6
.4 i
to' operate.any single active. component, technical l
. specifications'are established for reactor operation.
]
Normal operating' status of ECCS components is given in table.
6'.0.3-2.
1 The ECCS components are.available whenever the coolant energy 1
is high'and the reactor is critical.
During low-temperature physics tests there'is a negligible amount of stored energy in-the coolant and low decay heat; therefore, an accident comparable in severity to accidents occurring at operating conditions is not possible and ECCS components are not required.
The possibility of a LOCA during startup and shutdown has'been considered.
It has been demonstrated by analysis that
-e LOCA at'startup or shutdown is bounded by the LOCA analyses 10 described in-chapter 15, even though'.various ECCS components are intentionally disabled in the. shutdown mode. g The principal system parameters and the-number of components which may be out of operation in test, quantities and concentrations of coolant available, and allowable time in a degraded status are provided in the Techni~ cal Specifications.
.If efforts to restore the. operable status of the-ECCS are not ac:omplished within Technical Sp<scification requirements, the plant is required to be placed in a lower operational mode, 3, e.,' hot standby to hot shutdown,-hot shutdown to cold shutdown, etc.
additionally, portions of the ECCS may be ' temporarily realigned for check valve leakage testing prior to startup (i.e. Modes 3 and 4) by closing either HV-8809A or HV-88098.
Conservative analyses which assume ECCS f=.
configurations more restrictive than those established during check valve testing, demonstrate that the minimum ECCS flov delivery requirements continue to be met during check valve testing and that the chapter 15 LOCA analyses remain limiting.
V 6.3.3-8 Amend. 10 9/84 l
1
4 '
1 VEGP-E'SAR-6 i
l 6.3.4.1.2.2 Accumulators.
Each accumulator is filled with
~ l c
l water from.the refueling water storage tank and pressurized o
with the motor-operated valve on the discharoe line closed,
% 'g Then the valve is opened and the accumulator allowed to gg j
discharge into the reactor vessel as part of the operational g,
startup testing with the reactor cold and the vessel head off.
ng E
i O
6.3.4.2 Reliability Tests and Inspections either 5y p
I L
Routine periodic testing of the ECCS components an6 all necessary support systems at power is planned.
Val s which operate after a loss-of-coolant accident are operat d through a completecycle[;pumpsareoperatedindividuallyontheir miniflow linee except the charging pumps whicn are restea ny their normal tharging funct$ on.
If such testing indicates a u.
need for corrective maintcaance, the redundancy of equipment in
- 5 these systems permits such maintenance to be performed without shutting down under certain conditions.
These conditions
%y I
include considerations such as the period within which the
$g component should be restored to service and the capability of 3, a the remaining equipment to provide the minimum required level g y, of performance during such a period.
go 1
bm The series check valves between the accumulator and the P.CS are g8g i
tested to verify that each of the series check valves can 3',
l independently sustain differential pressure across its disc and m
L also verify that the valve is in its closed position.
The o
I required periodic tests are performed after each refueling Just
>, b,
I prior to plant startup, after the RCS has been pressurized.
Ejg l
Where series pairs of check valves form the high-pressure to C 8 "5 un low-pressure isolation barrier between the RCS and ECCS piping WEu outside the reactor containment, periodic testing of these e
check valves is performed to provide assurance that certain 50{
postulated failure modes will not result in a loss of coolant
.e e from the low-pressure system outside containment with a 05E simultaneous loss of ECCS pumping capacity.
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.g
+
The ECCS test line subsystem provides the capability for
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determination of the integrity of the pressure boundary formed guD by series check val'fes.
The tests performed verify that each
>%E 2B}u of the series check valves can independently sustain f
differential pressure across its disc and also verify that the valve is in its closed position.
The required periodic tests utx are performed after each refueling just prior to plant startup, g g, after the RCS has been pressurized.
4 5Id Lines in which the series check valves are to be tested are the "EM SI pump cold and hot leg injection lines and the R'IR pump cold
$"s
~
and hot leg injection lines.
u c 'E 22*5 6.3.4-2 W
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'..te VEGP-FSAR-6 To implement the periodic component testing requirements, 3
technical' specifications have been established.
During H
periodic system testing, a visual inspection of pump seals, valve packings, flanged connections, and relief valves is made to detect leakage.
Inservice inspection provides further-confirmation that no significant deterioration is occurring in the ECCS. pressure boundary.
Design measures have been taken to ensure.that the following testing can be performed:
A.
Active. components may be tested periodically for operability (e.g.,
pumps on miniflow, certain valves, j
etc.).
o' B.
An integrated system actuation test can be performed J
when the plant is cooled down and the RHR system is in.
E l
operation.
The ECCS is arranged so that'no flow is i
introduced into the RCS for this test.
Deta.iled cg discussion of SI signal testing-provisions is provided og in section 7.2.
g, 35 C. -An initial flow. test of the full operational sequence u o can be performed.
g*
Ed The design features which ensure this test capability are j[g specifically:
S. c -
A.
Power sources are provided to permit individual c;
actuation of each active component of the ECCS.
ii g mL B.
The SI pumps can be tested periodically during plant 5g operation using the miniflow recirculation lines l
=
previded.
j$
- j
- u C.
The RHR pumps are used every time the RHR system is
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{
put into operation.
They can also be tested Legs,,
'l per odically when t{ plant is at power using h j
D.
The centrifugal charging pumps are either normally in j
use for charging service or can be tested periodically on miniflow.
E.
Remotely operated valves can be exercised during I
routine plant r..aintenance.
F.
Level and prescure instrumentation is provided for each accumulator tank for continuous monitoring of these parameters during plant operation.
6.3.4-3
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