ML20034E782
| ML20034E782 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 02/24/1993 |
| From: | Fox J GENERAL ELECTRIC CO. |
| To: | Poslusny C Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20034E783 | List: |
| References | |
| NUDOCS 9303010362 | |
| Download: ML20034E782 (3) | |
Text
.
)
o' GE Nuclear Energy l*
c m o m ui:u w
- ct A1!T:C $D ' r? 5
,I 1
February 24,1993 Docket No. STN 52-001 L
Chet Poslusny, Senior Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of the Nuclear Reactor Regulation l
Subject:
SubmittrJ Supporting Accelerated ABWR Review Schedule - ECCS Subsystem Testing and ADS Ingic
Dear Chet:
Enclosed is a SSAR markup responding to COL Action Item 6.3.4.2-1.
Also enclosed is a copy of the revised Nuclear Boiler System IBD Drawing No.137C9464 (SSAR Figure 73-2) showing the revised ADS logic responding to Confirmatory item 6.33-1. This is a modification of earlier drawings and the proprietary affidavit under which it was originally issued is still applicable.
Please provide a copy of this transmittal to George Thomas.
Sincerely, Y
Jack Fox Advanced Reactor Programs l-cc: Norman Fletcher (DOE) w/o drawing Frank Paradiso (GE) w/o drawing R #Q1 y
taoooa
'Y
/.
lV -
l Rw38
(*
9303010362 930224
'PDR ADOCK 05200001 A
l COL G. 3 3 - 1 MkN 23A6100AD Standard Plant REV C o
conservative direction simultaneously. The 63.4.2 Reliability Tests and Inspections results of this calculation for the limiting case are given in Figure 63 67 through 63-75 and The average reliability of a standby Table 63-4. Since the ABWR results have large (nonoperating) safety system is a function of margins to the 10CFR50.46 licensing acceptance the duration of the interval between periodic criteria, the ABWR licensing PCT can be based on functional tests. The factors considered in the bounding PCT which is well below the 22000F determining the periodic test interval of the PCT limit.
ECCS are: (1) the desired system availability (average reliability); (2) the number of 6.33.8 LOCA Analysis Conclusions redundant functional system success paths; (3) the failure rates of the individual components Having shown compliance with the applicable in the system; and (4) the schedule of periodic acceptance criteria of Section 6.3.3.2, it is tests (simultaneous versus uniformly staggered concluded that the ECCS will perform its function versus randomly staggered).
in an acceptable manner and meet all of the criteria in Appendix 4B, given operation at or All of the active components of the HPCF below the MAPLHGRs provided by the utility for System, ADS, RHR and RCIC Systems are designed each fuel bundle. See Subsection 63.6.
so that they may be tested during normal plant operation. Full flow test capability is 6.3.4 Tests and Inspections provided by a test line back to the suction source. The full flow test is used to verify 63.4.1 ECCS Performance Tests the capacity of each ECCS pump loop while the plant remains undisturbed in the power All systems of the ECCS are tested for their generation mode. In addition, each individual operational ECCS function during the valve may be tested during normal plant preoperational and/or startup test program. Each operation, component is tested for power source, range, direction of rotation, setpoint, limit switch All of the active components of the ADS setting, torque switch setting, etc. Each pump System, except the safety / relief valves and is tested for flow capacity for comparison with their associated solenoid valves, are designed vendor data. (This test is also used to verify so that they may be tested during normal plant flow measuring capability). The flow tests operation. The SRVs and associated solenoid involve the same suction and discharge source valves are all tested during plant initial power (i.e., suppression pool).
ascension per Appendix A, Paragraph D.2.c of Regulatory Guide 1.68. SRVs are bench tested to All logic elements are tested individually and establish lift settings, then as a system to verify complete system response to emergency signals including the Testing of the initiating instrumentation and ability of valves to revert to the ECCS alignment controls portion of the ECCS is discussed in from other positions.
Subsection 73.1. The emergency power system, which supplies electrical power to the ECCS in Finally, the entire system is tested for the event that offsite power is unavailable, is response time and flow capacity taking suction tested as described in Subsection 83.1. The
~
from its normal source and delivering flow into frequency of testing is specified in the Chapter the reactor vessel. This last series of tests is 16 Technical Specifications. Visual impections performed with power supplied from both offsite of all the ECCS components located outside the power and onsite emergency power.
drywell can be made at any time during power operation. Components inside the drywell can be See Chapter 14 for a thorough discussion of visually inspected only during periods of access preoperational testing for these systems.
S ee S &a ch c.3. 6. 2. for col v-td
- g l i c.4 w s e wdo%aM a n e
E CCS desh) qw-e-63 13 Amendment 15
C '
ABWR 234uocin
- Standard Plant RIN C low water level and drywell high pressure plus indication that at least one RHR or HPCF pump is operating. The HPCF, RCIC, and RHR automatically return from system flow test modes to the emergency core cooling mode of operation following receipt of an automatic invitation signal. The RHR LPFL mode injection into the RPV begins when reactor pressure decreases to the RHR's pump discharge shutoff pressure.
HPCF injection begins as soon as the HPCF pump is up to speed and the injection valve is open, since the HPCF is capable of injection water into the RPV over a pressure range from 1177 psid to 100 psid or pressure difference between the vessel and drywell.
l 6.3.6 COL LicenseInformation 63.6.1 ECCS Performance Results The exposure dependent MAPLHGR, peak cladding temperature, and oxidation fraction for each fuel bundle design based on the limiting break size will be provided by the COL applicant to the USNRC for information. (See Subsection 633).
+
G.3. G.2 ECC F 7e r-h n R.a meks 6.3.7 Reference a e c.ordawcA w 4 "To c.h nic o I In L
General Electric Company Analytical Model 3ge ksc o%oe S R 3.5. i.T> k COL.
h ca A ws\\\\ f*v
& S41k for Loss-of-Coolant Analysis in Accordance app E C C S s u b s 3 s4e*3 i W w pveg A b 4. I u^
with 10CER50, Appendir K, (NEDE-20566-P-A),
- M * 'Y t*
September 1986.
4y.u g h'-M 4 0 W T "C] h s.s.4 t)
P D
s e g u.. ( s e e sa.s c
i f
l
[
[
M Amendment 23 L
M
\\ '
OVERSIZE DOCUMENT PAGE PULLED SEE APERTURE CARDS I
APERTURE CARD /HARD COPY AVAILABLE FROM RECORDS AND REPORTS MANAGEMENT BRANCH Y
a i
--v-n
. - - -.-----