ML20206L993
| ML20206L993 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 11/18/1988 |
| From: | Schnell D UNION ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| ULNRC-1863, NUDOCS 8811300334 | |
| Download: ML20206L993 (7) | |
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.e November 18, 1988 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station Pl-137 Washington, D.C.
20555 Gentlemen:
ULNRC-18 6 3 DOCKET 1RIMBER 50-483 CALLAWAY PLANT STEAM GENERATOR LEVEL REACTOR TRIP _MODIF_I_ CAT _I_ON Reference; ULNRC-1822 dated August 30, 1988 The reference letter transmitted an application for amendment to the Callaway operating license affecting Steam Generator Low-Low Level trip circuitry.
Union Electric and Westinghouse personnel met with the Staff on October 5 to present an overview of the submittal.
As a result of that meeting, we are providing the attached information to supplement our application request.
If there are any questions on this material, please contact us.
Very t ru.'.y yours,
, /(, / h&W Donald F.
Schnell DFS/ dis Attachment i
8811300334 881110 h
PDR ADOCK 05000403 P
PNV
3 i
O STATE OF MISSOURI )
)
Alan C.
Passwater, of lawful age, being first duly sworn upon oath says that he is Manager, Licensing and ruels (Nuclear) for Union Electric Company; that he has read the foregoing document and known the content thereof that he has executed the same for and on behalf of said company with full po'.1er and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
/]
By Alan C.
Passwater
!!anager, Licensing and Puols Nuclear SUBSCRIBED and sworn to before me this /f-day of 4, 1987 bittw @ h1
./
(i BAP3 ARA J. PF AFF NOT AtY f Uf uC. STAT! CF Wili3URI Mf COVV:S$10N [1NRI$ MR122,1943 ST.LOUl3 COUNTY
s cc Gerald Charnoff, Esq.
Shaw, Pittman, Potts & Trowbridge 2300 N. Street, N.W.
Washington, D.C.
20037 Dr. J. O. Cermak l
CFA, Inc.
4 Professional Drive (Suite 110)
Gaithersburg, MD 20879 R. C.
Knop Chief, Reactor Project Branch 1 L
U.S. Nuc1 car Regulatory Commission i
Region III l
799 Roosevelt Road Glen Ellyn, illinois 60137 l
Bruce Little Callaway Resident Office U.S. Nuclear Regulatory Commission RRil Steedman, Missouri 65077 Tom Alexion (2)
Off. ice of Nuclear Reactor Regulation l
U.S. Nuclear Regulatory Commission a
Mail Stop 316 l
7920 Norfolk Avenue Bethesda, MD 20014 Ron Kucera, Deputy Director l
l Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102 Manager, Electric Department Missouri Public Service Connission i
P.O. Box 360 l
Jefferson City, MO 65102 i
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l CALLAWAY TTD/EAM ktCENSING SUBMLTTAL_SAFJTY_6NALYSES Y
Reference 1: ULNRC 18*:2 dated 8/30/88 which submitted WCAP-11883-P l
1)
The following is in regards to a question raised during the 01tober 5 meeting by the flant Systems reviewer on the Callaway TTD/EAM licensing submittal safety analyses (Reference 1).
During the presentation of the specific analysis cases provided in WCAP-11883, a question was ueked about the use of WCAP-11325 generic analyses and sensitivities to support the Callaway trip time delays.
Specifically, why WCAP-11883 did not contain a l
Callaway-specific Feedline Break analysis to verify the l
acceptability of the 10% rated thermal power (RTP) interlock l
time delay as determined by analysis of the Loss of Normal l
The purpose of the seven WCAP-11883 safety analysis cases is to provide 1.
Determination of the Safety Analysis Limits for the i
Steam Generator Low-Low Level trip setpoint and trip l
time delays; or 2.
FSAR Chapter 15 reanalysis to reflect revised safety analysis assumptions; or 3.
Sample demonstration of the applicability of the generic sensitivities developed in WCAP-11325 to the Callaway Plant.
WCAP-11883 Cases I, II, III and IV are Loss of Normal Feedwater analyses performed to provide the safety analysis basis for the Technical Specification TTD power interlock time delays.
Case VI provides updated FSAR Loss of Normal Feedwater analysis results to support a revised Safety Analysis Limit for the Steam Generator Low-Low Level trip setpoint.
Case V provides updated FSAR Loss of AC Power to the Station Auxiliaries analysis results to support a revised Safety Analysis Limit for the Steam Generator Low-Low Level trip l
setpoint.
In addition, Case V addresses the effect of the l
EAM on part-power Loss of AC Power cases since, for the same l
trip setpoint, with no TTD-related time delays, the full I
power FSAR case bounds cases initiated at lower power levels.
The remaining required verification involves the time delay enabled by the TTD logic at indicated power levels below the maximum power TTD interlock setpoint.
Page 2-17, last paragraph, of WCAP-11883 provides additional discussion relating to this issue.
However, this additional discussion is considered to be proprietary, therefore it is l
not reprinted herein.
i Case VII is a Feedline Break case with the 20% RTP interlock time delay for 2/4 logic as determined by the Loss of Normal Feedwater analysis of Case III.
This case is a sample l
part-power Feedline Break performed to demonstrate that acceptable Feedline Break results are obtained at j
part-powers using the trip time delays as determined through analysis of the complete Loss of Normal Feedwater transient.
l This case is, therefore, a confirmation of the generic conclusions presented in WCAP-11325.
r Conclusion i
f The seven WCAP-11883 safety analysis cases form the basis for new Technical Specification limits for the Steam i
Generator Low-Low Level trip setpoints as enabled by the EAM i
and the time delays enabled by the TTD.
The generic i
findings of WCAP-11325 are used to minimize explicit l
confirmatory analyses for plant-specific implementations of l
these systems.
The combination of explicit part-power l
analyses, FSAR full power analyses, and safety evaluatione i
performed consistent with the WCAP-11325 methodology confirm t
that all applicable safety analysis acceptance criteria j
continue to be met.
1 2)
In response to an NRC question about TTD timer modules, the MC14536 programmable timer uses a variable RC network as an input to the on-chip clock enable circuit to calibrate for i
the desired time delay.
There is no software or microprocessor-related programming associated with the l
operation of this chip.
Figures 1 & 2 are a catalogue schematic diagram of the timer module and a vendor data i
sheet on the MC14536 timer chip.
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