ML20038C596
| ML20038C596 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 12/08/1981 |
| From: | Sargent C COMMONWEALTH EDISON CO. |
| To: | Tedesco R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8112110259 | |
| Download: ML20038C596 (9) | |
Text
,
N Commonwealth Edison 1 / One First National Plaza Chicago, Illinois j
V Address Reply to: Post Office Box 767 Chicago, Illinois 60690 December 8, 1981 e
/' "
J
/i 42)fj/
S Mr. R. L.
Tedesco I
Ol
- #"'%g 788 Division o f Licensing
'fA
%s:('%g 'O'/74 Ass!stant Director 1
U.S. Nuclear Licensing jf.
Washington, D.C.
20555
/>
i*
Subject:
LaSalle County Station Units 1 and 2 Control Rod Drive System Flow Rate Used as an Emergency High-Pressure Water Source NRC Docket Nos. 50-373 and 50-374 References (a):
L.
O. DelGeorge letter to A.
j Schwencer dated October 2, 1981.
(b):
A. Schwencer letter to L. O.
DelGeorge dated November 6, 1981.
Dear Mr. Tedesco:
4 The purpose of this letter is to provide the additional information on Control Rod Drive flow rate requested in Reference (b) and to occument information provided to the NRC staf f in meetings in your of fices on November 17 and 20, 1981.
The information below represents a summary o f the condi-tions at LaSalle County Station with respect to the Control Rod Drive System (CRD) flow used as an emergency high-pressure water source:
1.
The dual CRD pump leakage flow was measured at 130 gpm against rated vessel pressure.
2.
Fire protection and detection improvements at LaSalle markedly decrease the possibility for an uncontrolled fire similar to Brown's Ferry; the LaSalle fire hazards evaluation is complete and the last equipment improvements are being installed to comply with NRC's requirements.
3.
The relative probability for common cause power failure like that at Brown's Ferry is significantly less because LaSalle is a physically separated and electrically separated plant employing three electric divisions whose
. simultaneous failure along with that of the HPCS diesel engine would be required to set-up the Brown's Ferry power situation.
k 8112110259 811208 PDR ADOCK 05000373 6//p h
(
1 1
R. L.
Tedesco December 8, 1981 4.
LaSalle has a 6250 gpm engine-driven HPCS which was not available in the Brown's Ferry plant; this primary high pressure water source is also backed up by an automatic and manually activiated reactor depressurization system which uses air accumulators to actuate relief valves.
5.
When depressurized to ambient vessel pressure, the CRD leakage flow rate is calculated to be 260 gpm; the low pressure ECCS's can inject water into the core whenever the difference in pressure between the vesse] and the low pressure systems reaches the injection setpoint; low pressure ECCS volume rate is approximately 21,000 gpm.
6.
The make-up capability of the dual CRD pumps does not meet the NUREG-0619 recommendation which was based upon a GE (SAFE) analysis indicating that 180 gpm make-up flow would not result in core uncovery.
The LaSalle specific analysis at 130 gpm make-up flow, however, shows that partial core uncovery can exist in that the minimum water level will attain 3 feet above the bottom of the active fuel.
This LaSalle County Station unique analysis also shows that the 0
peak clad temperature remains below 2200 F for 3 to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after scram.
This is ample time for operator actions to restore other water systems.
In this situation the operator would have initiated the symptomatic emergency procedures (LGA Procedures at LaSalle) to maintain water level above the care; this source of potential make-up water via the CR0 pumps is only one of approximately 15 possible make-up water sources-injection routes that are attempted in the emergency procedure.
(See Figure 1) 7.
Reliance on the CRD water source for make-up is not a part of the design basis nor has it been recognized nor utilized for safety or transient analyses.
Technical Specification improvements since TMI prohibit the lock-out of ECCS and design improvements have resulted in required ECCS auto-restart capability.
It appears, therefore, that the NUREG-0619 recommendation predates the post-TMI fixes and fails to recognize other alternate make-up water sources which are preferred for the BWR.
8.
In the post-scram situation, if the vessel level were maintained above the core for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, rather than for just 40 minutes as assumed from Brown's Ferry, then the PCT would remain under 22000F if only 130 gpm o f make-up flow were provided following loss of ECCS.
Fo r LaSalle, with HPCS and ADS which enables the use of divisionalized low-pressure ECCS's it is extremely improbable that reliance on the CRD pumps would be required, but if that proved to be the case it would be discovered enroute through the symptomatic emergency procedures in an operator's attempt to keep the core covered by any possible means.
i i
.R.
L. Tedesco December 8, 1981 j
9.
The GE model originally used to show that the generic 180 gpm prevented core uncovery was independently used as a back-up analysis for the LaSalle unique situation with 130 gpm make-up flow.
It showed that approximated one-third of the core would uncover by the 4-hour post-scram time but that vessel level would turn-around and slowly increase therea f ter.
The worst PCT predicted by this transient model is approximately 16000F.
Reactor Water remains in the outside shroud to act as a heat sink for in-core heat.
10.
Modeling of a direct CRD pump to vessel by-pass line utilizing the same model as originally used to determine the 180 gpm, but with actual inplant measured AP's, showed that 180 gpm would not be attainable at LaSalle.
Thus a physical change to attain the 180 gpm is not feasible.
11.
CRD pump performance curves request by the NRC staf f are enclosed as follows:
- a. Union pump Company Curve 783367 ; March 28, 1972) from vendor's test o f the LaSalle CRD pumps.
(Figure 2).
- b. Figure 3.
CRD pump A, as installed at LaSalle, with 4
correction for headloss ascribed to discharge valve.
- c. Figure 4.
CRD pump B, as installed at LaSalle, with correction for headloss ascribed to discharge valve.
i
- d. Figure 5.
CRD pump B, discharge pressure taken upstream of the discharge valve by special test arrangement to avoid the discharge valve loss.
Based on the summary information provided above and in Reference (a), it is judged that in as.much as the CR0 return flow capability discussed in the SER Section 4.6.2 is not a design basis requirement, that the actual flows determine by test at LaSalle County Unit 1 are adequate and satisfy the concern raised in NUREG l
0619.
If there are any questions in this regard, please contact this office.
Very truly yours, bb 93 C. E. Sargent Nuclear Licensing Administrator Attachments cc:
NRC Resident Inspector - LSCS lm 3016N
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