ML20091Q460
| ML20091Q460 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 01/31/1992 |
| From: | Gates W OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-88-17, LIC-92-018R, LIC-92-18R, NUDOCS 9202040434 | |
| Download: ML20091Q460 (3) | |
Text
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j Omaha Publl: Power District 444 South 16th Street Mall Omaha, Nebraska 68102-2247 ff$h0hR 402/63G2000 V. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station PI-137 Washington, DC 20555
References:
1.
Docket No. 50-285 2.
Letter from OPPD W. G. Gates) to NRC dated September 4(,1991 (LIC-91-20lR) document Control Desk) 3.
Letter from NRC (D. L. Wigginton) to OPPD (W. G. Gates) dated December 5, 1991 Gentlemen:
SUBJECT:
Generic Letter 88-17 Enhancements Asrekuestedb Reference 3 attached is the listing of indications and alarms assoc ated witfi the Fort Cahhoun Station Decay Heat Removal (Shutdowa Cooling) system. This list of Control Room alarms and indic:tions is provided to assist the NRC in review of Reference 2.
If you should have any questi
- , please contact me.
Sincerely, M./
4 W. G. Gates Division Manager Nuclear Operations WGG/sel Attachment c:
LeBoeuf, tamb, Leiby & MacRae R. D. Martin, NRC Regional Administrator, Region IV D. L. Wigginton, NRC Senior Project Manager R. P. Mullikin, NRC Senior Resident Inspector 1
030042 9202040434 920131
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As previously discussed, in each case the relevant acceptance criteria is met wh;ch preserves the margin of safety provided by these criteria, it is therefore cor&dW j
that the requested changes do not involve a significant reduction in any margin c' safety.
Conclusions This evaluation describes investigations made for a ps.ver uprate to 3430 h1Wt, equivalent to 105% of original steam flow, A 5% increase in steam flow we factored h;o the original design basis for Fermi 2 hiajor analyses, i.e. overpressurization, ECCS/LOCA, and the radiological consequences of the DBA/LOCA, were originally performed ct 3430 htWt and were previously approved by the NRC. Those analyses were reperformed m 34;,0 hiWt + 2% and remain well within regulatory limits, IInving arrived at negative declarations with respect to these considerations of 10CFR50.92, this assessment constudu j
that uprated power operation at 3430 hiWt does not involve a significdu hyzatds consideration for Fermi 2, a
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At t achment LIC 92-018R f 0R1 CAlll0VN STA110N WILS1SILM.20R1ROLR00!LMARMLLlNDlM110MS At fort Calhoun Station the Low Pressure Safety injection (LPSI) pumps serve as the Decay lleat Removal (DilR) system pumps.
The plant specific term for DilR at f ort Calhoun Station is Shutdown Cooling.
The Containment Spray pumps may be used as a backup when the RCS 15 vented through a minimum of 47 square inches and RCS teinperature is less than 120'f. lhe pressurizer manway satisfies the minimum area requirement, lhe following alarms are presently available in the Control Room to alert the Operators to un off wrmal condition with the D}{R system (acept for item 2 which will be installed dud ng the 1992 Refueling Outage):
ReMior Coolant System Refueling Level Loi, u
- Alarms when Reactor C6ohnt system water level is 2 inches bdo. 4, t y 1.
w a.terline of the hot leg (LA-197, and LA-119).
7 MR-fC-89 025 completed during the 1989 outage, improved the accuracy of LA 197 and added the redundant channel LA 119. Calibration procedures for the alarms ensure that the alarms will be received prior to actual level Jecreasing more than 5 inches below hot leg centerlinc.
During the 1988 outage following f ull core off-load,. Reactor Coolant system level was lowered to determine the point at which the Decay lleat Removal system began to show signs of vortexing and drawing air into the suction line.
Pump motor amperage began minor fluctuations at 7 inches btlow hot leg centerline, lherefore, the alarm setpoint of 2 inches is appropriately sonservative to assure that the alarm will actuate prior to vortexing (for normal DilR flow rates).
2.
Shutdown Cooling System Low flow Alarm (new alarm to be installed by Modification MR-fC-89 019 during the 1992 Refueling Outage) down cooling
- Will alarm on a low flcw condition (< 1000 gpm) as sen ed by the shut flow elemert 'fE-326).
i
- Alarm sound:
+ the LPSI Pump 0,u load Ti p (A-34-1, f 7 and A-331, fl)ker is not closed.
3.
control switch is in AfiLR CLOSE and the pump brea A-34-1. D7 and A-33-1, 01) - If the pump control LPSI Pump Off Normal (he "69 switch is not in NORMAL, or the house hoist 4.
- witch is in PULLOUI, t switch indicates that the breaker is not racked in, the alarm is received.
( A-34-1, G7 and A-33 1 Gl) -
LPSI Pump Recirculation Mode Auto Trip 5.
Indicates that a Recirculation Actuation Signal (RAS) has stopped a LPSI pump.
Shutdown Cooling Valves Closed Signal f ail or Violation A2, C-lL-0) -
Alerts the operators that Reactor Coolant system pressure ha(c exceeded the 6.
maximum operating pressure of the Shutdown Cooling system a he shutdowr, cooling system is seing automatically isolated (llCV-30 a V-348 will close)d, the aato closure feature is disabled,During refueling conditions, when the
)ressurtier manway is remove lowever, the alarm is still functional.
Attachment tlc 92 018R The following ind aa are available in the Control Room to monitor and access the state of t*
.1
, stem:
1.
Reactor Coolant system icvel (ll-119 and LI-197).
2.
Decay Heat Ren. oval system return header p.' essure (F1325).
3.
Decay Heat Removal system suction and return header temperatures on a trend recorder (1R 346).
4.
Decay Heat Removt,1 system heat exchanger outlet t.vmperature (T1-339 and 11-340).
These temperatures are available on the flant Computer.
A request has been submitted for development of software that will assign an alarm to those temperatures.
This softwaru will be installed during the 1992 outage.
5.
Decay lleat Removal system heat exchanger cooling water inlet ard c.tlet temperatures (TI 4R6, TI-487, T1-493, TI 494, 11 495 and T1-496).
6.
Decay Heat Removal system total flow (flC-326).
7.
Decay Heat Removal system individual loop injection flow (f t-328, fl 330, fi-332 and fi 334).
Low Pressure and Containment Spray 18, AM/SI 3A, AM/SI-38 and AM/SI-3C. p m 8.
um 9.
Decay Heat Removal system valve aosition (FCV-326, HCV-327, r!CV-329. HCV-331, HCV-333, HCV-335, HCV 347, 1CV-348 HCV 2937 HCV 2938,itCV 2947 and HCV-2948).
10.
Twenty Eight (led.28) Core Exit Thermocouples (CETs) whtn the reactor vessel head is instal Two 1.idependent CETs must be avaliai3le durin inventory conditions when the reartor vessel head is installed,g reJuced i
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