ML20064E127

Forwards Responses to Latest NRC Questions Re Proposed Overpressurization Mitigating Sys for Subj Facils.Also Encl Are 4 Oversized marked-up Drawings Showing Preliminary Design of Sys,Available in Central Files

ML20064E127
Person / Time
Site:	Farley
Issue date:	11/03/1978
From:	Clayton F ALABAMA POWER CO.
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 7811140152
Download: ML20064E127 (19)

Text

P A.aCa*a Powe< Company 600 Narin 18 n S:reet

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Pest ONe B:= 2641 E r-f ra-A aca a 35291 Te e:none 205 323-5341 F. L CLAYTON, JR.

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Senior V.ce Pres. cent abamaPOWer

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the sout%m electnc system November 3, 1978 Docket No. 50-348 a -364 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.

20555 JOSEPH M. FARLEY NUCLEAR PLANT-UNITS 1 AND 2 REACTOR COOLANT SYSTEM OVERPRESSURIZATION MITIGATING SYSTEM Gentlemen:

Enclosed please find responses to the latest NRC questions transmitted to Alabama Power Company concerning the proposed overpressurization miti-gating system for the Farley Nuclear Plant. Four (4) marked-up drawings showing preliminary design of part of the subject system are also attached l

as requested, Should you have any questions, please inquire.

j Very truly yars, F. L. Clayton Jr.

FLCJr/TNE:bhj Attachments cc:

Mr. R. A. Thomas Mr. G. F. Trowbridge 9 d'///' 9'jt/sL tl Ai y4 l

+8*

i 1.

Question:

The esiiting OMS design uses the wide-range RCS pressure trarsmitters to initiaw auto-closure of the RHR system isolation valves. The wide-range RCS pressure transmitter range is 0 to 3000 psig. According to the WCAP-8541 report, the muimum deviation of a Foxboro EllGH transmitter can approach 13.5%

Justify of full scale which translates to a possible error of more than 400 psi.

the use of the wide-range RCS pressure sensors for the RHR system auto-closure interlock.

Response

The Foxboro EllGH wide-range RCS pressure transmitter deviation of 13.5% is the maximum deviation which could be encountered during a post-LOCA condition. The OMS is required to function during normal plant operating conditions of heatup and cooldown.

During normal operating conditions the deviation is limited to a maximum of 2.25% of the pressure range of 0 to 3000 psi. The 2.25% deviation is composed of 0.5% for transmitter error,1% for channel error and 0.75% for f

actuation error. The 2.5% deviation translates into a auto-closure setpoint deviation of 67.5 psi. The auto-closure setpoint is 700 psig.

By referring to Figures 4 and 6 of our 9/6/78 submittal it can be seen that the maximum RCS pressure following the worst overpressurization transients is limited to 565 psig. Therefore, an inadvertent closure of the RHR isolation valves at 632.5 psig (700-67.5) will not disable the OMS function during the postulated transients.

2.

Question:

Discuss the type of RHR isolation valve position indication available to the operator in the control room. If indication is not available, justify your

(

design. Discuss your audible control room alarm on inadvertent isolation of (or improper isolation valve position for) the RHR system.

If no such alarm exists, justify your design.

Response

The RHR isolation valves 8701A, 8701B, 8702A and 8702B have open and closeThis position indication available to the operator on the main control board.

indication is provided from the limit switch control located on the valves' motor operator.

No alarm is associated with the RHR isolation valve position indication.

Since the OMS is designed to function considering a single failure which includes an inadvertent isolation of one train, no alarm is considered necessary.

i 3.

Question:

Provide the portion of the operating procedures which envelope the alignment of the RHR system for shutdown cooling.

Response _:

The sequence of events for alignment of the RHR for shutdown cooling is as follows:

(1) Commence RCS cooldown by manually controlling the steam dumps.

Manually control pressurizer level at approximately.70%.

(2) Manually control the pressurizer spray valve and begin pressurizer cooldown and RCS pressure reduction.

ReduceRCSpressureto400t2g psig.

(Note that a bubble still exists in the pressurizer.)

(3) prior to placing RHR system in operation, close the RHR system to charging pump suction valves and rack out the breakers.

(4) When RCS temperature has been reduced below 350 F and pressure is 0

400 t 25 psig, place the RHR system in operation as follows:

O Align component cooling water to RHR heat exchangers.

a.

Close RHR heat exchanger to RCS cold leg isolation valves and b.

RWST suction valve.

Open RHR isolation valves.

c.

d.

Start RHR pumps and recirculate the RHR system. Sample RHR for boron concentration.

Stop the RHR pumps.

Close the RHR heat exchanger discharge valves. Open the RHR heat e.

exchanger.to RCS cold leg isolation valves.

f.

Start RHR pumps and establish cooldown flow by controlling the RHR heat exchanger discharge valves.

(Note that with RHR system in operation, the relief valves are aligned to provide overpressure protection.)

(5)

Increase pressurizer level by increasing charging flow rate and/or decreasing the RHR letdown flow.

(6) Maintain RCS pressure 400 25 psig by manual spray, charging and 0

RHR letdown.

When RCS temperature is between 290 F and 280 F, open and rack out circuit 0

0 (7) breakers for two charging pumps leaving only one operable.

(This action it, required to limit the possible mass input to RCS for overpressure pro-tection. Enable RCS Water Solid High pressure alarm.

Continue cooldown for RCS and pressurizer. When the bubble collapses, (8) adjust charging and letdown flow as required to maintain 400 ! 25 psig.

(At this point the RCS is solid with overpressure protection proVided by the RHR RV's.)

4.

Question:

Provide detailed electrical schematics or logic diagrams for the following:

a.

RHR isolation valve controls, b.

OMS alarm, and RHR-isolation valve interlocks and power supply arrangements.

c.

Respons,e_:

The detailed marked-up electrical schematics of the RHR isolation valves J

interlocks and power supply arrangements are shown in Figures 8, 9,10 and 11.

The logic diagrams and the block diagrams of the RHR isolation valves auto-closure and open permissive interlocks, and the general arrangement diagram of the RHR isolation and relief valves have been revised (Rev.1). These re-vised diagrams are shown in Figures IV-1, IV-2(a), IV-2(b), IV-3, and IV-4.

A logic diagram of the OMS alarm is shown in Figure IV-5.

5.

Question:

Discuss increased testing of your OMS relief valves.

Response

We consider that the increased testing of the OMS relief valves is not justified since all other relief valves, including the pressurizer relief and main steam safety valves, are only tested once every five (5) years in accordance with the ASME code.

Removing and testing of the OMS relief valves will: (1) require that one RHR train be made inoperable, and (2) require that the pressurizer relief tank be depressurized. This results in an increased maintenance and personnel exposure due to the necessity of making other safety and relief valves located inside the containment that relieve to the pressurizer relief tank inoperable.

(

6.

Question:

The submittal by the applicant on 9/6/78 compared 10CFR50, Appendix G curves for 0 F/hr cooldown and 60 F/hr heatup to their worst overpressure 0

0 transients. However, by technical specification they may cool down or heat up at up to 1000F/hr. The staff requires that either the applicant submit curves for 100 F/hr cooldown and heatup for comparison to the limiting transients, or 0

modify their technical specifications to limit their cooldown and heatup rates while on the RHR system to those analyzed.

Response

Figures 4, 5, 6 and 7 of our 9/6/78 submittal have been revised to show the peak RCS pressure following the worst mass and heat input transients in comparison 0

with the limiting Appendix G pressure for cooldown and heatup rates of 0 F/hr, 0

0 20 F/hr, 600F/hr and 100 F/hr.

.q.

As shown in Figures 4 and 6, the peak RCS pressure following the worst mass end heat input transients remains below the limiting Appendix G pressure for cooldown rates of 00F/hr and 20 F/hr.

For cooldown rates of 60 F/hr and 100 F/hr the peak RCS pressure gxceeds the limiting Appendix G pressure when 0

the RCS temperature is above % F and 126 F, respectively. We consider this to be of an insignificant nature for the following reasons:

l (a) Temperatures below 126 F are very impractical to achieve due to the decay 0

heat generation and the heat capacity of the RCS.

0 0

(b) The normal cooldown rates are always below 60 F/hr. The 100 F/hr cooldown rate is a limiting condition which, if ever achieved, is restricted in accordance with the Farley Technical Specification to a very short dura-tion of one hour. Thus,0the possibilities of an overpressurization event coupled with a 100 F/hr cooldown rate is highly unlikely.

Since the ASME Section III, Appendix G analysis per 10CFR50, Appendix (c)

G of the reactor vessel has significant built-in conservatism, actential un-likely violations as explained earlier will not cause vessel degradation.

Figures 5 and 7 show the peak RCS pressure following the worst mass and heat I

input transients remairs below the limiting Appendix G pressure for heatup 0

rates of 00F/hr, 200F/hr, 600F/hr and 100 F/hr for all RCS temperatures.

Therefore, conformance to Appendix G is assured.

7.

Quetticn:

Provide assurance that no portion of the RHR system is subjected to pressure in excess of 110% of design during any water-solid overpressurization.

Response:_

The RHR system pumps, piping, valves and the heat exchangers are designed for a minimum pressure of 600 psig. As shown in Figures 4, 5, 6, and 7 of our 9/6/78 submittal, the peak pressure following the worst overpressurization transients is 565 psig which is less than 660 psig (110% of 600 psig).

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20 40 60 Det TnMR ATitRF. OF

GENERAL ART 3EMENT OF THE RHR RELIEF AND I

'.ATION VALVES Rhy.1,10/31/78.,,

To Pressurizer Relief Tank i

A TRAIN A TO RHR PUMP 87028-B 8702A-A I

Cold Hot Leg Leg Reactor Vessel TO PRESSORIZER RELIEF TANK A

Hot Cold l

eg Leg TRAIN B TO RHR PUMP 8701B-B 8701A-A Inside Outside i

Containment Containment D

a

~

PROPOSED RHR ISOLATICN VALVE INTERLOCK LOGIC Figure IV-2(a)

Rev.1,10/31/78 Spring Return to Neutral Control Board Switches OPEN N

CLOSE OPEN N

CLOSE P-403 P-402 P-402 P-4 PRESSURE RESSURE RESSURE I

RESSURE I

TRMTR TRMTR TRMTR TRMTR 9

/

s-G l

'I N 'II l

i,'s f

1. g i 4

8 v

v u y

v MBi 5?lR E.w==nB

^WMN1

.5M?6iEl"4 i

- O I

PVST I

i l

l OPEN y

v CLOSE OPEN CLOSE 87018-B 8702A-A

(

Notes:

l.

The interlock shown in dotted lines indicates the method of applying diverse principles. ~

TRMTR - Transmitter PVST - Pressurizer Vapor Space Temperature

~_

PROPOSED RHR ISOLATION VALVE INTERLOCK LOGIC Figure IV-2(b)

Rey. 1,10/31/78 Spring Return to Neutral Control Board Switches

/

OPEN N

CLOSE OPEN N

CLOSE P-403 P-402 PRESSUREI o

TRMTR RESSURE TRMTR O

p-[G1 1 % 'II l

e,'s

(

tr*i y y 7v yy f

- v MW42 Co-:

N' "B

___J

~-cm I

i I

8 PVST l

I i

t OPEN y CLOSE OPEN

" CLOSE y

8702B-B 8701A-A' Notes:

1.

The interlock shown in dotted lines indicates the method of applying diverse principles.,

TRMTR - Transmitter PVST - Pressurizer Vapor Space Temperature

r

.d ' i '

FIGURE IV-3 EXISTING OPEN PERMISSIVE ACTUATION CIRCUITRY AND VALVE OPERATOR POWER SUPPLY BLOCK DIAGRAM 600V MCC 403 PT PCS - B ASC - B CUBICLE PP FV-V3 1

MOV PC 8702 B-B 600V MCC

(

40s PT PCS - B ASC - B CUBICLE PP FV-V2 MOV PC 8701 B-B 600V MCC 402 PT PCS - A ASC - A CUBICLE PP FU-G2 TS MOV PC 8702 A-A 600V MCC 402 PT PCS - A ASC - A CUBICLE PP FU-TS TS I0V PC 8701 A-A TS - Pressurizer Vapor Space Temp. Sensor PT - Wide Range RCS Pressure Transmitter

. ASC - Auxiliary Safeguards Cabinet PCS - Process Control System PP - Power Penetration MCC - Motor Cor. trol Center MOV - Motor Operated Valve (RHR System Inlet PC - Control Penetration Isolation Valve)

FIGURE IV-4 Rev.1,10/31/78 PROPOSED AUT0-CLOSURE INTERLOCK ACTUATION CIRCUITRY' AND VALVE OPERATOR POWER SUPPLY BLOCK OIAGRAM 9

600V MCC 403 PT PCS - B ASC - B CUBICLE PP FV-V3 MOV PC

~

8702 B-B 600V MCC 4

PT PCS - B ASC - B CUBICLE PP FV-V2 N

8 8

PC 8701 B-B teV C C 1 1 E

E y,-

600V MCC 402 PT PCS - A ASC - A CUBICLE PP FU-G2 10V l

PC 8702 A-A 600V MCC 402 PT PCS - A ASC - A FU-TS PC

!OV I

8701 A-A An Isolation device will be added to ensure channel independence requirement of the IEEE-279,1971 criteria at these valves.

OMS ALARM LOGIC DIAGRAM Figure IV-5 PT 403 PT 402 A

d

• /.>. -

MAINCNTROLB0kRD 0FF SELECTOR SWITCH 4

4

' PSIG 450

-20

.j

~

I

\\

[

l l

l f

RCS SOLID PRESSURE HIGH e

-