ML20071M274

Forwards Rev to Util 830303 Response to NRC 821112 Request for Addl Info on Fire Protection Program.Rev Clarifies Instrumentation Loops,Identified by Fire Shutdown Logic Diagram,As Being Required for Hot & Cold Shutdown

ML20071M274
Person / Time
Site:	Sequoyah
Issue date:	05/27/1983
From:	Mills L TENNESSEE VALLEY AUTHORITY
To:	Adensam E Office of Nuclear Reactor Regulation
References
NUDOCS 8305310167
Download: ML20071M274 (6)

Text

.

TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II May 27, 1983 Director of Nuclear Reactor Regulation Attention: Ms. E. Adensam, Chief Licensing Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Ms. Adensam:

In the Matter of ) Docket No. 50-327 Tennessee Valley Authority ) 50-328 Please refer to your November 12, 1981 letter to H. G. Parris which requested additional information on the fire protection program at the Sequoyah Nuclear Plant and to my subsequent response to you dated March 3, 1982.

Recent review of this information by TVA for insurance purposes has identified the need to revise the response to NRC question No. 3 The enclosed revision will clarify the instrumentation loops identifed by the Fire Shutdown Logic Diagram as being required for hot or cold shutdown.

If you have any questions concerning this matter, please get in touch with K. P. Parr at FTS 858-2685.

Very truly yours, TENNESSEE VALLEY AUTHORITY N3

. \.

L. M. Mills, Manager Nuclear Licensing Enclosure cc: U.S. Nuclear Regulatory Commission (Enclosure)

Region II Attn: Mr. James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 8305310167 80H3527 f PDR ADOCK 05000327 ( l F PDR An Equal Opportunity Employer

ENCLOSURE 3,

Provide a list of system parameters which must be monitored to assure proper plant conditions during hot shutdown and cold shutdown operation. Provide a list of instrumentation / alarms which will monitor these systes parameters and component functions in the event of fire (e.g., pressurizer pressure indicator, cold leg / hot I cg temperature, steam generator pressure and level, pump running indicators, condensate storage tank level). Verify that the applicable indicators are available in the MCR, ACR, and other remote shutdown boards.

TVA RESPONSE The parameters listed below are identified in the Fire Shutdown Logic Diagram (FSLD) as being essential for hot and cold shutdown:

Steam Generator Level Steam Generator Pressure Pressurizer Level Pressurizer Pressure Therefore, sufficient instrumentation (alarms, ir.dicators, records, etc.) regarding these parameters have been verified to be available to the operator in the MCR and, separately, in the ACR in the event of a fire within the plant.

~

The following intruments are protected fEom fire by Kaowool blankets from the reactor building wall to the MCR wall:

Steam Generator Level,_ Instrument Looos in MCR recuired by FSLU SG #1 L1-3-38,39,42 SG #2 LT-3-51,52,55 SG #3 LT-3-93,94,97,172 .

SG e4 LT-3-106,107,110 Steam Generator Pressure Instrument Loops in MCR reauired by FSLD SC di PT-1-2A,2B,5

SC #2 PT-1-9A,9B,12 l SG #3 PT-1-20A,20B,23 l SG #4 PT-1-27A,27B-30 Pressurizer Level Instrument Loops in MCR required by FSLD LT-68-339,335,320 l' -

P_re,ssurizer Pressure Instrument Loops in MCR Reauired by FSLD PT-68-340,334,323,322 l

The following instruments will also provide suf ficient data regarding the

' parameters required to function by the FSLD in the ACR. This instrumenta-tion will be available in the event of a fire in the MCR. See the response l

to concern No. 2 for MCR-ACR isolation.

l l .

) .

v

I l

Steam Generator Level Instrumentation Looos in ACR required by FSLD SC (11 LT-1-164 SC #2 LT-1-156 SC #3 LT-1-148 SC M LT-1-171 Steam Generator Pressure Instrument Leoos in ACR required by FS_LD SC #1 PT-1-1C SG #2 PT-1-8C SG #3 PT-1-19C SC M PT-1-26C Pressurizer Level Instrument Loops in ACR required by TSLD LT-68-326C, 325C l

Pressurizer Pressure Instrument Looos in ACK Required by FSLD PT-68 436C, 337C, 342C The parameters given below are not required by the fire shutdown logic to be available for the operator in the event of a fire within the plant. However, the paramet ers instrument loops have been wrapped in Kaowool blankets. Therefore, these parameters will be available to

~ ' '- -' ' '

the operator in the MCR.

Reactor Coolant System Temocrature TE-68-2A,2B: Loop 1 Hot Leg RTD Manifold Temperature

• TE-68-1: Loop 1 Hot Leg Temperature j

'TE-68-18: Loop 1 Hot Leg Temperature TE-68-25A, 25B: Loop 2 Hot Leg RTD Manifold Temperature i

• TE-68-43: Loop 3 Hot Leg Temperature.

TE-68-44A,44B: Loop 3 Hot Leg Manifold Tenperature TE-68-60: Loop 3 Cold Leg Tenperature i

TE-68-67A,67B: Loop 4 Hot Leg RTD Manifold Temperature.

• Instrument loops also available in the ACR.

Reactor Coolant Systen Flow 1 FT-68-6A,6B,6D: Loop 1 Coolant Flow FT-68-29A,29r ,290: Loop 2 Coolant Flow FT- 68-48A,498,49D: Loop 3 Coolant Flow FT-68-71A,71B,71D: Loop 4 Coolant Flow Steam Generator Feedwater Inlet Flow Loops SC #1: FI-3-35A,35B f SC #2 FT-3-48A,48B SC #3 PT-3-90A,90B SC M: FT-3-103A,103B

• • • -m==ew.,, ..,,,,,,,,p , ,, ,

e - - - - . - . ,, , -- - - -~

-~ ~---'c

T Steam Generator Steam Header Flow Loops -

SC #1: FT-1-3A,35 -

SC #2: FT-1-10A,105 SC #3: Fr- 1-21 A, 211. - "

SC 04: FT-1-28A,288 Miscellaneous Pressure Instrument Looos PT-68-66: RCS Loop #4 Hot Leg Pressure PT-1-72: High Pressure Tucbine Impulse Chamber Pressurc ,

PdT-30-42,43: Containment Pressure i Miscellaneous Level Instrument Loops LT-63-51,53 SIS RWST Level LT-63-176,177,179 Containment Level Civen below are additional parameters and instrumentation located in the ACk. The instrument cables between the reactor building and the ACR wall are not protected from fire. However, these instruments are not required by the FSLD to function in the event of fire in the ACK or between the ACR and reactor building. This instrumentation would j be us ed only in the event of a fire in the MCR and is electrically

- independent of the insrruments located in the MCR.

PT-1-1C,-8C,-19C,-26C Stian Generac' ors Nos. 1, 2, 3, 4, respectively, pr.essut44 0--1200 psig PT-3-122C, 132C Auxiliary Feeduater Pumps A&B backpressure 0-1600 psig i FI 3-142C Turbine Driven Auxiliary Feedwater Pump Flow 0-1000 gpa i

FI-3-147C,-155C,-163C,-170C Steam Generators Nos. 1, 2, 3, 4, f respectively, Auxiliary Feedvater Flow.

0-440 gym.

LT-3-148,- 156,-164,-171 Steam Generators Nos. 1, 2, 3, 4, respectively, Level 0-144 in water column PT-30-30C Containment Pressure

. +15 psig i

1E-62-80C Letdown Htx Outlet Temp j 50-150 F PT-67.r92C Char'ging Header Pressure 0-300') psig Fr-62-93C Charging Header Flow 0-200 gpa l

l l

I 8

- .-- ..- ~ - - __ . _ . .-. _ - -- - .

l LT-62-129C Volume Control Tank level 0 100I PT-63-59C,-83C,-102C,-120C . SIS Accumu.lator Tanks .Nos. 1, 2, 3, 4, respectively, Pressure 0-700 psig FT-63-173C RHR Hot Leg Inj ection 'or Recire After LOCA Flow 0-7000 gpa FT-63-91C,-92C KHR. Pump's Discharge Flow 0-4500 gpu FT-67-61C, 62C ERCW Supply Headers A&B' Flow 0-20,000 sP.

TE-68-1C,-24C,-43C,-65C RCS Loops Nos. 1, 2, 3, 4, respectively, Hot Leg Temp 0-650 F PT-68-311C RCS PRT Pressure 0-10 psig LT-68-312C . RCS PRT Level 0-100 in water column LT-68-325C,-326C RCS Pressurizer Level 0-525 in water column PT-68-336C,-337C RCS Pressurizer Pressure

- - 1700-2500 psig PT-68-342C RCS Pressurizer Pressure 0-3000 psig PT-70-17C,-24C Component Cooling Systez (CCS) Htx A&B Inlet Pressure 0-120 psig LT-70-63C,-99C CCS Surge Tank Level 0-100%

FT-70-159C,-165C CCS Flow to RHR Ntx A&B 0-6000 gym FT-70-164C CCS Misc Eqpt Supply Hde Flou 0-5000 8Pm TE-74-38C,-40C RHR Htx A&B Outlet Temp 50-400 F RR-90-210 Source Range Neutron Flux 1-106 O

e e = ,My

Therefore, we conclude that essential instrumentation, as required by the FSLD, and other desirableThis instrumentation willwill instrumentation be provide available the to the operator in the MCR or ACR.

operators'with sufficMt parameter data to obtain and maintain hot --

and cold shutdown.

e 4

J.

g

.s E .

- - - -- _ _ . _ . , __ * ' ' e - . _