ML20151Z032
| ML20151Z032 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/23/1988 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 TAC-51073, TAC-51074, TAC-51075, NUDOCS 8808290141 | |
| Download: ML20151Z032 (19) | |
Text
TENNESSEE VALLEY AUTHORITY CHATTANOOG A. TENNESSEE 374o1 SN 157B Lookout Place AUG 231988 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
In the Matter of
)
Docket Nos. 50-259 Tennessee Valley Authority
)
50-260 50-296 BROWHS FERRY HUCLEAR PLANT (BFH) - RESPONSE TO NRC'S SAFETY EVALUATION REPORT ON REGULATORY GUIDE 1.97 COMPLIANCE AS APPLIED TO EMERGENCY RESPONSE FACILITIES DATED JUNE 23, 1988 - TAC 51073, 51074, AND 51075 The subject Cafety Evaluation Report (SER) required TVA to include instruments used to monitor seven variables in our Environmental Qualification (EQ)
Program. TVA had requested an exception from the Regulatory Guide (R.G.) 1.97 classification for these instmments in a letter to NRC dated April 30, 1984.
Subsequent to receipt of the subject SER, a telecon was held between TVA and NRC to discuss the impact of the SER on BFN restart.
This telecon resulted in BFN providing further justification for our requested exceptions from R.G. 1.97, such as the use of alternate EQ quallflod instruments to monitor the required variables, or providing a schedule for EQ qualifying the required instrumentation.
Enclocure 1 provides TVA's position, justification, and schedule for compliance, if applicable, for each of the seven variables. Enclosure 2 provides revised individual instwment description sheets, if applicable, to replace those provided in our submittal dated April 30, 1984.
Summary statements of commitments contained in this submittal are provided in enclosure 3.
In regards to EQ of neutron monitoring instrumentation, BFN's current position is consistent with the Boiling Water Reactor Owners Group generic resolution documented in NEDO-31558 ("Position on NRC Regulatory Guide 1.97, Revision 3, Requirements for Post-Accident Neutron Monitoring System"). This document was transmitted to NRC by letter on April 1, 1988.
In this document, specific design criteria were proposed as an acceptable alternate to the Category 1 requirements specified in Regulatory Guide 1.97.
Some of these criteria will require plant specific evaluations. BFN's evaluations of these criteria are pending NRC acceptance of this generic resolution.
8806290141 880823 PDR ADOCK 05000259 di p
\\
An Equal Opportunity Employer
,' U.S. Nuclear Regulatory Cornission
/\\UG 231988 j
Please refer any questions concerning this submittal to M. J. May, BFN Site Licensing (205) 729-3570.
Very truly yours, j
TENNESSEE VALLEY AUTHORITY C(
l R. Gri ey, Manager Nuclear Licensing and Regulatory Affairs Enclosures cc (Enclosures):
Ms. S. C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. F. R. McCoy, Assistant Director for Inspection Prograns TVA Projects Division U.S. Nuclear Pegulatory Commission Region 11 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Browns Ferry Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35611 4
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ENCLOSURE 1 BROWNS FERRY NUCLEAR PLANT DISPOSITION OF REGULATORY GUIDE 1.97 VARIABLES FOR ENVIRONMENTAL QUALIFICATION This enclosure contains TVA's position on the inclusion of certain Regulatory Guide (R.G.) 1.97 variables in the Environmental Qualification (EQ) program as requested by the NRC letter dated June 23, 1988. provides revised individual instrument description sheets to repl' ace those provided in our
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original R.G.
1.97 submittal dated April 30, 1984.
VARIABLE D15 - CORE SPRAY SYSTEM FLOW TVA Position TVA will include this variable in the EQ program. contains a revised individual instrument description sheet for variable D15 to replace the sheet provided in our original R.C. 1.97 submittal dated April 30, 1984.
Schedule Unit 1 - Bofore restart Unit 2 - Before operation in cycle 7 Unit 3 - Before restart Justification The core spray system flow parameter is used to monitor the performance of a pair of core spray pumps discharging into a common spray header.
Each reactor has two such systems, either of which can provide adequate core cooling a short time after shutdown. The system is used at full flow to spray the coro or can be throttled to maintain water level postaccident. To verify the performance of the core spray function of the system. "pump running" status lights, pump amperage, and flow path valvo alignment (full open) are environmentally qualified alternatives. The pump switchgear and electrical boards are located in a mild environment.
The valvos in the flow path are either normally open or have motor operators which are included in the EQ program.
Although the valvo position indication function is not specifically considered under the EQ program, it originatos from the same limit switch assembly that controls the valve, and is thereforo expected to function in a l
postaccident environment. To verify the water level restoration / maintenance function of core spray system as specified in the Emergency Operating Instructions (EOIs), the reactor coolant level and pressure takes procedence over core spray system flow. The nood to throttic valvos and start /stop pumps is primarily based upon increasing / decreasing reactor coolant levol, and the l
reactor coolant pressure being in the range of coro spray system dischargo pressure capability.
Both coolant reactor level and pressure (variables D4 and D6) are included in the EQ program.
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. The minimum flow valve, which changes position upon detection of core spray system flow, is also a confirmation of system' performance and is included in the EQ program.
VARIABLE D16/D19 - LOW PRESSURE COOLANT INJECTION (LPCI) FLOW / RESIDUAL llEAT REMOVAL (R]IR) SYSTEM FLOW TVA Position:
TVA will include this variable in the EQ program.
Enclosuro 2 contains a revised individual instrument description sheet for variable D16 to replace the shcot provided in our original R.G. 1.97 submittal dated April 30, 1984.
Schedule:
Unit 1 - Beforo restart Unit 2 - Before operation of cycle 7 L' nit 3 - Before restart Justification The same instrument is used to satisfy LPCI flow (D16), RllR System flow (D19),
drywell spray flow (D8), and suppression pool spray flow (D3) variables.
In general, the RilR System functions can be monitored by pump breaker status, pump amperage and valve alignment for the various flow paths.
The pump switchgear and electrical boards are in a mild environment. The valves in the flow paths are either stationary before and during the accident or have motor operators which are included in the EQ program. 'Although the valvo position indication function is not specifically considered under the EQ program, it originates from the same limit switch assembly as the valvo control functions and is therefore expected to function postaccident.
Each function of RHR is further discussed separately below.
LpCI Flow - The purpose of this variable is to monitor operation of the RilR System when injecting water into the reactor vescol.
The RllR System has two separato loops, each having two pumps and heat exchangers sharing common dischacCo paths to the reactor vessel.
When used to restore / maintain reactor coolant level, the reactor coolant level and pressuco tako procedence over injection flow. The need to throttle valves or start /stop pumps is primarily based upon increasing / decreasing reactor coolant level as specified in the E01s and the reactor coolant pressure being in the range of RilR System dischargo pressure capability. Both reactor coolant level and pressure (variables D4 and D6) are included in the EQ program.
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- RilR Oystem Flow - The purpose of this variable is to monitne the performance of the RilR System when being used to remove decay heat from the primary containment. The RllR System consists of two loops, each having two pumps and two heat exchangers sharing a common discharge path to the suppression pool.
This is the path specifically designed for removing heat specified by the EOIs although injer* *.on into the reactor vessel via the LpCI path and allowing water to flow t.o the suppression pool via a breach in the primary system or
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safety relief valves also removes decay heat.
The performance of this system is confirmed by the trend of suppression pool water temperature (variable D6) which is included in the EQ program.
Drywell Spray Flow - The purpose of this variable is to monitor operation of the EllR System when it is being used to spray the drywell.
The RilR System consists of two loops, each having two pumps and two heat exchangers sharing a common discharge path to separate spray headers. The system is initiated to control drywell temperature in design basis accidents and to further control containment pcessure in beyond design basis scenarios as specified in the E01s. The performance of the system is directly confitved by drywell atmosphere temperature (variable A3) and drywell pressure (variable A2) response. Both of those variables are included in the EQ program.
Suppression pool Spray Flow - The purpose of this variable is to monitor the perforrance of the RllR System when it is being used to spray the suppression pool. Each RilR loop, as discussed above, is capable of spraying the suppression pool using separate spray headers.
Suppression pool spray is initiated in conjunction with drywell spray to control containment pressure.
The suppression pool spray performance can be directly c.anitored by drywell pressure response (variable A2), which is included in t,te EQ program.
VARIABLE D20 - RilR llEAT EXCllANGER OUTLET TEHpERATURE TVA position This variabic has been classified as category 3 in our previous subulttals on the basis that no operator action is based upon RllR heat exchanger outlet toeperature. The inclusion of this variable in the EQ program would net be a significant operator enhancement and therefore we request that it not bo included in the EQ program.
Schedule N/A Justification The RilR heat exchangers out.let temperature is for the purpose of monitoring EllR contalnment heat removal performance.
The variable can be used to determine if an individual heat exchanger is removing heat. Ilowever, the torus
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1 temperature trend can also be used to monitee the performance of the combination of heat exchangers being used. Tlie suppression pool temperature, suppression pool level, drywell temperature and pressure and reactor coolant level and pressure are primary indicatore to the operator of the heat energy remaining within the primary containment. The Emergency Operating Instructions key on these variables and each of these variables is included in the EQ program. Thus, a qualified alternate set, of parameters exists which is more useful to the operator.
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VARIABLE D21 - Cn0 LING WATER TEMPERATURE TO ENGINEERED SAFETY FEATURES (ESP)
SYSTEM CORPONENTJ TVA Position:
This variable was originally interpreted to be inlet water tet.perature to RHR heat exchangers.
After further review, it was determined that this variable applies to all ESF con.ponents requiring raw water for cooling. The cooling water for ES7 components, including RHR heat exchangers, is drawn from the Tennessee Rivee.
Instrumentation to monitor temperature in the forebay from which the RHRSW and emergency equipment cooling water (EECW) pumps take suction is available in the unit 2 control room. This parameter can change only over long periods of time and it is sufficient to have indication in only one location in the control complex.
The instrument und associated components are located in a mild environment and thus need not be included in the EQ program.
Thq cable for this Instrument passes through the-unit 3 reactor bu ild inr,.
This cable will be quallflod prior to unit 3 restart. contains a revised individual instrument description sheet for variable D21 to replace the sheet provided in our original R.G. 1.9/ submittal dated April 30, 1984.
Schedulo:
Unit 3 - Before r.2 start Justification R.G. 1.97 specifica the range of this instrumcnt as 40' F to 200* F.
This range appears to be selected for plants with closed cyclo cooling systems.
At UFN the cooling water temperM.-Ja can be affected only by tho ambient rivor water and the water stornd in the cooling tower dischargo channel. Neither of those sources of water eWeeed 9F during plant opet At'.on.
Thereforo, a maximum range of 100*F is adequate.
A cooling watcr temperaturo below 90*F would not be of concern ard it is therefore adequato t o have a minimum range of 90*F.
The primary interest in this variabic to the operator is the temperaturo approaching 93*F, which is the nAximum design inject k, t
I temperature for ESF !amponents, t
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-s-VAP! ABLE D22 - COOLING WATER FLOW TO ESF SYSTEM COMPONENTS [ RESIDUAL HEAT REhaVAL SERVICE WATER (RHRSW) SYSTEM]
TVA Position:
This variable will be included in the EQ program. Enclosure 2 contains a revised individual instrument description sheet for variable D22 to replace the sheet provided in our original R.G. 1.97 sub'mittal dated April 30, 1984.
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Schedule Unit 1 - Before restart Unit 2 - Before operation in cycle 7 Unit 3 - Before restart Justification The purpose of this variable is to monitor the performance of the raw water side of the RHR heat exchangers. The system consists of four separate supply headers common to all threo units with up to two common pumps and one heat exchanuce per unit connected to each header.
Flow from the headers through each heat exchanger is controlled by opening an outlet valve on each individual host exchanger. Flow through the heat exchangers can to alternately verified by pamp breaker status lights, pump motor amperage, and valve alignment. The pump switch gear and electrical boards are in a mild environment.,The valves in the flow path are either stationary before and during an accident or have motor operators which are included in the EQ program or are located in a mild environment.
Although valve position indicator function is not specifically considered under the EQ program, it originates from the same limit switch assembly as the valve control function and is therefore e>Tected to function postaccident.
Further, the ultimate performance of the RHRSW system is determined by monitoring tho trend of suppression pool water temperature as specified in the E01s (variable D6) which is included in the EQ program.
VARIABLE D22 - COOLING WATER FLOW TO ESF SYSTEM COMPONENTS [EMERGKNCY EQUIPMENT COOLIUG WATER (EECW))
TVA Posittor This variable has been classified as category 3 in our previous submittals on the basis that no operator action is based upon this parameter in a design basis accident. The inclusion of this variable in the EQ program would not be a significant operator enhancement; therefore, we request that it not bo included in the EQ program.
. Enclosure 2 contains a revised individual instrument description sheet for variable D22 to replace the sheet provided in our original R.C. 1.97 submittal dated April 30, 1984.
Schedule N/A Justification The purpose of this variable is to monitor the performance of the EECW system to deliver cooling water to ESF components. The system consists of two independent headers common to all three units which normally is connected to 2 punps per header, but can be connected to up to 4 pumps.
Each ESF heat load is redundantly supplied by both headers. The system has preset flow paths which are adjusted with manual valves on a periodic basis and administrative 1y controlled. Therefore, the only pertinent information as to the performance of the system is the "pump running" status.
This is given by breaker status lights and pump amperage. The pump switchgear and electrical boards are located in a mild environment. Therefore, a qualified alternative exists for EECW flow and it should not be included in the EQ program.
VARIABLE U24-EHERGENCY VENTILATION DAMPER POSITION TVA Position our submittal of April 30, 1984 listed the dampers which have status lights in the control room.
This list has been reviewed and is beinf revised to include only those dampers which perform a safety function to control radiological consequences. Of the dampers listed, several are in a mild environment and do not require inclusion in the EQ program. The posillot; indication for the dampers listed in table D24 as being in a harsh environment will bo included in the EQ program. contains a revised individual instrument description sheet for variablo D24 to replace the sheet provided in our original R.G. 1.97 submittal dated April 30, 1984.
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s Schedule Unit 1 - Before restart Unit 2 Secondary Containment and Standby Cas Treatment - Before Operation in cycle 7 Unit 3 - Before restart
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Justification BFN interprets this variable to be dampers which could release radiation to the surrounding plant environment or expose control room personnel to radiation. The purpose of these instruments is to monitor the performance of the control bay and secondary containment isolation systems and the Standby Cas Treatment (SBGT) System. Dampers in the control bay ventilation system are in a mild environment and requiro no further justification.
The secondary containment isolation system consists of redundant sets of dampers at each ventilation flow path through secondary containment. Each damper falla closed, isolation is initiated early in an accident, and the dampers cannot be reopened by the operator as long as an accident signal is present.
If a damper failed to close, no operator action could be taken to correct the condition if the dtepor were located in a harsh environment.
There is no alternate way of operating the system in response to this condition. Therefore, if damper positions were unavailable, there would be no adverso impact on safety.
The SUCT system dampers align for operation when the SBGT train with which they are associated is running.
Somo SBGT dampers are common to all three trains and operate upon a secondary containment isolation signal. The system as a whole is redundant and failure of one damper does not require any operator action to mitigate the effects, nor does it provent the overall system from performing its safety function. Thereforo, lack of damper position indication in SBGT has no adverso impact on safety.
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ENCLOSURE 2 REVISED IllDIVIDUAL INSTRUMENT DESCRIPTION SHEETS TO REPLACE THOSE PROVIDED IN ORIGINAL R.G. 1.97 OUBMITTAL DATED APRIL 30, 1984 l
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IDENTIFIER:
D15 VARIABLE:
Core Spray System Flow TYPE:
D CATEGORY:
3 (1)
INSTRUMENT NUMBER:
FI-75-21, FI-75-49 INSTRUMENT RANGE:
0 to 10,000 GPM (2)
REDUNDANCY:
N/A POWER SUPPLY Class 1E LOCATION OF DISPIAY:
Control Room SCHEDULE:
See response to NRC SER on R.G. 1.97 compliance dated June 23, 1988 REMARKO:
To be included in EQ Program
Purpose:
To monitor operation (1) See Section 1.1.2.
(2) O td 160% decir,n flow 1
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ILENTIFIER:
D16 VARIABLE:
LPCI Flow
. TYPE:
D CATEGORY:
3 (1)
INSTRUMENT NUMBER:
FI-74-50l FI-74-64 FR-74-64
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INSTRUMENT RANCE:
0 to 40,000 GPM (2)
MEDUNDANCY:
N/A POWER SUPPLY Class 1E, Non-1E Battery Backed (Recorder)
LOCATICH OF DIGPLAY:
Control Room SCHEDULE:
See response to NRC GER on R.G. 1.97 compliance dated June 23, 1988 REMARKS:
To be included in EQ Program
Purpose:
To inonitor operation (I) Oct Scotion 1.1.2.
(2) O to 200% design flow 1
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IDENTIFIER:
D21 1
VARIABLE:
Coolin5 Water Temperature to ESF Components (1)
TYPE:
D CATECORY:
3 (2, 3)
- INSTRUMENT NUMBER:
TI-27-144 INSTRUMENT RANGE:
90 to 100'F REDUNDANCY:
N/A POWER SUPPLY Non-1E Battery Backed LOCATION OF DISPLAY:
Control Room (Unit 2 only)
SCllEDULE:
See respcnse to NRC SER on R.C. 1.97 compliance dated June 23, 1988 REtLARKS:
Appropriate portion of instrument cable located in a harsh environment (U3 Rx Bid
.) will be included in EQ program 5
Pconse:
To monitor operation (1) Interpreted as temperature of water supply for RilRSW and EECW (2) See Section 1.1.2.
(3) Located in mild en'/ironment
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IDRNTIFIER:
D22 - Sheet 1 VARIABLE:
Cooling Water Flow to ESF System Components (1) (RHRSW)
TYPE: D CATEGORY:
3 (2)
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INSTRUMENT NUMBER:
FI-23-36, FI-23-42, FI-23-48, FI-23-54 (3)
INSTRUMENT RANGE:
0 to 6,000 GPM (4)
REDUNDANCY:
N/A POWER SUPPLY Class 1E LOCATION OF DISPLAY:
Control Room dCllEDULE:
See response to NRC SER on R.G. 1.97 cortpliance dated June 23, 1988 REMARKS:
Tc be included in EQ program
Purpose:
To monitor operation (1)
Interpreted as RHRSW flow to RilR heat exchangers (2)
See Section 1.1.2.
(3)
Four per unit for a total of twelvo (4)
O to 130% desige flow m
IDENTIFIER:
D22 - Sheet 2 VARIABLE:
Cooling Water Flow to ESF System Components (1) (EECW)
TYPE:
D CATEGORY:
2 (2)
INSTRUMENT NUMBER:
ii-67-3A, FI-67-6A, FI-67-9A, FI-67-12A (3;
INSTRUMENT RANGE:
0 to 7,500 GPM (4)
REDUNDANCY:
N/A POWER SUPPLY Class 1E LOCATION OF DISPLAY:
Control Room SCHEDULE:
N/A REMARKS:
Use as is
Purpose:
To monitor operation (1)
Interpreted as EECW header flow (2)
See Section 1.1.2.
(3)
Common for the three unite but each has indication in each unit (4)
O to 160% design flow
IDENTIFIER:
D24 a
VARIABLE:
Emergency Vantilation Damper Position 4-TYPE:
D CATEGORY:
3 (1)
INSTRUMENT NUMBER:
Status Lights on Control Boards (2)
INSTRUMENT RANGE:
Open-Closed REDUNDANCY :
N/A POWER SUPPLY (2)
LOCATION OF DISPLAY:
Control Room CCHEDOLE:
See response to NRC SER on R.G. 1.97 compilance dated June 23, 1988 RRHARKS:
To be included in EQ Program, as appropelate Pu rposq: To monitor operation of ventilation system.
(1) See Sectico 1.1.2.
(2) See Table D24 e
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Dampers Having Status Lights in C@ntrol Room Tablo D24 t
Power Numbers,
Description
,_ Supply Environment
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' Control Room FCO-31-150B Air supply to relay room and (1)
M units 1 and 2 control room air handling units FCO-31-150D Fresh air supply to unit 3 (1)
M FCO-31-150E Toilet room exhaust fan inlet (1)
M isolation FCO-31-150F Unit 3 toilet room exhaust fan (1)
M inlet isolation FCo-31-151 Control room (1)
M FCO-31-152 control room (1)
M Refueling and Reactor Zone FCO-64-5 Refueling zone air supply outboard (2)
M isolation FCO-64-6 Refueling zone air supply inboard (2)
M isolation FCO-64-7 Refueling zone outside air (2)
(3) isolation (unit 1 only)
PdCO-64-8 Refueling zone static pressure (2)
(3)
(unit 1 only)
FCO-64-9 Refueling zone exhaust duct (2)
H outboard isolation FCO-64-10 Refueling zone exhaust duct (2)
H inboard isolation FCO-64-44 Refueling zone exhaust to SBCT (2)
M (unit 1 only)
FCO-64-45 Refueling zone exhaust to SBGT (2)
H (unit 1 only)
FCO-64-63 Refueling zone outside air (2)
(3) isolation (unit 1 only)
PdCO-64-64 Refueling zone static pressure (2)
(3)
(unit 1 only)
FCO-64-65A Equipment access airlock inlet (1)
(4)
(
outboard (unit 1 only)
FCO-64-65B Equipment access airlock inlet (1)
(4) inboard (unit 1 only) i FCO-64-65C Equipment access airlock (1)
(4) exhaust inboard (unit 1 only) l 1
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Dampers Havinz Status Lights in Control Room Table D24 Power Numbers Description Supply Environment FCO-64-65D Equipment access airlock (1)
(4) exhaust outboard (unit 1 only)
FCO-64-13 Reactor zone air supply (2)
H
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outboard isolation FCo-64-14 Reactor zone air supply (2)
H inboard isolation FCO-64-15 Reactor zone outside (2)
(3) air isolation PdCO-64-16 Reactor zone static pressure (2)
(3)
FCO-64-40 Reactor zone exhaust to SBGT (2) 11 FCO-64-41 Reactor zone exhaust to SBGT (2)
H FCO-64-42 Reactor zone exhaust duct (2)
H inboard isolation FCO-64-43 Reactor zone exhaust duct (2)
H outboard isolation Standby Gas Treatment FCo-65-3 SBGT Train A Inlet (2)
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H FCo-65-4 SBGT Train A Decay lleat Removal
.(2)
H FCO-65-16 SBGT Filter Bank A Dutlet (2) 11 FCo-65-17 SBGT Fan A Inlet (2)
H FCo-65-22 SBGT Filter Bank A and B (2)
H Bypass FCO-65-25 SBCT' Train B Inlet (2)
H FCO-65-26 SBGT Train B Decay lleat Removal (2) 11 FCO-65-38 SbCT Filter Bank B Outlet (2)
H FCO-65-39 SBGT Fan B Inlet (2)
H FCo-65-51 SBGT Train C Inlet (2) 11 FCO-65-52 SBCT' Train C Decay lleat Removal (2)
H FCO-65-67 SBGT Train C Outlet (2)
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(1) Station Power i
(2) Class IE i
(3) Bolns Removed (4) Tagged Closed H: Hild 11: liarsh I
a Encicsues 3 List of Commitments 1.
The following unit 2 instruments will be EQ qualified before unit 2 operation in cycle 7:
FI-75-21 FI-23-36 FI-75-49 FI-23-42 FI-74-50 FI-23-48 FI-74-64 FI-23-54 FR-74-64 2.
The following unit 1 and unit 3 instruments will be EQ qualified before restart of the respective unit:
FI-75-21 FI-23-36 F1-75-49 FI-23-42 FI-74-50 FI-23-48 F1-74-64 FI-23-54 FR-74-64 3.
The status lights in the control room for the following unit 2 dampers will be EQ qualified before unit 2 operation in cycle 7:
FCO-64-9 FCo-64-43 FCO-65-26 FCO-64-10 FCO-65-3 FCO-65-38 FCO-64-44 FCO-65-4 FCo-65 1 FCO-64-45 FCo-65-16 FCo-65-51 FCO-64-40 FCo-65-17 FCO-65-52 FCO-64-41 FCO-65-22 FCO-65-67 FCO-64-42 FCO-65-25 4.
The status lights in the control room for the following unit 1 and unit 3 dampers will be'EQ qualified before restart of the respective unit:
FCO-64-9 FCO-64-43 FCO-65-26 FCO-64-10 FCO-65-3 FCo-65-38 FCO-64-44 FCO-65-4 FCO-65-39 i
FCO-64-45 FCo-65-16 FCo-65-51 FCO-64-40 FCO-65-17 FCO-65-52 FCO-64-41 FCO-65-22 FCo-65-67 FCO-64-42 FCo-65-25 i
5.
The appropriato portion of the cable running to temperature instrument TI-27-144 will be EQ qualified before restart of unit 3.
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