ML20206D853
| ML20206D853 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/03/1987 |
| From: | Gallagher J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Muller D NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8704130444 | |
| Download: ML20206D853 (16) | |
Text
I.
PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 (2151 841 5001 JOSEPH W. G ALLAGHER
.J!*.11".'/.'.".'"7...
Apri1 3, 1987 Docket Nos. 50-277 50-278 Mr. Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, DC 20555
SUBJECT:
ATWS Rule (10 CFR Section 50.62)
Peach Bottom Atomic Power Station Modifications
Reference:
Letter from D.
R. Muller, NRC, to E. G. Bauer, PECo, dated February 3, 1987
Dear Mr. Muller:
The referenced letter requested additional design information to demonstrate the adequacy of our proposed modifications to comply with 10 CFR Sections 50.62(c)(3) and 50.62(c)(5).
The items from your letter requesting additional information are restated herein followed by our response.
The ATWS Rule requires compliance by the second refuel outage following the effective date of the regulation.
For Peach Bottom Unit 3, the next refuel outage represents the second outage.
Accordingly, implementation of the ATWS modifications is scheduled and a timely review and approval of the ATWS design by the NRC is respectfully requested.
We propose, if necessary, a meeting with the NRC staff, following review of this submittal, to resolve any questions or concerns which could delay NRC approval.
i fo$
43 8704130444 870403
(
PDR ADOCK 05000277 P
pyg i
Mr. Daniel R. Muller, Director April 3, 1987 Page 2 ITEM 1:
The documentation to describe the analysis and/or cests to verify that the Alternate Rod Injection (ARI) system function time will begin within 15 seconds and be completed within 25 seconds from ARI initiation.
RESPONSE
The following discussion and Attachment A describe the ARI function time analysis.
The analysis shows that all control rods will begin motion within 14 seconds and will complete motion within 24 seconds, including instrument response time.
The ARI system response time consists of three components:
1)
Time from ARI initiation to opening of ARI vent valves (instrument and logic response).
2)
Time from ARI vent valves opening until the scram exhaust valves open and rod motion begins.
3)
Time from start of rod motion until rods are fully inserted.
Each of the components was determined individually and is discussed below.
The instrument and logic response time, including ARI vent valves opening time, is less than 3.5 seconds.
In order to determine the time from ARI vent valves opening until the scram exhaust valve opens and rod motion begins, a computer model was developed to simulate the scram air header venting characteristics.
Attachment A is a summary of the depressurization study.
The results of the study indicate that the longest time for an exhaust scram valve to open is 10.5 seconds after ARI vent valves opening, based on the smallest bleed hole size in the scram solenoid valves, a 20% error in the flow coefficients, and initial system temperature of 50F.
Therefore, rod motion will begin within 14 seconds after ARI initiation.
It has been concluded, based on General Electric Company experience and actual pre-operational test data on Limerick Generating Station, that the total time for the rods to fully insert once motion has begun will be less than ten seconds.
Therefore, since rod motion will begin within 14 seconds, the rods will be fully inserted within 24 seconds after ARI initiation.
Mr. Dr.niel R. Muller, Director April 3, 1987 Page 3 ITEM 2:
The documentation to describe the ARI System should also include:
a.
a complete set of piping and instrumentation diagrams b.
a complete set of electrical schematic diagrams from sensors to the final actuated devices, and c.
the interface with the Reactor Trip System (RTS), the scram discharge volume system, or other safety-related systems.
RESPONSE
A set of piping and instrumentation diagrams and electrical schematic diagrams necessary to describe the ARI/RPT system, including the interface with the Emergency Core Cooling System (ECCS), were sent directly to the NRC Project Manager on March 4, 1987 and March 12, 1987.
A draft revision to one drawing was sent to the NRC Project Manager on March 23, 1987.
There is no electrical interface with the RTS (Peach Bottom's Reactor Protection System) or scram discharge volume.
ITEM 3:
The documentation to describe the recirculation pump trip (RPT) system should also include:
a.
a complete set of piping and instrumentation diagrams b.
a complete set of electrical schematic diagrams from sensors to the final actuated devices, and c.
the interface with other safety-related systems.
RESPONSE
The response to Item 2 is applicable to Item 3 as well.
ITEM 4:
The qualification information on isolation devices:
a.
For the type of device used to accomplish electrical isolation, describe the specific testing performed to demonstrate that the device is acceptable for its application (s).
This description should include elementary diagrams
Mr. Daniel R. Muller, Director April 3, 1987 Page 4 a
when necessary to indicate the test 2
configuration and how the maximum credible faults were applied to the devices.
J b.
Data to verify that the maximum credible faults applied during the test were the maximum voltage / current to which the device could be i
exposed, and define how the maximum i
voltage / current was determined.
I c.
Data to verify that the maximum credible fault was applied to the output of the device in the transverse mode (between signal and return) and other faults were considered (i.e., open and short circuits).
i i
d.
Define the pass / fail acceptance criteria for each type of device.
i e.
Provide a commitment that the isolation devices comply with the environment qualifications (10 CFR 50.49) and with the seismic qualifications which were the basis for plant licensing.
j l
f.
Provide a description of the measures taken to i
protect the safety systems from electrical interference (i.e., Electrostatic Coupling, EMI, Common Mode and Crosstalk) that may be generated i
by the ATWS circuits.
l g.
Provide information to verify that the Class lE isolator is powered from a Class lE source.
RESPONSE
}
The Peach Bottom Atomic Power Station was designed and constructed using relay contact isolation between Class lE and non-lE circuits.
A Foxboro Model 2AO-L2C-R relay contact output f
isolator will be used to isolate the Emergency Core Cooling System Class lE signals from the non-lE ARI/ Recirculating Pump Trip (RPT) system.
An instruction booklet for this device is i
enclosed as Attachment B.
The Foxboro 2AO-L2C-R isolator meets the seismic and environmental qualification requirements which are the basis for i
Peach Bottom licensing.
The isolator is located in a mild environment, the Cable Spreading Room.
During qualification i
testing, 600 VAC was applied to the output contacts of the isolator without damage to the isolator.
Power supplies to control panel and cabinets housing ARI/RPT equipment are either 125 VDC or 120 VAC; therefore, testing of the relay contact 4
isolator at 600 VAC is satisfactory.
Foxboro Test Report Number i
i 1,
l.
Mr.' Daniel R. Muller, Director April 3, 1987 Page 5 T7-6082, which is proprietary to Foxboro Company, documents the qualification test.
i i
ARI/RPT circuits are fused to protect power supplies and wiring in.the event of a short circuit.
The fusing will limit the current associated with faults and, therefore, prevent any credible short circuit from affecting safety related circuits 1
associated with the relay.
The relay isolation provided at Peach Bottom has proven suitable to protect safety systems from electrical interference generated by other equipment.
Addition of new ATWS circuits is not expected to create detrimental electrical-interferences based on i
previous Peach Bottom experience.
i j.
The relay isolator is powered by the ECCS power supplies which j
are Clas,s lE power circuits.
j ITEM 5:
The proposed plant technical specification for ARI function time and the ARI system components.
(Similar i
to the instrumentation for RPT system in current I
technical specifications)
L
RESPONSE
Licensee is preparing a License Amendment Application to incorporate ARI into the Technical Specifications.
The proposed Technical Specifications will be on Tables 3.2.G and 4.2.G which j
presently apply only to RPT instrumentation.
Licensee will propose that the requirements for ARI and RPT be identical.
This proposal is consistent with the recommendation of the BWR Owners' Group ATWS Compliance Alternatives Committee that ARI Technical Specifications similar to current RPT Technical Specifications j
would be adequate.
Attachments C and D are the draft proposed i
Technical Specifications that we expect to submit through the j
normal license amendment application process.
An instrumentation calibration, functional check, and logic system functional test will be required once per operating cycle (Table 4.2.G).
The 3
proposed Technical Specifications for ARI/RPT also reflect t
revisions of the current action statements to impose a time limit l
and to impose an additional restriction in the event one of the j
two ARI/RPT trip systems is inoperable (Table 3.2.G).
Licensee does not intend to propose a Technical Specification j
function time test requirement for the ARI system.
Considering that ARI constitutes a second backup to the normal RPS scram i
initiation equipment and considering the surveillance j
requirements proposed for the instrumentation, Licensee does not believe that additional testing is warranted.
i I
4 1
i
Mr. Daniel R. Muller, Director April 3, 1987 Page 6 Currently the NRC's Technical Specification Improvement Committee is considering criteria developed by the BWR Owners' Group for determining the content of Technical Specifications.
Licensee believes that a decision to require an ARI Technical Specification, specifically for function time testing, should be assessed in accordance with the proposed criteria of the Committee.
Should changes to the Technical Specification be considered necessary, Licensee believes they should be handled as a generic issue for the industry.
4 ITEM 6:
The Maintenance Bypass and the means for Bypassing.
RESPONSE
The ARI/RPT trip system is fully testable up to and including the final actuation devices without causing an ARI ccram or recirculating pump trip (recirculating pump breaker trip mechanism excluded).
An ECCS instrument channel which provides the ARI/RPT input signal may be bypassed by plugging in test leads at the transmitter input test jacks located in cabinets C818 or C819.
Plugging test leads into the test jacks disconnects the'ECCS transmitter input, automatically actuates an alarm in the control room, and permits the introduction of a test signal.
When an instrument channel within cabinets C818 or C819 is to be tested, an alarm in the control room may also be manually initiated with a switch in the cabinet.
Testing of a single instrument channel will not cause an ARI/RPT trip nor will it prevent an ARI/RPT trip should valid trip signals occur on the instrument channels remaining in service.
Testing of a single instrument channel will trip only one of the two ARI/RPT trip systems.
The operator can verify a channel trip by observing the "ARI/RPT Channel A or B Trip" annunciator window l
light up.
The operator can also verify ARI vont valve operation by checking the valve position indicating lights.
A red light illuminated indicates that the ARI vent valve has moved to the open position.
After the tested channel has been reset, the "ARI/RPT Channel A or B Trip" annunciator can be reset and the red valve position indicating light will go out if the valve has returned to its normally closed position.
Testing of the other channels would proceed similarly.
ITEM 7:
The information readout to the control room operator for the ARI and RPT systems.
n.,
-,r.-r,--r-+----n--.----y-..- _ -, - -,-
- - - - - - - - - - - -, - -. - - ~,
y-
Mr. Dtniel R. Muller, Director April 3, 1987 Page 7
RESPONSE
1 Below is a tabulation of indications which will be available to the. operators in the control room.
Alarms Reference ARI/RPT Channel A or B Trip 6280-E-332 ARI/RPT Initiated 6280-E-332 l
ARI/RPT Power System Trouble 6280-E-332 ECCS LVL/ PRESS TRIP / MEAS In Test 6280-E-250 Indicating Lights Reference Red Light SV141A Tripped 6280-E-3030 Red Light SV142A Tripped 6280-E-3030 Green Light SV141A, SV142A Normal 6280-E-3030 Red Light SV141B Tripped 6280-E-3030 Red Light SV142B Tripped 6280-E-3030 Green Light SV1-41B, SVJ42B Normal 6280-E-3030 Red Light Recirc M-G Set A Drive Breaker Closed 6280-E-171 Green Light Recirc M-G Set A Drive Breaker Open 6280-E-171 l
Red Light Recirc M-G Set B Drive Breaker Closed 6280-E-171 Green Light Recirc M-G Set B Drive Breaker Open 6280-E-171 If you have any questions or require additional information, please do not hesitate to contact us.
Very truly yours, v)
Attachments:
A, B, C and D cc:
Addressee Dr. T. E. Murley, Administrator, NRC Region I T. P. Johnson, Resident Site Inspector R. J. Clark, Project Manager, USNRC
'Attachannt-A E-*
Psgn 1 of 3 Docket Nos.'50-277 50-278 l-i PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 SCRAM AIR HEADER DEPRESSURIZATION STUDY
SUMMARY
A recent NRC rule requires that an Alternate Rod l
Insertion (ARI) system be installed at all BWRs to provide a redundant method of venting the Scram Air Header and thus causing the control rods to be inserted into the reactor.
The BWR Owners Group report, " Assessment of ATWS Compliance Alternatives" (NEDC-30921 dated July 1985), provided the prime performance characteristic of an ARI system among other items.
This characteristic is that rod insertion motion will begin within 15 seconds and be completed within 25 seconds from ARI initiation.
The Control Rod Drive System is composed of 185 Hydraulic Control Units (HCOs), each containing a pair of pneumatically operated scram valves (inlet / exhaust).
During normal operation, the scram valve operators are pressurized with
)
instrument air through a series of interconnected headers to keep the scram valves closed.
Each pair of scram valve operators is connected through the scram solenoid valves and various fittings to 3/4-inch instrument air branch headers.
The scram solenoid valves are normally energized, permitting the air pressure to i
reach the scram valve operators and keep the scram valves closed.
{
During a scram, the scram solenoid valves are de-energized, venting the air from the pneumatic operators to atmosphere.
During an ARI scram, the air is vented to atmosphere through two i
pairs of ARI vent valves.
This method requires that the air i
pressurizing the scram valve operators must vent through two l
bleed holes within one scram solenoid valve.
l An analysis was performed to calculate the time required for ARI venting.
The differential and auxiliary equations for the model were solved on "ECo's mainframe computer l
using the Advanced Continuous Simulation Language.
The model was l
benchmarked against test data from both Peach Bottom and Limerick.
t i
The study consisted of the following:
i i
1.
A field survey was performed to determine the piping i
volume between the ARI vent valves and the scram l
i a
s
Attcchm:nt A Paga 2 of 3 Docket Nos. 50-277 50-278 2.
The volume between the scram solenoid valves and the scram valve operator diaphragms with the scram valve operators pressurized (i.e., the diaphragm is depressed) was determined generically by General Electric Company.
3.
Flow was conservatively assumed to be isothermal, thus, maximizing the venting time.
When there is no adiabatic cooling, the pressure drops more slowly because there is no effect of temperature on fluid density.
4.
The incompressible Darcy flow equation was used because the pressure drop in each section of header is less than ten percent of the upstream pressure.
S.
The K-factor (velocity head) method for calculating local resistance to flow was used because of the varying pipe diameters and the variety of fittings for which the K-factor is available.
6.
Flow through the ARI vent valves was treated by the
ISA compressible flow valve equations.
7.
The ideal gas law was used to relate mass, volume and temperature to pressure.
8.
Venting through the bleed holes in the scram solenoid valves was analyzed using the K-factor approach with the compressible form of the Darcy equation.
9.
Each pneumatic header was considered to be a series of four restrictor/ volume modules; each region contained the scram valve operators and tubing leading to the collection header, the resistance of this tubing, the volume associated with part of the collection header, and a resistance of the collection header.
10.
Resistance to flow was treated as a concentrated or lumped resistance in accordance with Crane Technical Publication Number 410.
The two largest resistances to flow which are treated by compressible flow equations are:
a)
The bleed holes in the scram solenoid valves.
b)
The two pairs of ARI vent valves.
Attachm2nt A Pag 3 3 of 3 Docket Nos. 50-277 50-278 The flow through the bleed holes in the scram solenoid valves is modeled using the Darcy compressible flow equation and K-factors.
Flow through the ARI vent valves is modeled using the ISA compressible flow equation.
11.
The initial conditions were assumed to be:
Pressure
= 75 psig (maximum normal header pressure)
Temperature = 50 F (minimum anticipated ambient temperature) 12.
The exhaust scram valves open when pressure on the operator diaphragm is between 31 and 40 psig.
The results of the analysis indicate that the pressure on the scram valve operator diaphragm furthest from the ARI vent valves will drop to 30 psig within 10.5 seconds.
This includes a conservative allowance for the dimensional tolerance of the grommet in the bleed holes in the scram solenoid valves and a 20%
error in the flow coefficients.
_~
~.
ATTAQMNP B Dccket NOs. 50-277 Page 1 Of 4 50-278 MI 2A0-113 Instruction muny m
- CONTACT OUTPUT ISOLATOR -
Model 2A0-L2C-R (Relay Output)
Canersl
_,...4 g
NEST The Pelay Contact Output Isolator is aa y denW ASSEMBLY input / output component locatej in the nest
,(
g ascembly. The relay isolator is used ac an s
inte rf tce between a 1ct. level signal such V j9 9 p lNPUT as frca on alarm or controller, and a hich p
p y 'Q lW T, SIGNAL power load.
CONNECTIONS
~ y 1 1 y-
.(
e The relay isolator has a maximum of y
four relaya and requires dual module space.
e
^ ',
The input (s) may be a logic signal, tran-sistor cwitch or a dry contact closure. It has one input and one output per relay.
.y'
- g#bD w~
g
,,M OUTPUT The isolator slides into the nest ascem-bly and is held by tuo captive screws en SIGNAL F
- 4 i, g3 CONNECTIONS the top and bottem of the fr:nt plate.
The W
isolator receives its pcwer frc= the supply bus in the nest asrembly. Tne signal con-p' g@
nectionc are made on the fr. t plate.
- c CONTACT
~P OUTPUT f,
j
, [l ISOLATOR g'.-
Wiring e'
The signal c;nnections are located on the front plate of the 1salutor. The tcp c:nnections are for O
O Inputs A, B, C m il D: the louer connt.ctionc are for shpur e l Cutputs A, B, C and D. The input to the isolater can
+
be a logic signal, transistor switch or a dry contact.
- *hY
- _ 3@ l 'N'UT O The output is pecvided by internal contacts of the l +*
relay. The MC (r.ormally cloced) contact is closed G
when the relay is de-energized; the NO (normally cren) 3
-30 lINPufC Contact 18 closel when the relay ic energized. The l f-
+
input A
+
0 0
cutrut connectior.3 are chown in the illustration below.
The input specificaticas are as follows:
(
O O
O O
Input High = 1) V min., 33 V max., at 553 a min.
O O
Input Lcw = 0.5 V max., at 53 C max.
e 0
gp,
I ocate I ccul o
+ l ccu
+
c output
,1 supra i i
i e
rn No!
lNe he No g
g eewl g gof- *-
- + lceu c
outeur ourPut A
e i
C
.po e s Nol INe 0
"0" 5 A max at 12] V ao cr 23 V c:
(
rmmT Output
=
2 A max. at 21] V a:
0 F0-1 a m,x. nt 43 y e i
1 J.5 A max. at 125 V de FODORO NorZ: A protective cover for the lower six termintls muct be attached whea circuita are alive.
y Docket Nos. 50-277 A'IT1CRENT B 50-278 MI 2AO-113 Page 2 Page 2 of (
Oceratienal Check If Isolator is removed from the nest assembly, connect the de power at the bus connector as shown on bottom of page.
Equipment Needed
,l O
O (For Operational Check and/or Troubleshooting)
,,,yy, l DC Voltmeter, Triplett 630 of equivalent
-,fg I '"*7 8
.ggl*
DC Power Supply, +15 V,100 mA N
'*NT A ~3 f+3+ - C'
-+
Juwpen For bench operational check I
l7 l immi c
+
or troubleshooting
+
0 0
0 0
0 0
NOTE: 'Ihe Isolator may have up to four ne no relays mounted on the assembly board.
+ lcou our,Pur The following operational check is for i>r coul one relay. Repeat the procedure for no]
e a
g,e C0" each additional relay
.n
- 1. Connect a voltmeter across the input 3e a@
"0.L.
"C terminals. It should read +15 volts, coul o f-Te
+
ceu oureur If correct, proceed to Step 2.
If e
c ounin a mot lwe incorrect, check fuse F1 on socket of relay Kl.
See location of fuse on component diagram on Page 4.
- 2. Connect a jumper across Input A and 0
Y an ohmmeter at OutFut A terminals
(- and +) as shown at right.
- 4. If fuse is good, alternately disconnect
- 3. The ohmneter should read zero ohms.
and connect one lead of the jumper. The If cor rect, the relay is operating relay should.make a click each time the normally. If incorrect, check fuse lead of the jumper is connected on the F1.
If fuse is blown, check the diode input terminal. If the relay does not across the relay coil for a short.
energize, replace the relay.
Calibration Wirina - Component Unit Removed From Nest The isolator de power is supplied through a bus strip in the nest assembly. When the isolator is removed from the nest, the de power is disconnected.
If operational check or troubleshooting is needed, l
/
mske the component supply (+15 volts) connections at
{ f
\\
the power bus plug as shown below. A power cable (Fart Number NO305Z3) is available in the System Calibrator to make the power connections at the bus A
plug. The signal connections on the front plate P
remain the same as sheen under operational check.
k
' 15 VOLTS D-C
+
COMPONENT SUPPLY M
l COMMON i 2 3 4 a8
' E' N L~!
- j POWER BUS PLUG (PART NUMBER NO300FX)
Rest View
r.;,.
_a Docket Nos. 50-277
- /
ATTAOIMENI B 50-278
- g Page 3 of 4 MI 2AO-113 Page 3 Schematic Diagram 10102LH (For Component Diagram, See Page 4)
T PI M1
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p (TPUT A CRI 'j[
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Ela t_ _ _ _I s
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K2
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l l5 Ell g.
OUTPUT s pl
> (rc2)
IN645 i
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TGI)
IN645 l
pl 7 E'S l
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4 ES INPUTC (TG3)
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OUTPUT 0 g
@~p CR41[
0 QG2)
IN645 g,
f ~~l LEGENO:
4 El input O SCREW TERNINAL CONNECTION
(~
0C4)
O BUS CONNECTOR PIN f OIAGNOSTic TEST PolNT E2 Parts List for Output Contact Isolator Relay Output - 2AO-L2C-R Item De sc ript ion Psrt No.
CR1, CR2, Diodes, Type IN645 N0258AF CR3, CR4 K1, K2,4 Relays N0152CK K3, K
(_.
F1 Fuse, 1/4 A N0262AB Termination Assembly (front plate)
NO300FP Power Bus Plug (rear of termination NO303FL assembly)
Relay socket assembly N0152LK
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e-l Attachment C Docket Nos. 50-277 50-278 TASLE 3.2.G INSTRUMENTATION THAT INITIATES ALTERNATE ROD INSERTION I
AND RECIRCULATION PUMP TRIP t
l l
I Minimum No.
Instrument Trip Level Setting Number of Ins t rut.ent Action i
l of Operable Channels Providen i
Instrument by Design Channels Per Trip System l
(1) 1 Reactor High Pressure i 1120 psig 4
(2)(3) 1 Reactor Low-Low water 1 -48 in. indicated 4
(2)(3)
Level level I
%4 Notes for Table 3.2.G
-.c 3
1.
Whenever the reactor is in the RUN Mode, two trip systems. each Containing at least one reactor pressure channel and one reactor level channel. shall oe operable.
2.
If the minimum nunner of operable instrument channels for one trip system cannot be met --
t ';
2,
- - : _. -_: : _- " : ', the effected trip system shall be placed in the 2
tripped condition within one hour.
3.
'If the minimum numoer of operable instrument channels for both trip systems cannot be met. the reactor shall De placed in a moce other than the RUN Mode within the nemt 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
L
ATIN39ENT D -
Docket Nos. 50-277 50-278 TABLE 4.2.G l
WINit0Utf TEST AND CALIBRATioh FREGUENCY FOR ALTERNATE ROD INSERTION AND RECTRCULATION PUMP TRIP 1-.,
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