L-82-429, Forwards Util Responses to NRC Concerns Re Inadequate Core Cooling Instrumentation,Per 820914 Telcon W/Nrc. Qualification Testing of Heated Junction Thermocouple Sys Scheduled for Completion by 821015
| ML17213A555 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie |
| Issue date: | 10/05/1982 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| L-82-429, NUDOCS 8210130289 | |
| Download: ML17213A555 (7) | |
Text
w REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR;8210130289 DOC OATEN'2/10/05 NOTARIZED'O FAOIL:50 389 St, Lucie Planti UniIt 2< Flor ida Power 8 Light Co, AUTH,NAME AUTHOR AFFILIATION UHRIGr R ~ E ~
Florida Power 8 Light Co, RSC IP, NAME RECIPIENT AFFILIATION EISENHUTIO ~ G.
Division of Licensing
SUBJECT:
For wards, util responses
-to NRC concerns ne inadequate core cooling instrumentationiper 820910 telcon w/NRC, Qualification testing of heated Junction ~thermocouple sys scheduled for completion by 821015, DISTRIBUTION CODE:
00018 COPIES RECEIVED>LTR P ENCL.$
SIZE:,
Li TITLE: Licensing Submittal:.PSAR/FSAR Amdts L Related Correspondence NQTES; DOCKET 05000389 RECIPIENT ID CODE/NAME A/0 LICENSNG lIC BR 43 LA
- lCOPIES, RECIPIENT LTTR ENCL ID CODE/NAME 1
0 LIC BR 0P BC 1
0
'ERSESs V ~
01 COPIES LT~TR ENCL 1
0 1
1 INTERNAL: ELO/HDS2 IE/DEP EPDS 35 NRR/DE/AEAB NRR/DE/EQB 13 NRR/OE/HGEB 30 NRR/DE/MTEB 17 NRR/OE/SAB 2Q NRR/OHFS/HFEB40 NRR/DHFS/OLB 34 NRR/DS I/ACB 26 NRR/DSI/CP8 10 NRR/DSI/ETSB 12 NRR/OS I/PSB 19 SB 23 REG ILE OQ Ml/MIB EXTERhAL:
ACRS 41 DMB/DSS (AMDTS)
LPOR 03 NS 1'C 05 1
0 1
1 1
0 3
3 2
2 1
1 1
1 1
1 1
1 1
1 1
1 1,
0 6
6 1
1 1
IE FIlE IE/OEP/EPLB 36 NRR/DE/CEB ii NRR/OE/GB 28 NRR/DE/MEB 18 NRR/OE/GAB 21 NRR/DE/SEB 25 NRR/DHFS/LOB 32 NRR/DHFS/PTRB20 NRR/DS I/ASB 27 NRR/DS I/CSB 09 NRR/DS I/ICSB 16 NRR/DS I/RAB 22 NRR/DST/LGB 33 RGN2 BNL(AMDTS ONLY)
FEMA~RCP DI V 39 NRC PDR 02 NTIS 1
1 3
1 1
2 2
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
2 2
TOTAL NUMBER OF COPIES REUUIREDi LTTR 55 ENCL 49
R )v il R
li
~ h')
<< ih'4)4 L l I h<<R'I f I<<g'(
a
))Mfg,if 4
)3 ),'kf
'i))
'R it>>
~ i>>1 "I 'MR h
1)
R It 'IIi,l f<<<<hfr'6
) R<<
It<< f
,9<<(;f'", ~fq,,h R
~
h Rg
.I Rt'p<<if hl'<<R R
II4""I f 9 f %g f
- >>I 4 "
I.,",R R Rtj, I)i 4
~, <<q) z I'I, I)'I'MR
~
)III h,
~
'I a r) R f)>>'i' i)) g Q ilr)i
', 'll, ),)) >>)i5 I
i) i'y R j I
Il
'<<h q'0 a
3
)g<<R)'
Rl ~,f'g i',ICY lll 1A)M R I
i 3 ki,,),)<<<<gg'4
)i>> f,)I)
~(
"M R'g'I
))<<'
fg)3f i
h illM Mf r
>>R.h f R r>
f II Cq))'il it
~
II 'r
)Il)~
i4 f R(.
i) h R>;4 ill
)I R l g,
)I I
I
~
II R 'I I(
g
'I II I )+ Pal>>i 1
~
14 tiii h
s i lil R 'I
> RI"h R S,, Rl,'I,M;,.'<<, 3 "I<< ii);
I.'l.
R g f R,h
<<<II,)ra
)3 hl, II; N Rf X if ff I<< R.J If>>i f
'(M<<)a I
r I
i
'I
$ RT II>>'l iif 4)I),
R Ii (I
R ~R I ',
R'M<<7
)4 I,),4
'i )
I
)E r) l lt it
@3
(,R r
<<'I )
4>
1
))t'I I
".M ')
))
,t3,
))
g'J,I
~
M
<M <<)
1<<
ii ii <<<>i'l MM' I<<<<EI;II I l <>>
f Y, f 'I
~',
II ))I,I)'() ll.l It ill 4 l)4~)<<
ll <<
h K
hl RR
<<Jl
)Q C, il<<
\\ 4
'hP>>,
+lp FLORIDAPOWER 5 LIGHTCOMPANY October 5, 1982 L-82-429 Office of Nuclear Reactor Regulations Attention:
Hr. Darrell G. Eisenhut, Director Division of Licensing U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555
Dear t1r. Eisenhut:
Re:
St. Lucie Unit No.
2 Docket No. 50-389 Instrumentation for Detection of Inadequate Core Cooling Attached are Florida Power and Light's (FPL) responses to the concerns raised by your staff regarding the inadequate core cooling instrumentation during a telephone conversation on September 14, 1982.
If you have any questions on this submittal, please contact us accordingly.
Very truly yours, Vice President Advanced Systems and Technology REU/RJS/JES/jea Attachment cc:
J:
P. O'Reilly, Region.II Harold F. Reis, Esquire pool
'82i0i30289 82i005
'PDR ADOCK 05000389 "A
pDR PEOPLE..'. SERVING PEOPLE
If 4)
ATTACHMENT Section.II F.2 Provide Inade uate Core Coolin (ICC) Information as follows:
l.
Qualification testing of the heated junction thermocouple system.
~ I
Response
Qualification testing of the heated junction thermocouple system is scheduled to be completed by 10/15/82.
Thd'eport on this testing will be submitted to the NRC by 10/31/82.
2.
Environmental and seismic qualification of the in-vessel and out-of-vessel instrumentation equipment.
Response
Qualification will be handled by the appropriate
- branch, there-fore no additional information will.be provided with this submittal.
3.
Modify Emergency Operating Procedures (EOP's) by incorporating ICC in-strumentation into the procedures as appropriate.
Response
Emergency Operating Procedures will be revised to incorporate ICC instrumentation by October 31, 1982.
4.
Proposed Changes to Technical Specifications.
Response
These changes are incorporated into the T. S. submittal of
- July, 1982.
I 5.
Description of ICC signal transmission processing and display information.
Response:'CC Si nal Transmission Processin and Dis la Information Sensors for ICC Detection The XCC instrumentation consists of four sensor types.
The sensors include:
- 1) pressure transmitter on the pressurizer,
- 2) Resistance Temperature Detectors (RTD) in the hot and cold
- legs,
- 3) pairs of'eated and unheated junction thermocouples (HJTC) arranged in an axial string in the upper plenum, and
- 4) Core Exit Thermocouples (CET).
Except for the HJTC, these sensors already exist in all C-E designed reactors.
Variables for ICC Indication The signals from the ICC sensors are processed to yield five variables.
The ICC variables include 1) temperature margin to saturation from pressurizer pressure and temperature of RTD, 2) temperature margin to saturation from pressurizer pressure and temperature of'unheated thermocouples in the HJTC,
- 3) collapsed coolant level above the core, detected by the
- HJTC,
- 4) temperature margin to saturation from CET and pressur-izer pressure, and 5) core exit steam temperature from the CET.
"> ATTACHMENT
. '"'nadequate Core Cool g
formation Pa e
2 Inade uate Core Coolin Associated Si nal Transmission (Ref. Fig. 1.9B-1 in FSAR)
The hot and cold leg temperatures
'(resistance analogs sensed in the control room) are sensed via conventional cabling from the primary (RCS) piping to the control room, where a resistance bridge measures the resistance of the RTD and converts it to a 4 to 20 ma DC analog signal (current) which becomes an input to the Sub Cooled Margin Monitor (SMM).
The pressurizer pressure transmitter provides a
4 to 20 ma DC analog signal from inside the containment to
.the control room via conventional cable.
In the control room this signal is routed to the
These pressure and temperature. signals are now existing instrument measurement channels of which there are 4 each.
h Th'e HJTC and CET's are Chromel/Alumel thermocouples which provide a DC milivolt signal via Mineral Insulated (MI) cable from the reactor vessel to the containment penetration.
Out-side of the containment these signals are transmitted via conventional cables to the control room where they are pro-cessed for the SMM.
(ref. fig. 1.9B-9 FSAR)
The signals from the various sensors are processed and then displayed (see table) on both QSPDS channels SA
& SB.
The QSPDS consists of microcomputers and plasma display uni'ts that are class IE.
Re uirements FPL has co'mmitted to having the SMM portion of the QSPDS for care load.
The remaining portion of the QSPDS will be im-plemented by 5% power.
'I Summar of Processin The following table lists the ICC variables.
For each variabPe, the table summarizes the thermal hydraulic requirements for display, trending and alarm.
ICC Variable Operator Access To Individual Sensor In ut Continuous Trended Dis la Audible Alarm Saturation Margin From RTDs Saturation Margin From HJTC X
X X (1)
X (1)
Saturation Margin From CETs X
X (2)
Collapsed Level From HJTC X
X (3)
ATTACHMENT Inadequate Core Coolx g nformation Pa e
3 0
Summar of Processin Re uirements (Table Continued)
ICC Variable Temperature Prom 'CETs Operator Access To Individual Sensor In ut Continuous Trended Dis la X
Audible Alarm X (2)
(1)
Highest temperature used for trend of Saturation Margin and for alarm oa-approach
'to saturation..
(2)
Alarm only earlier of CET superheat or maximum CET temperature and only
~ after prior saturation
- alarm, (1).
(3)
Alarm on first level indication.
6.
Detailed description of SMM system to be used during first cycle.
I
Response
The Saturation Margin Monitor is described in FSAR Chapter 1,
App. 1.9B.B 7.
Description of CET processing and display to be used during first cycle.
Response
The Core Exit Thermocouple system is described in PSAR Chapter 1, App.
1.9B AD.