ML20059A033
| ML20059A033 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Byron, Braidwood, Quad Cities, Zion, LaSalle  |
| Issue date: | 12/21/1993 |
| From: | Vonk M COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.101, RTR-REGGD-1.101 NUDOCS 9312290208 | |
| Download: ML20059A033 (12) | |
Text
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.Commonwrith Edison
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1400 Opus Place Downers Grove, Ilknois 60515 December 21, 1993 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attention:
Document Control Desk
Subject:
'Braidwood Station Units 1 and 2 Byron Station Units 1 and 2 Dresden Station Units 1,2, and 3 LaSalle County Station Units 1 and 2 Quad Cities Station LLits 1 and 2 Jion Station Units 1 and 2 Commonwealth Edison Supplemental Response to Request for Additional Information (RAI)
Submittal of NUMARC/NESP-007 Methodology Emergency Action Level (b.L) Classification Scheme for NRC Review and Approval NRC Dockets 50-454 and 50-455 NRC Dockets 50-456 and 50-457 NRC Dockets 50-10, 50-237 and 50-249 NRC Dockets 50-373 and 50-374 NRC Dockets 50-254 and 50-265 NRC Dockets 50-295 and 50-304 l
Reference:
- 1) Regulatory Guide 1.101, " Emergency Planning and Preparedness for Nuclear Power Reactors"
- 2) Letter from J. Burns to Mr. J. B. Martin dated September 1, 1993
- 3) Letter from Mr. G.
Dick to D. Farrar dated November 12, 1993
- 4) Letter from M. Vonk to Document Control Desk dated November 30, 1993
- 5) Letter from M. Vonk to Document Control Desk dated December 17, 1993 Pursuant to our telephone call on December 20, 1993 l
Commonwealth Edison is submitting additional information pertaining to our conversion'to Regulatory Guide 1.101/NESP-007 i
I Emergency Action Level (EAL) Philosophy.
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Document Control Desk (2)
December'21, 1993
' CECO has incorporated the NUMARC Fuel Clad Barrier for~ Core Exit Thermocouples (Loss / Potential Loss for Fuel Clad 3) into our-Fuel Clad 2a Core Cooling Critical Safety Function (CSF Red / Orange for Loss / Potential Loss, respectively).
The Core-Cooling CSF uses redundant indication for the average of the ten highest thermocouples for determination.
NUMARC allows the use of the Core Cooling ORANGE path in.the Reference Table section for Reactor Vessel Water Level (4) for sites using CSFSTs.
CECO utilizes the Core Cooling CSF ORANGE Path as a Potential Loss for our Fuel Clad-2a.
(Attached are copies of the applicable CSFs trees for Byron, Braidwood, and Zion.)
Zion's Core Cooling CSF (with RVLIS available) utilizes reactor vessel level indication as part of it's CSF criteria.
For Byron, Braidwood and for Zion's Core Cooling CSFs (without RVLIS available), core exit thermocouples are utilized as the d
indicators for determining the Core Cooling CSF which establishes the adequacy of existing subcooling.
The Core Exit Thermocouples are an indicator of the reactor vessel water level and the ability to maintain fuel cooling.
t CECO PWRs monitor the CSF Trees utilizing a manual inethod.
The Shift Control Room Engineers (SCREs) (CECO's Shift. Technical Advisors), are procedurally directed to begin monitoring the-control board indications for evaluating the status of the CSFs at specific points in the Emergency Operating Procedures (EOPs).
CSF status is not monitored directly by computer indications.
The indicators used for monitoring CSFs are Class lE indicators.
l If there are any questions or comments, please contact Ms.
)
Leslie Holden at (708) 663-6673 or Mr. Dave Stobaugh at (708) 663-6480.
j 1
Sincerely, l
f' 4artin J. Vonk Generic Issues. Administrator Nuclear Regulatory Services
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Document Control Desk (3)
. December 21, 1993 i
Attachment:
' Critical Safety Function Status Trees cc:
J. Martin, Regional Administrator-RIII I
G.
Dick, Commcnwealth Edison / Generic Issues Administrator, NRR I
i J. McCormick-Barger, NRC Region III J. O'Brien, NRR j
S. Dupont, Senior Resident Inspector (Braidwood)
H.
Peterson, Senior Resident Inspector (Byron) i M.
Leach, Senior Resident Inspector (Dresden)
D.
Hills, Senior Resident Inspector (LaSalle) l T. Taylor, Senior Resident Inspector (Quad Cities)
J.D.
Smith, Senior Resident Inspector (Zion) j File:
EPG-00-P20 File:
EPG-00-G35, w/o Attachments l
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6 ATTACHMENT A' i
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t CRITICAL SAFETY FUNCTION STATUS TREES j
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Rev. 3 F - 0.2 CORE COOLING FEB 0 71990 WITH RVLIS AVAILABLE NI.
NO RVUS NARROW GO TO CORE EXIT TCs RANGE GREATER FR4.1 k
LESS THAN
=
THAN 4F6 (50%
1200*F YES FOR ADV6RSE YES CONTAINMENT) -
f5
.!;t
- s@..
e p; ! GOTO CORE EXITTCs NO ggg; g
g c FR-C.2 LESS THAN
~ ~# '
700*F YES e?r Qy i GO TO f
,,g.
%:] FR-C.2 g
I RVUS NARROW NO RANGE GREATER THAN 40% (50% -.
FOR ADVERSE YES CONTAINMENT)
AT LEAST NO ONE RCP Q
RUNNINe YES GO TO FR-C.3 RCS SUBCOOUNG NO RVUS WIDE RANGE NO Ei$$$$-
2j GREATER THAN 25' F GREATER THAN:
ggj (80* F FOR ADVERSE 44% (54% ADV) 4 RCPs CONTAINMENT)
YES
~
30% (40% ADV) -3 RCPs '
20%(30% ADV) -2 RCPs GO TO 14% (24% ADV) -1 RCP YES OOO FR.C.3 A
j CSF
' SAT i
W Rev.3 F - 0.2 CORE COOLING g e o 2 1990 WITHOUT RVLIS AVAILABLE RI NO CORE EXITTCs N
LESS THAN 1200*F YES GO TO 5
'il FM.2
=, -
w NO CORE EXIT TCs LESS THAN 700* F YES O
7 OO FR-C.3 RCS SUBCOOUNG NO GREATER THAN 25* F (80* F FOR ADVERSE CONTAINMErlT)
YES SAT
- FINAL -
2 l
J
REV. 3 CORE COOLING 1 BwST-2 WOG-1 A UNIT 1 GOTO l
1 BwFR-C.1 Core exit TCs NO LESSTHAN 1200 9-YES BEEEEEEE gg l
18wFR-C.2 E
t40 Core exit TCs LESSTHAN 708 T YES eeeseeeeeeee coTo i
18wFR-C.3 RCS subcooling t40 ACCEPTAELEVALUE per iconic Display or Attachment A and Figure 18wST 2-1 YES CSF SAT APPROVED JAN 121991 Page 1 of 3 ESE7cv?cw
e REV. 3 CORE COOLING 1BWST-2:
WOG-1A UNIT 1 l
i ATTACHMENT A i
A.
Determination of Post-Accident RCS Subcooling:
- 1. Check Cnmt for ADVERSE conditions:
o Cnnt pressure greater than 5 PSIG
-0R-o Cnmt radiation greater than 105R/HR 1RT-AR020 Grid 4 4AS120 1RT-AR021 Grid 4 4AS121 i-
- 2. Check RCS pressure on wide range pressure instruments-f l
(1PI-403A/405).
- 3. Determine temperature for RCS pressure using NORMAL or ADVERSE ~
Cnmt curves per FIGURE IBwST 2-1.
t 4
Check average of ten highest core exit TCs from MCB indicators' (1TI-1T001/1T002).
- 5. If average of ten highest core exit TCs is less than temperature.
for RCS pressure, then acceptable subcooling exists.
i E
J l
1 i
ADPROVED (0230Q/0022Q/122190)
JAN 1"2 391 E.$$$cview 1
REV. 3 CORE COOLING 1BWST-2 WOG-1A UNIT 1 1
(NORMAL) l 200 300 400 500 600 700 1
2600 12600
,. g 2500
[/ [
- 2500 2400 f
f 2400 2300 i.i Q j f j 2300 2200
/ ) /
2200 2100 3
[ / [
2100 2000
[ f j 2000 m
O 1900
/ /
/
1900 0 H
1800
^CCEPTABLE f 'J f 1800 H w
w 1700
/ / /
1700 g
v 1600 j
)
1600 v 1500
[ f 1500 J
W f
w 1400 f
1400 g
j.,
g D 1300
[ [ [
13 0 0 J W 1200
[ f /
1200 W W
W 1100 r s
.r g
j g
- 1100 g
2 1000
((
1000 E r
1 900
/[ /
900 O-ADVERSE
,r, J
f NOT W
800 CNMi e
a J
ACCEPTABLE.
W r
U 700
// [
700 0
1 600 j) 600 1
500
/;
500 j
400 p
Q SATURATION' 400 300 300 NORMAL
'. ' /
200 CNMT
- 200 10e 100 I
I 200 303 400 500 600 700 TEMPERATURE CoF)
FIGURE IBWST 2-1 i
RCS SUBC00 LING MARGIN A DDR OVFD Page 3 of 3 (0230Q/0022Q/122190)
- N1 2;"'91 d?df%fA
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REV. 3 CORE COOLING 2BST-2
-WOG-1 A UNIT 2 GOTo l
2BFR-C.1 NO Core exit TCs LESS NAN V
1200'F YES EEEEEEEE GOTO l
E 2BFR-C.2 NO Core exit TCs LESSTHAN 708 9 YES I
eeeseeeeeees GOTO l
2BFR-C.3 f
RCS subcoolig NO APPROVED ACCEPTABLEVALUE per iconic Display JAN 111991 or Attachment A and Figure 2BST 2-1 YES B. O. S. R.
'OSAT-CSF Page 1 of 3
REV. 3 CORE COOLING 2BST-2 WOG-1A UNIT 2 ATTACHMENT A A.
Determinarjon of Post-Accident RCS Subcooling:
- 1. Check Cr.mt for M IRSI conditions:
o Cnnt pressure greater than 5 PSIG l
-OR -
5 o
Onmt radiation greater than LQ R/HR i
2RT-AR020 Grid 4 5AS120 2RT-AR021 Grid 4 5AS121
- 3. Determine temperature for RCS pressure using NORMAL or ADVERSE Cnmt curves per FIGURE 2BST 2-1.
I 4
Check average of ten highest core exit TCs from MCB indicators (2TI-2T001/2T002).
- 5. If average of ten highest core exit TCs is less than temperaturer for RCS pressure, then acceptable subcooling exists.
APPROVED JAN 111991 B.O.S.R.
Page 2 of 3 (0269E/ 0030t:'122190)
-l
REV. 3 CORE COOLING 2BST-2 WOG-1A UNIT 2 I
CNORMAL) i 200 300 400 500 600 700 2600
'2600 c
2500
[ [ [
2500 2400
[ [
f 2400 2302
) f j 2300 2200
[ ] [
2200 2100
[ [ [
2100 2000
[ f j 2000,
C 1900
[ / /
1900 C J
H 1800
^CCEPTABLE f
f 1800 1700
[ [
1700 v 1600
/ [ j
- 1600 v 1500
[
1500 1400 j
j 1400 J 1300
/ /
1300 J W 1200
[ [ /
1200 W W
W r i r
1100 g
, g j
-- 1100 g
E 1000
(( [
1000 2 1
900
/[,/
900 0-ADVERSE J
/
NOT
'rr 8OO CNMi
/ /
2 ACCEPTABLE <
W g
U 700
/[ f 702 y
2 620
[#
600 2
j f
500 j/ [j 500 420
[
k SATURATION'""""
400
,t y
/
300 300 NORMAL MP
/
-C NMT 200 200 100 100 200 300 400 500 600 700 TEMPERATURE C
F)
APPROVED FIGURE 2BST 2-1 RCS SUBC00 LING MARGIN ggy11I39l FD!,11.
B. O. S. R.
Page 3 of 3 (0269E/0030E/122190)
/