ML20081A146
| ML20081A146 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 03/01/1984 |
| From: | Schroeder C COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 8208N, NUDOCS 8403050063 | |
| Download: ML20081A146 (39) | |
Text
C'N Commonwe:lth Edison
[ O J'7 Address Reply to: Post Office Box 767 C
) one First Nationst Plaza. Chicago, lihnois
((j/ Chicago, Illinois 60690 March 1, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
LaSalle County Station Units 1 and 2 Fire Protection Sytem Analysis RCIC -
RHR High/ Low Pressure Intelface NRC Docket Nos. 50-373 and 50-374 References (a):
LaSalle County Station Unit 2 License NPF-18, dated December 16, 1983.
(b):
C. W. Schroeder letter to H. R.
Denton dated November 23, 1983.
(c): ' Region III Inspector Report Nos.
50-373/83-44 and 50-374/83-48.
Dear Mr. Denton:
Commonwealth Edison Company has completed our review / analysis of the possibility that a fire in a single' fire zone will result in the simultaneous fnadvertent opening of all three high/ low pressure interface valves (namely (1)2E51-F064, (1)2E12-F052A/B and (1)2E12-F087A/B) between the RCIC and RHR systems.
The enclosed attachment gives in detail the analysis process including failure mode; acceptance criteria; evaluation results and modifications to be performed.
This enclosure provides the basis for closure of the following items:
1.
Item 2.C.(15)(1) of Reference (a).
2.
Issue #12 of Reference (b).
3.
Item 16.C of Reference (c).
To the best of my knowledge and belief the statements contained herein and in the attachment are true and correct.
In some respects
-these statements are not based on my personal knowledge but upon infor-mation furnished by other Commonwealth Edison and contractor employees.
s Such information has been reviewed in accordance with Company practice and I believe it to be reliable.
- 'I* c
e]d,ce,s
..eem,eese e, cme, pon Apocn 05000373 F
PDR 9j t
r y
H. R. Denton March 1, 1984 Enclosed for your use are one signed original and nine (9) copies of this letter and the attachment, and three (3) copies of the applicable drawings.
If there are any further questions regarding this matter, please contact this office.
Very truly yours, I f/ /94-C. W. Schroeder Nuclear Licensing Administrator 1m cc:
NRC Resident Inspector - LSCS 1/1 l
i-
~8208N i.
l l-
High-Low Pressure Interface Analysis Per the request of Region III, the High-Low Pressure Interface between the RCIC steam line and the RHR Heat Exchangers was examined.
P, 1.~
Interface Description Reactor steam is routed through three normally closed valves when the RHR System is placed in the steam condensing mode.
Either the Division A and Division B heat exchanger may be used.
The interface consists of the following valves.
These valvas are shown on FSAR Figure 6.3-10, sheet 3.
To Div. A Heat Exchanger:
1)
E51-F064 2)
E12-F052A 3)
E12-F087A and E12-F051A*
To Div. B Heat Erchanger:
1)
E51-F064 2)
E12-F052B 3)
E12-F087B and E12-F051B*
- E12-F087A/B and E12-F051A/B are in parallel with each other High-low pressure protection are provided by (1) two redundant high steam pressure interlocks on each bypass valves E12-F087A/B which close the valve on high steam line pressure, and (2) relief valves E12-F055A/B will relieve pressure due to pressure controller failure on E12-F051A/B in the full open position.
2.
Failure Modes Failure of a power cable either by ground open or hct short would not effect the valve actuation logic.
There-fore, no further analysis will be performed for power cable since the valve will fail in the as is condition if these cables are disabled.
The cables from the limit switch to MCC are not included because no failure of tne limit switch or its cable can cause the valve to move.
Relief Valves E12-F055A and B provide mechanically actu-ated protection for a full open failure of control valves lE12-F051A and B.
Therefore, no further analysis was performed for control cable associated with E12-F051A and B. _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
A.
For the high-low pressure interface to open, the following conditions must be simultaneously met:
1.
E51-F064:
The contact on the control switch in.
the main control room must close.*
2.
E12-F052A/B:
The contact on the control" switch j,
in the main control must close.
3.
E12-F087A/B:
The contact on the control switch in the main control room must close.
4.
Steam line pressure as sensed by PS E12-N032A/B must be <500 psig.**
5.
Steam line pressure as sensed by PS E13-NO33A/B must be <500 psig.**
B.
Failure Conditions that Could Result in Potential Degraded Safety 1.
A short in the control switch or in the cable from the control switches will open the respective valve if all other permissives are met.
2.
The close position in the pressure permissive interlock contacts in the AEER logic panels will allow E12-F087A/B to open if the control switch is in the closed position or shorted out.
3.
A ground or open in pressure switch or cable from
'the steam line pressure switch will allow the pressure permissive contact to close or to remain closed, thus allowing E12-F087A/B to open if the control switch contact is in the closed position or shorted out.
A high differential pressure interlock would close this valve prevent it from opening'if a steam line break occurs.
No cn:
credit is taken for this interlock.
The contact is assumed to fail in the closed position.
- The pressure switch contact closes on high steam line pressure which opens the permissive in MCC circuit.
1 -
I
- e. '
3.
Acceptance Criteria The failure being considered in the simultaneous spurious opening of all three valves in a seriis in the high-low pressure interface while the steam line pressure is above the pressure permissive set point.
Paragraph 2.A describes the conditions that must be sensed by the control
,, logic for the valves to open.
Paragraph 2.B describes T,.thefailuresmodesconsidered.
~
If a control switch, interlock, or cabic is present in a fire zone, it is assumed to fail in the most detrimental
(
- manner, i.e., provide a signal to the valve logic that would permit the valve to open if all other necessary signals were present.
4.
Evaluation Results A.
Unit 1 Analysis Table A identifies the cables and panels reviewed for separation.
TRAIN A Control Room - Panels (Fire Area 4Cl)
The control switches for all three valves are located on lH13-P601 in the control room.
Therefore, we assume that the control switch contacts close if a fire is postulated in this area.
The high-low pressure boundary integrity is maintained because the logic and cables associated with the pressure permissive for lE12-F087A are independent of this area.
AEER - Logic Panels (Fire Areas 4El-1 and 4El-2)
Cables and logic for all three valves are located in the AEER.
The AEER has been divided into two subareas This by the installation of a 3-hour fire-rated wall.
' wall runs east-west from the east wall to the west wall of the AEER.
It is between the second and third row of panels nearest the south wall.
The Unit 1 AEER lay-out is shown on FSAR Figure H.4-1.
However, both panels associated with Train A lH13-P621 and lH13-P629 are in the same area (4El-2).
Therefore, it is postulated that all three valves in Train A could open.
This event is prevented by the measures described in Section 5 of this analysis. - - _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _
o t'
r gOther. Plant ' Fire Areas TEhe. control cable routing for all three valves 1E51-F064, 1E12-F087A, and lE12-F052A are found in tthe following fire zones: 2F-2, 4F3, and 4Dl-1.
Simul-daneous opening of this valve train is prevented by
- measures. described in Section 5 of this analysis.
b' I'
jTRAIN B
' Control Room - Panels (Fire Area 4Cl) 7tua control switches for all three valves are located on :lH13-P601 in the control room.
Therefore, we
- assumed for a postulated fire in this area that the control switch contacts close.
The high-low Pressure
. boundary integrity is maintained because the logic and cables associated with the pressure permissive for lE12-F087B are independent of this area.
AEER - Logic Panels (Fire Areas 4El-1 and 4El-2)
Cables and logic for all three valves are located in the AEER.
The AEER has been divided into two subzones by the installation of a 3-hour fire-rated wall.
This wall runs art-west from the east wall to the west wall of the AEER.
It is between the second and third row of panels nearest the south wall.
The Unit 1 AEER layout is shown on FSAR Figure H.4-1.
1H13-P618 is separated by this wall from 2H13-P621 and 2C61-P001.
Cable and logic associated with lE51-F064 are in 4El-2 and therefore, independent of cable and logic associated with 2E12-F087B in 4El-1.
Therefore, if a fire is postulated in either of the AEER fire areas, at least one valve would be unaffected.
Other Plant Fire Areas The control cable routing for all three valves lE51-F064, lE12-F087B, and lE-12-F052B are'found in only the following fire zone, 2F.
In fire zone 2F, the control cables for lE51-F064 in Subzone 2F-2 are separated by at least 150 feet from those for lE12-F087B and 1E12-F052B in Subzone 2F-1.
This separation into subzones 2F-1 and 2F-2 was accepted by the NRC staff as documented in the response to Question 10.74.
~
B.
Unit 2 Analysis Table B identifies the cables and panels reviewed for separation.
TRAIN A V
Control Room (Control Panels) (Fire Area 4Cl)
I' The control switches for all three Valves are located on 2H13-P601 in the control room.
Therefore, we assume that the control switch contacts close if a fire is postulated in this area.
The high-low pressure boundary integrity is maintained-because the logic and cables associated with the pressure persmissive for 2E12-F087A are independent of this area.
AEER (Logic Panels) (Fire Areas 4E2-1 and 4E2-2)
Cables and logic for all three valves are located in the AEER.
The AEER has been divided into two eubareas by the installation of a 3-hour fire-rated wall as described in FSAR paragraph H.4.2.40.
However, both panels associated with Train A 2H13-P621 and 2H13-P629 are in the same subarca (4E2-2).
Therefore, it is postulated that all three valves in Train A could open.
This event is prevented by the measures described in Section 5 of this anlaysis.
Other Plant Fire Areas The control cable routing for all three valves 2E51-F064, 2E12-F087A, and 2E12-F052A are found in the following fire zones:
Simultaneous opening of this valve train is prevented by measures described in Section 5 of this analysis.
TRAIN B Control Room - Control Panels (Fire Area 4Cl)
The control switches for all three valves are located on 2H13-P601 in the control room.
Therefore, we assumed for a postulated fire in this area that the control switch contacts close.
The high-low pressure -
J
J boundary integrity is maintained because the logic and cables associated with the pressure permissive for 2E12-F087B are independent of this area.
AEER (Logic Panels) (Fire Areas 422-1 and 4E2-2)
' Cables and logic for all three valves are located in the AEER.
The AEER has been divided into two sub-areas by the installation of a 3-hour fire-rated wall I
as described in the FSAR, paragraph H.4.2.40.
2H13-P621 is separated by this wall from 2H13-P618 and 2C61-P001.
Cable and logic associated with 2E51-F064 are in 4E2-1 and therefore, independent of cable and logic associated with 2E12-F052B and 2E12-F087B in 4E2-2.
Therefore, if a fire is postulated in either of the AEER fire areas, at least one valve would be unaffected.
Other Plant Fire Areas The control cable routing for all three valves 2E51-F064, 2E12-F087B, and 2E12-F052B are found in only the following fire zone, 3F.
In fire zone 3F, the control cables for 2E51-F064 in Subzone 3F-2 are separated by at least 140 feet from those for 2E12-F087B and 2E12-F052B in Subzone 3F-1.
This separation into subzones 3F-1 and 3F-2 was accepted by the NRC staff as documented in the response to Question 10.74.
5.
Modification Valves lE12-F087A and 2E12-F087A shall have power removed at the respective Motor Control Center by means of an out-of-service card or padlock or other suitable means when Reactor Pressure is greater than 500 psig.
Administrative
. controls shall be in place on both units prior to 5% power on Unit 2 to ensure that power is removed and only restored during steam condensing start-up (i.e., draining) or when reactor pressure is less than 500 psig.
e 4
4' 6.
Applicable Schematic Diagrams Schematic Diagrams Valve Unit 1 a.
lE-1-4226 AM lE51-F064 b.
lE-1-4220 CG/lE-1-4220 All lE12-F087A y
J' c.
lE-1-4220 CF/lE-1-4220 AL lE12-F087B d.
lE-1-4220 BX lE12'-F052A e.
lE-1-4220 BY lE12-F053B Unit 2
/
a.
lE-2-4220 CG/lE-2-4220 AII 2E12-F087A c.-
lE-2-4220 CP/lE-2-4220 AL 2E12-F087B i
d.
lE-2-4220 BX 2E12-F052A d.
lE-2-4220 BY 2E12-F053B These drawings have been submitted as required by Regu-
'latory Guide 1.70, Section 1.7.
They are in Volumes 3 and 6 of the La Salle FSAR, Section 1.7 submittal.
Additional copies are attached for your use.
?
O
+ x_
. i '*
,~
TABLE A Cable and Panel List - Unit 1 TRAIN A Connection Cable No.
f-lE51-F064 lH13-P601 to lH13-P621 1RH026/lRIl96*
lH12-P621 to.MCC 135X-1 1RH025*
o.
(
lE12-F087A b1I lH13-P601 to lH13-P629 1RH229 lH13-P629 to MCC 135Y-1 1RH228*
lH22-P018 to lH13-P629 1RH267(1)
Press Permissive-K60A 2E12-F052A lH13-P601 to 1H13-P629 12H221*
lH13-P629 to MCC 135Y-1 1RH220*
TRAIN B lE51-F064
'lH13-P601 to lH13-P621 1RIO26/lRIl96*
lH13-P621 to MCC 135X-1 1RIO25*
lE12-F087B 1RH233( I lH13-P601 to lH13-P618 lH13-P618 to MCC 136Y-2 1RH232 II lH22-P021 to lH13-P618 1RH266 Press Permissive-K60B lE12-F052B lH13-P601 to lH13-P618 1RH225*
lH13-P618 to 1C61-P001 1RH224*
1C61-P001 to MCCl36Y-2 1RH385*
Short in this cable postulated to open valve
.(1) Multiple failure of two identified cables needed
. to open valve t
6 1
_4 TABLE B Cable and Panel List - Unit 2 TRAIN A h
Connection Cable No.
-1 2E51-F064 2H13-P601 to 21113-P621 2RIO26/2RI196*
21112-P621 to MCC 235X-1 2RIO25*
l 2E12-F087A 21113-P601 to 21113-P629 2RH229 (1) 21113-P629 to MCC 235Y-1 2 RII228 II)
Press Permissive-2H22-P018 to 21113-P629 2RH267 K60A s
- 2H13-P601 to 2H13-P629 2RI!221*
2H13-P629 to MCC 235Y-1 2 RII220
- TRAIN B 4
2E51-F064 21113-P601 to 21113-P621 2RIO 26/2 RI196
- 2E12-F087B 21113-P601 to 2H13-P618 2 RII233 ( )
'2H13-P618 to MCC 236Y-2 2RH232(1) 21I22-P021 to 21Il3-P618 2RH266 Press Permissive-K60B
- a, 2E12-F052B 2H13-P601 to 21113-P618 2RH225*
' "' 4-21113-P618 to 2C61-P001 2RH224*
2C61-P001 to MCC236Y-2 2 RII385
- Short in_this cable postulated to open valve (1) Multiple failure of_the two identified cables needed to open valve
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