ML20094N787
| ML20094N787 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 08/07/1984 |
| From: | John Marshall COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 9032N, NUDOCS 8408160387 | |
| Download: ML20094N787 (6) | |
Text
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4 Commonwealth Edison one Fir t Nation't Plat 9, Chicago, lihnois Address Reply to: Post Office Box 767 Chicago. Illinois 60690 August 7, 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 Pump and Valve Inservice Testing Plan NRC Docket Nos. 50-373 and 50-374 References (a):
C.
W. Schroeder letter to A. Schwencer dated February 18, 1983.
(b):
C.
W.
Schroeder letter to H.
R. Denton dated August 2, 1983.
(c):
C. W. Schroeder letter to H. R. Denton dated November 12, 1983.
Dear Mr. Denton:
Enclosed are revisions to the LaSalle County Units 1 and 2 Pump and Valve Inservice Testing Plans.
These revisions consist of relief requests from certain ASME Section XI Code requirements for two specific valves.
These forms also contain the bases for these requests.
Relief Request RI-19 is applicable to both Units 1 and 2.
Insert into Part A, Tab 6 of the plan (one page).
Relief Requ3st RV-38 is applicable to Unit 1 only.
Insert into Part 8, Tab 7 of the Unit 1 plan (three pages).
One signed original and ten (10) copies of this letter and addendum are provided for NRC use and update of your pump and valve inservice testing plans.
If there are any questions on this matter, please contact this office.
l Very truly yours, h.90. We J. G. Marshall Nuclear Licensing Administrator im cc:
NRC Resident Inspector - LSCS 1/0 g(g]
Dr. A. Bournia - 1/0 8408160387 840007 l
DR ADOCK 05000 1032N p
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@; Commonwerith Edison INSERVICE INSPECTION LaSane County Nuclear Station Page 1 of I
e RELIEF REQUESTS FOR COMPONENTS AND PIPING Rev. O e
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Wo EXEMPTED TEST BASIS FOR RELIEF ALTERNATIVE 6E@
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COMPONENT REQUIREHENT TEST 00
'01 02 03 04 05 06 07 RI-19 Normally 1
Cat. B-P Pressure Leakage cr Hydro-The design of these gate Following valve Closed B15.70 Retaining Bonnet static Pressure Test valves makes it impossible maintenance operations Containment B15.71 Flange Assembly for the bonnet flange when the bonnet is Isolation E12-F008 connection to be pressure removed a VT-2 exam Class 1 tested at reactor pressure will be performed at Cate Valve:s or higher while the valve the operating pressure Located at disk is in a' closed of the low pressure a liigh Pressure position. Pressure piping with the valve testing at reactor disk in an open Piping / Low pressure with the disk in position.
Pressure an open position is not During routine ASME Piping possible because these Section XI system Interface valves are located at the pressure tests the interface of low pressure bonnet flange connectio and high pressure piping.
will be subjected to Therefore, the bonnet the same pressure as flange connection cannot exis'ts in the low be tested at a higher pressure piping.
pressure than is allowable D
in the low pressure piping O
without causing possible C,
damage to this piping.
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Commonwealth Edison INSERVICE INSPECTION tas.n. county Huci..r si uon Page 1 of 1
e RELIEF REQUESTS FOR COMPONENTS AND PIPlHG Rev. O e
er Ihl0 Elb!E3 SECTION XI ui U Er SYSTEM OR 3
dia@c o
EXEMPTED TEST BA515 FOR RELIEF ALTERNATIVE EfE!
COMPONENT (2
COMPONENT REQUIREMENT TEST 00
'01 02 03 04 05 06 07 RI-19 No rmally 1
Cat. B-P Pressure Leakage or Hydro-The design of these gate Following valve Closed B15.70 Retaining Bonnet static Pressure Test valves makes it impossible maintenance operations Containment B15.71 Flange Assembly for the bonnet flange when the bonnet is Isolation E12-F008 connection to be pressure removed a VT-2 exam Class 1 tested at reactor pressure will be performed at Cate Valves or higher while the valve the operating pressure Located at disk is in a* closed of the low pressure a High position. Pressure piping with the valve Pressure testing at reactor disk in an open Piping / Low pressure with the disk in position.
Pressure an open position is not During routine ASME Piping possible because these Pection XI system Interface valves are located at the pressure tests the interface of low pressure bonnet flange connectio l
and high pressure piping.
will be subjected to Therefore, the bonnet the same pressure as flange connection cannot exis'ts in the low be tested at a higher pressure piping.
pressure than is allowable in the low pressure piping without causing possible damage to this piping.
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@ t.assie county Nuclear Stauon UNt 1
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Commonwealth Edison PUMP & VALVE TESTING Pace' of RELIEF REQUESTS Md=4 l IIi ASME 33 PUMP OR QO SECTION XI VALVE NO.
FUNCTION TEST REQUIREMENT BASIS FOR RELIEF A'.TERNATIVE TEST g
L 00 01 02 03 04 05 06 RV-38 IE51-F065 1/C RCIC INJECTION OUT-EXERCISE QUARTERLY DUE TO NORMAL LEAKAGE EXERCISE DURING' COLD BOARD TESTABLE THROUGH RCIC INBOARD SHUTDOWN CHECK VALVE CHECK VALVE 1E51-F066 IT IS POSSIBLE DURING REACTOR POWER OPERATION THAT A PRESSURE APPROACHING 1000 PSIG MAY EXIST ON THE IN-BOARD SIDE OF TESTABLE CHECK VALVE 1E51-F065.
EXERCISING VALVE F065 USING THE TEST OPERATOR REQUIRES REDUCING THE AP ACROSS THE' VALVE DISK BY OPENING THE WARM-UP BY-PASS VALVE 1E51-F354.
THIS INTRODUCES THE HIGH REACTOR PRESSURE TO THE UPSTREAM SIDE OF STOP VALVE 1E51-F013. ONE PURPOSE OF F013 IS TO ISOLATE REACTOR PRESSURE FROM THE RCIC PIPING WHICll IS NORMALLY PRESSURIZED TO 60 PSIG.
INADVERTANT OPENING OR EXCESSIVE LEAK--
AGE THROUGH F013 WOULD RESULT IN A WATER HAMMER OF THE RCIC PIPING AND/OR DAMAGE TO THE LOW PRESSURl' PIPING ON THE SUCTION SIDI:
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@ LaSaHe County Nudear Stauon Una 1 Commonwealth Edison i
PUMP & V ALVE TESTING Page-of RELIEF REQUESTS a.n W \\
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ASME 33 PUMP OR QO SECTION XI y3 VALVE NO.
JN FUNCTION TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVETEST og
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00 01 02 03 04 05 06 0F THE RCIC PUMP WHICH IS DESIGNED FOR A MAXIMUM PRESSURE OF 100 PSIG.
RELIEF IS REQUESTED TO EXERCISE RCIC OUTBOARD CHECK VALVE lE51-F065 AT COLD SHUTDOWN WHEN REACTOR PRESSURE IS SUB-STANTIALLY REDUCED.
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O 00 01 02 03 04 05 06 07 /
08 09 10 11 12 13 lE51-F063 10 101-1 E8 1/A GT M0 0
Steam Supply Inboard LT RR RV-19 Isolation (M-15)
PIT RR (See flote 1,4,6) lE51-T064 10 101-1 E7 1/A GT M0 C
FS,ST
.CS 15 RV-15 A
Steam Supply Inboard LT RR RV-19 Isolation (To RilR)
(ii-15) (See flote' I,4)
IL31-f065 6
101-2 C7 1/C CV A0 C
E CS RV-19 A
RCIC injection Outboard PIT RR R$/-38 Testable Check (M-29)
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LT RR (See Note 5,7) 1E51-f066 6
101-2 CB 1/C CV A0 C
E CS RV-19 A
RCIC Injection Inboard PIT RR RV-35 Testable Check (M-29)
LT RR (See flote 5,7) lE51-f068 10 101-1 B7 2/A GT MO 0
FS,ST Q
55 RV-19 A
Turbine Exhaust isolatim LT RR (M-76) (See Note 4,6) lE51-f069 1.25 101-1 B7 2/A G'B M0 O
FS.ST Q
20.,6 RV-19 A
Barometric Condenser Vacuum Pump Discharge LT RR Stop (M-81)
(See Note,4,6) 1FSI-f076 1
101-1 E8 1/A GB M0 C
FS.SI Q
15 RV-19
'A Steam Supply I nboa n t Li RR Isola tion Va lve Llanu-lip Pil RR Bypass (M-l's)
(See Note 4,6)
GC - f 2 -l 180 L_
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