ML19338D092
| ML19338D092 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 09/11/1980 |
| From: | Naughton W COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8009190403 | |
| Download: ML19338D092 (83) | |
Text
__ _-
Commonwealth Edison e
One First Nabonal Ptza. Chicago, Ilhnois 8-
' Addr:ss Reply to: Pist Offica Box 767
\\
Chicago, Illinois 60690 m
September 11, 1980 Mr. Harold R. Denton, Director Of fice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Zion Station Units 1 and 2 Additional Information for Inservice Valve Test Program NRC Docket Nos. 50-295 and 50-304 References (a):
June 28, 1980 letter from W. F. Naughton to H.
R. Denton (b):
August 8, 1980 letter from S. A.
Varga to D. L. Peoples
Dear Mr. Denton:
In Reference (a), Commonwealth Edison Company submitted a license amendment request to incorporate the inservice inspection requirements and the pump and valve inservice testing requirements of 10 CFR 50.55a for Zion Station.
In Reference (b), the NRC Staff approved the Zion Station Inservice Inspection (ISI) program and provided relief where appropriate.
However, the NRC Staff indicated that the inservice testing (IST) program for pumps and valves was still under review and would be approved in a separate license amendment.
During the review of the Zion Station ISI program submittal, Reference (a), the NRC Staff identified the need for changes to the IST program These changes were communicated on June 18, 1980 to Zion Station via a telecon from Mr. V. Nerses of your staff.
Based on this telecon, Commonwealth Edison has revised the Zion Unit 1 and Unit 2 inservice test programs for valves.
Attachments 1 and 2 to this letter contain the Zion Unit 1 and Zion Unit 2 Inservice Valve Test Programs with pages 59 though 62, 69 through 77, 79 and 83 of the Reference (a) submittal for each unit revised.
Specific areas of revision are discussed below.
On page 60, in the Exercise column for Valve MOV-VC8100 quarterly (Q) testing was changed to cold shutdown with no reactor coolant pumps running (Cl).
Note 29 which was added to the Remarks column for this valye is also included on page 83 as the reference for the relief request.
On page 61, Note 15 was determined to be inappropriate for Valves MOV-RH8701 and MOV-RH8702 and therefore, deleted from the Remarks column.
In its place, Note 28, which is included on oage 83, is referenced.
8009190 Q3 p
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Mr. H. R. Denton, Director September 11, 1980 Page 2 On page 71, Note 9 was determined to be inappropriate for Valve PR0029 and therefore, deleted from the Remarks column.
In addition, a wholesale change of valve classification for containment isolation supplied with isolation valve seal water (ISVW) has been made.
These valves are identified by a " Note 9" in the Remarks column.
The valve classification has been changed from Category B to Category A.
This change to Category A requires that these valves be tested for seat leakage.
A relief request is thereby necessitated and is reflected by a change from "No" to-"Yes" in the Relief Request column for each of these valves and in a revision to Note 9 on page 79.
In effect, the changes enumerated above do not change t,he type or method of testing of containment isolation valves.
- However, these changes do properly categorize the valves and. allow the NRC
\\
Staff to address their review of the Zion Station IST program in a manner similar to other operating stations.
For the convenience of the NRC Staf f in its review of this program, the Zion Unit 1 and Unit 2 IST program including the technical specification change from the original license amendment request of May 27, 1977 has been consolidated in Attachments 1, 2, and 3 to this letter.
Thus, this submittal contains the information necessary for meeting the pump and valve inservice testing requirements of 10 CFR 50.55a for Zion Station.
The program changes of Attachments 1 and 2 and the technical specification change of Attachment 3 have been reviewed and approved by Commonwealth Edison Onsite and Offsite Review.
Please address any questions that you might have concerning this matter to this office.
One (1) signed original and thirty-nine (39) copies of this transmittal are provided for your use.
Very truly yours, f Y-W. F. Naug on Nuclear Licensing Administrator Pressurized Water Reactors attachments (3) cc:
Resident Office - Zion
..sv{ A r:
1 NRC Docket No. 50-295 ATTACHMENT 1 Zion Unit 1 Inservice Valve Test Program O
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?./,q'dit.i'on up to and including Summer 1975 Addenda, Subsect ions'
' 3,9 f the requirement of Section XI are requested
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'.a The alternative tests are indicated in the Test columns t'
arksi
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. Seal Water Inservice Test Program Rcv. 0 A.S.M.E. Code Class 1, 2 and 3 Valves Drr.n.ng Mr.ber:
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Request Remarks
- CV-IWOl NA C-1 X
1 G
AO C
60 YES Note 27 LCV-IWO2 NA B-1 X
1 G
AO C
60 YES Note 27 (CV-IWG3 liA C-1 X
1/2 G
AO C
60 YES Note 27 t
IN0001 NA. C-1 X
1 C
S C
YES Note 10
~
IW0003 IIA' C-1 X
1 C
S C
YES Note 10
'CV-INO3 NA B-5 X
3/4 G
AO O
60 NO CV-IWG9
!!A B-5 X
3/4 G
AO O
60 NO TCV-IW10 NA.
B-6 X
3/4 G
AO Q
60 NO fCV-IWil NA B-6 X
3/4 G
AO Q
60 NO
[CV-IW12 NA' B-3 X
1/2 G
AO O
60 NO 7CV-IW13 NA B,3 X
1/2 G
AO Q
60 NO (CV-IU14 NA B-7 X
1/2 G
AO O
60 NO
[CV-IU15 NA B-7 X
1/2 G
AO O
60 NO CV-IU16 NA B-3 X
3/4 G
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t60 NO ICV-IW17
.NA B-3 X
3/4 G
AO O
60 NO I
IN0073 INA C-7 X
3/8 C
S C
YES Note 10 IW0074 UA C-7 X
3/8 C
S C
YES Note 10 IU0075 NA D-3 X
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S C
YES Note 10 IWOO76 NA D-3 X
3/8 C
S C
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, X<
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S C
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YEC Note 10 YES Note 10 IWOO78 lNA D-3 X
3/8 C
S C
1U0079
- NA D-3 X
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S C
YES Note 10 IW0181 NA D-5 X
3/8 C
S C
YES Note 10 IW0182 NA D-5 X
3/8 C
S
- C YES Note 10 IWOl83 NA D-5 X
3/8 C
S C
YES Note 10 Ih0184
'JA D-6 X
3/8 C
S C
YES Note 10 IW0185 NA D-6 X-3/8 C
S C
YES Note 10 IN0198 NA C-4 X
1/2 C
S C
YES Note 10 IN0058 NA B-4 X
1/2 C
S C
YES Note 10 IU0059 NA B-4 X
1/2 C
S C
YES Note 10 j
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Isolation valve Zion Unit 01 Page _53 of 83' Seal Water Inservice Test Program Rev. O A.S.M.E. Code Class 1, 2 and 3 Valves D r ecc i r.g M r.b o r :
M-39 Test m
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S C
YES Note 10 IM0061 NA B-4 X
1/2 C
S C
YES Note 10 IWOG62 NA B-S X
1/2 C
S C
YES Note 10 IWOO63 NA B-6 X
1/2 C
S C
YES Note 10 IN0064 NA B-5 X
1/2 C
S C
YES Note 10 IM0065 NA B-S X
1/2 C
S C
YES Note 10 IWOO66 NA B-6 X
1/2 C
S C
YES Note 10 IW0067 NA C-3 X
1/2 C
S C
YES Note 10 IWOOGS NA C-3 X
1/2 C
S C
YES Note 10 IW0069 MA C-3 X
1/2 C
S C
YES Note 10 IW0070 NA C-4 X
1/2 C
S C
YES Note 10 IWD072 NA C-4 X
1/2 C
S C
YES Note 10 IM0030 MA D-3 X
1/2 C
S C
YES Note 10 IWOO81 NA E-5 X,
1/2 C
S C
YES Note 10 IWOG32 NA D-6 X
1/2 C
S C
YES Note 10 IN0083 NA D-6 X
1/2 C
S C
YES Note 10 IWOO84 NA D-4 X
1/2 C
S C
YES Note 10 IW0lGO NA B-2 X
1 R
S C
YES Note 10 IW0162 NA C-1 X
3/4 C
S C
YES Note 10
,(NA IWG090 Ui F-3 X
1/2 C
S C
YES Note 10 IF0095 r
E-S X
1/2 C
S C
YES Note 10 IW0186 lMA E-4
'X 3/8 C
S C
YES Note 10
Zion Unit il Page 54 of,8 3 Containcent Spray Rev, 0 Ey;tcn: _
Inservice Test Program A.S.M.E. Code Class 1, 2 and 3 Valves j
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- OV-CS0002 2
B-4 X
10 G
MO O
50 R
NO Note 7
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C-3 X
10 G
MO Q
50 NO t;V-C50004 2
D-4 X
10 G
MO Q
50 R
NO Note 7 3
.CV-CS0005 2
D-3 X
10 G
MO O
50 NO
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F-4 X
10 G
MO Q
50 R
NO Note 7 g
g
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F-3 X
10 G
MO Q
50 NO 5150 NO
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C-4 X
3 G
MO 10 15 NO GV-CS0009 3
E-4 X
3 G
MO O
15 b--d NO "0V-CS0010 3
F-4 X
3 G
MO Q
15 NO Locked Open ya59 CS0002 2
B-8 X
14 G
M NO Note 4 CS0003 2
B-8 X
10 C
S Q
CS0004 2
B-8 X
10 G
M NO Locked Open
[YJ ed ~
CS0005 2
B-4 X
10 C
S Q
NO Note 4 m_dhd I
NO Locked Open CS0006 2
D-8 X
14 G
M NO Mote 4
$3ED CS0007 2
D-8 X
10 C
S Q
NO Locked Open b
CS0008 2
D-8 X
10 G
M NO Note 4 CS0009 2
D-5 x
10 C
S Q
NO Locked Open CS0010 2
P-8 X
14 G
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F-8 X
10 C
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NO Note 4 NO Locked Open CS0012 2
F-8 X
10 G
M NO Note 4 CS0013 2
D-4 X
10 C
S O
CS0014 3
A-4 X
3 G
M NO Locked Open NO Locked Open CS0015 3
D-5 X
3 Gb M
CS0016 2
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M NO Locked Open CS0018 2
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Containment Soray
. Zion-Unit #1 Page _55 of' _'83 Inservice Test Prcgram Rev. 0 A.S.M.E. Code Class 1, 2 and 3 Valves Drawir.g ' Number:
M-44 1
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Steam Generator-Blowdown Zion Unit #1 Page 5 6 ' o f
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Inservice Test Program R v. O A.S.M.E. Code Class 1, 2 and 3 valves j
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!IOV-SI S 312A 2
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12 G
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15 NO MOV-SIR 312B 2
D-9 X
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NOTES 1) closure of the mainsteam isolation valves during unit oper-ation would result in reactor trip and safety injection actua-tion.
To avoid this transient, these valves will be partial- -
ly stroked every three months.
Full stroke testing will be done during cold shutdown.
i 2)
Full stroke exercising of this check valve will be demon-strated by establishing steam flow to the auxiliary feedwater pump turbine.. Acceptable pump operation will demonstrate acceptable check valve opening.
3)
Closure of the main feedwater isolation valves during unit operation would result in a reactor trip.
These valises provide water as the normal heat removal for the steam gen-erators.
To avoid any transient, these valves will not be stroke tested during unit operation or hot shutdown conditions.
These valves can only be tested at cold shutdown whenever the feedwater and condensate systems are not in operation.
In
,~
cold shutdown the steam generators are placed in the " wet lay-up" conditions with the secondary side essentially filled with feedwater.. Stroke _ testing in this condition with the feedwater or condensate systems in operation would introduce an overfill of the steam generators filling the main steam piping.
The potential of overpressurizing the secondary side of the steam generators would then exist.
This testing period will be each refueling outage as a maximum.
4)
Acceptable full stroke exercising of this check valve will be demonstrated by establishing proper pump discharge flow during periodic pump testing.
5)
These check valves are passively open during normal operation and their required position to perform their safety function is to be open.
The service water and component cooling system are continuously operated and donitored regarding their ability I
to provide adequate. cooling.
Upon system start up after a system shutdown the check, valve is verified as opening by veri-fication of proper system operation.
6)
Same as Note 5.
Additionally, the periodic test of the diesel generators demonstrates proper flow through these check valves by verification of proper 4.ngine fluids temperatures.
- 7).These valves will.be leak tested in accordance with 10CFR50, Appendix J.
Page 78 of 83
+
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Check valves in the spray additive system cannot be exercised without introducing NaOH contaminants into the spray. system.
Operability of these three valves will be verified at a fre-quency of one valve each year.
Operability will be verified by either disassembly of the valve to check for free movement of the moving parts or by a special full flow flushing procedure.
9)
These valves function as containment isolation valves.
Relief is requested from perforning seat leakage testing required by IWV-3420.
As an alternative these valves are tested in accord-ance with 10 CFR 50 Appendix J as required by. Tech. Spec. 4.10.
Additionally these valves are supplied by an Isolation Valve Seal Water System, which is functionally tested as part of this program and Tech. Spec. 4.9.1.
These alternative tests will ad-equately ensure that the containment isolation valve perform their intended function as described in the FSAR.
10)
These IVSW check valves can only be tested by observing flow through downstream tell-tale drain or by disassembly of the valve to verify proper disk freedon of movement.
This testing would render the system unable to perform its safety function.
These valves will be tested during cold shutdown, 11)
Manually operated valves in the reactor coolant pump seal infec-tion lines remain in a normally open condition during unit oper-ation.
Manually operated needle valves are adjusted to regulate seal injection flow to maintain correct pressure differentials at the pump seals.
The seal injection system remains in opera-tion following any postulated accident contributing to the safe-ty injection flow to the reactor coolant system while naintaining and protecting the purp seals.
Should it be required during a protracted accident these valves may be closed and provided with isolation valve seal water.
These valves will be manually stroke tested each cold shutdown providing all reactor coolant pumps are not in operation.
This testing period will be each refueling outage as a maximum.
Relief is taken from measuring stroke time on manual valves.
12)
These manual valves are maintained passively closed during unit operation and are not required to function, other than provide containment isolation, to safely shutdown the reactor or mitigate the consequences of an accident.
Exception is taken to the per-formance of exercising tests as required by IWV-3410.
l l
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Page 79 of 83 l
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13)
Full stroke exercising of the charging pump discharge check valves cannot be demonstrated during unit operation as the i
reactor coolant system pressure prevents the pumps from reach-ing full injection flow conditions.
Partial' stroke exercising of these. check. valves will be demonstrated by establishing proper pump discharge flow during periodic pump testing.
Full stroke exercising of this check valve will be demonstra-ted during cold shutdown providing the reactor vessel head is removed.
Performance of this test with the reactor coolant system intact could lead to an inadvertant overpressurization of the system.
The alternative method of protecting against overpressurization by partial draining of the reactor coolant system to provide a surge volume is not considered a safe practica due to concerns of maintaining adequate water level above the reactor core.
j 14)
Full stroke exercising of.the charging pump suction check valve cannot be demonstrated during unit operation as the reactor' coolant system pressure prevents the pumps from reach-ing full injection flow conditions.
Partial stroke exercising of this check valve will be demonstrated by verifying charg-i ing flow is maintained when the charging pump suction path is transferred from the Volume control Tank to the Refueling Water Storage Tank during the quarterly valve exercise test.
i Full stroke exercising of this check valve will be demonstrated during cold shutdown providing the reactor vessel head is removed. - Performance of this test with the reactor coolant j
- system intact could lead to an inadvertant overpressurization of the system.
The alternative method of protecting against overpressurization by partial draining of the reactor coolant system to provide a surge volume is not considered a safe i
practice due to concerns of maintaining adequate water level above the reactor core.
t f
15)
These check valves cannot be full stroke tested during unit operation as the shut off head of the pumps are lower than reactor coolant system pressure.
Partial stroke exercising of these check valves will be demon-strated by establishing proper pump discharge flow during periodic pump testing.
Full stroke exercising of this check valve can only be demon-strated during cold shutdown providing the reactor vessel head is removed.
This condition.is required to establish suction from the RWST and provide system flow conditions similar to design injection flow.
Performance of this testing with the reactor coolant system depressurized but intact would not provide adequate surge volume for influx from the RWST to allow the
-i R11R injection system to reach these design flows.
The alter-nativo method of providing a surge volume by,tartial draining of'the reactor coolant system is not considered a safe practice
! j cue to concerns of maintaining. adequate water level above the
-reactor core.
Page 80 of 83.
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i 16)
These check valves cannot be tested during unit operation as the shutoff head of the pumps are lower than reactor coolant system pressure.
Full stroke testing of all the branch run check valves will be demonstrated by total pump discharge flow during cold shutdown providing the reactor vessel head is re-moved.
Performance of this test with the reactor coolant system depressurized but intact could lead to an inadvertant overpres-surization of the system.
The alternative method of protecting against overpressurization by partial draining of the reactor coolant system to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core.
17)
These check valves cannot be tested during unit operation as the injection of cold, highly borated water would result in a change in reactor core reactivity and undue thermal cycling of the j
injection nozzles.
1 Full stroke exercising of all the branch run check valves will be i
. demonstrated by total pump discharge flow during cold shutdown providing the reactor vessel head is removed.
performance of i
this test with the reactor coolant system intact could lead to an inadvertant overpressurization of the system.
The alternative method of protecting against overpressurization by partial draining of the reactor coolant system to provide a surge volume is not considered a safe practice due to concerns of maintaining 4
adequate water level above the reactor core.
18)
These check valves cannot be full stroke tested during unit operation as the shut off head of the pumps are lower than reactor coolant system pressure.
Partial stroke exercising of these check valves will be demon-strated by establishing proper pump discharge flow during periodic pump testing.
Full stroke exercising of this check valve will be demonstrated during cold shutdown providing the reactor vessel head is removed.
Performance of this test with the reactor coolant system intact could lead to an.inadvertant overpresaurization of the system.
The alte" native method of protecting against overpressurization by partial draining of the reactor coolant system to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core.
19)
These check valves cannot be tested during unit operation as the shutoff head of the pumps are lower than reactor coolant system pressure.
(Con't)
I I
Page 81 of 83 L
~
i Full stroke exorcising of all the branch run check valves can only be demonstrated by total pump discharge during cold shut-i down providing the reactor vessel head is.romoved.
This condi-tion is required to establish suction from the RWST and provido system flow conditions similar to design injection flow.
Per-formance of this testing with the reactor coolant system depres-
' surized but intact would not provide adequate. surge volume for influx from Yh'e RWST to allow the RHR injection system to reach 4
these design flows.
The alternative method of providing a surge volume by partial draining of the reactor coolant system is not considered a safe practice due to concerns of maintaining adequate water level ~above the reactor core.
20)
The accumulator check valves cannot be tested during unit operation due to the pressure differential between the accumu-
}
lators (
600'psig) and the reactor coolant system (2235 psig).
These valves cannot-be full stroke tested except by a rapid 1
depressurization of the reactor coolant system as would occur during the design basis cold leg double guillotine break.
These j
valves will.be partial
- stroke tested during cold,. shutdown.
21)
Component cooling water flow to the reactor coolant pumps is required at all. times the pumps are in operation.
Failure of one of these valves in a closed position during exercise test would result in a logs of the cooling flow to the pumps.
Exemp-4 tion is taken to the quarterly exercise test.
The valves will be exercise tested during colc shutdown providing all reactor coolant pumps are not in operation.
This testing period will be r,..
each refueling outage as a maximum.
4 f
22)
This check valvo is in the containment air particulate and, gas.-
monitor return line.
The containment monitor is in continuous operation during unit operation and'is also required for con-tainment sampling an the event of an accident since it is passively open and required to stay open.
The continued preper operation of the system serves to demonstrate proper check valvo operation.
23)
This manual valve is in the containment air particulate and gas monitor return line.- Quarterly closing of this valve duriag
- operation.would render.the system unable to perform its sampling function.
Full stroko. testing will be performed during cold shutdown.. Relief is taken from measuring stroke time on manual valves.
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24)
The requirerent for the containnent _ air particulate and gas monitor return line isolation is one valve.
The leak test can only be perforned using both the check valve (PR0029) and the relief valve 'in series as one containment isolation bo indary.
25)
Closure of these valves during normal unit operation would result in a loss of letdown flow resulting in a reactor in a reactor coolant inventory transient and a subsequent reactor trip.
These valves will be full. stroke exercised during cold shutdown as required by ASME Section XI, IWV-3 410 (b) (1).
26)
These valves are located in a closed valve containment assenbly
- which is designed as an extension of the containnent boundary.
These valves are inaccessable during plant operation.
The valves can be unde accessable during plant shutdown by disassembly of the valve containnent assembly.
This requires approximately 100 man-hours per valve in a radiation field up to 50 mr per hour.
Verification that the valve position indication switches have changed in relation to valve position can be made by ob-serving that no significant change in valve stroke time has occurred.
Due to the burden in manpower and radiation exposure to perform the direct observation, relief is taken from the requirements of.IWV-3000.
27)
These valves can only be full stroke tested by rendering their control systems inoperable.
These valves will be full stroke tested during cold shutdown.
28)
The RHR Suction valves.from the reactor coolant system cannot be stroke tested during power operation.
These valves are inter-locked with reactor coolant system and are prohibited from open-ing above 425 psig.
Opening these valves would cause a depressur-iration of the reactor coolant system and overpressurization of the RHR System.
These valves will be full stroke tested during cold shutdown.
29)
This motor operated valve in the reactor coolant pump seal injection return line must remain in a normally open condition during uni.t-operation in order to maintain proper pump seal flow.
This valve will be stroke tested each cold shutdown providing all reactor coolant pumps are-not in operation.
This testing period will be each refueling outage as a maximum.
Page'83 of 83
~
t3RC Docket No. 50-304 ATTACHMENT 2 Zion Unit 2 Inservice Valve Test Program t
h I
i e
i -
i
=.. (
)
ZION UNIT 82 INSERVICC VALVE TEST PROGRAM The following table includes all of the valves required to be exercise and leak tested in accordance with ASME Section XIe 1974 edition up to and including Summer 1975 Addenda, Subsections IWV.
Relief from some of the requirement of Section XI are requested as indicated in~the Relief Request column with explanations given in the Remarks.
The alternative tests are indicated in the Test columns and also explained in the Remarks.
Below listed are the symbols' used'to indicate valve type,
~
valve actuator type, exercise test frequency, and leakage test frequency.
Valve Type:
G - Gate DG - Double Disk Gate I
Gb - Globe D - Diaphragm i
R - Angle Relief
.)
C - Swing Disk check B - Butterfly i
N - Needle ji ji Actuator Type:
AO - Air MO - Motor 1
HO - Hydraulic j
M - Manual S - Self-Actuating
}
Exercise Test Frequency:
Q --Quarterly l-C - Cold Shutdown
-l C1 - Cold Shutdown with no reactor coolant pumps operating.
C2 - Cold Shutdown with the reactor vessel h
head removed.
C3 - Cold Shutdown with feedwater and il condensate system not operating.
h R - Refueling Outage J
I - Frequency Defined by IWV-3510 I!
b
. i a
V 3
1 F
Page 46 of 83 l'it i __
+
g Page g)of _8_3_
Systen:~ M ain Steam Zion Unit f2 J
hstrvicoTestProgram R v. 0 A.S.M.E. Code Class 1, 2 and 3 Valves Drawing Nt:=ber: M-500 b
Test nmo o
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.-.e-Request Remarks l
l l
HOV-MS0001 j2 E-5 lX 34 AGb HO G/C 5
NO Note 1 HCV-MS0002 e2 D-5 X
34 AGb HO C/C 5
NO
- ote 1 HOV-MS0003 2
C-5 X
34 AGb HO O/C 5
NO Note 1 (HOV-MS0004 2,
A-5 X
34 AGb HO O/C 5
NO Note 1 i
MS0014 2
E-7 X
6 R
S I
NO t
MS0015 2-E-7 X
6 R
S I
NO MS0016 2 !
E-6 X
6 R
S I
NO I
MS0017 2
E-6 X
6 R
S I
NO f
MS0018 2
E-6 X
6 R
S I
NO j
HS0019 2
D-7 X
6 R
S I
NO j
MS0020 2
D-7
'X 6
R S
I NO MS0021 2
D-6 X
6 R
S I
NO
.MS0022 2
D-6 X
6 R
S I
NO MS0023 2
D-6 X
6 R
S I
NO MS0024 2
B-7 X
6 R
S I
NO MS0025 2
B-7 X
6 R
S I
NO MS0026 2
B-6 X
6 R
S I
NO MS0027 2
B-6 X
6 R
S I l--
NO MS0028 2
B-6 X
6 R
S I
g--
NO l--
NO MS0029 2
A-7 X
6 R
S I
NO I
MS0030 2
A-7 X
6 R
S I
I - l--
NO MS0031 2
A-6 X
6 R
S MS0032 2
A-6 X
6 R
S I
NO MS0033 2
A-6 X
6 R
S I
NO MOV-MS0005 2
F-9 X
6 G
MO O
30 NO MOV-MS0006 2
P-9 X
6 G
MO O
30 NO
, MOV-MS0011 3
C-8 X
6 G
MO O
30 NO FCV-MS57 3
F-5 X
4 G
AO Q '--
NO MS0006
- 3 F-9 X
6 C
S Q
NO Note 2 NO Note 2 MS0007 3
D-9 X
6 C
S Q
l I,
1
Sys' c=:
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Inservice Test Program Rev. 0 A.S.M.E. Code Class 1, 2 and 3 Valves
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.F-3 X
16 G
MO C3 30 NO Note 3 NU Note 3
':7.'-F :M17
'2 D-3 X4 16 G
MO C3 30 Y
.NO Note 3
- 77-n;0018 ~
2 B-3 X
16 G
MO C3 80 NO Note 3 6
9~
,/;7-?;2019
'2 A-3 X
16 G
MO C3 80 NO Note 4 0
>)
FWC3 6 2
-F-2 X
3 C
S Q
-~
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770067 2
D-2 X
3 C
S Q
NO Note 4 F 00C3 2
C-2 X
3 C
S Q
3 NO Note 4 O
.F:0069
- 2 A-2 X
3 C
S Q
D:0031 3
E-10 x
4 C
S O
NO Note 4 UO Note 4 7.X,~032 3
E-9 x
4 C.
S Q
NO Note 4 gg F :0 t33 3
E-8 X
'4 C
S Q
NO Locked Open FWOO34 3
E-10 X
6 Gb M
NO Locked Closed W
i FWOO35 3
E-9 X
4 Gb M
NO Locked Open g
FX.2036 3
E X 4
Gb M
NO Locked Closed FWG037 3
E-9 X
4 G
M g-NO Locked Open b
I n:0033 3-E-?
X 4
G M
g e
NO Locked Open
}
7N0039 3
D-10 X
lh Gb M
l FUO0f0 3
D-9 X
1 Gb I-1 NO Locked Open NO Locked Open
?WG041 3
D-3 X
lh Gb M
NO Locked Open FX0042 3
D-9 X
4 Gb M
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Page50)of83-Systems Mervice Water Zion Unit-#2 Rev. 0.
~F service Test Program A.S.M.E. Code Class 1, 2 and 3 Valves
.'y Dra:ing Number: M-32-2 Test Ao o
5 N
E.
b c
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'E Eo-Category N
g j
g Eunber o
oA A B C D E
M M
M d
Request Re arks NO MOV-SW0001 3
.D-6 X
20 G
MO O
100 NO MOV-SWOOO2 3
D-5 X
20 G
MO Q
100 NO
'MOV-SWOOO7 3
A-3 X
10 Gb MO Q
150 NO MOV-SW0008 3
A-3 X
10 Gb MO Q
150 NO MOV-SWOOO9 3
B-3 X
10 Gb MO Q
150 MOV-SWOO10 3
B-3 X'
10 Gb MO O
150 NO NO
-MOV-SWOOli 3
C-3 X
10 Gb MO Q
150 NO Note 6 SWOO10 3,
D-3 X
6 C
S Q
NO Note 6 SWOOll 3
E-3 X
6 C
S Q
NO Note 6
'OSWOO12 3
F-3.
X 6
C S
Q NO i
.MOV-0100 3
B-4 X
24 B
MO Q
60 MOV-0101-3 C-5 X
8 G
MO Q
40 NO MOV-0102 3
C-5 X
8 G
MO Q.
40 NO MOV-0103 3
C-4 X
8 G
MO Q
40 NO I 3 C-5 X
8 G
MO Q
40 NO MOV-0104 MOV-0105 3r C-4 X
8 G
MO Q
40 NO MOV-Oll5 3
B-4 X
24 B
MO Q
60 NO OMOV-SWOOO7 3
D-5 X
12 B
MO Q
60 NO CMOV-SW0008 3
D-5 X
12 B
MO Q
60 NO NO Locked Open SWOl79 3
C-5 X
8 G
M NO Locked Open SWO767.
3 A-4 X
20 B
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Isolntion Valve Zion Unit #2 Pacc _S2_ of _83 c _.
Inservice Test Progrc.m R v. O Sul Water A.S.M.E. Code Class 1, 2 and 3 Valves J
Dratting Number:
M-512 Test 2o o
t'
.C o
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- n o
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C C
C h
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H 04 o H
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Relief Number U
C4 A B C D E
M W
M 4
Request Remarks LCV-IE01 NA C-1 X
1 G
AO C
60 YES Note 27
, LCV-IWO2 NA B-1 X
1 G
AO C
60 YES Note 27 i PCV-IWO3 NA C-1 X
1/2 G
AO C
60 YES Note 27 i
IW0001 NA C-1 X
1 C
S C
YES Note 10 IWOOO3 NA C-1 X
1 C
S C
YES Note 10 FCV-IWO8 NA B-5 X
3/4 G
AO O
60 NO FCV-IWO9 UA B-5 x
3/4 G
AO Q
60 NO FCV-IU10 NA B-6 X
3/4 G
AO Q
60 NO FCV-IHil NA B-6 X
3/4 G
AO Q
60 NO FCV-IW12 NA B-3 X
1/2 G
AO O
60 NO FCV-IW13 NA, B-3 X
1/2 G
AO O
60 NO FCV-IW14 NA B-7 X
1/2 G
AO Q
60 NO FCV-IMIS NA B-7 X
1/2 G
AO Q
,60 NO FCV-IW16 NA B-3 X
3/4 G
AO Q
t60,--
NO FCV-IW17
,NA B-3 X
3/4 C
AO O
60'--
NO IU0073 8NA C ~1 X
3/8 C
S C.
YES Note 10 IWOO74 NA C-7 X
3/8 C
S C
YES Note 10 l
IN0075 NA D-3 X
3/8 C
S C
l --
YES Note 10 IWOO76 NA D-3 X
3/8 C
S C
j --
YES Note 10 IE0077 UA D-3
,X-3/8 C
S C
'l --
YES Note 10 lX IWOO78
,NA D-3 X
3/8 C
S C
YES Note 10 IN0079
'NA D-3 3/8 C
S C
YES Note 10 IWO181 NA D-5 X
3/8 C
S C
YES Note 10 IWO182 NA D-5 X
3/8 C
S C
YES Note 10 IWOl83 NA D-5 X
3/8
'f S
C YES Note 10 IW0lS4 NA D-6 X
3/8 C
S C
YES Note 10 IWOl85 NA D-6 X-3/8 C
S C
YES Note 10
--{-
IE0198 NA C-4 Xl 1/2 C
S C
YES Note 10 IW0058 NA B-4 X
1/2 C
S C
-- }--
YES Note 10 IU0059 NA B-4 X
1/2 C
S C
--f-YES Note 10
- _ $J[,cc5.
- ' isolalion valve' Zion. Unit #2 Page-53 of '83
~
i-Inservica Test Prcgram Rev. 0 Son 1 Water
' d A.S.!!.E. Code Class 1, 2 and.3 Valves 3
~"
lDrawir.g' Nt=ber:
M-512 Test n
U c
G e
c-E a
U 0.
r
-c C
C h-k 0
b*
<-i Do
.H b
O-fA U
S u
ca
~
v' GC or
- 4 Valve G
5
'o 4LS 4
o 3m o
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' valve l!
$0 Category-y g
g g
g g
p,yg,g t:: her U
CA A B C DlE G
M M
4 Request Remarks-IWOO60.
NA B X 1/2 C
S C
YES Note 10
~'
- IWOOG1 NA B-4 X
1/2' C
S C
YES Hote 10 In0062.
NA B-5 X
1/2 C'
S C
YES Note 10 IU0063 NA B-6 X
1/2 C
S C
YES Note 10 IW0064 NA B-5 X
1/2 C
S C
YES Note 10 1U0065 NA B-5 X
1/2 C
S C
YES Note 10 IM0066
'A B-6 X
1/2 C
S C
N YES Note 10 IU0067 NA C-3 X
1/2 C
S C
YES Note 10 IWOO68 NA C-3 X
1/2 C
S C
YES Note 10 IU0069 NA C-3 X
1/2 C.
S C
.YES Note 10 IWOO70 NA C-4 X
1/2 C
S C
YES Note 10 IWOO72 NA C-4 X
1/2 C
S C
YES Note 10
- IM0080; INA D-3 X
1/2 C
S C
YES Note 10 IWOO81 I
tUi E-5 X,
1/2 C
S C
YES Note 10 IWOO32-NA D-6 X
1/2 C
S C
YES Note 10 IWOO83-NA D-6 X
1/2 C-S C
YES Note 10 IWOOS4 NA D-4 X
1/2 C
S C
i YES Note.10 IUOl60
'IUt B-2 X
1 R
S C
YES Note 10 IWG162 NA C-1 X
3/4 C
.S C
YES Note 10 IM0090 NA F-3 X
1/2 C
S C
YES Note 10 IWOO95 NA
'E-5 X
'1/2 C
S C
YES Note-10 IWOl86 NA E-4:
X 3/8 C
S
,C YES Note 10 i
- 4
~
~
Zion Unit #2 Page _53_ cf._I83 i":ter :
containmont Sorav
~
Inservice Test Progrcm Rev. 0 A.S.M.E. Code Class 1, 2 and 3 Valves l
- Drawing Nur.ber
- ' M-514 Test Eo o
c
. e:
o e
m
=
0 c.
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No Category y
g g
g g
g g
- umber U
C4 A
B C D E
M
~N O
4 Request-Re narks MOV-CS0002.
2
.B-4 LX 10 G
MO O
50 R
NO Note 7 M3V-CS0003
'2 C-3 X
10 G
MO Q
50 NO MOV-CS0004 2
D-4 X
10 G
MO Q
50 R
NO Note 7 MOV-CS0005 2
D-3 X
10 G
MO Q
50 NO
.-;MOV-CS0006
- 2 F-4 X
10 G
MO O
50 R
NO Note 7 iMSV-CS0007-
'2 F-3 X
10 G
.MO O
50 NO
'MOV-CS0008-3 C-4 X
3 G
MO Q
15 NO MOV-CS0009 3
E-4 X
3 G
MO O
15 NO MOV-CS0010 3
F-4 X
3 G
MO O
15 NO CSC002
- 2 B-8 X
14 G
H NO Locked Open CS0003 2
B-8 X
10 C
S Q
NO Note 4 C50004
- 2 B-8 X
10 G
M NO Locked Open CS0005 2
B-4 X
10 C
S Q
NO Note 4 CS0006 2
D-8 X
14 G
M NO Locked Open
'CS0007 2
D-8 X
10 C
S Q
NO Note 4 C50008 2
D-8 X
10 G
M NO Locked Open 1
i CS0009 2
D-5 X
10 C
S Q
NO Note 4 i
CS0010 2
F-8 X
14 G
M NO Locked Open CS0011 2
F-8 X
10 C
S Q - l ---
NO Note 4 CS0012 2
P-8 X
10 G
M NO Locked Open
-C50013 2
D-4 X
10 C
S O
NO Note 4 CS0014 3
A-4 X
3 G
M NO Locked Open CS0015 3
D-5 X
3 Gb M
NO
. Locked Open
-CS0016 2
C-8 X
3 C
S T
YES Note 8 CS0017 2
C-8 X,
3 G
M NO Locked Open
-C50013 2
- C-9 X
6 C
S Q
NO Note 4 CS0019 3
.A-4 X
3 G
M NO Locked Open i
'CSC020 3
E-5 X
3 Gb M
NO Locked Open CSC021 2
E-8 K
3 C
S T
YES Note 8 C50022 2! E-9 I
X 3
G M
NO Locked.Open t
l I
_I
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t'
. a,w.
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-~a
+
~
o s,2yr a..: - Containment scrav Zion Unit #2
.hoo-55 of 83:
Inser.Vice Test Program Rav. - 0 A.S.M.E. Cod? Class 1, 2 and 3 Valves
. Drawi -g N=bar:
M-514 y
Test
. ts n
U2W o
m A'
O 6
m o
a.
c c
c C
- >i k
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4 o
Relief
. N-..b e r '
O Cd A B C D E
M N
M 4
Request Rer. arks CS0023; 2
D-4 X
6 C-S Q
NO Note 4 CS0024 3'-A-4 X
3 G
M NO Locked Open CS0025 3
F-5.
X 3
Gb
.M NO Locked Open
~
CS0026 -
.2 F-8 X
3 C
S T
YES Note 8
.CS0027 2
F-8 X
3 G
H NO Locked Open g
CS0028
.2 E-9.
X 6
C S
Q NO Note 4 CS0029 2
C-9 X
1 Gb M
NO Locked Closed CS0030.
2 C-9' X
1 Gb M
NO Locked Closed
..CS0031 2
E-9 X
1 Gb M
NO Locked Closed CS0032 2
E-9
.X 1
Gb M
NO Locked Closed CS0033 2
F-9
'X 1
Gb M
NO Locked Closed CS0034 2
F-9 X
1 Gb M
NO Locked Closed CS0037 2
E-4 X
X 6
G M
R NO Locked Closed, Note 7-CS0038 2
B-4 X
X 1
G M
R NO Locked Closed, Note 7 CS0039.
2 C-4 X
X 1/2 Gb M
-R NO Locked Closed, Note 7
.CS0040 2
C-4 X
X 6
G H
R NO Locked Closed, Note 7 CS0041 2
D-4 X
X 1
G M
-- j--
R NO Locked Closed, Note 7
.CS0042 2
D-4 X
X 1/2 Gb M
--j--
R NO Locked Closed,-Note 7 CS0043 2
E-4 X
X 6
G M
R NO Locked Closed, Note 7 CS0044 2
E- $
X X
1 G
M R
NO-Locked Closed, Note 7 CS0045 2
E-4 X
X 1/2 Gb M
R NO Locked Closed, Note 7 CS0049'
-3
'C-5 X
3 Gb M
NO Locked Closed CS0050 3
- E-5 X
3 Gb M
NO Locked Closed CS0051 3
F-5 X
3 Gb M
NO Locked Closed l
t 1
' Sys t cc.: ' Ste"m Generator Blowdown Zion Unit 02 Page 56 cf _43 Inservice Test Program Rev. 0 Drawir.g Number:
M-45-1 f
~
Test nm O
O C
.C O
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c o
x 4
o Relief
- ~1=her U
Q4 A
B C D E
W N
W 4
Request Remarks FCV-SS02 2
E-7 X
3/8 G
AO Q
60 NO FCV-S303 2
D-7 X
3/8 G
AO O
60 NO FCV-SSO4 g2, B-7 X
3/8 G
AO.Q 60 NO FCV-SSOS 2
A-7 X
3/8 G
-Q 60 NO
-FCV-B317 2
B-6 X
235 G
AO, O 60 NO 7.OV-BD0001 2
F-8 X
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Drawing. Number: M-521 i
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.-._-.-,.--.-~-a.-.~-...
Systen:
Smfety Iniection Zion Unit # 2 Pr.go g of g Inservice Test Program Rov. O A.S.M.E. Code Class 1, 2 and 3 Valves
- Drawing Nu.mber:
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Safety Iniection Sicn Unit #2 Page 66
.of ' 33 Inservice Test Program
~Rav. 0-ass 1, 2 and 3 Valves Drawing Number:
M-522 L
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B-6 X
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B-7 X
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NO SIB 880 2
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60-NO SI8948A 1
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Sys:cc:
Component Coolina Zion Unit #2 Pace 6 8 ' of ' '83 Inservice Test Program Rev. O
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Drawing Number:-
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Inservice' Test Program Rav. : 0
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NOTES 1)
Closure of the'mainsteam isolation valves during unit oper-ation would result in reactor trip and safety injection actua-tion.
To avoid this transient, these valves will be partial-ly stroked.every three months.
Full stroke testing will be done during cold shutdown.
2)
Full stroke exercising of this check valve will be demon-strated by establishing steam flow to the auxiliary feedwater pump-turbine.. Acceptable pump operation will demonstrate acceptable check valve opening.
3)
Closure of the main feedwater isolation valves during unit operation would result in a reactor trip.
These valves provide water as ^ the normal heat ren. oval for the steam gen-s erators.- To avoid any transient, these valves will not be stroke tested during unit operation or hot shutdown conditions.
.These valvesLcan only be tested at cold shutdown whenever the feedwaterLand condensate systemsfare not in operation.
In cold shutdown the steam generators are placed in the " wet lay-up" conditions'with the secondary side essentially filled with feedwater.- Stroke testing in this condition with the feedwater or condensate systems in~ operation would introduce an overfill I
of.the steam generators filling'the main steam piping.
The potential'of overpressurizing the secondary side of the steam generators'would then-exist.
This testing period will be each
}
refueling outage'as a maximum.
4). Acceptable full stroke exercising of this check valve will be demonstrated by establishing' proper pump discharge. flow during periodic. pump testing.
5)
These check valves are passively open during normal operation and their-required position to perform their safety-function is to:be open.
The service water and component cooling system are continuously operated and monitcred regarding their ability to' provide adequate cooling.
Upon system start up after a t
system shutdown the check valve is verified as opening by veri-
-fication of proper. system operation.
6)
Same as Note.5.s Additionally, the periodic test of the diesel generators demonstrates proper flow-through these check valves by verification of' proper engine fluids temperatures.
7)
TheseEvalves will besleak tested in accordance with 10CFR50, Appendix J.
-Page 78 of_83 a,;_
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- 8) ' Check valves in the spray additive system cannot be exercised without introducing NaOH contaminants into the spray. system.
Operability. of these three valves will be verified at a fre-quency of one valve each year.
operability will be verified
. by either disassembly of the valve to check for free movement of the moving parts or by a special full flow flushing procedure.
9)
These valves function as containment isolation valves.
Relief is requested from performing seat leakage testing required by IWV-3420.
As an alternative these valves are tested in accord-ance with 10 CFR 50 Appendix J as required by Tech. Spec. 4.10.
Additionally these valves are supplied by an Isolation Valve Seal Water System, which is functionally tested as part of this program and Tech. Spec. 4. 9.1.
These alternative tests will ad-equately ensure that the containment isolation valve perform their intended function as describe,d in the FSAR.
10)
These IVSW check valves can only be tested by observing flow through downstream tell-tale drain or by disassembly of the valve to verify proper disk freedon of novement.
This testing j
would render the system unable to perform its safety function, j
These valves will be tested during cold shutdown.
t i
11)
Manually operated valves in the reactor coolant pump seal infec-tion' lines remain in a normally open condition during unit oper-i ation.
Manually operated needle valves are adjusted to regulate I
seal injection flow to maintain correct pressure differentials 5
at the pump seals.
The seal injection system remains in opera-tion following any postulated accident contributing to the safe-i ty injection flow to the reactor coolant system while unintaining and protecting the pump seals.
Should it be required during a i
protracted accident these valves may be closed and provided with isolation valve seal water.
I1 These valves will be manually stroke tested each cold shutdown providing all reactor ' coolant pumps are not in operation.
This testing period will be each refueling outage as a maximum.
Relief is taken from measuring stroke time on manual valves.
12)
These manual valves are maintained passively closed during unit operation and are not required to function, other than provide i
containment isolation, to safely shutdown the reactor or mitigate the consequences of an accident.
Exception is taken to the per-formance of exercising tests as required by IWV-3410.
Y r
Page 79 of 33
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13)
Full stroke' exercising of the charging pump discharge check valves cannot be demonstrated during unit operation as the 1
reactor coolant system pressure prevents the pumps from reach-ing full injection flow conditions.
Partial stroke exercising of these' check valves will be demonstrated by establishing preper pump discharge flow during periodic pomp testing.
i Full' stroke exercising of this check valve will twe demonstrr-ted during cold shutdown providing the reactor vessel head is removed.
Performance of this tsat with the reactor coolant system intact could lead.to an inadvertant overpressurization a
E of the system.
The alternative method of protecting against overpressurization by partial draining of the reactor coolant system to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate water level
~
above the reactor. core.
4 14)
Full stroke exercising of the charging pump suction check 4
valve cannot be demonstrated during unit operation as the reactor coolant system pressure prevents the pumps from reach-ing full injection flow conditions.
Partial stroke exercising l
l of this check valve will be demonstrated by verifying charg-l ing flow is maintained when the charging pump suction path is transferred from the Volume Control Tank to the Refuelirg Water Storage Tank during the quarterly valve exercise test.
i Full stroke exercising of this check valve will be demonstrated during cold shutdown providing the reactor vessel itead is j
4 removed.
Performance of this test with the reactor coolant system intact could lead to an inadvertant overprassurization of the system.
The alternative method of protecting against overpressurization by partial draining of the reactor coolant system ~to provide a surge volume is not-considered a safe practice due to concerns of maintaining adequate water level above the reactor core.
15). These check valves cannot be full stroke tested during unit operation as.the shut off head of the pumps are lower than f
reactor coolant system pressure.
Partial stroke exercising of these check valves will be demon-strated by establishing proper pump discharge flow during periodic pump testing.
Full-stroke exercising of this check valve can only be demon-l
-strated during cold shutdown providing the reactor vessel head l
is' removed.- This condition is required to establish suction j
from'the RWST and provide system flow conditions.similar to
[
design' injection flow.
Performance of this testing with the reactor coolant system depressurized but intact would not provido adequate surge volume for influx from the RWST to allow the t
RHR in4cction systom to reach these donian flows.
The alter-1
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reactor core.
Page 80 of 83.
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These check valves cannot be tested during unit operation as the shutoff head of the pumps are lower than reactor coolant system pressure.
Full stroke testing of all the branch run check valves will be deronstrated by total pump discharge flow during cold shutdown providing the reactor vessel head is re-moved.
Performance of this' test with the reactor coolant systen r
depressurized but i.ntact could lead to an inadvertant overpres-surization of the system.
The alternative method of protecting
.against overpressurization by partial draining of the raactor coolant system to provide a surge volume is not considered a safe practice due to. concerns of maintaining adequate water level above tl.a reactor core.
17)
These check valves cannot be tested during unit operation as the injection of cold, highly borated water would result in a change 4
in reactor core reactivity-and undue thermal cycling of the injection nozzles.
Full stroke exercising of all the branch run check valves will be demonstrated by total pump discharge flow during cold shutdown i
providing the reactor vessel head is removed.
Performance of this test with the reactor coolant system intact could lead to an inadvertant overpressurization of the system.
The alternative method of protecting against overpressurization by partial draining of the reactor. coolant system to provide a surge volume is not considered a safe practice due to concerns of maintaining
- ads, te water level above the reactor core.
18)~
These check valves cannot be full stroke tested during unit operation as the shut off head of the pumps are lower than reactor coolant system pressure.
4 Partial stroke exercising of these check valves will be demon-
.strated by establishing proper pump discharge flow during periodic-pump testing.
Full stroke exercising of this check valve will be demonstrated during cold shutdown providing-the reactor vessel head is removed.
Performance of this test with the reactor coolant system intact could lead to an inadvertant overpressurization of the system.
The alternative method of protecting against overpressurization t
by rartial draining of the reactor coolant system to provide a su.ge volume ~is noc considered a safe practica due to concerns of maintaining adequate water letal above the reactor core.
19)
These check valves cannot be tested during unit operation as the shutoff head of the pumps are lower than reactor coolant system
-pressure.
(con't)
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l Page 81 of 83
I'
. Full stroke exerciping of all the branch run check valves van only be demonstrated by total pump discharge during cold shut -
This condi-down providing tho-reactor vessel head is removed.
]
. tion is required to establish suction from the RWS? and provido system flow conditions similar to design injection flow.
Per-formance of this testing with the reactor coolant system depres-surized but intn.ct.would not provide adequate surge volume for influx from't'he RWST to allow the RiiR~ injection system to reach these design flows.
The alternative method of providing a surgo volume by partial drtining of the reactor coolant system is not considered a safe p'ractice due to concerns of maintaining adequate water level'above the reactor-core.
20)
The accumulator check valves cannot be tested during unit operation due to the pressure differential between the accumu-lators (
600 psig) and the reactor coolant system (2235.psig).
These valves cannot be full stroke tested except by a rapid depressuriz'ation of the reactor coolant system as wocid occur These during the design basis cold leg double guillotine break.
valves will be partial' stroke tested during cold,. shutdown.
I 21)
Component cooling water flow to the reactor coolant pumps is reqaired at all. times the pumps are in operation.
Failure of one of those valves in a closed position during_cxercise test would result in a loss of the cooling flow to the pumps.
Exemp-
' tion is taken to the quarterly exercise test.
The valves will i
be exercise tested during cold shutdown providing all reactor
~,
coolant pumps are not in operation.
This testing period will be
)
l each refueling outage as a maximum.
t This check valve is in the containment-air particulate and, gas.
22)
.i monitor. return line.
The containment monitor is in' continuous operation during' unit operation and is also required for con-tainment sampling in the event of an accident since it is
. passively open and required to stay open.
The continued proper operation of the system serves to demonstrate proper check valve operation.
23)
This manual valve is in the containment air particulate and gas monitor return line.- Quarterly closing of this valve during operation'would render the system unable to perform its sampling function.
Full stroke testing will be performed during cold g
1 shutdown.
Relief is taken from measuring stroke time on manual valves..
1
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24)
The requirement for the containnent air particulate and gas monitor return line isolation is one valve.
The leak test can only be perforned using both the check valve (PR0029) and the relief valve in. series as one containment isolation bos.dary.
25) closure of these valves during normal unit operation would result in a loss of letdown flow resulting in a reactor in a reactor coolant inventory transient and a subsequent reactor trip.
These valves will be fu2 stroke e>ercised during cold shutdown. as required by ASME Section XI, IWV-3410 (b) (1).
26)
These valves are located in a closed valve containment assembly which is designed as an extension of the containment bounde.ry.
These valves are inaccessable during plant operation.
The valves can be made accessable during plant shutdown by disassembly of the valve containnent assembly.
This requires approximately 100 man-hours per-valve in a radiation field up to 50 mr per hour.
Verification that the valve position indication switches have changed in relation to valve' position can be made by ob-serving that no significant change in valve stroke tine has occurred.
Due to the burden in manpower and radiation exposure to perform the direct observation, relief is taken from the requirements of IWV-3000.
27)
These valves can only be full stroke tested by rendering their control systems inoperable.
These valves will be full stroke tested during cold shutdown.
28)
The RER Suction valves from the reactor coolant system cannot be stroke tested during power operation.
These valves are inter-locked with reactor coolant system and are prohibited from open-ing above 425 psig.
Opening these valves would cause a depressur-ization of the reactor coolant system and overpressurization of the RHR System.
These valves will be full stroke tested during cold shutdown.
29)
.This motor operated valve in the reactor coolant pump seal injection return line must remain in a normally open condition during unit operation in order to maintain proper pump seal flow.
This valve-will be stroke tested each cold shutdown providing all reactor coolant pumps are not in operation.
This testing period will be each refueling outage as a maximum.
t Page 83 of 83
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I,INITING CONDITION FOR OPERATION SURVEILLANCE REQUIRM ENT 3 3.4 4.3.4.C.1 2.
Inservice testing of ASME Code r
Class 1, Class 2, and Class 3 pumps and valves shall be performed.
in accordance with Section XI of the ASMB B0iler and Pressure.
Vessel Code and applicable addenda as required by 10CFR50, Section 50.55a(g), except where specific written relief has been granted by the NRC pursuant to 10CFR50, Section 50.55a(g)(6)(1).
103 a
a