ML20151D106
| ML20151D106 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 04/08/1988 |
| From: | Kent G PORTLAND GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20151D100 | List: |
| References | |
| PGE-1048, NUDOCS 8804130394 | |
| Download: ML20151D106 (200) | |
Text
- w k.-cra.::a
.. :1,r;u w ':s.
M..-ki;.
. O:.1: &
J ?r-.W 15hi
- k '.widtb Di1 l* 21 h N, a
s PGE-1048 Revisior. 1
(.%..;
7 3
3 t
i I
g I
TROJAN NUCLEAR Pt. ANT 9
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES SECOND 10-YEAR INTERVAL by Greg J. Kent l
i 1
\\..
t Portland General Electric Company 121 SW Salmon Street Portland OR 97204
^
9 s
8804130394 880400 DR ADOCK 05000 4
..-:. bm.W h.Lw.'.u:x 2:d% laOs w
,+m6
-.~m.,
- w. e w...: ~.
,,...a TROJAN NUCLEAR PLANT j (.]'
PUMP AND VALVE l/
INSERVICE TESTING PROGRAM CON'IENIS 1
i Section Title Pate
)
1.0 INTRODUCTION
1.0-1 t
2.0 ADMINISTRATIVE CUNTROLS 2.0-1
}
i 3.0 INSERVICE TESTING OF filMPS.
3.1-1 3.1 PUMP
SUMMARY
3.1-1 3.1.1 Reference Values and Tolerances 3.1-3 3.1.2 Records 3.1-4 3.2 RELIEF REQUESTS FOR PUMPS 3.2-1 T
3.2.1 Service Water System: Pumps P108A, P108B, P108C.
3.2-1 3.2.2 Diesel Fuel Oil System: Pumps P144A and P144B.
3.2-2 3.2.3 Feedwater System: / umps P102A and P102B.
3.2-4 i
3.2.4 Chemical and Volume Conv. col System: Pumps P205A and
[
P205B.
3.2-4 3.2.5 Component Coolin5 Unter System: Puuips 210A, P2108, j
and P210C.
3.2-5 3.2.6 Chemical and Volume Control System: Pumps P211A and P2 MB.
3.2-6 1
4.0 INSERVICE TESTING OF VALVES
,4.1-1 4.1 VALVE
SUMMARY
4.1-1 2
4.2 CATEGORY A AND B VALVES 4.1-4 4.3 CATEGORY C VALVES 4.1-5 4.4 MULTIPLE CATEGORY VALVES.
4.1-5 4.5 PASSIVE VALVES.
4.1-6 4.6 RECORDS 4.1-6 4.7 FULL-STROKE EXERCISING.
4.1-6 4.8 PART-STROKE EXERCISING 4.1-6 4.9 CONTAINMENT ISOLATION VALVES.
4.1-7 4.10 WASH-1400 EVENT V VALVES 4.1-8 4.11 LEAK TESTING MO-8701 AND MO-8702.
4.1-8 j
4.12 LEAK TESTING MO-8812.
4.1-8 4.13 RELIEF RJQUESTS.
4.1-8 6
i Revision 1 (April 1988)
)
o.
. ~.e.
--___..~_.._.2a._,
---_m...-u
. - _ w -. w.........__e
.____m.......:.._~.-_._
. -4,...,..
Li ll
)
TROJAN NUCLEAR PLANT d~
PUMP AND VALVE INSERVICE TESTING PROGRAM
- if:
TABLES t
- t.
- s 1
.i Section Title
?
L 3.1-1 Inservice Testing Program for Pumps 4.1-1 Valve Sununary Listing
~
w f
4.1-2 Valve Full-Stroke Exercising at Greater than 3-Month Frequency 3
')
4.1-3 Valve Part-Stroke Exercising 4
4.1-4 Additional Relief Requests a
o
.g e
+
i f
'6
)
6 1
11 Revision 1 (April 1988)
w.,.. -
._,,,w,,.L&s. u.k+.Naf_;iw_. l
- -a..
l t
i TROJAN NUCLEAR PLANT
$1 PUMP AND VALVE 3:
INSERVICE TESTING PROGRAM SECOND 10-YEAR INTERVAL 1.0 INTRODUCTIOW Title 10, Chapter 1, code of Federal Regulations - Energy, Part 50, Section 50.55a(s) (10 CFR 50.55a(g)) sets forth the requirements for inservice inspection of nuclear power plant components.
The American Society of Mechanical Engineers (ASME) Boiler and Prassure Vessel Code,Section XI, is referenced by 10 CFR 50.55a(g) as the standard to be used in developing a pre 5 ram for testing the operational readiness of pumps and valves. The Trojan Nuclear Plant ASME Code,Section III, Class 1, 2, and 3 components are committed to design and provision for access to enable the performance of tests for the opera-tional readiness of pumps and valves in accordance with ASME Code,Section XI, 1971 edition, and addenda through the winter of 1972. The ef f ective date for commercial operation of Trojan is May 20, 1976. The initial Pump and Valve Inservice Testing (IST) program fo'r Trojan was developed fo-the first 10 years of commercial operation, which extended through May 20, 1986. The first 10-year test program is described in Topical Report PCE-1022.
l This Topical Report deceribes the second 10-year interval extending through May 20, 1996.
Revisions to the Pump and Valve IST program are required to be made at 120-month intervals to upgrade the program to ceflect subsequently approved editions and addenda of ASME Code Section XI.
Approved editions and addenda are referenced in the effective issue of 10 CFR 50.55a(b)(2).
1.0-1 Revision 1 (April 1988)
d.<-. : w..x.
-.1. A.. -.-..; w.
s..
. a : -.,. ~.c..
_:-.=.~.
.-. e.- -..y.
i i
Svecessive 120-month intervals are required to meet the standards of the
^
approved edition and addenda in effect 12 months prior to the comence-ment of the applicable 120-month period. The 1985 edition of 10 CFR 50, 4,
in effect at that time, required the use of the 1980 edition, winter i
1982 addenda of ASME Code Section XI.
Paragraph 10 CFR 50.55a(s)(4)(iv)
\\
]
was invoked to write the program to meet the requir3ments set forth in
}
the sub' sequent addition and addenda of the Code which was incorporated by l
reference in the 1986 edition of 10 CFR 50.
This program will implement, to the maximum extent possible, the requirements of the 1983 edition.
sumer 1983 addenda of ASME Code Section XI, Subsections IWP and IW for Pump and Valve IST.
E Certain systems at the Trojan Nuclear Plant are safety-related or are required for safe shutdown, but were not designed to ASME Code, Sec-tion III, Class 1, 2 or 3 standards (eg, component cooling water, service water, etc). For the Trojan Nuclear Plant, those portions of h
systems designated Quality Group 1, 2, 3A, and 3B in the Final Safety Analysis Report (FSAR) and which are within the scope of ASME Section XI
.x are included in the IST program to meet the intent of proving operational
')
.s readiness of components required to function in the event of an accident.
Subsections IWP and IW of Section II of, the ASME Code,1983 edition and l
addenda through the sunmer of 1983, give the specific requirements for IST of rumps and valves which are a part of the Trojan Nuclear Plant Pump and Valve IST program. Implementing procedures for the IST program are to comply with these standards.
Those pumps and valves for which conf <>rmance with certain provisions of the approved Code requirements is impractical are identified by relief request. These relief requests once approved by the Nuclear Regulatory Commission (NRC) will form the basis for the alternative tests to be listed herein.
~
Re-rision 1 (April 1988)
2.. a;.. a.m.e.'..:.-
?i.a
. a.,,. s D
'.i u.;&::MA
.-L.
.i.
,s..
2.,
-. ~..
2.0 ADMINISTRATIVE CONTROLS
',. \\
e The IST program for pumps and valves is required by the Trojan Nuclear Plant Technical Specifications, Appendix A to racility Operating License
~ ~
Changes involving additional relief requests from ASME Code Section XI requirements will be submitted to tha NRC for approval.
Implementation of this program will be accomplished through Plant proca-dures in accordance with the Nuclear Quality Assurance Program PCE-8010.
These procedures will identify the specific Plant status, valve lineups, operating steps, and return of valves to a normal. lineup to accomplish the required testing at the established frequency. Compliance with the provisions of the testing requirements of ASME Code Section XI, Subsec-tions IWP and IWV, shall be assured by an Inspector as required by Paragraph IWA-2120.
4 9*
I 1
2.0-1 Revision 1 (April 1988)
., <.. :.c. la...N.
t u c a.. n.a w.:
., a.,, u.d;c:..;w;ig,v.;
i 1) 1 j
3.0 INSERVICE TESTING OF PUMPS The IST program for pumps is described in Section 3.1.
Section 3.2 l
provides the alternative testing of specific pumps and the basis for such test variance.
]
F 3.1 PUMP
SUMMARY
4 Table 3.1-1 is a complete listing of all pumps to be tested under the Trojan Nucleer ?lant Pump and Valve IST program. The listing includes:
(1) The identification number, description, and Piping &
Instrumentation Diagram (P&ID) location of each pump to be i
tested; (2) The applicable ASME Code class designation for each pump; (3) The test parameters to be measured for each pump; and (4) The required test frequency for each pump.
Pump design criteria for the Trojan Nucirae Plant are summarized in Section 3.2 and tabulated in Table 3.2-3 of the FSAR. Pump design code derignations used in this program for determining IST requirements are sununarized below:
ASME XI Test-ing Code Class l
Designation 1
2 3
O I
ASME Design Code Class ASME VIII Designation 1
2 3
Division 1 Troj an Quality Group 1
2 3A/3B 3B
^
l Minimum Code ASME III P&V P&V ASMC VIII Application Class A Class II class III Divisten 1
'3.1-1 Revision 1 (April 1988)
i 1C.h. _
_..__.; _. i.2_.c..__. x_._
_u..
- ~,_... : ic-,. Lm a _.a... _ __..,as....g.,
q l
-t I
For clarification, the following notes are provided for the pump design code designations used in the previous table:
J J
ASME III: ASME Boiler & Pressure Vessel Code,1968, Nuclear Vessels plus addenda and code interpretations to the date of purchase award.
1/or purchase awards on or af ter July 1,1971, reference to ASME III should be to ASME Boiler & Pressure Vessel Code, Nuclear Power Plant components, 1971 edition, plus addenda to the date of purchase award.
{
P&V: the November 1968 Deaft ASME Code for Pumps and Valves plus addenda to the date of purchase award.
ASME VIII means ASME Boiler & Pressure Vessel Code,Section VIII, Pressure Vessels, 1968 edition plus addenda to the date of purchase
{l award. These pumps are to meet the IST requirements for ASME XI Code Class 3 pumps.
31 For pumps designed to Quality Group 3B operating above 150 psi and 212*F,Section VIII, Division 1 of the ASME Boiler & Pressure Vessel
]-)
Code was used as a guide in calculating the thickness of the pressure rating parts and in sizing the cover bolting. Below 150 psi and 212*F the manufacturer's standard for service was used.
j Abbreviations for measured parameters in Table 3.1-1 are tientical to those listed in Article IWP-3000 and are repeated below for convenience:
N = Rotative speed (rpm).
I Rotative speed is not required to be measured for pumps directly l
coupled to motor drivers per Paragraph IWP-4400.
31 Pg = Inlet pressure (psig or feet).
Inlet pressure is measured prior to starting the pump and during 31 testing or following the test for pumps which were in service.
3.1-2 Revision 1 (April 1988)
-. w...i a. d 0...
~ L :
_.a.
. e. i a a. a u.
- ..._ s.u. ~._ u_d. -lL.D La i
j y
~
t 4
AP = Differential pressure across the pump (psid or ft).
Ih j
3
., 0 This value is' determined by measuring the pump discharge pressure (P,) and subtracting pump ini,et pressure (P ).
g e
Q = Pump flow rate (spm).
1 l
j V = Vibration amplitude (mils).
{
l t
1 T3 = Ber. ring temperature (F).
In addition to the ASME Section II requirements, major safety-related pumps will be tested as a performance check following critical maintenance. Examples of maintenance which could change pump performance include new motoru, pump housings / casings and impeller replacement.
Pumps included in this augmentud test program aret (1) residual heat removal pumpe (P 202A/B), (2) safety injection pumps (P 203A/B),
(3) Containment spray pumps (P 204A/B), and (4) centrifugal charging ymp- (P205A/B). Consider 9 tion shoul1 be given to extending similar test 7quirements to the Emergency Core Cooling System (ECCS) support systems
((
s 3), but these tests are not mandatory by this program. The per-formance check will monitor the approximate range required to demonstrate satisfactory accident mitigation. Areas evaluated should include:
1 (1) pump curve (head versus flow). (2) starting current, (3) power i
factor, and (4) time to speed (for degraded grid voltage concerns).
3.1.1 REFERENCE VALUES AND TOLERANCES Reference values are to be determined from the results of testing during the IST for each pump and are to be taken from proceduces which are readily duplicated for future testing. The reference values and allow-able ranges of IST quantities are specified in Plant procedures. The limits of operability are established according to the criteria set forth in the Trojan Nuclear Plant Technical Specifications, limitations imposed by the Trojan FSAR, and Paragraph IWP-3210.
10 3.1-3 Revision 1 (April 1988)
.. a. ~.. :w u. :-~....
.=.-.--...:.=~.,x...-.-....;.1-.----....-..--..-.-..-.-..=~p.%.
a l
After a pump has been repaired in a manner that affects the established f
reference values, the old reference values are to be reconfirmed or a new set of reference values are to be established within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> af ter returning the pump to service. Testing to reverify operability will be done in accordance with applicable IST procedures, and the reason for f
changing a set of reference values will be documented.
l
^
The criteria for establishing reference values is defined in Para-t graph IWP-3110. Administrative control of deviations or revisions to procedures will comply with the Trojan Nuclear Plant Administrative Orders (Aos).
[
3.1.2 RECORDS t
All IST records shall be retained for the service lifetime of the pump.
Records shall be readily accessible for review and shall be maintained in acer,rdance with the Trojan Nuclear Plant procedure for the control of Plant records. The records of IST of pumps shall be in accordance with Article IWP-6000.
4 e
i
- ~
Resion 1 (April 1988) l m.
_ y
,._,.I
..a a
f
<w
- j.
, J!
i
's TABIE 3.1-1 Sheet 1 of 3 i.'
I INSERVICE TESTaNG PROGRAM FOR PUMPS I
L-
\\'.
Relief Pump ASME P&lD No.
Measures Test Request y
1D No.
Description Code C13ss (Coordinates)
Paracters Frequenc1r Remarks
{
P102 A Auxiliary Feedwater ASME V111 M-213, Sheet 4 N, Pg. AP. V. Tb 3 Months
- 3. 2. 3 [ a,M h
i' j
(Turbine)
Division 1 (B-7)
I b.
P102 B Auxiliary Feedwater ASME VIII M-213 Sheet 4 M. Pg. AP V Tb 3 Months 3.2.3 S,b]
{
I (Diesel)
Division 1 (C-7) t P108 A Service Water ASME VIII M-218. Sheet 1 P. AP, Q V 3 Months 3.2.1[c]
{-
t Division 1 (C-7)
^
V p'
I P108 B Service Water ASME Vill M-218, Sheet 1 Pg, AP, Q V 3 Months 3.2.I CI l
Division 1 (D-7) i; -
P108 C Service Water ASME VIII M-218. Sheet 1 Pg, AP, Q V 3 Months 3.2.1 CI f
I Division 1 (E-7) a P144 A Diesel Fuel Oil ASME VIII M-226 Pg. AP 3 Months 3.2.2lCI I,
Division 1 (F-7)
>f P144 B Diesel Fuel Oil ASME V111 M-226 Pg AP 3 Months 3.2.2 CI I
Division 1 (D-7)
[
1-P148 A Service Water Booster 3
M-218, Sheet 1 P, AP, Q V Tb 3 Months
[a,b,c]
i
[
(G-5)
P148 B Service Water Booster 3
M-218 Sheet 1 Pg AP, Q, V. Tb 3 Months
[a,b.c]
(C-5)
C 4
v P148 C Service Water Booster 3
M-?l8 Sheet 1 Pg, AP, Q. V. Tb 3 Months
[a,b.cl 4
(F -5) e so f
g $ P148 D Service Water Booster 3
M-218 Sheet 1 Pg. AP Q, V. Tb 3 Months
[a,b.cl
" g (D-5) i
~;
i.
a-
.f,
9<
7e i
b'd
~ -. u
- a.. s.
.--s
>. ~ _.....l:
s 4+
a gy IABt.E 3,1-1 Sheet 2 of 3
? $.
\\*
e-n t
O p
53 Relief l1 Pump ASME P&lD No.
Measures Test Request
['
1D No.
Description Code Class (Coordinates)
Parameters Frequency Reserks v
P. AP, Q V Tb 3 Months
[a,b,c) t' P202 A Residual Heat Removal 2
M-205 t
m I"
l, (F-4)
P202 B Residual Heat Removal 2
M-205 Pg. AP, Q, V. Tb 3 Months
[a,b c]
f' (C-4)
L L
P203 A Safety Injection 2
M-206, Sheet 2 Pg AP, Q, V. Tb 3 Months
[a,b,c)
(C-4)
C
{
h P203 B Safety Injection 2
M-206 Sheet 2 Pg AP Q, V, Tb 3 Months
[a,b.c]
(
(B-4) 3 P. AP, Q, V, Tb 3 Months
[a,b.c]
P204 A Containment Spray 2
M-207 t
n (C-5) 0 i.
1 6
P204 B Containment Spray 2
M-207 Pg AP, Q, V. Tb 3 Months
[a,b,c]
(B-5) l-
- ,.y P205 A Centrifugal Chargingt 2
M-202 Pg. AP V. Tb 3 Months 3.2.4[a,b.cl f
(C-6)
P. AP V, Tb 3 Months 3.2.4[a,b,c]
P205 B Centrifugal Charging 2
M-202 t
(B-6) t l'
P210 A Component Cooling Water 3
M-215, Sheet 1 Pg. AP, Q V. Tb 3 Months 3.2.5[a,b,c)
(G-7)
I-m 3.2.5 a,b.c]
3 1
P. AP, Q V, Tb 3 Months P210 B Component Cooling Water 3
M-215. Sheet 1 t
(C-7) t.
{f P. AP, Q, V Tb 3 Months 3.2.5[a,b c) r P210 C Component Cooling Water 3
M-215. Sheet 1 t
(E-7)
{
l t-
['
i.I.
. f...
j t.
6
-w..
v
...n i
4 t.'
I l
-.s p}
l' l~
4 TABLE 3.1-1 Sheet 3 of 3 Relief Pump ASME PK.ID No.
Measures Test Request I
a ID No.
Descr gtlon Code Clay (Coordinates)
Parameters Frequency Remarks P211 A Boric Acid Transfer 3
M-202 Pg. AP. V. Tb 3 Months 3.2.6ta.b.cl
[
(C-2) i' 3.2.6 a,b.cl
[
1 P211 B Boric Acid Transfer 3
M-202 Pg. AP. V. Tb 3 Monthe (C-1) 9 s
t P218 A Component Cooling Water 3
M-215. Sheet 1 Pg. AP. V 3 sconths 3.2.y(c) l h
Makeup (H-7)
[
n
~
v I
P218 B Component Cooling Water 3
M-215. Sheet 1 Pg. AP. V 3 Months 3.2.7 CI
-l-Makeup (A-?)
l t
f.~
i tal Lubricant level and/or pressure are to be observed and/or verified to be within manufacturer's tolerances for each individual component. The requirement for observation of lubricant level and/or pressure is to be incorporated into each pump test procedure per IWP-3110.
Ib] Bearing temperatures are to be measured at least once each year during IST per IWP-3300.
(c) Pump is dire:tly coupled to a oo' Te driver of either the synchronous or the induction type; therefore, pommy speed will not be measured per IWP #
,0.
O>c u<
- 1 e l
u de 0-* W
- :s i
e J
I i
i.
1 t..
k
(
s
....>.u
.a..-.:. =....'
.,....e..~..
' s..
..=. J..e n
.:.u..,.
o
.-....~ w I
N 3.2 RELIEF REQUESTS FOR PUMPS The Code of Federal Regulations, 10 CFR 50.55a(g)(5)(iii), states that, f
"If the licensee has determined that conformance with certain code 2
requirements is impractical for his facility the licensee shall notify j
the Comission and submit information to support his determinations."
By interpretation, testing of pumps which does not conform to the I
standard test requirements for' measurement of specific parameters or for the frequency of performance of tests is assumed to be a nonconfotiaance.
This section identifies those pumps for which the Trojan Nuclear Plant is in nonconformance with the standard test requirements and provides the basis for the relief criquest and the provisions for alternate testing ref those pumps. Testing for these pumps will be performed in accordance with the following descriptions.
3.2.1 SERVICE WATER SYSTEM: PUMPS P 108A. P 108B. P 108C Code Class: ASME VIII, Division 1 s
Function: The service water pumps provide cooling and makeup water for safety-related and non-safety-related equipment and systems.
The pumps are also used -.cr d!1ution of liquid radwaste during discharge.
Test Requirement: Measure / observe pump inlet pressure, vibration amplitude, bearing temperature, and lubricant.
5 Basis for Variance: "Instrumentation Not Originally Provided."
ASME VIII pumps at Trojan were not required to be designed for testing for operational readiness as per 10 CFR 50.55a(g).
3.2-1 Revision i (April 1988)
w._; a. d.:-.._. :.. _,
a_. c.--._.....- - __L_- - -- _.-. ~. c. ~ -e-L.,.
e
~ ~~ce -
i The pumps are totally submerged inside the Intake St ructure. Pump bearings are inaccessible and the
.f 1 instrumentation required for measurement of pump i
inlet pressure, vibrat' ion amplitude, and bearing I
1 temperature was not provided in the original system design.
i Relief Request:
Inlet pressure for these pumps will be determined by 4
i measuring the Intake Structure water level.
2 q
The pumps are submerged in the Intake Structure and are not accessible for attachment of transducers for dis.
j placement measurement of vibration amplitudes during pump operations The pamp actor inboard bearing will be j
periodically monitored for vibration amplitude. Motor inboard bearing vibration measurements provide indica-tion of pump shaft alignment and deterioration. The pump bearing vibration amplitude will not be measured.
The pump bearing temperature will not be measured, and
)
the lubricant will not be observed.
3.2.2 DIESEL TUEL OIL SYSTEM: PUMPS P 144A AND P 144B i
Code Class: ASME VIII Division 1 Function: The diesel oli transfer pumps provide flow of fuel oil f rom j
the diesel oil storage tanks to the fuel oil day tanks.
Test Requirement: Measure pump inlet pressure, differential pressure, flow rate, vibration amplitude, bearing terperature, and lubricant. The resistance of the system shall be varied until either the measured differential pressure or the measured flow rate equals the corresponding reference value.
- ~
Revision 1 (April 1988)
7. w.... -... a. w.,
.l* ~.. w :~.L -- i L-.a
- ... -... w -.. ~ 2 -..h..
..~.=..-.........a.-
?
I Basis for Variance: "Instrumentation Not Originally trgvided."
,1 4
l U. 1 ASME VIII pumps at Trojan were not required to be designed for testing for operational readiness as per 10 CFR 50.55a(s).
Instrumentation was not provided for measurement of inlet pressure, dif-forential pressure, and flow rate. No recirculation (test) flow path available to establish reference I
flow or differential pressure conditions.
i "Accessibility".
These pumps are located inside the.
h diesel oil storage tanks. The pumps are inaccessi-ble for measurement of vibration amplitude and bearing temperature.
Relief Request: Pump discharge pressure will be measured while inservice refilling emergency diesel generator (EDG) day tanks.
The inlet pressure will be calculated from diesel oil storage tank level to determine the suction head on the pump. The differential pressure will be taken as the difference between pump discharge pressure and calcu-lated suction pressure. This calculated differential pressure will be monitored as a measure of pump per-formance. The pump flow rate will be calculated from a timed rise in the fuel oil day tank level. Operational readiness will be demonstrated by the pumps ability to supply 20 spa makeup to the EDC day tanks as assumed in i
the FSAR. The pumps are enclosed within the diesel oil storage tanks; accessibility is not available for measuring pump vibration. amplitude or bearing tempera-ture, and the lubricant cannot be observed.
i 3'2-3 Revision 1 (April 1988) 2
.. L :..w.. 1,
..-...-....-.-L--.-
- ~.. ~.
a-
.. - ~ ~ - -. - - - - - -
~ ~,~ ~, -
k J
i I
3.2.3 FEEDWATER SYSTEM: PUMPS P 102A and P 1028
-l Code Class: ASME VIII Division 1 j
', t Function:
1 The auxiliary feedwater (AFW) pumps provide a backup to the A
normal feedwater pumps to ensure the safety of the Plant and protection of steam generators when the normal feedwater pumps are unavailable.
I Test Requirement: Measure the flow rate every 3 months.
Basis for Variance: "Instrumentation Not Originally Provided." ASME Section VIII pumps at Trojan were not required to be designed for testing for operational readiness as per 10 CFR 50.55a(s). These pumps are tested using a fixed resistance flow path (recirculation flow to the condensate storage tank) since instrumentation was not provided for measurement of flow rate in the flow path, i
,)
Relief Request: The inlet pressure, dif ferential pressure, rotative speed, bearing temperature, and vibration amplitude will be measured for each of these pumps. Measurement of these pump parameters will provide evidence to assess the operational readiness of these pumps. Flow rate can be adequately evaluated from the pump differential e
pressure measurement since a fixed resistance path is 4
used.
3.2.4 CHEMICAL AND VOLUNE CONTROL SYSTEM: PUMPS P 205A and P 205B code class:
2 Function: These pumps normally are in service supplyin5 makeup flow to the Reactor Coolant System (RCS) and reactor coolant pumps i
Revision 1 (April 1988)
~ a. :....:
A.w
.r
. :.ms....
.- -..~.=-....: v..a 1 la
...-w f
I (RCP) seals. During a Loss-of-Coolant Accident, both of these
(
pumps operate as part of the Safety Injection System (SIS).
^
~ ~
Test Requirement: Measure the flow rate every 3 months.
Basis for Variance:
"Instrumentation Not Provided." Class 2 pumps at l
Trojan were not required to be designed for testing for operational readiness as per 10 CFR 50.55a(g).
These pumps are tested using a fixed resistance flow path (recirculation flow to the refueling f
water storage tank (RWST)) since instrumentation was not provided for measurement of flow rate.
Relief Request:
The inlet pressure differential pressure, behring r
temperature, and vibration amplitude will be measured for each of these pumps. Measurer.mnt of these pump parameters will provide ev'idence to assess the opera-tional readiness of these pumps. Flow rate can be
(
adequately evaluated from the pump differential pressure measurement since a fixed resistance path is used.
3.2.5 COMPONENT COOLING WATER SYSTEM: PUMPS P 210A. P 2108, and P 210C Code Class: 3 J
i Function: Supply and maintain the required cooling water flow to safety-related and other equipment vital to the safe shutdown and normal operation of the Plant. These londs include the RCPs, letdown heat exchanger, residual heat' removal (RHR) heat exchangers, and seal water heat exchanger.
Test Requirement: The resistance of the system shall be varied until either the measured differential pressure or the measured ficw rate equals the corresponding reference value.
3.2-5 Revision 1
' April 1988)
- s. _
~.w
-.12 L..
..r -
a - -
l.. -. a n
-- ~.:.. - u
-.. ~. - -
~~ " ~~'
y;
!i i
I
(,
Basis for Variance: A set or sets of reference values cannot be estab-l lished for either differential pressure or flow in f)
{
accordance with IWP-3110 due to piping configuration and operating loads supplied by the Component
)
Cooling Water (CCW) System. A recirculation (test) j' flow path is not available to establish a reference flow rate. Attempts to establish a reference f
differential pressure or flow rate would require
)
adjusting flow to various critical operating loads l
which could af fect the operability of the inservice equipment. This system is used during all modes of Plant operation, all requiring different minimum cooling flows to the supplied components.
(
Relief Request: Reference values will be established with respect to the manuf acturer's pump curve and allowable ranges specified in accordance with IWP-3210 to monitor pump performance.
Flow and differential pressure will be measured and com-pared to the specified ranges to determine pump opera-tional readiness.
~#
3.2.6 CHEMICAL AND VOLUME CORTROL SYSTEM: PUMPS P 211A and P 2118 I
code Class:
3 l
1 1
4 1
Function: Normally, one of these pumps is aligned with one boric acid tank and starts on demand from the reactor makeup control system.
Emergency boration, the supplying of 4-weight percent boric acid solution to the suction of the charging pumps, can be accomplished by either/or both of these pumps. These pumps are also used to transfer 4-weight percent boric acid solution from the batching tank to the boric acid tanks.
Test Requirement: Measure the flow rate every 3 months.
Revision 1 3.2-6 (April 1988)
)
., _ i _... L __ _ _ '.~
c a,,
c-
..... :. 'u _ a. a.. =.. - -
i i
i Basis for Variance: "Insttsmentation Not provided." Class 3 pumps at f,.; )
Trojan were not required to be designed for testing i
for operational readiness as per 10 CFR 50.55a(g).
t l
These pumps are tested using a fixed resistance flow path (recircutation flow to the boric acid tanks) 1 since instrumentation was not provided for measurement of flow rate.
Relief Request: The inlet pressure, differential pressure, bearing temperature, and vibration amplitude will be measured for each of these pumps. Measurement of ttsse pump parameters will provide evidence to assess the opera-tional readiness of these pumps. Flow rate can be evaluated from the pump differential pressure measure-ment since a fixed resistance path is used.
(/
4 b
3'2*I Revision 1 (April 1988)
(
- thA ab.. a wd a, --
_.t.. - -, -
- L e-
-- l - u%
4 j
l 1
R 4.0 INSERVICE TESTING OF VALVES i
Mh
\\:.l The IST program for valves is described in this section.
]
4.1 VALVE
SUMMARY
I
.l
-j Table 4.1-1 is a complete listing of all valves to be tested under the l
Trojan Nuclear Plant Pum and Valve IST program. The lis. ting includes:
i 3
(1) The identification number, description, P&ID location, and normal po-aition ot' each valve to be tested; (2) The applicable ASME Code Class designation and Section XI category for each valve; (3) The required tests for each valve; and (4) The required test frequency for each valve.
Valve design criteria for the Trojan Nuc1 car Plant are sommarized in Section 3.2 and tabulated in Table 3.2-3 of the FSAR. Valve design code h
designations used in this program for determining IST requirements are sumarized below:
i l
ASME XI Test-1 ing Code Claes 1
2 3
^
j
, Designation O
ASME Design Code Class ANSI Designation 1
2 3
331.1 Trojan Quality Group 1
2 3A 3B Minimum Code ANSI B16.5 P&V P&V Non-Nuclear Appilcation MSS-SP-66 Class II Class III ANSI B31.1 i
1 i
4.1. 1 Revision 1 (April 1988)
)
)
i
~
~.u..:~:...-...-.-.
.-.. ~- -. - ~ -. -- --
-- -- 3 4
1 1
1,
.s
]
For clarification, the following notes are provided for the pump design l
code designations used in the previous table:
)
i ei P&V: means the November 1968 Draft ASME Code for ? umps rnd Valves plus addenda to date of purchase award.
A I
Valves designated ANSI B31.1 are to meet the ICT requirements for
]:t a
- )
ASME II Code Class 3 valves.
j Valves whose test requirements deviate from the standard frequency
'I requirements of Subsection IVY are referenced to their applicable
((l justification or relief request.
Valves which have a limitation on their maximum stroke time in fulfilling their accident function are annotated in the Testing column. The limiting value of full-stroke time is rpecified in Plant Operating Procedures for implementing the Valve Test program.
The following abbreviations are used in Table 4.1-1:
')
~d a f II VALVE DESCRIPTION:
i A0 = Air Operated MO = Motor Operated SO = Solenoid Operated NORMAL POSITION:
i C = closed i
i O = Open
]
i C')
1 = Throt.tled j
1 ja I
Revision 1 4'l-2 (April 1988) f E
e' w-w-w-
~-nr~w vr-4--
e--s we
-, ~,
w
'9~~~v 4=',
, 2 W :4. u._._;........ ; D _. u..
u.c..>.. a u.'
_rm._ c.
k-_
l j
I i
TESTING:
3 ST/0 = Stroke timed for open position.
ST/C = Stroke timed for closed position.
' ~
ST/0C = Stroke timed for open and closed positions.
j EI = gxercise through one full valve cycle (manual valves).
.10 4
l (blank) = Stroke timing not required.
The test frequency for valves is indicatad by one of the following phrases:
(1) Three months implies at least once every 92 days.
(2) cold shutdown implies when the Plant is in or has been in a
Mode 5.
In the case of frequent cold shutdowns, the test need not be perfomed if less than 92 days have elapsed since the last performance of the test. Valve exercising shall co:snence
.[
within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of achieving cold shutdown and continue until
}
all testing is complete or the Plant is ready to retum to power. Slowever, it is not the intent of this program to keep the Plant in cold shutdown in order to completc cold shutdown tasting. Exception to the 48-hour tvle may be taken and testing 10 w
started at a later time if an extended shutdown is planned i
during which all cold shutdown testing will be performed.
(3) Refuelina implies when the Plant has been shut down for a scheduled refueling outage. The senedule for testing of safety and relief valves has been established to comply with Table IW-3510-1, based on refueling outage mode changes.
(4) Two years implies valve leak rate tests are required every two years per Paragraph IW-3422.
e l
i 4.1-3 Revision 1 1
(April 1988)
. y :;. :. ;,...*.. ~.. m-a.,...
a,. a.s w;;
-~
+..:..m
- . :.. uw- -
a - a
' _. :.. a..._
..a j
l (5) Five years implies at least once every five years h;1 required by s
Paragraph IW-3511. Five years represents the maximum limLt
}
between successive tests for all safety valves in the program.
1
)1 M CATEGORY A AND B VALVES i
e
- j Preservice testing of now valves which fall under the scope of this eI program is man.iatory. Valves which have been repaired or replaced must a
1 be tested prior to being returned to service. Test requirements result-a
}
ins from maintenance or replacement of a valve are to be controlled in
-l accordance with Trojan Nuclear Plant Aos and maintenance procedures.
Testing of valves is to be accotaplished in accordance with the designated reference procedure. Administrative control of deviations or revisions to procedures shall comply with Trojan Nuclear Plant A0s.
i Containment isolation valves are not to be tested for seat leakage rate ti under ASME Code Section XI.
Seat leakage rate testing and analyses are to comply with Appendix J to 10 CFR 50 for establishing Containment
."]
isolation valve integrity. Paragraph 4.9 provides the basis for relief (l
and justification for exemption of seat leakage rate testing from the l*
requirements of ASME Code Section II.
The requirements for testing ih in-series chhk valves which provide isolation between the RCS and other O
systems with a lower design pressure are.ncluded within the scope of this program for tracking purposes only.
e Va.tves whose test data is outside the tolerance ranges are to be evaluated for corrective action in accordance with Paragraphs IW-3417 9nd IW-3e27, with the exceptson that a 24-hour grace period is not ll allowed before declaring inoperable a valve that is not capable of perfod tg its specified function. Test data outside the established
- toleran, ranges is to be reported in accordance with th.a Trojan Nuclear
{;
Plant pt ocadure for documentation of IST of valves.
1 1.
l Revision 1 4.1-4 (April 1968) t m.
o
w,'..w a.a. 501. - _ - a a.C._
..... L,
- z. i w...;,
, +.. L..r m. d,.du, -
.a 9
f 3
i 1
4.3 CATEGORY C VALVES i
l1P; t
r Preservice testing of new valves which fall under the scope of this i
program is mandatory. Valves which have been repaired or replaced must be tested prior to being returned to service. Test requirements result-l ing feon maintenance or replacement of a valve are to be controlled in accordance with Trojan Nuclear Plant Aos and maintenance procedures.
Testing of valves is to be accomplished in accordance with the designated reference procedure. Administrative control of deviations or revisions 1
to procedures shall comply with Trojan Nuclear Plant AOs.
i corrective action for safety and relief valves is to be in accordance with Paragraph IWV-3514 Corrective action for check valves is to be in accordance with Paragraph IWV-3523, with the exception that a 24-hour grace period is not allowed before declaring inoperable a check valve that is not capable of performing its specified function.
4.4 MULTIPLE CATEGORY VALVES When a valve has a multiple category classification, such as AC, the test requirements of both categories must be met; however, duplication of testing is not required. Documentation shall meet the requirements of both cateseries.
i 4.5 PASSIVE VALVES Passive valves, as defined in Paragraph IWV-2100(b), will not be exercised, as noted in Table IWV-3700-1.
The passive valves which are included in this program are manual valves or check valves which are normally shut during power operation and are required to be shut to mitigate the consequences of an accident as Containment isolation boundaries. Valves which are normally open and remain open during accident conditions represent passive valves used only for operating convenience or maintenance and are exempted by Paragraph IWV-1200(a).
4.1-5 Revision 1 (April 1988) 1
-. ~, _-
. - ~ _,.. - -.. -
.,.....:., : 2..~.a....u:- - n
.. a..'n - -
. <u-.a>
- e. + "a ' - : + '
4 Ii 1
4 4.6 RgCORDS N
q S.{}'
]
All inservica inspection records shall be retained for the service lifetime of the valve. Records shall be readily accessibte for review g
and shall be in accordance with Trojan Nuclear Plant procedures for h
control of Plant records. Records of IST of valves shall be in d
accordan:o with Articic ;WV-6000, n
4.7 FULL-STROKE EXERCISING q
category A, B, and C active valves that cannot be exercised during Plant operation will be full-str'oke exercised during cold shutdowns or refuel-P ing outages. Table 4.1-2 lists these valves and includes the basis for why each valve cannot be tested during Plant operation.
u 3
4,8 PA2T-STROKE q[P, E E Category A B, and C active valves where only limited operation is practical during Plant oporttion will be part-stroke exercised during Plant operations and full-stroks exercised during cold shutdowns.
Table 4.1-3 lists these valves and includes the basis for why only limited operation is practical during Plant operation.
I 4.9 CONTAJjn!ENT ISOLATION VALVES These valves provide Conta!.nment isolation during reactor operation and/or isolate Containment to prevent release of radioactive products following a design basis accident.
1 Containment isolation valves are tesced for seat leakage under the f
criteria of Appendix J to 10 CFR 50.
These valves are tested and analyzed for seat tightness in accordance with the Trojan Nuclear Plant "Containment Local Leak Rate Test".
This procedure provides for local leak rate testing of valves. The acceptance criteria for allowable 1eakage rate under Appendix J to 10 CTR 50 varies from the acceptance l
criteria of Subsection IWV of ASME Code Section 11 in that the allowed Revision 1 4.1-6 (April 1988)
? I. 2_ m...h
._2..__. _-_ : ~.
..f w_._-
<~...u..:-
......_1
.:. -.c_..
4
}
t l
leakage is based on the total Containment leakage rate rather than on
.r.,
individual valve seat leakage criteria. This test program provides adequate documentation and individual analysis for valves to verify maintenance of Containment integrity. Failure of any valve to provide acequate seat tightness in maintaining Containment integrity will require the same corrective action for repair and replacement of the valvs.
Therafore, the 10 CFR 50, Appendix J requirements are adequate in lieu of IW-3420 requirements. Individual valve leakage rate requirements are assigned and actual leakage rates are compared with previous measurements, which are in compliance with the reTairements of IW-3426 and IW-3427.
These valvss are tasted for seat leakage rate during local leakage rate testing in accordance with Appendix J to 10 CFR 50 and will not be tested under this program. Individual valve leakage rate criteria is specified by PGE in accordance with IW-3426 and corecctive actians will be in
-accordance with IW-3427.
4.10 WASH-1400. EVENT V VAI.VES These valves are designated from a configuration of in-series check valves which provide a boundary between a high-pressure system and a system with a design pressure below i hat of the normal operating pressure of the high-pressure system. These valves will be leak tested at reduced pressures prior to entering Mode a af ter each refueling and prior to entering Mode 2 whenever the Plant has been in cold shutdown for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more, and if leakage testing has not been performed n. the previous 9 months. Testing of these valves is in accordance with Technical Specification 4.4.6.2.2.
4.11 f.2AX TESTING MO 8701 AND MO B702 PGE conunitted to individually leak test these valves in accordance with the requirements of IW-3420 in a letter dated May 18, 1984 in response to an NRC request dated March 14, 1984 in SER 180.
4 1-7 Revision 1 (April 1988)
G ^
.m.
m._....r..u._...,.s.._
...c....r..........u...m a..
..~.
...y i
8 I
i
- j 4.12 LEAK TESTING MO 8812 kj l
Amendment 26 of the Original Trojan FSAR,(dated December 1915) connitted PCE to submit a test program for MO 8812, '4HE. Suction From the RWST, to meet applicable safety requirements. The test program was submitted by O
PCE letter dated August 29,1978 (C. Goodwin, Jr. to A. Schwencer) and J
accepted by WRC letter dated January 15, 1979 (A. Schwencer to C. Goodwin, Jr.).
Charges to this program were made and accepted by WRC letter dated October 15,1985 (E. Butcher to B. Withers).
4.13 RELIEF REOURSTS Pursuant to the provisions of 10 CFR 50.55a(s)(5)(lii), PCE has deter-mined that conformance with certain ASME Code requirements is impractical and relief from these requirements is necessary. The requests for relief l
are included in ' fable 4.1-2 as Item C under RMR System, Item I under SIS Item A under Containment Spray System, Item D under CCW System, and j
Item A under Instrument Air Systemt in Table 4.1-3 as Item A under 3
Containment spray System; and in Table 4.1-4, "Additional Relief v
.y Requests".
l l
l 2
A 1
Revision 1 4.1-8 l
(April 1988)
m y
3._
p.
L i
I
- i;
,s....-
o s-i.
r
_ABLE 4.1-1 Sheet 1 of 37 T
p INSERVICE YESTING PROGRAM FOR VALVES
$[
c.r if !
'.4 SYSTEM: Reactor Coolant P&lD NO.:
M-201, Sheet 1. Revision 32 s,
ASME*
~
h Valve Vs1ve Dwg Code Sect 11 Norun Test Frequency ID Wo.
Description Loc Class Cat.
Pos Exercise Leakage Comunents Testing t ;,
s Solenoid 1-in. Globe E-6 2
B Closed Cold shutdown Not applicable 4.7 Stroke timed
~
Valve (C)
(NA) for open
{.
(SV) 1015A and closed h
positions (ST/OC)
SV 1015B D-6 C
ST/OC SV 1016A E-6 C
ST/OC m
f SV 1016B D-6 C
ST/OC C,.
Control 3/8-in. Air-F-5 2
B Open 3 months MA Stroke timod f,_
Valve Operated (AO)
(0) for closed (CV) 8032 clobe position b
(ST/C) 8900A 1-1/2-in.
C-5 1
C C
Cold shutdown MA 4.7 8900B Check C-5 C
8400C G-4 C
6900D C-5 C
A948A 10-in. Check B-6 1
AC C
Cold shutdown Cold shutdown 4.7, 4.10 s948B H-6 C
and refueling g
8948C H-3 C
e 8948D B-3 C
8949A 6-in. Check D-7 1-AC C
Cold shutdown Cold shutdown 4.7, 4.10 aw 89498 F-7 C
and refueling N$
8949C F-3 C
NI 8949D D-4 C
o 4
h
~* Araerican Socicly of Mechanical Engineers ( ASME)
S
?
e 9-
.(
.,-_u._.
--...__ 2.. p.
b.
t'
('
't I
TABLE 4.1-1 SheeL 2 of 37 m3
- n. o EN
{
"g SYSTEM: Reactor Coolant P&ID NO.:
M-201, Sheet 2. Revision 4 s
l
$~
~
[
Valve Valve Dws Code Sect II Norm Test Frequency I,
ID No.
Description Loc Class Cat.
Pos Exercise Leakage Comuments Testing l
t-I Pressure 3-in. AO Clobe G-7 1
B C
Cold shutdown MA 4.7 ST/OC
[
Control 1-Valve (PCV) b 455A I
8
{
PCV 456 G-7 C
ST/OC Motor-3-in. MO Cate G-7 1
B O
3 months MA ST/OC Operated (MO) 8000A g
MO 80.)OB G-7 O
ST/OC t'
'h a
Pressure 6-in. Safety C-6 1
C C
5 years NA Safety Valve (PSV) 8010A f,
PSV 8010B G-5 C
i, PSV 8010C G-5 C
CV 8025 3/8-in. AO G-1 2
A O
3 months 2 years 4.9 ST/C CV 8026 Clobe C-2 O
ST/C j
s CV 8028 3-in. AO F-1 2
A O
3 months 2 years 4.9 ST/C I
D!aphraga CV 8033 3/4-in. AO F-2 2
A O
3 months 2 years 4.9 ST/C Diaphragm 8046 3-in. Check F-2 2
AC C
MA 2 years 4.5, 4.9
[
8047 3/4-in. Check F-2 2
AC C
NA 2 years 4.5, 4.9 i,.
i.
L.,
8079 4-in. Check D-2 2
AC C
MA 2 years 4.5, 4.9
.t
{.
8090A 1/8-in. Manuel E-5 2
A C
MA 2 years 4.5, 4.9 k
80908 Necdle E-5 C
I t
g' U'
- I-
> ~_-... -
.. --.-.-. 7....
i l
?
i TABLE 4.1-1 Sheet 3 of 37
- ['
f?
SYSTEM: Chemical and Volume Control P&lD NO.:
M-202. Revisloei 32 F.
l ASME Valve Valve Dwg Code Sect X1 Woria Test Freet'ency l
ID No.
Description Loc Class Cat.
Pos Exercise Leakage Comumente Testing 1
l MO 1128 4-sn. NO Cate E-5 2
B O
3 months NA ST/C I '.
i40 112C E-3 e
O ST/C
{-
MO 112D 8-in. MO Cate C-5 2
B C
3 months NA Stroke timed f.
for open
}-
position l '-
(ST/0)
MO 112E C-5 C
ST/O i'
m l'
MO 8104 2-in. NO Globe C-4 2
B C
3 months NA ST/O
{
MO 8105 3-in. MO Ca.te F-7 2
B 0
3 months NA ST/C MO 8105 F-7 0
~
ST/C PSV 8117 3-in. Safety C-7 2
C C
5 years NA
~
PSV 8118 3/4-in. Safety D-6 2
C C
5 years NA I'
g PSV 8119 2-in. Safety H-5 2
C C
5 years NA t
PSV 812C 3-in. Safety C-6 2
C C
5 years NA
~
PSV 8124 3/4-in. Safety B-5 2
C C
5 years NA l
CV 8149A 2-in. AO Clobe F-8 2
A C
3 months 2 years 4.9 ST/C CV 81498 F-7 O
ST/C
[
CV 8149C F-7 C
ST/C
[-
1
- 3.
CV 8152 2-in. A0 Clobe G-7 2
A O
3 months 2 years ST/C AS --
'l 4.9 ll.
>o
- ' E i
- E p!
- ~
t l
5.
[
r i
b, I-
,t I
h t
~ - -
-m___...m_.&.,.
!s'
[-
ts TABLE 4.1-1 Sheet 4 of 37
- n e
m<
n s*
t C+ as e
"o SYSTEM: Chemical and Volume Contrcl P&ID NO.:
M-202, Revision 32 i
- :s i
e i.
a c--
gp a.
ASME a
Valve Valve Dws Code Sect XI Norm Test Frequency C
{
ID No.
Description Loc Class Cat.
Pos Exercise
-l Laakage C - ats Testing l
8481A 4-in. Check C-6 2
C C
3 mocths NA 4.8
)
{-
84818 B-6 C
8546 8-in. Check C-5 2
C C
Cold shutdown MA 4.7
}~f-t-
t i
er t
I' l-l t.
t.
I'
[f.
i, 1'
9
?
/
,b QM
.:l n
d
=.
t,
(
,u
- c)
T.
o TABLE 4.1-1 Sheet 5 of 37 V.
[t!
SYSTEM: Cheilcal and Volume Control P&ID NO.:
M-203, Revision 21 p.
ASME I
Velve Valve Dwg Code Sect II Mona Test Frequency f,
ID 50.
Description Loc Class Cat.
Pos Exercise Leakage Comuments Testing
['
l l
MO 8100 4-in. NO Cate C-2 2
A O
Cold stutdown 2 years 4.7. 4.9 ST/C Ji !
l l
n MO 8110 2-in. MD Clobe H-3 2
B O
Cold shutdown MA 4.7 ST/OC 3
}-
1 v'
l MO 8111 H-3 O
ST/OC rp, MO 8112 4-in. NO Cate F-2 2
A O
Cold shutiown 2 years 4.7, 4.9 ST/C L{
['i PSV 8121 2-in. Safety F-2 2
C C
5 years MA
^
PSV 8123 H-3 C
I{
8180 3/4-in. Check F-2 2
AC C
NA 2 years 4.5, 4.9 t
l 8368A 2-in. Check B-7 2
C 0
NA NA 4.5 I
83688 B-6 0
h.-
l 8368C B-4 0
8368D B-3 0
l t
0 p e F
.s O N
{
i g
ec
\\
n c~
?..
i O* es
}
l
(>* e
- r.
- ~
O e* 3 e
l e~
L
\\'
L i;
l l
/
l j
[
l-U l
i t
f s k
i
- i i
l i
i l
r
~
r
,w
- - ~ ~,-.
,e,,
7 L'
i:'
s s.
TABLE a.1-1 Sheet 6 of 37 i
,,>a
(
u.1 r r es i
g SYSTEM: Resldual Heat Removal P&ID NO.:
M-205, Revision 22 g :s t
$~
ASME v
Valve Valve Dwg Code Sect II Noria Test Frequency ID No.
Description Loc Class Cat.
Pos Exercise Leakage Cosmaamts Testing Hand Con-8-in. AO F-7 2
B O
3 months MA ST/OC trol Valve Butterfly
- i (HCV) 606 HCV 607 8-in. AO C-7 O
ST/OC I.
Butterfly i
I FCV 610 2-in. MO Clobe C-4 2
B C
3 months NA ST/OC L
i FCV 611 D-4 C
ST/OC Y
r.
CV 1782 3/4-in. AO C-6 2
B C
3 months NA ST/C
^
CV 1783 Clobe G-7 C
ST/C
.i.
v MO 8700A 14-in. MO Cate E-3 2
B O
3 months NA ST/OC h.
NO 87008 D-2 O
ST/OC MO 8701 14-in. NO Cate D-2 1
A C
Cold shu*doec 2 years 4.7. 4.11 ST/C MO 8702 E-2 C
ST/C MO 8703 12-in. MO Cate D-5 2
B C
Cold shutdown NA 4.7 ST/OC PSV 8708 3-in. Safety E-2 2
C C
5 years MA PSV S709 3/4-in. Safety D-6 2
C C
5 years NA MO 8716A 8-in. MO C.
E-7 2
B O
Cold shutdown NA 4.7 ST/OC MO 8716B C-7 0
ST/OC 8730A 8-in. Check F-4 2
C C
3 months NA 4.8 t
8730B C-4 C
~
8736A 8-in. Check lD-5 1
AC C
Cold shutdown Cold shutdown 4.7, 4.10 p
87368 D-5 C
and refueling
?*
l F
~
h Y,
L
.y L;
- a.
+
r
+
'hs
- [.
+
.___.____.___m______________.__._.____..__.__.________-,-____mm
..mm.
m
i
- a. '
g.
f TABLE 4.1-1 Sheet 7 of 37 e
i[
SYSTEM: Nesidual Heat Removal PE!O NO.:
M-205, Revision 22 l
[
ASME Valve Valve Dwg Code Sect II Norla Test Frequency t.
ID Mo.
Dascription Loc Class Cat.
Pos Exercise Leakage Comuments Testing i f
. f.
MO 8804A 8-in. MO Cate C-7 2
B C
Cold shutdown MA 4.7 ST/OC t.
MO 8804B A-7 C
ST/OC
[-
MO 8809A 8-in. NO Cate F-7 2
B D
Cold shutdown MA 4.7 Sf/O MO 8809B B-7 O
ST/O MO 8811A 14-in. MO Cate F-3 2
B C
3 mcnths MA ST/OC C
I MO 8811B B-2 C
ST/OC l
MO 8812 14-in. NO Cate D-2 2
A O
Cold shutdown 2 years 4.7. 4.12 ST/C 3818A 6-in. Check C-8 1
AC C
Cold shutdown Cold shutdown 4.7. 4.10 ll 8818B T-8 C
and refueling Vi 8818C B-8 C
l fd818D A-8 C
i' PSV 8856A 2-in. Safety C-7 2
C C
5 years MA g.
PSV 88568 B-7 C
8958 14-in, Check D-3 2
C C
Refueling NA 4.7, 4.13
'.q
- .\\
T' l
4 M %
T*
a Y nO i
g, i
o se s
i
?
9.
1
}.
t t'
I f, '
m,..
f u:-~-.
... a
'k TABI.F 4.1-1 Sheet 8 of 37 aw D, E
~
,a SYSTEM: Safety injection P&ID N0.:
M-206, Sheet 1 Revision 31 c
(-
$~
l v
{_
l Valve Valve Dwg Code Sect II Morm Test Freguency ID No.
Description t.oc Class Cat Pos Exercise Leakage Comuments Testing 8956A 10-in. Check D-7 1
AC C
Refueling 2 years 4.7, 4.13 i
8956B D-6 C
[ ]
8956c D-4 C
8956D D-3 C
f CV 8964 3/4-in. A0 C-3 2
A C
3 menths 2 years 4.9 ST/C l
Glots 8968 1-in. Check H-6 2
AC C
NA 2 years 4.5, 4.9 O
[.
v NO 8808A 10-in. NO Cate D-7 1
B O
Cold shutdown MA 4.7 ST/OC
?
MO 8808B D-6 0
ST/OC Idi MO 8808C D-4 O
ST/OC I -
f.
MO 8808D D-3 O
ST/OC f-PSV 88554 1-in. L.fety F-7 2
C C
5 years WA PSV 8855B F-6 C
i -
l rSV 8855C F-4 C
L PSV 8855D F-3 C
I-CV 8871 3/4-in. AO C-4 2
A C
3 mocths 2 years 4.9 ST/C I
Clobe p.
CV 8880 1-in. AO Clobe H-7 2
A C
3 months 2 years 4.9 ST/C l
h l.4 p.
f.
l ky l
(1 h'
l l
.k~,
4 3.-
w;m..
c..-
_._.o.
. /,
j-
{.,
{.
C. ')
Y t
i c.
i Y:
~
TABLE 4.1-1 Sheet 9 of 37 i.
E, l
SYSTEM: Safety Injection P&ID NO.:
M-206, sheet'2 Revision 5 p.
J.)
ASME f
f +
Valve Valve Dws Code Sect XI Nom Test Frequency ID No.
Description Loc Class Cat.
Pos Exercise f.eakage Comsments Testing MO 8801A 4-in. NO Cate G-6 2
B C
Cold shutdown MA 4.7 ST/O
. ', )
MO 88018 F-6 C
ST/O MO 8802A 4-in. MO Cate D-6 2
B C
3 months MA ST/OC
[
MO 8802B i
B-6 C
ST/OC
^
y MO 8806 8-in. MO Cate C-2 2
B O
Cold shutdown MA 4.7 ST/O MO 8807A 6-in. M0 Cate C-2 2
B C
3 months NA ST/OC lii MO 8807B B-2 C
ST/OC
'?
MO 8813 2-in. MO Clobe F-2 2
B O
Cold shutdcwn MA 4.7 ST/OC
{J MO 8814 O
ST/OC
[.
v ~;
8815 3-in. Check F-7 1
C C
Cold shutdown MA 4.7 I.U t, <.
8819A 2-in. Check E-8 1
AC C
Cold shutdown Cold shutdown 4.7. 4.10 8819B E-8 C
and refueling 8819C E-8 C
hj 88190 o-8 C
U N
i.9 i
t, -
O %
h., l-Nl p:c o
y
- 3 m e.*
I
=
\\
l 1-0
=
g.,
b
~
.-...a.~.._..o+=_-
og
-b i
+
TABLE 4.1-1 Sheet 10 of 37 l..
- >. O<
g e.1 s
r
" E-SYSTIGt: Safety Injection P&lD MO.:
M-206. Sheet 2. Revision 5
[ -
- o t
~a e
$~
ASME Valve Valve Dws Code Sect II Norla Test Frequency
, ' oc Class Cat.
Pos Exercise Leakage Comuments Testing
{
ID 50.
Description MO 8821A 4-in. NO Cate C-5 2
B o
3 smonths MA ST/O a
MO 8821B C-5 0
ST/0 C
[
MO 8835 4-in. NO Getc.
E-6 2
B O
Cold shutdown MA 4.7 ST/O h
PSV 8851 3/4-in. Safety C-5 2
C C
5 years NA L*
Psv 8853A D-5 C
5 years NA
[
PSV 88538 C-5 C
5 years NA
[
i*
PSV 8858 3/4-in. Safety C-3 2
C C
5 years MA I'
i I
9 y
4.*
f, I
r.
i,,
y
- -)
V 1
- ,.V
~f,. j V,
i I.
c.
,n A p!
(
p.
l-N l'
TABLE 4,1-1 Sheet 11 of 37
,f, h'
o SYSTEM: Safety Injection P&lD NO.:
M-206, Sheet 2. Revision 5 I,(.
- l. 4 ASME e.
Valve Valve Dwg Code Sect 11 Notu Test Frequency I, ',,
ID No.
Description Loc Class Cat.
Pos Exercise Leakage Ceaunents Testing e'
s CV 8888 3/4-in. A0 C-6 2
A C
3 months 2 years 4.9 ST/C Clobe f,
8905A 2-in. Check D-7 1
AC C
Cold shutdown Cold shutdown 4.7. 4.10 89058 B-7 C
and refueling
~
8905C C-T C
8905D B-7 C
lc n
8919A 3/4-in. Check C-4 2
C C
3 months NA C
8919B B-4 C
~
- l 8922A 4-in. Check D-4 2
C C
Cold shutdown MA 4.7 8922B B-4 C
[-
n-MO d923A 6-in. M0 Cate C-3 2
B 0
3 months M *.
ST/0
(;
h MO 89233 B-3 0
ST/0 e
MD 8924 6-in. M0 Cate B-2 2
B O
3 months NA ST/9 I'
{N 8926 8-in. Check C-2 2
C C
3 months MA 4.8 gf
- g. '
fn-
)..
P.
il I
b
- 1 h5 L1 t,
t.
-a$-
j)}
i l
~
d i
0
' i, ~
f.
r
.. ~ - -.
r--..:.-..-...----...---.r.~w i
(
a ;o TABLE 4.1-1 She*L 12 of 37
- > o ts <
e
- 1 i
c-e l "o SYSTEM: Containsment Spray P&lD No.:
M-207, Bevision 19 c-
- s 2-O ASME Valve Valve Dwg Code Sect XI Notin Test Frequency ID No.
Description Loc Class Cat.
Pos Exercise Leakage Comuments Testit.g CS O28 10-in. Check C-8 2
C C
Refueling NA 4.7. 4.13 CS 029 (10-HCB-9)
B-8 C
CS 2001 14-in. Check G-3 2
C C
3 months WA 4.8, 4.13 CS 2002 (14-HCB-14)
B-3 C
CS 2003 2-irt. Check E-4 2
C C
3 months NA f'
CS 2004 (2-CCB-9)
C-4 C
j C
MO 2050A 14-in. M0 Cate C-3 2
B O
3 months NA ST/C f
MO 20505 B-3 ST/C MO 2057A 14-in. NO Cate F4 2
B C
3 months MA ST/OC f
MO 20528 B-3 C
STIOC is 1t0 2053A IC-in. MO Cate C-7 2
B C
3 months NA ST/O MO 2053B B-7 C
ST/O
,I -
MO 2056A 2-in. M0 Clobe D-5 2
B C
3 months MA ST/0C MO 20568 D-5 C
ST/OC r.
4 Mo 2069A 18-in. No Cate D-3 2
B O
3 months EA ST/O f'
MO 20698 D-3 O
ST/O
[,
PSV 2078 1-1/2-in.
F-6 2
C C
5 years WA j
Safety j'
PSV 2084 2-in. Safety E-6 2
C C
5 years
!'A y
PSV 2085 2-in. Safety E-6 2
C C
5 years NA
(.
i 4
e r
i S
h i
t 9
~y.
U e
y N*
n.a
, r-t
-4 k
l/
i e */
{
I I
TABLE 4.1-1 Sheet 13 of 37 I
SYSTrJt:
Main Steam P&ID B0.:
M-208, Sheet 1. Revision 30 h
I.
i.
N Valve Valve Dws Code Sect XI Norm Test Frequency ID No.
Description Loc C.t.ss Cat.
Pos Exercise Leakage Comments Testing i-f, MS 220 1-in. Check C-2 2
C O
3 months MA 4.13 MS 221 E-2 0
MS 222 C-2 0
MS 223 B-2 O
U MS 224 C-2 O
d' MS 225 E-2 O
}
MS 226 C-2 O
O h
MS 227 B-2
!~
MS 2001 28-in. Check H-1 2
C 0
Cold shutdewn NA 4.7
[^
MS 2002 (28-EBB-1)
F-1 MS 2003 D-1 A
X MS 2004 B-1 C
MS 2006 3-in. Check C-3 B31.1 C
C 3 months MA MS 2007 (3-EBD-7)
E-3 C
b
)
MS 2008 C-3 C
I.
MS 2009 A-3 C
I...
tr CV 1451 3-in. AO Cate C-3 2
B C
3 months NA ST/OC CV 1452 E-3 C
ST/0C b,I CV 1453 C-3 C
ST/0C CV 1454 A-3 C
ST/OC b+
B C
Cold shutdown MA 4.7 ST/OC b
PSV 2207A 1-in. Safety C-2 2
C C
5 years WA L
PSV 2207C C-2 C
I".
PSV 2207B E-2 C
b m,
d *c PSV 2207D B-2 C
~
I n
g p.
U#
[<
g-p p*
s.
y 9-5;
-.r-ao-.
--e
+ -
4 e
l' t
TABLE 4.1-1 Sheet 14 of 37 N 'N
- i
- :
SYSTEH: Main Eteam P&ID MO.:
M-208, Sheet 1, Revision 30
- g ga
~
$~
ASME Valve Valve Dwg Code Sect XI Noru Test Frequency I
~
ID No.
Description Loc Class Cat.
Pos Exercise Leakage Cosuments Testing p
t PSV 2211 6-in. Safety H-3 2
C C
5 years MA i,
PSV 2212 H-3 C
PSV 2213 H-3 C
PSV 2214 H-3 C
PSV 2215 H-3 C
l CV 2216 28-in. A0 H-2 2
BC 0
Cold shutdown MA 4.7 ST/C k'
f check CV 2230 6-in. AO Clobo F-3 2
B C
Cold shutdown MA 4.7 ST/0C g
PSV 2231 6-in. Safety F-3 2
C C
5 years MA l-C PSV 2232 F-3 C
O PSV 2233 F-3 C
j, PSV 2234 F-3 C
i PSV 2235 F-3 C
[
i CV 2236 28-in. AO F-2 2
BC 0
Cold shutdown MA 4.7 ST/C p/
Check CV 2250 6-in. AO Clobe D-3 2
,8 C
Cold shutdown MA 4.7 ST/0C PSV 2251 6-in. Safety D-3 2
C C
5 years MA PSV 2252 C-3 C
PSV 2253 D-3 C
PSV 2254 E-3 C
PSV 2255 D-3 C
CV 2256 28-in. AO D-2 2
BC 0
Cold shutdown MA 4.7 ST/C b
Check
}
I~
CV 2270 6-in. A0 Clobe C-3 2
B C
Cold shutdown MA 4.7 ST/OC 4
e
.I' e
a k
y.
.}
, l.
-.- J r-L.
t TABt.E 4.1-1 Sheet 15 of 37
~ fi>
p k
SYSTEM: Main Steam P&ID 50.:
M-208. Sheet 1. Revision 30 p'*.
' Valve Valve Dwg Code Sect XI Norm Test Frequency ID No.
Description Loc Class Cat.
Pos Exercise Leekage Comments Testing
{';.
PSV 2271 6-in. Safety B-3 2
C C
5 years MA 0;_
h PSV 2272 B--3 C
PSV 2273 B-3 C
PSV 2274 B-3 C
{-
PSV 2275 B-3 C
f.3 I
28-in. AO B-2 2
BC 0
Cold shutdown MA 4.7 ST/C CV 2276 4
Check g
e' CV 2277 3-in. AO Clobe C-2 2
B O
3 months MA ST/C V
f h(
CV 2278 E-2 O
ST/C CV 2279 D-2 O
ST/C CV 2280 B-2 O
ST/C CV 2294 1-in. AO Cate E-4 2
B O
3 months NA ST/C
- h; CV 2295 C-4 O
ST/C h'
CV 2296 B-4 O
ST/C CV 2297 G-4 O
Sf/C Fj
.l. i
^s[.
b
- t. ;
I
(
n >e
>e r-ts <
v-v
- t
}-~ i Ca 84 c- -
O g
e, hr=
m
[
@ W g
t v
I p
s;-
t t.%
h i
(
1l.
s
- =:-----------=c
.s
![
i I
t a :o TABLE 4.1-1 Sheet 16 of 37
>u EN i
r."$
SYSTEM: Main and Auxiliary Feedwater P&lD NO.:
M-213, Sheet 2 Revision 12 ga
~
g~
ASME v
Valve Valve Dws Code Sect XI Norm Test Frequency h-ID No.
Description Loc Class Cat.
Pos Exercise Leakage Comments Testing W 2005 2-in. Check G-7 B31.1 C
C Cold shutdown MA 4.7 l I W 2006 (2-CCC-CK)
G-1 C
}
W 2007 G-3 C
}-
W 2008 G-5 C
FW 2009 3-in. Check G-7 2
C C
Cold shutdown MA
- 4. 7_
j; W 2010 (3-DBE-3 )
G-2 C
p N 2011 G-3 C
- q W 2012 G-5 C
l W 2013 3-in. Check G-7 2
C C
Cold shutdown MA 4.7 O
l W 2014 (3-EBE-3)
G-2 C
{.
W 2015 G-4 C
W 2016 G-6 C
l' W 2017 14-in. Check F-8 2
C O
Cold shutdown MA 4.7 W 2018 (14-EBE-3)
F-2 0
i' '
W 2019 F-4 0
W 2020 F-6 0
i*
P I'
CV 3M4A1 3-in. M0 Clobe F-6 B31.1 B
T 3 months MA ST/OC CV 3004B1 F-2 T
ST/OC CV 3004C1 F-3 T
ST/OC CV 3004D1 F-5 T
ST/OC s
i CV 3004A2 G-6 B31.1 B
T 3 months MA ST/OC i
CV 3004B2 G-2 T
ST/OC CV 3004C2 G-3 T
ST/OC CV 3004D2 G-5 T
ST/OC l-k' i.
I 1
_____________________.__.___________._________._______.___________________________m___
_____._m_______.___.________._____._.______m
. _ w _. 2... s
.i.
c.
..~ z ~u.c 1
.. r. g
)
~
ay o
e-4 4
e s :..
1
[:-f
- s. -
y<
TABLE 4.1-1 Sheet 17 of 37
.i
[Q SYSTY.M: Main and Auxiliary Feedwater P&ID NO.:
T1-213. Sheet 4, Revision 2
(.l ASME fl Valve Valve Dwg Code Sect XI Norm Test l'requency ID No.
Descripticn Loc Class Cat.
Pos Exercise Leakage Comuments Testing g
9 3
FW 2027 6-in. Check B-6 B31.1 C
C 3 months NA l'
W 2028 (6-DBD-43)
B-6 C
f, f W 2029 C-6 C
3 months NA i-l.i e
FW 2030 C-6 C
FW 2033 6-in. Check B-8 B31.1 C
C Cold shutdown NA 4.7 f
^
FW 2034 (6-DBD-5)
C-8
,c~
SW 2002 6-in. Check D-6 B31.1 C
C 3 months MA
/ AIFD-7)
'j MG -30iS A 6-in. MO Cate B-6 B31.1 B
C 3 months NA ST/O y
MO-3045B C-6 C
ST/O l '
b^
MO-30608 6-in. M0 C-6 B31.1 B
C 3 months MA ST/O j
Butterfly p
L k
01 a.
p
,x t~
p-9 ^~ (0 4.
8* >^
O g.,,
c== :3 p
e t-CD e co le r'
v h,
1 1.
. h i
p
(
)-
e TABLE 4.1-1 Sheet 18 of 37 a, <yo e<
n e-t-
e-a a
"E SYSTEM: Auxiliary Steam P&ID MO.:
M-214, Sheet 1. Revision 38 i'
- :s
- ?
e g-oo -
O ASME l
Valve Valve Dwg Code Sect II Noria Test FrsTuency O
f ID No.
Description Loc Class Cat.
Pos Exercise Leakage C m ts Testing i
g e
MO 3071 4-in. MO Clobe B-4 B31.1 B
C 3 months MA 3T/O MO 3170 B-4 O
ST/O
{s n.
.~
A v
k F
l, '
O m
f*
~
k5 i'
d e
s
.J l
I I-l 3,.
i 4
. jus y
t id t.
/
i
. u A _.m.i L _
- a., c
.mm
~
c.' ' y l
t;'
b p,
TABLE 4.1-1 Sheet 19 of 37
{
SYSTEM: Component Cooling Water P&ID NO.:
M-215 Sheet 1. Revision 32
{'
?<i ASME Valve Valve Dws Code Sect II Norm Test Frequency ID No.
Description Loc Class Cat.
Pos Exercise Leakage Comments Testing
?
t, CS 2001 1-in. Check G-3 B31.1 C
O Cold shutdown MA 4.7 CS 2002 (1-GBD-26)
D-3 O
l5 CS 2003 1/2-in. Check G-3 B31.1 C
C Cold shutdown MA 4.7
[
GC 2004 (1/2-HBD-65)
D-3 C
CC 2033 1.5-in. Check B-7 B31.1 C
C 3 months NA li CC 2034 B-7 C
CC 2044 H-7 C
r4 CC 2045 H-7 C
h CC 2037 24-in. Check C-6 B31.1 C
O 3 months NA CC 2038
( 24-HBD-2 7 )
D-6 C
{
CC 2039 G-6 C
9 CC 2040 F-6 0
!t CV 3303 18-in. AO E-7 B31.1 B
O 3 months NA ST/C g,
CV 3304 Butterfly D-7 0
ST/C y
PSV 3263 2-in. Safety E-4 B31.1 C
C 5 years NA PSV 3373 2-in. Safety G-4 B31.1 C
C 5 years NA PSV 3374 D-4 C
V I..
PSV 3392 G-4 C
y SV 3715A 3/4-in. SO G-7 B31.1 B
O 3 months NA ST/C
,(
SV 3715B Cate A-7 O
ST/C l%
nw h:
D <
(<
- ' en.
c.
O b.
t,'
e-* :3 e
k-OD e-=
i 8
i:
R
[-
h b=
[.~;
.-n
_7 3:
?
lc IABLE 4.1-1 Sheet 20 of 37
[
m,>c E1
~
I Nh SYSTEM. Component Cooling Water P&ID NO.:
M-215. Sheet 2. Revision 5 i
ga
+
m-$
ASME Valve Valve Dws Code Sect Il Norm Test Frequency p
ID No.
Description Loc Class Cat.
Pos Exercise Leakage Commsents Testing Of i.
CC 2035 1.5-in. Check B-3 B31.1 C
O Refuelins NA 4.7, 4.13
,k,
CC 2036 B-4 0
},
CC 2046 C-3 0
L~
(._
CC 2047 H-4 O
MO 3210A 12-in. M0 F-7 B31.1 B
C 3 months NA ST/O b
{.
MO 3210B Butterfly C-7 C
ST/O 1:
~
PSV 3285A 2-in. Safety C-5 B31.1 C
C 5 years NA C
h.
PSV 3285B B-5 C
['
l CV 3287 18-in. A0 F-3 B31.1 B
O 3 months NA ST/C l,
CV 3288 Butterfly D-3 O
ST/C l-Z-
MO 3290 14-in. M0 C-2 2
B O
Cold shutdown MA 4.7 ST/O
[
MO 3291 Butterfly C-2 O
ST/O
.J MO 3292 G-8 0
ST/O A
MO 3293 14-in. MO C-7 B31.1 B
C 3 months MA ST/O l~
Butterfly f,
MO 3294 6-in. M0 Cate H-2 B31.1 B
O Cold shutdown MA 4.7 ST/C MO 3295 8-in. No C-3 B31.1 B
O Cold shutdown MA 4.7 ST/C Butterfly MO 3296 4-in. MO Cate B-2 B31.1 B
O Cold shutdown NA 4.7 ST/C P
a I,
g*
i
.I.'
.t i.
{..
V O. %
.g.
m.
.u.2,
.~
']
r p
i e
s p
H EE 4.1-1 Sheet 21 of 37 1p 1::
n.
SYSTEM: Comiponent Cooling Water P&lD NO.:
M-215. Sheet 2 Revision 5 p
f.')
ASME t.
Valve Valve Dwg Code Sect 11 Norm Test Frequency ID Mo.
Description Loc Class Cat.
Pos Exercise Leakage Comunente Testing
'r, MO 3298A 1.5-in. MO C-3 B31.1 B
O Cold Shutdown MA 4.7 ST/C MO 32988 Cate A-3 O
ST/C
[9 T'.0 3298C A-4 O
ST/C b
I' MO 3298D G-4 0
ST/C HO 3300 6-in. MO Gate C-f B31.1 B
O Cold shutdown MA 4.7 ST/C f.
^
(a MO 3319 8-in. MO B-4 B31.1 B
O Cold shutdown MA 4.7 ST/C i
Butterfly
['d i,
MO 3320 4-in. MO Cate A-5 B31.1 B
O Cold shutdown MA 4.7 ST/C l
[ li PSV 3323A 2-in. Safety F-7 B31.1 C
C 5 years MA g
PSV 3323B C-7 C
MO 3346 14-in. MO A-8 2
B O
Cold shutdown MA 4.7 ST/O
[
Butterfly f'
MO 3347 14-in. NO A-7 B31.1 B
C 3 months NA ST/O Butterfly
{
r ba
^ :o I
kV t3" ;;
V g
o g~
k.
}. -
b h)h r
J i
- .~
.~
f -
m, TABLE 4.1-1 Sheet 22 of 37 I
<:5 <
3.
I "7
SYSTEM: Service Water P&ID NO.:
M-218. Sheet 1 Revision 38
?
G" 3
oo -
0 N
]-
Valve Valve Dws Code Sect 11 Norm Test Frequency T' do.
Description Loc Class Cat.
Pos Exercise Leakage Comuments Testing
.'~
z.
SW O22 12-in. Manual F-6 B31.1 4
C 3 months MA EE i
Butterfly
)
SW 023 4-in. Manual G-6 B31.1 B
C 3 months NA EI I.
SW 024 Cate G-6 C
EX k
s-SW 025 12-in. Manual D-7 B31.1 B
C 3 months MA EI 1"
Butterfly i'
SW 026 4-in. Manual C-7 B31.1 B
C 3 months NA EI C
j
^
SW O27 Cate C-7 C
EI 7l SW 028 C-7 C
EI
[
SW 029 30-in. Manual C-6 B31.1 B
O Cold Shutdown MA 4.7 EI SW 030 Butterfly B-6 0
Cold Shutdown 4.7 EI I
SW 031 G-5 C
3 months EI
!~
SW 032 B-5 C
3 months EI I'
SW 041 H-5 C
3 months EI f
SW 042 C-4 C
3 months EI SW 043 H-4 T
3 months 4.8 EI SW 044 C-4 T
3 months 4.8 EI b
SW 045 F-4 C
3 months EI
', ~
+
SW 046 N4 C
3 months EI SW 223 4-in. Manual C-6 B31.1 B
C 3 months NA EI Cate 1~
f 1
5 i
i
.5 V
C#
2 l
2-o
...__ a m. - --
1 _-. __.,%.y l
l e ;,.
I sm.
I
- .j l
t l
l (il l
.VC l
!.bl TABLE 4.1-1 Sheet 23 of 37 j2 SYSTEM: Service Water P&lD MO.:
M-218 Sheet 1, Revision 38 5
n -l I fh, ASME Valve Valve Dwg Code Sect II Norm Test Frequency E,
ID No.
Description Loc Class Cat.
Pos Exercise Leakage Comuments Testing
- [/ j r 'c.
n SW 395 6-in. Manual C-6 B31.1 B
C 3 months MA EI Eq "s
SW 397 Butterfly G-5 C
EK SW 2003 30-in. Check G-7 B31.1 C
O 3 months MA i
SW 2004
( 30- HFD--1)
C-7 C
- .y SW 2005 E-7 0
E
[1 SW 2012 12-in. Chcck F-6 B31.1 C
C 3 months MA SW 2013 D-7 C
- ?
SW 2014 10-in. Check G-5 B31.1 C
0 3 months NA SW 2015 (10-HFD-3)
F-5 C
I, a
i SW 2023 (10-HFD-2)
C-5 O
C h SW 2024 D-5 C
sg' j
PSV 3708A 3/4-in. Safety H-6 B31.1 C
C 5 years MA Q
PSV 3708B C-6 C
P J
CV 3712A 8-in. AO F-3 B31.1 B
C 3 months MA ST/O L r.
a
,c CW 37128 Butterfly E-3 C
ST/O
??
CV 3714 E-3 O
ST/C fi) 1 CV 3720A E-4 O
ST/C F.
h I
CV 3720B E-4 O
ST/C CV 3725 E-3 B
0 ST/C Ri f4 CV 3803 3-in. A0 D-1 B31.1 B
O 3 months MA ST/C l,"
CV 3804 Butterfly F-7 O
ST/C PSV 3832A' 2-in. Safety C-4 B31.1 C
C 5 years MA
[N J
e pa f
U $ PSV 3832B C-2 C
{b 4
E 7 PSV 3832C D-4 C
i "o
PSV 3832D B-2 C
[
E" Y, -
oo -
03 l4..
v (a
1
.i s r j
{?
.o :
1 e
c
~
~
2' f
^_
t,t.
?'<,I; 661t i!I. !I,l1t !rIge;.
. f 1?$3^
i:[tf r Ei? 4' f l;-
{i
,(l 7.
5f
' t :i.
^C
-~
7 3
g
,)G f
n o
i t
4 s
~
2 e
8 T
~
t 3
ee n
h o
S i
s iv s
~
e t
R n
e
~
m 1
mu o
t C
e eh S
8 1
2 e
g N
a y k c a n e e L O
u A
A A M
q N
N N e
D r
I F
&P ts e e
s T
ic s
s s r
r r r 1
e a
a a x
e e e 1
E y
y y i
L-4 5
5 5 ELB m
1 A
r s T
oo NP CC C C I
I
~
tt ca eC S
C C C s
Ees 1
1 1 Md a 1
1 1
S ol 3
3 3 ACC B
B B r
gc 33 5 7 e
wo t
DL GD A A a
W y
t e
e y
c n
f t
i o
a e
v i
S f
r et a n e
vp S i S
li n
- y ar i
. 2t V c n / e s
4 i 1i M
e
/
- a E
D 3
2 1 S T
SYS AB 33 4 5 33 3 3 88 8 8 eo 33 3 3 vN l
VV V V aD SS S S VI PP P P
, a < ** 7: -
s e
m>s1
.eo8 p
t*
i' ll t
V>
,}
' [;
3 Q
t.
~
?
. ~
TABI.E 4.1-1 Sheet 25 of 37 y
t I' r f
3{%
SYSTEM: Clean Radioactive Waste P&ID NO.:
M-220. Revision 32 ASME
('i s:
l' w
Ic Valve Valve Dws Code Sect II Norm Test Frequency h,,
ID No.
Description Loc Class Cat.
Pos Exercise Leakage Commaents Testing p
CV 4000 1-in. AO Clobe H-8 2
A O
3 months 2 years 4.9 ST/C t :'
^
(.
[-
NO 4005 3-in. MO Cate F-8 2
A
.O 3 months 2 years 4.9 ST/C (y
CV 4006 3-in. AO Cate E-7 2
A O
3 months 2 years 4.9 ST/C
[.'
CR 2035 1-in. Check G-8 2
AC C
NA 2 years 4.5.24.9
[_
r5 (1-CBB-1) l je g.-
- - ll u
s i.s I -
e3 e
4 j.:
8 l..
p
- ro pg i
e<
i
- 1 i
H 9^
O l
wU i
.t* th e
u O) W
. J. *,'
(D v
V i
[
f.D 5%
4-y;-
~..
w.-.
...... ~..........._--. w.
. s
. !.5 I
TABLE 4.1-1 Sheet 26 of 37 my
>e
.. +
y <
k 3--
,1 e*
~.
" o'^
SYSTEM: Dirty Radioactive Waste P&ID NO.:
M-221. Revision 26 f:
8:
g :s i
.~
ASME I.
a Valve Valve Dwg Code Sect II Norm Test Frequency
- r. -
^
ID No.
Description Loc Class Cat.
Pos Exercise Leakage Courments Testing
[
MO 4180 3-in. NO Cate H-8 2
A C
3 months 2 years 4.9 ST/C
'I h
CV 4181 3-in. AO Gate H-8 2
A C
3 months 2 years 4.9 ST/C i*:
F h:
1:-
- -.;.a.-
he' l'
l*
- ^
i _
g..
C'.
u:
- v..
.i l-l'
.te y-
.e i
n-.
J:
n 5 -
,w
^
..=
.i.. ;.. a a:oa;;
ii
'J
.~
,s
+-.)
th 49 W.. j
~ pl TABLE 4.1-1 Sheet 27 of 37
?
SYSTEM: Cascour. Radioactive Waste P&ID NO.:
M-222. Revision 28 7 ;'
,oe V;.'
- f.1 ASME l,';'*)
Valve Valve Dwg Code Sect II Norm Test Frequency
[
n ID No.
Description Loc Class Cat.
Pos Exercise Leakage Comments Testing C h t::
1 I, MO 4300 3-in. MO Cate G-8 2
A 0
3 months 2 years 4.9 ST/C D
CV 4301 3-in. Ao Cate H-7 2
A O
3 months 2 years 4.9 ST/C l '[,
h.'
6::
,.q
'<.1 I
Id m
'. *?
.I '
b % '
k u
.p r
, c' l'.,
4 b '
e i
>e a
e.1 r M (S
( [.
W &^
f' o
e*O
[*.'.<
O (D W io c
ab v
s*3 k,s y.
s 4
e t
Yb i
..3.
v.. s n u..
.k,.
I'!'
b i$-
- :o TABLE 4.1-1 Sheet 28 of 37 ff.
>e E$
Va.
r is "o
SYSTEM: Instrument and Service Air P&ID NO.:
M-223, Sheet 1, Revision 21 f
- :2 3-O ASME
~
t'alve Valve Dws Code Sect XI Notle Test Frequency
{.
ID No.
Description Loc Class Cat.
Pos Exercise Leakage Cosmaents Testing i
g.
^
g-v g
IA 2001 2-in. Check F-1 2
AC 0
Refueling 2 years 4.7, 4.9. 4.13
[,
(2-IIBE-8)
[y SA 2005 2-in. Check D-2 2
AC C
NA 2 years 4.5, 4.9
{-
(2-HBE-9)
CV 4470 2-in. AO Clobe D-2 2
A C
3 months 2 years 4.9 ST/C i~
t
~
CV 4471 2-in. AO Globe F-1 2
A O
Refueling 2 years 4.7. 4.9, 4.13 ST/C
{ ~
. [*
l.
4 i
}
j r I.
l
).
i4 I.
e I
l
[.-
,e I
r ep
, u.
v
.m
-..., w... ;
b ' l,.
p J
$f TABLE 4.1-1 Sheet 29 of 37
. -?1(
5;d
,, _h SYSTEM: Diesel Fuel Oil, P&ID MO.:
M-226 Revision 20
.0 ASME
^
Valve Valve Dwg Code Sect II Norla Test Frequency
- h.
ID No.
Description Loc Class Cat.
Pos Exercise Leakage Comments Testing p,('..
DO 2001 3-in. Check C-7 B31.1 C
C 3 months MA C
ld.
v m.
Do 2002 (3-HBD-72)
D-7 C
MO 4903A 3-in. MO Cate C-5 B31.1 a
C 3 months MA ST/O f;5 MO 4903B D-5 C
ST/O h'
MO 4907A 2-in. MO Clobe C-6 B31.1 B
C 3 mont.hs NA ST/O f
MO 4907B C-6 C
ST/O
{:n U ']
?'
'.I3 w
[ ',-
i ','
li-1 L
i) i it
- ;o
>a
.t u<
ts e1 >*
ru
_,O t.
e E3 w s
o CD v
t t
[T t1.'
f'!
s c
I; 6
'h
.D
+
4 F
l
_.o.
u~..-__.,_..
..;.. _ i _ _._<
r.
!' r c;
a :=
TABLE 4.1-1 Sheet 30 of 37
>e i..
is <
es c+
c-is o
SYSTEM: Spent Fuel Pool Cooling P&ID NO.:
M-227 Revision 25
- :s o
E, oo -
oo I
ASME w
Valve Valve Dws Code Sect II Noria Test Frequency ID No.
Description Loc Class Cat.
Pos Exercise Leakage Columents Testing I~.
SF-046 8-in. Gate F-2 2
A C
MA 2 years 4.5, 4.9
[;s:
[..
SF-062
- -in. Cate E-2 2
A C
MA 2 years 4.5, 4.9
,1, 1
SF-063 E-2 I
i.
SF-073 10-in. Cate B-2 2
A C
MA 2 years 4.5, 4.9 l-SF-074 B-2 C
f G
SF-080 8-in. Cate F-2 2
A C
MA 2 years 4.5, 4.9 1
1 y.
n CV 5075 4-in. AO Cate 0-7 3
B C
3 months MA ST/C
{.
CV 5076 D-7 C
ST/C l
y %
g e
?
I,.
f I
i.
3-r 5
.?~
.r Q)
Qj)
.p
.R
~ ?,).
l '.h, y
. * ;c TABLE 4.1-1 Sheet 31 of 37
[,* '
t '..
- l'.d SYSTEM: Makeup Water Treatment P&ID NO.:
M-228. Revision 36
. o
{;i.;
1:;!
}.
ASME Id Valve Valve Dws Code Sect II Norm Test Frequency f,9 ID No.
Description Loc Class Cat.
Pos Exercise Leakage Comuments Testing
[.'
~
MD 059 3-in. Manual F-1 2
A C
NA 2 years 4.5, 4.9 Cate g '.'
(i.$
MD 2011 3-in. Check F-1 2
AC C
NA 2 years 4.5, 4.9 (3-HCB-3) is, p,
6 L, ', _
I
('
)
n.
,1
[1
't N
e e
O N
> 0 t <
- {f' 8
- 1 r e
P (4
((.
rr a
1~ b'.
0
~ v
/
s (D *-=
03
$I J 7,;g 4
K
((
r;.
I-
[Il-1 m
m
..g _ q.
...a,
.. a.
x _ -.. :..-
~, a.
w a. w
.x.
=
_.: -: a..
py L..
p Ir:: -,
TABLE 4.1-1 Sheet 32 of 37 h
mw
>o e
e<
t.
N$
"E SYSTEM: Sampling P&ID NO.:
M-231. Sheet 1. Revision 27
.h -
g :s b:
[~ -
O ASME r
Valve Valve Dws Code Sect II Borm Test Frequency M
ID No.
Description Loc Class Cat.
Pas Exercise Leakage Comments Testing i;
o CV 2809 3/4-in. AO H-6 2
B O
3 months MA ST/C t
f/
CV 2811 Globe H-7 O
ST/C CV 2814 H-6 O
ST/C 2
CV 2880 H-7 O
ST/C No 5651A 3/4-in. MO H-4 2
A C
3 months 2 years 4.9 ST/C MO 56515 Globe H-4 C
ST/C MO 5651C H-4 C
ST/C g
MO 5651D H-4 C
ST/C b'
f '
CV 5652 3/4-in. AO 2
A C
3 months 2 years 4.9 ST/C
'G-4 Globe
'~
MO 5653 3/4-in. No H-6 2
A C
3 months 2 years A.9 ST/C 4
MO 5654 Globe H-5 C
ST/C t
CV 5655 3/4-in. AO G-6 2
A C
3 months.
2 years 4.9 ST/C C
Globe MO 5656 3/4-in. NO H-5 2
A C
3 months 2 years 4.9 ST/C Globe k
CV 5657 3/4-in. AO G-5 2
A C
3 months 2 years 4.9 ST/C Globe e
im MD 5658 3/4-in. NO H-5 2
A C
3 months 2 years.
4.9 ST/C Globe CV 5659 3/4-in. AO G-5 2
A C
3 months 2 years 4.9 ST/C 5
Globe MO 5660 3/4-in. No C-6 2
A O
3 months 2 years 4.9 ST/C i-Globe i.'
r t;
CV 5661 3/4-in. AO B-6 2
A O
3 months 2 years 4.9 ST/C 9
h, Globe i.
f~.1 C
U b
.+,
._.m.
- s---
3
(' ;,
- I-
.)
i b
- t:
g,
TABLE 4.1-1 Sheet 33 of 37 SYSTEM: Containment Ventilation P&ID NO.:
M-243. Revision 22 j*
n iSME
.s f
I Valve Valve Dws Code Sect XI Norla Test Frequency ID No.
Description Loc Class Cat.
Pos Exercise Leakage Cosaments Testing
- f. 3 SV 5642 3/4-in.
F-7 2
A C
3 months 2 years 4.9 ST/C j..
SV 5643 Solenoid E-7 C
ST/C MO $663 1-in. NO Clobe E-7 2
A O
3 months 2 years 4.9 ST/C MO 5671 E-7 O
ST/C MO $672 E-6 O
ST/C Y
MO 5673 E-7 O
ST/C fe.
MO 5674 E-7 C
ST/C O
![
MO 5675 F-7 C
ST/C b<
MO 5676 E-7 C
ST/C MO 5677 F-8 C
ST/C h
MO 5678 E-8 C
ST/C SV 5679 3/4-in.
E-7 2
A C
3 months 2 years 4.9 ST/C Solenoid
- 3
,n CV 10001 54-in. AC D-2 2
A C
Cold shutdown 2 years 4.7. 4.9 ST/C I'
Butterfly ST/C I.-
t '.
NO 10002 54-in. MO D-2 2
A C
Cold shutdown 2 years 4.7. 4.9 ST/C MO 10003 Butterfly D-7 C
ST/C Plk i
l CV 10004 54-in. A0 D-7 2
A C
Cold shutdown 2 years 4.7. 4.9 ST/C lll Butterfly IL t
V
^ ':o NE
~
E7
- I ',.
[
.c
$e
. N.
. :l.:
8 h
p
[.?
i i
1 +
r%
.. -. a...u.u w -. a
-.---==.:a.
b':e.
,n:-
5' L
l 1
I TABI.E 4.1-l' Sheet 34 of 37 Q{
,,>o
\\
ns <
i.
n r.
p.
r SYSTEM: Containment Ventilation P&ID NO.:
M-243. Revision 22 i'-
r :3 T
4 ce ~
k :.
ASME Valve Valve Dwg Code Sect II Noru Test Frequency ID No.
Description Loc Class Cat.
Pos Exercise Leakage ca===nts Testing j.
t-MO 10005 8-in. NO C-2 2
A C
3 months 2 years 4.9 ST/C
[
MO 10006 Butterfly C-2 C
ST/C
't MO 10007 C-2 C
ST/C i.
No 10008 C-2 C
ST/C n
s NO 10009 8-in. NO C-7 2
A C
3 months 2 years 4.9
'ST/C C
f MO 10010 Butterfly C-7 C
ST/C MO 10011 C-7 C
ST/C MO 10012 C-7 C
ST/C f-10610A 3/4-in. Cate D-7 2
A C
NA 2 years 4.5, 4.9 l
10610B D-7 C
lA 10611A C-7 C
l 106118 C-7 C
L.
I t'
I
.i i
lD
- -t 5
[
i y
=
p
-(.
i-
)
' ~
h
. -.. ~.... -
c.
. -....a l
,R
.s.
r i.
's i..)
r:;
I k-
.c TABLE 4.1-1 Sheet. 35 of 37 j
Y SYSTEM: Chilled Water P&lD HO.:
M-248, Sheet 1. Revision 18 ASne c
Valve Valve Dws Code Sect XI Noria Test Frequency
,D ID No.
Description Loc Class Cat.
Pos Exercise Leakage Comuments Testing
((*
m MO 10013 4-in. M0 B-3 2
A 0
3 months 2 years 4.9 ST/C
{l Butterfly l
s '.
CV 10014 4-in. AO B-4 2
A 0
3 months 2 years 4.9 ST/C
[
CV 10015 Butterfly B-4 O
ST/C
[
1-MO 10016 4-in. M0 B-3 2
A O
3 sionths 2 years 4.9 ST/C g
Butterfly i'
J.
1-i L
6 I
e t
- > e e
o a:
N. **
f W C' O
o* :3 6:
e t
OF W W
l V
I..
I e
i
(:
j
4-f__.
_. __._.._.- m _....._ _..... _ -
_.._m____
i' s
- t. <
{.'
I:
TABLE 4.1-1 Sheet 36 of 37 ts <
(' --
- 1 o*
>~ e
7 SYSTEM: Steam Generator Blowdown P&lD NO.:
M-348. Revision 25 f:-
e-a t'.
e
- I..
cc w g,'
(,
Valve Valve Dwg Code Sect II Norm Test Frequency ID No.
Description Loc Class Cat.
Pos Exercise Leakage Comments Testing
.f.
MO 2808 2-in. NO Cate D-7 2
B O
3 months MA ST/C NO 2810 H-7 O
ST/C h-MO 2812 E-7 O
ST/C F
MO 2813 F-7 O
ST/C j,.
I' MO 6716 2-in. M0 Globe H-8 2
B O
3 months MA ST/C MO 6717 F-8 O
ST/C k
MO 6718 E-8 O
ST/C
(-
MO 6719 D-8 O
ST/C s.
?
P
$V.
s I
f l
I h
h Ip I
i 1
t' l
r-b e-i l
l l
7 e.
,g l
'Q l
l 1
_m n
en.
. i.
6.- -!
Q l
5 v
i*
TABLE 4.1-1 Sheet 3? of 37
- F U
' t.
SYSTEM: Contairunent Personnel Air-Lock Leak Detection System P&ID 30.:
H-5008. Revision 2 l
f'.
A ASM8t l
Valve Valve Dwg Code Sect II Norm Test Frequency ID No.
Description Loc Class Cat.
Pos Exercise Leakage r e ts Testing C
I h
SV 6991 1/2-in.
C-6 2
A C
3 months 2 years 4.9 ST/C j-SV 6992 Solenoid G-5 C
ST/C D
e
.f.
f
]
$?b l
L, k
r i,
1 I
\\
^ 9e i.
i
>e ts c Pt M
- 4..
F GB V* W l
O W D I
\\
.l' 4
y-e.-.
i e
CD
-{-
6-5 4
t 4,
i 1
I f
t l.
g 8
)
~
8 J.
.r i
4
' w. a... -.... -.. l.. b II...
2..,
m.
- l.. :
..... :. J.
... ~... -.
j J
(
i TABLE 4.1-2 Sheet 1 of 29 th
(
N./
FULL-STROKE EXERCISED VALVES
.i The following Category A, B, and C active valves cannot be exercised during Plant operation and will be full-stroke exercised during cold 4
shutdowns as per Paragraphs IWV-3412 and -3522 or during refueling outages as indicated by relief requests.
M 201: Reactor Coolant Systes A.
Valves: SV 1015A, SV 10158, SV 1016A, and SV'i0l6B Category:
8 i
l Class: 2 Function: These valves are sol 6noid-operated isolation valves for the reactor vessel head vent lines. They permit venting of the reactor vessel head under abnormal conditions.
Test Requirement: Exercise for operability every three taonths during e,
Plant operation or during cold shutdown if the valves cannot be exercised during Plant operation.
I 4
Basis for
Conclusion:
Operation of these valves while the RCS is under pressure could result in venting primary coolant to the Containment atmosphere.
Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown.
f 6-x-s Revision 1
( April 1988'/
s
.s r
.1
. a.,u i - i.. i +. n.: a.1:.
.' A..
. w..a u.?
l t
.I
+ C2l TABLE e l-1 Sheet 2 of 29 c
B.
Valves: 8900A, 89008, 3900C, 8900D
]
Category: C
]
1 Class: 1 A
Function: Esch of these check valves prevents backflow from its respective RCS cold leg into the boron injection tank (BIT) during normal operation and allows flow from the BIT to the RCS during safety injection.
J Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
Exercising these valves would require injec-tion of the contents of the BIT into the RCS.
While the RCS is at normal operating pressure
.)
the contrifugal charging pump (CCP) cannot develop check valve design flow.
4 Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown at reduced RCS pressures where adequate flow can be obtained.
i j
C.
Valves: 8948A, 8948B, 8948C, 8948D l
i Category: AC Class: 1 9
Function: Each of these check valves prevents backflow from its respective RCS cold leg and sequentially allows flow from the SIS accumulators, the SIS pump discharge, and the RHR
')
i i
System during safety injection.
Revision 1 (April 1988) 1
_e.._..-
m.... m m..i u a. c.u. u > a :... e....,. e...
..,m s.,
i j
'i l
i TABLE 4.1-2 Sheet 3 of 29 10 9
Test Requirement: Exercise for operability every 3 months.
j g
l Basis for conclusion: Rxercising of these valves would require injection of concentrated boric acid into the J
RCS, causing a power transient that could result in a reactor trip. During power opera-tion, the SIS accumulators SIS pumps, and RHR pump's cannot overcome RCS pressure to achieve check valve design flow.
Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown using RHR pump flow.
D.
Valves: 8949A 89495, 8949C 8949D Category:
AC Class: 1 t
+%
Function: Each of these check valves prevents backflow from its respective RCS hot les to the safety injection pump and RHR pump discharge during normal operation and allows flow 1
for hot-les rec.rculation during accident conditions, i
3 l
Test Requirement: Exercise for operability every 3 months.
I Basis for conclusion: During power operation the safety injection and RHR System pucps cannot overcome RCS pressure.
Alternate Testing: These valves will be fv11-stroke exercised for
)
verification of operability during cold shutdown.
i Revision 1 1
(April 1988)
~,,-
c
..,h f,.J. t c
=
'w, m,,,
.,s.. a.. w.
,,.,s
.q,,,, ;
4 e
A i
I hl TAB 1.E 4.1-2 Sheet 4 of 29 i
(.
r
'.', /
E.
Valves PCV 455A and PCV 456 Category: 8 i
i i
class: 1 l
i runction: These valves prevent reactor pressure from activating the high-pressure reactor trip or from reaching the setpoint of the code safety valves. During periods of reduced RCS i
temperature (1290*F), these valves are used in the over-pressure mitigation system to prevent brittle fracture.
Test Requirements guercise for operability every 3 months.
Basis for
Conclusion:
Testing thc=c valves every 3 months increases the number of times each valve must open against desion RCS pressures in excess of
.s 2000 psig, thus deteriorating the valve seat and increasing the likelihood of damaging the valve seat and causing leakage.
In addition, these valves are not given credit in the i
design accident analysis, and since the Plant can operate without them, if they were to fall. they can be adeqvstely isolated by the j
block valves (No 8000A and B).
s Alternate Testing: These valves will be full-stroke exercised at cold shutdown.
t L
I Revision 1 (April 1988) s
l.a :
..'.:n.-....,.
..-..:. a.:
a~..-
.i.A:
..x.--.......
..--...a.;
e 1
o IAEf4E Sheet 5 of 29 l}
M 202 Chemical and Volume control System Valve 8546 Category: C s
Class: 2 Function: This check valve prevents backflow of water from the volume control tank (VCT) to the RWST during nomal operation and allows flow from the RWST to the CCP suctions during safe shutdown.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
Exercising of this valve would require injection of concentrated boric acid from the RWST into the RCS, causing a powe" dmient which could result in a reactor trip.
Alternate Testing: This valve will be full-stroke exercised for verification of operability during cold shutdown.
M 203: Chemical and Volume Control System A.
Valves: MO 8100 and MO 8112 Category: A Class: 2 3
Function: These nomally open Containment isolation valves close on a Containment isolation signal to isolate the RCP seal water return.
Revision 1 (April 1988)
IlL.,
. w ;. :...
J.. '
.6-.'
- i h [.
m.m c..& L.u tl S.. i v.
4..' * -
f
.. =..a o c:.,;
h t
Og TAE_LE 4.1-2 sheet 6 of 29 h
i j
Test Requirements guercise for operability every 3 months.
A i
i Basis for ConclusLont Failure of either of those valves in a closed i
b position would result in loss of sett 4eakoff i
flow.
}
1 Altemate Testing: These valves will be full-stroke exercLeod for veritication of operability during cold shutdown when the RCPs are, shut down.
2j 3.
Valves: No allo and MO 8111
(
i l
Categoryt 5 Class:
2 Function: These serles valves isolate CCP recirculation flow path return to the seal water heat exchanger.
t Test Requirementt Exercise for operability every 3 months.
[
Basis for conclusion: Failure of either of these valves in the J' '
closed position renders the recirculation flow
.i path inoperable. A mininum (low rate through the pumps is required to ensure puse cooling.
A safety injection actuation while either a
.{
valve is in the closed position could cause damage to both trains of high head safety
/*
injection if the RC8 pressure increases above 2
the discharge head of the CCP.
.i II Alternate Testing: These valves will be full-stroke exercised for verit1 cation of operability during cold shutdown.
l!
l.
1 l
Revision 1 (apt 11 1988) l 1
( -.
...w.
.. ~.,
~.a..
.~.a.
TABLE 4.1-2 Sheet 7 of 29 l}
M 205: Residual Heat Removal System 4.
Valves: MO 8701 and MO 8702 J
Category: A Class:
1 Function: These normally closed series valves connect the suction of the RRR pumps to the RCS Loop 4 hot leg. These valves are interlocked to prevent opening with RCS pressure >425 pais and to tutomatically close when RCS pressure exceeds 600 psis.
Test Requirement:
Exercise for operability every 3 months.
Basis for Co.sclusion:
Exercising of these valves during normal operation would require overriding of a safety Ju*triock. The potential for overprossuriza-
'Ji of the RHR System and depressur!:stion of tnw RCS make testing of these valves at normal RCS pressure unsafe.
Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown.
B.
Valves: 8736A 8736B Category: AC Class:
1 runction: These check valves prevent backflow from the RCS Loops 2 and 4 hot legs into the RHR System during normal operation.
Revision 1 (April 1988)
'.$~-.
,:n au.
. - G.
' 1:4, i n..i.a.:a..
. ;,.-a, -, e...
&.+
- . ~. -... -
- .u. -
L*
z.
\\
i 1
i
)
((l TABLE 4.1-2 Sheet 8 of 29 1
6 j
Test Requirement: 3xercise for operability every 3 months.
tj Basis for
Conclusion:
During normal operation, the RHR pumps cannot 4
3 overcome RCS pressure to achieve check valve design flow.
1
]
Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown.
C.
Valves: MO 8804A and MO 8804B Category: B Class:
2 Function: These valves are used during RCS cold-and hot-leg 1
recirculation where the RHR pump discharge is aligned to provide flow to the ruction of the CCPs and safety injection pumps.
Test Requirement: Exercise for operability every 3 months.
t
.~
\\
"f Basis for
Conclusion:
These valves are interlocked with the safety 1
injection pump recirculation flow isolation 1
valves (No 8813 and No 8814) which are exer-y cised on a cold shutdown frequency. Cycling these valves during power operation would require defeating the safety interlock.
Alternate Testing: These valves will be full-stroke exercised during cold shutdown with MO 8813 and MO 8814.
1 j
/
Revision 1 (April 1988)
--a v
..L.. u....- _ ~ :
w.'
-.:.,.. u:.... :.... x :
. -.. -., + :. : a.
~
.u.
. -.u 1
i.
?
,rw TABLE 4.1-2 Sheet 9 of 29 Ifh
.l (i. 'i 2:'.
i D.
Valves: MO 8809A and MO 8809B Category: B
}-
Class:
2 1
Function: These valves are aligned to provide RCS cold-leg injection flow from the RHR eystem.
Test Requirement: Exercise for operability every 3 months.
Basia for Conclusior..
These valves are required to be in th open position to meet the flow assumptions in the accident analysis.
Failure of either of these valves in the closed pcJition or safety injec-tion actuation while in the closed position could result in low head cafety injection flow at rate below that assumed in the safety analysis.
I Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown.
l 1
E.
Valve: HO 8812 Catedory: B Class:
2 Function: This normally open valve J repositioned to isolate the PMST from the RHR pump suction during the accident recirculation phase.
(
Test Requirement:
Exercise for operability overy 3 months.
Revision 1 (April 1988)
. s.._.. A......,
, < L.- m.... a
- w. a.. -._.. ; '.
e.u.. - ~;...
r m a., - -
L.
.,,.,p. t.sp 1
)
1 3
)
I
~
, n 401 TABLE 4.1-2 Sheet 10 of 29 I
4j Basis for conclusion: Failure of this valve in the closed position 4
would render the entire RHR System inoperable.
1 Alternate Testing: This valve will be full-stroke exercised for i
]
verification of operability during cold shutdown.
l1
?
F.
Valves: 8818A, 8818B, 8818C, 8818D 4
Category: AC t
Class: 1 f,
f Function: Each of these check valves prevents backflow from one of the RCS cold legs into the RHR System during normal opera-tion and allows flow from the RHR System into the RCS dur-ing cooldown, injection phase and cold-les recirculation
'~
phase of accident mitigation.
1 i
Test Requirement: Exercise for operability every 3' months.
I Basis for
Conclusion:
During normal operation, the RHR pumps cannot l
overcome RCS pressure, t
]
Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown.
4 5
G.
Valve:
8958 6
Category: C e
Class:
2 t.
Function: This check valve prevents backflow from RHR suction header to the RWST.
l Revision 1 (April 1988)
.. u L. :.....:.
...-. f.. a
-. w.
m ::a.
. -,. z. ~a t
I l
~
i TABLE 4.1-2 Sheet 11 of 29 l{}
j f, i,. 3
.~
6 Test Requirement: Exercise for operability every 3 months.
f Basis for
Conclusion:
Exercising this valve requires the RHR pumps drawing suction on the RWST. Operating modes
}
do not allow this because there is no place to store the water unless initiating large scale RWST recirculation (opening manual valve 8735).
l However, this is not feasible due to the RHR System operating in a degraded condition.
Cold shutdown is not feasible because the RHR is in circulation to the RCS using the RCS as a suction source. The only feasible Plant condition for which this valve can be exer-cised is during refueling when the RHR System is utilized to fill the refueling cavity.
\\
i' Relief Request: This valve will be full-stroke exercised during refueling outates when the refueling cavity is being j
filled.
1 4
H.
Valves: MO 8716A and MO 8716B Category: B Class: 2 1
n
\\
w 1
Function: These normally open valves cross-connect the discharge of the RRR pumps to ensure injection flow into all four RCS cold legs.
Test Requirement: Exercise for operability every 3 months.
Revision 1 (April 1988)
. ', <L. w : a.. ',.* c-L s.. -.-,s s,...a -.. ~. s ~. ~
sid ~
'el
- h ~*. a s- " s-s i --~~~
" ~ ^----"ar*"=f " *i' 5
~.
1 I
l t
I TABLE 4.1-2 Sheet 12 of 29 Nj?
j 1.I.E.
'i Basis for
Conclusion:
Failure of either of these valves in the closed position would pla e the system outside l
the design bases assumptions for single-active 7
failuta of an RHR pump. Flow could not be I
guaranteed to all four RCS cold less from the 1
I RHR System.
1 1
Alternate Testing: This valve will be full-stroke exercised for l
verification of operability during cold shutdown.
I.
Valve: MO 8703
(
2 l
i*
Category: B Y<
Class: 2
~
i Function: This normally closed valve isolates the RHR flow path to the RCS Loop 2 and 4 hot legs during normal operation.
Test Requiroment: Exercise for 'sperability every 3 months.
Basis for Concluslon.
Failure of this valve in the open position would redirect low head safety injection flow from the safety injection flow path.
i Alternate Testing: This valve will be full-stroke exercised for verification of operability during cold shutdown.
b h
Revision 1 (April 1988)
.i,
.o_.--.
.u.,
.. c,
i TABLE 4.1-2 Sheet 13 of 29 l}
<='
M 206: Safety Iniection System A.
Valves: MO 8801A and MO 8801B Category: B Class: 2 l
i I
Function: These normally closed parallel valves isolate the BIT during normal operation and open on a safety injection j
actuation to provide high head Emergency Core Cooling System flow to the RCS cold legs from the CCPs.
Basis for
Conclusion:
Opening either of these two valves would divert flow from the normal RCS charging and i
RCP seal injection and flush the contents of s,'
the BIT into the RCS.
Isolating the BIT inlet valves (normally open MO 8803A and MO 8803B) is not considered feasible should a safety injection actuation occur while testing, since these valves do not receive a signal to reposition. This condition could result in loss of both trains of high head safety injection and flow less than that assumed in
~
the safety analysis.
Alternate Testing: Full-stroke exercise for verification of operability duri.'s cold shutdown.
Fevision 1 (April 1988)
u p...:.: -.u
..~..a..
....a-..
... ~ -_~:. _ s -.c
-. a....--.._... ~.
t.... w.,d..w'. : a -
'.t
.g L'
A 1
1.']nd TABI.E 4.1-2 Sheet 14 of 29 bk i!lt J
B.
Valves: MO 8806 and MO 8835 If l'
l; Category: B
[:
0 l{
Class: 2 p
Function: These normally open valves isolate the RWST from the l
safety injection pump suction ('MO 8806) and the cold-les 1
j safety injection into the RCS (M0 8835).
l Test Requirement: Exercise for operability every 3 months.
d i
3.
Basis for conclusion: Failure of either valve in the closed position 1
would rander both trains of safety injection pumps inoperable.
Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown.
C.
Valves: MO 8808A, MO 8808B, MO 8803C, MO 8808D x
Category: B e
Class: 1
(
l L.
)
Function: These normally open valves provide isolation for the SIS s
aceutuulators. The valves are also designed to open on f!
receipt of a safety injection signal.
.1 Test Requirement:
Exercise for operability every 3 months.
I 4
l l
I l
l l.
i f
.)
l I
Revision 1 (April 1988)
.L..... i.. u : ~:...a. -..
.:w. w 1
1 l
n TABLE 4.1-2 Sheet 15 of 29 30 7, -
Basis for
Conclusion:
These valves are passive in that, under normal operating conditions, they are open and remain open in performance of their safety function.
The valves have been included in the IST program for testing due to their critical location in a safety-related system and the imposed administrative requirements which 4
require Plant shutdown for failure of one of these valves in a closed position.
Alternate Testing:
Exercise for verification of operability during cold shutdown.
j D.
Valves: MO 8813 and MO 8814 Category: B Class: 2 Function: These normally open series valves isolate the safety injection pump miniflow return flow path to the RWST.
s Basis for
Conclusion:
Failure of either valve in a closed position or safety injection actuation while closed would render the safety injection pumps inoperable. A minimum flow rate through the pumps is required to ensure pump cooling. The miniflow flow path guarantees this minimum flow during the safety injection initiation.
Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown.
Revision 1 (April 1988)
u..
1;._.i
. u, C s :
....._...m / b _
.a :..
- l..'_s Q 3 d p,
!'~
c U ;_.,.
, 0 :. f._.:. -
1 I,
l 31 TABLE 4.1-2 Sheet 16 of 29 I
G l,
E.
Valve: 8815 1
Category: C j
i I
i Class: 1 ti a
Li Function: This check valve prevents backflow from the RCS cold legs U
into the BIT during norinal operation and allows CCP high head injection via the BIT during a safety injection.
i Test Requirement: Exercise for operability every 3 months, d
Basis for
Conclusion:
Exercising of this valve would require injec-tion of the BIT into the RCS.
At normal RCS l
pressure, check valve design flow cannot be achieved.
'h
l' l:
Alternate Testing: This valve will be full-stroke exercised for l
l.
verification of operability during cold shutdown.
F.
Valves: 8819A, 8819B, 8819C, 8819D
(
h' l,
Category: AC I:
p*
l Class:
1 s
l
, Function: Each of these check valves prevents backflow from its
~[
respective RCS loop cold leg and allows flow from the discharge of the safety injection pumps during RCS cold-leg injection and recirculation.
Test Requirement: Exercise for operabi,lity every 3 months.
.s 0
6 Revision 1 (April 1988)
c m_
c_ >
.... i. :...
j 2 4.....,, '.. a:.u 3
l s
a TABLE 4.1-2 Sheet 17 of 29 62
/
hY,)
a V
~
Basis for
Conclusion:
During power operation, the safety injection pumps cannot overcome RCS pressure to achieve check valve design flow.
t Alternate Testing: These valves will be full-stroke exercised for
~
4 t'
verification of operability during cold shutdown.
G.
Valves: 8905A, 8905B, 8905C, 8905D Category: AC Class: 1
'2 Function: Each of these check valves prevent backflow from its l
respective RCS loop hot les and allows flow from the dis-charge of the safety injection pumps during RCS hot-les recirculation.
=
1 Test Requirement:
Exercise for operability every 3 months.
/
Basis for conclusion:
During power operation, the safety injection pumps cannot overcome RCS pressure to achieve check valve design flow.
\\1 ternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown.
h Valves: 8922A and 8922B Category: C Class: 2 4
Revision 1 (A'pril 1988)
q
.$ S e. a i : _.__, '_.__ _.-. _ -
.. _..._. _;. A...,, :n d,,, y
,, d _,;.,,,;;,,,;h;,a ',;,,,,p
...m._,
i I
i j ((l TABLE 4.1-2 Sheet 18 of 29 I- -
f Function: Check valves 8922A and 8922B are on the discharge of the j
safety injection pumps downstream of the recirculation i
return to the RWST and prevent backflow through the respective pump.
i j
Test Requirement:
Exercise for operability every 3 months.
Basis for
Conclusion:
The safety injection pumps cannot overcome RCS pressure during powe.' operation and, as a result, check valve design'cannot be-achieved, Alternate Testing: Valves 8922A and 8922B will be full-stroke i
exercised for verification of operability during cold shutdown.
I.
Valves; 8956A, 8955B, 8956C, and 8956D
< : }"
'(./
Category: AC Class: 1 Function:
These normally closed check valves prevent backflow from the RCS into the accumulators during normal operation, i
Test Requirement:
Exercise for operability every 3 months.
Basis for
Conclusion:
During normal operation, the accumulator cannot overcome RCS pressure. Full-stroke I
testing is not feasible during cold shutdowns i
due to limited Plant conditions for testing which require dischargics the accumulators into the open reactor vessel during refueling.
s
)
(.'
ll Revision 1 (April 1988) l l
C :. L..
s' z M.sa. t:
-.w.
.... a..
..:....... :,a..
s.
- a..
J. u:..u.a sj P
r.i w
a*
TABLE 4,1-2 Sheet 19 of 29 10 r.
f Relief Request: These valves will be full-stroke exercised during f
refueling outages when the reactor pressure vessel l
is open.
I f
H 207: Containment Spray System
]
a l
d A.
Valves: CS 028 and CS 029 (10-HCB-9)
O v
2, 4
Category: C i
1 t
l Class: 2 i
i Function: These check valves prevent backflow of air from the Containment atmosphere through the Containment spray ring header.
\\
Test Requirement: Extercise for operability every 3 months.
Basis for
Conclusion:
These valves do not have provision for testing under nomal conditions. Exercising the valves would require injection of the test medium into the Containment through the spray nozzles with no means available for verifica-4, tion of flow. Equipment damage and require-monts for extensive cleanup of the Containment would result.
l Relief Request: During refueling outage, these valves will be cartially disassembled and the d.4.se will be manually moved through a full stroke.
I i
Revision 1 (April 1988)
c
.... k.s.xus4-:n.1,*:-
..-........z.h.;,..-.....
- w. w.. a.
.l... c ~..
a.
I l
n Of BBLE 4.1-2 Sheet 20 of 29 j
?+Q-
?
l
)
M 208: Main Steam System i
h' A.
Valves: CV 2210, CV 2230, CV 2250, and CV 2270 i
Category: B i
class: 2 i
.I Function: These valves prevent reaching the safety valve setpoint during transients and dissipate reactor decay heat to the 1
atmosphere if the main condenser i,s not available.
l Test Requirement:
Exercise for operability every 3 months.
4 Basis for
Conclusion:
Testing these valves every 3 months increases
- O the normal number of times each valve opens against a differential pressure, thus deteriorating the valve seat and increasing the likelihood of causing leakage.
l Alternate Testing: These valves will be full-stroke exercised during cold shutdown.
(.
B.
Valves: CV 2216. CV 2236, CV 2256. CV 2276 4
Category: BC i
Class:
2 Function: These valvos provide main steam isolation in each of the respective mein steam headers.
Test Requirement: Exercise for operability every 3 months.
.)
w 4
Revision 1 (April 1988)
. ;..a
.xx.
.w
..n ;h.-
a... -a..
.~e....~..
,..] ~
1..., 2.
~
TABLE 4.1-2 Sheet 21 of 29 Ifh
~415 i
Basis for
Conclusion:
Shutting of one of these valves during
~ ~
fu!.1-power operation would result in a i
transient which would lead to a reactor trip and/or a steam dump to atmosphere. Repeated l
closure of these valves at full power will i
j reduce their reliability. Failure of a valve 1) in the closed position would remove its respective steam generator from operation.
Alternate Testing: These valves will ba exercised for verification of operability while in startup or hot standby during each reactor shutdown or subsequent T
startup, except that this test need not be J
' performed more often than once per 92 days.
Operability will be demonstrated by closure within 5 seconds on a closure activation signal.
s
-s C.
Valves: MS 2001, MS 2002 MS 2003, and MS 2004 (28-EBB-1)
I!;
Category: C i
Class:
2 Function: These check valves perform an accident-related function in that they are required to close in the event of a steam line break in Containment in order to prevent blowing down of more than one steam generator to Containnent.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
During normal operation, the main steam pressure cannot be overcome, and as a result the valves cannot be exercised.
Revision 1 (April 1988)
~,
,,M,'figa.,,1,d,g 3,d hp
.,... 4....'. _%,.z..., _ ; ;. 2. a.u.. n v.', u na.2,
..;. L,....,
- j
~
! ^
-i 01 TABLE 4.1-2 Sheet 22 of 29 (h
L Alternate Testing: These valves will be full-stroke exercised for a
j verification of operability during recovery from S
cold shutdown.
^i M 213: Main and Auxiliary Feedwater System t
's A.
Valves: W 2005, W 2006, W 2007, W 2f,08 (2-CCC-CK); W 2009,
- ^
' O W 2010, W 2011, W 2012 (3-DBE-3); W 2013. W 2014, W 2015, W 2016 (3-EBE-3); W 2033 and W 2034.(6-DBD-5)
Category: C Class: 2 and ANSI B31.1 i
Function: These check valves prevent backflow from the main feed lines to the AW System during normal operation.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
These valves cannot be exercised during power i operation without thermal shocking of the feed system nozzles.
d Alternate Testing These valves will be full-stroke exercised during
.,j cold shutdown.
i B.
Valves: FW 2017, FW 2018, W 2019 and W 2020 (14-EBE-3)
^
- i Category: C Class: 2 Function: These check valves prevent backflow from the steam
[
generators into the main feed system.
i' Revision 1 (April 1988)
, - - - - _ +
y g7 yw-,,--
e-
.n.\\w.'
. a. i-
.c.w.........
.. ~ _
.a.,
2.'
o
")
4 TABLE 4.1-2 Sheet 23 of 29 15 2 i
,g
-s a 1 y
i; 5
t Test Requirement: Exercise for operability every 3 months.
sf 1
Basis for
Conclusion:
Shutting of one of these valves during 4
l full-power operation would result in a transient rhich could lead to a reactor trip.
'1 Repeated closure of these valves at full power will reduce their reliability.
l Alternate Testing: This valve will be full-stroke exercised during
}
cold shutdown.
M 215: Component Coolina Water System
-i A.
Valves: MO 3290, MO 3291, MO 3292, MO 3294, MO 3296, MO 3300, MO 3320, MO 3346
(
Category: B Class:
2 (MO 3290, MO 3291, MO 3292, MO 3346) and ANSI B31.1 i
(MO 3?94, MO 3296, MO 3300, MO 3320)
Function: These normally open valves are on the supply and return lines of the CCW supply to. Containment and the RCPs.
Test Requirement: Exercise for operability every 3 months.
i "i
U Basis for
Conclusion:
Failure of one of these valves in the closed position would result in loss of cooling watee 4
to the RCPs.
1 l
Alternate Testing: These valves will be full-stroke exercised for verification of operability at cold shutdown.
Revision 1 (April 1988)
Y...~.a. :..:w.xm.a.- ui u,
l.-
4.M a.d.;A. L:ly:: :C.:thidS'.iO'
.u,
-x-n m a
?1 6
q
)
E er i
[')
TABLE 4.1-2 Sheet 24 of 29 4
4 y
l<'d.
,l B.
Valves: MO 3295 and MO 3319 d
Category: B I
Class:
'"1
.1 Function: These are the inlet and outlet isolation valves on the letdown and seal water heat exchangers. The valves are normally open and close on receipt of a Containment isolation signal.
4 4
.i Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
Failure of either of these valves in the closed position would result in loss of cooling water to the RCS letdown and the RCS
, ')
pump seal water heat exchangers requiring reactor shutdown.
Alternate Testing: These valves will be full-stroke exercised for verification of operability during cold shutdown.
C.
Valves: CS 2001, CS 2002 (1-CBD-26); CS 2003, GS 2004 (1/2-HBD-65)
Category: C 4
Class: ANSI B31.1 Function: CS 2001 and CS 2 are the normal Seismic Category II nitrogen supply eneck valves to the CCW System surge tanks. CS 2003 and CS 2004 are the emergency backup Seismic Category I nitrogen supply check valves which are normally closed.
]
Test Requirement: Exercise for operability every 3 months.
Revision 1
- (April 1988)
-v-+
e e
e w
w n.-e c
-vw
,,=
~,
...__ _,., i gl '
.z :
.m.
._m..
.w:,
{
3 J
~
TABLE 4.1-2 Sheet 25 of 29 i
(114 t'
Basis for
Conclusion:
Testing of these valves requires lowering CCW surge tank pressure below the emergency backup supply pressure setpoints to demonstrate i
l isolation of the normal supply check valves j
j and opening of the emergency backup supply l
Changes in sys.am pressure j
affect the flow to various critical operating loads which could af fect the operability of the inservice equipment vital to the operation of the Plant.
Alternate Testing: These valves will be full-stroke exercised for fh verification of operability during cold shutdown.
D.
Valves: CC 2035, CC 2036, CC 2046, and CC 2047 i-(' ~'
Category: C i
Class: ANSI B31.1 Function: These normally open valves are required to isolate in the event of a RCP thermal barrier failure to assure continued operation of the associated CCW train. These valves are required to close to prevent overpressurization of the i
other portions of the CCW System.
Test Requirement:
Exercise for operability every 3 months.
f f
Revision 1 (April 1988)
b.m_m _..W r.-
.S_;i_:. : w..u bn n.LEAM psi.;.
2._
.. _ __. _. _ u.;.
t i
TABLE 4.1-2 Sheet 26 of 29 l
Basis for
Conclusion:
Exercising these valves during normal Plant operation cannot be performed remotely. RCPs taust be shut down and test equipment connected to local vents and drains to demonstrate reverse flow check valve isolation. These test locations are inside.the bioshield of the reactor containment.
Relief Request: These valves will be full-stroke exercised for verification of operability during refueling outages.
E.
Valves: MO 3298A, MO 1298B, MO 3298C, and MO 3298D b
Category: B Class: ANSI B31.1 g
Function: These valves are required to isolate in conjunction with the check valved in Item D above in the event of a RCP thermal barrier f ailure. These valves are required to close to prevent overpeessurization of the other portions of the CCW System.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
Failure of these valves in the closed position during normal Plant operation with the RCPs running renders themal barrier cooling inoperable. Subsequent failure of seal injection to the pump could lead to rapid seal degradation in the RCP.
Alternate Testing: These valves will be full-stroke exercised for
~}
verification of operability during cold shutdown.
Revision 1 (April 1988)
- d 11 '.';.. - : :.... Y. '
a. *
...L.
~.ua
.L.
... ~..
y e
i TABLE 4.1-2 Sheet 27 of 29 4
- fcs, l
',(
,a n
M 218: Service Water A.
Valves:
SW 029 and SW 030 Category: B 4
4 4
i Class: ANSI B31.1 i
i Function: These manual valves supply service water cooling to the CCW heat exchangers. During a loss of river intake structure, they are closed to allow use of the Seismic Category II circulating water system from the cooling tower. The CCW heat exchangers provide the prir. ry
]
cooling to critical components cooled by the CCW System during normal operation.
I\\
~
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
Loss of cooling to the CCW heat exchanger from the Seismic Category I Service Water System 8
due to a failure of the valve during the exercise test would require use of the Seismic Category II circulating water system backup from the cooling tower or else the applicable ECCS train would be lost.
Alternate, Testing: These valves will be full-stroke exercised.for verification of operability during cold shutdown.
/
i Revision 1 (April 1988)
'~ ^ ^
..as L va. :.a...~-.. c.. a.u:. u.
4, a-c. ~~
a.
.. -..=.. u. O..w..,...c.La L u.uL. M.X.L:h w.h?l2kyh:yaj:
i i
I i
O i {l TABLE 4.1-2 Sheet 28 of 29 1
l
}
M 223: Instrument Air System A.
Valves: CV 4471 and IA 2001 (2-HBE-8) da t
Category: A and AC, respectively Class:
2 Function: These normally open series Containment isolation valves are the instrument air supply to pneumatic valves and instrumentation inside containment. The valves close on receipt of a containment isolation signal.
Test Requirement: Exercise for operability every 3 months.
Basis for
Conclusion:
Failure of either of the instrument air valves in a closed position removes the air supply to the Containment air-operated valves and pneumatic instrumentation. Valve 2-HBE-8 can only be verified shut during leak testing'at' refueling outages.
Relief Request: CV 4471 will be full-stroke exercised during refuel-ing. Check valve 2-HBE-8 will be full-stroke exer-cised for verification of operability during local leak rate testing per 10 CFR 50, Appendix J.
i j
l Revision 1 (April 1988)
,S.t :-.. n,a _'. '.. :.c.. '..~ - 2.
em.'; 4
..... m;.
2
.:., % e. _.
}
4
.-j TABLE 4.1-2 Sheet 29 of 29 10 a, dec..%
C v
.J
,4-l U?43: Containment Ventilation System I'
A.
Valves: CV 10001, MO 10C02, MO 10003, CV 10004 Category: A 3
Class: 2
.i Function: These valves are the Containment isolation valves for the main Containment purge system.
Test Requirement: Exercise for cperability every 3 months.
Basis for
Conclusion:
PCE has connitted to maintaining these valves in the closed position during Modes 1, 2, 3, and 4 in response to an NRC concern over Containssnt purging during normal operation.
5 Alternate Testing: These valves will be full-stroke exercised during cold shutdown.
r i
t i
Revision 1 (April 1988)
l e
a :.C.i'Ja
..). ; - _..
a..
..-: a::#e v:.r.
. :._,...k
.c 3
9
~
??
b 7
~
^
TABLE 4.1-3 Sheet 1 of 4 i
f:5 j
Y:f;)
PART-STROKE EXERCISED VALVES The following Category A, B, and C active valvos, where only limited t
operation is practical curing Plant operation, will be part-stroke exercised during Plant operations and full-stroke exercised during cold
]
shutdowns as por Paragraphs IWV 3412 and 3522.
5 i
1 M 202: Chemical and Volure Control System
'l 1
1 A.
Valves: 8481A and 8481B l
Category: C a
l'I Class: 2 t
runction: Each of these check valves is on the discharge of a CCP and prevents backflow.
i Test Requirement: Exercise for operability every 3 months.
~
Basis for
Conclusion:
During power operaticn, the charging flow path cannot accommodate full flow except through i
i
[
the BIT khich would require injection of 3
boric acid into the RCS, causing a power transient that could result in a treactor trip.
Alternate Testing: These valves will be part-stroke exercised at power every 3 months and full-stroke exercised at cold shutdown.
l N 205: ResidJal Heat Removal System h
A.
Valves: 8730A and 8730B Category: C Revision 1 (April 1988)
+. - _,.
,-,....-..,,2.-.....__.~__-,
' 2dQLx.M : 2,0;,..Q'
- w.':,/.a.. w, x. : = c:
1 un.~. % < :'L O + /.L a 2; J 'ii l'. '
, u a. ~-
i
'.l TABLE 4.1-3 Sheet 2 of 4
.a J.'?\\;)
e Class: 2 i
Function: These check valves are on the discharge of the RHR pumps j
and prevent backflow thecush their respective pump.
t
).
Test Requirement: Exercise for op6cability every 3 months.
i i
Basis for
Conclusion:
During power operation, the RRR pumps cannot overcome RCS pressure to achieve check valve design flow. The only alternate flow path which can accommodate full flow is on encircu-lation to the RWST. This flow path is i
unacceptable because it would require repositioning of the F.WST return isolation valve, 8735 (normally locked closed), which would render the RHR injuction system inoperable, Alternate Testing: Check valves 8730A and 8730B will be part-stroke exercised on miniflow during power operation and, full-stroke exercised during cold shutdown.
M 206: Safety Injection System A.
Valves: 8926 Category: C I
Class: 2 Function: Check valve 8926 is between the safety injection pumps suction and the RWST and preventr. backflow into.the RWST.
s Test Requirement:
Exercise for operability every 3 months, l
i Revision 1 (April 1988)
't w.
.'r.
1.2.
,a 2 n.x na.,
.~.
....w..
....n.
4 a
w 4
4 1
s TABLE 4.1-3 Sheet 3 of 4 e
,s D.'A
%./
3 da 1
Basis for
Conclusion:
The safety injection pumps cannot overcome RCS
.f pressure during power operation and, as a reruit, full flow cannot be accommodated.
I Alternato Testing: Check valve 8926 will be part-ptroke exercised s
during power operation and ful%- stroke exercised for verification of operability during cold
]
shutdown.
4 M 207: Containment Spray System
.i 3
i A.
Valves: CS 2001 and CS 2001 (14-HCB-14) l[,
I i
Category: C Class: 2 Function: These cheek valves prevent backflow into the RWST from the i
Containment spray suction header.
Test Requirement: Exercise for operability every 3 months.
i Basis for
Conclusion:
Full-stroke exercising of those valves during power operation would require injection of the test medium into the Containment in order to achieve design flow. Equipment damage and requirements for extensive cleanup of the Containment would result. The alternate test i
method requires initiating check valvo design flow using the RHR pump while discharging into the refueling cavity for flood-up in preparation for refueling.
Revision 1 (April 1988)
s.u =ut
,._::1.:.
.%, : ~. =..
..u : h:._ &
i:. 0.t::d n:U$hi M - lth.Wl?lh5 : Of... ~n :.'.
. !p,, ly.
i i
l TABLE 4.1-3 Sheet 4 of 4
(,).
's j-3
'l Relief Request: These valves will be part.-stroked every 3 months and full-stroke exercised during refueling outages.
i M 218: Service Water System i
A.
?
4 Category: B Class: ANSI B31.1 Function: These valves on the outlet of the CCW heat exchangers are required to be closed during a loss of river intake structure in order to valve in the Seismic Category II 3
circulating water system from the cooling tower.
Test Requirement:
Exercise for operability every 3 months.
Basis for
Conclusion:
Loss of cooling to the CCW heat exchanger due to a failure of the valve during the exercise !
test would require use of the Seismic Cate-gory II circulating water system backup from j
the cooling tower or loss of the ECCS train.
Alternate Testing: These valves will be part-stroked every 3 months and full-stroke exercised during cold shutdowns.
s 0
Revision 1 (April 1988)
A. ; r_... :.' ; :s k...
'..u~' Q )*.-.
s
[* ' M. f.. -. ' ';:=.z ; i ?.i:
.. =. :-! '
i
.w.
.v+
.{'
TABLE 4.1-4 m
of b.
ADDITIONAL RELIEF REQUESTS i-
)
M 208: Main Steam System i
i i
A.
Valves: MS 220, MS 221, MS 222, MS 223, MS 224, MS 225, MS 226, and MS 227 i
Category: C i
Class: 2 I
Function: These normally open check valves are required to close to iso-l late the normal air supply to the steam supply valves (CV 1451, CV 1452, CV 1453, and CV 1454) for the turbine-driven auxiliary feedwater pump and allow the backup air supply accunulators to provide air to these valves. This festure is only required during a loss of the normal Seismic Category II instrument air O
supply system to the pump steam supply valves to assure ac l
independence.
I Test Requirement:
Exercise each valve for operability every 3 months.
Basis for conclusion: These alves are configured with two valves in j
series on each of the four normal ali supply lines. The piping configuration has no test l
connections between check valves to allow individual valve testing, k
t Relief Request: Operational readiness will be shown by isolating the normal instrument air supply to each steam supply valve t
j and performing the periodic operating test on the l
steam-driven AFW pump using the backup accumulator air j
rupply. This test will demonstrate operability of the series configuration of two check valves in each air j
supply line. Only one steam supply valve is required to be open to assure pump operability.
Revision 1 (April 1988)
,