ML20058E528
| ML20058E528 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 10/25/1990 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20058E525 | List: |
| References | |
| 8.I.1.1, NUDOCS 9011070208 | |
| Download: ML20058E528 (174) | |
Text
_
BOSTON EDISON PILGRIM NUCLEAR POWER STATION Procedure No. 8.I.1.1 INSERVICE PUMP AND VALVE TESTING PROGRAM
'1 IN FORM AT.2 i ONLY I
Uso restricted to reference s
-(a]>,
Approved SW wvT +.iTW:N 4 r. 2. <
le/11)b'
'QAD'Haniger Date Approved b
ab&
\\0[E5f90
' Plant Manager i D&te '
Sifety Review:
Reques:ed/Not Required 8.I.1.1 Rev. 1
'9011070208 901025
{DR ADOCK 05000293 PDC
REVISION LOG Pages 1
Revision Djtta Affected Descriotion 1
i
'l 10/90 5
Added NRC publication " Minutes of the Public Heetings on Generic Letter 89-04" to L.
Reference section.
Various Revised the following Relief Requests to i
E provide additional clarity and resolve NRC questions.(Ref. BECo Letter to NRC L
l'
- 2.90.127 for summary-of changes):
RP-1, l
RP-3, RP-5, RP-7, RP-9, RV-03, RV-09, RV-ll, RV-16, RV-18, RV-20. RV-21. RV-23, RV-24 RV-25, RV-27, RV-29 RV-30 5,16,30 Removed HPCI GSC pump from this program, retracted Relief Request RP-10, and added i.
ERM 90-578 to Developmental Reference.
l; Clarified CS-16 to be consistent with this.
change.
34,35 Added discussion on check valve disassembly L'
practice to Section 6.'1[4), Heasurement of Test Quantities.
Listed the check valves i
within the disassembly program and their-category.
43 Provided additional. post maintenance test guidance when performing (PH program)~ valve greasing applications.
.Added ST open direction requirement for Containment ~Atm.. Control valves, s
136 Changed CK-1001-515 leakage test frequency from R0-to 2Y.-
A 148,171 Corrected Actuator Type typo errors from EP 1
to EX on' Valve Tables.
120,134,135, Updated PNPS test procedure number on Valve 144 Tables.
q
'Various Removed
- from Valve Table procedure
~
numbers to indicate required procedure
..f' revision for program implementation is complete.
0=
All Upgrade IST Program to increase cot.)onent scope and to incorporate the requirements-of Generic Letter 89-04.
This revision uses information'provided in PNPS 8.I.1 and SI-PG.4040.
8 I.l.1 Rev. 1 Page 2 of 172
+
f
}
TABLE OF CONTENTS PAQf 1.0 PURPOSE 4
2.0 DISCUSSION 4
3.0 DEVELOPMENTAL REFERENCES 5
4.0 COMPLIANCE 5
5.0?
' INSERVICE PUMP TESTING 6
5.1 GENERAL INFORMATION 6
5.2 POST-MAINTENANCE TESTING 9
5.3 HYDRAULIC CIRCUITS 13 5.4 RELIEF REQUESTS 18 5.5 PUMP PROGRAM TABLE 29 6.0
' INSERVICE VALVE TESTING 31 6.1 GENERAL-INFORMATION 31 6.2 POST-MAINTENANCE TESTING 41 6.3 COLD SHUTDOWN JUSTIFICATIONS 51 6.4 RELIEF REQUESTS 68
'6.5 VALVE PROGRAM TABLE 101 L
t 8.I.1.1 Rev. 1 Page 3 of 172
1.0 11lRPMI This procedure emcompasses and controls the PNPS Inservice Test (IST)
Program.
It identifies the scope of components-(pumps and -valves) and testing requirements for compliance with 10CFR50.55a(g), Inservice Inspection Requirements, and Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Program. This procedure will be utilized for the IST Program submittal to satisfy 10CFR50.55a(g)(4)(ii) and also identifies impractical code requirements per 10CFR50.55a(g)(5).
This procedure also provides post-maintenance guidelines to aid station personnel when determining test requirements for plant safety-related components.
2.0 DISCUSSION This procedure applies to Class 1, 2, 3 and safety significant pumps and valves for conformance with ASME Boiler and Pressure Vessel Code,Section XI (1980 Edition through Winter 1980 Addenda).
The procedure 1
details.the following items:
compliance requirements, post-maintenance testing guidelines, pump hydraulic circuits, valve cold shutdown justifications, relief requests and components (pumps and. valves) tested.
This procedure provides a cross-reference between a component test i
requirement and a station procedure implementing the test. Additional
- information is provided within the component tested listing:
safety j
class, category, test frequency, pump test parameters, valve test 1
requirements, relief requests, valve cold shutdown justifications and remarks. Newly incorporated component / test requirements will have implementing procedures identified for future incorporation.
All newly
- i identified component / test requirements shall'be initially tested during the next scheduled frequency (i.e., quarterly, cold shutdown, 1
refueling, and two year interval) following procedure approval date.
These. newly incorporated component / test requirements will be identified by-an-(*) asterisk next to the implementing procedure.
When using (*),
j procedures for post-maintenance testing the current approved procedure should be reviewed for applicability'(i~e., test requirement or component incorporated).
The inservice tests identified in this program will verify the operational-readiness of pumps and valves whose functions are required
)
to mitigate the consequences of an accident or to bring the reactor to a cold shutdown condition or maintain the reactor in a safe shutdown condition. Additional components considered to have a safety significant function may be incorporated. The ISI safety, classification of each pump and valve was determined in accordance with Regulatory Guide -1.26.
Safety related components not c"ssified as Group A, B or C per Regulatory Guide 1.26 are included non-classed (NC).
Additionally, all containment penetrations shall be classifed as ISI Class 1 or Class 2.
8.I.1.1 Rev. 1 Page 4 of 172 s
.2.0 DISCUSSION (Continued)
PNPS 8.I.1, Administration of Inservice Pump and Valve Testing, covers the administrative requirements for performance, compliance, evaluation and followup action for preservice and inservice testing in accordance with the ASME Code,Section XI, Subsections INP and INV.
PNPS.8.I.1 also details the following items:
Responsibilities Definitions, Test Requirements, Compliance Requirements. Evaluation and Disposition, Post-Maintenance Testing, and Administration.
3.0 DEVELOPMENTAL REFERENCES
-[1] -10CFR50.55a(g), Inservice Inspection Requirements
[2]
10CFR50.55a(b), Code and Standards, Reference Applicability
[3] ~ 10CFR, Appendix J. Primary Reactor Containment Leakage Testing
[4] ASME Boiler'and Pressure Vessel Code, Section.XI (Rules for Inservice Inspection of Nuclear Power Plant Components) 1980 Edition through Hinter 1980 Addenda, Subsections IHA, IHV and IHP
[5] Division 1 (Draft) Regulatory Guide and Value/ Impact Statement,
" Identification of Valves For Inclusion in Inservice Test Programs"
[6] NRC Staff Guidance for Preparing Pump and Valve Testing Programs
-and. associated Relief Request, November 1981
[7] Standard Review Plan 3.9.6, " Inservice Testing of Pumps and Valves"
[8] PNPS_ Inservice Testing Program for Pumps and Valves Submittal Revision IB a
[9] NRC Generic Letter 87-06, " Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves"
-[10] NRC' Generic Letter 89-04, " Guidance on Developing Acceptable Inservice Testing Programs" (11] NRC' Publication: " Minutes of the Public Meetings on Generic Letter 89-04", dated October 25, 1989
[12] ESR Response Memo ERM-90-578
[13] PNPS 8.I.1, " Administration of Inservice Pump and Valve Testing" g
(14] PNPS_ Q-List 4.0 COMPLIANCE The Pilgrim Nuclear Power Station Inservice Pump and Valve Testing Program will be in effect through the second 120-month inspection interval (December 7, 1992) and will be updated in accordance with the requirements of 10CFR50.55a(g).
8.I.1.1 Rev. 1 Page 5 of 172
)
t 4.0 COMPLIANCE (Continued)
This procedure outlines-the Inservice Testing Program based on the requirements of Section XI of ASME Boiler and Pressure Vessel Code, 1980 Edition through Hinter 1980 Addenda..
If this procedure (revised Inservice Testing Program for. the site) conflicts with PNPS Tech Specs, a Tech Spec amendment shall be t
submitted.to conform the Tech Spec'to this procedure in accordance with
[10CFR50.5Sa(g)(5)(ii)]. Until approval of the Tech Spec amendment, the most limiting requirement shall be met.
5.0 INSERVICE PUMP TESTING
-5.1 GENERAL INFORMATION
[13-Applicable Code This Inservice Testing Program for ISI Class 1, 2, 3 and NC Pumps meets the requirements of Subsection IHP of Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Hinter 1980 Addenda. Hhere these requirements are determined to be impractical, specific requests for relief have been written and included-in Section 5.4.
[2] Pump Program Table Description The table in Section 5.5 lists all pumps included in the Pilgrim
' Nuclear Power Station IST. Program.
This program defines pumps as t
mechanical devices used to move liquid and addresses centrifigal and positive displacement pumps per INP-1100..The data contained in the table identifies all pumps subject to inservice testing, the inservice test quantities, the inservice testing interval and any applicable remarks.
The column headings of the table are listed and explained below:
i (a) SYSTEM: System Title 11 J.-
(b) PUMP NUMBER:
Pump Identification Number (c). Ct. ASS:
ISI Classification (Class 1, 2, 3 or-NC) 1
.d)' P110:
PNPS drawing number y
(e): CQQE: Coordinate location on the P&ID I
-(f) SPEED. INLET PRES. DIFF PRES. FLOHRATE. VIBRATION. BEARING L
LUBRICANT and BEARING TEMP:- Inservice Test Quantities to be measured in accordance with: Table IHP-3100-1 (g) TEST INTERVAL: The frequency of IST as prescribed in IHP-3400
.l l
8.I.1.1 Rev. 1 Page 6 of 172
5.1 GENERAL INFORMATION.(Continued)
[3]
" Inservice Test Quantities" Columns PUMP SPEED. INLET (SUCTION) PRESSURE. DIFFERENTIAL PRESSURE (dP).
FLOHRATE. VIBRATION. BEARING TEMPERATURE AND LUBRICANT LEVEL OR L
PRESSURE: When the symbol ~"Y" appears in a particular measured L
parameter column, that quantity will be measured during inservice i
testing in accordance with Subsection IHP.
Requests for relief r
are identified with the letters RP" under the measured parameter column in the test table.
The requests for relief are-included in H
Section 5.4.
[4] Measurement of Inservice Test Quantities (a) Speed:
Per IHP-4400, shaft measurements are not applicable i
(NA) for pumps coupled to synchronous or induction type I
drivers.
For_ variable speed pumps, the pump speed shall be set at the reference speed per INP-3100.
(b) Inlet Pressure:
For submerged pumps, inlet pressure will be calculated (using appropriate correction factors) from a measured tank or basin level.
Since this method does not comply with the requirements of IHP-4200, relief requests RP-3 and RP-4 have been prepared. All other. inlet pressure measurements will be taken using pressure instruments at or near the pump inlet.
(c) Differential Pressure:
Differential pressure measurements 4
i l
will be calculated from inlet and discharge pressure h
measurements or by direct differential pressure measurement.
(d) Flowrate:
Pump discharge flowrate shall be measured.
(e)_. Vibration:
Pump vibration will be measured as.close as E
possible to the_ inboard bearing in a plane approximately l
perpendiculer to the rotating shaft, in a horizontal or vertical direction that has the largest deflection for that particular' pump. At least one displacement and one velocity measurement will be.taken with one of the instruments 1
referenced in IHP-4520 with exception if'a reading is not L
applicable for a pump..
(f) flearina Temperature:
Pump bearing temperature (s) will not be measured (See RP-2).
N (g) Bearina-Lubricant: As specified in Table INP-3100-1, the pump bearing lubricant level or pressure will be observed i
during inservice testing.
[5] Allowable Ranges of Test Quantities The allowable ranges specified in table IHP-3100-2 will be used L
for differential pressure, flow and vibration measurements except as discussed.
Should a measured test quantity fall outside the allowable range, the possibility of defining an expanded allowable range, per ASME Code Interpretatirn XI-1-79-19, will be investigated for operability.
8.I.1.1 Rev. 1 Page 7 of 172
' 5.1 GENERAL INFORMATION (Continued) r
['6] Corrective Action'
-j The operational' readiness of a pump shall be determined by-i comparing surveillance procedure test results to the established acceptable, alert and required action ranges.
Analysis of pump surveillance procedure test data shall be completed within four (4) workdays (Relief Request RP-8).
(a)
If deviations fall within the alert range, the frequency of testing shall be doubled until the cause of the deviation is determined and the condition corrected or an evaluation is performed and new reference values are established.
(b)
If deviations fall within the required action range, the pump shall immediately be declared inoperative and not returned to service 'until the cause of the deviation has been determined and the condition corrected or an evaluation is performed and s
new reference values are established.
(c) Corrective action shall be either replacement,- repair or an analysis to demonstrate that the condition does not irpair j
pump operability and that the pump will still fulfill its p
function.
When an analysis is considered necessary, 2 new i"
set of reference values shall. be established after analysis completion.
L
[7]
Instrument Accuracy g
lr L
Allowable instrument accuracies are given in table IHP-4110-1.
If t
the accuracies of plant installed instrumentation is not 4
l-acceptable, temporary instruments meeting the acceptable accuracies will be used.
o 1R
[8]
Exempt Safety Related-Pumps The Reactor Recirculation Pumps and the Reci: > Jiation Jet Pumps are exempt from inservice testing. These pumps do~not meet the
~
N"'
scope of IHP-1100 in that they are not required to perform a specific function in shutting down the reactor or mitigating the 4
consequences.of an accident nor are they provided with an emergency power source.
-t
/
8.I.l.1 Rev. 1 Page 8 of 172 i
l
f
'52
. PUMP POST-MAINTENANCE TESTING During the inservice life of a pump, work may be required to restore or maintain the pump performance to within the acceptable ranges.
The IST Program requires each pump to be verified as operationally ready after.
routine servicing, maintenance, repair or replacement.
The verification of operational readiness should be achieved by acceptable performance of a surveillance procedure used to verify test parameters which may have been affected.
The test parameters may be verified by other documented procedures as long as all test conditions or-parameters are complied with, in accordance with Subsection IHP.
. Pump post-maintenance testing guidance is provided using a step-by-step 1
determination process, a work scope guideline and a retest flowpath.
The RS&PD ASME Test Engineer may be consulted for questions or further clarification.
N
[1] Sten-By-Steo Determination (a) Steps as follows (reference Retest Flowpath):
Step 1: Using this procedure, Section 5.5, locate the pump and verify if.any test requirements are applicable.
Step 2: Verify if the work to be performed is identified within work scope guidelines below.
Step 3: All work identified within the work scope guideline as " Repair", " Replacement" or " Maintenance" requires an IST pump retest.
Identify the applicable PNPS Procedure No. on j
the Maintenance Request for retest.
All work identified within the work scope guideline as
" Routine Servicing" requires an IST pump retest QB equivalent documentation.
Identify either the applicable PNPS Procedure
.No. for retest 08 equivalent documentation that will verify the test parameter reference value was not affected (such as changing of oil - documented level.as visible) on the Maintenance Request.
[2] Hork Scone (HS) Guideline (a)- Routine Servicing - Performance of preventive maintenance which'does not require disassembly of the pump or replacement of parts; such as changing oil, flushing the cooling system, adjusting packing, adding packing rings or mechanical seal maintenance.
Exceotion: (1) When routine servicing is performed on a running pump, verification-that monitored parameters do not change may be substituted in place of the PNPS Procedure as. documented on the Maintenance Request.
(2)
When a parameter is verified within the maintenance instruction or prior to operation (i.e., verify acceptable oil level) no retest is required.
(b) Maintenance - Performance of preventive or corrective maintenance which requires disassembly of the pump or replacement of consumable items.
8.I.1.1 Rev. 1 Page 9 of 172
i 5.2 PUMP POST-MAINTENANCE TESTING (Continued)'
(c) Repair.- Performance of welding or grinding on a pump to correct a defect (does not include pump motor).
(d) Replacement - Installation of a new pump, pump part or.a modification to the pump (does not include pump motor)..
[3] Retest Flowcath i
Verify if _ Pump listed No IST Retest STEP 1 this procedure No_-
For Operational
- =
Section 5.5.
Readiness.
l L
i Yes Hork to be performed.
STEP 2 is identified within No HS auideline.
I Yes
. Locate Procedure No. in Section-5.5 of this pro-cedure;(or other.equiva-STEP 3 lent documentation) and identify for retest con-sideration on Maintenance Reauest.
1
'1 8.I.l.1 Rev. 1 Page 10 of 172
5.2 PUMP POST-MAINTENANCE TESTING (Continued)
[4] EXAMPLES:
(a) Salt Service Water Pump B (P-208B) reluires impeller replacement due to excessive wear per Maintenance Request.
a SSH Pump P-208B 1:, -
No retest re-STEP 1 listed on Page 30.
No -------------
quired for operability.
l Yes 4
4 1
Hork scope'to be per-I STEP 2 formed -is identified
No ------------------ J within Guidelines -
replacement.
F_QlE: Replacement of the pump impeller requires both new hydraulic and.
J Yes mechanical parameters to be established.
The retest performance u
pa-ameters shall be
-l PNPS 8.5.3.2: Perform evaluated and accepted STEP'3..
applicable steps of
- as nw reference values.
Section 7.0,.Prereq-uisites, and Section J
8.0. Procedure.
(b) Residual Heat Removal Pump A (P-203A) requires the lubricant reservoir to be filled because level indication is just visible per. Maintenance Request.
i RHR Pump P-203A '.s
.No retest re-STEP 1 listed on Pac;- 30.
No -------------
quired for operability.
l Yes 8
6 l
8 Hork. scope is identi-
. STEP 2 fled within Guide-
No ------------------ J lines - routine ser-vicina.
l l
Yes tLQIE: A Maintenance Request should always be used PNPS No.: 'not re-to document. routine ser-t.
quired - Maintenance vicing retests unless j
STEP 3
-Request package uti-the pump is' required lized to document to be run at its verification of adjusted reference 4
oroner oil level, values prior to measur-t ing the affected L
parameter.
8.I.1.1 Rev. 1 Page 11 of 172
5'.2 PUMP POST-MAINTENANCE TESTING (Continued)
(c) Core Spray Pump A (P-215A) requires the pump mechanical seal replacement per Maintenance Request.
CS Pump P-215A is No retest re-i STEP 1 listed on Page.30..
No -------------
quired for operability.
l Yes l.
4 I
Hork scope'is identi-l STEP 2 fied within Guide-
No------:-----------J lines - maintenance.
HDII: Maintenance of the pump mechanical seal (replace-ment of parts) requires Yes reconfirming previous-reference values, u
.PNPS 8.5.1.1: Perform applicable steps of STEP 3 Section 7.0, Prereq--
.uisites, and Section 8.0. Procedure.
(d).. Reactor Recirculation Pump B (P-201B). requires the motor to be replaced per Maintenance Request.
Rx.Recirc pump P-201B No retest re-STEP 1-is agt listed on.
No quired for Paae 30.
operability.
Yes I
l I
I
~Hork scope is nai STEP 2 within Guideline -
No------------------J NA.
Yys HQII: Maintenance performed on non-safety related pteus r
PNPS No.: Not.
should receive a post-
- Reauired, maintenance test, but they do not require retest in hccordance with Subsection INP (ISTP).
4 8.I.1.1 Rev. 1 Page 12 of 172
HYDRAULIC CIRCUITS d to identify pump test 5.3 Individual hydraulic and mechanicaltified wi The following IST hydraulic circuits are use paths and instrumentation. reference value test quantities are i f installed plant procedure.
MLTE instrumentation may be used in place oinst Measurement, be considered.
requirements are satisfied. differences due to instrument lo Salt Service Hater (SSH) Pumps 5.3.1 Test Frequency ling outage
[1]
SSH Pumps are tested on a quarterly and refue tion and frequency because of system design configura operational requirements.
Hydraulic Test Path Quarterly SSH pumps shall be shutoff (dead) head
[2]
plate speed tested (RP-5) by verifying operation at name to the (a) and that discharge head (ft) is compared established value.
d by Refueling Outage Each pump shall be testeestablishing t Exchanger, Valve for (b)
Then, using the Heat Exchanger Isolati dance with level (RP-4),
current Tech Spec requirements.
shall be recorded, and using suction bay
- d. ?.
d) will be the pump dif ferential pressure (total h j
lue.
f'
~
Instrumentation LI-3831A, LI-3831B (actual
[o]
Inlet Pressure, Pi (ft): measurement from ladder (a)
PI-3802, PI-3807, PI-3812, Discharae Pressure, (psig):
(b)
PI-3817, PI-3822.
FI-6240, FI-6241.
Flowrate, 0 (gpa0:
(c)
CCH) Pumps Reactor Building Closed Cooling Hater (RB 5.3.2 Test frequency fueling outage
[1]
RBCCH pumps are tested on a quarte tion and operational requirements.
l
- 8. I. l.1 Rev. 1 f
Je 13 of 172~- o
1 5.3 HYDRAULIC CIRCUITS E
The following IST hydraulic circuits are used to identify pump test paths and instrumentation.
Individual hydraulic and mechanical reference value test quantities are identified within each pump testing procedure.
M&TE instrumentation may be used in place of installed plant instruments provided that IHV-4000, Methods of Measurement, requirements are satisfied.
The effects of flow losses and elevation differences due to-instrument location must be considered.
5.3.1 Salt Service Hater (SSW) Pumps
[1]
Test Frequency SSH Pumps are tested on a quarterly and refueling outage frequency because of system design configuration and operational requirements.
[2]
Hydraulic Test Path (a) Quarterly - SSH pumps shall be shutoff (dead) head tested (RP-5) by verifying operation at nameplate speed and that discharge head (ft) is compared to the established value.
1 (b) Refueling Outage - Each pump shall be tested by establishing a-flowpath through a RBCCH Heat Exchanger.
Then, using the Heat Exchanger Isolation Valve for throttling, establish a flowrate in accordance with current Tech Spec requirements.
Pump discharge pressure shall be recorded, and using suction bay level (RP-4),
the pump differential pressure (total head) will be calculated and compared to the established value.
-[3]
Instrumentation (a)
Inlet Pressure, Pi (ft):
LI-3831A, LI-3831B (actual measurement from ladder as backup).
-(b) Discharae Pressure, (psig):
PI-3802, PI-3807, PI-3812, PI-3817, PI-3822.
(c)
Flowrate,-Q (gpm):
FI-6240, FI-6241.
5.3.2 Reactor Building Closed Cooling Hater (RBCCH) Pumps
[1]
Test Frequency RBCCH pumps are tested on a quarterly and refueling outage frequency because of system design configuration and operational requirements.
8.I.1.1
'Rev. 1 Page 13 of 172
1.
j 5.3.2-Reactor Building-Closed Cooling Hater (RBCCH) Pumps (Continued)
[2] Hydraulic Test Path' (a) Quarterly - RBCCH pumps shall be shutoff (dead) head tested'(RP-1) by verifying operation at nameplate speed and that discharge head (ft) is compared to the established value.
(b) Refueling Outage - Each pump shall be tested by establishing a flowpath through a RBCCH Heat Exchanger.
Then, using the Heat Exchanger Isolation Valve for throttling, establish a flowrate in accordance with current Tech Spec requirements. Pump discharge and suction pressures shall be recorded.
The differential pressure (total head) will be calculated and compared to the established value.
[3]
Instrumentation (a) 1plet Pressure, Pi (psig):
PI-4056A, PI-4054A, PI-4057A, PI-4006A, PI-4004A, PI-4007A.
-(b) Discharae Pressure, (psig):
PI-4056, PI-4054, PI-4057, PI-4006, PI-4004, PI-4007.
(c) E.lowrate, Q (gpm):
FT-6265, FT-6263.
i 5.3.3 Diesel Oil Transfer (DOT) Pumps
[1] Test Frequency DOT pumps are tested on a quarterly frequency.
[2] Hydraulic Test Path Each pump shall be tested by establishing a flowpath from the storage tank to the day tank.
Then, using the pump discharge
-isolation valve, throttle to a calculated differential pressure. An external clamp on flow meter will measure the flowrate.
[3] Instrumentation (a) Inlet Pressure, Pi (psig):
Test gauges at PI-45002, PI-45003.
(b) Discharae Pressure, (psig):
PI-4510, PI-4511.
.(c) Flowrate, Q (gpm): Test equipment at midpoint of straight piping.
5.3.4 Residual Heat Removal (RHR) Pumps
[1] Test frequency RHR Pumps are tested on a quarterly frequency.
8.I.l.1 Rev. 1 Page 14 of 172
5.3.4 Residual Heat Pemoval (RHR) Pumps (Continued)
[2]' Hydraulic Test Path Each pump shall be tested by establishing a flowpath with suction from and discharge returning to the Torus (Heat Exchanger Bypass Valve open). Then, using the Loop To Suppression Chamber Spray Cooling Valve for throttling, establish a flowrate.in accordance with current Tech Spec requirements.
Pump discharge and st'ction pressure shall be recorded.
The differential pressure (total head) will be calculated and compared to the established value.
[3]
Instrumentation (a)
Inlet Pressure, Pi (psig): PI-1001-70A, PI-1001-708, PI-1001-70C, PI-1001-700.
(b) -Discharae Pressure, (psig):
PI-1001-71A, PI-1001-718, PI-1001-71C, PI-1001-71D.
(c)
Flowrate, Q (gpm):
FI-1040-11A (Loop A), FI-1040-118 (Loop B).
5.3.5 Core Spray (CS) Pumps
[1]
Test Frequency CS pumps are tested on a quarterly frequency.
[2] Hydraulic Test Path Each pump shall be tested by establishing a flowpath with suction from and discharge returning to the Torus.
- Then, using the CS Full Flow Test Valve for throttling, establish a flowrate in accordance with current Tech Spec requirements.
Pump discharge and suction pressures shall be recorded and the differential pressure (total head) will be calculated and compared to the established value.
[3] ' Instrumentation 1
(a)
Inlet Pressure, Pi (psig): Test gauges at PI-40A, PI-40B.
(b) Rischarae Pressure, (psig): Test gauges at PT-1460A, PT-14608.
-(c)
Flowrate,.Q (gpm):
FI-1450-1A, FI-1450-18.
5.3.6 High Pressure Coolant Injection (HPCI) Pumps
[1]
Test Frequency HPCI pumps (main and booster) are tested on a quarterly frequency'when adequate steam pressure is available.
8.I.1.1 Rev. 1 Page 15 of 172
5.3.6 High Pressure Coolant Injection (HPCI) Pump (Continued)
[2] Hydraulic Test Path These pumps (main and booster) shall be tested by establishing a flowpath with suction from and discharge returning to the CST.
Then, using the HPCI full Flow Test Valve for throttling, establish the speed and flowrate in accordance with current Tech Spec requirements.
Pump discharge and suction pressure shall be recorded.
The differential (total head) pressure will be calculated and compared to the established value.
[3]
Instrumentation (a)
Inlet Pressure, Fi (psig):
PI-2340-7 (Booster), Test gauge at PX-2301-80 (Main).
(b)- Discharae Pressure, (psig):
Test gauge at PX-2301-80 (Booster), PI-2340-2 (Main).
(c)
Flowrate, Q (gpm):
FI-2340-1.
(d) Speed, N (rpm):
SI-2340-1, 1
1 t.
8.I.1.1 Rev. 1 Page 16 of 172
(
5.3.8 Reactor Core Isolation Cooling (RCIC) Pump
[1] Test Frequency-RCIC pump is tested on a quarterly frequency, when adequate steam pressure is available.
[2] Hydraulic Test Path The pump shall be tested by establishing a flowpath from and returning to the CST.
Then, using the test valve for throttling, establish the speed and flowrate in accordance with current Tech Spec requirements.
Pump discharge and suction pressures shall be recorded.
The differential (total head) pressure will be calculated and compared to the established value.
[3] Instrumentation (a). Inlet Pressure, Pi (psig):
PI-1340-2.
(b) Discharae Pressure, (psig):
PI-1340-7.
(c)- Flowrate Q (gpm): -FI-1340-1.
(d)
Speed, N (rpm):
SI-1340-1.
5.3.9 Standby Liquid Control (SLC) Pumps
[1] Test Frequency SLC pumps are tested on a quarterly frequency.
[2] Hydraulic-Test Path Each pump shall be tested by establishing a flowpath with suction from and discharge returning to the SLC Test Tank.
Then, using the test tank valve for throttling, establish a discharge pressure at a known reference value.
Measure the time elapsed, initial and final test tank level. Calculate the. flow rate by level change over time and compare to the established value.
[3] Instrumentaion (a); Inlet Pressure, Pi: Not applicable (RP-3).
(b) Discharae Pressure (psig):
PI-1159.
(c)
Flowrate, Q (inches): Heasuring Stick (yardstick).
8.I.l.1 Rev. 1 Page 17 of 172
5.4 RELIEF REQUESTS FOR INSERV!CE PUMP TESTING PROGRAM Pump Relief Requests (RP) are provided for conditions in which compliance to ASME Code,Section XI test requirements cannot be satisfied.
Each Relief Request identifies:
Pump (s) involved, test requirement (s) of non-compliance, basis for relief and alternate testing.
8.I.1.1 Rev. 1 Page 18 of 172
[1]
Felief Reauest RP-1 P'"PC*
P-202A, P-202B, P-202C, P-202D, P-202E, P-202F J
SYSTEM: Reactor Building Closed Cooling Hater CLASS: -3 FUNCTION:
Emergency Equipment Cooling y
TEST REOUIREMENTS:
Table IHP-3100-1, Inservice Test Quantities; Heasure pump flowrate.
1 BASIS FOR RELIEF:
Reactor Building Closed Cooling Water System instrumentation is not configured to measure individual 1
pump flowrate during plant operation.
Redesign of the 1
system would be necessary to install flow
(
instrumentation or to utilize portable flow instrumentation.- Piping configuration does not permit installation of flow orifices on the pump discharge piping that would be consistent with good instrument C
practices. Adequate distance downstream of elbows is not available on the individual pump discharge prior to where discharge piping joins a common header.
The Reactor Building Closed Cooling Water System is part of the ultimate heat sink for containment cooling functions and reactor vessel shutdown cooling. Test loops do not exist for
'individdal pump flow tests; therefore, disturbance of the i
system normal configuration during operation and cold shutdown conditions will have a negative impact on the plants ability to safely operate or maintain. the plant in the cold shutdown condition.
1 There is no method available to control the flowrates of individual _ pumps.
Shutoff. head will provide a repeatable parameter for measuring pump performance.
Individual-pump flowrate and pressure will be measured each refueling outage.
3 L
ALTERNATE TESTING:
Heasure pump shutoff head quarterly. Neasure-
' individual pump flowrate 'and pressures each refueling -
l outage.
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8.I.1.1 Rev. 1 Page 19 of 172 L
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[23-Relief Reauest RP-2 l
PUMPSi P-141A P-202C-P-203A P-205 P-208A P-208E P-141B-P-2020
-P-202B P-206 P-208B P-215A 1
P-202A P-202E P-203C P-20M P 208C P-215B i
P-202B P-202F P-203D P-2078 P-208D P-220 l
SYSTEMS:
-As ApplicableL
- CLASSES:
2, 3 or NC
- FUNCTIONS:
As applicable.
TEST RE0UIREMENT:
IHP-4310, Bearings - temperature of all centrifugal pump bearings outside the main flowpath and of the main
- l shaft bearings of reciprocating pumps shall be measured at points selected to be responsive to changes in the temperature of the bearing.- Lubricant temperature, when= measured after passing through the bearing and prior to entering a cooler, shall be considered the bearing temperature.
Table IHP-3100-1, Inservice Test Quantities - Bearing Temperature Tb.
1 Table.INP-3100-2, Allowable Ranges of Test Quantities -
Tb (Note (2)).
Note (2) Tb shall be within the limits specified by the Owner in the record of tests (IHP-6000).
I BASIS'FOR RELIEF:
(a)
Some pumps are cooled by their respective process fluid,~" Main Flowpath." Thus, bearing temperature-measurements:would be highly dependent on the 1
temperature of the cooling medium.
--(b)
Pump' bearing temperature is taken.at one (1) year
-intervals and provides very little data toward a
determining -the incremental degradation of a bearing or provide-any meaningful trend data.
(c)
All pumps.will.be subject to vibration. measurements per-
- Subsection INP-4500.
Vibration measurements (displacement and velocity) are a signifi:antly more:
reliable indication ~of pump bearing degradation than that'of temperature measurements.
g
. ALTERNATE TESTING:
Vibration measurements Lusing velocity as a measured-value, shall be taken on each pump in the same 0
locations as the required displacement measured 0
val ue s'.
Pumps with velocity amplitude exceeding 0.314 V
in/sec shall require investigation utilizing-spectrum analysis to determine bearing status.
l 8.I.l.1 Rev. 1 Page 20 of 172
(3)
-Relief Reauest RP-3 i
PUMPS:
P-207A, P-207B j
.YSTEM:' Standby Liquid Control CLASS:
2 3
EUNCTION:
Provides a method of shutting down the reactor without use of the control rods.
-TEST RE0VIREMENTS:
IHP-3300, Scope of Test - measurement and observation of inlet pressure (Pi) and differential pressure (dP) across the pumps.
IHP-3500, Duration of Tests - each pump shall be run at least 5 min. under conditions as stable as the system permits.
'1 INP-4600, Flow Measurement - flowrate shall be measured using a rate or quantity meter installed in the pump i
test circuit.
BASIS FOR RELIEF:
The standby liquid control pumps are required to supply.
the necessary flowrate at a given system pressure..The
' inlet pressure (no installed test equipment) will be equivalent to the static head provided by the' test tank'., Test tank. level-is established within the inservice test procedures. Also, the measurement of-inlet pressure on a positive displacement pump is not a significant test parameter.
The system resistance is set to specified discharge pressure reference value.
Then the test tank level change is measured to determine pump flowrate.
The SLC pumps are tested by pumping ir.to a test tank.
The test tank capacity does not allow operation of the pump for longer than ihree minutes.
Additional controls placed in the present test procedure has produced cor.sistent test results and
. provides good repeatabili ty.
ALTERNATE TESTIE:
Utilize pump discharge pressure reading in lieu of pump
' differential pressure reading and verify test tank level to ensure adequate scetion pressure.
The pump e
shall be_run for a duration of exactly 3 minutes and an accurate measurement of the test tank level before and after the 3 minute run shall be used to verify test parameters.
8.I.l.1 Rev. 1 Page 21 of 172
,(
I
[43-Relief Reauest RP-4 PUMPS: P-208A, P-208B, P-208C, P-2080, P-208E SYSTEM: Salt Service Water-CLASS:
3 FUNCTION:
Emergency Equipment Cooling j
TEST REOUIREMENT:
'IHP-4200, Pressure Measurement (Inlet Suction Pressure Pi).
BASIS FOR' RELIEF:
No instrumentation is installed to measure pump inlet pressure.
ALTERNATE TESTING:
Tide level will be used to calculate pump inlet pressure, and.to specify inlet pressure for test
. purposes.
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8.I.l.1 Rev.-l Page 22 of 172
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[5]
Relief Reauest RP-5 PUMPS: 'P-208A, P-208B, P-208C, P-208D, P-208E SYSTEM: Salt Service Hater CLASS:' 3 FUNCTION:
Emergency Equipment Cooling
- TEST REOUIREMENTS:
Table INP-3100-1, Inservice Test Quantities; Heasure pump flowrate.
BASIS FOR RELIEF:
Salt Service Water System instrumentation is not configured-to measure individual pump.flowrate during operation.
Redesign of the system would be necessary to. install flow instrumentation.
Piping configuration does not permit installation of flow orifices on the 4
pump discharge piping prior to where the pump discharge joins a common header. Ultrasonic indicators cannot be t
reliably utilized with the rubber lined piping used.in the salt' service water system, also the pump discharge piping is underground. The Salt Service Water System is the ultimate heat sink for containment cooling functions and reactor vessel shutdown cooling. Test loops do not exist for individual pump flow tests;
' therefore, disturbance of_ the system normal configuration during operation and cold shutdown 1
conditions will have a negative impact on -the plants ability to safely operate or maintain the plant in the cold shutdown condition.
4 There is no method available to control the flowrates of individual pumps.
Shutoff head will provide a repeatable parameter for measuring pump performance.
Individual pump flowrate and pressure will be measured each refueling outage.
t-
- ALTERNATE ~ TESTING:
Measure pump shutoff head quarterly. Measure i
..dividual pump flowrate and pressure each refueling outage.
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Page 23 of 172
~
1
[63-Relief Reauest RP-6
=
EUMESi P-208A, P-208B, P-208C. P-208D, P-208E SYSTEM: Salt Service Water CLASS:
3 FUNCTION:
Emergency Equipment Cooling
' TEST REOUIREMENT:
IWP-4500, Vibration Amplitude BASIS-FOR RELIEF:
The pump casing is physically located under water and is therefore inaccessible.
ALTERNATE TESTING:
Measure pump motor vibration at upper bearing using the Hydraulic Institute Standards for-location guidance.
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8.I.1.1 Rev. 1 Page 24 of 172 l
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[7]-
Relief Reauest RP-7 l
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EUMES: P-141A, P-141B SYSIIB: Diesel Fuel Oil Transfer CL&SS: NC FUNCTION:
The fuel oil transfer pumps maintain a sufficient operating level in the fuel oil day tank by transferring fuel oil from the g
fuel oil storage tank to the fuel oil-day tank.
?
\\
TEST RE00IREMENTS:
IHP-4600 Flow measurement (accuracy), IHP-3230(a) corrective action (alert range), and IHP-3230(b) corrective action (action range).
j L-BASIS FOR RELIEF:
One fuel oil transfer pump supplies each day tank.
There is no installed flow instrumentation for either pump. The capacity of a fuel transfer pump is approximotely 28 gpm with.the required design capacity.
of the Diesel Engine being.3.3 gpm.
Flowrate can be
! A measured with a portable survey flow meter.
The best
~
t obtainable accuracy for survey flow meters is approximately 151.
System configuration impairs the control of discharge pressure and flowrate-repeatability.
Each pump can meet its design function with greater than 75% degradation.
Review of pump design has shown that this pump will still function reliably with 25% hydraulic degradation
'provided that bearing vibration is not excessive.
Both displacement and velocity vibration is monitored on these pump bearings. Therefore, relief for expanded accuracy requirements er,u alert / action hydraulic ranges will adequately pruvide for pump operability assessment.
-ALTERNATE TESTING:-
Heasurement of flow by survey flow meter with an approximate 15% accuracy.
Corrective action ranges for flow shall be:
15% degradation for the alert range and 25% degradation for the action required range.
i 8.I.l.1 Rev. 1 Page 25 of 172 E
E
[8]
Relief Reauest RP-8 2UM25:
P-141A P-202D P-203C P-207B P-208E P-141B P-202E P-203D P-208A P-215A P-202A P-202F P-205 P-2088 P-215B P-202B P-203A P-206 P-208C P-220 P-202C P-203B P-207A P-2080 SYSTEMS: As Applicable CLASSIS: 2, 3 or NC FUNCTION:
As Applicable L^
TEST REQUIREMENT:
INP-3220. Time Allowed for Analysis of Tests - all test data shall be analyzed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after completion of a test.
BASIS FOR RELIEF: Test acceptance criteria is contained within the test procedures and the determination of equipment operability is made immediately by on-shift personnel. Therefore, j
on-shift personnel shall declare the pump inoperable ano the appropriate Technical Specification action time must be started. The analysis of results for degradation requiring increased testing or engineering evaluation will then occur when the appropriate personnel are available for reviewing the inservice pump test data. The appropriate personnel are not always readily available for this review effort.
ALTERNATE TESTING: Test data will be reviewed within four (4) work days (96 hrs) following the test, excluding wetkends (Saturday &
Sunday) and Holidays.
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8.I.1.1 Rev. 1 Page 26 of 172 l
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[9]
Relief Recuest RP-9 Eu!ES:
P-141A P-2020 P-203C P-2078 P-208E P-1418 P-2020 P-2030 P-208A P-215A P-202A P-202F P-205 P-208B P-215B l
P-2028 P-203A P-206 P-208C P-220 P-202C P-2038 P-207A P-2080 g
SYSTEMS: As Applicable CLASSES: 2, 3 or NC FUNCTIONS:
As Applicable TEST REOUIREMENT:
INP-4120. Range - the full-scale range of each instrrment shall be three times the reference values or less.
BASIS FOR RELIEF: The analog instrumentation (IRD) used to measure vibration amplitude has a range selector with multiples of 3 and 1 (i.e., full scale ranges of 0.1, 0.3, 1, 3, 10 and 30).
The INP-4120 range requirement translates into requiring all measurements to be in the upper 66% of the meter scale. When measur)'ng reference values that fall between; 0.030 to 0.033, 0.30 to 0.33, and 3.0 to 3.3, this requirement can not be met.
For these specific cases, the upper 70% of full scale must be used.
The code deviation described above occurs infrequently and is so minute, the effects are insignificant when compared to the many variables encountered during vibration data collection.
Measuring reference values using the upper 70% of the meter full scale does not impact vibration measuring consistency for nr91toring pump degradation.
ALTERNATE TESTING: Pump vibration reference values will be measured within the upper 70% of the vibration meter's full scale.
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8.I.1.1 Rev. 1 Page 27 of 172 w
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m (10)
Relief Recuest RP-10 RETRACTE" b
m 8.I.1.1 Rev. 1 Page 28 of 172
5.5 PUMP PROGRAM TABLE 1
This table identifies the scope of pumps within the ISTP and allows cross-referencing specific pump test quantities to their implementing station procedure.
The test quantities measured include:
Speed (N), Inlet Pressure (P1),
Differential Pressure (dP), flowrate (Q), Vibration (V), Lubricant Level (L) and Bearing Temperature (Tb).
)
8.I.l.1 Rev. 1 Page 29 of 172
-TABLE PUMPS TESTED ISI CLASS 1. 2, 3 AND NC FUMPS INSERVICE TEST CUANTITIES l
lIST I lP&ID l l
l SPEED l INLET lDIFF.
l FLOW l
l LUBRICANT l BEARING SYSTEM l PUMP # ICLASSI P&ID IC00RD.lTEST PROC.lFREO.I (N) l PRESS.(PillPRESS.fdPilRATE (0)lVIB. (VilLEVEL (L) ITEMP.(Tb)
SALT SERVICE lP-208Al 3 lM212 lB7 l8.5.3.2#l Q lNA lRP-4 l
Y l RP-5 lRP-6&9l Y
l RP-2 WATER (SSW) lP-2080l 3 lM212 lB8 l8.5.3.2#l Q lNA l RP-4 l
Y l RP-5 lRP-6&9l Y
l RP-2 l P-208C l 3 l M212 l B7 l 8.5.3.2# l Q l NA l RP-4 l
Y l RP-5 lRP-6 & 9]
Y l
RP-2 l P-2060 l 3 lM212 l56 l8.5.3.2#l Q lNA lRP-4 l
Y l RP-5 lRP-6 & 9l Y
l RP-2 I P '.08E I 3 i M212 I B5 I 8.5.3.2# I O I MA I RP-4 I
Y I RP-5 lRP-6 & 91 Y
I RP-2 REACTOR BUILDING 7, c-202A l 3 lM215 lF3 l8.5.3.1#l Q l NA l Y
l Y
l RP-1 l RP-9 l Y
l RP-2 CLOSED COOLING lP-2028l 3 lM215 lF3 l8.5.3.1#l Q lNA l Y
l Y
l RP-1 l RP-9 l Y
l RP-2 WATER (RBCCW) lP-202Cl 3 lM215 lG3 l8.5.3.1#l Q lNA l Y
l Y
l RP-1 l RP-9 l Y
l RP-2 l P-202D l 3 lM215 l G5 l8.5.3.1#l Q l NA l Y
l Y
l RP-1 l RP-9 l Y
l RP-2 lP-202El 3 lM215
-l G5 l 8.5.3.18 l Q l ML l Y
l Y
l RP-1 l RP-9 l Y
l RP-2 I P-202F l 3 I M215 i F5 I 8.5.3.1* I O I MA I Y
I Y
I RP-1 I RP-9 I Y
l RP-2 DIESEL OIL lP-141AlNC lM223 l F6 l8.9.1.1 l Q l NA l Y
l Y
l RP-7 l RP-9 l NA l
RP-2 TRANSFER (DOT) l P-141B I NC I M223 1 E6 I 8.9.1.1 I O l NA I Y
I Y
I RF-7 I RP-9 I NA l
RP-2 l.ESIDUAL HEAT l P-203A l 2 lM241(52)lD6 l8.5.2.2.1l Q lNA l Y
l Y
l Y
l RP-9 l Y
l RP-2 REMOVAL (RHR) l P-2038 l 2 [M241(S2)lD3 l8.5.2.2.2l Q l MA l Y
l Y
l Y
l RP-9 l Y
l RP-2 l P-203C l 2 lM241(52)lF6 l8.5.2.2.1l Q lNA l Y
l Y
l Y
l RP-9 l Y
l RP-2 l P-203D I 2 IM241(S2)I F3 I 8.5.2.2.2! O I NA l Y
I Y
l Y
l RP-9 l Y
I RP-2 CORE SPRAY (CS) l P-215A l 2 l M242 lF7 l8.5.1.1 l Q lNA l Y
l Y
l Y
l RP-9 l Y
l RP-2 i P-215B I 2 i M242 I F9 I 8.5.1.1 1 0 I NA I Y
l Y
l Y
I RP-9 I Y
l RP-2 HIGH PRESSURE l ?-205 l 2 lM244 lF9 l8.5.4.1 l Q l Y l Y
l Y
l Y
l RP-9 l Y
l RP-2 COOLANTINJECTIC'4]
l l
l l
l l
l l
l l
l l
(HPCI)
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I I
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REACTOR CORE ISOL] P-206 l 2 l M246 l FB l 8.5.5.1 l Q l Y l Y
{
-Y l
Y l RP-9 l Y
l RP-2 COOLING (RCIC)
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I l
l I
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1 STANDBY LIQUID lP-207Al 2 lM249 l E5 l8.4.1 l Q l NA lRP-3 lRP-3 l RP-3 l RP-9 l Y
l RP-2 CONTROL (SBLC)
I P-207B I 2 I M249 i F5 1 8.4.1 1 0 I NA I RP-3 I RP-3 I RP-3 I RP-9 I Y
I RP-2 O These pumps are tested in compliance with the ASME Code,Section XI Requirements each refueling outage. The refueling outage procedure shs11 be used for post-maintenance testing il plant conditions exist in which compliance to the Limitations and Precautions can be met.
8.I.1.1 Rev. 1 Page 30 of 172
6.0 INSERVICE VALVE TESTING 6.1 GENERAL INFORMATION (13 Applicable Code This Inservice Testing Program for ISI Class 1, 2, 3 and NC valves meets the requirements of Subsection IWV of Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Hinter 1980 Addenda. Where these requirements are determined to be impractical, specific requests for relief have been written and included in Section 6.4.
[2] Vaive Program Table The Tables contained in Section 6.5 list all ISI Class 1, 2, 3 and NC valves that are tested to meet IST requirements.
i The tables are sorted by system & Piping and Instrumentation Drawing (P&ID) number (s) and contain the following information.
(a) VALVE NUMBER: Valve identification number.
(b) 111D COORDINATE: Coordinate location and sheet number on the P&ID.
(c)
ISI CLASS:
Inservice inspection classification (Class 1, 2, 3 or NC).
(d) YALYE CATEGORY: Category assigned to the valve based on the definitions of IHV-2200.
Four (4) separate categories are defined in the Code:
(1) CATEGORY A - valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their function.
l (2) CATEGORY B - valves for which a specific amount of
[
leakage in the closed position is inconsequential for fulfillment of their function.
(3) CATEGORY C - valves which are self-actuating in response to some system characteristic such as pressure (relief valves) or flow direction (check valves).
l (4) CATEGORY D - valves which are actuated by an energy source capable of only one operation such as rupture i
disks or explosive actuated valves.
(S; CATEGORY AC - valves which exhibit both Category A and Category C characteristics.
(6) CATEGORY NA - valves which are not required by IHV to be
- tested, j
(e) VALVE SIZE:
Nominal pipe size (in inches).
8.I.1.1 Rev. 1 Page 31 of 172 l
6.1 GENERAL INFORMATION (Continued)
(f) VALVE TYPE: Valve Body Design; ANGLE AN PLUG PG BALL BL RELIEF RL BUTIERFLY BF RUPTURE DISC RD CHECK CK SAFETY SV GATE GA SHEAR SH GLOBE GL STOP CHECK SC NEEDLE ND SPRING CHECK SK (g) ACTUATOR TYPE: Valve Actuator Power; HOTOR OPERATOR H0 EXPLOSIVE ACTUATOR TX AIR OPERATOR A0 MANUAL MA SOLEN 0ID OPERATOR SO SELF ACTUATED SA HYDRAULIC OPERATOR H0 (h) NORMAL POSITION: Normal Position During Plant Operation:
NORMAL OPEN 0
LOCKED OPEN LO NORMALLY CLOSED C
LOCKED CLOSED LC (i) TEST REOUIREMENT: Test (s) that will be performed to fulfill the requirements of Subsection IWY.
The test definitions and abbreviations used are identified in Table 1, Inservice Valve Tests.
(j) TEST FRE00ENCY:
Frequency at which the tests will be performed.
The frequency defini'; ions and abbreviations used are identified in Table 2, Test.irequency.
(k) TEST DIRECTION:
Direction the valve is exercised to during stroke time measurements or a check valve exercise.
The direction for stroke time measurements is that which is required to fulfill its safety-related function per the FSAR and/or Tech Specs. The direction for check ve'.ve exercising is to the position required to fulfill their / unction.
0 - Open C - Closed FF - Forward Flow, Normally Closed Valves RF - Reverse flow, Normally Closed Valves (1) COLD SHUTDOWN JUSTIFICATION:
Refer to Section 6.3 for cold shutdown description.
Requests are identified as CS-XX.
(m) RELIEF REOUEST:
Refer to Section 6.4 for relief request description.
Requests are a sntified as RV-XX.
(n) REMARKS: Clarification to the particular column to identify a special or unique requirement.
8.I.1.1 Rev. 1 Page 32 of 172
i 6.1 GENERAL. INFORMATION (Continued)
[3]
Exempt Valves Valves exempt per INV-1200 and passive valves that do not have a specific maximum leakage requirement are not included in the IST Program.
Passive valves are those valves which are not required to change position to accomplish a safety-related function.
Subarticle IWV-1200, " Valves Exempt from Testing", includes:
(a) Valves used only for operating convenience, system control and maintenance.
(b)
External control and protection systems responsible for sensing plant conditions and providing signals for valve operation.
Control valves whose actuators are required to provide a fail-safe position have been included in the program per Generic Letter 89-04 and are fail-safe tested only.
Exempt valves with remote position indicators have been included so their position indicators will be checked with the exempt status noted. Dampers are considered exempt (i.e., HVAC System).
[4] Measurement of Test Quantities (a) STROKE TIME: Stroke time is the time interval from initiation of the actuating signal to the end of the actuating cycle.
Stroke time value(s) for each power operated valve is specified within the appropriate test procedure.
(b; POSITION INDICATION:
Valve disk movement is determined by exercising the valve while observing appropriate indicators which signal the required change of disk position.
Observation of actual valve taovement or indirect evidence (such as changes in system pressure, flowrate, level or temperature) which reflect stem or disk position will be used to verify that remote position indicators agree with valve travel direction.
(c) SEAT LEAKAGE:. Seat leakage is measured by one of the following methods:
(1) Draining the line, closing the valve, bringing one side to test pressure and measuring leakage through a downstream telltale connection.
(2) By measuring the feedrate required to maintain pressure between two valves or between two seats of a gate valve, provided the total apparent leak rate is charged to the valve or gate valve seat being tested and that the conditions required by INV-3423 are <atisfied.
(3) By performance of a Pressure Drop (Decay) Test to verify l
that an entire pressure boundary does not exceed its specified leakage criteria (Reference RV-30).
8.I.l.1 Rev. 1 Page 33 of 172
6.1 GENERAL INFORMATION (Continued)
(d) CHECK VALVE EXERCISE:
Check valve exercises will be confirmed by observing a direct indicator such as a position indicating device or by observing system changes such as flowrate, system pressure, level, temperature or other positive means.
The following test practices will be utilized:
(1)
Full Flow Check Exercise - will be verified by observation of substantially free flow through ths valve. When a required accident condition flowrate exists, it will be verified.
If the accident flowrate can not be confirmed, the valve may be exercised mechanically or placed in the disassembly program (Reference RV-27).
(2) Mechanical Exerciser - the force or torque delivered to the disk by the exerciser must be limited to less than 10% of the equivalent force or torque represented by the minimum emergency condition pressure differential acting on the disk or to 200% of the actual observed force or torque required to perform the exercise on the valve when the valve is new and in good operating condition, whichever is less.
(3) Vacuum Breaker - the exerciser force or torque delivered to the disk may be equivalent to the desired functional pressure differential force. Also, the disk movement shall be sufficient to prove that the disk moves freely off the seat.
If no functional pressure differential force is specified, only disk movement is required.
(e) CHECK VALVE DISASSEMBLY:
The verification of full opening during flow testing for some normally closed check valves is inhibited by system configuration or limitations.
For valves with these design limitations, the check valve testing hierarcy and disassembly guidance outlined in NRC Generic Letter 89-04 and published " Minutes of the Public Meetings on Generic Letter 89-04" will be followed.
This deviation from the Code (which is approved by the above documents) has been identified within Relief Request RV-27.
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8.I.1.1 Rev. 1 Page 34 of 172
I 6.1 GENERAL INFORMATION (Continued)
The check valve disassembly program will be controlled in accordance with PNPS 8.I.27.
These valves with their I
disassembly category are listed by system below:
SYSTEM CAT #
VALVE #'s Salt Service Water 1
AV-A.AV-B AV-C AV-D,AV-E
_129)
2A,28,2C,20 (1001) 2 68A.68B ECore Sorav (1400) 1 13A.13B High Pressure Coolant 1
39 Injection (2301) 2 40 3
34.216.217 1
27 Reactor Core 2
47 Isolation Cooling 3
63 (1301) 4 40,59 5
89 6
90
[5] Allowable Ranges of Test Quantities (a)
STROKE TIME:
(1) Motor Operated Valves The following values are based on a valve reference time (R) which is established from actual field test results.
REFERENCE TIME (R)
ALERT VALUE (SEC.)
REQUIRED ACTION VALUE (SEC.)
2 i R to 15 sec.
(1.2 x R) + (0.5)
(1.4 x R) + (0.5)
Round to nearest Round to nearest 1/10 sec.
1/10 sec.
5 < R to 1 15 sec.
(1.2 x R)
(1.4 x R)
Round to nearest Round to nearest 1/2 sec.
1/2 sec.
R > 15 sec.
(1,10 x R)
(1.2 x R)
Round to nearest:
Round to nearest:
1 sec. for times 1 50 sec.
I sec. for times 1 50 sec.
5th Integer for times 5th Integer for times
> 50 sec.
> 50 sec.
8.I.1.1 Rev. 1 Page 35 of 172
m 6.1 GENERAL INFORMATION (Continued) a.
The valve stroke time required action value shall not exceed either the Tech Spec or FSAR requirements, b.
Valve stroke time deviations faster than the reference value by a magnitude greater than the alert value will be considered erratic and investigated.
(2) Other Valves (Air, Hydraulic Solenoid, Etc.)
The following values are based on a valve reference time (R) which is established from actual field test results.
REFERENCE TIME (R)
ALERT VALUE (SEC.)
REOUIRED ACTION VALUE (SEC.)
1 1 R to 1 5 sec.
(1.5 x R) + (.5)
(2.0 x R) + (0.5)
Round to nearest Round to nearest 1/10 sec.
1/10 sec.
5 < R to 1 10 sec.
(1.5 x R)
(2.0 x R)
Round to nearest Round to nearest 1/2 sec.
1/2 sec.
R > 10 sec.
(1.25 x R)
(1.5 x R)
Round to nearest:
Round to nearest:
1 sec. for times 1 50 sec.
I sec. for times 1 50 sec.
5th Integer for times 5th Integer for times
> 50 sec.
> 50 sec.
a.
The valve stroke time required action value shall not exceed either the Tech Spec or FSAR requirements, b.
Valve stroke time deviations faster than the reference value by a magnitude greater than the tiert value will be considered erratic and
'uvestigated.
c.
Valves may be classified as fast-acting and assigned a 2-second required action value with the alert value being Not Applicable.
(3) A valve stroke time shall not exceed its specified alert value without increased test frequency or specified limiting stroke time (required action) value without being declared inoperable immediatelv and corrective action being taken.
(b) POSITION INDICATION:
During valve opening and closure, the remote position indicators shall-accurately reflect valve travel direction.
8.I.1.1 Rev. 1 Page 36 of 172
i 6.1 GENERAL INFORMATION (Continued)
(c) SEAT LEAKAGE:
(1) Valve leakage rates shall not exceed the value established by Boston Idison Company.
These leakage i
values are specified within the implementing test procedures. Valves that fail to meet the acceptance criteria shall be declared inoperable immediately and require corrective action.
(2)
For valves 6 in, nominal pipe size and larger (not to include containment isolation valves), the leakage rate shall not exceed that established by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate by 50% or i
greater.
The test frequency shall be doubled.
The tests shall be scheduled to coincide with a cold shutdown until corrective action is taken.
If tests show a leakage rate increasing with time and a projection based on three or more tests indicates that the leakage rate of the next scheduled test will exceed the maximum permissible leakage rate by greater than 10%, then corrective action will be taken.
[5]
Instrument Accuracy Instruments used to measure stroke times shall be capable of measurement to the nearest tenth of a second.
[6] Corrective Action (a) STROKE TIME: Corrective action shall be to repair or replace i
the valve.
I (b) SEAT LEAKAGE: Corrective action shall be to repair or replace the valve.
(c) RELIEF VALVES:
(1) Relief valves which fail to function properly during testing shall be:
- 1) adjusted 2) repaired or 3) replaced and retested to show acceptable operation.
Procedure credit may be taken for valves that are tested i
by the vendor / manufacturer provided that similar test I
methods are used and the documentation verifies
'l surveillance procedure acceptance criteria has been met.
(2)
If any relief valve in a system fails the regular test, an additional sampling of valves in that system shall be tested.
If any of these additional valves fail, then all the remaining relief valves in the system shall be tested.
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TABLE 1 INSERVICE VALVE TESTS 1E$1 TEST NAME TEST DESCRIPTION / DEFINITION LJ Containment Containment isolation valves (CIVs) will be seat Isolation Valves leak tested in accordance with 10CFR50, Appendix J, Type C Leak Test which is equivalent to the requirements of INV-3421 through INV-3425.
The practice of testing between CIVs is acceptable since the most restrictive CIV leakage limit is used to evaluate test results for acceptance and unacceptable test results require compliance to IHV-3426 and IHV-3427(a).
LP Pressura Isolation Pressure Isolation Valves are any two valves in Valves series within the Reactor Coolant Pressure Boundary which separated the High Pressure Reactor Coolant from an attached low pressure system and are normally closed.
These valves will be seat leak tested in accordance with ASME Boiler and Pressure Vessel Code,Section XI, IWV-3420 Valve Leak Rate Test.
The basis for valve selection is 1
provided in BECo's response to Generic Letter 87-06.
LX Miscellaneous Other safety related valves - Miscellaneous Isolation Valves Isolation Valves will be seat leak tested in accordance with; 10CFR50 Appendix J. ASME Boiler and Pressure Vessel Code Section XI, or standard pressure drop test tecnniques (RV-30).
FE Full-Stroke Exercise testing of Category A or B valves Exercise through one complete cycle of operation.
- 1) Normally open:
Full Stroke exercise the valve closed then return to open position.
- 2) Normally closed:
Full Stroke exercise the valve open then return to closed position.
ST Stroke Time Stroke time is the measurement of the time required to exercise test a Category A or B valve through an operation.
The direction for stroke time measurements is that which is required to fulfill its safety-related function per the FSAR and/or Tech Specs.
PE Partial Stroke Partial stroke exercise testing will be performed Exercise on those valves that cannot be full stroke exercised during plant operation and have the capability to be partially exercised.
The full stroke exercise shall be performed during cold I
shutdowns.
8.I.1.1 Rev. 1 Page 38 of 172
TABLE 1 INSERVICE VALVE TESTS (Continued) 1111 TEST NAME IfST DESCRIPTION / DEFINITION FC Check Valve Check valves will be exercised to assure Exercise freedom of motion and prevent sticking / seizure of parts from prolonged immobility.
1) forward Flow Direction (FF) - Normally closed valves:
Full Stroke open.
2)
Reverse Flow Direction (RF) - Normally open valves:
Full Stroke close.
PC Partial Check Partial (valve checked in same flow direction)
Exercise exercise is when 6 Category C valve can not be verified in its full flow position as required by an FC test.
RD Rupture Disk Non-Testable rupture disks were test certified Test by the manufacturer or the start-up testing program and no additional testing shall be required.
All rupture disks at PNPS are non-testable.
EX Explosive Test Testing of explosive charges by firing per ASME Section XI with at least 20% of the charges in a batch fired every 2 years with no charge exceeding 10 years.
RT Relief Set Point Relief and Safety Valve setpoints will be verified 1
Test in accordance with ASME Boiler and Pressure Vessel Code,Section XI (IRV-3510), ASME PTC 25.3-1976 with addenda and PNPS Technical Specifications.
FS fail Safe Test-Valves with fail safe actuators (e.g., air operated, spring loaded, solenoid operated and hydraulic operated) will be tested to verify o-proper fail safe operation upon loss of actuator power.
l-PI Position Indication Valves with remote position indicators will be Verification checked to verify that remote valve position indicators accurately reflect valve travel l
direction.
l 8.I.l.1 Rev. 1 Page 39 of 172
TABLE 1 INSERVICE VALVE TESTS (Continuedl IESI TEST NAME TEST DESCRIPTION / DEFINITION AP Check Alternate An augmented requirement which will verify a check (Safety) Position valve has returned to its normal operational Verification position. This verification will be implemented when the check valve performs a safety-related function in its normal operational position.
Check valves reposition themselves following an exercise.
This repositioning is verified by normal operational parameters, special testing or valve disassembly. Test frequency may be as often as every 92 days and will not exceed a refueling outage.
The following practices will be utilized for AP verification:
1.
Performance of a 2-year leak test satisfies an AP requirement for the closed position, thus if a normally closed valve has a leakage requirement, there will be no AP test requirement identified.
2.
Check valves requiring disassembly to satisfy the AP requirement may be placed in the Disassembly Sampling Program, Reference RV-27 for guidance.
3.
Check valves requiring an FC disassembly will be assigned an AP requirement on their test table and will have the AP performed during disassembly.
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L 8.I.1.1 Rev. 1 Page 40 of 172
TABLE 2 TEST FREOUENCY TEST FREO.
OPERATIONAL CONDITION FREOUENCY OF TESTING Q
Power Operation At least once per 92 days CS Cold Shutdown See (2) below R0 Refueling Outage See (1) below SY No operational Every five years (see INV-3511).
condition limitations Applies to RT test 2Y No operational Every two years (see IHV-3300).
condition limitations Applies to position indication tests and seat leakage tests (1)
Refueling outage conditions are as contained in the definitions of the PNPS Tech Specs.
(2)
Plant Cold Shutdown (as defined in PNFS Tech Specs) testing is acceptable when the following ct,nditions are met:
(a) Testing is to comment e as soon as practical when the Cold Shutdown enndition is achieved, but not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after shutdown and cantinue until complete or the plant is ready to return to power.
(b) Completion of all testing is not a prerequisite to return to power. Any testing not completed during one cold shutdown should be performed during any subsequent cold shutdown starting with those tests not previously completed.
(c) Testing need not be performed more often than once every 3 months.
(d)
In the case of extended cold shutdowns, the testing need not be started within the 48-hour limitation.
However.-in extended cold shutdowns, all Cold Shutdown Testing must be completed prior to returning to power.
(3)
PNPS Tech Spec Surveillance Interval definitions are to be applied to the following required frequencies for performing. inservice testing activities.
These required intervals may be extended as allowed by the PNPS Tech Spec " Surveillance Frequency" definition.
ASME B&PV CODE TERMINOLOGY REQUIRED FREQUENCIES FOR FOR IST ACTIVITIES PERFORHING IST ACTIVITIES Heekly At least once per 7 days Monthly At least once per 31 days Quarterly (every 3 months)
At least once per 92 days Semiannually (every 6 months)
At least once per 184 days Every 9 months At least once per 276 days Yearly At least once per 366 days 8.I.l.1 Rev. 1 Page 41 of 172
6.2 VALVE POST-MAINTENANCE TESTI W The IST Program require 5 each tabe to be verified as operationally ready after routine servicing, maintenance, repair or replacement. The verification of operational rear iness should be achieved by acceptable performance of a procedure used to verify test requirements which may have been affected.
The test requirements may be verified by other documented procedures as long as all test conditions are complied with in accordance with Subsection INV.
Valve post-maintenance testing guidance is provided using a i
step-by-step determination process, a work scope (HS) guideline, and a retest flowpath.
The RS&PD ASHE Test Engineer may be consulted for questions or further clarification.
The M -Epynd (Prework) Testing requirements can be determined through this process. As-Found testing is pertinent to Containment Isolation Valves (only) and must be identified prior to start of maintenance for compliance of 10CFR50 Appendix J.
[1] Steo-Bv-Sten Determination (a) Steps as follows (reference Retest Flowpath):
Step 1: Using this procedure, Section 6.6, locate the valve and verify if it is listed within the table.
Step 2: Note all test requirement (s) identified for the valve.
Step 3:
For each valve test requirement, verify if the work to be performed is identified within the HS guideline.
liQlE When using guidelines to determine containment-isolation valve As-Found (Prework) test requirements, if a post-maintenance LJ procedure requires retest for operational readiness, then an M -Found test must be considered.
When the work scope covered in a Maintenance Request is I
changed, it is important to re-verify this As-Found testing requirement.
1 l
Step 4:
Identify the applicable PNPS Procedure No(s).
08 equivalent documentation (that will verify the test requirement is performed in accordance with the Subsection INV) on the Maintenance Request.
8.I.l.1 Rev. 1 Page 42 of 172
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6.2 VALVE POST-MAINTENANCE TESTING (Continued) i
[2] Hork Stone Guideline (a) Routine Servicing - Performance of planned preventive maintenance which don ngi require disassembly of the valve or replacement of parts such as adjustment of stem packing.
(b) Maintenance - Performance of preventive or corrective maintenance which don require disassembly of the valve or j
replacement of consumable items. EXAMPLES:
replacement of packing, removal of bonnet, stem assembly or actuator, and disconnection of hydraulic or electrical lines, and Specified Maintenance - Performance of preventive or corrective maintenance which is unique to a test requirement and is identified within the test requirement work scope.
l The test requirement need only be performed if specifically identified within the work scope.
(c) Repair - Performance of welding or grinding on a valve to correct a defect (does not include valve actuator).
(d) Replacement - Installation of a new valve, valve part or a i
modification to the valve (does not include valve actuator).
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Cross-Reference Table (Test Requirement vs Hork Scope)
Test Reautrement Hork Stones FE, FC, ST, FS Routine servicing, maintenance, repair or replacement.
EXCEPTION: Application of grease i
through a grease fitting (for PM Program) does not require stroke exercise or timing.
3 LJ Specified maintenance, repair or replacement.
i Specified maintenance: repacking, lowering of motor-operated valve torque switch mechenism, i
l adjustment of motor-operated valve closing limit l
l switch for valves that close on limit switch, I
disassembly of valve internals or removal of valve 1
actuator. As-found (Pretest) testing is required t
l for Containment Isolation Valves.
Exception: Hotor operated valve diagnostic testing may sometimes be l
used to verify a torque setting has not been lowered in lieu of leak testing, 8.I.1.1 Rev. 1 i
l Page 43 of 172
?
r 6.2 VALVE POST-MAINTENANCE TESTING (Continued)
LP, LX Specified maintenance, repair or replacement.
Specified maintenance:
alteration to seating surface, lowering of motor-operated valve closing torque switch setting, replacement of motor-operated valve torque switch mechanism, adjustmentofmotor-operatedvalveclosingunit switch for motor-operated valves that close on limit switch. Exception: Same as LJ Test.
PI Specified maintenance, repair or replacement.
Specified maintenance:
adjustment or disassembly of limit switch mechanism for a remote position indicator, terminating / reterminating wiring for the remote indicator circuitry and/or reconnection of the valve actuator.
Exceotion: No retest for replacement of fuses or light bulbs and single lead lifting and landing wire removal method.
RT Specified maintenance, repair or replacement.
Specified maintenance:
adjustment of setting, disassembly or internal gagging.
RD Repair or replacement.
EX.
None (Manufacturer's Data acceptable).
h 8.I.1.1 Rev. 1 i
Page 44 of 172 i
6.2 VALVE POST-MAINTENANCE TESTING (Continued)
[3] PJLttiLf_lowcath CAUTION When a post-maintenance LJ test requirement is identified, a pretest (As-Found) test must be considered prior to commencing work.
Verify if Valve Listed No IST Retest STEP 1 within this procedure No For Operational Section 6.5.
Readiness.
l n
Yes Note test requirement (s)
STEP 2 for valve.
I Yes b
for each test requirement verify if work to be per-STEP 3 formed is identified No within HS auideline.
I Yes Locate Procedure No(s) in STEP 4 Section 6.5 of this proce-dure (or equivalent docu-mentation) and identify for retest consideration on Maintenance Reauest.
1 8.I.1.1 Rev. 1 Page 45 of 172
6.2 VALVE FOST-MAINTENANCE TESTING (Continued)
(4) EXAMPLES:
(a) A0-203-1A requires the valve seating surface to be machined (grinding) and lapped per Maintenance Request and the appropriate procedures to be used for retests.
A0-203-1A is listed on No IST Retest STEP 1 Page 154.
No ---------- For Operational Readiness.
Yes I
y Note valve test reqts.:
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Yes l
l n
e Hork Scope
- o be performed l
is identified within Guide-i STEP 3 lines - repair. This re-
No quires: FE, ST, FS, LJ, PI.
HQII:
The Local Leak Rate Test Yes (LJ) may require both Pre and Post Leak Rate a
Testing.
' Proc. Numbers:
STEP 4 FE.ST,fS; 8.7.4.4 LJ PI
- 8.7.1.6 Yes a
Perform app'icable steps Maintenance Request doc-of Section 7.0, Prereq-umentation not required, utsites and Section 8.0,
OR ------ retest must be performed Procedure, by Procedure.
8.I.l.1 Rev. 1 Page 46 of 172
1 6.2 VALVE POST-MAINTENANCE TESTING (Continued)
(b) 1001-PSV-44 requires the valve seating surface to be lapped per Maintenance Request and the appropriate procedures to be used for retests.
1001-PSV-44 is listed No IST Retest
-STEP 1 on Page 133.
No ---------- For Operational Readiness.
I I
Yes i
I 1
n Note valve test regts.:
l STEP 2 RT. LX.
i l
I Yes i
I i
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Work Scope to be performed i
is identified within Guide-I I
STEP 3 lines - specified mainten-
No ance. This requires:
RT, LX.
Yes o
Proc. Numbers:
STEP 4 RT; 8.I.26 LX: 8.I.26 Yes o
Perform applicable steps Maintenance Request doc-of Section 7.0, Prereq-umentation not required, uisites and Section 8.0,
OR ------ retest should be per-Procedure.
formed by Procedure.
8.I.l.1 Rev. 1 Page 47 of 172
6.2 VALV; POST-MAINTENANCE TESTING (Continued)
(c) MO-1400-24B requires the stem packing to be adjusted to minimize leaking and the retest is to be performed within the Maintenance Request package.
H0-1400-248 is listed No IST Retest STEP 1 on Page 136.
No --------- For Operational Readiness.
I I
Yes u
Note valve test reqts.:
l i
Yes l
ll Hork Scope to be performed is identified within Guide-g STEP 3 lines - routine servicing.
No This requires:
Yes a
Proc. Numbers:
Reviewed Proc. Section Maintenance Request steps 7.0, Prerequisites and could follow procedure Section 8.0, Procedure
- - - - -0 R - - - - - reqts to document the for retest reats, retests: FE, ST.
Using Maintenance Request steps to document retest re-quirements is not the recommended method.
8.I.l.1 Rev. 1 Page 48 of 172
6.2 VALVE POST-MAINTENANCE TESTING (Continued)
(d) HO-2301-3 requires the electric motor to be replaced per Maintenance Request and the appropriate procedures to be used for retest.
HO-2301-3 is listed on No IST Retest STEP 1 Page 138.
No ------
For Operational Readiness.
I i
I Yes I
u g
Note valve test regts.:
l l
Yes i
I o
I I
Hork Scope to be performed is identified within Guide-l STEP 3 lines - maintenance.
This
No requires:
Yes EQlE:
Motor replacement is 1
<r categorized as main-Proc. Numbers:
tenance.
STEP 4 FE & ST; 8.5.4.1 or 8.5.4.4 PI
- 8.5.4.4 Yes e
Perform applicable steps Maintenance Request steps of Section 7.0, Prereq-could follow procedure uisites and Section 8.0, AND reqts..to perform the PI Procedure for FE. ST.
retest. Using Maintenance Request steps te document retest requiremints is an1 the recommended method.
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8.I.1.1 Rev. 1 l
Page 49 of 172 1
6.2 VALVE POST-MAINTENANCE TESTING (Continued)
(e) H0-1001-33A requires the handwheel to be replaced per Maintenance Request.
H0-1001-33A is listed No IST Retest STEP 1 on Page 131.
No ---------,For Operational lReadinass.
a Yes o
Note valve test reqts.:
STEP 2 PI l
l Yes v
Hork Scope <:0 be performed is identified within Guide-STEP 3 lines - maintenance.
This No requires:
NA.
i l
Yes j
HQlE: Handwheel replacement is considered replacement of Proc. Numbers:-
valve actuator and falls STEP 4 Not Reauired.
within HS as maintenance.
Maintenance is nni iden-tified within the PI test regt. work scope.
8.I.1.1 Rev. 1 Page 50 of 172
)
I 6.3 COLD SHUTDOHN JUSTIFICATIONS Valve Cold Shutdown Justifications (CS) are provided for conditions where compliance to ASME Code,Section XI, Subsection IHV test requirements are satisfied, but conditions exist that necessitate a test frequency of " cold shutdown" in lieu of " quarterly".
Each Cold Shutdown Justification identifies: Valve (s) involved, compliance test i
requirement (s), basis for justification, and an alternate testing j
frequency of cold shutdown.
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8.I.1.1 Rev. 1 Page 51 of 172
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[1]
COLD SHUTDONN JUSTIFICATION CS-01 SYSTEM:
' Reactor Building Closed Cooling Hater System (30)
VALVES:
4009A, 4009B, 4002 CATEGORIES: A,B CLASSES:
2, 3 FUNCTION:
These valves provide isolation to drywell components cooled by RBCCK.
The components would require isolation for primary containment criteria and maintenance.
TEST REOUIREMENTS:
IHV-3411; Test frequency - exercise at least once every three months.
IHV-3413; Power operated valves - full stroke time.
MSJS FOR The testing of these valves would require isolation of the following components; Drywell Area Coolers, Reactor JUSTIFICATION:.
Recirculation Pump Seal Coolers, Reactor Recirculation Pump Lube Oil Coolers and additionally; The Reactor Hater Cleanup (RHCU) non-regenerative heat exchanger, B Fuel Pool Cooling Heat Exchanger, RHCU Pump Cooling System Coolers, Control Rod Drive (CRD) Pump Area Cooling and CRD Pump Thrust Bearing Coolers for testing of the 4009A and 40098.
The listed components supply numerous plant systems required for safe J
. plant operation.
The recirculation pumps and drywell coolers J
maybe required to support the plant during cold shutdown conditions to-prevent stratification of Reactor Vessel Lower s
Head Hater and overheating of Drywell components.
Exercise valves during cold shutdown when recirculation
' ALTERNATE TESTING:.
pumps and drywell coolers are not required but not to exceed a refueling outage.
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Page 52 of.172 L
[2]
COLD SHUTDOHN JUSTIFICATION CS-02 SYSTEM:
Residual Heat Removal System (1001)
VALVES:
47, 50, 60, 63 CATEGORY:
A CL&SS:
1 FUNCTION:
The 47 and 50 valves are the RHR shutdown cooling suction path primary containment and pressure isolation valves.
The 60 and 63 valves are the RHR head spray line primary containment and pressure isolation valves.
TEST REOUIREMENTS:
INV-3411; Test frequency - exercise at least once every three months.
IHV-3413; Power cperated valves - full stroke time.
R& SIS FOR The valves are interlocked to prevent opening when JUSTIFICATION:
reactor pressure is greater than 100 psig.
Each pressure isolation motor operated valve maintains one of the two high pressure barriers during plant operation.
To exercis) these valves during plant operation would involve a loss of one pressure isolation barrier between the high pressure reactor coolant system and low pressure RHR system.
ALTERNATE TESTING:
Exercise valves during cold shutdown.
8.I.1.1 Rev. 1 Page 53 of 172 j
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t (3)
COLD SHUTDOWN JUSTIFICATION CS-03 SYSTEM:
Residual Heat Hemoval System (i001)
VALVES:
6BA, 68B CATEGORY:
AC CLAE:
1 v
- FUNCTION:
These valves are the low nressure coolant injection pressure isolation check valves which provide a flowpath for shutdown cooling.
TEST REQUIREMENT: _
INV-3521; Test frequency - exercise at least once every three months, quarterly.
BASIS FOR Exercising these valves to the open position can only be JUSTIFICATION:
accomplished by verifying flow to the vessel.
Partial flow exercising of these valves is confirmed during shutdown cooling operations.
ALTERNATE TESTING:-
Partial exercise valve during cold shutdown not-to exceed refueling outage.
(
F
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7 8.I.1.1 Rev. 1 Page 54 of 172
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[4]'
COLD SHUTDGWN JUSTIFICATION CS-04 F
' SYSTEMS:
High Pressure Coolant Injection System (2301)
Reactor Core Isolation Cooling System (1301)
VALVES:
2301-7, 1301-50 CATEGORY:
AC CL/sSS-1 FUNCTION:
These valves are the HPCI and RCIC injection pressure isolation check valves.
l TEST REOUIREMENT:
IHV-3521; Test frequency - exercise at least once every three months, quarterly.
1 BASIS _EQR Testing these valves during normal operation would JUSTIFICATION:
require; l) injecting cold water into the reactor vessel using the HPCI (or RCIC) system which would result in both a reactivity excursion and thermal shock to the feedwater nozzle and piping and 2) loss of cne pressure isolation barrier between the high pressure reactor coolant system and low pressure HPCI (or RCIC) System.
These valves are manually stroke testable.
Since a maximum allowable torque on the mechanical test lever of j
120 ft-lbs for Valve 2301-7 and 75 ft-lbs for Valve
-1301-50 is specified by the manufacturer to prevent damage,.the valves can be tested by manual stroking only
~;
if the plant is not in an abnormal cold shutdown valve lineup (no differential pressure across these valves).
During a normal. cold shutdown, the-feedwater header is isolated.-
ALTERNATE TESTING:
Manually exercise during cold shutdown (normal cold-shutdown feedwater valve lineup) not to exceed refueling outage.
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Page 55 of 172 l
[5].
COLD SHUTDOWN JUSTIFICATION CS-05 SYSTEM:
Nuclear Boiler - Reactor Recirculation System (202)
I VALVES:
5A, SB CATEGORY:
B GASS:
1 i
FUNCTION:
.These valves are the reactor recirculation pump discharge valves and-function to close upon LOCA signals.
(This is the remaining function of LPCI Loop Selection Logic.)
l TEST REOUIREMENIS:
IHV-3411; Test Frequency - exercise at least once every U
three months.
i IHV-3412; Power operated valves - full stroke time.
BASIS FOR Closure of these valves during normal operation will JUSTIFICATION:
result in loss of forced circulation to the reactor, a condition prohibited by PNPS License.
E Closure of these valves during cold shutdown necessitates securing operation of the reactor recirculation pumps. This is detrimental because even though the moderator temperature is less than 212'F the i
recirculating system is usually kept in operation during cold shutdown to provide reactor coolant mixing-to prevent ~ reactor vessel temperature. stratification.
The reactor vessel temperature profile takes on an 4
increasing temperature gradient between the bottom vessel head and the shutdown core when mixing (forced i
circulation) is stopped. Additionally the water in the idle recirculation loops cools down.
This stratification can have the following adverse effects:
reactor vessel temperatures'become greater between the'
~ vessel bottom and top resulting in unnecessary thermal
. cycling, startup of the shutdown recirculation pump can cause a cold water intrusion affecting reactor vessel-1
=
metal. temperatures. Deliberate stopping and starting of the recirculation pumps creates unnecessary cycling wear on major equipment important to plant reliability, ALTERNATE TESTING:
Exercise valves during cold-shutdown when a respective s
reactor recirculation pump is not required, but not to exceed a refueling outage.
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Page 56 of 172 1
[6]
00LD SHUTDONN JUSTIFICATION CS-06 SYSTEM:
Nuclear Boiler - Main. Steam, Vent, Drain & Sampling System (220) i VALVES:
46, 47 CATEGORY:
B CLASS:
'l-FUNCTION:
These valves are used to vent the reactor vessel head and main steam-line "A" during startup.
'l TEST REOUIREMENTS:.
IHV-3411; Test Frequency - exercises at least once every three months.
IHV-3413; Power operated valves - full stroke time, IHV-3415; Fail safe - at least once every three months.
m BASIS FOR Exercising one of these valves during normal operation JUSTIFICATION:
leaves the other valve as the only barrier between the reactor vessel and the drywell sump. Any leakage through the closed valve could potentially pressurize the drywell which is an unnecessary risk for the sole purpose of. testing a valve.
Finally, operating procedures prohibit operation of these valves during-
+
power. operation.
ALTERNATE-TESTING:
Exercise valves during cold shutdown (not to exceed-a refueling outage).
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8.I.1.1 Rev. 1 Page 57 of 172
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[7]
COLD SHUTDONN JUSTIFICATION CS-07 SYSTEM:.
High Pressure Coolant Injection System (2301)
VALVES:
232, 233 CATEGORY:
C CLASS:-
2-i FUNCTION:-
These valves provide a vent path to relieve a vacuum created within the HPCI exhaust line after turbine operation.
TEST REOUIREMENT:
'INV-3521; Test Frequency - exercise at least once every l
three months.
BASIS FOR The HPCI Exhaust Vacuum Breaker Line Check Valves shall JUSTIFICATION:-
be forward flow exercised.
These normally closed check valves are verified in the open direction by isolating the vacuum breaker exhaust line and ensuring unrestricted flow.. The vacuum breaker line isolation will make the HPCI system inoperable.
Exercising is to' be performed during cold shutdown.
ALTERNATE TESTING:
Exercise during cold shutdown, i
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r 8.I.1.1 Rev. 1-Page 58 of 172
[8]
COLD SHUTDOWN JUSTIFICATION CS-08 SYSTEM:
Reactor Building Closed Cooling Hater (30)
VALVES:
4085A, 40858 l
' CATEGORY:
B CLASS:
3 FUNCTION:
Valves 4085A and 4085B are the nnn-safety related component isolation valves for RBCCH Loop A.
TEST REOUIREMENIS:
IHV-3411; Test Frequency - exercise at least once every three months.-
IHV-3413; Power operated valves - full stroke time.
. BASIS FOR~
Valves 4085A and 4085B are the non-safety related MSTIFICATION:
component isolation valves for RBCCH Loop A.
Components cooled by'this RBCCH branch include the. reactor recirculation pump motor-generator set fluid coupling oil and bearing coolers.
Stroke testing quarterly during power operation could result in loss of cooling to the recirculation pump motor-generator set fluid coupling oil and bearing coolers-with consequent loss of forced circulation to the reactor, requiring plant shutdown.
. Stroke testing at cold shutdown could result'in loss of the recirculation pump operation due to interruption of cooling to the recirculation pump motor-generator set fluid coupling oil and bearing coolers.
This is 1
~
detrimental because even though the moderator temperature is less than 212*F,-the recirculation system is kept in operation during cold shutdown to provide
- mixing of the reactor coolant to prevent reactor vessel
. temperature stratification..
The reactor vessel temperature profile takes on an i
increasing temperature gradient between the-bottom vessel head and the. core when mixing (forced circulation) is stopped. Additionally.the water in the idle recirculation loops cools down.
This stratification can have the following adverse effects:
reactor vessel metal temperature' differences become greater between reactor vessel bottom and top resulting in unwanted thermal cycling. Start up of the shutdown lm recirculation pumps causes a cold water intrusion which L
affects reactor vessel metal temperatures and causes i
thermal cycling of the reactor vessel.
4 ALIE! PLATE TESTING:
Exercise valves during cold shutdown when reactor recirculation pumps are not required but not to exceed a i
refueling outage.
8.I.1.1 Rev. 1 j
Page 59 of 172
[9]
COLD SHUTDONN JUSTIFICATION CS-09 SYSTEMS:
Residual Heat Removal System (1001)
Core Spray System (1400)
High Pressure Coolant Injection System (2301)
Reactor Core Isolation Cooling System (1301)
J VALVES:
1001-29A,1001-29B,1400-25A,1400-25B, 2301-8,1301-49 CATEGORY:
A CLASS:
1 FUNCTION:
These valves provide pressure isolation from the high pressure reactor coolant system.
TEST REOUIREMENTS:
IWV-3411; Test Frequency - Exercise at least once every three months.
INV-3413; Power operated valves - full stroke time, ESIS FOR These pressure isolation motor operated valves maintain JUSTIFICATION:
one of the two high to low pressure barriers during plant operation. The other pressure isolation barrier
)
is a check valve.
To exercise these valves during. plant i
operation results in a loss of one isolation barrier, Exercising these. motor operated valves quarterly with
'j the Reactor Vessel at pressure significantly increases the occurrence probabilities of an intersystem loss of l
coolant accident, ALTERNATE TESllN(i:.
Exercise valves during cold shutdown.
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8.I.l.1 Rev. 1 Page 60 of 172
4 (10]
COLD SHUTDONN JUSTIFICATION CS-10 SYSTEM:.
Residual Heat Removal System (1001)
VALVE:
64 t
CATEGORY:
AC i;
CLASS:
1 FUNCTION:
This valve provides pressure isolation and a flowpath for head spray (RHR) and fire water emergency source water.
TEST REOUIREMENT:
INV-3521; Test Frequency - exercise at least once every three months, quarterly.
i
- BASIS FOR This normally closed check valve provides reactor coolant 3
JUSTIFICATION:
pressure isolation to protect against overpressurization and an increased occurrence of an intersystem loss of coolant accident. Also, the head spray line motor l
operator valve receives a reactor high pressure 1
isolation signal (less than 100 psig) isolating the head l
spray flowpath. This' check valve will be forward flow l
exercised to verify the open direction during cold shutdown.
ALTERNATE TESTING:
Exercise valve during cold shutdown ('A' RHR loop r
shutdown cooling) not to exceed refueling outage.
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8.I.1.1 Rev. 1 Page 61 of 172 1
[113 COLD SHUTDONN JUSTIFICATION CS-11 SYSTEM:
Reactor Core Isolation Cooling System (1301)
VALVE:
9067 CATEGORY:
C CLASS:
2 FUNCTION:
This valve provides a vent path to relieve a vacuum created within the RCIC exhaust line after turbine operation.
TEST REOUIREMENT:
INV-3521; Test Frequency - exercise at least once every three months.
B& SIS FOR The RCIC turbine line exhaust vacuum breaker check valve JUSTIFICATION:
shall be forward flow exercised.
This normally closed check valve is verified-in the open direction by performing a test that ensures unrestricted flow.
. Performance of this test at power would require isolation of the RCIC turbine for safety reasons. This will make RCIC inoperable during preparation, testing and restoration of this system.
Exercising is to be performed during cold shutdown.
ALTERNATE TESTING:
Exercise valve during cold-shutdown.
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[12)-
COLD SHUTDONN JUSTIFICATION CS-12 t
SYSTEM:
Nuclear Boller - SRV Vacuum Relief (261)
YALVES:
96A, 96B, 96C, 97A, 97B, 97C, 970, 98A, 98B, 98C, 980 CATEGORY:
C CLASS:
NC
)
EMHCTION:
Vacuum breakers ensure that pressure is equalized for the main steam safety relief discharge lines.
{
TEST REQUIREMENT:
INV-3521; Test Frequency - exercise at least once every three months, quarterly.
y BASIS FOR The SRV suppression pool discharge vacuum breakers JUSTIFICATION:
provide a means for relieving the vacuum developed in r
the discharge lines caused by condensing steam. The vacuum breakers are located in the drywell (primary containment) and are normally closed. During power operation; the inerted drywell environment is nnsuitable for. manned entry due to atmosphere and high temperature. The forward flow exercising of these valves can only be verified manually. This method of exercising during power _ operation would have adverse safety and ALARA concerns.
Exercising will-be performed during cold shutdown when the drywell is deinerted.
ALTERNATE TESTINGi~
Exercise valves during cold ;5utdown (when drywell is deinerted) not to exceed a refueling outage.1 l
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8.I.1.1 Rev. 1 Page 63 of 172
[13]
COLD SHUTDONN JUSTIFICATION CS-13 S151EM:
Nuclear Boiler - Compressed Air (31)
VALVES:
372A, 3728, 372C, 372D CATEGORY:
AC l -
CLASS:
lNC g
~ FUNCTION:
These valves provide isolation and allow recharging of the ADS air j
TEST REOUIREMENT:
INV-3521; Test Frequency - exercise at least once every three months, quarterly.
BASIS FOR These check valves with their associated air 4
JUSTIFICATION:.
accumulators are located in the drywell (primary containment) and are not accessible during normal plant operations.
Check Valve forward flow exercising will be accomplished by bleeding air through the air-accumulators.
Therefore, exercising of these check -
I.
valves will be performed during cold shutdown when the L
drywell is deinerted.
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ALTERNATE ~ TESTING:
Exercise valves during cold shutdown (when drywell is deinerted) not to exceed a refueling outage.
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[14]
COLD SHUTDOWN JUSTIFICATION CS-14 SYSTEM:
Salt Service Hater System (29) i VALVES:
3801, 3805 CATEGORY:
B CLASS:
3:
FUNCTION:
These /alves control cooling water flow from the Turbine Building Closea Cooling Hater (TBCCH) heat exchanger, and therefore, the amount of cooling available for TBCCH equipment.
The safety
. function of these valves is to close on LOCA signal in order to direct maximum cooling water flow to the RBCCH heat exchanger.
TEST REOUIREMENTS:
-IHV-3411; Test Frequency - exercise at least once every-three months.
1 INV-3413; Power operated valves - full stroke time.
.lL&SJS_EQR Since critical power generation equipment such as the
.1"CVIFICAllDE:
turbine lube oil coolers, reactor feed pump coolers and generator hydrogen and stator coolers are serviced by TBCCH, a complete stroke closure of the valves would cause a disruption of cooling in the system.
This cooling disruption could lead to power generation equipment damage-and pos:iole plant scram from generator protective functions ALTERNATE TESTING:
Partial strokin; of valves quarterly.
Exercise valves during cold shutdown.
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Page 65 of 172 1,
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[15]
00LD SHUTDONN JUSTIFICATION CS-15 SYSTEM:
High Pressure Coolant Injection System (2301)
VALVE:
218 CATEGORY:-
AC CL815:
2 FUNCTION:
The'HPCI-exhaust drain pot containment isolation check valve allows a drain path for condensate between the exhaust line check valves.
TEST REOUIREMENT:-
IW-3E?l; Test Frequency - exercise at least once every p
three months, quarterly.
MSIS FOR The HPCI Exhaust Drain. Pot Line Check Valve shall be i
JUSTIFICATION:
forward flow exercised. This normally closed check valve is verified in the open direction by isolating a portion of the exhaust drain pot and performing a test o
that ensures flow through the check valve (thru HPCI Exhaust Drain Pot Level increase).. Performance of this test at power would require isolation of the HPCI turbine-for safety reasons. This will make HPCI inoperable during preparation, testing and restoration of this system.- Exercising is to be performed during I
cold shutdown.
ALTERNATE TESTING:
Exercise during cold shutdown.
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8.I.1.1 Rev. 1 Page 66 of 172
4 (16)
COLD SHUTDOM JUSTIFICATION CS d{t SYSTEM:
High Pressure Coolant Injection System (2301)
VALVE:
76-CATEGORY:
C CLASS:
2 EUNCTION:
The HPCI Gland Seal. Condenser Pump Discharge Check Valve allows a flowpath for condensate from the GSC to the HPCI Booster Pump suction.
TEST REOUIREMENT:
INV-3521; Test Frequency -- exercise at least once every three months, quarterly.
BASIS FOR The HPCI GSC Pump Discharge Check Valve shall be forward flow JUSTIFICATION:
exercised. This normally closed check valve is verified in the open direction during performance of a HPCI Valve Cold Shutdown Operability Test. To establish-a temporary hydraulic circuit for valve exercising, the HPCI System must be made inoperable for an extended period of time (approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />). Exercising is to be performed during told shutdown.
1 ALTERNATE TESTING:
Exertise during cold shutdown.
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8 I.l.1 Rev. 1 Page 67 of 172 s
- - - +. -
i 6.4-RELIEF REQUESTS
-Valve Relief Requests (RV) are provided for conditions in which compliance to ASME Code,Section XI Subsection INV, test requirements can not be satisfied.
Each Relief Request identifies:- Valve (s)
-involved, test requirement (s) of non-compliance, basis for relief and alternate. testing.
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- 8. I.'l.1 Rev. 1 Page 68 of 172
+
01]
RELIEF REQUEST RV-01
~ SYSTEM:
Reactor Building Closed Cooling Hater System (30)
VALVE:
'432 CATEGORY:
AC CLASS:-
2 FUNCTION:
This analve provides isolation to drywell components by RBCCH.
The components would require isolation for primary containment
. criteria and maintenance.
TEST REOUIREMENT:
IWV-3521; Test frequency - exercise at least once every three months, quarterly, i
' BASIS FOR RELIEF:
This check valve is the outboard primary containment isolation valve for a system considered inservice during plant operation.
The normally open check valve requires a reverse flow exercise.
Leak testing (per 10CFR50, Appendix J) ensures. valve exercising in the closed direction.
'ALTERNATETESTINGi Exercise valve at least once every two years.
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i 8.I.1.1 Rev. 1 Page 69 of 172
[2]
RELIEF REQUEST RV-02 3,
r L
SYSTEM:
Compressed Air System (31) 4 VALVE:
167 CATEGORY:- -AC CLASS:
2 j
FUNCTION:
This valve is the nitrogen / instrument air to drywell inboard
.i isolation valve for primary containment isolation, i
TEST REOUIREMENT:
INV-3521; Test frequency - exercise at least once every three months, quarterly.
BASIS FOR RELIEF:
This check valve is the inboard primary containment.
i isolation valve for a system considered inservice during plant operation.
The normally open check valve requires a reverse flow exercise.
Leak testing (per 10CFR50, Appendix J) ensures valve exercising in the closed direction..
ALTERNATE TESTING:
. Exercise valve at least once every two years.
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8.I.1.1 Rev. 1 Page 70 of 172 J
-[3]
RELIEF REQUEST RV-03 SYSTEM:
Containment Atmosphere Contro1' System (45)
VALVES:
X-201A X-201E X-201]
l X-201B X-201F X-20lK X-201C X-201G X-2010 X-201H CATEGORY:
AC' CLASS:
2 FUNCTION:
These valves are the pressure suppression chamber to drywell i
vacuum breaker valves which equalize the pressure between the two volumes when the suppression chamber pressure exceeds the drywell pressure.
TEST RE0UIREMENTS:
IHV-3420; Valve Leak Rate Test.
BASIS FOR RELIEF:.
A specific maximum leakage per valve is not applicable i
to the vacuum breaker valve testing. A gross leakage 3
(go/no go) pressure decay test is performed on the pressure suppression chamber atmosphere in accordance with PNPS Technical Specification on a quarterly basis.
1 The INV-3420 valve leak rate test requirements shall be verified by a pressure decay test which identifies a specific leakage rate from the Drywell to the pressure suppression chamber atmosphere in accordance with PNPS Technical Specification on a refueling outage basis.
ALTERNATE TESTING:
Valve leak rate test requirements shall be demonstrated-in accordance with PNPS Technical Specification.
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Page 71 of 172
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[4]
RELIEF REQUEST RV-04 e
- SYSTEMS:'
All Applicable VALVES:
All Applicable CATEGORIES: A,8-CLASSES:
All Applicable FUNCTION:
Not Applicable TEST REOUIREMENT:
INV-3417(a) Corrective Action BASIS FOR RELIEF:
Valves designed to be rapid acting have extremely short stroke times.
Since these valves stroke fast it is difficult to time them accurately and any deviation in trended time could be due to reaction time of the individual performing the testing rather than any change in the valve's performance.
Because of the rapid action of these valves, a two (2) second acceptance limit will be used and stroke times will not be recorded and trended. Valves exceeding the 2 second limit will be declared inoperable.
ALTERNATE TESTING:
Verify that all valves classified as rapid acting have stroke times of less than.two (2) seconds. No stroke time recording or trending will be performed.-
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-[5]
RELIEF REQUEST RV-05 SYSTEM:
Transverse.Incore Probe System (45)
VALVE:
N2 Purge Supply Check CATEGORY:.
AC CLASS:
2 FUNCTION:
This valve serves as the outboard primary containment isolation valve for the TIP purge system.
v TEST REOUIREMENT:
IHV-3521; Test frequency - exercise at least once every three months, quarterly.-
4 BASIS FOR RELIEF:'
This check valve is the primary containment isolation valve fu, a system considered inservice during plant operation. The normally open check valve requires'a-I reverse flow exercise.
Leak testing (per 10CFR50, l
Appendix J) ensures valve exercising in the closed direction.
ALTERNATE TESTING:
Exercise valve at least once:every two years.
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8.I.l.1 Rev. 1 Page 73 of 172
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.[6]
RELIEF REQUEST RV-06 i
SYSTEM:-
_ Core Spray System (1400)
J VALVES:-
9A, 9B CATEGORY:
AC e
CLASS:
1 FUNCTION:
These valves are the Core Spray Injection Pressure Isolation Check Valves.
' TEST REOUIREMENT:
IHV-3521; Test frequency - exercise at least once every three months, quarterly.
BASIS'FOR RELIEF:
Testing these valves during normal operation would require injecting cold water into the reactor vessel using the Core Spray system.
This would result in.both a reactivity excursion and thermal shock to the_ Reactor Vessel and Spray Sparger. Testing these valves during i
cold shutdown could cause a thermal shock to the reactor vessel when the vessel metal temperature is greater than 212*F.
The suppression pool ~is the Core Spray System's-water source.
Injection of suppression pool water into the reactor vessel during cold shutdown results in exceeding the EPRI Hater Chemistry Guidelines which PNPS has adopted to preclude the initiation and propagation of intergranular stress corrosion cracking in reactor J
coolant stainless steel components.
The chemistry of the suppression pool water (typical conductivity of 4-5 umho/cm) does not meet the chemical requirements of the reactor coolant (typical conductivity of 0,15-0.3 umho/cm).
Restart of the reactor is not permitted until the reactor coolant watn chemistry is within the EPRI
-Guidelines.
In addition, the amount of water that is injected into
')
the vessel'during the test of only one of the core' spray injection check valve results in significant vessel level increase'and may cause a' vessel isolation.
This would extend the length of-a shutdown since the only 1
means of water removal from the reactor is via the reactor water cleanup system line to the condenser.
The forward. flow exercise of the injection check valves -
Lwill require reactor vessel level control out of the normal parameter and a bleed and feed of the core spray system to improve water quality prior to testing.
ALTERNATE TESTING:
Exercise valves during refueling outages.
8.I.1.1 Rev. 1 Page 74 of 172 -
[7]
- RELIEF REQUEST RV-07 SYSTEM:
High Pressure Coolant Injection System (2301)
Y6 lye:-
24 (formerly HO-2) 1 CATEGORY:
B CLASS:
2 i
FUNCTION:
-The High Pressure Coolant Injection (HPCI) Turbine Throttle Valve regulates steam to the HPCI turbine in response to changes in the HPCI Pump Flowrate and ramp generator signals.
TEST REOUIREMENT:
IHV-3413; Power operated valves - full stroke time.
BAST.S FOR RELIEF:
During a HPCI Turbine Start, this normally closed throttle valve opens to a position as required to maintain the desired HPCI' Pump Flowrate.
The rate of positioning and number of poppets open are dependent upon varying plant parameters. The throttle valve fails in the closed position upon a trip of the HPCI turbine.
Therefore, the throttle valve timing is variable and will be verified by acceptable HPCI pump and operability testing.
L ALTERNATE TESTING:
HPCI throttle valve stroke timing shall be verified by HPCI. system operability (adequate valve response to system demand inputs).
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8.I.1.1 Rev. 1 Page 75 of 172.
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[8]
RELIEF REQUEST RV-08 SYSTEM:
Standby Liquid Control System (1101)
VALVES:
15, 16 CATEGORIES: C, A/C j
CLASS:
1 i
' FUNCTION:
LThese valves are the SLC injection check valves.
TEST RE0VIREMENT:
IHV-3521; Test frequency - exercise at least once every three months, quarterly.
BASIS FOR RELIEF:
To verify forward flow during normal operation or cold shutdown would require firing a squib valve and injecting water into the reactor vessel using the SLC pumps.
Injecting water during operation could result in adverse plant conditions such as changes in reactivity, power transient, thermal shock induced cracking and possible plant trip.
Injecting water during a cold shutdown can result in cyclical thermal shock-induced.
cracking as cold water enters the reactor vessel which is at an elevated temperature due to decay heat.
Injection of the SLC. system during cold shutdowns using demineralized water requires a lengthy flushing -
operation-to remove boron from the system.
Even after extensive flushing, boron remains present in system dead
. legs. -Scme of this boron propagates into the reactor vessel during injection and is difficult to remove from l
the system. The presence of horon in reactor water impedes the plants ability to' achieve criticality for-plant startup.
--Verify forward flow operability during refueling while' performing the standby _ liquid control system injection 1
test, which requires pumping demineralized water into the reactor vessel after firing at least one squib valve.
' ALTERNATE TESTING:
Exercise valves during each refueling outage.
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8.I.1.1 Rev. 1 Page 76 of 172 l-
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[9]
RELIEF REQUEST RV-09 f
SYSTEM:
con kci Rod Drive Hydraulic System (302)
VALVES:
114,115,126,127 (typical of 145 each) 1 CATEGORIES: B, C j
CLASS:
2 FUNCTION:
These valves are the CRD Discharge Header Check, Accumulator Supply Check, Scram Inlet and Outlet Valves.
-IEST REOUIREMENTS:
IHV-3411; Test' frequency - exercise at least once every three months.
INV-3413; Power operated valves - full stroke time.
IHV-3415; Fail safe - at least once every three months.
[::
IHV-3521; Test frequency - exercise at least once every i
three months.
BASIS FOR RELIEF:
These valves (with the exception of the 115) operate-coincidentally to-rapidly insert control rods and will
- be. tested by SCRAM timing control rod drives in accordance with Technical Specification Section 4.3.
This requires testing of at least 10% of the drives j
every 120 days.
Additionally, 100% of the. drives are tested during each shutdown that is greater than 120 days in duration.
Timing of the SCRAM function will be substituted for individual stroke timing, The Accumulator Supply Check Valves (115) will be verif.ied as. forward. flow exercised by observing that their respective.CRD accumulator fault lights clear j
following restoration from scram time testing.
In 1
addition, this valve is verified closed by securing the CRD pumps and verifying an absence of annunciator-indication or significant local pressure degradation from the HCU Scram Accumulators each refueling outage.
ALTERNATE TESTING:
Scram functional timing in accordance with Plant Tech i
Specs will be used to verify individual valve fail-safe and exercise testing for valves 114, 126, and 127. The Accumulator Supply Check Valves (115)-will be verified i
as forward flow exercised during restoration from Scram Time Testing.
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8.I.1.1 Rev. 1 Page 77 of~172
3 L[10]
RELIEi REQUEST RV-10
~
SYSTEM:
-Control Rod Drive Hydraulic System (302)
VALVES:
138 (typical of 145)
CATEGORY:
C CLASS:-
2 FUNCTION:
These valves are the CRD cooling water check valves.
TEST REOUIREMENT:
INV-3521; Test Frequency-exercise at least once every three months.
BASIS FOR RELIEF:
Failure of these valves to reverse flow exercise would
.l be identified by applying; 1) a notch-out signal which would result in a CR0 double-notch, or 2) a notch-in signal which would-result in a CRD non-notch.
Each 1
partially or fully withdrawn operable control rod shall 1
be exercised one notch at least once each week in accordance with the Technical Specifications.
ALTERNATE TESTING:
Exercise by meeting the surveillance requirements in PNPS Technical-Specification, s
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8.I.1.1 Rev. 1 Page 78 of 172
[11]
RELIEF REQUEST RV-11 i
SYSTEM:.
Nuclear Boiler - Main Steam Isol., ADS & Safety Relief System (203)
VALVES:
.3A, 3B, 3C, 3D CATEGORY:
AC CLASS:
1 t
FUNCTION:
The functions of the Reactor Safety. Relief Values (SRVs) are:
(1) 6 open upon receipt of an auto depressurization signal to blow down reactor (2) act as a primary system relief vahe which can be manually actuated from the control room, and (3) act automatically to relieve reactor pressure at set point.
TEST REOUIREMENTS:
IHV-3411; Test Frequency - exercise at least once every-three months.
IHV-3413; Power operated valves - full stroke time.
IHV-3415; Fail safe - at least once every three months.
BASIS FOR RELIEF:
Rel b f is requested from the Section XI required testing f:equency of once every three months (exercise _and fail 4
safe).
Exercising these valves during normal operation would cause primary system pressure spikes and reactor power fluctuations which could lead to a reactor scram.
'These: valves-are exercised and fail safe tested as specified in Technical Specification by energizing and de-energizing a solenoid which supplies and vents instrument air (power source) to the valve actuator.
l Relief is requested from the stroke timing requirements i
of Section XI. Valve position is verified by observing SRV tailpipe temperatures and acoustic monitors. These methods detect rough valve position by monitoring actual l
SRV steam flow and are not adequate for determining valve. stroke times.
T After past failures of two PNPS relief valves to open during bench testing at an independent laboratory
-(reported to NRC by LER), extensive failure analysis by metalographic examination was. conducted. The exam
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resulted in the following outstanding concern:
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L 8.I.1.1 Rev. 1 Page 79 of 172
[11]
RELIEF REQUEST RV-11 (Continued)
Operating the SRV at low operating pressure (150 psi) increases the potential-for sticking.
This is based on the theory that there is little cushioning effect on the spring force due to reactor system pressure.
This allows the disc to slam ir.to the seat fracturing carbides at the surface.
This gives corrosion more area (crevices) to adhere to, increasing sticking potential.
Testing these relief valves at higher reactor pressures (between 350 and 500 psi) has corrected this problem.
ALTERNATE TESTING:
Exercise and fail safe test valves during refueling outage (adequate pressure available) with stroke times not being measured. The response of these valves will be verified by observing their tailpipe acoustic monitor alarms.
8.I.l.1 Rev. 1 Page 80 of 172
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[12]
RELIEF REQUEST RV-12
' SYSTEM:
Nuclear Boiler - Feedwater System (6)
VALVES:
58A, 588, 62A, 62B j
CATEGORY:
AC-CLASS:
I
-FUNCTION:
These valves serve as the feedwater inlet check valves.
i TEST RE0VIREMENT:
IHV-3421; Test Frequency - exercise at least once every three months.
-BASIS FOR RELIEF:
These check valves are primary containment isolation valves for a system considered inservice-during plant operation.
The normally open check valve requires a reverse flow exercise.
Leak testing (per 10CFR50, Appendix J) ensures valve exercising in the closed direction.
ALTERNATE TESTING:
Exercise valves at least once every two years.
l 8.I.l.1 Rev. 1 Page 81 of 172
[13)
RELIEF REQUEST RV-13 OYSTEM:
Recirculation Pump Seal Water System (201)
YALES:
13A, 138, 17A 178 CATEGORY:
AC CLASS:
2 a
FUNCTION:
These valves serve as the recirculation pump seal water inboard and outboard containment isolation check valves.
TEST REOUIREMENT:
IWV-3521; Test frequency - exercise at least once every three months.
g6 SIS FOR RELIEF:
These check valves are the primary containnent isolation valves for a system considered inservice during plant operation and functionally r,'n-safety related.
These normally open check valves require a reverse flow exercise.
Leak testing (per 10CFR50, Appendix J) ensures valve exercising in the closed direction.
6,LTERNATE TESTING:
Exercise valves at least once every two years.
x 8.I.1.1 Rev. 1 Page 82 of 172
(14)
RELZEF REQUEST RV-14 SYSTEM:
Salt Service Water System (29)
VALVES:
3915, 3925 CATEGORY:
B i
CIASS:
3 FUNCTION:
These valves isolate the service water system from the screen wash system when LOCA occurs.
F TEST REOUIREMENT:
IRV-3412; Power operated valves - full stroke time.
BASIS FOR RELIEF:
When the screen wash pumps are turned off, these valves receive a signal to close.
There are no position indicator lights to show when the valves have closed after the pumps are tripped, therefore, the stroke times cannot be determined.
Proper valve closure is verified by observation of actuator stem position change after the screen wash pumps have tripped, i
ALTERNATE TEST!RG:
Valves stroke times shall not be measured.
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8.1.1.1 Rev. 1 Page 83 of 172
[15)
RELIEF REQUEST RV-15 5151 8 :
Diesel Oil Transfer Systec (38)
VALVES:
4521, 4522 CATEGORY:
B CL6SS:
NC FUNCTION:
These valves open automatically upon initiation of the diesel oil transfer pumps to allow oil to flow into the day tank.
TEST REOUIREMENT:
IWV-3412; Power operated valves - full stroke time.
MSJS FOR RELIEF:
These valves are not equipped with position indicators, therefore, stroke times cannot be obtained. Valve opening is indirectly verified by proper system operation.
ALTERNATE TESTING:
Valve stroke times shall not be measured.
8 I.1.1 Rev. 1 Page 84 of 172
[16)
RELIEF RE0 VEST RV-16 SYSTEM:
Reactor Core Isolation Cooling System (1301)
VALVES:
2 (HYD-1301-159)
CATEGORY:
B CLASS:
2 FUNCTION:
The Reactor Core Isolation Cooling Turbine Governor Valve regulates steam to the RCIC turbine in response to changes in RCIC Pump Flowrate.
TEST REOUIREMENT:
IWV-3413; Power operated valves - full stroke time.
BASIS FOR RELIEF:
During a RCIC Turbine start, this normally open governor valve closes to a position as required to maintain RCIC Pump Flowrate.
The rate of movement and valve position are dependent upon varying plant parameters.
The governor valve fails in the open position upon a trip of the RCIC turbine.
Therefore, the governor _ valve timing is variable and will be verified by acceptable RCIC pump and system operability testing.
ALTERNATE TESTING:
RCIC governor valve stroke timing shall be verified by RCIC system operability (adequate valve response to system demand inputs).
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7 (17)
RELIEF REQUEST RV-17 i
SYSTEM:
Control Rod Drive Hydraulic System (302)
VALVES:
120, 121, 122, 123 (Typical of 145)
CATEGDRY:
B C. LAM:
2 FUNCTION:
Direct Control Rod Drive (CRD) for the insertion and withdrawal of control rods.
TEST REOUIREMENTS:
INV-3411; Test Frequency - exercise at-least once every three months.
INV-3413; Power operated valves - Full stroke time.
INV-3415; Fall safe - at least once every three months.
BASIS FOR RELIEF:
The insertion and withdrawal of control rods is accomplished via positioning of these valves. The CRD Units are integrally constructed components. Notching of control rods causes rapid position changes to these valves. The recording of stroke time (e.g., less than tenth of a second) would only be indication of electrical circuitry delay and human response errors.
Proper insertion / withdrawal by notching shall verify valve operability.
ALTERNATE TESTING:
Verify control rod movement by notching weekly.
8.I.1.1 Rev. 1 Page 86 of 172
[18)
RELIEF REQUEST RV-18 SYSTEM:
Nuclear Boiler - Compressed Air (31)
VALVES:
84A, 840, 84C, 84D, 85A, 858, 85C, 850 CATEGORY:
C CLMS:
NC FUNCTION:
These valves cllow charging of the HSIV Accumulators.
TEST REOUIREMENT:
INV-3522(b); Normal Close Valves exercise procedure, i
BASIS FOR RELIEF:
These check valves are required to supply nitrogen / instrument air to recharge air accumulators during each Main Steam Isolation Valve (MSIV) i full-stroke cycle.
Failure of a check valve to open j
(forward flow exercise) would impede accumulator recharging and prevent the normal opening function of the MSIV.
Therefore, MSIV full-stroke exercise verifies the respective air accumulator check valve forward flow exercise.
ALTERNATE TESTING:
Verify forward flow exercising by MSIV full-stroke valve cycle testing.
8.I.1.1 Rev. 1 Page 87 of 172
(19]
RELIEF REQUEST RV-19 5151f115:
Diesel Generator Air Start System (47)
Diesel Generator Turbo Air System (47)
VALVES:
4586A, 4586B, 4587A, 45878, 458BA, 45888, 4589A, 4589B 4569A, 4569B, 4570A, 4570B CATEGORY:
B j
.CLAS.S:
NC FUNCTION:
These air start solenoid valves provide starting air to the emergency diesel generator.
TEST REOUIREMENTS:
IWV-3411; Test frequency - exercise at least once every three months.
INV-3413; Power operated valves - full stroke time.
IWV-3415; Fail safe - at least once every three months.
BASIS FOR RELIEF:
Valve design does not allow for any valve position indication verification.
During the Diesel Generator Alternate Air Bank Start monthly surveillance, failure of a valve to perform its open function will result in an increase in the starting time.
Also, failure of the valve to close will cause starting air to not secure.
ALTERNATE TESTING:
Valves shall be verified operable during monthly diesel generator Technical Specification surveillance testing.
The starting time will be monitored and trended to determine valve operability.-
8.I.l.1 Rev. 1 Page 88 of 172
(20)
RELIEF REQUEST RV-20 i
SYSTEM:
Residual Heat Removal System (1001)
Core Spray System (1400)
VALVES:
1001-362B, 363A 1400-212A, 212B CATEGORY:
C CMSS:
2 FUNCTION:
These check valves supply the flowpath for keepfill pressurization and makeup.
l TEST REOUIREMENT:
IWV-3521; Test Frequency - exercise at least once every three months, quarterly.
BASIS FOR RELIEF:
These normally closed check valves provide keepfill makeup and pressurization which is required to maintain these systems operable. No method exists to verify forward flow exercise of these valves while they are in service. These valves shall be partially exercised by performance of the keepfill system check (venting procedure) and full exercised in the open direction by filling the system following maintenance or testing during each refueling outage.
In addition, modifications to these systems, planned for RF0 #8, that add test connections, will allow reverse closure testing by flow without disassembly.
ALTERNATE TESTING:
Partial exercise valves quarterly and verify a full forward flow exercise during each refueling outage, not to exceed 2 years.
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1 8 I.1.1 Rev. 1 l
Page 89 of 172
I
[21)
RELIEF REQUEST RV-21 l
SYSTEM:
Reactor Water Cleanup System (1201)
VALVE:
81 CATEGORY:
C CLASS:
1 FUNCTION:
This valve provides the path for RWCU return flow to the reactor vessel.
TEST REOUIREMENI:
INV-3521; Test Frequency - exercise at least once every three months.
BASIS FOR RELIEF:
The reactor water cleanup return check valve shall be reversed flow exercised. This normally open check valve is verified in the closed direction by; isolating the RWCU return header, pressurizing the feedwater header, and venting the piping on the upstream side of this check valve to verify restricted flow. Controlled pressurization of the feedwater header to perform this test occurs during Hydrodynamic Leakage Testing of the RCIC Pressure Isolation Valves each refueling outage.
During cold shutdown conditions, this system is required to be operable in order to control reactor water level and primary system chemistry. Pressurization of the Feedwater Header for Hydrodynamic Leak Testing requires extensive valve alignment to the Feedwater System and renders both the Feedwater and RWCU Systems inoperable for an extended period of time.
ALTERNATE TESTING:
Exercise valve during Hydrodynamic Leak Testing each refueling outage.
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8.I.1.1 Rev. 1 l
Page 90 of 172 L
[22]
RELIEF REQUEST RV-22 SYSTEMS:
Core Spray System (1400)
High Pressure Coolant Injection System (2301)
Reactor Ccre Isolation Cooling System (1301)
Reacter Water Cleanup System (1201)
Recirculation Pump Instrumentation (262)
Nuclear Boiler Instrumentation (261)
Nuclear Boiler Instrumentation (263)
VALVES:
All Applicable CATEGORY:
AC CLASS:
1 FUNCTI0ti:
These excess flow check valves provide primary containment isolation in case of an instrument line break.
TEST REOUIREMENT:
INV-3521; Test Frequency - exercise at least once every three months.
IW-3422; Frequency - test shall be conducted at least once every 2 years.
BASIS FOR RELIEF:
These excess flow check valves are the primary containment isolation valves for systems considered inservice during plant operation.
These normally open instrument isolation check valves require a reverse flow exercise.
Leak testing (per ASME Code) performs valve exercising in the closed direction each refueling outage.
The leak rate testing of excess flow check valves requires the reactor coolant pressure boundary (Class 1) to be at a pressure of at least 600 psig. Testing requires valving out instruments which have a high probability of causing a. safety system function initiation and/or isolation. Therefore, the plant should be shutdown for testing. During plant shutdowns, the reactor coolant pressure boundary is not pressurized except when performing the once-per-refueling outage ASME Boller and Pressure Vessel Code,Section XI System Leakage Pressure Test. The excess flow check valve leak l
testing is conducted during this system leakage pressure l
test.
ALTERNATE TESTING:
Exercise and leak rate valves during each refueling outage.
8.I.1.1 Rev. 1 Page 91 of 172 L
1
[233 RELIEF REQUEST RV-23 5151 2 :
Diesel Oil Transfer System (38)
YALYLS:
116A, 1168 i
CATEGORY:
C CLASS:
NC
[MRCIlQg:
These valves provide the supply path for diesel fuel oil for running the Emergency Site Diesel Generators.
TEST REOUIREMENT:
IWV-3522; Check Valve Full Flow Exercising - exercise at least once every three months.
BASIS FOR RELIEF:
These check valves, located within the day tank, are required to supply fuel oil to each emergency diesel generator.
Failure of a check valve to open (forward flow exercise) would deprive the diesel of fuel.
Inadequate supply of fuel oil would cause the diesel load handling capabilities to be impaired during surveillance testing.
Therefore, proper operatic. of each emergency diesel generator during full load testing verifies the check valve forward flow exercise.
ALTERNATE TESTING:
Emergency diesel operability testing will verify check I
valve forward flow exercise.
i i
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1 i
Page 92 of 172
[24)
RELIEF REQUEST RV-24 SYSTEM:
Residual Heat Removal System (1001)
VALVES:
63, 64 CATEGORIES: A AC CL8SS:
1 FUNCTION:
These valves provide pressure isolation between the Reactor Coolant Pressure Boundary and Low Pressure Head Spray Line. The MO-63 valve also performs a containment isolation function.
TEST REOUIREMENTS:
INV-3422; Frequency - tests shall be conducted at least once every two years.
BASIS FOR RELIEF:
These normally closed valves provide Reactor Coolant Pressure isolation to protect against the possible occurrence of an Intersystem Loss of Coolant Accident.
The MD-63 valve also performs a containment isolation function and is leak tested in accordance with 10CFR Appendix J on a 2-year frequency.
However, pressure l
isolation (LP) leak testing of these valves requires removal of head spray (Class 1) piping for installation i
of a blank flange.
Installation of this flange is normally performed in conjunction with removal of the Drywell head and opening of the Reactor Pressure Vessel each refueling outage.
Pressure isolation leak rate testing for these valves will be performed during this refueling workscope.
i Most cycles provide ample time to meet the 2-year pressure isolation (LP) leakage test frequency.
However, unplanned or extended outages may occur which could extend the time to refuel.
Since this test is l
dependent on refuel activities, the 2-year frequency may t
be exceeded.
ALTERNATE TESTING:
Valve pressure isolation (LP) leak rate test l
requirements shall be demonstrated in accordance with INV-3420 during each refueling outage.
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8.I.1.1 Rev. 1 l
Page 93 of 172
[25)
RELIEF REQUEST RV-25 SYSTEM:
HighPressureCoolantInjectionSystem(2301)
VALVES:
9068A. 9068B CATEGORIES: A CLASS:
2 FUNCTION:
The HPCI exhaust drain pot isolation valves receive an isolation upon HPCI trip and perform a containment isolation function.
TEST REOUIREMENT:
INV-3413; Power operated valves - full stroke time.
BASIS FOR RELIEF:
These solenoid operated valves have no position indicators and are equipped with common (power on) light indication. Their fully enclosed "can" type construction prevents visual stroke movement to be observed locally. Therefore, individual valve stroke times cannot be obtained. Valve closure is verified by performance of local leak rate testing (Appendix J).
Valve opening is verified by normal HPCI operation.
ALTERNATE TESTING:
Valve stroke times shall not be measured.
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8.I.l.1 Rev. 1 Page 94 of 172 J
(26)
RELIEF REQUEST RV-26 SYSTEM:
Control Rod Drive Hydraulic System (302)
VALVES:
21A, 21B, 22A, 228, 23A, 238, 24A, 24B
~
CATEGORY:
B CLASS:
2 FUNCTION:
These valves close to isolate reactor coolant flow past the Control Rod Drive seals during a scram condition.
They open to drain the Scram Discharge Volume Tank and allow a scram condition to be reset.
TEST REOUIREMENT:
INV-3413; Power operated valves - full stroke time (closed)
B& SIS FOR RELIEF:
These air operated valves are stroked closed quarterly using a separate testing air vent (bleed) circuit.
Strokc times using the test circuit are erratic and can even exceed the Tech Spec Acceptance Criteria. Once per refueling outage, in accordance with Tech Specs, a full reactor scram is initiated which utilizes the normal vent circuit for these valves.
The valves are timed in their closed direction using electronic means. Trending these valves in the closed direction is impractical and meaningless because variations in the quarterly test stroke time do not reflect valve degradatim. Valve open stroke times are measured and trended quarterly to monitor for valve degraduilon.
ALTERNATE TESTING:
Measure close stroke times electronically by inserting a full reactor scram during each refueling outage in accordance with Tech Specs.
Perform closed direction stroke time trending following Tech Spec refueling outage testing.
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8.I.1.1 Rev. I 1
Page 95 of 172 i
[27]
RELIEF REQUEST RV-27 SYSTEM:
As Applicable VALVES:
29-AV-A, 29-AV-B 29-AV-C, 29-AV-D, 29-AV-E, 1001-2A, 1001-28, 1001 -2C, 1001 -20, 1001 -68A, 1001 -688, 1301 -27, 1301 -40, 1301 -47, 1301-59,1301-63,1301-89,1301-90,1400-13A 1400-13B, 2301-34, 2301-39, 2301-40, 2301-216, 2301-217 CATEGORY: AC and C CMSS:
1,2,3 and NC FUNCTION: All check valves whose ability to fully open can not be verified without disassembly.
TEST REOUIREMENT:
IWV-3521; Test Frequency - Exercise at least once every three months.
BASIS FOR RELIEF:
These check valves are normally closed and must open to perform their function. System design inhibits the verification of full open position during flow testing due to system configuration or limitations.
These valves will be placed in a check valve disassembly program, complying with the guidelines of Generic Letter 89-04. Other check valves which require a disassembly to verify operability may be incorporated into this program as long as the l
alternate testing guidelines are followed.
' ALTERNATE TESTItG: A sample disassembly and inspection plan which selects one valve in each group to be disassembled every refueling outage will be utilized.
Sample groups may consist of more than 4 valves, however, all valves within each group must be disassembled within a maximum of 4 refueling outages.
The sample disassembly and inspection program involves l
grouping similar valves and testing one valve in each group during each refueling outage. The sampling technique requires that each valve in the group be the same design L,
(manufacturer, size, model number, and materials of l'
construction) and have the same service conditions including valve orientation. During each disassembly, the licensee will verify that the disassembled valve is capable of full-stroking (through manual exercise) and that the internals of the valve are structurally sound (no loose or corroded parts).
A different valve for each group is required to be disassembled, inspected, and manually full-stroke exercised at each successive refueling outage, until the entire group has been tested.
If the disassembled valve is not capable of being full-stroke exercised or there is binding or failure of valve internals, the remaining valves in that group must also be disassembled, inspected, and manually full-stroke exercised during the same outage. Once this is completed, the sequence of disassembly will be repeated unless extension of the interval can be justified.
8.I.1.1 Rev. 1 Page 96 of 172
~ _ _ _ _ _ _ __. _.___. __ _ _.
[283 RELIEF REQUEST RV-28 l
SYSTEM:
As Applicabid VALVES:
Containment Isolation Valves CATEGORY:
AC and C CLAM:
I and 2 FUNCTION:
These valves provide the primary containment isolation barriers to minimize the consequences of an accident.
TEST REOUIREMENT:
INV-3427 (b); Corrective Action For valves 6 in, nominal pipe size and larger, if a leakage rate exceeds the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate by 501,or greater, the test frequency shall be doubled.
BASIS FOR RELIEF:
Local leakage rate test data trending does not provide reliable evidence for predicting future leak rate test failures. Many of these valves are located inside primary containment or high radiation areas.
Misapplication of trended data will result in increased test frequency which places unjustifiable operational constraints upon the plant by requiring extended shutdowns. Also, testing on an increased frequency with questionable basis increases radiation exposure for testing personnel inconsistent with PNPS ALARA l
practices.
Presently te: ting is conducted during refueling outages (not to exceed 2 years) to minimize exposure. The usefulness of the trend data does not justify the burden of Corrective Action Requirements.
Therefore, corrective action per INV-3427(b) will not be l
conducted based on unjustifiable operational constraints l
and ALARA considerations. This position is supported within Generic Letter No. 89-04.
ALTERNATE TESTING:
Containment isolation valves will be replaced or repaired as determined by the licensee or when the leakage rate exceeds that as stated in PNPS Tech Specs l-or INA-3427(a).
8.I.1.1 Rev. 1 l
Page 97 of 172 L
[29]
RELIEF REQUEST RV-29 SYSTEM:
As Listed VALVES:
As Listed CATEGORY:
A, 8 and AC CLASS:
1, 2, 3 and NC FUNCTION:
Power operated valves (POVs) used in safety significant systems in which their reference stroke times are established by the plant site.
IEST REOUIREMENT: INV-3417(a); Corrective Action - for power operated valves.
an increase in stroke time of 257, or more from the previous test for valves with full-stroke times greater than 10 i
seconds or 507, or more for valves with full-stroke times less than or equal to 10 seconds is observed, test frequency shall be increased to once each month until Corrective Action is taken.
BASIS FOR RELILE: 1) Historical stroke time data has shown that establishing an increased test frequency based on the most recent previous stroke time is not the most reliable method for detecting a valve's degraded condition. This method allows for gradual degradation of a valve without requiring corrective action. Determining a reference value based on stroke times when the valve is known to be in good condition and operating properly then measuring deviation from this J
established bench mark will more reliably monitor for valve degradation.
- 2) For POVs (excluding motor operated), recording of fast stroke tints (with reference times between 1 and 5 seconds) can result in deviations greater than 507,(e.g., human error, rounding off pract'ces, normal stroke deviation, and actuator source fluctuation) above the reference stroke time without significant valve degradation. These deviations may occur even though stroke times are recorded to within the nearest tenth of a second (which is far more restrictive than INV).
The inueitsed frequency testing requirement for these specific valves as stated below will account for this condition to minimize unnecessary Corrective Action and excessive valve cycling.
ALTERNATE TESTING:
- 1) Valve stroke times shall be compared against a reference stroke time for IWV 3417(a) Corrective Action implementation.
Reference stroke times will be determined by a PNPS Station Instruction.
- 2) POVs (excluding motor operated) whose reference times are between 1 and 5 seconds shall have their test frequency increased to monthly when their stroke times deviate by greater than [1.5 x reference time plus one half second).
8.I.1.1 hv. 1 Page 98 of 172
(30]
RELIEF REQUEST RV-30 SYSTEMS:
As Applicable VALVES.:
As Applicable CATEGORIES: A. AC CLASSES:
As Applicable FUNCTION:
Valves which are included within a pressure boundary that has a system integrity leakage criteria to ensure satisfactory performance of the system safety function. These system pressure boundaries are inclusive of numerous components / items (i.e..
valves, piping, fittings, accumulators and appurtenances) and therefore, the entire boundary must comply with a specific leakage limit.
TEST REOUIREMENT:
INV-3420; Valve Leak Rate Test BASIS FOR RELIEF:
Seat Leak Testing of valves categorized as "A" or "AC" normally involves a determination of specific leakage for each valve. Where a valve becomes An integral part of a pressure boundary, it no longer singularly maintains the specified leakage limit.
Each component within the pressure boundary must be considered when trying to satisfy the Acceptance Criteria. No one component or multiple components is allowed to leak in excess of the specified leakage limit. The method commonly used to verify leak tightness of a pressure boundary is a Pressure Drop (Decay) Test. The American Society for Non-Destructive Testing (ASNT) provides testing guidance (
Reference:
ASNT Non-Destructive Testing Handbook, Volume 1 Leak Testing) in which the results are equivalent and sometimes superior to Section XI. INV-3420. This testing will be conducted at least once every 2 years.
This relief does not apply to Containment Isolation Valves, Pressure Isolation Valves or other valves that have a component-specific leakage limit.
ALTERNATE TESTIJfS:
Perform Pressure Drop (Decay) Tests in lieu of INV-3420 Valve Leak Rate Tests, utilizing a pressure boundary specified leakage limit.
I l
8.I.l.1 Rev. 1 Page 99 of 172
[313 RELIEF REQUEST RV-31 SYSTEM:
H /0 Analyzer System (5065) 2 2 VALVES:
5117A, 51178, 5137A, 51378 CATEGORY:
B CLASS:
2 FUNCTION:
These valves open automatically during operation of the H /02 2
Analyzer to supply reagent gases for gas concentration analysis.
TEST REQUIREMENT:
INV-3412; Power operated valves - full stroke time.
j BASIS FOR RELIEF:
These solenoid valves are not equipped with position indicators, therefore, stroke times cannot be obtained.
Valve cycling is verified by proper system operation during surveillance testing per PNPS Technical l
Specification requirements for H /02 Analyzer System.
2 During system testing, placing the analyzer function selector switch to the zero position (i.e., flowmeter shows a downward deflection) and then to the span position (i.e., flowmeter shows an upscale movement with alarm actuation) indicates that the valves have properly cycled.
ALTERNATE TESTING:
Valve stroke times shall not be measured.
1 1
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l 8.I.1.1 Rev. 1 Page 100 of 172
6.5 VALVE PROGRAM TABLE This table, identifies the scope of valves within the ISTP and allows cross-referencing specific valve test requirements to their implementing station procedure.
[1] Valve Test Inder System E&lQ Revision Eagg Salt Service Water (29)
M-212 E20 103 Reactor Building Closed Cooling H-215 E24 105 Water (30)
Diesel Generator Air Start System (47)
M-219 E5 107 Compressed Air (31)
H-220 109 Sh 1 of 2 E24 Diesel Oil Transfer (38)
M-223 E5 110 Containment Atmosphere Control M-227
.111 (45 & 9)
Sh 1 of 2 E28 Sh 2 of 2 E13 Compressed Air (31)
M-227 119 Sh 1 of 2 E28 Nitrogen Supply (9)
H-227 120 Sh 2 of 2 E13 Radwaste Collection (20)
H-232 E12 121 Post Accident Sampling & Hydrogen M-239 122 r
And Oxygen Analyzer System (5065)
Sh 1 of 3 E8 Sh 2 of 3 E7 Residual Heat Removal System (1001)
M-241 -
130 Sh 1 of 3 E32 Sh 2 of 3 E17 Core Spray System (1400)
H-242 E16 137 High Pressure Coolant Injection H-243 139 (2301)
Sh 1 EIS H-244 Sh 2 E13 Reactor Core Cooling System (1301)
H-245 143 Sh 1 E13 M-246-Sh 2 E12 8.t.1.1 Rev. 1 Pag 9101 of 172 -
p 6.5 VALVES TESTED (Continued)
System 13dL Revision P_aae m.
Reactor Water Cleanup System (1201)
M-247 E22 147 Standby Liquid Control System (1101)
M-249 E12 148 i
Control Rod Drive Hydraulic M-250 149 i
System (302)
Sh 1 of 2 E18 Sh 2 of 2 E5 Recirc Pump Instrumentation (262)
M-251 E4 152 1
Feedwater System (6)
M-252 E17 153 Reactor Recirculation System (202)
M-252 E17 154 Main Steam Isol. ADS & Safety M-252 E17 155 Relief (203)
Nuclear Boiler System (220)
H-252 E17 158 i
Compressed Air (31)
M-252 E17 159 Nuclear Boiler (261)
M-252 E17 161 Nuclear Boiler Vessel H-253 165 l
l, Instrumentation (263)
Sh 1 of 2 E17 Sh 2 of 2 E12 H
Diesel Generator Turbo Air Assist H-259 E0 169 i
L System'(47)
I L
l~
Traverse Incore Probe (45)
MIQ-1-5 El 171 1
Standby Gas Treatment System (48)
M-294 E11 172 1
j i
The drawing revision level will require changing if:
1)-
The revision affects information within the program table y
gg 2)
A formal review of the program is performed against the latest i
- revision, i
I l
8 I.1.1 Rev. 1 Page 102 of 172 l
'b.
r
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION-P&IDi M-212 SYSTEM: SALT SERVICE WATER (29)
V.d ve P&ID-ISI Valvo. Valve Valve Actuator Nomal '
Test Test FNPS Proc.
Test Relief
. Number Coor Class Cat
' Sire Twoe ' Twee Position Ramt.
Free Nes6er Direction Request Notes 3800 G-8 3
B 18 BF MO-0 FE Q
8.5.3.11 ST Q
8.5.3.11 0
PI 2Y 8.5.3.11 3801 G-7 3
8 12 BF M0 O
PE Q
8.5.3.11:
FE CS 8.I.11.14 CS-14 ST CS 8.I.11.14 C
C5-14 PI 2Y 8.I.11.14 3805 G-6 3
8 12 BF M0 O
PE Q
8.5.3.11 FE CS 8.I.11.14 CS-14 ST CS 8.I.11.14 C
B 18 BF MO O
FE Q
8.5.3.11 ST Q
8.5.3.11 0
B 12 BF MO O
FE Q
8.5.3.11 ST Q
8.5.3.11 0/C PI ZY 8.5.3.11 3813 C-6 3
B 12 BF MO O
FE Q
8.5.3.11 ST Q
8.5.3.11 O/C PI 2Y 8.5.3.11 3915 D-4 3
8 6
BF A0 0
FE Q
8.5.3.11 ST Q
NA w-14 FS O
8.5.3.11 C
3925 C-4 3
B 6
BF A0 0
FE Q
8.5.3.11 ST Q
NA W-14 FS O
8.5.3.11 C
3850A C-7 3
C 12 CK SA 0
FC Q
8.5.3.2 RF AP RD 8.5.3.13*
Open 3880B C-8 3
C 12 CK SA 0
FC Q
Open 3880C C-6 3
C 12 CK SA 0
FC Q
8.5.3.2 RF AP RD 8.5.3.13*
Open 38800 C-6 3
C 12 CK SA 0
FC Q
8.5.3.2 RF AP 20 8.5.3.13*
Open 3880E C-5 3
C 12 CK SA 0
FC Q
8.5.3.2 RF AP 20 8.5.3.13*
Open 8.I.1.1 Rev. 1 Page 103 of 172
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=
TABLE INSERVICE VALVE TESTIteG PROGRAN ISI CLASS 1. 2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION
'P&ID: M-212 SYSTEM:. SALT SERVICE WATER (29)
Valve P&ID -ISI Valve Valve Valve Actuator _.
Normal Test Test PNPS Proc.
-Test Relief Number Coor Class Cat-Sire Twoe Tvoc
'osition Rasrt.
Frea 84suber Direction Reauest Notes AV-A C-7 3
C 2
CK -
SA -
C PC Q
8.5.3.2 FF FC RD 8.I.27' FF RW-27 Disassemble To AP RD 8.5.3.2 C1csed Emercise AV-8 C-8 3
C
-2 CK SA C
PC Q
8.5.3.2 FF FC NO 8.I.27' FF RV-27 Disassendple To AP RO 8.5.3.2 Closed Emercise AV-C C-7 3
C 2
CK SA C
PC Q
FF RV-27 Disassemble To AP RO 8.5.3.2 Closed Esercise AV-D C-6 3
C 2
CK SA C
PC Q
8.5.3.2 FF FC 10 8.I.27*
FF RW-27 Disassemble To AP RD 8.5.3.2 Closed Esercise AV-E C-5' 3
C 2
CK SA C
PC Q
8.5.3.2 FF FC ND 8.I.27*
FF RV-27 Disassea61e To AP RO 8.5.3.2 Closed Exercise 8.I.1.1 Rev. 1 Page 104 of 172 n
TABLE INS 0tVICE MLVE TESTING PROGRM ISI CLASS 1. 2, 3 AND NC MLVES '
PILGRIM IRICLFAR POWER STATION
~
PEID: M-215 SYSTEM: REACTOR BUILDING CLOSEB CDOLING MTER (39) '-
Valve P&ID ISI Valve. Valve. Valve Actuator
.. Normal Test Test : PNPS Proc.
Test Relief Number Coor Class Cat
' Size Tvoe Tvoe -
Position Rant.
Frea lhaber-Direction Request Notes 419 G-3 3
C 8
'CK SA 0
FC Q.
8.5.3.1 RF AP Rn 8.5.3.12*
Open 420 G-3 3
C 8
CK SA 0
FC Q
Open 421 F-3 3
C 8
CK SA 0
FC Q
Open 422 G-5 3
'C 8
CK SA 0
FC
.Q 8.5.3.1 RF AP a0 -
8.5.3.12*
Open 423 G-5 3
.. C S
CK SA 0-FC Q
Open 424 F-5 3
C 8
CK SA 0
FC Q
8.5.3.1 RF AP RD 8.5.3.12*
Open 432 C-6 2
AC 6
CK SA 0
FC R4 8.7.1.5 RF RV-01 LJ ZY 8.7.1.5 RV-28 4002 C-4 2
A 6
GA MO O-FE CS 8.I.11.13 CS-01 Note 1 ST CS 8.I.11.13 C
CS-01 Note 1 PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 RV-28 4039A D-6 3
8 8
GA MO O
FE CS 8.I.11.13 CS-01 Note 1 ST CS 8.I.11.13 C
CS-01 Note 1 PI 2Y 8.I.11.13 4009B C-4 3
B 8
GA MO O
FE CS 8.I.11.13 CS-01 Note 1 ST CS 8.I.11.13 C
CS-01 Note 1 PI 2Y 8.I.11.13 4010A G-7 3
B 12.
GA M0 C
FE Q
8.5.3.10 ST Q
8.5.3.10 0
PI 2Y 8.5.3.10 40108 H-7 3
8 12 GA-MO-C FE Q
8.5.3.10 ST Q
8.5.3.10 0
PI 2Y.
8.5.3.10
~
4020 D-1 3
C 0.75 RL SA C
RT SY-8.I.26*
4031 D-1 3
C 3
RL SA C
RT SY 8.I.26' 4032 H-7 3'
C 3
RL SA C
RT SY 8.I.26*
4036 H-7 3
C 0.75 RL SA C
RT SY 8.I.26*
NOTE 1: When core flow from recirculation pump operation is not required.
8.I.1.1 Rev. 1 Page 105 of 172
~.,
.9 TABLE INSERVICE MLVE TESTING PROGRful ISI CLASS 1, 2, 3 AIS NC MLVES _
PILERIM IRfCLEAR P(hfER STATISE PSIO: - M-215 SYSTER: REACTOR SUILDING CLOSED COOLING W TER (30)
V31ve P&ID ISI Valve Valve ' Valve Actuator Normal Test Test PNPS Proc..
Test Relief Number Coor Class Cat Size Type Twoe Position ' Rastt.
Free Number Direction Reauest Notes 4060A C-2 3
8 12 GA M0 C
FE Q
8.5.3.10 ST Q
8.5.3.10 0
PI 2Y 8.5.3.10 4060B D-2 3
8 12 GA MD C
FE Q
8.5.3.10 ST Q
8.5.3.10 0
PI 2Y 8.5.3.10 4065
.B-2 3
8 6
GA 90 0
FE Q
8.5.3.10 ST Q
8.5.3.10' C
PI 2Y 8.5.3.10 4083 E-4 3
8 10 BF M0 O
FE Q ~
8.5.3.10 ST Q
8.5.3.10 C
PI 2Y 8.5.3.10 4084 F-4 3
B 10 BF MO 0
FE Q
8.5.3.10 ST Q
8.5.3.10 C
PI 2Y 8.5.3.10 4085A E-2 3
B 8
GA MO O
FE CS 8.I.11.13 CS-08 Note 1 ST CS 8.I.11.13 C
CS-08 Note 1 PI 2Y 8.I.11.13 40858 D-3 3
B 8
GA MO O
FE CS 8.I.11.13 CS-08 Note 1 ST CS 8.I.11.13 C
CS-08 Note 1 PI 2Y 8.I.11.13 Note 1: Een core flow from recirculation pump operation is not required.
L 8.I.1.1 Rev. 1 Page 106 of 172 s
TABLE
-IstSUtVICE VALVE TESTING PROGNan
' ISI C1 ASS 1, 2J 3 AIS IIC VALVES PILGRIM IRICLEAR POW 0t STATIOlt
'PEID: M-219 SYSTEM: DIESEL GDIERATOR AIR START SYSTEM (47)
Valve.P&ID ISI Valve.Yalve Valve Actuator Nomal Test Test FMPS Proc.
Test Relief hanbar - Coor Class Cat Sire' Tvoe Tvoe Position Ret.
Free Number Direction Request Notes 101A G-7 IIC AC 0.75~
CK SA C
FC Q
8.9.1 FF LX 2Y 8.9.1.2*
RW-30 1018 D-7 NC AC 0.75 CK SA C
FC
.Q 8.9.1 FF t.X 2Y 8.9.1.2*
RV-30 a
FC Q
8.9.1 FF LX 2Y 8.9.1.2*
RV-30 101D B-7 NC AC 0.75 CK SA -
C FC Q
8.9.1 FF LX 2Y 8.9.1.2*
RV-30 102A F-6 IIC AC
~ 0.75 GA m
C FE IIA Ith LX 2Y 8.9.1.2*
RV-30 1028 C-6 NC AC 0.75 GA M4 C
FE M4 II4 LX 2Y 8.9.1.2*
RW-30 102C E-6 NC.
AC 0.75 GA m
C FE IIL IIA LX 2Y 8.9.1.2*
RV-30 102D A-6 NC AC 0.75 GA m
C FE 80 4 10 4 LX 2Y 8.9.1.2*
RV-30 4582A H-6 NC AC 0.75 SV SA C
RT SY 8.I.26' LX IIA 8.I.26*
RT Verifies 45828 D-6 IIC AC 0.75 SV SA C
RT SY 8.I.26*
LX IIA 8.I.26' RT Verifies 4582C F NC AC 0.75 SV SA C
RT SY 8.I.26*
l LX IIA S.I.26*
RT Verifies 45829 C-6 ftC AC 0.75-SV SA C
RT SY 8.I.26*
LX 10 4 8.I.26*
RT Verifies 8.I.l.1 Rev. 1 Page 107 of 172
-TABLE.
INSatVICE VALVE TESTING PROGRAR ISI CLASS 1, 2, 3 AfS NC VALVES
. PILGRIN IRfCLEAR POWER STATION P&ID: M-219 -
SYSTEM: DIESEL GUIERATOR AIR START SYSTEM (47) ~
Valve ~P&ID ISI Valve Valve Valve ' Actuator Normal Test-Test-PNPS Proc.
Test Relief Number Coor Class Cat Sire Tvoe Tvoe Positiort Ret.
Frea Number Direction Recuest Notes 4586A'.H-4 NC B
1.5 GA S0 C
FE Q
8.9.1 W-19~
ST Q
NA W -19 FS O
8.9.1 C
W-]9 45868 H-4 NC B
1.5 GA 50 C
FE Q
8.9.1 RW-19 ST '
Q-E RV-19 FS O
8.9.1 C
RW-19 4587A E-4 NC B
1.5 GA 50 C
-Q 8.9.1 RV-19 ST Q
NA RV-19 FS O
8.9.1 C
RV-19 4587B E-4 NC
-B 1.5 GA 50 C
FE Q
8.9.1 W-19 ST Q
NA W-19 FS O
8.9.1
'C W-19 4588A E-4 NC B
1.5 GA SO C
FE Q
8.9.1 W-19 i
-Q NA N 19 FS O
8.9.1 C
RV -19_
4588B D-4 NC B
1.5 GA 50 C
FE Q
8.9.1 RV-19 ST Q
NA RV-19 FS O
8.9.1 C
RV-19 4589A B-4 NC B
1.5 GA SO C
FE Q
8.9.1 RV-19 ST Q
NA RV-19 FS O
8.9.1 C
RV-19 45898 B-4 NC B-1.5 GA SO -
C FE Q
8.9.1 RV-19 ST Q
NA RV-19 FS 0
8.9.1 C
RW-19 I
8.I.1.1 Rev.- 1 Page 108 of 172
~
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P l q g
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R R R
8 'i C
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M i
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T c
S t e Y
s r F
S ei R
T D MS AEN c
R VO o
GLI r
55 OAT P r R VA e1 1 P
T Sd CS P
77 GN u
I N
R F I 88 l
t a LT 3 s e OY B
,R e r R2 AE A
T F T V 2E L
L A
,C V1 U N
t t ES s
e CJ CSM e
F L I AI T R VL R R CG E
L n
S I I o
NS P l i I I at mi r s 0
o o N P ro t
a u e t o c w A
AT S
ev e l e a w K
VT C
ev e l z ai 3
VS e
v l t 1
2 a a C
VC A fo 1
ss T
I a E
S l E
I C 2 H
S D r 0
I o 3 2
& c -
2 P C D
-M er v e 7 D
l b 6 I
a m 1 V u P
N
)
83 s
(
e t
R o
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F 1
S 2
N
. 7 A
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t 1
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5 1
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n o
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d d
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S t e s
s Y
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F T
F S
ei F l F l F
F F
F 0
0 T D C
C MS A E N c
R VO o
GL I r
OA T P r 1 1 1 1 1
1 1
1 1
1 R V A e
1 P
T Sb 1
1 1 1
1 1
1 1 A 1 1 A 1
C S P m 99 99 9
9 9 9 9.N 9 9. N 9 GN N m N
R P 9 88 88 8
8 8
8 8 8
8 8
E E~
P t a L T 3 s e Q0 QD 0
0 O O QQ0 QQO B
R er 3
R AE., A T F T V2E L
L A. C V1 JR t t
(,,
f ES s n CP CP C C C C LT S E T S C S M e a F A F A F
F F
F F S F F SF I AI T R
'y,
VL R RCG E
L n
SI I o
y.
NS P l i I I at mi r s C~
C C C C
C C
C o o NP ro t
aue
~
t o c v A
A AT S
S
? A A
A 0
0 S S S
A A
ev y l r a v K K
K K
K K
L L
VT C'
C C
C C C
B E
e v e 5
5 l r 5
5 7
7 5
s.
ai vS 2
2 1
1 0 0
1 1
e v
l t a a VC C
C C C C C B
B s
s I a Sl C
C C C C C C
I I C K
I N
N N N N
N D r 3
I o 7
7 5
5 4 4 5
5 2
& o 2
P C F
D F
E-G E-G E
-M e r A' 8
A 8 A 8 1 2
v e 1
1 5 5 6 6 2 2
D l b 0
0 0 0 1 1 5 5
I a m 1
V u 1
1 1 1 1 4 4
P N
5 4
_ TABLE -:
~
INSERVICE VALVE TESTING PROGRAM ISI-CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION
~P&ID: M-227 SHEET 1 of 2 SYSTEM: CONTAINMENT ATMDSPHERE CONTROL P&ID: M-227 SHEET 2 of 2 SYSTEM NUPEERS 45 & 9 -
Valve P&ID 13I Valve Valve Valve Actuator.
Normal.-
-Test
' Test-PNPS Proc.
Test Relief Number Coor Class ~ Cat Size 'Tvoe Tvoe Position ~ Ret.
Frec Humber Direction Recuest Notes 102
-C-6 2
A 1
GL'
~ fu C
FE.
NA NA-Passive (Manual)
(45)
(SH.1)
LJ 2Y 8.7.1.5 103 C-6
?
A l'
GL f%
-C FE-NA NA Passive (Manual)
(45) tSH.11 LJ 2Y-8.7.1.5 104 C-6 2
A 1-
. GL
-fu C
'NA
~ NA Passive (Manual)
(45)
(SH.1)
LJ 2Y 8.7.1.5' 105 C-6 2
A 1
-- GL MA-C FE NA NA Passive snanval)
(45)
(SH.1)
LJ 2Y
-8.7.1.5 106 E-5 2
. A 4
GA MA C
FE NA NA Passive (Manual)
(45)
(SH.1)
LJ 2Y 8.7.1.5 SA C
FC '
Q 8.A.1 FF X-201A C-7 2
AC 18 CK.
(45)
(SH.1)
(Testable).
PI 2Y 8.7.1.9 Also 8.I.30 LX RO 8.A.2 RV-03 8
CK SA C
'FC Q
8.A.1 FF X-201B C-7 2
AC 1
(45)
(SH.1)
(Testable)
PI 2Y 8.7.1.9 Also 3.I.30 LX RO
'8.A.2 RV-03 X-201C C-7 2
FC Q
8.A.1
'FF (45)
(SH.1)
(Testable)
PI 2Y 8.7.1.9 Also 8.I.20 LX RO 8.A.2 RV-03 X-201D C-7 2
'18 CK SA C
FC Q
8.A.1 FF (45) (SH.1)
(Testable)
PI 2Y 8.7.1.9 Also 8.I.30 LX RO 8.A.2 RV-03 X-201E C-7 2
FC Q
8.A.1 FF (45) (SH.1)
(T table)
PI 2Y 8.7.1.9 Also 8.I.30 LX RO 8.A.2 RV-03 8.I.1.1 Rev. 1 Page 111 of 172
--. ~...
..c
.-n
- - - - ~ - ~.-.
--.. ~ - - - - - - - -
- -.. ~~
e
-TABLE-
~
r INSERVICE VALVE TESTING PROGRAM ISI CLASS 1. 2,' 3 AND NC VALVES PILGRIM PRJCLEAR POWER. STATION P&ID: ~M-227 SHEET 1 of 2 SYSTEM: CONTAINMENT ATMOSPHERE CONTROL
-P&ID: M-227 SHEET 2 of 2 SYSTEM NUMBERS 45 & 9 Valve P&ID ISI Valve Valve Valve Actuator Normal
~ Test Test PNPS Proc.
Test Relief Number Coor Class Cat
-Sire Tvoe Tvoe Position Rtzet.
Frea Number Direction Reauest Notes X-201F C-7 2
FC
- Q 8.A.1 FF (45) (SH.1)
(Testable)
PI.
2Y 8.7.1.9 Also 8.I.30 LX RO 8.A.2 RV-43 X-201G C-7 2
AC 18
~ CK SA' C
FC Q
8.A.1 FF (45)
(SH.1)
(Testable)
PI 2Y 8.7.1.9 Also 8.I.30 LX RD 8.A.2 RV-03 X-201H C-7 2
FC
.Q 8.A.1 FF (45)
(SH.1)
- (Testable).
PI 2Y 8.7.1.9 Also 8.I.30 LX
'RD
'8.A.2 RV-03 X-201J C-7 2
FC Q
8.A.1 FF (45)
(SH.1)
(Testable)
PI 2Y 8.7.1.9 Also 8.I.30 LX RO 8.A.2 RV-03 X-201K C-7 2
AC 18 CK -
SA C
. FC Q
8.A.1 FF (45)
(SH.1)
(Testable)
PI 2Y 8.7.1.9 Also 8.I.30 LX RO 8.A.2 RV-03 X-212A A-8 2
FC Q
8.7.4.9 FF (45)
(SH.1)
PI 2Y 8.7.1.5 LJ
-2Y 8.7.1.5 RV-28 X-212B A-7 2
AC-20 CK SA C
. FC Q
8.7.4.9 FF (45)
(SH.1)
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 RV-28 8.I.1.1 Rev. 1 Page 112 of 172
~.-
--r.
-. -..,, - ~. -
. TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC n VES PILGRIM NUCLEAR POWER STATION P&ID: M-227 SHEET 1 of 2 SYSTEM: CONTAINMENT ATMOSPHERE CONTROL P&ID: M-227 SHEET 2 of 2 =
SYSTEM NUMBERS 45 & 9 Valve P&ID ISI Valve Valve : Valve Actuator Normal Test Test PNPS Proc.
Test Relief Number Coor Class Cat 5 re Tvoe Tvoe Posi tion Rtznt..Frea Iluu6er Direction Request Notes 5025 E-8 2
A 8
BF A0 C
FE E
E Passive (45)
(SH.1)
ST m
M (De-Energized)
FS m
M PI M
M LJ 2Y 8.7.1.5 RV-28' 5033A D-7 2
A 1
GL A0 C
FE Q
8.7.4.2 (9)
(SH.2)
-Q 8.7.4.2 C
FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 5033B C-6 2
A 4
GA A0 C
FE Q
8.7.4.2 (9)
(SH.2)
ST Q
8.7.4.2 C
FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 LJ 5.Y 8.7.1.5 5033C D-6 2
A 1
GL A0 C
FE Q
8.7.4.2 (9)
(SH.2)
ST Q
8.7.4.2 C
FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 5035A E-3 2
A 8
BF A0 C
FE Q
8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 C
FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 LJ 7Y 8.7.1.5 RV-28 50358 E-2 2
A 8
BF A0 C
FE Q
8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 C
FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 RV-28 8.I.1.1 Rev. 1 Page 113 of 172
~.
s TABLE INSERVICE VALVE TESTING FROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-227 SHEET 1 of 2 SYSTEM: CONTAINMENT ATMOSPHERE CONTROL
'P&ID: M-227 SHEET 2 of 2 SYSTEM NUMBERS 45 & 9 Valve P&ID ISI Valve ' ' Valve Valve Actuator Normal Test Test PNPS Proc.
Test Relief Number Coor Class Cat Size Type Tvoe-Position Rant.
Frea Nisber Direction Recuest Notes 5036A C-3 2
A 8-BF A0 C
FE Q
8.7.4.2 -
(45)
(SH.1)
ST Q
8.7.4.2 C
FS Q
8.7.4.2 C
PI 2Y 8,7.1.5 LJ 2Y
'8.7.1.5 RV-28 50368 C-2 2
A 8
BF A0 C
FE Q
8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 C
FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 RV-28 5040A B-8 2
A 20 BF A0 C
FE Q
8.7.4.9 (45)
(SH.1)
ST Q
8.7.4.9 O/C FS Q
8.7.4.9 0
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 RV-28 5040B B-7 2
A 20 BF A0 C
FE Q
8.7.4.9 (45)
(SH.1)
ST Q
8.7.4.9 O/C FS Q
8.7.4.9 0
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 RV-28 5041A C-8 2
A 2
GL A0 C
FE Q
8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 C
FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 5041B C-8 2
A 2
GL A0 C
FE Q
8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 C
FS Q
8.7.4.2 C
- 2Y 8.7.1.5 LJ 2Y 8.7.1.5 8.I.i.1 Rev. 1 Page 114 of 172
2-
. TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1.'2. 3 ANJ NC. VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-227 SHEET 1 of 2 SYSTEM: CONTAINMENT ATMOSPHERE CONTROL P&ID: M-227 SHEET 2 of 2 SYSTEM NUMBERS 45 & 9
. Valve P&ID ISI Valve Valve Valve Actuator Normal' Test Test PNPS Proc.
Test Relief Number Coc-Class Cat Sire Tvoe Tvoe Position R: pet.
Freo Number '
Direction Recuest Notes-5042A D-8 2
A 8
BF A0
.C FE,
Q 8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 C
FS Q
8.7.4.2 C.
PI ZY 8.7.1.5 LJ ZY 8.7.1.5 RY-28 5042B D 2 A
8..
BF A0 C
FE Q
8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 C
FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 RV-28 5043A E-7 2
A 2
GL A0 C
FE Q
8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 C
FS Q
8.7.4.2 C
' PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 50438 E-7 2
A 2
GL A0 C
FE Q
8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 C
FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 5044A F-7 2
A 8
BF A0 C
FE Q
8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 C
FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 RV-28 50448 F-7 2
A 8
BF A0 C
FE Q
8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 C
FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 RV-28 8.I.1.1 Rev. 1 Page 115 of 172
.w.
.s
- TABLE-
- 1 TVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES
. PILGRIM NUCLEAR POWER STATION
'P&ID: M-227 SHEET;1 of 2
~
SYSTEM: CONTAINMENT ATNJSPHERE CONTROL P&ID: M-227 SHEET 2 of 2 SYSTEM NUMBERS 45 & 9-Vslve - P&IDL ISI Valve Valve - Valve Actuator--
Normal-Test
' Test PNPS Proc.
Test Relief Number Coor ' Class -Cat Sire Tvoe Type-Position Rant.
Frea-h'er Direction ~ Request Notes 5081A G-6 2
A 1
GA SO C
FE Q
8.7.4.2 (45)- (SH.1)
ST Q.
8.7.4.2 O/C W-04 FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 Also 8.7.4 LJ 2Y 8.7.1.5 50818 G-6 2
A-1 GA.
50 C-FE
.Q 8.7.4.2 (45)
(SH.1)
- Q 8.7.4.2 O/C RV-04 FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 Also 8.7.4 LJ 2Y 8.7.1.5 5082A G-6 2
A 1
GA S0 -'
C FE Q
8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 O/C RV-04 FS
.Q 8.7.4.2 C
PI 2Y 8.7.1.5 Also 8.7.4 LJ 2Y 8.7.1.5 50829 G-6 2
A 1
GA 50 C.
FE Q
8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 0/C RV-04 FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 Also 8.7.4 LJ 2Y 8.7.1.5 5083A G-7 2
A 1
. GA -
50 C
FE Q
8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2-0/C RV-04 FS ~
Q 8.7.4.2 C
PI 2Y 8.7.1.5 Also 8.7.4 LJ 2Y 8.7.1.5 50838 G-7 2
A 1
GA SO C
-Q 8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 0/C RV-04 FS Q-8.7.4.2 C
PI 2Y 8.7.1.5 Also 8.7.4 LJ 2Y 8.7.1.5 8.I.1.1 Rev. 1 Page 116 of 172
.... ~ ~
- + -. -.
....,.n.
J-
~
^
'^
-; : : TABLE -
LINSERVICE VALVE-TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES c
PILGRIM NUCLEAR POWER STATION P&ID: M-227 SHEET 1 of 2--
SYSTEM: CONTAINMENT ATMOSPHERE CONTROL
.P&ID: M-227 SHEET 2 of 2 SYSTEM N M ERS 45 & 9 Valve P&ID ISI Valve Valve ~ Valve Actuator
~ Normal Test
-Test' FNPS Proc.
Test Relief Number Coor Class ' Cat Size-Tvoe-Tvoe Position-Rant.
Frea number Direction Recuest
-Notes 5084A H 2 A
-1 GA
. 50 -
C
- FE
.Q:
8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 0/C RV-04 FS Q
6.7.4.2 C
PI 2Y 8.7.1.5 Also 8.7.4 LJ 2Y 8.7.1.5 50848 H-7 2
A
-1
. GA S0 C
FE Q
8.7.4.2 (45).(SH.1)
_8.7.4.2 0/C RV-04
- FS
_Q 8.7.4.2 C
PI -
2Y 8.7.1.5 Also 8.7.4 LJ 2Y 8.7.1.5 5085A E-7 2
A 1
GA 50 C
FE Q
8.7.4.2 (9)
(SH.2)
ST-Q-
8.7.4.2 0/C RY-04 FS
.C 8.7.4.2 C
- 2Y 8.7.1.5 Also 8.7.4 LJ 2Y 8.7.1.5 5085B D-7 2
A 1
GA-50 '
C FE Q
8.7.4.2 (9)
(SH.2)
ST Q
8.7.4.2 0/C RV-04 FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 Also 8.7.4 LJ 2Y 8.7.1.5 5086A E-7 2
A 1
GA 50 C
FE Q
8.7.4.2 i
(9)
-(SH.2)
ST Q
8.7.4.2 0/C RV-04 FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 Also 8.7.4 LJ 2Y 8.7.1.5 5086B D-7 2
A-1 GA SO C
FE Q
8.7.4.2 (9)
(SH.2)
ST Q
8.7.4.2 O/C RV-04 FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 Also 8.7.4 LJ 2Y 8.7.1.5 1
i 8.I.1.1 Rev. 1-J Page 117 of 172 m.-..
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_-TABLE:
S
. INSERVICE VALVE TESTING PROGRAM ISI.0 LASS.1, 2, 3 AND NC VALVES 1 PILGRIM MJCLEAR POWER STATION -
P&ID: M-227 SHEET 1 of.2-SYSTEM: CONTAINMENT ATMDSPHERE CONTROL, P&IDi M-227 SHEET 2 of 2' SYSTEM NUPBERS 45 & 9 i-l Valve.P&ID ~ ISI-Valve - Valve Valve ' Actuator.
Normal Test Test PNPS Proc.
- Test Relief
(
'Nus6er Coor Class Cat Sire Tvoe Tvoe'.
Position Rant.
Free Number Direction Request Notes -
l 5087AJ E-8
.2~
A~
1
.GA SO.
C FE Q
'8.7.4.2 t
- (9)
(SH.2)
ST:
-Q 8.7.4.2 O/C RV-04 I
FS Q"
8.7.4.2 C
LJ 2Y
~8.7.1.5-50878 D-8
'2 A
1 GA 50 -
C..
FE Q~
8.7.4.2 (9).(SH.2)
ST Q
8.7.4.2 O/C RV-04
.FS
'Q 8.7.4.2 C
PI 2Y 8.7.1.5 Also 8.7.4 LJ 2Y 8.7.1.5 5088A: E-7 2
A-1' GA
~SO C
. FE.
Q 8.7.4.2 (9)
(SH.2)
ST Q
'8.7.4.2 0/C RV-04 FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 Also 8.7.4 LJ 2Y 8.7.1.5 50888 D-7 2
A 1
GA SO C
FE Q-8.7.4.2 (9)
(SH.2)
ST Q-8.7.4.2 O/C RV-44 FS Q
8.7.4.2 C
PI.
2Y 8.7.1.5 Also 8.7.4 LJ 2Y 8.7.1.5 8.I.1.1 Rev. 1 Page 118 of 172
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LTABLE.
~
INSERVICE VALVE TESTING PROGRAM
'ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-227 SHEET 1 of 2
~
SYSTEM: COMPRESSED AIR (31) :
Valve P&IO-ISI
~ Valve ' Valve Valve ' Actuator' Normal. ' Test.. Test-PNPS Proc.
Test
~ Relief-Number Coor Class Cat-Sire' 'Tvoe Type ~
Position Rant.
Frec %r Direction -Recuest' Notes 15A 8-3 NC C
3/4
'CK
- SA C --
FC-
~O 8 C.s5 FF 158 B-5 7 NC -
'C 3/4-
- CK SA C'
FC :
0 8.C.36-FF 434 B-6 2
AC l'
CK SA C-FC -
NA -'
M Exempt (Test)
LJ 2Y~
8.7.1.5 5003A C-2' NC C
- 3/4 RL SA C
RT SY - -
8.I.26*
50038 C-4 NC C
3/4 RL SA C
RT SY 8.I.26*
5046 B-6 2
A 1
GL
'A0
.C FE
-m NA Exempt (Test).
ST NA NA Exempt (Test)
FS~
NA NA Exempt (Test)
LJ 2Y 8.7.1.5~
i I
l 8.I.1.1 Rev. 1 Page 119 of 172 I-
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1;;. -;
IgesstVICE VALVE TESTIIIG PnostAM
.~
~
"ISI CLASS 1, 2,~3 AIID NC VALVES l
' PILGRIM IEUCLEAR POWER STATION SYSTEM: NITROGGI SUPPLY (9) :
'PEID: M-227 SHEET 2 of 2
Valve : Valve - Valve Actuator Normal Test 1 Test' PNPS Proc.
Test Relief
- Number - Coor-Class Cat Size' Twoe ' Tvoe
-Position' R et.
Frea-IIuder Direction Reauest Notes
.340 D-7 2
'AC 1
CK:
.- SA.
- C.-
+ FC lQ 8.A.1 FF L3 '
2Y 8.T.1.5 '
341 D-6.
2 AC '
l'
- CK
-SA-C --
. FC
-- Q 8.A.1 FF-LJ 2Y~
"8.7.1.5 8.I.1.1 Rev. 1 Page 120 of 172
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TABLE
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INSERVICE VALV5 TESTING PROGRAM I ISI' CLASS 1, 2,.3 AND NC' VALVES PILGRIM IRJCLEAR POWER STATION P&IDi..M-232
~SYSTCMi RADWASTE COLLECTION' (20)
Valve P&ID.. -ISI
. Valve' -Valve ~ Valve Actuato r.'
Normal
. Test. - Test. PNPS Proc.
' Test Relief
' Number Coor Class ' Cat Size Tvoe' Tvoe Position"R et.
Frea Nisaber~
Direction ' Request Notes 7011A G-6 2-A 2
- St.
AD C
.. FE "
.Q 8.7.4.3
-ST:
Q 8.7.4.3
.C FS
-Q
- 8.7.4.3' C
PI 2Y.
8.7.1 LJ -
2Y 8.7.1.5 70118 G-6 2
A 2
BL -
A0 C.
' 8.7.4.3 :
ST Q
8.7.4.3 C
FS Q-
'8.7.4.3 C
PI' 2Y
- 8.7.1.5 LJ 2Y 8.7.1.5 7017A D-6 2
A 2
BL A0 C
FE Q
8.7.4.3 ST Q
8.7.4.3 C
FS Q
8.7.4.3 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 7017B 'D-6 2
A 2.-
- BL A0 C
' FE Q
8.7.4.3 ST -
Q 8.7.4.3 C
FS Q
8.7.4.3 C-PI 2Y 8.7.1.5 LJ -
2Y 8.7.1.5 i
.i
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' ~
- INSERVICE VALVE TESTING PROGRAM
^
~
.. ISI. CLASS ' 1. 2. 3 AND NC VALVES -
~
- PILGRIM NUCLEAR POWER STATION
'P&ID: M-239 SHEET.1 of 3 SYSTEM: POST ACCIDENT SAMPLING & H2+O2 P&ID: M-239 SHEET 2 of.3 ANALYZER SYSTEM (5065)
~
Valve : P&ID ISI Valve Valve Valve Actuator
- Normal Test: -Test-PNPS Proc..
' Test Relief.
Numl>er Coor Class Cat'
' Sire ~ Tvoe Tvoe
' Position'R< sat.
Frea Naber
' Direction Recuest Notes 11A B-6 2
A 1
-GL
. 50 C
FE Q
8.7.4.1 (SH.1)
.Q 8.7.4.1 O/C' RV-04 FS
-Q.
8.7.4.1 C
PI 2Y 8.7.1.5' LJ 2Y 8.7.1.5 138 B-3 2
A' 1
GL ~
SO '
O FE Q~
8.7.4.1 (SH.1)
ST Q
8.7.4.1 0/C RV-04 FS Q
8.7.4.1 C
PI 2Y-8.7.1.5 LJ 2Y 8.7.1.5 14A B-6
-2 A
1 GL' SO O
FE Q'
8.7.4.1.
(SH.1)
ST Q
8.7.4.1 0/C RV--04 FS Q
8.7.4.1 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 ISB B-3 2
A 1
GL SO C
FE Q
8.7.4.1 (SH.1)
ST Q
8.7.4.1 0/C RV-04 FS Q
8.7.4.1 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 18A B-6 2
A 1
GL S0
-C FE Q
8.7.4.1 (SH.1)
. ST Q
8.7.4.1 O/C RV-04 FS Q
8.7.4.1 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 208 B-4 2
A 1
GL SO O
FE Q
8.7.4.1 I
(SH.1)
~ ST Q
8.7.4.1 0/C RV-04 l
FS Q
8.7.4.1 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 8.I.1.1 Rev. 1 Page 122 of 172 m
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TABLE C-INSERVICE. VALVE TESTING PROGRAM
- ISI CLASS'1, 2i 3 AND NC VALVES
~~
PILGRIM NUCLEAR POWER STATION SYSTEM: POST ArCbt.NT SAMPLING & H2+O' 2
'P&ID: M-239 SHEET 1 of 3 W LYZER SYSTEM (5065)
P&ID: M-239 SHEET 2 of 3 Ifalve P&ID ISI Valve Valve Valve ~ Actuator.
Normal Test Test PNPS Proc.
.' Test Relief Number Coor Class Cat
-Sire Tvoe Tvoe Position ' Rant.
Frea Number Direction Reauest Notes
-21A B-6 2
A 1
GL-50.
.O' FE Q
8.7.4.1 ST Q
-8.7.4.1 0/C RV-04 (SH.1)
FS Q
8.7.4.1.
C
' PI 2Y 8.7.1.5
- LJ 2Y 8.7.1.5 228 B-4 2
A
.1 GL
' SO '
C
. FE '
. Q 8.7.4.1 ST Q~
8.7.4.1:
O/C RV-04 (SH.1)
FS Q
.8.7.4.1 C
. PI.
2Y.
8.7.1.5 L3 2Y 8.7.1.5 24A B-6 2
A 1
GL SO O
FE Q
8.7.4.1 ST Q
8.7.4.1 O/C RV-04 (SH.1)
FS Q
8.7. 4.1 C
PI 2Y 8.7.3.5 LJ 2Y 8.7.1.5 258 B-4 2
A 1
GL SO C
Fe Q
8.7.4.1 ST Q
8.7.4.1 O/C RV-04 (SH.1)
FS Q
8.7.4.1 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 26A B-6 2
A 1
GL SO C
FE Q
8.7.4.1 ST Q
8.7.4.1 O/C RV-04 (SH.1)
FS Q
8.7.4.1 C
PI 2Y 8.7.1.5 LJ
' 2Y 8.7.1.5 278 B-3 2
A 1
GA SO C
FE Q
8.7.4.1 ST Q
8.7.4.1 0/C RV-04 (SH.1)
FS Q
8.7.4.1 C
PI 2Y.
8.7.1.5 LJ 2Y 8.7.1.5 8.I.1.1 Rev. 1 Page 123 of 172
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.g TABLE' INSERVICE VALVE TESTING PROGRAM ISI CLASS'1, 2, 3 AND NC VALVES PILGRIM NUCLEAR. POWER STATION.'
P&ID: M-239 SHEET 1 of 3 SYSTEM: 'P3ST ACCIDENT SAMPLING & H2+O2 P&ID. M-239 SHEET 2 of 3 AfstLYZER SYSTEM (5065)
. Valve ' Valve -Valve--Actuator
-Normal Test
' Test PNPS Proc.
Test Relief
' Nunner Coor Class-Cat Sire Tvoe ~Tvoe
~ Position Rant.
Free Number Direction-Request Notes 318 C-4 2
'A 1
GL.
50 C ~.
FE Q
-8.7.4.1 (SH.1)
ST Q.
8.7.4.1 0/C RV--04
- FS
.Qz 8.7.4.1 C
PI 2Y 8.7.1.5 LJ 2Y -
8.7.1.5
'33A C-6
'2 A
1
' GL S0-0.
FE Q
8.7.4.1 (SH.1).
ST Q
8.7.4.1 0/C RV-04 FS-
.Q-8.7.4.1 C
PI 2Y 8.7.1.5
-LJ 2Y -
8.7.1.5 35B C-4 2'
A-1 GL SO C
FE Q
8.7.4.1 (SH.1)
ST Q
8.7.4.1 O/C RV-04 FS Q-8.7.4.1 C
.2Y 8.7.1.5 LJ 2Y 8.7.1.5 37A C-6 2
A
'1 GL SO O.
FE Q
8.7.4.1 (SH.1)
ST Q
8.7.4.1 O/C RV-04 FS Q
8.7.4.1 C
- PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 63 G-7 1
A 1
GL SO.
C FE Q
8.7.4.1 (SH.2)
ST Q
8.7.4.1 0/C RV-04 FS Q
8.7.4.1 C
PI 2Y -
8.7.1.5 LJ 2Y' 8.7.1.5 64 G-6 1
A 1
GL SO C
FE Q
8.7.4.1 (SH.2)
- Q --
8.7.4.1 0/C RV-04 FS
.Q 8.7.4.1 C-PI
. 2Y 8.7.1.5 LJ 2Y 8.7.1.5 65 G-6 2
B 1
GA 50
-C
- FE Q
8.7.4.1 (SH.2)
ST Q
8.7.4.1 C
RY-04 FS Q
8.7.4.1 C
PI 2Y 8.7.4.8 8.I.1.1 Rev. 1
~
Page 124 of 172
.- ~ _ -,..
.~
-TABLE ~
~
INSERVICE VALVE TESTING PROGRAM
'ISI CLASS 1, 2.-3 AND NC VALVES PILGRIM NUCLEAR POWER STATION
-P&ID: M-239 SHEET 1 of 3
- l. SYSTEM: POST ACCIDENT SAMPLING &_M2+O2 P&ID: M-239 SHEET 2 of 3 ANALYZER SYSTEM (5065)
Valve P&ID ISI Valve Valve Valve Actuator
. Normal
. Test Test-PNPS Proc.
Test' Relief.
Number-Coor Class Cat Sire Tvoe Type Position Rant.
Frea Number Direction Recuest Notes 66 G-6 2
B 1
GA SO.
C FE Q
8.7.4.1 (SH.2)
ST Q
8.7.4.1 C
RW-04 FS
-Q 8.7.4.1 C
- 2Y 8.7.4.8 67 E-6 2
8 1
GA.
50 C
~ FE Q
8.7.4.1 (SH.2)
ST Q
8.7.4.1 C
RV-04 FS Q
8.7.4.1 C
PI 2Y 8.7.4.8 68 E-6 2
B 1'
GA 50 C
FE Q.
8.7.4.1 (SH.2)
ST Q
_8.7.4.1 C
RV-44
- FS Q
8.7.4.1 C
PI 2Y 8.7.4.8 69 D-6 2
8 1
GA 50 C
FE Q
8.7.4.1 (SH.2)
ST Q
8.7.4.1 C
RV-04
. FS Q
8.7.4.1 C
PI 2Y 8.7.4.8 70 D-6 2
8 1
GA SO C
FE Q
8.7.4.1 (SH.2)
ST Q
8.7.4.1-C RV-04 FS Q
8.7.4.1 C
PI 2Y 8.7.4.8 71 F-6 2
A 1
GA S0 C
FE Q
8.7.4.1 (SH.2)
ST Q
8.7.4.1 C
RV-04 FS Q
8.7.4.1 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 72 F-6 2
A 1
GA SO C
FE Q
8.7.4.1 (SH.2)
ST Q
8.7.4.1 C
RV-04 FS Q
8.7.4.1 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 8.I.1.1 Rev. 1 Page 125 of 172
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. +.:
. INSERVICE VALVE TESTING PROGRAM
~
'ISI CLASS 1,'2, 3 AND NC VALVES-
' PILGRIM NUCLEAR POWER STATION P&ID: M-239 SHEET 1 of 3 SYSTEM: POST ACCIDENT SAMPLING & H2+O:
2 P&ID: M-239 SHEET 2 of 3 ANALYZER SYSTEM (5065)-
Valve P&ID ISI Valve Valve Valve 1 Actuator-Normal-Test Test! PNPS Proc..
Test
~ Relief Number Coor Class Cat
-Sire Tvoe Type Position Rant.
Frea Number Direction Reauest Notes 73 C-6 2
8 1
GA SO
.C-
.FE Q
8.7.4.1 (SH.2)
~8.7.4.1 C
RW-04 FS
~ Q-8.7.4.1 C
PI 2Y
'8.7.4.8 74 C-6 2
8 1-GA 50 C
FE Q
8.7.4.1 (SH.2)
.Q 8.7.4.1 C
RV-04 FS Q
8.7.4.1 C
PI 2Y 8.7.4.8 75 B-6 2
8 1
. GA 50
.C FE Q
8.7.4.1 (SH.2)
ST Q
8.7.4.1 C
RV-04 FS
(
8.7.4.1 C-PI 2Y ~
8.7.4.8 76 8-6 2
B 1
GA 50 C
FE Q
8.7.4.1 (SH.2)
ST Q
.'.7.4.1 C
RV-04 FS Q
8.7. !
- C PI 2Y 8.7.4.8 77 E-6 2
A 1
GA S0 C
FE Q
8.7.4.1 (SH.2)
ST Q
8.7.4.1 C
RV-04 FS Q
8.7.4.1 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 78 E-6 2
A 1
GA -
50 C
FE Q
8.7.4.1 (SH.2)
ST Q
8.7.4.1 C
RV-04 FS Q
8.7.4.1 C
PI-2Y 8.7.1.5 LJ 2Y 8.7.1.5 8.I.1.1 Rev. 1 Page 126 of 172
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. TABLE IN5ERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2. 3 AND NC VALVES
' PILGRIM NUCLEAR POWER. STATION' P&iD:.M-239 SHEET 1 of 3 SYSTEM:. POST ACCIDENT SAMPLING & H2t 02
.P&ID: M-239 SHEET 2 of 3 ANALYZER SYSTEM (5065)
Valve
.P&ID.
ISI Valve Valve : Valve - Actuator Normal Test Test PNPS Proc.
' Test Relief Number Coor Class Cat Size Tvoe 'Tvoe Position Rartt.
Frec' Nimber Di rection Request Notes 79 D-6 2-B 1
'GA 50 C:
.Q-8.7.4.1 (SH.2)
ST.
Q 8.7.4.1 C
RV-04 FS Q-8.7.4.1 C
- PI 2Y 8.7.4.8 80 (Mi 2
B 1
GA '
50 C
.FE Q-8.7.4.1 (SH.2)
ST Q
8.7.4.1 C
Rv-04 FS Q
8.7.4.1 C
-PI 2Y 8.7.4.8 81 C-6 2
8 1
GA SO C
FE Q.
8.7.4.1
-(SH.2)
ST Q
.8.7.4.1 C
RV-04 FS Q
8.7.4.1 C'
PI 2Y 8.7.4.8 82 C-6 2
8 1
- GA 57 C
FE Q
8.7.4.1 (SH.2)
ST Q
8.7.4.1 C
RY-44 FS Q
8.7.4.1 C
PI 2Y 8.7.4.8 83 F-6 2
8 1
- GA 50 C
FE Q
8.7.4.1 (SH.2)
ST Q
8.7.4.1 C
RV-04 FS Q
8.7.4.1 C
PI 2Y 8.7.4.8 84 F-6 2
8 1
GA
-50 C
FE Q
8.7.4.1 (SH.2)
ST Q
8.7.4.1 C
RV-64 FS Q
8.7.4.1 C
PI 2Y 8.7.4.8 65 G-6 1
A 1
GA-50 C
FE Q
8.7.4.1 (SH.2)
ST -
Q 8.7.4.1 0/C RV-04 FS Q
8.7.4.1 C
-2Y 8.7.1.5 LJ 2Y 8.7.1.5 86 G-6 i
A-1 GA 50 C
FE Q
8.7.4.1 (SH.2)
ST Q
8.7.4.1 0/C RV-04 FS Q
8.7.4.1 C
PI 2Y 8.7.1.5 LJ 2Y
-8.7.1.5 8.I.1.1 Rev. 1 Page 127 of 172 x
~
-TABLE-M INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2,:3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-239 SHEET 1 of 3-SYSTEM. POST ACCIDENT SAMPLING & H + O 2
2.
P&ID: M-239 SHEET 2 of 3 AM.YZER SYSTEM (5065)
Valve P&ID ISI' Valve Valve ~ Valve. Actuator :.
Normal'. Test-Test' PNPS Proc.-
Test Relief-Number Coor Class Cat
' Size Type : Tvoe.
' Position ' Rant.
Frea Number Direction Request Notes 87 D-4 2
B 1
GL-A0 0
FE -
Q 8.7.4.1 (SH.1)
'Q-8.7.4.1 C
'RV-04 FS Q
8.7.4.1-C PI 2Y 8.7.4.8 88 D-4 2
8 1
GL
-A0 0
FE.
Q 8.7.4.1 (SH.1)
ST Q
8.7.4.1 C
RV-04 FS Q
8.7.4.1 C
PI 2Y 8.7.4.8 89 D-7 2
8 1
GL-
-A0 0
FE Q
8.7.4.1 (SH.1)
ST Q
8.7.4.1
.C RV-04 FS Q
8.7.4.1 C
PI 2Y 8.7.4.8 90 (Mi 2
B 1-GL A0 0
FE Q
8.7.4.1 (SH.1)
ST Q
8.7.4.1 C
RV-04 FS Q
8.7.4.1 C
PI 2Y 8.7.4.8 91 A-5 2
A 1
GA A0 0
FE Q
8.7.4.1 (SH.1)
ST.
Q 8.7.4.1 C
RV-04 FS Q
8.7.4.1 C
PI 2Y.
8.7.1.5 LJ 2Y 8.7.1.5 92 A-5 2
A 1
GA-AO.
O FE Q
8.7.4.1 (SH.1)
ST Q
8.7.4.1 C
RV-04 FS Q
8.7.4.1 C
PI 2Y 8.7.1.5 l
LJ 2Y 8.7.1.5 122A C-8 2
8
.375 GA SV O
' FE Q
8.7.4.1 j
(SH.1)
ST Q
8.7.4.1 0
RV-04 l-FS Q
8.7.4.1 C-PI 2Y 8.7.4.8 122B C-1 2
8
.375 GA SV C
FE Q
8.7.4.1 (SH.1)
ST Q
8.7.4.1 0
RV-04 FS Q
8.7.4.1 C
PI 2Y 8.7.4.8 l~
i 8.I.1.1 Rev. 1 Page 128 of 172 l
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TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES.'
PILGRIM NUCLEAR POWER STATION SYSTEM: P)ST ACCIDENT SAMPLING & H2+O2 P&ID: M-239 SHEET 1 of 3 A1ALYZER SYSTEM (5065)
P&ID: M-239 SHEET 2 of 3 tfalve P&ID ISI Valve Valve Valve Actuator '
Normal Test' ' Test PNPS Proc.
Test Relief Number Coor Class Cat Size-Tvoe Tvoe' Position Ramt.
Frea Number Direction _Recuest Notes 123A C-8 2
5
-.375 - GA SV C
- 8.7.4.1.
O RV-44 (SH.1)
FS
.Q 8.7.4.1 C'
PI 2Y 8.7.4.8 1238 C-1 2
8
.375 GA SV C
FE Q'
8.7.4.1 ST
.Q 8.7.4.i 0
RV-04 (SH.i)
FS Q
8.7.4.1 C
PI 2Y 8.7.4.8 124A C-7 2
B
.375 GA SV C
FE Q'
.8.7.4.1 ST Q
8.7.4.1 0
RV-04 (SH.1)
FS Q
8.7.4.1 C
PI 2Y 8.7.4.8 124B C-2 2
B
.375 GA SV C
FE Q
8.7.4.1 ST.
Q 8.7.4.1 D
RY-44 (SH.1)
FS Q
8.7.4.1 C
PI 2Y
~8.7.4.8 5117A H-6 2
8
.375 GA
'SV C
FE Q
8.M.3-13 ST NA NA RV-37 (SH.1)
FS O
8.M.3-13 C
5117B H-3 2
8
.375 GA SV C
- FE Q
8.M.3-13 ST NA NA RV-31 (SH.1)
FS O
8.M.3-13 C'
5137A G-6 2
B
.375-GA SV
.C FE Q
8.M.3-13 ST NA NA RV-31 (SH.1)
-FS 0
8.M.3-13 C
51378 G-3 2
8
.375
- GA SV '
C FE Q
8.M.3-13 ST M4 NA RV-31 (SH.1)
FS 0
8.M.3-13 C
8.I.1.1 Rev. 1 Page 129 of 172
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- E TABLE-;
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- INSERVICE VALVE TESTINC
?
Y ISI CLASS 1, 2. 3 Afe NC VALVES
- PIL9 TIM IRfCLEAR POWER STATION P&TD: M-241 SHEET-1 of 2 SYSTEM: -RESIDUAL HEAT REMDWAL SYSTEM (1901)
P&ID: M-241 SHEET 2 of 2 Valve P&ID ISI Valve Valve Valve Actuator' Normal
. Test Test PNPS Proc.
. Test Relief Nus6er Coor Class- -Cat Sire Tvoe Tvoe Posi tien Rtzet.
Frea Number Direction Request Notes 2A D-6 2
C 2
.CK SA.
C' PC-Q 8.5.2.2.1 FF Disassemble -
(SH.2)
- -C RO 8.I.27*
FF RV-27 To Exercise AP RO 8.5.2.2.1 Closed 28 D-3 2-C 2
-CK SA" C
PC Q'
8.5.2.2.2 FF Disassem61e-(SH.2)
FC" RO --
8.I.27*
FF_
RW-27 To Exercise
- AP -
RO 8.5.2.2.2 Closed 2C G-6 2
C 2
CK-SA.
C PC -
Q.
8.5.2.2.1 FF Disassemble (SH.2)
FC R0 8.I.27*
FF RV-27 To Emercise
.AP R0 8.5.2.2.1 Closed 2D G-3 2
C.
2 CK SA C
~PC Q
8.5.2.2.2 FF Disassemble (SH.2)
FC -
RO 8.I.27*
. FF P'-27 To Exercise AP RO S.5.2.2.2 Closed 7A D-5 2
B 18 GA MO.
O FE Q
8.5.2.3 (SH.2)
ST Q
8.5.2.3 0/C PI 2Y 8.5.2.3 7B D-4 2
B 18 GA MO.
0-FE Q
8.5.2.3 (SH.2)
ST Q
8.5.2.3 0/C PI 2Y 8.5.2.3 7C F-5 2
B 18 GA M0 O
FE Q
8.5.2.3 (SH.2)
ST Q
8.5.2.3 0/C PI 2Y 8.5.2.3 7D F-4 2
B 18 -
GA M0 O
FE Q
8.5.2.3 (SH.2)
ST Q
8.5.2.3 O/C iI 2Y 8.5.2.3 16A F-7 2
B 18 GL MO
.C FC-Q 8.'s.2.3 (SH.2)
ST Q
8.5.2.3 0
PI 2Y 8.5.2.3 16B E-2 2
'B 18 GL M0 C-FE Q
8.5.2.3 (SH.2)
.ST Q
8.5.2.3 0
PI 2Y 8.5.2.3 8.I.1.1 Rev. 1 Page 130 of 172
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TABLE jINSERVICE VALVE _1ESTING PNDGilAM ISI CIASS 1. 2, 3 afb HC VALVES PILGRIM MJCLEAR POWER STATION P&ID: f5-241 SHEET 1 of 2
' SYSTEM:. RESIDUAL HEAT REN NAL SYSTER (1001)
'PEID: 15-241 SHEET 2 of 2 Valve P&ID ISI Valve Valvel Valve - Actuator
' Normal Test Test-PNPS Proc.
Test Relief Nur6er Coor Class Cat Sire "Tvoe
-Tvoe~
Position Rant.
Frea-N suber Direction Request Notes 18A G-6 2
B 3-GA MO
~ 01 FE
-Q 8.5.2.3 (SH.2)
ST Q
8.5.2.3 O/C PI 2Y 8.5.2.3 1CB G-3
'2 a
3 GA '
I") -
0 FE Q
8.5.2.3 (SH.2)
ST.
Q
.8.5.2.3 O/C PI 2Y 8.5.2.3 19 B-7 2
8
-18 GA 10 0
FE Q
8.5.2.3 (SH.1)
ST Q
8.5.2.3 C
PI 2Y 8.5.2.3 21 B-3 2
A 4
GA MD C
FE Q
8.5.2.3 (SH.1)
ST Q
8.5.2.3 C
PI 2Y 8.5.2.11 LX 2Y 8.5.2.11*
22A F-8 2
AC 1
-RL SA C
~SY 8.I.26*
(SH.1)
LX NA 8.I.26*
RT Verifies 22B F-2 2
AC 1
RL' SA C-RT SY 8.I.26*
(SH.1)
LX -
N$.
8.I.26*-
RT Verifies 23A G-6 2
A 10 GA MO '
C FE Q
8.5.2.3 (SH.1)
ST Q
8.5.2.3 0/C PI 2Y 8.7.1.5 LJ ZY 8.7.1.5 RV-28 238 G-4 2
A 10 GA.
MD C
FE-Q 8.5.2.3 j
(SH.1)
ST Q
8.5.2.3 0/C PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 RV-28 26A G-5
~2 A
fc
~ GA M0 C
FE Q
8.5.2.3 (SH.1)
ST Q
8.5.2.3 O/C PI 2Y -
8.7.1.5 LJ 2Y 8.7.1.5 RV-28 268 G--4 2
A 10 GA M0 C
FE Q
8.5.2.3 (SH.1)
ST Q-8.5.2.3 O/C PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 RV-28 8.I.1.1 Rev. 1 Page 131 of 172
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/ TABLE' L INSERVICE VALVE TESTING PRDERAM
- ISI CLASS 1, 2, 3 Age NC VALVES PILGRIM SRfCLEAR POWER STATION SYSTEM: : RESIDULL HEAT RDWWAL SYSTEM (1001) -
P&ID: 42 0 05rT 1 of 2:
P&ID: W241 SHEET 2 of 2 Valve P&ID ISI Valve Valve : Valve ' Actuator Normal.
Test Test. PNPS Proc.
' Test Relief Number Coor Class Cat-Sire Tvoe Type Position Rett.
Frea Num6er
-Direction Reauest Notes 2SA F-6
'2 A
18 GL MO 0-FE Q
8.5.2.3 ST
.Q 8.5.2.3:
O/C (SH.1)
PI 2Y 8.7.1.5 -
LJ
~ 2Y 8.7.1.5 RV-28 288 F-4 2
A' 18 GL MD
-0 FE Q
8.5.2.3 ST Q
8.5.2.3 0/C (SH.1)
PI 2Y -
8.7.1.5 LJ 2Y 8.7.1.5 RV-20
.29A E-6 1
A 18 GA M0 C
FE CS 8.I.11.3-CS-09 ST CS 8.I.11.3 0/C CS-09 (SH.1)
PI 2Y 8.5.2.7 LJ.
2Y 8.7.1.5 RV.-28 LP 2Y 8.5.2.7 298 E-4 1
A 18
-GA M0 C
FE CS 8.I.11.4 CS-09 ST CS 8.I.11.4 O/C CS-09 (SH.1)
- PI 2Y 8.5.2.7 LJ
-2Y 8.7.1.5 RV-28 LP 2Y 8.5.2.7 32 B-3 2
A
-4
-GA NO C
FE Q
8.5.2.3 ST Q
8.5.2.3 C
(SH.1)
PI.
2Y 8.5.2.11 LX
'2Y 8.5.2.11 33A E-6 1
NA 18 GA-ML LO NA NA
' NA Exempt (Manual)
PI 2Y 8.5.2.7 (SH.1) 338 E-4 1
NA 18
'GA ML _
LO NA NA NA Exempt (Manual)
PI 2Y 8.5.2.7 (SH.1) 34A
'F-7 2
A 12 GA M0 C
FE Q
8.5.2.3 ST Q
8.5.2.3 0/C (SH.1)-
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 RV-28 34B F-3 2
A 12...
GA M0 C
FE Q
8.5.2.3 ST Q
8.5.2.3 0/C (SH.1)
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 RV-28 8.I.1.1 Rev. 1 Page 132 of 172
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TABLE:
'~
INSERVICE VALVE TESTING PROGRAR'
-ISI CLASS 1, 2. 3 afb NC VALVES
~
PILGRIM IRfCLEAR FOWER STATION
'P&IO: -M-241 SHEET 1 of 2-
' SYSTEM: RESIDUAL HEAT RDOWAL SYSTUI (1001) ;
P&ID: 74-241 SHEET 2 of 2 -
Valve-P&ID ISI.
Valve Valve Valve Actuator Normal Test Test FNPS Proc.
Test Relief Number Coor Class Cat Sire Tvoe 'Tvoe
- Position Rourt.
Free Humber Direction Recuest Notes 36A E 2 B
12
. GL MO C
FE Q
8.5.2.3 (SH.1)
ST Q
8.5.2.3 O/C PI 2Y 8.5.2.3 36B E-3 2
B 12 GL -
.to C
. FE Q
'8.5.2.3 (SH 1)
' ST
-Q 8.5.2.3
.0/C PI 2Y 8.5.2.3 37A E-7 2
A 6
~ 10 C
FE Q
8.5.2.3 (SH.1)
ST Q
8.5.2.3 0/C
' PI
-2Y 8.7.1.5 LJ 2Y 8.7.1.5 RV-28 37B E-3 2-A 6
GL-MO C
' FE Q
8.5.2.3
.(SH.1)'
ST Q
8.5.2.3
.0/C PI 2Y-8.7.1.5 LJ 2Y 8.7.1.5 RV-28 8.I 1.1 Rev. 1
.Page 133 of 172
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.s TABLE INSERVICE VALVE TESTING Pa0 GRAM ISI CLASS 1, 2. '3 Als NC VALVES '
PILGRIM IRfCLEAR POWER STATION P&ID: M-241 SHEET 1 of 2 SYSTEM: RESIDUAL HEAT RDOWAL SYSTEM (1001)
.PSID: M-241 SHEET 2 of 2 Valve P&IDL ISI Valve: Valve ' Valve Actuator.
Normal
. Test Test PNPS Proc.
Test Relief Number Coor ' Class Cat Sire Tvoe Tvoe Position Ret.
Frea Number Direction Request Notes 43A E-5 2
8 18 GA MD
'C FE Q
8.5.2.3 (SH.2)
ST Q
8.5.2.3 0
PI 2Y 8.5.2.3 438 E-4 2
8 18 GA 70 C
-Q 8.5.2.3 (SH.2)
ST Q
8.5.2.3-0 -
PI 2Y 8.5.2.3 43C G-5 2
8 18 GA MD C
.Q 8.5.2.3 (SH.2)
ST Q
8.5.2.3 0
PI 2Y 8.5.2.3 43D G-4 2
B 18 GA MD C
FE Q
8.5.2.3 (SH.2)
ST Q
8.5.2.3' O
PI 2Y 8.5.2.3 i
44 C-5 2
.RT SY 8.I.26*
(SH.1)
LX NA 8.I.26*
RT Verifies 47 C-5 1'
A 20
' GA MD C
CS-02 PI 2Y 8.5.2.8-LJ 2Y 8.7.1.5
.RV-28 LP 2Y 8.5.2.8 50 D-5 1
A 20 GA MO
~C FE CS 8.I.11.5 CS-02 (SH.1)
CS-02 PI 2Y 8.5.2.8 LJ 2Y 8.7.1.5 RV-28 LP 2Y 8.5.2.8 59 H-6 2
AC 1
RL' SA C
RT SY.
8.I.26*
(SH.1)
LX NA 8.I.26*
RT Verifies 60 H-5 1
A 4
GA.
MD C
FE NA NA '
Inoperative PDC (SH.1)
ST NA NA (Deenergized)
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 8.I.1.1 Rev. 1 Page 134 of 172
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.' TABLE '
INSUtVICE VALVE TESTING PROGRAM
- ISI C1 ASS I 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&lD: 'M-241 SHEET 1 of 2~
SYSTEM: RESIDUAL HEAT RDOfAL SYSTEM (1001)
-PEID: M-241 SHEET 2 of 2 Valve P&ID-ISI Valve Valve Valve Actuator
-Normal' Test'.
Test PNPS Proc.
Test Relief Norber Coor Cl as s Cat Sire JTvoe Tvoe -
Position Rcunt.
Frea Neber Direction Reauest Notes 63 G-5 1
A 4
GA -
MO
~C FE NA
- NA Inoperative PDC (SH.1)
ST N4 M4-(Deenergized)
PI 2Y-8.5.2.9 LJ 2Y 8.7.1.5 LP RO 8.5.2.9 RV-24 64
' G-5 1
AC 4
CK SA C
FC CS 8.I.11.6 CS-10 Inoperative PDC (SH.1)
-LP RD 8.5.2.9 RV-24 (Pipe Capped) 67A D-6 2
-C 12
.. CK SA C
FC
.Q 8.5.2.2.1 FF '
($H.2)
' Closed 678 D-3 2
C 12 CK SA
.C FC Q
8.5.2.2.2 FF (SH.2)
AP RO 8.5.2.2.2 Closed 67C F-7 2
C 12 CK SA' C;
FC Q
8.5.2.2.1 FF (SH.2)
AP RO-8.5.2.2.1 Closed 67D F-3 2
C 12 CK SA C
FC Q
8.5.2.2.2 FF (SH.2)
AP RO 8.5.2.2.2 Closed 68A E-6 1
PC CS 8.I.11.17 FF CS-03 (SH.1)
FC RO 8.I.27*
FF RV Disassemble To LP 2Y 8.5.2.7 Esercise G88 E-4 1
AC 18 CK-SA C/
PC CS 8.I.11.17 FF CS-03 (SH.1)
FC RO 8.I.27*
FF RV-27 Disassem6le To LP 2Y 8.5.2.7 Exey ise 362B F-2 2
AC 2
CK SA C
PC-Q-
8.5.2.3 FF (SH.2)
FC RO 8.5.2.13*
Closed LX 2Y 8.5.2.13*
8.I.1.1 Rev. 1 Page 135 of 172
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7 TABLE
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INSERVICE VALVE TESTING PH09 tan ISI CLASS 1, 2, 3 AND NC VALVES 2 PILGRIM NUCLEAR POWER STATION SYSTEM: CORE SPRAY SYSTEM (1400)
P&ID: M-242 Valve P&ID 151 Valve Valve Valve Actuator ~
Normal' Test- : Test PNPS Proc.-
Test 1 Relief Number Coor Class-Cat Sire Tvoe" Tvoe Position Ret.
Frec '
sr Direction Reouest Notes 3A
-F-7 2
8 18 GA.
i MO.
0' FE.
Q-
-8.5.1.3 ST. '
-Q.
8.5.1.3
.C PI 2Y '
8.5.1.3 38 F-8 2
8 18 GA MD
-0
- FE
.Q 8.5.1.3 ST Q
8.5.1.3 C
PI 2Y 8.5.1.3 4A C-6 2
B-6 GA.
M0 C
FE Q
8.5.1.1 ST Q
8.5.1.1 C
PI 2Y 8.5.1.1 48 C-6
-2 8
6 GA MO
^ C FE Q
8.5.1.1 ST-
'Q 8.5.1.1 C
PI 2Y 8.5.1.1 Exempt (Manual) 6A C-3 1
NA 10 GA
. M4 LO NA NA NA PI 2Y 8.5.1.6 68 C-3 1
NA 10 GA MA LO NA NA NA Exempt (Manual)
PI 2Y 8.5.1.6 7
D-4 1
AC 1
CK SA.
O FC RO 8.M.3-2 RF RV-22 PDC: 86-808 AP RO 8.M.3-2 Open Currently LX RO 8.M.3-2 RV-22 Inocerative 9A D-3 1
C FC RO 8.I.15 FF RV 46 LP 2Y 8.5.1.6 99 B-3 1
' 2Y -
8.5.1.6 13A E-7 2
C 3
SC SA C/LO PC Q
FF RV-27 Disassemble AP RO 8.I.27" Closed To Esercise 13B E-9 2
C 3
SC SA C/LO PC Q
8.5.1.1 FF FC RD 8.I.27*
FF RV-27 Disassemble AP RO 8.I.27*
Closed To Exercise _
24A D-5 2
A 10 GA M0 O
.FE
-Q 8.5.1.3 ST Q
8.5.1.3 O/C PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 RV-28 248 B-5 2
A 10 GA' MO.
O FF Q
8.5.1.3 ST Q
8.5.1.3 O/C PI 2Y.
8.7.1.5
'LJ 2Y 8.7.1.5 RV-28 8.I.1.1 Rev. 1 Page 137 of 172
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A 8
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A 8
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TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND MC VALVES PILGRIM 80 CLEAR F0WER STATION SYSTEM: HIGH PREtSURE COOLANT INJECTION (2301)
P&ID: 5243 SHEET 1 P&ID: M-244 SHEET 2 Valve P&ID ISI Valve vahe valve Actuator Normal Test Test PWPS Proc.
Test Relief Number Coor Class Cat
' Size Tvoe Tvoe Position Ryt.
Frea stadier Direction Request footes 2301-23 E-11 2
B 10 G4 HO C
FE Q
8.5.4.4 (HO-1) (SH.2)
ST Q
8.5.4.4 O/C 1
FS Q
8.5.4.4 C
PI 2Y 8.5.4.4 2301-24 E-11 2
NA 10 GV H0 C
FE Q
8.5.4.4
'rstrol Valve (HO-2) (SH.2)
ST Q
MA RV-67
' E.5T Augment-FS Q
8.5.4.4 C
e4 NRC regoire-PI 2Y 8.5.4.4 et 3
F-13 2
B 10 GA M0 C
FE Q
8.5.4.1 Alm 8.5.4.4 (SH.1)
ST Q
8.5.4.1 0
Also 8.5.4.4 PI 2Y 8.5.4.4 4
D4 1
A 10 GA M1 O
FE Q
8.5.4.4 ST Q
8.5.4.4 O/C (SH.1)
PI 2Y 8.7.1.5 LJ 2Y 8.7.s.5 RV-28 5
D-6 1
A 10 GA M0 O
FE Q
8.5.4.4 ST Q
8.5.4.4 O/C (SH.1)
PI 2Y 8.7.1.5 LJ ZY 8.7.1.5 E*-28 6
C-10 2
B 16 GA M0 O
FE Q
8.5.4.4 ST Q
8.5.4.4 O/C (SH.1)
PI ZY 8.5.4.4 7
H-5 1
LP ZY 8.5.4.8 8
H-5 1
A 14 CA MD C
ST CS 8.I.11.11 0/C CS-09 PI 2Y 8.5.4.8 LJ 2Y 8.7.1.5 RV-28 LP 2Y 8.5.4.8 9
H-6 2
B 14 GA M0 O
FE Q
8.5.4.4 ST Q
8.5.4.4 0
(SH.1)
PI 2Y 8.5.4.4 8.1.1.1 Rev. 1 Page 139 of 172
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TABLE' INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-243 SHEET l' SYSTEM: HIGH PRESSURE COOLANT INJECTION (2301)
P&ID: M-244 SHEET 2 Vsive P&ID ISI Valve Valve Valve Actuator Normal Test Test FWPS Proc.
Test Relief Nurber Coor Class Cat Sire Tvoe Tvoe Position R<urt.
Free Nudper Direction Request Notes 10 E-6 2
8 10 GL MD C
FE Q
8.5.4.4 (SH.1)
ST Q
8.5.4.4 C
PI 2Y 8.5.4.4 14 F-8 2
8 4
GL MD C
FE Q
8.5.4.4 (SH.1)
ST Q
8.5.4.4 O/C PI 2Y 8.5.4.4 15 D-7 NC 8
10 GA PC C
FE Q
8.5.4.4 (SH.1)
ST Q
8.5.4.4 C
PI 2Y 8.5.4.4 20 D-10 2.
B 16 CK SA C
FC Q
8.5.4.1 FF (SH.1) 23 D-8 2
AC 1
RL SA C
RT SY 8.I.26*
(SH.2)
LX NA 8.I.26*
RT Verifies 26 E-5 1
AC 1
SK SA 0
FC RO 8.M 3-2 RF RV-22 (SH.1)
AP RO 8.M.3-2 Open LX RO 8.M.3-2 RV-22 29 K-14 2
8 1
GL A0 0
FE Q
8.5.4.4 (SH.1)
ST Q
8.5.4.4 C
FS Q
8.5.4.4 C
PI 2Y 8.5.4.4 33 M-1 2
A 4
GA MO O
FE Q
8.5.4.4 (SH.1) 57 Q
8.5.4.4 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 34 L-2 2
A 4
GA M0 O
FE Q
8.5.4.4
($H.1)
ST Q
8.5.4.4 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 8.I.1.1 Rev. 1 Page 140 of 172
TABLE INSERVICE VALVE TESTING PROGRAM
.SI CLASS 1, 2, 3 AND NC VALVES FILGRIM NUCLEAR POWER STATION P&ID: M-243 SHEET 1 SYSTEM: HIGH FRESSURE COOLANT INJECTION (2301)
P&ID: M-244 SHEET 2.
Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test PNPS Proc.
Test Relief Number Cocr Class Cat Sire Tvoe Tvoe Position Ret.
Free teumber Direction Request Notes 34 K-5 2
C 2
CK SA C
PC Q
8.5.4.1 FF (SH.1)
FC RO 8.I.27*
8.I.Z7*
Closed Emercise 35 E-9 2
8 16 GA MD C
FE Q
8.5.4.4 (SH.1)
ST Q
8.5.4.4 O/C PI 2Y 8.5.4.4 36 M-5 2
B 16 GA MD C
FE Q
8.5.4.4 (SH.1)
ST Q
8.5.4.4 O/C PI 2Y 8.5.4.4 39 M-6 2
C 16 CK SA C
FC RO 8.I.27*
FF RV-27 Disassemble To (SH.1)
- 8. I. 2.
Closed Enercise 40 K-5 2
C 4
CK SA C
PC Q
8.5.4.1 FF (SH.1)
FC RO 8.I.27*
FF RV-27 Disassem61e To AP RO 8.I.27*
Closed Esercise 45 J-4 2
FC Q
8.5.4.1 FF (SH.1)
U 2Y 8.7.1.5*
RV-28 53 J-10 3
AC 1
RL SA C
RT SY 8.I.26' (SH.2)
LX NA 8.I.26' RT Verifies '
64 L-9 3
8 1
GA A0 C
FE Q
8.5.4.4 (SH.2)
ST Q
8.5.4.4 0;C FS Q
8.5.4.4 2
PI 2Y 8.5.4.4 68 K-11 2
0 16 RD SA C
RD NA NA Non-Testable (SH.1) 69 K-12 NC D
16 RD SA C
RD NA NA Non-Testable (SH.1) 74 J-3 2
8.5.4.1 FF (SH.1)
U ZY 8.7.1.5*
RV-28 75 K-8 2
C 4
CK SA C
FC Q
8.5.4.1 FF (SH.2) 76 L-8 2
C 2
CK SA C
PC Q
8.5.4.1*
FF (SH.2)
FC CS 8.I.11.18 FF CS-16 8.I.1.1 Rev. 1 Page 141 of 172
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1. 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: 5243 SHEET 1 SYSTEM: HIGH PRESSURE COOLANT INJECTION (2301)
P&ID: 5244 SHEET 2 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test PNPS Proc.
Test Relief Norber Coor Class Cat Site Tvoe Troe Position Ret.
Free Num6er Direction Recuest Notes 216 H-9 2
C 2
CK SA C
PC Q
8.5.4.1 FF (SH.2)
FC RO 8.I.27*
FF RV-27 Disassem61e To AP RO 8.I.27' Closed Emertise 217 K-4 2
C 2
CK SA C
PC Q
8.5.4.1 FF (SH.1)
FC RO 8.I.27*
FF RV-27 Disassemble To AP RO 8.I.27' Closed Esercise 218 J-3 2
AC 1
CK SA C
FC CS 8.I.11.8 FF CS-15 (SH.1)
U ZY 8.7.1.5 220 F-5 1
AC 1
SK SA 0
FC RO 8.M 3-2 RF RV-22 AP RO 8.M.3-2 Open (SH.1)
LX RC 8.M.3-2 RV-22 232 N1 2
C 3
CK SA C
FC CS 8.I.11.10 FF CS-07 (SH.1)
AP RO 8.I.11.10 Closed 233 51 2
C 3
CK SA C
FC CS 8.I.11.10 FF CS-07 (SH.1)
AP RO 8.I.11.10 Closed 9068A J-2 2
A 1
GL 50 C
FE Q
8.5.4.4 (SH.1)
ST Q
NA RV-25 F5 Q
8.5.4.4 C
U 2Y 8.7.1.5*
90688 J-2 2
A 1
GL 50 C
FE Q
8.5.4.4 (SH.1)
ST Q
NA RV-25 F5 Q
8.5.4.4 C
U 2Y 8.7.1.5*
9312 K-10 2
8 1
GL AO C
FE Q
8.5.4.4 (SH.1)
ST Q
8.5.4.4 C
F5 Q
8.5.4.4 C
PI 2Y 8.5.4.4 9313 K-10 2
B 1
GL A0 C
FE Q
8.5.4.4 (SH.1)
ST Q
8.5.4.4 C
FS Q
8.5.4 4 C
PI 2Y-8.5.4.4 8.I.1.1 Rev. 1 Page 142 of 172
TA8LE INSDtWICE VALVE TESTING PROGRAM ISI C1 ASS 1, 2. 3 afb NC VALVES PILGRIM IRfCLEAR POWER STATION PEID: M-245 SHEET 1 SYSTEM: REACTOR CDRE COOLING SYSTEM (1301)
PEID: IS-246 SHEET 2 V41ve P&ID ISI Valve Valve Valve Actuator Normal Test' Test PNPS Proc.
Test Relief Number Coor Class Cat Size Tvoe Tvoe Position Rant.
Free Num6er Direction Recuest Notes 1
E-12 2
B
?.
GA SO O
FE Q
8.5.5.1 (SH.2)
ST Q
8.5.5.1 C
RV-04 FS Q
8.5.5.1 C
Closed PI 2Y 8.5.5.1 2
E-11 2
NA 2
GV HO O
FE Q
8.5.5.1 Gov. Valve -
(HYD-159) (SH.2)
ST Q
8.5.5.1 O
mented Rut *mt PI 2Y 8.5.5.1 9
E-10 2
D 8
RD SA C
RD NA NA Mon-Testable (SH.2) 12 L-7 3
8 1
GL AO C
FE Q
8.5.5.4 (SH.2)
ST Q
8.5.5.4 C
FS Q
8.5.5.4 C
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP R0 8.M.3-2 Open (SH.1)
AC 1
SK SA 0
FC RO 8.M.3-2 RF RY-22 AP RO 8.M.3-2 Open (SH.11 LX RO 8.M.3-2 RW-22 16 C-6 1
A 3
GA MO O
FE Q
8.5.5.4 (SH.1)
ST Q
8.5.5.4 O/C PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 17 C-7 1
A 3
GA M0 O
FE Q
8.5.5.4 (SH.1)
ST Q
8.5.5.4 O/C PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 8.I.1.1 Rev. 1 Page 143 of 172
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TASLE INSutVICE VALVE TESTING PRDEIIAM ISI t2 ASS 1. 2. 3 MB NC VALVES PILGRIM IEELEAR POWER STATISE P&ID: M-245 SHEET 1 SYSTDt: REACTOR CDRE CDOLING SYSTEM (1301)
-P&ID: M-246 SHEET 2 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test PNPS Proc.
Test Relief Number Coor Class Cat Sire Type Tyce Position Ret.
Free Iluster Direction Recuest hotes 49 E-7 1
A 4
GA M0 C
ST CS 5.I.11.11 0/C CS-09 PI 2Y 8.5.5.7 LJ 2Y 8.7.1.5 LP 2Y 8.5.5.7 50 E-7 1
AC 4
CK SA C
FC CS 8.I.11.9 FF CS-04 iSH.1)
LP 2Y 8.5.5.7 53 D-8 2
9 4
GL M0 C
FE Q
8.5.5.4 (SH.1)
ST Q
8.5.5.4 C
PI ZY 8.5.5.4 59 J-7 2
C 2
CK SA C
PC Q
8.5.5.1 FF (SH.1)
FC RO 8.I.27*
FF RV-27 Disass d ie To AP RO 8.I.27' Closed Exercise 60 H-8 2
B 2
GL M0 C
FE Q
8.5.5.4 (SH.1)
ST Q
8.5.5.4 O/C PI
"'Y 8.5.5.4 61 E-13 2
B 3
GA M0 C
FE Q
8.5.5.1 Also 8.5.5.4 (SH.2)
ST Q
8.5.5.1 O/C Also 8.5.5.4 PI 2Y 8.5.5.4 62 J-7 2
8 2
GL M0 C
FE Q
8.5.5.4 (SH.2)
ST Q
8.5.5.4 0/C PI ZY 8.5.5.4 63 K-6 2
C 2
CK SA C
PC Q
FF RV-27 Disassemble To (SH.2)
AP NO 8.I.2F*
Closed Emercise 64 J-6 2
AC 8
SC SA LO/C FC Q
8.5.5.1 FF (SH.1)
LX 2Y 8.7.1.12 8.I.1.1 Rev. 1 Page 145 of 172
TABLE INSERVICE VALVE TESTING PRCSRUE ISI CLASS 1. 2, 3 AND NC VALVES PILGRIM 3RfCLEAR POWER STATIGE PEID: 84-245 SHEET 1 SYS1EM: REACTOR CORE C00LIeEE SYSTDI (1301)
PEID: 95-246 SHEET 2 -
V;1ve P&ID ISI Valve Valve Valve Actuator Normal Test Test FNPS Proc.
Test Relief Number Coor Class Cat Size Tvoe Type Position Rant.
Free Number Direction Request Notes 70 J-12 3
RT SY 8.I.26*
(SH.2)
LX 81 4 8.I.26' RT Verifles 89 J-10 3
C 1
CK SA C
FC RO 8.I.27*
FF RV-27 Disassedle To (SH.2)
AP E0 8.I.27*
Closed Enertise 90 K-11 3
C 1
CK SA C
PC Q
8.5.5.1 FF (SH.2)
FC RO 8.I.27' FF RW-27 Disassemele To AP n0 8.I.27*
Closed Esercise 9067 H--6 2
C 1
SK SA C
FC CS 8.I.11.10 FF CS-11 (SH.1)
AP RO 8.5.5.1 Closed 8.I.1.1 Rev. 1 Page 146 of 172
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N 1 1 1 1
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1. 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-250 SHEET 1 of 2 SYSTEM: CONTROL ROD DRIVE HYDRAl'LIC P&ID: M-250 SHEET 2 of 2 SYSTEM (302)
Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test PNPS Proc.
Test Relief Number Coor Class Cat Sire Tvoe Tvoe Position Rturt.
Frea Number Direction Request Notes 21A G-3 2
B 1
PG A0 0
FE Q
8.3.3 (SH.2)
ST -
Q 8.3.3 0
ST RD 8.M.1-31 C
RV-26 FS Q
8.3.3 C
PI 2Y 8.3.3 21B G-7 2
8 1
PG A0 0
FE Q
8.3.3 (SH.2)
ST Q
8.3.3 0
RV-26 FS Q
8.3.3 C
PI 2Y 8.3.3 22A D-4 2
B 2
PG A0 0
FE Q
8.3.3 (SH.2)
ST Q
8.3.3 0
RV-26 FS Q
8.3.3 C
PI 2Y 8.3.3 228 D-7 2
B 2
PG A0 0
FE Q
8.3.3 (SH.2)
ST Q
8.3.3 0
RV-26 FS Q
8.3.3 C
PI 2Y 8.3.3 23A G-3 2
B 1
PG A0 0
FE Q
8.3.3 (SH.2)
ST Q
8.3.3 0
RY-26 FS Q
8.3.3 C
PI 2Y 8.3.3 23B G-7 2
8 1
PG A0 0
FE Q
8.3.3 (SH.21 ST Q
8.3.3 0
ST RD 8.M.1-31 C
RV-26 i
FS Q
8.3.3 C
PI 2Y 8.3.3 8.I.1.1 Rev. 1 Page 149 of 172
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a TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-250 SHEET 1 of 2 SYSTEM: CONTROL R00 DRIVE HYDRAULIC P&ID: M-250 SHEET 2 of 2 SYSTEM (302)
V;1ve P&ID ISI Valve Valve Valve Actuator Non al Test Test PNPS Proc.
Test Relief Number Coor Class Cat Size Tvoe Tvoe f.;t.W e Rcant.
Frea Number Direction Request Notes 126 B-17 2
8 1
(SH.1)
RV-09 PI 2Y 9.9 127 A-17 2
B 0.5 PG A0.
(SH.1)
RV-09 PI ZY 9.9 132 C-18 2
D 0.5 RD SA C
RD NA NA Non-Testable (HCU)
(SH.1) 138 C-16 2
C 0.5 CK SA 0
FC Q
8.3.2 RF RV-10 (HCU)
(SH.1) 8.I.1.1 Rev. 1 Page 151 of 172
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-251 iYSTEM: RECIRC. PUMP INSTRUP!ENTATION (2fz)
Valve P&ID ISI Valve-Valve Valve Actuator Normal Test Test FMPS Proc.
Test Relief Number Coor Class Cat Size Tvoe Tvoe Position Ret.
Free Number Direction Recuest Notes 2-5A D-1 2
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open LX RO 8.M.3-2 RW-22 2-5B D-1 2-AC 1
SK SA 0
FC R0 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open Lx RO 8.M.3-2 RV-22 2-6A 0-1 2
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open LX RO 8.M.3-2 RV-22 2-6B D-1 2
AC 1
SK SA 0
FC it0 8.M.3-7 RF RV-22 AP RO 8.M.3-2 Open LX RO 8.M.3-2 RV-22 F013A C-2 2
FC RO 8.7.1.5 RF RV-13 LJ 2Y 8.7.1.5 F013B C-2 2
FC RO 8.7.1.5 RF RV-13 LJ ZY 8.7.1.5 F017A C-1 2
FC RO 8.7.1.5 RF ftV-13 LJ 2Y 8.7.1.5 F0178 C-1 2
FC R0 8.7.1.5 RF RV-13 LJ 2Y 8.7.1.5 8.I.1.1 Rev. 1 Page 152 of 172
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-252 SYSTEM: FEEDWATER SYSTEM (6)
Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test PNPS Proc.
Test Relief Rw6er Coor Class Cat Size Tvoe Tvec Position Ret.
Freo Mr Direction Reouest Notes 58A E-4 1
FC RO 8.7.1.5 RF RV-12 AP RO 9.3 Open LJ 2Y 8.7.1.5 RV-28 588 F-4 1
FC RO 8.7.1.5 RF RV-12 AP RD 9.3 Open LJ 2Y 8.7.1.5 W-28 62A E-3 1
FC RO 8.7.1.5 RF RV-12 AP RD 9.3 Open LJ ZY 8.7.1.5 RV-28 62B F-3 1
FC R0 8.7.1.5 RF RV-12 AP RO 9.3 Open LJ 2Y 8.7.1.5 RV-28 8.I.1.1 Rev. 1 Page 153 of 172
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-252 SYSTEM: REACTOR RECIRCULATION SYSTEM (202)
V;.1ve P&ID-ISI Valve Valve Valve Actuator Normal Test Test PNPS Proc.
Test Relief Number Coor Class Cat Size Tvoe Tvoe Position Rett.
Free Na6er Direction Recuest Notes 4A L-5 1
m 28 G4 m
0 m
m m
Passive PI 2Y 8.I.11.1 48 56 1
NA 28 GA 10 0
m m
M Passive PI 2Y 8.I.11.2 SA L-8 1
8 28 GA MO O
FE CS 8.I.11.1 CS-05 Note 1 ST CS 8.I.11.1 C
CS-05 Note 1 PI 2Y 8.I.11.1 58 M-6 1
B 28 GA M0 O
FE CS 8.I.11.2 CS-05 Note 1 ST CS 8.I.11.2 C
CS-05 Note 1 PI 2Y 8.I.11.2 NOTES:
1.
When core flow from recirculation pump operation is not required l
8.I.1.1 Rev. 1 Page 154 of 172
TABLE INSERVICE VALVE TESTING PROGPAM
'ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-252 SYSTEM: PAIN STEAM ISOL., ADS &
SAFETY RELIEF (203)
V;.lve P&ID ISI Valve Valve Valve Actuator Normal Test Test PNPS Proc.
Test Relief Number Coor Class Cat Sire Tvoe Twee Position Rant.
Frea Ember Direction Request Notes IA C-9 1
A 20 GL A0 0
FE Q
8.7.4.4 ST Q
8.7.4.4 C
FS Q
8.7.4.4 C
PI 2Y 8.7.1.6 LJ 2Y 8.7.1.6 RW-28 1B E-9 1
A 20 GL A0 0
FE Q
8.7.4.4 ST Q
8.7.4.4 C
FS Q
F.7.4.4 C
PI 2Y 8.7.1.6 LJ 2Y 8.7.1.6 RV-28 1C F-7 1
A 20 GL A0 0
FE Q
8.7.4.4 ST Q
8.7.4.4 C
FS Q
8.7.4.4 C
PI 2Y 8.7.1.6 LJ 2Y 8.7.1.6 RY-28 ID F-7 1
A 20 GL A0 0
FE Q
8.7.4.4 ST Q
8.7.4.4 C
FS Q
8.7.4.4 C
PI 2Y 8.7.1.6 LJ 2Y 8.7.1.6 RV-28 2A C-11 1
A 20 GL A0 0
FE Q
8.7.4.4 ST Q
8.7.4.4 C
FS Q
8.7.4.4 C
PI 2Y 8.7.1.6 LJ ZY 8.7.1.6 RV-28 1
8.I.1.1 Rev. 1 Page 155 of 172
TABLE INSEWICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND feC VALVES PILGRIM NUCLEAR POWER STATION F&ID:. M-252 SYSTEM: PEIN STEAM ISOL., ADS &
SAFETY RELIEF (203)
Vsive P&ID ISI Valve Valve Valve -Actuator Normal Test Test PNPS Proc.
Test Relief Number Coor Class Cat Size Tvoe Type Position Ront.
Frec Nt.Wr Direction Request Notes 28 E-9 1
A 20 GL A0 0
FE Q
8.7.4.4 ST Q
8.7.4.4 C
FS Q
8.7.4.4 C
PI ZY 8.7.1.6 LJ 2Y 8.7.1.6 RV-28 2C F-7 1
A 20 GL A0 0
FE Q
8.7.4.4 ST Q
8.7.4.4 C
FS Q
8.7.4.4 C
PI 2Y 8.7.1.6 LJ ZY 8.7.1.6 RV-28 2D F-7 1
A 20 GL A0 0
FE Q
8.7.4.4 ST Q
8.7.4.4 C
FS Q
8.7.4.4 C
PI 2Y 8.7.1.6 LJ 2Y 8.7.1.6 RV-28 3A C-7 1
AC 6
RL/SV A0/SA C
FE RO 8.5.6.2 RV-11 ST RO NA RY-11 FS RO 8.5.6.2 C
RV-11 PI ZY 8.5.6.2 RT SY 8.I.26*
LX MA 8.I.26' RT Verifies 38 F-7 1
AC 6
RL/SV A0/SA C
FE RO 8.5.6.2 RV-11 ST RO NA RV-11 FS RO 8.5.6.2 C
RV-11 PI ZY 8.5.6.2 RT SY 8.I.26*
LX NA 8.I.26' RT Verifies 8.I.1.1 Rev. 1 Page 156 of 172 N
w.-
TABLE INSERVICE VALVE TESTING PROGw.AM ISI CLASS 1. 2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-252 SYSTEM: M IN STEAM ISOL.. ADS 8.
SAFETY RELIEF (203)
V;1ve P&ID ISI Valve Valve Valve Actuator Normal Test Test F WS Proc.
Test Relief Number Coor Class Cat Sire Twoe Tvoe Position Rett.
Frea Ntader Direction Request Notes 3C F-7 1
AC 6
RL/SV A0/SA C
FE RO 8.5.6.2 RY-11 ST RO NA RV-11 FS RO 8.5.6.2 C
RY-11 PI 2Y 8.5.6.2 RT 5Y 8.I.26*
LX NA 8.I.26*
RT Verifies 3D E-9 1
AC 6
RL/SV A0/SA C
FE RO 8.5.6.2 RV-11 ST RO NA RV-11 FS RO 8.5.6.2 C
RV-11 PI 2Y 8.5.6.2 RT SY 8.I.26' LX NA 8.I.26*
RT Verifies 4A E-8 1
AC 6
RT SY 8.I.26*
LX NA 8.I.26*
RT Verifies 48 E-7 1
AC 6
RT SY 8.I.26' LX NA 8.I.26*
RT Verifies 8.I.1.1 Rev. 1 Page 157 of 172
.7
t.
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND MC VALVES PILGRIM NUCLEAR POWER STATION SYSTEM: NUCLEAR BOILER SYSTEM (220)
P&ID: M-252
. V;;1ve P&ID ISI Valve Valve Valve Actuator Nonnal Test Test PNPS Proc.
Test Relief Number Coor Class Cat Sire Type Tvoe Position Rett.
Frec Misaber Direction Request Notes 1
C-9 1
A 3
GA MD C
FE Q
8.7.4.3 ST Q
8.7.4.3 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 2
C-11 1
A 3
GA NO C
FE Q
8.7.4.3 ST Q
8.7.4.3 C
PI ZY 8.7.1.5 LJ 2Y 8.7.1.5 44 K-4 1
A 1
GA A0 C
FE Q
8.7.4.3 ST Q
8.7.4.3 C
FS Q
8.7.4.3 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 f
45 K-3 1
A 1
GL A0 C
FE Q
8.7.4.3 I
ST Q
8.7.4.3 C
FS Q
8.7.4.3 C
l PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 46 B-4 1
B 1
GL A0 C
FE CS 8.I.11.11 CS-06 ST CS 8.I.11.11 C
CS-06 FS CS 8.I.11.11 C
CS-06 PI 2Y 8.I.11.11 47 B-5 1
B 1
GL A0 C
FE CS 8.I.11.11 CS-06 ST CS 8.I.11.11 C
CS-06 FS CS 8.I.11.11 C
CS-06 PI 2Y 8.I.11.11 8.I.1.1 Rev. 1 Page 158 of 172
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-252 SYSTEM: COMPRESSED AIR (31)
Vsive P&ID ISI Valve Valve Valve Actuator Normal Test Test PNPS Proc.
Test Rei bf Number Coor Class Cat Size Tvoe Type Position Rant.
Free Hum 6er Direction Recuest Notes 84A B-9 3
C 1
CK SA C
FC Q
8.7.4.4 FF RV-18 AP RO 8.7.1.14 Closed 848 E-10 3
C 1
CK SA C
FC Q
8.7.4.4 FF RV-18 AP RO 8.7.1.14 Closed 840 E-11 3
C 1
CK SA C
'FC Q
8.7.4.4 FF RY-18 AP RO 8.7.1.14 Closed 84D E-11 3
C 1
CK SA C
FC Q
8.7.4.4 FF RV-18 AP R0 8.7.1.14 Closed 85A B-11 3
C 1
CK SA C
FC Q
8.7.4.4 FF RV-18 AP RO 8.7.1.14 Closed 858 E-10 3
C 1
CK SA C
FC Q
8.7.4.4 FF RV-18 AP RO 8.7.1.14 Closed BSC E-11 3
C 1
CK SA C
FC Q
8.7.4.4 FF RV-18 AP RO 8.7.1.14 Closed 850 E-11 3
C 1
CK SA C
FC Q
8.7.4.4 FF RV-18 AP RO 8.7.1.14 Closed 372A C-7 3
AC 1
CK SA C
FC CS 8.I.11.15 FF CS-13 LX 2Y 8.7.1.10 RV-30 3728 E-10 3
AC 1
CK SA C
FC CS 8.I.11.15 FF CS-13 LX ZY 8.7.1.10 RV-30 372C E-11 3
AC 1
CK SA C
FC CS 8.I.11.15 FF CS-13 LX 2Y 8.7.1.10 RV-30 3720 E-11 3
AC 1
CK SA C
FC CS 8.I.11.15 FF CS-13 LX 2Y 8.7.1.10 RV-30 373A B-7 3
A 3/4 GL M
C FE m
m Passive (Manual)
LK 2Y 8.7.1.10 RV-30 3738 E-9 3
A 3/4 GL m
C FE E
4*
Passive (Manual)
LX 2Y 8.7.1.10 RV-30 373C F-7 3
A 3/4 GL E
C FE E
E Passive (Manual)
LX ZY 8.7.1.10 RV-30 3730 F-8 3
A 3/4-GL m
C FE m
m Passive (Manual)
LX ZY 8.7.1.10 RV-30 8.I.1.1 Rev. 1 Page 159 of 172
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S S
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T T
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1 1 1 1 1 1 1 1
ai VS ev l t a a C C
C C
C C C C C C C C
VC A A
A A
ss I a S l 3 3
3 3
3 3 3 3 3 3 3 3
I C D r 2 2 2 2 7-9 9
9 9 9 9 9 1 1 1 1
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l b 6 8
8 8
8 8 8 8 8 88 8 I
a m 0 0
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9 9
9 9 9 9 9 99 9 P
N
TABLE INSERVICE VALVE TESTIIRE PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM IRfCLEAR POWER STATION FRID: M-252 SYSTEM: NtfCLEAR BOILER (261)
Vsive P&ID ISI Valve Valve Valve Actuator Normal Test Test PNPS Proc.
Test Relief Nr.ber Coor Class Cat Sire Tvoe Tvoe Position Rant.
Free Nas6er Direction Recuest Notes l
17A D-11 1
.1 SK SA-0 FC RO 8.M.3-2 RF NY-22 AP R0 8.M.3-2 Open LX RO 8.M.3-2 RV-22 17B E-11 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 l
AP RO 8.M.3-2 Open LX RD 8.M.3-2 RV-22 17C D-11 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open LX RO 8.M.3-2 RV-22 17D E-11 1
AC 1
SK SA 0
F.
RO 8.M.3-2 RF RV-22 AP R0 8.M.3-2 Open LX RO 8.M.3-2 RV-22 18A D-11 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open LX RO 8.M.3-2 RV-22 188 E-11 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open LX RO 8.M.3-2 RV-22 18C D-11 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open LX RO 8.M.3-2 RV-22 ISD E-11 1
AC 1
SK SA 0
FC R0 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open LX RO 8.M.3-2 RV-22 19A K-11 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RD 8.M.3-2 Open LX RO 8.M.3-2 RV-22 19B J-11 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open LX RO 8.M.3-2 Rv-22 20A K-11 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RW-22 AP RO 8.M.3-2 Open LX RO 8.M.3-2 RY-22 20B J-11 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open LX RO 8.M.3-2 RV-22 8.I.1.1 Rev. 1 Page 161 of 172
TABLE IItSOtVICE VALVE TESTING Pit 0GItAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM DEJCLEAR POWUt STATION P&ID: 75-252 SYSTDt: IRJCLEAR BOILER (261)
Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test PNPS Proc.
Test Relief Norber Coor Class Cat Sire Tvoe Twee Position R cytt.
Frea Number Direction Request Notes 21A K-11 1
AC 1
SK SA O
FC RO 8.M.3-2 RF RV-22 AP RD 8.M.3--2 Open LX RO 8.M.3-2 RV-22 218 L-11 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RD 8.M.3-2 Open LX RO 8.M.3-2 Itv-22 22A K-11 1
FC RO 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open LX RO 8.M.3-2 RY-22 228 L-11 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open LX RO 8.M.3-2 RV-22 67A E-3 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open LX RO 8.M.3-2 RV-22 678 E-3 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open LX R0 8.M.3-2 RV-22 67C E-3 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open LX RO 8.M.3-2 RV-22 67D E-3 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open LX RO 8.M.3-2 RV-22 67E D-3 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open LX RO 8.M.3-2 RV-22 i
67F 0-3 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RW-22 AP RO 8.M.3-2 Open LX RO 8.M.3-2 RV-22 67G D-3 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RD 8.M.3-2 Open LX RO 8.M.3-2 RW-22 67H D-3 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open LX RO 8 M.3-2 RV-22 8.I.T.1 Rev. 1 Page 162 of 172
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TABLE INSERVICE VALVE TESTING IMOGtAR ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM SRfCLEAR POWER STATIG8 SYSTEM: NUCLEAR h0ILER VESSEL PSID: M-253 SHEET 1 of 2 INSTRUMENTATION (263)
P&ID: M-253 SHEET 2 of 2 Valve P&ID ISI Valve -Valve Valve Actuator Normal Test Test PNPS Proc.
Test Relief Number Coor Class Cat Sire Tvoe Tvoe Position Rant.
Frec Mus6er Direction Request Notes 2-27 C-7 1
AC 1
'SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open (SH.2)
., JX RO 8.M.3-2 RY-22 2-31A B-7 1
AC 1
SK SA 0
FC R0 8.M.3-2 RF RV-22 AP R0 8.M.3-2 Open (SH.2)
~RO 8.M.3-2 RV-22 LX 2-31B B-7 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RY-22 AP RO 8.M.3-2 Open (SH.2)
LX RO 8.M.3-2 RV-22 2-33 D-4 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open (SH.2)
LX RO 8.M.3-2 RY-22 2-37 E-6 1
AC 1
SK SA 0
FC R0 8.M.3-2 RF RF-22 AP RO 8.M.3-2 Open
( SH.1 ) -
LX RO 8.M.3-2 RV-22 2-42A D-6 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RY-22 AP RO 8.M.3-2 Open (SH.1)
LX RO 8.M.3-2 RV-22 2-42B D-3 1
AC 1
SK SA 0
FC R0 8.M.3-2 RF RV-22 AP R0 8.M.3-2 Open (SH.1)
LX RO 8.M.3-2 RV-22 2-125A F-6 1
AC 1
SK SA 0
FC R0 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open (SH.1)
LX __
RO 8.M.3-2 RV-22 2-1258 F-3 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open (SH.1)
LX 90 8.M.3-2 RV-22 51 B-7 1
AC 1
SK SA O
~ RO 8.M.3-2 Open (SH.2)
LX R0 8.M.3-2 RV-22 53 B-7..
1 AC 1
SK SA 0
' FC RO d.M.3-2 RF RV-22 AP RO 8.M.3-2 Open (SH.2)
LX RO 8.M.3-2 RV-22 8.I.1.1 Rev. 1 Page 166 of 172
-.. -. ~
_. ~
- _ =
_. _ _ _ =
TABLE.
INSDtWICE VALVE TESTING PROGRAM ISI, CLASS 1, 2, 3 Als NC VALVES PILGRIM NUCLEAR POWut STATION SYSTEM: NUCLEAR BOILER VESSEL PSID: 5253 SHEET 1 of 2 INSTRUE NTATION (263)
PEID: 5253 SHEET 2 of 2 l
Volve P&ID ISI Valve Valve Valve Actuator Normal Test
' Test PNPS Proc.
Test Relief Number 'Coor Class Cat Sire Tvoe Type Position Rant.
Freo
""r Direction Reouest Notes 55 B-7 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF
.RV-22 AP RD
.8.M.3-2 Open (SH.2)
LX RD 8.M.3-2 RV-22 57 B-7 1
AC 1
SK SA 0
FC '
RO 8.M.3-2 RF RV-22.
LX RO 8.M.3-2 RV-22 59 B-7 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RD 8.M.3-2 Open (SH.2)
LX RO 8.M.3-2 RV-22 61 B-7 1
AC 1
- SK SA 0
FC RO 8 M.3-2 RF RV-22 AP RO 8.M.3-2 Open (SH.2)
LX RO 8.M.3-2 RV-22 63 B-7 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open (SH.2)
LX RO 8.M.3-2 RV-22 65 B-7 1
AC 1
SK SA 0
FC RO 8.M 3-2 RF RV-22 AP RO 8.M.3-2 Open (SH.2)
LX RO 8.M.3-2 RY-22 67 A-7 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RY-22 AP RO 8.M.3-2 Open (SH.2)
LX RO 8.M.3-2 RV-22 69 A-7 1
AC 1
SK SA -
0 FC RO 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open (SH.2)
LX
- RO 8.M.3-2 RV-22 71 A-7 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RO 8.M.3-2 Open i
. (SH.2)
LX RO 8.M.3-2 RV-22 73 A-7 1
AC 1'
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RO 8 M.3-2 Open (SH.2)
LX RO B.M.3-2 RV-22 75 A-7 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 AP RD 8.M.3-2 Open (SH.2)
LX RO
-8.M.3-2 RV-22 8.I.1.1 Rev. 1 Page 167 of 172
,. - -. ~... - -...
,.c-
TABLE
' INSERVICE VALVE TESTING PMDGRMt ISI CLASS 1, 2. 3 AIE NC VALVES PILGRIM NUCLEAft POW 0t STATION P&ID: M-253 SHEET 1 of 2 -
SYSTEM: IRJCLEAR BDILER VESSEL P&ID: M-253 SHEET 2 of 2 INSTRUpelTATION (263)
Valve P&ID ISI Valve Valve Valve Actuator Normal -
Test Test PMPS Proc.
Test Relief Number Coor Class Cat Sire ' Type Tvoe Position Rcytt.
Frea hr Direction Request Notes 77 A-7 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RW-22 (SH.2)
AP RO 8.M.3-2 Open LX RO 8.M.3 RW-22 79 E-4 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 (SH.2)
.Rn 8.M.3-2 Open LX RO S.M.3-2 RV-22 81 E-4 1
'1 SK SA O
FC RO 8.M.3-2 RF RV-22 (SH.2)
AP RC 8.M.3-2 Open LX Ru 8.M.3-2 RV-22 83 E-6 1
AC 1
SK SA 0
FC KO 8.M.3-2 RF RV-22 (SH.1)
AP RO 8.M.3-2 Open LX RO 8.M.3-2 Rv-22 90 E-4 1
AC-1 SK SA O
FC R0 8.M.3-2 RF RV-22 (SH.2)
AP R0 8.M.3-2 Open LX RO 8.M.3-2 RV-22 92 D-4 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 (SH.2)
AP RO 8.M.3-2 Open LX RO 8.M.3-2 RV-22 8.I.1.1 Rev. 3 Page 168 of 172
q TABLE !
_ INSERVICE VALVE TESTING PROGRAM ISI CLASS 1. 2,'3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-259
' SYSTEM: DIESEL GENERATOR TURBO AIR ASSIST U STEM (47)
Valve F&ID ISI Valve Valve Valve Actuator Normal Test' Test PNPS Proc.
Test Relief.
Number Coor Class Cat Sire Tvoe Tvoe Position Roset.
Frea Naber Direction Request Notes 201A G-7 NC
-AC 0.75 CK SA C
FC Q
' 8.9.1 FF tx 2Y 8.9.i.2*
RV-30 201B_
.C-7
-- NC
FC Q._
8.9.1 FF LX 2Y 8.9.1.2*
RW-30 201C E-7 NC AC-0.75 CK SA C
FC Q
8.9.1 FF LX 2Y 8.9.1.2*
RY-30 203A F-7 NC AC 0.75 GA m
C FE NA NA LX-2Y 8.9.1.2*'
RV-30 203B B-7 NC-AC 0.75 GA - m C
FE M4 NA LX 2Y 8.9.1.2*
RV-30 203C E-6 NC AC 0.75 GA m
C FE NA NA LX 2Y 8.9.1.2*
RV-30 301A C-4 NC AC 0.75 CK SA C
FC Q
8.9.1 FF LX 2Y 8.9.1.2*
RV-30 301B G-4 NC AC 0.75 CK SA C
FC Q
8.9.1 FF LX 2Y 8.9.1.2*
RV-30 301C E-4 NC AC 0.75 CK SA C
FC Q
8.9.1 FF LX 2Y 8.9.1.2*
RV-30 303A C-3 NC AC 0.75 GA m
C FE NA NA LX 2Y 8.9.1.2*
RV-30
~ 3039 F-3 NC AC 0.75 GA m
C FE NA NA LX 2Y 8.9.1.2*
RV-30 303C E-3 NC AC 0.75 GA m
C FE NA NA LX 2Y 8.9.1.2*
RV-30 8.I.1.1 Rev. 1 l
Page 169 of 172 L
- m' "W""'
" ' ' ^ ' * '"
TABLE.'
INSERVICE VALVE TESTING PROGRAM ZSI CLASS 1. 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-259 SYSTEM: DIESEL GENERATOR TURBO AIR ASSIST SYSTEM (47)
Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test PNPS Proc.
Test Relief.
Nuwber Coor Class Cat Size Type Tvoe Position Rant.
Frea Number Direction Reevest Notes 4563A G-7 NC AC 0.75 SV SA C
.. RT SY 8.I.26*
LX NA 8.I.26*
RT Verifies 45638 D-4 NC AC 0.75
RT SY 8.I.26*
LX MA 8.I.26*
RT Verifies 4563C D-7 NC AC 0.75 SV SA C
RT SY.
8.I.26*
LX NA 8.I.26*
RT Verifies __
4563D G-4 NC AC -
RT SY 8.I.26" LX NA 8.I.26*
kl Verifies 4565A E-7 NC AC 0.75 SV SA C
RT.
SY 8.I.26" LX NA 8.I.26*
RT Verifies 45658 E-4 NC AC 0.75 SV SA -
C RT SY 8.I.26*
LX
.4A 8.I.26*
RT Verifies 4569A E-6 NC B
1.5 GA 50 C
FE Q
8.9.1-RV-19 ST Q
NA RV-19 FS 0
8.9.1 C
RY-19 45698 E-2 NC B
1.5 GA 50 C
FE Q
8.9.1 RV-19 ST Q
NA RY-19 FS 0
8.9.1 C
RV-19 4570A F-6 NC B
1.5 GA SO C
FE.
Q 8.9.1 RV-19 ST Q
NA RY-19 FS 0
8.9.1 C
RV-19 45708 E-2 ht B
1.5 GA SO C
FE Q
8.9.1 RV-19
.ST Q
NA RY-19 FS 0
8.9.1 C
RV-19 8.I.1.1 Rev. 1 Page 170 of 172
-~
TABLE.
2NSERVICE VALVE TESTING P90 GRAM ISI CLASS 1. 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: MIQ-1-5 (VENDOR DRAWING)~
SYSTEM: TRAVERSE INCORE PROBE (45)
LValve P&ID ISI Valve Valve Valve Actuator Normal Test Test' PNPS Proc.
Test Relief Number Coor Class Cat Size 'Tvoe Tvoe Position Rant.
Frea Ntadner Direction Reccest Notes 300A
'2 A
0.25 BL 50 C
FE Q
8.7.4.3 (Ball A)
ST Q
8.7.4.3 C
RV-04 FS Q
8.7.4.3 C
'2Y 8.7.1.5 LJ 2Y 8.7.1.5 3008 2
A 0.25 BL SO C
FE Q
8.7.4.3 (Ball B)
ST Q
8.7.4,3 C
RV-04 FS Q
8.7.4.3 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 3000 2
A 0.25 BL 50 C
FE Q
8.7.4.3 (Ball C)
ST Q
8.7.4.3 C
RV-04 FS Q
8.7.4.3 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 300D 2
A 0.25 BL 50 C
FE Q
8.7.4.3 (Ball D)
ST Q
8.7.4.3 C
RV-04 FS Q
8.7.4.3 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 N Check 2
AC 0.25 CK.
SA O
FC RO 8.7.1.5 RF RV-05 2
LJ 2Y 8.7.1.5 301A LShear A) 2 D
0.25 SH EX 0
EX 10Y 3.M.2-5.6.8*
3018 (Shear B) 2 0
0.25-SH EX 0
EX 10Y 3.M.2-5.6.8*
301C (Shear C) 2 D
0.25 SH EX 0
EX 10Y 3.M.2-5.6.8*
301D (Shear D) 2 0
0.25 SH EX 0
EX 10Y 3.M.2-5.6.8*
8.I.1.1 Rev. 1 Page IT. of 172
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