ML20005F079
| ML20005F079 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 12/13/1989 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20005F077 | List: |
| References | |
| 8.I.1.1, NUDOCS 9001120266 | |
| Download: ML20005F079 (171) | |
Text
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BOSTON EDISON-5 thf0RMAison
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-l PILGRIM NUCLEAR POWER STATION
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Procedure No.'8.I.1.1 I
l INSERVICE PUMP AND VALVE TESTING PROGRAM-t
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g y y w S.2.0
.y Approved Oh
/ L3M BT QA Manager Date
/ /2.-4f1 Approved _ M 1 ant Manager.~
' Date Safety Review:
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Requi red
- 8. I.1.1 Rev. O Pr.ge 1 of 171
- 9001120266 900104 "PDR _ADOCK 05000293 PNU
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. REVISION' LOG S-Revision' Paget Description
. Level Affectef of Revision
.O
.All Upgrade IST Program to increase component 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.
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8.I.l.1 Rev. O Page 2 of 171
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' TABLE OF CONTENTSI a
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- 1 ^. 01 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
'6.0i
. INSERVICE VALVE TESTING 31
'6.1'-GENERAL INFORMATION 31
- 6.2. POST-MAINTENANCE TESTING 41 6.3J-COLD SHUTDOHN JUSTIFICATIONS 50 6.4' RELIEF REQUESTS.
67
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6.5. VALVE PROGRAM TABLE
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8.I.1.1 Rev. O Page 3 of 171
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1.0 PURPOSE y
This procedure emcompasses and controls the PNPS Inservice Test (IST)
~ Program.
It identifies the Scope of components (pumps and valves) and v
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)(11) and also identifies impractical code requirements l
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 DIS.CUSSION 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 Hinter 1980 Addenda).
The procedure 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.
p p
This procedure provides a cross-reference between a component test'
'L requirement and a station procedure implementing the test.
Additional information is provided within_the component tested listing:
safety class, category, test frequency, pump test parameters, valve test requirements, relief requests, valve cold shutdown justifications and l
remarks.
Newly incorporated component / test requirements will have l-implementing procedures identified for future incorporation. All newly identified _ component / test requirements shall be initially tested during L
the'next scheduled frequency (i.e., quarterly, cold shutdown,
~
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 (*),
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 e
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 classified as Group A, B or C per Regulatory Guide 1.26 are included as non-classed (NC). Additionally, all containment penetrations shall be classifed as e
ISI Class 1 or Class 2.
i 8.I.1.1 Rev. O Page 4 of 171
4 2.01 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 IHP 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.
3.0L 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 INA, IWV and IHP
[5] Division 1 (Draft)s 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
[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] PNPS 8.I.1, " Administration of Inservice Pump and Valve Testing"
[12] 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).
This procedure outlines the Inservice Testing Program based on the requirements of Section XI of ASME Boiler and Pressure Vessel Code, 1980 Edition through Winter 1980 Addenda.
8.I.1.1 Rev. O I
Page 5 of 171 I
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+74.0 COMPLIANCE.(Continued)'
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lIf this procedure (revised Inservice Testing Program for the site) conflicts with PNPS Tech Specs, a Tech Spec amendment shall be-cubmitted to conform the Tech Spec to this procedure in accordance~with
[10CFR50.55a(g)(5)(11)].
Until approval of the Tech Spec amendment,
. the most limiting ~ requirement shall be met.
.5.0 JESERVICE PUMP TESTIRG.
~
4 5.'11 GENERAL INFORMATION
{
Il] Applicable Code This Inservice-Testing Program for ISI Class 1, 2, 3 and NC Pumps meets the requirements of Subsection INP 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, specificLrequests 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 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:
(a) SYSTEM:
System Title (b), PUMP NUMBER:
Pump Identification Nutber (c) CLASS:
ISI Classification (Class 1, 2, 3 or NC)
(d) EklD:
PNPS drawing number (e) CQQB:
Coordinate location on the P&ID (f) SEEID. INLET PRES. DIFF PRES. FLONRATE. VIBRATION. BEARING 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 8.I.1.1 Rev. O 4
Page 6 of 171 I
.~' - - - _ - - - _ _ - - - - _ - - - -,. _ _ _ _ _ _ _, _ _ _ _ _ _
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5.1 GENERAL INFORMATION (Continued)
[3]: " Inservice: Test Quantities" Columns c,
PUMP SPEED. INLET (SUCTION) PRESSURE. DIFFERENTIAL PRESSURE (dP).
LLONRATE. VIBRATION. BEARING TEMPERATURE AND LUBRICANT LEVEL OR p
_ When the symbol'"Y" appears in a particular measured PRESSURE:
i parameter, column, that quantity will be measured during inservice testing in accordance with Subsection INP.
Requests for relief i
.are identified with~the letters "RP" under the measured parameter column in.the test table. The requests for relief are included in Section 5.4.
r
[4] Measurement of Inservice Test Quantities (a) Speed: Per IMP-4400, shaft measurements are not applicable (NA) for pumps coupled to synchronous or induction type drivers.
For variable speed pumps, the pump speed shall be set at the reference speed per INP-3100, p
(b) Inle_i_fressure:
For submerged pumps, inlet pressure will be calculated (using appropriate correction factors) from a measured tank or basin level.
Since this method does not t
comply with the requirements of-INP-4200, relief requests l
RP-3 and RP-4 have been prepared. All other inlet pressure j
measurements will be'taken using pressure instruments at or 1
near the pump inlet, j
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(c) Differential Pressure:
Differential pressure measurements I
w*ll be calculated from inlet and discharge pressure l
measurements or by direct d1N erential pressure measurement.
I.
(d)
Flowrate:. Pump discharge flowrate shall be measured.
1 (e) ylta.tlon:
Pump vibration will be measured as close as possible to the inboard bearing in a plane approximately l
. perpendicular 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 i
measurement will be taken with one of the instruments-referenced in IHP-4520 with exception if a reading.is not
-(
p applicable for a pump.
l-1 (f) Searina Temoerature:
Pump bearing temperature (s) will not be measured (See RP-2).
(g) Bearina Lubricant:
As specified in Table IHP-3100-1, the u
pump bearing lubricant level or pressure will be observed L
during inservice testing.
1^
[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 4
L as discussed.
Should a measured test quantity fall outside the
{
l allowable range, the possibility of defining an expanded allowable l
range, per ASME Code Interpretation XI-1-79-19, will be investigated for operability.
8.I.l.1 Rev. O q
Page 7 of 171 1.
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l5.l-GENERAL.INFORMATION-(Continued);
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[6] ' Corrective Action 1The operational readiness of a-pump shall be determined by 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 1
~
testing shall be doubled until the cause of the deviation is determined and the condition corrected or an evaluation is j
performed.and new reference values ~are established.:
(b) -If deviations fall within the required action range, the pumpi H
shallLimmediately be declared inoperative and not returned to service until the cause of the deviation has been determined and the r.ondition' corrected or an evaluation is performed and new reference values are established.
(c) Corrective action shall be either replacement. repair or an analysis to demonstrate that the condition does not impair pump operability and that the pump will still fulfill its function.
When an analysis is considered necessary, a new set of reference _ values shall be established after analysis completion.
[7] Instrument Accuracy, Allowable instrument accuracles are given in table INP-4110-1.
If l'
the-accuracies of plant installed _ instrumentation is not acceptable, temporary instruments meeting-the acceptable accuracies will be used.
[
[8] Exempt Safety Related Pumps 1.
L The Reactor Recirculation Pumps and the Recirculation Jet Pumps are exempt from inservice testing.
These pumps do not meet the scope of IHP-1100 in that they are not required to perform a specific function in shutting down the reactor or mitigating the I
consequences of an accident nor are they provided with an lu emergency power source.
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8.I.1.1 Rev. O Page 8 of 171
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PUMP POST-MAINTENANCE TESTING 5.2 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 determination process, a work scope guideline and a retest flowpath.
The RS&PD ASME Test Engineer may be consulted for questions or further clarification.
[1] Sten-By-Sten 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 the Maintenance Request for retest.
All work identified within the work scope guideline as
" Routine Servicing" requires an IST pump retest 0B equivalent documentation.
Identify either the applicable PNPS Procedure No. for retest QB 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.
l_
[2] Hork Scoce (WS) 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, i
I adjusting packing, adding packing rings or mechanical seal maintenance.
Exception: (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. O Page 9 of 171
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_562: PUNP POST-NAINTENANCE 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] Ratest Flownath Verify if Pump listed No IST Retest STEP 1-this procedure No For Operational Section 5.5.
Readinnst.
l.
Yes I
STEP 2
. Work to be performed is identified within No WS auideline.
I Yes I
Locate Procecure No in Sectica 5.5 of this pro-cedure (or other equiva-STEP 3 lent documentation) and identify for retest con-sideration on Maintenance Reauest.
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i 8.I.1.1 Rev. O Page 10 of 171
502 PUMP POST-MAINTENANCE TESTING (Continued)
[4]- EXAWLES:
(a) Salt Service Mater Pump B (P-2088) requires impeller replacement due to excessive wear per Maintenance Request.
SSN Pump P-2088 is No retest re-STEP 1 listed on Page 30.
No quired for t
operability.
I
-Yes i
Nork scope to be per-No STEP 2 formed is identified within Guidelines -
renlac m.".
HQIE: Replacement of the pump impeller requires both-new hydraulic and l
Yes mechanical parameters to be established.
The retest performance parameters shall be PNPS 8.5.3.2: Perform evaluated and accepted applicable steps of as new reference values.
STEP 3 Section 7.0, Prereq-uisites, and Section 8.0. Procedure.
l' (b) Residual Heat Removal Pump A (P-203A) requires the lubricant
(
reservoir to be filled because level indication is just l
visible per Maintenance Request.
RHR Pump P-203A is No retest re-quired for L
STEP 1 listed on Page 30.
N o ----
l operability.
I Yes I
I l
Hork scope is identi-l STEP 2 fled within Guide-
No --
8 lines - routine ser-vicina.
I l
Yes HQII: A Maintenance Request I
should always be used PNPS No.: not re-to document routine ser-quired - Maintenance vicing ratests unless STEP 3 Request package uti-the pump is required lized to document to be run at its verification of adjusted reference crocer oil level.
values prior to measur-ing the affected parameter.
8.I.1.1 Rev. O Page 11 of 171 l
5.ti PUMP POST-MAINTENANCE TESTING (Continued) j (c) Core Spray Pump A (P-215A) requires the pump mechanical seal f
replacement per Maintenance Request.
CS Pump P-215A is No retest re-STEP.I listed on Page 30.
No ---
quired for operability.
I Yes l
L Mork scope is identi-No ---
p STEP 2 fled within Guide-i lines - maintenance.
E: Maintenance of the pump L
mechanical seal (replace-ment of parts) requires Yes reconfirming previous-reference values.
PNPS 8.5.1.1: Perform l
applicable steps of STEP 3
.Section 7.0, Prereq-uisites, and Section 8.0.-Procedure.
l (d) Reactor Recirculation Pump B (P-201B) requires-the motor to be replaced per Maintenance Request.
Rx Recirc pump P-2018 No retest re-STEP 1 is ng.t listed on No quired for Pane 30.
operability.
I Yps li Hork scope is no.1 l
STEP 2 within Guideline -
N o --------
NA.
~
l Yes E: Maintenance performed on non-safety related putaps PNPS No.: Not should receive a post-Reauired.
maintenance test, but they do not require retest in accordance with Subsection IMP (ISTP).
8.I.1.1 Rev. O Page 12 of 171
h (5.3
' HYDRAULIC CIRCUITS The following IST hydraulic circuits are used to identify pump test paths and instrumentation.
Individual hydraulic and mechanical reference value test'quantitles are identified within each pump testing procedure..
M&TE instrumentation may be used in place of installed plant.
instruments provided taat-INV-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 Water (SSH) Pumps
[1] Test Frequency I
SSH Pumps are tested on a quarterly and refueling outage frequency because_of system design configuration-and operational requirements.
1
[2] Hydraulic Test Path j
(a) Quarterly - SSH pumps shall be shutoff (dead) head tested (RP-5) by verifying operation at nameplate speed I
and that discharge head (ft) is compared to the i
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-i throttling, establish a flowrate in accordance with a
current Tech Spec requirements.
Pump discharge pressure i
shall be recorded, and using suction bay level (RP-4),
the pump differential pressure (total head) will be l
calculated and compared to the established value.
[3] Instrumentation (a)
Inlet Pressure, Pi (ft):
LI-3831A, LI-3831B (actual measurement from ladder as backup).
j (b)
Discharae Pressure, (psig):
PI-3802, PI-3807, PI-3812, i
PI-3817, PI-3822.
(c)
Flowrata, 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. O Page 13 of 171
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5.3.2. Reactor Building Closed Cooling Hater (RBCCW) Pumps (Continued) m
[2): Hydraulic. Test Path L
(a) Quarterly - RBCCN pumps shall be shutoff (dead) head i
tested (RP-1)_by verifying operation at nameplate speed i
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 RBCCW 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..
[33 Instrumer.tation (a) Inlet 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) Flowrate, Q (gpm):
FT-6265, FT-6263.
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-4598, PI-4599.
(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.1.1 Rev. O Page 14 of 171
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5.3.4.' Residual Heat-Removal (RHR)-Pumps (Continued)
'[2]1HydraulicTestl Path
+
EachLpump 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 thrcttling, establish a flowrate in accordance with current Tech Spec requirements.
Pump discharge and suction pressure shall be recorded.
The differential pressure (total head) will be calculated and compared to the established value.
[3] Instrumentation (a) Inlet Pressurt,.Pi (psig): PI-1001-70A, PI-1001-70B, PI-1001-70C, PI-1001-70D.
-(b); Discharge Pres 1urg, (psig): PI-1001-71A, PI-1001-718, I
PI-1001-71C, PI-1001-71D.
'(c)
Flowrate, Q (gpm):
FI-1040-11A (Loop A), FI-1040-11B (Loop B).
5.3.5 Core Spray (CS) Pumps
[1] Test Frequency CS pumps are tested on a quarterly frequency.
[2] Hydraulic Test Path l
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 estabitshed value.
[3] Instrumentation (a)
Inlet Pressure, Pi (psig):
Test gauges at PI-40A, PI-408.
(b) DlSIharge Pressure, (psig): Test gauges at PT-1460A, PT-14608.
(c)
Flowrate, Q (gpm):
F1-1450-1A, FI-1450-1B, 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. O Page 15 of 171
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5.3.6 High Pressure Coolant-Injection (!!PCI) Pump (Continued)
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[2] Hydraulic Test Path i
These pumps-(main and booster) shall be tested-by establishing a flowpath with suction from and discharge i
returning to the CST.
Then, using the HPCI Full Flow Test Valve for throttling, establish the speed andiflowrate 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,-Pi (psig):
PI-2340-7 (Booster), Test gauge at PX-2301-80 (Main).
(b) Discharge Pressure, (psig): Test gauge at PX-2301-80 (Booster), PI-2340-2 (Main).
(c) Flowratt, Q (gpm):
FI-2340-1.
(d) 'Spand, N'(rpm):
SI-2340-1.
t 5.3.7 HPCI Gland Seal Condenser (GSC) Condensate Pump
[1] Test Frequency HPCI GSC Condensate Pump is tested on a cold shutdown frequency (RP-10).
[2] Hydraulic Test Path The pump shall be tested by establishing a flowpath from the Gland Seal Condenser to Clean Radwaste. Using the. pump discharge test valve for throttling and the Condensate Storage Tank water as makeup, establish a discharge pressure at a known reference value.
Isolate the CST supply water to the GSC while monitoring both time elapsed and GSC level change.
Level' change over time is converted into flowrate and compared to the established value.
[3] Instrumentation (a)
Inlet Pressure, Pi:
Not applicable (RP-10).
(b) Discharge Pressure, (psig):
Test gauge at H0-2301-66.
(c) Elowrate, Q (inches):
GSC Test rig (with measuring stick).
8.I.1.1 Rev. O Page 16 of 171
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p 5.3.8l
' Reactor Core Isolation Cooling ~(RCIC) Pump
[1] Test frequency RCIC pump is tested on a quarterly frequency, when adequate L
steam pressure is available.
L
'[23 Hydraulic._ Test Path The pump shall be tested by establishing a flowpath from and-returning.to the CST.
Then, using the test valve for' i
throttling, establish the speed and flowrate in accordance i
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 s
~'
established value.
[3]
Instrumentation (a)
Inlet Pressure, Pi (psig):
PI-1340-2.
(b) Discharge 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 j
[1] Test Frequency l
SLC pumps are tested on a quarterly frequency.
[2] Hydraulic Test Path Each pump.shall be tested by establishing a flowpath with i
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] Instrumentalon (a) Inlet Pressure, PI:
Not applicable (RP-3).
(b) Discharae Pressure (psig):
PI-1159.
(c) Flowrate, Q (inches): Heasuring Stick (yardstick).
8.I.1.1 Rev. O Page 17 of 171 w
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5.4 RELIEFLREQUESTS FOR' INSERVICE PUMP. TESTING PROGRAM-Pump Relief Requests'(RP) are provided for conditions in which compliance to ASME Code,.Section XI test requirements cannot be 3'
satisfied.
Each Relief Request identifies:
Pump (s)' involved, test 1'
requirement (s),of non-compliance; basis for. relief and alternate testing.
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8.I.1.1 Rev. O Page 18 of 171 L
m (1)
Relief Reauest RP-1 PUMPS:
P-202A, P-202B, P-202C, P-202D, P-202E, P-202F SYSTEM: Reactor Building Closed Cooling Hater CLASS:~ 3 FUNCTION:
Emergency Equipment Cooling
' TEST REOUIREMENTS:
Table INP-3100-1, Inservice Test Quantitles; Measure pump flowrate.
Table INP-3100-2, Allowable Ranges of Test Quantitles; dP high values.
BASIS FOR RELIEF:
Reactor Building Closed Cooling Nater System instrumentation is not configured to measure individual pump flowrate during plant operation.
Redesign of the 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 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 Mater System is part of 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 conditions will have a negative impact on the plants ability to safely operate or maintain the plant in the cold shutdown condition.
There is no method available to control the flowrates of individual pumps.
Shutoff head will provide a repeatable parameter for measuring pump performance.
Pumps are not run at shutoff head for more than 60 seconds by procedure. Due to minimum run time, the low values only for discharge pressure (Alert Range ard Required Action Range) shall be monitored and corrective action (IHP-3230) taken.
Individual pump flowrate and pressure will be measured each refueling outage.
l L
ALTERNATE TESTING:
Measure pump shutoff head quarterly with corrective action being taken for low allowable range only.
Measure individual pump flowrate and pressures each l
refueling outage.
8.I.l.1 Rev. 0 l
Page 19 of 171 L
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[2]
Relief Reauest RP-2 sa PUMPS:
P-141A P-202C P-203A P-205 P-208A P-208E P-141B P-202D P-203B' P-206 P-208B-P-215A P-202A P-202E P-203C P-207A P-208C P-215B P-202B P-202F P-203D P-207B P-208D P-220
- SYSTEMS
As Applicable
-CLASSES:
2, 3 or NC FUNCTIONS:
As applicable.
TEST REOUIREMENT:
INP-4310, Bearings - temperature of all centrifugal l
pump bearings outside the main flowpath and of the main-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 I
prior to entering a cooler, shall be considered the bearing temperature.
Table IHP-3100-1, Inservice Test Quantities - Bearing Temperature Tb.
1 Table IHP-3100-2 Allowable Ranges of Test Quantitles -
i Tb { Note (2)).
Note (2) Tb shall be within the limits specified by the Owner in the record of tests j
(INP-6000).
BASIS FOR RELIEF:
l (a)
Some pumps are cooled by their respective process fluid, "Hain Flowpath." Thus, bearing temperature l
rneasurements would be highly dependent on the temperature of the cooling medium.
(b)
Pump bearing temperature is taken at one (1) year intervals and provides very little data toward determining the incremental degradation of a bearing or provide any meaningful trend data.
i (c)
All pumps will be subject to vibration measurements per Subsection IHP-4500.
Vibration measurements (displacement and velocity) are a significantly more reliable indication of pump bearing degradation than that of temperature measurements.
ALTERNATE TESTING:
Vibration measurements, using velocity as a measured value, shall be taken on each pump in the same locations as the required displacement measured values.
Pumps with velocity amplitude exceeding 0.314 in/sec shall require investigation utilizing spectrum analysis to determine bearing status.
8.I.l.1 Rev. O Page 20 of 171
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.[3]
Relief Reauest RP PUMPS: P-207A, P-207B-
-SYSTEM: Standby Liquid Control CLASS: -2 J
FUNCTION:
Provides a method of shutting down the reactor without use of the control rods.
TEST REOUIREMENTS:
INP-3300, Scope of Test - measurement and observation of inlet pressure (P1) 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.
-IMP-4600, Flow Measurement - flowrate shall be measured using a rate or quantity meter installed in the pump test circuit.
ESIS 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 varied to establish the measured and observed discharge L
pressure as'the reference value.
Then the test tank l
1evel change is measured to determine pump flowrate.
I The SLC pumps are tested by pumping into a test tank.
The test tank capacity does not allow operation of the pump for longer than three minutes.
ALTERNATE TESTIEG:
Utilize pump discharge pressure reading in lieu of pump L
differential pressure reading and verify test tank' l
level to ensure adequate suction pressure.
The pump shall be run for a duration of 3 minutes to measure test parameters.
l 8.I.l.1 Rev. O Page 21 of 171
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-[4]'
Relief Reauest RP I ti,.
PUMPS:
P-208A, P-2088, P-208C, P-208D, P-208E SYSTEM: Salt _ Service Hater
]
CLASS:
3 FUNCTION:
Emergency Equipment Cooling TEST REOUIREMENT:
INP-4200, Pressure Measurement (Inlet Suction Pressure P1).
BASIS FOR RELIEF:
No instrumentation is installed to measure pump inlet 1
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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Page 22 of 171 y
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[5f Relief Reauest-RP -
EU3ES:
P-208A, P-208B, P-208C, P-208D, P-208E SYSTEM: Salt Service Water CL&SS:
3 i
L' FUNCTION: '
Emergency Equipment Cooling TEST REOUIREMENTS:
Table IHP-3100-1, Inservice Test Quantitles; Measure pump flowrate.
Table INP-3100-2, Allowable Ranges of Test Quantitles; dP High Values.
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 L
does not permit installation of flow orifices on the pump discharge piping prior to where the pump discharge joins a common header. Ultrasonic indicators cannot be reliably utilized with the rubber lined piping used in the salt service water system, also the pump discharge piping is underground.
The Salt Service Mater 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 L
conditions will have a negative impact on the plants ability to safely operate or maintain the plant in the cold shutdown condition.
There is no method available to control the flowrates of individual pumps.
Shutoff head will provide a repeatable parameter for measuring pump performance.
Pumps are not run at shutoff for more than 60 seconds by procedure. Due to minimum run time, the low values only for discharge pressure (Alert Range and Required Action Range) shall be monitored and corrective action (IHP-3230) taken.
Individual pump flowrate and pressure will be measured each refueling outage.
ALTERNATE TESTING:
Heasure pump shutoff head quarterly and take corrective action for only lower level alert and required action ranges. Measure individual pump flowrate and pressure each refueling outage.
8.I.l.1 Rev. O Page 23 of 171
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_ 6F Relief Reauest RP-6 L
0.
PUMPS:._P-208A, P-208B,'P-208C, P-'208D, P-208E SYSTEM:-Salt Service Water.
CLASS:
3-
. FUNCTION:
Emergency Equipment Cooling.
'lLST REOUIREMENT:
IHP-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.-
8.I.1.1 Rev. O Page 24 of 171
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[7]
Relief Reauest RP-7 PUMP.S:
P-141A, P-1418 SYSTEM: Diesel Fuel-011 Transfer q
CLASS:
NC.
FUNCTION:
The fuel oil transfer pumps maintain a sufficient operating.
level in the fuel oil day. tank by transferring fuel oil from the fuel oil storage tank to the fuel oil day tank.
1
. TEST REOUIREMENTS:
INP-4600 Flow measurement (accuracy),-IMP-3230(a) corrective action (alert range), and INP-3230(b) corrective action'(action range).
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 approximately 28 gpm with the required design capacity of the Diesel Engine being 3.3 gpm.
Flowrate can be measured with a portable survey flow meter.
The best obtainable accuracy for survey flow meters is.
approximately 15%. System configuration impairs the 1
control of discharge pressure and flowrate repeatability.
Each pump can meet its design function with greater tiean 75% degradation; therefore, relief for expanded accuracy requirements and alert / action ranges will adequately provide for pump operability assessment.
ALTERNATE TESTING:
Measurement 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.
8.I.l.1 Rev. O Page 25 of 171
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-[8]
Relief Reauest RP-BL l
PLDFS:
P-141A' P-202D P-203C P-2078 P-208E P-141B P-202E P-203D ~
P-208A P-215A-P-202A P-202F P-205 P-2088 :
P-2158
^e
-- P-202B -
.P-203A P-206 P-208C P-220 P-202C.
P-2038 P-207A P-2080' l,,
SYSTEMS:'As Applicable
]
CLASSES: 2, 3 or NC BIET10ll:l As Applicable TEST REQUIREMENT:
IMP-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..
f
- BASIS FOR RELIEF: Test acceptance criteria is contained within the test p
procedures and the determination.of equipment operability-L is made immediately by on-shift personnel. Therefore, on-shift personnel shall declare the pump inoperable and t
the appropriate Technical Specification action time must be 3
started.- The analysis of results-for degradation requiring increased testing or engineering evaluation will then occur l.
when the appropriate personnel are available for reviewing.
E 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 weekends (Saturday &
Sunday) and Holidays.
i I
8.I.1.1 Rev. O Page 26 of 171
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- [9]
- Relief Reauest RP-9 PLSFS
P-141A-P-202D P-203C.
P-2078 P-208E.
P-141B P-202E P-2030=
P-208A P-21$A P-202A P-202F P-205 P-2088 P-2158 P-202B P-203A P-206 P-200C' P-220:
P-202C.
P-2038 P-207A P-2080 SYSTEMS:.As.' Applicable-CLASSES: 2, 3 or NC 1
FUNCTIONS:
.As Appilcable TEST REQUIREMENT:
IMP-4120, Range - the fu11-scale range of each instrument shall be three times the reference values or less.
- BASIS FOR RELIEF: The-instrumentation.(IRD) used to measure vibration l.
aptitude has a range selector with multiples ef 0.03,'O.1, O.3, 1,-3 and others for full-scale reading:
When measuring reference values that would fall i'. ween; 0.031 to 0.033, 0.31 to 0.33, 3.1 to 3.3 the full-scale range requirement can not be met. The minimal portion of scale l
usage which does not comply-shall not degrade the p
-monttoring of the pump operational readinets status and the scale indication is close enough to the lower 1/3 which reflects an accurate vibration level reading.
1' ALTERNATE TESTING: The small range of reference values identified shall be
?
measured on the appropriate scale.
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8.I.1.1 Rev. O Page 27 of 171
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[10).
Relief Reauest RP-10 f53ES:
P-220
- SYSJDIS: High Pressure Coolant Injection System (2301) 1 CLASS:
2
)
FUNCTI0llS:
To maintain adequate Gland Seal Condenser (GSC) Notwell i
level by pumping Condensate from the GSC Hotwell to the.
'HPCI Booster Pump Suction or Clean Radwaste (as an alternate path).
L TE5T REQUIREMENT: INP-3300, Scope of test - measurement and observation of inlet pressure (PI) and differential pressure (dP) across the pump.
INP-3400, Test Frequency - test pumps at least every three months, quarterly.
INP-4600 Flow Measurement - flowrate shall be measured using a rate or quantity meter installed in the pump test circuit.
BASIS FOR RELIEF: The HPCI GSC Condensate Pump must transfer condensate from the GSC to verify proper operation. To establish a i
temporary hydraulic circuit for pump testing, the HPCI i
System must be made inoperable for an extended period of time (approx. 8 hrs).
System configuration does not allow measurement of flow or inlet pressure. Since the pump is positive displacement, inlet pressure is not a significant parameter for measuring pump performance.
During testing, the discharge pressure is established as the reference value by controlling system resistence. Then the GSC Hotwell level change is measured to determine pump flowrate.
ALTERNATE TESTING: Testing will be performed during cold shutdown utilizing pump discharge pressure in lieu of pump differential pressure. The GSC Hotwell level change will be monitored and timed to determine pump flowrate.
8.I.l.1 Rev. O Page 28 of 171
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. PUMP. PROGRAM TABLEi.
. i g-m-'
- This table Identifies the scope of pumps within_ the ISTP and allows' cross-referencing specific pump test. quantities.to their implementing:
station procedure.
lh'e test quantities measured include: Speed (N), Inlet Pressure-(P1),
[
R Differential' Pressure:(dP), Flowrate (Q), Vibration (V)', Lubricant:
F-,
Level (L);and Bearing Temperature (Tb).
2.
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l 8.I.1.1 Rev. O Page 29 of 171
3"3 TABLE PUMPS TESTED l
ISI CLASS 1, 2,'3 AND NC PUMPS j
INSERVICE TEST GUANTITIES l
lISIl lP&ID l l
l SPEED l INLET lDIFF.
l FLOW l
l LUBRICANT l BEARING SYSTEM l DUMP # lCLASSl P&ID IC00RD.lTEST PROC.IFREO.I (N) l PRESS.(PillPRESS.(dP11 RATE (0)lVIB. (V)lLEVEL (L) ITEPF.(Tb)
SALT SERVICE lP-208Al 3 lM212 l 87 l8.5.3.2#l Q lNA lRP-4 lRP-5 l RP-5 lRP-6&9l Y
-l RP-2 WATER (SSW) lP-2088l 3 l M212 lB8 l8.5.3.2#l Q l NA lRP-4 lRP-5 l RP-5.lRP-6&9]
Y l
RP-2 lP-208Cl 3 lM212 l87 l8.5.3.2#l Q lNA lRP-4 lRP-5 l RP-5 lRP-6 & 9l Y~
l
.RP j l P-2080 l 3 l M212 l86 l8.5.3.2#l Q l NA lRP-4 lRP-5 l RP-5 lRP-6 & 9l Y
l.
RP-2 l P-208E l 3 l M212 l 85 1 8.5.3.2# l 0 1 NA I RP-4 I RP-5 I RP-5 IRP-6 & 91 Y'
I
-RP-(__
REACTOR BUILDING l P-202A l 3 l M215 l F3 l 8.5.3.1# l Q lNA l Y
l Y
l RP-1 l RP-9 l Y
l RP-2 CLOSED COOLING lP-202Bl 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) l P-202C l 3 lM215 lG3 l8.5.3.1#l Q l NA l Y
l Y
l RP-1 l RP-9 l Y
l RP-2 l P-202D l 3 l M215 lG5 l8.5.3.1#l Q ] NA l Y
l Y
l RP-1 l RP-9 l Y
l RP-2 l P-202E l 3 lM215 lG5 l 8.5.3.1# l Q l NA l Y
l Y
l RP-1 l RP-9 l Y
l RP-2 i P-202F l 3 1 M215 I F5 l 8.5.3.1# l 0 l NA l Y.
i Y
l RP-1 I RP-7 I Y
l RF-2 DIESEL OIL l P-141A l NC lH223 lF6 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)
I P-141B I NC I M223 l E6 1 8.9.1.1 1 0 i NA l 7
1 Y
l RP-7 I RP-9 I NA I
RP-2 RESIDUAL HEAT lP-203Al 2 lM241(52)lD6 l8.5.2.2.1l C lNA l Y
l Y
l Y
l RP-9 l Y
l RP-2 REMOVAL (RHR) l P-2038 l 2 lM241(52)lD3 l8.5.2.2.2l Q lNA 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 l NA l Y
l Y
l Y
l RP-9 l Y
l RP-2 l P-2030 l 2 lM241(S2)l F3 I 8.5.2.2.21-Q_ l NA I Y
l Y
l Y
I RP-9 I Y
l R P-7,_
CORE SPRAY (CS) l P-215A l 2 l M242 l F7 l 8.5.1.1 l Q.l NA l Y
l Y
l Y
l RP-9 l Y
l
.RP-2 l P-2158 l 2 l M242 l F9 I 8.5.1.1 1 0 I NA I Y
l Y
I Y
I ~RP-9 I
Y I
RP-2 HIGH PRESSURE lP-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 COOLANTINJECTIONl l
l l
l l
l l
l l
l l
l (HPCI)
I l
l l
l l
l l
l 1
l I
l HPCI GLAND SEAL l P-220 l 2 l M244 lL13 l 8.I.11.18l CSlNA l RP-10 l RP-10 l RP-10 l RP-9 l NA l
~RP-2 CONDENSER (GSC) l l
l l
l lRP-10l l
l l
l l
l CONDENSATE l
l l
l l
l l
l l
l l
l I
REACTOR CORE ISOLl P-206 l 2 lM246 lF8 l8.5.5.1 l Q l Y l Y
l Y
l Y l RP-9 l Y
l RP-2 COOLING (RCIC)
I l
l I
I I
l l
l 1
l I'
I STANDBY LIQUID l P-207A l 2 l M249 lE5 l 6.4.1 l Q l NA lRP-3 lRP-3 l RP-3 l'RP-9 l Y
l RP-2 CONTROL (SBLQ l P-207B 1 2 l M249 l F5 l 8.4.1 1 0 i NA I RP-3 l RP-3 l RP-3 l RP-9 I Y
l RP-2
- These pumps are tested in corpliance with the ASME Code,Section XI Requirements each refueling outage. The refueling outage procedure shall 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. O Pace 30.of 171 m.
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o 6.0 -INSERVICE VALVE TESTING
]
6.' l GENERAL INFORMATION 4
[1)- Applicable Code This Inservice Testing Program for ISI Class 1, 2, 3'and-NC valves
'~
meets _the reautrements of Subsection IWV of Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter p=
1980 Addenda. Where these requirements are determined to be impractical, specific requests for relief have been written and included in Section 6.4.
.[2] Valve 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.
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) PilD_ COORDINATE: Coordinate location and sheet number on the P&ID.
(c)
ISI CLASS:
Inservice inspection classification (Class 1, 2, 3 or NC).
(d) VALVE CATEGORY: Category assigned to the valve based-on the definitions of INV-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.
(2) CATEGORY B - valves for which'a specific amount of leakage in the closed position is inconsequential for L,
fulfillment of their function.
l~
(3) CATEGORY C - valves which are self-actuating in response to some system characteristic such as pressure (relief valves) or flow direction (check valves).
(4) CATEGORY D - valves which are actuated by an energy source capable of only one operation such as rupture disks or explosive actuated valves.
(5) 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.
(e) VALVE SIZE:
Nominal pipe size (in inches).
8.I.1.1 Rev. O Page 31 of 171
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- 1 1
j E,1 GENERAL INFORMATION (Continu6d) 6 1
'j
-(f) - VALVE TYPE:. Valve' Body Design, ANGLE-AN-PLUG PG
- A BALL BL RELIEF RL BUTTERFLY BF RUPTURE DISC RD CHECK
-CK SAFETY SV-GATE GA SHEAR SH-GLOBE GL STOP CHECK SC 4
NEEDLE.
ND SPRING CHECK SK H
(g): ACTUATOR TYPE: Valve Actuator Power; MOTOR OPERATOR MO EXPLOSIVE ACTUATOR EX-l AIR OPERATOR A0 MANUAL MA s
SOLEN 0ID OPERATOR.
S0 SELF ACTUATED SA HYDRAULIC OPERATOR H0 (h)' NORMAL POSITION:
Normal Position During Plant Operation; HORMAL OPEN.
O LOCKED OPEN LO NORMALLY CLOSED C
LOCKED CLOSED LC (1) TEST RE0VIREMENT:
Test (s) that will be performed to fulfill the requirements of Subsection INV.
The test definitions and abbreviations used are identified in Table 1, Inservice Valve Tests.
(j) TEST FREOUENC1:
Frequency at which the tests will-be performed. The. frequency. definitions and abbreviations used are identified in Table 2, Test Frequency.
(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 valve exercising is to the position required to fulfill their function.
0 - Open C - Closed FF - Forward Flow, Normally Cic;;ed Valves RF - Reverse Flow, h'ormally Closed Valves (1) COLD SHUTDOHN JUSTIFICATION:
Refer to Section 6.3 for cold shutdown description.
Requests are identified as CS-XX.
(m) RELIEF REQUISI:
Refer to Section 6.4 for relief request description.
Requests are identified as RV-XX.
(n) BEHARKS: Clarification to the particular column to identify a special or unique requirement.
8.I.l.1 Rev. O Page 32 of 171
h:
7-N. l GENERAL'INFORMATION (Continued) 5.1 K
I
[3] Exempt: Valves
~
Valves exempt per INV-1200 and passive valves that do not have a e
specific maximum leakage requirement are not included in the IST E
Program.
Passive valves are those valves which are not required to change position to accomplish a safety-related function.
Subarticle INV-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 i
so their position indicators will be checked with the exempt status noted.
Dampers are considered exemot-(i.e., HVAC System).
L
[4] Measurement of Test Quantities (a) SlR0KLIBE:
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 INDICATI03: 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 movement 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) SE6J LEAKAGE:
Seat leakage 1:, 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 satisfied.
(3) By performance of a Pressure Drop (Decay) Test to verify that an entire pressure boundary does not exceed its specified leakage criteria (Reference RV-30).
8.I.l.1 Rev. O Page 33 of 171
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.I 7
6.1 GENERALLINFORMATION (Continued) l J
(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 4
< positive means..
The following test practices will be utilized:
(1). Full flow Check Exercise - will be verified by
~
observation'of-substantially free flow'through the 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 dise.ssembly 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.
[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.)~
REOUIRED ACTION VALUE (SEC.)
2 1 R to 1 5 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 115 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. O Page 34 of 171
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.6.10 GENERA 1. INFORMATION (Continued) a.
'The valve stroke time-required action value shall i
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.
(l 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 alert value will be considered erratic and investigated.
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 immediate1v and corrective action being taken.
(b) E0.SLIION INDICATION:
During valve opening and closure, the remote position indicators shall accurately reflect valve travel direction.
8.I.1.1 Rev. O Page 35 of 171
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6.1. GENERAL INFORMATION (Continued) i 3
-l (c)
SEAT' LEAKAGE:
(1) Valve leakage rates shall not. exceed the value I
established by Boston Edison Company.
These leakage values are specified within the. implementing test procedures. Valves that fail to meet the acceptance q
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 s
greater.
The test frequency shall be doubled.
The tests shall'be scheduled to coincide with a cold i~
shutdown until corrective action is taken.
If tests L
show a leakage rate increasing with time and.a projection based on three or more tests indicates that l
the. leakage rate of the next scheduled test will exceed i
I the maximum permissible leakage rate by greater than L
10%, then corrective action will be taken, s
[5)- Instrument Accuracy 1
Instruments used to measure stroke times shall be capable of measurement to the nearest tenth of a second.
9 l;
[6] Corrective Action L
l
. (a)
STROKE TIME: Corrective action shall be to repair or replace I
the valve.
a (b)
SEAT LEAKAGE: Corrective action shall be to repair or L
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.
1 Procedure' credit may be taken for valves that are tested by the vendor / manufacturer provided that similar test L
methods are used and the documentation verifles surveillance procedure acceptance criteria has been met.
(2)
If any relief valve in a system falls the regular test, an additional sampling of valves in that system shall be tested.
If any of these additional valves fall, then all the remaining relief valves in the system shall be tested.
8.I l.1 Rev. O Page 36 of 171 l
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TABLE 1 INSERVICE VALVE TESTS ILH TEST NAME TEST DESCRIPTION /DEFINITIQN 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 IWV-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 INV-3426 and IWV-3427(a).
LP Pressure Isolation Pressure Isolation Valves are any two valves in Valves series within the Reactor Coolant Pressure Boundary which separated the High Pressure Reacte-Coolant from an attached low pressure system anc 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 provided in BECo's response to Generic letter 87-06.
LX Hiscellaneous 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 techniques (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 shutdowns.
8.I.1.1 Rev. O Page 37 of 171
F TABLE 1 J)(SERVICE VALVE TESTS (Continued)
Ifjil TEST NAME TEST DESCRIPTION / DEFINITION FC Check Valve Check valves will be exercised to assure o
Exercise freedom of motion and prevent sticking /setzure 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.
2 PC Partial Check Partial (valve checked in same flow direction)
Exercise exercise is when a Category C valve can not be verified in its full flow position as required by-an FC test.
j RD Rupture Disk Non-Teslitble 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 end Safety Valve setpoints will be verified Test in acco. dance with ASME Boiler and Pressure Vessel Code,Section XI (INV-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 proper fail safe operation upon loss of actuator power.
PI Position Indication Valves with remote position indicators will be Verification checked to verify that remote valve position indicators accurately reflect valve travel direction.
8 I.1.1 Rev. O Page 38 of 171
n TABLE 1 i
INSERVICE VALVE TESTS (Continued) j i
JISI 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 i
function in its normal operational-position.
Check valves reposition themselves following an exercise. This repositioning is verified by i
normal. operational parameters, special testing or j
valve disassembly.
Test frequency may be as often i
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 l'
during disassembly.
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1 8.I.1.1 Rev. O Page 39 of 171
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TABLE 2 TEST FREQUENCY i
TEST FRE02 OPERATIONAL CONDITION FREOUENCY OF TESTING Q-Power Operation At least once per 92 days f
CS Cold Shutdown See (2) below RO Refueling Outage See (1) below SY No operational Every five years (see IWV-3511).
condition limitations Applies to RT test f
2Y No operational Every two years (see INV-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 PNPS Tech Specs) testing is acceptable when the following conditions are met:
(a) Testing is to commence as soon as practical when the Cold-Shutdown condition 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 continue 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 f.0R IST ACTIVITIES PERFORMING IST ACTIVITIES l
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.1.1 Rev. O Page 40 of 171 y_
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6.2 -
VALVE POST-MAINTENANCE TESTING The'IST Program requires each valve 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 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 gutdance is provided using a step-by-step determination process, a work scope (WS) guideline, and a retest flowpath.
The RSILPD ASME Test Engineer may be consulted for questions or further clarification.
The As-Found (Prework) Testing requirements can be determined through this process.
As-Found testing is pertinent to Containment Isolation Valves (only) and must be identified nrlor to start of maintenance for compliance of 10CFR50 Appendix J.
[1] Sten-By-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, i
HQlE When using guidelines to determine containment isolation valve As-lound (Prework) test requirements, if a post-maintenance LJ procedure requires retest for operational readiness, then an As-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.
Step 4:
Identify the applicable PNPS Procedure No(s).
OB equivalent documentation (that will verify the test requirement is performed in accordance with the Subsection IWV) on the Maintenance Request.
8.I.1.1 Rev. O Page al of 171
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6.2-VALVE POST-MAINTENANCE TESTING (Continued)
[2] Work Stone Guideline (a) Routine Servicing - Performance of planned preventive maintenance which don not require disassembly of the valve or replacement of parts such as adjustment of stem packing.
(b) Maintenance - Performance of preventive or corrective maintenance which do u require disassembly of the valve or replacement of consumable items.
EXAMPLES: replacement of packing, remov. of bonnet, stem assembly or actuator, and disconnection of hydraulic or electrical lines.
and I
Specified Maintenance - Performance of preventive or corrective maintenance which is unique to a test requirement and is identified within the test requirement work scope.
?
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 modification to the valve (does not include valve actuator).
Cross-Reference Table (Test Reauirement vs Work Scoce) l Test Reautrement Work Stones FE, FC, ST, FS Routine servicing, maintenance, repair or replacement.
LJ Specified maintenance, repair or replacement.
Specified maintenance: repacking, lowering of motor-operated valve torque switch mechanism, adjustment of motor-operated valve closing limit switch for valves that close on limit switch, disassembly of valve internals or removal of valve actuator. As-Found (Pretest) testing is required for Containment Isolation Valves.
Exception: Hotor operated valve diagnostic testing may sometimes be used to verify a torque setting has not been lowered in lieu of leak testing.
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Page 42 of 171 l
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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, adjustment of motor-operated valve closing unit 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.. Exception: 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.
l RD Repair or replacement.
EX None (Manufacturer's Data acceptable).
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I 8.I.1.1 Rev. O Page 43 of 171
402 VALVE POST-MAINTENANCE TESTING (ConttQued) l-
[3] Retest Flowpath CAUTION l
Nhen a post-eaintenance L3 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.
Readinnst.
l l
Yes I
Note test requirement (s)
STEP 2 for valve.
l Yes 1
For each test requirement verify if work to be per-STEP 3 formed is identified No within WS ouideline.
I Yes I
i 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 Raouest.
8.I.1.1 Rev. O Page 44 of 171 4
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6.2 VALVE p0ST-MAINTENANCE TESTING (Continued)
[4] EIAlsus:
(a) A0-203-1A requires the valve seating surface to be machined J
(grinding) and lapped per Maintenance Request and the appropriate procedures to be used for retests.
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AD-203-1A is listed on No !$T Retest STEP.1 Page 154.
No For Operattonal Readinant.
l i
1 Yes li i
Note valve test reqts.:
Yes l
l l
Nork Scope to be performed l
is identified within Guide-i STEP 3 lines - repair. This re-
No quires: FE, ST, FS, LJ, Pl.
liQII:
The Local Leak Rate Test Yes (LJ) may require both Pre and Post Leak Rate Testing.
Proc. Numbers:
STEP 4 FE.ST.FS; 8.7.4.4 LJ.PI
- 8.7.1.6 Yes Perform applicable steps Maintenance Request doc-of Section 7.0, Prereq-umentation not required, uisites and Section 8.0, ---- OR ------ retest must be performed Procedure.
by Procedure.
l 8.I.1.1 Rev. O Page 45 of 171
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- ~;-_-- - _ r _-_
~ 'T;; ;~' _
'(
6.2 VALVEPOST-MINTENANCETESTING(Continued) 1 (b) 1001-PSV-44 requires the valve seating surface to be lapped I
per Maintenance Request and the appropriate procedures to be esed for retests.
1001-PSV-44 is listed No IST Retest STEP 1 on Page 133.
No For Operational Readinant.
1 I
j i
2 Yes I
i Note valve yest retts.:
l STEP 2 RT. LX.
i e
i Yes l
i i
Nork Scope to be performed l
1s identified within Guide-I STEP 3 lines - specified mainten-No --- -
ance. This requires:
RT, LX.
i Yes Proc. Numbers:
STEP 4 RT; 8.I.26 I
LX: B.I.26 Yes Perform app icable steps Maintenance Request doc-of Section 7.0, Prereq-umentation not required, visites and Section 8.0, ----- OR ------
retest should be per-Etocedure.
formed by Procedure.
l-8.I.1.1 Rev. O Page 46 of 171
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)
6.2 VALVE POST-4EINTENANCE TESTING,(Continued)
(c) MD-1400-248 requiresthestenpackingtobeadjustedto einimize leaking and the retest is to be performed within the Maintenance Request package.
i MD-1400-248 is Itsted No 1$T Retest STEP 1 on Page 136.
No For Operational Readinant.
e i
Yes l'
i Nott valve test reqts.:
Yes j
i I
Work Scope to be performed l
is identified within Guide-i STEP 3 lines - routine servicing.
N o ---- -
This requires:
5 Yes l
Proc. Numbers:
l STEP 4 FE & ST; 8.5.1.3 Yes Reviewed Proc. Section Maintenance Request steps 7.0, Prerequisites and could follow procedure Section 8.0, Procedure OR reqts. to document the for retest rects.
retests: FE, ST. Using Maintenance Request steps to document retest re-quirements is no.t the recommended method.
8.I.1.1 Rev. O Page 47 of 171
,1 5.2 VALVE POST-MAINTEhANCE TESTING (Continued)
(d) NO-2301-3 requires the electric motor to be replaced per Maintenance Request and the appropriate procedures to be used for retest.
MD-2301-3 is listed on No !$T Retest
. STEP 1 Page 138.
No For Operational Readinant.
Yes l
i Note valve test reqts.:
l Yes Work Scope to be performed is identified within Guide-l STEP 3 lines - maintenance. This N o ------- -.
requires:
Yes EII: Motor replacement is 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 Perform applicable steps Maintenance Request steps of Section 7.0, Prereq-could follow procedure utsites and Section 8.0, AND reqts, to perform the PI Procedure for FE. ST.
retest. Using Maintenance Request steps to document retest requirements is DD.t the recommended method.
8.I.1.1 Rev. O Page 48 of 171
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6.2-VALVE POST-MAINTENANCE TESTING (Continued)
(e) D 1001-33A requires the handwheel to be replaced per Maintenance Request.
6 1001-33A is listed No !$T Retest STEP 1 on Page 131.
No For Operational n.atanza, Yes Note valve test reqts.:
STEP 2 PI Yes s
Nork Scope to be performed is identified within Guide-STEP 3 lines - maintenance. This No requires: NA.
l Yes l
EII: Handwheel replacement is considered replacement of i
Proc. Numbers:
valve actuator and falls STEP 4 Not Reauired.
Within MS as atintenance.
Maintenance is no.t iden-tified within the PI test regt, work scope.
8.I.1.1 Rev. O Page 49 of 171
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6.3 COLD SHUTDOWN JUSTIFICATIONS j
Valve. Cold Shutdown Justifications (CS) are provided for conditions where compliance to ASME Code,Section XI. Subsection INV test requirements are satisfied, but conditions exist that necessitate a i- -
test frequency of " cold shutdown" in lieu of " quarterly". Each Cold Shutdown Justification identifies: Valve (s) involved, compliance test requirement (s), basis for justification, and an alternate testing frequency of cold shutdown.
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8.I.l.1 Rev. O Page 50 of 171
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[1]
00LD SHUTD0001 JUSTIFICATION CS-01 SYSTEM:
Reactor Building Closed Cooling Water System (30)
VALVE _S:
4009A, 40098, 4002 CATEGORIES: A,B CLAS. SIS:
2, 3 FUNCT10E:-
These valves provide isolation to drywell components cooled by RBCCH.
The components would require isolation for primary containment criteria and maintenance.
TEST REOUIREMENTS:
INV-3411; Test frequency - exercise at least once every three months.
INV-3413; Power operated valves - full stroke time.
BASIS _ EOR The testing of these valves would require isolation of JilSTIFICATIQLI:
the following components: Drywell Area Coolers, Reactor Recirculation Pump Seal Coolers, Reactor Recirculation Pump Lube Oil Coolers and additionally; The Reactor Water Cleanup (RHCU) non-regenerative heat exchanger, B Fuel Pool Cooling Heat Exchanger, RWCU 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 plant operation.
The recirculation pumps and drywell coolers maybe required to support the plant during cold shutdown conditions to prevent stratification of Reactor Vessel Lower Head Hater and overheating of Orywell components.
ALTERNATE TESTING:
Exercise valves during cold shutdown when recirculation pumps and drywell coolers are not required but not to exceed a refueling outage.
i 8.I.1.1 Rev. O Page 51 of 171 i
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[2]
COLD SHUTDOWN JUSTIFICATION CS-02 SYSTEM:
Residual Heat Removal System (1001)
VALVES:
47, 50, 60, 63 CATEGORY:
A CLASS:
1 EUNCTION:
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.
INV-3413; Power operated valves - full stroke time.
BASIS 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 exercise 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.
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l 8.I.1.1 Rev.-0 Page 52 of 171
[3]
COLD SHUTD0001 JUSTIFICATION CS-03 SYSTEM:
Residual Heat Removal System (1001)
VALVES:
68A, 68B CATEGORY:
AC l
CLASS:
1 FUNCTIDH:
These valves are the low pressure coolant injection pressure isolation check valves which provide a flowpath for shutdown cooling.
IESI_BEQUIREMENT:
INV-3521: Test frequency - exercise at least once every three months, quarterly.
i B&S11_00R Exercising these valves to the open position can only be JUSIIE,tCall0N:
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.
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8.I.1.1 Rev. O Page 53 of 171 l
[4) 00LD SNUTD0001 JUSTIFICATION CS-04
.5151 2 5:
High Pressure Coolant Injection System (2301)
Reactor Core Isolation Cooling System (1301)
VALVES:
2301-7, 1301-50 CATEGORY:
AC CLASS:
1 I
FUNCTION:
These valves are the HPCI and RCIC injection pressure isolation check valves.
TEST REOUIREMENT:
IWV-3521; Test frequency 4-exercise at least once every three months, quarterly.
{
BASIS _ EOR Testing these valves during normal operation would JUSTIFICATION:
require; 1) injecting cold water into the reactor vessel using the HPCI (or RCIC) system which would result in
- oth a reactivity excursion and thermal shock to the feedwater nozzle and piping and 2) loss of one pressure j
i solation barrier between the high pressure reactor coolant system and low pressure HPCI (or RCIC) System.
l These valves are manually stroke testable.
Since a maximum allowable torque on the mechanical test lever of 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 i
lineup (no differential pressure across these valves).
l During a normal cold shutdown, the feedwater header is i solated.
ALTERNATE TESTING:
Manually exercise during cold shutdown (normal cold shutdown feedwater valve lineup) not to exceed refueling j
outage.
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[5]
COLD SNUTD0001 JUSTIFICATION CS-05 L
SYSTEM:
Nuclear Boiler - Reactor Recirculation System (202)
J 1
VALVES:
5A, 5B CATEGORY:
B CLASS:
1 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.)
IEST REOUIREMENTS:
INV-3411; Test Frequency - exercise at least once every three months, e
INV-3412; Power operated valves - full stroke time.
BASIS _E08 Closure of these valves during normal operation will JUSTIFICATION:
result in loss of forced circulation to the reactor, a condition prohibited by PNPS License.
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 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 increasing temperature gradient between the bottom i
vessel head and the shutdown 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 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 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 reactor recirculation pump is not required, but not to exceed a refueling outage.
8.I.1.1 Rev. O Page 55 of 171
~[6]
00LD SHUTDONN JUSTIFICATION CS-06 SYSTEM:
Nuclear Boiler - Main Steam, Vent, Drain & Sampling System (220)
VALVES:
46, 47 CATEGORY:
B i
CLASS:
1 TUNCTION:
These valves are used to vent the reactor vessel head and main l
steam line "A" during startup.
TEST REQUIREMENTS:
INV-3411; Test Frequency - exercises at least once every three months.
e INV-3413; Power operated valves - full stroke time.
IWV-3415; Fail safe - at least once every three months.
BASIS _fDR 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 refueling outage).
(
i 1
1 l
8.I.1.1 Rev. O Page 56 of 171
r i
h
[7]
00LD SHUTDOM JUSTIFICATION CS-07 SYSTEM:
High Pressure Coolant Injection System (2301)
VALVES:
232, 233 CATEGORY:
C CLASS:
2 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 three months.
BASIS _EDB The HPCI Exhaust Vacuum Breaker Line Check Valves shall 1USTIFICaI109:
be forward flow exercised.
These normally closed check valvet are verified in the open direction by isolating the vacuum breaker exhaust line and ensuring unrestricted flow. The vacuum breaker line isolation i
will make the HrCI system inoperable.
Exercising is to be performed during cold shutdown.
ALTERNATE TESTING:
Exercise during cold shutdown.
i l
1 1
l l
8.I.1.1 Rev. O Page 57 of 171 j
o
[8]
COLD SNllTD0001 JUSTIFICATION CS-08 SYSTEM:l Reactor Building Closed Cooling Hater (30)
VALVES:
4085A, 4085B CATEGORY:
B CLASS:
3 FUNCTION:
Valves 4085A and 4085B are the non-safety related component isolation valves for RBCCH Loop A.
TEST REOUIREMENTS:
INV-3411; Test frequency - exercise at least once every three months.
INV-3413; Power operated valves - full stroke time.
r BASIS._ EOR Valves 4085A and 4085B are the non-safety related JUSTIFICATION:
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 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 increasing temperature gradient between the bottom vessel head and the core when mixing (forced circulation) is stopped. Additionally, the water in the o
idle recirculation loops cools down.
This stratification can have the following adverse effects:
reactor vessel metal temperature differences become greater between rea: tor vessel bottom and top resulting l
in unwanted thermal cycling.
Start up of the shutdown recirculation pumps causes a cold water intrusion which l-affects reactor vessel metal temperatures and causes L
thermal cycling of the reactor vessel.
ALTERNATE TESTING:
Exercise valves during cold shutdown when reactor recirculation pumps are not required but not to exceed a refueling outage.
8.I.1.1 Rev. O j
Page 58 of 171 l
TABLE
'a INSERVICE VALVE TESTING PROGIAM ISI CLASS 1.,2, 3 AND NC VA8.VES PILGRIM NUCLEAR POWER STATION P&ID: M-239 SHEET 1 of R
_ SYSTEM: POST ACCIDENT SAMPLING & HZ*k P&ID: M-239 SHEET 2 of 3
.veALYZER SYSTEM (5065)
Valve P&lD ISI valve valve Valve Actuator Normal Test Test PIr5 Proc.
Test Relief tiveber Coor Clas_s__ Cat Size Twee Twee Position Rest.
Free Humb e _r D Mien Reeuest Nntes 06 G4 2
8 1
GA 58 C
FC 8.7.4.1 (SH.2)
.ST Q
8.7.4.1-C NV-44 F5 Q
8.7.4.1 C
n 2r 8.7.4.8 67 E-6 2
8 1
GA 58 C
E 8.7.4.1
($H.2)
ST 4
8.7.4.1 C
RW44 F5 g
8.7.4.1 C
n 2y 8.7.4.8 68 E-6 2
8 1
GA 58 C
E Q
8.7.4.1
($H.2)
ST 9
8.7.4.1 C
RW44 F5
(
8.7.4.1 C
n zy 8.7.4.8 69 M
2 8
1 GA 58 C
E 4
8.7.4.1
($H.2)
ST 4
8.7.4.1 C
WW-44 F5
(
8.7.4.1 C
n ZY 8.7.4.8 79 D-6 2
8 1
GA
$8 C
E 9
8.7.4.1-(3H.2)
ST g
8.7.4.1 C
WW-C4 F5 9
8.7.4.1 C
n ZY 8.7.4.8 71 F-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 72 F-6 2
A 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 8.7.1.5 LJ
?Y 8.7.1.5
+
8.I.1.1 Rev. 0' Page 124 of 17)
~.
y TASLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND MC VALVES PILGRIM NUCLEAR POER STATION P&ID; M-239 SHEET 1 of 3 SYSTEM: POST ACCIDENT SAMPLING & H2+Og P&ID: M-239 SHEET 2 of 3 ANALYZER SYSTEM (5065)
Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Fir 5 Proc.
Test Relief.
Ngeber Coor Class Cat Jize Twee Tvoe Position Rest.
Free Susher Direction Reeuest Notes 73 C-6 2
8 1
GA 50 C
FE Q
8.7.4.1 (SH.2)
ST Q
8.7.4.1 C
RV-94 F5 g
8.7.4.1 C
n 27 8.7.4.8 74 C-6 2
8 1
GA SS C
E 4
8.7.4.1 (SH.2)
ST 4
S.7.4.1 C
SW44 F5 g
8.7.4.1 C
n 27 8.7.4.8 75 5-6 2
e 1
GA SS C
FE 4
8.7.4.1 (5H.2)
ST 8.7.4.1 C
RW-94 F5 9
8.7.4.1 C
n 27 8.7.4.8 76 8-4 2
8 1
GA SS C
FE Q
8.7.4.1
. L Z)
ST Q
8.7.4.1 C
RV44 F5 4
8.7.4.1 C
n 2r 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-44 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
5.7.4.1 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 8.I.1.1 Rev. O Page 125 of 171
TABLE INSERVICE VALVE TESTING PROGRAN ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-239 SHEET 1 of 3_
SYSTEM: POST ACCIDDIT 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 PIPS Proc.
Test Relief 16vmber Comr Class Cat Size Type Twoe Position Rest.
Frea number Di m tion D t Notes 79 D4 2
8 1
GA 50 C
FE q
8.7.4.1 1
(SH.2)
ST Q
8.7.4.1 C
HV-84 F5 Q
8.7.4.1 C.
PI 2Y S.7.4.8 8e u
2 8
E q
8.7.4.1 (SM.2)
ST 8.7.4.1 C
RV-44 F5 9
8.7.4.1 C
PI 2Y 8.7.4.8 81 C4 2
B 1
E 4
8.7.4.1 (SM.2)
(
8.7.4.1 C'
RW44 F5
(
8.7.4.1 C-PI 2Y 8.7.4.8 82 C-6 2
8 1
$8 C
E 9
8.7.4.1 (SH.2)
ST 4
8.7.4.1 C
RW44 F3 4
8.7.4.1 C
PI 2Y 8.7.4.8 83 F-6 2
8 1
E.
(
8.7.4.1 (SM.2)
ST 4
8.7.4.1 C
RV-44 F5 g
8.7.4.1 C
PI 2Y 8.7.4.8 84 F-6 2
8 1
E 4
8.7.4.1
($H.2)
ST 8.7.4.1 C
RV-44 F5 9
8.7.4.1 C
PI 2Y s.7.4.8 85 G-6 1
A 1
GA 50 C
FE Q
8.7.4.1 (SH.2)
ST Q
8.7.4.1*
SfC RV-44 FS Q
8.7.4.1 C
PI 2Y 8.7.1.5 LJ ZY 8.7.1.5 86 G-6 1
A 1
GA 50 C
FE O
8.7.4.1 i
(SH.2)
ST Q
8.7.4.1*
WC RV-64 l
FS Q
8.7.4.1 C
l P1 2Y 8.7.1.5 i
LJ 2Y 8.7.1.5 l
l 8.I.1.1 Rev. O Page 126 of.171
rete -
unFWWIM MifE TESTEE P853155
~
ISI riatt 1. 2, 3 m IE inti;E5 PILMIR IWCtfAR PWlER STATIBI PRID: 15 2419EET 1 of 2 SYSTUt: N IEAT N SYSTM (M1)
PSIO: 96-241 SEET 2 of 2 l
Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test POW'S Proc.
Test Relief l
Number (ggr Class Cat Size Twee Twee Position Rest.
Free Eguber Dirgq;1 ige Reeuest Notes 2A D-6 2
C 2
CK SA C
PC Q
8.5.2.2.1*
FF DisassauM e-(SH.2)
FC RO 8.I.27*
FF W-27
'To Ezercise w
Sp a;5_7_7_1 Cieged 2B D-3 2
C 2
CK SA C
PC Q
8.5.2.2.2*
FF SisesseuMe (SH.2)
FC R8 8.I.27' FT W.27 Ts Fasercise w
me 8.5AL2 C1med 2C G-6 2
C 2
CK SA C
PC Q
8.5.2.2.1*
FF Disasweie (SH.2)
FC BR S.I.27' FF RW-27 To Enercise AP ES 3,j5 1 2.T Closed ID G-3 2
C 2
CK SA C
PC Q
8.5.2.2.2*
FF Disas M ie (SH.2)
FC R8 8.I.27*
FT W.ZF To Emercise e
me 8.5.LL2 Cleend 7A D-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 8.1 2.3 78 D-4 2
B 18 GA MO O
FE Q
8.5.2.3 (SH.2)
ST Q
8.5.2.3 0/C PI 2y a_5_7_1 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 ZY 8.5.2.3 70 F-4 2
8 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 16A F-7 2
B 18 GL MD C
FE Q
8.5.2.3 (SH.2)
ST Q
8.5.2.3 0
PI 2Y 8.5.2.3 168 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. O Page 129 of 171
= - - -
TABLE i'
INSERVICE VALVE TESTING PROGRAM ISI CLASS 1. 2. 3 AND 18C VALVES PILGRIM NUCLEAR POWER STATION i
P&ID: N-c39.J4E~T 1 of 3 SYSTEM: POST ACCIDENT SAMPLIIEi & H2*02 P&ID: M 239 SHEET 2 of 3 ANALYZER SYSTEM (5065)
Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Pers Proc.
Test Relief
!6 umber Coor.. Clus Cat Size Twee Type Position Rout.
Free IIgeber Direction _Reggst Noles 87 44 2
8 1
GL A0 9
FE q
8.7.4.1 (SH.1)
ST 4
8.7.4.1 C
RW-44 F5 4
8.7.4.1 C
n zy 8.7.4.8 86 D-4 2
8 1
E.
A8 0
FE 4
8.7.4.1 I
(SM.1)
ST 4
8.7.4.1 C
8V44 FS 4
8.7.4.1 C
n 2Y 8,7.4.8 89 D-7 2
8 1
G.
A8 0
FE 9
8.7.4.1 (SH.1)
ST Q
8.7.4.1 C
RW-44 F5 9
8.7.4.1 C
n 2Y 8.7.4.8 9e s.6 2
8 i
a Ao e
FE q
8.7.4.1 (SM.1)
ST Q
8.7.4.1 C
RW-94 F5 4
8.7.4.1 C
n 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 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 ZY 8.7.1.5 LJ ZY 8.7.1.5 122A C-8 2
8
.375 GA SV O
FE 4
8.7.4.1*
(SH.1)
ST q
6.7.4.1*
O WW.44 F5 9
8.7.4.1*
C PI RY B.7.4.8*
1228 C-1 2
8
.375 GA SV C
FE Q
8.7.4.1*
(SH.1)
ST Q
8.7.4.1*
O WW-44 F5 Q
8.7.4.1*
C PI 2Y 8.7.4.Y 8.I.1.1 Rev. O Page 127 of 171
TASLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2. 3 Ano NC VALVES PILGRIM NUCLEAR POWEP STATION P&ID: ' M-239 SHEET 1 of 3 SYSTEM: POST ACCIDDIT SAMPLING & H2+O2 P&ID: M-239 SHEET 2 of 3 ANALYZER SYSTEM (5065).
'<alve P&ID ISI Valve Valve Valve Actuator Normal Test Test Purs Proc.
Test Relief tiveber Coor Class (at Size Twee Twee Position Rest.
Free Muuter 9 M,ien Reemest Notes 123A C-8 2
8
.375 GA SV C
FE 4
8.7.4.1*
(SH.1)
ST 4
8.7.4.1*
9 NV-44 FS 9
8.7.4.1*
C Pt 2Y 8.7.4.P 1238 C-1 2
8
.375 GA SV C
E 9
8.7.4.1*
(SH.1)
ST q
8.7.4.1*
9 RV-84 F5 g
8.7.4.1*
C PI 2Y 8.7.4.P 1744 C-7 2
8
.375 GA SV C
E 4
8.7.4.1*
(SH.1)
ST 4
8.7.4.1*
9 EU-84 F5 g
8.7.4.1*
C PI 27 8.7.4.F 12e C-2 2
8
.375 GA SV C
E 4
8.7.4.1*
l (SH.1)
ST 4
8.7.4.1*
8 WW-84 l
F5 9
8.7.4.1*
C Pt 2Y 8.7.4.P 5117A H.6 2
8
.375 GA SV C
E 4
8.M.3-13*
(SH.1)
ST h4 m
WW-31 F5 9
8.N.3-13*
C' 51178 H-3 2
8
.375 GA SV
.C E
g 8.N.3-13*
(SH.1)
ST m
M WW-31 FS 9
8.N.3-13' C
5137A G-6 2
8
.375 GA SV C
E 4
8.M.3-13*
(SH.1)
ST M
M EW-31 FS 9
8,1h3-13*
C 51378 G-3 2
S
.375 GA SV C
FE 9
8.M 3-13*
(SH.1)
ST m
m NV-31 F5 e
8.n.3-13' C
8.I.1.1 Rev. O Page 128 of 171
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IIESERVICE VALVE TESTEE PEEERfet 15I cut $$ 1, 2. 3 M S IE 1NILVES
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PILERIN IEELEM PSER STATISE l
P&ID: M-241 SEET 1 of 2 SYSTEM: g3sanans IEAT MpWORL ST57BI (1991)
P&ID: M-241 9EET. 2 of 2 2t Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test FIPS Proc.
Test Relief Number (nor Class Cat Size Tvoe Tvoe -
Position Ramt.
Frea Nusher Direction Reouest teotes 28A F-6 2
A 18 GL M0 O
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 EV-23 288 F-4 2
A 18 GL MG 0
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 RV48 29A E-6 1
A 18 GA M0 C
8.I.11.3 0/C C5-89 PI 2Y 8.5.2.7 LJ 2Y 8.7.1.5 EV-28 LP 2Y 8.5.2.7 29B E-4 1
A 18 GA M0 C
ST CS 8.I.11.4 0/C C5-49 PI 2Y 8.5.2.7 LJ 2Y 8.7.1.5 WW-28 LP 2Y 8.5.2.7 32 B-3 2
A 4
GA M0 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 33A E-6 1
MA 18 GA MR LO IIA IIA IIA rg (nonnal)
(SH.1)
PI 2Y 8.5.2.7 338 E-4 1
MA 18 GA MA LO 18 4 HA 10 4 E W (Manual)
(SH.Il PI 2Y 8.5.2.7 34A F-7 2
A 12 GA M0 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-28 348 F-3 2
A 12 GA M0 C
FE Q
8.5.2.3 (SH.1)
ST Q
8.5.2.3 0/C PI-2Y 8.7.1.5 i
LJ 2Y 8.7.1.5 WV-28 8.I.1.1 Rev. O Page 131 of 171
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IN5ENIE VALE TESTIE PM ISI ClJS51. 2.'3 JUB EC VRI.VE5
'y PILERIII IEELEM FWER STATISI P&ID: 4241 SEET 1 ef 2 SYSTER-MIEWAR. IEAT N SYSTUI 0891)
P&ID: 94-241 SKET 2 of 2 Valve P&ID ISI Valve Valve. Valve Actuator
. Normal
' Test
. Test FIPS Pmc.
' Test Relief' Number Coor Class Cat Size Type Tvoe Position Ramt.
Free W
Direction Reeuest' Notes 36A E-7 2
B 12-GL MO C
FE Q
8.5.2.3 (SH.1)
-Q 8.5.2.3 0/C PI 2Y 8.5.2.3 368 E-3 2
B 12 GL M0 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
GL M0 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 N-28 37B E-3 2
A 6
GL 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 EW2B l
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IIESERVIE VIILVE TESTINE PR8ERAH ISI CLASS 1,: 2. 3 AIS NC _YALVES -
PILMIM IEERIM PSER STATIGI P&ID: 5241 SE ET 1 of 2 SYSTEM: EESIBIIRL IEAT MEWullt. SYSTER (1881)~ ~
P&ID: 5241 SK ET 2 of 2 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test PIE'S Proc.
Test Relief Numb _er__C_.tg r CIAss Cat Size Tvoe Tvoe Position Ramt.
Frea 30guber Direction Reevest Notes 43A E-5 2
B 18 GA MD C
FE Q
8.5.2.3 (SH.2)
ST Q
8.5.2.3 0
FI 2Y 8.5.2.3 43R E-4 2
B 18 GA te C
FE Q
8.5.2.3 (SH.2)
ST Q
8.5.2.3 0
'2Y 8.5.2.3 43C G-5 2
8 18 GA le C
FE Q
8.5.2.3 (SH.2)
ST y
8.5.2.3 0
PI 2Y 8.5.2.3 43D G-4 2
8 18 GA MD C
FE Q
8.5.2.3 (SH.2)
ST Q
8.5.2.3 9
PI 2Y 8.5.2.3 44 C-5 2
RT SY 8.I.26*
(SH.11 LX IR 8.I.26*
NT Verifies 47 C-5 1
A 20 GA MG C
ST '
-CS 8.I.11.5 C
CS-02 PI 2Y 8.5.2.8 LJ 2Y 8.7.1.5 EW-28 LP 2Y 8.5.2.8 50 D-5 1
A 20 GA M0 C
CS-02 PI 2Y 8.5.2.8 LJ 2Y 8.7.1.5 EW-28 LP 2Y 8.5.2.8 59 H-6 2
AC 1
RL SA C
RT-SY 8.I.26' (SH.11 L2 HA 8.I.26*
ET Verifies 60 H-5 1
A 4
GA M0 C
FE NA IIA Insperative PWC (SH.1)
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 8.I.1.1 Rev. O Page 133 of 171 m
IN5GVICE VALVE TESTIIE PESERan ISI CLASS 1. 2. 3 ABB IE VALVES PILMIM MELEAR PRER STATISI P&ID: N-241 S E ET 1 t.f 2 SYSTEN: N IEAT MIGURI. SY5TDI (1991)
PRID: N-241 S K ET 2 of 2 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test PIPS Proc.
Test Relief Number Cggr Class Cat Size Twee Type Position Rast.
Frea IImider Directies Reauest Ilotes 63 G-S 1
A 4
GA M0 C
FE NA NA Inoperative P9C (SH.1)
ST-NA NA (9eenergized)
PI 2Y 8.5.2.9 LJ 2Y 8.7.1.5 LP RS 8.5.2.9 RV-24 64 G-5 1
AC 4
CK SA C
FC CS 8.I.11.6 CS-19 Imeyerati w POC (jiH.11 LP RO 8.5.2.9 RV-24 (Pise CggadL
^
67A D-6 2
C 12 CK SA C
FC Q
8.5.2.2.1 FF (SH.2)
AP RO 8.5.2.2.1 Closed 67B D-3 2
C 12 CK SA C
FC Q-8.5.2.2.2 FF-i (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 no 8.5.2.2.1 C1. sed 67D F-3 2
C 12 CK SA C
FC Q
8.5.2.2.2 FF (SH.2)
Ar no 8.5.2.2.2 C1. sed 68A E-6 1
PC CS 8.I.11.17' FF CS-83 (SH.1)
FC RO 8.I.27*
FF M
Disa M ie To LP 2Y 8.5.2.7 Emmerise 688 E-4 1
PC CS
-8.I.11.17*
FF C5-83 (SH.1)
FC RO 8.I.27*
FF M
Disass d ie To LP 2Y 8.5.2.7 E arrise 362B F-2 2
AC 2
CK SA C
PC Q
8.5.2.2.2*
FF (SH.2)
FC RO 8.5.2.7*
Closed LX 2Y 8.5.2.13*
8.I.1.1 Rev. O I
Page 134 of 171
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PSID: 5241 SE ET 2 of 2 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test -FIPS Proc.
Test.
.. Relief N_uder Coor Class Cat Size Tvoe Twoe Position Ramt.
Frea Iluminer Directies Reauest IIntes '
~
363A G-8 2
AC 2
CK SA
.C
'PC Q
8.5.2.2.1" FF (SH.2)
FC R0 8.5.2.7*
Closed LX 2Y
-8.5.2.13*
515 D-3 2
AC 6
CK SA C
FC IIA.
IIA rummpt (pinist.)
(SH.1)
PI 2Y 8.5.2.14*
u RS 8.5.2.14"
~
8804 F-6 2
AC 1.5 E
SA C
RT SY 8.I.26*
(91.2)
U
IIA 8.I.26*
RT 11erifies 8085 D-6 2
AC 1.5 E
SA C
RT SY 8.I.26*
(91.2)
G IEA S.I.26*
RT Mlarifies 8086 D-4 2
AC 1.5 K
SA C
RT SY -
8.I.26*
(98,2)
U EA 8.I.26*
RT Marifies l
8007 F-4 2
AC 1.5 R
SA C --
RT SY 8.I.26*
(SH.2)
U IIA 8.I.26*
RT 11mrifies 8088 IL7 2
AC 1
R SA C
RT SY 8.I.26*
(98.2)
G IIA 8.I.26" N 11mrifies l
8009 D-3 2
AC 1
R SA C
RT SY 8.I.26*
l (9f.2) u ItA 8.I.26*
' RT 11eriflem l
l l
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.Page 13S of.171 c-r
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IN5ENICE 1mLVE TESTDE M ISI CLASS 1. 2.'3 N B NC imLVES-PILERIN IWCLEAR PSER STATIBI PEID: N-242 SYSTEN: CK SPRAY SYSTEN (140).
l l
Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test. Fir $ Proc.
Test Relief l
Number Coor Class Cat Size Twoe Twee Posi tion Rant.
Free End er Directies Recuest Notes 3A F-7 2
B 18 GA MO O
FE.
Q 8.5.1.3 ST Q
8.5.1.3 C
PI 2Y 8.5.1.3 38 F-8 2
B 18 GA M0 O
FE Q
8.5.1.3 ST Q
8.5.1.3 C
3 PI 2Y 8.5.1.3
(
4A C-6 2
B 6
GA M0 C
FE Q
8.5.1.1 i
ST Q
8.5.1.1 C'
PI 2Y 8.5.1.1 4B C-6 2
B 6
GA MO C
FE Q
8.5.1.1 ST Q
8.5.1.1 C
PI 2Y 8.5.1.1 6A C-3 1
NA le GA m
LO NA m
NA ExcePt (Nansal)
PI 2Y 8.5.1.6 68 C-3 1
NA 10 GA NA LO NA m
m E M (Nueuel)
PI 2Y 8.5.1.6 7
D-4 1
AC 1
CK SA 0
'FC RO 8.N.3-Z*
RF W-22 FEC: 86-85 AP RO 8.N.3-2*
Open Corrently LX RO 8.N.3-2*
EW22 t===arative 9A D-3 1
FC RO 8.I.15 FF RW-46 LP 2Y 8.5.1.6 98 B-3 1
FC R0 8.I.15 FF N.46 LP 2Y 8.5.1.6 13A E-7 2
C 3
SC SA C/LO-FC Q
8.5.1.1" FF FC R0 8.I.27*-
FT H
Dihie AP RD 8.I.27*
Closed To Euercise 138 E-9 2
C 3
SC SA C/LO PC '
Q 8.5.1.1*-
FF W-27 Di====mable AP BD 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-
- 0/C PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 RY-28 248 B-5 2
A 10 GA MO O
_Q 8.5.1.3 ST Q
8.5.1.3 0/C PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 RW28 8.I.1.1-Rev. O Page 136 of 171
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A t e 0 M
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S S S
S S
S c w M A T ev e l
o A A
L L
K K
K K K
K K
K a w G G
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C C
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C C
C VT ev e l
z 0 0
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1 1
6 0 0
2 2
6 ai 1 1
1 1
VS ev l t A a a A
C C
C C
C C C
C C
C VC A
A A
A A
A ss I a S l 1 1
2 2
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2 2 2
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2 I C D r 2
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4 4
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7 7
5 4
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w ad LINSERVICE VALVE TESTING.. PROGRAM
-ISI CLASS 1, 2, 3 AND NC VALVES.
y
' PILGRIM NUCLEAR POWER STATION P&ID: 5243 SHEET 1
. SYSTEM: HIGH PRESSURE COOLANT 18tJECTION (2381)'-
P&ID: M-244 SHEET 2 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Firs Proc.
Test Relief
!~
thLsker Coor Class Cat Size Tvoe Type Position Root.
Frea llymber
' Direction Reauest Notes 2301-23 E-11 2
B 10 GA H0 C
FE Q
8.5.4.4 (HO-1) (SH.2)
ST Q
8.5.4.4 0/C 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 Centeel Unive (HO-2) (SH.2)
ST Q
NA SV-47 f E,ST, Augment-FS Q
5.5.4.4 C
ed IRC require-PI 2Y 8.5.4.4 must 3
F-13 2
8 10 GA MO C
FE Q
8.5.4.1 Alse 8.5.4.4 (SH.1)
ST Q
8.5.4.1 0
Alse 8.5.4.4 PI 2Y~
8.5.4.4 4
D-4 1
A 10 GA M0 O
FE Q
8.5.4.4 (SH.1)
ST Q
8.5.4.4 0/C PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 SV-23 5
D-6 1
A 10 GA MO
'O FE -
Q 8.5.4.4 (SH.1)
ST Q.
8.5.4.4 0/C PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 SV.25 6
C-10 2
B 16 GA MO O
FE Q
8.5.4.4 (SH.1)
ST Q
8.5.4.4 0/C PI 2Y 8.5.4.4 7
H-5 1
( SH.1 )
LP 2Y 8.5.4.8 8
H-S 1
A 14 GA M0 C
'ST CS 8.I.11.11 0/C C5-49 PI 2Y 8.5.4.8 LJ 2Y 8.7.1.5 M
LP 2Y 8.5.4.8 9
H-6 2
8 14 GA MO O
FE.
Q.
8.5.4.4 (SH.1)
.ST Q
8.5.4.4 0
PI 2Y 8.5.4.4 8.I.1.1 Rev. O Page 138 of 171
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C C
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0 S
A A
A 0
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M I
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8 B
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-INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-243 SHEET 1 SYSTEM: HIGH PRESSURE COOLANT INJECTION (2301);
P&ID: M-244 SHEET 2 i
l-Valve P&ID ISI Valve Valve Valve Actuator Normal Test
. Test FIR'S Proc.
Test Relief l
Nutnber Coor Class Cal Size Tvoe Tvoe Position Rosit.
Frea Itamber DirMon Reouest Notes 34 K-5 2
C 2
CK SA C
PC Q
8.5.4.1" FF l
(SH.1)
FC '
RO 8.I.27*
FF RW-27.
Disassemble Te AP RS 8.I.27*
Closed Emmetise 35 E-9 2
8 16 GA M0 C
FE Q
8.5.4.4 (SH.1)
ST Q
8.5.4.4 0/C PI 2Y 8.5.4.4 36 M-5 2
B 16 GA M0 C
-Q 8.5.4.4 (SH.1)
ST Q
8.5.4.4 0/C PI 2Y 8.5.4.4 39 M-6 2
C 16 CK SA C
FC R0 8.I.27*
FF NV-27 Disassenhie To iSH.11 AP RS 8.I.27*
Closed Emise 40 K-5 2
C 4
CK SA C
PC Q
8.5.4.1*
FF (SH.1)
FC RO 8.I.27*
FF RW-27 Bisass d ie Te AP RD 8.I.27*
Closed Exercise 45 J-4 2
FC Q
8.5.4.1 FF (SH.1)
LJ 2Y 8.7.1.5*
RV-28 53 3-19 3
AC 1
Rt.
SA C
RT SY 8.I.26*
(21,21 LX IRA 8.I.26*
RT Verifies 64 L-9 3
8 1
GA AS C
FE -
Q 8.5.4.4 (SH.2)
ST Q
8.5.4.4*
8/C F5 Q
8.5.4.4 C
PI 2Y 8.5.4.4 68 K-11 2
D 16 RD SA C
RD NA IRA Non-Testable (SH.1) 69 K-12 NC D
16 RD SA C
RD NA IGA Mon-Testable (SH.1) 74 J-3 2
8.5.4.1 FF (SH.1)
LJ 2Y 8.7.1.5*
IV-28 75 K-8 2
C 4
CK SA C
FC.
Q 8.5.4.1 FF (SH.2) 76 L-6 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. O Page 140 of 171
- E-TABLE
. INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION
'P&ID: M-243 SHEET 1 SYSTEM:.HIGH.PRESSURC COOLANT INJECTION (2381)..
P&ID: M-244 SHEET 2 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test PIFS Proc.
Test Relief' Number Coor Class Ca_t Size Tvpf Type Position Rqmt.
Frea Number Directiert Ren9est Notes 216 H-9 2
C 2
CK SA C
PC -
9 8.5.4.1*
-FF (SH.2)
FC RO - 8.I.27*
FF NY.77 Disassw261e Te AP BB 8.I.27*
Gesed Emmecise 217 K-4 2
C 2
CK SA C
PC q
8.5.4.1*
FF (SH.1)
FC RO 8.I.27" FF WW-27 DisassemMe Te AP BB 8.I.27*
G=d Exercise 218 J-3 2
AC 1
CK SA C
FC CS 8.I.11.8*
FF CS-15 (SH.11 U
2Y 8.7.1.5' 220 F-5 1
AC 1
SK SA 0
FC RO 8.N.3-2 RF WW-22 AP no 8.n.3-2 open (SH.11 LX RB 8.M.3-2 EE.22 232 M-1 2
C 3
CK SA C
AP W
8.I.11.8*
G esad 233 H-1 2
C 3
CK SA C
' FC.
CS 8.I.11.8*
FF.
CS-07 (SH.1)
AP BB 8.I.11.8*
G-d 9068A J-2 2
A 1
E.
50 C
'FE 4
8.5.4.4 (SH.1)
Sr 4
.M RV-25 FS q
8.5.4.4 C
U 27 8.7.1.5*
906 3 J-2 2
A 1
GL 50 C
FE 4
8.5.4.4 (SH.i>
Sr q
m Ev.s FS 4
fi.5.4.4 C
U 27 8.7.1.5*
9312 K-10 2
8 1
E.
AG C
FE 4
8.5.4.4*
(SH.i)
Sr g
8.5.4.4*
C FS 4-8.5.4.4*
C PI 2Y 8.5.4.4*
9313 K-10 2
8 1
GL A0 C
FE Q
8.5.4.4 (SH.1)
ST Q
8.5.4.4 C
. r5 Q
s.5.4.4 C
PI 2Y 8.5.4.4 8.I;1.1 Rev. 0
-Page 141 of.171L a
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TMLE -
neuTICE WLVE TESTIIE PEemfWI ISI CutSS 1, 2, 3 25 HC MilLVES -
PILMIM IM3.Em PSER STATIM.
P&ID: N-245 SK ET 1 SYSTDt: REACTM CNE rams nec SYSTDI (1381)
P&ID: M-246 SKET 2 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test FIW'S Proc.
Test Relief Nymber Coor Class Cat Size Tvoe Tvoe Position Ramt.
Free Ilumber Direction Reevest-Notes 1
E-12 2
B 2
GA 50 0
. FE '
Q 8.5.5.1*
(SH.2)
-Q 8.5.5.1*
.C
-~ W-44.
FS Q
8.5.5.1*
C
- Closed
'PI
'2Y 8.5.5.1*
2 E-11 2
NA 2
GV H0 0.
FE Q
8.5.5.1*
- Gov. Valve -
(SH.2)
ST Q
NA.
' WW16 FE.5T WC Aug--
r5 Q
8.5.5.i*
a mented neg'=t PI 2Y 8.5.5.1*
9 E-19 2
0 8
HD SA C
.HD NA HA Mon-Testable '
(SH.2) 12 L-7 3
5 1
GL A0 C
FE q
8.5.5.4 (SH.2)
ST q
8.5.5.4 C
FS q
8.5.5.4 C
PI 2Y 8.5.5.4 15A B-6 1
AC 1
SK SA 0
FC RO 8.N.3-2 RF NW-22 AP Re 8.M.3-2 Open (SH.1)
LX ES '
8.N.3-2 EM 158 B-6 1
AC 1
SK SA 0
FC R0 8.M.3-2 RF RW22 AP RS 8.M.3-2 Open (SH.Il LX 30 8.N.3-2 EW,22 16 C-6 i
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 17 C-7 1
A 3
GA M0 O
FE Q
8.5.5.4 (SH.1)
ST Q
8.5.5.4
'0/C PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 "8.I.1.1
' Rev. O Page 142 of 171 y
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TABLE INSERVICE VALVE TESTIE PRRERM
. ISI CLASS 1, 2. 3 Am IE VALUES PILMIM IRfCLEAR F8bER STATIipt P&ID: M-245 SKET 1 SYSTEN: REACTM CK C88LBE SYSTUt (1MI).
P&ID: M-246 SKET 2 Valve P&ID ISI Valve Valve' Valve Actuator Normal Test Test Ftr5 Proc.
Test Relief Nys6er (por Class Cat Size Tvoe Twoe Position Ramt.
Frea Ituuhrr Direction Reevest Notes 22 D-11 2
B 6
GA M0 O
FE Q
8.5.5.4" (SH.1)
ST Q
8.5.5.4 0/C.
PI 2Y 8.5.5.4 23 D-11 2
C 6
CK SA C
FC Q
8.5.5.1*
FF' (SH.1) 25 L-8 2
B 6
GA M0 C
FE Q
8.5.5.4 (SH.1)
ST Q
8.5.5.4 O/C PI 2Y 8.5.5.4 26 D-10 2
8 6
GA M0 C
FE Q
8.5.5.4 (SH.1)
ST Q
8.5.5.4 0/C PI 2Y 8.5.5.4 27 L-9 2
C 6
CK SA C-FC R0 8.I.27' FF RV,Z7 Bisasseu6le Te (SH.1)
AP 30 8.I.27*
Closed Emercise
+
31 C-8 2
AC 2
RL SA C
RT SY 8.I.26*
iSH2 )
~ LI 10 4 8.I.26*
RT Verifies 34 K-13 2
8 1
GL A0 C
FE Q
8.5.5.4 (SH.1)
ST Q
8.5.5.4 C
FS Q
8.5.5.4 C
PI 2Y 8.5.5.4 40 J-9 2
AC 2
CK SA C
PC Q
8.5.5.1*
FF RV-27 Disassemble Te (SH.1) 12 2Y 8.7.1.12*
Exercise 41 J-6 2
AC 8
CK SA C
FC Q
8.5.5.1* -
FF (SH.1)
LX 2Y 8.7.1.12*
42 J-8 3
AC 1
RL SA C
RT SY 8.I.26*
($H 2)
LX IRA 8.I.26*
RT Verifies 2
47 H-8 2
AC 2
CK SA C
PC Q
FF RV,Z7 Disassemble To (SH.1)
LI 2Y 8.7.1.12*
Esercise 48 E-8 2
B 4
GA MO
-0 FE Q
8.5.5.4 (SH.1)
ST Q
8.5.5.4 O/C PI 2V 8.5.5.7 8.I.1.1 Rev. O Page 143 of 171~
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IN5ERVICE VALE TESTEME PEEERAM
~~9
'ISI CutSS 1,'2..3 153 E VRLVES '
~*
PILGRIN IEELEM PSER STATTWI PSIn: M-245 SHEET 1 SYSTEM: EEACTER CEBE CEOU NE 575791(1391)
~
PSID: 4246 SIEET 2 Valve P&ID ISI Valve Valve Valve Actuator Normal
- Test Test FIPS Proc.
Test Relief.
Number Cogr Class Cat Size Tvoe Type Position Rout. ~Freo Slumber Direction' Reauest Notes-49 E-7 1
A 4
GA M0 C
ST CS 8.I.11.11' 0/C CS-89 PI 2Y 8.5.5.7 LJ 2Y 8.7.1.5
' LP 2Y 8.5.5.7 50 E-7 i
AC 4
CK SA C
FC CS 8.I.11.9 FF CS (SH.11 LP 2Y 8.5.5.7 53 D-8 2
8 4
GL M0 C
FE.
'Q 8.5.5.4 (SH.1)
ST Q
'8.5.5.4 C
PI 2Y 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 Disassem61e Te AP RB 8.I.27*
Closed Exercise 60 H-8 2
B 2
GL NO C
FE Q-8.5.5.4 (SH.1)
ST Q
8.5.5.4 0/C PI 2Y 8.5.5.4 61 E-13 2
B 3
GA M0 C
FE Q
8.5.5.1
~Alse 8.5.5.4 (SH.2)
ST Q
8.5.5.1*
8/C Also 8.5.5.4 PI 2Y 8.5.5.4 62 J-7 2
B 2
GL M0 C
FE Q
8.5.5.4 (SH.2)
.5T Q
8.5.5.4*
O/C PI 2Y 8.5.5.4 63 K-6 2
C 2
CK SA C
PC Q
8.5.5.1*
. FF FC BD 8.I.27*
FF '
NV-27 Disassemble Te (SH.2)
AP MO 8.I.27*
Closed Exercise 64 J-6 2
AC 8
SC SA LD/C FC Q
8.5.5.1*
FF (SH.1)
LX 2Y 8.7.1.12 8.I.1.1 Rev. O Page 144 oF 171 4._.
w-
. TABLE i
swavIm VALVE TESTEIE PREElm.,
. ISI GASS. I. 2.' 3 Jg3 IE VALVES -
7 PILMIM IEKI.EM PSER STATIM P&ID: IS-245 SIEET 1 SYSTDt: NACTM CK m M SYSTUI (W1)
P&ID: 96-246 SEET 2 Valve P&ID ISI Valve Valve - Valve Actuator
- Normal Test Test PIr5 Proc.-
Test Relief Number Coor Class Cat Size Twee Twee Position -Rent.
Free h
Direction' Reemest' listes 70 J-12 3
AC.
1.5
.RL SA C
WT SY 8.I.26*'
(SH.2)
~LX HA 8.I.25*
NT vlerifism
'^~
89 J-le 3
C 1
m SA C:
FC HS 8.I.27*
FF EE-27 Disassemble To -
(91.2)
'M 8.I.27*
Ci d Exercise-98 K-11 3
C
'l m
.C PC' tt '~
8.5.5.1*
FF (SH.2)
' FC M
8.I.27'.-
FF-M ' Disass d ie To' AP W-
-8.I.27"'
C1 M Emercism 9067 H-6 2
C 1
SK SA C
FC-CS' 8.I.11.19
AP' RS 8.5.5.1*-
Closed t
6 8.I'.1.1 Rev. O Page 145.of 171 1.
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4 INSERVICE VALVE TESTING PROGRAM ~
ISI CLASS 1. 2, 3 AfG NC VALVES
' PILGRIM NUCLEAR POWER STATION
~
P&ID: M-250 SHEET 1 of 2
-SYSTEM: ~ CONTROL ROD DRIVE HYDRAULIC-P&ID: M-250 SHEET 2 of 2 SYSTEM (302)
Valve P&ID ISI Valve Valve Valve Actuator. '
Normal.
Test Test Firs Proc.
Test Relief Number Coor Class Cat Sire' Twee Tvoe Position Ramt.
Frea heder Directies Reevest Notes 21A G-3 2
8 1
-PG A0 0
FE Q
8.3.3 (SH.2)
ST Q-
,8.3.3 0
C RV-26 FS Q
8.3.3 C
' PI 2Y 8.3.3 218 G-7 2
B 1
PG A0 0
FE Q
8.3.3 (SH.2)
ST Q
8.3.3' 0
8.M.1-31*
C RW-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
ST R9 8.M 1-31*
C 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
0 ST RS 8.M.1-31".
C RV-26 FS Q
8.3.3 -
C' PI 2Y 8.3.3 23A G-3 2
8 1
PG A0 0
FE Q
8.3.3 (SH.2)
ST Q
8.3.3 0
C RW-26 FS Q
8.3.3 C'
PI 2Y 8.3.3 238 G-7 2
B 1
PG A0 0
FE Q
8.3.3 (SH.2)
. ST Q
8.3.3 0
ST R8 8.M.1-31*
C RW-26 FS Q
8.3.3 C
PI 2Y 8.3.3
.e 8.I.I.1
'Rev. 0 Page.148 of 171
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s, ITABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES-PILGRIM MUCLEAR POWER STATION P&ID: % 250 SHEET 1 of 2 SYSTEM: CONTROL R00 DRIVE HYDRAULIC' P&ID: M-250 SHEET 2 of 2 SYSTEM (302)
Valve P&ID ISI Valve Valva Valve.' Actuator Normal
. Test Test Mr5 Proc.
Test Relief Mumber Coor Class Cat Size Tvoe Tvoe Position Romet.
Free Ruder Directige Reauest
- Notes 24A D-4 2
B 2
PG A0 0
FE Q
8.3.3 -
(SH.2)
ST.
Q 8.3.3
.O ST 20 8.M.1-31*
C HV-26 FS Q
.8.3.3 C
PI 2Y 8.3.3 248 D-7 2
B 2
PG AO -
0
.FE Q
8.3.3 (SH.2)
ST Q
8.3.3 0
C RW-26 FS Q
8.3.3 C
PI 2Y 8.3.3 114 A-18 2
C 0.5 CK SA C
FC RO-9.9*
(SH.11 115 C-19 2
C 0.5 CK SA C
FC RO 9.9*
(SH.1)
Closed 120 B-18 2
8 8.5 2
50 C
FE q
8.3.2
' NW17.
(HCU)
(SH.1)
.Q NA WW17 FS O
8.3.2 C
EW17 121 B-18 2
8 6.5 m
50 C
FE Q
8.3.2 RW-17 (HCU)
(SH.1)
ST Q
m WW17 FS O
8.3.2 C
EW17 122 B-17 2
5 8.5 m
50 C
FE 4
8.3.2 RW-17 (HCU)
(SH.1)
ST Q
RA.
EU-17 FS 0
8.3.2 C
EW17 123 B-17 2
8 8.5 m
50 C
FE Q
8.3.2 RW-17 (HCU)
(SH.1)
-Q m
EW-17' FS 0
8.3.2 C
EW17 -
8.I.1.1 Rev. O Page 149 of 171
,-s
, nc :m3 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)-
Valve P&ID ISI Valve Valve ' Valve Actuator?
Normal-Test-Test FRPS Proc.'-
Test ~
Relief Humber Coor Class Cat Size Twee Twee' Position Raet.
Frea h
Direction Reeuest Notes 126 B-17 2
B 1
PG A0 C
HV-49 (HCU)
(SH.1)
MW-49 PI 2Y'
' 9.9" -
127 A-17 2
B 9.5 PG A0 C
FE R0
~9.9" N-(HCU)
(SH.1)
' NVE -
FS RO 9.9" O
EV-49 PI 2Y 9.9" 132 C-18 2
0 0.5 RD SA C
- RD NA L IIA Mon-Testable (HCU)
(SH.1) 138 C-16 2
C 0.5
.CK SA 0
FC Q
8.3.2 RF WW-M (HCU)
(SH.11
- 8.I.1.1 Rev. 0-Page 150 of 171 4
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A A
A A
A A
t o S S
S S
S S
S S
c w AT ev e l
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K K
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S S
C C
C C
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5 5
5 7
7 7
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0 0
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C C
C C
C C
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A A
A A
A A
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2 2
2 2
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5
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5 6
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TABLE-
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-INSERVICE VALVE TESTING PROGRAM b$-
~
l ISI CLASS 1. 2. 3 AND NC VALVES' 5c
'~,
~
' PILGRIM NUCLEARI?OWER STATION
(
P&ID: M-252
[ SYSTEM:~ FEED WTER SYSTEM (6)
Valve P&ID ISI Valve Valve Valve Actuator Norneal -
Test
-. Tes t FIPS Proc.
Test-'
Relief.
7' Number Coor Class Cat Size Twoe' Twee Position Rout.
Free h
Directies' Reensest Notes 58A E-4 1
.FC PO 8.7.1.5 '
RF' HV-12
.M
~' RO 9.3
- Open
^
LJ 2Y 8.7.1.5 MW-28 588 F-4 1
'O FC ~
.R0 8.7.1.5 RF RW-12 M
RO 9.3
- LJ 2Y 8.7.1.5 M
62A E-3 1
.FC R0 A.7.1.5
-RF-
-EV-12 M
30 9.3 *
-t'epen LJ 2Y' 8.7.1.5 EU.23 62B F-3 1
FC RO 8.7.1.5 RF RW-12
-M RS
' 9.3 * '
Spen LJ 2Y 8.7.1.5 EU-2B t
+
.]
.s 8.I.1.1
.Rev. 0 Page 152 of 171 c.
..s
.-n.
c-yy TABLE-
-INSERVICE VALVE TESTING PROGRAM i
g; ISI CLASS 1, 2.'3 AND NC. VALVES 7'
1 l-PILGRIM NUCLEAR POWER STATION' P&ID: M-252 SYSTEM: REACTOR RECIRCULATION SYSTEM (202)
Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test PIr5 Proc.
. Test--
' Relief-Number Coor Class Cat Size Twoe Twee Position Rest. -Frea Ihm6er Directies Reauest listes 4A L-5 1
NA 28 GA M
0 M
M M
Passive-PI 2Y 8.I.11.1 4
46 1
M 28 GA M-O M
MA-M Passive PI 2Y 8.I.11.2
'Hote 1 SA L-8 1
B 28 GA M0 O
.CS 8.I.11.1 CS-05
- ST -
CS 8.I.11.1
.C CS-05
~ Note 1 PI
'2Y 8.I.11.1 j
i 5B W6 1
B 28 GA MO' 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
- 8.I.1.1 Rev.' O Page 153 of 171~
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t t ES s m ET S I J ET S I J ET S I J ET S I J ET S I J CS M e a F SF P L F S F P L F S F P L F S F P L F S F P L I AI T R VL R RCG E
L n
SI I o
NS P l i I I at mi r s 0
0 0
0 0
o o N P r
n o
tau e 0
0 0
0 0
t o A
A A
A A
c v A T ev e L
L L
L L
l o G G
G G
G a v V T ev e l
z 0 0
0 0
0 ai 2 2
2 2
2 VS ev l t A A
A A
A a a VC ss I a 1 1
1 1
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2 I
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7 7
1 5
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E F
F C
M e r v etA B
C D
A D
l I
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TABLE-INSERVICE VALVE TESTING PROGRAM
~y ISI CLASS'1, 30 3 AND NC VALVES
~
PILGRIM NUCLEAR POWER STATION P&ID: M-252 SYSTEM: MAIN STEAM ISOL., ADS &
' SAFETY RELIEF (203)
Valve P&ID ISI Val ve Valve Valve _ Actuator Normal Test Test ' FIPS Proc.
. Test Relief Number Coor Class Cat Size Tvoc 'Twoe Position-Ramt.
Frea Sunber Direckige Request Notes-2B E-9 1
A 20 ~
GL A0
'O 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 ~
WW-23 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 2Y 8.7.1.6 RW-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 R0 8.5.6.2 RV-li ST RO NA RY-11 FS R0 8.5.6.2 C
RV-11 PI 2Y 8.5.6.2*
RT SY 8.I.26" LX NA 4.I.26*
RT Verifies 38 F-7 1
AC 6
RL/SV A0/SA C
FE RO 8.5.6.2 RV-11 ST R0 NA RV-11 FS R0 8.5.6.2 C
RV-11 PI 2Y 8.5.6.2*
- SY 8.I.26*'
LX NA 8.I.26*
~ RT Verifies 8.I.1.1 Rev. O Page 155 of 171'
,,y m--
-.m--
g m
y O-=f 7 w s-TME i Ji-5 INSERVICE VALVE TESTING PROGRAN r An
' ISI CLASS 1[ 2,' 3 AND NC VALVES
~
~
PILGRIM NUCLEAR POWER STATION' P
.P&ID: M-252 SYSTEM: NAIN STEAN.ISOL., 25 &
SAFETY RELIEF.(293)
~
Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test
'M r5 Proc.
Test-
' Relief Namber Coor Class Cat Size Tvoe Twee Position Rent.
Frea Ilumber Direglige Reevest-
-Notes 3C F-7 1
AC 6
RL/SV. A0/SA C
FE.
- RO
- NA RV FS R0 8.5.6.Z C
RV-11" PI
' 2Y 8.5.6.2*
RT SY 8.I.26*
LX NA 8.I.26*
RT Verifies 3D E-9 1
AC 6
RL/SV A0/SA C
'R0 8.5.6.2 RV-11 ST 90 NA RY-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 Verifi=s
- 8. I.1.1 Rev. 0
- Page 156 of 171-
.. _ ~ -
.. _ __., = _ ~ _ ~
~.
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~
- TA8LE'
~
INSERVICE VALVE TESTING PROGRAM
~
ISI CLASS-li 2, 3.AfE NC VALVES
' PILGRIM NUCLEAR POWER STATION
~
P&ID: M-2S2
. SYSTEM: NUCLEAR BOILER SYSTEM (220)
Val ve P&ID ISI Valve Valve Valve Actuator Normal Test Test Fir $ Proc.
Test Relief Number Coor Class Cat Size Twoe Twee Position Raet.
Frea h
Direction Reauest Notes 1
C-9 1
A 3
GA M0 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 MO 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 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 45 K-3 1
A 1
GL 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 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
8 1
GL A0 C
FE CS 8.I.11.11 CS ST CS 8.I.11.11 C
CS-06 ~
l FS CS' 8.I.11.11 C
CS-06 PI 2Y 8,I.11.11 l
l I
l 8.I.1.1' Rev. O Page 157 of 171
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A A
S S
s c u AT e
v e l
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W W W W W W W W a w S S
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1 1
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ss I a S l 3
3 3
3 3
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2 2
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9-9-9 9
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1 1
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TMLE DEENVIE WLE TESTBE NOMNI ISI CUISS 1, 2. 3 m E WLES PILMIn INCLEM FelER STATIM PSID-96-252 SYSTUt: smirnFM mtER (258)
Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test M r$ Proc.
Test Relief NAgr Coor Class Cat Size Twee Twee Positior! Rast.
Free Rusher Direction Reesest Notes 17A D-11 1
AC 1
SK SA 0
FC R0 8.n.3-2 RF EU-22 Ar no 8.n.3-2 epen tx N9 8.n.3-2 EE-22 173 E<11 1
AC 1
SK SA 0
FC RO 8.n.3-2 RF WW-22 Ar se 8.n.3 2 epen tx me _ S.n.3-2 us-22 17C D-.11 1
AC 1
SK SA 0
FC RC 8.n.3-2 RF mM2 Ar no 8.w.3-2 ep tx 4
8,n.3-2 EW,22 17D E-11 1
AC 1
SK SA 0
FC RO ti.n.3-2 RF nW-22 l
Ar M
8.n.3-2 lx W
SAJ-2 85-22 18A D-11 1
AC 1
SK SA 0
FC RO 8.n34 RF N.22 Ar no 8.N.3-2 epen tx as 8.n. M nW-22 188 C-11 1
AC 1
SK SA 0
FC R0 8.n.3-2 RF WW-22 Ar RD 8.N.3-2 tx W
B.n.3 2 EW-22 18C D-.11 1
AC 1
SK SA 0
FC R0 8.n.3-2 RF WW-22 Ar as 8.n.3-2 epen tx up 8.n. w av.22 18D E-11 1
AC 1
SK SA 0
FC RO 8.n.3-2 RF NV-2Tt Ar WS 8.n.3 2 tx W
8.n.3-2 nW-22 19A K-11 1
AC 1
SK SA 0
FC R0 8.n.3-2 RF WW-22 Ar M
S.M.3-2 tx no 8.Ja.3-2 nW-22 198 J-11 1
AC 1
SK SA 0
FC RO 8.N.3-2 RF WW-22 Ar as 8.n.3-2 even tx W
8.n.3-2 mu2 20A K-11 1
AC 1
SK SA 0
FC RO 8.n.3-2 RF E5-22 AP MO 8.M.3-2 Open tx as 8.n.3 2 nW-22 208 J-11 1
AC 1
SK SA 0
FC RO 8.N.3-2 RF WW-22 Ar WW 8.n.3-2 Spen tx M
6,n.3-2 EW-22 8.I.1.1 Rev. O Page 160 of 171
Tmt.E BEENIE VRLVE TESTEE FmRam ISI rn Mt 1, 2. 3 NB IE VALVES.
PILMIM IWCLEM FWIER STATIST P&ID: N-252 5Y5798: IM1EM WetuR (261)
Valve Pt.ID ISI Valve Valve Val v,+
Actuator Normal Test Test Pers Proc.
Test Relief Number Coor Class Cat Size Twee Twee Position Rout.
Frea nagter DigggMon Reensest IIstes ZIA K-11 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF W-22 AP WO 8.M.3-2 Open Lx Re 8.M.3-Z W-22 21B L-il 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF NY-ZZ AP N0 8.N.3-2 Spen tx as 8.n.3-2 W-22 22A K-11 1
AC 1
SK SA 0
FC R0 8.R.3-2 RF NEM AP ES 8.N.3-2 u
no 8.n. M W-22 22B t-11 1
AC 1
SK SA 0
FC R0 8.M.3-2 RF W-2Z e
no 8.w.3-2 spe.
AC 1
SK SA 0
FC RO S.M.3 2 RF W-2Z AP ES 8.M.3-2 Lx as 8.n.3-2 av-az 67B E-3 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF EV-22 AP 30 8.M.3-2 u
as 8.n 3-2 av-22 m
67C E-3 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF WW-2Z AP se 8.n. n spen tx as 8.n. M au-22 67D E-3 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF EW-2Z AP se 8.n.3-2 epen tx so 8.n.3-2 av-22 67E D-3 1
AC 1
SK SA 0
FC RO 8.N.3-2 RF WW-22 Ar ao 8.n.3-2 spen Lx W
8.n.3-2 W-22 67F 0-3 1
AC 1
SK SA 0
FC RO 8.M. M RF RW-22 AP no 8.n.3-2 eye.
tx as 8.n.3-2 au-22 67G D-3 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF WW-22 AP R0 8.M.3-2 Open tx no 8.n.3-2 W-22 67h D-3 1
AC 1
SK SA 0
FC R0 8.N.3-2 RF EW-22 AP We 8.M.3-2 Lx no 8.w.3-2 W-22 8.I.1.7 Rev. O Page 161 of 171
Teti BHENIE 1mLW 1ESTEE M 151 QAS51, 2, 3 ABB E WW.W5 -
FILEMn smarwas pWER STAHW PEle: 5 252 SYSTEN: muersm gggtER (251)
Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test FW5 Proc.
Test Relief Number Coor Class Cat Size Twee Twee Position Reust.
Free Enter M eetties Re====t Notes 89A t-3 1
AC 1
SK SA 0
FC RO s.n.3-2 RF N-22 e
ne s.n.3-z open tx as s.n.3-2 w-;tZ 89B N3 1
AC 1
SK SA 0
FC RO s.n.3 RF E%22 e
as s.n. n spen tx ne s.n.s 2 uw22 110A N3 1
AC 1
SK SA 0
FC RO s.n.3-2 RF WW2Z w
as s.n.3 2 epen tx ne s.n.3-z asa 1108 J-11 1
AC 1
SK SA 0
FC RO s.n.3-2 RF N-22 w
as s.n.3-z span tx as s.n.3-z um 139 43 1
AC 1
SK SA e
FC Re s.n.3-2*
K' NO22 PEC-M e
AG s.n.3-2*
Corrently tx as s,n.3 am Imamurative __
I i
8.I.1.1 Rev. O Page 162 of 171 l
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Time INSERVICE 1RLVE TESTEIE PEMMfDI ISI CutSS 1. 2. 3 Am IE inLVE5 PILMIM M PSER STATIM PSIB: M-253 SMEET 1 of 2 SY51DI: M FM ESElfR DESSEL P&ID: f4-253 SEET 2 of 2 N MEWI(253)
Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test PIPS Proc.
Test Relief Nywber Copr Class Cat Me Type Type Position Rget.
Freo _leumber Di_ryr. lion Request Notes 2-ISA F-6 i
AC 1
SK SA 0
FC RO 8.M.3-2 RF NY-22 (SH.1)
8.M.3-2 EE 22 2-15B F-3 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF M
(SH.1)
AP NS 8.M.3-2 LX W
8.M.3-2 W-22 2-17A E-6 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF M
(SH.1)
AP R3 8.M.3-2 LX as 8.M.3-2 Ev-22 2-178 E-3 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF W-22 (SH.1)
AP RS 8.M.3-2 Lx as 8.M.3-2 E5-22 2-19A E-6 1
AC 1
SK SA 0
FC R0 8.M.3-2 RF WW-22 (SH.1)
AP RS 8.M.3-2 LX RS 8.M.3-2 EU,22 2-196 E-3 1
AC 1
SK SA 0
FC RO 8.M.3 2 RF W-22 (SH.1)
8.M.3-2 H
2-20A E-6 i
AC 1
SK SA 0
FC RO 8.M.3 2 RF W-22 (SH.2)
AP RS 8.M.3-2 Spen tx as 8.M.3-2 EU.a 2-208 D-6 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF W -22 (SH.2)
AP RS 8.M.3-2 Spen LX NB 8.M.3-2 EU-22 2-23A E-6 i
AC 1
SK SA 0
FC RO 8.P.3-2 RF WW-22 (SH.2)
8.M.3-2 E5-22 2-238 E-6 i
AC 1
SK SA 0
FC RO 8.M.3 2 RF EW-22 (SH.2)
AP RD 8.M.3-2 Spen 4
LX RO 8 J.3-2 R1-22 2-25 C-7 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RW22 1
(SH.2)
AP EO 8.M.3-2 LX se 8.M.3-2 EV-22 i
8.I.1.1 Rev. O Page 164 of 171
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TMLE IM5ENVIE vuR.WE TESTBE PROERAN ISI CUtSS 1. 2. 3 m IE MuR.vES PILERIM M CLEAR PWaR STATISI PEID: M-253 SDEET 1 of 2 5T57D8: MCLEAR BOILM WFWE P&ID: M-253 SIEET 2 of 2 N AT M (253)
Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test FIPS Proc.
Test Relief Nvmber Coqr. Class __ lat Size Type Tvoe Position Reet.
Free Member Direction Reevest Notes 55 B-7 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 (SH.2)
AP RO 8.M.3-2 Open tx RS 8.M.3-2 E5-22 57 B-7 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF EW-22 (SH.2)
AP RO 8.M.3-2 tx as 8.M.3-2 av-22 59 B-7 1
AC 1
SK SA 0
FC R0 8.M.3-2 RF RW.ZE (SH.2)
M EG 8.M.3-2 Spen tx as 8.M.3-2 av-22 67 B-7 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RW-22 (SH.2)
8.M.3-2 55J2 63 B-7 1
AC 1
SK SA 0
FC R0 8.M. M RF WW-22 (SH.2)
AP RS 8.M.3-2 tx as 8.M.3-2 av-22 65 B-7 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF WW.22 (SH.2)
AP RS 8.M.3-2 l
tx as 8.M. w av-22 67 A-7 1
AC 1
SK SA 0
FC R0 8.M.3-2 RF WW-22 j
(SH.2)
AP RS 8.M.3-2 LX as 8.M 3-2 au-22 69 A-7 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF EW-22 (SH.2)
AP WS 8.M.3-2 tx M
8.M.3 2 Ev-22 71 A-7 1
AC 1
SK SA 0
FC R0 8.M.3-2 RF WM (SH.2)
AP 20 8.M.3-2 tx as 8.M.3-2 av-22 73 A-7 I
AC 1
SK SA 0
FC RO 8.M.3-2 RF EU.22 (SH.2)
AP HS 8.M.3-2 Spen LX R0 8.M.3-2 E5-22 75 A-7 1
AC 1
SK SA 0
FC RO 8.M.3-2 RF RV-22 (SH.2)
AP E9 8.M.3-2 Spen tx no 8.!s.3-2 av-22 8.I.1.1 Rev. O Page 166 of 171
TietE MENTIEVKEE N m ISI CUISS 1. 2. 3 JES IK 1RLEES PILEMR IWERDR FRER STATIGE P&ID: N-253 3 BEET 1 of 2 Sv5 FBI: amrnsaur gets WEsmL Pain: N-253 3 BEET 2 of 2 BENEBENFAFEWI (M3)
Valve P&ID ISI Valve Valve Valve Actuator
- Normal Test Test Firs Proc.
Test Relief ta etter Coor Class Cat Size Twee Twee Position Rest.
Free Muser Si @ Roemest notes u
77 A-7 i
AC 1
Rv-22 4
(SH.2)
LX W
S.N.3 2 3542 79 E-4 1
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SK SA 0
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M ES 8.N.3 2 LX M
8.N.3-2 E542 81 E-4 1
AC 1
SK SA G
FC RO 8.N.3 RF EU-22 (SH.2)
AP EB 8.N.3-2 tx as s.N.a-2 av 22 83 E-6 1
AC 1
SK SA 0
FC RO G.N.3-2 RF EW-22 (5H.1)
AP N0 8.N.3-2 lx M
m_m_ M EU-22 90 E-4 1
AC 1
SK SA 0
FC R0 8.N.3-2 RF WW-22 (SH.2)
AP RS 8.N.3-2 tx as 8.N.3-2 au-22 92 D-4 1
AC 1
SK SA 0
FC RO 8.N.3-2 RF WW-22 (SH.2)
AP BS 8.N.3-2 lx M
8.N.3-2 '
EE.22 8.I.1.1 Rev. O Page 167 of 171 w
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TABLE-INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2. 3 Al@ MC VALVES PILGRIM NUCLEAR POWER STATION MIQ-1-5 (VENDOR DRAWING)
SYSTEM: TRAVERSE INCORE PROBE (45)
P&ID:
Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Mr5 Proc.
Test Relief Mr Coor Class Cat Size Twee Twee Position Rant.
Frea Direction Recuest Notes 300A 2
A 0.25 K
SO 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
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 3008 2
A 0.25 K
S0 C
FE Q
8.7.4.3 (Ball 8)
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 300C 2
A 0.25 K
50 C
FE Q
8.7.4.3 (F.all 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 3000 2
t.
0.25 K
S0 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 3.7.1.5 LJ 2Y 8.7.1.5 N Check 2
FC R0 8.7.1.5 RF RW-45 2
LJ 2Y 8.7.1.5 301A
(% ear A1 2
0 0.25 SH EP O
EX 10Y 3.N.2-5.6.P 3018
(% ear 81 2
0 0.25 SH EP O
EX 10Y 3.M.2-5.6.P 301C i% ear C1 2
0 0.25 SH EP O
EX 10Y 3.N.2-5.6.P 301D
{$ hear D) 2 0
0.25 SH EP O
EX 10Y 3.N 2-5.6.P 8.I.1.1 Rev O Page 170 of 171 L.
_._.1___
_.._m,
.~
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INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND MC VALVES -
PILGRIM NUCLEAR POWER STATION P&ID: M-294 SYSTEM: STAND 8Y GAS TREATMENT SYSTEM (48) i Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Mr5 Proc.
Test Relief Number Coor Class Cat Size Twee Twee Positior Rest.
Free Euder Directies Reemest Notes N99 F-4 2
8 29 K
AS C
FE q
8.7.2. W ST 8.7.2. W 9/C Fs 9
8.7.2.ie*
e n
zy 9,12.W N196 8-6 2
8 29 K
AS C
FE 9
8.7.2.19*
ST 4
8.7.2. W S/C F5 9
8.7.2.19*
C-Pt 27 a.7.2. W Nies F-2 2
8 29 K
AS C
FE g
8.7.2. W ST 4
8.7.2. W S/C Ts t
8.7.2.ie-e Pt 27 S.7.2 W N112 9-2 2
8 20 K
AS C
FE 9
8.7.2. W ST 4
8.7.2.19*
S/C FS q
8.7.2. W C
Pt 27 8.7.2. W 8185 E-2 2
D 8
M SA C
M M
M<
Run-Testdie I.
- 8. I.1.1.
Rev. O Page 171 of 171 a- -.
-..n...
[9)
COLD SHUTDOWI 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) i VALVES:
1001-29A, 1001-29B, 1400-25A.'1400-25B, 2301-8, 1301-49 CATEGORY:
A g
l CLASS:
1 L
FUNCTION:
These valv'es provide pressure isolation from the high pressure reactor coolant system.
TEST REQUIREMENTS:
INV-3411; Test Frequency - Exercise at least once every three months.
[
INV-3413; Power operated valves - full stroke time.
BASIS _EDB 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 operation results in a loss of one isolation barrier.
Exercising these motor operated valves quarterly with the Reactor Vessel at pressure significantly increases the occurrence probabilities of an intersystem loss of coolant accident.
ALIERNATE TESTING:
Exercise valves during cold shutdown.
l 8.I.1.1 Rev. O Page 59 of 171
[10)
COLD SHUTDOWI JUSTIFICATION CS-10 l
SYSTDI:
Residual Heat Removal System (1001)
VALVE:
64 C&TEEIRY:
AC CLASS:
1 l
BRICIl0ll:
This valve provides pressure isolation and a flowpath for head i
spray (RNR) and fire water emergency source water.
TEST REQUIREMENT:
IW-3521; Test Frequency - exercise at least once every i
three unnths, quarterly.
BASIS FOR This normally closed check valve provides reactor coolant JUSTIFICATION:
pressure isolation to protect against overpressurization and an increased occurrence of an intersystem loss of coolant accident. Also, the head spray line untor operator valve receives a reactor high pressure isolation signal (less than 100 psig) Isolating the head spray flowpath. This check valve will be forward flow exercised to verify the open direction during cold shutdown.
ALIERNATE TESTING:
Exercise valve during cold shutdown ('A' RNR loop shutdown cooling) not to exceed refueling outage.
4 6
8.I.1.1 Rev. O Page 60 of 171
[11]
00LD SW1DOW JUSTIFICATION CS-11 SYSTEM:
Reactor Core Isolation Cooling System (1301)
I VALVE:
9067 C&ILGQRY:
C i
CLASS:
2 FUNCTION:
This valve provides a vent path to relieve a vacuum created within
- r the RCIC exhaust line after turbine operation.
TEST REQUIREMENT:
INV-3521; Test Frequency - exercise at least once every three months.
MSISl0B 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
+
n 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.
T 8.I.1.1 Rev. O Page 61 of 171
[12]
00LD SHUTDOMI JUSTIFICATION CS-12 SYSTEN:
Nuclear Boiler - SRV Vacuum Relief (261)
VALVES:
96A, 968, 96C, 97A, 978, 97C, 970, 98A, 988, 98C, 980 CAIEEIRY:
C.
l CLASS:
NC i
BBCTION:
Vacuum breakers ensure that pressure is equaltred for the main steam safety relief discharge lines.
TEST REQUIREMENT:
IW-3521; Test frequency - exercise at least once every r
three months, quarterly.
l BASIS _ EOR The SRV suppression pool discharge vacuum breakers JUSIlf1CAII0ff:
provide a means for relieving the vacuum developed in 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 unsuitable 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 l
during cold shutdown when the drywell is deinerted.
ALTERNATE TESTINS:
Exercise valves during cold shutdown (when drywell is deinerted) not to exceed a refueling outage.
i l
8.I.1.1 Rev. O Page 62 of 171 i
L
[13)
COLD SNU1 DOM JUSTIFICATION CS-13 SYSTEM:
huclear Boiler - Compressed Air (31) y& LYES:
372A, 372B, 372C, 372D CATEGORY:
AC CL&SS:
NC FUNCTION:
These valves provide isolation and allow recharging of the ADS air j
TEST REQUIREMENT:-
INV-3521; Test Frequency - exercise at least once every three months, quarterly.
BASIS FOR These check valves with their associated air 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-valves will be performed during cold shutdown when the i
drywell is deinerted.
ALTERNATE TESTING:
Exercise valves during cold shutdown (when drywell is deinerted) not to exceed a refueling outage.
i 8.I.1.1 Rev. O Page 63 of 171
o
[
[14]
COLD SHUTDOM JUSTIFICATION CS-14 S151Iti:
Salt Service Water System (29)
VALVES:
3801, 3805 CATEGORY:
B CLASS:
3 FUNCTION:
These valves control emling water flow from the Turbine Building Closed Cooling Water p&,H) heat exchanger, and therefore, the amount of cooling avall ele 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 RE0Q1REMENTS:
INV-3411; Test Frequency - exercise at least once every three months.
IWV-3413; Power operated valves - full stroke time.
jlASILEQR Since critical power generattor equipment such as the JUSilf1C&Il0!!:
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 possible plant scram from generator protective functions.
ALTERNATE TESTING:
Partial stroking of valves quarterly.
Exercise valves during cold shutdown.
8.I.1.1 Rev. O Page 64 of 171
j (153 00LD SHU1110001 JUSTIFICATION CS-15 SYSTEN:
High Pressure Coolant Injection System (2301)
VALVE:
218 CATEEIRY:
AC QASS:
2 FUNCTION:
The NPCI exhaust drain pot containment isolation check valve allows 4 drain path for condensate between the exhaust Ilne check valves.
TEST REQUIREMENT:
IW-3521; Test Frequency - exercise at least once every three months, quarterly.
i MSIS_E0B The NPCI Exhaust Drain Pot Line Check Valve shall be 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 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 NPCI turbine for safety reasons.
This will make HPCI inoperable during preparation, testing and restoration of this system.
Exercising is to be performed during cold shutdown.
ALTERNATE TESTING:
Exercise during cold shutdown.
3 t
8.I.1.1 Rev. O Page 65 of 171
~. -.
[16]
00LD SHUTD0601 JUSTIFICATION CS-16 SYSTDI:
High Pressure Coolant Injection System (2301)
YALYi:
76 CATEEIRY:
C CLASS:
2 l
i FUNCTIQH:
The HPCI Gland Seal Condenser Pump Discharge Check Valve allows a flowpath for condensate from the GSC to the NPCI booster pump suction.
TEST.RE@lREMENT:
INV-3521; Test Frequency - exercise at least once every three months, quarterly.
MSIS_f08 The HPCI GSC Puup Discharge Check Valve shall be forward JUSTIFICATIOff:
flow exercised. This normally closed check valve is vertfled in the open direction during performance of the GSC pump cold shutdown operability test. To establish a temporary hydraulic circuit for pump testing, the HPCI System must be made inoperable for an extended period of time (approx. 8 hrs). Exercising is to be performed i
during cold shutdown.
ALTERNATE TESTING:
Exercise during cold shutdown.
l l'
L 8.I.1.1 Rev. O Page 66 of 171
.l 6.4 RELIEF REQUESTS Valve Relief Requests (RV) are provided for conditions in which E
compliance to ASME Code,Section XI, Subsection IWV, 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.
l
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i t
i l
i i
i t
i l
l l
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8.I.1.1 Rev. O Page 67 of 171 I
r (1)
RELIEF REQUEST RV-01 I'
SYSIEM:
Reactor Building Closed Cooling Hater System (30)
VALVE:
432 CATEGORY:
AC CLASS:
2 FUNCTION:
This. valve provides isolation to drywell components by RBCCW..The components would require isolation for primary containnent criteria and maintenance.
TEST REOUIREMENT:
INV-3521; Test frequency - exercise at least once every three months, quarterly.
Bails 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.
ALTERNATE TESTING:
Exercise valve at least once every two years.
l 8.I.1.1 Rev. O Page 68 of 171 e
i t
[2T RELIEF REQUEST RV-02 j
L SYSTEM:
Compressed Air System (31)
VALVE:
167 i
i CATEGORY:
AC i
i CLASS:
2 EQHCTION:
This valve is the nitrogen / instrument air to drywell inboard isolation valve for primary containment isolation.
TEST REQUIREMENT:
INV-3521; Test frequency - exercise at least once every i
three months, quarterly.
BASIS FOR RELIEF:
This check valve is the inbcard primary containment 1 solation 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 TEEllHG:
Exercise valve at least once every two years.
b I
i 8.I.1.1 Rev. O Page 69 of 171 l
i i
[3]
RELIEF REQUEST RV 03 SYSTEM:
Containment Atmosphere Control System (45)
VALVES:
X-201A X-201E X-201J X-201B X-201F X-201K X-201C X-201G
-201H X-201D X
CATEGORY:
)
CLASS:
2 FUNCTION:
These valves are the pressure suppression chamber to drywell vacuum breaker valves which equaltre the pressure betwaen the two volumes when the suppression chamber pressure exceeds the drywell pressure.
4 TEST REOUIREMENTS:
INV-3420; Valve Leak Rate Test.
IW-3300: Valve Position Indicator Verification, valve with remote position indicators shall be observed at least once every 2 years to verify that valve operation is accurately indicated.
BASIS FOR RELIEF:
A specific maximum leakage per valve is not applicable to the vacuum breaker valve testing. A gross leakage (go/no go) pressure decay test is performed on the pressure suppression chamber atmosphere in accordance with PNPS Technical Specification on a quarterly basis.
The IW-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 presture suppression chamber atmosphere in accordance with PNPS Technical Specification on a refueling outage basis.
These vacuum breakers are located inside the suppression chamber and have a unique design which allows remote exercising using a testable pneumatic actuator. Their design includes a position indicator and annunciator circuitry to verify that the disk moves freely off the seat. Each refueling outage these vacune breakers are manually exercised and visually checked. At this time, the position indication is verified. Single personnel access (Drywell/ Torus Deinerting) must be available for performance of these test requirements. The position indicator verification shall be scheduled in conjunction to minimize safety hazards and ALARA.
l ALTERNATE TESTING:
Valve leak rate test requirements shall be demonstrated in accordance with PNPS Technical Specification.
Valve position indication verification shall be performed each refueling outage.
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8.I.1.1 Rev. O Page 70 of 171
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[4]
RELIEF REQUEST RV-04 l-SYSTEMS:
All Applicable VALVES:
All Applicable CATEGORIES: A,B CLASSES:
All Applicable J
FUNCTION:
Not Applicable c.,
' TEST REOUIREMENT:
INV-3417(a) Corrective Action i
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 a
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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8.I.1.1 Rey, o Page 71 of 171
[5]
RELIEF REQUEST RV-05 SYSTEM:
Transverse Incore Probe System (45)
VALVE:
N2 Purge Supply Check CATEGORY:
AC CLA15:
2 FUNCTION:
This valve. serves as the outboard primary containment isolation valve for the TIP purge system.
TEST REOUIREMENT:
INV-3521; Test frequency - exercise at least once every three months, quarterly.
BASIS FOR RELIEF:
This check valve is the 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.
ALTERNATE TESTING:
Exercise valve at least once every two years.
i 8.I.1.1 Rev. O Page 72 of 171
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[6]
RELIEF REQUEST RV-06 SYSTEM:
Core Spray System (1400)
' VALVES:
9A, 9B CATEGORY:
AC-CMSS:
.1 EUNCTION:
These valves are the Core Spray Injection Pressure Isolation Check Valves.
TEST REOUIREMENT:
INV-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 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 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 water 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 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 will require reactor vessel level control out of the normal parameter and a bleed ano 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. 0 1
Page 73 of 171
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[7]
RELIEF REQUEST RV SYSTEM:.
High Pressure Coolant Injection System (2301)
VALVE:
24-(formerly.HO-2)
CATEGORY:
B CLASS:
2 FUNCTION:
Thi High Pressure Coolant Injection (NPCI) 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.
BASIS 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 i
in the closed position upon a-trip of the HPCI turbine.
i Therefore, the throttle valve timing is variable and will be verified by acceptable HPCI pump and operability testing.
J 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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i 8.I.1.1 Rev. O Page 74 of 171
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[8L RELIEF REQUEST RV-08.
LSYSTEM:
Standby Liquid Control System (1101)
I VALVES:.
15, 16
. CATEGORIES: C, A/C 1
CLASS:
1
[ UNCTION:
These valves are the SLC injection check valves.
.IEST REOUIREMENT:
INV-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 dominera11 zed water requires a lengthy flushing-operation to remove boron from the system. Even after extensive flushing, boron remains present in system dead l
1egs. Some of this boron propagates into the reactor' vessel during injection and 1s-difficult to remove from L
the system. The presente of boron 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.
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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l 8.1.1.1 Rev. O Page 75 of 171
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[9T RELIEF REQUEST RV-09 l
SYSTEM:
Control Rod Drive Hydraulic System (302) j 1 VALVES:
114, 115, 126, 127 (typical of 145 each)
)
CATEGORIES:. B, C CLASS:
2 FUNCTION:.
These valves are the CRD Discharge Header Check, Accumulator Supply Check, Scram Inlet and Outlet Valves.
TEST REOUIREMENTS:
IHV-3411; Test frequency - exercise at-least once every three months.
IHV-3413; Power operated valves - full stroke time.
INV-3415; Fail safe - at least once every three months.
INV-3521; Test frequency - exercise at least once every-three months.
BASIS FOR RELIEF:
These valves (with the exception of the 115) operate coincidentally to rapidly insert control rods. Valve-will be tested by SCRAM timing control rod drives ^
accordance with Technical Specification Section 4.
This requires testing _of at least 10f, of the drivt every 120' days. Additionally,1001, of the drives at -
l tested during each shutdown that is greater than 120-days in duration.
Timing of the SCRAM fun: tion will be substituted for individual valve times, i
The Accumulator Supply Check Valves (115) will be I
verified as forward flow exercised by observing that their respective CRD accumulator fault lights clear following restoration from scram time testing.
ALTERNATE TESTING:
SCRAM function timing will be substituted for individual valve exercising.
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8.I.l.1 Rev. O Page 76 of 171
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[10I RELIEFRhQUESTRV-10 SYSTEM:
Control Rod Drive Hydraulic System (302)
VALVES:
138 (typical of 145)-
. CATEGORY:
C CLASS:
2 1
FUNCTION:-
These valves are the CRD cooling water check valves.
TEST REOUIREMENT:
IHV-3521; Test Frequency-exercise at least once every three months.
BASIS FOR RELIEF:
Failure of.these valves to reverse flow exercise would be identified by applying; 1) a notch-out signal which would result in a CRD double-notch, or 2) a notch-in signal which would result in a CRD non-notch.
Each partially or fully withdrawn operable control rod shall 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.
8.I.l.1 Rev. O Page 77 of 171
'[11]
RELIEF REQUEST RV-Il l
S.Y.SI.B:
Nuclear Boiler - Main Steam Isol., ADS & Safety Relief System (203)
- VALVES:
3A, 3B, 3C, 3D.
CATEGORY:
AC CLASS:
1 FUNCTION:
The functions of the reactor relief valves are:
(1) epen upon receipt of an auto depressurization signal to blow down reactor (2) act as a primary system relief valve 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.
L IHV-3413; Power operated valves - full stroke time, l-IHV-3415; Fall safe - at least once every three months.
BASIS FOR RELIEF:
Relief is requested fro'n the Section XI required testing frequency of once every three months.
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 as specified in Technical Specification.
Relief is requested from the stroke timing requirements of Section XI.
It is impractical to measure stroke 1.
times for relief and solenoid valves since the stroke.
times are on the order of 100 ms.
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 resulted in the following outstanding concern:
Operating the SRV at low operating pressure (150 psi) probably 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 into the seat fracturing carbides at the surface.
This gives corrosion more area (crevices) to adhere to, increasing sticking potential.
The exact pressure where this would not occur is not known but 500 psi appears acceptable.
The reason the valves are cycled is to insure they operate and are not stuck.
8.I.1.1 Rev. O Page 78 of 171
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-[11)
' RELIEF REQUEST RV-11 (Continued)
-Because of the outstanding-finding, PNPS intends to operate the relief valves at the higher reactor pressure
-between 350 and 500 psi.
ALTERNATE' TESTING:.
Exercise 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.1.1 Rev. O Page 79 of 171
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(12)
RELIEF REQUEST RV l SYSTEM:.
1 Nuclear' Boiler - Feedwater System (6) val,VES ': -
'58A, 58B, 62A, 62B CATEGORY:
AC CLASS:
1 FUNCTION:
These valves serve as the feedwater inlet check valves.
TEST REOUIREMENT:
INV-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.
8.I.l.1 Rev. O Page 80 of 171
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[
[131 RELIEF REQUEST RV-13 SYSTEM:
Recirculation Pump-Seal Water System (201)
F VALVES:
13A, 13B, 17A, 17B CATEGORY:
AC CLASS:.
2 FUNCTION:
These valves serve as'the recirculation pump seal water-inboard and outboard containment isolation check valves.
TEST REOUIREMENT:
IHV-3521; Test Frequency - exercise'at least once every y.
three months.
BASIS FOR RELIEF:
These check valves are the primary containment isolation valves for'a system considered inservice during plant operation and functionally non-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.
ALTERNATE TESTING:
Exercise valves at least once every two years.
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8.I.1.1 Rev. O Page 81 of 171
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'[143 RE' LIEF REQUEST RV-14 SYSTEM:-
Salt Service Hater System (29)
VALVES:
3915, 3925 l
CATEGORY:
B lc C]. ASS:
3
- FUNCTION:
These valves isolate the service water system from the screen wash system when LOCA occurs.
TEST REOUIREMENT:
INV-3412; Power operated valves - full stroke time.
SASIS FOR RELIEF:
When the screen wash pumps _are turned off, these valves receive a signal to close.
There are no position
' indicator' lights to shot < 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.
ALTERNATE TESTING:
Valves stroke times shall not be measured.
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8.I.l.1 Rev. O Page 82 of 171
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[15]
RELIEF REQUEST RV-15 e
, SYSTEM':
Diesel 011 Transfer System (38)
VALVES:
4521,.4522 CATEGORY:
B-CLASS:
HC
' FUNCTION:
These valves open automatically upon initiation of the diesel oil-transfer pumps to allow oil to flow into the day tank.
. TEST REOUIREMENT:
INV-3412; Power operated valves - full stroke time.
y.
BASIS 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.
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Page 83 of 171 l
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[16)'
RELIEF REQUEST RV-16 SYSTEM:
Reactor Core Isolation Cool!.ag System (1301)
YALVIS: -
2
- CATEGORY
B.
CL&ES:
2 FUNCTION:
-The Reactor Core Isolation Cooling' Turbine Governor Valve regulates steam to the RCIC turbine in response to changes in'RCIC Pump Flowrate.
3 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 i
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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8.I.1.1 Rev. O Page 84 of 171 l
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_[17)
RELIEF REQUEST RV-17
- SYSIEll
Control Rod Drive Hydraulic System (302)
VALVES:
120,121,122,123 (Typical of 145)
CATEGORY:
B-CLASS:
2
-)
FUNCTION:
' Direct Control Rod Drive (CRD) for the insertion and withdrawal of control rods.
TEST REQUIREMENTS:
INV-3411; Test Frequency - exercise at least once every three months.
IW-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.
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1 8.I.l.1 Rev. O Page 85 of 171
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[18]
RELIEF REQUEST RV-18 LSYSTEM:.
Nuclear Boller - Compressed Air (31)
VALVES:
84A, 84B, 84C, 84D, 85A, 85B, 85C, 850 l CATEGORY:
C CLASS:
NC FUNCTION:
These valves allow charging of the HSIV accumulators, i
TEST REOUIREMENT:-
IWV-3522(b); Normal Close Valves - exercise procedure, f
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 (forward flow exercise) would impede the normal opening function of the MSIV.
Therefore, proper MSIV i
-full-stroke exercise verifies the respective air accumulator check valve forward flow exercise.
5 ALTERNATE TESTING:
Verify forward flow exercising by MSIV full-stroke valve cycle _ testing.
8.I.1.1 Rev. O Page 86 of 171
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[19T REL'IEF REQUEST RV-19 1
SYSTEMS:
Diesel 1 Generator Air Start System (47)
Diesel Generator Turbo Air System;(47)
- VALVES
4586A, 4586B~ 4587A, 45878,-4588A, 4588B, 4589A, 4589B 4569A, 4569B, 4570A, 4570B CATEGORY:
B-CLASS:
' NC l
EUNCIl08:
These air start solenoid valves provide starting air to the emergency diesel generator.
r TEST REOUIREMENTS:
IHV-3411; Test Frequency - exercise at least once every three months.
IHV-3413;-Power operated valves - full stroke time.
IHV-3415; Fall safe - at least once every three months, t
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 svalve to close will cause starting air to not secure, r
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.
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l 8.I.l.1 Rev. O Page 87 of 171 l
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[20]-
RELIEF REQUEST RV-20 m
' SYSTEM:
Residual Heat Removal' System (1001) l Core Spray System (1400)
J VALVES:
1001-362B, 363A 1400-212A, 212B CATEGORY:
C
. CLASS:
2 FUNCTIO.N:
These check valves supply the flowpath for.keepfill pressurization and makeup.
I
-TEST REOUIREMENT:
INV-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 partia11y 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.
ALTERNATE TESTING:
Partial exercise valves quarterly and verify a full l
forward flow exercise during each refueling outage.:
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8.I.1.1 Rev. O Page 88 of 171
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(21]
RELIEF REQUEST RV-21 SYSTEM:.
Reactor Mater Cleanup System (1201) i VALVE:
81 CATEGDRY:
C.
CLASS:
1-EUllCII0ll:
-This valve provides the path for RNCU return flow to the reactor vessel.
TEST REQUIREMENT:
INV-3521; Test Frequency - exercise at least once every three months.
B& SIS FOR RELIEF:
The reactor water cleanup return check valve shall be
-reversed flow exercised. This normally open check valve' i
it vertfled in the closed direction by; isolating the RNCU return header, pressurizing the feedwater header, and venting the piping on the upstream side of this check valve to verify restricted flow. Controlled i
pressurization of the feedwater header to perform this l
test occurs during the Class 1 System Leakage Pressure Test or Hydrodynamic Testing of the RCIC Pressure Isolation Valves each refueling outage.
L ALTERNATE TESTING:
Exercise valve during each refueling outage.
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8.I.1.1 Rev. O Page 89 of 171 i
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a j
[22F RELIEF REQUEST RV-22:
3
(
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p SYSTEMS:
Core Spray System (1400)'
High Pressure Coolant Injection System (2301)
~ Reactor Core'Isolatic<n Cooling System (1301);
i-Reactor Water Cleanup System (1201)
J Recirculation-Pump Instrumentation (262) a L
Nuclear Boller Instrumentation-(261)
Nuclear Boller Instrumentation (263)
VALVES:
A11_' Applicable -
3 CATEGORY:-
AC CLASS:-
1 l
FUNCTION:
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.
INV-3422; Frequency - test'sha11 be conducted at least 1
once every 2 years.
BASIS FOR RELIEF:
'These excess flow check valves are the primary r
containment isolation valves for systems considered inservice during-plant' operation. These normally open 1
-instrument isolation check valves require a reverse flow J
' exercise.
Leak testing (per ASME Code) performs valve exercising.in the closed direction each refueling-outage.
L 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 testing is conducted during this system leakage pressure test.
ALTERNATE TESTING:
Exercise and leak rate valves during each refueling outage.
8.I.1.1 Rev. O Page 90 of 171 7
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[23)
RELIEF REQUEST RV-23 SYSTEM:-
Diesel Oil Transfer System (38)
L; 1 YALVISi.
116A 1168 L
CATEGDRY:
C
[
CLASS:
NC l.
IUKII0ll:.
These valves provide the supply path for diesel fuel oil for running the Emergency Site Diesel Generators.
TEST REQUIREMENT:
INV-3522; Check Valve Full Flow Exercising -- exercise at least once every three months.
t MSIS_ EOR 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.
l~
Inadequate supply of fuel oil would cause the diesel' load handling capabilities to be-lupaired during sbrveillance testing. Therefore, proper operation of each emergency diesel generator during run testing verifles the check valve forward flow exercise.
ALTERNATE TESTING:
Emergency diesel operability testing will verify check valve forward flow exercise.
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8.I.l.1 Rev. O Page 91 of 171 l
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[24]
RELIEF REWEST RV-24 SYSTEM:-
Residual Heat Removal System (1001)
VALVES:
63, 64 T
CATEEIRIES: A, AC 1
CLASS:
1 FUNCTION:
These valves provide pressure and containment isolation between
.the reactor coolant pressure boundary and the low pressure head spray line.-
TEST REWIREMENT:
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 MO-63 valve.also performs a containment isolation 1
function (10CFR Appendix J).
Pressure isolation (LP) leak testing of these valves requires removal of head
. spray (Class 1) piping for installation of a blank flange.
Installation of this flange is normally performed in conjunction with removal of the-drywell head and opening of the of reactor pressure vessel each refueling outage. Pressure isolation leak rate testing for these valves will be performed during this refueling workscope.
j ALTERNATE TESTING:
' Valve pressure isolation (LP) leak rate test' requirements shall be demonstrated in accordance with INV-3420 during each refueling outage.
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8.I.1.1 Rev. O Page 92 of 171 l
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[253-RELIEF REQUEST RV-25 p
SYSTEM:
High Pressure Coolant Injection System (2301)
VALVES:
9068A, 90688-fATEGORIES: A L
CLASS:
2 FUNCTION:
The HPCI exhaust drain pot isolation valves receive an isolation upon HPCI trip and perform a containment. isolation function.
IESI_ REQUIREMENT:
IW-3413; Power operated valves - full stroke time.
BASIS FOR RELIEF:
These valves are equipped with common position indicators; therefore, stroke times cannot be obtained, l
. 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.
8.I.l.1 Rev. O Page 93 of 171
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[26)
RELIEF REQUEST RV-26 1.
1 SYSTEM:
Control Rod Drive Hydraulic System (302)
L VALVES:
21A, 218,'22A, 228, 23A, 238. 24A, 24B b'
j CATEGORY:
B r
L Q.8SS:
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 REQUIREMENT:
INV-3413; Power operated valves - full stroke time (closed)
L BASIS FOR RELLEE:
These air operated valves are stroked closed' quarterly L
using a separate testing air vent (bleed) circuit.
Stroke times using the test circuit are erratic and can i
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 I
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 degradation. Valve open stroke times are measured and trended quarterly to l
monitor for valve degradation.
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.
l 8.I.1.1 Rev. O Page 94 of 171
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[27)
. RELIEF REQUEST RV-27 SYSTEM:'
As Applicable VALVES:
- As App 11 cable C&lEEIRY:
AC and C CLASS:
1,2,3 and NC FUNCTION:
All check valves whose ability to fully open can not be verified without disassembly.
TEST REQUIREMENT:
INV-3521; Test Frequency - Exercise at least once every
'l three montN.
BASIS FOR RELIEE:
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 l
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 L
program as long as the alternate testing guidelines are_
J h
followed.
ALIERNAIEJESIING:
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 l
L consist of more than 4 valves, however, all valves i
within each group must be disassembled within a maximum of 4 refueling outages.
The sample disassembly and inspection program involves 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 (manufacturer, size, model number, and materials of construction) and have the same service 1
l conditions including valve orientation. During each disassembly, the licensee will verify that the J
disassembled valve is capable of full-stroking (through i
manual exercise) and that the internals of the valve are structurally sound (no loose or corroded parts).
l 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 4
same outage. Once this is completed, the sequence of disassembly will be repeated unless extension of the l'
interval can be justified.
1 8.I.l.1 Rev. 0 Page 95 of ill
1 c
[28)
RELIEF REQUEST RV-28 SYSTEM:
As Applicable VALVES:
Containment Isolation Valves CATEGORY:
AC and C-CLASS:
I and 2 BBCIl0ll:
These valves provide the primary containment isolation barriers to minimize the consequences of an accident.
TEST REQUIREMENT:
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 50f,or greater, the test frequency shall be doubled.
l MSIS 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.
L Misapplication of trended data will result in increased test frequency which places unjustifiable operational constraints upon the plant by requiring extended l
shutdowns. Also, testing on an increased frequency with-L questionable basis increases radiation exposure for L
testing personnel inconsistent with PNPS'ALARA I
practices. Presently testing 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 conducted based on_ unjustifiable operational constraints and ALARA considerations. This position is supported within Generic Letter No. 89-04.
ALTERNATE TESTING:
Containment isolation valves will be replaced or L
repaired as determined by the licensee or when the l~
leakage rate exceeds that as stated in PNPS Tech Specs or INA-3427(a).
8.I.l.1 Rev. O Page 96 of 171
'3)
(,
-(29)'
RELIEF REQUEST RV-2g SYSTEM:
As Applicable VALVES:
As Applicable C& TEE)RY:
-A, B and AC CLASS:
1, 2, 3 and NC j
-l 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 25% or more from i
the previous test for valves wtth full-stroke times greater than 10 seconds or 50% or more for valves with full-stroke times less than or equal to 10 seconds is a
observed, test frequency shall bes increased to once each-month until Corrective Action is taken.
BASIS FOR RELIEF:
Historical stroke time data reveals that establishing an increased test frequency based on a 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'is the preferred method for establishing a reasonable test Acceptance Criteria.
For POVs (excluding motor operated), recording of fast stroke times (with reference times between 1 and 5 seconds) can-result in deviations greater than 501 (e.g., human error, rounding off practices, normal stroke deviation, and actuator source fluctuation) above the reference stroke time without significant valve-degradation. The=e deviations may occur even though stroke times are iecorded to within the nearest tenth of a second (which is far more restrictive than INV). The increased frequency testing requirement for these valves (as stated below) will account for this condition to minimize unnecessary Corrective Action and excessive valve cycling.
8LTERNATE TESTING:
Valve stroke times shall be compared against a reference stroke time for INV 3417(a) Corrective Action determination. POVs (excluding motor operated) stroke times must deviate by greater than [1.5 x reference time plus one half second) for times between 1 and 5 seconds before increased testing of monthly is required.
8.I.l.1 Rev. O Page 97 of 171
1
[303 RELIEF RE@EST RV-30
- SYSIDtS
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 boundarles are inclusive of numerous components /1tems-(i.e.,
- valves, piping, fittings, accumulators and appurtenances) and therefore. the entire boundary must comply with a specific leakage limit.
TEST REWIREMENT:
INV-3420; Valve Leak Rate Test
}
i 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.
ALTERNATE TESTING:
Perform Pressure Drop (Decay) Tests in lieu of INV-3420 i
Valve Leak Rate Tests, utilizing a pressure boundary specified leakage-limit.
L 8.I.l.1 Rev. 0 l
Page 98 of 171 b
o l
1
i
[31]
RELIEF REQUEST RV-31 l
SYSTEM:
H /02 Analyzer System (5065) 2 VALVES:
5117A, 51178, 5137A, 5137B 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.
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 L
During system testing, placing the analyzer function l'
selector switch to the zero position (i.e., flowpeter l:
shows a downward deflection) and then to the span position (i.e., floumeter shows an upscale movement with i-alarm actuation) indicates that the valves have properly L
cycled.-
ALTERNATE TESTING:
Valve stroke times shall not be measured.
p L
l 1
i l
8.I.1.1 Rev. O Page 99 of 171 L
q 1
4'
.6.5-VALVE' PROGRAM TABLE l
o This table identifies the, scope of valves within=the ISTP and allows.
l
- cross-referencing specific valve test requirements to their
. implementing-station procedure.
3 g
(1) Valve Test Index F
SYitta -
Ekl0 Revision EA.gt.
Salt Service Hater (29)
M-212 E20 102 Reactor Building Closed Cooling M-215 E24 104 Hater (30)
Diesel Generator-Air Start System (47)
M-219 ES:
106 Compressed Air (31)
M-220 108 Sh 1 of 2 E24 Diesel Oil Transfer (38)
M-223 E5 109 Containment Atmosphere Control
. M-227 110 (45 & 9)
Sh 1 of 2 E28 Sh 2 of 2-E13 Compressed Air (31)
M-227 118 Sh 1"of 2 E28 Nitrogen Supply (9)
M-227
'119 Sh 2 of 2 E13 Radwaste Collection (20)
H-232 E12 120 Post Accident Sampling & Hydrogen M-239 121 i
And Oxygen Analyzer System (5065)
Sh 1 of 3 E8 Sh 2 of 3 E7 Residual Heat. Removal System (1001)
M-241 129 Sh 1 of 3 E32 Sh 2 of 3 E17 Core Spray System (1400)
M-242 E16 136 l
1.
High Pressure Coolant Injection M-243 138 L,
(2301)
Sh 1 EIS M-244 p.
Sh 2 E13 Reactor Core Cooling System (1301)
M-245 142 Sh 1 E13 M-246 Sh 2 E12 1
8.I.1.1 Rev. 0 l
Page 100 of 171 1
1 6.5 VALVES TESTED (Continued)
I' System EklD Revision EAge i
Reactor Water Cleanup System (1201)
M-247 E22 146
.j
[
Standby Liquid Control System (1101)
M-249 E12 147 Control Rod Drive Hydraulic M-250 148 System (302)
Sh 1 of 2 E18 Sh 2 of 2 E5 i
L Recirc Pump Instrumentation (262)
M-251 E4 151 Feedwater System (6)
M-252 E17 152 g
Reactor Recirculation System (202)
H-252 E17 153 Main Steam Isol. ADS & Safety M-252 E17 154 Relief (203)
Nuclear Boiler System (220)
M-252 E17 157 Compressed Air (31)
M-252 E17 158 Nuclear Boiler (261)
M-252 E17 160 Nuclear Boiler Vessel H-253 164 Instrumentation (263)
Sh I of 2 E17 Sh 2 of 2 E12 Diesel Generator Turbo Air Assist M-259 E0 168 System (47)
Traverse Incore Probe (45)
MIQ-1-5 El 170 Standby Gas Treatment System (48)
M-294 E11 171 HQ.TE The drawing revision level will require changing if:
1)
The revision affects information within the program table DE 2)
A formal review of the program is performed against the latest revision.
8.I.1.1 Rev. O Page 101 of 171
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TABLE INSERVICE VALVC TESTING PW6ERAM ISI CLASS 1, 2, 3 AfD NC VALVES PILGRIM NUCLEAR POWER STATION i
P&ID: M-212 SYSTEM:' SALT SERVICE MATER (29)
Valve P&ID ISI Valve Valve Valve Actuator Morsel Test
. Test R FS Proc.
Test Relief
@r Coor Clas?
Cat Size Twee Twee Position Rest.
Free W Meestige Re-t Nets AV-A C-7 3
C 2
m SA C
PC 8.5.3.2 -
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Ggeef Emertise AW-E C-5 3
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PC
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FF EU 27 Msessemble To M
M 8.5.3.2 G emed rm ine B.I.1.1 Rev. O Page 193 of 171
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B 12 GA M0 C
FE Q
8.5.3. M ST Q
8.5.3.M 0
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CS-08 foote 1 PI 2Y 8.I.11.13 Isote 1: ISwn core flow free recirculation pump operation is met required.
l l
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8.I.T.1 Rev. 0 l
Page 105 of 171
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Test Relief Number Coor Class Cat Size Twee Twee Position Reet.
Free IW Wirectiem Re-t IIetes 4586A H-4 IIC B
1.5 GA 50 C
FE Q
8.9.1*
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1.5 GA 50 C
FE Q
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EU-19 ST Q
NA-EU-19 FS O-8.9.1*
C EW-19 4587A E-4 NC B
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FE Q
8.9.1*
EU-19 ST Q
NA EU-19 FS O
8.9.1*
C EU-19 4587B E-4 IIC B
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FE.
Q 8.9.1*
EW-19 ST Q
NA EW-19 FS 0
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EU-19 4588A E-4 IIC B
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RW-19 ST Q
MA WW-19 FS O
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FE Q
8.9.1*
WW-19 ST Q
NA HV-19 FS O
8.9.1*
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1.5 GA 50 C
FE Q
8.9.1*
EU-19 ST Q
NA E5-19 FS O
8.9.1*
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1.5 GA 50 C
FE Q
8.9.1*
EU-19 ST Q
NA EU-19 FS 0
8.9.1*
C EU-19 i
L
. 8.I.T.1 Rev. 0 Page 107 of 171
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D TASLE
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INSERVICE valve TESTING Mt0 GRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM MJCLEAR POWER STATION P&ID: M-227 SHEET 1 of 2 SYSTEM: CONTAIfSOff ATMOSPHERE CONTROL P&ID: M-227 SHEET 2 of 2 SYSTEM NUPSERS 45 & 9 Valve P&ID ISI Valve Valve Valve Actinator Moraal Test Test Fir 5 Proc.
Test Relief
!v aber Coor Class Cat Size Tuse Tvoe Position Rest.
Free. Ander Directies Reevest IIstas v
102 C-6 2
A 1
GL MA C
E NA NA Passive (Menval)
(451 (SH.1)
LJ 2Y 8.7.1.5 103 C-6 2
A 1
GL MA C
FE NA NA Passive (Manual)
(451 (SH.11 LJ ZY 8.7.1.5 104 C-6 2
A 1
GL MA C
E NA NA Passive (Menval)
(451 (SH.1)
LJ 2Y 8.7.1.5 105 C-6 2
A 1
GL MA C
E NA NA Passive (Menval)
(45)
(SH.11 L3 2Y 8.7.1.5 106 E-5 2
A 4
GA MA C
E NA NA Passive (Monval)
(45)
(SH.1)
LJ 2Y 8.'t.1.5 X-201A C-7 2
FC Q
8.A.1 FF (45)
(SH.1)
(Testable)
8.A.2*
E543 X-201B C-7 2
FC Q
8.A.1 FF (45)
(SH.1)
(Testable)
PI EB 8.7.1.F EW43 LX M
8.A.2*
EE43 X-201C C-7 2
FC Q
8.A.1 FP (45)
(SH.1)
(Testable)
PI M
8.7.1.F NE43 LX M
8.A.2*
E543 X-201D C-7 2
FC Q
8.A.1 FF (45) (SH.1)
(Testable)
PI M
8.7.1.F EU.43 LX M
8.A.2*
EE43 X-201E C-7 2
FC Q
8.A.1 FF (45) (SH.1)
(Testable)
PI EB 8.7.1.F E543 LX ES 8.A.2*
M i
8.I.1.1 Rev. O Page 110 of 171
y._
TABLE
..{
INSERVICE VALVE TESTING PR8 GRAM ISI CLASS 1, 2. 3 AM NC VALVES PILGRIM WUCLEAR P0tER STATION P&ID: M-227 SHEET 1 of 2 SYSTEM: CtBITAIISGIT ATMOSPMDIE CONT 90L P&ID: 5227 SHEET 2 of 2 SYSTEM HUPEDt3 45 & 9 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test FIPS Proc.
Test Relief tepu6er Cngr Class Cat size Tm Twee Position Rest.
Free Mugher DLryClies Reguest Mstes X-201F C-7 2
FC Q
8.A.1 FF j
(45) (SH.1)
(Testable)
PI M
8.7.1.9*
WW-43 LX M
S A Z*
EE43 X-201G C-7 2
FC Q
8.A.1 FF (45)
(SH.1)
(Testable)
PI N
8.7.1.9*
WW-43 LX M
8.A.2*
EU-83 X-201H C-7 2
FC Q
8.A.1 FF (45)
(SH.1)
(Testable)
PI N
8.7.1.9*
W-43 LX M
8.A.2*
EU-43 X-201J C-7 2
ft Q
8.A.1 FF (45)
(SH.1)
(Testable)
PI M
8.7.1.9*
EE43 LX M
8.A.2*
EE-83 X-201K C-7 2
FC Q
8.A.1 FF (45)
(SH.1)
(Testable)
PI M
8.7.1.9*
W-43 LX M
8.A.2*
EU-43 X-212A A-8 2
FC Q
8.7.4.9 FF (45)
(SH.1)
PI ZY 8.7.1.5 LJ 2Y 8.7.1.5 EW4 X-2128 A-7 2
FC Q
8.7.4.9 FF (45)
(SH.1)
PI ZY 8.7.1.5 1
LJ 2Y 8.7.1.5 55 3 8.I.T.1 Rev. O Page 111 of 171
.~
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR P0t!ER STATION P&ID: M-227 SHEET 1 of 2 SYSTEM: CONTAINNENT ATMOSPNERE CONTROL P&ID: M-227 SHEET 2 of 2 SYSTEM NUMBERS 45 & 9 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Hr5 Proc.
Test Relief Number Cogr Clais Cat Size Tuse Twee Position Rest.
Free Musher Dits;11gm Reagest Notes 5825 E-8 2
A 8
BF A0 C
FE M
M Passive (45)
(SH.1)
ST M-M (Se-Enerf red) i T5 m
m PI m
M LJ 27 8.7.1.5 8V-i23 5033A D-7 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 50338 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 2Y 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 ZY 8.7.1.5 LJ 2Y 8.7.1.5 EV-28 5035B E-2 2
A 8
BF A0 C
FE Q
8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 C
l FS Q
8.7.4.2 C
PI ZY 8.7.1.5 LJ 2Y 8.7,1.3 RV-RS 8.I.1.1 Rev. O Page 112 of 171
._.. __.._..=_,_______ _ _._
TABLE:
INSERVICE VALVE TESTING PROGRMt ISI CLASS 1, 2. 3 AfW NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-227 SHEET 1 of 2 SYSTEM: CONTAIIGENT ATMOSPHERE CONT 90L
-P&ID: N 227 SHEET 2 of 2 SYSTEM NUpWERS 45 & 9
~
Yalve P&ID ISI Valve Valve Val ve Actuator Normal Test Test NFS Proc.
Test Relief Nymber Coor Class Cat Size Twee Tvoe Position Rest.
Free Euder Direction _ Respost lenies 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 ZY 8.7.1.5 LJ 2Y 8.7.1.5 EM 5036B 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 WM 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 6
50408 B-7 2
A 20 BF AO C
FE Q
8.7.4.9 (45)
(SH.1)
ST Q
8.7.4.9 O/C FS Q
S.7.4.9 0
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 EUL2B 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 50418 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 8.I.1.1 Rev. O Page 113 of 171
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2. 3 M S NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-227 SHEET 1 of 2.
SYSTEM: CONTAINNENT ATMOSPNERE CONTROL P&ID: M-227 SHEET 2 of 2 SYSTEM NUpWERS 45 & 9 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test M r5 Proc.
Test Relief N r6er Cgor Class _ _ Cat Size Twee Tvoe Position Rout.
Free Sumher Sing 11em Regyuest Notes J
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 2Y 8.7.1.5 LJ 2Y 8.7.1.5 8W-28 5042B 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 2Y 8.7.1.5 LJ 2Y 8.7.1.5 H
5043A E-7 2
A 2
GL A0 C
FE Q
8.7.4.2 (45)
(SH.1)
ST Q
8.*.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 85 28 5044B 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 SV-28 8.I.1.1 Rev. O
.Page 114 of 171
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: CONTAIISIENT ATNOSPHERE CONTROL P&ID: M-227 SHEET 2 of 2 SYSTEM NUPOERS 45 & 9 Valve P&ID ISI Valve Valve Valve Actuater Normal Test Test PWS Proc.
Test Relief Number Coor Clan.... Cat Size Type... Type Position Rest.
Free number Direction Reggest Not_es..._
5081A G-6 2
A 1
GA 50 C
FE Q
8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 C
WW-84 FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 5081B G-6 2
A 1
GA 50 C
FE Q
8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 C
WW-84 FS Q
8.7.4.2 C
PI ZY 8.7.1.5 LJ ZY 8.7.1.5 5082A G-6 2
A 1
GA 50 C
FE Q
8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 C
WW-44 FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 5082B G-6 2
A 1
GA 50 C
FE Q
8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 C
WW-84 FS Q
8.7.4.2 C
PI ZY 8.7.1.5 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 C
WW-04 l
FS Q.
8.7.4.2 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 50838 G-7 2
A 1
GA 50 C
FE Q
8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 C
WW.44 FS Q
8.7.4.2 C
l PI ZY 8.7.1.5 LJ 2Y 8.7.1.5 8.I.1.1 Rev. O I
Page 115 of 171 l
l -
c.-
TABLE'
. INSERVICE VALVE TESTIlfG PROGUM ISI CLASS 1, 2, 3 AIS NC VALVES PILGRIM MUCLEAR POWER STATIOit
'P&ID: N227 SHEET 1 of 2 SYSTEM: C(pffAIIWetT ATMOSPHERE CONTROL P&ID: N227 SHEET 2 of 2 SYSTEM NUPWERS 45 & 9 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test PIFS Proc.
Test Relief Nys6er C.oor Class Cat Size Twee Twee Position Rest.
Free Bundsor 91r_gstige Reeuest Notes 5084A N7 2
A 1
GA SO C
FE Q
8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 C
WW-84 FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 U
2Y 8.7.1.5 50848 N7 2
A 1
GA 50 C
-Q 8.7.4.2 (45)
(SH.1)
ST Q
8.7.4.2 C
E5-44 FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 U
ZY 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 C
45-44 FS Q
8.7.4.2 C
PI ZY 8.7.1.5 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 C
WW-04 FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 U
2Y 8.7.1.5 5086A E-7 2
A 1
GA 50 C
FE Q
8.7.4.2 (9)
(SH.2)
ST Q
8.7.4.2 C
E5-64 FS Q
8.7.4.2 C
PI ZY 8.7.1.5 U
2Y 8.7.1.5 50868 D-7 2
A 1
GA 50 C
FE Q
8.7.4.2 (9)
(SH.2)
ST Q
8.7.4.2 C
EW-44 FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 LJ 2Y SJ.L5 8.I.1.1 Rev. O Page 116 of 171
~.
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TASLE 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: CONTAIIeqENT ATMOSPHERE C8NTROL P&ID: M-227 SHEET 2 of'2 SYSTEM NUpWERS 45 & 9 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test PIPS Proc.
Test Relief Le aber Coor Cla33__ Cat Size Twee Twee.
Position Rout.
Free Muuher Digglign Request Notes v
5087A E-8 2
A 1
GA 50 C
FE Q
8.7.4.2 (9)
(SH.2)
ST Q
8.7.4.2 C
RE44 FS Q
8.7.4.2 C
PI ZY 8.7.1.5 LJ 2Y 8.7.1.5 5087B D-8 2
A 1
GA 50 C
FE Q
8.7.4.2 (9)
(SH.2)
ST Q
3.7.4.2 C
EE44 FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 '
5088A E-7 2
A 1
GA 50 C
FE Q
5.7.4.2 (9)
(SH.2)
ST Q
8.7.4.2 C
EW-44 FS Q
8.7.4.2 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 50888 D-7 2
A 1
GA 50 C
FE Q
8.7.4.2 (9)
(SH.2)
ST Q
8.7.4.2 C
E544 FS Q
8.7.4.2 C
PI ZY 8.7.1.5 LJ 2Y 8.7.1.5 8.I.1.1 Rev. O Page 117 of.171
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t e T3 s e 4Y QY e r 2
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t t I
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L n
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C r s oo M P ro taue t e c w A
A A T S
S e
v e l
e a w K
K VT C
C e
v e l
z ai 1
1 VS e
v l t a a C
C 2
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A fo s
2 s
I a T
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7 6
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i' C D
D 5
f er v e 0
1 D
l b 4
4 I
a m 3
3 E
V u P
N
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TABLE INSUtVICE VALVE TESTING PROGRNt ISI CLASS 1, 2. 3 N e NC VALVES PILGRIM MJCLEAR POWER STATI(NI
~ P&ID: M-232 SYSTDt:- RA0unSTE COLLECTION (29) l l
Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test fir $ Proc.
Test Relief j
I!ymber Coor Class Cat size Twee Twee Posi tion Ramt.
Free Amster Direction Reemest' Hetes 7011A G-6 2
A 2
K A0 C
FE Q
8.7.4.3 ST Q
8.7.4.3-C FS Q-8.7.4.3 C
PI ZY 8.7.1.5 l
LJ 2Y 8.7.1.5 70118 G-6 2
A 2
K 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 7017A D-6 2
A 2
K 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 70178 D-6 2
A 2
K 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 8.1.1.1 Rev. O Page 120 of 171-
_..._,m
TA8t r-INSERVICE VALVE i n TING PROGRAM ISI CLASS 1,.2. 3 AfD NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-239 SHEET 1 of 3 SYSTEM: ' POST ACCIDENT SAMPLING & Hg+O2 P&ID: M-239 SHEET 2 of 3 ANALYZER SYSTEM (5065)
Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test PIr5 Proc.
Test Relief Number Coor C_1. ass Cat Size Twee Tvoe Position Rout.
Free iluser Directism Reevest Neles _
11A B-6 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
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 13B B-3 2
A 1
GL 50 0
FE Q
8.7.4.1 (SH.1)
ST Q
8.7.4.1*
S/C -
RV-04 FS Q
8.7.4.1 C
PI 2Y 8.7.1.5 LJ ZY 8.7.1.5 14A B-6 2
A 1
GL 50 0
FE.
Q 8.7.4.1 (SH.1)
ST Q
8.7.4.1*
S/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 50 C
FE Q
8.7.4.1 (SH.1)
ST Q
8.7.4.1*
t/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 50 C
FE Q
8.7.4.1 (SH.1)
ST Q
8.7.4.1*
S/C RV-04 FS Q
8.7.4.1 C
PI 2Y 8.7.1.5 LJ ZY 8.7.1.5 208 B-4 2
A 1
GL SO O
FE Q
8.7.4.1 (SH.1)
ST Q
8.7.4.1*
WC RV-44 FS Q~
8.7.4.1-
-C PI ZY 8.7.1.5 LJ 2Y 8.7.1.5 8.I.1.1 Rev. O Page 121 of 171
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AfW NC VALVES PILGRIM MELEAR POWER STATION P&ID: 95-239 SHEET 1 of 3 SYSTEM: POST ACCIDDIT SAMPLING & H2+02 P&ID: M-239 SHEET 2 of 3 ANALY2ER SYSTEM (5065)
Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test FtrS Proc.
Test Relief CI ss Cat Size Twee Twoe Position Rest.
Free Muster Directies Reguest Notes Ngatter (por A
21A B-6 2
A 1
GL SO O
FE Q
8.7.4.1 (SH.1)
ST Q
8.7.4.1*
WC RV-04 FS Q
8.7.4.1 C
PI 2Y 8.7.T.5 LJ 2Y 8.7.1.5 22B B-4 2
A 1
GL S0 C
FE Q
8.7.4.1 (SH.1)
ST Q
8.7.4.1*
WC RV-04 FS Q
8.7.4.1 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 24A B-6 2
A 1
GL SO O
FE Q
8.7.4.1 (SH.1)
ST Q
8.7.4.1*
WC RV-04 FS Q
8.7.4.1 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 25B B-4 2
A 1
GL SO
'C FE Q
8.7.4.1 (SH.1)
ST Q
8.7.4.1*
WC RV-04 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 50 C
FE O
8.7.4.1 (SH.1)
ST Q
8.7.4.1*
WC RV-04 FS Q
8.7.4.1 C
PI 2Y 8.7.1.5 LJ 2Y 8.7.1.5 27B B-3 2
A 1
GA 50 C
FE Q
8.7.4.1 (SH.1)
ST Q
8.7.4.1*
WC RV-04 FS Q
8.7.4.1 C
PI ZY 8.7.1.5 LJ 2Y 6.7.1.5 8.I.1.1 Rev. O Page 122 of 171
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