ML20153B106

Rev 1B to Inservice Testing Program for Pumps & Valves, Pilgrim Nuclear Power Station

ML20153B106
Person / Time
Site:	Pilgrim
Issue date:	03/14/1988
From:	Bellefeuille J, Hutton S, Sabina J BOSTON EDISON CO.
To:
Shared Package
ML20153B077	List: BECO-88-048, Forwards Rev 1B to Inservice Testing Program for Pumps & Valves,Second Ten Yr Interval,Pilgrim Nuclear Power Station ML20153B106
References
PROC-880314, NUDOCS 8803210382
Download: ML20153B106 (133)

Text

=

-INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES

. PILGRIM NUCLEAR POWER STATION REVISION No. IB Original Submittal Prepared By:

Nutech Engineers Chicago-Revision Prepared By:

BOSTON EDISON COMPANY Prepared by:

t Principal Consultant D epared by:

Reviewed by:

lb '

m b

J($.pabina

~

/ Belleffuille Sehior ASME Test Engineer SS & PG/ Leader

' Approved y:

Approved By:

/

f(

GA Ls

'R.J / Barrett 3(4. Seery/

Nuclear Operations Manager T4chnical Manager 8803210382 880314 PDR ADOCK 05000293 P-DCD l

TABLE OF CONTENTS l

P.Aga

1.0 INTRODUCTION

1-1 2.0 INSERVICE TESTING PROGRAM FOR PUMPS 2-1 2.1 General Info *mation 2-1 2.1.1 Applicable Coda 2-1 2.1.2 Pump Program Table Description 2-1 2.1.3 "Inservice Test Quantities" Columns 2-1 2.1.4 Measurement of Inservice Test Quantities 2-1 2.1.5 Allowable Ranges of Test Quantities 2-2 2.1.6 Bearing Lubricant 2-2 2.1.7 Instrument Accuracy 2-2 2.1.8 Exempt Pumps Hithin Systems Classified for ISI 2-2 2.2 Reilef Requests for Inservice Pump Testing Program 2-3 2.3 Inservice Pump Testing Program Table 2-13 3.0 INSERVICE TESTING PROGRAM FOR VALVES 3-1 3.1 General Information I-l 3.1.1 Applicable Code 3-1 3.1.2 Valve Program Table 3-1 3.1.3 Measurement of Test Quantities 3-3 3.1.4 Allowable Ranges of Test Quantities 3-3 3.1.5 Instrument Accuracy 3-4 Table Inservice Valve Tests 3-5 Table Test Frequency 3-7 3.2 Relief Requests for Inservice Valve Testing Program 3-9 3.3 Inservice Valve Testing Program Table 3-60 i

j

1.0 INTRODUCTION

Revision 18 of the Inservice Testing Program for Pumps and Valves -

Pilgrim Nuclear Power Station will be in effect from issuance date, covering through December 7, 1992 and supersedes Revision 1A. The period of time this revision of the program is effective represents a portion of the second 120 month (10 year) inspection interval.

This program will 'oe updated prior to the start of the third inspection interval in accordance with the requirements of 10CFR50.55a(g).

The program contained herein outlines the Inservice Testing (IST) requirements for Pilgrim Nuclear Power Station.

This program is based on the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Hinter 1980 Addenda.

All references to IHP or IHV in this document correspond to Subsection IHP or IHV of ASME Section XI,1980 Edition through the Hinter 1980 Addenda.

This IST program was developed using the ISI classification boundaries and the following documents:

Title 10, Code of Federal Regulations, Chapter 50.55a(g).

NRC Regulatory Guides Division 1.

Standard Review Plan 3.9.6, "Inservice Testing of Pumps and Valves".

Division 1 (Draft) Regulatory Guide and Value/ Impact Statement, "Identification of Valves for Inclusion in Inservice Test Programs".

"NRC Staff Guidance for Preparing Pump and Valve Testing Programs and Associated Relief Request" November 1978.

Final Safety Analysis Report, Pilgrim Nuclear Power Station.

Technical Specifications, Pilgrim Nuclear Pcwer Station.

The inservice tests identified in this program will verify the operational readiness of pumps and valves whose functions are required to mitigate the consequences of an accident or to bring the reactor to a cold shutdown condition or maintain the reactor in a safe shutdown condition. Additional valves considered to have a safety significant function may be incorporated. The IST classification of each pump and valve matches the ISI classification indicated on the P& ids with one exception, pumps and valves in the IST program which are not within the ISI classification boundaries are indicated as non-classed (NC).

Revision IB l-1

-. ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _. _. _ _ _ _ _ _ _ _ _ _. _ _ _ _. _ _ _ _ _

4 2.0 INSERVICE TESTING PROGRAM FOR PUMPS 2.1 General Information 2.1.1 Applicable Code This Inservice Testing Program for ISI Class 1, 2, 3 and NC Pumps meets the requirements of Subsection IHP of Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Hinter 1980 Addenda. Where these requirements are determined to be impractical, specific requests for relief have been written and included in Section 2.2.

2.1.2 Pump Program Table Description The table in Section 2.3 lists all pumps included in the Pilgrim Nuclear Power Station IST Program. 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:

SYSTEM:

System Title PUMP NUMBER:

Pump Identification Number CLASS:

ISI Classification E&lQ:

PNPS drawing number CQQR: Coordinate location on the P&ID SPEED. INLET PRES. DIFF PRES. FLOW RATE. VIBRATION and BEARING IEMP:

Inservice Test Quantities to be measured in accordance with Table IHP-3100-1 TEST INTERVAL: The frequency of;IST as prescribed in IWP-3400 2.1.3 "Inservice Test Quantities" Columns PUMP SPEED. IJLET (SUCTION) PRESSURE. DIFFERENTIAL PRESSURE (dP). FLOH-RATE. VIBRATION. BEARING TEMPERATURE AND LUBRICANT LEVEL OR PRESSURE:

When the symbol "Y" appears in a particular measured parameter celumn, that quantity will be measured during inservice testing in accordance -

with Subsection IHP. Requests for relief are identified with the letters "RP" under the measured parameter column in the test table.

The requests for relief are included in Section 2.2.

2.1.4 Measurement of Inservice Test Quantities Speed:

Per IHP-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 IHP-3100.

Revision IB 2-1

Inlet Pressure:

For submerged pumps, inlet pressure will be calculated (using appropriate correction factors) from a measured tank cr basin level. All other inlet pressure measurements will be taken using pressure instruments at or near the pump inlet.

Differential Pressure:

Differential pressure measurements will be calculated from inlet and discharge pressure measurements or by direct differential pressure measurement.

Flow Rate: Pump discharge flow rate shall be measured.

Vibration: Pump vibration will be measured as close as possible to the inboard bearing, in a plane approximately 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 measurement will be taken with one of the instruments referenced in IHP-4520, with exception if a reading is not applicable for a pump.

Bearina Temoerature:

Pump bearing temperature (s) will not be I

measured (See RP-2).

2.1.5 Allowable Ranges of Test Quantities The allowable ranges specified in table IHP-3100-2 will be used for differential pressure, flow and vibration measurements except as discussed. Should a measured test quantity fall outside the allowable range, the possibility of defining an expanded allowable range, per ASME Code Interpretation XI-1-79-19, will be investigated for operability.

2.1.6 Bearing Lubricant As specified in Table IHP-3100-1, the pump bearing lubricant level, pressure, or flow will be observed during insarvice testing.

2.1.7 Instrument Accuracy Allowable instrument accuracies are given in table IHP-4110-1.

If the accuracies of plant installed instrumentation is not acceptable temporary instruments meeting the acceptable accuracies will be used.

2.1.8 Exempt Pumps Hithin Systems Classified For ISI 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 consequences of an accident, nor are they provided with an emergency power source.

Revision 18 2-2

SECTION 2.2 RELIEF REQUESTS FOR INSERVICE PUMP TESTING PROGRAM l

l l

l l

l l

l l

l f

Revision 18 2-3

RELIEF REQUEST RP-1 PUMPS:

P-202A, P-2028, P-202C, P-202D, P-202E, P-202F SYSTEM: Reactor Building Closed Cooling Water CLASS:

3 FUNCTION:

Emergency Equipment Cooling TEST RE0VIREMENTS:

Table INP-3100-1, Inservice Test Quantitles; Measure pump flow rate.

Table INP-3100-2, Allowable Ranges of Test Quantities; dP high values.

BASIS FOR RELIEF:

Instrumentation is not installed to measure flow rate.

Redesign of the system would be necessary to install flow instrumentation or to utilize portable flow instrumentation. There is no method available to control the flow rates 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 and Required Action Range) shall be monitored and corrective action (INP-3230) taken.

Additionally, piping configuration does not permit installatioa of flow orifices on the pump discharge piping that would be const tent 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.

ALTERNATE TESTING:

Heasure pump shutoff head quarterly with corrective action being taken for low allowable range only.

i 1

i i

i I

Revision IB 2-4

RELIEF REQUEST RP-2 PUMPS: P-141A.

P-202D P-203C P-207B P-208E P-1418 P-202E P-203D P-208A P-215A P-202A-P-202F P-205 P-208B P-2158 P-202B P-203A P-206 P-208C P-202C P-203B P-207A P-208D SYSTEMS:

As Applicable CLASSES:

2, 3 or NC FUNCTIONS:

As applicable.

. TEST REOUIREMENT:

1HP-4310, Bearings - temperature of all centrifugal pump bearings outside the main flow path 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 prior to entering a cooler, shall be considered the bearing temperature.

Table IMP-3100-1, Inservice Test Quantities - Bearing Temperature Tb.

Table INP-3100-2, Allowable Ranges of Test Quantitles -

Tb { Note (2)}. Note (2) Tb shall be.within the limits specified by the Owner in the record of tests (INP-6000).

l.

BASIS FOK RELIEF:

(a)

Some pumps are cooled by their respective process fluid, "Main Flow Path." Thus, bearing temperature measurements would be highly dependent on the temperature of the cooling medium.

(b)

Pump bearing temperature is taken at one (1) year intervals, only, which provides very little data toward determining the incremental degredation of a bearing, or provide any meaningful trend data.

(c)

All pumps will be subject to vibration measurements per Subsection INP-4500. Vibration meaturements (displacement or 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. The owner will establish an alert condition (exceeding 0.314 in/sec) for each pump that shall require further investigation utilizing spectrum analysis to determine bearing status.

Revision 18 2-5

RELIEF REQUEST RP-3 PUMPS:

P-207A, P-207f SYSTEM: Standby Liquio Control CMSS: 2 FUNCTION:

Provides a method of shutting down the reactor without use of the control rods.

TEST RE0VIREMENTS:

INP-3300 Scope of Test - measurement and observation of inlet pressure (P1) and differential pressure (dP) acros:, the pumps.

INP-3500, Duration of Tests - each pump shall be run at least 5 min. under conditions as stable as the system permits.

INP-4520(b), Instruments to Measure Amplitude - the frequency response range of the readout system shall be from one-half minimum speed to at least maximum pump shaft rotational speed.

BASIS FOR RELIEF:

The standby liquid control pumps are required to supply the necessary flow rate 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 pressure as the reference value.

Flow rate is measured, observed and monitored to verify pump operability and degradation.

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.

The SLC pumps are positive displacement with a shaft rotational speed of 360 revolutions per minute (RPM).

The amplitude frequency lower response rar.ge for 180 RPM corresponds to a frequency of 3 cycles per second (cps). The International Research and Development, (IRD) vibration instrument lower range is calibrated to 5 cps even though it measures the entire frequency l

spectrum. The lower frequency responses indicate l

structural induced problems. These induced inputs are l

adequately covered by the calibrated range.

Revision 18 2-6

ALTERNATE TESTING:

Utilize pump discharge pressure reading in lieu of pump differential pressure reading and verify test tank level to ensure adequate suction pressure. The pump shall be run for a duration to measure test p&rameters.

The IRD equipment shall only require calibration to as low practical (approximately 5 cps).

Revision 18 2-7

(

RELIEF REQUEST RP-4 PUMPS: 'P-208A, P-208B, P-208C, P-2080, 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

. pressure.

ALTERNATE TESTING:

Tide level will be used to calculate pump inlet pressure, and to specify inlet pressure for test purposes.

/

Revision IB 2-8

RELIEF REQUEST RP-5 PUMPS: P-208A, P-2088, P-208C, P-208D, P-208E SYSTEM: Salt Service Water CLASS: 3 FUNCTI0il:

Emergency Equipment Cooling TEST REOUIREMENTS:

Table IMP-3100-1, Inservice Test Quantities; Measure pump flow rate.

Table IMP-3100-2, Allowable Ranges of Test Quantities; dP High Values.

BASIS FOR RELIEF:

Instrumentation is not installed to measure individual pump flow rate.

Redesign of the system would be necessary to install flow instrumentation. Piping configuration 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 utilized with the rubber lined piping used in the salt service water system, also the pump discharge piping is underground.

The salt service water system is tested to demonstrate that sufficient cooling water flow can be delivered to the RBCCH heat exchangers to meet heat removal requirements.

There is no method available to control the flow rates of individual pumps.

Shut off head will provide a repeatable parameter for measuring pump performance.

Pumps are not run at shutoff for more than 60 seconds 4

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 (INP-3230) taken.

ALTERNATE TESTING:

Heasure pump shutoff head quarterly with corrective action be.ng taken for low allowable range only.

Revision IB 2-9

RELIEF REQUEST RP-6 PUMPS:

P-208A, P-208B, P-208C, P-2080, P-208E SYSTEM: Salt Service Water CLASS:

3 FUNCTION:

Emergency Equipment Cooling IEST REOUIREMENT:

INP-4510, Vibration Amplitude BASIS FOR RELIEF:

The pump casing is physically located under water therefore, inaccessible.

ALTERNATE TESTING:

Measure pump motor vibration at upper bearing using the Hydraulic Institute Standards for location guidance.

Revision IB 2-10

RELIEF REQUEST RP-7 RETRACTED i

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{

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Revision 18 2-11

_. _ -. ~. _. _ _ _

l RELIEF P.EQUEST RP-8 PUMPS: P-141A, P-141B SYSTEM: Diesel Fuel Oil Transfer CLASS: 3 FUNCTION:

The fuel oil transfer pumps maintain a sufficient operating level in the fuel oil day tank by transferri:q fuel oil from the fuel oil storage tank to the fuel oil day tank.

TEST REOUIREHENTS:

INP-4600 Flow measurement (accuracy), INP-3230(a) corrective action (alert range), and IMP-3230(b)

~

corrective action (action range).

R&S1$ FOR RELIEF:

One fuel oil transfer pump supplies each day tank. The capacity of a fuel transfer pump is approximately 28 gpa with the required design capacity for the Diesel Engine being 3.3 gpm. Flow rate will be measured with a survey flowmeter which has an accuracy of approximately 15%. The pump can meet the design function with as much as 50% degradation; therefore, relief from accuracy requirements and alert / action ranges adequately allows assessment of pump operability.

ALTERNATE TESTING:

Measurement of flow by survey flowmeter (approximately 15%) with corrective action ranges for flow shall be:

25% degradation clert range and 50% degradation action range.

Revision 18 2-12

SECTION 2.3 INSERVICE PUMP TESTING PROGRAM TABLE Revision IB 2-13

~

TABLE INSERVICE PUMP TESTING PROGRAM BOSTON EDISON COMPANY ISI CLASS 1. 2, 3 AND NC PUMPS PILGRIM NUCLEAR POWER STATION IST PROGRAM REVISION 18 2/3/88 INSERVICE TEST OUANTITIES l

lISI l

lP&IDl l

l INLET lDIFF.

l FLOW l

l LUBRICANT l BEARING SYSTEM I PUMP NO. I CLASS l P&ID I COOR.I FREQUENCY l SPEED (N) l PRESS. (Pil l PRESS. (Pd) 1 RATE (C)- 1 VISPATION (V)l LEVEL (L) ITEMP.(Tb)

SALT SERVICE lP-208A l

3 lM212 l B7 l Q

l NA l

RP-4 l RP-5 l

RP-5 l

RP-6 l

Y l

RP-2 WATER (SSW) lP-2088 l

3 lM212 l B8 l Q

l NA l

PP-4 l RP-5 l

RP-5 l

RP-6 l

Y l

RP-2 lP-208C l

3 lM212 l B7 l Q

l NA l

RP-4 l RP-5 l

RP-5

[

RF l Y

l RP-2 j

l P-208D l

3 lM212 l B6 l Q

l NA l

RP-4 l RP-5 l

RP-5 l

RP-6 l

Y l

RP-2 l P-208E I

3 i M212 l B5 1 0

I NA I

RP-4 l RP-5 l

RP-5 I

RP-6 Y

I RP-2 j

REACTOR BUILDING l P-202A l

3 lM215 l F3 l Q

l NA l

Y l

Y l

kP-1 l

Y l

Y l

RP-2 CLOSED COOLING lP-2028 l

3 lM215 l F3 l Q

l NA l

Y l

Y l

RP-1 l

Y l

Y l

RP-2 WATER (RBCCW) lP-202C l

3 lM215 l G3 l Q

l NA l

Y l

Y l

RP-1 l

7 l

Y l

RP-2 lP-2020 l

3 lM215 l G5 l Q

l NA l

Y l

Y l

RP-1 l

Y l

Y l

RP-2 lP-202E l

3 lM215 l G5 l Q

l NA l

Y l

Y l

RP-1 l

Y l

Y l

RP-2 l P-202F l

3 i M215 l F5 1 0

l NA 1

Y l

Y l

RP-1 I

Y I

Y l

RP-2 DIESEL FUEL OIL lP-141A l

3 l M223 l F6 l Q

l NA l

Y l

Y l

RP-8 l

Y l

NA l

RP-2 TRANSFER (DOT) l P-141B I

3 l M223 I E6 1 0

1 NA I

Y I

Y l

RP-8 I

Y I

NA I

RP-2 RESIDUAL HEAT lP-203A l

2 lM241(S2)l D6 l Q

l NA l

Y l

Y l

Y l

Y l

Y l

RP-2 REMOVAL (RHR) lP-203B l

2 lM241(52)l D3 l Q

l NA l

Y l

Y l

Y l

Y l

Y l

RP-2 lP-203C l

2 lM241(S2)l F6 l Q

l NA l

Y l

Y l

Y l

Y l

Y l

RP-2 1 P-203D l

2 IM241(S2)I F3 1 0

1 NA l

Y l

Y l

Y l

Y l

Y l

RP-2 CCIE SPRAY (CS) l P-215A l

2 lM242 l F7 l Q

l MA l

Y l

Y l

Y l

Y l

Y l

RP-2 I P-2158 1

2 1 M242 I F9 1 0

l NA l

Y l

Y l

Y I

Y l

Y l

RP-2 HIGH PRESSURE lP-205 l

2 lM244 l F9 l Q

l Y

l Y

l Y

l Y

l Y

l Y

l RP-2 COOLANTINJECTIONl l

l l

l l

l l

l l

l l

(HPCI) l l

l l

l l

l l

l l

l l

REACTOR CORE lP-206 l

2 l M246 l F8 l Q

l Y

l Y

l Y

l Y

l Y

l Y

l RP-2

)

ISOLATIONCOOLINGl l

l l

l l

l l

l l

l l

(RCIC) l l

l l

l l

l l

l l

l l

i STANDBY LIQUID lP-207A l

2 lM249 l E5 l Q

l NA l

RP-3 l

RP-3 l

Y l

Y l

Y l

RP-2 CONTROL (SBLC) l P-207B l

2 i M249 l F5 1 0

I NA I

RP-3 l

RP-3 l

Y I

Y l

Y l

RP-2 l

Rrvision 1B 2-14 J

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3.0 INSERVICE TESTING PROGRAM FOR VALVES 3.1 General Information 3.1.1 Applicable Code This Inservice Testing Program for ISI Class 1, 2, 3 and NC valves meets the requirements of Subsection IHV~of Section XI of the ASME Boller and Pressure Vessel Code,1980 Edition through the Winter 1980 Addenda. Where these requirements are determined to be impractical, specific requests for relief have been written and included in Section 3.2.

.3.1.2 Valve Program Table The Table Section 3.3 lists all ISI Class 1, 2, 3 and NC valves that are tested to meet IST requirements.

Valves exempt per IWV-1200 are not listed. Subarticle INV-1200, Valves Exempt from Testing; include valves used only for operating convenience, system control, and maintenance. Also, exempt are external control and protection systems responsible for sensing plant conditions and providing signals for valve operation.

TABLE FORKAI:

The table provides system and piping and instrumentation drawing (P&ID) number, drawing revision number utilized, system Title / Identification number and IST program revision number with approval date.

COLUMN HEADINGS:

VALVE NUMBER: Valve identification number.

P&ID COORDINATE: Coordinate location and sheet number on the P&IO.

ISI CLASS:

Inservice inspection classification.

VALVE CATEGORY: Category (s) assigned to the valve based on the definitions of INV-2200.

Four (4) separate categories are defined in the Code:

CATEGORY A - valves for which seat leakage is limited to a l

specific maximum amount in the closed position for fulfillment of their function.

CATEGORY B - valves for which a specific amount of leakage in the closed position is inconsequential for fulfillment of their function.

i l

Revision IB 3-1 l

I

CATEGORY C - valves which are self-actuating in response to some system characteristic, such as pressure (relief valves) or flow direction (check valves).

CATEGORY D - valves which are actuated by an energy source capable of only one operation, such as rupture disks or explosive actuated valves.

CATEGORY AC - valves which exhibit both Category A and Category C characteristics.

VALVE SIZE: Nominal pipe size (in inches).

VALVE TYPE: Valve Body Design; ANGLE AN BALL BL bur'ERFLY BF CHECK CK GATE GA GLOBE GL NEEDLE ND PLUG PG RELIEF RL RUPTURE DISC RD SAFETY SV SHEAR SH STOP CHECK SC SPRING CHECK SK ACTUATOR TYPE: Valve Actuator Power; HOTOR OPERATOR H0 AIR OPERATOR A0 SOLEN 0ID OPERATOR SO HYDRAULIC OPERATOR H0 EXPLOSIVE ACTUATOR EX HANUAL HA SELF ACTUATED SA NORMAL POSITION:

Normal Position During Plant Operation; NORMAL OPEN 0

NORMALLY CLOSED C

LOCKED OPEN L0 LOCKED CLOSED LC TEST REOUI.REHENT:

Test (s) that will be performed to fulfill the requirements of subsection IHV. The test definitions and abbreviations used are identified in Table, Inservice Valve Tests.

TEST FREOUENCY:

Frequency at which the tests will be performed.

The frequency deft-'tions and abbreviations used are identified in Table, Test Frequency.

Revision IB 3-2

MAX. STROKE TIME:

Limiting maximum value of stroke time, in seconds, for valves in Category A or Category B.

MAX. LEAKAGE: Maximum leakage allowed during specific seat leakage tests.

Abbreviations for units of measurement are:

SLM

- Standard liters per minute SCCM

- Standard cubic centimeters per minute GPM

- Gallons per minute RELIEF RE00EST:

Reference to Section 3.2 for relief request description.

R:: quests are identified as RV-XX.

REHARKS:

Clarification for a particular column to identify a special or unique requirement.

3.1.3 Measurement of Test Quantities STROKE TIME: Stroke time is that time interval froia initiation of the actuating signal to the end of the actuating cycle. Stroke time values for each power operated valve is specified in the valve program table. Stroke time is measured to the nearest second, for times of 10 sec. or less, or 10% of the specified limiting stroke time for times greater than 10 sec.

POSITION INDICATION: Valve disk movement is determined by exercising the valve while observing appropriate indicators which signal the required change of disk position, or observing indirect evidence, such as changes in system pressure, flow rate, level or temperature, which reflect stem or disk position.

SEAT LEAKAGE: Seat leakage is measured by one of the following methods:

(a) draining the line, closing the valve, bringing one side to test pressure, and measuring leakage through a downstream telltale connection, or (b) by measuring the feed rate 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 IHV-3423 are satisfied.

3.1.4 Allowable Ranges of Test Quantities STROKE TIME:

(a)

If, for power operated valves, an increase in stroke time of 25%

or more from the previous test for valves with strc times greater than 10 sec. or 50% or more for valves with stroke times less than or equal to 10 sec. is observed, test frequency shall be increased to once each month until corrective action is taken.

For valves with stroke times less than or equal to two seconds (Relief Request RV-2), increased frequency testing is not required.

(b)

Valve stroke time shall not exceed its specified limiting stroke time value without corrective action being taken.

Revision 18 3-3

POSITION INDICATION: The valve disk shall move from the cpen position to the closed position or vice versa, with valve travel direction accurately indicated by remote pocition indicating lights.

SEAT LEAKAGE:

(a)

Valve leakage rates shall not exceed the value established by Pilgrim Nuclear Power Station (BECo).

(b)

For valves 6 in nominal pipe size and larger 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 501, or greater, the test frequency shall be doubled; the tests shall be scheduled to coincide with a cold shutdown until corrective action is taken.

If tests show a leakage rate increasing with time, and a projection based on three or more tests indicates that the leak.sge rate of the next scheduled test will exceed the maximum permissible leakage rate by greater than 101., corrective action will be taken.

3.1.5 Instrument Accuracy Instruments used to measure stroke times shall be capable of measurement to the nealest tenth of a second.

Revision IB 3-4 Y

TABLE INSERVICE VALVE TESTS JffSI TEST NAME TEST DESCRIPTION / DEFINITION LJ Containment Containment isolation valves will be seat leak Isolation Valves tested in accordance with 10 CFR 50, Appendix J. Type C Leak Test.

LP Pressure Isolation Pressure Isolation Valves will be seat leak tested Valves in accordance with ASME Boiler and Pressure Vessel Code,Section XI, INV-3420 Valve Leak Rate Test.

LX Miscellaneous Other safety related valves - Miscellaneous Isolation Valves

-Isolation Valves will be seat leak' tested in accordance with 10 CFR 50, Appendix J or ASME Boiler and Pressure Vessel Code,Section XI.

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 cicsed 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. Valve timing need only be in one direction to comply with ASME Boiler and Pressure Vessel Code,Section XI.

1) Stroke Direction (C) -Normally open:

Full Stroke time close.

2) Stroke Direction (0) - Normally closed:

Full Stroke time open.

Additional stroke timing may be required by other documents (i.e., PNPS Technical Specifications and PNPS Final Safety Analysis Report).

PE Partial Stroke Partial stroke exercise testing will be performed Exercise to confirm partial stroke capability when Full Stroke Exercise is impractical.

Revision IB 3-5

TABLE INSERVICE VALVE TESTS (Continued)

IESI TEST NAME TEST DESCRIPTION / DEFINITION FC Check Valve Exercise Category C (i.e., check valves) valve Exercise is to assure freedom of motion preventing sticking / seizure of parts from prolonged immobility.

1) Forward Flow Direction (F) - Normally closed:

Flow Stroke open.

2) Reverse Flow Direction (R) - Normally open:

Flow Stroke close.

PC Partial Check Partial (valve checked in same flow direction)

Exercise exercise is when a Category C valve can only be partially exercised.

RD Rupture Disk Rupture Test of all Category "D":

Non-Testable Test valves were performed by the manufacturer or the start-up testing program and no additional testing shall be required; Testable valves were performed by the start-up testing program and shall be routinely scheduled by BECo.

EX Explosive Test Testing of explosive charges by firing per ASME Section XI with at least 20% of the charges in a batch shall be fire every 2 years with no charge exceeding 10 years.

RT Relief Set Point Relief and Safety Valve set point will be verified Test in accordance with ASME Boller and Pressure Vessel Code,Section XI (INV-3511), ASME PTC 25.3-1976 and PNPS Technical Specifications.

FS Fail Safe Test Valves with fail safe actuators (e.g.,

air operated, solenoid operated, and hydraulic operated) will be tested to verify proper fail safe operation upon loss of actuator power.

PI Position Indicator Valves with remote position indicators will be Verification checked to verify that remote valve position j

'ndicators accurately reflect valve position.

l Revision IB 3-6 l

TABLE TEST FRE0UENCY TEST OPERATIONAL (1)

FREQUENCY FREOUENCY CONDITION OF TESTING Q

Power Operation At least once per 92 days CS Cold Shutdown See (2) below R0 Refueling See (1) below SY No operational Every five years (see Article condition limitations INV-3511). Applies to RT test 2Y No operational Every two years (see Article condition limitations INV-3300). Applies to position indication tests and seat leakage tests (1) Operational condition as defined in PNPS Technical Specifications.

(2)

Inservice valve testing will commence within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> when reaching the cold shutdown condition as provided within NRC guidelines.

Testing not completed before start-up may be completed during subsequent cold shutdowns. Valve testing need not be performed more often than once every three months.

In the case of extended cold shutdowns, the testing need not be started within the 48-hour limitation. However, in these instances, all valve testing must be completed prior to start-up.

HQIE:

Completion of all valve testing during cold shutdown is not required if plant operating conditions do not permit testing of specific valves.

(3)

Provisions of PNPS Technical Specification Surveillance Interval -

definition are to be applicable to the following required frequencies for performing inservice testing activities.

ASME BOILER AND PRESSURE VESSEL REQUIRED FREQUENCIES FOR CODE AND APPLICABLE ADDENDA PERFORMING INSERVICE TEST TERMINOLOGY FOR INSERVICE TESTING ACTIVITIES ACTIVITIES HEEKLY AT LEAST ONCE PER 7 DAYS MONTHLY AT LEAST ONCE PER 31 DAYS QUARTERLY OR EVERY 5 MONTHS AT LEAST ONCE PER 92 DAYS SEMIANNUALLY OR 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 Revision IB 3-7 l

t i

TABLE TEST FREQUENCY (3) (Continued)

NOTE:

PNPS Technical Specification Surveillance Interval - definition also states:

Each surveillance requirement shall be performed within the specified time interval, with a.

A maximum allowable extension not to exceed 25% of the surveillance interval, but b.

The combined time interval for any 3 consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval.

Revision IB 3-8

SECTION 3.2 REFIEF REQUESTS FOR INSERVICE VALVE TESTING PROGRAM Revision IB 3-9 L

l RELIEF REQUEST RV-01 RETRACTED t

Revision IB 3-10

/

/0 RELIEF REQUEST RV-02 SYSTEM:

Reactor Building Closed Cooling Hater System (30)

VALVES:

4009A, 40098, 4002 ChlEGORIES: A,B CLASSES:

2, 3 FUNCTION:

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 FOR RELIEF:

The testing of these valves would require isolate of the following components; Drywell Area Coolers, Reactor Recirculation ? ump Seal Coolers, Reactor Recirculation Pump Lube Oil Coolers and additionally; The Reactor Hater Cleanup (RHCU) non-regenerative heat exchanger, B Fuel Pool Cooling Heat Exchanger, RHCU Pump Cooling System Coolers, Control Rod Drive (CRD) Pump Area Cooling and CRD Pump Thrust Bearing Coolers for testing of the 4009A and 40098. The listed components supply numerous plant systems required for safe 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 Drywell components.

ALTERNATE TESTING:

Exercise valves during cold shutdown when recirculation pumps and drywell coolers are not required but not to exceed a refueling outage.

Pevision IB 3-11

RELIEF REQUEST RV-03 SYSIEM:

Reactor Building Closed Cooling Hater System (30)

YAllE:

432 CATEGORY:

AC CLASS:

2 FUNCTION:

This valve provides isolation to drywell components by RE'CCH.

The components would require isole. tion for primary containment criteria and maintenance.

TEST REOUIREMENT:

INV-3521; Test frequency - exercise at least once every three months, quarterly.

BASIS FOR REL711:

This check valve is the outboard primary containment isolation valve for a system considered inservice durin/

plant operation. The normally open check valve requires a reverse flow exercise.

Leak testing (per 10 CFR 50, Appendix J) ensures valve exercising in the closed direction each refueling outage.

ALTERNATE TESTING:

Exercise valve during refueling outage (at least once every two years).

Revision 1B 3-12

RELIEF REQUEST RV-04 RETRACTED V

Revision IB 3-13

RELIEF REQUEST RV-05 RETRACTED Revision 18 3-14 N

RELIEF REQUEST RV-06

$11I18:

Compressed Air System (31)

VALVE:

167 CATEGORY:

AC CLASS:

2 FUNCTION:

This valve is the nitrogen / instrument air to drywell inboard isolation valve for primary containment isolation.

(

TEST REOUIREMENT:

INV-3521; Test frequency - exercise at least once every three months, quarterly.

BASIS FOR RELIEF:

This check valve is the inboard primary containment isolation valve for a system considered inservice during plant operation. The normally open check valve requires a reverse flow exercise.

Leak testing (per 10 CFR 50, Appendix J) ensures valve exercising in the closed direction each refueling outage.

ALTERNATE TESTING:

Exercise valve during refueling outage (at least once every two years).

Revision 18 3-15 l

5i RELIEF REQUEST RV-07 SYSTEM:.

Containment Atmosphere Control System (45)

VALVES:-

X-201A X-201E X-201J X-201B X-201F X-20lK X-201C X-201G X-201D X-201H CA_TEGORY:

AC 4

CLASS:

2 FUNCTION:

These valves are the pressure suppression chamber to drywell vacuum breaker valves which equalize the pressure ijetween the two volumes when the suppression chamber pressure exceeds the drywell pressure.

TEST REOUIREMENTS:

INV-3420; Valve Leak Rate Test.

BASIS'FOR RELIEF:

A specific maximum leakage per valve is not applicable to the vacuum breaker valve testing. A pressure decay test is performed on the pressure suppression chamber atmosphere in accordance with PNFS Technical Specification on a quarterly basis. The valve leak rate test requirements shall be verified by a pressure decay test on the pressure suppression chamber atmosphere in accordance with PNPS Technical Specification on a refueling outage basis.

ALTERNATE TESTING:

Valve leak rate test requirements shall be demonstrated in accordance with PNPS Technical Specification.

Revision IB 3-16

REl.IEF REQUEST RV-08 SYSTEMS:

All Applicable VALVES:

All Applicable CATEGORIES: A,B CLASSES:

All Applicable FUNCTIQH:

Not Applicable t

TEST REOUIREMENT:

INV-3417(a) Corrective Action BASIS FOR RELIEF:

Valves designed to be rapid acting have extremely short stroke times.

Since these valves stroke fast, it is difficult to time them accurately and any deviation in trended time could be due to reaction time of the individual performing the test rather than any change in the valve's performance.

Because of the rapid action of these valves stroke times for valves having an acceptance criteria of two (2) seconds will not be trended or recorded but a two (2) second acceptance limit will be used.

ALTERNATE TESTING:

Verify that all valves have an acceptance criteria of less than two (2) seconds. No stroke time recording or trending will be performed.

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Revision IB 3-17

RELIEF REQUEST RV-09 SYSTEM:

Containment Atmosphere Control Nitrogen Makeup System (9)

VALVES:

340, 341 CATEGORY:

AC CLASS:

2 FUNCTION:

These valves serve as containment atmosphere control primary containment isolation valves on the 1 inch nitrogen makeup line to the 6rywell and torus.

1

0VIREMENT:

INV-3521; Test frequency - exercise at least once every three months, quarterly.

ha as FOR RELIEF:

These check valves are the first primary containment isolation valves for a system considered inservice during plant operation.

The normally open check valves require a reverse flow exercise.

Leak testing (per 10 CFR 50, Appendix J) er'Jres valve exercising in the closed direction each refur.itng outage.

ALTERNATE TESTING:

Exercise valve during refueling outage (at least once every two years).

i Revision IB 3-18

-~

RELIEF REQUEST RV-10 RETRACTED i.

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RELIEF REQUEST RV-11 SYSTEH:-

Transverse Incore Probe System (45)

VALVE:

N2 Purge Supply Check CATEGORY:

AC CLASS:

i 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.

fLASIS 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 10 CFR 50, Appendix J) ensures valve exercising in the closed direction each refueling outage.

ALTERNATE TESTING:

Exercise valve during refueling outage (at least once every two years).

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Revision 18 3-20 t

RELIEF REQUEST RV-12 SYSTEM:

Residual Heat Removal System (1001)

-VALVES:

47, 50, 60, 63 CATEGORY:

A CLASS:

1 FUNCTION:

The 47 and 50 valves are the RHR shutdown cooling suction path primary containment and pressure isolation valves.

The 60 and 63 valves are the RHR head spray line primary containment 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 RELIEF:

The valves are interlocked to prevent opening when 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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1 Revision IB 3-21 l

{

RELIEF REQUEST RV-13 SYSTEM:

Residual Heat Removal System (1001)

VALVES:

68A, 68B CATEGORY:

AC CLASS:

1 FUNCTION:

These valves are the low pressure coolant injection pressure isolation check valves which provide a flow path for shutdown cooling.

TEST RE0VIREMENT:

INV-3521; Test frequency - exercise at least once every three months, quarterly.

BASIS FOR RELIEF:

Exercising these valves to the open position can only be accomplished by verifying flow to the vessel.

Forward flow exercising of these valves is confirmed during shutdown cooling operations.

Both loops of shutdown cooling are not normally required during cold shutdown. Additional impact on plant availability and increased radiation exposure will be incurred to verify both check valves each cold shutdown.

Shutdown cooling loop selection will be based upon alternating the exercising of these valves.

ALTERNATE TESTING:

Exercise valve during cold shutdown (based on shutdown cooling loop availability) not to exceed a refueling outage.

l Revision IB 3-22 i

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RELIEF REQUEST RV-14 SYSTEM:

Core Spray System (1400)

VALVES:

9A, 98 CATEGORY:

AC fMSS:

1 FUNCTION:

These valves are the Core Spray Injection Pressure Isolation Check Valves.

TEST REOUIREHENT:

INV-3521; Test frequency - exercise at least once every three months, quarterly.

RASIS FOR RELIE:

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 pressure suppression pool is the Core Spray System's water source.

Injection of pressure suppression pool water into the reactor vessel during cold shutdown results in exceeding the EPRI Nater Chemistry Guidelines that PNPS has adopted to preclude the initiation and propagation of intergranular stress corrosion cracking of the reactor coolant stainless steel components. The chemistry of the pressure suppression pool water (typical conductivity of 4-5 umho/cm) does not meet the chemistry requirements of the reactor coolant (typical conductivity of 0.15-0.3 umho/cm).

Restart of the reactor is not permitted until the reactor I

coolant water chemistry is within the EPRI Guidelines.

In addition, the amount of water th&t 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 and feed of the core spray system to l

improve water quality prior to testing.

ALTERNATE TESTING:

Exercise valve during refueling outage.

Revision 13 3-23

RELIEF REQUEST RV-15 SYSTEMS:

High Pressure Coolant-Injection System (2301)

Reactor Core Isolation Cooling System (1301)

VALVES:

2301-7, 1301-50 CATEGORY:

AC CLASS:

1 FUNCTION:

These valves are the HPCI and RCIC injection pressure isolation check valves.

IEST REOUIREMENT:

INV-3521; Test frequency - exercise at least once every three months, quarterly.

BASIS FOR RELIEF:

Testing these valves during normal operation would require;

1) injecting cold water into the reactor vessel reing the HPCI (or RCIC) system which would result in bo" reactivity i

excursion and thermal shock to the feedwater nottie and piping and 2) loss of one pressure isolation barrier between the high pressure reactor coolant system and low pressure HPCI (or RCIC) System.

These valves are manually stroke testable.

Since a maximum allowable torque on the mechanical test lever of 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 if the plant is not in an abnormal cold shutdown valve lineup.

During normal cold shutdown, the feedwater header regulating valves are closed or isolated.

ALTERNATE TESTING:

Manually exercise during cold shutdown (normal cold shutdown feedwater valve lineup) not to exceed a refueling outage, i

l Revision IB 3-24

RELIEF REQUEST RV-16 SYSTEM:

High Pressure Coolant Injection System (2301)

VALVE:

24 (formerly H0-2)

CATEGORY:

B CLASS:

2 FUNCTION:

The High Pressure Coolant Injection Turbine Throttle Valve regulates steam to the HPCI turbine in response to changes in the HPCI Pump Flow Rate and ramp generator signals.

TEST RE0UIREMENT:

INV-3413; Power operated valves - full stroke time.

BASIS FOR RELIEF:

This normally closed throttle talve will position at a predetermined rate as governed by the HPCI Pump Flow Rate.

The rate of positioning and number of poppets open are dependent upon varying plant parameters. The throttle valve fails in the closed position upon a trip of the HPCI turbine. Therefore, the throttle valve timing is variable and shall be verified by HPCI system operability testing during ilPCI pump tests.

ALTERNATE TESTING:

HPCI throttle valve stroke timing shall be verified by HPCI system operability (adequate valve response to system demand j

inputs).

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RELIEF REQUEST RV-17 RETRACTED l

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Revision 1B 3-26

RELIEF REQUEST RV-18 RETRACTED i

l Revision IB 3-27 I

RELIEF REQUEST RV-19

. SYSTEM:

Standby Liquid Control System (1101)

VALVES:

15, 16 CATEGORIES: C, AC CLASS:

1 FUNCTION:

These valves are the SBLC injection check valves.

TEST REOUIREMENT:

INV-3521; Test frequency - exercise at least once every three months, quarterly.

BASIS FOR RELIEF:

To verify forward flow exercise during norma; operation would require firing a squib valve and injecting water into the reactor vessel using the SBLC pumps.

Injecting water during operation could result in adverse plant conditions such as changes in reactivity, power transient, thermal shock induced cracking and a possible plant trip. Verify forward flow operability during refueling while performing the standby liquid control system injection test.

This test requires firing at least one squib valve and pumping demineralized water into the reactor vessel.

ALTERNATE TESTING:

Exercise valve during refueling outage.

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l Revision 18 3-28

RELIEF REQUEST RV-20 RETRACTED Revision IB 3-29

RELIEF REQUEST RV-21 SYSTEM:

Control Rod Drive Hydraulic System (302)

VALVES:

114, 115, 126, 127 (typical of 145 each)

CATEGORIES: B, C-CLASS:

2 FUNCTION:

These valves are the CRD scram inlet, exhaust, discharge header check and accumulator supply check valves.

TEST RE0UIREMENTS:

INV-3411; Test frequency - exercise at least once every three months.

INV-3413; Power operated valves - full stroke time.

INV-3415; Fall safe - at least once every three months.

INV-3521; Test frequency - exercise at least once every three months.

BASIS FOR RELIEF:

These valves (with the exception of the 115) operate in coincidence to rapidly insert control rods. Valves will be tested by SCRAM timing control rod drives in accordance with Technical Specification Section 4.3.

This requires testing of 507. of the drives every 16 weeks and 1007. every 32 weeks.

Additionally, 1007. of the drives are tested each shutdown.

Timing of the SCRAM function will be substituted for individual valve times.

The Accumulator Supply Check Valve (115) will be verified forward flow exercised by the clearing of the accumulator fault light following restoration from scram time testing.

ALTERNATE TESTING:

SCRAM function timing will be substituted for individual valve exercising.

l Revision IB 3-30 l

1

RELIEF REQUEST RV-22 SYSTEM:

Control Rod Drive Hydraulic System (302)

VALVES:

138 (typical of 145)

CATEGORY:

C CLASS:

2 EURCI1ON:

These valves are the CRD cooling water check valves.

TEST REOUIREMENT:

INV-R521; 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.

ALTERNATE TESTING:

Exercise by meeting surveillance requirements PNPS Technical =

Specification.

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Revision IB 3-31

RELIEF REQUEST RV-23 SYSTEM:

Nuclear Boiler - Reactor Recirculation System (202) l VALVES:

5A, 58 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).

TEST REOUIREMENTS:

INV-3411; Test Frequency - exercise at least once every three months.

INV-3412; Power operated valves - full stroke time.

BASIS FOR RELIEF:

Closure of these valves during normal operation will result in loss of forced circulation to the reactor, a condition prohibited by PNPS's 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 l

temperature gradient between the bottom 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.

Revision IB 3-32

RELIEF REQUEST RV-24 SYSTEM:

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) open 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 RE0VIREMENTS:

IW-3411; rest Frequency - exercise at least once every three months.

IW-3413; Power operated valves - full stroke time.

IW-3415; Fall safe - at least once every three months.

BASIS FOR RELIEF:

Relief is requested from 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 once per operating cycle as specified in PNPS Technical Specification.

Relief is requested from the stroke timing requirements of Section XI.

It is impractical to measure stroke times for relief and solenoid valves since the stroke times are on the order of 100 ms.

After the recent failures of two of the 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 by an independent consultant.

Results of the exam revealed the following causes for failure:

1.

Normal cort. 'on of the pilot valve's Stellite 6 seat to the Stellite JB disc was the main reason for the sticking.

The corrosion process is basic to the environment during operation.

2.

It was discovered that the Stellite 6B disc had carbides at the surface.

The normal corrosion went around the carbides and tended to "key" into the surface. This was proyen by the examination of disc / seat surfaces.

The disc had microscopic holes where the carbides were pulled out.

Revision IB 3-33

RELIEF REQUEST RV-24 (Continued) 3.

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.

A material change to the pilot valve disc was made to correct items 1 and 2.

Because of the findings of item 3 above, PNPS intends to operate the relief valves at the higher reactor pressure between 350 and 500 psi. The analysis also indicates that mechanical interaction between the disc and the seat increases the potential for sticking.

This fact allows the conclusion that mechanical interaction from stroking the pilot valve should be minimized.

Based upon this information, no increase in frequency of testing beyond PHPS Technical Specification is advisable.

ALTERNATE TESTING:

Exercise valves-during refueling outage (adequate pressure available) with stroke times not being measured.

Revision 18 3-34

RELIEF REQUEST RV-25 SYSTEM:

Nuclear Boiler - Main Steam, Vent, Drain & Sampling System (220)

VALVES:

46, 47 CATEG0M:

B-CLASS:

1 FUNCTION:

These valves are used to vent the reactor vessel head and main steam line "A" during startup.

TEST REOUIREMENTS:

IHV-3411; Test Frequency - exercises at least once every three months.

INV-3413; Power operated valves - full stroke time.

IHV-3415; Fail safe - at least once every three months.

BASIS FOR RELIEF:

Exercising one of these valves during normal operation 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 pronibit operation of these valves during power operation.

ALTERNATE TESTING:

Exercise valves during cold shutdown (not to exceed refueling outage).

Revision IB 3-35

RELIEF REQUEST RV-26 SYSTEM:

Nuclear Boiler - Feedwater System (6)

VALVES:

58A, 58B, 62A, 628 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 10 CFR 50, Appendix J) ensures valve exercising in the closed direction each refueling outage.

ALTERNATE TESTING:

Exercise valves during refueling outage (at least once every two years).

Revision 1B 3-36

RELIEF REQUEST RV-27 SYSTEH:

Nuclear Boiler - Compressed Air System (31)

VALVES:

372A, 3728, 372C, 3720 CATEGORY:

AC CLASS:

3 FUNCTION:

These valves provide isolation and allow recharging of the ADS air accumulators.

TEST REOUIREMENTS:

INV-3420; Valve Leak Rate Test.

BASIS FOR RELIEF:

Verification of the leak rate test requirements for these valves shall be performed in conjunction with ADS accumulator pressure drop testing each refueling outage. The ADS accumulator pressure drop test can only be accomplished by disassembling a portion of the air supply system and accumulator pressure boundary.

This test verifies the leak tightness of the entire accumulator's pressure boundary of which the check valve is an integral component. Verification of the accumulator pressure boundary leak tightness verifies check valve seat leakage each refueling outage.

ALTERNATE TESTING:

Valve leak rate test requirements are demonstrated by an accumulator pressure drop test each refueling outage.

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RELIEF REQUEST RV-28 SYSTEM:

Recirculation Pump Seal Hater System (201)

VALVES:

13A, 13B, 17A, 17B CATEGORY:

AC CLASS:

2 FUNCTION:

These valves.se:ve as the recirculation pump seal water inboard and outboard check valves.

TEST REOUIREMEll:

INV-3521; Test Frequen y - exercise at least once every three months, quarterly.

BASIS FOR RELIEF:

These check valves are the primary containment isolation valves for a system considered inservice during plant operation. These normally open check valves require a reverse flow exercise.

Leak testing (per 10 CFR 50, Appendix J) ensures valve exercising in the closed direction each refueling outage.

6LTERNATE TESTING:

Exercise valves during refueling outage (at least once every two years).

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RELIEF REQUEST RV-29 RETRACTED Revision IB 3-39

RELIEF REQUEST RV-30 RETRACTED t

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Revision IB 3-40

RELIEF REQUEST RV-31 SYSTEMS:

High Pressure Coolant Injection System (T.301),

Reactor Core Isolation Cooling System (1301)

VALVES:

2301-39, 1301-27 CATEGORY:

C CMM:

2 FUNCTION:

These valves provide the alternate suction path for system operations.

TEST REOUIREMENT:

INV-3521; Test Frequency - exercise at least once every three months, quarterly.

BASIS FOR RELIEF:

During the normal system operating modes, water is t2 ken from the condensate storage tanks and not the pressure suppression pool.

These check valves would only be used when an abnornial plant condition existed and their exercise can not be verified by system flow. Attempting to test these check valves could result in exceeding the EPRI Hater Chemistry Guidelines that PNPS has adopted to preclude the initiation and propagation of'intergranular stress corrosion cracking.

This test would require pressure suppression pool water (typical conductivity of 4-5 umho/cm) to be cross-contaminated with the reactor grade water (typical conductivity of 0.15-0.3 umho/cm) of the Condensate Storage Tanks.

Therefore, the forward flow exercising of these check valves will be by disassembly or other positive means each refueling outage.

ALTERNATE TESTING:

Exercise valves during refueling outage by disassembly or other positive means.

i l

Revisior. 18 3-41

RELIE! REQUEST RV-32 SYSTEM:

Salt Service Hater System (29)

VALVES:

3915, 3925 CATEGORY:

B CLASS:

3 FUNCTION:

These valves isolate the service water system from the screen wash system when LOCA occurs.

IEST RE0VIREMENT:

INV-3412; Power operated valves - full stroke time.

BASIS FOR RELIEF:

When the screen wash pumps are turned off, these valves receive a signal to close. There are no position indicator lights to show when the valves have closed after the pumps are tripped, therefore, the stroke times cannot be determined.

Proper valve closure is verified by observation of actuator stem position change after the screen wash pumps have tripped.

ALTERNATE TESTING:

Valves stroke times shall not be measured.

Revision 18 3-42

RELIEF REQUEST RV-33 SYSTEM:

Diesel Oil Transfer System (38)

VALVES:

4521, 4522 CATEGORY:

B CLASS:

3 FUNCTION:

These valves open automatically upon initiation of the diesel oil transfer pumps to allow oil to flow into the day tank.

TEST REQUIREMENT:

INV-3412; Power oper3ted valves - full stroke time.

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.

Revision 1B 3-43

RELIEF REQUEST RV-34 1

4 SYSTEM:

High Pressure Coolant Injection System (2301)

VALVE:

9313 CATEGORY:

B CLASS:

2 FUNCTION:

This valve must close so as to isolate the nitrogen supply system from the turbine exhaust line.

TEST REOUIREMENT:

INV-3413; Power operated valves - full stroke time.

BASJJL FOR RELIEF:

Both A0-9312 and A0-9313 operate in tandem and provide isolation of the nitrogen supply system. A0-9313 is in the IST program because the ISI boundary stops at this valve.

There is no direct method for confirming that A0-9312 and A0-9313 close.

If these valves do not close properly, primary containment pressure will slowly increase. An increase in containment pressure will be detected by the primary containment monitoring system.

ALTERNATE TESTING:

Valve stroke time shall not be measured.

s Revision IB 3-44 1

RELIEF REQUEST RV-35 RETRACTED i

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Revision IB 3-45 l

l l

RELIEF REQUEST RV-36 SYSTEM:

Salt Service Hater System (29)

VALVES:

3801, 3805 CATEGORY:

B CLASS:

3 FUNCTION:

These valves control cooling water flow from the Turbine Building Closed Cooling Hater (TBCCH) heat exchanger, and therefore, the amount of cooling available for TBCCH equipm:'"

The safety function of these valves is to close on LOCA signal ic c-<ar to direct maximum cooling water flow to the RBCCH heat exchanger.

TEST REOUIREMENTS:

INV-3411; Test Frequency - exercise at least once every three months.

BASIS FOR RELIEF:

Since critical power generation equipment such as-the 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.

xlTERNATE TESTING:

Partial stroking of valves quarterly.

Exercise valves during cold shutdown.

Revision 18 3-46

I nI RELIEF REQUEST RV-37

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RELIEF REQUEST RV-38 1

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Revision 18 3-48

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RELIEF REQUEST RV-39 SYSTEM:

Reactor Core Isolation Cooling System (1301) ylLVE.S:

2 CATEGORY:

B CLASS:

2 FUNCTION:

The Reactor Core Isolation Cooling Turbine Thiottle Valve regulates steam to the RCIC turbine in response to changes in RCIC Pump Flow Rate.

TEST REOUIREMENT:

INV-3413; Power operated valves - full stroke time.

BASIS FOR RELIEF:

This normally open throttle valve shall close to a position governed by the RCIC Pump Flow Rate. The rate of movement and valve position are dependent upon varying plant parameters. The throttle valve fails in the open position upon a trip of the RCIC turbine.

Therefore, the throttle valve tiaing is variable and shall be verified by RCIC system operability testing during RCIC pump tests.

ALTERNATE TESTING:

RCIC throttle valve strie timing shall be verified by RCIC system operability (adequate valve response to system demand inputs).

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Revision 18 3-49

RELIEF REQUEST RV-40 RETRACTED l

l Revision IB 3-50

RELIEF REQUEST RV-41 SYSTEH; High Pressure Coolant Injection System (2301)

VALVES:

232, 233 CATEGORY:

C CLASS:

2 FUNCTION:

These valves provide a vent path to relieve vacuum created within the HPCI exhaust line after turbine operation.

TEST REOUIREMENT:

INV-3521; Test Frequency - exercise at least once every three months.

BASIS FOR RELIEF:

The HPCI Exhaust Vacuum Breaker Line Check valves shall be forward flow exercised. These normally closed check valves are verified in the open direction by isolating the vacuum breaker exhaust line and ensuring unrestricted flow. The vacuum breaker line isolation will make the HPCI system inoperable.

Exercising is to be performed during cold shutdown.

ALTERNATE TESTING:

Exercise during cold shutdown.

Revision 1B 3-51

RELIEF REQUEST RV-42 SYSTEMS:

Core Spray System (1400)

High Pressure Coolant Injection System (2301)

Reactor Core Isolation Cooling System (1301)

Reactor Water Cleanup Syster (1201)

Recirculation Pump Instrumentation (262)

Nuclear Boiler Instrumentation (261)

Nuclear Boiler Instrumentation (263)

VALVES:

All Applicable CATEGORY:

AC CLASS:

1 FUNCTION:

These excess flow check valves provide primary containment isolation in case of an instrument line break.

TEST REOUIREbEMI:

INV-3521; Test Frequency - exercise at least once every three months.

BASIS FOR RELIEF:

These excess flow check valves are the primary containment isolation valves for systems considered inservice during plant operation. These normally open instrument isolation check valves require a reverse flow exercise.

Leak testing (per ASME Code) performs valve exercising in the closed direction each refueling outage.

ALTERNATE TESTING:

Exercise valves during refueling outage (at least onco every two years.

1 l

1 l

Revision IB 3-52 l

l l

RELIEF REQUEST RV-43 SYSTEM:

Reactor Building Closed Cooling Hater (30)

VALVEf,:

4085A, 40858 CATEGORY:

B j

CLASS:

3 FUNCTION:

Valves 4085A and 40858 are the non-safety related component isolation valves for R5CCH Loop A.

TEST RE0UIREMENTS:

INV-3411; Test Frequency - exercise at least once every three months.

INV-3413; Power operated valves - full stroke time.

BASIS FOR RELIEF:

Valves 4085A and 4085B are the non-safety related component isolation valves for RBCCH Loop A.

Although classified as non-safety function, the components are not without importance. 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 securing operating of the recirculatior, pumps due to loss 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 idle recirculation loops cools down. This stratification can have the following adverse effects:

reactor vessel metal temperature differences become greater between reactor vessel bottom and top resulting in unwanted thermal cycling. Start up of the shutdown j

recirculation pumps causes a cold water intrusion which affects reactor vessel metal temperatures and causes thermal cycling of the reactor vessel.

l ALTERNATE TESTING:

Exercise valves during cold shutdown when reactor recirculation pumps are not required but not to exceed a refueling outage.

Revision 18 3-53 t

RELIEF' REQUEST RV-44 SYSTEM:

Nuclear Boiler - Compressed Air (31)

VALVES:

84A, 84B, 84C, 840, 85A, 858, 85C, 85D CATEGORY:

C CLASS:

3 FUNCTION:

These valves allow charging of the MSIV accumulators.

TEST REOUIREMENT:

INV-3522(b); Normal Close Valves - exercise procedure.

BASIS FOR RELIEF:

These check valves are required to supply nitrogen / instrument air to recharge air accumulators during each Main Steam Isolation Valve (MSIV) full-stroke cycle.

Failure of a check valve to open (forward flow exercise) would impede the normal opening function of the HSIV. Therefore, proper MSIV full-stroke valve verifies air accumulator check valve forward flow exercise.

ALTERNATE TESTING:

Verify forward flow exercising by MSIV full-stroke valve cycle testing.

i l

Revision 18 3-54 l

RELIEF REQUEST RV-45 SYSTEMS:

Diesel Generator Air Start System (47)

Diesel Generator Turbo Air System (47)

VALVES:

4586A, 4586B, 4587A, 45878, 4588A, 45888, 4589A, 45898 4569A, 4569B, 4570A, 45708 C6TEGORY:

B CLASS:

3 FUNCTION:

These air start solenoid valves provide startir.g air to the emergency diesel generator.

TEST RE0UIREMENTS:

INV-3411; Test frequency - exercise at least once every three months.

INV-3413; Power operated valves - full stroke time.

IRV-3415; fail safe - at least once every three months.

BASIS FOR RELIEF:

Valve design does not allow for any valve position indication verification. During the Diesel Generator Alternate Air Bank Start monthly surveillance, failure of a valve to perform its open function will result in an increase in the starting ti me. Also, failure of the valve to close will cause starting air not to secure.

ALTERNATE TESIING:

Valves shall be verified operable during monthly diesel generator technical specification surveillance testing. The i

starting time will be monitored and trended to determine valve operability, i

l Revision IB 3-55 n.

RELIEF REQUEST RV-46 SYSTEMS:-

-Residual Heat Removal System (1001)

Core Spray System (1400)

High Pressure Coolant Injection System (2301)

Reactor Core Isolation Cooling System (1301)

VALVES:

1001-29A, 1001-29B, 1400-25A, 1400-258, 2301-8, 1301-49 CATEGORY:

A CLASS:

1 FUNCTION:

These valves provide pressure isolation from t.Ne high pressure reactor coolant system.

TEST REOUIREMENTS:

INV-3411; Test Frequency - Exercise at least once every three months and INV-3413; Power operated valves - full stroke time.

BASIS FOR RELIEF:

These pressure isolation motor operated valves maintain one of the two high to low pressure barriers during plant operation.

To exercise these valves during plant operation would create 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 intersysten loss of coolant accident.

ALTERNATE TESTING:

Exercise valves during cold shutdown.

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Revision IB 3-56 i- --.

RELIEF REQUEST RV-47 SYSTEM:

Residual Heat Remov&1 System (1001)

Core Spray System (1400)

VALVES:

1001-362B, 1001-363A, 1400-212A, 1400-212B CATEGORY:

C CLASS:

2 FUNCTION:

These check valves supply the flow path for keep fill pressurization and makeup.

TEST RE0UIREMENT:

INV-3521; Test Frequency - exercise at least once every three months, quarterly.

BASIS FOR RELIEE:

These normally open check valves provide keep fill makeup and l

pressurization which is required to maintain these systems operable. No method exists to verify reverse flow exercise i

of these valves while they are in service. The valves shall be exercised and verified in the closed direction by disassembly or other positive means during each refueling outage.

ALTERNATE TESTING:

Exercise valves during refueling outage.

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l Revision IB 3-57

RELIEF REQUEST RV-48 SYSTEM:

Reactor Core Isolation Cooling System (1301)

YALVE:

9067 CATEGORY:

C CLASS:

2 FUNCTION:

This valve provides a vent path to relieve vacuum created within the RCIC exhaust line after turbino operation.

TEST REOUIREMENT:

INV-3521; Test Frequency - exercise at least once every three months.

BASIS FOR RELIEF:

The RCIC exhaust vacuum breaker line check valve shall be forward flow exercised. This normally closed check valve is verified in the open direction by isolating the vacuum breaker exhaust line and ensuring unrestricted flow. This vacuum breaker line isolation will render the RCIC system inoperable. Exercising is to be performed only during cold shutdown.

ALTERNATE TESTING:

Exercise valve during cold shutdown.

Revision IB 3-58 L

RELIEF REQUEST RV-49 SYSIEM:

Nuclear Boiler - Compressed Air (31)

VALVES:

372A, 3728, 372C, 3720 CATEGORY:

AC CLASS:

3 FUNCTION:

These valves provide isolation and allow recharging of the ADS air accumulators.

TEST REOUIREMfMI:

IWV-3521; Test Frequency - exercise at least once every three months, quarterly.

BASIS FOR RELIEF:

These check valves with their associated air 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 drywell is deinerted.

ALTERNATE TESTIhG:

Exercise valves during cold shutdown (when drywell is deinerted) not to exceed a refueling outage.

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l Revision IB 3-59 L

SECTION 3.3 INSERVICE VALVE TESTING PROGRAM l

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TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P1ID: M-215 REVISION: E14 BOSTON EDISON COMPANY SYSTEM: REACTOR BUILDING CLOSED COOLING WATER (30)

IST Program Revision is 2/5/88 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor Class Cat Size Tvoe Tvoe Position Rant.

Frea Time (s)

Leakaae Reauest Notes 4083 E-4 3

B 10 BF M0 C

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RV-43 Recirc. Pu p Sec.

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ST CS 40 (C)

RV-43 Rectrc. Pump Sec.

PI 2Y 3-63

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8 5

B 8

8 O

T N A OR s

I E s

S N I a I E Sl V G I C 3

3 3

3 3

3 3

3 3

3 3

3 ER LE S

D r 7-7 7

7 4

4 4

4 4

4 4

4 9 E I o 2 D PC G

D F-BH H

E E-E D

B B

1 I

& o

-M A

8 A

B A

8 4

8 M

e r A

8 C

0 6

6 7

7 8

8 9

9

E v e 1

1 1

1 8

8 8

8 8

8 8

8 DT l b 0

0 0

0 5

5 5

5 5

5 5

5 I S a m 1

1 1

1 4

4 4

4 4

4 4

4

& Y V u P S N

TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILCRIM MJCLEAR POWER STATION P&ID: M-220 REVISION: E16 BOSTON EDISON COMPANY SYSTEM: COMPRESSED AIR (31)

IST Program Revision le 2/5/88-volve P&'d ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Man Relief Number foor Class Cat Sire Tvoe Tvoe Position Rat.

Free Time (s)

Leakaae Reauest Notes

]

167 D-3 2

AC 3

CK SA 0

FC RO RV-06 Reverse flow LJ 2Y 7.89 SLM 3-65

l1 1

!i Y8 N8 A /

P 5 wwww M/

o o

e o

,O2 s

l l

l l

C e

f f

f f

t n

n N

o d d

d d

e e

O N

r r

r r

s o

S 8 a

a a

a o

C w

w w

w I 1 D

r r

r r

E n o

o o o o

F F

F F

Ni O s T i S v O e t

B R f s e e 3

3 m

i u 3

3 a

l a

r e e V

V g

R R R

R or P

e T

o S

a I

k x a a e ML M

S e

A E N k )

R VO o s G

L I r(

O A T t e R

VA S m P

T i

CS xT G

N a

A A

N R

M N

N I

D E T

N W S

AO E E P

t a L T 3

s e0 0

0 0

QQ0 QQO B

,R e r A

T F AE T V 2E L

L A

,C V

1 U N

t t e C C

C C ETS ETS E

S s

F F

F F

F SF F SF C

S M e

I AI T R V

L R 6

R C G 6

E L

n S

I I o

3 N

S P l i I

I at mi r s C

C C

C C

C oo NP ro tau e t o c v A

A A

A 0

0 AT S

S S

S A

A ev e l o a v K

K K

K L

L VT C

C C

C B

B ev e 5

5 5

5 l

z ai

)

VS 2

2 1

1 1

1 83(

e R

v 5 E l t E F a a S

VC C

C C

C 8

B N

A NR OT s

I s

S L I a I I Sl VO I C 3

3 3

3 3

3 ER LE S

D r 3 E I o 7

7 5

5 5

5 2 I

& o 2 D P C F

D F

E G

E

-M M

e r A

8 A

8 1

2

E v e 1

1 5

5 2

2 DT l b 0

0 0

0 5

5 1

1 1

1 4

4 I S a m

& Y V u P S N

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 REVISION: E9 BOSTON EDISON COMPANY P&ID: M-227 SHEET 2 of 2 REVISION: E7 SYSTEM: CONTAINMENT ATMDSPHERE COTROL (45) & (9)

IST Program Revision 18 2/5/88 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor Class Cat Size Tvoe Tvoe Position Rant.

Frea Time (s)

Leakaoe Request Notes 102 C4 2

A 1

BL M

C FC m

Passive (45)

(SH.1)

U 2Y 7.89 SLM 103 C4 2

A 1

GL m

C FC E

Passive (45)

(SH.1)

W 2Y 7.89 SLM 104 C4 2

A 1

GL m

C FC NA Passive (45)

(SH.1)

U 2Y 7.89 SLM 105 C4 2

A 1

GL m

C FC m

Passive (45)

(SH.1)

U 2Y 7.89 SLM 106 E-5 2

A 4

GA m

C FC NA Passive (45)

(SH.1)

U 2Y 7.89 SLM X-201A C-7 2

AC 18 CK SA C

FC Q

Forward flow (45)

(SH.1)

(Testable)

PI 2Y LX 2Y NA RV-07 X-2018 C-7 2

AC 18 CK SA C

FC Q

Forward flow (45)

(SH.1)

(Testable)

PI 2Y u

N m

W47 X-201C C-7 2

AC 18 CK SA C

FL Q

Forward flow (45)

(SH.1)

(Tes table)

PI 2Y LX 2Y NA RY-07 X-201D C-7 2

AC 18 CK SA C

FC Q

Forward flow (45)

(SH.1)

(Testable)

PI 2Y LX ZY NA RV47 X-201E C-7 2

AC 18 CK SA C

FC Q

Forward flow (45)

(SH.1)

(Testable)

PI 2Y LX 2Y NA RV-07 s

3-67

.1

TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES I

PILGRIM NUCLEAR POWER STATION P&ID: M-227 SHEET 1 of 2 REVISION: E9 BOSTON EDISON COMPANY P&ID: M-227 SHEET 2 of 2 REVISION: E7 SYSTEM: CONTAINMENT ATMOSPHERE COTROL (45) & (9)

IST Program Revision 15 2/5/88 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor Class Cat Size Tvoe Tvoe Position Ret.

Frea Time (s)

Leakaae Reauest Notes X-201F C-7 2

AC 18 CK SA C

FC Q

Forward flow (45)

(SH.1)

(Testable)

PI 2Y LX ZY NA RV-07 X-201G C-7 2

AC 18 CK SA C

FC Q

Forward flow (45)

(SH.1)

(Testable)

PI 2Y LX 2Y NA RV-07 X-201H C-7 2

AC 18 CK SA C

FC Q

Forward flow (45)

(SH.1)

(Testable)

PI 2Y LX 2Y NA RV-07 X-201J C-7 2

AC 18 CK SA C

FC Q

Forward flow (45)

(SH.1)

(Testable)

PI 2Y LX 2Y NA RV-07 X-201K C-7 2

AC 18 CK SA C

FC Q

Forward flow (45)

(SH.1)

(Testable)

PI 2Y LX 2Y NA RV-07 X-212A A-8 2

AC 20 CK SA C

FC Q

Forward flow (45)

(SH.1)

PI 2Y LJ 2Y 7.89 SLF1 X-212B A-7 2

AC 20 CK SA C

FC Q

Forward flow (45)

(SH.1)

PI 2Y LJ 2Y 7.89 SLM 3-68

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 REVISION: E9 80STCM EDISON COMPANY P&ID: M-227 SHEET 2 of 2 REVISION: E7 SYSTEM: CONTAINMENT ATMOSPHERE COTROL (45) & (9)

IST Program Revision 18 2/5/88 l.

Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor Class Cat Size Tvoe Tvoe Position Ret.

Frea Time (s)

Leakaoe Reauest Notes 5033A D-7 2

A 1

GL A0 0

FE Q

(9)

(SH.2)

ST Q

10 (C)

FS Q

Closed PI 2Y U

2Y 7.89 SLM 50338 C-6 2

A 4

GA A0 C

FE Q

(9)

(SH.2)

ST Q

10(C)

FS Q

Closed PI 2Y U

2Y 7.89 SLM 5033C D-6 2

A 1

GL A0 0

FE' Q

(9)

(SH.2)

ST Q

10(C)

FS Q

Closed PI 2Y U

2Y 7.89 SLM 3-69 f

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 REVISION: E9 BOSTON EDISON COMPANY P&ID: M-227 SHEET 2 of 2 REVISION: 67 SYSTEM: CONTAINMENT ATMOSPHERE C01ROL (45) & (9)

IST Program Revision is 2/5/88 Vstve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor Class Cat Size Tvoe Type Posi ti on Ret.

Free Time (s)

Leakaae Reauest Notes 503SA E-3 2

A 8

BF A0 C

FE Q

(45)

(SH.1)

ST Q

5(C)

FS Q

Closed PI 2Y U

2Y 7.89 SLM 50358 E-2 2

A 8

BF A0 C

FE Q

(45)

(SH 1)

ST Q

5 (C)

FS Q

Closed PI 2Y U

2Y 7.89 SLM 5036A C-3 2

A 8

BF A0 C

FE Q

(45)

(SH.1)

ST Q

5(C)

FS Q

Closed PI 2Y U

2Y 7.89 SLM 50368 C-2 2

A 8

BF A0 C

FE Q

(45)

(SH.1)

ST Q

5(C)

FS Q

Closed PI 2Y U

2Y 7.89 SLM 5040A B-8 2

A 20 BF A0 C

FE Q

(45)

(SH.1)

ST Q

30(0/C)

FS Q

Open PI 2Y U

2Y 7.89 SLM 5040B B-7 2

A 20 BF A0 C

FE Q

(45)

(SH.1)

ST Q

30(0/C)

FS Q

Open PI 2Y U

2Y 7.89 StM

$041A C-8 2

A 2

GL A0 C

FE Q

(45)

(SH.2)

ST Q

10(C)

FS Q

Closed PI 2Y U

2Y 7.89 SLM 3-70 l

)

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 REVISION: E9 BOSTON EDISON COMPANY P&ID: M-227 SHEET 2 of 2 REVISION: E7 SYSTEM: CONTAINMENT ATMOSPHERE COTROL (45) & (9)

IST Program Revision.18 2/5/88 Volve P&ID ISI Valve Valve Valve Actuator Normal Test Test Mar Stroke Max Relief N2nt>er Coor Class Cat Sire Twee Tvoe Position Ret.

Frea Time (s)

Leakaae Reauest Notes _

5041B C-8 2

A 2

GL A0 C

FE Q

(45)

(SH.1)

ST Q

10(C)

FS Q

Closed PI 2Y U

2Y 7.89 SUI 5042A D-8 2

A 8

BF A0 C

FE Q

(45)

(SH.1)

ST Q

5(C)

F5 Q

Closed PI 2Y U

2Y 7.89 SLM 50428 D-8 2

A 8

BF A0 C

FE Q

(45)

(SH.1)

ST Q

5(C)

FS Q

Closed PI 2Y U

ZY 7.39 SLM 5043A E-7 2

A 2

GL A0 C

FE Q

(45)

(SH.1)

ST Q

10(C)

FS Q

Closed PI 2Y

_W 2Y 7.89 SLM 5043B E-7 2

A 2

GL A0 C

FE Q

(45)

(SH.1)

ST Q

10(C)

FS Q

Closed PI 2Y U

2Y 7.89 SLM 5044A F-7 2

A 8

BF A0 C

FE Q

(45)

($H.1)

ST Q

5(C)

FS Q

Closed PI ZY U

2Y 7.89 SLM 5044B F-7 2

A 8

BF A0 C

FE Q

(45)

(SH.1)

ST Q

5 (C)

FS Q

Closed PI 2Y U

2Y 7.89 StM 3-71

TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 A M NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-227 SHEET 1 of 2 REVIS'ON: E9 BOSTON EDISON COMPANY P&ID: M-227 SHEET 2 of 2 REVISION: E7 SYSTEM: CONTAINMENT ATMOSPH8[RE COTROL (45) & (9)

IST Program Revision 15 2/5/88 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor Class Cat Sire Tvoe Twoe Position Ret.

Frea Tiswis)

Leakaae Reauest Notes 5046 B-6 2

A 1

GL A0 C

FE M4 Esempt (45)

(SH.1)

ST NA Exegt FS NA Esempt U

2Y 7.89 SLM 5081A G-6 2

A 1

GA 50 C

FE Q

(45)

(SH.14 ST Q

2(C)

FS Q

Closed PI 2Y U

2Y 7.89 SLM 50818 G-6 2

A 1

GA 50 C

FE Q

(45)

(SH.1)

ST Q

2(C)

FS Q

Closed PI 2Y U

2Y 7.89 SLM 5082A G-6 2

A 1

GA 50 C

FE Q

(45)

(SH.1)

ST Q

2(C)

FS Q

Closed PI 2Y U

2Y 7.89 SLM 5082B G-6 2

A 1

GA 50 C

FE Q

(45)

(SH.1)

ST Q

2(C)

FS Q

Closed PI 2Y U

2Y 7.89 SLM 5083A G-7 2

A 1

GA 50 C

FE Q

(45)

(SH.1)

ST Q

2(C) is Q

Closed PI 2Y U

2Y 7.89 SLM 5083B G-7 2

A 1

GA S0 C

FE Q

(45)

(SH.1)

ST Q

2(C)

FS Q

Closed PI 2Y U

2Y 7.89 SLM 3-72

TABLE INSERVICE VALVE TES1ING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-227 SHEET 1 of 2 REVISION: E9 80STON EDISON COMPANY P&ID: M-227 SHEET 2 of 2 REVISION: E7 SYSTEM: CONTAINMENT ATM0 SPHERE COTROL (45) & (9)

IST Program Revision 15 2/S/88 Vsive P&ID ISI Valve Valve Valve Actuator Normal

. Test Test Max Stroke Max Relief Number Coor Class Cat Size Twoe Tvoe Position Rant.

Frea Time (si Leakaae Reevest Notes 5084A H-7 2

A 1

GA S0 C

FE Q

(45)

(SH.1)

ST Q

2(C)

FS Q

Closed PI 2Y U

2Y 7.89 SLM 5084B H-7 2

A I

GA SO C

FE Q

(45)

(SH.1)

ST Q

2(C)

FS Q

Closed 1

PI 2Y U

2Y 7.89 SLM 5085A E-7 2

A 1

GA SO C

FE Q

(9)

(SH.2)

ST Q

2(C)

FS Q

Closed PI 2Y U

2Y 7.89 SLM 5085B D-7 2

A 1

GA SO C

FE Q

(9)

(SH.2)

ST Q

2(C)

F5 Q

Closed PI 2Y U

2Y 7.89 SLM 5086A E-7 2

A 1

GA SO C

FE Q

(9)

(SH.2)

ST Q

2(C)

FS Q

Closed PI 2Y U

2Y 7.89 SLM 50868 D-7 2

A 1

GA 50 C

FE Q

(9)

(SH.2)

ST Q

2(C) l FS Q

Closed PI 2Y U

2Y 7.89 SLM 5087A E-8 2

A 1

GA 50 C

FE Q

(9) iSH.2)

ST Q

2(C)

FS Q

Closed PI 2Y U

2Y 7.89 SLM 3-73

-- f.-

'_~

,, $/

TABLE ENSERUICE VALVE'TESTI23 FROGRAM _.

ISI CLASS 1, 2. 3 AiG NC VALVES PILGRIM NUCLEAR MWER STATION P&ID: M-227 SHEET 1 of 2 REVISION: (9

- BOSTON EDISON COMPAIK P&I6; M-227 S;iELT 2 of 2 REVISION: E7 SYSTEM: CONTAINMENT ATMOSPHERE COTROL (45) & (9)

IST Program Revision 18 2/5/88

_V;1oc P&ID ISI Valve Valve Valve Actuator Normal Test' Test Max Stroke Max Relief

'I= umber Coor Ciass Cat Size Tvoe Twoe Posi tion R< int.

Free Time (s)

Leakaoe Reauest

' Notes 5087B D-8 2

A i

GA 50 C

• E Q

(9)

(SH.2)

ST Q

2(C)

G Q

Ond

~M 2Y U '

2Y 7.89 SLM

~

508SA E-7 2

A 1

GA 50 C

FE Q

f (9)

(SH.2)

S'..

0 2(C)

T Q

Closed PI 2Y LJ 2Y 7.89 SLM 5088B D-7 2

A 1

GA 50 C

FE -

Q (9)

(SH.2)

ST Q

2(C)

FS Q

Closed PI 2Y

+

U 2Y 7,99 '>LM 4

Y--*.

m-s v,

i s

. j

=_

--s 3-74 i

s y w -- w y

w

-y 3

y w t

r-m

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 REVISION: E9

- BOSTON EDISON COMPANY SYSTEM: COMPRESSED AIR (31)

IST Program Revision 18. 2/5/88 Valve P&ID ISI Valve Valve Valve Actuator-Normal Test Test Max Stroke Max Relief.

S Number' Coor Class Cat Sire Tvoe Tvoe-Posi tion Rant.

Frea Time (s)

Leakaoe Reauest Notes 430A B-8 3

C 1

CK SA 0

FC 0

Forward flew 430B B-7 3

C 1

CK SA O

FC 0

Forward flow 434 B-6 2

'AC 1

CK SA 0

FC NA Emespt '

l a

LJ 2Y 7.895LM 1

4

..- [

C i

i J

.,* y ', _/'. /

7

e g

n 7

A y

e

/

i

.h n-9 d xy~

'f J

_ - ~ ~

.p r'-

V r

j e

j

'j u,

/

+

- /

~

~

y

-f

.,e f

J

+

,f ~~_ f 3 ;;

y,

~-

~.

~~.

/,_

.N *

,l.

W

.,2

)

g g

~

s W

y

[,

f f

N

.Lar* r

[-

p s

_m, nr

.. ~,

. ~.

W w

s. ? '

.,.~

m.

~.

3-75

'f.

}

- r

'd 4

j

\\

f

') j,)

.l.

/'.+,

w

, 1

.9 y

}'

~%.

// -

f.,.:.",

Q s

g

-- p

..---y.

s'

~

' TAB Q' b

,. 7 7 3

g,y. -y.

y

?--

'U

^

'V O'

~

y y

.,.<; y

'/

-INSERVJCE VALVE TEST!ty PROGRAM ~

.J 2,

- s;y

_.- f # A,

' ~~ " i " 3 g.s,,~

~

'- Mr e

y, y.

-s p

ISI'C( ASS 1, 2, 3 AND NC VALVES

}

.q

_r r 7; #

qd

-Y s-PILGRIM NUCLEAR POWER STATION O~.

-> J - a P&ID: M-227 SHEET 2 of 2 REVISION: E7

,I ~ '

isOSTON EDISON COMPANY'

. SYSTEM: flITROGEN SUPPLY (9) 14f Program Revision lB ~-2/5/08' f

,. ~

^ 3^:

. p

~

j, 1-,*

2 l Q Valva P&ID IST Valve Valve Valve Actuator No mai.

Test Test flax Stroke

?!a ',

Relief i1C

[4W7jdce Class-Cat Size Tvoe Tvoe Posi tion._ Ret.

Frea-, T N fs)'

Lukaae 'Reauest Notes'

/ 2" 7~

340 f -; -

2

.AC 1

CK SA 0

'FC

. RO

~RV-9 Reverse flow.

17 2Y 7.895LM 241 0-6 2

AC 1

CK SA 0

TCs RO

-RV-9 Reverse flow

~

~

[

_Q 2Y 7.89SU1,_-

7

/

/

f_-

- ~/

m c.

.:2 - j.

y

.s f

/

.s i

/

i

).

^^

j.

- r d

4 3-76

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 REVISION: E9 BOSTON EDISON COMPANY SYSTEM: COMPRESSED AIR (31)

IST Program Revision 18 2/5/88 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor (lass Cat Sire Tvoe Tvoe-Position Rant.

Frea Time (s)

Leakaoe Reauest-Notes 430A B-8 3

C 1

CK SA 0

FC 0

Forward flow 4308 B-7 3

C 1

CK

'SA 0

FC 0

Forward flow 434 B-6 2

AC 1

CK SA 0

FC NA Exempt LJ 2Y 7.895LM 3-75 m.-

Y8 N 8 A/

P S M/

O2 s

d d

d d

C e

e e

e e

t s

s s

s N

o o

o o

o O

N l

l l

l S 8 C

C C

C I 1 DE n o Ni O s T i S v O e t

B R f s e e m

i u a

l c

r e e g

R R or M

M M

M P

e_

L t

L L

T a

5 5

5 5

S a

9 9

9 9

8 8

8 8

I k

x a a e 7

7 7

7 ML M

S e

A E N k )

R VO o s L I r(

)

)

)

)

A T t e C

C C

C R

V A S m

(

(

(

(

P T

i 0

0 0

0 CS x T 2

2 2

2 G

N a

N R

M I

D E T

N W S

AO E E P

t a L T 3

s e QQQY Y QQQYY QQQYY QQQYY e r 22 2 2 22 22

,R B

A T F A E T V 2E L

L A

,C V

1 U N

t t E

5 s m ET SI J ET SI J ETSI J ETSI J C

S M e a F SF P L F SF P L F SF P L F S F P L I

AI T R 7

V L R R

CG 7

E L

n S

I I o

3 N

S P l i I

I at mi C

C C

C r s o o N P ro tau e t o 0

0 0

0 c v A

A A

A AT ev e l o G

G G

G a v P

P P

P VT ev e l

r 2

2 2

2 ai

)

V S 02(

e N

v 9O l t A

A A

A E I a a T

VC C

E N L O L s

I O s

S C I a 2

2 2

2 I

S l VE I C E T R SAW D r 2 D I o 6

6 6

6 3 A

& o 2 R P C G

G D

D

-M A

8 A

8 M

e r 1

1 7

7

E v e 1

1 1

1 D T l b 0

0 0

0 I S a m 7

7 7

7

& Y V u P S N

TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-239 SHEET 1 of 3 REVISION: E4 BOSTON EDISON COMPANY P&ID: M-239 SHEET 2 of 3 REVISION: E2 SYSTEM: POST ACCIDENT SAMPLING + H2+O2 ANALYZER SYSTEM (5065)

IST Program Revision IB

'2/5/88 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor Class Cat Size Tvoe Tvoe Position Rant.

Frea Time (s)

Leakage Recuest Notes llA B-6 2

A 1

GL S0 C

FE Q

(SH.1)

ST Q

2(C)

RV-08 FS Q

Closed PI 2Y LJ 2Y 7.895LM 13B B-3 2

A 1

GL SO O

FE Q

(SH.1)

ST Q

2(C)

RV-08 FS Q

Closed PI 2Y LJ 2Y 7.89SLM 14A B-6 2

A 1

GL SO O

FE Q

(SH.1)

ST Q

2(C)

RV-08 FS Q

Closed PI 2Y LJ 2Y 7.895LM 158 B-3 2

A 1

GL SO C

FE Q

(SH.1)

ST Q

2(C)

RV-08 FS Q

Closed PI 2Y LJ 2Y 7.895LM 18A B-6 2

A 1

GL SO C

FE Q

(SH.1)

ST Q

2(C)

RV-08 FS Q

Closed PI 2Y LJ 2Y 7.895LM 20B B-4 2

A 1

GL SO O

FE Q

(SH.1)

ST Q

2(C)

RV-08 FS Q

Closed PI 2Y LJ 2Y 7.895LM 3-78

TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-239 SHEET 1 of 3 REVISION: E4 BOSTON EDISON COMPANY P&ID: K-239 SHEET 2 of 3 REVISION: E2 SYSTEM: POST ACCIDENT SAMPLING + H2+O2 ANALYZER SYSTEM (5065)

IST Program Revision 18 2/S/88 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief I

Number Coor Class Cat Size Tvoe Tvoe Position Rant.

Frea Time (s)

Leakaoe Reauest Notes 21A B-6 2

A 1

GL SO O

FE Q

(SH.1)

ST Q

2(C)

RV-08 FS Q

Closed I

PI 2Y W

2Y 7.895LM 22B B-4 2

A 1

GL 50 C

FE Q

(SH.1)

ST Q

2(C)

RV-08 FS Q

Closed l

PI 2Y W

2Y 7.895LM 24A B-6 2

A 1

GL SO O

FE Q

l (SH.1)

ST Q

2(C)

RV-08 l

FS Q

Closed PI 2Y W

2Y 7.895LM 258 B-4 2

A 1

GL S0 C

FE Q

(SH.1)

ST Q

2(C)

RV-08 FS Q

Closed PI 2Y W

2Y 7.895LM 26A B-6 2

A 1

GL S0 C

FE Q

(SH.1)

ST Q

2(C)

RV-08 FS Q

Closed j

PI 2Y l

W 2Y 7.895LM 278 B-3 2

A 1

GA S0 C

FE Q

(SH.1)

ST Q

2(C)

RV-08 FS Q

Closed PI 2Y W

2Y 7.89SLM 3-79

TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-239 SHtTT 1 of 3 REVISION: E4 BOSTON EDISON COMPANY P&ID: M-239 SHEET ? of 3 REVISION: E2 SYSTEM: POST ACCIDEN: %MPLING + H2+O2 ANALYZER SYSTEM (5065)

IST Program Revision 18 2/5/88 ulve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke.

Max Relief Number Coor Class Cat Sire Tvoe Tvoe Position Rant.

Frea Time (s)

Leakaae Reauest Notes 31B C-4 2

A 1

GL SO C

FE Q

(SH.1)

ST Q

2(C)

RV-08 FS Q

Closed PI 2Y W

2Y 7.895LM 33A C-6 2

A 1

GL SO O

FE Q

(SH.1)

ST Q

2(C)

RV-08 FS Q

\\

Closed PI 2Y W

2Y 7.895LM 358 C-4 2

A 1

GL S0 C

FE Q

(SH.1)

ST Q

2(C)

RV-08 FS Q

Closed PI 2Y W

2Y 7.895LM 37A C-6 2

A 1

GL SO O

FE Q

(SH.1)

ST Q

2(C)

RV-08 FS Q

Closed PI 2Y W

2Y 7.895LM 63 G-7 1

A 1

GL S0 C

FE Q

(SH.2)

ST Q

2(C)

RV-08 FS Q

Closed PI 2Y W

2Y 7.895LM 64 G-6 1

A 1

GL S0 C

FE Q

(SH.2)

ST Q

2(C)

RV-08 FS Q

Closed PI 2Y W

2Y 7.895LM 3-80 L

.-s TABLE' INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-239 SHEET 1 of 3 REVISION: E4 BOSTON EDISON COMPANY P&ID: M-239 SHEET 2 of 3 REVISION: E2 SYSTEM: POST ACCIDENT SAMPLING + H2+02 ANALYZER SYSTEM (5065)

IST Program Revision 18 2/5/88 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor Class Cat Size Tvoe Tvoe Position Rant.

Frea Time (s)

Leakaoe Request Notes 71 F-6 2

A 1

GA S0 C

FE Q

(SH.2)

ST Q

2(C)

RV-08 FS Q

Closed PI 2Y U

2Y 7.895LM 72 F-6 2

A 1

GA SO C

FE Q

(SH.2)

ST Q

2(C)

RV-08 FS Q

Closed PI 2Y U

2Y 7.895tM 77 E-6 2

A 1

GA SO C

FE Q

(SH.2)

ST Q

2(C)

RV-08 FS Q

Closed PI 2Y LJ 2Y 7.895LM 70 E-6 2

A 1

GA S0 C

FE Q

(SH.2)

ST Q

2(C)

RV-08 FS Q

Closed PI 2Y U

2Y 7.89SLM 85 G-6 1

A 1

GA 50 C

FE Q

(SH.2)

ST Q

2(C)

RV-08 FS Q

Closed PI 2Y LJ 2Y 7.895LM 86 G-6 1

A 1

GA S0 C

FE Q

(SH.2)

ST Q

2(C)

RV-08 FS Q

Closed PI 2Y LJ 2Y 7.895LM 3-81

TABLE INSERVICE VALVE TESTING PROGRAM '

ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-239 SHEET 1 of 3 REVISION: E4 BOSTON EDISON COMPANY P&ID: M-239 SHEET 2 of 3 REVISION: E2 SYSTEM: POST ACCIDENT SAMPLING + H2+O2 ANALYZER SYSTEM (S06S)

IST Program Revision IB -2/S/88-Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor Class Cat Size Tvoe Tvoe Position Rant.

Frea

' Time (s)

Leakaae Reauest Notes 91 A-S 2

A 1

GA A0 0

FE Q

(SH.1)

ST Q

2(C)

RV-08 FS Q

Closed PI 2Y LJ 2Y 7.89SLM 92 A-5 2

A 1

GA A0 0

FE Q

(SH.1)

ST Q

2(C)

RV-08 FS Q

Closed PI 2Y LJ 2Y 7.895LM 3-82 m.

TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-241 SHEET 1 of 2 REVISION: E12 P&ID: M-241 SHEET 2 of 2 REVISION: E8 BOSTON EDISON COMPANY SYSTEM: RESIDUAL HEAT REMOVAL SYSTEM (1001)

IST Program Revision 18 2/S/88 Vs1ve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor Class Cat Size Tvoe Tvoe Posi tion Rant.

Frea Time (s)

Leakaae Request Notes 2A D-6 2

C 2

CK SA C

FC Q

Forward flow -

(SH.2) 2B D-3 2

C 2

CK SA C

FC

'Q Forward flow (SH.2) 2C G-6 2

C 2

CK SA C

FC Q

Forward flow (SH.2) 2D G-3 2

C 2

CK SA C

FC Q

Forward flow (SH.2) 7A D-5 2

B 18 GA 70 0

FE Q

(SH.2)

ST Q

90(0/C)

PI 2Y 78 D-4 2

B 18 GA M0 O

FE Q

(SH.2)

ST Q

90(0/C)

PI 2Y 7C F-S 2

B 18 GA M0 O

FE Q

(SH.2)

ST Q

90(0/C)

P' 2Y 70 F-4 2

B 18 GA M0 O

t r.

Q (SH.2)

ST Q

90(0/C)

PI 2Y 16A F-7 2

B 18 GL M0 C

FE Q

(SH.2)

ST Q

99(0)

PI 2Y 168 E-2 2

8 18 GL M0 C

FE Q

(SH.2)

ST Q

99(0)

PI 2Y 18A G-6 2

B 3

GA M0 O

FE Q

(SH.2)

ST Q

20(0/C)

PI 2Y 18B G-3 2

B 3

GA M0 O

FE Q

(SH.2)

ST Q

20(0/C)

PI 2Y 3-83 o

v

. TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-241 SHEET 1 of 2 REVISION: E8 BOSTON EDISON COMPANY M-241 SHEET 2 of 2 REVISION: E8 SYSTEM: RESIDUAL HEAT REMOVAL SYSTEM (1001)

IST Program Revision IB 2/S/88 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor Class Cat Size Tvoe Tvoe Position Rant.

Frea Time (s)

Leakaoe Recuest Notes al B-3 2

A 4

GA M0 C

FE Q

(SH.1)

ST Q

20(C)

PI 2Y u

2Y 2.OrpM 22A F-8 2

C 1

RL SA C

RT SY '

(SH.1) 22B F-2 2

C 1

RL SA C

RT SY (SH.1) 23A G-6 2

A 10 GA M0 C

FE Q

(SH.1)

ST Q

14(C)

PT 2Y U

2Y 7.895Ui 238 G-4 2

A 10 GA M0 C

FE _

Q (SH.1)

ST Q

14(C)

PI 2Y W

2Y 7.895LM 26A G-S 2

A 10 GA M0 C

FE Q

(SH.1)

M Q

14(C)

PI 2Y U

2Y 7.895LM 268 G-4 2

A 10 GA M0 C

FE Q

(SH.1)

ST Q

14(C)

PI 2Y W

2Y 7.895LM 28A F-6 2

A 18 GL MO O

FE Q

(SH.1)

ST Q

30(0/C)

PI 2Y U

2Y 7.895LM 288 F-4 2

A 18 GL M0 O

FE Q

(SH.1)

ST Q

30(0/C)

PI 2Y W

2Y 7.895LM 3-84

TABLE' INSERVICE VALVE T' STING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-241 SHEET 1 of 2 REVISION: E12 P&ID: M-241 SHEET 2 of 2 REVISION: E8 BOSTON EDISON COMPANY SYSTEM: RESIDUAL HEAT REMOVAL SYSTEM (1001)

IST Program Revision 18 2/5/88 Valve P&ID ISI Yalve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor Class Cat Size Tvoe Tvoe Position Rant.

Frea Time (s)

Leakaae Reauest Notes 29A E-6 1

A 18 GA M0 C

FE CS RV-46 (SH.1)

ST CS 30(0/C)

RV-46 PI 2Y U

2Y 7.895LM LP 2Y 5.0GPM 29B E-4 1

A 18 GA M0 C

FE CS RV-46 (SH.1)

ST CS 30(0/C)

RV-46 PI 2Y U

2Y 7.895LM LP 2Y 5.0GPM 32 B-3 2

A 4

GA MD C

FE Q

(SH.1)

ST Q

20(C)

PI 2Y LX ZY 2.0GPM 34A F-7 2

A 12 GA M0 C

FE Q

(SH.1)

ST Q

30(0/C)

PI 2Y U

2Y 7.895LM 34B F-3 2

A 12 GA M0 C

FE Q

(SH.1)

ST Q

30(0/C)

PI 2Y U

2Y 7.895LM i

3-85 i

TABLE

' INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-241 SHEET 1 of 2 REVISION: E12 P&ID: M-241 SHEET 2 of 2 REVISION: E8 BOSTON EDISON COMPANY SYSTEM: RESIOUAL HEAT REMOVAL SYSTEM (1001)

IST Program Revision 13 2/5/88 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Numt>e r Coor Class Cat Size Tvoe Tvoe Position Rant.

Frea Time (s)

Leakaoe Recuest Notes 36A E-7 2

B 12 GL M0 C

FE Q

(SH.1)

ST Q

30(0/C)

PI 2Y 368 E-3 2

B 12 GL M0 C

FE Q

(SH.1)

ST Q

30(0/C)

PI 2Y 37A E-7 2

A 6

GL M0 C

FE Q

(SH.1)

ST Q

33(0/C)

PI 2Y LJ 2Y 7.895LM 378 E-3 2

A 6

GL M0 C

FE Q

(SH.1)

ST Q

33(0/C)

PI 2Y LJ 2Y 7.89 SIN 47 C-5 1

A 20 GA M0 C

FE CS RV-12 (SH.1)

ST CS 30(C)

RV-12 PI 2Y U

2Y

~

7.895LM LP 2Y 5.0GPM 50 0-5 1

A 20 GA M0 C

FE CS RV-12 (SH.1)

ST CS 30(C)

RV-12 PI 2Y U

2Y 7.89SLM LP 2Y 5.0GPM 59 H-6 2

C 1

RL SA C

RT SY (SH.1) 3-86

~1

Y 8 N8 w

w w

w w

w w

w A/

o o

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o o

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d d

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r r

r r

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a a

a a

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w w

w w

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r r

r r

r v

v I 1 o

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R VO o s G

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C C

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f f o oT A

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F F S P L F S P L I

AI T R V

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n S

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M S

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t a L T 3

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t t P

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F F

F F

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L R 9

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n 3

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I at mi C

C C

C 0

0 C

C C

0 0

C r s o o N P ro tau e 0

0 A

A A

A A

A A

A A

A t o M

M S

S S

S S

S S

S S

S c v AT

)

e 1

v e 0

l o A

A L

L K

K K

K K

K K

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a v G

G R

R S

S C

C C

C C

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E E M

e

: E v e T

l z

0 0

2 2

1 1

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0 2

2 6

N NS ai 1

1 1

1 OO Y VS I I S SS I I L V V A e

E E V v

R R O l t M

a a A

A C

C C

C C

C C

C C

C_

2 2 E VC A

A R

f f o oT A

s 1 2E s

H I a T T S l 1

1 2

2 1

1 2

2 2

2 2

2 E E L I C E E A H H U S S D I

D r 1 1 S I

o 4 4

6 7

4 4

5 7

9 7

7 5

4 4 E

& o 2 2 R P C D

B E

B C

C E

E E

D B

E M M M

e r E

v e A

8 A

B A

B A

8 A

8 D

T l b 5

5 8

8 1

1 5

6 6

2 2

4 I

S a m 2

2 2

2 3

3

)3 3

1 1

1 Y

V u 2

2 2

P S

N

TABLE INSLRVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-243 SHEET 1 REVISION: E-6 BOSTON EDISON COMPANY P&ID: M-244 SHEET 2 REVISION: E-6 SYSTEM: HIGH PRESSURE COOLANT INJECTION (2301)

IST Program Revision 18 2/5/88 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor Class Cat Sire Tvoe Tvoe Position Rant.

Frea Timeis)

Leakaoe Reauest Notes HD-1 E-ll 2

B 10 GA H0 C

FE Q

(2301-23)(SH.2)

ST Q

30(0),5(C)

FS Q

Closed PI 2Y HD-2 E-11 2

NA 10 GV H0 C

FE Q

(2301-24)(SH.2)

ST Q

NA RV-16 FS Q

Closed PI 2Y 3

F-13 2

B 10 GA HO C

FE Q

(SH.1)

ST Q

20(0)

PI 2Y 4

D-4 1

A 10 GA M0 O

FE Q

(SH.1)

ST Q

25(0/C)

PI 2Y LJ 2Y 7.895LM S

D-6 1

A 10 GA M0 O

FE Q

(SH.1)

ST Q

25(0/C)

PI 2Y LJ 2Y 7.895LM 6

C-10 2

B 16 GA M0 0

FE Q

(SH.1)

ST Q

30(0/C)

PI 2Y 7

H-5 1

AC 14 CK SA C

FC CS RV-15 Forward flow (SH.1)

LP 2Y 5.0GPM 0

H-5 l

A 14 GA M0 C

FE CS RV-46 (SH.1)

ST CS 25(0/C)

RV-46 PI 2Y LP 2Y 5.0GPM tJ 2Y 7.895LM 9

H-6 2

B 14 GA M0 O

FE Q

(SH.1)

ST Q

25(0)

PI 2Y 3-90

TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-243 SHEET 1 REVISION: E6 BOSTON EDISON COMPANY P&ID: M-243 SHEET 2 REVISION: E6 SYSTEM: HIGH PRESSURE COOLANT INJECTION (2301)

IST Program Revision IB 2/5/88 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor Class Cat Size Tvoe Tvoe Position Rant.

Frea Time (s)

Leakaoe Reauest Notes 10 E-6 2

B 10 CL M0 C

FE Q

(SH.1)

ST Q

22(0)

PI 2Y 14 F-8 2

8 4

GL M0 C

FE Q

(SH.1)

ST Q

10(0/C)

PI 2Y 20 D-10 2

B 16 CK SA C

FC Q

Forward flow (SH.1) 26 E-5 1

AC 1

SK SA 0

FC 11 0 RV-42 Reverse flow (SH.1)

LX 2Y 0.5GPM 29 K-14 2

B 1

GL A0 C

FE Q

(SH.1)

ST Q

20(C)

FS Q

Closed PI 2Y 3-91

TABLE-INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-243 SHEET 1 REVISION: E6 BOSTON EDISON COMPANY P&ID: M-243 SHEET 2 REVISION: E6 SYSTEM: HIGH PRESSURE COOLANT INJECTION (2301)

IST Program Revision 18 2/5/88 Vaive P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor Class Cat Sire Tvoe Tvoe Position Rant.

Frea Time (s)

Leakaae Recuest Notes 33 M-1 2

A 4

GA M0 O

FE Q

(SH.1)

ST Q

30(C)

PI 2Y LJ 2Y 7.895LM 34 L-2 2

A 4

GA MD 0

FE Q

(SH.1)

ST Q

30(C)

PI 2Y LJ 2Y 7.895LM 35 E-9 2

B 16 GA MO C

FE Q

(SH.1)

ST Q

30(0/C)

PI 2Y 36 M-5 2

B 16 GA M0 C

FE Q

(SH.1)

ST Q

30(0/C)

PI 2Y 39 M-6 2

C 16 CK SA C

FC R0 RV-31 Forward flow (SH.1) 43 K-5 2

C 4

CK SA C

FC Q

Forward flow (SH.11 45 J-4 2

AC 20 CK SA C

FC Q

Forward flow (SH.1)

LX 2Y 7.895LM 68 K-ll 2

D 16 RD SA C

RD NA Non-Testable (SH.1) 3-92

l e

w w

w w

w l

o o

o o

o Y

8 s

b l

l l

l l

N 8

e a

f f

f f

f A

/

t t

d P

5 o

s d

d e

d d

e M

/

N e

r r

s r

r s

a a

r a

a o

O 2

T-w w

e w

w l

C n

r r

v r

r C

N o

o o

e o

o O

N F

F R

F F

S 8

I 1

D E

no t

N i

f s O

s e e 2

1 1

4 T

i i u 4

4 4

3 S

v l a O

e e e Y

V V

V B

R R R R

R R

R mar e

g a

M M

o a

L P

r k

5 G

P x a 9

5 a e 8

0 T

ML S

7 I

M S

e A

E N k )

R VO o s G

L I r(

A O

AT t e N

R V A S m P

T i

CS xT G

N a

N R

M I

D E T

N W S

A O EE P

t a L T 3

s e A

QY Q

OY S

S QQQY e r N

2 R 2 C

C 2

,R B

A T F AE T V 2 E L

L A

,C V

1 U N

t t e O CX C

CX C

C CT SI E

S s

R F L F

F L F

F F SF P C

S M e

I AI T R 3

V L R 9

R CG E

L n

S I I o

3 N

S P l i I

I at mi O

r s C

L C

0 C

C C

o o

/

N P C

ro tau e A

A A

A A

A 0

t o S

S S

S S

S A

c v

)

AT 1

03 e

2 v e

(

l o

D C

K K

K K

L a v R

S C

S C

C G

N V T O

I T

e C

v e 66E l

z 6

0 4

1 3

3 1

E E J ai 1

2 N

VS I

N NT OON e

I I A v

S S L l t D

C C

C C

C 8

I I O a a A

A V VO VC E E C R R ER s

1 2U s

S I a C

2 2

1 2

2 2

T T S Sl N

E E E I C E E R H H P

)

)

)

)

)

)

)

S S 1

1 2

1 1

1 1

H D r 2

0 3 3 G I o 1 H 3 H 8H 5H 1 H 1 H 1 H S

S S

- S F-M(

M(

K(

4 4 I

& o S

S S

2 2 H P C K(

J (

K(

(

M M M

e r

: E v e D D T l b 9

4 5

0 2

3 3

I I S a m 6

7 7

2 3

3 1

& & Y V u 2

2 2

3 P P S N

9

TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-245 SHEET 1 REVISION: E7 BOSTON EDISON COMPANY P&ID: M-246 SHEET 2 REVISION: E6 SYSTEM: REACTOR CORE ISOLATION COOLING SYSTEM (1301)

IST Program Revision IB 2/5/88 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor Class Cat Sire Tvoe Tvoe Position Rant.

Frea Time (s)

Leakaae Reauest Notes 1

E-12 2

8 2

GA SO O

FE Q

(SH.2)

ST Q

5(C)

FS Q

Open PI 2Y 2

E-11 2

NA 2

GV H0 0

FE Q

(SH.1)

ST Q

NA RV-39 FS Q

Closed PI 2Y 15A B-6 1

AC 1

SK SA 0

FC RD RV-42 Reverse flow (SH.1)

LX 2Y 0.5GPM 158 B-6 1

AC 1

SK SA 0

FC 11 0 RV-42 Reverse flow -

(SH.1)

LX 2Y 0.5GPM 16 C-6 1

A 3

GA M0 O

FE Q

(SH.1)

ST Q

20(0/C)

PI 2Y LJ 2Y 7.895LM 17 C-7 1

A 3

GA M0 O

FE Q

(SH.1)

ST Q

20(0/C)

PI 2Y LJ 2Y 7.895LM 3-94

l l

I 88/

w w

w w

w 5

o o

o o

o

/

s l

l l

l l

2 e

f f

d f

f f

t e

o d

d s

d d

d N

r r

o r

r r

Y 8

a a

l a

a a

w w

C w

w w

N 1

A r

r r

r r

P n

o o

o o

o M

o F

F F

F F

O i

C s

i N

v O

e t

S R

f s I

e e 1

D m

i u 3

E a

l a

r e e V

N g

R R R

O o

T r

S P

O e

M B

T a

L S

a 5

I k

98 x a a e ML 7

M S

e A

E N k )

R VO o s G

L I r(

)

)

)

)

O AT t e C

C C

)

C R

VA S m

/

/

/

0

/

0 0

0

(

0 P

T i

CS x T

(

(

(

0

(

S N

a 5

5 5

2 0

N R

M 3

5 3

2 I

DE T

N W S

AO E E P

t a L T 3

s e QQY Q

QQY QQY O

QQQY Q

QY Q

QQY B

,R e r 2

2 2

R 2

2 2

AE A

T F T V 2 E L

L A

,C V

1 U N

t t E

S s n ET I C

ET I E T I C

ET SI C

CX C

ET I C

S M e a F SP F

F SP FSP F

F SF P F

F L F

F SP I

AI T R V

L R 5

R CG 9

E L

n S

I I o

3 N

S P l i I

I at mi r s O

C C

C C

C C

C C

O o o NP r

)

o 1

t 0

a 3

u e 0

A D

0 A

0 A

A A

0 1

t o M

S M

M S

A S

S S

M

(

c v AT M

E T

e S

v e Y

l o A

K A

A K

L K

K K

A S

a v G

C G

G C

G C

C C

G VT GN I

e L

v e 7 6O l

r 6

6 6

6 6

1 2

8 2

4 E E O ai C

VS

: N N NO OOI e

I I T v

S S A l t 8

B B

8 C

8 C

C C

8 I I L a a A

VVO VC E E S R R I E

s 1 2 R s

O I a 2

2 2

2 2

2 2

2 2

2 T T C Sl E E I C E E R H H O

)

)

)

)

)

)

)

)

)

)

1 1

1 1

1 S S T 1

1 1

1 1

3 C

D r 1

1 0

56 A I o 1 H 1 H 8H 1 H 9H 1 H 9H 6H 8H 8 H 4 4 E

& o

- S S

- S

- S S

- S S

S S

- S H(

E (

2 2 R P C 0(

D(

L(

D(

L(

K(

J (

J (

MM M

er

: E v e D D T l b 2

3 5

6 7

4 0

1 7

8 I I S a m 2

2 2

2 2

3 4

4 4

4

& & Y V u P P S N

TABLE INSERVICC VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION i

P&ID: M-24S SHEET 1 REVISION: E7 BOSTON EDISON COMPANY P&ID: M-246 SHEET 2 REVISION: E6 SYSTEM: REACTOR CORE ISOLATION COOLING SYSTEM (1301)

IST Program Revision 18 2/S/88 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor Class Cat Sire Tvoe Tvoe Position Rept.

Frea Time (s)

Leakaoe Reauest Notes 49 E-7 1

A 4

GA M0 C

FE CS RV-46 (SH.1)

ST CS 20(0/C)

RV-46 PI 2Y L1 2Y 7.895LM LP 2Y 2.0GPM 50 E-7 1

AC 4

CK SA C

FC CS RV-15 Forward flow (SH.1)

LP 2Y 2.0GPM 53 D-8 2

B 4

GL M0 C

FE Q

(SH.1)

ST Q

21(C)

PI 2Y 60 H-8 2

B 2

GL M0 C

FE Q

(SH.1)

ST Q

10(0),7.5(C)

PI 2Y 61 E-13 2

8 3

GA MD.

C FE Q

(SH.2)

ST Q

21(0)

PI 2Y 62 J-7 2

8 2

GL M0 C

FE Q

(SH.2)

ST Q

13(0)

PI 2Y C3 K-6 3

C 2

CK SA C

FC Q

Forward flow (SH.2) 64 J-6 2

AC 8

SC SA/MA C

FC Q

Forward flow (SH.1)

LX 2Y 7.895LM 9067 H-6 2

C 1

SK SA C

FC CS RV-48 Forward flow iSH.1) 3-96

p-o TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION l

P&ID: M-247 REVISION: E11 BOSTON EDISON COMPANY SYSTEM: REACTOR WATER CLEANUP SYSTEM (1201)

IST Program Revision 18 2/5/88-l Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Nuet>er Coor Class Cat Size Tvoe Tvoe Position Rant.

Free Time (s)

Leakaae Recuest Notes 2

C-2 1

A 6

GA M0 O

FE Q

ST Q

2S(C)

PI 2Y U

2Y 7.895LM 5

C-3 1

A 6

GA M0 0

FE Q

ST Q

25(C)

PI 2Y U

2Y 7.895LM 80 B-9 1

A 4

GL NO O

FE Q

ST Q

30(C)

PI 2Y U

2Y 7.895LM 360 C-3 1

AC 1

SK SA 0

FC RO RV-42 Reverse flow LX ZY 0.5GPM 361 D-3 1

AC 1

SK SA 0

FC R0 RV Reverse flow LX 2Y 0.5GPM x

3-97

J Y8 N 8 A/

w w

w w

P 5 o o o

o M/

l l

l l

O2 s

f f

f f

C e

t d

d d

d N

o r

r r

r O

N a

a a

a S 8 w

w w

w I 1 r

r r

r D

o o o

o E n F

F F

F o

Ni O s T i S v O e t

B R f s e e 9

9 m

i u 1

1 a

l a

r e e V

V g

R R R

R or P

e M

M M

T o

L P

P S

a S

G G

I k

98 5

5 x a a e ML 7

1 1

M S

e A

E N k )

R VO o s G

L I r(

O AT t e R

VA S m P

T i

CS x T G

N a

N R

M I

D E T

N W S

AO E E P

t a L T 3

s e O 0Y QY QY Y

Y Y

Y B

R e r R

R 2 2

2 S

S 0

0 AE

,A T F 1

1 T V 2 E L

L A

,C V

1 U N

t t E

S s n C

CJ CX CX T

T X

X C

S M e a F

F L F L F L R

R E

E I

AI T R 8

V L R R

C G 9

E L

n S

I I o

3 N

S P l i I

I at mi r s C

C C

C C

C C

C o o N P ro t

lau e t o A

A A

A A

A P

P c v S

S S

S S

S E

E AT

)

1 e

0 v e 1

l o K K

K K

L L

H H

1 a v C

C C

C P

R S

S

(

VT M

E e

T v e 5

5, 5

5 5

5 S

l r

1 1

Y ai 1

1 S

VS 1

1 1

1 LOR e

T v

N l t C

C C

C C

C D

D 7 O a a A

A A

E C VC D

N I OU s

I Q s

S I I a 1

1 2

2 2

2 2

2 I L S l V

I C E Y R BDN D r 9A I o 2

1 4

4 4

4 2

2 4 T

& o 2 S P C J

H E

F D

H E

E M

M e r A

B

E v e A

8 A

B D T l b 5

6 3

3 5

5 6

6 I S a m 1

1 4

4 0

0 0

0

& Y V u 1

1 1

1 P S N

1 1

1 1

TABLE INSERVICE VALVE TESTING PROGRAM ISI CASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-250 SHEET 1 of 2 REVISION: E11 BOSTON EDISON COMPANY P&ID: M-250 SHEET 2 of 2 REVISION: E3 SYSTEM: CONTROL ROD DRIVE HYDRAULIC SYSTEM (302)

IST Program Revision 18' 2/S/88 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor Class Cat Size Tvoe Tvoe Position Rant.

Frea Time (s)

Leakaae Reauest Notes 21A G-3 2

8 1

PG A0 0

FE Q

(SH.2)

ST Q

30(0/C)

FS Q

Closed PI 2Y 218 G-7 2

B 1

PG A0 0

FE Q

(SH.2)

ST Q

30(0/C)

FS Q

Closed PI 2Y 22A D-4 2

B 2

PC A0 0

FE Q

(SH.2)

ST Q

30(0/C)

FS Q

Closed PI 2Y 228 D-7 2

B 2

PG A0 0

FE Q

(SH.2)

ST Q

30(0/C)

FS Q

Closed PI 2Y 23A G-3 2

B 1

PG A0 0

FE Q

(SH.2)

ST Q

30(0/C)

FS Q

Closed PI 2Y 238 G-7 2

B 1

PG A0 0

FE Q

(SH.2)

ST Q

30(0/C)

FS Q

Closed PI 2Y 24A D-4 2

B 2

PG A0 0

FE Q

(SH.2)

ST Q

30(0/C)

FS Q

Closed PI 2Y 248 D-7 2

B 2

PG A0 0

FE Q

(SH.2)

ST Q

30(0/C)

FS Q

Closed PI 2Y 3-99

TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES DILGRIM NUCLEAR POWER STATION P&ID: M-250 SHEET 1 of 2 REVISION: E11 BOSTON EDISON COMPANY P&ID: M-250 SHEET 2 of 2 REVISION: E3 SYSTEM: CONTROL R00 DRIVE HYDRAULIC SYSTEM (302)

IST Program Revision IB 2/5/88

~

Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor Class Cat Size Tvoe Tvoe Position R<snt.

Frea Time (s)

Leakane Reauest Notes 114 A-18 2

C 0.5 CK SA C

FC RO RV-21 Forwar11 flow (HCU)

(SH.1) 115 C-19 2

C 0.5 CK SA C

FC RO RV-21 Forward flow (HCU)

(SH.1) 126 8-17 2

B 1

PG A0 C

FE RO RV-21 (HCU)

(SH.1)

ST RO NA RV-21 FS RO RV-21 Goen 127 A-17 2

B

.75 PG A0 C

FE R0 RV-21 (HCU)

(SH.1)

ST RO NA RY-21 FS RO RV-21 Goen 132 C-18 2

D 0.5 RD SA C

RD MA Mon-Testable (HCU)

(SH.1) 138 C-16 2

C 0.5 CK SA 0

FC Q

RV-22 Reverse flow (HCU) fSH.1) s 3-100 m

4

o 2

-q'-?

'f.

~

a u

TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND K VALVES PILGRIM NUCLEAR POW STATION P&ID: M-251 REVISION: E3 BOSTON EDISON COMPANY S'rSTEM: RECIRC. PUMP INSTRUMENTATION (26M '

IST Program Revision 18 2/5/88 Llve P&ID. ISI Valve Valve Val ve Actuator Normal Test Test Max St.-oke

~ Max Relief Numoor Coor Class Cat Size Type Tvoe Position Rgnt.

Frea TimstLs) leakage Request Notes 2-5A 3-1 2

AC 1

~5K SA 0

FC R0 RV-42 Reverse flow

_i LW 2Y 0.5GPM 2-58 D-1 Z

AC 1

SK SA o

FC RO

~

RV42 Reverse flow LX ZY Q,$PM 2-6A D-1 2

AC 1

SK SA 0

FC R0 RV-42 Reverse flow LX 2Y 0.5GPM 2-68 D-1 2

AC 1

SK SA 0

rt RO RV-42

- Reverse flow LX 2Y 0.5GPM F013A C-2 2

AC 0.75 CK SA 0

FC R0 RV-28 Reverse flow

..\\

.x LJ 2Y 7.895LM F013B C-2 2

AC 0.75 CK SA 0

FC R0 RV-28 Reverse flow s

LJ 2Y 7.895LM F017A C-1 2

AC 0.75 CK SA 0

FC R0 RV-28 Reveile flow LJ 2Y 7.895tM F0178 C-1 2

AC

.0.75 CK SA 0

FC R0 RV-28 Reverse flow LJ 2Y 7.89581 I

l I

3-101 s

-w f

-TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1. 2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION PSID: M-252 REVISION: E7 BOSTON EDISON COMPANY SYSTEM: FEEDWATER SYSTEM (6)

IST Program Revision IB 2/5/86 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor Class Cat Size Tvoe Tvoe Position Rant.

Frea Time (s)

Leakage Request Notes 58A E-4 1

AC 18 CK SA 0

FC RO RV-26 Reverse flow LJ 2Y 7.895LM 588 F-4 1

AC 18 CK SA 0

FC RO RV-26 Reverse flow LJ 2Y 7.895LM 62A E-3 1

AC 18 CK SA 0

FC R0 RV-26 Reverse flow LJ 2Y 7.895LM 62B 7-3 1

AC 18 CK SA 0

FC RO RV-26 Reverse flow LJ 2Y 7.895LM 1

k.

s

~_ ' ~,

u s

+

l

,p g.

Am f

w

,Y

~

_/

k n

/

~

.g e.r h

m.

3-102

^

_ 'j.

x

, ^ g..

l

,q

/

s

.w

,4

~[

~

2. AW djt T p.

-Q~

INSERVICE VALVE TESTING PROGRAM

.m

~_.

q; ISI LLAS3 1, 2. 3 AND NC VALVES

'~

i'4.MIM NLf7 LEAP PCVER 3TMION 2

P&ID: M-IS2 REVISION

• E7 BOSTON EDISON COMPANY SYSTEM: REACTOR RECIRCLEATION $YSTEM (202) iSTProgramRevision18 2/5/88

.#~'

'M-N' A

y _ j+

Vm1ve P&ID ISI

. Valve VaNa Valve Actuator Normal Test Test Max Stroke Max Relief

.If

!!ymher Coor Class Cat Size Twoe Tvoe resition Rant.

Frea Timeis)

Leakac-c b guest ~

RMS.e _

5A L-8 1

8 28 GA M0 O

FE CS RVch

~

I ST CS 30(C)

RV-73

- _ ~ _ -

PI 2Y

.y 5B H-E 1

8 28 GA M0 O

FE CS RV-23 ST CS 30(C)

RV-23 2_

PI 2Y j

't

.4f.

3-103

TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-252 REVISION: E7 BOSTON EDISON COMPANY SYSTEM: MAIN STEAM ISOL., ADS & SAFETY RELIEF (203)

IST Program Revision 18 2/5/88-Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor Class Cat Sire Tvoe Tvoe Position Rosnt.

Frea Time (s)

Leakaae Reauest Notes lA G-9 1

A 20 GL A0 0

FE Q

ST Q

5(C)

G Q

Oud PI 2Y U

2Y 5.4285LM 18 E-9 1

A 20 GL A0 0

FE Q

ST Q

5(C)

FS Q

Closed PI 2Y W

2Y 5.4285LM 1C F-7 1

A 20 GL A0 0

FE Q

ST Q

5(C)

FS Q

Closed PI 2Y U

2Y 5.428StM ID F-7 1

A 20 GL A0 0

FE Q

ST Q

5(C)

FS Q

Closed PI 2Y W

2Y 5.4285L5 2A C-ll 1

A 20 GL A0 0

FE Q

ST Q

5(C)

FS Q

Closed PI 2Y U

2Y 5.4285LM 3-104 i

TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2, 3 AND NC VALVES i

PILGRIM NUCLEAR POWER STATION P&ID: M-252 REVISION: E7 BOSTON EDISON COMPANY' SYSTEM: MAIN STEAM ISOL., ADS & SAFETY RELIEF (203)

IST Program Revision is 2/5/88 l

Valve P&ID ISI Valve Valve Valve Actuator Psarmal Test Test Max Stroke Max Relief Number Coor Class Cat Size Tvoe Tvoe Fosition Rant.

Frea Time (s)

Leakaae Reauest Notes-28 E-9 1

A 20 GL A0 0

FE Q

ST Q

5(C)

S Q

Ciud PI 2Y LJ 2Y 5.4285LM 2C F-7 1

A 20 GL A0 0

FE Q

ST Q

5(C)

FS Q

Closed PI 2Y LJ 2Y 5.426SLM 2D F-7 1

A 20 GL A0 0

FE Q

ST Q

5(C)

FS Q

Closed PI 2V LJ 2Y 5.4285LM 3A C-7 1

AC 6

RL/SV A0/SA C

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TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1, 2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M-259 REVISION: EO BOSTON EDISON COMPANY SYSTEM: DIESEL GENERATOR TURBO AIR ASSIST SYSTEM (47)

IST Program Revision 18 2/5/88 Valve P&ID ISI Valve Valve Valve Actuator Normal Test Test Max Stroke Max Relief Number Coor Class Cat Sire Tvoe Tv2e Posi tiott Rant.

Frea Tima(s)

Lea.ipae Reauest Notes i

4569A E4 3

5 1.5 GA 50 C

FE Q

W-45 ST Q

W-45 FS O

W-45 Closed 45698 E-2 3

B 1.5 GA SO C

FE Q

W-45 ST Q

W-45 FS 0

W-45 Closed 4570A F4 3

B 1.5 GA SO C

FE Q

W-45 ST Q

W-45 FS 0

W-45 Closed 45708 E-2 3

8 1.5 GA 50 C

FE Q

W-45 ST Q

W-45 FS 0

W-45 Closed W

3-115

,