ML18102B668

Rev 8 to Inservice Testing Manual for Pumps & Valves Program.

ML18102B668
Person / Time
Site:	Salem
Issue date:	10/01/1997
From:	Binz R, Lake L, Neyhard J Public Service Enterprise Group
To:
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ML18102B667	List: ML18102B666 ML18102B668
References
PROC-971001, NUDOCS 9711170143
Download: ML18102B668 (408)

Text

• Salem Nuclear Generating Station Units 1 & 2 lnservice Testing Manual for

• Pumps & Valves Program Public Service Electric and Gas Company

• Salem Nuclear Generating Station Units 1and2 Inservice Testing Manual for Pumps and Valves lnservice Testing Manual for Pumps and Valves

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• 1* ................ .

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I I Basis Document J. Program Submittal

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Interval 2 Program June 30, 1987 through August 30, 1999 (includes 26 additional months for Salem Unit 2 extended shutdown)

October 1, 1997 Revision 8 Public Service Electric and Gas Company Hancock's Bridge, New Jersey

• Inservice Testing Manual for Pumps and Valves Program Revision 8 Signature Page Revision Summary: Combined "Implementation" Section and "Program" Section into one "Program Submittal" document. Added new IST manual summary, program text, table descriptions, etc. Removed historical copies of the IST Program. Removed historical NRC SER's and PSE&G correspondance.

Historical documents are available on DMS or Topic Search. The IST Program Manager retains copies of these files for information. Revision bars have not been used. The Program Submittal Document is being re-

• issued in it's entirety.

Prepared by:

Reviewed by:

Concurrence by: Louis Lake/~

• I z(. ~

Supervisor - ISl/IST Programs Approved by: A!=r~fl--_ Date:*

Inservice Testing Manual for Pumps and Valves

,. 1.0 Manual Summary Program List of Effective Pages Revision 8 2.0 Program Submittal Text Revision 8 3.0 Inservice Testing Program for Pumps Revision 8 4.0 Inservice Testing Program for Valves Revision 8 Table 1-1, System and P&ID Listing - ASl\1E Systems Revision 8 Table 1-2, System and P&ID Listing - Non-ASl\1E Systems Revision 8 Table 2-1, Salem Unit 1 Pump Test Table Revision 8 Table 2-2, Salem Unit 2 Pump Test Table Revision 8 Table 3-1, Salem Unit 1 Valve Test Table Revision 8 Table 3-2, Salem Unit 2 Valve Test Table Revision 8 Attachment 1, Technical Positions Revision 8 Attachment 2, Cold Shutdown Justifications Revision 8 Attachment 3, Refueling Outage Justifications Revision 8 Attachment 4, Pump Relief Requests Revision 8 Attachment 5, Valve Relief Requests Revision 8

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I 0/ 1/97 Revision 8 TABLE OF CONTENTS

• 1.0 MANUAL

SUMMARY

.................................................................................................. 1 2.0 PROGRAM SUBMITTAL 2.1 Program Revision Executive Summary .................................................................. 2 2.2 Program Purpose ................................................................................................. 2

') ...,

-*-' Regulatory Basis .................................................................................................. 3 2.4 Program Development. ......................................................................................... 5 2.5 References ........................................................................................................... 6 2.6 Definitions ........................................................................................................... 7 3.0 INSERVICE TESTING PROGRAM FORPIBvlPS ....................................................... 11

3. 1 Pump Inservice Testing Program Description ........................................ ;............ I 1 3 .2 Pump Test Table Description ............................................................................. 11 4.0. INSERVICE TESTING PROGRAM FOR VALVES .................................................... 13 4.1 Valve Inservice Testing Program Description ................................................ ~ .... 13 4.2 Valve Test Table Description ............................................................................. 13 TABLES 1-1 SYSTEM AND P&ID LISTING - ASME Systems 1-2 SYSTEM AND P&ID LISTING - Non-ASME Systems 2-1 Salem Unit 1 PIBvlP TEST TABLE 2-2 Salem Unit 2 PIBvlP TEST TABLE 3-1 Salem Unit 1 VAL VE TEST TABLE 3-2 Salem Unit 1 VAL VE TEST TABLE ATTACHMENTS TECHNICAL POSITIONS 2 COLD SHUTDOWN JUSTIFICATIONS 3 REFUELING OUTAGE JUSTIFICATIONS 4 PUMP RELIEF REQUESTS 5 VAL VE RELIEF REQUESTS

I 0/1 /97 Revision 8 1.0 MANUAL

SUMMARY

The Salem Nuclear Generating Station, Units 1 & 2 Inservice Testing Manual has two major sections: Basis and Program. The IST Manual for Pumps & Valves is issued controlled via the Document Information Management System (DIMS) and is available for reference under the Procedures (PROC) global menu selection. A description of the IST Manual sections is provided below:

Basis - This section identifies the pumps and valves that have safety functions which perform a specific function required to bring the reactor from any operating mode to the cold shutdown condition, in maintaining the cold shutdown condition, or in mitigating the consequences of an accident. For each system included in the program, each Process and Instrument Diagram (P&ID) sheet was analyzed to determine if any pumps or valves had safety functions. Each pump or valve associated with each safety function was analyzed to determine if it had an active safety function described in the UFSAR, Technical Specification, or other design basis documents. Note that some components with passive safety functions are not analyzed. An example of a passive component that is not analyzed is a manual vent, drain or test connection valve that is normally closed. All components with active safety functions are covered in the Basis document. The Basis document also contains test circuit diagrams, instrument accuracy tables, and a section for interpretation of requirements.

Program - This section is the submittal document for the Nuclear Regulatory Commission (NRC). This section meets the minimum content requirements for a Program Submittal, and is sufficiently complete to provide an adequate description of the program. This

• program document provides the following: a description of the IST Program, Salem IST Technical Positions, Cold Shutdown Justifications, Refueling Outage Justifications, Relief Requests, Pump Test Tables and Valve Test Tables .

10/1/97 2.0 PROGRAM SUBMITTAL

• • 2.1 PROGRAM REVISION EXECUTIVE

SUMMARY

Interval 2 Program - Revision 8: Full Program revision and total rewrite. This is not a ten year program update.

2.2 PROGRAM PURPOSE The purpose of this program plan document is to provide the requirements for assessing the operational readiness of pumps and valves whose specific functions are required to bring the reactor from any operating mode to the cold shutdown condition, in maintaining the cold shutdown condition, or in mitigating the consequences of an accident.

The commercial operating date for Salem Nuclear Generating Station Unit 1 is June 30, 1977. The commercial operating date for Salem Nuclear Generating Station Unit 2 is October 31, 1981.

The IST program inservice inspection interval for Salem Unit 2 was revised to coincide with Salem Unit 1 per a request in the IST Program Submittal to the NRC dated March 30, 1987. NRC SER dated 10/9/92 identified that the interval date for both units required clarification. NRC SER dated 4/15/94 documents NRC approval of concurrent intervals for Salem Units 1 and 2.

The Salem Inservice Testing Program for Pumps and Valves is applicable for a one hundred twenty (120) month interval. The second 120-month interval for Salem Station was intended to be 6/30/87 through 6/30/97. The second interval for Salem Station was extended an additional 26 months due to the June 1995 through August 1997 extended shutdown of Salem Unit 2. Salem Unit 1 remains shutdown as of May 1995 and is defueled at this time. The second ten year concurrent interval for both Salem Units 1 and 2 will now end on 8/30/99. The second concurrent interval IST Program is applicable beginning 6/30/87 and increased to twelve years and two months, ending on 8/30/99. This extension is allowed per IWA-2400, "Inspection Intervals" and is supported by NUREG 1482, Section 3.3.1, "Extension oflnterval." Specifically, Subsection IWA of Section XI applies to both IST and inservice inspections.

The "Program" portion of the IST Manual is submitted to the NRC for their review and approval of the successive 120'-month IST Program. The program documents submitted to the NRC are used to prepare for IST inspections and to review relief requests.

Regarding periodic changes, the program document need not be submitted more often than necessary to reflect major changes, but it is expected that licensees make changes to the document periodically, and once per cycle, or once every other cycle, a complete up-to-date copy should be submitted to the NRC.

This program plan establishes the requirements which are then translated into implementing (surveillance) procedures for inservice testing and evaluation of Class 1, 2, and 3 pumps and valves. Additionally, using the guidance in NUREG 1482, certain other

• 2

I 0/1/97 Revision 8 valves not required to be classified as Class 1, 2, and 3, but which perform a specific function required to bring the reactor from any operating mode to the cold shutdown condition, in maintaining the cold shutdown condition, or in mitigating the consequences of an accident, are also included.

2.3 REGULATORY BASIS Code of Federal Regulations, Title 10, Section 50.55a (10CFR50.55a), "Codes and Standards," states requirements for IST of certain safety-related pumps and valves. These components are required to oe tested according to the requirements of the 1983 Edition with Addenda through Summer 1983 of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI; Subsection IWP, Inservice Testing of Pumps in Nuclear Power Plants; and Subsection IWV, Inservice Testing of Valves in Nuclear Power Plants. The testing is intended to assess operational readiness of components. The tests conducted during the initial and successive 120-month intervals are to based on the requirements in the applicable edition and addenda of the Code, to the extent practical, within the limitations of design, geometry, and materials of construction, as described in 10 CFR50.55a(f)(4).

10 CFR50.55a(f)(4)(ii) requires that IST in each 120-month interval following the initial interval be conducted in compliance with the requirements of the latest edition and addenda of the Code incorporated by reference in 10CFR50.55a(b), in effect 12 months before the start of the interval. Pursuant to 10CFR50.55a(f)(4)(iv), IST may meet the requirements of subsequent editions and addenda incorporated by paragraph (b) or portions of a revised edition of Section XI. When portions of a revised edition are used, all related requirements of the respective editions or addenda must be met.

The NRC may authorize alternatives to Code testing requirements submitted as relief requests, or submitted in a similar format that includes a description of the requirements, a description of the proposed alternative, and the justification for approval of the alternative.

10CFR50.55a(a)(3)(i) allows the NRC to authorize alternatives if "the proposed alternatives would provide an acceptable level of quality and safety." The NRC will normally approve an alternative pursuant to this provision only if the licensee proposes a method of testing that is an equivalent method, or an improvement, to the Code method, or if the testing will comply or is consistent with the later Code editions approved by NRC in 10CFR50.55a(b). Where plant design makes the testing of certain components complicated or impossible, an alternate method of testing is documented in a Relief Request. Indices and text are provided as Attachment 4, "Pump Relief Requests", and as Attachment 5, "Valve Relief Requests".

The Salem Units 1 & 2 Inservice Testing Program for Pumps and Valves was developed in accordance with the requirements of the 1983 Edition with Addenda through Summer 1983 of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI; Subsection IWP, "Inservice Testing of Pumps in Nuclear Power Plants"; and Subsection IWV, "Inservice Testing of Valves in Nuclear Power Plants."

• 3

10/1/97 As permitted by NUREG 1482, certain parts of ASME/ANSI Oma-1988 Addenda to the ASME/ ANSI OM-1987 Edition have been adopted as Salem Station transitions toward the ten year update (8/30/99). Specifically, Part 6 - "Inservice Testing of Pumps in Light Water Power Plants" was adopted for elimination of certain measured parameters.

Testing positive displacement pumps using the hydraulic parameters of Part 6 will also be performed. Additionally, Part 10 - "Inservice Testing of Valves in Light-Water Power Plants" was adopted for valve stroke timing, check valve testing, and analysis of leakage rates.

Following component classification and categorization, test requirements and frequencies were assigned. Technical Specification, UFSAR and other licensing commitments were considered during the assignment of test frequencies. Additional guidance for the development of the Salem Units 1 & 2 Inservice Testing Program was obtained from NRC Generic Letter 89-04, "Guidance on Developing Acceptable Inservice Testing Programs",

and NUREG 1482, "Guidelines for Inservice Testing at Nuclear Power Plants" .

• 4

10/1/97 2.4 PROGRAM DEVELOPMENT

• The IST Program covers components in ASME Code Class systems and a limited number of Non-ASME Code Class systems. Components included in the IST Program are those whose specific functions are required to bring the reactor from any operating mode to the cold shutdown condition, in maintaining the cold shutdown condition, or in mitigating the consequences of an accident.

ASME Class 1, 2 and 3 piping and components are identified on the Salem Piping and Instrument Diagrams (P&ID's). The P&ID's were reviewed to identify every system or portion of system that are Code Class 1, 2, or 3. P&ID's containing Class 1, 2, or 3 plant pumps and valves or other pumps and valves with safety functions that require testing are listed in Table 1-1 and 1-2, "System and P&ID Listing." Each Class 1, 2, and 3 component was reviewed to determine which require testing to satisfy the scope requirements of 1983 Edition with Addenda through Summer 1983 of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI; Subsection IWP, "Inservice Testing of Pumps in Nuclear Power Plants"; and Subsection IWV, "Inservice Testing of Valves in Nudear Power Plants."

After all systems or portions of systems containing pumps and valves within the scope of the IST Program were identified, the safety functions for each component was determined.

The safety function of each component was identified and documented in a computer database (Access PC'). The references used in these determinations were also recorded and include the UFSAR, Technical Specifications, and other design basis documents. IST categories for valves, per the 1983 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI; Subsection IWV, "Inservice Testing of Valves in Nuclear Power Plants" were determined. In cases where an interpretation of the ASME Code. or applicable regulations was necessary, the interpretation was documented in a plant-specific Technical Position. These Technical Positions are included in this program plan as Attachment 1, "Technical Positions."

Where the testing of certain plant components is not possible during normal plant operation, an alternate testing schedule is documented in a Cold Shutdown Justification.

An index and text is provided in Attachment 2, "Cold Shutdown Justifications."

Where the testing of certain plant components is not possible during a cold shutdown, an alternate testing schedule is documented in a Refueling Outage Justification. An index and text is provided in Attachment 3, "Refueling Outage Justifications."

Where plant design makes the testing of certain components complicated or impossible, an alternate method of testing is documented in a Relief Request. Indices and text are provided in Attachment 4, "Pump Relief Requests", and Attachment 5, "Valve Relief Requests."

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10/1/97

2.5 REFERENCES

Technical Specifications, Salem Nuclear Generating Station .

Updated Final Safety Analysis Report, Salem Nuclear Generating Station.

Code of Federal Regulations, Title 10, Section 50.55a, "Codes and Standards" 10CFR50 Appendix A. General Design Criteria for Nuclear Power Plants I OCFR50 Appendix J, Primary Reactor Containment Leakage Testing ASME Code,Section XI, Subsections IWP and IWV, 1983 Edition.

OMa-1988 Addenda to the ASME/ANSI OM-1987 Edition (Part 6, and Part I 0)

Minutes Of The Public Meetings On Generic Letter 89-04, dated October 25, 1989 G. L. No. 89-04, Guidance on Developing Acceptable Inservice Testing Programs.

OM Code - 1990 Interpretation 91-3, Part 6, para 4.6.1.1 (OM-1987 through OMC-1990)

NUREG-0800, Standard Review Plan.

NUREG-1482, April 1995, Guidelines for Inservice Testing at Nuclear Power Plants NRC Inspection Procedure 73756, Inservice Testing of Pumps and Valves, July 27, 1995.

NRC Temp. Instruction 2515/110, Performance of Safety-Related Check Valves, 11/91.

NRC Temp. Instruction 2515/114, Inspection Requirements for GL 89-04, 1/92.

• NRC Reg. Guide 1.26, "Quality Group Classification and Standards for Water, Steam and Radioactive Waste Containing Components of Nuclear Power Plants."

NRC Regulatory Guide 1.137, "Fuel Oil Systems for Standby Diesel Generators."

NUREG/CP-0123, Second NRC/ASME Symposium on Pump & Valve Testing, Session 2.A. "Use of Ultrasonics and Acoustics in Measurement of Solenoid Valve Stroke Time."

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l 0/1/97 2.6 DEFINITIONS

• Active valves - Valves which are required to change obturator position to accomplish the required function(s) (e.g., valves which receive an automatic safety actuation signal, or check valves not locked or held in position).

• If a valve is routinely repositioned during power operations (or has an active safety function), it is an active valve. A valve need not be considered active if it is only temporarily removed from service or from its safety position for a short period of time, such as stroke time measurement for surveillance testing or manually opening a sample valve to take a sample while maintaining administrative control over the valve.

Active Failure - A malfunction in the active part of a component. An active failure in mechanical components could be due to a part moving that should not move, or a part failing to move.

Alert Range - The range for a given pump parameter outside the normal operating range in which an increased testing frequency is specified.

Category A, B, C or D - Groupings of valves by function. When more than one distinguishing category characteristic is applicable, all requirements of each category are applicable, although duplication or repetition of common testing requirements is not required. The valve categories are as follows:

a. Category A - valves for which seat leakage is limited to a specific maximum amount

• in the closed position for fulfillment of their function(s).

b. Category B - valves for which seat leakage in the closed position is inconsequential for fulfillment of their function(s).

c. Category C - valves which are self-actuating in response to some system characteristic, such as pressure (safety/relief valves) or flow direction (check valves) for fulfillment of the required function(s).

d. Category D - valves which are actuated by an energy source capable of only one operation, such as rupture disks or explosively actuated valves Containment Isolation Valve (CIV) - Any valve whose function is to prevent post accident containment atmosphere leakage to areas outside containment.

Enforcement Authority - A regional or local governing body, such as a state or municipality of the United States empowered to enact and enforce Boiler and Pressure Vessel Code Legislation.

Exercising - The demonstration, based on direct visual or indirect positive indications, that the moving parts of a valve will perform the required function(s) .

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I 0/1/97 Fail-Safe Valve - Valve that moves to the position required to fulfill its safety function upon loss of motive power (pneumatic, hydraulic or electric) .

• Full Stroke Time - The time interval from initiation of an actuating signal to a valve to the indicatiqn of the defined end of the operating stroke of the valve.

Inservice Test - A test for obtaining information through measurement or observation to determine the operational readiness of a pump or valve.

lnservice Test Program Submittal- The document that establishes scope and detailed testing requirements needed to comply with the ASME or OM Code, applicable IST Technical Specifications and other licensing basis documents. The IST Program provisions that are submitted to the Regulatory Authority (NRC) in accordance with applicable requirements.

lnservice Test Program - A collection of documents including the Inservice Test Program Submittal, procedures, records of tests, etc., that specify and implement inservice testing requirements.

Instrument Accuracy - The allowable inaccuracy of an instrument loop based on the square root of the sum of the squares of the inaccuracies of each instrument or component in the loop. For flow loops, this inaccuracy does not include the inaccuracies of the flow sensing element; e. g., orifice, venturi, etc.

When a difference in readings taken from the same or different instruments is required to

• determine a value of a parameter (e.g., two levels taken over a timed interval to determine flow rate) the inaccuracy of the result is to be based on the square root of the sum of the squares of the inaccuracies of each instrument loop reading.

Instrument Loop - Two or more instrument or components working together to provide a single output (e.g., a vibration probe and its associated signal conditioning and readout devices).

Leakage Rate Test - Verification of the leak tight integrity of a valve using differential gas or liquid pressure or system fluid pressure.

Maximum Required Accident Condition Flow - The largest flow rate for which credit is taken for a component in a safety analysis in any flow configuration. The safety analyses are those contained in the UFSAR but are not limited to accident and transient analyses.

Normal System Operating Conditions - System fluid, pressure, and temperature during the phase of plant operation for which that system is intended to function.

Obturator - Valve closure member (disk, gate, plug, ball, etc.).

Operational Readiness - The ability of a pump or valve to perform its intended function .

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10/1/97 Owner - The organization legally responsible for the operation, maintenance, safety, and power generation of the nuclear power plant.

Partial-Stroke Exercising -

a. Exercising a check valve to an open position less than full open or less than that required to pass the maximum required accident condition flow rate.

b. For power operated valves, exercising a valve to an intermediate position, versus fully open or fully closed.

Passive Valve - Valves which maintain obturator position and are not required to change obturator position to accomplish the required function(s) for shutting down the reactor to the cold shutdown condition, maintaining the reactor in cold shutdown, or in mitigating the consequences of an accident. If a valve is routinely repositioned during power operations (or has an active safety function), it is an active valve. A valve need not be considered active if it is only temporarily removed from service or from its safety position for a short period of time, such as stroke time measurement for surveillance testing or manually opening a sample valve to take a sample while maintaining administrative control over the valve.

Valves that are locked or deenergized in their required positions, or are only repositioned from their safety position under administrative control are, in most cases, considered passive. Valves that are routinely repositioned during plant operation are not considered

• passive. "Routine" includes valve operations which occur as a result of normal operating procedures. Valve operations included within off-normal or emergency procedures are not considered routine. Valve operations which occur as a result of system startup or shutdown procedures, or infrequent operating procedures may be considered routine depending upon the frequency of the operation.

Plant Operation - The condition of operation at power as defined by the plant Technical Specifications.

Pressure Isolation Valve (PIV) - Either of two normally closed valves in series that isolate the reactor coolant system from an attached low pressure system, as defined by the Technical Specifications.

Rapid-Acting Valves - An optional classification for power operated valves with a full stroke time of 2 seconds or less.

Reactor Coolant System Pressure Isolation - That function which prevents intersystem over pressurization between the reactor coolant system and connected low-pressure systems.

Reference Values - One or more values oftest parameters measured or determined when the equipment is known to be operating acceptably .

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10/1/97 Regulatory Authority - A federal government agency, such as the United States Nuclear Regulatory Commission, empowered to issue and enforce regulations concerning the design, construction, and operation of nuclear power plants.

Remote Actuation - Actuation of a pressure relief device through a generated signal rather than by static inlet pressure.

Required Action Range - That region outside the upper and lower limits in which the pump is considered inoperable until the cause of the deviation has been determined and the condition corrected Thermal Relief Valve - A relief valve shall be considered in a thermal application ff they serve to protect portions of safety-related systems or components solely from over pressure due to thermal expansion while the component or portion of system is in an isolated condition. The applicable system portion or component would not be isolated during normal operations or accident conditions.

Vertical Line Shaft Pump - As referred to in OM-6, shall be defined as a vertically suspended pump where the pump driver and pumping element are connected by a line shaft(s) within an enclosing column which contains the pump bearings .

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I 0/ I i97 Revision 8 3.0 lNSERVICE TESTING PROGRAM FOR PUMPS

• 3.1 Pump Inservice Testing Program Description This program establishes the requirements for the performance, administration, and implementation of the Inservice Testing Program for selected pumps at Salem Nuclear Station, Units 1 & 2. This program includes pumps that are provided with an emergency power source and are required in shutting down the reactor to the cold shutdown condition, maintaining the cold shutdown condition, or mitigating the consequences of an accident.

This program plan meets the requirements of ASME Section XI, Subsection IWP, "Inservice Testing of Pumps in Nuclear Power Plants." For specific discussion on adoption of certain parts of OM-6, refer to Technical Positions TP-2 and TP-4. Specific relief requests from Code requirements are contained in Attachment 4.

3.2 Pump Program Table Description The pumps included in the Salem Nuclear Generating Station, Units 1 & 2 IST Program are listed in Table 2. The information contained in this table identifies those pumps required to be tested to the requirements of ASME XI, Subsection IWP, "Inservice Testing of Pumps in Nuclear Power Plants." The pump tables show the following information:

• PUMP NO - Component number as used on the P&ID and other plant documents.

PUMP DESCRIPTION - A description of the component.

P +ID No - Salem Piping & Instrument Diagram, dash, sheet number.

P +ID Name - The name of the Salem Piping & Instrument Diagram.

Drawing Coordinates - A letter I number combination that aids in locating the component on the P&ID.

ASME Class - Classification per ASME Boiler and Pressure Vessel Code,Section III. Code classes are Class 1 (1), Class 2 (2), Class 3 (3), and non-class (NC).

Pump Type - Pump types are horizontal centrifugal, vertical line shaft centrifugal, or positive displacement.

Driver - The power conversion method for the pump. Drivers are motor or turbine.

Mfg. Model ID - The name or model identifier used by the manufacturer .

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l 0/1 /97 Revision 8 TEST TYPE - Parameter to be measured during test. Possible parameters are discharge pressure (P); differential pressure ( dP); suction pressure (Pi); flow rate (Q); speed (N); Vibration (V) .

TEST FREQ. - quarterly full flow (Q-F); quarterly recirculation (Q-R); cold shutdown full flow (CS-F); cold shutdown recirculation (CS-R); reactor refueling outage full flow (RF-F); or reactor refueling outage recirculation (RF-R).

REL. REQ. - If a relief request is associated with this pump, the relief request number is shown here.

TECH. POS. - If a technical position is associated with this pump, the technical position number is shown here.

COMMENTS - Any other information .

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IO/l /97 Revision 8 4.0 lNSERVICE TESTING PROGRAM FOR VALVES

• 4.1 Valve [nservice Testing Program Description This program establishes the requirements for the performance, administration, and implementation of the Inservice Testing Program for selected valves at Salem Nuclear Station, Units 1 & 2. This program includes those valves which are required to perform a specific function in shutting down the reactor to the cold shutdown condition, maintaining the cold shutdown condition, or mitigating the consequences of an accident.

This program plan meets the requirements of AS1\1E Section XI, Subsection IWV, Inservice Testing of Valves in Nuclear Power Plants." For specific discussion on adoption of certain parts of OM-10, refer to Technical Positions TP-1, TP-5 and TP-6. Specific relief requests from Code requirements are contained in Attachment 5.

4.2 Valve Program Table Description The valves included with the Salem Nuclear Generating Station, Units 1 & 2 IST Program are listed in Table 3. The information contained in these exhibits identifies those valves required to be tested to the requirements of AS1\1E Subsection IWV, "Inservice Testing of Valves in Nuclear Power Plants." Valves exempt per Subsection IWV-1200 are not listed. The headings for the valve tables are delineated below .

• VALVE NO - Component number as used on the P&ID and other plant documents.

VALVE DESCRIPTION - A description ofthe component.

P +ID No - Salem Piping & Instrument Diagram, dash, sheet number.

P +ID Name - The name of the Salem Piping & Instrument Diagram.

Drawing Coordinates - A letter I number combination that aids in locating the component on the P&ID.

ASME Class - Classification per AS1\1E Boiler and Pressure Vessel CC?de,Section III. Code classes are Class 1 (1), Class 2 (2), Class 3 (3), and non-class (NC).

IST Cat - Classification per AS1\1E Section XI Subsection IWV. IST Categories are A (gate and globe valves where the leak rate is critical to their safety function),

B (gate and globe valves), C (check and relief valves), AC (check and relief valves where the leak rate is critical to their safety function) or D (rupture disk or explosive actuated valve) .

• 13

I Oil /97 Revision 8 Valve Type - The possible valve types are diaphragm (DIA), check (CK), plug (PL), relief (RV), gate (GT), globe (GB), stop check (SCK), three way (JWA Y),

butterfly (BFY), ball (BALL), needle (Needle), modified check valve (MCK), or testable check valve (TCK), excess flow check valve (XFV).

Actuator Type - The possible actuator types are air operated (AO), manually operated (MAN), motor operated (MO), self operated (SELF), solenoid operated (SO), steam operated (STM), hydraulically operated (HO), or self operated with a motor operator (such as stop check valve) (SIM).

Valve Size - The nominal valve size in inches.

Normal Position - The possible normal positions are open (0), close (C), both open and close (O/C), modulating (M), locked closed (LC), locked open (LO),

throttled open (TO), or position dependent upon component operation (i.e.

operates automatically with main component) (A).

Safety Position - The possible safety positions. are open (0), close (C), both open and close (O/C), modulating (M), locked closed (LC), locked open (LO), or throttled open (TO).

A/P Classification - The classification of the valve as either Active or Passive. An Active (A) valve must reposition to fulfill its safety function. A Passive (P) valve need not reposition but must remain in its normal position to fulfill its safety function .

TEST TYPE - Parameter to be measured during test. Possible test types are as follows:

FSC Full stroke exercise to the closed position.

FSO Full stroke exercise to the open position.

FSTC - Fail safe test to the closed position.

FSTO - Fail safe test to the open position.

PIT Position indication test.

RV Relief valve test.

EX Explosive valve test.

STC Stroke time test to the closed position.

STO - Stroke time test to the open position.

CTC - Check valve test to the closed position.

CTO - Check valve test to the open position.

LT Leak rate test to ASME Section XI requirements. This test applies to valves where leakage might negatively affect their safety function but are not containment isolation valves, such as PIV s and accumulator check valves .

• 14

I 011/97 Revision 8 LJ A Type C leak rate test per 10CFR50 Appendix J requirements. This test applies to containment isolation valves .

PS Partial stroke exercise valve.

SAM - Sample Disassembly & Inspection Schedule TEST FREQ - Quarterly (Q), Cold shutdown (CS), Refueling outage (RF), Once every 18 months (18MO), Once every two years (2YR), Once every five years (5YR), Once every ten years (lOYR) or Technical Specification required frequency (TS).

COLD SHUT - If a cold shutdown justification is associated with this valve, the cold shutdown justification number is shown here.

REFUEL OUTAGE JUST. - If a refueling outage justification is associated with this valve, the refueling outage justification is shown here.

REL REQ - If a relief request is associated with this valve, the relief request number is shown here.

TECH POS - If a technical position is associated with this valve, the technical position number is shown here.

COMMENTS - Any other information .

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.J

I0/1/97 * *Revision 8 Table 1-1 System and P&ID Listing - Units 1 & 2 ASME Unit 1 Unit 2 System Name Analvsis 205201-1 205301-1 Reactor Coolant Pressurizer reliefs, pressurizer spray, and other pressurizer piping. Included in IST Program Basis.

205201-2 205301-2 Reactor Coolant 11(21) & 13 (23) steam generator, reactor coolant pump, and reactor and connecting piping. The reactor coolant pump is not required for plant safe shutdown. No other pumps or valves appear on this drawing.

205201-3 205301-3 Reactor Coolant 12 (22) & 14 (24) steam generator, reactor coolant pump, and reactor and connecting piping. The reactor coolant pump is not required for plant safe shutdown. No other pumps or valves appear on this drawing.

205202-1 205302-1 S. G. F & Cond. Condenser, condensate pumps & valves. This equipment is not required for plant safe shutdown.

205202-2 205302-2 S. G. F & Cond. Low pressure feedwater heaters, steam generator feed pumps. This equipment is not required for plant safe shutdown.

205202-3 205302-3 S. G. F & Cond. Steam generator feed pumps and feedwater piping. Certain valves required and included in IST Program Basis.

205203-1 205303-1 Main Steam Main steam reliefs and auxiliary feed pump turbine. Included in IST Program Basis.

205203-2 205303-2 Main Steam Main steam reliefs and auxiliary feed pump turbine. Included in IST Program Basis.

205203-3 205303-3 Main Steam Main steam supply to the high pressure turbine and steam generator feed pumps. This equipment is not required for plant safe shutdown.

205203-4 205303-4 Main Steam Steam supply to moisture separator reheaters and low pressure turbine. This equipment is not required for plant safe shutdown.

205203-5 205303-5 Main Steam Steam supply to moisture separator reheaters and low pressure turbine. This equipment is not required for plant safe shutdown.

10/1/9/ *

• K. .. :;ion S Table 1-l System and P&ID Listing - Units I & 2 ASME (Continued)

Unit 2 System Name Analysis 205203-6 205303-6 Main Steam Steam supply to moisture separator reheaters, low pressure turbine and radiation monitors. This equipment is not required for plant safe shutdown.

205216-1 205216-2 Chilled Water Chilled water supply to control room air conditioning system. Included in IST Program Basis.

205216-3 205216-3 Chilled Water Chilled water supply to emergency control air compressor cooling. Both units on this sheet. Included in IST Program Basis.

205216-4 Chilled Water Air conditioning for various plant areas. This equipment is not required for plant safe shutdown.

205216-5 Chilled Water Clean facilities building air conditioning. This equipment is not required for plant safe shutdown.

205216-6 Chilled Water Sample cooler pumps and coils. This equipment is not required for plant safe shutdown.

205216-7 Chilled Water Sample cooler pumps and coils. This equipment is not required for plant safe shutdown.

205216-8 Chilled Water Details of equipment shown on Sheets I & 2.

205217-1 Compressed Air Air compressors and distribution piping. This equipment is not required for plant safe shutdown.

205217-2 205317-1 Compressed Air Station air receivers and containment penetration test connections. The test connections are included in the IST Program Basis.

205217-3 205317-2 Compressed Air "

Compressed air distribution system and air drop stations. Primary containment penetration isolation is included in the IST Program Basis.

205217-4 Compressed Air Compressed air dryers. This equipment is not required for plant safe shutdO\vn.

205217-5 Compressed Air Machine shop compressed air drops. This equipment is not required for plant safe shutdom1.

2

10/1/9~ *

• 1'. .sion 8 Table 1-1 System and P&ID Listing - Units I & 2 ASME (Continued)

Svstem Name Anal vs is 205222-1 205222-2 Fire Protection Fire water distribution. Only primary containment penetration isolation valves are included in the IST Program Basis.

205222-3 Fire Protection Fire protection hose stations. This equipment is not required for plant safe shutdown.

205222-4 Fire Protection Fire hose stations for both units. Both units can supply water to the auxiliary feedwater system per the FSAR.

No pumps or valves shown on this drawing are required to operate for plant safe shutdown.

205222-5 Fire Protection Fire hose stations and sprinkler system supply. This equipment is not required for plant safe shutdown.

205222-6 Fire Protection Fire hose stations and sprinkler system supply. This equipment is not required for plant safe shutdown.

205225-1 205325-l S.G. Dm & Bldwn Steam generator blowdown lines and blowdown demineralizer. Blowdown isolation valves are on Sheet 2. This equipment is not required for plant safe shutdown.

205225-2 205325-2 S.G. Dm & Bldwn Steam generator blowdown lines and equipment. The blowdown isolation valves are included in the IST Program Basis.

205228-1 205328-1 eve Boric acid transfer pumps and piping. Included in the IST Program Basis.

205228-2 205328-2 eve Charging pumps and charging piping. Included in the IST Program Basis.

205228-3 205328-3 eve Reactor coolant pump bearing cooling water supplies. Included in the IST Program Basis.

205229-I 205329-1 eve Boric acid process recovery equipment. This quipment is not required for plant safe shutdo\\TI.

205229-2 205329-2 eve Boric acid process recovery equipment. This equipment is not required for plant safe shutdown.

3

I 011 /9~ *

• J, ,:;ion 8 Table 1-1 System and P&ID Listing - Units I & 2 ASME (Continued)

Unit 2 S\'stem Name Anal\'sis 205229-3 205329-3 CVC Boric acid process recovery equipment. This equipment is not required for plant safe shutdO\rn.

205231-1 205331-1 Comp. Cooling Cooling system for critical safety related equipment. Included in the IST Program Basis.

205231-2 205331-2 Comp. Cooling Header piping for critical safety related equipment. No valves shown on this drawing need to operate for plant safe shutdown.

205231-3 205331-3 Comp. Cooling Reactor coolant pump cooling and penetration isolation. Included in the IST Program Basis.

205232-1 205332-1 Resid. Heat Rem. Critical safety system. Included in the IST Program Basis.

205232-2 205332-2 Resid. Heat Rem. Critical safety system. Included in the IST Program Basis.

205233-1 205333-1 Spent Fuel System is not required for plant safe shutdown. Fuel pool maintenance is not an emergency event. Isolation valves are included in the IST Program Basis.

205234-1 205334-1 Safety Injection Safety injection equipment. Included in the IST Program Basis.

205234-2 205334-2 Safety Injection Safety injection pumps and piping. Included in the IST Program Basis.

205234-3 205334-3 Safety Injection Safety injection piping. Included in the IST Program Basis.

205234-4 205334-4 Safety Injection Safety injection accumulators and piping. Included in the IST Program Basis.

205235-1 205335-1 Cont. Spray Containment spray pumps and equipment Included in the IST Program Basis.

205236-1 205336-1 Aux.Feedwater Aux feedwater pumps and piping. Included in the IST Program Basis.

205238-1 205338-1 Containment Vent. Ventilation systems not in scope of Code Sections IWP and IWV. Radiation monitoring cooling isolation valves included in the IST Program Basis.

4

101119; * *

h. .sion 8 Table 1-1 System and P&ID Listing - Units 1 & 2 ASME (Continued)

System Name Analysis 205238-2 205338-2 Containment Vent. Ventilation system. No pumps or valves.

205238-3 Containment Vent. Ventilation system. No pumps or valves.

205239-1 205339-1 Waste Disp. Liquid Radioactive waste processing. This equipment is not required for plant safe shutdown.

205239-2 205339-2 Waste Disp. Liquid Radioactive waste processing. This equipment is not required for plant safe shutdown.

205239-3 205339-3 Waste Disp. Liquid Radioactive waste processing. Containment isolation valves are included in the IST Program Basis.

205239-4 Waste Disp. Liquid Radioactive waste processing. This equipment is not required for plant safe shutdown.

205239-5 Waste Disp. Liquid Radioactive waste processing. This equipment is not required for plant safe shutdown.

205242-1 205342-1 Service Water Nuc. Service water pumps and piping. Included in the IST Program Basis.

205242-2 205342-2 Service Water Nuc. Service water pumps and piping. Included in the IST Program Basis.

205242-3 205342-3 Service Water Nuc. Service water distribution piping to diesels and injection pumps. Included in the IST Program Basis.

205242-4 205342-4 Service Water Nuc. Service water distribution piping to injection pump coolers. Included in the IST Program Basis.

205242-5 205342-5 Service Water Nuc. Service water distribution piping to chillers. Included in the IST Program Basis.

205242-6 205342-6 Service Water Nuc. Service water distribution piping to containment fan coil units. Included in the IST Program Basis.

205244-1 205344-1 Sampling Sampling not required for safe shutdo\\'11. Containment isolation valves are included in the !ST Program Basis.

205244-2 205344-2 Sampling Sample sink drains. Sampling not required for safe shutdown.

205244-3 205344-3 Sampling Sample panel cooling. Penetration isolation valves included in the !ST Program Basis.

5

I 0/ I /9~ * *'" ,:;ion 8 Table 1-1 System and P&ID Listing - Units 1 & 2 ASME (Continued)

Unit 2 S\'stcm Name Anal\'sis 205244-4 205344-4 Sampling Sample lines. This equipment is not required for plant safe shutdmrn.

205244-5 Sampling Sample panel drains.This equipment is not required for plant safe shutdmm.

205246-1 205246-2 Demin. Water Demineralized water distribution is not require for safe shutdown. Penetration isolation valves are included in the IST Program Basis.

205247-1 205347-l Control Air Control air distribution to panels. Not required for safe shutdown. Penetration isolation valves included in the IST Program Basis.

205247-2 205347-2 Control Air Control air compressor, dryer, and distribution piping. Not required for safe shutdown.

205247-3 205347-3 Control Air PORV accumulators, accumulator valves, and penetration isolation valves are included in the IST Program Basis.

6

I 0/1/9- *

• I, ,sion 8 Table 1-2 System and P&ID Listing - Units I & 2 Non-ASME Code Systems in Testing Program P&ID-Sheet S\*stem Name Reason Included 205209-4 205209-4 Circulating Water Added to cover CL valves in piping connected to SW.

205217-2 205317-2 Compressed Air Added in order to cover containment pressure test connections.

205238-1 205338-1 Reactor Containment Vent Added to cover Radiation Monitoring System Sample Inlet &

Outlet Isolation Valves.

205238-2 205338-2 Reactor Containment Vent Added to cover Containment Purge Valves.

205241-1 205241-4 Diesel Engine Auxiliaries System added to comply with NUREG- 1482 requirements 205241-2 205241-5 Diesel Engine Auxiliaries System added to comply with NUREG-1482 requirements 205241-3 205241-6 Diesel Engine Auxiliaries System added to comply with NUREG-1482 requirements 205249-2 205249-3 Fuel Oil System added to comply with NUREG-1482 requirements

Salem Units 1 & 2 Inservice Test Program TABLE 2-1 Salem Unit 1 PUMP TEST TABLE

TABLE 2 PUMP TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 1 PUMP NO PUMP DESCRIPTION P +ID No P+IDName Drawing ASME Pump Type Driver Mfg Model ID Coordinates Class 1AFE4 Auxiliary Feedwater Pump 11 205236-1 Auxiliary Feedwater D2 3 Horizontal Centrifugal Motor Byron Jackson Model 3x6x9E Type I

I I

'I S1.0P-ST.AF-0005(0) DP, 0, V  : CS-F 100819  : TP-3 AUGMENTED FULL FLOW S1 .OP-ST.AF-0001 (0) i DP,O, V 0-R 100692 1AFE5 Auxiliary Feedwater Pump 12 205236-1 Auxiliary Feedwater D5 3 Horizontal Centrifugal Motor Byron Jackson Model 3x6x9E Type I

I I

, I I

I I

S1 .OP-ST.AF-0005(0)  :

t DP, 0, V :I CS-F  :

I 100819 :I TP-3 AUGMENTED FULL FLOW I 'I '

I 'I S1 .OP-ST.AF-0002(0)  : DP, 0, V 0-R  : 100693  :

1AFE6 Auxiliary Feedwater Pump 13 205236-1 Auxiliary Feedwater DB 3 Horizontal Centrifugal Turbine Byron-Jackson Model 4x6x9d Type I

I I I I 1 I I

S1.0P-ST.AF-0007(0) N, DP, 0, V : CS-F 100515  : TP-3 AUGMENTED FULL FLOW S1.0P-ST.AF-0003(0) j N, DP, 0, V j 0-R 100694 1CCE2 Component Cooling Pump 11 205231-1 Component Cooling E4 3 Horizontal Centrifugal Motor Gould Model 3405(L) 5-1:c;p~sl--.cc~aaa1-<c;>------*-!-**-op:-c;-.--v---*:-------**o~F-*------*r-----*--*----------*-*-**--r-*-----1*00~9-7-*------:-*-------,.F>~4--------*r**----------**---------*----------------------------------------------

1CCE3 Component Cooling Pump 13 205231-1 Component Cooling B4 3 Horizontal Centrifugal Motor Gould Model 3405(L) 5-1:c;P~sr cc~aaa3a) _________i_____op:-c;-.--v*---;---------o~F-------------------*-*-----*--*--*T-----*1006-99-------r*-------,.F>-~4*---------*----------*-*--------------------------------------------

1CCE4 Component Cooling Pump 12 205231-1 Component Cooling 04 3 Horizontal Centrifugal Motor Gould Model 3405(L)

S1 .OP-ST.CC-0002(0) DP,O,V 0-F 100698 i TP-4

TABLE 2 PUMP TEST TABLE 1011197 SALEM NUCLEAR PLANT - UNIT 1 Page 2 PUMP NO PUMP DESCRIPTION P+ ID No P+ID Name Drawing ASME Pump Type Driver Mfg Model ID Coordinates Class 1CHE5 Chilled Water Pump 11 205216-1 Chilled Water F3 3 Horizontal Centrifugal Motor Gould Model 3196MT I '

I '

I '

I 81.0P-ST.CH-0001(0) j DP, 0, V j 0-F j 100700 j .

1CHE6 Chilled Water Pump 12 205216-1 Chilled Water F5 3 Horizontal Centrifugal Motor Gould Model 3196MT S1 .OP-ST.CH-0002(0)  ! DP, 0, V , 0-F  ! 100701  !

1CSE1 Containment Spray Pump 11 205235-1 Containment Spray H4 2 Horizontal Centrifugal Motor Gould Model 3415 s-1-:op~sT.cs~aoci1*<a>--*-------**op:*a-:-v----r---*---a~R***-**--------------*****-******-***r*----1aa7<<1*1******T************---***--------------*************--*-***--*-*-------------------------------------

s1 .OP-ST.CS-0005(0)  ! DP, 0, V RF-F 100754 TP-3 AUGMENTED FULL FLOW 1CSE2 Containment Spray Pump 12 205235-1 Containment Spray E4 2 Horizontal Centrifugal Motor Gould Model 3415 S1 .OP-ST.CS-0002(0) DP, 0, V 0-R  ! 100708 j 81.0P-ST.CS-0005(0)  ! DP, 0, V RF-F 100754 TP-3 AUGMENTED FULL FLOW 1CVE4 Boric Acid Transfer Pump 11 205228-1 Chemical & Volume Cont E1 2 Horizontal Centrifugal Motor Gould Model 3196MT 1CVE5 Boric Acid Transfer Pump 12 205228-1 Chemical & Volume Cont E3 2 Horizontal Centrifugal Motor Gould Model 3196MT S1 .OP-ST.CVC-0002(0) DP,O,V 0-F 100696

TABLE 2 PUMP TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 3 PUMP NO PUMP DESCRIPTION P +ID No P +ID Name Drawing ASME Pump Type Driver Mfg Model ID Coordinates Class 1CVE20 Charging and Safety Injection Pump 11 205228-2 Chemical & Volume Cont D3 2 Horizontal Centrifugal Motor Pacific Model IJ (11 Stage) 5-1:0P~ST.CVC~-0003(a)*-*-r-*op:*c;,--V-*--;--*-*---Q~R----****-*-****-*********-******---*r*-----*1~~7-~2-******:***********-*****--******!**--**---**-*--*-******-****----***------**-----****************-----*

i DP,Q, V RF-F 101056 TP-3 AUGMENTED FULL FLOW 1CVE21 Charging and Safety Injection Pump 12 205228-2 Chemical & Volume Cont C3 2 Horizontal Centrifugal Motor Pacific Model IJ (11 Stage)

S1 .OP-ST.CVC-0004(Q) DP,Q,V : Q-R  : 100703  :

S1. OP-ST .SJ-0016(0) i DP,Q, V RF-F 101056 TP-3 AUGMENTED FULL FLOW 1CVE22 Charging Pump 13 205228-2 Chemical & Volume Cont 83 2 Positive Displacement Motor Union Model QX-300 S1.0P-ST.CVC-0005(Q)  ! P, Q, N, V ! Q  ! 100704  :

1DFE9 Fuel Oil Transfer Pump 11 205249-2 Fuel Oil AS N Positive Displacement Motor Viking Model HL475M AUGMENTED S1.0P-ST.DG-0004(Q) P, Q, V  ! Q  ! 100577 1DFE10 Fuel Oil Transfer Pump 12 205249-2 Fuel Oil Al N Positive Displacement Motor Viking Model HL475M AUGMENTED I

I I

I I

I I

I S1.0P-ST.DG-0005(Q) P, Q, V  ! Q  ! 101127 1RHE1 Residual Heat Removal Pump 11 205232-1 Residual Heat Removal E3 2 Vertical Centrifugal Motor Ingersoll-Rand Model 8x20W S1 .OP-ST.RHR-0001 (Q) DP,Q,V CS-F 101316 TP-3 S1 .OP-ST.RHR-0001 (Q) DP,Q,V Q-R 100705

TABLE 2 PUMP TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 4 PUMP NO PUMP DESCRIPTION P +ID No P+ ID Name Drawing ASME Pump Type Driver Mfg Model ID Coordinates Class

-TEST-PRO_C _______________________ T_TEST-TYPE*--;--iisi---FREQ.---*r**---R*E*L:-REQ-.~-----*r**-RECU_R_ _ TASK*-r***;:ECH:-pos:*--foo-MMENTS ----------------------------------------------------------

1RHE2 Residual Heat Removal Pump 12 20S232-2 Residual Heat Removal E3 2 Vertical Centrifugal Motor Ingersoll-Rand Model 8x20W

' I I

I 81 .OP-8T.RHR-0002(0) [ DP, 0, V [ CS-F 101315 TP-3 81 .OP-ST.RHR-0002(0)  ! DP, 0, V 0-R 100706 1SJE2 Safety Injection Pump 11 20S234-2 Safety Injection E3 2 Horizontal Centrifugal Motor Pacific Model JTCH (10 Stage) 81 .OP-ST.SJ-0001 (0) DP, 0, V  : 0-R  : 100709 81 .OP-8T.SJ-0014(0) DP,O,V RF-F 100097 TP-3 AUGMENTED FULL FLOW 1SJE3 Safety Injection Pump 12 20S234-2 Safety Injection E6 2 Horizontal Centrifugal Motor Pacific Model JTCH (10 Stage)

I I I I S1.0P-8T.SJ-0002(0)  : DP, 0, V  : 0-R  : 100710  :

S1 .OP-ST.SJ-0014(0) DP,O,V RF-F 100097 TP-3 AUGMENTED FULL FLOW 1SWE1 Service Water Pump 11 20S242-1 Service Water Nuclear A CS 3 Vertical Centrifugal Motor Aurora Model D26081 D I I' '

I '

I S1.0P-ST.SW-0001(0)  ! DP,O,V [ 0-F  ! 100711 1SWE2 Service Water Pump 12 20S242-1 Service Water Nuclear A ES 3 Vertical Centrifugal Motor Johnston Model 3171SS (3 Stage)

S1.0P-8T.8W-0002(0)  : DP, 0, V  : 0-F , 100712  :

1SWE3 Service Water Pump 13 20S242-1 Service Water Nuclear A GS 3 Vertical Centrifugal Motor Aurora Model D26081 81 .OP-8T.8W-0003(0) [ DP, 0, V [ 0-F 100713

TABLE 2 PUMP TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 5 PUMP NO PUMP DESCRIPTION P +ID No P+ ID Name Drawing ASME Pump Type Driver Mfg Model ID Coordinates Class TEST PROC  ! TEST TYPE  ! TEST FREQ. REL. REQ.  ! RECUR. TASK  ! TECH. POS. !COMMENTS 1SWE4 Service Water Pump 14 20S242-2 Service Water Nuclear A CS 3 Vertical Centrifugal Motor Aurora Model D26081

' I I I S1.0P-ST.SW-0004(Q) DP, Q, V ! Q-F  !' 100714 1SWE5 Service Water Pump 15 205242-2 Service Water Nuclear A ES 3 Vertical Centrifugal Motor Aurora Model D26081 I I I I S1.0P-ST.SW-0005(Q)  ! DP, Q, V ! Q-F i 100715 ,

1SWE6 Service Water Pump 16 20S242-2 Service Water Nuclear A GS 3 Vertical Centrifugal Motor Aurora Model D26081

' I I I S1 .OP-ST.SW-0006(0)  ! DP, Q, V ! Q-F  ! 100716  !

Salem Units 1 & 2 Inservice Test Program TABLE 2-2 Salem Unit 2 PUMP TEST TABLE

TABLE 2 PUMP TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 1 PUMP NO PUMP DESCRIPTION P +ID No P +ID Name Drawing ASME Pump Type Driver Mfg Model ID Coordinates Class TEST PROC  ! TEST TYPE  ! TEST FREQ.  ! REL. REQ.  ! RECUR. TASK  ! TECH. POS. !COMMENTS 2AFE4 Auxiliary Feedwater Pump 21 205336-1 Auxiliary Feedwater D2 3 Horizontal Centrifugal Motor Byron Jackson Model 3x6x9E Type I

I I

I I

I I

82.0P-ST.AF-0005(0) DP, 0, V j CS-F  ! 100820  ! TP-3 AUGMENTED FULL FLOW 82.0P.ST.AF-0001 (0) DP,O,V 0-R 100666 2AFE5 Auxiliary Feedwater Pump 22 205336-1 Auxiliary Feedwater D5 3 Horizontal Centrifugal Motor Ingersoll-Rand 82.0P-ST.AF-0005(0) DP,O,V CS-F  : 100820  : TP-3 AUGMENTED FULL FLOW S2. OP-ST .AF-0002(0) j DP, 0, V 0-R 100667 2AFE6 Auxiliary Feedwater Pump 23 205336-1 Auxiliary Feedwater DB 3 Horizontal Centrifugal Turbine Byron-Jackson Model 4x6x9d Type I l I o I 82.0P-ST.AF-0007(0)  : N, DP, O,V : CS-F 100376  : TP-3 AUGMENTED FULL FLOW 82.0P-ST.AF-0003(0) i N, DP, 0, V \ 0-R 100668 2CCE2 Component Cooling Pump 21 205331-1 Component Cooling E4 3 Horizontal Centrifugal Motor Gould Model 3405(L) 82.0P-ST.CC-0001 (0) i DP, 0, V . 0-F \ 100673 \ TP-4 2CCE3 Component Cooling Pump 23 205331-1 Component Cooling 84 3 Horizontal Centrifugal Motor Gould Model 3405(L) 82.0P-ST.CC-0003(0) \ DP,O, V 0-F  :' 100675  : TP-4 2CCE4 Component Cooling Pump 22 205331-1 Component Cooling D4 3 Horizontal Centrifugal Motor Gould Model 3405(L)

S,2.0P-ST. CC-0002(0) DP,O,V 0-F 100674 TP-4

TABLE 2 PUMP TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 2 PUMP NO PUMP DESCRIPTION P +ID No P +ID Name Drawing ASME Pump Type Driver Mfg Model ID Coordinates Class TEST PROC TEST TYPE  ! TEST FREQ. REL. REQ.  ; RECUR. TASK TECH. POS.  : COMMENTS 2CHE6 Chilled Water Pump 21 205216-2 Chilled Water F3 3 Horizontal Centrifugal Motor Gould Model 3196MT

'I .

'I I I

82.0P-ST.CH-0001 (Q) DP, Q, V  ! Q-F 100689  !

2CHE7 Chilled Water Pump 22 205216-2 Chilled Water F5 3 Horizontal Centrifugal Motor Gould Model 3196MT I

I I

S2.0P-ST.CH-0002(Q)  ! DP, Q, V ! Q-F  ! 100690  !

2CSE1 Containment Spray Pump 21 205335-1 Chilled Water H4 2 Horizontal Centrifugal Motor Gould Model 3415 82.0P-ST.CS-0001 (Q) DP,Q,V Q-R 100664 S2.0P-ST.CS-0005(Q) DP,Q,V RF-F 100636 AUGMENTED FULL FLOW 2CSE2 Containment Spray Pump 22 205335-1 Containment Spray E4 2 Horizontal Centrifugal Motor Gould Model 3415 S2. OP-ST. CS-0002(0) DP,Q,V Q-R 100672 S2.0P-ST.CS-0005(Q) DP,Q,V RF-F 100636 TP-3 AUGMENTED FULL FLOW 2CVE4 Boric Acid Transfer Pump 21 205328-1 Chemical & Volume Cont E1 2 Horizontal Centrifugal Motor Gould Model 3196MT 82.0P-ST.CVC-0001 (Q) DP,Q,V Q-F 100687 2CVE5 Boric Acid Transfer Pump 22 205328-1 Chemical & Volume Cont E3 2 Horizontal Centrifugal Motor Gould Model 3196MT S2.0P-ST.CVC-0002(Q) DP,Q,V Q-F 100688

TABLE 2 PUMP TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 3 PUMP NO PUMP DESCRIPTION P +ID No P +ID Name Drawing ASME Pump Type Driver Mfg Model ID Coordinates Class TEST PROC  ! TEST TYPE  ! TEST FREQ. REL. REQ.  ! RECUR. TASK TECH. POS. !COMMENTS 2CVE20 Charging and Safety Injection Pump 21 205328-2 Chemical & Volume Cont D3 2 Horizontal Centrifugal Motor Pacific Model IJ ( 11 Stage)

S2.0P-ST.CVC-0003(Q) DP,Q,V Q-R 100676 S2.0P-ST.SJ-0016(Q) j DP, Q, V RF-F 101048 TP-3 AUGMENTED FULL FLOW 2CVE21 Charging and Safety Injection Pump 22 205328-2 Chemical & Volume Cont C3 2 Horizontal Centrifugal Motor Pacific Model IJ (11 Stage)

S2. OP-ST. CVC-0004(0) DP, Q, V  ! Q-R  ! 100677 S2.0P-ST.SJ-0016(Q) DP, Q, V RF-F 101048 TP-3 AUGMENTED FULL FLOW 2CVE22 Charging Pump 23 205328-2 Chemical & Volume Cont 83 2 Positive Displacement Motor Union Model QX-300

' I I I S2.0P-ST.CVC-0005(Q)  ! P, Q, N, V ! Q , 100678  !

2DFE9 Fuel Oil Transfer Pump 22 205249-3 Fuel Oil AS N Positive Displacement Motor Viking Model HL475M AUGMENTED S2.0P-ST.DG-0004(Q)  ! P, Q, V  : Q  ! 100514 2DFE10 Fuel Oil Transfer Pump 21 205249-3 Fuel Oil Al N Positive Displacement Motor Viking Model HL475M AUGMENTED 82.0P-ST.DG-OOOS(Q) P,Q,V Q 101126 2RHE1 Residual Heat Removal Pump 21 205332-1 Residual Heat Removal E3 2 Vertical Centrifugal Motor Ingersoll-Rand Model 8x20W S2.0P-ST.RHR-0001 (Q) DP, Q, V CS-F 101317 TP-3 82.0P-ST.RHR-0001 (Q) DP,Q,V Q-R 100679

TABLE 2 PUMP TEST TABLE 10/1/97 SALEM NUCLEAR PLANT- UNIT 2 Page 4 PUMP NO PUMP DESCRIPTION P +ID No P +ID Name Drawing ASME Pump Type Driver Mfg Model ID Coordinates Class TEST PROC  : TEST TYPE i TEST FREQ. REL. REQ. RECUR. TASK TECH. POS. i COMMENTS 2RHE2 Residual Heat Removal Pump 22 20S332-2 Residual Heat Removal E3 2 Vertical Centrifugal Motor Ingersoll-Rand Model 8x20W S2.0P-ST.RHR-0002(Q) DP, Q, V : CS-F  : 101318 TP-3 S2.0P-ST.RHR-0002(Q) DP,Q,V Q-R 100680 2SJE2 Safety Injection Pump 21 20S334-2 Safety Injection E3 2 Horizontal Centrifugal Motor Pacific Model JTCH (10 Stage)

S2.0P-ST.SJ-0001 (Q)  : DP, Q, V  : Q-R  : 100669 S2.0P-ST.SJ-0014(Q) i DP, Q, V RF-F 100154 TP-3 AUGMENTED FULL FLOW 2SJE3 Safety Injection Pump 22 20S334-2 Safety Injection E6 2 Horizontal Centrifugal Motor Pacific Model JTCH (10 Stage)

S2.0P-ST.SJ-0002(Q) DP,Q,V Q-R 100670 S2.0P-ST.SJ-0014(Q) DP,Q,V RF-F 100154 TP-3 AUGMENTED FULL FLOW 2SWE1 Service Water Pump 21 20S342-1 Service Water Nuclear A CS 3 Vertical Centrifugal Motor Aurora Model D26081D S2.0P-ST.SW-0001 (Q)  ! DP, Q, V i Q-F  ! 100681 .

2SWE2 Service Water Pump 22 20S342-1 Service Water Nuclear A ES 3 Vertical Centrifugal Motor Johnston Model 3171SS (3 Stage)

S2.0P-ST.SW-0002(Q)  : DP, Q, V Q-F 100682 2SWE3 Service Water Pump 23 20S342-1 Service Water Nuclear A GS 3 Vertical Centrifugal Motor Aurora Model D26081 S2.0P-ST.SW-0003(Q) DP,Q,V Q-F 100683

TABLE 2 PUMP TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 5

~---------~----- ___ -,:_-_:;..=:'

PUMP NO PUMP DESCRIPTION P +ID No P +ID Name Drawing ASME Pump Type Driver Mfg Model ID Coordinates Class TEST PROC i TEST TYPE TEST FREQ. REL. REQ. RECUR. TASK TECH. POS. iCOMMENTS 2SWE4 Service Water Pump 24 20S342-2 Service Water Nuclear A CS 3 Vertical Centrifugal Motor Aurora Model D26081 I

I I

I I

I S2.0P-ST.SW-0004(Q)  : DP, Q, V i Q-F  : 100684 i 2SWE5 Service Water Pump 25 20S342-2 Service Water Nuclear A ES 3 Vertical Centrifugal Motor Aurora Model D26081 S2.0P-ST.SW-0005(Q) DP, Q, V  ! Q-F  ! 100685 2SWE6 Service Water Pump 26 20S342-2 Service Water Nuclear A GS 3 Vertical Centrifugal Motor Johnston Model 28 NMC (3 Stage)

S2.0P-ST.SW-0006(Q)  ! DP, Q, V  : Q  : 100686  :

Salem Units 1 & 2 Inservice Test Program

• TABLE 3-1 Salem Unit 1 VALVE TEST TABLE

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 1 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TESTTYPE!TEST FREQ.: C.S. JUST. : R.O. JUST.! REL. REQ.: RECUR. TASK !TECH. pos.! COMMENTS 11AF4 11 AUX FDWTR PMP SPLY CKVL 205236-1 Auxiliary Feedwater 01 3 c CK SELF 6 c O/C Active S1 .OP-ST.AF-0004(0) CTC 0 100717 S1 .OP-ST.AF-0005(0) CTO cs .CS-01 100819 S1 .OP-ST.AF-0001 (0) PS 0 CS-01 100692 12AF4 12 AUX FDWTR PMP SPLY CKVL 205236-1 Auxiliary Feedwater 04 3 c CK SELF 6 c O/C Active S1 .OP-ST.AF-0004(0) CTC 0 100717 S1 .OP-ST.AF-0005(0)_ CTO cs CS-01 100819 S1 .OP-ST.AF-0002(0) PS 0 CS-01 100693 13AF4 13 AUX FDWTR PMP SUCT CKVL 205236-1 Auxiliary Feedwater 07 3 c CK SELF 8 c O/C Active S1 .OP-ST.AF-0004(0) CTC 0 100717 S1 .OP-ST.AF-0007(0) CTO cs CS-01 100515 S1 .OP-ST.AF-0003(0) PS 0 CS-01 100694 11AF8 11 AUX FDWTR PMP DISCH CKVL 205236-1 Auxiliary Feedwater E3 3 c CK SELF 4 c 0 Active S1.0P-ST.AF-0005(0) CTO CS CS-02  !  ! 100819 S1 .OP-ST.AF-0003(0) PS 0 CS-02 100694 12AF8 12 AUX FDWTR PMP DISCH CKVL 205236-1 Auxiliary Feedwater E6 3 c CK SELF 4 c 0 Active S1 .OP-ST.AF-0005(0 CTO cs CS-02 100819

TABLE 3-1.- VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 2 VALVE NO VALVE DESCRIPTION P+ ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREa.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK !TECH. pos.! COMMENTS 13AF8 13 AUX FDWTR PMP DISCH CKVL 205236-1 Auxiliary Feedwater EB 3 c CK SELF 6 c 0 Active

--5*1:0F>~s,.-.AF~aaci7ca> ____________c:r0*----.-------cs _______ r____ cs~-a2*----,-----------------------------------,--------1oas1-i;------,-----------------,------------------------------------------------------------*

11AF11 11 AUX FDWTR STM GEN INLET AIR OPRD GLB VLV 205236-1 Auxiliary Feedwater Gl 3 B GB AIR 4 0 O/C Active S1 .OP-ST.RPl-0001 (Q)  ! PIT 2YR 100298 S1 .OP-ST.AF-0004(Q) STC Q 100717 12AF11 12 AUX FDWTR STM GEN INLET AIR OPRD GLB VLV 205236-1 Auxiliary Feedwater E6 3 B GB AIR 4 0 O/C Active S1 .OP-ST.RPl-0001 (Q)  ! PIT 2YR 100298 S1 .OP-ST.AF-0004(Q) STC Q 100717 13AF11 13 AUX FDWTR STM GEN AIR OPRD GLB VLV 205236-1 Auxiliary Feedwater Fl 3 B GB AIR 4 0 O/C Active S1 .OP-ST.RPl-0001 (Q) i PIT 2YR 100298 S1 .OP-ST.AF-0004(Q) STC Q 100717 14AF11 14 AUX FDWTR STM GEN INLET AIR OPRD GLB VLV 205236-1 Auxiliary Feedwater G6 3 B GB AIR 4 0 O/C Active S1 .OP-ST.RPl-0001 (Q) PIT 2YR 100298 S1 .OP-ST.AF-0004(Q) STC Q 100717

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 3 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK ! TECH. POS.! COMMENTS 11AF21 11 AUX FDWTR STM GEN AIR OPRD GLB VLV 205236-1 Auxiliary Feedwater H6 3 8 GB AIR 4 c MIC Active S1 .OP-ST.AF-0004(Q) FSTO ! Q  ! 100717 S1 .OP-ST.RPl-0001 (Q) PIT 2YR 100298 S1.0P-ST.AF-0004(Q) STC Q 100717 S1 .OP-ST.AF-0004(Q) STO Q 100717 12AF21 12 AUX FDWTR STM GEN INLET AIR OPRD GLB VLV 205236-1 Auxiliary Feedwater F6 3 8 GB AIR 4 c MIC Active S1 .OP-ST.AF-0004(Q) FSTO Q 100717 S1 .OP-ST.RPl-0001 (Q) PIT 2YR 100298 S1 .OP-ST.AF-0004(Q) STC Q 100717 S1 .OP-ST.AF-0004(Q) STO Q 100717 13AF21 13 AUX FDWTR STM GEN INLET AIR OPRD GLB VLV 205236-1 Auxiliary Feedwater F6 3 8 GB AIR 4 c MIC Active

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S1 .OP-ST.AF-0004(Q) FSTO Q 100717 S1 .OP-ST.RPl-0001 (Q) PIT 2YR 100298 S1 .OP-ST.AF-0004(Q) STC Q 100717 S1 .OP-ST.AF-0004(Q) STO Q 100717 14AF21 14 AUX FDTR STM GEN NLET AIR OPRD GLB VLV 205236-1 Auxiliary Feedwater G4 3 8 GB AIR 4 c MIC Active S1 .OP-ST.AF-0004(Q) FSTO Q 100717 S1 .OP-ST.RPl-0001 (Q) PIT 2YR 100298 S1 .OP-ST.AF-0004(Q) STC Q 100717 S1 .OP-ST.AF-0004(Q) STO Q 100717

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 4 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I < I I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK ! TECH. POS.! COMMENTS 11AF23 11 AUX FDWTR STM GEN INLET SCHK 205236-1 Auxiliary Feedwater H10 2 c SCK SELF 4 c O/C Active S1 .OP-ST.AF-0006(0) CTC 0 101150 S1 .OP-ST.AF-0005(0) CTO cs ! CS-03 100819 12AF23 12 AUX FDWTR STM GEN INLET SCHK VLV 205236-1 Auxiliary Feedwater F10 2 c SCK SELF 4 c O/C Active S1 .OP-ST.AF-0006(0) CTC 0 101150 S1 .OP-ST.AF-0005(0) CTO cs ! CS-03 100819 13AF23 13 AUX FDWTR STM GEN INLET SCHK VLV 205236-1 Auxiliary Feedwater F10 2 c SCK SELF 4 c O/C Active S1 .OP-ST.AF-0006(0) CTC 0 101150 S1 .OP-ST.AF-0005(0) CTO cs ! CS-03 100819 14AF23 14 AUX FDWTR STM GEN INLET SCHK VLV 205236-1 Auxiliary Feedwater G10 2 c SCK SELF 4 c O/C Active S1 .OP-ST.AF-0006(0) CTC 0 101150 S1 .OP-ST.AF-0005(0) CTO cs : CS-03 100819 11AF40 11 AUX FDWTR PMP DISCH AIR OPRD GLOBE VLV 205236-1 Auxiliary Feedwater D4 3 B GB AIR 2 0 O/C Active S1 .OP-ST.AF-0004(0) FSTO a 100717 S1 .OP-ST.RPl-0001 (0) PIT 2YR 100298 S1 .OP-ST.AF-0004(0) STC 0 100717 S1 .OP-ST.AF-0004(0) STO 0 100717

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 5 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I ' I I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK ! TECH. POS,! COMMENTS 12AF40 12 AUX FDWTR PMP DISCH AIR OPRD GLOBE VLV 205236-1 Auxiliary Feedwater D6 3 B GB AIR 2 0 O/C Active

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S1 .OP-ST.AF-0004(0) FSTO 0  ! 100717 i  !

S1 .OP-ST.RPl-0001 (0) PIT 2YR 100298 S1 .OP-ST.AF-0004(0) STC 0 100717 S1 .OP-ST.AF-0004(0) STO 0 100717 11AF52 11 AUX FDWTR PMP SUCT AIR OPRD GATE VLV 205236-1 Auxiliary Feedwater E1 3 B PL AIR 6 c O/C Active S1 .OP-ST.RPl-0001 (0) i PIT 2YR 100298 S1 .OP-ST.AF-0004(0) STO 0 100717 12AF52 12 AUX FDWTR PMP SUCT AIR OPRD GATE VLV 205236-1 Auxiliary Feedwater E4 3 B PL AIR 6 c O/C Active S1 .OP-ST.RPl-0001 (0) ! PIT 2YR 100298 S1 .OP-ST.AF-0004(0) STO 0 100717 13AF52 13 AUX FDWTR PMP SUCT AIR OPRD GATE VLV 205236-1 Auxiliary Feedwater El 3 B PL AIR 8 c O/C Active S1 .OP-ST.RPl-0001 (0) ! PIT 2YR 100298 S1 .OP-ST.AF-0004(0) STO 0 100717 11AF53 11 AUX FDWTR PMP SUCT CKVL 205236-1 Auxiliary Feedwater D1 3 c CK SELF 6 c 0 Active SC.MD-PM.ZZ-0044(0) i CTO SAM V-02 ' 202878 ' TP-6

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 6 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC [TEST TYPE !TEST FREQ.: C.S. JUST. j R.O. JUST. j REL. REQ. i RECUR. TASK iTECH. POs.l COMMENTS 12AF53 12 AUX FDWTR PMP SUCT CKVL 205236-1 Auxiliary Feedwater D4 3 c CK SELF 6 c 0 Active SC.MD-PM.ZZ-0044(0) i CTO SAM V-02 202877 TP-6 13AF53 13 AUX FDWTR PMP SUCT CKVL 205236-1 Auxiliary Feedwater D7 3 c CK SELF 8 c 0 Active CTO SAM V-02 202876 TP-6 1AF71 1 AUX FDWTR STOR INLET FROM DMNRLZD WTR CKVL 205236-1 Auxiliary Feedwater G2 3 c CK SELF 16 c c Active SC.MD-PM.ZZ-0045(0)  ! CTC SAM V-03 202872 TP-6 Valve is "COMMON" to Units 1 & 2.

1AF72 1 AUX FDWTR STOR TK DOM WTR TKS SPLY CKVL 205236-1 Auxiliary Feedwater G1 3 c CK SELF 16 c c Active

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1 1AF92 Manual Valve Isolation for Spool Piece Connecting AF to SW 205236-1 Auxiliary Feedwater E1 3 B GT MAN 8 LC O/C Active S1 .OP-ST.AF-0004(0) FSO 0 100717 11AF920 11 AUX FDWTR STM GEN INLET CKVL 205236-1 Auxiliary Feedwater H6 3 c CK SELF 4 c 0 Active S1.0P-ST.AF-0005(0) CTO i CS i CS-05 i 100819 12AF920 12 AUX FDWTR STM GEN INLET CKVL 205236-1 Auxiliary Feedwater F5 3 c CK SELF 4 c 0 Active S1 .OP-ST.AF-0005(0) CTO CS CS-05 100819

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 7 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I TEST PROC ;TEST TYPE ;TEST FREQ.; C.S. JUST. : R.O. JUST. : REL REQ.: RECUR. TASK ;TECH. POS.: COMMENTS 13AF920 13 AUX FDWTR STM GEN INLET CKVL 205236-1 Auxiliary Feedwater FS 3 c CK SELF 4 c 0 Active

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s1 .OP-ST.AF-0005(0)  ! CTO CS  : CS-05  : 100819 14AF920 14 AUX FDWTR STM GEN INLET CKVL 205236-1 Auxiliary Feedwater GS 3 c CK SELF 4 c 0 Active S1 .OP-ST.AF-0005(0) CTO cs  : CS-05 100819 11AF921 11 AUX FDWTR STM GEN INLET CKVL 205236-1 Auxiliary Feedwater H6 3 c CK SELF 4 c O/C Active S1 .OP-ST.AF-0005(0) CTC CS  : CS-06 100819 S1 .OP-ST.AF-0007(0) CTO CS  : CS-06 100515 12AF921 12 AUX FDWTR STM GEN INLET CKVL 205236-1 Auxiliary Feedwater El 3 c CK SELF 4 c O/C Active S1 .OP-ST.AF-0005(0) CTC cs  ; CS-06 100819 S1 .OP-ST.AF-0007(0) CTO cs  : CS-06 100515 13AF921 13 AUX FDWTR STM GEN INLET CKVL 205236-1 Auxiliary Feedwater F6 3 c CK SELF 4 c O/C Active S1 .OP-ST.AF-0005(0) CTC cs  : CS-06 100819 S1 .OP-ST.AF-0007(0) CTO cs  : CS-06 100515 14AF921 14 AUX FDWTR STM GEN INLET CKVL 205236-1 Auxiliary Feedwater Gl 3 c CK SELF 4 c O/C Active S1 .OP-ST.AF-0005(0) CTC CS CS-06 100819 S1 .OP-ST.AF-0007(0) CTO CS CS-06 100515

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 8 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC [TEST TYPE [TEST FREa.l C.S. JUST. : R.O. JUST. : REL. REQ.: RECUR. TASK !TECH. POs.: COMMENTS 11AF923 Manual Cross-Tie Between AF Feeds to Steam Generator 13 and Steam Generator 14 205236-1 Auxiliary Feedwater F5 3 B GT MAN 3 c c Passive No inservice testing required for this component.

12AF923 Manual Cross-Tie Between AF Feeds to Steam Generator 13 and Steam Generator 14 205236-1 Auxiliary Feedwater F5 3 B GT MAN 3 c c Passive No inservice testing required for this component.

11BF13 11 STM GEN FEED & COND ST GEN FDWTR INLET MOTOR OPERATED VALVE AUGMENTED 205202-3 Steam Generator Feed and Condensate D6 N B GT MO 14 0 c Active 51 .OP-ST.RPl-0003(0)  ! PIT 2YR 100301 51 .OP-ST.MS-0002(0) STC cs CS-10 100554 12BF13 12 STM GEN FEED & COND STGEN FDW INLET STOP MOV AUGMENTED 205202-3 Steam Generator Feed and Condensate DB N B GT MO 14 0 c Active 51 .OP-ST.RPl-0003(0) PIT 2YR 100301 51 .OP-ST.MS-0002(0) STC cs CS-10 100554 13BF13 13 STM GEN FEED & COND STGEN FDW INLET MOTOR OPERATED ISLN VALVE AUGMENTED 205202-3 Steam Generator Feed and Condensate D3 N B GT MO 14 0 c Active S1 .OP-ST.RPl-0003(0) PIT 2YR 100301 S1 .OP-ST.MS-0002(0) STC cs CS-10 100554 14BF13 14 STM GEN FEED & COND STGEN FDW INLET MOTOR OPERATED VALVE AUGMENTED 205202-3 Steam Generator Feed and Condensate D11 N B GT MO 14 0 c Active S1 .OP-ST.RPl-0003(Q) PIT 2YR 100301 51 .OP-ST.MS-0002(0) STC cs CS-10 100554

lABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 9 VALVE NO VALVE DESCRIPTION P +JD No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.: C.S. JUST. : R.O. JUST. : REL. REQ.: RECUR. TASK :TECH. pos.: COMMENTS 11BF19 11 STM GEN FEED & COND STGEN FDW INLET AIR OPERATED VALVE AUGMENTED 205202-3 Steam Generator Feed and Condensate E4 N B GB AIR 12 o C Active S1 .OP-ST.MS-0002(0) FSTC cs CS-07 100554 S1 .OP-ST.RPl-0003(0) i PIT 2YR 100301 S1 .OP-ST.MS-0002(0) STC cs CS-07 100554 12BF19 12 STM GEN FEED & COND STGEN FDW INLET AIR OPERATED GLB VALVE AUGMENTED 205202-3 Steam Generator Feed and Condensate E6 N B GB AIR 12 0 c Active S1 .OP-ST.MS-0002(0) FSTC cs CS-07 100554 S1 .OP-ST.RPl-0003(0) ! PIT 2YR 100301 S1 .OP-ST.MS-0002(0) STC cs CS-07 100554 13BF19 13 STM GEN FEED & COND STGEN INLET AIR OPERATED VALVE AUGMENTED 205202-3 Steam Generator Feed and Condensate E1 N B GB AIR 12 0 c Active S1 .OP-ST.MS-0002(0) FSTC CS CS-07 100554 S1 .OP-ST.RPl-0003(0)  ! PIT 2YR 100301 S1 .OP-ST.MS-0002(0) STC . : CS CS-07 100554 14BF19 , 14 STM GEN FEED & COND STGEN FDW INLET AIR OPERATED VALVE AUGMENTED 205202-3 Steam Generator Feed and Condensate E9 N B GB AIR 12 0 c Active S1 .OP-ST.MS-0002(0) FSTC cs CS-07 100554 S1 .OP-ST.RPl-0003(0) PIT 2YR 100301 S1 .OP-ST.MS-0002(0) STC cs CS-07 100554

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 10 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREa.1 C.S. JUST. ! R.O. JUST. 1 REL. REa.1 RECUR. TASK 1TECH. POs.1 COMMENTS 11BF22 11 STM GEN FEED & COND STM GEN FDW INLET MOTOR OPRD STOP CHECK VLV 205202-3 Steam Generator Feed and Condensate F5 2 B/C SCK MO 14 0 C Active S1 .OP-ST.MS-0002(0) CTC cs CS-08 100554 S1 .OP-ST.RPl-0003(0)  !, PIT 2YR 100301 S1 .OP-ST.MS-0002(0) STC cs CS-08 100554 12BF22 12 STM GEN FEED & COND STGEN FDW INLET STOP CHECK VALVE 205202-3 Steam Generator Feed and Condensate FB 2 B/C SCK MO 14 0 c Active

~ ~ -- -- -- -- ---------- ~ ----- -- - - - - - - - - - -. -- ---------------- ------- -------------- - - -

~ - - - --- - - -- -- ------------ ---- --------. ----- - - - - - - - - - - -- -- -- -- .

S1 .OP-ST.MS-0002(0) CTC cs CS-08 100554 S1 .OP-ST.RPl-0003(0) i PIT 2YR 100301 S1 .OP-ST.MS-0002(0) STC cs CS-08 100554 13BF22 13 STM GEN FEED & COND STGEN INLET MOTOR OPERATED STOP CHECK VALVE 205202-3 Steam Generator Feed and Condensate F2 2 B/C SCK MO 14 0 c Active

~ ~ -- -- -- ---- ------------------- - - -- - -- - - - - -- - - - ----------- --- - .

S1 .OP-ST.MS-0002(0) CTC cs CS-08 100554 S1 .OP-ST.RPl-0003(0) ! PIT 2YR 100301 S1 .OP-ST.MS-0002(0) STC cs CS-08 100554 14BF22 14 STM GEN FEED & COND STGEN FDW INLET MOTOR OPRD STOP CHECK VALVE 205202-3 Steam Generator Feed and Condensate F10 2 B/C SCK MO 14 0 c Active S1 .OP-ST.MS-0002(0) CTC cs CS-08 100554 S1 .OP-ST.RPl-0003(0) PIT 2YR 100301 S1 .OP-ST.MS-0002(0) STC cs CS-08 100554

TABLE.3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 11 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator

• Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ) C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK ! TECH. POS.! COMMENTS 11BF40 11 STM GEN FEED & COND STGEN INL CONT VLV 11BF19 BYP AIR OPRD VLV AUGMENTED 205202-3 Steam Generator Feed and Condensate E4 N B GB AIR 4 O/C c Active S1 .OP-ST.MS-0002(0) FSTC cs CS-09 100554 S1 .OP-ST.RPl-0003(0) ! PIT 2YR 100301 S1 .OP-ST.MS-0002(0) STC cs CS-09 100554 12BF40 12 STM GEN FEED & COND STGEN FDW INL CONTVLV BYPAIR OPRD GLB VLV AUGMENTED 205202-3 Steam Generator Feed and Condensate E6 N B GB AIR 4 O/C c Active S1.0P-ST.MS-0002(Q) FSTC CS CS-09 i 100554 S1 .OP-ST.RPl-0003(0)  ! PIT 2YR 100301 S1 .OP-ST.MS-0002(0) STC CS CS-09 100554 13BF40 13 STM GEN FEED & COND STGEN INL CONT VLV 13BF19 BYP AIR OPRD VLV AUGMENTED 205202-3 Steam Generator Feed and Condensate E1 N B GB AIR 4 O/C C Active S1 .OP-ST.MS-0002(0) FSTC CS CS-09 100554 S1 .OP-ST.RPl-0003(0) ! PIT 2YR 100301 S1 .OP-ST.MS-0002(0) STC CS CS-09 100554 14BF40 14 STM GEN FEED & COND STGEN INL CONT VLV 14BF19 BYP AIR OPRD VLV AUGMENTED 205202-3 Steam Generator Feed and Condensate E9 N B GB AIR 4 O/C c Active S1 .OP-ST.MS-0002(0) FSTC cs CS-09 100554 S1 .OP-ST.RPl-0003(0) PIT 2YR 100301 S1 .OP-ST.MS-0002(0) STC cs CS-09 100554

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 12 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.: C.S. JUST. j R.O. JUST. : REL. REQ.: RECUR. TASK j TECH. pos.: COMMENTS 11CA330 11 CONTAINMENT AIR HEADER 1A SUPPLY TO CONTAINMENT BUILDING AIR OPRD VLV 205247-1 No. 1 Unit - React. Cont. & Penetration Area E3 2 A GB AIR 2 O C Active S1 .OP-ST.ZZ-0003(0) FSTC o 100726 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290500 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.ZZ-0003(0) STC o 100726 12CA330 12 CONT AIR HOR 1B SUPPLY TO CONTNMT BLDG AIR OPRD VLV 205247-1 No. 1 Unit - React. Cont. & Penetration Area D3 2 A GB AIR 2 0 c Active S1 .OP-ST.ZZ-0003(0) FSTC o 100726 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290502 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.ZZ-0003(0) STC o 100726 11CA360 11 CONT AIR HOR 1A CONTNMT BLDG CHECK VLV 205247-3 No. 1 Unit- React. Cont. & Penetration Area C1 2 A/C CK SELF 2 0 c Active S1 .RA-IS.ZZ-0001 (0) CTC RF V-04 290501 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290501 12CA360 12 CONT AIR HOR 1B CONTNMT BLDG CHECK VLV 205247-3 No. 1 Unit- React. Cont. & Penetration Area B1 2 A/C CK SELF 2 0 c Active S1 .RA-IS.ZZ-0001 (0) CTC RF i V-04 290503 i S1 .RA-IS.ZZ-0001 (0) LJ 1BMO 290503 1CA1714 1 CONT AIR 100 ELEV AIR LOCK SUPPLY STOP VLV 205247-1 No. 1 Unit - React. Cont. & Penetration Area H3 2 A GB MAN 0.375 c c Passive S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290504

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 13 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ) C.S. JUST. ! R.O. JUST. i REL. REQ. ! RECUR. TASK !TECH. POs.! COMMENTS 1CA1715 1 CONT AIR 130 ELEV AIR LOCK SUPPLY STOP VLV 205247-1 No. 1 Unit - React. Cont. & Penetration Area H4 2 A GB MAN 0.375 c c Passive

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S1 .RA-18.ZZ-0001 (0) LJ 18MO 209505 1CA1768 CONTROL AIR ACCUMULATOR CHECK VALVE AUGMENTED 205247-3 No. 1 Unit - React. Cont. & Penetration Area H4 N AJC CK SELF 1 c c Active 8C.RA-18.PZR-0024(0) ! CTC RF V-05 101093 8C.RA-18.PZR-0024(0) ! LT 2YR 101093 1CA1769 PORV CONTROL AIR SUPPLY CHECK VALVE AUGMENTED 205247-3 No. 1 Unit - React. Cont. & Penetration Area G5 N AJC CK SELF 1 c c Active 8C.RA-18.PZR-0024(0) : CTC RF V-05 101093 SC.RA-18.PZR-0024(0) ! LT 2YR 101093 1CA1770 CONTROL AIR ACCUMULATOR CHECK VALVE AUGMENTED 205247-3 No. 1 Unit - React. Cont. & Penetration Area H6 N AJC CK SELF c c Active

- sC:Rft.~-l-S.-PZR~-6o24(6_) ___ r_ _ CTC-----r-*---RF-------,--**----------*---*---*--v~o5 1

_____ ----*----------- --------101-093---*---;-----**----*-*--- -------*----*-*-*--*-----*-*-**-----* ***---***---**-*-**

8C.RA-18.PZR-0024(0) i LT 2YR 101093 1CA1771 PORV CONTROL AIR SUPPLY CHECK VALVE AUGMENTED 205247-3 No. 1 Unit - React. Cont. & Penetration Area G6 N AJC CK SELF 1 c c Active SC.RA-18.PZR-0024(0)  : CTC  ! RF V-05 101093 i 8C.RA-IS.PZR-0024(0)  ! LT 2YR 101093 1CA2086 11SW534 CONTROL AIR ACCUMULATOR CK VALVE AUGMENTED 205247-1 Control Air CB N c CK SELF .5 c c Active 81.OP-8T.8W-0010(0) CTC 0 101213 81 .RA-18.SW-0001 (Q) LT 2YR (later) DCP 1EC-3668, Rec. Task (RT) prior to restart.

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 14

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------------:---==-.._--=-:..;:____:..__-:. ___.,_ _,

VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC :TEST TYPE :TEST FREQ.: C.S. JUST. : R.O. JUST.: REL. REQ.: RECUR. TASK :TECH. POs.: COMMENTS 1CA2091 11SW535 CONTROL AIR ACCUMULATOR CK VALVE AUGMENTED 20S247-1 Control Air C9 N c CK SELF .S c c Active S1.0P-ST.SW-0010(0) ' CTC . 0 . 101213 S1 .RA-IS.SW-0001 (0) LT 2YR (later) DCP 1 EC-3668, Rec. Task (RT) prior to restart.

1CA2093 12SW534 CONTROL AIR ACCUMULATOR CK VALVE AUGMENTED 20S247-1 Control Air E9 N c CK SELF .S c c Active S1.OP-ST.SW-0010(0) CTC 0 101213 S1 .RA-IS.SW-0001 (0) LT 2YR (later) DCP 1 EC-3668, Rec. Task (RT) prior to restart.

1CA2095 12SW535 CONTROL AIR ACCUMULATOR CK VALVE AUGMENTED 20S247-1 Control Air C6 N c CK SELF .S c c Active S1.OP-ST.SW-0010(0) CTC 0 101213 S1 .RA-IS.SW-0001 (0) LT 2YR (later) DCP 1EC-3668, Rec. Task (RT) prior to restart.

11CC1 11 CMPNT CLG PMP DISCH CKVL 20S231-1 Component Cooling ES 3 c CK SELF 12 0 O/C Active S1 .OP-ST.CC-0001 (0) CTC 0 100697 S1 .OP-ST.CC-0001 (0) CTO 0 100697 12CC1 12 CMPNT CLG PMP DISCH CHECK VALVE 20S231-1 Component Cooling cs 3 c CK SELF 12 0 O/C Active S1 .OP-ST.CC-0002(0) CTC 0 100698 S1 .OP-ST.CC-0002(0) CTO 0 100698

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 15 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification 1 I I I I I I TEST PROC !TEST TYPE !TEST FREQ,: C.S. JUST. : R.O. JUST. : REL. REQ.: RECUR. TASK :TECH. pos.: COMMENTS 13CC1 13 CMPNT CLG PMP DISCH CHECK VLV 205231-1 Component Cooling D5 3 c CK SELF 12 0 O/C Active S1 .OP-ST.CC-0003(0) CTC 0 100699 S1 .OP-ST.CC-0003(0) CTO 0 100699 11CC3 11 CMPNT CLG PMP DISCH HOR CRSVR TO HT EXCH GATE MOV 205231-1 Component Cooling D5 3 B GT MO 16 0 O/C Active S1 .OP-ST.RPl-0001 (0) i PIT 2YR '

. 100298 S1 .OP-ST.CC-0004(0) STC 0 100718 12CC3 12 CMPNT CLG PMP DISCH HOR CRSVR TO HT EXCH GATE MOV 205231-1 Component Cooling D5 3 B GT MO 16 0 O/C Active S1 .OP-ST.RPl-0001 (0) ! PIT 2YR 100298 S1 .OP-ST.CC-0004(0) STC 0 100718 11CC16 11 CMPNT CLG RHR HT EXCHG OUTLET GATE MOV 205231-1 Component Cooling F9 3 B GT MO 12 c 0 Active

~ - - - - -- - --- - - - . -- -- - -- - - -- - - -- - - --- ------------------------ - ----------------- -------------- -------------------------------------- --------.

S1 .OP-ST.RPl-0001 (0) i PIT 2YR 100298 S1 .OP-ST.CC-0004(0) STO 0 100718 12CC16 12 CMPNT CLG RHR HT EXCHG OUTLET MOV 205231-1 Component Cooling AB 3 B GT MO 12 c 0 Active S1 .OP-ST.RPl-0001 (0) PIT 2YR 100298 S1 .OP-ST.CC-0004(0) STO 0 100718

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 16 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I TEST PROC lTEST TYPE !TEST FREQ.: C.S. JUST. ~ R.O. JUST. 1 REL. REQ. ~ RECUR. TASK lTECH. POS.i COMMENTS 1CC17 1 CMPNT CLG PMP SUCT HOR GATE MOV 205231-1 Component Cooling D3 3 B GT MO 12 0 O/C Active

~ - - -- -- - - -- - -- - -- - ---- ------------ - - -- -- -- -- -- - --- -- --- - - --- -- - - -- - --- -- ---- - - .

S1 .OP-ST.RPl-0001 (0) [ PIT 2YR 100298 S1 .OP-ST.CC-0004(0) STC 0 100718 1CC18 1 CMPNT CLG PMP SUCT HOR GATE MOV 205231-1 Component Cooling C3 3 B GT MO 12 0 O/C Active S1 .OP-ST.RPl-0001 (0) : PIT 2YR 100298 S1 .OP-ST.CC-0004(0) STC 0 100718 1CC30 1 CMPNT CLG NO 12 HT EXCHG TO 11 RHR HT EXCH GATE MOV 205231-1 Component Cooling D7 3 B GT MO 16 0 c Active S1 .OP-ST.RPl-0001 (0) [ PIT 2YR 100298 S1 .OP-ST.CC-0004(0) STC 0 100718 1CC31 1 CMPNT CLG SPENT FUEL PIT HT EXCH INLET GATE MOV 205231-1 Component Cooling C6 3 B GT MO 16 0 c Active S1 .OP-ST.RPl-0001 (0) j PIT 2YR 100298 S1 .OP-ST.CC-0004(0) STC 0 100718 1CC71 1 CMPNT CLG LETDOWN HEAT EXCHANGER OUTLET BTFL VLV 205231-2 Component Cooling HS 3 B BF AO 6 0 c Active S1 .OP-ST.CVC-0007(0) FSTC cs CS-47 100582 S1 .OP-ST.RPl-0003(0) PIT 2YR 100301 S1 .OP-ST.CVC-0007(0) STC cs CS-47 100582

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 17

-~--- ---- - -

VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' o I I I I o TEST PROC !TEST TYPE !TEST FREQ.i C.S. JUST. i R.O. JUST. : REL. REQ. i RECUR. TASK i TECH. POs.: COMMENTS 1CC109 1 COMPONENT COOLING EXCESS LETDOWN HEAT EXCHANGER INLET CHECK VALVE 205231-3 Component Cooling D1 2 NIA CK SELF 3 0 0 Active

~ --. - - - -- - - -- - --- - - ----- ---- -- - . - . - - . -- -- -- -- - - -- - -- - .

81 .OP-ST.CC-0004(0)  : CTO i 0  : i i 100718 TP-6 i 1CC112 1 COMP COOLING EXCESS LETDOWN HT EXCHNGR OUTLET SAFETY RELIEF VLV 205231-3 Component Cooling E2 3 C RV SELF 3 c 0 Active SC.MD-PT.ZZ-0007(0)  : RV 5YR  : i i 204867  :

1CC113 1 CMPNT CLG EXCESS LETDOWN HT EXCHG OUTLET AIR OPRD GATE VLV 205231-3 Component Cooling 02 2 A GB AIR 3 O/C c Active 81 .OP-ST.CC-0004(0) i FSTC i 0 100718 81 .RA-IS.ZZ-0001 (0) LJ 18MO 290506 81 .OP-ST.RPl-0004(0) PIT 2YR 100302 81 .OP-ST.CC-0004(0) STC 0 100718 1CC118 1 CMPNT CLG REACTOR COOLANT PMP SPLY HDR GATE MOV 205231-3 Component Cooling CS 2 A GT MO 6 0 c Active 81 .RA-IS.ZZ-0001 (0) LJ 18MO 290508 81 .OP-ST.RPl-0003(0)  : PIT 2YR 100301 81 .OP-ST.CC-0005(0) STC cs CS-11 100487 1CC119 1 CMPNT CLG REACTOR COOLANT PMP SPLY HDR CKVL 205231-3 Component Cooling F5 2 A/C CK SELF 6 0 O/C Active S1 .RA-IS.ZZ-0001 (Q) CTC RF V-06 290509 81 .OP-ST.CC-0004(0) CTO 0 100718 81 .RA-IS.ZZ-0001 (0) LJ 18MO 290509

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 18 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification I I I I I I I TEST PROC !TEST TYPE !TEST FREQ.: C.S. JUST. : R.O. JUST. ; REL. REQ.; RECUR. TASK !TECH. pos.: COMMENTS 11CC128 11 CMPNT CLG REACTOR COOLANT PMP THERM BARR SUPPLY CHECK VLV 205231-3 Component Cooling F5 3 c CK SELF 2 0 c Active CTC RF V-08 100487 12CC128 12 CMPNT CLG REACTOR COOLANT PMP THERM BARR SPLY CHECK VLV 205231-3 Component Cooling F9 3 c CK SELF 2 0 c Active S1 .OP-ST.CC-0005(0) CTC RF V-08 100487 13CC128 13 CMPNT CLG REACTOR COOLANT PMP THERM BARR SPLY CHECK VLV 205231-3 Component Cooling C6 3 c CK SELF 2 0 c Active S1 .OP-ST.CC-0005(0) CTC RF V-08 100487  :  :

14CC128 14 CMPNT CLG REACTOR COOLANT PMP THERM BARR SPLY CHECK VLV 205231-3 Component Cooling cg 3 c CK SELF 2 0 c Active S1 .OP-ST.CC-0005(0) CTC RF V-08 100487 11CC129 11 CMPNT CLG REACTOR COOLANT PMP THERM BARR OUT SAF RLF VLV 205231-3 Component Cooling G7 3 c RV SELF 0.75 c O/C Active

~  ; - - - - - - - -- - - -- - -- -. -- - - - - -- --- - - - ---- ----- -- ; - - ---- -- - ------ - - --------------- ---------------- - --- -- -- -- -- - - - - -- -- - - -- - - - - - - .

SC.MD-PT.ZZ-0007(0) RV 5YR  : i 290083  :

12CC129 12 CMPNT CLG REACTOR COOLANT PMP THERM BARR OUT SAF RLF VLV 205231-3 Component Cooling G10 3 C RV SELF 0. 75 C O/C Active SC.MD-PT.ZZ-0007(0) RV 5YR 290085 13CC129 13 CMPNT CLG REACTOR COOLANT PMP THERM BARR OUT SAF RLF VLV 205231-3 Component Cooling D7 3 c RV SELF 0.75 c O/C Active SC.MD-PT.ZZ-0007(0) RV SYR 290087

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 19 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification 1 I I o I I I TEST PROC jTEST TYPE jTEST FREQ.j C.S. JUST. j R.O. JUST. j REL. REQ. j RECUR. TASK !TECH. POS.! COMMENTS 14CC129 14 CMPNT CLG REACTOR COOLANT PMP THERM BARR OUT SAF RLF VLV 205231-3 Component Cooling D10 3 c RV SELF 0.75 c O/C Active

-; ~

SC.MD-PT.ZZ-0007(0) RV 5YR 290089 1CC131 1 CMPNT CLG REACTOR COOLANT PMP THERM BARR RTN HOR GLB MOV 205231-3 Component Cooling C4 2 A GT MO 3 0 c Active

- - - - - - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - -. - - - - - - - - - - - - - - - - - -. - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -; - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - .

S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290510 S1 .OP-ST.RPl-0003(0) i PIT 2YR 100301 S1 .OP-ST.CC-0005(0) STC cs CS-12 100487 1CC135 1 CMPNT CLG REACTOR COOLANT PMP UPR & LWR BRG RTN HOR SAF RLF VLV 205231-3 Component Cooling E3 3 C RV SELF 3 c O/C Active

---

,------------------,------------------:-------------------:-------------------:------------------;-------------------------.------------------7------------------------------------------------------------

SC.MD-PT.ZZ-0007(0) RV 5YR 290091 1CC136 1 CMPNT CLG REACTOR COOLANT PMP BRG RTN HOR GATE MOV 205231-3 Component Cooling C4 2 A GT MO 6 0 c Active S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290513 S1 .OP-ST.RPl-0003(0) j PIT 2YR 100301 S1 .OP-ST.CC-0005(0) STC cs CS-12 100487 1CC147 1 CMPNT CLG SURGE TANK SAF RLF VLV 205231-1 Component Cooling F1 3 c RV SELF 3 c O/C Active SC.MD-PT.ZZ-0007(0) RV 5YR 290095  ! j 1CC148 1 CMPNT CLG SURGE TANK VACUUM BREAKER 205231-1 Component Cooling F2 3 c RV SELF 1 c O/C Active PTC-25.3 (Crane Proc.) ! RV 5YR 202231

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 20 VALVE NO VALVE DESCRIPTION P+ ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC [TEST TYPE [TEST FREQ.: C.S. JUST. : . RO. JUST. : REL REQ.: RECUR. TASK [TECH. pos.l COMMENTS 1CC149 1 CMPNT CLG SURGE TANK TO VENT HOR AIR CPR GLB VLV 205231-1 Component Cooling F2 3 8 GB AIR 2 0 C Active

... .. 100718 S1 .OP-ST.CC-0004(0) FSTC 0 . .

S1 .OP-ST.RPl-0001 (0) j PIT 2YR 100298

. S1 .OP-ST.CC-0004(0) STC 0 100718 1CC186 1 CMPNT CLG REACT COOL PMP BRG RTN HOR MOV 1CC187 BYP CKVL 205231-3 Component Cooling E3 2 A/C CK SELF 0.75 c O/C Active

---

.------------------.------------------;------------------;------------------;-----------------.-------------------------;-----------------7---------------------------------------------------------

S1 .RA-IS.ZZ-0001 (0) CTC RF V-07 290514 S1 .OP-ST.CC-0005(0) CTO RF V-07 100487 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290514 1CC187 1 CMPNT CLG REACTOR COOLANT PMP BRG RETURN HEADER GATE MOV 205231-3 Component Cooling E4 2 A GT MO 6 0 c Active S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290515 S1 .OP-ST.RPl-0002(0) j PIT 2YR 100299 S1 .OP-ST.CC-0005(0) STC cs CS-12 100487 1CC190 1 CMPNT CLG REACTOR COOLANT PMP THERM BARR OUT HOR GLB MOV 205231-3 Component Cooling D4 2 A GT MO 3 0 c Active S1 .RA-IS.ZZ-0001 (0)  : LJ 18MO 290511  :

S1 .OP-ST.RPl-0002(0)  ! PIT 2YR 100299 S1 .OP-ST.CC-0005(0) STC CS CS-12 100487 1CC195 COMPONENT COOLING DEMINERALIZED WATER SUPPLY CHECK VALVE 205231-1 Component Cooling D1 3 c CK SELF 3 O/C c Active SC.RA-IS.ZZ-0007(0)  :. CTC .: 0 290859

TABLE 3 VALVE TEST TABLE .

10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 21 VALVE NO VALVE DESCRIPTION P +JD No P+ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I  ! I I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK iTECH. POS.! COMMENTS 1CC208 1 CMPNT CLG REACT COOL PMP THERM BARR OUT HOR MOV 1CC190 BYP CKVL 205231-3 Component Cooling 04 2 A/C CK SELF 0. 75 C O/C Active 81 .RA-18.ZZ-0001 (0) CTC RF V-07 290512 81 .OP-8T.CC-0005(0) CTO RF V-07 100487 81 .RA-18.ZZ-0001 (0) LJ 18MO 290512 1CC210 COMPONENT COOLING PRIMARY WATER SUPPLY CHECK VALVE 205231-1 Component Cooling 01 3 c CK SELF 3 O/C c Active 8C.RA-18.ZZ-0007(0) CTC o 290859 1CC215 1 CMPNT CLG EXCESS LETDOWN HT EXCHG INLET AIR OPRD GATE VLV 205231-3 Component Cooling' 01 2 A PL AIR 3 0 c Active 81 .OP-8T.CC-0004(0) F8TC o 100718 81 .RA-18.ZZ-0001 (0) LJ 18MO 290507 81 .OP-8T.RPl-0004(0) PIT 2YR 100302 81 .OP-8T.CC-0004(0) 8TC o 100718 1CC317 1 CMPNT CLG CHGR SAF INJ PMP 11 HT EXCH SPLY CHECK 205231-1 Component Cooling 07 3 C CK SELF 1 0 0 Active 81.0P-8T.CC-0004(0) CTO 0 i 100718 i 1CC320 1 CMPNT CLG CHGR SAF INJ PMP HT EXCH SPLY CKVL 205231-1 Component Cooling G6 3 c CK SELF 1 0 0 Active 81 .OP-8T.CC-0004(0) CTO o  ! i 100718 i

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 22 VALVE NO VALVE DESCRIPTION P + ID No P + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. i RECUR. TASK !TECH. POS.! COMMENTS.

11CH13 11 CHL WTR PMP DISCH CKVL 205216-1 Chilled Water G3 3 c CK SELF 4 0 O/C Active

---

.------------------.------------------;------------------;------------------:------------------.-------------------------:------------------7-----------------------------------------*-----------------**

S1 .OP-ST.CH-0001 (0) CTC ' 0 100700 '

S1 .OP-ST.CH-0001 (0) CTO 0 , : 100700 12CH13 12 CHL WTR PMP DISCH CKVL 205216-1 Chilled Water G4 3 c CK SELF 4 0 O/C Active

--- - -- - -- ----------------- - - -- -- - ---------. -- ------- --- - - - - - -. -------- --------- - ~ - - - -- ---- -- -------:' --------------- --- :' -- - - --- -- --------. -------------- ---- ------- ~ -- - - - -- - -- -- - ----: ---------- -------- - - -- -- ------ - -- - -- - - - --- -- - - - -- - -- -- -- - - --.

S1 .OP-ST.CH-0002(0) CTC o 100701 S1 .OP-ST.CH-0002(0) CTO o 100701 1CH30 1 CHLWTR SPLY TO NORTH PEN AREA COOLERS AIR OPRD GLB VLV 205216-1 Chilled Water G1 3 B GB AIR 3 0 c Active

~ ~

S1 .OP-ST.CH-0003(0) FSTC o 100756 S1 .OP-ST.RPl-0004(0) j PIT 2YR 100302 S1 .OP-ST.CH-0003(0) STC o 100756 1CH55 1 CHL WTR FRESH WTR SPLY HOR CKVL 205216-1 Chilled Water Cl 3 c CK SELF 1 c c Active

- ----- -- -- -- -- -- -- -- -- ------ -- -- - - -- - -----.-- -- -- -- - - -- -- ----.-- ---- - - - - - - - - - - - -~- -- -- ---- -- -- - --- -- -- -- -- -- -- ---- - -

-~ ~ - - - -- - - -- -- -- -- --:-- -- ---- ---- -- --- --- -- -- -~ - - -- -- - - - - -- - -- - - ~ -- -- ------ ------ - -- - -- -- -- -- -- -- -- -------- - - - --- ---- -- - - - - - - .

S1 .OP-ST.CH-0003(0) CTC o 100756 1CH61 1 CHL WTR NORTH PEN AREA COOLERS RETURN LINE CKVL 205216-1 Chilled Water G1 3 c CK SELF 3 0 c Active

--5*1:0P~ST.-CH~ooo3(o)'-----*----*CTC*-------***---a*-***-*-,------*--------*-*:*----------*--*--------*------*-----*-------1oo756-------,--*--**-****--*-*:*--* .. *--**-** .. **--...................................... ..

1CH74 1 CHL WTR AIR COND UNIT COIL OUTLET/RETURN LINE AIR OPRD 3WAY VLV 205216-1 Chilled Water D2 3 B 3WAY AIR 3 O/C 0 Active S1 .OP-ST.CH-0003(0) FSTO o 100756 S1 .OP-ST.CH-0003(0) STO o 100756

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 23 VALVE NO VALVE DESCRIPTION P + ID No P + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I I I TEST PROC !TEST TYPEiTEST FREQ.! C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK !TECH. POS.~ COMMENTS 1CH117 1 CHL WTR CHILLER CLR OUT HOR TO COUNT RM COOLER AIR OPRD GATE VLV 205216-2 Chilled Water D11 3 B GB AIR 2 0 C Active 52.0P-5T.CH-0003(Q) F5TC Q 100448 52.0P-5T.RPl-0004(Q) \ PIT 2YR 100872 52.0P-5T.CH-0003(Q) 5TC Q 100448 1CH132 1 CHL WTR LAB CLR TO PMP SUCT HOR CKVL 205216-2 Chilled Water E10 3 c CK SELF 2 0 c Active

---

.------------------.------------------;-------------------:------------------:----*------------:-------------------------:-----------------7------------------------------------------------------------*

52.0P-5T.CH-0003(Q) CTC Q 100448 ' '

1CH143 1 CHL WTR EXPAN TK VENT SAFETY RELIEF VALVE 205216-1 Chilled Water F6 3 c RV SELF 0.75 c O/C Active 5C.MD-PT.ZZ-0007(Q) RV 5YR 290097 1CH150 1 CHL WTR CHILLER CLR OUT HOR TO COUNTING RM CLR AIR OPRD GATE VLV 205216-2 Chilled Water E11 3 B GB AIR 2 0 c Active 52.0P-5T.CH-0003(Q) F5TC Q 100448 52.0P-5T.RPl-0004(Q)  ! PIT 2YR 100872 52.0P-5T.CH~0003(Q) 5TC Q 100448 1CH151 1 CHL WTR SPLY TO NORTH PEN AREA COOLERS AIR OPRD GLB VLV 205216-1 Chilled Water G1 3 B GB AIR 3 0 c Active 51 .OP-5T.CH-0003(Q) F5TC Q 100756 51 .OP-5T.RPl-0004(Q) PIT 2YR 100302 51 .OP-5T.CH-0003(Q) 5TC Q 100756

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 24 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification 1 I I I I I I I TEST PROC iTEST TYPE iTEST FREQ . i C.S. JUST. ! R.O. JUST. i REL. REQ. i RECUR. TASK ! TECH. POS.! COMMENTS 1CH168 1 CHL WTR EMERG AIR COND COIL OUTLET AIR OPRD GLB VLV 205216-1 Chilled Water D5 3 B GB AIR 1.5 0 0 Passive

~ -

No inservice testing required for this component.

1CH216 1 CHL WTR EMERG CONT AIR COMP SPLY LINE AIR OPRD GLB VLV 205216-3 Chilled Water E7 3 B GB AIR 2 c 0 Active 51.0P-ST.CH-0003(0) FSTO  : 0 100756 51.0P-ST.CH-0003(0) STO 0 100756 1CH220 1 CHL WTR EMERG CONT AIR COMP INTER CLR INLET VENT SAF RLF VLV 205216-3 Chilled Water EB 3 c RV SELF 0.75 c 0 Active

_- ~

SC.MD-PT.ZZ-0007(0) RV 5YR  ! '  ! 290099 1CH232 1 CHL WTR CHILLER CLR TO EMERG CONT AIR COMP CKVL 205216-3 Chilled Water D7 3 c CK SELF 2 c 0 Active

' ~

S1 .OP-ST.CH-0003(0) CTO 0  ! 100756 i 1CH252 1 CHL WTR RAD MONITOR ENCLOSURE SPLY LINE AIR OPRD GATE VLV 205216-1 Chilled Water H2 3 B GB AIR 1 0 c Active S1 .OP-ST.RPl-0004(0) ! PIT 2YR 100302 S1 .~i:,>-ST.CH-0003(0) STC 0 100756 1CH253 1 CHL WTR RAD MONITOR ENCLOSURE SPLY LINE AIR OPRD GATE VLV 205216-1 Chilled Water H2 3 B GB AIR 1 0 c Active S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.CH-0003(0) STC 0 100756

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 25 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I 1 TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK !TECH. POS.! COMMENTS 1CH260 1 CHL WTR RAD MON ENCL TO PMP SUCT HOR CKVL 205216-1 Chilled Water E2 3 C CK SELF 1 0 C Active

---

.------------------.------------------:-------------------:-------------------.------------------.-------------------------:------------------7*-----------------------------------------------------------*

CTC 0 100756 11CS2 11 CONT SPRAY PMP DISCH MOT OP GATE VLV 205235-1 Containment Spray H6 2 A GT MO 8 c O/C Active S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290516 S1 .OP-ST.RPl-0001 (0) PIT 2YR 100298 S1 .OP-ST.C8-0003(0) 8TC 0 100719 81 .OP-ST.C8-0003(0) 8TO 0 100719 12CS2 12 CONT SPRAY PMP DISCH MOV 205235-1 Containment Spray E6 2 A GT MO 8 c O/C Active

~ ~ --- --- -- - - -- - - - - - : -- - - -- -- -- ---------- - - - - -- -- -- -- - - -- -- - - -- -------- - -- - -- - - - - .

81 .RA-18.ZZ-0001 (0) j LJ 18MO j 290518 j S1 .OP-8T.RPl-0001 (0) PIT 2YR 100298 S1 .OP-8T.C8-0003(0) 8TC 0 100719 S1 .OP-8T.C8-0003(0) 8TO 0 100719 11CS4 11 CONT SPRAY PMP DISCH SWG CK VLV 205235-1 Containment Spray HB 2 c CK SELF 8 c O/C Active S1 .OP-8T.C8-0005(0) CTO RF ' V-09 100754 '

12CS4 12 CONT SPRAY PMP DISCH SWG CK VLV 205235-1 Containment Spray EB 2 c CK SELF 8 c O/C Active S1 .OP-ST.C8-0005(0) CTO RF V-09  ! 100754 i

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 26 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification I ' I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK !TECH. POS.! COMMENTS 11CS5 11 CONT SPRAY PENETRATION AREA SAF RLF VLV 20S23S-1 Containment Spray G9 2 NIA RV SELF 0.7S c c Passive

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - "; - - - - - - - - - - - - - - - - - -. - - - - - - - - - - - - - - - - - - : - - - - - - - - - - - - - - - - - - ~ - - - - - - - - - - - - - - - - - - .- - - - - - - - - - - - - - - - - -. - - - - - - - - - - - - - - - - - - - - - - - - - : - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

• No inservice testing required for this component.

12CS5 12 CONT SPRAY PENETRATION AREA SAF RLF VLV 20S23S-1 Containment Spray EB 2 N/A RV SELF 0.75 c c Passive

---

.------------------.------------------;-------------------:-------------------:-----------------.-------------------------:------------------7------------------------------------------------------------*

No inservice testing required for this component.

1CS12 1 CONT SPRAY ADD TANK VAC BREAKER 20S23S-1 Containment Spray CS 3 c RV SELF 1 c O/C Active

---

.------------------.------------------:-------------------;------------------;-----------------.-------------------------.------------------7------------------------------------------------------------

5C.MD-PM.C5-0002(Q)  ! RV  ! 5YR . j 204785 1CS13 1 CONT SPRAY ADD TANK VAC BREAKER 20S23S-1 Containment Spray cs 3 c RV SELF 1 c 0 Active SC.MD-PM.CS-0002(Q)  ! RV 5YR 204786 1CS14 1 CONT SPRAY ADD TANK OUTLET MOT OP GATE VLV 20S23S-1 Containment Spray Bl 3 B GT MO 3 0 0 Active S1 .OP-ST.RPl-0001 (Q) PIT 2YR 100298 51 .OP-ST.CS-0003(0) STO 0 100719 1CS16 1 CONT SPRAY.ADD TANK OUTLET MOT OP GATE VLV 20S23S-1 Containment Spray D7 3 B GT MO 3 c 0 Active 51 .OP-ST.RPl-0001 (0) PIT 2YR 100298 51 .OP-5T.CS-0003(0) STO Q 100719

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 27 VALVE NO VALVE DESCRIPTION P+ ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.: C.S. JUST. : R.O. JUST. ! REL. REQ.: RECUR. TASK !TECH. POS.: COMMENTS 1CS17 1 CONT SPRAY ADD TANK OUTLET MOT OP GATE VLV 205235-1 Containment Spray 07 3 8 GT MO 3 c 0 Active S1 .OP-ST.RPl-0001 (0)  ! PIT 2YR 100298 S1 .OP-ST.CS-0003(0) STO 0 100719 11CS21 11 CONT SPRAY EDUCTOR SUP SWG CK VLV 205235-1 Containment Spray G7 3 c CK SELF 3 c O/C Active

-~

S1 .OP-ST.CS-0001 (0) CTC 0 ' 100707 '

S1 .OP-ST.CS-0001 (0) CTO 0 100707 12CS21 12 CONT SPRAY EDUCTOR SUPPLY CHECK VLV 205235-1 Containment Spray F6 3 c CK SELF 3 c O/C Active S1 .OP-ST.CS-0002(0) CTC 0 100708 S1 .OP-ST.CS-0002(0) CTO 0 100708 1CS26 1 CONT SPRAY ADD TANK SAF RLF VLV 205235-1 Containment Spray C4 3 c RV SELF 0.75 c O/C Active SC.MD-PT.ZZ-0007(0) RV SYR 290105 11CS36 11 CONT SPRAY RESIDUAL HT EXCHG TO SPRAY HOR MOT OP GATE STOP VLV 205235-1 Containment Spray H9 2 8 GT MO 8 c O/C Active S1 .OP-ST.RPl-0003(0) PIT 2YR 100301 S1 .OP-ST.CS-0004(0) STC cs CS-16 100489 S1 .OP-ST.CS-0004(0) STO cs CS-16 100489

TABLE 3 VALVE-TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 28 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC [TEST TYPE [TEST FREQ.: C.S. JUST. : R.O. JUST. [ REL. REQ. j RECUR. TASK j TECH. POS.j COMMENTS 12CS36 12 CONT SPRAY RESIDUAL HT EXCHG TO SPRAY HOR MOT OP GATE STOP VLV 205235-1 Containment Spray E9 2 B GT MO 8 C O/C Active S1 .OP-ST.RPl-0003(0) PIT 2YR 100301 S1.0P-ST.CS-0004(0) STC CS  : CS-16 100489 S1 .OP-ST.CS-0004(0) STO CS  ! CS-16 100489 11CS48 11 CONT SPRAY PMP DISCH SWG CK VLV 205235-1 Containment Spray H10 2 A/C CK SELF 8 c O/C Active S1 .RA-18.ZZ-0001 (0) CTC RF V-10 290517

. S1 .OP-ST.CS-0005(0) CTO RF V-10 . , 100754 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290517 12CS48 12 CONT SPRAY PMP DISCH SWG CK VLV 205235-1 Containment Spray E10 2 A/C CK SELF 8 c O/C Active 81 .RA-18.ZZ-0001 (0) CTC RF V-10 290519 81 .OP-ST.CS-0005(0) CTO RF V-10 100754 81 .RA-18.ZZ-0001 (0) LJ 18MO 290519 1CS900 1 CONT SPRAY SAMPLE TEST CONN GLB VLV 205235-1 Containment Spray G9 2 A GB MAN 0.375 c c Passive

---

.------------------------------------:-------------------:------------------.------------------.-------------------------:-----------------7------------------------------------------------------------*

LJ 18MO 290520 1CS901 1 CONT SPRAY SAMPLE TEST CONN GLB VLV 205235-1 Containment Spray F9 2 A GB MAN 0.375 c c Passive S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290521

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 29 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC [TEST TYPE [TEST FREQ.[ C.S. JUST. [ R.O. JUST. [ REL. REQ. [ RECUR. TASK iTECH. POS.[ COMMENTS 1CS902 1 CONT SPRAY TEST CONNECTION GLB VLV 205235-1 Containment Spray GB 2 A GB MAN 0.375 C C Passive S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290522 1CV3 1 eve LET DOWN ORIFICE ISOLATION AIR OPRD GLB VLV 205228-2 Chemical and Volume Control Operation FB 2 A GB AIR 2 0 c Active

~  :'  :' ~

S1 .OP-ST.CVC-0006(0) FSTC 0 100720 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290524 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.CVC-0006(0) STC 0 100720 1CV4 1 eve REGENERATIVE HT EXCH TO LET DOWN HT EXCH AIR OPRD GLB VLV 205228-2 Chemical and Volume Control Operation F9 2 A GB AIR 2 0 c Active S1 .OP-ST.CVC-0006(0) FSTC 0 100720 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290525 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.CVC-0006(0) STC 0 100720 1CV5 1 eve LET DOWN ORIFICE ISOLATION AIR OPRD GLB VLV 205228-2 Chemical and Volume Control Operation F9 2 A GB AIR 2 0 c Active S1. OP-ST.CVC-0006(0) FSTC 0 100720 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290526 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.CVC-0006(0) STC 0 100720 1CV6 1 eve REGENERATIVE HT EXCH TO LET DOWN HT EXCH SAF RLF VLV 205228-2 Chemical and Volume Control Operation G9 2 C RV SELF 2 c 0/C Active SC.MD-PT.ZZ-0007(0) RV 5YR  !  ! . 290107  !  !

TABLE 3-1.- VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 30 VALVE NO VALVE DESCRIPTION P+ ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I I TEST PROC iTEST TYPE iTEST FREQ.i C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK iTECH. POS.i COMMENTS 1CV7 1 eve LET DOWN HT EXCH INLET AIR OPRD GLB VLV 205228-2 Chemical and Volume Control Operation GB 2 A PL AIR 2 0 c Active S 1.OP-ST. CVC-0007 (0) FSTC cs CS-17 100582 S1 .RA-IS.ZZ-0001 (Q) LJ 18MO 290527 S1 .OP-ST.RPl-0003(0) PIT 2YR 100301 S1 .OP-ST.CVC-0007(0) STC cs CS-17 100582 1CV40 1 eve VOL CONT TK OUTLET GATE MOV 205228-1 Chemical and Volume Control Operation E9 2 B GT MO 4 0 c Active S1 .OP-ST.RPl-0003(0) PIT 2YR 100301 S1 .OP-ST.CVC-0007(0) i STC CS  ; CS-18 100582 1CV41 1 eve VOL CONT TK OUTLET GATE MOV 205228-1 Chemical and Volume Control Operation D9 2 B GT MO 4 0 c Active

~

S1 .OP-ST.RPl-0003(0) PIT 2YR 100301 S1 .OP-ST.CVC-0007(0) i STC cs CS-18 100582 1CV42 1 eve VOL CONT TK OUTLET CKVL 205228-1 Chemical and Volume Control Operation D9 2 c CK SELF 4 0 0 Passive

---

.------------------------------------.-------------------.-------------------.------------------.-------------------------.------------------7---------------------------------------------------------

No inservice testing required for this component.

1CV43 1 eve CHG SAF INJ PMP SUCT HOR SAF RLF VLV 205228-2 Chemical and Volume Control Operation E2 2 c RV SELF 0.75 c O/C Active SC.MD-PT.ZZ-0007(0) RV SYR 290109

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 31 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I o I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK !TECH. POS.! COMMENTS 1CV47 1 eve CHG SAF INJ PMP NO 11 DISCH CKVL 20S22B-2 Chemical and Volume Control Operation DS 2 c CK SELF 4 c O/C Active S1 .OP-ST.CVC-0003(Q) CTC Q 100702 S1 .OP-ST.SJ-0016(Q) CTO RF V-11 101056 S1 .OP-ST.CVC-0003(Q) PS Q 100702 1CV52 1 eve CHARGING SAFETY INJ PMP NO 12 DISCH CKVL 20S22B-2 Chemical and Volume Control Operation cs 2 c CK SELF 4 c DIC Active S1 .OP-ST.CVC-0004(Q) CTC Q 100703 81 .OP-ST.SJ-0016(Q) CTO RF V-11 101056 S1 .OP-ST.CVC-0004(Q) PS Q 100703 1CV63 1 eve RECIPROCATING CHARGING PMP DISCH CKVL 20S22B-2 Chemical and Volume Control Operation AS 2 c CK SELF 3 0 0 Active

~ ~

S1 .OP-ST.CVC-0005(Q) i CTO i Q i i 100704 1CV68 1 eve REGENERATIVE HT EXCH INLET GATE MOV 20S22B-2 Chemical and Volume Control Operation DB 2 A. GT MO 3 0 O/C Active S1 .RA-IS.ZZ-0001 (Q) LJ 18MO 290610 S1 .OP-ST.RPl-0003(Q) i PIT 2YR 100301 S1 .OP-ST.CVC-0007(Q) ! STC cs CS-19 100582 1CV69 1 eve REGENERATIVE HT EXCH INLET GATE MOV 20S22B-2 Chemical and Volume Control Operation DB 2 A GT MO 3 0 O/C Active S1 .RA-IS.ZZ-0001 (Q) LJ 18MO 290611 S1 .OP-ST.RPl-0003(0) PIT 2YR 100301 S1 .OP-ST.CVC-0007(Q) STC cs CS-19 100582

TABLE 3-1 -. VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 32 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST.! REL. REQ. ! RECUR. TASK !TECH. POS.! COMMENTS 1CV71 1 eve CHG SAFETY INJ TO REGEN HT EXCH INLET AIR OPRD GLB VLV 205228-2 Chemical and Volume Control Operation C7 2 B GB AIR 3 0 0 Passive No inservice testing required for this component.

1CV74 1 eve REGENERATIVE HT EXCH INLET CKVL 205228-2 Chemical and Volume Control Operation E10 2 A/C CK SELF 3 0 O/C Active

-  ;-  ;-  ;- ~ -- - - - - - ----- -- -- --- ----------------------- -- ---- --- --- - -- - - - .

81.RA-IS.ZZ-0001(0) CTC RF ' V-12 ' 290612 S1 .OP-ST.CVC-0006(0) i CTO 0 100720 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290612 1eV75 1 eve REGEN HT EXeH TO REAC PRESSURIZER AIR OPRD GLB VLV 205228-2 Chemical and Volume Control Operation E10 1 B GB AIR 2 c O/C Active S1 .OP-ST.CVC-0007(0) . FSTC ; CS . CS-44 . .  : 100582 . .

S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.CVC-0007(0) STC CS CS-44 100582 S1 .OP-ST.CVC-0007(0) STO CS CS-44 100582 1CV76 1 eve REGEN HT EXCH TO REAC PRESSURIZER CKVL 205228-2 Chemical and Volume Control Operation D10 1 c CK SELF 2 c 0 Active S1 .OP-ST.CVC-0007(0)  ! CTO cs  : CS-13 100582 1CV77 1 eve REGEN HT EXCH TO REAC COOL CHG LINE AIR OPRD GLB VLV 205228-2 Chemical and Volume Control Operation E10 1 B GB AIR 3 C!O 0 Active S1 .OP-ST.CVC-0006(0) FSTO 0 100720 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.CVC-0006(0) STO 0 100720

TABLE 3 VALVE TEST TABLE 1011197 SALEM NUCLEAR PLANT - UNIT 1 Page 33 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I t TEST PROC iTEST TYPE iTEST FREO.i C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK iTECH. POS.i COMMENTS 1CV78 1 eve REGEN HT EXCH TO REAC COOL CHG LINE CKVL 205228-2 Chemical and Volume Control Operation E11 1 c CK SELF 3 0 0 Active

; ~

S1 .OP-ST.CVC-0006(0) ! CTO o 100720 1CV79 1 eve REGEN HT EXCH TO REAC COOL CHG LINE AIR OPRD GLB VLV 205228-2 Chemical and Volume Control Operation E10 1 B GB AIR 3 DIC 0 Active S1 .OP-ST.CVC-0006(0) FSTO o 100720 S1 .OP-ST.RPl-0002(0) ! PIT 2YR 100299 S1 .OP-ST.CVC-0006(0) i STO o 100720

,cvso 1 eve REGEN HT EXCH TO REAC COOL CHG LINE CKVL 205228-2 Chemical and Volume Control Operation E11 1 c CK SELF 3 c 0 Active S1 .OP-ST.CVC-0006(0) i CTO o 100720 11CV99 11 eve REAC COOL PMP SUCT CKVL 205228-3 Chemical and Volume Control Operation F3 2 A/C CK SELF 2 0 c Active S1 .RA-IS.ZZ-0001 (0) CTC RF V-13 290531 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290531 12CV99 12 eve REAC COOL PMP SUCT CKVL 205228-3 Chemical and Volume Control Operation F3 2 A/C CK SELF 2 0 c Active S1 .RA-IS.ZZ-0001 (0) CTC RF V-13 290532 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290532 13CV99 13 eve REAC COOL PMP SUCT CKVL 205228-3 Chemical and Volume Control Operation C3 2 A/C CK SELF 2 0 c Active S1 .RA-IS.ZZ-0001 (0) CTC RF V-13 290533 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290533

TABL.E 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 34 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

• O I I I I I TEST PROC !TEST TYPE !TEST FREQ.: C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK i TECH. POS.! COMMENTS 14CV99 14 eve REAC COOL PMP SUCT CKVL 205228-3 Chemical and Volume Control Operation 83 2 A/C CK SELF 2 0 c Active S1 .RA-IS.ZZ-0001 (Q) CTC RF V-13 290534 S1 .RA-IS.ZZ-0001 (Q) LJ 18MO 290534 1CV115 1 eve REAC COOL PMP DISCH HOR SAF RLF VLV 205228-3 Chemical and Volume Control Operation C1 2 c RV SELF 2 c O/C Active

-; -; ~

RV 5YR 202137 1CV116 1 eve SEAL WTR FILTER INLET GATE MOV 205228-2 Chemical and Volume Control Operation HS 2 A GT MO 4 0 c Active

---

.------------------.------------------:------------------::-------------------;:------------------.-------------------------::------------------7------------------------------------------------------------

S1 .RA-IS.ZZ-0001 (Q) LJ 18MO 290528 S1 .OP-ST.RPl-0003(Q) ! PIT 2YR 100301 S1 .OP-ST.CVC-0007(0)  ! STC cs CS-20 100582 1CV135 1 eve CHG SAF INJ PMP NO 11 TO SEAL WTR HT EXCH CKVL 205228-2 Chemical and Volume Control Operation E4 2 c* CK SELF 2 c 0 Active

~ ~

S1 .OP-ST.CVC-0003(Q) ! CTO Q 100702 1CV137 1 eve CHG SAF INJ PMP NO 12 TO SEAL WTR HT EXCH CKVL 205228-2 Chemical and Volume Control Operation D4 2 c CK SELF 2 c 0 Active S1 .OP-ST.CVC-0004(Q) i CTO Q 100703 1CV139 1 eve CHG SAF INJ PMP TO SEAL WTR HT EXCH GLB MOV 205228-2 Chemical and Volume Control Operation E2 2 B GB MO 2 0 O/C Active S1 .OP-ST.RPl-0001 (Q) PIT 2YR 100298 S1 .OP-ST.CVC-0006(Q) STC Q 100720 S1 .OP-ST.CVC-0006(Q) STO Q 100720

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 35 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I 0 I I TEST PROC iTEST TYPE iTEST FREQ.: C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK i TECH. POS.i COMMENTS 1CV140 1 eve CHG SAF INJ PMP TO SEAL WTR HT EXCH GLB MOV 205228-2 Chemical and Volume Control Operation E3 2 B GB MO 2 0 O/C Active

---

.------------------.------------------;:------------------;:------------------::-----------------.-------------------------::-----------------7-------------------------------------- ---------------------*

S1 .OP-ST.RPl-0001 (0) PIT 2YR i 100298 i S1 .OP-ST.CVC-0006(0) i STC Q 100720 S1 .OP-ST.CVC-0006(0) ! STO 0 100720 1CV141 1 eve RECIPROCATING CHARGING PMP DISCH SAF RLF VLV 205228-2 Chemical and Volume Control Operation AS 2 C RV SELF 0.75 c O/C Active SC.MD-PT.ZZ-0007(0) RV 5YR 290111 11CV154 11 eve BORIC ACID TRANS PMP DISCH CKVL 205228-1 Chemical and Volume Control Operation F1 2 c CK SELF 2 c O/C Active S1 .OP-ST.CVC-0001 (0) i CTC 0 100695 S1 .OP-ST.CVC-0001 (0)  ! CTO 0 100695 12CV154 12 eve BORIC ACID TRANS PMP DISCH CKVL 205228-1 Chemical and Volume Control Operation F3 2 c CK SELF 2 c O/C Active S1 .OP-ST.CVC-0002(0)  ! CTC 0 100696 S1 .OP-ST.CVC-0002(0) i CTO 0 100696 11CV160 11 eve BORIC ACID TK INLET AIR OPRD GLB VLV 205228-1 Chemical and Volume Control G2 2 B GB AIR 2 0 c Active S1 .OP-ST.CVC-0006(0) FSTC 0 100720 S1 .OP-ST.RPl-0001 (0) PIT 2YR 100298 S1 .OP-ST.CVC-0006(0) STC 0 100720

• TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 36 VALVE NO VALVE DESCRIPTION P+ ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification I I I I I I TEST PROC iTEST TYPE iTEST FREO.i C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK i TECH. POS.i COMMENTS 12CV160 12 eve BORIC ACID TK INLET AIR OPRD GLB VLV 205228-1 Chemical and Volume Control G3 2 B GB AIR 2 0 c Active S1 .OP-ST.CVC-0006(0) FSTC 0 100720 S1 .OP-ST.RPl-0001 (0) ! PIT 2YR 100298 S1 .OP-ST.CVC-0006(0) ! STC 0 100720 1CV175 1 eve BORIC ACID TRANSFER LINE GLB MOV 205228-1 Chemical and Volume Control Operation F8 2 B GB MO 2 c 0 Active S1 .OP-ST.RPl-0001 (0)  ! PIT 2YR 100298 S1 .OP-ST.CVC-0006(0)  ! STO 0 100720 1CV176 1 eve BORIC ACID TRANSFER LINE CKVL 205228-1 Chemical and Volume Control Operation F8 2 c CK SELF 2 c 0 Active S1 .OP-ST.CVC-0007(0)  ! CTO cs i CS-21 100582 1CV241 1 eve VOLUME CONTROL TK TO HOLD-UP TK SAF RLF VLV 205228-1 Chemical and Volume Control Operation H10 2 c RV SELF 3 c 0 Active

---

-----------------------------------;------------------------------------------=-----------------------------------*-*----------------------------------------

SC.MD-PT.ZZ-0007(0) RV SYR 203980 1CV274 1 eve REGEN HT EXCH TO REAC COLD LEG CKVL 205228-2 Chemical and Volume Control Operation E10 1 c CK SELF 3 0 0 Active S1 .OP-ST.CVC-0006(0) i CTO 0 100720 1CV275 1 eve REGEN HT EXCH TO REAC COOL CHG LINE CKVL 205228-2 Chemical and Volume Control Operation E10 1 c CK SELF 3 c 0 Active S1 .OP-ST.CVC-0006(0) i CTO 0 100720

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 37 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ) C.S. JUST. : R.O. JUST.: REL. REQ.  ! RECUR. TASK !TECH. POs.i COMMENTS 1CV284 1 eve REAC COOL PMP DISCH HOR GATE VLV 205228-3 Chemical and Volume Control Operation C2 2 A GT MO 4 0 c Active

- - - - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - -. - - - - - - - - - - - - - - - - - ""; - - - - - - - - - - -- - - - - -- .. - - - - - - - - - - - - - - - - - - .. - - - - - - - - - - - - - - - - - - .- - - - - - - - - - - - - - - - - -. - - - - - - - - - - - - - - - - - - - - - - - - - ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

• S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290529 S1 .OP-ST.RPl-0002(0) ( PIT 2YR 100299 S1 .OP-ST.CVC-0007(0) ( STC cs CS-20 100582 1CV296 1 eve REAC COOL PMP DISCH HOR MOV 1CV284 BYPASS CKVL 205228-3 Chemical and Volume Control Operation C1 2 A/C CK SELF 0.75 c DIC Active S1 .RA-IS.ZZ-0001 (0) CTC RF V-14 290530 S1 .OP-ST.CVC-0007(0) i CTO RF V-14 100582 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290530 11DA6A 11 DIESEL GEN DIESEL STARTING AIR RECEIVER N0.11A INLET CHECK VLV AUGMENTED 205241-1 Diesel Engine Auxiliaries D4 N AIC CK SELF 0.75 DIC c Active

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.------------------.------------------;------------------;-------------------:-----------------:-------------------------:-----------------7------------------------------------------------------------

S1 .OP-ST.DG-0009(0) CTC 0 100753 12DA6A 12 DIESEL GEN DIESEL STARTING AIR RECEIVER N0.11B INLET CHECK VLV AUGMENTED 205241-1 Diesel Engine Auxiliaries D5 N A/C CK SELF 0.75 DIC c Active S1.0P-ST.DG-0009(0) CTC 0 100753 11DA6B 11 DIESEL GEN DIESEL STARTING AIR RECEIVER N0.12A INLET CHECK VLV AUGMENTED 205241-2 Diesel Engine Auxiliaries D4 N A/C CK SELF 0.75 DIC c Active S1.OP-ST.DG-0010(0) CTC j 0 . j 101136 j i 12DA6B 12 DIESEL GEN DIESEL STARTING AIR RECEIVER N0.12B INLET CHECK VLV AUGMENTED 205241-2 Diesel Engine Auxiliaries D5 N A/C CK SELF 0.75 DIC c Active S1.OP-ST.DG-0010(0) CTC 0 101136

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 38 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. i R.O. JUST. i REL. REQ.: RECUR. TASK !TECH. POS.: COMMENTS 11DA6C 11 DIESEL GEN DIESEL STARTING AIR RECEIVER N0.13A INLET CHECK VLV AUGMENTED 205241-3 Diesel Engine Auxiliaries D4 N AJC CK SELF 0. 75 O/C C Active S1.0P-ST.DG-0011(0) CTC 0 101137 12DA6C 12 DIESEL GEN DIESEL STARTING AIR RECEIVER N0.13B INLET CHECK VLV AUGMENTED 205241-3 Diesel Engine Auxiliaries D5 N A/C CK SELF 0.75 O/C c Active S1 .OP-ST.DG-0011 (0) j CTC . 0 . . i . 101137 .  : .

11DA10A 11 DIESEL GEN DIESEL STARTING AIR RECEIVER SAFETY RELIEF VLV AUGMENTED 20S241-1 Diesel Engine Auxiliaries E4 N C RV SELF 0.7S c 0/C Active RV SYR 290113 12DA10A 12 DIESEL GEN DIESEL STARTING AIR RECEIVER SAFETY RELIEF VLV AUGMENTED 205241-1 Diesel Engine Auxiliaries ES N c RV SELF 0.7S c O/C Active SC.MD-PT.ZZ-0007(0) RV 5YR 290119 11DA10B 11 DIESEL GEN DIESEL STARTING AIR RECEIVER N0.12A SAF RLF VLV AUGMENTED 20S241-2 Diesel Engine Auxiliaries E4 N C RV SELF 0.7S c O/C Active SC.MD-PT.ZZ-0007(0) RV 5YR 290115 12DA10B 12 DIESEL GEN DIESEL STARTING AIR RECEIVER SAFETY RELIEF VLV AUGMENTED 20S241-2 Diesel Engine Auxiliaries ES N c RV SELF 0.75 c O/C Active SC.MD-PT.ZZ-0007(0) RV 5YR  !  ! 290121  !

11DA10C 11 DIESEL GEN DIESEL STARTING AIR RECEIVER N0.13A SAF RLF VLV AUGMENTED 20S241-3 Diesel Engine Auxiliaries E4 N c RV SELF 0.75 c O/C Active SC.MD-PT.ZZ-0007(0) RV 5YR 290117

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 39 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I I TEST PROC iTEST TYPE iTEST FREQ.i C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK ]TECH. POS.i COMMENTS 12DA10C 12 DIESEL GEN DIESEL STARTING AIR RECEIVER SAFETY RELIEF VLV AUGMENTED 205241-3 Diesel Engine Auxiliaries E5 N c RV SELF 0.75 c O/C Active

~ ~ - - - - -- -- ---------- -----------------. ----- ----- - - -- -- - - - - ---- - -- ------------ -- - : -- - - - - - - - - ------ ----- -- - - - -- -- - - - - - - - ---- --------------- -- - - .

~ ~

RV 5YR 290123 11DA13A 11 DIESEL GEN STARTING AIR MOTOR 1A SV (SV878) AUGMENTED 205241-1 Diesel Engine Auxiliaries F4 N B GB SOL 2 c 0 Active

--- --------- ---- -- ---- -------- - - ------- - --. ---- --- --- -- - - --- -. - -- - --------------:- ------------------ -- - -- - -- -- -- -- -- -- ~ - - - - - - - - - - -- - - - --. -- ------------ -------- - - - - - -- -- -- - - -- ----- ----------- - - - -- -- - - -- - - -- -- - ---------------- --- -- -- - - -- - - - - .

S1 .OP-ST.DG-0006(0) FSO CS  ; CS-22 100350 S1 .OP-ST.DG-0001 (0) STO O V-37 101290 12DA13A 1A DIESEL GEN STARTING AIR MOTOR SV (SV877) AUGMENTED 205241-1 Diesel Engine Auxiliaries F5 N B GB SOL 2 c 0 Active

- - - - -- - -- - -- - --- -- ------------------------. ------------ - ---- -. --------------*- ---:- ---------------- - - -- -- - - ~ .. - - -- -- -- - - - - - - -- - -- -- -- -- -- - - -- - ------- -- ------ -- - - - - - - - - - - - -- - - -- -- - -- -- - - -- -- ---- -- ------ - --- -- -- - - - - -- -- -- - -- - -- - . ------------.

S1 .OP-ST.DG-0006(0) FSO cs  : CS-22 100350 S1 .OP-ST.DG-0001 (0) STO 0 V-37 101291 11DA13B 12 DIESEL GEN STARTING AIR MOTOR 1B SV (SV884) AUGMENTED 205241-2 Diesel Engine Auxiliaries F4 N B GB SOL 2 c 0 Active

- - ---- -- -- -- -- -- -- ---- ---- -- -- - --- - -- - -- - -. - - -- -- - - - - - - -- - - - -. - - - - -- - - - - - - -- -- - - ~- -- - - - - - - -- -- - - -- -.* ---- . - -- .. -- ---- -- --- -- --. --- . --- --;- --- -- -- -- -- - - - - -- --- - -- - -- -- ------ -- ---- - -- -- -- -- -- -- -- -- -- -- - - - - -- -- -- ---- -- ---- - - . - -- - - -- -- -- - - -- - - .

S1 .OP-ST.DG-0007(0) FSO cs  : CS-22 100359 S1 .OP-ST.DG-0002(0) STO 0 V-37 101292 12DA13B 1B DIESEL GEN STARTING AIR MOTOR SV (SV883) AUGMENTED 205241-2 Diesel Engine Auxiliaries F5 N B GB SOL 2 c 0 Active S1 .OP-ST.DG-0007(0) FSO cs  : CS-22 100359 S1 .OP-ST.DG-0002(0) STO 0 V-37 101293 11DA13C 13 DIESEL GEN STARTING AIR MOTOR 1C SV (SV890) AUGMENTED 205241-3 Diesel Engine Auxiliaries F4 N B GB SOL 2 c 0 Active S1 .OP-ST.DG-0008(0) FSO cs CS-22 100360 S1 .OP-ST.DG-0003(0) STO Q V-37 101294

TABLE 3-1 -VALVE. TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 40 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification I I I I I I I TEST PROC !TEST TYPE !TEST FREQ.!. C.S. JUST. ! R.O. JUST.! REL. REQ. ! RECUR. TASK !TECH, POS.! COMMENTS 12DA13C 1C DIESEL GEN STARTING AIR MOTOR SV (SV889) AUGMENTED 205241-3 Diesel Engine Auxiliaries F5 N B GB SOL 2 c 0 Active S1 .OP-ST.DG-0008(0) FSO cs  : CS-22 100360 S1 .OP-ST.DG-0003(0) STO 0 V-37 101295 11DA14A 11 DIESEL GEN STARTING AIR MOTOR 1A SV (SV879) AUGMENTED 205241-1 Diesel Engine Auxiliaries F4 N B GB SOL 2 c 0 Active S1 .OP-ST.DG-0006(0) FSO cs  : CS-22 100350 S1 .OP-ST.DG-0001 (0) STO 0 V-37 101290 12DA14A 1A DIESEL GEN STARTING AIR MOTOR SV (SV880) AUGMENTED 205241-1 Diesel Engine Auxiliaries F5 N B GB SOL 2 c 0 Active S1 .OP-ST.DG-0006(0) FSO cs  : CS-22 100350 S1 .OP-ST.DG-0001 (Q) STO 0 V-37 101291 11DA14B 12 DIESEL GEN STARTING AIR MOTOR 1B SV (SV885) AUGMENTED 205241-2 Diesel Engine Auxiliaries F4 N B GB SOL 2 c 0 Active S1 .OP-ST.DG-0007(0) FSO cs  : CS-22 100359 S1 .OP-ST.DG-0002(0) STO 0 V-37 101292 12DA14B 18 DIESEL GEN STARTING AIR MOTOR SV (SV886) AUGMENTED 205241-2 Diesel Engine Auxiliaries F5 N B GB SOL 2 c 0 Active S1 .OP-ST.DG-0007(0) FSO cs CS-22 100359 S1 .OP-ST.DG-0002(0) STO 0 V-37 101293

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 41 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification 1 I t I I '

TEST PROC iTEST TYPE iTEST FREa.i C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK i TECH. POS.i COMMENTS 11DA14C 13 DIESEL GEN STARTING AIR MOTOR 1C SV (SV891) AUGMENTED 205241-3 Diesel Engine Auxiliaries F4 N B GB SOL 2 c 0 Active S1 .OP-ST.DG-0008(0) FSO cs i CS-22 100360 S1 .OP-ST.DG-0003(0) STO o V-37 101294 12DA14C 1C DIESEL GEN STARTING AIR MOTOR SV (SV892) AUGMENTED 205241-3 Diesel Engine Auxiliaries F5 N B GB SOL 2 c 0 Active S1 .OP-ST.DG-0008(0) . FSO i CS  ! CS-22 . . . 100360 i  !

S1 .OP-ST.DG-0003(0) STO 0 V-37 101295 1DA17A 1 DIESEL GEN DIESEL TURBO BOOST AIR COMPRESSOR DISCH CHECK VLV AUGMENTED 205241-2 Diesel Engine Auxiliaries G1 N AJC CK SELF 0.75 O/C c Active S1 .OP-ST.DG-0009(0) CTC 0 100753 1DA17B 1 DIESEL GEN DIESEL TURBO BOOST AIR COMPRESSOR DISCH CHECK VLV AUGMENTED 205241-2 Diesel Engine Auxiliaries G1 N AJC CK SELF 0.75 O/C c Active S1.OP-ST.DG-0010(0) CTC o .

' 101136 1DA17C 1 DIESEL GEN DIESEL TURBO BOOST AIR COMPRESSOR DISCH CHECK VLV AUGMENTED 205241-3 Diesel Engine Auxiliaries G1 N AJC CK SELF 0.75 O/C c Active S1 .OP-ST.DG-0011 (Q) CTC o 101137 11DA19A 11 DIESEL GEN DIESEL TURBO BOOST AIR RECIEVER N0.11A SAF RLF VLV AUGMENTED 205241-1 Diesel Engine Auxiliaries G2 N C RV SELF 0.75 c O/C Active SC.MD-PT.ZZ-0007 (Q)  : RV 5YR 290125 12DA19A 12 DIESEL GEN DIESEL TURBO BOOST AIR RECEIVER N0.118 SAF RLF VLV AUGMENTED 205241-1 Diesel Engine Auxiliaries G3 N c RV SELF 0.75 c O/C Active SC.MD-PT.ZZ-0007 (0) RV i 5YR  : i 290131 i  :

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 42 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ, ! RECUR. TASK !TECH. POS.! COMMENTS 11DA19B 11 DIESEL GEN DIESEL TURBO BOOST AIR RECEIVER N0.12A SAF RLF VLV AUGMENTED 205241-2 Diesel Engine Auxiliaries G2 N C RV SELF 0. 75 C O/C Active SC.MD-PT.ZZ-0007 (Q) i RV SYR 290127 12DA19B 12 DIESEL GEN DIESEL TURBO BOOST AIR RECEIVER N0.12B SAF RLF VLV AUGMENTED 205241-2 Diesel Engine Auxiliaries G3 N C RV SELF 0.75 c O/C Active SC.MD-PT.ZZ-0007 (Q) i RV SYR 290133 11DA19C 11 DIESEL GEN DIESEL TURBO BOOST AIR RECEIVER N0.13A SAF RLF VLV AUGMENTED 205241-3 Diesel Engine Auxiliaries G2 N C RV SELF 0.75 c O/C Active SC.MD-PT.ZZ-0007 (Q) i RV SYR 290129 12DA19C 12 DIESEL GEN DIESEL TURBO BOOST AIR RECEIVER N0.13B SAF RLF VLV AUGMENTED 205241-3 Diesel Engine Auxiliaries G3 N C RV SELF 0.75 c O/C Active SC.MD-PT.ZZ-0007 (Q)  ! RV SYR 290135 1DA36A 1 DIESEL GEN DIESEL ENGINE LUBE OIL HEATER OUTLET CHECK VLV 205241-1 Diesel Engine Auxiliaries C9 N C CK SELF 4 0 0 Passive No inservice testing required for this component.

1DA36B 1 DIESEL GEN DIESEL ENGINE LUBE OIL HEATER OUTLET CHECK VLV 205241-2 Diesel Engine Auxiliaries C9 N c CK SELF 4 0 0 Passive No inservice testing required for this component.

1DA36C 1 DIESEL GEN DIESEL ENGINE LUBE OIL HEATER OUTLET CHECK VLV 205241-3 Diesel Engine Auxiliaries C9 N C CK SELF 4 0 0 Passive No inservice testing required for this component.

TABLE 3-1 -VALVE.TEST TABLE 10/1/97 SALEM NUCLEAR PLANT ..: UNIT 1 Page 43 VALVE NO VALVE DESCRIPTION P + ID No P + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC :TEST TYPE !TEST FREQ.:. C.S. JUST. : R.O. JUST. : REL. REQ. j RECUR. TASK j TECH. POs.! COMMENTS 11DF38 11 FUEL OIL DIESEL FUEL OIL TRANSFER PUMP DISCH CHECK VLV AUGMENTED 205249-2 Fuel Oil A6 N C CK SELF 2 C 0 Active S1 .OP-ST.DG-0004(0) CTO o 100577 12DF38 12 FUEL OIL DIESEL FUEL OIL TRANSFER PUMP DISCH CHECK VLV AUGMENTED 205249-2 Fuel Oil BB N c CK SELF 2 c 0 Active CTO o 101127 11DF61 11 FUEL OIL DIESEL FUEL OIL DAY TANK N0.1A INLET CHECK VLV AUGMENTED 205249-2 Fuel Oil H7 N C CK SELF 2 c 0 Active S1 .OP-ST.DG-0004(0) CTO o 100577 12DF61 12 FUEL OIL DIESEL FUEL OIL DAY TANK N0.1A INLET CHECK VLV AUGMENTED 205249-2 Fuel Oil H7 N c CK SELF 2 c 0 Active S1 .OP-ST.DG-0005(0) CTO o 101127 11DF62 11 FUEL OIL DIESEL FUEL OIL DAY TANK N0.1B INLET CHECK VLV AUGMENTED 205249-2 Fuel Oil G7 N C CK SELF 2 c 0 Active S1 .OP-ST.DG-0004(0) CTO o 100577 12DF62 12 FUEL OIL DIESEL FUEL OIL DAY TANK N0.1B INLET CHECK VLV AUGMENTED 205249-2 Fuel Oil Fl N C CK SELF 2 c 0 Active

~ - - - -- -- - - - - -- -- -- -- - - -- -- -- -- - - -- - - - -- - - - -- - - - - -- .

81.0P-ST.DG-0005(0) [ CTO 0 101127 [

11DF63 11 FUEL OtL DIESEL FUEL OIL DAY TANK N0.1C INLET CHECK VLV AUGMENTED 205249-2 Fuel Oil D7 N C CK SELF 2 c 0 Active S1 .OP-ST.DG-0004(0) CTO o 100577

TABLE 3-1 -VALVE TEST TABLE 1011197 SALEM NUCLEAR PLANT - UNIT 1 Page 44

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VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Norma/ Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC :TEST TYPE !TEST FREQ.: c_s_ JUST. ! R.O. JUST. ! REL. REQ.: RECUR. TASK !TECH. POs.: COMMENTS 12DF63 12 FUEL OIL DIESEL FUEL OIL DAY TANK N0.1C INLET CHECK VLV AUGMENTED 205249-2 Fuel Oil El N C CK SELF 2 C 0 Active

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -. - - - - - - - - - - - - - - - - - -. - - - - - - - ~ - - - - - - - - - - .- - - - - - - - - - - - - - - - - - - : - - - - - - - - - - - - - - - - - - :- - - - - - - - - - - - - - - - - -. - - - - - - - - - - - - - - - - - - - - - - - - - .- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - * - - - - - - -- * - - - - - - - - - * -

81 .OP-8T.DG-0005(0)  ! CTO 0 101127  :

1DR7 1 DEMINERALIZER WATER AUX FEEDWATER TANK INLET CHECK VALVE 205246-1 Deminera/ized Water - Restricted Areas D5 3 c CK SELF 6 O/C c Active

- ----- -- -- -- - - - ----- --- -- -- - -- ---- . - -- -- --: - - - - - - -- -------- - -. - - - - -- ----------- - .- - - - - - - - - - - --- ----- ~ -- - - -- - - - - - - -- ---- ~ ----- - - - - -- -- -- - -. - - - - -- -- - - -------- -- - - - - - .- - - -- ------- --- -- -  : -- -- - -- - - - -- - ------------- --- - - - - - -

CTC o 100726 1DR29 1 DEMIN WTR UNIT 2 INLET LINE AIR OPRD GLB VLV 205246-1 Deminera/ized Water - Restricted Areas DB 2 A GT AIR 4 c c Active

" -

' ~

81 .OP-ST.ZZ-0003(0) F8TC o 100726 81 .RA-18.ZZ-0001 (0) LJ 18MO 290535 81 .OP-8T.RPl-0004(0) PIT 2YR 100302 81 .OP-8T.ZZ-0003(0) 8TC o 100726 1DR30 1 DEMIN WTR UNIT 1 INLET LINE CKVL 205246-1 Demineralized Water - Restricted Areas DB 2 A/C CK SELF 4 c O/C Active

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------------------------------- ----------------**t**-----------------:---------------- ------------------------- -------------------------------

81 .RA-18.ZZ-0001 (0) CTC RF V-34 290536 81 .OP-8T.ZZ-0005(0) CTO RF V-34 (later) TP-6 Rec. Task (RT) prior to restart.

81 .RA-18.ZZ-0001 (0) LJ 18MO 290536 1FP147 1 FIRE PROT REAC CONTMT AREA INLET AIR OPRD PLUG/CTL VLV 205222-1 Fire Protection El 2 A GT AIR 4 c c Active 81 .OP-ST.ZZ-0003(0) FSTC o 100726 81 .RA-IS.ZZ-0001 (0) LJ 18MO 290537 81 .OP-8T.RPl-0004(0) PIT 2YR 100302 81 .OP-8T.ZZ-0003(0) 8TC o 100726

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 45 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC :TEST TYPE !TEST FREQ.! C.S. JUST. : R.O. JUST.! REL. REQ.: RECUR. TASK !TECH. POS.! COMMENTS 1FP148 1 FIRE PROT REAC CONTMT AREA INLET CHECK VLV 205222-1 Fire Protection El 2 A/C CK SELF 4 c O/C Active S1 .RA-IS.ZZ-0001 (0)  : CTC RF  ! V-34 290538 S1 .OP-ST.ZZ-0005(0) CTO RF V-34 (later) TP-6 Rec. Task (RT) prior to restart.

S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290538 11GB4 11 STM GEN ORN & BLOWN STM GEN TO NO 12 COND AIR OPRD GLB VLV 205225-2 Steam Generator Drains and Blowdown H10 2 A GB AIR 3 0 c Active

- -- - -- - - - - -- - - -- - - - - -- -- - - - - -- -- - - -- -- - -- -- - - - - - - - - - - - - - - - - - - -- - -- - - -- - -- -- -- ~ -------- - -- - - - - - - - .- - - -- - - - - - - -- -- -- -- - - - -- - -- - --- ----- - - -- - - - - -- -- - - -- - - -- - - - - - - - - - -- - -- - ---- -- - -- -- -- -- -- - - - -- - . - - - - - - - - - - - - - - - - - -- - - -- - -- - - - - . - ..

S1 .OP-ST.MS-0001 (0) FSTC i 0 i  ! 100465 SC.RA-IS.GB-0004(0) LT 2YR 291148 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.MS-0001 (0) STC 0 100465 12GB4 12 STM GEN ORN & BLOWN STM GEN TO COND AIR OPRD GLB VLV 205225-2 Steam Generator Drains and Blowdown G10 2 A GB AIR 3 0 c Active 81 .OP-ST.MS-0001 (0) : FSTC : 0 i i 100465 SC.RA-IS.GB-0004(0) LT 2YR 291148 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.MS-0001 (0) STC O 100465 13GB4 13 STM GEN ORN & BLOWN STM GEN TO NO 12 COND AIR OPRD GLB VLV 205225-2 Steam Generator Drains and Blowdown G10 2 A GB AIR 3 0 c Active S1 .OP-ST.MS-0001 (0) FSTC 0 100465 SC.RA-IS.GB-0004(0) LT 2YR 291148 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.MS-0001 (0) STC 0 100465

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 46 VALVE NO VALVE DESCRIPTION P +ID No P+ JD Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.: C.S. JUST. : R.O. JUST. : REL. REQ.: RECUR. TASK TECH. pos.i COMMENTS i

.14GB4 14 STM GEN ORN & BLOWN STM GEN TO NO 12 COND AIR OPRD GLB VLV 20S22S-2 Steam Generator Drains and Blowdown F10 2 A GB AIR 3 O C Active S1 .OP-ST.MS-0001 (0) FSTC 0 100465 SC.RA-IS.GB-0004(0) LT 2YR 291148 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.MS-0001 (0) STC 0 100465 11MS7 11 MN STM & TRB BY PASS HOR STM ORN AIR OPRD ISOLVLV 20S203-1 Main, Reheat, and Turbine Bypass Steam ES 2 B GB AIR 2 O/C c Active 51.0P-ST.MS-0001(0) FSTC 0 [ 100465 [

S1 .OP-ST.RPl-0004(0) [ PIT 2YR 100302 S1 .OP-ST.MS-0001 (0) STC 0 100465 12MS7 12 MN STM & TRB BY PASS MS HOR DRAIN LINE AIR OPRD GLB VLV 20S203-2 Main, Reheat, and Turbine Bypass Steam C6 2 B GB AIR 2 O/C c Active S1 .OP-ST.MS-0001 (0) FSTC 0 100465 S1 .OP-ST.RPl-0004(0)  ! PIT 2YR 100302 S1 .OP-ST.MS-0001 (0) STC 0 100465 13MS7 13 MN STM & TRB BY PASS HOR STM ORN AIR OPRD ISOL VLV 20S203-1 Main, Reheat, and Turbine Bypass Steam AS 2 B GB AIR 2 O/C c Active S1 .OP-ST.MS-0001 (0) FSTC 0 100465 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.MS-0001 (0) STC 0 100465

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 47 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREa.i C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK !TECH. pos.1 COMMENTS 14MS7 14 MN STM & TRB BY PASS MS HOR DRAIN LINE AIR OPRD GLB VLV 205203-2 Main, Reheat, and Turbine Bypass Steam F6 2 B GB AIR 2 DIC C Active S1 .DP-ST.MS-0001 (0) FSTC 0 100465 S1 .DP-ST.RPl-0004(0) ! PIT 2YR 100302 S1 .DP-ST.MS-0001 (0) STC 0 100465 11MS10 11 MN STM & TRB BY PASS AIR OPRD RLF VLV (Power Operated Relief Valves) 205203-1 Main, Reheat, and Turbine Bypass Steam G7 2 B GB AIR 6 c DIC Active S1 .DP-ST.MS-0002(0) FSTC cs CS-24 100554 S1 .DP-ST.RPl-0003(0) PIT 2YR 100301 S1 .OP-ST.MS-0002(0) STC cs CS-24 100554 S1 .DP-ST.MS-0002(0) STD cs CS-24 100554 12MS10 12 MN STM & TRB BY PASS STM GEN AIR OPRD RLF VLV (Power Operated Relief Va ves) 205203-2 Main, Reheat, and Turbine Bypass Steam D6 2 B GB AIR 6 c DIC Active S1 .DP-ST.MS-0002(0) FSTC cs CS-24 100554 S1 .DP-ST.RPl-0003(0) PIT 2YR 100301 S1 .DP-ST.MS-0002(0) STC cs CS-24 100554 S1 .DP-ST.MS-0002(0) STO cs CS-24 100554 13MS10 13 MN STM & TRB BY PASS AIR OPRD STM GEN RLF VLV (Power Operated Relief Valves) 205203-1 Main, Reheat, and Turbine Bypass Steam D7 2 B GB AIR 6 c DIC Active S1 .DP-ST.MS-0002(0) FSTC cs CS-24 100554 S1 .DP-ST.RPl-0003(0) PIT 2YR 100301 S1 .DP-ST.MS-0002(0) STC cs CS-24 100554 S1 .DP-ST.MS-0002(0) STD cs CS-24 100554

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 48 VALVE NO VALVE DESCRIPTION P+ ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I 1 I TEST PROC iTEST TYPE !TEST FREa.i C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK iTECH. POS.! COMMENTS 14MS10 14 MN STM & TRB BY PASS STM GEN AIR OPRD RLF VLV (Power Operated Relief Valves) 205203-2 Main, Reheat, and Turbine Bypass Steam G6 2 B GB AIR 6 C OIC Active S1 .OP-ST.MS-0002(0) FSTC cs CS-24 100554 S1 .OP-ST.RPl-0003(0) PIT 2YR 100301 S1 .OP-ST.MS-0002(0) STC cs CS-24 100554 S1 .OP-ST.MS-0002(0) STO cs CS-24 100554 11MS11 11 MN STM & TRB BY PASS STM GEN SAF RLF VLV 11MS1 205203-1 Main, Reheat, and Turbine Bypass Steam F3 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001 (0) i RV 5YR 290153 12MS11 12 MN STM & TRB BY PASS STM GEN SAF RLF VLV 12MS11 205203-2 Main, Reheat, and Turbine Bypass Steam D3 2 c RV SELF 8 c O/C Active RV 5YR 290155 13MS11 13 MN STM & TRB BY PASS STM GEN SAF RLF VLV 13MS11 205203-1 Main, Reheat, and Turbine Bypass Steam C3 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001 (0) i RV 5YR 290157 14MS11 14 MN STM & TRB BY PASS STM GEN SAF RLF VLV 14MS11 205203-2 Main, Reheat, and Turbine Bypass Steam G3 2 c RV SELF 8 c O/C Active RV 5YR 290159 11MS12 11 MN STM & TRB BY PASS STM GEN SAF RLF VLV 11MS12 205203-1 Main, Reheat, and Turbine Bypass Steam F4 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001 (0) RV 5YR 290161

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 49 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK !TECH. POS.! COMMENTS 12MS12 12 MN STM & TRB BY PASS STM GEN SAF RLF VLV 12MS12 205203-2 Main, Reheat, and Turbine Bypass Steam D4 2 c RV SELF 8 c O/C Active

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RV SYR 290163 13MS12 13 MN STM & TRB BY PASS STM GEN SAF RLF VLV 13MS12 205203-1 Main, Reheat, and Turbine Bypass Steam C4 2 c RV SELF 8 c 0/C Active SC.MD-ST.MS-0001 (Q) ! RV SYR 290165 14MS12 14 MN STM & TRB BY PASS STM GEN SAF RLF VLV 14MS12 205203-2' Main, Reheat, and Turbine Bypass Steam G4 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001 (Q) ! RV  ! 5YR  !  : 290167  !  !

11MS13 11 MN STM & TRB BY PASS STM GEN SAF RLF VLV 11MS13 205203-1 Main, Reheat, and Turbine Bypass Steam FS 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001 (Q) ! RV SYR . ' 290169 12MS13 12 MN STM & TRB BY PASS STM GEN SAF RLF VLV 12MS13 205203-2 Main, Reheat, and Turbine Bypass Steam DS 2 c RV SELF 8 c O/C Active

---

.------------------.------------------.-------------------.-------------------;-----------------.-------------------------.------------------7------------------------------------------------------------

SC.MD-ST.MS-0001 (Q)  ! RV  ! SYR 290171  !

13MS13 13 MN STM & TRB BY PASS STM GEN SAF RLF VLV 13MS13 205203-1 Main, Reheat, and Turbine Bypass Steam CS 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001(0)  : RV  : SYR  !  :. 290173  :  !

14MS13 14 MN STM & TRB BY PASS STM GEN SAF RLF VLV 14MS13 205203-2 Main, Reheat, and Turbine Bypass Steam G4 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001 (Q) RV SYR 290175

TABLE 3-1 -VALVE. TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 50 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREa.i C.S. JUST. : R.O. JUST. : REL. REQ.: RECUR. TASK !TECH. pos.! COMMENTS 11MS14 11 MN STM & TRB BY PASS STM GEN SAF RLF VLV 11MS14 205203-1 Main, Reheat, and Turbine Bypass Steam F6 2 C RV SELF 8 C OIC Active SC.MD-ST.MS-0001 (Q) i RV SYR 290177 12MS14 12 MN STM & TRB BY PASS STM GEN SAF RLF VLV 12MS14 205203-2 Main, Reheat, and Turbine Bypass Steam D5 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001 (Q) i RV SYR 290179 i i 13MS14 13 MN STM & TRB BY PASS STM GEN SAF RLF VLV 13MS14 205203-1 Main, Reheat, and Turbine Bypass Steam C6 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001 (Q) j RV SYR 290181 14MS14 14 MN STM & TRB BY PASS STM GEN SAF RLF VLV 14MS14 205203-2 Main, Reheat, and Turbine Bypass Steam GS 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001 (Q) i RV SYR i 290183 i 11MS15 11 MN STM & TRB BY PASS STM GEN SAF RLF VLV 11MS15 205203-1 Main, Reheat, and Turbine Bypass Steam F6 2 c RV SELF 8 c O/C Active RV SYR 290185 12MS15 12 MN STM & TRB BY PASS STM GEN SAF RLF VLV 12MS15 205203-2 Main, Reheat, and Turbine Bypass Steam D6 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001 (Q) i RV SYR '

' 290187 13MS15 13 MN STM & TRB BY PASS STM GEN SAF RLF VLV 13MS15 205203-1 Main, Reheat, and Turbine Bypass Steam C6 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001 (Q)  : RV SYR  ! 290189 .

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 51 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST.FREQ) C.S. JUST. : R.O. JUST.: REL. REQ.: RECUR. TASK . !TECH. POs.: COMMENTS 14MS15 14 MN STM & TRB BY PASS STM GEN SAF RLF VLV 14MS15 205203-2 Main, Reheat, and Turbine Bypass Steam G6 2 c RV SELF B c O/C Active 5C.MD-5T.M5-0001 (Q) i RV 5YR 290191 11MS18 11 MN STM & TRB BY PASS STM GEN ISOLVLV AIR OPRD BY PASS VLV 205203-1 Main, Reheat, and Turbine Bypass Steam E4 2 B GT AIR 3 O/C c Active 51 .OP-5T.M5-0001 (Q) F5TC Q 100465 51 .OP-5T.RPl-0004(Q) i PIT 2YR 100302 51 .OP-5T.M5-0001 (Q) 5TC Q 100465 12MS18 12 MN STM & TRB BY PASS MS HOR BY PASS LINE AIR OPRD GATE VLV 205203-2 Main, Reheat, and Turbine Bypass Steam C4 2 B GT AIR 3 O/C c Active 51 .OP-5T.M5-0001 (Q) F5TC Q 100465 51 .OP-5T.RPl-0004(Q) i PIT 2YR 100302 51 .OP-ST.M5-0001 (Q) 5TC Q 100465 13MS18 13 MN STM & TRB BY PASS STM GEN ISOLVLV AIR OPRD BY PASS VLV 205203-1 Main, Reheat, and Turbine Bypass Steam B4 2 B GT AIR 3 O/C c Active

~ ~

51 .OP-5T.M5-0001 (Q) F5TC Q 100465 51 .OP-5T.RPl-0004(Q) : PIT 2YR 100302 51 .OP-5T.M5-0001 (Q) 5TC Q 100465 14MS18 14 MN STM & TRB BY PASS MS HOR BY PASS LINE AIR OPRD GATE VLV 205203-2 Main, Reheat, and Turbine Bypass Steam F4 2 B GT AIR 3 O/C c Active 51 .OP-5T.M5-0001 (Q) F5TC Q 100465 51 .OP-5T.RPl-0004(Q) PIT 2YR 100302 51 .OP-5T.M5-0001 (Q) 5TC Q 100465

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 52 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

---~~~~-~~~~---------------------h-~~~-~~~~-:~~~~-~~~~T-~.-~---~~~~.--:---~.-~:-~~~~:-r-~~~---~-~-a:-:--~~~-~-~--~~~~---r~~~~:-~~~:;-~~~-~~~~~------**---------*------------------------

11MS45 11 MN STM & TRB BY-PASS AUX FDWTR PMP TRB 1MSE3 STM HOR ISOLVLV 205203-1 Main, Reheat & Turbine By-pass Steam G3 2 B GT MANUAL 6 O C Active 81 .OP-ST.AF-0003(0) FSC 0 100694 13MS45 13 MN STM & TRB BY-PASS AUX FDWTR PMP TRB 1MSE3 STM HOR ISOL VLV 205203-1 Main, Reheat & Turbine By-pass Steam D3 2 B GT MANUAL 6 0 c Active

'  :'  :' ~

FSC 0 100694 11MS46 11 MN STM & TRB BY PASS AUX FD PMP TURB STM SUP HOR CKVL 205203-1 Main, Reheat, and Turbine Bypass Steam H3 2 C CK SELF 6 c O/C Active S1 .OP-ST.AF-0006(0) CTC 0 101150 S1 .OP-ST-AF-0006(0) CTO 0 101150 13MS46 13 MN STM & TRB BY PASS AUX FD PMP TURB STM SUP HOR CKVL 205203-1 Main, Reheat, and Turbine Bypass Steam G3 2 c CK SELF 6 c O/C Active S1 .OP-ST.AF-0006(0) CTC 0 101150 S1 .OP-ST.AF-0006(0) CTO 0 101150 1MS132 1 MN STM & TRB BY PASS AUX FD PMP TURB AIR OPRD START-STOP VLV 205203-1 Main, Reheat, and Turbine Bypass Steam H4 2 B GT AIR 6 c O/C Active S1 .OP-ST.AF-0003(0) FSTO 0 100694 S1 .OP-ST.RPl-0001 (0) PIT 2YR 100298 S1 .OP-ST.AF-0003(0) STC 0 100694 51 .OP-ST.AF-0003(0) STO 0 100694

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 53 VALVE NO VALVE DESCRIPTION P+ ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST.! REL. REQ. ! RECUR. TASK !TECH. pas.! COMMENTS 11MS167 11 MN STM & TRB BY PASS HYO OPRD STM GEN ISOL VLV (MSIV) 205203-1 Main, Reheat, and Turbine Bypass Steam F7 2 B GT STM 32 0 c Active S1 .OP-ST.MS-0003(0) FSTC cs CS-24 100944 S1 .OP-ST.RPl-0003(0) i PIT 2YR 100301 S1 .OP-ST.MS-0003(0) STC cs CS-24 100944 12MS167 12 MN STM & TRB BY PASS STM GEN HYO OPRD ISOL VLV (MSIV) 205203-2 Main, Reheat, and Turbine Bypass Steam D7 2 B GT STM 32 0 c Active S1 .OP-ST.MS-0003(0) FSTC cs CS-24 100944 S1 .QP,ST.RPl-0003(0)  ! PIT 2YR 100301 S1 .OP-ST.MS-0003(0) STC cs CS-24 100944 13MS167 13 MN STM & TRB BY PASS HYO OPRD STM GEN ISOL VLV (MSIV) 205203-1 Main, Reheat, and Turbine Bypass Steam C7 2 B GT STM 32 0 c Active S1 .OP-ST.MS-0003(0) FSTC cs CS-24 100944 S1 .OP-ST.RPl-0003(0)  ! PIT 2YR 100301 S1 .OP-ST.MS-0003(0) STC cs CS-24 100944 14MS167 14 MN STM & TRB BY PASS STM GEN HYO OPRD ISOL VLV (MSIV) 205203-2 Main, Reheat, and Turbine Bypass Steam G7 2 B GT STM 32 0 c Active S1 .OP-ST.MS-0003(0) FSTC cs CS-24 100944 S1 .OP-ST.RPl-0003(0) i PIT 2YR 100301 S1 .OP-ST.MS-0003(0) STC cs CS-24 100944 11MS169 11 MN STM & TRB BY PASS STM GEN ISOL VLV AIR OPRD STM ASSIST VLV 205203-1 Main, Reheat, and Turbine Bypass Steam G7 2 B GT AIR 2 c 0 Active 81 .OP-8T.MS-0002(0) FSTO . cs CS-25 100554 81 .OP-ST.MS-0002(0) 8TO cs C8-25 100554

TABLE 3 VALVE TEST TABLE.

10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 54 VALVE NO VALVE DESCRIPTION P +ID No P+/DName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK !TECH. Pos.! COMMENTS 12MS169 12 MN STM & TRB BY PASS MS HOR ATM VENT AIR OPERATED ANGLE VALVE 205203-2 Main, Reheat, and Turbine Bypass Steam DB 2 B GT AIR 2 C O Active

---

.------------------.------------------;-------------------;:-------------------;:------------------;-------------------------:------------------7------------------------------------------------------------*

S1 .OP-ST.MS-0002(Q) FSTO i CS i CS-25 100554 S1 .OP-ST.MS-0002(Q) STO CS  ! CS-25 100554 13MS169 13 MN STM & TRB BY PASS STM GEN ISOL VLV AIR OPRD STM ASST VLV 205203-1 Main, Reheat, and Turbine Bypass Steam Cl 2 B GT AIR 2 c 0 Active

---

.------------------;------------------:-------------------:-------------------:------------------.------------------------- -----------------7-------------------------------------------------------------

s1 .OP-ST.MS-0002(Q) i FSTO i CS i CS-25 100554 i S1.0P-ST.MS-0002(Q) STO CS  ! CS-25 100554 14MS169 14 MN STM & TRB BY PASS MS HOR ATMOS VENT AIR OPRD ANGLE VLV 205203-2 Main, Reheat, and Turbine Bypass Steam GB 2 B GT AIR 2 c 0 Active

---

.------------------.------------------:-------------------:-------------------=------------------.------------------------

S1 .OP-ST.MS-0002(Q) FSTO i CS i CS-25 100554 S1 .OP-ST.MS-0002(Q) STO CS i CS-25 100554 11MS171 11 MN STM & TRB BY PASS STM GEN ISOL VLV AIR OPRD STM ASSISTVLV 205203-1 Main, Reheat, and Turbine Bypass Steam GB 2 B GT AIR 2 c 0 Active

• • 5*1:0P~si Ms~*aoo2ca)*-*--*--*-i=sio--*i--*****cs*-----*r----cs~2s-----,----------*-*-----,-***-**--*--*-**-.*-*-****1ao55_4 _____ _

S1.0P-ST.MS-0002(Q) STO CS i CS-25 100554 12MS171 12 MN STM & TRB BY PASS MS HOR ATM VENT AIR OPERATED ANGLE VALVE 205203-2 Main, Reheat, and Turbine Bypass Steam DB 2 B GT AIR 2 c 0 Active S1 .OP-ST.MS-0002(Q) FSTO cs CS-25 100554 S1 .OP-ST.MS-0002(Q) STO cs CS-25 100554

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 55 VALVE NO VALVE DESCRIPTION P+ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

---~~~~-~~~-~----------------------h-~~~-~~~~h~~~-~~~aT-~.-;.-~~~~---i--~.-~.--~~~~:-r-~~~-~-~~~.-r~~~-~-~.-~~~~---r~~~~:-~~-~T~~~-~~~~~------------------------------------------

13MS171 13 MN STM & TRB BY PASS STM GEN ISOL VLV AIR OPRD STM ASST VLV 205203-1 Main, Reheat, and Turbine Bypass Steam DB 2 B GT AIR 2 c 0 Active S1 .OP-ST.MS-0002(0) FSTO : CS i CS-25 100554 S1 .OP-ST.MS-0002(0) STO CS i CS-25 100554 14MS171 14 MN STM & TRB BY PASS MS HOR ATMOS VENT AIR OPRD ANGLE VLV 205203-2 Main, Reheat, and Turbine Bypass Steam GB 2 B GT AIR 2 c 0 Active S1 .OP-ST.MS-0002(0) FSTO : CS  : CS-25 i 100554 i S1 .OP-ST.MS-0002(0) STO CS i CS-25 100554 1NT25 1 REACT COOL PZR RELIEF TK NITROGEN SUPPLY AIR OPRD VLV 205201-1 Reactor Coolant C10 2 A DIA AIR 0.75 O/C c Active

---

*---.------------------.------------------;-------------------;-------------------=------------------.-------------------------:-----*----------- --------------------------------------------------------*****

S1 .OP-ST.ZZ-0003(0) FSTC 0 100726 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290539 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.ZZ-0003(0) STC 0 100726 1NT26 1 REACT COOL NITROGEN SUPPLY TO PZR RELIEF TANK CHECK VLV 205201-1 Reactor Coolant C9 2 A/C CK SELF 0.75 O/C c Active

-~ -- -- - . - - ----. ------- -- ---- . --- . - . - . - -- - - - -- -- -- -- . - . - -- -. -.

S1 .RA-IS.ZZ-0001 (0) CTC RF V-15 290540 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290540 1NT32 1 SAFETY INJ BOTTLED H.P. N2 TO ACCUMULATORS ISOL AIR OPRD GLB VLV 205234-3 Safety Injection H7 2 A GB AIR 1 O/C c Active S1 .OP-ST.ZZ-0003(0) FSTC 0 100726 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290541 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.ZZ-0003(0) STC 0 100726

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 56 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification 1 I I I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK !TECH. POS.! COMMENTS 1NT34 1 SAFETY INJ BOTTLED H.P. N2 TO ACCUMULATORS CHECK VLV 205234-3 Safety Injection H7 2 A/C CK SELF 1 O/C c Active

-  ;-  ;- - - - - - - --- - - ---- --. ------ ------ ----- - - - - - -- - ;- -------------- ---~ -------- -- -- - - -- - -- - -- - - -- - - -- - - -- - - - - -- - - - -----------------

S1 .RA-IS.ZZ-0001 (0) CTC RF V-15 290542 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290542 1PR1 1 POPS PRESSURIZER OUTLET AIR OPRD VLV 205201-1 Reactor Coolant F1 1 B GB AIR 3 c O/C Active S1 .OP-ST.PZR-0003(0) FSTC CS CS-26 101288 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.PZR-0003(0) STC CS CS-26 101288 S1 .OP-ST.PZR-0003(0) STO CS CS-26 101288 1 PR2 1 POPS PRESSURIZER TO PRESSURIZER RELIEF TANK AIR OPRD VLV 205201-1 Reactor Coolant F2 1 B GB AIR 3 c O/C Active S1 .OP-ST.PZR-0003(0) FSTC CS CS-26 101288 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.PZR-0003(0) STC CS CS-26 101288 S1 .OP-ST.PZR-0003(0) STO CS CS-26 101288 1PR3 1 POPS PRESSURIZER SAFETY RELIEF VALVE 205201-1 Reactor Coolant F2 1 c RV SELF 6 c O/C Active SC.MD-PT.RC-0001 (0)  ! RV 5YR 290193 1PR4 1 POPS PRESSURIZER SAFETY RELIEF VALVE 205201-1 Reactor Coolant F3 1 c RV SELF 6 c O/C Active

~ -- -- - --- -- ---- ---- ----- ---- --- -- - -

SC.MD-PT.RC-0001 (0) ! RV 5YR 290195

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 57 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' ' I t I I I I I I I I TEST PROC :TEST TYPE :TEST FREQ.: C.S. JUST. : R.O. JUST. : REL. REQ. : RECUR. TASK !TECH. POS.! COMMENTS 1PR5 1 POPS PRESSURIZER SAFETY RELIEF VALVE 205201-1 Reactor Coolant F4 1 c RV SELF 6 c O/C Active SC.MD-PT.RC-0001 (0) [ RV [ 5YR 290197 [

1PR6 1 POPS PRESSURIZER RELIEF STOP MOTOR OPERATED VLV 205201-1 Reactor Coolant F1 1 B GB MO 3 0 O/C Active

'  :' ~ -;

S1 .OP-ST.RPl-0002(0) PIT ~R  : i 100299 S1 .OP-ST.PZR-0002(0) i STC o 101237 S1 .OP-ST.PZR-0002(0) i STO o 101237 1PR7 1 POPS PRESSURIZER RELIEF STOP MOTOR OPERATED VLV 205201-1 Reactor Coolant F2 1 B GB MO 3 0 O/C Active

'  :' ~

S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.PZR-0002(0) [ STC o 101237 S1 .OP-ST.PZR-0002(0) [ STO o 101237 1PR17 1 POPS PRESSURIZER RELIEF TANK TO GAS SAMPLE AIR OPRD VLV 205201-1 Reactor Coolant D9 2 A GB AIR 0.375 c c Active S1 .OP-ST.ZZ-0003(0) FSTC o 100726 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290543 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.ZZ-0003(0) STC 0 100726

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 58 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ~ REL. REQ. ! RECUR. TASK ! TECH. POS.! COMMENTS 1PR18 1 POPS PZR RELIEF TANK TO GAS SAMPLE AIR OPRD VLV 205201-1 Reactor Coolant 0-10 2 A GB AIR 0.375 c c Active S1 .OP-ST.ZZ-0003(0) FSTC o 100726 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290544 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.ZZ-0003(0) STC o 100726 1PR25 1 POPS PRESSURIZER RELIEF TANK INLET CHECK VLV 205201-1 Reactor Coolant E9 2 A/C CK SELF 4 c O/C Active

~ - - - -- -- -- -- -- - - --. ------------ - - - - - --- - -- - - - - -- - - - - -- -- - - - - - - - - - - - ---- -- ------- - ---------------- -- -- - - -- - - -- - - -- - ----- --

S1.RA-IS.ZZ-0001(0) CTC  ! RF  !  : V-16 290545 S1 .OP-ST.ZZ-0003(0) CTO 0 100726 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290545 1PS1 1 PZR PRESSURIZER SPRAY AIR OPRD VLV 205201-1 Reactor Coolant F5 1 8 GB AIR 0.5 O/C c Active S1 .OP-ST.PZR-0003(0) FSTC cs CS-27 101288 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.PZR-0003(0) STC cs CS-27 101288 1PS3 1 PZR PRESSURIZER SPRAY AIR OPRD VLV 205201-1 Reactor Coolant 06 1 B GB AIR 0.5 O/C c Active S1 .OP-ST.PZR-0003(0) FSTC cs CS-27 101288 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.PZR-0003(0) STC cs CS-27 101288

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 59 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.: C.S. JUST. : R.O. JUST. : REL. REQ. ! RECUR. TASK j TECH. POS.! COMMENTS 1RC40 1 REACT COOL REACT HEAD VENT VLV 1RC40 SV 205201-1 Reactor Coolant GB 1 B GB SOL 0.75 c O/C Active S1 .OP-ST.PZR-0003(0) FSTC cs CS-28 101288 S1 .OP-ST.RC-0009(0) PIT 2YR 100283 S1 .OP-ST.PZR-0003(0) STC cs CS-28 101288 S1 .OP-ST.PZR-0003(0) STO cs CS-28 101288 1RC41 1 REACT COOL REACT HEAD VENT VLV 1RC41 SV 205201-1 Reactor Coolant G7 1 B GB SOL 0.75 c O/C Active S1.0P-ST.PZR-0003(Q) i FSTC CS CS-28  ! 101288 S1 .OP-ST.RC-0009(0) PIT 2YR 100283 S1.0P-ST.PZR-0003(Q) STC CS CS-28 101288 S1 .OP-ST.PZR-0003(0) STO CS CS-28 101288 1RC42 1 REACT COOL REACT HEAD VENT VLV 1 RC42 SV 205201-1 Reactor Coolant GB 1 B GB SOL 0.75 c O/C Active S1 .OP-ST.PZR-0003(0) . FSTC . CS ' CS-28 . 101288 S1 .OP-ST.RC-0009(0) PIT 2YR 100283 S1 .OP-ST.PZR-0003(Q) STC CS CS-28 101288 S1 .OP-ST.PZR-0003(0) STO cs CS-28 101288 1RC43 1 REACT COOL REACT HEAD VENT VLV 1 RC43 SV 205201-1 Reactor Coolant G7 1 B GB SOL 0.75 c O/C Active S1 .OP-ST.PZR-0003(0) FSTC cs CS-28 101288 81 .OP-ST.RC-0009(0) PIT 2YR 100283 S1 .OP-ST.PZR-0003(0) STC cs CS-28 101288 81 .OP-ST.PZR-0003(Q) STO cs CS-28 101288

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 60 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I TEST PROC iTEST TYPE iTEST FREO.i C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK !TECH. POS.i COMMENTS 1RH1 1 RHR COMMON SUCT MOT OP GATE VLV 205232-2 Residual Heat Removal G10 1 A GT MO 14 c O/C Active S1 .OP-ST.SJ-0021 (Q) LT 2YR 101302 S1 .OP-ST.RPl-0002(Q) PIT 2YR 100299 S1 .OP-ST.RHR-0004(0) STC cs CS-29 100583 S1 .OP-ST.RHR-0004(Q) STO cs CS-29 100583 1RH2 1 RHR COMMON SUCT MOT OP GATE VLV 205232-2 Residual Heat Removal G10 1 A GT MO 14 c O/C Active S1 .OP-ST.SJ-0021 (Q) LT 2YR 101302 S1 .OP-ST.RPl-0002(Q} PIT 2YR 100299 S1 .OP-ST.RHR-0004(Q) STC cs CS-29 100583 S 1. OP-ST. RHR-0004(Q) STO cs CS-29 100583 1RH3 1 RHR SAF RLF VLV TO PZR RELIEF TANK 205232-2 Residual Heat Removal H9 2 c RV SELF 3 c O/C Active SC.MD-PT.ZZ-0007(0) RV 5YR 290199 11RH4 11 RHR PMP SUCT MOV GATE VLV 205232-1 Residual Heat Removal E1 2 B GT MO 14 0 O/C Active S1 .OP-ST.RPl-0001 (Q) ! PIT 2YR 100298 81 .OP-ST.RHR-0003(Q)  ! STC Q 100721 12RH4 12RHRPMPSUCTGATEMOV 205232-2 Residual Heat Removal E1 2 B GT MO 14 0 O/C Active S1 .OP-ST.RPl-0001 (Q) PIT 2YR 100298 S1 .OP-ST.RHR-0003(Q) STC Q 100721

, TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 61 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I. I I I TEST PROC !TEST TYPE !TEST FREQ.j C.S. JUST. j R.O. JUST. j REL. REQ. j RECUR. TASK !TECH. POS.! COMMENTS 11RH8 11 RHR PMP DISCH CHECK VALVE 205232-1 Residual Heat Removal E3 2 c CK SELF 8 c O/C Active S1 .OP-ST.RHR-0001 (0) CTC o 100705 S1 .OP-ST.RHR-0001 (0) j CTO cs CS-30 101316 S1 .OP-ST.RHR-0001 (0) j PS o CS-30 100705 12RH8 12 RHR PMP DISCH CHECK VLV 205232-2 Residual Heat Removal F3 2 c CK SELF 8 c O/C Active S1 .OP-ST.RHR-0002(0) CTC Q 100706 S1 .OP-ST.RHR-0002(0)  ! CTO CS [ CS-30 101315 S1 .OP-ST.RHR-0002(0)  ! PS 0  : CS-30 100706 11RH18 11 RHR HX FLOW CONT AIR OPRD BTFL VLV 205232-1 Residual Heat Removal FB 2 B BFY AIR 8 O/C 0 Active S1 .OP-ST.SJ-0005(0) FSTO cs CS-31 100404 S1 .OP-ST.RPl-0003(0) j PIT 2YR 100301 S1 .OP-ST.SJ-0005(0) STO cs CS-31 100404 12RH18 12 RHR HX FLOW CONT AIR OPRD BTFL VLV 205232-2 Residual Heat Removal FB 2 B BFY AIR 8 O/C 0 Active S1 .OP-ST.SJ-0005(0) FSTO cs CS-31 100404 S1 .OP-ST.RPl-0003(0) ! PIT 2YR 100301 S1 .OP-ST.SJ-0005(0) STO cs CS-31 100404 11RH19 11 RHR HX DISCH CROSS CONN MOV GATE VLV 205232-1 Residual Heat Removal EB 2 B GT MO 8 0 O/C Active S1 .OP-ST.RPl-0001 (0) PIT 2YR 100298 S1 .OP-ST.RHR-0004(0) STC cs CS-32 100583

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 62 VALVE NO VALVE DESCRIPTION P +ID No P+ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC ~TEST TYPE ~TEST FREQ.~ C.S. JUST. : R.O. JUST. i REL. REQ. ~ RECUR. TASK !TECH. POS.: COMMENTS 12RH19 12 RHR HX DISCH CROSS CONN GATE MOV 205232-2 Residual Heat Removal EB 2 B GT MO B 0 O/C Active

'  ; ~ - - -- -- - - -- - - - -- - -; -- -- -- -- -- - - - - -- - - - - -- - - -- - - --- - -- - - -- -----

-- ---- ---- - - - . --- - -- -- -- -- - --- -- - - -- - -- -- -- -- - .. - . -- - - - - .. -

S1 .OP-ST.RPl-0001 (0) i PIT 2YR 100298 S1 .OP-ST.RHR-0004(0) i STC CS j CS-32 100583 1RH21 RHR Tie to Refueling Water Storage Tank 205232-1 Residual Heat Removal EB 2 A GT MAN B c c Passive

~ ~ ~

S1 .OP-ST.RC-0008(0) LT i 2YR i (later)  : Rec. Task (RT) prior to restart.

1RH25 1 RHR SAF RLF VLV TO PZR RELIEF TANK 205232-1 Residual Heat Removal H9 2 c RV SELF 0.75 c O/C Active

-- - -------- - -- - - -- -- - -- --- ---------- - --- - - - - -- - - - - - ----- ---- --- - - - - - -- - - - -- - -- ~ - - - - - - ------ ------- -- -- -- -- -- - - - - - - -- - - - - - -- -- -- -- - - -- -- -- - --- - - -- ---- -- -- -----.- -- -- - - -- - - - - - - -- - - -- - - - - - - -- -- -- -- - - -- - - - - - ------------ -- -

~

SC.MD-PT.ZZ-0007(0) RV 5YR  : 290201  :

1RH26 1 RHR HOT LEG ISOL GATE MOV 205232-1 Residual Heat Removal G10 1 B GT MO 12 c O/C Active S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.RHR-0004(0) i STC cs CS-51 100583 S1 .OP-ST.RHR-0004(0) i STO cs CS-51 100583 13RH27 13 RHR HOT LEG CHECK VALVE 205232-1 Residual Heat Removal G10 1 A/C CK SELF B c O/C Active

.S1 .OP-ST.SJ-0020(0) CTC RF V-40 100744 S1 .OP-ST.RHR-0005(0) CTO RF V-40 100608 81 .OP-ST.SJ-0020(0) LT 2YR 100744

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 63 VALVE NO VALVE DESCRIPTION P+ ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I t I I I TEST PROC !TEST TYPE !TEST FREQ) C.S. JUST. ! R.O. JUST.! REL. REQ. ! RECUR. TASK !TECH. POS.! COMMENTS 14RH27 14 RHR HOT LEG CHECK VALVE*

205232-1 Residual Heat Removal G10 1 A/C CK SELF 8 c O/C Active 51 .OP-5T.5J-0020(0) CTC RF V-40 100744 51 .OP-5T.RHR-0005(0) \ CTO RF V-40 100608 51 .OP-5T.5J-0020(0) LT 2YR 100744 11RH29 11 RHR PMP MIN FLOW MOV GLB VLV 205232-1 Residual Heat Removal G4 2 B GB MO 2 c O/C Active

~ ~

51 .OP-5T.RPl-0001 (0) PIT 2YR 100298 51 .OP-5T.RHR-0003(0) i 5TC 0 100721 51 .OP-5T.RHR-0003(0) ! 5TO 0 100721 12RH29 12 RHR PMP MIN FLOW GLB MOV 205232-2 Residual Heat Removal G4 2 B GB MO 2 c O/C Active

~  :' -;

51 .OP-5T.RPl-0001 (0) PIT 2YR 100298 51 .OP-5T.RHR-0003(0) ! 5TC 0 10072.1 51 .OP-5T.RHR-0003(0)  ! 5TO a 100721 1SA118 1 STAT AIR HOR CONTAINMENT ISLN GATE VLV 205217-3 Compressed Air D9 2 A GT MAN 3 LC c Passive LJ 18MO 290546 1SA119 1 STAT AIR CONTAINMENT HOR CHECK VALVE 205217-3 Compressed Air D10 2 A/C CK SELF 3 c c Passive

~

51 .RA-15.ZZ-0001 (0) LJ 18MO 290547

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 64 VALVE NO VALVE DESCRIPTION P +ID No P+ JD Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C,S. JUST. : R.O. JUST. i REL. REQ. ! RECUR. TASK !TECH. POS.: COMMENTS 1SA262 1 STAT AIR CONTAINMENT PRESS TEST ISLN GLB VALVE 205217-2 Compressed Air EB 2 A GB MAN 0.75 LC c Passive S1 .RA-IS.ZZ-0001 (Q) i LJ 18MO i 290548 1SA264 1 STAT AIR CONTAINMENT PRESS TEST ISLN GLB VALVE 205217-2 Compressed Air E9 2 A GB MAN 0.75 LC c Passive

~

LJ 18MO 290549 1SA265 1 STAT AIR CONTAINMENT PRESS TEST LINE ISLN GLB VALVE 205217-2 Compressed Air EB 2 A GB MAN 0.75 LC c Passive S1 .RA-IS.ZZ-0001 (Q)  ! LJ  ! 18MO 290550  !

1SA267 1 STAT AIR CONTAINMENT PRESS TEST LINE ISLN GLB VALVE 205217-2 Compressed Air E9 2 A GB MAN 0.75 LC c Passive S1 .RA-IS.ZZ-0001 (Q) LJ 18MO 290551 1SA268 1 STAT AIR CONTAINMENT PRESS TEST LINE ISLN GLB VALVE 205217-2 Compressed Air EB 2 A GB MAN 0.75 LC c Passive S1 .RA-IS.ZZ-0001 (Q) LJ 18MO 290552 1SA270 1 STAT AIR CONTAINMENT PRESS TEST LINE ISLN GLB VALVE 205217-2 Compressed Air E9 2 A GB MAN 0.75 LC c Passive S1 .RA-IS.ZZ-0001 (Q) LJ 18MO 290553 1SF22 1 SPNT FUEL CLG REFUEL WTR PURIF PMP SUCT FROM CANAL DIAPH VLV 205233-1 Spent Fuel Pool Cooling A6 2 A DIA MAN 3 c c Passive S1 .RA-IS.ZZ-0001 (Q) ' LJ ' 18MO . 290554

TABLE 3 VALVE TEST. TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 65 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I ' ' ' I TEST PROC iTEST TYPE iTEST FREQ.i C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK iTECH. POS.i COMMENTS 1SF36 1 SPNT FUEL CLG REFUELWTR PURIFICATION FILTER TO REFUELING CANAL 205233- t Spent Fuel Pool Cooling A3 2 A DIA MAN 2 C C Passive S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290556 1SJ1 1 SAFETY INJ REF WTR STRG TK TO CHG PMPS STOP VLV 205234-t Safety Injection F2 2 B GT MO 8 c O/C Active S1 .OP-ST.RPl-0003(0) PIT 2YR 100301 S1 .OP-ST.SJ-0003(0) STC 0 100723 S1 .OP-ST.SJ-0003(0) STO 0 100723 1SJ2 1 SAFETY INJ REF WTR STRG TK TO CHRG PMP STOP VLV 205234-t Safety Injection Ft 2 B GT MO 8 c O/C Active 51 .OP-ST.RPl-0003(0) i PIT 2YR i 100301 S1 .OP-ST.SJ-0003(0) STC 0 100723 S1 .OP-ST.SJ-0003(0) STO 0 100723 1SJ3 1 SAFETY INJ TO CHG PMPS SUCT CHECK VLV 205234-t Safety Injection Et 2 c CK SELF 8 c O/C Active S1 .OP-ST.SJ-0003(0) CTC 0 100723 S1 .OP-ST.SJ-0016(0) CTO RF V-18 101056 S1 .OP-ST.CVC-0007(0) PS cs V-18 100582 1SJ4 1 SAFETY INJ BORON INJ TK INLET MOV 205234-t Safety Injection 84 2 B GT MO 4 0 O/C Active S1 .OP-ST.RPl-0003(0) PIT 2YR 100301 S1 .OP-ST.SJ-0003(0) STC 0 100723

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 66 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST.  ! REL. REQ. ! RECUR. TASK ! TECH. POS.! COMMENTS 1SJS 1 SAFETY INJ BORON INJ TK INLET MDV 205234-1 Safety Injection 84 2 B GT MO 4 0 DIC Active S1 .OP-ST.RPl-0003(0)  ! PIT 2YR 100301 S1 .OP-ST.SJ-0003(0) STC 0 100723 1SJ12 1 SAFETY INJ BORON INJ TK OUTLET MOV 205234-1 Safety Injection DB 1 B GT MO 4 c DIC Active S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.SJ-0003(0) STC 0 100723 S1 .OP-ST.SJ-0003(0) STO 0 100723 1SJ13 1 SAFETY INJ BORON INJ TK OUTLET MOV 205234-1 Safety Injection DB 1 B GT MO 4 c DIC Active S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.SJ-0003(0) STC 0 100723 S1 .OP-ST.SJ-0003(0) STO 0 100723 11SJ17 11 SAFETY INJECTION BORON INJECTION TANK TO COLD LEG CHECK VALVE 205234-1 Safety Injection H7 1 AIC CK SELF 1.5 c DIC Active S1 .OP-ST.SJ-0020(0) CTC RF V-19 100744 S1 .OP-ST.SJ-0016(0) CTO RF V-19 101056 S1 .OP-ST.SJ-0020(0) LT 2YR 100744 12SJ17 12 SAFETY INJ BORON INJ TK TO COLD LEG CKVL 205234-1 Safety Injection HB 1 A/C CK SELF 1.5 c DIC Active S1 .OP-ST.SJ-0020(0) CTC RF V-19 100744 S1 .OP-ST.SJ-0016(0) CTO RF V-19 101056 S1 .OP-ST.SJ-0020(0) LT 2YR 100744

TABLE 3-1 -VALVE. TEST TABLE.

10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 67 VALVE NO VALVE DESCRIPTION P+ ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification I I I I I I TEST PROC !TEST TYPE !TEST FREQ.!. C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK !TECH, POS.! COMMENTS 13SJ17 13 SAFETY INJ BORON INJ TK TO COLD LEG CKVL 205234-1 Safety Injection H10 1 A/C CK SELF 1.5 c O/C Active S1 .OP-ST.SJ-0020(Q) CTC RF V-19 100744 S1 .OP-ST.SJ-0016(Q) CTO RF V-19 101056 S1 .OP-ST.SJ-0020(Q) LT 2YR 100744 14SJ17 14 SAFETY INJ BORON INJ TK TO COLD LEG CKVL 205234-1 Safety Injection H9 1 A/C CK SELF 1.5 c O/C Active S1 .OP-ST.SJ-0020(Q) CTC RF V-19 100744 S1 .OP-ST.SJ-0016(Q) CTO RF V-19 101056 S1 .OP-ST.SJ-0020(Q) LT 2YR 100744 11SJ29 11 SAFETY INJ ACCUMULATOR SAF RLF VLV 205234-4 Safety Injection G2 3 c RV SELF 1 c O/C Active

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -- -- -- - - - -. - - - - - - - - - - - - - - - - - -. - - - - - - - - - - - - - - - - - - .- - - - - - - - - - - - - - - - - - - ; - - - - - - - - - - - - - ~ - - - - ~ - - - - - - - -- - - - - - - - -. - - - - - - - - - - - - - - - - - - - - - - - - - ; - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

• SC.MD-PT.ZZ-0007(0) RV 5YR i i 290207 12SJ29 12 SAFETY INJ ACCUMULATOR SAF RLF VLV 205234-4 Safety Injection GS 3 c RV SELF 1 c O/C Active

-- ------ -------- ---------- -- - - - --- ---- ----. ----------- - - - -- - -. -- - - - - - - - - - - - - -- - - :- - - - - - -- - ----- -- -- -:- . - ---------- -- ----:- ------- ----------. ---------------------- ---:- ------------ ----- -------------- ---------- ------ ------------------ ------ ---- --. ~

RV 5YR 290213 13SJ29 13 SAFETY INJ ACCUMULATOR SAF RLF VLV 205234-4 Safety Injection G7 3 c RV SELF 1 c O/C Active SC.MD-PT.ZZ-0007(Q)  : RV . 5YR . .  ! . 290215 .  !

14SJ29 14 SAFETY INJ ACCUMULATOR SAF RLF VLV 205234-4 Safety Injection G10 3 c RV SELF 1 c O/C Active SC.MD-PT.ZZ-0007(Q) i RV i 5YR  ! 290217

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 68 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC iTEST TYPE !TEST FREQ) C.S. JUST. l R.O. JUST.! REL. REa. RECUR. TASK !TECH. POs.l COMMENTS l 1SJ30 1 SAFETY INJ REFUEL WTR STOR TK TO SAF INJ PMPS STOP MOV 20S234-2 Safety Injection G2 2 B GB MO 8 0 DIC Active S1 .OP-ST.RPl-0003(0) [ . PIT 2YR 100301 S1 .OP-ST.SJ-0005(0) STC CS  ! CS-34 100404 1SJ31 1 SAFETY INJ REFUEL WTR STOR TK TO SAF INJ PMPS CHK VLV 20S234-2 Safety Injection G2 2 C CK SELF 8 c DIC Active S1 .OP-ST.SJ-0003(0) CTC 0 100723 S1 .OP-ST.SJ-0014(0) CTO RF V-20 100097 S1 .OP-ST.SJ-0001 (0) PS 0 100709 S1 .OP-ST.SJ-0002(0) PS 0 100710 1SJ32 1 SAFETY INJ PMP SUCT SAF RLF VLV 20S234-2 Safety Injection GS 2 c RV SELF 0.7S c DIC Active SC.MD-PT.ZZ-0007(0) RV 5YR 290219 11SJ33 11 SAFETY INJ PMP SUCT MOV 20S234-2 Safety Injection G2 2 B GT MO 6 0 0 Passive PIT 2YR 100298 12SJ33 12 SAFETY INJ PMP SUCT MOV 20S234-2 Safety Injection GS 2 B GT MO 6 0 0 Passive S1 .OP-ST.RPl-0001 (0)  ! PIT 2YR

.. 100298 11SJ34 11 SAFETY INJECTION PUMP DISCHARGE CHECK VALVE 20S234-2 Safety Injection OS 2 c CK SELF 4 c DIC Active S1 .OP-ST.SJ-0002(0) CTC 0 100710 S1 .OP-ST.SJ-0014(0) CTO RF V-21 100097

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 69 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC [TEST TYPE!TEST FREQ) C.S. JUST. ! R.O. JUST. [REL. REQ. ! RECUR. TASK [TECH. POS.! COMMENTS 12SJ34 12 SAFETY INJECTION PUMP DISCHARGE CHECK VALVE 205234-2 Safety Injection D7 2 C CK SELF 4 C O/C Active S1 .OP-ST.SJ-0001 (0) CTC 0 '

' ' 100709 S1 .OP-ST.SJ-0014(0) CTO RF V-21 100097 11SJ39 11 SAFETY INJ HOR SAF RLF VLV 205234-2 Safety Injection DB 2 c RV SELF 0.75' c O/C Active SC.MD-PT.ZZ-0007(0) RV 5YR 290221 12SJ39 12 SAFETY INJ HOR SAF RLF VLV 205234-2 Safety Injection DB 2 c RV SELF 0.75 c O/C Active SC.MD-PT.ZZ-0007(0) RV 5YR [ [ [ 290223 11SJ40 11 SAFETY INJ PMP DISCH TO HOT LEG HOR STOP MOV 205234-2 Safety Injection G9 1 B GT MO 4 c O/C Active

. S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.SJ-0005(0) STC cs CS-36 100404 S1 .OP-ST.SJ-0005(0) STO cs CS-36 100404 12SJ40 12 SAFETY INJ HOR STOP MOV 205234-2 Safety Injection GB 1 B GT MO 4 c O/C Active S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.SJ-0005(0) STC cs CS-36 100404 S1 .OP-ST.SJ-0005(0) STO cs CS-36 100404

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 70 VALVE NO VALVE DESCRIPTION P + ID No P + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST.! REL. REQ. ! RECUR. TASK !TECH. POS.! COMMENTS 11SJ43 11 Sl/RHR HEAT EXCHANGER TO COLD LEG CHECK VALVE 205234-4 Safety Injection E3 1 A/C CK SELF 6 c O/C Active S1 .OP-ST.SJ-0020(0) CTC RF V-22 100744 SC.MD-PM.ZZ-0075(0) CTO SAM V-22 203790 TP-6 S1 .OP-ST.SJ-0020(0) LT 2YR 100744 S1 .OP-ST.SJ-0005(0) PS cs V-22 100404 12SJ43 12 SAFETY INJ COLD LEG LINE CHECK VLV 205234-4 Safety Injection ES 1 A/C CK SELF 6 c O/C Active S1.0P-ST.SJ-0020(0) CTC  ! RF [ V-22 100744 [

SC.MD-PM.ZZ-0075(0) CTO SAM V-22 204018 TP-6 S1 .OP-ST.SJ-0020(0) LT 2YR 100744 S1.0P-ST.SJ-0005(0) PS CS V-22 100404 13SJ43 13 SAFETY INJ RESID HT REMOVAL HT EXCHG TO COLD LEG CHECK VLV 205234-4 Safety Injection DB 1 A/C CK SELF* 6 c O/C Active S1 .OP-ST.SJ-0020(0) CTC RF V-22 100744 SC.MD-PM.ZZ-0075(0) CTO SAM V-22 204022 TP-6 S1 .OP-ST.SJ-0020(0) LT 2YR 100744 S1 .OP-ST.SJ-0005(0) PS cs V-22 100404 14SJ43 14 SAFETY INJ RESID HT REMOVAL HT EXCHG TO COLD LEG CHECK VLV 205234-4 Safety Injection D11 1 A/C CK SELF 6 c O/C Active S1 .OP-ST.SJ-0020(0) CTC RF V-22 100744 SC.MD-PM.ZZ-0075(0) CTO SAM V-22 204025 TP-6 S1 .OP-ST.SJ-0020(0) LT 2YR 100744 S1 .OP-ST.SJ-0005(0) PS cs V-22 100404

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 71 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification I I I I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK ! TECH. POS.! COMMENTS 11SJ44 11 SAFETY INJECTION CONTAINMENT SUMP SUCTION STOP MOV 205234-3 Safety Injection 83 2 B GT MO 14 c O/C Active S1 .OP-ST.RPl-0003(0) PIT 2YR V-23 101399 S1 .OP-ST.SJ-0005(0) STC CS  : CS-37 100404 S1 .OP-ST.SJ-0005(0) STO CS  : CS-37 100404 12SJ44 12 SAFETY INJECTION CONTAINMENT SUMP SUCTION STOP MOV 205234-3 Safety Injection 83 2 B GT MO 14 c O/C Active

- -- --- - - -- - - -- -- - - -- - - - --- ------ ------------------ ------ -- -------------- -- -- - - - - - - -- - - - - - - - - - . -- -- - - --- - - - ---- ------; --- -- -- ---- ------------ ---------- - - -- -- - - -- - - -- - -- - - - --- ~ --------------- --- -- - - - - -- -- - - -- -- -- -- ---- --- -- -------------

S1.0P-ST.RPl-0003(0) PIT 2YR ' V-23 101400 '

81 .OP-ST.SJ-0005(0) STC CS  ! CS-37 100404 S1 .OP-ST.SJ-0005(0) STO CS  ! CS-37 100404 11SJ45 11 SAFETY INJ RESID HEAT REMOVAL TO SAF INJ PMP STOP MOV 205234-2 Safety Injection G6 2 B GT MO 8 c O/C Active S1 .OP-ST.RPl-0003(0) ! PIT 2YR 100301 S1 .OP-ST.SJ-0005(0) STO CS  ! CS-38 100404 12SJ45 12 SAFETY INJ RESIDUAL HEAT REMOVAL PMP TO CHGING PMPS STOP MOV 205234-1 Safety Injection E3 2 B GT MO 8 c O/C Active

~

S1 .OP-ST.RPl-0003(0) ! PIT 2YR 100301 S1 .OP-ST.SJ-0005(0) STO CS  ! CS-38 100404 11SJ48 11 SAFETY INJECTION LOW HEAD LINE SAFETY RELIEF VALVE 205234-3 Safety Injection H6 2 C RV SELF 2.5 c O/C Active

~ .... --. -- - - --

SC.MD-PT.ZZ-0007(0) RV 5YR 290225

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 72 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification I I o I '

TEST PROC lTEST TYPE ~TEST FREQ.! C.S. JUST. ~ R.O. JUST. ~ REL. REQ. l RECUR. TASK lTECH. POS.~ COMMENTS 12SJ48 12 SAFETY INJ LOW HEAD LINE SAF RLF VLV 205234-3 Safety Injection E6 2 c RV SELF 2.5 c O/C Active SC.MD-PT.ZZ-0007(0) RV  ! 5YR 290227  :

11SJ49 11 SAFETY INJ RESID HT REMOVAL OUTLET TO COLD LEG MOV 205234-3 Safety Injection G7 1 8 GT MO 8 0 O/C Active S1 .OP-ST.RPl-0004(0) [ PIT  ! 2YR !  : 100302 S1 .OP-ST.SJ-0005(0) STC CS  : CS-39 100404 12SJ49 12 SAFETY INJ RESID HT REMOVAL OUTLET TO COLD LEG MOV 205234-3 Safety Injection D6 1 8 GT MO 8 0 O/C Active S1 .OP-ST.RPl-0004(0) [ PIT [ 2YR  ! 100302 81 .OP-ST.SJ-0005(0) STC CS  : CS-39 100404 1SJ53 1 SAFETY INJ HOR TEST AIR OPRD GATE VLV 205234-2 Safety Injection F10 1 A GB AIR 0.75 c c Passive

~ ... - -- -- -- - - - - - - . - - - - -- - -

S1 .OP-ST.SJ-0003(0) [ FSTC 0 [ 100723 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290558 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.SJ-0003(0) STC 0 100723 11SJ54 11 SAFETY INJ ACCUMULATOR OUTLET MOV 205234-4 Safety Injection E2 1 B GT MO 10 0 O/C Active S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.SJ"0004(0) STC cs CS-50 (later) Rec. Task (RT) prior to restart.

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 73 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC :TEST TYPE !TEST FREQ.! C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK !TECH. POS.: COMMENTS 12SJ54 12 SAFETY INJ ACCUMULATOR OUTLET MOV 205234-4 Safety Injection E4 1 B GT MO 10 0 O/C Active

'; ~ ';

S1 .OP-ST.RPl-0002(0) ! PIT 2YR 100299 S1 .OP-ST.SJ-0004(0) STC cs ! CS-50 (later) Rec. Task (RT) prior to restart.

13SJ54 13 SAFETY INJ ACCUMULATOR OUTLET MOV 205234-4 Safety Injection E7 1 B GT MO 10 0 O/C Active S1 .OP-ST.RPl-0002(0) ! PIT 2YR 100299 S1 .OP-ST.SJ-0004(0) STC CS  ! CS-50 (later) Rec. Task (RT) prior to restart.

14SJ54 14 SAFETY INJ ACCUMULATOR OUTLET MOV 205234-4 Safety Injection E10 1 B GT MO 10 0 O/C Active S1 .OP-ST.RPl-0002(0) ! PIT 2YR 100299 S1 .OP-ST.SJ-0004(0) STC cs : CS-50 (later) Rec. Task (RT) prior to restart.

11SJ55 11 SAFETY INJ ACCUMULATOR OUTLET LINE TO COLD LEG CHECK VLV 205234-4 Safety Injection E2 1 AIC CK SELF 10 c O/C Active S1 .OP-ST.SJ-0020(0)  ! CTC . RF  !  ! i V-24 . 100744 S1 .OP-ST.SJ-0006(0) CTO RF V-24 100635 S1.0P-ST.SJ-0020(0) LT 2YR 100744 12SJ55 12 SAFETY INJ ACCUMULATOR OUTLET TO COLD LEG CHECK VLV 205234-4 Safety Injection 04 1 AIC CK SELF 10 c O/C Active S1 .OP-ST.SJ-0020(0) CTC RF V-24 100744 S1 .OP-ST.SJ-0006(0) CTO RF V-24 100635 S1 .OP-ST.SJ-0020(0) LT 2YR 100744

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 74 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ) C.S. JUST. : R.O. JUST. : REL. REQ.: RECUR. TASK !TECH. pos.: COMMENTS 13SJ55 13 SAFETY INJ ACCUMULATOR OUTLET CHECK VLV 205234-4 Safety Injection El 1 A/C CK SELF 10 c O/C Active S1 .OP-ST.SJ-0020(Q) CTC RF i i i V-24 . 100744 i S1 .OP-ST.SJ-0006(Q) CTO RF V-24 100635 S1 .OP-ST.SJ-0020(0) LT 2YR 100744 14SJ55 14 SAFETY INJ ACCUMULATOR OUTLET TO COLD LEG CHECK VLV 205234-4 Safety Injection D10 1 AIC CK SELF 10 c O/C Active S1 .OP-ST.SJ-0020(Q) CTC RF V-24 100744 S1 .OP-ST.SJ-0006(0) CTO RF V-24 100635 S1 .OP-ST.SJ-0020(Q) LT 2YR 100744 11SJ56 11 SAFETY INJECTION ACCUMULATOR OUTLET TO COLD LEG CHECK VALVE 205234-4 Safety Injection C2 1 AIC CK SELF 10 c O/C Active S1 .OP-ST.SJ-0020(Q) CTC RF V-25 100744 S1 .OP-ST.SJ-0006(Q) CTO RF V-25 100635 S1 .OP-ST.SJ-0020(Q) LT 2YR 100744 S1 .OP-ST.SJ-0005(0) PS cs V-25 100404 12SJ56 12 SAFETY INJECTION ACCUMULATOR OUTLET TO COLD LEG CHECK VALVE 205234-4 Safety Injection C4 1 AIC CK SELF 10 c O/C Active S1 .OP-ST.SJ-0020(Q) CTC RF V-25 100744 S1 .OP-ST.SJ-0006(Q) CTO RF V-25 100635 S1 .OP-ST.SJ-0020(Q) LT 2YR 100744 S1 .OP-ST.SJ-0005(Q) PS cs V-25 100404

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 75 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.: C.S. JUST. : R.O. JUST. : REL. REQ.: RECUR. TASK [TECH. POs.l COMMENTS 13SJ56 13 SAFETY INJECTION ACCUMULATOR OUTLET TO COLD LEG CHECK VALVE 205234-4 Safety Injection Cl 1 AJC CK SELF 10 C O/C Active S1 .OP-ST.SJ-0020(0) CTC RF . V-25 100744 '

S1 .OP-ST.SJ-0006(0) CTO RF V-25 100635 S1 .OP-ST.SJ-0020(0) LT 2YR 100744 S1 .OP-ST.SJ-0005(0) PS CS V-25 100404 14SJ56 14 SAFETY INJECTION ACCUMULATOR OUTLET TO COLD LEG CHECK VALVE 205234-4 Safety Injection C10 1 A/C CK SELF 10 c O/C Active S1 .OP-ST.SJ-0020(0) CTC RF V-25 100744 S1 .OP-ST.SJ-0006(0) CTO RF V-25 100635 S1 .OP-ST.SJ-0020(0) LT 2YR 100744 S1 .OP-ST.SJ-0005(0) PS cs V-25 100404 1SJ60 1 SAFETY INJ ACCUMULATOR TEST LINE AIR OPRD STOP GLB VLV 205234-4 Safety Injection B4 1 A GB AIR 0.75 c c Passive S1 .OP-ST.SJ-0003(0)  ! FSTC 0  ! 100723 i S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290559 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.SJ-0003(0) STC 0 100723 1SJ63 1 SAFETY INJ HOT LEG HEADER ACCUMULATOR INLET AIR OPERATED GLOBE VALVE 205234-4 Safety Injection B6 1 B GB AIR 0. 75 c c Active S1 .OP-ST.SJ-0003(0) FSTC 0 100723 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.SJ-0003(0) STC 0 100723

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 76 VALVE NO VALVE DESCRIPTION p + ID No P + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ) C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK !TECH. POs.! COMMENTS 11SJ64 11 SAFETY INJ PMP DISCH MIN FLOW CHECK VLV 205234-2 Safety Injection 05 2 c CK SELF 0.75 c O/C Active S1 .OP-ST.SJ-0002(0) CTC o 100710 .

S1 .OP-ST.SJ-0001 (0) CTO o 100709 12SJ64 12 SAFETY INJ PMP MIN FLOW CHK VLV 205234-2 Safety Injection 07 2 c CK SELF 0.75 c 0/C Active

-  ;

- ~ ~

S1 .OP-ST.SJ-0001 (0) CTC 0 100709 S1 .OP-ST.SJ-0002(0) CTO 0 100710 1SJ67 1 SAFETY INJ PMP MIN FLOW CONTRL VLV 205234-2 Safety Injection C3 2 B GB MO 2 0 O/C Active S1 .OP-ST.RPl-0001 (0) [ PIT 2YR 100298 S1 .OP-ST.SJ-0005(0) STC CS i CS-40 100404 1SJ68 1 SAFETY INJ PMP MIN FLOW CONTRL VLV 205234-2 Safety Injection C2 2 B GB MO 2 0 O/C Active S1 .OP-ST.RPl-0001 (0) [ PIT 2YR 100298 S1 .OP-ST.SJ-0005(0) STC CS i CS-40 100404 1SJ69 1 SAFETY INJ RESID HT REMOVAL SUCT FROM REFUEL WTR STOR TK MOV 205234-3 Safety Injection E1 2 B GT MO 12 0 O/C Active S1 .OP-ST.RPl-0003(0) PIT 2YR 100301 S1 .OP-ST.RHR-0004(0) STC cs CS-41 100583

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 77 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK !TECH. POS.! COMMENTS 1SJ70 1 SAFETY INJ REFUEL WTR STOR TK HOR CHECK VLV 205234-3 Safety Injection E1 2 c CK SELF 12 0 O/C Active 81 .OP-8T.RHR-0005(0) i CTC RF V-26 100608 81 .OP-8T.RHR-0005(0) \ CTO RF V-26 100608 11SJ93 11 SAFETY INJ ACCUMULATOR N2 INLET AIR OPRD GLB VLV 205234-4 Safety Injection G2 3 B GB AIR 1 c c Passive

---

.------------------.------------------;------------------;------------------.------------------.-------------------------;-----------------7------------------------------------------------------------*

81 .OP-8T.RPl-0002(0) i PIT 2YR 100299 12SJ93 12 SAFETY INJ ACCUMULATOR N2 INLET AIR OPRD STOP GLB VLV 205234-4 Safety Injection G4 3 B GB AIR 1 c c Passive

~

81 .OP-8T.RPl-0002(0) i PIT 2YR 100299 13SJ93 13 SAFETY INJ ACCUMULATOR N2 INLET AIR OPRD STOP GLB VLV 205234-4 Safety Injection G7 3 B GB AIR 1 c c Passive 81 .OP-8T.RPl-0002(0) i PIT 2YR 100299 14SJ93 14 SAFETY INJ ACCUMULATOR N2 INLET STOP AIR OPRD GLB VLV 205234-4 Safety Injection G10 3 B GB AIR 1 c c Passive 81 .OP-8T.RPl-0002(0) j PIT 2YR 100299 11SJ113 11 SAFETY INJ PMP CROSS OVER MOV 205234-1 Safety Injection E2 2 B GT MO 4 c O/C Active 81 .OP-8T.RPl-0001 (0) PIT 2YR 100298 81 .OP-8T.8J-0003(0) 8TO 0 100723

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 78 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

. TEST PROC !TEST TYPE !TEST FREQ) C.S. JUST. : R.O. JUST. : REL. REQ.: RECUR. TASK !TECH. Pos.: COMMENTS 12SJ113 12 SAFETY INJ PMP CROSS OVER MOV 205234-1 Safety Injection E3 2 B GT MO 4 c O/C Active

---

.------------------;------------------=-------------------:-*-----------------;------------------;-------------------------.------------------ ------------------------------------------------------------

81 .OP-ST.RPl-0001 (0) i PIT 2YR 100298 81 .OP-ST.SJ-0003(0) STO 0 100723 1SJ123 1 SAFETY INJ ACCUMULATOR TEST LINE AIR OPRD STOP GLB VLV 205234-4 Safety Injection 84 1 A GB AIR 0.75 c c Passive 81 .OP-ST.SJ-0003(0) FSTC 0 100723 81 .RA-IS.ZZ-0001 (0) LJ 18MO 290560 81 .OP-ST.RPl-0002(0) PIT 2YR 100299 81 .OP-ST.SJ-0003(0) STC 0 100723 11SJ134 11 SAFETY INJ PMP DISCH TO COLD LEG MOV 205234-2 Safety Injection F9 2 B GT MO 4 0 O/C Active 81 .OP-ST.RPl-0004(0) i PIT 2YR 100302 81 .OP-ST.SJ-0003(0) STC Q 100723 12SJ134 12 SAFETY INJ PMP TO COLD LEGS MOV 205234-2 Safety Injection FB 2 B GT MO 4 0 O/C Active 81 .OP-8T.RPl-0004(0) i PIT 2YR ' '

100302 81 .OP-8T.8J-0003(0) 8TC 0 100723 1SJ135 1 SAFETY INJ PMPS TO COLD LEG MOV 205234-2 Safety Injection G9 1 B GT MO 4 0 O/C Active 81 .OP-ST.RPl-0003(0) PIT 2YR 100301 81 .OP-8T.SJ-0005(0) STC cs CS-42 100404

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 79 VALVE NO VALVE DESCRIPTION P + ID No P + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK !TECH. POS.i COMMENTS 11SJ139 11 SAFETY INJ PMP DISCH TO HOT LEG CHK VLV 205234-3 Safety Injection D11 1 A/C CK SELF 2 c O/C Active S1 .OP-ST.SJ-0020(0) CTC RF V-27 100744 S1 .OP-ST.SJ-0015(0) CTO RF V-27 101055 S1 .OP-ST.SJ-0020(0) LT 2YR 100744 12SJ139 12 SAFETY INJ PMP DISCH TO HOT LEG CHK VLV 205234-3 Safety Injection C11 1 A/C CK SELF 2 c O/C Active S1 .OP-ST.SJ-0020(0) CTC RF V-27 100744 S1 .OP-ST.SJ-0015(0) CTO RF V-27 101055 S1 .OP-ST.SJ-0020(0) LT 2YR 100744 13SJ139 13 SAFETY INJ HOT LEG CHK VLV 205234-3 Safety Injection G10 1 A/C CK SELF 2 c O/C Active S1 .OP-ST.SJ-0020(0) CTC RF V-27 100744 S1 .OP-ST.SJ-0015(0) CTO RF V-27 101055 S1 .OP-ST.SJ-0020(0) LT 2YR 100744 14SJ139 14 SAFETY INJ HOT LEG CHECK VLV 205234-3 Safety Injection GB 1 A/C CK SELF 2 c O/C Active S1 .OP-ST.SJ-0020(0) CTC RF V-27 100744 S1 .OP-ST.SJ-0015(0) CTO RF V-27 101055 S1 .OP-ST.SJ-0020(0) LT 2YR 100744

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 80

\

VALVE NO VALVE DESCRIPTION P + ID No P + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST .. j R.O. JUST. j REL. REQ. j RECUR. TASK !TECH. POS.i COMMENTS 11SJ144 11 SAFETY INJECTION COLD LEG LINE CHECK VALVE 205234-4 Safety Injection D3 1 A/C CK SELF 2 c O/C Active S1 .OP-ST.SJ-0020(0) CTC RF V-28 100744 S1 .OP-ST.SJ-0014(0) CTO RF V-28 100097 S1 .OP-ST.SJ-0020(0) LT 2YR 100744 12SJ144 12 SAFETY INJ COLD LEG FLOW CHECK VLV 205234-4 Safety Injection F6 1 A/C CK SELF 2 c DIC Active

- --- -- - - -- -- -- -- -- - --------- --------------. -- -- -- ---- -- - -- - - -. - -- - - - - - . - -- - - - - -- ~ - - - -- - - - - -- --- ----~ -------- - - -- -- -- -- ----------- - - - - -

S1 .OP-ST.SJ-0020(0) CTC RF V-28 100744 S1 .OP-ST.SJ-0014(0) CTO RF V-28 100097 S1 .OP-ST.SJ-0020(0) LT 2YR 100744 13SJ144 13 SAFETY INJ COLD LEG HOR CHECK VLV 205234-4 Safety Injection FB 1 A/C CK SELF 2 c O/C Active S1 .OP-ST.SJ-0020(0) CTC RF V-28 100744 S1 .OP-ST.SJ-0014(0) CTO RF V-28 100097 S1 .OP-ST.SJ-0020(0) LT 2YR 100744 14SJ144 14 SAFETY INJ COLD LEG LINE CHECK VLV 205234-4 Safety Injection F11 1 A/C CK SELF 2 c O/C Active S1 .OP-ST.SJ-0020(0) CTC RF V-28 100744 S1 .OP-ST.SJ-0014(0) CTO RF V-28 100097 S1 .OP-ST.SJ-0020(0) LT 2YR 100744

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 81 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! . R.O. JUST. : REL. REQ. ! RECUR. TASK ! TECH. POS.! COMMENTS 1SJ150 1 SAFETY INJECTION BORON INJECTION TANK TO COLD LEG CHECK VALVE 205234-1 Safety Injection F9 1 A/C CK SELF 3 c O/C Active S1 .OP-ST.SJ-0020(0) CTC RF V-29 100744 S1 .OP-ST.SJ-0016(0) CTO RF V-29 101056 S1 .OP-ST.SJ-0020(0) LT 2YR 100744 11SJ156 11 SAFETY INJ HOT LEG CHK VLV 205234-3 Safety Injection G11 1 A/C CK SELF 6 c O/C Active S1 .OP-ST.SJ-0020(0) CTC RF V-30  ! 100744 i S1 .OP-ST.SJ-0015(0) CTO RF V-30 101055 S1 .OP-ST.SJ-0020(0) LT 2YR 100744 12SJ156 12 SAFETY INJ HOT LEG CHK VLV 205234-3 Safety Injection G11 1 A/C CK SELF 6 c O/C Active S1 .OP-ST.SJ-0020(0) CTC RF V-30 100744 S1 .OP-ST.SJ-0015(0) CTO RF V-30 101055 S1 .OP-ST.SJ-0020(0) LT 2YR 100744 13SJ156 13 SAFETY INJ HOT LEG CHK VLV 205234-3 Safety Injection H9 1 A/C CK SELF 6 c O/C Active S1 .OP-ST.SJ-0020(0) CTC RF V-30 100744 S1 .OP-ST.SJ-0015(0) CTO RF V-30 101055 S1 .OP-ST.SJ-0020(0) LT 2YR 100744

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 82 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I I TEST PROC !TEST TYPE !TEST FREQ.j C.S. JUST. j R.O. JUST. j REL. REQ. j RECUR. TASK !TECH. POS.j COMMENTS 14SJ156 14 SAFETY INJ HOT LEG CHK VLV 205234-3 Safety Injection H9 1 AJC CK SELF 6 c O/C Active 81 .OP-8T.8J-0020(0) CTC RF V-30 100744 81 .OP-8T.8J-0015(0) CTO RF V-30 101055 81 .OP-8T.8J-0020(0) LT 2YR 100744 1SJ158 1 SAFETY INJECTION TEST LINE AIR OPERATED STOP GLOBE VALVE 205234~4 Safety Injection H1 1 B GB AIR 0.75 c c Active 81 .OP-8T.8J-0003(0) F8TC 0 100723 81 .OP-ST.RPl-0002(0)  : PIT 2YR 100299 81 .OP-8T.8J-0003(0) 8TC 0 100723 1SJ159 1 SAFETY INJECTION AIR OPERATED STOP VALVE 205234-4 Safety Injection BB 1 B GB AIR 0.75 c c Active

---

.---------------*--.------------------;-------------------.-------------------;------------------.-------------------------:------------------7------------------------------------------------------------*

81 .OP-8T.8J-0003(0) F8TC 0 100723 81 .OP-8T.RPl-0002(0) i PIT 2YR 100299 81 .OP-8T.8J-0003(0) 8TC 0 100723 ,*

1SJ166 1 SAFETY INJ BORON INJ TANK TO COLD LEG TEST LINE AIR OPER GLOBE VLV 205234-1 Safety Injection E9 1 B GB AIR 0.75 c c Active 81 .OP-ST.SJ-0003(0) FSTC 0 100723 81 .OP-ST.RPl-0002(0) j RPI 2YR 100299 81 .OP-ST.8J-0003(Q) 8TC 0 100723 1SJ167 1 SAFETY INJ COLD LEG SAF RLF VLV 205234-2 Safety Injection GB 2 c RV SELF 0.75 c O/C Active

- -- -- - - . --; -. - . -- . - . ----- -- - - ~ ------- - - - - - -- --. -- - - - - -- ----------------- .- - - - - -- - . - - - - - - - - - : - . - - . - - . - -.. -- ------ -- -.... - -. -- - -

8C.MD-PT.ZZ-0007(0)  ! RV ! 5YR 290229

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 83 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST . Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC jTEST TYPE !TEST FREQ.: C.S. JUST. : R.O. JUST.: REL. REQ.: RECUR. TASK !TECH. POS.: COMMENTS 1SS27 1 SMPLG SYS ACCUMULATOR SAMPLE HEADER ISLN AIR OPRD GLB VLV 205244-1 Sampling E6 2 A GB AIR 0.375 O/C c Active

~

S1 .OP-ST.PAS-0001 (0) FSTC 0 100570 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290561 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.PAS-0001 (0) STC 0 100570 1SS33 1 SMPLG SYS REACT COOL SAMPLE HEADER ISLN AIR OPRD GLB VLV 205244-1 Sampling G6 2 A GB AIR 0.375 O/C c Active S1 .OP-ST.PAS-0001 (Q) FSTC 0 100570 S1 .RA-IS.ZZ-0001 (Q) LJ 18MO 290563 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.PAS-0001 (0) STC 0 100570 1SS49 1 SMPLG SYS PZR LIQUID SAMPLE ISLN AIR OPRD GLB VLV 205244-1 Sampling G6 2 A GB AIR 0.375 O/C c Active S1 .OP-ST.PAS-0001 (Q) FSTC 0 100570 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290565 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.PAS-0001 (0) STC 0 100570 1SS64 1 SMPLG SYS PZR STEAM SAMPLE ISLN AIR OPRD GLB VLV 205244-1 Sampling H6 2 A GB AIR 0.375 O/C c Active S1 .OP-ST.PAS-0001 (0) FSTC 0 100570 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290567 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.PAS-0001 (0) STC 0 100570

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 84 VALVE NO VALVE DESCRIPTION P + ID No P + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC. !TEST TYPE !TEST FREa.! C.S. JUST. ! R.O. JUST.! REL. REQ. ! RECUR. TASK !TECH. POs.! COMMENTS 11SS94 11 SMPLG SYS STM GEN BLOWDOWN ISLN AIR OPRD GLB VLV 205244-1 Sampling D7 2 B GB AIR 0.375 0 C Active S1 .OP-ST.PAS-0001 (0) FSTC 0 100570 81.0P-ST.RPl-0004(0)  ! PIT 2YR 100302 S1 .OP-ST.PAS-0001 (0)  ! STC 0 100570 12SS94 12 SMPLG SYS FROM STM GEN SLOWDOWN LINE AIR OPRD GLS VLV 205244-1 Sampling C7 2 B GB AIR 0.375 0 c Active S1 .OP-ST.PAS-0001 (0) FSTC 0 100570 S1 .OP-ST.RPl-0004(0) i PIT 2YR 100302 S1 .OP-ST.PAS-0001"(0) i STC 0 100570 13SS94 13 SMPLG SYS FROM STM GEN SLOWDOWN LINE AIR OPRD GLS VLV 205244-1 Sampling B7 2 B GB AIR 0.375 0 c Active S1 .OP-ST.PAS-0001 (0) FSTC 0 100570 S1 .OP-ST.RPl-0004(0) ! PIT 2YR 100302 S1 .OP-ST.PAS-0001 (0)  ! STC 0 100570 14SS94 14 SMPLG SYS FROM STM GEN SLOWDOWN LINE AIR OPRD GLS VLV 205244-1 Sampling A7 2 B GB AIR 0.375 0 c Active S1 .OP-ST.PAS-0001 (0) FSTC 0 100570 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.PAS-0001 (0) STC 0 100570

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 85 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification 1 I I I I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK ! TECH. POS.: COMMENTS 1SS103 1 SMPLG SYS ACCUMULATOR SAMPLE HEADER ISLN AIR OPRD GLB VLV 205244-1 Sampling El 2 A GB AIR 0.375 O/C c Active S1 .OP-ST.PAS-0001 (0) FSTC 0 100570 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290562 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.PAS-0001 (0) STC 0 100570 1SS104 1 SMPLG SYS REACT COOL SAMP HEADER ISLN AIR OPRD GLB VLV 205244-1 Sampling G7 2 A GB AIR 0.375 O/C c Active S1 .OP-ST.PAS-0001 (0) FSTC 0 100570 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290564 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.PAS-0001 (0) STC 0 100570 1SS107 1 SMPLG SYS PZR LIQUID SAMPLE HEADER ISLN AIR OPRD GLB VLV 205244-1 Sampling G7 2 A GB AIR 0.375 O/C c Active 81 .OP-ST.PAS-0001 (0)  ! FSTC  ! 0 100570 S1 .RA-IS.ZZ-0001 (0) LJ 1BMO 290566 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.PAS-0001 (0) STC 0 100570 1SS110 1 SMPLG SYS PZR STEAM SAMPLE HEADER ISLN AIR OPRD GLB VLV 205244-1 Sampling H7 2 A GB AIR 0.375 O/C c Active S1 .OP-ST.PAS-0001 (0) FSTC 0 100570 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290568 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.PASS-0001 (0) STC 0 100570

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 86 VALVE NO VALVE DESCRIPTION P + ID No P + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC. \TEST TYPE !TEST FREQ.! C.S. JUST. : R.O. JUST. : REL. REQ.: RECUR. TASK [TECH. pos.[ COMMENTS 11SS181 11 SMPLG SYS INBOARD HOT LEG AIR OPRD GLB VLV 205244-3 Sampling Cl 2 A GB AIR 0. 75 C C Passive 51 .OP-5T.PA5-0001 (0) F5TC 0 100570 S1 .RA-15.ZZ-0001 (0) LJ 18MO 290569 51 .OP-5T.RPl-0004(0) PIT 2YR 100302 51 .OP-ST.PA5-0001 (0) 5TC 0 100570 13SS181 13 SMPLG SYS OUTBOARD HOT LEG AIR OPRD GLB VLV 205244-3 Sampling D7 2 A GB AIR 0.75 c c Passive 51 .OP-5T.PA5-0001 (0) F5TC 0 100570 51 .RA-15.ZZ-0001 (0) LJ 18MO 290573 51 .OP-5T.RPl-0004(0) PIT 2YR 100302 51 .OP-5T.PA5-0001 (0) 5TC 0 100570 11SS182 11 SMPLG SYS INBOARD HOT LEG AIR OPRD GLB VLV 205244-3 Sampling CB 2 A GB AIR . 0.75 c c Passive 51 .OP-5T.PA5-0001 (0) F5TC 0 100570 51 .RA-15.ZZ-0001 (0) LJ 18MO 290570 51 .OP-5T.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.PA5-0001 (0) STC 0 100570 13SS182 13 SMPLG SYS INBOARD HOT LEG AIR OPRD GLB VLV 205244-3 Sampling DB 2 A GB AIR 0.75 c c Passive 51 .OP-5T.PA5-0001 (0) F5TC 0 100570 51 .RA-15.ZZ-0001 (0) LJ 18MO 290574 51 .OP-5T.RPl-0002(0) PIT 2YR 100299 51 .OP-5T.PA5-0001 (0) 5TC 0 100570

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 87 VALVE NO VALVE DESCRIPTION P + ID No P + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK !TECH. POS.! COMMENTS 13SS184 13 SMPLG SYS INBOARD HOT LEG RETURN AIR OPRD GLB VLV 205244-3 Sampling CB 2 A GB AIR 0. 75 C C Passive 81 .OP-8T.PA8-0001 (0) F8TC 0 100570 81 .RA-18.ZZ-0001 (0) LJ 18MO 290575 81 .OP-8T.RPl-0002(0) PIT 2YR 100299 81 .OP-8T.PA8-0001 (0) 8TC 0 100570 13SS185 13 SMPLG SYS OUTBOARD HOT LEG RETURN AIR OPRD GLB VLV 205244-3 Sampling Cl 2 A GB AIR 0.75 c c Passive 81 .OP-8T.PA8-0001 (0) F8TC 0 100570 81 .RA-18.ZZ-0001 (0) LJ 18MO 290576 81 .OP-8T.RPl-0004(0) PIT 2YR 100302 81 .OP-8T.PA8-0001 (0) 8TC 0 100570 11SS188 11 SMPLG SYS TO CONTAINMENT SUMP AIR OPRD GLB VLV 205244-3 Sampling BB 2 A GB AIR 0.75 c c Passive 81 .OP-8T.PA8-0001 (0) F8TC 0 100570 81 .RA-18.ZZ-0001 (0) LJ 18MO 290571 81 .OP-8T.RPl-0002(0) PIT 2YR 100299 81 .OP-8T.PA8-0001 (0) 8TC 0 100570 11SS189 11 SMPLG SYS TO CONTAINMENT SUMP AIR OPRD GLB VLV 205244-3 Sampling Bl 2 A GB AIR 0.75 c c Passive 81 .OP-8T.PA8-0001 (0) F8TC 0 100570 81 .RA-18.ZZ-0001 (0) LJ 18MO 290572 81 .OP-8T.RPl-0004(0) PIT 2YR 100302 81 .OP-8T.PA8-0001 (0) 8TC 0 100570

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 88 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK ! TECH. POS.! COMMENTS 1SS650 SAMPLING SYSTEM THERMAL OVERPRESSURIZATION PROTECTION RV AUGMENTED 205244-1 Sampling EB N C RV SELF .5 C 0 Active

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.------------------.------------------:-------------------;-------------------.------------------.-------------------------.------------------7---------------------------------- ---*-*-------------------

SC.MD-PT.ZZ-0007(0) RV 5YR (later) DCP 1EC-3687, see PMCR 970527197 1SS653 SAMPLING SYSTEM THERMAL OVERPRESSURIZATION PROTECTION RV 205244-1 Sampling EB 2 c RV SELF .5 c O/C Active S1 .RA-IS.ZZ-0001 (0) LJ 18MO (later) Added per DCP 1EC-3687 Pkg. 1.

SC.MD-PT.ZZ-0007(0) RV 5YR (later) Added per DCP 1EC-3687 Pkg. 1.

1SV1198 PORV AIR ACCUMULATOR SUPPLY SOLENOID VALVE AUGMENTED 205247-3 No. 1 Unit - React. Cont. & Penetration Area H7 N B 3WAY SOL 1 c 0 Active S1 .RA-IS.PZR-0025(0) i FSTO ; RF  ; V-35 i (later) Rec. Task (RT) prior to restart.

S1 .RA-IS.PZR-0025(0) STO RF V-35 (later) Rec. Task (RT) prior to restart.

1SV1199 PORV AIR ACCUMULATOR SUPPLY SOLENOID VALVE AUGMENTED 205247-3 No. 1 Unit - React. Cont. & Penetration Area H7 N B 3WAY SOL 1 c 0 Active S1 .RA-IS.PZR-0025(0) FSTO  : RF V-35 (later) Rec. Task (RT) prior to restart.

S1 .RA-IS.PZR-0025(0) STO RF V-35 (later) Rec. Task (RT) prior to restart.

11SW2 11 SERVICE WATER AUTO STR OUTLET CHK VLV 205242-1 Service Water Nuclear Area Cl 3 c CK SELF 20 O/C O/C Active S1 .OP-ST.SW-0001 (0) CTC 0 100711 S1 .OP-ST.SW-0001 (0) CTO 0 100711 12SW2 12 SVCE WTR AUTO STR OUTLET CHK VLV 205242-1 Service Water Nuclear Area El 3 c CK SELF 20 O/C O/C Active S1 .OP-ST.SW~0002(0) CTC 0 100712 S1 .OP-ST.SW-0002(0) CTO 0 100712

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 89 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE!TEST FREQ.! C.S. JUST. ! R.O. JUST.! REL. REQ.: RECUR. TASK !TECH. POs.! COMMENTS 13SW2 13 SVCE WTR AUTO STR OUTLET CHK VLV 205242-1 Service Water Nuclear Area Gl 3 c CK SELF 20 0 O/C Active S1 .OP-ST.SW-0003(Q) [ CTC Q 1007°13 S1 .OP-ST.SW-0003(Q) [ CTO Q 100713 14SW2 14 SVCE WTR AUTO STR TO DISCH HEADER CHK VLV

• 205242-2 Service Water Nuclear Area Cl 3 c CK SELF 20 0 O/C Active S1 .OP-ST.SW-0004(Q) [ CTC Q 100714 S1 .OP-ST.SW-0004(Q)  ! CTO Q 100714 15SW2 15 SVCE WTR AUTO STR TO DISCH HEADER CHK VLV 205242-2 Service Water Nuclear Area El 3 c CK SELF 20 0 O/C Active S1 .OP-ST.SW-0005(Q) [ CTC Q 100715 S1 .OP-ST.SW-0005(Q) ! CTO Q 100715 16SW2 16 SVCE WTR AUTO STR TO DISCH HEADER CHK VLV 205242-2 Service Water Nuclear Area Gl 3 c CK SELF 20 0 O/C Active S1 .OP-ST.SW-0006(Q) CTC Q 100716 S1 .OP-ST.SW-0006(Q) CTO Q 100716

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 90 VALVE NO VALVE DESCRIPTION P+ ID No P + ID Name Drawing ASME /ST Valve Actuator Valve Normal sa;ety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. i REL. REQ. ! RECUR. TASK ! TECH. pas.! COMMENTS 12SW5 12 SVCE WTR PMP DISCH HEADER TO NUCLEAR HEADER CKVL 205242-1 Service Water Nuclear Area EB 3 c DCK SELF 24 DIC DIC Active SC.MD-PM.ZZ-01230) CTC RF V-31 203455 TP-6 SC.MD-PM.ZZ-01230) CTD RF V-31 203455 TP-6 S1 .DP-ST.SW-0001 (0) PS 0 V-31 100711 S1 .DP-ST.SW-0006(0) PS 0 V-31 100716 S1 .DP-ST.SW-0003(0) PS 0 V-31 100713 S1 .DP-ST.SW-0005(0) PS 0

• V-31 100715 S1 .DP-ST.SW-0002(0) PS 0 V-31 100712 14SW5 14 SVCE WTR PMP DISCH HEADER TO NUCLEAR HEADER CHK VLV 205242-2 Service Water Nuclear Area GB 3 c DCK SELF 24 DIC DIC Active SC.MD-PM.ZZ-01230) CTC RF V-31 203457 TP-6 SC.MD-PM.ZZ-01230) CTD RF V-31 203457 TP-6 S1 .DP~ST.SW-0004(0) PS 0 V-31 100714 11SW13 11 SVCE WTR PMP MTR BRG CLR OUTLET CHECK VLV 205242-1 Service Water Nuclear Area C4 3 c CK SELF 0.75 DIC D Active CTO 0 100711 12SW13 12 SVCE WTR PMP MTR BRG CLR OUTLET CHK VLV 205242-1 Service Water Nuclear Area E4 3 c CK SELF 0.75 DIC D Active

- - - - - - -- -------- - - - -- --- -- -- - - - - - ------- - -. -- - - - - -- -- ---- -- -. -. -- -- - - - - - - - - - - -- ~ - - - -- - - - - - - ---. ---~ --- --- - - - . - - - . -- - - .- - . - -- . ----------. ---- . - -- - ---- ----- - - -- - - - .- - - -- - - . - -- -- - - - -- : - - - - ---------- -- -- -

S1 .DP-ST.SW-0002(0) ! CTO 0 100712 13SW13 13 SVCE WTR PMP MTR BRG CLR OUTLET CHK VLV 205242-1 Service Water Nuclear Area G4 3 c CK SELF 0.75 DIC 0 Active

~ ~ ~

S1 .DP-ST.SW-0003(0) i CTO i 0 i j 100713  :

TABLE 3-1 -.VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 91 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification I I I I I I TEST PROC iTEST TYPE iTEST FREO.i C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK !TECH. POS.i COMMENTS 14SW13 14 SVCE WTR PMP MTR BRG CLR OUTLET CHK VLV 205242-2 Service Water Nuclear Area C4 3 c CK SELF 0.75 O/C 0 Active 81.0P-8T.8W-0004(0)  ! CTO 0 100714 ' '

15SW13 15 SVCE WTR PMP MTR BRG CLR OUTLET CHK VLV 205242-2 Service Water Nuclear Area E4 3 c CK SELF 0.75 O/C 0 Active CTO 0 100715 16SW13 16 SVCE WTR PMP MTR BRG CLR OUTLET CHK VLV 205242-2 Service Water Nuclear Area G4 3 c CK SELF 0.75 O/C 0 Active 81 .OP-8T.8W-0006(0)  ! CTO 0 100716 11SW17 11 SVCE WTR DISCH HEADER INTERTIE MTR OPRD BTFL VLV 205242-1 Service Water Nuclear Area G7 3 B BFY MO 30 0 0 Active

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S1 .OP-ST.RPl-0005(0) i PIT 2YR 100300 S1 .OP-ST.SW-0007(0)  ! STO 0 100725 12SW17 12 SVCE WTR DISCH HEADER INTER-TIE MTR OPRD BTFL VLV 205242-2 Service Water Nuclear Area C7 3 B BFY MO 30 0 0 Active S1 .OP-ST.RPl-0005(0) i PIT 2YR 100300 S1 .OP-ST.SW-0007(0) i STO 0 100725 11SW20 11 SERVICE WATER DISCHARGE HEADER TO TURBINE AREA MTR OPRD BTFLVLV 205242-1 Service Water Nuclear Area C7 3 B BFY MO 30 O/C c Active S1 .OP-ST.RPl-0005(0) PIT 2YR 100300 81 .OP-ST.SW-0007(0) STC 0 100725

TABLE 3-1.- VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 92 VALVE NO VALVE DESCRIPTION P +ID No P+ JD Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK !TECH. pos.! COMMENTS 12SW20 12 SVCE WTR NUCLEAR HEADER LINE INLET MTR OPRD BTFLVLV 205242-1 SeNice Water Nuclear Area EB 3 B BFY MO 24 O O Active S1 .OP-ST.RPl-0005(0)  ! PIT 2YR 100300 S1 .OP-ST.SW-0007(0) i STO 0 100725 13SW20

• 13 SVCE WTR DISCH HEADER TO TURB AREA MTR OPRD BTFL VLV 205242-2 SeNice Water Nuclear Area F7 3 B BFY MO 30 O/C c Active S1 .OP-ST.RPl-0005(0) i PIT 2YR 100300 S1 .OP-ST.SW-0007(0) i STC 0 100725 14SW20 14 SVCE WTR PMP DISCH HEADER TO NUCLEAR HEADER MTR OPRD BFLY VLV 205242-2 SeNice Water Nuclear Area G7 3 B BFY MO 24 0 0 Active S1 .OP-ST.RPl-0005(0)  ! PIT 2YR 100300 S1 .OP-ST.SW-0007(0) i STO 0 100725 11SW21 11 SVCE WTR NUCLEAR HEADER TO DSL GEN JKT WTR CLR 1A BTFL MOV 205242-3 SeNice Water Nuclear Area H6 3 B BFY MO 8 0 0 Passive PIT 2YR 100298 12SW21 12 SVCE WTR NUCLEAR HEADER TO DSL GEN JKT WTR CLR 1A BTFL MOV 205242-3 SeNice Water Nuclear Area H6 3 B BFY MO 8 0 0 Passive S1 .OP-ST.RPl-0001 (0) i PIT 2YR i 100298 i 11SW22 11 SVCE WTR NUCLEAR HEADER MTR OPR BTFL VLV 205242-3 SeNice Water Nuclear Area G5 3 B BFY MO 24 0 0 Passive

- - -- -- -- -- -- -------------- -- -- -- ---- -. -- - - ------------ -- - - - -. - - . - - - -- -------- -- ~ - - - - - --- - ---

S1 .OP-ST.RPl-0004(0) i PIT 2YR 100302

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 11 Page 93 VALVE NO VALVE DESCRIPTION P + JD No p + JD Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TESTFREa.! C.S. JUST. : R.O. JUST. j REL. REQ. j RECUR. TASK. iTECH. pos.! COMMENTS 12SW22 12 SVCE WTR NUCLEAR HEADER MTR OPRD BTFL ISLN VLV 205242-3 Service Water Nuclear Area G5 3 B BFY MO 24 0 0 Passive 81 .OP-ST.RPl-0004(0) i PIT 2YR 100302 11SW23 11 SVCE WTR NUCLEAR HEADER INTER-TIE MTR OPRD BTFL VLV 205242-3 Service Water Nuclear Area F5 3 B BFY MO 24 c c Active 81 .OP-ST.RPl-0004(0)  ! PIT 2YR  : 100302  :

81 .OP-ST.SW-0007(0) i STC Q 100725 12SW23 12 SVCE WTR NUCLEAR HEADER INTER-TIE MTR OPRD BTFL VLV 205242-3 Service Water Nuclear Area F6 3 B BFY MO 24 c c Active 81 .OP-ST.RPl-0004(0) i PIT 2YR 100302 81 .OP-ST.SW-0007(0) i STC a 100725 1SW26 1 SVCE WTR DISCH HEADER TO TURB AREA MTR OPRD BTFL VLV 205242-1 Service Water Nuclear Area CB 3 B BFY MO 30 0 c Active 81 .OP-ST.RPl-0003(0) i PIT 2YR . 100301  ;

81 .OP-ST.SW-0011 (0)  ! STC CS ~ CS-43 100885 11SW34 11 SVCE WTR NUCLEAR HEADER TO DSL GEN JKT WTR CLR A CHK VLV 205242-3 Service Water Nuclear Area H7 3 C DCK SELF 6 c 0 Active

- ------- - - - - - ----- ---- - - -- -- - - . ----- ---- - -. -------- -- ---- - - - -: -------- - - - - - ----- ~ ------- -- -- -- - - - -- ---- - -- - - - -- - - - --- - ---- -- - - -- - - ----: ---- - ---------- - -- -- - - --- - -. ---------- - -- -: ---- -- -- -- - - -- -- -- -- - - -- - --- ------------ - - - - -- -- -- -- -- - - -- --

~ ~ ~

CTO a 100143 12SW34 12 SVCE WTR DSL GEN JKT WTR CLR 1A INLET CHK VLV 205242-3 Service Water Nuclear Area H7 3 c DCK SELF 6 c 0 Active S1 .OP-ST.DG-0001 (0)  ! CTO  ! O  !  ! 100143

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT *1 Page 94 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I ' l ' I '

TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK iTECH. POS.! COMMENTS 11SW36 11 SVCE WTR DSL GEN JKT WTR CLR B INLET CHK VLV 205242-3 Service Water Nuclear Area Gl 3 c DCK SELF 6 c 0 Active S1.0P-ST.DG-0002(0)  ! CTO 0 j 100144 j i 12SW36 12 SVCE WTR NUC HOR TO DSL GEN JKT WTR CLR 1B CHK VLV 205242-3 Service Water Nuclear Area Gl 3 c DCK SELF 6 c 0 Active S1 .OP-ST.DG-0002(0) CTO 0 100144 11SW38 11 SVCE WTR DSL GEN JKT WTR CLR 1C INLET CHK VLV 205242-3 Service Water Nuclear Area Fl 3 c DCK SELF 6 c 0 Active S1 .OP-ST.DG-0003(0) CTO 0  ! 100146 j 12SW38 12 SVCE WTR DSL GEN JKT WTR CLR 1C INLET CHK VLV 205242-3 Service Water Nuclear Area Fl 3 c DCK SELF 6 c 0 Active S1 .OP-ST.DG-0003(0) CTO 0 100146 11SW39 11 SVCE WTR DSL GEN JKT WTR CLR 1A INLET AIR OPRD BALL VLV 205242-3 Service Water Nuclear Area HB 3 B BALL AIR 6 c 0 Active S1 .OP-ST.DG-0001 (0) FSTO i 0 100143 S1 .OP-ST.DG-0001 (0) STO 0 100143 12SW39 12 SVCE WTR DSL GEN JKT WTR CLR 1B INLET AIR OPRD BALL VLV 205242-3 Service Water Nuclear Area GB 3 B BALL AIR 6 c 0 Active S1 .OP-ST.DG-0002(0) FSTO 0 100144 S1 .OP-ST.DG-0002(0) STO 0 100144

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 95 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I '

TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. i R.O. JUST. : REL. REQ. i RECUR. TASK !TECH. POS.: COMMENTS 13SW39 13 SVCE WTR DSL GEN JKT WTR CLR 1C INLET AIR OPRD BALL VLV 205242-3 Service Water Nuclear Area FB 3 B BALL AIR 6 c 0 Active

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.------------------.------------------:------------------;------------------;-----------------.-------------------------::------------------7------------------------------------------------------------*

S1 .OP-ST.DG-0003(0) FSTO  : 0 100146 S1 .OP-ST.DG-0003(0) STO 0 100146 11SW44 11 SVCE WTR DSL GEN LUBE OIL CLR 1A OUTLET CHK VLV 205242-3 Service Water Nuclear Area E9 3 c DCK SELF 6 c 0 Active S1.0P-ST.DG-0001(0) CTO 0 j  ! 100143 j 12SW44 12 SVCE WTR DSL GEN LUBE OIL CLR 1B OUTLET CHK VLV 205242-3 Service Water Nuclear Area D9 3 c DCK SELF 6 c 0 Active S1 .OP-ST.DG-0002(0) CTO 0 100144 13SW44 13 SVCE WTR DSL GEN LUBE OIL CLR 1C OUTLET CHK VLV 205242-3 Service Water Nuclear Area C9 3 c DCK SELF 6 c 0 Active S1.0P-ST.DG-0003(0)  ! CTO 0 j 100146  :

11SW47 11 SVCE WTR DSL GEN LUBE OIL CLR 1A OUTLET CHK VLV 205242-3 Service Water Nuclear Area E10 3 C DCK SELF 8 c 0 Active SC.MD-PM.ZZ-0123(0) j CTO  ! RF  ! V-31 204114 TP-6 S1 .OP-ST.DG-0001 (0) PS 0 V-31 100143 12SW47 12 SVCE WTR DSL GEN LUBE OIL CLR 1A OUTLET CHK VLV 205242-3 Service Water Nuclear Area D10 3 c DCK SELF 8 c 0 Active SC.MD-PM.ZZ-0123(0) CTO RF V-31 204115 TP-6 S1 .OP-ST.DG-0001 (0) PS 0 V-31 100143

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 96 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ) C.S. JUST. : R.O. JUST. : REL. REQ.: RECUR. TASK !TECH. pos.i COMMENTS 11SW51 11 SVCE WTR NUC HOR TO CONT FAN COIL UNIT INLET HOR CHK VLV 205242-6 Service Water Nuclear Area H1 3 C DCK SELF 16 O O/C Active SC.MD-PM.ZZ-0123(0)  ! CTC RF ' V-38 ' 202870 TP-6 S1.OP-ST.SW-0010(0) i CTO 0 101213 12SW51 12 SVCE WTR CHL COND INLET HOR TO CONT FAN COIL UNIT HOR CKVL 205242-5 Service Water Nuclear Area G3 3 C DCK SELF 16 0 O/C Active SC.MD-PM.ZZ-0123(0)  ! CTC RF V-38 202869 TP-6 81.0P-ST.SW-0010(0)  ! CTO 0 101213 11SW53 11 SVCE WTR FAN COIL UNITS COMMON INLET HDRCHK VLV 205242-6 Service Water Nuclear Area E1 3 C DCK SELF 10 0 O/C Active SC.RA-IS.ZZ-0007(0) CTC 0 ' 290305 '

81.0P-ST.SW-0010(0) i CTO 0 101213 125W53 12 SVCE WTR FAN COIL UNITS COMMON INLET HOR CHK VLV 205242-6 Service Water Nuclear Area D1 3 c DCK SELF 10 0 O/C Active

---

.------------------.------------------=-------------------;-------------------=------------------.-------------------------;------------------ ------------------------------------------------------------

SC.RA-IS.ZZ-0007(0) CTC 0 290306 S1.OP-ST.SW-0010(0)  ! CTO 0 101213 11SW57 11 SVCE WTR CONT FAN COIL UNIT INLET AIR OPRD GLB VLV 205242-6 Service Water Nuclear Area H2 3 B GB AIR 8 M 0 Active S1 .OP-ST.SW-0010(0) FSTO 0 101213 S1 .OP-ST.SW-001 O(Q) STO 0 101213

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 97 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I o I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK iTECH. POS.! COMMENTS 12SW57 12 SVCE WTR CONT FAN COIL UNIT INLET AIR OPRD GLB VLV 205242-6 Service Water Nuclear Area F2 3 B GB AIR 8 M 0 Active 51.0P-ST.SW-0010(0) ! FSTO : 0 101213 S1.OP-ST.SW-0010(0) ! STO 0 101213 13SW57 13 SVCE WTR CONT FAN COIL UNIT INLET AIR OPRD GLB VLV 205242-6 Service Water Nuclear Area E2 3 B GB AIR 8 M 0 Active S1.OP-ST.SW-0010(0) i FSTO  : 0 101213 S1.OP-ST.SW-0010(0)  ! STO 0 101213 14SW57 14 SVCE WTR CONT FAN COIL UNIT INLET AIR OPRD GLB VLV 205242-6 Service Water Nuclear Area C2 3 B GB AIR 8 M 0 Active S1.OP-ST.SW-0010(0) : FSTO : 0 101213 S1 .OP-ST.SW-0010(0) ! STO 0 101213 15SW57 15 SVCE WTR CONT FAN COIL UNIT INLET AIR OPRD GLB VLV 205242-6 Service Water Nuclear Area B2 3 B GB AIR 8 M 0 Active S1 .OP-ST.SW-001 O(Q) ! FSTO : 0 101213 S1.OP-ST.SW-0010(0)  ! STO 0 101213 11SW58 11 SVCE WTR CONT FAN COIL UNIT INLET AIR OPRD BTFL VLV 205242-6 Service Water Nuclear Area H3 2 B BFY AIR 10 0 O/C Active S1.OP-ST.SW-0010(0) FSTC Q 101213 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1.OP-ST.SW-0010(0) STC 0 101213

• TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 98 VALVE NO VALVE DESCRIPTION P+ ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

- --- - -- -- - - -- - - - -- --------- -- -- -- - - - - - - - - - - - - - -- - -- -- -------- ---------------- --- --- ---- ----- --- ---- - - -- - - - - -- - - - - - - -- - - - - - - - - -- - - - -- -- - ------------- ------------------------------------ ---------- --- -- - - - - - -- -- - -- - -- -- . - - - -- - ~ -- -- - --- ---- --

TEST PROC !TEST TYPE !TEST FREQ) C.S. JUST. ! R.O. JUST.! REL. REQ. ! RECUR. TASK !TECH. POs.! COMMENTS 12SW58 12 SVCE WTR CONT FAN COIL UNIT INLET AIR OPRD BTFL VLV 205242-6 Service Water Nuclear Area F3 2 B BFY AIR 10 O OIC Active 51.OP-5T.5W-0010(0) F5TC o 101213 51 .OP-5T.RPl-0004(0)  ! PIT 2YR 100302 51.OP-5T.5W-0010(0)  ! STC o 101213 13SW58 13 SVCE WTR CONT FAN COIL UNIT INLET AIR OPRD BTFL VLV 205242-6 Service Water Nuclear Area E3 ,2 B BFY AIR 10 D DIC Active 51.0P-5T.SW-0010(0) FSTC o 101213 S1 .OP-ST.RPl-0004(0)  ! PIT 2YR 100302 51.0P-ST.5W-0010(0)  ! 5TC o 101213

.~~-'-~~~-'-~~~-'-~~~----'-~~~-'-~~~~~~~~~'--~~~~~~~~~~~~

14SW58 14 SVCE WTR CONT FAN COIL UNIT INLET AIR OPRD BTFL VLV 205242-6 Service Water Nuclear Area C3 2 B BFY AIR 10 0 O/C Active 51 .OP-5T.5W-0010(0) F5TC o 101213 51 .OP-ST.RPl-0004(0) i PIT 2YR 100302 51.OP-5T.SW-0010(0) i 5TC o 101213 15SW58 15 SVCE WTR CONT FAN COIL UNIT INLET AIR OPRD BTFL VLV 205242-6 Service Water Nuclear Area 83 2 B BFY AIR 10 0 DIC Active S1.OP-5T.SW-0010(0) FSTC o 101213 51 .OP-ST.RPl-0004(0)  ! PIT 2YR 100302 51 .OP-5T.5W-0010(0)  ! 5TC o 101213 11SW65 11 SVCE WTR CONT FAN COIL UNIT OUTLET AIR OPRD BTFL VLV 205242-6 Service Water Nuclear Area H7 3 B BFY AIR 10 M 0 Active S1.OP-ST.5W-0010(0) FSTO o 101213 S1 .OP-ST.SW-001 O(Q) 5TO o 101213

• TABLE 3 VALVE TEST TABLE 1011197 SALEM NUCLEAR PLANT - UNIT 1 Page 99 VALVE NO VALVE DESCRIPTION P+ ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST.! REL. REQ. ! RECUR. TASK !TECH. pos.! COMMENTS 12SW65 12 SVCE WTR CONT FAN COIL UNIT OUTLET AIR OPRD BTFL VLV 205242-6 Service Water Nuclear Area Fl 3 B BFY AIR 10 M 0 Active

--5-1:0P~ST.SW~oofr>"(Ci)---**!-****FSTO ____:________Q________________________________________________________________.------**1a121*i****** ----------------- ---------------------------------------*-**-*-*************

S1 .OP-ST.SW-0010(0)  ! STO Q 101213 13SW65 13 SVCE WTR CONT FAN COIL UNIT OUTLET AIR OPRD BTFLVLV 205242-6 Service Water Nuclear Area El 3 B BFY AIR 10 M 0 Active S1.0P-ST.SW-0010(Q) ! FSTO ; Q 101213 S1 .OP-ST.SW-001 O(Q) \ STO Q 101213 14SW65 14 SVCE WTR CONT FAN COIL UNIT OUTLET AIR OPRD BTFL VLV 205242-6 Service Water Nuclear Area Cl 3 B BFY AIR 10 M 0 Active s1 .0F>~si.sw~oo1-1ica> ___ T___i=s:r0*-*-:------*-a**--------------------------------------------,-------------------------1a1*21-3**----- ----------------- ------------------------------------------------------------

s1.oP-sT.sw-001oca> i sTo a 101213 15SW65 15 SVCE WTR CONT FAN COIL UNIT OUTLET AIR OPRD BTFL VLV 205242-6 Service Water Nuclear Area Bl 3 B BFY AIR 10 M 0 Active S1 .OP-ST.SW-001 O(Q) ! FSTO : Q '

' 101213 S1 .OP-ST.SW-001 O(Q) ! STO Q 101213 11SW72 11 SVCE WTR CONT FAN COIL UNIT OUTLET AIR OPRD BTFL VLV 205242-6 Service Water Nuclear Area Hl 2 B BFY AIR 10 0 O/C Active S1 .OP-ST.SW-001 O(Q) FSTC Q 101213 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.SW-001 O(Q) STC Q 101213

fABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 100 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing' ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREa) C.S. JUST. : R.O. JUST. ! REL. REQ.: RECUR. TASK !TECH. POs.! COMMENTS 12SW72 12 SVCE WTR CONT FAN COIL UNIT OUTLET AIR OPRD BTFLVLV 205242-6 Service Water Nuclear Area F7 2 8 BFY AIR 10 0 O/C Active S1 .OP-ST.SW-0010(0) FSTC o 101213 S1 .OP-ST.RPl-0004(0) i PIT 2YR 100302 S1.OP-ST.SW-0010(0) i STC o 101213 13SW72 13 SVCE WTR CONT FAN COIL UNIT OUTLET AIR OPRD BTFL VLV 205242-6 Service Water Nuclear Area E7 2 B BFY AIR 10 0 O/C Active S1.OP-ST.SW-0010(0) FSTC o 101213 S1 .OP-ST.RPl-0004(0) i PIT 2YR 100302 51.0P-ST.SW-0010(0) ! STC o 101213 14SW72 14 SVCE WTR CONT FAN COIL UNIT OUTLET AIR OPRD BTFL VLV 205242-6 Service Water Nuclear Area C7 2 8 BFY AIR 10 0 DIC Active S1.OP-ST.SW-0010(0) FSTC o 101213 S1 .OP-ST.RPl-0004(0) i PIT 2YR 100302 S1.OP-ST.SW-0010(0)  ! STC o 101213 15SW72 15 SVCE WTR CONT FAN COIL UNIT OUTLET AIR OPRD BTFL VLV 205242-6 Service Water Nuclear Area 87 2 8 BFY AIR 10 0 O/C Active S1.OP-ST.SW-0010(0) FSTC o 101213 S1 .OP-ST.RPl-0004(0) i PIT 2YR 100302 S1 .OP-ST.SW-0010(0) i STC o 101213 11SW77 11 SVCE WTR FAN COIL UNITS COMMON OUTLET HOR CHK VLV 205242-6 Service Water Nuclear Area E9 3 C DCK SELF 10 0 0 Active S1.OP-ST.SW-0010(0) CTO o 101213

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 101 VALVE NO VALVE DESCRIPTION P + ID No p + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC [TEST TYPE [TEST FREQ) C.S. JUST. [ R.O. JUST. [ REL. REQ. [ RECUR. TASK [TECH. POs.[ COMMENTS 12SW77 12 SVCE WTR FAN COIL UNITS COMMON OUTLET HOR CHK VLV 205242-6 Service Water Nuclear Area D9 3 c DCK SELF 10 0 0 Active

---

.------------------;------------------;------------------;-------------------;-----------------.-------------------------;-----------------7------------------------------------------------------------*

CTO Q 101213 11SW79 11 SVCE WTR COND CIRC WTR DISCH HOR CHK VLV 205242-3 Service Water Nuclear Area C11 3 c DCK SELF 24 0 0 Active SC.MD-PM.ZZ-0123Q) CTO RF V-36 203460 S1 .OP-ST.SW-0009(Q) i PS Q V-36 101020 12SW79 12 SVCE WTR COND CIRC WTR DISC HOR CHK VLV 205242-3 Service Water Nuclear Area C11 3 c DCK SELF 24 0 0 Active SC.MD-PM.ZZ-0123Q) CTO RF V-36 203461 S1 .OP-ST.SW-0009(Q) i PS Q V-36 101020 11SW92 11 SVCE WTR CHL COND INLET AIR OPRD GLB VLV 205242-5 Service Water Nuclear Area F4 3 B GB AIR 4 c 0 Active S1 .OP-ST.SW-0009(Q) j FSTO i Q 101020 S1 .OP-ST.SW-0009(Q) ! STO Q 101020 12SW92 12 SVCE WTR CHL COND INLET AIR OPRD GLB VLV 205242-5 Service Water Nuclear Area D4 3 B GB AIR 4 c 0 Active S1 .OP-ST.SW-0009(Q)  ! FSTO i Q 101020 S1 .OP-ST.SW-0009(Q) i STO Q 101020 13SW92 13 SVCE WTR CHILLER CONDENSER INLET AIR OPRD GLB VLV 205242-5 Service Water Nuclear Area C4 3 B GB AIR 4 c 0 Active S1 .OP-ST.SW-0009(0) FSTO 0 101020 S1 .OP-ST.SW-0009(0) STO 0 101020

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 102 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.: C.S. JUST. j R.O. JUST. j REL. REQ. j RECUR. TASK !TECH. POs.! COMMENTS 11SW99 11 SVCE WTR CHL COND RECIRC PMP DISCH CHK VLV 205242-5 Service Water Nuclear Area E6 3 C CK SELF 4 OIC C Active S1 .OP-ST.SW-0009(0)  ! CTC 0 101020 12SW99 12 SVCE WTR CHL COND RECIRC PMP DISCH CHK VLV 205242-5 Service Water Nuclear Area D6 3 c CK SELF 4 O/C c Active CTC 0 101020 13SW99 13 SVCE WTR CHL COND RECIRC PMP DISCH CKVL 205242-5 Service Water Nuclear Area BB 3 c CK SELF 4 O/C c Active

-- - - -- -- - - -- -- -- -- ;- - - -- -- - - - - - - - - - -. -- - - - - -- - - -- -- - - -- -------; - ----- -----------~ ------------------------- -- - - -- --- -- --- - -- -- - - -- -- - -- -------

S1 .OP-ST.SW-0009(0) ! CTC 0 101020 11SW122 11 SVCE WTR CMPNT CLG HT EXCHG INLET AIR OPRD BTFL VLV 205242-3 Service Water Nuclear Area B3 3 B BFY AIR 20 M O/C Active

~ - - - - -- -- -- -- - -- - - -- - -- -- -- ------ ---- -------- - - -- -- - - -- -- - - - - .

S1 .OP-ST.SW-0008(0) FSTC 0 101019 S1 .OP-ST.SW-0008(0) ! STC 0 101019 S1 .OP-ST.SW-0008(0) ! STO 0 101019 11SW129 11 SVCE WTR CMPNT CLG PMP RM CLR INLET AIR OPRD GLB VLV 205242-3 Service Water Nuclear Area C4 3 B GB AIR 1.5 O/C 0 Active S1 .OP-ST.~W-0014(0)  ! FSTO  : 0 100303 S1 .OP-ST.SW-0014(0)  : STO 0 100303 12SW129 12 SVCE WTR CMPNT CLG PMP RM CLR INLET AIR OPRD GLB VLV 205242-4 Service Water Nuclear Area G6 3 B GB AIR 2 O/C 0 Active S1 .OP-ST.SW-0014(0) FSTO 0 100303 S1 .OP-ST.SW-0014(0) STO 0 100303

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 103 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification 1 I I 1 I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL, REQ. ! RECUR. TASK ! TECH. POS.! COMMENTS 1SW137 1 SVCE WTR AUX FDWTR PMP RM CLR INLET AIR OPRD GLB VLV 205242-3 Service Water Nuclear Area C4 3 B GB AIR 2 O/C 0 Active S1 .OP-ST.SW-0014(0)  ! FSTO  : 0 100303 S1 .OP-ST.SW-0014(0)  ! STO 0 100303 11SW145 11 SVCE WTR CONT SPRAY PMP RM CLR INLET AIR OPRD GLB VLV 205242-3 Service Water Nuclear Area 03 3 B GB AIR 1.5 O/C 0 Active S1 .OP-ST.SW-0014(0)  ! FSTO  : 0 '

' 100303 S1.0P-ST.SW-0014(Q)  ! STO 0 100303 12SW145 12 SVCE WTR CONT SPRAY PMP RM CLR INLET AIR OPRD GLB VLV 20524Q-4 Service Water Nuclear Area Bl 3 B GB AIR 1.5 O/C 0 Active S1 .OP-ST.SW-0014(0)  ! FSTO  : 0 100303 S1 .OP-ST.SW-0014(0) j STO 0 100303 11SW153 11 SVCE WTR RHR PMP RM CLR INLET AIR OPRD GLB VLV 205242-3 Service Water Nuclear Area G4 3 B GB AIR 1.5 O/C 0 Active S1 .OP-ST.SW-0014(0)  ! FSTO  : 0 100303 S1 .OP-ST.SW-0014(0)  ! STO 0 100303 12SW153 12 SVCE WTR RHR PMP RM CLR INLET AIR OPRD GLB VLV 205242-4 Service Water Nuclear Area F6 3 B GB AIR 1.5 O/C 0 Active 81 .OP-ST.SW-0014(0)  : FSTO 0 100303 S1 .OP-ST.SW-0014(0)  ! STO 0 100303 11SW161 11 SERVICE WATER COOLER HEADER TO AUX FEEDWATER STOP BUTTERFLY VALVE 205242-3 Service Water Nuclear Area C4 3 B BFY MAN 8 c O/C Active S1 .OP-ST.AF-0004(0) FSO 0 100717

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 104 VALVE NO VALVE DESCRIPTION P+ ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ) C.S. JUST. ! R.O. JUST.! REL. REQ. ! RECUR. TASK !TECH. POS.! COMMENTS 12SW161 11 SERVICE WATER COOLER HEADER TO AUX FEEDWATER STOP BUTTERFLY VALVE 205242-4 Service Water Nuclear Area G10 3 B BFY MAN 8 C O/C Active 51 .OP-5T.AF-0004(0) F50 0 100717 1SW163 1 SVCE WTR SAFTY INJ PMP LUBE OIL CLR INLET AIR OPRD GLB VLV 205242-3 Service Water Nuclear Area G4 3 B GB AIR 1.5 c 0 Active 51.0P-5T.5J-0002(0) F5TO : 0 100710 51 .OP-5T.5J-0002(0) 5TO 0 100710 1SW169 1 SVCE WTR SAF INJ PMP LUBE OIL CLR NO 11 INLET AIR OPRD GLB VLV 205242-4 Service Water Nuclear Area Cl 3 B GB AIR 1.5 c 0 Active 51 .OP-5T.5J-0001 (0) F5TO  : 0 100709 51 .OP-5T.5J-0001 (0) 5TO 0 100709 1SW175 1 SVCE WTR SAF INJ PMP RM CLR INLET AIR OPRD GLB VLV 205242-4 Service Water Nuclear Area Cl 3 B GB AIR 2 c 0 Active 51.0P-5T.5W-0014(0)  ! F5TO  ! 0 100303 51.0P-5T.5W-0014(0)  ! 5TO 0 100303 1SW185 1 SVCE WTR CHG PMP CLR NO 11 INLET AIR OPRD GLB VLV 205242-4 Service Water Nuclear Area Dl 3 B GB AIR 1.5 c 0 Active 51 .OP-5T.CVC-0003(0) ! F5TO  : 0 100702 51 .OP-5T.CVC-0003(0) \ 5TO 0 100702 1SW191 1 SVCE WTR CHG PMP RM CLR INLET AIR OPRD GLB VLV 205242-4 Service Water Nuclear Area Dl 3 B GB AIR 2 O/C 0 Active 51 .OP-5T.5W-0014(0) F5TO 0 100303 S1 .OP-5T.SW-0014(0) 5TO 0 100303

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 105 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I ' I I I TEST PROC iTEST TYPE iTEST FREQ.j C.S. JUST. j R.O. JUST. j REL. REQ. j RECUR. TASK iTECH. POS.j COMMENTS 1SW199 1 SVCE WTR CHARGING PMP NO 12 CLR INLET AIR OPRD GLB VLV 205242-3 Service Water Nuclear Area E4 3 B GB AIR 1.5 C O Active

'

'  ;'  ;' ~

S1 .OP-ST.CVC-0004(0 i FSTO i 0

' 100703 S1 .OP-ST.CVC-0004(0 i STO 0 100703 1SW205 1 SVCE WTR CHG PMP RM CLR NO 12 INLET AIR OPRD GLB VLV 205242-3 Service Water Nuclear Area E4 3 B GB AIR 2 O/C 0 Active

---

;------------------.------------------;-------------------;-------------------;------------------.------------------------- -----------------7------------------------------------------------------------*

S1 .OP-ST.SW-0014(0) j FSTO : 0 100303 51 .OP-ST.SW-0014(0) j STO 0 100303 1SW213 1 SVCE WTR CHG PMP RM CLR NO 13 INLET AIR OPRD GLB VLV 205242-4 Service Water Nuclear Area Bl 3 B GB AIR 1.5 O/C 0 Active

---

.------------------.------------------:-------------------:-------------------;------------------.------------------------- -----------------7------------------------------------------------------------*

S1 .OP-ST.SW-0014(0) i FSTO : 0 100303 S1 .OP-ST.SW-0014(0) i STO 0 100303 11SW223 11 SVCE WTR CONT FAN COIL UNIT OUTLET AIR OPRD GLB VLV 205242-6 Service Water Nuclear Area H9 3 B GB AIR 8 O/C O/C Active S1.OP-ST.SW-0010(0) FSTO 0 101213 S1.OP-ST.SW-0010(0)  ! STC 0 101213 S1.OP-ST.SW-0010(0) j STO 0 101213 12SW223 12 SVCE WTR CONT FAN COIL UNIT OUTLET AIR OPR GLB VLV 205242-6 '* 'Service Water Nuclear Area F9 3 B GB AIR 8 O/C O/C Active S1 .OP-ST.SW-0010(0) FSTO 0 101213 S1.OP-ST.SW-0010(0) STC 0 101213 S1 .OP-ST.SW-0010(0) STO 0 101213

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 106 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC . !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. : REL. REQ. ! RECUR. TASK !TECH. pos.! COMMENTS 13SW223 13 SVCE WTR CONT FAN COIL UNIT OUTLET AIR OPRD GLB VLV 205242-6 Service Water Nuclear Area E9 3 B GB AIR 8 O/C O/C Active

; ~

S1 .OP-ST.SW-0010(0) FSTO 0 101213 S1 .OP-ST.SW-0010(0) STC 0 101213 S1 .OP-ST.SW-0010(0) STO 0 101213 14SW223 14 SVCE WTR CONT FAN COIL UNIT OUTLET AIR OPRD GLB VLV 205242-6 Service Water Nuclear Area C9 3 B GB AIR 8 O/C OIC Active S1 .OP-ST.SW-0010(0) FSTO 0 101213 S1 .OP-ST.SW-0010(0) STC 0 101213 S1.OP-ST.SW-0010(0) STO 0 101213 15SW223 15 SVCE WTR CONT FAN COIL UNIT OUTLET AIR OPRD GLB VLV 205242-6 Service Water Nuclear Area B9 3 B GB AIR 8 O/C O/C Active S1 .OP-ST.SW-0010(0) FSTO 0 101213 S1 .OP-ST.SW-0010(0) STC 0 101213 S1 .OP-ST.SW-0010(0) STO 0 101213 1SW308 1 SVCE WTR RIVER DISCH OUTLET AIR OPRD BALL VLV 205242-1 Service Water Nuclear Area A6 3 B BALL AIR 8 c c Passive No inservice testing required for this component.

1SW311 1 SVCE WTR RIVER DISCH AIR OPR BALL VLV 205242-2 Service Water Nuclear Area H4 3 B BALL AIR 8 c c Passive No inservice testing required for this component.

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 107 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ) C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK :TECH. POs.: COMMENTS 12SW376 12 SVCE WTR CMPNT CLG PL HT EXCH B INLET STOP AIR OPRD BTFL VLV 205242-4 Service Water Nuclear Area H6 3 B BFY AIR 14 D DIC Active 81 .OP-8T.8W-0008(0) F8TC o 101019 81 .OP-8T.RPl-0001(0) PIT 2YR 100298 81 .OP-8T.8W-0008(0) 8TC o 101019 81 .OP-8T.8W-0008(0) 8TO o 101019 12SW380 12 SVCE WTR CMPNT CLG PL HT EXCH A INLET STOP AIR OPRD BTFL VLV 205242-4 Service Water Nuclear Area H4 3 B BFY AIR 14 D DIC Active 81 .OP-8T.8W-0008(0) F8TC o 101019 81 .OP-8T.RPl-0001 (0) PIT 2YR 100298 81 .OP-8T.8W-0008(0) 8TC o 101019 81 .OP-8T.8W-0008(0) 8TO o 101019 11SW532 11 SVCE WTR CONTAINMENT FAN COIL UNIT NUCLEAR HOR INLET CHECK VLV 205242-6 Service Water Nuclear Area H1 3 c DCK SELF 16 D DIC Active

~ ~ - - - - - -- -- -- -- -- - . -

8C.MD-PM.ZZ-0123(0) : CTC  : RF  :  :  : V-38 (later) TP-6 DCP 1 EC-3668, Rec. Task (RT) prior to restart.

81 .OP-8T.8W-0010(0) j CTO 0 101213 12SW532 12 SVCE WTR NUCLEAR HOR TO REACTOR CONTAINMENT CHECK VLV 205242-5 Service Water Nuclear Area G3 3 c DCK SELF 16 D DIC Active 8C.MD-PM.ZZ-0123(0) CTC RF V-38 * (later) TP-6 DCP 1 EC-3668, Rec. Task (RT) prior to restart.

81.OP-8T.8W-0010(0) CTO o 101213

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 108 VALVE NO VALVE DESCRIPTION P +ID No P +JD Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ) C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK ! TECH. POS.i COMMENTS 11SW534 11 SERVICE WATER ACCUMULATOR VESSEL DISCHARGE ISOLATION VLV 205242-7 Service Water Nuclear Area F9 3 B 8FY AIR 10 C O/C Active

~ - - -- -- -- - - -- -- - - - - -- - -- -- -- - - - - -- . - -- -- -- - - -- - - - - -- -- - - - - - - -- -- -- -

81.OP-8T.8W-0010(0) F8TO 0 101213 81.OP-8T.8W-0010(0) i 8TC 0 101213 81.OP-ST.8W-0010(0) i 8TO 0 101213 12SW534 12 SERVICE WATER ACCUMULATOR VESSEL DISCHARGE ISOLATION VLV 205242-7 Service Water Nuclear Area 89 3 B 8FY AIR 10 c O/C Active 81.OP-8T.SW-0010(0) F8TO 0  ! i 101213 81 .OP-8T.8W-0010(0) ! 8TC 0 101213 81 .OP-ST.SW-0010(0) i STO 0 101213 11SW535 11 SERVICE WATER ACCUMULATOR VESSEL DISCHARGE ISOLATION VLV 205242-7 Service Water Nuclear Area F9 3 B 8FY AIR 10 c O/C Active 81.OP-ST,SW-0010(0) FSTO 0 101213 S1.OP-ST.SW-0010(0) : STC 0 101213 S1.OP-ST.SW-0010(0) ! STO 0 101213 12SW535 12 SERVICE WATER ACCUMULATOR VESSEL DISCHARGE ISOLATION VLV 205242-7 Service Water Nuclear Area 89 3 B 8FY AIR 10 c O/C Active S1 .OP-8T.SW-0010(0) i FSTO i 0 101213 S1.OP-ST.SW-0010(0) ~ 8TC 0 101213 81.OP-ST.8W-0010(0) ~ STO 0 101213 11SW536 11 NUCLEAR SUPPLY HEADER COLUMN SEPARATION PROTECTION CHECK VLV 205242-7 Service Water Nuclear Area FB 3 c DCK SELF 10 c O/C Active 81.OP-ST.SW-0010(0) CTC 0 101213 SC.MD-PM.ZZ-0123(0) CTO RF V-39 (later) DCP 1EC-3668, Rec. Task (RT) prior to restart.

TABLE 3-1 -VALVE TEST TABLE 1011197 SALEM NUCLEAR PLANT - UNIT 1 Page 109

-=~-==..::..;:-=-: ------ - - - - - - - - - - - - - - - - - - - - - - - - - --= *--'

VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC :TEST TYPE !TEST FREQ.! C.S. JUST. i R.O. JUST. : REL. REQ. i RECUR. TASK iTECH. POS.! COMMENTS 12SW536 12 NUCLEAR SUPPLY HEADER COLUMN SEPARATION PROTECTION CHECK VLV 20S242-7 Service Water Nuclear Area CB 3 C DCK SELF 10 C O/C Active S1 .OP-ST.SW-0010(0) CTC 0 ' 101213 '

SC.MD-PM.ZZ-0123(0) i CTO RF V-39 (later) DCP 1 EC-3668, Rec. Task (RT) prior to restart.

11SW596 11 SERVICE WATER ACCUMULATOR VESSEL WATER FILL CHECK VLV 20S242-7 Service Water Nuclear Area GS 3 C CK SELF 1 c c Active S1.OP-ST.SW-0010(0) CTC 0 101213 12SW596 12 SERVICE WATER ACCUMULATOR VESSEL WATER FILL CHECK VLV 20S242-7 Service Water Nuclear Area cs 3 c CK SELF 1 c c Active S1.OP-ST.SW-0010(0) CTC 0 101213 11SW597 11 SERVICE WATER ACCUMULATOR VESSEL WATER FILL CHECK VLV 20S242-7 Service Water Nuclear Area GS 3 c CK SELF 1 c c Active S1.OP-ST.SW-0010(0) CTC 0 101213 12SW597 12 SERVICE WATER ACCUMULATOR VESSEL WATER FILL CHECK VLV 20S242-7 Service Water Nuclear Area cs 3 c CK SELF 1 c c Active S1.OP-ST.SW-0010(0) CTC 0 10'1213 1SW626 11 SVCE WTR ACCUMULATOR VESSEL RELIEF VALVE 20S242-7 Service Water H2 3 c RV SELF 1 c 0 Active SC.MD-PT.ZZ-0007(0) RV 5YR (later) DCP 1 EC-3668, see PMCR 970601180 1SW628 12 SVCE WTR ACCUMULATOR VESSEL RELIEF VALVE 20S242-7 Service Water D2 3 c RV SELF 1 c 0 Active SC.MD-PT.ZZ-0007(0) RV 5YR (later) DCP 1 EC-3668, see PMCR 970528086

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 110 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.: c.s, JUST. ! R.O. JUST.: REL. REQ. ! RECUR. TASK !TECH. pas.! COMMENTS 11SW640 11 SERVICE WATER ACCUMULATOR VESSEL NITROGEN FILL CHECK VLV 205242-7 Service Water Nuclear Area H4 3 C CK SELF 1 C C Active S1.OP-ST.SW-0010(0) ! CTC o 101213 12SW640 12 SERVICE WATER ACCUMULATOR VESSEL NITROGEN FILL CHECK VLV 205242-7 Service Water Nuclear Area D4 3 c CK SELF 1 c c Active S1.OP-ST.SW-0010(0) ! CTC o

' 101213 11SW641 11 SERVICE WATER ACCUMULATOR VESSEL NITROGEN FILL CHECK VLV 205242-7 Service Water Nuclear Area H4 3 C CK SELF 1 c c Active S1.0P-ST.SW-0010(0) ! CTC 0  ! 101213  !

12SW641 12 SERVICE WATER ACCUMULATOR VESSEL NITROGEN FILL CHECK VLV 205242-7 Service Water Nuclear Area D4 3 C CK SELF 1 C C Active S1.0P-ST.SW-0010(0) ! CTC o 101213 1VC1 1 CONTMT VENT PURGE SUPPLY OUTBOARD AIR OPRD VLV 205238-2 Reactor Containment - Ventilation C5 2 A BFY AIR 36 O/C c Active S1 .OP-ST.CBV-0002(0) FSTC cs CS-48 100842 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290577 S1 .OP-ST.RPl-0003(0) PIT 2YR 100301 S1 .OP-ST.CBV-0002(0) STC cs CS-48 100842

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 111 VALVE NO VALVE DESCRIPTION P + ID No P + ID Name Drawing ASME IS.T Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position . Position Classification TEST PROC [TEST TYPE [TEST FREQ.: C.S. JUST. : R.O. JUST. : REL. REQ.  ! RECUR. TASK : TECH. POS.: COMMENTS 1VC2 1 CONTMT VENT PURGE SUPPLY INBOARD AIR OPRD VLV 205238-2 Reactor Containment - Ventilation C3 2 A BFY AIR 36 O/C c Active S1 .OP-ST.CBV-0002(0) FSTC cs CS-49 100842 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290578 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.CBV-0002(0) STC cs CS-49 100842 1VC3 1 CONTMT VENT PURGE EXHAUST INBOARD AIR OPRD VLV 205238-2 Reactor Containment - Ventilation E3 2 A BFY AIR 36 c c Active S1 .OP-ST.CBV-0002(0) ' FSTC CS ' CS-49 100842 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290579 S1 .OP-ST.RPl-0002(0) PIT 2YR  :

• 100299 S1 .OP-ST.CBV-0002(0) STC CS CS-49 100842 1VC4 1 CONTMT VENT PURGE EXHAUST OUTBOARD AIR OPRD VLV 205238-2 Reactor Containment - Ventilation D5 2 A BFY AIR 36 c c Active S1 .OP-ST.CBV-0002(0) FSTC CS CS-48 100842 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290580 S1 .OP-ST.RPl-0003(0) PIT , . 2YR 100301 S1 .OP-ST.CBV-0002(0) STC CS CS-48 100842 1VCS 1 CONTMT VENT PRESS-VACUUM RELIEF OUTBOARD AIR OPRD VLV 205238-2 Reactor Containment - Ventilation C5 2 A BFY AIR 10 O/C c Active S1 .OP-ST.CBV-0001 (0) FSTC o 100755 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290581 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.CBV-0001 (0) STC o 100755

TABLE 3-1 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 112 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I I TEST PROC iTEST TYPE !TEST FREO.i C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK iTECH. POS.i COMMENTS 1VC6 1 CONTMT VENT PRESS-VACUUM RELIEF INBOARD AIR OPRD VLV 205238-2 Reactor Containment - Ventilation C3 2 A BFY AIR 10 O/C c Active 81 .OP-8T.CBV-0001 (0) F8TC 0 100755 81 .RA-18.ZZ-0001 (0) LJ 18MO 290582 81 .OP-8T.RPl-0002(0) PIT 2YR 100299 81 .OP-8T.CBV-0001 (0) 8TC 0 100755 1VC7 1 CONTMT VENT RAD MON SYS INSIDE CONTMT OUTLET SAMPLE INBOARD AIR OPRD VLV 205238-1 Reactor Containment - Ventilation H6 2 A GB AIR 1 0 c Active 81 .OP-8T.CBV-0001 (0) F8TC 0 100755 81 .RA-18.ZZ-0001 (0) LJ 18MO 290583 81 .OP-8T.RPl-0002(0) PIT 2YR 100299 81 .OP-8T.CBV-0001 (0) 8TC 0 100755 1VC8 1 CONTMT VENT RAD MON SYS OUT CONTMT OUTLET SAMPLE AIR OPRD VLV 205238-1 Reactor Containment - Ventilation HS 2 A GB AIR 1 0 c Active 81 .OP-8T.CBV-0001 (0) F8TC 0 100755 81 .RA-18.ZZ-0001 (0) LJ 18MO 290584 81 .OP-8T.RPl-0004(0) PIT 2YR 100302 81 .OP-8T.CBV-0001 (0) 8TC 0 100755 1VC9 1 CONTMT VENT RAD MON SYS INSIDE CONTMT OUTLET SAMPLE AIR OPRD VLV 205238-1 Reactor Containment - Ventilation H6 2 A GB AIR 1 c c Passive 81 .OP-8T.CBV-0001 (0) F8TC 0 100755 81 .RA-18.ZZ-0001 (Q) LJ 18MO 290585 81 .OP-8T.RPl-0002(0) PIT 2YR 100299 81 .OP-8T.CBV-0001 (0) 8TC 0 100755

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 113 VALVE NO VALVE DESCRIPTION P +ID /"{Q P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK ! TECH. POS.! COMMENTS 1VC10 1 CONTMT VENT RAD MON SYS OUT CONTMT OUTLET SAMPLE AIR OPRD VLV 205238-1 Reactor Containment- Ventilation HS 2 A GB AIR 1 C C Passive S1 .OP-ST.CBV-0001 (Q) FSTC Q 100755 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290586 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.CBV-0001 (Q) STC Q 100755 1VC11 1 CONTMT VENT RAD MON SYS INSIDE CONTMT INLET SAMPLE AIR OPRD VLV 205238-1 Reactor Containment - Ventilation G6 2 A GB AIR 1 0 c Active

~

S1 .OP-ST.CBV-0001 (Q) FSTC 0 100755 S1 .RA-IS.ZZ-0001 (Q) LJ 18MO 290587 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.CBV-0001 (Q) STC 0 100755 1VC12 1 CONTMT VENT RAD MON SYS OUTSIDE CONTMT INLET SAMPLE AR OPRD VLV 205238-1 Reactor Containment- Ventilation GS 2 A GB AIR 1 0 c Active S1 .OP-ST.CBV-0001 (0) FSTC Q 100755 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290588 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.CBV-0001 (Q) STC Q 100755 1VC13 1 CONTMT VENT RAD MON SYS INSIDE CONTMT INLET SAMPLE AIR OPRD VLV 205238-1 Reactor Containment - Ventilation F6 2 A GB AIR 1 c c Passive S1 .OP-ST.CBV-0001 (0) FSTC i 0 i 100755 S1 .RA-IS.ZZ-0001 (Q) LJ 18MO 290591 81.0P-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.CBV-0001 (0) STC Q -,: 100755

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 114 VALVE NO VALVE DESCRIPTION P + ID No P + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FR~a.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK !TECH. POs.! COMMENTS 1VC14 1 CONTMT VENT RAD MON SYS OUTSIDE CONTMT INLET SAMPLE AIR OPRD VLV 205238-1 Reactor Containment - Ventilation F5 2 A GB AIR 1 c c Passive S1 .OP-ST.CBV-0001 (Q) FSTC Q 100755 S1 .RA-IS.ZZ-0001 (Q) LJ 18MO 290592 S1 .OP-ST.RPl-0004(Q) PIT 2YR 100302 S1 .OP-ST.CBV-0001 (Q) STC Q 100755 11VC17 11 POST ACC SAMP PEN 36 OUTBD AIR SAMPLE SPLYAIR OPRD GATE VLV 205244-3 Sampling Gl 2 A GB AIR O.l5 c c Passive S1 .OP-ST.CBV-0001 (Q) FSTC Q 100755 S1 .RA-IS.ZZ-0001 (Q) LJ 18MO 290593 S1 .OP-ST.RPl-0004(Q) PIT 2YR 100302 S1 .OP-ST.CBV-0001 (Q) STC Q 100755 12VC17 12 POST ACC SAMP PEN 30 OUTBD AIR SAMPLE SPLY AIR OPRD GATE VLV 205244-3 Sampling El 2 A GB AIR . O.l5 c c Passive S1 .OP-ST.CBV-0001 (Q) FSTC Q 100755 S1 .RA-IS.ZZ-0001 (Q) LJ 18MO 290589 S1 .OP-ST.RPl-0004(Q) PIT 2YR 100302 S1 .OP-ST.CBV-0001 (Q) STC Q 100755 11VC18 11 POST ACC SAMP PEN 36 OUTBD AIR SAMPLE RETURN AIR OPRD GATE VLV 205244-3 Sampling Fl 2 A GB AIR 0.75 c c Passive S1 .OP-ST.CBV-0001 (Q) FSTC Q 100755 S1 .RA-IS.ZZ-0001 (Q) LJ 18MO 290595 S1 .OP-ST.RPl-0004(Q) PIT 2YR 100302 S1 .OP-ST.CBV-0001 (Q) STC Q 100755

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 115 VALVE NO VALVE DESCRIPTION P+IDNo P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. l R.O. JUST. l REL. REa. l RECUR. TASK lTECH. pos.l COMMENTS 12VC18 12 POST ACC SAMP PEN 30 OUTBD AIR SAMPLE RETURN AIR OPRD GATE VLV 205244-3 Sampling El 2 A GB AIR 0. 75 C C Passive S1 .OP-ST.CBV-0001 (0) FSTC 0 100755 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290597 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.CBV-0001 (0) STC 0 100755 11VC19 11 POST ACC SAMP PEN 36 INBD AIR SAMPLE SPLY AIR OPRD GATE VLV 205244-3 Sampling GB 2 A GB AIR 0.75 c c Passive

~ --- --------- -- ------- - -- -- -- -- -- - - -- -- - - -- -- - -- - ------ -- -----

51 .OP-ST.CBV-0001 (Q) FSTC Q  !  ! j 100755 S1 .RA-IS.ZZ-0001 (0) LJ 1BMO 290594 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.CBV-0001 (0) STC 0 100755 12VC19 12 POST ACC SAMP PEN 30 INBD AIR SAMPLE SPLY AIR OPRD GATE VLV 205244-3 Sampling EB 2 A GB AIR . 0. 75 C C Passive S1 .OP-ST.CBV-0001 (0) FSTC 0 100755 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290590 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.CBV-0001 (0) STC 0 100755 11VC20 11 POST ACC SAMP PEN 36 INBD AIR SAMPLE RETURN AIR OPRD GATE VLV 205244-3 Sampling FB 2 A GB AIR 0.75 c c Passive S1 .OP-ST.CBV-0001 (0) FSTC 0 100755 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290596 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.CBV-0001 (0) STC 0 100755

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 116 VALVE NO VALVE DESCRIPTION P + ID No P + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I TEST PROC [TEST TYPE [TEST FREQ) C.S. JUST. [ R.O. JUST. [ REL. REQ. [ RECUR. TASK [TECH. POS.[ COMMENTS 12VC20 12 POST ACC SAMP PEN 30 INBD AIR SAMPLE RETURN AIR OPRD GATE VLV 205244-3 Sampling EB 2 A GB AIR O.l5 c c Passive S1 .OP-ST.CBV-0001 (0) FSTC 0 100755 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290598 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.CBV-0001 (0) STC 0 100755 1WL12 1 RAD WST LQD REACT COOL DR PMP DISCH ISLN INBOARD AIR OPRD DIAPH VLV 205239-3 Waste Disposal Liquid Cl 2 A DIA AIR 3 c c Active S1 .OP-ST.ZZ-0003(0) FSTC 0 100726 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290599 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.ZZ-0003(0) STC 0 100726 1WL13 1 RAD WST LQD RC DR PMP DISCH ISLN AIR OPRD DIAPH VALVE 205239-3 Waste Disposal Liquid Cl 2 A DIA AIR 3 0 c Active

- -------------- -- - - ------------ - - -- - - - ----. ------- - -- -- - ---*--: ------- ----- -- --- - :-- -- -------------- -:- - - -- - - ---------- --~ - --- - -- - - - - -- - ---: ------------------ -- - - - - - -- - ---- - --- --- -- -------------------------------- ------ -- -- -- -- - - ------------.

S1 .OP-ST.ZZ-0003(0) FSTC 0 100726 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290600 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.ZZ-0003(0) STC 0 100726 1WL16 1 RAD WST LQD CONTMT SUMP PMP DISCH AIR OPRD VALVE 205239-3 Waste Disposal Liquid Bl 2 A GB AIR 3 0 c Active S1 .OP-ST.ZZ-0003(0) FSTC 0 100726 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290601 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.ZZ-0003(0) STC 0 100726

TABLE 3-1 -VALVE. TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 117 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification 1 I I < I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST.! REL REQ. ! RECUR. TASK !TECH POS.; COMMENTS 1WL17 1 RAD WST LQD CONTMT SUMP PMP DISCH AIR OPRD VLV 205239-3 Waste Disposal Liquid BB 2 A GB AIR 3 0 c Active

---

.------------------:-------------------.-------------------=------------------.------------------------- ----------------- ------------------------------------------------------------*

S1 .OP-ST.ZZ-0003(0) FSTC 0 100726 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290602 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.ZZ-0003(0) STC 0 100726 1WL96 1 RAD WST LQD RC DR TK TO GAS ANALYZER AIR OPRD DIAPH VALVE 205239-3 Waste Disposal Liquid F7 2 A DIA AIR 0.75 c c Active S1 .OP-ST.ZZ-0003(0) 1 FSTC j Q j j 100726 S1 .RA-IS.ZZ-0001 (0) LJ 1BYR 290603 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.ZZ-0003(0) STC 0 100726 1WL97 1 RAD WST LQD RC DR TK TO GAS ANALYZER CONT VLV 205239-3 Waste Disposal Liquid FB 2 A DIA AIR 0.75 c c Active S1 .OP-ST.ZZ-0003(0) FSTC 0 100726 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290604 S1 .OP-ST.RPl-0004(0) PIT 2YR 100302 S1 .OP-ST.ZZ-0003(0) STC 0 100726 1WL98 1 RAD WST LQD RC DR TK TO VENT HOR INBOARD CONT VLV 205239-3 Waste Disposal Liquid F7 2 A DIA AIR 1 0 c Active S1 .OP-ST.ZZ-0003(0) FSTC 0 100726 S1 .RA-IS.ZZ-0001 (0) LJ 18MO 290605 S1 .OP-ST.RPl-0002(0) PIT 2YR 100299 S1 .OP-ST.ZZ-0003(0) STC 0 100726

• TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 118 VALVE NO VALVE DESCRIPTION P + ID No P + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE!TEST FREQ.: c.s. JUST. i R.O. JUST.: REL. REQ. i. RECUR. TASK iTECH. POs.i COMMENTS 1WL99 1 RAD WST LQD RC DR TK TO VENT HOR CONT VLV 205239-3 Waste Disposal Liquid F9 2 A DIA AIR 1 0 c Active

---

,------------------.------------------;-------------------;-------------------,;------------------.-------------------------.------------------7------------------------------------------------------------*

51 .OP-5T.ZZ-0003(0) F5TC 0 100726

$1 .RA-15.ZZ-0001 (0) LJ 18MO 290606 51 .OP-5T.RPl-0004(0) PIT 2YR 100302 51 .OP-5T.ZZ-0003(0) 5TC 0 100726 1WL108 1 RAD WST LQD N2 VENT LINE OUTBOARD AIR OPRD DIAPH VALVE 205239-3 Waste Disposal Liquid G9 2 A DIA AIR 1 c c Active 51 .OP-5T.ZZ-0003(0) F5TC 0 100726 51 .RA-15.ZZ-0001 (0) LJ 18MO 290607 51 .OP-5T.RPl-0004(0) PIT 2YR 100302 51 .OP-5T.ZZ-0003(0) 5TC Q 100726 1WL190 1 RAD WST LQD REFUEL WTR PURIF PMP DR TO ANULUS DIAPH VLV 205239-3 Waste Disposal Liquid F3 2 A DIA MAN 3 LC c Passive 51 .RA-15.ZZ-0001 (0) LJ 18MO 290557 1WL191 1 RAD WST LQD REFUEL CANAL DR TO REFUEL WTR PURIF PMP DIAPH VLV 205239-3 Waste Disposal Liquid E2 2 A DIA MAN 3 LC c Passive

---

.------------------,------------------=-------------------=-------------------=------------------.-------------------------:------------------:------------------*-----------------------------------------

S1 .RA-IS.ZZ-0001 (0) LJ  : 18MO 290555 1WR80 1 REACT COOL PRIMARY WATER SUPPLY STOP AIR OPRD VLV 205201-1 Reactor Coolant C10 2 A DIA AIR 3 O/C c Active S1 .OP-ST.ZZ-0003(0). F5TC 0 100726 S1 .RA-15.ZZ-0001 (0) LJ 18MO 290608 51 .OP-5T.RPl-0004(0) PIT 2YR 100302 51 .OP-5T.ZZ-0003(0) 5TC 0 100726

TABLE 3-1 -VALVE TEST TABLE.

10/1/97 SALEM NUCLEAR PLANT - UNIT 1 Page 119 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST.; REL. REQ.; RECUR. TASK !TECH. POS.! COMMENTS 1WR81 1 REACT COOL PRIMARY WATER CHECK VLV 205201-1 Reactor Coolant C9 2 A/C CK SELF 3 O/C O/C Active S1 .RA-IS.ZZ-0001 (Q) CTC RF V-34 290609 S1 .OP-ST.ZZ-0003(0) CTO Q 100726 TP-6 S1 .RA-IS.ZZ-0001 (Q) LJ 18MO 290609

Salem Units 1 & 2 Inservice Test Program

• TABLE 3-2 Salem Unit 2 VALVE TEST TABLE

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 1 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL REQ. ! RECUR. TASK !TECH. POs.! COMMENTS 21AF4 21 AUX FEEDWATER PUMP SUCTION CHECK VALVE 205336-1 Auxiliary Feedwater D1 3 c CK SELF 6 c O/C Active S2.0P-ST.AF-0004(Q) CTC  ! Q  ! . 100655 i S2.0P-ST.AF-0005(Q) CTO CS CS-01 100820

'S2.0P-ST.AF-0001(Q) PS Q CS-01 100666 22AF4 22 AUX FDWTR PMP SPLY CKVL 205336-1 Auxiliary Feedwater D4 3 c CK SELF 6 c O/C Active S2.0P-ST.AF-0004(Q) CTC Q 100655 S2.0P-ST .AF-0005(Q) CTO cs CS-01 100820 S2.0P-ST.AF-0002(Q) PS Q CS-01 100667 23AF4 23 AUX FDWTR PMP SPLY CKVL 205336-1 Auxiliary Feedwater D7 3 c CK SELF 8 c O/C Active S2. OP-ST.AF-0004(Q) CTC Q 100655 S2.0P-ST .AF-0007(Q) CTO cs CS-01 100376 S2. OP-ST .AF-0003(Q) PS Q CS-01 100668 21AF8 21 AUX FDWTR PMP DISCH CKVL 205336-1 Auxiliary Feedwater E4 3 c CK SELF 4 c 0 Active S2.0P-ST.AF-0005(Q) CTO CS  ! CS-02 100820  !  !

22AF8 22 AUX FDWTR PMP DISCH CKVL 205336-1 Auxiliary Feedwater E6 3 c CK SELF 4 c 0 Active S2.0P-ST.AF-0005(Q)  ! CTO* ! CS ' CS-02 100820

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 2 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK ! TECH. POS.! COMMENTS 23AF8 23 AUX FDWTR PMP DISCH CHECK VLV 205336-1 Auxiliary Feedwater EB 3 c CK SELF 6 c 0 Active S2. OP-ST .AF-0007 (Q) CTO cs i CS-02 100376 S2.0P-ST.AF-0003(Q) PS Q  ! CS-02 100668 21AF11 21 AUX FDWTR STM GEN INLET AIR OPRD GLB VLV 205336-1 Auxiliary Feedwater G7 3 B GB AIR 4 0 O/C Active S2.0P-ST.RPl-0001 (Q)  ! Pff 2YR 100208 S2.0P-ST.AF-0004(0) STC Q 100655 22AF11 22 AUX FDWTR STM GEN INLET AIR OPRD GLB VLV 205336-1 Auxiliary Feedwater E6 3 B GB AIR . 4 0 O/C Active S2.0P-ST.RPl-0001 (Q) ! PIT 2YR 100208 S2.0P-ST.AF-0004(Q) STC Q 100655

• 23AF11 23 AUX FDWTR STM GEN INLET AiR OPRD GLB VLV 205336-1 Auxiliary Feedwater F7 3 .B GB AIR

• 4 0 O/C Active S2.0P-ST.RPl-0001 (Q) ! PIT 2YR 100208 S2.0P-ST.AF-0004(Q) STC Q 100655 24AF11 24 AUX FDWTR STM GEN INLET AIR OPRD GLB VLV 205336-1 Auxiliary Feedwater F7 3 B GB AIR 4 0 O/C Active S2.0P-ST.RPl-0001 (Q) PIT 2YR 100208 S2.0P-ST.AF-0004(Q) STC Q 100655

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 3 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification I

I I

I I

I I

I I I I I TEST PROC :TEST TYPE :TEST FREQ.: C.S. JUST. : R.O. JUST. : REL. REQ.: RECUR. TASK ~TECH. POS.: COMMENTS 21AF21 21 AUX FDWTR STM GEN INLET AIR OPRD GLB VLV 205336-1 Auxiliary Feedwater H6 3 B GB AIR 4 c MIC Active S2. OP-ST .AF-0004(0) FSTO 0 100655 S2.0P-ST.RPl-0001 (0) PIT 2YR 100208 S2. OP-ST .AF-0004(0) STC 0 100655 S2. OP-ST .AF-0004(0) STO 0 100655 22AF21 22 AUX FDWTR STM GEN INLET AIR OPRD GLB VLV 205336-1 Auxiliary Feedwater F6 3 B GB AIR 4 c MIC Active S2. OP-ST .AF-0004(0) FSTO 0 100655 S2.0P-ST.RPl-0001 (0) PIT 2YR 100208 S2.0P-ST.AF-0004(0) STC 0 100655 S2.0P-ST.AF-0004(0) STO 0 100655 23AF21 23 AUX FDWTR STM GEN INLET AIR OPRD GLB VLV 205336-1 Auxiliary Feedwater F6 3 B GB AIR 4 c MIC Active S2.0P-ST.AF-0004(0) FSTO 0 100655 S2.0P-ST.RPl-0001 (0) PIT 2YR 100208 S2.0P-ST.AF-0004(0) STC 0 100655 S2.0P-ST.AF-0004(0) STO 0 100655 24AF21 24 AUX FDWTR STM GEN INLET AIR OPRD GLB VLV 205336-1 Auxiliary Feedwater G4 3 B GB AIR 4 c MIC Active S2.0P-ST.AF-0004(0) FSTO 0 100655 S2.0P-ST.RPl-0001 (0) PIT 2YR 100208 S2.0P-ST.AF-0004(0) STC 0 100655 S2.0P-ST.AF-0004(0) STO 0 100655

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 4 VALVE NO VALVE DESCRIPTION P +ID No P+/DName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I TEST PROC !TEST TYPE !TEST FREQ.j C.S. JUST. j R.O. JUST. j REL. REQ. j RECUR. TASK j TECH. POS.! COMMENTS 21AF23 21 AUX FDWTR STM GEN INLET SCHK 205336-1 Auxiliary Feedwater H9 2 c SCK SELF 4 c O/C Active S2. OP-ST .AF-0006(0) CTC 0 101151 S2. OP-ST .AF-0005(0) CTO cs  ! CS-03 100820 22AF23 22 AUX FDWTR STM GEN INLET SCHK 205336-1 Auxiliary Feedwater F10 2 c SCK SELF 4 c O/C Active S2. OP-ST .AF-0006(0) CTC 0 101151 S2 .OP-ST .AF-0005(0) CTO cs  ! CS-03 100820 23AF23 23 AUX FDWTR STM GEN INLET SCHK 205336-1 Auxiliary Feedwater F10 2 c SCK SELF 4 c O/C Active S2.0P-ST.AF-0006(0) CTC 0 101151 S2.0P-ST.AF-0005(0) CTO CS i CS-03 100820 24AF23 24 AUX FDWTR STM GEN INLET SCHK 205336-1 Auxiliary Feedwater G10 2 .C SCK SELF* 4 c O/C Active S2.0P-ST.AF-0006(0) CTC 0 101151 S2. OP-ST .AF-0005(0) CTO cs  ! CS-03 100820 21AF40 21 AUX FDWTR PMP DISCH AIR OPRD GLB VLV 205336-1 Auxiliary Feedwater D4 3 B GB AIR 2 0 O/C Active S2 .OP-ST .AF-0004(0) FSTO 0 100655 S2.0P-ST .RPl-0001 (0) PIT 2YR 100208 S2.0P-ST.AF-0004(0) STC 0 100655 S2. OP-ST .AF-0004(0) STO 0 100655

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 5 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification 1 I I I I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK .! TECH. POS.! COMMENTS 22AF40 22 AUX FDWTR PMP DISCH AIR OPRD GLB VLV 205336-1 Auxiliary Feedwater D6 3 B GB AIR 2 0 O/C Active S2. OP-ST .AF-0004(0) FSTO 0 100655 S2.0P-ST.RPl-0001 (0) PIT 2YR 100208 S2.0P-ST.AF-0004(0) STC 0 100655 S2. OP-ST .AF-0004(0) STO 0 100655 21AF52 21 AUX FDWTR PMP SUCT AIR OPRD GLB VLV 205336-1 Auxiliary Feedwater E1 3 B PL AIR 6 c O/C Active

~

S2.0P-ST.RPl-0001 (0) : PIT  : 2YR  : 100208 [ [

S2.0P-ST.AF-0004(0) STO 0 100655 22AF52 22 AUX FDWTR PMP INLET AIR OPRD VLV 205336-1 Auxiliary Feedwater E4 3 B PL AIR 6 c O/C Active

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -: - - - - - - - - - - - - - - - - - -. - - - - - - - - - - - - - - - - - - .- - - - - - - - - - - - - - - - - - - .- - - - - - - - - - - - - - - - - - - .- - - - - - - - - - - - - - - - - -. - - - - - - - - - - - - - - - - - - - - - - - - - ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - .

S2.0P-ST.RPl-0001 (0) i PIT 2YR  :

100208 S2.0P-ST.AF-0004(0) STO 0 100655 23AF52 23 AUX FDWTR PMP SPLY AIR OPRD GLB VLV 205336-1 Auxiliary Feedwater El 3 B PL AIR 8 c DIC Active

---

.------------------.------------------.-------------------.-------------------.-------------------------------------------.------------------7------------------------------------------------------------

S2.0P-ST.RPl-0001 (0) ! PIT 2YR 100208 S2.0P-ST.AF-0004(0) STO 0 100655 21AF53 21 AUX FDWTR PMP SUCT CHECK VLV 205336-1 Auxiliary Feedwater D1 3 c CK SELF 6 c 0 Active SC.MD-PM.ZZ-0044(0) CTO SAM V-02 202875 TP-6

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 6 VALVE NO VALVE DESCRIPTION P +JD No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE [TEST FREQ) C.S. JUST. [ R.0. JUST.! REL. REQ. i RECUR. TASK !TECH. POS.! COMMENTS 22AF53 22 AUX FDWTR PMP SUCT CKVL 205336-1 Auxiliary Feedwater 04 3 C CK SELF 6 C 0 Active CTO SAM V-02 202874 TP-6 23AF53 23 AUX FDWTR PMP SPLY CHECK VLV 205336-1 Auxiliary Feedwater El 3 c CK SELF 8 c 0 Active SC.MD-PM.ZZ-0044(Q) [ CTO . SAM . [ . V-02 . 202873 . TP-6 [

2AF92 Manual Valve Isolation for Spool Piece Connecting AF to SW 205336-1 Auxiliary Feedwater E1 3 B GT MAN 8 LC O/C Active S2.0P-ST.AF-0004(Q) FSO i Q [  : i 100655 i 21AF920 21 AUX FDWTR STM GEN INLET CKVL 205336-1 Auxiliary Feedwater H6 3 c CK SELF 4 c 0 Active S2.0P-ST.AF-0005(Q) CTO CS  : CS-05 100820 22AF920 22 AUX FDWTR STM GEN INLET CKVL 205336-1 Auxiliary Feedwater F5 3 *c CK SELF 4 c 0 Active CTO cs : CS-05 100820 23AF920 23 AUX FDWTR STM GEN INLET CKVL 205336-1 Auxiliary Feedwater F5 3 c CK SELF 4 c 0 Active S2. OP-ST .AF-0005(Q) CTO cs  : CS-05 100820 24AF920 24 AUX FDWTR STM GEN INLET CKVL 205336-1 Auxiliary Feedwater G5 3 c CK SELF 4 c 0 Active S2.0P-ST.AF-0005(Q) CTO CS CS-05  ! 100820  :

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 7 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE iTEST FREQ.! C.S. JUST. : R.O. JUST. : REL. REQ. : RECUR. TASK : TECH. Pos.! COMMENTS 21AF921 21 AUX FDWTR STM GEN INLET CKVL 205336-1 Auxiliary Feedwater G6 3 C CK SELF 4 C OIC Active

• • 52:01:>~si.A:i=~oac>s<a>**---r*--**c:rc*---*------*-c5**--*--r**-*c;5~*as*------------------------------------------------*100820*--------------------------------------------------------------------------------------

s2.0P-sT.AF-0001ca> CTO cs  ! CS-06 100376 22AF921 22 AUX FDWTR STM GEN INLET CKVL 205336-1 Auxiliary Feedwater E7 3 c CK SELF 4 c O/C Active

~

S2.0P-ST.AF-0005(Q) CTC cs CS-06 100820 S2.0P-ST.AF-0007(Q) CTO cs CS-06 100376 23AF921 23 AUX FDWTR STM GEN INLET CKVL 205336-1 Auxiliary Feedwater F6 3 c CK SELF 4 c O/C Active

---

.------------------.------------------:-------------------:-------------------:------------------.-------------------------:------------------7------------------------------------------------------------

S2.0P-ST .AF-0005(0) CTC cs CS-06 100820 S2.0P-ST.AF-0007(Q) CTO cs CS-06 100376 24AF921 24 AUX FDWTR STM GEN INLET CKVL 205336-1 Auxiliary Feedwater G7 3 .C CK SELF 4 c O/C Active

---

.------------------.------------------:-------------------:-------------------:------------------.-------------------------:------------------7------------------------------------------------------------*

S2.0P-ST.AF-0005(Q) CTC cs  : CS-06 100820 S2.0P-ST.AF-0007 (Q) CTO cs  ! CS-06 100376 21AF923 Manual Cross-Tie Between AF Feeds to Steam Generator 23 and Steam Generator 24 205336-1 Auxiliary Feedwater F5 3 B GT MAN 3 c c Passive

---

.------------------.--- --------------:-------------------:-------------------:------------------.-------------------------:------------------7------------------------------------------------------------*

':  : No inservice testing required for this component.

22AF923 Manual Cross-Tie Between AF Feeds to Steam Generator 23 and Steam Generator 24 205336-1 Auxiliary Feedwater FS 3 B GT MAN 3 c c Passive No inservice testing required for this component.

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 8 VALVE NO VALVE DESCRIPTION P +ID No P+ JD Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification 1 I I I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST.! REL. REQ. ! RECUR. TASK !TECH. POS.! COMMENTS 21BF13 21 STM GEN FEED & COND STM GEN INLET GATE MOV AUGMENTED 205302-3 Steam Generator Feed and Condensate D5 N B GT MO 14 0 c Active S2.0P-ST.RPl-0003(0) i PIT 2YR 100873 S2.0P-ST.MS-0002(0) STC CS ( CS-10 100844 22BF13 22 STM GEN FEED & COND STM GEN INLET GATE MOV AUGMENTED 205302-3 Steam Generator Feed and Condensate D7 N B GT MO 14 0 c Active

--52:0P~ST.-RPi~ooo3-(Ci) ____ 1_______Pl_T, ___________2YR ________ --------------------------*----------------------------------100873_________________________ -------------------------*---------*--*--*----**--*------**-

S2.0P-ST.MS-0002(0) STC CS  ! CS-10 100844 23BF13 23 STM GEN FEED & COND STM GEN INLET GATE MOV AUGMENTED 205302-3 Steam Generator Feed and Condensate D3 N B GT MO 14 0 c Active

---

;------------------=--------------------------- - --------------------------;-------------------------;------------------ ------------------------------------------------------------

S2.0P-ST.RPl-0003(0) ! PIT i 2YR  ! 100873 S2.0P-ST.MS-0002(0) STC CS  ! CS-10 100844 24BF13 24 STM GEN FEED & COND STM GEN 24 REG VLV ISOL VLV AUGMENTED 205302-3 Steam Generator Feed and Condensate D9 N .B GT MO 14 0 c Active S2.0P-ST.RPl-0003(0) ! PIT 2YR 100873 S2.0P-ST.MS-0002(0) STC CS  ! CS-10 100844 21BF19 21 STM GEN FEED & COND STM GEN INLET AIR OPRD GLB VLV AUGMENTED 205302-3 Steam Generator Feed and Condensate E4 N B GB AIR 12 0 c Active S2 .OP-ST .MS-0002(0) FSTC cs CS-07 100844 S2.0P-ST.RPl-0003(0) PIT 2YR 100873 S2. OP-ST. MS-0002(0) STC cs CS-07 100844

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 9 VALVE NO VALVE DESCRIPTION P+ ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I TEST PROC jTEST TYPE ~TEST FREQ.~ C.S. JUST. ~ R.O. JUST. i REL~ REQ. ~ RECUR. TASK ~TECH. POS.! COMMENTS 22BF19 22 STM GEN FEED & COND STM GEN INLET AIR OPRD GLB VLV AUGMENTED 205302-3 Steam Generator Feed and Condensate E6 N B GB AIR 12 0 c Active S2.0P-ST.MS-0002(Q) FSTC CS CS-07 100844 S2.0P-ST.RPl-0003(Q) i PIT 2YR 100873 S2.0P-ST.MS-0002(Q) STC CS CS-07 100844 23BF19 23 STM GEN FEED & COND STM GEN INLET AIR OPRD GLB VLV AUGMENTED 205302-3 Steam Generator Feed and Condensate E1 N B GB AIR 12 0 c Active S2.0P-ST.MS-0002(Q) FSTC cs CS-07 100844 S2.0P-ST.RPl-0003(Q) i . PIT 2YR 100873 S2.0P-ST.MS-0002(Q) STC cs CS-07 100844 24BF19 24 STM GEN FEED & COND STM GEN 24 CONT VLV AUGMENTED 205302-3 Steam Generator Feed and Condensate EB N B GB AIR 12 0 c Active S2.0P-ST.MS-0002(Q) FSTC cs CS-07 100844 S2.0P-ST.RPl-0003(Q) i PIT 2YR 100873 S2.0P-ST.MS-0002(Q) STC cs CS-07 100844 21BF22 21 STM GEN FEED & COND STM GEN INLET STOP CHECK MOV 205302-3 Steam Generator Feed and Condensate F4 2 B/C SCK SELF 14 0 c Active S2.0P-ST.MS-0002(Q) CTC cs CS-08 100844 S2.0P-ST.RPl-0003(Q) PIT 2YR 100873 S2.0P-ST .MS-0002(0) STC cs CS-08 100844

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 10 VALVE NO VALVE DESCRIPTION P + ID No P + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.: C.S. JUST. ! R.O. JUST. : REL. REQ. ! RECUR. TASK !TECH. POS.! COMMENTS 22BF22 22 STM GEN FEED & COND STM GEN INLET STOP CHECK MOV 205302-3 Steam Generator Feed and Condensate F6 2 B/C SCK MO 14 0 c Active S2. OP-ST .MS-0002(0) CTC cs CS-08 100844 S2.0P-ST.RPl-0003(0) i PIT 2YR 100873 S2.0P-ST.MS-0002(0) STC cs CS-08 100844 23BF22 23 STM GEN FEED & COND STM GEN INLET STOP CHECK MOV 205302-3 Steam Generator Feed and Condensate F2 2 B/C SCK MO 14 0 c Active S2.0P-ST.MS-0002(0) CTC cs CS-08 100844 S2.0P-ST.RPl-0003(0) ! PIT 2YR 100873 S2.0P-ST.MS-0002(0) STC cs CS-08 100844 24BF22 24 STM GEN FEED & COND STM GEN 24 STOP CHECK VLV 205302-3 Steam Generator Feed and Condensate F9 2 B/C SCK MO 14 0 c Active S2.0P-ST.MS-0002(0) CTC CS CS-08 100844 S2.0P-ST.RPl-0003(0) i PIT 2YR 100873 S2.0P-ST.MS-0002(0) STC CS CS-08 100844 21BF40 21 STM GEN FEED & COND STM GEN INLET CONT VLV BYP AIR OPRD GLB VLV AUGMENTED 205302-3 Steam Generator Feed and Condensate E4 N B GB AIR 4 O/C c Active 52.0P-ST.MS-0002(0) FSTC cs CS-09 100844 S2.0P-ST.RPl-0003(0) PIT 2YR 100873 S2.0P-ST.MS-0002(0) STC cs CS-09 100844

• TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 11 VALVE NO VALVE DESCRIPTION P +JD No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification 1 I I I I I o TEST PROC !TEST TYPE !TEST FREQ.: C.S. JUST. ! R.O. JUST.  ! REL. REQ.  ! RECUR. TASK ! TECH. POS.! COMMENTS 22BF40 22 STM GEN FEED & COND STM GEN INL CONT VLV BYP AIR OPRD GLB VLV AUGMENTED 205302-3 Steam Generator Feed and Condensate E6 N B GB AIR 4 O/C c Active S2.0P-ST.MS-0002(Q) FSTC CS CS-09 100844 S2.0P-ST.RPl-0003(Q) i PIT 2YR 100873 S2.0P-ST.MS-0002(Q) STC CS CS-09 100844 23BF40 23 STM GEN FEED & COND STM GEN INLET CONT VLV BYP AIR OPRD GLB VLV AUGMENTED 205302-3 Steam Generator Feed and Condensate E2 N B GB AIR 4 O/C c Active S2.0P-ST.MS-0002(Q) FSTC cs CS-09 100844 S2.0P-ST.RPl-0003(Q) i PIT 2YR 100873 S2.0P-ST.MS-0002(Q) STC cs CS-09 100844 24BF40 24 STM GEN FEED & COND STM GEN 24 CONT VLV BYPASS VLV AUGMENTED 205302-3 Steam Generator Feed and Condensate EB N B GB AIR 4 O/C c Active S2.0P-ST.MS-0002(Q) FSTC cs CS-09 100844 S2.0P-ST.RPl-0003(Q) i PIT 2YR 100873 S2.0P-ST.MS-0002(Q) STC cs CS-09 100844 21CA330 2 CONT AIR HOR 2A INLET AIR OPRD GLB VLV 205347-1 No. 2 Unit - React. Cont. & Penetration Area E3 2 A GB AIR 2 0 c Active S2.0P-ST.ZZ-0003(Q) FSTC Q 100665 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290700 S2.0P-ST.RPl-0004(Q) PIT 2YR 100872 S2.0P-ST.ZZ-0003(Q) STC Q 100665

.TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 12 VALVE NO VALVE DESCRIPTION P+ ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

---~~~~-~~~-~--------------------h~~~-~~~~-:~~~~-~~~~:r*-~--~--~~~~---r*-~.-~:-~~~~:*:--~~~---~-~~:1*-~~~-~-~---~~~~---r~~~~:-~~~:1*~~~-~~~~~--*------------*--------*-*--*-----*------

22cA330 22 CONT AIR HOR 2B INLET AIR OPRD GLB VLV 205347-1 No. 2 Unit - React. Cont. & Penetration Area D3 2 A GB AIR 2 0 c Active S2.0P-ST.ZZ-0003(Q) FSTC Q 100665 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290702 S2.0P-ST.RPl-0004(Q) PIT 2YR 100872 S2.0P-ST.ZZ-0003(Q) STC Q 100665 21CA360 21 CONT AIR HOR 2A CONTMT RETURN CHECK VLV 205347-3 No. 2 Unit - React. Cont. & Penetration Area C1 2 A/C CK SELF 2 0 c Active S2.RA-IS.ZZ-0002(Q) CTC RF V-04 290701 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290701 22CA360 22 CONT AIR HOR 2B CONTMT RETURN CHECK VLV 205347-3 No. 2 Unit- React. Cont. & Penetration Area 81 2 A/C CK SELF 2 0 c Active S2.RA-IS.ZZ-0002(Q) CTC RF V-04 290703 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290703 2CA1714 2 CONT AIR LOCK AIR SPLY TO SEALS ELEV 100 VLV 205347-1 No. 2 Unit - React. Cont. & Penetration Area H3 2 A GT MAN 0.375 c c Passive LJ 18MO 290704 2CA1715 2 CONT AIR LOCK AIR SPLY TO SEALS ELEV 130 VLV 205347-1 No. 2 Unit- React. Cont. & Penetration Area H4 2 A GT MAN 0.375 c c Passive S2.RA-IS.ZZ-0002(Q) LJ 18MO 290705

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 13 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

. - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -,- - - - .. - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I - - - - - - - - - - - - - - - - - I - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - -, - - - - - - . - - - - - - - - - - - - - - - - - - I - - - - - - - - - - - - - - - - - ~ - - . - . - .. - - . - - . - . - - - - - . - - - .. - - - - - .. - ..... - - - . - ........ - ... - - .

TEST PROC iTEST TYPE iTEST FREQ.: C.S. JUST. : R.O. JUST. i REL. REQ. i RECUR. TASK iTECH. POS.i COMMENTS 2CA1785 CONTROL AIR ACCUMULATOR CHECK VALVE AUGMENTED 205347-3 No. 2 Unit - React. Cont. & Penetration Area H6 N A/C CK SELF 1 c c Active SC.RA-IS.PZR-0024(0) ! CTC RF V-05 101094 SC.RA-IS.PZR-0024(0) [ LT 2YR 101094 2CA1786 CONTROL AIR ACCUMULATOR CHEn\ VALVE AUGMENTED 205347-3 No. 2 Unit- React. Cont. & Penetration Area H4 N A/C CK SELF 1 c c Active SC.RA-IS.PZR-0024(0)  ! CTC RF V-05 101094 SC.RA-IS.PZR-0024(0) [ LT 2YR 101094 2CA1787 CONTROL AIR ACCUMULATOR CHECK VALVE AUGMENTED 205347-3 No. 2 Unit - React. Cont. & Penetration Area G6 N AJC CK SELF 1 c c Active SC.RA-IS.PZR-0024(0) i CTC RF V-05 101094 SC.RA-IS.PZR-0024(0) [ LT 2YR 101094 2CA1788 CONTROL AIR ACCUMULATOR CHECK VALVE AUGMENTED 205347-3 No. 2 Unit - React. Cont. & Penetration Area G6 N A/C CK SELF 1 c c Active SC.RA-IS.PZR-0024(0) i CTC RF V-05 101094 SC.RA-IS.PZR-0024(0) i LT 2YR 101094 2CA2086 21SW534 CONTROL AIR ACCUMULATOR CK VALVE AUGMENTED 205347-1 Control Air CB N c CK SELF .5 c c Active S2. OP-ST.SW-0010(0) CTC 0 101214 S2.RA-IS.SW-0001 (0) LT 2YR 200278

TABLE 3r2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 14 VALVE NO VALVE DESCRIPTION P + ID No P + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST.! REL. REQ. ! RECUR. TASK !TECH. Pos.i COMMENTS 2CA2091 21SW535 CONTROL AIR ACCUMULATOR CK VALVE AUGMENTED 205347-1 Control Air C9 N C CK SELF .5 C C Active

; ~

82.0P-8T.8W-001 O(Q) ! CTC Q 101214 82.RA-18.8W-0001 (Q) LT 2YR 200279 2CA2093 22SW534 CONTROL AIR ACCUMULATOR CK VALVE AUGMENTED 205347-1 Control Air E9 N c CK SELF .5 c c Active 82.0P-8T.8W-001 O(Q) j CTC Q 101214 82.RA-18.SW-0001 (Q) LT 2YR 200280 2CA2095 22SW535 CONTROL AIR ACCUMULATOR CK VALVE AUGMENTED*

205347-1 Control Air C6 N c CK SELF .5 c c Active 82.0P-8T.8W-001 O(Q)  ! CTC Q 101214 82.RA-18.8W-0001 (Q) LT 2YR 200281 21CC1 21 CMPNT CLG PMP DISCH CHECK VALVE 205331-1 Component Cooling E5 3 .C CK SELF 12 0 O/C Active 82.0P-8T.CC-0001 (Q) CTC Q 100673 82.0P-8T.CC-0001 (Q) CTO Q 100673 22CC1 22 CMPNT CLG PMP DISCH CHECK VLV 205331-1 Component Cooling C5 3 c CK SELF 12 0 OIC Active S2.0P-ST.CC-0002(Q) CTC Q 100674

82. OP-ST. CC-0002(0) CTO Q 100674

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 15 VALVE NO VALVE DESCRIPTION P + ID No P + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE lTEST-FREa.l C.S. JUST. [ R.O. JUST. j REL. REQ. [ RECUR. TASK . !TECH. POs.l COMMENTS 23CC1 23 CMPNT CLG PMP DISCH CHECK VLV 205331-1 Component Cooling D5 3 c CK SELF 12 0 O/C Active S2.0P-ST.CC-0003(0) CTC 0 100675 S2.0P-ST.CC-0003(0) CTO 0 100675 21CC3 21 CMPNT CLG PMP DISCH HOR CRSVR TO HT EXCH GATE MOV 205331-1 Component Cooling D5 3 B GT MO 16 0 O/C Active S2.0P-ST.RPl-0001 (0) ! PIT 2YR 100208 S2.0P-ST.CC-0004(0) STC 0 100660 22CC3 22 CMPNT CLG PMP DISCH HOR CRSVR TO HT EXCH GATE MOV 205331-1 Component Cooling D5 3 B GT MO 16 0 O/C Active S2.0P-ST.RPl-0001 (0) ! PIT 2YR 100208 S2.0P-ST.CC-0004(0) STC 0 100660 21CC16 21 CMPNT CLG RHR HEAT EXCHANGER OUTLET GATE MOV 205331-1 Component Cooling F9 3 .B GT MO 12 c O/C Active S2.0P-ST.RPl-0001 (0) PIT 2YR 100208 S2.0P-ST.CC-0004(0) STC 0 100660 S2. OP-ST. CC-0004(0) STO 0 100660 22CC16 22 CMPNT CLG RESIDUAL HT EXCH OUTLET MOV 205331-1 Component Cooling A9 3 B GT MO 12 c O/C Active S2.0P-ST.RPl-0001 (0) PIT 2YR 100208 S2. OP-ST. CC-0004(0) STC 0 100660 82.0P-ST.CC-0004(0) STO 0 . 100660

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 16 VALVE NO VALVE DESCRIPTION P + ID No P + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position

• Classification TEST PROC !TEST TYPE !TEST FREQ) C.S. JUST. : RO. JUST. ! REL. REQ. ! RECUR. TASK iTECH. POS.! COMMENTS 2CC17 2 CMPNT CLG PMP SUCT HOR GATE MOV 205331-1 Component Cooling D3 , 3 B GT MO 12 0 O/C Active

---

.------------------.------------------=-------------------;-------------------.----------------- ------------------------

52.0P-ST.RPl-0001 (Q) i PIT 2YR 100208 S2.0P-ST.CC-0004(Q) STC Q 100660 2CC18 2 CMPNT CLG PMP SUCTION HEADER ISOLATION GATE MOV 205331-1 Component Cooling C3 3 B GT MO 12 0 O/C Active 52.0P-ST.RPl-0001 (Q) i PIT 2YR 100208 52.0P-ST .CC-0004(Q) STC Q 100660 2CC30 2 CMPNT CLG 21 HT EXCH TO SPENT FUEL PIT HT EXCH GATE MOV 205331-1 Component Cooling C6 3 B GT MO 16 0 c Active 52.0P-ST.RPl-0001 (Q) i PIT 2YR 100208 S2.0P-ST.CC-0004(Q) STC Q 100660 2CC31 2 CMPNT CLG TO SPENT FUEL PIT HEAT EXCHANGER GATE MOV 205331-1 Component Cooling C6 3 . B GT MO 16 0 c Active

$2.0P-ST.RPl-0001 (Q) ! PIT 2YR 100208 S2.0P-ST.CC-0004(Q) STC Q 100660 2CC71 2 CMPNT CLG LETDOWN HEAT EXCHANGER OUTLET BTFL VLV 205331-2 Component Cooling HS 3 B BF AO 6 0 c Active S2.0P-ST.CVC-0007(Q) FSTC cs CS-47 100456 S2.0P-ST.RPl-0003(Q) PIT 2YR 100873 S2.0P-ST.CVC-0007(Q) STC cs CS-47 100456

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 17 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification I I l I I I I TEST PROC .!TEST TYPE !TEST FREQ.! C.S. JUST.  ! R.O. JUST. i REL. REQ.  ! RECUR. TASK i TECH. POS.i COMMENTS 2CC109 COMPONENT COOLING EXCESS LETDOWN HEAT EXCHANGER INLET CHECK VALVE 205331-3 Component Cooling D1 2 N/A CK SELF 3 0 0 Active S2.0P-ST.CC-0004(Q) CTO Q  !  ! 100660 TP-6  :

2CC112 COMP COOLING EXCESS LETDOWN HT EXCHNGR OUTLET SAFETY RELIEF VLV 205331-3 Component Cooling E2 3 c RV SELF 3 c 0 Active SC.MD-PT.ZZ-0007(0) RV  ! SYR 204868  !

2CC113 2 CMPNT CLG EXCESS LETDOWN HT EXCHG OUTLET AIR OPRD GLB VLV 205331-3 Component Cooling D2 2 A GT AIR 3 O/C c Active

~ - - - - - - - - -- - -- -- - - - -- -- -- - ----- - -- -- - - - - -- - - - - - - - - . -- . - - - - - - --- -- ---. ----- -

S2.0P-ST.CC-0004(Q) FSTC Q 100660 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290706 S2.0P-ST.RPl-0004(Q) PIT 2YR 100872 S2.0P-ST.CC-0004(Q) STC Q 100660 2CC118 2 CMPNT CLG REACTOR COOLANT PMP UPR & LWR BRG SPLY HOR GATE MOV 205331-3 Component Cooling CS 2 .A GT MO

• 6 0 c Active S2.RA-IS.ZZ-0002(Q) LJ  ! 18MO  !  ! 290708 S2.0P-ST.RPl-0003(Q)  ! PIT 2YR 100873 S2.0P-ST.CC-0005(Q) STC CS CS-11 100450 2CC119 2 CMPNT CLG REACTOR COOLANT PMP BRG & SEAL SPLY HOR CKVL 205331-3 Component Cooling FS 2 A/C CK SELF 6 0 O/C Active S2.RA-IS.ZZ-0002(Q) CTC RF V-06 290709 S2.0P-ST.CC-0004(Q) CTO Q 100660 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290709

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 18 VALVE NO VALVE DESCRIPTION P+ JD No P+ JD Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.: C.S. JUST. : R.O. JUST. : REL. REQ. : RECUR. TASK : TECH. Pos.! COMMENTS 21CC128 21 CMPNT CLG REACTOR COOLANT PMP THERM BARR SPLY CHECK VLV 205331-3 Component Cooling F5 3 c CK SELF 1.5 0 c Active 82.0P-ST.CC-0005(0)  ! CTC RF V-08 100450  !

22CC128 22 CMPNT CLG REACTOR COOLANT PMP THERM BARR SPLY CKVL 205331-3 Component Cooling F9 3 c CK SELF 1.5 0 c Active 82.0P-ST.CC-0005(0) CTC RF  ! V-08 100450  !

23CC128 23 CMPNT CLG REACTOR COOLANT PMP THERM BARR SPLY CKVL 205331-3 Component Cooling C6 3 C CK SELF 1.5 0 c Active 82.0P-ST.CC-0005(0) j CTC RF  ! V-08 100450  !

24CC128 24 CMPNT CLG REACTOR COOLANT PMP THERM BARR SPLY CHECK VLV 205331-3 Component Cooling C9 3 C CK SELF 1.5 O C Active 82.0P-ST.CC-0005(0) CTC RF V-08 [ 100450  !

21CC129 21 CMPNT CLG REACTOR COOLANT PMP THERM BARR OUT SAF RLF VLV 205331-3 Component Cooling G7 3 c RV SELF 0.75 c O/C Active

"'; ~ ~

SC.MD-PT.ZZ-0007(0) RV 5YR 290084 22CC129 22 CMPNT CLG REACTOR COOLANT PMP THERM BARR OUTLET SAF RLF VLV 205331-3 Component Cooling G10 3 C RV SELF 0.75 c O/C Active SC.MD-PT.ZZ-0007(0) RV [ 5YR  ! 290086 23CC129 23 CMPNT CLG REACTOR COOLANT PMP THERM BARRIER OUTLET SAF RLF VLV 205331-3 Component Cooling D7 3 C RV SELF O. 75 c O/C Active SC.MD-PT.ZZ-0007(0) RV 5YR 290088

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 19 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. i R.O. JUST. ! REL. REQ. ! RECUR. TASK !TECH. pos.i COMMENTS 24CC129 24 CMPNT CLG REACTOR COOLANT PMP THERM BARRIER OUT SAF RLF VLV 205331-3 Component Cooling 010 3 C RV SELF 0. 75 C DIC Active SC.MD-PT.ZZ-0007(0) RV 5YR 290090 2CC131 2 CMPNT CLG REACTOR COOLANT PMP THERM BARR RTN HOR GLB MOV 205331-3 Component Cooling C4 2 A GT MO 3 0 c Active

~

S2.RA-IS.ZZ-0002(Q) LJ 18MO 290710 S2.0P-ST.RPl-0003(Q) j PIT 2YR 100873 S2.0P-ST.CC-0005(Q) STC cs CS-12 100450 2CC135 2 CMPNT CLG REACTOR COOL PMP UPR BRG OUT HOR SAF RLF VLV 205331-3 Component Cooling E3 3 C RV SELF 3 c O/C Active

---

.------------------.------------------:------------------:------------------.------------------.-------------------------:-----------------7-----------------------------------------

SC.MD-PT.ZZ-0007(0) j RV 5YR  : 290092 j 2CC136 2 CMPNT CLG REACTOR COOLANT PMP UPR & LWR BRG RET HOR GATE MOV 205331-3 Component Cooling C4 2 A GT MO 6 0 c Active S2.RA-IS.ZZ-OQ02(Q)  : LJ 18MO  : 290713 S2.0P-ST.RPl-0003(Q)  : PIT 2YR 100873 S2.0P-ST.CC-0005(Q) STC cs CS-12 100450 2CC147 2 CMPNT CLG SURGE TK SAF RLF VLV 205331-1 Component Cooling F1 3 c RV SELF 3 c O/C Active SC. MD-PT .ZZ-0007 (Q) RV 5YR 290096 2CC148 2 CMPNT CLG SURGE TK VACUUM BREAKER 205331-1 Component Cooling F2 3 c RV SELF 1 c O/C Active PTC-25.3 (Crane Proc.) j RV 5YR 102230

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 20 VALVE NO VALVE DESCRIPTION P + ID No P + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification 1 I I t I I TEST PROC !TEST TYPE!TEST FREQ.! C.S. JUST. ! -R.O. JUST.! REL. REQ. ! RECUR. TASK !TECH. POS.! COMMENTS 2CC149 2 CMPNT CLG SURGE TK VENT AIR OPRO GLB VLV 205331-1 Component Cooling F2 3 B GB AIR 2 0 c Active S2.0P-ST.CC-0004(Q) FSTC Q 100660 52.0P-ST.RPl-0001 (Q) i PIT 2YR 100208 S2.0P-ST.CC-0004(Q) STC Q 100660 2CC186 2 CMPNT CLG REACTOR COOL PMP LWR SEAL RET HOR MOV BYP CHECK VLV 205331-3 Component Cooling E3 2 A/C CK. SELF 0.75 c DIC Active

~

S2.RA-IS.ZZ-0002(Q) CTC RF V-07 290714 S2.0P-ST.CC-0005(Q) CTO RF v~o1 100450 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290714 2CC187 2 CMPNT CLG REACTOR COOLANT PMP RET LWR SEAL RTN HOR GLB MOV .

205331-3 Component Cooling D4 2 A GT MO 6 0 c Active S2.RA-IS.ZZ-0002(Q) LJ 18MO 290715 S2.0P-ST.RPl-0002(Q) ! PIT 2YR 100207 S2.0P-ST.CC-0005(Q) STC cs CS-12 100450 2CC190 2 CMPNT CLG REACTOR COOLANT PMP THERM BARR RET HOR GLB MOV 205331-3 Component Cooling D4 2 A GT MO 3 0 c Active S2.RA-IS.ZZ-0002(Q) LJ 18MO 290711 S2.0P-ST.RPl-0002(Q) i PIT 2YR 100207 S2.0P-ST.CC-0005(Q) STC cs CS-12 100450 2CC195 COMPONENT COOLING OEMINERALIZEO WATER SUPPLY CHECK VALVE 205331-1 Component Cooling D1 3 c CK SELF 3 DIC c Active SC.RA-IS.ZZ-0007(0) CTC Q 290860

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 21 VALVE NO VALVE DESCRIPTION P + ID No P + ID Name *Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE [TEST FREQ) C.S. JUST. f R.O. JUST. f REL. REQ. f RECUR. TASK : TECH. POS.: COMMENTS 2CC208 2 CMPNT CLG REACT COOL PMP THERM BARR RTN HOR MOV BYP CHECK VLV 205331-3 Component Cooling 04 2 A/C CK SELF 0.75 c O/C Active 52.RA-15.ZZ-0002(0) CTC RF V-07 290712 52.0P-5T.CC-0005(0) CTO RF V-07 100450 52.RA-15.ZZ-0002(0) LJ 2YR 290712 2CC210 COMPONENT COOLING PRIMARY WATER SUPPLY CHECK VALVE 205331-1 Component Cooling 01 3 c CK SELF 3 O/C c Active 5C.RA-15.ZZ-0007(0) CTC 0 290859 2CC215 2 CMPNT CLG EXCESS LETDOWN HT EXCHG INLETAIR OPRD GLB VLV 205331-3 Component Cooling 01 2 A PL AIR 3 0 c Active 52.0P-5T.CC-0004(0) F5TC 0 100660 52.RA-15.ZZ-0002(0) LJ 18MO 290707 52.0P-5T.RPl-0004(0) PIT 2YR 100872 52.0P-5T. CC-0004(0) 5TC 0 100660 2CC317 2 CMPNT CLG CHGR SAF INJ PMP 21 HT EXCH SPLY CHECK VLV 205331-1 . Component Cooling 07 3 C CK SELF 1 0 0 Active 52.0P-5T.CC-0004(0) CTO 0 ) 100660 ' )

2CC320 2 CMPNT CLG CHGR SAF INJ PMP 22 HT EXCH SPLY CHECK VLV 205331-1 Component Cooling G6 3 C CK SELF 1 0 0 Active 52.0P-5T.CC-0004(0) CTO 0 100660

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 22 VALVE NO VALVE DESCRIPTION P + ID No P + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC [TEST TYPE [TEST FREQ.! C.S. JUST. : R.O. JUST. : REL. REQ.: RECUR. TASK iTECH. Pas.! COMMENTS 21CH13 21 CHL WTR PMP DISCH CKVL 205216-2 Chilled Water G9 3 c CK SELF 4 0 O/C Active

$2.0P-ST.CH-0001 (Q) CTC Q 100689

$2.0P-ST.CH-0001 (Q) CTO Q 100689 22CH13 22 CHL WTR PMP DISCH CKVL 205216-2 Chilled Water G7 3 c CK SELF 4 0 O/C Active S2.0P-ST.CH-0002(Q) CTC Q 100690 S2.0P-ST.CH-0002(Q) CTO Q 100690 2CH30 2 CHL WTR SPLY TO S PEN AREA CLRS AIR OPRD GLB VLV 205216-2 Chilled Water H11 3 B GB AIR 3 0 c Active S2.0P-ST.CH-0003(Q) FSTC Q 100448 S2.0P-ST.RPl-0004(Q) \ PIT 2YR 100872 S2.0P-ST.CH-0003(Q) STC Q 100448 2CH55 2 CHL WTR FRESH WTR SPLY HOR CKVL 205216-2 Chilled Water C3 3 c CK SELF 1 c c Active CTC Q 100448 2CH61 2 CHL WTR S PEN AREA CLRS TO PMP SUCT HOR CKVL 205216-2 Chilled Water F11 3 c CK SELF 3 0 c Active S2.0P-ST.CH-0003(Q) CTC Q \ \  : 100448 \

2CH74 2 CHL WTR AIR COND UNIT COIL OUTLET/RETURN LINE AIR OPRD 3WAY VLV 205216-2 Chilled Water 3 B 3WAY AIR 3 O/C 0 Active S2.0P-ST.CH-0003(Q) FSTO a 100448

52. OP-ST .CH-0003(0) STO Q 100448

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 23 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ) C.S. JUST. j R.O. JUST. i REL. REQ. j RECUR. TASK !TECH. POS.i COMMENTS 2CH143 2 CHL WTR EXPAN TK VENT SAF RLF VLV 205216-2 Chilled Water E3 3 c RV SELF 0.75 c OIC Active 5C.MD-PT.ZZ-0007(0) RV 5YR 290098 2CH151 2 CHL WTR SPLY TO S PEN AREA CLRS AIR OPRD GLB VLV 205216-2 Chilled Water H11 3 . B GB AIR 3 0 c Active 52.0P-5T.CH-0003(0) F5TC 0 100448 52.0P-5T.RPl-0004(0) [ PIT .2YR 100872 S2.0P,.5T.CH-0003(0) 5TC 0 100448 2CH168 2 CHL WTR EMERG AIR COND COIL OUTLET AIR OPRD GLB VLV 205216-2 Chilled Water D4 3 B GB AIR 1.5 0 0 Passive

": ~ - - - - - - - - - -- ------- -- - - -- -- ---------- - - - -- - - ----------. - - - - -- - --------- ------ -- - - - - - -- ---------- -: - --- -- - - ---------- -- - - - - - - - - ------------ - --- -- -- - - -- -- -- - -- -.

~ ~ ~

No inservice testing required for this component.

2CH216 2 CHL WTR EMERG CONT AIR COMP SPLY LINE AIR OPRD GLB VLV 205216-3 Chilled Water E1 3 B GB AIR 2 c 0 Active 52.0P-5T. CH-0003(0) F5TO i 0 100448 52.0P-5T.CH-0003(0) 5TO 0 100448 2CH220 2 CHL WTR EMERG CONT AIR COMP INTER CLR INLET VENT SAF RLF VLV 205216-3 Chilled Water E2 3 C RV SELF 0.75 c 0 Active 5C.MD-PT.ZZ-0007(0) RV 5YR 290100 2CH232 2 CHL WTR CHILLER CLR TO EMERG CONT AIR COMP CKVL 205216-3 Chilled Water E1 3 c CK SELF 2 c 0 Active 52.0P-5T.CH-0003(0) CTO 0  : 100448  :  :

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 24 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE!TEST FREQ.: C.S. JUST. : R.O. JUST.: REL. REQ.: RECUR. TASK !TECH. POs.i COMMENTS 2CH252 2 CHL WTR RAD MON ENCL SPLY LINE AIR OPRD GATE VLV 205216-2 Chilled Water H10 3 B GB AIR 1 0 c Active

• • 52:0P~s:.r.-i~Pi~i:ioa4*(a)"**-r*****;:;i-r******.******2:yR*-----,----------------**:**----------------,------------------------*1aa87£*----,-----------------,----------------------*******************----*----**********

S2.0P-ST.CH-0003(Q) STC Q 100448 2CH253 2 CHLWTR RAD MON ENCL SPLY LINE AIR OPRD GATE VLV 205216-2 Chilled Water H10 3 B GB AIR 1 0 c Active

~  ;

S2.0P-ST.RPl-0004(Q) i PIT 2YR 100872 S2.0P-ST. CH-0003(Q) STC Q 100448 2CH260 2 CHL WTR RAD MONITOR ENCL TO PMP SUCT HOR CKVL 205216-2 Chilled Water G10 3 c CK SELF 1 0 c Active S2.0P-ST.CH-0003(Q) CTC Q 100448 i i 21CS2 21 CONT SPRAY PMP DISCH MOV 205335-1 Containment Spray H6 2 A GT MO 8 c O/C Active S2.RA-IS.ZZ-0002(Q) LJ 18MO 290716 S2.0P-ST.RPl-0001 (Q) PIT 2YR 100208 S2. OP-ST. CS-0003(Q) STC Q 100658 S2.0P-ST.CS-0003(Q) STO Q 100658 22CS2 22 CONT SPRAY PMP DISCH MOV 205335-1 Containment Spray E6 2 A GT MO 8 c O/C Active S2.RA-IS.ZZ-0002(Q) LJ 18MO 290718 82.0P-ST.RPl-0001 (Q) PIT 2YR 100208 S2.0P-ST.CS-0003(Q) STC Q 100658 S2. OP-ST. CS-0003(Q) STO Q 100658

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 25 VALVE NO VALVE DESCRIPTION P+ ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK iTECH. POS.! COMMENTS 21CS4 21 CONT SPRAY PMP DISCH INBD CHECK VLV 20S33S-1 Containment Spray HB 2 c CK SELF B c O/C Active 82.0P-8T.C8-0005(Q) CTO RF V-09 100636 22CS4 22 CONT SPRAY PMP DISCH INBD CHECK VLV 20S33S-1 Containment Spray EB 2 c CK SELF B c O/C Active CTO RF V-09 ~00636 21CS5 21 CONT SPRAY PMP DISCH SAF RLF VLV 20S33S-1 Containment Spray G9 2 N/A RV SELF 0.7S c c Passive

;  ;  ; No inservice testing required for this component.

22CS5 22 CONT SPRAY PMP DISCH SAF RLF VLV 20S33S-1 Containment Spray EB 2 N/A RV SELF 0.7S c c Passive No inservice testing required for this component.

2CS12 2 CONT SPRAY ADDITIVE TANK VAC BREAKER 20S33S-1 Containment Spray cs 3 c RV SELF 1 c O/C Active 8C.MD-PM.C8-0002(Q) j RV 5Y 204787 2CS13 2 CONT SPRAY ADDITIVE TANK VAC BREAKER 20S33S-1 Containment Spray cs 3 c RV SELF 1 c 0 Active 8C.MD-PM.C8-0002(Q)  ! RV  ! 5YR  !  ! 204788 2CS14 2 CONT SPRAY ADDITIVE TANK OUTLET MOV 20S335-1 Containment Spray 87 3 B GT MO 3 0 0 Active 82.0P-8T.RPl-0001 (Q) PIT 2YR 100208 82.0P-8T .C8-0003(Q) 8TO Q 100658

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 26 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification 1 I I I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK !TECH. POS.! COMMENTS 2CS16 2 CONT SPRAY ADDITIVE TK OUTLET MOV 205335-1 Containment Spray D7 3 B GT MO 3 C 0 Active

~

52.0P-ST.RPl-0001 (0) ! PIT 2YR 100208 52.0P-ST.CS-0003(0) STO 0 100658 2CS17 2 CONT SPRAY ADDITIVE TK OUTLET MOV 205335-1 Containment Spray D7 3 B GT MO 3 c 0 Active 52.0P-ST.RPl-0001 (0) ! PIT 2YR 100208 52.0P-ST.CS-0003(0) STO 0 100658 21CS21 21 CONT SPRAY EDUCTOR SUPPLY CHECK VLV 205335-1 Containment Spray G6 3 c CK SELF 3 c O/C Active 52.0P-ST.CS-0001 (0) CTC 0 100664 52.0P-ST.CS-0001 (0) CTO 0 100664 22CS21 22 CONT SPRAY EDUCTOR SPRAY ADDITIVE INLET CHECK VLV 205335-1 Containment Spray F6 3 .c CK SELF 3 c O/C Active 52.0P-ST. CS-0002(0) CTC 0 100672

52. OP-ST. CS-0002(0) CTO 0 100672 2CS26 2 CONT SPRAY ADDITIVE TK SAF RLF VLV 205335-1 Containment Spray C4 3 c RV SELF 0.75 c O/C Active SC.MD-PT.ZZ-0007(0) RV 5YR 290106

TABLE.3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 27 VALVE NO VALVE DESCRIPTION P + JD No p + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPEhEsT FREQ.: C.S. JUST. ! R.O. JUST.! REL. REQ. RECUR. TASK !TECH. pos.! COMMENTS i 21CS36 21 CONT SPRAY RHR STOP MOV 205335-1 Containment Spray H9 2 B GT MO 8 c O/C Active S2.0P-ST.RPl-0003(0) PIT 2TR 100873 S2. OP-ST. CS-0004(0) STC cs CS-16 100453 S2. OP-ST .CS-0004(0) STO cs CS-16 100453 22CS36 22 CONT SPRAY RHR STOP MOV 205335-1 Containment Spray E9 2 B GT MO 8 c DIC Active S2.0P-ST.RPl-0003(0) PIT 2YR 100873 S2.0P-ST. CS-0004(0) STC cs f CS-16 100453 S2.0P-ST.CS-0004(0) STO cs i CS-16 100453 21CS48 21 CONT SPRAY PMP DISCH OUTBD CHECK VLV 205335-1 Containment Spray H9 2 A/C CK SELF 8 c O/C Active S2.RA-IS.ZZ-0002(0) CTC RF V-10 290717 S2. OP-ST. CS-0005(0) CTO RF V-10 100636 . '

S2.RA-IS.ZZ-0002(0) LJ 18MO 290717 22CS48 22 CONT SPRAY PMP DISCH OUTBD CHECK VLV 205335-1 Containment Spray E9 2 A/C CK SELF 8 t DIC Active S2.RA-IS.ZZ-0002(0) CTC RF V-10 290719 S2. OP-ST. CS-0005(0) CTO RF V-10 100636 S2.RA-IS.ZZ-0002(0) LJ. 18MO 290719 2CS900 2 CONT SPRAY TEST CONN GLB VLV 205335-1 Containment Spray G9 2 A GB MAN 0.375 c c Passive S2.RA-IS.ZZ-0002(0) LJ 18MO 290720

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 28 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I TEST PROC !TEST TYPE!TEST FREQ.! C.S. JUST. i R.O. JUST.! REL. REQ, ! RECUR. TASK !TECH. POS.! COMMENTS 2CS901 2 CONT SPRAY TEST CONN GLB VLV 205335-1 Containment Spray F9 2 A GB MAN 0.375 c c Passive

---

,------------------.------------------=-------------------:-------------------:------------------.-------------------------:------------------:-*----------------------------------------------------------*

S2.RA-IS.ZZ-0002(Q) LJ 18MO  ! 290721  !

2CS902 2 CONT SPRAY TEST LINE FILL GLB VLV 205335-1 Containment Spray GB 2 A GB MAN 0.375 c c Passive S2.RA-IS.ZZ-0002(Q) LJ 1BMO  !  ! ~90722 '

2CS903 2 CONT SPRAY TEST CONN GLB VLV 205335-1 Containment Spray FB 2 A GB MAN 0.375 c c Passive

- - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - - - - - - - - -. - - - - - - * - - - - - - - - - - -. - * - - - - - - * - - - - - - - - - ;- - - - - - - - -- -- - - - - - - - ;- - - - - - - - ~ - - - - - - - - - - ;- - - - - - - - - - - - - - - - - -; - - - - - - - - - - - - - - - - - - - - - - - - - ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

• No inservice testing required for this component.

2CV3 2 eve LTDOWN ORIFICE ISOLATION AIR OPRD GLB VLV 205328-2 Chemical and Volume Control Operation FB 2 A GB AIR 2 0 c Active S2.0P-ST.CVC-0006(Q) FSTC Q 100455 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290724 S2.0P-ST.RPl-0002(Q) PIT 2YR 100207 S2.0P-ST. CVC-0006(Q) STC Q 100455 2CV4 2 eve REGEN HT EXCHG OUT TO LET DOWN HT EXCHG AIR OPRD GLB VLV 205328-2 Chemical and Volume Control Operation F9 2 A GB AIR 2 0 c Active S2.0P-ST.CVC-0006(Q) FSTC Q 100455 S2 .RA-IS .ZZ-0002(Q) LJ 18MO 290725 S2. OP-ST .RPl-0002(Q) PIT 2YR 100207 S2.0P-ST.CVC-0006(Q) STC Q 100455

• TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT

• UNIT 2 Page 29 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety* Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ) C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK ! TECH. POS.! COMMENTS 2CV5 2 eve LET DOWN ORIFICE ISOLATION AIR OPRD GLB VLV 205328-2 Chemical and Volume Control Operation F9 2 A GB AIR 2 O C Active 82.0P-ST.CVC-0006(0) FSTC o 100455 S2.RA-IS.ZZ-0002(0) LJ 18MO 290726 S2.0P-ST.RPl-0002(0) PIT 2YR 100207 S2.0P-ST. CVC-0006(0) STC o 100455 2CV6 2 eve REGEN HT EXCHG TO LET DOWN HT EXCHG LINE SAF RLF VLV 205328-2 Chemical and Volume Control Operation G9 2 C RV SELF 2 c 0/C Active

---

.------------------.------------------;-------------------;-------------------;-----------------.-------------------------:------------------7-------------------------------------------------------------

SC.MD-PT.ZZ-0007(0) RV 5YR  ! 290108 i 2CV7 2'CVC REGEN HT EXCHG TO LET DOWN HT EXCHG STOP AIR OPRD GLB VLV 205328-2 Chemical and Volume Control Operation GB *2 A PL AIR 2 o c Active S2.0P-ST.CVC-0007(0) ' FSTC ' CS ' CS-17 100456 S2.RA-IS.ZZ-0002(0) LJ 18MO 290727 S2.0P-ST.RPl-0003(0) PIT 2YR 100873 S2.0P-ST.CVC-0007(0) STC CS CS-17 100456 2CV40 . 2 eve VOLUME CONTROL TK OUTLET STOP MOV 205328-1 Chemical and Volume Control Operation E9 2 B GT MO 4 0 c Active S2.0P-ST.RPl-0003(0) ! .PIT 2YR 100873 S2.0P-ST.CVC-0007(0) ! STC CS  ; CS-18 100456 2CV41 2 eve VOLUME CONTROL TK OUTLET LINE OUTBD GATE MOV 205328-1 Chemical and Volume Control Operation D9 2 B GT MO 4 0 c Active 82.0P-ST.RPl-0003(0) PIT 2YR 100873 S2. OP-ST. CVC-0007 (0) STC cs CS-18 100456

TABLE 3-2 -VALVE TEST TABLE

• 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 30 VALVE NO VALVE DESCRIPTION P + ID No P + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ_! C.S. JUST. ! R.O. JUST.! REL. REQ. ! RECUR. TASK !TECH. POs.! COMMENTS 2CV42 2 eve VOLUME CONTROL TK OUTLET TO CHG PMP HEADER CHECK VLV 20S328-1 Chemical and Volume Control Operation D9 2 c CK SELF 4 0 0 Passive No inservice testing required for this component.

2CV43 2 eve CHG SAFETY INJ PMP SUCT HEADER SAF RLF VLV 20S328-2 Chemical and Volume Control Operation E2 2 c RV SELF 0.75 c O/C Active SC.MD-PT.ZZ-0007(0) RV SYR 290110 2CV47 2 eve CHG SAFETY INJ PMP 21 DISCH CHECK VLV 20S328-2 Chemical and Volume Control Operation DS 2 c CK SELF 4 c O/C Active

---

.------------------;------------------;------------------;------.------------;-----------------.-------------------------;-----------------7------------------------------------------------------------*

82.0P-ST.CVC-0003(0) CTC 0 100676 82.0P-ST.SJ-0016(0) CTO RF V-11 101048 82.0P-ST .CVC-0003(0) PS 0 100676 2CV52 2 eve CHG SAFETY INJ PMP 22 DISCH CHECK VLV 20S328-2 Chemical and Volume Control Operation cs 2 c CK SELF 4. c DIC Active

- - - - - - -- - - - - - - - - - - - - - - - - -- - - - - -- - - - - - - - - - -. - - - - - - - - - - - - - - - - - -. - - - - - - - - - - - - - - - - - - ; - - - - - - - - - - - - - - - - - - ; - - - - - - - - - - - - - - - - - - ; - - - - - - - - - - - - - - - - -. - - - - - - - - - - - - - - - - - - - - - - - ~ - ; - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ***

82.0P-ST.CVC-0004(0) j CTC 0 j 100677 52.0P-ST.SJ-0016(0) CTO RF V-11 101048 s2.0P-sr:cvc-0004co> PS o 100677 2CV63 2 eve CHG SAFETY INJ PMP 23 DISCH CHECK VLV 20S328-2 Chemical and Volume Control Operation AS 2 c CK. SELF 3 0 0 Active 82.0P-ST.CVC-0005(0) j CTO 0  ;  : 100678  :

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 31 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I o TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK i TECH. POS.! COMMENTS 2CV68 2 eve CHG SAFETY INJ TO REGEN HT EXCHG STOP GATE MOV 20532B-2 Chemical and Volume Control Operation DB 2 A GT MO 3 0 O/C Active

~. ~ - - - - -- -- - - -- - - - - . - - - --- - - - ------ ---. -------------------------.- -----------------: ------------ ---------- - - -- - ----- -- -- ---- -- -- -- -- -- - - -- - - -- - - .

~

S2.'RA-IS.ZZ-0002(Q) LJ 18MO 290811 S2.0P-ST.RPl-0003(Q) i PIT 2YR 100873 S2.0P-ST.CVC-0007(Q) i STC . cs CS-19 100456 2CV69 2 eve CHG SAFETY INJ TO REGEN HT EXCHG STOP GATE VLV 20532B-2 Chemical and Volume Control Operation DB 2 A GT MO 3 0 O/C Active S2.RA-IS.ZZ-0002(Q) LJ 18MO 290812 i  !

S2.0P-ST.RPl-0003(Q) i PIT 2YR 100873 S2.0P-ST.CVC-0007(Q)  ! STC cs CS-19 100456 2CV71 2 eve CHG SAFETY INJ TO REGEN HT EXCH INLET AIR OPRD GLB VLV 20532B-2 Chemical and Volume Control Operation Cl 2 B GB AIR 3 0 0 Passive

~ - - - - - -- - - -- ---- --. - ------------- - - ---------.- ---------- ----- --

-- - - - - - - - - - - ---- -- - - - ------------- - --- - - -- -- - --- -- -- ---- - --- .

No inservice testing required for this component.v 2CV74 2 eve CHG SAFETY INJ TO REGEN HT EXCHG INLET CHECK VLV 20532B-2 Chemical and Volume Control Operation EB 2 A/C CK SELF 3 0 O/C Active S2.RA-IS.ZZ-0002(Q) CTC RF V-12 290813 S2.0P-ST.CVC-0006(Q)  ! CTO Q 100455 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290813 2CV75 2 eve REGEN HT EXCHG OUT CHG LINE TO PZR AUX SPRAY AIR OPRD VLV 20532B-2 Chemical and Volume Control Operation E10 1 B GB AIR 2 c O/C Active S2.0P-ST.CVC-0007(Q) FSTC cs CS-44 100456 S2.0P-ST.RPl-0002(Q) PIT 2YR 100207 S2. OP-ST. CVC-0007 (Q) STC cs CS-44 100456 S2. OP-ST. CVC-0007 (Q) STO cs CS-44 100456

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 32 VALVE NO VALVE DESCRIPTION P+ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.: C.S. JUST. j. R.O. JUST. j REL. REQ. j RECUR. TASK j TECH. POS.j COMMENTS 2CV76 2 eve REGEN HT EXCHG CHG LINE TO PZR AUX SPRAY CHECK VLV 205328-2 Chemical and Volume Control Operation E10 1 C CK SELF 2 C O Active S2:0P-ST.CVC-0007(0) j CTO CS i CS-13 100456 2CV77 2 eve REGENERATIVE HT EXCHG OUTLET ISOLATION AIR OPRD GLB VLV 205328-2 Chemical and Volume Control Operation E10 1 B GB AIR 3 C/O 0 Active

~- -; ~

S2.0P-ST. CVC-0006(0) FSTO 0 100455 S2.0P-ST.RPl-0002(0) ! PIT 2YR 100207 S2.0P-ST.CVC-0006(0) ! STO 0 100455 2CV78 2 eve REGEN HT EXCHG TO REACT COOL 23 COLD LEG OUTBD CHECK VLV 205328-2 Chemical and Volume Control Operation E11 1 C CK SELF 3 0 0 Active S2.0P-ST.CVC-0006(0) ! CTO 0 100455 2CV79 2 eve REGEN HT EXCHG TO REACT COOL 24 COLD LEG AIR OPRD GLB VLV 205328-2 Chemical and Volume Control Operation E10 1 B GB AIR 3 O/C 0 Active S2. OP-ST. CVC-0006(0) FSTO 0 100455 S2.0P-ST.RPl-0002(0)  ! PIT 2YR 100207 S2.0P-ST.CVC-0006(0). f STO 0 100455 2CV80 2 eve REGEN HT EXCHG TO REACT COOL 24 COLD LEG LINE CHECK VLV 205328-2 Chemical and Volume Control Operation E11 1 c CK SELF 3 c 0 Active

~

S2.0P-ST.CVC-0006(0) \ CTO 0 i i 100455 i  :

21CV99 21 eve RCP SEAL WTR INJ SUPPLy CHECK VLV 205328-3 Chemical and Volume Control Operation F3 2 A/C CK SELF 2 0 c Active S2.RA-IS.ZZ-0002(0) CTC RF V-13 290731 S2.RA-IS.ZZ-0002(0) LJ 18MO 290731

TABLE 3 VALVE TEST TABLE.

10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 33 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREa.! C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK !TECH. POs.i COMMENTS 22CV99 22 eve RCP SEAL WTR INJ SUPPLY LINE CHECK VLV 205328-3 Chemical and Volume Control Operation F3 2 A/C CK SELF 2 0 c Active S2.RA-IS.ZZ-0002(Q) CTC RF V-13 290732 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290732 23CV99 23 eve RCP SEAL WTR INJ SUPPLY LINE CHECK VLV 205328-3 Chemical and Volume Control Operation C3 2 A/C CK SELF 2 0 c Active S2.RA-IS.ZZ-0002(Q) CTC RF V-13 290733 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290733 24CV99 24 eve RCP SEAL WTR INJ SUPPLy LINE CHECK VLV 205328-3 Chemical and Volume Control Operation 83 2 A/C CK SELF 2 0 c Active S2.RA-IS.ZZ-0002(Q) CTC RF V-13 290734 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290734 2CV115 2 eve RCP SEAL WTR INJ RETURN HEADER TO PZR RLF TK SAF RLF VLV 205328-3 Chemical an(1 Volume Control Operation C1 2 c RV SELF 2 c O/C Active SC.MD-PT.ZZ-0007 (Q) RV 5YR 202136 2CV116 2 eve RCP SEAL WTR RET HOR STOP GATE MOV 205328-2 Chemical and Volume Control Operation HS 2 A , GT MO 4 0 c Active S2.RA-IS.ZZ-0002(Q) LJ i 18MO i i 290728 '  !

S2.0P-ST.RPl-0003(Q)  : PIT 2YR 100873 S2.0P-ST.CVC-0007(Q)  ! STC CS CS-20 100456 2CV135 2 eve CHG SAFETY INJ PMP 21 TO SEAL WTR HT EXCHG ISLN CHECK VLV 205328-2 Chemical and Volume Control Operation E4 2 C CK SELF 2 c 0 Active S2.0P-ST.CVC-0003(Q) : CTO .: Q 100676

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 34 VALVE NO VALVE DESCRIPTION P+ ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! RO. JUST.! REL. REQ. ! RECUR. TASK !TECH. pos.! COMMENTS 2CV137 2 eve CHG SAFETY INJ PMP 22 TO SEAL WTR HT EXCHG LINE CHECK VLV 205328-2 Chemical and Volume Control Operation D4 2 C CK SELF 2 c O Active S2.0P-ST.CVC-0004(Q) ! CTO Q 100677 2CV139 2 eve CHG SAFETY INJ PMPS TO SEAL WTR HT EXCHG LINE STOP MOV 205328-2 Chemical and Volume Control Operation E3 2 B GB MO 2 0 O/C Active S2.0P-5T.RPl-0001(Q) ' PIT 2YR 100208 '

52.0P-5T.CVC-0006(Q)  ! STC Q 100455 52.0P-5T.CVC-0006(Q)  ! 5TO Q 100455 2CV140 2 eve CHG SAFETY INJ PMPS TO SEAL WTR HT EXCHG LINE STOP MOV 205328-2 Chemical and Volume Control Operation E3 2 B GB MO 2 0 O/C Active 52.0P-ST.RPl-0001 (Q) PIT 2YR 100208 S2.0P-ST.CVC-0006(Q) i 5TC Q 100455 52.0P-5T.CVC-0006(Q) i 5TO Q 100455 2CV141 2 eve RECIP CHG SAFETY INJ PMP 23 DISCH LINE SAF RLF VLV 205328-2 Chemical and Volume Control Operation A5 2 C RV SELF 0.75 c 0/C Active

~ ~

5C.MD-PT.ZZ-0007(Q) RV 5YR 290112  ! i 21CV154 21 eve BA TRANS PMP DISCH CHECK VLV 205328-1 Chemical and Volume Control Operation F1 2 c CK SELF 2 c O/C Active 52.0P-5T.CVC-0001 (Q) CTC Q 100687 52.0P-5T.CVC-0001 (Q) CTO Q 100687

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 35 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

• I I I t I I I TEST PROC !TEST TYPE!TEST FREQ.! C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK !TECH. POS.! COMMENTS 22CV154 22 eve BA TRANSFER PUMP DISCH CHECK VLV 205328-1 Chemical and Volume Control Operation F3 2 c CK SELF 2 c O/C Active S2.0P-ST.CVC-0002(0) i CTC 0 100688 52.0P-ST.CVC-0002(0) i CTO 0 100688 21CV160 21 eve BORIC ACID TK INLET AIR OPRD GLB VLV 205328-1 Chemical and Volume Control G2 2 B GB AIR 2 0 c Active S2.0P-ST.CVC-0006(0) FSTC 0 100455 82.0P-ST.RPl-0001 (0)  ! PIT 2YR 100208 S2.0P-ST.CVC-0006(0)  ! STC 0 100455 22CV160 22 eve BORIC ACID TK INLET AIR OPRD GLB VLV 205328-1 Chemical and Volume Control G3 2 B GB AIR 2 0 c Active S2.0P-ST. CVC-0006(0) FSTC 0 100455 82.0P-ST.RPl-0001 (0) [ PIT 2YR 100208 S2.0P-ST.CVC-0006(0) [ STC 0 100455 *'

2CV175 2 eve BA TRANSFER LINE STOP MOV 205328-1

• Chemical and Volume Control Operation F8 2 B GB MO 2 c 0 Active 82.0P-ST.RPl-0001 (0) j PIT 2YR 100208 S2.0P-ST.CVC-0006(0) j STO 0 100455 2CV176 2 eve BA TRANS VOLUME CONTROL TK BY PASS LINE CHECK VLV 205328-1 Chemical and Volume Control Operation F8 2 c CK SELF 2 c 0 Active 82.0P-ST.CVC-0007(0) ! CTO cs CS-21 100456 '

TABLE 3.2 - VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 36 VALVE NO VALVE DESCRIPTION P + ID No p + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREa.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK !TECH. POs.! COMMENTS 2CV241 2 eve VOLUME CONTROL TK TO HOLD UP TANKS SAF RLF VLV 205328-1 Chemical and Volume Control Operation H10 2 c RV SELF 3 c 0 Active SC.MD-PT.ZZ-0007(0) RV 5YR 203981 2CV274 2 eve REGEN HT EXCHG CHG LINE TO REACT COOL LOOP 23 INBD CHECK VLV 205328-2 Chemical and Volume Control Operation E10 1 C CK SELF 3 0 0 Active S2.0P-ST.CVC-0006(Q) ! CTO a . .

100455 2CV275 2 eve REGEN HT EXCHG TO REACT COOL 24 COLD LEG INBD CHECK VLV 205328-2 Chemical and Volume Control Operation E10 1 C CK SELF 3 c 0 Active S2.0P-ST.CVC-0006(Q)  ! CTO a 100455 2CV284 2 eve RCP SEAL WTR INJ RETURN HEADER STOP GATE MOV 205328-3 Chemical and Volume Control Operation C2 2 A GT MO 4 0 c Active S2.RA-IS.ZZ-0002(Q) LJ 18MO 290729 S2.0P,.ST.RPl-0002(Q) i PIT 2YR 100207 S2.0P-ST.CVC-0007(Q) i STC cs CS-20 100456 2CV296 2 eve RCP SEAL WTR INJ RETURN STOP MOV 2CV296 RECIRC LINE CKVL 205328-3 Chemical and Volume Control Operation C2 2 A/C CK SELF 0.75 c O/C Active S2.RA-IS.ZZ-0002(Q)  ! CTC RF  ; V-14  ! 290730 i S2.0P-ST.CVC-0007(Q) i CTO RF V-14 100456 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290730 21DA6A 21 DIESEL GEN DIESEL STARTING AIR RECEIVER INLET CHECK VLV AUGMENTED 205241-4 Diesel Engine Auxiliaries D4 N AIC CK SELF 0.75 O/C c Active

82. OP-ST .DG-0009(0) CTC Q [ i 100449 l

TABLE 3-2 -VALVE TEST TABLE, 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 37 VALVE NO VALVE DESCRIPTION P+ ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I I TEST PROC !TEST TYPE !TEST FREO.i C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK !TECH. POS.! COMMENTS 22DA6A 22 DIESEL GEN DIESEL STARTING AIR RECEIVER INLET CHECK VLV AUGMENTED 205241-4 Diesel Engine Auxiliaries D5 N AJC CK SELF 0.75 DIC c Active S2.0P-ST.DG-0009(Q) CTC Q 100449 21DA6B 21 DIESEL GEN DIESEL STARTING AIR RECEIVER INLET CHECK VLV AUGMENTED 205241-5 Diesel Engine Auxiliaries D4 N AJC CK SELF 0.75 DIC c Active

-  ;- ~

CTC Q 101138 22DA6B 22 DIESEL GEN DIESEL STARTING AIR RECEIVER INLET CHECK VLV AUGMENTED 205241-5 Diesel Engine Auxiliaries D5 N AJC CK SELF 0.75 c c Active S2.DP-ST.DG-001 O(Q) CTC Q 101138 21DA6C 21 DIESEL GEN DIESEL STARTING AIR RECEIVER INLET CHECK VLV AUGMENTED 205241-6 Diesel Engine Auxiliaries D4 N AJC CK SELF 0.75 DIC c Active S2.DP-ST.DG-0011(Q) CTC Q  ! 101139  !

22DA6C 22 DIESEL GEN DIESEL STARTING AIR RECEIVER INLET CHECK VLV AUGMENTED 205241-6 Diesel Engine Auxiliaries D5 N AJC CK SELF 0.75 DIC c Active S2.DP-ST.DG-0011 (Q) CTC Q 101139 21DA10A 21 DIESEL GEN DIESEL STARTING AIR RECEIVER SAF RLF VLV AUGMENTED 205241-4 Diesel Engine Auxiliaries E4 N C RV SELF 0.75 c DIC Active

-*sc:M-o~F>=r-.:zz~-ooo7(a)--***.--*-**-Rv--*---r*--*-5:yR**----,---**--*-****---*--------------*-****,-*---*-------*-*-.----*--2901-1-4-------:------------------;**-**--*---------------------- *--------*--------*-*--------*

22DA10A 22 DIESEL GEN DIESEL STARTING AIR RECEIVER SAFETY RELIEF VLV AUGMENTED 205241-4 Diesel Engine Auxiliaries E5 N c RV SELF 0.75 c OIC Active SC:MD-PT.ZZ-0007(0) RV SYR 290120

TABLE 3 VALVE TEST TABLE.

10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 38 VALVE NO VALVE DESCRIPTION P+ ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.: C.S. JUST. : RO. JUST. : REL. REQ.: RECUR. TASK iTECH. POS.: COMMENTS 21DA10B 21 DIESEL GEN DIESEL STARTING AIR RECEIVER SAF RLF VLV AUGMENTED 20S241-S Diesel Engine Auxiliaries E4 N C RV SELF 0. 7S C O/C Active SC.MD-PT.ZZ-0007(0) RV 5YR 290116 22DA10B 22 DIESEL GEN DIESEL STARTING AIR RECEIVER SAFETY RELIEF VLV AUGMENTED 20S241-S Diesel Engine Auxiliaries ES N C RV SELF 0.7S c O/C Active

-*----------------------------------------------------------i*---------------------------------------------------------------------------------------------------------------------------------------------------------------------------------

SC.MD-PT.ZZ-0007(0) RV 5YR 290122 21DA10C 21 DIESEL GEN DIESEL STARTING AIR RECEIVER SAF RLF VLV AUGMENTED 20S241-6 Diesel Engine Auxiliaries E4 N C RV SELF 0.7S c O/C Active SC.MD-PT.ZZ-0007(0) RV 5YR 290118 22DA10C* 22 DIESEL GEN DIESEL STARTING AIR RECEIVER SAFETY RELIEF VLV AUGMENTED 20S241-6 Diesel Engine Auxiliaries ES N C RV SELF 0.7S c O/C Active SC.MD-PT.ZZ-0007(0) RV 5YR 290124 21DA13A 2A DIESEL GEN STARTING AIR MOTOR SV (SV878) AUGMENTED 20S241-4 Diesel Engine Auxiliaries FS 'N B GB SOL 2 c 0 Active-

• • 52:ap~si.i>C3~0-oosca>-*--------*r:50-*--*-- -----cs_______ r____ cs~22-----* -*- ------------- -------------------------100345_________________________ -*-------------*-----*---*-*-**--**-*----*---*-----*--------

s2.oP-sT.oG-0001co> sTo o V-37 101295 22DA13A 2A DIESEL GEN STARTING AIR MOTOR SV (SV877) AUGMENTED 20S241-4 Diesel Engine Auxiliaries FS N B GB SOL 2 c 0 Active S2. OP-ST .DG-0006(0) FSO cs CS-22 100345 82.0P-ST.DG-0001 (0) STO o V-37 101297

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 39 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification 1 I I I I I I TEST PROC !TEST TYPE !TEST FREQ.: C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK !TECH. Pas.: COMMENTS 21DA13B 2B DIESEL GEN STARTING AIR MOTOR SV (SV884) AUGMENTED 205241~5 Diesel Engine Auxiliaries F5 N B GB SOL 2 c 0 Active S2.0P-ST.DG-0007(0) FSO cs i CS-22 100351 S2.0P-ST.DG-0002(0) STO o V-37 101298 22DA13B 2B DIESEL GEN STARTING AIR MOTOR SV (SV883) AUGMENTED 205241-5 Diesel Engine Auxiliaries F5 N B GB SOL 2 c 0 Active S2.0P-ST.DG-0007 (0) FSO cs i CS-22 100351 S2.0P-ST.DG-0002(0) STO o V-37 101299 21DA13C 2C DIESEL GEN STARTING AIR MOTOR SV (SV890) AUGMENTED 205241-6 Diesel Engine Auxiliaries F5 N B GB SOL 2 c 0 Active S2. OP-ST .DG-0008(0) FSO cs i CS-22 100346 S2.0P-ST.DG-0003(0) STO o V-37 101300 22DA13C 2C DIESEL GEN STARTING AIR MOTOR SV (SV889) AUGMENTED 205241-6 Diesel Engine Auxiliaries F5 N B GB SOL 2 c 0 Active S2.0P-ST.DG-0008(0) FSO cs i CS-22 100346 S2.0P-ST."DG-0003(0) STO o V-37 101301 21DA14A 2A DIESEL GEN STARTING AIR MOTOR SV (SV879) AUGMENTED 205241-4 Diesel Engine Auxiliaries F4 N B GB SOL 2 c 0 Active S2.0P-ST.DG-0006(0) FSO cs CS-22 100345 S2.0P-ST.DG-0001 (0) STO Q V-37 101296

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 40 VALVE NO VALVE DESCRIPTION P + ID No P + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification 1

• I I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK iTECH. POS.! COMMENTS 22DA14A 2A DIESEL GEN STARTING AIR MOTOR SV (SVBBO) AUGMENTED 205241-4 Diesel Engine Auxiliaries F5 N B GB SOL 2 c 0 Active S2.0P-ST.DG-0006(Q) FSO cs ! CS-22 100345 S2.0P-ST.DG-0001 (Q) STO Q V-37 100422 21DA14B 2B DIESEL GEN STARTING AIR MOTOR SV (SV885) AUGMENTED 205241-5 Diesel Engine Auxiliaries F4 N B GB SOL 2 c 0 Active S2.0P-ST.DG-0007(Q) FSO cs : CS-22 100351 S2.0P-ST.DG-0002(Q) STO Q V-37 101298 22DA148 28 DIESEL GEN STARTING AIR MOTOR SV (SV886) AUGMENTED 205241-5 Diesel Engine Auxiliaries F5 N B GB SOL 2 c 0 Active S2.0P-ST.DG-0007(Q) FSO cs  ! CS-22 100351 S2.0P-ST.DG-0002(Q) STO Q V-37 101299 21DA14C 2C DIESEL GEN STARTING AIR MOTOR SV (SV891) AUGMENTED 205241-6 Diesel Engine Auxiliaries F4 N B GB SOL 2 c 0 Active S2.0P-ST.DG-0008(Q) FSO cs ! CS-22 100346 S2.0P-ST.DG-0003(Q) STO Q V-37 101300 22DA14C 2C DIESEL GEN STARTING AIR MOTOR SV (SV892) AUGMENTED 205241-6 Diesel Engine Auxiliaries F5 N B GB SOL 2 c 0 Active S2.0P-ST.DG-0008(Q) FSO cs  ! CS-22 100346 S2.0P-ST.DG-0003(Q) STO Q V-37 101301 2DA17A 2 DIESEL GEN DIESEL TURBO BOOST AIR COMPRESSOR OUTLET CHECK VLV AUGMENTED 205241-4 Diesel Engine Auxiliaries G1 N A/C CK SELF 0.75 DIC c Active S2.0P-ST.DG-0009(Q) ! CTC i Q j 100449  !

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 41 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.: C.S. JUST. : R.O. JUST. : REL. REQ. : RECUR. TASK : TECH. POS.: COMMENTS 2DA17B 2 DIESEL GEN DIESEL TURBO BOOST AIR COMPRESSOR OUTLET CHECK VLV AUGMENTED 205241-5 Diesel Engine Auxiliaries G1 N AIC CK SELF 0.75 O/C C Active 82.0P-ST.DG-0010(0) CTC 0 101138 2DA17C 2 DIESEL GEN DIESEL TURBO BOOST AIR COMPRESSOR OUTLET CHECK VLV AUGMENTED 205241-6 Diesel Engine Auxiliaries G1 N AIC CK SELF 0.75 O/C c Active 82.0P-ST.DG-0011 (0) CTC i 0 i 101139 21DA19A 21 DIESEL GEN DIESEL TURBO BOOST AIR RECEIVER SAFETY RELIEF VLV AUGMENTED 205241-4 Diesel Engine Auxiliaries G2 N C RV SELF 0.75 c O/C Active

---

*-:*-----------------.------------------;-------------------;-------------------:------------------.-------------------------:------------------7------------------------------------------------------------*

SC.MD-PT.ZZ-0007(0) RV SYR 290126 22DA19A 22 DIESEL GEN DIESEL TURBO BOOST AIR RECEIVER SAFETY RELIEF VLV AUGMENTED 205241-4 Diesel Engine Auxiliaries G3 N C RV SELF 0. 75 C OIC Active

~ ~ ~

SC.MD-PT.ZZ-0007(0) RV SYR 290132 21DA19B 21 DIESEL GEN DIESEL TURBO BOOST AIR RECEIVER SAFETY RELIEF VLV AUGMENTED 205241-5 Diesel Engine Auxiliaries G2 N c RV SELF 0.75 c O/C Active SC.MD-PT,ZZ-0007(0) RV SYR 290128 22DA19B 22 DIESEL GEN DIESEL TURBO BOOST AIR RECEIVER SAFETY RELIEF VLV AUGMENTED 205241-5 Diesel Engine Auxiliaries G3 N C RV SELF 0.75 c O/C Active SC.MD-PT.ZZ-0007(0) RV SYR ' ' 290134  !  :

21DA19C 21 DIESEL GEN DIESEL TURBO BOOST AIR RECEIVER SAFETY RELIEF VLV AUGMENTED 205241-6 Diesel Engine Auxiliaries G2 N c RV SELF 0.75 c O/C Active SC.MD-PT.ZZ-0007(0) RV SYR 290130

TABLE 3 VALVE TEST .TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 42 .

VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST.! REL. REQ. ! RECUR. TASK !TECH. pos.! COMMENTS 22DA19C 22 DIESEL GEN DIESEL TURBO BOOST AIR RECEIVER SAFETY RELIEF VLV AUGMENTED 205241-6 Diesel Engine Auxiliaries G3 N C RV SELF 0. 75 C O/C Active SC.MD-PT.ZZ-0007(0) RV 5YR ' 290136 '

2DA36A 2 DIESEL GEN DIESEL ENGINE LUBE OIL HEATER OUTLET CHECK VLV 205241-4 Diesel Engine Auxiliaries C9 N C CK SELF 4 0 0 Passive

'  :'  :'  :' ~

No inservice testing required for this component.

2DA36B 2 DIESEL GEN DIESEL ENGINE LUBE OIL HEATER OUTLET CHECK VLV 205241-5 Diesel Engine Auxiliaries C9 N C CK SELF 4 0 0 Passive No inservice testing required for this component.

2DA36C 2 DIESEL GEN DIESEL ENGINE LUBE OIL HEATER OUTLET CHECK VLV 205241-6 Diesel Engine Auxiliaries C9 N c CK SELF 4 0 0 Passive No inservice testing required for this component.

21DF38 21 FUEL OIL DIESEL FUEL OIL TRANSFER PUMP OUTLET CHECK VLV AUGMENTED 205249-3 Fuel Oil A6 N c CK SELF 2 c 0 Active 52.0P-ST.OG-0004(0) CTO 0 100514 22DF38 22 FUEL OIL DIESEL FUEL OIL TRANSFER PUMP OUTLET CHECK VLV AUGMENTED 205249-3 Fuel Oil 84 N c CK SELF 2 c 0 Active 52.0P-ST.DG-0005(0) CTO i 0 i i 101126 21DF61 21 FUEL OIL DIESEL FUEL OIL DAY TANK NO 2A INLET CHECK VLV AUGMENTED 205249-3 ~00 m N C CK SELF 2 c 0 Active S2. OP-ST. DG-0004(0) CTO 0 100514

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 43 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position

• Position Classification I I I l I I I TEST PROC iTEST TYPE iTEST FREO.i C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK iTECH. POS.i COMMENTS 22DF61 22 FUEL OIL DIESEL FUEL OIL DAY TANK N0.2A INLET CHECK VLV AUGMENTED 205249-3 Fuel Oil H4 N C CK SELF 2 C 0 Active S2.0P-ST.DG-0005(Q) CTO Q 101126 21DF62 21 FUEL OIL DIESEL FUEL OIL DAY TANK N0.2B INLET CHECK VLV AUGMENTED 205249-3 Fuel Oil GS N C CK SELF 2 c 0 Active

~

S2.0P-ST.DG-0004(Q) CTO Q 100514 22DF62 22 FUEL OIL DIESEL FUEL OIL DAY TANK N0.2B INLET CHECK VLV AUGMENTED 205249-3 Fuel Oil F5 N C CK SELF 2 c 0 Active CTO Q 101126 21DF63 21 FUEL OIL DIESEL FUEL OIL DAY TANK N0.2C INLET CHECK VLV AUGMENTED 205249-3 Fuel Oil D5 N C CK SELF 2 c 0 Active S2.0P-ST. DG-0004(0) CTO Q  ;  !  ! 100514 22DF63 22 FUEL OIL DIESEL FUEL OIL DAY TANK N0.2C INLET CHECK VLV AUGMENTED 205249-3 Fuel Oil E5 N C CK SELF 2 c 0 Active S2.0P-ST ..OG-0005(Q) CTO Q 101126 2DR7 2 DEMINERALIZER WATER AUX FEEDWATER TANK INLET CHECK VALVE 205246-2 Demineralized Water - Restricted Areas D7 3 c CK SELF 6 O/C c Active CTC. Q 100665

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 44

========================================= ----~---------~----- ---_,

VALVE NO VALVE DESCRIPTION P+ ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

• I ' I I I '

TEST PROC :TEST TYPE !TEST FREQ.: C.S. JUST. i R.O. JUST. i REL. REQ.: RECUR. TASK iTECH. POS.i COMMENTS 2DR29 2 DEMIN WTR UNIT 1 TO CONTMT AIR OPRD GATE VLV 205246-2 Demineralized Water - Restricted Areas E4 2 A GT AIR 4 C C Active S2.0P-ST.ZZ-0003(0) FSTC 0  ! i 100665 82.RA-IS.ZZ-0002(0) LJ 18MO 290735 82.0P-ST.RPl-0004(0) PIT 2YR 100872 82.0P~ST.ZZ-0003(0) STC 0 100665 2DR30 2 DEMIN WTR REACT CONTMT INLET LINE CKVL 205246-2 Demineralized Water - Restricted Areas E3 2 AJC CK SELF 4 c O/C Active

~-

S2.RA-IS.ZZ-0002(Q) 1 CTC RF  ! V-34 290736 l ~

82.0P-ST.ZZ-0005(0) CTO RF V-34 101429 TP-6 82.RA-IS.ZZ-0002(0) LJ 18MO 290.736 2DR177 CONTAINMENT ISO VLV OVERPRESSURE PROTECTION RELIEF VALVE AUGMENTED 205246-2 Demineralized Water - Restricted Areas E3 N C RV SELF .5 c 0 Active SC.MD-PT.ZZ-0007(0) RV 5YR  ! i (later) DCP 2EC-3612, see PMCR 970320324 2FP147 2 FIRE PROT REAC CONTMT INLET AIR OPRD PLUG/CTL VLV 205222-2 *Fire Protection F5 2 A GT AIR 4 c c Active 82.0P-ST.ZZ-0003(0) FSTC 0 100665 82.RA-IS.ZZ-0002(0) LJ 18MO 290737 82.0P-ST.RPl-0004(0) PIT 2YR 100872 S2. OP-ST .ZZ-0003(0) STC 0 100665

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 45 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE :TEST FREQ.: C.S. JUST. [ R.O. JUST. j REL. REQ. j RECUR. TASK : TECH. POS.[ COMMENTS 2FP148 2 FIRE PROT REAC CONTMT INLET CHK VLV 205222-2 Fire Protection F4 2 AJC CK SELF 4 C O/C Active S2.RA-IS.ZZ-0002(0)  ! CTC RF  : V-34 290738  :

82.0P-ST.ZZ-0005(0) CTO RF V-34 101429 TP-6 82.RA-IS.ZZ-0002(0) LJ 18MO 290738 2FP153 CONTAINMENT ISO VLV OVERPRESSURE PROTECTION RELIEF VALVE AUGMENTED 205222-2 Fire Protection D3 N c RV SELF .75 c 0 Active SC.MD-PT.ZZ-0007(0) RV 5YR (later) Refer to PMCR 970602146.

21GB4 21 STM GEN ORN & BLOWN OUTLET AIR OPRO ISOL GLB VLV 205325-2 Steam Generator Drains and Blowdown H10 2 A GB AIR 3 0 c Active S2.0P-ST.MS-0001 (0) ! FSTC : 0 . .  ! . 100544 SC.RA-IS.GB-0004(0)_ LT 2YR 291145 S2.0P-ST.RPl-0004(0) PIT 2YR 100872 S2.0P-ST.MS-0001 (0) STC 0 100544 22GB4 22 STM GEN ORN & BLOWN STGEN OUTLET AIR OPRD STOP GLB VLV 205325-2 *Steam Generator Drains and Blowdown G10 2 A GB AIR 3 0 c Active S2.0P-ST.MS-0001 (0) FSTC 0 100544 SC.RA-IS.GB-0004(0) LT 2YR '291145 S2.0P-ST.RPl-0004(0) PIT 2YR 100872 S2.0P-ST.MS-0001 (0) STC 0 100544

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 46 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ) C.S. JUST. ! R.O. JUST. : REL. REQ.: RECUR. TASK j TECH. POS.: COMMENTS 23GB4 23 STM GEN ORN & BLOWN STGEN TO OUTLET AIR OPRD GLB VLV 205325-2 Steam Generator Drains and Blowdown G10 2 A GB AIR 3 0 c Active 82.0P-8T.M8-0001 (Q) F8TC Q 100544 8C.RA-18.GB-0004(Q) LT 2YR 291145 82.0P-8T.RPl-0004(Q) PIT 2YR 100872 82.0P-8T.M8-0001 (Q) 8TC Q 100544 24GB4 24 STM GEN ORN & BLOWN STGEN OUTLET A R OPRD GLB VLV 205325-2 Steam Generator Drains and Blowdown F10 2 A GB AIR 3 0 c Active 82.0P-8T.M8-0001 (Q) F8TC Q 100544 8C.RA-IS.GB-0004(Q) LT 2YR 291145 82.0P-8T.RPl-0004(Q) PIT 2YR 100872 82.0P-8T.M8-0001 (Q) 8TC Q 100544 21MS7 21 MN STM & TRB BY PASS STGEN ISLN VLV BODY DR HOR AIR OPRD ISLN V 205303-1 Main, Reheat, and Turbine Bypass Steam ES 2 B GB AIR 2 O/C c Active 82.0P-8T.M8-0001 (Q) F8TC Q 100544 82.0P-8T.RPl-0004(Q)  ! PIT 2YR 100872 82.0P-8T.M8-0001 (Q) 8TC Q 100544 22MS7 22 MN STM & TRB BY PASS STGEN ISLN VLV DR HOR AIR OPRD ISLN VALVE 205303-2 Main, Reheat, and Turbine Bypass Steam C6 2 B GB AIR 2 O/C c Active 82.0P-8T.M8-0001 (Q) F8TC Q 100544 82.0P-8T.RPl-0004(Q) PIT 2YR 100872 82.0P-8T.M8-0001 (Q) 8TC Q 100544

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 47 VALVE NO VALVE DESCRIPTION P+ ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC iTEST TYPE iTEST FREO.i C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK !TECH. POS.! COMMENTS 23MS7 23 MN STM & TRB BY PASS STM GEN ISOL VLV BODY AIR OPRD ORN VLV 205303-1 Main, Reheat, and Turbine Bypass Steam AS 2 B GB AIR 2 O/C c Active S2.0P-ST.MS-0001 (0) FSTC 0 100544 S2.0P-ST.RPl-0004(0)  ! PIT 2YR 100872 S2.0P-ST.MS-0001 (0) STC 0 100544 24MS7 24 MN STM & TRB BY PASS STGEN ISLN VLV BODY DR AIR OPRD ISLN VALVE 205303-2 Main, Reheat, and Turbine Bypass Steam F6 2 B GB AIR 2 O/C c Active S2.0P-ST.MS-0001(0) \ FSTC \ 0 . . . . 100544 .

S2.0P-ST.RPl-0004(0) i PIT 2YR 100872 S2.0P-ST.MS-0001 (0) STC 0 100544 21MS10 21 MN STM & TRB BY PASS POWER OPRO SAF RLF VLV 205303-1 Main, Reheat, and Turbine Bypass Steam G7 2 B GB AIR 6 c O/C Active S2. OP-ST .MS-0002(0) FSTC cs CS-24 100844 S2.0P-ST.RPl-0003(Q) PIT 2YR 100873 S2.0P-ST.MS-0002(0) STC cs CS-24 100844 S2.0P-ST ,MS-0002(0) STO cs CS-24 100844 22MS10 22 MN STM & TRB BY PASS STM GEN HOR AIR OPRD VENT VLV 205303-2 Main, Reheat, and Turbine Bypass Steam D6 2 B GB AIR 6 c O/C Active S2.0P-ST.MS-0002(0) FSTC cs CS-24 100844 S2.0P-ST.RPl-0003(Q) PIT 2YR 100873 S2. OP-ST. MS-0002(0) STC cs CS-24 100844 S2.0P-ST.MS-0002(Q) STO cs CS-24 100844

TABLE 3-2 -VALVE TEST. TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 48 VALVE NO VALVE DESCRIPTION P + ID No p + ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification I I I I I I TEST PROC !TESTTYPE!TEST FREQ) C.S. JUST. i R.O. JUST. i REL. REQ. ! RECUR. TASK !TECH. POS.!COMMENTS 23MS10 23 MN STM & TRB BY PASS AIR OPRD POWER RLF VLV 205303-1 Main, Reheat, and Turbine Bypass Steam C7 2 B GB AIR 6 c O/C Active S2.0P-ST.MS-0002(0) FSTC cs CS-24 100844 S2.0P-ST .RPl-0003(0) PIT 2YR 100873 S2. OP-ST .MS-0002(0) STC cs CS-24 100844 S2. OP-ST .MS-0002(0) STO cs CS-24 100844 24MS10 24 MN STM & TRB BY PASS NO 24 STGEN HOR AIR OPRD GLB VALVE 205303-2 Main, Reheat, and Turbine Bypass Steam G6 2 B GB AIR 6 c O/C Active S2.0P-ST.MS-0002(Q) FSTC cs CS-24 100844

82. OP-ST.RPl-0003(0) PIT 2YR 100873 S2. OP-ST .MS-0002(0) STC cs CS-24 100844 S2. OP-ST. MS-0002(0) STO cs CS-24 100844 21MS11 21 MN STM & TRB BY PASS STGEN SAF RLF VLV 205303-1 Main, Reheat, and Turbine Bypass Steam F3 2 c RV SELF 8 c O/C Active

---

:------------------:------------------.-------------------;------------------;------1----------;*------------------------.------------------:---------------------------------------*--------------------*

SC.MD-ST.MS-0001 (0) ! RV 5YR  :  : 290154 22MS11

• 22 MN STM & TRB BY PASS STGEN SAF RLF VLV 205303-2 Main, Reheat, and Turbine Bypass Steam D3 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001 (0) ! RV 5YR 290156 23MS11 23 MN STM & TRB BY PASS STM GEN SAF RLF VLV 23MS11 205303-1 Main, Reheat, and Turbine Bypass Steam C3 2 c RV SELF 8 c O/C Active RV 5YR 290158

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 49 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification I o I I I I I TEST PROC . !TEST TYPE !TEST FREQ.! C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK !TECH. POS.! COMMENTS 24MS11 24 MN STM & TRB BY PASS STGEN SAF RLF VALVE 205303-2 Main, Reheat, and Turbine Bypass Steam G3 2 c RV SELF 8 c O/C Active

"'. ~ ~

SC.MD-ST.MS-0001 (Q) i RV SYR 290160 21MS12 21 MN STM & TRB BY PASS STM GEN SAF RLF VLV 205303-1 Main, Reheat, and Turbine Bypass Steam F4 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001 (Q) i RV SYR 290162 22MS12 22 MN STM & TRB BY PASS STGEN SAF RLF VLV 205303-2 Main, Reheat, and Turbine Bypass Steam D4 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001(0) i RV  ! SYR 290164 i 23MS12 23 MN STM & TRB BY PASS STM GEN SAF RLF VLV 23MS12 205303-1 Main, Reheat, and Turbine Bypass Steam C4 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001 (Q) i RV SYR 290166 24MS12 24 MN STM & TRB BY PASS STM GEN SAF RLF VLV 205303-2 Main, Reheat, and Turbine Bypass Steam G4 2 c RV SELF 8 c O/C Active SC.MD-ST:MS-0001 (Q) i RV SYR 290168 21MS13 21 MN STM & TRB BY PASS STGEN SAF RLF VLV 205303-1 Main, Reheat, and Turbine Bypass Steam F5 2 c RV SELF 8 c O/C Active

~ - - -- - - - - -- - - - - -- -

------ -- -- -- - --- - -- - -- -- - - -- -- -- - - ------- - - - - -- - -- . - . - .. - .. - .

SC.MD-ST.MS-0001 (Q) ! RV i SYR  ; 290170 22MS13 22 MN STM & TRB BY PASS STGEN SAF RLF VLV 205303-2 Main, Reheat, and Turbine Bypass Steam D5 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001 (Q) i RV SYR 290172

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 50 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification I I I I I I TEST PROC . !TEST TYPE !TEST FREQ) C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK i TECH. POS.! COMMENTS 23MS13 23 MN STM & TRB BY PASS STM GEN SAF RLF VLV 23MS13 20S303-1 Main, Reheat, and Turbine Bypass Steam cs 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001 (Q) ! RV SYR 290174 24MS13 24 MN STM & TRB BY PASS STGEN SAFETY RELIEF VALVE 20S303-2 Main, Reheat, and Turbine Bypass Steam G4 2 c RV SELF 8 c O/C Active

- -- - -- - ----- -------- -- -- -- - ----- --- --- - - --. -- - --------- -- --- -. -- - - -- - -- - -- -- ----.- ------- -------- - - - ;- - - - - -- -- - ---------: ------- - - -- - - - -- -. ---------------- ---- - - - - - ;- -- - - - --- - -------- ~ ------------ ---- -- - - -- -- - - -- -- - - -- ----------------. ------ -- - .

SC.MD-ST.MS-0001 (Q) ! RV SYR 290176 21MS14 21 MN STM & TRB BY PASS STGEN SAF RLF VLV 20S303-1 Main, Reheat, and Turbine Bypass Steam F6 2 c RV SELF 8 c O/C Active

- - - - -- ---- --------- - - -- -- ----- ------. --- - - -- ------------- - - -. - - -- - ----- -- ------;- ---- -- - --- - - - -- - -  ;- - - . --- ------ ------.- --- - - -- - - - - - --- --. -------------- ---- - - - - -- - : - - - - - - - - -- - -. - ---~ ---------- - - - - -- - . -- - - - - -- -- - - -- -- -- - --- . - - . - . -----. -- ------.

SC.MD-ST.MS-0001 (Q) ! RV 5YR 290178 22MS14 22 MN STM & TRB BY PASS STGEN SAF RLF VLV 20S303-2 Main, Reheat, and Turbine Bypass Steam DS 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001 (Q) ! RV SYR 290180 23MS14 23 MN STM & TRB BY PASS *sTM GEN SAF RLF VLV 23MS14 20S303-1 Main, Reheat, and Turbine BJ'.pass Steam C6 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001 (Q)  ! RV SYR 290182 24MS14 24 MN STM & TRB BY PASS STGEN SAFETY RELIEF VALVE 20S303-2 Main, Reheat, and Turbine Bypass Steam GS 2 c RV SELF 8 c O/C Active

---

.------------------.------------------.--------- ---------;------------------;-----------------.-------------------------.------------------7--------------------------------------------------*---------*

SC.MD-ST.MS-0001 (Q) ; RV SYR 290184 21MS15 21 MN STM & TRB BY PASS STGEN SAF RLF VLV 20S303-1 Main, Reheat, and Turbine Bypass Steam F6 2 c RV SELF 8 c O/C Active

---

*-*-------------------------------------- ---------------------------.------------------.----------------------------*-----------*--7 --------*-**----------*-*******

SC.MD-ST.MS-0001 (Q)  ! RV SYR 290186

TABLE 3-2 -VALVE TEST TABLE 1011197 SALEM NUCLEAR PLANT - UNIT 2 Page 51

---

*-~---~* - - - - - - - - - - - - - - - - --- _:;_ __-..:::.=="--=~-=---_::~::.._ __ ::_=

VALVE NO VALVE DESCRIPTION P +ID No P +JD Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE!TEST FREQ.! C.S. JUST. i R.O. JUST.! REL. REQ.: RECUR. TASK !TECH. POS.! COMMENTS 22MS15 22 MN STM & TRB BY PASS STGEN SAF RLF VLV 205303-2 Main, Reheat, and Turbine Bypass Steam D6 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001 (Q)  : RV 5YR 290188 23MS15 23 MN STM & TRB BY PASS STM GEN SAF RLF VLV 23MS15 205303-1 Main, Reheat, and Turbine Bypass Steam C6 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001 (Q)  : RV 5YR  :  ! 290190 24MS15 24 MN STM & TRB BY PASS STGEN SAFETY RELIEF VALVE 205303-2 Main, Reheat, and Turbine Bypass Steam G6 2 c RV SELF 8 c O/C Active SC.MD-ST.MS-0001 (Q) : RV 5YR  !  ! 290192 21MS18 21 MN STM & TRB BY PASS STM GEN ISOL VLV AIR OPRD BYPASS VLV 205303-1 Main, Reheat, and Turbine Bypass Steam E4 2 B GT AIR 3 O/C c Active S2.0P-ST.MS-0001 (Q) FSTC Q 100544 S2.0P-ST.RPl-0004(Q) PIT 2YR 100872 S2.0P-ST.MS-0001 (Q) STC Q 100544 22MS18 .22 MN STM & TRB BY PASS STM GEN ISOL VLV AIR OPRD BYPASS VLV 205303-2 Main, Reheat, and Turbine Bypass Steam C4 2 B GT AIR 3 O/C c Active S2.0P-ST.MS-0001 (Q) FSTC Q 100544 S2.0P-ST.RPl-0004(Q) PIT 2YR 100872 S2.0P-ST.MS-0001 (Q) STC Q 100544

~-

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 52 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST.. R.O. JUST. ! REL. REQ.: RECUR. TASK ! TECH. POS.! COMMENTS 23MS18 23 MN STM & TRB BY PASS AIR OPRD STM GEN ISOL VLV BYPASS VLV 205303-1 Main, Reheat, and Turbine Bypass Steam B4 2 B GT AIR 3 O/C c Active S2.0P-ST.MS-0001 (Q) FSTC Q 100544  :  !

S2.0P-ST.RPl-0004(Q)  ! PIT 2YR 100872 S2.0P-ST.MS-0001 (Q) STC Q 100544 24MS18 24 MN STM & TRB BY PASS STM GEN ISOL AIR OPRD GLB VLV 205303-2 Main, Reheat, and Turbine Bypass Steam F4 2 B GT AIR 3 O/C c Active S2.0P-ST.MS-0001 (Q) FSTC Q  !  ! 100544  :

S2.0P-ST.RPl-0004(Q) ! PIT 2YR 100872 S2.0P-ST.MS-0001(Q) STC Q 100544 21MS45 21 MN STM & TRB BY-PASS AUX FDWTR PMP TRB 2MSE3 STM HOR ISOL VLV 205303-1 Main, Reheat & Turbine By-pass Steam G3 2 B GT MANUAL 6 0 c Active

~ ~

S2.0P-ST.AF-0003(Q) FSC Q  : .

100668 23MS45 23 MN STM & TRB BY-PASS AUX FDWTR PMP TRB 2MSE3 STM HOR ISOL VLV 205303-1 Main, Reheat & Turbine By-pass Steam 03 2 B GT MANUAL 6 0 c Active

~

S2.0P-ST.AF-0003(Q) FSC  ! Q  !  ! 100668 21MS46 21 MN STM & TRB BY PASS AUX FDW PMP TRB 2MSE3 STM HOR CHECK VALVE 205303-1 Main, Reheat, and Turbine Bypass Steam H3 2 C CK SELF 6 c O/C Active S2.0P-ST.AF-0006(Q) CTC Q 101151 S2.0P-ST.AF-0006(Q) CTO Q 101151

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 53 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE ;TEST FREQ.! C.S. JUST. ! R.O. JUST.  ! REL. REQ. ! RECUR. TASK !TECH. POS.! COMMENTS 23MS46 23 MN STM & TRB BY PASS AUX FDWTR PMP TRB 2MSE3 STM SUP HOR CKVL 205303-1 Main, Reheat, and Turbine Bypass Steam G3 2 c CK SELF 6 c O/C Active S2.0P-ST.AF-0006(Q)  ! CTC Q  ! 101151 S2.0P-ST.AF-0006(Q) CTO Q 101151 2MS132 2 MN STM & TRB BY PASS AUX FDWTR PMP TRB 2MSE3 START-STOP VLV 205303-1 Main, Reheat, and Turbine Bypass Steam H4 2 B GT AIR 6 c O/C Active

~ ~ . . -- - . ---. - .. - - .... - -- ------ . ---. ---.. --.. -- . - - -. -- . -.... - -

S2.0P-ST.AF-0003(Q)  : FSTO Q  ! 100668 S2.0P-ST.RPl-0001 (Q) PIT 2YR 100208 S2.0P-ST.AF-0003(Q) STC Q 100668 S2.0P-ST.AF-0003(Q) STO Q 100668 21MS167 21 MN STM & TRB BY PASS STM GEN HYO OPRD ISOL VLV 205303-1 Main, Reheat, and Turbine Bypass Steam Fl 2 B GT STM 32 0 c Active S2.0P-ST.MS-0003(Q) FSTC cs CS-24 100943 S2.0P-ST.RPl-0003(Q) ! PIT 2YR 100873 S2.0P-ST.MS-0003(Q) STC cs CS-24 100943 22MS167 *22 MN STM & TRB BY PASS STM GEN HYO OPRD ISOL VLV 205303-2 Main, Reheat, and Turbine Bypass Steam Cl 2 B GT. STM 32 0 c Active S2.0P-ST.MS-0003(Q) FSTC cs CS-24 100943 S2.0P-ST.RPl-0003(Q) PIT 2YR 100873 S2.0P-ST.MS-0003(Q) STC cs CS-24 100943

TABLE 3-2 -VALVE TEST TABLE 1011197 SALEM NUCLEAR PLANT - UNIT 2 Page 54

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VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I ' ' ' I ITITTPROC ~ITITTTIPE!T~TFREO.!.c.s.Jus~! R.~._.1u_s_r_._!_R_EL_._R_E_a_.!_R_E_c_u_R_._T_As_K~!_T_E_cH_._P_o_s_.~_c_o_M_M_E_N_T_s~~~~~~~~-

23MS167

• 23 MN STM & TRB BY PASS STM GEN HYO OPRD ISOL VLV 205303-1 Main, Reheat, and Turbine Bypass Steam Bl 2 B GT STM 32 0 c Active

- -- - - - - - -- - - - - -- -- - - - -- - - - -------- -- ----- - -- - - -- -- -- - -- - - - *. - - - ---- -- - - -- - - -- ~ --- ------ . -- --------- -- - - -- - ------- - -: -. - - - . - . - -- -- - - - -. -- -- -- -- - - -- - - - - - - - - -- --- -. - - - - --- - - ---- -- - ---- ---- - - -- - - - - - - - - - - -- -- - - - --- - ---- -- --- . ----- --

S2.0P-ST.MS-0003(0) FSTC cs CS-24 100943 S2.0P-ST.RPl-0003(0) i PIT 2YR 100873 S2.0P-ST.MS-0003(0) STC cs CS-24 100943 24MS167 24 MN STM & TRB BY PASS STM GEN HYDR OPRD GATE VLV 205303-2 Main, Reheat, and Turbine Bypass Steam Gl 2 B GT STM 32 0 c Active S2.0P-ST.MS-0003(0) FSTC CS CS-24 100943 S2.0P-ST.RPl-0003(0) i PIT 2YR 100873 S2. OP-ST. MS-0003(0) STC CS CS-24 100943 21MS169 21 MN STM & TRB BY PASS STGEN ISLN VLV AIR OPRD STM ASST VLV 205303-1 Main, Reheat, and Turbine Bypass Steam G7 2 B GT AIR 2 c 0 Active S2. OP-ST. MS-0002(0) FSTO : cs : CS-25 100844 S2.0P-ST.MS-0002(0) STO cs : CS-25 100844 22MS169 22 MN STM & TRB BY PASS STM GEN ISOL VLV STM ASSIST VLV 205303-2 Main, Reheat, and Turbine Bypass Steam DB 2 B GT AIR 2 c 0 Active S2. OP-ST. MS-0002(0) FSTO : CS  : CS-25 100844 S2.0P-ST.MS-0002(0) STO CS  ! CS-25 100844 23MS169 23 MN STM & TRB BY PASS STM GEN ISOL VLV AIR OPRD STM ASST VLV 205303-1 Main, Reheat, and Turbine Bypass Steam Cl 2 B GT AIR 2 c 0 Active S2.0P-ST.MS-0002(0) FSTO cs CS-25 100844 S2.0P-ST.MS-0002(0) STO cs CS-25 100844

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 55

==~==----------------- --------- - = =

VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification I ' I ' I I '

TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK !TECH. POS.! COMMENTS 24MS169 24 MN STM & TRB BY PASS STM GEN AIR OPRD ANGLE VLV 205303-2 Main, Reheat, and Turbine Bypass Steam GB 2 B GT AIR 2 C O Active S2. OP-ST. MS-0002(0) FSTO : cs  : CS-25 100844 S2.0P-ST.MS-0002(0) STO cs  : CS-25 100844 21MS171 21 MN STM & TRB BY PASS STGEN ISLN VLV AIR OPRD STM ASST VLV 205303-1 Main, Reheat, and Turbine Bypass Steam GB 2 B GT AIR 2 c 0 Active S2. OP-ST. MS-0002(0) FSTO  : CS  : CS-25 ,: 100844 S2.0P-ST.MS-0002(0) STO CS  : CS-25 100844 22MS171 22 MN STM & TRB BY PASS STM GEN ISOL VLV AIR OPRD STM ASSIST VLV 205303-2 Main, Reheat, and Turbine Bypass Steam DB 2 B GT AIR 2 c 0 Active

~ ---- - - -- - - ---- -- - -- - - - - -- - - - --- - - - --- - -- -- - . - -- -- ------------ - -- - - - - - - - -- - - - ..

S2. OP-ST. MS-0002(0) FSTO  : cs  : CS-25 100844 S2. OP-ST. MS-0002(0) STO cs  ! CS-25 100844 23MS171 23 MN STM & TRB BY PASS STGEN ISLN VLV AIR OPRD STM ASST VLV 205303-1 Main, Reheat, and Turbine Bypass Steam DB 2 GT AIR 2 c 0 Active S2.0P-ST.~S-0002(0) FSTO : *cs : CS-25 100844 S2. OP-ST. MS-0002(0) STO CS  : CS-25 100844 24MS171 24 MN STM & TRB BY PASS STM GEN AIR OPRD ANGLE VLV 205303-2 Main, Reheat, and Turbine Bypass Steam GB 2 B GT AIR 2 c 0 Active S2.0P-ST.MS-0002(0) FSTO cs CS-25 100844 S2. OP-ST. MS-0002(0) STO cs CS-25 100844

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 56

====~= ---------------------=-= = = = = =

VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ_j C.S. JUST. j R.O. JUST. ! REL. REQ.: RECUR. TASK !TECH. POS.~ COMMENTS 2NT25 2 REACT COOL PZR RLF TK NITROGEN SUPPLY LINE AIR OPRD DIAPH VLV 205301-1 Reactor Coolant C10 2 A DIA AIR 0.75 O/C c Active S2.0P-ST.ZZ-0003(Q) FSTC Q 100665 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290739 S2.0P-ST.RPl-0004(Q) PIT 2YR 100872

82. OP-ST .ZZ-0003(Q) STC Q 100665 2NT26 2 REACT COOL PZR RLF TK NITROGEN SUPPLY LINE CHECK VLV 205301-1 Reactor Coolant C9 2 A/C CK SELF 0.75 O/C c Active S2.RA-IS.ZZ-0002(Q) CTC  ! RF  : V-15  : 290740 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290740 2NT32 2 SAFETY INJ BOTTLED H.P. N2 TO ACCUMULATORS AIR OPRD GLB VLV 205334-3 Reactor Coolant H6 2 A GB AIR 1 O/C c Active S2.0P-ST.ZZ-0003(Q) FSTC Q 100665 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290741 S2.0P-ST.RPl-0004(Q) PIT 2YR 100872 S2.0P-ST.ZZ-0003(Q) STC Q 100665 2NT34 2 SAFETY INJ BOTTLED H.P. N2 TO ACCUMULATORS CHECK VLV 205334-3 Reactor Coolant H7 2 A/C CK SELF 1 O/C c Active S2.RA-IS.ZZ-0002(Q) CTC RF V-15 290742 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290742

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 57 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I TEST PROC ~TEST TYPE ~TEST FREQ.! C.S. JUST. ! R.O. JUST. ~ REL. REQ.: RECUR. TASK !TECH. POS.! COMMENTS 2PR1 2 REACT COOL POPS PZR VENT LINE AIR OPRD GLB VLV 205301-1 Reactor Coolant F1 1 B GB AIR 3 c O/C Acffve

---

.-------------------.------------------*;***---- ---------.-------------------------.------------------7------------ ----------------------- -------------------

S2.0P-ST.PZR-0003(Q) FSTC cs CS-26 101289

S2.0P-ST.RPl-0002(Q) PIT 2YR 100207 S2.0P-ST.PZR-0003(Q) STC cs CS-26 101289 S2.0P-ST.PZR-0003(Q) STO cs CS-26 101289 2PR2 2 REACT COOL POPS VENT LINE AIR OPRD GLB VLV 205301-1 Reactor Coolant F2 1 B GB AIR 3 c O/C Active S2.0P-ST.PZR-0003(Q) FSTC  : CS CS-26  ! j 101289  ! j S2.0P-ST.RPl-0002(Q) PIT 2YR 100207 S2.0P-ST.PZR-0003(Q) STC CS CS-26 101289 S2.0P-ST.PZR-0003(Q) STO CS CS-26 101289 2PR3 2 REACT COOL POPS PZR SAF RLF VLV 205301-1 Reactor Coolant F2 1 c RV SELF 6 c O/C Active SC.MD-PTRC-0001 (Q)  ! RV 5YR 290194 2PR4 2 REACT COOL POPS PZR SAF RLF VLV 205301-1 Reactor Coolant F3 1 c RV SELF 6 c O/C Active SC.MD-PT.RC-0001 (Q) i RV 5YR 290196 2PR5 2 REACT COOL POPS PZR SAF RLF VLV 205301-1 Reactor Coolant F4 1 c RV SELF 6 c O/C Active SC.MD-PT.RC-0001 (Q) j RV 5YR 290198

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 58 VALVE NO VALVE DESCRIPTION P+ ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. : REL. REQ.: RECUR. TASK ! TECH. POS.! COMMENTS 2PR6 2 REACT COOL POPS PZR RLF STOP MOV 205301-1 Reactor Coolant F1 1 B GB MO 3 0 O/C Active S2.0P-ST.RPl-0002(Q) PIT 2YR 100207 S2.0P-ST.PZR-0002(Q)  ! STC Q 101238 S2.0P-ST.PZR-0002(Q)  ! STO Q 101238 2PR7 2 REACT COOL POPS PZR RLF LINE STOP MOV 205301-1 Reactor Coolant F2 1 B GB MO 3 0 O/C Active S2.0P-ST.RPl-0002(Q) PIT 2YR 100207 S2.0P-ST.PZR-0002(Q) : STC Q 101238 S2.0P-ST.PZR-0002(Q) : STO Q 101238 2PR17 2 REACT COOL POPS PZR RLF TK VENT TO GAS ANALYZER AIR OPRD GLB VLV 205301-1 Reactor Coolant D9 2 A GB AIR 0.375 c C Active S2.0P-ST.ZZ-0003(Q) FSTC Q 100665 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290743 S2.0P-ST.RPl-0002(Q) PIT 2YR 100207 S2.0P-ST.ZZ-0003(Q) STC Q 100665 2PR18 2 REACT COOL POPS PZR RLF TK VENT TO GAS ANALYZER AIR OPRD GLB VLV 205301-1 Reactor Coolant D10 2 A GB AIR 0.375 c c Active S2.0P-ST.ZZ-0003(Q) FSTC Q 100665 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290744 S2.0P-ST.RPl-0004(Q) PIT 2YR 100872 S2.0P-~T.ZZ-0003(Q) STC Q 100665

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 59 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. i R.O. JUST. : REL. REQ. ! RECUR. TASK :TECH. POS.! COMMENTS 2PR25 2 REACT COOL POPS SAFETY INJ PMP RLF LINE TO PZR RLF TK CHECK VLV 205301-1 Reactor Coolant E9 2 A/C CK SELF 4 C O/C Active S2.RA-IS.ZZ-0002(Q) CTC RF V-16 290745 S2.0P-ST.ZZ-0003(Q) CTO Q 100665 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290745 2PS1 2 REACT COOL PZR SPRAY INLET STOP AIR OPRD GLB VLV 205301-1 Reactor Coolant ES 1 B GB AIR 0.5 OIC c Active S2.0P-ST.PZR-0003(Q) FSTC ! CS  ! CS-27  ! 101289 S2.0P-ST.RPl-0002(Q).  ! PIT 2YR 100207 S2.0P-ST.PZR-0003(Q) i STC CS CS-27 101289 2PS3 2 REACT COOL PZR SPRAY INLET LINE STOP AIR OPRD GLB VLV 205301-1 Reactor Coolant D6 1 B GB AIR 0.5 OIC c Active S2.0P-ST.PZR-0003(Q) FSTC cs CS-27 101289 S2.0P-ST.RPl-0002(Q) i PIT 2YR 100207 S2.0P-ST.PZR-000.3(Q)  ! STC cs CS-27 101289 2RC40 2 REACT COOL REACT HEAD VENT VLV 2RC40 SV 205301-1 Reactor Coolant Hl 1 B GB SOL 0.75 c O/C Active S2.0P-ST.PZR-0003(Q) FSTC cs CS-28 100289 S2.0P-ST.RC-0009(Q) PIT 2YR 100284 S2.0P-ST.PZR-0003(Q) STC cs CS-28 100289 S2.0P-ST.PZR-0003(Q) STO cs CS-28 100289

TABLE3~-VALVETESTTABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 60

--- --=--=--==

VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! c_s_ JUST.  ! R.O. JUST. ! REL. REQ. ! RECUR. TASK ! TECH. POS.! COMMENTS 2RC41 2 REACT COOL REACT HEAD VENT VLV 2RC41 SV 205301-1 Reactor Coolant H7 1 B GB SOL 0.75 c O/C Active S2.0P-ST .PZR-0003(0) FSTC cs CS-28 101289 S2.0P-ST.RC-0009(0) PIT 2YR 100284 82.0P-ST.PZR-0003(0) STC cs CS-28 101289 S2.0P-ST.PZR-0003(0) STO cs CS-28 101289 2RC42 2 REACT COOL REACT HEAD VENT VLV 2RC42 SV 205301-1 Reactor Coolant H7 1 B GB SOL 0.75 c O/C Active

---

--- ------------ -- - -- .. --- -- - - -- . - -- -- - --. - -------- ----... -. - - - - . --- -- - - -- ~ - - - - - - - - - -- - - - - -- --

S2.0P-ST.PZR-0003(0) FSTC : CS CS-28  : 101289 S2.0P-ST.RC-0009(0) PIT 2YR 100284 S2.0P-ST.PZR-0003(0) STC CS CS-28 101289 S2.0P-ST.PZR-0003(0) STO CS CS~8 101289 2RC43 2 REACT COOL REACT HEAD VENT VLV 2RC43 SV 205301-1 Reactor Coolant H7 1 B GB SOL 0.75 c O/C Active S2.0P-ST.PZR-0003(0) FSTC cs CS-28 101289 S2. OP-ST .RC-0009(0) PIT 2YR 100284 S2.0P-ST.PZR-0003(0) STC cs CS-28 101289 S2. OP-ST .PZR-0003(0) STO cs CS-28 101289 2RH1 2 RHR COMMON SUCT MOV GATE VLV 205332-2 Residual Heat Removal G10 1 A GT MO 14 c O/C Active S2.0P-ST.SJ-0021 (0) LT 2YR 101303 S2. OP-ST. RPl-0002(0) PIT 2YR 100207 S2.0P-ST.RHR-0004(0) STC cs CS-29 100358 S2.0P-ST.RHR-0004(0) STO cs CS-29 100358

TABLE3~-VALVETESTTABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 61 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC :TEST TYPE :TEST FREQ.: C.S. JUST. : R.O. JUST. : REL. REQ.: RECUR. TASK !TECH. POS.: COMMENTS 2RH2 2 RHR COMMON SUCT MOV GATE VLV 205332-2 Residual Heat Removal G10 1 A GT MO 14 c O/C Active S2.0P-ST.SJ-0021 (Q) LT  :' 2YR .: 101303 S2.0P-ST.RPl-0002(Q) PIT 2YR 100207 S2.0P-ST.RHR-0004(Q) STC CS CS-29 100358 S2.0P-ST.RHR-0004(Q) STO CS CS-29 100358 2RH3 2 RHR 22 TO PZR RLF TK SAF RLF VLV 205332-2 Residual Heat Removal H9 2 c RV SELF 3 c O/C Active

- - - - -- - - -- -- - - - - - - -- -- - - -- -- - - - - - - - - -- - - - -. - - -- -- . - - - - - - - -- . - - - - - -- - - --- - -- . - -- ~ - . --. -- . - . - - - -- - - - - - - -- -- - - - - -- - - -- - -:

SC.MD-PT.ZZ-0007(0) RV  : SYR  :  ! 290200 21RH4 21 RHR PMP SUCT MOV GATE VLV 205332-1 Residual Heat Removal E1 2 B GT MO 14 0 O/C Active 82.0P-ST.RPl-0001 (Q) i PIT 2YR 100208 S2.0P-ST.RHR-0003(Q) i STC Q 100662 22RH4 22 RHR PMP SUCT MOV GATE VLV 205332-2 Residual Heat Removal E1 2 B* GT MO 14 0 O/C Active 82.0P-ST.RPl-0001 (Q)  ! PIT 2YR 100208 S2.0P-ST.RHR-0003(Q)  ! STC Q 100662 21RH8 21 RHR PMP DISCH CHECK VALVE 205332-1 Residual Heat Removal E3 2 c CK SELF 8 c O/C Active S2.0P-ST.RHR-0001 (Q) CTC Q 100679 S2.0P-ST.RHR-0001 (Q) CTO cs CS-30 101317 S2.0P-ST.RHR-0001 (Q) PS Q CS-30 100679

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 62

~-==.:...-=----::~_:;::::_-- __ _, _________ - - - - - - - - - -------*--====-==="°--- __: _,::::..:..:..-=:.=-...:....:..-::_- ...::;:......:......:..:.:....:.......: *.:==.;:--* --------------~ - - - ----------*::-.;_-:::=:_....::: *....=::::.... - -

VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC :TEST TYPE :TEST FREQ.: C.S. JUST. : R.O. JUST. : REL. REQ.: RECUR. TASK : TECH. POs.: COMMENTS 22RH8 22 RHR PMP DISCH CHECK VALVE 205332-2 Residual Heat Removal F3 2 c CK SELF 8 c O/C Active S2.0P-ST.RHRc0002(Q) CTC Q 100680 S2.0P-ST.RHR-0002(Q) : CTO CS  : CS-30 101318 S2.0P-ST.RHR-0002(Q) : PS Q  : CS-30 100680 21RH18 21 RHR HX FLOW CONT AIR OPRD BTFL VLV 205332-1 Residual Heat Removal FB 2 B BFY AIR 8 O/C 0 Active S2. OP-ST.SJ-0005(0) CS-31 100200 S2.0P-ST.RPl-0003(Q)  : PIT 2YR 100873 S2.0P-ST.SJ-0005(Q) STO cs CS-31 100200 22RH18 22 RHR HX FLOW CONT AIR OPRD BTFL VLV 205332-2 Residual Heat Removal FB 2 B BFY AIR 8 O/C 0 Active S2.0P-ST.SJ-0005(Q) FSTO cs CS-31 100200 S2.0P-ST.RPl-0003(Q)  : PIT 2YR 100873 S2.0P-ST.SJ-0005(Q) STO cs CS-31 100200 21RH19 21 RHR HX DISCH X-CONN MOV GATE VLV 205332-1 Residual Heat Removal EB 2 B GT MO 8 0 O/C Active S2.0P-ST.RPl-0001 (Q)  : PIT 2YR 100208 S2.0P-ST.RHR-0004(Q) ; STC cs CS-32 100358 22RH19 22 RHR HX DISCH X-CONN MOV GATE VLV 205332-2 Residual Heat Removal EB 2 B GT MO 8 0 O/C Active S2.0P-ST.RPl-0001 (Q) PIT 2YR 100208 S2.0P-ST.RHR-0004(Q) STC cs CS-32 100358

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 63 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC ~TEST TYPE ~TEST FREQ) C.S. JUST. : R.O. JUST. ~ REL. REQ. i RECUR. TASK iTECH. POS.~ COMMENTS 2RH21 RHR Tie to Refueling Water Storage Tank 205332-1 Residual Heat Removal EB 2 A GT MAN 8 c c Passive S2.0P-ST.RC-0008(0)  ! LT 2YR 101428 2RH25 2 RHR 21 TO PZR RLF TK SAF RLF VLV 205332-1 Residual Heat Removal H9 2 c RV SELF 0.75 c O/C Active SC.MD-PT.ZZ-0007(0)  ! RV 5YR  !  ! 290202 2RH26 2 RHR HOT LEG ISOL MOV GATE VLV 205332-1 Residual Heat Removal F10 1 B GT MO 12 c O/C Active S2.0P-ST.RPl-0002(0)  ! PIT 2YR  ! 100207 S2.0P-ST.RHR-0004(0)  ! STC CS CS-51 100358 S2.0P-ST.RHR-0004(0)  ! STO CS CS-51 100358 23RH27 23 RHR HOT LEG CHECK VALVE 205332-1 Residual Heat Removal G10 1 A/C CK SELF 8 c O/C Active S2. OP-ST .SJ-0020(0) CTC RF V-40 100743 S2.0P-ST.RHR-0005(0) : CTO RF V-40 100395 S2. OP-ST .SJ-0020(0) LT 2YR 100743 24RH27 24 RHR HOT LEG CHECK VALVE 205332-1 Residual Heat Removal G10 1 A/C CK SELF 8 c O/C Active

82. OP-ST.SJ-0020(0) CTC V-40 100743 S2.0P-ST.RHR-0005(0) CTO V-40 100395 S2.0P-ST.SJ-0020(0) LT 2YR 100743

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 64

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ----,=== --------------,*===

VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I ' I TEST PROC !TEST TYPE!TEST FREQ.! C.S. JUST. i R.O. JUST.! REL. REQ. i RECUR. TASK !TECH. POS.! COMMENTS 21RH29 21 RHR PMP MIN FLOW MOV GLB VLV 205332-1 Residual Heat Removal G4 2 B GB MO 2 c O/C Active

---

.------------------------------------*-;-**---------------.-------------------------;------------------7-------------------------------

S2.0P-ST.RPl-0001 (Q) i PIT 2YR 100208 i S2.0P-ST.RHR-0003(Q) ! STC Q 100662 S2.0P-ST.RHR-0003(Q) i STO Q 100662 22RH29 22 RHR PMP MIN FLOW MOV GLB VLV 205332-2 Residual Heat Removal G4 2 B GB MO 2 c O/C Active S2.0P-ST.RPl-0001 (Q) PIT 2YR 100208 S2.0P-ST.RHR-0003(Q) : STC Q 100662 S2.0P-ST.RHR-0003(Q) i STO Q 100662 2RH75 2 RHR PMP SUCT CHECK VALVE 205332-1 Residual Heat Removal E1 2 c CK SELF 14 c O/C Active

~ -- - - - - - -- - - - - - - - - - - -- -- . - -- - -- -- - . - - - - . - . -- - - .. - . - - .

S2.0P-ST.RHR-0001 (Q) i CTC j Q j 100679 S2.0P-ST.RHR-0001(Q)  ! CTO CS CS-46 101317 2RH76 2 RHR 22 PMP SUCT CHECK VALVE 205332-2 Residual Heat Removal E1 2 c CK SELF 14 c O/C Active

~ ~

S2.0P-ST.RHR-0002(Q j CTC Q i i 100680  ! i S2.0P-ST.RHR-0002(Q) j CTO CS  ! CS-46 101318 2SA118 2 STAT AIR CONTAINMENT ISLN VLV 205317-2 Compressed Air D9 2 A GT MAN 3 LC c Passive S2.RA-IS.ZZ-0002(Q) LJ 18MO 290746

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 65 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ; R.O. JUST. ! REL. REQ. ! RECUR. TASK ! TECH. POS.! COMMENTS 2SA119 2 STAT AIR CONTAINMENT ISLN CHECK VLV 205317-2 Compressed Air D10 2 A/C CK SELF 3 c c Passive S2.RA-IS.ZZ-0002(Q) LJ 18MO  ! 290747  !

2SA262 2 STAT AIR CONT PRESS TEST ISLN VALVE 205317-1 Compressed Air A6 2 A GB MAN 0.75 LC c Passive

~ .. - - . - . -- --- - --- - . - . - . -- - . - - . -- . . . -

S2.RA-IS.ZZ-0002(Q) i LJ 18MO i 290748 2SA264 2 STAT AIR CONT PRESS TEST ISLN GLB VLV 205317-1 Compressed Air A7 2 A GB MAN 0.75 LC c Passive S2.RA-IS.ZZ-0002(Q)  ! LJ 18MO 290749  :

2SA265 2 STAT AIR CONT PRESS TEST ISLN GLB VLV 205317-1 Compressed Air A6 2 A GB MAN 0.75 LC c Passive

- ~ - . ----- ----- - -- --. -- - - - --- ------- - - - - - - - - - . .- -- ---. -- - - -- - - - - - : -- ---- ----- - - .. - - -- . --- - - -- - . -

S2.RA-IS.ZZ-0002(Q) LJ 18MO 290750 2SA267 2 STAT AIR CONT PRESS TEST LINE ISLN GLB VLV 205317-1 Compressed Air A7 2 A GB MAN 0.75 LC c Passive S2.RA-IS.ZZ-0002(Q) LJ 18MO i 290751 i 2SA268 2 STAT AIR CONT PRESS TEST LINE ISLN GLB VLV 205317-1 Compressed Air A6 2 A GB MAN 0.75 LC c Passive S2.RA-IS.ZZ-0002(Q)  ! LJ . : 18MO i  : 290752  :

2SA270 2 STAT AIR CONT PRESS TEST ISLN GLB VLV 205317-1 Compressed Air A7 2 A GB MAN 0.75 LC c Passive S2.RA-IS.ZZ-0002(Q) LJ 18MO 290753

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 66

==~~=-=*------~---

VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK !TECH. POS.! COMMENTS 2SF22 2 SPNT FUEL CLG REFUEL WTR PURIF PMP INLET DIAPH VLV 205333-1 Spent Fuel Pool Cooling A6 2 A DIA MAN 3 C C Passive LJ 18MO 290754 2SF36 2 SPNT FUEL CLG REFUEL WTR PURIF FLTR TO REFUELING CANAL DIAPH VLV 205333-1 Spent Fuel Pool Cooling A3 2 A DIA MAN 2 c c Passive

- - ~ ~ ~ - -

S2.RA-IS.ZZ-0002(Q) LJ  : 18MO  !  ! 290756  :  :

2SJ1 2 SAFETY INJ REFUEL WATER STOR TK TO CHARGING PUMPS MOV 205334-1 Safety Injection F1 2 B GT MO B c O/C Active S2.0P-ST.RPl-0003(Q) PIT 2YR 100873 S2.0P-ST.SJ-0003(Q) STC Q 100481 S2.0P-ST.SJ-0003(Q) STO Q 100481 2SJ2 2 SAFETY INJ REFUEL WATER STOR TK TO CHARGING PUMPS MOV 205334-1 Safety Injection F1 2 B GT MO B c O/C Active S2.0P-ST.RPl-0003(Q)  ! PIT i* 2YR .  ! . 100873 S2.0P-ST.SJ-0003(Q) STC Q 100481 S2.0P-ST.SJ-0003(Q) STO Q 100481 2SJ3 2 SAFETY INJ REFUEL WATER STOR TK TO CHARGING PUMPS CHECK VLV 205334-1 Safety Injection E1 2 C CK SELF B c O/C Active S2.0P-ST.SJ-0003(Q) CTC Q 100481 S2.0P-ST.SJ-0016(Q) CTO RF V-18 101048 S2. OP-ST. CVC-0007 (Q) PS cs V-18 100456

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 67

.:.-------- ---*---~------*--- --*---------------:=-==~=~---==-==-:~:::.::.0...::..,.:..:----------*--- - - - - - - - - - - - - * - - - - - - - * - - - * = - : = . . : : . . . . : . : = ; : . . : : - " ==~=:::~:!::..:'"' . * : - :,__- -~=-:....-::....-::..-::..--==-====-~---=

VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.: C.S. JUST. : R.O. JUST. : REL. REQ.: RECUR. TASK : TECH. pos.! COMMENTS 2SJ4 2 SAFETY INJ CHARGING PUMPS TO BORON INJ TK MDV 205334-1 Safety Injection 84 2 B GT MO 4 0 O/C Active

---

.------------------=-------- -------*-------- ------------ ---------------- ------------------------------------------- ------ ---------------------------- ----------------------

S2.0P-ST.RPl-0003(0) ! PIT 2YR 100873 S2.0P-ST.SJ-0003(0) STC 0 100481 2SJ5 2 SAFETY INJ CHARGING PUMPS TO BORON INJ TK MDV 205334-1 Safety Injection 84 2 B GT MO 4 0 O/C Active S2.0P-ST.RPl-0003(0) : PIT 2YR 100873 S2.0P-ST.SJ-0003(0) STC 0 100481 2SJ12 2 SAFETY INJ BORON INJ TK OUTLET TO COLD LEG MOV 205334-1 Safety Injection DB 1 B GT MO 4 c O/C Active S2.0P-ST.RPl-0004(0) j PIT 2YR j j 100872 S2.0P-ST.SJ-0003(0) STC 0 100481 S2.0P-ST.SJ-0003(0) STO 0 100481 2SJ13 2 SAFETY INJ BORON INJ TK OUTLET TO COLD LEG MDV 205334-1 Safety Injection DB 1 B GT MO 4 c O/C Active S2. OP-ST. RP 1-0004(0) PIT 2YR 100872 S2. OP-ST. SJ-0003(0) STC 0 100481 S2.0P-ST.SJ-0003(0) STO 0 100481 21SJ17 21 SAFETY INJ TO NO 21 COLD LEG CHECK VLV 21SJ17 205334-1 Safety Injection H7 1 A/C CK SELF 1.5 c O/C Active S2.0P-ST .SJ-0020(0) CTC RF V-19 100828 S2. OP-ST .SJ-0016(0) CTO RF V-19 101048 S2.0P-ST.SJ-0020(0) LT 2YR 100828

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 68 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC ~TEST TYPE :TEST FREQ.: C.S. JUST. ~ R.O. JUST. ~ REL. REQ. ! RECUR. TASK ! TECH. POS.~ COMMENTS 22SJ17 22 SAFETY INJ COLD LEG LINE CHECK VLV 205334-1 Safety Injection HB 1 A/C CK SELF 1.5 c O/C Active S2.0P-ST.SJ-0020(Q) CTC RF V-19 100828 S2.0P-ST.SJ-0016(Q) CTO RF V-19 101048 S2.0P-ST.SJ-0020(Q) LT 2YR 100828 23SJ17 23 SAFETY INJ COLD LEG LINE CHECK VLV 205334-1 Safety Injection H10 1 A/C CK SELF 1.5 c O/C Active S2.0P-ST.SJ-0020(Q) CTC RF V-19 100828 S2.0P-ST.SJ-0016(Q) CTO RF V-19 101048 82.0P-ST .SJ-0020(0) LT 2YR 100828 24SJ17 24 SAFETY INJ COLD LEG LINE CHECK VLV 205334-1 Safety Injection H9 1 A/C CK SELF 1.5 c O/C Active S2.0P-ST.SJ-0020(Q) CTC RF V-19 100828 S2.0P-ST.SJ-0016(Q) CTO RF V-19 101048 S2.0P-ST.SJ-0020(Q) LT 2YR 100828 21SJ29 21 SAFETY INJ ACCUMULATOR SAF RLF VLV 205334-4 Safety Injection G2 3 c RV SELF 1 c O/C Active SC.MD-PT.ZZ-0007(0)  : RV 5YR  : 290208 22SJ29 22 SAFETY INJ ACCUM 22 SAF REL VLV 205334-4 Safety Injection GS 3 c RV SELF 1 c O/C Active SC.MD-PT.ZZ-0007(0) RV 5YR 290214

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 69

=-=------ -~----*---------~..====::::=::.:~=:..::::::-~-:=c:=:-...::'.-::-:=:=~-=-=.:.:=---=-""'=-===,==-------------------- -------- *-=-=-~...::_:=--==-:: ~,._::_:;:;:_ ::::::.*-=-:.*::...-:::::::...-: ---=~-:=- :::.:::_-::-.:o.::::-==---=--:.::==~ -

VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

• I ' I I I l TEST PROC ~TEST TYPE ~TEST FREQ.~ C.S. JUST. ~ R.O. JUST. : REL. REQ. ~ RECUR. TASK ~TECH. POS.~ COMMENTS 23SJ29 23 SAFETY INJ ACCUM 23 SAF REL VLV 205334-4 Safety Injection Gl 3 c RV SELF 1 c O/C Active SC. MD-PT .ZZ-0007 (0) RV 5YR 290216 24SJ29 24 SAFETY INJ ACCUM 24 SAF REL VLV 205334-4 Safety Injection G10 3 c RV SELF 1 c O/C Active SC.MD-PT.ZZ-0007(0) RV 5YR 290218 2SJ30 2 SAFETY INJ REFUEL WATER STOR TK TO PUMPS STOP MOV 205334-2 Safety Injection G2 2 B GB MO 8 0 O/C Active S2.0P-ST.RPl-0003(0)  : PIT 2YR 100873 S2.0P-ST.SJ-0005(0) STC CS  : CS-34 100200 2SJ31 2 SAFETY INJ REFUEL WATER STOR TK TO PUMPS CHECK VLV 205334-2 Safety Injection G2 2 c CK SELF 8 c O/C Active S2.0P-ST.SJ-0003(0) CTC 0 100481 .'

52.0P-ST.SJ-0014(0) CTO RF V-20 100154 S2.0P~ST.SJ-0002(0) PS 0 100670 52.0P-ST.SJ-0001 (0) PS . 0 100669 2SJ32 2 SAFETY HOR INJ SAF RLF VLV FOR PMPS SUCT HOR 205334-2 Safety Injection GS 2 c RV SELF 0.75 c O/C Active SC.MD-PT.ZZ-0007(0) ' RV i 5YR j 290220 21SJ33 21 SAFETY INJ PMP SUCT MOV 205334-2 Safety Injection G2 2 B GT MO 6 0 0 Passive 82.0P-ST.RPl-0001 (0) PIT 2YR 100208

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 70

.:---------: _:;:.._-:-=-=====--~==...:====.::.. __ .::..""::..:....~:.....;:;.=-=--.:o..._:...:.::.- --=*-=**=----=*--= -- -- -- -------* --=-=-=*=--=*-=-= = - - - ---*-* ...::....: .. :-:. ..: - *.: : . .. __:._ .: :... : : :: *-- _.:.. _.. **-c.;::: .:.... _:.:: .* ::...:*. ..:o... ..'...:::.':. - ;__:..:._===-=-"'--

VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ) C.S. JUST. ! R.O. JUST. ; REL REQ.: RECUR. TASK ! TECH. POS.! COMMENTS 22SJ33 22 SAFETY INJ PMP 22 SUCT VLV 205334-2 Safety Injection GS 2 B GT MO 6 0 0 Passive S2.0P-ST.RPl-0001 (0) i PIT 2YR 100208 21SJ34 21 SAFETY INJ PMP DISCH CHECK VLV 205334-2 Safety Injection DS 2 c CK SELF 4 c O/C Active S2.0P-ST.SJ-0002(0) CTC 0  ! 100670  :

S2.0P-ST.SJ-0014(0) CTO RF V-21 100154 22SJ34 22 SAFETY INJ PMP 22 DISCH CHECK VLV 205334-2 Safety Injection D7 2 c CK SELF 4 c O/C Active S2.0P-ST.SJ-0001 (0) CTC 0 100669 S2.0P-ST.SJ-0014(0) CTO RF V-21 100154 21SJ39 21 SAFETY INJ SAF REL VLV ON PMP 21 DISCH HOR 205334-2 Safety Injection D9 2 c RV SELF 0.75 c O/C Active SC.MD-PT.ZZ-0007(0) RV 5YR  ! 290222  !

22SJ39 22 SAFETY INJ PMP 22 DISCH HOR SAF REL VLV 205334-2 Safety Injection DB 2 c RV SELF 0.75 c O/C Active

... -.. --.... -. --.. -. -. --.... -....... -.. - - .... - ... \. ....... - .... .

SC.MD-PT.ZZ-0007(0) RV 5YR 290224 21SJ40 21 SAFETY INJ HOT LEG 24 HOR STOP VLV 205334-2 Safety Injection G9 1 B GT MO 4 c O/C Active S2. OP-ST .RPl-0004(0) PIT 2YR 100872 S2. OP-ST.SJ-0005(0) STC cs CS-36 100200 82.0P-ST.SJ-0005(0) STO cs CS-36 100200

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 71

• ~~=~=--==='=====

VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC ~TEST TYPE ~TEST FREQ.: C.S. JUST. j R.O. JUST. 1 REL. REQ. ~ RECUR. TASK ~TECH. POS_~ COMMENTS 22SJ40 22 SAFETY INJ PMP 22 HOR STOP VLV 205334-2 Safety Injection GB 1 B GT MO 4 c O/C Active

~ . - - - -- -- -- - - - - ---- --- - - -- - - - - - - -- - - ---------- -- -- -- - - -- -- - -- ---- - - -- - - -

S2.0P-ST.RPl-0004(0) PIT 2YR 100872 S2.0P-ST.SJ-0005(0) STC cs  : CS-36 100200 S2.0P-ST.SJ-0005(0) STO cs  ! CS-36 100200 21SJ43 21 SAFETY INJ CHECK VLV TO COLD LEG 21 205334-4 Safety Injection E3 1 AJC CK SELF 6 c O/C Active S2. OP-ST. SJ-0020(0) CTC RF V-22 100828 SC.MD-PM.ZZ-0075(0) CTO SAM V-22 203766 TP-6 S2.0P-ST.SJ-0020(0) LT 2YR 100828 S2.0P-ST.SJ-0005(0) PS cs V-22 100200 22SJ43 22 SAFETY INJ COLD LEG 22 CHECK VLV 205334-4 Safety Injection D5 1 A/C CK SELF 6 c O/C Active S2.0P-ST.SJ-0020(0) CTC RF V-22 100828 SC.MD-PM.ZZ-0075(0) CTO SAM V-22 203823 TP-6 S2. OP-ST. SJ-0020(0) LT 2YR 100828 S2.0P-ST.SJ-0005(0) PS cs V-22 100200 23SJ43 23 SAFETY INJ COLD LEG 23 CHECK VLV 205334-4 Safety Injection DB 1 AJC CK SELF 6 c O/C Active S2. OP-ST .SJ-0020(0) CTC RF V-22 100828 SC.MD-PM.ZZ-0075(0) CTO SAM V-22 203828 TP-6 S2.0P-ST.SJ-0020(0) LT 2YR 100828 S2.0P-ST.SJ-0005(0) PS cs V-22 100200

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 72

--~

---

-- - - - - - - - - - - - - - - - - - - - - - ----= .=-....::... o::.. -=--==- ..::: --=-----=-*=-.=.=~~'- --* - -----" ~--==-~-,==::.=-.----::..:.*:;:..=-=--=-':--.--

VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC. :TEST TYPE :TEST FREQ.: C.S. JUST. : R.O. JUST.: REL REQ.: RECUR. TASK !TECH. pos.: COMMENTS 24SJ43 24 SAFETY INJ COLD LEG 24 CHECK VLV 205334-4 Safety Injection D11 1 A/C CK SELF 6 c O/C Active S2.0P-ST.SJ-0020(0) CTC RF V-22 100828 SC.MD-PM.ZZ-0075(0) CTO SAM V-22 203832 TP-6 S2. OP-ST .SJ-0020(0) LT 2YR 100828 S2.0P-ST.SJ-0005(0) PS CS V-22 100200 21SJ44 21 SAFETY INJ CONTMT SUMP ISOL VLV 205334-3 Safety Injection 83 2 B GT MO 14 c O/C Active S2. OP-ST .RP 1-0003(0) PIT 2YR V-23 101397 S2.0P~ST.SJ-0005(0) STC cs  : CS-37 100200 S2.0P-ST.SJ-0005(0) STO cs  : CS-37 100200 22SJ44 22 SAFETY INJ CONTMT SUMP SUCT VLV 205334-3 Safety Injection 83 2 B GT MO 14 c 0 Active S2.0P-ST.RPl-0003(0) PIT 2YR V-23 101398 S2.0P-ST.SJ-0005(0) STC cs  : CS-37 100200 S2.0P-ST.SJ-0005(0) STO cs  : CS-37 100200 21SJ45 21 SAFETY INJ PMPS STOP VLV FROM RH.R 205334-2 Safety Injection G6 2 B GT MO 8 c O/C Active S2.0P-ST.RPl-0003(0)  : PIT 2YR 100873 S2.0P-ST.SJ-0005(0) STO CS CS-38 100200 22SJ45 22 SAFETY INJ RESIDUAL HT REMOVAL TO CHARGING PMP STOP MOV 205334-1 Safety Injection E3 2 B GT MO 8 c O/C Active S2.0P-ST.RPl-0003(0) PIT 2YR 100873 S2.0P-ST.SJ-0005(0) STO cs CS-38 100200

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 73 c--~~ ----------**-*--:=..:..::-=.-::__::::===.:::.-:. *. .:. . .:=====--:.:....--*-=::::_:::.::= .:=:::::..::::;;:c VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC :TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ.: RECUR. TASK ! TECH. POS.! COMMENTS 21SJ48 21 SAFETY INJ SAF REL VLV FOR RHR DISCH TO COLD LEG HOR 205334-3 Safety Injection G6 2 c RV SELF 2.5 c O/C Active

- - -- ------ ---------- ----- - -- -- - - - - -- -- - - - -. -- - - -- -- - - - - - --- --. -- -- --- -- --- . - - - - - ~ - - . - - - - -- - - ------ ---- - - - - - -- - - ------ -: - - --- - - - - - - -- -- - -. -- -- -------- -- -- - -- - - - - - - .- - - -- - - - ----- -- -- - : - -- - - -- - - - ------ - - - - -- - -- -- -- ------ - - -- - - -- - - -- .. -- - -- - . -

SC.MD-PT.ZZ-0007(0) RV SYR 290226 22SJ48 22 SAFETY INJ LOW HEAD SAF REL VLV 205334-3 Safety Injection 06 2 c RV SELF 2.5 c O/C Active

~  ; - - . - - - - - --- - -- ---. ---- - - -- -- -- - . - - -- - - --------- --- - . - - - - - - - - - - - -- - ---- ----- - - -- - . - . - - - -- - -- -- - -- - --- - . - - . - . -

SC.MD-PT.ZZ-0007(0) RV  ! SYR  ! 290228 21SJ49 21 SAFETY INJ TO RHR DISCH TO COLD LEG HOR 205334-3 Safety Injection G7 1 B GT MO 8 0 O/C Active S2.0P-ST.RPl-0004(0)  ! PIT 2YR 100872 S2.0P-ST.SJ-0005(0) STC CS  : CS-39 100200 22SJ49 22 SAFETY INJ FROM RHR DISCH TO COLD LEGS ISOL 205334-3 Safety Injection D6 1 B GT MO 8 0 O/C Active S2.0P-ST.RPl-0004(0)  ! PIT 2YR 100872 S2. OP-ST.SJ-0005(0) STC cs  : CS-39 100200 2SJ53 2 SAFETY INJ TEST LINE AIR OPRD GLB VLV 205334-2 Safety Injection F10 1 A GB AIR 0.75 c c Passive S2. OP-ST. SJ-0003(0) FSTC 0 100481 S2.RA-IS.ZZ-0002(0) LJ 18MO 290758 S2.0P-ST.RPl-0004(0) PIT 2YR 100872 S2. OP-ST. SJ-0003(0) STC 0 100481

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 74 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC :TEST TYPE !TEST FREQ.~ C.S. JUST. ! R.O. JUST. ~ REL. REQ. ~ RECUR. TASK :TECH. POS.: COMMENTS 21SJ54 21 SAFETY INJ ACCUM 21 OUTLET VLV 205334-4 Safety Injection E2 1 B GT MO 10 0 O/C Active S2.0P-ST.RPl-0002(Q)  : PIT 2YR 100207 S2.0P-ST.SJ-0004(Q) STC CS  : CS-50 100463 22SJ54 22 SAFETY INJ ACCUM 22 OUTLET VLV 205334-4 Safety Injection E4 1 B GT MO 10 0 O/C Active S2.0P-ST.RPl-0002(Q) PIT 2YR 100207 S2.0P-ST.SJ-0004(Q) STC cs  : CS-50 100463 23SJ54 23 SAFETY INJ ACCUM 23 OUTLET VLV 205334-4 Safety Injection El 1 B GT MO 10 0 O/C Active S2.0P-ST.RPl-0002(Q)  ! PIT 2YR 100207 S2.0P-ST.SJ-0004(Q) STC CS  : CS-50 100463 24SJ54 24 SAFETY INJ ACCUM 24 OUTLET VLV 205334-4 Safety Injection E10 1 B GT MO 10 0 O/C Active S2.0P-ST.RPl-0002(Q)  : PIT 2YR 100207 S2. OP-ST .SJ-0004(0) STC CS  : CS-50 100463 21SJ55 21 SAFETY INJ ACCUM 21 OUTLET CHECK VLV 205334-4 Safety Injection D2 1 A/C CK SELF 10 c O/C Active S2.0P-ST.SJ-0020(Q) CTC RF V-24 100828 S2.0P-ST.SJ-0006(Q) CTO RF V-24 100657 S2.0P-ST.SJ-0020(Q) LT 2YR 100828

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 75

---

=--::---* -----------------------~-------:=.,!..--::=~==..:::=---=::..=:-------------------------==..::=*=--::-_ oo....=:::::.:::..:::_,_ * .::*.:.-=.-:::..=--'---=-==--'-- _ .o:--_::._. ::::......--:.== .: .:::~ .::::::::::=-__:;_=.:.

VALVE NO VALVE DESCRIPTION P +ID No P+ JD Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.~ C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK ~TECH. POS.! COMMENTS 22SJ55 22 SAFETY INJ ACCUM 22 OUTLET CHECK VLV 205334-4 Safety Injection D4 1 A/C CK SELF 10 c O/C Active

- -- ---- - - - -- -- - - - - - - - - - - - - - - -- - - - - - - - - -- -- - - - - -- - - - - - - - -- - --. - ------ ---- - -- -- - - .- - -- - - ---- -------- - ~ - - -- -

S2.0P-ST.SJ-0020(0) i CTC i RF V-24 100828 S2.0P-ST.SJ-0006(0) CTO RF V-24 100657 S2.0P-ST.SJ-0020(0) LT 2YR 100828 23SJ55 23 SAFETY INJ ACCUM 23 OUTLET CHECK VLV 205334-4 Safety Injection D7 1 A/C CK SELF 10 c O/C Active 82.0P-ST.SJ-0020(0) i CTC  : RF

' V-24 100828 82.0P-ST.SJ-0006(0) CTO RF V-24 100657 82.0P-ST.SJ-0020(0) LT 2YR 100828 24SJ55 24 SAFETY INJ ACCUM 24 OUTLET CHECK VLV 205334-4 Safety Injection D10 1 A/C CK SELF 10 c O/C Active S2.0P-8T.8J-0020(0) CTC RF V-24 100828 S2. OP-ST .SJ-0006(0) CTO RF V-24 100657 82.0P-8T.SJ-0020(0) LT 2YR 100828 21SJ56 21 SAFETY INJ ACCUM 21 OUTLET CHECK VLV 205334-4 Safety Injection C2 1 A/C CK SELF 10 c O/C Active

82. OP-ST .SJ-0020(0) CTC RF V-25 100828 82.0P-ST.SJ-0006(0) CTO RF V-25 100657 S2.0P-ST.8J-0020(0) LT 2YR 100828 82.0P-8T.SJ-0005(0) PS cs V-25 100200

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 76

---

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VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK ! TECH. POS.! COMMENTS 22SJ56 22 SAFETY INJ COLD LEG 22 CHECK VLV 205334-4 Safety Injection C4 1 A/C CK SELF 10 c O/C Active S2.0P-ST.SJ-0020(Q) CTC  ! RF  ! V-25 100828 S2.0P-ST.SJ-0006(Q) CTO RF V-25 100657 S2.0P-ST.SJ-0020(Q) LT 2YR 100828 S2.0P-ST.SJ-0005(Q) PS CS V-25 100200 23SJ56 23 SAFETY INJ COLD LEG 23 CHECK VLV 205334-4 Safety Injection Cl 1 A/C CK SELF 10 c O/C Active S2.0P-ST.SJ-0020(Q) CTC RF V-25 100828 S2.0P-ST.SJ-0006(Q) CTO RF V-25 100657 S2.0P-ST.SJ-0020(Q) LT 2YR 100828 S2.0P-ST.SJ-0005(Q) PS cs V-25 100200 24SJ56 24 SAFETY INJ COLD LEG 24 CHECK VLV 205334-4 Safety Injection C10 1 A/C CK SELF 10 c O/C Active S2.0P-ST.SJ-0020(Q) CTC RF V-25 100828 S2.0P-ST.SJ-0006(Q) CTO RF V-25 100657 S2.0P-ST.SJ-0020(Q) LT 2YR 100828 S2.0P-ST.SJ-0005(Q) PS cs V-25 100200 2SJ60 2 SAFETY INJ BORON INJ TK TO HOLD UP TK AIR OPRD GLB VLV 205334-4 Safety Injection 84 1 A GB AIR 0.75 c c Passive S2.0P-ST.SJ-0003(Q) FSTC Q 100481 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290759 S2. OP-ST. RP 1-0004(0) PIT 2YR 100872 S2.0P-ST.SJ-0003(Q) STC Q 100481

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 77

- ------- .,:.":;:_-:;==..--=-=-~==-~=---:==..::===..::-=-===------=...;:.::._== -=-- ::o..:. ** .....:.___ __:~-=-=.=::=..-=-==""=-:: ------- - ---

VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC ~TEST TYPE ~TEST FREQ.~ C.S. JUST. ~ R.O. JUST. ~ REL. REQ. ~ RECUR. TASK ; TECH. POS.~ COMMENTS 2SJ63 SAFETY INJ HOT LEG HEADER ACCUMULATOR INLET AIR OPERATED GLOBE VALVE 205334-4 Safety Injection B6 1 B GB AIR 0.75 c c Active S2.0P-ST.SJ-0003(0) FSTC 0 100481 S2.0P-ST.RPl-0002(0)  : PIT 2YR 100207 S2. OP-ST.SJ-0003(0) STC 0 100481 21SJ64 21 SAFETY INJ PMP TO REFUEL WATER STOR TK CHECK VLV 205334-2 Safety Injection D4 2 c CK SELF 0.75 c O/C Active S2.0P-ST.SJ-0002(0) CTC 0 100670 S2.0P-ST.SJ-0001 (0) CTO 0 100669 22SJ64 22 SAFETY INJ PMP 22 MIN FLOW LINE CHECK VLV 205334-2 Safety Injection Dl 2 c CK SELF 0.75 c O/C Active S2.0P-ST.SJ-0001 (0) CTC 0 100669 S2.0P-ST.SJ-0002(0) CTO 0 100670 2SJ67 2 SAFETY INJ PMP MIN FLOW MOV 205334-2 Safety Injection C3 2 B GB MO 2 0 O/C Active S2.0P-ST.RPl-0001 (0) ~ PIT 2YR 100208 S2.0P-ST.SJ-0005(0) STC cs CS-40 100200 2SJ68 2 SAFETY INJ PMP MIN FLOW MOV 205334-2 Safety Injection C2 2 B GB MO 2 0 O/C Active S2.0P-ST.RPl-0001 (0) PIT 2YR 100208 S2. OP-ST .SJ-0005(0) STC cs CS-40 100200

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 78 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC :TEST TYPE :TEST FREQ.: C.S. JUST. ! R.O. JUST. . REL. REQ.; RECUR. TASK ! TECH. POS.! COMMENTS 2SJ69 2 SAFETY INJ RESIDUAL HT REMOVAL PMP SUCT MOV 205334-3 Safety Injection D1 2 B GT MO 12 0 O/C Active S2.0P-ST.RPl-0003(Q) : PIT  : 2YR  ! 100873 S2.0P-ST.RHR-0004(Q) : STC CS  : CS-41 100358 2SJ70 2 SAFETY INJ RESIDUAL HT REMOVAL PMP SUCT CHECK VLV 205334-3 Safety Injection Et 2 C CK SELF 12 0 O/C Active S2.0P-ST.RHR-0005(Q) : CTC RF V-26 100395 S2.0P-ST.RHR-0005(Q) : CTO RF V-26 100395 21SJ93 21 SAFETY INJ ACCUMULATOR N2 INLET AIR OPRD GLB VLV 205334-4 Safety Injection G2 3 B GB AIR 1 c c Passive S2.0P-ST.RPl-0002(Q) ! PIT  : 2YR  :  !  : 100207  :

22SJ93 22 SAFETY INJ ACCUMULATOR N2 INLET AIR OPRD STOP GLB VLV 205334-4 Safety Injection G4 3 B GB AIR 1 c c Passive S2.0P-ST.RPl-0002(Q)  : PIT  : 2YR  :  :  ! 100207  :

23SJ93 23 SAFETY INJ ACCUMULATOR N2 INLET AIR OPRD STOP GLB VLV 205334-4 Safety Injection G7 3 B GB AIR 1 c c Passive S2.0P-ST.RPl-0002(Q)  : PIT 2YR  :  : 100207 24SJ93 24 SAFETY INJ ACCUMULATOR N2 INLET STOP AIR OPRD GLB VLV 205334-4 Safety Injection G10 3 B GB AIR 1 c c Passive S2.0P-ST.RPl-0002(Q)  : PIT 2YR 100207

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 79

==--=-=-~=--=-=-=~---==-=~==--=:...=::...

VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive

- Coordinates Class Cat Type Type Size Position Position Classification

• ' I ' I TEST PROC iTEST TYPE iTEST FREO.i C.S. JUST. i R.O. JUST. i REL. REQ.: RECUR. TASK !TECH. POS.i COMMENTS 21SJ113 21 SAFETY INJ RHR TO CHARGING PMPS MOV 205334-1 Safety Injection E2 2 B GT MO 4 c O/C Active

~ -- - - -- - - -- ---- - -- -- --- - -- - - -- - - -----------. -- -- --- - - ---. -..... - -- - . -- . --- - . .

S2.0P-ST.RPl-0001 (0) i PIT 2YR 100208 S2.0P-ST.SJ-0003(0) STO 0 100481 22SJ113 22 SAFETY INJ CHARGING PMP CROSS OVER MOV 205334-1 Safety Injection E3 2 B GT MO 4 c O/C Active S2.0P-ST.RPl-0001 (0) ! PIT 2YR 100208 S2. OP-ST .SJ-0003(0) STO 0 100481 2SJ123 2 SAFETY INJ BORON INJ TK TO HOLD UP TK AIR OPRD STOP GLB VLV 205334-4 Safety Injection 84 1 A GB AIR 0.75 c c Passive

~ - - ----- ----. --- - ------ - - - - - - - - - --- ------- ---- - - -- -. - - - - -- - ------ - - ---------- - - - - -- - - - - - --- - --- .. -. -- -- - - -- - - -- - . -. -- --

S2.0P-ST.SJ-0003(0) FSTC 0 100481 S2.RA-IS.ZZ-0002(0) LJ 18MO 290760 S2. OP-ST. RPl-0002(0) PIT 2YR 100207 S2. OP-ST.SJ-0003(0) STC 0 100481 21SJ134 21 SAFETY INJ COLD LEG ISOL VLV 205334-2 Safety Injection F9 2 B GT MO 4 0 O/C Active S2.0P-ST.RPl-0004(0)  ! PIT 2YR 100872 S2.0P-ST.SJ-0003(0) STC Q 100481 22SJ134 22 SAFETY INJ PMP 22 TO COLD LEGS VLV 205334-2 Safety Injection FB 2 B GT MO 4 0 O/C Active S2.0P-ST.RPl-0004(0) PIT 2YR 100872 S2.0P-ST.SJ-0003(Q) STC Q 100481

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 80 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I ' I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. i R.O. JUST. i REL. REQ.: RECUR. TASK iTECH. POS.! COMMENTS 2SJ135 2 SAFETY INJ PUMPS DISCH TO COLD LEG MOV 205334-2 Safety Injection G9 1 B GT MO 4 0 O/C Active

~

S2.0P-ST.RPl-0003(Q)  ! PIT 2YR 100873 S2.0P-ST.SJ-0005(Q) STC cs  ! CS-42 100200 21SJ139 21 SAFETY INJ CHECK VLV TO HOT LEG 21 205334-3 Safety Injection D11

• 1 A/C CK SELF 2 c O/C Active S2. OP-ST .SJ-0020(Q) CTC RF V-27 100828 S2.0P-ST.SJ-0015(Q) CTO RF V-27 101047 S2.0P-ST.SJ-0020(Q) LT 2YR 100828 22SJ139 22 SAFETY INJ HOT LEG 22 CHECK VLV 205334-3 Safety Injection C11 1 A/C CK SELF 2 c O/C Active S2.0P-ST.SJ-0020(Q) CTC RF V-27 100828 S2.0P-ST.SJ-0015(Q) CTO RF V-27 101047 S2.0P-ST.SJ-0020(Q) LT 2YR 100828 23SJ139 23 SAFETY INJ HOT LEG 23 CHECK VLV 205334-3 Safety Injection G10 1 A/C CK SELF 2 c O/C Active S2.0P-ST.SJ-0020(Q) CTC RF V-27 100828 S2.0P-ST.SJ-0015(Q) CTO RF V-27 101047 S2. OP-ST .SJ-0020(0) LT 2YR 100828 24SJ139 24 SAFETY INJ HOT LEG 24 CHECK VLV 205334-3 Safety Injection GB 1 A/C CK SELF 2 c O/C Active S2. OP-ST. SJ-0020(Q) CTC RF V-27 100828 S2.0P-ST.SJ-0015(Q) CTO RF V-27 101047 S2.0P-ST.SJ-0020(Q) LT 2YR 100828

TABLE 3-2 -VALVE TEST TABLE 1011197 SALEM NUCLEAR PLANT - UNIT 2 Page 81 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC ~TEST TYPE ~TEST FREQ.! C.S. JUST. ~ R.O. JUST. ~ REL. REQ. ~ RECUR. TASK ~TECH. POS.~ COMMENTS 21SJ144 21 SAFETY INJ COLD LEG 21 CHECK VLV 205334-4 Safety Injection D3 1 A/C CK SELF 2 c O/C Active S2.0P-ST.SJ-0020(Q) CTC RF V-28 100828 S2.0P-ST.SJ-,0014(Q) CTO RF V-28 100154 S2.0P-ST.SJ-0020(Q) LT 2YR 100828 22SJ144 22 SAFETY INJ COLD LEG 22 CHECK VLV 205334-4 Safety Injection F6 1 A/C CK SELF 2 c O/C Active S2.0P-ST.SJ-0020(Q) CTC RF V-28 100828 S2.0P-ST.SJ-0014(Q) CTO RF V-28 100154 S2. OP-ST. SJ-0020(0) LT 2YR 100828 23SJ144 23 SAFETY INJ COLD LEG 23 CHECK VLV 205334-4 Safety Injection FB 1 A/C CK SELF 2 c O/C Active S2.0P-ST.SJ-0020(Q) CTC RF V-28 100828 S2.0P-ST.SJ-0014(Q) CTO RF V-28 100154 S2.0P-ST.SJ-0020(Q) LT 2YR 100828 24SJ144 24 SAFETY INJ COLD LEG 24 CHECK VLV 205334-4 Safety Injection F11 1 A/C CK SELF 2 c O/C Active S2.0P-ST.SJ-0020(Q) CTC RF V-28 100828 S2.0P-ST.SJ-0014(Q) CTO RF V-28 100154 S2.0P-ST.SJ-0020(Q) LT 2YR 100828

TABLE3~-VALVETESTTABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 82

---

===--::.:::.=-==....:...==-=-==--==-- --- ---------------= --=-=-- =::=--- -- - - - - - - - - - : - - - - - - - - - - - -- - - - - -------:=.==--=:.___:=:=-:..:::::..=....-:--==-=-- ---=---=::...:==- -=--- -*

VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC :TEST TYPE :TEST FREQ.: C.S. JUST. : R.O. JUST. : REL. REQ.: RECUR. TASK : TECH. pos.: COMMENTS 2SJ150 2 SAFETY INJ BORON INJ TK TO COLD LEG CHECK VLV 205334-1 Safety Injection F9 1 A/C CK SELF 3 c O/C Active 82.0P-ST.SJ-0020(0) CTC RF V-29 100828 82.0P-ST.SJ-0016(0) CTO RF V-29 101048 S2. OP-ST. SJ-0020(0) LT 2YR 100828 21SJ156 21 SAFETY INJ HOT LEG 21 CKVL 205334-3 Safety Injection G11 1 A/C CK SELF 6 c O/C Active 82.0P-ST.SJ-0020(0) CTC RF V-30 100828 S2.0P-ST .SJ-0015(0) CTO RF V-30 101047 S2.0P-ST.SJ-0020(0) LT 2YR 100828 22SJ156 22 SAFETY INJ HOT LEG 22 CHECK VLV 205334-3 Safety Injection G11 1 A/C CK SELF 6 c O/C Active 82.0P-ST.SJ-0020(0) CTC RF V-30 100828 82.0P-ST.SJ-0015(0) CTO RF V-30 101047 82.0P-ST.SJ-0020(0) LT 2YR 100828 23SJ156 23 SAFETY INJ HOT LEG 23 CHECK VLV 205334-3 Safety Injection H9 1 A/C CK SELF 6 c O/C Active 82.0P-ST.SJ-0020(0) CTC RF V-30 100828 82.0P-ST.SJ-0015(0) CTO RF V-30 101047 82.0P-ST.SJ-0020(0) LT 2YR 100828

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 83

,-,:=:- - - - - - - --::---------*---~--===..--==c:....--==::==-~=-=;;.:.=::....:_-=:::..::..:_--=.....:--=::-.:====--:.:: -

VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK !TECH. POS.! COMMENTS 24SJ156 24 SAFETY INJ HOT LEG 24 CHECK VLV 205334-3 Safety Injection H9 1 A/C CK SELF 6 c O/C Active 82.0P-ST.SJ-0020(0) CTC RF V-30  : 100828 i 82.0P-ST.SJ-0015(0) CTO RF V-30 101047 82.0P-ST.SJ-0020(0) LT 2YR 100828 2SJ158 SAFETY INJECTION TEST LINE AIR OPERATED STOP GLOBE VALVE 205334-4 Safety Injection H1 1 B GB AIR 0.75 c c Active S2. OP-ST .SJ-0003(0) FSTC 0 100481 82.0P-ST.RPl-0002(0)  ! PIT 2YR 100207 82.0P-ST.SJ-0003(0) STC 0 100481 2SJ159 SAFETY INJECTION AIR OPERATED STOP VALVE 205334-4 Safety Injection BB 1 B GB AIR 0.75 c c Active 82.0P-ST.SJ-0003(0) FSTC 0 100481 82.0P-ST.RPl-0002(0)  ! PIT 2YR 100207 82.0P-ST.SJ-0003(0) STC 0 100481 2SJ166 SAFETY INJ BORON INJ TANK TO COLD LEG TEST LINE AIR OPER GLOBE VLV 205334-1 Safety Injection E9 1 B GB AIR 0.75 c c Active 82.0P-ST.SJ-0003(0) FSTC .o  ! 100481 i 82.0P-ST.RPl-0002(0)  ! PIT 2YR 100207 82.0P-ST.SJ-0003(0) STC 0 100481 2SJ167 2 SAFETY INJ COLD LEG LINE SAF RLF VLV 205334-2 Safety Injection GB 2 c RV SELF 0.75 c O/C Active SC.MD-PT.ZZ-0007(0) RV 5YR 290230

TABLE 3-2 -VALVE TEST TABLE 1011197 SALEM NUCLEAR PLANT - UNIT 2 Page 84 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.: C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK ; TECH. POS.! COMMENTS 2SJ417 SJ SYSTEM TEST LINE THERMAL OVERPRESSURIZATION PROTECTION RV 205334-3 Safety Injection DB 2 C RV SELF . 75 C 0 Active SC.MD-PT.ZZ-0007)0) RV 5YR  !  !  : (later) DCP 2EC-3605, see PMCR 970104072 2SS27 2 SMPLG SYS ACCUMULATOR SAMPLE HOR ISOL AIR OPRD GLB VLV 205344-1 Sampling E6 2 A GB AIR 0.375 O/C c Active

- -- -- - -- ------ -- -- - - - -- -- --------- -- -- -- - - --------- - -- -- - - - - --- --------- - - -- - - .- - -- - - - - -- ----- --- - ~ - - - - - - - - - -- ------- .- - -- - - -- -- - - - - -- - - -- ------ -------- - - -- - - - - - - - - - - - - - -- -- - - -- - -- - - -- -- - - -- --

S2.0P-ST.PAS-0001 (0) j FSTC : 0 ~ j 100846 S2.RA-IS.ZZ-0002(0) LJ 18MO 290761 S2.0P-ST .RPl-0004(0) PIT 2YR 100872 S2.0P-ST.PAS-0001 (0) STC 0 100846 2SS33 2 SMPLG SYS REACTOR COOLANT SAMP HOR ISOL AIR OPRD GLB VLV 205344-1 Sampling G6 2 A GB AIR 0.375 O/C c Active S2.0P-ST.PAS-0001 (0) : FSTC  : 0 j 100846 82.RA-IS.ZZ-0002(0) LJ 18MO 290763 82.0P-ST.RPl-0004(0) PIT 2YR 100872 S2.0P-ST.PAS-0001 (0) STC 0 100846 2SS49 2 SMPLG SYS PZR LIQ SAMP ISOL AIR OPRD GLB VLV 205344-1 Sampling G6 2 A GB AIR 0.375 O/C c Active S2.0P-ST.PAS-0001 (0) FSTC 0 100846 82.RA-IS.ZZ-0002(0) LJ 18MO 290765 S2. OP-ST. RP 1-0004(0) PIT 2YR 100872 S2.0P-ST.PAS-0001 (0) STC 0 100846

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 85

= = ------- ---- =-====

VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

~ - --- - - -- - -- -- -------------------- **----------- -------------------------- ------------------------------------------------

TEST PROC !TEST TYPE !TEST FREQ.: C.S. JUST. ~ R.O. JUST. i REL. REQ. i RECUR. TASK ! TECH. POS.: COMMENTS 2SS64 2 SMPLG SYS PZR STEAM SAMP ISOL AIR OPRD GLB VLV 205344-1 Sampling H6 2 A GB AIR 0.375 O/C c Active S2.0P-5T.PAS-0001 (Q) F5TC Q 100846 52.RA-IS.ZZ-0002(0) LJ 18MO 290767 52.0P-5T.RPl-0004(Q) PIT 2YR 100872 52.0P-5T.PA5-0001 (Q) 5TC Q 100846 21SS94 21 SMPLG SYS STEAM GEN SLOWDOWN SAMP ISOL AIR OPRD GLB VLV 205344-1 Sampling 07 2 B GB AIR 0.375 0 c Active S2.0P-5T.PAS-0001 (Q) F5TC a 100846 52.0P-5T.RPl-0004(Q)  ! PIT 2YR 100872 S2.0P-5T.PAS-0001 (Q)  ! STC a 100846 22SS94 22 SMPLG SYS STEAM GEN SLOWDOWN SAMP ISOL AIR OPRD GLB VLV 205344-1 Sampling C7 2 A GB AIR 0.375 0 c Active 52.0P-5T.PA5-0001 (Q) F5TC a 100846 52.0P-5T.RPl-0004(Q)  : PIT 2YR 100872 52.0P-ST.PAS-0001 (Q)  ! STC a 100846 23SS94 23 SMPLG SYS STEAM GEN SLOWDOWN SAMP ISOL AIR OPRD GLB VLV 205344-1 Sampling B7 2 B GB AIR 0.375 0 c Active 52.0P-5T.PAS-0001 (Q) F5TC a 100846 52.0P-ST.RPl-0004(0) PIT 2YR 100872 S2.0P-5T.PAS-0001 (Q) 5TC Q 100846

• I

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 86 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE ~TEST FREQ.: C.S. JUST. j R.O. JUST. j REL. REQ. j RECUR. TASK j TECH. POS.J COMMENTS 24SS94 24 SMPLG SYS STEAM GEN BLOWDOWN SAMP ISOL AIR OPRD GLB VLV 205344-1 Sampling Al 2 A GB AIR 0.315 0 c Active 82.0P-ST.PAS-0001 (Q) FSTC Q  : j 100846 j S2.0P-ST.RPl-0004(Q) j PIT 2YR 100872 82.0P-ST.PAS-0001 (Q) j STC Q 100846 2SS103 2 SMPLG SYS ACCUMULATOR SAMP HOR ISOL AIR OPRD GLB VLV 205344-1 Sampling El 2 A GB AIR 0.315 O/C c Active 82.0P-ST.PAS-0001 (Q) FSTC a 100846 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290762

82. OP-ST. RP 1-0002(0) PIT 2YR 100207 82.0P-ST.PAS-0001 (Q) STC a 100846 2SS104 2 SMPLG SYS REACTOR COOLANT SAMP HOR ISOL AIR OPRD GLB VLV 205344-1 Sampling Gl 2 A GB AIR 0.315 O/C c Active

~ - - -- - - -- -- - - - - --- - ------- --------- - -- - -- - - - - - - -- - -- -- -- - - - --- . - - - -- -- -- -- -- - - - --- -- ---. -- - - -- - - . - . -

82.0P-ST.PAS-0001 (Q) FSTC a '

100846 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290764 S2.0P-ST.RPl-0002(Q) PIT 2YR 100207 82.0P-ST.PAS-0001 (Q) STC a 100846 2SS107 2 SMPLG SYS PZR LIQ SAMP HOR AIR OPRD GLB VLV 205344-1 Sampling Gl 2 A GB AIR 0.315 O/C c Active 82.0P-ST.PAS-0001 (Q) FSTC Q 100846 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290766 S2.0P-ST.RPl-0002(Q) PIT 2YR 100207 82.0P-ST.PAS-0001 (Q) STC Q 100846

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 87 c:= ---~------,------------- ----- ------------------------.,..=::::.:..: -------=--===:=-__;===* -- ----- ----------~*---~------::;.:;:-_;;:;--==~----~-=-===-

VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE!TEST FREQ.: C.S. JUST. : R.O. JUST.: REL. REQ. ! RECUR. TASK !TECH. POS.: COMMENTS 2SS110 2 SMPLG SYS PZR STEAM SAMP HOR ISOL AIR OPRD GLB VLV 205344-1 Sampling H7 2 A GB AIR 0.375 O/C c Active 82.0P-8T.PA8-0001 (Q)  ! F8TC  ! Q  ! 100846 82.RA-18.ZZ-0002(0) LJ 18MO 290768 82.0P-8T.RPl-0002(Q) PIT 2YR 100207 82.0P-8T.PA8-0001 (Q) 8TC Q 100846 21SS181 21 SMPLG SYS OUTBOARD HOT LEG AIR OPRD GLB VLV 205344-3 Sampling C9 2 A GB AIR 0.75 c c Passive 82.0P-8T.PA8-0001 (Q) F8TC Q 100846 82.RA-18.ZZ-0002(0) LJ 18MO 290769 82.0P-8T.RPl-0004(Q) PIT 2YR 100872 82.0P-8T.PA8-0001 (Q) 8TC Q 100846 23SS181 23 SMPLG SYS OUTBOARD HOT LEG AIR OPRD GLB VLV 205344-3 Sampling D9 2 A GB AIR 0.75 c c Passive 82.0P-8T.PA8-0001 (Q) F8TC .: Q  :. 100846 82.RA-18.ZZ-0002(0) LJ 18MO 290773 82.0P-8T.RPl-0004(Q) PIT 2YR 100872 82.0P-8T.PA8-0001 (Q) 8TC Q 100846 21SS182 21 SMPLG SYS INBOARD HOT LEG AIR OPRD GLB VLV 205344-3 Sampling C10 2 A GB AIR 0.75 c c Passive 82.0P-8T.PA8-0001 (Q) F8TC Q 100846 82.RA-18.ZZ-0002(0) LJ 18MO 290770 82.0P-8T.RPl-0002(Q) PIT 2YR 100207 S2.0P-8T.PA8-0001 (Q) 8TC Q 100846

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 88

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VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE ~TEST FREQ.! C.S. JUST. ! R.O. JUST. : REL. REQ. ! RECUR. TASK !TECH. POS.: COMMENTS 23SS182 23 SMPLG SYS INBOARD HOT LEG AIR OPRD GLB VLV 205344-3 Sampling D10 2 A GB AIR 0.75 c c Passive 82.0P-8T.PA8-0001 (Q) F8TC Q 100846 82.RA-18.ZZ-0002(0) LJ 18MO 290774 82.0P-8T.RPl-0002(Q) PIT 2YR 100207 82.0P-8T.PA8-0001 (Q) 8TC Q 100846 23SS184 23 SMPLG SYS INBOARD HOT LEG RETURN AIR OPRD GLB VLV 205344-3 Sampling C 1O 2 A GB AIR 0.75 c c Passive 82.0P-8T.PA8-0001 (Q) F8TC Q 100846 82.RA-18.ZZ-0002(0) LJ 18MO 290775 82.0P-8T.RPl-0002(Q) PIT 2YR 100207 82.0P-8T.PA8-0001 (Q) 8TC Q 100846 23SS185 23 SMPLG SYS OUTBOARD HOT LEG RETURN AIR OPRD GLB VLV 205344-3 Sampling C9 2 A GB AIR 0.75 c c Passive

- --------------- -- - - -- -- -- -- -- -- - - ------ -- - ----- - - -- - - - - - --.. - - - -- - - - - - - - - - - - - ~ -- - -- - - - - -- - - - - -- - -- -- - - --- - --- --- - -

~ ~ - -- --. -- --- -----. -------------- - - - - ----- -- : -- -- - - -- -- - -- - -- -

82.0P-8T.PA8-0001 (Q) F8TC Q 100846 82.RA-18.ZZ-0002(0) LJ 18MO 290776 82.0P-8T.RPl-0004(Q) PIT 2YR 100872 82.0P-8T.PA8-0001 (Q) 8TC Q 100846 21SS188 21 SMPLG SYS INBOARD HOT LEG RETURN AIR OPRD GLB VLV 205344-3 Sampling B10 2 A GB AIR 0.75 c c Passive 82.0P-8T.PA8-0001 (Q) F8TC Q 100846 82.RA-18.ZZ-0002(0) LJ 18MO 290771 82.0P-8T.RPl-0002(Q) PIT 2YR 100207 82.0P-8T.PA8-0001 (Q) 8TC Q 100846

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 89 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ) C.S. JUST. ~ R.O. JUST. ! REL. REQ. ! RECUR. TASK ! TECH. POS.! COMMENTS 21SS189 21 SMPLG SYS OUTBOARD HOT LEG RETURN AIR OPRD GLB VLV 205344-3 Sampling 89 2 A GB AIR 0. 75 C C Passive S2.0P-ST.PAS-0001 (Q) FSTC Q 100846 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290772 S2.0P-ST.RPl-0004(Q) PIT 2YR 100872 S2.0P-ST.PAS-00_01 (Q) STC Q 100846 2SS650 SAMPLING SYSTEM THERMAL OVERPRESSURIZATION PROTECTION RV AUGMENTED 205344-1 Sampling EB N C RV SELF .S c 0 Active SC.MD-PT.ZZ-0007(0) RV 5YR  : i (later) DCP 2EC-3602, see PMCR 970104073 2SV1198 PORV AIR ACCUMULATOR SUPPLY SOLENOID VALVE AUGMENTED 205347-3 No. 2 Unit - React. Cont. & Penetration Area H7 N B 3WAY SOL 1 c 0 Active S2.RA-IS.PZR-0025(Q) FSTO i RF V-35 101094 S2.RA-IS.PZR-0025(Q) STO RF V-35 101094 2SV1199 PORV AIR ACCUMULATOR SUPPLY SOLENOID VALVE AUGMENTED 205347-3 No. 2 Unit - React. Cont. & Penetration Area HS N B* 3WAY SOL 1 c 0 Active

~  ; -- - - - - -- -- - - -- ---- ---------------- -- ----- --- - - -- - - - - - - -- -- - -- - - - - - - - - -- - - - -- -- - - -- - - -- ---- - - -- -- - - - - - - - -- -- -- -- - - - - - - - - - --- -- -- - . -

S2.RA-IS.PZR-0025(Q) FSTO i RF V-35 101094 S2.RA-IS.PZR-0025(Q) STO RF V-35 101094 21SW2 21 SVCE WTR PMP AUTO STRAINER OUTLET CHECK VLV 205342-1 Service Water Nuclear Area Cl 3 c CK SELF 20 O/C O/C Active S2.0P-ST.SW-0001 (Q) CTC Q 100681 S2.0P-ST.SW-0001 (Q) CTO Q 100681

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 90 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification I I '

I TEST PROC ~TEST TYPE ~TEST FREQ.~ C.S. JUST. ~ R.O. JUST. ; REL. REQ.; RECUR. TASK ~TECH. POS.~ COMMENTS 22SW2 22 SVCE WTR AUTO STRAINER OUTLET CHECK VLV 205342-1 Service Water Nuclear Area El 3 c CK SELF 20 O/C O/C Active 82.0P-ST.SW-0002(0) CTC 0 100682 82.0P-ST.SW-0002(0) CTO 0 100682 23SW2 23 SVCE WTR PMP AUTO STRAINER OUTLET CHECK VLV 205342-1 Service Water Nuclear Area Gl 3 c CK SELF 20 0 O/C Active 82.0P-ST.SW-0003(0) CTC .: 0  :' 100683 82.0P-ST.SW-0003(0) CTO 0 100683 24SW2 24 SVCE WTR AUTO STRAINER OUTLET CHECK VLV 205342-2 Service Water Nuclear Area Cl 3 c CK SELF 20 0 O/C Active S2.0P-ST.SW-0004(0) CTC 0 100684 S2. OP-ST .SW-0004(0) CTO 0 100684 25SW2 25 SVCE WTR AUTO STRAINER OUTLET CHECK VLV 205342-2 Service Water Nuclear Area El 3 c CK SELF 20 0 DIC Active S2.0P-ST.SW-0005(0) CTC 0 100685 S2.0P-ST.SW-0005(0) CTO 0 100685 26SW2 26 SVCE WTR AUTO STRAINER OUTLET CHECK VLV 205342-2 Service Water Nuclear Area Gl 3 c CK SELF 20 0 O/C Active S2. OP-ST. SW-0006(0) CTC 0 100686 S2.0P-ST.SW-0006(0) CTO 0 100686

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 91 VALVE NO VALVE DESCRIPTION P+ ID No P+/D Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification I I '

' I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. : R.O. JUST. ! REL. REQ.: RECUR. TASK !TECH. POS.! COMMENTS 22SW5 SVCE WTR PMPS DISCH TO 21 NUCLEAR HEADER 205342-1 Service Water Nuclear Area CB 3 c DCK SELF 24 O/C O/C Active

---

-- -- -- -- - - - - -- - -- - -- -- - - - - - --- - . - - . - - - -- ---- ------ ------- . - - --- - -- -- - - ~ - - - - - - ----- - . ----- .* - - -- - -- - -- - - - - ----.* ---- - -- - - -- - - - - - -. - - -- . -- - ---- ---------- - - - : -- - - -- -- -- - - -- - - -: -- - -- - -- - - - - -------- .. -- - -- - - - - - . --- . . - - - - - - - -- - - - - . - -- . - - .

SC.MD-PM.ZZ-01230) CTC RF V-31  : 204056 TP-6  !

SC.MD-PM.ZZ-0123(0) CTO RF V-31 204056 TP-6 S2.0P-ST.SW-0002(0) PS 0 V-31 100682 S2.0P-ST.SW-0001 (0) PS 0 V-31 100681 S2.0P-ST.SW-0003(0) PS 0 V-31 100683 24SW5 24 SVCE WTR NUCLEAR AREA HEADER CHECK VLV 205342-2 Service Water Nuclear Area FB 3 c DCK SELF 24 O/C O/C Active SC. MD-PM .ZZ-01230) CTC RF V-31 204062 TP-6 SC.MD-PM.ZZ-0123(0) CTO RF V-31 204062 TP-6 S2.0P-ST.SW-0006(0) PS 0 V-31 100686 S2. OP-ST. SW-0005(0) PS 0 V-31 100685 S2. OP-ST. SW-0004(0) PS 0 V-31 100684 21SW13 21 SVCE WTR MTR UPPER BEARING COOLER OUTLET CHECK VLV 205342-1 Service Water Nuclear Area C4 3 G CK SELF 0.75 O/C 0 Active S2.0P-ST.SW-0001 (0) i CTO 0 ' '

100681 22SW13 22 SVCE WTR PMP MTR BEARING COOLER OUTLET CHECK VLV 205342-1 Service Water Nuclear Area E4 - 3 C CK SELF 0.75 O/C 0 Active S2.0P-ST.SW-0002(0)  : CTO 0  !  ! 100682  !

23SW13 23 SVCE WTR PMP MTR UPPER BEARING COOLER OUTLET CHECK VLV 205342-1 Service Water Nuclear Area G4 3 c CK SELF 0.75 O/C 0 Active S2.0P-ST.SW-0003(0)  ; CTO 0 100683

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 92 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC iTEST TYPE iTEST FREQ.: C.S. JUST. i R.O. JUST. i REL. REQ.: RECUR. TASK iTECH. POS.i COMMENTS 25SW13 25 SVCE WTR PMP MTR UPPER BEARING COOLER OUTLET CHECK VLV 205342-2 Service Water Nuclear Area E4 3 c CK SELF 0.15 O/C 0 Active S2.0P-ST.SW-0005(Q) i CTO i Q i  :  ! 100685  !

26SW13 26 SVCE WTR PMP MTR UPPER BEARING COOLER OUTLET CHECK VLV 205342-2 Service Water Nuclear Area G4 3 c CK SELF 0.75 0/C 0 Active S2.0P-ST.SW-0006(Q)  : CTO  ! Q  :  !  : 100686 21SW17 21 SVCE WTR PMP DISCH HEADER CROSS TIE MTR OPRD VLV 205342-1 Service Water Nuclear Area Gl 3 B BFY MO 30 0 0 Active S2.0P-ST .RPl-0005(0) PIT 2YR 100834 S2. OP-ST .SW-0007 (Q) STO Q 100663 22SW17 22 SVCE WTR PUMPS DISCH TRAIN 1 CROSS TIE ISLN MTR OPRD VLV 205342-2 Service Water Nuclear Area Cl 3 B BFY MO 30 0 0 Active S2.0P-ST.RPl-0005(Q) PIT 2YR 100834 S2.0P-ST.SW-0007(Q) STO Q 100663 21SW20 21 SVCE WTR PMP DISCH TO TURBINE GENERATOR AREA MTR OPRD VLV 205342-1 Service Water Nuclear Area Fl 3 B BFY MO 30 O/C c Active S2.0P-ST.RPl-0005(Q) PIT 2YR 100834 S2.0P-ST .SW-0007 (Q) STC Q 100663 22SW20 22 SVCE WTR PMP DISCH TO 21 SYSTEM HEADER MTR OPRD VLV 205342-1 Service Water Nuclear Area CB 3 B BFY MO 24 0 0 Active S2.0P-ST.RPl-0005(Q) PIT 2YR 100834 S2. OP-ST .SW-0007 (Q) Q STO 100663

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 93 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK !TECH. POS.! COMMENTS 23SW20 23 SVCE WTR TURBINE GENERATOR AREA HEADER SUPPLY MTR OPRD VLV 205342-2 Service Water Nuclear Area G7 3 B BFY MO 30 O/C c Active 82.0P-8T.RPl-0005(Q)  ! PIT 2YR 100834 82.0P-8T.8W-0007(Q)  ! 8TC Q 100663 24SW20 24 SVCE WTR NUCLEAR HEADER SUPPLY MTR OPRD VLV 205342-2 Service Water Nuclear Area Fl 3 B BFY MO 24 0 0 Active 82.0P-8T.RPl-0005(Q) i PIT 2YR 100834 82.0P-8T.8W-0007(Q)  ! 8TO Q 100663 21SW21 21 SVCE WTR DIESEL GEN JACKET WTR COOLERS SUPPLY HOR BTFL MOV 205342-3 Service Water Nuclear Area G6 3 B BFY MO 8 0 0 Passive 82.0P-8T.RPl-0001 (Q)  ! PIT 2YR 100208 22SW21 22 SVCE WTR DIESEL GEN JACKET WTR COOLERS SUPPLY HOR BTFL MOV 205342-3 Service Water Nuclear Area G6 3 B BFY MO 8 0 0 Passive 82.0P-8T.RPl-0001 (Q) i PIT 2YR 100208 21SW22 21 SVCE WTR NUCLEAR HOR STOP MTR OPRD BTFL VLV 205342-3 Service Water Nuclear Area F5 3 B BFY MO 24 0 0 Passive 82.0P-8T.RPl-0004(Q) i PIT 2YR '

100872 22SW22 22 SVCE WTR NUCLEAR HEADER SUPPLY MTR OPRD BTFL VLV 205342-3 Service Water Nuclear Area F5 3 B BFY MO 24 0 0 Passive 82.0P-8T.RPl-0004(Q) i PIT 2YR  ! 100872  !

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 94

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*-*--=:~--='--"- ~.:.c;:.::::::::==~:.=..."': . ..;:.-'....:".o:-..:*::..:*.::.:.~.:==--*=**-::::.=-=-::::.=.:=*-=-=---* -*-

VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

• I I I I I TEST PROC iTEST TYPE iTEST FREQ.i C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK :TECH. POS.i COMMENTS 21SW23 21 SVCE WTR NUCLEAR HOR CROSS-CONNECT TO 22 NUCLEAR HOR BTFL MOV 205342-3 Service Water Nuclear Area F5 3 B BFY MO 24 c c Passive S2.0P-ST.RPl-0004(Q) i PIT 2YR 100872 i i S2.0P-ST.SW-0007(Q) ) STC Q 100663 22SW23 22 SVCE WTR NUCLEAR HEADER CROSS-CONN MTR OPRD BTFL VLV 205342-3 Service Water Nuclear Area F6 3 B BFY MO 24 c c Active S2.0P-ST.RPl-0004(Q)  ! PIT 2YR 100872 S2.0P-ST.SW-0007(Q) i STC Q 100663 2SW26 2 SVCE WTR DISCH TO TURB GEN AREA MTR OPRD BTFL VLV 205342-2 Service Water Nuclear Area G10 3 B BFY MO 30 0 c Active S2.0P-ST.RPl-0003(Q)  ! PIT 2YR 100873 .

S2.0P-ST.SW-0011 (Q)  ! STC cs  : CS-43 100347 21SW34 21 SVCE WTR DIESEL GEN 2A JACKET WTR CLR SUPPLY HOR CHECK VLV 205342-3 Service Water Nuclear Area H7 3 C DCK SELF 6 c 0 Active S2.0P-ST.DG-0001(Q) CTO  ! Q 100148 i 22SW34 22 SVCE WTR DIESEL GEN 2A JACKET WTR CLR SUPPLY HOR CHECK VLV 205342-3 Service Water Nuclear Area G7 3 C DCK SELF 6 c 0 Active S2.0P-ST.DG-0001 (Q) CTO Q 100148 21SW36 21 SVCE WTR DIESEL GEN 2B JACKET WTR CLR SUPPLY HOR CHECK VLV 205342-3 Service Water Nuclear Area G7 3 C DCK SELF 6 c 0 Active S2.0P-ST .DG-0002(0) CTO Q 100149

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 95

---~--  :~::..:...::::..:..::======-===-- --- ---------.=~~=--=-*-- __-_...;.--=-~....:;:::==:=..==---~---------*- ------------- ~------**-- .. :==-:.=:.:::.=-=..-:.=c. _ _; __. .:;.: ='-~-- :.:-.*.:. .:. . . :: ::...-==";::.:;_=.:.....::.:o.~::..=:-.==.:...:..--:=:::::;*....:.=---==---"- --

• VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I ' I ' I TEST PROC iTEST TYPE iTEST FREO.i C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK iTECH. POS.i COMMENTS 22SW36 22 SVCE WTR DIESEL GEN 28 JACKET WTR CLR SUPPLY HOR CHECK VLV 205342-3 Service Water Nuclear Area Fl 3 C DCK SELF 6 C 0 Active S2.0P-ST.DG-0002(0) CTO 0 100149 21SW38 21 SVCE WTR DIESEL GEN 2C JACKET WTR CLR SUPPLY HOR CHECK VLV 205342-3 Service Water Nuclear Area F7 3 c DCK SELF .6 c 0 Active S2.0P-ST.DG-0003(0) [ CTO [ 0 i  !  ! 100150 i 22SW38 22 SVCE WTR DIESEL GEN 2C JACKET WTR CLR SUPPLY HDR CHECK VLV 205342-3 Service Water Nuclear Area F7 3 C DCK SELF 6 c 0 Active 52.0P-ST.DG-0003(0) CTO 0 [ [ 100150 i 21SW39 21 SVCE WTR DIESEL GEN 2A JACKET WTRCLR INLET AIR OPRD BALL VLV 205342-3 Service Water Nuclear Area HB 3 B BALL AIR 6 C 0 Active S2.0P-ST.DG-0001 (0) FSTO : 0 100148 S2.0P-ST.DG-0001 (0) STO 0 100148 22SW39 22 SVCE WTR DIESEL GEN 2B JACKET WTR CLR INLET AIR OPRD BALL VLV 205342-3 Service Water Nuclear Area GB 3 B BALL AIR 6 c 0 Active

52. OP-ST. DG-0002(0) FSTO  ; 0 100149 S2. OP-ST. DG-0002(0) STO 0 100149 23SW39 23 SVCE WTR DIESEL GEN 2C JACKET WTR CLR INLET AIR OPRD BALL VLV 205342-3 Service Water Nuclear Area FB 3 B BALL AIR 6 c 0 Active 82.0P-ST.DG-0003(0) FSTO Q 100150

52. OP-ST. DG-0003(0) STO Q 100150

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 96

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- .*-*====~======~~---- ~=====

VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC iTEST TYPE iTEST FREO.i C.S. JUST. i R.O. JUST. ; REL. REQ. i RECUR. TASK i TECH. POS.i COMMENTS 21SW44 21 SVCE WTR DIESEL GEN 2A LUBE OIL CLR OUTLET CHECK VLV 205342-3 Service Water Nuclear Area EB 3 c DCK SELF 6 c 0 Active S2.0P-ST.DG-0001 (0) CTO 0 100148 22SW44 22 SVCE WTR DIESEL GEN 28 LUBE OIL CLR OUTLET CHECK VLV 205342-3 Service Water Nuclear Area DB 3 C DCK SELF 6 c 0 Active S2.0P-ST.DG-0002(0) ! CTO 0 . .  ! . 100149  ! .

23SW44 23 SVCE WTR DIESEL GEN 2C LUBE OIL COOLER OUTLET CHECK VLV 205342-3 Service Water Nuclear Area CB 3 C DCK SELF 6 c 0 Active S2.0P-ST.DG-0003(0) CTO 0 100150 21SW47 21 SVCE WTR DIESEL GEN LUBE OIL COOLERS DISCH HOR CHECK VLV 205342-3 Service Water Nuclear Area E9 3 C DCK SELF B c 0 Active SC.MD-PM.ZZ-0123(0) i CTO RF V-31 204058 TP-6 S2.0P-ST.DG-0001 (0) PS 0 V-31 100422 22SW47 22 SVCE WTR DIESEL GEN LUBE OIL COOLERS TO 22 DISCH HOR CHECK VLV 205342-3 Service Water Nuclear Area D9 3 C DCK SELF B c 0 Active SC.MD-PM.ZZ-0123(0)  ! CTO RF V-31 204059 TP-6 S2.0P-ST.DG-0001 (0) PS 0 V-31 100422 21SW51 21 SVCE WTR CONTAINMENT FAN COIL UNIT NUCLEAR HOR INLET CHECK VLV 205342-6 Service Water Nuclear Area H1 3 C DCK SELF 16 0 O/C Active SC.MD-PM.ZZ-0123(0) CTC RF V-38 204055 TP-6 S2.0P-ST.SW-0010(0) CTO 0 101214

TABLE 3 VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 97 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC [TEST TYPE !TEST FREQ.! C.S. JUST. [ R.O. JUST. ! REL. REQ. ! RECUR. TASK !TECH. POS.! COMMENTS 22SW51 22 SVCE WTR NUCLEAR HOR TO REACTOR CONTAINMENT CHECK VLV 205342-5 Service Water Nuclear Area G3 3 C DCK SELF 16 O OIC Active SC.MD-PM.ZZ-0123(0) i CTC RF V-38 204060 TP-6 S2.0P-ST.SW-0010(0)  ! CTO 0 101214 21SW53 21 SVCE WTR CONTAINMENT FAN COIL UNIT COMMON HOR INLET CHECK VLV 205342-6 Service Water Nuclear Area E1 3 C DCK SELF 10 0 O/C Active SC.RA-IS.ZZ-0007(0) CTC i 0 . . i  : 290328 S2.0P-ST.SW-0010(0)  ! CTO 0 101214 22SW53 24 SVCE WTR CONTAINMENT FAN COIL UNIT COMMON INLET HOR CHECK VLV 205342-6 Service Water Nuclear Area 01 3 C DCK SELF 10 0 O/C Active SC.RA-IS.ZZ-0007(0) CTC 0 290329 S2.0P-ST.SW-0010(0) i CTO 0 101214 21SW57 21 SVCE WTR CONTAINMENT FAN COIL UNIT ISLN AIR OPRD VLV 205342-6 Service Water Nuclear Area H2 3 B GB AIR 8 M 0 Active S2.0P-ST.SW-0010(0)  ! FSTO : 0 101214 S2.0P-ST.SW-0010(0) [ STO 0 101214 22SW57 22 SVCE WTR CONTAINMENT FAN COIL UNIT ISLN AIR OPRD VLV 205342-6 Service Water Nuclear Area F2 3 B GB AIR 8 M 0 Active S2.0P-ST .SW-0010(0) FSTO 0 101214 S2.0P-ST.SW-0010(0) STO 0 101214

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 98 VALVE NO VALVE DESCRIPTION P +ID No P+ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I 1 I I I I '

TEST PROC :TEST TYPE!TEST FREQ.: C.S. JUST. i R.O. JUST. i REL. REQ.: RECUR. TASK !TECH. POS.! COMMENTS 23SW57 23 SVCE WTR CONTAINMENT FAN COIL UNIT ISLN AIR OPRD VLV 205342-6 Service Water Nuclear Area E2 3 B GB AIR 8 M o Active S2.0P-ST.SW-001 O(Q) i FSTO  : Q 101214 82.0P-8T.8W-001 O(Q)  : STO Q 101214 24SW57 24 SVCE WTR CONTAINMENT FAN COIL UNIT ISLN AIR OPRD VLV 205342-6 Service Water Nuclear Area C2 3 B GB AIR 8 M 0 Active S2.0P-ST.SW-001 O(Q) : FSTO ! Q ~  : 101214 S2.0P-ST.8W-001 O(Q)  ! STO Q 101214 25SW57 25 SVCE WTR CONTAINMENT FAN COIL UNIT ISLN AIR OPRD VLV 205342-6 Service Water Nuclear Area B2 3 B GB AIR 8 M 0 Active

--s2:0F>~sr.-sw~oo1-ii(a)"****i*****i=5;:0--*-r-----*a**------,------------*----,----------------*-----------*-----------**--1a1*21*4*------ ----------------- -------*-----------------------------------------***---*-

s2.0P-8T.8w-001oca)  ! sTo a 101214 21SW58 21 SVCE WTR CONTAINMENT FAN COIL UNIT INLET AIR OPRD VLV 205342-6 Service Water Nuclear Area H3 2 B BFY AIR 10 0 O/C Active 82.0P-8T.SW-001 O(Q) F8TC Q 101214 82.0P-8T.RPl-0004(Q) i PIT 2YR 100872 S2.0P-8T.8W~001 O(Q)  : 8TC Q 101214 22SW58 22 SVCE WTR CONTAINMENT FAN COIL UNIT INLET AIR OPRD VLV 205342-6 Service Water Nuclear Area F3 2 B BFY AIR 10 0 O/C Active S2.0P-8T.SW-001 O(Q) F8TC Q 101214 82.0P-8T.RPl-0004(Q) PIT 2YR 100872 S2.0P-ST.SW-001 O(Q) STC Q 101214

l TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 99

- ~~~;::::...:....::.=::==-=-=--=-=-=-~==--------------*-*- -:--=:.:.=::..:..... ..=....-=~--=- *--.

VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC ;TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ.  ! RECUR. TASK i TECH. POS.! COMMENTS 23SW58 23 SVCE WTR CONTAINMENT FAN COIL UNIT INLET AIR OPRD BTFL VLV 205342-6 Service Water Nuclear Area E3 2 B BFY AIR 10 0 O/C Active S2.0P-ST .SW-001 O(Q) FSTC Q 101214 S2.0P-ST.RPl-0004(Q)  ! PIT 2YR 100872 S2.0P-ST.SW-001 O(Q)  ! STC Q 101214 24SW58 24 SVCE WTR CONTAINMENT FAN COIL UNIT INLET AIR OPRD VLV 205342-6 Service Water Nuclear Area C3 2 B BFY AIR 10 0 O/C Active S2.0P-ST.SW-001 O(Q) FSTC Q  ! i 101214 S2.0P-ST.RPl-0004(Q)  : PIT 2YR 100872 S2.0P-ST.SW-001 O(Q)  ! STC Q 101214 25SW58 25 SVCE WTR CONTAINMENT FAN COIL UNIT INLET AIR OPRD VLV 205342-6 Service Water Nuclear Area 83 2 B BFY AIR 10 0 O/C Active S2.0P-ST.SW-001 O(Q) FSTC Q ..

101214 S2.0P-ST.RPl-0004(Q)  : PIT 2YR 100872 S2.0P-ST.SW-0010(Q)  ! STC Q 101214 21SW65 21 SVCE WTR CONTAINMENT FAN COIL UNIT OUTLET AIR OPRD VLV 205342-6 Service Water Nuclear Area H7 3 B BFY AIR 10 M 0 Active S2.0P-ST.SW-001 O(Q)  ! FSTO  : Q 101214 S2.0P-ST.SW-001 O(Q)  : STO Q 101214 22SW65 22 SVCE WTR CONTAINMENT FAN COIL UNIT OUTLET AIR OPRD VLV 205342-6 Service Water Nuclear Area Fl 3 B BFY AIR 10 M 0 Active S2.0P-ST.SW-001 O(Q) FSTO Q 101214 S2.0P-ST.SW-001 O(Q) STO Q 101214

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 100

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VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC iTEST TYPEiTEST FREQ) C.S. JUST. i R.O. JUST. i REL. REQ. i RECUR. TASK iTECH. POS.i COMMENTS 23SW65 23 SVCE WTR CONTAINMENT FAN COIL UNIT OUTLET AIR OPRD VLV 205342-6 Service Water Nuclear Area E6 3 B BFY AIR 10 M 0 Active S2.0P-ST.SW-0010(Q) i FSTO : Q  : 101214  :

S2.0P-ST.SW-0010(Q) i STO Q 101214 24SW65 24 SVCE WTR CONTAINMENT FAN COIL UNIT OUTLET AIR OPRD VLV 205342-6 Service Water Nuclear Area C6 3 B BFY AIR 10 M 0 Active S2.0P-ST.SW-0010(Q)  : FSTO  : Q 101214 S2.0P-ST.SW-0010(Q) i STO Q 101214 25SW65 25 SVCE WTR CONTAINMENT FAN COIL UNIT OUTLET AIR OPRD VLV 205342-6 Service Water Nuclear Area 87 3 B BFY AIR 10 M 0 Active S2.0P-ST.SW-0010(Q) i FSTO  : Q .

' 101214 S2.0P-ST.SW-001 O(Q) i STO Q 101214 21SW72 21 SVCE WTR CONTAINMENT FAN COIL UNIT OUTLET AIR OPRD VLV 205342-6 Service Water Nuclear Area HB 2 B BFY AIR 10 0 O/C Active S2.0P-ST.SW-001 O(Q) FSTC Q 101214 S2.0P-ST.RPl-0004(Q) i PIT 2YR 100872 S2.0P-ST.SW-0010(Q) i STC Q 101214 22SW72 22 SVCE WTR CONTAINMENT FAN COIL UNIT OUTLET AIR OPRD VLV 205342-6 Service Water Nuclear Area Fl 2 B BFY AIR 10 0 O/C Active S2.0P-ST.SW-001 O(Q) FSTC Q 101214 S2.0P-ST.RPl-0004(Q) PIT 2YR 100872 S2.0P-ST.SW-001 O(Q) STC Q 101214

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 101 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC [TEST TYPE[TEST FREQ.: C.S. JUST. : R.O. JUST.: REL. REQ.: RECUR. TASK [TECH. pos.: COMMENTS 23SW72 23 SVCE WTR CONTAINMENT FAN COIL UNIT OUTLET AIR OPRD VLV 205342-6 Service Water Nuclear Area El 2 B BFY AIR 10 0 O/C Active

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - * - - - - - - - - - - - - - - - - - - - ~ - - - - - - - - - - - - - - - - -. - - - - - - - - - - - - - - - - - - - - - - - - - .- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

82.0P-8T.8W-001 O(Q) F8TC Q 101214 S2.0P-8T.RPl-0004(Q) i PIT 2YR 100872 S2.0P-ST.SW-001 O(Q)  : STC Q 101214 24SW72 24 SVCE WTR CONTAINMENT FAN COIL UNIT OUTLET AIR OPRD VLV 205342-6 Service Water Nuclear Area CB 2 B BFY AIR 10 0 O/C Active S2.0P-ST.8W-001 O(Q) FSTC Q 101214 S2.0P-ST.RPl-0004(Q) i PIT 2YR 100872 S2.0P-ST.8W-001 O(Q) i STC Q 101214 25SW72 25 SVCE WTR CONTAINMENT FAN COIL UNIT OUTLET AIR OPRD VLV 205342-6 Service Water Nuclear Area BB 2 B BFY AIR 10 0 O/C Active 82.0P-ST.8W-001 O(Q) F8TC Q 101214 S2.0P-8T.RPl-0004(Q) i PIT 2YR 100872 82.0P-8T.8W-001 O(Q) i 8TC Q 101214 21SW77 21 SVCE WTR CONTMT FAN COIL UNIT COMMON OUTLET HOR CHK VLV 205342-6 Service Water Nuclear Area E10 3 c DCK SELF 10 0 0 Active S2.0P-8T.8W-0010(Q) i CTO Q 101214 22SW77 22 SVCE WTR CONTMT FAN COIL UNIT COMMON OUTLET HOR CHK VLV 205342-6 Service Water Nuclear Area 010 3 C DCK SELF 10 0 0 Active S2.0P-ST.8W-001 O(Q) CTO Q 101214

TABLE 3-2 -VALVE TEST TABLE 1011197 SALEM NUCLEAR PLANT - UNIT 2 Page 102

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------------- -=-....:==~=-~==::...= .. :::...:":.:--~=:......=.....:== ::::...=::::=-;==:::::::--========-.:.=..:..=:....=-=='::'-*= --:::0. "-'-.-- ::. - - - - - -:._::. __-: -:.::::

VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC ~TEST TYPE :TEST FREQ.~ C.S. JUST. ~ R.O. JUST.~ REL. REQ.: RECUR. TASK ~TECH. POS.; COMMENTS 21SW79 21 SVCE WTR NUCLEAR HOR BYPASS TO CIRC WTR DISCH CHECK VLV 205342-3 Service Water Nuclear Area C11 3 c DCK SELF 24 0 0 Active SC.MD-PM.ZZ-01230) CTO RF V-36 204052 S2. OP-ST. SW-0009(0) PS 0 V-36 101022 22SW79 22 SVCE WTR NUCLEAR HOR BYPASS TO CIRC WATER DISCH CHECK VLV 205342-3 Service Water Nuclear Area C10 3 C DCK SELF 24 0 0 Active SC.MD-PM.ZZ-01230) CTO RF V-36  ! 204051 i 82.0P-ST.SW-0009(0) PS 0 V-36 101022 21SW92 21 SVCE WTR CHILLER CONDENSER INLET AIR OPRD GLB VLV 205342-5 Service Water Nuclear Area F4 3 B GB AIR 4 c 0 Active S2.0P-ST.SW-0009(0) FSTO  : 0 101022 S2.0P-ST.SW-0009(0) STO 0 101022 22SW92 22 SVCE WTR CHILLER CONDENSER INLET AIR OPRD VLV 205342-5 Service Water Nuclear Area E4 3 B GB AIR 4 c 0 Active 82.0P-ST.SW-0009(0) FSTO : 0 101022 S2.0P-ST.SW-0009(0) STO 0 101022 23SW92 23 SVCE WTR CHILLER CONDENSER INLET AIR OPRD VLV 205342-5 Service Water Nuclear Area D4 3 B GB AIR 4 c 0 Active S2.0P-ST.SW-0009(0) FSTO  : 0 101022 S2.0P-ST.SW-0009(0) STO 0 101022 21SW99 21 SVCE WTR CHILLER CONDENSER RECIRC PMP DISCH CHECK VLV 205342-5 Service Water Nuclear Area F6 3 c CK SELF 4 O/C c Active S2.0P-ST.SW-0009(0) CTC Q 101022

TABLE 3 VALVE TEST TABLE 1011197 SALEM NUCLEAR PLANT - UNIT 2 Page 103

- --===~=-*=-=:;.:-------------------::=...:..:=-~ ~ ====-==-=~===:

VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK ! TECH. POS.! COMMENTS 22SW99 22 SVCE WTR CHILLER CONDENSER RECIRC PMP DISCH CHECK VLV 205342-5 Service Water Nuclear Area 06 3 c CK SELF 4 O/C c Active S2.0P-ST.SW-0009(Q)  ! CTC Q 101022 23SW99 23 SVCE WTR CHILLER CONDENSER RECIRC PMP DISCH CHECK VLV 205342-5 Service Water Nuclear Area C6 3 c CK SELF 4 O/C c Active S2.0P-ST.SW-0009(Q)  ! CTC  : Q  !  !  ! 101022 21SW122 21 SVCE WTR CMPNT CLG HT EXCHG INLET AIR OPRD BTFL VLV 205342-3 Service Water Nuclear Area 83 3 B BFY AIR 20 M O/C Active

~ ~ -- - - -

82.0P-ST.SW-0008(0) FSTC ! Q i 101021 S2.0P-ST.SW-0008(Q) i STC Q 101021 S2.0P-ST.SW-0008(Q)  ! STO Q 101021 22SW122 22 SVCE WTR CMPNT CLG HT EXCHG INLET CONT VLV 205342-4 Service Water Nuclear Area H6 3 B BFY AIR 20 M OIC Active S2.0P-ST.SW-0008(Q) FSTC Q 101021 S2.0P-ST.SW-0008(Q) i STC Q 101021 S2.0P-ST.SW-0008(Q)  : STO Q 101021 21SW129 21 SVCE WTR CMPNT CLG PMP ROOM COOLER INLET AIR OPRD GLB VLV 205342-3 Service Water Nuclear Area C4 3 B GB AIR 1.5 O/C 0 Active S2.0P-ST.SW-0014(Q) FSTO Q 100569 S2.0P-ST.SW-0014(Q) STO Q 100569

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 104 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification I I I I I I TEST PROC !TEST TYPE !TEST FREQ.: C.S. JUST. ! R.O. JUST. ! REL. REQ. i RECUR. TASK !TECH. POS.! COMMENTS 22SW129 22 SVCE WTR CMPNT CLG PMP ROOM CLR INLET AIR OPRD VLV 205342-4 SeNice Water Nuclear Area G6 3 B GB AIR 2 O/C 0 Active

~ ~  ; - - -- -- - - - -- - - ----. -- - --- . -- --. - .. - . - -. . - . - -- . - - - . - - . - - . - . -

S2.0P-ST.SW-0014(Q) ! FSTO : Q .'

. 100569 S2.0P-ST.SW-0014(Q) : STO Q 100569 2SW137 2 SVCE WTR 21 AUX FDWTR PMP RM CLR INLET AIR OPRD GLB VLV 205342-3 SeNice Water Nuclear Area C4 3 B GB AIR 2 O/C 0 Active S2.0P-ST.SW-0014(Q)  ! FSTO : Q 100569 S2.0P-ST.SW-0014(Q)  ! STO Q 100569 21SW145 21 SVCE WTR CONT SPRAY PMP ROOM CLR INLET AIR OPRD GLB VLV 205342-3 SeNice Water Nuclear Area D4 3 B GB AIR 1.5 O/C 0 Active S2.0P-ST.SW-0014(Q) ! FSTO : Q 100569 S2.0P-ST.SW-0014(Q)  ! STO Q 100569 22SW145 22 SVCE WTR CONT SPRAY PMP ROOM CLR INLET AIR OPRD VLV 205342-4 SeNice Water Nuclear Area Bl 3 B GB AIR 1.5 O/C 0 Active S2.0P-ST.SW-0014(Q)  : FSTO  : Q 100569 S2.0P-ST.SW-0014(Q)  ! STO Q 100569 21SW153 21 SVCE WTR RHR PMP ROOM COOLER INLET AIR OPRD GLB VLV 205342-3 SeNice Water Nuclear Area G4 3 B GB AIR 1.5 O/C 0 Active S2.0P-ST.SW-0014(Q) FSTO Q 100569 S2.0P-ST.SW-0014(Q) STO Q 100569

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 105 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I TEST PROC iTEST TYPE iTEST FREO.i C.S. JUST. : R.O. JUST. i REL. REQ. i RECUR. TASK iTECH. POS.i COMMENTS 22SW153 22 SVCE WTR RHR PMP ROOM CLR INLET AIR OPRD VLV 205342-4 Service Water Nuclear Area F6 3 B GB AIR 1.5 O/C 0 Active S2.0P-ST.SW-0014(0)  ! FSTO  ! 0 100569 S2.0P-ST.SW-0014(0)  ! STO 0 100569 21SW161 21 SERVICE WATER COOLER HEADER TO AUX FEEDWATER STOP BUTTERFLY VALVE 205342-4 Service Water Nuclear Area G9 3 B BFY MAN B c O/C Active

~- - -- - -- - - - - - -- -- - - - - -- - -

S2.0P-ST.AF-0004(0) FSO  ! 0  !  !  !  ! 100655 :

22SW161 21 SERVICE WATER COOLER HEADER TO AUX FEEDWATER STOP BUTTERFLY VALVE 205342-4 Service Water Nuclear Area G9 3 B BFY MAN 8 c O/C Active

- --- - ------- - --- -- -- -- -- - - - -- --------- -- ---- ------ . -- - -- -- - -. -- - - - - -- -- - - - - - - -- .- - - - -- - - -- - - - - - - -- - ~ -- -- -- - - -- - - - - - -- - .- - - -- ---------- -- -. -. -- - - ----- - -- - - -- - - - - - - - .- -- - - - - -- - - - - -- -- - : -- -- --- - -- -- -- ---- - - -- - --- -- - - -- - . ------ -- - -- -- - - -- - . - - -

S2.0P-ST.AF-0004(0) FSO o 100655 ..

2SW163 2 SVCE WTR 22 SAFETY INJ PMP LUBE OIL CLR AIR OPRD VLV 205342-3 Service Water Nuclear Area G4 3 B GB AIR 1.5 c 0 Active S2. OP-ST .SJ-0002(0) FSTO  : o 100670 S2. OP-ST. SJ-0002(0) STO o 100670 2SW169 2 SVCE WTR 21 SAFETY INJ PMP LUBE OIL CLR AIR OPRD GLB VLV 205342-4 Service Water Nuclear Area Cl 3 B GB AIR 1.5 c 0 Active S2.0P-ST.SJ-0001 (0) FSTO  ; o  ;

100669 S2.0P-ST.SJ-0001 (0) STO o 100669 2SW175 2 SVCE WTR 21 SAFETY INJ PMP ROOM CLR INLET AIR OPRD VLV 205342-4 Service Water Nuclear Area Cl 3 B GB AIR 2 c 0 Active S2.0P-ST .SW-0014(0) FSTO Q 100569 S2.0P-ST.SW-0014(Q) STO Q 100569

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 106 VALVE NO VALVE DESCRIPTION P+ ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC :TEST TYPE!TEST FREQ.! C.S. JUST. : R.O. JUST. j REL. REQ. j RECUR. TASK :TECH. pos.: COMMENTS 2SW185 2 SVCE WTR 21 CHG PMP CLRS INLET AIR OPRD VLV 205342-4 Service Water Nuclear Area D7 3 B GB AIR 1.5 c 0 Active S2.0P-ST.CVC-0003(Q) ! FSTO  : Q 100676 S2.0P-ST.CVC-0003(Q) ! STO Q 100676 2SW191 2 SVCE WTR 21 CHG PMP ROOM CLR INLET AIR OPRD VLV 205342-4 Service Water Nuclear Area D7 3 B GB AIR 2 O/C 0 Active S2.0P-ST.SW-0014(Q)  ! FSTO  : Q  :  : 100569 S2.0P-ST.SW-0014(Q)  ! STO Q 100569 2SW199 2 SVCE WTR CHARGING PMP COOLERS OUTLET AIR OPRD GLB VLV 205342-3 Service Water Nuclear Area E4 3 B GB AIR 1.5 c 0 Active S2.0P-ST.CVC-0004(Q  ! FSTO  : Q 100677 S2.0P-ST.CVC-0004(Q)  ! STO Q 100677 2SW205 2 SVCE WTR CHG PMP 22 ROOM CLR INLET AIR OPRD VLV 205342-3 Service Water Nuclear Area E4 3 B GB AIR 2 O/C 0 Active S2.0P-ST.SW-0014(Q)  ! FSTO  : . 100569 S2.0P-ST.SW-0014(Q)  ! STO Q 100569 2SW213 2 SVCE WTR CHG PMP 23 ROOM CLR INLET AIR OPRD VLV 205342-4 Service Water Nuclear Area Bl 3 B GB AIR 1.5 O/C 0 Active S2.0P-ST.SW-0014(Q) FSTO Q 100569 S2.0P-ST.SW-0014(Q) STO Q 100569

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 107 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC :TEST TYPE !TEST FREQ.! C.S. JUST. i R.O. JUST.: REL. REQ.: RECUR. TASK :TECH. POS.: COMMENTS 21SW223 21 SVCE WTR CONTAINMENT FAN COIL UNIT OUTLET AIR OPRD VLV 205342-6 Service Water Nuclear Area H9 3 B GB AIR 8 O/C O/C Active S2.0P-ST.SW-001 O(Q) FSTO Q . .' 101214 S2.0P-ST.SW-001 O(Q)  : STC Q 101214 S2.0P-ST.SW-001 O(Q) i STO Q 101214 22SW223 22 SVCE WTR CONTAINMENT FAN COIL UNIT OUTLET AIR OPRD VLV 205342-6 Service Water Nuclear Area F9 3 B GB AIR 8 O/C O/C Active S2.0P-ST.SW-001 O(Q) FSTO Q 101214 S2.0P-ST.SW-001 O(Q)  ! STC Q 101214 S2.0P-ST.SW-001 O(Q)  ! STO Q 101214 23SW223 23 SVCE WTR CONTAINMENT FAN COIL UNIT ISLN AIR OPRD VLV 205342-6 Service Water Nuclear Area E9 3 B GB AIR 8 O/C O/C Active S2.0P-ST.SW-001 O(Q) FSTO Q 101214 S2.0P-ST.~W-001 O(Q) i STC Q 101214 S2.0P-SJ.SW-001 O(Q)  ! STO Q 101214 24SW223 24 SVCE WTR CONTAINMENT FAN COIL UNIT OUTLET AIR OPRD VLV 205342-6 Service Water Nuclear Area C9 3 B GB AIR 8 O/C O/C Active S2.0P-ST.SW-001 O(Q) FSTO Q 101214 S2.0P-ST.SW-001 O(Q) STC Q 101214 S2.0P-ST.SW-001 O(Q) STO Q 101214

TABLE 3-2 -VALVE TEST TABLE 1011197 SALEM NUCLEAR PLANT - UNIT 2 Page 108 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name . Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC iTEST TYPE iTEST FREO.i C.S. JUST. : R.O. JUST. i REL. REQ. i RECUR. TASK iTECH. POS.i COMMENTS 25SW223 25 SVCE WTR CONTAINMENT FAN COIL UNIT OUTLET AIR OPRD VLV 205342-6 Service Water Nuclear Area B9 3 B GB AIR B O/C O/C Active

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S2.0P-ST.SW-0010(0) FSTO 0 101214 S2.0P-ST.SW-0010(0) STC 0 101214 S2.0P-ST.SW-0010(0) STO 0 101214 2SW308 2 SVCE WTR PRESS CONT HOR CONTROL BALL VLV 205342-1 Service Water Nuclear Area B6 3 B BALL AIR B c c Passive No inservice testing required for this component.

2SW311 2 SVCE WTR PRESS CONT HOR CONTROL BALL VLV 205342-2 Service Water Nuclear Area H4 3 B BALL AIR B c c Passive

:  :  : No inservice testing required for this component.

21SW531 21 SVCE WTR CONTAINMENT FAN COIL UNIT OUTLET RELIEF VALVE 205342-6 Service Water HB 3 c RV SELF 1 c 0 Active SC.MD-PT.ZZ-0007(0) RV RF (later) DCP 2EC-3590, see PMCR 961017267 22SW531 22 SVCE WTR CONTAINMENT FAN COIL UNIT OUTLET RELIEF VALVE 205342-6 Service Water FB 3 c RV SELF 1 c 0 Active SC.MD-PT.ZZ-0007(0) RV RF (later) DCP 2EC-3590, see PMCR 961017267 23SW531 23 SVCE WTR CONTAINMENT FAN COIL UNIT OUTLET RELIEF VALVE 205342-6 Service Water EB 3 c RV SELF 1 c 0 Active SC.MD-PT.ZZ-0007(0) RV RF (later) DCP 2EC-3590, see PMCR 961017267 24SW531 24 SVCE WTR CONTAINMENT FAN COIL UNIT OUTLET RELIEF VALVE 205342-6 Service Water CB 3 c RV SELF 1 c 0 Active SC.MD-PT.ZZ-0007(0) RV RF (later) DCP 2EC-3590 , see PMCR 961017267

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 109

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VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I 1 I I I I TEST PROC :TEST TYPE :TEST FREQ.: C.S. JUST. : R.O. JUST. : REL. REQ.: RECUR. TASK : TECH. POS.: COMMENTS 25SW531 25 SVCE WTR CONTAINMENT FAN COIL UNIT OUTLET RELIEF VALVE 205342-6 Service Water BB 3 c RV SELF 1 c 0 Active SC.MD-PT.ZZ-0007(0) RV RF  ;  :  : (later)  ; DCP 2EC-3590, see PMCR 961017267 21SW532 21 SVCE WTR CONTAINMENT FAN COIL UNIT NUCLEAR HOR INLET CHECK VLV 205342-6 Service Water Nuclear Area Ht 3 C DCK SELF 16 0 O/C Active SC.MD-PM.ZZ-0123(0)  : CTC RF V-38 204869 TP-6 S2.0P-ST.SW-0010(0)  : CTO 0 101214 22SW532 22 SVCE WTR NUCLEAR HOR TO REACTOR CONTAINMENT CHECK VLV 205342-5 Service Water Nuclear Area G3 3 c DCK SELF 16 0 O/C Active

~ ~ -. --. --- - - - . -

SC.MD-PM.ZZ-0123(0)  : CTC  : RF  :  : V-38 204887 TP-6 82.0P-ST.SW-0010(0)  ! CTO 0 101214 21SW534 21 SERVICE WATER ACCUMULATOR VESSEL DISCHARGE ISOLATION VLV 205342-7 Service Water Nuclear Area F9 3 B BFY AIR 10 c O/C Active S2.0P-ST.SW-0010(0) FSTO 0 101214 S2.0P-ST.SW-0010(0)  : STC 0 101214 82.0P-ST.SW-0010(0)  : STO 0 101214 22SW534 22 SERVICE WATER ACCUMULATOR VESSEL DISCHARGE ISOLATION VLV 205342-7 Service Water Nuclear Area 89 3 B BFY AIR 10 c O/C Active S2.0P-ST.SW-0010(0) FSTO 0 101214 S2.0P-ST.SW-0010(0) STC 0 101214 S2.0P-ST.SW-001 O(Q) STO 0 101214

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 110 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE :TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK !TECH. POS.! COMMENTS 21SW535 21 SERVICE WATER ACCUMULATOR VESSEL DISCHARGE ISOLATION VLV 205342-7 Service Water Nuclear Area F9 3 B BFY AIR 10 c 0/C Active

~

S2.0P-ST.SW-0010(0)  ! FSTO 0  !  ! 101214 S2.0P-ST.SW-0010(0)  : STC 0 101214 S2.0P-ST.SW-0010(0)  : STO 0 101214 22SW535 22 SERVICE WATER ACCUMULATOR VESSEL DISCHARGE ISOLATION VLV 205342-7 Service Water Nuclear Area 89 3 B BFY AIR 10 c OIC Active S2.0P-ST.SW-0010(0) j FSTO j 0 . . 101214 .  !

S2.0P-ST.SW-0010(0)  ! STC 0 101214 S2.0P-ST.SW-0010(0)  ! STO 0 101214 21SW536 21 NUCLEAR SUPPLY HEADER COLUMN SEPARATION PROTECTION CHECK VLV 205342-7 Service Water Nuclear Area FB 3 c DCK SELF 10 c O/C Active S2.0P-ST.SW-0010(0)  ! CTC 0 101214 SC.MD-PM.ZZ-0123(0)  : CTO RF V-39 204888 22SW536 22 NUCLEAR SUPPLY HEADER COLUMN SEPARATION PROTECTION CHECK VLV 205342-7 Service Water Nuclear Area CB 3 c DCK SELF 10 c O/C Active 82.0P-ST.SW-0010(0)  : CTC 0  ! 101214  !

SC.MD-PM.ZZ-0123(0)  : CTO RF V-39 204889 21SW596 21 SERVICE WATER ACCUMULATOR VESSEL WATER FILL CHECK VLV 205342-7 Service Water Nuclear Area GS 3 c CK SELF 1 c c Active S2.0P-ST.SW-001 O(Q)  : CTC 0 101214

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 111

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VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC :TEST TYPE :TEST FREQ.: C.S. JUST. : R.O. JUST. : REL. REQ.: RECUR. TASK :TECH. POs.: COMMENTS 22SW596 22 SERVICE WATER ACCUMULATOR VESSEL WATER FILL CHECK VLV 20S342-7 Service Water Nuclear Area cs 3 c CK SELF 1 c c Active 82.0P-8T.8W-001 O(Q) CTC Q 101214 21SW597 21 SERVICE WATER ACCUMULATOR VESSEL WATER FILL CHECK VLV 20S342-7 Service Water Nuclear Area GS 3 C CK SELF 1 c c Active 82.0P-8T.8W-0010(0) CTC Q  ! j j 101214 j 22SW597 22 SERVICE WATER ACCUMULATOR VESSEL WATER FILL CHECK VLV 20S342-7 Service Water Nuclear Area CS 3 C CK SELF 1 c c Active 82.0P-ST.SW-001 O(Q) CTC Q 101214 2SW626 21 SVCE WTR ACCUMULATOR VESSEL RELIEF VALVE 20S342-7 Service Water H2 3 c RV SELF 1 c 0 Active*

8C.MD-PT.ZZ-0007(0) j RV j SYR  : 204886  : Added per DCP 2EC-3590 2SW628 22 SVCE WTR ACCUMULATOR VESSEL RELIEF VALVE 20S342-7 Service Water D2 3 c. RV SELF 1 c 0 Active 8C.MD-PT.ZZ-0007(0)  : RV SYR j (later) DCP 2EC-3590, see PMCR 961017267 21SW640 21 SERVICE WATER ACCUMULATOR VESSEL NITROGEN FILL CHECK VLV 20S342-7 Service Water Nuclear Area H4 3 c CK SELF 1 c c Active 82.0P-ST.8W-001 O(Q) CTC Q 101214 22SW640 22 SERVICE WATER ACCUMULATOR VESSEL NITROGEN FILL CHECK VLV 20S342-7 Service Water Nuclear Area D4 3 c CK SELF 1 c c Active 82.0P-8T.8W-0010(0) i CTC 0 101214

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 112 VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK ! TECH. POS.! COMMENTS 21SW641 21 SERVICE WATER ACCUMULATOR VESSEL NITROGEN FILL CHECK VLV 205342-7 Service Water Nuclear Area H4 3 c CK SELF 1 c c Active S2.0P-ST.SW-0010(Q) ! CTC a 101214 22SW641 22 SERVICE WATER ACCUMULATOR VESSEL NITROGEN FILL CHECK VLV 205342-7 Service Water Nuclear Area 04 3 c CK SELF 1 c c Active S2.0P-ST.SW-001 O(Q)  : CTC a 101214 2VC1 2 CONTMT VENT PURGE SUPPLY LINE OUTBD ISLN AIR OPRD BTFL VLV 205338-2 Reactor Containment - Ventilation 03 2 A BFY AIR 36 DIC c Active S2.0P-ST.CBV-0002(Q) ! FSTC ! CS . CS-48  ! . 100843 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290777 S2.0P-ST.RPl-0003(Q) PIT 2YR 100873 S2.0P-ST.CBV-0002(Q) STC .CS CS-48 100843 2VC2 2 CONTMT VENT PURGE SUPPLY ISLN AIR OPRD BTFL VLV 205338-2 Reactor Containment - Ventilation 02 2 A BFY AIR 36 O/C c Active S2.0P-ST.CBV-0002(Q) FSTC : CS CS-49 i 100843 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290778 S2.0P-ST.RPl-0002(Q) PIT 2YR 100207 S2.0P-ST.CBV-0002(Q) STC CS CS-49 100843 2VC3 2 CONTMT VENT PURGE EXH LINE INBD ISLN AIR OPRD BTFL VLV 205338-2 Reactor Containment - Ventilation E2 2 A BFY AIR 36 c c Active S2.0P-ST.CBV-0002(Q) FSTC cs CS-49 100843 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290780 S2.0P-ST.RPl-0002(Q) PIT 2YR 100207 S2.0P-ST.CBV-0002(Q) STC cs CS-49 100843

l TABLE 3-2 -VALVE TEST TABLE 1011197 SALEM NUCLEAR PLANT - UNIT 2 Page 113 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC :TEST TYPE ;TEST FREQ.: C.S. JUST. : R.O. JUST. ; REL. REQ.: RECUR. TASK : TECH. pos.: COMMENTS 2VC4 2 CONTMT VENT PURGE EXH LINE OUTBD ISLN AIR OPRD BTFL VLV 205338-2 Reactor Containment - Ventilation E3 2 A BFY AIR 36 c c Active S2. OP-ST. CBV-0002(0) FSTC cs C8-48 100843 S2.RA-IS.ZZ-0002(0) LJ 18MO 290781 S2. OP-ST. RP 1-0003(0) PIT 2YR 100873 S2.0P-ST.CBV-0002(0) STC cs C8-48 100843 2VC5 2 CONTMT VENT CONT PRESS TEST INBD AIR OPRD BTFL VLV 205338-2 Reactor Containment - Ventilation D3 2 A BFY AIR 10 O/C c Active 82.0P-ST.CBV-0001 (0) F8TC : 0  ! 100845  !

S2.RA-18.ZZ-0002(0) LJ 18MO 290782 S2.0P-ST.RPl-0004(0) PIT 2YR 100872 S2.0P-8!-CBV-0001 (0) STC 0 100845 2VC6 2 CONTMT VENT CONT PRESS TEST OUTBD AIR OPRD BTFL VLV 205338-2 Reactor Containment - Ventilation D2 2 A BFY AIR 10 O/C c Active 82.0P-ST.CBV-0001 (0) FSTC 0 100845 82.RA-IS.ZZ-0002(0) LJ 18MO 290783 S2.0P-ST.RPl-0002(0) PIT 2YR 100207 82.0P-8T.CBV-0001 (0) STC 0 100845 2VC7 2 CONTMT VENT RAD MONITORING SYS OUTLET AIR OPRD GLB VLV 205338-1 Reactor Containment - Ventilation H6 2 A GB AIR 0.75 0 c Active 82.0P-ST.CBV-0001 (0) FSTC 0 100845 82.RA-IS.ZZ-0002(0) LJ 18MO 290784 82.0P-ST.RPl-0002(0) PIT 2YR 100207 82.0P-8T.CBV-0001 (Q) STC 0 100845

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 114 VALVE NO VALVE DESCRIPTION P +ID No P+IDName Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I ' I I I TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK ! TECH. POS.! COMMENTS 2VC8 2 CONTMT VENT RAD MONITORING SYS OUTBD OUTLET AIR OPRD. GLB VLV 20S338-1 Reactor Containment - Ventilation HS 2 A GB AIR 0.7S 0 c Active S2.0P-ST.CBV-0001 (0) FSTC 0 100845 52.RA-IS.ZZ-0002(0) LJ 18MO 290785 52.0P-ST .RPl-0004(0) PIT 2YR 100872 52.0P-ST.CBV-0001 (0) STC 0 100845 2VC9 2 CONTMT VENT RAD MONITORING SYS OUTLET AIR OPRD GLB VLV 20S338-1 Reactor Containment - Ventilation H6 2 A GB AIR 0.7S c c Passive S2.0P-ST.CBV-0001(0)  ! FSTC 0  ! 100845 52.RA-IS.ZZ-0002(0) LJ 18MO 290786

52. OP-ST .RPl-0002(0) PIT 2YR 100207 52.0P-ST.CBV-0001 (0) STC 0 100845 2VC10 2 CONTMT VENT RAD MONITORING SYS OUTBD OUTLET AIR OPRD GLB VLV 20S338-1 Reactor Containment - Ventilation HS 2 A GB AIR 0.7S c c Passive 52.0P-ST.CBV-000.1 (0) FSTC 0 100845 S2. RA-IS.ZZ-0002(0) LJ 18MO 290787 52.0P-ST.RPl-0004(0) PIT 2YR 100872 52.0P-ST.CBV-0001 (Q) STC 0 100845 2VC11 2 CONTMT VENT RAD MONITORING SYS SAMPLE INLET AIR OPRD GLB VLV 20S338-1 Reactor Containment - Ventilation G6 2 A GB AIR 0.7S 0 c Active 52.0P-ST.CBV-0001 (0) FSTC 0 100845 52.RA-IS.ZZ-0002(0) LJ 18MO 290788 S2.0P-ST :RPl-0002(0) PIT 2YR 100207 52.0P-ST.CBV-0001 (Q) STC 0 100845

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 115

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VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC :TEST TYPE :TEST FREQ.i C.S. JUST. : R.O. JUST. i REL. REQ.: RECUR. TASK i TECH. POS.i COMMENTS 2VC12 2 CONTMT VENT RAD MONITORING SYS OUTBD INLET AIR OPRD GLB VLV 20S338-1 Reactor Containment - Ventilation GS 2 A GB AIR 0.7S 0 c Active 82.0P-8T.CBV-0001 (Q) .: F8TC .; Q .; 100845 82.RA-18.ZZ-0002(Q) LJ 18MO 290789 82.0P-8T.RPl-0004(Q) PIT 2YR 100872 82.0P-8T.CBV-0001 (Q) 8TC Q 100845 2VC13 2 CONTMT VENT RAD MONITORING SYS INLET AIR OPRD GLB VLV 20S338-1 Reactor Containment - Ventilation G6 2 A GB AIR 0.7S c c Passive 82.0P-8T.CBV-0001 (Q) F8TC Q 100845 82.RA-18.ZZ-0002(Q) LJ 18MO 290792 82.0P-8T.RPl-0002(Q) PIT 2YR 100207 82.0P-8T.CBV-0001 (Q) 8TC Q 100845 2VC14 2 CONTMT VENT RAD MONITORING SYS OUTBD INLET AIR OPRD GLB VLV 20S338-1 Reactor Containment - Ventilation GS 2 A GB AIR 0.7S c c Passive 82.0P-ST.CBV-0001 (Q) F8TC Q 100845 82.RA-18.ZZ-0002(Q) LJ 18MO 290793 82.0P-ST.RPl-0004(Q) PIT 2YR 100872 82.0P-ST.CBV-0001 (Q) 8TC Q 100845 21VC17 21 POST ACC SAMP PEN 36 OUTBD AIR SAMPLE SPLY AIR OPRD GATE VLV 20S344-3 Sampling G9 2 A GB AIR 0.7S c c Passive 82.0P-ST.CBV-0001 (Q) F8TC Q 100845 82.RA-IS.ZZ-0002(Q) LJ 18MO 290794 S2.0P-ST.RPl-0004(Q) PIT 2YR 100872 82.0P-ST.CBV-0001 (Q) STC Q 100845

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 116

.:_....:::...:..::::------====--..::.====-=-=-_:;_;------------------.""--=-~.::-

VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC fTEST TYPEfTEST FREQ.: C.S. JUST. ! R.O. JUST.! REL. REQ. ! RECUR. TASK f TECH. pas.! COMMENTS 22VC17 22 POST ACC SAMP PEN 30 AIR SAMPLE SPLY AIR OPRD GATE VLV 205344-3 Sampling E9 2 A GB AIR 0.75 c c Passive S2.0P-ST.CBV-0001 (0) : FSTC [ 0 [ . 100845 '

S2.RA-IS.ZZ-0002(0) LJ 18MO 290790 S2.0P-ST.RPl-0004(0) PIT 2YR 100872 S2.0P-ST.CBV-0001 (0) STC 0 100845 21VC18 21 POST ACC SAMP PEN 36 OUTBD AIR SAMPLE RETURN AIR OPRD GATE VLV 205344-3 Sampling F9 2 A GB AIR 0.75 c c Passive S2.0P-ST.CBV-0001 (0) FSTC o 100845 S2.RA-IS.ZZ-0002(0) LJ 18MO 290796 S2. OP-ST. RP 1-0004(0) PIT 2YR 100872 S2.0P-ST.CBV-0001 (0) STC o 100845 22VC18 22 POST ACC SAMP PEN 30 OUTBD AIR SAMPLE RETURN AIR OPRD GATE VLV 205344-3 Sampling E9 2 A GB AIR 0.75 c c Passive S2.0P-ST.CBV-0001 (0) [ FSTC  : 0 100845 S2.RA-IS.ZZ-0002(0) LJ 18MO 290798 S2.0P-ST.RPl-0004(0) PIT 2YR 100872 S2.0P-ST.CBV-0001 (0) STC 0 100845 21VC19 21 POST ACC SAMP PEN 36 INBD AIR SAMPLE SPLY AIR OPRD GATE VLV 205344-3 Sampling G10 2 A GB AIR 0.75 c c Passive S2.0P-ST.CBV-0001 (0) FSTC o 100845 S2. RA-IS .ZZ-0002(0) LJ 18MO 290795 S2.0P-ST.RPl-0002(0) PIT 2YR 100207 S2.0P-ST.CBV-0001 (0) STC o 100845

TABLE 3-2 -VALVE TEST TABLE 1011197 SALEM NUCLEAR PLANT - UNIT 2 Page 117 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

~ -- - - --- - - - - -- - - -- --------- - ---- - - -- -- -- -- -- - - -- - - -- -- - - --- ---- - ----- - . - - - - - -- -- - . - - - - - - -- ---- -- -- - ------- -------- ------ - - - - - - - - -- - - - - ---- ---- -- -- - ------- -- - -- --- -- - - - -- - - -- -- - -- ---- . - --

TEST PROC [TEST TYPE [TEST FREQ.[ C.S. JUST. [ R.O. JUST. [ REL. REQ. [ RECUR. TASK [TECH. POS.! COMMENTS 22VC19 22 POST ACC SAMP PEN 30 INBD AIR SAMPLE SPLY AIR OPRD GATE VLV 205344-3 Sampling E10 2 A GB AIR 0. 75 C C Passive 82.0P-8T.CBV-0001 (Q) F8TC Q 100845 82.RA-18.ZZ-0002(0) LJ 18MO 290791 82.0P-8T.RPl-0002(Q) PIT 2YR 100207 82.0P-8T.CBV-0001 (Q) 8TC Q 100845 21VC20 21 POST ACC SAMP PEN 36 INBD AIR SAMPLE RETURN AIR OPRD GATE VLV 205344-3 Sampling F10 2 A GB AIR 0.75 c c Passive 82.0P-8T.CBV-0001 (Q) F8TC : Q  !  ! 100845 82.RA-18.ZZ-0002(0) LJ 18MO 290797 82.0P-8T.RPl-0002(Q) PIT 2YR 100207 82.0P-8T.CBV-0001 (Q) 8TC Q 100845 22VC20 22 POST ACC SAMP PEN 30 INBD AIR SAMPLE RETURN AIR OPRD GATE VLV 205344-3 Sampling E10 2 A GB AIR 0. 75 C C

• Passive 82.0P-8T.CBV-0001 (Q) F8TC Q 100845 82.RA-18.ZZ-0002(0) LJ 18MO 290799 82.0P-8T.RPl-0002(Q) PIT 2YR 100207 82.0P-8T.CBV-0001 (Q) 8TC Q 100845 2WL12 2 RAD WST LQD RC DR PMP DISCH ISOL AIR OPRD DIAPH VLV 205339-3 Waste Disposal Liquid B7 2 A DIA AIR 3 c c Active 82.0P-8T.ZZ-0003(Q) F8TC Q 100665 82.RA-18.ZZ-0002(0) LJ 18MO 290800 82.0P-8T.RPl-0002(Q) PIT 2YR 100207 82.0P-8T.ZZ-0003(Q) 8TC Q 100665

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 118

=--- ~-- -- - - - - - - - - - - - - - - - - - - * -==;=::-=-=-=-=-=:~=-=---=---=..:...-==--===---==-==-----:=--~==-..:._ -=-=

VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC !TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ! REL. REQ. ! RECUR. TASK ! TECH. pos.! COMMENTS 2WL13 2 RAD WST LQD RC DR PMP DISCH AIR OPRD ISOL DIAPH VLV 205339-3 Waste Disposal Liquid Bl 2 A DIA AIR 3 0 c Active S2.0P-ST.ZZ-0003(Q) ~ FSTC Q ~ i i 100665 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290801 S2.0P-ST.RPl-0004(Q) PIT 2YR 100872 S2.0P-ST.ZZ-0003(Q) STC Q 100665 2WL16 2 RAD WST LQD CONTAINMENT SUMP PMP DISCH TO WST AIR OPRD DIAPH VLV 205339-3 Waste Disposal Liquid Bl 2 A GB AIR 3 0 c Active S2.0P-ST.ZZ-0003(Q) FSTC Q 100665 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290802 S2.0P-ST.RPl-0002(Q) PIT 2YR 100207 S2. OP-ST.ZZ-0003(0) STC Q 100665 2WL17 2 RAD WST LQD CONTAINMENT SUMP PMP DISCH TO WST AIR OPRD DIAPH VLV 205339-3 Waste Disposal Liquid BB 2 A GB AIR 3 0 c Active S2.0P-ST.ZZ-0003(Q) FSTC Q 100665 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290803 S2.0P-ST.RPl-0004(Q) PIT 2YR 100872 S2.0P-ST.ZZ-0003(Q) STC Q 100665 2WL96 2 RAD WST LQD RC DR TK TO GAS ANALYZER AiR OPRD DIAPH VLV 205339-3 Waste Disposal Liquid Fl 2 A DIA AIR 0.75 c c Active S2. OP-ST .ZZ-0003 (Q) FSTC Q 100665 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290804 S2.0P-ST.RPl-0002(Q) PIT 2YR 100207 S2.0P-ST.ZZ-0003(Q) STC Q 100665

TABLE 3-2 -VALVE TEST TABLE 1011197 SALEM NUCLEAR PLANT - UNIT 2 Page 119

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VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification TEST PROC :TEST TYPE :TEST FREQ.: C.S. JUST. : R.O. JUST. : REL. REQ.: RECUR. TASK :TECH. pos.: COMMENTS 2WL97 2 RAD WST LQD RC DR TK TO GAS ANALYZER AIR OPRD DIAPH VLV 205339-3 Waste Disposal Liquid FB 2 A DIA AIR 0.75 c C Active 82.0P-ST.ZZ-0003(0) FSTC 0  : 100665  :

82.RA-IS.ZZ-0002(0) LJ 18MO 290805 82.0P-ST.RPl-0004(0) PIT 2YR 100872 82.0P-ST.ZZ-0003(0) STC 0 100665 2WL98 2 RAD WST LQD RC DR TK TO VENT HOR AIR OPRD DIAPH VLV 205339-3 Waste Disposal Liquid Fl 2 A DIA AIR 1 0 c Active 82.0P-ST.ZZ-0003(0) FSTC Q 100665 82.RA-IS.ZZ-0002(0) LJ 18MO 290806 82.0P-ST.RPl-0002(0) PIT 2YR 100207 82.0P-ST.ZZ-0003(0) STC 0 100665 2WL99 2 RAD WST LQD RC DR TK TO VENT HOR AIR OPRD DIAPH VLV 205339-3 Waste Disposal Liquid F9 2 A DIA AIR 1 0 c Active 82.0P-ST.ZZ-0003(0) FSTC Q .

' 100665 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290807 S2.0P-ST.RPl-0004(Q) PIT 2YR 100872 82.0P-ST.ZZ-0003(0) STC Q 100665 2WL108 2 RAD WST LQD N2 SUPPLY TO RC DR TK AIR OPRD DIAPH VLV 205339-3 Waste Disposal Liquid G9 2 A DIA AIR 1 c c Active

82. OP-ST .ZZ-0003(0) FSTC 0 100665 82.RA-IS.ZZ-0002(0) LJ 18MO 290808 S2. 0 P-ST. RP 1-0004(0) PIT 2YR 100872 S2. OP-ST .ZZ-0003(0) STC 0 100665

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 120 VALVE NO VALVE DESCRIPTION P +ID No P+ ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I t I I I t TEST PROC :TEST TYPE :TEST FREQ.: C.S. JUST. : R.O. JUST. : REL. REQ. i RECUR. TASK iTECH. pos.: COMMENTS 2WL190 2 RAD WST LQD REFUEL CANAL INLET DIAPH VLV 205339-3 Waste Disposal Liquid F3 2 A DIA MAN 3 LC c Passive S2.RA-IS.ZZ-0002(0) LJ 1SMO  ! 290757  !

2WL191 2 RAD WST LQD REFUEL WTR PURIFICATION PMP SUCT DIAPH VLV 205339-3 Waste Disposal Liquid E2 2 A DIA MAN 3 LC c Passive

---

.------------------.------------------;------------------:------------------;-----------------;-------------------------:-----------------7------------------------------------------------------------

S2.RA-IS.ZZ-0002(0) LJ 1BMO  :  : 290755 2WL475 CONTAINMENT ISO VLV OVERPRESSURE PROTECTION RELIEF VALVE AUGMENTED 205339-3 Waste Disposal Liquid Cl N C RV SELF 1 c 0 Active SC.MD-PT.ZZ-0007(0) ' RV 5YR i (later)  : DCP 2EC-3612, see PMCR 970320324 2WL476 CONTAINMENT ISO VLV OVERPRESSURE PROTECTION RELIEF VALVE 205339-3 Waste Disposal Liquid Cl 2 A/C RV SELF 1 c O/C Active

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -. - - - * - - - - - - - - - - - - - -. - - - - - - - - - - - - - - - - - - :' - - - - - - - - - - - * - - - - - - :' - - - - - - - - - - - - - - - - - - .- - - - - - - - - - - - - - - - - -. - - - - * - - - - - - - * - - - - - * - - - - - - : - - * - - - - - * - * - - - - - - 7. - * - ** - * - - - - - - - - - - - - - - - - - - - - - - - - - - * - - - - - - - - - - - - - *** - -

82.RA-IS.ZZ-0002(0) LJ 18MO (later) DCP 2EC-3612 , see BPAR 970715187 SC.MD-PT.ZZ-0007(0) RV 5YR (later) DCP 2EC-3612 , see PMCR 970320324 2WL477 CONTAINMENT ISO VLV OVERPRESSURE PROTECTION RELIEF VALVE AUGMENTED 205339-3 Waste Disposal Liquid Bl N C RV SELF 1 c 0 Active SC.MD-PT.ZZ-0007(0) RV 5YR (later) DCP 2EC-3612 , see PMCR 970320324 2WL478 CONTAINMENT ISO VLV OVERPRESSURE PROTECTION RELIEF VALVE 205339-3 Waste Disposal Liquid BB 2 A/C RV SELF 1 c O/C Active 82.RA-IS.ZZ-0002(0) LJ 18MO (later) DCP 2EC-3612, see BPAR 970715187 SC.MD-PT.ZZ-0007(0) RV 5YR (later) DCP 2EC-3612, see PMCR 970320324

TABLE 3-2 -VALVE TEST TABLE 10/1/97 SALEM NUCLEAR PLANT - UNIT 2 Page 121

--*----------*--**--------~------------~,:. __ _.

VALVE NO VALVE DESCRIPTION P +ID No P +ID Name Drawing ASME /ST Valve Actuator Valve Normal Safety Active/Passive Coordinates Class Cat Type Type Size Position Position Classification

' I I I I I TEST PROC ~TEST TYPE !TEST FREQ.! C.S. JUST. ! R.O. JUST. ~ REL. REQ.: RECUR. TASK !TECH. POS.~ COMMENTS 2WR80 2 REACT COOL PZR RLF TANK PRIMARY WTR SUPPLY AIR OPRD DIAPH VLV 205301-1 Reactor Coolant C10 2 A DIA AIR 3 O/C C Active S2.0P-ST.ZZ-0003(Q) FSTC Q  ! 100665  ! j S2.RA-IS.ZZ-0002(Q) LJ 18MO 290809 S2.0P-ST.RPl-0004(Q) PIT 2YR 100872 S2.0P-ST.ZZ-0003(Q) STC Q 100665 2WR81 2 REACT COOL PZR RLF TK PRIMARY WTR SUPPLY LINE CHECK VLV 205301-1 Reactor Coolant C9 2 A/C CK SELF 3 O/C O/C Active S2.RA-IS.ZZ-0002(Q)  ! CTC RF V-34  ! 29081 O  !

S2.0P-ST.ZZ-0003(Q) CTO Q 100665 TP-6 S2.RA-IS.ZZ-0002(Q) LJ 18MO 290810 2WR191 CONTAINMENT ISO VLV OVERPRESSURE PROTECTION RELIEF VALVE AUGMENTED 205301-1 Reactor Coolant CB N c RV SELF 1 c 0 Active

~ - ~

SC.MD-PT.ZZ-0007(0)  : RV 5YR  : j j (later)  ! DCP 2EC-3612, see PMCR 970320324

Salem Units 1 and 2 Inservice Test Program ATTACHMENT 1 TECHNICAL POSITIONS

Salem Units 1 and 2 Inservice Test Program Technical Position (TP-1)

I. Title Power-Operated Valve Stroke Testing:

Reference and Acceptance Criteria Values.

ll. Issue Discussion a) Currently, Salem is utilizing the 'Previous Value' method to determine acceptance criteria per AS1\.1E XI, IWV-3000, 1983 Edition with Addenda through Summer 1983. As a prelude to the Salem IST 10-Year update, Salem will be utilizing parts of OM-10 1987, 1988 Addenda, 'Inservice Testing of Valves in Light-Water Reactor Power Plants,' specifically, 'Valve Exercising Tests' as described in Section 4. 2.1, and 'Reference Values' in Section 3. 3 with associated Sections 3 .4 and 3.5. Section 5, 'Acceptance Criteria and Corrective Action' and Section 6,

'Records and Reports' are also applicable.

b) OM-10 utilizes 'Reference Values' to base the stroke time acceptance criteria. Per OM-10 Section 3.3, reference values will be determined from the results of past inservice testing. These tests will be performed under conditions as near as practicable to those expected during subsequent inservice testing.

• III.

c) OM-10 specifies stroke time acceptance criteria in Section 4.2.1.8. The limiting values of stroke time testing are to be established by the owner according to Section 4.2.1.4.

Initial Reference Value Calculation (OM-10, Section 3.3):

a) As stated above, Salem is utilizing the 'Previous Value' method to determine acceptance criteria. OM-10 requires that an initial reference value be established for each valve or group of valves. The acceptance criteria is an allowable percentage above or below (+/-) the reference value. Per OM-10, Section 3.3, reference values will be determined from the results of past inservice tests. These tests are performed under conditions as near as practicable to those expected during subsequent inservice testing.

b) In updating from 'Previous Value' to 'Reference Value' method, various methods of obtaining a reference value for stroke times were reviewed. The method selected for calculating stroke reference values is as follows:

For each valve or group of valves:

1) Ascertain last 5 stroke times

2) Remove high and low values

3) Average the remaining 3 stroke times

• 10/1/97 Revision 8

Salem Units 1and2 Inservice Test Program TP-1 (Cont)

The average obtained from step 3 establishes the reference value for the particular valve.

IV. Reference Values (OM-10, Sections 3.3 and 3.4) a) OM-10 requires reference values be determined from the results of past inservice tests (see method above). These tests are performed under conditions as near as practicable to those expected during subsequent inservice testing.

b) According to OM-10, Section 3 .4, when a valve or its control system has been replaced, repaired or has undergone maintenance* that could affect the valve's performance, a new reference value will be determined or the previous value reconfirmed by an inservice test run prior to the time the valve is returned to service or immediately if not removed from service, to demonstrate that performance parameters which could be affected by the replacement, repair, or maintenance are within acceptable limits. Verification that the new values represent acceptable operation will be documented in the record of tests.

c) Deviations between the previous and new reference values will be identified and analyzed. This analysis will review the ~t (previous minus new) between the

• reference values and determine whether this change is consistent with any changes that the valve or its control system has undergone. If the changes in stroke times are consistent with the changes that the valve or its control system has undergone, the new reference value will be applied to the valve. If the changes in stroke times are inconsistent with the changes that the valve or its control system has undergone, the IST Implementation Manager may elect to perform further evaluations and determine if the previous value should remain as the reference value.

d) If it is desired to establish an additional set of reference values, the requirements of OM-10, Section 3.5 must be met.

• Adjustment of stem packing, limit switches, or control system valves, and removal of the bonnet, stem assembly, actuator, obturator, or control system components are examples of maintenance that could affect valve performance parameters.

V. Stroke Time Acceptance Criteria (OM-10, sections 4.2.1.4, 4.2.1.8 and 4.2.1.9) a) The OM-10 standard recognizes that operating characteristics of electric motor operated valves are more consistent than those of air operated valves. The acceptance criteria for electric motor operated valves and air operated valves are different to reflect the operating characteristics .

• 10/l/97 Revision 8

Salem Units 1 and 2 Inservice Test Program TP-1 (Cont) b) Per OM-10 Section 4.2.1.8, stroke time acceptance criteria are calculated based on the reference values established above. The stroke time acceptance criteria calculations are shown below:

Reference Acceptance Limiting Operator Value (RV) Criteria Stroke Time (LST)

Type (Notes 1,2,3) (Note 4) (Notes 4, 5)

Motor RV> 10.0 0.85RV - l.15RV :S 1.30RV 4.0~V:'O: 10.0 0.75RV - 1.25RV :S l.50RV RV< 4.0 ** RV+/- 1.0 sec. RV+2.0 sec.

Other RV> 10.0 0.75RV - 1.25RV :S l.5RV RV:.,:; 10.0 ** 0.50RV - 1.50RV :S 2.0RV All RV<2.0 ** NIA :S 2.0 sec c) According to OM-10, Section 4.2.1. 9, if a valve does not meet its acceptance criteria, it will be immediately retested or declared inoperable. If the valve is retested and the second set of data also does not meet the acceptance criteria, either the data shall be analyzed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> to verify that the new stroke time represents acceptable valve operation, or the valve will be declared inoperable. If the second set of data meets the acceptance criteria, the cause of the initial deviation will be analyzed and the results documented in the record of tests.

Valves that stroke in less that 2 seconds may be exempted from use of the Acceptance Criteria ranges shown for 'Motor' and 'Other' Operator types. In such cases, the maximum limiting stroke time shall be 2 seconds (Ref OM-I 0, Section 4.2.1.8.e).

VI. Limiting Stroke Time The Limiting Stroke Time (LST) is bounded by the system requirements or values specified in the safety analyses for system performance (FSAR or Technical Specifications). When the identified limiting value is exceeded, the valve shall be declared inoperable and the applicable Technical Specification Limiting Condition for Operation (LCO) shall be entered. Following the declaration that the valve is inoperable, the valve may be repaired, replaced, or the data may be analyzed to determine the cause of the deviation and the valve shown to be operating acceptably. Valve operability based upon analysis shall have the results of the analysis recorded in the record of tests. Prior to returning a repaired or replacement valve to service, a test demonstrating satisfactory operation shall be performed .

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Salem Units 1 and 2 Inservice Test Program TP-1 (Cont)

• VII. Notes

1) RV is the reference value in seconds for an individual valve or valve grouping.

2) Standard rounding techniques are used when rounding off stopwatch readings during valve stroke timing (e.g. 10.45 rounds to 10.5 and 10.44 rounds to 10.4 seconds). All measured stroke times are rounded to the nearest tenth of a second.

3) When reference stroke time values are affected by other parameters or conditions, then these parameters or conditions must be analyzed and the above factors adjusted.

4) If the above calculated acceptance values exceed a Technical Specification (TS) or Final Safety Analysis Report (FSAR) value, then the TS or FSAR value must be used for the Limiting Value of Full-Stroke Time.

5) If a minimum limiting stroke time exists for a given valve, the minimum value shall be used as the Lower Limiting Stroke Time. For valves with no lower limiting number, the Lower Limiting Stroke Time shall be NI A.

VIII. References

• a) b)

Code of Federal Regulations, Title 10, Part 50.55a ASME Boiler and Pressure Vessel Code,Section XI ( 1983 Edition with addenda through Summer, 1983) c) ASME/ANSI OM-1987, Operation and Maintenance of Nuclear Power Plants (through Oma-1988) d) NRC NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants e) Salem UFSAR, Section 3.9.4, Inservice Testing of Pumps and Valves f) Salem Technical Specification, Section 4.0.5, Surveillance Requirements g) NC.NA-AP.ZZ-0012(Q), Technical Specification Surveillance Program h) NC.NA-AP.ZZ-0070(Q), Inservice Testing Program i) Salem Generating Station IST Manual

• 10/ 1/97 Revision 8

Salem Units 1 and 2 Inservice Test Program Technical Position (TP-2)

• I. Title Pump Testing:

Pump Test Parameters.

II. Issue Discussion a) Currently, Salem performs pump testing in accordance with the requirements of ASME Section XI, 1983 Edition with Addenda through Summer 83, Subsection IWP, "Inservice Testing of Pumps in Nuclear Power Plants". As a prelude to the Salem IST 10-Year update, Salem will be utilizing some testing requirements of OM-1987, OMa-1988 Addenda, Part 6 (OM-6) "Inservice Testing of Pumps in Light-Water Reactor Power Plants", specifically, portions of Section 5 and 6 relating to positive displacement pump discharge pressure measurement and evaluation.

b) NUREG-1482, Section 5.1.2, "Continued Measurement of Parameters Deleted from OM-6", provides guidance to licensees not yet using OM-6 for IST of pumps. This section specifies that licensees may eliminate test parameters deleted from the inservice testing (IST) requirements of OM-6 and that relief requests need not be submitted to delete the measurement of these test parameters. The test parameters listed are inlet pressure, differential pressure for positive displacement pumps, proper lubricant level or pressure and bearing temperature.

The section further states that there is no specific related requirements for using the recommendation; however, discharge pressure for positive displacement pumps must be monitored as specified by OM-6. If the recommendation is used, the documents for the IST program must discuss the implementation.

c) Title 10 of the Code of Federal Regulations, Part 50.55a(10CFR50.55a) specifies requirements for applying industry codes and standards to boiling or pressurized water-cooled nuclear power facilities. Paragraph (t)(4)(iv) specifies that inservice testing of pumps may meet the requirements in subsequent editions and addenda incorporated by reference in paragraph 50.55a(b), subject to the limitations and modifications listed in paragraph 50.55a(b), and subject to Commission approval.

Portions of editions or addenda may be used if all related requirements of the respective editions or addenda are met. The 1989 edition of Section XI was incorporated by reference into paragraph 50.55a(b). This edition specifies that the rules for the IST of pumps are stated in the ASME/ ANSI Operations and Maintenance (OM) Standards, Part 6, "Inservice Testing of Pumps in Light-Water Reactor Power Plants."

• 10/l/97 Revision 8

Salem Units 1 and 2 Inservice Test Program TP-2 (Cont)

• III. Implementation:

a) Pump Inlet Pressure - Pump inlet pressure will not be required. OM-6 recognizes that the owner is responsible to address testing limitations in the procedure and does not include it. Note: Where differential pressure gauges are not available, pumps requiring dynamic suction pressure to be recorded in order to calculate the developed differential pressure will still require inlet pressure be measured and recorded.

b) Pump Bearing Temperature - Pump bearing temperature measurement will not be required. Measurement of pump bearing temperature on a yearly basis has been shown to be unreliable in the detection of pending pump bearing failure. Pending pump bearing failure is only indicated when the bearing temperature 1s continuously monitored, which does not apply for standby pumps.

c) Proper Lubricant Level or Pressure - Pump proper lubricant level or pressure will not be required to be verified. This is routinely monitored during pump operation by plant personnel as part of regular maintenance practice, and has little value in determining pump performance trends.

d) Vibration Measurement and Evaluation - Pump vibration will be measured and evaluated in accordance with the requirements of ASME XI, Subsection IWP. As part of the transition to OM-6, informational vibration measurements will also be taken in units of velocity and compared with OM-6 criteria to identify and repair problem pumps before full OM-6 compliance is invoked. Current industry practice recognizes that vibration in terms of velocity provides a more representative and responsive measurement for pump bearings with pump speeds greater than 600 rpm and that vibration in terms of displacement is more sensitive for pump speeds less than 600 rpm.

e) Positive Displacement Pump Differential Pressure - Positive displacement pump performance will be based on pump discharge pressure in accordance with OM-6 which recognizes that discharge pressure is independent of inlet pressure for positive displacement pumps. Positive displacement pump performance will be monitored and evaluated based on the limits specified in Table 3b.

t) Duration of Tests - Pumps will be run at least 2 minutes after pump conditions are as stable as the system permits per OM-6.

IV. References a) Code ofFederal Regulations, Title 10, Part 50.55a b) ASME Boiler and Pressure Vessel Code,Section XI (1983 Edition with addenda through Summer, 1983) 10/1/97 Revision 8

Salem Units 1 and 2 Inservice Test Program

• c) d)

AS:ME/ ANSI OM-1987, Operation and Maintenance of Nuclear Power Plants (through Oma-1988)

NRC NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants e) Salem UFSAR Section 3.9.4, Inservice Testing of Pumps and Valves f) Salem Technical Specification, Section 4.0.5, Surveillance Requirements g) NC.NA-AP.ZZ-0012(Q), Technical Specification Surveillance Program h) NC.NA-AP.ZZ-0070(Q), Inservice Testing Program i) Salem Generating Station IST Manual

• LO/l/97 Revision 8

Salem Units 1 and 2 Inservice Test Program Technical Position '(TP-3)

I.

Pump Testing:

Pump Full Flow Testing.

II. Issue Discussion a) Currently, Salem performs pump testing in accordance with the requirements of ASME XI, 1983 Edition with Addenda through Summer 83, Subsection IWP, "Inservice Testing of Pumps in Nuclear Power Plants". Paragraph IWP-1400 specifies that, where a pump cannot practically be tested in its regular circuit, a bypass loop may be used.

b) Generic Letter 89-04 (GL 89-04), "Guidance on Developing Acceptable Inservice Testing Programs", provides specific guidance for pump testing in NRC Staff Position 9, "Pump Testing Using Minimum-flow Return Lines With or Without Flow Measuring Devices". This staff position specifies that in cases where flow can only be established through a non-instrumented minimum-flow path during quarterly pump testing and a path exists at cold shutdowns or refueling outages to perform a test of the pump under full or substantial flow conditions, the staff has determined that the increased interval is an acceptable alternative to the Code

• requirements provided that pump differential pressure, flow rate, and bearing vibration measurements are taken during this testing and that quarterly testing also measuring at least pump differential pressure and vibration is continued. Data from both of these testing frequencies should be trended. In cases where only the minimum-flow return line is available for pump testing, regardless of the te~t interval, the staff's position is that flow instrumentation which meets the requirements of IWP-4110 and 4120 must be installed in the minimum-flow return line.

c) In response to GL 89-04 (NLR-N89196), Salem Generating Station specified that all pump testing at Salem Station utilizing mini-flow return lines is conducted through instrumented flow lines. Additionally, the response states that all of the affected pumps also receive a full flow test when plant conditions permit.

Ill Implementation:

a) Safety-related pumps that are tested quarterly utilizing an instrumented minimum-flow line shall also be full-flow tested during cold shutdowns or refueling outages, as applicable. These full-flow tests will provide for pump differential pressure, flow rate, and bearing vibration measurement. The full-flow tests will be considered "augmented testing", since Code requirements are met during quarterly testing .

• 10/1/97 Revision 8

Salem Units 1 and 2 lnservice Test Program TP-3 (Cont)

• b) Pump performance criteria developed for the full-flow test will not include alert values. The pump will be determined to be degraded and inoperable if the measured test parameters are outside the acceptable range listed in Part 6, Table 3b of AS.ME/ANSI OM-1987, Oma-1988 Addenda or do not meet the applicable Technical Specification limits for pump operability.

c) This position applies to the following pumps in the current Salem IST Program:

1AFE4, 1AFE5, 1AFE6, lCSEl, 1CSE2, 1CVE20, 1CVE21, 1SJE2, ISJE3, 2AFE4, 2AFE5, 2AFE6, 2CSEI, 2CSE2, 2CVE20, 2CVE21, 2SJE2, and 2SJE3.

As stated above in III(a), full-flow testing on these pumps is not used to satisfy quarterly Code test requirements.

d) The following pumps will have acceptance criteria established which will include alert values: IRHEl, IRHE2, 2RHE1, 2RHE2. These pumps have full flow testing performed during each surveillance for which the 92 day interval falls during Modes 5 and 6. Credit is taken for the Code required surveillance testing under these tests. Thus, alert values will be used for these pumps.

IV. References a) Code ofFederal Regulations, Title 10, Part 50.55a b) AS.ME Boiler and Pressure Vessel Code,Section XI ( 1983 Edition with Addenda through Summer, 1983) c) NRC Generic Letter 89-04, Guidance on Developing Acceptable lnservice Testing Programs d) AS.ME/ANSI OM-1987, Operation and Maintenance of Nuclear Power Plants (through Oma-1988) e) NRC NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants f) Salem UFSAR, Section 3.9.4, Inservice Testing of Pumps and Valves g) Salem Technical Specification, Section 4.0.5, Surveillance Requirements h) NC.NA-AP.ZZ-0012(Q), Technical Specification Surveillance Program i) NC.NA-AP.ZZ-0070(Q), Inservice Testing Program j) Salem Generating Station IST Manual

• [()/ 1/97 Revision 8

Salem Units 1 and 2 Inservice Test Program Technical Position (TP-4)

• I.

Pump Testing:

Pump Fixed Reference Value Variance.

II. Issue Discussion a) Currently, Salem performs pump testing in accordance with the requirements of AS1\1E XI, 1983 Edition, Summer 83 Addenda, Subsection IWP, "Inservice Testing of Pumps in Nuclear Power Plants". Paragraph IWP-3100 specifies that, when performing a pump test, the resistance of the system shall be varied until either the measured differential pressure or the measured flow rate equals the corresponding reference value. Paragraph IWP-4150 allows the use of symmetrical damping devices or averaging techniques to reduce instrument fluctuations to within 2 percent of the observed reading. Table IWP-4110-1 specifies acceptable analog instrument accuracy for pressure, differential pressure and flow rate instruments as+/- 2 percent of full scale.

b)

• NUREG-1482, Section 5.3 recognizes that certain plant designs are not conducive to adjusting system resistance to obtain an exact fixed reference value. The staff has determined that, if the design does not allow for establishing and maintaining

• • flow at an exact value, achieving a steady flow rate or differential pressure at approximately the set value does not require relief for establishing pump curves.

The allowed tolerance for setting the fixed parameter must be established for each case individually including the accuracy of the instrument and the precision of its display. This will necessitate verification of the effect of precision on accuracy as considered in the design of the instrument gauge. A total tolerance of+/- 2 percent of the reference value is allowed without approval from the NRC. For tolerance greater than +/- 2 percent (may be necessary depending on the precision of the instrument), a corresponding adjustment to the acceptance criteria may be made to compensate for the uncertainty, or an evaluation be performed and documented justifying a greater tolerance. In using this guidance, the variance must be documented in the IST program documents or implementing procedures.

c) NUREG-1482, Section 5.5 provides guidance for range and accuracy of analog and digital instruments used to measure pump flow rate and differential pressure and recognizes that IWP does not address digital instruments. The staff recommends that the requirements in Part 6 of AS1\1E/ ANSI OM-1987, Oma-1988 Addenda (OM-6) for digital instruments be applied when used for IST.

d) OM-6 requires digital instruments 1) be selected such that the pump reference value shall not exceed 70 percent of the calibrated range, and 2) be accurate to 2 percent over the calibrated range .

• 10/ l/97 Revision 8

Salem Units 1 and 2 Inservice Test Program TP-4 (Cont)

• III. Implementation:

a) When system design prohibits setting flow rate at a specific reference value, an allowable tolerance shall be determined to aid performance of the inservice test.

The tolerance shall be determined based on the applicable instrument accuracy and precision of display. In no case will the total tolerance exceed+/- 2 percent of the reference value without a corresponding adjustment to the associated acceptance criteria or an evaluation being performed to justify the greater tolerance.

b) The total tolerance shall be determined in a manner similar to the following example.

For an analog instrument with a full range of 0-10,000 gpm, accuracy of 1 percent full scale, and precision (increments) of 200 gpm used in a pump test with a reference flow rate of 6,000 gpm. Readings on the gauge would be acceptable to a degree of precision no greater than one-half the smallest increment. For this example, standard reading between increments is 100 gpm (200 gpm/2). This is the smallest flow rate that can be read on this gauge. To meet the requirements of NUREG-1482, the sum of the specified tolerance and the indicated accuracy, rounded to the nearest readable increment, must be less than or equal to 2 percent of full scale. Therefore, for the specified information:

• Gauge accuracy=+/- (10,000 gpm x .01) = +/- 100 gpm Specified Tolerance= +/- (6,000 gpm x .02) = +/- 120 gpm Note: Since the minimum readable increment is 100 gpm, the specified tolerance can be either +/- 100 gpm or +/- 200 gpm.

If specify +/- 100 gpm:

100 gpm + 100 gpm s 200 gpm 200 gpm = 200 gpm Acceptable If specify +/- 200 gpm:

200 gpm + 100 gpm s 200 gpm 300 gpm > 200 gpm Unacceptable Therefore, the pump test procedure would specify the system resistance be adjusted to set observed flow rate to 6,000 +/- 100 gpm. No relief request, NRC

• l ()/[ /97 approval or further evaluation is required .

Revision 8

Salem Units 1 and 2 Inservice Test Program

• c) If required to use averaging techniques to reduce instrument fluctuations as allowed in IWP-4150, the average gauge reading shall be set within the allowable tolerance. For example, if the specified test flow rate is 1000 +/- 100 gpm and the observed reading is fluctuating, the average gauge reading shall be less than 1100 gpm but greater than 900 gpm, or the system resistance shall be varied until this condition is met.

IV. References a) Code ofFederal Regulations, Title 10, Part 50.55a b) AS1\1E Boiler and Pressure Vessel Code,Section XI ( 1983 Edition with addenda through Summer, 1983) c) NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs d) AS1\1E/ANSI OM-1987, Operation and Maintenance of Nuclear Power Plants (through Oma-1988) e) NRC NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants

• f) g)

h)

Salem UFSAR, Section 3.9.4, Inservice Testing of Pumps and Valves Salem Technical Specification, Section 4.0.5, Surveillance Requirements NC.NA-AP.ZZ-0012(Q), Technical Specification Surveillance Program i) NC.NA-AP.ZZ-0070(Q), Inservice Testing Program j) Salem Generating Station IST Manual

• Ill/ l/97 Revision 8

Salem Units 1 and 2 Inservice Test Program TP-4 Attachment 1

• Evaluation of Unit 1 CC Pump Flow Instrumentation (Unit 2 CC Pump Flow Instrumentation Evaluation has been deleted since flow instrument replacements meet Code range, accuracy and readability requirements.)

Issue Discussion Installed flow instruments for 1CCE2, l CCE3 and 1CCE4 Pumps do not meet the +/- 2 percent of reference value tolerance specified in Technical Position 4. This evaluation is required to justify the continued use of and acceptability of the installed instruments.

The l CCE3 Pump, for example, has a reference value of 4100 gpm. Two percent of reference value would be 82 gpm. The digital flow instrument (FIR.601A) reads in 100 gpm increments.

The procedure directs flow to be set at 4100 gpm +/- 100 gpm.

Evaluation NUREG-1482, Section 5.3 recognizes that adjusting system resistance to obtain an exact reference value may not be possible due to system design. For the CC Pumps the instrument accuracy is 0.58%, but its display is limited to 100 gpm increments. To meet the 2 percent

• requirement flow would be required to be in the 4018 to 4182 gpm band. The additional 18 gpm allowed due to gauge readout limitation would allow pump head to increase or decrease by less than 0.5 ft water. This corresponds to about 0.2 psid for differential pressure test acceptance criteria.

The small increase (less than one-half percent) in the range of acceptable reference value settings will not decrease the ability of the test to detect degradation of the pump. The instruments that are currently installed will provide adequate ability to ensure test reliability and repeatability and will be used during pump testing .

• [()/ 1/97 Revision 8

Salem Units 1 and 2 Inservice Test Program TP-4 Attachment 2

• Evaluation of SJ Pump Flow Instrumentation Issue Discussion Installed flow instruments for 21 and 22 SJ Pumps do not meet the+/- 2 percent of reference value tolerance specified in Technical Position 4. This evaluation is required to justify the continued use of and acceptability of the installed instruments.

The 21and22 SJ Pumps, have a reference value of30 +/- 1 gpm. Two percent of reference value would be 30.6 gpm. The analog flow instrument reads in lgpm increments. The procedure directs flow to be set at 30 gpm +/- 1 gpm.

Evaluation NUREG-1482, Section 5 .3 recognizes that adjusting system resistance to obtain an exact reference value may not be possible due to system design. For the SJ Pumps the instrument accuracy is 2% and its display is limited to 1 gpm increments. To meet the 2 percent requirement flow would be required to be in the 29.4 to 30.6 gpm band. The additional 0.6 gpm allowed due to gauge readout limitation would allow pump head to increase or decrease by less than 0.005 ft water. This corresponds to about 0.05 psid for differential pressure test acceptance criteria.

The small increase in the range of acceptable reference value settings will not decrease the ability of the test to detect degradation of the pump. The instruments that are currently installed will provide* adequate ability to ensure test reliability and repeatability and will be used during pump testing .

• [()/1/97 Revision 8

Salem Units 1 and 2 Inservice Test Program Technical Position (TP-5)

• l.

Valve Testing:

Seat Leakage Testing per 10 CFR 50 Appendix J.

ll. lssue Discussion a) Currently, Salem performs valve testing in accordance with the requirements of ASME XI, 1983 Edition, Summer 83 Addenda, Subsection IWV, "Inservice Testing of Valves in Nuclear Power Plants". Paragraph IWV-2200 provides guidance on categorizing valves and defines a Category A valve as one for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their function. Paragraph IWV-3420 specifies valve leak rate test requirements for Category A valves. Paragraph IWV-3426 requires each valve be assigned a permissible leakage rate and the measured leakage rate compared to previous measurements.

b) Generic Letter 89-04 (GL 89-04), NRC Staff Position 10, "Testing Containment Isolation Valves," specifies that "all containment isolation valves (CIVs) that are included in the Appendix J program should be included in the IST program as Category A or A/C valves." The staff has determined that the leak rate test

• procedures and requirements for CIVs specified Title 10, Part 50, Appendix J of the Code of Federal Regulation (10CFR50 Appendix J) are equivalent to the requirements of IWV-3421 through 3425, provided that the Analysis of Leakage Rates and Corrective Action requirements of Paragraph IWV-3426 and 3427(a) are complied with. The staff further determined that usefulness of IWV-3427(b) does not justify the burden of complying with this requirement and, since the position represents a deviation from the Code requirements, it should be documented in the IST program.

c) NUREG-1482, Section 4.4.3 recognizes that certain plant designs are not conducive to individual seat leakage testing of containment penetrations with multiple isolation branches. Valves may be leak tested in groups as allowed by Part 10 of ASME/ANSI OM-1987, Oma-1988 Addenda (OM-10). If two or more valves on a containment penetration are tested as a group, limiting leakage-rate values must be assigned to the group for the purpose of monitoring the valve condition and taking corrective action. If the limiting values are exceeded, actions must be taken to determine the leakage path.

d) NUREG-1482, Section 4.4.5 provides guidance on leak-rate testing using OM-10 and specifies that Paragraph 4.2.2.3 may be used to update IST programs pursuant to 10CFR50.55a(t)(4)(iv) and meeting all of the requirements of Paragraphs 4.2.2.1 and 4.2.2.3 .

• 10/l/97 Revision 8

Salem Units 1 and 2 Inservice Test Program TP-5 (Cont)

• e) Paragraph 4.2.2.2 ofOM-10 specifies that Category A valves which are CIVs shall be tested in accordance with Federal regulation 10CFR50, Appendix J.

Containment isolation valves which also provide a reactor coolant system pressure isolation function shall additionally be tested in accordance with paragraph 4.2.2.3.

f) Paragraph 4.2.2.3 of OM-10 specifies the requirements for determining valve leakage rates for valves other than CIV s.

III. lmplementation:

a) Category A containment isolation valves will be tested in accordance with the requirements of Technical Specification 3/4.6.1.2 and 10CFR50, Appendix J.

Technical Specification 3/4.6.1.2 surveillance testing for measuring valve leakage is consistent with the requirements of Appendix J. Analysis of leakage rates and corrective action shall be as specified in OM-10, 4.2.2.3(e) and (f), as required by 10CFR50.55a(f)(4).

b) Containment isolation valves which also perform a reactor coolant system pressure isolation function shall additionally be tested in accordance with paragraph IWV-3420, with the exception that corrective actions stated in IWV-3427(b) will not be performed .

• IV. References a) b)

Code of Federal Regulations, Title 10, Part 50.55a AS1\1E Boiler and Pressure Vessel Code,Section XI (1983 Edition with addenda through Summer, 1983) c) NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs d) AS1\1E/ANSI OM-1987, Operation and Maintenance of Nuclear Power Plants (through Oma-1988) e) NRC NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants f) Salem UFSAR, Section 3.9.4, Inservice Testing of Pumps and Valves g) Salem Technical Specification, Section 4.0.5, Surveillance Requirements h) Salem Technical Specification, Section 3/4.6.1.2, Containment Leakage i) NC.NA-AP.ZZ-0012(Q), Technical Specification Surveillance Program 10/ 1/97 Revision 8

Salem Units 1 and 2 Inservice Test Program TP-5 (Cont)

• j) k)

NC.NA-AP.ZZ-0070(Q), Inservice Testing Program Salem Generating Station IST Manual

• !0/1/97 Revision 8

Salem Units 1 and 2 Inservice Test Program Technical Position (TP-6)

• I.

Exercising Tests for Check Valves:

Exercising Tests and Check Valve Sample Disassembly Requirements.

ll. Issue Discussion

1) Currently, Salem performs valve testing in accordance with the requirements of AS:ME XI, 1983 Edition, Summer 83 Addenda, Subsection IWV, "Inservice Testing of Valves in Nuclear Power Plants". As a prelude to the Salem IST l 0-Y ear update, Salem will be utilizing parts of OM-10 1987 w/1988 Addenda, "Inservice Testing of Valves in Light-Water Reactor Power Plants." Specifically, "Exercising Tests for Check Valves", Section 4.3.2.

Paragraph 4 .3. 2. 1 specifies that check valves shall be exercised at least once every 3 months, except as provided by paragraphs 4.3.2.2, 4.3.2.3, 4.3.2.4, and 4.3.2.5.

Paragraph 4.3.2.2 specifies that check valves shall be exercised as follows:

(a) During plant operation, each check valve shall be exercised or

• (b) examined in a manner which verifies obturator travel to the closed, full-open or partially open position required to fulfill its function.

If full-stroke exercising during plant operation is not practicable it may be limited to part-stroke during plant operation and full-stroke during cold shutdowns.

( c) If exercising is not practicable during plant operation, it may be limited to full-stroke exercising during cold shutdowns.

(d) If exercising is not practicable during plant operation and full stroke during cold shutdowns is also not praticable, it may be limited to part-stroke during cold shutdowns, and full-stroke during refueling outages.

( e) If exercising is not practicable during plant operation or cold shutdowns, it may be limited to full-stroke during refueling outages.

(f) Valves full-stroke exercised at shutdowns shall be exercised during each shutdown, except as specified in (g) below. Such exercise is not required if the time period since the previous full-stroke exercise is less than 3 months .

• ' LU/1/97 Revision 8

Salem Units 1 and 2 lnservice Test Program TP-6 (Cont)

• (g) Valve exercising shall commence within 48 hr. of achieving cold shutdown, and continue until all testing is complete or the plant is ready to return to power. For extended outages, testing need not be commenced in 48 hr. provided all valves required to be tested during cold shutdown will be tested prior to plant startup.

However, it is not the intent of this Part to keep the plant in cold shutdown in order to complete cold shutdown testing.

(h) All valve testing required to be performed during a refueling outage shall be completed prior to returning the plant to operation.

Paragraph 4.3.2.3 specifies that check valves which operate in the course of plant operation at a frequency which would satisfy the exercising requirements of this Part need not be additionally exercised provided that the observations otherwise required for testing are made and analyzed during such operation and are recorded in the plant records at intervals no greater than specified in paragraph 4.3 .2.1.

Paragraph 4.3.2.4 specifies valve obturator movement as follows:

(a) The necessary valve obturator movement shall be demonstrated by exercising the valve and observing that either the obturator travels to the seat on cessation or reversal of flow, or opens to the position required to fulfill its function, as specified in paragraph 1. 1, or both .

Observation may be by observing a direct indicator such as a position indicating device, or by other indicator(s) such as changes in system pressure, flow rate, level, temperature, seat leakage testing or other positive means.

(b) If a manual exerciser is used to move the obturator, the force or torque required to initiate movement (breakaway) shall be measured and recorded. The breakaway force shall not vary by more than 50% from the established reference value. The reference value used shall be the value obtained when the valve is known to be operating properly and shall be taken under conditions which the valve will be tested, e.g., wet vs. dry, equivalent static head, etc.

(c) As an alternative to the testing in (a) or (b) above, disassembly every refueling outage to verify operability of check valves may be used.

Paragraph 4.3.2.5 specifies that for a valve(s) in a system declared inoperable or not required to be operable, the exercising test schedule need not be followed. If the test schedule is not followed, within 3 months prior to placing the system in an operable status the valve(s) shall be exercised and the schedule followed in accordance with the requirements of this Part .

10/1/97 Revision 8

Salem Units 1 and 2 Inservice Test Program TP-6 (Cont)

• Paragraph 4.3 .2.6 specifies that if a check valve fails to exhibit the required change in obturator position it shall be declared inoperable. A retest showing acceptable performance shall be run following any required corrective action before the valve is returned to service.

2) Generic Letter 89-04 (GL 89-04), NRC Staff Position 2, "Alternative to Full-flow Testing of Check Valves," recognizes that, for some check valves, it is impractical to establish or verify sufficient flow to full-stroke exercise the valve open. In fact, in some designs, establishing design accident flow through some check valves for testing could result in damage to major plant equipment. The NRC staff position is that valve disassembly and inspection can be used as a positive means of determining that a valve's disk will full-stroke exercise open or of verifying closure capability. The staff has established the following positions regarding testing check valves by disassembly:

(a) During valve testing by disassembly, the valve internals should be visually inspected for worn or corroded parts, and the valve disk should be manually exercised.

(b) Valve disassembly and inspection may be performed during reactor refueling outages. Since this frequency differs from the Code required frequency, this deviation must be specifically noted in the IST program.

• (c) Where the licensee determines that it is burdensome to disassemble and inspect all applicable valves each refueling outage, a sample disassembly and inspection plan for groups of identical valves in similar applications may be employed.

The NRC guidelines for a sample disassembly and inspection plan are:

(a) The sample disassembly and inspection program involves grouping similar valves and testing one valve in each group during each refueling outage.

The sampling technique requires that each valve in the group be the same

. design (manufacturer, size, model number, and materials of construction) and have the same service conditions including valve orientation.

(b) At each disassembly, the disassembled valve's full-stroke capability shall be verified and that the internals are structurally sound (no loose or corroded parts). If the disassembly is to verify the full-stroke capability of the valve, the disk should be manually exercised.

(c) A different valve of each group is required to be disassembled, inspected, and manually full-stroke exercised at each successive refueling outage, until the entire group has been tested. If the disassembled valve is not capable of being full-stroke exercised or there is binding or failure of valve IOI l/97 Revision 8

Salem Units 1 and 2 Inservice Test Program TP-6 (Cont) internals, the remaining valves in that group must also be disassembled,

• ( d) inspected, and manually full-stroke exercised during the same outage .

Extension of the valve disassembly/inspection interval to one valve every other refueling outage or expansion of the group size above four valves should only be considered in cases of extreme hardship where the extension is supported by actual in-plant data from previous testing.

(e) If possible, partial valve stroking quarterly or during cold shutdowns, or after reassembly must be performed.

3) NUREG-1482, Section 4.1 provides additional guidance on check valve grouping, in that it discusses grouping of valves in multiple units of like design and construction. This Section specifies that, if units are "identical" and the grouped valves have similar operational experience and otherwise meet the grouping criteria, it is acceptable to group valves from multiple units.

4) NRC Generic Letter 96-06, "Assurance of Equipment Operability and Containment" was issued 9/30/96. The purpose was to notify licensees about safety- significant issues that could affect containment integrity and equipment operability during accident conditions. Engineering evaluations* S- l-ZZ-MEE-1231 and S-2-ZZ-MEE-1145 document the Salem resolution to the generic letter significant issues. In resolving potential over-pressurization of containment penetrations and piping "credit" has been taken for certain check valves now performing an open safety function to relieve pressure. Since for this application the overpressure source is only the thermal expansion of trapped water, the check valve will only lift or "burp" an insignificant amount to relieve the overpressure condition. The lifting function of these valves will be demonstrated by evidence that the disk moves off its seat. Neither disassembly & inspection or maximum required accident condition flow, as described in NRC GL 89-04, will be performed to take credit for a full-stroke exercise due to the insignificant amount of disk movement required for the valve to fulfill its intended safety function. The test method in use exceeds GL 89-04 expectations in that unquantified flow is demonstrated which exceeds the short duration lift or "burp" that would actually occur during accident conditions.

III. Implementation:

a) As a prelude to the Salem IS T 10-Year update, Salem will be utilizing parts of OM-10 1987 w/1988 Addenda, "Inservice Testing of Valves in Light-Water Reactor Power Plants." Specifically, "Exercising Tests for Check Valves", Section 4.3.2.

b) When system design prohibits full-stroke or reverse exercising a check valve at any plant condition, the valve shall be disassembled and inspected at a refueling outage frequency. Where practical, a partial stroke exercise test shall be performed after

• 10/1/97 Revision 8

Salem Units 1 and 2 Inservice Test Program TP-6 (Cont) reassembly to verify valve disassembly and reassembly did not impair the valve's ability to perform its safety function.

c) When more than one valve of the same design and service conditions are involved, a sample disassembly and inspection program, based on the requirements of GL 89-04, shall be used to verify valve operability. No more than four valves will be included within one group.

d) Extension of the valve disassembly/inspection intervals to longer than once every 6 years shall be supported based on actual in-plant data from previous testing and shall be documented as set forth in GL 89-04.

e) The lifting function of GL 96-06 check valves will be demonstrated by evidence that the disk moves off its seat. Neither disassembly & inspection or maximum required accident condition flow, as described in NRC GL 89-04, will be performed.

IV. References a) Code of Federal Regulations, Title 10, Part 50.55a

• b) c)

ASME Boiler and Pressure Vessel Code,Section XI ( 1983 Edition with addenda through Summer, 1983)

NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs d) ASME/ANSI OM-1987, Operation and Maintenance of Nuclear Power Plants (through Oma-1988) e) NRC NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants f) Salem UFSAR, Section 3.9.4, Inservice Testing of Pumps and Valves g) Salem Technical Specification, Section 4.0.5, Surveillance Requirements h) NC.NA-AP.ZZ-0012(Q), Technical Specification Surveillance Program i) NC.NA-AP.ZZ-0070(Q), Inservice Testing Program j) Salem Generating Station IST Manual

• 10/1/97 Revision 8

Salem Units 1 and 2 lnservice Test Program Technical Position (TP-6) Salem Check Valve IST Disassembly Grouping Data Valve Valve. Unit Manuf. Model Number Type Size Orientation Valve Body Material Nonnal Service Conditions SYS PSBP Orientation Group ID Reference I IAF71 SC Velan B20-0l 14B-2TS Swing 16" Horizontal CS GR. II, SA-105 Normally closed, with piping drained. Air AF 121145 219489sh I Valve environment.

I IAF72 SC Velan B20-0l 14B-2TS Swing 16" Horizontal CS GR. II, SA-105 Normally closed, with piping drained. Air AF 121145 219489 sh I Valve environment.

2 11AF53 SI Velan Bl4-0l 14C-2TS Swing 6" Horizontal CS GR. WCB, SA-216 Normally closed, AFW pump alternate AF 136382 207482 sh 3 Valve suction. Demin Water@ ~ 65F, 25 psig 2 12AF53 SI Velan Bl4-0l 14C-2TS Swing 6" Horizontal CS GR. WCB, SA-216 Normally closed, AFW pump alternate AF 136382 207482 sh 3 Valve suction. Demin Water@ ~ 65F, 25 psig 3 21AF53 S2 Velan Bl4-0l 14C-2TS Swing 6" Horizontal CS GR. WCB, SA-216 Normally closed, AFW pump alternate AF 136382 AF22 sh I Valve suction. Demin Water@~ 65F, 25 psig 3 22AF53 S2 Velan Bl4-0l 14C-2TS Swing 6" Horizontal CS GR. WCB, SA-216 Normally closed, AFW pump alternate AF 136382 AF22 sh I Valve suction. Demin Water@ ~ 65F, 25 psig 4* 13AF53 SI Velan Bl5-0114B-2T Swing 8" Horizontal CS GR. WCB, SA-216 Normally closed, AFW pump alternate AF 136383 207482 sh 4 Valve suction. Demin Water@~ 65F, 25 psig 4* 23AF53 S2 Velan Bl5-0l 14B-2T Swing 8" Horizontal CS GR. WCB, SA-216 Normally closed, AFW pump alternate AF 136383 AF22 sh I Valve suction. Demin Water@~ 65F, 25 psig 5 llSJ43 SI Velan Bl4-3114B-13M Swing 6" Horizontal SS F316, Al82 Normally closed. During RHR, 1500 gpm SJ 106252 RHl3A sh 2 Valve borated water@ 65-300 F, 0-300 osil!

5 12SJ43 SI Velan Bl4-3114B-13M Swing 6" Horizontal SS F316, Al82 Normally closed. During RHR, 1500 gpm SJ 106252 RHl3A sh 2 Valve borated water@ 65-300 F, 0-300 osil!

5 13SJ43 SI Velan Bl4-3l14B-13M Swing 6" Horizontal SS F316, Al82 Normally closed. During RHR, 1500 gpm SJ 106252 RHl3A sh 2 Valve borated water@ 65-300 F, 0-300 psig 5 14SJ43 SI Velan Bl4-3114B-13M Swing 6" Horizontal SS F316, Al82 Normally closed. During RHR, 1500 gpm SJ 106252 RHl3A sh 2 Valve borated water@ 65-300 F, 0-300 osil!

6 21SJ43 S2 Velan Bl4-3l14B-13M Swing 6" Horizontal SS F316, Al82 Normally closed. During RHR, 1500 gpm SJ 106252 RH23 sh I Valve borated water@ 65-300 F, 0-300 psig 6 22SJ43 S2 Velan Bl4-3114B-13M Swing 6" Horizontal SS F316, Al82 Normally closed. During RHR, 1500 gpm SJ 106252 RH23 sh 3 Valve borated water@ 65-300 F, 0-300 psig 6 23SJ43 S2 Velan Bl4-3l14B-13M Swing 6" Horizontal SS F316, Al82 Normally closed. During RHR, 1500 gpm SJ 106252 RH23 sh I Valve borated water@ 65-300 F, 0-300 osil!

6 24SJ43 S2 Velan Bl4-3114B-!3M Swing 6" Horizontal SS F316, Al82 Normally closed. During RHR, 1500 gpm SJ 106252 RH23 sh 4 Valve borated water @ 65-300 F, 0-300 osil!

• Valves 13AF53 and 23AF53 are grouped across Salem Units I and 2. Since the AF53s are in the normally drained alternate suction lines for the AF pumps, this grouping meets the TP-6 criteria that across-unit valves have similar operating experience.

10/1/97 Re\'ision 8

Salem Units 1 and 2 Inservice Test Program Technical Position (TP-7)

• I.

Pump and Valve Testing:

Skid Mounted Components.

11. Issue Discussion a) Currently, Salem performs valve testing in accordance with the requirements of ASME XI, 1983 Edition, Summer 83 Addenda, Subsections IWP, "Inservice Testing of Pumps in Nuclear Power Plants" and IWV, "Inservice Testing of Valves in Nuclear Power Plants".

These sections provide the rules and requirements for inservice testing of certain Class l, 2 and 3 plant components that are required to perform a specific function in shutting down a reactor to cold shutdown condition or in mitigating the consequences of an accident and, for pumps, that are provided with an emergency power source.

b) NUREG-1482, Section 3 .4 recognizes that the Code class piping systems may include skid-mounted components or component sub-assemblies such as valves in diesel air-start subassemblies, diesel skid-mounted fuel oil pump(s) and valves, steam admission and trip throttle valves for auxiliary feedwater pump turbine drivers, steam traps, and air supply system check valves and solenoid-operated valves for main steam isolation valves. If these components are identified as ASME Code Class 1, 2, or 3, in the Safety Evaluation Report (SER), they are subject to IST. If these components are not identified as ASME Code Class 1, 2, or 3, in the SER (or the SER indicates that they are maintained as Code class, but are not required to be Code class), they are not subject to IST in accordance with Part 50.55a of Title 10 of the Code of Federal Regulation (10CFR50.55a). However, these cornponents may be subject to periodic testing in accordance with 10 CFR 50, Appendix A and Appendix B. The staff has determined that the testing of the major component is an acceptable means for verifying the operational readiness of the skid-mounted and component subassemblies if this approach is documented in the IST program. This is acceptable for both Code class components and non-Code class components tested and tracked in the IST Program.

Ill. Implementation:

a) The operational readiness of components and sub-assemblies that are skid-mounted or are integral parts of a major component will be verified during testing of the major component. The individual components will not be specifically listed in the IST Program and will not be individually tested. Satisfactory operation of the major component verifies the operation of the skid-mounted component or sub-assembly .

• IO/l/lJ7 Revision 8

Salem Units 1 and 2 Inservice Test Program TP- 7 (Cont)

• IV. References a) Code of Federal Regulations, Title 10, Part 50.55a b) ASl'v1E Boiler and Pressure Vessel Code,Section XI ( 1983 Edition with addenda through Summer, 1983) c) NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs d) ASl'v1E/ANSI OM-1987, Operation and Maintenance ofNuclear Power Plants (through Oma-1988) e) NRC NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants t) Salem UFSAR, Section 3.9.4, Inservice Testing of Pumps and Valves (J)

, Salem Technical Specification, Section 4.0.5, Surveillance Requirements h) NC.NA-AP.ZZ-0012(Q), Technical Specification Surveillance Program i) NC.NA-AP.ZZ-0070(Q), Inservice Testing Program j) Salem Generating Station IST Manual

• ill/ l/'J7 Revision 8

Salem Units 1 and 2 Inservice Test Program

• ATTACHMENT 2 COLD SHUTDOWN JUSTIFICATIONS

• l0/1197 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS- 01

• COMPONENTS:

FUNCTION:

l 1AF4, 12AF4, 13AF4 21AF4, 22AF4, 23AF4 These valves are located in the normal suction supply piping to the motor and steam driven auxiliary feed (AF) pumps from the auxiliary feed storage tank (AFST). The valves perform an active safety function in both the open and closed positions. In the closed position, the valves prevent diversion of suction supply when the AF pumps are aligned to their alternate suction supply source. These valves must be capable of opening upon pump start to allow passage of design accident flow.

CATEGORY: C CLASS: 3 TEST REQUIREJ\1ENTS:

Open Position - Check valves shall be exercised at least once every 3 months, m accordance with the requirements of IWV-3 521.

DEFERRED TEST JUSTIFICATION:

• Exercising these check valves to the full open position during power operation would require establishing auxiliary feedwater flow to the steam generators since the recirculation line to the AFST is of insufficient size to allow full exercising during quarterly pump testing. Establishing high flow to the steam generators during plant operation would result in steam generator level problems and thermal shocking of piping.

During plant operation cooldown cycles are to be minimized to reduce the potential for feedwater nozzle cracking and prevent water hammer due to cold water stratification phenomenon. The AFW pumps are only started at power when piping temperature is 160 degrees or more and then only at the smallest possible flow to allow piping/pump cooling in the event of system back leakage.

ALTERNATE TESTING:

These valves will be partially exercised to the open position during the quarterly pump test by recirculating water from the AFST. Full stroke exercising to the open position shall be performed during startup after each cold shutdown. These valves are not required to be operable during cold shutdown therefore testing need not be performed quarterly during cold shutdown. In cases *of frequent cold shutdowns these valves need not be full exercised more often than once every 3 months.

References:

Cale: S-C-F400-l\1FD-032 l Rev. 2 Cale: S-C-F400-MSE-0370 Rev. 0

• 10/ 1/97 Procedure: S2.0P-PT.AF-0002(Q) 2 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 02

• COrvIPONENTS:

FUNCTION:

l 1AP8, 12AP8, 13AP8 21 AP8, 22AP8, 23 AF8 These check valves are located in the discharge piping from the motor driven and steam driven auxiliary feed pumps. The valves perform an active safety function in the open position. The valves must be capable of opening upon associated pump start to allow passage of design accident flow.

CATEGORY: C CLASS: 3 TEST REQUIREMENTS:

Open Position - Check valves shall be exercised at least once every 3 months, m accordance with the requirements ofIWV-3521.

DEFERRED TEST JUSTIFICATION:

Exercising these check valves to the full open position or the motor driven APP check valves to the partial open position during power operation would require establishing auxiliary feedwater flow to the steam generators. Establishing high flow to the steam generators during plant operation would result in steam generator level problems and thermal shocking of piping. During plant operation cooldown cycles are to be minimized to reduce the potential for feedwater nozzle cracking and prevent water hammer due to cold water stratification phenomenon. The APW pumps are only started at power when piping temperature is 160 degrees or more and then only at the smallest possible flow to allow piping/pump cooling in the event of system back leakage.

ALTERNATE TESTING:

The motor and steam driven APP check valves will be full stroke exercised to the open position during startup after each cold shutdown. These valves are not required to be operable during cold shutdown therefore testing need not be performed quarterly during cold shutdown. The steam driven APP check valve will be partial exercised quarterly using the available test return line. In cases of frequent cold shutdowns these valves need not be full exercised more often than once every 3 months.

References:

Cale: S-C-F400-MFD-032 l Rev. 2 Cale: S-C-F400-MSE-0370 Rev. O Procedure: S2.0P-PT.AP-0002(Q)

• 10/1/97 3 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 03

• COMPONENTS:

FUNCTION:

l 1AF23, 12AF23, 13AF23, 14AF23 21AF23, 22AF23, 23AF23, 24AF23 These stop check valves are located in the auxiliary feedwater injection lines to the steam generators. The valves perform an active safety function in both the open and closed positions. In the closed position, the valves prevent inleakage of steam to the auxiliary feedwater piping and components. This function prevents the potential of steam binding of the auxiliary feed water pumps. The valves must be capable of opening upon pump start to allow passage of design accident flow.

CATEGORY: C CLASS: 3 TEST REQUIREMENTS:

Open Position - Check valves shall be exercised at least once every 3 months, m accordance with the requirements ofIWV-3521.

DEFERRED TEST JUSTIFICATION:

• Exercising these stop check valves to the full or partial open pos1t1on during power operation would require establishing auxiliary feedwater flow to the steam generators.

Establishing high flow to the steam generators during plant operation would result in steam generator level problems and thermal shocking of piping. During plant operation cooldown cycles are to be minimized to reduce the potential for feedwater nozzle cracking and prevent water hammer due to cold water stratification phenomenon. The AFW pumps are only started at power when piping temperature is 160 degrees or more and then only at the smallest possible flow to allow piping/pump cooling in the event of system back leakage.

ALTERNATE TESTING:

These valves will be full stroke exercised to the open position during startup after each cold shutdown. These valves are not required to be operable during cold shutdown therefore testing need not be performed quarterly during cold shutdown. In cases of frequent cold shutdowns these valves need not be full exercised more often than once every three months.

References:

Cale: S-C-F400-MFD-0321 Rev. 2 Cale: S-C-F400-MSE-0370 Rev. O Procedure: S2.0P-PT.AF-0002(Q)

• 10/ l/97 4 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 04

• (Valves l 1SW53, 12SW53, 21SW53, 22SW53 to be radiographed quarterly)

CSJ deleted in Revision 7 of the IST Program

• L0/1/97 5 Revision 8

Salem Units 1 and 2 Inservice Test Program

• COLD SHUTDOWN TEST JUSTIFICATION - CS - 05 COMPONENTS: l 1AF920, 12AF920, 13AF920, 14AF920 21AF920, 22AF920, 23AF920, 24AF920 HJNCTION:

These check valves are located in the discharge piping from the motor driven auxiliary feed pumps to the steam generator feedwater headers. The valves perform an active safety function in the open position. The valves must be capable of opening upon associated pump start to allow passage of design accident flow.

CATEGORY: C CLASS: 3 TEST REQUIREMENTS:

Open Position - Check valves shall be exercised at least once every 3 months, m accordance with the requirements ofIWV-3521.

DEFERRED TEST JUSTIFICATION:

• Exercising these check valves to the full or partial open position during power operation would require establishing auxiliary feedwater flow to the steam generators. Establishing high flow to the steam generators during plant operation would result in steam generator

.level problems and thermal shocking of piping. During plant operation cooldown cycles are to be minimized to reduce the potential for feedwater nozzle cracking and prevent water hammer due to cold water stratification phenomenon. The AFW pumps are only started at power when piping temperature is 160 degrees or more and then only at the smallest possible flow to allow piping/pump cooling in the event of system back leakage.

ALTERNATE TESTING:

These valves will be full stroke exercised to the open position during startup after each cold shutdown. These valves are not required to be operable during cold shutdown therefore testing need not be performed quarterly during cold shutdown. In cases of frequent cold shutdowns these valves need not be full exercised more often than once every 3 months.

References:

Cale: S-C-F400-l\1FD-0321 Rev. 2 Cale: S-C-F400-MSE-0370 Rev. 0 Procedure: S2.0P-PT.AF-0002(Q)

• [()/1/97 6 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 06

• COl\1PONENTS:

FUNCTION:

l 1AF921, 12AF92 l, 13AF921, 14AF921 21 AF92 l, 22AF92 l, 23 AF92 l, 24 AF92 l These check valves are located in the discharge piping from the steam driven auxiliary feed pump to the steam generator feedwater headers. The valves perform an active safety function in both the open and closed positions. The valves must be capable of opening upon associated pump start to allow passage of design accident flow. The valves perform an active safety function in the closed position to prevent diversion of motor driven AF pump discharge flow to the turbine driven AF pump.

CATEGORY: C CLASS: 3 TEST REQUIREMENTS:

Open & Closed Position - Check valves shall be exercised at least once every 3 months in accordance with the requirements oflWV-3521.

DEFERRED TEST JUSTIFICATION:

Exercising these check valves to the full or partial open position during power operation would require establishing auxiliary feedwater flow to the steam generators. Establishing

• high flow to the steam generators during plant operation would result in steam generator level problems and thermal shocking of piping. During plant operation cooldown cycles are to be minimized to reduce the potential for feedwater nozzle cracking and prevent water hammer due to cold water stratification phenomenon. The AFW pumps are only started at power when piping temperature is 160 degrees or more and then only at the smallest possible flow to allow piping/pump cooling in the event of system back leakage.

Reverse flow exercising these valves at power requires opening the motor driven auxiliary feedwater pump steam generator inlet valve using the pressure override defeat pushbutton while venting upstream of the steam driven driven auxiliary feedwater pump steam generator inlet check valve. This action requires declaring two auxiliary feedwater pumps inoperable and entry into a six hour shutdown LCO.

ALTERNATE TESTING:

These valves shall be reverse flow exercised to the closed position during cold shutdown when the AF pumps are not required to be operable and full stroke exercised to the open position during startup after each cold shutdown. These valves are not required to be operable during cold shutdown therefore testing need not be performed quarterly during cold shutdown. In cases of frequent cold shutdowns these valves need not be full exercised more often than once every 3 months.

References:

Cale: S-C-F400-l\.1FD-032 l Rev. 2

• 10/1/97 Cale: S-C-F400-MSE-0370 Rev. 0 Procedure: S2.0P-PT.AF-0002(Q) 7 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 07

• COMPONENTS:

FUNCTION:

l lBFl 9, 12BF19, 13BF19, 14BF19 21BF19, 22BF19, 23BF19, 24BF19 These air operated, fail-closed valves are the main feedwater control valves which perform an active safety function in the closed position. The valves must be capable of automatic closure upon receipt of a safety injection signal subsequent to a main steam line break to prevent excessive cooldown of RCS and overpressurization of the containment. The valves also closes on a high-high steam generator water level signal to prevent feedwater flow from exceeding assumed limits by analysis. Additionally, the valve closes upon receipt of a reactor trip signal coincident with a low reactor coolant system average temperature condition.

CATEGORY: B CLASS: None TEST REQUIREMENTS:

Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements of IWV-3411.

• DEFERRED TEST JUSTIFICATION:

These valves are located in the flow path for the main feedwater supply to the steam generators. Valve exercising during power operation would require isolation of a feedwater loop which is not permissible. Plant Technical Specifications (3.4.5 for Salem I

& 3.4.6 for Salem 2) requires each steam generator to be operable during Modes 1, 2, 3 and 4. Partial exercising these valves during power operation could result in a power reduction and reactor oscillations which would place the reactor plant in an unstable condition.

ALTERNATE TESTING:

These valves shall be exercised on an augmented program basis to the closed position in accordance with the requirements of IWV-3410 during cold shutdowns. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• 10/1/97 8 Revision 8

Salem Units 1 and 2 lnservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 08

• COMPONENTS:

FUNCTION:

l 1BF22, 12BF22, 13BF22, 14BF22 21BF22, 22BF22, 23BF22, 24BF22 These motor operated, stop check valves are located in the main feedwater supply headers to the steam generators. The valves perform an active safety function in the closed position. The valves must be capable of automatic closure (simple check valve function) upon cessation and reversal of flow subsequent to a main feedwater line break to prevent loss of inventory from the affected steam generator. Additionally, these valves must close to prevent diversion of auxiliary feedwater flow upon a loss of normal feed water. These valves also serve as a Class 2 to non-Code boundary barrier. Remote-manual operation from the control room ensures positive isolation during all accident scenarios to satisfy GDC 57 criterion.

CATEGORY: B/C CLASS: 2 TEST REQUIRE1\.1ENTS:

Closed Exercising - Valves (Category B) shall be exercised at least once every 3 months, in accordance with the requirements of IWV-3412. Closed Position - Check valves

• (Category C) shall be exercised at least once every 3 months, in accordance with the requirements of IWV-3 521.

DEFERRED TEST JUSTIFICATION:

These valves are located in the flow path for the main feedwater supply to the steam generators and are normally open during power operation. Valve exercising during power operation would require isolation of a feedwater loop which could cause a feedwater transient with a potential for a reactor trip. Additionally, valve closure during power operation is not permissible due to Plant Technical Specifications (3.4.5 for Salem 1 &

3. 4. 6 for Salem 2) requiring each steam generator to be operable during Modes 1, 2, 3 and 4.

ALTERNATE TESTING:

These motor operated stop check valves shall be exercised to the closed pos1t1on in accordance with the requirements of IWV-3412 and IWV-3520 during cold shutdowns.

The safety function of the valve is dependent upon the simple check valve function for normal feedwater isolation and the motor operated positve shut-off function for containment isolation. Reverse flow exercise testing and stroke timing the remote-manual stop check feature will be performed to satisfy both Code requirements. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

I 0/ 1/97 9 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 09

• CONIPONENTS:

FUNCTION:

l 1BF40, 12BF40, 13BF40, 14BF40 21BF40, 22BF40, 23BF40, 24BF40 These air operated, fail-closed valves are the main feedwater bypass control valves which perform an active safety function in the closed position. The valves must be capable of automatic closure, if open, upon receipt of a safety injection signal subsequent to a main steam line break to prevent excessive cooldown of RCS and overpressurization of the containment. The valves also close on a high-high steam generator water level signal to prevent feedwater flow from exceeding assumed limits per analysis. Additionally, the valves close upon receipt of a reactor trip signal coincident with a low reactor coolant system average temperature condition.

CATEGORY: B CLASS: None TEST REQUIRHv1ENTS:

Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements of IWV-3411.

• DEFERRED TEST JUSTIFICATION:

These valves are located in the flow path for the main feedwater supply to the steam generators. Valve exercising during power may cause a feedwater level perturbation due to main feedwater control valve (BF 19) changing position to follow load. Plant Technical Specification (3.4.5 for Salem 1 & 3.4.6 for Salem 2) requires each steam generator to be operable during Modes 1, 2, 3 and 4. Quarterly partial exercising these valves during power operation could result in a power transient potentially placing the reactor plant in an unstable condition. In the event maintenance is required during plant operation, post-maintenance partial stroking is performed following packing adjustments.

ALTERNATE TESTING:

These valves shall be exercised on an augmented program basis to the closed position in accordance with the requirements of IWV-3410 during cold shutdowns. Partial stroke exercising during plant operation is not practical and will not be performed except as PMT for packing adjustments. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• I0/ 1/97 10 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS- 10

• COMPONENTS:

FUNCTION:

l 1BF13, 12BF13, 13BF13, 14BF13 21BF23, 22BF13, 23BF13, 24BF13 These motor operated valves are the main feedwater isolation valves which perform an active safety function in the closed position to provide redundant isolation capability for the feedwater control and bypass valves (BF19 and BF40). The valves must be capable of automatic closure upon receipt of a safety injection signal subsequent to a main steam line break to prevent excessive cooldown of RCS and overpressurization of the containment.

These valves also close on a high-high steam generator water level signal to prevent feedwater flow from exceeding assumed limits per analysis. Additionally, the valve closes upon receipt of a reactor trip signal coincident with a low reactor coolant system average temperature condition.

CATEGORY: B CLASS: None TEST REQUIREMENTS:

Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements of IWV-3411.

• DEFERRED TEST JUSTIFICATION:

These valves are located in the flow path for the main feedwater supply to the steam

• generators. Valve exercising during power operation would require isolation of a feedwater loop which is not permissible. Plant Technical Specifications (3 .4.5 for Salem l

& 3.4.6 for Salem 2) requires each steam generator to be operable during Modes 1, 2, 3 and 4. Additionally, the control circuitry of these valves does not permit partial exerc1smg.

ALTERNATE TESTING:

These valves shall be exercised on an augmented program basis to the closed position in accordance with the requirements of IWV-3410 during cold shutdowns. Partial stroke exercising during plant operation will not be performed. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• 10/1/97 11 Revision 8

Salem Units 1 and 2 lnservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 11

• C01\1PONENTS:

FUNCTION:

lCCl 18 2CC118 These motor operated valves are located in the Component Cooling Water (CCW) supply line which provides cooling water to the Reactor Coolant Pump (RCP) bearings and thermal barriers. These valves are designated as an outboard containment isolation valve, and performs an active safety function in the closed position to maintain* containment integrity.

CATEGORY: A CLASS: 2 TEST REQUIRE1\.1ENTS:

Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements of IWV-3411.

DEFERRED TEST JUSTIFICATION:

During normal plant operation this valve remains in the open pos1t1on to ensure a continuous supply of cooling water to the motor bearings and thermal barriers of all four RCPs of each reactor plant. Exercising these valves to the closed position, during power operation, could result in extensive pump damage due to the interruption of cooling water flow. In advertant valve failure in the closed position, during testing, would require plant shutdown, in addition to causing pump damage. The control circuitry associated with this valve does not provide for partial stroke capability.

ALTERNATE TESTING:

These motor operated valves shall be exercised to the closed position in accordance with the requirements of IWV-3410 during cold shutdowns when the RCPs can be removed from service. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• IOI 1/97 12 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 12

• COMPONENTS:

FUNCTION:

1CC131, 1CC136, 1CC187, 1CC190 2CC131, 2CC136, 1CC187, 2CC190 These motor operated valves are located in the Component Cooling Water (CCW) return lines from the Reactor Coolant Pump (RCP) bearing coolers and thermal barriers. The valves are designated as inboard and outboard containment isolation valves, and perform an active safety function in the closed position to maintain containment integrity.

CATEGORY: A CLASS: 2 TEST REQUIREMENTS:

Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements of IWV-3 411.

DEFERRED TEST JUSTIFICATION:

During normal plant operation these valves remain in the open position to provide a return flow path for cooling water from the motor bearing coolers and thermal barriers on all

• four RCPs of each reactor plant. Exercising these valves to the closed position, during power operation, could result in extensive pump damage due to the interruption of cooling water flow. In advertant valve failure in the closed position during testing would require plant shutdown, in addition to causing pump damage. The control circuitry associated with these valves does not provide for partial stroke capability.

ALTERNATE TESTING:

These motor operated valves shall be exercised to the closed position in accordance with the requirements of IWV-3410 during cold shutdowns when the RCPs can be removed from service. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• 10/1/97 13 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 13

• COMPONENTS:

FUNCTION:

1CV76 2CV76 These check valves are located in the auxiliary spray line to the pressurizer from the Chemical Volume Control (CVC) system and serve as the auxiliary pressurizer spray injection check valves. These valves performs an active safety function in the open position. These valves must be capable of opening to provide a flow path for pressurizer depressurization utilizing the charging system. This function may be required to depressurize the Reactor Coolant System (RCS) to achieve cold shutdown when the reactor coolant pumps are unavailable.

CATEGORY: C CLASS:

TEST REQUIREMENTS:

Open Position - Check valves shall be exercised at least once every 3 months, m accordance with the requirements ofIWV-3521.

DEFERRED TEST WSTIFICATION:

This check valve is maintained in the closed position during power operation by RCS pressure on the downstream side of the disk. Exercising this valve to the full or partial open position at power is not possible because it would allow the injection of relatively cold water into the pressurizer resulting in pressure control instability in the system and possible reactor trip.

ALTERNATE TESTING:

This check valve shall be full stroke exercised to the open position during cold shutdown in accordance with the requirements of IWV-3520. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• J()/ l/97 14 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS- 14

• (Valves lCS 16, lCS 17, 2CS 16, 2CS 17 to be tested quarterly)

CSJ deleted in Revision 7 of the IST Program

• 10/l/97 15 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 15

• (Valves l 1CS21, 12CS21, 21CS21, 22CS21 to be tested quarterly)

CSJ deleted in Revision 6 of the IST Program

• 10/1/97 16 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 16

• COMPONENTS:

FUNCTION:

l 1CS36, 12CS36 21CS36, 22CS36 These motor operated valves are located in the residual Heat Removal (RHR) heat exchanger discharge cross-connects to the Containment Spray (CS) system. These valves perform an active safety function in the open and closed positions. The valves must be capable of opening to align the RHR heat exchangers to the CS system and closing to terminate containment spray during the post-accident recirculation phase. The valves also perform a inactive safety function in the closed position to prevent diversion of CS flow during the containment spray mode of operation.

CATEGORY: B CLASS: 2 TEST REQUIREivffiNTS:

Open & Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements of IWV-3411.

DEFERRED TEST JUSTIFICATION:

The CS36 motor operated valves remain in the closed pos1t1on during normal plant operation to isolate the RHR heat exchanger from the Containment Spray system.

Exercising these valves to the full or partially open position at power is not possible due to the presence of interlocks between Safety Injection system containment sump isolation valves (SJ44). These interlocks prevent the opening of the CS36 valves unless the containment sump isolation valves (SJ44) are full open. Opening the SJ44 valves individually at power would require closure ofRHR Pump Suction valve RH4, restoration of control power to the SJ44 valve (removed per TS 4.5.2.a. l) and entry into a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO for one ECCS subsystem inoperable. UFSAR 7.3.2.7 also takes credit for control power being removed from the SJ44 valve circuit during normal operation. Inadvertant containment sump isolation valve failure in the open position during testing would require a plant shutdown and subsequent manway removal to gain access to the SJ44 valve.

ALTERNATE TESTING:

The CS36 valves shall be exercised to the open and closed positions in accordance with the requirements of IWV-3520 during cold shutdown. Valve exercising will require alternating RHR loops, if operating in the shutdown cooling mode, to prevent spray down of the containment. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• 10/1/97 17 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 17

• COMPONENTS:

FUNCTION:

1CV7 2CV7 These normally open, fail-closed air operated valves are located in the inlet line to the letdown heat exchanger from the regenerative heat exchanger. The valve performs an active safety function in the closed position to provide containment isolation. The valve automatically closes on receipt of a Phase A containment isolation signal.

CATEGORY: A CLASS: 2 TEST REQUIRE1\.1ENTS:

Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance With the requirements of IWV-3411.

DEFERRED TEST JUSTIFICATION:

These air operated valves are maintained in the open position to provide a flow path from the Reactor Coolant System (RCS) to the Chemical Volume Control System (CVCS) during normal letdown operation. This flow path is required during all phases of plant operation to maintain proper reactor coolant inventory by means of a continuous feed and bleed process. Exercising these valves to the closed position at power would require isolating normal letdown flow through the regenerative heat exchanger and placing excess letdown in operation. Isolation of the regenerative heat exchanger would prevent the transfer of heat from the letdown flow to the charging flow. This creates the potential of thermal shock to the RCS charging inlet nozzle branch connections and thermal sleeves by the injection of relatively cold water. The injection of cold water could also result in a power transient and RCS instability during plant operation. Additionally, the valve control circuitry is not provided with partial stroke capability.

ALTERNATE TESTING:

These valves shall be exercised to the closed position in accordance with the requirements of IWV-3400 during cold shutdown. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• 10/l/97 18 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 18

• COrvtPONENTS:

FUNCTION:

1CV40, 1CV41 2CV40, 2CV41 These normally open, motor operated valves are located in the charging pumps suction supply from the Volume Control Tank (VCT). The valves perform an active safety function in the closed position to provide isolation between the VCT and the Reactor Water Storage Tank. (RWST) during safety injection. The valves close on receipt of a safety injection signal to align the RWST to the charging pump suction.

CATEGORY: B CLASS: 2 TEST REQUIREMENTS:

Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements ofIWV-3411.

DEFERRED TEST JUSTIFICATION:

These motor operated valves are maintained in the open position to align the VCT to the charging pumps to support normal charging. This flow path is required during all phases of plant operation to maintain proper reactor coolant inventory by means of a continuous feed and bleed process. These valves are interlocked to prevent their closing unless either R WST isolation valve (SJl or SJ2) is open. Exercising these valves to the closed position at power would require shifting charging pump suction from the VCT to the RWST. The RWST inventory is 2300 ppm borated water which if injected into the RCS would result in a loss in reactor power and possibly take the reactor subcritical. Additionally, the valve control circuitry is not provided with partial stroke capability.

ALTERNATE TESTING:

These valves shall be exercised to the closed position in accordance with the requirements of IWV-3400 during cold shutdown. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• 10/1/97 19 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS- 19

• COMPONENTS:

FUNCTION:

1CV68, 1CV69 2CV68, 2CV69 These normally open, motor operated valves are located in the charging line to the regenerative heat exchanger. The valves perform an active safety function in the closed position to provide containment isolation and to isolate the Chemical Volume Control System (CVCS) charging line during a safety injection. The valves close on receipt of a safety injection signal. The valves also perform a passive safety function in the open position to permit passage of charging flow from the Charging Pumps to the Reactor Coolant System Cold Leg. This flow path is also utilized during emergency boration.

CATEGORY: A CLASS: 2 TEST REQUIREMENTS:

Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements of IWV-3411.

DEFERRED TEST JUSTIFICATION:

These motor operated valves are maintained in the open position to provide a flow path for normal charging. This flow path is required during all phases of plant operation to maintain proper reactor coolant inventory by means of a continuous feed and bleed process. Exercising these valves to the closed position at power would interrupt normal charging flow which could cause a loss of pressurizer level control resulting in a reactor trip. Additionally, the valve control circuitry is not provided with partial stroke capability.

ALTERNATE TESTING:

These valves shall be exercised to the closed position in accordance with the requirements of IWV-3400 during cold shutdown. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• 10/l/97 20 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 20

• COMPONENTS:

FUNCTION:

lCVl 16, 1CV284 2CV 116, 2CV284 These normally open, motor operated valves are located in the Reactor Coolant Pump (RCP) seal water return lines to the seal water filter. The valves perform an active safety function in the closed position to provide containment isolation and automatically close on receipt of a Phase A containment isolation signal.

CATEGORY: A CLASS: 2 TEST REQUIRE:tvffiNTS:

Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements of IWV-3411.

DEFERRED TEST JUSTIFICATION:

These motor operated valves are maintained in the open position to provide a path for seal water return flow. This flow path is required to. support continued operation of the RCPs .

Exercising these valves to the closed position at power would interrupt seal water return flow which could cause damage to the pump seals resulting in a reactor shutdown or plant trip. Additionally, the valve control circuitry is not provided with partial stroke capability.

AL TERN ATE TESTING:

These valves shall be exercised to the closed position in accordance with the requirements of IWV-3400 during cold shutdown. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• 10/1/97 21 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 21

• CONIPONENTS:

FUNCTION:

1CV176 2CVI76 These check valves are located in the rapid boration line from the boric acid tank to the charging pump suction supply. The operational function is to provide isolation between the charging pump suction supply header and the boric acid tanks. This function prevents diversion of flow and dilution of the boric acid tank inventory during quarterly exercising of upstream motor operated valve CVI75. The valves perform an active safety function in the open position to allow passage and to provide a flow path during emergency boration in the absence of an safety injection signal.

CATEGORY: C CLASS: 2 TEST REQUIRErvIENTS:

Open Position - Check valves shall be exercised at least once every 3 months, m accordance with the requirements ofIWV-3 521.

DEFERRED TEST JUSTIFICATION:

• These check valves are normally in the closed position due to upstream power operated valve CVI 75 being maintained in the closed position. Exercising this valve to the open position, would require initiating flow from the boric transfer pump to the charging pump

• suction supply. This is not feasible nor practical during normal operation. Injection of highly concentrated boric acid into the reactor coolant system from the boric acid tank would result in a loss in reactor power and possibly take the reactor subcritical. Partial exercising would result in the same consequences as full exercising.

ALTERNATE TESTING:

The valve shall be exercised to the open position in accordance with the requirements of IWV-3 520 during cold shutdown. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• 10/ 1/97 22 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 22

• C0!\1PONENTS:

FUNCTION:

l 1DA13A, 12DA13A, l 1DA14A, 12DA14A, 13B, &

13B, &

14B"&

14B, &

13C 13C 14C 14C 21DA13A, 22DA13A, 21DA14A, 22DA14A, 13B, 13B, 14B, 14B,

&13C

& 13C

&14C

&14C These solenoid operated globe valves are located in the air supply lines to the diesel generator starting air motors from the starting air receivers. These valves perform an active safety function in the open position. The valves must be capable of opening when the associated engine receives a start signal to provide a flow path for starting air to the engme.

CATEGORY: B CLASS: NONE TEST REQUIREMENTS:

Open Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements ofIWV-3411.

DEFERRED TEST JUSTIFICATION:

The four (4) solenoid valves per generator are exercised together during monthly diesel generator start testing however, individual valve operation is not readily determined.

These valves are maintained in the closed position and are not provided with remote position indication to facilitate individual valve testing. Individual open exercising is accomplished by depressing the individual valve/air start motor test button while simultaneously listening for air start motor operation and monitoring the engine RPM indicator. During this test evolution the engine overspeed trip mechanism is manually engaged, rendering the engine inoperable. This augmented test activity is not practicable during normal operation due to the extent of manual action required to restore the engine should an accident occur.

ALTERNATE TESTING:

These valves shall be individually full stroke exercised to the open pos1t1on on an augmented program basis during cold shutdowns. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months. Valve exercising is accomplished by depressing the individual valve test button while simultaneously listening for air start motor operation and monitoring the engine RPM indicator without starting the Diesel. This test activity is adequate to verify individual valve open exercise requirements .

• I0/ 1/97 23 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 23

• COJ\1PONENTS:

FUNCTION:

llMSIO, 12MS10, 13MS10, 14MS10 These air operated, fail-closed valves are the steam generator atmospheric dump valves.

The valves perform an active safety function in the open and closed positions. The valves are credited in UFSAR 15.2.9 as being capable of opening during a station blackout (SBO) to assist in maintaining the plant at hot standby until AC power is restored. The valves must be capable of closure, if open, for steam generator pressure control and to isolate the affected steam generator during a steam generator tube rupture.

CATEGORY:B CLASS: 2 TEST REQUIREMENTS:

Open & Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements of IWV-3411.

DEFERRED TEST JUSTIFICATION:

• These valves are normally in the closed position to maintain pressure boundary integrity of the main steam headers. Exercising these valves to the open position during power operation would require closing the manual block valve to prevent the release of steam to the atmosphere. The closure of the 6" pipe diameter manual valves to facilitate quarterly valve exercising exposes the operator to potential heat stress and burn hazard conditions, and could complicate recovery actions if a transient were to occur when the MS 10 valves are isolated. The valve control circuitry is not provided with partial stroke capability.

Quarterly valve exercising is therefore considered impracticable without a compensating increase in the level of quality and safety.

ALTERNATIVE TESTING:

Previous problems associated with these valves (i.e. controller reset wind-up) no longer exists and would not have been detected by quarterly inservice testing. It is therefore appropriate that these valves be exercised in accordance with the requirements of IWV-3410 during cold shutdowns. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months.

10/ 1/97 24 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 24

• COivlPONENTS:

FUNCTION:

l 1MS167, 12MS167, 13MS167, 14MS167 21MS167, 22MS167, 23MS167, 24MS167 These valves function as the main steam isolation valves (MSIVs). The MSIVs perform an active safety function in the closed position. The valves must be capable of automatic closure in the event of a main steam line break inside or outside of containment. Valve design is such that flow is stopped from either direction when the valve is closed.

Additionally, loss of air to the MSIV steam dump valves MS 169 and/ or MS 171 results in their failing to the open position which dumps steam from the MS 167 actuator allowing the MSIV MS 167 valve to go closed.

CATEGORY: B CLASS: 2 TEST REQUIREMENTS:

Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements ofIWV-3411.

• DEFERRED TEST JUSTIFICATION:

These valves are located in the flow path for steam from the steam generators to the main turbine and remain in the open position during normal operation. Valve exercising during power operation would result in a power reduction, isolation the associated steam generator from the main steam line which is not permissible and possibility of plant trip.

Plant Technical Specifications (3.4.5 for Salem 1 & 3.4.6 for Salem 2) requires each steam generator to be operable during Modes 1,2,3 and 4. TS 3.7.1.5 requires all main steam isolation valves to be operable during Modes 1,2, and 3. The valve actuating circuitry does not provide for controlled partial stroke capability.

ALTERNATE TESTING:

The MSIV MS 167 steam operated valves shall be exercised to the closed position during startup following cold shutdown in accordance with the requirements of IWV-3410. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• ltl/l/97 25 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 25

• CO:rvtPONENTS:

FUNCTION:

l lMS 169, 11MS171, 21MS169?

21MS171, 12MS 169, 12MS171, 22MS169, 22MS171, 13MS 169, 13MS171, 23MS169, 23MS171, 14MS 169 14MS171 24MS169 24MS171 These valves function as the Main Steam Isolation (MSIV) dump valves. The MSIV MS 169 and MS 171 dump valves perform an active safety function in the open position.

Actuation of the MSIV MS 167 valve is accomplished by venting steam off the top of the power piston via the MSIV MS 169 and/or MS 171 dump valves. This creates a pressure imbalance shift which drives the MSIVs closed using high pressure steam to isolate the steam line. Venting control air to open the MSIV MS 169 and MS 171 dump valves provides fail-safe (closed) design for the MSIV MS 167 valve on loss of control air.

CATEGORY: B CLASS: 2 TEST REQUIREMENTS:

Open Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements ofIWV-3411.

DEFERRED TEST JUSTIFICATION:

The normally closed MS 169 and MS 171 valves are located in the vent path for dumping steam from the MSIV actuator. Valve exercising to the open positiOn during power operation without using the motor operated three-way valve would result in closure of the associated MSIV. The motor operated three-way valve is located between the MSIV and the associated dump valves (MS 169/MS 171) and is aligned such that in mid-position both vent paths provide discharge capability. This three-way valve could be utilized to allow individual exercising of the dump valves however, if three-way valve seat leakage is at a rate greater than that which can be replenished through the MSIV equalizing orifice in the piston, the MSIV will go closed. Inadvertent closure of a MSIV during power operation could result in a power transient potentially placing the reactor plant in an unstable condition. The MS 169 and MS 171 dump valve actuating control circuitry does not provide for partial stroke capability.

ALTERNATE TESTING:

The MS 169 and MS 171 air operated valves shall be exercised to the open position during startup following cold shutdown in accordance with the requirements of IWV-3410. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• IO/l/97 26 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 26

• COMPONENTS:

FUNCTION:

lPRl, 1PR2 2PR1, 2PR2 These valves function as the pressurizer power operated relief valves (PORVs). The PORVs perform an active safety function in the open and closed positions. The valves must be capable of opening, during plant shutdown conditions, to provide low temperature overpressure protection as required by 10CFR50 Appendix G. The valves must be capable of closure, if open, to limit the loss of Reactor Coolant System (RCS) inventory.

CATEGORY: B CLASS:

TEST REQUIRENIBNTS:

Open & Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements ofIWV-3411.

DEFERRED TEST JUSTIFICATION:

• These normally closed air operated valves provide RCS pressure control, when required, by discharging to the pressurizer relief tank. Exercising these valves to the open position at power could result in a loss of RCS inventory (small break LOCA) should the valve fail to reclose with a single active failure of the associateq block valve. Additionally, the low

• temperature overpressure protection function. is not required during power operation.

Quarterly exercising these valves is impractical without a compensating increase in the level of quality and safety. Ref NUREG 1482, 4.4.1 for concurrence on PORV cold shutdown testing.

ALTERNATE TESTING:

These air operated valves shall be exercised to the open and closed positions during cold shutdown in accordance with the requirements of IWV-3410. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• 10/l/97 27 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 27

• CONIPONENTS:

FUNCTION:

lPSl, 1PS3 2PS1, 2PS3 These valves serve as the pressurizer spray valves. The process function of these valves is to provide a means to reduce primary system pressure during non-safety related operational transients to preclude the actuation of the pressurizer safety valves. Spray operation for pressure control using the spray valves relies on reactor Coolant Pump (RCP) operation to provide the spray driving force. RCP operation during design basis accidents is neither required or assumed. These valves perform an active safety function in the closed position. The valves must be capable of closure, if open, coincident with a loss of offsite power. This capability ensures adequate flow is directed to the pressurizer if auxiliary spray is used for depressurization.

CATEGORY: B CLASS:

TEST REQUIREMENTS:

Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements oflWV-3411.

DEFERRED TEST JUSTIFICATION:

These normally closed, air operated valves operate automatically during power operation to maintain RCS system pressure within limits during normal operational transients. Fully opening these valves during power operation for the purpose of performing exercise tests to the closed position could result in an undesirable RCS pressure transient:

ALTERNATE TESTING:

These air operated valves shall be exercised to the closed position during cold shutdown in accordance with the requirements of IWV-3410. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• I0/1/97 28 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 28

• COl\1PONENTS:

FUNCTION:

1RC40, 1RC41, 1RC42, 1RC43 2RC40, 2RC41, 2RC42, 2RC43 These valves are located in the reactor vessel head vent piping and function as the head vent valves. The valves perform an active safety function in the open and closed positions.

The valves must be capable of opening during post accident conditions to vent noncondensible gases from the Reactor Pressure Vessel (RPV) head to ensure natural circulation for core cooling. The vented gases are discharged to the Pressureizer Relief tank (PRT). The valves must be capable of closing, if open, to maintain RCS pressure boundary integrity.

CATEGORY: B CLASS: I TEST REQUIREMENTS:

Open & Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements ofIWV-3411.

• DEFERRED TEST JUSTIFICATION:

These normally key-lock switch closed, fail-closed, solenoid operated valves provide RCS pressure boundary integrity and have power removed during plant operation. These valves are used only during plant startup and post accident conditions. During startup, following venting activities, a flush is performed to minimize the potential for valve failure due to boric acid residue during plant operation. These valves are installed in series with two valves in each path. It is not practical to exercise these valves during power operation, hot standby, or hot shutdown because the valve design and installation is such that testing can cause "burping" (momentary 1 to 2 sec. opening) of the second dosed valve. Exercising these valves at power potentially results in radioactive discharge of reactor coolant to the PRT. Additionally, testing at power under a higher differential pressure than would be experienced during post accident conditions may affect valve indication due to sensitive reed switch positions resulting in unnecessary plant shutdown.

TS 3 .4.12 requires the vent paths to be closed during plant operation.

ALTERNATE TESTING:

These valves shall be exercised to the open and closed positions during cold shutdown in accordance with the requirements of IWV-3410 and once per 18 months IAW Technical Specification (TS) 4.4.12.2. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• IOI l/97 29 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 29

• COl\1PONENTS:

FUNCTION:

lRHl, 1RH2 2RH1, 2RH2 These valves are located in the respective Reactor Coolant System RCS No.11 and 21 hot leg supply to the Residual Heat Removal (RHR) pump suction. The valves perform an active safety function in the open and closed positions. The valves must be capable of opening to provide a flow path for RHR suction from the (RCS) hot leg loop during the shutdown cooling mode of RHR subsequent to a loss of offsite power without safety injection. Additionally, the valves must also be capable of opening to ensure that a relief path exists from the RCS loop to the RHR suction line relief valve when the RCS is at low pressure and water solid. If open, the valves must be capable of closing for alignment to cold leg recirculation. Additionally, these valves perform a containment isolation and pressure isolation function. The pressure isolation function prevents exposing the low pressure RHR system piping to RCS pressure.

CATEGORY: A CLASS:

TEST REQUIREMENTS:

• Open & Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements ofIWV-3411.

DEFERRED TEST JUSTIFICATION:

During plant operation these normally closed, motor operated valves provide a pressure boundary barrier between the low pressure piping and components of the RHR system and the high pressure of the RCS. Exercising these valves at power is not possible due to interlocks with RCS pressure channels which prevent their opening when RCS pressure is

> 375 psig.

ALTERNATE TESTING:

These valves shall be exercised to the open and closed positions during startup following cold shutdown in accordance with the requirements of IWV-3410. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• 10/1/97 30 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 30

• C0!\.1PONENTS:

FUNCTION:

l 1RH8, 12RH8 21RH8, 22RH8, These check valves are located in the discharge piping of the Residual Heat Removal (RHR) pumps. The valves perform an active safety function in the open and closed pos1t1ons. The valves must be capable of opening upon RHR system initiation to accomplish emergency core cooling when reactor pressure has decreased to the point to allow low pressure injection. The valves must be capable of closure to prevent diversion of flow from an inservice RHR pump through an idle or failed pump in lieu of providing accident flow to the reactor.

CATEGORY: C CLASS: 2 TEST REQUIREMENTS:

Open Position - Check valves shall be exercised at least once every 3 months, m accordance with the requirements ofIWV-3521.

• DEFERRED TEST JUSTIFICATION:

During plant operation the RHR pumps are maintained in a standby condition, therefore these check valves remain in the closed position. Forward exercising these check valves at power would require utilizing the full flow test loop recirculating back to the RWST.

Utilizing this test loop requires opening manual valve RH2 l to align the pump discharge to the RWST. Should this valve seize in the open position or system initiation occur during testing, the LPSI mode of RHR would be compromised by allowing pump flow to be diverted to the RWST. Additionally, RH2 l is a Category A passive valve due to the test line being a potential leakage path for radioactive contaminates to a tank vented to atmosphere when RHR is operating in the recirculation mode. Opening and closing RH2 l to facilitate pump testing is burdensome due to the necessity of verifying leak tight integrity subsequent to closure.

ALTERNATE TESTING:

These check valves shall be exercised to the closed position and the partially open position during quarterly pump testing and to the full open position during cold shutdowns when the RHR is operating in the shutdown cooling mode. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• IOI 1/97 31 Revision 8

Salem Units l and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 31

• COl\1PONENTS:

FUNCTION:

l 1RH18, 12RH18 21RH18, 22RH18 The valves perform an active safety function in the open position as a subsystem of the ECCS designed to deliver high flow to the core at low pressures. Abnormal operating procedures specify that these valves are throttled during the post-accident recirculation phase therefore they are considered active valves. If closed, the valves must be capable of opening to allow RHR flow from the heat exchangers during safety injection, recirculation and shutdown cooling modes of RHR. These air operated valves are used for throttling the discharge flow from the Residual Heat Removal (RHR) heat exchangers to maintain the cooldown rate during normal shutdown activities.

CATEGORY: B CLASS: 2 TEST REQUIRErvIBNTS:

Open Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements of IWV-3 411 .

• DEFERRED TEST JUSTIFICATION:

During plant operation these valves are maintained in the fail open position with their

. control air removed to protect against inadvertent mispositioning and to ensure the RHR injection flow path is maintained to the Reactor Coolant System. Exercising these valves at power would require restoring control air to facilitate valve exercising. Subsequent failure in the closed position would render the applicable RHR flow path through the associated heat exchanger inoperable. Testing would require restoration of control power to the valve and entry into a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO (TS 3.5.2) with one ECCS subsystem inoperable. Using the guidance of NUREG 1482, testing can be deferred to cold shutdown if inservice testing results in repositioning of breakers from "off" to "on" or involves a hardship; i.e., the necessity of manual operator actions to restore the system if an accident occurred. Minimizing the potential for misaligment of RHR valves is consistent with the guidance in IE Notice 87-01. Quarterly valve exercising is impractical without a commensurate increase in the level of quality an safety.

ALTERNATE TESTING:

These air operated valves shall be exercised to the open position during cold shutdowns in accordance with the requirements of IWV-3410. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• 10/1/97 32 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 32

• COJ\1PONENTS:

FUNCTION:

l 1RH19, 12RH19, 21RH19, 22RH19 These motor operated valves are located in the cross connect of the RHR heat exchanger discharges. The valves perform a passive safety function in the open position and an active safety function in the closed position. The valves are maintained in the open position, at power, to provide a flow path for both RHR pumps to supply all four RCS cold legs during the injection phase. The valves must be capable of closure during the cold leg recirculation mode when RWST inventory is depleted.

CATEGORY: B CLASS: 2 TEST REQUIREMENTS:

Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements ofIWV-3411.

DEFERRED TEST JUSTIFICATION:

• During plant operation these valves are maintained and verified in the open position per TS 4.5.2.a.2 to ensure ECCS subsystems are aligned as assumed in the design basis for the ECCS-LOCA. This requirement ensures valves are not inadvertently mispositioned, thereby providing injection capability into all four RCS cold legs. Exercising these RHR crosstie valves at power would result in rendering both trains of RHR inoperable. Testing would require restoration of control power to the valve and entry into a one hour LCO (TS 3.5.2) with both ECCS subsystems inoperable for surveillance testing. Using the guidance of NUREG 1482, testing can be deferred to cold shutdown if inservice testing results in both ECCS subsystems being completely removed from service or if testing a valve whose failure in a non-conservative position during cycling would cause a loss of system function. It should be noted that in May 1989 PSE&G proposed TS changes to eliminate the reporting requirement when an action statement is entered as a result of periodic inservice testing at full power. Entry into the one hour LCO when performing valve testing without reporting was approved per SER to TS Amendments 70 and 94 however, the guidance of NUREG 1482 is currently utilized to justify cold shutdown frequency testing.

ALTERNATE TESTING:

These motor operated valves shall be exercised to the closed pos1t1on during cold shutdowns in accordance with the requirements of IWV-3410. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• l 0/ l/97 33 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 33

• (Valves lSJl, 1SJ2, 2SJ1, 2SJ2 to be tested quarterly)

CSJ deleted in Revision 7 of the IST Program

• 10/l/97 34 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 34

• COrvIPONENTS:

FUNCTION:

1SJ30, 2SJ30 These motor operated valves are located in the suction supply line from the reactor Water Storage Tank (RWST) to the Safety Injection (SI) pumps. These valves perform an active safety function in the closed position. These valves must be capable of closure during the recirculation phase of safety injection to prevent backflow from the Residual Heat Removal (RHR) heat exchanger discharge to the RWST. Additionally, closure of these valves during the recirculation phase prevents the potential release of radioactivity to the atmosphere via the RWST vent. These valves perform a passive safety function in the open position to provide a flow path from the R WST to the respective SI pump suction.

CATEGORY: B CLASS: 2 TEST REQUIRENIENTS:

Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements of IWV-3411.

• DEFERRED TEST JUSTIFICATION:

During plant operation these valves are maintained in the open position per TS 4.5.2.a. l with the power removed from the operator to ensure Emergency Core Cooling System (ECCS) subsystem operability. Preventing valve rnispositioning ensures intermediate head safety injection capability to the Reactor Coolant System (RCS). Exercising these valves at power, with subsequent failure in the closed position, would result in rendering both SI pumps inoperable. Testing would require restoration of control power to the valve and entry into a one hour LCO (TS 3.5.2) with both ECCS subsystems inoperable for surveillance testing. Using the guidance of NUREG 1482, testing can be deferred to cold shutdown if inservice testing results in both ECCS subsystems being completely removed from service or if testing a valve whose failure in a non-conservative position during cycling would cause a loss of system function. It should be noted that in May 1989 PSE&G proposed TS changes to eliminate the reporting requirement when an action statement is entered as a result of periodic inservice testing at full power. Entry into the one hour LCO when performing valve testing without reporting was approved per SER to TS Amendments 70 and 94 however, the guidance of NUREG 1482 is currently utilized to justify cold shutdown frequency testing.

ALTERNATE TESTING:

These motor operated valves shall be exercised to the closed pos1t1on during cold

• • l 0/1/97 shutdowns in accordance with the requirements of IWV-3410. In cases of frequent cold shutdowns the valve need not be exercised more often than once every 3 months.

35 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 35

• (Valves ISJ3 l & 2SJ3 l are now exercised quarterly using VCT pressure to show valves are closed)

CSJ deleted in Revision 8 of the IST Program

• 10/l/97 36 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 36

• CONIPONENTS:

FUNCTION:

l 1SJ40, 12SJ40, 21SJ40, 22SJ40 These motor operated valves are located in the respective Safety Injection (SI) pumps discharge to the RCS hot legs. The valves perform an active safety function in the open and closed position. The valves must be capable of opening during the hot leg recirculation phase to provide a path for SI flow to each respective hot leg of the Reactor Coolant System (RCS) loop. The valves perform an active safety function in the closed position for containment isolation if required during the recirculation phase of operation.

These valves also perform an inactive safety function to act as Class 1 to Class 2 boundary barrier valves to ensure safety injection flow is properly directed to the RCS during the injection phase and cold leg recirculation mode of operation.

CATEGORY: B CLASS:*

TEST REQUIREMENTS:

Open & Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements of IWV -3411 .

• DEFERRED TEST nJSTIFICATION:

During plant operation these valves are maintained in the closed position per TS 4.5.2.a. l with the power removed from the operator to ensure emergency Core Cooling (ECCS) subsystem operability. Preventing valve mispositioning ensures intermediate head safety injection capability to the RCS cold legs. Exercising these valves individually at power, with subsequent failure in the open position, would result in rendering one ECCS subsystem incapable of performing its design safety function during the injection phase.

Testing would require restoration of control power to the valve and entry into a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO (TS 3.5.2) with one ECCS subsystem inoperable. Using the guidance of NUREG 1482, testing can be deferred to cold shutdown if inservice testing results in unnesessary cycling of equipment, repositioning of breakers from "off' to "on" or involves a hardship; i.e., the necessity of manual operator actions to restore the system if an accident occurred.

It should be noted that in May 1989 PSE&G proposed TS changes to eliminate the reporting requirement when an action statement is entered as a result of periodic inservice testing at full power. Entry into the one hour LCO when performing valve testing without reporting was approved per SER to TS Amendments 70 and 94 however, the guidance of NUREG 1482 is currently utilized to justify cold shutdown frequency testing.

ALTERNATE TESTING:

These motor operated valves shall be exercised to the open and closed position during cold shutdowns in accordance with the requirements of IWV-3410. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months.

10/1/97 37 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 37

• COMPONENTS:

FUNCTION:

l 1SJ44, 12SJ44, 21SJ44, 22SJ44 These motor operated valves are located in the supply lines from the containment sump to the respective Residual Heat Removal (RHR) pump suction. The valves perform an active safety function in the open and closed position. The valves must be capable of opening to align the containment sump to the Emergency Core Cooling System (ECCS) subsystem during the recirculation phase of emergency core cooling. These valves perform an active closed safety function to provide containment isolation if required during the recirculation phase of operation. These valves also provide a inactive safety function in the closed position to properly align ECCS subsystems to the Reactor Water Storage Tank (RWST)

• during the injection phase of emergency core cooling, and to prevent the RWST inventory backflow to the containment sump.

CATEGORY: B CLASS: 2 TEST REQUIREJ\1ENTS:

Open & Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements of IWV-3411.

DEFERRED TEST JUSTIFICATION:

During plant operation the SJ44 valves are maintained in the closed position to prevent backflow from the RWST to the containment sump, and to ensure that ECCS subsystems are properly aligned for the injection phase of emergency core cooling. Opening the SJ44 valves individually at power would require closure of RHR Pump Suction valve RH4, restoration of control power to open the SJ44 valve (removed per TS 4.5.2.a. l) and entry into a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO for one ECCS subsystem inoperable. UFSAR 7.3.2.7 also takes credit for control power being removed from the SJ44 valve circuit during normal operation. Inadvertant containment sump isolation valve failure in the open position during testing would require a plant shutdown and subsequent manway removal to gain access to the SJ44 valve. It should be noted that in May 1989 PSE&G proposed TS changes to eliminate the reporting requirement when an action statement is entered as a result of periodic inservice testing at full power. Entry into the one hour LCO when performing valve testing without reporting was approved per SER to TS Amendments 70 and 94 however, the guidance of NUREG 1482 is currently utilized to justify cold shutdown frequency testing.

ALTERNATE TESTING:

These motor operated valves shall be exercised to the openand closed position during cold shutdowns in accordance with the requirements of IWV-3410. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months.

IO/l/97 38 Revision 8

Salem Units 1 and 2 lnservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 38

• COJ\1PONENTS:

FUNCTION:

l 1SJ45, 12SJ45, 21SJ45, 22SJ45 These motor operated valves are located in the discharge lines from the Residual Heat Removal (RHR) heat exchangers to the SI and Charging/Safety Injection pumps suction supplies. The valves perform an active safety function in the open position. The valves must be capable of opening to align the containment sump to the Emergency Core Cooling System (ECCS) subsystems during the recirculation phase of emergency core cooling.

The valves perform a passive safety function in the closed position to properly align ECCS subsystems to the Reactor Water Storage Tank (RWST) during the injection phase of emergency core cooling, and to prevent the RWST inventory from backflowing to the containment sump.

CATEGORY: B CLASS: 2 TEST REQUIREMENTS:

Open Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements ofIWV-3411.

• DEFERRED TEST JUSTIFICATION:

During plant operation the SJ45 valves are maintained in the closed position to prevent backflow from the RWST to the containment sump, and to ensure that ECCS subsystems are properly aligned for the injection phase of emergency core cooling. Exercising the SJ45 valves at power requires closure of RHR Pump Suction valve RH4, restoration of control power to open the SJ44 valve (removed per TS 4.5.2.a.l for Salem 1) and entry into a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO for one ECCS subsystem inoperable. UFSAR 7.3.2.7 also takes credit for control power being removed from the SJ44 valve circuit during normal operation. Inadvertant containment sump isolation valve failure in the open position during testing would require a plant shutdown and subsequent manway removal to gain access to the SJ44 valve. It should be noted that in May 1989 PSE&G proposed TS changes to eliminate the reporting requirement when an action statement is entered as a result of periodic inservice testing at full power. Entry into the one hour LCO when performing valve testing without reporting was approved per SER to TS Amendments 70 and 94 however, the guidance of NUREG 1482 is currently utilized to justify cold shutdown frequency testing.

ALTERNATE TESTING:

These motor operated valves shall be exercised to the open position during cold shutdowns in accordance with the requirements of IWV-3410. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months lO/l/97 39 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 39

• COMPONENTS:

FUNCTION:

l 1SJ49, 12SJ49, 21SJ49, 22SJ49 These motor operated valves are located in the Residual Heat Removal (RHR) heat exchanger discharge lines to the reactor Coolant System (RCS) cold legs. The valves perform an active safety function in the closed position. The valves must be capable of closure for alignment to the recirculation mode from the injection/containment spray mode of emergency core cooling. The valves perform a passive safety function in the open position to ensure RHR pump discharge flow is properly directed to the RCS cold legs during the injection phase and for decay heat removal during shutdown cooling.

CATEGORY: B CLASS: 1 TEST REQUIREMENTS:

Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements of IWV-3411.

DEFERRED TEST JUSTIFICATION:

• During plant operation these valves are maintained in the open position per TS 4.5 .2.a. I with the power removed from the operator to ensure Emergency Core Cooling system (ECCS) subsystem operability. This requirement ensures against inadvertent mispositioning of the valves, thereby providing RHR low head safety injection capability to the RCS cold legs. Exercising these valves at power, with subsequent failure in the closed position, would result in rendering both ECCS subsystems incapable of performing their design safety function during the injection phase. Testing would require restoration of control power to the valve and entry into a one hour LCO (TS 3.5.2) with both ECCS subsystems inoperable for surveillance testing. Using the guidance of NUREG 1482, testing can be deferred to cold shutdown if inservice testing results in both ECCS subsystems being completely removed from service or if testing a valve whose failure in a non-conservative position during cycling would cause a loss of system function. It should be noted that in May 1989 PSE&G proposed TS changes to eliminate the reporting requirement when an action statement is entered as a result of periodic inservice testing at full power. Entry into the one hour LCO when performing valve testing without reporting was approved per SER to TS Amendments 70 and 94 however, the guidance of NUREG 1482 is currently utilized to justify cold shutdown frequency testing.

ALTERNATE TESTING:

These motor operated valves shall be exercised to the closed pos1tton during cold

• I 0/1/97 shutdowns in accordance with the requirements of IWV-3410. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months.

40 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 40

• COMPONENTS:

FUNCTION:

1SJ67, 1SJ68, 2SJ67, 2SJ68 These motor operated valves are located in the safety Injection (SI) pump common minimum flow recirculation line to the Reactor Water Storage Tank (RWST). The valves perform an active safety function in the closed during the recirculation phase to ensure flow is directed to the reactor vessel and to prevent containment fluid from being pumped to the RWST. This function prevents the release of radioactivity to the atmosphere via the RWST vent. The valves perform a passive safety function in the open position during the injection phase of emergency core cooling to protect the SI pumps from overheating during low flow or dead-headed operation.

CATEGORY: B CLASS: 2 TEST REQUIRENIENTS:

Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements of IWV-3411.

DEFERRED TEST JUSTIFICATION:

• During power operation these valves are maintained in the open position per TS 4.5.2.a. l with the power removed from the operator to ensure Emergency Core Cooling System (ECCS) subsystem operability. This requirement assures that the pumps will not be damaged when running at or near shut-off head by inadvertent mispositioning of the valves, thereby providing intermediate head safety injection capability to the RCS cold legs. Exercising these valves at power, with subsequent failure in the closed position, could result in rendering both safety injection pump incapable of performing their design safety function during the injection phase. Testing would require restoration of control power to the valves and entry into a one hour LCO (TS 3.5.2) with both ECCS subsystems inoperable for surveillance testing. Using the guidance of NUREG 1482, testing can be deferred to cold shutdown if inservice testing results in both ECCS subsystems being completely removed from service or if testing a valve whose failure in a non-conservative position during cycling would cause a loss of system function. It should be noted that in May 1989 PSE&G proposed TS changes to eliminate the reporting requirement when an action statement is entered as a result of periodic inservice testing at full power. Entry into the one hour LCO when performing valve testing without reporting was approved per SER to TS Amendments 70 and 94 however, the guidance of NUREG 1482 is currently utilized to justify cold shutdown frequency testing.

ALTERNATE TESTING:

These motor operated valves shall be exercised to the closed position during cold shutdowns in accordance with the requirements of IWV-3410. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months.

IO/ l/97 41 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS- 41

• COl\1PONENTS:

FUNCTION:

1SJ69, 2SJ69 These motor operated valves are located in the Residual Heat Removal (RHR) pump suction supply from the Reactor Water Storage Tank (RWST). The valves perform an active safety function in the closed position during the recirculation phase to prevent backflow from the RHR heat exchanger discharge to the RWST. Valve closure ensures required flow is directed to the reactor vessel during cold leg recirculation and prevents containment sump fluid from being pumped to the RWST. This function also prevents the release of radioactivity to the atmosphere via the RWST vent. The valve performs a passive safety function in the open position during the injection phase of emergency core cooling to provide suction supply to the pump from the RWST.

CATEGORY: B CLASS: 2 TEST REQUIREMENTS:

Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements of IWV-3411.

• DEFERRED TEST JUSTIFICATION:

During power operation these valves are maintained in the open position per TS 4.5.2.a. l with the power removed from the operator to ensure Emergency Core Cooling System (ECCS) subsystem operability. This requirement ensures against inadvertent mispositioning of the valves, thereby providing low head safety injection capability to the RCS cold legs. Exercising this valve at power, with subsequent failure in the closed position, would result in rendering both RHR pumps incapable of performing their design safety function during the injection phase. Testing would require restoration of control power to the valves and entry into a one hour LCO (TS 3.5.2) with both ECCS subsystems inoperable for surveillance testing. Using the guidance of NUREG 1482, testing can be deferred to cold shutdown if inservice testing results in both ECCS subsystems being completely removed from service or if testing a valve whose failure in a non-conservative position during cycling would cause a loss of system function. It should be noted that in May 1989 PSE&G proposed TS changes to eliminate the reporting requirement when an action statement is entered as a result of periodic inservice testing at full power. Entry into the one hour LCO when performing valve testing without reporting was approved per SER to TS Amendments 70 and 94 however, the guidance of NUREG 1482 is currently utilized to justify cold shutdown frequency testing.

ALTERNATE TESTING:

• 10/l/97 These motor operated valve shall be exercised to the closed position during cold shutdowns in accordance with the requirements ofIWV-3410. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months.

42 Revision 8

Salem Units 1 and 2 lnservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 42

• C01\1PONENTS:

FUNCTION:

1SJ135, 2SJ135 These motor operated valves are located in the Safety Injection (SI) pump common discharge to the reactor Coolant System (RCS) cold legs. The valves perform an active safety function in the closed position during the switchover from safety injection or cold leg recirculation to the hot leg recirculation phase. The valves perform a passive safety function in the open position to provide a flow path from the SI pumps to the RCS cold legs during safety injection and cold leg recirculation.

CATEGORY: B CLASS: 2 TEST REQUIRE1\1ENTS:

Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements of IWV-3411.

DEFERRED TEST mSTIFICATION:

• During power operation these valves are maintained in the open position per TS 4.5.2.a. l with the power removed from the operator to ensure Emergency Core Cooling System (ECCS) subsystem operability. This requirement prevents inadvertent mispositioning of the valves, thereby providing intermediate head safety injection capability to the RCS cold legs. Exercising these valves at power, with subsequent failure in the closed position, would result in rendering both safety injection pumps incapable of performing their design safety function during the injection phase. Testing would require restoration of control power to the valves and entry into a one hour LCO (TS 3.5.2) with both ECCS subsystems inoperable for surveillance testing. Using the guidance of NUREG 1482, testing can be deferred to cold shutdown if inservice testing results in both ECCS subsystems being completely removed from service or if testing a valve whose failure in a non-conservative position during cycling would cause a loss of system function. It should be noted that in May 1989 PSE&G proposed TS changes to eliminate the reporting requirement when an action statement is entered as a result of periodic inservice testing at full power. Entry into the one hour LCO when performing valve testing without reporting was approved per SER to TS Amendments 70 and 94 however, the guidance of NUREG 1482 is currently utilized to justify cold shutdown frequency testing.

ALTERNATE TESTING:

These motor operated valves shall be exercised to the closed position during cold shutdowns in accordance with the requirements of IWV-3410. In cases of frequent cold

• 10/1/97 shutdowns these valves need not be exercised more often than once every 3 months.

43 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 43

• COl\1PONENTS:

FUNCTION:

1SW26 2SW26 These motor operated valve is located in the respective Service Water (SW) supply header to the turbine generator area. The valves perform an active safety function in the closed position. The valves must be capable of closure by remote manual switch or on receipt of a safety injection signal. This function isolates non-essential, non-safety related SW loads and ensures adequate SW flow to safety related equipment.

CATEGORY: B CLASS: 3 TEST REQUIRE1\1ENTS:

Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements ofIWV-3411.

DEFERRED TEST JUSTIFICATION:

During power operation these valves are maintained in the open position to supply cooling water flow to the various non-safety related heat loads in the turbine building. Exercising these valves to the closed position at power is not practical because of potential damage to components, or possible transients which may cause a plant trip. The valve control circuitry is not provided with partial stroke capability.

ALTERNATE TESTING:

These motor operated valves shall be exercised to the closed pos1t1on during cold shutdowns in accordance with the requirements of IWV-3410. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• I0/1/97 44 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 44

• COJ\1PONENTS:

FUNCTION:

1CV75 2CV75 These air operated valves are located in the respective auxiliary spray line to the pressurizer from the Chemical Volume Control (CVC) system and serves as the auxiliary pressurizer spray isolation valve. The valve performs an active safety function in the open and closed position. If open during plant depressurization without the reactor coolant pumps, the valves would be required to close to limit plant pressurization rate and plant cooldown rate. The valve must be capable of opening to provide a means of pressurizer depressurization utilizing the charging system. This function may be required to depressurize the reactor Coolant (RCS) to achieve cold shutdown when the reactor coolant pumps are unavailable.

CATEGORY: B CLASS: l TEST REQUIREMENTS:

Open & Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements oflWV-3411.

DEFERRED TEST JUSTIFICATION:

These air operated valves are maintained in the closed position during power operation to isolate the RCS from the charging system. Exercising the valves to the open position at power is not possible because it would allow the injection of relatively cold water into the pressurizer resulting in pressure control instability and possible reactor trip. The valve control circuitry does not provide for partial stroke capability.

ALTERNATE TESTING:

These air operated valves shall be exercised to the open and closed positions during cold shutdown in accordance with the requirements of IWV-3410. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• 10/1/97 45 Revision 8

Salem Units I and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 45

• (Valves l SJ3, 2SJ3 to be tested quarterly)

CSJ deleted in Revision 7 of the IST Program

• I 0/1/97 46 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 46

• COl\1PONENTS:

FUNCTION:

2RH75, 2RH76 These check valves are located in the suction piping of the Residual Heat Removal (RHR) pumps. The valves perform an active safety function in the open position. The valves must be capable of opening upon RHR system initiation to accomplish emergency core cooling when reactor pressure has decreased to the point to allow low pressure injection.

The valves must be capable of closure to prevent diversion of flow and deadheading of one RHR pump when both RHR pumps are in operation (ref non-IST commitment C05 l 6 - PSL T N93106 for reverse flow test information). This is required in the unlikely event that one RHR pump develops a greater dicharge head over the other inservice pump.

CATEGORY: C CLASS: 2 TEST REQUIREMENTS:

Open Position - Check valves shall be exercised at least once every 3 months, m accordance with the requirements of IWV-3 521 .

DEFERRED TEST JUSTIFICATION:

During plant operation the RHR pumps are maintained in a standby condition, therefore these check valves remain in the closed position. Forward exercising these check valves at power would require utilizing the full flow test loop recirculating back to the RWST since the return of the minimum flow line is down stream. Utilizing this test loop requires opening manual valve RH21 to align the pump discharge to the RWST. Should this valve seize in the open position or system initiation occur during testing, the LPSI mode of RHR would be compromised by allowing pump flow to be diverted to the RWST. Additionally, RH21 is a Category A passive valve due to the test line being a potential leakage path for radioactive contaminates to a tank vented to atmosphere when RHR is operating in the recirculation mode. Opening and closing RH2 l to facilitate pump testing is burdensome due to the necessity of verifying leak tight integrity subsequent to closure.

ALTERNATE TESTING:

These check valves shall be exercised to the full open p_osition during cold shutdowns when the RHR is operating in the shutdown cooling mode. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• 10/1/97 47 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 47

• COMPONENTS:

FUNCTION:

1CC71, 2CC71 This normally open, fail-closed, air operated control valve is located in the outlet line from the letdown heat exchanger. This control valve has an active safety function in the closed position to isolate CC flow to the Letdown Heat Exchanger to prevent CC pump runout and ensure sufficient CC flow exists to the safety-related portion of the component cooling system. This valve interlocked with Letdown Containment Isolation valve CV7 such that when CV7 is fully closed, valve CC71 closes. Valve CC71 closes automatically (via CV7 interlock) during a LOCA on a Containment Isolation Phase A signal, or manually when letdown is secured during plant shutdown.

• CATEGORY: B CLASS: 3 TEST REQUIREMENTS:

Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements ofIWV-3411.

• DEFERRED TEST JUSTIFICATION:

This air operated control valve is maintained in the open position to provide a flow path from the Letdown Heat Exchanger during normal letdown operation. This flow path is required during all phases of plant operation to support eves operation which maintains proper reactor coolant inventory by means of a continuous feed and bleed process.

Exercising this valve to the closed position at power would require isolating normal letdown flow through the regenerative heat exchanger and placing excess letdown in operation. Isolation of the regenerative heat exchanger would prevent the transfer of heat from the letdown flow to the charging flow. This creates the potential of thermal shock to the RCS charging inlet nozzle branch connections and thermal sleeves by the injection of relatively cold water. The injection of cold water could also result in a power transient and RCS instability during plant operation. Additionally, the valve control circuitry is not provided with partial stroke capability.

ALTERNATE TESTING:

This valve shall be exercised to the closed position in accordance with the requirements of IWV-3400 during cold shutdown. In cases of frequent cold shutdowns this valve need not be exercised more often than once every 3 months .

• IOI 1/97 48 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 48

• COrvIPONENTS:

FUNCTION:

1VC1, 1VC4 2VC1, 2VC4 These air operated valves are located in the primary containment purge supply and exhaust ventilation ductwork and serve as outboard containment isolation valves. These valves perform an active safety function in the closed position. They must be capable of automatic closure, if open, upon receipt of a containment isolation signal or when high radioactivity is detected in primary containment. This function prevents the release of radioactivity from the containment environment in the event of a LOCA.

CATEGORY: A CLASS: 2 TEST REQUIREl'v!ENTS:

Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements ofIWV-3411.

BASIS FOR RELIEF :

These valves are maintained in the closed position during power operation with control air to the valve operators isolated and tagged out of service. Exercising these valves at power, with subsequent failure in the open position, would result in the possibility of compromising primary containment integrity. Additionally, these valves are prohibited by TS 3. 6. 1. 7 from being exercised to the open position whenever primary containment integrity is required. This requirement is also a commitment to the NRC in LER 50-272/79-55/01 T.

ALTERNATE TESTING:

These air operated valves shall be exercised to the closed position during cold shutdown whenever primary containment vent and purge activities are performed via the large volume flow path. In cases of frequent vent and purge activities, these valves need not be exercised more often than once every 3 months. This alternate testing was previously identified in NRC Safety Evaluation dated 4/15/94 (TAC Nos. M88144 and M88145) .

• I0/1/97 49 Revision 8

Salem Units 1 and 2 Inservice Test Program

• COLD SHUTDOWN TEST JUSTIFICATION - CS - 49 COMPONENTS: 1VC2, 1VC3 2VC2, 2VC3 FUNCTION:

These air operated valves are located in the primary containment purge supply and exhaust ventilation ductwork and serve as inboard containment isolation valves. These valves perform an active safety function in the closed position. They must be capable of automatic closure, if open, upon receipt of a containment isolation signal or when high radioactivity is detected in primary containment. This function prevents the release of radioactivity from the containment environment in the event of a LOCA.

CATEGORY: A CLASS: 2 TEST REQUIREMENTS:

Category A and B valves shall be exercised at least once every 3 months, in accordance

• with the requirements ofIWV-3411.

DEFERRED TEST JUSTIFICATION:

These valves are maintained in the closed position during power operation with control air to the valve operators isolated and tagged out of service. Exercising these valves at power, with subsequent failure in the open position, would result in the possibility of compromising primary containment integrity. Also, these valves are prohibited by TS 3.6.1.7 from being exercised to the open position whenever primary containment integrity is required. This requirement is also a commitment to the NRC in LER 50-272/79-55/01 T.

ALTERNATE TESTING:

These air operated valves shall be exercised to the closed position during cold shutdown whenever primary containment vent and purge activities are performed via the large volume flow path. In cases of frequent vent and purge activities, these valves need not be exercised more often than once every 3 months. This alternate testing was previously identified in NRC Safety Evaluation dated 4/15/94 (TAC Nos. l\188144 and M88145) .

• 10/ 1/97 50 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN TEST JUSTIFICATION - CS - 50 COMPONENTS: l 1SJ54, 12SJ54, 13SJ54, 14SJ54, 21SJ54, 22SJ54, 23SJ54, 24SJ54 FUNCTION:

These motor operated valves are located in the respective Safety Injection (SI) accumulator discharge to the RCS cold legs. The valves perform an inactive safety function in the open position to allow accumulator safety injection. These valves are closed during plant cooldown and depressurization to prevent unnecessary injection by the SI Accumulators and to achieve a cold shutdown condition. During a small break LOCA the SJ54 valves are closed in order to allow faster Reactor Coolant System (RCS) depressurization so the RCS leak can be isolated. However, if the valves do not close, then leak isolation will take longer and greater RCS will be released to Containment.

CATEGORY: B CLASS:

TEST REQUIREI\ffiNTS:

Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements of IWV-3411.

• DEFERRED TEST msTIFICATION:

During plant operation these valves are maintained in the open position per TS 4.5.1 with the power removed from the operator to ensure emergency Core Cooling (ECCS) subsystem operability. Preventing valve mispositioning ensures SI accumulator injection capability to the RCS cold legs. Technical specifications do not allow these valves to be closed at any time in Modes 1, 2 or 3. Exercising these valves individually at power, with subsequent failure in the closed position, would result in rendering the affected SI accumulator incapable of performing its design safety function during the injection phase.

Testing would require restoration of control power to the valve and entry into a one hour LCO (TS 3.5.1.b) with one accumulator inoperable.

AL TERN ATE TESTING:

These motor operated valves shall be exercised to the closed pos1t1on during cold shutdowns in accordance with the requirements of IWV-3410. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months .

• [()/J/97 51 Revision 8

Salem Units 1 and 2 Inservice Test Program COLD SHUTDOWN JUSTIFICATION CS-51

• COMPONENTS:

FUNCTION:

1RH26, 2RH26 These motor operated valves are located in the flow path to the RCS hot legs. The valves perform a active safety function in the open position. The valves must be capable of opening to provide a flow path for mode 4 LOCA mitigation and recirculation flow via the RCS hot legs. These normally closed valves also perform a active safety function in the closed position to provide containment isolation during power operation in modes 1 through 3.

CATEGORY: B CLASS:

TEST REQUIREMENTS:

Open & Closed Position - Category A and B valves shall be exercised at least once every 3 months, in accordance with the requirements ofIWV-3411.

BASIS FOR RELIEF:

• During power operation, the RH26 valve is maintained and verified in the closed position per TS 4.5.2.a.2 to ensure ECCS subsystems are aligned as assumed in the design basis for the ECCS-LOCA. This requirement ensures valves are not inadvertently mispositioned, thereby providing injection capability into all four RCS cold legs. Exercising these RHR hot leg injection valves at power would result in rendering both trains of RHR inoperable.

Testing would require restoration of control power to the valve and entry into a one hour LCO (TS 3.5.2) with both ECCS subsystems inoperable for surveillance testing. Using the guidance of NUREG 1482, testing can be deferred to cold shutdown if inservice testing results in both ECCS subsystems being completely removed from service or if testing a valve whose failure in a non-conservative position during cycling would cause a loss of system function.

ALTERNATE TESTING:

These motor operated valves shall be exercised to the open and closed position during cold shutdowns in accordance with the requirements of IWV-3410. In cases of frequent cold shutdowns these valves need not be exercised more often than once every 3 months.

L0/1/97 52 Revision 8

Salem Units 1and2 Inservice Test Progam ATTACHMENT 3 REFUELING OUT AGE JUSTIFICATIONS (MIXED WITH RELIEF REQUESTS AT THIS TIME)

• • I 0/1/97 Revision 8

Salem Units 1and2 Inservice Test Progam ATTACHMENT4 PUMP RELIEF REQUESTS

{NONE AT THIS TIME)

• 1()/1/97 Revision 8

ATTACHMENT 5 VAL VE RELIEF REQUESTS

Salem Units 1 and 2 Inservice Test Progam VALVE RELIEF REQUEST- V- 01 CO.rvtPONENTS: Various Safety and Relief Valves FUNCTION:

Provide over pressure protection for various AS:ME Class 1, 2 and 3 components and ptpmg.

CATEGORY: C (safety and relief valves)

CLASS: 1, 2, and 3 TEST REQUIRE:MENTS:

The 1983 Edition, with Summer 1983 Addenda, of AS:ME Boiler and Pressure Vessel Code,Section XI, Subsection IWV-3500 requires the testing of Category C safety and relief valves. Subsection IWV-3512, Test Procedure, states that safety and relief valve set points shall be tested in accordance with ASME Performance Test Code (PTC) 25.3-1976. AS:ME PTC 25.3-1976, paragraph 3.02, Qualification of Person Supervising the Test, states that "a person whom has obtained a degree in a branch of Engineering from a recognized school of Engineering and in addition, has had at least two-years practical

• experience in fluid-flow measurement, may be considered qualified to supervise the test."

BASIS FOR RELIEF:

The requirements of PTC 25 .3 are primarily applicable to the manufacturer's acceptance testing of new valves. Salem Generating Station maintenance activities and test procedures verify valve operational readiness as stipulated in paragraph 4.09 of the PTC.

The 1977 Addendum of PTC 25. 3, issued September 1977, revised paragraph 3. 02, Qualification of Person Supervising the Test, to read " A person who supervises the test shall have a formal education in thermodynamics and fluid mechanics. In addition, he shall have at least two years practical experience in fluid flow measurement and have had experience in test supervision." The AS:ME Code committee issued Code Case N-442 on February 23, 1987, which states that "It is the opinion of the Committee that the 1977 Addendum may be included in all references to ANSI/ ASME PTC 25. 3-197 6 in Section III, Division 1, Subsections NB, NC, ND, and NE." In responding to inquiry number IN-92-027, the AS:ME Code Committee,Section XI, stated that, although the test supervisor's qualifications of ASME PTC 25.3-1976, paragraph 3.02, apply when performing set point testing in accordance with Section XI, IWV-3 512, the provisions stated in PTC 25.3-1976, paragraph 3.02, are permissive (allow discretion). Therefore, the guidance for test supervisor qualification in Code Case N-442 is an acceptable alternative to Section XI inservice testing requirements as well asSection III design capacity verification .

• I 0/1/97 Revision 8

Salem Units 1 and 2 Inservice Test Progam V - 01 (Cont)

• ALTERNATE TESTING:

Perform Category C safety and relief valve testing in accordance with AS1\.1E Section XI, IWV-3512 and PTC 25.3-1976 with testing supervisors meeting the qualification requirements set forth in Section 3.02 of PTC 25.3-1976 September 1977 Addendum (Code Case N-442). These qualification requirements have been incorporated into the Salem Maintenance Department qualification requirements for test supervisors of safety and relief valve testing. This alternate testing was previously approved in NRC Safety Evaluation dated April 15, 1994 (TAC Nos. M88144 and M88145) and in NUREG-1482, Section 4.3.3 .

• 10/1/97 Revision 8

Salem Units 1 and 2 lnservice Test Progam VALVE RELIEF REQUEST- V- 02 COMPONENTS: l 1AF53, 12AF53, 13AF53 21AF53, 22AF53, 23AF53 FUNCTION:

These check valves are located in the alternate suction supply piping to the auxiliary feedwater pumps and perform an active safety function in the open position. The valves must be capable of opening to allow passage of design accident flow when the auxiliary feedwater pumps are aligned to their alternate source.

CATEGORY: C CLASS: 3 TEST REQUIREl\ffiNTS:

Open Position - Check valves shall be exercised at least once every 3 months, m accordance with the requirements ofIWV-3521.

BASIS FOR RELIEF:

• Exercising these check valves to the open position during normal plant operation or cold shutdown would require utilizing the alternate supply source during pump testing. This is undesirable due to the likelihood of creating adverse chemistry conditions in the steam generators or contaminating the AFST due to the lower water quality of the alternate supply source. Additionally, the lines which contain these check valves are maintained in a vented condition during normal plant operation, due to the lines being routed through a vital relay room. If the lines were placed in a solid condition, line leakage could result in extensive damage to electronic components, in addition to causing a reactor trip .. Partial stroke exercising would result in the same consequences as full stroke exercising.

ALTERNATE TESTING:

These check valves shall be disassembled and inspected during refueling to verify operability. Partial exercising will be unable to be performed subsequent to reassembly.

In accordance with the NRC guidance provided in Generic Letter 89-04, Attachment l, Position 2, a sample disassembly and inspection program shall be implemented as outlined in Technical Position 6. This alternate testing was previously identified in NRC Safety Evaluation dated October 9, 1992 (TAC Nos. M74790 and M74791) and is pre-approved by Generic Letter 89-04.

NOTE: PR 950929134 is currently in process to evaluate removal of the internals of these check valves 10/1/97 Revision 8

Salem Units 1 and 2 Inservice Test Progam VALVE RELIEF REQUEST- V - 03 COrvt:PONENTS: 1AF71, 1AF72 FUNCTION:

These check valves are located in the AF alternate suction supply piping from the demineralized water storage tanks and fire protection/domestic water storage tanks. The valves perform an active safety function in the closed position. The valves must be capable of closure when the AF system is aligned to service water as the alternate suction supply source. This function prevents diversion of the qualified AF alternate suction supply (SW) to the non-safety related, non-seismic system piping of demineralized and fire protection/domestic water systems.

CATEGORY: C CLASS: 3 TEST REQUIRE1\1ENTS:

Closed Position - Check valves shall be exercised at least once every 3 months, m accordance with the requirements ofIWV-3521.

• BASIS FOR RELIEF:

The lines which contain these check valves are maintained in a vented condition during normal plant operation, due to the lines being routed through a vital relay room. Whereas, line leakage could result in extensive damage to electronic components, in addition to causing a reactor trip. Exercising these check valves to the closed position during normal plant operation or cold shutdown would require filling the vented line and utilizing an outside pressure source to verify valve closure. This activity is undesirable during power operation due to the potential for leakage and the necessity to drain the line subsequent to testing either which could result in a plant trip or damage to electronic components.

Testing during cold shutdown would require an abnormal valve alignment and the use of temporary test equipment which could delay plant restart. These valves are maintained in a dry condition and are seldom placed in service. Reverse exercising during plant operation or cold shutdown is burdensome without a commensurate increase in the level of quality or safety .

• 10/1/97 Revision 8

Salem Units 1 and 2 lnservice Test Progam V - 03 (Cont)

ALTERNATE TESTING:

These check valves shall be disassembled and inspected during refueling to verify operability. Partial exercising will be unable to be performed subsequent to reassembly.

In accordance with the NRC guidance provided in Generic Letter 89-04, Attachment 1, Position 2, a sample disassembly and inspection program shall be implemented as outlined in Technical Position 6. This alternate testing was previously identified in NRC Safety Evaluation dated October 9, 1992 (TAC Nos. M74790 and M74791) and is pre-approved by Generic Letter 89-04 .

• 10/1/97 Revision 8

Salem Units 1 and 2 Inservice Test Progam

• CO.rvt:PONENTS:

FUNCTION:

VALVE RELIEF REQUEST- V - 04 l 1CA360, 12CA360 21CA360, 22CA3 60 These check valves are located in the compressed air supply lines to the containment. The valves are designated as inboard containment isolation valves, and perform an active safety function in the closed position to maintain containment integrity.

CATEGORY: AC CLASS: 2 TEST REQUIREMENTS:

Closed Position - Check valves shall be exercised at least once every 3 months, m accordance with the requirements of IWV-3521.

BASIS FOR RELIEF:

During normal plant operation these valves remain in the open pos1t1on to ensure a continuous supply of compressed air to various safety related components located in the containment which are dependent upon compressed air for actuation and control.

Exercising these check valves to the closed position would require securing the associated compressed air header, then venting the header while simultaneously applying a temporary pressure source downstream of the check valve. This activity is not practicable during power operation due to the prolonged interruption of control air to various safety related components resulting in a loss of operability, and the necessity to enter containment to perform testing. This test activity is burdensome during cold shutdown due to the abnormal valve alignment and the necessity of using temporary test equipment which could delay plant restart.

ALTERNATE TESTING:

These check valves shall be exercised to the closed position at refuelings during the performance of Type C seat leakage testing. This alternate frequency and method of testing is supported by NUREG - 1482, Paragraph 4.1.4. This alternate testing was previously approved in NRC Safety Evaluation dated October 9, 1992 (TAC Nos.

M74790 and M74791) and is pre-approved by Generic Letter 89-04 .

• 10/ l/97 Revision 8

Salem Units 1 and 2 Inservice Test Progam (NON-CODE) VALVE REFUELING OUTAGE JUSTIFICATION - V- 05 COMPONENTS: 1CA1768, 1CA1769, 1CA1770, 1CA1771 2CA1785, 2CA1786, 2CA1787, 2CA1788 FUNCTION:

These check valves are located in the compressed air supply lines to the POR V accumulators. The valves perform an active safety function in the closed position to maintain the pressure boundary integrity of the PORV accumulators upon loss of the normal actuating air supply.

CATEGORY: AC CLASS: None TEST REQUIREMENTS:

Closed Position - Check valves shall be exercised at least once every 3 months, m accordance with the requirements of IWV-3 521.

BASIS FOR RELIEF:

• During normal plant operation these valves remain in the closed position. The valves open as required to pressurize the PORV accumulators. Exercising these check valves to the closed position would require securing the associated Control Air header, then venting the header while performing a valve seat leakage or pressure decay test. This activity is not practicable during power operation due to the prolonged interruption of control air to various safety related components resulting in a loss of operability, and the necessity to enter containment to perform testing. Technical Specifications require the pressurizer over-pressure protection system (POPS) to be operable in Modes 5 & 6 when the reactor head is installed and the RCS is not vented. Typically in Cold Shutdown (Mode 5) the RCS is not vented. This test activity is burdensome during cold shutdown due to the abnormal valve alignment and the necessity to utilize temporary test equipment (i.e. LRM, N2 Bottle, Tools, etc.) inside containment which could delay plant restart.

ALTERNATE TESTING:

These check valves shall be exercised on an augmented program basis to the closed position at refuelings by performing seat leakage tests. This alternate test frequency and method of testing is supported by NUREG - 1482, Paragraph 4.1.4. Testing shall be performed in accordance with the provisions of paragraph 4.3.2.2.(e) of OM-10.

Implementation of OM-10 paragraph 4.3.2 is discussed in Technical Position TP-8 .

• 10/1/97 Revision 8

Salem Units 1 and 2 lnservice Test Progam VALVE REFUELING OUTAGE JUSTIFICATION - V- 06 COl\1PONENTS: lCCl 19 2CC119 FUNCTION:

This check valve is located in the CCW supply line which provides cooling water to the RCP bearings and thermal barriers. The valve performs an active safety function in the open position to provide thermal overpressure protection to the associated containment penetration piping and components. The valve is designated as an inboard containment isolation valve, and performs an active safety function in the closed position to maintain containment integrity.

CATEGORY: AC CLASS: 2 TEST REQUIREMENTS:

Closed Position - Check valves shall be exercised at least once every 3 months, m accordance with the requirements ofIWV-3521.

• BASIS FOR RELIEF:

During normal plant operation this valve is maintained in the open pos1t1on by a continuous supply of cooling water flow to the motor bearings and thermal barriers on all four of the RCPs. Exercising this check valve to the closed position would require securing the CCW supply header and applying a temporary pressure source downstream of the valve disk to verify closure. This activity is not possible during power operation due to the necessity of removing all four of the RCPs from service to prevent extensive pump damage. Stopping the Reactor Coolant Pumps at cold shutdown could extend the shutdown period. This test activity is burdensome during cold shutdown due to the necessity of securing the RCP's, entering containment and the use of temporary test equipment which could delay plant restart.

ALTERNATE TESTING:

These check valves shall be exercised to the closed pos1t1on at refuelings during the performance of Type C seat leakage testing. This alternate test frequency and method of testing is supported by NUREG - 1482, Paragraph 3 .1. 1. 4. It should be noted that alternate testing to reverse exercise during cold shutdown and during refueling was previously identified in NRC Safety Evaluation dated October 9, 1992 (TAC Nos.

M74790 and M74791) and is pre-approved by Generic Letter 89-04. Cold shutdown testing has been discontinued as recommended by NUREG 1482. Testing shall be performed in accordance with the provisions of paragraph 4.3.2.2.(e) of OM-10 .

Implementation of OM-10 paragraph 4.3.2 is discussed in Technical Position TP-8.

l 0/1/97 Revision 8

Salem Units 1 and 2 Inservice Test Progam

• COMPONENTS:

VALVE REFUELING OUTAGE JUSTIFICATION - V- 07 1CC186, 1CC208, 2CC186, 2CC208 FUNCTION:

These check valves are located in bypass lines around inboard containment isolation valves CC187 and CC190. The valves perform an active safety function in the open position to provide thermal overpressure protection to the associated containment penetration piping and components. The valves are designated as inboard containment isolation valves, and perform an active safety function in the closed position to maintain containment integrity.

CATEGORY: AC CLASS: 2 TEST REQUIREMENTS:

Open & Closed Position - Check valves shall be exercised at least once every 3 months, in accordance with the requirements of IWV-3 521.

BASIS FOR RELIEF:

During normal plant operation these valves are maintained in the closed pos1t1on by cooling water return flow from the motor bearings and thermal barriers on all four of the RCPs. Individually exercising these check valves to the closed position would require securing the CCW supply and return headers and applying a temporary pressure source downstream of the valve disk to verify closure. Individually exercising these check valves to the open position would require securing the CCW supply and return headers and applying a dernineralized supply source upstream of the valves to verify opening capability. These activities are not possible during power operation due to the necessity of removing all four of the RCPs from service to prevent extensive pump damage. Stopping the Reactor Coolant Pumps at cold shutdown could extend the shutdown period. This test activity is burdensome during cold shutdown due to the necessity of securing the RCP' s, entering containment and the use of temporary test equipment which could delay plant restart. Partial exercising these valves to the open position would result in the same consequences as full exercising.

ALTERNATE TESTING:

These check valves shall be exercised to the closed position at refuelings during the performance of Type C seat leakage testing. This alternate test frequency and method of testing is supported by NUREG - 1482, Paragraph 3 .1.1.4. These check valves shall be exercised to the open position at refuelings. It should be noted that alternate testing to open exercise test during cold shutdown and during refueling was previously identified in NRC Safety Evaluation dated October 9, 1992 (TAC Nos. M74790 and M74791) and is pre-approved by Generic Letter 89-04 .. Cold shutdown testing has been discontinued as recommended by NUREG 1482. Testing shall be performed in accordance with the

• I 0/1/97 provisions of paragraph 4.3.2.2.(e) ofOM-10. Implementation of OM-10 paragraph 4.3.2 is discussed in Technical Position TP-8.

Revision 8

Salem Units 1and2 Inservice Test Progam VAL VE RELIEF REQUEST - V - 08 COMPONENTS: l 1CC128, 12CC128, 13CC128, 14CC128 21CC128, 22CC128, 23CC128, 24CC128 FUNCTION:

These check valves are located in the CC supply lines to the RCP thermal barriers. The valves perform an active safety function in the closed position to prevent overpressurization to the CC piping as a result of RCS inleakage subsequent to a breach of the thermal barrier pressure boundary integrity.

CATEGORY: C CLASS: 3 TEST REQUIREMENTS:

Closed Position - Check valves shall be exercised at least once every 3 months, m accordance with the requirements ofIWV-3521.

BASIS FOR RELIEF:

• During normal plant operation these valves are maintained in the open pos1t1on by component cooling water supply flow to the RCP thermal barriers. Individually exercising these check valves to the closed position would require securing the CC supply lines to the motor bearing oil coolers and thermal barrier while venting within the isolated boundary upstream of the check valve. Then measuring valve leakage at the vent connection. This activity is not possible during power operation due to the necessity of removing an RCP from service. T:S.3.4.1.1 requires all reactor coolant loops to remain operable during Mode 1. Stopping the Reactor Coolant Pumps during cold shutdown could extend the shutdown period. This test activity is burdensome and hazardous to test personnel during cold shutdown, due to the necessity of entering containment, the manipulation of various manual valves, and the exposure oftest personnel to chromated water. This test activity is not only a personnel health and environmental hazard, but could also delay plant restart.

ALTERNATE TESTING:

These check valves shall be exercised to the closed position during refuelings after the component cooling system has been dechromated. This alternate testing was previously identified in NRC Safety Evaluation dated October 9, 1992 (TAC Nos. M74790 and M74791) and is pre-approved by Generic Letter 89-04 .

• 10/1/97 Revision 8

Salem Units 1 and 2 Inservice Test Progam

• VALVE RELIEF REQUEST - V - 09 COMPONENTS: l 1CS4, 12CS4 21CS4, 22CS4 .

FUNCTION:

These check valves are located in the individual containment spray headers. The valves perform an active safety function in the open position. The valves must be capable of opening upon spray pump initiation to allow flow to be directed to the containment spray nozzles.

CATEGORY: C CLASS: 2 TEST REQUIREMENTS:

Open Position - Check valves shall be exercised at least once every 3 months, m accordance with the requirements ofIWV-3521.

BASIS FOR RELIEF:

• During normal plant operation the containment spray headers are maintained in a dry condition and no external means exists to facilitate valve exercising. Individually exercising these check valves to the open position would require initiating pump flow.

This activity is not possible during power operation without spraying down containment resulting in equipment and lagging damage which would require extensive cleanup and repair. Forward exercising these check valves during cold shutdown is also not possible due to the full flow test line discharging to the refueling cavity which is available only during refueling outages. The likelihood of valve degradation is improbable due to the condition in which the headers are maintained. Therefore, this test activity is burdensome without a commensurate increase in the level of valve reliability.

ALTERNATE TESTING:

These check valves shall be full exercised to the open pos1t1on during refuelings in accordance with the requirements of IWV-3520. This alternate testing was previously identified in NRC Safety Evaluation dated October 9, 1992 (TAC Nos. M74790 and M74791) and is pre-approved by Generic Letter 89-04.

10/1/97 Revision 8

Salem Units 1 and 2 Inservice Test Progam VALVE RELIEF REQUEST - V - 10 COMPONENTS: l 1CS48, 12CS48, 21CS48, 22CS48 FUNCTION:

These check valves are located in the individual containment spray headers. The valves perform an active safety function in the open and closed positions. The valves must be capable of opening upon spray pump initiation to allow flow to be directed to the containment spray nozzles. The valves are designated as inboard containment isolation valves, and perform an active safety function in the closed position to maintain containment integrity.

CATEGORY: AC CLASS: 2.

TEST REQUIRErvtENTS:

Open & Closed Position - Check valves shall be exercised at least once every 3 months, in accordance with the requirements of IWV-3 521.

BASIS FOR RELIEF:

During normal plant operation the containment spray headers are maintained in a dry condition and no external means exists to facilitate valve exercising. Individually

• exercising these check valves to the open position would require initiating pump flow .

. This activity is not possible during power operation without spraying down containment resulting in equipment and lagging damage which would require extensive cleanup and repair. Forward exercising these check valves during cold shutdown is also not possible due to the full flow test line discharging to the refueling cavity which is available only during refueling outages. Exercising these valves to the closed would require manual isolation of the individual spray header downstream of the check valve while venting upstream, then applying an outside pressure source to verify valve closure. This test activity is not practicable during power operation or cold shutdown due to the necessity for containment entry to isolate the header and apply temporary test equipment which could delay plant startup. The likelihood of valve degradation is improbable due to the condition in which the headers are maintained.

ALTERNATE TESTING:

These check valves shall be full exercised to the open pos1t1on during refuelings in accordance with the requirements of IWV-3520. These check valves shall be exercised to the closed position at refuelings during the performance of Type C seat leakage testing.

This alternate test frequency method of testing is supported by NUREG - 1482, Paragraph 4.1.4. This alternate testing was previously identified in NRC Safety Evaluation dated October 9, 1992 (TAC Nos. M74790 and M74791) and is pre-approved by Generic Letter 89-04 .

• I 011/97 Revision 8

Salem Units 1 and 2 Inservice Test Progam

• VALVE RELIEF REQUEST - V - 11 C01\.1PONENTS: 1CV47, 1CV52 2CV47, 2CV52 FUNCTION:

These check valves are located in the respective # 11 & # 12 and #21 & #22 charging/safety injection pumps discharge lines. The valves perform an active safety function in the open and closed positions. The valves* must be capable of opening upon safety injection pump initiation to allow flow to be directed to the RCS cold legs. The valves must also be capable of closure to prevent diversion of flow through an adjacent idle or tripped charging/safety injection pump.

CATEGORY: C CLASS: 2 TEST REQUIREMENTS:

Open Position - Check valves shall be exercised at least once every 3 months, m

• accordance with the requirements ofIWV-3521 .

BASIS FOR RELIEF:

At power, the centrifugal charging/safety injection pumps are in operation to provide normal charging. Exercising these valves to the full open position would require establishing flow through the safety injection flow path. This is not possible at power due to the interruption of normal charging flow which could cause a loss of pressurizer level control resulting in a plant trip. Additionally, insufficient expansion volume exist in the reactor vessel to accommodate flow. Exercising these valves to the full open at cold shutdown is not practicable due to the potential of creating a low temperature overpressure condition. Additionally, flow measurement requires the installation of temporary test equipment inside primary containment which could delay plant restart.

ALTERNATE TESTING:

These check valves shall be partially exercised to the open position during quarterly pump testing and full exercised at refuelings in accordance with the requirements of IWV-3520.

This alternate testing was previously identified in NRC Safety Evaluation dated October 9, 1992 (TAC Nos. M74790 and M74791) and is pre-approved by Generic Letter 89-04 .

• 10/1/97 Revision 8

Salem Units 1 and 2 Inservice Test Progam

• COl'vtPONENTS:

VALVE REFUELING OUTAGE JUSTIFICATION - V - 12 1CV74 2CV74 FUNCTION:

This check valve is located in the charging line to the respective regenerative heat exchanger. The valve performs an active safety function in the open and closed positions.

The valve must be capable of passing required flow for emergency boration in the absence of an SI signal. The valve must also be capable of closure on reversal or loss of flow to provide containment isolation.

CATEGORY: AC CLASS: 2 TEST REQUIREMENTS:

Closed Position - Check valves shall be exercised at least once every 3 months, m accordance with the reg uirements of IWV-3 521 .

• BASIS FOR RELIEF:

At power, the centrifugal charging/safety injection pumps are in operation to provide normal charging flow. Exercising this valve to the closed position would require stopping normal charging flow, then utilizing an outside pressure source to verify valve closure.

This is not possible during normal operation. Interruption of charging flow could cause a loss of pressurizer level control resulting in a plant trip. Valve exercising during cold shutdown is .impractical due to the necessity of entering primary containment to facilitate the installation of temporary test equipment and to reposition various manual valves. This type of test activity during cold shutdown could potentially delay plant restart.

ALTERNATE TESTING:

These check valves shall be exercised to the closed pos1t1on at refueling during the performance of Type C seat leakage testing. This alternate frequency and method of testing is supported by NUREG - 1482, Paragraph 4. 1.4 and is pre-approved by Generic Letter 89-04. Testing shall be performed in accordance with the provisions of paragraph 4.3.2.2.(e) of OM-10. Implementation of OM-10 paragraph 4.3.2 is discussed in Technical Position TP-8 .

• I 011/97 Revision 8

Salem Units 1 and 2 Inservice Test Progam

• COMPONENTS:

VALVE REFUELING OUTAGE JUSTIFICATION - V - 13 l 1CV99, 12CV99, 13CV99, 14CV99 21CV99, 22CV99, 23CV99, 24CV99 FUNCTION:

These check valves are located in the CVCS supply lines to the RCP shaft seals. The operational function is to provide a path for CVCS flow to the RCP shaft seals for cooling purposes and to prevent RCS leakage past the #1 seal. The valves perform an active safety function in the closed position, and must be capable of closure on reversal or loss of flow to provide containment isolation.

CATEGORY: AC CLASS: 2 TEST REQUIREMENTS:

Closed Position - Check valves shall be exercised at least once every 3 months, m accordance with the requirements of IWV-3 521.

• BASIS FOR RELIEF:

The RCPs are required to remain in service during normal operation. per T. S. 3. 4. 1. 1, to provide forced circulation of RCS through the reactor to meet heat transfer and power generation requirements. Exercising these check valves to the closed position would require stopping CVCS flow to the associated RCP, then utilizing an outside pressure source to verify valve closure. This is not possible during normal operation. Interruption of CVCS flow to the RCP seals could cause damage to the pump seals resulting in a reactor shutdown or plant trip. Stopping the Reactor Coolant Pumps during cold shutdown could extend the shutdown period. Valve exercising during cold shutdown is impractical due to the necessity of securing the RCP's, entering primary containment to facilitate the installation of temporary test equipment and to reposition various manual valves. This type of test activity during cold shutdown could potentially delay plant restart.

ALTERNATE TESTING:

These check valves shall be exercised to the closed pos1t1on at refueling during the performance of Type C seat leakage testing. This alternate frequency and method of testing is supported by NUREG - 1482, Paragraph 3 .1.1.4 and is pre-approved by Generic Letter 89-04. Testing shall be performed in accordance with the provisions of paragraph 4.3.2.2.(e) of OM-10. Implementation of OM-10 paragraph 4.3.2 is discussed in Technical Position TP-8 .

10/1/97 Revision 8

Salem Units 1 and 2 Inservice Test Progam

• COJ\1PONENTS:

FUNCTION:

VALVE REFUELING OUTAGE JUSTIFICATION - V- 14 1CV296, 2CV296 This check valve is located within the containment penetration piping in the CVCS supply lines to the RCP shaft seals. The operational function is to provide a path for CVCS flow to the RCP shaft seals for cooling purposes and to prevent RCS leakage past the # l seal.

The valve performs an active safety function in the open and closed positions. The valve must be capable of closure on reversal or loss of flow to provide containment isolation.

The valve must also be capable of opening to provide thermal overpressure protection to the associated containment penetration piping and components.

CATEGORY: AC CLASS: 2 TEST REQUIREMENTS:

Open & Closed Postion - Check valves shall be exercised at least once every 3 months, in accordance with the requirements of fWV-3 521.

BASIS FOR RELIEF:

• The Reactor Coolant Pumps are required to remain in service during normal operation per T.S. 3.4.1.1, to provide forced circulation of RCS through the reactor to meet heat transfer and power generation requirements. Exercising these valves to the open or closed position would require stopping CVCS flow to the associated RCP, then utilizing a temporary pressure source to verify valve opening and closure capability.

• This is not possible during normal operation. Interruption of CVCS flow to the RCP seals could cause damage to the pump seal resulting in a reactor shutdown or plant trip. Stopping the Reactor Coolant Pumps during cold shutdown could extend the shutdown period. Valve exercising during cold shutdown is impractical due to the necessity of securing the RCP' s, entering primary containment to facilitate the installation of temporary test equipment and to reposition various manual valves. This type of test activity during cold shutdown could potentially delay plant restart. Partial stroke exercising this check valve at power or cold shutdown is not possible due to the inability to verify the passage of flow.

ALTERNATE TESTING:

This check valve shall be exercised to the open and closed pos1t1ons at refueling.

Verification of valve closure shall be accomplished during the performance of Type C seat leakage testing. This alternate frequency and method of closure testing is supported by NUREG - 1482, Paragraph 4.1.4 & 3.1.1.4. It should be noted that alternate testing to open exercise during cold shutdown and during refueling was previously identified in NRC Safety Evaluation dated October 9, 1992 (TAC Nos. M74790 and M74791) and is pre-approved by Generic Letter 89-04. Cold shutdown testing has been discontinued as recommended by NUREG 1482. Testing shall be performed in accordance with the provisions of paragraph 4.3.2.2.(e) ofOM-10. Implementation ofOM-10 paragraph 4.3.2 is discussed in Technical Position TP-8.

10/ l/97 Revision 8

Salem Units 1 and 2 lnservice Test Progam VALVE REFUELING OUTAGE JUSTIFICATION - V- 15 COl\1PONENTS: 1NT26, 1NT34 2NT26, 2NT34 FUNCTION:

These check valves are located in the nitrogen supply line to the safety injection accumulators (NT34) and the pressurizer relief tank (NT26). The valves are designated as inboard containment isolation valves for their respective penetrations, and perform an active safety function in the closed position to maintain containment integrity.

CATEGORY: AC CLASS: 2 TEST REQUIREMENTS:

Closed Position - Check valves shall be exercised at least once every 3 months, m accordance with the requirements ofIWV-3521.

BASIS FOR RELIEF:

• During normal operation these check valves remain in the closed positron, however periodic nitrogen makeup may be necessary. Exercising these check valves to the closed position would require securing the nitrogen supply, then venting the header while simultaneously applying a temporary pressure source downstream of the check valve to verify valve closure. This activity is not practical during power operation due to the necessity to enter containment to perform testing. This test activity is burdensome during cold shutdown due to the abnormal valve alignment and the necessity of using temporary test equipment inside containment which could delay plant restart.

ALTERNATE TESTING:

These check valves shall be exercised to the closed position at refuelings during the performance of Type C seat leakage testing. This alternate frequency and method of testing is supported by NUREG - 1482, Paragraph 4.1.4 and is pre-approved by Generic Letter 89-04. Testing shall be performed in accordance with the provisions of paragraph 4.3.2.2.(e) of OM-10. Implementation of OM-10 paragraph 4.3.2 is discussed in Technical Position TP-8 .

• I 0/1/97 Revision 8

Salem Units 1 and 2 Inservice Test Progam

• C01\1PONENTS:

FUNCTION:

VALVE REFUELING OUTAGE JUSTIFICATION -V- 16 1PR25, 2PR25 This check valve provides a relief path to the PRT for various safety related relief valves.

The valve performs an active safety function in the open and closed positions. The valve must be capable of opening to allow passage of relief valve discharge. The valve is designated as an inboard containment isolation valve and performs an active safety function in the closed position to maintain containment integrity.

CATEGORY: AC CLASS: 2 TEST REQUIREJ\.1ENTS:

Closed Position - Check valves shall be exercised at least once every 3 months, m accordance with the requirements ofIWV-3521.

BASIS FOR RELIEF:

During normal operation this check valve remains in the closed position and is open only in the event of relief valve discharge flow. The normal operating pressure of the PRT is 3 psig, which is insufficient pressure to satisfactorily reverse exercise the check valve.

Meaningful reverse exercising this check valve would require securing the relief path downstream of the check valve with a blank flange, then venting the header upstream

• while simultaneously applying a temporary pressure source downstream of the check valve to verify valve closure. This activity is not possible during power operation due to the necessity of rendering various safety related relief valves inoperable and the need to enter containment to perform testing. This test activity is burdensome and time consuming during cold shutdown due to the use of temporary test equipment inside containment which could delay plant restart.

• ALTERNATE TESTING:

These check valves shall be exercised to the closed pos1t1on at refuelings during the performance of Type C seat leakage testing. This alternate frequency and method of testing is supported by NUREG- 1482, Paragraph 4. 1.4. It should be noted that alternate testing to partial flow and disassemble & inspect for the open position and local leak rate testing for the closed position was previously identified in NRC Safety Evaluation dated October 9, 1992 (TAC Nos. M74790 and M74791) and is pre-approved by Generic Letter 89-04. Partial flow testing and disassembly & inspection has been discontinued since open testing is performed quarterly. Reverse flow testing shall be performed in accordance with the provisions of paragraph 4.3.2.2.(e) of OM-10. Implementation of OM-10 paragraph

• 10/l/97 4.3.2 is discussed in Technical Position TP-8 .

Revision 8

- '-"' 1 Salem Units 1 and 2 Inservice Test Progam VALVE RELIEF REQUEST - V - 17 NOT USED.

e

• 10/1/97 Revision 8

Salem Units 1 and 2 Inservice Test Progam

• CONIPONENTS: 1SJ3 2SJ3 VALVE RELIEF REQUEST- V- 18 FUNCTION:

This check valve is located in the charging/safety injection pumps suction supply from the respective RWST. The valve performs an active safety function in the open and closed positions. The valve must be capable of opening to provide a flow path from the RWST to the Charging/Safety Injection pumps suction for high head safety injection. The valve must be capable of closure during the switchover to the recirculation phase to prevent backflow from the RHR heat exchanger discharge to the RWST. This function would be necessary in the event the upstream parallel MOVs failed to close during the switchover, thereby satisfying single failure criteria. Additionally, valve closure prevents the potential release of radioactivity to the atmosphere via the RWST vent when inventory in the tank is depleted and ECCS subsystems are operating in the recirculation phase of emergency core cooling.

CATEGORY: C CLASS: 2 TEST REQUIREMENTS:

Open Position - Check valves shall be exercised at least once every 3 months, m accordance with the requirements ofIWV-3521.

BASIS FOR RELIEF:

At power, the centrifugal charging/safety injection pumps are in operation to provide normal charging with the VCT as the suction supply source. There is no recirculation flow path back to the RWST available during plant operation. Exercising this valve to the full open position during normal operation would require establishing flow through the safety injection flow path with the suction supply from the RWST. This is not possible during normal operation. Not only would normal charging flow be interrupted, but the injection of 2300 ppm boron solution into the RCS would result in negative reactivity rendering the reactor subcrictical. Partial exercising, at power would result in the same consequences as ful