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             *Tables.
             *Tables.
Surry Unit 2 is committed to meeting the leak rate testing requirements of:
Surry Unit 2 is committed to meeting the leak rate testing requirements of:
: 1)  lOCFRSO, Appendix J for containmerit isolation valves and
: 1)  10CFRSO, Appendix J for containmerit isolation valves and
: 2)  Section XI for other valves for which seat leakage is limited to a specific maximum amount (i.e.
: 2)  Section XI for other valves for which seat leakage is limited to a specific maximum amount (i.e.
pressure isolation valves) unless relief is specifically requested from Section XI requirements.
pressure isolation valves) unless relief is specifically requested from Section XI requirements.
Line 1,709: Line 1,709:
This valve will be exercise to the open_and closed positions every cold shutdown .
This valve will be exercise to the open_and closed positions every cold shutdown .
* S2PV-6R3 4-84 Rev. 3 March 19, 1992
* S2PV-6R3 4-84 Rev. 3 March 19, 1992
* 4.7  ALTERNATIVE TESTING FOR NON-CODE VALVES According to the minutes of public meeting on Gen~-c Letter 89-04, "Paragraph (g) of lOCFR 50.55a requires the use of Section XI of the-ASME Code for inservice testing of components covered by the Code. For other components important to safety, the licensee also has the burden of demonstrating their continued operability." The minutes go on to state that, "The Code-required IST program is a reasonable vehicle to provide a periodic demonstration of the operability of pumps and valves not covere4 by the Code. If non-Code components are included in the ASME Code IST program (or some other licensee-developed inservice testing program) and certain Code provisions cannot be met, the Commission regulations (10 CFR 50.55a) do not require a
* 4.7  ALTERNATIVE TESTING FOR NON-CODE VALVES According to the minutes of public meeting on Gen~-c Letter 89-04, "Paragraph (g) of 10CFR 50.55a requires the use of Section XI of the-ASME Code for inservice testing of components covered by the Code. For other components important to safety, the licensee also has the burden of demonstrating their continued operability." The minutes go on to state that, "The Code-required IST program is a reasonable vehicle to provide a periodic demonstration of the operability of pumps and valves not covere4 by the Code. If non-Code components are included in the ASME Code IST program (or some other licensee-developed inservice testing program) and certain Code provisions cannot be met, the Commission regulations (10 CFR 50.55a) do not require a
             'request for relief' to be submitted to the staff.
             'request for relief' to be submitted to the staff.
Nevertheless, documentation that provides assurance. of the continued operability of the non-Code components through the performed tests should be available at the plant site." Non-Code components are components that are important to safety but are not in systems or portions of systems that are classified ASME Class 1, 2 or 3.
Nevertheless, documentation that provides assurance. of the continued operability of the non-Code components through the performed tests should be available at the plant site." Non-Code components are components that are important to safety but are not in systems or portions of systems that are classified ASME Class 1, 2 or 3.

Revision as of 14:40, 6 November 2019

Rev 3 to Surry Power Station,Unit 2 Inservice Testing Program Plan for Pumps & Valves,Second Insp Interval 821222-921222.
ML18151A371
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Site: Surry  Dominion icon.png
Issue date: 03/19/1992
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VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
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ML18151A309 List:
References
PROC-920319, NUDOCS 9208040072
Download: ML18151A371 (192)
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Text

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE TESTING PROGRAM PLAN FOR PUMPS AND VALVES SECOND INSPECTION INTERVAL MAY 1, 1983 - MAY 1, 1993 REVISION 3 ADDRESSES:

    • VIRGINIA ELECTRIC AND POWER COMPANY P. 0. BOX 26666 RICHMOND, VIRGINIA 23261 SURRY POWER STATION P. 0. BOX 315 SURRY, VIRGINIA 23883
    • S2PV-iR3 Rev. 3 March 19, 1992 9208040072 9207.24- -------- -,
l. ~DR ADOCK 050002SO

'l.lli . PDR

  • TABLE OF CONTENTS INSERVICE TESTING PROGRAM PLAN FOR PUMPS AND VALVES i.O INTRODUCTION 2.0 PROGRAM DESCRIPTION 3.0 PUMP INSERVICE TEST PROGRAM DESCRIPTION 3.1 Program Development Philosophy
3. 2 . Program Implementation 3.3 Program Administration 3.4 Pump Reference List 3.5 Pump Inservice Test Tables 3.6 Pump Test Program Relief Request 3.7 Alternative Testing for Non-Code Pumps 4.0 VALVE INSERVICE TEST PROGRAM DESCRIPTION
    • 4.1 4.2 4.3 4.4 4.5 4.6 Program Development Philosophy Program Implementation Program Administration Valve Inservice Test Table Valve Test Pr*ogram Relief Request Valve Test Program Cold Shutdown Justification 4.7 Alternative Testing for Non-Code Valves 5.0 REPORTING OF INSERVICE TEST RESULTS 5.1 Pump Inservice Program 5.2 Valve Inservice Program 6.0 QUALITY ASSURANCE PROGRAM
  • INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES

1.0 INTRODUCTION

This Pump and Valve Inservice Test Program Plan is applicable to the Surry Power Station Unit 2 which began commercial operation on May 1, 1973. This program plan is comprised of two independent subprograms - the Pump Inservice Test Program and the Valve Inservice Test Program.

The development, implementation and administration of these two programs are detailed in subsequent sections.

Surry Power Station received a Safety Evaluation Report (SER) for the IST Program in August of 1990. Certain program anomalies were identified in the SER. *Surry Power Station submitted updates to Revision 2 of the IST Program on November 28 and 30, 1990 in part to correct these anomalies. The updates are included in this program revision .

1-1 Rev. 3 March 19, 1992

  • 2.0 PROGRAM DESCRIPTION This Inservice Testing Program for ISI Class 1, 2, 3 and NC pumps and valves meets the requirements of Subsections IWP and IWV of Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1980 Addendum. Where these requirements are determined to be impractical, specific requests for relief have been written and included in the program plan attached *
  • 3.0 PUMP INSERVICE TEST PROGRAM DESCRIPTION 3.1 PROGRAM DEVELOPMENT PHILOSOPHY Highly reliable safety-grade equipment is a vital consideration in the operation of a nuclear generating station. To help assure operability, the ,surry Power Station Unit 2 Pump Inservice Test Program has been developed.

The Program is designed to detect and evaluate significant hydraulic or mechanical changes in the operating parameters of vital pumps and to initiate corrective action when necessary. The Program is based on the requirements of the ASME Boiler and Pressure Vessel Code (B&PV),Section XI, Subsection IWP. To the maximum extent practical, the Program complies with the specifications of ASME B&PV Code,Section XI, Subsection IWP, 1980 Edition with Addendum through Winter .of 1980; 10CFR50.55a(g); and NRC Staff guidelines for complying with certain provisions of 10CFR50.55a(g) "Inservice Inspection Requirements."

The Nuclear Regulatory Commission and Code Committee recognized that design differences among plants may

  • render impractical certain Code requirements. Where such impracticalities exist, they have been substantiated as exceptions as allowed by the Code .

.Alternate testing requirements have been proposed when warranted.

3.2 PROGRAM IMPLEMENTATION Surveillance testing is performed to detect equipment malfunction or degradation and to initiate corrective action. Since the safeguards pumps are normally in standby mode, periodic testing of this equipment is especially important. The Surry Power Station Unit*2 Inservice Test Program provides a schedule for testing safety-grade pumps and will be implemented as part of normal periodic surveillance testing.

R~ference data will be gathered during initial surveillance tests. In most cases, test parameters

_will be measured with normal plant instrumentation.

This approach will simplify the.test program and will promote timely completion of periodic surveillance testing. When permanently installed instrumentation is not available, portable instrumentation will be used to record the required parameters .

  • During subsequent surveillance tests, flow rate will normally be selected as the independent test parameter and will be set up* to match the reference flow rate.

Other hydraulic and mechanical performance parameters will be measured and evaluated against the appropriate reference values. The resuits of such evaluations will determine whether or not corrective action is warranted.

Each pµmp in the Pump Inservice Test Program will be tested according to a detailed test procedure. The procedure* will include, as minimum: .

1)

References:

This section will identify references applicable to Technical Specifications and other necessary material as drawings.

2) Purpos*e: This section will identify test objectives.
3) Initial Conditions: Each procedure should identify those independent actions or procedures which shall be completed and station conditions which shall exist prior to use.
4) Precautions: Precautions should be established to alert the individual performing the task to those situations in which important measures should be taken early or where extreme care should be used to protect equipment and personnel. Cautionary notes applicable to specific steps in the procedure should be included in the main body of the procedure as appropriate and should be identified as such.
5) Instructions: The main body*of a procedure should contain step by step instructions in the degree of detail necessary for performing a required test.
6) Acceptance Criteria:* The ranges within which test data will be considered acceptable will be established and included in the test procedure. In the event that data fall outside the acceptable range, operator action will be governed by approved station procedures~

Finally, it is recognized that the Pump Inservice Test Program sets forth minimum testing requirements.

Additional testing will be performed, as required, after pump maintenance or as determined necessary by

    • S2PV-1R3 personnel at Surry Power Station .

3-2 Rev. 3 March 19, 1992

  • 3.3 PROGRAM ADMINISTRATION The operations and engineering staffs at Surry Power station are responsible for administration and execution of the Pump Inservice Test Program. The Program was officially implemented on May 1, 1983 and will govern pump testing for a 120 month period. Prior to the end of the 120 month period, the Program will be r~viewed and upgraded to assure continued compliance with 10CFR50.55a(g) (4). The Program will be updated a minimum*of at least once every 40 ~onths for new*

systems, relief request, etc.

3.4 PUMP REFERENCE LIST This list gives a brief description of*each pump identified in the. Pump Inservice Test Program. The pump's ASME Code Classifications are specified in "PUMP INSERVICE TEST TABLES".

2-CH-P-lA 2-CH-P-1B 2-CH-P-1C High Head Safety Injection or Charging Pumps provide

  • high pressure flow for the Safety Injection System and during normal operation, maintain pressurizer level and seal water injection to the Reactor Coolant Pumps. See drawing 11548-CBM-SSB, Sheet 2.

2-SI-P-lA 2-SI-P-lB Low Head Safety Injection Pumps provides low pressure safety injection to the core for long term cooling and as a backup to accumulators. See drawing 11548-CBM-89A, Sheet 1.

2-CS-P-lA 2-CS-P-lB Containment Spray Pumps provide a cooled, chemically treated, borated spray to reduce containment pressure following a loss of coolant accident. See drawing 11548-CBM-84A, Sheet 2 *

  • 2-RS-P-2A 2-RS-P-2B Outside Recirculation Spray Pumps aid the Containment Spray System in reducing containment pressure rapidly following a loss of coolant accident. See drawing 11548-CBM-84B, Sheet 2.

2-RS-P-1A 2-RS-P-1B Inside Recirculation Spray Pumps aid the containment spray system in reducing containment pressure rapidly following a loss of coolant accident. See drawing 11548-CBM-84B, Sheet 1.

2-FW-P-3A 2-FW-P-3B 2-FW-P-2 Auxiliary Feedwater Pumps supply the steam generator with feedwater in the event of a complete loss of n_ormal feedwater. See drawing 11548-CBM-GBA, Sheet 3.

2-RH-P-1A

1-CC-P-lC 1-CC-P-lD Component Cooling Water Pumps are used to supply water to remove heat from the Residual Heat Removal System.

See drawing 11448~CBM-72D, Sheet 1.

1-CH-P-2C 1-CH-P-2D Boric Acid Transfer Pumps supply boric acid to suction of charging pumps via normal coolant boron concentration and emergency makeup. See drawing 11448-CBM-BSA, Sheet 1 .

  • 2-CC-P-2A 2-CC-P-2B Charging Pump Cooling Water Pumps provide water to transfer heat from the charging pump mechanical seals.

See drawing 11548-CBM-71B, Sheet 2.

2-SW-P-10A 2-SW-P-10B Charging Pump Service Water Pumps provide cooling water for Charging Pump Cooling Water Systems. See drawing 11548-CBM-71B, Sheet 1.

1-EE-P-1B 1-EE-P-lC 1-EE-P-1E Fuel Oil Pumps supply fuel oil to emergency diesel generators wall mounted tank. See drawing 11448-CBB-JSA, Sheet 2 *

  • 3.5 PUMP INSERVICE TEST TABLES This tabulation identifies the pumps to be tested, code classes, required test quantities and frequencies.

Relief from test requirements is reguested in cases where test requirements have been determined to be impractical. Where relief is requested, technical justification is provided along with alternative test methods when applicable.

For non-Code pumps, a request for relief is not necessary when provisions of the Code cannot be met.

Section 3.7 contains a discussion of the testing requirements for non-Code pumps and descriptions of alternative testing in cases where the provisions of the Code cannot be met.

To aid the reader in interpreting the Pump Inservice Test Table, brief explanations of the table headings and abbreviations are provided below.

1) Pump Number - Each pump in the plant has a unique "tag" number which identifies the system to which the pump belongs.
2) Code Class - ASME Code Class of each pump as per 10CFR50.55a and Regulatory Guide 1.26.

Note: NC is for non-Code pumps. These pumps are important to safety but are not in systems that are classified ASME Class 1, 2 or 3.

'3) System Resist - Either FIX for a test loop with a fixed system resistance or VAR for a test loop with a system resistance that can be varied.

4) The required Section XI test quantities of Inlet Pressure, Differential Pressure (Discharge Pressure is not a required test quantity but is listed for clarity), Flow Rate, Vibration, Bearing Temperature, Pump Speed and.Lubrication Level/Pressure are given as column headings. The following abbreviations are used to describe the test status:

Q - the test will be performed on a quarterly basis CSD - the test will be performed every cold shutdown. A relief request explains the need for*

deviating from Section XI test frequency

  • requirements 3-6 S2PV-1R3 Rev. 3 March 19, 1992
  • NA - the test is not applicable, see corresponding relief request RR - the test will be performed every reactor refueling. A relief request explains the need for deviating from Section XI test frequency requirements.
  • 2Y - the test will be performed every 24 months Under pump speed, NA applies to constant speed pumps which do not require the measurement of speed. Therefore, no relief is necessary.

Under Lubrication Level/Pressure, NA applies to pumps that have a lubrication system with no level or pressure indication. No relief is necessary .

Pump

!dent.

  • ASME System Class Resist Inlet Disch Press Press Diff Press
  • PUMP IN SERVICE TEST TABLE Flow Bearing Pump Rate Vibration Temperature Speed Lubrication
  • Relief Level/Pressure Request 2-CH-P-lA 2 VAR 0 0 0 0 0 NA NA 0 1 2-CH-P-*lB 2 VAR 0 0 0 0 0 NA NA 0 1 2-CH-P-lC 2 VAR 0 0 0 0 0 NA NA 0 1 2-SI-P-lA 2 FIX 0 0 0 0 0 NA NA NA 1 2-SI-P-*lB 2 FIX 0 0 0 0 0 NA NA NA 1 2-CS-P-lA 2 FIX 0 Q Q 0 0 NA NA Q 1 2-CS-P-lB 2 FIX 0 0 0 0 0 NA NA 0 1 2-RS-P-2A 2 FIX 2Y 2Y 2Y 2Y 2Y NA . NA NA 1,4 2-RS-P-2B 2 FIX 2Y 2Y 2Y 2Y 2Y NA NA NA 1,4 2-RS-P-lA 2 VAR RR RR RR RR RR NA NA NA 1,5,15 2-RS-P-lB 2 VAR RR RR RR RR RR NA NA NA 1, 5, 15 2-FW-P-JA 3 VAR 0 0 0 0 0 NA NA 0 1 2-FW-P-JB 3 VAR 0 0 0 0 0 NA NA 0 1 2-FW-P-2 3 VAR 0 0 0 0 0 NA 0 'Q 1 2-RH-P-lA 2 VAR CSD CSD CSD CSD CSD NA NA NA 1.7,15 2-RH-P-lB 2 VAR CSD CSD CSD CSD CSD NA NA NA 1.7,15 1-CC-P-lC 3 VAR 0 0 0 0 0 NA NA 0 1.16 1-CC-P-lD 3 VAR 0 0 0 0 0 NA. NA 0 1.16 3-8 S2PV-2R3 Rev. 3 May 18, 1992

Pump

  • ASME System Inlet Disch Diff
  • PUMP INSERVICE TEST TABLE Flow Bearing Pump Lubrication
  • Relief

!dent. Class Resist Press Press Press Rate Vibration Temperature Speed Level/Pressure Request 1-CH-P-2C 2 VAR Q Q Q Q Q NA NA NA 1.18 1-CH-P-2D 2 VAR Q Q Q Q Q NA NA NA 1.18 2-CC-P-2A 3 VAR Q Q Q Q Q NA NA NA 1 2-CC-P-2B 3 VAR Q Q Q Q Q NA NA NA 1 2-SW-P-lOA 3 VAR Q Q 0 0 0 NA NA NA 1 2-SW-P-lOB 3 VAR Q 0 Q Q 0 NA NA NA 1 1-EE-P-lB NC FIX NA Q NA 0 Q NA NA NA 1,PNC-1 1-EE-P-lC NC FIX NA 0 NA Q 0 NA NA NA 1,PNC-1 1-EE-P-lE NC FIX NA Q NA 0 Q NA NA NA 1,PNC-1 Note: PNC-1 is not a request for relief but a description of alternative testing for non-Code pumps. Refer to Section 3. 7.

3-9 S2PV-2R3 Rev. 3 May 1, 1992

  • 3.6 PUMP TEST PROGRAM RELIEF REQUEST Relief Requests identify code requirements which are impractical for Surry Unit 2 and provide justification for the requested exception. Where appropriate, alternate testing to be performed in lieu of the code requirements is proposed .
  • RELIEF REQUEST P-0 Relief Request Withdrawn
  • Rev. 3 March 19, 1992
  • systems:

Pump(s):

Various RELIEF REQUEST P-1 IWP Progra.m Pumps. See PUMP INSERVICE TEST TABLE.

ClassSection XI Code Requirements For Which Relief Is Requested Measure pump bearing temperatures and vibration in mils.

Basis For Request Pump vibration and bearing temperature measurements are used to detect changes in the mechanical characteristics -of a pump.

Regular testing. should detect developing problems, thus repairs can be initiated prior to a pump becoming inoperable. The ASME Section XI minimum standards require measurements of the vibration amplitude displacement in mils every three months and bearing temperatures once per year.

Our proposed program is based on vibration readings in velocity

  • units rather than-vibration amplitude in mils displacement. This technique is an industry accepted method which is more sensitive to small changes that are indicative of developing mechanical problems and hence more meaningful. Velocity measurements detect not only high amplitude vibrations that indicate a major mechanical problem, but also the equally harmful low amplitude high frequency vibrations due to misalignment in balance, or bearing wear that usually go undetected by simple displacement measurements.

In addition, these readings go far beyond the capabilities of a bearing temperature monitoring program. A bearing will be seriously degraded piior to the detection of increased heat at the bearing housing. Quarterly vibration velocity readings should achieve a much higher probability of detecting developing problems than the once per year reading of bearing temperatures.

Bearing temperature tests present problems which include the following:

1. Certain systems have no recirculation test loops and a limited source of water. An enforced thirty minute run time would deplete the source .
  • 2.

RELIEF REQUEST P-1 (Cont.)

The lubrication fluid for some pumps is taken from the~*

process water, which can change te~perature depending on ambient conditions. Data trending for these cases is not meaningful.

Therefore, the detection of possible bearing failure by a yearly temperature measurement is extremely unlikely. The small probability of detection of a bearing failure by temperature measurement does not justify the additional pump operating time required to obtain the measurements. In addition, it is impractical to measure bearing temperatures on many pumps.

Alternate Testing Proposed Pump vibration measurements will be taken in vibration velocity (in/sec). The evaluation of the readings will be per the attached table. The ranges of Test parameters given in the attached table were taken from ANSI/ASME OM (Part 6), An American National Standard In-Service Testing of Pumps .

  • RELIEF REQUEST P-1 (cont.)

RANGES OF TEST PARAMETERS (1)

  • PUMP PUMP TEST ACCEPTABLE ALERT REQUIRED.

TYPE SPEED PARAMETER RANGE RANGE ACTION RANGE Centrifugal -<600 rpm Va 52.5 Vr >2.5Vr to 6Vr >6 Vr And Vertical Line Shaft but not >10.5 mils but not >22 mils

~600 rpm Vv 52.5 Vr (2) >2.5 Vr to 6Vr >6 Vr but not >0.325 in/sec but not >0.70 in/sec Reciprocating _>2.5 Vr to 6Vr >6 Vr Note: (1) Vr is the vibration reference value in the selected units Vd is vibration displacement measured peak-to-peak, unfiltered Vv is vibration velocity measured peak, unfiltered (2) Small-values for Vr will produce small acceptable ranges for pump operation. Based on a small acceptable range, an adequately anq smoothly running pump .could be subject to corrective action. To avoid this situation, a minimum value for Vr of 0.05 in/sec has been established for velocity measurements. Pumps with a measured reference value below 0.05 in/sec shall have subsequent test results compared to an acceptable range based on 0.05 in/sec *. Use of a minimum value for Vr is allowed for a three year period which ends in August, 1993. This interim period.is discussed in the Surry Safety Evaluation Report received in August of 1990 (Serial No~.90-546).

3-14

  • RELIEF REQUEST P-2 Relief Request Withdrawn RELIEF REQUEST P-3 Relief Request Withdrawn
  • System:

Pump(s):

RELIEF REQUEST P-4 Recirculation Spray 2-RS-P-2A 2-RS-P-2B Class 2 Section XI Code Requirements For Which Relief Is Requested

1. An inservice test shall be run on each pump nominally every 3 months during normal plant operation.
2. Each pump shall be run at least five minutes under conditions as stable as the system permits prior to measuring the test quantities.
3. Measure inlet pressure and differential pressure .
  • Basis For Request
1. The outside recirculation pumps take suction from the
  • containment sump and discharge to the containment spray arrays. To test these deep draft pumps, the pump pit and the recirculation test loop must be filled with primary grade water and vented. The filling and venting process takes approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. After the test is completed, the pump pit and recirculation piping must be slowly drained to avoid floodi~g the basement.

Testing is the only source of operational based degradation for the pumps. During normal operation, the outside recirculation spray system lacks fluid inventory except for some primary grade water trapped in the bottom of the pump pit. The portions of the pump exposed to this standing water are made of stainless steel and not subject to corrosion.

Considering the complexity of testing these pumps described above, the exposure to degradation caused by frequent testing and the lack fluid inventory during normal operation, there is no compensating increase in safety achieved by testing these pumps every three months.

This position is supported by ANSI/ASME OM (Part 6), An American Standard In-Service Testing of Pumps, Paragraph 5.5, which states, "Pumps lacking required fluid inventory, (e.g.,

pumps in dry sumps) need not be tested in accordance with this Part every 3 months. These pumps shall be tested at least

  • once every 2 years except as provided in para. 5.4. The required fluid* inventory shall be provided during this test."

3-16 S2PV-4R3 Rev. 3 March 19, 1992

  • RELIEF REQUEST P-4 (Cont.)

Paragraph 5.4 discribes the testing frequency of pumps in systems which are declared inoperable or not required for service.

2. The test loop for these pumps contains a small volume of water. A four inch test recirculation line branches off the ten inch pump discharge line a short distance from the pump.

The recirculation line discharges into the pump pit which is a cylinder approximately 50 feet deep and two feet in diameter.

Because of the small volume in the test loop, the hydraulic parameters stabilize quickly. Therefore, a five minute stabilization period is not necessary to achieve repeatable test results.

In addition, if the pump is run for too long of a period, the water will heatup due to the limited water volume. This heatup can lead to excessive pressures in the test loop.*

3. Inlet pressure instrumentation is not installed. *However, the outside recirculation spray pumps obtain flow through a suction bell immersed in the pump casing. During testing, a casing level is established by filling the casing with PG
  • water to provide NPSH to the pump. Flow is recirculated through the pump, recirculation line, and back to the casing.

By establishing a casing level and maintaining it constant for the tests, any variation in pump differential pressure would be directly indicated by monitoring pump discharge pressure.

The static inlet pressure will be calculated and subtracted from t~e discharge pressure to yield a differential pressure.

Alternate Testing Proposed These pumps will be flow tested on their recirculation paths at least once every two years. Maintaining a constant pump casing water level from test to test by filling the casing with PG water will yield the same suction pressure for each- test. The static inlet pressure will be calculated and subtracted from the discharge pressure to yield a differential pressure. After a two minute stabilization period, static inlet pressure, differential pressure as determined from the calculated static inlet pressure and measured discharge pressure, flow rate and vibration measurements will be taken .

  • S2PV'-4R3 3-17 Rev. 3 March 19, 1992
  • System:

Pump(s): 2-RS-P-lA RELIEF REQUEST P-5 Recirculation Spray 2-RS-P-lB Class 2 Section XI Code Requirements For Which Relief Is Requested Measure test quantities every quarter.

Measure inlet pressure and differential pressure.

Basis For Request These pumps are located inside containment, therefore, flow testing cannot be performed during plant operation.

Flow testing of these pumps requires the installation of a temporary recirculation line and the erection of a temporary dike to contain the recirculated water. Approximately five to six days are needed to set up, perform the test, and return the system to its normal configuration. Testing on a cold shutdown fr~quency would not allow enough time to plan for and perform a five to six day flow test.

Because these pumps are designed to take suction from a *sump, measurement of inlet pressure is not practical. Also, the sump level canriot vary more than one foot during testing because of the limitations in the test dike design and the requirements for NPSH. Therefore, inlet pressure will be calculated from sump level.

Alternate Testing Proposed These pumps will be bump tested to verify operability every quarter. Each pump-is equipped with a sensor to detect pump rotation which alarms in the control room. This alarm will be observed during each pump test. A flow test which includes vibration measurement will be performed every reactor refueling.

Differential pressure will be determined from the measured-discharged pressure and the calculated inlet pressure .

  • RELIEF REQUEST P-6 Relief Request Withdrawn
  • System:

Pump(s): 2-RH-P-lA RELIEF REQUEST P-7 Residual Heat Removal 2-RH-P-lB Class 2

.Section XI Code Requirements For Which Relief Is Requested Frequency .of Pump Test.

Measure inlet pressure. l Basis For Request The low pressure RHR pumps take suction from and discharge to the reactor coolant system which operates at 2235 psig. This is well above the operating pressure for the RHR pumps. Therefore, testing.during normal operation is not possible.

The use of permanent inlet and discharge pressure* instrumentation

  • for determining differential pressure is not feasible because the inlet pressure can vary between 20 and 200 psig depending upon plant conditions. Therefore, ranges for the inlet and discharge pressure gauges must vary from test to test. The current method is to install temporary inlet and discharge gauges. Properly matching the ranges of the temporary instrumentation to existing plant con~itions has proved to be difficult.

To eliminate this difficulty, differential pressure gauges will be installed during the next refueling outage., With the installation of the differential pressure gauges, the measurement of inlet pressure will no longer be necessary to trend pump performance. The new ASME Code for pump testing, Section IST, Subsection ISTB, Inservice Testing of Pumps in Light-Water Reactor Power Plants, does not require the measurement of inlet pressure if differential pressure gauges are used *

  • RELIEF REQUEST P-7 (Cont.)

Also, the installation of the temporary gauges result in a high dose (approximately 70 to 100 mrem per gauge). Because measurement of inlet pressure presents a hardship in terms of dose and does not add meaningful information for trending pump performance, inlet pressure will not be measured after the installation of the differential pressure gauges.

Alternate Testing Proposed Pumps will be tested each cold shutdown (but not more frequently than every three months). Differential pressure will be measured directly after the installation of the differential pressure gauges during the next refueling outage (first quarter, 1993).

At this time, inlet pressure will no longer be measur~d .

  • RELIEF REQUEST P-8 Relief Request Withdrawn RELIEF REQUEST P-9 Relief Request Withdrawn RELIEF REQUEST P-10 Relief Request Withdrawn RELIEF REQUEST P-11
  • Relief Request Withdrawn RELIEF REQUEST P-12 Relief Request Withdrawn RELIEF REQUEST P-13 Relief Request Withdrawn RELIEF REQUEST P-14
  • S2PV-4R3 Relief Request Withdrawn 3-22 Rev. 3 March 19, 1992
  • system:

INTERIM RELIEF REQUEST P-15 Residual Heat Removal Inside Recirculation Spray Pump(s): 2-RH-P-lA 2-RH-P-lB 2-RS-P-lA 2-RS-P-lB Class 2 Section XI Code Requirements For Which Interim Relief Is Requested Measure Flow Rate Within an Accuracy of+ 2 Percent.

Basis For Request On May 30, 1991, personnel at Surry Power station determined that flow instrumentation used for testing pumps in the Surry Units 1 and 2 ASME Section XI Inservice Testing Programs may have flow instrument loop accuracies that are not within+ 2 % as required by the Code because certain calibration requirements may not have been met prior to using the instruments.

  • An evaluation* was performed to determine if the decreased instrument accuracies affected the operable status of the pumps.

The last measured flow rates for the affected pumps were adjusted to compensate for the uncertainty in the decreased instrument accuracies. The adjustment factor (FA) in gpm was determined as follows:

FA= FS*(CSA - 2) where FS = the full range of the instrument in gpm CSA= the revised loop accuracy in percent For test procedures that compare the measured flow to the ASME acceptance range, the adjustment factor was subtracted from the last measured flow rate. The adjusted flow rate was then compared to the acceptance criteria *

  • INTERIM RELIEF REQUEST P-15 (Cont.)

For test procedures that set flow to a reference value and then measure differential pressure, the pump curve must be used to determine the adjusted differential pressure. In these cases, FA was added to the recorded reference flow rate which results in an adjusted differential pressure as determined from the pump curve that is lower than the original test value. The adjusted differential pressure was then compared to the acceptance criteria.

The evaluation showed that the Section XI pumps have adequate operational margin after the affects of the decreased instrument accuracies were factored into the comparison of test results to the Section XI acceptance criteria.

Alternate Testing Proposed Pumps 2-RH-P-1A and Bare tested every cold shutdown. For thesa pumps, the necessary instrument calibrations will be performed by the first required (cold shutdown) test after September 30, 1991 to ensure that the flow instrument accuracies are within+ 2.0 %.

The flow transmitters for these pumps are located inside containment, which is a subatmospheric design, and are

  • inaccessible during normal operation
  • Pumps 2-RS-P-1A and Bare tested every reactor refueling per relief request P-5. For these pumps, the necessary instrument calibrations will be performed with accuracies within+ 2.0 % and the pumps retested during the next scheduled refueling outage when a temporary dike can be installed in containment to support the pump testing *
  • . RELIEF REQUEST P-16 System: Component Cooling Pump(s): 1-CC-P-lC 1-CC-P-lD Class 3 Section XI Code. Requirements For Which Relief Is Requested ASME Section XI, Subarticle IWP-3110 requires reference values to be one or more fixed set of measured values. All subsequent test results shall be compared to these reference values.

Basis For Request During testing of the component cooling.water pumps, flow is adjusted to the reference flow rate using an 18 inch butterfly valve. The butterfly valve is a crude throttling device and does not provide the fine tuning that is required to duplicate the reference flow rate from test to test. Consequently, throttling to the same reference flow rate during each test is not

  • practical .

Alternate Testing Proposed Two reference *points of flow versus differential pressure will be established from the reference test for each pump. A straight line approximation will be used to determine differential pressure reference points as a function of flow between the two test points. By keeping the difference between two test points small, the straight line is a good approximation of the pump curve within the two test points.

During the subsequent tests, test flow will be throttled as close as practic_al to the reference flow value. The test flow must fall between the two reference points used to establish the straight line approximation. The test flow and the corresponding differential pressure will be compared to either graphical and/or tabular acceptance criteria based on the straight line approximation of the reference pump curve based on the straight line approximation of the reference pump curve .

  • RELIEF REQUEST P-16 (Cont.)

For example, given the straight line equation determined from the two .reference points for flow and differential pressure:

Prdif f = a + b*Q where

  • Prdiff = the reference differential pressure based on the test value for flow (Q) recorded during subsequent tests and, a and bare constants, the acceptance criteria for the flow (Q) would be as follows:

Upper Required.Action= l.03*Prdiff Upper Alert = 1.02*Prdiff Lower Alert = 0.93*Prdiff Lower Required Action= 0.90*Prdiff The multipliers on Prdiff are taken from Table IWP-3100-2 in Section XI. The actual recorded differential pressure (Padiff) will then be compared to the acceptance criteria determined from Prdiff* Also, the tests results can be trended from test to test

  • by normalizing Padiff to Prdiff* For acceptable operation, the ratio of Padiff/Prdiff must fall between 0.93 and 1.02. A decrease in the ratio from test t6 test would indicate a steady.

degradation in .pump performance.* *

  • System:

Pump(s):

Various RELIEF REQUEST P-17 IWP Program Pumps. See PUMP INSERVICE TEST TABLE.

ClassSection XI Code Requirements For Which Relief Is Requested Pump inlet pressure shall be measured before starting a pump and during the test (Table IWP-3100-1)

Basi~ For Request If the pump being tested is in operation as a result of plant or system needs, it is unreasonable to reconfigure system lineups just to provide for the measurement of static inlet pressure.

Inlet pressure prior to pump startup is not a significant*

parameter needed for evaluating pump performance or condition.

Alternate Testing Proposed

  • When performing a test on a pump that is already in operation, inlet pressure will only be measured during pump operation .
  • system:

Pump(s): l-CH-P-2C RELIEF REQUEST P-18 Chemical and Volume Control l-CH-P-20 Class 2 Section XI Code Requirements For Which Relief Is Requested The full-scale range of each instrument shall be three times the reference value or less (IWP-4120).

Basis For Request The inlet pressure gauges for the boric acid transfer pumps have a full scale range of o to 15 psig. These instruments were sized by evaluating the static pressures present at the suction side of the pumps and applying the three times rule of IWP-4120. The static pressures range from 6 to 7 psig.

When the pumps are started, the pressure at the suction side of

  • the pumps drops to approximately 2 psig; therefore, the inlet pressure gauges do not meet the three times rule for dynamic inlet pressure.

Using a lower range pressure gauge (i.e. o to 5 psig) would meet the three times rule for dynamic inlet pressure; however, the lower range gauge could not measure static inlet pressure and the lower range gauges would be repeatedly exposed to an overrange condition (static pressures in excess of 5 psig) which would damage the instruments.

Using a lower range temporary gauge on a quarterly basis presents a hardship because the process fluid contains boric acid and is contaminated. If contaminated, the temporary instruments would probably become waste material.

However, with the current Oto 15 psig inlet pressure gauges, a differential pressure can be determined that exceeds the accuracy requirements for differential pressure. Each boric acid transfer pump inlet pressure gauge (Oto 15 psig range) and discharge pressure gauge (0 to 150 psig range) has an instrument loop accuracy of 1.59%. Computing the maximum error for differential pressure using the current instrument configuration yields an error of 2.6 psid .

  • RELIEF REQUEST P-18 (Cont.)

Computing the Code allowed error for differential pressure for an inlet pressure gauge with a 2% accuracy and a Oto 5 psig range and a discharge pressure instrument with a 2% accuracy and a Oto 150 psig range yields an error of 3.1 psid. With the current instrument configuration, the loop accuracy of each pressure instrument could be as high as 1.8%, which equates to a 2.97 psid error, and still be within the Code allowed error of 3.1 psid for differential pressure. Therefore, for purposes of trending pump degradation using differential pressure and flow, the current instrument is adequate as long as the pressure instrument loop accuracies remain at or below 1.8%.

Alternate Testing Proposed The inlet pressure gauges with a full scale range of o to 15 psig will be used to measure both static and dynamic inlet pressures.

Also, the loop accuracies for the inlet and discharge pressure gauges will be maintained at or below an accuracy of 1.8% to ensure that the differential pressure error is below that the differential pressure error allowed by the Code .

3.7 ALTERNATIVE TESTING FOR NON-CODE PUMPS According to the minutes of public meeting on Generic Letter 89-04, "Paragraph (g) of 10CFR 50.55a requires the use of Section XI of the ASME Code for inservice testing of components covered by the Code. For other components important to safety, the licensee also has the burden of demonstrating their continued operability." The minutes go on to state that, "The Code-required IST program is a reasonable vehicle to provide a periodic demonstration of the operability of pumps and valves not covered by the Code. If non-Code.

components are included in the ASME Code IST program (or some other licensee-developed inservice testing program) and certain Code provisions cannot be met, the Commission regulations (10 CFR 50.55a) do not require a

'request for relief' to be submitted to the staff.

Nevertheless, documentation that provides assurance of the continued operability of the non-Code components through the performed tests should be available at the plant site." Non-Code components are components that are important to safety but are not in systems or portions of systems that are classified ASME Class 1, 2 or 3.

  • Surry Power Station has elected to include certain non-Code components in the ASME IST program. Where the Code provisions cannot be met for non-Code components, alternative testing is performed that is adequate to ensure continued operability. The alternate testing is described in this section. There may be other deviations from Code provisions that are not described in this section. For these cases, documentation is available at the plant site.

As indicated in the minutes of public meeting on Generic Letter 89-04, a 'request for relief' need not be submitted for non-Code components. Therefore, the alternative tests described in this section are not

'requests for relief' but are provided for information.

The procedure of providing alternative testing descriptions instead of requests for relief for non-Code components begins with Revision 3. Requests for relief that were approved by the NRC in Revision 2 for non-Code components will remain in place .

  • System:

Pump(s):

NON-CODE ALTERNATIVE TESTING PNC-1 Fuel Oil 1-EE-P-1B 1-EE-P-1C 1-EE-P-1E Class NC Section XI Code Requirements Which Cannot Be Met Measure test quantities after the pump has been running for five minutes.

Measure pump bearing temperatures and vibration in mils.

Measure Inlet and differential pressure.

Basis For Alternate Testing The pump operating time is limited due to operational restraints.

While the diesels are running, these pumps start automatically

  • when the fuei oil level in the day tank reaches the low level switch, and stop when the level reaches the high level switch.

The pump run time can vary depending upon the diesel load and the resulting fuel consumption rate. If the pumps are allowed to run for five minutes prior to measuring the test quantities and the fuel consumption rate is low, not enough time is available to gather all of the required Section XI test data.

The basis for alternative testing for vibration and temperature is described in Relief Request P-1.

The diesel fuel oil transfer pumps are positive displacement pumps. One characteristic of positive displacement pumps is that the discharge pressure is independent of inlet pressure.

Therefore, to determine pump degradation, only discharge pressure need be measured and compared to the acceptance criteria. The ASME OM Code-1990, Subsection ISTB, Table ISTB 5.2-1, which is replacing Section XI, Subsection IWP, requires that only discharge pressure need be measured for positive displacement pumps .

  • NON-CODE ALTERNATIVE TESTING PNC-1 (Cont.)

Alternate Testing The measurement of Section XI quantities will begin when the pump automatically starts on a low tank level signal.

The alternative testing for vibration and temperature is described in Relief Request P-1.

Inlet pressure will not be measured. Discharge pressure, flow and vibration will be measured at least once every three months in accordance with Section XI requirements. The acceptance criteria for flow and discharge pressure will be based on the criteria given in ASME OM Code-1990, Subsection ISTB, Table ISTB 5.2-2b. The acceptance criteria for vibration is addressed in Relief Request P-1 .

    • 4.0 VALVE INSERVICE TEST PROGRAM DESCRIPTION 4.1 PROGRAM DEVELOPMENT PHILOSOPHY Surry Power station Unit 2 is* a Pressurized Water Reactor being operated in compliance with the ASME Boiler and Pressure Vessel Code. The qode requires*

periodic testing of certain safety related valves in order to verify their operability and physical integrity. The Surry Unit 2 Val.ve Inservice Test Program satisfies thes~ requirements.

The program will detect potentially adverse changes in the mechanical condition of valves within the scope of Section XI, Subsection IWV of the Code. This includes all valves "which are required to perform a specific function in shutting down a reactor to the cold shutdown condition or in mitigating the consequences of' an accident." It is important to note that the scope of ASME Section XI and the Surry Inservice Testing Program for its implementation includes many valves which are not required to operate to meet FSAR license condition of hot shutdown nor limiting conditions in the plant Technical Specifications. In these cases, the requirements of Section XI shall be met except I

  • where relief has been granted .

To generate the Surry Unit 2 Valve Program, ASME Class 1, 2 and 3 valves were analyzed to determine their required type and frequency of testing. The valves to be tested under Section XI, Subsection IWV commitments

.are listed by system and drawing in the Valve Test

  • Tables.

Surry Unit 2 is committed to meeting the leak rate testing requirements of:

1) 10CFRSO, Appendix J for containmerit isolation valves and
2) Section XI for other valves for which seat leakage is limited to a specific maximum amount (i.e.

pressure isolation valves) unless relief is specifically requested from Section XI requirements.

Valves subject to leak testing per Appendix J will be tested to the requirements of Section XI, Paragraphs IWV-3426 and 3427. Appendix J satisfies the testing requirements of Section XI, Paragraphs IWV-3421 to 3425 .

  • March 19, 1992
  • The Code recognizes that certain of its requirements may be impractical for a specific plant and contains provisions for requesting relief from impractical requirements.

The relief requests for the Valve Inservice Test Program identify testing impracticalities, provide technical basis for the request and propose alternate testing where warranted.

The stroke times of solenoid controlled, air operated valves is both extremely rapid and subject to considerable variation. Exception is taken to complying with stroke time variations defined by Paragraph IWV-3417(a).

The Surry Unit 2 Valve Inservice Test Program complies with the intent of the applicable codes, regulations and guidelines and it will make a positive contribution to the safe operation of the plant._

4.2 PROGRAM IMPLEMENTATION The Valve Inservice Test Program will be executed as part of the normal plant surveillance routine. Three types of tests will be conducted as part of the Valve

  • Test Program:*
1) Valve Operability Tests,
2) Valve Leakage Tests and
3) Safety Valve Tests "The Operability Tests will verify that:
1) the valve responds to control commands,
2) the valve stroke time is within specific limits and
3) remote position indication accurately reflects the observed valve position. Remote valve position indication will be verified every two years.

Fail safe valves will be tested by observing the valve operation upon loss of actuating power. In most cases, this can be accomplished using normal control circuits.

The follo~ing clarification shall apply to those valves which are scheduled to be exercised during cold shutdown:

"Valve testing shall coiilmence not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after reaching cold shutdown and continue until complete or unit is ready to

  • S2PV-5R3 return to power. Completion of the valve 4-2 Rev. 3 March 19, 1992
  • testing is not a prerequisite to return to power. Any testing not completed at*one cold shutdown should be performed during the subsequent scheduled cold shutdowns to meet the code specified testing frequency."

Valve Leakage Tests will verify that valves are leak tight in accordance with Appendix J or ASME Section XI.

Relief and Safety valves are not required to be leak rate tested (IWV-3512) and are not included as valves to be leak tested.

Certain valves cannot be full stroke exercised during normal operation following maintenance. These valves are described in the relief requests and cold shutdown justifications. If maintenance cannot be deferred to a shutdown condition, then an engineering evaluation must be performed prior to the maintenance to determine the effect of the maintenance on valve performance. If the evaluation shows that performance will not be affected, then no post mainten*ance testing will be required. A partial stroke test will be performed if possibler To test check vaives to the full open position, the maximum required accident condition flow must be

  • measured through the valve. In certain cases, this flow cannot be practically established or verified.

Aqcording to Generic Letter 89-04, disassembly and inspection of the check valves on a sampling basis is an acceptable alternative testing method.

_As described in Generic Letter 89-04, the sample disasse~bly 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. -The group size cannot exceed four valves.

Additionally, at each disassembly it must be verified that the disassembled valve is capable of full-stroking and that the internals of the valve are structurally sound. Also, to verify the full stroke capability of the valve, the disk should be manually exercised.

A different valve of each group is required to be disassembled, inspected, and manually full stroked exercised at each successive refueling outage, until

  • the entire group has been tested. If the disassembled valve is not capable of being full stroked exercised or 4-3 S2PV-5R3 Rev. 3 March.19, 1992
  • 4.3 there is binding or failure of valve internals, the remaining valves in that group must be disassembled, inspected, and manually full stroked exercised during the same outage.

PROGRAM ADMINISTRATION The operations and engineering staffs at Surry Power Station are responsible for administration and execution of the Valve Inservice Test Program. The program was officially implemented on May 1~ 1983 and governs vaive testing for a 120 month period. Prior the to end of the 120 month period, the program will be reviewed and upgraded to assure continued compliance with 10CFR50.55a(g) (4). The program will be updated a minimum of at least once every 40 months or for a new system, relief request, etc.

4.4 VALVE INSERVICE TEST TABLES The Valve Inservice Test Tables are the essence of the Valve Program to meet ASME Section XI, Subsection IWV requirements.* The tables reflect the positions taken in support of the relief requests~ To aid the reader in the inter*pretation of the tables, brief explanations

  • of the table headings and-abbreviations are provided .

For non-Code valves, a request for relief is not necessary when provisions of the Code cannot be met.

Section 4.7 contains a discussion of the testing requirements for non-Code valves and descriptions of alternative testing in cases where the provisions of

  • the Code cannot be met.
1) Valve Number - Each valve in the plant has a unique "tag" number which identifies the system to which the equipment belongs and type of equipment~ *
2) Drawing Location - The specific coordinates of each valve are supplied to facilitate location of the valves on the flow diagrams provided.
3) Function - A brief description of the function of the valve.
4) Code Class - ASME Code Class of each valve as per 10 CFR 50.55a and Regulatory Guide 1.26.

NOTE: NC is for non-Code valves. These valves are important to safety but are not in systems that are

4-4 S2PV-5R3 Rev. 3 March 19, 1992

    • 5) Category - Categories are defined by ASME Section XI, Subsection IWV. Each valve has specific testing requirements which are determined by the category to which it belongs. Valves marked with an "E" are passive valves.
6) Size - Nominal pipe diameter to which valve connects is given in inche~.
7) Valve Type - A brief description of the actuator and valve type.

The following abbreviations are used to describe actuator types. Valves may be actuated in more than one way.

MO - Motor Operated AO - Pneumatic (Air Operated)

MAN - Manually Operated so - Electronic s9lenoid Operated Valves

8) Isolation Valve Type - Valves that are assigned a maximum leakage. The following abbreviations are used to describe the isolation valve types:
  • CIV - Containment Isolation Valve subject to Appendix J. leakage testing.

PIV - Pressure Isolation Valve *which protects low pressure safety related piping from RCS pressure.

Technical Specification Section 3.1.C specifies the pressure isolation valves that are tested in accordance with this program.

9) Test Position - The following abbreviations are used to describe normal valve positions to which the valves are tested (including the valve safety position):

o - Open C - Closed oc - Open and Closed

10) Test Required - Testing r~quirementi identified for the valves are identified here.

ST - *stroke times shall be measured per Section XI, Subsubarticle IWV-3410 or as modified by a specific relief request. **

  • EV - Exercise valve for operability at least once every 3 months per Section XI, Subsubarticle IWV-3410* or as modified by a specific relief request or cold shutdown justification.

LT - Leak test shall be performed per Section XI~

Subsubarticle IWV-3420 or as modified by specific relief request.

CV - Check valves shall be exercised at least once every 3 months per section XI, Subsubarticle IWV-3520 or as modified by a specific relief request or cold shutdown justification.

VP - Valve position indication shall be verified per Section XI, Subsubarticle IWV-3300 or as modified by a specific relief request.

SP - Set points of safety and relief valves shall be tested per Section IX, Subsubarticle IWV-3510 or as modified by a specific relief request.

FS - Valves with fail-safe actuators shall be tested by observing the operation of the valves

  • upon loss of the actuator power at least once every 3 months per Section XI, Subsubarticle IWV-3415 or as modified by a specific relief request or cold shutdown justification .

VIRGINIA POIJER COMPANY PAGE: 1 OF 63

  • SURRY UNIT 2 REVISION: 03 SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE . ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAt POS TYPE TYPE v- csv- VNC*

2-BD-TV-200A 11548-CBM-124A 1 OF 4 C-7 AO GATE 3.00 2 B C EV 21 FS 21 ST 34 VP "A" STEAM GENERATOR BLOWDOWN, OUTSIDE CON-TAINMENT ISOLATION VALVE 2-BD-TV-200B 11548~CBM-124A 1 OF 4 C-6 AO GATE 3.00 2 B C EV 21 FS 21 ST 34 VP "A" STEAM GENERATOR BLOWDOWN, INSIDE CON-TAINMENT ISOLATION VALVE 2-BD-TV-200C 11548-CBM-124A 2 OF 4 C-7 AO GATE 3.00 2 B C EV 21 FS 21 ST 34 VP "B" STEAM GENERATOR BLOWDOIJN, OUTSIDE CON-TAINMENT ISOLATION VALVE 2-BD-TV-200D 11548-CBM-124A 2 OF 4 C-6 AO GATE 3.00 2 B C EV 21

  • FS 21 ST 34 VP 11 811 STEAM GENERATOR SLOWDOWN, INSIDE CON-TAINMENT ISOLATION VALVE 2-BD-TV-200E 11548-CBM-124A 3 OF 4 C-7 AO GATE 3.00 2 B C EV 21 FS 21 ST 34 VP 11 C11 STEAM GENERATOR BLOWDOIJN, OUTSIDE CON-TAINMENT ISOLATION VALVE 2-BD-TV-200F 11548*CBM-124A 3 OF 4

TAINMENT ISOLATION VALVE

  • SURRY UNIT 2 REVISION: 03 SECOND INSPECTION INTERVAL DATE: 3/19/92
  • 1NSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRA\JING SHEET DR\JG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT PCS TYPE TYPE v- . csv- VNC-

--- ----

1-CC-569 11448-CBM-OnD 1 OF 5 B-5 CHECK VALVE 18.00 3 C oc CV

11 011 COMPONENT COOLING PUMP DISCHARGE CHECK VALVE 1*CC-578 11448-CBM-072D .* 1 OF 5 B-5 CHECK VALVE 18.00 3 C oc CV

---*

11

C" COMPONENT COOLING PUMP DISCHARGE CHECK VALVE 2-cc-001 11548-CBM-072A 2 OF 7 F-7 CHECK VALVE 6.00' 3 C C CV 6 CC SUPPLY TO "A" RC PUMP LO, STATOR SHROUD &

THERM BARRIER COOLERS, ISOL CHECK VLV 2-CC-058 11548-CBM-072A 3 OF 7 F-7 CHECK VALVE 6.00 3 C C CV 6 CC SUPPLY TO 11 811 RC PUMP LO, STATOR SHROUD &

.

THERM BARRIER.

COOLERS, ISOL CHECK VLV

2-CC-059 11548-CBM-072A 4 OF 7 F-7 CHECK VALVE C C CV 6 CC SUPPLY TO 11 C11 RC PUMP LO, STATOR SHROUD &

THERM BARRIER COOLERS, !SOL CHECK VLV

  • 2-CC-094 11548-CBM-072A* 2 OF 7 C-6 CHECK VALVE 2.0 . 3 C C CV 45 COMPONENT COOLING \JATER TO RCP THERMAL BARRIER ISOLATION CHECK VALVE 2-CC-095 11548-CBM-072A 3 OF 7 C-6 CHECK VALVE 2.0 3 C C CV 45 COMPONENT COOLING \JATER TO RCP THERMAL BARRIER ISOLATION CHECK VALVE

*----------------~--------

2-CC-176 11548-CBM-072A 1 OF 7 F-7 CHECK VALVE 18.00 3 C oc CV 5 CC SUPPLY TO RHR HEAT EXCHANGER CHECK VALVE 2-CC-177 11548-CBM-072A 1 OF 7 F-7 CHECK VALVE 18.00 3 C oc CV 5 CC SUPPLY TO RHR HEAT EXCHANGER CHECK VALVE

*--

2-CC-181 11548-CBM-072A 1 OF 7. E-2 MANUAL BFLY 18.00 3 B oc EV 26 CC RETURN FROM RHR HEAT EXCHANGER MANUAL ISOLATION VALVE 2-CC-185 11548-CBM-072A 1 OF 7 C-2 MANUAL BFLY 18.00 3 B oc EV 26 CC RETURN FROM RHR HEAT EXCHANGER MANUAL ISOLATION VALVE

    • -------*-------------------------------*---------------. -------------------------------------------------*--------------

.2-CC-224 '11548-CBM-0728 1 OF 3 D-2 CHECK VALVE 6.00 3 C C CV 5 CC SUPPLY TO 11 C11 RECIRC AIR COOLING COILS, OUTSIDE CONTAINMENT ISOLATION CHECK VALVE

  • VIRGINIA POWER COMPANY PAGE: 3 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL COLD ALT VALVE. DRAIJING SHEET DRIJG VALVE VALVE ASHE TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT PCS TYPE TYPE v- csv- VNC-2-CC-233 11548-CBM-0728 1 OF 3 D-6 CHECK VALVE 6.00 3 C C CV 5

*-----------------------

CC SUPPLY TO 8 RECIRC AIR COOLING COILS, 11 11 ClJTSIDE CONTAINMENT ISOLATION CHECK VALVE

* ----------------------------------------------- .----------------------------------------------------------

2-CC-242 11548-CBM-0728 1 OF 3 D-8 CHECK VALVE 6.00 3 C C CV 5 CC SUPPLY TO "A"RECIRC AIR COOLING COILS, ClJTSIDE CONTAINMENT ISOLATION CHECK VALVE 2-CC-329 11548-CBM-0718 2 OF 2 D-3 CHECK VALVE 2.00 3 C oc CV CHARGING PUMP COOLING IJATER PUMP DISCHARGE CHECK VALVE 2-CC-555 11548-CBM-072A 2 OF 7 C-6 CHECK.VALVE 2.0 3 C C CV 45 COMPONENT COOLING IJATER TO RCP THERMAL BARRIER ISOLATION CHECK VALVE 2-CC-556 11548-CBM-072A 3 OF 7 C-6 CHECK VALVE 2.0 3 C C CV 45 COMPONENT COOLING IJATER TO RCP THERMAL BARRIER ISOLATION CHECK VALVE

-------------------------------* --------

2-CC-557 11548-CBM-072A 4 OF 7 C-6 CHECK VALVE 2.0 3 C C CV 45

----*-----------------------------

COMPONENT COOLING IJATER TO RCP THERMAL BARRIER ISOLATION CHECK VALVE 2.0 3 C C CV 45 2-CC-764 11548-CBM-0718 2 OF 2 C-7 CHECK VALVE 2.00 3 C oc CV CHARGING PUMP COOLING IJATER PUMP DISCHARGE CHECK VALVE -

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

2-CC-806 11448-CBMo072E 1 OF 2 C-5 CHECK VALVE 1.00 3 C 0 CV 30 CHARGING PUMP SEAL COOLING SURGE TANK MAKEUP CHECK VALVE 2-CC*LCV-201 11548-CBM-0718 2 OF 2 D-5 AO GATE 1.00 3 B oc EV 31 FS 31 ST 47 CHARGING PUMP SEAL COOLING SURGE TANK LEVEL CONTROL/ISOLATION VALVE 2*CC*RV-212A 11548-CBM-0728 1 OF 3 C-7 RELIEF VALVE 0.75 3 C 0 SP REACTOR CONTAINMENT AIR RECIRCULATION COOLER RELIEF VALVE

-

.

(

VIRGINIA POIJER COMPANY PAGE: 4 OF 63 SURRY UNIT 2 REVISION: 03

  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE.

NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE V- CSV- VNC-2-CC*RV-2128 11548-CBM-Ons 1 OF 3 c-s RELIEF VALVE o_.75 3 C 0 SP

REACTOR CONTAINMENT AIR RECIRCULATION COOLER RELIEF VALVE 2-CC*RV-212C 11548-CBM-OnB 1 OF 3 C-3 RELIEF VALVE 0.75 3 C 0 SP REACTOR CONTAINMENT AIR RECIRCULATION COOLER RELIEF VALVE 2-CC*RV-219A 11548-CBM-OnA 1 OF 7 E-3 RELIEF VALVE 1.50 3 C 0 SP 11A11 RHR HEAT EXCHANGER COMPONENT COOLING RELIEF VALVE 2-CC*RV-219B 11548-CBM-OnA 1 OF 7 0-3 RELIEF VALVE 1.50 3 C 0 SP 11 811 RHR HEAT EXCHANGER COMPONENT COOLING RELIEF VALVE 2-CC*RV-224 11548-CBM-OnA 5 OF 7 F-6 RELIEF VALVE 0.75 3 C 0 SP COMPONENT COOLING PIPING RELIEF

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

2-CC-RV-238A 11548-CBM-OnA 2 OF 7 F-6 RELIEF VALVE 0.75 3 C 0 SP

  • 2-CC*RV-238B REACTOR SHROULD COOLING COIL RELIEF VALVE 11548-CBM*OnA 3 OF 7 REACTOR SHROULD COOLING COIL RELIEF VALVE F-6 RELIEF VALVE 0.75 3 C 0 SP 2-CC-RV-238C 11548*CBM-072A 4 OF 7 F-6 RELIEF VALVE 0.75 3 C 0 SP REACTOR SHROULD COOLING COIL RELIEF_ VALVE.

. .

2-CC*RV-250 11548-CBM-OnA 1 OF 7 E-7 RELIEF.VALVE 3 C 0 SP CC RETURN HEADER RELIEF VALVE 2*CC*TV-205A 11548-CBM*OnA 2 OF 7 B-4 AO BALL 6.00 3 B C EV 6 FS 6 ST VP CC RETURN FROM "A" RC PUMP LO,STATOR & SHROUD COOLERS, OUTSIDE CONTAINMENT ISOLATION VAL-VE 2*CC*TV-205B 11548-CBM-OnA 3 OF 7 B-4 AO BALL 6.00 3 B C EV 6 FS 6 ST VP CC RETURN FROM 11 811 RC PUMP LO,STATOR & SHROUD COOLERS, OUTSIDE CONTAINMENT ISOLATION VALVE

  • -- - -- -------- ---- -

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

VIRGINIA POWER COMPANY PAGE: 5 *OF 63 SURRY UNIT 2 REVISION: 03

  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASHE TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC*

2*CC*TV*205C 11548*CBM*072A 4 OF 7 B-4 AO BALL 6.00 3 B C EV 6 FS 6 ST VP CC RETURN FROM "C" RC PUMP LO,STATOR & SHROUD COOLERS, OUTSIDE CONTAINMENT ISOLATION VALVE

.

Z*CC*TV-207

--------------------------------------------------------------------------------------

11548*CBM*072A 1 OF 7 D-7 AO.GLOBE 2.50 3 B C EV 27 FS 27 ST 34 VP

*-----------

CC RETURN FROM REACTOR COOLANT PUMP THERMAL BARRIERS, OUTSIDE CONTAINMENT ISOLATION VALVE

* --------------------------------* ------

2*CC*TV*209A 11548*CBM*072A 1 OF 7 B-7 AO BFLY 18.00 3 B oc EV FS ST VP CC RETURN FROM 11 A" RHR HEAT EXCHANGER, OUT*

SIDE CONTAINMENT ISOLATION VALVE

.---------------------------*

2*CC*TV*209B

11548-CBM*O?ZA 1 OF 7 C-7 AO BFLY 18.00 3 B OC EV FS *

  • ST VP CC RETURN FROM "B" RHR HEAT EXCHANGER, OUT*

SIDE CONTAINMENT ISOLATION VALVE 2*CC*TV*210A 11548*CBM*072B 1 OF 3 E-7 AO BFLY 6.00 3 B C EV FS ST VP CC RETURN FROM "A" RECIRC AIR COOLING COILS, OUTSIDE CONTAINMENT ISOLATION VALVE 2*CC*TV*210B 11548*CBM*072B 1 OF 3 E*S AO BFLY 6.00 3 B C EV FS ST VP CC RETURN FROM "B" RECIRC AIR COOLING COILS,.

.

OUTSIDE CONTAINMENT ISOLATION VALVE . .

2*CC*TV*210C 11548*CBM*072B 1 OF 3 E-4 AO BFLY

6.00 3 B C EV FS ST VP

* ---------------------------------------

CC RETURN FROM "C" RECIRC AIR COOLING COILS, OUTSIDE CONTAINMENT iSOLATION VALVE

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

  • SURRY UNIT 2 REVISION: 03 SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE V- CSV- VNC-2-CC-TV-220A 11548-CBM-072A 2 OF 7 C-5 AO GATE 1.50 3 B C EV 27 ST VP CC RETURN FROM REACTOR COOLANT PUMP THERMAL BARRIER ISOLATION VALVE 2-CC-TV-220B 11548-CBM-072A 3 OF 7 C-5 AO GATE 1.50 3 B C EV 27 ST VP CC RETURN FROM REACTOR COOLANT PUMP THERMAL BARRIER ISOLATION VALVE 2-CC-TV-220C 11548-CBM-072A 4 OF 7 C-5 AO GATE 1.50 3 B C EV 27 ST VP CC RETURN FROM REACTOR COOLANT PUMP THERMAL BARRIER ISOLATION VALVE
  • VIRGINIA POWER COMPANY PAGE: 7 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL . DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE
  • ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE

__ ;. _ v- csv- VNC-1-CH-109 11448-CBM-OBBA 1 OF 4 C-5 CHECK VALVE

2.00 2 C 0 CV l 11 C BORIC ACID TRANSFER PUMP DISCHARGE CHECK 11 VALVE 1-CH-116 11448*CBM-088A 1 OF 4 C-4 CHECK VALVE -~-DO 2

*------------------------------------------

2-CH-228 11548-CBM-0888 1 OF 2 B-4 MANUAL GATE

  • -----------------------------------------------------------

1.0 2 B 0 EV 19 MANUAL EMERGENCY BORATION PATH MANUAL VALVE 2-CH-229 11548-CBM-0888 1 OF 2 B-4 CHECK VALVE CV 19

  • 1.0 2 C 0 MANUAL EMERGENCY BORATION PATH CHECK VALVE 2-CH-230 11548-CBM-0888 1 OF 3 C-6 CHECK VALVE 4.00 2 C 0 CV CHARGING PUMP *suPPLY FROM VOLUME CONTROL TANK DISCHARGE CHECK VALVE

*-------------------------------------*------------------

2-CH-256 11548-CBM-0888 2 OF 2 D-7 CHECK VALVE 2.00 2 C 0 CV 11 A11 CHARGING PUMP DISCHARGE RECIRC LINE CHECK VALVE 2-CH-258 11548-CBM-0888 2 OF 2 D-7 CHECK VALVE 3.00 2 C oc CV 14 11 A CHARGING PUMP DISCHARGE CHECK VALVE 11 2*CH-265 11548-CBM-0888 2 OF 2 D-6 CHECK VALVE 2.00 2 C 0 CV 8 CHARGING PUMP DISCHARGE RECIRC LINE CHECK 11 11 VALVE

~------- *-------------------------------*

2-CH-267

11548-CBM-0888 2 OF 2 0*6 CHECK VALVE 3.00. 2

oc CV C 14 11 811 CHAR.GING PUMP DISCHARGE CHECK VALVE

*-----------------------~---------

2-CH-274 11548-CBM-0888 2 OF 2 D-4 CHECK VALVE

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

2.00 2 C 0. CV I "C" CHARGING PUMP DISCHARGE RECIRC LINE CHECK VALVE

  • VIRGINIA PO'.IER COMPANY PAGE: 8 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL COLD ALT VALVE DRA\IING SHEET DR\IG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE V- CSV- VNC-2-CH-276 11548-CBM-0888 2 OF 2 D-4 CHECIC VALVE 3.00 2 C OC CV 14

11 C CHARGING PUMP DISCHARGE CHECIC VALVE 11 2-CH-309 11548-CBM*OSSC

  • 1 OF 2 D-4 CHECIC VALVE 3.00 2 AC C CIV CV 20 LT MAIN CHARGING SUPPLY HEADER, INSIDE CONTAIN*

MENT ISOLATION CHECIC VALVE 2-CH*FCV-2113A 11548-CBM-OSSB 1 OF 2 C-3 AO GLOBE ,.o 2 B 0 EV FS ST VP MANUAL EMERGENCY BORATION PATH FLOIJ CONTROL VALVE

*----------------------------------------------------------

2-CH-FCV*2113B 11548-CBM-OSSB 1 OF 3 b-5 AO GATE 2.00 2 B C EV FS ST VP MAKEUP TO CHARGING PUMP SUCTION LINE ISOLATION VALVE

  • 2*CH*FCV*2114A 11548-CBM*OSSB 1 OF 2 D-4 AO GLOBE

~-----

PRIMARY GRADE \IATER SUPPLY TO BORIC ACID BLENDER ISOLATION VALVE 2.0 2 B C EV FS ST VP 2-CH*FCV-2114B 11548-CBM-OSSB 1 OF 3 0-5 AO GATE 2.00 2 B C EV FS ST VP PRIMARY GRADE \IATER TO VCT LINE ISOLATION VALVE 2-CH*FCV-2160 11548-CBM*OSSC 1 OF 2 B-4 AO GLOBE 2.00 AE C CIV LT VP CHARGING FLO\I CONTROL TO LOOP FILL HEADER, OUTSIDE CONTAINMENT ISOLATION VALVE 2*CH*LCV*2115B 11548-CBM-OSSB 2 OF 2 B*8 MO GATE 8.00 2 B oc EV ST VP CHARGING PUMP SUPPLY ISOLATION VALVE FROM REFUELING \IATER STORAGE TANK

.------------- *------------------------------.------------------------------------------------

  • SURRY UNIT 2 REVISION: 03 SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHE.ET . DRWG VALVE VALVE ASHE TEST VALVE TEST REC SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS
  • TYPE TYPE V* CSV* VNC*

2*CH*LCV-2115C 11548*CBM*088B 1 OF 2 C-6 MO GATE 4.00 2 B C EV 11 ST VP CHARGING PUMP SUPPLY ISOLATION FROM VOLUME CONTROL TANK

' '

  • ----------------

2*CH*LCV-2115D 11548*CBM-088B 2 OF. 2 C-8 MO GATE 8.00 - 2 B oc EV ST VP

*-------------

CHARGING PUMP SUPPLY ISOLATION VALVE FROM REFUELING WATER STORAGE TANK 2*CH*LCV*2115E 11548*CBM*088B 1 OF 2 C-6 MO GATE 4.00 2 B C EV 11 ST VP

*--------

CHARGING PUMP SUPPLY ISOLATION VALVE, FROM VOLUME CONTROL TANK

.------------- .----------------------------------------------------*----------------------------------------

2-CH*LCV-2460A 11548*CBM-088C OF 2 F-7 AO GLOBE 2.00 B C EV 15 FS 15 ST VP

------- --------------- -----------------

NORMAL LETDOWN TO REGENERAHVE HEAT EXCHANGER ISOLATION VALVE

-- .-----------------------------------------------------------------------------------------------*----------

2*CH*LCV*2460B , 11548*CBH*088C 1 OF 2 F-7 AO GLOBE 2.00 B C EV 15 FS 15 ST VP NOR~L LETDOWN TO REGENERATIVE HEAT EXCHANGE.R ISOLATION VALVE 2*CH*HOV-2267A 11548*CBH*088B 2 OF 3 C-7 HO GATE 6.00 2 B oc EV ST VP

.

'

CHARGING PUMP SUCTION ISOLATION VALVE FROM RWST, VCT AND LHSI PUMP 2*CH*MOV*2267B 1154S*CBM-088B 2 OF 3 B-7 MO GATE 6.00 2 E 0 VP LO'J HEAD SI PUMP TO CHARGING PUMP SUCTION ISOLATION VALVE 2*CH*MOV*2269A 11548*CBH-088B 2 OF 3 C-5 MO GATE 6.00 2 B oc EV ST VP CHARGING PUMP SUCTION ISOLATION VALVE FROM RWST, VCT AND LHSI PUMP

*---------------

  • VIRGINIA PO\IER COMPANY PAGE: 10 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME TEST VALVE TEST REQ, SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE V* CSV* VNC*

2*CH*MOV-2269B 11548-CBM*088B 2 OF 3 B*S MO GATE 6.00 2 E 0 VP

LOW HEAD SI PUMP TO CHARGING PUMP SUCTION ISOLATION VALVE 2*CH*MOV-2270A 11548-CBM-088B 2 OF 3 C-3 MO GATE 6.00 2 B oc EV ST VP CHARGING PUMP SUCTION ISOLATION VALVE FROM RWST, VCT AND LHSI PUMP

2*CH*MOV*2270B 11548*CBM*088B 2 OF 3 B-3 MO GATE 6.00 2 E

  • --------------------------------------

0 VP LOW HEAD SI PUMP TO CHARGING PUMP SUCTION ISOLATION VALVE

*-----------------------------------------

. 2*CH*MOV*2275A 11548*CBM*088B 2 OF 2 D-7 MO GATE 2.00 2 B oc EV ST VP "A" CHARGING PUMP MINIMUM RECIRCULATION ISO*

LATION VALVE 2-CH*MOV-2275B 11548*CBM-088B 2 OF 2 D-5 MO GATE 2.00 2 B oc EV ST

  • VP "B" CHARGING PUMP MINIMUM RECIRCULATION ISO*

LATION VALVE 2*CH*MOV*2275C 11548*CBM*088B 2 OF 2 D-3 MO GATE 2.00 2 B oc EV ST VP 11 c *cHARGING PUMP 11 MINIMUM RECIRCULATION ISO*

LATION VALVE 2*CH*MOV*2286A 11548*CBM*088B 2 OF 2 E-7 MO GATE 3.0 2 B oc EV ST VP CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 2*CH*MOV*2286B 11548*CBM-088B 2 OF 2 E-6 MO GATE 3.0 2 B oc EV ST VP CHARGING PUMP MAIN D.ISCHARGE ISOLATION VALVE

. .

2*CH*MOV*2286C 11548-CBM-0888 2 OF 2 E-4 MO GATE 3.0 2 B oc EV ST VP CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE

*----------------------------------------------------------------------------------------------

  • VIRGINIA PO'JER COMPANY PAGE: 11 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASHE TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE. CLASS CAT POS TYPE TYPE v- csv- VNC-2*CH*MOV-2287A 11548-CBM*OSSB 2 OF 2 D-7 MO GATE 3.0 2 B oc EV ST VP CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE

*----

2-CH-MOV-2287B 11548-CBM-088B 2 OF 2 D-6 MO GATE 3.0 oc EV 2 B ST VP CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE

**----------------------------*---------------------------------------------------

2-CH-MOV-2287C 11548*CBM-088B 2 OF 2 0-4 MO GATE 3.0 oc EV 2 B ST VP CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 2-CH-MOV-2289A 11548-CBM*OSSC 1 OF 2 B-4 MO GATE 3.00 2 A C CIV EV 16 LT ST VP

  • MAIN CHARGING HEADER ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE .

2*CH-MOV-2289B 11548-CBM*OSSC 1 OF 2 B-3 MO GATE 3.00 2 B C EV 16 ST VP MAIN CHARGING HEADER ISOLATION VALVE, OUTSIDE CONTAINMENT 2-CH-MOV-2350 11548-CBM-088B 1 OF 2 B-5 MO GATE. 2.00 2 B 0 EV 19 ST VP EMERGENCY BORATION TO CHARGING PUMP SUCTION 2-CH-MOV-2373 11548-CBM*OSSB 2 OF 2. E-7. MO GATE 3.00 2 B 0 VP CHARGING PUMP RECIRCULATION HEADER ISOLATION VALVE 2-CH*MOV-2381 11548-CBM*OSSB 1 OF 2 C-8 MO GATE. 3.00 2 A. C CIV EV 13 LT ST VP REACTOR COOLANT PUMP SEAL WATER RETURN, OUT*

SIDE CONTAINMENT ISOLATION VALVE

  • VIRGINIA POWER COMPANY PAGE: 12 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL _COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE V- CSV- VNC-2-CH-RV-2203 11548-CBM-OSSC 1. OF 2 F-4 RELIEF VALVE 2.00 2 C 0 SP

LETDOWN RELIEF VlV DOWNSTREAM OF REGEN HX, RV DISCHARGE TO PRESSURIZER RELIEF TANK 2-CH**RV-2382A 11548-CBM-OSSC 2 OF 2 F-5 RELIEF VALVE 2.00 2 C 0 SP REACTOR COOLANT PUMP SEAL WATER RELIEF VALVE, RV DISCHARGE TO PRESSURIZER RELIEF TANK 2-CH-RV-2382B 11548-CBM-OSSB 1 OF 2 C-7 RELIEF VALVE 2.00 2 C 0 SP SEAL WATER HEAT EXCHANGER RELIEF VALVE, RV DISCHARGE TO VOLUME CONTROL TANK 2-CH-TV-2204A 11548-CBM-OSSC 1 OF 2 D-3 AO GATE 2.0 2* B C CIV

  • EV 15 FS 15 LT ST VP

. LETDOWN CONTROL FROM REGEN HX, INSIDE CONTAINMENT ISOLATION VALVE 2-CH-TV-2204B 11548°CBM-088A 4 OF 4 D-3 AO GATE 2.0. 2 B C CIV EV 15 FS 15

  • LT ST 34 VP LETDOWN CONTROL FROM REGEN HX, OUTSIDE CONTAINMENT ISOLATION VALVE

* ---------------------------------------

  • VIRGINIA PO~ER COMPANY PAGE: 13 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLO ALT VALVE ORA~ING SHEET OR~G VALVE VALVE
  • ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE V- CSV- VNC-2-CS-013 11548*CBH-084A 2 OF 3 F*4 CHECK VALVE 8.00 2 AC OC CIV CV 43 LT 11 A11 CONT SPRAY PUMP INSIDE CONTAINMENT ISOLATION DISCHARGE CHECK VALVE 2-CS-024 11548*CBH*084A 2 OF 3 E*4 CHECK VALVE 8.00 2 AC OC CIV CV 43 LT "B" CONT SPRAY PUMP INSIDE CONTAINMENT ISOLATION DISCHARGE CHECK VALVE 2-CS-104 11548*CBH*084A 2 OF 3 F-3 CHECK VALVE 8.00 2 C oc CV 43 CONTAINMENT SPRAY PUMP DISCHARGE CHECK VALVE

J 2-CS-105 11548-CBM-084A 2 OF 3 E-3 CHECK VALVE 8.00. 2 C OC CV 43 CONTAINMENT SPRAY PUMP DISCHARGE CHECK VALVE 2-CS-MOV-200A 11548*CBM*084A 2 OF 3 B*7 MO GATE 12.00 2 B 0 EV ST VP

  • CONTAINMENT SPRAY PUMP SUCTION ISOLATION VALVE 2-CS-MOV-200B 11548*CBM*084A 2 OF 3 A*7 MO GATE 12.00 2 B 0 EV ST VP CONTAINMENT SPRAY PUMP SUCTION ISOLATION VALVE 2-CS-MOV-201A 11548*CBM*084A 2 OF 3 F*S HO GATE 8.00 2 A oc CIV EV LT 39 ST VP "A" CONT SPRAY PUMP DISCHARGE ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2*CS-MOV*201B 11548*CBM*084A 2 OF 3 F*S MO GATE 8.00 2 A oc CIV EV LT 39 ST VP "A" CONT SPRAY PUMP DISCHARGE ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2*CS*MOV*201C 11548*CBM*084A 2 OF 3 E*S HO GATE 8.00 2 A oc CIV EV LT 39 ST VP "B" CONT SPRAY PUMP DISCHARGE ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE
  • VIRGINIA PO\lER COMPANY PAGE: 14 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASHE TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC-

---*--

2-CS-MOV*201D 11548-CBM-084A 2 OF 3 E-5 MO GATE 8.00 2 A _DC CIV EV LT 39 ST VP "B" CONT SPRAY -PUMP DISCHARGE ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE

---*------------------------------------------------.-----------------------------------------------------------.---------

2*CS-MOV-202A 11548-CBM-084A 3 OF 3 C-6 MO GATE

  • 6.00 2 B 0 EV ST VP CHEMICAL ADDITION TANK DISCHARGE TO.RWST ISOLATION VALVE 2*CS-MOV-202B 11548-CBM-084A 3 OF 3 B-6 MO GATE 6.00 2 B 0 EV ST VP CHEMICAL ADDITION TANK DISCHARGE TO RWST ISOLATION VALVE

~----------------------------------------------------------------------------------'

  • VIRGINIA PO\JER COMPANY PAGE: 15 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL COLD ALT VALVE DRA\,/ING SHEET DR\,/G VALVE VALVE ASME TEST VALVE TEST REC SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE V- CSV- VNC-2-cv-002 11548-CBM*OSSA 1 OF 2 D-4 MAN GATE 8.00 2 AE C CIV LT CONTAINMENT VACUUM EJECTOR SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 2-CV-HCV-200 11548-CBM*OSSA 1 OF 2 D-3 AO GATE 8.00 2 AE C CIV LT VP CONTAINMENT VACUUM EJECTOR, INSIDE CONTAIN*

MENT ISOLATION VALVE

*----------------------------------------------------------------

2-CV*TV-250A 11548-CBM*OSSA 2 OF 2 E-4 AO GATE 2.00 2 A C CIV EV FS LT ST 34 VP "A" CONTAINMENT VACUUM PUMP SUCTION ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2-CV-TV-250B 11548-CBM*OSSA 2 OF 2 E-5 AO GATE 2.00 2 A C CIV EV FS LT ST 34 VP

"A" CONTAINMENT VACUUM PUMP SUCTION ISOLATION VALVE, OUTSIDE CONTAINMENT* ISOLATION VALVE 2-CV*TV*250C 11548-CBM*OSSA 2 OF 2 D-4 AO GATE 2.00 2 A C CIV EV FS LT ST 34 VP "B" *coNTAINMENT VACUUM PUMP SUCTION ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2*CV*TV*250D 11548*CBM-085A 2 OF 2 D-5 AO GATE 2.00 2 A C CIV EV FS LT ST 34 VP "B" CONTAINMENT VACUUM PUMP SUCTION ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE

  • VIRGINIA POWER COMPANY PAGE: 16 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASHE TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE
  • TYPE v- csv- VNC-2-CW-117 11548-CBM-071A 2 OF 3 F-3 MANUAL BFLY 12.00 NC 8 0 EV 2

*----------------------------------------

DISCHARGE TUNNEL VENT VALVE 2-CW-MOV-200A 11548-CBM-071A 2 OF 3 F*7 MO BFLY 96.00 NC 8 C EV ST VP

*----------

CONDENSER DISCHARGE ISOLATION VALVE

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

11548-CBM-071A 2 Of 3 F-7 MO BFLY 96.00 NC EV

-

2-CW-MOV-200B 8 C ST VP CONDENSER DISCAHRGE ISOLATION VALVE 2-CW-MOV-200C 11548-CBM-071A 2 OF 3 F-6 MO BFLY 96.00 NC B C EV ST VP CONDENSER DISCHARGE ISOLATION VALVE

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

  • 2-CW-MOV-200D 11548*CBM-071A 2 OF 3 F-5 MO BFLY 96.00 NC B C EV ST VP CONDENSER DISCHARGE ISOLATION VALVE 2-CW-MOV-206A 11548-CBM*071A 2 OF 3 D-7 MO BFLY 96.00. 3 8 C EV ST VP CONDENSER INLET ISOLATION VALVE 2-CW-MOV-206B 11548-CBM-071A 2 OF 3 D-7 MO BFLY 96.00 3 8 C EV ST VP CONDENSER INLET ISOLATION VALVE 2-CW-MOV-206C 1154S*CBM-071A 2 OF 3 0-5 MO BFLY 96.00 . 3 8 C EV ST VP CONDENSER INLET ISOLATION VALVE 2*CW-MOV*206D 11548*CBM*071A 2 OF 3 D-5 MO BFLY 96.00 3 8 C EV ST VP CONDENSER INLET ISOLATION VALVE
  • SURRY UNIT 2 REVISION: 03 SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET .DRWG VALVE VALVE ASHE TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC-2-DA*TV-200A 11548-CBM-083B 3 OF 3 B-3 AO GATE 2.00 2 A C CIV EV FS LT ST 34 VP REACTOR CONTAINMENT SUMP PUMPS DISCHARGE, OUTSIDE CONTAINMENT ISOLATION VALVE

. -----------------------------------------------*-------------------------------------------------

2-DA*TV-200B 11548-CBM-083A 1 OF 2 E-3 AO GATE 2.00 2 A C CIV EV FS LT ST 34 VP REACTOR CONTAINMENT SUMP PUMPS DISCHARGE, INSIDE CONTAINMENT ISOLATION VALVE 2-DA-TV-203A 11548-CBM-083B 3 OF 3 E-3 AO GATE 2.00 2 A C CIV EV FS LT ST 34 VP POST ACCIDENT SAMPLE SYSTEM RETURN, OUTSIDE

  • CONTAINMENT ISOLATION VALVE

-----<<---------------------------

2-DA-TV-203B 11548-CBM-083B 3 OF 3 E-3 AO GATE 2.00 2 A C CIV EV FS LT ST 34 VP

* ------------------------

POST ACCIDENT SAMPLE SYSTEM RETURN, OUTSIDE CONTAINMENT TRIP VALVE .

  • SURRY UNIT 2 REVISION: 03 SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC-

2-DG-TV-208A 11548-CBM-083B 1 Of 3 B-2 AO GATE 2.00 2 A C .CIV EV FS LT ST VP PRIMARY DRAIN TRANSFER PUMPS DISCHARGE, INSIDE CONTAINMENT ISOLATION VALVE

. --------------------------*

2-DG-TV-2088

* -------------------------------------------------------------

11548-CBM-083A 2 OF 2 C-3 AO GATE 2.00 2 A C CIV EV

FS LT ST 34 VP PRIMARY DRAIN TRANSFER PUMPS DISCHARGE, OUT*

SIDE CONTAINMENT ISOLATION VALVE

,I I

  • VIRGINIA PO\.IER COMPANY PAGE: 19 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHF.ET DRI.IG VALVE VALVE. ASME TEST VALVE TEST .REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE V- CSV* VNC-1-EE-013 11448-CBB*038A 2 OF 3 D-7 CHECK VALVE 1.50 NC C 0 CV DIESEL EMERGENCY GENERATOR FUEL OIL PUMP DISCHARGE CHECK VALVE 1-EE-019 11448-CBB-038A 2 OF 3 F-7 CHECK VALVE 1.50 NC C 0 CV DIESEL EMERGENCY GENERATOR FUEL OIL PUMP DISCHARGE CHEC~ VALVE 1-EE-031 11448-CBB-038A 2 OF 3 D-6 CHECK VALVE 1.50 NC C 0 CV DIESEL EMERGENCY GEIIERATOR FUEL OIL PUMP DISCHARGE CHECK VALVE 1-EE-RV-104 11448-CBB-038A 2 OF 3 D-7 RELIEF VALVE 0.50 NC C 0 SP DIESEL FUEL OIL PUMP DISCHARGE RELIEF VALVE 1-EE-RV-105 11448-CBB-038A 1 OF 3 F-7 RELIEF VALVE 0.50 NC C 0 SP DIESEL FUEL OIL PUMP DISCHARGE RELIEF VALVE 1-EE*RV-107 11448-CBB-038A 2 OF 3 D-6 RELIEF VALVE 0.50 NC C 0 SP
  • 1-EE*SOV-102 DIESEL FUEL OIL PUMP DISCHARGE RELIEF VALVE 11448-CBB*038A 2 OF 3 D-4 SO GATE DIESEL FUEL OIL PUMP DISCHARGE VALVE 1.00 NC B 0 EV 36 1-EE-SOV-103 11448-CBB*038A 2 OF 3 D-4 SO GATE 1.00 NC B 0 EV 36 DIESEL FUEL OIL PUMP DISCHARGE VALVE 1-EE-SOV-104 11448-CBB-038A 2 OF 3 F-4 SO GATE 1.00 NC B 0 EV 36 DIESEL FUEL OIL PUMP DISCHARGE VALVE

VIRGINIA POl,IER COMPANY PAGE: 20 OF 63 SURRY UNIT 2 REVISION: 03

  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME TEST VALVE TEST . REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC*

2-EG-040' 11448-CBB-046B 1 OF 2 B-8 CHECK VALVE 0.75 NC AC C CV

--- --- -

LT DIESEL GENERATOR COMPRESSOR DISCHARGE CHECK VALVE

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

2-EGs042 11448-CBB-046B 1 OF 2 B-4 CHECK VALVE 0.75 NC AC C CV LT

-DIESEL GENERATOR COMPRESSOR DISCHARGE* CHECK VALVE 2-EG-043 11448-CBB-046B 1 OF 2 E-7 AIR PILOT NC B 0 EV ST 3 EMERGENCY DIESEL GENERATOR STARTING AIR/DRIVE AIR CONTROL/RELAY VALVE 2*-EG-044 11448-CBB-046B 1 OF 2 E-3 AIR *PILOT NC B 0 _EV ST 3 EMERGENCY DIESEL GENERATOR STARTING AIR/DRIVE AIR CONTROL/RELAY VALVE

---------------------------------------------------------------------------------------------------

c

  • oc*

2-EG-045 11448-CBB-046B 1 OF 2 E-7 CHECK VALVE NC 3

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

2-EG-046 11448*CBB-046B. 1 OF 2 E-4 CHECK VALVE NC C oc CV 3 EMERGENCY DIESEL GENERATOR START PRESSURE EQUALIZING CHECK VALVE 2-EG*SOV-200A 11448-CBB-046B 1 OF 2 0-7 SO GATE 1.00 NC B oc EV ST 37 DIESEL AIR START SYSTEM SOLENOID VALVE 2-EG*SOV-200B 11448-CBB-046B 1 OF 2 0-4 SO GATE 1.00 NC B oc EV*

ST 37 DIESEL AIR START SYSTEM SOLENOID VALVE

  • VIRGINIA PO\JER COMPANY PAGE: 21 OF 63 SURRY UNIT 2
  • REVISION: 03 SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME TEST VALVE TEST REC SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC-2-FP-151 11448-CBB-0478 1 OF 3 D-4 MAN BALL 4.00 2 AE C CIV LT

FIRE PROTECTION SUPPLY TO CONTAINMENT, OUTSIDE CONTAINMENT ISOLATION VALVE 2-FP-152 11448-CBB-0478 1 OF 3 D-5 MAN BALL 4.00 2 AE C CIV LT FIRE PROTECTION SUPPLY TO CONTAINMENT, OUTSIDE CONTAINMENT ISOLATION VALVE

  • PAGE: 22 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASHE TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE V* CSV* VNC*

2*FW*010 11548*CBM*068A 1 OF 4 E-6 CHECK VALVE 14.00 2 C C CV 5

"A" MAIN FEEDWATER SUPPLY, INSIDE CONTAINMENT PENETRATION CHECK VALVE 2*FW*027 11548*CBM-068A 1 OF 4 E-6 CHECK VALVE 3.00 2 C 0 CV 4 "A" AUXILIARY FEEDWATER HEADER CHECK VALVE AT MAIN FEEDWATER HEADER

. .

2*FW*041 11548-CBM*068A 1 OF 4 D*6 CHECK VALVE 14.00 2 C C CV 5 11 8" MAIN FEEDWATER HEADER SUPPLY, INSIDE CONTAINMENT PENETRATION CHECK VALVE

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

2-FW-058 11548*CBM*068A

. .

1 OF 4 C*6 CHECK VALVE 3.00 2 C 0 CV 4

"B" AUXILIARY FEEDWATER HEADER CHECK VALVE AT MAIN FEEDWATER HEADER

*

CV

2* FW-072 11548*CBM*068A 1 OF 4 C-6 CHECK VALVE 14.00 2 C C 5 "C" MAIN FEEDWATER SUPPLY, I.NS IDE CONTAINMENT

. PENETRATION CHECK VALVE

* -------------------------

2-FW-089 11548-CBM-068A 1 or 4 B-7 CHECK VALVE 3.00 2 C 0 CV 4

MAIN FEEDWATER HEADER 11548*CBM*068A 1 OF 4 8*4 CHECK VALVE AUXILIARY FEEDWATER HEADER CHECK VALVE AT CONTAINMENT PENETRATION* INSIDE 6.00 2 C 0 CV 4*

-*------------------------------------------------------------------------------------------------------------------------

2-FW-133 11548*CBM*068A 1 OF 4 8*4 CHECK VALVE 6.00. 2 C 0 CV 4 AUXILIARY FEEDWATER HEADER CHECK VALVE AT CONTAINMENT PENETRATION* . OUTSIDE .

2-FW* 136 11548*CBM*068A 1 OF 4 A-4 CHECK VALVE 6.00 2 C 0 CV 4

AUXILIARY FEEDWATER HEADER CHECK VALVE AT

  • ------

CONTAINMENT PENETRATION* INSIDE 2-FW* 138 11548*CBM*068A 1 OF 4 A-4 CHECK VALVE 6.00 2 C 0 CV 4 AUXILIARY FEEDWATER HEADER CHECK VALVE AT.

CONTAINMENT PENETRATION* OUTSIDE

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

2-FW-142

~-----------*

11548*CBM*068A 3 OF 4 D-8 CHECK VALVE 6.00 3

C oc CV 4 TURBINE_DRIVEN AUXILIARY FEEDWATER PUMP DISCHARGE CHECK VALVE

11548*CBM*068A 3 OF 4 D-7 CHECK VALVE

  • ---------------------------------------------------

1.00 3 CV 41 2*FW*144 C 0 TURBINE DRIVEN AUXILIARY FEEDWATER PUMP RECIRC LINE CHECK VALVE .

  • VIRGINIA POWER COMPANY PAGE: 23 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO
  • REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE V- CSV- VNC-2-F.W-148 11548-CBM-068A 3 OF 4 E-7 CHECK VALVE 1.00 3 C 0 CV 41

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

AUXILIARY FEEDWATER TO PUMP OIL COOLER CHECK VALVE 2-FW-157 11548-CBM-068A 3 OF 4 D-6 CHECK VALVE C oc CV 4

. .

"A" MOTOR DRIVEN AUXILIARY FEEDWATER PUMP DISCHARGE CHECK VALVE 2:;~:;;~---------;;;4a:~;;:o~---i-~;-4--~:6---~~~~~-~~~~~-------;~oo---i------~----~------------~~------;;;-------------- ~

"A" MOTOR DRIVEN AUXILIARY FEEDWATER PUMP RECIRC LINE. CHECK VALVE 2-FW-163 11548-CBM-068A 3 OF 4 E-6 CHECK VALVE 1.00 3 C* 0 CV 41 AUXILIARY FEEDWATER TO PUMP OIL COOLER CHECK VALVE 2-FW-172 11548-CBM-068A 3 OF 4 D-5 CHECK VALVE 6.00 3 C QC CV 4 "B" MOTOR DRIVEN AUXILIARY FEEDWATER PUMP DISCHARGE CHECK VALVE 2-FW-174 11548-CBM-068A. 3 OF 4 D-5 CHECK VALVE 1.00 3 C 0 CV 41

.RECIRC LINE CHECK VALVE 11548-CBM-068A 3 OF 4 E-4 CHECK VALVE AUXILIARY FEEDWATER TO PUMP OIL COOLER CHECK VALVE 1.00 3 C 0 CV 41 2-FW-272 11548-CBM-068A 1 OF 4 A-8 CHECK VALVE 6.00 2 C 0 CV 4 CHECK VALVE AT CONT PENE (CROSS - CONNECT FOR UNIT 1 AUX FEED FROM UNIT 2) . .

2-FW-273 11548-CBM-068A 1 OF 4 A-7 CHECK VALVE 6.00 2 C 0 CV 4 CHECK VALVE AT CONT PENE (CROSS - CONNECT FOR UNIT 1 AUX FEED FROM UNIT 2) 2-FW-305 11548-CBM-068A 1 OF 4 A-5 CHECK VALVE 6.00 2 C 0 CV 4 CHECK VALVE AT CONT PENE (CROSS - CONNECT FOR UNIT 1 AUX FEED FROM UNIT 2) 2-FW-306 11548-CBM-068A 1 OF 4 A-5 CHECK VALVE 6.00 2 C 0 CV 4 CHECK VALVE AT CONT PENE (CROSS - CONNECT FOR UNIT 1 AUX FEED FROM UNIT 2)

- -----------------------------------------------------*--------------------------------------------------------------------

2-FW*FCV-2478 11548-CBM-068A 1 OF 4 E-4 AO GATE 14.00 NC B C EV 28 FS .. 28 ST VP

VIRGINIA POWER COMPANY PAGE: 24 OF 63 SURRY UNIT 2 REVISION: 03 SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASHE TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC*

2-FW-FCV-2488 11548-CBM-068A 1 Of 4 D-4 AO GATE 14-00 NC B C EV 28 FS 28 ST VP MAIN FEEDWATER REGULATING VALVE 2-FW-FCV-2498 11548-CBM*068A 1 OF 4 B-4 AO GATE 14.00 NC B C EV 28 FS . 28 ST VP MAIN FEEDWATER REGULATING VALVE 2-FW*HCV*255A 11548-CBM-068A 1 OF 4 F-3 AO GATE 4.00 NC B C EV* 28 FS 28 ST

. VP

  • MAIN FEEDWATER REGULATING VALVE BYPASS VALVE 2*FW*HCV*255B 11548-CBM~068A 1 OF 4 D-3 AO GATE 4.00 NC B C EV 28 FS . 28
  • ST VP MAIN FEEDWATER REGULATING VALVE BYPASS VALVE 2*FW*HCV*255C 11548-CBM*068A 1 OF 4 C-3 AO GATE 4.00 NC B C EV 28 FS 28 ST VP MAIN FEEDWATER REGULATING VALVE BYPASS VALVE

.

.

2*FW*MOV*251A 11548-CBM*068A 1 OF 4 B-7 MO GLOBE 3.00 2 B oc EV ST VP NORMAL AUXILIARY FEEDWATER SUPPLY TO "C" STEAM GENERATOR 2-FW*MOV-251B 11548*CBM*068A 1 OF 4 B-7 MO GLOBE 3.00 2 B oc EV ST VP STANDBY AUXILIARY FEEDWATER SUPPLY TO 11 C11

  • STEAM GENERATOR

. -

**---------------------------------------------------------------------------------

2-FW*MOV*251C 11548-CBM-068A 1 OF 4 B-6 MO GLOBE 3.00 2 B oc EV ST VP STANDBY AUXILIARY FEEDWATER SUPPLY TO "B" STEAM GENERA TOR

  • VIRGINIA POIJER COMPANY PAGE: 25 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE . DRAWING SHEET DRWG VALVE VALVE. ASHE TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT P.OS TYPE TYPE v- csv- VNC-2-FW-MOV-251D 11548-CBM-068A 1 OF 4 B-6 MO GLOBE 2 B oc EV ST VP NORMAL AUXILIARY FEEDWATER SUPPLY TO "B" STEAM GENERATOR

2-FW-MOV-251E 11548-CBM-068A 1 OF 4 B-6 MO GLOBE 3.00 2 B oc EV ST VP STANDBY AUXILIARY FEEDIJATER SUPPLY TO "A" STEAM GENERATOR, 2-FW-MOV-251F 11548-CBM-068A 1 OF 4 B-5 MO GLOBE 3.00 2 B oc EV ST VP STANDBY AUXILIARY FEEDWATE.R SUPPLY TO 11A11 STEAlil GENERATOR 2-FW-MOV-260A 11448-CBM-068A 3 OF 4 F-7 MO GLOBE 6.00 3 B 0 EV ST VP CROSS - CONNECT FOR UNIT 1 AUXILIARY FEED-

  • WATER FROM UNIT 2 2-FW-MOV-260B 11448-CBM-068A 3 OF 4 F-7 MO GLOBE 6.00 3 B o EV ST VP CROSS - CONNECT FOR UNIT 1 AUXILIARY FEED-WATER. FROM UNIT 2
  • VIRGINIA POIJER COMPANY PAGE: 26 OF 63 SURRY UNIT 2 REVISION: 03
    • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL COLD AP VALVE DRAWING SHEET DRWG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC*

--- --- -

2-GW*TV-200 11448*CBM*090C 1 OF 1 C-4 SO GATE 0.375 2 A C CIV EV FS LT ST 34 VP

*------------------

SUCTION LINE TO HYDROGEN ANALYZER* UNIT 1 2-GW*TV-201 l1448*CBM-090C 1 OF 1 C-4 SO GATE 0.375 2 A C CIV EV FS LT ST 34 VP SUCTION LINE TO HYDROGEN ANALYZER* UNIT 1 2-GW*TV-202 11448*CBM-090C 1 OF 1 B-4 SO GATE 0.375 2 A C CIV EV FS LT ST 34 VP DISCHARGE LINE TO HYDROGEN ANALYZER* UNIT 1

  • 2*GW*TV*203 11448*CBM-090C 1 OF 1 B-4 SO GATE DISCHARGE LINE TO HYDROGEN ANALYZER* UNIT 1 0.375 2 A C CIV EV FS LT ST VP 34 2-GW*TV*204 11448*CBM-090C 1 OF 1 E-4 SO GATE 0.375 2 A C CIV EV FS LT ST 34 SUPPLY TO UNIT 2 HYDROGEN ANALYZER, OUTSIDE VP I

CONTAINMENT ISOLATION VALVE 2*GW*TV*205 11448*CBM-090C 1 OF 1 E-4 . SO GATE 0.375 2 A C CIV EV FS LT ST 34 VP SUPPLY TO UNIT 2 HYDROGEN ANALYZER, OUTSIDE CONTAINMENT ISOLATION VALVE

.

2-GW*TV-206

  • --------------------------------------------------------*----------------------------------

11448-CBM*090C 1 OF 1 D-4 SO GATE 0.375 2 CIV A C EV FS LT ST 34 VP

  • RETURN FROM UNIT 2 HYDROGEN ANALYZER, OUTSIDE CONTAINMENT ISOLATION VALVE

VIRGINIA PO\IER COMPANY PAGE: 27 OF 63 SURRY UNIT 2 REVISION: 03

  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASHE TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYP.E SIZE CLASS CAT POS TYPE TYPE v- csv- VNC*

.

2-GW-TV-207 11448-CBM-090C 1 OF 1 D-4 SO GATE 0.375 2 A C CIV EV FS LT ST 34 VP RETURN FROM UNIT 2 HYDROGEN ANALYZER, OUTSIDE I

CONTAINMENT ISOLATION VALVE 2-GW*TV-211A 11448*CBM-090C 1 OF 1 F-3 SO GATE 0.375 2 A C CIV *EV FS LT ST 34 VP UNIT 1 SAMPLE LINE TO AIR SAMPLE PANEL, INSIDE CONTAINMENT ISOLATION VALVE 2-GW-TV-2118 11448-CBM-090C 1 OF 1 F-3 SO GATE 0.375 2 A c. CIV EV FS .

LT ST 34 VP UNIT 1 SAMPLE LINE TO AIR SAMPLE PANEL, OUTSIDE CONTAINMENT ISOLATION VALVE

  • -------------------------------~---------------*----------------------------------------------------------------------* ---
  • VIRGINIA PO'JER COMPANY PAGE: 28 OF .63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG . VALVE VALVE ASHE TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC-2-IA-381 11548-FM -075C 2 OF 2 B-6 CHECK VALVE 0.75 NC AC C CV LT

*----------.

BOTTLED AIR SUPPLY TO 2-RC-PCV-2456 ISOLATION CHECK VALVE 2-IA-384 11548-FM -075C 2 OF 2 B-5 CHECK VALVE 0.75 NC AC C CV LT

*------------------.------------------

BOTTLED AIR SUPPLY TO 2-RC-PCV-2455C ISOLATION CHECK VALVE 2- IA-395 11548-FM -075C 2 OF 2. B-6 CHECK VALVE 0.75 NC C 0 CV BOTTLED AIR SUPPLY TO 2-RC-PCV-2456 SUPPLY CHECK VALVE 2-IA-396 11548-FM -075C 2 OF 2 B-5 CHECK VALVE O. 75 NC C 0 CV BOTTLED AIR SUPPLY TO 2-RC-PCV-2455C SUPPLY CHECK VALVE 2-IA-446 11448-CBM-075C 1 OF 4 D-7 MAN GATE 2.00 2. AE C CIV LT BACKUP INSTRUMENT AIR TO CONTAINMENT FROM UNIT 2

  • 2-IA-704 2-IA-864 11548-CBM-075B UNIT 2 .

11548-CB~-075C 2 OF 2 C-3 1 OF 2 E-3 MAN.GATE BACKUP INSTRUMENT AIR TO CONTAINMENT FROM CHECK VALVE 2.00 2.00 2

2 AE AC C

C CIV CIV LT CV LT 39 44 INS1RUMENT AIR SUPPLY TO CONTAINMENT, INSIDE CONTAINMENT ISOLATION CHECK VALVE 2-IA-868 11548-CBM-075C 1 OF 2 E-3 CHECK VALVE 2.00 2 AC C CIV CV 44 LT INSTRUMENT AIR SUPPLY TO CONTAINMENT, INSIDE CONTAINMENT ISOLATION CHECK VALVE 2-IA-947 11548-FM -0750 1 OF 1 B-7 CHECK VALVE 0.5 NC AC C CV LT BOTTLED AIR SUPPLY TO 2-MS-SOV-202A,B ISOLATION CHECK VALVE .

*----------------------------------------------------------------------------------------------------------*

2-IA-948 11548-FM -075D 1 OF 1 9-8 CHECK VALVE 0.5 NC C 0 CV

BOTTLED AIR SUPPLY TO 2-MS-SOV-202A,B SUPPLY CHECK VALVE 2-IA-RV-210 11548-CBM-075C 2 OF 2 B-6 RELIEF VALVE NC C* 0 SP BOTTLED AIR SUPPLY TO PORV'S RELIEF VALVE

  • VIRGINIA POWER COMPANY PAGE: 29 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE.TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAIJING SHEET DRIJG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMl!ER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC-2-IA-RV-211 11548-CBM-075C 2 OF 2 B-5 RELIEF VALVE NC C 0 SP

BOTTLED AIR SUPPLY TO PORV'S RELIEF VALVE 2-IA-TV-200 11548-CBM,075B 2 OF 2 B-3 AO GATE 2.00 2 A C CIV EV FS LT 39 ST 34 VP INSTRUMENT AIR SUPPLY TO CONTAINMENT, OUTSIDE CONTAINMENT ISOLATION VALVE 2-IA-TV-201A 11548-CBM-075J 1 OF 1 A-3 AO GATE 3.00 2 A C. CIV EV FS LT ST VP INSTRUMENT AIR SUCTION FROM CONTAINMENT 2-IA-TV*201B 11548-CBM-075J 1 OF 1 A-3 AO GATE 3.00 2 A C CIV EV FS LT

  • ST 34 VP INSTRUMENT AIR SUCTION FROM CONTAINMENT
  • VIRGINIA PQ',/ER COMPANY PAGE: 30 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRA\JING SHEET DR\JG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC-2-LM-TV-200A 11548-CBM-OBSA 1 OF 2 B-6 AO GATE 0.375 2 A C CIV EV FS LT 39 ST 34 VP CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 2-LM*TV*200B 11548-CBM-OBSA 1 OF 2 B-6 AO GATE 0.375 2 A C CIV EV FS LT 39 ST 34 VP CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 2-LM-TV-200C 11548-CBM-OBSA
  • 1 OF 2 B-5 AO GATE 0.375 2 A C CIV EV FS LT 39 ST 34 VP CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE
  • 2-LM*TV-200D 11548-CBM-OBSA 1 OF 2 B-5 AO GATE CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 0.375 2* A C CIV EV FS LT ST VP 39 34

* --------------------------------------*---------------------------------------------------------------

2-LM*TV-200E 11548-CBM-OBSA 1 OF 2 B-4 AO GATE 0.375 2 A C CIV EV FS LT 39 ST 34 VP CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 2-LM-TV-200F 11548-CBM-OBSA 1 OF 2 B-5 AO GATE 0.375 2 A C CIV EV FS LT 39 ST 34 VP CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 2*LM*TV-200G 11548-CBM-OBSA 1 OF 2 B-6 AO GATE 0.375 2 A C CIV EV FS LT 39 ST 34 VP

  • CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE

VIRGINIA PO\JER COMPANY PAGE: 31 OF 63 SURRY UNIT 2 REVISION: 03

  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL COLD ALT VALVE DRAIJING SHEET DRIJG VALVE VALVE. ASME TEST VALVE TEST REC SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SI_ZE CLASS CAT POS TYPE TYPE V* CSV* VNC-2*LM-TV-200H 11548-CBM*OBSA 1 OF 2 B-7 AO GATE 0.375 2 A C CIV EV FS LT 39 ST 34 VP CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE
  • VIRGINIA Pa.lER COMPANY PAGE: 32 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAIJING SHEET DRIJG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE V- CSV* VNC-2-MS-087 11548-CBM-064A 1 OF 6 C-6 MANUAL GATE 4.0 2 B C EV MAIN STEAM LINE TO TURBINE DRIVEN AUXILIARY FEEDIJATER PUMP ISOLATION VALVE

*

2-MS-120 11548-CBM-064A 2 OF 6 C-6 MANUAL GATE 4.0 2 B C EV

MAIN STEAM LINE TO TURBINE DRIVEN AUXILIARY FEEDIJATER PUMP ISOLATION VALVE

2-MS-158 11548-CBM-064A 3 OF 6 C-6 MANUAL GATE 4.0

  • --2 *-----------------------------------------------

B C EV MAIN STEAM LINE TO TURBINE DRIVEN AUXILIARY FEEDIJATER PUMP iSOLATION VALVE 2-MS-176. 11548*CBM-064A 4 OF 6 C-7 CHECK VALVE 3.00 2 C oc CV 42 "A" MAIN STEAM HEADER SUPPLY CHECK VALVE TO TURBINE DRIVEN AUXILIARY FEEDIJATER PUMP 2-MS-178 11548*CBM-064A 4 OF 6 D-7 CHECK VALVE 3.00 2 C QC CV 42 11 8" MAIN STEAM HEADER SUPPLY CHECK VALVE TO TURBINE DRIVEN AUXILIARY FEEDIJATER PUMP

*-----------------------------------

QC 2-MS-182 11548-CBM*064A 4 OF 6 D-7 CHECK VALVE 3.00 2 C CV 42

. FEEDIJATER

.

11548-CBM-064A 1 OF 6 E-4 MO STOP CHECK "A" MAIN STEAM HEADER NON-RETURN VALVE PUMP

30.00 2 C C CV VP 48 2-MS*NRV-2018 11548-CBM-064A 2 OF 6 D-3 MO STOP CHECK 30.00 2 C C CV 48 VP 11 811 MAIN STEAM HEADER NON-RETURN VALVE 2-MS*NRV-201C 11548-CBM-064A 3 OF 6 D-3 MO STOP CHECK 30.00 2 C C CV 48 VP "C" MAIN STEAM HEADER NON-RETURN VALVE 2-MS-PCV-202A 11548-CBM-064A 4 OF 6 C-4 AO GATE 3.00 2 B QC EV FS ST VP MAIN STEAM SUPPLY TRIP VALVE TO TURBINE DRIVEN AUXILIARY FEEDIJATER PUMP

  • SURRY UNIT 2 REVISION: 03 SECOND INSPECTION INTERVAL DATE: 3/19/92 JNSERVJCE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC-2-MS-PCV-2028 11548*CBM-064A 4 OF 6 D*S AO GATE 3.00 2 B oc EV FS ST VP MAIN STEAM SUPPLY TRIP VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP

2-MS-RV-201A 11548-CBM-064A 1 OF 6 E-5 AO ANGLE 4.00 2 B oc . EV FS ST 47 VP "A" MAIN STEAM HEADER DISCHARGE TO ATMOSPHERE POWER OPERATED RELIEF VALVE 2-MS-RV-201B 11548-CBM-064A 2 OF 6 E-6 AO ANGLE 4.00 2 B oc EV FS ST 47 VP 11 911 MAIN STEAM HEADER DISCHARGE TO ATMOSPHERE POWER OPERATED RELIEF VALVE 2-MS-RV-201C 11548-CBM-064A 3 OF 6 E-5 AO ANGLE 4.00 2 B oc EV

  • FS ST 47 VP "C" MAIN STEAM HEADER DISCHARGE TO ATMOSPHERE POWER OPERATED RELIEF VALVE 2-MS-SV-201A 11548-CBM-064A 1 OF 6 E-6 SAFETY VALVE 4.00 2 C 0 SP "Au MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2-MS-SV-201B 11548-CBM-064A 2 OF 6 D-6 SAFETY VALVE 4.00 2 C 0 SP 11 911 MAIN STEAM HEADER SAFETY VALVE, SY DISCHARGE TO ATMOS 2-MS-SV-201C 11548-CBM-064A 3 OF 6 D-6 SAFETY VALVE 4.00 2 C 0 SP "C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS

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

2-MS-SV-202A 11548-CBM-064A 1 OF 6 E-6 SAFETY VALVE

  • ---------------------------------------------------------------

6.00 2 C 0 SP "Au MAIN STEAM HEADER SAFETY VALVE, SY DISCHARGE TO ATMOS 2-MS-SV-2028 11548-CBM-064A 2 OF 6 D-5 SAFETY VALVE 6.00 2 C 0 SP 11811 MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS

  • SURRY UNIT 2 REVISION: 03 SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL COLD ALT VALVE -DRAWING SHEET DRWG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS .CAT POS TYPE TYPE V* CSV* VNC-2_*MS*SV*202C 11548*CBM*064A 3 OF 6 D-6 SAFETY VALVE 6.00 2 C 0 SP

C MAIN STEAM HEADER SAFETY VALVE, SV 11 11 DISCHARGE TO ATMOS 2*MS*SV-203A 11548-CBM-064A 1 OF 6 E-6. SAFETY VALVE 6.00 2 C 0 SP 11 A11 MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO.ATMOS 2*MS*SV*203B 11548-CBM*064A 2 OF 6 D-6 SAFETY VALVE 6.00 2 C 0 SP 11 811 MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGEE TO ATMOS 2*MS*SV-203C 11548*CBM-064A 3 OF 6 D-6 SAFETY VALVE 6.00 2 C 0 SP 11 C11 MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2*MS*SV-204A 11548-CBM-064A 1 OF 6 E-6 SAFETY VALVE 6.00 2 C 0 SP

*----------------

A MAiN STEAM HEADER SAFETY VALVE, SV 11 11 DISCHARGE TO ATMOS 11548-CBM-064A 2 OF 6 D-6 SAFETY VALVE 6.00 2 SP

  • 2*MS*SV*204B C 0 11 811 MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2*MS*SV*204C 11548*CBM*064A 3 OF 6 D-6 SAFETY VALVE 6.00 2 C 0 SP "C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2-MS*SV-205A. 11548*CBM*064A 1 OF 6 E-5 SAFETY VALVE 6.00 2 C 0 SP 11 A" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2*MS*SV*205B 11548-CBM*D64A 2 OF 6 D-5 SAFETY VALVE 6.00 2 C 0 SP 11 8" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2*MS*SV*205C 11548~CBM*D64A 3 OF 6 D-5 SAFETY VALVE 6.00 2 C 0 SP 11 C11 MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2*MS*TV-201A 11548-CBM*D64A 1 OF 6 0*4 AO CHECK VALVE 30.00 2 B C EV ST VP
  • ------------------------------------------.--

11 A11 MAIN S.TEAM HEADER TRIP VALVE

  • VIRGINIA POWER COMPANY PAGE: 35 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMaER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC-2-MS-TV-201B 11548-CBM-064A 2 OF 6 C-4 AO CHECK VALVE 30.00 2 B C EV ST VP 11 B" MAIN STEAM HEADER TRIP VALVE 2-MS-TV-201C 11548-CBM-064A 3 OF 6 C-4 AO CHECK VALVE 30.00 2 B C EV ST VP 11 C11 MAIN STEAM HEADER TRIP VALVE 2-MS-TV-209 11548-CBM-064A 4 OF 6 F-5 AO GATE 3.00 2 B C EV FS ST VP
  • MAIN STEAM HIGH PRESSURE DRAIN ISOLATION TO CONDENSER 2-HS-TV-210 11548-CBM-064A 4 OF 6 F-7 AO GATE 2.00 2 B C EV FS ST 34 VP

2-MS-TV-220 11548-CBM-064A 4 OF 6 C-4 AO GATE MAIN STEAM SUPPLY TRIP VALVE TO TURBINE

  • ------------------------------------

3 B 0 EV ST VP

  • -------------------

DRIVEN AUXILIARY FEEDWATER PUMP

* ---------------------------------------------------------------------------------------*-----------

  • VIRGINIA POWER COMPANY PAGE: 36 OF 63 SURRY UNI.T 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL COLO ALT VALVE DRAWING SHEET , DRWG VALVE VALVE ASHE TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC*

2-RC-160 11548-CBM-0868 2 OF 3 D-7 CHECK. VALVE* 3.00 2 AC C CIV CV 44 LT

*--------

PRIMARY GRADE WATER SUPPLY TO PRESSURIZER RELIEF TANK

2*RC*HCV*2556A 11548-CBM*086A 1 OF 3 E-8 AO PLUG

---------------------

VP

2.0.0 E C LOOP FILL BOUNDARY VALVE

*----------------------------------------------------------------------------------

2-RC*HCV-2556B 11548*CBM-086A 2 OF 3 D-8 (10 PLUG 2.00 1 E C VP LCX>P FILL BOUNDARY VALVE 2*RC*HCV-2556C .11548-CBM-086A 3 OF 3 D-3 AO PLUG 2.00 E C VP.

LOOP FILL BOUNDARY VALVE 2-RC*MOV-2535

  • 11548*CBM-086B 1 OF 3 E-4 MO GATE 3.00 B . OC EV ST VP BLOCK VALVE FOR PRESSURIZER Poi.lER OPERATED

-* 2-RC*MOV-2536 RELIEF VALVE

* ---------------------------------------------------------------------

11548*CBM-086B 1 OF 3 D-4 MO GATE BLOCK VALVE FOR PRESSURIZER POIJER OPERATED RELIEF VALVE 3.00 B oc EV ST VP

.------------------------------------------------* ------------------------------------------------------------------------*-

2*RC*PCV*2455C 11548-CBM*086B 1 OF 3 D-3 AO PLUG 3.00 BC OC EV 7 FS 7 ST 34 VP PRESSURIZER POWER OPERATED PRESSURE CONTROL VALVE DISCHARGE TO PRESSURIZER RELIEF TANK

.-----------------*----------------------------------*-----------------------------------------------------.-

2*RC*PCV*2456 11548*CBM-086B 1 OF 3 E-3 AO PLUG 3.00 BC. OC EV 7 FS 7 ST 34 VP PRESSURIZER POWER OPERATED PRESSURE CONTROL VALVE DISCHARGE *TO PRESSURIZER RELIEF TANK 2*RC*SOV-200A1 11548-CBM-086A 3 OF 3 B-5 SO GATE 1.00 B OC EV 31 FS 31 ST. ~4 VP REACTOR VESSEL VENT LINE ISOLATION VALVE TO REFUELING CAVITY

  • .

VIRGINIA PO\IER COMPANY PAGE: 37 OF 63

  • SURRY UNIT 2 REVISION: 03 SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE* ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE V- CSV- VNC*

2-RC*SOV-200A2 11548-CBM-086A 3 OF 3 A-5 SO GATE 1.00 8 oc EV 31 FS 31 ST 34 VP REACTOR VESSEL VENT LINE ISOLATION VALVE TO REFUELING CAVITY

*-----------------------------------------------------------------------.

2-RC-SOV-200B1 11548-CBM-086A 3 OF 3 8-5 SO GATE 1.00 B

oc EV 31 FS 31 ST 34 VP REACTOR VESSEL VENT LINE ISOLATION VALVE TO REFUELING CAVITY

.

2-RC-SOV-20082 11548-CBM-086A 3 OF 3 A-5 SO GATE 1.00 B oc EV 31 FS 31 ST 34 VP REACTOR VESSEL VENT LINE ISOLATION VALVE TO REFUELING CAVITY 2-RC-SV-2551A 11548-CBM-0868 1 OF 3 E-6 SAFETY VALVE 6.00 C 0 SP

  • 2-RC-SV*2551B PRESSURIZER SAFETY VALVE, SV DISCHARGE TO PRESSURIZER RELIEF TANK

*----------------------------------

11548-CBM-0868 1 OF 3 E-5 SAFETY VALVE PRESSURIZER SAFETY VALVE, SV DISCHARGE TO PRESSURIZER RELIEF TANK 6.00 C 0 SP

*--------------------------------------------------------------------------------------------------------

2*RC-SV*2551C 11548-CBM-0868 1 OF 3 E-5 SAFETY VALVE 6.00 C* 0 SP PRESSURIZER SAFETY VALVE, SV DISCHARGE TO PRESSURIZER RELIEF TANK

*--------------------------------------------------------*-.--------------------------------------------------

2-RC*TV*2519A 11548-CBM-0868 2 OF 3 D-7 AO GATE 3.00 2 A C CIV EV FS LT ST VP PRIMARY GRADE WATER SUPPLY TO PRT*#2 RCP SEAL STANDPIPES & FLUSH CONNECT, OUT CONT ISO VLV

  • SURRY UNIT 2 REVISION: 03 SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL COLD ALT VALVE DRAIJING SHEET DRIJG VALVE VALVE ASHE
  • TEST VALVE TEST REQ .SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT* POS TYPE TYPE V- CSV- VNC-2-RH-005 11548-CBM-087A 1 OF 2 E*S CHECK VALVE 10.00 2 C QC CV 8

"B" RHR PUMP DISCHARGE CHECK VALVE

.-----------------------------------------------------------------------------------------------------------------------*-

QC CV 2-RH-011 11548-CBM-087A. 1 OF 2 E-7 CHECK VALVE

*-------------------------

RHR DISCHARGE TO LOOP 2 COLD LEG CHECK VALVE 2-RH-FCV-2605 11548-CBM~087A 2 OF 2 C-7 AO BFLY 12.00 2 B C EV 14 FS 14 ST 47 RHR HEAT EXCHANGERS BYP~SS FLOIJ CONTROL VALVE 2-RH*HCV-2758 11548-CBM-087A 2 OF 2 C-5 AO BFLY 12.00 2 B 0 EV 14 FS 14 ST 47

  • 2-RH*MOV-200 RHR HEAT EXCHANGERS DISCHARGE FLOIJ CONTROL VALVE 11548*CBM-087A . 2 OF 2 E-3 MO GATE

.----------------------------*---

RHR SUPPLY ISOLATION TO REFUEL IJATER STORAGE TANK, OUTSIDE CONTAINMENT ISOLATION VALVE

*

6.00 2 AE C CIV LT

2-RH*MOV-2700 115~8-CBM-087A 1 OF 2 A-5 MO GATE 14.00 B 0 EV 9 ST VP RHR PUMP SUPPLY ISOLATION FROM RC LOOP 1 HOT LEG 2-RH-MOV-2701 11548-CBM-087A 1 OF 2 A-4 MO GATE 14.00 B 0 EV 9 ST VP RHR PUMP SUPPLY ISOLATION FROM RC LOOP 1 HOT LEG 2*RH*MOV-2720A 11548-CBM-087A 2 OF 2 C-3 MO GATE 10.00 B 0 EV 10 ST VP RHR RETURN ISOLATION TO 11 8 11 ACCUMULATOR DISCHARGE LINE 2-RH*MOV-2720B 11548-CBM-087A 2 OF 2 B-3 MO GATE 10.00 B 0 EV 10 ST VP

VIRGINIA POWER COMPANY PAGE: 39 OF 63 SURRY UNIT 2 REVISION: 03

  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG
  • VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT PCS TYPE TYPE V- CSV- VNC-

......

2-RH-RV-2721 1154S-CBM-087A 2 OF 2 D-4 RELIEF VALVE 3 *.00 2 C 0 SP

RHR SYSTEM RELIEF VALVE

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

  • VIRGINIA PO\JER COMPANY PAGE: 40 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE V- CSV- VNC-2-RL-003 11448-CBM-118A 3 OF 3 D-7 MAN DIAPHRAGM 3.00 2 AE C CIV LT 39

REFUELING PURIFICATION FROM RP PUMPS TO REACTOR CAVITY, OUTSIDE CONT ISOLATION VALVE 2-RL-005 11448-CBM-118A 3 OF 3 D-6 MAN DIAPHRAGM 3.00 2 AE C CIV LT 39 REFUELING PURIFICATION FROM RP PUMPS TO REACTOR CAVITY, INSIDE CONT ISOLATION VALVE 2-RL-013 11448-CBM-118A 3 OF 3 B-7 MAN DIAPHRAGM 3.00 2 AE C CIV LT REFUELING PURIFICATION FROM REACTOR CAVITY TO RP PUMPS, INSIDE CONT ISOLATION VALVE 2-RL-015 11448-CBM-118A 3 OF 3 B-7 MAN DIAPHRAGM 3.00 2 AE C CIV LT REFUELING PURIFICATION FROM REACTOR *CAVITY TO RP PUMPS, OUTSIDE CONT ISOLATION VALVE

  • VIRGINIA POWER COMPANY PAGE: 41 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAIJING SHEET DRIJG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC-2-RM-003 11548-CBP-014B 1 OF 1 B-5 CHECK VALVE 0.75 2 AC C CIV CV 44 LT

 :-----------------------------------

RETURN TO CONTAINMENT FROM RADIATION MONITOR-ING CABINET, INSIDE CONT !SOL CHECK VALVE

11548-CBP-014B 1 OF 1 B-4 AO GATE CIV

EV 2-RM-TV-200A 0.75 2 A C FS LT ST 34 VP RETURN ISOLATION FROM AIR RADIATION MONITOR TO CONTAINMENT, OUTSIDE CONT ISOLATION VALVE 2-RM-TV-200B 11548-CBP-014B OF F-8 AO GATE 0.75 .2 A* C CIV EV FS LT ST 34 VP SUPPLY !SOL TO AIR RAD MONITOR FROM CONTAIN-MENT VENT DUCT, OUTSIDE CONT ISOLATION VALVE

--

2-RM-TV-200C

.------------- ----------------------. --------------------------------------- *-----------------

11548-CBP-014B 1 OF 1 E-8 AO GATE 0.75 2 A C* CIV EV FS

  • LT ST 34 VP SUPPLY !SOL TO AIR RAD MONITOR FROM.CONTAIN-MENT VENT DUCT, l~SIDE CONT ISOLATION VALVE
  • SURRY UNIT 2 REVISION: 03 SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASHE TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC-2-RS-011 11548-CBM-0848 2 OF 2 E-5 CHECK VALVE 10.00 2 AC oc CIV CV LT 43 1

"B" OUTSIDE RECIRC SPRAY PUMP INSIDE CONTAINMENT ISOLATION CHECK VALVE 2-RS-017 11548-CBM-084B 2 OF 2 D-5 CHECK VALVE 10.00 2 AC OC CIV CV 43 LT "A" OUTSIDE RECIRC SPRAY PUMP INSIDE

.

CONTAINMENT ISOLATION CHECK VALVE .

2-RS-046 11548-CBM-084B 2 OF 2 A-6. MAN GATE 2 AE C CIV LT 39 OUTSIDE RECIRC SPRAY PUMP*SUCTION BYPASS LINE ISOLATION VALVE 2-RS-053 11548-CBM-0848 2 OF 2 B-6 MAN GATE 2 AE C CIV LT 39 OUTSIDE RECIRC SPRAY PUMP SUCTION BYPASS LINE ISOLATION VALVE

*-------------------------------------------------------------------------- .-------------------------------

2-RS*MOV-255A 11548-CBM-084B 2 OF 2 B-6 MO PLUG 12.00 2 A CC CIV EV LT 39 ST

  • VP "A" OUTSIDE RECIRC SPRAY PUMP SUCTION ISOLAT VALVE FROM CONTAINMENT SUMP 2-RS*MOV*255B 11548-CBM-084B 2 OF 2 B-6 MO PLUG 12.00 2 A CC CIV EV LT 39 ST

. VP "B". OUTSIDE REC I RC SPRAY PUMP SUCTION ISOLAT VALVE FROM CONTAINMENT SUMP 2-RS*MOV-256A 11548-CBM-084B 2 OF 2 D-6 MO BFLY 10.00 2 A CC CIV EV LT ST VP 11 A11 OUTSIDE RECIRC SPRAY PUMP DISCHARGE ISO*

LATION, OUTSIDE CONTAINMENT ISOLATION VALVE 2-RS*MOV*256B 11548*CBM*0S4B 2 OF 2 E-6 MO BFLY 10.00 2 A CC CIV EV LT ST VP "A" OUTSIDE RECIRC SPRAY PUMP DISCHARGE ISO*

LATION, OUTSIDE CONTAINMENT ISOLATION VALVE

  • VIRGINIA PO\IER COMPANY PAGE: 43 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAlollNG SHEET DRlolG VALVE VALVE. ASME TEST VALVE TEST REC SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE V- CSV- VNC-2-RT-02 11548-CBM-124A 1 .OF 4 . E-7 MANUAL GLOBE 3_00 2 AE C LT

* -------------------------

STEAM GENERATOR RECIRCULATION INSIDE CONTAINMENT ISOLATION VALVE 2-RT-06 11548-CBM-124A 1 OF 4 E-6 MANUAL GLOBE 3.00 2* AE C LT

*-------------------

STEAM GENERATOR RECIRCULATION OUTSIDE

,CONTAINMENT ISOLATION VALVE 2-RT-21 11548-CBM-124A 2 OF 4 E-7 MANUAL GLOBE 3.00 2 AE C LT STEAM GENERATOR RECIRCULATION INSIDE CONTAINMENT ISOLATION VALVE 2-RT-25 11548-CBM-124A 2 OF 4 E-6 MANUAL GLOBE 3.00 2 AE C LT

'STEAM GENERATOR RECIRCULATION OUTSIDE CONTAINMENT ISOLATION VALVE 2-RT-40 11548-CBM-124A 3 OF 4 E-7 MANUAL GLOBE 3.00 2 AE C LT STEAM GENERATOR RECIRCULATION INSIDE CONTAINMENT ISOLATION VALVE 2-RT-44 11548-CBM-124A 3 0: 4 E-6 MANUAL GLOBE 3.00 2 AE C LT

  • ---------------* ------------------- .--- .------

STEAM GENERATOR RECIRCULATION OUTSIDE CONTAINMENT ISO~ATION VALVE

  • VIRGINIA POIJER COMPANY PAGE: 44 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASHE TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE* CLASS CAT POS TYPE TYPE v- csv- VNC-

--- --- ..

2-SA-081 11548-CBM-075E 1 OF 1 B-6 MAN GATE 2.00 2 AE C CIV LT SERVICE AIR SUPPLY TO UNIT 1 CONTAINMENT, INSIDE CONTAINMENT ISOLATION VALVE 2-SA-082 11548-CBM-O?SE 1 OF*1 B-6 MAN GATE 2.00 2 AE C CIV LT SERVICE AIR SUPPLY TO UNIT 1 CONTAINMENT, OUTSIDE CONTAINMENT ISOLATION VALVE

  • VIRGINIA POWER COMPANY . PAGE: 45 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBE~ COQR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC-2-SI-025 11548-CBM*089A 1 OF 3 E-5 CHECK VALVE 8.00 2 C oc CV 28

RWST SUPPLY CHECK VALVE TO CHARGING PUMP SUCTION HEADER

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

1.00 2 AE C CIV 2-Sl-032 11548-CBM-0898 1 OF 4 E-3 MAN GLOBE LT ACCUMULATOR MAKEUP LINE, OUTSIDE CONTAINMENT ISOLATION VALVE 2-Sl-046A 11548*CBM*089A 1 OF 3 A-3 CHECK VALVE 12.00 2 C 0 CV 21 RWST SUPPLY CHECK VALVE TO 11 A11 LOW HEAD SI PUMP SUCTION 2-Sl-046B 11548*CBM*089A 1 OF 3 B-3 CHECK VALVE 12.00 2 C 0 CV 21 RWST SUPPLY CHECK VALVE TO "B" LOW HEAD SI PUMP SUCTION

.

2-Sl-047 11548-CBM-089A 1 OF 3 B-5 CHECK VALVE 12.00 2 C

*---------------------

0 CV 20 11 811 LOIJ HEAD SI PUMP SUCTION CHECK VALVE FROM CONTAINMENT SUMP 2-Sl~OSO 11548*CBM*089A 1 OF 3 C-4 CHECK VALVE 10.00 2 C oc

  • CV 21

_ 2.00 2 C 0 CV

*-----------------------*--------------------------------------------------------------------------*

2*Sl*OS6 11548*CBM*089A 1 OF 3 B-7 CHECK VALVE 12.00 2 C 0 CV 20 "A" LOW HEAD SI PUMP SUCTION CHECK VALVE FROM CONTAINMENT SUMP 2-Sl-061 11548*CBM*089A 2 OF 3 8*5 CHECK VALVE 2.00 2 C 0 CV "A" LO'J.HEAD SI PUMP MINIMUM FLOW/TEST LINE DISCHARGE CHECK VALVE 2*Sl*073 11548*CBM*089A. 2 OF 3 E*7 MAN GLOBE 0.75 2 AE C CIV LT ACCUMULATOR TEST LINE, OUTSIDE CONTAINMENT ISOLATION VALVE 2-SI -079 - 11548*CBM*089B 4*0F 4 F-7 CHECK VALVE 6.00 1 AC OC PIV CV 27 LT RC_S COLD LEG SI ADMISSION CHECK VALVE

  • VIRGINIA POWER COMPANY PAGE: 46 OF 63 SURRY UNIT 2 . REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASHE TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC-2-SI-082 11548-CBM-089B 4 OF 4 E-7 CHECK VALVE 6.00 AC oc PIV CV 27 LT

RCS COLD LEG SI ADMISSION CHECK VALVE 2-SI-085 11548-CBM-089B 4 OF 4. D-7 CHECK VALVE 6.00 AC OC PIV CV 27 LT RCS COLD LEG SI ADMISSION CHECK VALVE

*-----------------------------------------------------------------------------------*-**--*

2-SI-088 11548-CBM-089B 4 Of 4 D-7 CHECK VALVE 6.00 C OC CV 27 1

RCS HOT LEG SI ADMISSION CHECK VALVE I

2-SI-091 11548-CBM-089B 4 OF 4 C-7 CHECK VALVE 6.00 C oc CV 27 RCS HOT LEG SI ADMISSION CHECK VALVE 2-SI-094 . 11548-CBM-089B 4 OF 4 B-7 CHECK VALVE 6.00 C oc CV 27 RCS HOT LEG SI ADMISSION CHECK VALVE

C 0

oc CV CV 26 26 29 VALVE 2*SI-128 11548-CBM-089B 2 OF 4 B-6 CHECK VALVE 12.00 C 0 CV 26 11 811 ACCUMULATOR DISCHARGE CHECK VALVE 2-SI-130 11548-CBM-089B 2 OF 4 B-7 CHECK VALVE 12.00 C oc CV 26 29 11 8 11 ACCUMULATOR COLD LEG ADMISSION CHECK VALVE

*

2*SI*145 11548-CBM-089B 3 OF 4 B-5 CHECK VALVE 12.00

CV C 0 26 "C" ACCUMULATOR DISCHARGE CHECK VALVE "C" ACCUMULATOR COLD LEG ADMISSION CHECK VALVE

  • VIRGINIA POIJER COMPANY. PAGE: 47 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET . DRWG VALVE VALVE ASHE TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT pos TYPE TYPE V- CSV* VNC*

2-SI-150 11548-CBM*OS9A 3 OF 3 F-6 MAN GLOBE

  • 0.75 2 AE C CIV LT 39

BORON INJECTION TANK BYPASS LINE ISOLATION VALVE - TO RCS COLD LEG

2-SI-174 11548-CBM*089A. 3 OF 3 D-6 MAN GLOBE

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

0.75 2 AE C CIV LT 39 HIGH HEAD SAFETY INJECTION TO RCS

*-----------------------------------------------------------------------------------------------------------------

2-SI~201 11548-CBM-089A 1 OF 3 C-7 CHECK VALVE 0.75 2 C C CV RWST SUPPLY CHECK VALVE TO LHSI PUMP SEALS

. .

1154S*CBM-089A 1 OF 3 C-5. CHECK VALVE 0.75 2 CV 2-Sl-207 C. C RWST SUPPLY CHECK VALVE TO LHSI PUMP SEALS

*---------------------

. 27 2-Sl *224 11548-CBM-089B 4 OF 4 F-3 CHECK VALVE 3.00 .2 C 0 CV HIGH HEAD SI FROM CHARGING PUMPS TO.RCS COLD LEGS, INSIDE CONT CHECK VALVE 2-Sl-225 11548-CBM-089B 4 OF 4 E-3 CHECK VALVE 3.00 2 C 0 CV 27.

  • 2-Sl-226 HIGH HEAD SI FROM.CHARGING* PUMPS TO RCS COLD.

LEGS, INSIDE CONT CHECK VALVE

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

1154S*CBM-089B 4 OF 4 C-3 CHECK VALVE HIGH HEAD SI FROM CHARGING PUMPS TO RCS HOT LEGS, INSIDE CONT CHECK VALVE 3.00 2 C 0 CV 27

  • -------------

2-Sl-227 11548-CBM*OS9B 4 OF 4 C-3 CHECK VALVE 3.00 2 C 0 CV 27 HIGH HEAD SI FROM CHARGING PUMPS TO RCS HOT LEGS, INSIDE CONT CHECK VALVE 2-Sl-228 11548-CBM*OS9B 4 OF 4 B-3 CHECK VALVE 6.00 2 C 0 CV 27 LOW HEAD SI FROM LHSI PUMP TO RCS HOT LEGS, INSIDE CONT CHECK VA~VE 2-SI-229 11548-CBM-089B 4 OF 4 B-3 CHECK VALVE 6.00 2 C 0 CV 27 LOW HEAD SI FROM LHSI PUMP TO RCS HOT LEGS, INSIDE CONT CHECK VALVE 2:;;:23s*---*-*--;;s4~:~;~:c;~9;** -4*c;;*4 ** ;:;** ~~~~~-~~~~~--- -***2:c;c;** -------- ---*c;*-----------~~-----*2;*------------- I .*

~

HIGH HEAD SI TO RCS COLD LEG, INSIDE MISS.ILE BARRIER CHECK VALVE .

2-Sl-236 11548-CBM-089B 4 OF 4 E-7 CHECK VALVE 2.00 C 0 CV 27 HIGH HEAD SI TO RCS COLD LEG, INSIDE MISSILE BARRIER CHECK VALVE

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

  • VIRGINIA POWER COMPANY PAGE: 48 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT

-VALVE DRAWING SHEET DRWG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE V- CSV- VNC-2-SI-237 11548*CBM-089B 4 OF 4 D*7 CHECK-VALVE 2.00 C 0 CV 27 HIGH HEAD SI TO RCS COLD LEG, INSIDE MISSILE BARRIER CHECK VALVE 2-SI-238 11548-CBH*089B 4 OF 4 D-7 CHECK VALVE 6.00 C OC CV 27 LOW HEAD SAFETY INJECTION SUPPLY CHECK VALVE TO RCS HOT LEG 2-Sl-239 11548-CBH-089B 4 OF 4 C-7 CHECK VALVE 6.00 C QC CV 27 LOW HEAD SAFETY INJECTION SUPPLY CHECK VALVE TO RCS HOT LEG

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

2-SI-240 11548-CBH-089B 4 OF 4 B-7 CHECK VALVE 6.00 c OC - CV 27 LOW HEAD SAFETY INJECTION SUPPLY CHECK VALVE TO RCS HOT LEG 2-SI-241 11548-CBH-089B 4 OF 4 F-7 CHECK VALVE 6.00 AC OC PIV CV 27 LT LOW HEAD SI TO RCS COLD LEG ISOLATION CHECK VALVE

. LT LOW.HEAD SI TO RCS COLD LEG ISOLATION CHECK VALVE 2-Sl-304 11548-CBH*089B 1 OF 4 F-3 CHECK VALVE 1.00 2 AC C CIV CV 44 LT NITROGEN SUPPLY TO ACCUMULATORS, INSIDE CONTAINMENT ISOLATION CHECK VALVE

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

2-SI-321 11548-CBM-.089A 1 OF 3 A-5 MAN GLOBE 0.75 2 AE C CIV LT 39 LOW HEAD SI FROM CHARGING HEADER TO RCS COLD LEGS, BYPASS LINE ISOLATION VALVE 2-SI *322 11548-CBM-089A 1 or 3 B-7 MAN GLOBE 0.75 2 AE C CIV LT 39 LOW HEAD SI FROM CHARGIN~ HEADER TO RCS COLD LEGS, BYPASS LINE ISOLATION VALVE 2-SI-327 . 11548-CBM-089A 1 OF 3 C-6 CHECK VALVE 10.00 2 C oc CV 21

* -------------------------------------

"A" LOW HEAD SI PUMP DISCHARGE CHECK VALVE

  • SURRY UNIT 2 REVISION: 03 SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL* COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE. ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE .CLASS CAT POS TYPE TYPE v- csv- VNC-2-Sl-400 11548-CBH-089A 1 OF 3 E-4 CHECK VALVE 10.00 2 C 0 CV 28

RWST SUPPLY CHECK VALVE TO CHARGING PUMP SUCTION HEADER

2-SI-MOV-2842 11548-CBH-089A 3 OF 3 D-7 MO GATE 3.Cio 2

  • -----------------.

EV 25

LT ST VP HIGH HEAD SI_ FROM CHARGING HEADER TO RCS COLD LEGS, OUTSIDE CONTAINMENT ISOLATION VALVE

                                                                                                                                          • ,****************************************** ***** r 2-SI-MOV-2860A 11548-CBM-089A 1 OF 3 B-7 MO GATE 12.00 2 A 0 CIV EV LT 39 ST VP

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

"A" LOW HEAD SI PUMP SUCTION ISOLATION FROM CONTAINMENT SUMP 2-SI-MOV-2860B 11548-CBM-089A 1 OF 3 B-5 MO GATE 12.00 2 A 0 CIV EV LT 39 ST VP

  • 11 B" LOW HEAD SI PUMP SUCTION ISOLATION FROM CONTAINMENT SUMP

.--

2-SI-MOV~2862A 11548-CBM-089A 1 OF 3 A-3 MO GATE 12.00 2 B C EV ST VP "A" LOW HEAD SI PUMP SUCTION FROM RWST 2-SI-MOV-2862B 11548-CBM-089A 1 OF 3 B-3 HO GATE 12.00 2 B C EV

.ST VP 11 611 LOW HEAD SI PUMP SUCTION FROM RWST

------------------------------------------------------------------------------------------------------------------

2-Sl*MOV*2863A 11548-CBM-089A 2 OF 3 C-5 HO GATE 8.00 2 B oc EV ST VP A LO',I HEAD SAFETY INJECTION PUMP SUPPLY .

11 11 ISOLATION TO CHARGING PUMPS

.

2*Sl*HOV*2863B 11548-CBH-089A 2 OF 3 D-3 MO GATE

8.00 2 B oc.-----------------------------------

EV ST VP "B" LOW HEAD SAFETY INJECTION PUMP SUPPLY ISOLATION TO CHARGING PUMPS

  • VIRGINIA POWER COMPANY PAGE: 50 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC-

---

2-SI-MOV-2864A 11548-CBM-089A 2 OF 3 0-6 MO GATE 10.00 2 B oc EV ST VP "A" LOW HEAD SI PUMP COLD LEG DISCHARGE STOP VALVE

2-Sl~MOV-2864B 11548-CBM-089A 2 OF 3 D-4 MO GATE 10.00 2 B oc EV ST VP "B" LOW HEAD SI PUMP COLD LEG DISCHARGE STOP VALV!;

2-SI-MOV-2B65A 11548-CBM-089B 1 OF 4 C-7 MO GATE 12.00 2 B oc EV ST VP "A" ACCUMULATOR DISCHARGE ISOLATION VALVE TO RCS COLD LEG 2:;;:;~~=2~~;;---;;;~~=~;;:~~~;---2-~;-~--~=~---;;-~;~------- --;2:~~---2------;----~~-----------~~---------------------- I ST VP "B" ACCUMULATOR DISCHARGE ISOLATION VALVE TO

  • RCS COLD LEG 2-SI-MOV-2865C 11548-CBM-089B 3 OF 4 C-5 MO GATE 12.00 2 B oc EV ST VP 11 C11 ACCUMULATOR DISCHARGE ISOLATION VALVE TO RCS COLD LEG 2-SI-MOV-2867C 11548-CBM-089A 3 OF 3 F-6 MO GATE 3.00 2 A .OC CIV EV 18 LT 39 ST VP BORON INJECTION TANK OUTLET TO RCS COLD LEG, OUTSIDE CONTAINMENT ISOLATION VALVE

* ------------------------------------------------

oc CIV 18 2-SI-MOV-28670 11548-CBM-089A 3 OF 3 E-6 MO GATE 3.00 2 A EV LT. 39 ST VP BORON INJECTION TANK OUTLET TO RCS COLD LEG, OUTSIDE CONTAINMENT ISOLATION VALVE 2-SI-MOV-2B69A 11548-CBM-089A 3 OF 3 C-7 MO GATE 3.00 2 A oc CIV EV 25 LT 39 ST VP HIGH HEAD SI FROM CHARGING HEADER TO RCS HOT LEGS, OUTSIDE CONTAINMENT ISOLATION VALVE

  • VIRGINIA POWER COMPANY PAGE: 51 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC-o 2-Sl*MOV-28698 11548-CBM-089A 3 OF 3 E-4 MO GATE 3.00 2 A oc CIV EV 25 LT ST VP HIGH HEAD SI FROH CHARGING HEADER TO RCS HOT LEGS, OUTSIDE CONTAINMENT ISOLATION VALVE 2-SI-MOV-2885A 11548-CBM-089A 2 OF 3 B-5 MO GATE 2.00 2 , B C EV ST VP "A" LOW HEAD SI PUMP MINIMUM FLOW/TEST LINE ISOLATION 2-SI-MOV*2885B 11548-CBM-089A 2 OF 3 B-4 MO GATE 2.00 2 B C EV ST VP 11 8" LOW HEAD SI PUMP MINIMUM FLOW/TEST LINE ISOLATION 2-SI-MOV-2885C 11548-CBM-089A 2 OF 3 B-4 MO GATE 2.00 2 B C EV ST VP
  • 11 811 LOW HEAD SI PUMP MINIMUM FLOW/TEST LINE ISOLATION 2*SI*MOV-2885D 11548-CBM-089A 2 OF 3 B-5 MO GATE 2.00 2 B C EV ST VP "A" LOW HEAD SI PUMP MINIMUM FLOW/TEST LINE ISOLATION

, .

2-S1*MOV-2890A 11548-CBM-089A 2 OF 3 C-7 MO GATE 10.00 2 A QC CIV EV LT ST VP "A" LOW HEAD SI PUMP HOT LEG DISCHARGE STOP

_VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2*Sl*MOV*2890B 11548-CBM-089A 2 OF 3 E-7 MO GATE 10.00 2 A QC CIV EV LT ST VP 8 LOW HEAD SI PUMP HOT LEG DISCHARGE STOP 11 11 VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2-SI-MOV-2890C 11548-CW4-089A 2 OF 3 D-7 MO GATE 10.00 2 A QC CIV EV 17 LT ST VP LOW HEAD SI PUMPS COLD LEG DISCHARGE STOP VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE

.----------------------------------------------.------------------------------------* --

VIRGINIA POWER COMPANY PAGE: 52 OF 63 SURRY UNIT 2 REVISION: 03

  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASHE TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE V* csv- VNC*

I

- .. --

2*Sl*RV-2845A 11548*CBM-089A 2 OF 3 E-6 RELIEF VALVE 1.00 2 C 0 SP

"A" LOW HEAD SI PUMP DISCHARGE RELIEF VALVE, RV DI SCHA.RGE TO SAFEGUARDS AREA SUMP 2*Sl*RV-2845B 11548-CBM-089A 2 OF 3 E-5 RELIEF VALVE 1.00. 2 C 0 SP LOW HEAD SI HEADER TO COLD.LEG RELIEF VALVE, RV DISCHARGE TO SAFEGUARDS AREA SUMP 2*Sl*RV*2845C 1154S*CBM*089A 2 OF 3 E-5 RELIEF VALVE 1.00 2 C 0 SP

  • 11 811 LOW HEAD SI PUMP DISCHARGE RELIEF VALVE,
  • RV DISCHARGE TO SAFEGUARDS AREA SUMP

*-------------

2*Sl*TV*200 11548*CBM*089A 3 OF 3* 8*7 AO GATE 1.00 2 A C CIV EV FS LT ST 34 VP NITROGEN SUPPLY TO ACCUMULATORS, OUTSIDE CONTAINMENT ISOLATION VALVE 2-Sl*TV*201A 11548-CBM*089B 1 OF 4 C*.3 AO GATE 1.00 2 A C CIV EV FS

INSIDE CONTAINMENT ISOLATION VALVE

* -------* ----------------.--------------------------* ----------------------------------------------------------

CIV *Ev

. 2*SI *TV*201B 11548*CBM*089B

  • 1 OF 4 B-2 AO GATE 1.00 2 A C FS LT ST 34 VP ACCUMULATORS TO WASTE GAS CHARCOAL FILTERS, OUTSIDE CONTAINMENT ISOLATION VALVE 2*Sl*TV-202A 11548*CBM*089k 1 OF 3 E*7 AO GATE 8.00 2 B 0 EV FS ST VP UNIT 1 RWST TO UNIT 2 RWST CROSS TIE

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

2*Sl*TV*202B 11548*CBM*089A 1 OF 3 E*7 AO GATE 8.00 2 B 0 EV FS

. ST VP UNIT 1 RWST TO UNIT 2 RWST CROSS TIE

~--

VIRGINIA POIJER COMPANY PAGE: 53 OF 63

  • SURRY UNIT 2 REVISION: 03 SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC-2*SS*TV-200A 11548-CBM-082A 2 OF 3 F-7 SO GATE <i.375 1 A C CIV EV FS LT ST 34 VP PRESSURIZER LIQUID SPACE SAMPLE LINE, INSIDE CONTAINMENT ISOLAllON VALVE

. ----------------------------------------------------------------------------. -------*------ -----------

2-SS-TV-200B 11548-CBM-082A 2 OF 3 F*6 SO GATE 0.375 A C CIV EV FS LT ST 34 VP PRESSURIZER LIQUID SPACE SAMPLE LINE, OUTSIDE CONTAINMENT ISOLATION VALVE 2-SS-TV-201A 11548-CBM-082A 2 OF 3 E-7 SO GATE 0.375 A C CIV EV FS LT ST 34 VP I

PRESSURIZER .VAPOR SPACE SAMPLE LINE, INSIDE

  • CONTAINMENT ISOLATION VALVE

* ------------------~-----------------------------------------------------~-----------------------------

2-SS*TV-201B

  • 11548-CBM-082A 2 OF 3 E-6 SO GATE 0.375 1 A C CIV EV FS LT ST 34 VP PRESSURIZER VAPOR SPACE SAMPLE LINE, OUTSIDE CONTAINMENT ISOL~TION VALVE 2-SS-TV-202A 11548-CBM-082A 2 OF 3 D-7 SO GATE 0.375 1. A C CIV EV FS

. LT ST 34 VP REACTOR COOLANT COLD LEGS SAMPLE HEADER, INSIDE CONTAINMENT ISOLATION VALVE 2*SS*TV*202B 11548-CBM-082A 2 OF 3 D-6 SO GATE 0.375 A C CIV EV FS LT ST 34 VP

* ----------

REACTOR COOLANT COLD LEGS SAMPLE HEADER, OUTSIDE CONTAINMENT ISOLATION VALVE RHR SAMPLE HEADER, INSIDE CONTAINMENT ISOLA*

TION VALVE

--

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

  • VIRGINIA POIJER COMPANY PAGE: 54 OF 63
  • SURRY UNIT 2 REVISION: 03 SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRIJG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC*

2-SS*TV-203B 11548*CBM*082A 2 OF 3 F-6 SO GATE 0.375 2 AE C CIV LT VP RHR SAMPLE HEADER, OUTSIDE CONTAINMENT ISOLA-TION VALVE 2-SS-TV-204A 11548*CBM*082A 2 OF 3 D-.7 SO GATE 0.375 2 A C CIV EV FS LT ST 34 VP PRESSURIZER RELIEF tANK GAS SPACE SAMPLE LINE, INSIDE CONTAINMENT ISOLATION VALVE

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

2*SS*TV-204B 11548*CBM-082A 2 OF 3 C-6 SO GATE 0.375 2 A C CIV EV FS LT ST 34 VP

. PRESSURIZER RELIEF TANK GAS SPACE SAMPLE LINE, OUTSIDE CONTAINMENT ISOLATION VALVE 2*SS*TV*206A 11548*CBM*082A 2 OF 3 E-7 SO GATE 0.375 A C CIV EV

  • FS LT ST 34 VP REACTOR COOLANT HOT LEGS SAMPLE HEADER, INSIDE CONTAINMENT ISOLATION VALVE 2*SS*TV*206B 11548-CBM*082A 2 OF 3 E-6 SO GATE 0.375 A C CIV EV FS LT '

ST 34 VP REACTOR COOLANT HOT LEGS SAMPLE HEADER, OUT*

SIDE CONTAINMENT ISOLATION VALVE

  • VIRGINIA POWER COMPANY PAGE: 55 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE. ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC-2-SV-TV-202A 11548-CBM-066A . 2 OF 3 E-4 AO GATE 6.00 2 A C CIV EV FS LT ST VP CONDENSER AIR REMOVAL DISCHARGE TO CONTAIN-MENT, OUTSIDE CONTAINMENT ISOLATION VALVE

.---------------------------* --------------------------------

  • VIRGINIA PQl,IER COMPANY PAGE: 56 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAYING SHEET DRYG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMaER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC-

--- ----

2-SW-108 11548-CBM-071B 1 OF 2 B-4 CHECK VALVE 2.00 3 C oc CV CHARGING PUMP SERVICE YATER PUMP CHECK VALVE 2-SW-113 11548-CBM-071B 1 OF 2 B-7 CHECK VALVE 2.00 3 C oc CV CHARGING PUMP SERVICE WATER PUMP CHECK VALVE 2-SY-130 11548-CBM-071B 1 OF 2 D-7 CHECK VALVE 2.00 3 C 0 CV CIRCULATING WATER TO DISCHARGE TUNNEL CHECK VALVE

* -------------*-------------------------------------------------- *-------------------------------

11548-CBM-071A 3 OF 3. E-8 MAN GATE 2-SY-206 2.00 2 AE C CIV LT CONTAINMENT ISOLATION VALVE FOR SERVICE YATER ORAi NS TO HEAT EXCHAIIGER

.

11548-CBM-071A 3 OF 3 E-8 MAN GATE

'

2-SY-208 2.00 2 AE C CIV LT CONTAINMENT ISOLATION VALVE FOR SERVICE YATER DRAINS TO HEAT EXCHANGER 2-SY-246 11548-CBM*071A 3 OF 3 D-8 CHECK VALVE 3.00 NC C 0 CV

  • 2-SY-247 RECIRCULATION SPRAY .HEAT EXCHANGER SERVICE YATER RETURN VENT VALVE 11548-CBM-071A 3 OF 3 D-7 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY VENT VALVE 3.00 3 C 0 CV 46 2-SY-248 11548-CBM*071A. 3 OF 3 D-7 CHECK VALVE 3.00 NC C 0 CV RECIRCULATION SPRAY HEAT EXCHANGER SERVICE YATER RETURN VENT VALVE

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

2-SY-249

~

11548-CBM-071A 3 OF 3 D-6 CHECK VALVE 3.00 3 C 0 CV 46

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

RECIRCULATION .SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY VENT VALVE 2-SY-250 11548-CBM-071A ~ OF 3 D-6 CHECK VALVE 3.00 NC C 0 CV RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER RETURN VENT VALVE

-- *-----------------------------------------------------------------------------------------------------------------------

2-SY-251 11548-CBM*071A 3*0F 3 D-6 CHECK. VALVE 3.00 3 C 0 CV 46 RECIRCULATION SPRAY HEAT EXCHANGER SERVICE

~ATER SUPPLY VENT VALVE

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

2-SW-252 11548-CBM-071A 3 OF 3 D-5 CHECK VALVE

  • -------------------------------------

3.00 NC C 0 CV RECIRCULATION SPRAY HEAT EXCHANGER SERVICE YATER RETURN VENT V~LVE

  • VIRGINIA POWER COMPANY PAGE: 57 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE V* csv- VNC*

2*SW*253 11548*CBM*071A 3 OF 3 D*S CHECK VALVE 3.00 3 C 0 CV 46

RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY VENT VALVE 2*SW*442 11548*CBM-071B 1 OF 2 B-4 CHECK VALVE 2.00 3 C 0 CV CHARGING PUMP SERVICE WATER PUMP DISCHARGE CHECK VALVE

*-----------------------------------------------------------------------------------------------------------~

2°SW*445 11548*CBM*071B 1 OF 2 8*6 CHECK VALVE 2.00 3 C 0 CV CHARGING PUMP SERVICE WATER PUMP DISCHARGE CHECK VALVE 2*SW-MOV*201A 11548-CBM*071A 3 OF 3 8*4 MO BFLY 36.00 3 B C EV ST VP BEARING COOLING WATER HEAT EXCHANGER

  • ISOLATION VALVE 2*SW*MOV*201B 11548*CBM*071A 3,0F 3 B-4 MO BFLY 36.00 3 B C EV ST VP
  • BEARING COOLING WATER HEAT EXCHANGER ISOLATION VALVE 2-SW*MOV*202A 11548*CBM*071A 2 OF 3 D*6 MO BFLY 42.00 3 B C EV ST VP SERVICE WATER HEADER SUPPLY ISOLATION TO COMPONENT COOLING HEAT EXCHANGERS

,

2*S\J*MOV*202B 11548*CBM*071A 2 OF 3 D*S MO BFLY

*

42.00 3 B C

EV ST VP SERVICE WATER HEADER SUPPLY ISOLATION TO COMPONENT COOLING HEAT EXCHANGERS 2*SW*MOV*203A 11548*CBM-071A 3 OF 3 8*8 MO BFLY 30.00 3 B 0 EV ST VP

* ---

SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS

2*SW*MOV*203B 11548*CBM*071A 3 OF 3 B*B MO BFLY* 30.00 3 B 0 EV ST VP SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS

  • SURRY UNIT 2 REVISION: 03 SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- . VNC-
  • 2-SW-MOV-203C 1154S-CBM-071A 3 OF 3 B-3 MO BFLY 30.00 3 B 0 EV ST VP SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 2-SW-HOV-203D 1154S-CBM-.071A 3 OF 3 B-2 MO BFLY 30.00 3 B 0 EV ST VP SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 2-SW-HOV-204A 1154S-CBM-071A 3 OF 3 D-7 MO BFLY 24.00 3 B QC EV ST VP SERVICE WATER SUPPLY TO 11 A11 RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE

QC EV

  • -------------------

2-SW-HOV-204B 1154S-CBH-071A 3 OF 3 D-6 MO BFLY 24.00 3 B ST VP

  • SERVICE WATER SUPPLY TO 11 B" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2-SW-HOV-204C 11548-CBM-071A 3 OF 3 D-5 MO BFLY 24.00 3 B oc EV ST VP SERVICE WATER SUPPLY TO "C" RECIRC SPRAY HEAT EXCHANGER, OUTSID.E CONT ISOLATION VALVE

*-----------------------

2-SW-HOV-204D 115~8-CBH-071A 3 OF 3 D-4 HO BFLY 24.00 3 B oc EV ST VP SERVICE WATER SUPPLY TO 110 11 RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2-SW-HOV-205A 11548-CBM-071A 3 OF 3 D-8 MO BFLY 24.00 3 B QC EV ST VP

. -----------, -------

SERVICE WATER RETURN FROM "Ai, RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2-SW-HOV-205B 11548-CBM-071A 3 OF 3 D-7 MO BFLY 24.00 3 B oc EV ST VP SERVICE WATER RETURN FROM "B" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE

  • SURRY UNIT 2 REVISION: 03 SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASHE TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC-2-SW*MOV-205C 11548-CBM~071A 3 OF 3 D-6 MO BFLY 24.00 3 B oc EV ST VP SERVICE lolATER RETURN FROM 11 C11 RECIRC SPRAY HEAT EXCHANGER,*OUTSIDE CONT ISOLATION VALVE 2-SW*MOV-205D 11548-CBM-071A 3-0F 3 D-5 MO BFLY 24.00 3 B oc EV ST VP SERVICE WATER RETURN FROM 110 11 RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2-SW*TCV-208A .11548-CBM-071B 1 OF 2 E-7 AO GATE 1.5 3 B 0 EV FS ST 47 SERVICE WATER TO CH.ARGING PUMP LUBE OIL COOLER TEMPERATURE CONTROL VALVE

*-----------------------------------------------------

2-SW-TCV-208B 11548-CBM-071B 1 OF 2 E-5 AO GATE 1.5 3 B 0 EV FS ST 47

  • VIRGINIA PO'JER COMPANY PAGE: 60 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL COLD ALT VALVE DRAIJING SHEET DRIJG VALVE VALVE ASME TEST VALVE TEST REC SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE V* CSV- VNC-2-VA-001 11548*CBM-083B 3 OF 3 F-3 MAN GATE 2.00 2
  • AE C CIV LT VENT LINE FROM PRIMARY VENT POT, OUTSIDE CONTAINMENT ISOLATION VALVE 2-VA-009 11548*CBM-083B 3 OF 3 F-4 MAN GATE 2.00 2 AE C CIV LT VENT LINE FROM PRIMARY VENT POT, INSIDE CONTAINMENT ISOLATION VALVE
  • VIRGINIA POWER COMPANY PAGE: 61 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT POS TYPE TYPE v- csv- VNC-2*VG*TV-209A 11548-CBH-083B 1 OF 3 E-3 AO GATE 2.00 2 A C CIV EV FS LT ST 34 VP VENT LINE !SOL FROM PRIMARY DRAINS TRANSFER TANK TO GAS STRIPPERS, INSIDE CONT !SOL VLV

* -----------

2*VG-TV-209B 11548-CBH-083A 2 OF 2 F-3 AO GATE 2.00 2 A C CIV EV FS LT ST 34 VP VENT LINE !SOL FROM PRIMARY DRAINS TRANSFER TANK TO GAS STRIPPERS, OUTSIDE CONT !SOL VLV

  • VIRGINIA POYER COMPANY PAGE: 62 OF 63 SURRY UNIT 2 REVISION: 03
  • SECOND INSPECTI~ INTERVAL DATE: 3/19/92 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASHE TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMF,ER COOR TYPE SIZE CLASS CAT POS TYPE TYPE V- - CSV* VNC*

1154S-CBM-066A 2 OF 3 F-4 CHECK VALVE 6.00 2 AC C CIV CV 44 LT

CONDENSER AIR REMOVAL DISCHARG TO CONTAINMENT INSIDE CONTAIN ISOLATION CHECK VALVE

-*

  • SURRY UNIT 2 REVISION: 03 SECOND INSPECTION INTERVAL DATE: 3/19/92 INSERVICE TESTING. PROGRAM - VALVE TABLE NC ISO REL COLD ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASHE TEST VALVE TEST REQ SHUT TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT PCS TYPE TYPE v- csv- VNC*

2-VS-HOV-200A 11548-CBB-006A 1 OF 2 C-7 MO BFLY 36.00 2 AE C CIV LT 39 VP CONTAINMENT PURGE SUPPLY, INSIDE CONTAINMENT ISOLATION VALVE 2-VS-HOV-200B 11548-CBB-006A 1 OF 2 C-8 MO BFLY 36.00 2 AE C CIV LT 39 VP CONTAINMENT PURGE SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 2-VS-HOV-200C 11548-CBB-006A 1 OF_2 D-7 MO BFLY 36.00 2 AE C CIV LT 39 VP CONTAINMENT PURGE EXHAUST, INSIDE CONTAINMENT ISOLATION VALVE 2-VS-HOV-2000 11548-CBB-006A 1 OF 2 D-8 MO BFLY 36.00 2 AE C

. CONTAINMENT PURGE EXHAUST, OUTSIDE CONTAIN-MENT ISOLATION VALVE 2-VS-HOV-201 11548*CBB-006A 1 OF 2 D-7 MO BFLY 8.00 2 AE C CIV LT 39

  • VP CONTAINMENT PURGE BYPASS, OUTSIDE CONTAINMENT ISOLATION VALVE

. 2-VS*HOV-202 11548-CBB-006A 1 OF 2 C-7 MO BFLY 18.00 2 AE C CIV LT 39 VP CONTAINMENT VACUUM BREAKER

  • 4.5 VALVE TEST PROGRAM RELIEF REQUEST Relief Requests identify code requirements which-are impractical for Surry Unit 2 _and provide justification for the requested exception. Where appropriate, alternate testing to be performed in lieu of code requirements is proposed .
  • System Valve(s):

Various RELIEF REQUEST V-1 All safety and relief valves category:

Class

  • Function:

Section XI Code Requirement For Which Relief Is Requested Safety and relief valve setpoints are tested in accordanc~ with PTC-25.3-1976 as directed by IWV..,;3512.

Basis For Request The American National Standard, ANSI/ASME OM 1981, Requirements for Inservice Performance Testing of Nuclear Power Plant Pressure Relief Devices, is approved for use in the 1986 Edition of ASME Section XI, Subsection IWV. OM-1.represents

  • current industry practices for tesiing relief valves and is a better standard for setpoint testing than PTC-25.3-1976.

Alternate Testing-Proposed Safety and relief valves will be tested in accordance with ANSI/ASME OM 1981 .

  • RELIEF REQUEST V-5 System Feedwater Valve(s): 2-FW-10 2-FW-41 2-FW-72 category: c Class 2 Function: Main Feedwater check valves at Containment Penetrations.

Section XI Code Requirement For Which Relief Is Requested Exercise valve every three months.

Basis For Request Clos.ure of these valves during power operation would require securing feedwater which would result in reactor trip. Cold

  • shutdown testing of valves using flow to verify closure is inconclusive due to the inability to establish adequate differential pressure across the valve disc.

A test was conducted in an effort to verify whether closure of these valves can be determined using flow. Because there is no isolation boundary between the steam generators and the valves, the test volume must include the steam generators. A steam generator was pressurized with a nitrogen blanket to approximately 5 psig. The 0.75 inch drain valve just upstream of the check valve was opened and flow was observed. The 14 inch check valve did not stop the back flow through the vent. It was concluded that the flow was inadequate to seat the check valve completely. Just a small gap between the disc and the seat was sufficient to create a flow area equa+ to or greater than the flow area through the drain. T}1erefore, the pressure differential associated with the back flow is being created across the drain valve and not the disc of the check valve.

The above test proved to be inconclusive because of the inability to establish a sufficient .differential pressure across the disc.

The only way to increase the differential pressure is to increase the flow area from the test volume. However, this is not*

achievable for the existing configuration. Immediately upstrea~

of the drain valve is another 14 inch check valve, so the only

  • available flow area from the test volume is the drain valve .

4-10 S2PV-5R3 Rev. 3 March 19, 1992

  • RELIEF REQUEST V-5 (Cont.)

Alternate Testing Proposed These valves will be grouped together and one valve from this group will be disassembled every reactor refueling. A different valve will be disassembled every reactor refueling .

  • RELIEF REQUEST V-6 Relief Request Withdrawn RELIEF REQUEST V-7 Replaced by Cold Shutdown CSV-5 RELIEF REQUEST V-8 Replaced by Cold Shutdown Justification CSV-6 RELIEF REQUEST V-9
  • system Valve(s}:

RELIEF REQUEST V-14 Chemical and Volume Control 2-CH-258 2-CH-267 2-CH-276 category: c Class  : 2 Function: Charging Pump Discharge Check Valve Section XI Code Requirement For Which Relief Is Requested Exercise valves every three moriths.

Basis- For Request With present plant design, these valves can only be partial stroke exercised during power operation because the charging .

pumps cannot achieve design accident flow when pumping into the

Alternate.Testing Proposed These valves will be partially stroked every three months and full flow tested each refueling .

-. S2PV-5R3 4-15 Rev. 3 March 19, 1992

  • system Valve(s): 2-SI-56

. RELIEF REQUEST V-2 0 Safety Injection 2-SI-47 category: c Class 2 Function: Low Head Safety Injection Pump suction from Containment Sump Check Valve Section XI Code Requirement .

For Which Relief Is Requested Exercise valves every three months.

Basis For Request To partial or full flow test these valves requires taking suction from the reactor containment sump which contains untreated water.

This water should not be introduced into the system.

~ Alternate Testing Proposed These valves will be grouped together and one valve from this group will be disassembled and inspected every reactor refueling.

A different valve will be disassembled every reactor refueling .

  • System Valve(s):

RELIEF REQUEST V-21 Safety Injection Valves affected by this request are identified in Table F.

Category:

Class Function:

Section XI Code Requirement For Which Relief Is Requested Exercise valves every three months.

Basis For Request These valves cannot be full stroke exercised during plant power operation. The only full flow path is into the Reactor Coolant System and Low Head Safety -Injection pumps cannot overcome Reactor Coolant System operating pressure. These valves will be

  • partially stroked every three months through the pump recirculation line. During cold shutdown, the Reactor Coolant System pressure still prevents full flow testing of the ch~ck valve. During cold* shutdown, the charging flow could cause an
  • overpressurization condition.

Testing valves 2-SI-50 and 327 to the closed position requires isolating.the suction lines to the low head safety injection pumps, venting on the upstream side of the valve being tested, starting the pump on the other path, checking for leakage and then repeating the process for the other valve. This test can take up to a hour to complete and places the unit into a LCO per Technical Specification 3.3 if performed during normal operation.

Alternate Testing Proposed These valves will be partially stroked every three months and full stroked every refueling.

Valves 2-SI-50 and 327 will be tested to the closed position every cold shutdown .

  • Valve RELIEF REQUEST V-21 (Cont.)

Category TABLE F Class Function 2-SI-46A,B C 2 Low Head Safety Injection Pump Suction from Refueling Water Storage Tank Check 2-SI-50 C 2 Low Head Safety Injection 2-SI-327 Pump Discharge Check

  • Relief Request Withdrawn
  • System Valve(s): 2-SI-107 RELIEF REQUEST V-26 Safety Injection 2-sI..:109 2-SI-128 2-SI-130 2-SI-145 2-SI-147 category: C Class 1 Function: Accumulator Discharge Check Section XI Code Requirement For Which Relief Is Requested Exercise valves every three months.

Basis For Request These valves cannot be partial or full flow tested during normal operation because the accumulator pressure (600 t9 650 psig) is below Reactor Coolant System pressure and the injection of

    • borated water would upset the reactor coolant chemistry. During cold shutdown, the RCS pressure still prevents full flow testing.

To achieve full flow*through the valves during reactor refueling, the accumulator would have to be discharged from an initial pressure of 600 psig. Discharging the accumulator from this pressure would stress the piping system and inject nitrogen into the RCS. *Nitrogen in the RCS has been linked to gas binding of the RHR pumps.

Alternate Testing Proposed To verify that these valves will stroke to the open position, they will be placed into two groups. Valves 2-SI-130 and 147 are in one group and.valves 2-SI-107, 109, 128 and 145 are in the other group. Because 2-SI-130 and 147 are downstream from where RHR connects to the SI line, they experience different service conditions than the other valves.

One valve from the group of four valves (2-SI-107, 109, 128 and 145) will be disassembled and inspected every refueling outage.

These valves will be partial flow tested every reactor refueling .

  • RELIEF REQUEST V-26 (Cont.)

Partial flow can be established through valves 2-SI-130 and 147 using RHR pump flow since these valves are downstream of where the two RHR lines discharge into the cold leg safety injection lines. Testing experience has shown that the flow from both RHR pumps can drive the disk of valves 2-SI-130 and 147 to the back seat. This impact event will be recorded using acoustic monitoring instrumentation for both valves each reactor refueling. The data will be analyzed to show that the disk struck the back seat, thus verifying that the disk stroked to the full open position *

  • System Valve(s):

RELIEF REQUEST V-27 Safety Injection Valves affected by this request are identified in*

Table G.

  • Category:

Class Functiqn:

Section XI Code Requirement For Which Relief Is Requested Exercise valves every three months.

Basis For Request The valves on the high head injection lines cannot be partial or full stroke exercised during power operation because flow through these valves would thermal shock the injection system and .cause unnecessary plant transients. *Flow cannot be established in the

  • low head injection lines during power operation. During cold shutdown,*the Reactor coolant System pressure still prevents full design flow. Also, a partial or full stroke test could cause an overpres~urization of the Reactor Coolant System and force a safety system to .function.

To verify closure, valves 2-SI-79, 82, 85, 241, 242 and 243 must be vented *upstream and a leakage test performed. Per Technical Specification Table 4.1-2A, periodic leakage testing on each valve shall be accomplished prior to entering power operation condition after each time the plant is placed in the cold shutdown condition for refueling and after each time the plant is placed in cold shutdown condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> *if testing has not been accomplished in the proceeding 9 months. No significant increase in safety will be realized by performing the leakage tests every cold shutdown.

Alternate Testing Proposed There is no installed instrumentation that can measure individual

.flow rates for valves 2~SI-79, 82, 85, 88, 91, 94, 238, 239, 240, 241, 242 and 243. Full flow through the hot leg safety injection valves (2-SI-88, 91, 94, 238, 239 and 240) will be verified using clamp on ultrasonic flow instrumentation .

  • RELIEF REQUEST V-27 (Cont.)

Using low head pump flow, the cold leg injection valves (2-SI-79, 82, 85, 241, 242 and 243) will be acoustically monitored for the disk striking the back seat every reactor refueling. The data will be analyzed to show that the disk struck the back seat, 'thus verifying that the disk stroked to the full open position.

Valves 2-SI-224, 225, 226, 227, 228, 229, 235, 236 and 237 will be full stroke exercised with flow every reactor refueling.

Valves 2-SI-79, 82, 85, 241, 242 and 243 will be tested to the closed position every reactor refueling per Technical Specification Table 4.1-2A.

Valves 2-SI-88, 91, 94, 238, 239 and 240 are confirmed closed by monitoring leakage from the Reactor Coolant System per Technical Specifications 3.1.C and 4.3. Individual valve verification to the closed position is not possible with the current line configurations.

The remaining valves need only to open .

  • Valve 2-SI-88, 91 2-SI-94, 238 Category C

TABLE G Class 1

Function Safety Injection to RCS Hot Legs 2-SI-239, 240 2-SI-235 C 1 High Head Safety Injection 2-SI-236 to RCS Cold Legs 2-SI-237 2-SI-241 AC 1 Low Head Safety Injection 2-SI-242 to RCS Cold Legs 2-SI-243 2-SI-224, 225 C 2 High Head Safety Injection 2-SI-226, 227 Check Valve at Containment Penetrations 2-SI-228, 229 C 2 Low Head Safety Injection Check Valves at Containment Penetrations

2-SI-79, 82, 85 AC i Safety Injection to RCS Cold Legs 4.:.23 S2PV-6R3 Rev. 3 April 15, 1992

  • system Valve(s): 2-SI-25 RELIEF REQUEST V-28 RWST Cross Tie 2-SI-400 Category: C Class 2 Function: Charging Pump Suction from RWST Cross Tie Section XI Code Requirement For Which Relief Is Requested Exercise valves for operability every three months.

Basis For Relief Exerci$ing these valves during power operation would require the charging pump suctions to be aligned with the refueling water storage tank. This would cause a sudden increase in reactor coolant boron inventory .

  • Full.flow for the charging system can only be established during reactor refueling when the RCS is depressurized.

Valve 2-SI-25 must close to preserve inventory from the Unit 1 RWST when *the cross tie lines are opened. There are no vents or pressure instrumentation upstream of the valve; therefore, the valve cannot be backseat tested with flow.

Alternate Testing Proposed These valves will partial flow tested during every cold shutdown and full flow tested during every reactor refueling.

Valve 2-SI-25 will be disassembled and inspected every other

.refueling outage to verify valve closure. Per the guidelines of Generic Letter 89-04, this valve is the only one in the sample group and is therefore subject to disassembly every outage.

However, disassembling this valve every outage represents excessive intrusive maintenance.* If inspection results indicate degradation, the disassembly interval will be increased t6 once every refueling outage .

  • System Valve(s):

RELIEF REQUEST V-31 Reactor Coolant 2-RC-SOV-200A-l

  • 2-RC-SOV-200A-2 2-RC-SOV-200B-1 2-RC-SOV-200B-2 Category: B Class 1 Function: Head Vent for Reactor Vessel Section XI Code Requirements For Which Relief Is Requested Exercise valves and perform fail-safe testing_ every three months.

Basis For Request These valves isolate the reactor vessel from containment

  • atmosphere. Partial or full stroke exercising the valves during normal operation or during cold shutdowns where the reactor coolant system is pressurized could result in the release of uncontrolled contamination to containment.

Alternate Testing Proposed Exercise for operability during cold shutdowns when the reactor coolant system is not pressurized (but not more frequently than once per three months) .

  • System Valve(s):

Various RELIEF REQUEST V-34 Valves affected by this request are identified in

  • Table J.

Category:

Class Function:

Section XI Code Requirement For Which Relief Is Requested Section XI, IWV-3417(a) "Corrective Action" Basis For Request These valves have a normal stroke time of 2 seconds or less; therefore, they could be considered rapid acting valves.

Alternate Testing Proposed

  • Whenever. the stroke time of these valves exceeds 2 seconds, IWV-3417(b) will be applied.

Note: The list of valves in Table J may change due to maintenance activities which affect valve performance. An updated list of rapid acting valves will be maintained by ISI site personnel .

  • Valve RELIEF REQUEST V-34 (Cont.)

Category TABLE J Class Function 2-MS-TV-210 B 2 Main steam Drain to Blowdown 2-CC-TV-207 B 3 Component Cooling from RCP 2-SS-TV-200.A,B A 1 *Pressurizer Liquid Space Sample 2-SS-TV-201A,B A 1 Pressurizer Vapor Space Sample 2-SS-TV-206A,B A 1 Primary Coolant Hot Leg Sample 2-SS-TV-202A,B A 1 Primary Coolant Cold Leg Sample 2-SS-TV-204A,B A 2 Pressurizer Relief Tank Gas

-Space Sample 2-DA-TV-200A,B A 2 Reactor Containment Sump Pump

  • 2-DA-TV-203A,B 2-VG-TV-209A,B A

A 2

2 Discharge Isolation Post Accident Sample Retµrn Line*

Gas Vent Header Isolation 2-LM-TV-200A-H A 2 Leakage Monitoring System Isolation 2~cv,;,_TV-250A-D A 2 Containment Vacuum Pump Suction Isolation 2-RC-PCV-2456 BC 1 Pressurizer Power Operated Relief Valve 2-RC-PCV-2455C BC 1 Pressurizer Power Operated Relief Valve 2-RC-SOV-200A-1,-2 B 1 Reactor Vessel Head Vent 2-RC-SOV-200B-1,-2

  • Valve RELIEF REQUEST V-34 (Cont.)

Category TABLE J Class Function 2-CH-TV-2204B A 2 RCS Letdown Isolation Trip Valves 2-GW-TV-200-207 A 2 Suction/Discharge Line to Hydrogen Analyzer 2-GW-TV-211A,B A 2 Containment Grab Sample 2-BD-TV-200A-F B 2 Steam Generator Blowdown Isolation 2-RM-TV-200A,B,C A 2 Isolation on Monitor Return Line 2-DG-TV-208B A 2 Primary Drain Transfer Pump Discharge Isolation 2-IA-TV-200 A 2 Instrument Air Supply to

  • Containment Isolation 2-IA-TV-201B A 2 Instrument Air Suction from Containment Isolation 2-SI-TV-200 A 2 Nitrogen Supply to Accumulators Containment Isolation 2-SI-TV-201B A 2 Accumulators to Waste Gas Charcoal Filters Containment Isolation
  • System  :

Valve (s) :.

EE 1-EE-SOV-102 RELIEF REQUEST V-36 1-EE-SOV-103 1-EE..;.SOV-104 Category: B Class NC Function: Diesel Fuel Oil Pump Discharge ValvesSection XI Code Requirement For Which Relief Is Requested Exercise valves for operability every three months.

Basis For Request These valves are small {l"), fast acting solenoid operated gate

  • valves with no position indication lights and no iocal visual means of determining stroke time. Valve operability can only be
  • indirectly observed by verifying system operability .

Also, these valves are interlocked with the pumps to open and close upon pump startup and shutdown.

Alternate Testing Proposed These solenoid valves will be stroke tested quarterly by observing that the solenoid valves perform their intended function (fuel oil is flowing to the day tank after the solenoid valve has been opened) .

  • RELIEF REQUEST V-37 system EG Valve(s) 2-EG-S0V-200A 2-EG-SOV-200B Category B Class NC Function: Diesel Air Start System Solenoid ValvesSection XI Code Requirement For Which Relief Is Requested Section XI, IWV-3413 "Power Operated Valves" Basis For Request These valves have actuation times considerably under a second and there is no visual reference on the solenoid valve when it has stroked; therefore, the stroke time cannot be measured.
  • Alternate Testing Proposed These solenoid valves will be stroke tested quarterly by observing that the solenoid valves perform their intended function, which is to start the diesel engines. Adequate performance of the valves will be verified by reco~ding the time it takes for the diesel engines to reach a predetermined RPM and comparing.the time to an acceptance criterion.

Also, the failure of these valves to open or close will promptly give a diesel engine trouble alarm. Further investigation would identify problems with the operability of these valves .

  • RELIEF REQUEST V-38 Relief Request Withdrawn

~ RELIEF REQUEST V-39 System Various Valve(s): Valves affected by this request are identified by Table K Category:

Class Function:

Section XI Code Requirement For Which Relief Is Requested Leakage rate measurements shall be compared with the permissible leakag~ rates specified by the plant owner for~ specific valve.

Basis For Request The piping configurations for some containment penetrations do not allow for the individual leakage testing of the containment isolation valves which isolate the penetrations.

  • Alternate Testing Proposed In cases where containment isolation valves cannot be individually leakage tested, the containment isolation valves are grouped based on the configuration restraints and the groups are assigned permissible leakages. The valve groups are subject to the acceptance criteria described in IWV-3426 and 3427 .

i

  • Valve RELIEF REQUEST V-39 (Cont.)

Category Table K Class Function 2-SI-150 AE 2 Boron Injection Tank 2-SI-MOV-2867C A Isolation 2-SI-MOV-2867D. A 2-SI-174 AE 2 High Head Safety Injection 2-SI-MOV-2869A A to Reactor Coolant System 2-SI-MOV-2860A .A 2 Low Head Safety Injection 2-SI-MOV-2860B Pump Suction from 2-SI-321, 322 AE Containment sump 2-IA-TV-200 A 2 Instrument Air Discharge 2-IA-704 AE to Containment 2-LM-TV-200A A 2 .Leakage Monitoring System 2-LM-TV-200C Isolation 2-LM-TV-200E 2-LM-TV-200G

  • 2--LM-TV-200B 2-LM-TV-200D 2-LM-TV-200F 2-LM-TV-200H A 2 Leakage Monitoring System Isolation 2-CS-MOV-201A A 2 Containment Spray Pump 2-CS-MOV-201B Discharge 2-CS-MOV-201C A 2 Containment Spray Pump 2-CS-MOV-201D Discharge**

2-RS-MOV-255A A 2 Recirculation Spray Pump 2-RS-MOV-255B Suction from Containment 2-RS-46, 53 AE Sump 2-VS-MOV-200C AE 2 Containment Purge Exhaust 2-VS-MOV-200D Isolation 2-VS-MOV-201

  • Valve RELIEF REQUEST V-39 (Cont.)

Category TABLE K Class Function 2-VS-MOV-200A AE 2 Containment Purge Supply 2-VS-MOV-200B Isolation 2-VS-MOV-202 2-RL-3 AE 2 Reactor Cavity 2-RL-5 Purification Return Line

___J

  • RELIEF REQUEST V-40 Relief Request Withdrawn
  • System Valve(s)

FW 2-FW-144 RELIEF REQUEST V-41 2-FW-159 2-FW-174 2-FW-148 2-FW-163 2-FW-178 Category C Class  : 3 Function Auxiliary Feedwater Pump Recirc Line and Pump Oil Cooler Check ValvesSection XI Code Requirement For Which Relief Is Requested Exercise valves for operability every three months.

Basis For Relief These check valves cannot be partial or full flow tested because instrumentation is not installed to measure flow or differential pressure. There is no other indirect means to verify full flow

  • for these valves with the current configuration .

Alternate Testing Proposed Valves 2-FW-144, 159, and 174 will be grouped together; valves 2-FW-148, 163, and 178 will be grouped-together and one valve from each group will be disassembled and inspected every reactor refueling: A different valve from each group will be disassembled every reactor refueling. These valves will be part stroke exercised every three months .

  • System Valve(s)

MS 2-MS-176 RELIEF REQUEST V-42 2-MS-178 2-MS-182 Category C Class 2 Function Main steam Header Supply Check Valves To Turbine Driven Auxiliary Feedwater Pump Section XI Code Requirement For Which Relief Is Requested Exercise valves for operability to the closed position every three months.

Basis For Relief These check valves cannot be exercised to the closed position

  • during normal operation because this test would require the venting of process steam while verifying the closed position.

Venting of process steam would endanger the test personnel.

Alternate Testing Proposed These valves will be grouped together and one valve from this group will be disassembled and inspected every reactor refueling~

A different valve will be disassembled every reactor refueling.

The valves will be full flow tested every three months .

  • system Valve(s):

cs 2-cs-104 RELIEF REQUEST V-43 2-cs~13 2-Rs-11 2-CS-105 2-CS-24 2-RS-17 Category: AC (2-CS-13,24 and 2-RS-11,17) and C (2-CS-104,105)

Class 2 Function: Containment Spray Pump Discharge Check ValvesSection XI Code Requirement For Which Relief Is Requested Exercise valves for operability every three months.

Basis For Relief These check valves cannot be partial or full *flow exercised during normal operation because this test would introduce containment spray to containment. These valves cannot be locally exercised during normal operation because they are located inside

  • containment .

These valves are located upstream of the spray nozzles. Fo.r valves 2-CS-13 and 24, and 2-RS-11 and 17, the only way to perform a test (partial open or closed) is to install a blank flange downstream and local!~ perform an partial open and close test using air. The small increase in safety gained by performing this test every cold shutdown does not justify the burden of installing the blank flange and locally back seat ,

testing the valves at the increased cold shutdown test frequency.

There are no blank flanges installed downstream for valves 2-CS-104 and 105. .Therefore, a back seat test or a partial open test cannot be performed on these valves with the current piping configuration. These valves have no external lever arms. The only means to exercise valves 2~CS-104 and 105 to the open and closed positions is by di~assembly.

Valves 2-CS-13 and 24, and 2-RS-11 and 17 do have weight-loaded lever arms, however, the weight position and lever arm angle are subject to adjustment to ensure that the valves open when a pressure differential using air is applie~ every 1S months as required by T. s. 4.5.C. Therefore, torque measurements would not be repeatable .

. I I

  • RELIEF REQUEST V-43 (Cont.)

Alternate Testing Proposed For testing to the open and closed positions, valves 2-CS-104 and 105 will be grouped together and one valve from the group will be disassembled and inspected every reactor refueling. A different valve will be disassembled every reactor refueling. A partial open test cannot be performed on valves 2-CS-104 and 105 with the current piping configuration.

For testing to-the full open position; valves 2-CS-13 and 24 will be grouped together; and valves 2-RS-11 and 17 will be grouped_

together and one valve from each group will be disassembled and inspected every reactor refueling. A different valve from each group will be disassembled every reactor refueling.

Technical Specifications Paragraph 4.5.C. requires verification that valves 2-CS-13 and 24, and 2-RS-11 and 17 open when the discharge line of the pump is pressurized with air and seat when a vacuum is applied. This test partially strokes the valves open . .Valves 2-CS-13 and 24, and 2-RS-11 and 17 are containment isolation valves and are tested to the closed position each refueling outage as part of the Appendix J leak testing program .

  • System Valve(s):

Various RELIEF REQUEST V-44 Valves affected by this justification are identified by Table L.

Category:

Class Function:

Section XI Code Requirement For Which Relief Is Requested Exercise valves for operability to the closed position every three months.

Basis For Relief These check valves must seat upon reversal of flow in order to fulfill their safety functions. The only way to verify closure is to perform a local leak rate/back pressure test. Since the

  • valves are located inside containment, they cannot be tested quarterly.

These valves are containment isolation valves and are subject to leak testing every reactor refueling outage per the requirements of the Appendix J leak testing program and Section XI IWV-3426 and 3427. The leak tests not only.verify that the valves close adequately as does a normal back pressure test, but the tests also reveal the condition of the valve seating surfaces. As required by IWV-3426 and IWV-3427, the leak tests include acceptance criteria for the maximum allowed leakage.

Performing a back seat test every cold shutdown does not provide enough increase in safety to justify the burden of back seat testing on a more frequent basis.

Alternate Testing Proposed Exercise to the closed position every reactor refueling .

  • Valve RELIEF REQUEST V-44 (Cont.)

Category TABLE L Class Function 2-IA-864 AC 2 Instrument Air Containment 2-IA-868 Isolation 2-RC-160 AC 2 Primary Grade Water to Pressurizer Relief Tank 2-RM-3 AC 2 Isolation on Monitor Return Line 2-SI-304 AC 2 Nitrogen Accumulators N2 Supply 2-VP-12 AC* 2 Condenser Air Removal Discharge to Containment

  • system Valve(s): 2-CC-94 RELIEF REQUEST V-45 Component Cooling 2-CC-555 2-CC-95 2-CC-556 2-CC-592 2-CC-55_7 Category: c Class 3 Function: Component Cooling Supply to RCP Thermal Barrier Isolation Section XI Code Requirement_

For Which Relief Is Requested Exercise valves for operability to the closed position every three months.

Basis For Relief These check valves must seat upon reversal of flow in order to

  • fulfill their safety function to prevent gross-leakage. For the following reasons, it is not practical to test the thermal barrier check valves quarterly or at cold shutdown:

1.) the valves are inside a locked radiation area located inside containmeDt; therefore, they are not accessible during normal operation, 2.) the valves are inaccessible for about 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after cold shutdown ~ue to deconta~ination activities which must be performed before entry intd the are~,

3.) the reactor cooling pump(s) may be running with the reactor cooling system temperature less than 200 OF if an RHR loop is unavailable (in this case the valves and thus cooling to the thermal barriers would normally not be isolated) and 4.) the valves have soft seats that are replaced every five years and using pressure to back seat these valves on the more frequent cold shutdown frequency may accelerate the degradation of the soft seats.

These valves will be exercised only during refueling outages because the small increase in safety gained by performing this

  • test every cold shutdown does not justify the burden of performing a local back pressure test.

4-45 S2PV-6R3 Rev. 3 March 19, 1992

  • RELIEF REQUEST V-45 (Cont.)

Alternate Testing Proposed Exercise to the closed position every reactor refueling *

March 19, 1992

  • system Valve(s): 2-SW-247

.RELIEF REQUEST V-46 Service Water 2-SW-251 2-SW-249 2-SW-253 category: C Class  : 3 Function: Recirculation Spray Heat Exchanger Service water Supply Vent ValvesSection XI Code Requirement For Which Relief Is Reguested Exercise valves for operability to the open position every three months.

Basis For Relief These check valves must open to provide an effective vent path to

.the recirculation spray heat exchangers is quickly.established .

There is no instrumentation to measure flow or differentail.

pressure across the valves. The valves are inaccessible and cannot be manually manipulated without disassembly. The valves can .be partial stroked open only when service water is sent through t~e recirculation spray heat exchangers. The recirculation spray heat exchangers are maintained dry to avoid fouling. With*the current piping configuration, there is no means to partial stroke test these valves without fouling the heat exchangers.

Alternate Testing Proposed These valves will be grouped together and one valve from this group will be disassembled and inspected every reactor refueling.

A different valve will be disassembled every reactor refueling .

  • System Valve(s):

Various RELIEF REQUEST V-47 Valves affected by this relief request are identified by Table M.

Category:

Class Function:

Section XI Code Requirement For Which Relief Is Requested IWV-3417(a) - If, for power operated valves, an increase in stroke time of 25% or more from the previous test for valves with full stroke time greater than 10 sec or 50% or more for valves with full stroke time less than or equal to 10 sec is observed, test frequency shall be increased to once each month until corrective action is taken.

Basis For Relief

  • The valves listed in Table M typically exhibit stroke time data scatter from test to test that exceeds the 25% and 50% required by IWV-3417(a). These valves .either have no remote indication and/or no remote control, or no remote open/close control, or the test requires that the power source be interrupted at the valve and not at the switch. Therefore, applying the r~quirements of IWV-3417(a) in these cases is not practical~

Valve 2-CC-LCV-201 maintains the water level in the seal cooling water tank for component cooling to charging pump cooling system.

Because this valve is being added to the IST Program, there is currently no stroke time data. However, this valve has no.remote indication or manual position switch. The valve can be exercised by manipulating the tank level signal and timed by locally observing stem movement. Differences in interpreting when the valve stem starts and stops will affect the repeatability of the stroke time measurements.

The position of valves 2-MS-RV-201A, Band c is controlled by a potentiometer. Although the valves have remote position _

indication, there is no open/closed switch. The speed at which the valve goes open or closed depends upon the speed at which the operator turns the potentiom~ter knob, which in turn affects the repeatability of the stroke time measurements .

  • RELIEF REQUEST v~47 (Cont.)

Valves 2-RH-FCV-2605 and 2-RH-HCV-2758 have no remote indication.

The stroke time is measured by locally.observing stem movement.

Differences in interpreting when the valve stem starts and stops affect the repeatability of the stroke time measurements.

Valves 2-SW-TCV-208A, Band C control the flow of service water to the charging pump lube oil coolers. Because these valves are being added to the IST Program, there is currently no stroke time data. However, there is no remote indication or manual position switch. Valve position is controlled by lube oil temperature.

The valves can be locally manipulated and timed by observing stem movement. Differences in interpreting when the valve stem starts and stops will affect the repeatabiiity of the stroke time measurements.

Alternate Testing Proposed Maximum .stroke times will be established in accordance with IWV-3417(b). However, the ranges described in IWV-3417(a) will not be applied .

  • Valve RELIEF REQUEST V-47 (Cont.)

Category TABLE M Class Function 2-CC-LCV-201 *B 3 Charging Pump Seal Cooling Surge Tank Level Control

.2-MS-RV-201A, B, C B 2 Main steam Header Discharge to Atmosphere PORV 2-RH-FCV-2605 B 2 RHR Heat Exchanger Bypass Flow Control Valve 2-RH-HCV-2758 B 2 .RHR Heat Exchanger Discharge Flow Control Valve 2-SW-TCV-208A,B,C B 3 Service Water to Charging Pump Lube Oil Cooler Temperatur~ Control Valves

  • INTERIM RELIEF REQUEST V-48 System Main* Steam Valve_(s): 2-MS-NRV-201A 2-MS-NRV-201B 2-MS-NRV-201C Category: C Class 2 Function: Main Steam Non-Return ValvesSection XI Code Requirement For Which Interim Relief Is Requested Exercise valve for operability to the closed position every three months.

Basis For Interim Relief These stop check valves ara currently verified closed by driving the stem down onto the disk using the motor ope~ator after the

  • main steam system has been isolated during plant shutdown. Full stroke or part stroke exercising of these valves during power

Closure testing of stop check valves was initially addressed in response to Question 25 in the original meeting minutes to Generic Letter 89-04. The question and response are as follows:

Question 25:

Previous to this, it was permissible to verify closure of stop check valves simply by operation of the stem ( shaft) . Is this acceptable instead of reverse flow testing?

Response

Verification of closure capability of stop check valves by using the handwheel meets the ASME Code requirements. This, however, is not the pref erred method of test. The NRC staff considers reverse flow testing to be a more reliable indication of valve operability .

  • INTERIM RELIEF REQUEST V-48 (Cont.)

However, Item c in the NRC letter dated September 26, 1991 entitled, "Supplement to Minutes of the Public Meetings on Generic Letter 89-04," provided the following revision to the Question 25 response:

If a prompt closure of these valves on cessation or reversal of flow is required to accomplish a safety-related function, closure must be verified by reve_rse flow testing or such other positive means as acoustic monitoring or radiography.

Surry Power station interpreted the original Question 25 response to mean that driving the stem down onto the disk is a valid ASME Code closure test for stop check valves. However, Item C in the revision to the Question 25 response indicates that this test method is not adequate and that reverse flow testing or some other positive means as described above be used.

It is not practical to perform a reverse flow test at power for the reason previously stated. It is not practical to perform a reverse flow test during shutdown because it would require that the valve stems remain in the open position during plant

  • shutdown. To ensure double valve isolation during a normal shutdown, the secondary plant piping is isolated from the steam source by driving the stem of the stop check valves onto the disk.

After the plant is shutdown, back seat testing these valves with air would require pressurizing over the disk to verify closure.

Given the.mass of the 30" diameter disk and the large volume of pipe involved,*lifting the disk off the seat to show free movement is not practicable. Disassembly and inspection or other visual inspection techniques would be meaningless because the disk could have been driven to the seat during normal shutdown; therefore, the inspection would not prove verification that the disk went freely to its seat after cessation of flow.

Another test method identified in Item C is radiography. This inspection technique suffers the same limitations as the visual inspection techniques discussed above. Also, given the size of these valves (30 11 nominal pipe size diameter) and internal surface irregularities, radiograph resolution would be poor.

The other test method identified in Item c is acoustic monitoring.* Virginia and Electric Power Company is reviewing in-house and vendor capabilities to acoustically monitor the valves.

during shutdown .

  • INTERIM RELIEF REQUEST V-48 (Cont.)

Interim Alternate ~esting Proposed During the Surry Unit 2, 1993 refueling outage, one or more test*

methods will be evaluated in the field to determine their practicality. If a test method, as described in Item C,* can be developed, it will be implemented at Surry Power Station Unit 2 during the next refueling outage following the Unit 2 1993 refueling outage.

Until the new test methods are implemented, Surry Power Station will continue to test these stop check valves to the closed position by driving the stem to the disk every cold shutdown.

This test will be adequate to demonstrate that the disk can be properly positioned on the seat.* Also, free movement of the disk from the seat to the full open position is demonstrated when steam flow is established in the mainsteam lines and 100% power is achieved .

(.

  • System Valve(s):

Various RELIEF REQUEST V-49 All Valves Subject to Appendix J Leakage Testing (Category A CIV Valves) category: A and AC Class  : Various Function: Limit Leakage to a Specific Maximum Amount Section XI Code Requirement For Which Relief Is Requested IWV-3427(b) - Specifies corrective actions in addition-to IWV-3427(a) for valve sizes of six inches and larger if a leakage rate exceeds the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate by 50%. Also, corrective actions are required if a projection based on thre.e or more tests indicates that the leakage rate of the next scheduled test will exceed the maximum permissible leakage rate by greater than 10%.

Basis For Relief Most valves that are leak rate tested are tested in the "as found" condition, subject to maintenance and retested in the !las left" condition. The valve maintenance is -performed on.a routine basis and it effectively resets the leakage to a small amount.

Therefore; basing corrective actions on previous test results or projections serves no useful function.

Alternate Testing Proposed.

The requirements of IWV-3427(a) will be applied; however, the requirements of IWV-3427(b) will not be implemented. The alternate testing presented in this Relief Request conforms to NRC Generic Letter 89-04, Attachment 1, Item 10 .

  • 4.6 VALVE TEST PROGRAM COLD SHUTDOWN JUSTIFICATION Section XI, Paragraphs IWV-3412 and IWV-3522 all---owfor the full stroke exercising of valves during Cold Shutdown (but not more frequently than every three months) if the valves cannot be exercised during normal operation. Therefore, no request for relief from

.testing every three months is necessary.

However, the code does require that these .valves be specifically id'entified by the owner. The cold shutdown justifications identify and provide the technical basis for valves exercised during cold shutdown but not during normal operation .

  • system Valve{s):

COLD SHUTDOWN JUSTIFICATION CSV-1 Main steam 2-MS-TV-201A 2-MS-TV-201B 2-MS-TV-201C Category: B Class 2 Function: Main Steam Line Trip Valves Cold Shutdown Justification Full stroke or part stroke exercising of these valves during power operation could result in a turbine and reactor trip.

Note: The technical specification acceptance* criteria are more limiting than the standard Section XI test criteria because the technical specification requires the measurement of elapsed time from the manual initiation of steam line isolation to initiation of main trip valve

    • motion {must be less than or equal to 4.0 seconds) and the measurement of elapsed time from full open to full closed

{must be less than or equal to 5.0 seconds). If either of the limiting times are exceeded, the valve fails the test.

Section XI requires the measurement of elapsed time from initiation of steam line isolation to full valve closure, which is a less conservative test .

  • System Valve(s):

COLD SHUTDOWN JUSTIFICATION CSV-4 Auxiliary Feedwater Valves affected by this justification are identified by Table A.

Category:

Class Function:

Cold Shutdown Justification Partial or full opening these valves during power operation .would introduce cold auxiliary feedwater to the. steam generators resulting in thermal stress and possible steam generator tube degradation.

To test valves 2-FW-142, 157 and 172 to the closed position, flow must be established to the steam generators in order to back seat the valves on the discharge side of the non-running pumps. This test would also introduce cold auxiliary feedwater to the steam

  • gerierators if performed during nor~al operation .

. 4-58 Rev. 3 March 19, 1992*

Category TABLE A Class Function 2-FW-27 C 2 Auxiliary Feedwater Header 2-FW-58 Check at Main Feedwater 2-FW-89 Header Valves 2-FW-131 C 2 Auxiliary Feedwater Header 2-FW-133 Check Valves at 2-FW-136 Containment Penetration 2-FW-138 2-FW-142 C 3 Auxiliary Feedwate:t Pump 2-FW-157 Discharge *Check Valves 2-FW-172 2-FW:-272 C 2 Check Valves at 2-FW-273 Containment Penetration (Cross-Connect for Unit 1 Aux. Feed. from Unit 2)

  • 2-FW-e305 C 2 Check Valves at 2-FW-306 Containment Penetration (Cross-Connect for Unit 1 Aux. Feed. from Unit 2)
  • system Valve(s):

COLD SHUTDOWN JUSTIFICATION CSV-5 Component Cooling Valves affected by this justifica~ion are identified by Table B Category:

Class Function:

Cold Shutdown Justification These valves are.located in the containment and may be normally open or closed depending on system lineup. A containment entry and manipulation of other system valves are necessary to test these valves to either the open or closed position. This is*

considered impractical during power operation.

  • TABLE B Valve Category Class Function 2-CC-176 C 3 Component Cooling to RHR 2-CC-177 Heat Exchanger Check Valves 2-CC-242 C 3 Component Cooling to 2-CC-233 Reactor Containment Air
  • 2-CC-224 Recirculation Coolers
  • system Valve (s) :

COLD SHUTDOWN JUSTIFICATION CSV-6 Component Cooling

.Valves affected by this justification are identified by Table C.

category:

Class

. Function:

Cold.Shutdown Justification To perform an operability or a fail-safe test, the component cooling lines must be isolated, thereby stopping the flow of cooling water to the Reactor Coolant Pumps. Loss of cooling water to these pumps can be damaging, even for short periods of time.

  • Valve 2-cc-1 Category C

TABLE C Class 3

Function Component Cooling to 2-CC-58 Reactor Coolant Pumps 2-CC-59 2-CC-TV-205A B 3 Component Cooling from 2-CC-TV-205B Reactor Coolant Pumps 2-CC-TV-205C

March 19, 1992

  • System Valve(s):

COLD SHUTDOWN JUSTIFICATION CSV-7 Reactor Coolant 2-RC-PCV-2456 2-RC-PCV-2455C Category: BC Class  : 1 Function: Pressurizer Power Operated Relief Valves Cold Shutdown Justification These pressurizer power operated relief valves have shown a high probability of sticking open while being exercised during power operation. Also, these valves are not required for overpressure protection unless the primary system temperature is under 350 degre~s F per Technical Specification Paragraph 3.1.G.1.b(3).

These valves will be tested on approach to Cold Shutdown and testing shall not be deferred .

4-62 Rev. 3 March 19, 1992

  • System Valve(s):

COLD SHUTDOWN JUSTIFICATION CSV-8 Residual Heat Removal 2-RH-5 2-RH-11 2-RH-47 Category: C Class 1 (2-RH-47), 2 (2-RH-5 and 11)

Function: RHR Pump Discharge Check Valve Cold* Shutdown Justification*

These valves can only be partial or full stroke exercised to the open position and verified closed during the testing of RHR pumps 2-RH-P-lA and lB (refer to Relief Request P-7). The low pressure pumps take suction.from and discharge to the reactor coolant system which operates at 2235 psig. This pressure is well above the operating pressure of the pumps; therefore, testing during normal operation is not possible .

  • System Valve(s):

COLD SHUTDOWN JUSTIFICATION CSV-9 Residual Heat Removal 2-RH-MOV-2700 2-RH-MOV-2701 category: B Class  : 1 Function: RHR suction form Reactor Coolant System Cold Shutdown Justification These valves are interlocked with Reactor Coolant System pressure such that the valves cannot be opened at elevated reactor coolant system pressure. Overpressurization of the suction line may cause a LOCA. The interlocks cannot be bypassed with normal control-circuits .

  • System Valve(s):

COLD SHUTDOWN JUSTIFICATION CSV-10 Residual Heat Removal 2-RH-MOV-2720A 2-RH-MOV-2720B Category: B Class 1 Function: RHR Discharge to Reactor Coolant System Cold Shutdown Justification With the MOV* shut and if its respective check valve is leaking, there is no way to determine whether or not an-overpressure condition exists before opening the MOV.

If the MOV was opened and an overpressure condition did exist between the MOV and the RCS, the primary pressure of 2235 psig will be released on the Residual Heat Removal System with a relief valve setting of 700 psig. This would be an unnecessary challenge to the Residual Heat *Removal System .

    • Since the MOV is also part of the discharge piping of an accumulator, there is a possibility of discharging an accu~ulator.

into the RHR system and disabling it. The accumulators are maintained at *pressure above the normal operating or shutdown pressure o_f the Residual Heat Removal System. Opening of these valves wo~ld dump accumulator water into the Residual Heat Removal System. This will dilute the boron concentration of the accumulator as well as lower its level and pressure, which is a violation of Technical Specifications .

  • System Valve(s):

COLD SHUTDOWN JUSTIFICATION CSV-11 Chemical and Volume Control 2-CH-LCV-2115C 2-CH-LCV-2115E Category: B Class  : 2 Function:* Charging Pump Suction from Volume Control Tanks Cold Shutdown Justification Partial or full stroke exercising these valves during power operation would require the charging pump suctions to be aligned with the refueling water storage tank. This would cause a sudden increase in Reactor Coolant System boron inventory, which would cause a plant transient .

Rev. 3 March 19, 1992

  • System Valve(s):

COLD SHUTDOWN JUSTIFICATION CSV-13 Chemical and Volume Control 2-CH-MOV-2381 Category: A Class 2

  • Function: Reactor Coolant Pump Seal Water Return Cold Shutdown Justification:

Closure of this valve with Reactor Coolant Pumps in operation will cause a loss of seal flow resulting in possible pump seal damage .

  • System Valve(s):

COLD SHUTDOWN JUSTIFICATION CSV-14 Residual Heat Removal 2-RH-FCV-2605 2-RH-HCV-2758 category: B Class 2 Function: Residual Heat Removal Exchanger flow control Cold Shutdown Justification These valves have no remot~ position indication and are located inside containment. The valves can only be exercised (partial or full stroke) and timed by locally observing stern movement.

Because a containment entry is required to perform the exercise and fail-safe tests, it will be conducted every cold shutdown .

    • -systein Valve(s):

COLD SHUTDOWN JUSTIFICATION CSV-15 Chemical and Volume Control 2-CH-TV-2204A 2-CH-LCV-2460A 2-CH-TV-2204B 2-CH-LCV-2460B category: A (2-CH-TV-2204A, B) and B {2-CH-LCV-2460A, B)

Class . . 1 {2-CH-LCV-2460A, B) and_ 2 (2-CH-TV-2204A, B)

Function: Reactor Coolant system Letdown Isolation Trip and Level Control Valves Cold Shutdown Justification Exercising these valves during power operation interrupts letdown flow from the reactor coola_nt system (RCS) to the volume control tank. If the valves should fail closed, reactor coolant inventory control would be lost.

  • The pressurizer level control program controls reactor coolant inventory by regulating the operation of the charging flow control valve so that the charging input flow to the RCS and

Also, exercising these valves during normal operation will interrupt letdown flow through the regenerative heat exchanger.

This flow interruption would allow a slug of relatively cool charging water to thermal shock the nozzle connecting the 3 11 charging line to the 27" loop 2 cold leg injection line.

The valve controllers do not allow for a part stroke exercise test .

  • System Valve(s):

COLD SHUTDOWN JUSTIFICATION CSV-16 Chemical and Volume Control 2-CH-MOV-2289A 2-CH-MOV-2289B Category: A (2-CH-MOV-2289A) and B (2-CH-MOV-2289B)

Class . 2 Function: Normal Charging Header Isolation Cold Shutdown Justification Failure of these valves*in the closed position during exercising would cause a loss of charging flow and could result in an inability to maintain reactor coolant inventory .

  • Syste~

Valve(s):

COLD SHUTDOWN JUSTIFICATION CSV-17 Safety Injection 2-SI-MOV-2890C Category: A Class  : 2 Function: Low Head Safety Injection to Reactor Coolant System Cold Legs Cold Shutdown Justification In accordance with Technical Specification 3.3.A.8, during power operation; the A.C. power shall be removed from 2-SI-MOV-2890C.

with the valve in the open position. If this valve was stroked during power operation and failed in the closed position, the Low Head Safety Injection System would be rendered inoperable .

I~

  • System Valve(s):

COLD SHUTDOWN JUSTIFICATION CSV-18 Safety Injection 2-SI-MOV-2867C 2-SI-MOV-2867D Category: A Class 2 Function: High Head Safety Injection Isolation Cold Shutdown Justification These valves cannot be partial or full stroke exercised during power operation. Opening these valves would allow excess charging flow into the Reactor Coolant System causing a reactivity transient .

l:".'!11

  • System Valve(s):

COLD SHUTDOWN JUSTIFICATION CSV-19 Chemical and Volume Control 2-CH-225 2-CH-228 2-CH-227 2-CH-229 2-CH-MOV-2350 Category: B (2-~H-MOV-2350, 2-CH-228) and C (2~CH-225,227,229)

Class 2 Function: Emergency and Manual Emergency Boration Line Isolation Valves Cold Shutdown Justification To achieve full flow through Check valves and 2-CH-225, 227 and 229, the boric acid transfer pumps must be set at high speed, which could inject enough boric acid into the reactor coolant system to cause a reactor power transient. Under.normal plant operating conditions or when the plant is shutdow~, yalve 2-CH-MOV-2350 can be full stroke exercised and valves 2-CH-225, 227

  • Low concentrations of boric acid occur* near the end of the fuel cycle.

Manual valve 2-CH-228 will be stroked open when the alternate boration path is established every cold shutdown. The increased level of safety gained be exercising this valve every quarter does not justify the added burden of performing a separate test just for the manual valve.

  • Valve 2-CH-MOV-2350 will be full stroke exercised and check valves 2-CH-225, 227 and 229 will be part stroked exercised every quarter during normal operation when the reactor coolant boric acid concentration is above 100 ppm. Check valves 2-CH-225, 227 and 229, and manual valve 2-CH-228 will be full stroked exercised every cold shutdown .
  • System Valve(s):

..

COLD SHUTDOWN JUSTIFICATION CSV-20 Chemical and Volume Control 2-CH-309 1 category: AC Class  : 2 Function: Normal Charging Isolation Check Valve Cold Shutdown Justification Closure testing of 1-CH-309 cannot be performed during power operation because the*test would interrupt the normal charging flow path .

  • System Valve(s):

COLD SHUTDOWN JUSTIFICATION CSV-21 steam Generator Blowdown 2-BD-TV-200A 2-BD-TV-200D 2-BD-TV-200B 2-BD-TV-200E 2-BD-TV-200C 2-BD-TV-200F Category: B Class  : 2 Function: steam Generator Blowdown Isolation Cold Shutdown Justification Closing these valves during power operation causes the downstream piping to become empty due to drainage and water flashing to steam. When the valves reopen, a flow surge could occur which automatically isolates the inner valves due to high flow. Then a

.containment entry is necessary to reset these valves and ~pon reopening the process may occur.again *

  • System Valve(s):

COLD SHUTDOWN JUSTIFICATION CSV-25 Safety Injection 2-SI-MOV-2842 2-SI-MOV-2869A 2-SI-MOV-2869B Category: A Class 2 Function: High Head Safety*Injection to reactor Coolant System Cold Shutdown Justification These.valves cannot ~e partial or full stroke exercised during power operation. Opening these valves would allow excess charging-flow into the Reactor Coolant System causing a reactivity transient and possible thermal shock to the High Head Safety _Injection System.

  • power operation ..
  • System Valve(s):

COLD SHUTDOWN JUSTIFICATION CSV-26 Component Cooling 2-CC-181 2-CC-185 Category: B (manual)

Class 3 Function: Component Cooling Supply/Return to/from RHR Heat Exchanger Isolation Valves Cold Shutdown Justification A containment entry is required to exercise these manual butterfly valves. Therefore, they will be exercised every cold shutdown .

'!

  • System Valve(s):

COLD SHUTDOWN JUSTIFICATION CSV-27 Component Cooling 2-CC-TV-207 2-CC-TV-220A 2-CC-TV-220B 2-CC-TV-220C category: B Class  : 3 Function: Component Cooling Return from Reactor Coolant Pump Thermal Barrier Isolation Valves Cold Shutdown Justification Exercising these valves during normal operation would isolate.*

component cooling water to the reactor coolant pump thermal barriers. Cooling water mµst be available to the reactor coolant pump thermal barriers when the reactor coolant system temperature is above 200 °F. Col°d shutdown is entered when the reactor

  • coolant system temperature drops below 200 °F. The valve controllers do not allow for a part stroke exercise test.

These valves will be full stroke tested every cold shutdown .

  • system Valve(s):

COLD SHUTDO~ JUSTIFICATION CSV-28 Feedwater 2-FW-FCV-2478 2-FW-FCV-255A 2-FW-FCV-2488 2-FW-FCV-255B 2-FW-FCV-2498 2-FW-FCV-255C Category: B Class  : NC Function: Main Feedwater Regulating and Regulating Bypass Isolation Valves Cold Shutdown Justification These valves are in positions required to sustain power operation. Full stroke exercising the valves would result in a reactor trip. The main feedwater regulating valves 2-FW-FCV-2478, 2488 and 2498 move during normal operation as they perform their regulating function. The bypass valves 2-FW-FCV-255A, B and C remain closed during power operation.

  • These valves will be part stroke exercised every three months and full stroke exercised every cold shutdown .
  • System V_alve (s):

COLD SHUTDOWN JUSTIFICATION CSV-29 Safety Injection 2-SI-109 2-SI-130 2-SI-147 Category: C Class 1 Function: SI Accumulator Discharge Isolation Check Valve Cold Shutdown Justification These check valves are located inside containment and are back seat tested using the installed sampling system. To ensure that all of the leakage that could pass by the check valves is collected, the accumulator discharge motor operated valves (2-SI-MOV-2865A, Band C) must be closed. However, these motor operated valves must be open and de-energized when the reactor coolant system pressure is above 1000 psig according to Technical

    • Specification Paragraph 3.3.A.10. Therefore, the accumulator check valves will be tested to the closed position every cold shutdown .
  • System Valve(s):

.

COLD SHUTDOWN JUSTIFICATION CSV-30 Component Cooling 2-CC-806 category: C Class 3 Function: Charging Pump Seal Cooling Surge Tank Makeup Valve Cold Shutdown Justification This valve must open to provide a flow path from the component cooling water system to the charging pump seal water surge tank as a supply of makeup water to the surge tank.* There is no flow instrumentation to verify partial or full flow for the check valve.

There is level instrumentation on the surge tank. The surge tank can be isolated, dr,ained down and refilled. However, the surge tank provides the NPSH for the charging pump cooling water pumps and it should not be isolated from the system during normal

  • operation when component cooling.water for the charging pumps is required.

This valve will be tested to the full open position every cold shutdown .

  • System Valve(s):

COLD SHUTDOWN JUSTIFICATION CSV-31 Component Cooling 2-CC-LCV-201 Category: B Class 3 Function: Charging Pump Seal Cooling Surge Tank Level Control Valve Cold Shutdown Justification This valve must open to maintain the level in the charging.pump seal water surge tank and must close to prevent overflowing the surge tank and potentially draining the surge tank through the over flow line. The valve fails closed on lose of operating air.

Valve position is determine solely from tank level. In order to manipulate the valve for testing, the surge tank must be isolated. However, the surge tank providei the NPSH for the charging pump cooling water pumps and it should not be isolated

  • from the system during normal operation when component cooling water for the charging pumps is required.

This valve will be exercise to the open_and closed positions every cold shutdown .

  • 4.7 ALTERNATIVE TESTING FOR NON-CODE VALVES According to the minutes of public meeting on Gen~-c Letter 89-04, "Paragraph (g) of 10CFR 50.55a requires the use of Section XI of the-ASME Code for inservice testing of components covered by the Code. For other components important to safety, the licensee also has the burden of demonstrating their continued operability." The minutes go on to state that, "The Code-required IST program is a reasonable vehicle to provide a periodic demonstration of the operability of pumps and valves not covere4 by the Code. If non-Code components are included in the ASME Code IST program (or some other licensee-developed inservice testing program) and certain Code provisions cannot be met, the Commission regulations (10 CFR 50.55a) do not require a

'request for relief' to be submitted to the staff.

Nevertheless, documentation that provides assurance. of the continued operability of the non-Code components through the performed tests should be available at the plant site." Non-Code components are components that are important to safety but are not in systems or portions of systems that are classified ASME Class 1, 2 or 3.

  • Surry Power Station*has elected to include certain non-Code components in the ASME IST program. Where the Code provisions cannot be met for non-Code components, alternative testing is performed that is adequate to ensure continued operability. The alternate testing is described in this section. There may be other deviations from Code provisions that are not described
  • in this section. For these cases, documentation is available at the plant site.

As indicated in the minutes of public,meeting on Generic Letter 89-04, a 'request for relief' need not be submitted for non-Code components. Therefore, the alternative tests described in this section are not

'requests for relief' but are provided for information.

The procedure of providing alternative testing descriptions instead of requests for relief for non-Code components begins with Revision 3. Requests for relief that were approved by the NRC in Revision 2 for non-Code components will remai~ in place .

  • System Valve(s):

NON-CODE ALTERNATIVE TESTING VNC-1 Instrument Air 2-IA-381 2-IA-396 2-IA-384 2-IA-947 2-IA-395 2-IA-948 category: c Class NC Function: Bottled Air system Supply/Isolation Section XI Code Requirements Which Cannot Be Met Measure flow to verify full stroke.

Exercise valves every three months.

Basis For Alternate Testing

  • Valves 2-IA-381-, 384 and 947 must close to ensure that bottled air is available to actuate the.main valves (2-RC-PCV~2455C, 2-RC-PCV-2456 1 and 2-MS-SOV-202A and B). Valves 2-IA-395, 396 and 948. must open to allow bottled air to reach the main valves.

There is no direct means to measure the flow of air through the check valves.

However, after the instrument air system is isolated and the lines vented, the stroke times of the main valves are measured and compared to acceptance criteria. Measuring the stroke times provides indirect eVidence that valves 2-IA-395, 396 and 948 open properly and that valves 2-IA-381, 384 and 947 close properly.

The performance of this test renders the main valves inoperable; therefore~ the tests cannot be performed during normal operation.

After stroking the main valves with the air bottles, the air bottles must be replaced. The safety gained in testing the valves every cold shutdown versus every reactor refueling does not justify the burden of replacing the air bottles on the more frequent basis .

  • NON-CODE ALTERNATIVE TESTING VNC-1 (Cont.)

Alternative Testing Valves 2-IA-381, 384 and 947 will be tested closed and valves 2-IA-395, 396 and 948 will be tested open by isolating and venting the instrument air lines, and then stroking the main valves with the bottled air. fhe stroke times of the main valves will be measured and compared to acceptance criteria. This test will be performed every reactor refueling .

  • System Valve(s):

NON-CODE ALTERNATIVE TESTING VNC-2 Circulating Water 2-CW-117 Category: B (manual)

Class  : NC Function: Discharge Tunnel Vent Valve Section XI Code Requirements Which Cannot Be Met Exercise valve every three months.

Basis For Alternate Testing This valve is located on a line. from the discharge tunnel to the discharge canal. The valve is opened.following*the initiation of an event to reduce the vacuum in the discharge tunnel which reduces the flow rate through the essential heat exchangers. By

  • reducing the flow rater cooling water in~entory is conserved in the intake canal. Full or partial opening of this valve during normal operation or during cold shutdown will reduce cooling to the component cooling system and the bearing cooling system which will disrupt plant operations.

Alternative Testing This valve will be exercised every reactor refueling .

  • System Valve(s):

NON-CODE ALTERNATIVE TESTING VNC-3 Emergency Generator 2-EG-43 2-EG-45 2-EG-44 2-EG-46 Category: B (2-EG-43,44)

C (2-EG-45,46)

Class  : NC*

Function: 2-EG-43,44 EOG Starting Air/Drive Air Control/Relay Valves 2-EG-45,46 EOG Air start Pressure Equalizing Check Valves Section Xi Code Requirements Which cannot Be Met For valves 2-EG-43,44, measure stroke time.

For valves 2-EG-45,46, measure flow to verify full open

  • Basis For Alternate Testing Valves 2-EG-43 and 44 are air pilot valves that open to supply drive air to the EDG air starting motors. These valves have actuation times considerably under a second and there is no visual reference on the valve to observe the stroke; therefore, the stroke time cannot be measured.

Valves 2-EG-45 and 46 are check valves that close to prevent opening the air start valves before the air motor pinion gears are fully engaged. They open to ensure that the air motor pinions remain engaged (hold-in feature) when the air motors are operating. The only indication of the proper operation of the check valves is the proper operation of the pinion gears. The.

air pilot valves and the check valves work in concert with the air start solenoid valves to start the emergency diesels upon demand within the required time. *

  • NON-CODE ALTERNATIVE TESTING VNC-3 (Cont.)

Alternative Testing These valves will be stroke tested quarterly by observing that the valves perform their intended function, which is to start the diesel engines. Adequate performance of the valves will be verified by recording the time it takes for the diesel engines to reach a predetermined RPM and comparing the time to an acceptance criterion.

Also, the failure of these valves to perform will promptly give a diesel engine trouble alarm. Further investigation would identify problems with the operability of these valves .

  • 5.0 REPORTING OF INSERVICE TEST RESULTS 5.1 PUMP INSERVICE PROGRAM Records of Pump Inservice Tes*t Results will be in accordance with the intent of Article IWP~6000. Files will be established for each pump and will include:
1) Pump identification by equipment number, manufacturer and serial number.
2) The record of test shall include:

a) date of test, b) measured and observed quantities, c) identification of instruments used, d) comparison with allowable ranges of test valves and analysis of deviations, e) requirements for corrective actions, and f) conducting and analyzing the test

3) Inservice test plans. ~his may be by surveillance test procedure by which the pump is tested with reference drawing.
  • 4) summaries of corrective action some by maintenance report_ number, etc.

The Pump Inservice Test Program, associated surveillance test procedures and results will be kept at Surry Power Station. They will be available for audit by the Authorized Nuclear Inservice Inspector and

  • the NRC.

5.2 VALVE INSERVICE PROGRAM Records of Valve Inservice Test Results will be in accordance with the intent of Article IWV-6000, files will be established for each valve and will include:

1) Valve identification by equipment number, manufacturer, size, valve type, actuator type.
2) The record of test*shall include:

a) date of test, b) measured and observes quantities where applicable, c) identification of instruments used where

' March 19, 1992

  • .d) e)

f) comparisons with allowable ranges of test valves and analysis of deviations, maintenance history, and signature of the person or persons responsible for conducting and analyzing the test.

3) summaries of maintenance history may be maintenance report numbers, etc.

The Valve Inservice Test Program, associated surveillance test procedures and results will be kept at Surry Power station. They will be available for audit by the Authorized Nuclear*

Inservice Inspector and the NRC. *

March 19, 1992

  • 6.0 QUALITY ASSURANCE PROGRAM The Pump and Valve Inservice Test Program activities will be conducted in accordance with the Nuclear Operat~ons Department Standards Manual and Technical Specifications for Surry Power Station .
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