ML18011A111

Rev 8 of ISI Program ISI-203, ASME Section XI Pump & Valve Program Plan.

ML18011A111
Person / Time
Site:	Harris
Issue date:	07/07/1993
From:	Woods L CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18011A110	List: ML18011A109 ML18011A111
References
ISI-203, NUDOCS 9308300356
Download: ML18011A111 (246)

Text

Osl CAROLINA POWER & LIGHT COMPANY

'HEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 6 PART 7 PROCEDURE TYPE: Inservice Inspection Program (ISI)

NUMBER: ISI-203 TITLE: ASME Section XI Pump and Valve Program Plan REVISION 8 NOTE: This procedure has been screened in accordance with PLP-100 criteria and determined to be a Case III procedure. No additional management involvement is required.

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TITLE: MANAGER - TECHNICAL SUPPORT JUL 0 9 1993 DOCUMENT CONTROL Page 1 of 228

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OS1 Table of Contents Section ~Pa e 1.0 PURPOSE

2.0 REFERENCES

3.0 RESPONSIBILITIES 4.0 DEFINITIONS/ABBREVIATIONS 10 5.0 PROCEDURE 10 5.1 Definitions 10 5.2 General Relief Requests for Pumps 5.3 General Relief Requests for Valves 5.4 Inservice Pump Test Program 12 5.4.1 Introduction 12 5.4.2 Pump IST Program Plan Concept,. 12 5.4.3 Code Interpretation . 13 5.4.4 Pump List 15 5.4.5 Pump Table Nomenclature ~ ~ 15 5.4.6 Pump Test Table Notes 16 5.4.7 Pump Test Table 17 5.4.8 Pump Relief Request 18 5.5 Inservice Valve Test Program 23 5.5.1 Introduction 23 5.5.2 Valve IST Program Plan Concept 23 5.5.3 Code Interpretation 23 5.5.4 Valve Table Nomencl'ature 30 5.5.5 Valve Test Table Format 3'3 5.6 Valve Test Tables and Relief Reques ts 35 5 . 6 . 1 Containment HVAC .36 5.6.2 Reactor Auxiliary Building (RAB) HVAC 41 5.6.3 Control Room HVAC 44 5.6.4 Fuel Building HVAC 48 5.6.5 Switchgear and Protection Room HVAC 51 5 '.6 Main Steam 54 5.6.7 Feedwater 63 5.6.8 Auxiliary Feedwater 67 5.6.9 Condensate 81 ISI-203 Rev. 8 Page 2 of 228

OS1 Table of Contents (continued)

Section ~Pa e 5.6.10 Service Water 86 5.6.11 Containment Spray 94 5.6.12 Steam Generator Blowdown 100 5.6.13 Process Sampling 103 5.6.14 Diesel Generator Fuel Oil Transfer 108 5.6.15 Radiation Monitor and Hydrogen Analyzer 112 5.6.16 Diesel Generator Air Start 116 5.6.17 Demineralized Water 119 5.6.18 Containment Sump Drains 123 5.6.19 Service Air . . . . . . . . . . . . . . . . . . . 126 5.6.20 Instrument Air 130 5.6.21 Fuel Pool Cooling 137 5.6.22 Emergency Screen Wash 141

~ 5.6.23 Fire Protection . 144 5.6.24 Essential Chilled Water 148 5.6.25 Reactor Coolant 154 5.6.26 Chemical and Volume Control 163 5.6.27 Safety Injection 187 5.6.28 Containment Waste Processing 201 5.6.29 Component Cooling Water 204 5.6.30 Residual Heat Removal 216 Containment Integrated Leakage Detection l'.6.31 221 5.7 Test Data Processing '24 5.7.1 Software 224 5.7.2 Testing Procedures 224 5'.7.3 Data Entry, Trending, and Detection of Deviations OSTs 224 5.7.4 Deviation Tracking and Notification 225 5.7.5 Deviation Resolution and Close Out 225 6.0 DIAGRAMS/ATTACHMENTS 225 Attachment 6.1 - Pump/Valve Test Deviation Record 226 Attachment 6.2 - Pump Baseline Record 227 Attachment 6.3 - Test Data Processing Flow Chart 228 ISI-203 Rev. 8 Page 3 of 228

OS1 List of Effective Pa es

~Pa e Revision 1 - 228 ISI-203 Rev. 8 Page 4 of 228

OS1 1.0 PURPOSE 1.1 Introduction This document presents'he Program Plan for Inservice Testing (IST) of pumps and valves at the Shearon Harris Nuclear Power Plant (SHNPP) in compliance with the requirements of 10CFR50.55a. 10CFR50.55a(g) specified that the Section XI Pump and Valve Inservice Testing Program shall be initiated at the start of commercial operation of the facility. Further, the Program Plan must conform to the requirements of the Code edition and addenda in effect no more than twelve months prior to the date of issuance of the operating license.

This program plan has been prepared to the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, Subsections IWP and IWV, 1983 Edition through the Summer 1983 Addenda.

This plan updated will then for be in effect for. the first 120 month interval. It each subsequent 120-month interval to conform to the Code Edition will be and Addenda in effect no more than twelve months prior to the start of the interval.

1.2 Basis In addition to the reference Code Edition and Addenda, these Program Plans have been prepared in compliance with the NRC guidance contained in "Guidance for Preparing Pump and Valve Testing Program Descriptions and Associated Relief Requests Pursuant to 10CFR50.55a(g)" and the November 1981 Draft Regulatory Guide "Identification of Valves for Inclusion in Inservice Testing Programs." These three documents provide the basis for selection of components, test requirements, relief requests, and format.

All information except individual valve maximum stroke times, requested by the reference documents has been included in this Program Plan. Maximum stroke times for valves have been determined from the pre-operational test program,

~ Technical Specifications, system operational considerations and manufacturers information. Since individual valve maximum stroke times may require revision after modification, repair or maintenance, SHNPP has elected to exclude them from the Program Plan submittal. Maximum stroke times will be established prior to the'nd of the first refueling outage and will be maintained in the appropriate test. procedures.

1.3 General Pro ram Plan Conce t The Program Plan specifiesSection XI testing requirements for components providing, either by action or position, a safety-related function. By definition, a safety-related function is one that is needed to:

1. Mitigate the consequences of an accident Shut down the reactor to the cold shutdown condition Maintain the reactor in a safe shutdown condition ISI-203 Rev. 8 Page 5 of 228

OS1 1.3 General Pro ram Plan Conce t (continued)

Plant Technical Specifications, special manufacturer's tests, system operating conditions, etc., may dictate additional components which should be included in the overall plant testing program, but whose functions fall outside the criteria above, and are not addressed by this Program Plan.

Section XI requires quarterly testing of all components unless it is impractical to do so. This program specifies quarterly testing of pumps and valves unless it has been determined that such testing would:

4. Be impractical due to system or component design

5. Render a safety-related system inoperable Cause a reactor scram or turbine trip Require significant deviations from normal operations

8. Require entry into inaccessible plant areas Increase the possibility of an inter-system LOCA Excluded from exercising during normal operations are all valves which, exercised, could place the plant in an unsafe condition. Cases where valve if exercising could compromise plant safety include:

10. All valves whose failure in a non-conservative position during the cycling test'. would cause a loss of system function will not be exercised. Valves in this category would typically include all non-redundant valves in lines such as single discharge line from the refueling water storage tank, or accumulator discharge lines.

Other valves may fall into this category under certain system configurations or plant operating modes. For example, when one train of a redundant system such as ECCS is inoperable, non-redundant valves in the remaining train should not be cycled since their failure would cause a loss of total system function.

All valves, whose failure to close during a cycling test would result in a loss of containment integrity will not be tested.

Valves in this category would typically include all valves in containment penetrations where the redundant valve is open and inoperable.

12. ~

All valves, which when cycled, could subject a system to pressures in excess of their design pressures. It is assumed for purpose of a cycling test, that one or more of the upstream check valves has failed unless positive methods are available for determining the pressure or lack thereof on the high pressure side of the valve to be cycled. Valves in this category would typically include the isolation valves of the residual heat removal/shutdown cooling system and, in some cases certain ECCS valves.

Each component excluded from quarterly testing has been analyzed to determine when appropriate testing may be performed. If'xercising of a valve is not practical during plant operation, the Code allows part-stroke exercising during normal plant operation, and full-stroke exercising at cold shutdown.

ISI-203 Rev. 8 Page 6 of 228

Osl 1.3 General Pro ram Plan Conce t (continued)

Since the Code allows testing at cold shutdown, this program does not request relief for those valves for which testing is delayed until cold shutdown.

The Valve IST Program Plan does provide a justification for the delay of testing until cold shutdown. These justifications are prepared in a format similar to relief requests, and are included following the Valve Test Tables for each system.

Where it has been determined that testing is not practical during plant operation, or at cold shutdown, a specific relief request has been prepared.

Each specific relief request provides justification for not performing the Code required testing, and provides appropriate alternative testing. Certain reliefs may be written within the guidelines of Generic Letter (GL) 89-04.

These reliefs do not require separate written concurrence of the NRC as long as they comply with the Generic Letter.

In addition to specific relief requests, general relief requests which address specific Code requirements found to be impractical for this site have been prepared. Because of the general nature of these relief requests, and the number of components involved, they ape presented in separate sections and are not repeated in the individual system sections.

Cold Shutdown and Refueling as used in this test program includes mode changes going into and coming out of plant Technical Specification defined modes 5 and 6. Because of unique system operating conditions, it will be necessary to perform some tests during mode change. For example, a steam driven turbine scheduled for testing at cold shutdown cannot be tested during mode 5 when there is no steam available. In this case, testing will be performed during a mode change when sufficient steam is available.

The Pump and Valve Inservice Testing Program Plan is organized into four independent parts, each of which can be removed from the Program Plan for review. Sections 5.1-5.3 present the general program commitment basis, the conceptual framework used in developing the Program Plans, and general relief requests for Code requirements found to be impractical for this site.

Section 5.4 deals specifically with the Pump Test Program, and Sections 5.5-5.6 deal specifically with the Valve Test Program. Section 5.7 outlines the data entry and analysis process along with tracking and resolution of identified test, deviations.

Sections 5.4-5.6 are formatted in a manner to aid review. Each section summarizes the basis and concepts used to formulate the Pump and Valve Testing Program. Pump testing requirements are summarized in a single Pump Test Table attached to Section 5.4. Valve test requirements are summarized in Valve Test Tables attached to Section 5.6. The Valve Test Tables are arranged into separate attachments for each system. Where quarterly testing has been found to be impractical, either a justification for delay of test to cold shutdown, or a relief request, is provided following the appropriate Pump or Valve Test Tables. In those cases where additional discussion of the test requirements for a component is needed, the remarks column of the Test Table contains a Note Number. These Notes m'ay be found proceeding the Test Tables.

ISI-203 Rev. 8 Page 7 of 228

Osl

2.0 REFERENCES

1. ASME Boiler and Pressure Vessel Code,Section XI, 1983 Edition through Summer 1983 Addenda

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

3. SHNPP Technical Specifications, Section 4.0.5 Generic Letter No. 89-04, Guidance on Developing Acceptable Inservice Testing Programs

5. EST-212, Type C Local Leak Rate Tes'ts

6. ANSI/ASME. OM-1 1981

7. TSG-254, Inservice Testing Program Data Entry and Analysis

8. EST-211, Auxiliary Relief Valve Testing

9. ISI-800, Inservice Testing of Pumps

10. ISI-801, Inservice Testing of Valves

11. PLP-103, Surveillance and Periodic Test Program

12. MMM-012, Maintenance Work Control Procedure (AMMS)

13. TMM-128, Technical Support Memorandum Communication System

14. MOD-103, Engineering Evaluations

15. PLP-400, Postmaintenance Testing

16. EST-202, Main Steam Safety Valve Test

17. EST-203, Pressurizer Safety Valve Test

18. TMM-100, Technical Support Conduct of Operations

19. TMM-103, Technical Support Work Management System 3.0 RESPONSIBILITIES 3.1 Technical Su ort Unit The Technical Support Unit is responsible for overall administration of the program including:

1. Determination of the program plan scope.

2. Revision of the program plan as necessary based on plant design changes.

ISI-203 Rev. 8 Page 8 of 228

OS1 3.1 Technical Su ort Unit (continued)

Preparation and disposition of reports as necessary (e.g.,

Pump/Valve Test Deviation Records, Pump Baseline Records, etc.).

Requesting relief from testing for components that cannot be tested in accordance with Reference 2.0.1.

5. Determining acceptance criteria.

6. Trending and analysis of test results.

System Engineering will provide input/approval when establishing baseline values and acceptance criteria, or evaluating test deviations. This includes signoffs of Pump Baseline Records and Test Deviation Records as required.

3.2 0 erations Unit The Operations Unit is responsible for:

Preparation and performance of surveillance test procedures'hat implement the program requirements.

Evaluation of test results based on acceptance criteria determined by the Technical Support Unit.

3.3 Administration Section The Administration Section is responsible for:

Maintaining test records consistent with the requirements of Reference 2.0.1.

3.4 Work Control Unit The Work Control Unit is responsible for:

1. , Issuing STSS Tasks for Category A and B active component testing (i.e., OSTs).

2. Establishing and activating STSS Tasks for components that are

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placed on ITF, at the request of Technical Support.

3.5 Maintenance Unit The Maintenance Unit is responsible for:

Performing corrective maintenance in accordance with Reference 2.0.12.

The Engineering Support Subunit may be requested to provide support in evaluating component deviations.

ISI-203 Rev. 8 Page 9 of 228

OS1 4.0 DEFINITIONS ABBREVIATIONS

1. ASME - American Society of Mechanical Engineers.

2. CFR - Code of Federal Regulations.

5.0 PROCEDURE The following is a detailed description of the ASME Section XI pump and valve program as implemented at SHNPP. The format is consistent with NRC recommendations.

5.1 Definitions The terms below, when used in the Inservice Testing Program Plan, are defined as follows:

Quarterly: An interval of 92 days for testing components which can be tested during normal plant operation.

Cold Shutdown: Testing delayed until cold shutdown will commence within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of achieving cold shutdown, and continue until all testing is complete or the plant is ready for return to power. If the plant feels that an outage will be lengthy enough to complete all cold shutdown testing, testing need not be commenced within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Cold shutdown testing not performed during one particular cold shutdown will receive priority in subsequent cold shutdowns.

Refueling: All testing delayed to refueling will be performed during the normal scheduled refueling shutdown before returning to power operation.

Period: Category C safety and relief valves (IWV-3511),

Category D explosive actuated valves (IWV-3610) and Category D rupture disks (IWV-3620) are periodically tested as defined in the appropriate Code Sections.

Pressure Isolation: Any valve which acts as an isolation boundary between the high pressure Reactor Coolant System and a system having a lower operating or design pressure.

Containment Isolation: Any valve which performs a containment isolation function and is included in the Appendix J, Type C, Local leak Rate Test program.

Active: Any valve which is required to change position to accomplish its safety-related function.

Passive: Any valve which is not required to change position to accomplish a specific function and for which the Code does not require stroke testing.

ISI-203 Rev. 8 Page 10 of 228

OS1 5.2 General Relief Re uests for Pum s This section requests relief from specific requirements of Section XI found to be impractical for this site. Since they are general in nature, and pertain to a number of components, this section requests general relief as presented below.

General Relief Request: PG-1 Pumps: All centrifugal pumps Test Requirements: Differential pressure alert and required action ranges (Table IWP-3100-2).

Basis for Relief: Pump overpressure is an indicator of pump clogging or improper maintenance and as such is an important test parameter to measure.

However, small positive increases in measured differential pressure across a centrifugal pump are most likely not a significant indicator of pump degradation. Adherence to the Code specified alert and required action ranges could result in unnecessary pump testing and repair.

In order to preclude unnecessary testing and repair, pump differential pressure will be measured and expanded alert and required action ranges used.

betimes Alternate Testing: In lieu of the Code specified values, the high side acceptance range will be 1.05 times the reference pump differential pressure. The high side alert and required action ranges will be 1.05 to 1.07 and ) 1.07 the reference pump differential pressure respectively.

5.3 General Relief Re uests for Valves This section requests relief from specific requirements of Section XI found to be impractical for this site. Since they are general in nature, and pertain to a number of components', this section requests general relief as presented below.

General Relief Request: VG-1 Component: Rapid actuating power 'operated valves with stroke times of 2 seconds or less.

Category: A, B Code Requirements: IWV-3417 requires corrective action if the measured stroke time for a valve which normally strokes in ten seconds or less increases by fifty percent from the last measured stroke time. IWV-3413 allows measurement to the nearest second for stroke times of ten seconds or less.

ISI-203 Rev. 8 Page ll of 228

Osl 5.3 General Relief Re uests for Valves (continued)

Basis for Relief: For rapid actuating power operated valves the application of the above criteria could result in requiring corrective action when the valves are functioning normally. These valves are generally small air and solenoid operated valves which because of their size and actuator types stroke very quickly. Operating history on this type of valve indicates that they generally either operate immediately or fail to operate in a reasonable length of time. The intent of the referenced Code sections is to track valve stroke time as a means of detecting valve degradation. This type of valve does not lend itself to this tracking technique.

Alternate Testing: A maximum stroke time of two seconds will be specified for each rapid actuating valve.

the measured valve stroke time is two seconds or If less it will be considered as acceptable and no corrective action"will be required. If the measured valve stroke time exceeds two seconds it will be considered inoperable and appropriate corrective action will be taken.

5.4 Inservice Pum Test Pro ram 5.4.1 Introduction This section presents the Program Plan for Inservice Testing of safety-related Pumps at Unit 1 of the Shearon Harris Nuclear Power Plant, in compliance with the requirements of 10CFR50.55a. This Program Plan has been prepared to the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWP, 1983 Edition through the Summer 1983 Addenda.

5.4.2 Pum IST Pro ram Plan Conce t The Pump Program Plan specifiesSection XI testing requirements for all ASME Class 1, 2 and 3 pumps provided with an emergency power source, and which are required for safety-related system operation. Test requirements determined. to be impractical for a large number of pumps have been addressed in Section I under General Relief Requests for Pumps. 'n addition to those General Relief Requests, this section includes requests for relief from Code requirements found to be impractical for specific pumps. Each relief request provides justification for deviation from the Section XI specified test, and proposes appropriate alternate testing.

ISI-203 Rev. 8 Page 12 of 228

OS1 5.4.3 Code Inter retation Pump Test Data within the Required Action Range (Table IWP-3100-2)

When test results show deviations that fall within the required action range of Table IWP-3100-2, a Pump/Valve Test Deviation Record (Att. 6.1) will be completed to document the deviation and the action taken. The Test Deviation Record will be filed and retained by the Technical Support ISI group. The following guidelines will be used.

First, the pump will be declared inoperable and will not be returned to service until the cause of the deviation has been determined and the condition corrected or evaluated as acceptable. The instruments involved may be checked for accuracy and the test rerun. If the second test provides results falling within the required action range, appropriate corrective action must be initiated. This corrective action may be either replacement, repair, or analysis to demonstrate that the condition does not impair pump operability, and that the pump will still fulfillits safety-related function. If the analysis verifies that the pump is operable, a new set of reference values will be established and documented on .a Pump Bas'eline Record (Attachment 6.2),

which will be filed and retained by the Technical Support ISI group. If the instrumentation is checked, and the test rerun with results in, the acceptable range, the first set of test results will be discarded, and the second set retained.

Pump Test Data Within the Alert Range (Table IWP-3100-2)

If test values fall within the alert range, the frequency of testing will be doubled until the cause of the deviation is determined and the condition corrected. If corrective action is taken and/or if subsequent test results revert back to the acceptable value (a minimum of two consecutive satisfactory tests required for unexplained deviations), the original test frequency will be resumed. Correction can take the form of analysis in lieu of or in combination with increased frequency testing. In addition, the instruments involved may be checked for accuracy and the test rerun. If the rerun gives results in the acceptable range, the first set of results will be discarded, and the second set retained. A Pump/Valve Deviation Record (Attachment 6.1) will be completed, documenting the deviation and the action taken. This Deviation Record will be filed and retained by the Technical Support ISI group.

Analysis of Data within 96 Hours (IWP-3220)

All Code required test parameters will be reviewed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after completion of test to verify that they do not fall within the required action range. Those that fall within the required action range will be processed as described above. Those that do not fall within the required action range will be analyzed within four working days after completion of test. This fulfills the intent of the Code to require immediate action on pumps falling within the required action range and allows orderly reduction of data taken on weekends or holidays, when sufficient staff may not be available to perform the Code required analysis.

ISI-203 Rev. 8 Page 13 of 228

OS1 5.4.3 Code Inter retation (continued)

Scope of Tests (IWP-3300)

Section IWP-3300 requires that each inservice test measure and observe all the quantities in Table IWP-3100-1 except bearing temperature, which shall be measured at least once a year. The Code assumes that each pump installation can be instrumented to obtain the specified quantities. In some installations it is not possible to provide instrumentation to obtain Code specified quantities. For example, submerged pumps cannot be instrumented to measure inlet pressure and observation of proper lubricant level or pressure is not possible for a greased bearing pump. In some cases it is possible to substitute an alternate method. For example, inlet pressure for a submerged pump can be calculated by measuring the head of water relative to the pump suction. This program does not request relief from Section XI testing for those quantities which cannot be obtained due to pump design or installation.

Explanatory notes have been used in the Pump Test Table when Section XI testing is not possible due to pump design or installation.

Establishment of New or Additional Sets of Reference Values (IWP-3112)

If it becomes necessary to establish a new or additional set of reference values, an inservice test shall first be run at the conditions of an existing set of reference values and the results analyzed. If operation is satisfactory, a second test run at the new reference conditions shall follow as soon as practical. No modifications ar maintenance shall be performed in this interval which may affect performance. The results of this test shall establish the new or additional set of reference values. Whenever a new or additional set of reference values is established, the reasons for so doing shall be justified and documented.

One situation that might require establishment of a new set of reference values is the revision of a test procedure that might invalidate current reference values. Care should be taken that any procedure revision that might change test conditions follow the procedure above.

Data Falling Directly on the ASME XI Limits (Table IWP-3100-2)

V Test data which falls on the borderline between the ASME XI Alert and Acceptable ranges will be considered acceptable. This applies to flow rate, differential pressure, and vibration measurements.

ISI-203 Rev. 8 Page 14 of 228

OS1 5.4.4 ~Pum List Pumps required for safety-related operation for this site are as follows:

SYSTEM DWG. NO. REV.NO. NO. of PUMPS Auxiliary Feedwater S-0545 16 Emergency Service Water S-0547 14 S. W. Booster S-0547 14 Containment Spray S-0550 D.G. Fuel Oil Transfer S-0563 Emerg. S.W. Intake S-0808 Screen Wash Chilled Condenser Water S-0998 S02 S-0999 S02

.S.I. Charging S-1305 Boric Acid Transfer S-1307 Component Cooling Water S-1319 Residual Heat Removal S-1324 Spent Fuel Pool Cooling S-0805 5.4.5 Pum Table Nomenclature The following abbreviations have been used in the Pump Test Table:

N Rotational Speed-Pi Inlet Pressure (Before and after pump start)

DP Differential Pressure Across Pump Qf - Flow Rate V Vibration Amplitude Tb Bearing Temperature 1 - Quarterly 2 Cold Shutdown 3 Refueling X Measurement/Observation per IWP L Lubricant Level or Pressure PR Relief Request ISI-203 Rev. 8 Page 15 of 228

OS1 5.4.6 Pum Test Table Notes In the Pump Test Table, the test parameters to be measured or observed, and the test frequency are identified. Footnotes 1 through 10 refer to amplifications, deviations, and exceptions to the Code requirements and are further discussed below:

Pump with constant speed drive, speed is not measured since test will be performed at nominal motor nameplate speed as required by Section XI, IWP-3100.

Inlet pressure to be calculated from the inlet liquid level.

The liquid level will be measured while establishing and verifying Reference Data sets, and used as information during subsequent test analysis.

Bearing temperature measurement not required (IWP-4310) since bearings are in the pumped fluid flow path.

4. Bearing temperatures to be measured once a year as stipulated by Section XI, IWP-3300.

5. Lubricant level or pressure not observed because of bearing lubrication design.

Any one of three component cooling or three charging pumps is an installed spare. One pump is normally running, the second is aligned as an automatic backup to the operating pump and the third pump is electrically disconnected. In the event of failure of the operating pump, the second pump automatically starts and the installed spare is electrically connected and valved in as the reserve pump. The normally operating and reserve pump will be tested. The installed spare is required to be tested only when is connected to the system.

it Quarterly testing of the motor driven pumps is performed using pump recirculation flow through a small diameter recirculation line. A full flow test will be performed on the way to cold shutdown.

Quarterly testing of the steam driven pump is performed using pump recirculation flow through a small diameter recirculation line. A full flow test will be performed on the way to cold shutdown.

Pump and motor are an integral unit with no bearings in the pump.

Motor upper bearing will be treated as if it were a pump bearing.

Motor bearing has installed vibration monitoring, temperature measurement and are water lubricated.

10. Observe only.

ISI-203 Rev. Page 16 of 228

5.4.7 Pum Test Table PUhIP LIST MEASURED PARAMETERS System Pump I.D. P Ss I.D. Class Test Freq. Pi DP Tb (4)

IANNA AUXILIARYFEEDWATER IANNA $ 4)545 J-7 3 1,2 (7) 0) X X X PR-I 00)

IBSB J-8 3 1,2 (7) 0) X X X PR-I 00)

IANNA IX4AB J-9 3 1,2 (8) X X X X PR-I 00)

EMERGENCY SERVICE IANNA $ 4547 C-3 0) (2) X X X (3) (5)

WATER IB4B C-3 0) X X X X (3) (5)

IANNA D.G. FUEL OIL $ 4)563 F-2 0) X X PR-2 X PR-3 00)

TRANSFER IBSB F-7 0) X X PR-2 X PR-3 00)

IANNA EMERG. S.W. INTAKE $ 4)808 C-12 0) x X X X PR-7 00)

SCREEN WASH IB4B C-15 0) X X X X PR-7 00)

IANNA CHILLED WATER $ 4)998 S02 Ik 0) X X X X PR-7 00)

I BOB IANNA

$ 4)999 $ 02 1-6 0) x X X X PR-7 00)

S.l. CHARGING S-1305 H-9 I (6) 0) X X X X PR-7 00)

IB4B J-9 I (6) 0) X X. X X PR-7 00)

IANNA IC4AB K-9 X X I (6) 0) X PR-7 00)

BORIC ACID TRANSFER S-1307 D-8 1,2 0) X X X PR-6 PR-6 IB4B G-8 1,2 0) X X X PR4 PRA COhl PON ENT COOLING $ -1319 F-7 I (6) 0) X X X X PR-7 00)

WATER IBSB L-7 I (6) 0) X X X X PR-7 00)

IANNA ICSAB 1-7 I (6) 0) x X X X PR-7 00)

RESIDUAL HEAT $ -1324 I 0) X X X (9). (9) (9)

REMOVAL IB4B I 0) X X X (9) (9) (9)

SPENT FUEL POOL IANNA $ 4805 H-10 0) X X X X PR-7 (5)

COOLING IBSB K-10 0) X X X X PR-7 (0 CONTAINhIENT SPRAY IA-SA $ -550 F-8 0) X X (9) (9) (9)

IBSB K-8 0) X X (9) (9) (9)

S.W. BOOSTER $ 4)547 H4 0) X X X (3) (5)

IBSB H-15 0) X X X (3) (5) 0

OS1 5.4.8 Pum Relief Re uest PR-1 System: Auxiliary Feedwater Pump: 1A-SA, 1B-SB, 1X-SAB Glass:

Function: Provide Auxiliary Feedwater to the Steam Generators on loss of Main Feedwater.

Test Requirements: Measure Bearing Temperature (IWP-4300).

Basis for Relief: Quarterly pump testing is performed using a pump recirculation line back to the GST. In this mode of operation the temperature of the pumped fluid is constantly increasing and operation is limited to a maximum of one hour.

IWP-3500(b) requires the pumps be operated until bearing temperature stability is achieved, but for no less than thirty minutes. Since the pumped fluid temperature is constantly increasing, bearing temperature will not reach stability in one hour. In addition, good operating procedure will limit. operation of the pumps in this mode to as short a time as possible to preclude pump degradation. When the pumps are full flow tested at cold shutdown or refueling the length of operation is dictated by plant operating conditions and it cannot be guaranteed that plant conditions will allow operation of each pump until bearing temperature stabilizes without significant impact on nor'mal plant operations.

Alternate Testing: Pump differential pressure, flow and vibration

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measurements will be used to evaluate pump performance.

ISI-203 Rev. 8 Page 18 of 228

OS1 5.4.8 Pum Relief Re uest (continued)

PR-2 System: Diesel Generator Fuel Oil Transfer Pump: 1A-SA, 1B-SA Class:

Function: Transfer Diesel Fuel Oil from the Storage tanks to the Day .Tanks.

Test Requirements: Measure pump flow rates to the requirements of Table IWP-3100-2.

Basis for Relief: There age no system design provisions for direct flow measurements. Flow rate will be calculated from measured change in Day Tank level during pump operation. This method is not accurate enough to comply with the allowable ranges of test quantities of Table IWP-3100-2.

Alternate Testing: Flow rate will be calculated from observed change in Day Tank level during pump operation.

ISI-203 Rev. 8 Page 19 of 228

OS1 5.4.8 Pum Relief Re uest (continued)

PR-3 System: Diesel Fuel Oil Transfer Pump: 1A-SA, 1B-SB Class:

Function: Transfer diesel fuel oil from the storage tank to the day tank.

Test Requirements: Per IWP-3500(b), when the measurement of bearing temperature is required, each pump shall be run for a minimum of thirty minutes until bearing temperature stabilizes.

Basis for Relief: Diesel Fuel Oil Pump running time is dictated by interlock circuitry and administrative limits corresponding to allowable Day Tank levels. The interlocks, which"'control automatic transfer pump operation, limit operation of the pumps below minimum allowable or above maximum allowable tank levels. Operation of the pumps .

with tank levels above maximum allowable is precluded by administrative controls and alarms.

The time required to fill the tank from minimum level to maximum level is less than thirty minutes.

Alternative Testing: Bearing condition will be evaluated by pump bearing vibration measurements.

ISI-203 Rev. 8 Page 20 of 228

OS1 5.4.8 Pum Relief Re uest (continued)

PR-6 System: Boric Acid Transfer Pump: 1A-SA, 1B-SB Class:

Function: Transfer of concentrated Boric Acid from the Boric Acid Tank to the CVCS.

Test Requirements: Measure pump bearing temperature and observe lubrication level.

Basis for Relief: These pumps are Model GVHS-lOK Pumps made by Chempump Division of the Crane Co. This type of pump has no bearings in the pump and is a integral unit with the motor. The pump bolts directly onto the integral motor end housing flange, such that" the motor bearings are completely inclosed. Motor bearings are lubricated and cooled by diverting a portion of pump flow through the motor and back to the pump suction. All cooling and lubrication are associated with the motor would not provide any information about the pumps Alternate Testing: None ISI-203 Rev. 8 Page 21 of 228

OS1 5.4.8 Pum Relief Re uest (continued)

PR-7 System: Chilled Water, S.I. Charging, Component Cooling Water and Spent Fuel Pool Cooling, ESW Intake Screen Wash.

Pump: 1A-SA, 1B-SB (Chilled Water);

1A-SA, 1B-SB, 1C-SAB (S.I. Charging);

1A-SA, 1B-SB, 1C-SAB (C.C.W.); 1A-SA, 1B- SB (SFPC); lA-SA, 1B-SB (ESW Intake Screen Wash)

Class: 2 3 Function: HVAC Chilled Water, Safety Injection and Cooling Water for safety-related equipment.

Test Requirements: Measure bearing temperature (IWP-4300).

Basis for Relief: These pumps. have rio installed instrumentation to measure bearing temperature. Measurement of temperature of the pump bearing housing would not be indicative of actual bearing temperature because of temperature gradients caused by operation of space coolers, pump location, pumped fluid, etc. The once a year measurement will not provide significant information about pump condition. The long pump running time required to achieve temperature stability could result in unnecessary wear on the pumps and result in increased pump maintenance and repair.

Deletion of this measurement will not have significant affect on the pump monitoring program, since other required test parameters are being measured.

Alternate. Testing: Pump differential pressure, flow and vibration will be used to monitor pump performance.

ISI-203 Rev. 8 Page 22 of 228

OS1 5.5 Inservice Valve Test Pro ram 5.5.1 Introduction This section presents the Program Plan for Inservice Testing of Valves at the Shearon Harris Nuclear Power Plant, in compliance with the requirement of 10CFR5.55a. This Program Plan has been prepared to the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWV, 1983 Edition through the Summer 1983 Addenda.

5.5.2 Valve IST Pro ram Plan Conce t The Valve Test Program Plan was developed to verify the operability of safety-related systems. The valves addressed are those whose operability is essential to safety-related system operation.Section XI valve testing is then specified for each of these" valves to verify individual valve operability. The Program Plan specifies either-Section XI or alternate testing, as appropriate, for all valves which perform a safety-related function.

Valves are selected for inclusion in the test program based on a review of all plant systems. This review identifies those systems performing safety-related functions. Each safety-related system is then analyzed to determine which valves are essential to the safety-related operation of the system. These valves are investigated to determine whether Section XI testing can be performed during normal operation. Those valves for which quarterly testing is determined to be inappropriate are analyzed further to determine If if Code allowed testing at cold shutdown is possible. so, a justification for delay of test to cold shutdown is provided following the appropriate Valve Test Tables. Relief requests describing appropriate alternative testing, and justifying exclusion from Section XI testing, have been prepared for valves which cannot be tested quarterly or during cold shutdown, and are provided following the appropriate Valve Test Tables..

5.5.3 Code Inter retation Subsection IWV of the Code contains a number of items which require a certain degree of cl'arification by the owner in order for a program commitment to be adequately stated. These code clarifications are provided below.

Relief Valves:

The Code requires testing of pressure relief valves in accordance with ANSI/ASME OM-1 1981. The relief valves designated for test are only those which perform a system pressure relief function. Thermal relief valves, whose only function is to protect components 'or piping from thermal expansion are not included in the IST program. Where a relief valve performs both a system and a thermal relief function it has been included as testable. A number of thermal relief valves have been included in the valve test tables to comply with a North Carolina State Requirement for testing of relief valves which protect pressure vessels. SHNPP has elected to include these thermal relief valves in'heir Section XI test program. All relief valves included to comply with North Carolina State Regulations are so noted in the valve test tables.

Valve testing will be performed in accordance with ANSI/ASME OM-1 1981 in lieu of ASME XI, IWV-3510.

ISI-203 Rev. 8 Page 23 of 228

Osl 5.5.3 Code Inter retation (continued)

Passive Valves:

The reference Code excludes valves used only for operating convenience and/or maintenance from testing. Also, the Code defines passive valves but specifies no operability test requirements. This program defines as passive power operated valves which do not have to change position, but whose position has a direct bearing on safety-related system operation. Manual flow path maintenance and system alignment valves are excluded. Manual passive Containment Isolation and pressure isolation valves have been included for leak testing only.

S stem Test Valves:

Power operated valves included in a system to align the system for testing are included for Section XI testing if their position is critical to safety-related system operation. The system analysis postulates that the system is in a test mode when the initiation signal occurs. All valves, including those used only for testing, which must respond to the initiation signal, are included in the test program.

Pressure and Flow Control Valves:

The reference Code excludes valves which perform pressure or flow control functions. This program excludes them unless they also perform a system safety-related response function such as automatic closure on system initiation or fai,l safe operation. The program addresses these valves by specifying testing of the safety-related function, and excluding the normal pressure or flow control functions. These valves will be stroke timed are equipped with valve test provisions or if if a repeatable exercising method they is possible.

Automatic Power 0 crated Valves:

Power operated valves which receive an automatic signal on system initiation are included in the program.

Remote Power 0 crated Valves:

The program includes power operated valves activated by remote switches they are required to change position to align a system for safety-related if operation, .terminate safety-related system operation, or provide containment isolation capability during the long term post-LOCA operating mode.

Normal vs. Safet -Related S stem 0 eration:

Valves in systems which have both normal and safety-related operating modes are included in the program only if they perform a safety-related function. Valves which provide normal system operation control and whose position has no effect on safety-related operation are excluded from the program.

ISI-203 Rev. 8 Page 24 of 228

OS1 5.5.3 Code Inter retation (continued)

Dual Function Valves:

Valves which provide more than one function are tested for their safety-related function only. Valves with multiple safety-related functions are tested for each function.

Sim le Check Valves:

This Program Plan considers any. check valve to be a 'simple check valve has no means of changing position other than by reversal of fluid flow if it

,direction. Simple check valves are tested to verify operability in the safety-related flow direction. Normally closed simple check valves which must open are tested to verify full opening with forward flow. Normally'open simple checks which must close on cessation of flow are tested to verify closure on cessation of forward flow. Normally closed simple check valves which remain closed on system initiation are tested to verify absence of reverse flow. Normally open simple check valves which are required to remain open, are tested to verify full flow in the forward direction. Simple check valves which are required to cycle open and closed are tested to verify full opening with forward flow and closure on loss of forward flow.

Manual Sto Check Valves:

Manual'top check valves are tested to verify operability in the safety-related flow direction. If the manual operator is withdrawn, the valve operates as a simple check in the forward flow direction and is tested as a simple check. Reverse flow closure is verified as a simple check, possible, or by use of the manual operator.

if Testable Check Valves:

Check valves equipped with manual exercisers will be tested as a simple check, or by exercising using the manual exercising device. Check valves equipped with a power operator installed for the sole purpose of exercising the valve for operability will be tested as a simple check, or by use of the power operator.

Power 0 crated Sto Check Valves:

Testing of power operated stop check valves is based on the function of the operator. If the valve operator is always withdrawn, and the valve operates as a simple check valve except during maintenance, the valve is tested as a simple check. If the operator is normally withdrawn, such that the valve operates as a simple check in the forward direction, and the operator provides positive closure, it is tested as a simple check in the forward direction, and exercised closed using the operator. In addition to exercising, the operator will be timed. and fail safe actuation tested as appropriate.

ISI-203 Rev. 8 Page 25 of 228

S OS1 5.5.3 Code Inter retation (continued)

Pum Dischar e Check Valves:

As a minimum, pump discharge check valves in safety-related systems will be forward flow exercised. In addition, reverse flow closure will be verified when failure of the valve to close could result in a substantial reduction of system performance. Such a potential exists with parallel pumps connected to common suction and discharge headers. If the check valve on the idle pump fails to close, a significant amount of system flow could be diverted back through the idle pump to the suction header.

S stem Pi in Kee Fill Check Valves:

Keep fill lines are those lines attached to ECCS system piping whose function is maintenance of system water inventory to preclude water hammer. Forward flow operability is verified by a system check of water inventory performed at least quarterly. Reverse flow closure verification is performed only failure of the valve to close could result in a significant reduction of ECCS if system operation.

Check Valve Full Partial Stroke:

In most cases full design flow through a check valve requires less than full mechanical valve movement. As used in this program, the term full stroke refers to the ability of the valve to pass design flow,,and not the full mechanical stroking. Forward flow full stroke operability testing will be by any method that verifies the valve capable of passing design flow. Any test that verifies less than full design flow capability is considered as a partial stroke test.

Cate or A Containment Isolation Valve Leak Testin All valves specified for Appendix J, Type C, Local Leak Rate testing are included in the Valve IST Program as Category A valves. Appendix J, Type C, valve local leak rate testing fulfills the intent of Articles IWV-3421 through IWV-3425 and will be performed in lieu of Section XI testing. Analysis of leakage rates and corrective actions requirements of IWV-3426 and IWV-3427(a) will be performed. The requirements of IWV-3427(b) will not apply (Reference 2.4). The Program plan reflects the current list of valves receiving Appendix J, Type C testing. Any future change to that list will be incorporated into the valve test program.

Cate or A Pressure Isolation Valve Leak Testin All valves designated as pressure isolation valves in Table 3.4-1 of plant Technical Specifications are considered to perform a pressure isolation function between the Reactor Coolant System and a low pressure system and are included in the Valve IST Program as Category A valves. These valves will to the requirements specified in IWV-3420. Any change to the list of be'ested pressure isolation valves in Technical Specifications will automatically be incorporated into the Valve Test Program.

ISI-203 Rev. 8 Page 26 of 228

OS1 5.5.3 Code Inter retation (continued)

Cate or A Containment and Pressure Isolation Valve Leak Testin Valves which perform both a containment isolation and a pressure isolation function are included in the Valve IST Program Plan as Category A Valves.

These valves will be tested to requirements of both Appendix J and Section XI.

Cate or A Pressure Isolation Valve 0 erabilit Testin Reactor Coolant System pressure isolation valves will be demonstrated operable in accordance with plant Technical SpeciEication 4.4.6.2.2 by veri. Eying leakage to be within specified limits.

Locked Valves:

This program plan classifies as locked valves only those which are physically restrained from movement (i.e., chain and padlock), or sealed (i.e., wire and seal) in position. Keylocked valves are not considered to be physically locked. This program plan makes no distinction between locked and non-locked manual valves and considers both to be passive.

Maximum Stroke Times:

Maximum stroke times were developed based on actual observed times obtained during pre-operational testing and operational test data for valves which could not be timed under repeatable test conditions during the pre-operational testing. These times along with manufactures data and Technical Specifications have been used to specify maximum stroke times for each valve.

Where actual stroke times are much less than Technical Specification values the limiting value of maximum stroke time will be determined from actual observed values, but at no time will maximum stroke time exceed Technical Specification values. A plant criteria has been developed for determining values of maximum stroke times from measured values as follows:

1. Stroke time greater than 10 Seconds 2 X baseline Stroke time greater than 2 seconds 3 X baseline but equal to or less than 10 seconds

3. Stroke time equal to or less than 2 seconds - 2 seconds NOTE: For valves with normal reaction times that border on 2 seconds, ISI may, at their discretion, apply either the 2 second limit or the 2X limit.

If the 2X limit is elected, normal Section XI alert limits will apply.

These plant criteria may be deviated from (conservatively) provided a basis for the alternate maximum stroke time is documented and filed for retention by Technical Support ISI.

Values of maximum stroke times will be maintained separate from this document.

This will allow for changes in maximum stroke times necessitated by changing test conditions, repairs, maintenance, modifications, etc., without requiring revision of the approved Valve Test Program Plan.

ISI-203 Rev. 8 Page 27 of 228

OS1 5.5.3 Code Inter retation (continued)

Roundin Off of Stroke Times For purposes of determining operability and establishment of Alert limits, the official stroke time will be the measured stroke time rounded off to the nearest full second. Measured stroke times which fall on the half-second (i.e., 2.5, 4.5, etc.) will be rounded ~u to the nearest full second.

Valve Position Indicator Verification:

IWV-3390 requires that all valves with remote position indicators shall be observed at least once every two years to verify that valve operation is accurately indicated. It is the intent of this program that such verification will be performed on all valves included in this program which have remote position indicators.

Valve Stroke Direction:

Valves will be stroked and timed in their safety-related direction(s). For example, a motor operated test valve whose safety-related operation is to close on system initiation will only be exercised and timed closed. If the valve must operate in both directions for. safety-related system operati'on, will be exercised and timed in both directions.

it Valve Fail Safe Direction:

Valves will be tested to verify operability of the fail safe operator in the direction that the valve travels to perform its safety-related function.

Valves equipped with fail safe operators for convenience only and which do not have to change position on loss of power for adequate safety-related operation will not be fail safe tested.

Tem erature Inter-Locked Valves Valves which open and close in response to local temperature controls will not be tested unless they are interlocked to system operation. For example, temperature interlocked valves on local area heat exchangers will not be tested unless they are interlocked to go open/closed on system initiation for safety-related operation.

Check Valve Disassembl Valve disassembly is utilized as an alternative for check valves where been determined that testing is impractical. A sampling plan is used for it has groups of check valves which are identical (i.e., same manufacturer, type, size, etc.) in construction and for which the system operating environment is the same. The sampling plan selects one valve from each group for disassembly during each refueling outage. If the selected valve passes inspection a second valve is selected for disassembly at the next refueling, etc., until the group has. been completed or until such time that sufficient inspections have been performed to justify an alternate sampling plan. For those cases disassembly indicates that there are no valve problems, a new relief 'here request may be prepared to perform less frequent inspections.

Failure of the selected valve to pass inspectian will initiate additional valve disassembly as specified by the appropriate relief request.

ISI-203 Rev. 8 Page 28 of 228

OS1 5.5.3 Code Inter retation (continued)

The visual inspection of disassembled valves includes verification that the valve is capable of full stroke operation. All valves specified for disassembly are of the bolted bonnet design. For valves with hinge pins in the valve body, full stroke operability will be verified by manually exercising the valve through a complete cycle. For valves with hinge pins in the removable bonnet such that the valve internals are removed from the valve body during disassembly direct verification of full stroke operability by manually exercising is not possible. 'For these valves, full stroke operability will be by verification of full stroke travel of valve internals for evidence of wear, binding, etc. and by stringent valve reassembly procedures.

Containment Entr Entry into the Containment structure during normal operation or cold shutdown is strictly regulated by plant operating procedures. Because of environmental and ALARA considerations, entry is made only for tasks that are absolutely necessary for plant operation and duration inside the Containment is limited to as-short-as-possible. Because of this, valve testing that would require entry into Containment to perform special testing is considered to be beyond the scope of Section XI and is delayed to refueling.

Cate or A&B Test Deviations Valve Exercisin If a test shows an increased stroke time from the previous test which exceeds the criteria of IWV-3417(a), the test frequency will be increased to once each month. If corrective action is taken and/or if subsequent test results revert back to the acceptable value (a minimum of two consecutive satisfactory tests required for unexplained deviations), the original test frequency will be resumed. In either case a Pump/Valve Test Deviation Record (Attachment 6.1) will be completed to document both the deviation and return to normal testing

~

frequency. The Deviation Record will be filed and retained by Technical Support ISI.

NOTE: The use of the test deviation record and increased frequency testing may, a't the discretion of ISI, be extended to include excessively fast stroke .times and'"erratic data."

If during a test a valve fails to change position or exceeds its limiting stroke time value, it will be declared inoperable and corrective action will be initiated immediately. A retest will be performed satisfactorily before any failed valve is returned to operable status.

Cate or A Test Deviations Leak Rate Testin If leakage rate measurements exceed specified limits, the valve will be repaired or replaced.

ISI-203 Rev. 8 Page 29 of 228

OS1 5.5.3 Code Inter retation (continued)

Cate or C Test Deviation:

If either a relief valve or check valve fails to function properly during testing, the valve will be repaired or replaced.

5.5.4 Valve Table Nomenclature The following abbreviations have been used in the Valve .Test Table.

V~alve T e Actuator T e BF - Butterfly Valve AO - Air BA - Ball Valve PO - Piston CK - Check Valve EH - Electro-Hydraulic DA - Diaphragm Valve MA - Manual GL - Globe Valve MO - Motor GA - Gate Valve NO - Nitrogen ND - Needle Valve SA - Self RG - Regulator Valve SO - Solenoid RL - Relief Valve SK - Spring Check Valve Stroke Direction 3W - Three Way Valve 0 - Open PG - Plug Valve C - Closed Normal Position Check Valve Test Direction 0 - Open FF - Forward Flow C - Closed BS - Reverse Flow LO - Locked Open LC - Locked Closed TH - Throttled LT - Locked Throttled ISI-203 Rev. 8 Page 30 of 228

OS1 5.5.4 Valve Table Nomenclature (continued)

Test Re uirements FS Full Stroke Exercise Valve for operability in accordance with Article IWV-3412.

FC Exercise valve with a fail-safe actuator to the closed position in accordance with Article IWV-3415.

FO Exercise valve with a Fail-safe actuator to the open position in accordance with Article IWV-3415.

LC - Leak Test per both Appendix J, Type C, and Section XI.

Leak Test per Appendix J, Type C, in Accordance with Appendix J of 10 CFR 50 (containment isolation function only).

LK - Leak Test per Section XI, in accordance with Article IWV-3420.

PE Partial Stroke Exercise in accordance with Article IWV-3412.

PV - Passive Valve as defined by Article IWV-2100.

RD - Rupture Disk as defined by Article IWV-3620.

RL - Relief Valve in accordance with Article IWV-3512 TS Stroke Time valve in accordance with Article IWV-3413 for valves with maximum stroke times specified in Plant Technical Specifications.

TM- Stroke Time valve in accordance with Article IWV-3413 for valves other than those with maximum stroke times specified in Plant Technical Specifications.

PI Valve with remote position indication verified in accordance with Article IWV-3300. 'I DS Valve will be disassembled and visually inspected as described in the Relief Request.

SP A special valve test procedure in lieu of Section XI testing, and described in the Relief Request.

Test Fre uenc Once per 92 days 2 Testing. performed during cold shutdown (but no sooner than 92 days) in accordance with Article IWV-3412. I ISI-203 Rev. 8 Page 31 of 228

OS1 5.5.4 Valve Table Nomenclature (continued)

NOTE: Testing may be performed during plant operating modes between normal operation and Tech. Spec. defined cold shutdown conditions.

3 Once per refueling outage NOTE: Testing may be performed during plant operating modes between normal operation and Technical Specification defined refueling conditions.

4 Tested during the time period defined in:

IWV-3511 and ANSI/ASME OM 1981 (safety and relief valves)

IWV-3620 (rupture disks) 5 Once per 2 Years in accordance with Article IWV-3300.

ISI-203 Rev. 8 Page 32 of 228

OS1 5.5.5 Valve Test Table Format Valve No. Unique number assigned to each valve.

Class and Dwg. Coor. The ASME valve class and drawing reference location. This is a two line entry with the class on the first line and drawing coordinate on the second line.

Valve Cat. Valve category,.as defined in Subsection IWV-2200.

Size (in.) and'Type A two line entry with the first being the valve size in inches, and the second the valve type.

Actu. Type The type of operator used to change valve position. For dual function valves this will be a two line entry. For example, a locked open stop check valve is entered as self actuating on one line, and manual on the other.

N'orm. Posit. The valve position during normal plant operation.

Test Req. The test requirements which apply to the valve.

For dual function valves, multiple line entries of applicable tests which correspond to actuator type.

Stroke Direct. This a multiple line entry for safety-related stroke direction. If both directions are safety-related, two lines are used. This column also includes direction for positive closure power operated check valves.

Check Valve Direction of check valve operability Test Direction verification. May be a two line entry operability is safety-related in both if valve.

directions.

C.S. Just. or Reference number of the cold shutdown Relief Req. No. justification or relief request located following the Valve Test Tables for each system.

C.S. or Alt. Cold shutdown or alternate testing which Test Perf. is being performed in lieu of the Code specified quarterly testing.

ISI-203 Rev. 8 Page 33 of 228

OS1 5.5.5 Valve Test Table Format (continued)

Remarks Key to notes providing amplifying remarks.

These notes are located prior to the Valve Test Tables.

Rev. No. tern This column records the document revision number for each valve.

~Ne ~Dw . No. Section Containment HVAC 2165-S-1017 5.6.1 Reactor Aux. Bldg. HVAC 2168-G-517 S03 5.6.2 Control Room HVAC 2165-S-1017 5.6.3 Fuel Bldg. HVAC 2168-G-533 5.6.4 Switchgear and Protection 2168-G-517 S05 5.6.5 Room HVAC Main Steam 2165-S-542 5.6.6 Feedwater 2165-S-544 5.6.7 Auxiliary Feedwater 2165-S-544 5.6.8 Condensate 2165-S-545 5.6.9 Service Water 2165-S-547 5.6..10 2165-S-588 Containment Spray 2165-S-550 5.6.11 Steam Generator Blowdown 2165-S-551 5.6.12 Process Sampling 2165-S-551 5.6.13 2165-S-552 D.G. Fuel Oil Transfer 2165-S-563 5.6.14 2165-S-633 S03 Rad. Monitor and H2 Analyzer 2165-S-605 5.6.15 D.G. Starting Air 2165-S-633 S04 5.6.16 Demineralized Water 2165-S-799 5.6.17 lSI-203 Rev. 8 Page 34 of 228.

OS1 5.5.5 Valve Test Table Format (continued)

~setem ~Dw . No. Section CTMT. Sump Drains 2165-S-685 5.6.18 Service Air 2165-S-800 5.6.19 Instrument Air 2165-S-801 5.6.20 2165-S-1017 Fuel Pool Cooling 2165-S-561 5.6.21 2165-S-805 Emergency Screen Wash 2165-S-808 5.6.22 Fire Protection 2165-S-888 5.6.23 Essential Chilled Water 2165-S-998 5.6.24 2165-S-998 S02 2165-S-999 2165-8-999 S02 Reactor Coolant 2165-8-1301 5.6.25 2165-S-1309 CVCS 2165-S-1303 5.6.26 2165-S-1303 Sol 2165-S-1303 S02 2165-S-1304 2165-S-1305 2165-S-1306 2165-S-1307 Safety Injection 2165-S-1308 5.6.27 2165-S-1309 2165-S-1310 CTMT. Waste Processing 2165-S-1313 5.6.28 Component Cooling Water 2165-S-1319 5.6.29 2165-S-1320 2165-S-1321 2165-S-1322 2165-S-1322 Residual Heat Removal Sol'165-S-1324 5.6.30 CTMT. Integrated Leakage 2166-S-916 5.6.31 Detection 5.6 Valve Test Tables and Relief Re uests ISI-203 Rev. 8 Page 35 of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.1 VALVE TEST TABLES AND RELIEF REQUESTS FOR CONTAINMENT HVAC DWG. NO. 2165-S-1017 ISI-203 Rev. 8 Page 36 of 228

OS1 SYSTEM: CONTAINMENT HVAC NO. NOTE Containment Vacuum relief Containment isolation valves.

Post-accident Hydrogen Purge Back-up to Recombiners. Valves are maintained closed except for Pose-LOCA Hydrogen Purge.

Normal Containment Purge and Make-'up Isolation Valves.

Plant Tech. Spec. 3.6.1.7 allows these valves to be opened for safety-related reasons only in Modes 1-4.

Containment Isolation Valves for Pre-Entry Purge. Valves are incapable of closing against accident flow. Plant Tech.

Spec. 3.6.1.7 requires maintaining these valves closed during normal operation.

Valve numbers have been revised as follows:

2CB-Bl - 1CB-2 2CP-Bl - 1CP-9 2CB-B2 1CB-6 2CP-B4 1CP-7 2CB-Vl 1CB-3 2CP-B3 1CP-10 2CB-V2 1CB-7 2CP-B6 1CP-3 2CM-B4 - 1CM-4 2CP-B5 - 1CP-5 2CM-B5 1CM-2 2CP-B8 1CP-1 2CM-B6 w 1CM-5 2CP-B7 1CP-14 2CM-Vl 1CM-7 2CP-B2 1CP-6 Containment Isolation Valve Operability of these valves in terms of their active function is only required during Mode 5 or 6 when containment closure is required and the valves are to be operated for containment purge (i.e., when they are not locked closed). In accordance with IWV-3416 (Reference 2.1), these valves will be exercised just prior to entering Modes 5 & 6, with the above conditions, and quarterly thereafter. Each valves passive function or leak

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tightness for containment isolation applies to Modes 1-4 and is tested in accordance with IWV-3422.

ISI-203 Rev. 8 Page 37 of 228

OS1 VALVE RELIEF RE UEST RV-1

'System: Containment HVAC Valve: 1CB-3,7 :1CM-7

,Category: AC Class:

Function: Containment Vacuum Relief Isolation Check Valves (1CB-3,7), and Hydrogen Purge Make-up Isolation Valve (1CM-7).

Test Verify forward flow operability and reverse flow Requirements: closure.

Basis for Relief: These are inside Containment simple check valves and do not have position verification capability. To verify forward flow operability using system fluid would require injecting large quantities of air into the Containment and would result in .a Containment overpressurization condition. The only practical method to verify forward flow operability is by mechanically exercising the. valve disk through a complete cycle by hand. Entry into Containment during cold shutdown is limited by plant procedures to perform only necessary repair and maintenance work. In cases of short shutdowns caused by problems external to the Containment there may be no entry made into the Containment. The only method available to verify reverse flow closure is by valve leak rate testing during Appendix J, Type C, Testing at refueling.

Alternate Testing: Verify forward flow operability by using a manual exercising procedure via a spring scale at Refueling. Verify reverse flow closure during Appendix J, Type C, Testing at Refueling.

ISI-203 Rev. 8 Page 38 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: CONTAINMENT HVAC DMG. NO. 2165-6-1017 VALVE CLASS VALVE SIZE ACTH. NORM. TEST STROKED CHECK C.S. C.S. REV.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DMG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1CB-2 2 24 AO C FS-1 C NOTE 1,5 G-15 BF TS-1 0 FC-1 PI-5 LJ-3 1CB-3 2 AC 24 SA C FS-1 FF RV-1 SP-3 NOTE 1,5 G-16 CK BS-1 BS RV-1 SP-3 LJ-3 1CB-6 2 24 AO C FS-1 C NOTE 1,5 H-15 BF TS-1 0 FC-1 PI-5 LJ-3 1CB-7 2 AC SA C FS-1 FF RV-1 SP-3 NOTE 1,5 H-16 BS-1 BS RV-1 SP-3 LJ-3 1CM-2 2 3 AO C FS-1 C NOTE 2,5,6 C-16 BF TM-1 FC-1 PI-5 LJ-3 1CM-4 2 3 MA LC PV NOTE 2,5,6 C-14 BF LJ-3 1CM" 5 2 3 MA LC PV NOTE 2,5,6 H-14 BF LJ-3 1CM-7 2 AC 3 SA C FS-1 FF RV-1 SP-3 NOTE 2,5,6 H-16 CK BS-1 BS RV-1 SP-3 LJ-3 1CP-1 2 A 42 AO C FS-3 C NOTE 4,5 E-15 BF TS-3 FC-3 PI-5 LJ-3 ISI-203 Rev. 8 Page 39 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: CONTAINMENT HVAC DWG. NO. 2165-S-1017 VALVE CLASS VALVE SIZE ACTH. NORM. TEST STROKED CHECK C.S. C.S.

NUMBER (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1CP-3 2 A 8 AO 0/C FS-1 NOTE 3,5 F-15 BF TS-1 FC-1 PI-5 LJ-3 1CP-4 2 42 AO C FS-3 NOTE 4,5 E-16 BF TS-3 FC-3 PI-5 LJ-3 1CP-5 2 8 AO 0/C FS-1 NOTE 3,5 F-16 BF TS-1 FC-1 PI-5 LJ-3 1CP-6 2 8 AO 0/C FS-1 C NOTE 3,5 F-15 BF TS-1 FC-1 PI-5 LJ-3 1CP-7 2 42 AO C FS-3 NOTE 4,5 G-15 BF TS-3 FC-3 PI-5 LJ-3 1CP-9 2 8 AO 0/C FS-1 C NOTE 3,5 F-16 BF TS-1 FC-1 PI-5 LJ-3 1CP-10 ~

2 42 AO C FS-3 NOTE 4,5 G-16 BF TS-3 FC-3 PI-5

~ LJ-3 ISI-203 Rev. 8 Page 40 of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.2 VALVE TEST TABLES AND RELIEF REQUESTS FOR REACTOR AUXILIARYBUILDING (RAB) HVAC DWG. NO. 2168-G-517 S03 ISI-203 Rev. 8 Page 41 'of 228

OS1 SYSTEM: Reactor Auxiliar Buildin HVAC NO. NOTE NONE ISI-203 Rev. 8 Page 42 of 228

OS1 SHEARON HARRIS NUCLEAR PONER PLANT VALVE TEST TABLE SYSTEM: REACTOR AUXILIARY BUILDING HVAC DMG. NO. 2168-G-517 S03 CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S. REV.

AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

3AV-B1SA-1 3 B 20 HO C FS1 0 F-14 BF TM-1 PI-5 3AV-B2SA-1 3 20 HO C FS-1 0 F-17 BF TH-1 PI-5 3AV-B3SB"1 3 6 HO C FS-1 0 E"14 BF TH-1 PI-5 3AV-B4SB-1 3 20 HO C FS 1 0 G-14 BF TH-1 PI-5 3AV-BSSB-1 3 20 HO C FS1 0 G-17 BF TM-1 PI-5 3AV-B6SA-1 3 6 HO C FS 1 0 G-14 BF TH-1 PI-5 3AV-V3-1 3 6 SA C FS-1 FF E-14 CK 3AV-V4-,1 3 6 SA C FS-1 G-14 CK ISI-203 Rev. 8 Page 43 of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.3 VALVE TEST TABLES AND RELIEF REQUESTS FOR CONTROL ROOM HVAC DWG. NO. 2165-S-1017 ISI-203 Rev. 8 Page 44 of 228

OS1 SYSTEM: CONTROL ROOM HVAC NO. NOTE The backseat function of these valves is only required during normal control room HVAC operation. During post accident operations there will either be forward flow through the valves or conditions will be such that reverse flow through them is not possible.

ISI-203 Rev. 8 Page 45 of 228

OS1 SHEARON HARRIS NUCLEAR POHER PLANT VALVE TEST TABLE SYSTEM: CONTROL ROOM NVAC DMG. NO. 2165-S-1017 VALVE CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR ALT.

COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1CZ-1 3 B 16 0 FS-1 C H-2 BF TM-1 PI"5 1CZ-2 3 B 16 0 FS-1 C H-2 BF TM-1 PI-5 1CZ 3 3 B 12 0 FS-1 C E-2 BF TH-1 PI-5 1CZ-4 3 12 HO 0 FS-1 E-2 BF TH-1 PI-5 1CZ-9 3 12 HO C FS-1 O,C N"5 BF TH-1 PI-5 1CZ-10 3 12 HO C FS-1 O,C N-5 BF TH-1 PI-5 1CZ-11 3 12 HO C FS-1 O,C N-11 BF TM-1 PI-5 1CZ-12 3 12 HO C FS-1 O,C N-11 BF TH-1 PI-5 1CZ-13 3 30 C FS-1 B-4 BF TM-1 PI-5 1CZ-14 3 30 C FS-1 B-4 BF TH-1 PI-5 1CZ-17 3 36 C FS-1 G-2 BF TH-1 PI-5 1CZ-18 3 36 C FS-1 G-2 BF TM-1 PI-5 ISI-203 Rev. 8 Page 46 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: CONTROL ROOM HVAC DWG. NO. 2165-6-1017 VALVE CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S.

NUMBER AND (CAT.) (IN. ) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1CZ-19 3 B 20 HO C FS-1 0 H-7 BF TH-1 PI-5 1CZ-20 3 20 HO C FS-1 0 H-6 BF TH-1 PI-5 1C2-21 3 20 HO C FS1 0 K-6 BF TM-1 PI-5 1CZ-22 3 20 HO C FS-1 0 K"37 BF TM-1 PI-5 1CZ-23 3 20 HO C FS-1 0 L-6 BF TM-1 PI-5 1CZ-24 3 20 C FS-1 0 L-7 BF TM-1 PI-5 1CZ-25 3 36 HO 0/C FS-1 0 G 4 BF TH-1 PI-5 1CZ-26 3 36 HO 0/C FS 1 0 H-4 BF TH-1 PI-5 1CZ-15 3 C 6 SA C FS-1 FF NOTE 1 L-7 CK 1CZ-16 3 C 6 SA 0 FS" 1 FF NOTE 1 L-7 CK I

ISI-203 Rev. 8 Page 47 of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.4 VALVE TEST TABLES AND RELIEF REQUESTS FOR FUEL BUILDING HVAC DWG. NO. 2168-G-533 ISI-203 Rev. 8 Page 48 of 228

OS1 SYSTEM: FUEL BUILDING HVAC NO. NOTE NONE ISI-203 Rev. 8 Page 49 of 228

OS1 SHEARON HARRIS NUCLEAR PONER PLANT VALVE TEST TABLE SYSTEH: FUEL BUILDING HVAC DNG. NO. 2168-G-517 533 VALVE CLASS VALVE SIZE ACTU. NORH. TEST STROKED CHECK C.S. C.S.

NUNS ER AND (CAT.) (IN. ) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DNG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERP.

3FV-B2SA- 3 B 24 HO C FS1 0 1-4 G-14 BF TM-I PI-5 3FV-B4SB-1 4 3

F-14 B

'F24 HO C FS 1 TH-I 0

PI-5 ISI-203 Rev. 8 Page 50 of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.5 VALVE TEST TABLES AND RELIEF REQUESTS FOR SWITCHGEAR AND PROTECTION ROOM HVAC DWG. NO. 2168-G-517 S05 ISI-203 Rev. 8 Page 51 of 228

OS1 SYSTEM: SWITCHGEAR AND PROTECTION ROOM HVAC NO. NOTE Valises close and Blowers shutdown on a SIS signal.

ISI-203 Rev. 8 Page 52 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: SWITCHGEAR Sc PROTECTION ROOM HVAC DWG. NO. 2168-G-517 S05 VALVE CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S.

NUMBER AND (CAT.) (IN. ) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. .TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

3CZ-B5SA-1 3 12 0 FS-1 C NOTE 1 L-3 BF TM-1 PI-5 3CZ-B6SB-1 3 12 0 FS-1 C NOTE 1 L-3 BF TM-1 PI-5 3CZ-B7SA-1 3 B 12 MO 0 FS"1 C NOTE 1 K"10 BF TM-1 PI-5 3CZ-B8SB-1 3 B 12 MO 0 FS-1 C NOTE 1 K-9 BF TM-1 PI-5 ISI-203 Rev. 8 Page 53 of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.6 VALVE TEST TABLES AND RELIEF REQUESTS FOR MAIN STEAM DWG. NO. 2165-S-542 ISI-203 Rev. 8 Page 54 of 228

OS1 SYSTEM: MAIN STEAM NO. NOTE Main Steam to Auxiliary Feedwater Pump Turbine Trip and Throttle Valves.

Main Steam Sample Valves.

Main Steam Relief Valves.

4 Main Steam Power Operated Relief Valves. Valves are Nitrogen supplied, electro/hydraulic operated globe

'valves.

Main Steam to Auxiliary Feedwater Turbine Line Block Valves.

Main Steam Supply to Auxiliary Feedwater Turbine Line Check Valves. Partial forward flow operability is verified by Turbine operation. Reverse flow closure is required to prevent steam flow between the Main Steam lines when line block valves are open (both block valves open on system isolation).

Main Steam Line Isolation Valves. Valve operators are designed to perform a partial stroke closed test with full steam flow.

Bypass Line Valves around the Main Steam Line Isolation Valves.

Main Steam Line drip leg drain Isolation Valves.

ISI-203 Rev. 8 Page 55 of 228

OS1 COLD SHUTDOWN TEST JUSTIFICATION CS-1 System: Main Steam Valve: 1MS-58,60,62 Category: B Class:

ASME Section XI Quarterly Test Requirements: Exercise, Time and Fail.

Cold Shutdown Test Justification: Exercising these valves during normal operation would cause a decrease in Main Steam line pressure and an increase in secondary system steam demand, resulting in a serious self imposed plant transient. This transient could result in a forced plant shutdown.

Quarterly Part Stroke Testing: Valves are full stroke on initiation and cannot be partial .stroke exercised.

Cold Shutdown Testing: Exercise, time and fail.

ISI-203 Rev. 8 Page 56 of 228

OS1 COLD SHUTDOWN TEST JUSTIFICATION CS-2 System: Main Steam Valve: 1MS-80,82,84 Category:

Class:

ASME Section XI Quarterly Test Requirements: Exercise, Time and Fail.

Cold Shutdown Test Justification: Exercising these valves during normal operation isolates one line of steam flow to the Turbine and would cause a severe pressure transient in the Main Steam line which could result in a forced plant shutdown. Reducing power level to perform testing without causing a transient would significantly impact plant operations and power production.

Quarterly Part Stroke Testing: Valves are equipped with a partial stroke closed exerciser and will be partial stroke exercised Quarterly.

Cold Shutdown Testing: Exercise, time and fail.

ISI-203 Rev. 8 Page 57 of 228

OS1 VALVE RV-1 System: Main Steam Valve: 1MS-G Category:

Class:

Function: Auxiliary feedwater steam driven turbine Governing Valve (1MS-G)

Test Requirements: Measure stroke time Quarterly.

Basis for Relief: The purpose .of this valve is to regulate steam flow to the AFP steam driven turbine.

Operability is adequately demonstrated by proper turbine operation. Valve position is steam line pressure and turbine speed dependent and therefore will not repeatedly throttle to the same position. During turbine operation this valve moves in response to control signals.

Alternate Testing: Proper operation of this valve will be verified during turbine testing. No stroke time testing will be performed.

ISI-203 Rev. 8 Page 58 of 228

OS1 VALVE RELIEF RE UEST RV-2 System: Main Steam Valve: 1MS-71,73 Category:

Class:

Function: Main Steam to Auxiliary Feedwater Pump Turbine Line Check Valves.

Test Requirements: Verify forward flow and reverse flow closure.

Basis for Relief: The only possible method to verify forward flow operability is by running the Auxiliary Feedwater Pump Turbine at full flow conditions.

The quarterly pump test is performed with flow through a minimum flow line which is not a full flow test. These check valves are also safety-related to prevent cross-flow between the Main Steam lines when the upstream motor operated valves are open (both motor operated valves open on initiation of Auxiliary Feedwater). To verify reverse flow closure would require blanking (the turbine stop valve is not a leak tight valve) the turbine line, injecting fluid into the'line and monitoring upstream of the valves for evidence of gross leakage. Upstream of these valves are the Main Steam lines and Steam Generators. Because of the long time to perform this test and the large volume of waste water involved, it is not a practical test method.

Alternate Testing: Both valves will be partial flow exercised in the forward direction quarterly during Auxiliary Feedwater Pump testing and one of the Check valves will be disassembled at Refueling and visually inspected. Alternate valves will be inspected at each Refueling, unless the inspected valve fails to pass inspection. If either valve fails to pass inspection the other valve will also be disassembled and inspected.

Both valves will be full flow exercised in the forward direction on a cold shutdown frequency when the full. flow test on the Turbine Driven Aux Feed Pump is performed.

ISI-203 Rev. 8 Page 59 of 228

OS1 SHEARON HARRIS NUCLEAR PONER PLANT VALVE TEST TABLE SYSTEH: MAIN STEAM DHG. NO. 2165-S-542 CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S.

AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

AND TEST OR ALT.

COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1HS-G 3 B 4 EH 0 FS-1 NOTE 1 N-1 GL TH-1 RV-1 SP-1 1MS-T 3 B 4 HO 0 FS-1 NOTE 1 N-1 GL TM-1 PI-5 1HS-25 2 B 1 AO <<0/C FS-1 NOTE 2 D-2 GL TH-1 FC-1 PI-5 1HS-27 2 B 1 AO 0/C FS"1 NOTE 2 G-2 GL TH-1 FC-1 PI-5 1HS-29 2 B 1 AO 0/C FS-1 NOTE 2 K-2 GL TM-1 FC-1 PI-5 1HS-43 2 C 6X10 SA C NOTE 3 C-3 RL 2 C 6X10 SA C NOTE 3 G-3 RL 1HS-45 2 C 6X10 SA C NOTE 3 J-3 RL 1HS-46 2 C 6X10 SA C NOTE 3 C-4 RL 1HS-47 1HS-46 ""

1HS" 49 2

G-4 2

J"4 2

C-5 C

C C

RL'OTE 6X10 RL 6X10 RL 6X10 SA SA SA C

C C

NOTE 3 NOTE 3 3

1HS-50 2 C 6X10 SA C RL-4 NOTE 3 G-5 r RL ISI-203 Rev. 8 Page 60 of 228

OS1 SHEARON HARRIS NUCLEAR POHER PLANT VALVE TEST TABLE SYSTEH: MAIN STEAH DNG. NO. 2165-S-542 CLASS AND VALVE (CAT.)

SIZE (IN.)

ACTU.

TYPE NORH.

POS.

TEST REQ.

STROKED DIRECT.

CHECK VALVE

'.S.

JUST.

C.S.

OR NO.

AND TEST OR ALT.

COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1HS-51 2 C 6X10 SA C NOTE 3 J-5 RL 1HS-52 2 C 6X10 SA C C-6 RL 1HS-53 2 C 6X10 SA C NOTE 3 G-6 RL 1HS-54 2 C 6X10 SA C NOTE 3 J-6 RL 1HS-55 2 C 6X10 SA C NOTE 3 C-6 RL 1HS-56 2 C 6X10 SA C NOTE 3 G-6 RL 1HS-57 2 C 6X10 SA C RL-4 NOTE 3 J-6 RL 1HS-58 .2 BC 8 EH FS-1 CS-1 FS-2 NOTE 4 C-8 GL NO TH-1 CS-1 IM"2 FC-1 CS-1 FC-2 PI-5 1HS-60 2 F-8 BC 8,,EH C FS-1 CS-1 FS-2 NOTE 4 GL NO TH-1 CS-1 TH-2 FC-1 CS-1 FC-2 PI-5 1HS-62 2 BC 8 EH C FS-1 CS-1 FS-2 NOTE 4 J"8 GL NO TM-1 CS-1 TH-2 FC-1 CS-1 FC-2 PI-5 1MS-70 2 B 6 HO C FS-1 NOTE 5 H-7 GA TH-1 PI-5 1HS-71 3 C 6 SA C FS-1 FF RV-2 PE-1 NOTE 6 H-7 CK BS-1 BS RV-2 DS 1HS-72 2 K-7 B,6 GA HO C FS-1 TH-1 NOTE 5 PI-5 ISI-203 Rev. 8 Page 61 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEH: HAIN STEAM DWG. NO. 2165-S-542 VALVE CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S. REV.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ. NO. PERF.

1MS" 73 3 SA C FS-1 FF RV-2 PE-1 NOTE 6 K-7 BS-1 BS RV-2 DS 1HS" 80 2 32 0 FS-1 C CS-2 FS-2 NOTE 7 D-9 GL TS-1 CS-2 TS-2 FC-1 CS-2 FC-2 PI-5 PE-1 1MS-81 2 3 AO C FS-1 C NOTE 8 D-9 GL TS-1 FC-1 PI-5 1HS-82 2 32 0 FS-1 C CS-2 FS-2 NOTE 7 G-9 GL TS-1 CS-2 TS-2 FC-1 CS-2 FC-2 PI-5 PE-1 1HS-83 2 3 AO C FS-1 C NOTE 8 N"9 GL TS-1 FC-1 PI-5 IMS-84 2 32 0 FS-1 C CS"2 FS-2 NOTE 7 J-9 GL TS-1 CS-2 TS-2 FC-1 CS-2 FC-2 PI-5 PE-1 1HS-85 2 3 AO C FS-1 C NOTE 8 K-9 GL TS-1 FC"1 PI-5 1HS-231 2 2 AO 0 FS" 1 C NOTE 9 E-8 GL TS-1 FC-1 .

PI-5 1HS-266 2 2 AO FS"1 NOTE 9 I-8 GL TS-1 FC-1 PI-5 1HS-301 2 2 AO 0 FS-1 NOTE 9 L-8 GL TS-1 FC-1 PI-5 ISI-203 Rev. 8 Page 62 of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.7 VALVE TEST TABLES AND RELIEF REQUESTS FOR FEEDWATER DWG. NO. 2165-S-544 ISI-203 Rev. 8 Page 63 oE 228

OS1 SYSTEM: FEEDWATER NO. NOTE Feedwater Isolation Valves, close on isolation signal.

Valves are equipped with partial stroke operators for testing at full flow.

Chemical Addition Isolation Valves.

3. Feedwater Isolation Valve Bypass Valves which close on an isolation signal.

ISI-203 Rev. 8 Page 64 of 228

OS1 COLD SHUTDOWN TEST JUSTIFICATION CS-1 System: Feedwater Valve: 1FW-159,217,277 Category: B Class:

ASME Section XI Quarterly Test Requirements: Exerci,se, Time and Fail.

Cold Shutdown Test Justification: Exercising these valves closed during normal operation would result in a loss of Feedwater to the associated Steam Generator. Isolation of Feedwater flow during normal operation would cause a severe Steam Generator operating transient which could result in a forced plant shutdown and/or Reactor trip.

Quarterly Part Stroke Testing: Valves are equipped with partial stroke exercisers. Each valve will be exercised to it's 90% open position and back to the full open position.

Cold Shutdown

- Testing: Exercise, Time and Fail.

ISI-203 Rev. 8 Page 65 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: FEEDWATER DWG. NO. 2165-S-544 VALVE CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR ALT.

COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERP.

1FW-159 2 B 16 EH 0 FS-1 CS-1 FS-2 NOTE 1 B-6 GA TS-1 CS-1 TS-2 FC-1 CS-1 FC-2 PI-5 PE-1 1FW-163 2 B 1 AO 0/C FS-1 NOTE 2 B-6 GA TS-1 FC-1 PI-5 1FW-165 2 B 1 AO 0/C FS-1 NOTE 2 B-5 GA TS-1 FC-1 PI-5 1FW-217 2 B 16 EH 0 FS-1 CS-1 FS-2 NOTE 1 D-4 GA TS"1 CS-1 TS-2 FC"1 CS-1 FC-2 PI-5 PE-1 1FW-221 2 B 1 AO 0/C FS-1 C NOTE 2 D-4 GA TS-1 FC-1 PI-5 1FW-223 2 B 1 AO 0/C FS-1 NOTE 2 D-4 GA TS-1 FC-1 PI-5 1FW-277 2 B 16 EH FS-1 CS-1 FS-2 NOTE 1 E-4 GA TS-1 CS-1 TS"2 FC-1 CS-1 FC-2 PI-5 PE-1 1FW-279 2 B 1 AO 0/C FS" 1 C NOTE 2 E-4 GA TM-1 FC-1 PI-5 1FW-261 2 B 1 AO 0/C FS-1 NOTE 2 E"3 GA TM-1 FC-1 PI-5 IFW-307 2 B 3 AO TH FS-1 NOTE 3 B-6 GA TM-1 FC"1 PI"5 1FW-313 B

' AO FS-1 2'-4 TH NOTE 3 GA TM-1 FC-1 PI-5 1FW-319 2 B 3 AO TH FS-1 NOTE 3 F-4 GA TM-1 FC-1 PI-5 ISI-203 Rev. 8 Page 66 of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.8 VALVE TEST TABLES AND RELIEF REQUESTS FOR AUXILIARY FEEDWATER DWG. NO. 2165-S-544 ISI-203 Rev. 8 Page 67 of 228

OS1 SYSTEM: AUXILIARY FEEDWATER NO. NOTE Auxiliary Feedwater Bypass Line to Condensate Storage Tank Line Check Valve. Failure to close would not degrade system operation.

DELETED Motor Driven Auxiliary Feed Pump Discharge Check Valve. Reverse flow closure necessary to preclude diversion of flow back across idle pump.

Motor Driven Pump Discharge Pressure Control Valves.

Valves are installed in the discharge lines of the motor driven pumps and regulate pump discharge pressure to prevent pump damage caused from a runout condition. The valves prevent pump runout by automatically throttling as Steam Generator pressure decreases. Valves are normally open when the system is in standby and automatically throttle in response to line pressure on initiation.

Mot'or Driven and Steam Driven Pump Discharge Flow Control Valves. Each of the six Pump discharge lines contains a remote-manually controlled flow control valve. Flow from 0 to 100 Percent is manually selected using remote control logic switches. In addition to flow control, the valve control logic causes the valves to close in each Steam Generator Feedwater Header if a Feedwater Header rupture or Main Steam Header rupture occurs.

Pump Discharge Line Check Valves. Valves prevent cross flow between the motor driven and steam driven .

pump discharge headers and reverse flow from the Steam Generators back through the pumps. Each flow path contains three check valves in series.

Auxiliary Feedwater Motor-operated Isolation Valves.

Valves allow for isolation of each header for maintenance or header rupture.

Auxiliary Feedwater Isolation From Normal Feedwater Valves.

Auxiliary Feedwater Isolation From Normal Feedwater Check Valves'0.

Auxiliary Feedwater Inlet to Steam Generator Check Valves.

Chemical Addition Valves. Valves are normally closed when the system is idle. Chemicals are added as necessary when the system is in operation.

ISI-203 Rev. 8 Page 68 of 228

OS1 COLD SHUTDOWN TEST JUSTIFICATION CS-1 System: Auxiliary Feedwater Valve: 1AF-64,81,102 Category: B Class:

ASME Section XI Quarterly Test Requirements: Exercise, Time and Fail.

Cold Shutdown Test Justification: These six inch valves are normally open and supply eighteen percent of the normal Feedwater to the Steam Generators. Exercising during normal operation would cause Steam Generator transients and would have a significant undesirable effect on plant operations.

Quarterly Part Stroke Testing: Valves are full stroke on initiation and cannot be partial stroke exercised.

Cold Shutdown Testing. Exercise, Time and Fail.

ISI-203 Rev. 8 Page 69 of 228

OS1 COLD SHUTDOWN TEST JUSTIFICATION CS-2 System: Auxiliary Feedwater Valve: lAF-16, 31 Category:

Class:

Function: Motor Driven Auxiliary Feedwater Pump discharge check valves.

Test Requirements: Verify forward flow operability and reverse flow closure.

Basis for Relief: The only way to verify forward flow operability is by operating the motor driven Auxiliary Feedwater pumps and injecting relatively cold condensate water directly into the hot Steam Generators. The introduction of cold water into the hot Steam Generators during normal operation would result in large thermal shock to the Feedwater Nozzles which could cause cracking of the nozzles. In addition, to test Auxiliary Feedwater during normal operation would require starting the Auxiliary Feedwater pumps and securing the normal Feedwater System flow, which would have an adverse effect on Steam Generator water level control and could cause a forced plant shutdown. Quarterly pump testing is done through the pump recirculation lines and the downstream flow control valves automatically close so that the pumps are essentially isolated from each other and reverse flow closure of these pump discharge check valves cannot be verified until full Auxiliary Feedwater flow is injected into the Steam Generators.

Alternate Testing: i Verify forward flow operability and reverse flow closure on a cold shutdown frequency when full flow test is performed on motor driven auxiliary feed pumps.

ISI-203 Rev. 8 Page 70 of 228

OS1 COLD SHUTDOWN TEST JUSTIFICATION CS-3 System: Auxiliary Feedwater Valve: 1AF-19,34,49,50,51,129,130,131 Category: B Class:

Function: lAF-19,34: Auxiliary Feedwater Pump Discharge Pressure Control Valves.

1AF-49.,50,51,129,130,131: Auxiliary Feedwater Pump Discharge Flow Control Valves.

Test Requirement: Exercise, Time, and Fail Basis for Relief: Position of these valves is automatically modulated during pump operation to control Auxiliary Feedwater flow rate. To test these valves would require use of control logic defeating methods, such as temporary jumpers.

In order to minimize the impact on the auxiliary feedwater system by forcing these valves to their non fail safe position, valve testing will be performed on a cold shutdown frequency.

Alternate Testing: Exercise, time and fail on a cold shutdown frequency.

I ISI-203 Rev. 8 Page 71 cf 228

OS1 COLD SHUTDOWN TEST JUSTIFICATION CS-4 System: Auxiliary Feedwater Valve: 1AF-54,73,92,201,202,203 Category:

Class:

Function: Motor driven Auxiliary Feedwater Pump discharge check valves.

Test Requirements: Verify forward flow operability.

Basis for Relief: The only way to verify forward flow operability is by operating the motor driven Auxiliary Feedwater pumps and injecting relatively cold condensate water directly into the hot Steam Generators. The introduction of cold water into the hot Steam Generators during normal operation would result in large thermal shock to the Feedwater Nozzles and could cause cracking of the nozzles.'n addition, to test the Auxiliary Feedwater during normal operation would require starting the Auxiliary Feedwater pumps and securing the normal Feedwater System flow, which would have an adverse effect on Steam Generator water level control and could cause a forced plant shutdown.

Alternate Testing: Verify full forward flow operability at cold shutdown when the Auxiliary Feedwater Pumps are being full flow tested.

ISI-203 Rev. 8 Page 72 of 228

OS1 COLD SHUTDOWN JUSTIFICATION CS-5 System: Auxiliary Feedwater Valve: 1AF-117, 136, 142, 148, 204, 205, 206 Category:

Class:

Function: Steam driven Auxiliary Feedwater pump line to Steam Generator series check valves.

Test Requirement: Verify forward flow operability.

Basis for Relief: These valves can only be forward flow operability tested by operation of the steam driven pump and injection of full flow to the Steam Generators, 'which cannot be done during normal operations (See CS-2). The only source of steam to the steam driven turbine is from the Main Steam System. To operate the turbine requires that the Steam Generators be producing sufficient steam to drive the turbine. Control of Steam Generator .water level when producing steam is much more critical than during the refilling process, where the motor operated pumps are tested. To perform flow testing during steam production would have a significant impact on Steam Generator water level control on all three Steam Generators, would require a significant amount of startup time and could result in a forced plant shutdown.

Alternate Testing: Perform full forward flow operability testing of these valves during full steam driven pump testing on a cold shutdown frequency when the impact on plant operations will be minimized.

ISI-203 Rev. 8 Page 73 of 228

OS1 COLD SHUTDOWN JUSTIFICATION CS-6 System: Auxiliary Feedwater Valve: 1AF-117 Category:

Class:

Function: 1C-SAB Discharge Check Valve Test Requirements: Verify reverse flow closure.

Basis for Relief: The system has no design provision for verification of reverse flow closure. The only possible test method involves pressurizing the downstream section of pipe and monitoring an upstream tap for evidence of gross leakage performing this at power could result in a loss of steam generator level control and could cause a plant shutdown.

Alternate Testing: Verify reverse flow closure on a cold shutdown frequency when test can be performed with little impact on plant condition.

ISI-203 Rev. 8 Page 74 of 228

OS1 VALVE RELIEF RE UEST RV-1 System: Auxiliary Feedwater Valve: 1AF-65, 84, 103 Category:

Class:

Function: Auxiliary Feedwater Isolation From Normal Feedwater Line Check Valves.

Test Requirements: Verify reverse flow closure.

Basis for Relief: The system has no design provision for verification of reverse flow closure. The only possible test method involves pressurizing the downstream section of pipe and monitoring an upstream tap for evidence of gross leakage.

This method involves filling and draining large segments of the system. Because of the time involved, ALARA consideration and large amounts of wastes, it is not practical to perform testing except at refueling. The only other alternative testing is to disassemble and visually inspect each valve.

Alternate Testing: One valve will be disassembled and visually inspected at each refueling, and alternate valves will be done during subsequent refuelings. Failure to pass inspection will initiate disassembly and inspection of the other two valves.

ISI-203 Rev. 8 Page 75 of 228

OS1 VALVE RELIEF RE UEST RV-2 "System: Auxiliary Feedwater Valve: 1AF-201, 202, 203 204, 205, 206 Categoiy:

Class:

Function: Auxiliary Feedwater Pump Discharge Line to Feedwater Line Check Valves.

Test Requirement: Verify reverse flow closure.

Basis for Relief: The system has no'design provision for verification of reverse flow closure. The only possible test method involves pressurizing the downstream section of pipe and monitoring an upstream tap for evidence of gross leakage.

This method involves filling and draining large segments of the system. Because of the time involved, ALARA consideration, and large amounts of wastes, it is not practical to perform testing except at refueling. The only other alternative testing is to disassemble and visually inspect each valve.

Alternate Testing: During normal plant operation, the valves 1AF-201, 202, 203, 204, 205, and 206 will be verified to be in the closed position through the continual monitoring of installed temperature elements. Unacceptable conditions require action in accordance with Plant Operating Procedure. In addition, 1 valve off of the Motor Driven Train and 1 valve off Turbine Driven Train will be disassembled and inspected at each refueling, and alternate valves will be done during subsequent refuelings. Failure to pass inspection will initiate disassembly and inspection of the other valves on the same train.

ISI-203 Rev. 8 Page 76 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: AUXILIARYFEEDWATER DWG. NO. 2165-S-544 CLASS VALVE SIZE ACTH. NORM. TEST STROKED CHECK C.S. C.S.

AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

lAF-4 3 C 2 SA C FS-1 NOTE 1 N-6 CK 1AF-16 3 C 4 SA C FS-1 FF CS-2 FF-2 NOTE 3 L-6 CK BS-1 BS CS-2 BS-2 1AF-19 3 B 4 EH 0 FS-1 CS-3 FS-2 NOTE 4 K-6 GL FO-1 ,FO-2 PI-5 lAF-23 3 C 2 SA C FS"1 FF NOTE 1 N-9 CK 1AF-31 3 C 4 SA C FS-1 FF CS-2 FF-2 NOTE 3 L-8 CK BS-1 BS CS-2 BS-2 lAF-34 3 B 4 EH 0 FS-1 CS-3 FS-2 NOTE 4 K-8 GL FO-1 FO-2 PI-5 1AF-49 3 B 4 EH 0 FO-1 CS-3 FO-2 NOTE 5 J-6 GL PI-5 C FS-2 FS-1 TM-2 TM-1 1AF-50 3 B 4 EH 0 FO-1 C CS-3 FO-2 NOTE 5 J-7 GL FS-1 TM"2 TM-1 FS-2 PI-5 1AF-51 3 B 4 EH 0 FO-1 C CS-3 FO"2 NOTE 5 J-8 GL FS-1 FS-2 TM-1 TM-2 PI-5 1AF-54 3 C 4 SA C FS-1 FF CS-4 FF-2 NOTE 6 F-6 CK 1AF-55 2 B 4 MO 0 FS-1 NOTE 7 F-6 GA TS-1 PI-5 1AF-64 2 B 6 AO 0 FS-1 CS-1 FS-2 NOTE 8 C-6 GA TM-1 CS-1 TM-2 FC-1 CS"1 FC-2 PI-5 lAF-65 2 C 6 SA 0 FS-1 BS RV-1 DS NOTE 9 C-6 CK SP-3 ISI-203 Rev. 8 'age 77 'of 228

OS1 SHEARON HARRIS NUCLEAR P(NER PLANT VALVE TEST TABLE SYSTEM: AUXILIARY FEEDMATER DNG. NO. 2165-S-544 VALVE CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C. S. REMARKS REV.

NUMBER AND (CAT. ) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR ALT.

COOR. TYPE DIRECT. RELIEF TEST REQ. NO. PERF.

1AF-68 2 C 6 SA 0 FS-1 FF NOTE 10 C-2 CK 1AF-73 3 C 4 SA C FS-1 FF CS-4 FF-2 NOTE 6 H-7 CK 1AF-74 2 B 4 MO 0 FS-1 C NOTE 7 G-7 GA TS-1 PI-5 1AF-81 2 B 6 AO 0 FS-1 C CS-1 FS-2 NOTE 8 E-7 GA TM-1 CS-1 TM-2 FC-1 CS-1 FC-2 PI-5 1AF-84 2 C 6 SA 0 FS-1 BS RV-1 DS NOTE 9 E-5 CK SP-3 1AF-87 2 C 6 SA 0 FS-1 FF NOTE 10 K-2 CK 1AF-92 3 C 4 SA FS-1 CS-4 FF-2 NOTE 6 I-8 CK 1AF-93 2 B 4 ~

MO 0 FS-1 C NOTE 7 H-8 GA TS-1 PI-5 1AF-102 2 B 6 AO 0 FS-1 C CS-1 FS-2 NOTE 8 F-4 GA TM-1 CS-1 TM-2 FC"1 CS-1 FC-2 PI-5 1AF-103 2 C 6 SA 0 FS-1 BS RV-1 DS NOTE 9 F"4 CK SP-3 1AF-106 2 6 SA 0 FS"1 NOTE 10 G-2 IAF-110 3 C 2 SA FS-1 NOTE 1 N-11 CK 1AF-117 3 C 6 SA FS-1 FF CS-5 FF-2 NOTE 6 L-19 CK BS-1 BS CS-6 BS-2 IAF-129 3 B 4 EH 0 FO-1 CS-3 FO-2 NOTE 5 J-9 GL FS-1 FS-2 TM-1 TM-2 PI-5 IAF-130 3 B 4 EH 0 FO-1 CS-3 FO-2 NOTE 5 J-10 GL FS-1 FS-2 TM-1 TM-2 PI-5 ISI-203 Rev. 8 Page 78 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEH: AUXILIARY FEEDWATER DWG. NO. 2165-S-544 VALVE CLASS VALVE SIZE ACTU. NORH. TEST STROKED CHECK C.S. C.S.

NUHBER AND (CAT. ) (IN. ) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR ALT.

COOR. TYPE DIRECT. RELIEF TEST RFA}.NO. PERP.

1AF-131 3 B 4 EH 0 FO-1 C CS-3 FO-2 NOTE 5 J-11 GL ~ FS-1 FS"2 TH-1 TH-2 PI-5 1AF-136 3 4 SA C FS1 FF CS-5 FF-2 NOTE 6 F-6 CK 1AF-137 2 4 HO 0 FS-1 C NOTE 7 F-6 GA TS-1 PI-5 1AF" 142 3 4 SA C FS-1 FF CS-5 FF-2 NOTE 6 H-9 CK 1AF" 143 2 4 HO 0 FS 1 C NOTE 7 H-9 GA TS-1 PI-5 1AF-148 3 SA C FS-1 FF CS-5 FF-2 NOTE 6 H-7 1AF 149 2 B 4 HO 0 FS 1 C NOTE 7 G-7 GA TS" 1 PI-5 1AF-153 2 B 1 AO C FS-1 NOTE 11 B-4 GA TH-1 FC-1 PI-5 1AF-155 2 1 AO C FS-1 NOTE 11 B-3 GA TH-1 FC-1

~ PI-5 1AF-157 2 1 AO C FS-1 NOTE 11 G-4 GA TH-1 FC-1 PI-5 lAF-159 2 1 AO C FS-1 C NOTE 11 G-3 GA TH-1 FC-1 PI-5 1AF-161 2 1 AO C FS-1 C NOTE 11 K-4 GA TH-1 FC-1 PI-5 ISI-203 Rev. 8 Page 79 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: AUXILIARY FEEDWATER DWG. NO. 2165-S-544 VALVE CLASS VALVE SIZE ACTH. NORM. TEST STROKED CHECK C.S. C.S. REV.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERP.

1AF-163 2 B 1 AO C Fs 1 C NOTE 11 K-3 GA TM-1 FC-1 PI-5 1AF-201 3 H-5 CK'A 4 C PS-1 BS-1 FF BS CS-4 RV-2 FF-2 DS NOTE 9 1AF-202 . 3 SA C FS-1 FS CS-4 FF-2 NOTE 9 I-8 BS-1 BS RV-2 DS 1AF-203 3 SA C FS-1 FS CS-4 FF-2 NOTE 9 I-6 BS-1 BS RV-2 DS 1AF-204 3 C FS-1 'S CS-5 FF-2 NOTE 9 H-7 BS-1 BS RV-2 DS lAF-205 3 SA C FS-1 FS CS-5 FF-2 NOTE 9 H-10 BS-1 BS RV-2 DS 1AF-206 3 SA C FS-1 FS CS-5 FF-2 NOTE 9 H-ll BS-1 BS RV-2 DS ISI-203 Rev. 8 Page 80 of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.9 VALVE TEST TABLES AND RELIEF REQUESTS FOR CONDENSATE DWG. NO. 2165-S-545 ISI-203 Rev. 8 Page 81 of 228

OS1 SYSTEM: CONDENSATE NO. NOTE Condensate Storage Tank to Auxiliary Feedwater Pump Inlet Check Valves. Reverse flow closure required to prevent flow of service water into the Condensate Storage Tank.

Relief Valves which protect the Low Pressure Suction piping from back leakage across the Pump Discharge Check Valves.

ISI-203 Rev. 8 Page 82 of 228

OS1 COLD SHUTDOWN TEST JUSTIFICATION CS-1 System: Condensate Valve: 1CE-36,46,56 Category:

Class:

Function: Condensate Storage Tank to Auxiliary Feedwater Pump Inlet Check Valves.

Test Requirements: Verify forward flow operability.

Basis for Relief: The only way to verify full forward flow operability is by operating the motor driven Auxiliary Feedwater pumps and injecting relatively cold condensate water directly into the hot Steam Generators. The introduction of cold water into the Steam Generators during normal operation would result in large thermal shock to the Feedwater Nozzles and could cause cracking of the nozzles. In addition to test the Auxiliary Feedwater during normal operation would require starting the Auxiliary Feedwater pumps and securing the normal Feedwater System flow, which would have an adverse effect on Steam Generator water level control and could cause a forced plant shutdown.

Alternate Testing: Valves will be partial stroke exercised during quarterly pump testing with flow through the small pump recirculation line back to the Condensate Storage Tank. Valves will be full flow exercised on the way to cold shutdown when the Aux. Feed System is in operation.

ISI-203 Rev. 8 Page 83 of 228

OS1 VALVE RELIEF RE UEST RV-1 System: Condensate Valve: 1CE-36,46,56 Category:

Class:

Function: Condensate Storage Tank to Auxiliary Feedwater Pump Inlet Check Valve which prevents back-flow from the Service Water System into the Condensate Storage Tank.

Test Requirements: Verify reverse flow closure.

Basis for Relief: These valves are in the line from the Condensate Storage Tank to the Auxiliary Feedwater Pump Inlet and are upstream from the cross-tie with the Service Water System. In this location the valves prevent back-flow from the Service Water System into the Condensate Storage Tank. The only possible method to verify reverse flow closure would be by monitoring for a increase in tank level. This technique is not possible in this case because of the volume of the tank and the normal level changes which occur during normal operation.

Alternate Testing: One valve will be disassembled and visually inspected at refuel'ing and alternate valves will be done during subsequent refuelings. Only one' valve will be inspected at a refueling unless fails to pass inspection. Failure to pass it inspection will initiate disassembly and inspection of the other two valves.

ISI-203 Rev. 8 Page 84 of 228

OS1 SHEARON HARRIS NUCLEAR P(NER PLANT VALVE TEST TABLE SYSTEM: CONDENSATE DWG. NO. 2165-6-545 VALVE CLASS VALVE SIZE ACTH. NORM. TEST STROKED CHECK C.S. C.S.

NUMBER (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DNG. AND TEST OR ALT.

COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1CE-36 3 H"7 C 6 CK SA C FS-1 FS-1 BS-1 FF FF BS

'S-1 CS-1 RV-1 FF-2 PR-1 DS NOTE 1 ICE-46 3 C 6~ SA C FS-1 FF CS-1 FF-2 NOTE 1 H-8 CK FS-1 FF CS-1 'PE-1 BS-1 BS RV-1 DS 1CE-56 3 8 SA C FS-I FF CS-1 FF-2 NOTE 1 H-9 CK FS-1 FF CS-1 PE-1 BS-1 BS RV-1 DS 1CE-1157 3 1Xl SA C RL-4 NOTE 2 I-7 RL 1CE-1158 3 1X1 SA C RL-4 NOTE 2 I-8 RL 1CE-1159 3 1X1 SA C RL-4 NOTE 2 I-9 RL ISI-203 Rev. 8 Page 85 of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.10 VALVE TEST TABLES AND RELIEF REQUESTS FOR SERVICE WATER DWG. NO. 2165-S-547 2165-S-588 2165-S-936 ISI-203 Rev. 8 Page 86 of 228

Osl SYSTEM: SERVICE WATER NO. NOTE Pump Discharge Check Valves. Valves prevent backflow through the pumps.

CTMU Pump Inlet Isolation Valves.

Cross-tie to Normal Service Water Isolation Valves.

Valves Close to Isolate Non-Safety-Related Loads.

Thermal Relief Valve added to Program to comply with Noith Carolina State Requirements.

Emergency Service Water to Containment Fan Coolers Isolation Valves.

Emergency Service Water to Containment Fan Coolers Isolation Valves.

Orifice Bypass Valve. Valve closes on system initiation.

Back-up Water Supply to the Auxiliary Feedwater Pumps.

10. Normal CTMUP and EWS Water sources for ESW Intake Structure Fan Coolers. Valves are controlled by local temperature elements and as such are temperature control valves, exempt from Section ZI test requirements. Normal CTMUP isolates and ESW source initiates on loss of site power LOCA condition.

Valves are tested for fail-safe operation only.

Normal Service Water to the Non-Safety-Related Containment Fan Coolers. Can only be tested when the ~

Emergency Service Water system is in operation with flow through the Emergency Containment Fan Coolers Containment Isolation Valve.

12. Normal Service Water to Non-Safety-Related Containment Fan Coolers inside Containment Isolation Check Valve.

Reverse flow closure for Containment isolation.

13. Return Header Isolation Valves.

ISI-203 Rev. 8 Page 87 of 228

OS1 VALVE RELIEF RE UEST RV-1 System: Service Water Valve: 1SW-233 Category: AC Class:

Function: Normal Service Water System Inside Containment Isolation Check Valve.

Test Requirements: Verify reverse flow closure.

Basis for Relief: The only method available to verify reverse flow closure is by valv'e leak testing during Appendix J, Type C, Testing at refueling.

Alternate Testing: Reverse flow closure will be verified during Appendix J, Type C, Testing at refueling.

ISI-203 Rev. 8 Page 88 of 228

OS1 SBEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: SERVICE WATER DWG. NO. 2165-S-547 CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S.

AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR ALT.

COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1SW 9 3 C 30 SA C FS-1 FF NOTE 1 E" 2 CK BS-1 BS 1SW-10 3 C 30 SA C PS-1 FF NOTE 1 E-3 CK BS-1 BS 1SW-20 3 B 3 PO 0/C FS-1 0 NOTE 2 F-1 BA IH-2 FO-1 1SW-23 3 B 3 PO 0/C FS-1 0 NOTE 2 F-4 Bh TH-1 FO-1 1SW-39 3 B 30 HO 0/C FS-1 0 NOTE 3 1-1 BF TH-1 C PI-5 1SW-40 3 B 30 HO 0/C FS-1 0 NOTE 3 I-2 BF TH-1 C PI-5 1SW-60 3 C 3/4X1 RL C RL-4 NOTE 5 I-6 RL 1SW-86 3 C 14 SA 0/C FS-1 FF NOTE 6 F-6 CK BS-2 BS 1SW-91 2 B 8 HO 0 FS-1 0 NOTE 7 C-6 BF TS-1 - C PI-5 1SW-92 2 B 8 HO 0 FS-1 0 NOTE 7 C-7 BF TS-1 C PI-5 1SW-97 2 8 HO 0 FS-1 0 NOTE 7 C-8 BF TS-1 C PI-5 1SW-98 2 C-9 8

BF

'O 0 FS-1 TS-1 0

C NOTE 7 PI-5 1SW-95 2 1X14; SA C RL-4 NOTE 5 C-8 RL 1SW-96 2 1X1% SA C RL-4 NOTE 5 C-9 RL ISI-203 Rev. 8 Page 89 'of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEH: SERVICE WATER DWG. NO. 2165-S-547 CLASS VALVE SIZE ACTU. NORH. TEST STROKED CHECK C.S. C.S.

AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF REQ.NO. PERP.

1SW-109 2 8 HO 0 FS-1 0 NOTE 7 C-12 BF TS-1 C PI-5 ISW-110 2 8 HO 0 FS1 0 NOTE 7 C-13 BF TS-1 C PI-5 1SW-116 3 14 AO 0 FS-1 NOTE 8 H-7 BF TH-1 FC-1 PI-5 1SW-118 3 14 AO 0 PS-1 C NOTE 8 G-13 BF IH-1 FC-1 PI-5 1SW 121 3 8 HO C FS-1 NOTE 9 J-8 BF TH-1 PI-5 1SW-123 3 8 'O C FS-1 0 NOTE 9 J-8 BF IH-1 C PI-5 1SW-124 B 8 HO C FS-1 0 NOTE 9 I-8 BF TH-1 C PI-5 1SW-126 3 B 8 HO C FS-1 . 0 NOTE 9 I"8 BF TH-1 C PI-5 1SW-127 .3 8 C FS-1' NOTE 9 I-9 BF TH-1 C PI-5 1SW-129 3 8 C FS-1 0 NOTE 9 I-9 BF TH-1 C PI-5 ISW-130 3 8 C FS-1 0 NOTE 9 I-9 BF TH-1 C PI-5 1SW-132 3 8 C FS-1 0 NOTE 9 J-10 BF TH-1 C PI-5 ISI-203 Rev. 8 Page 90 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: SERVICE WATER DWG. NO. 2165-S-547 VALVE CLASS VALVE SIZE ACTU. NORH. TEST STROKED CHECK C.S. C.S.

NUHBER AND (CAT.) (IN. ) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERP.

1SW-141 3 1~ SA 0/C FS-1 FF H-8 CK BS 1SW-143 3 14 SA 0/C FS-1 FF H-9 CK BS 1SW-152 3 14 SA 0/C FS-1 FF H-10 CK BS r

1SW-154 2 14 SA 0/C FS-1 FF H-11 CK BS 1SW-163 3 1% SA 0/C FS-1 H" 11 CK ,BS 1SW-165 3 C 1% SA 0/C FS-1 FF H-12 CK BS ISW-107 ' C SA C NOTE 5 IX'L C-12 1SW-108 2 C 1X1% SA C NOTE 5 C-13 RL 1SW-171 3 C 3/4X1 SA C NOTE 5 F-11 RL 1SW-179 3 B 4 PO 0 FS"1 NOTE 4 I-15 GA TH-I FC-1 PI-5 ISW-180 3 B 4 PO 0 FS-1 NOTE 4 I-15 GA , TH-I FC-1 PI-5 ISW-204 3 B 4 PO 0 FS"1 NOTE 4 K-16 GA TH-I FC-1 PI-5 ISW-206 3 B 4 PO 0 FS-1 NOTE 4 K-16 GA TH-I FC-1 PI-5 ISW-220 3 C 14 SA 0/C FS-1 FF NOTE 6 ~

F"6 CK BS-1 BS 1SW-225 2 B 8 HO 0 FS-1 0 NOTE 7 C" 14 BF TS-1 C PI-5 ISI-203 Rev. 8 Page 91 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEH: SERVICE WATER DWO. NO. 2165-S-547 VALVE CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S. REV.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1SW-227 2 B 8 HO 0 FS-1 0 NOTE 7 C-14 BF TS-1 C PI-5 1SW-231 2 A 12 AO 0 FS-1 C NOTE 11 C-15 BF TS-1 FC-1 PI-5 LJ-3 1SW-233 2 AC 12 SA 0 FS-1 BS RV-1 SP-3 NOTE 12 C-15 CK LJ-3 ISW-240 2 A 12 0 FS-1 C NOTE 11 D-17 BF AO -TS-1 FC-1 PI-5 LJ-3 1SW-242 2 12 AO 0 FS-1 NOTE 11 E-17 BF TS-1 FC-1 PI"5 LJ"3 1SW-257 3 0 3/4XI SA C RL-4 NOTE 5 I-13 RL 1SW-270 3 30 HO C FS-1 0 NOTE 13 K-16 BF TH-1 C PI-5 1SW-271 3 30 HO C FS-1 0 NOTE 13 J-16 BF TH-1 C PI-5 I 1SW-274 3 30 HO 0 FS-1 0 NOTE 13 L"16 BF TH-1 C PI-5 1SW-275 3 30 HO 0 FS-1 0 NOTE 13 L-16 BF TH-1 C PI-5 1SW-276 3 36 HO 0 FS-1 0 NOTE 13 H-15 BF TH-1 C PI-5 ISI-203 Rev. 8 Page 92 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: SERVICE WATER DWG. NO. 2165-S-547 VALVE CLASS VALVE SIZE ACTH. NORM. TEST STROKED CHECK C.S. C.S.

NUMBER (CAT.) (IN. ) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF REQ.NO. PERP .

1MP-70 3 B 2 SO 0 FC-1 NOTE 10 C-18 GL PI-5 1MP-71 3 B 2 SO 0 FC-1 NOTE 10 C-19 GL PI-5 1SW-1000 3 B 2 SO C FO-1 0 NOTE 10 C-18 GL PI-5 1SW-1001 3 B 2 SO C FO-1 0 NOTE 10 C-19 GL PI-5 1SW-150 3 C 3/4X1 SA C NOTE 5 F-8 RL 1SW-160 3 C 3/4X1 SA C RL-4 NOTE 5 F-8 RL ISI-203 Rev. 8 Page 93 OE 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.11 VALVE TEST TABLES AND RELIEF REQUESTS FOR CONTAINMENT SPRAY DWG. NO. 2165-S-550 ISI-203 Rev. 8 Page 94 of 228

OS1 SYSTEM: CONTAINMENT SPRAY NO. NOTE Relief Valve which protects Safety-Related Equipment.

NaOH Additive Valves. Valves open on CSAC signal and close on low tank level.

CTMT Spray Eductor Test Valves. Valves close on system initiation.

RWST to Pump Inlet Block Valves. Valves close on switch over to recirculation mode.

RWST to Pump. Inlet Check Valves. Test line is large enough to verify full design forward flow.

Engineering Evaluation (PCR-3921) showed that at no time would sump water have the tendency to flow in the direction of the RWST. Therefore, backseat testing is not required.

Pump Test Line to RWST Block Valves. Valves close on system initiation.

Containment Isolation Valves.

NaOH Injection Check Valves. Reverse flow closure is required to separate headers, since both motor operated block valves open on initiation.

Containment Sump Isolation Valves. Valves open for Recirculation operating mode and close for CTMT isolation. Cycling will drain system water into the Stainless Steel sumps.

10. Spring loaded check valves used as vacuum breakers on the Spray Additive Tank. Valves open with a 0.17 Psid

"'maximum) across the valves. They will be treated and tested in a manner similar to relief valves. At each refueling, one of the valves will be tested. Failure of valve to pass test will result in other valve being tested.

ISI-203 Rev. 8 Page 95 of 228

OS1 COLD SHUTDOWN TEST JUSTIFICATION CS-1 System: Containment Spray Valve: 1CT-102,105 Category: B Glass:

Function: Containment Recirculation Sump Isolation Valves.

Test Requirements: Exercise and Time Basis for Relief: Exercising these valves, even with the in-line block valves closed, would result in a small amount of water being drained into the Containment Sump.'his highly oxygenated; stagnant water could result in excessive corrosion of the sump structure. The amount of water is insufficient to insure adequate pump NPSH so it cannot be removed with the system pumps. There are no provisions for removing the water except by a temporary sump pump and entering the sump to hand dry the wetted surfaces.

Alternate Testing: Exercise and Time at cold shutdown when sump water can be removed.

ISI-203 Rev. 8 Page 96 of 228

OS1 VALVE RELIEF RE UEST RV-1 System: Containment Spray Valve: 1CT-53,91 Category: AC Class:

Function: Containment Spray System Inside Containment Isolation Check Valves.

Test Requirements: Verify forward flow operability and reverse flow closure.

Basis for Relief: Since there is no test recirculation line the only way to verify forward flow operability would be by using the pumps and injecting a large quantity of water into the Containment.

Spraying the Containment would result in extensive damage to safety-related equipment located inside Containment. Using air as a test medium is not practical since large segments of the system would have to be drained and high pressure air pumped into the system through a small test connection. The amount of air that could be injected using this method would be insufficient to verify full stroke opening and could result in an overpressurization of the Containment structure. The only method available to verify leak testing during Appendix J, Type C, testing at refueling.

Alternate Testing: One of the valves will be disassembled and visually inspected at refueling. Valve inspections will alternate with subsequent refuelings. Failure to pass inspectzon will initiate disassembly and inspection of the other valve. Reverse flow closure will be verified during Appendix J, Type C, valve leak testing at refueling.

ISI-203 Rev. 8 Page 97 of 228

OS1 SHEARON HARRIS NUCLEAR P(HER PLANT VALVE TEST TABLE SYSTEM: CONTAINMENT SPRAY DWG. NO. 2165-6-550 VALVE CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S.

NUMBER AND (CAT.> (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DHG, AND TEST OR ALT.

COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1CT-5 3 B-9 IXI'A RL C RL-4 NOTE 1 1CT-11 3 2 C FS-1 0 NOTE 2 I-12 GL IM-1 C PI-5 1CT-12 3 2 C FS-1 0 NOTE 2 H-12 GL TM-1 C PI-5 1CT-24 2 2 C FS-1 NOTE 3 H-14 GL TM-1 PI-5 1CT-25 2 2 C FS-1 NOTE 3 H-14 GL TM-1 PI-5 1CT-26 2 B 1Z MO D FS-1 NOTE 4 F-15 BA TM-1 PI-5 1CT-27 2 C 12 SA C FS-1 FF NOTE 5 F-14 CK 1CT-47 2 B 6 MO C FS-1 NOTE 6 E-5 GA TM-1 PI-5 ICT-50 2 8 C FS-1 0 NOTE 7 F-4 Gh TS-1 C PI-5 LJ-3 1CT-53 2 AC SA C FS-1 FF RV-1 DS NOTE 7 F"3 BS-1 BS RV-1 SP-3 LJ-3 1CT-62 2 SA C FS-1 FF NOTE 8 H-8 BS-1 BS 1CT-65 2 2 SA C FS-1 FF NOTE 8 J-8 CK BS-1 BS 1CT-71 2 12 0 FS-1 C NOTE 4 K-16 BA TM-1 PI-5 ISI-203 Rev. 8 Page 98 of 228

OS1 SHEARON HARRIS NUCLEAR PONER PLANT VALVE TEST TABLE SYSTEM: CONTAINMENT SPRAY D%. NO. 2165-S-550 CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S.

(CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR ALT.

COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1CT-72 2 12 SA C FS-1 FF NOTE 5 K-15 CK 1CT-88 2 8 C FS-1 0 NOTE 7 K-4 GA TS-1 C PI-5 LJ-3 1CT-91 2 AC SA C FS-1 FF RV-1 DS NOTE 7 K-3 BS-1 BS RV-1 SP"3 LJ-3 1CT-95 2 6 C FS-1 C NOTE 6 L-5 GA TH-1 PI-5 1CT-102 2 B 12 FS-1 0 CS-1 FS-2 NOTE 9, H-7 GA TM-1 - C CS-1 TH-2 7 PI-5 1CT-105 2. 12 FS-1 0 CS-1 FS-2 NOTE 9, N-7 GA IH-1 C CS-1 TH-2 7 PI-5 1CT-E017 3 SA FS-1 NOTE 10 A-8 1CT-E018 3 2 SA FS-1 NOTE 10 A-8 CK ISI-203 Rev. 8 Page 99 of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.12 VALVE TEST TABLES AND RELIEF REQUESTS FOR STEAM GENERATOR BLOWDOWN DWG. NO. 2165-S-551 ISI-203 Rev. 8 Page 100 of 228

OS1 SYSTEM: STEAM GENERATOR BLOWDOWN NO. NOTE Steam Generator Blowdown Line Block Valves.

ISI-203 Rev. 8 Page 101 'of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: STEAM GENERATOR BLOWDOWN DWG. NO. 2165-S-551 VALVE CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERP.

1BD-1 2 2 AO 0 FS-1 C NOTE 1 D-3 GL TS-1 FC-1 PI-5 1BD-7 2 4 0 FS-1 C NOTE 1 C-3 GL TS" 1 FC-1 PI-5 1BD-11 2 4 AO 0 FS-1 C NOTE 1 D-7 GL TS-1 FC-1 PI-5 IBD-20 2 2 AO 0 FS1 C NOTE 1 I-3 BL TS-1 FC-1 PI-5 1BD-26 2 4 PO 0 FS-1 C NOTE 1 H-3 GL TS-1 FC-1 PI"5 1BD-30 2 AO 0 FS-1 C NOTE 1 I-6 GL TS-1 FC-1 PI-5 1BD-39 2 2 AO 0 FS-1 C NOTE 1 N-3 GL TS-1 FC-1 PI-5 1BD-45 2 ,0 F61 C NOTE 1 L-3 BL TS-1 FC-1 PI-5 1BD-49 2 , B 4 AO 0 FS-1 C NOTE 1 n-7 GL TS-1 FC-1 PI-5 ISI-203 Rev. 8 Page 102 OE 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR

'I SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.13 VALVE TEST TABLES AND RELIEF REQUESTS FOR PROCESS SAMPLING DWG. NO. 2165-S-551 2165-S-552 ISI-203 Rev. 8 Page 103 of 228

OS1 SYSTEM: PROCESS SAMPLING NO. NOTE Steam Generator Sample Block Valves.

Sampling System Containment Isolation Valves.

Position Indication will be verified during performance of Appendix J, LLRT Testing.

ISI-203 Rev. 8 Page 104 of 228

OS1 SHEARON HARRIS NUCLEAR POHER PLANT VALVE TEST TABLE SYSTEM: PROCESS SAMPLING DNG. NO. 2165-S-551 VALVE CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S. REMARKS REV.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERP.

1SP-214 2 B 3/4 AO 0/C FS-1 C NOTE 1 C-4 GL TS-1 FC-1 PI-5 1SP-216 2 B 3/4 AO 0/C FS-1 C NOTE 1 C-4 GL TS-1 FC-1 PI-5 ISP-217 2 B 3/4 SO 0/C FS-1 C NOTE 1 C-6 GL TS-1 FC-1 PI-5 1SP-219 2 3/4 AO 0/C FS-1 C NOTE 1 G-4 GL TS-1 FC-1

,PI-5 16P-221 2 3/4 AO 0/C FS-1 C NOTE 1 H-4 GL TS-1 FC-1 PI-5 1SP-222 2 3/4 SO 0/C FS-1 C NOTE 1 H-6 GL TS-1 FC-1 PI-5 16P-224 2 3/4 AO 0/C FS-1 C NOTE 1 L-4 ~ GL TS-1 FC-1 PI"5 1SP-226 2 3/4 AO 0/C FS-1 C NOTE 1 M-4 GL TS-1 FC-1 PI-5 ISI-203 Rev. 8 Page 105 of 228

OS1 SHEARON HARRIS NUCLEAR POHER PLANT VALVE TEST TABLE SYSTEM: PROCESS SAMPLING DHG. NO. 2165-S-552 VALVE CLASS VALVE SIZE ACTH. NORM. TEST STROKED CHECK C.S. C.S. REMARKS REV.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

16P-227 2 B 3/4 SO 0/C FS-1 NOTE 1 L-6 GL TS-1 FC-1 PI-5 1SP-40 2 A 3/8 SO 0 FS-1 NOTE 2, 3 C-4 GL TS-1 FC-1 PI-5 LJ-3 1SP-41 2 A 3/8 SO 0 FS-1 NOTE 2, 3 C-5 GL TS-1 FC-1 PI-5 LJ3 ISP-59 2 3/8 SO 0 FS-1 C NOTE 2, 3 D-4 GL TS-1 FC-1 PI-5 LJ-3 1SP-60 2 3/8 SO 0 FS-1 NOTE 2, 3 D-5 GL TS-1 FC-1 PI-5 LJ-3 1SP-78 2 3/8 SO C FS-1 NOTE 2, 3 D-3 GL TS-1 FC-1 PI-5 LJ-3 1SP-81 2 A 3/8 SO C FS-1 NOTE 2, 3 E"3 GL TS-1 FC-1 PI-5 LJ-3 1SP-84 2 A 3/8 SO C FS-1 NOTE 2, 3 F-3 GL TS-1 FC-1 PI-5 LJ-3 1SP-85 2 A 3/8 SO C FS-1 NOTE 2, 3 E-4 GL TS-1 FC-1 PI-5 LJ"3 ISI-203 Rev. 8 Page 106 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: PROCESS SAMPLING DWG. NO. 2165-S-552 VALVE CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR ALT.

COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1SP-200 2 1 C FS-1 C NOTE 2, 3 N-6 GL TS-1 FC-1 PI-5 LJ-3 1SP-201 2 1 SO C FS-1 C NOTE 2, 3 N-5 GL TS-1 FC-1 PI-5 LJ-3 1SP-208 2 3/4 SO C FS-1 C NOTE 2, 3 N 6 GL TS-1 FC-1 PI-5 LJ-3 1SP-209 2 3/4 SO C FS-1 C NOTE 2, 3 N-5 GL TS-1 FC-1 PI-5 LJ-3 1SP-948 2 3/8 SO 0 FS-1 C NOTE 2, 3 B-4 GL TS-1 FC-1 PI-5 LJ-3 1SP-949 2 3/8 SO 0 FS" 1 - C NOTE 2, 3 B-5 GL TS-1 FC-1 PI-5 LJ-3 ISI-203 Rev. 8 Page 107 of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.14 VALVE TEST TABLES AND RELIEF REQUESTS FOR DIESEL GENERATOR FUEL OIL TRANSFER DWG. NO. 2165-S-563 ISI-203 Rev. 8 Page 108 of 228

OS1 SYSTEM: DIESEL GENERATOR FUEL OIL TRANSFER NO. NOTE D.G. Fuel Oil Transfer Pump Discharge Check Valves.

Failure of the check valves to close on reverse flow will not siphon the tank or degrade system operation, so, verification of reverse flow closure is not required.

2.'elief valve which protects safety-related equipment.

ISI-203 Rev. 8 Page 109 of 228

OS1 SHEARON HARRIS NUCLEAR POHER PLANT VALVE TEST TABLE SYSTEM: DIESEL GENERATOR FUEL OIL TRANSFER I

DHG. NO. 2165-S-563 VALVE CLASS 'ALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1DFO-168 3 C 2 SA C FS-1 NOTE 1 G-2 CK 1DFO" 170 3 C 3/4X1 Sh C RL-4 NOTE 2 G-1 RL 1DFO-186 3 C 2 SA C FS 1 FF NOTE 1 G-7 CK 1DFO-188 3 C 3/4X1 SA C RL-4 NOTE 2 G-5 RL ISI-203 Rev. 8 Page 110 of 228

OS1 SHEARON HARRIS NUCLEAR P(NER PLANT VALVE TEST TABLE SYSTEH: DIESEL GENERATOR FUEL OIL TRANSFER DMG. NO. 2165-S-633 S03 VALVE CLASS VALVE SIZE ACTU. NORH. TEST STROKED CHECK C.S. C.S. REV.

NUHBER AND (CAT. ) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1DFO-176 3 C 14 SA C RL-4 A-12 RL NOTE 2 1DFO-194 3 C 14 SA C RL-4 H-12 RL NOTE 2 ISI-203 Rev. 8 Page 111 of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.15 VALVE TEST TABLES AND RELIEF REQUESTS FOR RADIATION MONITOR AND HYDROGEN ANALYZER DWG. NO. 2165-S-605 ISI-203 Rev. 8 Page 112 of 228

OS1 SYSTEM: RADIATION MONITOR AND HYDROGEN ANALYZER NO. NOTE Containment Isolation Valves.

Position Indication will be verified during performance of Appendix J, LLRT Testing.

ISI-203 Rev. 8 Page 113 of 228

OS1 SHEARON HARRIS NUCLEAR POHER PLANT VALVE TEST TABLE SYSTEM: RADIATION MONITOR A HYDROGEN ANALYZER DNG. NO. 2165-S-605 VALVE CLASS VALVE SIZE ACTH. NORM. TEST STROKED CHECK C.S. C.S.

NUHBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1SP-12 2 1 SO FS-1 NOTE 1, 2 C-12 GL TS-1 FC-1 PI-5 LJ-3 1SP-16 2 ) SO 0 FS-1 NOTE 1, 2 C-13 GL TS-1 FC-1

/ PI-5 ISP-42 2 1 SO FS-1 NOTE 1, 2 G"12 GL TS-1

'FC-1 PI-5 LJ-3 1SP-62 2 1 SO FS-1 C NOTE 1, 2 I"12 GL TS-1 TC-1 PI-5 LJ-3 1SP-915 2 1 SO FS-1 NOTE 1, 2 C-12 GL TS-1 FC-1 PI-5 LJ-3 1SP-916 2 B 1 SO 0 FS-1 C NOTE 1, 2 C-12 GL TS-1 FC-1 PI-5 LJ-3 ISP-917 2 A 1 'SO 0 FS-1 NOTE 1, 2 D"12 GL TS-1 FC-1 PI"5 LJ-3 1SP-918 2 B ~ 1 SO 0 FS-1 NOTE 1, 2 D-13 GL TS-1 FC-1 PI-5 LJ-3 16P-919 2 A 1 SO FS-1 NOTE 1, 2 G-12 GL TS-1 FC-1 PI-5 LJ-3 ISI-203 Rev. 8 Page 114 of 228

OS1 SHEARON HARRIS NUCLEAR POHER PLANT VALVE TEST TABLE SYSTEH: RADIATION MONITOR S. HYDROGEN ANALYZER DNG. NO. 2165-S-605 VALVE CLASS VALVE SIZE ACTU. NORH. TEST STROKED CHECK C.S. C.S.

NUNBER AND (CAT.) (IN. ) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1SP-939 2 B 1 SO 0 FS-1 NOTE 1 ~ 2 D-13 GL TS-1 FC-1 PI-5 LJ-3 1SP-941 2 A 1 SO 0 FS-1 NOTE 1, 2 D-12 GL TS-1 FC-1 PI"5 LJ"3 1SP-943 2 A 1 SO C FS-1 NOTE 1, 2 I-12 GL TS-1 FC-1 PI-.5 LJ-3 ISI-203 Rev. 8 Page 115 of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.16 VALVE TEST TABLES AND RELIEF REQUESTS FOR DIESEL GENERATOR AIR START DWG. NO. 2165-S-633 S04 ISI-203 Rev. 8 Page 116 of 228

OS1 SYSTEM: DIESEL GENERATOR AIR START NO. NOTE D.G. Air Compressor to Air Receiver Check Valves.

Valves are exercised by normal operation of the Compressors in the forward direction. Air Receivers are alarmed to indicate drop in pressure. Reverse flow verification is required to maintain sufficient Receiver inventory for D. G. Starting.

Relief Valve which protects safety-related equipment.

ISI-203 Rev. 8 Page 117 of 228

OS1 SHEARON HARRIS NUCLEAR ONER PLANT VALVE TEST TABLE SYSTEM: DIESEL GENERATOR AIR START DWG. NO. 2165-S-633 S04 VALVE CLASS VALVE SIZE ACTH. NORM. TEST STROKED CHECK C.S. C.S.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1EA-4 3 13$ SA 0/C FS-1 BS NOTE 1 C-11 CK 1EA-6 3 1$$ SA C RL-4 NOTE 2 A-12 RL 1EA-19 3 1$$ SA 0/C FS-1 BS NOTE 1 F-11 CK 1EA-21 3 1$$ SA C RL-4 NOTE 2 E-12 L 1EA-35 3 1$$ SA 0/C FS-1 BS NOTE 1 J-11 CK 1EA-37 3 Ij$ SA C RL-4 NOTE 2 H-12 RL 1EA-50 3 15 SA 0/C FS-1 BS NOTE 1 M-11 CK 1EA-52 3 1$$ SA C RL-4 NOTE 2 L-12 RL IS?-203 Rev. 8 Page 118 of 228 E

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.17 VALVE TEST TABLES AND RELIEF REQUESTS FOR DEMINERALIZED WATER DWG. NO. 2165-S-799 ISI-203 Rev. 8 Page 119 'of 228

OS1 SYSTEM: DEMINERALIZED WATER NO. NOTE Containment Isolation Valves.

ISI-203 Rev. 8 Page 120 of 228

OS1 VALVE RELIEF RE UEST RV-1 System: Demineralized Water Valve: 1DW-65 Category: AC Class:

Function: Containment Isolation Simple Check Valve (reverse flow closure for containment isolation only).-

Test Requirements: Verify reverse flow closure Basis for Relief: The only method available to verify reverse flow closure is by valve leak testing during Appendix J, Type C, testing at refueling.

Alternate Testing: Reverse flow closure will be verified during Appendix J, Type C, testing at refueling.

ISI-203 Rev. 8 Page 121 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: DEMINERALIZED WATER DWG. NO. 2165-S-799 VALVE CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S. REV.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERP.

1DW-63 2 A 3 MA LC PV NOTE 1 H-5 GA LJ-3 1DW-65 2 AC 3 SA C FS-1 BS RV-1 SP-3 NOTE 1 H-6 CK LJ-3 ISI-203 Rev. 8 Page 122 of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.18 VALVE TEST TABLES AND RELIEF REQUESTS FOR CONTAINMENT SUMP DRAINS DWG. NO ~ 2165-S-685 ISI-203 Rev. 8 Page 123 of 228

OS1 SYSTEM: CONTAINMENT SUMP DRAINS NO. NOTE Containment Isolation Valves.

ISI-203 Rev. 8 Page 124 of 228

OS1 SHEARON HARRIS NUCLEAR P(NER PLANT VALVE TEST TABLE SYSTEM: CONTAINMENT SUMP DRAINS D%. NO. 2165-S-685 VALVE CLASS VALVE SIZE ACTU. NORH. TEST STROKED CHECK C.S. C.S.

NUMBER AND (CAT.) (IN; ) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DNG. AND TEST OR ALT.

COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

IED-94 2 A 3 MO 0 FS-1 C NOTE 1 H-7 GA TS-1 PI~5 LJ-3 1ED-95 2 A 3 HO 0 FS-1 C NOTE 1 H-7 GA TS-1 PI-5 LJ-3 ISI-203 Rev. 8 Page 125 'of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.19 VALVE TEST TABLES AND RELIEF REQUESTS FOR SERVICE AIR DWG. NO. 2165-S-800 ISI-203 Rev. 8 Page 126 of 228

OS1 SYSTEM: SERVICE AIR NO. NOTE Containment Isolation Valves.

ISI-203 Rev. 8 Page 127 of 228

OS1 VALVE RELIEF RE VEST RV-1 System: Service Air Valve: 1SA-82 Category:

Class:

Function: Containment Isolation Simple Check Valve (reverse flow closure for containment isolation only).

Test Requirement: Verify reverse flow closure.

Basis for Relief: The only method available to verify reverse flow closure is by valve leak testing during Appendix J, Type C, testing at refueling.

Alternate Testing: Reverse flow closure will,be verified during Appendix J, Type C, testing at refueling.

ISI-203 Rev. 8 Page 128 of 228

OS1 SHEARON HARRIS NUCLEAR POMER PLANT VALVE TEST TABLE SYSTEM: SERVICE AIR DWG. NO. 2165-S-800 VALVE CLASS VALVE SIZE ACTH. NORH. TEST STROKED CHECK C.S. C.S.

NUHBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DNG. AND TEST OR COOR. 'YPE DIRECT. RELIEF TEST REQ.NO. PERF.

1SA-80 2 A 2 HA LC PV NOTE 1 C-2 GL LJ-3 1SA-82 2 AC 2 SA C FS-1 BS RV-1 SP-3 NOTE 1 C-3 CK LJ-3 ISI-203 Rev. 8 Page 129 of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.20 VALVE TEST TABLES AND RELIEF REQUESTS FOR INSTRUMENT AIR DWG. NO. 2165-S-801 2165-S-1017 ISI-203 Rev. 8 Page 130 of 228

OS1 SYSTEM: INSTRUMENT AIR NO. NOTE Containment Isolation Valves.

Accumulator fill line check valves. Accumulators are maintained charged and are alarmed during normal operations.

Valve numbers have been revised. Valves formally numbered as: 1CB-VOlA, V01B, V02A, V02B AND 1CV-1,2.

ISI-203 Rev. 8 Page 131 of 228

OS1 COLD SHUTDOWN TEST JUSTIFICATION CS-1 System: Instrument Air Valve: IIA-819 Category:

Class:

ASME Section XI Quarterly Test Requirements: Exercise, Time and Fail.

Cold Shutdown Test Justification: Instrument Air supplies a number of components inside Containment which are necessary for normal operation. Testing during normal operation would deprive these components of their normal air supply and, since the system has no reserve air storage capacity, could result in operating transients and a possible forced plant shutdown.

Quarterly Part Stroke Testing: Valves are equipped with full stroke only operators and cannot be partial stroke exercised.

Cold Shutdown Testing: Exercise, Time and Fail at cold shutdown when the normal Instrument Air can be isolated without causing loss of instruments and components necessary for normal plant operations.

ISI-203 Rev. 8 Page 132 of 228

OS1 VALVE RELIEF RE UEST RV-1 System: Instrument Air Valve: 1IA-220 Category: AC Class:

Function: Containment Isolation Simple Check Valve (reverse flow closure for Containment isolation only).

Test Requirements: Verify reverse flow closure'asis for Relief: The only method available to verify reverse flow closure is by valve leak testing during Appendix J, Type C, testing at refueling.

Alternate Testing: Reverse flow closure will be verified during Appendix J, Type C, testing at refueling.

ISI-203 Rev. 8 Page 133 of 228

OS1 VALVE RV-2 System: Instrument Air Valve: 1IA-784, 785, 786, 787, 788, 789 Category:

Class:

Function: Instrument Air To Air Operated Containment Isolation Valve Accumulators.

Test Requirements: Verify reverse flow closure.

Basis for Relief: Each fill line to the accumulators contains two simple check valves in series and there are no system provisions for individual valve closure verification. Only one automatic actuating valve is required to isolate the non-classed instrument air system from the accumulators.

The two valves function as a single unit and if either of them close proper operation of the accumulators is assured. To verify reverse flow closure of the unit requires isolating and depressurization of a large segment of the Instrument Air System for an extended length of time. Loss of instrument air during operation would cause loss of'nstrumentation needed for normal operations. Because of the time required to perform testing, performing verification at ~

cold shutdown could cause delays in returning the plant to normal operations.

Alternate Testing: One valve on the accumulator side and one valve on the instrument air side will be disassembled and inspected at each refueling. Failure of the tested valve will initiate testing of the other two corresponding valves.

ISI-203 Rev. 8 Page 134 of 228

OS1 SHEARON HARRIS NUCLEAR PONER PLANT VALVE TEST TABLE SYSTEM: INSTRUMENT AIR DWG. NO. 2165-S-801 CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S.

AND (CAT.) (IN. ) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. 'YPE DIRECT. RELIEF TEST REQ.NO. PERF.

1IA-220 2 3 SA 0 FS-1 BS RV-1 SP-3 NOTE 1 C"3 CK LJ-3 1IA-819 2 3 PO 0 FS-1 CS-1 FS-2 NOTE 1 C-3 GA TS-1 CS-1 FS-2 FC-1 CS-1 FS-2 PI-S LJ-3 ISI-203 Rev. 8 Page 135 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: INSTRUMENT AIR DWG. NO. 2165-S-1017 CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S.

(CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1IA-784 2 C 3/4 SA 0/C FS-1 BS RV-2 DS-3 NOTE 2, 3 B-7 CK 1IA-785 2 C 3/4 SA 0/C FS-1 BS RV-2 DS-3 NOTE 2 3 B-8 CK 1IA-786 2 C 3/4 SA 0/C FS-1 BS RV-2 DS-3 NOTE 2, 3 G-2 CK 1IA-787 2 3/4 SA 0/C FS-1 BS RV-2 DS-3 NOTE 2, 3 G-3 CK 1IA-788 2 3/4 SA 0/C FS-1 BS RV-2 DS-3 NOTE 2, 3 H-2 CK 1IA-789 2 3/4 SA 0/C FS-1 BS RV-2 DS-3 NOTE 2, 3 H-3 CK ISI-203 Rev. 8 Page 136 of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.21 VALVE TEST TABLES AND RELIEF REQUESTS FOR FUEL .POOL COOLING DWG. NO. 2165-S-561 2165-2-805 ISI-203 Rev. 8 Page 137'of 228

OS1 SYSTEM: FUEL POOL COOLING NO. NOTE Containment Isolation Valves.

Fuel Pool Cooling Pump Discharge Check Valves. In normal operation only one pump is in service and the Discharge Header is isolated between the pumps by normally closed valves. Since .recirculation flow back across the idle pump is not possible verification of reverse flow closure is not required.

Thermal Relief Valve added to the program to comply with North Carolina State Requirements.

ISI-203 Rev. 8 Page 138 of 228

OS1 SHEARON HARRIS NUCLEAR P(NER PLANT VALVE TEST TABLE SYSTEM: FUEL POOL COOLING DWG. NO. 2165-S-561 CLASS VALVE SIZE ACTH. NORH. TEST STROKED CHECK C.S. C.S.

AND (CAT.) (IN. ) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DMG. TEST OR ALT.

COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1SF-116 2 4 LC PV NOTE 1 E-2 GA LJ-3 1SF-119 2 4 LC PV NOTE 1 E-3 GA LJ-3 1SF-144 2 LC PV NOTE 1 A"3 GA LJ-3, 1SF-145 2 4 MA LC PV NOTE 1 A-2 GA LJ-3 ISI-203 Rev. 8 Page 139 of 228

OS1 SHEARON HARRIS NUCLEAR PONER PLANT VALVE TEST TABLE SYSTEM: FUEL POOL COOLING DNG. NO. 2165-S-605 VALVE CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S.

NUMBER AND (CAT.) (IN. ) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DHG. AND TEST OR ALT.

COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERP.

1SF-3 3 C 12 SA 0/C FS-1 FF NOTE 2 G-9 CK 1SF-13 3 C 12 SA 0/C FS-1 FF NOTE 2 J-9 CK 1SF-45 3 C 3/4X1 SA C RL-4 NOTE 3 H-3 RL 1SF-66 3 C 3/4X1 SA C RL-4 NOTE 3 K-3 RL ISI-203 Rev. 8 Page 140 of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.22 VALVE TEST TABLES AND RELIEF REQUESTS FOR EMERGENCY SCREEN WASH DWG. NO. 2165-S-808 ISI-203 Rev. 8 Page 141 of 228

OS1 SYSTEM: EMERGENCY SCREEN WASH NO. NOTE Emergency Screen Wash Pump Discharge to Screen Line Block Valves. Valves are used for system alignment and fail closed.

Emergency Screen Wash Pump Discharge Check Valves.

Failure of the valve to close on reverse flow will not degrade system operation, so, verification of reverse flow closure is not required.

XSI-203 Rev. 8 Page 142 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: EMERGENCY SCREEN WASH DWG. NO. 2165-6-808 VALVE CLASS VALVE SIZE ACTH. NORM. TEST STROKED CHECK C.S. C.S.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERP.

ISC-20 3 3 EH 0/C FS-1 C NOTE 1 D-16 GL TM-1 0 FC-1 PI-5 1SC-24 3 SA 0/C FS-1 FF NOTE 2 C-15 ISC-30 3 3 EH 0/C FS-1 C NOTE 1 D-13 GL TM-1 0 FC-1 PI-5 1SC-34 3 SA 0/C FS-1 FF NOTE 2 C-12 ISC-37 3 3 EH 0/C FS-1 C NOTE 1 B-13 GL TM-1 -0 FC-1 PI-5 ISC-40 3 3 EH 0/C FS-1 C NOTE 1 B-16 GL TM-1 0 FC-1 PI-5 3SC-41 3 3 EH 0/C FS-1 C NOTE 1 B-16 GL TM-1 FC-1 PI-5 ISI-203 Rev. 8 Page 143 'of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.23 VALVE TEST TABLES AND RELIEF REQUESTS FOR FIRE PROTECTION DWG. NO. 2165-S-888 ISI-203 Rev. 8 Page 144 of 228

OS1 SYSTEH: FIRE PROTECTION NO. NOTE Containment Isolation Valves.

ISI-203 Rev. 8 Page 145 oE 228

OS1 VALVE RELIEF RE UEST RV-1 System: Fire Protection Valve: 1FP-349,357 Category: AC Class:

Function: Containment Isolation Simple Chedk Valve (reverse flow closure for containment isolation).

Test Requirements: Verify reverse flow closure.

Basis for Relief: The only method, available to verify reverse flow closure is by valve leak testing during Appendix J, Type C, testing at refueling.

Alternate Testing: Reverse flow closure will,be verified during Appendix J, Type C, testing at refueling.

ISI-203 Rev. 8 Page 146 of 228

OS1 SHEARON HARRIS HUCLEAR POHER PLANT VALVE TEST TABLE SYSTEM: FIRE PROTECTION DWG. NO. 2165-S-888 VALVE CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. ~ C.S.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. TEST OR ALT.

COOR. 'YPE DIRECT. RELIEF TEST REQ. NO. PERF.

1FP-347 2 A 6 AO 0 FS-1 C NOTE 1 L-2 GL TS-1 FC-1 PI-5 LJ-3 IFP-349 2 AC 6 SA 0 FS-1 BS RV-1 SP-3 NOTE 1 L-3 CK LJ-3 1FP-357 2 AC 4 SA C FS-1 BS RV-1 SP-3 NOTE 1 L-3 CK LJ-3 1FP-355 2 A 4 MA C LJ-3 NOTE 1 L-2 GA ISI-203 Rev. 8 Page 147 of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.24 VALVE TEST TABLES AND RELIEF REQUESTS FOR ESSENTIAL CHILLED WATER DWG. NO. 2165-S-998 2165-2-998 S02 2165-2-999 2165-S-999 S02 ISI-203 Rev. 8 Page 148 of 228

OS1 SYSTEM: ESSENTIAL CHILLED WATER NO. NOTE Valves Isolate Non-Safety-Related from Safety-Related portions of system and close on system initiation.

Relief Valve which protects Safety-Related Equipment.

Valve is a normally throttled pressure control valve.

Valve automatically responds to changes in system pressure and as such is exempt from Section XI testing. Valve fails open on loss of power.

Test fail open function only.

Thermal Relief Valve added to the program to comply with North Carolina State Requirements.

Recirculation Pump Discharge Check Valve. Reverse flow closure is required to prevent flow by-passing the Condenser.

Safety-Related Make-up to the Chillers Line Check Valve. Normally closed in-line block valve is only open when water is being added. Thus, Verification of reverse flow closure is not required.

Safety-Related Make-up to the Chillers, which is only used after an S Signal.

ISI-203 Rev. 8 Page 149 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: ESSENTIAL CHILLED WATER DWO. NO. 2165-S-896 VALVE CLASS VALVE SIZE ACTH. NORM. TEST STROKED CHECK C.S. C.S.

NUHBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. FERF.

1CH-115 3 H-14 B 4 BF

'O 0 FS-1 XH-I C NOTE 1 FC-1 PI-5 1CH-116 3 B 4 AO 0 FS-1 C NOTE 1 H-14 BF TH-1 FC-1 PI-5 1CH-125 3 AO 0 FS-1 C NOTE 1 L-10 BF TH-I FC-1 PI-5 1CH126 3 B 4 AO 0 FS-1 NOTE 1 L-10 BF TH-I FC-1 PI-5 h

h' XSl-203 Rev. 8 Page 150 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: ESSENTIAL CHILLED WATER DWG. NO. 2165-S-998 S02 VALVE CLASS VALVE SIZE ACTH. NORH. TEST STROKED CHECK C.S. C.S.

NUNBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1CH 6 3 C 1X1 SA C RL 4 NOTE 2 F-4 RL ICH-10 3 C 1X1 SA C RL-4 NOTE 2 I-4 RL ~

1CH-19 3 C 3/4X1 SA C RL-4 NOTE 2 H-6 RL 1CH-1397 3 B 1 SO 0 FS-1 NOTE 1

-J-4 GL TH-1 FC-1 PI-5 1CH-1398 3 B 1 SO 0 FS-1 NOTE 1 J-4 GL TH-1 FC-1 PI-5 1SA-494 3 B 1 SO 0 FS-1 NOTE 1 E-3 GA TH-I FC-1 PI-5 1SA-495 3 B 1 SO 0 FS-1 NOTE 1 E-3 GA TH-I FC-1 PI-5 1SW-1055 3 B 10 EH TH FO-1 0 NOTE 3 E-6 BF PI-5 1SW-1078 3 C 3/4X1 SA C NOTE 2 C-8 RL 1SW-1079 3 C 8 SA 0/C 'S"1 NOTE 5 C-8 ~ . CK BS-1 BS 1SW-1170 3 C 1 SA C FS-1 FF NOTE 6 1SW-1171 G-5 3,

F-3 B

CK 1

GL SO C FS-1 TH-1 C

0 NOTE 7 FC-1 PI-5 1CH 34 3 C 3/4Xl SA C NOTE 4 F-11 RL ISI-203 Rev. 8 Page 151 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEN: ESSENTIAL CHILLED WATER DWG. NO. 2165-S-999 VALVE CLASS VALVE SIZE ACTH. NORH. TEST STROKED CHECK C.S. C.S. REV.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWS. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERP.

1CH-146 3 B 4 AO 0 FS-1 C NOTE 1 A-16 BF TH-I FC-1 PI-5 1CH"149 3 4 AO 0 FS-1 C NOTE 1 A-16 BF TM-I FC-1 PI-5 1CH-196 3 4 AO 0 FS-1 C NOTE 1 L-16 BF TH-I FC-1 PI-5 1CH-197 3 B 4 AO 0 FS-1 C NOTE 1 L-16 BF TH-I FC-1 PI-5 ISI-203 Rev. 8 Page 152 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEH: ESSENTIAL CHILLED WATER DWG. NO. 2165-S-999 SO2 VALVE CLASS VALVE SIZE ACTH. NORM. TEST STROKED CHECK C.S. C.S.

NUHBER (CAT.) (IN. ) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1CH-50 3 C 1X1 SA C RL-4 NOTE 2 G-3 RL 1CH-54 3 C 1X1 SA C NOTE 2 I-3 RL 1CH-63 3 C 3/4X1 SA C NOTE 2 H-7 RL 1CH-1399 3 B 1 SO 0 FS-1 NOTE 1 J-4 GL TM-I FC-1 PI-5 1CH-1400 3 B 1 SO 0 FS-1 NOTE 1 J-4 GL TH-I FC-1 PI-5 1SA-502 3 B 1 SO 0 FS-1 NOTE 1 E"3 GL TM-I FC-1 PI"5 1SW-1203 3 C 1 SA C FS-1 NOTE 6 G-3 CK 1SW-1204 3 B 1 SO C FS-1 NOTE 7 H-5 GL TH-1 FC-1 PI-5 1SA-503 3 B 1 SO 0 FS-1 NOTE 1 E-3 GL TH-I FC-1 PI-5 1SW-1208 3 B 10 EH TH FO-1 NOTE 3 F-6 BF PI-5 1SW-1231 3 C 3/4X1 SA C NOTE 2 C-8 RL 1SW-1232 3 C 8 SA 0/C FS-1 NOTE 5 D-8 CK BS-1 BS 1CH-78 3 C 3/4X1 SA C RL-4 NOTE 4 F-10 RL ISI-203 Rev. 8 Page 153 of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.25 VALVE TEST TABLES AND RELIEF REQUESTS FOR REACTOR COOLANT DWG. NO. 2165-S-1301 ISI-203 Rev. 8 Page 154 of 228

OS1 SYSTEM: REACTOR COOLANT NO. NOTE Pressurizer Power Operated Relief Line Block Valves.

Pressurizer Power Operated Relief Valves. These valves are controlled by the Pressurizer Over Pressure Protection System, which automatically opens two of the valves at 'a preset pressure. These valves are tested/timed in both the open and closed directions.

Pressurizer Relief Valves.

Containment Isolation Valve.

Reactor Pressure Vessel and Pressurizer Vent Path Block Valves. Tech. Spec. 3.4.11 requires that only one path be operable and the other valves be electrically disabled during normal operation.

Reactor Pressure Vessel'and Pressurizer Vent Path Block Valves downstream of normally closed vent valves.

Reactor Pressure Vessel and Pressurizer Vent Path Check Valve.

Position Indication will be verified during performance of GP-OOl.

RCS Vent Check Valve. Backseat function for testing only. Reference PCR-2397.

10. Pressurizer PORV accumulator keep full check valve from nitrogen supply.

Pressurizer PORV accumulator keep full check valve from instrument air supply.

12. Relief valve that protects safety related system.

ISI-203 Rev. 8 Page 155 of 228

OS1 COLD SHUTDOWN TEST JUSTIFICATION CS-1 System: Reactor Coolant Valve: 1RC-114, 116, 118 Category: B, C Class:

Function: Pressurizer Power Operated Relief Valves (PORVs)

Test Requirements: Exercise, Time, and Fail quarterly.

Cold Shutdown Identification: The PORVs are controlled by the Pressurizer Overpressure Protection System, which automatically opens two of the valves at a preset pressure. At power, set pressures are established to limit undesirable opening of the spring-loaded Safety Valves. The PORVs are relied upon during reactor startup and shutdown to protect the RCS from potential low temperature overpressurization transients. In the event of a Steam Generator Tube Rupture, the PORVs may be required to open for accident mitigation. In accordance with Generic Letter 90-06, these valves will be tested on the way to cold shutdown during Modes 3 or 4, prior to LTOPS operation at startup, and during Modes 3 or 4 upon return to power.

Quarterly Part Stroke Testing: Valve operators are full-stroke on initiation and cannot be partial-stroke exercised.

Cold Shutdown Testing: Exercise, time, and fail during Modes 3 or 4 on the way to cold shutdown, prior to LTOPS operation in Mode 5 or 6, and during Modes 3 or 4 upon return to.

power from cold shutdown.

ISI-203 Rev. 8 Page 156 of 228

OS1 COLD SHUTDOWN TEST JUSTIFICATION CS-2 System: Reactor Coolant Valve: 1RC-900, 901, 902, 903, 904, 905 Category: B Class:

Function: RCS Vent Valves Test Requirements: Exercise valve for operability, observe proper operation of fail-safe actuators, and measure stroke time quarterly.

Cold Shutdown Justification: Valves are RCS high point vent valves, which were installed subsequent to TMI accident, and are intended to provide venting capabilities during a natural circulation cool-down evolution. Valves are routinely used during cold shutdown to provide a path for RCS venting.

Technical Specification 3.F 11 requires that one vent path from the Reactor pressure vessel head and one vent path from the pressurizer be operable and closed during operation. Technical Specifications require testing of these valves every 18 months. Testing of these valves during power operation could result in an uncontrolled blowdown should the downstream block valves inadvertently open or experience excessive leakage resulting in a loss of RCS inventory to the pressurizer relief tank or containment atmosphere.

Quarterly Part Stroke Testing: None. These valves are not equipped with part stroke exercisers.

Cold Shutdown Testing: 1RC-900, 901, 902, 903, 904, 905:

Exercise valves for operability, observe proper operation of fail-safe actuators, and measure stroke time at Cold Shutdown.

ISI-203 Rev. 8 Page 157 of 228

OS1 COLD SHUTDOWN TEST JUSTIFICATION CS-3 System: Reactor Coolant Valves: 1RC-174, 1RC-176, ISI-444, ISI-446 Category: AC Class:

Function: Pressurizer PORV Accumulator Keep Full Check Valves Test Requirements: Prove that each valve travels to its seat upon cessation of flow, quarterly.

Cold Shutdown Justification: Backseat testing of these valves at power would require containment entry with the reactor critical.

This practice would deviate from the principles of ALARA. The pressurizer'PORVs, which these valves supply, are required to be stroke tested on the way to cold shutdown.

Quarterly Part Stroke Testing: Partial stroke testing does not apply to backseat testing of check valves.

Cold Shutdown Testing: Backseat testing will be performed at cold shutdown.

ISI-203 Rev. 8 Page 158 of 228

OS1 VALVE RELIEF RE UEST RV-1 System: Reactor Coolant Valve: 1RC-164 Category: AC Class:

Function: Containment Isolation Simple Check Valves (reverse flow closure for containment isolation only).

Test Requirements: Verify reverse flow closure.

Basis for Relief: The only method available to verify reverse flow closure is by valve leak testing during Appendix J, Type C, testing at refueling.

Alternate Testing: Reverse flow closure will be verified during Appendix J, Type C, Testing at Refueling.

ISI-203 Rev. 8 Page 159 of 228

OS1 VALVE RELIEF RE VEST RV-2 System: Reactor Coolant Valve: 1RC-993 Category:

Class: N/A Function: RCS Vent to Pressurizer Relief Tank Check Valve Test Requirements: Verify Full Forward Flow Exercise Basis for Relief: A full flow exercise of this valve would involve venting at full RCS pressure. To do so while in

'Modes 1-4 would introduce a LOCA. At cold shutdown and refueling there would be insufficient driving head to provide full flow testing. In accordance with Generic Letter 89-04, this valve will be disassembled, manually exercised, and visually inspected every refueling outage.

Alternate Testing: Valve will be partially exercised at cold shutdown and will be disassembled every refueling.

ISI-203 Rev. 8 Page 160 of 228

OS1 SHEARON HARRIS NUCLEAR PONER PLANT VALVE TEST TABLE SYSTEH: REACTOR COOLANT DMG. NO. 2165-S" 1301 VALVE CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S.

NUHBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

TEST OR ALT.

COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1RC-113 1 B 3 HO FS-1 NOTE 1 H-2 GA TH-1 PI-5 1RC-114 1 BC 3 AO FS-1 C CS-1 FS-2 NOTE 2 H-I GL TH-1 0 CS-1 TM-1 FC-1 CS-1 FC-1 PI-5 1RC-115 1 B 3 HO 0 FS-1 NOTE 1 F-2 GA TM-1 PI-5 1RC-116 1 BC 3 AO FS-1 CS-1 FS-2 NOTE 2 F-1 GL TM-1 CS-1 TH-2 FC-1 CS-1 FC-2 PI-5 1RC-117 1 B 3 HO 0 FS-1 C NOTE 1 E-2 GA TM-1 PI-5 1RC-118 1 BC 3 AO FS-1 CS-1 FS-2 NOTE 2 E-l GL TM-1 CS-1 TH-2 FC-1 CS-1 FC-2 PI-5 1RC-123 1 C 6X6 SA NOTE 3 F 4 RL 1RC-125 1 C 6X6 SA NOTE 3 F"6 RL 1RC-127 1 C 6X6 SA NOTE 3 F-8 RL 1RC 141 2 A 1 AO 0 FS-1 ~ NOTE 4 C-16 DA TS-1 FC-1 PI-5 LJ-3 1RC-144 2 1 AO 0 FS-1 NOTE 4 C-17 DA TS-1 FC-1 PI-5 LJ-3 1RC-161 2 3 AO FS-1 NOTE 4 D-17 DA TS-1 FC-1 PI-5 LJ-3 1RC"164 2 AC SA FS-1 BS RV-1 SP-3 NOTE 4 D-16 LJ-3 IRC-900 2 1 PI-5 CS-2 FS-1 NOTE 5, 8 A-7 GL FS-1 TH-2 TM-1 FC-2 FC-1 ISI-203 Rev. 8 Page 161 of 228

OS1 SHEARON HARRIS NUCLEAR POHER PLANT VALVE TEST TABLE SYSTEH: REACTOR COOLANT DWG. NO. 2165-S-1301 CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S.

(CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DHG. AND TEST OR ALT.

COOR. TYPE DIRECT. RELIEF TEST REQ. NO. PERP.

1RC-901 2 1 SO C PI-5 C CS-2 FS-2 NOTE 5, A-7 GL FS-1 0 TH-2 8 TM-1 FC-2 FC-1 1RC-902 2 1 SO C PI-5 D CS-2 FS-2 NOTE 5, B-7 GL FS-1 0 TH-2 8 TH-1 FC-2 FC-1 1RC-903 2 1 SO C PI-5 C CS-2 FS-2 NOTE 5, B-7 GL FS-1 0 TH-2 8 TH-1 FC-2 FC-1 1RC-904 2 1 SO C PI"5 C CS-2 FS-2 NOTE 6, B-5 GL FS-1 0 TH-2 8 TH-1 FC-2 FC-1 1RC-905 2 1 SO C PI-5 C CS-2 FS-2 NOTE 6, A-8 GL FS-1 0 TM-2 8 TH-1 FC-2 FC-1 1RC-993 A-9 1 SA C FS-1 RV-2 FS"2 NOTE 9 CK DS 1RC-174 3 AC 1 SA C FS-1 BS CS-3 FS-2 NOTE 10 C-9 CK LK-3 1RC-176 3 AC 1 SA C FS-1 BS CS-3 FS-2 NOTE 10 B-9 CK LK-3 1SI-444 3 AC 1 SA C FS-1 BS CS-3 FS-2 NOTE 11 B-6 CK LK-3 1SI-446 3 AC 1 SA C FS-1 BS CS-3 FS-3 NOTE 11 A"6 LK-3 1RC-1003 3 AC 1X2 SA C RL-4 NOTE 12 B-9 LK-3 1RC-1004 3 AC 1X2 SA .C RL-4 NOTE 12 A-9 RL LK-3 ISI-203 Rev. 8 Page 162 of 228

OS1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.26 VALVE TEST. TABLES AND RELIEF REQUESTS FOR CHEMICAL AND VOLUME CONTROL DWG. NO. 2165-S-1303 2165-S-1303 S01 2165-S-1303 S02 2165-S-1304 2165-S-1305 2165-S-1306 2165-S-1307

~t ISI-203 Rev. 8 Page 163 oE 228

OS1 SYSTEM: CHEMICAL AND VOLUME CONTROL NO. NOTE RCS Normal Letdown to the CVCS Containment Isolation Valves. Valves are in parallel and can be exercised quarterly without terminating normal RCS Letdown Flow.

Relief Valve which protects Safety-Related Equipment.

RCS Normal Letdown to CVCS Containment Isolation Valves. Failure in the closed position would cause loss of Pressurizer Level Control.

CVCS Charging Flow to RCS Containment Isolation Valves.

CVCS to and from the RCS Pump Seals Containment Isolation Valves.

A check valve which functions as a thermal relief valve when both containment isolation valves are closed. The only Safety-Related function is containment isolation.

RCS Alternate Charging Line from the CVCS Block Valve.

Provides redundant flow path to the RCS.

RCS Alternate Charging Line Check Valves.

RCS Normal Charging Line Check Valves.

10. Alternate Charging Pump Minimum Flow Path Block Valves. Valves open in a S signal to prevent dead heading the pumps.

Thermal Relief Valve added to the program to comply with North Carolina State Requirements.

12. Volume Control Tank Valves are interlocked with the RWST Block Valves such that the VCT Block Valves cannot be closed until the RWST Block Valves are fully open.

13. VCT Outlet Check Valve. VCT provides head to the charging pumps 'until the RWST Block Valves are fully open. Reverse flow closure is required to prevent diversion of S.I. flow to the RHT during the recirculation phase of S.I.

14. Charging Header Pump Inlet Header Block Valves.

ISI-203 Rev. 8 Page 164 of 228

OS1 SYSTEM: CHEMICAL AND VOLUME CONTROL NO. NOTE Charging Pump Discharge Check Valves. Charging Pump C is an installed spare and will not be connected unless Pump A or B is out of service. Only those valves associated with Charging Pumps in service will be tested.

16. Charging Pump Minimum Flow Line Check Valves. Inline Motor operated valves close on a S signal. Since one pump is an installed spare a manual valve between headers is maintained closed and the two operating pumps are isolated from each other and reverse closure is not required for system operation.

17. Charging Pump Minimum Flow line Block Valves. Valves close on an S signal.

18. Charging Pump Discharge Header Isolation Valves.

Valves used for system alignment for Post-LOCA System operation.

19. Charging Pump Discharge Header Line to the RCS.

Provides flow control during normal operation and fails open to guarantee full flow.

20. Charging Pump Discharge Header Line to the RCS Block Valve. Valve receives an S signal to close on system initiation.

21. Valves used for Emergency Boron Addition. Check valve is down stream of a normally closed flow control valve which will only be open during Boron addition.

Reverse flow closure is not required for system operation.

22. RWST Line to Charging Pump Inlet Header Check Valve.

To verify full forward flow testing requires full flow through the Charging Pumps.. The valve will be partially forward flow tested and backseat tested at cold shutdown and full forward flow tested at refueling.

23. Boric Acid Transfer Pump Discharge Check Valves.

Reverse flow closure required t'o prevent recirculation flow through idle pump.

24. Valves open for Boric Acid Transfer for guaranteed cold shutdown.

ISI-203 Rev. 8 Page 165 of 228

OS1 SYSTEM: CHEMICAL AND VOLUME CONTROL NO. NOTE

25. Containment Isolation Valve.

26. Conditional cold shutdown testing. Refer to Relief Request.

27. RCS Normal Charging Line block valve.

ISI-203 Rev. 8 Page 166 of 228

OS1 COLD SHUTDOWN TEST JUSTIFICATION CS-1 System: Chemical and Volume Control Valve: 1CS-11,231,235,238 Category: A(1CS-11,238)  : B(1CS-231,235)

Class:

ASME Section XI Quarterly Test Requirements: Exercise and Time (1CS-235,238)

Exercise, Time and Fail (1CS-11,231).

Cold Shutdown Test Justification: These valves are in the normal letdown and charging lines to the RCS. Exercising during normal operation would disrupt normal RCS charging and letdown flow which could lead to a pressurizer level control transient. Failure of a letdown valve in the closed position coincident with normal charging flow could result in a high RCS water level trip. Because of this and a potential for thermal shock to the Regenative Heat Exchanger, valve testing wi.ll be delayed to cold shutdown.

Quarterly Part Stroke Testing: Valves are equipped with full stroke only operators and cannot be partial stroke exercised.

Cold Shutdown Testing: Exercise and time (1CS-235,238)

Exercise, time and fail(1CS-11,231).

ISI-203 Rev. 8 Page 167 of 228

OS1 COLD SHUTDOWN TEST JUSTIFICATION CS-3 System: Chemical and Volume Control Valve: 1CS-165,166,291,292 Category: B Class:

Function: Volume Control Tank Discharge Block Valves (1CS-165,166) and RWST to CVCS Charging Pump Suction Safety Infection Block Valves (1CS-291,292).

Test Requirement: Exercise and Time Cold Shutdown Testing Justification: The RWST to CSIP block valves cannot be stroked while at power because to do so would result in an overboration of the RCS and possibly, a reactivity transient. The Volume Control Tank outlet valves cannot be exercised, because to do so would require having the RWST to CSIP block valves open and this would again result in overboration of the RCS.

Alternate Testing: Exercise and Time at cold shutdown.

ISI-203 Rev. 8 Page 168 of 228

OS1 COLD SHUTDOWN TEST JUSTIFICATION CS-4 System: Chemical and Volume Control Valve: 1CS-279 Category:

Class: 1CS-279: 2 Function: 1CS-279: Check valve in the line from the CVCS BA Filter to the Charging Pump Header.

Test Requirement: Verify forward flow operability.

Cold Shutdown Testing Justification: The only possible way to verify forward flow operability is by passing concentrated Boric Acid Fluid through the valve to the Charging Pump Inlet Header.

Alternate Testing: Verify forward flow operability when borating to go to cold shutdown.

ISI-203 Rev. 8 Page 169 of 228

OS1 COLD SHUTDOWN TEST JUSTIFICATION CS-5 System: Chemical and Volume Control Valve: 1CS-294 Category:

Class:

Function: RWST line to CVCS Charging Pump Inlet Header Check Valve.

Test Requirement: Verify backseat operability.

Cold Shutdown Testing Justification: To verify backseat operability at power would involve first passing flow in the forward direction, thereby injecting highly borated water into the RCS, which could lead to a reactivity transient.

Alternate Testing: Verify operability at cold shutdown when there is no adverse consequence to injecting boric acid.

ISI-203 Rev. 8 Page 170 of 228

Osl COLD SHUTDOWN TEST JUSTIFICATION CS-6 System: Chemical and Volume Control Valve: 1CS-775, 776 Category:

Class:

Function: RHR HX Line to CVCS Charging Pump Inlet Header Check Valve verify forward and backseat operability.

Test Requirement:

Cold Shutdown Testing Justification: To verify forward"flow and backseat operability during normal plant operation would require the installation of electrical jumpers to open 1RH-25 and 1RH-63. This could lead to a plant transient and abnormal system line up.

Alternate Testing: Verify forward flow and backseat operability at cold shutdown when testing will not affect normal plant operation.

ISI-203 Rev. 8 Page 171 of 228

OS1 COLD SHUTDOWN TEST JUSTIFICATION CS-7 System: Chemical and Volume Control Valve 1CS-480, 1CS-483, 1CS-486, 1CS-492 Category: B (1CS-480, 1CS-492)

C (1CS-483, 1CS-486)

Class: 1 (1CS-483, 1CS-486) 2 (1CS-480, 1CS-492)

ASME Section XI Quarterly Test Requirements: Exercise and Time (1CS-480, 1CS-492)

Forward Flow, Full stroke (1CS-483, 1CS-486)

Cold Shutdown Test Justification: Testing valves 1CS-480, 1CS-483, 1CS-486 at Power has been determined to cause thermal cycling of charging path piping. This problem has been the'lternate documented by Westinghouse in letter CQL-90-562, dated 09/27/90. Likewise, valve 1CS-492 cannot be exercised since this would require flowing through the alternate path to avoid isolation of charging and letdown.

These valves will be tested on a cold shutdown frequency.

Quarte'rly Part Stroke Testing: Valve 1CS-480, 1CS-483, and 1CS-486 cannot be partial stroke exercised for the same reason as at power.

Valve 1CS-492 does not have capability for partial stroking.

Cold Shutdown Testing: Exercise and Time (1CS-480, 1CS-492) Forward flow; full stroke (1CS-483, 1CS-486)

ISI-203 Rev. 8 Page 172 of 228

OSl COLD SHUTDOWN TEST JUSTIFICATION CS-8 System: Chemical and Volume Control Valve 1CS-167 Category:

Class:

ASME Section XI Quarterly Test Requirements: Verify backseat operability.

Cold Shutdown Test Justification: Backseat testing of valve 1CS-167 requires that the CSIP's take suction on a source, other than the VCT, which provides a higher pressure than normally exists in the VCT. The only available borated sources (i.e.,

RHR 6 Boric Acid Makeup) would also introduce high concentrations of boric acid which could lead to a plant reactivity transient.

Alternate Testing: Verify backseat operability at, cold shutdown when testing would not adversely affect reactivity.

l ISI-203 Rev. 8 Page 173 of 228

OS1 RELIEF RE UEST RV-1 System: Chemical and Volume Control Valve: 1CS-344,385,426,471,477 Category: AC Class:

Function: Containment'solation Simple Check Valve (reverse flow closure for containment isolation only).

Test Requirement: Verify reverse flow closure.

Basis for Relief: The only method available to verify reverse flow closure is by valve leak testing during Appendix J, Type C, testing at refueling.

Alternate Testing: Reverse flow closure will be verified during Appendix J, Type C, testing at refueling.

ISI-203 Rev. 8 Page 174 of 228

OS1 VALVE RELIEF RE UEST RV-2 System: Chemical and Volume Control Valve: 1CS-178,192,206 Category:

Class:

Function: Charging Pump Discharge Line Check Valves.

Test Requirements: Verify forward flow operability.

Basis for Relief: These Charging Pump discharge check valves cannot be verified for full flow operability quarterly. Normal operating charging flow is automatically controlled by downstream flow control valve*(lCS-231) in response to RCS operating conditions. To inject full flow into the RCS during normal operation would result in undesirable RCS boron concentrations and system pressure, temperature and level transients.

Full stroke exercising these valves at cold shutdown would result in RCS pressure and level transients due to limitations on letdown capability.

Alternate Testing: Valves will be partial stroke exercised quarterly and verification of full forward flow operability performed at 'refueling.

ISI-203 Rev. 8 Page 175 of 228

OS1 VALVE RELIEF RE UEST RV-3 System: Chemical and Volume Control Valve: 1CS-294 Category:

Class:

Function: RWST Line to CVCS Charging Pump Inlet Header Check Valve Test Requirements: Verify forward flow operability.

Basis for Relief: Verification of forward flow operability can only be performed by injecting RWST water into the RCS. While at power, the charging pumps have insufficient head to overcome normal RCS operating pressure for a full flow test. Partial stroke exercising while at power would adversely affect RCS boron concentration and could lead to a reactivity transient.

Full forward flow verification at cold shutdown could result in a cold overpressurization of the RCS. The only time that there is sufficient RCS expansion volume is during refueling while the reactor vessel head is removed.

Alternate Testing: Valve will be partial stroke exercised at cold shutdown and full stroke exercised at refueling.

ISI-203 Rev. 8 Page 176 of 228

OS1 VALVE RELIEF RE UEST RV-4 System: Chemical and Volume Control Valve: 1CS-341, 382, 423, 470, 472 Category:

Class:

Function: CVCS Seal Mater Flow to and from the Reactor Coolant Pumps Containment Isolation Valves Test Requirements: Exercise and Time Basis for Relief: Exercising these valves "'during normal operation" would damage the RCP seals. Exercising valves 1CS-341, 1CS-382, and 1CS-423 at cold shutdown would result in a loss of normal seal water to the RCS Pump Seals.

seal water were terminated, Reactor Coolant would be If forced from the higher pressure RCS into the seals.

Reactor Coolant normally contains a high particulate concentration which, if carried with RCS inleakage, could contaminate and damage the seals.

Alternate Testing: Valves 1CS-470 and 1CS-472 will be tested at cold shutdowns when seal leakoff is terminated. Valves 1CS-341, 1CS-382, and 1CS-423 will be tested at cold shutdowns when the RCS is drained to.,below the level of the RCP Seal packages, where seal injection can be safely terminated. All five valves will be tested at refueling.

ISI-203 Rev. 8 Page 177 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: CHEMICAL AND VOLUME CONTROL DWG.N0.2166.8-1303 CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK C.S. C.S. REMARKS REV VALVE AND (CAT.I (IN.) TYPE POSIT. REQ. DIRECT. VALVE JUST. OR NUMBER DWG. AND TEST OR ALT. NO.

COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1CS7 2 2 AO ,0 FS.1 C NOTE 1 8-10 GL TS-1 FC-1 PI.6 LJ.3 1CS8 2 2 AO 0 FS.1 NOTE 1 8-11 CK TS-1 FC.1 PI.6 LJ.3 1CS.S 2 2 AO 0 FS-1 C NOTE 1 8-1 2 GL TS-1 FC.1 PI.6 LJ'3 1CS-10 2 2X3 SA RLA NOTE 2 A-10 RL LJ-3 1CS.11 2 3 AO 0 FS-1 C CS.1 FS.2 NOTE 3 A-17 GL TS-1 CS-1 TS-2 FC-1 CS-1 FC-2 Pl.6 LJ.3 1 CS.238 2 A 3 MO 0 FSr1 C CS-1 FS.2 NOTE 4 817 GA TS.1 CS-1 TS.2 Pl-6 CS.1 LJ.3 1CS.341 2 A 1 1/2 MO 0 FS-1 C RV.4 FS.3 NOTE 6 K-3 GL TS 1 TS.3 NOTE 28 PI.6 FS.2 LJ-3 TS 2 1CS-344 2 AC 1 1/2 SA 0 . FS1 BS RV.1 SP-3 NOTE 6 K.3 CK LJ 3 F0.1 Pl 6 ISI-203 Rev. 8 Page 178 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: CHEMICAL AND VOLUME CONTROL DWG.N0.2165.S 1303 CLASS VALVE SIZE NORM, TEST STROKE CHECK C.S. C.S. REMARKS REV VALVE AND (CAT.) IIN3 POSIT. REQ. DIRECT. VALVE JUST. OR NUMBER DWG. AND TEST OR ALT. NO.

COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1CS.470 2 A 2 MO 0 FS I C RV.4 FS.3 NOTE 6 D 16 GL TS.1 TS-3 NOTE 26 FS.2

'I.B LJ.3 TS.2 1CS.471 2 AC 3/4 SA C FS.1 BS RV-1 SP-3 NOTE 6 E-16 CK LJ.3 1CS.472 2 A 2 MO 0 FS-I C RV.4 FS.3 NOTE 6 D.17 GL TS.1 TS-3 NOTE 26 PI.B FS-2 LJ-3 TS.2 1 CS-477 2 AC 3 SA 0 F91 FF NOTE 4 8-16 CK LJ-3 BS RV-1 SP-3 1CS.480 2 8 3 AO FS-1 0 CS.7 FS.2 NOTE 7 8.4 GL TM-1 TM.2 FO-1 PI.S 1CS.483 1 C 3 SA FS-1 FF CS-7 FS 2 NOTE 8 8.3 CK 1CS-486 1 3 SA FS.1 FF CS.7 FS 2 NOTE 8 8-3 CK 1CS.492 2 8 ' AO 0 FS-1 CS-7 FS.2 NOTE 7 C-4 GL TM.1 TM.2 F0.1 PI 8 1CS.497 1 3 SA 0 FS-1 FF NOTE 9 C-3 CK 1CS.SOO 1 3 SA 0 FS.1 FF NOTE 9 C.3 CK ISI-203 Rev. 8 Page 179 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: CHEMICAL AND VOLUME CONTROL DWG. NO. 2165.6 1303 601 CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK C.S. C.S. REMARKS REV VALVE AND (CATO (IN.) TYPE POSIT. REQ. DIRECT. VALVE JUST. OR NUMBER DWG. AND TEST OR ALT. NO.

COOR. TYPE DIRECT. REUEF TEST REQ.NO. .PERF.

I CS-362 2 A 1 1/2 MO 0 FS.1 C RV 4 FS 3 NOTE 6 L-3 GL TS.1 TS.3 NOTE 26 PI.S FS.2 LJ.3 TS.2 1CS.365 2 AC 1 1/2 SA 0 FS.1 BS RV-1 SP-3 NOTE 6 K.3 CK LJ-3 r

ISI-203 Rev. 8 Page 180 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: CHEMICAL AND VOLUME CONTROL DWG. NO. 2165.6.1303 602 CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK C.S. C.S. REMARKS REV VALVE AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE JUST. OR NUMBER DWG. AND TEST OR ALT. NO.

COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1CS-423 2 A 1 1/2 MO 0 FS.1 C RV-4 FS.3 NOTE 6

~ K.3 GL TS 1 TS.3 NOTE 26 PI.6 FS.2 LJ-3 TS.2 1CS-426 2 AC 1 1/2 SA 0 FS-1 BS RV-1 SP-3 NOTE 6 K-3 CK LJ.3 ISI-203 Rev. 8 Page 181 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: CHEMICAL AND VOLUME CONTROL DWG. NO. 2166-S-1304 CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK C.S. C.S. REMARKS REV.

VALVE AND I CAT.) IIN.) TYPE POSIT. REQ. DIRECT. VALVE JUST. OR NO.

NUMBER DWG. AND TEST OR ALT.

COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1CS-746 2 B 2 MO C FS1 0 NOTE 10 H-1B GL TM-I C PI.B 1CS-762 2 B 2 MO C FS1 0 NOTE 10 l.1B GL TM1 C Pl 6 ISI-203 Rev. 8 Page 182 'of 228

081 SHEARON HARRIS NUCLEAR POWER PLANT VALVETEST TABLE SYSTEM: CHEMICAL AND VOLUME CONTROL DWG. NO. 2165 6.1305 CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK C.S. C.S. REMARKS REV.

VALVE AND (CAT.I IIN.I TYPE POSIT. REQ. DIRECT. VALVE JUST. OR NO.

NUMBER DWG. AND TEST OR ALT.

COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1CS-165 2 8 4 MO 0 FS1 C CS-3 FS-2 NOTE 12 G.1 1 GA TM.1 CS-3 TM.2 PI.S I CS.166 2 B 4 MO 0 FS1 C CS.3 FS-2 NOTE 12 G-11 GA TM.1 TM.2 PI.5 1CS 167 2 AC 4 SA 0 FS-1 FF CS.B BS.2 NOTE 13 G 11 CK BS-1 BS LK-3 1CS-188 2 8 MO 0 FS1 C NOTE 14 I-11 GT TM-1 Pl-5 1CS-169' 2 8 MO 0 FS1 C NOTE 14 J-11 GT TM.1 PI.5 CS.170 2 8 MO 0 F81 C NOTE 14 1-11 GT TM.1 PI.5 I CS 171 2 8 MO 0 FS-1 C NOTE 14 K-11 GT TM-1 PI 5 1CS-178 2 3 SA OIC FS-1 FF RV.2 NOTE 15 H7 CK 88-1 BS 1CS 179 2 2 SA 0/C FS-1 FF NOTE 16 HB CK

'I CS.182 2 2 MO 0 FS I C NOTE 17 G-7 GL TM-1 PI.B ISI-203 Rev. 8 Page 183 of 228

091 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: CHEMICAL AND VOLUME CONTROL DWG.N0.2185-8.1305 CLASS VALVE SIZE NORM. TEST STROKE CHECK C.S. C.S. REMARKS REV VALVE AND (CAT.) IIN.) POSIT. REQ. DIRECT. VALVE JUST. OR NUMBER 'WG. AND TEST OR ALT.

COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1CS.192 2 C 3 SA 'OIC FS-1 FF RV-2 FS-3 NOTE 16 K-7 CK BS.I BS PE-1 I CS-193 2 C 2 SA 0/C FS-I FF NOTE 18 K.B CK I CS-196 2 8 2 MO 0 F81 C NOTE 17 J7 GL TM.1

, Pl-6 I CS-208 2 C 3 SA OIC FS-1 FF RV-2 FS-3 NOTE 16 J-7 CK 88-1 BS PE-1 1 CS.207 2 2 SA OIC FS-I FF NOTE 18 18 CK 1CS-210 2 2 MO 0 F81 C NOTE 17 1-7 GL TM. I Pl.6 I CS-214 2 3 MO 0 FS-1 C NOTE 17 G4 GA TM.1 Pl 6 I CS.217 2 4 MO 0 FS-1 C NOTE 18 1.8 GA TM-1 Pl-6 1CS 218 2 4 MO 0 F81 C NOTE 18 JS GA TM-1 Pl-6 I CS.219 2 4 MO 0 FS-I C NOTE 18 1.8 GA TM. I PI.6 I

1CS.220 2 4 MO 0 FS-1 . C NOTE 18 K-8 GA TM-I Pl-6 ISI-203 Rev. 8 Page 184 of 228

081 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: CHEMICAL AND VOLUME CONTROL DWG.N0.2186 8.1306 CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK C.S. C.S. REMARKS REV VALVE AND ICAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE JUST. OR NUMBER DWG. AND TEST OR ALT. NO.

COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

I CS 231 2 B 3 AO TH FS.1 0 CS.1 FS-2 NOTE f9 H-4 GL TM-1 CS-1 TM-2 F0.1 CS.1 F0.2 PI.6 1 CS.236 2 B 3 MO 0 FS-1 C CS.1 FS.2 NOTE 20 H.2 GA TM.1 CS.1 TM.2 Pl-6 1 CS.278 2 B 2 MO C FS.1 0 NOTE 21 J.18 GL TM-1 PI-6 1CS.279 2 C 2 SA C FS-1 FF CS.4 FS 2 NOTE 21 J-13 CK 1CS-290 2 C 3/4 X 1 SA C RL-4 NOTE 2 J-13 RL 1CS.291 2 B 8 MO C FS-1 C CS.3 FS-2 NOTE 12 I~ 12 GA TM-1 0 TM-2 PI 6 1CS.292 2 8 8 MO C FS-1 C CS.3 FS.2 NOTE 12 K-12 GA TM-1 0 TM 2 PI.6 1CS-293 2 C 3/4 X 1 SA C RL.4 NOTE 2 K.13 RL 1CS-294 2 C 8 SA C FS-1 FF CS 6 FF-3 NOTE 22 K.14 CK BS RV.3 88-2 PE.2

~ 1CS.310 2 C 3/4 X 1 SA C RL.4 NOTE 11 E-4 RL 1 CS.776 2 C 8.00 SA C FS-1 FF CS.S J.13 CK BS I CS-778 2 C 8.00 SA C FS-1 FF CS8 K-13 CK BS ISI-203 Rev. 8 Page 185 of 228

OS1 SHEARON HARRIS NUCI.EAR POWER PLANT VALVETEST TABLE SYSTEM: CHEMICAL AND VOLUME CONTROL DWG.NO.2166.6-1307 CLASS VALVE SIZE A CTU. NORM. TEST STROKE CHECK C.S. . C.S. REMARKS REV VALVE AND (CAT.) IIN.) TYPE POSIT. REQ. DIRECT. VALVE JUST. OR NUMBER DWG. AND TEST OR ALT.

COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1CS 636 3 C 2 SA C FS.1 FF NOTE 23 E.7 CK BS.1 BS 1CS 646 3 C 2 SA C FS.1 FF NOTE 23 G-7 CK BS-1 BS Pl.6 1CS 669 3 B 2 PO 0 FS-1 0 NOTE 24 E-3 PG TM-1 FO.1 PI.S 1CS-663 3 E-2 B 2,- PO 0 FS.1 0 NOTE 24 PG TM 1 FO.'I PI.6 ISI-203 Rev. 8 Page 186 of 228

os1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.27 VALVE TEST TABLES AND RELIEF REQUESTS FOR SAFETY INJECTION DWG. NO. 2165-S-1308 2165-S-1309 2165-S-1310 ISI-203 Rev. 8 Page 187 of 228

os1 SYSTEM: SAFETY INJECTION NO. NOTE BIT Inlet Block Valves. Valves open on a S signal for BIT injection.

BIT Discharge to RCS at CTMT Penetration M-17. Valves open on a S signal and close for CTMT Isolation by operator action.

Safety Injection into the RCS Line Check Valves.

CVCS Charging Pump Discharge to CTMT Penetration Isolation Valves. At cold shutdown only one Charging Pump is in operation due to potential for cold overpressurization. Pump Discharge Header cannot be isolated without loss of seal injection flow.

RHR Heat Exchanger Outlet to RCS Line Check Valves.

Containment Isolation Valves.

Accumulator Safety Relief Valves.

Accumulator Discharge to RCS Line Check Valves. Valves are pressure isolation valves.

Accumulator Drain to RWST Containment Isolation Valves.

10. Recirculation Sump Line Block Valves. Because of inline block valves it should, be possible to exercise these valves without injecting water into the Containment Recirculation Sumps. If it is found that valve exercising does drain water back into the sumps a relief request will be prepared to delay testing to refueling when water can be removed from. the sumps after exercising.

Forward flow of these 14 inch check valves is verified by flow through the RHR Pump 8 inch test line to the RWST. The test line flow is adequate to verify that the valves will pass full design operating flow.

Engineering Evaluation (PCR-3921) showed that at no time would sump water have the tendency to flow in the direction of the RWST. Therefore, backseat testing is not required.

ISI-203 Rev. 8 Page 188 'of 228

os)

SYSTEM: SAFETY INJECTION NO. NOTE

. RWST Line Block Valves. Valves close for recirculation mode of system operation.

13. Cross-tie Header Block Valves.

14. Relief Valves which protect Safety-Related Equipment.

RHR Heat Exchanger Line to RCS Block Valves.

16. Low Head Safety Injection Line Check Valves. Valves are high pressure isolation valves between the RCS and the RHR systems.

17. A pressure isolation valve with a single downstream check valve. To preclude opening during operation the valve is electrically disabled.

18. 'Parallel path check valve. Reviewed for adequacy of testing by PCR-5281.

ISI-203 Rev. 8 Page 189 of 228

os1 COLD SHUTDOWN TEST JUSTIFICATION CS-1 System: Safety Inj ection Valve: 1SI-81, 82, 83, 134, 135, 136, 137, 346, 347, 356, 357, 358 Category: AC(1SI-134, 135, 136, 137, 346, 347, 356, 357, 358) C (1SI-81, 82, 83)

Class: 1(1SI-81, 82, 83, 134, 135, 136, 137, 356, 357, 358) 2(1SI-346,347)

ASME Section XI Quarterly Test Requirements: Verify forward flow operability.

'old Shutdown Test Justification: Verification of forward flow operability of these normally closed check ~alves can only be performed bg injecting RHR water into the RCS.

During normal operation the Low Pressure RHR Pumps cannot overcome the higher RCS operating pressure. Testing these valves with high head safety injection will cause pressurizer level control problems along with borating the RCS possibly leading to a reactor scram. The isolation valve test subsystem provides the capacity for determination of the integrity of these pressure isolation valves. It is used to verify that each of the series check valves are closed and can sustain operational differential pressure. This is a required periodic procedure performed at each refueling after RCS has been pressurized.

Quarterly Part Stroke Testing: N/A Cold Shutdown Testing: Verify forward flow operability during RHR System operation.

ISI-203 Rev. 8 Page 190 of 228

OS1 COLD SHUTDOWN TEST JUSTIFICATION CS-2 System: Safety Injection Valve: 1SI-359 Category:

Class:

ASME Section XI Quarterly Test Requirements: Exercise and Time.

Cold Shutdown Test Justification: This valve is a normally closed motor operated valve upstream of a single check valve and serves as the second high pressure boundary valve between the RCS and the low pressure piping of the Residual Heat Removal System. To prevent opening during normal operation the valve is electrically disconnected (see Tech.

Spec. 4.5.2..8) and administratively maintained closed. Exercising during normal operation could result in an overpressurization of the RHR System piping and result in an Inter-System-LOCA condition.

Quarterly Part Stroke Testing: Valve is electrically disconnected.

Cold Shutdown Testing: Exercise and Time.

ISI-203 Rev. 8 Page 191 of 228

os1 VALVE RV-1 System: Safety Injection Valve: 1SI-8, 9, 10, 72, 73, 74, 104', 105, 106, 127, 128, 129, 138 Category:

Class:

Function: Safety Injection to the RCS Check Valves.

Test Requirements: Verify forward flow.

'asis for Relief: Verification of forward flow operability can only be performed by injecting charging water into the RCS. The charging pumps have insufficient head to overcome normal RCS operating pressure for a full flow test.

Partial testing using the charging pumps would inject CVCS water which has bypassed the Regenerative Heat Exchanger and could result in thermal shocking to the RCS piping. Forward flow verification at cold shutdown could result in a cold overpressurization of the RCS.

Alternate Testing: Verify forward flow operability at refueling when the Reactor Vessel Head is removed and full charging pump flow can be injected into the RCS.

ISI-203 Rev. 8 Page 192 of 228

os1 VALVE RELIEF RE UEST RV-2 System: Safety Injection Valve: 1SI-52,86,107 Category:

Class:

Function: Safety Injection to the RCS Hot Legs Containment Isolation Valves.

Test Requirement: Exercise and Time.

Basis for Relief: Exercising these 'valves during normal operation would result in injecting charging water flow directly into the RCS. This diverted charging water bypasses the Regenative Heat Exchanger which could cause thermal shocking to RCS piping and could also cause an overtemperature condition in the normal CVCS Letdown Line. At cold shutdown one Charging Pump is running (Tech. Spec. 3.5.3, A maximum of one Charging Pump shall be operating when RCS temperature is

( 335 degrees F). This pump is supplying both RCP Pump Seals and required charging water.

Seal Water flow is maintained during cold shutdown to preclude damage to the pump seals, thus if these valves were exerci'.sed at cold shutdown charging water would be injected into the RCS and a cold overpressurization of the RCS could'result.

Alternate Testing: Valves will be exercised and timed at refueling.

ISI-203 Rev. 8 Page 193 of 228

os1 VALVE RELIEF RE UEST RV-3 System: Safety Injection Valve: 1SI-182;290 Category: AC Class:

Function: Containment Isolation Simple .Check Valve (reverse flow closure for containment isolation only).

Test Requirement: Verify reverse flow closure.

Basis for Relief: The only method available to verify reverse flow closure is by valve leak testing during Appendix J, Type C, testing at refueling.

Alternate Testing: Reverse flow closure will be verified during Appendix J, Type C, testing at refueling.

ISI-203 Rev. 8 Page 194 'of 228

OS1 VALVE RELIEF RE UEST RV-4 System: Safety Injection Valve: 1SI-249,250,251,252,253,254 Category: AC Class:

Function: Accumulator Discharge to RCS Check Valves.

Test Requirement: Verify forward flow operability.

Basis for Relief: The Accumulator Tanks are isolated from the RCS by these normally. closed check valves. Each Accumulator is charged with a Nitrogen blanket at approximately 650 psig, which is insufficient to inject into the RCS during normal operation.

To exercise these valves to their full open position at cold shutdown would inject approximately 925 Cubic Ft. of high Boron Content water into t'e RCS, which could cause a cold overpressurization of the RCS. Dumping the full Accumulator inventory into the RCS at refueling could flush large amounts of crud into the RCS and Cleanup Systems. High particulates in the RCS at refueling reduces visibility for refueling operations and generates large amounts of contaminated wastes, which could lengthen the outage and increase personal exposures.

Alternate Testing: .Partial forward flow operability will be verified at cold shutdown by performing an accumulator partial dump test. In addition one valve will be disassembled and visually inspected at refueling. Valve inspections will alternate with subsequent refuelings.. Failure of a valve to pass inspection will either initiate inspection of the remaining valves or initiate verification of the remaining valves by Accumulator injection into the RCS.

ISI-203 Rev. 8 Page 195 of 228

081 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEH: SAFETY INJECTION DWG. NO. 2165-S-1308 VALVE CLASS VALVE SIZE ACTU. NORH. TEST STROKED CHECK C.S. C.S.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1SI-1 2 B 3 HO ~ C FS-1 0 NOTE 1 H-6 GA TS-1 C PI-5 1SI-2 2 B 3 . HO C FS-1 0 NOTE 1 N-6 GA TS-1 C PI-5 1SI-3 3 A 3 HO C FS-1 0 NOTES 2,6 G-2 GA TS-1 C PI-5 1SI-4 2 A 3 HO C FS-1 0 NOTES 2,6 F-11 GA TS-1 C PI-5 1SI-8 1 2 SA C FS-1 FF RV-1 FF-3 NOTES 3,6 D-3 CK 161-9 1 SA C FS-1 FF RV-1 FF-3 NOTES 3,6 D 4 ISI-IO . 1 SA C FS-1 FF RV-1 FF-3 NOTES 3,6 D-5 1SI-52 . 2 3 FS-1 0 RV-2 ~ FS-3 NOTES 4,6 F-11 GA TS-1 C RV-2 TS"3 PI-5 1SI-72 1 SA FS-1 FF RV-1 FF-3 NOTES 3,6 D-6 1SI-73 1 SA FS-1 FF RV-1 FF-3 NOTES 3,6 D-7 1SI-74 1 SA FS-1 FF RV-1 FF-3 NOTES 3,6 D-8 1SI-81 1 6 SA FS-1 FF CS-1 FF-2 NOTE 3 B-3 CK ISI-203 Rev. 8 Page 196 of 228

081 SHEARON HARRIS NUCLEAR P(NER PLANT VALVE TEST TABLE SYSTEM: SAFETY INJECTION DWG. NO. 2165-S-1308 CLASS VALVE SIZE ACTH. NORM. TEST STROKED CHECK C.S. C.S.

AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1SI-82 1 C 6 SA FS-1 FF CS-1 FF-2 NOTE 3 C-3 CK 1SI-83 1 C 6 SA FS-1 FF CS-1 FF-2 NOTE 3 D-3 CK 1SI-86 2 A 3 MO FS-1 0 RV-2 FS-3 NOTES 4,6 F-12 GA TS-1 C RV-2 TS-3 PI-5 1SI-104 1 C 2 SA FS-1 FF RV-1 FF-3 NOTES 3,6 D-12 CK 1SI-105 1 C 2 SA FS-1 FF RV-1 FF-3 NOTES 3,6 D-13 CK 1SI-106 1 C 2 SA FS-1 RV-1 FF-3 NOTES 3,6 D 4 CK 1SI-107 2 A 3 MO FS-1 0 RV-2 FS-3 NOTES 4,6, F-15 GA TS-1 C RV"2 TS-3 PI-5 1SI-127 1 2 SA FS-1 RV-1 FF-3 NOTES 3,6 D-15 CK 1SI-128 1 SA FS-1 FF RV-.1 FF-3 NOTES 3,6 D-15 1SI-129 1 2 SA FS-1 FF RV-1 FF-3 NOTES 3,6 D-16 CK 1SI-134 1 AC 6 SA FS-1 CS-1 FF-2 NOTES B-11 LK-3 5,6,18 1SI-135 1 AC 6 SA FS-1 CS-1 FF-2 NOTES C-11 CK LK-3 5,6,18 1SI-136 1 6 SA FS" 1 FF CS-1 FF-2 NOTE 3,18 B-17 CK 1SI-137 1 6 SA FS-1 CS-1 FF-2 NOTE 3,18 C-17 CK 1SI-138 1 6 SA FS-1 FF RV-1 FF-3 NOTE 3 D-17 CK ISI-203 Rev. 8 Page 197 of 228

081 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: SAFETY INJECTION DHG. NO. 2165-S-1309 VALVE CLASS VALVE SIZE ACTH. NORM. TEST STROKED CHECK C.S. C.S.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR ALT.

COOR. ~ TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1SI-179 2 A 1 AO C FS-1 NOTE 6 K-17 GL TS-1 FC-1 PI-5 LJ-3 1SI-182 2 AC 1 SA C FS-1 BS RV-3 SP-3 NOTE 6 K-16 CK LJ-3 1SI-225 2 1X2 SA C NOTE 7 B-12 RL 1SI-226 2 1X2 SA C NOTE 7 E-12 RL 1SI-227 2 1X2 SA NOTE 7 H-12 RL 1SI-249 2 AC 12 SA C FS-1 FF RV-4 PE-2 NOTE 8 D-6 CK LK-3 DS-3 1SI-250 2 AC 12 SA C FS-1 RV-4 PE-2 NOTE 8 D-3 CK LK-3 DS-3 1SI-251 2 AC 12 SA C FS-1 FF RV-4 PE-2 NOTE 8 G-6 CK LK-3 DS-3 1SI-252 2 AC 12 SA C FS-1 FF RV-4 PE-2 NOTE 8 G-3 CK LK-3 DS-3 1SI-253 2 AC 12 SA C FS-1 FF RV-4 PE-2 NOTE 8 J-6 CK LK-3 DS-3 1SI-254 2 AC 12 SA C FS-1 FF RV-4 PE-2 NOTE 8 J-3 CK LK-3 DS 3 1SI-263 2 3/4 AO C FS-1 NOTE 9 D-4 GL TS-1 FC-1 PI-5 LJ-3 1SI-264 2 3/4 AO C FS-1 NOTE 9 D-4 GL TS-1 FC-1 PI-5 LJ-3 1SI-287 2 1 AO C FS-1 NOTE 6 C-17 GL TS-1 FC"1 PI-5 LJ-3 1SI-290 2 AC 1 SA C PS-1 BS RV-3 SP-3 NOTE 6 C-16 CK JL-3 ISI-203 Rev. 8 Page 198 of 228

061 SHEARON HARRIS NUCLEAR P(NER PLANT VALVE TEST TABLE SYSTEH: SAFETY INJECTION DNG. NO. 2165-S-1310 VALVE CLASS VALVE SIZE ACTU. NORH. TEST STROKED CHECK C.S. C.S.

NUHBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1SI-300 2 B 14 HO C FS-1 0 NOTES N-6 GA TS-1 C 10,6 PI-5 1SI-301 2 B 14 HO C FS-1 0 NOTES H-6 GA TS-1 C 10,6 PI-5 1SI-310 2 B 14 HO C FS-1 0 NOTE 10 N-7 GA TS-1 PI-5 1SI-311 . 2 B 14 HO C FS-1 0 NOTE 10 H-7 GA TS-1 PI-5 1SI-320 2 N-12 C 14 CK SA C FS-1 FF NOTE il 1SI-321 2 C 14 SA FS-1 H-12 'K C FF NOTE 11 1SI-322 2 B 14 HO 0 FS-1 C NOTE 12 N-10 GA TH-1 0 PI-5 1SI-323 2 B 14 HO 0 FS-1 C NOTE 12 H-10 GA IH-1 0 PI-5 1SI-326 2 B 10 HO 0 FS-1 C NOTE 13 D-6 GA TH-1 0 PI-5 1SI-327 2 B 10 HO 0 FS-1 C NOTE 13 E-6 GA TH-1 0 PI-5 1SI-328 2 C 3/4X1 SA C RL-4 NOTE 14 B-4 RL 161-329 2 C 3/4X1 SA C RL-4 NOTE 14 E"4 RL 1SI"330 2 C 3/4X1 SA C RL-4 NOTE 14 B-5 RL 1SI-340 2 B 10 HO 0 FS-1 C NOTE 15 C-4 GA TS-1 0 PI-5 1SI-341 2 B 10 HO 0 FS-1 C NOTE 15 E-4 GA TS-1 0 PI-5 ISI-203 Rev. 8 Page 199 of 228

OS1 SHEARON HARRIS NUCLEAR POHER PLANT VALVE TEST TABLE SYSTEM: SAFETY INJECTION DWG. NO. 2165-S"1310 VALVE CLASS VALVE SIZE ACTH. NORM. TEST STROKED CHECK C.S. C.S.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DHG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1SI-346 2 AC 10 SA C FS-I FF CS-1 FF-2 NOTES C-3 CK LK-3 16,6 1SI-347 2 AC 10 SA C FS-1 FF CS-1 FF-2 NOTES E-3 CK LK-3 16,6 1SI-356 1 AC 6 SA C FS-1 FF CS-1 FF-2 NOTE 16 C-2 CK LK-3 1SI-357 1 AC SA C FS-1 FF CS-1 FF-2 NOTE 16 E-2 LK-3 1SI-356 1 AC SA C FS-1 FF CS-1 FF-2 NOTE 16 E-2 LK-3 161-359 2 10 C FS-1 0 CS-2 FS-2 NOTES B-4 GA TS-1 C CS-2 TS-2 17,6 PI-5 LK-3 ISI-203 Rev. 8 Page 200 'of 228

os]

PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.28 VALVE TEST TABLES AND RELIEF REQUESTS FOR CONTAINMENT WASTE PROCESSING DWG. NO. 2165-S.-1313 ISI-203 Rev. 8 Page 201 of 228

os1 SYSTEM: CONTAINMENT WASTE PROCESSING NO. NOTE Containment Isolation Valves.

ISI-203 Rev. 8 Page 202 of 228

061 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: CONTAINMENT WASTE PROCESSING DWG. NO. 2165-S-1313 VALVE CLASS VALVE SIZE ACTH. NORM. TEST STROKED CHECK C.S. C.S.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

IED-119 2 3 MA LC PV NOTE 1 E" 17 DA LJ-3 1ED-121 2 3 AO 0 FS-1 C NOTE 1 E-16 GL TS-1 FC-1 PI-5 LJ-3 1ED-125 2 3 AO 0 FS-1 C NOTE 1 D-16 DA TS-1 FC-1 PI-5 LJ"3 1ED-161 2 3/4 AO 0 FS-1 0 NOTE 1 C"7 DA TS-1 FC-1 PI-5 LJ-3 IED-164 2 3/4 AO 0 FS-1 .C NOTE 1 E-6 DA TS-1 FC-1 PI-5 LJ-3 ISI-203 Rev. 8 Page 203 of 228

os1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.29 VALVE TEST TABLES AND RELIEF REQUESTS FOR COMPONENT COOLING WATER DWG. NO. 2165-S-1319 2165-S-1320 2165-S-1321 2165-S-1322 2165-S-1322 S01 ISI-203 Rev. 8 Page 204 of 228

os1 SYSTEM: COMPONENT COOLING WATER NO. NOTE One of the three pumps is an installed spare. During normal operation one pump is running, a second pump aligned to automatically start if the running pump fails and the third is electrically disabled. Only those valves associated with the operating and reserve pumps will be tested. When one of these is removed from service and the installed spare put into service, valve operability will be verified and section XI testing initiated.

Pump Discharge Check Valves. Reverse flow closure required to prevent recirculation flow back across the idle reserve pump.

Header Cross-tie Block Valves. Valves used to isolate Trains for Post-LOCA system alignment.

'Sample System Block Valves. Valves close on a S signal.

Sample System Return Check Valve. Valve is relatively large and reverse flow closure is required to prevent excessive leakage from the system.

Thermal relief valves added to the program to comply with North Carolina State Requirements.

CCW to RHR Heat Exchanger Block Valves. Valves open when RHR is in operation.

Excess Letdown and Reactor Coolant Drain Tank Line Block Valves.

CCW to Reactor Coolant Pump Thermal Barriers. Cooling water must b'e provided at all times when RCS temperature*is. above 200 Degrees F. CCW to the thermal barriers is not required during an accident.

10. CCW Inlet to Reactor Coolant Pump Thermal Barriers.

Reverse flow closure required to prevent damage to CCW low pressure piping from excessive high pressure thermal barrier leakage.

Relief Valve which protects Safety-Related Equipment.

ISI-203 Rev. 8 Page 205 of 228

os1 SYSTEM: COMPONENT COOLING WATER NO. NOTE

12. Containment Penetration Isolation Valve By-Pass Check Valve. Valve functions as a thermal relief when both CTMT. Pen. Isolation Valves are closed. Only Safety-Related function is to provide containment isolation.

13. CCW to Gross Failed Fuel Detector Block Valves.

Valves close on a S signal.

14. Containment Isolation Valve ISI-203 Rev. 8 Page 206 'of 228

os1 VALVE RV-1 System: Component Cooling Water Valve: 1CC-211,250,298 Category: AC Class:

Function: Containment Isolation Simple Check Valve (reverse flow closure for containment isolation only).

Test Requirement: Verify reverse flow closure.

Basis for Relief: The only method available to verify reverse flow closure is by valve leak testing during Appendix J, Type C, testing at refueling.

Alternate Testing: Reverse flow closure will be verified during Appendix J, Type C, testing at refueling.

ISI-203 Rev. 8 Page 207 of 228

os1 VALVE RELIEF RE UEST RV-2 System: Component Cooling Water Valve: 1CC-216,227,238 Category:

Class:

Function: These Check Valves will close to protect the low pressure CCW piping from RCP Thermal Barrier Leakage.

Test Requirement: Verify Reverse flow Closure.

Basis for Relief: The Westinghouse RCS Pumps must have cooling

~ater to the bearing oil coolers and thermal barriers at all times when the RCS temperature is above 200 degrees F. and there are no installed taps or position indicators that could be used to verify reverse flow closure. Any possible test involves verification of these and associated upstream non-safety-related check valves as a single unit. To verify reverse flow closure at cold shutdown would involve draining large segments of the system and providing an alternate source of pressurized water inside the containment which may not be accessible during cold shutdown. Also, this test would involve waste processing of the water removed for testing and of the water used for testing. This type'of te'sting would involve an excessive amount of time and personnel and could cause delays in plant startup.

Alternate Testing: One valve will be disassembled and visually inspected at refueling and alternate valves will be done during subsequent refuelings. Only one valve will be inspected at a refueling unless fails to pass inspection. Failure to pass it inspection will initiate disassembly and inspection of the other two valves.

ISI-203 Rev. 8 Page 208 of 228

os I VALVE RELIEF RE UEST RV-3 System: Component Cooling Water Valve: 1CC-207,208,249,251,252,297,299 Category: A(1CC-208,249,251,252,297,299)

B(1CC-207)

Class:

Function: Component Cooling Water to the Reactor Coolant Pump Thermal Barriers and Bearing Oil Coolers.

Test Requirements: Exercise and Time.

Basis for Relief: These are the Containment Isolation and Block valves in the RCP thermal barrier and bearing oil cooler lines. A loss of cooling water for more than a few minutes could result in extensive damage to the Reactor Coolant Pumps.

Westinghouse-Document 1B5710-100-07A states that cooling water must be provided to the pumps at all times when the RCS temperature is above 200 degrees F.. Because of local temperature variations in the RCS at RCS temperature near 200 degrees F, at least one RCP may be kept in operation during short duration cold shutdowns where the RCS temperature is maintained near 200 degrees F. It is felt that under these conditions stopping cooling water to the operating pump could contribute to pump degradation and result in unnecessary pump repairs..

Alternate Testing: Exercise and time at cold shutdown, when the RCS temperature is less than or equal to 200 degrees. It is our intent to perform this test when the corresponding RCP can be stopped.

ISI-203 Rev. 8 Page 209 of 228

091 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: COMPONENT COOLING WATER DWG. NO. 2165-S-1319 VALVE CLASS VALVE SIZE ACTU. NORH. TEST STROKED CHECK C.S. C.S.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR ALT.

COOR. .TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1CC-33 3 C 18 SA 0/C FS-1 FF NOTES 1,2 E-8 CK BS-1 BS 1CC-50 3 C 18 SA 0/C FS-1 FF NOTES 1,2 K-8 CK BS-1 BS 1CC"64 3 C 18 SA 0/C FS-1 FF NOTES 1,2 H-8 CK BS-1 BS 1CC-99 3 B 18 HO 0 FS-1 C F-17 BF TH-1 PI-5 1CC-113 3 B 18 HO 0 FS-1 C NOTE 3 G-17 BF TM-1 PI-5 1CC-114 3 B 4 AO 0 FS-1 C NOTE 4 F-18 DA TM-1 FC-1 PI-5 1CC-115 3 B 4 AO 0 FS-1 C NOTE 4 F-18 DA TH-1 FC-1 PI-5 1CC-118 3 C 4 SA 0/C FS-1 BS NOTE 5 H-2 CK 1CC-119 3 C 4 SA 0/C FS-1 BS NOTE 5 I-2 CK 1CC-127 3 B 18 HO 0 FS-1 C NOTE 3 H-3 BF TH-1 PI-5 1CC-128 3 B 18 HO 0 FS-1 C NOTE 3 G-3 BF TM-1 PI-5 1CC-129 3 C 3/4X1 SA C RL-4 NOTE 6 G-4 RL ISI-203 Rev. 8 Page 210 of 228

031 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: COMPONENT COOLING WATER DWG. NO. 2165-S-1320 CLASS VALVE SIZE ACTU. NORH. TEST STROKE CHECK C.S. C.S.

VALVE NUMBER AND (CAT. (IN. TYPE POSIT REQ. DIRECT VALVE JUST. OR NO.

DWG. ) ) TEST OR ALT.

COOR. AND DIRECT RELIEF TEST TYPE REQ.NO PERF.

1CC-147 3 B 12 HO C FS-1 0 NOTE 7 A-7 GA TH-1 PI-5 1CC-167 3 B 12 HO C FS 1 0 NOTE 7 L-7 GA TH-1 PI-5 LSI-203 Rev. 8 Page 211 of 228

081 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: COMPONENT COOLING WATER DWG. NO. 2165-S-1321 VALVE CLASS VALVE SIZE ACTU. NORH. TEST STROKED CHECK C.S. C.S.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1CC-176 2 B 6 HO 0 FS-1'S-1 NOTES D-3 GA 8,14 PI-5 1CC-186 2 C 3/4X1 SA C RL-4 NOTES D-8 RL 6,14 1CC-194 2 C 3/4X1 SA C RL-4 NOTES E-8 RL 6,14 ICC-202 2 A 6 MO 0 FS-1 NOTES B-10 GA TS-1 8,14 PI-5 1CC-207 2 B 6 HO 0 FS-1 RV"3 RS-2 NOTE 9 E-1 GA TH-1 TM-2 PI-5 FS"3 TM-3

'CC-208 2 A 6 0 FS-1 C RV-3 FS-2 NOTES F"1 GA TH-1 TM-2 9,14 PI-5 FS-3 LJ-3 TS-3 1CC-211 2 AC SA 0 FS-1 BS RV-1 SP-3 NOTE 9,14 F-1 LJ-3 1CC-216 3 C 2 SA 0 FS-1 BS RV-2 DS NOTE 10 N-2 CK 1CC-219 3 C 3/4X1 SA C RL"4 NOTE 11 N-4 RL 1CC-227 3 C 2 SA 0 FS-1 BS RV-2 DS NOTE 10 N-5 CK 1CC-230 3 C 3/4X1 SA C RL-4 NOTE 11 N-8 RL 1CC-238 3 C 2 SA 0 FS-1 BS RV-2 DS NOTE 10 N-9 CK 1CC-241 3 C 3/4X1 SA C RL-4 NOTE 11 N-11 RL 1CC-249 2 A 4 ~ HO 0 FS-1 C RV-3 FS-2 'OTES F-15 GA TS-1 TS-2 9, 14 PI-5 FS-3 LJ-3 TS-3 1CC-250 2 AC 3/4 SA C FS-1 BS RV-1 SP-3 NOTES F-15 CK LJ-3 12, 14 1CC-251 2 A 4 . HO 0 FS-1 C RV-3 FS-2 NOTES E-15 Gh TS-1 TS-2 9,14 PI-5 FS-3 LJ-3 . TS-3 ISI-203 Rev. 8 Page 212 of 228

091 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEH: COMPONENT COOLING WATER DWG. NO. 2165-S-1321 VALVE CLASS VALVE SIZE ACTU. NORH. TEST STROKED CHECK C.S. C.S.

NUMBER AND (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR ALT.

COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1CC"252 2 4 HO 0 FS-1 C RV-3 FS-2 NOTE 9 D-14 GA TS-1 TH-2 PI-5 FS-3 TH-3 1CC-294 2 3/4 SA C RL-4 NOTE 11 F-12 RL ICC-297 2 6 HO 0 FS 1 C RV-3 FS-2 NOTES F-12 GA TS-1 TS-2 9,14 PI-5 FS-3 LJ-3 TS-3 1CC-298 2 AC 3/4 SA C FS-1 BS RV-1 SP-3 NOTE 12 F-13 CK LJ-3 1CC"299 2 6 HO O,FS-l C RV-3 FS-2 NOTES E"12 GA TS"1 TS-2 9,14 PI-5 FS-3 LJ-3 TS-3 ISI-203 Rev. 8 Page 213 of 228

OS1 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: COMPONENT COOLING WATER DWG. NO. 2165-S-1322 CLASS VALVE SIZE ACTH. NORM. TEST STROKE CHECK C.S. C.S.

VALVE NUMBER AND (CAT. (IN. TYPE POSIT REQ. DIRECT VALVE JUST. OR NO.

DWG. ) ) TEST OR COOR. AND DIRECT RELIEF TEST TYPE REQ.NO PERF.

1CC-304 3 B 3/4 AO 0 FS-1 C NOTE 13 A-6 .GA TM-1 FC-1 PI-5 1CC-305 3 B 3/4 AO 0 FS-1 C NOTE 13 A-6 GA TM-1 FC-1 PI-5 1CC-313 3 C 3/4XI SA C RL-4 NOTE 6 E"5 RL lSI-203 Rev. 8 Page 214 of 228

061 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: COMPONENT COOLING WATER DWG. NO. 2165-S-1322 S01 CLASS VALVE SIZE ACTU. NORM. TEST STROKE CHECK C.S. C.S.

VALVE AND (CAT.) (IN.) TYPE POSIT. REQ. DIRECT. VALVE JUST. OR NO.

NUMBER DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1CC-520 3 C 3/4X1 SA C RL-4 NOTE 6 E" 14 RL 1CC-534 3 C 3/4X1 SA C RL-4 NOTE 6 H-10 RL ISI-203 Rev. 8 Page 215 of 228

os1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.30 VALVE TEST TABLES AND RELIEF REQUESTS FOR RESIDUAL HEAT REMOVAL DWG. NO. 2165-S-1324 ISI-203 Rev. 8 Page 216 of 228

os1 SYSTEM: RESIDUAL HEAT REMOVAL NO. NOTE Boundary valves between high pressure RCS and the low pressure RHR. Valves are maintained closed during normal operation and are Pressure Isolation Valves.

Relief Valve which protects Safety-Related Equipment.

RHR Cross-tie to the CVCS opens for Safety-Related modes of operation.

RHR Heat Exchanger Outlet Flow Control Valves. Valves are used to control flow during RHR System operation.

Valves are normally open, fail open and are maintained open with the controller for LPCI mode of operation.

Test only the fail open feature for Section XI testing.

RHR Pump Min. Flow Line Block Valves. Valves close to prevent recirculation flow and to prevent flow, diversion during system operation.

RHR System LHSI Lfne Check Valves. Reverse flow closure is required to prevent flow recirculation through the idle pump. Forward flow is verified using the 8 inch test line which is adequate to verify full flow operability of these 10 inch Valves.

Flow Control Valves which modulate to maintain flow in conjunction with RHR Hx Outlet Valves. Valves are normally closed and may be required to close in Mode 4.

ISI-203 Rev. 8 Page 217 of 228

os1 COLD SHUTDOWN TEST JUSTIFICATION CS-1 System: Residual Heat Removal Valve: 1RH-1,2,39,40 Category:

Class:

ASME Section XI Quarterly Test Requirements: Exercise and Time.

Cold Shutdown Test Justification: These are boundary valves between the high pressure Reactor coolant System and the low pressure Residual Heat Removal System piping.

The valves are interlocked to RCS pressure and cannot be opened with RCS pressure greater than 425 psig. Defeating the interlocks to perform testing is not desirable since they are pressure isolation valves. If the inline valves were inadvertently opened during testing an Inter-System-LOCA could occur.

Quarterly Part Stroke Testing: Partial valve exercising is precluded for the same reasons as full stroke exercising.

. Cold Shutdown Testing: Exercise and Time.

ISI-203 Rev. 8 Page 218 of 228

061 SHEARON HARRIS NUCLEAR P(NER PLANT VALVE TEST TABLE SYSTEM: RESIDUAL HEAT REMOVAL DNG. NO. 2165-S-1324 VALVE CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S. REMARKS RE V.

NUMBER AND (CAT.) (IN. ) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DNG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ. NO. PERP.

1RH-1 1 12 MO C FS-1 0 CS-I FS-2 NOTE 1 L-3 GA TS-1 C CS-1 TS-2 PI-5 LK-3 1RH-2 1 12 MO C FS-1 0 CS-1 FS-2 NOTE 1 L-4 GA TS-1 C CS-1 TS-2 PI-5 LK-3 1RH" 7 2 3X3 SA NOTE 2 H-6 1RH-25 2 6 MO C FS-1 0 NOTE 3 C-12 GA TM-1 PI-5 1RH-30 2 B 10 AO 0 FO-1 0 NOTE 4 C-11 BF 'M-1 PI-5 1RH-31 2 3 MO 0 FS-1 C NOTE 5 H-7 GA TM-1 PI-5 1RH-34 2 10 SA C FS-1 FF NOTE 6 C-7 CK BS-1 BS IRH-39 1 12 MO C FS-1 0 CS-1 FS-2 NOTE 1 1-3 GA TS-1 C CS-1 TS-2 PI-5 LK-3 1RH-40 1 12 MO C FS-1 0 CS-1 FS-2 NOTE 1 1-4 GA TS-1 C CS-1 TS-2 PI-5 LK-3 1RH-45 2 3X3 SA C RL-4 NOTE 2 K-6 RL ISI-203 Rev. 8 Page 219 of 228

081 SHEARON HARRIS NUCLEAR POWER PLANT VALVE TEST TABLE SYSTEM: RESIDUAL HEAT REMOVAL DWG. NO. 2165-S-1324 VALVE CLASS VALVE SIZE ACTU. NORM. TEST STROKED CHECK C.S. C.S.

NUMBER AND (CAT.) (IN. ) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DWG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1RH-63 2 8 MO C FS-1 0 NOTE 3 F-12 GA TM-1 PI-5 1RH-66 2 10 AO 0 FO-1 0 NOTE 4 E-11 BF TM-1 PI-5 1RH-68 2 3 MO 0 FS 1 C NOTE 5 H-8 GA TM-1 PI-5 1RH-70 2 10 SA C FS,-1 FF NOTE 6 E-8 CK BS-1 BS 1RH-120 2 3/4X1 SA C RL-4 NOTE 2 L-4 RL 1RH-121 2 3/4X1 SA C RL-4 NOTE 2 I-4 1RH-20 2 8 AO C FC-1 NOTE 7 E-11 BF TM-1 PI-5 1RH-58 2 8 AO C FC-1 C NOTE 7 G-12 BF TM-1 PI-5 ISI-203 Rev. 8 Page 220 of 228

os1 PUMP AND VALVE INSERVICE TESTING PROGRAM PLAN FOR SHEARON HARRIS NUCLEAR POWER PLANT SECTION 5.6.31 VALVE TEST TABLES AND RELIEF REQUESTS FOR CONTAINMENT INTEGRATED LEAKAGE DETECTION DWG. NO. 2166-S-916 ISI-203 Rev. 8 Page 221 of 228

os1 SYSTEM: CONTAINMENT INTEGRATED LEAKAGE DETECTION NO. NOTE Locked Closed Manual Containment Isolation Valves.

ISI-203 Rev. 8 Page 222 of 228

061 SHEARON HARRIS NUCLEAR PONER PLANT VALVE TEST TABLE SYSTEM: CONTAINMENT INTEGRATED LEAKAGE DETECTION DNG. NO. 2166-S-916 VALVE CLASS VALVE SIZE ACTH. NORM. TEST STROKED CHECK C.S. C.S.

NUMBER (CAT.) (IN.) TYPE POS. REQ. DIRECT. VALVE JUST. OR NO.

DNG. AND TEST OR COOR. TYPE DIRECT. RELIEF TEST REQ.NO. PERF.

1LT-4 2 A 6 MA LC PV NOTE 1 F-3 GA LJ-3 1LT-6 2 A 1 MA LC PV NOTE 1 F-7 GL LJ-3 1LT-10 2 1 MA LC PV NOTE 1 G-7 GL LJ-3 ISI-203 Rev. 8 Page 223 of 228

Test Data Processin E~tachment 6.3 gives a flow chart representation of this process. a e or

.1 Software s be test data will be maintained on a computerized data base which provides :est ease of data entry and on-spot analysis. Software will also allow for icy phical trending and ease of report preparation. .o, a omputer data base will also be maintained for scheduling and documentation and all relief valve tests and check valve disassemblies which are within the pe of this program procedure (Reference 2.0.7). of if

.2 Testin Procedures as of h few exceptions, ASME XI Category A & B component testing (i.e. valve oke time testing, check valve exercising, pump testing, leak testing, etc.) :ntly performed through Operational Surveillance Tests (OSTs) by the Operations

t. Category A leakage tests of containment isolation valves are performed conjunction with the Appendix J program (Reference 2.0.5). Relief valves tested in accordance with References 2.0.8, 2.0.16, 2.0.17, while check ve disassembly is performed and documented within the framework of the :tive omated Maintenance Management System (AMMS), (Reference 2.0.12). mce erences 2.0.9 and 2.0.10 provide test procedure references for all IST ice oonents. All scheduling of OSTs is performed through the Surveillance Test duling System (STSS) in accordance with Reference 2.0.11. Relief valve ins tin , check valve disassembly, and Appendix J testing is scheduled by the iport

.3 Data Entr Trendin and Detection of Deviations OSTs 'alve Operations Unit is responsible for performing all OSTs. If during the ormance of an OST, any test data exceeds its acceptance criteria, (i.e.,

rs a required action range) the affected component is declared inoperable remains so until corrective maintenance has been performed and the :he

=maintenance test successfully performed. After the OST has been completed reviewed by operations, it is routed by Operations to the Technical

~ort, ISI group so that the data can'e reviewed within four (4) working irm to

-. of the OST's completion date. Upon r'eceiving the completed OST, the ISI ited

.sp enters the data into the Inservice Testing (IST) data base and performs

';ysis and trending using the'istorical and most recent data

il

en

=erence 2.0.7). :able lork test, data that falls within the alert range, or that is deemed unusual by 'eby is flagged as a deviation and is compiled along with relevant trend

)hs and/or data reports for follow-up investigation. record.'or After all OST data been entered and the first stage data analysis is complete, ISI personnel

e the OST to the ANII for review. After the ANIl review is complete, the is routed back to Operations and it is eventually vaulted as a gA 203 Rev. 8 Page 224 of 228 i 228

os1 ATTACHMENT 6.1 PUMP/VALVE TEST DEVIATION RECORD COMPONENT: OST/EST NO:

DATE TEST COMPLETED:

DESCRIPTION OF TEST DEVIATION:

ACTION TAKEN:

] CORRECTIVE MAINTENANCE WORK REQUEST NO:

] TEST EVALUATION "

TRACKING DOC. NO:

[ ) INCREASED TEST FREQUENCY

[ ] RETEST COMPLETED SATISFACTORILY DATE:

[ ] NONE REQUIRED. EXPLAIN IN COMMENTS.

COMMENTS ON ACTION TAKEN:

ATTACHMENTS:

APPROVED BY:

SYSTEM ENGINEER+ DATE ISI TEST ENGINEER DATE PROJECT SPECIALIST ISI DATE

• Required if Test Evaluation Performed.

ISI-203 Rev. 8 Page 226 of 228

os1 ATTACHMENT 6.2 PUMP BASELINE RECORD COMPONENT: OST NO:

DATE:

[ ] NEW COMPONENT BASELINE* WORK REQUEST NO:

] BASELINE UPDATE DUE TO MAINTENANCE>> WORK REQUEST NO:

[ ] NEW BASELINE WITH OPERABILITY ANALYSIS* TRACKING DOC. NO:

] ORIGINAL COMPONENT BASELINE

[ ] OTHER PUMP PERFORMANCE TEST ACCEPTANCE VALUES:

BASELINE VALUES SECTION XI RANGES SUCTION PRESSURE m"" ALERT *~*

IDLE NOT REQUIRED OPERATING NOT REQUIRED

• • DIFFERENTIAL PRESSURE HIGH RANGE LOW RANGE

• ~TOTAL FLOW HIGH RANGE LOW RANGE VIBRATION I.H. HIGH VALUE O.H. HIGH VALUE I.V. HIGH VALUE 0 V. HIGH VALUE SPEED (IF REQUIRED)

TEST USED TO ESTABLISH NEW BASELINE:

PROCEDURE NO: DATE:

COMPUTER DATA BASE UPDATED. PRINTOUT ATTACHED.

SIGNATURE APPROVED BY:

SYSTEM ENGINEER DATE ISI TEST ENGINEER DATE PROJECT SPECIALIST ISI DATE To be accompanied by a Pump/Valve Test Deviation Record.

The "fixed" parameter will be given a tolerance (+ or -) that is more conservative than the Section XI ranges.

Mark "N/A" for "fixed" parameter.

b ISI-203 Rev. 8 Page 227 of 228

Osl ATTACHMENT 6.3 TEST DATA PROCESSING FLOW CHART hors Control SISS I

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