ML20149E277

Rev 4 to Inservice Testing Program Plan for Pumps & Valves

ML20149E277
Person / Time
Site:	Rancho Seco
Issue date:	01/29/1988
From:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20149E273	List: ML20149E270 ML20149E277
References
PROC-880129, NUDOCS 8802100481
Download: ML20149E277 (134)

Text

Part I HP36808/D-01998 Part II HP32108/0-0199B=

IlSERVICE TESTING PROGRAM' PLAN Raticho Seco Nuclear Generating Station Docket No.' 50-312- -,

Revision 4 I

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INSERVICE TESTING PROGRAM PLAN FOR PUMPS AND VALVES Record of Revisions s

i Revision Date 3 6-23-87 4 1-29-88 Rev. 4 i

Table of Contents EAat l

Title Page- )

Record of Revisions i Table of Contents 11

1.0 INTRODUCTION

1 2.0 TESTING PROGRAM FOR PUMPS 2 2.1 General 2 2.1.1 Code 2 2.1.2 Pump Program Table 2 2.1.3 Allowable Ranges of Test Quantities 2 2.1.4 Bearing Lubricant 2 2.1.5 Instrumentation 2 2.1.6 Testing Intervals 2 2.1.7 Deferred Testing 2 2.2 Relief Requests for Pump Testing 3 through 20 3.0 TESTING PROGRAM FOR VALVES 21 3.1 General 3.1.1 Code 21 3.1.2 Valve Program Table 21 3.1.3 Deferred Testing 21 3.1.4 Manual Valves 21 3.1.5 Testing Intervals 21 3.1.6 Cold Shutdown Testing 22 3.1.7 Position Indication Testing 22 3.1.8 Fail-safe Testing 22 3.1.9 Stroke Time Evaluation 22 3.1.10 Stop-Check Valve Testing 23 3.1.11 Valve Disassembly 23 ,

3.2 Relief Requests for Valve Testing 24 through 54 APPENDIX A -

SUMMARY

- INSERVICE TESTIh5 PROGRAM - PUMPS APPENDIX B -

SUMMARY

- INSERVICE TESTING PROGRAM - VALVES APPENDIX C - COLD SHUTDOWN TESTING JUSTIFICATION APPENDIX 0 -

SUMMARY

OF PROGRAM CHANGES i

Rev. 4 ii l

1.0 INTRODUCTION

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Revision 4 of the Rancho Seco (Unit 1) ASME Inservice Testing Program Plan will be in effect through the end of the second 120-month (10-year) inspection interval, unless changed for other reasons. The Plan will be updated prior to the start of the third inspection interval in accordance with the requirements of 10 CFR 50.55a(g).

This document outlines the Inservice Testing (IST) Program for Rancho Seco, based on the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition, including Hinter, 1981 Addenda. All references to IHP or IHV in this document correspond to Subsections IHP or IHV, respectively, of ASME Section XI, 1980 Edition, unless otherwise noted.

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

• Title 10, Code of Federal Regulations, Part 50

• NRC Regulatory Guides - Division 1 Standard Review Plan 3.9.6, "Inservice Testing of Pumps and Valves" Final Safety Analysis Report, Rancho Seco Unit 1 Technical Specifications, Rancho Seco Unit 1 The inservice tests required in this Plan will verify the operational readiness of pumps and valves which have a specific function in mitigating the consequences of an accident or bringing the reactor to a safe shutdown condition.

l Rev. 4

LD TESTING PROGRAM FOR PUMPS 2.1 General 2.1.1- Code This IST Program Plan for pumps meets the requirements of Subsection IHP of Section XI of the ASME B&PV Code. Where these requirements <

are determined to be impractical, specific requests for relief are included in Sections 2.2.

'2.1.2 Pump Program Table Appendix A lists the pumps included in the IST Program. Data contained in this table identifies those pumps subject to inservice testing with the respective inservice test parameters, intervals, and any other applicable remarks.

2.1.3 Allowable Ranges of Test Quantities The allowable ranges specified in Table IHP-3100-2 will be used for differential pressure, flow, and vibration measurements except as provided for in relief requests. In some cases, the performance of a pump may be adequate to fulfill its safety function even though there -

may be a measurement that falls outside the allowable ranges as set forth in Table IHP-3100-2. Should this situation occur, an expanded allowable range may be determined, on a case base, in accordance with IHP-3210 and ASME Code Interpretation XI 'l-79-19.

2.1.4 Bearing Lubricant As specified in Table IHP-3100-1, pump bearing lubricant level or pressure will be observed prior to or during testing, when practical.

2.1.5 Instrumentation Instrumentation used in the IST Program will generally conform to the requirements of IWP except where specific relief is requested.

2.1.6 Testing Intervals The test frequency for pumps-in the Program will be as set forth in Appendix A and the associated relief requests. A band of +25 percent of the test interval may be applied to the test schedule, as needed, to provide necessary operational flexibility.

2.1.7 Deferred Testing In conducting inservice testing of pumps if the duplicate (redundant) pump has been declared inoperable er is out of service for any

! reason, a pump shall not be tested during power operation until the

! redundant component has been restored to operability or the l operational actions required by the inoperable condition have been completed.

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[- 2.2 Relief Requests for Pump Testing l The following pages in this section include relief requests PR-1:

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~~ through PR-15 for IST pump testing.

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RELIEF REQUEST NO. PR-1  !

PUMPS:

Applicable to all pumps in the Program.

RE0VIREMENT:

Reference values shall be at points of operation readily duplicated during subsequent inservice testing. (IHP-3110)

BASIS FOR RELIEF:

Operating experience has shown that it is not always practical to duplicate points of operation with the available flow control systems and instrumentation. Efforts to exactly duplicate the reference values may not be possible or would require excessive valve manipulation which could result in damage to valve components or excessive personnel exposure.

ALTERNATE-TESTING:

During pump reference tests, a reference pump curve may be established or the manufacturer's pump curve confirmed. In lieu of duplicating a specific reference flowrate during subsequent inservice tests, a flowrate (Qa) will be obtained and recorded along with the corresponding differential pressure (dPa). The differential pressure value (dPa) will then be compared to the theoretical differential pressure corresponding to the measured flowrate (Qa) on the pump curve. The acceptance criteria of Table IHP-3100-2 will be applied as appropriate.

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RELIEF REQUEST NO. PR-2 PUMPS:

Applicable to all pumps in the Program.

REOUIREMENT:

At least one displacement vibration amplitude (peak-to-peak composite) shall be read during inservice testing. The direction of displacement shall be measured in a plane approximately perpendicular to the rotating shaft, and in the horizontal or vertical direction that has the largest deflection for the particular pump installation. (IHP-4510)

BASIS FOR RELIEF:

Heasuring vibration in velocity units rather than displacement is an industry accepted method considered to be more sensitive to small changes that are indicative of developing mechanical problems. Velocity measurements detect not only high-amplitude vibration, characteristic of major mechanical problems, but low-amplitude vibration caused by misalignment, imbalance, or bearing wear.

It is impractical to search for the direction with the largest deflection and procedurally return to that location on successive tests. Also, the direction of maximum deflection may change with pump age and materill condition, thus, this is not necessarily a conservative nor proper practice.

ALTERNATE TESTING:

At the option of the plant staff, pump vibration measurements may be taken and trended in either displacement or velocity units. Acceptance criteria for velocity measurements will conform to Table 2.1.

Vibration measurements will be taken in two pre-established mutually perpendicular directions in a plane perpendicular to the rotating shaft.

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RELIEF REQUEST NO. PR-2 (Continued)

Table 2.1: Allowable Ranges of. Vibration Levels (ips)*

Ref. Vib. Acceo. Ranae Alert Action Ren

<0.15 0 - 0.3 0.301 - 0.45 > 0.45

-+~ 0.15 - 0.3 0 - 0.45 0.451 - 0.7 > 0.7 0.3 - 0.6 0 - 0.7 None > 0.7 0.6 - 0.7 0 - 0.7 None > 0. '/ t

• Limits based on ASME Technical Paper 78-HA/NE-5. All units in inches per second (ips) l l

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RELIEF REQUEST NO. PR-3

PUMPS:

Applicable to all pumps in the Program.

REOUIREMENT:

The full-scale range of each instrument shall be three times the reference value or less (IHP-4120) .-

BASIS FOR RELIEF:

The commercially available state-of-the-art instruments used for measuring pump vibration do not provide range selections that guarantee adherence to the range limitations per Subirticle IHP-4120. Ranges are typically expanded beyond the multiple of three as required by the Code and, in the case of the digital instruments used cur ently at Rancho Seco, the instrument is self scaling over a broad range of measurements.

The accuracy of instruments used to measure vibration are generally based on the actual measured value and is unrelated to the instrument range. The instrument accuracies are typically approximately i 5 percent of the reading. This is considerably better than that specified by the Code (i 5 percent FS) that can be as much as i 15 percent of the reading.

ALTERNATE TESTING:

Commercially available instrumentation will be used to measure pump vibration with an overall reading accuracy equal to or better than that required by

- IHP-4100 (15 percent).

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RELIEF REQUEST NO. PR-4 PUMPS:

Applicable to all pumps in the l'rogram.

REOUIREMENT:

The allowable ranges of inservice test quantities in relation to the reference values are tabulated in Table IHP-3100-2. This table limits the acceptable performance of each pamp dependent variable (flowrate or differentia 1' pressure) to a maximum of 102 percent of the respective reference value for the alert condition and 103 percent for the action-required range. -If the test parameter should exceed these limits, the subject pump shall be tested at more frequent intervals for the alert range or declared inoperative and removed from service if the test parameter falls in the action required range. (IHP-3200)

BASIS FOR RELIEF:

The requirement to declare a pump inoperative when a test parameter (flowrate or differential pressure) exceeds the reference value by 3 percent is not technically justified, sound engineering judgement, nor acceptable plant operating practice for the following reasons:

Indiscriminately declaring safety system pumps inoperative could result in excessive and unneeded testing of other plant safeguard systems and components. Such testing could ultimately detract from the overall reliability of plant safety systems. In addition, unwarranted testing unnecessarily adds to the burden of the operating staff and dilutes efforts focused on the performance of their primary duties. Such testing also results in unnecessary radiation exposure.

The case where a test parameter exceeds the reference.value does not indicate pump degradation. It may merely signify that the reference value is probably on the lower side of the statistical scatter of the test data and the specific test in question is on the upper side. Note that the reference values are subject to the same elements of statistical error associated with any other individual test. .

The 3-percent limitation is overly restrictive when compared to the accuracy of the instrumentation used to gather the test data as required by Paragraph INP-4110 (z 2 percent).

Power plant operating systems are not configured in a way that allows for the accuracy and precision of the testing needed to consistently and reliably provide the repeatability needed to meet this requirement.

Rev. 4

RELIEF REQUEST NO. PR-4 (Continued)

This requirement provides no additional measure of reliability to the equipment.

ALTERNATE TESTING:

The acceptance criteria of Table IHP-3100-2 will be utilized,~unless otherwise noted, with the following exceptions:

a) The Required-Action Range (HIGH', will be greater than 110 percent of the reference value for test quantities of flowrate and differential pressure; and (b) The Alert Range (HIGH) will br between 105 to 110 percent of the reference value for test quantities of flowrate and differential pressure.

Rev. 4

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RELIEF REQUEST NO. PR-5 PUMPS:

Applicable to all pumps in the Program.

REOUIREMENT:

The temperature of all centrifugal pump bearings outside the main flowpath shall be measured at points selected to be responsive to changes in the temperature of the bearings. (IHP-4310)

BASIS FOR RELIEF:

Many of the bearings of the centrifugal pumps included in the Rancho Seco IST Program are water cooled -- cooling water supplied from the flowstream or auxiliary closed cooling water systems. Thus, bearing temperature measurements are highly dependent on the temperature of the cooling medium and not necessarily indicative of bearing condition.

The data associated with bearing temperatures taken at one-year intervals provides little statistical basis for determining the incremental degradation of a bearing or any meaningful trending information or correlation.

Vibration measurements are a significantly more reliable and meaningful indication of an imminent or existing bearing failure. It is highly unlikely that such a condition would go unnoticed during routine pump operation or surveillance testing. Other indications of bearing problems include audible noise, reduced pump performance, seal failure, unusual vibration, increased motor current, etc.

The gain from taking bearing measurements, which in most cases must be done locally using portable instruments, cannot offset the cost in terms of dilution of resources, distraction of operators from other primary duties, excessive operating periods for normally idle pumps, and personnel radiation exposure.

ALTERNATE TESTING:

None proposed.

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RELIEF REQUEST NO. PR-6 PUMPS:

Applicable to all pumps in the Program.

REOUIREMENT:

Measure pump inir? pressure before starting the pump and during the test.

(Table IHP-3100-i)

BASIS FOR RELIEF:

If the pumps being tested are in operation as a result of plant or system needs, it is unreasonable and impractical to reconfigure system lineups simply to provide for measurement of the static inlet pressure.

Inlet pressure prior to pump startup is not a significant parameter needed for evaluating pump performance or material condition.

ALTERNATE TESTING:

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

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RELIEF REQUEST NO. PR-7 PUMPS:

P-r36 Makeup Pump P-MS A & B High Pressure Injection Pumps REOUIREMENT:

An inservice tesi. shall be run on each pump nominally every 3 months during normal plant operation. (IHP-3400)

Pump testin'g shall be based on establishing a set of reference values, then comparing subsequent test results to these reference values. Inherent in this is the requirement to determins which of the pump parameters (flowrate I or differential pressure)is to be the independent variable, then, in '

subsequent tests, this parameter is set to the reference value by adjusting system resistance. The value obtained for the dependent variable is compared to its respective reference value with Table IHP-3100-2 establishing acceptance criteria. During the test, the test quantities shown in Table IHP-3100-1 shall be measured and recorded. (IHP-3100 & 3110)

BASIS FOR REid1E:

The only practical method of full ficw testing these pumps is to inject water into the Reactor Coolant System requiring initiation of HP Injection and pumping water from the BHST. This would cause transients in pressurizer level and reactor power and is considered to be imprudent during power operation. In addition, injection of cold water into Reactor Coolant System during operation would cause thermal shocking of the injection cozzles.

During cold shutdown, the HP Injection Isolation motor-operated valves are deenergized closed and the pumps are electrically disabled to prevent low temperature over-pressurization. Consequently, the only practical method of testing is to circulate water through the minimum flow line for each pump.

Because of this, the maximum flowrate achievable is approximately 20-percent of the nominal rated pump flow. Note that there is no flow measuring instrumentation installed in the minimum flow circuit.

During partial-flow testing, the region of the pump curve in which the testing will be performed is near shutoff head and flowrate readings are not necessarily meaningful from the viewpoint of trending.

Since the HP injection pumps stand idle except for periods of testing, significant inservice degradation is unlikely.

ALTERNATE TESTING:

These pumps will be tested quarterly with the fixed resistance of the minimum flow line. During these tests, all appropriate pump operational parameters will be measured and evaluated with respect to Table IHP-3100-2 and associated relief requests with the exception of flowrate.

During each refueling outage, each pump will be tested under nominal full-flow conditions and all required parameters will be measured, including flowrate.

Rev. 4

, RELIEF REQUEST NO. PR-8 PUMPS:

Nuclear Service Raw Hater; Pump Nos. P-472A and P-4728

- TDI-Diesel Fuel 011; Pump Nos. P-108 A thru D

- Bruce GM-Diesel Fuel 011; Pump Nos. P-888 A thru D REOUIREMENT:

Measure pump inlet pressure before starting the pump and during the test.

(Table IHP-3100-1)

BASIS FOR RELIEF:

These pumps are submerged and, as such, have inlet pressures corresponding to the water level in the spray pond basin or oil level in the fuel oil tanks.

- There is no practical mechanism for measurement of suction (inlet pressure).

Also, changes of le *e1 during testing is insignificant.

ALTERNATE TESTING:

Inlet pressure will be calculated from the height of liquid above the

- pump suction prior to or during each test, but only once per test.

i Rev. 4 RELIEF REQUEST NO. PR-9 DELETED Rev. 4 RELIEF REQUEST NO. PR-10 P_UBES:

Nuclear Service Raw Hater, Pump Nos. P-472 A & B Nuclear Service Cooling Hater, Pump Nos. P-482 A & B REOUIREMENT:

The test quantities shown in Table IHP-3100-1 (including flowrate) shall be measured or observed and recorded. (IHP-3100)

BASIS FOR RELLEE:

There is no installed instrumentation for measuring the flowrate in any of the above piping systems.

ALTERNATE TESTING:

Appropriate flowrate measuring instrumentation will be installed in these

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systems prior to or during the next Refueling Outage No. 7 (Loading Core

- Cycle 8). In the interim the following will apply.

For pumps P-472 A & B, flowrate will be derived by measuring the spray header pressure and determining flowrate from curves of spray header pressure vs. flowrate empirically developed during the Rancho Seco Startup Testing Program.

For pumps P-482 A & B, it is assumed that the system resistance is fixed and only pump differential pressure will be measured and evaluated.

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RELIEF REQUEST PR-11 PUMPS:

- P-236 - Makeup P-238 A&B HP Injection P-261 A&B Decay Heat Removal P-291 A&B Reactor Building Spray

- P-705 A&B Boric Acid REOUIREMENT:

The full-scale range of each instrument shall be three times the reference value or less (IHP-4120).

BASIS FOR RELIEF:

The installed suction pressure gauge of a pump is generally sized to accommodate the maximum pressure it would experience under normal or emergency conditions. In many cases, this results in an instrument range that exceeds the Code requirement since, under test conditions, high suction pressures are typically not experienced. Strict Code compliance would require the installation of temporary gauges that would not be suitable for routine or emergency pump operation.

Suction pressure measurements serve two primary functions. First they provide assurance that the pump has an adequate suction head for proper operation. Secondly, the suction pressure is used to determine the pump differential pressure.

For the determination of suction head, the accuracy and range requirement is overly restrictive. Since, in most cases, plant pumps are provided with a considerable margin of suction head, accuracy on the order of 0.5 to 0.75 psig should be adequate.

When used in determining pump differential pressure, the accuracy of the suction pressure measurement has little or no effect on the calculation since, generally, the pump discharge pressure is higher than the suction pressure by 2 or 3 orders of magnitude.

ALTERNATE TESTING:

n When measuring the suction pressure of a pump, in lieu of meeting the

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instrument range requirement of IHP-4120, instruments will be installed such that the accuracy meets the requirements set forth below:

• Accuracy will be at least : .5 psi

. The accuracy of the differential pressure calculation will be limited to 2 percent of the differential pressure calculated value.

• Accuracy of the suction pressure instrument will be better than

. z.5 percent of the calculated differential pressure.

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W RELIEF REQUEST PR-12 DELETED l

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RELIEF REQUEST PR-13 l PUMPS:- l l

TDI-Diesel Fuel 011; Pumps Nos. P-108A thru D l Bruce GM-Diesel Fuel 011; Pumps Nos. P-888A thru D REOUIREMENT:

When measurement of bearing temperature is not required, each pump shall be run at least 5 minutes under conditions as stable as the system permits. At the end of this time at least one measurement or observation of each of the quantities specified : hall be made and recorded. (IHP-3500(a))

BASIS FOR RELIEF:

1 The only mechanism of measuring flowrate for these pumps is by measuring the increase of oil level in the day tanks and relating it to the respective pump operating time. There is insufficient available volume in the day tanks to allow the pumps to run for five minutes prior to taking data without significantly affecting test accuracy.

ALTERNATE 1ESTING:

During testing of these pumps, data will be taken as soon as flow and pressure conditions have stabilized following pump start.

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RELIEF REQUEST PR-14  !

i PUMPS:

TDI-Diesel Fuel 011; Pump Nos. P-108A thru D Bruce GM-Oiesel Fuel 011; Pump Nos. P-888 A thru D REQUIREMEll.I: ,

At least one displacement vibration amplitude (peak-to-peak composite) shall be read during each inservice test. (IHP-4510)

BASIS FOR REL111:

Each of thete pumps is submerged within its respective fuel oil tank thus, the bearing housings are inaccessible for vibration measurements.

ALTERNATE TEEIIBG:

Vibration measurements will not be taken.

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RELIEF REQUEST PR-15 PUMPS:

Bruce GM-Diesel Fuel 011; Pump Nos. P-888A thru D RE0UIREMENT:

If deviations fall within the Alert Range of Table IHP-3100-2, the frequency of testing specified in IHP-3400 shall be doubled until the cause of the deviation is determined and the condition corrected (IHP-3230(a)).

BASIS FOR RELIEF:

Since their in no practical mechanism for draining tne day tanks, these pumps are tested by draining down the day tank with diesel generator operation and subsequently measuring the tank fill rate to determine pump flow rate. Thus, testing these pumps requires diesel generator operation. Should a pump enter an alert range, the increased test frequency per IHP-3230(a) would require additional starts and operation of the related diesel generator. Such additional testing is considered to be detrimental to diesel generator reliability.

Since the pumps are only operated during testing, their is no credible mechanism of pump deterioration between tests. Thus increasing the test frequency is of little value.

ALTERNATE TESTING:

I The increased test reluirements of paragraph IHP-3230(a) will not be applied to these pumps.

Rev. 4

I 3.0 TESTING PROGRAM FOR VALVES

, 3.1 General 3.1.1 Code This IST Program Plah for valves meets the requirements of Subsection IHV of Section XI of the ASME B&PV Code. Where these requirements were determined to be impractical, specific requests for relief are incluc9d in Section 3.2.

3.1.2 Valve Program Table Appendix B lists the valves included in the IST Program. Data contained in this table id9ntifies those valves subject to inservice testing with the respective descriptive inforraation, test requirements, test intervals, and applicable remarks and references to relief requests.

3.1.3 Deferred Testing When one or more valves in a redundant system are determined to be inoperable, non-redundant valves in the other train may not be tested, as required by procedures and this Program, but may be exercised after the inoperable valve is returned to service.

3.1.4 Manual Valves Several manual valves are included in this Program in order to make it consistent with the Rancho Seco Technical Specifications as they relate to the issue of Appendix J leakrate testing. Although these valves are categorized as "Category A" valves, they are considered to be passive per Table INV-3700-1 and, as such, will not be exercised as required by Paragraph IHV-3410.

3.1.5 Testing Intervals The test frequency for valves in the Program will be a set forth in Appendix B and associated relief requests. An allowable band of +25 i percent of the test interval may be applied to the testing schedule, as needed, to provide necessary operational flexibility.

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a x 3 .1. '6 Cold Shutdown Testing For those valves designated to be exercised or tested during cold shutdown, exercising / testing will commence as soon as practical after the plant reaches a stable cold shutdown condition as defined by the

- Rancho Seco Technical Specifications but no later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after reaching Cold Shutdown. If an outage is sufficiently long enough to allow testing of all valves required to be tested during Cold Shutdown, then the 48-hour requirement need not apply if all valves are tested during the outage. Furthermore, valve testing will not necessarily be performed more often than once every three (3) months. Completion of all valve testing during a cold shutdown outage will not be required if plant conditions preclude testing of specific valves or if the cold shutdown period is insufficient to complete all testing. Testing not completed before startup maj be completed during subsequent cold shutdown outages in a sequence such that cheduled testing does not omit nor favor certain valves or

- groups of valves. Note: Additional restrictions may be applied as stated in specific relief requests.

Refer to Appendix C of this Program for cold shutdown justifications.

3.1.7 Position Indication Testing For those valves with remote position indicators, tests will be performed to ensure the indication correctly reflects actual valve position and operation in accordance with the requirements of IHV-3300. -

3.1.8 Fail-safe Testing

! The normal methods for exercising power-operated valves also tests the failsafe functions of these valves if they exist. Thus, no l aaditional testing is required and the respective cold shutdown t

justifications and relief requests apply to the requirements of paragraph IHV-3415, when applicable, l

- 3.1.9 Stroke Time Evaluation Where stroke time measurement of power-operated valves is required, maximum allowable stroke times will be established based on test history, manufacturer's specifications, FSAR/USAR analyses, technical specification requirements and engineering judgment. Generally, the most limiting value will dictate the limit. Measured stroke times will be evaluated and corrective action taken in accordance with IHV-3417.

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- 3.1.10 Stop/ Check Valve Testing Where testing of stop/ check valves is required, exercising the stem to the fully closed direction will be employed as an acceptable method of verifying valve closure.

3.1.11 Valve Disassembly As per INV-3522, check valves may be disassembled, manually exercised and inspected in lieu of flow (and flow reversal) testing as described in the Code.

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4' 3.2 Relief Requests for Valve Testing The following pages in this.section include relief requests VR-1

- through VR-23, for IST valve testing, 0

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E RELIEF REQUEST NO. VR-1 SYSTEMS:

i All systems YALYES:

- Solenold-operated valves

- Turbine Stop/ Throttle Valves (TV-1, TV-2, TV-3, TV-4)

CATEGORIES:

A and B FUNCTIONS:

Various REOUIREMENT:

If, for power-operated valves, an increase in stroke time of 50% or more for vaives with full-stroke times less than or equal to 10 seconds is observed, the test frequency shall be increased to once each month until corrective action is taken, at which time the original test frequency shall be resumed.

(IHV-3417)

BASIS FOR RELIEF:

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The stroke times of most solenoid and the Main Turbine Stop/ Throttle Valves are rapid and stroke time measurements are subject to considerable variation due to test conditions as well as operator reaction time.

&LIERNATE TESTING:

When exercising these valves with stroke times measuring less than 2 seconds, stroke time measurements will be recorded but will only be verified to be

less than two seconds. The requirements of INV-3417 will not apply.

M Rev. 4 RELIEF REQUEST NO. VR-2 SYSTEMS:

Various VALVES:

All power-operated valves to be exercised only during cold shutdown or refueling outages.

CATEGORIES:

A and B FUNCTIONS:

Various REOUIREMENT:

If, for power-operated valves, an increase in stroke time of 25% or more from the previous test for valves with 'ull-stroke times greater than 10 seconds or 50 percent or more valves with full-stroke times less than or equal to 10 seconds is observed, test frequency shall be increased to once each month until corrective action is taken, at which time the original test frequency shall be resumed. (INV-3417)

BASIS FOR RELIEF:

Strict adherence to this requirement, as stated, could require a plant i shutdown or operation under unusual conditions each month for testing until l it is determined that the valve is coerating satisfactory and has not undergone significant degradation or some corrective maintenance action is performed to correct the condition.

Since valve stroke time would be less than the maximum allowable, it would continue to be considered operable and thus, corrective maintenance, along with the accompanying time and personnel exposure costs, may not be warranted I or justified.

AiTIRNATE TESTING:

(for valves that are only tested during Cold-Shutdown). If valve testing during Cold-Shutdown should result in required increased test frequency per l INV-3417, the valve condition shall be evaluated an the valve demonstrated to be operable prior to the plant returning to power operation. This action is in lieu of increased test frequency required per IWV-3417.

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Rev. 4

!' RELIEF REQUEST NO. VR-4 SYSTEMS:

Various VALVES:

• PENETRATION # $15 VALVE I.D.

3 CCH CCH-036 SFV-46014 4 CCH SFV-46203 SFV-46204 16,56,58,68 SIM SIM-019.020.021,022 SFV-23616 19 NGS NGS-017 NGS-018 20 SIM SIM-040 SFV-23809 21 SIM SIM-036 SFV-23811 SFV-23604 22 SIM HV-23801 HV-23802 SFV-23810 23 SIM SIM-047 SFV-23812 24 RSS SFV-72501 SFV-72502 25 CBS SFV-29107 C85-009 26 CBS SFV-29108 CBS-010 27 DHS DHS-016 DHS-039 DHS-497 SFV-26006 HV-26011 28 DHS DHS-015 OHS-498 DHS-038 SFV-26005 Rev. 4 i

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RELIEF REQUEST NO. VR-4 I

i VALVES (Continued): ;j PENETRATION # SYS VALVE I.D. l 3 CC4 CCH-036  !

SFV-46014 4- CCW SFV-46203 SFV-46204  !

16,56,58,68 SIM SIM-019,020,021,022 !

SFV-23616 19 NGS NGS-017 NGS-018 l 20 SIM SIM-040 SFV-23809 21 SIM 'SIM-036 SFV-23811 SFV-23604 22 SIM HV-23801 HV-23802 SFV-23810 23 SIM SIM-047 S FV-23812 24 RSS SFV-72501 SFV-72502 25 CBS SFV-29107 CBS-009 26 CBS SFV-29108 CBS-010 27 DHS DHS-016 DHS-039 DHS-497 SFV-26006 HV-26011 28 DHS DHS-015 DHS-498 DHS-038 SFV-26005 l

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Rev. 4

'J m RELIEF REQUEST NO. VR-4 (Continued)

CATEGORIES:

A and A/C FUNCTIONS:

Valves provide containment isolation when in the closed position.

RE0VIREMENIl Category A valves shall be seat leak tested and a maximum permissible leakage rate shall be specified. Individual va.1ve leakage rates shall be trended and analyzed as required by paragraphs INV 3426 and IHV-3427.

BASIS FOR RELIEF:

Due to the configuration of the system piping and components, in many cases individual leakage rate tests are impractical. In these cases it is customary to perform tests with the test volume between valves in series or behind several valves in parallel paths.

ALTERN&TE TESTING:

l In those cases where individual valve testing is impractical, valves will be leak tested simultaneously in multiple valve arrar>gements and a maximum permissible leakage rate will be applied to each combination of valves. Test results from tests of multiple valve ccabinations will be evaluated in accordance with IHV-3426 and INV-3427.

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RELIEF REQUEST NO. VR-5 i

SYSTEM:

Reactor Coolant VALVES:

RIVVWX Thru RIVVZY (8 valves)

CATEGORY:

C FUNCTION:

These valves open to equalize pressure across reactor vessel internals.

REOUIREMENT:

Check valves shall be exercised at least once every 3 months, except as provided by INV-3522. (INV-3521)

BASIS FOR RELIEF:

These valves are located on the reactor core support assembly anc' exercising is impossible without vessel disassembly-normally performed only during refueling outages.

ALTERNATE TESTING:

Each valve will be manually exercised during each refueling outags.

Rev. 4

RELIEF REQUEST NO. VR-6 SYSTEMS:

Nakeup and Purification (M-521)

YALVES1 ENS-019 BHS-044 SIM-043 SIM-052 I:ATEGORY:

C JUNCTION:

These valves open to supply water to the Hakeup and High Pressure Injection Jumps from the Borated Hater Storage and Concentrated Boric Acid Tanks.

REOUIREMENT:

Check valves shall be exercised at least every 3 months, except as provided by IWV-3522. (IWV-3521)

BASIS FOR RELIEF:

The only method of opening these valves during plant operation is to inject water from the Makeup or HP Injection Pumps into the Reactor Coolant System via the Pressurizer Level Control Valve or the RCP seals or via the minimum flow recirculation line to the Makeup Tank. Due to the highly concentrated boric acid solution in these tanks, injecting this water would cause undesirable changes in RCS boric acid concentration resulting in reactor power transients or difficulty in maintaining constant boric acid concentration due to over-concentratien of the Makeup Tank.

During cold shutdown, recirculating solution from the Concentrated Boric Acid or Borated Water Storage Tanks would result in over-concentration of the Makeup Tank and significantly increase the time and difficulty of the plant startup.

i ALTERNATE TESTING:

Each of the four (4) vel"es will be full-stroke exercised during each refueling outage, i

Rev. 4 i

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RELIEF REQUEST NO. VR-7

$1SIEMS:

Makeup and Purification (M-521)

VALVES:

SIM-002 SIM-045 SIM-058 CATEGORY:

C FUNCTION:

These valves are check valves at the discharge of the Mikeup and HP Injection Pumps. They open upon pump start to provide a flow path for injection into the Reactor Coolant system and close to prevent overpressurization of the suction piping leading to the idle pump (s) and recirculation back to the Borated Hater Storage and Concentrated Boric Acid tanks.

REOUIREMENT:

Check valves shall be exercised at least every 3 months, except as provided by INV-3522. (INV-3521)

BASIS FOR RELIEF:

The only method of full-stroke testing these valves is to inject water from l the respective pump into the Reactor Coolant System. For valves SIM-045 and SIM-058, this would require initiation of HP Injection and pumping water from

~~

the BHST. This would cause transients in pressurizer level and reactor power and is considered imprudent during power operation. During cold shutdown periods, injection it precluded due to low-temperature pressurizatiod concerns and associated procedural restrictions that require disability of

~ pumps and valves in the injection paths.

Normal operation of the Makeup Pump and quarterly testing of the HP Injection Pumps demonstrate operability via a partial-stroke exercise (less thin the 500 gpm required for full-stroking) of each valve. During this time, the flowrate is restricted by letdown and RCP Seal Hater System demand.

Rev. 4

o RELIEF RsQJEST NO. VR-7 (Continued)

ALTERNATE TESTING:

Each valve'will be partial-stroke exercised during normal Hakeup Pump operatton or quarterly pump testinge During each refuelir,g outage all three valves will be full-stroke exercised.

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Rev. 4

RELIEF REQUEST NO. VR-8 SYSTEMS:

Makeup and Purification (M-521)

VALVES:

HV-23801 SIM-036 SIM-037 SIM-040 SIM-041 SIM-047 SIM-049 SIM-050 CATEGORIES:

C and A/C FUNCTIONS:

I These valves open to provide a flow path from the Makeup and HP Injection Pumps into the Reactor Coolant System. Valves HV-23801, SIM-036, SIM-040, and SIM-047 close to provide containment isolation.

REOUIREMENT:

Check valves shall be exercised at least once every 3 months, except as provided by INV-3522. (INV-3521)

BASIS FOR RELIEF:

The only practical rnethod of exercising these valves is to inject water into the Reactor Coolant System via the Makeup and/or HP Injection Pumps. For all valves, except SIM-036 and SIM-037, this would require initiation of HP Injection and pumping water from either the BMST or the CBAT. This would

> cause transients in pressurizer level and reactor power and is considered to l

be imprudent during power operation. In addition, injection of cold water

, into the Reactor Coolant System during operation would cause thermal shocking l oftheinjectionnozzles. Valves SIM-036 and SIM-037 are partial - stroke

! exercised to the open direction during normal operation of the Makeup System; I however system flowrate is generally less than the 500 gpm required for l stroking the valves to their fully opened position based on design flow conditions, l

l Rev. 4 l - 3S -

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l RELIEF REQUEST NO. VR-8 (Continued)

During cold shutdown, the HP Injection Isolation motor-operated valves and pumps are closed and electrically disabled to prevent low-temperature over pressurization. Cold shutdown testing is thereby precluded.

ALTERNATE TESTING:

Valves SIM-036 and SIM-037 will be partial-stroked to the open position in conjunction with the normal operation of the Makeup System and verified to close at cold shutdown by handwheel operation.

Each of these valves will be full-stroke exercised during each refueling outage.

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dev. 4

RELIEF REQUEST NO. VR-9 SYSTEM:

Decay Heat Removal (M-522)

VALVES: ,

CFS-001 CFS-002 DHS-015 DHS-016 RCS-001 RCS-002 CATEGORY:

A/C FUNCTION:

These valves open to provide a flowpath for water into the Reactor Coolant System and close to prevent overpressurization of the low pressure portions of the Decay Heat Removal System.

REOUIREMENT:

The leakage rate for valves 6 inches NPS or greater shall be evaluated per Subsection INV-3427(b).

BASIS FOR RELIEF:

Leak testing of these valves is for the purpose of confirming their pressure retaining integrity with respect to their capability of preventing overpressurization and catastrophic failure of the low pressure decay heat removal piping and components. In this regard, special leakage acceptance criteria is established and included into the Rancho Seco Technical Specifications (Reference Table 3.3-1) that addresses the question of valve integrity in a more appropriate manner for these valves.

Rev. 4 l

RELIEF REQUEST NO. VR-9 (Continued)

ALTERNATE TESTING The leakage rate acceptance criteria for these valves will be as set forth in the Rancho Seco Technical Specifications Table 3.3-1, namely:

1. Leakage rates less than or equal to 1.0 gpm are considered acceptable.

2. Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are considered acceptable if the latest measured rate has not exceeded the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.

3. Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm ,

are considered unacceptable if the latest measured rate exceeded the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maxirium permissible rate of 5.0 gpm by 50% or greater.

4. Leakage rates greater than 5.0 gpm are considered unacceptable.

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RELIEF REQUEST NO. VR-10 SYSTEM:

Decay Heat Removal (M-522)

VALVE:

BHS-045 CATEGORY:

C FUNCTIOM:

This valve provides a flowpath from the boric acid pumps and filters to the suction of the decay heat removal pumps.

REQUIREMENT:

Check valves shall be exercised at least every 3 months, except as provided by IRV-3522. (INV-3521)

BASIS FOR RELIEF:

In order to exercise this valve flow must be inductd from the Boric Acid Pumps through the Decay Heat Removal System thence to the BHST. This would necessarily introduce a large quantity of highly concentrated boric acid solution (7750 ppm) into the Decay Heat System drop leg. This concentrated boric acid will remain in the drop leg until the Decay Heat Removal system is placed in service. After successive tests in this manner, a pocket of highly concentrated boric acid could accumulate with the potential of crystallization since the decay heat removal piping is not heated.  ;

Subsequently this could adversely affect the operability of the decay heat removal system.

During cold shutdown, injecting the concentrated boric acid solution would likewise cause an unwanted increase of the boric acid concentration in the

- Reactor Coolant System that would result in additional radwaste loads and would cause delays due to excessive deborating prior to plant

- startup.

ALTERNATE TESTING:

This valve will be full-stroke exercised during each refueling outage. l t

Rev. 4 RELIEF REQUEST NO. VR-ll SYSTEM:

Decay Heat Removal (M-522)

VALVES:

CFS-001 CFS-002 CATEGORY:

A/C FUNCTION:

These valves open to provide a flowpath for water from the Core Flood Tanks to the Reactor Vessel and close to provide pressure isolation between the Reactor Vessel and the Core Flood Tanks.

REQUIREME%T_:

- Check valves shall be exercised at least every 3 months, except as provided by INV-3522. (INV-3521)

BASIS FOR RELIEF:

Exercising these valves during plant operation is not possible since the maximum Core Flood Tank pressure is considerably less than that of the Reactor Coolant System.

Full-stroke testing during cold shutdown or refueling would require a rapid depressurization of the Reactor Coolant System or, conversely, rapid pressurization of the Core Flood Tanks; neither is practical.

These valves are seldom operated, therefore, valve degradation as a result of wear or abuse is not likely.

A partial-stroke test followed by a leakrate test adequately ensures that a valve of this type is intact and functioning properly. Any significant deterioration of the valve internals or operating mechanism will likely be discovered during such a leak test.

Rev. 4 1

RELIEF REQUEST NO. VR-11 (Continued)

ALTERNATE TESTING:

~ During cold shutdown, if not tested in the previous 3 months, each valve will be partial-stroke tested prior to returning to power operation. Additionally during cold shutdown, each valve will be leak tested if not tested in the previous 9 months. Prior to plant startup at the next Refueling Outage No. >

7, (Loading Core Cycle 8) one of these valves will be disassembled, manually exercised, and inspected internally. If, as a result of inspection, it is determined that its full-stroke capability is in question, the other valve will be disassembled, manually exercised and inspected.

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Rev. 4 s

RELIEF REQUEST NO. VR-12 i

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DELETED i

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Rev. 4 -

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RELIEF REQUEST NO. VR-13 SYSTEM:

Decay Heat Removal (M-522)

YALYES1 CBS-035 CBS-036 CAIEGOAY1 C

FUNCTION:  !

These valves open to provide a flowpath for sodium hydroxide from the Reactor Building Spray Additive Tanks to the Decay Heat System.

REOUIREMENT:

Check valves shall be exercised at least every 3 months, except as provided  ;

by INV-3522. (INV-3521)

BASIS FQR RELIEF:  ;

These are spring-loaded eneck valves and thus, the only method of testing requires injection of sodium hydroxide into the Decay Heat Removal System. -

- This is highly undesirable under any plant condition. Contamination of the Decay Heat Renoval System with NADH solution could ultimately result in NADH in the Reactor Coolant System with the possibility of causing stress '

cracking, increased radiation levels due to sodium activation and chloride contamination as a result of residual chlorides 17 the .WA0H solution.

ALTERNATE TESTING:

On an alternating schedule, one of these valves will be disassembled and inspected to ensure operability during each refueling outage. If this inspection results in questionable operability of the inspected valve, then the remaining valve will be similarly disassembled and inspected.

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Rev. 4 F

RELIEF REQUEST NO. VR-14 ,

SYSTEM:

Reactor Building Spray (M-524) i D],ES:  !

CBS-009 ,

CBS-010 CATEGORY:

A/C FUNCTION:

These valves open to provide a flowpath from the Reactor Building Spray System to the spray headers inside the Reactor Building and close as required for containment isolation.

REOUIREMENT:

Check valves shall be exercised at least once every three months, except as provided by INV-3522. (IHV-3521)

BASIS FOR RELIEF:

The only method of exercising these valves is to operate the Reactor Building spray pumps and inject water through the valves to the spray headers. Since there is no practical means of isolating the spray headers and providing a recirculation, this would fesult in spraying down the Reactor Building, which is highly undesirable.

ALTERNATE TESTING:

• During each refueling outage, on an alternating schedule, one of these valves will be disassembled and manually exercised to ensure operability. If this inspection results in questionable operability of the inspected valve, then the remaining valve will be disassembled, exercised and inspected in a similar manner, i

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r-RELIEF REQUEST NO. VF-15 SYSTEM:

Reactor Building Spray (M-524)

VALVES:

CBS-021 CBS-022 CBS-027 CBS-028 SFV-29015 SFV-29016 CATEGORY:

C t

FUNCTION:

These valves are check or stop-check valves that provide flowpaths from the Reactor Building spray additive tanks to the Reactor Building spray pump suction in order to effect sodium hydroxide distribution in the Reactor Building.

RE0VIREMENT:

Check valves shall be 1xercised at least once every three months, except as provided by IWV-3522. (INV-3521)

BASIS FOR RELIEF:

Full flow testing of these valves would require injection of sodium hydroxide into the Reactor Building spray system and the borated water storage tanks.

This is undesirable since this could ultimately result in kA0H in the Reactor Coolant System with the potential for causing stress cracking, increased i radiation levels due to sodium activation and chloride contamination due to

- residual chlorides in the NA0H solution, i

r Partial flow testing of these valves during plant operation requires isolation and disabling of one train of the Reactor Building Spray System ,

along with the elimination of the redundancy of Reactor Building Spray Additive Tanks. This is undesirable from the 1spect of plant safety. ,

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ALTERNATE TESTING:

During cold shutdown periods, each of these valves will be partial-stroke tested. t The motor operators and-stem assemblies of SFV-29015 and SFV-29016 will be exercised quarterly.

During each Reactor refueling outage, on s\n alternating schedule one of each type of valve will be disassembled and man 1 ally exercised to ensure operability. If it is found that the inspected value's operability is in

- question, then the remainder of the valves of that type will be disassembled,

- exercised and inspected in a similar manner.

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RELIEF REQUEST NO. VR-16 SYSTEM:

Various VALVES:

This relief request applies to all safety / relief valves included in the Program.

CATEGORY:

C FUNCTION:

These valves provide overpressure protection to the associated system components.

REOUIREMENT:

Safety and relief valves shall be tested in accordance with Subsection INV-3510.

BASIS FOR RELIEF:

ANSI /ASME OH-1-1981 - Requirements for Inservice Performance Testing of Nuclear Power Plant Pressure Relief Devices, was developed to supersede the requirements of Subsection INV-3510. This standard is more definitive and  ;

better suited to operational testing than is ASME/PTC 25.3 which is referenced in INV-3510.

4 ALTERNATE TESTING:

Safety and relief valves will be tested in accordance with the requirements of ANSI /ASME OH-1-1981.

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RELIEF REQUEST NO. VR-17 SYSTEM:

High Pressure Feedwater Heater (M-533)

VALVES:

FHS-049 FHS-050 CATEGORY:

C FUNCTION:

These valves open to provide a flowpath for minimum flow from the respective auxiliary feedwater pumps.

REQJIREMENI:

Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522 (INV-3521)

R& ifs FOR RELIEF:

There is no way these valves can be verified to be in the full open position without isolating the recirculation line for both auxiliary feedwater pumps fros the LP condenser which would result both auxiliary feedwater pumps to be considered inoperable. Thus, testing during plant operation is not practical from the viewpoint of reactor safety.

Performing the tests, including verification of full flow, requires special  !

(unusual) valve lineups and the installation of special test equipment. Such testing is considered out of the normal workscope expected during a typical cold shutdown (non-refteling) outage.  !

ALTERNATE TESTING:

r These valves will be exercised on a quarterly basis without verification of full flow. Verification of full-flow through the valves will be performed t

during each refueling outage.

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Rev. 4 l l  :

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RELIEF REQUEST NO. VR-18 DELETED Rev. 4

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i RELIEF REQUEST NO. VR-19 i SYSTEM 1: l Coolant Radwaste (M-560)

YALYLS: l

- SFV-dOOOI

- SFV-60003 i CMEGQM:

A FUNCTION:

~~ Primary containment isolation for Reactor Coolant Vent and Drain Header.

REQUIREMERI:

Valve seat leakage tests shall be made with the pressure differential in the same direction as when the valve is performing its function, with exceptions as stated in IHV-3423(a) through (d) (IHV-3423).

BASIS _FOR RELIEF:

~~ In these cases it is impractical to test gate valves in their futational direction. Where valves are provided with a bonnet tap or other F ans of venting between the seats, it is conservative to pressurize in the e werse direction with the valve internal space betseen the seats vented. Th:t provides an acceptable neans of determining the material condition of to downstream seating surface that must perform the leaktight service.

ALTERNATE TESJJRG:

Category A gate valves my be seat leak tested in a direction opposite to that when the valve is performing its function. When testing is performed in this manner, a valve body ser.t will be open to atmosphere to vent the cavity between the seats. The seating surface is subjected to the full differential pressure in the reverse direction. This is conservative since the effect of the imposed pressure tends to unseat the valve.

Rev. 4 u _ l

i RELIEF REQUEST NO. VR-20 1151 2 Decay Heat Removal (M-522)

VALVES:

HV-26515

. HV-26516 1

CATEGORY:

A I FUNCTIONS:

These valves are used for occasional sampling and draining of the core flood tanks and close to provide containment isolattor,.  !

RE0ullBfHI:

Valve seat leakage tests shall be made with the pressure differential in the same direction as '.then the valve is performing its function, with exceptions -

as stated in IWV-3423(a) through (d) (IWV-3423).

BASIS FOR RILIIE:

Testing these valves in the "accident direction" would require draining the core flood tanks, resulting in c large quantity of liquid radwaste (7500  :

gallons / tank) requiring processing and disposal. This is considered impractical from the view point of placing undue demands on the existing radioactive waste processing factitty and increases in personnel radiation

. exposure, f

These valves are one-inch solid wedge gate valves. It is reasonable to [

assume that, for this size and type of valve, the seating performance at a i test pressure of 52 psig is equivalent in either direction. In the past,  !

with a nominal pressure differential of approximately 600 psig present during normal plant operation, these valves have proven to be highly reliable with  ;

respect to their leaktight integrity.

l r

ALIERNATE TESTING:

Each of these valves may be leaktested in a direction opposite to that '

expected when the valve is performing its containment isolaticn function.

At least once per operating cycle each valve will be checked for excessive leakage while the core flood tanks are pressurized to normal operating i pressure.

Rev. 4  ;

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RELIEF REQUEST NO: VR-21 SYSTEM '

Bruce GM-Emergency Olesel Generator (M-583)

TDI Diesel Generator - Train "A" (H-585)

TOI Diesel Generator - Train "B" (M-585)

VALVES:

FY-89025 FY-89028 FV-89029 FV-89031 FY-89027 FY-89026 FV-89030 FV-89032 HV-10050A HV-10050B HV-10051A HV-100518 -

CATEGORY: i i

8 [

FUNCTIONS:

These valves open to supply compressed air to their respective diesel i generators to provide the motive force for engine starting.

• REOUIREMENT:

The stroke time of all power operated valves shall be measured to the nearest second, for stroke times 10 seconds or less, or 10% of the specified limiting ,

stroke time for full-stroke times longer than 10 seconds whenever such a '

valve is full stroke tested. (INV-3413(b)) ,

BASIS FOR RELIEF:

Since these valves have no position indication mechanism, stroke timing is  ;

not practical.

ALTERNATE TEil1NG:

These valves will be full-stroke exercised in conjunction with starting of the diesel generators per testing required by Rancho Seco Technical specifications. Proper startup and. operating of the diesel generators will demonstrate satisfactory valve operation - - valve stroke time will not be measured.

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RELIEF REQUEST No: VR-22 SYilB Reactor Coolant (M-520)

VALVES:

PSV-21511 CATEGORY:

8 FUNCTIOMS:

This valve opens to prevent cold overpressurization while in cold shutdown, conditions. l i

REQUIREMENT:

Ca egory B valves shall be exercised at least every three months.

BASIS FOR RELIEF:

This valve requires system pressure to open. Thus, opening while installed requires the use of reactor coolant system pressure. Tais ccold subject the associated system and piping components to undesirable transients. Removal of the valve during each cold shutdown would be an unwarranted burden on the plant staff.

ALTERNATIVE TESTING:

During each Reactor Coolant System cooldown, this valve will be functionally tested with the Block Valve (HV-21505) closed. During each refueling.

PSV-21511 will be fu1*l-stroke exercised via bench testing, i

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Rev. 4 L_

RELIEF REQUEST NO: VR-23 SYSTEM TDI Diesel Generator - Train "A" & "B" Air' Start (M-585 Sheet 2 & 4)

VALVES:

EGS-565 EGS-564 EGS-567 EGS-566 CATEGORY:

C FUNCTIONS:

These valves are check valves at the inlet to the receiver. They opt n to provide a flow path from the Air Compressor to the receivers and close to isolate the air receivers.

REOUIREMENT:

Check valves shall be exercised at least once every 3 months, except at:

provided by IWV-3522 (IWV-3521)

BASIS FOR RELIEF:

Due to the piping configuration of this system the only method of testing would require depressurization of the upstream piping. This would be an unacceptable method since it would require removing a portion of the air start system and compromising the start capabilities of the Emergency Diesel Generator System.

ALTERNATE TESTING:

One of these valves will be disassembled and inspected to ensure operability during each refueling outage. If this inspection resuies in questionable operability of the inspected valve, then the remaining valves will be similarly disassembled and inspected.

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J Appendix A: Summary-Inservice Testing Program - Pumps LEGEND Notation used in the pump summary table is as follows:

PUMP The pump identification number.

NAME The functional name of the pump.

CLASS The inservice inspection classification of the pump.

P&ID The Rancho Seco drawing number for the P&ID referring te. the particular pump of interest. (See drawing list in Appendix B.)

PARAMETERS Refers to the test quantities to be measured or observed.

When the character "Y" appears under a specific parameters then that measurement is made for that pump in accordance with the Code. A reference to a relief request accompanying the "Y" indicates some deviation from Code requirements. If the character "N" appears, that particuler ,arameter will not be measured or observed and a relief request is provided if required. Request: for relief are identified as "PRXX".

All re ior requests are included in Section 2.2.

TEST INTERVAL The respective frequency of testing for each pump. The letter "0" denotes a quarterly interval.

Rev. 4

-A APPENDIX A:

SUMMARY

-INSERVICE TESTING PROGRAM - PUMPS PARAMETERS INLET DIFF TEST EUME _NMiE O ASS P & ID SPEED PRESS PRESS f1W YlB J_E_E INTERVAL P-108A TDI DIESEL F0 PUMP "A" NC M-547 NA N-PR8 Y Y-PR13 N-PR14 N Q P-108B TDI DIESEL F0 PUMP "B" NC M-547 NA N-PR8 Y Y-PR13 N-PR14 N Q P-108C TDI DIESEL F0 PUMP "A" NC M-547 NA N-PR8 Y Y-PR13 N-PR14 N O P-108D TDI DIESEL F0 PUMP "B" NC M-547 NA N-PR8 Y Y-PR13 N-PR14 N Q P-236 MAKEUP 2 M-521 NA Y-PR11 Y N-PR7 Y N Q P-238A HP INJECTION 2 M-521 NA Y-PR11 Y N-PR7 Y N. Q P-238B HP INJECTION 2 M-521 NA Y-PRil Y N-PR7 Y N Q P-261A DECAY HEAT REMOVAL 2 M-522 NA Y-PR11 Y Y Y N O P-261B DECAY HEAT REMOVAL 2 M-522 NA Y-PR11 Y Y Y N Q P-291A REACTOR BUILDING SPRAY 2 M-524 NA Y-PR11 Y Y Y N O P-291B REACTOR BUILDING SPRAY 2 M-524 NA Y-PR11 Y Y Y N Q

~~

P-318 DUAL DR AUXILIARY FEEDHATER 3 M-533 Y' Y Y Y Y N Q P-319 MOTOR-DRIVEN AUX. FEEDHATER 3 M-533 NA Y Y Y Y N Q NOTE: Relief requests PRI through PR6 apply to all pumps, as applicable.

Speed will be measured only during turbine-driven operation.

Rev. 4 A-2

APPENDIX A:

SUMMARY

-INSERVICE TESTING PROGRAM - PUMPS (Continued) ,

i PARAMETERS INLET DIFF TEST EUME NAME CLASS P & ID SPEED PRESS PRESS ELQH YIH IEME INTERVAL P-472A NUCLEAR SERVICE RAN HATER 3 M-544 NA N-PR8 Y N-PRIO Y N Q P-4728 NUCLEAR SERVICE RAH HATER 3 M-544 NA N-PR8 Y N-PRIO Y N Q P-482A NUCLEAR SERVICE COOLING HATER 3 M-545 NA Y Y N-PRIO Y N Q P-482B NUCLEAR SERVICE COOLING HATER 3 M-545 NA Y Y N-PRIO Y N Q P-705A BORIC ACID 2 H-570 NA Y-PR11 Y Y Y N Q P-705B BORIC ACID 2 M-570 NA Y-PRll Y Y Y N Q P-888A Bruce GM DIESEL F0 PUMP "A" NC M-582 NA N-PR8 Y Y-PR13 N-PR14 N Q-PR15 P-8888 Bruce GM DIESEL F0 PUMP "A" NC H-582 NA N-PR8 Y Y-PR13 N-PR14 N Q-PRIS P-888C Bruce GM DIESEL F0 PUMP "B" NC H-582 NA N-PR8 Y Y-PRl3 N-PR14 N Q-PRIS P-888D Bruce GM DIESEL F0 PUMP "B" NC M-582 NA N-PR8 Y Y-PR13 N-PR14 N Q-PRIS NOTE: Relief requests PRI through PR6 apply to all pumps, as applicable.

Rev. 4 A-3

APPENDIX B

SUMMARY

INSERVICE TESTING PROGRAM

- VALVES -

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Refercnce Drawings i

Drawina No. Egya. System Paae I H-520, Sh 1 34 Reactor Coolant System 13-5 H-520, Sh 2 14 Reactor Coolant System B-6 H-521, Sh 1 14 Hake-up and Purification System B-7 H-521, Sh 2 15 Hake-up and Purification System E-8 H-522, Sh 1 33 Decay Heat Removal System B-12 H-524 10 Reactor Building Spray System B-18 H-530, Sh 1 13 HP and Auxillary Turbines System B-20 H-530, Sh 2 12 HP and Auxiliary Turbines System B- 21 H-530, Sh 2A

• 3 HP and Auxiliary Turbines System B-22 H-530, Sh 3 17 HP and Auxiliary Turbines System B-26 H-532, Sh 1

• 9 Steam Generator System B-27 H-532, Sh 2 6 Steam Generator System B .10 H-532, Sh 3 6 Steam Generator System B-31 H-533, Sh 3 10 High Pressure Feedwater Heater System B-32 H-536 26 Condenser System B-33 H-537, Sh 3 12 Auxiliary Steam System B-34 H-543, Sh 1 6 Component Cooling Hater System B-35 H-543, Sh 4 13 Component Cooling Hater System B-35 H-544 20 Nuclear Service Raw Hater Systen B-37 4545 15 Nuclear Service Cooling Hater System B-38

~~

H-547 0 TDI Diesel Fuel Oil System B-41 H-551 27 Reactor Building Heating, Ventilating, B-42 and Air Conditioning Systems M-560, Sh 3 8 Coolant Radwaste System B-45 H-561, Sh 3 5 Hiscellaneous Liquid Radwaste System B-46 H-570 25 Reactor Coolant Chemical Addition B-47 and Sampling System H-573 17 Turbine Plant Sampling System B-49

- H-582, Sh 1 25 Diesel Oil Systems B-50 H-583, Sh 1 14 Emergency Diesel Generator B-51 H-585, Sh 1 0 TDI Diesel Generator System - Train "A" B-52 H-585, Sh 2 0 TDI Diesel Generator System - Train "A" B-53 I H-585, Sh 3 0 TDI Diesel Generator System - Train "B" B-54

- H-585, Sh 4 0 TDI Diesel Generator System - Train "B" B-55 H-590, Sh 1 37 Plant Air System B-56 H-591, Sh 1 37 Auxiliary Gas System B-57 H-593, Sh 2 12 Hiscellaneous Hater Systems B-58 l

l

• The EFIC valves, included in the program, will be shown on later revisions of these drawings.

l Rev. 4

-B i i

i

Appendix B: Summary-Inservice Testing Program - Valves LEGEND Notation used in the valve sunmary table is as follows:

VALVE The valve alpha-numerical identification.

COOR The location of the valve on the referenced P&IO.

FUNCTION The functional system description of the valve.

CLASS The ISI classification. The characters "NC" denote that the particular valve is outside the ISI boundary.

CAT The valve category per paragraph INV-2200.

SIZE The nominal valve size in inches.

TYPE The valve type as follows:

CK Check GT Gate GL Globe BF Butterfly PSV Safety / relief SCK Stop-check-ACT The valve actuator type as follows:

H0 Motor-operated A0 Air-operated SO Solenoid SA Sel f-actuated MAN Marual POS The normal position of the valve during plant. operation - open or closed.

Rev. 4

-B , -

l

)

Appendix B: Summary-Inservice-Testing Program - Valves LEGEND (Cont.)

REQHT Test requirement as follows:

FSTO Full-stroke exercise to open position with stroke-time measurement for power-operated valves.

FSTC Full-stroke exercise to the closed position with stroke-time measurement for power-operated valves.

SSTC Slow speed exercising to the closed direction. Stroke time will not be measured.

PE0 Partial-stroke exercise to open position.

PEC Partial-stroke exercise to the closed position SLTJ Leakage test in accordance with 10 CFR 50. Appendix J SLTP Leakage test - Event V GLT Leakage test for gross leakage. Leakrate will not be measured nor trended.

VI Visual inspection of valve internals.

VSP Setpoint test of safety / relief valves per IWV-3510 FREQ The required test interval as follows:

0 Quarterly during plant operation.

CS Cold shutdown. See Paragraph 3.1.5.

RF Nominally every two years during reactor refueling outage.

SP See appropriate relief request.

5Y Refers to the test period for testing safety / relief valves ANSI /ASME Standard OH-1-1981 (5 or 10 years, as appropriate) 10Y See applicable relief request.

AP As practical or available. Refer to appropriate relief request.

REKARKS Relief Requests are designated VR-XX. Refer to Section 3.2 for

relief requests.

l l Rev. 4 1 -B l l

SYSTEM REACTOR COOLANT DRAHING N0:

VALVE C00R FUNCTION CLASS CAT SIZE TYFE ACT POS REOMT FRE0 REMARK RIWHX -

Rx Internals Vent -

C 14 CK SA C FST0 RF VR-5 RIWHZ -

Rx Internals Vent -

C 14 CK SA C FST0 RF VR-5

_ k*

4 RIWXH -

Rx Internals Vent -

C 14 CK SA C FST0 RF VR-5 RIWXY -

Rx Internals Vent -

C 14 CK SA C FST0 RF VR-5 ,

RIWYX -

Rx Internals Vent -

C 14 CK SA C FST0 RF VR-5 RIWYZ -

Rx Internals Vent -

C 14 CK SA C FST0' RF VR-5 RIWZH -

Rx Internals Vent -

C 14 CK SA C FST0 RF VR-5 ,

i RIWZY -

Rx Internals Vent -

C 14 CK SA C FST0 RF VR-5 Rev. 4

-B .

SYSTEM: REACTOR COOLANT DRAHING N0: M-520 Sh 1 VALVE C00R FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FREO REMARK HV-21505 F5 PORV Blocking 1 B 2.5 GT N0 0 FSTC Q VPI .RF HV-21522 C6 Press Hi Pt Vent-0tbd 1 B .5 GT S0 C FST0 CS VPI RF HV-21528 D6 Press Hi Pt Vent-Inbd 1 8 .5 GT S0 C FSTO CS VPI RF PSV-21506 DS Pressurizer Safety 1 C 3.0 PSV SA C VSP SY PSV-21507 E3 Pressurizer Safety 1 C 3.0 PSV SA C VSP SY PSV-21511 C5 Power Oper Relief Valve 1 B 2.5 POV S0 C FSTO RF VR-22 PE0 CS VR-22 Rev. 4

-B SYSTEM: REACTOR COOLANT DRAHING NO: M-520 Sh 2 VALVE C00R FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FREO REMARK l HV-20533 D2 Stm Gen E-205A 1 8 .5 GT S0 C FST0 CS INBD Hi Pt Vent VPI RF HV-20534 D13 Stm Gen E-2058 1 B .5 GT S0 C FST0 CS INBD Hi Pt Vent VPI RF HV-20579 C2 Stm Gen E-20SA 1 8 .5 GT S0 C FST0 CS OTBD Hi Pt Vent VPI RF HV-20580 E13 Stm Gen E-2058 1 B .5 GT S0 C FST0 CS OTBD Hi Pt Vent VPI RF I

t 1

Rev. 4

-B SYSTEM: MAKE-UP AND PURIFICATION DRAMING NO: M-521 Sh 1 VALVE C00R FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FREO REMARK SFV-22005 B2 Letdown to E-220A 1 B 2.5 GT M0 0 FSTC CS VPI RF SFV-22006 D2 Letdown to E-2208 and 1 B 2.5 GT M0 O FSTC CS E-220C VPI RF

~~

SFV-22009 C6 Letdown-Otbd Isol 2 A 2.5 GT A0 0 FSTC CS SLTJ RF VPI RF SFV-22023 C5 Letdown-Inbd Isol 2 A 2.5 GT M0 O FSTC CS SLTJ RF VPI RF

! SFV-22025 Cl Letdown from Stm Gen 1 8 2.5 GT M0 0 FSTC CS I 205A VPI RF SFV-23645 H7 HP INJ/MU Pump Min 2 8 2 GT M0 O FSTC Q Flow VPI F.F SFV-23646 I7 HP INJ/MU Pump Min 2 B 2 GT M0 O FSTC. Q Flow VPI RF SFV-24004 G5 RCP Seal Hater Ret 2 A 4 GT M0 O FSTC CS Inbd SLTJ RF VPI RF SFV-24013 G6 RCP Seal Water Ret 2 A 4 GT A0 0 FSTC CS Otbd SLTJ RF VPI RF Rev. 4 -

-B SYSTEM: MAKE-UP AND PURIFICATION __

DRAHING NO: M-521 Sh 2 VALVE C00R FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FREO REMARK BHS-019 G14 Supply from CBAT 2 C 2 CK SA C FST0 RF VR-6 BHS-044 B14 Supply from CBAT 2 C 2 CK SA C FST0 RF VR-6 HV-23801 J3 Disch to Rx Inlet 1 A/C 2.5 SCK M0 O FSTC Q Motor Only Loop B FSTO RF- VR-8 FSTC RF

~~

SLTJ RF VR-4 1

VPI RF Stem Only i

HV-23802 IS Disch to Aux Spray 1 A 2 GL M0 C FST0- Q FSTC Q

~~

SLTJ RF VR-4 VPI RF l SFV-23508 E14 Disch from Make-up 2 B 4 GT M0 0 FSTC CS l Tank VPI RF SFV-23604 C7 Makeup Line Isol. 2 A 2.5 GL M0 O FSTC CS

~'

'SLTJ RF VR-4 VPI RF i

SFV-23616 E8 RCP Seal Supply 2 A 4 GT M0 O FSTC CS

~~

SLTJ RF VR-4 VPI RF SFV-23809 A4 Disch to Rx Inlet 2 A 2.5 GL M0 C FSTO Q Loop A FSTC Q

~

SLTJ RF VR-4 VPI RF i Rev. 4

-B . . . ..

SYSTEM: MAKE-UP AND PURIFICATION ORAHING NO: M-521 Sh 2 VALVE C00R FUNCTION CLASS CAT SIZE TYPE ACT POS REONT FRE0 REMARK SFV-23810 J4 Disch to Rx Inlet 2 A 2.5 GL M0 C FSTO Q Loop B FSTC Q SLTJ RF VR-4 VPI RF SFV-23811 B4 Disch to Rx Inlet 2 A 2.5 GL HC C FSTO Q Loop A FSTC Q SLTJ RF VR-4 VPI RF SFV-23812 J4 Disch to Rx Inlet 2 A 2.5 GL M0 C FSTO Q Loop B FSTC Q SLTJ RF VR-4 VPI RF SIM-002 Ell Make-up Pump Disch. 2 C 4 CK SA 0 PE0 Q VR-7 PEC Q VR-7 FST0 RF VR-7 FSTC RF VR-7

+ SIM-019 H2 RCP 210A Seal Sup 2 A/C 2 SCK MAN O FSTC CS SLTJ RF VR-4 SIM-020 E2 RCP 210B Seal Sup 2 A/C 2 SCK MAN O FSTC CS SLTJ RF VR-4

SIM-021 F2 RCP 210C Seal Sup 2 A/C 2 SCK MAN 0 FSTC CS

SLTJ RF VR-4 SIM-022 G2 RCP 2100 Seal Sup 2 A/C 2 SCK MAN O FSTC CS SLTJ RF VR-4 SIM-023 H2 RCP "A" Seal Inj Vent 2 A 1 GL MAN C SLTJ RF Passive Rev. 4

-B SYSTEM: MAKE-UP AND PURIFICATION DRAHING NO: M-521 Sh 2 VALVE C00R FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FRE0 REMARK SIM-025 F2 RCP "C" Seal Inj Vent 2 A 1 GL MAN C SLTJ RF Passive SIM-026 G3 RCP "D" Seal Inj Vent 2 A 1 GL MAN C SLTJ RF Passive SIM-036 C4 Disc to Rx Inlet 1 A/C 2.5 SCK MAN O PE0 Q VR-8 e- Loop A PEC CS VR-8 FSTO RF VR-8 FSTC RF VR-8

~~ SLTJ RF VR-4 SIM-037 C1 Disc to Rx Inlet Lp A 1 C 2.5 CK SA 0 PE0 Q VR-8 PEC CS VR-8 FST0 RF VR-8 SIM-040 B4 Disc to Rx Inlet Lp A l A/C 2.5 SCK MAN 0 FST0 RF VR-8 FSTC RF VR-8

~~

SLTJ RF VR-4 SIM-041 81 Disc to Rx Inlet Lp A 1 C 2.5 CK SA C FSTO kF VR-8 -

SIM-043 H14 Disch from BST 2 C 6 CK SA C FST0 RF VR-6 SIM-045 Hll HP Inj Pup 2388 Disch 2 C 4 CK SA C PE0 0 PEC Q FST0 RF VR-7 FSTC RF VR-7 l SIM-047 J3 Disch to Rx Inlet Lp B 1 A/C 2.5 SCK MAN O FSTO RF VR-8 VR-8 FSTC RF

~~

SLTJ RF VR-4 2.5 SIM-049 J1 Disch to Rx Inlet Lp B 1 C CK SA C FSTO RF VR-8 -

SIM-050 J1 Disch to Rx Inlet Lp B 1 C 2.5 CK SA C FST0 RF VR-8 Rev. 4

-D ._ .

SYSTEM: MAKE-UP AND PURIFICATION ORAHING NO: M-521 Sh 2 VALVE C00R FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FREO REMARK SIM-052 A13 Disch from BST 2 C 6 CK SA C FST0 RF VR-6 SIM-058 Bil HP Inj Pump 238A Disch 2 C 4 CK SA C PE0 0 PEC Q FSTO RF VR-7 FSTC RF VR-7 SIM-078 Gil HP Inj. Pump"B"Min Flow 2 C 2.5 SCK MAN O FSTC Q SIM-079 D11 Makeup Pump Min Flow 2 C 2.5 SCK MAN 0 FSTC Q SIM-081 All HP Inj. Pump"A"Min Flow 2 C 2.5 SCK- MAN 0 FSTC Q t

i

, Rev. 4

-B .

~

.O, v

SYSTEM: DECAY HEAT REMOVAL DRANING NO: M-522 Sh 1 VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARK j

BNS-003 G4 Disch Fr BMST to P-261B 2 C 16 CK SA .C FST0 Q BNS-004 G4 Disch Fr BNST to P-261A 2 C 16 CK SA C FSTO Q BNS-045 F12 Boric Ac. Pump 2 C .75 CK SA C FSTO RF VR-10 Disc To DHR CBS-035 I10 Spray Add to P-2618 2 C 2 CK SA C VI RF VR-13 CBS-036 JS Spray Add to P-261A 2 C 2 CK SA C'. VI .RF VR-13

. CFS-001 C7 Inj from Core Flood 1 A/C 14 CK SA C PE0 CS VR-11 i Tk 265A PEC CS VR-11 i VI 10Y VR-11 ,

SLTP. RF 'VR-9 i CFS-002 C9 Inj from Core Flood 1 A/C 14 CK SA C PE0 CS VR-11 4

Tk 2658 PEC CS VR-11 VI 10Y- .VR-11 SLTP RF VR-9

CFS-003 B3 CFT Sample Isolation 2 A .5 GL MAN C SLTJ. RF Passive CFS-004 C3 CFT Drain Line Isol 2 A .5 GL- MAN C SLTJ NF. Passive CFS-005 A4 N2 Supply to CFT 265A 2 A 1 GL ti?" C SLTJ i VR-4, Passive CFS-006 A4 N2 Supply to CFT 265B 2 .A 1 GL MN C SLTJ- RF VR-4, Passive-CFS-009 B4 CFT 265A Fill Line 2 A 1 GL MAN C SLTJ RF VR-4, Passive-CFS-010 B4 CFT 2558 Fill Line 2 A 1 GL MAN C SLTJ RF VR-4, Passive l Rev. 4

-B ... - . - _ . . . . . . . . . . - - . _ _ - - . - - . , . . .. .. . . . -. . .

J' SYSTEM: DECAY HEAT REMOVAL DRAWING NO: % 522 Sh 1 ,

VALVE C00R FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FRE0 REMARK CFS-011 B5 CFT 265A Fill Fr BAAP 2 A .75 GL MAN C SLTJ RF VR-4, Passive i

CFS-012 B4 CFT 265B Fill Fr BAAP 2 A .75 GL MAN C SLTJ RF VR-4, Passive l DHS-003 18 P-261-B Suct Fr BHST 2 C 16 CK SA C FSTO Q DHS-004 19 P-261-B Suct Fr BHST 2 C 16 CK SA C FSTO Q DHS-007 H8 Decay Ht Rem Pop 2 C 10 CK SA C FSTO Q 261A Disch. 4 DHS-008 H9 Decay Ht Rem Pop 2 C 10 CK SA C FST0 0 261B Disch.

DHS-015 b7 Decay Ht Ret from 1 A/C 10 SCK MAN 0 FST0 CS E-260A FSTC CS SLTP RF VR-9

~~

SLTJ RF VR-4 DHS-016 09 Decay Ht Ret from 1 A/C 10 SCK MAN 0 FSb CS E-260B FSTC CS SLTP RF VR-9 SLTJ RF VR-4 DMS-017 E7 Dec Ht Rem to CFT "A" 2 A/C .75 SCK MAN 0 FSTC CS SLTJ RF DHS-018 09 Dec Ht Rem to CFT "B" 2 A/C .75 SCK MAN 0 FSTC 'CS SLTJ RF DHS-038 E7 fuel Xfer Canal Fill 2 A 10 GT MAN C SLTJ RF VR-4, Passive DHS-039 E10 Fuel Xfer Canal Fill 2 A 10 GT MAN C SLTJ RF VR-4, Passive Rev. 4 ri __ , . - ., _ - _ _ . . . . _ _ _ _ _ _ _ _ - _ - _ _ _ _ - _ _ _ _

SYSTEM: DECAY HEAT REMOVAL DRAHING NO: M-522 Sh 1 VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FREO REMARK DHS-059 E10 Dec Ht Rem to Pres Spr. 1 C 1.5 CK SA C FST0 CS DHS-497 E10 Fuel Xfer Canal Fill 2 A 1 GL MAN C SLTJ RF VR-4, Passive DHS-498 E7 fuel Xfer Canal Fill 2 A 1 GL MAN C SLTJ RF VR-4, Passive HV-20001 011 Rx Co ol Supply to 1 B 12 GT M0 C FSTO CS DH Rem Pops FSTC CS GLT RF-VPI RF HV-20002 D12 Rx Cool Supply to 1 B 12 GT M0 C FST0 CS DH Rem Pops FSTC CS GLT RF VPI RF HV-20003 D13 DH Remov. Dump to Sump 2 B 2 GL M0 C FST0 CS VPI RF HV-20005 I13 Dec Ht Supply to 2 8 12 Gi M0 C FSTO Q P-261B FSTC 0 VPI RF HV-20006 I12 Dec Ht Supply to 2 B 12 GT H0 C FS f0 Q P-261A FSTC Q VPI RF HV-26007 F5 Dec Ht Disch to 2 B 4 GT M0 C FSTO Q P-23BA VPI RF HV-260C0 F10 Dec Ht Disch to 2 B 4 GT M0 C FSTO Q P-238B VPI RF Rev. 4

-B  ;

SYSTEM: DECAY' HEAT REMOVAL DRANING NO: M-522 Sh 1 VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS REONT FRE0 REMARK HV-26011 P10 Dec Ht Rem To Press Sp 1 A 1.5 GT M0 C SLTJ RF VR-4 HV-26046 F8 Dec Ht Rem X Conn 2 B -8 GL M0 C FSTO Q to SFP VPI RF HV-26047 F8 Dec Ht Rem X Conn 2 B 8 GL M0 C FSTO Q to SFP VPI RF HV-26105 E13 P-261 "A" Suct fr Sump 2 A 18 GT M0 C FST0 CS FSTC CS SLTJ RF VPI RF HV-26106 E13 P-261 "B" Suct fr Sump 2 A 18 GT M0 C FST0 CS FSTC CS SLTJ RF VPI RF HV-26515 D7 CFT "A" Drain /Samp 2 A 1 GT M0 C FSTC Q SLTJ RF VR-4, VR-20 VPI RF HV-26516 010 CFT "B" Drain /Samp 2 A 1 GT M0 C FShC Q

~~

SLTJ RF VR-4, VR-20 VPI RF HV-26517 87 CFT "A" N2 Sup/ Fill 2 A 1 GT M0 C FSTC Q SLTJ RF VPr RF HV-25518 310 CFT "B" N2 Sup/ Fill 2 A 1 GT M0 C FSTC Q SLTJ RF VPI RF Ray, 4

-B .. .- . .,.

r

. x; 1

SYSTEM: DECAY HEAT REMOVAL DRANING NO: M-522 Sh 1 i VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FRE0 REMARK PSV-20004 D13 Dec Ht Rem Ret Rel. 2 C .75 PSV SA C VSP- SY "M PSV-25009 J7 P-261A Suct fr BNST 2 C .75 PSV SA C VSP SY I

Relief PSV-25010 19 P-2618 Suct fr BNST 2 C .75 PSV SA C VSP SY i Relief I PSV-26101 H7 P-261A Disch Relief 2 C .75 .PSV SA C VSP SY j MV-26102 H9 P-2618 Disch Relief 2 C .75 PSV SA C VSP SY PSV-26109 F14 P-261A Suct fr Sump 2 C .75 PSV SA C VSP SY Relief ,1 PSV-26110 F13 P-261B Suct fr Sump 2 C .75 PSV SA C VSP SY q Relief PSV-26509 A7 Core Flood Tank 265A 2 C i PSV SA C VSP SY Safety PSV-26510 A10 Core Flood Tank 2658 2 C 1 PSV SA C VSP SY Safety RCS-001 DS Dec Ht/ Core Flood 1 A/C- 14 CK SA C FST0 CS l

. to Rx Vess FSTC CS l SLTP RF VR-9 RCS-002 D9 Dec Ht/ Core Flood 1- A/C 14 .CK SA C FST0 CS .;

i to Rx Vess FSTC CS l

SLTP RF VR-9 H i

l

~

RCS-042 A6 N2 to Nitro..Prehtr 2 A 1 GL MAN 'C SLTJ RF VR-4, Passive-i H Rev. 4

-B .I

SYSTEM: DECAY HEAT REMOVAL DRANING NO: M-522 Sh 1 '

VALVE C00R FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FREO REMARK SFV-25003 I6 P-260A Suct fr BHST 2 8 16 GT - M0 C FSTO Q FSTC Q VPI RF SFV-25004 I6 P-260B Suct fr BH 2 8 16 GT M0 C FSTO Q FSTC Q VPI. RF SFV-26005 E7 E-260A Disch to RCS 2 A 10 GT M0 C FSTO Q FSTC Q SLTJ RF VR-4 VPI RF SFV-26006 E9 E-260B Disch to RCS 2 A 10 GT M0 C FSTO Q FSTC Q

~

SLTJ RF VR-4 VPI RF SFV-26039 G/ E-260A Disch 2 8 10 BA M0 O FSTO Q VPI RF SFV-26040 G9 Eh608Disch 2 B 10 BA M0 O FSTO Q VPI RF Rev. 4

-B .;

l SYSTEM: REACTOR BUILDING SPRAY DRAWING NO: M-524 VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FRE0 REMARK CBS-001 E6 R 8 Spr. P 291A Suct. 2 C 10 CK SA C FSTO Q CBS-002 E10 R B Spr. P 2918 Suct. 2 C 10 CK SA C FSTO Q CBS-005 F6 R B Spr. P 291A Disc. 2 C 8 CK SA C FST0 Q CBS-006 F9 R B Spr. P 2918 Disc. 2 C 8 CK SA C FST0 Q CBS-009 D7 R B Spr. A-Inbd Isol. 2 A/C 8 SCK MAN C VI RF VR-la

~~

SLTJ RF VR-4 CBS-010 D8 R B Spr. B-Inbd Isol. 2 A/C 8 SCK MAN C VI RF VR-14 4

~~

SLTJ RF VR-4 CBS-021 H6 Sp Add Tank 290A Disc 2 C 2 CK SA C PE0 CS VR-15 VI RF VR-15 CBS-022 H9 Sp Add Tank 2908 Disc 2 C 2 CK SA C PE0 CS VR-15 VI RF VR-15 CBS-027 H7 Sp Add Tank 2908 Disc 2 C 2 CK SA C PE0 CS VR-15 VI RF VR-15 CBS-028 H9 Sp Add Tank 290A Disc 2 C 2 CK SA C PE0 CS VR-15 VI RF VR-15 CBS-029 17 NA0H to Dec Ht. Rem 2 B h GT MAN C FSTO Q CBS-030 19 NA0H to Dec Ht. Rem 2 B 2 GT MAN C FSTO Q CBS-033 J10 NA0H to Dec Ht. Rem 2 B 2 GT MAN C FST0 0 Rev. 4

-B s

I r

l SYSIEM: REACTOR BUILDING SPRAY QFAMING NO: H-524 VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FRE0 REMARK CBS-034 J10 NA0H to Dec Ht. Ree 2 B 2 GT MAN C FSTO Q j CBS-504 F12 Rx Bldg Sp Add Tank 2 C 2 CK SA C FSTO Q 2908 Vac Bkr CBS-505 F3 Rx Bldg Sp Add Tank 2 C 2 CK SA C FSTO Q 290A Vac Bkr PSV-7.9117 G5 Cont Sp Disch Re1 2 C .75 PSV SA C VSP SY PSV-29118 G10 Cont Sp Disch Re1 2 C .75 PSV SA C VSP SY SFV-29015 H7 Sup to Eject. 292A 2 C 2 SCK M0 ~C FSTO Q Hotor only PE0 CS VR-15 VI RF VR-15 VPI RF Sten only SFV-29016 H9 Sup to Eject. 2928 2 C 2 SCK M0 C FSTO Q Motor only PE0 CS VR-15 VI RF VR-15 VPI RF Stem only SFV-29107 D7 Rx Bldg Spray "A" 2 A 8 GT N0 C FSTO Q*

Otdb Isol FSTC Q

~~

SLTJ, RF VR-4 VPI RF SFV-29108 D8 Rx Bldg Spray "C" 2 A 8 GT M0 C FSTO Q Otdb Isol FSTC Q

~~

SLTJ RF VR-4 VPI RF-Rev. 4 ~

-B I

.i SYSTEM: HP AND AUXILIARY TURBINES DRANING NO: M-530. Sh 1 VALVE C00R FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FRE0 REMARK i TV-1 H11 Main Turbine Throttle 2 B 26 GT HYD 0 SSTC Q

' ~~

FSTC CS VR-1 VPI RF; TV-2 011 Main Turbine Throttle 2 B 26 GT HYD 0 SSTC Q

~~

FSTC CS VR-1 VPI RF i TV-3 Ill Main Turbine T5rottle 2 B 26 GT HYD 0 SSTC Q FSTC CS VR-1

VPI RF l TV-4 C11 Main Turbine Throttle 2 B 26 GT HYO O SSTC 0 FSTC CS VR-1 VPI RF l

Rev. 4

-B *

. , - - - - , ,, ,. - - - , , , , . - - - . _ _ , m_

,_m.,

SYSTEM: HP AND AUXILIARY TURBINES DRANING NO: M-530. Sh 2 VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARK HV-20560 08 Stu to Aux Steam 2 B 8 GT M0 0 FSTC Q VPI RF-HV-20565 H8 Sta to Aux Steam 2 B 8 GT M0 O FSTC Q j VPI RF HV-20597 H6 Sta to Rhtrs. 2 B 8 GT M0 O FSTC CS '

A and C VPI RF-HV-20598 E6 Sta to Rhtrs. 2 B 8 GT M0 0 FSTC CS B and D VPI RF HV-32243 H10 Sta Drain and Pegging 2 B 14 GT M0 O FSTC Q Steam VPI RF HV-35069 04 Steam Drain 2 B 2 GT M0 0. FSTC Q VPI RF HV-35070 H4 Steam Drain 2 B 2 GT M0 O FSTC Q VPI RF Rev. 4

-B .. - . -- , - _ -

j _

- .::.= 3p gg&m SYSTEM: HP AND AUXILIARY TURBINES DRANING NO: M-530. Sh 2A VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS REONT FREO REMARK' HV-20517 H4 Atmos. Stu Dump Iso 2 B 8 GT M0 O FSTO Q FSTC Q VPI RF-HV-20518 C4 Atmos Stu Dump Iso 2 8 8 GT M0 O FSTO Q FSTC Q VPI RF HV-20521 18 Turb BP Iso "A" 2 8 10 GT M0 O FSTC CS  :'

VPI RF HV-20522 B8 Turb BP Iso "B" 2 B 10 GT M0 O FSTC CS VPI RF HV-20569 Gil Supply to Aux FP 2 8 6 GT N0 0 FSTO Q Turbine FSTC Q VPI RF HV-20570 I13 Stra drain to LP Cond 2 B 2 GT M0 O FSTC Q YPI RF HV-20571 C13 Sta drain to LP Cond 2 8 2 GT MO 0 FSTC Q VPI RF HV-20596 E11 Supply to Aux FP 2 8 6 GT M0 O FSTO Q l Turbine FSTC Q VPI RF MSS-051 C11 Supply to Aux FP 2 C 6 CK SA C FSTO Q FSTC CS MSS-052 Ill Supply to Aux FP 2 C 6 CK ?A C FSTO Q FSTC CS Rev. 4

-B SYSTEM: HP AND AUXILIARY TURBINES DRAHING NO: M-530. Sh 2A VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FREO REMARK PSV-20533 K3 Hein Steam Relief 2 C 6 PSV SA C VSP SY PSV-20534 85 Main Steam Relief 2 C 6 PSV SA C VSP SY PSV-20544 B7 Main Steam Relief 2 C 6 PSV SA C VSP SY

+

PSV-20545 K6 Main Steam Relief 2 C 6 PSV SA C VSP SY PSV-20546 B7 Main Steam Relief 2 C 6 PSV SA C VSP SY PSV-20547 K6 Main Steam Relief 2 C 6 PSV SA C VSP SY PSV-20548 B6 Main Steam Relief 2 C 6 PSV SA C VSP SY PSV-20549 K5 Main Steam Relief 2 C 6 PSV 5A C VSP SY PSV-20550 B5 Main Steam Relief 2 C 6 PSV SA C VSP SY PSV-20551 K4 Main Steam Relief 2 C 6 PSV SA C VSP SY PSV-20552 B4 Main Steam Relief 2 C 6 PSV SA C VSP 5Y PSV-20553 K4 Main Steam Relief 2 C 6 PSV SA C VSP SY PSV-20554 83 Main Steam Relief 2 C 6 PSV SA C VSP SY

! PSV-20555 K2 Main Steam Relief 2 C 6 PSV SA C VSP SY l

PSV-20556 83 Main Steam Relief 2 C 6 PSV SA C VSP SY PSV-20557 K2 Main Steam Relief 2 C 6 PSV SA C VSP SY PSV-20558 B2 Main Steam Relief 2 C 6 PSV SA C VSP 5Y Rev. 4

-B __ _ , _ _ _ _ _ __ _ _

SYSTEM: HP AND AUXILIARY TURBINES DRAWING NO: M-530. Sh 2A.

VALVE CCOR FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FREO REMARK PSV-20559 K1 Main Steam Relief 2 C 6 PSV SA C VSP SY PV-20561 G9 Main Turbine Bypass 2 B 8 GT A0 C FST0 CS FSTC CS VPI RF PV-20562A D4 Atmos. Steam Dump 2 B 8 GT' A0 C FST0 CS FSTC CS VPI RF PV-205628 D1 Atmos. Steam Dump 2 B 8 GT A0 C FSTO CS FSTC CS VPI RF PV-20562C 03 Atmos. Steam Dump 2 8 8 GT A0 C FST0 CS FSTC CS VPI RF PV-20563 G8 Main Turbine Bypass 2 B 8 GT A0 C FSTO CS FSTC CS VPI RF PV-20564 E9 Main Turbine Bypass 2 B 8 GT A0 C FST0 CS FSTC CS VPI RF PV-20566 E8 Main Turbine Bypass 2 B 8 GT A0 C FST0 CS FSTC CS VPI RF PV-20571A G4 Atmos Steam Dump 2 B 8 GT A0 C FST0 CS FSTC CS VPI RF Rev. 4

-B .. - .

c l

SYSTEM: HP AND AUXILIARY TURBINES _ DRAMING NO: M-530. Sh 2A VALVE C00R FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO ROERK PV-20571B G1 Atmos Steam Dump 2 B 8 GT A0 C FSTO CS FSTC CS VPI RF PV-20571C G3 Atmos Steam Dump 2 B 8 GT A0 C FST0 CS FSTC CS VPI RF t

Rev. 4

-B _ , .

_.,__r ,

SYSTEM: HP AND AUXILIARY TURBINES DRANING NO: M-530. Sh 3

VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FREO REMARK MSS-068 G9 Aux FP Turbine Exh. NC C 8 CK SA C- FSTO Q HV-30801 19 Aux FP Turbine Stop 3 8 4 GL MD C FSTO Q VPI. RF

• -re, i

5 I

i s.

_ ._ _ ._. Rev. 4 __.__..__._.._.____2__-

-B -

ycm--s-..m y* mmg,e. gir- w- -- - + -e im -r ip y. rw --%, --- -. w p e --s-- - . - - q. - -

P., ,

SYSTEM: STEAM GENERATOR DRANING NO: H-532 Sh 1 VALVE COOR FUNCTION CLASS CAT SIZF TYPE ACT POS RE0MT FREO REMARK FV-20525 D8 Main Feed to SG 205A 2 B 16 GL A0 0 FSTC CS VPI RF FV-20526 H9 Main Feed to SG 205B 2 8 16 GL A0 0 FSTC CS VPI RF FV-20527 B7 Emerg FH Stop to 2 8 6 GT A0 C FSTO Q SG 205A FSTC Q VPI RF FV-20528 G10 Emerg FH Stop to 2 B 6 GT A0 C FSTO Q SG 205B FSTC Q VPI RF

~~

FV-20531 C7 Emerg Feed to SG205A 2 A 6 GT SO C FSTO Q FSTC Q VPI RF FV-20532 H10 Emerg Feed to SG205B 2 B 6 GT M0 C FSTO Q FSTC Q VPI RF FV-20575 E6 feed BP to SG 205A 2 B 6 GL A0 0 FSTC CS VPI RF FV-20576 18 Feed GP to SG 205B 2 B 6 GL A0 0 FSTC CS VPI RF FHS-061 B12 Emerg Feed to SG 205A 2 C 6 CK SA C FST0 CS See Para 3.1.6 FHS-062 G12 Emerg Feed to SG 205B 2 C 6 CK SA C FST0 CS See Para 3.1.6

~~

FHS-101 F12 Stm Gen Cleaning NC A 10 GT MAN C SLTJ RF VR-4, Passive Rev. 4

-B - . __. .

A' SYSTEM: STEAM GENERATOR DRAHING NO: M-532 Sh 1 1

VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FREO REMARK HV-20515 D12 Main Feed to SG 205B 2 B 20 GT M0 O FSTC CS VPI RF Main Feed to SG 205A HV-20516 H12 2 B 20 GT M0 O FSTC CS VPI RF HV-20529 D8 Main Feed Stop to 2 B 20 GT M0 O FSTC CS SG 205A VPI RF HV-20530 H9 Main Feed Stop to 2 B 20 GT M0 0 FSTC CS SG 205B VPI RF HV-20577 C7 Emerg Feed to SG 205A 2 B 6 GT M0 C FSTO Q FSTC Q VPI RF HV-20578 G10 Emerg Feed to SG 2058 2 8 6 GT M0 C FSTO Q FSTC Q VPI RF HV-20581 B7 Emerg Feed to SG 205A 2 B 6 GT M0 C FSTO Q FSTC Q VPI RF HV-20582 H10 Emerg Feed to SG 205B 2 8 6 GT M0 C FSTO Q FSTC Q VPI RF HV-20611 J12 SG Dr Boost Pump Disc NC A 4 GL M0 C FSTC Q SLTJ RF VR-4 VPI RF Rev. 4

-B . - .

SYSTEM: STEAM GENERATOR DRAWING NO: M-532 Sh I' VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FREO REMARK HV-31826 C3 Aux FP Crossover 3 8 6 GT M0 O FSTO Q FSTC Q VPI RF HV-31827 G3 Aux FP Crossover 3 8 6 GT M0 O FSTO Q FSTC Q' VPI RF Rev. 4

-B .. p

-.,==7;y g SYSTEM: STEAM GENERATOR DRANING NO: M-532 Sh 2 VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARK FHS-102 J3 Stm Gen Cleaning Iso NC A 10 GT MAN C SLTJ RF Passive HV-20609 H11 Stm Gen 205A Drain 2 A 1.5 GL M0 C FSTC Q

~

SLTJ RF VR-4 VPI RF 1

1 Rev. 4

-B . _ .- - . _ . , -., , ._. --- . _ - . - ,, - .

a. 4 W

s*

SYSTEM: STEAMGEiERAiOR DRAMING NO: M-532 Sh 3

_yALVE COOR FUNCTION CLA5S CAT SIZE TYPE ACT POS RE0MT FREO REMARK FMS-080 J2 Sta Gen Booster Pump NC A 4 GT MAN C SLTJ RF' Passive Disch HV-20610 H11 Stm Gen 2058 Drain 2 A 1.5 GL M0 C FSTC Q

~ SLTJ RF VR-4 VPI RF l

\

Rev. 4

-B 4

SYSTEM: HIGH PRESSURE FEEDHATER HEATER DRANING NO: M-533. Sh 3 VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REHARK FHS-047 D9 Aux FP 318 Disch 3 C 6 CK SA C FSTO Q

-- FSTC Q FHS-048 H9 Aux FP 319 Disch 3 C 6 CK SA C FSTO Q

-- FSTC Q FHS-049 C9 Aux FP 318 Min Flow 3 C 2.5 CK SA C PE0 0 FSTO RF VR-17 FMS-050 G9 Aux FP 319 Min Flow 3 C 2.5 CK SA C PE0 0 FSTO RF VR-17 Rev. 4

-B - . . - - _ - ._ ,

Y SYSTEM: CONDENSER DRANING NO: M-536 VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FREO REMARK MCM-059 I2 CST disch to Aux FP 3 C 8 CK SA C FSTO Q' P-318 MCM-060 I2 CST disch to Aux FP 3 C 8 CK SA C FSTO Q P-319 PSV-31800 J3 Aux FP P-318 Suct Re1 3 C .75 PSV' SA C VSP SY PSV-31900 J3 Aux FP P-319 Suct Re1 3 C .75 PSV SA C VSP SY PSV-35804 G2 CST Relief /Vac Bk 3 C 2 PSV SA C . VSP SY PSV-35805 G3 CST Relief /Vac Bkr 3 C 2 PSV SA C VSP SY s

Rev. 4

-B .__

SYSTEM: AUXILIARY STEAM DRAHING NO: M-537. Sh 3 VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FREO REMARK .!

~

ASC-048 E10 Aux. Steam to RB-Otbd 2 A 1 GT MAN C SLTJ RF VR-4, Pe.ssive ASC-049 E12 Aux. Steam to RB-Inbd 2 A/C 1 SCK MAN C SLTJ RF VR-4, Passive Rev. 4

-B-34--

APPENDIX A SUHHARY INSERVICE TESTING PROGRAM

- PUMPS -

l l

t i

l l

l l

SYSTEM: COMPONENT COOLING MATER DRAWING N0: M-543. Sh 1 VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FREO REMARK CCH-036 H11 CCW Supply to RB-INB0 2 A/C 12 SCK MAN O FSTC CS SLTJ RF VR-4 SFV-46014 J11 CCH Supply to RB-0TBD 2 A 12 BF A0 0 FSTC CS SLTJ RF VR-4 VPI RF SFV-46203 H12 CCH Ret FR Rd - INBD 2 A 12 BF M0 O FSTC CS

~~

SLTJ RF VR-4 VPI RF SFV-46204 J12 CCW Ret FR RB - OTB0 2 A 12 BF A0 0 FSTC CS

~~

SLTJ RF VR-4 VPI RF Rev. 4

-B , ,_ _

SYSTEM: COMPONENT COOLING MATER DRAWING NO: M-543. Sh 4 VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS REONT FREO R94 ARK CCH-194 B11 CCW Supply to CRD-INB0 2 A/C 3 SCK MAN O FSTC CS SLTJ RF SFV-46906 D11 CCW Supply to CRD-0TBD 2 A 3 GL A0 0 FSTC CS SLTJ RF VPI RF SFV-46907 Bil CCH Ret Fr CRD-INBD 2 A 3 GT M0 O FSTC CS SLTJ RF VPI RF SFV-46908 Dil CCH Ret. FR CRD-0TBD 2 A 3 GL A0 0 FSTC CS SLTJ RF VPI RF Rev. 4

-B - - - , . . - .

SYSTEM: NUCLEAR SERVICE RAW HATER DRAHING NO: M-544 VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARK PSV-47205A E4 Pump 472A Vac Bkr 3 C 2 PSV SA C VSP SY PSV-47205B E8 Pump 472B Vac Bkr 3 C 2 PSV SA C VSP SY i

Rev. 4 i

-B ,

w -- e t- , , - - _- e m o + - - ,e-- m---s-- ~ ym- sw-- r--

SYSTEM: NUCLEAR SERVICE COOLING HATER ORANING N0: M-545 VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FREO REMARK SFV-26016 H4 Dec HT Rem Clr 2608 3 8 12 BF M0 C FSTO Q Inlet VPI RF SFV-26017 G4 Dec HT Rem Clr 260A 3 8 12 BF M0 C FSTO Q Inlet VPI RF SFV-26018 I4 Dec HT Rem Clr 2608 3 8 12 BF M0 C FSTO Q Outlet VPI RF SFV-26019 F4 Dec HT Rem Clr 260A 3 8 12 BF M0 C FSTO Q Outlet VPI RF PSV-48411 A4 Nuc Syc C1g Ntr Surge 3 C 3 PSV SA C VSP SY Tank PSV-48412 All Nuc Syc C1g Ntr Surge 3 C 3 PSV SA C VSP SY Tank PSV-48415 A4 Nuc Svc C1g Ntr Surge 3 C 3 PSV SA C VSP SY Tank Vac Bkr PSV-48416 All Nuc Syc C1g Htr Surge 3 C 3 PSV SA C VSP SY Tank Vac Bkr Rev. 4

-B _. - - ..

SYSTEM: NUCLEAR SERVICE COOLING MATER DRANING NO: M-545 VALVE COOR FUNCTION _ CLASS CAT SIZE TYPE ACT POS RE0MT FREO REMARK SFV-50005 F6 Rx Bldg. Clg "anit 2 B 10 BF M0 C FSTO Q 500A Inlet VPI RF SFV-50006 H6 Rx Bldg. C1g Unit 2 8 10 BF MO C FSTO Q 5006 Inlet VPI RF SFV-50007 G6 Rx Bldg. C1g Unit 2 8 10 BF M0 C FS10 0 500C Inlet VPI RF SFV-50008 16 Rx Bldg. C1g Unit 2 B 10 BF MD C FSTO Q 5000 Inlet VPI RF SFV-50009 E6 Rx Bldg. Cig Unit 2 8 10 BF M0 C FSTO Q 500A Outlet VPI RF SFV-50010 I6 Rx Bldg. C1g Unit 2 B 10 BF M0 C FSTO Q 5006 Outlet VPI RF Rev. 4

-B _ ._ - - _ _ . _ _ - -

g K

R A

M E

R O

E R F F F QR QR T O O N TI TI O SP SP E FV FV R

S O C C P

D D T M M C

A E F F P B B Y

T 5 E 4 Z 0 0 5 I 1 1

- S M 4 -

0 4

T v O A 8 8 e2 N C R -

G N

I S N S A A 2 2 R L D C R

E t t T i i A n n M U U G g g N 1 t 1 t I Ce Ce L l O N .t gu

.l gu t

O O C I dO dO T l l E C BC B0 C N 0 0 I U x0 x0 V F R5 R5 R

E S

R A e E n 6 6 L n F J C e U

N 1 2 1 1

0 0 M E 0 0 E V 5 5 T L - - -

S A V V Y V F F S S S l l l

SYSTEM: TDI DIESEL FUEL OIL DRANING NO: M-547

. VALVE C00R FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMMtK DFO-318 84 Diesel Fo Pump NC C 2 CK SA C FSTO Q 1088 Disch FSTC Q DFO-319 86 Diesel Fo Pump NC C 2 CK SA C FSTO Q 108A Disch FSTC Q DFO-322 B4 Diesel Fo Pump NC C 2 CK SA C FSTO Q 108D Disch FSTC Q DFO-323 B6 Diesel Fo Pump NC C 2 CK SA C FSTO Q 108C Disch FSTC Q l

e Rev. 4

• -B -. - - =.-- . . . . - , - - . . . - - - . . . - . - .-. .-- . . - . - - - . - ..- - .. _

SYSTEM: REACTOR BUILDING HEATING. VENTILATING AND AIR CONO. DRANING NO: N-SSI VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FRE0 REMARK HGS-005 Gil H2 Purge Intake NC A 1 GT MAN C SLTJ RF Passive HGS-010 Fil H2 Purge Intake NC A 3 GT kWI C SLTJ RF Passive HGS-012 C11 ILRT Test Conn NC A .75 GL MAN C SLTJ RF Passive HGS-013 C12 ILRT Test Conn NC A .75 GL MAN C SLTJ RF Passive HV-53617 J14 H2 Purge Inbd Iso NC A 2 GT S0 C FSTC Q SLTJ RF VPI RF HV-53618 I14 H2 Purge Inbd Iso NC A 2 GT S0 C FSTC Q SLTJ RF VPI RF

~

HV-53620 H2 H2 Recombiner NC A 4 GT M0 C SLTJ RF Passive HV-53621 H2 H2 Recombiner NC A 4 GT M0 C SLTJ RF Passive HV-53622 Hi H2 Recombiner NC A 4 GT M0 C SLTJ RF Passive HV-53623 H1 H2 Recombiner NC A 4 GT M0 C SLTJ RF Passive o HV-70040 J8 H2 Mon. Return MC A 1 GT S0 C FSTC 0 SLTJ RF VPI RF HV-70041 J8 RB Air Sample NC A 1 GT SO C FSTC Q

~~

SLTJ RF VR-4 VPI P.F Rev. 4

~~

-B ---- _-, -_- . _ _ . -_ . _ _

'l .

SYSTEM: REACTOR BUILDING HEATING. VENTILATING AND AIR CONO. DRANING MO: M-551 VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS' REONT FREO REMMK HV-70042 J8 R8 Air Sample NC A 1 GT SO C FSTC Q

~

SLTJ RF VR-4 VPI RF HV-70043 III Pass Return NC A 1 GT SO C FSTC Q ,e i -

SLTJ RF VR-4

VPI RF i

HV-70044 511 Pass Return NC A 1 GT SO C FSTC Q SLTJ RF VR-4 VPI RF MV-70045 J11 Pa:s Atmos. Sample NC A 1 GT SO C FSTC Q SLTJ RF VR-4 VPI RF HV-70046 J1! Pass Atmos. Sample NC A 1 GT SO C FSTC 0

+ SLTJ RF VR-4 VPI RF

~

HV-70047 18 H2 Mon. Return NC A 1- GT SO C FSTC Q' -,

SLTJ RF ,

, VPI RF SFV-53503 Eli R8 Purge Inlet-Otbd NC A 66 SF A0 C' FSTC ' CS SLTJ RF VR-4 VPI RF i

i SFV-53504 Fil RB Purge Inlet-Inbd NC A 66 BF MO' -C FSTC . CS SLTJ RF VR-4

'VPI RF 3

Rev. 4  :

e

- -B I

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

O- 4 SYSTEM: REACTOR BUILDING HEATING. VENTILATING AND AIR COND. DRANING NO: M-551 VALVE C00R FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARK __

SFV-53603 H11 RB furge Inlet-Inbd NC A 12 BF M0 O FSTC- Q

~

SLTJ RF VR-4 VPI RF SFV-53604 Fil RB Purge Outlet-Inbd MC A 66 SF AG C' FSTC CS SLTJ RF VR-4 VPI RF SFV-53605 Fil RS Purge Outlet-Inbd MC A 66 BF M0 C FSTC CS SLTJ RF VR-4 VPI RF SFV-53610 H11 RB Purge Inlet-Inbd NC A 12 BF A0 0 FSTC Q

~

SLTJ RF VR-4 VFI RF SFV-53612 Fil From H2 Purge Ex Bir NC A 1 GT A0 C FSTC Q "B" SLTJ RF VPI RF SFV-53613 G12 From H2 Purge Ex Bir NC A 1 GT A0 C- FSTC  ;

P SLTJ RF VPI RF SFV-53615 H14 H2 Purge Exh Isol NC A 2 GT S0 C FSTC Q SLTJ RF VPI RF SFV-53616 114 H2 Purge Exh Isol NC A 2 GT SO C FSTC Q SLTJ RF VPI RF Rev. 4

_ _s-44_

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

T :: ::

SYSTEM: COOLANT RADMASTE SYSTEM [)_RANING NO: M-560. Sh 3

- VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARK SFV-60001 B3 Rx Cool Vent Hdr Isol 2 A 3 GT M0 C FSTC Q SLTJ RF VR-19 VPI RF SFV-60002 84 Rx Cool Vent Hdr Iso 2 A 3 GL A0 C FSTC 0 SLTJ RF VPI RF SFV-60003 E4 Rx Cool Dr Hdr Iso 2 A 6 GT M0 C FSTC Q SLTJ RF VR-19 VPI RF SFV-60004 ES Rx Cool Dr Hdr Iso 2 A 6 GL A0 C FSTC Q SLTJ RF VPI RF Rev. 4

-B , g- < - .--.ge- - - -+w e m.--w.og-rr, , - - - - - .,

- --+p- - g & * ' - m- - - +-- -* * -

---y .-e --

• J SYSTEM: MISCELLANEOUS LIOUID RADNASTE DMNING 100: M-561. Sh 3 VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARK SFV-66308 F2 Rx Bldg Sump Pump Disc NC A 4 GT M0 C FSTC Q SLTJ RF VPI RF SFV-66309 G2 Rx Bldg Sump Pump Disc NC A 4 GT M0 C FSTC Q SLTJ RF VPI RF

=

4 i

Rev. 4

-E 4 --

- . - - . , , - + =r,- - --ew ,--y+ - - . , , , - - - - - - - - ,---r- .r , , - - -- , = ~ , - - - . - -->,,+-r -- --

--. . i _ . - . . - , . .

SYSTEM: REACTOR COOLANT CHEMICAL ADDITION AND SAMPLING DRAWING N0: M-570 VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FREO REMARK BNS-033 M8 Boric Acid Pump 705A NC C 2 CK SA C FSTO Q Disc BNS-034 H9 Boric Acid Pump 7058 NC C 2 CK SA C FSTO Q ~~ ~

Disc BNS-035 18 Boric Acid Pump 705A 2 8 2 GT N C/0 FSTO Q Isoittion BNS-036 J9 Boric A(.id Pump 705B 2 8 2 GT MAN C/0 FSTO Q Isolation BNS-040 J5 Boric Acid Disch to 2 B 2 GL MAN C FSTO Q HPI Pumps BNS-041 J5 Boric Act:1 Disch to 2 8 .75 GL MAN C FSTO Q Decay HT hem Sys.

BNS-054 J5 Boric Acid Disch to 2 8 2 GL MAN C FSTO Q P-2388 RSS-500 C3 Sample to Makeup 2 A .75 GT MAN C SLTJ RT Passive PSV-70505 J8 Boric Acid Pump Disch NC C .75 PSV SA C VSP SY Relief SFV-70001 C2 Press Liq Sample-Inbd 1 A. .75 GT MD C FSTC Q SLTJ RF VPI RF SFY-70002 C3 Press Sample-Otbd 2 A .75 GL A0 C FSTC Q SLTJ RF -

VPI RF Rev. 4

-B 4

SYSTEM: REACTOR COOLANT CHEMICAL ADDITION AND SAMPLING DRANIE NO: M-570 VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMMtK SFV-70003 C2 Press Vapor Sample- 1 A .75 GT MD C FSTC Q Inbd SLTJ RF VPI RF SFV-72501 D2 PRT Cas Sample-Inbd 2 A .75 GT M0 C FSTC Q

~

SLTJ RF VR-4 VPI RF SFV-72502 E2 PRT Gas Sample-Otbd 2 A .75 GL M0 C FSTC Q

• SLTJ RF VR-4 VPI RF 4

k Rev. 4 48-

- . - - - _ . -=- ..- - . . . _ .

' - - - " m--'a.-...m,2z,,, -

SYSTEM: TURBINE PLANT SAMPLI E DRAMING NO: M-573 VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS RE(MT FREO' *EMMK HV-20587 83 Sta Gen Sample 2 8 .75 GT A0 C FSTC Q l

VPI RF i HV-20588 D4 Stm Gen Sample 2 8 .75 GT A0 C FSTC Q.

VPI RF HV-20593 F3 Sta Gen Sample 2 8 .75 GT A0 C FSTC Q VPI RF HV-20594 F2 Stm Ce9 Sample 2 8 .75 GT A0 C FSTC Q VPI RF i

.I Rev. 4 49-

._. _ . ._... _ ,_ _ _ ._._,., _ -. _.-- ._ _ _ ___. . _ _ -. - -~,_.._ .

SYSTEM: BRUCE G4-DIESEL OIL DRANIM NO: 44')2

. VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMMK DFO-017 H9 Diesel F0 Pump NC C 2 CK SA C FSTO Q 888A Disch FSTC 0-DFO-018 H9 Diesel F0 Pump NC C 2 CK SA C FSTO Q 8888 Disch FSTC Q DFO-019 H11 Diesel F0 Pump NC C 2 CK SA C FSTO Q 888C Disch FSTC Q DFO-020 H11 Diesel F0 Pump NC C 2 CK SA C FSTO Q .2 888D Disch FSTC Q E

l e .ig. - .-a=- _ --i+---e.+ *-m--- - - - --*=we - - - *- ==+--h

- -B . _ - . _ , - . . _ . - - - . _- _ __ _ ..

- SYSTEM: EMERGENCY DIESEL GENERATOR DRAHING NO: M-583 VALVE C00R FUNCTION CLASS CAT SIZE TYPE ACT- POS RE0MT FREO REMARK EGS-010 C7 Air Comp C-889A Disch NC C 1.5 CK SA C FSTC Q'

__. s EGS-011 C7 Air Comp C-891A Disch NC C 1.5 CK SA C FSTC Q EGS-021 C7 Air Comp C-8898 Disch NC C 1.5 CK SA C. FSTC Q.

EGS-022 C7 Air Comp C-891B Disch NC C 1.5 CK SA C FSTC Q FY-89025 E6 Emer Diesel G886A NC B 1.5 GL S0 C FSTO Q VR-21 Air Start FY-89026 E6 Emer Diesel G886B NC B 1.5 GL S0 C FSTO Q VR-21 i

Air Start FY-89027 F6 Emer Diesel G886A NC B 1.5 GL S0 C FST0 Q VR-21 Air Start FY-89028 E6 Emer Diesel G886B NC B 1.5 GL S0 C FSTO Q VR-21 Air Start l

FV-89029 E6 Air Supply to NC B 1.5 GL A0 C FSTO Q VR-21 l Y-890-1C&lD FV-89030 E6 Air Supply to NC B 1.5 GL A0 C .FSTO Q .

VR-21 .

l Y-890-1E&lf 1

i FV-89031 E6 Air Supply to NC B 1.5 GL A0 C FSTO Q VR-21 Y-890-1A&lB

~

FV-89032 E6 Air Supply to NC B 1.5 GL A0 C FSTO Q VR-21 j Y-890-1G&lH

_ _ _ _ _ _ _ _ __ _ . . _ _ _ _ _ _ _ _ _ _ _ _ Rey, 4 _ ._ _ _ . . _ _ _ . a_-

- ~B . . -. . . -- , . - -- - . . .

1 1

- SYSTEM: TDI DIESEL GENERATOR - TRAIN "A" DRAHING NO: M-585. Sh 1 COOR FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARK VAULE EGS-843 D3 EDG G-100A Air Start NC C 3 CK SA C FSTO Q FSTC Q EGS-845 E3 EDG G-100A Air Start NC C 3 CK SA C FSTO Q FSTC Q HV-10051A E3 EDG G-100A Air Start NC B 3 CK SO C FSTO Q VR-21 HV 10051B D3 EDG G-100A Air Start NC B 3 CK S9 C FSTO Q VR-21 l

Rev. 4

- -B L---- - - --- ,

~

SYSTEM: TDI DIESEL GENERATOR - TRAIN "A" DRANING NO: M-585. Sh ?m VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FRE0 REMARK EGS-565 F3 Receiver V-101 C Ir.lat NC C 1.5 CK -SA C FSTC RF. VR-23 EGS-567 F4 Receiver V-101 A Inlet NC C 1.5 CK SA- C FSTC RF- VR-23

(

___ _ -_ ..- .~_ R e v . 4 - - - -. --- --- - - - - - - . . .

-B _ _ _ _ __ ..

• SYSTEM: TDI DIESEL GENERATOR - TRAIN "B" DRAHING NO: M-585. Sh 3 VALVE C00R FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT- FREO REMARK EGS-844 D3 EDG G-100B Air Start NC C 3 CK SA C FST0 0 FSTC Q EGS-846 E3 EDG G-1008 Air Start NC C 3 CK SA C FST0 Q i FSTC Q HV-10050A E3 EDG G-1008 Air Start NC B 3 GL S0 C FSTO Q VR-21 HV-10050B D3 EDG G-1008 Air Start NC B 3 GL S0 C FSTO Q VR-21 i

1 4

Rev. 4

-B . _ _ -

. _ ____.=--_____

SYSTEM: TDI DIESEL GENERATOR - TRAIN "B" DRAHING NO: M-585. Sh 4 VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FREO REMARK EGS-564 F3 Receiver V-101D Inlet NC C 1.5 CK -SA C FSTC RF VR-23 EGS-566 F4 Receiver V-101B Inlet NC C 1.5 CK SA C FSTC RF VR-23 l

4 Rev. 4

-B _

SYSTEM: PLANT AIR DRAHING NO: M-590. Sh 1 VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS REOMT FREO REMARK SAS-052 E13 Service Air Supply NC A 2 GT MAN C SLTJ RF Passive SAS-054 E13 Service Air Supply NC A 2 GT MAN C SLTJ RF Passive I

i Rev. 4

~~ -B .

SYSTEM- AUXILIARY GAS DRAHING NO: H-591. Sh 1 VALVE C00R FUNCTION CLASS CAT SIZE TYPE ACT POS RE0HT FREO REMARK NGS-011 F12 N2 Supply to PRT NC A/C 1 SCK MAN C SLTJ RF Passive NGS-017 H12 N2 Sup to Stm. Gen NC A 2 GL MAN C SLTJ RF VR-4, Passive NGS-018 Il2 N2 Supply to Stm. Gen NC A/C 2 SCK MAN C SLTJ RF VR-4, Passive SFV-92520 Fil N2 Supp to PRT NC A 1 GL A0 C FSTC Q SLTJ RF VPI RF 1

l Rev. 4

-- -B SYSTEM: MISCELLANEOUS HATER DRAHING NO: M-593. Sh 2 VALVE COOR FUNCTION CLASS CAT SIZE TYPE ACT POS RE0MT FREO REMARK DMH-024 Il0 Misc Hater to RB 2 A 3- GT MAN C SLTJ RF Passive DMW-025 Ill Misc Hater to RB 2 A/C 3 SCK MAN C- SLTJ RF Passive i

l l

l l

Rev. 4

-B Appendix C COLD SHUT 00HN VALVE TESTING JUSTIFICATION i

1

)

I

COLD SHUTDOHN TEST JUSTIFICATION Reactor Coolant System (M-E20)

HV-20533 - Steam Generator E-205A Hi-Point Vent HV-20534 - Steam Generator E-205B Hi-Point Vent HV-20579 - Steam Generator E-205A Hi-Point Vent HV-20580 - Steam Generator E-205B Hi-Point Vent HV-21522 - Pressurizer Hi-Point Vent HV-21528 - Pressurizer Hi-Point Vent Opening any of these valves during normal operation would reduce the isolation of the reactor coolant system to only one valve which could result in leakage into the reactor building. In addition, during plant operation, power to the valve actuators is removed per Rancho Seco Technical Specifications Section 3.1 (Appendix R).

Makeuo and Purification (M-521)

SFV-22005 - Letdown Isolation to Heat Exchanger E-220A SFV-22006 - Letdown Isolation to Heat Exchanger E-2208 & C SFV-22009 - Letdown Outboard Containment Isolation SFV-22023 - Letdown Inboard Containment Isolation SFV-22025 - Letdown Isolation from Steam Generator 205A t Valves SFV-22009, SFV-22023, and SFV-22025 and either SFV-22005 or SFV-22006 l are normally open during plant operation to provide continuous letdown and l reactor coolant purification flow. Closing any of these valves would interrupt letdown flow and result in fluctuations in pressurizer level and a potential plant trip or forced shutdown.

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! SFV-24004 - Reactor Coolant Pump Seal Water Return SFV-24013 - Reactor Coolant Pump Seal Hater Return These valves are normally open to provide a return path for reactor coolant l

pump seal water. Closure of these valves during pump operation would result l in a loss of seal water flow and an imbalance in the interstage pressures within the seal. This could result in seal failure and ultimately plant shutdown.

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Rev. 4

-C l l

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COLD SHUTDOHN TEST JUSTIFICATION (Continued)

SFV-23508 - Makeup Tank Isolation Valve During plant operation, this valve must remain open to supply water to the makeup pump. Closing this valve would result in potential damage to the makeup pump and loss of RCP seal injection and pressurizer level control flow with the potential for a plant trip or forced shutdown.

- SFV-23G04 - Makeup Line Isolation Valve During plant operation, this valve is normally open to permit automatic pressurizer level control via LV-21503. Failure of SFV-23604 in the closed position would require operator action to manually control pressurizer level. During this evolution, a transient in pressurizer icvel could occur which could lead to a plant trip.

SFV-23616 - Reactor Coolant Pump Seal Hater Supply This valve is normally open to provide a flow path for injection water to the reaction coolant pumps. Closure of this valve during pump operation would result in a loss of seal water flow with the probability of seal failure and subsequent plant shutdown.

- SIM-019 - RCP 210A Seal Hater Supply SlH-020 - RCP 210B Seal Water Supply S1H-021 - RCP 210C Seal Water Supply S1H-022 - RCP 2100 Seal Water Supply Closure of these valves during plant operations would stop seal water flow to their respective reactor coolant pump seal and would ultimately result in seal failure. Furthermore, these valves are located inside the secondary shield walls and this access is limited.

Rev. 4

-C COLD SHUTDOHN TEST JUSTIFICATION (Continued)

Decay Heat Removal (M-522)

DHS-015 - Decay Heat Removal Discharge to RCS DHS-016 - Decay Heat Removal Discharge to RCS RCS-001 - Decay Heat Removal / Core Flood Discharge to RCS RCS-002 - Decay Heat Removal / Core Flood Discharge to RCS Neither the decay heat removal pumps nor the core flow tanks are capable of overcoming reactor pressure during operation which would be required to

- exercise these valves.

- DHS-017 - Decay Heat Leakage to CFT "A" DHS-018 - Decay Heat Leakage to CFT "B" These valves are inside containment and are'not accessible during plant

- operation. They will be verified closed by handwheel operation.

DHS-059 - Decay Heat Removal Supply to Pressurizer Spray In order to exercise this valve during plant operation, spray flow must be initiated from the high-pressure injection system into the pressurizer.

Initiating flow into the pressurizer in this manner would subject the spray nozzle to unneccessary thermal shocking and potential damage.

HV-20001 and HV-20002 - Decay Heat Removal Supply Valves These valves are normally closed to isolate the decay heat removal system from the reactor coolant system. Opening either of these valves during power operation would reduce the level of protection of the decay heat removal system from overpressurization. In addition, these valves are electrically interlocked to prevent opening when RCS pressure is greater than 255 psig.

HV-20003 - Decay Heat Removal Dump to Sump In order to open HV-20003 without draining the decay heat removal piping, DHS-461 must be closed. DHS-461 is not accessible while the plant is in operation, thus, testing of HV-20003 is not practical during operation.

Rev. 4

-C COLD SHUT 00HN TEST JUSTIFICATION (Continued) 1

- HV-26105 - P-261 Suction from Rx Building Sump HV-26106 - P-261 Section from Rx Building Sump To preclude flooding into the Reactor Building sump when either of these two valvos is operJd, the manual isolation valve (s) at the borated water storage tank must be closed. This, in turn, renders one train of each of the decay heat, safety injection, and containment spray systems inoperable simultaneously. This is considered imprudent during normal (power) plant

- operation.

HP and Auxiliary Turbines (M-530)

TV-1 through TV Main Turbine Throttle Valves Exercising these valves in the normal, fail-safe manner requires initiating a main turbine trip which would result in an inacceptable plant transient.

There is, however, a feature on the valve operating mechanism that provides the capability of slow exercising of each valve individually. Thus, on a quarterly basis, each valve will be slowly exercised to its closed position.

Since this is a special mode of operation, the stroke time is insignificant

- and will not be measured. At cold shutdown, the valves will be full stroked

- at normal speed and stroke times will be measured.

HV-20597 - Main Steam Supply to Reheaters A and C HV-20598 - Main Steam Supply To Reheaters B and D These valves are normally open to provide reheat steam for the turbine cycle. Closure and reopening of these valves would interrupt the steam supply to the reheaters and could result undesirable and potentially damaging pressure and thermal transients on plant equipment. In addition, there is some question regarding the capability of the installed motor-operators to reopen the valves with the plant at power.

Rev. 4

-- -C COLD SHUTDOHN TEST JUSTIFICAIl0E (Continued)

PV-20561 - Main Turbine Bypass Valve PV-20563 through PV-20566 - Main Turbine Bypass Valves These valves are normally closed. In order to test them without subjecting the plant to unnecessary transients, each would be required to be isolated from the main steam lines. During the period of time that a valve is isolated, the ability to respond to plant upset conditions such as reactor or turbine trips is diminished. Thus, performing such tests during plant operation at power is not considered prudent.

- PV-20562A through C - Atmospheric Steam Dumps PV-20571A through C - Atmospheric Steam Dumps These valves are normally closed. Since they are electrically interlocked such that the three (3) valves on each main steam header must open simultaneously, this would require isolating the "A" valves to prevent unnecessary transients to the steam dumps piping. During the period of time that the valves are isolated, the ability to respond to plant upset condition such as reactor and turbine trips is diminished. Thus, performing such tests

- during plant operation at power is not considered prudent.

MSS-051 and MSS-052 Steam Supply to Auxiliary Feedwater Pump.

In order to verify closure of these valves, the supply line to the auxiliary feedwater pump must be isolated and the line pressurized with air. This would also require depressurization of the related steam generator.

HV-20521 and HV-20522 - Isolation Valves to Turbine Bypass Valves.

These valves are normally open. Closing these valves would depressurize and possibly cool the downstream piping. Due to the length of piping downstream of these valves, upon reopening, a pressure transient could result with the potential for damaging the downstream piping or associated components.

Rev. 4

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-C .-- - -_-- _ _ _ _ _ -_______

i COLD SHUTDOHN TEST JUSTIFICATION (Continued)

Steam Generator (M-5321 FV-20525 Main Feedwater Iso to Steam Gen 205A FV-20526 Main Feedwater Iso to Steam Gen 205B FV-20575 Main Feedwater Bypass to Steam Gen 205A FV-20576 Main Feedwater Bypass to Steam Gen 205B HV-20529 Main Feedwater Stop to Steam Gen 205A HV-20530 Main Feedwater Stop to Steam Gen 205B These valves are located in the main feedwater supply lines to the steam generators. Closing or opening any these valves while operating at power could result in a loss of steam generator level control and a plant trip.

FHS-061 - Emergency Feedwater Check to Steam Gen 205A FHS-062 - Emergency Feedwater Check to Steam Gen 2058 Exercising these valves requires injection of feedwater from the auxiliary feedwater pumps into the steam generators. With the reactor plant at operating temperature, injection of cold water from the auxiliary feedwater pumps would result in thermal shocking of the auxiliary feedwater nozzles and possibly undesirable reactor plant transients.

HV-20515 and HV-20516 - Main Feedwater Stops to Steam Generators 205 A and B Closing either of these valves during plant operation will interrupt makeup flow to the respective steam generator resulting in a loss of steam generator water level control and a probable plant trip.

Comoonent Coolina Hater System (M-543)

I CCH-036 & SFV-46014 - Cooling Hater Supply to Reactor Building l

SFV-46203 & SFV-46204 - Cooling Hater Return From Reactor Building CCH-194 & SFV-46906 - Cooling Hater Supply to Control Rod Drives SFV-46907 & SFV-46908 - Cooling Hater Return From Control Rod Drives l

, C!c:ure of any of these valves during plant operation at power will interrupt l cooling to the reactor coolant pumps, letdown coolers, or the control rod l drive mechanisms--depending on which valves are closed. This would likely l cause damage to associated equipment and components that require continuous cooling.

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Rev. 4

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-C i

i COLD SHUTDOHN TEST JUSTIFICATION- (Continued)

Reactor Buildina Heatina. Ventilatina and Air Cond System (M-551)

SFV-53503 and SFV-53504 - Reactor Building Purge Inlet Valves SFV-53603 and SFV-53604 - Reactor Building. Purge Outlet Valves These valves must remain closed and electrically disabled during plant operation per Rancho Seco Technical Specification 3.6.7.

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w - - , - , - _ _ . , . - . _ , . . - - _ _ _ , . , _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ . _ _ _ _ _ _ _ ,_ _ _ _ _ _ _ _

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Appendix 0

SUMMARY

OF pgogggy cypyggg

SUMMARY

OF PROGRAM CHANGES Summary of Changes: Second 10-Year Inservice Testing Program -

Revision 4 vs. Revision 3 (Submitted 6/25/87)

Pumps:

1. Corrected typographical error in Table 2.1 of Relief Request PR-2.

2. Revised PR-3 to reflect a more general description of vibration instrumentation.

3. Revised PR-4 to include a required action range (high) above 110 percent of the reference value.

4. Provided additional justification in the basis of PR-7.

5. Added diesel fuel oil pumps to Relief Request PR-8 and added requirement to calculate suction pressure during each test.

6. Deleted Relief Requests PR-9 and PR-12.

7. Clarified refueling outage reference in PR-10.

8. Specified pumps related to Relief Request PR-ll and clarified instrument requirements.

9. Added Relief Request PR-13 to eliminate the 5-minute run time requirement for the diesel fuel oil pumps.

10. Added Relief Request PR-14 to eliminate measuring the vibration of the submerged diesel fuel oil pumps.

11. Added PR-15 for fuel oil transfer Pumps 888A-D.

12. Added the diesel fuel oil pumps to the Program.

13. Added a note to Appendix A for measuring the speed of the dual drive auxiliary feedwater pump during motor operation and revised to reflect applicable reliefs.

Valves:

1. Clarified paragraph 3.1.6 with regards to the administration of cold shutdown testing.

2. Added Paragraph 3.1.9 discussing stroke time acceptance criteria and evaluation requirements.

3. Added Paragraph 3.1.10 reiterating the NRC position with respect to verifying stop-check valve position utilizing stem operation.

Rev. 4

- -D _. . . - _.

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U

SUMMARY

OF PROGRAM CHANGES (Continued)

4. Added Paragraph 3.1.11 explaining NRC interpretation of IWV-3522 with respect to valve disassembly and inspection.

5. Revised Relief Request-VR-1 to relate to solenoid and the main turbine stop/ throttle valves only and to reference IHV-3417 specifically.

6. Revised Relief Request VR-2 to explain restart requirements should a valve enter the alert range with respect to stroke time, during cold shutdown.

7. Deleted Relief Request VR-3.

8. Revised Relief Request VR-4 to specifically require evaluation in accordance with IHV-3426 and IWV-3427. Specified valves to which this applies.

9. Clarified basis of Relief Request VR-7.

10. Revised VR-8 to reflect NRC position for testing stop/ check valves.

11. Expanded justification in the basis for Relief Request VR-10.

12. Alternate testing of Relief Request VR-11 is rewritten.

13. Deleted Relief Request VR-12.

14. Expanded basis of Relief Request VR-13 and revised the alternate testing to reflect NRC policy.

15. Revised alternate testing of Relief Request VR-14 to reflect NRC policy.

16. Expanded basis of Relief Request VR-15 and revised alternate testing to reflect NRC policy.

17. Deleted Relief Request VR-18.

18. Relief Request VR S,7ecified applicable valves and clarifie'J alternate testing requirement.

I 19. Added Relief Request VR-21 for measuring stroke time of diest.1 generator

! air start valves.

L 20. Added VR-22 for testing of PORV (PSV-21511) each refueling.

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21. Added VR-23 for sample disassembly of TDI air start receiver check valves.

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SUMMARY

OF PROGRAM CHANGES (Continued) g - 22. (M-520) Added to'the PORV and test requirements.

23.- (M-521) Changed SFV-22009 from Globe to Gate.

24. (M-521) Change the frequency of exercising the following valves-to cold shutdown:

SFV-23604 SIM-019 SIM-020 SIM-021 i

SIM-022

25. (M-521) Revised to reflect applicable reliefs.

26. (M-521) Changed the position of SIM-002 to open vs closed.

27. (M-521) Added a requirement for verifying closure of SIM-036 and SIM-037 during cold shutdown. <

28. (M-521) Added valve position for SFV-23508 thru SFV-23812.

29. (M-522) Changed the frequency of exercising the following valves to cold shutdown:

DHS-017 DHS-018 HV-26105 HV-26106

30. (M-522) Revised to reflect applicable reliefs

31. (M-522) Changed testing requirements for HV-26011 - valve de-energized in closed position.

32. (M-522) Deleted valves HV-26037 and HV-26038 from Program - not within the scope of IHV-1100.

33. (M-522) Recategorized HV-26105 and HV-26106 to Category A, added leak -

test requirement, and clarified pump identification.

34. (M-524) Revised to reflect applicable reliefs.

35. (M-530) Chsnged the frequency of exercising the following valves to cold shutdown as justified on page CS:

PV-205628 <

PV-20562C PV-205718 l PV-20571C l

Rev. 4 D l i

SUMMARY

OF PROGRAM CHANGES (Continued):

36. (M-530) Revised to reflect applicable reliefs.

37. (M-530) Changed SFV-30801 to HV-30801 due to EFIC changes.

~38. (M-532) Corrected typographical error on FV-20531 and revised to reflect applicable reliefs.

39. (M-533) Added exercise to the closed position for FHS-047 and FHS-048.

40. (M-537) Revised to reflect applicable reliefs.

41. (M-543) Revised to reflect applicable reliefs.

42. (M-547) Added diesel fuel oil transfer pump discharge check valves-DF0-318, 319, 322, and 323.

43. (M-551) Corrected function for HV-70040 and HV-70047.

44. (M-551) Revised to reflect applicable reliefs.

45. (M-560) Revised to reflect applicable reliefs.

46. (M-570) Revised to reflect applicable '

reliefs and corrected type for SFV-72502.

47. (M-551) Changed testing requirements for valves HV-53620 thru HV-53623 due to plant modification and valves locked closed.

48. (M-551) Revised to reflect applicable reliefs.

49. (M-582) Added diesel fuel oil transfer pump discharge check valves DFO-017, 018, 019, and 020.

50. (M-583) Added diesel starting air compressor discharge and air start valves:

EGS-010 EGS-021 FV-89029 EGS-011 EGS-022 FV-89030 FY-89025 FY-89028 FV-89031 FY-89027 FY-89026 FV-89032

51. (M-585) Added TDI diesel air start system valves.

I EGS-564 EGS-845 EGS-565 EGS-846 ECS-566 HV-10050A EGS-567 HV-100508 EGS-843 HV-10051A l

EGS-844 HV-100518 1

52. (M-591) Revised to reflect applicable reliefs.

Rev. 4

- -D _ _

1

SUMMARY

OF PROGRAM CHANGES (Continued) l

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53. Added cold shutdown justification for the following valves:

SFV-23604 HV-26105 I SIM-019 HV-26106 SIM-020 PV-20562B l SIM-021 PV-20562C. i SIM-022 PV-20571B  !

DHS-017 PV-20571C l DHS-018 i

54. Removed cold shutdown justification for HV-26011.

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55. Clarified cold shutdown justification for TV-1 thru TV-4.

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Rev. 4

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