ML20246A408
| ML20246A408 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 08/16/1989 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20246A406 | List: |
| References | |
| PROC-890816, NUDOCS 8908220454 | |
| Download: ML20246A408 (130) | |
Text
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ATTACHMENT INSERVICE TESTING PROGRAM PLAN Rancho Seco Nuclear Generating Station Docket No. 50-312 Revision 5
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INSERVICE TESTING PROGRAM PLAN FOR PUMPS AND VALVES Record of Revisions Revision Date 3 6-23-87 4 1-29-88 5 8-14-89 i
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Rev. 5 i .
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Table of Contents EASA 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 21 3.0 TESTING PROGRAM FOR VALVES 22 3.1 General 3.1.1 Code 22 3.1. 2 - Valve Program Table 22 3.1.3 Deferred Testing 22 3.1.4 Manual Valves. 22 3.1.5 Testing Intervals 22 3.1.6 Cold Shutdown Testing 23 3.1.7 Position Indication Testing 23 3.1.8 Fail-safe Testing 23 3.1.9 Stroke Time Evaluation 23 3.1.10 Stop-Check Valve Testing 24 3.1.11 Valve Disassembly 24 3.2 Relief Requests for Valve Testing 25 through 55 APPENDIX A -
SUMMARY
- INSERVICE TESTING PROGRAM - PUMPS Al - A3 APPENDIX B -
SUMMARY
- INSERVICE TESTING PROGRAM - VALVES B1 - 856 APPENDIX C - COLD SHUTDOWN TESTING JUSTIFICATION C1 - C7 APPENDIX D -
SUMMARY
OF PROGRAM CHANGES D1 - D2 Rev. 5 ii L
1.0 INTRODUCTION
i Revision 5 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) i inspection interval, unless changed for other reasons. The Plan will be i
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 l- 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.
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La' TESTING PROGRAM FOR PUMPS E 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, a1 expanded allowable range may be determined, on a case base, in accordance with INP-3210.and ASME Code Interpretation XI-1-79-19.
2.1.4 Bearing Lubricant As specified in Table INP-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 IHP 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 or 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 operational actions required by the inoperable condition have been completed.
Rev. 5
, E. t 2.2- Relief Reauests for Pumo Testino The following pages in this section include relief requests PR-1 through PR-15 for IST pump testing.
e Rev. 5
U RELIEF REQUEST NO. PR-1 PUMPS:
Applicable to all pumps in the Program.
REQUIREMENT:
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 be1 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 INP-3100-2 will be applied as appropriate.
1 Rev. 5
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RELIEF REQUEST NO. PR-2 PUMPS:
Applicable to all pumps in the Program.
REQUIREMENT:
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. (IWP-4510)
BASIS FOR RELIEF:
Measuring 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 mecharical 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 material condition, thus, this is not necessarily a conservative nor proper practice.
ALTERNATE TESTING:
Vibration Measurements will be taken and evaluated in accordance with the requirements of OH-6 (Draft 11) as follows:
. Instrumentation Instrument Quality - 5%
Analog - % of Full Scale Digital - over the calibrated range frequency Response Range Frequency response range of the vibration measuring transducers and their readout system shall be from one-third minimum pump shaft rotational speed to at least 1000 Hertz.
- Vib ation Measurements
- a. On centrifugal pumps, measurements shall be taken in a plane approximately perpendirnlar to the rotating shaft in two orthogonal directions on each accessible pump bearing housing. Measurement also shall be taken in the axial direction on each accessible pump thrust bearing housing.
Rev. 5
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' RELIEF REQUEST NO. PR-2 (Continued).
b.- On. vertical line shaft pumps, measurements shall be taken on the
'4 upper _ motor bearing'housirg in three orthogonal. directions, one of-which is the axial-direction.
c.- If a portable vibration indicator is'used, the reference points must be clearly identified on:the pump to permit subsequent duplication in both location and plane.
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. Testing Method Vibration measurements are to be broad band'(unfiltered). If-velocity measurements _are used,'they shall be peak. ~If displacement amplitudes are.used, they shall be peak-to-peak.
Acceptance Criteria' Acceptance Criteria ~shall be established per Table 2.1.
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i RELIEF,. REQUEST NO..PR (Continued)
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Rev. 5
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RELIEF REQUEST NO. PR-3 PUMPS:
u Applicable to all pumps in the Program.
REQUIREMENT:
- The full-scale range of each instrument shall be three times'the reference value or.less (IHP-4120)
BASIS'FOR REllif:
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 Subarticle INP-4120. Ranges are typically expanded beyond~the multiple of three as-required.by the Code and, in the case of the digital instruments used currently 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 accuracles 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 INP-4100 (15 percent).
Rev. 5
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RELIEF REQUEST NO. PR-4 DELETED L
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RELIEF REQUEST NO. PR-5
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PUMPS:
Applicable to'all pumps in'.the Program.
REQUIREMENT:
L 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. (IWP-4310)
BASIS FOR RELIEF:
Hany of the bearings of the centrifugal pumps included in the Rancho Seco IST Program are water cooled (i.e., 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 temperature 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.
Rev. 5
- P s i l 4 RELIEF REQUEST NO. PR-6 PUMPS:
Applicable to all pumps in the Program.
REQUIREMENT:
- Heasure pump inlet pressure before starting the pump and during the test.
(Table INP-3100-1)-
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.
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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.
Rev. 5 l
RELIEF REQUEST NO. PR-7 PUMPS: j P-236 Makeup Pump P-238 A & B High Pressure Injection Pumps ]
i REQUIREMENT: j t
An inservice ~ test shall be run on each pump nominally every 3 months during normal plant operation. (INP-3400)
Pump testing 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 determine which of the pump parameters (flowrate 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 RELIEF:
The only practical method of full flow 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 nozzles.
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 min'5um 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. 5
P . .
3 RELIEF REQUEST NO. PR-8 PUMPS:
' Nuclear Service Raw Hater; Pump Nos. P-472A and P-472B TDI-Diesel Fuel.011; Pump Nos. P-108 A thru D
- Bruce GM-Diesel Fuel 011; Pump Nos.-P-888 A thru D REQUIREMENT:
Measure pump inlet pressure before starting _the pump and during the test;
- (Table'INP-3100-1)
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BASIS FOR RELIEF:
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- 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 level.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.
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l RELIEF REQUEST NO. PR-9 DELETED 1
Rev. 5
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RELIEF REQUEST NO. PR-10 I
PUMPS:
Nuclear Service Raw Hater, Pump Nos. P-472 A & B Nuclear Service Cooling Water, Pump Nos. P-482 A & B REQUIREMENT:
The test quantities shown in Table IHP-3100-1 (including flowratel shall be measured or observed and recorded. (IHP-3100)
BASIS FOR RELIEF:
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 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.
Rev. 5 cm ,= = =- -
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RELIEF REQUEST PR-11 1 EUtlES:
1 P-236'- Makeup P-238 A&B HP-Injection P-261'A&B Decay Heat Removal P-291 A&B Reactor Butiding Spray i P-705 A&B Boric Acid REQUIREMENT:
The full-scale range of each instrument shall be three times the reference 1 value or less (IHP-4120).
BASIS FOR RELIEF:
L 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.
O Nhen 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:
When measuring the suction pressure of a pump, in lieu of meeting the 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 2 .5 psi The accuracy of the differential press';re calculation will be limited to 2 2 percent of the differential pressure calculated value.
Accuracy of the suction pressure instrument will be better than 2.5 percent of the calculated differential pressure.
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RELIEF REQUEST PR-12 y;c DELETED i
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RELIEF REQUEST PR-13 i
' PUMPS:
TDI-Diesel-Fuel 011; Pumps Nos. P-108A thru 0 Bruce GM-Diesel.' Fuel 011; Pumps Nos. P-888A thru D REQUIREMENT:
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.shall be made and recorded. (IHP-3500(a))
Flowrate shalf. De measured using a. rate or quantity meter-installed in the'
- pump. test circuit. (INP-4600) ;
BASIS-FOR RELIEF: !
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 d Tallow the pumps to run for five minutes prior to taking data without -l significantly affecting test accuracy.
ALTERNATE TESTING:
'During testing of these pumps, data'will be taken as soon as flow and pressure conditions have: stabilized following pump start.- Flowrate will be determined by measuring the increase'of oil level in'the day tanks relative to.the' a
. length of operating time for the pump being tested.
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RELIEF REQUEST PR-14 PUMPS:
- TDI-Diesel Fuel Oil; Pump Nos. P-108A thru D Bruce GM-Diesel Fuel 011; Pump Nos. P-888 A thru D REQUIREMENT
At least one displacement vibration amplitude (peak-to-peak composite) shall be read during each inservice test. (IWP-4510)
BASIS FOR RELIEF:
'Each of these pumps is submerged within its respective fuel oil tank thus, the bearing housings are inaccessible for vibration measurements.
ALTERNATE TESTING:
Vibration measurements will not be taken.
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.3 oi RELIEF REQUEST PR-15 PUMPS:
- Bruce GM-Diesel fuel 011; Pump Nos. P-888A thru D REQUIREMENT:
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 RELLEE:
Since their in no practical mechanism for draining the 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 INP-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:
The increased. test requirements of paragraph INP-3230(a) will not be applied to these pumps, i
Rev. 5
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'3'.0 TESTING PROGRAM FOR VALVES
.3.1 General ~
~3.1.1 Code This IST Program. Plan 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 included 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 identifies those valves subject to inservice testing with the respective descriptive information, 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 1eakrate testing. Although these valves are categorized as " Category A" valves, they are considered to be passive per
. Table IHV-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 percent of the test interval may be applied to the testing schedule, as needed, to provide necessary operational flexibility.
Rev. 5
3.1.6' Colo' Shutdown Testing i
'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 1 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 may be completed during subsequent cold shutdown outages in a sequence such that scheduled testing does not omit nor favor certain valves or groups of valves. Note: Additional restrictions may be applied as ;
stated in specific relief requests.
l Refer to Appendix C of this Program for cold shutdown justifications. l 3.1.7 .. Position Indication Testing 1
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 additional testing is required and the respective cold shutdown justifications and relief requests apply to the requirements of i paragraph IHV-3415, when applicable.
3.1.9 Stroke Time Evaluation Where stroke time measurement of power-operated valves is required, I 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 IWV-3522, check valves may be disassembled, manually exercised and-inspected in lieu of flow (ard flow reversal) testing as described in the Code.
Check valve capability of sample disassembly may be used to verify full stroke check valves.
Check valves with the same design (manufacturer, size, model number, and materials of construction) and same service conditions will be classified as a sample group.
each inspection interval (refuel'ng) one valve will be selected forDuring disassembly, manual stroking and inspection. The inspection shall verify that the internals are structurally sound (no loose or corroded parts) and the valve is capable of full stroking.
A different valve shall be disassembled, inspected, and manually stroked at each inspection interval, until the entire group has been tested.
If it is found that the disassembled valve's full stroke
- capability is in question, the remainder of the valves in the group shall be inspected.
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l 3.2 Relief Reauests for Valve Testing l
j .. .The.following pages in this section include relief requests VR-1 4 through VR-23, for IST valve testing.
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'r t, p i s i A RELIEF REQUEST NO. VR-1
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i E, LSYSTEMS-iAll systems
. VALVES:-
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Rapid. acting valves (valves with normal-stroke time >2 seconds)
Turbine Stop/ Throttle Valves-(TV-1, TV-2, TV-3, TV-4)-
CATEGORIES:
1 A and B FUNCTIONS:
Various REQUIREMENT:
- If, for power-operated valves, t an increase'in stroke time of'50%'or more'for Evalves with- full-stroke times less than or equal to 10 seconds is observed, Ethe test! frequency shall be increased to once each month until corrective Jaction is taken . at which time the original test frequency shall be . resumed.
'(INV-3417):
BASIS FOR RELIEF:
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.
' ALTERNATE TESTING:
When exercising these valves with stroke times measuring less~ than 2 seconds, a maximum stroke time of 2 seconds will be assigned. Stroke time measurements' will be recorded but will only be verified to be less than two seconds. The requirements of IWV-3417(a) will.not' apply. Should the stroke time for these valves exceed two seconds, corrective action will be'taken as required by INV-3417(b).
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RELIEF REQUEST NO. VR-2 DELETED i
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RELIEF. REQUEST N0. VR-3 DELETED Rev. 5
p-C n-RELIEF REQUEST NO. VR-4
. SYSTEMS:
Various VALVES:
l PENETRATION # SYS 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 24 RSS SFV-72501 SFV-72502 25 CBS SFV-29107 l CBS-009 P'b 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 Rev. 5
j RELIEF REQUEST NO. VR-4 (Continued)
SYSTEMS:
Various VALVES:
PENETRATION # SlS VALVE I.D.
- 34. HVS SFV-53504 SFV-53503 35 HVS SFV-53604 SFV-53605 44 CFS CFS-005 CFS-009 CFS-011 45 CFS CFS-006 RCS-042 CFS-010 CFS-012 47- CFS HV-26515 HV-26516
- 48. FHS HV-20609 HV-20610 HV-20611 57 SYS ASC-048 ASC-049 62 FHS HV-70043 HV-70044 FHS-101 65 HVS HV-70041 HV-70042 HV-70045 HV-70046 SFV-53603 SFV-53610 Rev. 5
c--.
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F'
' RELIEF REQUEST.NO. VR-4 (Continued) l' i; _ CATEGORIES: '
l' A and A/C FUNCTIONS:
Valves provide containment isolation when in the closed position.
-REQUIREMENT:
~
Category ALvalves shall be seat leak tested (IWV-3423 and IWV-3424) and a maximum permissible leakage rate shall be specified (IWV-3426). Individual valve leakage rates shall be trended and analyzed as required by paragraphs IWV-3426 and IWV-3427.
' BASIS FOR RELIEF:
Due to the configuration of the system piping and components, in many cases individual leakage rate tests'aro 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.
ALTERNATE TESTING:
In those' cases where individual valve testing is impractical. valves will be.
leak' tested simultaneously in multiple valve arrangements and a maximum permissible leakage. rate will be applied to each combination of valves. Test results from tests of multiple valve combinations will be evaluated in accordance with IWV-3426 and IWV-3427.-
Rev. 5
r RELIEF REQUF.ST NO. VR-5 SYSTEM:
Reactor Coolant VALVES; RIVVHX Thru RIVVZY (8 valves)
CATEGORY:
C FUNCTION:
These valves open to equalize pressure across reactor vessel internals.
REQUIREMENT:
Check valves shall be exercised at least once every 3 months, except as provided by IHV-3522. (IHV-3521)
BASIS FOR RELIEF:
These valves are located on the reactor core support assembly and exercising
- is impossible without vessel disassembly-normally performed only during refueling outages.
ALTERNATE TESTING:
Each valve will be manually exercised during each refueling outage.
Rev 5
RELIEF REQUEST NO. VR-6
- k. SYSTEMS:
[ Makeup and Purification (M-521)
VALVES; BHS-019 BHS-044-
- SIM-043 SIM-052 CATEGORY:
C FUNCTION:
These. valves open to' supply water to the Makeup and High Pressure' Injection Pumps.from the Borated Hater Storage and Concentrated Boric Acid Tanks.
RE0VIRB mil Check valves shall be exercised at least every 3 months, except as provided by IHV-3522. (IHV-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 horic acid
. concentration due to over-concentration 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.
l ALTERNATE TESTING:
{
Each of the four (4) valves will be full-stroke exercised during each refueling outage.
I Rev. 5 l
_._,_m.._._.___.____._..______.
' RELIEF: REQUEST NO. VR-7 sn SYSTEMS:
g ,
Makeup and Purification-(M-521) . i p VALVES:
SIM-002'-
SIM-045
,, SIM-058 CATEGORY:
C FUNCTION:
These alves are check valves at the discharge of the Makeup 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 r
suction piping leading to the idle pump (s) and recirculation back to the
. Borated. Hater Storage and Concentrated Boric.' Acid tanks.
REQUIREMENT:
Check valves shall be exercised at least every 3 months, except as provided by IWV-3522. (IHV-3521) fLASIS FOR RELIEF:
L :The.only method of full-stroke testing these valves is to inject water from 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 is precluded due to low-temperature pressurization 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 than the 500 gpm required for full-stroking) of each valve. During this time, the flowrate is restricted by letdown and RCP Seal Water System demand.
Rev. 5
RELIEF RE0 VEST NO. VR-7 (Continued) !
ALTERNATE TESTING 1 Each valve will be partial-stroke exercised during normal Makeup Pump operation or quarterly pump testing.
During each-refueling outage all three-valves will be full-stroke exercised.
i i I l
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Rev. 5 1 j
lY s
. j- + 4 p'
q I. -
4 o
RELIEF REQUEST NO. VR-8 L -
t SYSTEMS:
E Makeup and Purification (M-521)-
= VALVES:
I' HV-23801
- SIM-036' L SIM-037-L SIM-040' SIM-041. l SIM-047 L
SIM-049 SIM-050-L CATEGOR ES:
C and.A/C EUNCTIONS:
These valves open to provide a flow path from the Makeup and HP Inject!on Pumps into the Reactor Coolant System. Valves HV-23801,.SIM-036, SIM-040, and SIM-047 close to provide containment isolation.
REQUIREMENT:
Check valves shall be exercised at least once every 3 months, except as provided by IHV-3522. (IHV-3521)
BASIS FOR RELIEF:
. The only practical method 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 Injectica and pumping water from either the BHST or the CBAT. 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 the' Reactor Coolant System during operation would cause thermal shocking of the injection nozzles. Valves'SIM-036 and SIM-037 are partial . stroke exercised to the open direction during normal operation of the Makeup System; however system flowrate is generally less than the 500 gpm required for stroking the valves to their fully opened position based on design flow conditions.
Rev. 5 1
l i' h
RELIEF REQUEST NO. VR-8 (Continued)'
u During: cold shutdown, the HP Injection Isolation' motor-operated valves and .,
pumps are closed and electrically disabled to prevent. low-temperature over; '"
' pressurization. aCold shutdown testing is = thereby preclu"Jed.
- ALTERNATE TESTING:
Valves SIM-036 and SIM-037 will be partial-stroked to the open. position in
.4+- conjunction with the normal operation of the Makeup System. SIM-036 will'be verified to close at cold shutdown by handwheel operation. -
Each'of these valves will be full-stroke exercised during each refueling outage.
i -
f Rev. 5 e_-____. _.
_m-_--____ __ _ ._ _
~. t y=
RELIEF. REQUEST NO. VR-9 s
SYSTEM:
Decay Heat Removalf(M-522)
VALVES:
~
CFS-001
'CFS-002.
.0HS-015' DHS-016 RCS-001)
RCS-002 CATEGORY:
IA/C-FONCTION:
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.
RE0VIREMENT:
The, leakage rate for valves.6 inches NPS or greater shall be evaluated per Subsection INV-3427(b).
BASIS FOR RELIEF:
Leak.tes'tng.of t th'ese 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. 5
(
p' -r:
L, RELIEF REQdEST 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:
f Leakage rates less than or equal to 1.0 gpm are considered acceptable.-
-. L'eakage 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.
L 3. Leakage rates; greater than.1.0 gpm butyless 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 L . margin between measured leakage rate and the maximum permissible rate of'5.0 gpm by 50% or greater.
- 4. -Leakage rates greater than 5.0 gpm are considered unacceptable.
L Rev. 5 i
um__
s b
I RELIEF REQUEST NO. VR-10 SYSTEM:
L
' Decay.. Heat Removal (M-522)
J' VALVE:
BHS-045 i CATEGORY:
H, C FUNCTION:
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'IHV-3522. (IHV-3521)
BASIS FOR RELIEF:
In order to exercise this valve flow must be induced 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.
Rev. 5
0 RELIEF REQUEST NO. VR-ll
,Y
! SYSTEM:
'h '
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.
- REQUIREMENT:
Check valves shall be exercised at least every 3 months, except covided by:INV-3522. (IHV-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 se 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.
1
(
Rev. 5
, > [
l' 4
RELIEF REQUEST NO. VR-11 (Continued) 2 ALTERNATE TESTING:
During cold shutdown, if. not tested in the previous 3 months, each valve will be partia'l-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. 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. (See Section 3.1.11)
Rev. 5 x = __ _ - _ _ _ _ _ _
- RELIEF REQUEST NO. VR-12 DELETED L>
I Rev. 5 RELIEF REQUEST NO. VR-13 SYSTEM:
Decay H ot Removal (M-522)
VALVES:
CBS-035 !
CBS-036 l CATEGORY:
C FUNCTION: l l
These valves open to provide a flowpath for sodium hydroxide from the Reactor Building Spray Additive Tanks to the Decay Heat System.
REQUIREMENT:
Check valves shall be exercised at least every 3 months, except as provided by INV-3522. (IHV-3521)
BASIS FOR RELIEF:
4 These are spring-loaded check valves and thus, the only methcv ' testing l requires injection of sodium hydroxide into the Decay Heat Removal System. i This is highly undesirable under any plant condition. Contamination of the Decay Heat Removal System with NA0H solution could ultimately result in NA0H 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 in the NA0H solution.
l ALTERNATE TESTING: 3
)
On an alternating schedule, one of these valves will be disassembled and inspected to ensure operability durir.g each refueling outage. If this inspection results in questionable operability of the inspected valve, then the remaining valve will be similarly disassembled and inspected.
(See Section 3.1.11) {
i l
l l
Rev. 5 l 1
_ _ - - - - - _ - _ - - - - - - - - - - - - - - - - - - - -_a
. = 3 ;g---- . -- - y 7 i 9 _,
< A w ltl t ,
(H; y, '
V k g ,
RELIEF REQUEST NO. VR-14 4
l SYSTEM::
0
~ Reactor Building Spray ~(M-524) tr- VALVES:
R' '
CBS-009L CBS-010 1 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.
REQUIREMENT:.
Check valves ~shall be exercised at least once 'every three months, except as
'provided byiINV-3522. (INV-3521)
BASIS FOR RELIEF:
The only method'of exercising these valves is-to operate.the Reactor Building ispray pumps and inject water through:the valves to the spray headers. Since there _is no practica1'means of isolating the spray headers and providing a-recirculation, this would result in spraying down the' Reactor. Building, which
- is highly undesirable.
ALTERNATE TESTING:
- 10n an~ alternating schedule, one of these valves will be disassembled and n -inspected to ensure operability during' each refueling outage. .If'this inspection results-in questionable operability of the inspected valve, then y the remaining valve will be disassembled, exercised and inspected in a similar manner. (See.Section 3.1.11)
) Y Rev 5 A > -.
y
. . .. .,. . . _ . _ . . . ~ . . ... . -
l RELIEF REQUEST NO. VR-15 SYSTEM:
Reactor Building Spray (M-524)
VALVES:
CBS-021 CBS-022 CBS-027 CBS-028 SFV-29015 SFV-29016 CATEGORY:
.C 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.
REQUIREMENT:
Check valves shall be exercised at least once every three months, except as provided by INV-3522. (IHV-3521) 4 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 NA0H in the Reactor Coolant System with the potential for causing stress cracking, increased radiation levels due to sodium activation and chloride contamination due to residual chlorides in the NADH solution.
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 aspect of plant safety.
Rev. 5
RELIEF REQUEST NO. VR-15, (Continued)-
ALTERNATE TESTING:
o During cold ~ shutdown periods, each of these valves will be partial-stroke .
tested.
~ The motor operators and stem assemblies of SFV-29015 and SFV-29016 will be exercised quarterly.
On an alternating sch'edule, one of each type of valve will be disassembled and inspected to ensure operability during each refueling outage. If this inspection results.in questionable operability of the inspected valve, then-i the remainder of the valves of that type will be disassembled.. exercised and
~
inspected in a similar manner.-(S.ee Section 3.1.11) l-l l
Rev. 5
_- o
wr. g yin n y ,
- RELIEF REQUEST NO. VR -
' SYSTEM:
Various:
VALVES:
This relief-request applies to all safety /rell'ef valves included in the
.- Program.
- _. CATEGORY:
, C-FUNCTION:
These valves provide overpressure protection to the associated system
. components.
_ REQUIREMENT:
i Safety and relief _ valves shall be tested in accordance with Subsection' >-
INV-3510.
BASIS FOR RELIEF:
ANSI /ASME OM_1-1981_- Requirements for. Inservice' Performance Testing of-Nuclear Power Plant Pressure Relief Devices, was-developed to. supersede'the
. requirements of. Subsection IHV-3510. This standard is more definitive and^ ,
-better suited to operational; testing than is ASME/PTC 25.3 which is Lreferenced in INV-3510.
ALTERNATE TESTING:
Safety and relief-valves will be tested in accordance with the requirements of ANSI /ASME OM-1-1981.
l l
s Rev 5 t~
________._________1_______.________
1 d.
M,
' RELIEF' REQUEST NO-.'VR-17 SYSTEM:
High Pressure Feedwater Heater (M-533)
VAtVES:
lFHS-049
.FHS-050-CATEGORY:
C' FUNCTION:
e .These valves open to provide a flowpath for minimum flow from the respective L auxiliary;feedwater pumps.
' REQUIREMENT:
l-LCheck valves.shall be exercised at least once every 3' months, except as provided by IHV-3522.(IHV-3521)
BASIS 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 from the LP' condenser which would result both auxiliary feedwater pumpseto be.
considered. inoperable. Thus, testing during plant operation is not practical from the viewpoint of' reactor safety.
Performing the tests, incibding 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-refueling) outage.
ALTERNATE-TESTING:
These valves will be exercised on a quarterly basis without verification of' full flow. Verification of full-flow through the valsas will be performed during~each refueling outage.
Rev. 5
__-_-_-_________a
_ - - _ - - - - - _ - - , - . - - - - . - . , - - , ---,-_--- - -- w-s RELTEF' REQUEST NO. VR-18 DELETED-l Rev. 5
m
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R ,
RELIEF REQUEST NO. VR-19 o SYSTEMS:
1 Coolant'Radwaste (M-560)-
,. VALVES:-
SFV-60001:
SFV-60003t CATEGORY:
4 A FUNCTION:
Primary; containment; isolation' for Reactor Coolant Vent and Drain Header.
REQUIREMENT:
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~ functional.
direction. Where valves are provided with a bonnet tap or other means of 1 venting between the seats, it is conservative to pressurize in the reverse-direction with.the valve internal space between the' seats vented. 'This provides an acceptable means of: determining the material condition.of the downstream seating surface that must' perform the leaktight service.
EALTERNATE-TESTING:.
'CategoryIA~gatevalvesmaybeseatleaktestedinadirectionoppositeto Lthat when;the valve is performing its function. When~ testing is performed in this. manner, a valve body vent 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. 5
_ m_ ,
RELIEF REQUEST NO. VR-20 SYSTEM Decay Heat Removal (M-522)
VALVES:
HV-26515 HV-26516 CATEGORY:
A EUNCTIONS:
These valves are used for occasional sampling and draining of the core flood tanks and close to provide containment isolation.
REQUIREMENT:
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 INV-3423(a) through (d) (IHV-3423).
BASIS FOR RELIEF:
Testing these valves in the " accident direction" would require draining the core flood tanks, resulting in a large quantity of liquid radwaste (7500 tallons/ tank) requiring processing and disposal. This is considered impractical from the view point of placing undue demands on-the existing radioactive waste processing facility and increases in personnel radiation exposure.
- 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 test pressure of 52 psig is equivalent in either direction. In the past, 4 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, j I
ALTERNATE TESTING: j Each of these valves may be leaktested in a direction opposite to that expected when the valve is performing its containment isolation 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
, pressure.
l l-Rev. 5 l i
i L___. _ _ . _ _ _ _
i
, RELIEF REQUEST NO: VR-21 2' , -SYSTEM L
' Bruce GM-Emergency Diesel' Generator (M-583)-
4 TDI. Diesel' Generator - Train "A" (M-585)
_TDI 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:
.B FUNCTIONS:
These valves open to supply compressed air to their respective diesel generators to provide the.' motive force for. engine starting.
REQUIREMENT:
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. (IHV-3413(b))
BASIS FOR RELIEF:
Since these valves have no position indication mechanism, stroke timing is not practical.
ALTERNATE TESTING:
These valves will be full-stroke exercised in conjunction with starting of' the diesel generators per testing required by Rancho Seco Technical 4 Specifications. Proper startup and operating of the' diesel generators will
-demonstrate satisfactory valve operation - - valve stroke time will not be ,
. measured. '
Rev. 5
- .2____ - _ _ _ _ _ _ _ _ _ _ . - -
']
q j
j RELIEF REQUEST N0: VR-22 l
SYSTEM. 1
- Reactor Coolant (M-520)
VALVES:
PSV-21511-s CATEG081:
B FUNCTIONS:
This valve opens to prevent cold overpressurization while in cold shutdown
' conditions.
REQUIREMENT:
Category 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. This could 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 p1 ant. staff.
ALTERNATIVE TESTING:
- During each. Reactor Coolant System cooldown, this valve will be functionally Jtested with the' Block Valve (HV-21505) closed. During each' refueling, PSV-21511 will:be full-stroke ~exercisedivia bench testing.
, Rev. 5 p
9 ,
t *\< '
~ ~
l l
RELIEF REQUEST NO: VR-23
[ t ,
LS STEM; jTDI; Diesel. Generator Train "A" &'"B" Air Start (M-585 Sheet 2 & 4)-
VALVESi EGS-565 'EGS-564 EGS-567_'EGS-566 CATEGORY:
- -
- C-FUNCTIONS:~
These valves are' check valves at the inlet to the receiver. -They open to provide _a flow' path from the. Air Compressor to the' receivers and close to:
isolate the air receivers.
REQUIREMENT:'
Check valves shall be exercised at least once every 3 months, except as
. .provided by.IWV-3522 (IHV-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 startisystem and compromising.the start capabilities of'the Emergency Diesel.
Generator System.-
' ALTERNATE TESTING:.
On an alternating schedule, one of these valves will be disassembled and
. inspected to_ ensuro operability during each refueling outage. If this
' inspection results in questionable operability of'the inspected valve,Lthen
- the remaining valveswill- be similarly disassembled and-inspected. -(See Section 3.1.11) n
)
Rev. 5 Mt r l
l
'l ?'
t i
APPENDIX A
SUMMARY
INSERVICE TESTING PROGRAM
- PUMPS -
N ' ,, '
Appendix A: Summary-Inservice Testing Program - Pumps
- LEGEND Notation used in'the pump summary. table is aslfollows
- 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 to 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 mea:urement 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 particular-parameter will not be measured or observed and a relief request is provided if requ. red. Requests for' relief are identified as "PRXX".
All relief requests are' included in Section 2.2.
L TEST INTERVAL The respective frequency of testing for each pump. The' letter "Q" denotes a. quarterly interval-.
I Rev. 5
-A I
, " 1 ST -
EN TI P
M '
E NNNM NNN NN NN NN T .
L 4444 1 1 1 1 RRRR B PPPP 1 - - - - .
V NNNN YYY YY YY YY
.~
~ 3333 w 1 1 1 1 777 H RRRR RRR O PPPP PPP L - - - - - - -
S F YYYY NNN YY YY YY P - .
M U
P S .
S c
- - E YYYY YYY YY YY YY i R .
b M P a A c R S i .
G R l n O E 1 1 1 1 1 1 1 p p
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APPENDIX B
SUMMARY
. INSERVICE TESTING PROGRAM
- VALVES -
l l
l l.
L i - _________. _ ______ ___ ___ _. _ ___
y-Reference Drawinos Drawina No. Egg. System Pace M-520, Sh 1 34 Reactor Coolant System B-5
'M-520,-Sh 2. .14 Reactor Coolant System- B-6
.M-521, Sh 1 14 Make-up andl Purification System B-7 M-521, Sh 2 15 Make-up and Purification System B-8.
M-522, Sh.1 33 Decay Heat Removal System B-12 M-524 ' 10 Reactor Building Spray System B-1B M-530, Sh 1 13- HP and Auxiliary Turbines System B-20
'M-530. Sh 2 12 HP and Auxiliary Turbines System B-21
~~
M-530, Sh 2A. 9 HP and Auxiliary Turbines System B-22.
M-530, Sh 3 17 HP and Auxiliary Turbines System' B-26
~~
M-532, Sh 1 25 . Steam Generator System B-27 M-532,.Sh 2 6 Steam Generator System B-30 M-532, Sh 3 6 Steam Generator System B-31 M-533, Sh 3 10. High Pressure Feedwater Heater System B-32 M-536 . 26 Condenser System B-33 M-537, Sh 3. 12 Auxiliary Steam System B-34 M-543, Sh 1 6 Component Cooling Hater System B-35 M-543, Sh 4 13 Component Cooling Water System B-36 H-544 20 Nuclear Service Raw Hater System B-37 M-545 15 Nuclear Service Cooling Hater System B-38 M-547 0 TDI Diesel Fuel Oil System B-41 M-551 27 Reactor Building Heating, Ventilating, B-42 and Air Conditioning Systems M-560, Sh 3, 8 Coolant Radwaste System B-45 M-561, Sh 3 5 Miscellaneous Liquid Radwaste System B-46 M-570 25 Reactor Coolant Chemical Addition B-47 anu Sampling System M-573 . 17 Turbine Plant Sampling System B-49
.M-582, Sh 1 . 25 Diesel Oil Systems B-50 M-583, Sh 1- 14 Emergency Diesel Generator B-51 M-585, Sh 1 0 TDI Diesel Generator System - Train "A" B-52 M-585, Sh 2 0 TDI Diesel Generator System - Train "A" B-53 M-585, Sh'3' 0 TDI Diesel Generator System - Train "B" B-54 M-585, Sh 4 0. TDI Diesel Generator System - Train "B" B-55 M-590, Sh 1 37- Plant Air System B-56 M-591, Sh 1 37 Auxiliary Gas System B-57 M-593, Sh 2 12 Miscellaneous Water Systems B-58 L
Rev. 5
-B
- f Appendir, B: Summary-Inservice Testing Program - Valves LEGEND Notation used in the valve summary table is as follows:
VALVE The valve alpha-numerical identification.
COOR The location of the valve on the referenced P&ID.
FUNCTION The functional system description of the vaive.
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:
M0 Motor-operated A0 Air-operated 50 Solenoid SA Self-actuated MAN Manual POS The normal position of the valve during plant operation - open or closed.
Rev. 5
-B l
_ _ _ ___ _ . - - _ -_ _ _ - - _ -- - )
fh #
r 1
Appendix B: ~ Summary-Inservice Testing Program - Valves l LEGEND (Cont.)
REQMTs 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. . l 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 ANSI /ASME Standard OH-1-1981. (See VR-16)
VPI . Verification of remote position indicator to verify _ valve operation is accurately indicated.
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.
Refers to the test period for testing safety / relief valves SY ANSI /ASME' Standard OM-1-1981 (5 or 10 years, as appropriate) 10Y See applicable relief request.
AP As. practical or available. ' Refer _.to appropriate' relief request.
REMARKS Relief Requests are designated VR-XX. Refer to Section 3.2;for relief requests.
l L
Rev. 5
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Appendix C COLD SHUTDOWN VALVE TESTING JUSTIFICATION
4 COLD SHUTD0HN TEST JUSTIFICATION Reactor Coolant System (M-520)
- 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 va~1ve 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-220B & C SFV-22009 - Letdown Outboard Containment Isolation SFV-22023 - Letdown Inboard Containment Isolation SFV-22025 - Letdown Isolation from Steam Generator 205A Valves SFV-22009, SFV-22023, and SFV-22025 and either SFV-22005 or SFV-22006 are normally open during plant operation to provide continuous letdown and 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.
SFV-24004 - Reactor Coolant Pump Seal Water Return SFV-24013 - Reactor Coolant Pump Seal Water Return These valves are normally open to provide a return path for reactor coolant pump seal water. Closure of these valves during pump operation would result in a loss of seal water flow and an imbalance in the interstage pressures within tlte seal. This could result in seal failure and ultimately plant shutdown.
Rev. 5
-C _ _ _ _ - - _ - - - _ _ _ - _
COLD' SHUTDOWN TEST JUSTIFICATION (Continued):
SFV-23508 - Makeup Tank Isolation Valve l .During plant operation, this valve must remain open to supply water to the:
l 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-23604 - 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 L position would require operator action to manually control pressurizer level. During this evolution, a transient in pressurizer level could occur which could lead ~to a plant trip.
SFV-23616 - Reactor Coolant Pump Seal Water 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 Water Supply SIM-020 - RCP 2108 Seal Water Supply SIM-021 - RCP 210C Seal Water Supply
'SIM-022 - RCP 210D 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 lir'ted. -l i
I Rev. 5
-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 unnecessary 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 ptotection of the decay heat removal system from overpressurization. In addition, these valves are electrically
~~
interlocked-to prevent opening when RCS pressure is greater than 215 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 l operation, thus, testing of HV-20003 is not practical during operation.
l Rev. 5
-C f l _ -
COLD SHUTDOWN TEST JUSTIFICATION (Continued)
HV-2610S - P-261 Suction from Rx Building Sump HV-26106 - P-261 Suction from Rx Building Sump To preclude flooding into the Reactor Building sump when either of these two valves is opened, 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 unacceptable 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 0 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.
I Rev. 5
-C _ _ _ _ _ _ _ - _ _ _ _ _ _ _ ~
COLD SHUTDOWN TEST JUSTIFICATION (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.
l h 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.
l Rev. 5
- C , _ __. . _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _
. COLD SHUTDOWN TEST JUSTIFICATION (Continued)
Steam Generator (M-532)
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 205B 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 Water System (M-543)
CCH-036 & SFV-46014 - Cooling Hater Supply to Reactor Building 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 Closure of any of these valves during plant operation at power will interrupt cooling to the reactor coolant pumps, letdown coolers, or the control rod drive mechanisms--depending on which valves are closed. This would likely cause damage to associated equipment and components that require continuous cooling.
Rev. 5
-C _ _ _ _ _ _ _ _ _ _ _ _
f
, COLD SHUTDOWN TEST JUSTIFICATION (Continued)
Reactor Buildina Heatina. Ventilating and Air Cond System (M-551)
SFV-53503 and SFV-53504 - Re' actor Building. Purge Inlet Valves STV-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.
)
Rev. 5
-C _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ -
l i
i Appendix D
SUMMARY
OF PROGRAM CHANGES t
I
SUMMARY
OF PROGRAM CHANGES
- Summary of Changes: Second 10-Year Inservice Testing Program -
Revision 5 vs. Revision 4 (Submitted 8/14/89)
Revision 5 to the IST Program Plan incorporates changes required to meet the NRC Safety Evaluation Report (SER) [Reynolds to Firlit 5/16/89]. Some editorial changes were also made as noted below.
GENERAL:
- 1. Section 1.0 revised to reflect revision 5.
- 2. Revised REFERENCE DRAWING LIST to list proper drawings for EFIC valves
- 3. Revised LEGEND to correct VSP code reference. Added definition of VPI.
PUMPS:
- 1. Revised Pump Relief No. PR-2 to incorporate vibration monitoring requirements of OM-6 as " Alternate Testing" per SER.
- 2. Deleted Pump Relief No. PR-4 (Acceptance criteria range expansion).
Relief denied per SER.
- 3. Revised PR-13 to include relief for flow measuring equipment to meet requirements of the SER.
VALVES:
- 1. Added additional discussion of " sample / disassembly" method of check valve testing to clearly state NRC philosophy as defined in the SER.
- 2. Revised Valve Releif No. VR-1 to clafify definition of " rapid acting valve" and to include required corrective action should the 2 second stroke time be exceeded as discussed in SER.
- 3. Deleted Valve Relief No. VR-2 (Increased testing for valves tested only at CSD). Relief was denied.
- Rev. 5
-D I
9 0
-SUMHARY OF PROGRAM CHANGES (Continued)
- 4. Revised Valve Relief No. VR-4 to. clarify code section for which relief L- is being requested.
- 5. Revised Valve Relief No. VR-8 to correct " Alternate Testing" for SIM-037. _This valve is a check valve and cannot be storked per-handwheel operation as previously stated.
- 6. Revised Valve Relief.VR-11 as required by SER. Testing of CFS-001/002 will be performed each refueling per sample disassembly method.
- 7. Revised' Valve Relief No.s VR-13, 14, 15, & 23 to reference section l
3.1.11 for c1:rification of sample disassembly test method, i 8. Revised va s 34 sting to'show correct class identity as reflected on t
H-1500 seriec drawings.
- 9. (M-521) - HV-23801 - Corrected listing of valves testing as specified in VR-4.
- 10. (M-521 sh 2) - SIM-036 - Corrected testing as specified in VR-8.
- 11. -(M-068) Remove testing of MSS-068. Per DCP 89-0038 the internals of this valve have been removed.
- 12. (M-544) Removed testing of PSV-47205A/B since they are not within the scope'of INV-1100 as they do not serve as a pressure relief device required to perform a specific function in shutting down the reactor or in mitigating the consequences of an accident. These valves serve as system air vents for filling and draining of the system. They function by float action and have no setpoint adjustments. Each is'provided with an isolation valve. ,
-13. Revised COLD SHUTDOWN TEST JUSTIFICATION for HV-20001/2 to reflect correct interlock set pressure.
- Rev. 5
-D _ _ _ _ _ _