ML20216H822
| ML20216H822 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 06/25/1987 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20216H811 | List: |
| References | |
| PROC-870625, NUDOCS 8707010591 | |
| Download: ML20216H822 (119) | |
Text
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WP3210B/0-01708 -- i
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' INSERVICE TESTING PROGRAM PLAN Rancho Seco Nuclear Generating Station.
Docket No. 50-312
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List of Effective Pages Pace Revision Date i
s INSERVICE TESTING PROGRAM PLAN FOR PUMPS AND VALVES Record of Revisions Revision Date -
3 6-23-87 !
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1 Table of Contents Page Title Page List of Effective Pages i ;
I Record of Revisions ii q
Table of Contents iii
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 i 2.1.4 8 earing Lubricant 2
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2.1.5 Instrumentation 2 2.1. 6 Testing Intervals 2 2.1.7 Deferred Testing 2
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2.2 Relief Requests for Pump Testing 3 through 17 l 1
3.0 TESTING PROGRAM FOR VALVES 18 )
1 3.1 General ]
3.1.1 Code 18 3.1.2 Valve Program Table 18 3.1.3 Deferred Testing 18 3.1.4 Manual Valves 18 3.1.5 Testing Intervals 18 3.1.6 Cold Shutdown Testing 19 ,
3.1.7 Position Indication Testing 19 l 3.1.8 Fail-safe Testing 19 3.2 Relief Requests for Valve Testing 20 through 44 APPENDIX A -
SUMMARY
- INSERVICE TESTING PROGRAM - PUMPS APPENDIX B -
SUMMARY
- INSERVICE TESTING PROGRAM - VALVES APPENDIX C - COLD SHUTDOWN TESTING' JUSTIFICATION ,
APPENDIX D -
SUMMARY
OF PROGRAM CHANGES i iii
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1.0 INTRODUCTION
j Revision 2 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).
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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 Winter,1981 Addenda. All references to IWP or IWV in this document correspond.to Subsections IWP or IWV, 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.
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1 2.0 TESTING PROGRAM FOR PUMPS 2.1 General 2.1.1 Code j "This IST Program Plan for pumps meets the requirements of Subsection -3 IWP of Section XI of the ASME B&PV Code. Where these requirements are determined.to be impractical, specific requests for relief'are ;
included in Section 2.2. l J
2.1.2 Pump. Program Table Appendix A lists-the pumps included in the IST Program. Data j contained in:this table identifies those pumps subject to inservice j testing with the. respective inservice test parameters, intervals, and J any other applicable remarks.-
2.1.3 Allowable Ranges of Test Quantities The allowable. ranges specified in Table IWP-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 IWP-3100-2. Should this situation occur, an expanded allowable range may be determined, on a case base,.in.accordance with '
IWP-3210 and ASME Code Interpretation XI-1-79-19.
2.1.4 Bearing Lubricant j As specified in Table IWP-3100-1, pump bearing lubricant level or pressure will be observed prior. to or during testing, when practical. -1 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 .l The test frequency for pumps in the Program will be as set forthlin' ;
Appendix A and the associated relief requests.' A band of +25 percent i of the test interval may be applied to the test schedule, as needed, '
to provide necessary operational flexibility.-
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2.1.7 Deferred Testing '
In conducting inservice-testing of pumps ifithe duplicate-(redundant) pump has been declared-inoperable;or is out of service for any - i 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.
f-2.2 Relief Requests for Pump Testing i The following pages in this section include relief requests PR-1 through PR-12 for IST ptimp testing. j l
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I RELIEF REQUEST NO. PR-1 I PUMPS:
Applicable to all pumps in the Program. )
TEST RE0VIREMENT:
Reference values shall be at points of operation readily duplicated during ,
subsequent inservice testing. (IWP-3110) j BASIS FOR RELIEF:
I 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 I be possible or would require excessive valve manipulation which could result 3 in damage to valve components or excessive personnel exposure.
ALTERNATE TESTING:
During pump reference tests, a refererece pump curve may be established or the manufacturer's pump curve confirmed. In lieu of duplicating a specific I reference flowrate during subsequent inservice tests, a flowrate (Qa) will be ]
obtained and recorded along with the corresponding differential pressure 1 (dPa). The differential pressure value (dPa) will then be compared to the l theoretical differential pressure corresponding to the measured flowrate (Qa) l on the pump curve. The acceptance criteria of Table IWP-3100-2 will be {
applied as appropriate. 1 1
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l RELIEF REQUEST NO. PR-2 i
PUMPS:
Applicable to all pumps in the Program. I 1
TEST REQUIREMENT: )
At least one displacement vibration amplitude (peak-to-peak composite) shall I' 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) j BASIS FOR RELIEF:
Measuring vibration in velocity units rather than displacement is an industry i 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 l 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:
At the option of the plant staff, pump vibration measurements may be taken j and trended in either displacement or velocity units. Acceptance criteria l for velocity measurements will conform to Table 2.1. l Vibration measurements will be taken in two pre-established mutually- )
perpendicular directions in a clane perpendicular to the rotating shaf t, i I
RELIEF REQUEST NO. PR-2 (Continued)
Table 2.1: Allowable Ranges of Vibration Levels (ips)*
Ref. Vib. Acceo. Range Alert Action Rea.
<0.15 0 - 0.3 0.301 - 0.45 > 0.45 0.15 - 0.3 0 - 0.45 0.451 - 0.75 > 0.75 0.3 - 0.6 0 - 0.7 None > 0.7 0.6 - 0.7 0 - 0.7 None > 0.7
- Limits based on ASME Technical Paper 78-WA/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.
TEST REQUIREMENT:
The full-scale range of each instrument shall be three times the reference value or less (IWP-4120)
BASIS FOR RELIEF:
The commercially available instruments used for measuring pump vibration do not provide range selections that guarantee adherence to the range limitations per Subsubarticle IWP-4120. Specifically, for the.
instrumentation used at Rancho Seco, the scale ranges are 0-0. 3, 0-1. 0, 0-3.0, 0-10 and 0-30 mils or in/sec.
The accuracy of instruments used to measure vibration are generally based on the actual measured value and is generally unrelated to the instrument range.
ALTERNATE TESTING:'
No alternate method for vibration measurement is proposed. Vibration measurements will be taken with the instrument range selection at the lowest possible scale that includes the measured level of vibration.
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I j RELIEF REQUEST NO. PR-4 PUMPS:
Applicable to all pumps in the Program.
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TES'T REQUIREMENT:
The allowable ranges of. inservice test quantities in relation to the reference, values are tabulated in Table IWP-3100-2. This table limits the acceptable-performance of each pump dependent variable-(flowrate or differential pressure) to a maxiinum 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 f rom service if the test parameter falls-in the action-required range. (IWP-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 engineeringfjudgement, nor acceptable plant ,
operating practice for the following reasons:
- Indiscriminate 1y 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 systemr. 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 vtith 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 2 percent).
by Paragraph IWP-4110 (
- 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. _
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1 RELIEF REQUEST NO. PR-4 (Continued) I l
- This requirement provides no additional measure of reliability to the l equipment.
ALTERNATIVE TESTING:
The acceptance cr i teri a of Table IWP-3100-2 will be utilized, unless ,
otherwise noted, with the following exceptions:
a) The Required-Action Range (HIGH) will be eliminated for test quantities of flowrate and dif ferential. pressure; and b) The Alert' Range (HIGH) will be equal to 105 percent of the reference ,
value and above for test quantities'of flowrate and differential pressure. j 1
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RELIEF REQUEST NO. PR-5 PUMPS:
Applicable to all pumps in the Program.
TEST REQUIREMENT:
The temperature of all centrifugal pump bearings outside .the main flowpath shall be measured at points selected to.be responsive to changes in the 4 i
. temperature of the bearings. (IWP-4310)
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BASIS FOR RELIEF
- l 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 1 auxiliary closed cooling water systems. Thus, bearing temperature l measurements are highly dependent on the temperature of the cooling medium l 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 l 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 j 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 f rom other primary duties, excessive operating periods for normally idle pumps, and personnel radiation exposure.
ALTERNATIVE TESTING:
I None proposed.
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RELIEF REQUEST NO. PR-6 PUMPS:
Applicable to all pumps in the Program.
TEST REQUIREMENT:
Measure pump inlet pressure before starting the pump and during the test.
(Table IWP-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. f l
Inlet pressure prior to pump startup is not a significant parameter needed ,
for evaluating pump performance or material condition. i I
ALTERNATIVE TESTING: j l
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. j l
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RELIEF REQUEST NO. PR-7 PUMPS: I
.J P-236 Makeup. Pump .
P-238 A & B High. Pressure Injection Pumps I TEST REQUIREMENT:
An inservice test shall be run on each pump nominally every 3 months during normal plant operation. (IWP-3400)
Pump testing shallbe based on establishing a set of reference values, then I 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 IWP-3100-2. establishing acceptance criteria. During the test, the test quantities 'shown in Table IWP-3100-1 shall be measured and recorded. (IWP-3100 & 3110)
BASIS FOR RELIEF:
During .nonnal plant operation none of these pumps has a full flow test loop available. 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.
1 During partial-flow testing, the region of.the pump curve in which the i testing will be performed is near shutoff head and flowrate. readings are not, j necessarily meaningful from the viewpoint of trending. j Since the HP injection pumps stand idle except for periods of testing, significant inservice degradation is_unlikely. q 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 !
wi_11 be measured and evaluated with respect to Table IWP-3100-2 and- a associated relief requests with the exception of flowrt.te. t During each refueling outage, each pump will be tested under nominal -
full-flow conditions'and all required. parameters will be measured, including' ,
flowrate.
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RELIEF REQUEST NO. PR-8 PUMPS:
Nuclear Service Raw Water; Pump Nos. P-472A and P-4728 TEST REQUIREMENT:
Measure pump inlet pressure before starting the pump and during.the test.
(Table IWP-3100-1)
BASIS FOR RELIEF: l These pumps are submerged and, as such, have inlet pressures corresponding to the water level in the spray pond basin. Since the level of the pond basin ,
is maintained constant by wiere level, variation of level and, thus, suction !
pressure is not possible. '
ALTERNATE TESTING:
Inlet pressure will be calculated on a one time basis from the normal height of water above the pump suction and not measured or calculated during or ,
prior to each test.
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RELIEF REQUEST NO. PR-9 I I
PUMP:
Dual Drive Auxiliary Feedwater Pump, No. P-318 TEST REQUIREMENT: l
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For variable speed pumps, measure pump speed. (Table IWP-3100-1) j BASIS FOR RELIEF:
Pump operation in the motor-driven mode is performed at a constant speed -
motor speed is non-variable.
ALTERNATE TESTING Pump speed will only be measured when pump is operated in the turbine-driven mode during testing. I t
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RELIEF REQUEST NO. PR-10 PUMPS:
Nuclear Service Raw Water, Pump Nos. P-472 A & B .
Nuclear Service Cooling Water, Pump Nos. P-482 A & B j REQUIREMENT:
The test quantities shown in Table IWP-3100-1 (including flowrate) shall be measured or observed and recorded. (IWP-3100) I
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BASIS FOR RELIEF:
There is no installed instrumentation for measuring the flowrate in:any of the above piping systems.
ALTERNATIVE TESTING:
Appropriate flowrate measuring instrumentation will be installed in these l systems prior to or during the next refueling outage-(#7). In the interim I the following will apply. )
3 For pumps P-472 A & B, flowrate will be derived by measuring the spray l 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. 1 i
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RELIEF REQUEST PR-11 PUMPS Applicable to all pumps in the' Program.
TEST REQUIREMENT The full-scale range of each instrument shall be three times'the reference value or less (IWP-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 When measuring the suction pressure of a pump, in lieu'of meeting the instrument range requirement of IWP-4120, instruments will-be chosen such that the accuracy meets the requirements set forth below:.
Accuracy will be at least t .5 psi The accuracy of the differential ~ pressure calculation will be limited to t 2 percent of the differential pressure calculated value.
Accuracy of the suction pressure instrument will be better than.
t .5 percent of the calculated differential pressure.'
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p RELIEF RE0UEST PR-12 PUMPS Boric Acid Pumps, P-705A and B. l REQUIREMENT Instrumentation accuracy shall be within the limits of Table IWP-4110-1.
(IWP-4110) For flowrate measuring instrumentation, the accuracy requirement is 2 percent of full scale.
BASIS FOR RELIEF The existing instrumentation for measuring boric acid pump flowrate has a stated accuracy of i 5 percent.
ALTERNATE TESTING The existing flow instrumentation will be used during pump performance testing until new instrumentation is installed that meets Code requirements.
In the interim, the existing flow instrumentation will be subjectedtto frequent calibration to ensure that test data is as accurate and representative as possible.
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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 IWV 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 they are considered to be passive per Table IWV-3700-1 and, as such, will not be exercised as required by Paragraph IWV-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.
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3 .1. 6 ' Cold Shutdown Testing For those valves designated to be exercised or tested during cold j 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. Due to scheduling and manning limitations, such testing may not be performed for cold shutdown periods that are not expected to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Furthermore, valve testing will not necessarily be performed'more often than once every 1 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.
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 IWV-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 paragraph IWV-3415, when applicabic.
3.2 Relief Requests for Valve Testing The following pages in this section include relief requests VR-1 through VR-20, for IST valve testing.
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RELIEF REQUEST NO. VR-1 SYSTEMS::
All systems i ,
VALVES:
Various CATEGORIES:
A and B FUNCTIONS:
Various REQUIREMENT:
If, for power-operated valves, an inc'rease in stroke time of 50% or more for valves 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.
(IWV-3417)
BASIS FOR RELIEF:
The stroke times of most solenoid, air-operated valves and of 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 1 When exercising valves with stroke times measuring less than 5' seconds, stroke timo measurements will be recorded but will only be verified to be less than five seconds. Only when the stroke time of a valve exceeds five (5) seconds will the trending requirements of IWV-3417 be met. Any abnormality or erratic operation of a valve will be evaluated.
I RELIEF REQUEST NO. VR-2 ;
SYSTEMS: a '
i Various VALVES: l All power-operated valves to be exercised only during cold shutdown or refueling outages. 1 CATEGORIES:
A and B FUNCTIONS:
Various RE0VIREMENT:
l If, for power-operated valves, an increase in stroke time of 25% or more from the previous test for valves with full-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 f requency shall be resumed. (IWV-3417)
BASIS FOR RELIEF:
J Strict adherence to this requirement, as stated, could require a plant j shutdown or operation under unusual conditions each month for testing until !
it is determined that the valve is operating 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 max'imum 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 or justified.
ALTERNATE TESTING:
If valve testing during cold shutdown should result in valve stroke time increases as stated in Article IWV-3417(a) requiring increased frequency testing, until valve perforiaance allows return to normal testing frequency,
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the subject valve will be tested only during cold shutdown or refueling periods (as applicable) on a frequency determined by the intervals between !
shutdowns as follows:
- for intervals of one (1) month (30 days) or longer, tests will be performed during each shutdown;
- for intervals of less than 1 month (30. days), stroke testing will not be performed unless'1 month has passed since the last stroke test for that particular valve.
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RELIEF REQUEST NO. VR-3 SYSTEMS:
Various VALVES:
This relief request pertains to all check valves in the Program.
CATEGORY:
C FUNCTION:
Various REOUIREMENT:
Check valves shall be exercised per Paragraph IWV-3522.
BASIS FOR RELIEF:
Due to circumstances that cannot be foreseen, there may be periods of time when required exercising is not practical due to system or plant conditions.
A visual inspection of valve internals and subjective evidence of the freedom of motion and other items that could affect valve operation is equivalent to a prescribed flow test.
l ALTERNATE TESTING:
At the option of the_ plant staff, valve disassembly and visual inspection, a with manipulation of a valve's obturator and subjective evaluation as to the l valves operability, may be substituted for flow testing.
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< J RELIEF REQUEST NO. VR-4
.t SYSTEMS:
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- Various
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vat VES_:
Category A or A/C valves.
[ATEGORIES:
A and A/C FUNCTIONS:
f' Valves provide. containment isolation when in the closed position.
REQUIREMENT:
Category A valves shall be seat leak tested and a maximum permissible leakage rate shall be specified. Individual valve leakage rates shall be trended and analyzed as required by paragraphs IWV-3426 and IWV-3427.
p 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.
ALTERNATE TESTING:
7 1 When practical, category A or A/C valves will be leak tested individually.
- In those cases where this is not the case, valves will be leak tested r
simultaceously in multiple valve arrangements and a maximum permissible leakage rate will be applied to each combination of valves.
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RELIEF REQUEST NO. VR-5 SYSTEM:
. VALVES:
R1VVWX Thru R1VVZY (8 valves)
CATEGORY: ,
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FUNCTION:
1 These valves open to equalize pressure across reactor vessel internals. !
1 RE0VIREMENT:
Check valves shall be exercised at least once every 3 months, except as c provided by IWV-3522. (IWV-3521)
BASIS FOR RELIEF:
i 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.
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RELIEF REQUEST NO. VR-6 SYSTEMS:
Makeup and Purification (M-521)
VALVES:
BWS-019 BWS-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 Water Storage and Concentrated Boric Acid Tanks.
REQUIREMENT:
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-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.
ALTERNATE TESTING:
Each of the four (4) valves will be full-stroke exercised during each refueling outage.
s..
RELIEF REQUEST NO. VR-7 SYSTEMS:
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 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.
suction piping leading to the idle pump (s) and recirculation back to the Borated Water Storage and Concentrated Boric Acid tanks.
RE0VIREMENT:
Check valves shall be exercised at least every 3 months, except as provided !
by IWV-3522. (IWV-3521) l BASIS FOR RELIEF:
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 l SIM-058, this would require initiation of HP Injection and pumping water from l either the BWST or the CBAT. 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.
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.
+
i RELIEF REQUEST NO. VR-7 _ ( Cr.ntinued) .
ALTERNATE TESTING:
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.
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RELIEF REQUEST NO. VR-8 1
SYSTEMS:
Makeup and Purification (M-521) ,
i l
VALVES:
l HV-23801 I SIM-036 d SIM-037 SIM-040 SIM-041 SIM-047 SIM-049 i 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.
l REQUIREMENT:
Check valves shall be exercised at least once every 3 months, except as provided by IWV-3522. (IWV-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 Injection and pumping water from either the BWST 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
-onditions.
wOSO
I 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. ~ i Each of these valves will be full-stroke exercised during each refueling outage. .
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l RELIEF REQUEST NO. VR-9 SYSTEM:
Decay Heat Removal (M-522)
VALVES:
CFS-001 CFS-002 1 '
DHS-015.
DHS-016 RCS-001 j RCS-002 ,
.j CATEGORY:
l A/C l
FUNCTION: j l 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.
REQUIREMENT: .
The leakage rate for valves 6 inches NPS or greater shall be evaluated per- .!
Subsection IWV-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- -1 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.
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i RELIEF REQUEST NO. VR-9 (Continued) .
ALTERNATE TESTING l 1
The leakage rate acceptance criteria for these valves will be as set forth in l
. the Rancho Seco Technical Specifications, Table 3.3-1, namely: l
- 1. Leakage rates less than or equal to.l.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 i 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 maximum 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 i
SYSTEM:
Decay Heat Removal (M-522)
VALVE:
I BWS-045 l
CATEGORY: 1 C
FUNCTION:
This valve provides a flowpath from the boric acid pumps and filters to the suction of the decay heat removal pumps.
RE0VIREMENT:
Check valves shall be exercised at least every 3 months, except as provided :
by IWV-3522. (IWV-3521) l 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 BWST. This would necessarily introduce a large quantity of . highly concentrated boric acid solution into the Decay Heat System piping. Subsequently, this would result in undesirable increases in the Reactor, Coolant System boric acid concentration when the Decay Heat Removal System is placed in service.
i During cold shutdown, injecting the concentrated boric- acid solution would likewise cause an unwanted increase of the boric acid concentration in the j Reactor Coolant System.
]
ALTERNATE TESTING:
These valves will be full-stroke exercised during each refueling outage.
~ RELIEF REQUEST NO. VR-11 l
SYSTEM: j Decay Heat Reraoval (M-522) ]
VALVES:
i CFS-001 1 CFS-002 j CATEGORY: ,
A/C FUNCTION:
These valves open to provide a flowpath for water from the Core Flood Tanks j 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 as provided by IWV-3522. (IWV-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.
ca 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.
ALTERNATE TESTING:
Prior to plant startup at the next refueling outage (No. 7), each of these valves will be disassembled, manually exercised, and inspected internally. -
During cold shutdown each valve will be partial-stroke tested and, at each refueling outage, will be leak tested. Once during each 10-year inspection interval, each valve will be disassembled and' manually exercised.
-RELIEF REQUEST NO. VR-12 )
SYSTEM:
Make-up and Purification (M-521, Sh 2)
VALVES:
I SIM-019 l SIM-020 l SIM-021 i SIM-022 l CATEGORY:
A/C ,
FUNCTIONS:
1 SIM-019 thru SIM-022 open to provide a flowpath.for' seal water to the Reactor . l Coolant Pumps and close in the absence of seal water flow for containment 1 isolation. l 1
REQUIREMENT: j Check valves shall be exercised at least every 3 months, except as provided by IWV-3522. (IWV-3521) Check valves shall be tested / exercised per the 2 l
requirements of IWV-3522.
BASIS FOR RELIEF:
These are stop check valves where the disc or plug is not physically connected to the valve stem and there is no practical mechanism of determining valve disc position external to the valves.
In order to prove that the valves are. operating properly, a leakage test is ,
required. Generally, a leakage test such as this is not considered to be reasonably added to the workscope of a typical cold shutdown outage.
ALTERNATE TESTING:
During each refueling outage, these valves will be checked for proper closure and leak tested.
RELIEF REQUEST NO VR-13 SYSTEM:
Decay Heat Removal (M-522)
VALVES:
CBS-035-CBS-036 ,
CATEGORY:
)
c FUNCTION:
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 IWV-3522. (IWV-3521) -
BASIS FOR RELIEF:
These are spring-loaded check 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.
ALTERNATE TESTING:
Each of these valves will be disassembled and inspected to ensure operability i during each refueling outage. {
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RELIEF REQUEST NO. VR-14 i
SYSTEM: 1 Reactor Building Spray (M-524)
{
l VALVES: )
l CBS-009 f CBS-010 CATEGORY:
I A/C' FUNCTION:
These valves open to provide a flowpath f rom 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 l provided by IWV-3522. (IWV-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 result in spraying down the Reactor'Suilding, which is highly undesirable.
ALTERNATE TESTING:
. During each refueling outage, each of these valves will be disassembled and manually exercised to ensure operability.
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l RELIEF REQUEST NO. .VR-15 SYSTEM:
Reactor Building Spray (M-524)
VALVES:
i CBS-021 CBS-022 '1 CBS-027 CBS-028 .:
SFV-29015 g SFV-29016 y .
CATEGORY:
C FUNCTION: .
These valves are check or stop-check valves that provide flowpaths from the !
Reactor Building spray additi've tanks to the Reactor Building spray pump ,
suction in order to effect sodium hydroxide distribution in the Reactor Building.
RE0VIREMENT:
Check valves shall be exercised at least once every three months, except as provided by IWV-3522. (IWV-3521)
BASIS FOR RELIEF:
Full flow testing of these valves would require injection of sodium hydroxide 9 into the Reactor Building ~ spray system and.the borated water storage tanks.
.This is unacceptable.
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, j 1
i
I ALTERNATE TESTING:'
l During cold shutdown periods, each'of these valves will' be partial-stroke j tested. J l
The motor operators and stem assemblies of SFV-29015 and SFV-29016 will be exercised quarterly.
.During each Reactor refueling outage, each valve will be disassembled and manually exercised to ensure operability. j l
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RELTEF REQUEST NO. VR-16 SYSTEM: l 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. ,
i REQUIREMENT: j Safety and relief valves shall be tested in accordance with Subsection IWV-3510. ;
BASIS FOR RELIEF:
i ANSI /ASME OM-1-1981 - Requirements for Inservice Performance Testing of !
Nuclear Power Plant Pressure Relief Devices, was developed to supercede the '
requirements of Subsection IWV-3510. This standard is more definitive and better suited to operational testing than is ASME/PTC 25.3 which'is referenced in IWV-3510.
ALTERNATE TESTING:
Safety and relief valves will be tested in accordance with the requirements of ANSI /ASME OM-1-1981.
'N RELIEF REQUEST NO. VR-17 SYSTEM:.
High Pressure Feedwater Heater (M-533) -l VALVES:
\.
.FWS-049' FWS-050 j CATEGORY C 4 l
FUNCTION:. - 'j These valves open-to provide a flowpath for minimum flow from the respective auxiliary feedwater pumps.
REQUIREMENTS:-
Check' valves shall be exercised at least once every 3 months, except as provided by IWV-3522 (IWV-3521) .
BASIS FOR RELIEF:
There is no way these valves can be verified to'be in the full'open positio'n without isolating the recirculation line for both auxiliary;feedwater pumps.
from 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 f full. flow, requires 'special. 4 (unusual) valve lineups and the installation of special test equipment. Such i testing is considered out of the . normal workscope expected during a typical cold shutdown (non-refueling) outage.
ALTERNATIVE TESTING' These valves will be exercised on a quarterly basis without verification.of ~
full flow. Verification of' full-flow through.the valves will be performed.
during each refueling outage.
1
s RELIEF REQUEST NO. VR-18 SYSTEM: l Decay Heat Removal (M-522)
VALVES: l l
DHS-017 DHS-018 CATEGORY ,
'A/C ;
FUNCTION:
These valves open.to discharge water from the decay heat si: tem inlet piping to the core flood tanks and close to provide containment isolation.
REQUIREMENT:
Check valves shall be exercised at least once every three months, except as l
provided by IWV-3522 (IWV-3521). I Valves that are normally open during plant operation and whose function is to prevent reversed flow shall be tested in a manner that proves that the disk travels to the seat promptly on cessation or reversal of flow (IWV-3522(a)) l BASIS FOR RELIEF: 1 Testing these valves in the closed direction requires isolation of the reactor coolant drain header and pressurization of the related ' core flood tank. This is a complex and time-consuming operation of'a sort that is not i normally included in the workscope of a non-refueling outage.
ALTERNATIVE TEST Each of these valves will be verified to close during each refueling outage.
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- g RELIEF REQUEST .NO. VR-19 '
-l SYSTEMS l Various
-VALVES-Category A gate valves
]
-CATEGORY:
A l
1 FUNCTION: {
Primary 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 IWV-3423(a) through (d) (IWV-3423).
BASIS'FOR RELIEF '
In many cases it.is impractical or undesirable to test gate valvesiin their 1 functional direction. In these instances, where valves are provided with a bonnet tap or other means of 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 I condition of the' downstream seating surface that must perform the leaktight: I service.
ALTERNATE TESTING i
' Category.A gate valves may be seat leak tested in a direction opposite to _
l that when the valve is performing its function. 'When_ testing is performed in this manner, a valve body vent will be open to atmosphere to ensure the effective seating surface is_ subjected to the full differential ~ pressure.
e m .
RELIEF RQUEST VR-20 SYSTEM Decay Heat Removal (M-522)
VALVES:
HV-26515 HV-26516 CATEGORY:
A FUNCTIONS:
Ie l These valves -are used for occasional sampling and draining of the core flood I
1 tanks and close to provide containment isolation.
RE0VIREMENT:
i i
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 IWV-3423(a) through (d) (IWV-3423).
BASIS FOR RELIEF:
l Testing these valves in the " accident direction" would require draining the !
core flood tanks, resulting in a 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 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, )
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.
ALTERNATIVE TESTING:
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.
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l APPENDIX A l
SUMMARY
INSERVICE TESTING PROGRAM l
- PUMPS - 1 I
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Appendix A: Summary-Inservice Testing Program - Pumps ,
I 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.
l P&IO 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 j then that measurement is made for that pump in accordance l with the Code. A reference to a relief request accompanying l the "Y" indicates some deviation from Code requirements. If .1 the character "N" appears, that particular parameter will l not be measured or observed and a relief request is_ provided !
if required. Requests for relief are identified as "PRXX".
All relief _ requests are included'in Section 2.2.
TEST INTERVAL The respective frequency of testing for each pump. The letter "Q" denotes a quarterly interval.
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-A 1
.o.m L..
l L
A TV SR QQ QQ EE QQQ QQ QQ QQ QQ TT N 7 I
0 P M
E T
NNN NN NN NN NN NN NN B YY YY YY I YYY YY YY YY V
OO OO 22 11 .
II II W
O 777 RRR RR RR RR e PP PP PP l L PPP - - - - - - b F - - - NN NN YY a NNN YY YY YY c S i S R l E S p W
U T S YY YY YY YY YY YY p P
E E YYY a M R A P s R 88 a M A RR A P PP R FS - - s G FS YY YY NN YY YY p IE YYY YY m _
O DR u _
R P p _
P 9 R l G TD P AA AA N EE AAA AA AA A AA NN l
a I
LE NNN NN NN YN NN NN T NP o S
E T
IS t y
D E
C I
V I
D N
111 222 555 22 22 55 44 22 55 33 33 55 44 44 55 55 44 55 00 77 55 MM l
p p
a 2
A R A MMM MM MM MM MM MM 1 E
0 S N
I Y
P S
S 222 22 22 33 33 33 22 1
R P
d R A n -
A L a 4 C
- 6 -
l u R S RR P EE _
RR TT h
- EE AA g A TT RR WW u AA EE o X WW TT GG r I YY DD AA NN h D AA EE WW II t N RR EE LL E PP FF WW OO I R
P LL SS AA OO P P AA Y . RR CC A VV GG RX s OO NN AU EE EE IA CC CC t MM II s
E EE DD L II II VV e M NN RR LL IN VV A OO II XE RR RR u q
N II TT UU UV EE EE DD TT CC EE AA EE HH BB RR AI RD R
r --
OO D - AA AA f PJ J R EE EE CC e UEN EII YY AA TT CC LO LL LL II i K - CC AA AT CC CC RR l APP EE EE UO UU UU OO e DD RR DM NN NN BB R MHH AB AB A8 AB A8 AB :
11 89 22 22 55 E 688 11 88 00 T W
U 333 222 66 22 99 22 11 33 77 44 44 77 O
N P - - - - - - - - - - - - -
PPP PP PP PP PP PP PP
- 0
{
APPENDIX B 1
SUMMARY
l INSERVICE TESTING PROGRAM l
- VALVES - !
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g3SO r - -- - - - . -------i- - -- --
- h. . _ _ __ ._ . . ___ ._m_-_____.__m...- _
1 I
I Reference Drawings j Drawing No. Rev. System Page 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 and 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-18 g 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
- 3 HP and Auxiliary Turbines System B-22 M-530, Sh 3. 17 HP and Auxiliary Turbines System B-26 M-532, Sh 1
- 9 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 1 M-537, Sh 3 12 Auxiliary Steam. System B-34 I M-543, Sh 1 6 Component Cooling Water System B-35 '
M-543, Sh 4 13 Component Cooling Water System B-36 M-544 20 Nuclear Service Raw Water System B-37 M-545 15 Nuclear Service Cooling Water System B-38 M-551- 27 Reactor Building Heating, Ventilating, B-41 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 Chemica1' Addition B-47 and Sampling System M-573 17 lurbine Plant Sampling System B-49 M-590, Sh 1 37 Plant Air System B-50 M-591, Sh 1 37 Auxiliary Gas System B-51 M-593, Sh 2 12 Miscellaneous Water Systems B-52
- The EFIC valves, included in the program, will be shown on later revisions of these drawings.
-B Appendix B: Summary-Inservice Testing Program - Valves-LEGEND Notation used in the valve summary table is.as follows:
VALVE The valve alpha-numerical identification.
C00R The location of the valve on the referenced P&ID.
s FUNCTION The functional system description of the valve.-
A CLASS The ISI classification. 'The characters'"NC" denote that the-particular valve is outside.the.ISI' boundary. .
CAT The valve category per paragraph IWV-2200.- j ,
SIZE The nominal valve size in inches. -
TYPE The valve type as follows:
CK Check GT Gate GL Globe BF Butterfly n PSV Safety / relief SCK Stop-check ,
ACT The valve actuator type as follows:-
i M0 Motor-operated A0 Air-operated SO Solenoid SA Self-actuated-MAN Manual POS The normal position of the valve during plant operation;- open~ or closed.
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-B >
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Appendix 8: Summary-Inservice Testing Program - Valves LEGEND (Cont.)
REQMT Test requirement as follows: .
FST0 Full-stroke exercise to open riosition with stroke-time measurement for power-operated valves. J 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- i 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 OM-1-1981 (5 or 10 years, as appropriate) i 10Y. See applicable relief request. l AP As practical or available. Refer to appropriate relief l request.
REMARKS Relief Requests are designated VR-XX. Refer to Section 3.2 for relief requests.
i
-B ...i
- - - - - W K - - - - - M R - - - - -
A S S 5 .5 5 5 5 - 5 -
M - - - - - - - - - - - - - W E R R - R - R R R R - R
- R V V V - V V V V V -
~ - - - - -
- Q - - - - - -
E - - - - -
R F F - F F F F F F #
F R R - R - R R R R R -
T O 0 0 O 0 O O - O -
M T T T T T T T T
- Q S S S S S S S S -
E F F F F F F F F
- R - - - - -
- S - - - - -
- O C C C C C C C - C -
P - - - - - - 6 A A A ,A A A A A -
T S S S S S S S S
- C A
E K K - K - K K K K K
- P C C C C C C C C -
Y - - - .- - -
T - - - - - -
- E - - -
~
Z 4 - 4 - 4 4 - 4 4 4 - 4 -
I 1 1 1 .1 1 1 1 1 *
- S - - - - -
- y - * -
- - - _- - - - 4
- T - - - - - - -
A C - C - C C - C C C - C
- B C - - - - - - -
- - - - - - M O - - - - - G N - - - - - M S - - - - -
- G S - - - - .
N A - - - - - - - - - - - - - M I L - - - - - M W C - - - - - -
A - - - - - -
R - - - - -
- D - - - - .-
- M _
t _ t - t t t t t - t .W n - n - n - n - n n n - n h e - e - e - e - e e e - e
- V - V - V V V V V - V
- s - s - s .- s - s s s - s
- l - l - 1 l ,l
- l l - l -
a - a - 4 - a A a a - a -
n - n _n - n - n n n - n .-
N r - r - r - r - r r r - r -
O e - e - e, - e - e e e - e -
I t - t - t t - t t t - t -
T n - n - n - n - n n n - n .-
T C I - I - - I - I I I - I -
N N .- -'I - - - -
A 3 N - x - x -~x - x x R
x - x - _
L F R - R - R - R - R R - R -
O - - - - - -
O C .-
R - - - - -
O R - - .'
T O - - - - -- - -
C O - - - - - - - - - - - - - -
A E
R C - -
- .-- ~
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i Appendix C COLD SHUTDOWN VALVE TESTING !
JUSTIFICATION l i
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COLD SHUTDOWN 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 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) l I
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 i interrupt letdown flow and result in fluctuations in pressurizer level and a i 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 the seal. This could result in seal failure and ultimately plant shutdown.
-C -.-
COLD SHUTDOWN TEST JUSTIFICATION (Continued) l 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-23616 - Reactor Coolant Pump Seal Water Supply This valve is normally open to provide a flow path for injection water to the 1 l
reaction coolant pumps. Closure of this valve during pump operation would j result in a loss of seal water flow with the probability of seal failure and i subsequent plant shutdown.
l Decay Heat Removal (M-522) I DHS-015 - Decay Heat Removal Discharge to RCS ;
DHS-016 - Decay Heat Removal Discharge to RCS j RCS-001 - Decay Heat Removal / Core Flood Discharge to RCS RCS-002 - Decay Heat Reinoval/ 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. 1 HV-26011 - Decay Heat Removal Supply to Pressurizer Spray l
Opening this valve would result in only one isolation valve between the high !
pressure reactor coolant system and the low pressure decay heat ' removal ;
system. This is considered imprudent.
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.
-C ..
COLD SHUTDOWN TEST JUSTIFICATION (Continued)
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.
HP and Auxiliary Turbines (M-530)
TV-1 through TV-4 -- Main Turbine Throttle Valves Exercising these valveA 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 11s insignificant and will'not 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.
-C -.-
COLD SHUTDOWN TEST JUSTIFICATION (Continued)
PV-20561 Main Turbine Bypass Valve PV-20562A Atmospheric Steam Dump PV-20563 through PV-20566 Main Turbine Bypass Valves PV-20571A Atmospheric Steam Dump 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. '
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 I would also require depressurization of the related steam generator.
HV-20521 and HV-20522 - Isolation Valves to Turbine Bypass Valves. l These valves are normally open. Closing these valves would depressurize and ,
possibly cool the downstream piping. Due to the length of piping downstream l of these valves, upon reopening, a pressure transient could result with the l potential for damaging the downstream piping or associated components.
\
4 Steam Generator (M-532) l FV-20525 Main Feedwater Iso to Steam Gen 205A '
FV-20526 Main Feedwater Iso to Steam Gen 2058 l FV-20575 Main Feedwater Bypass to Steam Gen 205A l 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 2058 '
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.
FWS-061 - Emergency Feedwater Check to Steam Gen 205A FWS-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.
-C ...
COLD SHUTOOWN TEST JUSTIFICATION (ContinuGd)
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.
Component Coolina Water System (M-543)
CCW-036 & SFV-46014 - Cooling Water Supply to Reactor Building SFV-46203 & SFV-46204 - Cooling Water Return From Reactor Building ,
CCW-194 & SFV-46906 - Cooling Water Supply to Control Rod Drives j SFV-46907 & SFV-46908 - Cooling Water 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 reouire continuous I
cooling.
Reactor Building 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 l These valves must remain closed and electrically disabled during plant operation per Rancho Seco Technical Specification 3.6.7.
j l
9
-C .._
k p .
\.
9 Appendix D
SUMMARY
OF PROGRAM CHANGES
\
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SUMMARY
OF PP MRAM CHANGES Summary of-Changes: Second 10-year Inservice Testing .
Program - Revision 2 vs. Revision 3 i General
- 1. The Program format is revised and improved.
t
- 2. The second 10-year Program (Revision 3) is based on the 1980 Edition of Section XI of the ASME Boiler and Pressure Vessel Code including the .
Winter,1981 Addenda.
Pumps:
General:
l a) Several new relief requests of a general nature are added to the {
Program including the following: )
PR-t- Allows comparison of test parameters to a continuous pump ,
curve instead of at a selected reference value for the 1 I
independent variable.
PR-2 Clarifies requirements for measuring pump vibration and allows trending of vibration in velocity units vs displa;erent.
) PR-3 Addresses deviations from the Code with respect to the range requirement of the vibration measuring instruments.
PR-4 Eliminates Action-required High limits and liberalizes the I i High Alert range given in Table IWP-3100-2. l PR-52 Eliminates the requirement to measure bearing temperatures.
l}' P44 Eliminates the requirement to measure static (no-flow) suction pressure for pumps that are in operation at the time the periodic tests are performed.
PR ill' Permits the use of installed instrumentation for measuring pump suction pressure.
M6ee!-r/p_;and Purification System Added a relief request (PR-7) to eliminate measurements of flowrate for Makeup and.HP injection Pumps during tests performed at intervals other than refueling.
Nuclear Service Water System-Added relief requests relAted to measuring suction pressure (PR-8) and flowrate (PR-10) when testing the Nuclear Service Water Pumps.
Nuclear ig4 ce i Raw Water System -
Added reYief requests related to measuring flowrate (PR-10) when testing the. Nuclear Service Raw Water Pumps.
-D '
l
SUMMARY
OF PROGRAM CHANGES (Continued) l HP and Auxiliary Turbines System l Clarified speed measuring requirement for the dual-drive auxiliary feedwater pump, P-318.
Spent Fuel Pool Cooling Spent Fuel Pool Cooling Pump No. P-272 is eliminated from the Program -
does not meet scope requirement per IWV-1100. j RC Chemical Addition and Sampling Added relief request (PR-12) for instrumentation associated with the flowrate measurement for the boric acid pumps (P-705A & B). j i
valves:
General a) The direction of exercising each valve is given in the tabulation.
b) The function / description for each valve is provided.
c) General editorial changes. i d) Justification for cold shutdown testing is provided in Appendix C l vs. relief requests. {
e) Manual valves are deleted except those leaktested per Appendix J '
(LLRT) or required to be operated for post-accident system alignment. The exercising and position verification requirements for the remaining manual valves are deleted except where valve i I
manipulation is required for post-accident system operation.
f) Paragraph 3.1.5 pertaining to test f requency tolerance is added.
g) Paragraph 3.1.7 pertaining to position indication testing is added.
h) Paragraph 3.1.8 pertaining to fail-safe testing is added.
- 1) A new relief request (VR-2) is included that clarifies the test frequency adjustment for valves that are tested during cold shutdown and are in Alert status.
j) Relief request VR-4 is included for simultaneous leak testing of Category A valves, k) Relief request (VR-1) is included elaborating on the stroke time analysis of fast-acting valves.
- 1) A relief request (VR-16) is included ' substituting the requirements of IWV-3510 with those of ASME Std OM1 for testing safety / relief valves.
m) The standard frequency for exercising valves is changed from monthly to quarterly.
n) A relief request (VR-19)'is provided for measuring leakrates of gate valves in a direction opposite that which relates to the -
leaktight function of the valves.
-D . . . -
)
SUMMARY
OF PROGRAM CHANGES (Continued) I 1
Reactor Coolant (M-520)
- 1. Deleted PSV-21511- no specific safety function I
- 2. Added the following valves:
1 HV-20533 HV-20580 '
HV-20534 HV-21522 HV-20579 HV-21528 3 1
Makeup and Purification (M-521) i
- 1. Valves SFV-22005 and SFV-22006 are exercised at cold shutdown vs.
quarterly.
- 2. The valve stroking requirements for HV-23801 are clarified.
- 3. Valves SFV-23809 through SFV-23812_ are exercised quarterly vs. at cold shutdown.
- 4. Valves SIM-019 through SIM-022 are exercised at refueling intervals vs cold shutdown. !
- 5. Valve HV-23504 is deleted from the Program - no safety function.
- 6. Added a requirement for partial stroking of SIM-036 and SIM-037 during operation (quarterly).
- 7. Valves PLS-045 and PSV-23505 are deleted from the Program.
l
- 8. Changed designation of SHV-23802 to HV-23802. 1
- 9. The following Category E valves are deleted:
SIM-001 SIM-055 SIM-003 SIM-056 SIM-038 SIM-057 SIM-039 SIM-059-SIM-042 SIM-068 SIM-044 SIM-069 ;
SIM-046 SIM-077 i SIM-051 SIM-053 1 SIM-080 SIM-054 j SIM-086
-D i WIO
SUMMARY
OF PROGRAM CHANGES (Continued)
- 10. The following valves are added:
SIM-023 SIM-078 SIM-025 SIM-079 SIM-026 SIM-081 SIM-043 ,
Decay Heat Removal System (M-522)
- 1. Added a leakage test requirement for HV-20001, HV-20002, DHS-015 and DHS-016.
- 2. RCS-001 and RCS-002 - Added full-stroke and leakage test requirements and recategorized as category A/C.
- 3. CFS-001 and CFS-002 - The stroke testing is clarified, added :
requirements to leak test and disassemble, and changed their category to l A/C. 1
- 4. HV-26011 - Added leak test requirements and recategorized as A vs B.
- 5. HV-26105 and HV-26106 - Changed exercising frequency to quarterly vs cold shutdown and changed categories from A to B (deleted leakrate test).
- 6. BWS-003, BWS-004, DHS-003 and DHS-004 - Change testing to full-stroke exercising quarterly vs. partial-stroke quarterly and full-stroke at refueling.
- 7. Added a relief request (VR-9) to modify the leakage rate acceptance criteria and evaluation for valves CFS-001, CFS-002, DHS-015, DHS-016 RCS-001, and RCS-002.
- 8. HV-26037 and HV-26038 - Deleted exercising requirements - passive valves.
- 9. CBS-035 and CBS-036 - Added a requirement to disassemble and inspect at refueling intervals.
- 10. Deleted DHS-057 and DHS-058 - No safety function.
- 11. Added relief request (VR-20) for leakrate testing of HV-26515 and HV-26516 in the reverse direction.
4-
SUMMARY
OF PROGRAM CHANGES (Continued)
- 12. Deleted the following category E valves:
BWS-001 DHS-035 BWS-002 OHS-036 DHS-001 DHS-055 DHS-002 DHS-056 OHS-005 DHS-486 OHS-006 DHS-495 DHS-012 RSS-020 DHS-011 RSS-021
- 13. The following valves are added:
HV-20005 DHS-017 HV-20006 DHS-018 HV-26515 DHS-497 HV-26516 DHS-498 HV-26517 RCS-042 HV-26518 Spent Fuel Pool Coolina (M-523) 1.
Deleted valves PSV-27003 and SFC-002.
_ Reactor Buildina Sorav System (M-524) 1.
\
CBS-009 and CBS-010 - Chan disassembly / inspection vs.ged the refueling test requirement to partial-stroke.
2.
Changed the excercising requirement from partial-stroke at each refueling to partial-stroke at cold shutdown and disassembly at each refueling for the below listed valves.
CBS-021 CBS-028 CBS-022 SFV-29015 C85-027 SFV-29016 3.
CBS-504 and CBS-505 - Changed exercising requirement te full-stroke quarterly vs. partial-stroke at refueling outages.
- 4. Deleted Category E valies as follows:
CBS-003 CBS-016 CBS-025 CBS-004 C85-018 CBS-026 CBS-007 C85-019 CBS-031 C85-008 CBS-020 CBS-032 CBS-013 CBS-023 CBS-045 CBS-014 CBS-024 CBS-046 CBS-015
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L -.
. _ _ . _ - - - - - - - - - - - - ^~~ ~ _ _ _ - - - - - - -
SUMMARY
.0F PROGRAM CHANGES (Continued) ,
t
- 5. Deleted safety / relief valves PSV-29013, PSV-29014.
HP and Auxiliary Turbines (M-530)
- 1. Changed valve number FV-30801 to _ read SFV-30801
- 2. Added the following valves:
FV-20525 FV-20576- HV-20521 I FV-20526 HV-20515 ' HV-20522 _
FV-20531 HV-20516 HV-20581 l i
FV-20532- HV-20517 HV-20582 FV-20575 HV-20518 MSS-068
- 3. Deleted category.E valves MSS-049, MSS-050, MSS-011, and MSS-012.
- 4. Changed test frequency of PV-20562 8 and C and PV-20571 8 and C to quarterly vs. cold shutdown. -
respectively.
- 6. Changed valve numbers SFV-20577 and SFV-20578 to HV-20577 and HV-20578, respectively.
- 7. Changed frequency \of testing MSS-051 and' MSS-052 to cold shutdown vs.
quarterly. -
Steam Generator (M-532)
- 1. FWS-013 and FWS-014 are deleted from the Program.
- 3. HV-20609, HV-20610, and HV-20611 - Recategorized as A and added-~
requirement for leak testing.
- 4. FWS-101 and FWS-102 - Recategorized as category- A' and added leaktest requirement.
- 5. Added FWS-080.
- 6. Category E valves FWS-063, FWS-064, FWS-119 and FWS-120 are deleted.
m.
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)
SUMMARY
OF PROGRAM CHANGES (Continued) l High-Pressure Feedwater Heater System (M-533)
- 1. FWS-047 and FWS-048 - Changed f requency of testing to quarterly vs. cold shutdown.
- 2. FWS-049 and FWS-050 - Changed frequency of exercising from quarterly to partial stroke quarterly and full-stroke at refueling outages.
- 3. Category E valves FPS-45, FWS-46, and FWS-51 through FWS-54 are deleted.
1 Condenser (M-536)
- 1. The following category E valves are deleted:
PCW-076 MCM-057 PCW-079 MCM-058
- 2. MCM-059 and MCM-060 - Changed f requency of testing to quarterly vs.
partial-stroke quarterly and full-stroke at cold shutdown.
Nuclear Service Raw Water (M-5441
- 1. The below listed category E valves are deleted:
NRW-001 NRW-005 NSW-015 NSW-060 NRW-002 NSW-0.06 NSW-016 NSW-061 NRW-003 NSW-007 NSW-017 NSW-062 NRW-004 HSW-008 NSW-025 NSW-063 NRW-005 NSW-009 NSW-026 NSW-064 NRW-006 NSW-010 NSW-055 NSW-065 NRW-007 NSW-011 NSW-056 NSW-066 .
NRW-008 NSW-012 NSW-057 NSW-067 NRW-019 NSW-013 NSW-058 NSW-068 NRW-020 NSW-014 NSW-059 NSW-070
- 2. The below listed thermal safety / relief valves are deleted:
l PSV-23704 PSV-29122 PSV-48018 PSV-52914 I PSV-23905 PSV-47305 PSV-48701 PSV-52915 PSV-23906 PSV-47306 PSV-48702 PSV-52916 PSV-29121 PSV-48017 PSV-52913 PSV-52917
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l
SUMMARY
OF PROGRAM CHANGES (Continued)
Nuclear Service Coolina Water (M-545)
- 1. The below listed category E valves are deleted:
NSW-004 NSW-087 l NRW-041 NSW-088 j NRW-042 NSW-083 l
NSW-001 NSW-084 NSW-089 NSW-002 NSW-085 NSW-090 j NSW-003 NSW-086 l
- 2. The below listed thermal safety / relief valves are deleted. l 1
PSV-50013 1 PSV-26029 PSV-26030 PSV-50014 i PSV-50015 -
PSV-48015 PSV-48016 PSV-50016 (
)
Reactor Building Heatina. Ventilating and Air Cond (M-551) I
- 1. SFV-53612 and SFV'-53613-Changed exercising frequency to quarterly vs. l cold shutdown.
- 2. Added leak test requirement to HGS-012 and HGS-013.
- 3. SFV-53503, SFV-53504, SFV-53604, and SFV-53605-Changed exercising frequency to cold, shutdown versus quarterly.
- 4. Added the following valves:
HV-53617 HV-53622 HV-70042 HV-70046 HV-53618 HV-53623 HV-70043 HV-70047 HV-53620 HV-70040 HV-70044 SFV-53615 HV-53621 HV-70041 HV-70045 SFV-53616 j Reactor Coolant Chemical Addition and samplina (M-570)
- 1. Added valves RSS-500, 8SW-35 and BWS-36. l
- 2. Deleted the following category E valves: ,
BWS-028 8WS-031 BWS-029 8WS-032 ;
1 8WS-030
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