ML20248H881
| ML20248H881 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/04/1989 |
| From: | ALABAMA POWER CO. |
| To: | |
| Shared Package | |
| ML20248H858 | List: |
| References | |
| FNP-1-M-042, FNP-1-M-42, NUDOCS 8910120127 | |
| Download: ML20248H881 (55) | |
Text
. __ _ _
o FNP-1-M-042
- 1. INTRODUCTION 1.1 GENERAL This document presents the program for inservice testing (IST) of pumps and valves at Unit 1 of the Farley Nuclear Plant (FNP) in compliance with the requirements of 10 CFR 50.5Ea. According to 10 CFR 50.55a (g)(4)(ii),
following completion of the first 120-month inspection interval, successive 120-month inspection intervals shall comply with the requirements of the latest edition and addenda of the American Society of Mechanical Engineers (ASME) Code incorporated by reference in paragraph (b) of 10 CFR 50.55a 12 months prior to the start of the 120-month inspection interval. The second 120-month inspection interval for Farley Unit I will commence on December 1, 1987. Based upon this date, the Farley Unit 1 IST program for the second 120-month inspection interval is in compliance with the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition with Addenda through Summer 1983.
This program contains relief requests which were granted on an interim basis per the NRC's letter dated December 10, 1987.
I.2 DEFINITIONS The terms below, when used in the Inservice Testing Program, are defined as follows:
Quarterly: An interval of 92 days for testing components which can be tested during normal plant operation.
Cold Shutdown: Testivj delayed until cold shutdown will commente as soon as cold shutdown condition is achieved, 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 achieving cold shutdown. Testing will continue until all tests are complete or the plant is ready to return to power.
Completion of testing is not a prerequisite to return tr pwer, and any testing not l completed at one cold shutdown will be performed during subsequent cold shutdowns before the refueling outage. No cold shutdown testing will be performed on any compone,ns tested less than 92 days prior to achieving cold shutdown. The 48-hour interval will not hold for planned cold shutdowns where all required testing will be completed. In addition, all components which have testing delayed to cold shutdown will be tested during each refueling unless I the component has been tested during the previous three months.
fM 0220127 sn oog gDn ADock c"U S I-l REV. 3 L_____ _
' 46 4
FNP-1-M-042 General Relief .
Request: VG-2 Components:
Category:
Code Requirements:
Valve General Relief Request VG-2 has been deleted.
Basis for Relief:
Alternate Testing:
General Relief Request: VG-3 Component: Containment Isolation Valves Code Requirements: Articles IW-3421 through IW-3425 require valve leak rate testing for each Category A valve in the Inservice Test Program. Article IWV-3427(b) specifies corrective action requirements for valves 6 in. and larger which fail testing.
Category: A, AC Basis for Relief: Containment isolation valves which are designated as Category A or AC are leak rate tented to the requirements of Appendix J to 10 CFR 50. Appendix J, 4 Type C, valve local leak rate test procedures and requirements fulfill the intent of Articles IW-3421 through IW-3425. NRC Generic Letter No. 89-04, Attachment 1, Item 10 states that the additional testing requirements of IWV-3427(b) are unreason-ably burdensome and without a conrnensurate benefit in extended valve operation.
04571 1-4 Rev.3
FNP-1-M-042 Alternate Testing: Containment isolation valves will be local leak rate tested to the requirements of Appendix J, Type C testing in lieu of those required by Articles IWV-3421 through Im/-3425. The g analysis of leakage rates and corrective action requirements of Articles IWV-3426 and IWV-3427 (a) will be performed. l General Relief Request: VG-4 Component: Pressure Isolation Valves Code Requirements: For Section XI Category A valves, IWV-3426 requires comparison of measured leakage rates with previous measured leakage rates.
Category: A, AC Basis for Relief: Technical Specification Section 3.4.7.2 defines the limiting conditions for operations and Section 4.4.7.2.2 defines the surveillance requirements for pressure isolation valves as follows:
"Each reactor coolant system pressure isolation valve specified in Table 3.4-1 shall be demonstrated operable pursuant to Specification 4.0.5 except that in lieu of any leakage testing required by Specification 4.0.5, each valve should be demonstrated operable by verifying leakage to be within the allowable leakage critera of 0.5 gpm per inch of nominal valve size with an upper limit of the maximum allowable leakage in Table 3.4-1; and the measured leak rate for any given test cannot reduce the difference between the results of the previcus test and the maximum allowable leakage specitted in Table 3.4-1 by more
. than 50%: )
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. PUMP RELIEF REQUEST 1 1
PR-11 System: Service Water Pump: P001A-A, P001B-A, P001C-AB, P001D-B, P001E-B Class: 3 Function: Provide cooling water to safety-related equipment.
Test Requirement: Table IWP-3100-2 specifies acceptable, alert, and required action ranges for pump flow testing.
Basis for Relief: The service water pumps must be tested in two-pump combinations to meet safe plant operation requirements (see Pump Relief Request PR-10). The pump test flow rate is measured by annubar flow elements (see Pump Relief PR-13) installed in the service water headers downstream of the strainers. The annubar flow elements have an instrument accuracy of 2% but, because of the system configuration, have an estimated installed system accuracy of up to 8%. The acceptable, alert, and required action ranges of Table IWP-3100-2 are based on an instrument accuracy of 2% and are inappropriate for this application.
Application of the Table IWP-3100-2 ranges would result in unnecessary pump maintenance and repair.
Alternate Testing: The service water pumps will be tested in two-pump combinations and pump flow rate measured using the installed annubar flow elements. The swing pump will be tested in combination with either of the other two pumps in the train to which it is aligned. Based on the installed accuracy of the annubar flow elements, the acceptable, alert, and required action ranges used for pump testing will be as follows:
Acceptable: .94 - 1.06 Qr Alert Low: .90 - <.94 Qr Alert High: >1.06 - 1.10 Qr Required Action Low: <.90 Qr Required Action High: >1.10 Qr 11-1-22 REV. 3
' '* PUMP RELIEF REQUEST PR-11 (cont.)
Alternate Testing (Cont'd): Considering the installed accuracy of the annubar flow elements, the use of these alternative ranges will be sufficient to detect pump degradation without causing unnecessary pump maintenance and repair.
If a two-pump combination flow rate falls in the alert or required action ranges each will be tested in combination with another appropriate pump to assess the individual pump operational readiness.
f 11-1-23 REV. 3
. ENP-1-M-042 PUMP RELIEF REQUEST PR-12 System: Service Water Pump: P001A-A, P001B-A, P001C-AB, P001D-B, POO1E-B 4
)
Class: 3 I Function: Provide cooling water to safety-related e quipment.
-Test Requirement: IWP-4500 specifies measuring vibration at a pump housing or its structural support unless it is separated from its driver by a resilient mounting.
Basis for Relief: These pumps are submerged in a pit which makes them inaccessible for measuring vibration amplitude at the pump bearings. I Alternate Testing: Vibration amplitude is to be measured on the top of the motor housing (which contains l the motor thrust bearing) horizontally in two planes 90 degrees apart. l I
1 0387I II 24 REV. 3
FNP-1-M-042 PUMP RELIEF REQUEST l PR-13 i system: Service Water Pump: P001A-A, P001B-A, P001C-AB, P001D-B, POO1E-B l '
Class: 3 Function: Provide cooling water to safety-related e quipment. ;
Test Requirement: Table IWP-4110-1 requires that flow rate q instrument accuracy be +2 percent of 1 full-scale.
Basis for Relief: In order to obtain the 1.1 percent accuracy for the installed annubar flow elements, they must be installed with at least 3 to 4 pipe diameters downstream and 6 pipe diameters upstream. Due to system pipe configuration, the downstream installation is in compliance but the upstream installation is a half-pipe diameter short. The annubars are certified for a 0.1 percent repeatability. Repeatability is a more important consideration in monitoring for pump flow degradation. All flow measuring instrumentation associated with the annubars is in compliance with the requirements of Table IWP-4110-1.
Alternate Testing: The installed annubar flow elements will be used to measure pump test flow rate to the requirements of pump Relief Request PR-11. l' 0387I II-1-25 REV. 3 I
i
- - _ - - - _ _ _ _ _ - - _ _ l
4 FNP-1-M-042 PUMP RELIEF REQUEST PR-14 i
System Service Water Pump: POO1A-A, POO1B-A, P001C-AB, P001D-B, j POOlE-B Class: 3 Function: Provide cooling water to safety-related equipment.
Test Requirement: Table IWP-4120 requires that the full-scale range of each instrument be no more than three times the reference value.
Basis for Relief: Reference values for discharge pressure for these pumps are between 88 and 92 l psig. This would require discharge pressure gauges of 0-265 psig maximum.
The accuracy required for these gauges would be 2 percent of 265 psig, which is 15.3 psig. The installed pump discharge pressure gauges are 0-300 16.0 psig. 'l Although the installed instruments are above the maximum range limits, they are essentially equal to the accuracy l requirements and are therefore adequate for pump testing.
Alternate Testing: The installed instruments will be used for taking inlet pressure measurements during pump testing. l
.. 2.
l 0387I II 2 6 G E N REV. 3
FNP-1-M-042 PUMP RELIEF REQUEST PR-15 System: Component Cooling Water
- Pump: P001A-B, P001B-AB, P001C-A Class: 3 Function: Provide cooling water to safety-related equipment.
Test Requirement: IWP-3100 requires that each measured test quantity be compared to the reference value of the same quantity.
Any deviations determined shall be compared to the limits given in Table IWP-3100-2. j Basis for Relief: This system does not have an installed pump test line and system operating conditions will not allow adjusting system resistance without significant impact on plant opertions. This is a variable resistance system that is in continuous operation during all modes of plant operation. Depending on plant operating conditions and climatic conditions, the cooling requirements range from minimum cooling loads to 100 percent with many of the loads automatically placed in operation in response to local temperature requirements. Because of these normal operating requirements, it is not possible to specify a reference test flow path or flow rate that can be repeated for each test.
Alternate Testing: Pump testing will be performed with the systam in the as-found operating configuration and the test results compared with a curve of. reference values . whir:h ast1b.%sh th : 31stionship between flow rate and differential pressure in a ba'nd around the design point. The " Required Action" and " Alert" ,
ranges of Table IWP-3100-2 will be applied. 1 0387I II-1 27 REV.3 1
>b :
FN P-1-M-042 PUMP RELIEF REQUEST FR-16 System:. Diesel Generators Fuel Oil Transfer Pump: P501 A-A, P5018-B, P502A-A, P502B-B, P503A-A, P503B-B, P504A-A, P5048-B Class: 3 Function: Transfer diesel generator fuel oil from the storage tanks to the diesel generator day tanks.
Test Requirement: Measure pump test inlet pressure, differential pressure and flow rate in accordance with the requirements of IWP-3100 and pump test duration requirements of IWP-3500.
Basis for Relief: The diesel generator fuel oil transfer pumps are located inside the storage tank with the pump discharge plenum and motor bolted to a flange on top of the tank. None of the pumps have installed instrumentation to measure either flow or discharge pressure. The only possible flow measurement is by measuring change in day tank level over time. The 4075 K.W. Diesel Generators have, by design, a maximum fuel consumption of 5.6 gpm and the 2850 K.W. units have a fuel consumption of 4.2 cpm. Plant procedures require that day tank level be maintained approximately 80 percent full. To comply with the Code requirement to run the pumps for five minutes prior to taking test measurements would require draining the day tanks below a safe operating level.
Altemate Testing: Pump test flow rate will be obtained by measuring a change in day tank level over time. A day tank level change of approximately 10 percent shall be timed and the flow n_te determined from tank curves. An Alert Range of +6% and a Required Action Range of +10% shall be applie~d as provided by IWP-3210 and clariTied by Code Interpretation XI-1-79-19. Also, flow rates of 5.6 gal. Anin. for the P501 A/B and P502 A/B pumps and 4.2 gal./ min. for the P503 A/B and P504 A/B pumps will be applied as an absolute minimum.
0380L 11-1 28 Gen. Rev. 3
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FNP-1-M-042' PUMP RELIEF REQUEST PR-17 System: Diesel Generators Fuel 011 Transfer Pump: P501A-A, P501B-B, P502A-A, P502B-B, P503A-A, P503B-B, P504A-A, P504B-B
. Class: 3 Function: Transfer diesel generator fuel oil from the storage tanks to the diesel generator day tanks.
Test Requirement: Measure pump vibration in accordance with IWP-3100.
Basis for Relief: The diesel generator fuel oil pumps are located inside the storage tanks with
.the pump discharge plenum and motor bolted to a flange on top of the tank.
The pumps are inaccessible for pump bearing vibration measurements.-
Alternate Testing: Motor vibration measurements will be performed quarterly in lieu of Code required pump vibration measurements.
0387I II 29 Gen. REV. 3
,. .FNP-l-M-042~
[ +-
l PUMP RELIEF REQUEST PR-18 t-
- - . System
- All i
Pump: All Class: 2, 3 Function: Various
. Test Requirement: :IWP-4120 requires that the full scale range of each instrutunt be no more than three times the reference value.
Basis for Relief: FNP uses an IRD Model 618 for monitoring pump vibrations. -The IRD Model 818 is a microprocessor- l controlled digital vibration monitor. When used in the English measurement mode the instrument autoscales in decade ranges. The requirement of IWP-4120 is not appropriate for vibrational measurement'using this type of instrument. The accuracy of the' instrument is 5% over all ranges.
The IRD provides a digital display of vibration measurement to three (3) decimal places. ' This instrument provides significantly higher accuracy-
-than an analog amplitude meter which is read visually and subject to human error and parallax.
This problem is recognized in An American National Standard Inservice Testing of_ Pumps, OM-6-7/15/87 (draft Rev,11), paragraph 4612(c).
Alternate Testing: The autoscaling digital vibretion monitor will be j used for Code required pump vibration measurements.
11-1-30 Rev. 3 i
l" p ,
3 FNP-1-M-042
[ III.4 DRAWING' LIST' ASME Class 1, 2, and 3 Systems 9
Boundary i
System Diagram P&ID No. No.
Reactor Coolant (Q1B13) D-175037/1 D-351114/1 D-175037/2 D-351114/2 RER/LHSI(Q1E11) D-175038/1 D-351115/1 D-175038/2 D-351115/2 D-175041 D-351118 Reactor. Cavity Cooling (Q1E12) .D-175010/2 D-351108/2 Containment Spray (Q1E13) D-175038/3 D-351115/3 Containment Isolation (Q1E14) D-175010/2 D-351108/2-Penetration Room Filt. (Q1E15) D-175022 D-351126 HHSI/CVCS (Q1E21) D-175038/1 D-351115/1 D-175038/2 D-351115/2 D-175039/1 D-351116/1 D-175039/2 D-351116/2 D-175039/3 D-351116/,3 Reactor cavity Post-LOCA Dilution (Q1E22) D-175019 D-351109 Post-Accident Containment Vent and Sample (Q1E23) D-175019 D-351109 Liquid Waste Disposal (Q1021) D-175004/1 D-351105/1 l D-175042/1 D-151119/1 Steam Generator Blowdown.(Q1G24) D-175071/1 D-351122/1-Spent Fuel Pool Cooling (Q1G31) D-175043 D-351120 Main Steam (Q1N11) D-175033/1 D-351110/1 Auxiliary Steam (Q1N12) D-175033/2 D-351110/2 Feedwater (Q1N21/Q1C22) D-175073 D-351123 Auxiliary Feedwater (Q1N23) D-175007 D-351106
-Chemical Injection (N1N25) D-175000/1 D-351102/1 Demineralized Water (Q1P11) D-175047 D-351121 Containment Purge (Q1P13) D-175010/1 D-351108/1 Sampling (Q1P15) D-175010/2 D-351108/2 D-175009/1 D-351107/1 D-175009/2 D-351107/2 Service Water (Q1P16) D-170113 D-351128 D-170119/1 D-351130/1 D-170119/2 D-351130/2 D-170119/3 D-351130/3 D-175003/1 D-351104/1 D-175003/2 D-351104/2 Camponent Cooling Water (Q1P17) D-175002/1 D-351103/1 D-175002/2 D-351103/2 Service Air (Q1P18) D-175035/1 D-351112/1 0381I III-5 REV.3
FNP-1-M-042 ASME Class 1, 2, and 3 Systems (cont.)
Boundary System Diagram P&ID No. _ No.
Instrument Air (Q1P19) D-175034/1 D-351111/1 D-175034/2 D-351111/2 Cont'ainment Cooling and Purge (Q1P23) D-175010/1 D-175034/3 D-351111/3 D. G. Air Start (Q1R43. QSR43) D-351108/1 g D-170806/1 D-351133 D-170806/2 D-351134 l
D-170807/1 D-351135 D-170807/2 D-351136 Non-Radioactive Vent (QSV47) D-175012 Spent Fuel Fool Vent and Filtration D-351124 (Q1V48)
D-175022 D-351126 Control Room HVAC and Filtration (QSV49)
D-175012 D-351124 D. G. D-205012 D-351125 Fuel Oil Transfer (QSY52) D-170060 D-351132 e
03811 III-6 REV. 3
L' FNP-2-M-042 RELIEF REQUEST Q1E11-RV-3 System: LHSI/RHR Valve: QVO51A, QVO51B, QVO51C Category:. C Class: 1 Function: HHSI/LHSI to RCS cold leg injection line check valves.
ASME Section XI Quarterly Test Requirements: Verify forward-flow operability quarterly or at cold shutdown ,
(IWV-3521). '
Basis for-Relief: Disassembly of these valves can only be done with the RCS depressurized and the reactor vessel level at mid-plane.
Alternate Testing: Valves will be disassembled on a staggered basis at refueling per Request Q1E11-RV-5.
Relief l
III-1-2-9 REV.3
~
g FNP-1-M-042 1
RELIEF REQUEST ]
Q1E11-RV-4 System: LHSI/RHR j Valve: QV021A, QV021B, QV021C l i
Category: AC ,
1 Class: 1 ASME Section XI Quarterly Test Requirements: Verify forward flow operability (IWV-3522).
Basis for Relief: These 6-inch Velan swing check valves are located in the low-head safety injection flow paths to the reactor coolant system cold legs. Individual line flow rate cannot be used to verify individual valve operability due to lack of instrumentation. I Alternate Testing: one of these valves will be disassembled and manus 11y full stroke tested at each refueling on a staggered test basis.
The valve internals will be verified as structurally sound (no loose or corroded parts) and the disk manually exercised to verify full stroke capability. If the disassembled valve is not capable of being full-stroke exercised or there is binding or failure of valve internals, the remaining valves in that group must also be disassembled, inspected, and manually full-stroke exercised during the same outage.
III-1-2-10 REV.3
FNP-1-M-042 RELIEF REQUEST QlEll-RV-5 System: LHSI/RHR Valve: QVOSIA, QVO51B, QVO51C Category: C Class: 1 ASME Section XI Quarterly Test l Requirements: Verify forward flow operability i (IWV-3522).
Basis for Relief: These 6-inch Velan swing check valves ,
)
are' located in the shared low-head and high-head safety injection lines to the reactor coolant system cold legs.
Individual line flow rate cannot be used to verify individual valve operability due to lack of instrumentation.
l Alternate Testing: one of these valves will be disassembled and manually full stroke tested at refueling on a staggered test basis.
The valve internals will be verified as structurally sound (no loose or corroded parts) and the disk manually exercised to verify full stroke capability. If the disassembled valve is not capable of being full-stroke exercised or there is binding or failure of valve internals, the remaining valves in that grouo must also be disassembled, inspected, and !
manually full-stroke exercised during the same outage, i
l l
111-1-2-11 REV . 3 1
FNP-1-M-042 RELIEF REQUEST Q1E11-RV-7 System: LHSI/RHR Valve QV021A, QV021B, QV021C Category: AC Class: 1 Function: LHSI/RHR to RCS cold leg injection line j check valves l
ASME Section XI Quarterly Test Requirements: Verify forward flow operability quarterly or at cold shutdown (IWV-3521)
Basis for Relief: Disassembly of these valves can only be done with the RCS depressurized and the reactor vessel level at mid-plane.
Alternate Testing: Valves will be disassembled on a staggered basis at refueling per Relief g Request Q1E11-RV-4 1
i l
l l
I III-1-2-13 REV.3 l i
COLD SHUTDOWN TEST JUSTIFICATION Q1E12-CS-1 System: Reactor Cavity Cooling Valve: QV001A, QV001B Category: B Class:
ASME Section XI Quarterly Test -
Requirements: Exercise, time and fail.
Cold Shutdown Test Justification: Technical Specifications impose specific limits on containment temperature during normal operation. Failure of either of these valves in the closed position could cause these limits to be exceeded at the reactor cavity sample points and would result in a forced plant shutdown.
Quarterly Part Stroke Testing: Valves full stroke on initiation and cannot be partial-stroke exercised.
Cold Shutdown Testing: Exercise, time and fail.
III-1-3-2 Rev.3 4
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FNP-1-M-042 RELIEF REQUEST QlE13-RV-3 Systems Containment Spray Valves. QV007A, QV007B Category: C Class: 2 Function: Spray additive tank to eductor line check valves.
ASME Section XI Quarterly Test Requirements: verify forward-flow operability.
Basis for Relief: The only way to verify forward-flow operability is by measuring for design flowrate through the line while operating the containment spray pumps under design flow conditions. There are no system design provisions for performing full-flow pump testing, except when spool pieces are installed and full-flow pump testing is performed at refueling. Quarterly pump testing is through a small 2-inch line from the pump discharge back to the RWST. With this test configuration, there is no flow through the valves, and testing for flow through the check valves is not possible without opening additional valves which vill introduce sodium hydroxide into the RWST (ECCS water supply).
Alternate Testing: One valve will be disassembled and manually full stroke tested at each refueling on a staggered test basis. The valve internals will be verified as structurally sound
. (no loose or corroded parts) and the disk manually exercised to verifv full stroke canabilitv. If the disassembled
. valva is not capable of be'ing full-stroke exerc, sed or there is binding or failure of valve internals, the remaining valve must also be disassembled, inspected, and manually full-stroke exercised during the same outage.
1 0363I III-1-4-6 Rev. 3 j
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FNP-1-M-042 RELIEF REQUEST QlE21-RV-2 System: SI/CVCS Valve: OV032A OV032B OV032C, QV037A,, QV037B,, QV037C l Category: AC Class: 1 Function: Accumulator discharge to RCS check valves.
ASME Section XI Quarterly Test Requirements : Verify forward flow operability.
Basis for Relief: The safety injection system accumulator tanks are isolated from the RCS by these normally closed check valves. Each accumulator is charged with a nitrogen blanket from 600 to 650 psig. This pressure'is insufficient during operation to inject into the RCS. If these valves were to be exercised at cold shutdown, the contents of the tank would be dumped into the RCS at the charge pressure of 600 to 650 psig which would result in the overpressurization of the RCS.
Alternate Testing: one of these valves in each of the three- '
valve groups will be disassembled and visually inspected on a staggerd test basis at each refueling. The valve internals will be verified as structurally.y sound (no loose or corroded parts) and the disk manually exercised to verify full stroke capability. If the disassembled valve is not capable of being full-stroke exercised or there is binding or failure of valve internals, the remaining valves in that group must also be disassembled, inspected, and manually full-stroke exercised during the same outage.
III-1-7-17 REV. 3
o I: FNP-1-M-042
.7 RELIEF REQUEST QIE21-RV-4 System: SI/CVCS Valve: QV062A, QV062B,-QV062C Category: C
. Class: 1 Function: Boron injection tank to RCS cold leg line check valves.
ASME Section XI Quarterly Test Requirements: Verify forward flow operability quarterly or at cold shutdown (IWV-3521).
Basis for Relief: The only possible way to verify full-flow operability of these check valves is by using the CVCS charging pump flow through the boron injection tank into the RCS cold legs. However, injecting water into the RCS through the boron injection tank during power operation exposes the safety injection nozzles to thermal shock and interrupts normal charging and letdown. Injection of CVCS charging pump flow at cold shutdown would result in a low temperature overpressurization of the RCS.
Verification of full design flow rate operability cannot be done at cold shutdown due to back pressure from the RCS. Verification of full flow operability can only be done at refueling with the RCS depressurized, the reactor vessel head removed, upper internals in place, and the refueling cavity at refueling level.
Disassembly of these valves can only be done with the RCS depressurized and the reactor vessel level at mid-plane.
Alternate Testing: Forward flow operability will be verified by full flow test or by disassembly. One of these valves will be disassembled and manually full stroke tested at each refueling on a staggered test basis.
The valve internals will be verified as structurally sound (no loose or corroded parts) and the disk manually exercised to verify full stroke capability. If the disassembled valve is not capable of being full-stroke exercised or there is binding or failure of valve internals, the 111-1-7-19 Rev. 3 1
1
- _ _ _ _ . __ _ 1
m , ,
_i. '
FNP-1-M-042 1L*? >
'Q1E21-RV-4 (cont.)
~ Alternate Testing:x(cont )
.- remaining valves in. that group must also be . .,
disassembled, inspected, and manually full-stroke exercised'during the.same outage.
p t
111-1-7-20 Rev. 3 L_______________________________
. FNP-1-M-042 RELIEF REQUEST Q1E21-RV System: SI/CVCS Valve: QV063, QV068, QV072 Category: B Class: 2 Function: Safety injection (SI) to the RCS hot and cold legs containment isolation valves.
ASME Section XI Quarterly Test Requirements: Exercise and time.
Basis for Relief: Exercising these valves during normal i operation would result in injecting charging water flow directly into the RCS. This diverted charging water bypasses the regenerative heat exchanger which would cause thermal shocking to the RCS piping.and would also cause an overtemperature condition in the normal CVCS letdown line. Normal plant practice is to collapse the pressurizer steam bubble early in the shutdown procedure and cool the plant down in the solid condition. This is normally done well before reaching cold shutdown conditions.
There is a period of time after reaching Technical Specification defined cold shutdown when one charging pump is maintained in operation. By plant procedure one charging pump is maintained in operation to maintain flow to the reactor coolant pump seals until the reactor vessel is drained down to the mid-plane level. If these valves were exercised open during that period of operation, charging pump flow would be injected directly in to the RCS. Over-pressure protection during cold shutdown nyeration is provided by RHR pump suction relief valves QV015A,B. This injection of charging pump flow could result in lifting these relief valves. '
Alternate Testing: Exercise and time during cold shutdown when the RCS is drained down to the mid-plane level and all charging pumps are secured or placed in an alignment that allows testing.
III-1-7-21 GEN. REV 3 l
[ .g FNP-1-M-042 {
RELIEF REQUEST l Q1E21-RV-6 1 l
I System: SI/CVCS Valve: QVO66A, QVO66B,,QVO66C, QVO78A, QVO78B, QVO78C, QVO79A, QVO79B, QVO79C I
Category: C Class: 1 Function: Safety injection to the RCS check valves.
ASME Section XI Quarterly Test Requirements: Verify forward flow operability quarterly or at cold shutdown (IWV-3521).
Basis for Relief: Verification of forward flow operability can only be performed by injecting charging water into the RCS. The charging pumps have insufficient head to overcome normal RCS operating pressure for a full flow test. Partial testing using the charging pumps would inject CVCS water which has bypassed the regenerative heat exchanger and would result in thermal shock to the RCS piping. Verification of full design flow rate operability cannot be done at cold shutdown due to back pressure from the RCS. Verification of full flow operability can only be done at refueling with the RCS depressurized, the reactor vessel head removed, upper internals in place, and the refueling cavity at refueling level. ;
Disassembly of these valves can only be done with the RCS depressurized and the reactor vessel level at mid-plane.
Alternate Testing: Forward flow operability will be j verified by full flow test or by
% disassembly on a staggered basis at l!
refueling per Relief Request Q1E21-RV-10.
l I I I 7 -2'2 REV. 3
_, FNP-1-M-042 RELIEF REQUEST Q1E21-RV-7 System: SI/CVCS Valve: QV122A, QV122B, QV122C Category: C Class: 2 Function: Charging pump discharge line check valves. !
ASME SECTION XI Quarterly Test Requirements: Verify forward flow operability.
Basis for Relief: These charging pump discharge check valves cannot be verified for full flow operability quarterly. Normal operating charging flow is automatically controlled by downstream flow control-valve QV347 in response to RCS operating conditions. To inject full flow into the RCS during normal operation would result in undesirable RCS boron concentrations and system pressure, temperature and level transients.
Full-stroke exercising these valves at cold shutdown would result in RCS pressure and level transients due to limitations on letdown capability.
Alternate Testing: Valves will be partial-stroke exercised quarterly and verification of full forward flow operability performed at refueling.
I I I-1 2 3 GEN. REV.3
FNP-1-M-042 RELIEF REQUEST Q1E21-RV-8 System: SI/CVCS l Valve: QV249A, QV249B Category: A Class: 2 !
Function: CVCS seal water flow to the reactor coolant pumps containment isolation valves.
ASME Section XI Quarterly Test Requirements: Exercise and time.
Basis for Relief: Exercising these valves during normal operation or at cold shutdown results in a loss of normal seal water to the RCS pump seals. If seal water is terminated, reactor coolant is forced from the high pressure RCS into the seals. Reactor coolant normally contains a high particulate matter concentration which is carried with RCS inleakage and contaminates the seals.
Westinghouse has studied this problem (see Westinghouse Document NSD TB-7515, 1978) and recommends that seal flow be maintained at cold shutdown as well as during normal operations.
Alternate Testing: Exercise and time at cold shutdown when the RCS is vented or open to the atmosphere.
I I I-1 2 4 GEN. REV. 3 l
l
. FNP-1-M-042 RELIEF REQUEST Q1E21-RV-9 t
System: SI/CVCS Valve: QV326A, QV326B, QV327A, QV327B i
Category: B Class: 2 Function: CVCS charging pump discharge header block valves.
ASME Section XI Quarterly Test Requirements: Exercise and time.
Basis for Relief: During normal operation only one charging pump is in operation which supplies both charging water to the RCS and seal water to the RCS pump seals.
Due to system design configuration, exercising any of these valves will terminate either normal charging flow or seal water flow. Disruption of charging water flow would decrease significantly the capability of the CVCS to provide the proper boron concentration. If seal water is terminated,. reactor coolant is forced from the high pressure RCS into the ceals and can cause seal degradation. Valves full-stroke on initiation and cannot be partial stroke exercised.
Alternate Testing: Exercise and time at cold shutdown when the RCS is vented or open to atmosphere.
N l
III-1-7 -2 5 GEN. REV. 3
__ . _ _ _ _ _ _ _ _ .__ _.__._.._.___...._m
FNP-1-M-042 I
^
RELIEF REQUEST Q12E21-RV-10 System: SI/CVCS Valve: QV062A, QV062B, QV062C j QV066A, QV066B, QV066C i QV078A, QV078B, QV078C QV079A, QV079B, QV079C Category: C S Class: 1 l Function: Safety injection to the RCS check valve.
ASME Section XI Quarterly Test Requirements: Verify forward flow operability (IWV-3522).
Basis for Relief: These 2-inch Kerotest check valves are located in the parallel high head injection flow paths to the reactor coolant system. Individual line flow rate cannot be used to verify individual valve operability due to lack of instrumentation.
Alternate Testing: One of the valves in each of the three-valve groups will be disassembled and manually full stroke tested at each refueling on a staggered test basis. The valve internals will be verified as structurally sound (no loose or corroded parts) and the disk manually exercised to verify full-stroke capability. If the disassembled valve is not capable of being full-stroke exercised or there is binding or failure of valve internals, the remaining valves in that group must also be disassembled, inspected, and manually full-stroke exercised during the same rctage. ;
1 l
1 l
111-1-7-26 REV. 3 .
l
_ _ _ _ _ _ _ _ _ _A
FNP-1-M-042 RELIEF REQUEST c .
. System: SI/CVCS Valves' gV077A,.QV077B, QV077C Category: AC Class: 1 Function: HHSI to RCS hot Aeg injection line check' valves.
ASME.Section XI !
Quarterly Test Requirements: . Verify forward flow operability quarterly or at cold shutdown (IW-3521 ) .
Basis-for Relief: Disassembly of these valves can only be done with the RCS depressurized and the reactor vessel at mid-plane.
Alternate Testing: Valves will be disassembled on a a staggered basis at refueling per Relief Request Q1E21-RV-14 l III-1-7 -27 REV.3
_ _ _ _ _ _ _ _ _ _ _ _ - - - - - _ - - - - - - - - - - - - - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -- - -- -------------------------------J
'-~*
FNP-1-M-042 RELIEF REQUEST Q1E21-RV-12 System: SI/CVCS Valve: QV115A, QV115B, QV115C Category: AC Class: 2 Function: CVCS seal injection to RCS pumps.
ASME Section XI Quarterly Test Requirements: Verify forward flow operability.
Basis for Relief: These valves must remain open to allow operation of the reactor coolant pumps and these pumps are required to be operable by Technical Specifications prior to entry into mode 3. Technical Specification 3.4.7.2.e requires a total flow of no more than 31 gpm through all three valves. Administrative controls require a flow of at least 6.7 gpm through each valve.
Alternate Testing: The total flow of less than 31 gpm will [
be monitored every 31 days per Technical l Specifications. If flow drops below 6.7 gpm a plant main control board alarm l is actuated and flow is reestablished via annunciator response procedures.
NOTE: Per NRC's interim approval of the Unit 2 Inservice Testing Program for Pumps and Valves dated 3/31/89 Enclosure 1,
' Item 2; thic testing is not a deviation from the Code requirements and relief is not necessary. The basis for this was discussed with the NRC and it was concluded that the testing defined in the NRC Generic Letter 89-04,
" Guidance on Developing Acceptable Inservice Testing Programs"., Attachment 1 Position 1 is not applicable to these valves since the maximum flow rate specified in the Technical Specifications is limited to less than 31 GPM, each line being alarmed at flow less than 6.7 GPM.
l III-1 28 REV. 3 i
. . . 1
! L. ,
ENP-1-M-042 RELIEF REQUEST Q1E21-RV-13 System: SI/CVCS Valve: QV121A, QV121B, QV121C Category: C Class: 2 Function: Charging pump min. flow line check valves.
Quarterly Test Requirements: Verify forward flow operability.
Basis for Relief: In verifying full forward flow !
operability would require measuring the flow rate through each of the charging pump minimum flow lines. Neither the individual minimum flow lines nor the common header is instrumented to measure flow rate.
Alternate Testing: One of these valves will be disassembled and manually full stroke tested at each ,
refueling on a staggered test basis. The !
valve internals will be verified as structurally sound (no loose or corroded parts) and the disk manually exercised to verify full stroke capability. If the disassembled valve is not capable of being full-stroke exercised or there is binding or failure of valve internals, the remaining valves in the group must also be disassembled, inspected, and manually full-stroke exercised during the same outage.
III-1-7-2 9 REV. 3
2 ' I
- . FNP-1-M-042 l
RELIEF REQUEST Q1E21-RV-14
)
System: SI/CVCS l Valve: QV077A, QVO77B, QV077C Category: AC Class: 1 Function: HHSI to RCS hot leg injection line check valve.
ASME Section XI Quarterly Test Requirements: Verify forward flow operability (IWV-3522).
Basis for Relief: These 6-inch Velan swing check valves .)
are located in the safety injection lines to the reactor coolant system hot legs. Individual line flow rate cannot be used to verify valve operability due to lack of instrumentation.
Alternate Testing: One of these valves will be disassembled and manually full stroke tested at each refueling on a staggered test basis.
The valve internals will be verified as stru'cturally sound (no loose or corroded parts) and the disk manually exercised to verify full stroke capability. If the disassembled valve is not capable of being full-stroke exercised or there is binding or failure of valve internals, the remaining valves in that group must also be disass.embled, inspected, and manually full-stroke exercised during the same outage.
III-1 3 0 REV. 3
l 1 1 RELIEF REQUEST j r
Q1N23-RV-1 System: Auxiliary Feedwater Valve: QV006,QV007A,QV007B Category: C
);
Class: 3 i i'
Function: Condensate storage tank to auxiliary feedwater pump suction line check valves.
ASME Section XI Quarterly Test
' Requirements: Verify reverse flow closure.
Basis for Relief: There are no system design provisions for verification of reverse flow closure. The only possible test method would involve isolating the condensate storage tank, draining a large section of piping, and injecting service water into the auxiliary feedwater system. The service water is of poor quality and would contaminate the auxiliary feedwater piping. It j cannot be guaranteed that flushing will remove all '
contamination after testing. Any contaminants which remain in the piping may be injected into the steam generators which could adversely affect secondary water chemistry and contribute to steam generator degradation.
Alternate Testing: One of the QV007A, B valves will be disassembled and manually full stroke tested at each refueling on a staggered test basis. The valve internals will be verified as structurally sound (no loose or corroded parts) and the disk manually exercised to verify full stroke capabililty. If the disassembled valve is not capable of being full-stroke exercised or there is binding or failure of valve internals, the remaining valve must also be disassembled, inspected, and manually full-stroke exercised during the same outage.
Valve QV006 will be disassembled and manually full stroke tested at each refueling. The valve internals will be verified as structurally sound (no loose or corroded parts) and the disk manually exercised to verify full stroke capability.
111-1-16-7 REV. 3
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FNP-1-M-042
.L RELIEF REQUEST Q1P16-RV-3 System: Service Water Valve QV564, QV565 Category: C Class: 3 Function:
Service water return from diesel generator header line check valves.
ASME Section XI Quarterly Test Requirements:
Verify forward flow operability.
Basis for Relief: There are no system design provisions for verification of full forward flow operability.
Alternate Testing: Partial-stroke operability will be verified in conjunction with diesel generator testing by monitoring D.G.
jacket cooling water temperature. In addition, one valve will be dise.ssembled and manually full full stroked tested at each refueling on a st'aggered test basis.
The valve internals will be verified as structurally sound (no loose or corroded t parts) and the disk manually exercised to
{ , verify full stroke capability. If the disassembled valve is not capable of being full-stroke exercised or there is binding or failure of valve internals, the remaining valve must also be disassembled, inspected, and manually full-stroke exercised during the same outage.
l
! 1 1
0382I III-1-21-11 REV. 3 i
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. . .y RELIEF REQUEST Q1P16-RV-4 System: Service Water Valve: QV635A, QV635B, QV636A, QV636B Category: C Class: 3 Function: Nontreated service water to the service water pump seals and motor coolers (QV635A, B) and treated service water to the SW pump seals and motor coolers (QV636A, B).
- Quarterly Test I Requirements: Verify forward flow operability (QV635A, B).
Verify reverse-flow closure (QV636A, B).
Basis for Relief: There are no system design provisions for verification of either full forward flow operability or reverse-flow closure.
Alternate Testing: Partial-stroke operability is verified during normal operations by monitoring pump motor temperature. In addition, one valve from QV635A, B and one valve from QV636A, B will be disassembled and manually full stroke tested at each refueling '
on a staggered test basis. The valve internals will be verified as structurally sound (no loose or corroded parts) and the disk manually exercised to verify full stroke capability. If the disassembled valve is not capable of being full-stroke exercised or there is binding or failure of valve internals, the remaining valve must also be disassembled, inspected, and manually full-stroke exercised during the same outage.
111-1-21-12 REV. 3 j i
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rE. 1 FNP-1-M-042 e
RELIEF REQUEST Q1R43-RV-1 System: Diesel Generator Air Start valve: QV519, QV520, QV582, QV583, QV638, QV639, QV640, QV641 Category: B Class: -
Function: Diesel Generator air start solenoids.
ASME Section XI' Quarterly Test I Requirements: Measure stroke time.
Basis for Relief: These are three-way solenoid valves mounted on the diesel generator (DG) skid mounted package. They are in the DG air start line between the air receiver tanks and the air start manifolds. Since each generator has two tanks and two manifolds, the DG may start on air supplied by either or both tanks. The diesel generator test procedure verifies operability of each of these valves independently on an alternating basis by isolating one air start header and starting the DG from one header at a time. Stroke time cannot be measured because there are no position indicators and visual observation is not possible due to valve design. The total time from initiation to DG operation is measured such that in effect each valve's stroke time is verified as acceptable. The DG start test is performed more frequently than required by Section XI so that actual valve testing criteria is more limiting than Section XI requirements.
Altarnste Testing: These valves will be tested as part of the diesel generator air start test.
Acceptable diesel generator start time will be used to verify valve operability and acceptable stroke time.
0428I III-1-26-4 REV.3
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