ML20235V442
| ML20235V442 | |
| Person / Time | |
|---|---|
| Site: | Millstone |
| Issue date: | 10/31/1987 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20235V441 | List: |
| References | |
| ISI-3.0, ISI-3.0-R02, ISI-3.0-R2, NUDOCS 8710150163 | |
| Download: ML20235V442 (186) | |
Text
{{#Wiki_filter:_ _ _ Docket No. 50-423 B12701 MILLSTONE POINT UNIT NO. 3 INSERVICE TESTING PROGRAM DOCUMENT NO: ISI-3.0 Revision: 2 i i l f October,1987 I B710150163 871007 PDR ADOCK 05000423 P PDR 1
l . INSERVICE TESTING PROGRAM MP-3 i CONTENTS I i ABSTRACT I 140 INTRODUCTION 1.1 General 1.2 Codes and Standards 1.3 Component Classification
2.0 REFERENCES
3.0 DEFINITIONS 4.0 DEVELOPMENT OF THE INSERVICE TESTING PROGRAM 4.1 Valve Classification 4.2 Valve Selection Basis 4.3 Required Valve Testing I 4.4 Pump Selection Basis 4.5 Pump Testing Procedure 5.0 TEST PLAN TABLES 5.1 Symbols and Abbreviations Used in Valve Test Tables 5.2 Valve Test Requirement Tables 5.3 Pump Test Requirement Tables 5.4 Maximum Stroke Times for Power-Operated Valves 6.0 RELIEF REQUESTS i 6.1 Valve Relief Request Bases 6.2 Pump Relief Request Bases 7.0 DEFERRED TEST.S 7.1 Valves With Testing Deferred to Cold Shutdown 8.0 PRESSURE TEST PROGRAM 8.1-Class 1 System Pressure Tests 8.2 Class 2 System Pressure Tests 8.3 Class 3 System Pressure Tests
- - = - - - -. ..- ) M rt ' f $1X y t i ,:D ABSTRACT ~! y The Inservice Testing' Program and pressure test < program for Millstone Point Unit'3, was developed in accordance with subsections IWA, IWP, and' 'IW of..the ASME Boiler and Pressure Vessel Code, Section XI, 1983 Edition, including Addenda-through Summer 1983 except where specific-relief is requested in:accordance with110 CFR'50.55(a)(g)(5)(iii). This programLapplies to the first inspection-interval as defined for Inspe'etion Program B in'Subsubarticle IWA-2420 of Section XI. i i .d I l p N j l r 9 i
7__ z - I i
1.0 INTRODUCTION
1.1 General This test plan describes the inservice testing (IST) program to l verify the operational readiness of certain Class.1, 2, and 3 pumps and valves and their actuating and position' indicating systems and the inservice pressure test program for Class 1, 2, and 3 systems. 1.2 Codes and Standards i Pursuant to Title 10 of the Code of Federal Regulations, Part 50, Paragraph 50.55(a), the inservice testing requirements 'for the first inspection interval at Millstone Unit 3 (MP-3), are based on the rules set forth in the 1983 Edition of the ASME Boiler and Pressure Code, Section XI, including Addenda through Summer, 1983. Any references to Section XI or the code refer to the above edition and addenda to Section XI, unless stated otherwise. Where conformance with certain code require-ments is determined to be impractical, specific relief will be requested as required by 10 CFR 50.55a (g) (5)(111). The relief request bases are located in Section 6.0 of this test plan. As perritted by Paragraph 50.55a(g)(4)(iv), the owner may ic, for certain components, to meet the requirements as set j forth in subsequent editions and addenda which are incorporated by reference in Paragraph (b) of 10 CFR 50.55a. Any such " upgrading" will be specifically identified by revisions to this document. 1.3 Component Classification The pumps and valves selected for inclusion in the inservice testing program are classified as Class 1, 2, and 3 based on the classification of the system or portion of system in which they are located. The system code classification scheme used for both inservice testing and inservice inspection is detailed in Section 1.0 of the MP-3 Preservice and Inservice Inspection Manuals (Reference 1) i' I l l i________ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _
7_ __ l;, t I 2.0. REFERENCES 2.1 PSI-2.01, Millstone Point Unit 3 Preservice Inspection Plan. 2.2 Title 10, Code of Federal Regulations, Part 50. l 2.3 ASME Boiler and Pressure Vessel Code, Section XI, 19.80 Edition, including Addenda through Winter 1981'. ] l i l i If i l l l l l
3.0 DEFINITIONS s The following is a # <r of definitions for various terms used in the inservice testing progn4m or in the referenced code section. Active Valve: Valves which are required to change position to accomplish a specific function. Exercising: The demonstration based on direct or indirect visual or other positive indication that the moving parts of a valve function satisfactorily. Inservice Life: The period of time from installation and accep-tance until retired from service. l l l Inservice Test: A special test procedure for obtaining informa 1 tion through measurement or observation to determine the operational readiness of a valve l or pump. Maintenance Routine valve servicing or work on a valve (Valves): undertaken to correct or prevent an abnormal or unsatisfactory condition. Normal Plant The conditions of start-up, hot standby, Operation: operation within the normal power range, or cooldown and shutdown of the power plant. Operational The capability of a pump or valve to fulfill its Readiness: function. Passive Valve: Valves which are not required to change positions to accomplish a specific function.
m. 7 l 1 Pressure Isola-A valve requir d to protect a lower-pressure tion Valve:' system from accidental pressurization from the j Reactor Coolant System. To qualify.as a pressure isolation valve, the following .-.4 conditions must be met: ) a. The high-pressure system must be connected. l to the Reactor Coolant System. b. There must be high pressure to low pressure interface present in the line. c. The pressure isolation valves are located .at a Class 1 to Class 2 boundary. 'd. The valves must be in one of the configura-tions identified in Figure 3.1. The piping line must have a diameter e. greater than one inch nominal pipe size. 1 Pressure isolation valves are classifed as ASME XI category A valves. 1 System Pressure A test conducted by subjecting the sytem or j Test: portion of a system to a given pressure and f .I conducting a visual examination VT-2 to detect ] 1 leakage. System Leakage A pressure test conducted following opening and Test: reclosing of a component in the system after pressurization to nominal operating pressure. l i
m ~ 3 g f. 1 5 5 1 ^ s {i x ,'j.D ). System Functional. A. test. conducted.to verify operability in.- s Test: systems (or components) not' required.to operate during' normal plant 1 operation while'under. system operating pressure. ' System Iitservice. ' A. test conducted'.to' perform.a visual; examination x.
- . Test:
VT-2 while the system is in service under - operating pressure. LSystem Hydrostatic: A pressure ' test conducted.during a plant.- Test: shutdown at a pressure above nominal operating pressure.or system pressure for which overpressure protection is provided. System Pneumatic ' A test conducted in lieu.of a' hydrostatic Test:" - pressure test for components within the scope'of IWC and IWD. A r I 1' l l ly 1 1 --___.-.__A.___ ._ -.. _ _. - ~ __ _._._._ __-a..._____
t,.. jy- -l 1 ,a. j 1 PRESSURE ISOLATION VALVE CONFIGURATIONS I i 1 l .j i i J l RCS l ) l l l i l I RCS k i I l s CLASS I CLASS II a ll !) (i il h FIGURE 3.1 I v i 4
- I.
Routine Servicing The = performance of planned, preventive main-(Pumps): tenance which does not require disassembly of the pump or replacement of pump parts, such as changing oil, flushing the cooling system, adjusting packing,. adding packing rings, or mechanical seal maintenance. System Resistance: The hydraulic resistance to flow in a system. The Code: Refers to ASME Boiler and Pressure Vessel Code, Section XI, 1983 Edition, including Addenda through Summer 1983 unless otherwise specified. h i l l l i i t k f l l l L
g..,. _ r-5 4.0 DEVELOPMENT OF'THE INSERVICE TESTING PROGRAM' 41 Valve Classification ~ '4.1.1 The valves selected for inclusion in the inservice testing program are classified as followst. a. Category A'- Valves for which seat-leakage is limited to a specific maximum amount'in the closed position for fulfillment of their function. b. Category B - Valves for which sent leakage in the closed position is inconsequential for fulfillment of their function. c. -Category C - Valves which are self-actuating in response to some system characteristic, such as, pressure'(relief valves) or flow direction 11 (check valves). ~4.2' Valve Selection Bases - i ~ 4.2.1 The valves selected for inclusion in the IST program include certain Class 1, 2, and 3 valves and their actuating and position indicating systems which are required to perform a specific function in shutting down the reactor to the cold shutdown condition or in mitigating the consequences of an accident. 4.2.2 The following valves are exempt from readiness - i testing under Section XI: Valves used only for operating convenience (such a. as manual vent, drain, instrument, and test valves), valves only used for system control (such as pressure-regulating valves), and valves used only for maintenance. b. Valves which are part of external control and protection systems responsible for sensing plant conditions and providing signals for valve operation. 1 w_--.---___-
2 t 4.3 Required Valve Testing 4.3.1 The tests required and their frequencies for the valves designated as Category A, B, and C are listed Table IWV-3700-1. In certain cases it is not practical to test individual valves at the listed frequencies, so other frequencies are specified on the tables in Section 5.0. Where a test frequency has been designated as each refueling outage, a specific request for relief has been prepared as required by 10 CFR 50.55a(g)(5)(iii). Where a test frequency of each cold shutdown has been specified, no request for relief is required. 4.3.2 Cold shutdown testing of valves will be conducted as follows: a. Testing will commence within 48 hours of achieving the cold shutdown condition, and continue until complete, or the plant is ready to return to power. b. Completion of all valve testing is not a prerequisite to return to power. c. Any testing not completed daring one cold shutdown should be performed during any subsequent cold shutdowns that may occur before refueling to as closely as possible meet the Code-specified testing frequency, d. For planned cold shutdowns, where ample time is available for testing all the valves identified for the cold shutdown test frequency in the IST program, exceptions to the 48 hours may be taken.
I s 1 4 1 L4~.3.3 Valves: or their. control systems which are-replaced, I repaired, or have undergone maintenance which could j affect their operation'shall be tested.to the' extent. il necessary to demonstrate-that the' performance L' fparameters which could have'been affected are within 4 acceptable ~ limits. 4.3.4 Valves with remote position' indicators shall be observed at'least once every two years to verify that valve operation is accurately indicated. ~ Power-operated' valves shall be checked: for stroke 4.3.5 time each time they are full-stroke exercised to' meet the requirements of this program. ~ 4.3.6- 'When practical, valves with fail-safe' actuators shall i be tested for proper 1 actuation upon loss of power .each time the valve is exercised to meet the require-ments'of~this' program. If the valve can only be part -stroked during operation, the fail-safe mechanism shall be tested when the valve is full stroke tested .during a cold shutdown. 4.3.7 Valves in systems that have been declared inoperable, or are not required to be operable, do not need to be exercised in accordance with the normal schedule. i These valves, however, must be exercised within 30 days prior to returning the system to service and the test schedule resumed as required by Paragraph IWV-3416 of the Code. 4.3.8 Valves which operate at a frequency which meets or exceeds the required test frequency need not be additionally exercised to meet the requirements of this program, provided that the required observations are made, analyzed, and the resultant data recorded at the specified intervals.
c.. ) Hd s 1 a .1 5 4 J' 4.' 3. 9 :
- The~following'special'. testing requirements' apply to; containment isolation valves:
- )
1 a. All' containment isolation valves are considered ] Cat'egory A valves. ~j b. Valves which perform only a containment: isolation. function and not a pressure isolation * ~ function-are exempt from Section XI leak rate-j -testing. These valves are leak rate tested under the requirements of 10 CFR 50, Appendix J.
- For a definition of pressure isolation valves, see l
Section 3.0. 1 1 c. -Valves which perform only a containment isolation function and are not required to + change position on a containment isolation' signal,-including normally. closed checks valves, Lare considered passive and are exempt from J 'Section XI operability testing. 4.4. Pump Selection Basis 4.4.1 The pumps selected for inclusion in the IST program i ~ d . include Class 1,,2, and 3 centrifugal.and- .j displacement type pumps that are required to perform a specific function in the shutting down of the reactor.or in mitigating the consequences of an accident and are provided with an emergency power l l source. l 4.4.2 The following Code. allowed exclusions apply to pump te. sting: a. Drivers are excluded from the requirements of subsection IWP, except where the pump and driver .] 1 from an integral unit.and the pump bearings are j in the driver. 'l b. Class 1, 2, and 3 pumps that are supplied with 1 emergency power solely for operating convenience 1 are excluded. 1
1 n.'( p., t J _4.4.3 All tests and examination. procedures required by. ] ~ Subsection IWP,' including schedules, reference values, the location and. type of measurement for each
- of'the required test quantities, records of results, and all corrective action taken shall be performed by NNECO for Millstone Unit No.
3.. -U - 4.5 Pump Testing Program / 4.5.1 Inservice tests shall be conducted with the pump . operating at nominal motor speed. 7 T A series of reference values are determined for quantities listed below, as observed or measured when the equipment is known to be operating correctly. q ... Inservice Test Quantities j ' Inlet Pressure, Pi i Differential Pressure, AP i Flow Rate, Q Vibration Signature,'V Proper Lubricant Level or Pressure Speed N - (if Variable Speed) In place of U (Vibration Amplitude), NNECO will.use a Vibration Signature Analysis program as described in- ] 4. Section 4.5.5. This program also eliminates the requirement for measuring bearing temperatures annually due to the program's ability to detect i bearing problems at a very early stage. _ _ _ = _ _ _ _
p:-;- ~- ~, ~ ~ } i t l q l l s In aniinservice test',Itheseiquantities :are remeasured' H and co'mparSd wit'h the reference values' to ' determine if> corrective action is needed! When a reference - value or s6t of. values may; have been affected by ; i repl'acement, L repair, or. routine servicing ;of 'the - -0 pump, a new> reference value.or set of values'shall be: -l . determined or the previous value reconfirmed by an l inservice test run within 96 ' hours af ter return' of, s-the pump t' normal: service. o 4.5.2 Test Frequency Each inservice test shall include < the measurement and i L observation' of applicable test quantities. An inservice : test shall be run on each applicable pump, at a' frequency and scope as stated in Table-IWP-1. d -If practicable, this test' frequency shall be m If the pump is not-maintained during plant shutdown. tested during plant shutdown, it shall:be tested within one" week after the plant is returned to steady. state operation.- 1 1 1 Pmnps that are operating need not be run or stopped for a special test, provided the plant log shows each such pump was operated at refererce conditions and L the quantities specified were measured, observed, recorded, and analyzed. ( l-P I > s
y1 'V f u .m \\}N > " l 1 V M +
- 4.5.3
' Analysis and Corrective Action I 4.5.3.1-Analysis of test; data shall be performed k ,within:96 hours following completion of the ' test. -The test quantities 1shall be-compared to the: allowable range of I quantities provided in TablerIWP-3100-2 of Subsection-IWP. LIf the ranges cannot be 1 met, reduced. range: limits, allowing the i ut pump to fulfill its function, may be used in lieu of those:in Table'IWP-3100-2. i These' reduced-range limits'shall be specified by NNECO in the_ pump testing; procedures. Vibration Signature: Analysis: ,1 is covered in Section 4.5.5. 4.5.3.2 Corrective action to be taken by NNECO in the event that measured test quantities-i fall ~outside the allowable range shall be as follows: a) If deviations fall within the Alert' l Range, the testing frequency shall'be doubled until the cause of the deviation is determined and the j condition corrected. l 1 b) If the deviations fall within the Required Action Range, the pump shall be declared inoperable until the cause of the deviation is determined and-the condition corrected. l 1 1 _j
c) Corrective action shall be either replacement or repsir per paragraph IWP-3111 of Section XI, or shall be an analysis which demonstrates that the condition does not impair pump-operability and that the pump will still fulfill its function. When such an analysis is used, a new set of reference values shall be established. \\. I d) If, as a result of the analysis, it is 1 suspected that the deviation may be due to the test instruments being out of calibration, the instrmnents involved may be recalibrates and the test rerun prior to declaring the pump inoperable. This action must be completed within 96 hours of the l original test. 4.5.4 Records of Inservice Tests 4.5,4.1 The following information shall be maintained by Millstone to meet the requirements for inservice testing: 1) A' record for each pump, including the name of the manufacturer, the model, and the serial or other identification
- number, 2)
An inservice test plan including: a. The hydraulic circuit to be used, b. The location and type of measurement for each required test quantity, c. The test quantity reference values, the limits of P (Table IWP-3100-2), and any other required information.
3) Test record giving pertinent ' nformation such as test date, i instruments deed, results, corrective action required, and signatures of persons conducting and analyzing the test. 4) A record of corrective actions ano subsequent inservice tests verifying-operational adequacy. All inservice test plans and records shall be main-tained at the Millstone Unit No. 3 plant, and shall be accessible for audit. 4.5.5 Vibration Signature Analysis Program 4.5.5.1 General Procedure Vibration will be monitored at least quarterly Lsing equipment which collects vibration velocity signatures.
- Overall, vibration velocity (in/sec RMS) will be compared to the following acceptance criteria:
Acceptance Range - O to 2.5 times Reference Velocity Alert Range - > 2.5 to 5 times l Reference Velocity l Required Action Range - > 5 times j Reference Velocity I l' l l l l l l l l 'L
/ Reference Velocity shall be the average overall velocity determined during an inservice test at reference conditions when the pump is known to be operating acceptably. In addition to the above quantitative analysis of overal.1 vibration levels, vibration signatures will be reviewed at least quart'erly by a knowledgeable person to identify potential bearing degradation or other developing faults. 'When potential faults arc identified, action as required for a pump in the Alert Range of vibration will be initiated. The measurement locations to be urad for l quarterly baseline vibration signature data are established and specified for* each pump in the NNECO procedures. l l l l
4 .\\.* J 1 i. l 1 o 4 s1 / iu' 't i ,1 c I 1 '- g t-(:q, i t l /) i i 5.0 TEST PLAN TABLES 't.
- )
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- f. '
), I d i n i . N l e-i i ., 'i i I. 4. y-( \\ j i 5l l i l / ll 1 I i 1 '1
- - rry, --f..,3 9..,-
- d...
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^ i + <. v + c ;.: g. .- r.e. y' 1 <3 ~ p y w 5l~Syboj{,a,nd'AbbreviationsUsed'in:ValveTestTables , gy q g u (:/.1 Va:{.v.s. Type b. ^ dp.utterfly - (f. .BFLY. = s ~ C);R. = Check ,3 y; g p){ $N'3 . DIA}; - Diaphragm h9 (tf-L} ' 'p GA.
- =.
Gate:
- vh :
<y o" ..,,.G, ir, =; Globe f,
- REL.
1=. LRelief y d-JN1.. w % a. ' ? ',SAF. i =. ' Safety 3 ..? I ;'j SCifX. 4 Stop-Check " t '[(Ay ] i1
- y' s,t ? ~ ',p' a
- ?
i 'I st-Period.p s' g-in Qv .. J =, Quarterly s a [_);- BI "= Biennial. . 17,- 2 4 q'.. i g CS, = Cold Shutdown y
- y
.{0; =I Each Refueling. .g (4 ~I,NT = . Each Inspection Interval 3,,s .q. t e-3 $$ Required Testing 4 $~ ' Check to see if valve goes to its full fail-safe- 'FT J =- ~ position on loss of actuator power 4 ! h.. My (pdagraph IW-3415). n;. o T! SS T = . Full; stroke exercise. .g ii, /Ilr j. LeakWate test' (Subarticle IW-3420 or - + =- y,j ~s. R i 10 CFR 50, Appendix J, as appropriate). -y i 4 MT = Stroke' time' measurement. s JT. F ,s q.P PI = Check for preper operation of remote position h }m. b. PS = Part stroke exercise. ind'cators (Subarticle IW-3300). i (- 4[p y M i [- }h,hhs[ i Safety and relief valve test (Subarticle SRV' = .1 -e T.: IW-3500). i 1
- j; C(.
Note: Items'in parenthesis refers to the appropriate item 7.. 3 ,p. in Section XI. -o 3- ./ :. ..,,h .)' k x. i I. 25_____.____________.__ ~ m
y-- c 4 l 5.2 VALVE TEST REQUIREMENTS TABLES ) l i l l I e h 4 l l t i ( l 1 l L___-_--_ i
4 I { i f:; i (' i 5.4 MAXIMUM STROKE TIMES FOR POWER-OPERATED VALVES 1 9 i I I. l l l l \\ I ~ l 1 l
,s. 5.4 Maximum Allowable Stroke Times for Power-Operated Valves Reactor Coolant System Valve Number Operator Number Max. Stroke Time 3RCS-V167 (MV-8000A) NSR(1) - 23 sec. 3RCS-V168 (PCV-455A) ~2 sec. 3RCS-V169 (MV-8000B) NSR(1) - 19 sec. 3RCS-V170 (PCV-456) 2 sec. 3RCS-V174 (AV-8145) NSR(1) - 57 sec. 3RCS-V960 (HCV-442A) NSR(1) - 15 sec. -3RCS-V961 (HCV-442B) NSR(1) - 16 sec. 3RCS-V962 (SV-8095A) NSR(1) - 5 sec. 3RCS-V963 (SV-8095B) NSR(1) - 5 sec. 3RCS-V964 (SV-8096A) NSR(1) - 5 sec. 3RCS-V965 (SV-8096B) NSR(1) - 5 sec. Chemical and Volume Control System 3CHS-V5 (CV-8152) 60 sec. 3CHS-V40 (LCV-112B) 25 sec. 3CHS-V41 (LCV-112C) 25 sec. 3CHS-V56 (MV-8106) 25 sec. 3CHS-V57 (MV-8105) 25 sec. 3CHS-V259 (LCV-112D) 25 sec. 3CHS-V260 (LCV-112E)- 25 sec. 3CHS-V269 (MV-8110) 25 sec. 3CHS-V393 (MV-8109A) NSR(1) - 34 sec. 3CHS-V433 (MV-8109B) NSR(1) - 33 sec. 3CHS-V466 (MV-8109C) NSR(1) - 33 sec. 3CHS-V500 (MV'-8109D) NSR(1) - 32 sec. 3CHS-V532 (MV-8112) 60 sec. 3CHS-V533 (MV-8100) 60 sec. 3CrS-V665 (MV-8511A) 25 sec. i 3CHS-V666 (MV-8511B) 25 sec. 3CHS-V667 (MV-8512B) 60 sec. ] _--__-__________________-____________O
3CHS-V668 (MV-8512A) 60 sec. 3CHS-V697 (MV-8111C) 25 sec. 3CHS-V698 (MV-8111B) 25 sec. 3CHS-V699 (MV-8111A) 25 sec. 3CHS-V700 (HCV-190A) NSR(1) - 13 sec. 3CHS-V70.1' (MV-8116) 'NSR(1) - 19 sec. 3CHS-V702 (MV-8438A) 60 sec. 3CHS-V703 (MV-8438C) 60 sec. 3CHS-V704 (MV-8438B) 60'sec. 3CHS-V705 (HCV-190B) NSR(1) - 13 sec. 3CHS-V708 (MV-8468B) 60 sec. 3CHS-V709 (MV-8468A) 60 sec. 3CHS-V710 (MV-8507B) NSR(1) - 17 sec. l 3CHS-V712 (MV-f,507A) NSR(1) - 18 sec. 3CHS-V802 (CV-8160) 60 sec. Charging Pump Cooling System l 3CCE-V3 (A0V-30A) NSR(1) - 9 sec. 3CCE-V11 (A0V-26A) NSR(1) - 9 sec. 3CCE-V15 (A0V-30B) NSR(1) - 9 sec. 3CCE-V23 (A0V-26B) NSR(1) - 11 sec. Acrated Drains 3DAS-V9 (CTV-24) 60 sec. 3DAS-V10 (CTV-25) 60 sec. Reactor Plant Gaseous Drains 3VRS-V2 (CTV-20) 60 sec. 3VRS-V3 (CTV-21) 60 sec. 3DGS-V18 (CTV-24) 60 sec. L 3DGS-V19 (CTV-25) 60 sec. l l h -__-____-____--___w
Q Low Pressure Safety Injection 3SIL-V2 (MV-8812A) 60 sec. 3SIL-V5 (MV-8809A) NSR(1) - 20 sec. 3SIL-V8 (MV-8812B) 60 sec. 3SIL-V11 (MV-8809B) NSR(1) - 22 sec. 3SIL-V14-(MV-8808A)- NSR(1) - 19 sec. j 3SIL-V16 (MV-8808B) NSR(1) - 20 sec. 3SIL-V18 (MV-8808C) NSR(1) - 18 sec. 3SIL-V20 - (rfV-8808D) NSR(1) - 19 sec. l 3SIL-V22 (MV-8804A) 60 sec. 3SIL-V23 (MV-8804B) 60 sec. 3SIL-V25 (MV-8840) NSR(1) - 18 sec. 3SIL-V30 (CV-8890A) 60 sec. 3SIL-V31 (CV-8890B) 60 sec. 3SIL-V34 (CV-8825) 60 sec. 3SIL-V38 (CV-8880) 60 sec. 3SIL-V39 (CV-8968) 60 sec'. 3SIL-V45 (HCV-943A) NSR(1) - 13 sec. 3SIL-V883 (HCV-943B) NSR(1) - 13 sec. Residual Heat Removal System 3RHS-V4 (MV-8716A) NSR(1) - 13 sec. 3RHS-V8 (MV-8716B) NSR(1)'- 14 sec. 3RHS-V610 (FCV-610) NSR(1) - Later 3RHS-V611 (FCV-611) NSR(1) - Later 3RHS-V994 (MV-8702A) NSR(1) - 228 sec. 3RHS-V995 (MV-8701B) NSR(1) - 224 sec. 3RHS-V996 (MV-8702B) NSR(1) - 24 sec. '3RHS-V997 (MV-8701A) NSR(1) - 23 sec. 3RHS-V998 (MV-8702C) NSR(1) - 22 sec. 3RHS-V999 (MV-8701C) NSR(1) - 28 sec. l I l-l.
i i Recirculation Spray System ~3RSS-V1 .(MV-23A) NSR(1) - 60 sec. 3RSS-V4 (MV-23C)' NSR(1) - 60 sec. 3RSS-V7, (MV-23B) NSR(1) - 57 sec. 3RSS-V10 (MV-23D) NSR(1) - 57 sec. 3RSS-V932 (MV-38A). NSR(1) - 32 sec. I 3RSS-V945-(MV-38B) NSR(1) - 32 sec. 3RSS-V954-(MV-20A) NSR(1) - 58 sec. 3RSS-V955 (MV-20C) NSR(1) - 59 sec. 3RSS-V956 (MV-20B) NSR(1) - 62 sec. 3RSS-V957 (MV-20D) NSR(1) - 57 sec. 3RSS-V974 (MV-8837A) 60 sec. l 3RSS-V975 (MV-8838A) 60 sec. 3RSS-V985 (MV-8837B) 60 sec. 3RSS-V986' (MV-8838B) 60 sec. High Pressure Safety I.njection 3SIH-V3 (MV-8801A) NSR(1) - 20 sec. 3SIH-V4 (MV-8801B) NSR(1) - 19 sec. 3SIH-V10 (MV-8806) NSR(1) - 21 sec. 3SIH-V12 (MV-8923A) NSR(1) - 20 sec. 3SIH-V15 (MV-8821A) NSR(1) - 18 sec. 3SIH-V16 (MV-8923B) NSR(1) - 22 sec. 3SIH-V19 (MV-8921B) NSR(1) - 19 sec. 3SIH-V20 (MV-8835) NSR(1) - 18 sec. 3SIH-V65 (CV-8843) 60 sec. j 3SIH-V76 (MV-8807A) 60 sec. 3SIH-V77 (MV-8807B) 60 sec. !) .I ] 3SIH-V78 (MV-8924) 60 sec. 3SIH-V82 (MV-8814) 60 sec. 3SIH-V84 (MV-8920) 60 sec. 3SIH-V93 (MV-8802A) NSR(1) - 20 sec. I i 3SIH-V94 (CV-8888) 60 sec. 3SIH-V100 (MV-8802B) NSR(1) - 20 sec. l j l _ _ = - - _ - _ _ _ _.
3SIH-V102 (CV-8881) 60 sec. 3SIH-V103 '(CV-8824) 60 sec. 3SIH-V104 (CV-8823) 60 sec. 3SIH-V962 (CV-8813) 60 sec. 3SIH-V987-(CV-8964) 60 sec. '3SIH-V988 (CV-8871) 60 sec. Quench Spray System 3QSS-V3-(MV-34A) NSR(1) - 40'sec. 3QSS-V7 (MV-34B) NSR(1) - 40 sec. 3QSS-V9 (A0V-27) 30 sec. 3QSS-V10 (A0V-28) 30 sec. 3QSS-V30 (MV-29B) 30 sec. 3QSS-V31 (MV-29A) 30 sec. Primary Grade Water System 3PGS-V31. (CV-8028) 60 sec. 3PGS-V32 (CV-8046) 60 sec. Reactor Plant Component Cooling Water ~ 3CCP-V17 (MV-45A) 60 sec. 3CCP-V19 (MV-223) NSR(1) - 43 acc. 3CCP-V20 (MV-222) NSR(1) - 43 sec. l 3CCP-V21 (MV-224) NSR(1) - 43 sec. 3CCP-V22 (MV-225) NSR(1) - 42 sec. 3CCP-V44 (A0V-179A) NSR(1) - 60 sec. l 3CCP-V45 (A0V-180A) NSR(1) - 60 sec. 3CCP-V48 (MV-48A) 60 sec. 3CCP-V49 (KV-49A) 60 sec. 3CCP-V59 (MV-45B) 60 sec. 3CCP-V80 (MV-227) NSR(1) - 42 sec. 3CCP-V81 (MV-226) NSR(1) - 42 sec. l 3CCP-V82 (MV-228) NSR(1) - 42 sec. 3CCP-V83 (MV-229) NSR(1) - 44 sec.
- - - - - - - - - - -- q 2 l i I 3CCP-V84 (A0V-179B) NSR(1) - 73 sec. 3CCP-V85 (A0V-180B) NSR(1) - 74 sec. c 3CCP-V88' (MV-48B) 60 sec. 3CCP-V89 (MV-49B) 60 sec. 3CCP-V105 (FV-66A) NSR(1) - 94 sec. 3CCP-V119 (FV-66B)- NSR(1) - 96 sec. 3CCP-V122 .(A0V-197A) NSR(1) - 90 sec. 3CCP-V123 (A0V-10A) NSR(1) - 96 sec. 3CCP-V202-(A0V-194A) NSR(1)'- 76 sec. i 3CCP-V203 (A0V-19A) NSR(1) -'88 sec. 3CCP-V204 -(A0V-197B) NSR(1) - 30 sec. 3CCP-V205 (A0V-10B) NSR(1) - 24 sec. 3CCP-V288 (A0V-194B) NSR(1) - 32 sec. 3CCP-V289 (A0V-19B) NSR(1) - 34 sec. { Reactor Plant Chilled Water System 3CDS-V55 (CTV-38A) 60 sec. 3CDS-V56 (CTV-91A) 60 sec. 3CDS-V96 (CTV-40A) 60.sec. 3CDS-V97 (CTV-39A) 60 sec. 3CDS-V105 (CTV-91B) 60 sec. 3CDS-V106 (CTV-38B) 60 sec. f 3CDS-V145 (CTV-40B) 60 sec. 3CDS-V146 (CTV-39B) 60 sec. Main Steam and Blowdown Systeps 3 MSS-V1 (CTV-27A) 5 sec. 3 MSS-V2 (HV-28A) 10 sec. 3 MSS-V4 (CTV-27B) 5 sec. 3 MSS-V5 (HV-28B) 10 sec. 3 MSS-V7 (CTV-27C) 5 sec. 3 MSS-V8 (KV-28C) 10 sec. 3 MSS-V10 (CTV-27D) 5 sec. 3 MSS-V11 (HV-28D) 10 sec. 1
- v.
.h s . i ,( 4. 4') R t t J /3 MSS-V12-(MV-17A). NSR(1) -1621sec. ^ 3 MSS-V37 .(MV-17B). NSR(1) - 56 'se~c'. - 3 MSS-V38' (MV-17D)-~ .NSR(1)l ' 60tsec. . 3 MSS-V893L (MV-74A) NSR(1) - 134'sec. .3 MSS-V894 (MV-74B)
- NSR(1)l-220-sec.
t p 3 MSS-V895-(MV-74C)- NSR(1);- 204'sec. - 3 MSS-V896 ~ (MV-74D) NSR(1) -'216 sec. 3 MSS-V897-(A0V-31A). NSR(1) -c 30 sec. q 3 MSS-V898' (A0V-31B) NSR(1) - 30'sec. ') 3 MSS-V899 ~ (A0V-31D). NSR(1);-L30Jsec.' d 3BDG-V3- . (CTV-22B) 10 sec. ~ '3BDG-V10 (CTV-22A) 10 sec. ^3BDG-V17 (CTV-220) '10 sec. } 3BDG-V24 (CTV-22D) 10 sec. - 3 MSS-V47 (MV-18 A) NSR(1) - 72 sec. 3 MSS-V48 (PV-20 A) NSR(1) - 46 sec. 3 M'SS-V54 - (MV-18 B) NSR(1) - 72 sec. I ~ 3 MSS-V55 (PV-20 B), NSR(1) - 54 sec. i '3 MSS-V61, (MV-18 C). NSR(1) - 71 sec. 3 MSS-V62 - (PV-20.C) NSR(1) - 82 sec. 3 MSS-V68. (MV-18 D). NSR(1) - 71 sec. 3 MSS-V69. (PV-20 D) NSR(1) - 58 sec. Main and Auxiliary Feedwater 3FWS-V15' (FCV-510)- 5 sec. (fail safe) -j 3FWS-V18 (LV-550) 5 sec. (5 sec. fail close) - 3FWS-V20 (CTV-41A) 5 sec. 3FWS-V22 (FCV-520) 5 sec. (fail safe) 3FWS-V25 (LV-560) 5 sec. (5 sec. fail close) E 5 sec. L 3FWS-V27 (CTV-41B) 3FWS-V29 (FCV-530) 5 sec. (fail safe) if 3FWS-V32 (LV-570) 5 sec. (5 sec. fail close) '3FWS-V34 (CTV-41C) 5 sec. 3FWS-V36 (FCV-540) 5 sec. (fail safe) i-n 9 ___m___________m_ ___m.-
_ _ _ _ __ _ - =_ ___ _ _ ____ _______ _ - ____ _-____ 3FWS-V39' (LV-580) 5 sec. (5 sec, fail close) 3FWS-V41 .(CTV-41D) 5 sec. 3FWA-V53 (A0V-25) 60 sec. 3FWA-V54 .(A0V-26) 60.sec. 3FWA-V63 (A0V-23B) 60 sec. 3FWA-V65 (A0V-23A) 60 sec. 3FWA-V856 (A0V-61A) 60 sec. 3FWA-V857-(A0V-61B) 60 sec. Chemical Feed System 3SGF-V28 (A0V-24A). 60 sec. 3SGF-V30 (A0V-24B) 60 sec. 3SGF-V32 (A0V-24C) 60 sec. 3SGF-V34 (A0V-24D) 60 sec. Service Water System 3SWP-V2 (MV-102D) 40 sec. 3SWP-V4 (MV-102B) 40 sec. 3SWP-V6 (MV-102C) 40 sec. 3SWP-V8 (MV-102A) 40 sec. 3SWP-V17 (A0V-39A) 180 sec. 3SWP-V25 (MV-54A) 200 sec. 3SWP-V27 (MV-54C) 200 sec. 3SWP-V29 (MV-71A) 60 sec. 3SWP-V33 (MV-50A) 200 sec. 3SWP-V50 (A0V-39B) 180 sec. f 3SWP-V58 (MV-54B) 200 sec. 3SWP-V60 (MV-54D) 200 sec. 3SWP-V62 (MV-71B) 60 sec. 3SWP-V65 (MV-50B) 200 sec. l 3SWP-V72 (MV-24D) NSR(1) - 32 sec. 3SWP-V73 (MV-24B) NSR(1) - 23 sec. 3SWP-V74 (MV-24C) NSR(1) - 25 sec. 3SWP-V75 (MV-24A) NSR(1) - 22 sec. l
l j l 3SWP-V97 (MV-115B)- 60 sec. 1 3SWP-V99 (MV-115A) 60 sec. I ~3SWP-V862 (MV-130A)' NSR(1) - 30 sec. 3SWP-VB75 (MV-130B) -NSR(1) - 31 sec. 3VIC-V1 (A0V-25A) 60 sec. 3VIC-V11. (A0V-24A) 60 sec. 3WTC-V12 (A0V-24B) 60 sec. 3WTC-V972 (A0V-25B) 60 sec. 3WTC-V998 (A0V-50B) 60 sec. I 3VIC-V999 (A0V-50A) 60 sec. Service and Instrument Air 3IAS-V131 (PV-15) 60 sec. 3IAS-V809 (MV-72) 60 sec. Nitrogen Supply 3GSN-V181 (CV-8033) 60 sec. 3GSN-V962 (CTV-105) 60 sec. Reactor Plant 'ampling S 3SSR-V1 (CTV-20) 60 sec. 3SSR-V2 (CTV-21) 60 sec. 3SSR-V3 (CTV-22) 60 sec. 3SSR-V4 (CTV-23) 60 sec. 3SSR-V5 (SOV-24A) NSR(1) - 5 sec. 3SSR-V6 (SOV-24B) NSR(1) - 5 sec. 3SSR-V7 (CTV-26) 60 rec. 3SSR-V8 (CTV-27) 60 sec. 3SSR-V9 (SOV-28A) NSR(1) - 5 sec. i 3SSR-V10 (SOV-?SB) NSR(1) - 5 sec. 3SSR-V11 (SOV-28C) NSR(1) - 5 sec. 3SSR-V12 (S0V-28D) NSR(1) - 5 sec. 3SSR-V13 (CTV-29) 60 sec. 3SSR-V14 (CTV-30) 60 sec. l
Y J + x 9: = (M5! V LJ r 4 3SSR'V19: (CTV-32) 60 sec. s m K< 3SSR-V20s '(CTV-33)- '60'sec. '3SSR M21- ) .(CV-8026) 60 sec. U 4 J L3SSR-V22 (CV-80'25) -60 sec. .3SSR-V24. (CTV-19D) 10Esec. 4 - $3SSR-V267 (CTV-19C); L10 sec. ,.g, -, g.fi '3SSR-V28
- (CTV-19B)
~10 sec. 3SSR-V30 (CTV-19A). 10 sec. 3SSR-V978' (S0V-171). .NSR(1) - 5 sec. .'(., t' ' Turbine Plant' Miscellaneous Drains-3DTM-V70. (A0V-63A) 10. s e c '. 'E 3DTM-V71 (A0V-64A) 10 sec. 3DTM-V77 (A0V-29A) 10 sec. q-3DTM-V78! (A0V-61A) 10 sec. 3DTM-V84 (A0V-29B) 10 sec. .3DTM-V85 -(A0V-61B) '10 sec.
- 3DTM-V91
-(A0V-29C) 10 sec. -3DTM-V92 -(A0V-61C) 10 sec. .3DTM-V98 (A0V-29D) 10 sec. '3DTM-V99 (A0V-61D) 10 sec. 3DTM-V926 (A0V-64B) 10 sec. 3DTM-V927 (A0V-63B) 10 sec. 3DTM-V938 (A0V-64D) 10 sec. '3DTM-V939 (A0V-63D) 10 sec. 1 Fire Protection System 3FPW-V663 (CTV-49) 60 sec. j 3FPW-V668 (CTV-48) 60 sec. 1 l Control Building HVAC 3HVC-26 (SOV-74B) 2 sec, t i 3HVC-2.7 (SOV-74A) 2 sec. 3HVC-V70 (A0V-25) 3.7 sec. i ~ :E
p t r ~ 3HVC-V71 (A0V-26) 3.7 sec. - 3HVC-V72 (60V-22) 3.7 sec. 3HVC-V73 (A0V-23) 3.7 sec. 3HVC-V74' (A0V-20) 3.7 sec. 3HVC-V75 (A0V-21) 3.7 sec. Containment Vacuum and Ventilation ( [- 3CVS-V2 (CTV-20A) 60 sec. L 3CVS-V3 .(CTV-21A) 60 sec. 3CVS-V6 (CTV-20B) 60 sec. 3CVS-V7 (CTV-21B) 60 sec. 3CVS-V971 (MV-25) NSR(1) - 62 sec. Containment Monitoring System l . 3 CMS-V4 (CTV-20) 60 sec. 3 CMS-V5 (CTV-21) 60 sec. 3 CMS-V8 (CTV-23) 60 sec. 3 CMS-V993 (MV-24) 60 sec. Postaccident Sample System 3 SSP-V1. (SOV-1A) NSR(1) - 5 sec. 3 SSP-V2 (SOV-1B) NSR(1) - 5 sec. 3 SSP-V3 (SOV-1C) NSR(1) - 5 sec. L 3 SSP-V4 (SOV-1D) NSR(1) - 5 sec. l 3 SSP-V5 (SOV-2A) NSR(1) - 5 sec. 3 SSP-V6 (SOV-2B) NSR(1) - 5 sec. 3 SSP-V9 (SOV-5) NSR(1) - 5 sec. 3 SSP-V10 (SOV-3) NSR(1) - 5 sec. 3 SSP-V11 (CTV-7) 60 sec. 3 SSP-V12 (CTV-8) 60 sec. l l
i ) (1)NSR - No maximum allowable stroke time is required for f.l-for this valve according to design criteria. For ISI purposes, the maximum allowable stroke time will be 5 sec. or two times the baseline stroke time measured during preservice testing rounded to the next. highest whole second, whichever.is . greater. s
1 i ,'v.i i l l 6.0 RELIEF REQUESTS l l I 1 l l l l' t l 1 ~
_?_.-._-__._________________________
_ J
l d ,t' 1 4 4 I e i. 1) l l l 6.1 VALVE RELIEF REQUEST BASES l r I I i l l 4
Relief Request: E-1 Valves: 3RCS*V26, V102; 3SIL*V27, V29; 3SIH*V110, V112 Category: AC Code Class: 1 Function: Pressure isolation betweeh the reactor coolant system and the safety injection system (SIH). Test Requiremr.nts: Exercise (full stroke) quarterly. Basis for Relief: The source of flow to full stroke exercise these valves is the safety injection pumps (3SIH* PIA and PIB). The shutoff head of these pumps (1,520 psig) is insufficient to stroke these valves against the normal reactor coolant system (RCS) pressure. Full stroking cannot be performed during cold shutdown because the required flow would risk overpressurization of the RCS. Alternate Testing: The valves will be full stroke exercised during refueling outages when the reactor closure head is removed. The backup pressure isolation check valves (3SIH*V110 and V112) will be part stroke exercised quarterly. l l L___z_
~ u 4 t j.: t J ~ Relief Request: R-2l<:
- f.
.: Valves: J3CHS*V58', V394, V434, V467, V501 ~ L ' Category: 'AC JCode Class: 2 [l~ aFunction: , Containment; Isolation' Valve Test Requirements: Exercise closed'(full stroke) quarterly. Basis for Relief: TheLfunction of,these valves is to provide containment isolation.upon cessation of normal charging or seal flow. 3CHS*V394, V434, V467, and V501 cannot be tested'at power or cold shutdowns unless the RCS is-depressurized and drained (per Westinghouse Tech. Manual),.otherwise damage to'the RCP seals may occur, Cold shutdowns which depressurize the RCS do not'have a motive force to. verify the valves are closed. During cold shutdown there is no ff 4. oath available .to pressurize' the downstream side ot cae normal charging valve (3CHS*V58) to demonstrate that the valve 'is closed when normal. charging flow is secured, e since it is isolated from the RCS by two check valves in series. EAlternate' Testing: These. valves are subject to local leak rate, testing every two years as~ required by 10 CFR 50, Appendix J. This test verifies their adequacy for containment isolation and requires that the valves be' shut to successfully complete the test. l l
(l.. s e_g ?. " t; 'h \\ 3-P.,., .i Relief Request: 'R-3 -j i 1 Valves: '3SIL*V15,'V17, V19, V21 Category: .AC' i ' Code Class: 1 i Function: Pressure' isolation between the reactor coolant system and the safety injection accumulator tanks, A ' Test Requirements: Exercise (full stroke) quarterly. H . Basis for Relief: These valves cannot be. full stroke or part stroke exercised during operation since no flow path exists to accomplish such a test. The valves cannot be full stroke or part stroke exercised durirg a cold shutdown because this would result in a complete or partial. discharge of the tanks into the reactor vessel which could result in low teraperature overpressurization of the RCS. 1 . These valves will be partially disassembled,- Alternate Testing: inspected and manually exercised on a staggered sampling basis each refueling outage. During each disassembly, the valve internals will be inspected for structural soundness (no loose or corroded parts). In the event that a disassembled valve's i full-stroke capability is questionable, additional valves will be disassembled until one hundred percent (100%) of the valves identified in this group have been disassembled and inspected. i I- ^ L
p ;:- . - ~ ' -.m + .c ,m c--
- c n
r ' water causing premature' failure of the component. Full stroking cannot be performed-during. cold shutdown because the required flow would risk a-overpres'surization'of the RCS. O _ Alternate' Test.ing: Th'e valve will be full. stroke exercised during .eefueling outages when the reactor closure head is removed. o l )
g.; , :}Ih ] ;i 1,1
- t t [
'f, 'k-' A q f'. r i If !. R-5 1 ' ' Relief Requesti v 4 4 3SIL*V982/V983: Valves:
- o
. Category: ' C-l Code' Class: 2 ,c[ Function: - Isolation'of theiRHS system. The valves..are required i I to open.for containment recirculation'. 4 I Test Requirements: - ExerciseL(full-stroke) quarterly. Basis for Relief: - There.is'no flow path.available to. test'these. valves during power operation, cold shutdown, or refueling shutdowns. The isolation-valves, 3SIL*V23 and 3SIL*V22 are interlocked requiring the RHS and RSS l-l systems be' lined up for containment' recirculation before.they can be, opened. -{ Alternate Testing: - These valves will be partially. disassembled, .i ~ inspected and manually exercised on a staggered sampling basis for each. refueling' outage. During t each disassembly, the valve internals.will.be inspected for. structural soundness-(no loose'or 'I corroded parts)..In the event that-a disassembled i valve's full-stroke capability is questionable, ' additional valves will be disassembled until one hundred percent (100%) of the valves identified in this group have been disassembled and inspected. i l I l
i ( E Relief Request: R-6' Valves: 3RSS*V3, V6, V9, V12 Catego ry: AC Code Class: 2 Function: Containment Isolation a Test Requirements: Exercise (full stroke) quarterly. Basis for Relief: There is no flow path available to full stroke exercise these valves without actual initiation of recirculation spray. This could' result in damage to plant equipoent and spread of radioactive contamination. q; Alternate Testing: These values will be partially disassembled, inspected and manually exercised on a staggered sampling basis for each refueling outage. During each disassembly, the valve internals will be insp'ected for structural soundness (no loose or corroded parts). In the event that a disassembled . valve's full-stroke capability is questionable, additional valves will be disassembled until one hundred percent (100%) of the valves identified in this group have been disassembled and inspected. f i i .1
+ Ef(N y t ) 4 o 's. < Relief Request:. R-7 t' g, ' I
- Valves't ;
!3QSS*V4,.V8,1V978,.V979 sn . I (' '.. : Category: - AC/C i I SCAde Class: .2' ~Functionj Containment Isolation / Isolate the appropriate quench -sprayLsystem-(QSS) header in the event it should i becomeLinoperative. Test' Requirements: Exercise (full. stroke) quarterly.
- Basis 'for Relief:
There[is'noflowpathavailabletofullstroke exercise these valves without actual initiation of quench' spray. This could result in damage to plant equipment and spread of radioactive contamination'. -51 ternate Testing: These: valves will'be partially disassembled, inspected.and manually exercised on a staggered sampling basis for each refueling outage. During each disassembly, the valve-internals will-be inspected for' structural sourdness (no loose or corroded parts). In.the event that a disassembled valve's~ full-stroke capability is questionable, additional valves will be disassembled until one. 'hundred percent'(100%)'of the' valves identified in this group have been disassembled and inspected. l
.a I i l- [. I Relief Request: R-f l Valves: 3QSS*V976, V977 C6tegory: C t Code Clata: 2 Function: Isolate the appropriate quench spray system (QSS) header in the event it should become inoperative. Test Requirements: Exercise'(full stro'se) quarterly. Basis for Relief: There is no flow path available to full stroke exercise these valves without actual initiation of quench spray. Tais could' result in damage to plant equipment and upread of radioactive contamination. Alternate Testing: These valves will be partially disassembled, inspected and manually exercised on a staggered sampling basis for each refueling outage. During each disassembly,-the valve internals will be inspected for structural soundness (no loose or corroded parts)..In the event that a disassembled valve's full-stroke capability is questionable, additional valves will be disassembled until one hundred precent (100%) of the valves identified in this group have been disassembled and inspected. 1 I 1 1 t i
t x +
- t.-
'q ~ c s 7 x - 4 y. ) -:e Relief Request: LR-9. . Valves: -3SIH*V13,1V17' tf, , Category:. C F [i Code' Class: '2 Functio'n: To' prevent bAckf1'ow to'the associated safety ' injection' pump when secured and the parallel pump is in operation.- Test Requirements: Exercise (full stroke) q'uarterly. - Basis for Relief: .The. source of flow to full sttoke exercise these' 2 valves is the safety. injection pumps (3SIH* PIA'and PIB). ;The shutoff. head.of these, pumps (1,520 psig)-- is ' insufficient to stroke these valves against the normal reactor coolant. system (RCS) pressure (this is the only path to establish flow through thesei -valves). Full stroking cannot be performed during cold shutdown because the required flow would risk overpressurization of the RCS. Alternate-Testing: The val'ves will be-full stroke exercised during refueling outages when the reactor closure head is removed. 'l l f a m. _______..____.__..m_____.__.__..____________.__,_...-____m.__m_.
m. .e"* e '.), E 4 s ,'dk. I ~ 1 p c ' i;> o- .v. tr .t- ~ ..R-10l Relief Request: Valves:.. $3SIH*V22,'V24,'V26',V28 { bategory: 0' IY Code' Class': 2 < 4. Function: To prevent. backflow into the safety injection system i whil'e the residual heat removal' system is in p .operacion, Test' Requirements: Exercise-(full stroke) quarterly. Basis for Reliefi The source of flow to full stroke exercise these is the safety-injection pumps (3SIH* PIA and PIB). The shutoff head of these pumps (1,520 psig)'is Le ' insufficient to stroke these valves against the normal reactor coolant system.(RCS) pressure. ' Full-stroking cannot be performed during cold shutdown U because'the required flow would risk over pressurization of the RCS. Alternate Testing: 'The valves will be full' stroke exercised during refueling" outages when the reactor closure head is: removed. 'l l i b a _------__a
l'
- f. /
..4.. f( .\\ ' b' - ) i 7 ,t i Relief Request: R-11
- h T I
X J l 6h si! I . Valves: 3CHS*V261 Catego ry : C S Code Class: 2- , g' - i .r t s1-v L Function: To prevent backflow from the chemical and volume control system to the refueling water storage tank, (RWST). l v 4 f Test Requirements: Exercise (full stroke) quarterly. Thisvalveisinthesuctionlinebetweenthechargir${) f? . Basis for Relief: pumps (3CHS*P3A, P3B, and P3C) and the refueling
- -{'
I water storage tank. Stroking this valve by taking' suction from RWST with the charging pnmps during operation would result in uncontrolled boration'of l 1 the reactor coolant system and a plant shutdown. Stroking this valve during cold shutdown would restIlt I in overpressurization of the RCS. l i i Alternate Testing: The valve will be full stroke tested during refueling t outages. i I / f i I l I< l t .l u \\' fi i b_.
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a. n a N 7. v - m 4, k,&,. [ 3, y _f li . v. a lc h;E - @ n#d '. _R.e.. lief Request: .R-12 . ' /,. / ,!' 9,. >f :"".;;t,\\ ;,p p; 1 ye L -ik'*fiI Q'. ' bqk 1fQ!).y Valves:- .3SIH*V11
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.g ' Category: LC-i f'.n 3 P .4f ..[ Code ~ Class: ,.2-1yd*~ p ff , h' ,3 .a. j -Function: -To prevent backflow to the Refueling Water Storage = f 't >. gg[$ . t Tank during ceitain modes of Safety Injection - E b-i) Operation, h < : if,g 9. s L t 1 I s-. a
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t N/ am y ' this. valve during power operations since:the safety t .y s ,7 j -injection pumps do;not develt,t$ sufficient-h'ead to w .u. t b. P ' overcome RCS pressure. Full stroke testing cannot be h .F. ' Performed during. cold shutdown because the' require'd 4 yj K+ f 3. j . flow would' risk'overp' pressurization of the RCS. Iw4 r .s $y'l .I , ~ Alternate Testing: This valve will be part stroke tested ~ quarterly-it ' 7 c .during the surveillar ce tests for the Safety. m. - se f 1 - Y t, ts Injection' Pungs 3SIH* PIA and -3SIH*PIB. Full stroke + 8.. i, ..t 4 s I testing,,wil.(beperformedduringrefuelingoutages y sy' when phe reactor closure hear 4 is removed. .p f j , ;. /,f. - 1 i j YN, * ? y 7 I, I \\' k l I l I;*. i Ll O ik fg ) y e-a e _ __ _ :_ _. ,a
A Relief Request: R-131 I Valves: 3RCS*V29, V70,.V106, V145 Category: AC Code Class: 2 I i Function: Pressure isolation between'the reactor coolant system (RCS) and the chemical and volume control system . (CVCS), i Test' Requirements: Exercise (full stroke) quarterly. Basis for Relief: Full stroke exercising these valves during power 1 operation would unnecessarily thermally shock the HPSI inlet nozzles to the reactor coolant system l t (RCS) cold legs by injecting nonpreheated water. Full stroking cannot be performed during cold shutdown because the required flow would risk overpressurization of the RCS. Alternate Testing: The valves will be full stroke exercised during refueling outages when the closure head is removed, i l i i l f
Relief Request: 'R-14 i Valves: 3SWP*V25, V27, V58,-V60 .l i Catego ry: B-Code Cla-s: 3 Function: Service wate'r supply valves to the recirculation spray system coolers. Test Requirements: Exercise (full stroke) quarterly. i Basis for Relief: These valves are interlocked so that they cannot be i opened unless valves 3SWP*V33 and V65 are closed shutting off service water. supply to the component cooling water coolers. Component cooling water (CCP) cannot be secured during power operation. A failure of CCP during power operation'would inop. 1 Tech. Spec. required train of CCP and related safety equipment. Component cooling water cannot be secured j during cold shutdown. This would prevent proper cooling of safety related and non-safety related equipment and cause a SWP pump runout. ~ Alternate Testing: Full stroke during refueling outages. l f' (. Y l i
h' 1-g Relief-Request: R-16 l. Valves: 3HCS*V7, V14 Catego ry: AC Code' Class: 2' Function: Containment Isolation Valve Test Requirements: Exercise closed (full stroke) quarterly. Basis'for Relief: The function of these va1ves is to provide containment isolation when the hydrogen recombiner is not in operation. There is no other flow path available to stroke these valves closed during power operations or cold shutdown. The dowstream side of these valves-is open to containment atmosphere. To verify 'these valves closed during the LLRT tests, a special test connection is installed to pressurize between the valves and the special connections. This connection is removed during power operation and cold shutdown. Therefore, these valves cannot be exercised during power operations or cold shutdowns. Alternate Testing: This valve is subject to local leak rate testing every two years as required by 10CFR50, Appendix J. This test uses a temporary pressurization source to check the valve's leakage rate which verfies that it goes to the closed position.
p !f. Reliev Request: R-17 Valves: 3CHS*V393, V433, V466, V500, V532, V533 Category: A l Code Class: 2 J l - Function: Seal Water Supply and Return Containment Isolation Valve-Test Requirements Exercise closed (full stroke) quarterly. I Basis for Relief: Plant operating procedures (per Westinghouse Tech. 'j Manual) require #1 seal return flow to be maint.ained whenever (RCS) pressure exceeds 100 psig. Isolating I these valves during plant operation, or cold l shutdowns in whic'h the RCS is pressurized could damage the RCP seals. Alternate Testing: These valves will be full stroke exercised during j refueling when the RCS is depressurized to less than f 100 psig. NOTE: Full-stroke exercising of the seal. return valves will be performed during cold shutdown when the RCS is depressurized (i.e., for cold shutdowns which depressurize the RCS to less than 100 psig). NOTE: Full stroke exercising of the seal supply valves will be done on cold shutdowns in l which the RCS is drained down to a level which uncovers the RCP seals (i.e., refueling or cold shutdowns which drain the RCS). x-_.___._._
[ q w-1; .k' ./k 4. Felie f. Reques t': ' R-18. Val'ess' ~3CHS*V46, V47,LV48: v ' Category: Cs Co'de Class: 2~ Function: To prevent backflow'through the associated charging pump lwhen secured and at least' one other charging pump is operating. l Test Requirements: = Exercise open (full stroke) quarterly, q l Basis for Reliaf: The normal loads on the charging pumps do not generate. H sufficient flow (design flow) to full stroke the valves during normal charging operations. Establishing injection' flow through the-HP. injection lines is .g.. . impossible because it could cause thermal shock, reactivity changes due to cold' water injection, and' abnormal pressurizer level deviations. These valves l cannot be exercised during shutdowns since injection l l flow could result in low temperature over pressurization of the RCS. '{ lo Alternate Testing: These valves will be quarterly part stroked, and full 1 stroked exercised by subjec' ting them to full design 7 flow during refueling outages. I l l l l i. s
wx / 'y 4 O', v{ Relief Request - 'R-21' ( . Valves: iAll'10'CFR 50 Appendix J Tested Containment Isolation ~ 4 Valves that serve only a containment isolation: ~ function. Category: A and'AC Code Class: 2 , ;p. containment-Isolation Function:' 1 Test Requirem'ents: IWV-3421 through IWV-3425 Basis'for; Relief: -Leak test procedures and requirementsLfor containment" ' isolation valves are determined by 10 CFR. 50 Appendix.J, 'IWV 3426'and 3427 ' Relief from paragraphs.IWV-3421 'through'3425.(1983 Edition.through Summer 1983 A'ddenda)' presents no' safety. problem since the intent of these ' paragraphs is met by Appendix J requirements. ' Alternate Testing: All.10 CFR 50 Appendix J test'ed valves that serve only a containment isolation function shall be tested in accordance with the requirements of Appendix J.
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_ ;.;lg E ~ ] / , g. L b : 7.. ., '. 3-a - ,,t -Relief Request: R-22:- g n: a' Valves: 3SIL*V2'6,'V28; 3RCS*V69,'V142 a b 1 L Category:- AC Co'de Class: -2 .n Function:= Pressure isolation between-the Reactor. Coolant System and Residual Heat Removal System. 5 q: ETest Requirements: Exercise (full stroke) quarterly. Basis for Relief: There;is no flow path available to test these valves- .during power operation with a pressure source capable +- of overcoming Reactor Coolant-System pressure. The normal; pressure sources'which would be used during an accident to' stroke the valves are the Residual Heat- . Removal (RHS)-pumps which. develop a shutoff head of' ~ only 200 pounds. Pumping into the RCS via the RHR s pumps is the only flow path'to full flow exercise these valves. The'se valves'cannot be exercised during cold shutdown because establishing. flow q through.these valves could result in RHR cooling flow bypassing the reactor core. Alternate Testing: These valves.will be full stroke tested during 7 refueling outages. a. I
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4-Relief Request:
- R-23 Valves
3SWP*V705, 706, 707, 708 Catego ry : C Code Class: 3 Function: Safety injection pump coolers /MCC and rod control booster pump suction. LTest Requirements: Full stroke exercise (quarterly). I Basis for Relief: Full stroke exercising these valves closed would require stopping the Service Water Pumps which provide both safety-related cooling capability at power operation as well as shutdown cooling capability during cold shutdown. Alternate Testing: These valves will be partially disassembled, inspected and manually exercised on a staggered sampling basis for each refueling outage..During each disassembly, the valve internals will be i inspected for structural soundness (no loose or corroded parts). In the event that a disassembled valve's full-stroke capability is questionable, additional valves will be' disassembled until one hundred percent (100%) of the valves identified in this group have been disassembled and inspected. l L I l l l l. 1-l ____.________-_--___a
L f, f Relief' Request: R-24 Valves: ~3RCS*V30, V71, V107, V146 Category: AC Code Class: 'l Function: Pressure isolation between the reactor coolant system 1 and the safety injection accumulator tanks. Test Requirements: Exercise (full stroke) quarterly. Basis'for Relief: -These valves cannot be full stroke or part stroke exercised during operation since no flow path can be established to accomplish such a test. Normal flow through these valves during cold shutdown is provided from the RHR pumps. The discharge path from a single pump' injects through two loop check valves, and, since no individual loop flow indication is available, stroking of a single valve cannot be verified. Flow from the accumulators cannot be initiated because this would result in a complete or partial discharge of the l tanks into the reactor vessel which could result in low temperature overpressurization of the R'CS. i l Alternate Testing: These valves will be partially disassembled, l inspected and manually exercised on a staggered sampling-basis each refueling outage. During each disassembly, the valve internals will be inspected for structural soundness (no loose or corroded parts). In the event that a disassembled valve's full-stroke capability is questionable, additional valves will be disassembled until one hundred percent (100%) of the valves identified in this group have been disassembled and inspected. l
ll h Relief Request: R-25 Valves: 3EGF*V25, 26, 51, 52 l Ca tego ry: B 1 i . Code Class: 3 Function: Emergency Diesel Generator Air Start Solenoid Valves. e Test Requirements: Full stroke testing quarterly. - Basis for Relief: It is impractical to measure the limiting value of i full-stroke time of these valves. These valves do not have remote position indication. Measuring the stroke time of these valves by observing stem travel would require disassembly of the operator. The safety function of these valves is to open to support the start-up of its respective diesel to provide rated frequency and voltage in less than ten seconds. Successful start-up of each emergency diesel generator within the above specified conditions is dependent upon the proper operation and speed of these valves. Measuring start-up time of each emergency diesel generator is an indirect method of verifying the degradation of these valves and meets the intent of the code. Upon failure of the diesel I generators to start as required, corrective action shall be taken to assure proper diesel start-up conditions. l Alternate Testing: These valves shall be full-stroke tested using the [ i emergency diesel generator start-up times per Surveillance Procedure 3646A.1 & 2 as an indirect j indication of valve operability. i _m-_m
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- Relief Request
- L R-291
( I i - 4 aValves: 3RCS-V175i C '" 1 m 'C p ~ Category: 4 ~ Code Class: 1 Function: Provide emergency / backup means of pressurizer /RCS- , pressure control. Test' Requirements: SExercise (full stroke) quarterly 3 Basis'for Relief: This valve' isolates the, pressurizer auxiliary. header- ,i J .from the normal' charging heade'r. Stroke. testing of 'this valve during power' operation would result in a {= _ pressurizer pressure transient and thermally shock the pressurizer spray nozzle. ~ . Full stroke exercising, at cold shutdown, is not -practical while solid since there is no flow device i ~ to measure flow and there would be no'effect on -plant pressure. If a steam bubble were to exist at cold shutdown the differentia 1' temperature is too high and cause a thermal cycle (refer to Technical Specification 3.4.9.2 and 5.7.1). - l ) -4 . Alternate Testing: This valve will be full stroke exercised during o refueling when the RCS is depressurized and the j pressurizer is drained down. 'l \\ t t - e
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g) ,All power operated valves listed in the. valve lists. l Component Identification: -ASME Code Class: 1,'2, 3 y -IWV 2200 Valve Category: A, B U; Valve Function: .As' identified in. valve lists. 19 Test Requirements: Paragraph IWV-3417; "(a) If, for power fl 1 y operated valves,'an increase.in~ stroke' time of 25% or morelfrom the previous test for' j valves;with full-stroke times greater than j 7; ~10 seconds or.50% or more for. valves with. gj i l ' full-stroke. times less than or. equal to l ,:.c 10 seconds is observed,- test frequency I shall be increased to once each month until ~ I corrective action is taken, at which-time the original' test frequency shall be resumed. In any case, any abnormality or erratic action shall be reported. Code' Relief: Relief is requested from comparing present stroke times to stroke times from the previous test. I i h r 1 1 y, J-s l
U~ u. 'l L } -1 s Basis for Relief: Use of the " previous test" stroke time does l I I not adequately identify slow degradation of I valve performance. For example, repeated increases in stroke time of 15 to 24 percent would not rbquire that the valve be considered in'" Alert", with attendant additional investigation and testing. The j proposed alternative acceptance criteria would identify such valves and require that they be formally evaluated for acceptability or declared inoperable. In instances where the evaluation does not result in.a determination of inoperability additional or increased frequency testing may be specified to aid in evaluating valve perfo rmance. This criteria'provides increased assurance that degrading valves are promptly identified and that such t degradation is promptly evaluated for its impact on valve operability. ? Proposed Alternative: Test results shall be compared to the reference values of stroke time for each valve. a. Valves with reference stroke times greater than 10 seconds shall exhibit no more than a 125% change in stroke time when compared to the reference
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. r;M..yg .c. . Valves with reference stroke times' b. 'a ,.p 3 :. I less1than 10 seconds shall exhibit no more than a-50% or 1.second (which J s a,., ever is greater) change in stroke time o. .?" when compared to'the referenceLvalue. JE c. . Valves with reference stroke. times of less than 2 seconds.shall not exhibit a' stroke time in' excess of 2 seconds. ' Valves with measured. stroke times'which do not1 meet the-above acceptance criteria shall be immediately' retested (or declared inoperable). If retested and the second set of' data also does not. meet th'e acceptance criteria either the' data shal'1 be analyzed within 96' hours ~ to.v'er'ify that'the new s'troke time' represents l acceptable' valve operation, or the valve shall be declared' inoperable. If the analysis indicates.the' deviation is acceptable, operation of the valve shall be tested monthly until it is repaired or declared i inoperable, or until a new reference value a' is established. 'If trended test results 1 indicate the valve will exceed the limiting value of stroke time prior to the next test I or that valve operation is unreliable the valve shall be declared inoperable. The >? evaluation shall be documented in the record of the tests. ,i< l i. r L= :__
m.. v j-1 e p1 ' n. ~' i :- ~r s 'If'the second set'of data meets.the i p' acceptance' criteria,cthe'cause of the. .i 1 initial. deviation shall be analyzed and the. - results; documented in'th'e record of tests. ~ s F . Valves'for which measured' stroke times D i exceed limiting values for stroke times: j s .1 shall be.immediately declared inoperable. -i i Valves which are declared: inoperable ~shall 1 be readjusted, repaired, or replaced prior ] to returning'the valve,to s'ervice. A' test' -j demonstrating satisfactory. valve : performance shall;be performed prio'r to returning the valve to service. i 'l a -l 1 i b 1 1 a 1 t.~ .J I I 'd-I 4 i
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D * '. r 'yl ,.l 1 4 4;,' ~ g, p. X Relief Request': R-19 , w: 4 Specific relief is.being. requested from.the Sub-section IWP-4500 for'the method of testingland a: 1 ' allowable l ranges ~(Table 3100-1 and 3100-2) for pump. 7 33 vibration measurements of all safety-related pumps. R Code Requirement: At least one Displacement' Vibration Amplitude (peak-to-peak composite) measurement shall be taken b 'during each inservice test and' the allowable ranges, - in relation to reference values, are tabulated in n: ~ Table'IWP-3100-2. ~ Basis for Relief: Experience has shown that measurement of overall' >;O vibration amplitude in mils does not' provide the desired early. warning of pump degradation. Vibration' amplitude is adequate for measuring unbalance,' misalignment,.and other low frequency failure modes, 'It does not give early warning of bearing degradation '~ since.the magnitude of higher frequency vibrations created by such degradation is 10 to 1,000 times i lower than the normal. pump movements. Experience at Northeast Utilities has shown that monitoring pump' vibration velocity (in/sec) provides earlier warning 1 Lof pump degradation-Collection and review of vibration " signatures" (plots'of vibration velocity l vs. frequency) over a range from slightly below running frequency.to several times running frequency provides optimal early warning of pump degradation. 1 1, l Os l l i 'I [ i
1 1 1 i Alternate Testing: In lieu of measuring overall amplitude (mils), the j following vibration monitoring program will be ) i implemented: 'l ,i Vibration will be monitored at least quarterly using equipment which collects vibration velocity i signatures. 'Overall, vibration velocity (in/sec RMS) will be compared to the following acceptance criteria: NOTE: This acceptance criteria is based on Draft 11.of O&M-6. t Acceptance Range - O to 2.5 times Reference Velocity Alert Range - > 2.5 to 5 times Reference Velocity but not greater than 0.325 in/sec. (RMS) Required Ac' ion Range - > 5 times Reference Velocity t but not greater than 0.07 in/sec. (RMS) i Reference Velocity shall be the average overall velocity determined during an inservice test at reference conditions when the pump is kncwn to be operating acceptably. In addition to the above quantitative analysis of overall vibration levels, vibration signatures will be reviewed at least quarterly to identify potential bearing degradation or other developing faults. When potential faults are identified, action as required for a pump in the Alert Range of vibration will be initiated. i
s Rell'f Request: R-20 e K Specific relief is being requested from Section XI requirement to measure bearing temperature yearly and I. it is proposed to evaluate bearing performance using E a vibration signature analysis for each safety-related pump. Code' Requirement: Measure annually the temperature of centrifugal pump . bearings and main shaft bearings'of reciprocating j pumps at points selected to be responsive to changes l l in temperature of the bearing. ' l 1 Basis for Relief: Bearing metal temperature monitoring can be effective in detecting bearing problems. However, none of the tabulated pumps have adequate design provisions to allow meaningful bearing temperatures to be taken. The annual measurement of bearing housing temperature l is far less effective in detecting bearing problems than the quarterly performance of vibration signature analysis being performed by NNECO. l In general, as internal bearing metal temperatures i increase due to bearing overload, improper lubrication of faulty installation, etc., much of the 'I heat will be dissipated throughout the relatively massive housings, oil reservoir and attached casing. As a result, bearing housing temperatures will respond much less than bearing metal temperature, greatly reducing the sensitivity to detect bearing heatup problems.
s t Another important requirement to assure reliable -bearing temperature monitoring it that it be continuous, not periodic. Experience indicates that failing bearings whether anti-friction type or sleeve often exhibit fluctuations between normal and abnormal metal temperatures. A good e'xample is the l babbitt. lined sleeve bearing which will initially. experience a. rapid rise in temperature and~then return to normal temperatures after the bearing wipes and clearances open up causing increased oil flow. The abnormal temperature rise would most probably go l undetected unless continuously monitored. I I The vibration signature analysis conducted by NNECO will detect bearing problems at a very early state. At the onset of a bearing problem, low level vibration will be generated at characteristic frequencies depending on the nature of the problem. The low level vibration typically amounts to less than 1 percent of the overall vibration amplitude and therefore cannot be detected by a simple amplitude monit'oring program conforming to IWP minimum requirements. However, the low level changes in l bearing distress frequencies are routinely detected 1 1 in the MP3 signature analysis program and analyzed to pinpoint the cause. l Alternate Testing: As an alternate, the pump vibration signature tests ~ ) will be performed, recorded and analyzed quarterly as described in Relief Request-19. This analysis will provide more meaningful analysis of pump bearing condition than annual measurement of bearing temperature. l l lL-__-_-_-----____._
,.1 i i ~! ' Relief Request: R-26 Pumps: 3SWP*P1A, P1B,'PIC, P1D Code Class: 3 o l . Function:7 Pumps are required to perform a function in shutting [ down' the, reactor, or ' mitigating the consequences of ) an accident, and are provided with an emergency power a I source. Test Requirements: IWP-4200 Pressure Instruments. 9 Basis for Relief: The service water pumps are vertical shaft pumps with l no direct means to obtain the inlet pressure as required by IWP-4200. i Alternate Testing: The inlet pressure will be calculated based on the. I water level (tide between 0-4 ft per the surveillance procedure).above the pump inlet. This method provides sufficient information for evaluation of the hydraulic condition of the pumps. NOTE: The flow rate is measured by shedding all loads except for a CCI, CCE-and EDG bypass ) flow.(these are very minimal flow losses), ) ~ the output through one CCP heat exchanger i i is then throttled to the reference flow identified in the surveillance procedure. 3 l 1
p-i- y )' I jG l ? h i Relief Request: R-28 Pumps: 3EGF* PIA,'1B, 1C, ID - Code Class: -3 Function: Pumps provide the emergency diesel' day. tanks with i proper fuel oil supply. Test Requirements: 1WP-4200 Pressure Measurements. Basis for-Relief: The-fuel oil transfer pumps take suction directly from the fuel oil storage tanks and discharges to the fuel. oil day tank. No inlet (suction) pressure l indication is available. Pump discharge pressure is available and will be recorded. - Alternate Te' sting: The fuel oil storage tanks are required per Technical Specifications 3.8.1.1.b.2 to be filled to a minimum volume of 88% (32,760 gallons) not to exceed 95% (due to overflowing of the tank) The pressure difference between 89% and 95% is less than a fourth of a pound (psi). The discharge pressure will be recorded quarterly and the ASME limits per Table IWP-3100-2 will be applied to this reading. j i l l 'l l 1 l l whi_._- _ _ _ _ __ _ _ _ _ ____
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~. 4 1 l 7.1 Valves With Testing Deferred to Cold Shutdown 1 As permitted by IWV-3412(a), the following valves which cannot j be exercised during plant. operation will be exercised during cold ehutdown. Certain valves, for which limited operation is practical during operation, will be part stroke' tested during plant operation, as well as full stroked-during cold shutdown. These valves are denoted by (PS) following the valve identification. Reactor Coolant System 3RCS*V142 (8949D) 3RCS*V174 (AV-8145) 3RCS*V168 (PCV-455A) 3RCS*V175 (8377) 3RCS*V170 (PCV-456) l l Chemical and Volume Control System 3CHS*VS (CV-8152)' 3CHS*V333 (8508B) 3CHS*V40 (LCV-112B) 3CHS*V710 (MV-8507B) 3CHS*V41 (LCV-112C) 3CHS*V711 (MV-8508A) 3CHS*V56 (MV-8106) 3CHS*V712 (MV-8507A) 3CHS*V57 (MV-8105) 3CHS*V802 (CV-8160) 3CES*V320 (8442) Low Pressure Safety Injection System 3SIL*V5 (MV-8809A) 3SIL*V18 (MV-8808C) 3SIL*V6 (8818A) (PS) 3SIL*V20 (MV-8808D) 3SIL*V7 (8818B) (PS) 3SIL*V25 (MV-8840) 3SIL*V11 (MV-8809B) 3SIL*V984 (8847D) 3SIL*V12 (8818C) (PS) 3SIL*V985 (8847C) 3SIL*V13 (8818D) (PS) 3SIL*V986 (8847B) 3SIL*V14 (MV-8808A) 3SIL*V987 (8847A) 3SIL*V16 (MV-8808B) 1 1
c.... 4 ~ R Res1 dual Keet' Removal System J3RHS*V4 Of/-8716A) 3RHS*V996 (MV-8702B)- t Y 3RHS*V8 - (W-8716B) ' 3RHS*V997 (MV-8701A) 3RHS*V994 (trJ-8702A) -3RHS*V998 (MV-8702C) 3RHS*V995'(M7-B791B)' 3RHS*V999.(MV-8701C) High Pressure Safety Injection System '3SIH*V3 -(MV-8801A) 3SIH*V93 '(MV-8802A). '3SIH*V4-(MV-8801B) 3SIH*V100 (MV-8802B) 3SIH*V10 (MV-8806) 3SIH*V962 (MV-8813) 3SIH*V20 (MV-8835) hin Steam System 3 MSS *V1 (CTV-27A)'(PS) 3 MSS *V7 (HV-27C).(PS)' 3 MSS *V2-(CTV-28A) 3 MSS *V8 (HV-28C) '3 MSS *V4' -(CTV-27B).(PS) 3 MSS *V10 (CTV-27D) (PS) y 3 MSS *V5. (HV-28B) .3 MSS *V11 (HV-28D) ' Main Feedwater System 3FWS*V15 (FCV-510) 3FWS*V34 (CTV-41C) .3FWS*V18 (LV-550) 3FWS*V36 (FCV-540) i 3FWS*V20 (CTV-41A) 3FWS*V39 (LV-580) 3FWS*V22- (FCV-520) 3FWS*V41 (CTV-41D) 3FWS*V25 (LV-560) 3FWG*V898 3FWS*V27 (CTV-41B) 3FWS*V899 3FWS*V29 (FCV-530) 3FWS*V920 -3FWS*V32 (LV-570) 3FWS*V921 Service Water System 3SWP*V33 (MV-50A) 3SWP*V65 (MV-50B) s _m _ __.m__m_._._____t._____
y Auxiliary Feedwater System 3FWA*V3 . 3FWA*V28 3FWA*V7 3FWA*V31 3FWA*V9 3FWA*V35 3FWA*V12 3FWA*V39 3FWA*V14~' 3FWA*V43 3FWA*V17 3FW.2,*V47 3FWA*V21 3FWA%YB82 3FWA*V23 3FWA*V883 3FWA*V26 3FWA*V884 3FWA*V885 i Instrument Air Systg 3IAS*V131 (PV-15) 3IAS*V809 (MV-72) Primary Component. Cooling 3CCP*V60 3CCP*V18 t 4 f 1 I l l' 1 l
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, f ' 1 i. s i. 'j['(. ' " ~ ut 7 F f .a - i f LRelikf Rdquesti CSR-l' Valvesi. L. SIL' V6l V7, V12, V13, V984, V985',' V986', :V987.. gU 1 0 Category:I .AC. I M
- Code' Class
l T Function:- Pressure' isolation between th'e Reactor Coolant. System 'and Residual' Heat Removal ystem. r; Test Requirements ; Exercise (full stroke) quarterly.
- Basis for Relief:..There is.no flow ~ path.available to test these valves during power operation with a pressure source. capable.
of overcoming Reactor Coolant System pressure. The normal pressure sources which would be used during an accident to stroke the valves are the residual heat ( removal'(RHS) pumps which develop a shutoff head of-only 200' pounds. -Alternate Testing: These valves will be full stroke tested during cold'- shutdowns when the Residual Heat Removal. System is.in-operation. i l 1> l '. i l 1 ---.a-a- - -
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- CSR-2 DELETED
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't. Valves: T - + t I Catego:y! " ', ~ Ql ,g. Code'classij y e' .\\ function: b '. / 'k1 ~ g ..l - leg.1 hquirements: ~ g 1T s- / s a l~ - 's1s 4 3 .Ba_s._/. s f o r Relie f : (L ' l \\ Alternate Testing: n ~ 1, )'. e f i a 1 I 1 6
L L [- E Relief Request: CSR-3 Valves: -3RCS*V168, V170 ) ~ Category: B ' Code Class: 1 Function: Provide overpressurization protection for the Reactor Coolant System at reduced temperatures and pressures. Test Requirements: Exercise (full stroke) quarterly. Basis for Relief: Full stroke exercise testing of these valves during power operation is not practical, since they are not 4 required for overpressure protection at power and have shown a high probability of sticking open. The valves are relied on to protect the Reactor Coolant System from low temperature overpressurization. Alternate Testing: These valves will be. full' stroke tested during cold shutdowns. 1 i 4 l
f, ). Relief Request: CSR-4 Valves: '3RCS*V174 Category: B, C Code Class: 1 I i Function: Auxiliary Spray isolation valve i Test Requirements: Exercise (full stroke) quarterly. 1 1 Basis for Relief: This valve isolates the pressurizer auxiliary header from the normal charging header. Stroke testing of this valve during power operation would result in a ~ pressurizer pressure transient and thermally shock the pressurizer spray nozzle. Alternate. Testing: This valve will be fiill stroke tested during cold shutdowns. 1 I I j 1
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- Relief Request:
CSR-5 -l al i Valves: 3CHS*V5, V56, V57, V802 t f Category: A and B ,o Code Class: 2 i - Function: Containment Isolation Valves / 1 g Charging Flow Controller Isolation Test Requirements: Exercise (full stroke) quarterly Basis for Relief: The charging and letdown subsystems of the CVCS is to establish a programmed water level in the pressurizer to maintain proper reactor coolant inventory and proper chemical control of the Reactor Coolant System. Full stroking exercising these valves on a quarterly basis during power operation could cause a loss of pressurizer level control and possibly a reactor trip. The plant is designed with a limited number of letdown isolation thermal cycles. As letdown is disrupted, the charging water to the RCS A is no longer heated up and causes a thermal cycle on the hot path to the RCS. e Alternate Testing These valves will be full stroke tested during cold shutdowns. .a-l l-L 1 1 I e.
ll 4];b ^" b hhh [, 4 "' r 'i ji '. L ~ Ls,,' TRel'iSf Request:. .CSR-6J o ). I% o 3CHS*V40,'V41, -Valves: 7 ,o l 'B-
- Category:
s, Code Class: 2 i Function: ' Isolation of the Volume Control Tank.from the; suction-side of the charging pumps. 4, Test.equiremen t's : 'Exerciae (full stroke)Lquarterly. 1 . Basis for Relief: Stroke testing of these valves during' power operation would result in a disruption of 'nonnal charging ~ flow and cause loss'of suction pressure to'an operating .charg'ing pump. This could give rise.to a loss of pressurizer' level' control 'resulting in a' plant trip. 'Use of the alternate pump suction source may. result 'with injecting high concentration of boric acid into the RCS. Alternate Testing: These' valves will be full stroke tested during. cold-shutdowns. i i x___-
4 Relief Request:c OSR-7 DELETED l ' Valves: 4 'l Category: i Code Class. I l i Function: f Test Requirements: Basis for Relief: Alternate Testing: l i a l 1 l l i I 1 l l 1 1. 1 1
7.. ); 1.): i Relief Request: CSRv8 Valves: 3CHS*V333, V710, V711, V712 Catego ry: C and B Code Class: 3 ' Function: Provide a gravity boration path i Test Requirements: Exercise (full stroke) quarterly i Basis for Relief: In order to line up the charging system to permit exercising of these valves during power operation, it would be necessary to interrupt normal charging and letdown flow. Additionally, testing of these valves i at power would result in uncontrolled boration of the Reactor Coolant system with the reactor critical. A' rapid boration would introduce a large amount of negative reactivity to the RCS causing a plant shutdown. I i Alternate Testing: These valves will be full stroke tested during cold shutdowns when the reactor is shutdown. I 1 i -i l
a ] ~ i. l 1 i Relief Request: CSR-9 Valves: 3SIL*V14, V16, V18, V20 I Category : B Code Class: 2 Function: Isolate the safety. injection accumulator tanks when i RCS pressure is below accumulator tank pressure. 1 Test Requirements: Exe'rcise (full stroke) quarterly Basis for Relief: Stroke testing these valves during power operation is not possible, since plant operating procedures and Technical Specifications required the power to the valve operators to be disconnected and the valves to be open. ' Alternate Testing: These valves will be full stroke tested at a cold shutdown frequency during either plant heatup or plant cooldown. = _ _ _ _ -
- 9113, q.
e a_ y y. y 4 ~. 3 V x i e i, -> .L. ~' s l'^ w . Relief Request: 'CSR-11 L r '.I alves: 3RHS*V994,'V995, V996, V997, V998',.V999 2 V T 1 4 g < !.E '. l ,e , Category: A l 'l 'f L . Code Class: 1 l 4 g; Function: Pressure isolation'- ? t 1 Test' Requirements: Exercise (full stroke) quarterly. Basis-for Relief: Stroke testing of these' valves a't power is not possible. V994, V995, V996 and V997 are interlocked'- l to prevent operation (opening) when the Reactor 1 t Coolant System pressure is above 375 psig.. Full. _j stroke exercising V998, V999. poses unnecessary o -exposure to a low pressure system LOCA. These valves are'RCS pressure isolation valves required to be closed per Tech. Spec. 4.4.6.2 and are' leak tested within 24 hours after operation. In order to leak test these valves, a containment entry (personnel ~ i safety risk, th containment at MP3 is subatmospheric to 9 psia),is reg, ced, any leakage through.these valves flaches to steam.and must be vented to containment atmosphere (hydrogen and radioactive gaseous problem). Alternate Testing: These valves will be full stroke tested during cold shutdowns.
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- 4..
L -' I ,'l .,y ,w.,,'. 7.: . : Cate go ry :.-. A" <.,. r. ; I I d - i (.Y, r DCode Class:' L2' e L#fh I I I y,p,.:e Function:- LProvide an'. injection path for High Pressure Safety 3 .y- -, Injection and Containment < Isolation. -y : 'l' . i e 01 Test Requirements: ; Exercise-(full st.roke) quarterly' y,- Basis for Rell'ef: Stroke testing these. valves during' power' operation would require disruption of normal charging flow and .the. injection'of nonpreheated water'into the Reactor y Coolant System resulting'in thermai ahock to the l-;.1 < 's g::,R*- cinlet nozzles. Alternate Testing: These valves'will be full stroke tested during cold c i. shutdowns. t .'?.f,: 9 i <-) _j'.'- .I f) 9 -'I.' ( t t' s > I =. l' ,9 {._ i -' e-L. : L-__l _ L L.
i ' Relief Request: CSR-13 Valves: 3SIH*V10 Category: B Code Class: 2 Function: Realignment from injection to recirculation mode Test Requirements: Exercise (full stroke) quarterly Basis for Relief: This valve is in the position required during the initial phases of an accident requiring safety injection. The valve does not receive a safety signal, since realignment of the valve to the recirculation mode is accomplished by manual
- repositioning of the valve. Testing of this valve during power operation would place it in a nonconservative position temporarily disab' ling both safety injection trains and possibly causing damage to both pumps if an SIS were to occur.
If required, the valve can be repositioned locally so that deferring the testing of this valve to cold shutdown would not compromise plant safety. Alternate Testing: This valve will be stroke tested during cold shutdowns. l
[7 a L JJ t; -1 1 J i. i Relief Request: CSR-14 .1 i Valves: 3CCP*V18, V60 ) I Category: AC Code Class: 2 ' Function: Containment Isolation Test Requirements: Exercise (full stroke) quarterly i Basis for Relief: In order to full stroke (close) each of these valves, it would be necessary to secure component cooling.to the associated train. ("A" train for V18 and "B" train for V60). This would cause in a temporary loss of cooling water to the letdown heat exchanger for' ~ train "A" and the seal water heat exchanger for train "B". The result would be unnecessary thermal cycling of the supplied components causing premature failure of the charging lines to the RCS and, in the case of th'e letdown heat exchanger, an increase in the inlet temperature to the CVCS demineralizers. In addition to these components,. cooling would be l l lost to a number of important non-safety related components including the containment penetration coolers. Alternate Testing: These valves will be full stroke tested during cold shutdowns when the heat load to the supplied components is at a minimum. um_
Relief Request: CSR-15 Valves: 3 MSS *V1,'V4, V7, V10 Category: B l Code Class: 2 Function: Main Steam Isolation l Test Requirements: Exercise (full stroke) quarterly Basis for Relief: Full stroking these valves to the closed position during power operation would result in an unbalanced steam flow condition producing an abnormal power l distribution in the reactor core possibly causing a reactor" trip. Therefore, full closure of these valves for the purpose of testing requires plant shutdown. l' Alternate Testing: These valves will be part stroke tested during power operation and full stroke tested during cold shutdowns. 1
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(,> - 7, ReliefLRequesth ' CSR-16 e ~ Valves = 3 MSS *V2, V5, V8, V11 Category:, ~ B-e o Code' Class: .2' Function: Provide steam to warm lines'down stream of.the MSIVs-and' equalize pressure prior.to opening. m Test Requirements: Exercise'(full stroke)' quarterly . Basis for Relief': These-valves are only required'to'be.open while-warming the steam lines and remain closed during power operation. Opening these. valves at power -( merely toLtest that they close'could result in a '~ ' ct-failure of these valves in.a nonconserrative_(i.e., open) position resulting in'an uncontrolled cooldown. ~ Since these valves provide no safety function during power operations they will be full stroke tested at' cold shutdown. Alternete Testing: These valves will be' tested at a cold shutdown frequency to ensure closure.immediately following opening during' plant start-up before placing the 3 c -turbine in operation. 1
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- p Valves
3FWS*V15,;V22; V29, V36;- a.s I Category: ~B 1 - r -1 Code' Class: '2' lt } f ).4 e Function: Feedwater control valves' JJ Test Requirements: JExercise (full stroke) quarterly ' Bssis' for Relief: Strokettesting'these. valves shut during power operation would temporarily secure flow to an e operating steam generator and'potentially lead to a reactor trip.on low steam generator water level. l. ~ Alternate Testing: -These valves will be. fully stroked to the closed position during. cold shutdowns. l l l' l' 9 f. ( l s L..-
i ~! d Relief Request: CSR-18 i Valves: 3FWS*V20, V27, V34, V41 j . Ca tego ry : B d i Code Class: 2 l ] Function: Feedwater Isolation Test Requirements: Exercise (full stroke) quarterly f Basis for Rel'ief: ' Stroke testing these valves during power operation g would secure flow to an operating steam generator and cause a' loss of feedwater and a plant trip. I Alternate Testing: These valv'es will be stroke tested during cold j shutdowns. l 1 i I 1 a i 4 ) l __:__==- j
e ./ Relief Request: 'CSR Valves: 3FWS*V18, V25, V32,.V39' . Category: B Code' Class: 2 Function: To control feedwater at low power . Test Requirements: ' Exercise (full stroke) quarterly-Basis for Relief: These valves remain closed (their safety position) above 20 percent reactor power. Opening these valves to test that they close would subject the feedwater system to an unnecessary transient (on the steam o. generator water level control) possibly causing a reactor trip. Alternate Testing: These valves will be stroke tested during cold shutdowns. i ,l I l l b = _ - _ -. _ _ _ _
- t 4 .{ 'l Relief Request: CSR-20 Valves: 3FWS*V898, V899, V920, V921 Category: C Code Class: 2 Function: To prevent backflow'from the associated steam generator on loss of feed i Test Requirements: Exercise (full stroke) quarterly Basis for Relief: Stroke testing these valves at power would require securing feed flow to the associated operating steam generator causing a plant trip. Alternate Testing: These valves will be verified closed when feed to the associated steam generator is secured during cold shutdown. 4 1 l~ 1 l'
77.,- --- g,.m i L .I) Relief Request: CSR-21 I 1 Valves: 3FWA*V3, V7', V12, V17, V21, V26, V31, V35, V39, V43, j a 1 V47 1 Category: C 1 W q Code Class: 2 -l Function: Pass. required' auxiliary feedwater flow to the steam generator. Test Requirements:. Exercise (full stroke) quarterly Basis for Relief: Operating the auxiliary feedwater system at power is-undesirable at the required flows to fully open these check valves. This places an' undesirable thermal transient on the feedwater piping. Alternate Testing: These valves will be full stroke. tested open during cold shutdowns. j
m; '.j.J '.q -- 7 ,. g t ) 1-i 4 1 '.i. l( ').-. i a. l i Relief Request: 1CSR-22. Valves:' 3 ids *V131,.V809. L Category:.! A -y '2i -l 1; Code Class: ,n
- Function
~ Containment Isolation 4 5 1 LTest-Requirements: Exercise-(full stroke) quarterly- ' Basis for Relief: .These valves isolate the entire inside containment instrument air system from their normal source .L ' I .outside. containment. Full stroke. testing of these-valves during power operation would cause a' complete loss of instrument air inside containment.' As.a. .l result, all valves'inside containment supplied by. instrument air would stroke to their fail safe ~ position resulting in a plant shutdown at power. Alternate Testing: These valves will be full stroke' tested during cold shutdown. p. J L l' 4 h _ - = - =_ _ -
~ t Relief Request: CSR :- L Valves: 3CHS*V320 Category: C i; ' Code Class: 2 Function: Provide an_ emergency boration path le Test Requirements: Exercise (full stroke) quarterly Basis for Relief: Testing of this valve from the closed to open position during power. operation would result in boration of the Reactor Coolant System possibly causing a plant shutdown. Alternate Testing: This valve will be full stroke tested during cold shutdown. l
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- CSR-24 Valves:
3SIL*VS, V11 l . Ca tego ry.: A j j Code Class: 1 2 Function: RHR Cold Leg Containment Isolation Valve l ' Test' Requirements: Exercise (full stroke). quarterly. f Basis for Relief: These valves are required to be open with power ( i removed from the operators during modes 1, 2 and.3 1 per Tech. Spec. 3/4.5.2 to ensure operability of this 3 ECCS subsystem. Alternate Testing: These valves will be full stroke tested during cold l shutdown. b l, 3 l 1 j L
I t. t I \\ Relief Request: CSR-25 3SIL*V25/3SIH*V93, V100 - Valves: i c Catego ry: A ./ Code Class: 2 i Function: -SIL/SIH Hot Injection Isolation Test Requirements: ' Exercise (full. stroke) quarterly l Basis for Relief: These valves are required to be closed with power operation removed from the operators during modes 1, 2 and 3 per Tech. Spec. 3/4.5.2 to ensure operability of this ECCS subsystem. Alternate Testing: These valves will be full stroke tested during cold shutdown. i 1 3 i i 1
m. 4 Relief' Request: CSR-26 Valves: 3RHS*V4, V8' Category: B 'l Code Class: 2 Function: RHR Discharge Cross Connects Test Requirements: Exercise (full stroke) quarterly i Basis for Relief: Full stroke exercising these valves closed during j power operation would render the RHR system inoperable by isolating two of the four cold leg injection paths to the RCS from RHR. Alternate Testing: These valves will be full stroked tested during cold shutdown. .f k s I l l 1
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g l. lj.l.' l. L Relief Request: CSR-27 l' Ualves: 3SIH*V20 1. Category: A Code _Cl_ ass: 2 Function: RPSI'to Cold Leg Master Isol Test Requirements: -Exercise (full stroke) quarterly Basis for rem e_f,: This valve is required to be open and power removed f from the operators during modes 1, 2 and 3 per Tech. Spec. 3/4.5.2 to ensure operability of this ECCS subsystem. Alternate Testing: These valves will be full stroke tested closed during cold shutdown. a w__-_-___--'.
i 1 i Relief Request: CSR-28 4 Valves: 3SWP*V33, V65 Catego ry: B Code Class: 3 Function: Train A & B Service Water Header to RPCCW Heat Exchanger Inlet Manifold Test Requirements: Exercise (full stroke) quarterly Basis for Relief: Full stroke exercising either of these valves closed quarterly would isolate component cooling water heat exchanger resulting in equipment damage to both safety related and non-safety related trains. Alternate Testing: These valves will be full stroke tested during cold shutdown. l
t, ~ Relief Request: CSR-29~ (= Valves: 3SIH*V962 Category: B Code Class: 2 ..a ' Function: HPSI Master Mini Flow Isolation Test Requirements: Full stroke exercise closed quarterly Basis for Relief: Full stroke exercising of SIH*V962 closed during power operation would render both trains of HPSI unavailable to perform their safety function. Failure of this valve closed during power operations, if an SI signal occured and the RCS did not depressurize to the Safety Injection pump discharge head, it would dead head the pumps. Alternate Testing: The valve will be full stroke tested closed during cold shutdowns.
4 .i- ' l t I l' Relief Request: CSR 30 i i Valves: 3FWA*V9, V14, V23,'V28, V882, V883, V884, V885 Category: C i Code Class: 2 ) i Function: Pass required auxiliary feedwater flow to the steam generator. -Test Requirements: Exercise (full stroke) quarterly' Basis for Relief: Operating the auxiliary feedwater system at power is undesirable at the required flows to fully open these check valves. This places an unnecessary perturbation on the main feedwater control system f which could result in a reactor trip. It also causes undesirable thermal transient on the feedwater piping. Alternate Testing: These valves will be full stroke tested during cold shutdowns. I J
r-s-9 T i e( M; 6 i, l: Relief Request: CCR-31 .i- of Valved: /.?CBS*V665,7v666 l-1 g> i,. Category: 2 L. O I Code' Class: B Function: ' Charging Pump Relief Isolation Valves 4-i Trikt,;Requireg,epts : Exercise (full stroke) quart.erly .j e p
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Basis for' Relief: Stroke testing these valves during power. operation is not possible since these valves are interlocked to open when 3CHS*LCV112B and C (VCT isolation to suction of charging pumps) go/ closed. This would J. t,, p disrupt normal charging flow and cause a loss of' 1 '(,i suction pressure to an operating charging pump, _ resulting in loss of pressurizer level control and a PAant trip. 4a. y Alternate Testing: These valves will be full stroke tested during cold shutdown. /' mV / 4. ^+ i s 4 Y
4 1 i 8.0 SYSTEM PRESSURE TESTS 8.1 System Pressure Tests - Class 1 8.1.1 System pressure tests are conducted on Class I systems and' components as follows: 1 (a) A System leakage test is conducted prior to l 8 plant start-up following each occurrence where ] the Class'1 pressure boundary'is breached, such I as during a refueling outage. The pressure retaining boundary subject to the leakage test ) corresponds to the reactor coolant system l boundary, as established with all valves aligned as required by approved plant operating i i procedures for start-up and normal reactor ] operation. The'VT-2 examination boundary extends to include the second closed valve at the boundary extremity, which may be a check valve opposing Reactor Coolant system pressure. I The test is conducted at system operating g temperature and pressure, f (b) A System Hydrostatic Test is conducted on all Class 1 piping and components within the system l boundary at or near the end of the inspection interval. The system boundary is determined in accordance with the requirements of paragraph IWA-5229 of the Code, q 8.1.2 The system boundaries subject to system leakage and system hydrostatic tests are shown on the pressure i test boundary drawings, (See Section 5.0). i ) I ( l 1 I
.) 1 y 1 1 8.2 System Pressure Tests - Class 2 8.2.1 .The pressure retaining components within the Class 2 system boundaries are subjected to System Pressure-Tests in accordance with IWC-5210 and visually j examined (BT-2) per IWA-5240. The tests are conducted as follows: (a) System Functional Tests, IWA-5211(b) - For those systems, or portions of systems, not. required to operate during normal reactor 1 operation, but for which periodic system or component functional tests are performed, as required by the Plant Technical Specifications and/or the Pump and Valve (IST) program, a VT-2 examination is performed at least once during each period during the system or component l functional test. The boundary subject to pressurization during a System Functional Test includes only those pressure retaining components within the system boundary pressurized under the test mode required during the performance of the periodic system (or component) functional-test. Nominal operating pressure of the system functional test is acceptable as the system test pressure. (b) A System Hydrostatic Test, IWA-5211 (d) is performed on Class 2 systems at least once during each inspection interval. The boundary subject to test pressurization during a System Hydrostatic Test is defined as the Class 2 system boundary and includes only those portions of the cystem required to operate or support the safety system function up to and including the first normally cl'osed valve (including a safety or relief valve), or valve capable of automatic l closure when the safety function is required. ) Y_ __-_ _ __ _
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- m The VT-2 examination, performed during' a System Hydrostatic Test, is used to satisfy the system 1
pressure test requirements of (a) above, for the period in which it is conducted. ] 8.2.2 The boundaries' subject to steam pressure tests j e 1 (functional and hydrostatic), are shown on the pressure test boundary drawings (see Section'5.0). { 8.3 System Pressure Test - Class 3 D: 8.3.1 The pressure retaining components within the boundary of each system specified for Examination Categories D-A, D-B, and D-C are pressure tested and visually examined (VT-2) for leakage during the following tests: List of Systems A. Auxiliary Feedwater System B. Chemical & Volume Control C. Component Cooling Water D. . Fuel Pool Cooling E. Service Water F. Steam Generator Blowdown (a) For systems required to operate during normal plant operation, a System Inservice Test, IWA-5211(c) is conducted at least once each period while the system is in-operation and at operating pressure. The boundary subject to test pressurization, during a System Inservice Test, extends to those pressure retaining components under operating pressures during o normal system operations; I L I L OR l' f 1 k I L I L'+
' - ~ ~ ~c~ ~ '~--- ' - - - 7- ,c6 a .i s.* ? )w, jl l .Q.y, e j ? l?:9f a. ) 1 n b'., a J D1 .. j P.. [. lf., ' ^.. !(b) System' Functional Test, IWA-5211(b) - ~ g. .For:those systems, or pcrtions of. systems, not, tO W.:c = required ' to' operate during' 'nonnal. plant: i r . operation, a ' VT-2. examination. is performed K during a= periodic system-orfcomponent.. functional
- test,J asl required.by: the Plant Technical!
l "E Specifications and/or the Pump and' Valve (IST) Program.. The boundary. subject to rest pressurization during a System' Functional Test includes only thoses pressure retaining .g', 4 . components within'the'sytem boundary pressurized T ,yl under the. test mode required'during.the -j 1 performance of the periodic system (or l r u component) functional test. 'The. nominal vF ' ' operating pressure of the system functional. test. ' ~ is acceptable as the system test pressure. 3 1 v AND 1 , 4 l 't (c) System Hydrostatic Test, IWA-5211(d) - is performed on Class 3 systems once in.each -interval. The boundary subject to test 'l pressurization extends up.to and includes the j first normally closed valves, or valve capable j of ~ automatic closure, as required to perform the i safety-related' system function. The system i pressure requirements are defined in subarticle' IWD-5223 of'ASME Section XI. The VT l ~ i C;f examination,. performed.during a System j Hydrostatic Test, is.used to satisfy the system ~l y , E b.; pressure test requirements of (a) and (b) above for that period in which it is conducted. v. ~ l I d o
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a A ~ p . ( f ,')' ' NOTE: Pressure Test Boundary Drawings g.,bg .q ' &.s Class l', 2 and.3 (Sections 8.1, ' 8. 2,.. 8 '. 3 ' 1 e. r g,p. respectively) System Pressure. Test Boundary.' ] ,. < m ,.q, ! Drawings are in course or preparation, j s. They/will be added by revision when~ i .; j b completed. g J I t / \\.l 1 l ') k" .]i I 4 j. l .'l i s ',1
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NQ 'r r r r e P P P P oog EE NN a-mR e-e- e-e - t f p p p p ~- ' n 0L ~ t t t t P J J. - J J no CA m s C ei ei ei ' sx ei I s x s x sx ei t i E td td td td a cv P n n n n oe S k e k e k e k e a p a p a p a p DR E ep ep ep ep r LA LA LA LA m S " e FT tt ES I E ns - LU a y4 l S4 EQ P 9 RE rn2 - R - g6 oi-tl2 c p1 am2 ) ) ) ) ) ) ) ea5 2 2 2 2 2 2 .D 2 R S.2 RO O 2h 2 'h 2h 3h 5h 3h 5h m g C - S - S - S - S - S - S - S e n E( F{ F( F( F( D( D( t i s w y a S r D { D EG RN SrTI STTI STTI T StTI SfTIT STTIr II UT STTI QS FMFP Ff FP FMFP FMFPL FMFP Ff FPL FNEPt f f EE RT ~ D TO ~ SI Q I Q I Q I Q I Q I Q I Q I 3 ' ER B B B B B B B TG TE I N .P n NI UTS TEM NTA I R R OEG NO EOT .PCO I R TI A s s s s s s s EVP OTC e e e e e e e NR MI I Y Y Y Y Y Y Y OE ESD TS RON SN PJ LI L I M ERE UD LO C C C C C C C I M F F F F F F F AF N N O/O / / / ! LI d d d d d d d TAT e e e /e /e / e /e I MC s n s n s n ns ns ns ns SRN oe oe oe eo eo eo eo l p l p l p pl pl pl pl OOU PNF CO CO CO OC OC OC OC NO d d d d d d d I i i i i i i i T o o o o o o o A n n n n n n n U e e e e e e e T l l l l l l l C o o o o o o o A S S S S S S S E Y A A A A A A A. P T G G G G G G G TS GS TA 2 2 2 2 2 2 2 EAI B B B A A A A ZCC 8 8 8 4 4 4 4 I / / / / / / / SEE 3 3 3 3 3 3 3 DD OO CC 0 l 2 3 4 9 0 R 1 l 1 1 1 l 2 WE VB VC VD V V V V LB - 8 - 8 - 8 - 9 - 0 - 2 - 3 N SV SV SV SV SV SV SV AM R2 R2 R2 R2 R3 R3 R3 VL S - S - S - S - S - S - S - O O O T T T T 3S 3S 3S 3C 3C 3C 3C ~ i
Q P oog EE r r NN a MR e-e - P M p p t n OL J J no CA t t ei I s x s x ms C ei ei ui E td t d cv P n n oe S k e k e DR a p a p ep ep LA LA m S e FT tt ES ns I E a y4 LU l S4 EQ P 9 RE g6 R rn2 oi - tl 2 c p1 a m2 ea5 ) ) ) ) ) ) ) RS2 D 2 2 1 1 1 1 2 RO O 3h 5h 2h 2h. 2h 2h 2h
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- S - S - S - S - S - S S me n B( B( J( H( F( D( I ( t i s w y a S r D D EG RN I I UT STTI T STTI T STTI SrTI STTI STTI SrTI f f QS FMFPL FMFPL FHFP FP FP FMFP FMIP Ft FP EE RT D TO 3 SI Q I Q I Q I Q I Q I Q I Q I ER B B B D B B B TG TE I N P NI UTS TEM NTA I R R OEG NO PCO EGT I R TI A s s s s s s s EVP OTC e e e e e e e NR MI I Y Y Y Y Y Y Y OE ESD TS RON SN PI LI L I M ERE UD LO C C C C C C C I M F F F F F F F AF N N O/O / I LI d d d d d d d TAC /e /e /e /e / e /e e I M ns ns ns ns ns ns s n SRN eo e o e o eo e o e o oe OOU pl pl pl pl pl pl l p PNF OC OC OC OC OC OC CO NO d d d d d d d I i i i i i i i T o o o o o o o A 1 n n n n n n n 1 e e e e e e e 1 l l l l l l l C o o o o o o o A S S S S S S S EP Y A A. A. A A A A T G G G G G C G YS CS TA 2 2 2 2 2 2 2 EAL A A B B B B B ZCC 4 4 4 4 4 4 8 I / / / / / / / SEE 3 3 3 3 3 3 3 DD OO CC 8 1 2 4 6 8 0 7 ER 2 2 2 2 2 3 9 VE V6 V5 VD VC VB VA V1 LB - 2 - 2 - 9 - 9 - 9 - 9 7 AM R0 R 0 R1 R1 R1 R 1 R1 VU S8 S 8 S - S - S - S - S - N S - S - SV SV SV SV SV V - V - T - T - T - O I 3C 3C 3C 3C 3C 3C 3S
TU i. e NQ J og EE ~ NN a MR P M t n OL no CA ei I ms C ui E cv P oe S D. R 4 S FT t ES us I E t n4 LU ii4 EQ Pa9 RE r6 R eD2 n i 2 b c1 rs2 ui5 ) ) ) ) ) ) ) ) TM2 D 1 1 1 1 1 1 1 1 R O O 4h 5h 2h 3h 2h 3h 2h. 3h m
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- S - S - S - S - S - S - S - S e n J( J( A( A( A( A( A( A( t i s w y a S r ,D D EG RN I I UT STTI STTI STTI STTI STTI STTI STTI STT QS FMFP FMI P FMEP FMFP FNFP FMFP FMIP FMF E T. RT D TO 3 SI Q I Q I Q I Q I Q I Q I Q I Q ER B B B B B B B TG TE I N P NI UT - S TEM NTA I R R OEG NO PCO EOT I R TI A s s s s s s s s EVP OTC e e e e e e e e NR MI I Y Y Y Y Y Y Y Y OE ESD TS RON SN PI lI I I M ERE UD LO C C C C C C C C I M F F F F F F F F AF N N O/O I LI d d d d d d d d TAT /e / e /e /e /e / e / e /e I MC ns ns ns ns ns ns ns ns SRN eo eo e o e o e o eo eo eo OOU pl pl pl pl pl pl pl pl PNF OC OC OC OC OC OC OC OC NO I T r r r r r r r r A i i i i i i i i U A A A A A A A A TC A E A A. A A A A A PY A T G G G G G G G G YS GS TA EAI 2 2 2 2 2 2 2 2 ZCC B B B B B B B B I I I 3 3 3 3 3 3 SEEDD OO CC 0 1 7 8 4 5 1 2 ER 7 7 7 7 8 8 9 9 E VA VA VA VA VB VB VC VC V. B I - 3 - 4 - 9 - 9 1 - 9 1 AM M6 M6 M2 M6 M2 M6 M2 M6 VU T - T - T - T - T - T - T - T - N DV DV DV DV DV DV DV DV - O - 0 - 0 - O - O - D - O - O 3A 3A 3A 3A 3A 3A 3A 3 A
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M. Q T oog EE r p r rp r NN a t R 1 e( e - e( e - s P t 1 p p p p t n 0L 5 J J J J no CA 3 t t t t ei I s x s x s x s x W ms C ei6 ei ei ei ui E td5 td td6 td cv P I n n n5 n oe S k e. k e k e - k e DR r a pn a p a pn a p e epe ep epe ep P LAP LA LAP LA n S o FT i ES t I E c 6 LU e 4 EQ t 9 RE s 6 R r 2 P m-e2 et1 r s2 i y5 ) ) ) ) FS2 D 2 2 2 2 R O 3 4h 4h 4h. 4h. O m g C - S - S - S - S e n B C( C( B( B( t i s w y a S r D D EG RN I I V UT R T STTI T T STTI T QS S L FMFPL L FMI PL EE RT D TO 3 SI I Q I I Q I ER B B B B TG TE I N P NI UTS i EM hTA I R R OEG NO PCO EOT I R TI A EVP OTC NR MI I OE ESD TS RON SN PI LI L I M ERE UD LO C C I M F F AF N N O/O / / / I LI d ddd d ddd d TAT e e e e /e ee e / e i I ! C s n k s s ns k s s ns SRN oe c oo e o c oo eo OOU l p ol l pl ol l pl PNF CO LCC OC LCC OC NO I l l T a r a r A u i u i U n A n A C M ia T a r A P L L Y E Y L Y E L E L F T R G B G B YS GS TA 2 EAL C 2 2 2 2 ZCC 4 A A A A I / 6 6 6 6 SEE 3 DD OO CC 2 1 3 6 8 4 6 6 6 6 ER 6 6 6 6 6 VE V V V V V LB - 9 - 8 AM W7 W W4 W W4 Vt P8 P P - P P - h F - F FV F FV - V - T - T 3R 3 3C 3 3C
NQ .e oog EE NN a MR P M t n OL no CA ei I ms C ui E cv P oe S DR n S g i FT d ES l ~ IE i 1 LU u 5 EQ B 9 RE 6 R l 2 o r 2 tC1 nA2 oV5 ) ) ) ) ) ) ) ) CH2 D 1 1 1 1 2 2 2 2 R O O 4h 3h 4h 5h 2h. 2h 2h. 2h m g C - S S S - S - S - S - S S e n H( H( A( A( M( M( M( M( t i s w y a S r D D EG RN I I UT STrI STTI STTI STII STTI STTI STTI STT QS FMTP FMFP FMFP FNFP FMFP FMFP FMFP FN EE RT D TO 3 SI Q I Q I Q I Q I Q 1 Q I Q I Q ER B B B B B B B TG TE I N P NI UT S T7M N1A I R R OEG NO PCO EOT ~- I R TI A s s s s s s s s EVP OTC e e e e e e e e NR MI I Y Y Y Y Y Y Y Y OE ESD TS RON SN PI LI L I M E - RE UD LO O O C C C C C C I M F F F F F F F F AF N N O/O / / I LI d d d d d d d d TAT e e / e / e / e / e / e I MC s n s n ns ns ns ns ns /ens SRN oe oe eo ec eo eo eo eo OO! l p l p pl pi pl pl pl pl PNR CO CO OC OC OC OC OC OC NO d d I i i T o o r r r r r r A n n i i i i i i U e e A A A A A A T l l C o o A S S E Y Y Y Y Y Y P L L L L L L Y A A F F F E F F T G G B B B B B B YS GS TA 3 3 EAL B B 3 3 3 3 3 3 ZCC 5 5 B B B B B B SEE 1 1 1 1 1 6 0 0 I 6 6 6 1 1 1 DD OO CC 6 7 0 1 2 3 4 5 ER 2 2 7 7 7 7 7 7 VE VB VA V V V V V V LB - 4 - 4 - 5 - 6 - 2 - 3 - 0 1 AM C7 C7 C2 C2 C2 C2 C2 C2 VU V - V - V - V - V - V - V - V - N HV HV HV HV HV HV HV HV O O - D - G - O D - O - 0 3S 3S 3A 3A 3 A 3 A 3A 3A Il
oog EE r r r r rl r rl NN a HR e - e - e-e- e( e - e( P N p p p p p p p 't n. CA t t t t t t t OL J J J J J J J no ei I s x s x s x s x s x1 s x s x ms C ei ei ei ei ei2 eie ei7 e ui E t d td td td td1 t d v td3 v cv P n n n n n ni n .i oe S k e k e k e k e k e. k es k e s DR ap ap a p a p a pn a ps a pns ep ep ep ep epe e pa epe a LA LA LA LA LAP LAP LAPP n aucn S ao FT Vi ES t I E t a3 LU nl5 EQ ei9 RE mt6 R nn2 i e - aV2 ~t 1 nd2 on5 C a2 DRO O 3 3 5 5 4 2 2 g C me n F D F E E G F t i s w y a S r D D EG RN I I UT STTI T STTI T STTI T STTI T T T T QS FMFPL FMIPL FMFPL FHFPL L L L EE RT D TO 3 SI Q I Q I Q I Q I I I I ER B B B B B B B TG TE I N P NI UTS TEM NTA I R R OEG NO PCO EOT I R TI A s s s s EVP OTC e e e e NR MI I Y Y Y Y OE ESD TS RON t SN PI LI L I ERE UD LO C C C C I H F F F F AF n n n n e e e e p p p p N N O O O O O/O r/- r/- r/- r/- / / / I LI odd odd odd odd dd dd ddd TAT ee e e ee ee ee ee ee e I MC ns s ns s ns s ns s s s s s k s s SRN e oo eoo eo o eoo o o oo c oo OOU pl l pl l pl l pl l l l l l ol l PNF OCC OCC OCC OCC CC CC LCC N O I l l T r r r r a r a A i i i i u i u U A A A A n A n T a a C M M A E Y P A A A A A L Y I I I I I F A. T D D D D D B G YS GS TA EAL 2 2 2 2 2 2 2 ZCC A A A A A A A I 2 2 2 2 2 8 8 SEE DD OO CC 3 9 0 ER 2 3 6 7 1 l 2 VE VA VA VB VB V V V LB - 0 1 - 0 1 - 3 AM S2 S2 S2 S2 S S 2 S VU V - V - V - V - V V - V ~ N CV CV CV CV C CV C - T - 1 - T T - O 3C 3C 3C 3C 3 3A 3
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