ML19337A800
| ML19337A800 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/30/1980 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML19337A798 | List: |
| References | |
| PROC-800930, NUDOCS 8009300245 | |
| Download: ML19337A800 (70) | |
Text
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Attachment G
Docket 50-245 b
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MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1 INSERVICE INSPECTION AND TESTING PROGRAM
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For the Ten-Year Interval From December 28, 1980 to December 2'8, 1990 i
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ASME CODE CIASS 1 COMpONFNTS Table-ASME Section XI IWB-2500-1 Examination Component or Area Compliance Item No.
Category to-Be Examined Method Reactor Vessel Bl.10 B-A Longitudinal and circumferentla?. hell welds Volumetric No (Note 1)
Bl.20 B-A Meridional and circumferential head welds
-Volumetric In compliance Volumetric
Head to flange weld B3.10 B-D Nozzle to vessel welds and nozzle inside Volumetric In compliance radiused section 84.10 B-E Vessel penetrations, including control rod Visual In compliance drive and instrumentation penetrations 55.10 B-F Nozzle to safe end welds Voltanetric and surface In compliance Surface In compliance 86.10 5-C-1 Closure head nuts Volumetric In compliance B6.20 B-G-1 Closure stude, in place Volumetric and surface In compliance 86.30 5-C-1 Closure studs, removed Volumetric In compliance B6.40 5-G-1 Ligaments between stud holes Visual in compliance B6.50 B-G-1 Closure washers, bushings Visual In compliance 87.10 B-G-2 Bolts, st us, and nuts Surface in compliance 58.10 IL-H Vessel support Visual In compliance I
B13.10 B-N-1 Vessel interior Visual In compliance 7
B13.20 B-N-2 Interior attachments and core support struc-tures B14.10 B-0 Welds in CRD housings Volumetric or surface Exempt under IWB-1220(a)
B15.10 B-P Pressure retaining boundary System leakage test in compliance System hydro in compliance Pipina Pressure _ Boundary 85.50 B-F Pressure retaining dissimilar metal welds Volumetric and surface in compliance 86.15 B-G-1 Bolts and studs, in place Not appItcable Note 2 B7.50 B-G-2 Bolts. studs, and nuts Not applicable Note 2 84.5 (S75)
B-J Circumferential and longitudinal pipe welds Volumetric In compliance 84.6 (S75)
B-J Branch pipe connection welds exceeding 6" Volumetric In compliance in diameter Surface In compliance 84.7 (S75)
B-J Branch pipe connection welds 6" in diameter and smaller Surface in compliance B4.8 (575)
B-J Socket welds Volumetric or surface In compliance B10.10 5-K-1 Welded support members Visual in compliance Bil.le B-K-2 Component supports Visual In compliance BE.30 B-P System leakage test Visual In compliance o15.51 B-P System hydrostatic test Pumys 86.180 B-G-1 Pump bolting, larger than 2",
in place Volumetric In compliance B6.190 B-G-1 Pump bolting, larger than 2", removed Volumetric and surface In compliance
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.. e INSERVICE INSPECTf_0*QRfV3E(WB-2412J ASME CODE CLASS 1 FApONFNTS Table IWB-2500-1 Examination Component or Area ASME Section XI Item No.
Category to Be Examined Method Cnmpliance Pumps B6.200 B-G-l' Bolting Visual In compliance 87.60 B-G-2 Bolts, studs, and nuts, 2" and smaller Visual In cogliance B10.20 B-K-1 Pump supports Volumetric or surface in to yllance
-B11.20 B-K-2 Pump supports visual In compliance 512.10' B-L Pump casing welds Not applicable Note 7 B12.20>
,B-L-2 Pump casing Visual No (Note 3) 815.60 B-P System leakage test Visual In compliance B15.61 B-P System hydrostatic test Visual in compliance Valve Pressure Boundary 86.210 B-G-1 Bolts and studs, in place Not applicable Note 2 B7.70 B-G-2 Bolts, studs, and nuts Visual In compliance B10.30 B-K-1 Welded attachments, valves Volumetric or surface In, compliance 511.30 B-K-2 Support components Visual.
I.a compliance B12.10 5-M-1 Pressure retaining welds Not appilcable
. Note 2
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B12.20 B-N-2 Internal boundary surfaces Visual No (Note 4) 515.70 B-P System leakage test Visual in compliance B15.71 B-P System hydrostatic test Visual In compliance i
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NOTES - CLASS 1 PROGRAM NOTE 1 The reactor vessel is insulated with permanent reficctive insulation and surrounded by the concrete biological shield. The annular space between the inside diameter of the biological shield and the outside diameter of the insulation is a nominal 6 L 0 inches. Thus, access for removal of the insulation pancis is extremely limited, and this inaccessibility precludes direct examination of the belt-line region welds from the outside surface. The interior surface of the reactor vessel is stainless A
stael clad, and the vessel's internals, shroud, and jet pumps would make an internal volumecric examination of the belt-line region welds impractical.
NNECO will examine:
(a) volumetrically all of the accessible length of each longi-tudiosi weld and all of the accessible length of each circumferential weld, from either inside or outside the vessel, (b) visually, to the extent practical, and from the vessel inside surface, the areas of welds required to be examined, and (c) in the event that a code unacceptance flaw is detected, a volumetric examination shall be performed on the welds listed, per code. This complies with Amendment 64 to, Provisional Operating License No. DPR-21.
Please see Figure IWB attached.
NOTE 2 No components of this category.
NOTE 3 NNECO plans to postpone the B-L-2 (visual) examination of the recirculation pump until major maintenance needs to be performed on the pump. Visual examination of the casing exterior during operational leak tests has shown no signs of degradation.
Based upon BWR service to date, cast stainless steel pump and valve bodies have been acceptable with no degradation noted. Our vibration monitoring program is used to assess the mechanical condition of the pump and is sufficiently sensitive to detect any major internal pump changes. Disassembly and inspection of a re-circulation pump would result in exposures in excess of 100 man-rems, and NNECO does not believe the incremental increase in the assurance of pump casing integrity by disassembly warrants the exposure. Wall thickness measurement is not practical for this pump.
As an alternate examination, NNECO will continue to perform visual inspections of both pump casing exteriors during periodic leak tests or hydrostatic tests during each refueling outage.
If any through-wall crack developed, the drywell leak detection system would provide an alarm at an early stage when leakage first occurs. The Millstone Unit No. 1 technical specifications limit unidentified Icakage inside containment to 2.5 GPM.
NOTE 4 This category is in compliance with code; however, relief must be requested for certain valves which require lowering or draining of water in the reactor vessel and/or installation of a suitable plug.
See Table B-M-2 for a listing of these valves.
(Cont'd.)
_3-
NOTE 4 (Cont'd.)
These valves are subjected to the system Icakage and hydrostatic. tests required by IWB-5221 and IWB-5222. Other valves in lines which penetrate the reactor pressure vessel experience similar thermal-hydraulic conditions. These valves were manufac-tured from the same materials as the valves listed in Table B-M-2 and will be in-epected internally during this inspection interval.
In addition, NNECO will inspect the internal surfaces of the valves listed if unacceptable conditions exist in those valves inspected or when drainage of the reactor vessel is necessary for other purposes.
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TABLE B-M-2 VALVES REQUIRING CORE REMOVAL FOR EXAMINATION Valve Valve System Description Number 6
Feedwater 18" Stop 1-FW-11A 18" Stop 1-FW-11B LPCI 18" Stop 1-LP-12B Shutdcwn Cooling 14" M0 Stop*
1-SD-1 Isolation Condenser 14" M0 Stop*
l-IC-1 10" M0 Stop*
l-IC-4 Core Spray 10" Stop 1-CS-7A 10" Stop 1-CS-7B Cleanup Water 8" Stop 1-CU-l 8" Stop 1-CU-30 8" M0 Stop*
1-CU-3 f
Recirculation 28" M0 Stop*
l-RR-1A 1-RR-2A 1-RR-1B l-RR-2B 22" M0 Stop 1-RR-4A (Tech. Specs. 3.6 H.3 1-RR-4B prohibits use) l l
- 0perational readiness tested in accordance with IWV. All other valves shown on this table are maintenance valves and are exempt from inservice testing per IWV-1300.
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ASME CODE CLASS 2 COMPO!!ENTS Table ASME Section XI IWC-2500-1
. Examination Component or Area
. Item No.
Category to Be Examined Method Compliance C1.10 C-A Shell circumferential welds Not applicable Note 1 C1.20 C-A Head circumferential welds Not applicable Note 1 C1.30
.C-A Tube sheet to shell weld
%1umetric No (Note 2)
C2.10 C-B Nozzle. welds in vessels - " and less - LPCI Surface in compliance HX C2.20..
C-5 Nozzle welds in vessels - over Volumetric and surface No (Note 3)
C3.10-C-C Integrally welded supports - LPCI HX Surface in compliance C 3. 20.
C-C Component supports Visual In compliance C3.40 C-E Integrally welded piping supports - base Not applicable Note 1 material exceeding 3/4" C3.50' C-E Piping component supports Visual in compliance C3.60 C-E Supports - mechanical and hydraulic Visual in compliance C3.70 C-E.
Integrally welded pump supports Not applicable Note 1 C3.80 C-E Component supports - bolting Visual In compliance C3.100 C-E Integrally welded valve supports Not applicable Note 1 C3.110 C-E Component supports visual in compliance C4.1.2.3.4 C-D Pressure retaining bolting, exceeding 2",
in Not applicable Note 1 vessels, piping, pumps, and valves Circumferential butt welds Volumetric in compliance C2.1 (S75)
C-F. C-C y
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C-r,0-C Longitudinal weld joints in fittings Volumetric No (Note 4)
C2.3 (575)
C-F.C-G Branch pipe-to-pipe veld joints Volumentric in compliance C6.10 C-C Pump casing welds Not applicable Note 1.
C6.20 C-C Valve casing welds Not applicable Note 1 C-H All pressure retaining components Visual In compliance i
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NOTES - CLASS 2 SECTION NOTE 1 There are no components of this category.
NOTE.2 The geometry of the circumferential tube sheet to shell weld on the LPCI heat ex-i changer is such that volumetric examination of this weld, utilizing either ultra-sonic or radiograph techniques, cannot be performed to produce meaningful results.
NNECO will perform a surface examination of at least 20 percent of this weld in the. proximity of the nozzles. Please see sketch, Figure C-A.
t NOTE 3 The isolation condenser nozzle to vessel welds are covered by encapsulation sleeves which were installed as a result of the high energy pipe break study. NNECO will
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perform surface examinations on these welds from the nozzle interior in conjunction with scheduled eddy-current examinations of isolation condenser tubing. Eddy-current examination of the tubes is performed every second refueling outage, and a primary I
side pressure test is performed at refueling outages.
Picase see sketch, Figure C-B.
The shutdown heat exchanger nozzle to vessel weld is similar to a branch pipe weld (See Figure IWB-2500-10). A volumetric examination ~of this weld, utilizing either ultranonic or radiograph techniques, cannot be performed to produce meaningful results. NNECO will perform a surface examination of this weld. Please see sketch, Figure C-C.
NOTE 4 Examinaticus in this category are in compliance for the most part; however, certain welds in the isolation condenser system are covered by high energy pipe break encapsulation sleeves which prevent access. The isolation condenser system re-ceives a pressure test at reactor refuelings under an augmented inspection program.
The areas adjacent to welds will be visually checked for leakage at that time.
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INSERVICE INSPECTION PROGRAM ASME SECTION 'III CLASS 3 COMPONENTS a
Class 3 components will be tested and examined in accordance with IWA-5000, IWD-5000, and IWD-2600, as modified in Tabic BCD-5000 " System Pressure Tests,"
by the expir~ation of each inspection interval.
Supports and hangers for components exceeding four-inch nominal pipe size, whose structural integrity is relied upon to withstand design loads when the system function is required, shall be visually examined to detect any loss of support capability and evidence of inadequate restraint.
The Class 3 components are in compliance with ASME Section XI with exceptions i
as noted in Table BCD-5,000 (System Pressure Tests),
i In addition, 100 percent of the components shall have been examined in ac-cordance with IWA-5240 and IWD-2600 while in operation or during system inservice testing by' the expiration of every one-third of each inspection in te rval.
Class 3 component pressure cests are listed under the section on. pressure tests, Table BCD-5000.
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a PUMP INSERVICE TESTING SCOPE This program-lists those pumps that are required to perform a specific function in shutting down a reactor or in mitigating the consequences of an accident and are provided with an emergency power source.
o All tests and examination procedures required by Subsection IWP, int.uding sched-ules, reference values, the location and type of measurement for each of the required test quantities, records of the results, and all corrective action taken, shall be defined and performed by NNECO for M111 stone Unit No.1.
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TABLE IWP OPERATIONAL READINESS TESTINC FOR P* h t
en se MOTOR INLET DIFFERENTIAL VIBRATION BEARING FLUID
. TEST PUMP CURRENT RPM PRESSURE PRESSURE FIDW SIGNATURE LUBRICATION TD4PERATURE TEMPERATURE FREQUENCY M8-75A X
3570 X
X X
X X
X Monthly
.LPCI M8-755 ~
X 3570 X
X X
X X
X Monthly M8-75C X
3570 X
X X
X X
X Monthly MS-75D I
3570 X
X X
X X
X Monthly
'M8-74A
.X 3560 X
X X
X X
X Monthly Core Spray M8-748 X
3560 X
X X
X X
X Monthly Rtactor Feed (WCI)
M2-10A X
3580 X
X X
X X
X X
Monthly M2-108 X
3580 X
X X
X X-X X
See Note 4
@ M2-10C X
3580 X
X X
X X
X X
Condensate Booster (WCI)
M2-7A X
1780 X
X Note 3 X !;;
X X H X H Monthly h
0 Monthly X
M2-78 X
1780 X
X Note 3 X b X
X x$m Monthly i
O M2-7C x
1780 K
x Note 3 X a x
xg a
x w
~g b
b b
a Condensate (FWCI)
Monthly H
X -
M2-6A X
1185 K
X Note 3 X3 X
h Monthly h
X M2-6B X
1185 K
X Note 3 X b X
@ M2-6C X
1185 K
X Note 3 X
X g'
X Monthly g
g 8
8 8
a u
Emergency Condensate Transfer X
Monthly M7-28 X
1780 X
X X
X X
w w
w 5
{
Z
"'-'^
Service Water Pt>
Monthly m
X m M4-7B X
1180 Sea Level Note 5 Note 3 X m X
M4-7C X
1180 Sea Level Note 5 Note 3 X
X X
Monthly M4-7D X
1180 Sea Level Note 5 Note 3 X
X X
Monthly M4-13A X
1770 Sea Level Note 5 X
X X
X Monthly Emergency Service Water M4-13B X
1770 Sea Level Note 5 K
X X
X Monthly M4-13C X
1770 Sea Level Note 5 X
X X
X Monthly M4-13D X
1770 Sea Level Note 5 X
X X
X Monthly Standby Liquid Control 420 Tank Level Note 5 X
X X
X Monthly 420 Tank Level Note 5 I
X X
X Monthly 1102A 1102B M4-10A X
1775 X
X Note 3 X
X X
X Monthly Reactor Building CCW M4-10B X
1775 X
X Note 3 X
X X
X Monthly i
continued...
-,~
e 8
e TABLE IWP OPERATIONAL READINESS TESTING FOR PLHPS MOTOR-INLET DIFFERENTIAL VIBRATION BEARING FLUID TFST PUMP CURRENT RPM PRESSURE PRESSURE FLOW SIGNATURE LUBRICATION TEMPERATURE TEMPERATURE FREQUENCY Secondary CCW M4-15A 1775 X
X Note 3 X
X X
X' Monthly 1775 K
X Note 3 X
X X
X Nnthly M4-158 e
s 9-0 0
0 Reactor Shutdown Cooling g
X' S ColdShutdownh 1002A 1770 X
X Note 3 X S X,
X 10028 1770 X
X Note 3 X $
X X a:
X $
See Note 6
)
s,.
s.
s d
d d
Control Rod Drive 302-3A X
4210 X
X X
X d X
X d X d Monthly
[
[
See Note 7 )
[
[
X X
X
,302-38 X
4210 X
X X
X o
o g
Fuel Pool Cooling
~
M4-11A 3550 X
X X
X X
X
'X Monthly y
Monthly h
y-X X
X M4-11B 3550 X
X X
X
=
z z
w sa na Feed Pump Seal Water M2-17A 1745 X
X Note 3 X d X
X d X d
. Monthly M2-178 1745 X
X Note 3 X
X X
X Monthly b,
6 M2-17C 1745 K
X Nota 3 X
X X
X Monthly Y
X = Indicates parameters to be measured or observed.
- = 480 volt power supply. Motor amaneter not installed.
- = All pumps are constant speed (induction motor driven).
O - rumps are not safety related. Shown for inforination only.
In most cases, differential pressure will be obtained by noting the inlet pressure or tank or source water level and discharge piessure.
i
)
NOTES - TABLE IWP NOTE 1 - Vibration Analysis Relief Request Components All pumps shown on Table IWP.
Test Requirement Measure at least one displacement vibration amplitude during each inservice test.
Basis for Relief and Alternate Testing To meet the vibration monitoring requirements of ASME Section XI, Subsection IWP, exception is taken to the specific vibration requirements of IWP and an alternate, more effective vibration signature analysis program, as described herein, is proposed. During the inservice pump test, vibration data shall be acquired in the form of a " vibration signature" rather than a simple reading of overall vibration amplitude.
The vibration signature shall consist of a plot of vibration amplitude in units of inches per second peak velocity, versus frequency in cycles per second, typically over a frequency range of 0 to 500 cycles per second. The vib, ration signature analysis approach provides a more reliable means of detecting a deterioration of pump mechanical condition, a determination of the cause of the problem, and a more accurate assessment of viFration severity. The periodically acquired vibration signatures shall be compared to a baseline reference signature and analyzed for changes in amplitude peaks exceeding a threshold value. Criteria for evaluation of changes as to cause, severity, and the establishment of the alert and required action ranges shall be specified in the NNECO procedures.
Vibration measurements are made typically with an accelerometer mounted at a reference location on the equipment bearing housing, and the data is processed by a spectrum analyzer'to produce a'hard copy vibration signature. The vibra-tion sensors can also be interfaced directly with the spectrum analyzer.
The measurement locations to be used for monthly and baseline vibration signa-ture data shall be established and specified by NNECO procedures, h
NOTE 2 - Bearing Temperature Relief Request Components All pumps shown on Table IWP.
(Cont'd.),
NOTE 2 (Cont'd.)
Test Requirement Measure annually the temperature of centrifugal pump bearings and main shaf t bearings of reciprocating pumps at points selected to be responsive to changes in temperature of the bearing.
Basis for Relief Bearing metal temperature monitoring can be effective in detecting bearing problems. However, only six of the tabulated pumps (three feedwater and three condensate booster) have the permanently installed temperature sensors required to measure bearing metal temperature; i.e., outer race of anti-friction bearing or babbitt lining of sleeve bearing. The annual measurement of bearing housing temperature is far less effective in detecting bearing problems than the monthly performance of vibration signature analysis being performed by NNECO. The re-maining pumps listed in Table IWP do not have adequate design provisions to allow meaningful bearing temperatures to be taken:
Low pressure coolant injection, core spray, cc cansate, service water, and e
emergency service water pumps are vertical desa,n pumps with bearings lo-cated in the motor driver and pump casing. The bearings are inaccessible for temperature measurements. Please refer to the Safety Evaluation at-tached to Amendment 64 of POL No. DPR-21.
Standby liquid control pump bearings are mounted in a massive oil-filled
)
e reservoir which is in direct contact with the pumped fluid.
Thus, measure-ment of housing temperature is not indicative of bearing condition, i
RBCCW, reactor shutdown cooling, secondary CCW, fuel pool cooling, feed e
pump seal water, and CRD pumps have recessed bearings and housing tempera-ture measurements are possible but of questionable value, The emergency condensate transfer pump bearing tem'perature cannot be con-
)
e sidered meaningful since the pump hydraulic circuit (condensate storage j
tank to condenser hotwell - no recirculation path) allows only about five minutes of operation before the hotwells are filled. This short run time does not allow the bearing temperature to stabilize.
Service water and emergency service water pump bearings are underwater and e
. inaccessible.
In general, as internal bearing metal temperatures increase due to bearing over-load, improper lubrication, or faulty installation, etc., much of the heat will bc 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 heat-up problems.
-Another important requirement to assure reliable bearing temperature monitoring is that it be continuous, not periodic.
Experience indicates that failing (Cont'd.)
4 NOTE 2 Basis for Relief (Ccnt'd.)
bearings, whether anti-friction type or sleeve, often exhibit fluctuations between normal and abnormal metal temperatures. A good example is the babbitt lined sleeve bearing which will initially experience a rapid rise in temparature 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 undetected unless continuously monitored.
The monthly vibration signature analysis conducted by NNECO will detect bearing problems at a very early stage. 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 monitoring program conforming to IWP minimum requirements. However, the low level changes in bearing distress frequencies are routinely detected in the Millstone signature analysis program and analyzed to pinpoint the cause.
Alternate Testing,
Record and analyze pumpsvibration signature monthly. Signature will be measured as velocity spectrum betwegn 0 and 500 hertz. This monthly analysis will provide more meaningful analysis of' pump bearing condition than annual measurement of bearing temperature.
NOTE 3 - Flow
.surement Relief Request i
Components Condensate, condensate booster, RBCCW, secondary CCW, reactor feed seal water pumps, nervice water, and reactor shutdown cooling pumps.
Test Requirement Measure individual pump flow rates during periodic testing.
Basis for Relief Individual pump flow measurement instrumentation does not exist in the hydraulic circuits for these pumps. Pump differential pressure, motor current (except as noted on the table), and/or system flow rate can be used to measure each pump's 6
performance, providing that an established set of reference conditions are utilized for each test.
Please refer to the Safety Evaluation attached to Amendment 64 of POL No. DPR-21.
Alternate Testing Reference conditions for these pumps will be established using installed instru-mentation as shown in Table IWP.
(Cont'd.) -
NOTE 4 - Test Frequency Relief Request Component Reactor Feed Pump.
Test Requirement An inservice test shall be run on each pump, nominally each month during normal plant operation.
Basis for Relief Two of the three reactor feed pumps are running during norcal plant operation and are rotated every three months to equalize wear.
Several years of operating experience on the feed pumps have established this rotation schedule as being the most ef fective in terms of equipment reliability, operational readiness, and reduction of potential plant flow transients which might be brought about by continuous pump switching.
Alternate Testing Perform inservice testing of the reactor feed pumps for those pumps running on a monthly basis.
NOTE 5 - Dif ferential Pressure Relief Request Component Service water, emergency service water, and standby liquid control pumps.
Test Requirement Measure pump differential pressure during periodic testing.
Basis for Relief The service water and emergency service water pumps take suction directly from 4
Niantic Bay and are not instrumented for suction pressure, as the inlet pressure difference, caused by tidal swing, would be inconsequential in regard to pump performance.
The standby liquid control pump is a positive displacement pump, so differential pressure measurement would be meaningless.
Alternate Testing Measure pump discharge pressure and sea level for the service water pumps.
(Cont ' d. )
1" NOTE 5 Alternate Testing (Cont'd.)
For the SBLC pumps, the discharge pressure is throttled to a constant value during the pump capacity test. Pump flow and discharge pressure will be measured to ensure acceptable pump performance.
NOTE 6 - Test Frequency Relief Request Component Reactor shutdown cooling pumps.
Basis for Relief Shutdown cooling system design does not provide for pump testing unless the reactor is in a cold shutdown mode and the system is being used to remove
. residual heat (there is no test loop).
Alternate Testing Reactor shutdown cooling pumps will be tested monthly while in operation during shutdowns. Please refer to the Safety Evaluation attached to Amendment 64 of POL No. DPR-21.
NOTE 7 - 1est Frequency Relief Request Component Control rod drive hydraulic pump.
Basis for Relief One control rod drive pump is in service during normal power operation. The pumps are rotated when pump suction filters require changing (approximately three months). Observation of these pumps has shown that frequent starts and stops of these high speed, high pressure pumps have led to pump deterioration.
Alternate Testing The operating CRD pump will be tested monthly.
NOTE 8 - Pumped Fluid Temperature Measurement Relief Request Component All pumps shown on Table IWP.
(Cont'd.) -
NorE 8 (Cont'd.)
Basis for Relief j.
Pumped fluid temperature measurement is not a meaningful parameter to measure for this series.of operational readiness tests. This was recognized by ASME Section XI in code addenda subsequent to the Summer, 1978 addenda when this requirement was deleted.
e Alternate Testing
)
None.
i I
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VALVE INSERVICE TESTING SCOPE e
This section provides a listing of all Class 1, 2, and 3 valves required to be exercised and tested to verify operational readiness. These valves (with their actuating and position indicating devices) are required to perform a special function in bringing a reactor to cold shutdown condition or in mitigating the consequences of an accident.
When it is not practical to exercise valves to the position required to fulfill their function or to the partial position during power operation, a relief re-quest is included for exercising at cold shutdowns.
Inservice valve testing at cold shutdowns will commence not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after cold shutdown condi-tion is achieved and will continue as time permits and on subsequent shutdowns without repeating valve exercising and tests until the entire list is complete.
Such. exercising and testing is not required more of ten than every three months.
All exercising and testing procedures required by Article IWV, including sched-ules and the limiting values of observed parameters, shall be defined and per-formed by NNECO.
September, 1980 1
DBG-c102 TABLE IW-1 MILLSTONE UNIT NO. 1 September 1980
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zm Feedwater Coolant Injection 25202-26032 Sh. 2 1-FCX-1 2C Relief Valve 3
REL SRV l-FCX-4 2C Pump Discharge Check 14 CK C
CV 1-FCX-5 2B Pump Discharge Isolation Valve 14 GA MO C
Q MT 90 Sec. to Open PI 1-CN-2A 2C Condensate Pump 1A Disch. Check 20 CK O
CV X
CS g
Y l-CN-2B 2C Condensate Pump 1B Disch. Check 20 CK 0
CV X
CS 1-CN-2C 2C Condensate Pump IC Disch. Check.
20 CK 0
CV X
CS 1-CN-58 2B SJAE Minimum Flow FCV-2-4 16 GL A0 C
Q X
CS 1-CN-30A 2C Cond. Booster Pump A Disch. Check 20 CK 0
CV X
CS 1-CN-30B 2C Cond. Booster Pump B Disch. Check 20 CK 0
CV X
CS 1-CN-30C 2C Cond. Booster Pump D Disch. Check 20 CK 0
CV X
CS 1-CN-701 2B Supply to Recombiner Condenser 6
BFLY A0 0
Q X
JTK-c33 RELIEF REQUEST BASIS SYSTEM:
FEEDWATER COOLANT INJECTION SYSTEM 1.
Valve:
1-CN-2A, 28, 2C,1-CN-30A, 308, 30C Class / Category:
2C Function:
Condensate and Condensate Booster Pump discharge check valves Test Requirement:
Exercise for opening every three months.
Basis for Relief:
During reactor full power operation, all three condensate and condensate booster pumps are operating.
It would not be possible to rotate pumps to test the reverse flow operability of these valves without introducing the potential for flow transients in the condensate and feed-water systems.
Alternate Testing:
In that the valves are in their accident position in the normal gpgrating mode, NNEC0 proposes to exercise the valves, per Code requirements, during cold shutdowns upon pump startups.
2.
Valve:
1-CN-58 Class / Category:
2B Function:
Steam jet air ejector minimum flow control Test Requirement:
Exercise valve for operability every three months, and test fail position.
Basis for Relief:
To exercise this valve during operations would require disrupting condensate flow and bypassing it to the main condenser. This valve is closed by a FWCI signal, is a system isolation valve, and is not in the FWCI flow path.
Alternate Testing:
Exercise valve and test fail position during cold shutdowns, not to exceed once every three 6
months.
DBG-c102 2
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zu Feedwater Coolent Injection 25202-26032 Sh. 2 1-W-2A 2C RFP 1A Discharge Check 18 CK 0
CV X
1-W-2B 2C RFP IB Discharge Check 18 CK 0
CV X
l-W-2C 2C RFP IC Discharge Check 18 CK 0
CV X
l-W-4A 2B W Control Valve' 5A Stop 14 GA MO O
Q X
l-W-4B 2B W Control Valve 5B Stop 14 GA MO O
Q X
CS MT 56 Sec. to Open PI l-W-5 A 2B W Control Valve SA 12 GL A0 0
Q X
CS 1-W-5B 2B W Control Valve SB 12 GL
.A0 0
Q X
'4 Sec. to Open FT X
CS 1-W-5 C 2B W Control Valve SC 4
GL A0 C
Q X
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zu ex Feedwater Coolant Injection 25202-2(J32 Sh. 2 1-W-9 A 1AC Outside Containment Check 18 CK 0
CV Verify Open Only LT X
LLRT l-W-9B 1AC Outside Containment Check 18 CK 0
CV Verify Open Only LT X
LLRT 1-W-10A 1AC Inside Containme~nt Check 18 CK 0
CV Verify Open Only LT X
LLRT I
l-W-10B 1AC Inside Containment Check 18 CK 0
CV Verify Open Only LT X
LLET 1-W-144 2B RFP 1A Recire. Miniflow 6
GL A0 C
Q X
CS PI l-W-14B 2B RFP IB Recire. Miniflow 6
GL A0 C
Q X
CS PI l-W-14C 2B RFP IC Recire. Miniflow 6
GL A0 C
Q X
l 1
RELIEF REQUEST BASIS FEEDWATER COOLANT INJECTION SYSTEM (Cont'd)
SYSTEM:
3.
Valve:
1-CN-701 Class / Category:
2B i
Function:
Cooling water supply to off-gas condensers Exercise valve for operability (full stroke)
Test Requirements:
c"ery three months, test fail position and verify remote position indicator.
Basis for Relief:
Exercising this valve during plant operation would cause a flow disruption to the off-gas condenser, which would lead to a vacuum decrease in the main condenser, in that the off-gas is drawn from the latter.
Part stroke testing is not possible for this valve design.
Alternate Testing: Exercise valve during cold shutdowns.
4.
Valve:
1-FW-2A, 2B, 2C Class / Category:
2C Function:
Feed pump discharge check valves Test Requirement:
Exercise for closing upon reversal or cessation of flow every three months.
Basis for Relief:
Two of these valves are in normal service and are exercised as pumps are routinely rotated.
Each 'ndividual valve will not be exercised every three months. Two of the three feed pumps are normally operating.
Alternate Testing: NNEC0 believes these valves are being properly demonstrated for operational readiness and wishes to continue to exercise them as pumps are rotated in service upaa pump startup.
5.
Valve:
1-FW-4A, 4B, 5A, 5B, SC Class / Category:
2B Function:
These valves control and regulate feedwater flow to the reactor.
Test Requirement:
Exercise for operability every three months.
e Basis for Relief:
Exercising these valves during operation would interrupt normal balanced flow to the reactor causing reactor water level fluctuations.
Alternate Testing: These valves will be exercised during cold shutdowns, not to exceed once every three months. -
RELIEF REQUEST BASIS SYSTEM:
FEEDWATER COOLANT INJECTION SYSTEM (Cont'd) 6.
Valve:
1-FW-14A, 148, 14C Class / Category:
2B
-Function:
Feed pump minimum flow control valves - recirculate to main condensers.
Test Requirement:
Exercise valves for operability (full stroke) every three months. Test fail position of valves every three months.
Basis for Relief:
These valves are normally closed and open only for periods of low flow into the reactor vessel, during startup. They remain closed during FWCI. Opening these valves during power operation would require a load reduction because feedwater flow to the ieactor would be diminished.
Alternate Testing: Exercise valve for operability and test fail position during cold shutdowns.
+
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Control Rod Drive Hydraulic System 25202-26032 Sh. 4 302-19A 2B Air Valve-Reactor Protection System 1 GL SOL C
Q X
RR 302-19B 2B Air Valve-Reactor Protection System 1 GL SOL C
Q X
RR 302-20A 2B Air Valve-Reactor Protection System 1 GL SOL C
Q X
RR 302-20B 2B Air Valve-Reactor Protection System 1 GL SOL C
Q X
RR L
305-114*
.75 CK O
CV X
RR 7
305-115*
2C Charging Water Supply to Scram
.5 CK 0
CV X
RR 305-120*
2B HCU Withdraw to Exhaust
.5 GA SOL C
Q 305-123*
2B HCU Insert From Drive' Water
.5 GA SOL C
Q 305-126*
2B Scram Insert 1
GL AO C
Q X
RR 305-127*
2B Scram Withdraw
.75 GL A0 C
Q X
RR 305-138*
2C Cooling Water to HCU
.5 CK O
CV 301-138 2B CRD Return Isolation 3
GT H
O Q
Passive Valve Verify Open Only
- Refers to one of 145 Units
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1 GL A0 0
Q Close 30 sec.
MT FT PI 302-21B 2B Scram Volume Kaader Vent 1
GL AO O
Q Close 30 Sec.
MT FT PI 302-22 2B Scram Volume Header Drain 2
GL A0 0
Q Close 30 Sec.
4
RELIEF REQUEST BASIS SYSTEM:
CONTRUL R0D DRIVE HYDRAULIC SYSTEM 1.
Valve:
302-19A, 198, 302-20A, 20B Class / Category:
28 Function:
Air valves from reactor protection system.
Test Requirement:
Exercise for operability.every three months.
Basis for Relief:
These valves are solenoid operated thus cannot be part stroked.
Full stroking could cause an unscheduled reactor trip. These valves are operated 145 times each refueling as part of control rod testing.
Alternate Testing: These valves will be exercised each refueling.
2.
Valve:
305-114, 115, 126, 127 Class / Category:
28, 2C Function:
Control valves for scram operation of control rods in each of 145 units.
Test Requirement:
Exercise for operability every three months.
Basis for Relief:
These valves cannot be part stroked because of their construction. They cannot be exercised at cold shutdown because of system interlocks.
The cold shutdown mode switch prohibits the withdrawal of control rods.
Alternate Testing: Exercise for operability at reactor refueling.
s 4
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Core Spray 25202-26032 Sh. 9 1-CS-2A 2B Core Spray Pump A Suction 12 GA MO O
.Q MT 90 Sec. Open/
PI Close 1-CS-2B 2B Core Spray Pump B Suction 12 GA MO O
Q MT 90 Sec. Open/
PI Close
'l-CS-3A 2C Pump A Discharge Check 10 CK C
CV Y
l-CS-3B 2C Pump B Discharge Check 10 CK C
CV l-CS-4A 2B Admission Valve 10 GA MO O
Q MT 10 Sec. - Open PI 20 Sec. - Close 1
1-CS-4B 2B Admission Valve 10 GA MO O
Q MT 10 Sec. - Open PI 20 Sec. - Close 1-CS-5A 1A Admission Valve 10 GA MO C
Q X
CS MT 10 Sec. - Open PI 20 Sec. - Close LT X
LLRT l
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Q X
CS MT 10 Sec. - Open PI 20 Sec. - Close LT X
LLRT l-CS-6A 1C Pump Discharge to Vessel 10 CK C
CV X
RR l-CS-6B 1C Pump Discharge to Vessel 10 CK C
CV X
RR I
y 1-CS-14A 2C CS Pump to Torus Test Valve 6
CK CV 1-CS-14B 2C CS Pump to Torus Test Valve 6
CK CV l-CS-18A 2C Low Pressure Relief 2
REL SRV l-CS-18B 2C Low Pressure Relief 2
REL SRV 1-CS-21A 2B Test Line to Torus 6
GA MO C
Q MT 35 Sec. to Close PI 1-CS-21B 2B Test Line to Torus 6
GA M0 C
RELIEF REQUEST BASIS SYSTEM: CORE SPRAY SYSTEM 1.
Valve:
1-CS-6A, 6B Class / Category:
1C Function:
Inside containment check valves.
Test Requirement:
Exercise normally closed valves to open position every three months.
Basis for Relief:
There is no design provision for manually exer-cising these valves and stroking with system flow requires that water be pumped into the reactor vessel. This is not possible at power, because of pressure differences and thermal-hydrau'ic considerations.
Alternate Testing: These valves will be exercised at reactor refueling after the RPV head has been removed and there is room to accommodate the flow volume required for full stroke exercising.
2.
Valve:
1-CS-5A, SB Class / Category:
1A Function:
Core Spray Admission Valves Test Requirement:
Exercise normc11y closed valves to open position every three months and perform leakage tests.
Basis for Relief:
These valves together with 1-CS-6A, 68 isolate the Reactor Coolant System from the Core Spray System. There is no positive method for deter-mining the leak tightness or closure of 1-CS-6A, 6B.
By cycling 1-CS-5A, 5B at power there is a possibility of subjecting the system to pressure in excess of their design pressures.
Test con-nections are being added (1980 outage) to enable 1-CS-5A, SB to receive a type "C" test to 43 psid as stated in our Appendix "J" proposal.
In that the valves are gates, this test pressure would be conservative with respect to the higher test pressures associated with pressure isolation testing per ASME Section XI. Additionally there is an alarm set at 350 psig immediately downstream of 1-CS-5A, SB which sounds in the control room.
Alternate Testing: These valves will be exercised at cold shutdown and receive a type "C" leakage test at refueling outages.
Note:
Present Tech. Specs. require these valves to be stroked monthly.
A Tech. Spec. change request has been submitted to eliminate this requirement....
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Turbine Building Secondary Closed Cooling Water, 25202-26032 Sh. 6 1-SC-2A 3C Pump A Discharge Check 10 CK O/C CV 1-SC-2B 3C Pump B Discharge Check 10 CK O/C CV Low Pressure Coolant Injection 25202 2o032 Sh. 5 d
1-LP-2A 2B Pump A Suction Valve 18 GA MO O
Q MT 120 Sec. to Open PI l-LP-2B 2B Pump B Suction Valve 18 GA MO O
Q MT 120 Sec. to Open PI 1-LP-2C 2B Pump C Suction Valve 18 CA MO O
Q MT 120 Sec. to Open PI l-LP-2D 2B Pump D Suction Valve 18 GA MO O
Q MT 120 Sec. to Open PI l-LP-3A 2C Pump A Discharge Check 12 CK C
CV
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CV l-LP-3C 2C Pump C Discharge Check 12 CK C
CV l-LP-3D 2C Pump D Discharge Check 12 CK C
CV l-LP-7A 2B Heat Exchanger Bypass 18 GA MO O
Q MT 40 Sec. to Close PI iw 1-LP-7B 2B Heat Exchanger Bypass 18 GA MO O
Q MT 40 Sec. to Close PI l-LP-9A 2BC Outboard Stop, LPCI to Recire. Loop 18 GL MO O
Q STOP MT 40 Sec. to Open CK CV PI 1-LP-9B 2BC Inboard Stop, LPCI to Recire. Loop 18 GL MO O
Q STOP MT 40 Sec. to Open CK CV PI
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>z Low Pressure Coolant Injection 25202-26032 Sh. 5 1-LP-10A 1A Inboard Stop, LPCI to Recire. Loop 18 GL M0 C
Q X
CS MT 18 Sec. - Open PI 40 Sec. - Close LT X
LLRT l-LP-10B 1A Inboard Stop, LPCI to Recire. Loop 18 GT M0 C
Q X
CS MT 18 Sec. - Open PI 40 Sec. - Close LT X
LLRT 7
1-LP-llA IC Inside Check 18 CK C
CV X
RR l-LP-llB IC Inside Check 18 CK C
CV X
CS 1-LP-13A 2B Outboard Stop to Torus Spray 6
GT MO C
Q MT 60 Sec. to Open PI l-LP-13B 2B Outboard Stop to Torus Spray 6
GT M0 C
Q MT 60 Sec. to Open PI l-LP-14A 2B Inboard Stop to Torus Spray 6
GL MO C
RELIEF REQUEST BASIS SYSTEM: LOW PRESSURE COOLANT INJECTION 1.
Valve:
1-LP-11A Class / Category:
IC Function:
Inside Containment Check Valve Test Requirement:
Exercise normally closed valve to full open position every three months.
Basis for Relief:
There is no design provision for manually exercising this valve.
Stroking with system flow requires that water be pumped into the reactor vessel. This is not possible at power, because of pressure differences and thermal-hydraulic considerations.
Alternate Testing: This valve will be exercised at reactor refueling after the RPV head has been removed and there is room to acconnodate the flow volume ro"Jired for full stroke exercising.
2.
Valve:
1-LP-11B Class / Category:
1C Function:
Inside containment check valve in LPCI system to reactor recirculation loop.
Test Requirement:
Exercise normally closed valve to open position every three months.
Basis for Relief:
There is no provision for manual operation of this valve. Hydraulic stroking requires pumping water into the reactor vessel. Because of pressure differentials this cannot be done while vessel is pressurized.
Alternate Testing: NNEC0 will exercise this valve whenever the reactor is in the shutdown cooling phase of operations as this valve is in the shutdown flow path. Shutdown cooling occurs at cold shutdowns.
RELIEF REQUEST BASIS SYSTEM: LOW PRESSURE COOLANT INJECTION (Cont'd) 3.
Valve:
1-LP-10A, 10B Class / Category:
1A Function:
Inboard Stop, LPCI to Recirculation Loops Test Requirement:
Exercise normally closed valve to full c' en position every three months and perform seat leakage tests.
Basis for Relief:
These valves together with 1-LP-11 A,11B isolate the Reactor Coolant System from the Low Pressure Coolant System. There is no positive method for determining the leak tightness or closure of 1 -LP-11 A, 118. By cycling 1-LP-10A, 10B, there is a possibility of subjecting the system to pressure in excess of their design pressures.
Test connections are being added (1980 outage) to enable 1-LP-10A,10B to receive a type "C" test to 43 psid as stated in our Appendix "J" proposal.
In that the valves are gate valves, this test pressure would be conservative with respect to the higher test pressures associated with pressure isolation testing per ASME Section XI. Additionally there is an alarm downstream of 1-LP-9A, 9B which alarms in the control room at 350 psig.
Alternate Testing: These valves will be exercised at cold shutdown and will receive a type "C" test at refueling outages.
Note:
Present Tech. Specs. require that these valves be stroked monthly. A Tech. Spec. change request has been made to eliminate this requirement.
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.M Low Pressure Coolant Injection 25202-26032 Sh. 5 1-LP-14B 2B Inboard Stop to Torus Spray 6
GL M0 C
Q MT 60 Sec. to Open PI 1-LP-15A 2B Outboard Stop to Containment Spray 10 GL M0 C
1-LP-15B 2B Outboard Stop to Containment Spray 10 GL M0 C
Q MT 60 See, to Open PI l-LP-16A 2B Inboard Ston to Containment Spray 10 GA M0 C
Q MT 60 Sec. to Open PI l-LP-16B 2B Inboard Stop to Containment Spray 10 GA MO C
Q MT 60 Sec. to Open PI l-LP-24A 2C LPCI Pump A Miniflow Check 2
CK CV 1-LP-24B 2C LPCI Pump B Miniflow Check 2
CK CV l-LP-24C 2C LPCI Pump C Miniflow Check 2
CK CV
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CK CV l-LP-26A 2B Minimum Flow Bypass to Torus 3
GT MO O
Q MT 40 Sec. to Close PI l-LP-26B 2B Minimum Flow Bypass to Torus 3
GT MO O
Q MT 40 Sec. to Close 1
PI L
4 7
1-LP-32A 2C Main Line Relief 2.5 REL SRV l-LP-32B 2C Main Line Relief 2.5 REL SRV l-LP-43A 2B Outboard Stop Test Line to Torus 10 GT MO C
Q MT 40 Sec. to Close 1-LP-43B 2B Outboard Stop Test Line to Torus 10 CT M0 C
Q MT 40 Sec. to Close 1-LP-44A 2B Inboard Stop Test I ine to Torus 10 GL M0 C
Q MT 40 Sec. to Close 1-LP-44B 2B Inboard Stop Test Line to Torus 10 GL MO C
Q MT 40 Sec. to Close 4
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>z Main Steam 25202-26032 Sh. 1 1-MS-1A 1A Inside Containment Stop 20 GL AO O
Q MT 3-5 Sec. to Close LT X
LLRT FT X
RR PI l-MS-1B 1A Inside Containment Stop 20 GL AO O
O MT 3-5 Sec. to Close LT X
LLRT g
FT X
RR w'
PI 1-MS-1C 1A Inside Containment Stop 20 GL A0 0
Q MT 3-5 Sec. to Close LT X
LLRT FT X
RR PI l-MS-1D 1A Inside Containment Stop 20 GL A0 0
Q MT 3-5 Sec. to Close LT X
LLRT FT X
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>z Main Steam 25202-26032 Sh. 1 1-MS-2A 1A Outside Containment Stop 20 GL A0 O
Q MT 3-5 Sec. to Close LT X
LLRT FT X
RR PI l-MS-2B 1A Outside Containment Stop 20 GL A0 0
Q MT 3-5 Sec. to Close LT X
LLRT I
H X
R PI
'l-MS-2C 1A Outside Containment Stop 20 GL A0 0
Q MT 3-5 Sec. to Close LT X
LLRT FT X
RR PI 1-MS-2D 1A Outside Containment Stop 20 GL A0 0
Q MT 3-5 Sec. to Close LT X
LLRT FT X
RR PI 1-MS-3A 1C Relief-Electro-Mechanical 6
REL SRV l-MS-3B IC-Relief-Electro-Mechanical 6
REL SRV
RELIEF REQUEST BASIS SYSTEM: MAIN STEAM 1.
Valve:
1-MS-1A, 1B, 10, lD 1-MS-2A, 28, 2C, 2D Class / Category:
lA Function:
Main steam line isolation valves inside and outside containment.
Test Requirement:
Perform seat leakage tests and check fail position.
Perfcrm position indication veri-fication.
Basis for Relief:
NNEC0 proposes a continuation of the 25 psig test pressure currently being used to verify seat leakage, per Tcch Specs, section 4.7 as this pressure is consistent with presently approved local leak rate test criteria.
It is not possible to test the fail function or the position indication of these valves while at power.
Alternate Testing:
Perform seat leakage tests per Tech Specs.
Perform fail testing and position indication testing at reactor refueling.
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REL SRV
'l-MS-3D IC Relief-Electro-Mechanical 6
REL SRV l-MS-3E IC Relief-Electro-Mechanical 6
REL SRV l-MS-3F IC Relief-Electro-Mechanical 6
REL SRV 1
Instrument Air i
1-1A-30 3C Emergency Air to ADS Valves 2
CK C
CV Open only 1-1A-124 3A Emergency Air to Instrument Air 2
CK 0
CV Operational only LT 1-1A-99A 3A Instrament Air to Accumulator 1
CK 0
CV Operational only LT l-1A-99B 3A Instrument Air to Accumulator 1
CK 0
CV Operational only LT l-1A-99C 3A Instrument Air to Accumulator 1
CK 0
CV Operational only LT i
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zu Isolation Condenser 25202-26032 Sh. 8 1-IC-1 1A Steam Isolation Valve 14 GA MO O
Q MT 24 Sec. to Close LT X
LLRT PI l-IC-2 1A Steam Isolation Valve 14 GA MO O
Q MT 24 Sec. to Close LT X
C' l-IC-3 1A Condensate Return Valve 10 GA MO C
Q 19 Sec. to Close MT LLRT LT X
PI 1-IC-4 1A Condensate Return Valve 10 GA MO O
Q MT 19 Sec. to Close LT X
.75 CON AO O
Q MT 5 Sec. to Close LT X
l-IC-7 2A Steam Vent
.75 CON A0 0
Q MT 5 Sec. to Close LT X
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GL MO C
Q MT 30 Sec. to Open.
PI i
1-lC-11.
3C Makeup Check 3
CK CV X
RR I-cm
RELIEF REQUEST BASIS SYSTEM:
ISOLATION CONDENSE _R R
1.
Valve:
1-1C-1, 2, 3, 4 Class / Category:
1A Function:
To insure containment integrity in event of requirement to isolate.
Test Requirement:
Determine leak tightness not less than once every two years.
Basis for Relief:
The safety function of these valves is to provide containment isolation when required.
These valves are and have been tested as con-tainment isolation valves as specified in Tech Specs Section 4.7 - Local Leak Rate tests.
Alternate Testing: Perform seat leakage tests per Tech Specs.
2.
Valve:
1-1C-11 Class / Category:
3C Function:
Reverse flow check in makeup line to isolation condenser.
Test Requirement:
Exercise closed valve to open position every
.three months.
Basis for Relief:
In order to exercise this valve, flow must be established into the shell side of the Isolation Condenser.
In that the shell side water inventory must be in compliance with Tech Specs, Section 3.05, this cannot be done except during reactor refuelings when it is possible to drain the shell side to a low level and refill to the operating band.
Because of the complexity of this test, NNEC0 prefers not to attempt it during cold shutdowns. Makeup flow l
to the Isolation Condenser is not required until 40 minutes after the LOCA.
j Alternate Testing:
Exercise this valve at reactor refueling.
3.
Valve:
1-lC-6, 7
~*
Class / Category:
lA Function:
To insure containment integrity in event of requirement to operate.
Test Requirement:
Test for leak tightness not less than once every two years.
Basis for Relief:
These valves have no provision for local leak rate tests.
Alternate Testing: These valves are leak tested as a part of the Integrated Leak Rate Test when containment is leak tested at 43 psig.
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Service Water 25202-26032 Sh. 10 1-SW-1A-3C Pump A Discharge Check 20 CK CV l-SW-1B 3C Pump B Discharge Check 20 CK CV 1-SW-1C 3C Pump C Discharge Check 20 CK CV l-SW-lD 2C Pump D Discharge Check 20 CK CV l-SW-9 3B Isolation Valve to Turbine Building Cooling HX's 20 GA MO O
Q X
RR MT 180 Sec. to Close PI 1-SW-99 3B Emergency Diesel Cooling 6
GL AO C
Q MT 30 Sec. to Open FT
}
RELIEF REQUEST BASIS SYSTEM: SERVICE WATER 1.
Valve:
1-SW-9 Class / Category:
3B Function:
Service Water stop to turbine building closed cooling water heat exchangers.
Test Requirement:
Exercise valve for operability every three months.
Basis for Relief:
This valve is in the flow path of service water to the Turbine Building closed cooling water heat exchangers.
If this valve fails to reopen after exercising to close, the TBCCW heat exchangers would not provide essential cooling for many balance of plant components, such as generator stator windings, hydrogen coolers, off gas blowers, etc.
The remote position indicating test is done when the valve is exercised.
Alternate Testing: This valve goes closed upon loss of normal power and is exercised in conjunction with the LNP test each refueling.
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>z Emergency Service Water 25202-26032 Sh. 5-1-LPC-1A 3C ESW Pump A Discharge Check 10 CK CV 1-LPC-1B 3C ESW Pump B Discharge Check-10 CK CV 1-LPC-lC 3C ESW Pump C Discharge Check 10 CK CV l-LPC-lD 3C ESW Pump D Discharge Check 10 CK CV f
1-LPC-4A 3B Heat Exchanger Discharge Stop 12 GL MO C
Q MT y
PI 1-LPC-4B 3B Heat Exchanger Discharge St.cp 12 GL MO C
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zu Reactor Luilding Closed Cooling Water, 25202-26032 Sh. 11 1-RC-2A 3C Pump Discharge Check 14 CK CV 1-RC-2B 3C Pump Discharge Check 14 CK CV 1-RC-6 3C Header Inlet Check 6
CK CV X
None 1-RC-15 3B Header Outlet Stop 6
GA MO O
Q X
None Passive Value MT 60 Sec. to Close t
l-RC-39 3B Shutdown Heat Exchanger Cooling 8
Discharge 12 GL MO C
Q X
CS MT Fuel Pool Cooling 25202-26032 Sh. 3 1-FP-3A 3C FP Pump A Discharge Check 6
CK CV 1-FP-3B 3C FP Pump B Discharge Check 6
CK CV Shutdown Cooling 25202-26032 Sh. 13 1-SD-3A 2C Pump Discharge Check 10 CK CV X
CS 1-SD-3B 2C Pump Discharge Check 10 CK CV X
RELIEF REQUEST BASIS SYSTEM: REACTOR BUILDING CLOSED COOLING WATER 1.
Valve:
1-RC-6, 15 Class / Category:
3C, 3B Function:
Inlet and outlet valves on drywell header.
Test Requirement:
Exercise valves (full stroke) for operability every three months.
Basis for Relief:
The RBCCW cooling requirements for equipment inside containment are nonessential during accident modes of operation and so the positions of 1-RC-6 and 15 are inconsequential, and left to the discretion of plant operators.
- Further, the valves are not considered containment isolation valves, per the present plant Technical Specifications, section 4.7.
Alternate Testing:
None.
2.
Valve:
1-RC-39 Class / Category:
3B l
Function:
Stop valve in RBCCW system discharge from shutdown heat exchangers.
Test Requirement:
Exercise for operability every three months.
Basis for Relief:
The shutdown heat exchanger is " laid up" between operations and is operated as necessary to control temperature at specified conditions during cold shutdowns.
Alternate Testing:
Exercise for operability at cold shutdowns, not to exceed once every three months.
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RELIEF REQUEST BASIS i
I l
SYSTEM: SHUTDOWN COOLING SYSTEM 1
l 1.
Valve:
1-SD-3A, 3B l
Class / Category:
2C Function:
Pump discharge check valves.
Test Requirement:
Exercise valves (full open) every three months.
Basis for Relief:
System is in " wet layup" and does not operate except at cold shutdowns.
System recirculates reactor coolant only and has limited make-up capabilities.
Alternate Testing: Exercise for operability at cold shutdowns, not to exceed once every three months.
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>z Containment Isolation Valves 1-HS-4 1A Head Spray Outer Isolation Valve 2
GA M0 C
Q X
L'I X
LLRT PI l-HS-5 1AC Head Spray Inner Isolat. ion Valve 2
CK C
CV X
CS LT ILRT l-SL-7 1AC Standby Liquid Disch. Check 1.5 CK C
CV X
ILRT 4
T l-SL-8 1AC Standby Liquid Disch. Check 1.5 CK C
CV X
RR LT X
ILRT l-MS-5 1A Steam Drain Header Stop 4
GT MO C
Q X
LLRT PI l-MS-6 1A Steam Drain Header Stop 4
GT MO C
Q X
LLRT PI 1-SD-1 1A Shutdown Suction Isolation 14 GA MO C
Q X
LLRT PI 1-SD-2A 1A Shutdown Pump A Suction 12 GA MO C
Q X
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Containment Isolation Valv'es 1-SD-2B 1A Shutdown Pump B Suction 12 GA M0 C
Q X
LLRT PI l-SD-4A 1A SD Heat Exchanger Disch. Stop 10 GL MO C
Q.
2 l-SD-4B 1A SD Heat Exchanger Disch. Stop 10 GL MO C
Q X
LLRT PI l-SD-5 1A Shutdown Discharge Isolation 12 GA MO C
Q X
LLRT PI l-SS-3 2A Drywell Drain Valve 2
GA A0 C
Q MT LT X
ILRT l-SS-4 2A Drywell Drain Valve 2
GA A0 C
Q MT LT X
ILRT l-SS-13 2A Drywell Equip. Drain Valve 2
GA A0 C
Q MT LT X
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zm Containment Isolation Valves 1-SS-14 2A Drywell Equip. Drain Valve 2
GA A0 C
Q MT.
LT X
ILRT l-CU-2 1A Supply to CU System Inside Drywell 8
GA MO O
Q MT 18 Sec. to Close LT X
~i ~
1-CU-2A 1A Bypass to 1-CU-2
.5 GA A0 C
Q y'
MT 10 Sec. to Close LT X
LLRT PI l-CU-3 1A Auxiliary Pump Bypass.
8 GA MO O
Q MT 18 Sec. to Close LT X
LLRT PI 1-CU-5 1A Auxiliary Pump Suction 8
GA M0 C
Q MT 18 Sec. to Close LT X
LLRT PI l-CU-28 1A Regen. Heat Exchanger Discharge 8
GA MO O
Q MT 18 Sec. to Close LT X
LLRT PI l-AC-2A 2AC Vacuum Relief from Sec. Containment 20 CK CV LT X
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Containment Isolation Valves 1-AC-2B 2AC Vacuum Relief from Sec. Containment 20 CK CV LT X
LLRT l-AC-3A 2AC Vacuum Relief from Sec. Containment 20 BFLY A0 Q
MT 10 Sec. to Close LT X
LLRT PI 1-AC-3B 2AC Vacuum Relief from Sec. Containment 20 BFLY A0 Q
i MT 10 Sec. to Close LT X
LLRT PI l-AC-4 2A Purge Air Supply 18 BFLY A0 C
Q MT 10 Sec. to Close LT X
LLRT PI l-AC-5 2A Purge Air to Drfwell 18 BFLY A0 C
Q MT 10 Sec. to Close l
LT X
LLRT PI l-AC-6 2A Purge Air to Drywell 10 BFLY A0 C
Q MT 10 Sec. to Close LT X
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Q MT 10 Sec. to Close LT X
_Drywell Vent to Main Exhaust 18 BFLY A0 C
Q MT 10 Sec. to Close LT X
1-AC-9 2A Drywell Vent Bypass 2
BFLY A0 C
Q MT 15 Sec. to Close-LT X
LLRT PI 1-AC-10 2A Standby Gas Treatment Inlet 12 BFLY A0 Q
HT 10 Sec. to Close LT X
LLRT PI l-AC-11 2A Torus Vent 18 BFLY A0 C
Q MT 10 Sec. to Close LT X
LLRT PI 1-AC-12 2A Torus Vent Bypass 2
BFLY A0 C
Q MT 15 Sec. to Close LT X
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BFLY AO C
Q 2
MT 15 Sec. to Close LT X
LLRT PI l-1A-68 2K Instrument Air Stop 2
GL M
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Passive MT LT PI l-1A-69 2AC Instrument Air Check 2
CK O
CV Open only LT X
I-SM-1 1A Reactor Coolant Sampling Isolation
.75 GL SOL C
Q Passive LT l-SM-2 1A Reactor Coolant Sampling Isolation
.75 GL SOL C
Q Passive MT 1201-83 2AC Clean-Up Relief Discharge of Torus 12 CK C
CV Passive LT 1201-84 2AC Clean-Up Relief Discharge of Torus 12 CK C
CV Passive LT
RELIEF REQUEST BASIS CONTAINMENT ISOLATION VALVES o
SYSTEM: VARIOUS - CONTAINMENT ISOLATION 1.
Valve:
See list of Containment Isolation Valves.
Class / Category:
All Category A Valves.
Function:
To insure containment integrity in event of requirements to isolate.
Test Requirement:
Exercise all active valves every three months and determine leak tightness not less than once every two years.
Basis for Relief:
This list consists of valves whose only safety function is containment isolation.
Present Tech Specs require both an individual and an
)
integrated leakage rate test for containment isolation valves and penetrations. Tech Specs also require repair and retest of any valve j
exceeding the leakage criteria.
NNEC0 feels that these tests insure the leak-tightness of all containment' isolation valves, in that they are tested under the conditions for which they are designed.
Operability testing of these valves during normal plant operation could cause a loss of containment integrity and/or system function if a valve failed in a nonconservative position.
NNECO also requests relief from paragraph IWV-3420(f) " Analysis of Leakage Rates" in that present rules for local leak rate testing of containment isolation valves provide analytical data for determining acceptance criteria, based on combined leakage of several valves.
Based on seat leakage data recorded to date, in connection with the containment leak rate tes:
program, NNEC0 requests relief from paragraph IWV-3420(g)(2) in that no meaningful trends have been established.
RELIEF REQUEST BASIS CONTAINMENT ISOLATION VALVES SYSTEM:
VARIOUS - CONTAINMENT ISOLATION (Cont'd)
Alternate Testing: NNEC0 proposes to use existing procedures for leak testing of valves used for containment isolation. Modifications to procedures as agreed upon by NNECO and NRC Staff concerning
" App. J" tests and exemptions will be reflected in this program.
Exercise requirements shall be per plant technical specifications (i.e. normally open power operated valvos shall be fully closed and reopened, at least once per quarter). Operating time shall be per Tech Specs, Table 3.7.1.
2.
Valve:
1-HS-4, 1-HS-5 Class / Category:
l A, l AC Function:
Inner and outer containment isolation valves for head spray.
Test Requirement:
Exercise for operability every three months.
Basis for Relief:
These normally closed valves have no safety related functions and are listed as containment isolation valves only.
These valves are opened to admit water to cool the head and upper reactor internals before removal of the closure head.
Alternate Testing: Exercise for operabil_ity at cold shutdowns.
3.
Valve:
1-SL-7, 8 Class /Categorf.
1/AC Function:
Combined discharge checks inside and outside drywell.
Test Requirement:
Exercise normally closed valves to open position every three months.
Basis for Relief:
There is no oravision for manual operation of these valves. Hydraulic stroking requires pumping into the reactor vessel and the operation i
of a squib valve. There are no test connections at present by which an individual valve leak rate test could be performed.
i i
RELIEF REQUEST BASIS CONTAINMENT ISOLATION VALVES Alternate Testing: These check valves will be exercised each refueling as the standby liquid system is tested by pumping into the reactor.
Leak tightness of these valves is checked during containment integrated leak rate tests.
4.
Valve:
1-MS-5, 1-MS-6 Class / Category:
1A Function:
Main steam line drain stops-Test Requirement:
Exercise for operability every three months.
Basis for Relief:
These normally closed valves are used at startups and shutdowns only and have no safety related function other than containment isolation valves.
Alternate Testing:
Exercise for operability at cold shutdowns only.
5.
Valve:
1-SD-1, 2A, 2B, 4A, 4B, 5 Class / Category:
lA Function:
These valves are used to isclate the Shutdown Cooling System from the Reactor Recirculation System during power operations.
Test Requirement:
Exercise for operabili'yy every three months.
Basis for Relief:
_This system is held in " wet layup" until such time as it is desired to be operated. The system operates as necessary to control temperature at specified conditions during cold shutdown.
Alternate Testing: Exercise for operability at cold shutdowns not to exceed once every three months.
4.
LEGEND FOR VALVE TESTING Exercise valve (full stroke) to verify satisfactory operation Q
every three (3) months.
4 Valves are lea tested per Section XI Article IWV-3420.
LT 1
ILRT -
Containment Isolation Valves are leak tested in conjunction with containment integrated leak test.
MT Stroke time measurements are taken per Section XI Article IWV-3410, for power operated valves.
CV Exercise check valves to the position required to fulfill their function every three (3) months.
Safety and alief valves are tested per Section XI Article SRV IWV-3510.
Verify and record valve position before operations are performed ET and after operations are completed, and verify that valve is locked or sealed.
Exercise valve (full stroke) to verify satisfactory operation CS at cold shutdown.
RR Exercise valve (full stroke) to verify satisfactory operation at reactor refueling.
Visually observe, every two years or less, actual valve position PI to confirm that remote valve position indications accurately reflect valve operation.
Remove actuator power from valves with fail-safe actuators to FT confirm that the valve travels to its fail-safe position every three (3) months.
Containment Isolation Valves individually tested at 43 psig.
LLRT t
TABLE IWV-2 SAFETY / RELIEF VALVE SETPOINTS Se'rvice Sta. No.
Valve Type Set Point (Tol.)
Core Spray Low Pressure Relief 1-CS-18A 2" R-V 375 (+15, -5) 1-CS-18B 2" R-V 375 (+15, -5)
LPCI Main Line Relief 1-LP-32A 2 1/2 R-V 400(+10,-5) 1-LP-32B 2 1/2 R-V 400 (+10, -5)
Standby Liquid Control Pump Disc.
1-SL-22A 1 1/2 R-V 1400(+25,-20)
Relief 1-SL-22B 1 1/2 R-V 1400 (+25, -20)
Main Steam Electro-pnewnatic Relief 1-MS-3A 6" SRV 1095 (+1%)
1-MS-3B 6" SRV 1125 ( %)
1-MS-3C 6" SRV 1125 (
%)
1-MS-3D 6" SRV 1110 ( %)
1-MS-3E 6" SRV 1125(
%)
1-MS-3F 6" SRV 1125 ( %)
FWCI Condenser Transfer Relief 1-FCX-1 3" R-V 275 (+10)
(V7-156) 4 1
h T
SYSTEM PRESSURE TESTS The accompanying table lists the system and hydrostatic tests required under Categories B-P, C-H, and D-A for the Class 1,-2, and 3 systems.
Precautions must be taken in view of the differences that exist in Class 1/
Class 2 test pressures to prevent overpressurization of the Class 1 components.
The following systems are affected:
System Class 1 Boundary Class 2 Boundary Feedwater 1-FW-11A/B HP Heater Discharge Isolation Valves Standby Liquid Control 1-S L-8 1-SL-6 Core Spray 1-CS-6A/B l-CS-5A/B LPCI 1-LP-11A/B l-LP-10A/B Reactor Cleanup Return 1-CD-29 CRI) Return Penetration (Dormant From Cap at Cap Penetration to RPV)
Reference Boundary Diagram, Figure 1 Because of the design of those systems listed, isolation of Class 1 and Class 2 systems at the boundary cannot be accomplished. To prevent overpressurization of the Class 1 portions of these systems (1,080 psig for Class 1 versus 2,875 psig for Class 2), the portions of these systems which cannot be tested to the code required pressure must be visually inspected during system operation to the extent practicable, a
?
TABLE BCD-5000 SYSTEM PRESSURE TESTS System Hydrostatic System Pressure Pressure Remarks t
Class 1 Reactor Coolant Pressure Boundary 1000 1080 0 200 F In Compliance Class 2 Main Steam 1000 1370 In Compliance CRD System 1563 1563 Note 1 Standby Liquid Control 1225 1540 In Compliance FWCI - Condensate 155 210*
Note 2
- Condensate Booster 525 665 In Compliance
- Feedwater 1650 2875 Note 3 Emergency Condensate Transfer 100 100*
In Compliance Shutdown Cooling 1000 1370 In Compliance Isolation Condenser 1000 1370 In Compliance LPCI 95 200*
In Compliance Core Spray 260 260*
In Compliance
~
Class 3 Secondary Closed Cooling Water 115 190 In Comr.11ance Reactor Building Closed Cooling Water 80 190 In Compliance Fuel Pool Cooling 175 250 In Compliance Emergency Service Water 200 375 In Compliance Service Water 55 55 Note 4 Atmospheric Control 0
43 Note 5
- Test pressure to be obtained by operating the system pump at shutof f head, allowing some recirculation for cooling. The exact pressure will depend on specific test conditions.
Ilydro testing will be conducted at temperatures meeting fracture toughness criteria applicable to the ferritic materials from which the system com-ponents are constructed.
O f
i NOTES 1.
CRD mechanism seal leakage limits this test pressure. There is no safety valve in this system other than the scram volume relief set at 1285. This l
g-system is not designed to be isolated for testing, 2.
The system maximum operating pressure (condensate pump shutoff head) is g
'.10 psig. Leakage past valve seats in this system's large gate valves would preclude a test pump's ability to achieve an additional 78 psi to reach the desired 288 psig. Normal operating pressure is 150 psig.
3.
Feedwater/FWCI system piping and components between the feed pump discharge isolation valves and the maintenance stops downstream of the HP heatet s will be tested to 2875 psig. Piping between the HP heater stop valves and the reactor vessel cannot be tested at this pressure because of the double check i
valve arrangement at the containment penetration and the lower test pressure of the reactor coolant-pressure boundary components.
This piping will be observed for leakage during system operation. Feedwater piping between the feed pumps and the discharge isolation valves will be pressure tested with the condensate booster /FWCI system.
4., Due to the essential cooling functions of this system, NNECO will test these i
systems by utilizing the pump head and throttled flow for continuous cooling of the vital system components.
5.
This system is pneumatically tested in accordance with 10CFR50, Appendix J, Integrated Leak Test Program.
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