ML20127L527
| ML20127L527 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/21/1993 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20127L522 | List:
|
| References | |
| NUDOCS 9301270188 | |
| Download: ML20127L527 (171) | |
Text
.
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK HUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUEER_AliD VALVES i
)
Reviewed by: Plant Operations Review Committee ik" ll)
Date:
l Ji k)s Meeti No.
Approved by:
.f u o
/
,/
Date: N/n// '
HESIDENT MANAGER Page No.
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Rev. No.
.6 Page i of 11 9301270188 930121 PDR ADOCK 0D000333 P
NEW YORK POWER AUT!!ORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT IHRERYlEE TEDIIHg_ PROGMM FOR PUMPS. AFD V%Y10 OG Tablo of contents 1.
INTRODUCTION..........................................
1 2.
APPLICABLE DOCUMENTS..................................
1 3.
INSERVICE TESTING PROGRAM FOR PUMPS...................
2 4.
INSERVICE TESTING PROGRAM FOR VALVES..................
3 5.
SYSTEMS SUBJECT TO TESTING............................
5 i
APPENDIX A - PUMP TESTING PROGRAM..........................
6 APPENDIX B - VALVE TESTING PROGRAM........................
34 APPENDIX C -
SUMMARY
OF Cl!ANGES..........................
165 t
Rev. No.
6 Page 11 of 11
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT IN B BJJS R_TE GIINQJ!nqqBA}LI9RJ?.UMH_AND_XAkVIQ 1.0 IEIRQD1!CIlRH Revision 6 of the James A FitzPatrick ASME Inservice Testing (IST)
Program will be in effect through the end of the second 120-month (10-year) interval unless changed and re-issued for reasons other than the routine update required at the start of the third interval per 10 CFR 50.55a(g).
The third inspection interval begins on July 28, 1995.
This document outlines the IST Program for J.A.
Fitzpatrick based on the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition, through Winter 1981 Addenda (the Code).
References in this document to "IWP" or "IWV" correspond to Subsections IWP and
- IWV, respectively, of the
- Code, unless otherwise noted.
2.O MS$LCADLE_QQC.pME1[TS This IST Program Plan was developed per the requirements of the following documents:
Title 10, Code of Federal Regulations, Part 50 Final Safety Analysis Report, J.A.
Fitzpatrick Nuclear Power Plant e
J.A. Fitzpatrick Technical Spec.4.fications O
ASME Boiler and Pressure Vessel Code,Section XI,1980 Edition e
through Winter 1981 Addenda.
NRC Safety Evaluation by the Office of Nuclear Reactor Regulation related to the Inservice Testing Program Relief Requests Power Authority of the State of New York James A.
FitzPatrick Nuclear Power Plant Docket No.
50-333, Dated January 8, 1992.
Safety Evaluation for Innervice Testing (IST) Program Relief Requests, James A. FitzPatrick Nuclear Power Plant, Dated July 28, 1992.
Other documents used for guidance in the development of the IST Program are listed below:
NRC Regulatory Guide 1.26, " Quality Group Classifications and Standards for Water,
Steam,
and Radioactive-Waste-Contaminating Components of Nuclear Power Plants" Standard Review Plan NUREG 0800, Section 3.9.6,
" Inservice Testing of Pumps and Valves" NRC Generic Letter 89-04, " Guidance on Developing Acceptable Inservice Testing Programs" NRC Minutes of the Public Meetings on Generic Letter 89-04 Page 1__ of 167 Rev. No.
6
NEW YORK POWER AUT}{0RITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT IBMILY1SI_TIllT1H9_EILO3 RAM _F_QiLPEMP.R_hMD__YALYAA
- )
-1 3.0 INSERVICE TESTIltG PROGRAM FOR PUMPS 3.1 Code.Comoliance This IST Program for pumps is based on the requirements of interpretations.l Subsection IWP of the Code and any Code Where these requirements have been determined to be impractical, conformance would cause unreasonable hardship without any compensating increase in safety, or an alternative test provides an acceptable level of quality and safety, relief from Code requirements is requested pursuant to the requirements of 10 CFR 50. 55a(g) (iii).
3.2 Allgyable Ranges of Test Ounntities The allowable ranges for test parameters as specified in Table IWP-3100-2 will be used for all measurements of pressure, flow, and vibration except as provided for in specific relief.
requests approved by the NRC.
In some cases the performance of a pump may be adequate to fulfill its safety function even though there may be a value of an operating paramotor that f alls outside the allowable ranges as set f orth in Table IWP-3100-2.
3.3 Tcstina Intervals ThetestfrequencyforpumpsincludedintheISTProgramwilll be as set forth in IWP-3400.
A band of 125 percent of the test interval may be applied to a test schedule as allowed by the J.A Fitzpatrick Technical Specifications to provide for operational flexibility.
3.4 Pump Proqram Table Appendix A lists those pumps included in the IST Program with references to parameters to be measured and applicable requests for relief.
3.5 Relief Recuests for Pump Tere _ ting Appendix A includes relief requests related to pump testing.
O Page 1 of 167.
Rev. No.
3
i NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUNPS AHD VALVFJ t
n 4.0 INSERVICE TESTING PROGRAM FOR VALVES 4.1 Code Compliants This IST Program for valves is based on the requirements of Subsection IWV of the Code and any Code interpretations or additional requirements imposed by Generic Letter 89-04.
Where these requirements have been determined to be impractical, conformance would cause unreasonable hardship without any compensating increase in safety, or an alternative test provides an acceptable level of quality and safety, relief from Code requirements is requested pursuant to the requirements of 10 CFR 50.55a(g) (iii) and Generic Letter 89-04.
4.2 Igplina Intervalg The test frequency for valves included in the IST Program will forth in IWV-3400 and related relief requests.
A be as set band of 125 percent of the test interval may be applied to a schedule as allowed by the J. A. Fitzpatrick Technical test Where Specifications to provide for operational flexibility.
quarterly testing of valves is impractical or otherwise undesirable, testing may be performed during cold shutdown Justifications for this periods as permitted by IWV-3412 (a).
O deferred testing are provided in Appendix B with elaboration Fitzpatrick plant policy set forth in Relief Request of J.A.
NOTE V51.
4.3 Stroke Time Acceptance Criteria The acceptance criteria for the stroke times of power-operated l valves will be as set forth in IWV-3410 and using the guidance of Generic Letter 89-04.
4.4 Check Valve Testina Full-stroke exercising of check valves to the open position using system flow requires that a test be performed whereby the predicted full accident condition flowrate through the valve be verified and measured.
Any deviation to this satisfy the requirements of Generic Letter requirement must 89-04, Position 1.
O Page _2_ of 167 Rev. No.
3
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVER 4.5 Valve Procram Table Appendix B lists those valves included in the IST Program with references to required testing, respective test intervals, applicable requests for relief and cold shutdown justificationis.
4.6 Relief Reauests for Valve Testing Appendix D includes all relief requests and cold shutdown justifications related to valve testing.
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Rev. No.
5 Page 4
of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES 5.0 SYSTEMS SUBJECT TO TESTING DRAWING SYSTEM #
SYSTEM NAME 01-125 Standby Gas Treatment FM-48A 02-2 Reactor Water Recirculation FM-26A 02-3 Nuclear Boiler Instrumentation FM-47A 03 Control Rod Drive FM-27B 07 Neutron Tip Monitors FM-119A 10 Residual Heat Removal FM-20A FM-20B l
11 Standby Liquid Control FM-21A 12 Reactor Water Cleanup FM-24A 13 Reactor Core Isolation Cooling FM-22A 14 Core Spray FM-23A 15 Reactor Building Closed Loop FM-15A l
Cooling FM-15B 16-1 Leak Rate Analyzer FM-49A 19 Fuel Pool Cooling FM-19A 20 Radioactive Waste FM-17A 23 High Pressure Cooling injection FM-25A 27 Containment Atmosphere Dilution FM-18A FM-18B FM-18D 29 Main Steam FM-29A 34 Feedwater FM-34A 39 Breathing, Instrument & Service FM-39C Air 46 Service & Emergency Service Water FM-46A FM-46B 66 Reactor Building Service Water FB-10H 70 Control Room Service & Chill Water FB-35E O
Rev. No.
6 Page 5
of 167.
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK HUCLEAR POWER PLANT I
IHHIRVICE TESTING PROGRAM FOR__ PUMPS AND VALVER APPENDIX A PUMP TESTING PROGRAM O
O l
Rev. No.
- _1_,
Page 6
of _152__
NEW YORK POWER AUTHORITY
-JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INS.ERVICE TESTING PROGRAM FOR PUMPS AND VALVE 8 APPENDIX A PUMP TESTING PROGRAM Table of Contents Pump Table Explanation........................................ 8 Pump Table.....................................................
9 Relief Requests...............................................
11 NOTE P1:
WITHDRAWN.........................................
11 NOTE P2:
RHRSW and Emergency Service Water.................
12 NOTE P3:
WITHDRAWN........................................ 13 NOTE P4:
WITHDRAWN........................................ 13 NOTE PS:
RHRSW and Emergency Service Water.................
14 NOTE P6:
WITHDRAWN.........................................
15 NOTE P7:
Standby Liquid Control............................
16 NOTE P8:
WITHDRAWN.........................................
17 NOTE P9:
RHRSW and Emergency Service Water.................
18.
/"T NOTE P10:
WITHDRAWN.........................................
19 tj NOTE Pil: Core Spray........................................
20 s
NOTE P12: Standby Liquid Control............................
22 NOTE P13: Standby Liquid Control............................
23 NOTE P14: Generic - Bearing Temperature Measurements........ 27 NOTE P15:
WITHDRAWN.........................................
29 NOTE P16: Generic - Suction Pressure Measurement............
30 NOTE P17: Generic - Digital Instruments.....................
32 NOTE P18: WITHDRAWN........................................ 33 Rev No.
6 Page 7
of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT IPSERVICE TESTING PROGRAM FOR PUHPS AND VALVES APPENDIX A PUMP TABLE EXPLANATION-Summarv of Information Provided The Fump Table provides the following information:
Individual pump identifier Test type
" Design" refers to tests where design or substantial flowrate is achieved.
The drawing on which the pump appears Drawing 8 coordinates Speed (
Inlet pressure
- Flow rate
- Vibration amplitude
- Observation of lube oil level
- Test interval Bearing temperature
- These parameters are each addressed with either an "X" indicating the parameter is measured, an "X" with a note number indicating the carameter is measured but with some exception to the code, or by a O
note number indicating relief is requested to eliminate measurement of the parameter.
A blank indicates that measurement of the respective parameter is not applicable.
Pump Relief Reauests Notes PXX refer to relief requests for the Pump Testing Program.
Each pump request for relief provides the following information:
System Individual pump identifier ISI Classification Safety Function Code test requirement for which relief is requested Basis for relief Proposed alternate testing O
Page 8
of _167 Rev. No.
3
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NEW Y0RK POWER AUTHORITY p
JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE 7E$ TING PROGRAM F0R PUMPS ANO VALVES PUMP TABLE DRAWING DWG INLET DIFFERENTIAL FLOW V1BRATION BEARING LUBE Ott INSPECTION I PUMP ID TEST' TYPE NUM8ER CO-OR SPEED PRESSURE PRESSURE RATE AMPLITUDE TEMPERATURE LEVEL / PRESSURE FREGUEasCY i-l:
! J10P,1A DESIGN FM-208 B-6 X P2 '
X X P17 X P9 P14 PS 1 - eUARTERtf i
y DESIGN" FM-208 B-5 X P2 X
X P17 X P9 P14 PS 1 - QUARTERLY
- 10P-1B 1 10P-1 C.'
DESIGN FM 208 C-6 X P2 X
X PIT X P9 '
Pts PS 1 - QUARTERLY-l
.,10P-10 DESIGN FM-20s C-5 X P2 X
X PIT X P9 P14 PS 1 - QUARTERLY s
10P'3A~
DESIGN FM-20A B-7 X P16 X
X P17 X
P14 X
1 - QUARTERLY 4
10P-35 DESIGN-FM-20A 9-3 X P16 X
X P17 X
P14 X
1 - QUARTERLY 10P-3C DESIGN FM-20A C-7 X P16 X
X P17
'X P14 X
1 - QUARTERLY i
10P-30 DEstGN FM-20A C-3 X P16 X
X P17 X
P14 X
1 - QUARTERLY l
11P-2A DESIGN FM-21A D-4 X P12 X
X PT X P13 Pl4 X
1 - GUARTERLY
'117-28 DESIGN FM-21A B-4 X P12 X
X PT X P13 P14 X
1 - GUARTERLY I
t t
14P-1A DESIGN FM 23A C-8 X P11.
X P17 -
X P17 X
P14
'X
.1 - GUARTERLY -
'DEstGN
-FM-23A C3 X P11 X P17 X PIT X
P14 -
X 1 - GUARTERLY 23P DESIGN FM-25A
.E-5
'X P17' X
X P17 X
P14 X
1 - GUARTERLY j.
23P-1.'l DESIG8
'FM-25A ~
E-4 X P17 X.
X P17 X P17 X
P14 X
1 - GUARTERLY 46P-2A DESIGN FM-464 D-8 X P2-X X P17 X P9 P14 -
PS 1 - euARTERLY
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. REY.' NO:_. 6 PAGE 9 0F 167 l
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V NEu YORK POWER AUTNORI TY JAME5 A.
F 1 T'Z P A T R I C K NUCLEAE POWER PLANT IN5ERVICE TESTING PROGRAM FOR PUMPS AND VALVES PUMP TA8LE DRAWING DWG INLET DIFFERENTIAL FLOW VIBRATION BEARING LUSE Oil INSPECTION PUMP ID TEST TYPE NUMBER CO-OR SPEED PRESSURE PRESSURE RATE AMPLITLEE TEMPERATURE LEVEL / PRESSURE FREQUEECY 46P-28 DESIGN FM-46A C-8 X P2 X
X P17 X P9 P14 PS 1 - QUARTERL l
PAGE 10 0F 167 REv. No: 6 l
l
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICl; NUCLEAR POWER PLANT.
INSERVICE TESTING. PROGRAM FOR PUMPS AND VALVES APPENDIX A Pump Relief Requests NOTE P1 This relief request has been withdrawn.
O V
f(_h
-Rev. No.
3 E"9"
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT l
l IE8JRVICE TESTING PROGRAM FOR PUMPB AND VALVE 8 APPENDIX A Ob Pump Relief Recuests NOTE 22.
SYSTEMS:
RHR Service Water Emergency Service Water PUMPS:
C, D
3 FUNCTION:
These pumps provide cooling water under accident conditions from the forebay to various safety related heat exchangers and back-up injection points.
TEST REQUIREMENT:
IWP-3100 and Table IWP-3100-1 requires that inlet pressure be measured before pump startup and during the test.
Also, IWP-4230 requires inlet pressure measuring taps be located in a section of the flowpath that is expected to have p
reasonably stable flow as close as practical to the pump.
BASIS FOR RELIEF:
These pumps are of a vertical submerged open line shaft design.
There is no installed instrument-for direct measurement of the inlet pressure.
Instead, the minimum pumping level is monitored to insure adequate NPSH is available for pump operation.
Since the forebay water level is not expected to change significantly during the testing of these pumps, only one measurement per test is required.
ALTERNATE TESTING:
During each test, the difference in elevation between the forebay water level and the pump discharge pressure gauge will be determined by measurement. This value will be verified to be less than or equal to the value corresponding to the minimum water level required for pump operation and will also be used to calculate pump differential pressure.
(]
L Rev. No.
5 Page 12 of 167
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPB AND VALVER APPENDIX A d
Pump Relief Requests NOTE P3 This relief request has been withdrawn.
NOTE P4 This relief request has been withdrawn.
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6 Page.13 of 167
s NEW YORK POWER AUTHORITY-JAMES A.'FITZPATRICK NUCLEAR POWER PLANT IMBERVICE TESTING PROGRAM FOR'PUNPS AMD VALVEE-APPENDIX A Pump Religf Reauests i
NOTE P5 SYSTEMS:
RHR. Service Water Emergency-Service Water
-t PUMPS:
C, D
3 FUNCTION:
Provide emergency cooling water from intake bay to various emergency. heat exchangers-and back-up injection points.
TEST REQUIREMENT:
IWP-3100 and Table IWP-3100-1 require observation of proper lubrication level or' pressure.
BASIS FOR RELIEF:
These putaps are of a vertical submerged = open line shaft design.
The pump. bearings are water lubricated and the lube oil observation cannot be.
performed.
ALTERNATE TEST:
Other Code required. parameters being. measured,
will detect degradation of the mechanical condition of the pumps.
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Rev_. No.
._1 Page _.11._ of 167-
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. = -.
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NEW YORK POWER AUTil0RITY JAMES A. FITZPATRICK HUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FQR PUMPS AND VALVEB i
APPENDIX A-O v
Purno Relief Recuerg
-HQIE PJi This relief request has been withdrawn.
J O
O Rev. No.
3 Page._1]i of..167.
- NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPB AND VALVER APPENDIX A O
Pump Relief Roquests NOTE P7 SYSTEM:
PUMPS:
2 FUNCTION:
These pumps inject borated water into the reactor vessel as an alternate means for negative reactivity addition and reactor shutdown.
TEST REQUIREMENT!
IWP-3500 specifies that a pump shall be run for at least five minutes under stable conditions before recording the required test data.
IWP-4600 specifies that flowrate shall be measured using a rate or quantity meter installed in the pump test circuit.
A BASIS FOR RELIEF:
The SLC test loop is not equipped with flow V
instrumentation and the only practical means of determining flowrate is to monitor the change of level in a test tank from which water is being pumped.
The installed test tank has a capacity of only 210 gallons and in not capable of accommodating 5 minutes of pump operation at rated conditions (1 50 gpm).
ALTERNATE TESTING:
The flowrate of the SLC pumps will be determined by measuring the change in water level in the test tank during.a period of pump operation at the reference discharge pressure over a period of at least two (2) minutes.
F l
l l O Rev. No.
5 Page 16 of _.152_.
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM _FOR PUMPS AND VALVES APPENDIX A s..e Pump Relief Recuestn NOTEJ_Q This relief request has been withdrawn.
O L)
Rev. No.
3 Page 17 of.16L
HEW YORK POWER AUTilORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGLAM FOR PUMPS AND VALVES APPENDIX A
\\
J Pump Belief Recuests NOTE P9 SYSTEMS:
RilR Service Water (RHRSW)
Emergency Service Water (ESW)
PUMPS:
C, D
3 Ful:0 TION :
Provide emergency cooling water from the intake bay to various emergency heat exchangers and backup injection points.
TEST REQUIREMENT:
IWP-4510 requires that, on a pump coupled to the driver, vibration measurements shall be taken on the bearing housing near the coupling.
BASIS FOR RELIEF:
These pumps are of a vertical submerged open-line shaft design with the pump bearings p!
submerged and inaccessible below the floor slab.
The bearing / seal housing near the upper coupling, which is accessible, in in a confined area in close proximity to the rotating shaft and coupling.
Access to this area for vibration monitoring is considered to present an unacceptable personnel safety hazard during pump oper3 tion.
ASME/ ANSI OMa-1988, Part 6,
" Operation and Maintenance of Nuclear Power Plants", Paragraph 4.6.4 (b) identifies the access problem associated with measuring vibration of vertical line shaft pumps and directs that measurements be taken on the upper motor bearing housing in three orthogonal directions.
This Standard considers measuring in this manner an acceptable method for monitoring vibration.
ALTERNATE TESTING:
Vibration measurements on these pumps will be taken on the upper motor bearing housing per ASME/ ANSI OMa-1988, Part 6,
" Operation and Maintenance of Nuclear Power Plants", Paragraph
- 4. 6. 4 (b).
In addition, vibration measurements will comply with the applicable requirements of p;)
Paragraphs 4.3, 4.4, 4.5, 4.6.1, 4.6.4, 5.1, 5.2 and 6.1 of that standard.
Rev. No.
6_
Page 18.of 167
NEW YORK POWER $UTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVIQJ TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX A O
Pum) Relief Requests NOTE P10 This relief request has been withdrawn.
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Rev. No.
6 Page
- 19. of 167 4
NEW YORK POWER AUTilORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT Il{DIRVICE TPSTIlfG PROQRAM FOR PUMPS AND VALVER APPENDIX A Pump Rolinf Requents NOTE P11.
SYSTEM:
Core Spray PUMPS:
14P-1A,B CLASS:
2 FUNCTION:
Pump cooling water from the suppression pool to the reactor in the event of a LOCA.
TEST REQUIREMENT:
Por IWP-4120, the full-scale range of the pump inlet pressure instrument shall be three times the reference value or less.
BASIS FOR RELIEF:
The installed core spray pump inlet pressure indicators are designed to provide adequate inlet pressure indication during all expected operating conditions.
The full-scale range, 60 psig, is suf ficient for a post-accident condition when the torus is at the maximum accident' pressure.
- This, O
- however, exceeds the range limit for inlet pressure under the test condition (approx.
5 psig).
Suction pressure measurements serve two functions.
First, they provide assurance that the prescribed NPSH requirements for the pumps are met.
Secondly, they are used for determining pump diffcrential,Jessure.
The installed gauges are calibrated to within i2%
accuracy (FS),
thus the maximum variation in measured suction pressure due to inaccuracy would be 11.2 psi.
This is considered to be suitable f or determining that adequate NPSil is available for proper-pump operation.
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Page 20 of 167 -
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NEW YORK POWER AUTHORITY JAMES A.-FITZPATRICK' NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES
^ " " " " ^
O Pump Ralief Recuests NOTE Pil (cont.)
Pump discharge pressure during -testing is-typically 300 psig. which results in a calculated differential pressure of'approximately-295 ps3d.
Given - the accuracy of the discharge - pressure -
measurement ' of ' 2.5. psi, the resultant maximum variation in calculated differential pressure will be 3.7 psi. or
- 1. 2 5%.-
This is. consistent with the requirements of Table IWP-4110-1.- that only requires that instrument accuracy _be-better than-2% of full scale.
ALTERNATE TESTING:
Use existing vendor supplied inlet pressure in_dicators (as described above) for --testing of.
the core spray pumps. (See-Relief Request NOTE.
P16) 1 O
1
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3-Page 21 of 167
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NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX A f%
Pump Relief Reauests N_OTE P12 SYSTEM:
PUMPS:
11P-2 A, B
CLASS:
2 FUNCTION:
These pumps inject borated water into the reactor vessel as an alternate means for negative reactivity addition and reactor shutdown.
TEST REQUIREMENT:
Per IWP-4120, the full-scale range of the pump inlet pressure instrument shall be three times the reference value or less.
BASIS FOR RELIEF:
The pump in.1.et pressure indicators are' designed to provide adequate _ inlet pressure indication when pumping from the SLC storage tank.
These instruments have a range of 0-30 psig and are-(
calibrated to within 2% accuracy.
Thus, there t
is a potential for a variation of 0.6 psi due to instrument accuracy.
Since the SLC pumps are of the reciprocating positive displacement type, pump flowrate is not sensitive to pump differential pressure.
In addition, the typical pump inlet pressure (approx. 1 psi) is less than 0.1% of the developed differential pressure (1279 psid).
A variation of 0.6 psi in the inlet pressure will not significantly affect pump parameters.
ALTERNATE TESTING:
Use existing vendor supplied inlet pressure indicators for the SLC pump flow test.
(See Relief Request NOTE P16)
O Rev. No.
3 Page
?a of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT f
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX A g
Putnp Relief Recuests NOTE P13 SYSTEM:
PUMPS:
11P-2A,B CLASS:
2 FUNCTION:
These pumps inject borated water into the reactor vessel as an alternate means for negative reactivity addition and reactor shutdown.
TEST REQUIREMENT:
Per IWP-4520(b),
vibration measurement instruments shall have a frequency response range from one half minimum to at least maximum pump shaft rotational speed.
BASIS FOR RELIEF:
The nominal speed of the SLC pumps is 520 RPM which correlates to a rotational frequency of 8.67 Hz.
IWP-4 52 0 (b) requires vibration instrumentation be accurate to 5% full scale p) over a range of 4.33-8.67 Hz for these pumps.
The Authority has purchased new instruments for use during surveillance testing with cercified accuracy of 5% full scale over a range of 5-2000 Hz.
Calibration is verified accurate using a system test methodology over a range of 6-500 Hz in units of displacement (Mils Pk-Pk) anil f-1000 Hz in units of both velocity (IPS Pk) and acceleration (g's Pk).
The system test verification is limited by the capability of the calibration shaker system to accurately sustain vibration at meaningful amplitudes outside the tested frequencies.
The certified calibration 5% range is arrived at through addition of individual transducer and meter inaccuracies over the stated frequency range.
The instrument lower frequency response limits are a result of high-pass filters installed to eliminate low-frequency elements associated with the input signal from entering the process of single and double integration.
These filters prevent low frequency electronic noise in from distorting readings in the resultant units (IPS, 3
'")
Mils).
As a side effect, any actual vibration occurring at low frequencies is filtered out.
This is a necessary trade-off, as 1 mv of Rev. No.
6 Page _2.2_. of 167 l
NEW YORK POWER AUTHORITY JAMES A.-FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX A O
Pumo Relief Recuests NOTE P13 (cont.)
electronic noise at 4.33 Hz translates to = 20.86 Mils Pk-Pk with the accelerometer used with these instruments.
The Authority-has ; extensively researched this issue concerning Code compliance and intent, and j
i strongly feels that, for these pumps, procurement-of equipment _ capable of meeting the Code re, quired accuracy is impractical with-little--or no benefit.
Instrumentation capable of meeting the Code for_these pumps is cumbersome', difficult to operate, prone to human error, costly to purchase
.i and expensive to calibrate.
_The number of vendors that suppl'y instrumentation accurate at-tho e frequencies is limited, and there are even fewer qualified vendors capable of performing the; j
required calibration services.
Most standard j
qualified calibration __ laboratories provide calibration services only to a minimum of 10:Hz..
In addition t_o the impracticability of procuring O
the instruments, - the Authority feels that the.
Instruments presently used are adequate to assess the condition of these. pumps.
The manufacturer of these pumps, Union Pump.Co., Battle LCreek, Michigan, has stated that these. pumps, beingJof a
simplified. reciprocating design,- have 'no failure mechanisms that would be revealed at.
frequencies less'than shaft' speed.
Union Pump-has stated that all failure modes of this pump resulting in increasing vibration; will be.
manifested at shaft speed frequency or harmonics thereof.
In lightLof the information provided by Union Pump, monitoring sub-synchronous vibration for these pumps is.not-needed,. but super-synchronous readings will-_ provide-meaningful
~f 2 imminent-information in the detection o
machinery faults.
A search of the INPO NPRDS database has revealed only one failure reported for pumps offthis or similar
. design.-whose discovery mentioned increased vibration levels.
The cited'cause of1.
the failure was improper end play set leading to'-
bearing-failure.
Failures of this type would normally. be detected at-running;:(shaf t); speed-O frequency,. harmonics ' thereof,. or non-harmonic-M super-synchronous _ bearing defect: frequencies.
Rev. No.
6 Page,_2.i_ ofl 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING VROGRAM FOR PUMPS AND VALVES APPENDIX A V
Puno Relief Pecuests NOTE P13 (cont._1 It should also be noted that these are standby pumps which are normally operated only during pump and valve testing.
In the unlikely event this system is required to fulfill its design function, only one of the two redundant pumps need operate for a period of 23 to 125 minutes.
In addition to vibration monitoring performed for the IST Program, these pumps are included in the Authority's Rotating Equipment Monitoring Program. Vibration spectral data is periodically collected and analyzed for the pump and gear motors in addition to those required by the Code.
The equipment used by the Rotating Equipment Program is certified accurate i
5%
over a
frequency range 5-2000 Hz and is also limited by high-pass integrating filters, but allows for discrete frequency analysis and trending using FFTs.
Vendor specifications state that this equipment should provide fairly accurate data down to 2 Hz in units of acceleration (g's Pk) p (using the raw transducer signal - negating the Q
need for integration).
Study of low-frequency spectra taken in g's Pk with these instruments has revealed no distinct su,b-synchronous peaks above the noise floor acceleration signal.
In light of their rigorous testing and limited design run time, it is not likely that a minor mechanical fault would prevent these pumps from fulfilling their design function and unlikely that development of a major fault would go unnoticed.
In conclusion, the Authority feels that the use of high quality, commercially available vibration monitoring equipment calibrated to be at least accurate 5% full scale over a range of 6 Hz to 8.67 Hz) is an 500 Hz (nominal shaft speed appropriate method of monitoring the mechanical condition of the SLC pumps.'
Such instruments will provide meaningful and useful measurements over the frequency range in which pump faults will develop and manifest.
This meets the intent of the Code and certainly will neither adversely".
impact system reliability nor the health and f w).
safety of the general public.
In addition, it i
relieves the Authority of the burden and expense involved in the procurement, calibration, I
Rev. No.
6 Page 25 o f _.117_,_
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMP 8 AND VALVE 8 I
APPENDIX A Pump Re1lef Recues,t_s NOTE P13 (cont.)
training and certification associated with obtaining new equipment which is simply not needed to adequately assess the condition of the subject pumps.
ALTERNATE TESTING:
The vibration measurements will be taken using instrumentation accurate 5% full scale over a frequency range of 6 Hz to 500 Hz.
The data will be evaluated per IWP-3200.
O s
O Rev. No-5 Page 26 of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX A
\\s/
Pump Relief Recuests NOTE P14 SYSTEMS:
Various PUMPS:
All pumps in Program CLASS:
2 and 3 FUNCTION:
Various TEST REQUIREMENT:
IWP-3300 and IWP-4310 requires that the temperature of all centrifugal pump bearings outside the main flowpath and of the main shaft bearings of reciprocating pumps shall be measured at points selected to be responsive to changes in the temperature-of the bearings.
BASIS FOR RELIEF:
The data associated with bearing temperatures taken at one-year intervals provides little statistical basis f or determining the incremental t'")%
degradation of a
bearing or any meaningful y,
trending information or correlation.
In many cases pump bearings are water-cooled and thus, bearing _ temperature is a function of the temperature of the cooling medium, which can vary considerably.
' ibration measurements are a significantly more reliable indication of pump bearing degradation than are temperature measurements.
All pumps in the program are subjected to vibration measurements in accordance with IWP-4500.
Although excessive bearing temperature is an indication of an imminent or existing bearing
- failure, it is highly unlikely that such a condition would go unnoticed during routine surveillance testing since it would manifest itself in other obvious indications such as audible noise, unusual vibration, increased motor current, etc.
[v Page 27_ of 167 Rev. No.
3
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES 4
APPENDIX A b(%
Pump Relief Reauests NOTE P14 (cont.)
Any potential gain from taking bearing temperature measurements, which in most cases would be done locally using
. portable instrumentation, cannot offset the cost in terms of dilution of operator effort, distraction of operators from other primary duties, excessive operating periods for standby
- pumps, and unnecessary personnel radiation exposure.
ALTERNATE TESTING:
Vibration monitoring will be performed in accordance with IWP-4500.
Such vibration monitoring will provide adequate monitoring and evaluation of the material condition of the pump bearings.
O Rev. No.
6 Page 28 of 167
NEW YORK POWER AUTHORITY JAMES A.-FITZPATRICK NUCLEAR POWER PLANT.
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX A C\\
's i
Pump Relief Recuests NOTE P15 This relief request has been withdrawn.
4 i
4 IC T
Rev. No.
6 Page 29 of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCI EAR POWER PLANT INSERVICE TFeSTING PROGRAM FOR PUMPS AND VALVES APPENDIX A
(-(
Pump Relief Requests NOTE P16 SYSTEMS:
Various PUMPS:
Various CLASS:
Various FUNCTION:
This is a generic relief request.
TEST REQUIREMENT:
Per IWP-4210, if the presence or absence of liquid.in a gage line could produce a difference-of more than 0.25% in the indicated value of the measured pressure, means shall be provided to ensure or determine the presence or absence of liquid as required for the st tic correction used.
BASIS FOR RELIEF:
When this requirement is applied to the measurement of pump suction pressure where
/3 measured pressures are at relative low levels, (j
the 0.25%
limit is overly restrictive and oftentimes results in complicated venting procedures and unnecessary health physics risks associated with handling and disposal
.of radioactive contaminated water with no commensurate gain or improvement
-of test reliability.-
Normally, the only quantitative use of suction pressure measurements, where significant accuracy is required, is in determining pump differential pressure or head.
In most cases the pump discharge pressure exceeds the suction pressure by at least a factor of.five (5).
This being the-a 0.25% error introduced into..the suction
- case, pressure measurement results in an error of 0.05%.
in the differential pressure calculation.
This is insignificant in light of the potential. 6%
error allowance applied to both the suction and discharge pressure instruments (Ref IWP-4110).
13 V
Page 30 Of 167 Rev. No.
3
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUC, LEAR POWER _ PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX A r
's Pump Relief Recuests NOTE P16 (cont.1 ALTERNATE TESTING:
If the presence or absence of liquid in'a gage line used for sensing pump suction pressure could produce a difference of more than 0.25% in the calculated value of the pump differential pressure, means shall be provided to ensure or determine the presence or absence of liquid as required for the static correction used.
l l
O Rev. No.
3 Page 31 Of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPB AND VALVES APPENDIX'A O
Pump Relief Requests NOTE P17 SYSTEMS:
Various PUMPS:
This is a generic relief request.
CLASS:
Various k.
FUNCTION:
Various TEST REQUIREMENT:
IWP-4120 requires that the full-scale range of each instrument shall be three time the reference value or less.
^
BASIS FOR RELIEF:
In several instances instruments used to measure pump parameters 4qe digital readouts.
Although-these instruments are highly accurate and suitable f or use, they are virtually unlimited in range and thus do not meet the bode requirement.
ASME/ ANSI OM-1987, Part 6,
Paragraph 4.6.1.2 O
allows the use of digital instruments with limiting provisions.
ALTERNATE TESTING:
Digital instruments may be used during pump testing provided that the reference value shall not exceed 70% of the calibrated range of the instrument.
Digital instruments shall have an accuracy of 12 percent
( 5 percent for vibration) over the calibrated range of the instrument.
N O
Rev. No.
3 Page 32 Of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWEn PLANT DiSERVICE TESTING PROGRAM FOR PUMP 8 AND VALVES l
" " " " " ^
O Pump Relief Requests NOTE P18 This relief request has been withdrawn.
O O
Page 33 of 167 Rev. No.
5 e
NEW YORK POWER AUTHORITY JAMES A..FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVE 8 O
APPENDIX B VALVE TESTING PROGRAM O
O Page 34 of 167 Rev. No. 1
HEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B i\\
VALVE TESTING PROGRAM Table of Contents Valve Table Explanation.......................................
38 Valve Symbols.................................................
41 Valve Types................................................. 41 Valve Actuator Types........................................
41 Test Method.................................................
42 Test Frequency..............................................
42 Valve Table...................................................
43 Cold Shutdown Justification..................................
108 CS1:
Reactor Water Recirculation..........................
108 CS2:
Residual Heat Removal................................
108 CS3:
Residual Heat Removal................................
109 CS4:
Rea; tor Building Closed Loop Cooling.................
109 CSS:
Reactor Building Closed Loop Cooling.................
109 CS6:
HPCI.........................e.......................
110
/
CS7:
Control Rod Drive Hydraulics.........................
110
(
CS8:
DELETED............................................. 110 CS9:
Feedwater............................................
110 CS10: Containment Vent and Purge...........................
111 CS11:
DELETED..............................................
111 CS12: Main Steam...........................................
111 CS13: Main Steam...........................................
111 CS14: Reactor Building Closed Loop Cooling.................
112 CS15: Reactor Building Closed Loop Cooling.................
112 CS16: High Pressure Coolant Injection......................
112 CS17: Reactor Coolant Isolation Cooling....................
113 CS18: Reactor Coolant Isolation Cooling....................
113 RELIEF REQUESTS..............................................
114 NOTE V1:
Reactor Water Recirculation......................
114 NOTE V2:
Control Rod Drive................................
115 NOTE V3:
WITHDRAWN........................................
117 NOTE V4:
WITHDRAWN........................................
117 NOTE V5:
Standby Liquid Control...........................
118 NOTE V6:
Reactor Core Isolation Cooling...................
119 NOTE V7:
WITHDRAWN........................................
121 NOTE V8:
WITHDRAWN........................................
121 NOTE V9:
HPCI.............................................
122 NOTE V10:
WITHDRAWN........................................
123
(~N NOTE Vil: WITHDRAWN........................................
123
.......... 124
(,)
NOTE V12:
Feedwater.............................
NOTE V13:
WITHDRAWN........................................
125 i
i l
Page 35 of 167 Rev. No.
6
NEW YORK POWER AUTHORITY JAMES A.-FITZPATRICK NUCLEAR POWER-PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPEN. DIX B VALVE TESTING PROGRAM Table of Contents Relief Requests (Cont'd)
NOTE V14: Instrument Air...................................
126 NOTE V15:
WITHDRAWN........................................
127 NOTE V16:
WITHDRAWN........................................
127 NOTE V17:
HPCI.............................................
128 NOTE V18:
WITHDRAWN........................................
130 E-NOTE V19: Containment Isolation............................
131 NOTE V20:
WITHDRAWN.................,,.......................
133 NOTE V21:
WITHDRAWN.................'.......................
133 NOTE V22:
HPCI.............................................
134 NOTE V23:
WITHDRAWN........................................
135 NOTE V24:
WITHDRAWN........................................
135 NOTE V25:
WITHDRAWN........................................
135 NOTE V26:
WITHDRAWN........................................
135 NOTE V27: ADS and Main Steam...............................
136 NOTE V28: Excess Flow Checks...............................
138 NOTE V29: Fast Acting Valves...............................
140 0
NOTE V30:
WITHDRAWN........................................
142 NOTE V31:
WITHDRAWN........................................
142 NOTE V32:
WITHDRANN........................................
142 NOTE V33:
WITHDRAWN..................................,
.... 142 NOTE V34:
HPCI.............................................
143 NOTE V35:
HPCI.............................................
145 NOTE V36:
WITHDRAWN........................................
146 NOTE V37:
WITHDRAWN........................................
146 NOTE V38:
WITHDRAWN........................................
146 NOTE V39:
WITHDRAWN........................................
146 NOTE V40:
WITHDRAWN........................................
146 NOTE V41:
WITHDRAWN........................................
146 NOTE V42:
WITHDRAWN........................................
146 NOTE V43:
WITHDRAWN........................................
146 NOTE V44:
WITHDRAWN............................
........... 146 NOTE V45:
WITHDRAWN........................................
146 NOTE V46: Containment Isolation Valves.....................
147 NOTE V47: High Pressure Coolant Injection..................
149 NOTE V48: Containment Atmospheric Dilution.................
150 NOTE V49: Emergency Service Water..........................
151 NOTE V50: Traversing Incore Probe..........................
152 NOTE V51: Generic - Cold Shutdown Testing..................
153 NOTE V52:
WITHDRAWN........................................
155 NOTE V53:
WITHDRAWN........................................
155 0
Rev. No.
6 Page 36 of 167
NEW YORK POWER AUTHORITY
-JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVE 8 APPENDIX B f^\\.
U VALVE TESTING PROGRAM l
Table of Contents Relief Requests (Cont'd)
NOTE V54:
HPCI.............................................
156 NOTE V55: Core Spray.......................................
157 N'TE V56: Residual Heat Removal............................
158 NOTE V57: Core Spray.......................................
159 NOTE V58: Automatic Depressurization'.......................
161 NOTE V59: Main Steam.......................................
162 NOTE V60: Residual Heat Removal............................
163 l
i i
{j, N
\\
\\
I 1
l-i I
l
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(L (._)
page 37 of 167 Rev. No.
6 i
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM F'OR PUMPS AND VALVE 8 l
l APPENDIX B O
v VALVE TABLE EXPLANATION Summary of Information Provided The Valve Table is sorted by system number then drawing number and provides the following information:
Individual valve identifier Drawing coordinatesSection XI ISI Classification Section XI IWV category Nominal size Valve type Actuator type (f
Section XI test required Relief request (RR)/ cold shutdown (CS) justification Alternate test Remarks O
l l
Page 38 of 167 Rev. No.
3
NEW YORK POWER AbTHORITY JAMES A.
FITZPATRICK NUCLEAR POWTR PLANT IESERVICE TESTING PROGRAM FOR PUMP 8 JWD VALVES APPENDIX B
,e
(
Cold Shutdown Justification Notes CSXX refer to cold shutdown justifications which provide the justification f or testing af fected components at cold shutdown instead of every three months.
(Refer to Relief Request NOTE V51)
The Cold Shutdown Justifications provide the following information:
System Individual valve identifier Section XI categcry Safety function Justification n
/'N
'%.)
Page 79 of 167 Rev. No.
3
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT YNSERVICE TESTING PROGRAM-FOR PUMPS AND VALVES APPENDIX B O
valve Relief Requests Notes VXX refer to Relief Requests for the Valve Testing Program. The valve Relief Requests provide the following information:
System Individual valve identifier Section XI category ISI Classification Safety Function Test requirement from w'lich relief is requested Basis for relief Alternate testing O
1 l
9 i
Rev. No.
3 Page 40 of _167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSE3VICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B VALVE SYMBOLS Valve Types 3W Three-way valve AN Angle valve BP Butterfly valve BK Ball check BL Ball valve CK Swing check GA Gate valve GL Globe valve LK Lift check NK Non-return check PG Plug valve RL Relief valve SC Stop check SK Spring check TK Testable check WK Wafer Check XP Explosive valve O
Valve Actuator Types AO Air operator EH Electro-hydraulic HO Hydraulic operator MA Manual operator Mo Motor-eperator PA Pilot actuated SA Self actuated SO Solenoid operator SP Spring operator SQ Squib actuator O
Rev. No.
5 Page 41 of 167
- NEW YORK POWER ~ AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER-PLANT..
~
IN8ERVICE TESTING PROGRAM'FOR PUMPS AND VALVES j
APPENDIX B' O
Test Method
~
- TS Stroke time measured during valve exercising IWV-3413 TM Stroke time measured during valve exercising-IWV-3413.
FS Full stroke exercise IWV-3412 FC Fail-safe to close position IWV-3415 FO Fail-safe to open position
~ IWV-3415 PE Partial stroke exercise IWV-3412 LK Leak test
.IWV-3420-LJ-Leak test per 10CFR50 Appendix J Type C RL Relief valve test IWV-3512 i
PI Remote position indication verification IWV-3300 1
DA Disassemble and inspect per relief request
- SP Special test (Refer to relief request)
XP Explosively actuated-valve test IWV-3610 FF Forward flow check valve test IWV-3522 RF Check valve closure test IWV-3522 PF Partial flow check valve test MS Manual. stroke test (non-intrusive)
IWV-3522 ME Exercising check valves using manual operator IWV-3522 Test Freauency
- 2. Years
- 1_
Quarterly -Special Test per Relief Request
-2 Cold Shutdtwn
-6
-3 Refueling
--7
. Monthly
-4 IWV-3511/3610
- t O
Rev.-No.
5 Page _ R _,-of 167 m
_ __ _ _ _ _ _. _ _ _ _ _ ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _,- _ _
r
.m
)
t 3
I
~d G/ '
G')
NEW YORK P O ld E R AUTNORiTY JAMES A.
FIT 2 PATRICK WUCLEAR POWER PLANT INSERVICE TESTING PROGRAN FOR PUMPS AND WALVES VALVE TABLE 9 tawing:'FM-48A SYSTEM: Starxty Gas Treatment - SYSTEM ID: 01-125 VALVE ID DWG CO-DR CLASS VALVE CATEGORY SIZE (IN)
VALVE TYPE ACTUATOR TYPE SECT. XI TEff RR / CS ALTERNATE TEST REMARKS 01-125MOV-100A C-6 2.
8 4.00 BF Mo TM-1 PI-3 01-125MOV-100s F-6 2
5 4.00 BF Mo TM-1 PI-3 01-125MOV-11 G-8 2
B 24.00 SF MO TM-1 PI-3 01-125MOV-12 F-8 2
8 24.00 BF MO TM-1 PI-3 01-125MOV-14A D-7 2
B 24.00 SF MO TM-1 PI-3 01-125MOV-14B E-7 2
8 24.00 BF Mo TM-1 P!-3 01-125MOV-15A D-3 2
8 24.00 er MO TM-1 PI-3 01-125Mov-158 F-3 2
8 24.00 BF MO TM-1 PI-3 PAGE 43 0F 167 REV. No: 5
f) f%
()'
\\.
\\
i NEW Y0RK POWER AUTM0R17Y JAMES A.
FIT 2 PATRICK NUCLEAR POWER PLAN 7 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES VALVE TA8LE SYSTEX: Automatic Depressuritation System - SYSTEM 10: 02 DRAWING: FM-294 -
VALVE ID DWG Co-OR CLASS VALVE CATEGORT SIZE (18!) VALVE TYPE ACTUATOR TYPE SECT. RI TEST RR / CS ALTERNATE TEST REMARKS 02RV-1 H-7 2
C 3.00 CK SA MS-2 M8 02RV-10 G-7 2
C 3.00 CK SA MS-2 M8 02RV-11 G-7 2
C 3.00 CK SA MS-2 M8 02Ri-2 H-7 2
C 3.00 tK SA MS-2 M8 023-3 H-7 2
C 3.00 CK SA MS-2 M8 02RV-4 H-7 2
C 3.00 CK SA A
M8 I
02RV-5 H-7 2
C 3.00 CK SA MS-2 M5 02RV-6 H-7 2
C 3.00 CK SA MS-2 M8 02RV-7 H-7 2
C 3.00 CK SA nS-2 M8 02RV-71A G-6 1
BC 6.00 RL SA A0 FS-1 V27 FS-3 VALVE SETP0fMT-1140 PStG kL-4
'02RV-715 G-6 1
BC 6.00 RL SA A0 FS-1 V27 FS-3 YALVE SETPolWT-1140 PSIG RL-4 02RV-71C G-6 1
BC 6.00 RL SA A0 FS-1 V27 FS-3 VALVE SETPOINT-1140 PSIG RL-4 l
02RV-71D F-6 1
SC 6.00 RL SA A0 FS-1 V27 FS-3 VALVE SETPOINT-1105 PSIG RL-4 i
j.
l
\\
4
(
REV. NO: 6 PAGE 44 0F 167.
)
l t
l l
i.
.L
/.m m
.O) w.)
C NEW YORK POWER AUTHORITY JAMES A.
F1YZPATRICK NUCLEAR POWER PLANT f
INSERVICE TESTING PROGRAM FOR PUMPS AND VAtVES VALVE TABLE j
l DRAWING: FM-29A l
l STSTEM: Automatic Depressurization System - SYSTEM ID: 02 i
l l
VALVE ID LWG CO-OR CLASS VALVE CATECORY SIZE (IN)
VALVE TYPE ACTUATOR TTPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 02RV-71E F-7 1
BC 6.00 RL SA A0 FS-1 V27 FS-3 VALVE SETPo!WT-1105 PSIG RL-4 02RV-71F F-7 1
BC 6.00 RL SA A0 FS-1 V27 FS-3 VALVE SETPOIRT.1140 PSIG RL-4 02RV-71G G-7 1
BC 6.00 RL SA AO FS-3 V27 FS-3 VALVE SETPolti-1143 PSIG RL-4 02RV-71H G-7 1
BC 6.00 RL SA A0 FS-1 V27 FS-3 VALVE SETPOINT 1140 PSIL RL-4 l
02RV-71J G7 1
BC 6.00 RL SA A0 FS-1 V27 FS-3 VALVE SETPOINT-1140 PSIG l
RL-4 02RV-71K G-6 1
BC 6.00 RL SA A0 FS-1 V27 FS-3 VALVE SETPOINT-1090 PSIG RL-4 02RV-71L C-7 1
BC 6.00 RL SA -AO FS-1 V27 FS-3 VALVE SETPO!NT-1090 PSIG RL-4 02RV-8 G-7 2
C 3.00 CK SA MS-2 V58 02RV-9 G-7 2
C 3.00 CK SA MS-2 V58 02VB-1 H-8 2
C 10.00 CK SA MS-2 V58 02VB-10 G-8 2
C 10.00 CK SA MS-2 V58 PAGE 45 or 167 REV. No: 6
NEW YORK POWER AUTNORITY JANES A-FITZPATRICK NUCLEAR POWER PLANT
! L4 SERVICE TESTING PROGRAM F0R PUMPS AND VALVES VALVE TABLE DRAWING: FM-29A SYSTEM: Automatic Depressurization system - SYSTEM ID: 02 VALVE ID dug Co OR CLASS VALVE CATEGORT S!ZE (!N)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS
~~~-------------- - - ------
02V8-11 G-8 2
C 10.00 CK SA MS-2 V58 02V8-2 N-8 2
C 10.00 CK SA MS-2 V58 02vs-3 H8 2
C 10 00 CK SA MS-2 V58 10.00 CK SA MS-2 V58 02Vs-4 H-8 2
C 02V8-5 H-8 2
C 10.00 CK SA MS-2 V58 02VB-6 H8 2
C 10.00 CK SA MS-2 V58 02VB-7 H-8 2
C 10.00 CK SA MS-2 V58 02VB 8 G-8 2
C 10.00 CK SA MS-2 V58 02V8 9 G-8 2
C 10.00 CK SA MS 2 V58 PAGE 46 0F 167 REV 20: 6
_.,___.__,_.._..__._.i..-
NEW YORK POWNR AUTHORITY JAMES A.
FIT 2 PATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES VALVE TABLE DRAWikG: FM-26A SYSTEM: Reactor Water Recirculation - SYSTEM ID: 02-2 VALVE ID DWG Co-OR CLASS VALVE CATEGORT SIZE (IN)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 02-2A0V-39 E-4 1
A 0.75 GA A0 TM-1 FC-1 PI-3 LJ-3 02-2ADV 40 F-2 1
A 0.75 GA A0 M
FC-1 PI-3 LJ-3 02-2EFV-PS-128A B-6 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02-2EFV-PS-1288 B-6 1
AC 1.00 BK SA LK-1 v28 IK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02-2EFV-PT-24A C-3 1
AC 1.00 SK SA LK-1 v28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02-2EFV-PT-248 C-5 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02-2EFV-PT-25A C-3 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOL ATES ON EXCESS FLOW LK-3 02-2EFV-PT-258 C-8 1
AC 1.00 BK SA LK-1 v23 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02-2RWR-13A C-3 1
AC 0.75 SK SA RF-1 V1 LJ-3 LJ-3 PAGE 47 0F 167 REY. K0: 6 i
N NEW Y0RK POWER AUTH0RITY JAMES A
FITZPATRICK NUCLEAR POWER PLAN 7 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES VALVE iABLE DRAWING: FM-264 SYSTEM: Reactor Water Recirculation - SYSTEM 10: 02-2 VALVE ID DWG Co-OR CLASS VALVE CATEGORY SIZE (!N)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTE*NATE TEST REMARKS
~~~--------- ----~=---
..--..-..--.----.....--. ------------- ------------ ----------- ------------------------------------- -----------------------------~~----- -- ----
02-2RWR-138 C-8 1
AC 0.75 SK SA Rf-1 V1 LJ-3 LJ-3 02-2SOV-001 0-3 1
A 0.75 Gt 50 TM-1 V29 FC-1 PI-3 LJ-3 02-2SOV-002 D-8 1
A 0.75 CL So TM-1 V29 FC-1 PI-3 LJ-3 022EFV1DPT111A E-3 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 022EFV1DPT111B E-8 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW tK-3 022EFV1FT110A F-3 1
AC 1.00 SK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 022EFV1FT110C 0-3 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLCW LK-3 022EFV" - 110E F-7 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 022EFv1FT110G D-8 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 PAGE 48 0F 167 REV. :0: 5
,~
.m Gr NEW Y0RK POWER AUTH0RITY JAMES A.
F!T2 PATRICK NOCLEAR POWFR PLA4T INSERV1CE TESTING PR0 CRAM F0R PUMPS AND VALVES VALVE TABLE SYSTEn: Reactor Water Recirculation - SYSTEM ID: 02-2 DRAWING: FM-26A
-VAtVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IM)
VALVE TYPE ACTUATnR TYPE SECT. XI TEST RR / CS ALTEENATE TEST REMARKS
'022EFV2DPT111A E-3 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 022EFV2DPT1119 E-8 1
AC 1.00 SK SA LK-1 V28 LK-3 VALVC ISOLATES ON EXCESS FLOW LK-3 022EFv2FT110A F-3 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 022EFV2FT110C D-3 1
AC 1.00 BK SA LK-1 v28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 022EFY2FT110E F-8 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 022EFV2FT110G 0-8 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02mV-53A C-3 1
B 28.00 GA Mo TM-2 CS1 P1-3 02MOV-53B C-7 1
B 28.00 CA Mo TM CSI PI-3 REV. No: 5 PAGE 49 0F 167 '
j.
NEW YORK POWER -AUTHORITY 4
JAMES A.-
FIT 2PATRfCK NUCLEAR POWER PLANT
-1NSERVICE TESTING PR0 GRAM -FOR PUMPS 'AND VALVES VALVE TA8LE i
' DRAWING: FM-47A
).
SYSTEM: ' Nuclear Boiter vesset Instruments - SYSTEM 10: 02-3 t
VALVE 10 DWG Co-OR, CLASS VALVE CATEGORY SIZE'(IN)
VALVE TYPE ACTUATOR TYPE-SECT. XI TEST RR / CS ALTERNATE TEST REMARKS-02-3EFV-11 F.7 1
- VALVE ISOLATES ON EXCESS FLOW LK-3 02-3EFV 13A E-7 1
AC.
1.00 8K SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 s
02.tEFV-138.
E-4 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK 3 02 3EFV-15A E-7 1
AC 1.00
.8K SA LK-1 V28 LK-3 VALVE IS0tATES ON EXCESS FLOW LK-3
'02 3EFV-158 E-4 1
AC 1.00
'BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 i
02-3EFV-15N 87 1
AC 1.00 8K SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW f,
LK-3 02-3EFV-17A D-7 1
AC 1.00 SK SA LK.1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 1
i 02-3EFV-178 D4 1
AC-1.00 8K SA LK-1 V28 LK-3
' VALVE ISOLATES ON EXCESS FLOW '
LK-3 02-3EFV-19A D-7 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02-3EFV-198 D-4 1
AC.
1.00 8K SA LK.1 V28
-LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3
'PAGE 50 0F 167 REV. NO: 5 i
o r
z
O NEW Y0RK POWER AUTNORITY JAMES A.
F1TZPATRICK NUCLEAR POWER PLANT INSERVICE TEST ING PROGRAM FOR PUMPS AND VALVES VALVE TABLE DRAWING: FM-47A SYSTEM: Nuclear Boiler Vessel Instrunents - SYSTEM 10: 02-3 VALVE ID DWG Co-OR CLASS VALVE CATEGORT SIZE (lu)
VALVE TYPE ACTUATOP TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS.
---~~--------------~~-------*-*--~~~~~-----~~~~-***-------
02-3EFV-21A H-5 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES Old EXCESS FLOW LK-3 02-3EFV-218 C-7 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 VALVE ISOLATES UM EXCESS FLOW 02 3EFv-21C C-4 1
AC 1.00 BK SA LK-1 V28 LK-3 LK-3 02-3EFV-210 H-4 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02-3EFV-23 F-7 1
AC 1.00 BK SA LK-1 v28 LK-3 VALVE ISOLATES ON EXCESS FLOW l
LK-3 VALVE ISOLATES ON EXCCSS FLOW 02-3EFV-23A H-5 1
AC 1.00 BK SA LK-1 V28 LK-3 LK-3 02-3EFV-238 0-7 1
AC 1.00 8K SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02-3EFV-23C D-4 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02-3EFV-23D H-4 1
AC 1.00 SK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 I
02-3EFV-25 C-7 1
AC 1.00 8K SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 PACE 51 0F 167 REV. No: 5
._.m.,
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NEW YORK POWER AUTHORITY T-JANES A.
FI7ZPATRICK NUCLEAR POWER PLANT i-IN$ERVICE TEST 1NG PR0 GRAM FOR PUMPS AND VALVES
)
VALVE TABLE
. SYSTEn: Nuclear Boiler vesset 'Instrunents - SYSTEM 10: 02 3 ORAWING:'FM-474
- VALVE ID DWG CO-OR CLASS - VALVE CATEGORY SIZE (IN)- VALVE TYPE. ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS
............................................................................................................................................................................3 02-3EFV-31A H-5 1
AC 1.00 BK SA LK 1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW,.
LK-3 02-3EFV-318 H-5 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW-LK-3 02-3EFV-31C H-5 1
.LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW-~
[
. (K-3 v
02-3EFV-310 M-5 1
'1.00 BK SA LK-1 v28 LK-3 VALVE ISOLATES ON EXCESS FLOW-LK-3 i
02-3EFV-31E D-7 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02-3EFV-31F H-5 1
AC -
1.00' BK..
SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02-3EFV-31G
'H-5 1
. AC '
't.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 3EFV-31H H-5 '
'LK-3 VALVE ISOLATES ON EXCESS FLOW:
LK-3
'02-3EFV-31J M-4 1'
.1.00 BK SA LK-1 V28 LK-3
. VALVE ISOLATES ON EXCESS FLOW
. LK-3 02-3EFV-31K N-4 1
AC 1.00 BK SA LK-1 V28 LK-3' VALVE ISOLATES ON EXCESS FLOW LK-3 KEV. Ko: 5' PAGE 52 0F'167:
- y i
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NEW Y0RK POuER AUTH0R1TY JAMES A.
F!T2 PATRICK NUCLEAR POWER PLANT INSERVICE TE5 TING PROGRAM FOR PUMPS AND VALVES VALVF TABLE DRAWING: FM-47A SYSTEM: Nuclear Boiler vessel Instrunents - SYSTEM 10: 02-3 VALVE 10 DWG CO OR CLASS VALVE CATEGORT SIZE (IM)
VALVE TYPE ACTUATOR TYPE SECT. XI f^ST RR / CS ALTERNATE TEST REMARKS
*----- --------------------------~~-
~~ --------------------- 28 02-3EFV-31L H-4 1
LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02-3EFV 31M D4 1
AC 1 00 BK SA LK 1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02-3EFV-31M H-4 1
AC 1.00 SK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCU-5 FLOW LK-3 02-3EFV-31P H4 1
AC 1 00 SK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02-3EFV-31R H-4 1
AC 1.00 SK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02 3EFV-31S H-4 1
Af.
1.00 SK SA LK-1 v28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 02-3EFV-33 8-4 1
AC 1.00 SK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 PAGE 53 0F 167 REV no: 5 l
NEW YORK POWEC AUTNORITY JAMES A-F17ZPATRICK NOCLEAR POWER PLANT IN5ERVICE TESTING PROGRAM F0R PUMPS AND WALWE5 VALVE YABLE DRAWING: FM-2TB SYSTER: Control Rod Drive - SYSTEM ID: 03 VALVE ID dug CO-OR CLASS VALVE CATEGORY
$1ZE (IN)
VAtvE TYPE ACTUATOR T?FE SECT. XI TEST RR / CS ALTE.NATE TEST REMARKS
--~~~~-----------~~~
.----.....~. ---.---.--------.------.----------------- ------------------------------ --------------------------------------- -----------~~------~~~-
03A0V-126 C-4 2
8 1.00 GA Ao TM-1 V2 FS-6 FO-1 V2 FO-6 03A0V-127 D-4 2
s 1.00 CA A0 TM-1 V2 FS-6 FO-1 V2 FO-6 TECM SPEC STROKE TIE LIMIT-30,SEC 03Aov 32 H4 2
8 1.00 GA A0 TS-1 FC-1 PI-3 TECM SPEC STROKE TIME LIMIT-30 SEC 03ADV-33 F-4 2
8 2.00 cA Ao TS-1 FC-1 PI-3 TECM SPEC STROKE TIME LIMIT-3C SEC 03A0V-34 H-4 2
s 1.00 GA A0 TS-1 FC-1 PI-3 TECM SPEC STROKE TIME LIMIT-30 SEC 03ADV-35 F-4 2
B 2.00 CA Ao TS-t FC-1 PI-3 TECM SPEC STROKE 'IME LIMIT-30 SEC 03/mV-36 H-6 2
a 1.00 CA A0 TS-t FC-1 PI-3 TECM SPEC STROKE TIME LIMIT-30 SEC 03A0V-37 F-6 2
a 2.00 CA AO 75-1 FC-1 PI-I PAGE % OF 167 REY. No: 5
WEW YORK POWER AUTMORITY JAMES A.
FIT 2 PATRICK NUCLEhR POWER PLAuT ENSERVICE TESTIWG PROGRAM FOR PUMPS AND VALVES VALVE TABLE DRAW 1mG: FM-27B SYSTEM: Control Rod Drive - SYSTEM ID: 03 YALVE ID DWG Co-OR CLASS VALVE CATEGORY SIZE (!N)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTEREATE TEST REMARES
- - - - - - - - - - - - - - ~ - - * - - ~ ~ - - - - - - - " - - - - " - - - - - - - - -
........ -.......................... - - - - - - - - - - - - - - - - - - - - - - - - - - -. - - - - - - - - - - - - - - - - - ~ - - - - -
TECM SPEC STRO E TIME LIMIT-30 SEC 03A0V-38 M-6 2
s 1.00 GA A0 TS-1 FC-1 PI-3 TEC.1 SPEC STROKE Time Ltutt-30 SEC 03A0V-39 F-6 2
s 2.00 GA A0 TS-1 FC-1 PI-3 03ncu-114 0-4 2
C 0.75 sr SA FF-1 V2 FF-6 03MCU-115 C-4 2
C 0.75 BC SA RF-2 CST sEVERSE FLOW TESTED VIA R@ MOTION 03Mcu-138 C-4 2
l PAGE 55 or 167 EEV. No: 5
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F1TZPATRICC WUCLEAR POWER PLANT I4 SERVICE TESTING PROGRAM FOE pumps A#D WALVES VALVE T4sLE SYSTEM: Traveting Im Core Probe - SYSTEM ID: 07 DRAW!aG: Fn.1194 i
Vr.tvE 10 DWG Co-OR CLASS VALVE CATEGORY SIZE (tu)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERSATE TEST REMARES 07EV-104A F-5 2
0 0.37 XP
$2 XP-4 07EY-104s F-4 2
0 0.37 XP SC XP-4 07EV-104C F-4 2
0 0.37 XP SC W-4 0750V-1044 F-5 2
A 0.37 st 50 Tu-1 60 FC-1 P1-3 LJ-3 075cV-1048 T-4 2
A 0.37 st 50 Tu-1 V50 FC-1 PI-3 LJ-3 0750V-104C F-4 2
A 0.37 BL So TM-1 v50 i
FC-1 PI-3 LJ-3 REY. a0: 6 PAGE 56 0F 167 i
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FITZPATRICK NUCLEAR POWER PLAWT INSERVICE iEST14G PROGRAM FOR PUMPS AED VALVES VALVE TABLE DRAG 1mG: FM-20A SYSTE1: Residual Heat Removal - SYSTEM ID: 10 VALVE Ib DWG Co-OR CLASS VALVE CATEGORY SITE (IN)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTER 4 ATE TEST REMARKS 10noV-668 0-3 '
2 B
20.00 GL mo in-1 PI-3 10RMR-262 n-3 2
C 4.00 CK sA RF-1 10RM-2TT G-8 2
C 4.00 CK SA RF-1 10RNR-42A C-8 2
C
-16.00 CK SA FF-1 RF-1 i
10RNR-428 C-3 2
C 16.00 CK SA FF-1 RF-1
'10RHR-4 C C-8 2
C 16.00 CK SA FF-1 2
RF-1 10RNR-42D-C-3 2
C 16.00 CK SA FF-1 RF-1 10RM-52A G-6 2
'A 2.00 GA MA LJ-3 V19 10RM-52s G-5 2
A 2.00 GA MA LJ-3 V19 10RMR-64A C-8 2
C 3.00 CK SA FF-1 RF-1 6 i
' 10RM-648 C-3 2
C 3.00 CK SA "
FF-1 l
RF-1 PAGE 61 OF 167 REV. No: 6
}
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NEW YORK POWER AUTNORITY JAMES A.
FITZPATRICK MUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AWD YALVES VALVE TA8LE DRAW!sG: FM-20A SYSTEM: Residaat Heat Removat. SYSTEM ID: 10 VALVE l'a DWG Co-OR CLASS VALVE CATEGORT SIZE (la)
VALVE TYPE ACTUATM TYPE SECT. Rt TEST RR / CS ALTERNATE TEST REMARKS 10RMR-64C 0-8 2
C 3.00 CK SA FF-1 RF-1 10RNR-64D 0-3 2
C 3.00 CK SA FF-1 RF-1 10Rpt-95A C-8 2
C 0.75 SK SA RF-1 VS6 RF-3 10RMR-958 B-5 2
C 0.75 SK SA RF-1 V56 RF-3 10SV-35A E-8 2
C 1.00 RL SA RL-4 10SV-355 E-3 2
C 1.00 RL SA RL-4 10SV-40 D-5 2
C 1.00 RL SA RL-4 PAGE 62 OF 167 REV. No: 6
O C
O NEW YORK POWER AUTNORITY JAME$
A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND WALVES l
VALVE TABLE l
SYSTE^1: Residual Heat Removal - SYSTEM 10: 10 ORAING: Fys-20s VALVE ID DWG Co-OR CLASS VALVE CATEGORY SIZE (IN)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 10MOV-894 D-6 3
8 16.00 GA MO TM-1 PI-3 l
l '
10MOV-898 E-5 3
8 16.00 GA Mo in-1 1
PI-3 I
10RNR-14A B-T 3
C 12.00 CK SA FF-1 RF-1 10RHR-148 8-4 3
C 12.00 CK SA FF-1 RF-1 10RNR-14C C-7 3
C 12.00 CK SA FF-1 RF-1 1
10RNR-14D C-4 3
C 12.00 CK SA FF-1 RF-1 10s0V-101A B-6 3
8 0.75 GL So in-1 FO-1 FF-3 1050V-1018 8-5 3
a 0.75 GL SO in-1 FO-1 FF-3 10SOV-101C C-6 3
s C.75 GL So TM-1 FO-1 FF-3 REY. NO: 6 PAGE 63 or 167 1
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JAMES A.
FifZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALYES bALVE TABLE l
SYSTEM: Residual Heat Removal - SYSTEM 10: 10 DRAuttsG: FM-205 VALVE ID DWG Co-OR CLASS VALVE CATEGORY SIZE (IN)
VALVE TYPE ACTUATOR TYPE SECT. RI TEST RR / CS ALTERNATE TEST REMARKS 10ScV-1010 C-5 3
8 0.75 GL So TM-1 70-1 FF-3 i
i l
REV. NO: 6 PAGE 64 OF 167 1
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N NEW YORK POWER AUTNORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANY IN$ERVICE TESTING PROGRAM FOR PUMPS ANO VALVES V A.L V E TABLE SYSTEM: Steney Liquid controt - SYSTEM ID: 11 DRAWING: FM-21A VALVE ID DWG Co-OR CLASS VALVE CATEGORY SIZE (IN)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 11EV-14A D-6 1
0 1.50 xP SQ XP-4 11EV-142 B6 1
0 1.50 XP SQ XP-4 11SLC-16 C-7 1
AC 1.50 CK SA FF-1 V5 FF-3 RF-1 V5 LJ-3 LJ-3 11SLC-17 0-7 1
AC 1.50 SK SA FF-1 V5 FF-3 RF-1 V5 LJ-3 LJ-3 11SLC-434 0-6 2
C 1.50 SK SA FF-1 RF-1 11SLC-438 8-6 2
C 1.50 SK SA FF-1 RF-1 11SV-39A D-4 2
C 1.00 RL SA RL-4 11SV-398 C-4 2
C 1.00 RL SA RL-4 REV. No: 5 PAGE 65 or 167
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FIT 2 PATRICK NUCLEAR POWER PLANT INSERVICE TESTING PR0 GRAM FOR PUMPS AND VALVES VALVE TABLE SYSTEM: Reactor Core Isolation Cooting - SYSTEM 1D: 13 DRAWIWG: FM-22A l
VALVE 10 -
DWG CO-OR CLASS VALVE CATECORT SIZE (IN)
VALVE TYPE ACTUATOR TTPE SECT. XI TEST RR / CS ALTERMATE TEST REMARKS 13EFV-01A G-7 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 13EFv-018 G-7 1
AC 1.00 SK SA LK-1 Y28 LK-3 VAlb1 ISOLATES ON F XESS FLOW LK-3 13EFV-02A G-7 1
AC 1.00 BK SA LK-1 v28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 1
13EFV-028 F-7 1
AC 1.00 BK SA LK-1 v2E LK-3 VALVE ISCLATES ON EXCESS FLOW LK-3 13MOV-15 F-7 1
A 3.00 GA Mo TS-1 PI-3 LJ-3 V19 i.
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A 3.00 GA MO TS-1 PI-3 LJ-3 V19 13MOV-21 F-5 1
A 4.00 GA Mo TM-1 PI-3 LJ-3 V19 13MOV-27 E-5 2
8 2.00 GL Mo TS-1 PI-3 13MOV-41 D-7 2
B 6.00 GA M0 TM-1 PI-3 REY. h0: 5 PAGE 67 OF 167 l
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F1TZPATRICK NUCLEAR POWER PLAMT INSERVICE TESTING PR0 GRAM FOR PUPPS AND VALVES 4
i VALVE TA8LE DRAWING: fM-22A SYSTEM: Reactor Core 1sotation Cooling - SYSTEM ID: 13
'YALVE ID DWG Co-OR CLASS VALVE CATECORY SIZE (IN)
VALVE TYPE ACTUATOR TTPE SECT. XI TEST RR / CS ALTEtuATE TEST REMARKS 13RCIC-37 E-6 2
C 1.50 CK SA FF-2 CSIT 13RCIC-38 E-6 2
C 1.50 CK SA FF-2 CS17 13RCIC-4 D-6 2
AC 8.D0 LK SA RF-1 V6 LJ-3 LJ-3 13RCIC-5 C-6 2
AC 8.00 LK SA RF-1 V6 LJ-3 LJ-3
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PAGE 68 or 167 REW. No: 6
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FITZPATRICK NUCLEAR POWER PLANT I
INSERV!CE TESTING PROGRAM FOR PUMPS AND WALVES I
VALVE iA8LE SYSTE*I: Core spray - SYSTEM ID: 14 DRAW 1mG: FM-23A VAtVE ID DWG CO-OR CLASS VALVE CATEGatY SIZE (IM) VALVE TTPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMArts 14A0W-13A F-6 1
AC 10.00 ft SA A0 PE-2 v57 RF-2 FF-3 LK-3 PI-3 14A0V-138 F-5 1
RF-2 FF-3 LK-3 PI-3 14 CSP-10A D-8 2
C 12.00 CK SA FF-1 14 CSP-108 D-3 2
C 12.00 CK SA FF-1 14 CSP-62A E-7 2
C 1.00 SK SA RF-1 V55 RF-3 14 CSP-628 E-3 2
C 1.00 sr sA RF.1 V55 RF-3 14 CSP-764 F-7 2
C 2.00 SK SA RF-1 14 CSP-768 F-4 2
C 2.00 SK SA RF-1 14EFV-31A E-4 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE 15ftATES ON EXCESS FLOW LK-3 14EFV-318 E-4 1
AC 1.00 BK SA LK-1 V23 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 REV. No: 6 PAGE 69 0F 167
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VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TES1 REstangS i
1&MOV-7A C-6 2
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s 16.00 GA Mo TM-1 P!-3 145V-2CA E-8 2
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FITZPATRICE uuCLEAR POWER PLAuf e
I45ERvICE TE5 TING PRoGRAa FOR PUMPS AMD VALVE $
VAtVE TABLE SYSTE'4: Resctor suildirs Closed Loop Cootirg - SYSTEM 10: 15 ctAgtnG: Fu-1 VALG 10 DWG CD-OR CLASS VALVE CATEGORY SIZE (Is)
%ALVE TYPE ACTUATOR TYPE SECT. NI TEST RR / CS ALTERDATE TEST REM AES
............... -.................... - -..... - -..... -......... - - -.... - -... - - -... -....................... - - - - - - - - - - - - - - - - - - - - - - - -.... - - - - - -. - - - -.... - = - -
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F1YZPATRICK NUCLEAR POWER PLANY a
VICE TEST 1NG PROGRAM FOR PUMPS AND VALVES VAtdE TABLE CAAWINc: FM-tSe SYSTE::: Ceactor Building Closed Loop Coolirg - SYSTEM ID: 15 i
VALVE ID DWG CD-OR CLASS VALVE CATEGORY SIZE (th) VALVE TYPE ACTUATOR TYPE SECT. It TEST RR / CS ALTERNATE TEST REMARKS e
PE-T PI-3 LJ-3 1
15A0v-130s D-5 3
A 4.00 GL A0 TM-2 CS5 PE-T PI-3 LJ-3 15A0v-131A E-T 3
A 4.00 GL A0 TM-2 CSS PE-7 PI-3 LJ-3 15A0v-1318 E-4 3
A-4.00 GL A0 TM-2 CSS PE-T PI-3 LJ-3 l
15A0V-132A F-5 3
A 4.00 GL Ao TM-2 CS4 PE-T PI-3 LJ-3 15A0v-1328 F-7 3
A 4.00 GL A0 TM-2 CS4 PE-7 FI-3 LJ-3 PAGE 73 0F 147 REV. NO: 6-
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fit 2 PATRICK NUCLEAR POWER PLA5T INSERVICE TESTI4G PROGRAM FOR PUMPS AND VALVES VALVE TABLE SYSTEM: Reactor Building Closed Loop Ceoling - SYSTEM 10: 15 DRAutnG: Fn.15s VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERaiATE TEST REMARKS ll 15ADV-133A F-5 1
A 4.00 GL A0 Tse-?
Cs4 PE-7 PI-3 (J-3 I
l 15A0V-1338 F-7 3
A 4.00 GL A0 TM-2 C*.,4 PE-T PI-3 LJ-3 f
15A0V-134A C-6 3
A 1.50 GL AO TM-2 CSS PE-7 PI-3 LJ-3 15RBC-21A F-4 3
AC 4.00 CK SA RF-2 Cs14 LJ 3 V19 15RBC-21s F-7 3
AC 4.00 tK SA RF-2 CS14 LJ-3 V19 l
15RBC-22A F-4 3
A 4.00 GL MA FS-2 Cs14 LJ-3 l
15RBC-228 F-7 3
A 4.00 GL MA FS-2 Cs14 LJ-3 15RBC-24A C-7 3
LJ-3 V19 1
' red. No: 6 PnGE 74 0F 167
NEW YORK POWER AUTHOR!TY JAMES A.
FITZPATRICK NUCLEAR POWER PLAWT INSERVICE TESTING PROCRAM FOR PUMPS AND VALWES VALVE fA8LE CRAWin t: FM-15s Reactor Building Closed Loop Cooting - SYSTEM ID: 15 SYSTEM:
VALVE ID DWG Co-OR CLASS VALVE CATEGORY SIZE (IN)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS l
'1528C-248 D-4 3
AC 4.00 CK SA RF-2 CSIS LJ-3 V19 f
15RBC-26A E-7 3
A 4.00 GL MA FS-2 CSIS LJ-3 f
15RBC-268 E 3 A
4.00 GL MA FS-2 CSIS LJ-3 l
152CC-33 C-6 3
A 1.50 GL MA FS-1 I
LJ-3 15tsC-35A D-4 3
C 1.50 SK SA RF-1 15RSC-358 D-8 3
C 1.50 SK SA RF-1 15:8C-35C D-3 3
C 1.50 SK SA RF-1 15:8C-35D E-8 3
C 1.50 SK SA RF-1 15RBC-3aA F-4 3
C 1.50 SK SA RF-1 15R8C-3Sa F-3 3
C 1.50 SK SA RF-1 15ISC-61 F-7 3
C 1.00 SK SA RF-1 l
l PAGE 75 OF 167 REV. 20: 6
NEW YORK POWER AUTMOR1TT JAME$
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FIT 2 PATRICK NUCLEAR POWER PLANT IN5ERVICE iEST1PG PROGRAM F0R PUMPS AND VALVE 4 VALVE iABLE DRAWING: FM-49A SYSTEM: Leak Rate Analyzer - SYSTEM ID: 16-1 DVG Co-OR flats VALVE CATECORT SIZE (IN)
VALVE TYPE ACTUA10R TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS VALVE ID l
16-1A0V-10TA 0-7 2
A 0.37 CA A0 TM-1 V29 FC-1 PI-3 LJ-3 V19 16-1A0V-1018 E-7 2
A 0.37 GA A0 TM-1 V29 FC-1 PI-3 LJ-3 V19 16-1A0V-102A 0-7 2
A 0.37 GA A0 TM-1 V29 FC-1 PI-3 LJ-3 V19 16-1A0V-102B C-7 2
A 0.37 CA A0 TM-1 V29 FC-1 PI-3 LJ-3 V19 i
PAGE 76 OF 167 REV. NO: 6
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FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTIhG PROGRAM FOR PUMPS AND VALVES VALVE TA8LE DRAulNG: FM-1TA SYSTE;; Rackaste - SYSTEM ID: 20 VI.LVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERKATE TEST REMARKS l
20A0V-83 F-6 2
A
'3.00 8L A0 TM-1 FC-1 PI-3 LJ 3 20A0V-95 C-6 2
A 3.00 SL A0 TM-1 FC-1 PI-3 LJ-3 20MOV-82 F-7 2
A 3.00 GA Mo 75-1 PI-3 LJ-3 20MOV-94 C-7 2
A 3.00 GA MO TS 1 PI-3 LJ-3 PAGE 78 OF 167 REV. NO: 6
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F I T Z P A T.R I C K NUCLEAR POWER PLANY 1NSERVICE TESTING PR0 GRAM FOR PUMPS AND VALVES I
VALVE TA8LE STSTEM: Nigh Pressure Coolant Injection
. SYSTEM ID: 23 DRAWING: FM-25A' i ; VALVE 10-DWG CO-OR' CLASS' VALVE CATEGORY SIZE (IN)' VALVE TYPE ' ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS i.............................................................................................................................................................................
23A0V 'B 2 8
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1.00 GA A0 TM-1 V29 FC-1 PI-3 j -23EFV-01A G-7 1
AC 1.00 8K SA LK-1' V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 i
123EFV-018 G-7' 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 i "23EFV-02A.
G-7 1
AC 1.00' BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 l
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FIT 2 PATRICK WUCLEAR POWER PLANT INSERVICE TESTING PR0 GRAM F0R PUMPS AND VALVES VALVE TA8LE i
, SYSTEM: High Pressure Coolant Injection - SYSTEM ID: 23 DRAWIuG: FM-25A l VALVE 10 DWG Co-OR CLASS VALVE CATEGORY SIZE (IM)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 23HPI-130 C-5 2
C 2.00 SK SA fF-1 V54 DA-3 PF-1 23HPI-18 F-7 1
C 14.00 CK SA ME-2 CS6 23HPI-32 G-5 2
C 16.00 CK SA FF-1 23HPI-402 E-7 2
C 2.00 CK SA FF-2 V17 RF-2 V17
.23HPI-403 E-T 2
C 2.00 C%
SA FF-2 V17 RF-2 V17 23HPI-56 C-6 2
C 2.00 SK SA FF-1 V22 DA-3 23HPI-61 B-7 2
C 16.00 Cr SA FF-1 V9 DA-6 PF-3 23HPI-62 F-4 2
C 4.00 CK SA FF-1 V47 DA-6 23HPI-65 C-6 2
AC 20.00 LK SA FF-1 RF-1 V34 LJ-3 LJ-3 23MOV-14 F-3 2
8 10.00 GA M0 TM-1 PI-3 23MOV-15 F-7 1
A 10.00 GA MO TS-1 TM-1 PI-3 LJ-3 V19 REV. NO: 6 PAGE 80 of 167
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-r NEW FORK POWER' AUTHORITY p-JAMES A.
FITZPATRICK NUCLEAR POWER PLANT
' INSERVICE T E S T I N G.
PR0 GRAM FOR, PUMPS AWD VALVES VALVE TABLE
' SYSTE :: High Pressure Coolant Injection - SYSTEM ID: 23 DeuwlWG: FM 25A
". VALVE ID '
DWG CO-OR CLASS VALVE CATEGORY-SIZE (IN)
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8 8.00 GL-Mo TM-1 PI-3 23Mov-25 F-5
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FIT 2 PATRICK WUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES VALVE TABLE DRAWING: FM-25A SYSTEM: High Pressure Coolant injection - SYSTEM ID: 23
'YPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERuATE TEST REMARKS VALVE ID dug Co-cR CLASS VALVE CATEGORY SIZE (IN)
M #- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ ~ - - - ~ ~ * - - - - - - ~ -
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NEW YORK POWER AUTH0RITY JAMES A-FITZPATRICK NUCLEAR POWER PLANT 1NSEPVICE TESTING PROGRAM FOR PUMPS AND VALVES VALVE TA8f E DRAWIMG: FM-18A SYSTEM: Contairvwnt Atmosphere Dilution - SYSTEM 10: 27 VALVE 10 DWG Co-OR CLASS VALVE CATECORY SIZE (IN)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERkATE TEST REMARKS 27AOV-126A G-5 2
8 1.00 GL A0 TM-1 V29 P!-3 27A0V-1268 E-5 2
s 1.00 GL A0 TM-1 V29 PI-3 27A0V-128A G-4 2
8 1.50 GL A0 TM-1 V29 PI-3 27ADV-1288 E-4 2
8 1.50 GL A0 TM-1 V29 PI-3 27AOV-129A F-4 2
B 1.00 GL A0 TM-1 V29 PI-3 27ADV-1298 F-4 2
8 1.00 GL A0 TM-1 V29 PI-3 27 CAD-19A G-6 2
C 2.00 CK SA FF-1 27 CAD-198 C-6 2
C 2.00 CK SA FF-1 275V-115A G-4 2
C 0.%
C 0.50 RL SA RL-4 275V-118A C5 2
C O.50 RL SA RL-4 RL-4 27SV-1188 C-6 2
C 0.50 RL PACE 83 0F 167 REV. NO: 5
NEW YORK POWER AUTH0RITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES VALVE TABLE DRAWING: FM-18s STSTEM: Containment Atmosphere Ditution - SYSTEM ID: 27 VALVE ID DWG Co-OR CLASS VALVE CATEGORY SIZE (IN)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 27A0V-101A C-6 2
A 20.00 BF A0 TM-1 FC-1 PI-3 LJ-3 V19 27A0V-1018 C-6 2
A 20.00 BF A0 TM-1 FC-1 PI-3 LJ-3 V19 27ADV-111 C-2 2
A 24.00 8F A0 TS-2 CS10 FC-2 CS10 PI-3 LJ-3 V19 1
i 27A0V-112 C-3 2
A 24.00 BF A0 TS-2 CS10 FC-2 CS10 PI-3 LJ-3 v19 27A0V-113 D-8 2
A 24.00 BF A0 TS-2 CS10 FC-2 CS10 PI-3 LJ-3 V19 27A0V-114 D-8 2
A 24.00 SF A0 TS-2 CS10 FC-2 CS10 PI-3 LJ-3 V19 PAGE 84 0F 167-REY. 20: 5 I
NEW YORK POWER AUTHOR 1TT JAMES A.
FITZPATRICK WUCLEAR POWER PLANT 1N$ERVICE TESTING PROGRAM F0R PUMPS AND VALVES VALVE TABLE DRAWING: FM-188 SYSTEM: Containment Atmosphere Dilution - SYSTEM ID: 27 VALVE ID DWG Co-OR CLASS VALVE CATEGORY SIZE (!N)
VALVE TYPE ACTUATOK TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 27A0V-115 C-2 2
A 20.00 BF A0 TS-2 CS10 FC-2 CS10 PI-3 LJ-3 V19 27ADV-116 C-3 2
A 20.00 BF AO TS-2 CS10 FC-2 CS10 P!-3 LJ-3 V19 A
20.00 BF A0 TS-1 27A0V-117 B-8 FC-1 PI-3 LJ-3 V19 27A0V-118 8-8 2
A 20.00 BF A0 TS-1 FC-1 PI-3 LJ-3 V19 27A0V-131A C-4 2
A 1.50 CA A0 TS-1 g
TM-1 FC-1 PI-3 LJ-3 VI?
27A0V-1318 C-3 2
A 1.50 CA A0 TS-1 TM-1 FC-1 PI-3 l
LJ-3 V19 PAGE 85 OF 167 REV. NO: 6
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FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMP $ AND VALVES VALVE TABLE STS.. et: Containment Atmosphere Dilution - SYSTEM ID: 27 DRAWING: FM-188 VALVE ID DWG Co-OR CLASS VALVE CATEGORY SIZE (IN)
%ALVE TYPE ACTUATOL TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 27A0V-132A c-4 2
A 1.50 CA A0 TS-1 TM-1 FC-1 PI-3 LJ-3 v19 27A0V-1328 C-3 2
A 1.50 GA A0 TS-1 TM-1 FC-1 Pi-3 LJ-3 V19 27 CAD-67 C-4 2
AC 1.50 SK SA FF-1 RF-1 LJ-3 V19 27 CAD-68 C-4 2
AC 1.50 SK SA FF-1 RF-1 LJ-3 V19 27 CAD-69 C-3 2.
AC 1.50 SK SA FF-1 RF-1 LJ-3 v19 27 CAD-70 C-3 2
AC 1.50 SK SA FF-1 RF-1 LJ-3 V19
.27MOV-113 C-8 2
A 3.00 BF MO TS-1 TM-1 PI-3 LJ-3 vi9 PAGE 86 0F 167 REV, No: 5
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NEW YORK POWER AUTHORITY JAMES A.
F!TZPATRICK NUCLEAR POWER PLANT IN$ERVICE TESTING PROGRAM FOR PUMPS AND VALVES VALVE TA8LE SYSTEM: Contalrnent Atmosphere Dilution - STSTEM ID: 27 DRAWING: FM-188 VALVE 10 DWG CO-OR CLASS VALVE CATEGORY SIZE (IM)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS
-27MOV-117 88 2
A 3.00' BF MO TS-1 TM-1 PI-3 LJ-3 V19 27MOV-121 H8 2
8 6.00 8F Mo TM-1 PI-3 l
l 27MOV-122 C-8 2
A 3.00 GL MO TS-1 TM-1 PI-3 Lb1 V19 l
27MOV 123 8-8 2
A 3.00 ct Mo TS-1 TM-1 l
PI-3 l
LJ-3 V19 i
l l
2750V-125A F-5 2
A 1.00-ct 50 TM-1 V29 FC-1 PI-3 LJ-3 2750V-1258 F-4 2
A 1.00 ct 50 TM-1 V29 FC-1 PI-3 i
LJ-3 2750V-125C F-5 2
A 1.00 CL 50 TM-1 V29 FC-1 PI-3 LJ-3 PAGE 87 0F 167 REV. NO: 5
NEW YORK POWER AUTMORITY JAMES A.
F!T2 PATRICK MUCLEAR POWER PLANT I N S E R V I'C E TESTINC PROGRAM FOR PUMPS AND VALVE 5 VALVE TA8LE DRAW 14G: FM 188 SYSTEM: Containment Atmosphere Dilution - SYSTEM 10: 27 VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (IN)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 27scV-1250 F-4 2
A 1.00 ct 50 TM-1 V29 FC-1 PI-3 LJ-3 27sov-135A E-5 2
A 1.00 ct 50 TM-1 V29 FC-1 PI-3 LJ-3 2750V-1358 F-5 2
A 1.00 CL So TM-1 V29 FC-1 PI-3 LJ-3 27sov-135C E-5 2
A 1.00 ct so TM-1 V29 FC-1 PI-3 LJ-3 27S0V-1350 F-5 2
A 1.00 GL S0 TM-1 V29 FC-1 PI-3 LJ-3 27VB-1 C-6 2
PI-3 PAGE 88 0F 167 REV. mo: 5
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U NEW YORK P O W'E R AUTHORITT JAMES A.
FIT 2 PATRICK WUCLEAR POWER PLANT INSERVICE TE$ TING PR0 GRAM FOR PUMPS AWD VALVES VALVE TABLE SYSTEM: Contairrnent Atrnosphere Dilution - SYSTEM ID: 27 DRAWING: FM-1SB VALVE ID DWG CO-OR CLASS VALVE CATEGORT SIZF (IN)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 2M 2 C-6 2
AC 30.00 CK SA ME-1 LK-3 v48 PI-3 27Vs-3 C-6 2
AC 30.00 CK SA ME-1 LK-3 V48 PI-3 27Vs-4 C-6 2
AC 30.00 CK SA ME-1 LK-3 v48 PI-3 27VB-5 C-6 2
AC 30.00 CK SA ME-1 LK-3 V48 91-3 27V8-6 C-6 2
AC 20.00 CK SA ME-1 LJ-3 V19 PI-3 27V3-7 C-6 2
AC 20.00 CK SA ME-1 LJ-3 V19 PI-3 REV. No: 5 PAGE 89 0F 167
NEW YORK POWER AUTHORITY JAMES A.
FIT 2 PATRICK WUCLEAR POWER PLANT INSERVICE TESTING PR0 GRAM F0R PUMPS AND VALVES VALVE TA8LE DRAWING: FM-18D SYSTEM: Containment Atmosphere Dilution - SYSTEM ID: 27 VALVE ID DWG Co-OR CLASS VALVE CATEGORY SIZE (IN)
VALVE TYPE ACTUAT02 TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMtRKS 27s0V-119E1 C-7 2
A 0.37 CL 50 TM-1 V29 FC-1
.l PI-3 LJ-3 27S0V-119E2 C-6 2
A 0.37 GL SO TM-1 V29 FC-1 PI-3 LJ-3 27$0V-119F1 D-4 2
A 0.37 GL So TM-1 V29 FC-1 PI-3 LJ-3 27s0V-119F2 0-4 2
A 0.37 GL So TM-1 V29 FC-1 PI-3 LJ-3 2730V-120E1 F-6 2
A 0.37 CL So TM-1 V29 FC-1 PI-3 LJ-3 j
27s0V-120E2 F-6 2
A 0.37 CL So TM-1 v29 FC-1 PI-3 LJ-3 PAGE 90 0F 16T REV. NO: 6
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FITZPATRICK NUCLEAR POWER PLANT IN$ERVICE TESTING PR0 GRAM F0R PUMPS AND VALVES VALVE 7ABLE SYSTEO: Contaiteent Atmosphere Dilution - SYSTEM ID: 27 DRAWING: FM-180 VI.LVE ID DWG Co-OR CLASS VALVE CATEGORY S!2E (IN)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 2750V-120F1 G-4 2
A 0.37 GL SO YM-1 V29 FC-1 PI-3 LJ-3 2750V-120F2 G-4 2
A 0.37 GL So TM-1 V29 FC-1 PI-3 LJ-3 2750V-122E1 F-6 2
A 0.37 GL So TM-1 V29 FC-1 f
PI-3 LJ-3 2750V-1"R2 F-6 2
A 0.37 GL So TM-1 V29 FC-1 PI-3 LJ-3 2750V-122F1 G-4 2
A 0.37 GL So TM-1 V29 FC-1 PI-3 LJ-3 I
2750V-122F2 G-4 2
A 0.37 GL So TM-1 V29 1
FC-1 l
PI-3 LJ-3 PAGE 91 0F 167 PEV. No: 5
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NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK. NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES VALVE TABLE D u WING FM-tso SYSTEil: Containment Atmosphere Dilution - SYSTEM ID: 27 VALVE 10 DWS CO-OR CLASS VALVE CATEGORY SIZE (IM)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 27SOV-123E1 E-6 2
A 0.37 CL So TM-1 V29 FC-1 l
PI-3 l
LJ-3 l
2750V-123E2 E-6 2
A 0.37 GL So TM-1 V29 FC-1 PI-3 LJ-3 l
2750V-123F1 F-4 2
A 0.37 GL So TM-1 V29 FC-1 PI-3 I
LJ-3 27SOV-123F2 F-4 2
A 0.37 CL So TM-1 V29 FC-1 PI-3 LJ-3 l
2750V-124E1 C-4 2
A 1.00 CL So TM-1 V29 FC-1 PI-3 LJ-3 l
2750V-124E2 C-4 2
A 1.00 GL So ~
TM 1 V29 FC-1 PI-3 LJ-3 PAGE 92 0F 167 l
REV. c3: 5
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FITZPATRICK WUCLEAR POWER. PLANT l
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES VALVE iABLC SYSTEM: Contairunent Atmosphere Dilution - SYSTEM ID: 27 DRAWING: FM-18D VALVE 10 DWG CO-OR CLASS VALVE CATEGORY $!2E (tN)
VALVE TYPE ACTUATOR T'PE SECT. XI TEST RR / CS ALTERNATE TEST REMAM S 27S0V-124F1 C-3 2
A 0.37 GL So TM-1 V29 l
FC-1 l
l PI-3 LJ-3 i
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A 0.37 CL SO TM-1 V29 1'
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REV. NO: 5 PAGE 93 0F 167 '
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FITZPATRICK RUCLEAR POVER
- LANT IkSERV1CE iESTI4G PR0 CRAM F0R PUMPS AND VALVES VALVE TABLE DRAWING: FN-39C SYSTEM: Contairunent Atmosphere Dilution - SYSTEM ID: 27 VALVE 10 dug Co-OR CLASS VALVE CATE00aY SIZE (IN)
VALVE TYPE ACTUATO:: T7PE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 2750V-141 E-6 2
A 1.00 GL So TM-1 V29 FO-1 PI-3 LJ-3 27SOV-145 G-5 2
A 1.00 GL So TM-1 V29 70-1 FI-3 LJ-3 PAGE 94 of 167-REV. C3: 6
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FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PR0 GRAM F0R PUMP $ AND VALVES VALVE TABLE SYSTEM: Main Stearn - SYSTEM 10: 29 DRAWING: FM 29A VALVE ID CwG Co-OR CLASS VALVE CATECORY SI2E (IN)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 29A0V-80A E-5 1
A 24.00 GL AO TS-1 TECH SPEC LIMIT ON CLOSE TIME 3-5 SEC FC-2 V59 PI-3 LJ 3 V19 29AW-808 D-5 1
A 24.00 CL A0 TS-1 TECH SPEC LIMIT ON CLOSE TIME 3-5 SEC FC-2 V59 PI-3 LJ-3 V19 29A0V-80C D-5 1
A 24.00 CL A0 TS-1 TECH SPEC LIMIT CN CLOSE TIME 3-5 SEC FC-2 V59 PI-3 LJ-3 V19 29A0V-800 D-5 1
A 24.00 CL A0 TS-1 TECH SPEC LIMIT ON CLOSE T!ME 3-5 SEC FC-2 V59 PI-3 LJ-3 V19 29ADV-86A C-4 1
A 24.00 GL A0 TS-1 TECH SPEC LIMIT ON CLOSE T!ME 3-5 SEC FC-2 CS12 PI-3 LJ-3 V19 29A0V-868 F-4 1
A 24.00 GL A0 TS-1 TECH SPEC LIMIT ON CLOSE TIME 3-5 SEC FC-2 CS12 PI-3 LJ-3 V19 PAGE 95 0F 167 REV, CO: 5
N NEW YORK P O W E'R AUTNOR!TT
-JAMES A.
FITZPATRICK NUCLEAR ' POWER PLANT INSERV!CE TESTING PROGRAM FOR P tl M P S AND VALVES l '-
l E
VALVE TABLE ORAWING: FM-294 l SYSTEM: Main Steam - SYSTEM 10: 29
! VALVE ID DWG Co-OR CLASS VALVE CATEGORF SIZE (IN)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST' REMARKS I
29A0V-86C E-4 1
.A 24.00
-GL A0 TS-1 FC-2 CS12 PI-3 LJ-3 V19 TECH SPEC LIMIT ON CLOSE TIME 3-5 SEC 29A0V-86D D-4 1
A 24.00 GL A0 TS-1 FC-2 CS12 PI-3 s
i LJ-3 V19 29EFv-30A F-5
_ 1-AC 1.00 at SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW
-LK-3 29EFV-303 F-5 1
'Ac 1.00 -
BK
'SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW ~
LK-3 i
29EFV-3CC F-5' 1
AC 1.00 BK SA LK-1 V28-LK-3 VALVE ISOLATES ON EXCESS FLOW i
LK-3
.29EFV-300 F-5 1
AC 1.00 BK
. SA LK-1 V28 LK-3
. VALVE ISOLATES ON EXCESS FLOW'
[
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~ 29EFV-34A F-8 1
AC 1.00 SK SA LK-1 V28 LK-3 VALVE.lSOLATES ON EXCESS FLOW v
I LK-3 i
29EFv-348 F-8
~1 AC >
1.00 SK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 29EFV-34C F-8 1
AC 1.00 BK '
SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW D
LK-3 PAGE 96 0F 167 '
REV. NO: 5 h
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FITZPATRICK NUCLEAR POWER PLANI INSERVICE TESTING PROGRAM F0R PUMPS AND VALVES VALVE TABLE l-DRAWING: FM-29A SYS!IO: Main Steam - SYSTEM ID: 29 VALVE ID DWG CO-OR CLASS VALVE CATECORY SIZE (!N)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 29EFV-340 F-8 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 29EFV-53A E-8 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 29EFV-538 E-8 1
AC 1.00 BK SA LK-1 v28 LK-3 VALVE ISOLATES ON EXCESS FLOW LK-3 l
29EFV-53C E-8 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES 04 EXCESS FLOW LK-3
(
29EFV-530 E-8 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EMSESS FLOW LK-3 l
29EFV-54A E-5 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES Ost EXCESS FLOW LK-3 29EFV-548 E-5 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE if0LAYES ON EXCESS FLOW LK-3 29EFV-54C E-5 1
AC 1.00 BK SA LK-1 V28 LK-3 VALVE ISOLATES ON EXCESS FLOW (K-3 t
i 290V-54D E-5 1
AC 1.00 BK SA LK-1 V2S LK-3 VALVE ISOLATES 04 EXCESS FLOW LK-3 l
29MOV-200A C-3 2
a 1.00 GL MO TM-1 I
PI-3 1
PAGE 97 0F 167 F.EV. No:.5
NEW Y0RK POWER AUTMOR1iY JAMES A.
F!T2PATR1CE NUCLEAR POWFR PLANT INSERVICE TESTING PROGMAM FOR PUMPS AND VALVES VALVE TABLE DRAWING: FM-294 SYSTEM: Main Steam - SYSTEM ID: 29 VALVE ID DwG Co-OR CLASS VALVE CATEGORT SIZE (IN)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS
- - - ~ ~ - - - - - - ~ ~ - - - - - - - = - - - ~ ~ ~ ~ ~ ~ ~ - ~ ~ ~ ~ ~ ~ ~ ~ - - - - -
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29MOV-2008 s-3 2
8 1.00 GL MO TM-1 PI-3 29MOV-201A C-3 2
8 1.00 GL Mo TM-1 PI-3 29MOV-2019 B-3 2
8 1.00 Gt Mo TM-1 Pi-3 29Mov 202A C-3 2
8 1.00 GL Mo TM-1 PI-3 29MOV-2025 B-3 2
s 1.00 GL M0 TM-1 PI-3 29Mov-203A H-3 2
8 1 00 GL MO TM-2 CST 3 PI-3 29MOV-2039 H-3 2
8 1.00 GL Ma TM-2 CS13 PI-3 29MOV-204A C-3 2
s 1.00 ct M0 TM-1 PI-3 29MOV-2043 s-3 2
s 1.00 GL MO TM-1 PI-3 l
29MOV-74 c-6 1
A 3.00 CA MO TS-1 PI-3 L2-3 PAGE 96 0F 167 REV to: 5 f.
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FIT 2 PATRICK NUCLEAR POWER PLANT INSERVICE TEST 14G PROGRAM F0R PUMPS AND VALWES VALVE TABLE SYSTE"!: Main Steam - SYSTEM 10: 29 DRAWING: FM-29A VALVE ID CWG Co-OR CLASS VALVE CATEGORY SIZE (IN)
VALVE TYPE ACTUATOR TYPE SECT. N1 TEST RR / CS ALTEttATE TEST REMARKS 29MCrf-77 C5 1
A 3.00 GA Mo TS-1 PI-3 LJ-3 REV. NO: 5 PAGE 99 or 167
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NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES VALVE TA8LE DRAWING: FM-39C SYSTEM: Instrtsnent Air Systeve - SYSTEM ID: 39 VALVE ID DVG CO OR CLASS VALVE CATECORT SIZE (IN)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS l
39fAS-22 E-S 2
RF-1 LJ-3 39IAS.29 F-3 2
AC 1.00 CK SA FF-2 V14 RF-1 LJ-3 PAGE 101 0F 167 REV, No: 6
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JAMES A.
FITZPATRICK NUCLEAR POWER PLANT l
INSERVICE T E S T'I N G PROGRAM FOR PUMP $ AND VALVES i..
VALVE TABLE f
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SYSTE!1: Service Water SYSTEM 10: 46
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l DRAWING: FB-10H '
l VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (!N)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 46SWS-60A C-5 3
C 4.00 CK SA RF-1 46SWS-608 C-5 3
.C 4.00 CK SA RF-1 66PCV-101 D-3 3
8 3.00 GL AO FO-1 66TCV-107E C-4 3
a 2.50 CL AO FO-1 66TCV-107F C-7 3
8 2.50 GL AO FO-1 REV. C3: 6 PAGE 102 0F 167
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FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PuhPS AND VALVES 1
VALVE TABLE SYSTEM: Emergency Service Water - SYSTEM 10 46 DRAWING: FB-35E VALVE 10 DWG Co-OR CLASS VALVE CATEGOPY SIZE (IN) VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 70WAC-53 D-2 3
8 4.00 GA MA FS-1 REV. NO: $
PAGE 104 0F 167
NEW YORK POVER AUTHORITY J A M E.S A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PR0 GRAM F0R PUMPS AND VALVES VALVE TA8LE I
DRAWING: FM-46A SYSTEM: Emergency Service Water - STSTEM ID: 46 i
i VALVE 10 DWG Co 0R CLASS VALVE CAIEGORY SIZE (IN)
VALVE TYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS j
46E::W-19A B-6 3
C 2.00 SK SA FF-1 l
46ESW-20s B-8 3
C 2.00 SK SA FF-1 46ESW-21s a-8 3
C 2.00 SK SA FF-1 46ESW-22A B-7 3
C 2.00 SK SA FF-1 46SWS-67A 8-6 3
C 3.00 CK SA RF-1 46SWS-678 8-7 3
C 3.00 CK SA RF-1 46SWS-68 8-6 3
C 3.00 CK SA RF-1 46SVS-69 8-8 3
C 3.00 CK SA RF-1 67PCV-101 D-2 3
8 2.50 GL A0 FO-1 l
. PAGE 105 of 167 REV. 20: 6
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NEW YORK POV R AUTHORITY JAMES A.
F1TZPATRICK NUCLEAR POWER PLANT INSERVICE TEST!NG PROGRAM FOR PUMPS AND VALVES VALVE TABLE SYSTEM: Emergency Service Water - SYSTEM ID: 46 DRAWING: FM-468 VALVE ID DWG CO-OR CLASS VALVE CATEGORY SIZE (lN)
VALVE fYPE ACTUATOR TYPE SECT. XI TEST RR / CS ALTERNATE TEST REMARKS 46ESW-13A E-3 3
C 3.00 CK SA FF-1 46ESW-13B C-2 3
C 3.00 CK SA FF-1 46ESW-15A E-2 3
AC 4.00 CK SA RF-1 LJ-3 V19 46ESW-15B C-3 3
AC 4.00 CK SA RF-1 LJ-3 V19 46ESW-16A E-3 3
AC 4.00 CK SA RF-1 LJ-3 V19 46ESW 168 C-3 3
AC 6.00 CK SA RF-1 LJ-3 V19 46ESW-1 A E-7 3
C 12.00 CK SA FF-1 46ESU-18 0-7 3
C 12.00 CK SA FF-1 46ESW-40A E-5 3
C 1.00 CK SA RF-1 46ESW-408 E-4 3
C 1.00 CK SA RF-1 46ESW-7A E-5 3
C 6.00 CK SA FF-1 46ESW-7B E-5 3
C 6.00 CK SA FF-1 46ESW-9A E-4 3
C 8.00 CK SA FF-1 REV. NO: 6 PAGE 106 0F 167
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NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS add VALVES VALVE YABLE SYSTEM: Emergency service Water - SYSTEM ID; 46 DRAWING: FM-468 VALVE 10 DWG CO-OR CLASS VALVE CATEGORY SIZE (!N)
VALVE TYPE ACTUATOR TYPE SECT.;
TEST RR / CS ALTERNATE TEST REMARKS 46ES9-98 0-4 3
C 8.00 CK SA FF-1 46MOV-101A E-6 3
8 10.00 GA MO TM-1 P!-3 46MOV-1018 D-6 3
B 10.00 CA MO TM-1 PI-3
'46MOV-102A E-6 3
8 8.00 CA MO TM-1 PI-3 4M OV-1028 D6 3
8 8.00 CA M0 TM-1 PI-3 REV. to: 5 PAGE 107 of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT l
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVE 8 i-APPENDIX B 7_
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Cold Shutdown Justifications 1.
SYSTEM:
REACTOR WATER RECIRCULATION (RWR)
COMPONENTS:
02MOV-53A, B CATEGORY: B SAFETY FUNCTION:
These valves close, on low reactor pressure to isolate the faulted loop coincident with initiation of the RHR System in the LPCI mode, to prevent diversion of LPCI flow.
JUSTIFICATION:
In order to exercise these valves, the respective recirculation pump must be secured.
Securing either pump (single loop operation) is limited by Technical Specification requirements and is not prudent.
Single loop operation also requires a reduction in power.
2.
SYSTEM:
RESIDUAL HEAT REMOVAL COMPONENTS:
10AOV-68A, B CATEGORY: A,C SAFETY FUNCTION:
These valves open to provide flowpaths for LPCI and core spray injection to the reactor vessel.
They close for pressure isolation from the reactor vessel.
JUSTIFICATION:
With the reactor at operating pressure, the RHR pumps cannot develop sufficient discharge pres-sure to open these valves.
The installed air operators are designed to open these valves at zero dif ferential pressure which is not practical with the reactor at operating pressure.
Therefore, these valves cannot be full or part-stroke exercised during normal plant operation.
Since there is no position indication for these
- valves, closure verification must be done by backflow testing.
Such testina during plant operation is impractical due to personnel safety concerns related to the potential release of radioactive steam at high pressure.
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l Rev. No.
6 Page 108 of 167
NEW YORK POWER AUTHORITY I.
JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVE 8 APPENDIX B f%.
Cold Shutdown Justifications 3.
SYSTEM:
RESIDUAL EEAT REMOVAL l
COMPONENTS:
10MOV-17 and 10MOV-18 CATEGORY: A SAFETY FUNCTION:
These valves remain closed to protect the RHR-System piping and components from over-pressurization during plant-operation
.and inadvertent drain down events while in cold shutdown.
They also-perform a
containment isolation function.
JUSTIFICATION:
With the reactor pressure greater than 75 psig, these valves are prevented from opening by an electrical interlock.
4.
SYSTEM:
REACTOR BUILDING CLOSED LOOP COOLING COMPONENTS:
15AOV-132A, B; 15AOV-133A, B CATEGORY: A SAFETY FUNCTION:
These valves close to provide containment p) isolation.
JUSTIFICATION:
During normal plant operation, these valves must remain open to provide cooling water to the recirculation pump motor ~ and seal coolers.
Closing these valves would result in damage to the recirculation pumps.
5.
SYSTEM:
REACTOR BUILDING CLOSED LOOP COOLING COMPONENTS:
15AOV-130A, B; 15AOV-131A, B; 15AOV-134A CATEGORY:-A SAFETY FUNCTION:
These valves close to provide containment isolation.
JUSTIFICATION:
Du? ting plant operation, these valves must remain open to provide cooling water to the Drywell coolers and Drywell equipment drain sump cooler.
Closing these valves during operation could cause a spike in Drywell pressure due to the. loss of-cooling water flow which may result a reactor scram and plant shutdown.
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Rev.'No.
3 Page 109 of 167
s NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INDERVICE TESIlyG PROGRAM FOR PUliPJ_AND VALVES APPENDIX B i
n v
cold stutdown Justificationn 6.
SYSTEM:
HIGli PRESSURE COCLANT INJECTION COMPONENT:
2311PI-18 CATEGORY: C SAFETY FUNCTION:
This valve opens to provi flowpath for the HPCI system injection to th sactor vessel.
JUSTIFICATION:
With the reactor at operating ressure, the HPCI pump can develop suf ficient discharge pressure to open this valve, however HPCI injection of cold water to the reactor vessel during critical operation could result in an undesirable reactivity excursion and thermal transient to the piping components.
During plant operation the differential pressure developed across the valve disc could be in excess of 1000 paid - precluding manual manipulation of the valve.
Therefore, these valves cannot be exercised during normal plant operation.
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7.
SYSTEM:
CONTROL ROD DRIVE HYDRAULICS COMPONENTS:
03HCU-115 (Typical for 137 HCUs)
CATEGORY: C SAFETY FUNCTION:
These valves close on initiation of a scram to prevent diversion of ucram drive water f3cw into a depressurized charging header.
JUSTIFICATION:
Exercising these valves dt. ring operation wou'.d require depressurization of the charging header with the potential for a loss of scram function.
8.
DELETED 9.
SYSTEM:
FEEDWATER COMPONENTS:
34NRV-111A,B CATEGORY: A,C SAFETY FUNCTION:
These valves close to provide containment isolation and to prevent diversion of HPCI flow into the feedwater system.
JUSTIFICATION:
Exercising these valves during operation would require isolation of feedwater flow to the 0.4 reactor vessel.
This not prudent nor practical without a plant shutdown.
Rev. No.
6 Page 110 of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR PCWER PLANT IEDIBYlCZ_lIDIIFO PROGRhM FOR PUMPS AllD_.YhkVIE APPENDIX D cold Shutdown Justifications
- 10. SYSTEM:
CONTAINHENT VENT & PURGE COMPONENTS:
27AOV-111, 112, 113, 114, 115, 116 CATEGORY: A SAFETY FUNCTION:
These valves close to provide a containment isolation function.
JUSTIFICATION:
Due to N9C concerns that these valves will not close under Design Basis AccidenP. conditions, they will not be opened whenever primary containment is required except for safety-related reasons.
For this rcapon these valves will be tested at cold shutdown when primary containment is not required.
11.
DELETED
- 12. SYSTEM:
MAIN STEAM COMPONENTS:
29AOV-86A, B,
C, D
CATEGORY: A SAFETY FUNCTION:
These valves close to provide containment isolation.
JUSTIFICATION:
Performance of the fail close test for the MSIVs requires entry into the steam Tunnel. This cannot*
be done during normal operation.
- 13. SYSTEM:
MAIN STEAM COMPONENTS:
29MOV-203A, B CATEGORY:
B SAFETY FUNCTION:
These valves open to provide flowpaths for post-accident MSIV packing leak-off to the standby gas treatment system.
JUSTIFICATION:
Opening these valves during power operation could sub' ject downstream piping to pressures in excess of its 150 psi design pressure.
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5 Page 111 of 167
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT Il(RIAVICE TESTING _ PROGRAM FOR EVMPS AND VALVES APPENDIX D Cold Shutdown Justifications
- 14. SYSTEM REACTOR BUILDING CLOSED LOOP COOLING COMPONENTS:
15RBC-21A,B CATEGORY:
AC ISRBC-22A,B C\\TEGORY:
A SAFETY FUNCTION:
These valves close for containment isolation.
JUSTIFICATION:
Closing these valves would interrupt cooling water flow to the reactor recirculation pumps.
During normal plant operating conditions, this could result in significant damage to these pu:nps.
- 15. SYSTEM:
REACTOR DUILDING CLOSED LOOP COOLING COMPONENTS:
15RBC-24A,B CATEGORY:
A SAFETY FUNCTION:
These valves close for containment isolation.
JUSTIFICATION:
Exercising these valves will interrupt cooling water flow to one of the two operating containment vessel (drywell) cooling water trains.
Due to the limited capacity of the drywell cooling system, under normal operating conditions this could result in a significant temperature excursion within the drywell with the associated potential for a plant trip on "high containment pressure".
- 16. SYSTEM:
HIGH PRESSURE COOLANT INJECTION COMPONENT:
23HPI-13 SAFETY FUNCTION:
This valve opens to allow condensate drainage from the steam exhaust piping to the suppression chamber.
It closes for containment isolation.
JUSTIFICATION:
Closure verification for this valve is accomplished by performing a back flow test where the drain line is isolated from the steam exhaust line and the torus - is vented to atmosphere.
Placing the HPIC system and containment in this configuration during plant operation is undesirable and could. adversely affect the
~
plant's response in the event of an accident.
Rev. No.
6 Page 112 of 167
NEW YORK POWER AUTil0RITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PRQGRAM FOR PUMPS AND VALVES r
APPENDIX B v
- 17. SYSTEM:
REACTOR COOLANT ISOLATION COOLING COMPONENT:
13RCIC-37 and 13RCIC-38 SAFETY FUNCTION:
These valves open to eliminate any differential pressure that could force water from the suppression chamber into the RCIC steam exhaust piping when the suppression chamber pressure is greater than atmospheric.
JUSTIFICATION:
Verifying proper operation of these valves involves a test that requires isolation of the vacuum breakers for an extended period of time.
During this test the RCIC System is considered to be inoperable.
Due to operational cencerns associated with the plant's response to possible transients without an operable RCIC system, it is O
considered to be imprudent to test these valves while the plant is operational.
- 18. SYSTEM:
REACTOR COOLANT ISOLATION COOLING COMPONENT:
13RCIC-7 SAFETY FUNCTION:
This valve opens to allow condensate drainage from the steam exhaust piping to the suppression chamber.
It closes for containment isolation.
JUSTIFICATION:
Closure verification for this valve is accomplished by performing a back flow test where the drain line is isolated from the steam exhaust line.
Placing the RCIC system in this configuration during pl. ant operation is undesirable and could adversely affect the plant's response in the evedt'of a transient.
1O Rev. No.
6 Page 113 of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT IEDIBILQE TESTING PROGRAM EOR PUMPB AFD VALyXS APPENDIX D O
Valve Relief Requests NOTE V1 SYSTEM:
Reactor Water Recirculation (RWR)
VALVES:
02-2RWR-13A, B CATEGORY:
A,C CLASS:
1 FUNCTION:
These recirculation pump seal water injection valves close to provide conthinment isolation.
TEST REQUIREMENT:
Per IWV-3521, exercise' valves closed every three inonths.
BASIS FOR RELIEF:
To test during normal operations or cold shutdown requires securing the RWR pumps and entering containment to check the valves closed via a back-leakage test.
Testing during operation is therefore impossible and, during cold shutdown, O
performing back-leakage tests would place an undue burden on the plant staff.
ALTERNATE TESTING:
During each refuel outage, these normally open valves will be verified to close during leak testing performed per 10CFR50, Appendix J.
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O Rev. No.
3 Page 114_ of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B
- O Valve Relief Requests 8
EPlE_Y2 SYSTEM:
Control Rod Drive (CRD)
VALVES:
03AOV-126 03HCU-114 03A0V-127 CATEGORY:
B C
CLASS:
2 2
FUNCTION:
DCME reactor scram, 03 AOW-12 6 and -127 receive a signal to open and thus allow the scram charging water flow from the HCU accumulators to the CRD mechanism and the scram discharge water flow from-the CRD mechanism to the scram discharge volumes.
Check valve 03HCU-114 is located downstream of 03AOV-127, and opens to permit scram discharge flow.
TEST REQUIREMENT:
Per IWV-3411, exercise these valves for operability O
every three months.
Per IWV-3413(b), the strokeI time of all power-operated valves shall be measured.
BASIS FOR RELIEF:
Exercising these valves quarterly during power operations would result in rapid insertion of control rods.
This is undesirable because of subjecting the reactor core to rapid reactivity transients The AOVs are fast-acting valves with full-stroke time within a fraction of a second and are not equipped with indication o f *. b o t h open and close position.
Direct measurement of full stroke time is impractical.
ALTERNATE TESTING:
These valves will be tested in accordance with the JAF Technical Specificatios scram time test requirements as follows:
10% of all operable control rods shall be e
scram time tested every 16 weeks (TS Section 4.3.C.2)
O Rev No.
3 Page 115 of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT IN8ERVICE TESTING PROGRAM FOR PUMP 8 AND VALVE 8 APPENDIX B Valve Relief Recuests NOTE V2 (cont'd.)
All operable control rods shall be scram time tested after each refueling outage with reactor pressure above 950 psig (TS Section 4.3.C.1).
In all cases the measurede scram time will. be evaluated.
A satisfactory scram time test verifies proper operation of these valves.
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Rev. No.
3 -
Page 116.of __167_
NEW YORK POWER AUTHORITY,
JAMES A. FITZPATRICK NUCLEAR POWER PLANT IFSERVICE TESTING PROGRAM FOR PUMPS AND VALVES _
APPENDIX D (m).
y Valve Relief Recuests NOTE V3 This relief request nas been withdrawn.
NOTE V4 This relief request has been withdrawn.
i O
1 Rev. No.
6 Page 117 of 167
11EW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVER APPENDIX D Valve Relief Recuests
-NOTE V5 SYSTEM:
VALVES:
11SLC-16 5
11SLC-17 CATEGORY:
A,C CLASS:
1 FUNCTION:
These valves prohibit backflow from the reactor vessel to the SLC System and provide for containment isolation.
They open to permit SLC System flow to the reactor vepsel.
TEST REQUIREMENT:
Per IWV-3521, exerciso valves every-three
- months, t,
BASIS FOR RELIEF:
Full or partial-stroke exercising these valves requires that flow be established through the
(
subject check valves.
The only practical means of initiating flow through these valves requires actuation of the SLC system and pumping from the SLC Tank te the reactor vessel.
This would introduce boron into the rea*ctor vessel resulting in unacceptable reactivity and chemistry transients.
Testing during cold shutdown would-result in chemistry transients and undue burden on-the plant staff with respect to maintenance of the SLC Pump explosive valves.
ALTERNATE TESTING:
Once during each operating cycle (ncrmally a refuel outage) and as required by Technical Specifications, the valves shall be cycled-open by injecting water into the reactor vessel by use of the Standby. Liquid Control pymps.
Following the exercise test ag described above,-the valves will be verified to close by means of a leakrate test performed per LOCFR50, Appendix J.
D Rev. No.
'3 Page 118 of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B O
valve Relief Recuests NOTE V6 SYSTEM:
Reactor Core Isolation Cooling VALVES:
13RCIC-04 13RCIC-05 CATEGORY:
A,C CLASS:
2 FUNCTION:
These valves close to provide containment isolation.
TEST REQUIREMENT:
Per IWV-3521, exercise these valves closed every three months.
BASIS FOR RELIEF:
These valves are exercised open during RCIC surveillance testing performed periodically during n
plant operations in accordance with. the JAF
(
Technical Specifications.
S i n c e there is no provision on either of these valves that provides' position indication of ' he disc, valve closure must be verified by backflow or leakage testing.
In order to verify valve closure by. the backflow technique, the RCIC exhaust line must be isolated for the duration of the tdst causing the RCIC System to be inoperable.
potential safety impact of voluntarily placing'Thethe RCIC System in an l
inoperable rtatus during plant operation at power is considered to be imprudent and unwarranted in relation to any apparent gain in system reliability derived from the closure verification.
In
- addition, the valves are located approximately twenty (20) feet from the floor necessitating erection of a large scaffold in the vicinity of_ the RCIC pump.
This also is considered to be undesirable from the aspect of potential damage to l
RCIC System components should the scaffold be subjected to structural failure.
l Rev. No.
5 Page 119 of.167 l-
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPB AND VALVES APPENDIX B O
Valve Relief Requests NOTE V6 (cont'd.)
Based on the foregoing discussion, testing of these valves during plant operation at power is considered to be impractical.
During cold shutdowns, erection of the scaffold in addition to other activities related to test performance would place an extreme burden on ' the plant staff and would likely result in unwarranted extehsions to all forced outages with the added negative-impact on plant performance and avat, lability.
Verifying closure of these' valves during each refuel outage will provide sufficient assurance that the valves will continub to be operable with respect to their capability to close.
ALTERNATE TESTING:
At each refueling outage, these valves will ~ be verified to close in conjunction with leak testing performed per 10CFR50, Appendix J.
O-t bv Rev. No..
5 Page 120 of 167
NEW YORK POMER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR_ PUMPS AND VALVES
.i APPENDIX B e.
O Valve Relief Rectuests I
l NOTE V7 This relief request has been withdrawn.
1 NOTE V8 This relief request has been withdrawn.
l i
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page 121. f 167.
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT IEEIRVICE TESTING PROGRAM FOR PUMPS AND VALVER APPENDIX B O
valve Relief Reauests NOTE V9 SYSTEM:
High Pressure Coolant Injection (HPCI)
VALVE:
23HPI-61 CATEGORY:
C CLASS:
2 FUNCTION:
This valve opens to provide a flowpath from the suppression chamber to the suction of the HPQI booster pump.
TEST REQUIREMENT:
Per IWV-3521, exercise this_ valve open every three months.
BASIS FOR RELIEF:
The only practical method available to full flow' exercise this valve is to pump water from the sup-pression pool into the reactor vessel or the Condensate Storage Tank.
Due to the lack of O
suitable water quality in the suppression' pool 3 neither of these options is practical.
ALTERNATE TESTING:
This valve will be partial-flow tested once per operating cycle.
At least once every six (6) years this valve will be disassembled, inspected,,, and verified to be operable.
O Rev. No.
3 Page 122 of 167
.~ _._ _ _. _ __ _ _... _
NEW YORK POWER' AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER. PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES i
3 e
APPENDIX B.
valve Relief Reauests NOTE V10 This relief request has been withdrawn.
I i
NOTE Vil This relief request has been withdrawn.
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.Rev.
No.-.
6 Page~ 123- 'of 167' f.
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NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INDERVICE TESTING PROGRAM FOR PUMPB AND VALVEg APPENDIX D O
Valve Relief Requests NOTE VLZ SYSTEM:
Feedwater System VALVES:
34FWS-28A, B CATEGORY:
A,C CLASS:
1 FUNCTION:
These valves close for containment isolation upon cessation of feedwater flow during accident conditions.
TEST REQUIREMENT:
Per IWV-3521, exercise thesd valves closed every three months.
BASIS FOR RELIEF:
There are no position indicators on these valves or other means to verify closure,
- thus, the only practical means of verifying closure is to perform a backflow or leakage test.
Performing such a test O.
requires entry into the containment vessel and extensive system preparations, including draining of the main feedwater piping,from the outlet of the sixth point feedwater heaters'to the reactor vessel isolation valves (approximately 2000 gallons per line).
Furthermore, testing of 34FWS-28B requires shutdown of the cleanup system.
It is estimated that testing of either of these valves would require up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and demand significant staff resources.
During plant operation at
- power, these valves cannot be closed without precipitating a plant shutdown.
Verifying closure of these valves during each refuel outage will provide sufficient assurance that the valves continue to be operable with respect to their capability to close.
ALTERNATE TESTING:
At each refueling outage, these valves will be verified t: close in conjunctJon with leak testing performed per 10CFR50, Append.ix J.
Rev. No.
5 Page -124 of-167
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVE 8 I
APPENDIX B O
Valve Relief Requestn NOTE V13 This relief request has been withdrawn.
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Rev. No. _1_
Page 121_ of 16' _
NEW YORK POWER AUTil0RITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT U!DIEVICE TEDTING PROGRAM FOR PUMPS KliD VALVES APPENDIX D O
Valve Relief Requents NOTE V14 SYSTEMt Instrument Air VALVES:
391AS-22 391AS-29 CATEGORY A,C CLASS:
2 FUNCTION:
These valves open to provide n'itrogen to the MSIV's and the SRV accumulators inside the containment.
They close for containment isolation.
TEST REQUIREMENTS Per IWV-3521, exercise these valves open every three months.
BASIS FOR RELIEF:
Exercising these valves (open) is performed by charging the bleed-down header following MSIV testing.
During plant operation at power, this is impractical since closure of the MSIV's would cause a
plant trip.
- Also, performing such a test requires entry into the containment vessel and local manipulation of test connections located inside the drywell.
During plant operation at power and, on occasion, while in the cold shutdown mode, the containment atmosphere is maintained in a nitrogen-inerted condition.
During such periods, entry into the containment is not practical due to personnel safety concerns.
ALTERNATE TESTING:
These valves will bra exercised (open) during cold shutdown periods when the containment is de-inerted consistent with the requirements of IWV-3522 and the provisions of Note V51.
O Rev. No.
5 Page 126 of 167
_ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _1 NEW YORK POWER AUTHORITY
)
JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTINQ_PRQQBAM FOR PUMPS AND VALyIl J
i APPENDIX D
>O Valve Relief Requests l
NOTE V15 This relief request has been withdrawn.
NOTE V16 This rollef request has been withdrawn.
e 4
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I U l-Rev.-No.
6 Page 127 of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSE_RVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX D O
Valve Relief Requests 1{D.TE V l?
SYSTEM:
High Pressure Coolant Injection VALVES:
23HPI-402 23HPI-403 CATEGORY:
C CLASS:
2 FUNCTION:
These v.
= open to eliminate any differential pressure t
could force water from the suppressw aamber into the HPCI exhaust piping when the suppression chamber pressure is greater than atmospheric.
They close to prevent HPCI exhaust steam f rom entering the suppression chamber air space, thus bypassing the quenching action of the suppression pool.
TEST REQUIREMENTS:
Per IWV-3 521, exercise these valves open and closed O
every three months.
BASIS FOR RELIEF:
There are no position indicators on these valves or other means for verifying valve closure, thus-the only practical means of verifying closure is to perform a backflow or leaksge test.
Since the valves are installed in serie's with no intermediate test tap, verifying that each individual valve closes is not practical.
In order to perform the specified safety function in the closed direction, only,one valve of the pair needs to close.
Thus, verify.ing that either valve closes is adequate to demonstrate reliable operation of the pair.
Operation of the HPCI pump turbine itself does not prove operability of these valves and special testing is required.
This testing necessitates isolation of the vacuum breaker piping which, in
- turn, results in the inoperability of the HPCI System for the duration of the test.
Due to the importance of the HPCI system function and the lack of a redundant HPCI train, it is not considered prudent to perform this testing during plant operation at power.
Rev. No.
_.5_.
Page 128 of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX D Valve Relief Reauests NOTE V17 (cont'd.)
ALTERNATE TESTING:
These valves will be exercised open and the pair (at least one valve) will be verified to close during cold shutdown periods per IWV-3522.
Should the closure test of both valves
- fail, then corrective action will be applied to both valves prior to returning the system to operability.
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oG Rev. No.
5 Page 129 of _112__
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWEg PLANT INSERVICE TESTING PROGRAM FOR PUMPB AND VALVES APPENDIX B
\\s valve Relief Recuests NOTE V18 This relief request is withdrawn.
l f)
C/
Rev. No'.
3 Page 130 of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER' PLANT INSERVICE TESTING PROGRAM FOR PUMP 3 AND VALVES APPENDIX B Valve Relief Recuests NOTE V19 SYSTEM:
Containment Isolation Valves VALVES:
See Valve List Attached CATEGORY:
A CLASS:
See Valve List Attached FUNCTION:
Containment Isolation.
TEST REQUIREMENT:
Per IWV-3426, measure individual containment isolation valves leak rates.
BASIS FOR RELIEF:
By original plant design, these valves are tested in established groupings to determine a penetration leak rate.
The Appendix J,
Type C LLRT test methodology has been reviewed and addressed in Section 3.7 of the Technical Specifications.
-C
(
ALTERNATE TESTING:
Test these containment isolation valves by the original design groupings.
v Rev. No.-
3 Page 131 of 167 t
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT-INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B
(,
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Valve Relief Recuests NOTE V19 (cont.1 VALVE ID CLASS VALVE ID CIASS 10MOV-26A,B 2
10MOV-31A,B 2
10MOV-38A,B 2
10MOV-39A,B 2
27AOV-116 2-10RHR-52A,B 2
12MOV-69 1
13MOV-15 1
27AOV-131A,B 2
13MOV-16 1
27AOV-132A,B 2
13MOV-21 1
27 CAD-67,68,69,70 2
15RBC-21A,B 3
27MOV-113, 2
15RBC-24A,B 3
16-1A0V-101A,B 2
16-1AOV-102A,B 2
23MOV-15 1
27VB-6 2
23MOV-16 1
27VB-7 2
23MOV-19 1
29AOV-80A,B,C,D 1
l 23MOV-60 1
29AOV-86A,B,C,D 1
27AOV-101A,B 2
34NRV-111A,B 1
46ESW-15A,B 3
46ESW-16A,B 3
9 N
'Og Rev. No.
6 Page 132' of 167
= _. =.
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~
NEW YORK POWER AUTHORITY
. JAMES A.
FITZPATRICK NUCLEAR. POWER PLANT.-
INSERVICE TESTING PROGRAM FOR PUMPS AND VALvR APPENDIX B O
Valve Relief Recuests NOTE V20 This relief request has been withdrawn.
NOTE V21 This relief request has been withdrawn.
4 i
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I NEW YORK POWER AUTHORIT'Y JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVE 8 APPENDIX B
(~),
. \\J Valve Relief Reouests NOTE V22 SYSTEM:
High Pressure Coolant Injection VALVE:
23HPI-56 CATEGORY:
C CLASS:
2 FUNCT FN:
Opens to permit HPCI turbine condensate to drain to the suppression chamber.
TEST REQUIREMENTS:
Per IWV-3521, exercise this valve open every three months.
BASIS FOR RELIEF:
There is no means for exercising this valve to the open position where positive indication of acceptable valve performance,is verified.
f ALTERNATE TESTING:
In accordance with Generic Letter 89-04 Position 2, 73 t (s) at least once during each operating cycle (normally l
a refuel outage) the valve will be disassembled, inspected, and verified to be operable.
1 f
I l
Rev. No.
3 Page 134 of. 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B
!O Valve Re1lef Rectuests 110TE V23 This relief request has been withdrawn.
NOTE V24 This relief request has been withdrawn.
110TE V2 5 This relief request has been withdrawn.
IJOTE V26 This relief request has been withdrawn.
O O
Rev. No.
6 Page 135_ of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWElt PLANT l
l INSERVICE TESTING PROGRAM FOR PUMPS AND VALyfa APPENDIX D p
Valve Relief Requests NOTE V27 SYSTEM:
Automatic Depressurization (ADS)/ Main Steam VALVES:
02RV-71A,B,C,D,E,F,G,H,J,K and L CATEGORY:
B,C
~
CLASS:
1 FUNCTION:
All these valves are required to open when actuated by manual switch to relieve reactor pressure during an accident or transient condition.
Valves 02RV-71A,B,C,D,E,G, and H open upon receipt of ADS actuation signal.
TEST REQUIREMENT:
Per IWV-3411 and 3413 (b), exercise and measure the stroke time every three months.
BASIS FOR RELIEF:
These valves are f ast-acting valves and do not have s' '
position indication.
Therefore, stroke time cannot be effectively measured.
When testing these valves, a reactor pressure of at least 50 psig is needed for opening by the pilot assembly and a minimum reactor pressure of 940 psig is specified to minimize potential damage to the pilot valve and disc surfaces.
Testing at each start-up from a cold shutdown condition would produce additional stress cycles which may lead to a low cycle fatigue failure.
ALTERNATE TESTING:
Following each refuel outage pr once each operating cycle with reactor pressure at least 940 psig, these valves will be exercised in accordance with the operational test requirements set forth in the JAF Technical Specifications.
SRV ta ilpipe --
temperature and acoustic monitors will be used to verify valve opening.
Additionally, in accordance with Technical Specification requirements, the pilot assembly for each SRV will be bench tested at least once every two operating cycles. The bench.
testing includes "as-found" setpoint, leakage and pilot disc sticking tests.
G l
Page -136 of 167 Rev. No.
3
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX D O
Valve Relief Recuests NOTE V27 (cont.)
In addition to the pilot assembly bench testing, refurbishment is performed, if necessary, in accordance with the valve manufacturer's procedure including inspection of the pilot valve stem labyrinth seal area.
Thise program of testing, inspections, and maintenance is performed in accordance with the related 'BWROG recommendations to monitor and resolve setpoi,nt drift problems.
O O
Rev. No.
3 Page 137 of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPB AND VALVES APPENDIX B Valve Relief Recuests NOTE V28 SYSTEM:
Various VALVES:
Excess Flow Check Valves (Attached)
CATEGORY:
A,C CLASS
- 1 FUNCTION:
Tht. 'e valves close to, isolate the respective instrument lines in the event of a pipe break downstream of the valves.
TEST REQUIREMENT:
Per IWV-3521, exercise these valves closed every three months.
BASIS FOR RELIEF:
Testing these valves requires isolation of their associated safety-related instrument which could place the plant in an unsafe condition.
In
- addition, the induced hydraulic transients 9
resulting from establishing flow and subsequent valve closure would most likely result in an engineered safety feature actuation.
During such' testing, radiation doses to test personnel would be y
high due to the location of these valves and effluence of reactor water during the test.
These valves have proven to be highly reliable and-testing at the Code-required frequency would not significantly increase the, reliability of these valves.
ALTERNATE TESTING:
Exercise these valves closed for operability once each operating cycle.
O Rev. No.
3 Page 138 of 167
NEW YORK POWER AUTHORITY
. JAMES A.-FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPB AND VALVE 8 APPENDIX B O
valve Relief Reauests NOTE V28 (cont.)
EXCESS FLQW CHECK VALVES 02-2EFV-PS-128A,B 02-3EFV-11 02-3EFV-23 02-2EFV-PT-24A,B 02-3EFV-13A,B 02-3EFV-25 02-2EFV-PT-25A,B 02-3EFV-15A,B 02-3EFV-31A,B,C,D 02-2EFV1-DPT-111A,B 02-3EFV-15N 02-3EFV-31E,F,G,H 02-2EFV1-FT-110A,C,E,G 02-3EFV-17A,B 02-3EFV-31J,K,L,M 02-2EFV2-DPT-111A,B 02-3EFV-19A,B 02-3EFV-31N,P,R,S 02-2EFV2-FT-110A,C,E,G 32-3EFV-21A,B,C,D 02-3EFV-33 02-3EFV-23A,B,C,D 13EFV-01A,B 14EFV-31A,B 13EFV-02A,B 23EFV-01A,B 29EFV-30A,B,C,D 29EFV-53A,B,C,D
)
23EFV-02A,B 29EFV-34A,B,C,D 29EFV-54A,B,C,D O
?
O Rev. No. _1_
Page 139 of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT IMEM19.E_1ERTING PROQBA}i_f_QR PUMPB AFD VALVM APPENDIX B O
valve nelief Requests NOTE V29 SYSTEM:
Varjous VALVES:
Fast Acting Valves (Attached)
CATEGORY:
See Valve List on Next Page CLASS:
See Valve List on Next Page FUNCTION:
See Valve List on Next Page TEST REQUIREMENT:
Valve stroke time shall be evaluated and test intervals changed with respect to corrective action requirements of IWV-3417(a).
BASIS FOR RELIEF:
The measured stroke times of these valves are consistently well below two (2) seconds and can vary significantly due to circumstances unrelated to the condition of the valves.
Two reasons for these variations are inconsistency of operator reaction times and changes in system parameters.
,]
Because of this, trending the stroke times of these fast acting valves will provide inaccurate, and sometimes misleading indication of valve degradation.
ALTERNATE TESTING:
In accordance with Generic Letter 89-04, Position 6,
if the measured stroke time is greater than the maximum limiting stroke time of 2
- seconds, corrective action per IWV-3417 ( b) will be taken.
Test records will verify satisfactory stroke time is achieved but, need not require recording of the actual measured stroke time.
O Rev. No.
3 Page 140 of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING-PROGRAM FOR PUMPS AND VALVES APPENDIX B io yalve Relief Requests NOTE V29 (cont.)
VALVE ID CATEGORY CLASS FUNCTION 02-2SOV-001 A
1 Close 02-2SOV-002 A
1 Close 16-1AOV-101A, B A
2 Clo'se 16-1AOV-102A, B A
2 Close 23HOV-1 B
2 Close 23AOV-39 B
2 Close 23AOV-42 B
2 Close 27SOV-119E1, E2, F1, F2 A
2 Close-27SOV-120E1, E2, F1, F2 A
2 Close 27SOV-122E1, E2, F1, F2 A
2 Close 27SOV-123E1, E2, F1, F2 A
2 Close r-27SOV-124E1, E2, F1, F2 A
2 Close
(
27SOV-125A, B,
C, D
A 2
Close 27SOV-135A, B,
C, D
A 2
Close 27SOV-141 A
2 Open, Close 27SOV-145 A
2 Open, Close 27AOV-126A, B B
2 Open, Close 27AOV-128A, B B
2 Open, close 27AOV-129A, B B
2 Open, Close Note:
Function is the direction in which the valve-is considered to be fast acting, 5 2 seconds.
Rev. No.
6 Page 141 of _lf7_
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVE 8 APPENDIX B O
Valve Relief Recuests' NOTE V30 This relief request has been withdrawn.
NOTE V31 This relief request has been withdrawn.
NOTE V32 This relief request has been withdrawn.
NOTE V33 This relief request has been withdrawn.
O O
Rev. No.
6 Page 142 of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B Valve Relief Requests NOTE V34 SYSTEM:
High Pressure Coolant Injection VALVES:
23HPI-12 23HPI-65 CATEGORY:
A,C CLASS:
2 FUNCTION:
These valves open to provide a flowpath from the' HPCI turbine exhaust to the suppression pool.
They close to provide containment isolation.
TEST REQUIREMENTS:
Per IWV-3521, exercise these valves closed every three months.
BASIS FOR RELIEF:
These valves are exercised open quarterly during HPCI surveillance testing performed during plant operation in accordance with the JAF Technical 9
Specifications.
Since there is no disc position indication on either of these valves, closure must be verified by. backflow or leakage testing.
In order to verify valve closure by the backflow technique, the HPCI exhaust line must be isolated for the duration of the test, causing the HPCI System to be inoperable.
The potenti '
safety impact of voluntarily placing the HPCI System in an inoperable status during plant operation at power is considered to be imprudent and unwarranted in relation to any apparent gain in system reliability derived from the closure verification.
In
- addition, the valves are located approximately twenty (20) feet from the floor, nece,ssitating erection of a large scaf f old in the vicinity of the HPCI pump.
This also is considered to be undesirable from the aspect of potential damage to HPCI System components should the scaffold -be subjected to structural failure.
O Page 143 of 167 Rev. No.
5
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT IEEERVICE TESTING PROGRAM FOR PUMPS AHp VALVE 8 APPENDIX B Valvn Relief Recuests FOTE V34 (co_DLA1 Based on the foregoing discussion, testing of these valves during plant operation at power is considered to be impractical.
During cold shutdowns, erection of the scaffold in addition to other activities related to test performance would place an e xtrer.e burden on the plant staff and would likely result in unwarranted extensions to all forced catages with the added negative impact on plant performance and availability.
Verifying closure of these valves during each refuel outage will provide sufficient assurance that the valves will continue to be operable with respect to their capability to close.
ALTERNATE TESTING:
At each refuel
- outage, these valves will be verified to close in conjunction with leak testing performed per 10CFR50, Appendix J.
O l
Page 144 of _167 Rev. No.
5
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B
/l-4 v
4 Valve Relief Recuests i
NOTE V35 SYSTEM:
High Pressure Coolant Injection VALVE:
2 311PI-13 CATEGORY:
C
]
CLASS:
2 FUNCTION:
This valve opens to permit HPCI turbine condensate to drain to the suppression chamber.
TEST REQUIREMENTS:
Per IWV-3521, exercise this valve-open every three months.
BASIS FOR RELIEF:
There is no position indicator on this valve or any other means to verify the valve opens.
ALTERNATE TESTING:
In accordance with Generic Letter 89-04 Position 2, at least once each operating cycle -(normally a 7-s refuel outage) the valve will be disassembled,-
( j inspected, and verified to be operable.
Rev. No.
3 Page 145 of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVE 8 APPENDIX B O
valve Relief Reauests NOTE V31 This relief request has been withdrawn.
NOTE V37 This relief request has been withdrawn.
NOTE V38 This relief request has been withdrawn.
NOTE V39 This relief request has been withdrawn.
NOTE V40 This relief request has been withdrawn.
NOTE V41 This relief request has been withdrawn.
NOTE-V42 This relief request has been withdrawn.
()
NOTE V43 This relief request has been withdrawn.
NOTE V44 This relief request has been withdrawn.
NOTE V45 This relief request has been withdrawn.
O l
l Rev. No.
6 Page 146 of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS,AND VALVE 8 APPENDIX B pU Valve Relief Requests NOTE V46 SYSTEM:
Various VALVES:
Containment Isolation Val"es (26 inches Nominal Pipe Size)
CATEGORY:
A and A,C CLASS:
1 or 2 FUNCTION:
These valves close to provide containment isolation.
TEST REQUIREMENTS:
Per IWV-3427 (b), seat leakage rate shall be trended and corrective action taken.
BASIS FOR RELIEF:
Based on input from many utilities and NRC staff review of testing data at some plants, the NRC determined that the usefulness of IWV-3427(b) does not justify the burden of complying with the O'
requirements of IWV-3427(b).
ALTERNATE TESTING:
In accordance with Generic Letter 89-04, Position 10, these valves are provided with leak rate limits specified in accordance with IWV-3426 and will be repaired or replaced whenever seat leakages exceed established limits.
O Rev. No.
5 Page 147 of 167.
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE _1ESTING PROGRAM FOR PUMPB AND VALVER APPENDIX D O
valve Rollef Requents NOTE V46 (cont 21 VALVE ID VALVE ID 10MOV-26A,B 27AOV-101A,B 10MOV-27A,B 27AOV-111 10MOV-31A,B 27AOV-112 10MOV-39A,B 27AOV-113 12MOV-15 27AOV-114 12MOV-18 27AOV-115 13RCIC-4 27AOV-116 13RCIC-5 27AOV-117 14MOV-11A,B 27AOV-118 15AOV-130A 27VB-6 15RBC-24A 27VB-7 23HPI-12 29AOV-80A,B,C,D 23HPI-65 29AOV-86A,B,C,D 23MOV-15 34FWS-28A,B 23MOV-16 34NRV-111A,B 23MOV-19 46ESW-16B O
Rev. No.
5 Page 148 of 167
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-NEW YORK:pOWERJAUTHORITY<
^
JAMES'A.:FITZPATRICK? NUCLEAR PO.WERJPLANT
~
INSERVICE TEDTING PROGRAM ' FOR ' PUMP!t',hlID ~ VALVER 3
APPENDIX B.
'sQ Yalve Relief Recuests NOTE V47 SYSTEM:
liigh I'ressure Coolant JInjection.-
VALVES:.
2 31tPI-02 CATEGORY:
C CLASS:
2-FUNCTION:
This ' valve opens to provide a flowpath for minimum flow-from the HPCI main pump.
TEST REQUIREMENTS:
Per IWV-3521, exercise this valve;open every threel months.
BASIS FOR RELIEF:
Due to-the. configuration of the minimum.' flow motor:
operated valve control-logic, fully developed flow cannot- ~be -achieved through this-check. valve.-
Additionally, full-stroke exercisingL-_ca'nnot_'be, b
verified
-with existing instrumentation,-
'and
(
therefore cannot be performed. -
ALTERNATE TESTING:
In accordance ~with Generic Letter 89-04 ; Position 2,
-the valve will be disassembled and. inspected each operating cycle 1(normally a refuel! outage).;
1
(
1 r
O Rev.JNo.,_1.
Page-149 of. 167
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NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR-POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B' Valve Relief Recuests NOTE V48 SYSTEM:
Containment Atmospheric Dilution (CAD)
VALVES:
27VB-1 thru 5 CATEGORY:
A,C CLASS:
2 FUNCTION:
These valves open to relieve vacuum from.the suppression chamber to the drywell if differential pressure between them should exceed 0.5 psid.
They close to prevent bypass flow from the drywell to-the suppression chamber without the quenching action of the suppression pool.
TEST REQUIREMENTS:
Per IWV-3424 and IWV-3426, measure individual valve leakrates for valves.
Per IWV-34 27 (b), seat' leakage rate shall be trended t
and corrective action taken.
BASIS FOR RELIEF:
The configuration of the vacuum breaker lines precludes measuring individual valve leakrates.
In accordance with JAF Technical Specifications,.
Section 4.7.A.S.d, these valves are leak tested each cycle (normally during Itfueling outages) as a group with other elements of the containment vessels in conjunction with an integrated drywell/ suppression chamber bypass leakage test.
This test method may be subjected to significant variations associated with other contributing factors involved with the difficulty of performing the test rather-than indication of valve degradation.
As such, the usefulness of applying IWV-3427(b) would not justify the burden and uncertainties associated with the performance of this test.
ALTERNATE TESTING:
These valves will be tested together and appropriate acceptance criteria established in accordance with JAF Technical Specifications, Section 4.7.A.S.d.
O l
Rev. No.
5 Page _150 of 167
NEW YORK POWER AUTHORITY'~
JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALyla APPENDIX B O
valve Relief Fequests NOTE V49 SYSTEM:
Emergency Service Water VALVES:
46 (70) ESW-101 thru 104 CATEGORY:
B CLASS:
3 FUNCTION:
These valves are manually opened to provide ESW flow to Control and Relay Room air handlers to ensura continued cooling in the event the normal chilled water system is rendered inoperable.
TEST RECUIREMENTS:
Per IWV-3411, exercise these valves open every three months.
BASIS FOR RELIEF:
These valves provide isolation between the raw ESW System and the glycol / water mixture in the chilled water system.
Opening these valves will cause O
contamination of the glycol / water solution.
ALTERNATE TESTING:
These valves will be exercised during each reactor refueling outage.
O Page 151. of 167 Rev. No.
5
- - - - - - - ~ - - ~ -
NEW YORK POWER AUTHORITY' JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGIgMi FOR PUMP 8 AND VALVES APPENDIX B valve Relief Requests NOTE V50 SYSTEM:
Transversing In-Core Probe (TIP)
VALVES:
07SOV-104A, B,
C CATEGORY:
A CLASS:
~2 FUNCTION:
These valves close to provide containment isolation.
TEST REQUIREMENTS:
Per IWV-3 413 ( b), measure the full stroke time of the valve.
BASIS FOR RELIEF:
The computer control system for TIP system includes a provision for measuring valve cycle time (opened and closed) and not closure time alone.
The sequence opens the subject valve (stroke 2
seconds),
maintains it energized for 10 seconds O*
(including the opening stroke), and de-energizes the valve solenoid allowing the valve to stroke closed
(<
2 seconds).
The total elapsed valve cycle time is specified to be $ 12 seconds.
ALTERNATE TESTING:
The overall cycle time (opened and -closed) for these valves will be measured and evaluated per IWV-3413 and IWV-3417.
O l
Rev. No.
3 Page 152 of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK HUCLEAR POWER PLANT INSERVICE TESTING PROGRAM TOR PUMPS AND VALVE 8 APPENDIX B-Valve Re1lef Requests NOTE VS1 SYSTEM:
Various VALVES:
All valves tested during cold shutdown conditions, g
CATEGORY:
Various CLASS:
Various FUNCTION:
Various TEST REQUIREMENT:
Valves shall be exercised... unless such operation is not practical during plant operation.
If only limited operation is practical during plant operation, the valve shall be part-stroke oxercised during plant operation and full ctroke exercised during cold shutdowns.
Full stroke exercising during cold shutdowns for all valves not full-stroke exerciced during plant operation shall be on a frequency determined by the intervals between 9
shutdowns as follows:
exercise For intervals of 3 months or longer during each shutdown. (IWV-3412 and IWV-3522)
BASIS FOR RELIEF:
In many instances testing of all valves designated for testing during cold shutdown cannot be completed due to the brevity of an outage or the lack of plant conditions dbeded for testing specific valves.
It has been the policy of the NRC that if testing commences in a reasonable time and reasonable efforts are made to test all valves, then outage extension is not required when the only reason is to provide the opportunity for completion of valve testing.
ASME/ ANSI OMa-1987, Operation and Maintenance of Nuclear Power Plants, Part 10 (Paragraphs 4.2.1.2 and 4.3.2.2) recognizes this issue and allows deferred testing as set forth below.
O Rev. No.
5 Page 153 of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT 4
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES APPENDIX B O
valve Relief Requests NOTE V51 (cont.)
ALTERNATE TESTING:
For those valves designated to be exercised or tested during cold
- shutdown, exercising chall commence as soon as practical after the plant reaches a stable cold shutdown condition as defined by the applicable Technical S$ecification but no later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after reaching cold shutdown.
The 48-hour requirement need not apply if all valves are tested during an outage.
Valve testing need not be performed more often than once every three (3) months except as provided for in IWV-3417(a).
Completion of all valve testing during a cold shutdown outage is not required if the length of the shutdown period is insufficient to complete all testing.
Testing not completed prior to startup will be rescheduled for the next cold shutdown in a sequence such that the test schedule does not omit nor favor certain valves or groups of valves.
O O
Rev. No.
5 Page 154 of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT IN8ERVICE TESTING PROGBAM FOR' PUMPS AND VALVES APPENDIX B
(\\,,),
Valve Relief Requests NOTE V52 This relief request has been withdrawn.
NOTE V51 This relief request has been withdrawn.
l ob (J
L Rev. No.
6
' Page 155 of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS NND VALVES APPENDIX D O
Valve Relief Requests NOTE V54 SYSTEM:
High Pressure Coolant Injection VALVE:
23HPI-130 CATEGORY:
C CLASS:
2 FUNCTION:
This valve opens to provide a flowpath for cooling water circulation through the HPCI turbine lube oil cooler.
TEST REQUIREMENTS:
Per IWV-3521, exercise this valve open every three months.
BASIS FOR RELIEF:
This valve has no means of determining disc position or flowrate
- and, thus there is no mechanism for verifying full accident flow and nor 9
full-strche of this Nalve.
Satisfactory operation of the HPCI turbine during quarterly testing verifies adequate operation of valve and cooling system.
ALTERNATE TESTING:
In accordance with Generic Letter 89-04 Position 2, at least once during each operating cycle (normally a refuel outage) the valve will be disassembled, inspected, and verified to be operable.
\\
\\
O Rev. No.
3 Page 156 of 167
- - - = - - -
.------------~-----------------------q NEW YORK POWER AUTHORITY j
JAMES.A. FITZPATRICK NUCLEAR POWER PLANT j
_i IN8ERVICE TESTING PROGRAM-FOR' PUMPS AND VALVE 8_
.j i
APPENDIX B
^
' Valve'Re1lef Reouests-
-j
..i
-I NOTE-VSS SYSTEM:
Core Spray VALVES:
14 CSP-62A,B CATEGORY:
C CLASS:
2 FUNCTION:
The 14 CSP.-62A and B valves open to-provide minimum flow required for the core spray' holding pump and<
close to prevent reverse flow from the. Torus.,
TEST REQUIREMENTS:
Per IWV-3521, exercise these valves closed every three months.
' BASIS FOR RELIEF:
There are no position indicators or other meaus to verify closure of these.. valves, thus, the: only-practical--method of verifying' closure-is by means of back-leakage tests.
Due to-the lack Lof 0,
appropriate: isolation and test connections these valves cannot be verified to close by' means: of a reverse flow test.
Any system modification perf ormed to:- provide E a
-means by which these valves can be backflow tested will result-in'an: arrangement that requiresiset-up land connection of a hydrodtatic. pump --inFa Thigh radiation area.
System line-
. changes land. effort i
involved-with testing wet,ld.
constitute
- an unreasonable-burden on the plant-staff; ALTERNATE TESTING:
During the. next -reactor re ueling. outage, the system will be modified-to provide an appropriate means of - - reverse flow testingt these. valves to verify closure.- Following'the modification, during each refuel outage these valves will be verified to
-close via a hydrostatic leak rate test.
k '*.
Rev. No.
6 Page 157 of -167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT I
INSERVICE TESTING PROGRAM FOR PUMPS AND VALVE 8 l
APPENDIX B O
Valve Relief Recuests NOTE V56 SYSTEM:
Residual Heat Removal VALVES:
10RHR-95A,B CATEGORY:
C CLASS:
2 FUNCTION:
These valves close to prevent reverse flow from the Torus.
TEST REQUIREMENTS:
Per IWV-3521, exercise these valves closed every three months.
BASIS FOR RELIEF:
These are simple check valves with no means of determining disc position without performing a backleakage test.
Performing such a test, would require setting.up a hydrostatic pump in a high radiation area.
O During cold shutdown, the system lineup changes and effort involved with testing would constitute an unreasonable burden on the plant staff.
ALTERNATE TESTING:
During each refuel outage these valves will be verified to close during a hydrostatic leakrate 8
test.
's O
Rev. No.
3 Page 158 of 167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVE 8 p
APPENDIX B valve Relief Recuests NOTE V57 SYSTEM:
Core Spray VALVES:
14AOV-13A,B CATEGORY:
A,C CLASS:
1 FUNCTION:
These valves open to provide flowpaths from the Core Spray System to the reactor vessel.
They close for pressure isolation protection of the low pressure core spray piping.
TEST REQUIREMENTS:
Per IWV-3521, exercise these valves open every three months.
BASIS FOR RELIEF:
There is no mechanism by which these valves can be full-stroke exercised without injecting water from G
the core spray pumps to the reactor vessel.
V During plant operation, the core spray pumps cannot produce sufficient discharge pressure to overcome reactor vessel pressure and provide flow into the vessel.
The installed air operators are capable of exercising the. valves, providing there -is no differential pressure across the valve seat; obviously this is not the case.
During cold shutdown, injecting into the reactor.
vessel requires a major effort to establish the prerequisite conditions and realignment of the Core Spray System to allow supplying water from the CST.
Torus water cannot be used since it does not meet ~
the chemistry requirements for reactor grade make-up.
It'is estimated that such a test would take-about 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perform and' would result in a significant burden on the plant operating staff. In addition, there is a potential for overfilling the reactor vessel and flooding the main steam lines.
This could adversely affect the performance of the main steam safety / relief valves (SRV's) since there is cause.to believe that a contributing factor to the historically poor performance of the SRV's'is water contamination of the operators.
O Rev. No.
5 Page 159 of 167
..NEW-YORK; POWER'AUTHORITE. w
{
JAMES:A.:-FITZPATRICK-~ NUCLEAR POWER PLANT
-INSERVICE TESTING' PROGRAM FOR PUMPS AND VALVE 8 4
-l I
APPENDIX-B i
O 1
Valve-Relief Requests NOTE V57 (cont.1 The'. installed check valve. operators are_ capable.of exercising the' valves throughx their full stroke;.:
- Lhowever, the-. sizing' ' of the.~ operators, does' not '
satisfy the criteria set-- forth - in IWV-3522 (b).
ALTERNATE TESTING:
During cold shutdown, each.of these valves will be-exercised using the installed ~ operators.
Each of these valves will'be full-stroke exercised during each refuel outage by injecting-full accident flow into the reactor. vessel.:.
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4 pey, No.-
5 Page -160 of -167
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NEW YORK' POWER AUTHORITY I
JAMES A.
FITZPATRICK NUCLEAR POWER PLANT IMSIRVICE TESTING PROGRAM FOR-PUMPS AND VALVES APPENDIX D Valve Re}iof Requests-NOTE V58 SYSTEM:
Automatic Depressurization VALVES:
02RV-1 thru 02RV-11 02VB-1 thru 02VB-11 CATEGORY:
C CLASS:
2 FUNCTION:
These valves remain closed to prevent steam from an open safety / relief valve (SRV) from entering the drywell.
They open following closure of an SRV to.
prevent the formation of a water column within the downcommer that could cause' torus damage during; subsequent lifting of the same $RV.
TEST REQUIREMENTS:
Per IWV-3521, exercise these valves open and closed every three months.
k BASIS FOR RELIEF:
Exercising these valves require local manipulation of each valve and thus entry into the containment.
During plant operation at power, and on occasion while in cold. shutdown, the containment atmosphere is maintained in a nitrogen-inerted condition.
During such periods, entry _into the containment is not practical due to personnel safety concerns.
ALTERNATE TESTING:
These valves will be exercised during cold shutdowns when the containment is de-inerted consistent with the requirements of IWV-3522 and the provisions of Note VSI.
O Rev. No.
5 Page 161 of 167
i NEW YORK POWER AUTHORITY JAMES A.
FIT 2 PATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVER
~
APPENDIX B U
Valve Polief Requents NOTE V59 SYSTEM:
Main Steam VALVES:
29AOV-80A, B,
C, D
CATEGORY:
A CLASS:
1 FUNCTION:
These valves are normally open to provide steam to the main turbine generator and auxiliaries.
They close to isolate steam flow and for containment isolation.
TEST REQUIREMENTS:
Per IWV-3415, fail-safe test these valves closed every three months or during cold shutdowns.
BASIS FOR RELIEF:
Fall-safe exercising these valves requires local manipulation of valves located inside the
(
containment vessel and thus entry into the (gJ containment.
During plant operation at power, and on occasion while in cold shutdown, the containment atmosphere is maintained in-a nitrogen-inerted condition.
During such periods, entry 'into the-containment is not practical -due to personnel safety concerns.
ALTERNATE TESTING:
These valves will be fail-safe exercised during-cold shutdowns when the containment is de-inerted' consistent with the requirements of IWV-3415 and the provisions of Note V51.
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Rev. No.
5 Page 162 of 167
1 NEW YORK POWER AUTHORITY JAMES-A. FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VAIVE_8 j
8 t
l
\\
APPENDIX B m
qy v
Valvt Relief Reauests NOTE V60 l
SYSTEM:
Residual Heat Removal VALVES:
10AOV-68A,B CATEGORY:
A,C CLASS:
1 FUNCTION:
These valves open to provide LPCI injection and close to provide containment-and pressure isolation.
TEST REQUIREMENTS:
Per IWV-3 521, exercise these valves open and closed every three months.
BASIS FOR RELIEF:
These valves may be exercised by-either operation using the installed air operators or by flow from l
the RHR pumps into the Recirculation System.
Q During plant operation, neither method is practical since the RHR pumps cannot develop sufficient head to overcome reactor pressure and the air operators are designed to -open the valves with zero differential pressure.
At cold shutdown,- a zero differential pressure is obtainable and operation with the air operators _is possible.
However, the -theoretical force of the-operators does not satisfy the, quantitative limit of IWV-3522(b).
Thus, exercising by using the air actuators can only be considered a part-stroke excrcise.
During cold shutdown when the RHR System is in the shutdown cooling mode, these valves are opened by normal shutdown cooling flow.
Full accident flow (as required by GL 89-04, Position 1)'is currently defined as 13,900 GPM which can only be obtained by operating two pumps in parallel.
Unacceptable vibration levels related to system and component design preclude throttling of the pump flow.
- Thus, with two RHR pumps in parallel, the resultant flow would be approximately 17,000 to 18,000 GPM.
It has yet to be confirmed that the system can be A)
(
operated safely in the shutdown cooling ' mode at-this high flowrate due to the size of the common pump suction header.
Rev.-No.
5 Page 163 of _J67
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AhT VALVE 8 APPENDIX B v,O Valve Relief Requegg NOTE V60 (cont.)
These valves cannot be fully opened at a single pump flowrate.
Thus, full stroke exercising using one pump, in conjunction with confirmation of full stroke valve operation by a non-intrusive-testing method, is also not possible.
Therefore, if operation cf two RHR pumps in parallel is not practical, these valves will be disassembled and inspected on a rotating basis, one each refuel outage.
ALTERNATE TESTING:
Each valve will be full flow exercised open (if practical) and closed during each cold shutdown in accordance with the requir ements of Note V51.
should full flow exercising, as outlined above, be found to be impractical, each valve will be partial-stroke exercised with flow.at cold shutdown -
and'each cycle (normally a refuel outage) one of t'
these valves will be disassembled and inspected on a rotating basis in accordan*ce with GL 89-04, Position 2.
U Rev. No.
5 Page 164 of _167
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES l
-APPENDIX C
SUMMARY
OF CHANGES O
O Rev. No.
3 Page 165 of 167
tiEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT lEEl'< M M_TfBTING PRpSRAM FOR_PyMPS AND VALYXE APPE!TX C Pumo Chances PAGE PUMP ID(s)
CHANGE REASON Various Various Combined consecutive To shorten the document withdrawn Relief Request Notes onto one rage 9,10 14P-1A,B Added reference to ncte Pl7 Note is applicable for 46P-2A,8 for flowrate measurer ent these pumps 9,19 23P 1B,M Deleted Relief Requ.st Note A pressure gage was P10 installed in the cross-over line from the booster to the main pump via modification 9,29 10P-Deleted Relief Request Note Vibration readings
=>
3A,B,C,D, P15 currently being taken are 14P-1A,B in accordance with the intent of the Code 23P-1B,M 18 10P-1A,B,C,0 Revised Relief Request Note To comply with NRC SER O
46P-2A,B P9 requirements 23,24,25, llP-2A,B Revised Relief Request Note To provide additional 26 P13 justification for relief 28 Various Deleted reference to Relief Relief Request Note P15 Request Note P15 from P14 has been withdrawn.
O Page ~166 of _}67 Rev. No. _f_
NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT INSEIWlEILlERTIER__EB& GRAM FOR PUMPS AND VALVER APPENDIX C Valve Chanaes PAGL(s)
VALVL IU(s)
I CHANGL RLASON Various Various Drawing and Coordinate f M/0P consolidation ef f ort changes Various Various Combined consecutive 10 shorten the document withdrawn Relief Reoues.
Notes onto one page 47,141 02-2A0V-39,40 Deleted reference to Relief Valves were replaced via Request Note V29 medification and are no
'onger fast acting I--
57,108 10A0V-68A,B Revised Sect. XI test codes lo more adequately and CS2 represent current testing 61,62 10RHR-Deleted PF-1 test Valves are full flow 64A,B,C,0 requirement tested per Code requirements 62 10SV-44 Valve deleted from the Valve no longer has a '
program safety function due to the removal of the head spray l
line 63 10RHH-14C Deleted IM test requirement Typographical errer O
63,64.155 1050V'-
Deleted Relief Request Note Determined that the 101A,B.C,0 V53 Relief Request current test methodology Withdrawn meets the intent of the Code 66,131 12MOV-18 Deleted reference of this Valve tested individually valve in Relief Request vl9 due to removal of 12H0V-80 this Refuel Outage 68,113 13RCIC-37,38 These valves were added to Determined to have a the IST Program and added safety function to open C517 68,113 13RCIC-7 Revised Sect. XI test from 10 address GL89-04 meeting ME-1 to RF-2 and added CS18 minutes Supplement 1 69 14A0V-13A,8 Revised Sect XI test codes lo more adequately represent current testing 69,157 14 CSP-62A,B Revised the alternate lo address NRC SER
(
testing performed on these concerns valves 78,141 20A0V 83,95 Deleted reference to Relief Valves were replaced via
~
Request Note V29 modification and are no longer fast acting 79, 112 23HPI-13 Revised Sect. XI tTst from To address GL89-04 meeting ME-1 to RF 2 and Added CS16 minutes Supplement 1 80,110 23HPI-18 Revised Valve 1.0. from ADV Air operator was removed to HPl.
Revised CS6 via modification accordingly O.
132 Various Revised the valve table
, Typographical errors Rev. No.
6 Page 167 of 167
ATTACHMENT lil TO JPN 93-001 DESCRIPTION OF IST PROGRAM DEVELOPMENT The Second 10 year Interval IST Program document reflects the scope requirements of IWP-1100 and IWV 1100. It includes Class 1,2, and 3 (equivalent) pumps and valves that are required to perform a specific safety function in shutting down and cooling down the reactor in the event of an accident. The program scope was developed over the past 12 years by FitzPatrick engineering staff with assistance from experienced contract personnel and with input from the NRC staff. The program for the first 10 year interval was reviewed and approved by NRC (Reference A).
The second 10 year Pro 0 ram was based on an updated version of the NRC approved first 10-year Program. In addition, the NRC staff requested additional information (Reference B) that resulted in the evaluation of a large number of components that were not addressed in the initial submittal. As a result, the scope of the second 10 year Program was re evaluated and expanded. The approach to this effort included:
An evaluation of all safety related power-operated and self-actuated valves on the O list in conjunction with the FitzPatrick Self Assessment Program.
Review of the FitzPatrick updated Final Safety Analysis Report.
Review of the FitzPatrick Technical Specifications.
Review of the applicable FitzPatrick Loss of Coolant Accident Analysis.
After the expanded version of the Program was compiled, it received Authority management review, followed by review and approval by the FitzPatrick Plant Operating Review Committee (PORC).
in addition to the above process, a separate and independent study (Reference C) was performed to evaluate each power operated valve in the Program as to which direction it must move (open or closed) to support its safety function (s).
Maintaining the Program current is accomplished by the IST coordinator. The review of plant modification packages by the Technical Services Department includes a review with respect to the IST Program (Reference D). Based on these modification packages and interaction with -
applicable modification engineers, the IST coordinator identifies and implements appropriate changes to the IST program. Revisions to the IST program are also subjected to -
management reviews and approval by PORC.
BEFERENCES:
A.
NRC letter, D. Vassallo to J. Bayne, dated December 5,1983, " James A.
FitzPatrick Safety Evaluation Report."
B.
NRC letter, H. Ableson to J. Brons, dated August 11,1988, " Inservice Testing Program for Second 10 year Interval Request for Additional Information."
C.
NYPA memorandum. JTS-89-0601, dated November 17,1989, "lST Power Operated Valve Stroke Time Test Requ;rements."
D.
NYPA Modification Control Procedure, MCM-3, " Modification Package Preparation, Review and Approval."
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OVERSIZE DOCUMENT PAGE PULLED SEE APERTURE CARDS NUMBER OF OVERSIZE PAGES FILMED ON APERTURE CARDS APERTURE CARD /HARD COPY AVAILABLE FROM MECORDS AND REPORTS MANAGEMENT BRANCH
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