ML20063L239
| ML20063L239 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 01/31/1994 |
| From: | NEBRASKA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20063L219 | List: |
| References | |
| PROC-940131, NUDOCS 9403040131 | |
| Download: ML20063L239 (93) | |
Text
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T-C 1
JANUARY 1994 ADDENDA I
N.
COOPER NUCLEAR STATION INSERVICE TESTING PROGRAM FOR ASME CLASS 1, 2. AND 3 COMPONENTS (REVISION 6)
DATE OF ISSUE: JANUARY 31, 1994 l
i This is an addenda to the loose-leaf version of the Inservice Testing Program, Revision 6, and is issued in the form of replacement or additional pages which l'
contain changes, additions, or deletions.
i
SUMMARY
OF CHANGES 1
This is the fourth addenda to be published to the Inservice Testing Program, Revision 6.
Changes listed below are identified on the affected program pages l
by a margin note (i.e., 1/94) adjacent to the affected area, with the exception of pump or valve summary listing pages.
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AFFECTED DESCRIPTION PAGE(S) 1 Added a new H listing under Section IV which is entitled "Open Testing of Check Valves Using Flow".
This addition was previously inadvertently omitted, l
i 2
The first sentence was revised to clarify that this program i
covers the second ten year interval.
5,6,8 Added relief request numbers RP-12 and RP-13 to the ' Notes and/or Description' column for each pump listed.
These relief requests apply to these pumps.
j 7
Added relief request number RP-04 to.the ' Notes and/or j
Description' column for both' pumps. Relief request RP-04 applies to these pumps and was previously inadvertently 3
omitted 9
Added relief request numbers RP-12, RP-13 and RP-16 to the
' Notes and/or Description' column.
Changed pump CIC from l
RCIC-P-1 to RCIC-P-MP.
These relief requests apply to this pump and the pump CIC was in error.
)
10 Added relief request number RP-13 to the ' Notes.and/or i
Description' column for pumps SW-P-BPA, SW-P-BPB, SW-P-BPC and I
SW-P-BPD; This relief request applies to these pumps.
l 11 Deleted pumps SW-P-GWSA, SW-P-GWSB, SW-P-GUSC, SW-P-GWSD, SW-P-BPGWSA, SW-P-BPCWSB, SW-P-BPGWSC.and.SW-P-BPGWSD, including all other associated pump information. These pumps were removed from the plant via Design Changes (DCs):
DC 90-174A, Amendment 1, and DC 90-174B, Amendment 1, "E
9403040131 94og31 O
DR ADOCK 0500029s p
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AFFECTED DESCRIPTION PAGE(S) 16 Changed 'CR-W' to 'CR-D' and ' Water Check' to " Dual Disk Check'.
This was revised to clarify the description of this type of check valve.
21 Added relief request number RV-62 to the NOTES / DESCRIPTION column for valves CS-RV-10RV, CS-RV-11RV, CS-RV-12RV and
[
CS-RV-13RV.
Relief Request RV-62 is applicable to these valves.
23 Deleted 'RV-45' from the NOTES / DESCRIPTION column for valves' j
RHR-MOV-M025A, RHR-MOV-M025B, RHR-MOV-M027A and RHR-MOV-M027B.
Relief Request RV-45 no longer applies to these valves - they can be tested individually.
27, 28 Added relief request number RV-62 to the NOTES / DESCRIPTION column for valves RHR-RV-10RV, 11RV, 12RV, 13RV, 14RV, 15RV, 17RV, ISRV, 19RV, 20RV and 21RV. Relief Request RV-62 is applicable to these valves.
28 Deleted 'RV-45' from the N0YES/ DESCRIPTION column for valves RHR-MOV-M017 and RHR-MOV-M018. Relief Request RV-45 no longer applies to these valves - they can be tested individually.
t 29 Changed the
'B' to an
'A' in the IST CAT column, added 'AT-l' i
to the TEST RQMT column, added 'RR' to the TEST FREQ column, and added relief request number RV-01 to the NOTES / DESCRIPTION l
column for valves RHR-MOV-M057 and RER-MOV-M067. These valves were identified as containment isolation valves and thus require leak rate testing.
30 Deleted 'RV-45' from the NOTES / DESCRIPTION column for valves SLC-CV-12CV and SLC-CV-13CV.
Relief Request RV-45 no longer applies to these valves - they can be tested individually.
j 30 Added relief request number RV-62 to the NOTES / DESCRIPTION column for valves SLC-RV-10RV and SLC-RV-11RV. Relief Request RV-62 is applicable to these valves.
j 31 Changed 'BAC' to 'BAL' in the VALVE TYPE column for valves HPCI-A0V-A070 and HPCI-A0V A071.
These were typing errors.
31, 32 Changed
'2' to
'4' in the ISI CLASS column for valves HPCI+A0V-A071 and HPCI-CV-16CV. Classification boundaries were redefined, 1
31 Added relief request number RV-60 to the NOTES / DESCRIPTION j
column for valves HPCI-A0V A070 and HPCI-A0V-A071.
Relief Request RV-60 is applicable to these valves.
32 Added relief request number RV-62 to the NOTES / DESCRIPTION column for valves HPCI-RV-10RV and HPCI-RV-12RV. Relief Request RV-62 is applicable to these valves.
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i AFFECTED DESCRIPTION PAGE(S) 32 Added 'CTCP' in the TEST RQMT column and 'Q' in the TEST FREQ column for valve HPCI-CV-17CV. A partial-stroke test is being l
performed quarterly.
{
33 Changed
'D' to
'2' in the ISI CLASS column for valves HPCI-V-44 l
and HPCI-V-50.
These were typing errors.
l 36 Changed 'CK-P' to 'CK-S' in the VALVE TYPE column for valve RCIC-CV-12CV.
An Equipment Spec Change (ESC), ESC 90-290,
)
replaced the piston check valve with a swing check valve design.
36 Changed
'2' to
'4' in the ISI CLASS column for valve RCIC-CV-20CV.
Classification boundaries were redefined.
37 Added relief request number RV-62 to the NOTES / DESCRIPTION column for valves RCIC-RV-10RV and RCIC-RV-11RV. Relief Request RV-62 is applicable to these valves.
38 Changed '2041' to '2043' in the P&ID column for valve RCIC-A0V-PCV23. The valve's P&ID was incorrectly identified.
41, 42 Added relief request number RV-62 to the NOTES / DESCRIPTION column for valves MS-RV-70ARV, 70ERV, 70CRV, 71ARV, 71BRV, 71CRV, 71DRV, 71ERV, 71FRV, 71CRV and 71HRV. Relief Request RV-62 is applicable to these valves.
42, 43 Changed 'RR' to 'CS' in the. TEST FREQ column and changed
'RV-28' to 'TJV-15 RV-58' for valves MS-CV-20CV through MS-CV-35CV.
It was determined these valves could be tested at i
cold shutdowns, but only when de-inerted.
45, 46 Deleted 'RV-45' from the NOTES / DESCRIPTION column for valves l
RWCU-MOV-M015, RWCU-MOV-M018, RW-A0V-A082, RW-A0V-A083, i
RW-A0V-A094 and RW-A0V-A095.
Relief Request RV-45 no.lon5er I
applies to these valves - they can be tested individually.
46 Changed
'3' to
'4' in the ISI CLASS column for valves-RW-A0V-A082, A083, A094 and A095.
Classification boundaries were redefined.
)
47, 48 Changed
'2' to
'4' in the ISI CLASS column for valves PC-MOV-230MV, 231MV, 232MV, 233MV, PC-A0V-237AV, 238AV, 245AV, 246AV, 243AV, 244AV, PC-CV-13CV, 14CV, PC-MOV-305MV and PC-MOV-306MV.
Classification boundaries were redefined.
I 48 Changed 'CK-W' to 'CK-D' in the VALVE TYPE column for valves PC-CV-13CV and PC-CV-14CV.
Revised the designation to clarify the description of this type of check valve.
{
50, 51,.
Changed
'2' to
'4' in the ISI CLASS column for valves i
52, 53 PC-MOV-130lMV through PC-MOV-1306MV, PC-MOV-1308MV, PC-MOV-1310MV, 1311MV, 1312MV, CRD-A0V-CV127, CRD-CV-CV114, 3
CRD-A0V-CV126, CRD-CV-CVil5 and CRD-CV-138.
Classification boundaries were redefined.
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AFFECTED DESCRIPTION PAGE(S)
-52, 53 Changed
'2' to
'l' in the ISI CLASS column for valves CRD-CV-13CV, 14CV, 15CV and 16CV.
Classification boundaries were redefined.
53 Added valves CRD-CV-25CV and CRD-CV-26CV, including all associated information. These new valves were installed via DC 89-285A.
54 Changed 'SW-MOV-ll7MV' to 'SW-MOV-36MV' in the VAL 5'E CIC column f
and changed 'NON CRITICAL SERVICES HEADER SUPPLY' to 'SW NON-CRITICAL HEADER ISOLATION VALVE' in the NOTES / DESCRIPTION column for this valve.
DC 93-057 removed SW-MOV-117MV and installed SW-MOV-36MV.
54, 25 In the NOTES / DESCRIPTION column, changed
'B' to
'A' for valves I
SW-MOV-650MV, SU-CV-28CV and
'A' to
'B' for valves SW-MOV-651MV, SW-CV-27CV.
DC 93-057 swapped portions of system between Division I and Division II.
j 55 Changed 'CK-W' to 'CK-D' in the VALVE TYPE column for valves SW-CV-10CV, 11CV, 12CV, 13CV, 27CV and 28CV. Revised the I
designation to c.arify the description of this type of check valve.
55, 56 Deleted vals>s SW-CV-39CV through SW-CV-42CV, SW-CV-46CV through SW-CV-49CV, 14CV, 17CV, SW-A0V oCV361A and j
SW-A0V-PCV361B, including associated fuformation. These valves t
were removed from the plant via DCs 90-174A, Amendment 1, and l
90-174B, Amendment 1.
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57 Added valves SW-CV-81CV, 82CV, 84CV and 85CV, including associated information. These valves were installed via l
DC 90-174B, Amendment 1.
58, 59 Deleted valves REC-MOV-694MV, 695MV, 697MV, 698MV, 721MV and a
722MV, including associated information. Testing of these valves is no longer required due to system changes made via
-]
DC 93-057.
i 58, 59 Changed
'4' tn
'2' in the ISI CLASS column for valves' REC-MOV-702MN and REC-MOV-709MV.
Classification boundaries were redefined.
59 Changed 'C4' to 'D4' in the P&ID COOR. column and changed
' SOUTH' to ' NORTH' in the NOTES / DESCRIPTION column for valve REC-MOV-711MV; changed 'D4' to 'C4' in the P&ID COOR. column' i
and changed ' NORTH' to ' SOUTH' in the NOTES / DESCRIPTION column for valve REC MOV-714MV.
Divisional power supplies were swapped for these valves via DC 93-057.
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i AFFECTED DESCRIPTION PA';E (S )
59 Changed 'E3' to 'D2' in the P&ID COOR. column and changed 'B SUPPLY' to 'A OUTLET' in the NOTES / DESCRIPTION column for valve REC-MOV-712MV; changed 'D3' to 'C2' in the P&ID COOR. column and changed 'A SUPPLY' to 'B OUTLET' for valve REC-MOV-713MV.
Also deleted 'BTO' in the TEST RQMT column and 'Q' in the TEST FREQ column for both valves.
Swapped locations of these valves with manual valves.
62 Changed '2 1/2' to
'3' in the VALVE SIZE column for valves DSCA-CV-18CV, 19CV, 20CV and 21CV. Valves were replaced va ESC 90-346.
65 Changed
'2' to
'l' in the ISI CLASS column for all valves through li.ited on these pages.
Classification boundaries were 71 redefined.
70 Changed 'AC' to
'A6' in the P&ID COOR. column for valve CS-CV-16BCV.
Typing error.
72 Added relief reques; number RV-60 to the NOTES / DESCRIPTION column for valves NMT-NVA-104A, B, C and D.
Relief Request RV-60 is applicable for these valves.
75 Changed 'C2' to 'G2' in the P&ID COOR. column for valve SCT-A0V-250$V.
Typing error.
75 Deleted valve SGT-CV-10CV, including associated information.
Valve internals are not installed as verified by MWR 93-1814 (DC 93-064).
75 Changed 'CK-W' to
'CK-D' in the VALVE TYPE column for valves SGT-CV-14CV and SCT-CV-15CV.
Revised the designation to clarify the description of this type of check valve.
75 Changed
'3' to
'4' in the ISI CLASS column for valves SGT-A0V-DPCV546A and 546B.
Classification boundaries were redefined.
77 Deleted 'THIS PAGE INTENTIONALLY LEFT BLANK', added the heading
' SYST EM : RADIATION MONITORING - VENTILATION', and added valves RKV-A0V-10AV, llAV, 12AV and 13AV, including associated information.
These valves were installed in the plant via DC 90-226-2.
78 Changed the Description of RP-14 to ' Withdrawn' and deleted Approval Notes.
This relief request is no longer required - components removed from plant.
78, 79, Changed Approval Note to
'9' for RP-16, RV-11, RV-53, RV-54, 81 RV-55, RV-56 and P7-57.
Status of relief approval has changed.
79 Changed Approval Note to
'5' for RV-17, RV-20 and RV-23.
{Nx_,}
Approval status changed since content of relief request has been revised.
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AFFECTED DESCRIPTION PAGE(S) 79 Changed the Description of RV-28 to ' Withdrawn' and deleted Approval Note.
This relief no longer required - the valves can i
be tested at cold shutdown.
80 Changed Approval Note to '10' for RV-29, RV-42 and RV-44.
l' Status of relief approval has changed.
81 Added new relief request numbers RV-58, RV-59, RV-60, RV-61-and.
RV-62, including Description and Approval Note information, f
New relief requests are being added to the IST Program.
i 81A Added NOTES 9, 10, and 11 to further clarify status of relief j
approval.
I 82 Deleted reference to SGT-CV-10CV from the Description for TJV-14.
SCT-CV-10CV is no longer being tested.
{
82 Added new technical justification numbers TJV-15 and TJV-16, I
including Description. New technical justifications are being added to the IST Program.
94, 95 Changed 'RCIC-P-1* to 'RCIC-P-MP' in the PUMP section. Pump CIC is in error.
95 Deleted reference to Service Water (SW) pumps / system in the PUMP, CLASS, FUNCTION, and BASIS FOR RELIEF sections. Also changed 0.2% to 0.8 percent in the BASIS FOR RELIEF section.
The flow instruments used'to monitor SW pump flow were. replaced with instruments of better accuracy.
Relief from SW pump flow rate measurement accuracy is no longer required.
96 Deleted Relief Request RP-14 This relief request is withdrawn since the subject components were removed from the plant.
l 97A Changed the first section heading from ' VALVE' to ' PUMP'.
Typing error..
98, 124, Added a
'4' to the CLASS section. Classification boundaries j
132, 142 were redefined.
101, 103, Changed the
'2' to
'4' in the CLASS section.
Classification 123, 149 boundaries were redefined.
104, 121, Changed the
'2' to
'1' in the CLASS section.
Classification 145 boundaries were redefined.
108 Deleted 'in accordance with IWV-3522(b)' from the REQUIRED TEST
}
section; deleted 'with flow' from and added ' full-stroke or i
part-stroke' to the last sentence in the BASIS FOR RELIEF f
section; changed ' disassembled, inspected and manually' to
'mechanica11y' in the ALTERNATIVE TEST section. Wording was revised as such to clarify that relief is being sought for test
-j frequency and not test method.
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i r'
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i AFFECTED DESCRIPTION l
PAGE(S) l 110, 113 Deleted 'in accordance with IWV-3522(b)' (page 110 only) from the REQUIRED TEST section; deleted 'with flow on a routine l
basis' from and added ' full-stroke or part-stroke' and 'during operations or cold shutdowns' to the last sentence in the BASIS FOR RELIEF section; changed ' disassembled, inspected and manually' to 'mechanica11y' in the ALTERNATIVE TEST section.
Wording revised as such to clarify that relief is being sought for test frequency and not test method.
i 118 Deleted Relief Request RV-28.
This relief request is withdrawn
.i since it was determined the valves may be tested during cold shutdowns when de-inerted.
127 Changed
'3' to
'4' in the CLASS section.
Classification boundaries were redefined.
i 131 Deleted penetration numbers X-12, X-13A, X-13B, X-14, X-18, X-19 and X-42, including associated valves, from the VALVE section. Valves associated with these penetrations are now being tested individually.
132 BASIS FOR RELIEF and ALTERNATIVE TEST sections were completely reworded to provide a better understanding for the l
basis-for-relief and to clarify alternative testing. NPPD l
letter NSD930791, C. R. Horn to USNRC, dated July 6,1993, i
committed to include revised Relief Request RV-45 in the next
{
IST Program addendum.
.i 143B Added a new relief request, RV-58, for relief from testing i
MS-CV-20CV through MS-CV-35CV during cold shutdowns when the l
drywell is not de-inerted. Relief is required if not practical j
to test at cold shutdowns.
143C Added a new relief request, RV-59, to allow use of a pressure decay test method when leak rate testing valves CRD-CV-25CV and l
CRD-CV-26CV.
The pressure decay method is not an allowable j
Code method.
i 143D Added a new relief request, RV-60, for relief from the 50%-stroke-time-increase / increase test frequency requirement.
l It is impractical to apply this requirement to the subject valves.
143E Added a new relief request, RV-61, to allow for testing of only.
Class 1, 2 and 3 valves required to perform a function in shutting down a reactor to the hot shutdown I
condition / mitigating consequences of an accident in lieu'of cold shutdown condition / mitigating consequences of an accident.
Code requires cold shutdown - CNS licensed for hot shutdown.
l l
143F Added a new relief request, RV-62, for relief from safety / relief valve test suparvisor qualifications and specific
')
responsibilities.
These re mirements are impractical and therefore relief is required.
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i AFFECTED DESCRIPTION PAGE(S) 151 Deleted reference to SGT-CV-10CV in the VALVE and FUNCTION I
section.
This valve is being deleted from the IST Program.
P 151A Added a new technical justification, TJV-15, to document justification for not testing the MS vacuum breaker valves at power operations.
Dryw".ll entry is required to test and f
therefore can only be performed at cold shutdowns (when de-inerted).
151B Added a new technical justification, TJV-16, to document ~
justification for not testing CRD-CV-25CV'and CRD-CV-26CV at power operations.
System circumstances dictate testing at cold 3'
shutdowns in lieu of at power operations.
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Page1 Rev 6 TABLE OF CONTENTS l
I Pace Table of Contents 1
1.
INTRODUCTION..
2 II.
TESTING PROGRAM FOR PUMPS............
2 A.
Applicable Code......
2 B.
Pump Summary Listing 2
C.
Allowable Ranges of Test Quantities........
2 D.
Instrumentation 3
3 f
E.
Bearing Lubricant..
F.
Testing Intervals......
3 G.
Relief Requests for Pump Testing 3
3 i
III.
PUMP
SUMMARY
LISTING i
14 i
IV.
TESTING PROGRAM FOR VALVES A.
Applicable Code 14 14 l
B.
Valve Summary Listing.
C.
Testing Intervals..........
14 D.
Cold Shutdown Testing.........
14 i
E.
Fail Safe Testing........
14 F.
Maximum Allowable Stroke Times 15 G.
Valve Disassembly 15 H.
Open Testing of Check Valves Using Flow................
15 1/94 1.
Relief Requests and Technical Justifications for Valve Testing... 15 1
V.
VALVE
SUMMARY
LISTING...........................
15 VI.
RELIEF REQUESTS AND TECHNICAL JUSTIFICATIONS..........
78 i
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Page 2 Rev 6 l
I.
INTRODUCTION
' This program details the. inservice testing of pumps and valves at Cooper Nuclear-Station (CNS) that shall be tested during' the second 120-month period.
1/94
.i (second ten year interval). The Program will be updated prior to the start of the next
}
120-month period in accordance with the requirements of 10CFR50.55a(g).
j l
The CNS Inservice Testing (IST) Program is based on the requirements of Section XI j
of the ASME Boiler and Pressure Vessel (B & PV) Code,1980 edition, including Winter 1981 addenda. All references to IWP or IWV in this document correspond to j
subsection IWP or IWV, respectively, of ASME Section XI,1980 edition, unless.
i othenvise noted.
1 This IST Program was developed using the Inservice Inspection (ISI) classification j
boundaries and the following documents:
Title 10, Code of Federal Regulations, Part 50 o
NRC Regulatory Guides - Division 1
]
o Standard Review Plan 3.9.6, " Inservice Testing of Fumps and Valves" l
o Final Safety Amlysis Report, Cooper Nuclear Station j
o Technical Specifications, Cooper Nuclear Station o
The inservice tests identified in this program will verify the operational readiness of j
pumps and valves whose functions are required to mitigate the consequences of an i
accident or to bring the reactor to a cold shutdown condition.
O II.
TESTING PROGRAM FOR PUMPS t
A.
Applicable Code 1
This testing program for pumps meets the requirements of Subsection IWP of.
the ASME B & PV. Code. Where these requirements are determined to be impractical, specific requests for relief have been written.
B.
Pump Summary Listing The Pump Summary Listing,Section III, lists the pumps included in the CNS l
IST Program. Data contained in the listing's tables identifies those pumps i
subject to inservice testing, the inservice test quantities to be measured, the j
test frequency, references to relief requests, and other applicable information.
j C.
Allowable Ranges of Test Quantities The allowable ranges specified in Table IWP-3100-2 will be used for differential' pressure, flow, and vibration measurements except as provided for in relief requests. In some cases, the performance of a pump may be adequate to fulfill 1
its safety function even though there may be a measurement that falls outside the allowable ranges as set forth in Table IWP-3100-2.
O i
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.'1 Page 5 '
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- SYSTEM:
Core Spray (CS) t Pump CIC Class Parameters Frequency Drawing Notes and/or Description
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CS-P-A 2
Q, DP, Pi, V, L Q
2045 Pump 1A, Loop A I
RP-01, RP-04, RP-11, RP-12, RP-13 i
- I q-
.I CS-P-B 2
Q, DP, Pi, V, L Q
2045 Pump 1B, Loop B t
t j
RP-01, RP-04, RP-11, RP-12, RP-13 i
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A i
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4 h
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B 3
3 3
3 1
1 1
1 P
P P
P e
6 n
R R
R R
r o
w e
i a
p 2
2, 2
2, g
t 1
1 1
1 i
P r
c P
P P
P s
R R
R R
eD 1
1 1,
1 r
1 1
1 1
o r
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pR
'pR pR w
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a o,
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o o
o4 s
L0 L0 L0 L0 e
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to AR BR 0R DR i
N 1
1 1
1 p1 p1 p1 p1 m0 m0 m0 m0 uP uP uP uP
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PR PR PR PR
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0 i
R w
4 4
4 i
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2 2
2 2
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eu Q
Q Q
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L L
L M
sr V
V V,
V E
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t e
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P P
P P
S a
P P
P, P,
a D
D D
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r w
P Q
Q Q
Q e
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ssa 2
2 2
2 l
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+
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C a
A B
C D
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Page 7 -
7
. s L
- SYSTEM: Standbv Liould Control (SLC)
.i l-Pump CIC Class Parameters Frequency Drawing Notes and/or
Description:
3 i
SLC-P-A 2
Q,Pd,V Q
2045 Pump 1A i:
RP-01, RP-02, RP-04, RP-11
- i l
i a
j=
SLC-P-B 2
Q,Pd,V Q
2045 Pump 1B RP-01, RP-02, RP-04, RP-11 t
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.-r-.-
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-w.. < -. -.. ~ -. ~.
..-.,--..---w---m.- -. -. -
.-.w.,e,,,-..e..w<...m,.-w-.vs>,-~
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..+---+-,,,n,n.+-.n,---,-v-n--+
.w,
- ~,---,----r,-
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O OL Pe,e e C 4 SYSTEM: High Pressure Coolant Iniection (HPCI)
Pump CIC Class Parameters Frequency Drawing Notes and/or Description HPCI-P-MP 2
- Q, N,- DP, Pi, V, L Q
2044-HPCI Pump 1A l
RP-01, RP-04, RP-11, RP-12, RP-13 HPCI-P-BP
- NOTE: HPCI main and booster pumps will be tested simultaneously.
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.ww
..w,.w m,s.m---s-
---m~i.Aw.,,ws.._,-
v,,11.,
-,,.-m u en <
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- ~ - - -
cr
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P. ; O V 2-SYSTEM: Reactor Core Isolation Cooline (RCIC)
Pump.CIC Class Parameters Frequency Drawing Notes and/or Description RCIC-P-MP 2
Q, N, DP, Pi, V, L Q
2043 RCIC Pump 1A RP-01, RP-04, RP-11, RP-12, RP-13, RP-16 1-t i
- j l
i f ?
5WeF mew _.,ye-++wweIn e-uw-re c-W W g.Abe
.h
-4*'wh'm e.
- r
'eet hw emms-4 - 1Du 4s+-'%eset wed' e -9 w-w e-w tvm-e e qua * +wfne t
--s
'9-ium*E'
-*W-W-==-
-+"h'-9&T%D-Jt um
'L--
- - --h-am.e-a*h-uwu-h--mm-"-
ma-m-
s------------A------
u
v w
l l
l l
f' l
N 1
1 1
1 1
1 1
1 P
P P
P
' 0 n
R R
R R
1 o
i 8
8, 8
8 3
3 3
3 e
t m
g p
0 0
0 0
1 1
1 1
i a
r P
c P
P P
P P
P P
P s
R R
R R
R R
R R
eD 4
4, 4,
1 1
1
. 1, 4
e r
0 0
0 0
1 1
1 1
=
+
/o P
P P
P P
P P
P d
R R
R R
R R
R R
n 4
4 4
4, a
3, 3,
3 3
s 0
0 0
0 0
0 0
0 v
e e
t
- P P
P
,P P
P P
P o
+&
N 1
1 I
I 1
1 1
1 p1 p1 p1 p1 p1 p1 p1 p1 m0 m0 m0 m0 m0 m0 m0 m0 e
w uP uP uP uP uP uP uP uP w
PR PR PR PR PR PR PR PR re w
+
gn 6
6 6
6 6
6 6
6 i
w 0
0 0
0 0
0 0
0 e
)
W a
0 0
0 0
0 0
0 0
-w r
2 2
2 2
2 2
2 2
i
+
S D
e
(
re w
ta W
yc c
n e
e e
e iv u
Q Q
Q Q
Q Q
Q Q
e r
q e
e S
r
~
F v
=
=
- M L
L L
L E
s V
V V
V T
r V
V V
V S
e i,
i i
i i
i e
i t
P P
P P
Y e
i P
P P
P
- w S
m P
P P
P r
D D
D D
P P,
P P,
e a
w w
D D
D D
z a
P Q
Q Q
Q Q
Q Q
Q w
e
-o e
ma S
4
-r e
s e
s w
a 4
4 4
4 4
4 4
4 e
=
l e
C e
e w
w
=
e
'+
e v
C A
B C
D
+
e w
P P
P P'
IC A
B C
D B
B B
B u
e p
P P
P P
P P
P P
m N
u W
W W
W W
W W
W P
S S
S S
S S
S S
m w
a d.
u e
W il j
4
A.
4 a.
e e
s h
O E
N
' M C) te c5 A
i I
i e
h I
s b
D i
A C
c5 P
dc) t t
=
c5 C
.O M
Co a
.N b
a be c3 l
l
.m l
Cb i
v i
I i
i 1
1 I
i i
i I
i l
Page 16 ' Rev 6_
VALVE 'IYPE:
The valve body design as indicated by the following abbreviations.
ANG Angle l
BAL Ball BTF
. Butterfly CK-B Ball Check CK-L Lift Check i
CK-P Piston Check i
CK-S Swing Check j
CK-T Tilting Disk Check 1
CK-D Dual Disk Check '
1/94' DIA Diaphragm GA Gate 1
GL Globe l
RV Relief SCK Stop Check SHR Shear
)
I ACT TYPE:
The type of valve actuator as indicated by the following abbreviations:
Air Operator AO CH Explosive Charge l!
HO Hydraulic Operator M
Manual i
MO Motor Operation j
SA Self Actuated SO Solenoid Operator i
NORM POS:
The position of the valve during normal plant operation, specified as follows:
i O
Normally Open.
C Normally Closed -
l TEST RQMT:
The test (s) that will be performed to fulfill the requirements of' i
Subsection IWV. The abbreviations are defined as follows:
i AT-1:
. Leakage. test in accordance with 10CFR50, Appendix J.'
l l
AT-2:
Excess flow check valve leakage testin accordance with CNS Technical Specifications.
AT-3:
Leakage test of air / nitrogen accumulator check
.1 l
valves.
AT-4:
Other leakage tests than already specified.
j LO
')
-,., +
~
o SYSTEM:
CORE SPRAY (CS)
Pg 21 Rev 6 VALVE l P&tD l P&lD l ISI llST 'l VALVE l VALVE l ACT l NORM l TEST l TEST l NOTES / DESCRIPTION f
CiG l
lCOORl CLASS l CAT l SIZE l TYPE l TYPE lPOS lROMT lFREO l CS - RV-10RV l 2045 l F2 l 2
l C l 3/4 l RV l SA l C
l CTSR l SY l CORE SPRAY PUMP A SUCTION l
l l
l l
l l
l l
l l RELIEF RV-62 CS - RV-11 RV l 2045 l F4 l 2
lC l 2 l RV l SA l C
l CTSR l5Y l CORE SPRAY PUMP A DISCHARGE l
l l
l l
l l
l l
l l RELIEF RV_62 CS-RV-12RV l 2045l C3 l 2
l C l 3/4 l RV l SA l C
l CTSR l6Y l CORE SPRAY PUMP B SUCTION l
l l
[
]
l l
l l
l l REllEF RV-62 CS-RV-13RV l 2045l C4 l 2
l C l 2 l RV [ SA l C
l CTSR l 5Y l CORE SPRAY PUMP B DISCHARGE l
l l
l l
l l
l l
l l REllEF RV-62 CS-MOV-MO11 A l 20451 FS l 1
l A l 10 l GA l MO l O
lAT-1 (RR l CORE SPRAY SYSTEM A INJECTION l
l l
l l
l l
l lBTO lO l THROTTLE l
l l
l
[
[
l l
lBTC
[O
[ RV-01, RV-45, RV-56 l
l l
l l
l l
l l PIT l2Y l
CS-MOV-MO11 B l 2045l DS l 1
lA l 10 l GA l MO l O
lAT_1 lRR l CORE SPRAY SYSTEM B INJECTION -
l l
l l
l l
l l
lBTO lO l THROTTLE l
l l
l l
l l
l lBTC lO l RV-01, RV-45, RV-56 l
l l
l l
l l
l
[ PIT
[2Y l
CS-MOV-MO26A l 2045l F5 l 2
l A l 10 l GL l MO l C
lAT-1 lRR l CORE SPRAY PUMP A TEST LINE l
l l
l l
l l
l lBTC lO llSOLATION l
l l
l l
l l
l l PIT l2Y l RV-01, RV-56 CS-MOV-MO26B l 2045 l C5 l 2
l A l 10 l GL l MO l C
lAT-1 lRR l CORE SPRAY PUMP B TEST LINE l
l l
l l
l l
l lBTC
[O llSOLATION l
l l
l l
l l
l l PIT l2Y l RV_01, RV-56 CS-MOV-MO5A l_2045l E4 l 2
lA l 3 l GA l MO l O
lAT-1 lRR l CORE SPRAY PUMP A MINIMUM FLOW l
l l
l l
l l
l lBTO lO l REClRC ISOLATION l
- l l
l l
l l
l lBTC
[O l RV-01 l
l l
l l
l l
l l PIT l2Y l
CS-MOV-MOSB l 2045 l 84 l 2
lA l 3 l GA [ MO l 0
lAT-1 lRR l CORE SPAY PUMP B MINIMUM FLOW l
l l
l l
l l
l l
lBTO lO l RECIRC ISOLATION l
1 I
I i
I i
i i
IBTC lO l Rv_01 l
l l
l l
l l
l-l PIT -
l2Y
{
?
l o
l l
,m
. ~,
.-v,
.-+n
., e = v e
- w 1
n~-.-<.
+e.-
w,~~
~
em
.~-
a
- - > ~.,,, - --
v
,m (f ~)
(
)
(xV)
V' V
SYSTEM:
RESIDUAL HEAT REMdVAL (RHR)
Pg 23 Rev 6 VALVE l P&lD lP&lD l ISI llST IVALVE] VALVE l ACT l NORM l TEST l TEST l NOTES /DESCR!PTION CIC
]
lCOORl CLASS l CAT l SIZE l TYPE l TYPE lPOS lROMT [FREQ l RHR-M OV-M O25A l 2040l C5 l 1
l A l 24 l GA l MO l C
lAT-1 lRR l RHR LOOP A INJECTION INBOARD
[
l l
l l
l l
l lBTO lQ llNSOLATION l
l l
l l
l l
l lBTC lQ l RV-01, RV-56 l
l l
l l
l l
l l PIT l2Y l
RH R _ MOV-MO25B l 2040l C8 l 1
l A l 24 l GA l MO l C
lAT-1 lRR l RHR LOOP B INJECTION INBOARD l
l l
l l
l l
l lBTO lO llNSOLATION l
l l
l l
l l
l lBTC
]O l RV-01, RV-56 l PIT l2Y l
RHR-MOV-MO27A l 2040l C4 l 1
l A l 24 l ANG l MO l C
lAT-1 lRR
[ LOOP AINJECTION OUTBOARD l
l l
l l
l l
l lBTO lQ l THROTTLE l
l l
l l
l l
l lBTC lQ l RV-01, RV-56 l PIT l2Y l
RHR-MOV-M O278 l 2040l C9 l 1
l A l 24 l ANG l MO l C
lAT_1 lRR
[ LOOP B INJECTION OUTBOARD l
l l
l l
l l
l lBTO lO
[ THROTTLE l
l l
l l
l l
l lBTC lQ l RV-01, RV-56 l PIT l2Y l
RH R-M OV-M 01 GA l 2040i E3 l 2
l A l 4 l GA l MO l C
lAT-1 lRR l PUMP A AND C MIN! MUM FLOW l
l l
l l
l l
l lBTO lQ l RV-01, RV-45 l
l I
l l
l l
l lBTC lQ l
l l
l l
l l
l l
l PIT l2Y l
RHR-MOV-M0168 l 2040 l E10 l 2
l A l 4 l GA l MO l C
[AT-1 lRR
[ PUMP B AND D MINIMUM FLOW l
l l
l l
l l
l lBTO lO l RV-01, RV-45 l
l l
l l
l l
l lBTC lO l
l l
l l
l l
l l
l PIT l2Y l
RH R-M OV-MO21A l 2040l H2 l 2
l A l 4
[ GA l MO l C
lAT-1 [RR l RHR HX A DRAIN TO SUPPRESSION l
l l
l l
l l
l lBTC
]Q l CHAMBER l
l l
l l
l l
l l PIT l2Y lRV-01 RH R _ M OV-MO21B l 2040 [ H11 l 2
lA l 4
[ GA l MO l C
lAT-1 lRR l RHR HX B DRAIN TO SUPPRESSION l
l l
l l
l l
l lBTC lQ l CHAMBER l
l l
l l
l l
l l PIT l2Y l RV-01 t--
t SYSTEM:
Pg 27 Rev 6 VALVE l PalO l PAID l ISI llST l VALVE l VALVE l ACT l NORM l TEST l TEST l NOTES / DESCRIPTION CIC l
lCOORl CLASS l CAT l SIZE l TYPE l TYPE lPOS lROMT lFREO l RH R _ CV-14CV l 2040l G3 l 2
l C l 16 lCK-Tl SA l C
lCTCG lQ l RHR PUMP A DISCHARGE I
l 1
1 I
I I
I ICTCC lO l
RHR-CV-15CV l. 2040 l G10 l 2
l C l 16 l CK-T l SA l C
lCTCO lO l RHR PUMP B DISCHARGE 1
1 I
I I
I I
I ICTCC lQ l
RH R-CV-16CV l 2040 l H3 l 2
l C l 16 l CK-T l SA l C
lCTCO lO l RHR PUMP C DISCHARGE I
I I
I I
i I
i ICTCC 10 l
RH R-CV-17CV l 2040l H10 l 2
l C ] 16 [ CK-T l SA l C
lCTCO lO l RHR PUMP D DISCHARGE I
i I
i l
i i
i ICTCC 10 l
RH R -CV-18CV l 2040 l A9 l 2
l C l 4 lCK-Sl SA l C
lCTCC lO l CONDENSATE MAKEUP SUPPLY TO l
l l
l l
l l
l l
l l HEAD SPRAY I
I I
I I
I I
I I
I IRV-15 RH R -CV-19CV l 2040l A9 l 2
lC l 4 l CK-S l SA l C
lCTCC lO l CONDENSATE MAKEUP SUPPLY TO l
l l
l l
l l
l l
l l HEAD SPRAY I
I I
I I
I I
I i
i IRV-15 RHR-CV-20CV l 2040l E3 l 2
l C ] 14 l CK-T l SA l C
lCTCO lRR l SW/RHR CORE STANDBY COOLING I
I I
I I
I I
I I
I I SUPPLY I
I I
I I
I I
I I
i 1 RV-17 RH R -CV-24CV l 2040] C4 l 2
lC l 4 l CK-S l SA l C
lCTCC lQ l RHR LOOP A PRESSURE l
l l
l l
l l
l l
l l MAINTENANCE SUPPLY I
I I
I I
I I
I I
i 1RV-15 RHR-CV-25CV l 2040 l C4 l 2
.l.C l 4 l CK-S l SA l C
lCTCC l0 l RHR LOOP A PRESSURE l
l l
l l
l l
l l
l l MAINTENANCE SUPPLY I
I I
I I
I I
I I
I IRV-15 RH R-RV-10RV l 2040 l G5 l 2
l C.l 1
l RV l SA l C
lCTSR l5Y
[ RHR PUMP A SUCTION RV-62 RHR-RV-11 RV l 2040 l G8 l 2
lC l 1 l RV l SA l C
lCTSR l5Y l RHR PUMP B SUCTION RV-62 RH R -RV-12RV l 2040 l H5 l 2
lC l 1 l RV l SA l C
lCTSR l5Y l RHR PUMP C SUCTION RV-62 I
I i
1 1
1 I
I I
I i
_m.aa._
._a.miu..
.__m_
-___m___.
j m.
f SYSTEM:
Pg 28 Rev 6 VALVE lP&lO l PalG ' l 181 llST l VALVE l VALVE l ACT l NORM iTEST l TEST l NOTES / DESCRIPTION
. CIC -
l l COOR l CLASS l CAT l SIZE l TYPE l TYPE l POS lROMT lFREQ l RHR-RV-13RV l 2040l H8 l 2
l C l 1
l RV l SA l C -lCTSR l5Y l RHR PUMP D SUCTION I
I I
I I
I i
l l
l 1RV-62 RH R -RV-14 RV l 204G l C3 l.
2 l C l 1 l RV l SA l C
lCTSR [5Y l RHR LOOP A SUPPLY l
i I
i i
l i
I I
i 1 RV-62 RH R -RV-15RV l 2040 ! C10 l 2
l C l 1
l RV l SA l C
lCTSR lSY l RHR LOOP B SUPPLY I
I I
I I
I i
i i
IRV-62 RH R -RV-17RV l 2040 l F5 l 2
[ C l 1 l RV l SA !
C lCTSR l5Y l SHUTDOWN COOUNG SUPPLY l
i I
I I
I I
I I
i 1RV-62 RH R-RV-18RV l 2041 l G1 l 2
l C l 21/2 l RV l SA l C
lCTSR l5Y l STEAM SUPPLY TO RHR HX A I
I I
I I
I I
I l
i 1RV-62 RH R -RV-19RV l 2041 l G3 ;
2 l C l 21/2 l RV l SA l C
lCTSR [5Y l STEAM SUPPLY TO RHR HX B I
I I
I I
I I
I I
I IRV-62 RHR-RV-20RV l 2041 l G2 l 2
[ C l 1 1/2 l RV l SA l C
lCTSR l5Y l RHR HX A SHELL SIDE REUEF l
l l
1 I
I I
I I
I 1RV-62 RH R -RV-21 RV l 2041 l G2 l 2
l C l 1 1/2 l RV l SA l C
lCTSR l5Y l RHR HX B SHELL SIDE REUEF I
I I
I I
I I
I I
I IRV-G2 RHR-MOV-M O17 l 2040l D5 l 1
lA l 20 l GA ] MO l C
lAT-1 lRR l RHR SHUTDOWN COOUNG SUPPLY I
l l
1 1
1 I
I IBTO ICS l OUTBOARD ISOLABON I
I I
i i
i i
i IBTC
[CS l TJV-02, RV-01, RV-56 l
l l
l l
l l
l l PIT l2Y l
RH R-M OV-M O18 l 2040 l D6 l 1
l A l 20 l GA l MO l C
lAT-1 lRR l RHR SHUTDOWN COOLING SUPPLY
{
l l
l l
l l
l lBTO lCS llNBOARD ISOLATION l
l l
l l
l l
l-lBTC lCS l TJV-02, RV-01, RV-56 l
l l
l l
l l
l l PIT l2Y-l RHR-MOV-MO13A l 2040 l G6 l 2
l A l 20 l GA l MO l O
lAT-1 jRR l RHR PUMP A SUCTION FROM l
l l
l l
l l
l lBTO lQ l SUPPRESSION CHAMBER I
l l
l l
l l
l l
lBTC lQ l RV-01, RV-56
[
l I
I I
I I
I i
IPIT l2Y l
L.
.~
~.
.~
O SYSTEM:
Pg 29 Rev 6 VALVE l P&lD l P&lD l ISI lIST l VALVE l VALVE l ACT NORM l TEST l TEST l NOTES / DESCRIPTION CIC l
l COORl CLASS l CAT l SIZE l TYPE lT"PE POS l ROMT l FREO [
RHR-MOV-MO138 l 2040 l G8 l 2
l A l 20 l GA l MO l O
lAT-1 lRR l RHR PUMP B SUCTION FROM l
l l
l l
l l
l lBTO lQ l SUPPRESSION CHAMBER
[
]
l l
l l
l l
lBTC lO l RV-01, RV-56 l
l l
l l
l l
l l PIT l2Y l
RHR-MOV-M013C l 2040 l G6 l 2
l A l 20 l GA l MO l O
lAT-1 lRR l RHR PUMP C SUCTION FROM l
l l
l l
l l
l lBTO lO l SUPPRESSION CHAMBER l
l l
l l
l l
l lBTC lQ l RV-01, RV-56 l
l l
l l
l l
l l PIT l2Y l
s RHR-MOV-MO13D l 2040l G7 l 2
l A l 20 l GA l MO l O
lAT-1 lRR l RHR PUMP D SUCTION FROM l
l l
l l
l l
l lBTO lQ l SUPPRESSION CHAMBER l
l l
l l
l l
l lBTC lO
[ RV-01, RV-56 l
l l
l l
l l
l l PIT l2Y l
RHR-MOV-MO15A l 2040 l G5 l 2
l B l 20 l GA l MO l C
lBTO
[Q l RHR PUMP A SHUTDOWN COOLING l
l l
l l
l l
l l PIT l2Y l SUCTION RHR-MOV-MO158 l 2040 l G8 l 2
l B l 20 l GA l MO l C
lBTO
]Q
[ RHR PUMP B SHUTDOWN COOUNG l
l l
l l
l l
l l PIT l2Y l SUCTION RHR-MOV-MO15C l 2040 l H5 l 2
l B l 20 l GA l MO l C
lBTO lO l RHR PUMP C SHUTDOWN COOLING l
l l
l l
l l
l l PIT l2Y l SUCTION RHR-MOV-MO15D l 2040 l H8 l 2
l B l 20 l GA l MO l C
[BTO lQ l RHR PUMP D SHUTDOWN COOLING l
l l
l l
l l
l l PIT l2Y
[ SUCTION RHR-MOV-MO57
-l 2040 l H7 l 2
l A [ 4 l GL l MO l C
lAT-1 lRR
[ RHR DISCHARGE TO RADWASTE l
l l
l l
l l
l lBTC lQ llNBOARD THROTTLE i
i I
I i
i i
i I PIT l2Y l RV-01
.i RHR-MOV-MO67 l 2040 l H7 l 2
lA l 4 l GA l MO l C
lAT-1 lRR l RHR DISCHARGE TO RADWASTE I
l l
l l
l l
l l
lBTC lO l OUTBOARD SHUTOFF l
l l
l l
l l
l l
l PIT l2Y l RV-01 1
I I
I I
I I
I I
I I
I I
I I
I I
I I
i l
I l
i I
I I
i i
i l
l l
- m SYSTEM:
STANDBY UQUID CONTROL (SLC)
Pg 30 Rev 6 VALVE' lP&lD l P&lD l ISI llST l VALVE l VALVE l ACT l NORM l TEST l TEST l NOTES / DESCRIPTION CIC l
lCOORl CLASS l CAT l SIZE l TYPE l TYPE lPOS
[ROMT l FREO l SLC-CV-12CV l 2045) E8 l 1
l A,C l 11/2 l CK-L l SA l C
lAT_1 lRR
] SLC INJECTION UNE OUTBOARD I
I I
I I
I I
I ICTCO lRR l CHECK l
I I
I I
I I
I ICTCC lRR l RV-18, RV-01 SLC-Cv_13Cv l 20451 E7 l 1
l A,C l 11/2 l CK-L l SA l C
[AT-1 lRR l SLC INJECTION UNE INBOARD l
l l
l l
l l
1 ICTCO lRR l CHECK I
I I
I I
l 1
I ICTCC lRR l Rv_ t s, Rv_01 SLC_ Cv_10Cv
' l 2045 l E9 l 2
l C l 1 1/2 l CK-L l SA l C
lCTCO lO l SLC PUMP A DISCHARGE CHECK I
I I
I I
I I
I ICTCC iRR lRV-47 SLC_CV-11CV l ' 2045 l F9 l 2
[ C l 1 1/2 l CK-L l SA l C
lCTCO lO l SLC PUMP B DISCHARGE CHECK
. I I
I I
I I
I I
ICTCC lRR lRV-47
' SLC_RV-10RV l 2045 l D10 l 2
l C l 3/4 l RV l SA l C
l CTSR l5Y l SLC PUMP A DISCHARGE REUEF -
1 I
I I
I I
I I
I I
1RV-62 SLC-RV-11RV l 2045 l G9 l 2
l C l 3/4 l RV l SA. ]
C l CTSR 'l 5Y l SLC PUMP B DISCHARGE REUEF I
I I
I I
I I
I I
I IRV-62 SLC-SOBV-14A l 2045 l E8 l 1
- l D l 1 1/2 l SHR l CH l C
l DT l2YR l SLC EXPLOSIVE VALVE A I
l-1 I
I I
I I
I I
I SLC_SOBv-148 l 2045 l E8 l 1
l D l11/2 l SHR l CH l C
l DT [ 2YR l SLC EXPLOSIVE VALVE B l-1 I
I I
I I
I I
I I
l I
i I
i i
i i
i l
l I
I I
I I
I I
I 1.
I I
l i
I I
I I
I I
I I
l~
l i
I I
l-1 I
I I
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l i
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1.
I I
I I
I
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I i
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I
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I
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l i
l' N
w.
u w
wwew er
=
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m
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0 SYSTEM:
HIGH PRESSURE COOLANTINJECTION (HPCI)
Pg 31 Rev 6 VALVE l P&lD l PalO l ISI
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lA l 3/4 l GL l AO l O
lAT-1 lRR l RM-4 CONTAINMENTISOLATION, l
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_________________._________________________.__________._____._l2Y l
RMV-AOV-13AV l 2022 ] F10 l 4
lA l 3/4 l GL l AO l 0
lAT-1 lRR l RM-4 CONTAINMENT ISOLATION, l
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Page 78 - Rev 6 VI.
RELIEF REQUESTS AND TECHNICAL JUSTIFICATIONS RELIEF REQUESTS j
Approval RR No.
Descrirtion Note 5
RP-01 Bearing Temperature Measurement 1
RP-02 SLC Pump Inlet Pressure Measurement
.1 RP-03 Withdrawn RP-04 Pump Vibration Measurement Method 1
RP-05 Withdrawn RP-06 Withdrawn j
RP-07 Withdrawn l
.j RP-08 SW Pump Inlet Pressure Measurement 1
RP-09 DOT Pump Inlet Pressure Measurement 1
l RP-10 Withdrawn j
RP-11 Required Action Range-High and Alert 1
Range-High Limits l
RP-12 CS, RHR, HPCI, RCIC Pumps Suction Pressure 1
Gauge Range RP-13 CS, RHR, HPCI, RCIC, SW, and SWB Pumps 1
j Instrument Accuracy i
RP-14 Withdrawn 1/94 l
RP-15 REC Pumps Flow Rate Gauge Range 5,6 -
8/91 j
RP-16 RCIC Pump /I'urbine Speed Measurement Range 9
12/92, 1/94 l
RV-01 Valve Leak-Rate Test Method and Criteria 1
RV-02 Withdrawn l
RV-03 Withdrawn RV-04 Main Steam Isolation Valve Stroke Time, Required 1
l Action Relief j
f RV-05 Reactor Feedwater Check Valve Reverse Flow Test 1
RV-06 Valves CRD-AOV-CV126, CRD-AOV-CV127, and 3
CRD-CV-CV114 Testing Relief RV-07 Check Valve CRD-CV-CV115 Testing Relief 3'
i l
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Page 79 Rev 6 I
RELIEF REQUESTS (Continued)
~
Approval RR No.
Description Note r
RV-08 Withdrawn l-RV-09 Withdrawn RV-10 Withdrawn RV-11 Excess Flow Check Valves Testing Relief 9
1/94 i
RV-12 Withdrawn RV-13 Withdrawn
- RV-14 Core Spray Pressure Maintenance Check Valves 1
Testing to the Closed Position (CS-CV-12CV, i
13,14, and 15)
)
RV-15 RHR Pressure Maintenance Check Valves Testing to 1
l the Closed Position (RHR-CV-18CV,19,24, and 25) i RV-16 HPCI Pressure Maintenance Check. Valves Testing 1
e to the Closed Position (HPCI-CV-18CV and 19) i RV-17 RHR/SW Core Standby Cooling Check Valve Testing 5
1/94 Relief (RHR-CV-20CV)
RV-18 SLC-CV-12CV and SLC-CV-13CV Testing Frequency 1
j f
RV-19 Withdrawn RV-20 HPCI-CV-11CV Testing Relief 5
1/94 RV-21 HPCI-V-44 and HPCI-V-50 Testing to the 1
Closed Position r
RV-22 HPCI-CV-24CV,25,26, and 27 Testing Frequency 2
.i RV-23 RCIC-CV-11CV Testing Relief 5-1/94 I
RV-24 RCIC-CV-180V and 19 Testing to the 1
Closed Position i
RV-25 RCIC-V-37 and RCIC-V-42 Testing to the 1
Closed Position RV-26 RCIC-CV-22CV,23,24, and 25 Testing Frequency 2
[
t RV-27 Main Steam Relief Valve Exercising Testing 1
l Frequency (MS-RV-71 ARV to 71HRV) f RV-28 Withdrawn 1/94 I
l
Page 80 Rev 6 i
REL1EF REQUESTS (Continued)
Approval-RR No.
Description -
Note j
RV-29 IA Accumulator Check Valve Testing / Frequency 10 1/94-(IA-CV-17CV,18,19,20,21,22,36, and 37)-
I i
RV-30 RWCU-CV-15CV Test Frequency 1
RV-31 CRD-CV-13CV,14,15, and 16 Exercise Testing 1
Frequency RV-32 Withdrawn
[
]
RV-33 Withdrawn RV-34 Service Water Motor-Operated Valves to RHR 1
(SW-MOV-MOS9A and 89B) Testing Relief RV-35 Withdrawn
'j RV-36 PC-CV-13CV and 14 Testing Frequency 1
l RV-37 Withdrawn i
F RV-38 HPCI-CV-15CV,16,17 Testing to the Closed 1
Position RV-39 RCIC-CV-12CV,13, and 15 Testing to the Closed 1
l Position RV-40 Main Steam Isolation Valves (MS-AOV-AO80A, B, 1~
j C, D, 86A, B, C, and D) Fail Safe Test Frequency
~
RV-41 REC-CV-16CV Closure Test Frequency 1
RV 42 Diesel Generator Air Start Valves Stroke Time-10-
-1/94 Measurement
)
RV-43 Suppression Chamber Vacuum Breaker Check Valves 1-Open Test Frequency RV-44 IA Accumulator Check Valve Testing / Frequency 10 1/94.
l (IA-CV-28CV, 29, 30, 31, 32,' 33, 34, 35)
RV-45 Group Leak Rate Testing of Primary Containment 1
I isolation Valves RV-46 TIP Ball Valves Position Indication Test 1
RV-47 SLC-CV-10CV and 11 Closure Testing Frequency 5,7 8/91 RV-48 PC-AOV-NRV20 through 31 Group Leak Rate Testing 5,8 8/91 0
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Page 81 Rev 6 RELIEF REQUESTS (Continued)
-Approval R R N o'.
.D.2scription Note j
RV 49 Withdrawn 8/91
'j RV-50 CS-CV-18CV,19, RHR-CV-26CV and 27 Cold 5,7 8/91 l
Shutdown Testing Caveat RV-51 RF-CV-14CV and 16 Opening Test Frequency.
5,8.
8/91 RV-52 SW-CV-57CV, 58, 59, 60, 61, 62, 63, and 64 5,8'
.8/911 l
Group Closure Testing l
RV-53 HPCI-CV-13CV and 17 Disassembly Testing 2,9 1/94
)
Frequency RV-54 RHR-CV-10CV,11,12, and 13 Disassembly Testing 2,9
' 1/94
-l Frequency RV-55 RCIC-CV-20CV and 21 Disassembly Testing 2,9
- 1/94-Frequency l
RV-56 IWV-3427 (b) Relief 4,9 1/94 I
RV-57 RF-CV-14CV, RF-CV-16CV Post Maintenance Testing 2,9 7/92, 191 RV-58 MS-CV-20CV through MS-CV-35CV Cold Shutdown 5
- 1/94 Testing Caveat RV-59 CRD-CV-25CV and CRD-CV-26CV Leak Rate Test 10.
1/94
)
Method and Closure Test Frequency RV-60 Rapid Acting Valves Percent Increase 11 1/94 l
l RV-61 Hot Shutdown Component Testing 5
--1/94 RV-62 Relief Valve Test Supervisor 5
1/94 l
1
- NOTES:
j 1.
Relief Requestis approved by Generic Letter (GL) 89-04 via submittal prior to April 3, 1989.
j
- 2.
Relief Request is approved by GL 89-04, Position 2.
3.
Relief Request is approved by GL 89-04, Position 7.
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Page 81A Rev 6 i
4.
Relief Request is approved by GL 89-04, Position 10..
'l 5.
Relief Request submitted after April 3,1989.
i 6.
Relief Request is approved by NRC Safety Evaluation, NRC Letter " Cooper Nuclear 8/91 j
Station Inservice Testing Progivun ReliefRequests (TAC No. 76990)," dated August 31, 1990.
4 7.
Relief Request is approved by NRC Safety Evaluation, NRC Letter " Cooper Nuclear 8/91 Station InserviceTestingProgram ReliefRequests(TAC No. 77076)," dated March 11, 1991.
i f
8.
Relief Request is approved by NRC Safety Evaluation, NRC Letter " Cooper Nuclear 8/91 Station Inservice Testing Program Relief Requests (TAC No. 76991),". dated July 5, i
1991.
a 9.
Relief Request is approved by NRC Safety Evaluation, NRC Letter " Safety Evaluation 1/94 of the October 15,1991, September 14,1992, and February 15,1993 Relief Requests Related to the Inservice Testing Program for Pumps and Valves for Cooper Nuclear Station (TAC No. M84734)," dated April 7,1993.
f 10.
NRC approvalis not required. These are non-code class items.
1/94 11.
Relief Request is approved by GL 89-04, Position 6.
1/94 i
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.I Page 82 Rev 6 l
TECHNICAL JUSTIFICATIONS' TJ No.
Description TJV-01 RHR-MOV-920MV and RHR-MOV-921MV Testing Frequency
' TJV-02
.RHR-MOV-M017 and RHR-MOV-M018 Testing Frequency TJV-03 Deleted TJV-04 RR-MOV-MO53A and 53B Testing Frequency TJV CS-CV-18CV,19, RHR-CV-26CV, and 27 TJV-06 Deleted TJV-07 Deleted TJV-08 Deleted TJV-09 Deleted TJV-10 Deleted TJV-11 DGSA-CV-14CV,15,16, and 17 Testing Frequency TJV-12 CRD-CV-138 (Typical of 137) Test Method TJV-13 HPCI-CV-29CV and RCIC-CV-26CV Test Frequency 7/92.
TJV-14 SGT-CV-14CV and 15 Testing Frequency 7/92, 1/94 TJV-15 MSRV Discharge Line Vacuum Breaker Check Valve Test Frequency 1/94 TJV-16 CRD-CV-25CV and CRD-CV-26CV Test Frequency 1/94 l
l l
O
Page 94 Rev 6 RELIEF REQUEST RP-12 PUMP:
Core Spray CS-P-A,'CS-P-B Residual Heat Removal RIIR-P-A, RHR-P-B, RHR-P-C, RHR-P-D High Pressure Coolant Injection HPCI-P-MP/BP Reactor Core Isolation Cooling RCIC-P-MP 1/94 C' SASS:
2 FUNCTION:
Emergency core cooling.
REQUIRED TEST:
The full-scale range of each instrument shall be three times the reference value or less (IWP-4120).
4 BASIS FOR 4
RELlEF:
The permanently installed suction pressure gauge of a pump is generally sized to accommodate the maximum pressure it would experience under
- i normal or emergency conditions.
In many cases, this results in an instrument range that exceeds the Code requirements since, under test conditions, normal or emergency condition suction pressures are typically not experienced.
6 Suction pressure measurements serve two primary functions. First, they provide assurance that the pump has an adequate suction head for proper operation.
For suction head determination, the accuracy and range requirement is overly restrictive. Since, in most cases, plant pumps are provided with a considerable margin of suction head, an accuracy of i
1.0 percent or less should be adequate, Secondly, the suction pressure is used to determine the pump differential pressure. When used in determining differential pressure, the accuracy of the suction pressure measurement has little or no effect on the calculation since, generally, the pump discharge pressure is higher than the suction pressure by two or three orders of magnitude.
j ALTERNATIVE l
TEST:
When measuring pump suction pressure, the range requirement: of-IWP-4120 will not be followed, however, instruments used shall have an accuracy of 1.0 percent or better.
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Page 95 Rev 6 RELIEF REQUEST RP-13.
PUMP:
Core Spray CS-P-A, CS-P-B Residual Heat Removal RHR-P-A, RHR-P-B, RHR-P-C, RHR-P-D High Pressure Coolant Injection HPCI-P-MP/BP Reactor Core Isolation Cooling RCIC-P-MP 1/94' 1/94
. Service Water Booster SW-P-BPA, SW-P-BPB, SW-P-UPC, SW-P-BPD -
CLASS:
2 - CS, RHR, HPCI, and RCIC 4 - SW Booster (SWB)
, l 1/94 FUNCTION:
CS, RHR, HPCI, RCIC - Emergency ccre cooling.
1/94 SWB - Residual heat removal equipment cooling REQUIRED TEST:
Instrument accuracy shall be within the limits of Table - IWP-4110-1 (IWP-4110).
l BASIS FOR RELIEF:
The instrument loop accuracies listed below do not meet the requirements of Table IWP-4100-1 FUNCTION LOOP ACCURACY (2%)
CS Pump Discharge Pressure 2.06 CS Pump Flow Rate 2.02 RHR Pump Flow Rate 2.08 HPCI Pump Flow Rate 2.03 RCIC Pump Flow Rate 2.03 1/94 SWB Pump Flow Rate 2.03 The difference between the existing loop accuracies and the Code required accuracy (maximum difference. is.08 percent) is insignificant - when compared to the cost of manpower required to obtain the
-1/94 2 percent accuracy.
ALTERNATIVE TEST:
Inservice test measurements of pressure and flow rate, as described above, will be made using instruments with loop accuracies as indicated.
O
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. Page 96 Rev 6
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Page 97A Rev 6 RELIEF REQUEST RP-16 12/92 PUMP:
Reactor Core Isolation Cooling, RCIC-P-MP 1/94 CLASS:
2 FUNCTION:
Emergency core cooling REQUIRED TEST:
The full-scale range of each instrument shall be three times the reference value or less (IWP-4120).
I BASIS FOR RELIEF:
Based on previous work history, permanent plant tachometer, RCIC-SI-3067, for measurement of RCIC pump / turbine speed, may not provide the required consistency needed for inservice testing unless instrument calibration is performed inunediately prior to each test. This-
" extra" calibration places an additional burden on limited Instrument &
Control personnel resources.
Hand-held tachometers have proven to be more reliable instruments as far a:; producing consistent readings. The tachometers available to be used for IGT, have ranges of 10-99,999 rpm ' or 6-30,000 rpm.
The respective reference value is 4500 rpm. Therefore, the range limitation imposed by IWP-4120 (3 times the reference value or less) is not met by these hand-held tachometers.
However, the accuracy of the 10-99,999 rpm tachometer is 9 rpm. An j
instrument - accuracy of e 9 rpm on - a full range of 0-13,500 rpm (3 x 4500 rpm)would be.07 percent of the full range which is better than the accuracy required by IWP-4110 (i.e.
2 percent of full scale). For the 6-30,000 rpm tachometer, accuracy is 99 rpm.
99 rpm accuracy on a range of 0-13,500 rpm is
.73 percent which is also better than j
2 2 percent.
l Therefore, the proposed range and accuracy results in measurement with accuracy better than Code requirements and will provide reasonable i
assurance of component operational readiness.
ALTERNATIVE a
TEST:
RCIC pump / turbine speed will be measured via available tachometers identified in the Basis For Relief.
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j Page 98-Rev 6-
)
1 RELIEF REQUEST RV-01 l
j VALVE:
Category A Containment Isolation Valves CIASS:
1,2,4 1/94 FUNCTION:
Primary Containment Isolation REQUIRED TEST:
Valve seat leakage may be determined by measuring leakage through a.
downstream telltale connection or by measuring the makeup feed rate needed to maintain constant pressure in the test volume (IWV-3424).
BASIS FOR RELIEF:
The. pressure decay method is suitable for measuring air or nitrogen '
leakage and is one of the methods permitted by 10CFR50, Appendix J.
ALTERNATIVE TEST:
The pressure decay method may be used as an alternate option to leak rate I
testing methods ofIWV-3424 to determine seat leakage. Measurement of i
valve seat leakage will be performed in accordance with Appendix J Local.
Leak Rate Tests.
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Page.101 Rev 6-RELIEF REQUEST RV-06
- VALVE
CRD-AOV-CV126 (typical of 137 each)
CRD-AOV-CV127 (typical of 137 each)
CRD-CV-CV114 (typical of 137 each)
CLASS:
4 1/94
- FUNCTION.:
CRD-AOV-CV126 - Open with scram signal to pressurize lower side of l
CRD pistons from accumulator or charging header.
CRD-AOV-CV127 - Open with scram signal to vent top of CRD pistons to' l-scram discharge header.
CRD-CV-CV114 - Open to allow flow from the top of the CRD pistons to'the l
REQUIRED
'i TEST:
Full stroke exercise, observe proper operation of fail-safe mechanism, and measure stroke time quarterly or each cold shutdown (IWV-3411, IWV-3413, IWV-3415, IWV-3521, and IWV-3522).
t BASIS FOR RELIEF:
These valves are required to operate for rapid insertion (scram) of control j
rods. Each valve is tested by scram-timing control rods in accordance with Technical Specification Sections 3.3 and 4.3. The Technical Specifications require testing 10 percent of the CRDs every 16 weeks and 100 percent of the drives each refueling. The CRDs must fully insert within specified time limits. Should either the insert or exhaust valves fail, the CRDs'would not be able to meet Technical Specification requirements.
The air-operated valves fail-open on loss of air or power, Normal opening
[
removes power to the pilot solenoid valve, simulating a loss of power. On -
1 loss of power, the solenoid vents the air operator and CRD-AOV-CV126 and CRD-AOV-CV127 are spring-driven open. Thus, each time a scram signal is given, the valves " experience" a loss of air / power to. verify each valve's -
fail-safe open feature. In effect, scram-testing meets or' exceeds the functional testing requirements of.Section XI to assess operational readiness. Individual stroke time measurements of CRD-AOV-CV126 and CRD-AOV-CV127 is impractical due to their rapid acting operation and the-1 absence of remote position indication that is.needed for measuring stroke time.
One hundred percent of the valves cannot be tested more often than each refueling outage. To test 100 percent of the valves wouhl result in a full reactor scram. An excess number of scrams performed routinely could cause thermal and reactivity transients, which could lead to fuel, vessel, CRD, or piping damage. The CRDs cannot be tested during cold shutdown because the control rods are inserted and must remain inserted.
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1 Page 103 RevG RELIEF REQUEST RV-07
("
VALVE:
CRD-CV-CV115 (typical of 137 each) l CLASS:
4 1/94 FUNCTION:
Prevent bypassing scram water (from the accumulator) to charging water header (if depressurized).
l REQUIRED TEST:
Exercise quarterly or each cold shutdown in accordance with IWV-3522 (IWV-3521 and IWV-3522).
l 11 ASIS FOR i
RELIEF:
Exercising these valves ri%uires the control rod drive pumps to be stopped for depressurization of the control rod drive charging water header. This is imprudent during normal plant operation due to the potential for pressure variations in the CRD System duiing the test evolution. Also, stopping the pumps results in loss of cooling water to all control rod drive
]
mechanisms and seal damage could result.
Exercising these valves at cold shutdown intervals is impractical because the control rod drive pumps supply seal water to the reactor recirculation pumps and one of the recirculation pumps is usually kept running. Testing would also place an undue burden on plant personnel.
]
ALTERNATIVE TEST:
These valves will be tested during each reactor refueling in the reverse flow direction (closed position) by isolating each of the CRD scram accumulators and venting pressure on the upstream side of the check valve. Accumulator pressure decay would be observed should the respective valve fail to close properly.
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Page 104 Rev 6
.I RELIEF REQUEST RV-11 VALVE:
Excess Flow Check Valves NBI-CV-10BCV to 47BCV (Drawing 2026)
RR-CV-10CV to 13CV (Drawing 2027)
J RR-CV-15CV to 18CV (Drawing 2027)
]
RR-CV-27CV to 28CV (Drawing 2027)'
l RR-CV-30CV to 33CV (Drawing 2027) '
8/91 MS-CV-10BCV to 17BCV (Drawing 2041)
HPCI-CV-10BCV to 11BCV (Drawing 2041)
RCIC-CV-10BCV to 13BCV (Drawing 2041)
CS-CV-16BCV to 17BCV (Drawing 2045)
CLASS:
1 1/94 FUNCTION:
These valves are installed in instrument lines that provide signals for operation of safety-related valves and pumps. They prevent excess flow of reactor water should an instrument line break outside containment.
REQUIRED TEST:
Test in accordance with Section XI, IWV-3521, and IWV-3522.
BASIS FOR RELIEF:
Uninterrupted function of these valves is essential for safety. Routine O
testing in accordance with Section XI would cause instrument line interruptions. This would disable instruments required for safe plant -
operations, safety-system actuation, reactor shutdown, or sensing accident conditions.
The excess flow check valves are tested using a modified leak-rate test to assess operability. Testing is performed at least once each operation cycle in accordance with Technical Specification 4.7.D.I.d.
Testing more frequently could jeopardize the safety of the reactor.
ALTERNATIVE TEST:
In lieu of Section XI testing, a modified leak-rate test will be performed at least once each operation cycle.
O
Page 108 Rev 6 RELIEF REQUEST RV-17
.l J
l VALVE:
RHR-CV-20CV CLASS:
2 i
FUNCTION:
RHR-CV-20CV is the emergency Service Water (SW)(river water) supply for core flooding.
l REQUIRED TEST:
Exercise each quarter or cold shutdown.
1194
'l R
BASIS FOR RELIEF:
Routine exercising with SW flow could potentially allow corrosive materials l
and sand to be introduced into the Reactor Coolant system via RHR. This could lead to poor water purity, loss of chemical control, fuel degradation,-
i and mechanical fouling of the reactor, associated pumps, piping, and valves.
This would lead to reactor and/or system damage.
Therefore, 1/94 RHR-CV-20CV cannot be full-stroke or part-stroke exercised during operations or cold shutdown.
j i
ALTERNATIVE TEST:
The valve will be mechanically exercised during each refueling outage.
1/94.
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-__m Page 110 Rev 6 -
~ RELIEF REQUEST RV-20
(
VALVE:
HPCI-CV-11CV j
. CLASS:
2 l
1 FUNCTION:
This valve is the HPCI pump suction line check valve from the torus and is normally closed.
REQUIRED TEST:
Exercise cach quarter or cold shutdown.
1/94-1
~
BASIS FOR RELIEF:
Partial or full-stroke exercising this valve is not possible with the existing.
j system design. It would necessitate a system design change to permit recirculation to and from the torus.
Also, routine circulation of torus water through the HPCI System could l
potentially lead to system fouling, corrosion, and degradation. Degradation and damage to the HPCI could lead to a larger problem if the HPCI System was needed for an emergency. In order to preserve the integrity of the.
-1/94 HPCI System, this valve will not be full-stroke or part-stroke exercised during operations or cold shutdowns.
ALTERNATIVE TEST:
The valve will be mechanically exercised during each refueling outage.
1/94 l
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Page 113 Rev 6 i
i.
RELIEF REQUEST RV-23 VALVE:
RCIC-CV-11CV CLASS:
2 i
FUNCTION:
This valve is the RCIC pump suction line check valve from the torus and
[
is normally closed.
REQUIRED TEST:
Exercise each quarter or cold shutdown.
i BASIS FOR REIIEF:
Partial or full-stroke exercising this valve is not possible with the existing system design.
It would involve a system design change to permit' l
recirculation to and from the torus.
Also, routine circulation of torus water through the RCIC System could potentiallylead to system fouling, corrosion, and degradation. Degradation and damage to the RCIC System could lead to a larger problem if the RCIC System was needed for an emergency. In order to preserve the 1/94 integrity of the RCIC System, this valve will not be full-stroke or part-stroke exercised during operations or cold shutdowns.
l ALTERNATIVE TEST:
The valve will be mechanically exercised during each refueling outage.
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Page 118 Rev 6 i
(This page intentionally left blank).
1/94 l
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Page 121 Rev 6 -
RELIEF REQUEST RV 31 VALVE:
CRD-CV-13CV CRD-CV-14 CV CRD-CV-15CV CRD-CV-16CV CIASS:
1 1/94 FUNCTION:
Containment isolation valves for Control Rod Drive seal injection water for i
the Reactor Recirculation (RR) pumps.
REQUIRED TEST:
Exercise each quarter or cold shutdown.
BASIS FOR RELIEF:
These valves cannot be exercised during operation. Stopping or reversal of.
flow would impose a severe thermal transient on the RR pump seals, which could possibly lead to premature seal failure.
During cold shutdown, there is insufficient pressure in the seal to verify.
l flow reversal; thus, testing is impractical.
i ALTERNATIVE TEST:
Each valve will be verified as operating properly (closing) during the leak rate test performed each refueling outage.
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Page 123 Rev 6 RELIEF REQUEST RV-36 VALVE:
PC-CV-13CV PC-CV-14CV CLASS:
4 1/94 FUNCTION:
Torus Vacuum Relief REQUIRED TEST:
Exercise each quarter or cold shutdown.
t BASIS FOR RELIEF:
Access to these valves is extremely difficult and hazardous. Despite the i
personnel hazard, they have been tested quarterly for over ten years and have never experienced a failure. The valves do not experience excessive use or stress which could lead to valve degradation. For these reasons, the testing frequency will be changed to once each refueling outage.
ALTERNATIVE l
TEST:
Exercise once each refueling outage.
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Page 124 Rev6 n.
RELIEF REQUEST RV 38 VALVE:
HPCI-CV-16CV HPCI-CV-170V i
HPCI-CV-15CV CLASS:
2, 4 1/94
.i i
I FUNCTION:
HPCI-CV-16CV - Closes for primary containment isolation.
l HPCI-CV-17CV - Opens to provide a flowpath for HPCI pump minimum l
flow; closes for primary containment isolation'.
HPCI-CV-150V - Opens to provide an exhaust path fbr the HPCI Turbine; l closes for primary containment isolation.
REQUIRED TEST:
Check valves shall be exercised at least once every three months, except as provided by IWV-3522 (IWV-3521).
BASIS FOR RELIEF:
These valves are simple check valves, and thus, have no mechanism by which valve closure can be verified. Thus, the only practical method of testing in the closed position is to impress a reverse differential pressure on the valves and measure the seat leakage.
Performing such a test renders the HPCI system inoperable, thus it is not 1
practical to perform during plant operation. Performing such a test at cold shutdowns could increase and complicate the outage workscope considerably and prove to be an undue burden on the plant staff.
ALTERNATIVE TEST:
These valves will be verified to the closed position during each refueling outage in conjunction with Appendix J leak rate testing activities.
Page 127 Rev 6 RELIEF REQUEST RV-41 VALVE:
REC-CV-16CV CLASS:
4 1/94 FUNCTION:
This valve closes to prevent backflow into the non-critical Reactor Building Closed Cooling Water (RBCCW) return header from the suction of the RBCCW pumps.
REQUIRED TEST:
Check valves shall be exercised at least once every three months, except as provided by IWV-3522 (IWV-3521).
BASIS FOR RELIEF:
To test CV-16 in the closed direction requires depressurization' of the non-critical REC return header. This, in turn, would interrupt cooling to important equipment, including the control rod drive pumps, RWCU pumps -
and heat exchangers, drywell ventilation coolers, reactor recirculation-pumps, and the recirculation pump motor generator sets. This could not be done during normal operation without subjecting major equipment to damage from overheating.
During cold shutdown periods,it is not unusual to maintain these critical systems / components in operation. Thus,in most instances, testing dud.ng cold shutdown is not practical.
ALTERNATIVE TEST:
During each reactor refueling interval, this valve will be exercised to the closed position.
Page 131 Rev 6 RELIEF REQUEST RV 45 VALVE:
Penetration Valves X-7A MS-AOV-A080A, MS-AOV-AOS6A 1
X 7B MS-AOV-A0808, MS-AOV-A086B j
X-7C MS-AOV-AO800, MS-AOV-AO86C X-7D MS-AOV-AO80D, MS-AOV-A086D X-8 MS-MOV MO74, MS-MOV M077 X-9A RF-CV-15CV, RCIC-CV 26CV, RWCU-CV-15CV 7/92 X-9B RF-CV-13CV, HPCI-CV-290V 7/92 X-10 RCIC-MOV MOIS, RCIC-MOV-MOl6 X-11 IIPCI-MOV M015, IIPCI MOV-MOl6
.l X-16A CS-MOV-Moll A, CS-MOV-M012A X-16B CS-MOV M011B, CS-MOV-M012B 1
1/94 X-25 PC-MOV-232MV, PC-AOV-238AV I
X-25 PC-MOV-1305MV, PC-MOV-1306MV X-26 PC-MOV-231MV, PC-AOV-246AV, PC-MOV-306MV, PC-MOV-1310MV X-39A RHR-MOV-MO26A, RHR-MOV-MO31A X-39B RHR-MOV-MO26B, RHR-MOV-MO31B X-39B PC-MOV-1311MV, PC-MOV-1312MV X-41 RR-AOV-740AV, RR-AOV-741AV 1/94 O
X-205 PC-MOV-233MV, PC-AOV-237AV X-205 PC-AOV-243AV, PC-CV-13CV X-205 PC-AOV-244 AV, PC-CV-14CV X-205 PC-MOV-1303MV, PC-MOV-1304MV X-210A RCIC-MOV MO27, RCIC-CV-13CV X 210A RHR-MOV-MOl6A, RHR-CV-10CV, RHR-CV-12CV X-210B IIPCI-MOV-MO25, HPCI-CV-17CV X-210B RHR-MOV-MOl6B, RHR-CV-11CV, RHR-CV-13CV-X 210A,211A RHR-MOV-MO34 A, RHR-MOV-MO38A, RHR-MOV-MO39A X-210B, 211B RHR-MOV-MO34B, RHR-MOV-MO38B, RHR-MOV-MO39B X-211B PC MOV-1301MV, PC-MOV-1302MV X-212 RCIC-CV-15CV,' RCIC-V-37 X-214 HPCI-CV 15CV, HPCI-V-44 X 214 RHR-MOV MOl66A, RHR-MOV-MOl67A X-214 RHR-MOV-MOl66B, RHR-MOV-MOl67B X-214
'HPCI-AOV-A070, HPCI-AOV A071 X-220 PC-MOV-230MV, PC-AOV-245AV, PC-MOV-305MV, PC-MOV-1308MV X-221 RCIC-CV-12CV, RCIC-V-42 X-222 HPCI CV-16CV, HPCI V-50
Page 132 Rev6 j
RELIEF REQUEST RV-45 (Continued)
CLASS:
1,2,4 1/94 FUNCTION:
Primary Containment Isolation Valves REQUIRED TEST:
Category A valves shall be seat leak tested to a specific maximum amount for each valve in the closed position for fulfillment of their safety function at least once every two years (IWV-3421,3426).
BASIS FOR i
RELIEF:
Even though individual testing of these valves is not performed, the actual 1/94 testing methods utilized are set up to provide comparable results and acceptance criteria.
The configuration of the piping systems are such that individual testing is.
1/94 j
either not possible or practical. Several penetrations do not contain a' manual isolation valve that can be used as a test boundary. Other penetrations do not have sufficient test connections to allow for individual testing. In some cases a test configuration could be developed using valves outside the containment boundary to individually test the applicable valves in the reverse direction or to block a leakage path through one valve while attempting to determine leakage through another, llowever, it would be very difficult to obtain accurate and meaningful results. These test e
configurations would typically involve considerably larger and more complex test volumes which include valves in the test boundary that were never intended to be leak tight. As a result, this testing would cause a considerable burden regarding manhours required, additional exposure, maintaining additional test boundary valves and plant outage delays, without providing additional assurance of containment integrity.
Furthermore, for all simultaneous valve leak rate testing, conservatism is 1/94 applied to assignment ofleak rate test results. When a leak rate has been obtained for a simultaneous test, that leakage rate is assigned to each valve in the set within the test boundary. Corrective action is taken on all associated valves unless additionalinformation is obtained which identifies the leaking valve.
Multiple valve leak rate testing, combined with conservatively applied leak 1/94' rates, outweighs the burden of individual leak rate test attempts. This testing will identify stuck open valves and provide adequate assurance of containment integrity.
ALTERNATIVE TEST:
Valves in each set (penetration) will be leak-rate tested simultaneously.
1/94 The measured leakage, which represents the combined leakage from the valves in the set, will be assigned to each valve.
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Page 142 Rev 6 '
l RELIEF REQUEST RV-55 i
VALVE:
RCIC-CV-20CV RCIC-CV-21CV l
CLASS:
2, 4 1/94 FUNCTION:
Botb valves open to provide a flowpath for the RCIC condensate pump discharge.
REQUIRED l
TEST:
Exercise each quarter or cold shutdown in accordance with IWV-3522(b).
I BASIS FOR RELIEF:
There is no practical means of verifying sufficient flow to full-stroke -
exercise the valves open. System configuration and absence of appropriate instrumentation prohibits full stroke open verification.
ALTERNATIVE i
TEST:
The valves will be disassembled, inspected and manually exercised during 12/92 i
each refueling outage. In addition, a partial stroke exercise test, with flow, will be performed quarterly, and after each disassembly / inspection.
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Page 143B RevG t
RELIEF REQUEST RV-58 1/94 VALVE:
MS-CV 20CV MS-CV-240V MS-CV-26CV MS-CV-32CV M S-CV-21C'v MS-CV-25CV MS-CV-29CV MS-CV-33CV MS-CV-22CV MS-CV-26CV MS-CV-30CV MS-CV-34CV MS-CV-23CV MS-CV-27CV MS-CV-31CV MS-CV-35CV CLASS:
3 FUNCTION:
Check valves required to open for vacuum relief of the main steam relief lines to the containment.
REQUIRED TEST:
Exercise each quarter or cold shutdown in accordance with IWV-3522.
BASIS FOR RELIEF:
For the reasons stated in Technical Justification TJV-15, these valves can only be exercised during cold shutdowns. TJV-15 also contains a caveat such that cold shutdown testing can only be performed when the drywell is de-inerted. Since these valves are located in the drywell, access is limited. Therefore, the valves are only accessible when the plant is shutdown and the drywell de-inerted.
The drywell is not always de-inerted when reaching the cold shutdown condition. In fact, de-inerting is undesirable since de-inerting/re-inerting is costly and takes a considerable amount of time. If required to de-inert for check valve testing only, this would cause a considerable startup delay.
Furthermore, this is only an issue if the_ plant goes to cold shutdown.
Except for refueling outages, cold shutdowns are usually not planned and if a shutdown occurs, down time is kept at a minimum.
ALTERNATIVE TEST:
These valves will be mechanically exercised during cold shutdown periods when the drywell is de-inerted.
i Page 143C Rev 6 -
RELIEF REQUEST RV-59 1/94 l
VALVE:
CRD-CV-25CV CRD-CV-26CV CIASS:
4 FUNCTION:
Close to prevent possible CRD bypass leakage from exiting secondary containment.
i REQUIRED TEST:
Valve seat leakage may be determined by measuring leakage through a
.I downstream tell tale connection or by measming the makeup feed rate-needed to maintain constant pressure in the test volume (IWV-3424).
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BASIS FOR RELIEF:
The preferred leak testing method at CNS is the pressore decay method.
CNS leak testing equipment and instruments are set up mainly for i
perfonning the pressure decay method. The pressure decay method is an j
acceptable method per 10CFR50, Appendix J. Therefore,it-is considered an adequate leak testing method, capable of providing equally reliable l
results as would be obtained by ASME IWV-3424 leak testing methods.
ALTERNATIVE TEST:
The pressure decay method may be used as an alternate option to leak rate testing methods of IWV-3424 for leak testing / closure testing during cold shutdowns.
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Page 143D Rev 6 t
RELIEF REQUEST RV 1/94 9
VALVE:
HPCI-AOV-AO70 HPCI-AOV-A071 NMT-NVA-104A NMT-NVA-104B i
NMT-NVA-104C NMT-NVA-104D CLASS:
2 and 4 (HPCI-AOV-AO71)
FUNCTION:
HPCI-AOV-AO70 and HPCI-AOV-AO71 - Close for primary containment isolation.
NMT-NVA-104A, B, C, D - Close to prevent leakage back through the Traversing In-Core Probe line.
REQUIRED TEST:
If, for power operated valves, an increase in stroke time of 50 percent or more for valves with full-stroke times less than or equal to ten seconds is observed, test frequency shall be increased to once each month until corrective action is taken, at which time the original test frequency shall be resumed (IWV-3417(a)).
BASIS FOR RELIEF:
These valves are rapid acting valves, since their normal stroke time is less than two seconds. It is difficult to apply the code 50 percent stroke time increase requirement to these valves.
For these valves, much of the difference in stroke times from test to test comes from inconsistencies in the operator or timing device used to gather data.
Thus, the results may not be representative of actual valve
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degradation. Therefore, the 50 percent increase criteria is not practical for these valves.
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ALTERNATIVE TEST:
The 50 percent increase criteria will not be applied to these valves. A two second maximum limiting value of full-stroke time will be assigned to these valves and, upon exceeding this limit, will declare the valve inoperable l
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Page 143E Rev 6 RELIEF REQUEST RV-61 1/94
}
VALVE:
Non-Component Specific CLASS:
Non-Class Specific FUNCTION:
Not Applicable n
REQUIRED TEST:
This Subsection provides the rules and requirements for inservice testing to verify operational readiness of certain Class 1,2, and 3 valves (and their actuating and position indicating systems) in light-water cooled nuclear i
plants, which are required to perform a specific function in shutting down C
a reactor to the cold shutdown condition or in mitigating the consequences of an accident (IWV-1100).
j BASIS FOR RELIEF:
Cooper Nuclear Station's accident analyses do not carry the plant response j
to an accident (e.g., Design Basis LOCA) to a point beyond a hot shutdown condition (i.e., to a cold shutdown condition). The licensing basis does not i
require the plant to go to the cold shutdown condition in order to satisfy 10CFR100 radiological release guidelines.
Since Safe Shutdown is defined in the CNS licensing basis as the hot shutdown condition, inservice testing of components which are required to achieve cold shutdown is unwarranted, and does not provide any increase in the level of program quality or safety to the public.
j ALTERNATIVE TEST:
Cooper Nuclear Station's Inservice Testing (IST) Program will implement the rules and requirements for inservice testing to verify operational-readiness of certain Class 1, 2, and 3 valves (and their actuating and position indicating systems)in light-water cooled nuclear plants, which are required to perforrn a specific function in shutting down a reactor to the hot shutdown condition or in mitigating the consequences of an accident.
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Components which support achievement of cold shutdown only, are not required to be included in the IST Program.
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RELIEF REQUEST RV-62 1/94 i
VALVE:
All Safety Relief and Relief Valves j
CIASS:
1, 2 i
FUNCTION:
Various l
REQUIRED TEST:
Safety valve and relief valve set point shall be tested in accordance with ASME PTC 25.3-1976 (IWV-3512). PTC 25.3-1976:
3.02 Qualification of Person Supervising the Test. A person who has obtained a degree in a branch of engineering from a recognized school of engineering and in addition, has had at least two years practical experience in fluid-flow measurement, may be considered i
qualified to supervise the test.
t 3.03
_ Responsibility of Person Supervising the Test.
The person supervising the test shall be present at all times during the test.
-i BASIS FOR
~
RELIEF:
PTC 25.3-1976 was written for testing at the manufacturer's facility and includes requirements that are difficult to apply to an operating power i
plant. The OM Committee has recognized this and have issued OM-1,
" Requirements for Inservice Performance Testing of Nuclear Power Plant O
Pressure Relief Devices," for application to IST. Paragraph 1.3.2.1(d) of l
OM-1 lists "the qualification of personnel who perform testing and i
maintenance" as an item for which the owner has responsibility.
Furthermore, it is not necessary for the test supervisor to be present at all times during testing. CNS procedures for relief valve testing provide step by step instructions, including Quality Control (QC) witness and hold points / signatures at critical steps. The procedure also requires a test.
performer to have the ability, skill, training or experience regarding relief valve testing.
The alternative for these requirements, as specified below, provides for code equivales relief valve testing and does not reduce test quality.
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ALTERNATIVE TEST:
For relief valve testing on site, the educational requirements in i
PTC 25.3-1976 for the test supervisor will not be followed, nor wih the test -
supervisor be present at all times during the test. CNS has established the -
criteria for qualifying the test supervisor and documented the qualifications -
in the test implementation procedures.
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If a vendor is used to perform safety or relief valve testing, then that -
testing will be performed in accordance with PTC 25.3-1976, with 1977 Addendum.
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.I Page 145. Rev 6 TECHNICAL JUSTIFICATION TJV-02 VALVE:
RHR-MOV-M017 RHR-MOV-M018 j
CIASS:
1 1/94 FUNCTION:
Reactor vessel return to the RHR pump suction and containment isolation during reactor operations.
They are only opened for low pressure l
i
- BASIS FOR l
TECHNICAL JUSTIFICATION: Valves RHR-MOV-M017 and RHR-MOV-M018 are interlocked for pressure isolation during plant operation. Opening these valves during operations could possibly allow high pressure reactor coolant water into the low pressure suction lines of the RHR system. Therefore, it is f
essential that these valves remain closed during plant operations.
ALTERNATIVE TEST:
The test frequency will be during cold shutdowns in accordance with IWV-3412(a).
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Page 149 Rev 6 a
i TECHNICAL JUSTIFICATION TJV-12 VALVE:
CRD-CV-138 (Typical of 137)
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CLASS:
4 1/94-FUNCTION:
Close to prevent reverse flow into cooling water header during SCRAM.
I BASIS FOR TECHNICAL JUSTIFICATION: This technical justification is written to document the testing method of the cooling water header check valves as required by G.L. 89-04, position 7. Normal control rod motion will verify _these check valves have moved to their safety function position. Industry experience has shown that rod motion may not occur if this check valve were to failin the open position.
i ALTERNATIVE l
TEST:
During normal plant operation above 30 percent power, each partially or fully withdrawn operable control rod is exercised one notch at least once each week (Technical Specification 4.3.A.2). A cooling water header check valve is verified closed when a control rod is successfully exercised.
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i Page 151 Rev G j
TECHNICAL JUSTIFICATION TJV-14 7/92 q
VALVE:
SGT-CV-14CV and SGT-CV-15CV 1/94 j
CLASS:
4 i
FUNCTION:
SGT-CV-14CV and SGT-CV-15CV - Open to provide flow paths from 1/94 exhaust fans.
l BASIS FOR TECHNICAL i
t JUSTIFICATION: The acceptance full flow rate for these valves isz 1602 cfm. During plant power operations, system conditions exist that prevent the SGT system from achieving a flow rate of2 1602 cfm. Reactor building differential pressure and back pressure from the Off Gas Dilution Fans act against i
SGT system pressure restricting SGT system flow rate. Therefore, it is j
impractical to perform a full flow rate test of these valves at power l
operanons.
1 ALTERNATIVE TEST:
A partial open stroke test will be performed on these valves during plant power operations on a quarterly frequency. A full flow open test will be performed on these valves during cold shutdown periods.
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Page 151A Rev 6 TECHNICAL JUSTIFICATION TJV-15 1/94 VALVE:
MS-CV-20CV MS-CV-24CV MS-CV-28CV MS-CV-32CV MS-CV-21CV MS-CV-25CV MS-CV-29CV MS-CV-33CV MS-CV-22CV MS-CV-26CV MS-CV-30CV MS-CV-34CV 1
MS-CV-23CV MS-CV-27CV MS-CV-31CV MS-CV-35CV CLASS:
3 FUNCTION:
Check valves required to open for vacuum relief of the main steam relief lines to the containment.
BASIS FOR l
TECIINICAL l
JUSTIFICATION: These vacuum breaker check valves are located inside containment and are not equipped with actuators or position indicators. Manual exercising requires drywell access. The drywell is not accessible during normal station operations and therefore the valves cannot be full-stroke or partial-stroke exercised during normal station operations.
ALTERNATIVE TEST:
Each valve will be mechanically exercised during cold shutdowns, when the drywell is de-inerted, in accordance with IWV-3522.
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i Page 151B Rev 6 TECHNICAL JUSTIFICATION TJV-16
'1/94 f
VALVE:
CRD-CV-25CV CRD-CV-26CV CLASSi 4
I FUNCTION:
Close to prevent possible CRD bypass leakage from exiting secondary
(
containment.
BASIS FOR TECHNICAL JUSTIFICATION: It is impractical to perform a closure test or a partial closure test on l
these valves during power operations. These valves are located in the i
line from the CRD pumps supplying drive water and charging water to the control rod's Hydraulic Control Units (HCUs).
During power operations these valves are open since drive water is constantly supplied to the HCUs. Closure or partial closure testing would require the CRD pumps to be secured and the portion of the system containing these i
vrdves to be isolated.
r Isolating the valves or securing the CRD pumps terminates the constant drive water supply to the HCUs, which causes all control rods to be inoperable. All control rods inoperable at power operations puts the plant into a Tech. Spec. LCO requiring shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, which is operationally undesirable. Also, without a continuous charging water supply, HCU accumulators would eventually depressurize, since the -
associated accumulator check valves are not designed to be leak tight; Administrative controls require a
SCRAM initiation upon depressurization of two HCU accumulators, which is a highly undesirable situation.
The increased potential for plant shutdown during testing at power operations outweighs the minor increase in confidence of component
^
operational readiness when testing quarterly.
i ALTERNATIVE TEST:
These valves will be tested closed during cold shutdown periods.
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