ML20236U330
| ML20236U330 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/24/1987 |
| From: | Richey R CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20236U332 | List: |
| References | |
| NLS-87-261, NUDOCS 8712020438 | |
| Download: ML20236U330 (25) | |
Text
_ _ _ - _ _ _ _ _ _
4:sadhaw
- - a e e.~.,
P. O Box 1551
- Raleigh, N C. 27602 NOV 2 4 567 R B. RICHEY, Manager Licensing & Nuclear Fuel Department L
SERIAL: NLS-87-261 l
10CFR50.55a United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS.- DPR-71 & DPR-62 IN-SERVICE TESTING PROGRAM Gentlemen:
Carolina Power & Light Company participated in a meeting concerning the Brunswick Steam Electric Plant (BSEP) Units 1 and 2 In-Service Testing (IST) Program on July 21 and 22, 1987.
The minutes of that meeting were issued by the NRC on September 28, 1987.
In the meeting, the NRC identified several open items i
which needed to be addressed to allow completion of their review of the Program.
This information is provided in Enclosure 1.
The Company has revised the IST Program for BSEP to address NRC concerns and to provide a more consistent, concise document.
- contains descriptions of changes made to the Program which were not addressed in response to NRC questions.
i-Administrative changes, such as typographical errors, valve information (i.e., coordinates) or additional test type / relief request references added for consistency between the units are not identified. contains the revised IST Program.
The Company requests that interim approval of this Program be granted by January 31, 1988 in order to support inspection activities required during the upcoming BSEP-2 refueling outage.
This outage is scheduled to begin on January 2, 1988.
/9 o
i i
l 8712020438 87112f g\\
PDR ADOCK 05000324 p
PDR L----
_ - - -_~
1
.i
~
. Document Control-Desk-NLS-87-261 /-Page 2
]
l Please refer any questions to Mr. Sherwood R..Zimmerman.at-(919) 836-6242.
4 Yours very truly, 1
4 ff R.
B. Richey
Enclosures:
1.
Summary of Additional Actions Taken
- 2. Summary of Additional Changes
'l
- 3. Revised IST Program
'l cc:
Dr. J. Nelson Grace Mr. W. H. Ruland Mr.-E.
D. Sylvester Mr. J.
Blake cc's receive all Enclosures.
1 l
l l
'l I
L
1 ENCLOSURE 1 Summary of Additional Actions Taken Since Initial Responses A. General ODerations and Comments 1.
This item was resolved in the July meeting.
No additional action was necessary.
2.
This item was resolved in the July meeting.
No additional action was necessary.
3.
Check Valves 1-VA-IA-CV-CB, 1-VA-1B-CV-CB, 2-VA-2A-CV-CB,
)
and 2-VA-2B-CV-CB have been added to Pages 152 (Unit 1) and 222 (Unit 2) of the revised IST Program Valve Tables.
I B.
Service Water System 1.
Relief Request VR-15 on Page 49 of the revised IST Program has been revised and Relief Requests VR-16, on Pages 50-51, and VR-17, on Page 52, have been generated to include the Service Water System (Lubricating Water) check valves in a I
disassembly program until the completion of the appropriate I
plant modification (s).
Pages 98-99 (Unit 1) and 157 (Unit
- 2) of the Valve Tables were also changed to reflect this I
information.
As stated in the meeting on July 21-22, 1987, a decision will be made by December 15, 1987 as to which l
option will be implemented at BSEP.
A submittal will be made after that date which will provide implementation plans.
C.
Diesel Generator Service Water System 1.
Relief Request VR-18 on Page 53 of the revised IST Program has been generated to include Valves SW-V272, SW-V273, SW-V274, and SW-V275 in a disassembly program.
Pages 96-97 (Unit 1) and 166-167 (Unit 2) of the Valve Tables were also changed to reflect the applicability of Relief Request VR-18 to these valves.
l l
Page 1 L__
ENCLOSURE 1 (Continued)
D.
Containment Atmosoberic Control System' 1.
Remote position indicator verification has.been added to' Valves CAC-X18A through J.
This is shown in the revised IST Program Valve Tables, Pages 101-102 (Unit 1) and.169-170 (Unit 2)under " Test Type" and " Test Frequency."
q 2.
The applicability of Relief Request VR-03 to Valves 1-CAC-V160 and 1-CAC-V162 has been added on Page.1031of the revised IST Program Valve Tables.
3.
The P&ID location of valves 2-CAC-SV-4344 and 2-CAC-SV-4345 has been identified on Page 168 of the revised IST Program Valve Tables.
4.
The P&ID' location of Valve 2-CAC-V170 has been corrected on Page 171 of the revised IST Program Valve Tables..
5.
The information relating to Valve 2-CAC-V171 has been revised on Page 168 of the revised IST Program Valve Tables.
E. Control Rod Drive System 1.
Relief Request VR-04 on Pages 35 and 36 of the revised IST Program has been revised to further address. testing of Valve C11/C12-138 and to delete Valve C11/C12-115.
Cold Shutdown Justification VC-17 on Page 82 has been generated to address testing of C11/C12-115.
Pages 105 (Unit 1) and 173 (Unit 2) of the Valve Tables have also been revised to reflect this information.
2.
Relief Request VR-04 on Page 35 of the revised IST Program has been revised to further address stroke timing of Valves C11/C12-CV126 and C11/C12-CV127.
Pages 105 (Unit 1) and 173 (Unit 2) of the Valve Tables have also been revised to reflect this information.
F.
Reactor Coolant Recirculation System 1.
Relief Request VR-05 on Pages 37 through 39 of the revised IST Program has been revised to add more~ technical detail. '
2.
Pages 107, 138, 175, and 206 of the revised IST Program Valve Tables has been revised to show that the normal position of Valves B32-F032A and B32-F032B is open.
Page 2
.---_.--..--,.-s-i--------,---,-------,--____----,---,,-_.
ENCLOSURE 1 (Continued)
G.
Nuclear Steam Sucolv System 1.
Pages 110 and 112 (Unit 1) and 178 and 180 (Unit 2) of the revised IST Program Valve Tables have been revised to reflect the current exercising frequency for the ADS valves.
2.
Relief Request VR-08 on Page 42 of the revised IST Program has been deleted and Cold Shutdown Justification VC-16 on Page 81 has been generated to address testing of the valves during cold shutdown.
Pages 111 (Unit 1) and 179 (Unit 2) of the Valve Tables have also been revised.
H. HJah Pressure Coolant Iniection System 1.
Cold Shutdown Justification VC-14 on Page 79 of the revised IST Program has been generated to allow testing of Valve E41-F002 at a cold shutdown frequency.
Pages 117 (Unit 1) and 185 (Unit 2) of the Valve Tables have also been revised to reflect this information.
2.
It has been determined that Valve E41-F019 does perform a safety function in the closed position.
Relief Request VR-20 on Page 55 of the revised IST Program has been i
generated to include the check valve in a disassembly program.
Pages 117 (Unit 1) and 185 (Unit 2) of the Valve Tables have also been revised to reflect this information.
3.
Relief Request VR-19 on Page 54 of the revised IST Program has been generated to allow partial exercise of Valve E41-F046 quarterly and to include the check valve in a disassembly program.
Pages 117 (Unit 1) and 185 (Unit 2) of the Valve Tables have also been revised to reflect this information.
4.
Relief Request VR-21 on Page 56 of the revised IST Program has been generated to include check valve E41-V93 in a disassembly program.
Check valve E41-V94 has been deleted from the IST Program and the ISI boundary P& ids will be revised to show the class break at Check Valve E41-V93.
Pages 117 (Unit 1) and 185 (Unit 2) of the Valve Tables have also been revised to reflect this information.
5.
Valve E41-F011 has been added to the revised IST Program on Pages 117 (Unit 1) and 185 (Unit 2) of the Valve Tables.
Page 3
i i
ENCLOSURE 1 (Continued) 6.
Relief Request VR-06 on Page 40 of the' revised IST Program and Pages 118 (Unit 1) and 186 (Unit 2)of the Valve Tables have been revised to delete Valves E41-F021 and E41-F022.
Cold Shutdown Justification VC-18 on Page 83 has been generated to state that the check valves will'be verified closed by handwheel at a cold shutdown frequency.
7.
Relief Request VR-22 on Pagef57 of the revised IST Program j
has been. generated to allow partial exercise of Valve j
E41-F045 quarterly and to include the check valve in a disassembly program.
Pages 118 (Unit 1) and 186 (Unit 2) of the Valve' Tables have also been revised.
J 8.
Valves E41-V8 and E41-V9 have been-deleted from the IST Program.
This is reflected on Pages 117- (Unit 1) and 185 (Unit 2) of the Valve Tables.
1
)
9.
Cold Shutdown Justification VC-19 on Page 84'of the revised
]
IST Program has been generated to add Valves E41-F076 and E41-F077 to the IST Program at a cold shutdown frequency.
]
Pages 118 (Unit 1) and 186 (Unit 2) of the Valve Tables have also been revised to reflect this information.
I.
Core Sorav System 1.
Relief Request VR-09 on Page 43 of the revised IST Program has been revised to add more technical detail.
2.
Valves E21-F007A and E21-F007B are manual valves and have therefore been removed from the revised IST Program.
Pages 1
120-121 (Unit 1) and 188-189 (Unit 2) of the Valve Tables have been revised to reflect this information.
3.
Relief Request VR-21 on Page 56 of the revised IST Program has been generated to include check valves E21-F030A'and E21-F030B in a disassembly program.
Check Valves E21-F029A and E21-F029B have been deleted from the IST Program and the i
ISI boundary P& ids will be revised to show the class break at Check Valves E21-F030A and E21-F030B.
Pages 120-121 (Unit 1) and 188-189 (Unit 2) of the Valve Tables have also been revised to reflect this information.
Page 4
1 ENCLOSURE 1 (Continued) 1 J. Residual Heat Removal 1.
Cold Shutdown Justification VC-11 on Pages 75 and 76 of.the revised IST Program has been revised to add'more technical detail and Pages 123 and 126 (Unit 1), and 191 and 194 (Unit 2) of the Valve Tables have been revised to show the valves being tested at a cold shutdown frequency in both' units.
1 2.
Page 123 (Unit 1) of the Valve Tables has been revised to reflect that both the 1 E11-F016A and the 2-E11-F016A valves are stroke tested in both directions as discussed in the July meeting.
3.
Page 195 (Unit 2) of the Valve Tables have been revised to j
correct the typographical error as discussed in the July
- )
meeting.,
R i
4.
Relief Request VR-19 on Page 54 of the revised IST Program
]
has been generated to allow partial exercise of Valves E11-F046A,B,C, and D quarterly and to include the check valves in a disassembly program.
Pages 124 and 127 (Unit 1) and 192 and 195 (Unit 2) of the Valve Tables have also-been revised to reflect this information.
5.
Relief Request VR-21 on Page 56 of the revised IST Program has been generated to include check valves E11-V193, l
E11-F089 (Unit 1) and E11-F090 (Unit 2) in a disassembly program.
Check valves E11-V192, E11-F090 (Unit 1) and E11-F089 (Unit 2) have been deleted from the revised IST l
Program, and the ISI boundary P& ids will be revised to show j
the class break at E11-V193, E11-F089 (Unit.1) and E11-F090 (Unit 2).
Pages 124 and 128 (Unit 1) and 192 and 196 (Unit 2) of the Valve Tables have been revised to reflect i
this information.
6.
Valves E11-F022 and E11-F023 have been changed to passive i
valves. See Program Remark V-07 on Page 92 of the Revised IST Program and Pages 126 (Unit 1) and 194 (Unit 2) of the revised IST Program Valve Tables.
7.
Valves E11-F078 and E11-F075 have been added'to the revised I
IST Program, and Relief Request VR-23, on Page 58 of the I
Revised IST Program has been generated to provide.for i
testing these valves at a refueling frequency.
Pages 125 (Unit 1) and 193 (Unit 2) of the Valve Tables have also been l
changed to reflect this information.
Page 5
)
i ENCLOSURE'1 (Continued)
)
l 1
Additional Comments:
Valves E11-LVF053A and E11-LVF053B have j
been deleted from the' revised IST Program.~of the Valve See'Pages 122 1
and 125 (Unit 1) and 190 and 193 (Unit 2)
Tables.
K. Reactor Water Cleanuo System 1
j 1.
Valva G31-F039.is required to close upon Reactor Core
')
Ise'8acion Cooling (RCIC) injection.
As discussed in Section "L" below, RCIC is not~ safety related..Therefore, G31-F039 does not perform a safety related function and has been deleted from the revised IST Program.
See Pages 129 (Unit 1) and 197 (Unit 2) of the Valve Tables.
L. Reactor Core Isolation Coolina System 1.
Reactor Core Isolation Cooling System.(RCIC) is not addressed in any. accident scenario in the FSAR.
- However, the Plant will be placed in a' Limiting Condition'for l
Operation (LCO) if the system is declared inoperable.
j Therefore, Cold Shutdown Justification VC-15, Page 80 of the revised IST Program has been generated'to.. test Valve E51-F007 at a cold shutdown frequency.
Pages 130 (Unit 1) and 198 (Unit 2) of the Valve Tables have also been revised to reflect this information.
2.
Valves E51-V72 and E51-V73 have been deleted from'the revised IST Program.
See Pages 130 (Unit 1)'and 198 (Unit 2) of the Valve Tables.
3.
The full-stroke exercise to.the open position for Valve E51-V88 has been deleted from Pagen'130 (Unit 1) and 198 (Unit 2) of the revised IST Program Valve Tables.
4.
Valves E51-V8 and E51-V9 have been deleted from the revised IST Program. See Pages 130.(Unit 1) and 198 (Unit 2) of the Valve Tables.
5.
Relief Request VR-06 on Page 40 of the revised IGT Program has been revised to delete Valves E51-F001 and E51-F002.
Cold Shutdown Justification VC-18 on'Page 83 has been Page 6
ENCLOSURE 1 (Continued) l l
generated to state that the check valve will be verified closed by handwheel at a cold shutdown frequency.
Pages 131 (Unit 1) and 199 (Unit 2) of the Valve Tables have been l'
revised to reflect this information.
6.
Valve E51-F021 has been deleted from the revised IST I
Program.
This is reflected on Pages 131 (Unit 1) and 199
)
(Unit 2) of the Valve Tables.
i 7.
Valve E51-F030 has been deleted from the revised IST Program.
This is reflected on Pages 131 (Unit 1) and 199 (Unit 2) of the Valve Tables.
B.
Valves in the RCIC System that do not perform a Primary Containment Isolation function (E51-F010, E51-F012, E51-F014, E51-F017, E51-F021, E51-F022, E51-F029, E51-F030, E51-F045, E51-V8, E51-V9, E51-V72, E51-V73) have been I
deleted from the revised IST Program.
For valves that j
perform a Primary Containment Isolation function and were i
full-stroke exercised (timed) to the open position j
(E51-F013, E51-F031, E51-F040, E51-V88) the full-stroke exercise (timed) to the open position has been deleted from the revised IST Program. This is reflected on Pages 130-131 3
(Unit 1) and 198-199 (Unit 2) of the Valve Tables, j
I i
M.
Service Water System 1
1.
No additional response or changes to the IST Program are necessary.
j 2.
Relief Request VR-24 on Page 59 of the revised IST Program i
has been generated to address concerns relating to Valves E11-F068A (Unit 2) and Ell-F068B (Unit 2).
Relief Request VR-23 on Page 58 has been generated to address concerns l
relating to Valve E11-F073.
Pages 132-133 (Unit 1) and l
200-201 (Unit 2) of the Valve Tables have also been revised l
to reflect this information.
l N.
Standby Liauid Control System 1.
Relief Request VR-25 on Page 60 of the revised IST Program has been generated to address concerns relating to the C41-F033A (Unit 2) and C41-F033B (Unit 2) Valves.
Page 205 l
of the Valve Tables has also been revised to reflect this information.
Page 7
ENCLOSURE 1 (Continued)
]
O.
Fuel Pool Coolina and Filterina System 1.
No additional response is necessary.
P.
Instrument Air Suonly System i
3 1.
Relief Request VR-11 on Page 45 of the1 revised IST Program
.has been deleted and the check valves added to Cold Shutdown Justification VC-09 on Page 73.
Cold. Shutdown Justification VC-09 has been revised.to add more technical detail.
Pages 141-143, and 146 (Unit 1) and'210-212 and 215 (Unit 2) of the Valve Tables have also been revised to reflect this information.
2.
Pages 213 and 214 (Unit.2) of the Valve Tables have been l
corrected to reflect the P&ID locations of Valves 2-RNA-5261
^
and 2-RNA-5262.
3.
Cold Shutdown Justification VC-09' on Page 73 of the revised
]
IST Program has been revised ~to add more technical detail.
Q. Containment Atmosphere Monitorina System 1.
Cold Shutdown Justification VC-10 on-Page 74 of the revised IST Program has been revised to add more technical. detail, i
R. Standbv Gas Treatment System t
1.
The remote position indicator verification test has been added for valves SGT-V8 and SGT-V9 on Pages 153 (Unit 1) and' 221 (Unit 2) of the revised IST Program Valve Tables.
S. Diesel Generator Startina Air System i
1.
Pages 158-161 (Unit 2) of the revised IST Program Valves Tables have been revised'to reference Relief Request VR-13, as stated in the July meeting.
2.
Relief Request VR-13 on Page 47 of the revised IST Program has been revised to add more technical detail.
3.
Relief Request VR-26 on Page.61 of the revised IST Program has been generated to include the check valves.in a-disassembly program.
Pages.158-161 (Unit 2) of the Valve Tables have also been revised to reflect this information.
Page 8
ENCLOSURE 1 (Continued) l 2.
PUMP TESTING I
1.
Relief Request PR-03 on Page 11 of the revised IST Program has been revised to delete the Unit 1 pumps and add a note l
addressing completion of modifications that will make Relief Request PR-03 unnecessary.
2.
This item was resolved in the July meeting.
No additional action is necessary.
3.
Relief Request PR-05 on Page 13 of the revised IST Program has been revised to state that the Service Water Lube Water System may be deactivated or down-graded. It also states that the plant is currently. evaluating options and a decision about what will be done will be made by December 15, 1987 at which time a revised relief request will be submitted.
4.
Relief Request PR-04 on Page 12 of the revised IST Program has been revised to state that the modifications required to j
install required instrumentation will be initiated by the i
end of 1987 and implemented by the end of 1988.
l S.
Pages 2, 18, 20, 21, and 22 of the Pump Table have been revised to add a lubricant level / pressure column and an information column.
l Page 9
.______a
.1 il'i i
j ENCLOSURE.2 Additional Changes Not Addressed In Enclosure 1 Page Number
-Description of Chances Made 4
Added RCIC pumps to Paragraph 2.1.7
]
since the RCIC system is not' safety related.
'l l
5 Deleted references to'the RCIC pumps q
l since the RCIC system is not safety related.
i 8
Deleted references to'the RCIC' pumps since~the RCIC system is not. safety related.
20 Deleted references'to the RCIC' pumps since the RCIC system'is not safety related.
21 Deleted references to the RCIC pumps since the RCIC' system is not safety related.
26 Replace the "L" test designation with-two tests;."LLRT"'.and "L-XI" to.
distinguish between two separates leak rate tests.
"LLRT"' refers to.the
'I 10CFR50, Appendix'J local leak rate tests and "L-XI" refers to the ASME Section XI leak tests.
The valves listed on Tables 1, 2,
and 3 of this AttachmentLrequired leak tests since they were part of-the.10CFR50; i
Appendix J testing program..On'May 12,-
j 1987, CP&L received interpretations of i
several requested Appendix J exemptions 1
from the NRC.
The' changes made result-y from these interpretations, i
The valves listed in Table 1'are i
connected.to sealed transmitters and are i
designed.to withstand the stresses of,a i
design basis loss of coolant accident' I
The instrument lines are exposed to' containment pressure'during Integrated
.j Leak Rate Tests (ILRTs).
Since the-Page 1
]
i
.j
ENCLOSURE 2 (Continued)
Pace Number Description of Chances Made valves are required.to be operable I
during normal operation, shutdownj and accidents in order to monitor critical parameters, the lines are considered an extension of the containment barrier.
Therefore, the instrument isolation valves do not require local leak rate testing to meet the intent of Appendix J.
Consequently, the leak test requirement has been removed from the submittal for these valves and the.
1 valves have been recategorized as "B"
valves.
Table 2 includes valves in the sample supply and return lines for the hydrogen / oxygen monitors.
These valves are designed to,open after a loss of coolant accidentito permit discharge of the containment atmosphere into the i
closed hydrogen / oxygen system outside of l
containment.
These sampling lines constitute an extension of the l
containment boundary and with these l
valves open, leakage outside the plant is prevented by the leak-tight nature of the monitoring system lines.
Assurance is provided that system piping will not leak by the performance of periodic ILRTs and soap bubble testing of the pipe joints.
Thus, the leak test requirement for these valves has been deleted from the submittal.
Table 3 constitutes valves that now receive a section XI leak test using water as the medium rather than an Appendix J air test.
This is due to the j
penetrations being located below the minimum torus drawdown level, and consequently, do not represent a potential atmospheric leak path.
33 Changed the second paragraph under l
ALTERNATE TESTING from "less than or 3
equal to 10 secsnds" to " greater than 2 seconds and less than or equal to 10 seconds."
Also change the third paragraph under ALTERNATE TESTING from I
j "less than 2 seconds" to "less than or equal to two seconds."
i Page 2 a
l
ENCLOSURE 2 (Continued)
.i Eace Number Description'of Chances Made 34 Added "Non Interruptable Instrument Air"~
and " Diesel-Generator' Starting Air" under SYSTEM.
40 Specifically addressed opening and closing of valves under TEST REQUIREMENT and ALTERNATE TEST.
44 Deleted. statement-under BASIS FOR RELIEF-that the test tank is required to be aligned to'the SLC. tank.:
62 Added Relief Request VR-27.
62a Added Relief Request VR-28-(also added references to Relief Request VR-28 on.
Pages 118, 122, 123,_125, 126, 131, 186, l
190, 191, 193, 194, and 199).
I 106 Deleted Valves 1-C11-SVF009A and l
1-C11-SVF009B since they provide
" signals for valve operation" and'are therefore exempt per IWV-1200.
108 Added Valve 1-B21-IV2149 to the Valve
'{
Table.
This. valve was added via a plant 1
modification, l
122 Valve 1-E11-F080A was added to the Valve Tables since it-is listed in the Technical Specifications as a containment isolation valve.
Setpoint testing (R) for relief valve Ell-FOSSA was deleted _from the program.
This valve was required for' heat-exchanger protection during steam l
condensing mode of RHR; this mode of RHR i
is no longer operational.-
l 124 Valve 1-E11-F060A was deleted since it is a manual valve and exempt'per IWV-1200.
1 125 Valve 1-E11-F080B was added since this valve is listed in the Technical Specifications as a containment:
isolation' valve.
Page 3
1 ENCLOSURE 2 (Continued)
I
'd Pace Number Description of Chances Made i
Setpoint testing (R)' for Valve
'1-E11-F055B was deleted.
This' valve.was j
required for heat exchanger protection.
j
.during steam condensing mode of RHR;-
-this mode of RHR is no longer.
q operational.
j 4
127 1 Valve 1-E11-F040 was added since?it is l
listed in the Technical Specifications as a containment isolation-valve.
Valve 1-E11-F060B was deleted since it is a' manual valve and exempt per IWV-1200.
)
i 132-Valve position indicator verification-
]
test (V) was deleted for Valves i
1-SW-V128, 1-SW-V129, 1-SW-V130 and.
j 1-SW-V131 since these valves do not have l
remote indication.
I Fail safe test (F) was added for Valves 1-SW-V136 and 1-SW-V137.
133 Valve 1-SW-V124 was added since this.
valve did not have an actuator when'the IST Program was first submitted.
The valve position indicator verification test (V) was deleted'for' Valves 1-SW-V123, 1-SW-V124, 1-SW-V125 j
and 1-SW-V126 since these valves do not have remote indication.
l Fail safe test - (F) was added for Valves 1-SW-V138 and 1-SW-V139.
151 The 10CFR50 Appendix J leakage test'was added for Valves 1-RNA-SV5251 and 1-RNA-SV5253 since it was' inadvertently omitted from the original submittal.
153 The valve position indicator verification test (V) was added for Valve 1-RXS-SV4192 since it was inadvertently omitted from the original
' submittal.
Page 4
I i
ENCLOSURE 2 (Continued) 1 l
Pace Number Description of Chances'Made l
.I i
156 Relief Valves 2-SW-RV4, 2-SW-RV5, 2-SW-RV6,.2-SW-RV9, 2-SW-RV10, and 1
2-SW-RV111were~ deleted.
These valves-are not required for system protection.
i 157 Relief valves 2-SW-RV7, 2-SW-RV8, 2-SW-RV12, and.2-SW-RV13 were deleted.
These. valves are not required for cystem protection.
1 168 Changed Valve Number 2-CAC-PV1209D to Ej 2-CAC-SV1209D, 2-CAC-PV1218C to 2-CAC-SV1218C, 2-CAC-PV1219B to 2-CAC-SV1219B, 2-CAC-PV1219C to 4
2-CAC-SV1219C, 2-CAC-PV1225C to 2-CAC-SV1225C, 2-CAC-PV4344'to 2-CAC-SV4344, and 2-CAC-PV4345 to' 2-CAC-SV4345. These valves were' changed from air operated valves to. solenoid valves.by plant modification.
)
i Valve 2-CAC-V22 was added since.it'was I
' inadvertently left out in the original-submittal.
173 Change valve'designationLfrom "C11" to "C12" since it was not' correct in the original submittal.
174 Valves 2-C11-SVF009A and 2-C11-SVF009B-since they provide signals for' valve operation and are therefore exempt per IWV-1200.
Changed valve designation for the valves on this page from "C11" to "C12" since it was not correct in the original submittal.
190 Valve 2-E11-F080A was added since-this valve is listed in the Technical Specifications ac a containment isolation valve.
1 Page 5
ENCLOSURE 2 (Continued)
Pace Number Description of Chances Made Setpoint testing (R) for relief valve 2-E11-F055A since this valve was required for heat exchanger protection-during steam condensing mode of RHR; this mode of RHR is no longer operational.
192 Valve 2-E11-F060A was deleted since it is a manual valve and therefore exempt per IWV-1200.
193 Valve 2-E11-F080B was added since it is in the Technical Specifications as a containment isolation valve.
Setpoint testing (R) was deleted for Valve 2-E11-F055 since it was required for heat exchanger protection during l
steam condensing mode of RHR; this mode of RHR is no longer operable.
l 195 Valve 2-E11-F040 was added since it is listed in the Technical Specifications l
as a containment isolation valve.
Valve 2-E11-F060B was deleted since it l
is a manual valve and is therefore i
exempt per IWV-1200.
200 Valve position indicator verification j
test (V) was deleted for Valves 2-SW-V128, 2-SW-V129, 2SW-V130, and 2-SW-V131 since they do not have remote indication.
Fail safe test (F) was added for Valves 2-SW-V136 and 2-SW-V137.
201 Valve position indicator verification test (V) was deleted for Valves 2-SW-V123, 2-SW-V124, 2SW-V125 and l
2-SW-V126 since these valves do not have remote indication.
Fail safe test (F) was added for Valves 2-SW-V138 and 2-SW-V139.
Page 6
ENCLOSURE 2 L (Continued) 1 l
Pace Number Description of Chances'Made-216
-Changed valve numbers from "2-CAC-PV..." to "2-CAC-SV..." since these valves were changed from air-operated valves to solenoid valves by plant modification.
217
-Changed valve' numbers from "2-CAC-PV..." to "2-CAC-SV..." since
.these valves were changed from air.
operated valves to solenoid valves by.
plant modification.
218 Changed valve numbers from "2-CAC-PV..." to "2-CAC-SV..." since.
these valves were changed from' air operated valves to solenoid valves by plant modification.
1 220 The 10CFR50 Appendix J leakage test was added'for Valves 2-RNA-SV5251 and 2-RNA-SV5253 since they were inadvertently-omitted in the original submittal.
221 Valve position indicator verification test (V) was added for Valve 2RXS-SV4192 since it was inadvertently omitted in the original submittal, i
I s
Page 7
l
' ENCLOSURE.2 (Continue'd)
Table 1 Pacos valve Numbers 100-1-CAC-SV-1209D 1-CAC-SV-1218C.
'l-CAC-SV-1219B 1-CAC-SV-1219C 1-CAC-SV-1225C-1-CAC-SV-4344 1-CAC-SV-4345 i
118-119 1-E41-SV1218D 1-E41-SV1219D 1-E41-SV1220D' 1-E41-SV1221D j
i 124 1-E11-SV-F03 7 A'
.j 1-E11-SV-F037C 1-E11-SV-F043A 1-E11-SV-F043C 128 1-E11-SV-F037B 1-E11-SV-F037D l
1-E11-SV-F043B 1-E11-SV-F043D
-168 2-CAC-SV1209D CAC-SV1218C 2-CAC-SV1219B 2-CAC-SV1219C 2-CAC-SV1225C 2-CAC-SV4344 2-CAC-SV4345 4
186-187 2-E41-SV1218D
[
2-E41-SV1219D 2-E41-SV1220D 2-E41-SV1221D 192 2-E11-SV-F037A 2-E11-SV-F037C 2-E11-SV-F043A 2-E11-SV-F043C Page 8
m
- l l
i ENCLOSURE: 2. (Continued)?
Table 1 Pages Valve Numbers i
']
196 2-E11-SV-F037B 2-E11-SV-F037D~
~'
2-E11-SV-F043B.
2-E11-SV-F043D-1 J
j I
l t
I Page 9 h
ENCLOSURE 2;(Continued);
l 4
TABLE'2' Page Valve Numbers H
148 1-CAC-SV1218A1 1-CAC-SV1227A 1-CAC-SV1227B.
1-CAC-SV1227C, 1-CAC-SV1231B-1-CAC-SV4410-1 1-CAC-SV4410-2 1
.1-CAC-SV4410-3 1-CAC-SV4410-4 1-CAC-SV4541-1 i
1 149
- 1-CAC-SV1205E 1-CAC-SV1209A~
'l-CAC-SV1209B 1-CAC-SV1213A
'l-CAC-SV1215E 1-CAC-SV4409-1 1-CAC-SV4409-2 CAC-SV4409-3 1-CAC-SV4409-4 1-CAC-SV4540-J 217 2-CAC-SV1218A-2-CAC-SV1227A :
2-CAC-SV1227B-2-CAC-SV1227C.
2-CAC-SV1231B
'2-CAC-SV4410-1 2-CAC-SV4410 2-CAC-SV4410 2-CAC-SV4410-4 2-CAC-SV45411 218 2-CAC-SV1205E 2-CAC-SV1209A 2-CAC-SV1209B 2-CAC-SV1213A 2-CAC-SV1215E 2-CAC-SV4409-1 2-CAC-SV4409-2 2-CAC-SV4409-3 2-CAC-SV4409-4 2-CAC-SV4540 Page'10 1.
'; i ENCLOSURE 2 ' (Continued)'
TABLE 3 Paces
' Valve Numbers.
117
-l-E41-F012 118 1-E41-F021 1-E41-F022 1-E41-F040 1-E41-F042-I 1-E41-F049 g
]
120 1-E21-F001B 1-E21-F015B'
~a 1-E21-F031B l
l l
l 121 1-E21-F001A l
1-E21-F015A 1-E21-F031A.
I l
122 1-E21-F011A' 1-E21-F025A 1-E21-F055A I
1-E21-F103A 1-E21-V20 123-124 1-E11-F007A 1-E11-F020A 1-E11-F029 3
i'l 125 1-E11-F011B-1-E11-F025B 4
1-E11-F055B.
I 1-E11-F103B i
1-E11-F097 l
1-E11-V21 J
126 1-E11-F007B 1-E11-F020B 131 1-E51-F001 1-E51-F002 j
1-E51-F019 1-E51-F028 1-E51-F031 i
'l-E51-F040-140 1-TD-V2-Page 11
~.]
i;j ENCLOSURE 2 (Continued)-
TABLE 3 i
Pages Valve Numbers
.1 185 2-E41-F012-R l
186 2-E41-F021~
.2-E41-F022-l 2-E41-F040 2-E41aF042.
2-E41-F049
)
i q
188 2-E21-F001B
'l 2-E21-F015B.
.2-E21-F031B'
.j
.)
189 2-E21-F001A 2-E21-F015A-L1 2-E21-F031A l
1 1
190 2-E21-F011A
]
2-E21-F025A 2-E21-F055A.
2-E21-F103A E21-V20 l
u 191-192 2-E11-F007A-2-E11-F020A--
2-E11-F029 l
i 193 2-E11-F011B 2-E11-F025B 2-E11-F055B 2-E11-F103B 2-E11-F097 2-E11-V21 1
194 2-E11-F007B 2-E11-F020B i
i l
199 2-E51-F001 d
2-E51-F002
.j 2-E51-F019 2-E51-F028 2-E51-F031 2-E51-F040 l
o
.l Page 12 j
i ENCLOSURE 2 (Continued)
TABLE 3 Paces Valve Numbers 209 2-TD-V2 l
4
\\
l l
)
l l
l 1
1 l
l I
1 1
i I
Page 13 l
g i
l 4
ENCLOSURE 3 REVISED IST PROGRAM i
f i