ML20209D080
| ML20209D080 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 08/29/1986 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20209D084 | List: |
| References | |
| NUDOCS 8609090192 | |
| Download: ML20209D080 (11) | |
Text
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y'o UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20555
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-374 LA SALLE COUNTY STATION, UNIT 2 1
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 25 License No. NPF-18 1.
The Nuclear Regulatory Commission (the Comission or the NRC) having found that:
A.
The application for amendment filed by the Commonwealth Edison Company (thelicensee),datedJune 11, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; R.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endanoerino the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the Dublic; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-18 is hereby amended i.o read as follows:
(2) Technical Specificatirans and Environmental Protection Plan l
The Technical Specifications contained in Appendix A, as revised through Amendment No. 25, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8609090192 860829 PDR ADOCK 05000374 P
2-3.
This amendment is effective upon startup following the first refueling.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Director BVP Project Directorate No. 3 Division of BWR licensing
Enclosure:
Channes to the Technical Specifications Date of Issuance: August 29, 1986 I
l
ENCLOSURE TO LICENSE AMENDMENT NO. 25 FACILITY OPERATING LICENSE NO. NPF-18 DOCKET NO. 50-374 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed paces. The revised pages are identified by Amendment number and contain a vertical line indicating the area of chanoe.
REMOVE INSERT 3/4 6-18 3/4 6-18 3/4 6-28 3/4 6-28 3/4 6-37 3/4 6-37 3/4 8-27 3/4 8-27 3/4 8-28 3/4 8-28 3/4 8-29 3/4 8-29 3/4 8-30 3/4 8-30 R 3/4 6-2 8 3/4 6-2 m
l CONTAINMENT SYSTEMS DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.8 The drywell and suppression chamber purge system may be in operation with the drywell and/or suppression chamber purge supply and exhaust butterfly isolation valves open for inerting, deinerting, and pressure control.
Purging l
through the Standby Gas Treatment System shall be restricted to less than or equal to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per 365 days.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
With a drywell and/or suppression chamber purge supply and/or exhaust butterfly isolation valve open for other than inerting, deinerting, or pressure control, g
close the butterfly valve (s) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT SHUTDOWN with-in the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS I
4.6.1.8.1 The cumulative time that the drywell and suppression chamber purge a
system has been in operation purging through the Standby Gas Treatment System shall be verified to be less than or equal to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per 365 days prior to use in this mode of operation.
LA SALLE - UNIT 2 3/4 6-18 Amendment No. 25
TABLE 3.6.3-1 (Continued) 5 PRIMARY CONTAINMENT ISOLATION VALVES s
~
p MAXIMUM ISOLATION TIME VALVE FUNCTION AND NUMBER VALVE GROUP (a)
(Seconds)
EZ Automatic Isolation Valves (Continued) ro 8.
Containment Vent and Purge Valves 4
2VQO26
< 10 2VQ027 7 10 2VQO29 7 10 2VQO30 7 10 2VQO31 7 10 2VQ032 7 5 2VQ034 7 10 l
2VQ035 7 5 R
2VQ036 7 10 2VQ040 7 10 T
2VQ042 7 10 y
2VQ043
$10 2VQ047
< 5 2VQ048 7 5 2VQ050 7 5 2VQ051 7 5 2VQ068 7 5 9.
RCIC Turbine Exhaust Vacuum Breaker 9
H.A.
Line Valves 2E51-F080 2E51-F086 10.
LPCS, HPCS, RCIC, RHR Injection Testable Check Bypass Valves (9)
N.A.
N.A.
E Ba a
F
TABLE 3.6.3-1 (Continued) b PRIMARY CONTAINMENT ISOLATION VALVES 1
v, i
VALVE FUNCTION AND NUMBER I
E Other Isolation Valves (Continued) i i
7.
Post LOCA Hydrogen Control c-zZ 2HG001A, B 2HG002A, B 3
m 2HG005A, B l
2HG006A, B 8.
Standby Liquid Control System 2C41-F004A, B 2C41-F007 j
9.
Reactor Recirculation Seal Injection l
2B33-F013A,B(I)
W w
j 1
2833-F017A, B T
10.
Drywell Pneumatic Valves U
21N018 TABLE NOTATIONS
- But > 3 seconds.
g (a) See 5pecification 3.3.2, Table 3.3.2-1, for isolation signal (s) that operates each valve group.
(b) Not included in total sum of Type B and C tests.
(c) May be opened on an intermittent basis under administrative control.
(d) Not closed by SLCS actuation.
(e) Not closed by Trip Functions' Sa, b, or c, Specification 3.3.2, Table 3.3.2-1.
(f) Not closed by Trip Functions 4a, c, d, e, or f of Specification 3.3.2, Table 3.3.2-1.
l (g) Not subject to Type C leakage test.
(h) Opens on an isolation signal.
Valves will be open during Type A test.
No Type C test required.
(i) Also closed by drywell pressure-high signal.
y (j) Hydraulic leak test at 43.6 psig.
(k) Not subject to Type C leakage test - leakage rate tested per Specification 4.4.3.2.2.
S-(1) These penetrations are provided with removable spools outboard of the outboard isolation valve.
During operation, these lines will be blind flanged using a double 0-ring and a type B leak test.
In addition, the packing of these isolation valves will be soap-bubble tested to ensure y
insignificant or no leakage at the containment test pressure each refueling outage.
52.oN tnemdnemA 72-8 4/3 2 TINU - ELLASAL suounitnoC B560F - 1282 metsys retawdeef niaM suounitnoC A560F - 12B2
.f suounitnoC 370F - 1282 suounitnoC 270F - 12B2 suounitnoC 170F - 12B2 suounitnoC 960F - 12B2 suounitnoC 070F - 1282 suounitnoC 860F - 1282 suounitnoC 020F - 12B2 snoitidnoC tnediccA 610F - 12B2 snoitidnoC tnediccA 910F - 12B2 snoitidnoC tnediccA D760F - 12B2 snoitidnoC tnediccA C760F - 12B2 snoitidnoC tnediccA 8760F - 12B2 metsys maets niaM snoitidnoC tnediccA A760F - 12B2
.e snoitidnoC tnediccA 920RW2 snoitidnoC tnediccA 040RW2 snoitidnoC tnediccA 081RW2 metsys WCCBR snoitidnoC tnediccA 971RW2
.d I
snoitidnoC tnediccA 73OQV2 snoitidnoC tnediccA 860QV2 snoitidnoC tnediccA 150QV2 snoitidnoC tnediccA 050QV2 snoitidnoC tnediccA 840QV2 i
snoitidnoC tnediccA 740QV2 l
snoitidnoC tnediccA 53OQV2 metsys egrup dna tnev snoitidnoC tnediccA 23OQV2 tnemniatnoc yramirP snoitidnoC tnediccA 83OQV2
.c I
snoitidnoC tnediccA B360PV2 snoitidnoC tnediccA A360PV2 snoitidnoC tnediccA B350PV2 snoitid. roc tnediccA A350PV2 snoitidnoC tnediccA B411PV2 snoitidnoC tnediccA A411PV2 srelooc retaw dellihc snoitidnoC tnediccA B311PV2 tnemniatnoc yramirP snoitidnoC tnediccA A311PV2
.b snoitidnoC tnediccA 300GV2 snoitidnoC tnediccA 100GV2 snoitidnoC tnediccA 300GVI STGBS snoitidnoC tnediccA 100GVI
.a DETCEFFA
)snoitidnoC tnediccA()suounitnoC(
REBMUN EVLAV
)S(METSYS ECIVED SSAPYB NOITCETORP DAOLREVO LAMREHT SEVLAV DETAREPO ROTOM 1-3 3 8 3 ELBAT
TABLE 3.8.3.3-1 (Continued)
MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS DEVICE SYSTEM (S)
VALVE NUMBER (Continuous)(Accident Conditions)
AFFECTED g.
2E21 - F001 Continuous LPCS system 2E21 - F005 Accident Conditions 2E21 - F011 Accident Conditions 2E21 - F012 Accident Conditions i
h.
2C41 - F001A Accident Conditions SBLCS 2C41 - F001B Accident Conditions 1.
2G33 - F001 Accident Conditions RWCU 2G33 - F004 Accident Conditions j.
2E12 - F052A Accident Conditions RHR system 2E12 - F064A Accident Conditions 2E12 - F087A Accident Conditions 2E12 - F004A Continuous 2E12 - F047A Continuous 2E12 - F048A Accident Conditions 2E12 - F003A Continuous 2E12 - F026A Accident Conditions 2E12 - F068A Continuous 2E12 - F073A Continuous 2E12 - F074A Continuous 2E12 - F011A Accident Conditions 2E12 - F024A Accident Conditions 2E12 - F016A Accident Conditions 2E12 - F017A Accident Conditions 2E12 - F027A Accident Conditions 2E12 - F004B Continuous 2E12 - F047B Continuous 2E12 - F048B Accident Conditions 2E12 - F003B Continuous 2E12 - F068B Continuous 2E12 - F073B Continuous 2E12 - F074B Continuous 2E12 - F026B Accident Conditions 2E12 - F011B Accident Conditions j.
2E12 - F024B Accident Conditions RHR system 2E12 - F006B Continuous 2E12 - F016B Accident Conditions 2E12 - F017B Accident Conditions 2E12 - F042B Accident Conditions 2E12 - F064B Accident Conditions 2E12 - F093 Continuous 2E12 - F021 Accident Conditions 2E12 - F004C Continuous 2E12 - F052B Accident Conditions 2E12 - F087B Accident Conditions LASALLE - UNIT 2 3/4 8-28 Amendment No. 25 7
_ _ -,. - - - _ - _ _ _, - _ _ _ _ _ ~. _ -. _ _. _.
TABLE 3.8.3.3-1 (Continued)
MOTOR OPERATED VALVES THERMAL OVERLOAD PROTEGIION BYPASS DEVICE SYSTEM (S)
VALVE N' MBER (Contir.uous)(Accident Conditions)
AFFECTED J
2E12 - F099B Accident Conditions 2E12 - F099A Accident Conditions 2E12 - F008 Accident Conditions 2E12 - F009 Accident Conditions 2E12 - F040A Accident Conditions 2E12 - F040B Accident Conditions 2E12 - F049A Accident Conditions i
2E12 - F049B Accident Conditions 2E12 - F053A Accident Conditions 2E12 - F053B Accident Conditions 2E12 - F006A Continuous 2E12 - F023 Accident Conditions 2E12 - F027B Accident Conditions 2E12 - F042A Accident Conditions 2E12 - F042C Accident Conditions l
2E12 - F064C Accident Conditions 2E12 - F094 Continuous k.
2E51 - F086 Accident Conditions RCIC system 2E51 - F022 Accident Conditions 2E51 - F068 Continuous 2E51 - F069 Continuous i
2E51 - F080 Accident Conditions 2E51 - F046 Accident Conditions 2E51 - F059 Accident Conditions 2E51 - F063 Accident Conditions 2E51 - F019 Accident Conditions 2E51 - F031 Continuous 1
2E51 - F045 Accident Conditions 2E51 - F008 Accident Conditions i
2E51 - F010 Accident Conditions 2E51 - F013 Accident Conditions 2E51 - F064 Accident Conditions 2E51 - F076 Accident Conditions 1.
2E32 - F001A Accident Conditions MSIV-LCS l
2E32 - F002A Accident Conditions 2E32 - F003A Accident Conditions 2E32 - F001E Accident Conditions 2E32 - F002E Accident Conditions 2E32 - F003E Accident Conditions 2E32 - F001J Accident Conditions 2E32 - F002J Accident Conditions 2E32 - F003J Accident Conditions 2E32 - F001N Accident Conditions 2E32 - F002N Accident Conditions LASALLE - UNIT 2 3/4 8-29 Amendment No. 25 I
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TABLE 3.8.3.3-1 (Continued)
MOTOR OPERATED VALVES THERMAL OVERLOAD PR0ltCIION BYPASS DEVICE SYSTEM (S)
VALVE NUMBER (Continuous)(Accident Conditions)
AFFECTED 2E32 - F003N Accident Conditions 2E32 - F006 Accident Conditions 2E32 - F007 Accident Conditions 2E32 - F008 Accident Conditions 2E32 - F009 Accident Conditions m.
2E22 - F001 Accident Conditions HPCS system 2E22 - F004 Accident Conditions 2E22 - F010 Accident Conditions 2E22 - F011 Accident Conditions 2E22 - F012 Accident Conditions 2E22 - F015 Accident Conditions 2E22 - F023 Accident Conditions 4
l 1
)
.i l
I LASALLE - UNIT 2 3/4 8-30 Amendment No. 25 1
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CONTAINMENT SYSTEMS BASES 3/4.6.1.5 PRIMARY CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the facility.
Structural integrity is required to ensure that the containment will withstand the maximum pressure of 45 psig in the event of a LOCA.
The measurement of containment tendon lift-off force, the tensile tests of the tendon wires or strands, the visual examination of tendons, anchorages and exposed interior and exterior surfaces of the containment, the chemical and visual examination of the sheathing filler grease, and the Type A leakage test are sufficient to demonstrate this capability.
The surveillance requirements for demonstrating the primary containment's structural integrity and the method of predicting the prestress losses are in compliance with the recommendations of Regulatory Guide 1.35, " Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containment Structures,"
January 1976, and proposed Regulatory Guide 1.35.1, " Determining Prestressing Forces for Inspection of Prestressed Concrete Containment Structures," April 1979 with the following clarification:
the tested lift-off force of individual tendon tension shall be greater than or equal to the initial prestress minus the losses, as predicted in the as-built design, which occur between the initial pre-operational structural integrity test and the time of subsequent surveillance.
The required Special Reports from any engineering evaluation of contair,-
ment abnormalities shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedure, the tolerances on cracking, the results of the engineering evalua-tion, and the corrective action taken.
3/4.6.1.6 DRYWELL AND SUPPRESSION CHAMBER INTERNAL PRESSURE I
The limitations on drywell and suppression chamber internal pressure ensure that the containment peak pressure of 39.6 psig does not exceed the design pressure of 45 psig during LOCA conditions or that the external pres-sure differential does not exceed the design maximum external pressure differen-tial of 5 psid.
The limit of 2.0 psig for initial positive primary containment pressure will limit the total pressure to 39.6 psig which is less than the design pressure and is consistent with the safety analysis.
3/4.6.1.7 DRYWELL AVERAGE AIR TEMPERATURE The limitation on drywell average air temperature ensures that the containment peak air temperature does not exceed the design temperature of 340'F during LOCA conditions and is consistent with the safety analysis.
3/4.6.1.8 DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM The drywell and suppression chamber purge supply and exhaust isolation l
valves are required to be closed during plant operation except as required for inerting, de-inerting and pressure control. These valves have been 2
demonstrated capable of closing during a LOCA or steam line break accident i
from the full open position, g
LA SALLE UNIT 2 B 3/4 6-2 Amendment No. 25
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