ML20199G171
| ML20199G171 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 04/02/1986 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20199G176 | List: |
| References | |
| NUDOCS 8604090080 | |
| Download: ML20199G171 (8) | |
Text
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COMHONWEALTH EDISON COMPANY
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D0CKET NO. 50-373 tA SALLE COUNTY $TATION, UNIT 1 AMENDNENT TO FACILITY OPERATING LICENSE Amendment No. 37 License No. NPF-11 i
1.
The. Nuclear Regulatory Comission (the Comission or the NRC) having found that:
A.
The application for amendment filed by the Comonwealth Edison Company (the licensee) dated October 2,1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B.
The facility will cperate in conformity with the application, the provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance:
(i) that the activities authorized by thic atenchnent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not he inimical to the ccer.on defense and se:urity or to the health and safety of the public; and E,
The itsuance of this smendinent is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satitfied, 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attactment to this licecse amendment and paragraph 2.C(2) of Facility Operating License No. NPF-11 is hereby amended to read as follows:
(2), Technical Specificatior.s and Environmental Protection Plan The Tec;hnical Specificatfors contained in Appendix A, as revised through Amendment No. 37, and the Environmental Protection Plan contained in Appendix S, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
0604090080 860402,
DR ADOCK 0300
2-3.
This amendment is effective upon startup following the first refueling.
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FOR THE NUCLEAR REGULATORY COMMISSION
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Elinor G. Adensam, Qirector BWR Project Directorate No. 3 Division of BWR Licensing
Enclosure:
Changes to the Technical Specifications Date of Issuance: An
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ENCLOSURE TO LICENSE AMENDMENT NO. 37 FACILITY OPERATING LICENSE NO. NPF-11 DOCKET NO. 50-373 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
REMOVE INSERT 3/4 6-15 3/4 6-15 3/4 6-25 3/4 6-25 3/4 6-34 3/4 6-34 3/4 8-27 3/4 8-27 8 3/4 6-2 8 3/4 6-2
CONTAINMENT SYSTEMS DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM
- i LIMITING CONDITION FOR OPERATION' 3.6.1.8 The drywell and suppression chamber perge system may be in operation j
with the drywell and/or suppression chamber purge supply and exhaust butterfly isolation valves open for inerting, de-inerting and pressure control.
Purging 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, de-inerting or pressure control, close the butterfly valve (s) within one hour or be in at least HOT SHUTDOWN l
within 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 4.6.1.8.1 The cumulative time that the drywell and suppression chamber purge 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 t'o use in this mode of operation.
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LA SALLE - UNIT 1 3/4 6-15 Amendment No. 37 l
g TABLE 3.6.3-1 (Continued) l PRIMARY CONTAINMENT' ISOLATION VALVES t-MAXIMUM i
ISOLATION TIME E
VALVE FUNCTION AND NUMBER VALVE GROUP (a)
(Seconds)
U Automatic Isolation Valves (Continued) s 8.
Containment Vent and Purge Valves 4
IVQO26
< 10 IVQO27 7 10 1VQO29 7 10 1VQ030 7 10 IVQ031 7 10 IVQ032 75 1VQO34 7 10 l
R IVQ035 75 IVQ036 7 10 i
IVQ040 7 10 ij IVQ042 7 10 1VQ043 7 10 IVQ047 75 IVQ048 55 IVQ050 55 IVQ051 5 5 IVQ068
<5 9.
RCIC Turbine Exhaust Vacuum Breaker 9
N.A.
Line Valves IE51-F080 1E51-F086 10.
LPCS, HPCS, RCIC, RHR Injection Testable Check Bypass Valves M. A.-
N.A.
a.
c
TABLE 3.6.3-1 (C:ntinued)
PRIMARY CONTAINMENT ISOLATION VALVES
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VALVE FUNCTION AND NUMBER Other Isolation Valves (Continued)
E 7.
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1HG001A, B 1HG002A, B 1HG005A, B 1HG006A, B 8.
Standby Liquid Control System IC41-F004A, B 1C41-F007 9.
Reactor Recirculation Seal Injection ***
IS) 1833-F013A, B w
fd) 1 1833-F017A, B i
10.
Drywell Pneumatic System W
IIN018 But > 3 seconds.
(a) See 3pecification 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.
(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.
I (j) Hydraulic leak test at 43.6 psig.
(k) Not subject to Type C leakage test - leakage rate tested per Specif! cat. ion 4.4.3.2.2, (1) These penetrations.are provided with removable spools outboard of the outboard isolation valve.
U 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 E
insignificant or no leakage at the containment test pressure each refueling outage.
(
The specified 18-month interval may be waived for Cycle 1 provided the surveillance is performed during Refuel 1, which is to commence no later than October 27, 1985.
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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 pre-stress loses are in compliance with the recommendations of Regulatory Guide 1.35.1, " 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 De greater than or equal to the initial pre-stress minus the loses, as predicted in the as-built design, which occur between thc. initial pre-operational structural ' integrity test and the time of subsequent surveillance.
The required Special Reports from any engineering evaluation or contain-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 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 accident 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 accident analysis.
3/4.6.1.8 DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM The drywell and suppression chamoer purge supply and exhaust isolation valves are required to be closed during plant operation except as required for inerting, de-inerting and pressure control.
These valves have been demonstrated capable of closing during a LOCA or steam line break accident from the full open position.
LA SALLE UNIT 1 B 3/4 6-2 Amendment No. 37