ML20080B352
| ML20080B352 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 01/17/1984 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19264F078 | List: |
| References | |
| NUDOCS 8402070071 | |
| Download: ML20080B352 (5) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION 5
.t WASH NGTON, D. C. 20555
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COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-373 LA SALLE COUNTY STATION, UNIT I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.15 License No. NPF-11 1.
The Nuclear Regulatory Comission (the Comission or the NRC) having found that:
A.
The applic6 tion for amendment filed by the Comonwealth Edison Company, dated January 4,1984, 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 operate in confonnity 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 endangering the health and safety of'the public, and (ii) that such activities will be conducted in ccmpliance with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance.with-10.CFR Part SL__
of the Comission's regulations and all applicable reouirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Op.erating License No. NPF-11 is heret,y amended to read as follows:
(2) Technical Specifications and Environinental Protection Plan The Technical Specifications contained in Appercix A, as revised through Amendment No.15, and the E'nv'ir'enmental 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 Plar..
s402070071 840117 DR ADOCK 05000
m 3.
This amendment was effective as of January 4, 1984.
FOR THE NUCLEAR REGULATORY COMMISSION OTI inaiSI ng E
A. Schwencer, Ch f Licensing Branch No. 2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: January 17, 1984 Qi) 5
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ATTACHMENT TO LICENSE AMENDMENT NO.15 FACILITY OPERATING LICENSE NO. NP M 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 vertical lines indicating the area of change.
REMOVE INSERT 3/4 1-4 3/4 1-4 3/4 1-11 3/4 1-11 4
6
- n.*
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~ REACTIVITY CONTROL SYSTEM LIMITING CONDITION FOR OPERATION-(Continued)
ACTION (Continued) 2.
If the inoperable control rod (s) is inserted:
a)
Within one hour disarm the associated directional control valves ** either:
1)
Electrically, or
.2)
Hydraulically by closing the drive water and exhaust water isolation valves.
b)
Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
3.
The provisions of Specification 3.0.4 are not applicable.
t c.
With more than 8 control rods inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The scram discharge volume drain and vent valves shall be demonstrated OPERABLE by:
a.
At least once per 31 days verifying each valve to be open*, and b.
At least once per 92 days cycling each valve through at least one complete cycle of full travel.
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4.1.3.1.'2 When above the low power setpoint of the RWM and RSCS, all withdrawn control rods not required to have their directional control valves disarmed electricalTy or hydraulically shall be demonstrated OPERABLE by moving each control rod at least one notch, a.
At least once per 7 days, and b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when ary cdntrol rod is immovable as a result of excessive friction or mechanical interference.
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l 4.1.3.1.3 All control rads shall be demonstrated OPERABLE by perf_ormance of L
Surveillance Requirements 4.1.3.2, 4.1.3.4,.4.1.3.5, 4.1.3.6 and 4.1.3.7.
j "These valves may be closed intermittently for testing under administrative control.
- May be rearmed intermittently, under administrative control, to permit testing associated with restoring the control rod to OPERABLE status.
l LA SALLE - UNIT 1 3/4 1-4 L
8xataLng 15
REACTIVITY CONTROL SYSTEM CONTROL ROD DRIVE COUPLING LIMITING CONDITION FOR OPERATION 3.1.3.6' All control rods shall be coupled to their drive mechanisms.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2 and 5*.
ACTION; a.
In OPERATIONAL CONDITION 1 and 2 with one control rod not coupled to its associated drive mechanism:
1.
Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, either:
a)
If permitted by the NWM and RSCS, insert the control rod drive mechanism to accomplish recoupling and verify recoupling by withdrawing the control rod, and:
1)
Observing any indicated response of the nuclear instrumentation, and 2)
Demonstrating that the control rod will not go to the overtravel position.
b)
If recoupling is not accomplisned on the first attempt or, if not permitted by the RWM or RSCS then until permitted
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by the RWM and RSCS, declare the control rod inoperable and insert the control rod and disarm the associated
. directional control valves ** either:
1)
Electrically, or 2)
Hydraulically by closing the drive water and exhaust L
water isolation valves.
2.
Otherwise, be in at least HOT SHUTDOWN within the'next 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s-s l
b.
In OPERATIONAL CONDITION 5* with a withdrawn control rod not coupled
(
to its associated drive mechanism, within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, either:
1.
Insert the control rod to accomplish recoupling and verify i
l recoupling by withdrawing the control rcd and demonstrating that the control rod will nct go to the overtravel position, or 2.
If recoupling is not accomplished, insert the control rod w
y anddisarmtheassociateddirecti[onalcontrolvalves**either:
l%g a)
Electrically, or i
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b)
Hydraulically by closing thd dri've water and exhaust water l.
isolation valves.
c.
The provisions of Specification 3.0., are not applicable.
l "At least each withdrawn control rod.
Not applicable to control rods removed per Specification 3.9.-10.1 or 3.9.10.2.
- May be rearmed intermittently, under administrative control. to permit testing associated with restoring the control rod to OPERABLE status.
LA SALLE - UNIT 1 3/4 1-11 Amendment No.15
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