ML20055A838
| ML20055A838 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 07/09/1982 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20055A839 | List: |
| References | |
| NUDOCS 8207200033 | |
| Download: ML20055A838 (7) | |
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COMMONWEALTif EDISON COMPANY s
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AMENLHENT TO FACILITY OPERATING LICENSE ~>
x License No. NPF-11 m
s Amendment No. 2
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1.
The Nuclear Regulatory Commission ~(the Commission or the NRC) having foundi,
that:
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A.
The application for amendment by the Commonwealth Edison Company, dated June 14, 1982 and July 2,'41982, complies with the standards and requirenents;of the Atcaic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR i
Chapter I;
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B.
The f acility will operate in conformity with the application, the provisions of the Act, and the reculations of the Commission;
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C.
There is reasonable assuranc'e:
(1) that the activities authorized
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by this amendaent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance 6f this. amendment will not be inimical to'the comm6' defense and sei:urity ordo the health and safety of the ~public; and
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The issuance of this amendment is in accordance with 10 CFR Part 51.
w of the Commission's reculations and all ' applicable requirements
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2.
Accordingly, the license fea' ended by changet to the Technical'Specf ficattiinD "~h as indicated in the attachmett to this license lamendnent and paragraph 2.C.(2) of the Facility Operating License'No,'NPF-11 is hereby amendid'v to read as follows:
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(2) Technical Specificati6ns
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The Technical Specifications contained in Appendices A.and.B. as' ~
3.
revised through Amendment No. 2, are hereby incorporitedsin the v
license. The licensee shall operate the facility in accordance with the Technical Specifications.
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This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Original signed by:
A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing Attachments:
Changes to the Technical Specifications Date of issuance: JUL &
1382 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 2 FACILITY OPERATING LICENSE NO. NPF-11 DOCKET NO. 50-373 Replace the followinq 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 3-53 3/4 3-53 3/4 3-72 3/4 3-72 3/4 9-4 3/4 9-4 3/4 4-8 3/4 4-8 OFFICE h cuauur)
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TABLE 3.3.6-2 2>
g CONTROL R0D WITHDRAWAL BLOCK INSTRUMENTATION SETPOINTS y
m TRIP FUNCTION TRIP SETPOINT ALLOWABLE VALUE 1.
R0D BLOCK MONITOR 5
a.
Upscale
< 0.66 W + 40%
< 0.66 W + 43%
b.
Inoperative NA NA c.
Downscale
> 5% of RATED THERMAL POWER
> 3% of RATED THERMAL POWER 2.
APRM a.
Flow Biased Simulated Thermal Power-Upscale 5 0.66 W + 42%*
5 0.66 W + 45%
- b.
Inoperative NA NA c.
Downscale
> 5% of RATED THERMAL POWER
> 3% of RATED THERMAL POWER d.
Neutron Flux-High 312%ofRATEDTHERMALPOWER 314%ofRATEDTHERMALPOWER 3.
SOURCE RANGE MONITORS R
a.
Detector not full in NA NA 5
5 b.
Upscale
< 2 x 10 cps
< 5 x 10 cps T
c.
Inoperative NA NA d.
Downscale
> 0.7 cps
> 0.5 cps l
4.
INTERMEDIATE RANGE MONITORS a.
Detector not full in NA NA b.
Upscale
< 108/125 of full scale
< 110/125 of full scale
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c.
Inoperative NA NA d.
Downscale
> 5/1250f full scale
> 3/125 of full scale 5.
Water Level-High 5 765' 5\\"
1 765' Sk" b.
Scram Discharge Volume Switch in Bypass NA NA Ng 6.
REACTOR COOLANT SYSTEM RECIRCULATION FLOW k
a.
Upscale
$ 108/125 of full scale 5 111/125 of full scale s
b.
Inoperative NA 5 11% flow deviation NA
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c.
Comparator
$ 10% flow deviation O
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- The Average Power Range Monitor rod block function is varied as a function of recirculation loop flow (W).
The trip setting of this function must be maintained in accordance with Specification 3.2.2.
INSTRUMENTATION SOURCE RANGE MONITORS
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LIMITING CONDITION FOR OPERATION 3.3.7.6 At least three source range monitor channels shall be OPERABLE.
APPLICABILITY:
OPERATIONAL CONDITIONS 2*, 3 and 4.
ACTION:
a.
In OPERATIONAL CONDITION 2* with one of the above required source range monitor channels inoperable, restore at least 3 source range monitor channels to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or 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 />.
b.
In OPERATIONAL CONDITION 3 or 4 with two or more of the above required source range monitor channels inoperable, verify all insertable control rods to be inserted in the core and lock the reactor mode switch in the Shutdown position within one hour.
SURVEILLANCE REQUIREMENTS 4.3.7.6 Each of the above required source range monitor channels shall be demonstrated OPERABLE by:
a.
Performance of a:
1.
CHANNEL CHECK at least once per:
a) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in CONDITION 2*, and b) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in CONDITION 3 or 4.
2.
CHANNEL CALIBRATION ** at least once per 18 months.
b.
Performance of a CHANNEL FUNCTIONAL TEST:
1.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to moving the reactor mode switch from the Shutdown position, if not performed within the previous 7 days, and 2.
At least once per 31 days.
c.
Verifying, prior to withdrawal of control rods, that the SRM count rate is at least 0.7 cps with the detector fully inserted.
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- With IRM's on range 2 or below.
- Neutron detectors may be excluded from CHANNEL CALIBRATION.
LA SALLE - UNIT 1 3/4 3-72 Amendment No. 2
REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) b.
Performance of a CHANNEL FUNCTIONAL TEST:
1.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the start of CORE ALTERATIONS, and 2.
At least once per 7 days.
c.
Verifying that the channel count rate is at least 0.7 cps:
l 1.
Prior to control rod withdrawal, 2.
Prior to and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during CORE ALTERATIONS, and 3.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
d.
Verifying that the RPS circuitry " shorting links" have been removed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to and at least'once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during:
1.
The time any control rod is withdrawn,## or 2.
Shutdown margin demonstrations.
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- Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.
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LA SALLE - UNIT 1 3/4 9-4 Amendment No. 2 l
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.3.2.2 Each reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1 shall be demonstrated OPERABLE:
a.
Pursuant to Specification 4.0.5, except that in lieu of any leakage testing required by Specification 4.0.5, each valve shall be demonstrated OPERABLE by verifying leakage to be within its limit:
1.
At least once per 18 months, and 2.
Prior to returring the valve to service following maintenance, repair or replacement work on the valve which could affect its leakage rate.
In addition, until the LPCS system and the LPCI system injection valve differential pressure-low permissive is modified during or before the first refueling cutage, the LPCS system check valve 1E21-F006 and the LPCI system check valves 1E12-F041 A, B, and C shall also be demonstrated OPERABLE by verifying leakage to be within its limit:
1.
Whenever the unit has been in COLD SHUTDOWN or REFUELING, after the last valve disturbance prior to reactor coolant system temperature exceeding 200*F 2.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following valve disturbance except when in COLD SHUTDOWN or REFUELING.
The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 3.
b.
By demonstrating OPERABILITY of the high/ low pressure interface valve leakage pressure monitors by performance of a:
1.
CHANNEL FUNCTIONAL TEST at least once per 31 days, and 2.
CHANNEL CALIBRATION at least once per 18 months, With the alarm setpoint for the:
1.
HPCS system i 100 psig.
2.
LPCS system 1 500 psig.
3.
LPCI/ shutdown cooling system 5 400 psig.
4.
RHR shutdown cooling i 190 psig.
5.
RCIC 1 90 psig.
l LA SALLE - UNIT 1 3/4 4-8 Amendment No. 2
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