ML20210P213
| ML20210P213 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 02/03/1987 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210P217 | List: |
| References | |
| NUDOCS 8702130333 | |
| Download: ML20210P213 (7) | |
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g UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20086 COMMONWEALTH EDISON COMPANY DOCKET NO. 50-373 LA SALLE COLINTY STATION UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. NPF-11 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated December 15, 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 It R.
The facility will operate in confomity with the application, the provisions of the Act, and the regulations of the Connission; 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 compliance with the Commission's regulations set forth in 10 CFR Chapter I; i
D.
The issuance of this amendment will not be inimical to the connon 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 51 of the Connission's regulations and all applicable requirements have been satisfied.
I 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-11 is hereby amended to i
read as follows:
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( P.) Technical Specifications and Environmental Protection Plan l
The Technical Specifications contained in Appendix A as revised through Amendment No. 48, and the Environmental Protection Plan contained in l
Appendix B, are hereby incorporated in the license. The licensee shall l
operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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This amendment is effective as of date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION s
Elinor G. Adensam, Director RWR Pro.iect Directorate No. 3 Division of RWP Licensing
Enclosure:
Changes to the Technical Specifications Date of Issuance:
February 3,1987 s
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' ENCLOSURE TO LICENSE AMENDMENT N0. 48 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.
PEMOVE INSERT 3/4 1-6 3/4 1-6 3/4 1-7 3/4 1-7 3/4 1-8 3/4 1-8 3/4 1-11 3/4 1-11
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c.
REACTIVITY CONTROL SYSTEM CONTROL ROD MAXIMUM SCRAM INSERTION TIMES LIMITING CONDITION FOR OPERATION 3.1.3.2 The maximum scram insertion time of each control rod from the fully withdrawn position
- to notch position 05, based on de-energization of the scram l
pilot valve solenoids as time zero, shall not exceed 7.0 seconds.
APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.
ACTION:
With the maximum scram insertion time of one or more control rods a.
exceeding 7.0 seconds:
1.
Declare the control rod (s) with the sicw insertion time inoper-able, and 2.
Perform the Surveillance Requirements of Specification 4.1.3.2.c at least once per 60 days when operation is continued with three or more control rods with maximum scram insertion times in excess of 7.0 seconds.
Otherwise, 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 />.
b.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.1.3.2 The maximum scram insertion time of the control rods shall be demonstrated through measurement with reactor coolant pressure greater than or equal to 950 psig and, during single control rod scram time tests, the control rod drive pumps isolated from the accumulators:
For all control rods prior to THERMAL POWER exceeding 40% of RATED a.
THERMAL POWER following CORE ALTERATIONS ** or after a reactor shutdown that is greater than 120 days, b.
For specifically affected individual control rods following maintenance on or modification to the centrol rod or control rod drive system which could affect the scram insertion time of those specific control rods, and For at least 10% cf the control rods, on a rotating basis, at least c.
once per 120 days of operation.
" Control rod 10-47 may use position 46 as the fully withdrawn position for Cycle 2.
- Except movement of SRM, IRM or special movable detectors or normal control rod movement, LA SALLE - UNIT 1 3/4 1-6 Amendment No. 48 t
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REACTIVITY CONTROL SYSTEM CONTROL ROD AVERAGE SCRAM INSERTION TIMES LIMITING CONDITION FOR OPERATION 3.1.3.3 The average scram insertion time of all OPERABLE control rods from the fully withdrawn position,* based on de-energization of the scram pilot l
valve solenoids as time zero, shall not exceed any of the following:
Position Inserted From Average Scram Inser-Fully Withdrawn tion Time (Seconds) 45 0.43 39 0.86 25 1.93 05 3.49 APPLICABILITY:
OPERATIONAL CONDITIONS 1 and 2.
ACTION,:
With the average scram insertion time exceeding any of the above limits, 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 4.1.3.3 All control rods shall be demonstrated OPERABLE by scram time testing from the fully withdrawn position as required by Surveillance Requirement 4.1.3.2.
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" Control rod 10-47 may use position 46 as the fully withdrawn position for Cycle 2.
9 LA SALLE - UNIT 1 3/4 1-7 Amendment No. 48 g--
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,o REACTIVITY CONTROL SYSTEM FOUR CONTROL ROD GROUP SCRAM INSERTION TIMES LIMITING CONDITION FOR OPERATION 3.1.3.4 The average scram insertion time, from the fully withdrawn position,*
l for the three fastest control rods in each group of four control rods arranged in a two-by-two array, based on deenergization of the scram pilot valve solenoids as time zero, shall not exceed any of the following:
Position Inserted From
~ Average Scram Inser-Fully Withdrawn tion Time (Seconds) 45 0.45 39 0.92 25 2.05 05 3.70 i
APPLICABILITY:
OPERATIONAL CONDITIONS 1 and 2.
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ACTION:
With the average scram insertion times of control rods exceeding the a.
above limits:
l 1.
Declare the control rods with the slower than average scram insertion times inoperable until an analysis is performed to determine that required scram reactivity remains for the slow four control rod group, and 2.
Perform the Surveillance Requirements of Specification 4.1.3.2.c at least once per 60 days when operation is continued with an average scram insertion time (s) in excess of the average scram insertion time limit.
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 />.
b.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.1.3.4 All control rods shall be demonstrated OPERABLE by scram time testing from the fully withdrawn position as required by Surveillance Requirement 4.1.3.2.
" Control rod 10-47 may use position 46 as the fully withdrawn position for Cycle 2.
LA SALLE - UNIT 1 3/4 1-8 Amendment No. 48
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.
l APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 5*.
ACTION:
In OPERATIONAL CONDITION 1 and 2 with one control rod not coupled to a.
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 RWM 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 accomplished on the first attempt or, if not permitted by the RWM or RSCS then until permitted 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 water isolation valves.
2.
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 />.
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 l
recoupling by withdrawing the control rod and demonstrating l
that the control rod will not go to the overtravel position, or 2.
If recoupling is not accomplished, insert the control rod and disarm the associated directional control valves ** either:
a)
Electrically, or b)
Hydrat.lically by closing the drive water and exhaust water isolation valves.
l c.
The provisions of Specification 3.0.4 are not applicable.
i l
"At least each withdrawn control rod.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
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- May be rearmed intermittently, under administrative control, to permit testing l
associated with restoring the control rod to OPERABLE status.
- Control rod 10-47 is exempt for Cycle 2 provided the rod is fully inserted when less than or equal to 20% of RATED THERMAL POWER and neutron instru-mentation response is verified during rod withdrawal.
LA SALLE - UNIT 1 3/4 1-11 Amendment No. 48
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