ML20213G098
| ML20213G098 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/11/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20213G099 | List: |
| References | |
| NUDOCS 8705180121 | |
| Download: ML20213G098 (4) | |
Text
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l ENCLOSURE TO LICENSE AMENDMENT NO. 30 FAILITY OPERATING LICENSE NO. NPF-18 DOCKET NO. 50-374 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
Remove Insert 3/4 1-7 3/4 1-7 3/4 10-11 3/4 10-11 B 3/4 10-2 B 3/4 10-2 i
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0705100121 070511 f* DR ADOCK 03000374 p
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l REACTIVITY CONTROL SYSTEM I
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CONTROL ROD AVERAGE SCRAM INSERTION TIMES t
LIMITING CONDITION FOR OPERATION 6
l 3.l.3.)The average scram insertion time of all OPERA 8LE control rods from l
the fully withdrawn position, based on de-energization of the scram pilot valve solenoids as time zero, shall not exceed any of the following:
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Position Inserted From Average Scram Inser-i Fully Withdrawn tion Time (Seconds) 45 0.43 39 0.86 25 1.93 J
05 3.49 I
t APPLICABILITY: OPERATIONAL CONDITIONS 1# and 2.
l ACTION:
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With the average scram insertion time exceeding any of the above limits, be in i
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 />.
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i SURVEILLANCE REQUIREMENTS
!i 4.1.3.3 All control rods shall be demonstrated OPERABLE by scram time testing 6
from the fully withdrawn position as required by Surveillance Requirement 4.1.3.2.
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- See Special Test Exception 3.10.10 i
g LA SALLE - UNIT 2 3/4 1-7 Amendment No. 30 i
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SPECIAL TEST EXCEPTIONS 3/4.10.10 CONTROL R005 1
LIMITING CONDITION FOR OPERATION 1
3.10.10 The provisions of Specifications 3.1.3.1 and 3.1.3.7 may be suspended for control rod 02-43 during the second fuel cycle to allow the deu nstration of a fine motion control rod drive installed at this control rod location, provided conditions of 3.10.9 are satisfied.
i APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 5.
ACTION:
1 With the requirements of 3.10.9 not satisfied, immediately insert control l
rod 02-43 and disarm the drive motor electrically.
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SURVEILLANCE REQUIREMENTS l
4.10.10 The provisions of Specification 4.1.3.lthrv 4.1.3.7 may be suspended i
for control rod 02-43 during the second fuel cycle to allow the demonstration of a fine motion control rod drive installed at this location.
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4, LA SALLE - UNIT 2 3/4 10-11 Amendment No. 30
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s REACTIVITY CONTROL SYSTEMS SPECIAL TEST EXCEPTIONS BASES 6
e 3/4.10.8 CONTROL ROD PROGRAM CONTROLS With the in plant demonstration of a fine motion control rod drive (FMCRD) installed at the peripheral location 02-43 during the second fuel cycle, position 02-43 will be bypassed in the Rod Sequence Control System (RSCS) and programmed out of the Rod Worth Minimizer (RW). This will free the FMCRD rod from the Banked Position Withdrawal Sequence (8PWS) and notch movement restrictions.
By requiring that thermal power be greater than 25% rated thermal power and a rod pattern be established (after the withdrawal / insert sequences of its Banked Position Withdrawal Sequence Group are complete) before movement of control rod 02-43, one ensures that this rod will be moved only under conditions when the RSCS and RWM are not required to be operable.
After one cycle of demonstration with this control rod, position 02-43 will be returned to the RSCS and RWM in conjunction with the reinstallation of the original locking piston control rod.
3/4.10.9 SHUTDOWN MARGIN With the in plant demonstration of a fine motion control rod drive installed at 02-43 during the second fuel cycle, the shutdown margin shall be demonstrated assuming this control rod is at the fully withdrawn position.
In other words, during the second fuel cycle, the shutdown margin shall be equal to or greater than the values specified in Specification 3.1.1 with the most reactive control rod and the fine motion control rod fully withdrawn.
3/4.10.10 CONTROL R00 A fine motion control rod drive will be installed at LaSalle County Station j
Unit-2 during the second fuel cycle. To minimize the safety impact, a peri-pheral location 02-43 is selected. 'Due to the temporary test nature of this control rod drive, safety evaluation has been performed to justify continued safe operation of the reactor assuming this control rod drive is inoperable.
However, this rod is not considered inoperable in the context of specifications 3.1.3.1 through 3.1.3.7 and any scram time will not be incluoed in T,,, in specification 3/4.2.3. Thus during the second fuel cycle operation the LCO and surveillance requirements applicable to regular control rods are exempted for this control rod. After one cycle of demonstration, this control rod drive will be removed and the original locking piston control rod drive will be reinstalled at this location.
LA SALLE - UNIT 2 8 3/4 10-2 Amendment No. 30 w
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