ML19325E172
| ML19325E172 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/20/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19325E170 | List: |
| References | |
| GL-88-16, NUDOCS 8911020169 | |
| Download: ML19325E172 (3) | |
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9 UNifED STATES l, ' ' f il ~ ' -
n' NUCLEAR REGULATORY COMMISSION fF Ojf wAsmNGTON, D. C. 20665 3.....
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a SAFETY. EVALUATION.BY THE.0FFICE 0F NUCLEAR. REACTOR. REGULATION p
o SUPPORTIljGAMENDMENTNO.:120.TOFACILITY, OPERATING. LICENSE.NO.DPR-25 p
AND AMENDMENT NO.116-TO. FACILITY.0PERATING LICENSE.NO DPR-30 4
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COMMONWEALTH EDISON COMPANY g
IOWA-ILLINOIS GAS'AND, ELECTRIC COMPANY u
L QUAD. CITIES NUCLEAR. POWER' STATION.. UNITS 1 AND 2 DOCKET NOS. 50-254/265
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1.0 INTRODUCTION
By letter d6ted July 11, 1989 as amended b 14, 1989, Commonwealth Edison Company (the licensee) y letter dated Augustproposed change I
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-Specifications (TS) for Quad Cities Nuclear Power Station, Units 1.and 2.
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l proposed changes would modify specifications having cycle-specific parameter Report (y. replacing these limits with a reference to the Ccte Operating LimitsThe pr limits b i
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COLR).-
L arid Administrative Controls Sections of TS. Guidance on the proposed changes l
.was deve oped by NRC on t e basis of a lead-plant proposal submitted on the l
h ll Oconee plant. docket by Duke Power Company. Subsequently, this guidance was provided to all power reactor licensees and applicants by Generic Letter 88-16, dated.0ctober 4, 1988.
I 2.0 EVALUATION The licensee's proposed changes to the TS are in accordance with the guidance l
provided by Generic Letter 88-16 and are addressed below.
(1) The Definition Section of the TS was modified to include a definitioni of I
the Core Operating Limits Report. This definition notes that plant operation within these limits is addressed by individual specifications.
(2) The following specificatior.s were revised to replace the values of cycle-specific parameter limits with a reference to the COLR that provides these limits.
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Specifications 3.2.0(Table 3.2-3)and3.6.H.3d 8911020169 891020 7 PDR ADOCK 05000254, P
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. The Rod Withdrawal Block Monitor Upscale Instrumentation Setpoint.
equation for these Specifications is provided in the COLR.
b.
Specification 3.3.C.5 3
The overall average of the 20 percent insertion scram time limit;for this l
Specification is provided~1n the COLR.
Specification 3.5.I c.
The Average Planar Linear Heat Centration Rate (APLHGR) limit for this 1
Specification is provideo in the COLR.
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Specification 3.5.J l
D The Linear Heat Generatica Rate (LHGR) limit for this Specification is
.provided in the COLR.'
e.
Specifications 3.5.K and 3.6.H.3a j
TheMinimumCriticalPowerRation(MCPR)limitsfortheseSptcifications-l' are provided in the COLR.
(f)' Specification'3.5.K-The K factors that are applied to the operating limit minimum critical f
power ratio (hCPR) for this Specification are provided in the COLR.
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The bases of effected specifications have been modified by the licensee to include appropriate reference to the COLR. : Based on our review, we conclude that the changes to these bases are acceptable, j
i (3) Specification 6.6.A.4 was added to' the' reporting requirements of the L
Administrative Controls Section of the TS. This specificetion requires i
that the COLR be submitteo, upon issuance, to the NRC Document Control Desk with copies to the Regioral Administrator and Resident Inspector.
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The COLR provides the values of cycle-specific operating limits that are L
applicable for the current fuel cycle.
Furthermore, this specification
. requires that the valees of these limits be established using NRC approved l
methodology and be consistent with all applicable limits of the safety L
analysis. The approved methodology is NEDE-24011-P-A, " General Electric i
L Standard Application for Reector fuel," (latest approved version).
L Finally, this specification requires that all changes in cycle-specific parameter limits be documented in the COLR before each reload cycle or H
remaining part of a reload cycle, and submitted upon issuance to the NRC prior to reactor operation within the new parameter limits.
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4 Based upon a detailed review of the above items, the NRC staff concludes that the licensee provided an acceptable response to Generic Letter 88-16 on removing cycle-specific operating limits from TS. Because plant operation continues to 1
be limited in accordance with the values of cycle-specific limits that are Y
established using an NRC approved methodology,-the NRC staff concludes that this change is administrative in nature and there is no impact on' plant safety
- as a consequence. Accordingly, the staff find's that the proposed changes are acceptable.
As part of the implementation of Generic Letter 88-16, the staff also reviewed a sample COLR provided by the licensee. On the basis of this review, the staff concludes that the format and content of the sample COLR> are acceptable.
NRC staff reviewed the request by Comonwealth Edison Company to modify the Technical Specifications of the Quad Cities station Units 1 and 2,'to remove
' the specific values of some cycle-dependent operating limits and place them in j
a Core Operating Limits Report referenced by TS. NRC staff concludes that the aforementioned Technical Specification modifications are acceptable.
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3.0 ENVIRONMENTAL CONSIDERATION
These. amendments involve a change to a requirement with respect to the installation or use of a facility component located within the restricted areas as defined in 10 CFR Part 20. The staff has determined that these amendments i
involve no significant increase in the amounts, and no significant change in
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the types, of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that these amendments involve no significent hazards consideration and there has been no public coment on such finding. Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). These amendments also involve changes in recordkeeping, reporting or administrative procedures or requirements. Accordingly, with respect to these items, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 551.22(c)(10).
Pursuant 10CFR51.22(b),noenvironmentalimpactstatementorenvironmental assessment need be prepared in connection with the issuance of this amendrent.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed previously, that:
(1) there is reasona'le assurance that the health and safety of the public s
will not be endangered by operation in the proposed manner, (2) such activities o-will be conducted in compliance with the Commission's regulations and, (3) the issuance of this amendment will not be inimical to the common defense and
^f-security nor to the hecith and safety of the public.
Principal Contributor:
D. Fieno Dated: October 20, 1989 L -
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