ML20137Y716
| ML20137Y716 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 10/02/1985 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20137Y688 | List: |
| References | |
| NUDOCS 8510080076 | |
| Download: ML20137Y716 (8) | |
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UNITED STATES NUCLEAR REGULM ORY COMMISSION j
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SAFETY EVALUATION AMENDMENT N0.26TO NPF-11 AND AMENDMENT N0.14T0 NPF-18 LA SALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374 Introduction By letter dated April 17, 1985, Consnonwealth Edison Company (the licensee) requested amendments to the La Salle, Units 1 and 2 Technical Specifications.
The proposed changes would incorporate:
(1) correction of typographical and administrative errors and inclusion of a limit ct.rve when the end-of-cycle reactor pump trip is inoperable; (2) a statement that Specification 3.0.4 does not apply in Specification 3.6.3 by pennitting reactor startup as long as assurance is provided that a system which is inoperable would not affect plant safety; (3) clarification to indicate required action on failure of either " Full In" or " Full Out" reactivity position and specifying system surveillance of " Full In" indication; (4) correction allowed for time for decay of liquid effluent batch releases for lower limit of detection; (5) new method of calculating the kilowatt capacity for electric heaters in the control room emergency air make-up train; and (6) reactor core isolation cooling differential temperature instrumentation with respect to set points, surveillance requirements and required remedial actions.
Evaluation (1) Correction of Typographical and Administrative Errors and inclusion of
,a new Minimum Critical Power Rated Curve E
Several valve stroke times on Technical Specification Table 3.6.3-1 do not reflect actual valve operating times and the licensee is correcting them for the actual valve times. All times changed were reduced making the action more conservative. Also, the licensee has submitted typographical and editorial errors to be corrected. The staff considers these corrections as administrative changes in order to make the Technical Specifications consistent with the as-built configuration and to make the Technical Specifications grammatically correct.
In addition, the licensee submitted a Technical Specification change to include the Minimum Critical Power Ratio (MCPR) operation limit with the end-of-cycle recirculation pump trip (E0C-RPT) system inoperable. The pur-pose of this Technical Specification change is to increase operating flexibility during the plant operation. The operating limit MCPR is detennined by an analysis of the transients to obtain their effect on the core critical power ratio ( a CPR). The maximum value of A CPR is then j
added to the safety limit MCPR to obtain the operating limit MCPR. The maximum value of a CPR includes multipliers which are required to account for uncertainties in the transient calculational method.
8510000076 851002 DR ADOCK O 33
' The methods as described in NE00-24011-A, " General Electric Standard Application for Reactor Fuel" was used to obtain the operating limit MCPR, and these methods are applicable generally to boiling water reactor transient analysis. We find that these methods are acceptable for deter-mining the operating limit MCPR for operation with E0C-RPT system inoperable for la Salle Units 1 and 2.
We reviewed the analytical results submitted by the licensee and find that the approved method was used and the results of analysis support the proposed MCPR operating limit to avoid violation of the MCPR safety limit for La Salle Units 1 and 2 design basis transients.
Therefore, the staff concludes that reasonable assurance has been provided that the proposed Technical Specification changes for La Salle Units 1 and 2 will not pose a threat to the health and safety of the public and are acceptable.
(2) Specification 3.0.4 Does not apply Specification 3.0.4 is provided to ensure that plant operation is not initiated with either inoperable systems or other limits being exceeded.
However, exceptions are provided for startup with inoperable systems, if plant safety is not affected.
Specification 3.6.3 requires the operability of the primary containment isolation valves to ensure that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere.
Presently, the Technical Specifi-cation requires that if the isolation of the valve renders a system re-quired to be operational inoperable, the plant cannot proceed to startup.
The licensee has proposed to modify Specification 3.6.3 to clarify that if an isolation valve that is declared inoperable can be secured in its isolated position, plant startup should be allowed, since containment integrity is not degraded. This change is consistent with the footnote to T. S. Table 3.6.3-1 and merely clarifies the action required to allow waiver of T.S.3.0.4.
J Based on the NRC staff's review of this item, the staff concludes that the proposed change does not increase the consequences of previously evaluated accidents and will not decrease the margin of safety previously found acceptable. Therefore, the subject change is acceptable.
(3) Rod Position Indication and Surveillance The proposed Technical Specification changes for required action on failure of either " Full In" or " Full Out" of the Rod Position Indication System and the surveillance of " Full In" indication was requested by the licensee.
Essentially, the change would substitute the Standard Technical Specifica-l tion for the solid state Rod Sequence Control System (RSCS) for the present Technical Specification which is appropriate for a non-solid state RSCS.
The revised Technical Specification would accomplish the same ends as the present one but is written in a manner more suited to the solid state RSCS which is present in the La Salle Units 1 and 2.
Also, a surveillance re-quirement is added for the " Full In" position indicator which was omitted in the original Specification. The staff finds the proposed change to the Technical Specifications to be acceptable. This finding is based on the fact that the intent and effect of the Technical Specifications are not changed and that the revised Specification is more appropriate to the "as-built" La Salle Units 1 and 2 hardware. The additional surveillance re-quirement of " Full In" make the resulting Technical Specifications more conservative and is, therefore, acceptable since there is no change in the accuracy of sample analysis.
(4) Decay Correction of Liquid Effluent In the La Salle Units 1 and 2 Technical Specifications, the equation on Table 4.11.1-1 requires the use of a typical value for at (the elapsed time between the midpoint of the sample collection and the time of counting) for estimating the lower limit of detectability of bankground sample when measuring liquid radioactivity concentration from a tank prior to discharge. The licensee is reauesting a change to allow the time duration between taking the sample and measuring the sample to be zero because no tank discharges would occur until after the sample measurements are made (i.e., time decay in the tank is the same as the time decay in the sample; therefore, the sample results reflect tank contents without correction for decay). The staff finds this change technically acceptable since there is no change in the accuracy of sample analysis.
(5) Control Room Emergency Air Make-Up Train Heaters The duct heaters for the Control Room Emergency Air Make-Up are designed to reduce the relative humidity of the airflow to a maximum of 70 percent relative humidity at the worst inlet conditions. A 20 KW single stage heater is provided for this function. These heaters are provided with surveillance requirements in the La Salle Units 1 and 2 Technical Speci-fications to ensure they provide their design function. The Technical Specifications indicate that these heaters are to maintain 20 2 kV during these surveillance tests to verify the heaters are functioning properly. Because of the supply voltage variations about the nominal design value of 480 volts, the actual power consumption could fall out-side the specified range. The licensee is requesting that the Technical Specifications be changed to allow an acceptance range of 20 2 KW to the heaters when the supply voltage is appropriately corrected for varia-tions from 480 volts at the bus. The staff finds this change acceptable because this change does not affect the ability of the heater to reduce relative humidity to the required level.
(6) Reactor Core Isolation Cooling Pump Room Differential Temperature Isolation The licensee is requesting changes to the La Salle Units 1 and 2 Technical Specifications which involve:
(a) pump and room differential temperature isolation for the reactor core isolation cooling (RCIC) system, and (b) several clarifications and relaxation of requirements for Specification 3/4.3.2, " Isolation Action Instrumentation."
._ Technical Specification 3/4.3.2 for La Salle Units 1 and 2 does not in-clude the RCIC pump room differential temperature instrumentation which is installed at these plants and described in Table 5.2-8 of the Updated Final Safety Analysis Report. As noted in the licensee's submittal, this instrumentation is also not included in NUREG-0123 Revision 3. " Standard Technical Specification for General Electric Boiling Water Reactors (BWR/5)." The licensee submitted proposed changes to Table 3.3.2-1, Table 3.3.2-2 and Table 3.3.2-3 of the Technical Specifications to in-clude this instrumentation. We find these proposed Technical Specifi-cation changes to be acceptable since they merely describe installed equipment.
In addition, the following changes were made to Technical Specification 3/4.3.2:
a) changes to clarify that for trip systems having more than one channel per trip system, it is acceptable to trip the inoperable channel or channels and not necessary to place the trip system in the tripped condition.
b) changes to clarify the action required to allow one hour to restore at least one channel prior to taking the action of Table 3.3.2-1 for single systems.
c) changes to clarify the specific number of channels in each area, d) changes to allow sufficient time to perform required surveillance testing of those trip systems which have only one channel.
e) correction of a typographical error involving the level initiation setpoint for the RCIC system.
The staff has reviewed these proposed changes and found them to be acceptable because they do not affect the ability of the RCIC system to function as in-tended and because they allow sufficient times to complete operability sur-veillance.
Based on the above, we conclude that all these changes to the La Salle Units 1 and 2 Technical Specifications are appropriate and should be incorporated into the respective Technical Specifications.
Environmental Consideration These amendments involve a change in the use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveil-lance requirements. The staff has determined that these amendments involve no significant increase in the amounts, and no significant change in types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The l
. Comission has previously issued a proposed finding that these amendments in-volve no significant hazards consideration and there has been no public com-ment on such finding. Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 5.22(b) no environmental impact statement or environmental assess-ment need be prepared in connection with the issuance of these amendments.
Conclusion The Commission made a proposed determination that these amendments involve no significant hazards consideration which was published in the Federal Register (50 FR 23545) on June 4, 1985. No public coments were received.
We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activi-ties will be conducted in compliance with the Commission's regulations and l
the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Dated: (R88M5
Docket No. 50-373/374 M 02 E Mr. Dennis L. Farrar Director of Licensing Comonwealth Edison Company P.O. Box 767 Chicago, Illinois 60690
Dear Mr. Farrar:
SUBJECT:
ISSUANCE OF ADMENDMENT N0. 26 TO FACILITY OPERATING LICENSE NO. NPF-11 AND AhEN0hENT N0.14 TO FACILITY OPERATING LICENSE N0. HPF-18 LA SALLE COUNTY STATION, UNITS 1 AND 2
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The Nuclear Regulatory Comission has issued the enclosed Amendment ho. 26 to Facility Operating License No. NPF-11 and Amendment No. 14 to Facility Operating License No. NPF-18 for the La Salle County Station, Units 1 and 2.
These amendments are in response to your letter dated April 17, 1985. The amendments incorporate:
(1) correction of typographical and administrative errors and inclusien of a limit curve when the end-of-i cycle reactor pump trip is inoperable; (2) a statement that Specification 3.0.4 does not apply in Specification 3.6.3 by pennitting reactor startup as long as assurance is provided that a systen inoperable would not affect plant safety; (3) clarificatico to indicate required action on failure of either " Full In" or Full Out" reactivity position and specifying system surveillance of " Full In" indication; (4) correction allowed for time decay of liquid effluent batch releases for lower limit of detection; (5) new method of calculating the kilowatt capacity for electric heaters in the control room emergency air make-up train; and (6) the reactor core isolation cooling differential temperature instrumentation with respect to set points surveillance requirements and required remedial actions.
A copy of the related safety evaluation supporting Amendment No.26 to Facility Operating License No. NPF-11 and Amendment No.14 to Facility Operating License Nc. NPF-18 is enclosed.
Sincerely, VJ Walter R. Butler, Chief Licensing Branch No. 2 Division of Licensing
Enclosures:
- 1. Amendment No. 26 to NPF-11
- 2. Amendment No.14 to NPF-18
- 3. Safety Evaluation cc: w/ enclosures See next page DISTRIBUTION See next page LB#2/DL LB# DL OELC LB#2/DL l
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FOR THE NUCLEAR REGULATORY C0fif11SSION j
origiWO signed by:
Walter R. Butler, Chief Licensing Branch No. 2 Division of Licensing
Enclosure:
Changes to the Technical Specifications Date of Issuance: OCT 08 HE t
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FOR THE NUCLEAR REGULATORY COMMISSION oristaal sisued by:
Walter R. Butler, Chief Licensing Branch No. 2 Division of Licensing
Enclosure:
Changes to the Technical Specifications Date of Issuance: M 02 3 4
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