ML20059N961
| ML20059N961 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 10/04/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059N959 | List: |
| References | |
| NUDOCS 9010240188 | |
| Download: ML20059N961 (3) | |
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WASHINGTON, o. C. 20sss SAFETY EVALUATION SY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 59 TO FACILITY OPERATING LICENSE N0. NPF-43 DETROIT EDISON COMPANY FERMI-2 DOCKET NO. 50-341
- 1. 0 : INTRODUCTION l
By letter dated December 22, 1988, as supplemented May 31, 1989, the Detroit Edison Company (DECO or the licensee) requested amendment to the Technical Specifications (TSs) appended to Facility Operating License No. NPF-43 for Fermi-2.
The proposed amendment will add new Sections to the TS with Limiting 4
Conditions For Operation (LCO) and Surveillance Requirements (SR) for the Alternative Shutdown System.
The Alternative Shutdown System has been installed to mitigate the effects of a fire in the control room.
2.0 EVALUATION
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Deco has installed an Alternative Shutdown System to allow operators to safely i
shut down the reactor following a fire in the control room complex if normal shutdown capability becomes disabled.
The proposed TS will' add new LCOs and SR for the dedicated instrumentation and controls as well as for several systems which are utilized in the alternative shutdown system but which are not presently listed in the TS.
These systems include the. Standby Feedwater (SBFW) System; the Combustion Turbine Generator (CTG) 11 Unit 1; and the Drywell Cooling Units.
i The required instrumentation for the alternate shutdown system is identified in Supplement No. 5 to NUREG-0798, Safety Evaluation Report, related to the operation of Fermi-2.
The proposed TS add a new Section 3/4.3.11 which includes the instrumentation to provide indications of the reactor water level, reactor pressure,- standby feedwater flow, condensate storage tank level, torus water.
temperature. - torus water-level, and the primary containment temperature.
The power for the-dedicated shutdown system is provided by CTG 11.-
The instrumentation provided for CTG 11 provides indication of. the output voltage,.
frequency and power level.
Control circuits have been provided for black starting-the CTG 11 from the Alternate Shutdown Panel.
In addition, control circuits have been provided for controlling the SBFW system, residual heat removal (RHR) system "C", the RHR heat exchanger "A", Division I of the.
emergency equipment cooling water (EECW) system, and drywell coolers.
The i-l action statements in the proposed TS LCOs allow 7 days for any one instrumenta-tion or control circuit to be out of service with the exception of the CTG j
instrumentation. Af ter 7 days the proposed action statements require the-9010240188 901004 PDR ADOCK 05000341 P
reactor to shut down.
The 7 day allowable out-of-service time limits and the exclusion from the provisions of TS Section 3.0.4 are consistent with TS Section 3/4.3.7.4, Remote Shutdown System Instrumentation and Controls.
The action statement for the CTG instrumentation requires, if one channel becomes inoperable, that the action required by the new proposed TSs for the CTG be taken tat action statement also allows a 7 day out of service time prior to shutting the reactor down or establishing an alternative power source.
The proposed TS for the instrumentation circuits require that each circuit has a channel check performed monthly and a channel calibration performed every refueling.
The proposed TS requires each control circuit to be demonstrated operable by verifying its capability to perform its intended functions at least once per 18 months.
These SR are consistent with similar TSs for other instrumentation systems which are safety-related or important to safety.
4 The proposed TSs include a new Section 3/4.7.11, Appendix R. Alternative Shutdown Auxiliary Systems, which incorporate LCOs and SRs for the SBFW system, CTG, Orywell Cooling Units, and Appendix R Alternative Shutdown Control Circuits, q
which have been discussed above.
The proposed TSs implement a 7 day inoperability limit on the SBFW system, I
and the drywell cooling units, which is consistent with the Standard Technical Specification limits.
The proposed TSs implement an inoperability limit of 4
seven. days for the CTG or allows the ability to provide an alternative power supply or the reactor is required to be shut down.
These limits, which cover the time period when the CTG may be inoperable, are consistent with similar TSs for dedicated shutdown panels for fire protection.
An alternative source of power is defined in the proposed bases for this section of the TSs as one which does not rely on offsite p ser for:
(1) starting, if required; or (2) operating, if already running.
It-is also capable of supplying the required loads associated with the alternative shutdown system.
The proposed TS change requires the CTG to be demonstrated operable every 31 days._' This is in conformance with the Standard Technical Specifications.
The proposed TSs define operability of the CTG'as the ability of the unit to develop at least 10 megawatts of power.
1 There are two SBFW pumps and two drywell coolers.
Either SBFW pump can supply i
-all the required cooling for achieving safe shutdown and either non-safety.
l related drywell cooler is capable of providing adequate cooling to achieve safe-shutdown Accordingly, the licensee has proposed to demonstrate that each SBFW pump is operable every 92 days on a-staggered test basis.
The SR for the SBFW system are based upon the RCIC surveillance.. The proposed TS defines operability of.the SBFW pumps as the capability of being able to pump greater i
than or equal to 600 gallons per minute.
If one SBFW pump becomes inoperable-the proposed TS increases the flow test frequency to monthly to compensate for the loss of redundancy.
Since one SBFW is adequate for the purpose of achieving f
safe shutdown, continued operation is 'not. further limited.
The Drywell Cooling units are like the SB.'W pumps in that they are redundant in the ability to support alternative shutdown.
Therefore, a similar surveillance requirement has i
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been proposed in.the new TSs.
Normally, the units will be checked quarterly on a staggered test basis and the frequency increased to monthly if redundancy is lost.
The Drywell Coolers are verified operable in the proposed TS by requiring the units to operate with the fan speed in "HIGH" for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Cooling to each drywell cooling unit is provided by the Emergency Equipment Cooling Water (EECW) System.
Therefore TS Section 3.7.11 will be added to the listing of specifications which must be referred to for action requirements for an inoperable EECW system subsystem.
Based on the above evaluation the staff finds that the proposed TSs for the alternative shutdown system provides adequate LCOs and SRs to assure that the system can be relied upon at all times.
The proposed TSs are consistent with similar TSs and the Standard TSs.
Therefore, the staff finds the proposed changes to the TSs are acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change to a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or a change to a surveillance requirement.
The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in 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 this amendment involves no significant hazards consideration and thare has been no public comment on such finding.
Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
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 activities 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 security or to the health and safety of the public.
P Principal-Contributor:
John Stang Date: October 4, 1990
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