ML20101B868
| ML20101B868 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 03/11/1996 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20101B856 | List: |
| References | |
| NUDOCS 9603150103 | |
| Download: ML20101B868 (2) | |
Text
-.
E849k UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, o.C. 20006 0001 e,,4*
s SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.108 TO FACILITY OPERATING LICENSE NO. NPF-30 UNION ELECTRIC COMPANY CALLAWAY PLANT. UNIT 1 DOCKET NO. 50-483
1.0 INTRODUCTION
By letter dated December 9,1994, as supplemented by letters dated September 13, 1995, and February 9, 1996, Union Electric Company (the licensee) requested changes to the Technical Specifications (TS) (Appendix A to Facility Operating License No. NPF-30) for the Callaway Plant, Unit No.1.
The proposed changes would revise TS 4.3.2.2, TS 4.7.1.2.1, and the Bases for TS 3/4.7.1.2 to decrease the frequency of auxiliary feedwater pump testing, remove inconsistencies in testing requirements for the turbine-driven auxiliary feedwater pump (TDAFP), and clarify performance parameters in the TS Bases.
The September 13, 1995, and February 9, 1996, letters provided additional clarifying information and did not change the original no significant hazards consideration determination published in the Federal Reaister on February 1, 1995 (60 FR 6314).
2.0 EVALUATION The auxiliary feedwater system supplies feedwater to the steam generators to remove decay heat from the reactor coolant system upon the loss of normal feedwater supply. The system is served by two motor-driven pumps and one turbine-driven pump. The current TS require testing these pumps during i
operation every 31 days and during a shutdown every 18 months.
This amendment extends the interval between auxiliary feedwater pump surveillance tests in TS 4.7.1.2.1 from 31 days to 92 days. This change adopts the provisions of NUREG-1431, " Standard Technical Specifications -
Westinghouse Plants," and incorporates the recommendations of NRC Generic Letter (GL) 93-05, "Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation."
In a letter dated September 13, 1995, the licensee stated that auxiliary feedwater train unavailability has been consistently less than 2 percent since 1992. The change is therefore compatible with plant operating exserience. Overall, by reducing the pump out-of-service time, the change slig1tly decreases the calculated core damage frequency. The change is consistent with the guidance in GL 93-05, and the staff finds it acceptable.
4 9603150103 960311 PDR ADOCK 05000403 p
1 e This amendment also adds an exception to the requirements of TS 4.0.4 to test the TDAFP as established in TS 4.7.1.2.1 and TS 4.3.2.2, and eliminates the requirement in TS 4.7.1.2.1 to test the TDAFP while the plant is shut down.
TS 4.0.4 prohibits changes in operational modes unless surveillance However, the TDAFP must have adequate steam requirements have been met.
i pressure if the surveillance testing is to be valid and not damage the pump.
Eliminating the requirement to test the TDAFP before entry inte MODE 3 allows suitable testing conditions to be established before testing. The TS requirement to test the motor-driven auxiliary feedwater pumps during shutdown remains the same. These changes clarify the TS for the TDAFP, and are consistent with NUREG-1431. Therefore, the staff finds that the changes are acceptable.
The staff also reviewed the changes to the Bases for TS 3/4 7.1.2 and found that the changes had no effect on safety and are acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Missouri State official The State official was notified of the proposed issuance of the amendment.
had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes 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 and changes surveillance requirements. The NRC 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 The Comission has previously issued a occupational radiation exposure.
proposed finding that the amendment involves no significant hazards consideration, and there has been no public coment on such finding (60 FR 6314). Accordingly, the amendment meets the eligibility criteria for Pursuant to 10 CFR categorical exclusion set forth in 10 CFR 51.22(c)(9).
SI.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
The Comission has concluded, based on the considerations discussed above, there is reasonable assurance that the health and safety of the that (1)ill not be endangered by operation in the proposed manner, (2) such public w activities will be conducted in compliance with the Comission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
A. Dumer Date:
March 11, 1996