ML20199L924
| ML20199L924 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 07/01/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20199L921 | List: |
| References | |
| NUDOCS 8607100060 | |
| Download: ML20199L924 (2) | |
Text
.
a rng',
o UNITED STATES
~g 8
NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D. C. 20555
%...../
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 45 TO FACILITY OPERATING LICENSE N0. DPR-22 NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT DOCKET N0. 50-263
1.0 INTRODUCTION
By the letter dated September 24, 1982, Northern States Power Company (the licensee) requested several changes to the Monticello Nuclear Generating Plant Technical Specifications (TS). Two of these changes were:
(1) Revise the TS to reflect the installation of Alternate (or ATWS) Rod Injection (ARI) system, and (2) Revise Table 3.7.1 to show the correct normal position (open) of the recirculation loop sample valves. The other changes requested in this application either have been resolved or will be addressed in separate licensing actions.
2.0 EVALUATION The ARI system was installed for Monticello as an additional fix to mitigate ATWS. The modifications were completed and the system made operational in 1980. ARI is a means to control blade injection by the normal control rod drive units which are triggered by a new diverse ATWS logic and scram pilot air header dump valves. The system is automatically initiated by either reactor vessel high pressure or low low water level.
Initiation of the system causes the scram pilot air header to bleed down through the ATWS dump valves.
The ARI system uses the same logic as the Recirculation Pump Trip (RPT) system and the necessary TS changes simply extend the requirements estab-lished for the RPT logic to ARI also. Amendment No. 35 to Provisional Operating License No. DPR-22 issued September 15, 1978 approved the Limiting Conditions for Operation and Surveillance Requirements for the RPT system.
Subsection (C)(3) of 10 CFR 50.62 requires that each boiling water reactor must have an ARI that is diverse from sensor output to final actuation device.
Therefore, for the reasons given above, the staff finds the proposed changes 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. The staff has determined that the amend-ment 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 8607100060 860701 PDR ADOCK 0500 3
P
radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there 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 nor environmental assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
will not be endangered by operation in the proposed manner, and (2) public (1) there is reasonable assurance that the health and safety of the such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security nor to the health and safety of the public.
Principal Contributor:
R. Auluck
~
Dated: July 1, 1986 e
l I
1
,