ML20140B990
| ML20140B990 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 03/18/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20140B986 | List: |
| References | |
| NUDOCS 8603250061 | |
| Download: ML20140B990 (3) | |
Text
'o Un;'TED STATES
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SAFETY EVAltlATION BY THE OFFICE OF NllCLEAR REACTOR REGilLATION SUPPORTING AMENDMENT NO. 40 TO FACILITY OPERATING LICENSE NO. DPP-?2 NORTHERN' STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263
1.0 INTRODUCTION
y By letter dated August 30, 1984, as revised on November 8, 1084 and Auaust 30, 1985 Northern States Power Cnmpany (the licensee) renuested Technical Specification chances to amend Appendix A of Facility Operatino License No. DPR-27. The chances under consideration include (al clarification of functions and appropriate setpoints for the Reactor Buildino Vent Plenum Monitors (RPV-PM) and the Reactor Buildino Vent-Wide Range Gas Monitors (RRV-WRGM) (Sections 3.2/4.2 and 3.8/4.8),
(b) deletion of Radioactive Effluent Limiting Conditions for Operation (LCO) from Section 4, Surveillance Requirements, and incorporation into Section 3, limiting Conditions for Operation, and (c) editorial chances to (11 eliminate confusion between the words effluent and liquid radwaste, (?) add a footnote to ensure existina calibration requirements are implemented for the discharge canal radiation monitors, and (31 ensure that replacement monitors are eoual to or better"than the present system and meet current calibration requirements. The licensee also requests changing " Reactor Low Water Level" to " Reactor low Low Water Level" in the (a) Trip Function, Table 3.2.7, for the Reactor Ruilding Ventilation Isolation and Standby Gas Treatment System Initiation, Specification 3.2.E.2 and Table'3.2.4, and (h) the Instrument Channel, Table 4.2.1, Minimum Test and Calibration Frequency for Core Cooling, Dod Block, and Isolation Instrumentation.
2.0 EVAltlATION a.
Chance to Clarify the Function and Surveillance of RRV-PM and RBV-WRGM (pages 47, 59, 62, 68, 70, 198k, 1981, 198n, 1980, and 198y).
The licensee has proposed changes to clarify the function of and surveillance requirements for the RRV-PM and the RBV-WRGM, Sections 3.2/4.2 and 3.8/4.8. The newly installed R8V-WRGM are set at the equivalent of 10 CFR Part 20 allowable release rates.in accordance with methods in the aoproved Offsite Dose Calculation Manual (ODCM). We concur that the new monitors, usina methods provided in the ODCM, provide a routine release isorlation function for compliance with 10 CFR Part 20 and 10 CFR Part 50, Appendix I; therefore, the staff finds the change is acceptable.
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b.
Change to RBV-PM Trip Setpoint (pages 59 and 70)
Tables 3.2.4 and 3.2.7 were modified to change the trip setpoint on the RBV-PM monitors from 3 mR/hr with a deviation of 0.2 mR/hr to 100 mR/hr with a deviation of 5 mR/hr.
Because the RBV-PM no longer provides an isolation function for routine releases, the 100 mR/hr limit is reasonable for an accident condition; the higher setpoint for this monitor is acceptable, c.
Rearrangement of LC0 and Surveillance Requirements (pages 192, 193, 197, and 198d)
The licensee has rearranged Section 3.8/4.8 " Radioactive Effluents" to better describe the LC0 and Surveillance Requirements.
This change is administrative in nature; no wording or intent is left out or chanced. Therefore, the change is acceptable.
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Miscellaneous Chances for Clarification j
l In Table 4.8.1 (pace 198m) a footnote change was made concerning Discharge Canal Monitors calibration requirements. The change provides for continued use of solid sources traceable to National Bureau of Standards (N9S) standards for instrument calibration.
The original calibration used a liquid source traceable to NRS standards which the applicant used for correlation with the solid source. This change provides an acceptable calibration practice; therefore, the staff finds this change acceptable.
In Table 3.8.1 (page 1981) a minor word change was made to clarify possible confusion between effluent and liquid radwaste.
The proposed change is editorial; therefore, it is acceptable.
Tables 4.2.1 (page 62) and 3.2.7 (page 70) have been changed to correctly indicate that the trio isolation function occurs at' Reactor Low Low Water Level rather than Reactor low Water Level.
This change is editorial, correcting a previous error; therefore, it is acceptable.
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3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves changes to requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and changes to the surveillance requirements. 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 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).
Fursuant to 10 CFR 51.22(b) no environmental impact statement nor environmental assessment need be prepared in connection witn the issuance of this amendment.
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- l d.0 CONCLUSION The staff has concluded, based on the considerations discussed above, that:
4 (1) there is reasonable assurance that the. health and safety of the public i
will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Conriission's regulations i
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.
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i Principal Contributor:
W. B. Grant, L. R. Greger and.K. R. Ridgway.
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Dated: March 18,1986 1
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