ML17279A956
| ML17279A956 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 04/04/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17279A955 | List: |
| References | |
| TAC-64942, NUDOCS 8804120280 | |
| Download: ML17279A956 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.
51 TO FACILITY OPERATING LICENSE NO.
NPF-21 WASHINGTON PUBLIC POWER SUPPLY SYSTEM WPPSS NUCLEAR PROJECT NO.
2 DOCKET NO. 50"397 1.0 2.0
3.0 INTRODUCTION
By application dated March 10, 1987, the Washington Public Power Supply System (the licensee) requested an amendment to the Technical Specification for Facility Operating License No.
NPF-21 for the WNP-2 Plant.
The Amendment would change the fuel vault criticality monitor alarm setpoint value in Table 3.3.7. 1-1 from < 10 R/h(a) to a revised value of < 5 R/h(a).
EVALUATION The Code of Federal Regulations 10 CFR 70.24.a. 1 requires that the monitoring system shall be capable of detecting a criticality that produces an absorbed dose in soft tissue of 20 rads of combined neutron and gamma radiation at an unshielded distance of 2 meters from the reacting material within one minute.
Coverage of all areas shall be provided by two detectors.
The licensee stated that the current alarm setpoint value of < 10 R/h(a) was determined by calculation using criteria from ANSI 16.2 1569, Appendix "Example of Criticality Accident Alarm System."
The change request from < 10 R/h(a} to < 5 R/h(a) reflects utilization of the revised criteria presented in ANSI/ANS 8.3 1979, "Criticality Accident Alarm System,"
Appendix B.
The calculated dose rate using the new criteria is 5.05 R/hr.
The allowable value for the alarm setpoint was therefore established at 5 R/hr.
The staff finds that the revised alarm setpoint value is more conservative than th*e~current alarm setpoint value.
This setpoint will meet or exceed the crit'eria set forth in 10 CFR 70.24.a.1.
Therefore, the changed proposed"in the application is acceptable.
ENVIRONMENTAL CONSIDERATION This amendment involves a change in the installation and use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that this amendment involves no significant increase in the amounts, and no significant change in the types, of effluents that may be released offsite, and that there is no significant increase in in-dividual or cumulative occupational radiation exposure.
The Commission has 804i20280 sgppppq7 804oe PDR ADOCK D P
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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 to prepared in connection with the issuance of this amendment.
4.0 CONTACT WITH STATE OFFICIAL The Corrmission has consulted with the State of Washington concerning the proposed determination that the amendment involves no significant hazards consideration.
The state of Washington did not have any comment.
- 5. 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 regula-tions and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Hulbert Li, NRR Dated:
April 4, 1988
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