ML20091B344
| ML20091B344 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/20/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20091B342 | List: |
| References | |
| NUDOCS 9106030087 | |
| Download: ML20091B344 (3) | |
Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLCAR REACTOR REGULATION RELATED TO AMENDMENT NO. 157 TO FACILITY OPERATING LICENSE NO. DPR-32 AND AMENDMENT NO.156TO FAClllTY OPERATING LICENSE NO. DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-280 AND 50-281
1.0 INTRODUCTION
By letter dated March 27, 1991, Virginia Electric and Power Company (the licensee) requested amendments to the Surry, Units 1 and 2 Technical Specifi-cations (TS). The proposed changes would incorporate the location of the gaseous effluent release point associated with the newly constructed Radwaste Facility into Figure 5.1-1 of the TS, A station process vent would also be identified as a mixed mode release point.
2.0 EVALUATION Figure 5.1-1 of the TS defines the unrestricted areas with respect to the Surry Power Station effluent release points. The licensee is presently completing construction of a new Radwaste facility to supplement the radwaste systems at the Surry Power Station under the provisions of 10 CFR 50.59.
The Radwaste Facility is located within a restricted area east of the station, and when operational the f acility will have a gaseous effluent release point that is not shown in Figure 5.1-1 of the current TS. Therefore, the proposed amendments would modify figure 5.1-1 to show the gaseous release point associated with the.
Radwaste Facility. The proposed change is administrative in nature since there are no limiting conditions for operation, action statements, or surveillance requirements associated with Section 5, including Figure 5.1-1, of the current
('
or proposed TS.
The Radwaste Facility, which includes the use of demineralizers and an evapo-rator, is designed to treat liquid and solid wastes, provide a decontamination f acility, and store packaged processed radwaste material prior to shipment.
Off-gassing will occur during processing of the liquid radwaste which is discharged by way of the Radwaste Facility vent and constitutes only a small portion of the normal gaseous release during station operation. The Radwaste Facility is equipped with a radiation monitoring system to ensure radiological protection of the f acility personnel and members of the general public, as well as to monitor, record, and control the release of radioactive materials. Based on its 10 CFR 50.59 evaluation, the licensee has concluded that there will oe no increase in the total gaseous release of radioactive material from the Surry Power Station as a result of the operation of the Radwaste Facility. Although the thyroid component of the calculated dose from routine liquid radwaste will 9106030087 910520 PDR A09CK 05000280 P
t increase slightly the overall calculated 10 CFR Part 50 Appendix ! exposures woulddecreasewiththeuseoftheRadwasteFacility.
Tlieconsequencesof any accident associated with the operation of the Radwaste Facility are bounded by Chapter 14 analyses of the Updated Final Safety Analysis Report.
Additionally, the station process vent at a 131 foot elevation is being identified as a mixed mode release point, i.e., both elevated and ground level dispersion components are accounted for.
This vent has been treated as a mixed mode release point but never identified as such in the TS.
3.0
SUMMARY
Based on the staff's evaluation of the licensee's submittal, we conclude that the proposed amendments are acceptable and are, therefore, approved.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Virginia State official was notified of the proposed issuance of the amendments. The State official had no comment.
l
5.0 ENVIRONMENTAL CONSIDERATION
l These amendments change a requirement with respect to installation or use of a l
facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve 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 these amendments involve no significant hazards consideration and there has been no public comment on such finding (56 FR 15646). Accordingly, these amendments meet 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 these amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that:
k (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Colitributor:
B. Buckley Date: May 20, 1991 i
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DATED:
Ma,y 20,1991 AMENDMENT N0.
157 TO FACILITY OPERATING LICENSE NO. DPR SURRY UNIT 1 AMENDfiENT NO.
156 TO FAClllTY OPERATING LICENSE N0. DPR SURRY UNIT 2 LDocketFile~
NRC & Local PDRs PDll-2 Reading S. Varga, 14/E/4
- 6. t.ainas,14/H/3 H. Berkow D. Miller B. Buckley OGC-WF D. Hagan, 3302 MNBB i
E. Jordan, 3302 MNBB l
B. Grimes, 9/A/2 G. Hill (8), P-137 l
Wanda Jones, P-130A J. Calvo, 11/F/23 i
ACRS (10)
GPA/PA i
OC/LFMB l
PD Plant-specific file [ Gray Filel M. Sinkule, R-Il Others as required cc:
Plant Service list ll i
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