ML20056E090
| ML20056E090 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/02/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056E089 | List: |
| References | |
| NUDOCS 9308190320 | |
| Download: ML20056E090 (2) | |
Text
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l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.167 TO FACILITY OPERATING LICENSE NO. DPR-51 l
l ENTERGY OPERATIONS. INC.
ARKANSAS NUCLEAR ONE. UNIT NO. 1 DOCKET N0. 50-313
1.0 INTRODUCTION
By letter dated March 19, 1993, Entergy Operations, Inc. (the licensee),
submitted a request for changes to the Arkansas Nuclear One, Unit No. 1 (ANO-1) Technical Specifications (TS). The amendment would update the reactor coolant system (RCS) leakage test pressure in TS 4.3.2 to agree with the requirements of the 1980 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI (through winter 1981 addenda).
2.0 EVALUATI0ff The NRC staff's review of the proposed amendment included an assessment of TS 4.3, " Testing Following Opening of System." Specifically, the existing specification requires a minimum RCS leakage test pressure of 2285 psig.
IWA-5000 of the 1980 Edition of the ASME Boiler and Pressure Vessel Code,Section XI, requires leakage tests be performed at the nominal operating pressure (2155 psig).
The licensee proposes to update TS 4.3.2 to allow RCS leakage tests to be performed at nominal operating pressure (2155 psig). Currently, the RCS leakage detection tests are performed at 2285 psig.
This specification is based on the 1971 Edition of the ASME Boiler and Pressure ~ Vessel Code (through winter 1971 addenda), which did not address RCS leakage tests. A leakage test pressure of 1.06 times nominal operating pressure was specified to provide conservatism.
For the second 10-year inservice inspection (ISI) interval, the licensee committed to perform RCS inservice inspections and tests in accordance with the 1980 Edition of the ASME Boiler and Pressure Vessel (through winter 1981-addenda).
IWA-5000 of that Edition requires RCS leakage tests be performed at operating oressure (2155 psig) following normal openings.
1 The licensee indicates that RCS leakage testing requires operators to manually control RCS pressure at 2285 psig for up 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The reactor protection system (RPS) RCS high-pressure setpoint is 2355 psig.
Performance of the 9308190320 930802 PDR ADOCK 05000313 P
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Additionally, surveillance testing at the reduced pressure will demonstrate-the integrity of the RCS pressure boundary following normal openings in accordance with the ASME Boiler and Pressure Vessel Code.
Since the tests will be conducted in accordance with IWA-5000 of the 1980 Edition of the ASME Boiler and Pressure Vessel Code, which allows RCS leakage tests to be performed at nominal operating pressure (2155 psig), and since the nominal operating pressure reduces the likelihood of RPS actuation without reducing the safety margin, the staff concludes that the proposed changes are acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Arkansas State official was notified of the proposed issuance of the amendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. 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 occupational radiation
-exposure. The Commission has previously issued a proposed finding.that the amendment involves no significant hazards consideration, and there has.been no public comment on such finding (58 FR 30194). Accordingly, the 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 be prepared in. connection with the-issuance of the amendment.
5.0 CONCLUSION
The Commission has 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,- (2)Lsuch activities will be conducted. in compliance with the Commission'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:
V. Gaddy-Date: August 2,~ 1993 M