ML19332D206
| ML19332D206 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 11/20/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19332D204 | List: |
| References | |
| NUDOCS 8911300158 | |
| Download: ML19332D206 (2) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMIS$10N WASHINGTON,D.O S0006 5
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 40 ' TO FACILITY OPERATING LICENSE NO. NPF-47 GULF STATES UTILITIES COMPANY j
i RIVER BEND STATION, UNIT 1
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.c DOCKET NO. 50-458
1.0 INTRODUCTION
By letter dated June 23, 1989, Gulf States Utilities Company (GSU) (the licensee) requested an amendment to Facility Operating License No. NPF-47 for the River Bend Station Unit 1.
The proposed am u dment would add two J
Gould Type HE43 circuit breakers to Table 3.8.4.1-1 of the Technical Specifications. These circuit breakers would provido primary containmnt J
l conductor overcurrent protection for circuits providing power to two 480V receptacles in the drywell.
During the first refueling outage and previous outages, maintenance and construction work at River Bend Station required that temporary power cables be run into the drywell. To avoid running temporary power cables for outages, the licensee decided to provide two 480V receptacles in the l.
drywell to power tools and other temporary equipment during future outages.
2.0- EVALUATION GSU has proposed changes to the Technical Specifications to include two additional circuit breakers in Table 3.8.4.1-1, ' Primary Containment Penetration Conductor Overcurrent Protection Devices," These circuit i
breakers will feed 480V receptacles in the drywell to
)ower tools and l
otner temporary equipment during outages and require tie use of a contain-ment electrical penetration.
River Bend safety analysis report Secticn 8.3.1.1.4.3 states that containment electrical penetration assemblies are designed to withstand, without loss of mechanical integrity, the maximum fault current versus time condition which could occur because of single random failure of circuit overload protective devices.
Overload protection of el.ectrical protection 480V motor control center power circuits is provided by a series-connected molded case circuit breaker and fuse; each rated to open the circuit during overload conditions, thus providing redundant protection. The circuit protection design provided for the two receptacles in this proposed change conforms to these I
requirements. Also, the design is identical to the configuration for L
receptacle IPOP-WRZA01 already listed on Technical Specification Table
- 3. 8. 4.1 -1.
The new receptacles perform no safety-related function and no L
safety-related systems, other than the containment penetrations are l
affected by this modification. The conduit, cable and equipment associated with this modification are being installed in accordance with IEEE 384.
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r The NRC staff has reviewed the licensee's submittal and has found that the electrical penetration assembly for the two receptacles is designed l
to withstand without the loss of mechanical integrity, the_ maximum i
avtalable fault current versus time conditions that could occur given single random failures of circuit overload protective devices, as recommended i
by Regulatory Guide 1.63; thercfore, the staff finds that the proposed
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change is acceptable, j
3.0 ENVIRONMENTAL' CONSIDERATION f
The amendment. involves a change in requirements with respect to installation or use of a facility component. located within the restricted area as i
defined in 10 CFR Part 20. The staff has determined that the anendnent involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that i
there is no significant increase in individual or cumulative occupational radiation exposures. The Commission has previously issued a proposed finding that the anendment involves no significant hazards consideration and there has been no public comnent on such finding. Accordingly, the forth in 10 CFR Section 51.22(y' criteria for categorical exclusion set amendment meets the eligibilit c)(9). Pursuant to 10 CFR 51.22(b), no environnental'inipact statement or envirorn. ental assessment need be prepared in connection with the issuance of the amendment.
4.0 CONCLUSION
7 The staff has concluded, based on the considerations discussed above, that:
(1) there'is reasonable assurance that the health end safety of the l
will not be endangered by operation in the proposed manner, and (2) public such activities will be conducted in compliance with the Commission's regulations, l
and the issuance of the amendnent will not be inimical to the coninon defense and security or to the health and safety of the public. The staff therefore concludes that the proposed changes are acceptable.
Dated: November 20, 1989 Principal Contributor:
N. Trehan w
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