ML20205F293
| ML20205F293 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 10/24/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205F285 | List: |
| References | |
| NUDOCS 8810280034 | |
| Download: ML20205F293 (3) | |
Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 17 TO FACILITY OPERATING LICENSE NO. NPF-58 THE CLEVELAND ELECTRIC ILLUMINATING COMPANY, ET AL.
PERRY NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-440 1.0 MTRODUCTION Technical Specification (TS) 3.8.4.1 of the Perry Nuclear Power Plant Unit 1 TS requires that all containment penetration conductor overcurrent protective devices shown in Table 3.8.4.1-1 shall be operable in operational conditions 1, 2 and 3.
TS 4.8.4.1 requires surveillance tests to be completed at 18 and 60 months to demonstrate operability of these devices.
By letter dated June 9,1988, The Cleveland Electric 111uminating Company, Duquesne Light Company (, Ohio Edison Compey, Pennsylvania Power Company and Toledo Edison Company licensees) submitted an application for amendment to the operating license for the Perry Nuclear Power Plant, Unit 1.
The proposed amendrrent would delete spare circuit breakers from Table 3.8.4.1-1 of the Perry Unit 1 TS. These breakers were originally connected to motor operated valve space heaters used during construction which have since been disconnected.
They are no longer connected to any load inside or outside containment. The proposed amendaent would also correct three typographical errors in the table.
2.0 EVALVATION General Design Criterion 50 "Containment Design Basis" requires, in part, that the reactor containment structure, including penetrations, shall be designed so that the containment structure can accomodate, without exceeding the design leakage rate, the calculated pressure, temperature, and other environmental conditions resulting from any Loss-of-Coolant Accident. When a load is connected to a circuit passing through an electrical penetration, the potential exists for an electrical fault inside containment to result in e penetration seal failure, such that a breach of containnent might occur. When such a potential exists, the associated penetrations are provided with protection devices, such as circuit breakers.
The licensees have identified 17 circuit breakers in Table 3.8.4.)~1 which are "spares". These circuit breakers were left in the table by the licensees during Technical Specification development, to pe. nit future plant modifications using these circuit breakers without requiring a TS change.
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. However, the licensees now feel that it is more beneficial to remove the spare circuit breakers from the table, thereby decreasing the required amount of surveillance testing. The licensees further believe that the majority of future modifications that could use these circuit breakers would require additional TS changes, and therefore, adding the circuit breakers onto the Table at that time would not be a problem.
The staff has reviewed electrical drawings for the Perry 120 volt electrical system and has verified that the circuit breakers designated by the licensees as "spares" are, in fact, unconnected to any electrical load inside or outside containment. Therefore, they are not required to function as protection devices and may be removed from the Table. The staff notes that prior to proposing future TS changes which would utilize any of these circuit breakers as containment penetration conductor overcurrent protection oevices in Table 3.8.4.1-1, operability must be demonstrated.
With regard to the typographical error on the Table, the licensees have indicated that the correct circuit number for circuit breaker 1R25-5043-CB21 is IC41-B8XB vice B9XB. The other typographical errors involve the last entry on the first page of Table 3.8.4.1-1 (TS page 3/4 8-23).
The load circuit and primary circuit breaker listed are IF42-B3X and 1R25-5097-CB3, respectively. However, this circuit and breaker does not supply power through any containment penetration.
The correct numbers should be 1F42-B4X and 1R25-5097-CB4 This circuit and breaker supplies power to the space heater for the fuel +.ransfer equipment hydraulic supply panel in containment, and as such is a containment penetration conductor overcurrent protective device.
The ifcensees have indicated that the circuit breaker has not been energized curing plant operations.
It has been included in the surveillance test instructions required by TS 4.8.4.1.
The licensees have further indicated that these surveillance tests will be perforned prior to energizing the circuit that includes this breaker.
Energi-zation of this circuit and breaker will be required in order to utilize the fuel transfer equipment, in preparation "or the upcoming first refueling outage. Testing of this equipment could begin as early as October of 1988.
Following completion of this testing, the space heater circuit will continue to be energized during plant operations.
The staff has reviewed the licensees proposed corrections of typographical errors on Table 3.8.4.1-1 and finds them to be acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change to a requirement with respect to the instal-lation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or a change to a surveillance requirement. 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
3 rgleased offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Comission has previously issued a proposed finding that this arnendment involves no significant hazards consideration and there has been no pv511c coment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forthin10CFR51.22(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 this amendment.
4.0 CONCLUSION
The staff 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 inanner, and (2) such activities will be conducted in compliance with the Comission's regulations and the issuance of this amendment will hot be inimical to the corrrnon defense and security or to the health and safety of the public.
Principal Contributor: T. Colburn Dated:
October 24, 1988 4