ML20045E045
| ML20045E045 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/24/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20045E044 | List: |
| References | |
| NUDOCS 9307010027 | |
| Download: ML20045E045 (2) | |
Text
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t UNITED STATES
!I
,j NUCLEAR REGULATORY COMMISSION
's WASHINGTON, D.C, 20666 4 001
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SAFETY EVALUATION BY THE OFFICr 0F NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.186 TO FACILITY OPERATING LICENSE DPR-57 GEORGIA POWER COMPANY. ET AL.
EDWIN I. HATCH NUCLEAR PLANT. UNIT 1 DOCKET N0. 50-321
1.0 INTRODUCTION
By letter dated November 18, 1991, Georgia Power Company, et al. (the licensee), proposed a license amendment to change-the Technical Specifications (TS) for the Edwin I. Hatch Nuclear Plant, Unit 1.
The proposed change.would revise the TS to reflect the as-built plant condition and to resolve the NRC;~
staff's concern identified during the 1991 Electrical Distribution System Functional Inspection. The proposed change would only update the TS to t
accurately reflect the function of the emergency bus undervoltage relays.
It does not change the surveillance and operability requirements of its relays.
The original design required a loss of voltage on both the emergency 4160 V bus and the alternate power supply fed from IC startup transformer (SUT IC) before the loss of offsite power (LOSP) relay would trip the offsite power breaker, allowing the emergency diesel generator (EDG) breaker to close and supply the emergency bus. The original design, as reflected in the previous TS Tables 3.2-13 and 4.2-13, refers to " loss of voltage" relays monitoring voltage on SVT 1C and provides a permissive for the diesel generator output breaker to close. Design Change Request (DCR) 82-34, implemented in 1983, modified the undervoltage relay logic and removed the contacts from the auxiliary relays controlled by the SUT IC undervoltage relays from the LOSP lockout relay circuit. According to this design, the circuit would only require a loss of voltage signal from the emergency bus to trip the LOSP lockout relay and allow the emergency diesel generator breaker to close.
2.0 EVALUATION The licensee has proposed to delete the previous TS Tables 3.2-13 and 4.2-13.
These Tables list surveillance requirements for the SUT IC undervoltage relays and state that these relays " initiate energization of onsite power sources."
The current design, implemented in 1983, removed from the LOSP lockout relay circuits the contacts from the auxiliary relays controlled by the SVT IC undervoltage relays. According to this design, the circuit would only require a loss of voltage signal from the emergency bus to energize the LOSP lockout relays and allow the diesel generator output' breaker to close.
Because these relays nf;i longer input to the LOSP lockout relays circuitry, the licensee has proposed to delete these Tables from the TS. The staff finds this change acceptable.
9307010027 930624 PDR ADOCK 05000321 P
2-i The licensee has also proposed to change the titles of Tables 3.2-12 and i
4.2-12 to agree with the titles of the corresponding Unit 2 tables; page 11; the table on page 3.2-1; and the Bases Section in support of the above i
described changes. The staff finds these administrative changes acceptable.
Based on its review of the licensee's submittal, the staff finds that the proposed TS revision does not change the surveillance and-operability requirements of.the undervoltage relays, has no adverse impact on safety, and does not pose an undue risk to public health and safety. Therefore, the TS revision is acceptable.
j
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Georgia State official was notified of the proposed issuance of the amendments. The-State official l
had no comments.
i
4.0 ENVIRONMENTAL CONSIDERATION
1 The amendment' changes a requirement with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR j
Part 20 and changes surveillance requirements. The NRC staff has determined 1
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 (57 FR 20511 dated May 13,1992). Accordingly,.the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant l
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) such 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: N. K. Trehan Date: June 24, 1993 4
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