ML14175A839
| ML14175A839 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 10/12/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14175A838 | List: |
| References | |
| NUDOCS 8411080604 | |
| Download: ML14175A839 (3) | |
Text
UNITED STAT ES NUCLEAR REGULATORY COMMISSiON W ASHINGTON, 0. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 86 TO FACILITY OPERATING LICENSE NO. DPR-23 CAROLINA POWER AND LIGHT COMPANY H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 Introduction By letter dated January 9, 1984, the licensee s.ubmitted a request for a license amendment concerning Technical Specification (TS) revisions to correct errors and to achieve consistency within the TS. The changes concern the Automatic Feedwater (AFW) pump initiation. NRC Inspection Report 83-09 (IER 83-09), dated April 26, 1983, requested that the licensee clarify discrepancies between Table 3.4-1 and other existing AFW TS.
Evaluation The licensee has requested a revision in the H. B. Robinson Unit 2 Technical Specification Table 3.4-1 to require the AFW flow automatic initiation system be operable whenever the RCS is greater than 350'F.
Currently, the notes to Table 3.4-1 imply that the AFW pump automatic initiation feature is required above 200 0F whereas.TS 3.4.1 and Table 3.5-5 require operability of other AFW system components above 350oF. Therefore, the licensee requested that the temperature reouirement in Table 3.4-1 be changed to 350'F to be consistent with the other AFW TS requirements.
The 4 kV Bus undervoltage signal to start the turbine-driven AFW pump (Item 2) should also be operable under the same conditions. The only item in Table 3.4-1 which should not be under this temperature specification is the AFW actuation signal from trip of both main feedwater pumps (Item 5).
It should not be changed because this signal is defeated prior to securing both main feed pumps at no load temperature in order to prevent the undesirable condition of an AFW auto start and the subsequent steam generator blowdown valve auto closure.
We have reviewed the licensee's request and find that the requested changes would provide consistency within the Technical Specifications thus eliminating confusion due to two-temperature requirements. In addition, the change would be consistent with the Westinghouse Standard Technical Specifications, NUREG-0452. Therefore, the staff finds these changes acceptable.
841101604O 04101 PDR AD0C 05o00261
-2 Environmental Consideration This amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
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 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 this amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR Sec 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 this amendment.
Conclusion We have 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, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Dated:
October 12, 1984 Principal Contributor:
G. Requa
O ctober 12, 1984 D
B MEMORANDUM FOR:
James R. Miller, Chief ORB#l. Rdg Operating Reactors Branch #3 CParrish Division of Licensing Memo File FROM:
Steven A. Varga, Chief Jier Operating Reactors Branch #1 Siar Division of LicensingSVarga
SUBJECT:
REQUEST FOR PUBLICATION IN MONTHLY FR NOTICE - NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE Carolina Power and Light Company, Docket No. 50-261, H. B. Robinson Steam Electric Plant, Unit No. 2, Darlington, South Carolina Date of application for amendment:
January 9, 1984 Brief description of amendment:
The amendment would revise the Technical Specifications to correct inconsistencies regarding AFW pump automatic initiation.
Date of issuance:
October 12, 1984 Effective date: October 12, 1984 Amendment No. 86 Facility Operating License No. DPR-23. Amendment revised the Technical Specifications.
Date of initial notice in Federal Register:
March 22, 1984 (49 FR 10732)
The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated October 12, 1984 Significant hazards consideration comments received: No Local Public Document Room location:
Hartsville Memorial Library, Home and Fifth Avenues, Hartsville, South Carolina 29535
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