ML17229A659
| ML17229A659 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 02/25/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17229A658 | List: |
| References | |
| NUDOCS 9803110266 | |
| Download: ML17229A659 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 S
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-6 OS OC 0-335 50-389 By letter dated August 22, 1997, Florida Power and Light Company (the licensee) submitted a request for changes to the St. Lucie Plant, Units 1 and 2 Technical Specifications (TS). The proposed changes would remove the requirements for inservice testing of pumps and valves from Specification 4.0.5 and replace it with an equivalent administrative requirement in Section 6 of the Technical Specifications (TS). The requirement for "specific written approval" of relief where Code requirements are impractical is eliminated in deference to the approval requirement stated in 10 CFR 50.55a.
The proposed amendment also provides conforming changes to several Surveillance Requirements to change the reference from Specification 4.0.5 to the Inservice Testing Program.
Changes to the Bases reflecting these changes were also submitted.
2.0 CG OU D
The April 7, 1995, revised version of the Standard Technical Specifications (STS) (NUREG-1432), relocates the inservice testing requirements to the administrative controls section of the TS. NUREG-1482, "Guidelines for Inservice Testing at Nuclear Power Plants," Chapter 6, recommends that licensees revise their TS to incorporate the revised STS for inservice testing programs.
I The licensee has proposed to revise TS 4.0.5.a to delete reference to inservice testing of pumps and valves and relocate the requirement for an inservice testing program to TS 6.8.4.i. TS 4.0.5.b and c have been deleted and the requirements relocated to TS 6.8.4.i. These revisions were based on the guidance of NUREG-1482 and NUREG-1432, Revision 1. Section 5.5 of the revised STS contains the requirements for the inservice testing program. This TS provides, in part, the definition of surveillance intervals for inservice testing of pumps and valves and the applicability of TS 4.0.2 for surveillance interval extensions.
This change to the licensee's TS is consistent with the revised STS and the intent of the regulatory guidance in NUREG-1482. The inservice testing requirements are given in 10 CFR 50.55a, which the licensee documents via its 10-year interval program requirements.
This change is acceptable since the regulatory requirements are delineated in 10 CFR 50.55a, and the change eliminates inconsistencies between the TS and the regulations.
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In the markup of the current TS pages, the licensee proposed to add the words "and testing" in TS 4.0.5.a and to the Bases for 4.0.5 to denote the inservice inspection program.
The licensee's intent was to provide clarification that the inservice inspection program included system pressure testing.
However, the NRC staff determined that the addition of the words "and testing" could lead to confusion with the inservice testing program, which was being relocated as described above.
Therefore, the existing wording for the inservice inspection program was retained in TS 4.0.5.a and in the Bases for 4.0.h. The words "and testing" were also deleted from the first line of TS 4.0.5 and from TS 4.0.5.d to avoid similar confusion.
Revisions were proposed throughout Units 1 and 2 TS to change the reference for testing of pumps and valves from Specification 4.0.5 to the Inservice Testing Program.
This revision is an administrative change and is necessary because inservice testing of pumps and valves will no longer be governed by TS 4.0.5 but by the Inservice Testing Program.
Therefore these changes are acceptable.
Changes to the Bases to conform to these changes were also submitted.
The NRC staff has no objection to the changes to these Bases.
40S CO SU TO Based upon the written notice of the proposed amendments, the Florida State official had no comments.
5.0 S
These amendments change a surveillance requirement'with respect to installation or use of a facilitycomponents located within the restricted area as defined in 10 CFR Part 20. The US Nuclear Regulatory Commission staff has determined that the amendments involve 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 amendments involve no significant hazards consideration.and there has been no public comment on such finding (62 FR 50006). Accordingly, these amendments meet the eligibilitycriteria 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 these amendments.
The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public willnot be endangered by operation in the proposed manner, (2) such activities willbe conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments willnot be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
L. Wiens Date: Febr uar y 25, 1998
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