ML17229A493
| ML17229A493 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 10/02/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17229A492 | List: |
| References | |
| NUDOCS 9710080252 | |
| Download: ML17229A493 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATiON RELATED TO AMENDMENT NO.
TO FACILITY OPERATING LICENSE NO.
NPF-16 FLORIDA POWER AND LIGHT COMPANY ST.
LUCIE PLANT UNIT NO.
2 DOCKET NO. 50-389
- 1. 0 INTRODUCTION By letter dated August 1, 1997, Florida Power and Light Company (FPL or licensee) requested changes to the St. Lucie Unit 2 Technical Specifications (TS) to modify the surveillance interval for certain Engineered Safety Features Actuation System (ESFAS) subgroup relays.
Specifically, the semi-annual surveillance interval specified in Table 4.3-2 for testing the ESFAS subgroup relays would be extended to a refueling interval consistent with Combustion Engineering Owners Group (CEOG) Report CEN-403. Revision 1-A,
- March, 1996.
The Bases would also be revised to include guidance for evaluating the adequacy of the ESFAS relay surveillance interval.
2.0 BACKGROUND
The Nuclear Regulatory Commission (NRC) staff formed a Task Group in August 1983 to investigate problems concerning surveillance testing requi red by TS.
and to recommend approaches to effect improvements.
As a result of the recommendations of this Task Group. the Technical Specifications Improvement Program (TSIP) was established in December 1984.
As an element of the TSIP.
TS surveillance requi rements were comprehensively examined.
The study found that. while some testing at power is essential, safety can be improved, equipment degradation decreased.
and unnecessary personnel burden prevented by reducing the amount of testing at power.
The CEOG requested ABB-CE to perform generic comparative analyses of ESFAS subgroup relay performance in Combustion Engineering (CE) Nuclear Steam Supply System (NSSS) plants.
The CEOG Topical Report, CEN-403. Revision 1-A. was prepared to justify extending, the surveillance test interval for ESFAS subgroup relays used in CE plants.
and documents an analysis of subgroup relay performance which included the St. Lucie Unit 2 ESFAS.
This effort resulted in the CEOG recommendation that the applicable subgroup relays be tested at a
minimum required.frequency of once per fuel cycle.
The type of relays employed in the St. Lucie Unit 2 Auxiliary Feedwater Actuation System (AFAS).
which is a separate system performing the ESFAS functions for auxiliary feedwater.
was not included in the relay failure analysis reported in CEN-403.
In a Safety Evaluation (SE) dated February 27, 1996. the NRC staff found the CEOG topical report acceptable.
and further concluded that licensees referencing the report as a basis for proposed TS changes should:
(1) confirm applicability of the CEN-403, Rev.
1, analyses for their plant.
and 97i0080252 97i002 PDR ADOCK 05000389 P
(2) confirm that the applicable setpoint calculations account for any increase in instrument drift caused by the extended test interval.
In addition, the staff determined that if two or more ESFAS subgroup relays fail in a 12-month period. the licensee should consider the design, maintenance.
and testing of all ESFAS subgroup relays to evaluate the adequacy of the surveillance interval. If the licensee determines that the surveillance interval is inadequate for detecting a single relay failure, the surveillance interval should be decreased such that the licensee can detect an ESFAS subgroup relay failure prior to occurrence of a second failure.
3.0 EVALUATION The licensee's proposed changes to the TS are in accordance with the recommendations contained in CEN-403.
Rev.
1 and the guidance contained in the February 27.
1996.
SE.
The specific changes are addressed below.
Revisions to TABLE 4.3-2.
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS, were proposed as follows:
(1)
The surveillance frequency notation shown for the Automatic Actuation Logic CHANNEL FUNCTIONAL TEST applicable to Safety Injection (SIAS),
Containment Isolation (CIAS), Main Steam Isolation, and Containment Sump Recirculation (RAS), is to be changed to read "R(3)."
(2)
Footnote (3) is to be added to describe the ESFAS subgroup relay test.
which "shall be performed on a
STAGGERED TEST BASIS at subintervals of 6 months, such that each subgroup relay is tested at least once per 18 months."
(3)
Footnote (2). which will continue to apply to the Auxiliary Feedwater (AFAS) Automatic Actuation Logic, is to be revised to more accurately reflect terminology associated with AFAS.
Bases 3/4.3. 1 and 3/4.3.2, REACTOR PROTECTIVE AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEMS INSTRUMENTATION. is to be"revised to include a new paragraph which provides additional information relative to evaluating the adequacy of ESFAS subgroup relay testing.
In the August 1, 1997, submittal, the licensee confirmed that the relay data presented in CEN-403, Revision 1-A, was applicable to St. Lucie Unit 2.
Two minor discrepancies were identified in the data contained in the report.
The NRC staff reviewed these discrepancies and confirmed that they did not affect the conclusions of the SE.'he licensee also confirmed that setpoint uncertainty calculations would not be affected by the surveillance interval extension.
Finally, in accordance with the guidance in the staff's SE, the Bases was revised to include information relative to evaluating the adequacy of ESFAS subgroup relay testing.
On the basis of our review of the above items, the staff concludes that the proposed changes are in accordance with the guidance in CEOG Report CEN-403,
II Revision 1-A and the associated NRC SE.
Therefore, the staff finds these changes acceptable.
4.0 STATE CONSULTATION
Based upon the written notice of the proposed amendments, the Florida State official had no comments'.
0 ENVIRONMENTAL CONSIDERATION These amendments change surveillance requirements.
The NRC 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 45457).
Accordingly. these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51 '2(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments' CONCLUSION The Commission has concluded'ased 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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
Len Wiens Date:
pc<aber 2, 1997
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