ML20081K542
| ML20081K542 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 06/18/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20081K541 | List: |
| References | |
| NUDOCS 9106280102 | |
| Download: ML20081K542 (3) | |
Text
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UNITED STATES (k'f i NUCLEAR REGULATORY COMMISSION d$
(%....f f WA$mNGTON. o C. TM6 SAFETY EVALUATION BY THE OFFICE OF NHC FAR REACTOR REGULATION RELATED TO AMENDMENT NO. 88 TO FACILITY OPERATING LICENSE NpF-35 AND AMENDMENT NO. 82 TO FACILITY OPERATING LICENSE NPF-52 DUKE POWER COMDANY, ET AL.
CATAWPA NUCLEAR STATION. UNITS 1 AND 2 DOCKET NOS. 50 413 AND 50-414
1.0 INTRODUCTION
By letter dated April 2,1991, the Duke Power Ccmpany (the licensee) submitted a request for changes to the Catawba Nuclear Station, Units 1 and 2, Technical Specifications (TSs). The requested changes would revise the visual inspection requirements for snubbers in TS 4.7.8 in response to the guidance provided in the NRC's Generic Letter 90-09, " Alternative Requirements for Snubber Visual Inspection Intervals and Corrective Actions."
l 2.0 EVALUATION The present sr.ubber visual examination schedule in the TSs is based on the number of inoperable snubbers identified in the previous visual examiaation.
The schedule is determined only by the absolute number of the inoperable snubbers discovered during the previous visual examination and does not depend on the size of the snubber population.
Therefore, licensees with a large snubber population find the schedule excessively restrictive.
Generic Letter 90-09 provides an acceptable alternative visual examination schedule permitting licensees to perform visual examinations and corrective actions during refueling outages without disturbing the confidence level provided by the existing surveillance requirements. The basic examination I
interval is the normal fuel cycle up to 24 months.
This interval may be extended to as long as twice the fuel cycle or reduced to as small as two-thirds of the fuel cycle depending on the number of unacceptable snubbers found during the visual examination. The examination interval may vary by 125 percent to coincide with the actual outage.
If one or more snubbers are found inoperable during a visual examination, the Limiting Conditions for Operation (LCO) in the present TSs require the licensee to restore or replace the inoperable snubber (s) to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or declare the attached system inoperable and follow the appropriate action statement for that system.
This LCO will remain in the TSs, However, the permissible number of inoperable snubber (s) and the subsequent visual examination interval will now be determined in accordance with the new visual examination schedule (proposed TS Table 4.7-2).
As noted in the guidance of Generic Letter 90-09 for this line item TS improvement, certain corrective actions may have to 9106200102 910618 PDR ADOCK 05000413 p
i 2
be performed deperming on the number of inoperable snubbers found. All require-ments for corrective actior.s and evaluations associated with the use of the 1
visual examination schedulc and those stated in Footnotes 1 through 7 (Table 1 of Generic Letter 90-09) are proposed to be included in the TSs.
The licensee has proposed changes to TS 3/4.7.8 that are consistent with the guidance provided in Generic Letter 90-09 for the replacement of the snubber visual examination schedule with Table 1 (including Footnotes 1 through 7) of Generic Letter 90-09.
The NRC staff has reviewed the proposed amendments, and finds that the proposed changes to the TSs for Catawba 1 and 2 are acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the South Carolina State official was notified of the proposed issuance of the amendments.
The State officiel had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendments change requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change surveillance requirements.
The NRC staff has determined that the amendment; involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released off site, 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 (56 FR 20033). Accordingly, the amendments meet the eligibility criterio 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 the amendments.
5.0 CONCLUSION
l 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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
H. Shaw u te:
June 18, 1991 I
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s O 199I DATED:
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AffEtiD!!Etil f 0. 88
';1LITY OPEltATitiG lICEllSE fiPF Catawba liuclear Station, Unit 1 n,
AtiltiDt'Elli 140. 82 10 F A ' C. T'"iATiliG LICEtiSE tiPF Catawba lluclear Station, Unit 2 DIST Ril;UT 10f!:
IIliiTITTi1e f1RC f. Local PDRs PD 11-3 R/F Catawtia R/f i
S. Varga 14-L-4 G. Lainas 14-H-3 i
D.11a t thews 9-H-3 R. Ingram 9-H-3 j
R. fiartin 9-H-3 OGC-WT 15-l:-18 i
D. Hagan tillBB 470?
G. Hill (8)
Pl-37 W. Jones lif4BD 7103 C. Grimes ll-F-22 ACRS (10)
P-135 GPA/PA 17-F-2 OC / '.f t1B 11NBD 470?
L. Reyes Rll H. Shaw 7 E-23
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