ML20077B341
| ML20077B341 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/08/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20077B330 | List: |
| References | |
| GL-90-05, GL-90-09, GL-90-5, GL-90-9, NUDOCS 9105140220 | |
| Download: ML20077B341 (2) | |
Text
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UNITED 8TATES
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NUCLEAR REGULATORY COMMISSION ra wAsHmoToN. o, c. rosas s,e....
I SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION 4
RELATED AMENDMENT NO.152 TO FACILITY OPERATING LICENSE NO. DPR 71 AND AMENDMENT NO.182 TO FACILITY OPERATING LICENSE NO. DPR-62 CAROLINA POWER & LIGHT COMPANY t
BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324
1.0 INTRODUCTION
By letter dated January (the licensee) submitted a request for changes to the 7, 1991, as supplemented April 9, 1991, the Carolina Power & Light Company Brunswick Steam Electric Plant (BSEP),-Units 1 and 2. Technical Specifications-(TS).- The April 9 1991 submittal forwarded typed TS pages and did not change the.initialdetermInationofnosignificanthazardsconsiderationaspublished in the Federal Register. The. requested changes would remove the existing visual inspection requirements and acceptance criteria associated with TS 3/4.7.5, Snubbers, and insert a refueling-outage-based examination schedule, as shown in Table 4.1-2 of Enclosure B in Generic Letter (GL) 90-09. Visual
. inspection Intervals, dated December 11, 1990.
2.0' EV,ALUATION V
-The snubber visual examination schedule in the existing TS is based on the-permissible' number of inoperable snubbers found during the visual examination.
Because the existing. snubber visual _ examination schedule is based only on the absolute number of inoperable snubbers found during the visual examinations irrespective of the total population of snubbers, licensees with a large snubber population find the visual examination schedule excessively restrictive. The purpose of the alternative visual examination schedule is to allow the licensee to perform visual examinations and corrective actions during plant outages without reducing the confidence level provided by the existing visual examination schedule. The new visual examination schedule specifies the permissible number of inoperable snubbers for various snubber populations. The basic examination interval is the r.ormal fuel cycle, up to 24 months.
Depending on the number of unacceptable snubbers found during the visuki examination, this interval may be-extended to as long as twice the fuel cycle or reduced to as short as two-thirds of the fuel cycle.
The examination interval may vary by 25 percent to coincide with the actual outage.
In the event that one or more snubbers are found inoperable during a visual examination, the-Limiting Conditions for Operation (LCO) in the pissent TS 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 9105140220 910508 PDR ADOCK 05000324 P
2 follow the appropriate action statement for that system.
This LCO will remain in the TS; however, the permissible number of inoperable snubbers and the subsequent visual examination interval will now be determined in accordance with the new visual examination schedule (Table 1 of GL 90-05, dated December 11,1990).
As noted in the guidance for this line item TS improvement corrective actions may have to be performed depending on the number of, certain inoperable snubbers found. All requirements for corrective actions and evaluat'ons associated with the use of the visual examination schedule as statedinfootnotes1through7ofTable1ofGL90-09,shallbeincludedin the TS.
The licensee has proposed changes to Specification 3/4.7.5 that are consistent with the guidance provided in GL 90-09 for the replacement of the snubber visual examination schedule with Table 1 (including footnotes 1 through
- 7) of GL 90-09. On the basis of its review, the staff finds that the proposed changes to the TS for BSEP are acceptable.
3.0 STATE CONSULTATION
in accordance with the Commission's regulations, the State of North Carolina.
State official was notified of the proposed issuance of the amendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes the Surveillance Requirements.
The NRC 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 si occupatlonalradiationexposure.gnificantincreaseinindividualorcumulative 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 (56 FR 4861). Accordingly, the amendment meets the eligibility criteria 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 amendment.
5.0 CONCLUSICH 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:
J. Rajan Date:
May 8, 1991
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