ML20118B070
| ML20118B070 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/21/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20118B067 | List: |
| References | |
| GL-90-09, GL-90-9, NUDOCS 9209290376 | |
| Download: ML20118B070 (3) | |
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SAFETY EVALVATION BY THE OFFICE OF NUCLEAR R(ACTOR REGULATION RELATED TO AME@MNT N05.171 AND 173 TO FAClllTY OPERATIE LICEN.5E NOS. DPR-44 and DPR-56 PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPAN1 ATLANTIC CITY ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION. UNIT N05. 2 AND 3 DOCKET N05, 50-277 AND 50-278
1.0 INTRODUCTION
By letter dated August 5, 1992, and supplemented by letter dated September 11, 1992, the Philadelphia Electric Company (PEco or the licensee) submitted a request for changes to the Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, Technical Specifications (TS).
The requested changes would revise TS Section 4.11.D a..d the associated Bases to incorporate the recommendations on snubber visual inspection frequencies contained in Generic Letter (GL) 90-09,
" Alternative Requirements for Snubber Visual Inspection Intervals and Corrective Actions" dated December 11, 1990.
Specifically, the revisions would remove the snubber visual examination schedule in the existing TS and replace it with a refueling outage based visual examination schedule as listed in Table 1 of GL 90-09.
The information provided in the supplemental letter was not outside the scope of the original Federal Reqister notice and did not change the initial no significant hazards consideration determination.
2.0 EVALVATION The snubber visual examination schedule in the existing Technical Specifications is based on the permissible, umber of inoperable snubbers found during the visual examination. Because the existing snubber visual examination schedule is based only on the a%olute number of inoperable snubbers founti during the licensees visual examination regardless 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 reduction of the confidence level provided by the existing visual examination schedule.
The new visual examination schedule specifies the permissibh:
number of inoperable snubbers for various snubber populations.
The basic examination interval is the normal _ fuel cycle up to 24 months.
This interval may be extended to as long as twice the fuel cycle depending on the number of 9209290376 920921 PDR ADDCK 05000277 P
' acceptable snubbers found during the visual examination.
The examination interval may vary by 125 percent to coincide with the actual outage.
In the event one or more snubbers are found inoperable during a visual examinat an, the Limiting Condition for Operation (100) in the present 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 ino(perable and follow the appropriate tction statement for that system.
This LCO will remain in the TS; however, the permissible number of inoperable snubber (s) and the subsequent visual inspection interval will now be determined in accordance with the visual examination schedule (Table 1 of Generic Letter 90-09, dated December 11,1990). As noted in the guidance for this line item TS improvement, c3rtain corrective actions may have to be performed depending on the number of inoperable snubbers found. All requirements, for corrective actions and evaluations associated with the use of-the visual examination schedule and stated in the footnotes 1 through 7 (Table-] of Generic Letter 90-09), shall be included-in the TS.
The licensee has provided changes to Specification 4.11.0 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. On the basis of its review of this matter, the staff finds that the proposed changes to the TS for Peach Bottom Atomic Power Station, Units 2 and 3 are acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendments.
The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendments change 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 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 (57 FR 37570). Accordingly, the amendments meet 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 amendments.
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5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health am' safety of the public will.not be endangered by operation in the proposed nannar, (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:
J. Rajan Date: September 21, 1992 W
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