ML20050D993
| ML20050D993 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/16/1982 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20050D980 | List: |
| References | |
| NUDOCS 8204120451 | |
| Download: ML20050D993 (3) | |
Text
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UNITED STATES y
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aj wasmNGTON, D. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 48 TO FACILITY OPERATING LICENSE NO. DPR-66 DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY BEAVER VALLEY POWER STATION, UNIT NO. 1 DOCKET NO. 50-334 INTRODUCTION Duquesne Light Company, by letter dated November 9,1981, requested changes to the Appendix A Technical Specifications for Beaver Valley Power Station, Unit No. 1.
The changes modify the inspection requirements for the reactor vessel nozzle to safe end welds and updates the ASME code reference for steam generator tube inspections.
DISCUSSION AND EVALUATION The licensee has requested to change Technical Specification 4.4.10b which reads:
b.
At the second and third refueling outages dye penetrant inspections shall be performed on all six nozzles and volumetric inspections shall be performed on at least two nozzles in the same manner as the baseline inspections so that all six nozzles shall be volumetrically inspected during the first three refueling outages.
to the following:
b.
At the second refueling outage, a dye penetrant examination shall be performed on all six nozzle to safe end welds and an ultrasonic examination shall be performed on all six nozzle-to-safe end welds l
from the outside diameter.
At the third refueling outage, a dye penetrant examination shall be performed on all six nozzle to safe end welds and an ultrasonic examination shall be performed on all six nozzle-to-safe end welds from the outside diameter. Ultrasonic examination shall be performed on the three outlet nozzle-to-safe end welds from the inside diameter.
8204120451 820316 PDR ADOCK 05000334 p
Licensee Basis for Requesting Change Dye penetrant examinations have been performed on all six reactor vessel nozzles and volumetric examinations have Been performed on two of the nozzles with no reportable defects found. The alternate examination methods and frequency proposed by the change will provide sufficient data to detect nozzle-to-safe end defects, minimize the num6er of core barrel lifts that must be made to perform the examinations and will reduce the personnel radiation exposure related to this task.
Evaluation The alternate examinations proposed by the licensee have been evaluated and found to be beyond Section XI requirements. The proposed examinations will reduce personnel exposure to radiation and enhance the effectiveness of the nozzle-to-safe end weld examinations. We therefore find the Technical Specification change acceptable.
The licensee has requested to change Technical Specification Section 4.4.5.2 to read:
...In Article 8
" Eddy current examination method for installed non-ferromagnetic steam generator heat exchanger tubing," as contained in ASME Boiler and Pressure Vessel Code, Seciton V -
" Nondestructive Examination," and referenced in ASME Boiler and Pressure Vessel Code - Appendix IV of the 1980 Edition through Winter 1980 Addenda of Section XI
" Inservice Inspection of Nuclear Power Plant Components." The tubes...
l, Licensee Basis for Requesting Change The Technical Specifications presently recognize the ASME Section XI 1974 Edition through the 1975 Summer Addenda, a review of the ASME Section XI Appendix IV Summer 1976 Addenda has been performed and it was found that the newer edition is the first time that inservice inspection of installed steam generator tubing is addressed, therefore, the new edition must be referenced to satisfy the Technical Specification surveillance requirements. The Inservice Inspection program pertaining to steam generator tube inspection will then be revised to comply with the newer edition, Appendix IV of ASME Section XI Summer 1976 Addenda.
Evaluation The original request was to update to the Summer 1976 Addenda of the 1974 Edition of Section XI for reasons explained above. The 1980 Edition is more complete in requirements for steam generator tube examination than the Summer 1976 Addenda of the 1974 Edition of Section XI. The 1980 Edition contains
. ~
requirements for examination of personnel and referencesSection V for examination method requirements. The 1980 Edition through. Winter 1980 Addenda was recently approved 5y the NRC and incorporated in paragraph (b) of 10 CFR 50.55a. The licensee agreed to use the lE8a Editton of Section XI for steam generator tube examination in lieu of the 1976 Winter Addenda of the 1974 Edition of Section XI. The staff finds this change acceptable.
ENVIRONMENfAL CONSIDERATION We have determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 551.5(d)(4), that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
CONCLUSION We have concluded, based on the considerations discussed above, that:
(1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in com-pliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Date:
March 16,1982