ML19345A480
| ML19345A480 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 05/03/1977 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19345A475 | List: |
| References | |
| NUDOCS 8011210709 | |
| Download: ML19345A480 (2) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
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.s SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AfENDfENT NO. N TO FACILITY OPERATING LICENSE NO. DpR-3 YANKEE ATOMIC ELECTRIC COMPANY YANKEE NUCLEAR POWER STATION (YANKEE-ROWE)
DOCKET NO. 50-29 Introdection By application dated December 9,1976, Yankee Atomic Electric Company (the licensee) proposed a change in the Technical Specifications appended to License No. DPR-3 for the Yankee-Rowe reactor. The proposal involves deletion of the requirement for visual inspections of the reactor coolant system of Section 4.4.5.2.e. in the Technical Specifications.
Evaluation Following the issuance of Section XI of the ASME Boiler and Pressure Vessel cme on January 1,1970, the licensee adopted an inservice inspection a agram for components within the reactor coolant pressure boundary consistent with the code requirements and compatible with the "as built" conditions of the plant. On June 29, 1971, the Commission published the Interim Policy Statement on Interim Acceptance Criteria (IAC) for emergency core cooling systems (ECCS).
The IAC required in part interim improvements of operating techniques as are practical and worthwhile in improving ECCS performance er reliability, including augmentation of the inservice inspection program and implementation of measures for the detection and reduction of reactor coolant system leakage. To meet these provisions in the IAC, the licensee augmented and accelerated the inservice inspection program and proposed Technical Specifications to reduce reactor coolant system leakage.
In addition, the licensee committed to enter the containment twice a week for visual inspections of accessible portions of the reactor cooling system.
The current Technical Specifications include the approved inservice inspection requirements and the limiting condition for operation relating to allowable reactor coolant system leakage.
The licensee's commitment to the interim measure involving visual inspections of the reactor cooling system was incorporated in the current new format Technical Specification as a surveillance requirement.
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l 2-The specified inservice inspection program for the Yankee-Rowe reactor coolant system ensures that the structural integrity of these components will be maintained at an acceptable level throughout the life of the plant.
The specified reactor coolant system leakage detection systems have previously been found to be acceptable for Yankee-Rowe and are consistent with methods indicated in Regulatory Guide (R.G.) 1.45 " Reactor Coolant Pressure Boundary Leakage Detection Systems". While R.G. 1.45 advises prudent selection of detectibn methods it does not prescribe any visual inspections.
In addition we find that deletion of visual inspections will eliminate unnecessary containment entries through the personnel airlock which might adversely affect the airlock seal integrity. We have concluded that the proposed deletion of visual inspections does not involve a reduction in the required level of safety of this facility and is therefore acceptable.
Environmental 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 te endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance 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.
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