ML20213G542
| ML20213G542 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 11/12/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20213G533 | List: |
| References | |
| NUDOCS 8611180193 | |
| Download: ML20213G542 (4) | |
Text
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UNITED STATES k
O NUCLEAR REGULATORY COMMISSION j
g WASHINGTON, D. C. 20555 e
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT N0. 87 TO FACILITY OPERATING LICENSE N0. DPR-61 CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT DOCKET N0. 50-213
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1.0 INTRODUCTION
By letter dated September 4, 1986, the Connecticut Yankee Atomic Power Company (CYAPC0) submitted a request for changes to the Haddam Neck Plant technical specifications concerning inservice inspection of a
reactor coolant pump flywheels.
This license amendment modifies Section 4.10.C of the technical specifications to incorporate inservice inspection surveillance requirements for the reactor coolant pump (RCP) flywheels consistent with the guidance found in Regulatory Guide 1.14, Revision 1.
In particular, this amendment would increase the frequency of each pump flywheel inspection to include an ultrasonic volumetric examination of the bore and keyway areas at approximately 3-year intervals and a surface examination and 100% volumetric examination at approximately 10-year intervals. The present technical specifications require only a surface examination and volumetric examination of only one reactor coolant pump every second outage.
A Notice of Consideration of Issuance of Amendment to License and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing related to the requested action was published in the Federal Register on October 8, 1986 (51 FR 36086). No comments or requests for hearing were received.
8611180193 861112 DR ADOCK 05000213 PDR
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- 2.0 EVALUATION The flywheels on reactor coolant pump motors provide inertia to ensure a slow decrease in coolant flow in order to prevent fuel damage as a result of a loss of power to the pump motors. During operation at nonnal speed, a flywheel has sufficient kinetic energy to produce high-energy missiles and excessive vibration of the reactor coolant pump assembly if the flywheel should fail. The technical specifications currently require the licensee to perform a surface examination and volumetric examination of one RCP flywheel every other outage as a means of minimizing the potential for failures of the flywheels of the reactor coolant pump motors.
By letter dated September 4,1986, CYAPC0 requested a modification of the Haddam Neck Plant technical specifications to incorporate a requirement for a more comprehensive inspection program for the RCP flywheels consistent with the guidance of Regulatory Guide 1.14, Regulatory Position C.4.b.
More specifically, the inservice inspection of each RCP flywheel will include:
(1) An in-place ultrasonic volumetric examination of the areas of higher stress concentration at the bore and keyway at approximately 3-year intervals during the refueling or maintenance shutdown coinciding with the inservice inspection schedule as required by Section XI of the ASME Code.
(2) A surface examination of all exposed surfaces and complete ultrasonic volumetric examination at approximately 10-year intervals during the plant shutdown coinciding with the inservice inspection schedule as required by Section XI of the ASME Code.
- (3) Examination procedures should be in accordance with the requirements of Subarticle IWA-2200 of Section XI of the 1
ASME Code.
(4) Acceptance criteria should conform to the recommendations of Regulatory Guide 1.14, Revision 1, Regulatory Position C.2.f.
(5) If the examination and evaluation indicate an increase in flaw size or growth rate greater than predicted for the service life of the flywheel, the results of the examination and evaluation should be submitted to the staff for evaluation.
The staff has reviewed the licensee's request and concludes that the proposed license amendments meets all current regulatory criteria for the inservice inspection of reactor coolant pump flywheels. The staff, therefore, concludes that the proposed change is acceptable.
3.0 ENVIRONMENTAL CONSIDERATI0!!
This amendment involves a change to a requirement with respect to the installation or use of facility components located within the restricted i
area as defined in 10 CFR Part 20 and changes to the surveillance 5
requirements. The 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 significant increase in individual or cumulative occupational radiation i
exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, this 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 this amendment.
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4.0 CONCLUSION
The staff 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, and (2) 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.
5.0 ACXNOWLEDGEMENT This Safety Evaluation has been prepared by F. Akstulewicz.
Dated:
November 12, 1986
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