ML17221A418
| ML17221A418 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 09/11/1987 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17221A417 | List: |
| References | |
| NUDOCS 8709250307 | |
| Download: ML17221A418 (8) | |
Text
~ ~ Ip 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION FLORIDA POVER AND LIGHT COMPANY DOCKET NO. 50-389 flOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPFPATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION The U.S. Nuclear Regulatory Commission
<the Conmission's considering issuance of an amendment to Facility Operating License No. NPF-16, issued to Florida Power and Light Company, et al., (the licenseel
~or operation of the St. Lucie Plant, Unit No. 2, located in St. Lucie County, Florida.
The proposed amendment would add a special inspection region associated with the batwings of the steam generators.
Research conducted by the licensee and Combustion Engineering (CE) has concluded that augmented inspec-tion of the batwing area of the CE-designed model 3410 steam generators is necessary in order to monitor tube wear and to take remedial action, as neces-sary.
The wear is the result of out-of-plane vibration of the batwing supports.
The inspection n~ the remaininq tubes will continue to be governed by the current technical specification requirements.
The proposed change to the tech-nical specifications would be made in response to the licensee's application for amendment dated September 4, 1987, as supplemented by letter dated September ll, 1987.
Refore issuance of the proposed license amendment the Cooeission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Conmission's regulations.
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The Commission has made a proposed det~rmination that the request for amendment involves no significant hazards consideration.
Under the Comoission's regulations in 10 CFR 50.9R, this means that operation of the facility in accordance with the proposed amendment would not (1> involve a significant increase in the probability or consequences of an accident previously evaluated; or '2> create the possibility of a neo or different kind of accident from any accident previously evaluated; or (3) involve a siqnificant reduction in a margin of safety.
The licensee addressed the above three standards in the amendment application, as restated below:
(1>
Operation of the facility in accordance with -the proposed amendment would not involve a significant increase in the probability or conse-quences of an accident previously evaluated.
,The proposed amendment increases the surveillance requirements, for a defined area of tubes in the steam generators.
This inspection pattern ensures that the area within the steam generator tube bundle representing the highest likelihood of damage will always be examined.
The inspection of the remainder of the tube bundle will continue to be governed by the current technical specification requirements.
The probability of not detecting a steam generator tube problem becomes very low.
(P)
Use of the modified specification would not create the possibility o< a new or different kind of accident from any accident previously evaluated.
This modified specification applies to region of tubes in the steam generator of the specification.
Since no change the systems or components of the plant not create the possibility of a new or from any previously evaluated.
the inspection of a specific while maintaining the intent to the design or operation of are involved, this change will different kind of accident
(3)
Use of the modified speci<ication would not involve a significant reduction in a margin of safety.
The margin of safety involved in, steam generator tube inspection depends on the accuracy and completeness of the examination.
The wear mechanism seen at St. Lucie Unit 2 is we11I.-]defined and we'll within the capability n~ the inspe'ction techniques.
Using the pre-dictive models based upon experiments and ana~ysis, the area of con-.
cern is identified and will continuously he inspected.
The current
'Technical Specifications will be applied elsewhere in the steam generator to ensure [that] future problems (if any) are identified.
Therefore, this change will not'nvolve a significant reduction in a margin of safety.
The St. Lucie Plant, Unit No.
2 is scheduled for refueling in early October.
One of the requirements during refueling is to inspect steam generator tubes.
The existing technical specifications do,not address the recently identified need to inspect steam generator tubes in the batwing region of the steam generators where wear is occurring.
The proposed chanqe would add a special inspection region associated with the batwings, for the upcoming and all couture steam generator tube inspections, in order to fully characterize the region, monitor tube wear and take remedial action as necessary.
The inspection of the remaining tubes in the steam generators will he conducted per the existing technical specifications.
Although the wear is a long-term phenomenon which is expected to occur over the life of the steam generators, it fs prudent to take action now, during the early stages of the wear.
The staff has determined that failure to act in a timely manner would result in requiring the licensee to follow the existing technical specifications regarding steam generator tube sample selection and inspection.
The staff has further determined that the overall safety of the plant would be enhanced if the special inspection area was added to the technical specifications prior to the scheduled inspection.
The inspection of the steam generator tubes is one of the first major outage-related efforts undertaken because of the length of time that is required to inspect tubes during the outage.
Therefore, the Comnission has insufficient time to issue its usual 30-day notice of the proposed action for public cogent.
If the proposed determination becomes final, an opportunity for a hearing will be published in the FEDERAL REGISTER at a later date and any hearing request will not delay the effective date of the amendment.
If the Comnission decides in its final determination that the amendment does involve a significant hazards consideration, a notice of opportunity for a prior hearing will be published in the FEDERAL REGISTER and, if a hearing is granted, it will be held before any amendment is issued.
The Comnission is seeking public co+vents on this proposed determination of no significant hazards consideration.
Comnents on the proposed determination may be telephoned to Herbert Berkow, Project Director, Project Directorate II-2, by collect call to.(301) 492-7872, or submitted in writing to the Rules and Procedures Branch, Division of Rules and Records, Office of Administration, U.S. Nuclear Regulatory Cmefssion, Washington, D.C. 20555.
Written comnents may also be delivered to Room 4000, Maryland National Bank Building, 7735 Old Georgetown Road, Bethesda, Maryland from 8:15 a.m. to 5:00 p.m.
All comnents received by October 2, 1987 will be considered in
P C
li reaching a final determination.
A copy of the application and any comments received may be examined at the Coomission's Public Document
- Room, 1717 H
- Street, N.W., Washington, D.C.,
and at the Indian River Junior College Library, 3209 Virginia Avenue, Fort Pierce, Florida 33450.
Dated at Bethesda, Maryland, this 11th.
day of September, 1987.
FOR THE NUCLEAR PFGULATORY COMMISSION Herbert N. Berkow, Project Director PWR Project Directorate f2 Division of Reactor Proiects-I/II
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