ML20210Q055
| ML20210Q055 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/02/1986 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210Q042 | List: |
| References | |
| NUDOCS 8605130596 | |
| Download: ML20210Q055 (5) | |
Text
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' 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION FLORIDA POWER CORPORATION, ET AL.
. NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operating License No. DPR-72, issued to Florida Power Corporation (the licensee), for operation of the Crystal River Unit No. 3 Nuclear Generating Plant (CR-3) located in Citrus County, Florida.
The proposed amendment would permit plant operation with the reactor .
coolant pump supports redesigned in accordance with the recently noticed -
amendment to General Design Criterion 4 (GDC-4), 10 CFR Part 50, Appendix A (51 FR 12502), which will be effective May 12, 1986.
The proposed amendment would be in response to the licensee's application for amendment dated April 24, 1986, which requested that the previous exemption request dated February 1,1985, as supplemented by several additional submittals, be considered an amendment request as required by the supplementary information in the notice for the amended GDC-4. It was further requested that noticing of this amendment be treated as an emergency since insufficient time exists for the Commission's usual 30-day notice without extending the current shutdown.
Before issuance of the proposed license amendment, the Commission will
, have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations. -
8605130596 860502 2 PDR ADOCK 05000 P
, 7590-01 The Commission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Cormnission's regulations in 10 CFR 50.92, 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 new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
The amended GDC-4 states that "the dynami effe. cts associated with postulated pipe ruptures of primary coolant loop piping in pressurized water reactors may be excluded from the design basis when analyses demonstrate the f
probability of rupturing such piping is extremely low under design basis conditions." Based on the licensee's submittals and the Commission's review i
to date of these submittals, the advanced fracture mechanics techniques employed provide assurance that flaws in primary system piping will be detected before they reach a size that could lead to unstable crack growth. Therefore, the probability of large pipe breaks in the primary coolant system is sufficiently low such that dynamic effects associated with postulated pipe breaks need not be a design basis. In addition, based on the review to date, the revised design for the reactor coolant pump supports adequately considers all remaining design basis loads. The accident mitigation features (e.g., emergency core cooling system,-containment) of the plant are j not affected by the proposed amendment. Therefore, operation of the facility in accordance with the proposed amendme t would not involve a significant increase in the probability or consequences of an accident previously evaluated.
1
. 7590-01 Based on the Commission's review to date, the revised design for the reactor coolant pump supports adequately considers all remaining design basis loads. The proposed change introduces no new mode of plant operation.
Therefore, operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident from any accident previously evaluated.
Based on the Commission's review to date of the licensee's submittals, .
Code design criteria for the reactor coolant piping will not be exceeded.
The revised design of the reactor coolant pump supports will result in improved support system reliability and may therefore improve overall safety margins for the plant. Therefore, operation of the facility in 3 accordance with the proposed amendment would not involve a significant reduction in a margin of safety.
Therefore, based on these considerations and the three criteria given above, the Commission has made a proposed determination that the amendment request involves no significant hazards consideration.
The Commission has determined that failure to act in a timely way would result in extending the present unplanned outage. Therefore, the Commission has insufficient time to issue its usual 30-day notice of the proposed action for public comment.
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.
l
. 7590-01 If the Comission decides in its final determination that the amendment does involve a significant hazards consideration, a notice of cpportunity 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 Comission is seeking public comments on this proposed determination of no significant hazards consideration. Comments on the proposed determination may be telephoned to John F. Stolz, Director, PWR Project .
Directorate No. 6, by collect call to 301-492-7288 or submitted in writing to the Rules and Records Branch, Division of Rules and Records, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555.
All coments received by May 19, 1986, will be considered in reaching a final determination. A copy of the application may be examined at the Comission's Public Document Room, 1717 H Street, N.W., Washington, D.C., and at the Crystal River Public Library, 668 N.W. First Avenue, Crystal River, Florida 32629.
Dated at Bethesda, Maryland, this 2nd day of May 1986.
FOR THE NUCLEAR RE ULATORY COMMISSION J in F. Stolz, Direct R Project Director e #6 ivision of PWR Licensing-B
f.
. D D I
DISTRIBUTION:
Lkcket F1D May 2, 1986 PBD#6 Rdg RIngram DOCKET NO. 50-302 Rules and Procedures Branch MEMORANDUM FOR:
Division of Rules and Records Office of Administration FROM: Office of Nuclear Reactor Regulation SUBJEC. MRIM N CORPORATION, ET AL CRYSTAL RIVER UNIT NO. 3 l
One signed original of the Federal Regiefer Notice identified below is enclosed for your transmittal to the Office of the Federal i Re ) of the Notice are enclosed for your use. Please arrante foOister foroublication.
publication Additional conformed copies ( 5 immediately. '
Notice of Receipt of Application for Construction Permit (s) and Operating License (s).
Notice of Receipt of Partial Application for Construction Permit (s)and Facility License (s): Time for Submission of Views on Antitrust Matters.
Notice of Consideration of issuance of Amendment to Facility Operating License.
Notice of Receipt of Application for Facility License (s); Notice of Availability of Applicant's Environmental Report; and Notice of Consideration of issuance of Facility License (s) and Notice of Opportunity for Hearing.
Notice of Availability of NRC Draft / Final Environmental Statement.
Notice of Limited Work Authorization.
Notice of Availability of Safety Evaluation Report.
Notice of issuance of Construction Permit (s).
Notice of Issuance of Facility Operating License (s) or Amendment (s).
Order.
1 Exemption.
Notice of Granting Exemption. I Environmental Assessment.
Notice of Preparation of Environmental Assessment.
Other:
Office of Nuclear Reactor Regulation PNR Project Directorate #6, PWR-B
Enclosure:
As stated
Contact:
Phone:
orricEm P cu n"* '"
Q Ingram- - .
o^rj> .5/.2/86 .
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