ML20128D909
| ML20128D909 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 01/27/1993 |
| From: | Mcmeekin T DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20128D912 | List: |
| References | |
| GL-90-02, GL-90-2, NUDOCS 9302100263 | |
| Download: ML20128D909 (7) | |
Text
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,lhar nmer Compny (I00%I.5-CO)
AfcGuire Nuclear Sution 12700 llagen Terry thmd fluntenulle, NC 2$07839M OUKEPOWER January 27, 1993 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555
Subject:
McGuire Nuclear Station Units 1 & 2 Docket Nos.~50-369,370 Revise the Frequency of the Radiological-Effluent Report and Modit'yj the -requirements for. Fuel Assemblies in' Design Features Section of Technical Specifications in accordance with Generic Letter
'90-02, Supplement 1 Gentlemen:
The NRC has amended 10 CFR 50 to reduce the regulatory burden on nuclear licensees.
These amendments were issued as final rules and published in the Federal Register : on - August 31, 1992(57 FR 39353).
The NRC has identified. revising-_the frequency of 'the Radiological Effluent Reports as an action that eliminates _duplicative or
--inconsistent reguletory requirements' without reducing the protection of the-public health and safety.
Also, on July 31,'1992, the NRC issued Supplement"1 to Generic Lettter 90-02, " Alternative Requirements for Fuel Assemblies in.
the Design Features. Section of Technical: Specifications"'.
This change provides_ flexibility'in the repair of f uel ' assemblies.
containing. damaged and leaking fuel-rods-by-reconstituting the assemblies.
McGuire Nuclear Station has chosen;to adopt the model Technical Specification provided with> Supplement.1.
Pursuant to 10 CFR 50.90, please find attached proposed'11 cense amendments to facility operating licenses NPF-9 and-NPF-17 for McGuire Nuclear Station Units 11 and.2 respectively.
This proposed Technical Specification (TS) revision contains the' follow 1ng-proposed' changes:
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Revised frequency;for the Radiological Effluent Report =
2.
Modified requirements for " Fuel Assemblies" in the
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" Design Features" Section of TS in accordance with Generic Letter (GL) 90-02, Supplement 1-Attachment I provides a technical discussion, no significant hazards analysis, and environmental impact analysis supporting-these proposed revisions.
Attachment II provides the proposed McGuire TSs changes.
Duke Power request a timely review and approval of the proposed TS revisions in view of the McGuire-Unit-2 end of cycle 8 shutdown schedule which has a projected start date of July 1, 1993.
McGuire Unit-2 Cycle'8 has indications of fuel rod failures-and plans are being made to remove-the rods and--insert =new rods with'a shorter active fuel rod length during the McGuire end.of cycle 8 refueling i
shutdown.
' Pursuant to 10 CFR 50.91(b) (1), a copy of this amendment request 4
l has been provided to the appropriate-North Carolina state official.
Should there-be any questions concerning' this matter. or.:if additional information is required,-please= advise.
Very truly yo rs, b
i T. C. McMeekin i-i-adj/TSC2 l--
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U.S. NRC January 27, 1993 Page 3 xc:
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Ebneter Regional Administrator, Region II T. A. Reed, ONRR P.
K. Vandoorn Senior Resident Inspector (MNS)
Dayne Brown, Chief Division of Radiation Protection P.
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Box 27687
- Raleigh, N.C.
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January 27, 1993 Page 4 T.
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McMeekin, being duly sworn, states that the he is Vice-Prasident of Duke Power Company; that he is authorized on the part of said company to sign and file with the U.S. Nuclear Regulatory Commission these revisions to the McGuire Nuclear Station License-Nos. NPF-9 and NPF-17; and, that all statements and matters set forth therein are true and correct to the best of his knowledge.
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McMeekin, Site Vice-President subscribed and sworn to before me this twenty-seventh day of January 1993.
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ATTACHMENT I DUKE POWER COMPANY-McGUIRE NUCLEAR STATION Technical Discussion, No Significant Hazards and Environmental-Analysis 4
Technical Discussion-The purpose of the proposed amendment requests for McGuire Nuclear Station are to:'
1..
Revise.the frequency for the Radiological Effluent Report 2.
Modify the requirements for " Fuel Asssemblies" in the " Design Features" Section of TS in accordance with GL 90-02, Supplement =
1 The bases for these changes are provided in.the following paragraphs.
1.
Revise the frequency for the Radiological Effluent, Report The NRC amended-its regulations to reduce-the regulatory burden on nuclear licensees.
This action reflects an initiative undertaken-by the Commission in response to a Presidential. memorandum requesting that selected ~ Federal-agencies review and modify _ regulations-_that would eliminate any unnecessary burden of. governmental regulations and ensure: that the regulated community'1s'not subject;to duplicative cut inconsistent regulation.
Revising the:requirementefornthe:
submission.of reports concerning:the quantity of. principal-nuclides-released to'unrestrictedLareas in liquid and' gaseous; effluents'from semiannually to annually was-an area identified where: regulations could be= revised 1to reduce regulatory: burden on licensees:without in any.way reducing the' protection forithe public health and safety or.the common defense-and security.
2.
Modify.the requirements for " Fuel Assemblies"rin the " Design-Features" section of TS in ~accordance with-GL 90-02, Supplement.
1-4 The requirements for. fuel assemblies specify-the quantity of fuel assemblies,-the active fuel-rod lengthrand.the numbercof
- fuel rods per_ assembly. Flexibility'to; deviate from.theinumber-of fuel 1 rods-percassembly andfactive fuel: rod length is desirable to permit timely' removal of' fuel _ rods that are found to be-leaking during a refueling outage or are determined to
.tx) probable sources of future leakage.- Thisfimprovement--in the
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1 Attachment I January 27, 1993 Page 2 licensee's fuel performance program will provide for reductions in future occupational radiation exposure and plant radiological releases.
No Significant Hazards Analysis a
10 CFR 50.91 requires that the following analysis be provided concerning whether ' the proposed amendment requests : involved a significant hazards consideration as defined in.10 CFR - 50. 92.
Standards for determinatilon that an amendment request does not 4
involve a significant hazards consideration are if 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 l
possibility of a new or different kind of accident from any -
previously evaluated;-or, 3)
Involve a significant reduction-in a margin of safety.
1.
Revise the frequency for the Ra'diological Effluent Report-The proposed revision to the frequency of the Radiological Ef fluent Report will not involve a significant increase--in-the probability.
or consequences of an accident-previously evaluated because.there will be-no change in the-types and amounts of effluents-that will be released, nor will there be an increase -in -individual or cumulative occupational radiation exposures.
Implementation of 'the revised frequency: for the-Radiological Effluent Report - will not create the possibility of a new or-different kind.of accident from any.previously-evaluated because-the revision is administrative and will.not change-the types.and amounts of ef fluents that will be released.-
By' modifying :the regulations to eliminate any unnecessary burden of duplicative or; e
inconsistent regulatory reporting,: the' present margin: of safety is not reduced.
Accordingly, this proposed change does not involve a'significant hazard.-
2.
Modify the requirements for " Fuel Assemblies".in the " Design Features" section of TS in accordance-with GL 90-02,. Supplement-1 i
The proposed change to the requirements for " Fuel Assemblies in the " Design. Features" section of TS will not; involve a significant increase. in the ' probability or-consequences of 'an. accident-previously.. evaluated,- because the.modificationE merely provides a -
4 broader blanket under which any future-specific modifications to the plant or changes to its safety analysis' may be performed, while i
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Attachment I January 27, 1993 Page 3 still requiring that any such change meet the same standards and criteria that they would have been subject to.
The creation of a new or different kind of accident from any previously evaluated accident is not considered a possibility because the change is administrative in nature and does not represent an actual modification to the plant or change to its safety analyses.
The margin of safety is maintained by adherence to other fuel related TS limits and the FSAR design bases.
The change does not directly affect any safety system or the safety limits, and ihus does not affect the plant margin of safety.
Accordingly, this proposed change does not involve a significant hazard.
Environmental Impact Analysis The proposed TS amendments have been reviewed against the criteria of 10 CFR 51.22 for environmental considerations.
The proposed amendments do not involve a significant hazards consideration, nor increase the types and amounts of effluents that may be released
- offsite, nor increase individual or cumulative occupational radiation exposures.
The proposed amendment requests are administrative in nature and therefore, meet the criteria given in 10 CFR 51.22(c)(9) for a categorical exclusion from the requirement for an Environmental Impact Statement.