ML20082M792
| ML20082M792 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire  |
| Issue date: | 04/12/1995 |
| From: | Tuckman M DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20082M795 | List: |
| References | |
| NUDOCS 9504240377 | |
| Download: ML20082M792 (10) | |
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DukePbuerOnnpany M S Toaown
' p.o Box ja SeniorVicePksident p pc282011006 NuclearGenemtron (7MJM2-22000tlice (700%24360 Fat DUKKPottet April 12,1995 t
U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Subject:
Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369 and 50-370 Proposed Technical Specifications (TS) Changes Relocation ofTurbine Overspeed Protection to Selected Licensee --
Commitment (SLC) Manual (TS 3/4.3.4 and Bases) i Gentlemen:
Pursuant to 10CFR50.4 and 10CFR50.90, attached are license amendment requests to i
Appendix A, Technical Specifications, of Facility Operating Licenses NPF-35 and NPF-52 for Catawba Nuclear Station Units 1 and 2, respectively and Facility Operating Licenses NPF-9 and NPF-17 for McGuire Nuclear Station Units 1 and 2, respectively. The requested amendments relocate the requirements for the turbine overspeed protection.
instrumentation from the TS to the SLC Manual. The SLC Manual is Chapter 16 of the Final Safety Analysis Report (FSAR).
I Attachment I contains a background and description of the enclosed amendment requests. contains the requiredjustification and safety evaluation. Pursuant to 10CFR50.91,~ Attachment 3 provides the analysis performed in accordance with the standards contained in 10CFR50.92 which concludes that the requested amendments do not involve a significant hazards consideration. Attachment 3 also contains an environmental impact analysis for the requested amendments. Attachments 4a and 4b contain the marked-up TS amendment pages for Catawba and McGuire, respectively.
Attachments 5a and 5b contain the proposed SLC Manual sections for Catawba and McGuire, respectively. Duke Power Company is forwarding a copy of this amendment request package to the appropriate North Carolina and South Carolina state officials.
950424o377 95o412 PDR ADOCK 05000369
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Page 2 April 12,1995 Should there be any questions concerning these amendment requests or should additional information be required, please call L.J. Rudy at (803) 831-3084.
Very truly yours, W
M.S. Tuckman LJR/s l
Attachments xc (with~ attachments):
S.D. Ebneter, Regional Administrator Region II R.J. Freudenberger, Senior Resident Inspector i
G.F. Maxwell, Senior Resident Inspector f
R.E. Martin, Senior Project hianager f
ONRR V. Nerses, Senior Project Manager
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Max Batavia, Chief l
Bureau of Radiological Health, SC Dayne Brown, Chief l
Division of Radiation Protection, NC American Nuclear Insurers
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M&M Nuclear Consultants INPO Records Center i
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1 Document Control Desk
' Page 3 April 12,1995 i
M.S. Tuckman, being duly sworn, states that he is Vice President of Duke Power Company; that he is authorized on the part of said Company to sign and file with the Nuclear Regulatory Commission these revisions to the Catawba Nuclear Station License Nos. NPF-35 and NPF-52 and the McGuire Nuclear Station License Nos. NPF-9 and NPF-17; and that all statements and matters set forth therein are true and correct tu the best of his knowledge.
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M.S. Tuckman, Vice President I
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Subscribed and sworn to before me this 12th day of April,1995.
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My commission expires:
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i ATTACllMENT I I
BACKGROUND AND DESCRIPTION OF AMENDMENT REQUEST
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Background
Section 3/4.3, Instmmentation, of the Catawba and McGuire TS delineates requirements for various instrumentation throughout the plant. Section 3/4.3.4 in the Catawba and McGuire TS governs the turbine overspeed protection instrumentation. This section was originally included in the Catawba and McGuire TS due to its being contained in NUREG-0452, " Standard Technical Specifications for Westinghouse Pressurized Water Reactors".
On September 28,1992, the NRC issued NUREG-1431, " Revised Standard Technical Specifications for Westinghouse Plants" The NRC has encouraged utilities to pursue adoption of the Revised Standard Technical Specifications (RSTS). Where utilities have elected not to adopt the entire RSTS, the NRC has indicated that they will allow the adoption of selected RSTS sections and has encouraged utilities to propose license amendments consistent with the content of the RSTS.
At Catawba and McGuire, each unit's turbine-generator consists of a tandem arrangement of a double-flow, high-pressure turbine and three identical double-flow low-pressure turbines driving a direct-coupled generator. The Catawba turbine-generators were manufectured by General Electric and the McGuire turbine-generators were manufactured by Westinghouse. Both stations employ a turbine overspeed protection system that is divided into the two basic categories of mechanical overspeed protection in the turbine itself and electrical overspeed protection in the turbine controller. The specific design of the mechanical and electrical overspeed protection subsystems differs slightly between Catawba and McGuire. Section 10.2.2 in the Catawba and McGuire Final Safety Analysis Reports describes the detailed design cf these subsystems.
The purpose of these amendment requests is to relocate the requirements for the turbine overspeed protection system from the TS to the SLC Manual for Catawba and McGuire.
Description of Amendment Request TS section 3/4.3.4, Turbine Overspeed Protection, along with the corresponding Bases section, is relocated from the TS to the SLC Manual. The TS Index for each station is also modified to reflect the above changes. No changes are being made to the technical content of the affected TS section for either Catawba or McGuire. (Note that an obsolete footnote is being deleted from the Catawba TS when the requirements are relocated to the SLC Manual. Also, for both stations, Surveillance Requirement 4.3.4.1 regarding the non-applicability of Specification 4.0.4 i.; being deleted, since this statement does not apply when the requirements are relocated to the SLC Manual.)
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ATI'ACIIMENT 2 JUSTIFICATION AND SAFETY EVALUATION i
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JuAtification and Safety Evaluation As no technical changes are being proposed to the TS section being relocated to each station's SLC hianual, the requested amendments are considered purely administrative in I
l nature. All technical requirements will continue to be met when the afrected TS section is relocated to the SLC hianual. In addition, all surveillance requirements for the turbine overspeed protection systems will continue to be met.
The reliability of the turbine overspeed protection system will not be impacted by the proposed amendments. No changes to the manner in which the system operates are being made, so plant operation will not be affected.
The proposed changes are consistent with the Westinghouse Revised Standard Technical Specifications in that the affected TS section is no longer contained in the RSTS. When the RSTS was developed, the NRC did not consider the turbine overspeed protection system to warrant technical specification control. Further, the NRC has encouraged licensees to pursue changes to technical specifications to make them consistent with the RSTS, either through wholesale adoption of the RSTS, or through adoption of selected sections of the RSTS. The proposed amendments are consistent with that philosophy.
Once the affected TS requirements are relocated to the SLC hianual, future changes to these requirements will be made under the provisions of 10CFR50.59. As an example, l
Catawba is planning to pursue changes which will increase the smveillance interval of SURVEILLANCE REQUIREh1ENT 4.3.4.2b from monthly to quarterly. This efrort is being pursued with the support of the turbine manufacturer (General Electric) and will be implemented with manufacturer concurrence using the 10CFR50.59 evaluation process.
Finally, the NRC has approved deletion of the turbine overspeed protection system requirements from TS for other plants (reference license amendment #60 for Clinton Power Station, Docket No. 50-461).
Duke Power Company maintains that approval of the proposed amendments will not be inimical to the health and safety of the public.
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ATTACIIMENT 3 l
NO SIGNIFICANT IIAZARDS CONSIDERATION DETERMINATION
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AND ENVIRONMENTAL IMPACT ANALYSIS i
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No Sirnificant iia 7ards Consideration Determination As required by 10CFR50.91, this analysis is provided concerning whether the requested amendments involve significant hazards considerations, as defined by 10CFR50.92.
Standards for determination that an amendment request involves no significant hazards considerations are if operation of the facility in accordance with the requested 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 requested amendments relocate the controls for the turbine overspeed protection system for Catawba and McGuire from the TS to the SLC Manual.
The Commission has previously determined that amendment requests similar to the enclosed request do not constitute a significant hazards consideration (reference license amendment #60 for Clinton Power Station, Docket No. 50-461).
Criterion 1 The requested amendments will not involve a significant increase in the probability or consequences of an accident previously evaluated. Relocation of the affected TS section to the SLC Manual will have no effect on the probability of any accident occurring. In addition, the consequences of an accident will not be impacted since the above system will continue to be utilized in the same manner as before. No impact on the plant response to accidents will be created.
Criterion 2 The requested amendments will not create the possibility of a new or different kind of accident from any accident previously evaluated. No new accident causal mechanisms will be created as a result of relocating the affected TS requirements to the SLC Manual.
Plant operation will not be affected by the proposed amendments and no new failure modes will be created.
Criterion 3 The requested amendments will not involve a significant reduction in a margin of safety.
No impact upon any plant safety margins will be created. Relocation of the affected TS requirements to the SLC Manual is consistent with the content of the Westinghouse RSTS, as the NRC did not require technical specification controls for the turbine overspeed protection system in the RSTS. The proposed amendments are consistent with the NRC philosophy of encouraging utilities to propose amendments that are consistent with the content of the RSTS.
Based upon the preceding analyses, Duke Power Company concludes that the requested amendments do not involve a significant hazards consideration.
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EnvironmentalImpact Analysis The proposed license amendments have been reviewed against the criteria of 10CFR51.22 for environmental considerations. The proposed amendments do not involve a significant hazards consideration, nor do they increase the types and amounts of effluents that may be released offsite, nor do they increase individual or cumulative occupational radiation exposures. Therefore, the proposed amendments meet the criteria given in 10CFR51.22(c)(9) for a categorical exclusion from the requirement for an Environmental Impact Statement.
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