ML20135F263
| ML20135F263 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 12/09/1996 |
| From: | Nerses V NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20135F267 | List: |
| References | |
| NUDOCS 9612120469 | |
| Download: ML20135F263 (10) | |
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7590-01-P UNITED STATES NUCLEAR REGULATORY ColetISSION DUKE POWER COMPANY DOCKET NOS. 50-369 AND 50-370 NOTICE OF CONSIDERATION OF ISSL'"CE OF AMENDfETS TO FACILITY OPERATING LICENSES. PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION. AND OPPORTUNITY FOR A HEARING The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of amendments to Facility Operating License Nos. NPF-9 and NPF-17 issued to Duke Power Company (the licensee) for operation of the McGuire Nuclear Station, Units I and 2, located in Mecklenburg County, North Carolina.
The proposed amendments would allow a one-time only change necessary to replace the existing 125-volt D.C. battery cells with new cells.
Before issuance of the proposed license amendments, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations.
The Commission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Commission's regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendments 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. As required by 10 CFR 50.91(a), the licensee j
has provided its analysis of the issue of no significant hazards 4
l consideration, which is presented below:
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9612120469 961209 PDR ADOCK 05000369 P
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l, First Standard Operation of the facility in accordance with the proposed amendment will not involve a significant increase in the probability or consequences of an accident previously evaluated.
The 125 volt DC Vital Instrumentation and Control Power System is not an accident initiator.
It serves as an accident mitigation system. The new battery will be seismically mounted. There is no change in cabling required for the new battery and no change in the physical and electrical separation provisions for the battery. The performance of plant safety functions will not be degraded by the new battery.
The replacement battery consists of conventional low specific gravity cells which will be purchased to meet the same plant requirements as the j
installed battery. The replacement batteries will be purchased from a 10CFR21 Supplier whose 10CFR50 Appendix B Program has been audited by Duke's Supplier Verification Group.
Implementation of each battery bank replacement will require approximately 30 days. During the replacement period, a temporary battery bank, procured through the Commercial Grade Program for IE usage, will be connected in place. The temporary battery will be installed in the Service Building due to space limitations in the Battery Room in the Auxiliary Building. During each battery replacement period, the remaining three vital battery banks and their associated equipment will remain in their normal configuration and will not be reconfigured for preplanned activities or routine maintenance. The performance of their safety functions will not be degraded. The 125VDC Vital I&C Power System will be restored to the fully qualified configuration following each battery replacement period.
The ability to cross-tie the electrical buses for the batteries (as allowed by TS [ Technical Specification l LCO [ Limiting Condition for Operation)ActionStatements)bymanua;iactionperprocedureremains available as a backup in the event that the temporary battery is rendered unavailable during the replacement period.
Each vital battery is sized to carry the continuous emergency and anticipated momentary loads of its own vital bus, and to also assume the loads of another vital bus (in a backup capacity), all for a one hour duty cycle.
The ambient temperature surrounding the temporary battery will be periodically monitored to ensure it remains with the battery specifications. Available ventilation in the temporary battery area is sufficient to prevent accumulation of excess hydrogen.
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For the above reasons, it can be concluded that the proposed am2ndment will not involve a significant increase in the probability or consequences of an accident previously evaluated.
Second Standard The amendment would not create the possibility of a new or different kind of accident from any kind of accident previously evaluated.
There are no new or common failure modes created by the use of low specific gravity cells. The low specific gravity battery has exhibited consistently high reliability and will perform the same function as the existing batteries.
The GNB Type NCN stationary battery... has been chosen as the first option to replace the AT&T round cells. The GNB Type NCN battery is of a conventional rectangular cell design with a traditional vertical plate design. The second option is to use new low specific gravity round i
cells for replacement. Both options for battery replacement are sized i
in accordance with IEEE Std. 485-1983.
The temporary battery will be comprised of new low specific gravity cells. The temporary battery and its rack will be the same equipment that is normally used with the exclusion of the seismic bracing and i
mounting apparatus. With the temporary battery connected, there are no new failure modes for the distribution equipment associated with the battery being replaced.
The temporary battery installation creates a potentially new failure mode due to lack of seismic mounting and the location of the temporary batteries (outside of the Vital Area in a non-Seismic Category 1 i
structure). This new failure mode is considered insignificant due to l
the short duration for which the temporary configuration will be in i
place. Duke Power has analyzed the temporary battery configuration from a probabilistic risk assessment standpoint and has found the temporary battery has no significant impact on the CDF [ core damage frequency) at 1
McGuire.
For these reasons, the possibility of a new or different kind of accident from any kind of accident previously evaluated is not created.
l Third Standard The amendment would not involve a significant reduction in a margin of safety.
I The vital batteries are required to power emergency and safe shutdown loads for safety related instrument and control equipment during certain accident conditions. Ultimately, safety related equipment required to j
maintain the integrity of fission product barriers depend upon proper i
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performance of the new battery. The new low specific gravity battery I
will meet the current licensing basis and will perform the same safety function as the existing vital battery. As such, the replacement i
battery will not affect any fission product barriers. The temporary battery is also fully capable of performing the safety function of the system if required and, thus, will have no detrimental impact on any fission product barriers. All required procedures and training will be developed and implemented prior to battery replacement. During the i
periods of battery replacement, if the temporary battery should become i
unavailable, the affected 125VDC channel will be declared inoperable and the nomal TS LCO will be applied.
Since the acceptance limits with respect to the required redundancy and functional capability of the battery system are not affected by this j
change, there is no reduction in the margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on this j
review, it appears that the three standards of 10 CFR 50.92(c) are satisfied.
Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration.
The Commission is seeking public comments on this proposed t-j determination. Any comments received within 30 days after the date of j
publication of this notice will be considered in making any final determination.
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Normally, the Commission will not issue the amendment until the i
expiration of the 30-day notice period. However, should circumstances change during the notice period such that failure to act in a timely way would result, for example, in derating or shutdown of the facility, the Commission may issue the license amendment before the expiration of the 30-day notice period, provided that its final determination is that the amendment involves no significant hazards consideration. The final determination will consider all public and State comments received. Should the Commissien take this
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action, it will publish in the FEDERAL REGISTER a notice of issuance and provide for opportunity for a hearing after issuance. The Commission expects that the need to take this action will occur very infrequently.
Written comments may be submitted by mail to the CMef, Rules Review and Directives Branch, Division of Freedom of Information and Publications Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, and should cite the publication date and page number of this FEDERAL REGISTER notice. Written comments may also be delivered to Room 6D22, Two White Flint North,11545 Rockville Pike, Rockville, Maryland, from 7:30 a.m. to 4:15 p.m. Federal workdays.
Copies of written comments received may be examined at the NRC Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC.
The filing of requests for hearing and petitions for leave to intervene l
is discussed below.
By January 13, 1997
, the licensee may file a request for a hearing with respect to issuance of the amendment to the subject facility operating license and any person whose interest may be affected by this proceeding and who wishes to participate as a party in the proceeding must file a written request for a hearing and a petition for leave to intervene.
Requests for a hearing and a petition for leave to intervene shall be filed in accordance with the Commission's " Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2.
Interested persons should consult a current copy of 10 CFR 2.714 which is available at the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC, and at the local public i
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- j. i document room located at the Atkins Library, University of North Carolina, Charlotte, (UNCC Station), North Carolina.
If a request for a hearing or i
petition for leave to intervene is filed by the above date, the Commission or l
an Atomic Safety and Licensing Board, designated by the Commission or by the i
j Chairman of the Atomic Safety and Licensing Board Panel, will rule on the 1
l request and/or petition; and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order.
As required by 10 CFR 2.714, a petition for leave to intervene shall set l
forth with particularity the interest of the petitioner in the proceeding, and how that interest may be affected by the results of the proceeding. The petition should specifically explain the reasons why intervention should be permitted with par'ticular reference to the following factors:
(1) the nature
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of the petitioner's right under the Act to be made party to the proceeding; i
(2) the nature and extent of the petitioner's property, financial, or other i
interest in the proceeding; and (3) the possible effect of any order which may
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be entered in the proceeding on the petitioner's interest. The petition should also identify the specific aspect (s) of the subject matter of the i
proceeding as to which petitioner wishes to intervene. Any person who has 4
filed a petition for leave to intervene or who has been admitted as a party may amend the petition without requesting leave of the Board up to 15 days prior to the first prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described above.
Not later than 15 days prior to the first prehearing conference
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scheduled in the proceeding, a petitioner shall file a supplement to the petition to intervene which must include a list of the contentions which are 4
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sought to be litigated in the matter.
Each contention must consist of a specific statement of the issue of law or fact to be raised or controverted.
In addition, the petitioner shall provide a brief explanation of the bases of the contention and a concise statement of the alleged facts or expert opinion which support the contention and on which the petitioner intends to rely in proving the contention at the hearing. The petitioner must also provide references to those specific sources and documents of which the petitioner is aware and on which the petitioner intends to rely to establish those facts or j
expert opinion.
Petitioner must provide sufficient information to show that a genuine dispute exists with the applicant on a material issue of law or fact.
Contentions shall be limited to matters within the scope of the amendment under consideration. The contention must be one which, if proven, would entitle the petitioner to relief. A petitioner who fails to file such a supplement which satisfies these requirements with respect to at least one l
contention will not be permitted to participate as a party.
l Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the opportunity to participate fully in the conduct of the hearing, including the opportunity to present evidence and cross-examine witnesses.
If a hearing is requested, the Commission will make a final determination on the issue of no significant hazards consideration. The final i
determination will serve to decide when the hearing is held.
If the final determination is that the amendment request involves no significant hazards consideration, the Commission may issue the amendment and i
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- f. make it immediately effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendment.
If the final determination is that the amendment request involves a significant hazards consideration, any hearing held would take place before the issuance of any amendment.
A request for a hearing or a petition for leave to intervene must be filed with the Secretary of the Comission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Docketing and Services l
Branch, or may be delivered to the Commission's Public Document Room, the l
Gelman Building, 2120 L Street, NW., Washington, DC, by the above date. Where l
petitions are filed during the last 10 days of the notice period, it is requested that the petitioner promptly so inform the Commission by a toll-free j
telephone call to Western Union at 1-(800) 248-5100 (in Missouri 1-(800) 342-6700). The Western Union operator should be given Datagram Identification Number N1023 and the following message addressed to Herbert N. Berkow:
petitioner's name and telephone number, date petition was mailed, plant name, and publication date and page number of this FEDERAL REGISTER notice. A copy of the petition should also be sent to the Office of the General Counsel, U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, and to Mr. Albert Carr, Duke Power Company, 422 South Church Street, Charlotte, North Carolina 28242, attorney for the licensee.
Nontimely filings of petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for hearing will not be l
entertained absent a determination by the Commission, the presiding officer or the presiding Atomic Safety and Licensing Board that the petition and/or
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request should be granted based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(1)-(v) and 2.714(d).
For further details with respect to this action, see the application for amendments dated November 26, 1996, which is available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC, and at the local public document room located at the Atkins Library, University of North Carolina, Charlotte (UNCC Station), North Carolina.
Dated at Rockville, Naryland, this 9th day of December, 1996 FOR THE NUCLEAR REGULATORY COP 911SSION Victor Nerses, Senior Project Nanager Project Directorate 11-2 l
Division of Reactor Projects - I/II i
Office of Nuclear Reactor Regulation l
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