ML20100C726
| ML20100C726 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 01/26/1996 |
| From: | Assa R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20100C728 | List: |
| References | |
| NUDOCS 9601310159 | |
| Download: ML20100C726 (9) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION i
CO N NWEALTH EDISON COMPANY DOCKET NOS. STN 50-454. STN 50-455. STN 50-456 AND STN 50-457 j
NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSE. PROPOSED NO SIGNIFICANT HAZARDS i
CONSIDERATION DETERMINATION. AND OPPORTUNITY FOR A HEARING The U.S. Nuclear Regulatory Commission (the Commission) is considering
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issuance of amendments to Facility Operating License Nos. NPF-37, NPF-66, 4
NPF-72, and NPF-77, issued to Commonwealth Edison Company for operation of Byron Station, Units 1 and 2, located in Ogle County, Illinois and Braidwood j
Station, Units 1 and 2, located in Will County, Illinois.
The proposed amendments would remove certain technical specification requirements that are applicable when one of the two source range detectors is inoperable greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The affected requirements are:
suspension of all operation activates involving positive reactivity changes and verifying valves CV-1115, CV-8428, CV-8441, and CV-8435 are closed and secured in position.
The requirement to open the reactor trip breakers when one of the two source range detectors (SRD) is inoperable greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or when both SRD's are inoperable will not be changed.
a 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 j
regulations in 10 CFR 50.92, this means that operation of the facility in j
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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 j
accident from any accident previously evaluated; or (3) involve a significant i
j reduction in a margin of safety. As required by 10 CFR 50.91(a), the licensee 4
has provided its analysis of the issue of no significant hazards j
consideration, which is presented below:
1 1.
The proposed change does not involve a significant increase j
in the probability or consequences of an accident previously j
evaluated.
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This proposed change does not result in the installation of i
any new equipment, and no existing equipment is modified.
Operability of source range detectors in Modes 3, 4 and 5 with [ reactor trip breakers] RTBs open is not assumed as the precursor or initiator for any accident previously analyzed.
One operable source range detector is acceptable in Modes 3, l
4, and 5 with the RTBs open, since under these conditions, j
no core alterations that could affect core reactivity are j
l possible, and control rod withdrawal is not possible. Under i
these conditions, the source range is only providing i
indication and input to the boron dilution protection system l
(BDPS). The impact of an inoperable source range detector
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i on BDPS is addressed by compliance with the Action i
Requirements of TS 3.1.2.7, " Boron Dilution Protection i
System." TS 3.1.2.7 addresses the potential for a positive i
reactivity addition via a dilution event. With one source i
range detector operable, indication of any positive i
reactivity changes will still be available via the operable j
source ranqe detector. Also, BDPS will still respond automatica ly to mitigate a positive reactivity change.
j Thus, with one source range detector inoperable and RT8s open, indication of a positive reactivity change is still i
provided via the operable source range detector, and i
automatic mitigation is still available via BDPS to ensure i
1 that there is no significant increase in the consequences of an accident previously evaluated.
With no source range detectors operable, the proposed action statement requires that the RT8s be immediately opened, all positive reactivity changes be immediately suspended, d
shutdown margin be initially verified within one hour and at
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1 east once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter and dilution valves be closed.
Thus, with no source range detectors available, j
potential sources of positive reactivity addition are 1
i disabled and the shutdown condition of the core is j
periodically verified which ensures that there is no i
significant increase in the consequences of an accident j
previously evaluated.
j-Therefore, this proposed change does not involve a significant increase in the probability or consequences of an accident j
previously evaluated.
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2.
The proposed change does not create the possibility of a new i
or different kind of accident from any accident previously evaluated.
a j
This proposed change deals only with the Action Requirements i
for inoperable source range instruments. No new equipment is being installed, no existing equipment is being modified.
l No new system configurations will be introduced as a result i
of this proposed change. Therefore, no new or different j
failure modes are being introduced.
Thus, the proposed change does not create the possibility of a new or different kind of accident from any accident previously l
l evaluated.
1 3.
The proposed change does not involve a significant reduction in a margin of safety.
With one source range detector inoperable beyond 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, this proposed revision requires that the RTBs be opened.
With the RTBs open, the source range instruments provide only indication and input to BDPS. With only one source range detector inoperable, the indication function is still i
satisfied by the operable source range detector. The impact i
of an inoperable source range detector on BDPS is addressed i
by compliance with the Action Requirements of TS 3.1.2.7,
" Boron Dilution Protection System." Also, BOPS will still respond automatically to mitigate a positive reactivity i
change based on input from the operable source range detector. Thus with one source range detector inoperable the proposed action requirement places the affected unit in 2
a condition where the reactor trip function of the source i
range is no longer required, and the remaining source range functions are satisfied by the operable source range s
i indicator. Thus, with one source range detector inoperable, this proposed change does not involve a significant reduction in a margin of safety.
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With no source range detectors operable, the proposed action statement requires that the RTBs be immediately opened, all positive reactivity changes be immediately suspended, shutdown margin be initially verified within one hour and at i
least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter and dilution valves be closed and secured in position. This is] provides protection equivalent to that provided[by the current j
specification. Thus, with both source range detectors J
inoperable, this proposed change does not involve a significant reduction in a margin of safety.
Therefore, this proposed change does not involve a significant j
reduction in a margin of safety.
j The NRC staff has reviewed the licensee's analysis and, based on this i
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 l
involves no significant hazards consideration.
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The Commission is seeking public comments on this proposed determination. Any comments received within 30 days after the date of j
I publication of this notice will be considered in making any final f
determination.
Normally, the Commission will not issue the amendments until the l
expiration of the 30-day notice period. However, should circumstances change l
during the notice period such that failure to act in a timely way would l
result, for example, in derating or shutdown of the facility, the Commission j
may issue the license amendments before the expiration of the 30-day notice period, provided that its final determination is that the amendments involve no significant hazards consideration. The final determination will consider all public and State comments received. Should the Commission take this action, it will publish in the FEDERAL REGISTER a notice of issuance and i
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provide for opportunity for a hearing after issuance. The Commission expects that the need to take this action will occur very infrequently.
Written consents may be submitted by mail to the Rules Review and Directives Branch, Division of Freedom of Information and Publications l
Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555, 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 1s discussed below.
By March 1, 1996
, the licensee may file a request for a hearing with respect to issuance of the amendments 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 document rooms; for Byron, located at the Byron Public Library District,109 N.
Franklin, P.O. Box 434, Byron, Illinois 61010; for Braidwood, the Wilmington
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Public Library, 201 S. Kankakee Street, Wilmington, Illinois 60481.
If a request for a hearing or petition for leave to intervene is filed by the above j
date, the Commission or an Atomic Safety and Licensing Board, designated by 2
the Commission or by the Chairman of the Atomic Safety and Licensing Board i
Panel, will rule on the request and/or petition; and the Secretary or the j
designated Atomic Safety and Licensing Board will issue a notice of hearing or j
an appropriate order.
As required by 10 CFR 2.714, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and f
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 particular reference to the following factors:
(1) the nature I
of the petitioner's right under the Act to be made party to the proceeding; (2) the nature and extent of the petitioner's property, financial, or other interest in the proceeding; and (3) the possible effect of any order which may i
be entered in the proceeding on the petitioner's interest.
The petition j
should also identify the specific aspect (s) of the subject matter of the proceeding as to which petitioner wishes to intervene. Any person who has i
flied 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 l
l an amended petition must satisfy the specificity requirements described above.
Not later than 15 days prior to the first prehearing conference scheduled in the proceeding, a petitioner shall file a supplement to the l
petition to intervene which must include a list of the contentions which are t
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1 sought to be litigated in the matter.
Each contention must consist of a specific statement of the issue of law or fact to be raf.
or controverted.
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In addition, the petitioner shall provide a brief explar. won of the bases of i
the contention and a concise statement of the alleged facts or expert opinion 1
which support the contention and on which the petitioner intends to rely in proving the contention at the hearing. The petitioner must also provide j
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 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.
i Contentions shall be limited to matters within the scope of the amendments l
under consideration. The contention must be one which, if proven, would l
1 entitle the petitioner to relief. A petitioner who fails to file such a supplement which satisfies these requirements with respect to at least one contention will not be permitted to participate as a party.
j Those permitted to intervene become parties to the proceeding, subject l
to any limitations in the order granting leave to intervene, and have the a
opportunity to participate fully in the conduct of the hearing, including the l
opportunity to present evidence and cross-examine witnesses.
l If a hearing is requested, the Commission will make a final determination on the issue of no significant hazards consideration. The final determination will serve to decide when the hearing is held.
l If the final determination is that the amendment request involves no significant hazards consideration, the Commission may issue the amendments and 4
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make it immediately effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendments.
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 amendments.
A request for a hearing or a petition for leave to intervene must be f
filed with the Secretary of the Comission, U.S. Nuclear Regulatory Commission, Washington, DC 7,0555, Attention: Docketing and Services Branch, or may be delivered to the Comission's Public Docunnt Room, the Gelman Building, 2120 L Streat, NW., Washington, DC, by Me above date. Where petitions are filed durirg the inst 10 days of the netice period, it is requested that the petitlener promptly so inform tM Comission by a toll-free telephone call to Western Union at 1-(800) 248-5100 (in Missouri 1-(800) 342-6706). The Western Union operator should be given Datagram Identification Number N1023 and the following message addressed to Robert A. Capra:
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 aise he sent to the Office of the General Counsel, U.S.
Nuclear Regulatory Comission, Washington, DC 20555, and to Michael I. Miller, Esquire; Sidley and Austis, One First National Plaza, Chicago, Illinois 60603, attorney for the licensee.
Nontimely filings of petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for hearing will not be entertained absent a determination by the Comission, 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 January 11, 1996, which is available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street, i
NW., Washington, DC, and at the local public document rooms; for Byron, i
located at the Byron Public Library District,109 N. Franklin, P.O. Box 434, f
Byron, Illinois 61010; for Braidwood, the Wilmington Public Library, 201 S.
Kankakee Street, Wilmington, Illinois 60481.
Dated at Rockville, Maryland, this 26th day of January 1996.
FOR THE NUCLEAR REGULATORY COMMISSION
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Ramin R. Assa, Project Manager i
Project Directorate III-2 Division of Reactor Projects - IV/V j
Office of Nuclear Reactor Regulation i
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