ML20246C126
| ML20246C126 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 04/24/1989 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246C116 | List: |
| References | |
| GL-83-28, GL-85-09, GL-85-9, NUDOCS 8905090269 | |
| Download: ML20246C126 (9) | |
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION COMMONWEALTH EDISON COMPANY DOCKET NOS. 50-295 AND 50-304 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION AND OPPORTUNITY FOR HEARING The U. S. Nuclear Regulatory Comission (the Comission) is considering issuance of an' amendment to Operating License Nos. DPR-39 and DPR-48, issued to Commonwealth Edison Company (the licensee), for operation of Zion Station, Units 1'and 2 located in Lake County, Illinois.
This amendment request dated April 17, 1989, is being made in accordance i
with Generic Letter 85-09, entitled " Technical Specifications for Generic
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Letter 83-28, Items 4.3," to change Tables 3.1-1 and 4.1-1 of Technical Specifications for Zion Station. The proposed changes involve addition and/or clarifications to the operability and surveillance requirements for:
1)Hanual
. Reactor Trip; 2) Automatic Reactor Trip Logic; and 3) Reactor Trip and Bypass Breakers.
Before issuance of the proposed license amendment, the Comission will have.made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations.
The Comission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Comission's 8905090269 890424 PDR ADOCK 05000295 PDC l
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i regulations in 10 CFR 50.92, this means that operation of the facilities in accoroance with the proposed amendment would not (1) involve a significant l
increase in the probability or consequences of an accident previously l
evaluated; or (2) create the possibility of a new or different kind of accident from any accident previo.isly evaluated; or (3) involve a significant reduction in a margin of safety.
The Connonwealth Edison has evaluated the proposed amendment and
' determined that it involves no significant hazards consideration. The licensee's evaluation is provided below.
The proposed amendment involves revisions to the operability and surveillance requirements given in Technical Specification Tables 3.1-1 and 4.1-1 for Zion Station. The changes clarify the operability requirements for Automatic Reactor Trip Logic to include the Reactor Trip Breakers. The changes to Table 4.1-1 clarify the surveillance requirements for the Manual Reactor Trip function to require independent verification of the operability w
of the Undervoltage and Shunt Trip circuits and the operability of the Bypass Breaker circuit; the Monthly Functional Test for the Automatic Reactor Trip Logic has been clarified to require testing each train on alternate months (at a 62-day interval) and to explicitly state where operability of circuit contacts may be verified by the use of indication circuitry. Monthly and Refueling Surveillance Requirements have been defined for Reactor Trip Breakers and Bypass Breakers.
All of the proposed changes have been worded in accordance with the guidelines of HRC Generic Letter 85-09, and are consistent with Technical Specifications in effect for other Pressurized Water Reactors of similar
4 1 vintage.- The clarification notes for the Automatic Reactor Trip Logic
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l Surveillance and the use of the alternate month testing interval are similar
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to the specifications currently in effect at [other plan +s.]
1)
The proposed changes do not involve a significant increase to the j
probability or consequences of an accident previously evaluated.
The addition of the requirement for automatic actuation of the shunt trip device provides an alternate method to open the reactor trip breakers. Therefore', when a reactor trip signal is generated, there are diverse mechanisms u provide a reactor breaker trip which should minimize the possibility of an Anticipated Transient Without Scram (ATWS). The proposed changes revise the surveillance to require independent testing of the undervoltage and shunt trip devices for the manual reactor trip and the reactor trip breakers.
These surveillance ensure reactor trip breaker operability when required and thus do not involve a significant increase to the probability or consequences of an accident that was previously evaluated.
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The proposed changes do not create the possibility of a new or i
i different kind of accident 'from any previously evaluated.
i The proposed changes do not change the manner in which the reactor i
l protection system provides plant protection. The addition of the j
1' shunt trip attachment provides an alternate method to open the breakers when a reactor trip signal is generated. Therefore, if one trip inechanism fails, the other trip mechanism is available, which
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! increases the reliability of the reactor protection system and decreases the possibility of an ATWS event and therefore does not create the possibility of a new or different kind of accident that was previously evaluated.
3)
The proposed changes do not involve a significant reduction in a mergin of safety.
The proposed changes are expected to increase the overall margin of safety because they provide an alternate method to trip the reactor trip breakers, thereby limiting the potential for an ATWS event.
The proposed surveillance changes are designed to verify oper6bility of the reactor trip and bypass breakers and therefore do not involve a significant reduction in the margin of safety.
1 Based upon the above evaluation, Commonwealth Edison concluded that the
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proposed changes to the Technical Specifications do not involve a significant hazards consideration.
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The staff has reviewed the licensee's evaluation and agrees with the
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licensee that these proposed amendments involve no significant hazards
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consideration.
Before issuance of Generic Letter 85-09, by letter dated March 25, 1985, the licensee originally requested similar changes to clarify the automatic reactor trip logic testing in accordance with Generic Letter 83-28. The staff issued no significant hazard consideration notice on May 21, 1985 (50FR20973). The April 17, 1989, submittal substantially revised the previous submittal dated March 25, 1985.
This notice supersedes the previous notice, i
. l The Comission is seeking public comments on this proposed determination.
Any comments received within 30 days after the date of publication of this notice will be considered in making any final determination. The Comission will not normally make a final determination unless it receives a request for a hearing.
Written comments may be submitted by mail to the Rules and Procedures Branch, Divisien of Rules and Records, Office of Administration, U.S. Nuclear Regulatory Comission, Washington, D.C. 20555, and should cite the publication date and page number of the FEDERAL REGISTER notice. Written co m nts may also be delivered to P-216, Phillips Building, 7920 Norfolk Avenue, Bethesda, Maryland from 8:15 a.m. to 5:00 p.m.
Copies of written comments received may be examined at the NRC Public Document Room, 2120 L Street, N.W., Washington, D.C.
The filing of requests for hearing and petitions for leave to intervene is discussed below.
By May 30, 1989
, 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 petition for leave to intervene. Request for a hearing and petitions 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.
If a request for hearing or petition for leave to intervene is filed by the above date, the Comission or an Atomic Safety and Licensing Board, designated by the Comission
4 or by the Chairman of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition and the Secretary of the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order.
As required by 10 CFR 92.714, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how that interest may be affected by the results to the proceeding. The petition should specifically explain the reasons why intervention should be permitted with particular reference to the following factors:
(1) the nature of the petitioner's right under the Act to be made a 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 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 proceedings as to which petitioner wishes to intervene. Any person who has fileo 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 fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity I
requirements described above.
Not later than fifteen (15) days prior to the first prehearing conference i
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 sought to be litigated in the matter, and the bases for each contention set forth with reasonable specificity. Contentions shall be limited to matters j
within the scope of the amendment under consideration. A petitioner who fails 1
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' 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.
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 heerf ng is requested, the Comission 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.
If the final determination is that the amendment request involves no significant hazards consideration, the Comission may issue the amendment and make it 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 involves a significant hazards consideration, any hearing held would take place before the issuance of any amendment.
Normally, the Commission will not issue the amendment until the l
expiration of the 30-day notice periot 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 Comission may issue the license amendment before the expiration of the 30-day notice period, provided that its final determination is that the amendment invo hes no significant hazards consideration. The final determination will consider all public and State comments received. Should the Comission take this i
. l action, it will publish a notice of issuance and provide for opportunity for a I
hearing after issuance. The Comission expects that the need to take this action will occur very infrequently.
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 i
Comission, Washington, D.C. 20555, Attention: Docketing and Service Branch, or may be delivered to the Comission's Public Document Room, 2120 L Street,
- N.W., Washington, D.C., by the above date. Where petitions are filed during the last ten (10) days of the notice period, it is requested that the petitioner promptly so inform the Comission by a toll-free telephone call to Western Union at 1-800-325-6000(inMissouri 1-800-342-6700). The Western Union operator should be given Datagram Identification Number 3737 and the following message addressed to Daniel R. Muller: petitioner's name and 1
telephone number; date petition was mailec; plant number; 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 - Rockville, Maryland, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, and to Michael Miller, Esquire; Sidley and Austin, 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 Atomic Safety and Licensing Board that the petition and/or request should be granted based upon a balancing of the factors specified in 10 CFR 2.174(a)(1)(1)-(v) and2.714(d).
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,. For further details with respect to this action, see the application for amendment which is available for public inspection at the Comission's Public Document Room, 2120 L Street N.W., Washington, D.C., and for Zion Station, the Waukegan Public Library,128 N. County Street, Waukegan Illinois 60085.
Dated at Rockville, Maryland, this 24 th day of April 1989.
FOR THE NUCLEAR REGULATORY COMMISSION Daniel R. Nuller, Director Project Directorate III-2 Division of Reactor Projects - III, i
IV, Y and Special Projects
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