ML20247A863
| ML20247A863 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 04/25/1989 |
| From: | Stefano J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247A868 | List: |
| References | |
| NUDOCS 8905230299 | |
| Download: ML20247A863 (9) | |
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'Y 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DETROIT EDISON COMPANY i
t WOLVERINE POWER SUPPLY COOPERATIVE INCORPORATED DOCKET NO. 50-341
!'l NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO I
l FACILITY OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS i
CONSIDERATION DETERMINATION AND OPPORTUNITY FOR HEARING The U. S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operating License No. NPF-43, issued to Detroit Edison Company and Wolverine Power Supply Cooperative (the licensees),
for operation of the Fermi-2 plant, located in Monroe County, Michigan.
The amendment would revise the Technical Specifications sections 3/4.6.5.1 SECONDARY CONTAINMENT and DEFINITION 1.36 to reflect design modifications to the reactor building's railroad bay air lock doors in accordance with the licensees application for amendment dated April 21, 1989.
The design change is a result of a concern with the reliability of secoadary containment integrity barriers that depend on non-safety related air supply systems.
Before issuance of the proposed license amendment, 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 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 8905230299 890428 DR ADOCK 05000341 PDC
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accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
The licensees have evaluated the proposed changes to the TS against the above standards as required by 10 CFR 50.92. The licensees ' concluded that:
(1) The proposed changes do not involve a significant increase.in the probability or consequences of an accident previously evaluated because the capability and reliability of SECONDARY CONTAINMENT INTEGRITY has been increased.
Two railroad bay ~ air lock doo's will be required t'o be r
closed and sealed during normal operation as opposed to one railroad bay air lock door which is currently required by the existing Technical Specifications.
The subject door's seals will be supplied from a safety related, seismically qualified and fully redundant non-interruptible air supply system.
The existing air supply for these door seals is not '
safety related, not seismically qualified and not redundant.
The proposed system will be single failure proof provided both railroad bay air lock doors are closed.
The proposal includes ACTIONS of one of the two rai'Iroad bay air lock doors inoperable; in this case, the railroad bay secondary containment penetration is still isolated by the other railroad bay air lock door.
The existing ACTIONS are based upon situations where SECONDARY CONTAINMENT INTEGRITY is completely compromised.
The 7 day out-of-service time limit on proposed ACTION "b.1." is consistent with
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Technical Specification 3.6.5.3, Standby Gas Treatment System (SGTS) and the General Electric Standard Technical Specification (GESTS) for the SGTS.
The SGTS configuration and function, and the proposed l
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modifications configuration are similar in that both systems support SECONDARY CONTAINMENT INTEGRITY, both systems have 100% redundant capabilities and both systems are safety related.
Proposed ACTION "b.2" is consistent with existing ACTION "b" and the GESTS for SECONDARY CONTAINMENT INTEGRITY.
The proposed footnote that will allow ingress and egress through one railroad bay air lock door or routine testing of the doors' alarm /
indication instrumentation is based on engineering judgement considering the low probability of a single failure on the close~d door, the frequen>cy T
of a door being open and the low probability of an accident requiring SECONDARY CONTAINMENT INTEGRITY.
If within the four or 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> time period allowed for one railroad bay air lock door to be open, the closed becomes inoperable because of a loss of door sesi pressure (the only component dependent on an active system) control reom personnel would immediately receive the low seal pressure alarm.
Secondary containment functionality could then be restored by closing the door that was open.
The existing Technical Specification allows four hours to recover from a complete loss of SECONDARY CONTAINMENT INTEGRITY before a raattor shut down is required.
The footnote's 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> time period is only applicable when fuel is received onsite which is only expected to consist of approximately eight shipments in 18 months.
The existing 31-day surveillance requirement, 4.6.5.1.b.1, has been modified so that both railroad bay doors are required to be verified closed every 31-days.
Therefore, the proposed changes do not significantly increase the probability or consequences of an accident previously evaluated because l
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l two railroad bay doors are required OPERABLE and closed and the door seals will be supplied by a safety related and redundant air system.
The proposed ACTIONS are consistent with accepted industry standards for related systems or similar redundancy and safety classification which are also required to support SECONDARY CONTAINMENT INTEGRITY.
(2) The proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated because the capabilities of the railroad bay air lock door system have been increased and the. railroad bay air lock door seals will be supplied with safety related air from the existing NIAS System.
The NIAS System is safety related, fully redundant and seismically supported.
The NIAS System's air compressors are automatically loaded on to the EDGs upon the loss of offsite power to the air compressor (s) electrical bus (es).
An engineering evaluation has determined that sufficient capacity exists in the NIAS System to supply the railroad bay door seals concurrent with the system's existing loads.
The design modification will provide restrictive orifices and receiver tank:; such that a rupture of the railroad bay air lock seals will not affect the function of other equipment which depend on the NIAS System.
Control room alarms for low railroad bay air lock door seal pressure will be installed for each door.
l This will allow continuous monitoring by control room personnel of the l
l railroad bay air lock door's SECONDARY CONTAldhENT INTEGRITY.
The door seal's pressure provides an excellent indication of the railroad bay air lock's SECONDARY CONTAINMENT INTEGRITY because the seals are the only f
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active component on the doors which rely on active equipment for their L
OPERABILITY, Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated because the railroad bay air lock door seals will be supplied from a fully qualified air system and the new design will enhance the system's capability and not degrade any related systems or equipment functions.
l (3) The proposed changes do 'not involve a significant reduction in the margiri of safety because the previously stated design modifications and propos'ed Technical Specifications increase the capability and reliability of
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SECONDARY CONTAINMENT INTEGRITY compared to the existing configuration.
The design modification and proposed Technical Specification changes effectively add an " additional barrier" between secondary containment and the environment for the railroad bay air lock.
Additionally, the only active component utilized for these redundant barriers will be supported from a fully qualified safety related system.
The Commission 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 Commission will not normally make a final determination unless it receives a request for a hearing.
. Written comments may be submitted by mail to the Regulatory Publications Branch, Division of Freedom of Information and Publications Services, Office of Administration and Resources Management, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, and should cite the publication date and page number of this FEDERAL REGISTER notice.
Written comments may also be delivered to Room P-216, Phillips Building, 7920 Norfolk Avenue, Bethesda, Maryland, from
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. 4 7:30 a.m. to 4:15 p.m.
Copies of written comments received may be examined at the NRC Public Document Room, the Gelman Building, 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
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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 a hearing or petition for leave to intervene is filed by the above date, the Commission or an Atomic Safety and Licensing Board, designated by the Commission or by the i
Chairman of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hea' ring or an appropriate order.
As required by 10 CFR 2.714, r 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 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 of the petitioner's right under the Act to be made a party to the proceeding; (2) the nature and i
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 proceeding as to which l
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petitioner wishes to intervene.
Any person who has 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 fifteen (15) days prior to the first pre-hearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described above.
Not later than fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, a petitioner shall file a supplement to the petition-to intervene which must include a list of the cont.entions which are sought to be litigated in the matter, and the bases for each contention set forth with reason-able specificity.
Contentions shall be limited to matters within the scope of the amendment under consideration.
A petitioner who fails to file such a supple-ment 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 oppor-l tunity to participate fully in the conduct of the hearing, including the oppor-tunity 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 haz'ards 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 Commission 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.
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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.
Normally, the Commission will not issue the amendment until the 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 Commission take this action, it will publish 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 infreque.itly.
A request for a hearing or a petition for leave to intervene must be filed with tne Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, Attention:
Docketing and Service Branch, or may be delivered to the Commission's Public Document Room, the Gelman Building, 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 Commission by a toll-free telephone call to Western Union at (800) 325-6000 (in Missouri (800) 342-6700).
The Western Union operator should be given Datagram Identification Number 3737 and the following message addressed to John Stefano, Acting Project Director, Project Directorate III-1, Division of Reactor Projects III, IV, V, & Special Projects:
petitioner's name and telephone number; date petition was mailed; plant name; and publication
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, I 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, D.C. 20555, and to John Flynn, Esq., Detroit Edison Company, 2000 Second Avenue, Detroit, Michigan 48226, attorney for Detroit Edison Company.
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 Commission, the presiding officer or the presiding
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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 2.714(a)(1)(1)-
(v) and 2.714(d).
For further details with respect to this action, see the application for amendment which is available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street, N.W., Washington, D.C.
- 20555, and at the Monroe County Library System, 3700 South Custer Road, Monroe, Michigan 48161.
Dated at Rockville, Maryland, this 25th day of April.
FOR THE NUCLEAR REGULATORY COMMISSION Jo n S efano Acti rector Pr je t Di ctorate II-1 visio of Reactor Projects III, IV, IV, & Special Projects Office of Nuclear Reactor Regulation
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