ML20058L525
| ML20058L525 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/01/1990 |
| From: | Jaffe D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058L532 | List: |
| References | |
| NUDOCS 9008070273 | |
| Download: ML20058L525 (9) | |
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHEAST NUCLEAR ENERGY COMPANY, ET. Al s
DOCKET 110. 50-423
-NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT T0 t
FACILITY OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION AND OPPORTUNITY FOR HEARING The U.S. Nuclear Regulatory Commission (the Commission) is considering.
i issuance of an amendment to Facility Operating License No. NPF-49, issued to Northeast Nuclear Energy Company, et. al. (the licensee) for operation of Millstone Unit No. 3 located in New London County, Connecticut.
Millstone Unit 3 Technical Specification (TS) 4.6.6.1.a requires that each of two Supplemental Leak Collection and Release Systems (SLCRS) demonstrate a flow rate of 9,500 cfm i 10% every 31 days on staggered test basis.
On July 16, 1990, the 'B' SLCRS fan failed its monthly performance (Surveillance 4.6.6.1.a) test with 85 percent of 9500 cfm.
The minimum required flow per Surveillance 4.6.6.1.a is 9500 cfm i 10 percent.
The 'B' SLCRS train was declared inoperable, and the plant entered a 7-day ACTION statement per the requirements of TS 3.6.6.1.
On July 20, 1990, the licensee subm :.ted an application for license amendment and request for temporary waiver concerning the requirements of TS 3/4.6.6.1.
The application for license amendment would incorporate a revised SLCRS flow rate, based upon testing i
completed on July 20, 1990, in TS 4.6.6.1.a., 4.6.6.1.b.1 and 3, 4.6.6.1.d.1, 4.6.6.1.e and 4.6.6.1.f.
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- Section 6.5.1.2 of the Millstone Unit 3 FSAR indicates that:
The SLCRS system is designed to maintain a 0.25 inches [ water gage] wg negative pressure in the containment enclosure building and associated contiguous structures (auxiliary building, ESF building, main steam valve building, and hydrogen recombiner building) during LOCA.
This is accomplished by exhausting air from these areas passing it through a charcoal filter assembly before releasing to atmosphere.
One purpose of the Surveillance Requirements of TS 3/4.6.6.1 is to demonstrate that SLCRS will attain adequate flow to produce the required 0.25 inches wg negative pressure within 60 seconds following a LOCA (50 seconds from a system start signal).
The licensee indicated in its July 20, 1990, letter that the required SLCRS flow rate of 9,500 cfm 10%.is based upon blower name plate data rather than test requirement's flow rate data.
On July 20, 1990, the c) licensee tested the SLCRS and found that a flow rate of 7040 scfm would produce a 0.25 inches wg negative pressure in less than 30 seconds.
The licensee proposed a SLCRS flow rate of 7,600 cfm to 9,800 cfm to replace the 9,500 cfm 10% requirement of TS 3/5.6.6.1.
The NRC staff issued a Temporary Waiver of Compliance regarding TS 3.6.6.1 on July 23, 1990.
i 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.
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The Commission has made a proposed determination that the July 20, 1990, amendment request involves no significant hazards considerations.
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 L
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- o. 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 licensee has determined that the Technical Specificat %ns Change Request involves no significant hazards considerations as defined in 10 CFR 50.92.
That determination is as follows:
The proposed change does not involve a significant consideration because the change would not:
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Involve a significant increase.in the probability or consequences of an accident previously analyzed.
In the event of a DBA such as loss-of-coolant accident (LOCA), aethity is released to the containment atmosphere.
The SLCRS collects most of the primary containment leakage from the buildings contiguous to the containment, filters it, and releases it to the atmosphere through the Millstona Unit No I stack.
The SLCRS is not normally in operation.
The SLCRS-starts on an SIS and is required by Technical Specification 4.6.6.1.d.3 to be able to draw -0.25 inch wg in the annulus within 50 seconds after a start signal.
In the accident analysis for Millstone Unit No. 3 (FSAR Section 15.6.5.4), it is assumed that the SLCRS:will be able to achieve -0.25 inch wg pressure in the annulus within 60 seconds.
Until this time, it is assumed that all of the containment leakage is an unfiltered ground level-release.
After the negative pressure is attained, only a small fraction of containment. leakage (e.g., secondary containment bypass leakage) is not assumed to be processed by the SLCRS. With the reduced flow rate, the SLCRS will still be capable of meeting the existing Technical Specification surveillance requirements.
Therefore, the proposed change will have no impact on the ability of the SLCRS to meet the performance requirements as assumed in the design basis analysis.
The proposed revised flow rate will not change the assumptions of the radiological consequence analysis concerning the filter efficiencies. Therefore, the proposed change will not adversely affect the calculated off-site doses.
In addition, the proposed change does not have an impact on the probability of an accident.
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Create the possibility of a new or different kind of accident from that previously analyzed, t
The preposed change will hsve no impact on plant response.
No physical design changes see proposed.
Only the minimum flow rate specified in the surv=111ance requirement is affected.
As discussed above, evin at the lower flow rate, the SLCRS will perform as assumed in the design basis analysis.
There are no few failurs modes introduced.
3' Involve a significant reduction in a margin of safety.
The proposed change has no direct impact on any protective boundaries. As discussed above, the proposed change will not affect the ability of the SLCRS to perform its safety function as assumed in the design basis analysis.
The proposed change does not affect the consequences of any accident previously analyzed.
Therefore, there is no significant reduction in the margin of safety.
The staff has reviewed the licensee's no significant hazards consideration determination analysis and agrees with its conclusion.
Therefore, the staff proposes to determine that the application for amendment does not involve a significant hazards consideration.
The Commission is seeking public comments on this proposed determination.
l Any comments received within fifteen (15) 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.
I Written comments may also be delivered to Room P-223, Phillips Building,
. 7920 Norfolk Avenue, Bethesda, Maryland, from 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.
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, the licensee may file a request for a hearing with respect to issuance of the amend.nent to the subject facility operating
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license and any person whose interest may be affected by this proceeding and
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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.
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, N.W., Washington, D.C.-20555 and at the Local Public Document Room located i
at the learning Resources Center, Thames Valley State Technical College, 574 New London Turnpike, Norwich, Connecticut 06360.
If a request for a hearing or 6
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 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 hearing or an appropriate order.
y 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, i
l-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
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6-1 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 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 petitioner wishes to intervene.
Any person who has i
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 prehearing 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 contentions which are sought to r
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.
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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 e
l expert opinion.
Petiticier must provide sufficient information to show that a genuine dispute exists with the applicant on a material issue of law or fact.
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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 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 the,, amendment is issued before the expiration of 30-days, the Commission will make a final determination on the issue of no significant hazards consideration.
If a hearing is requested, 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.
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 15-day notice period.
However, should circumstances change during the notice period, such that failure to act in a timely way would result, for example,
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- in.derating or shutdown of the facility, the Co6' mission may issue the license amendment before the expiration of the 15-day no'; ice period, provided that its final determination is that the amendment involve 3 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.
The Commission 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 Commission, U.S. Nuclear Regulatory Commission,-
Washington, D.C. 20555, Attention:
Docketing and Services' Branch, or roay 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 1-(800) 325-6000 (in Missouri 1-(800) 342-6700).
Tho Western Union operator should be given Datagram Identification Number 3737 and the l'
following message addressed to John F. Stolz:
(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, D.C. 20555, and to Gerald Garfield, Esquire, Ocy, Berry & Howard, Counselors at Law, City Place, Hartford, Connecticut 06103-3499,; attorney for the licensee.
. fL I 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 presid ng 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 1) CFR 2.714(a)(1)(i)-(v) and 2.714(d),
For further details with respect to this action, see the application for amendment dated July 20, 1990, 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 Local Public Document Room located at the Learning Resources Center, Thames Valley State Technical College, 574 New London Turnpike, Norwich, Connecticut 06360.
Dated at Rockville, Maryland, this 1st day of August,1990.
FOR THE NUCLEAR REGULATORY COMMISSION I
DahidH.Jaf, Project Manager Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation 1'
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