ML20056A569
| ML20056A569 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 08/06/1990 |
| From: | Wang A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056A568 | List: |
| References | |
| NUDOCS 9008080237 | |
| Download: ML20056A569 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMIS$10N CONNECTICUT YANKEE ATOMIC POWER COMPANY 1
DOCKET NO. 50-213 a
a NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO
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FACILITY OPERATING LICENSE AND PROPOSED NO $1GNIFICANT HAZARDS 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. DPR-61, issued to Connecticut Yankee Atomic Power Company (the licensee), for operation of the Haddam Neck Plant located in Middlesex County, Connecticut.
The amendment would add an exception from the requirements of Technical Specification 4.0.4 to Surveillance Requirements 4.7.1.2.2.a. b and c for entry into Mode 3.
With the current Technical Specifications the plant cannot progress from
-Mode 4 to Mode 3 until it has demonstrated auxiliary feedwater system operability (surveillance requirement 4.7.1.2.2).
In order to demonstrate auxiliary feedwater system operability the plant must be in Mode 3 (or higher) when secondary ste'am temperature and pressure are sufficient to operate the auxiliary feedwater pumps.
The Commission has determined that exigent circumstances exist as the Technical Specifications prevents the resumption of power plant operation.
The NRC staff issued a Temporary Waiver of Compliance regarding TS 4.7.1.2.2 on July 27, 1990.
t 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.
l 9008080237 900803 PDR ADOCK 05000213 P
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2 The Comission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Comission'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 accident previously evaluated; or (3) involve a significant reduction in a margin of safety,
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The licensee has reviewed the proposed request and has provided the following no significant hazards consideration determination:
The proposed change would not involve a significant hazards consideration because the change would not:
1.
Involve a significant increase in the probability of occurrence or consequences of an accident previously analyzed.
Since assurance of operability of auxiliary feedwater in Modes 1 and 2 is not affected, design basis accidents which are postulated to occur during power operation will not be affected.
Only those accidents initiated from suberitical (i.e., Mode 3) conditions such as steam line break or uncontrolled rod withdrawal could be affected.
Also, the effect of this change on decay heat removal with main feedwater unavailable (e.g., due to a loss of normal powir I
(LMP),etc)hasbeenevaluated.
for accidents which can have significant consequences during i
Mode 3 operation, such as steam line break, operation of auxiliary feedwater typically results in more se<ere consequences (i.e.,increasedcooldown).
Since decay heat 1; ads are significantly reduced at the time of transition from Mode 4 '.o Mode 3, auxiliary feedwater flow requirements are far less significant than for other limiting transients initiated from power.
Therefore, not having demonstrated operability of auxiliary feedwater prior to entry into Mode 3 will not result in increased consequences of any design basis accident initiated from Mode 3.
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e With respect to long-term decay heat removal, in Mode 3, only i
the steam generators are available for decay heat removal, and auxiliary feedwater is the only safety-related system for supplying water to the steam generators.
In the event that auxiliary feedwater fails while in Mode 3, a cooldown to residual heat removal (RHR) entry conditions would be required in order tu reestablish stable long-term decay heat removal.
4 T.S 3.4.1.2 requires at least two steam generators to be operable during Mode 3.
With a minimum indicated level, each steam generator has a substantial amount of water available to cool down the reactor coolant system (RCS), especially considering the fact that decay heat load is significantly reduced.
The low decay heat load would provide a substantial amount of time for manual actions to align / start auxiliary feedwater, or to restore the AFW system or additional steam generators to operable statut,, while the (RCS) is maintained hot with decay heat removal through the steam generator safety valves.
Based on the above, it is concluded that not having demonstrated operability of the auxiliary feedwater system under the conditions wh:en the 4.0.4 exemption would apply will not have any significant impact on the ability to maintain adequate long-term decay heat removal.
The proposed change has no impact on the probability of occurrence of any design basis accident.
In addition, there is no impact on the probability of failure of AFW.
No physical changes or changes in operating procedures are proposed.
2.
Create the possibility of a new or different kind of accident from any previously evaluated.
The possibility of an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report is not created.
Since there are no changes in the way the plant is operated, the potential for an unanalyzed accident is not created.
No new failure modes are introduced.
3.
Involve a significant reduction in a margin of safety.
l The proposed changes do not have any adverse impact on the protective boundaries.
The margin of safety, as defined in the basis for any Technical Specification, is not reduced.
The proposed ch.anges do not adversely impact any of the safety systems, nor do they increase the number of challenges to the safety systems.
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Accordingly, the Commise n proposes to determine that this change does i
not involve a significant hazards consideration.
The Commission is seeking public comments on this proposed determination.
Any coments received within fif teen (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, Written comments may be submitted by mail to the Regulatory Publications Branch, Division of Freedom of Information and Publications Services, Office of Administration, 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-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, NW, Washington, D.C.
The filing of requests for hearing and petitions for leave to intervene is discussed below.
By September 10, 1990, 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 hearing and a petition for leave to intervene.
Requests for a hearing and petitions for leave to intervene shall be filed in accordance
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5 with the Commission's " Rules of Practice for Domestic Licensing Proceedings" in
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Interested persons should consult a current copy of 10 CFR 2.714 which is available at the Commission's Public Document Room, the i
Gelman Building, 2120 L Street, N.W., Washington, D.C. 20555 and at the Local 1
Public Document Room located at Russell Library,123 Broad Street, Middletown, Connecticut 06457.
If a request for a hearing or petition for leave to intervene is filed by the 1
above date, the Commission or an Atomic Safety and Licensing Board, designated l
by 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 l
designated Atomic Safety and Licensing Board will issue a notice of hearing or i
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 l
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 che following factors:
(1) the nature of the petitioner': eight under the Act to be made a party to the proceeding; (2) the nature and extent of the petitioner's property, financial, or other l
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 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 fif teen (15) days pr.ior to the first prehearing conference scheduled in the proceeding, but suca an amended petition must satisfy the specificity requirements described above.
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6-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 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 i
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 te 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 entitic 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 pemitted 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, s'id have the opportunity I
to participate fully in the conduct of the hearing, including the opportunity l
to present evidence and cross-examine witnesses.
If the amendment is issued before the expiration of 30-days, the Comission will make a final determination on the issue of no significant hazards consideration.
If a hearing is requested, the final determination will serve l
to decide when the hearing is held.
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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 i
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, in derating or shutdown of the facility, the Commission may issue the license amendment before the expiration of the 15-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 in the FEDERAL REGISTER a notice of issuance.
The Commission expects that the need to take this action will occur very infrequently.
i A request for a hearing or a petition for leave to intervene must be filed with the Secretary of the Connission, U.S. Nuclear Regulatory Commission.
Washington, D.C. 20555, Attention:
Dock 6 ting and Services 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) dt.ys of the notice period, it is tr. quested that the petitioner promptly so inform the Connission by a toll-free telephone ceil to Western Union at 1-(800) 325-6000 (in Missouri 1-(800) 342-6700).
7% Western
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Union operator should be given Datagram Identification Number 3737 and the 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 Oce of the General Counsel, U.S. Nuclear Regulatory Commission, i
Washington, D.C.
3.L.i, and to Gerald Garfield,-Esquire, Day, Berry & Howard, Counselors at Law City Place, Hartford, Connecticut 06103-3499, attorney for the licensee.
Nontimely filings of petitions for leave to intervene, amended petitions,s supplemental petitions and/or requests for hearing will not be entertained absent a determination by the Commission, the presiding officer or the presiding 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. dated July 26, 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, Russell Library, 123 Broat Street, Middletown, Connecticut 06457.
Dated at Rockville, Maryland, this 6th day of August,1990.
FOR THE NUCLEAR REGULATORY CONNISSION kg itM[
Alan B. Wang, Project Manager Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation X