ML20085M786
| ML20085M786 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/11/1983 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20085M789 | List: |
| References | |
| TAC-49637, NUDOCS 8311090363 | |
| Download: ML20085M786 (9) | |
Text
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e 7590-01 i
UNITED STATES NUCLEAR REGULATORY COMMISSION FLORIDA POWER CORPORATION, ET AL DOCKET NO. 50-302 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARD,S_
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-72, issued to Florida Power. corporation, City of Alachua, City of Bushnell, City of Gainsville, City of Kissimmee, City of Leesburg, City of New Smyrna Beach and Utilities Commission, City of 'New Smyrna Beach, City of cal a, Orlando Utilities Commission and City of Orlando, Sebring Utilities Commis-sion, Seminole Electric Cooperative, Inc., and the City of Tallahassee (the licensees), for operation of the Crystal River Unit No. 3 Nuclear Generating Plant (the facility) located in Citrus County, Florida.
The proposed amendment would revise the Crystal River Unit 3 Technical Specifications insofar as which section of tile Technical Specifications contains requirements for the emergency feedwater system ultrasonic flow indicator.
Following the Three Mile Island, Unit 2 accident, the Commission required installation of control-grade direct indication of auxiliary (or emergency) feedwater into all steam generators at each operating nuclear -
t power plant.
These indicators were not intended to be safety-related 8311090363 831011 PDR ADOCK 05000302 P
7590-01 2-instrumentation but instead an interim measure pending upgrading auxiliary feedwater systems as a whole -to safety-grade. When these interim feedwater flow indicators were installed at Crystal River 3, the corresponding Technical Specification requirements were placed in the section dealing with the emergency feedwater system (Section 4.7.1.2) rather than in the section dealing with post-accident monitoring instrumentation (4.3.3.6).
The result of this. oversight has been an unnecessary restriction on operability of the Crystal River Unit 3 emergency feedwater system.
Specifically, by having the operability requirement in the system section of the Technical Specifi-cations, an entire train of the emergency feedwater system must be declared inoperable if the control-grade ultrasonic flow sensor is not functioning properly.
This could result in placing the entire reactor plant in a shutdown condition if the instrument could not be repaired within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
The licensees consider that this would constitute an unnecessary and unintended cycle on the plant.
The licensees submitted an application for amendment to make this change on February 7,1983.
Before issuance of the proposed license amendment, the Commission will have made findings required by the Atemic 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 r
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7590-01 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 po:sibility of : new cr different kind of accident fec: any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
The Commission has provided guidance concerning the application of these standards by providing certain examples (48'FR 14870).
One of the examples of guidance regarding actions not likely to involve significant hazards considerations is a change which either may result in some increase to the probability or consequences of a previously analyzed accident or may reduce in some way a safety margin, but where the results of the change are clearly within all acceptable criteria with respect to the system or component specified in the Standard Review Plan.
The proposed change, although largely administrative in nature, does slightly alter the nature of the monthly operational check of the ultrasonic feedwater flow instrument and removes tne existing requirement that declarir.g this instrument inoperable renders an entire emergency feedwater train inoperable.
By classifying this instrument as a post-accident monitoring instrument I
rather than part of the emergency feedwater system, the action statement for restoring operability would have an associated time limit of 30 days rather than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
This instrumentation was installed on an interim basis as a redundant indication of energency (or auxiliary) i l
l l
75900-01 feedwater flow during an abnormal event or accident.
Other indications, primarily steam generator level indication, are also used to verify proper operation of tnis system.
lnese indicators are, in fact, non-safety grade post-accident monitoring instruments.
The Technical Specification change requested by the licensees is cons' sten,t with the Standard Technical Specifications (STS) for Babcock & Wilcox Pressurized Water Reactors (NUREG-0103), as well as with the Technical Specifications for other operating Babcock & Wilcox plants, in that the auxiliary feedwater ficwrate instrumentation is included in the accident monitoring instrumentation section and not in the auxiliary feedwater system section.
Therefore, the Commission proposes to determine that the amendment will involve no significant hazards considerations.
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.~
Comments should be addressed to the Secretary of the Con. mission, U.S.
Nuclear Regulatory Commission, Washington, D.C.
20555, Attn:
Docketing and Service Branch.
7590-01 By November 28, 1983, the licensees 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 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 Chainnan 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.
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 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 ' actors:
(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 proceeding as to which petitioner wishes to intervene.
Any per, son who has
7590-01
- 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 be litigated i'n the matter, and the bases for each contention set forth with reasonable specificity.
Contentions shall be limited to matters within the scope of the amendment under consideration.
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 evidenct. add cross-examine witnesses.
If a hearing is requested, the Canmis: ion will make a final determination on the issue of no significant hazards consideration.
Tne final determina-tion will serve to decide when the hearing is held.
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7590-Oi
. If the final determination is that the amendment request involves no significant ha7ards consideration, tha Cnmmission may issue the amendment i
i and make it effective, notwithstanding the request for a hearing.
Any i
hearing held would take place after issuance of the amendment, l
It 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 expir-ation of the 30-day notice period.
However, should circumstances change during the notice period such that failure to act in a timely way would j
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 consideratica.
The final determination will consider l
all public and State comments received.
Should the Commission take this i
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 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 Reaulatory Commission, O
7590-01 Washington, D.C. 20555. Attention: Docketing and Service Branch, or may be delivered to the Commission's Public Document Room,1717 H 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 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 Executive Legal Director, U.S. Nuclear Regulatory Commissior, Washington, D.C.
20555, and to S. A. Brandimo're, Florida Power Corporation, Vice President and General Counsel, P. O. Box 14042, St. Petersburg, Florida 33733.
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 Atomic Safety and Licensing Board designated to rule on the petition and/or request, that the petitioner has made a substantial showing of good cause for the granting of a late petition and/or request.
That determination will be based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(1)-(v) and 2.714(d).
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O 7590-01
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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 Commission's Public Document Room,1717 H Street, N.W., Washington, D.C., and at the Crystal River Public Library, 668 N.W. First Avenue, Crystal River, Florida.
Dated at Bethesda, Maryland, this lith day of October 1983.
FOR THE NUCLEAR REGULATORY COMMISSION l
Joh F. Stolz, Chief j
Opefating Reactors Bra d #4 gDi ision of Licensing 1
-n.