ML20214G116
| ML20214G116 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/18/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214G119 | List: |
| References | |
| TAC-63412, NUDOCS 8611250579 | |
| Download: ML20214G116 (8) | |
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i 7590-01 8
UNITED STATES NUCLEAR REGULATORY COPWISSION GEORGIA POWER COMPANY, ETAL.
4 DOCKET N0. 50-366 NOTICE OF CONSIDERATION OF ISSUANCE OF AHENDMENT TO FACILITY OPERATING LICENSE AND PROPOSED NO SIGNIF4 CANT 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. NPF-5 issued to Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, City of Dalton, Georgia, for operation of the,Edwin f
I. Hatch Nuclear Plant, Unit No. 2 located in Appling County, Georgia.
i The amendment would modify the Technical Specification Sections related to operability requirements for the Main Control Room Environmental Control System (MCRECS) to (1) delete the requirement for automatic actuation of the control room pressurization mode of operation of the MCRECS upon receipt of a I
low-low reactor vessel water level signal, (2) change the requirement for j
automatic actuation of the control room pressurization mode of the MC, RECS upon receipt of a high radiation signal in the refueling floor exhaust to require automatic actuation based on a high radiation signal in the refueling floor area (i.e., the word " exhaust" would be replaced by the word " area"), (3) i change the location and format of the requirements related to the operability of the MCRECS to clarify and facilitate their use, (4) correct errors in the i
identification numbers listed for instrumentation that provides actuation signals for operation of the MCRECS, and (5) augment the MCRECS applicability j
8611250579 861121 DR ADOCK 05000366 PDR i
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. requirements (Operational Conditions for which the MCRECS is required to be operable) to include additional Operational Conditions.
1 Proposed changes (1) and (2) above are needed to make the Technical Specifications compatible with the existing plant design and the design as described and evaluated in the Hatch Unit 2 Final Safety Analysis Report.
4 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.
i The Comission has made a proposed determination that the amendment t
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 accident previously evaluated; or (3) involve a significant i
reduction in a margin of safety.
With respect to change (1), the existing Technical Specification:
requires that the control room pressuriz3 tion mode of MCRECS operation be automatically actuated upon receipt of a low-low (Level 2) reactor vessel l
water level signal and upon receipt of a low-low-low (Level 3) reactor vessel i
water level signal. The Standard Review Plan and the Standard Technical Specifications do not specify a requirement for actuation of the control room pressurization mode based on low reactor vessel water level. Thus removal of one of the two actuation requirements based ca low reactor l
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, vessel water level is acceptable.
In addition, the existing Technical Specification also requires actuation of the control room pressurization mode based on high drywell pressure. Thus the remaining low-low-low reactor vessel water level together with this high drywell pressure actuation requirement continue to provide diverse LOCA signal actuation of the control
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room pressurization mode, and the elimination of the redundant reactor vessel water level actuation requirement does not significantly change the safety margin provided by the current Technical Specification requirements.
With respect to change (2), the location of the radiation monitors that will actuate the control room pressurization mode of MCRECS operation will be area radiation monitors and will be located in the refueling floor area close to the exhaust ducts rather than inside the ducts as currently required.
Because these area radiation monitors will be in a direct line of sight to the refueling pool surface, they should respond to direct radiation from any bubbles that rise to the top of the pool and therefore should provide quicker 4
actuation of the pressurization mode of operation than would the currently required monitor inside the exhaust ducts which has less exposure to direct radiation.
In addition, because the area radiation monitors will be located close to the exhaust ducts they should detect any radioactive gases that l
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would be detected by monitors located inside the ducts. Therefore, the proposed requirement is essentially equivalent and possibly provides improved detection of radioactive releases and actuation of the control room pressurization mode.
Changes (3) and (4) do not modify any current Technical Specification requirements. They change the location and format of information and correct instrument numbers related to MCRECS requirements.
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. Change (5) adds requirements a) that the control room isolation mode of MCRECS operation shall be operable when the reactor is in the Cold-Shutdown.
Operational Condition and b) that the MCRECS be operable when the reactor is in the Refueling Operational Condition and when irradiated fuel is being handled in the secondary containment. This addition should increase the
' safety of operation in these situations None of the above proposed modifications change the existing plant design or require modification of the accident analysis as described in the Hatch 2 Final Safety Analysis Report, nor do the proposed modifications change the manner in which the plant is operated. Accordingly, the changes are not expectedto(1)increasetheprobabilityorconsequencesofanaccident previously evaluated; or (2) create the possibility of a new or different l
kind of accident previously evaluated; or (3) involve a significant reduction 1
in a margin of safety.
On the basis of the above, the Comission has determined that the requested amendments meet the three criteria and therefore has made a proposed determination that the amendment application does not involve a significant hazards consideration.
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 Comission will not normally make a final determination unless it receives a request for a hearing.
l Written comments should be addressed to the Rules and Procedures Branch, Division of Rules and Records, Office of Administration, U.S. Nuclear Regulatory Comission, Washington, D.C.
20555, and should cite the h__-
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publication date and page number of this FEDERAL REGISTER notice. Copies of comments received may be examined at the NRC Public Document Room, 1717 H i
Street, NW, Washington, D.C.
By December 26, 1986
, the licensee may file a request for a hearing with, respect to issuance of the amendment to the subject facility operating liceUseandanypersonwhoseinterestmaybeaffectedbythisproceedingand who wishes to participate as a party in the proceeding must file a written i
petition for leave to intervene. Request for a hearing 'and petitions for t
leave to intervene shall be filed in accordance with the Comission'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 i
above date, the Commission or an Atomic Safety and Licensing Board, designated by the Comission or by the Chainnan of the Atomic Safety and Panel, will rule on the request and/or petition and the Secretary or the designated Atomic 4
Safety and Licensing Board will issue a notice of hearing or an appropriate order.
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As required by 10 CFR 62.714, 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 pennitted with particular reference to the following factors: (1)thenature 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 I
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 fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, but such an amended petition must satisfy th'e 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 1
petition to intervene which must include a list of the contentions which are i
sought to be litigated in 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.
l Those permitted to intervene become parties to the proceeding, subject to l
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.
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If a hearing is requested, the Comission will make a final determination on the issue of no significant hazards consideration. The final determination l
will serve 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 held would take place after issuance of the amendment.
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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.
1 Normally, the Commission will not issue the amendment until the 4
expiration of the 30-day notice period. However, should circumstances change
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during the notice period such that failure to act in a timely way would result ir, derating or shutdown of the facility, the Comission may issue the license i
amendment before the expiration of the 30-day notice period, provided that its final determination is that the amendment involves no significant hazards 1
i consideration. The final determination will consider all public and State coments received. Should the Comission 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 infrequently.
A request for a hearing or a petition for leave to intervene must be i
filed with the Secretary of the Comission, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, Attn: Docketing and Service Branch, or t
may be delivered to the Comission's Public Document Room,1717 H Street, NW, t
l Washington, D.C., by the above date. Where petitions are filed during the l
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 l
l Union at (800) 325-6000 (in Missouri (800) 342-6700). The Western Union operator should be given Datagram Identification Number 3737 and the following l
I message addressed to Daniel R. Muller, Director, BWR Project Directorate #2, Division of BWR Licensing: 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-Bethesda, U. S. Nuclear Regulatory Commission, Washington, D.C.
20555, and to Bruce W. Churchill, Esquire, Shaw, Pittman, Potts & Trowbridge, 1800 M Street, N.W., Washington, D.C.
20036, 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 presiding Atomic Safety and Licensing Board, that the petition and/or request should be granted based upon a balancing of factors specified in 10 CFR 2.714(a)(1)(1)-(v)and2.714(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, 1717 H Street, NW, Washington, D.C., and at the Appling County Public Library, 301 City Hall Drive, Baxley, Georgia.
Dated at Bethesda, Maryland, this 18th day of November 1986.
FOR THE NUCLEAR REGULATORY COMMISSION
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V Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing Lc -
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