ML19341B339
| ML19341B339 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/13/1981 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| Shared Package | |
| ML19341B340 | List: |
| References | |
| NUDOCS 8101300757 | |
| Download: ML19341B339 (7) | |
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7590-01 Uk1(ED STATES OF AMERICA N'*t. EAR REGULATORY COMMISSION In the Matter of
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POWER AUTHORITY OF THE STATE OF )
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(James A. FitzPatrick Nuclear
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Power Plant)
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Docket No. 50-333 ORDER FOR MODIFICATION OF LICENSE AND GRANT OF EXTENSION OF EXEMPTION I.
The Power Authority of the State of New York (the licensee) is the holder of Facility Operat ng License No. DPR-59 which authorizes the operation of the James A. Fit:Pa: rick Nuclear Power Plant at power levels up to 2436 megawatts thermal rated power. The facility consists of a boiling water reactor located at the licensee's site in Oswego County, New York.
II.
On February 28, 1978, the Commission granted to the licensee an interim
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exemption from the requirements of General Design Criterion 50, " Containment f
Design Basis," of Appendix A to 10 CFR Part 50 (Federal Register Vol. 43, No. 61, March 29, 1978). This exemption is related to the demonstrated safety margin of the Mark I containment system to withstan<l recently identified suppression pool hydrodynamic loads associated with postulated design basis loss-of-coolant accidents and primary system transients. Al though there v.as a reduction in the margin of safety from that called for by j
General Design Criterion 50, the Commission found that a sufficient margin would exist to preclude undue risk to the health and safety of the public for 3n interim period while a more detailed review was being conducted.
8101300757.
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. 7590-01 s
The Commission's evaluation was documented in the NRC staff's " Mark I Containment Short-Term Program Safety Evaluation Report," NUREG-0408, dated December 1977, which concluded that ne BWR facilities with the Mark I con-tainment design could continue to ope.te without undue risk to the health and safety of the public while a
~.e comprehensive Long-Tem Program was oeing conducted. N purpose of the Long.erm Program was to define design basis (i.e., conservative) loads that are appropriate for the anticipated life (40 years) of each EWR/ Mark I facility, and to restore the original intended design safety margins for each Mark I containment system. In order to provide uniform, consistent, and explicable acceptance criteria for the Long-Tem Program, the Summer 1977 Addenda of the ASME Boiler and Pressure Vessel Code have been used as the basis for defining the intended margin of safety, rather than using the particular version of the ASME Code which was applicable to the initial licensing of each facility. In some instances, the allowable stresses are higher under the later edition of the Code. The basis for acceptance criteria is described in the " Mark I Containment Long-Term Program Safety Evaluation Report," NUREG-0661, dated July 1980.
As a result of our review of the exteasive experi'.tental and analytical programs conducted by the Mark I Owner. Group, the NRC staff has concluded t
l that the Owners Group's prop'ssed load definition and structural assessment l
techniques, as set forth in the " Mark I Containment Program Lead Def nition Report," NEDO-21888, dated December 1978, and the " Mark I Containment Program i
Structural Acceptance Criteria Plant Unique Analysir Application Guide,"
l dated October 1979, (subsequently referred to as NEDO-21888 and NED0-24583-1, NED0-24583-1) and as modified in certain. details by the staff's Accertance t
. 7590-01 Criteria, will provide a conservative basis for determining whether any struc-tural or other plant modifications are needed to restore the original intended margin of safety in the containment design. The staff's Acceptance Criteria are contained in Appendix A to HUREG-0661. The basis for the staff's req irements and conclusions is also described in NUREG-0661.
III.
In letters dated March 12, 1979, each BWR/ Mark I licensee was requested by the NRC to submit a schedule for carrying out an assessment of the need for plant modifications for each of the licensee's BWR/ Mark I units, based on the Owners Group's proposed generic 1)ad definition and assess 1ent techniques, and for the subsequent insta11atio1 of the plant modifications determined to be needed by such an assessment.
In response to oer letter, the licensee's ' letters dated June 29,1979 and September 9,1980 indicated its commitment to undertake plant-unique assessmen:s based on the Owners Group's generic assessment techniques, to modify the plant systems as needed, and also indicated that its schedule for this effort would result in a plant shutdown to complete the plant modifications by October 31, 1981.
On October 31, 1979, the staff issued an initial version of its acceptance criteria to the affected licensees. These criteria were subsequently revised in February 1980 to reflect acceptable alternative assessment techniques which would enhance the implementation of this program. Throusnout the development of these acceptance criteria, the staff has worked closely wit'.1 the Mark I Owners Group in order to encourage partial plant-t-ique assest.ments an.1 modi-fications to be undertaken.
. 7590-01 The modification schedules submitted in response to the March 12, 1979 letter have subsequently been revised to reflect the development of the acceptance criteris c+! addi?,1osal information concerning plant modifications that will be n2eded to acmor:Lrate conformance with those criteria.
In consideration of the range of-ccmpletion estimates reflected by all of the affected licensees and the staff's assessment of the nature of the effort involved in the reas-sessment work and in the design and installation of the needed plant modifica-l-
tions, the staff has concluded that the licensee's proposed completion schedule is both prompt and practicable.
Under the circumstances, the NRC staff has determined that the licensee's commitment to undertake the reassessment of suppression pool hydrodynamic loads and to design and complete installation of the plant modifications, if any, needed to conform to the generic acceptance criteria by October 31,1981 shou' d '
be confirmed and formalized by Order.
4 IV.
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The Commission hereby extends the exemption from General Design Criterion 50' of Appendix A to 10 CFR Par.t 50 granted to the licensee on February 28, 1978, only for the time necessary to complete the actions required by Section V or VI of this Order. Substantial imprevements have already been made in the margins of safety of the containment systems and will continue to be improved -
l during this period whenever practicable, and, in any event, all.needed improve-J ments, if any, must be completed in accordance with the provisions of Section
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V or VI of this Order.
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The Commission has detemined that good cause exists for the extension of this exemption, that such exemption is authorized by law, will not endanger life or property or the common defense and security, and is in the public interest. The Commission has detemined that the granting of this exemption will not result in any significant environmental impact and that, pursuant to 10 CFR 51.5 (d)(4), an environmental impact statement or negative declara-tion and environmental impact appraisal need n9t be prepared in connection with this action.
V.
Accordingly, pursuant to the Atomic Energy Act of 1954, as amended, and the Commission's regulations in 10 CFR Parts 2 and 50, IT IS HEREBY ORDERED THAT the license be amended to include the following conditions:
1.
the licensee shall promptly assess the suppression pool hydrodynamic loads in accordance with NEDO-21888 and NEDO-24583-1 and the Acceptance Criteria, contained in pendix A to NUREG-0561.
2.
any plant modifications needed to assure that the facility confoms to l
the Acceptance Criteria contained in Appe1 dix A to NUREG-0661 shall be designed and its installation shall be completed not later than October 31, l
1981 or, if the plant is shutdown on that date, before the resumption of l
power thereafter.
VI.
i The licensee or any person whose interest may be affected by the Order set forth in Section V hereof may request a hearing within thirty days of the date of publi-l cation of this Order in the Federal Register. Any request for a hearing shall be addressed to the Director, Office of Huclear I'eactor Regulation, U. S. Nuclear
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. 7590-Oi Regulatory Commission, Washington, DC 20555, and to Cha rles M. Pratt, Assistant General Counsel, Power Authority of the State of New York,10 Columbus Circle, New York,10019, attorney for the licensee.
If a hearing is held concerning such Order, the issues to be considered at the hearing shall be:
1.
whether the licensee should be required to promptly assess the suppression pool hydrodynamic loads in accordance with the requirements of Section V of this Order; and, 2.
whether the licensee should be required, as set forth in Section V of this Order, to complete the design and installation of plant modifications, if any, needed to assure that the facility conforms to the Acceptai.ce Criteria contained in Appendix A to HUREG-0661.
The Order set forth in Section V hereof will become effective on expiration of the period during which the licensee may request a hearing or, in the event a hearing is held, on the date specified in an order issued following further proceedings on this Order.
VII.
For further details concerning this action, refer to the following documents which are available for inspection at the Commission's Public Document Room at 1717 H Street, NW, Washington, DC 70555 or through the Commission's local public document room at the State University College at Oswego, Penfield Library
- Documents, Oswego, New York 13126.
Alabama:
1.
" Mark I Containment Program Load Definition Report," General Electric Topical 1
Report, JEDO-21888, December 1978.
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4 I
' 7590-01 2.
" Hark I Containment Program Structural Acceptance Criteria Plant Unique Ana*ysis Applications Guide," General Electric Topical Report, NEDO-24583-1, October 1979.
3.
" Mark I Containment Long Term Program. Safety Evaluation Report,"
NUREG-0661, July 1980.
4.
Letter dated June 29, 1979 to T. A. Ippolito (NRC) from P. J. Early (PASNY).
5.
Letter dated September 9,1980 to T. A. Ippolito (NRC) from J. P. Bayne (PASNY).
6.
Letter to licensee dated January 13,19o1.
FOR THE NUCLEAR REGULATORY COMMISSION r
8 lit %l Darrell G. E enhut, Director Division of icensing Office of Nuclear Reactor Regulation Dated: January 13, 1981 Bethesda, Maryland 1
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