ML19281C928
| ML19281C928 | |
| Person / Time | |
|---|---|
| Issue date: | 07/30/1980 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19281C929 | List: |
| References | |
| FOIA-81-82, REF-GTECI-A-07, REF-GTECI-CO, TASK-A-7, TASK-CA, TASK-SE SECY-80-359, NUDOCS 8009090095 | |
| Download: ML19281C928 (15) | |
Text
July 30, 1980 SECY-80-359 COMMISSIONER ACTION For:
The Conmissioners From:
Harold R. Denton, Director Office of Nuclear Reactor Regulati Thru:
William J. Dircks Acting Executive Director for Operations
Subject:
RESOLUTION OF THE MARK I CONTAINMENT LONG-TERM PROGRAM (GENERIC TASK A-7)
Purpose:
Approval for the issuance of Orders to the licensees of BWR-Mark I facilities in order to complete the staff's efforts on Generic Task A-7 and confirm the completion dates for this program.
Discussion:
In SECY 79-606, dated November 6,1979, the status and inple-mentation plans for the Mark I Containment Long-Term Program (USI A-7) were described.
That document was the latest in a rather lengthy series of documents and discussions pertain-ing to the Mark I containment design.
Included in that report was the staff's. criteria tor the Mark I Long-Term Program.
On December 20, 1979, we met with representatives of the Mark I Owners Group to discuss the inplementation plans for this program.
Based on the ccaments made by the Owner's representa-tives in that meeting, we subsequently refined our acceptance criteria to allow the Mark I licensees reasona'>le latitude, consistent with our safety objective, such tht.t there would be a timely resolution of this issue.
On February 8,1980, we met with the ACRS full committee to discuss the revised staff criteria.
These criteria, their bases, and the ACRS letter are contained in the staff's
Contact:
D. Eisenhut, DL 49-27672 C. Grimes, DST 009090c g
The Comissioners Safety Evaluation Report for the Mark I Containment Long-Term Program (NUREG-0661), which is in the process of being published.
In letters dated February 28, 1978, the staff granted exemptions from General Design Criterion 50 of Appendix A to 10 CFR Part 50 to the Mark I licensees.
The Federal Register Notice of this action stated that "this exe@ tion is granted for an interim period of approximately two years while a more detailed review is conducted.
At the conclusion of this review, the design safety margin of the containment system"..."will be restored to that which was originally intended at the time" the plant "was licensed for operation." During the course of the Long-Term Program, most of the Mark I licensees have implemented plant modifications such that, in many cases, the margins of safety for the containment design currently exceed that reported for the Short-Term Program (NUREG-0408).
In letters dated March 12, 1979, we requested that each Mart I licensee submit schedules for the Mark I related modifications.
These schedules are summarized in Enclosure 1 and an example of a detailed plant-specific modification schedule is presented in Enclosure 2.
Some of the schedules reflect subsequent changes which evolved from changes in the generic program over the past year and recommendations by the staff for improved modification schedules.
We believe that it is appropriate at this time to confirm the completion dates for this program by issuing confirmatory Orders to the Mark I licensees,. like the sample shown in Enclosure 3, and to extend the exemptions previously granted to the Mark I licensees for the time necessary to coglete the long term modifications.
Upon co@letion of these modifications, Unresolved Safety Issue A-7 will be fully settled.
Coordination:
The Office of the Executive Legal Director has no legal objection to the proposed action and the sample Order.
\\30 Harold R. Denton, Director 1y Office of Nuclear Reactor Regulation
Enclosures:
1.
Mark I Modification Schedules 2.
Sagle Plant-Specific Modification Schedule 3.
Sagle Order for Modification of License and Extension of Exemption
. Commissioners' comments should be provided directly to the Office of the Secretary by c.o.b. Thursday, August 15, 1980.
Commission Staff Office comments, if any, should be submitted to the Commissioners NLT August 7,1980, with an information copy to the Office of the Secretary.
If the paper is of such a nature that it requires additional time for analytical review and comment, the Commissioners and the Secretariat should be apprised of when comments may be expected.
DISTRIBUTION Commissioners Commission Staff Offices Exec Dir for Operations ACRS ASLBP ASLAP Secretariat
MARK I MODIFICATION SCHEDUIES l
1980 l
1981 l
1982 ASONDJFMAMJJASONDJFMAMJJAS0NDJFMAMJJAS0ND Browns Ferry #1 XXXXXXXX Browns Ferry #2 XXXXXXXX Browns Ferry #3 XXXXXXX Brunswick #1 XXXX XXX XXXX Brunswick #2 XXXXX XXXX Cooper XXXX XXXX Dresden #2 XXXX0CXXXX Dresden #3 XXXXX XXXXXXXX Duane Amold XXXXXX XXXX FitzPatrick XXXXXXX XXXXXXC l
Hatch #1 XXXX XXXX Hatch #2 XXXX XXXX Millstone #1 XXXX XXXX Monticello XXXX XXXX Nine Mile Point XXXXXX Oyster Creek XXXX XXXX XXXX Peach Bottom #2 XXXXXXXX XXX V
1 Peach Bottom #3 XXX XXXXXXX Y
Pilgrim XXXXXXX Y
g 8
Quad Cities #1 XXXXXXX 8
Quad Cities #2 XXXXXXX XXXXXXXX
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h Vemont Yankee XX XX V Completion date for external modifications.
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of ) ) ) Docket No. ) ) ORDER FOR MODIFICATION OF LICENSE AND GRANT OF EXTENSION OF EXEMPTION I. (the licensee) is the h61 der of Facility Operating License No. DRP-which authorizes the licensee to operate the at power levels not in excess of megawatts thermal (rated power). The facility is a boiling water reactor located at the licensee's site in II. On February 28, 1978, the Commission granted to [ INSERT LICENSEE] an interim exemption from the requirements of General Design Criterion 50, " Containment Design Basis," of Appendix A to 10 CFR Part 50 (Federal Register Vol. 43, No. 61, March 29, 1978) [ NOTE: ORESDEN #2 - (Federal Register Vol. 43, No. 79, April 24,1978)] This exemption is related to the demonstrated safety margin of the Mark I containment system to withstand recently identified suppression pool hydrodynamic loads associated with postulated design basis loss-of-coolant accidents and primary system transients. Although there was a reduction in the margin of safety from that called for by General Design Criterion 50, the Commission found that a sufficient margin would exist to preclude undue risk to the health and safety of ti 3 public for an interim period while a more detailed review was being conducted. ENCLOSURE 3
. h 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 the BWR facilities with the Mark I con-tainment design could continue to operate without undue risk to the health and safety of the public while a more comorehensive Long-Term Program was being conducted. The purpose of the Long-Term Program was to define design basis (i.e., conservative) loads that are appropriate for the anticipated life (40 years) of each BWR/ Mark I facility, and to restore the original intended design safety margins for each Mart I cantainment system. The review of the Long-Term Program has now been complei.ed. As a result of our review of the extensive experimental and analytical programs conducted by the Mark I Owners Group, the NRC staff has concluded that the Owners Group's proposed load definition and structural assessment techniques, as set forth in the " Mark I Containment Program Load Definition Report," NEDC-21888, dated December 1978, and the " Mark I Containment Program Structural Acceptance Criteria Plant Unique Analysis Application Guide," NED0-24583-1, dated October 1979, (subsequently referred to as NED0-21888 and NED0-24583-1) as modified in certain details by the staff's Acceptance Criteria, will provide a conservative basis for determining whether any structural or other plant modifications are needed to restore the original intended margin of safety in the containment design. The staff's Acceptance Criteria are attached. The bases for the staff's requirements and conclusions are described in the Mark I Containment Long-Term Program Safety Evaluation Report, NUREG-0661.
. Since the staff has cogleted its generic evaluation and has determined that there are acceptable methods for assessing suppression pool hydro-dynamic loads for all elements of the Mark I containment design, I have determined that the public health, safety, and interest require that such assessments be completed as promptly as practicable, and that any plant modifications needed to conform to these accepted generic procedures should be designed and installed as soon as practicable. 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 load definition and assessment tech-niques, and for the subsequent installation of the plant modifications determined to be needed by such an assessment. In response to our letter, the licensee's letter (s) dated [ INSERT RESPONSE DATES] indicated its comit-ment to undertake plant-unique assessments 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 [ INSERT LAST OUTAGE DATE FOR EACH UNIT]. The nature of the changes in the acceptance criteria since our March 12, 1979 letter are such that they would not affect the time needed to design and install any required plant modifications beyond that expected from
. scheduling and material delivery uncertainties. Inasmuch as partial plant-unique assessments and modifications have been undertaken by the majority of affected licensees during the course of this program, and giving due consideration to the time which has elapsed since our March 12, 1979 letter, the time required to coaplete the development of the acceptance criteria, the range in completion estimates reflected in the responses from all licensees, and the staff's assessment of the nature of tne effort involved in the reassessment work and in the design and installation of the needed plant modifications, the staff has concluded that the licensee's proposed coapletion 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 com-plete installation of the plant modifications, if any, needed to conform to the generic acceptance criteria by [ INSERT LAST OUTAGE DATE FOR EACH UNIT] should be confirmed and formalized by Order, and that the public health, safety, and interest require that such Order be effective immediately. IV. The Commission hereby extends the exeaption from General Design Criterion 50 of Appendix A to 10 CFR Part 50 granted to the licensee on February 28, 1978, only for the time necessary to complete the actions required by the Order. Substantial improvements have already been made in the margins of safety of the containment systems and will continue to be improved during this period whenever practicable, and, in any event, all needed improvements, if any, must be conpleted not later than [ INSERT LAST GUTAGE DATE FOR EACH UNIT].
. The Commission has determined tnat 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 determined 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 statemert or negative declara-tion and environmental impact appraisal need not 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 NED0-21888 and NED0-24583-1 and the attached Acceptance Criteria; 2. any plant modifications needed to assure that the facility conforms to the attached Acceptance Criteria shall be designed and its installation shall be completed not later than [ INSERT LAST OUTAGE DATE FOR EACH UNIT], or, if the plant is shutdown on that date, before the resumption of power thereafter. VI. The licensee or any person whose interest maybe affected by the Order set forth in Section V hereof may request a hearing within thirty days of the date of such Order. Any request for a hearing will not stay the effectiveness of such Order. Any request for a hearing shall be addressed to the Director, Office
. of Nuclear Reactor Regulation, U. S. Nuclear Regulatory Comission, Washington, D. C. 20555. If a ht:arina 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.equirements of Section V of this 0rder; and, 2. whether the licensee should be required, as set forth ir Section V of this Order, to conplete the design and installation of plant modifications, if any, needed to assure that the facility conforms to the Acceptance Criteria attached to this Order. Operation of the facility on terms consistent with this Order is not stayed by the pendency of any proceedings on the Order. VII. For further details concerning this action, refer to the following documents which are available for inspection at the Comission's Public Document Room at 1717 H Street, N. W., Washington, D. C. 20555 or through the Comission's local public document room in [ INSERT LPDR]: 1. " Mark I Containment Program Load Definition Report," General Electric Topical Report, NED0-21888, December 1978. 2. " Mark I Containment Program Structural Acceptance Criteria Plant Unique Analysis Applications Guide," General Electric Topical Report, NED0-24583-1, October 1979.
. 3. " Mark I Containment Long Term Program Safety Evaluation Report," NUREG-0661, July 1980. 4. [ INSERT LICENSEE LETTERS REGARDING MODIFICATION SCHEDULES). 5. [ INSERT TRANSMITTAL LETTER FOR THIS ORDER]. FOR THE NUCLEAR REGULATORY COMMISSION Harold R. Denton, Di
- tor Office of Nuclear Reat. tor Regulation Effective Date:
Bethesda, Maryland}}