ML20040F118
| ML20040F118 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 01/19/1982 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| Shared Package | |
| ML20040F119 | List: |
| References | |
| NUDOCS 8202080342 | |
| Download: ML20040F118 (11) | |
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7590-01 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of Docket No. 50-277 PHILADELPHIA ELECTRIC COMPANY, ET. AL )
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(Peach Bottom Atomic Power Station
)
Unit No. 2)
)
MODIFICATION OF JANUARY 13,1981 ORDER I.
The. Philadelphia Electric Company (the licensee) and three other co-owners are the holders of Facility Operating License No. DPR-44 which authorizes the licensee to operate the Peach Bottom Atomic Power Station, Unit No. 2 (the facility) at power levels not in excess of 3293 megawatts thermal (r.ated power). The facility is a boiling water reactor located at the licensee's' site in Peach Bottom, York County, Pennsylvania.
II.
On January 13, 1981 the Comission issued an Order modifying the license requiri ng:
(1) the licens'ee to prorrptly assess the suppression pool hydro-dynamic loads in accordance with NED0-21888 and NED0-24583-1 and the Acceptance Criteria contained in. Appendix A to NUREG-0661 and (2) design and install any plant modifications needed to assure that'the facility conforms to the Acceptance Criteria contained in Appendix A to NUREG-0661.
The Order, published in the Federal Register on January'28,1981' (46 FR 9294) required installs-tion of any plant modifications needed to provide. compliance with the Acceptance Criteria in Appendix A to NUREG-0661 be completed not later than January 31, 1982, or, if the plant is shutdown on that date, before the resumption.
of power operation thereafter.
8202080342 820119 PDR ADOCK 05000277 P
7590-01
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III.
On October 31, 1979 the stc#f 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. Throughout the development of these acceptance criteria, the staff has worked clo:ely with the Mark I Owners Group in order to encourage partial plant-unique ossessments and modifications to be undertaken.
Since the development of these acceptance criteria, significant progress has been made by the licensee in meeting the Order requirements. However, in the June 29, 1981 Mark I Owners Group Status Summary Report, the licensee identified unforeseen difficulties and delays primarily related to one or more of the following: (1) torus and torus attached piping analyses; (2) equipment delivery; (3) the use of-interpretations and/or alternate approaches to the NUREG-0661 Acceptance Criteria; (4) plant-unique design and modification problens; and (5) slippages in refueling outages that have necessitated revision of the Order date. "
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The major modifications, which are those associated with the torus, vent system, internal structures and safety relief valve piping, which comprise approximately 4 -
75% of the total program effort, will be completed during the outage that is prior to or expected to coincide with the existing Order date.
The remaining items to be cogleted are primarily associated with the torus attached piping modifications.
The Comission believes that substantial improvements have already been made in the margins of safety of the containment systems and expects improvements will continue to be made during the period until all the modifications required for compliance with this Order are. completed.
The Comission further bel! eves an acceptable balance has been achieved between co@letion of the major modifications, which provide significant improvement in the safety margin, and the granting of additional time for conpletion of the remaining modifications which fully restore the originally intended safety margin.
In consideration of the range of completion dates submitted by all of the affected licensees and an assessment of the nature of the remaining effort involved in the analysis, design and installation of the needed plant modifications, the Comission has concluded that the licensee's proposed completion schedule is both responsive and practicable.
The Com'ssion has, therefore, determined to modify the January 13, 1981 Order to extend the previously imposid completion dates for needed plant modifications.
This Order continues in effect the exemption to General Design Criterion 50 of Appendix A to 10 CFR Part 50 granted on January 13, 1981.
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IV.
Accordingly, pursuant to the Atomic Energy Act of 1954, as amended, including Sections 103 and 1611, and the Comission's rules and regulations in 10 CFR Parts 2 and 50, IT IS ORDERED that the completion date specified in Section V of the January 13,1981, "0'rder for Modification of License," is hereby changed to read as follows:
"no later than the start of Cycle 6 for conpletion of the major modifications and no later than the start of Cycle 7 for completion of the remaining modifications." The Order of January 13, 1981, except as modified herein, remains in effect in accordance with its terms.
V.
The licensee may request a hearing on this Order within 30 days of the date of publication of this Order in the Federal Register.
A request for hearing shall be submitted to the Director, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Comission, Washington, D.C.
20555.
Copies of the request shall also be sent to the Secretary of the Comission and the Executive Legal Director at the same address.
If a hearing is req'uested by the licensee, the Comission will issue an order designating the time and place of,any such hearing.. If a hearing is held, the issue to be considered at such a hearing shall be whether the co191etion date s;.ecified.in Section V of the January 13, 1981,
" Order for Modification of License," should be changed to read as follows:
"no later than the start of Cycle 6 for conpletion of the major modifications and no later than the start of Cycle 7 for completion of the remaining modifications."
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0 This Order shall become effective upon expiration of the period within which a hearing may be requested or, if a hearing is requested, on the date specified in an order issued following further proceedings on this Order.
F R THE NUCLEAR REGULATORY COMMISSION t
I Darrell G.'Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Dated at Bethesda, Maryland, this 19th day of January 1982.
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7590-01 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
)
)
Docket No. 50-278 PHILADELPHIA ELECTRIC COMPANY, ET. AL (Peach Botto.n Atomic Power Station
)
Unit No. 3)
)
MODIFICATION OF JANUARY 13,1981 ORDER I.
The Philadelphia Electric Company (the licensee) and three other co-owners are the holders of Facility Operating Licensa No. DPR-56 which. authorizes the licensee to operate the Peach Bottom Atomic Power Station, Unit No. 3 (the facility) at power levels not in excess of 3293 megawatts thermal (rated power). The facility is a boiling water reactor located at the licensee's site in Peach Bottom, York County, Pennsylvania.
II.
On January 13, 1981 the Comission issued an Order modifying the license
~
requiring:
(1) the licensae to pronptly assess the suppression pool hydro-dynamic loads in accordance with NED0-21888 and NED0-24583-1 and the Acceptance
- teria contained in Appendix A to NUREG-0661 and (2) design and install any plant modifications needed to assure that the facility conforms to the Acceptance Criteria contained in Appendix d'to NUREG-0661.
The Order, published in the Federal Register on January 28,1981 (46 FR 9297) required installa-tion,0f any plant. modifications needed to provide compliance with the Acceptance Criteria in Appendix A.to NUREG-0661 be completed not later than January 31, 1982, or, if the plant is shutdown on that date, before the resumption of power operation thereafter.
7590-01 2
III.
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 enh'ance the implementation of this program.
Throughout the developn.ent of these acceptance criteria, the staff has worked closely with the Mark I Owners Group,in order to encourage partial plant-unique assessments and modifications to be undertaken.
Since the development of these acceptance criteria, significant progress has been made by the licensee in meeting the Order requirements. However, in the June 29, 1981 Mark I Owners Group Status Summary Report, the licensee identified unforeseen difficulties and delays primarily related to one or more of the following: (1) torus and torus attached piping analyses; (2) equipment delivery; (3) th'e use of interpretations and/or alternate approaches
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to the NUREG-0661 Acceptance Criteria; (4) plant-unique design and modification problens; and (5) slippages in refueling outages that have necessitated revision of the Order date.
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7590-01 3
.4x The major modifications, which are those associated with the torus, vent system, internal, structures and safety relief valve piping, which comprise approximately 75% of the total program effort have already been completed or are in the process of being completed during the current outage. The remaining itens to be completed are primarily associated with the torus attached piping modifications.
The Commission believes that substantial improvements have already been f
made in the margins of safety of the containment systens and expects
'n; improvements will continue to be made during the period until all the modifications required for compliance with this Order are completed.
The Commission further believes an acceptable balance has been achieved
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between completion of the major modifications, which provide significant improvement in the safety margin, and the granting of additional time for conpletion of the remaining modifications which fully restore the originally intended safety margin.
In consideration of the range of completion dates submitted by all of the affected licensees and an assessment of the nature.-
of the remaining effort involved in the analysis, design and installation of the needed plant modifications, the Commission has concluded that ' he t
licensee's proposed conpletion schedule is both responsive and practicable.
The Commission has, therefore, determined to modify the January 13, 1981 Order to extend the previously imposed completion dates for neeoed plant modifications.
Th.is Order continues in effect the exemption to General Design Criterion 50 of Appendix A to 10 CFR Part 50 granted on January 13, 1981.
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IV.
Accordingly, pursuant to the Atomic Energy Act of 1954, as ame,ded, including Sections 103 and 1611, and the Commission's rules and regulations in 10 CFR Parts 2 and 50, IT IS ORDERED that the completion date specified in Section V of the January 13,1981, " Order for Modification of License," is hereby changed to read as follows:
"no later than the start of Cycle 6."
The Order of January 13, 1981, except as modified herein, remains in effect in accordance with its terms.
V.
The licensee nay request a hearing on this Order within 30 days of the date of publication of this Order in the Federal Register.
A request for hearing shall be submitted to the Director, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555.
Copies of the request shall also be sent to the Secretary of the Commission and the Executive Legal Director at the same address.
If a hearing is requ,ested by the licensee, the Commission will issue an order designating the time and place of any such hearing.
If a hearing is held, the issue to be censidered at such'a hearing shall be whether the coaple. tion date specified in Section V of the: January 13, 1981,
" Order for Modification of License," should be changed to read as follows:,-
"no later than the start of Cycle 6."
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This Order shall become effective upon expiration of the period within which a hearing may be requested or, if a hearing is requested, on the date specified in an order issued following further proceedings on this Order.
FOR THE NUCLEAR REGULATORY COMMISSION I
Darre G; E s or Division of Licensing Office of Nuclear Reactor Regulati,on Dated at Bethesda, Maryland, this 19th day of January 1982.
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