ML20057E170
| ML20057E170 | |
| Person / Time | |
|---|---|
| Issue date: | 10/01/1993 |
| From: | Murley T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9310080014 | |
| Download: ML20057E170 (6) | |
Text
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October 1,1995 MEMORANDUM TO:
Files DRAFT COPY OF ALTERNATE LICENSE RENEWAL RULE At the Licensee Renewal Wcrkshop on September 30, 1993, I was given a copy of the enclosed draft altern' ate' License Renewal Rule by a represent'ative of Yankee Atomic Electric Corp.
OriginalBigned W ThomasE.MurleY.
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Thomas E. Murley,. Director Office of Nuclear Reactor
. Regulation
Enclosure:
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DRAFT
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R-3 9/28/93 AN ALTERNATIVE APPROACH (BOUNDING ANALYSES)
REQUIREMENTS FOR RENEWAL OF OPERATING LICENSES FOR NUCLEAR POWER PLANTS l
L Sections deleted from existine Part 54.
]
54.3 Definitions.
Age-Related Degradation Unique to License Renewal Effective Program Integrated Plant Assessment Systems, Structures and Components (SSCs) Important to License Renewal 54.21(b)
CLB Changes.
(e)
CLB changes during NBC review of application.
54.22 Contents of application - technical specifications.
54.25 Report of the Advisory Committee on reactor safeguaras.
54.33(d)
Maintenance of programs l
54.37(b)
Annual FSAR update.
(c)
Annual list of program changes.
2.
Sections retained intact from existing Part 54.
5
4.1 Purpose and Scope
54.3 Definitions Current Licensing Basis Nuclear Power Plant Renewal Term j
54.5 Interpretations i
54.7 Written Communications i
54.9 Information collection requirements: OMB approvat 54.11 Public inspection of applications.
54.13 Completeness and accuracy ofinformation.
i 54.15 Specifi.: exemptions.
54.17 Filing of application.
54.19 Contents of application - general information.
54.23 Contents of application - environmentalinformation.
54.29(b)
Satisfaction of10 CFR 5L 1
(c)
Addressal of 2.758 issues.
54.31 Issuance of a renewed license.
54.33(a)
Applicability of 10 CFR 50.54.
(c)
Environmentallicense conditioni (e)
Legal status of licensing basis (as riew (d)).
54.35 Requirements during term of rena ed license.
54.37(a)
Auditable and retrievable form of records.
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- C76\\S61 1
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DRAFT REQUIREMENTS FOR RENEWAL OF OPERATING LICENSES FOR NUCLEAR POWER PLAh"rS (Continued) 54.41 Violations.
54.43 Crimi==1 penalties.
3.
Revised languare by section.
3 l
54.3 Definitions.
. l Age-related degradation means an adverse change in a system's performance _
sufficient in dagrada its functional canability resulting from changes in a l
constituent component's or structure's characteristics caused wholly or in f
part by one or more agmg mechaniams. Examples of this type of change include changes in dimension, ductility, fatigue resistance, fracture toughness, mechanical strength, polymerization, viscosity, and dielectric strength.~
Performance Monitoring Program means a periodic observation, measurement or assessment of a component or structure, or group thereof, for performance or condition against licensee-established goals or objectives,.
in a manner sufficient to provide reasonable assurance that such component i
or structure is capable of fulfilling its intended safety function.
l System means an integrated set of components which can consist of equipment and/or structures or portions of structures which together accomplish a function or severel functions.
t 54.21 Contents of application - technical information.
Each application shall contain:
(a)
The results and conclusions from the following evaluations:
(1)
List all components whose service life will exceed 40 years g/
during the renewal term, and for which the safety function (s):
(a) are not managed by a performance monitoring program, or (b) were acceptable for the renewal term on the basis of a bounding analysis which now must be revised to envelope the renewal term.
2-C76\\S61 n....
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DRAFT REQUIREMENTS FOR RENEWAL OF OPERATING LICENSES FOR NUCLEAR POWER PLANTS (Continued)
(2)
For those components identified in step (1) above provide one of the following whichEssures)decuate performance of thI
_ safety function despite the potential effects of age-related-degradation dunng the renewal period:
(a) an augmentation to existing performance monitoring, or i
(b) an analysis which bounds the renewal term, or (c) specific test results, or j
(d) mitigating action in the event of component failure.
(3)
Based on_a review of monitorirm procrama for the reactor.
vessel and the containment, show that performance of these systems is reasonably assured, despite the potential effects of age-related degradation during the renewal period.
(b)
A list of all plant-specific exemptions granted pursuant to 10 CFR 50.12 and reliefs granted pursuant to 10 CFR 50.55a. For those exemptions and reliefs that either were granted on the basis of an assumed service life or period of operation bounded by the original license term of the facility, an evaluation that justifies the continuation of these exemptions and reliefs for the renewal term must be provided.
(c)
Identification of any assumptions or limits based on the original license term and provisions for revisions to accommodate the renewal term.
(d)
A description of any proposed modifications to the facility or its administrative control procedures necessary to ensure that systems important to license renewal will be adequately managed during the renewal term.
(e)
The results and conclusions from (a)-(d) above shall be incorporated into the Final Safety Analysis Report (FSAR) for the facility.
Additionally, the information supporting the decisions to exclude components from the list required by Paragraph (a)(1) and to exclude exemptions and reliefs from the list required by Paragraph (b) shall be maintained at the plant site available for audit by the hTC staff. C76\\361 l
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DRAFT REQUIREMENTS FOR RENEWAL OF OPERATING LICENSES FOR j
NUCLEAR POWER PLANTS 1
(Continued)
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54.29 Standards for issuance of a renewed license, i
A renewed license may be issued by the Commission, up to the full term authorized by 654.31, based on the following findings:
(a)
There is, based on the agency's evaluation of the application and the result of any audit deemed appropriate pursuant to 54.21, raaennahia -
i aneurann, that svetome will narrnrm their reouired safety function
~durince the renewal period and that any changes made to the plant's current licensing basis in order to comply with this paragraph are otherwise in accord with the Act and the Commicsion's regulations.
(b)
Same.
l (c)
Same.
I 54.33 Continuation of current licensing basis and conditions of renewed license.
(a)
Same.
(b)
Each renewed license will be issued in such form and mntain such conditions and limitations, including technical specifications, as the l
Commusion deems appropriate and necessary to reasonably assure that systems important to license renewal will perform their required _
safety function during the renewal period.
(c)
Same.
(d)
Same as old (e).
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. C76\\S61 I
October 1,1993 i
MEMORANDUM T0:
Files DRAFT COPY OF ALTERNATE LICENSE RENEWAL RULE At the Licensee Renewal Workshop on September 30, 1993, I was given a copy of the enclosed draft alternate License Renewal Rule by a representative of Yankee Atomic Electric Corp.
OriB ng1gigspabt i
nemasE.Murley Thomas E. Hurley, Director Office of Nuclear Reactor Regulation
Enclosure:
As stated DISTRIBUTION Central Files i
PDR TMurley R/F V
(I R:NRR TMurley:aj 10/
/93 i