ML20116D281
| ML20116D281 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 10/28/1992 |
| From: | Mcmeekin T DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20116D284 | List: |
| References | |
| GL-91-01, GL-91-1, NUDOCS 9211050288 | |
| Download: ML20116D281 (7) | |
Text
Duke huvr Cmpany T C AfDmit Ali Cuire blev Gewauon Detsartment nce l'rmdo:t Ili%Itum irrry kid th!CulA)
(T04)$i3 4800 flunter>ntle, NC2MiB b%3 (704675 499in DUKEPOWER October 28, 1992 U.F Nuclear Regulatory Commission Do ' wnt-Control Desk l
-Washington ~D.C.
20555 Subjectt' McGuire Nuclear Station
. Docket Nos. 50-369, 370 Rovision to the Reactor Vessel Material Surveillance Program - Withdrawal Schedule and 1
Removal of tho Schedule for the Withdrawal of Reactor Vossol Material Specimens from Tnchnical L
Specifications as prescribed in Generic Lotter 91-
'01 Gontlement In.the McGuiro response dated July 3, 1992 to Genoric Lotter
=92-01,; -McGuire committed to submitting a
now withdrawal schedule for Unit - l ' per the recommendations of Survoillance Capsule Report (WCAP-12354) and concurrently requesting the C
removal of the withdrawal schedule from Technical Specifications por Gonoric.Lotter 91-01.
Or, January 4,
- 1991, the NRC ' issued Generic Lotter 91-01,
" Removal:of the Schedule for the Withdrawal of Reactor-Vossel Material. Specimens.from Technical Specifications".-
This Generic-Letter encouraged licensees to submit proposed changes
-to Technical = Specifications (TS).to remove the-table that
_provides=the schedule;for surveillance specimen withdrawal.
Pursuant to 10 CFR 50.90, ple'aso find attached proposed license amendments, to facility operating licensos NPF-9 and NPF-17 for
'McGuiro Nuclear Station Units 1 and 2, respectively.
This propocod technical' specification-revision = contains the following proposed changes:
' 1.. Revised' Reactor Vessel-Material Surveillance Program - Withdrawal. Schedule (Table 4.4-5)
-2.
Removal of'the Schedule for the. Withdrawal of p
Roactor Vessel Material Specimens from Tochnical Specifications in accordance with Generic Letter.91-01.
9211050288.921028
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Nuclear Reguletory commission October 28, 1992 Page 2 Attachment I provides a technical discussion, no significant hazards analysis, and environmental impact analysis supporting thoso. proposed revisions.
The proposed changos to the station i
TS in.the form of pen and ink - marked pages are included an Attachment II.
McGuire will includo the NRC-approved vorolon of the specimen withdrawal in the 1993 revision of the updated safety analysis report.
Pursuant to 10 CFR 50. 91 (b) (1), a copy of those amendment requests have boon provided to the appropriato North Carolina l
official.
Very truly yo ro, 9YIMHL.
Tod C. McMockin adj/r9201 Attachments E
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e U.S.-Nuclear _ Regulatory Commission Octohe 28, 1992 Page 3 xc:l W/ Attachments Mr.
S.-D.
Ebneter, Regional Administrat.or U.
S. Nuclear Regulatory Commission, Region II 101 Marietta Street, NW - Suite 2900 Atlanta, Georgia 30323 Mr.- T. A. Reed Office of Nuclear _ Reactor Regulatior.
U.
S. Nuclear Regulatory Commission Washington,.D.C.
20555 Mr.
P. K. VanDoorn-
' Senior Resident Inspector McGuire: Nuclear' Station
-Mr. Dayne Brown, Chief Radiation Protection-Branch Division of Facility Services Department of Hunan Resources 701'Barbour Drive Raleigh,fN.C.- 27603-2008 1
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Nc= lear Regulatory. Commission vot.ober 28, 1992 Page 4 Ted C.
McMeekin, being duly sworn, states that he is Vice President of Duke Power Company and is authorized on the part of said Company to sign and file with the Nucle.r Regulatory
-Commission this revision to the Mcuuire Nuclear Station License Nos. NPF-9 and NPF-17, and that all statements and matters set forth-therein are true and correct to th
- best of his knowledge'.
j
.Ted-C. McMeekin, Site Vice President fglL Subscribed and sworn to before me this exet day of October, 1992'
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NogaryPublic My Commission Expires:
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Attachment I Duke Power company McGuire Nuclear Station
. Technical Discussion, No Significant Hazards and Fnvironmental Analysis Technical Discussion The purpose of the proposed amendment requests for McGuire Nuclear Station are to:
1.
. Revise the Reactor Vessel Surveillance Program - Withdrawal Schedule (TS Tablo 4.4-5) 2.
Removal'of the Schedule for the Withdrawal of Reactor Vessel Material Specimens from TS in accordance with Generic Letter.91-01.
The bases for these changes is provided in the following paragraphs,
- 1. - Revised Capsule Withdrawal Schedule Table 4.4-5 has been revised to reflect the disposition of capsules for each McGuire unit.-
Changes made to McGuire Unit.1 surveillance withdrawal schedule are based on the analysis of Capsule X and the recommendations submitted by Westinghouse in WCAP-12354, ted August 1989 which was
. submitted by' Duke to the NRC.a a letter dated November 15, 1989.
In addition -to the recommended surveillance causule removal schedule in WCAP-12354, -standby Capsule Z will be withdrawn at-7 EFPY and stored. -The purpose for storing this capsule is to maintain a versatile surveillance-program which will
. prevent the spare capsule from becoming over irradiated and therefore losing:its.usefulness.
Removing standby Capsule Z at 7 EFPY will give Duke Power the most flexibility because at this time Capsule Z would have experienced 40Lyears of radiat1s' (32EFPY) and it could be used to obtain additional data at-End of Licensed Life, it could be reinserted to obtain addf tonal data at a higher fluence or-if needed, it could be '.ieat treated to simulate
.an annealing process to determine recovery of toughness.
McGuire Unitf2 surveillance withdrawal schedule is based on the analysis,of' Capsule X and the recommendations submitted by/ Westinghouse-in WCAP-12556, dated April 1990 which Was. submitted by Duke to the NRC in a letter dated August'30, 1990.
The NRC approved version of the Unit 2 surveillance withdrawal schedule was incorpoated into TS on
4 October 28, 1992 Page 2-November 15, 1990.
There are two differences from the NRC approved version of the Unit 2 surveillances capsule withdrawal schedule, Capsule W will be withdr wn at 9 EFPY instead of 10 EFPY and standby Capsule Y will be withdrawn at 7 EFPY and stored.
The purpose for removing capsule W at 9 EFPY instead of 10 is that it would have obtained approximately 3.16 n/cm x 10" fluence, which is the 2
estimated fluence at 60 years of operating life (48EFPY) which is 1.5 times license life.
Capsule Y will be stored for the same reason as Capsule Z in Unit 1.
2.
Removal of the Schedule for the Withdrawal of Reactor Vessel Material Specimens from TS in accordance with Generic Letter 91-01.
The removal from TS of the schedule for the withdrawal of reactor vessel material surveillance specimens will not result in any loss of regulatory control because changes to this schedule are cuntrolled by the requirements of Appendix H to 10 CFR Part 50.
AlFo, the NRC-appr'uved version of the specimen withdrawal scheduled will be maintained in the Finhl Safety Analysis Report.
Based on the above discussions, it can be concluded that the proposed changes are justified and will not reduce safety.
I No Significant Hazards Analysis 10 CFR 50.91 requires that the following analysis be provided concerning whether the proposed amendment requests involve a significant hazards consideration as defined in 10 CFR 50.92.
Standards for determination that an amendment request does not involve a significant hazards consideration are if 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 previously evaluated; or, 3)
Involve a significant reduction in a margin of safety.
The proposad revision to TS Table 4.4-5 will update the reactor vessel surveillance capsule withdrawal schedule which identifies.the disposition of capsules and future capsule withdrawal dates.
Updating the capsule removal schedule and subsequently removing it from TS will not involve a significant
T A
October 28,.1992 Page.3 increase-in the probability or consequences of an accident
. proviously evaluated, nor will it_ create the possibility of a new or. different kind of accident from any provicusly
,~
evaluated, nor will a margin in safety be reduced because this revision complies with ASTM E185-82," Standard Practice for conducting Surveillance Test for Light Water Cooled Nuclear Powered Reactor Vessels" which is approved by the NRC as described in 10 CFR 50_ Appendix H,
" Reactor Vesse. Material Surveillance-Program Requirements" and Generic Letter 91-01," Removal of the Schedule for the Withdrawal of Reactor vessel Material-Specimens from Technical Specifications".
As discussed above, we have determined the proposed amendment
- requests do not involve a significant hazards consideration as defined by 10 CFR 50.92.
Environmental Impact Analysis The proposed Ts amendments have been reviewed against the criteria of,10 CFR 51.22 for environmental considerations.
The proposed amendments do not involve a significant hazards consideration, nor increase the types and amour.ts of effluents that may be released' offsite, nor increase individual or cumulative occupational radiation exposures.
Therefore, the
- proposed TS amendments meet the criteria given in 10 CFR 51.22(c) t9) for a categorical exclusion from the requirement for;an Environmental Impact Statement.
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