ML20012A122
| ML20012A122 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 03/02/1990 |
| From: | Rhodes F WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20012A123 | List: |
| References | |
| ET-90-0043, ET-90-43, NUDOCS 9003080320 | |
| Download: ML20012A122 (6) | |
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W$LF CREEK 1
NUCLEAR OPERATING CORPORATION
$1}se"ni March 2, 1990 3
Enshwwine a wohnas s visse ET 90-0043 U. S'. ' Nuclear Regulatory Conunission ATTN s Document Control Desk Mail Station P1-137-
[
Washington, D. C. 20555 L
Reference:
Letter, dated March 23, 1989, from D. V. Pickett, NRC,.
to B. D. Withers, WCNOC
Subject:
' Docket'No. 50-482: Revision to Technical Specification.
3/4.8.4.- Deletion of References to Table 3.8-1 L
Gentlemen:-
r The purpose of.this letter is to transmit an application for amendment fto
' Facility' Operating : License No.
NPF-42:for' Wolf Creek Generating Station.
(WCGS), Unit No..
1.
This license amendment request would revise Technical.
Specification Surveillance-Requirement
.4.8.4.1 and the Technical Specification Table of Contents to delete. the. reference to Table
- 3. 8,-1.
Table' 3.8 1 had been previously removed from the WCGS Technical.
Specifications by Amendment 28 which was transmitted to Wolf Creek Nuclear
. Operating Corporation (WCNOC) in the Reference.
A~ Safety Evaluation and'No Significant Hazards Consideration determination lare provided as Attachments I and II, respectively.; The proposed chan8es to L
the-Technical. Specifications are provided in Attachment III.
In accordance
-with 10. CFR-50.91,- 'a copy of this application, with attachments is'being.
l provided to the~ designated Kansas State official. This proposed revision to.
the WCGS Technical Specifications-will be fully implemented within 30 days-of formal Nuclear Regulatory Commission approval.-
If you have any= questions -concerning this' matter, please contact me or Mr.-H. K. Chernoff of my staff.
Very truly yours i
w o N T. Rhodes Vice President Engineering & Technical Services FTR/aem Attachments:
I'- Safety Evaluation II - Addressing The Standards to 10 CFR 50.92 III - Proposed Technical Specification Changes ces G. W. Allen (KDHE) w/a E. J. Holler (NRC) w/a g6 R. D. Martin (NRC) w/a D. V. Pickett (NRC) w/a j
k M. E. Skow (NRC) w/a P.O. Box 411/ Burlington, KS 66839 / Phone: (316) 364-8831 9003080320 900302 i
An Equal Opportunity Employer WFIHcNET PDR ADOCK 05000482
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.q STATE OF KANSAS
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Forrest T. Rhodes, of lawful age, being first duly sworn upon oath says.that he is 'Vice President Engineering and Technical Services-of Wolf Creek' i
Nuclear Operating Corporations that he has-read the foregoing document and-knows the-content thereof:' that he has executed that same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge,.
Information and belief.
t By
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Forrest T. Rhodes Vice President Engineering & Technical Services
-SUBSCRIBED and sworn to before me this c2wd day of Mc4,1990.
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Attachment I to ET 90-0043 Page.1 of 1 SAFETY EVALUATION Description of channes Technical Specification 3/4.8.4 provides the requirements for. Containment Penetration Conductor Overcurrent Protective Devices.
On March 13,
- 1989, the NRC issued Amendment 28 which revised Technical Specification 3/4.8.4 and deleted Table 3.8-1, which listed the Containment Penetration Conductor Overcurrent Protect Devices.
During a review of Amendment 28 by Wolf Creek Huclear Operating Corporation' (WCNOC) personnel, it was discovered that there were still references to Table 3.8-1 in the Technical Specifications.
This. proposed Technical Specification change would delete the references to Table 3.8-1 which remain in the WCGS Technical Specifications.
These remaining. references are located in the Table of Contents and in Surveillance Requirement 4.8.4.1.
EVALUATION Table 3.8-1 provided information on the location, size and equipment protected by the Containment Penetration Conductor Overcurrent Protective
. Devices.
The information which was in ' Table 3.8-1 is currently being a&ninistratively controlled in plant procedures.
The references to this table which remain were inadvertently overlooked when the table was originally requested to be removed from Technical Specifications.
Removing the references to the table is now being pursued in order to minimize the confusion from referring. to a table which no longer exists.
This. is an administrative change which does not change any of the requirements of the WCGS Technical Specifications.
This change does not include any technical changes and is considered to be editorial in nature.
~ Based on the above discussions and the considerations presented in Attachment II, the proposed revision to the WCGS Technical Specifications does not increase the probability of occurrence or the consequences of an accident -or malfunction of equipment important to safety previously evaluated in the safety analysis reports or create a possibility for an accident or malfunction of a different type than any previously evaluated in the safety analysis reporti or reduce the margin of safety as defined in the basis for any technical specification.
Therefore, the proposed revision does not adversely affect or endanger the health or safety of the general public or involve a significant safety hazard.
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ATTACIDEENT II anmangIng TgE STANMEDS IN 10- CFR-50.92' I
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' Attachment II to ET 90 0043 Page-1 of 1-AnnmaaSING TNE STANDARDS IN 10 CFR 50.92 The proposed change would revise the Technical Specification Table of Contents and Technical Specification Surveillance Requirement 4.8.4.1 to delete' references to Table 3.8-1 which was previously removed from Technical Specifications in Amendment 28.
The'following sections discuss the proposed' changes under the three 10 CFR 50.92 standards:
Involve a Significant Increase in the Probability _ or Standard.
.1 Consequences of an Accident Previously Evaluated j
These changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. This is an administrative change which does not change any of the requirements of the current Technical Specifications.
This change does not include any technical changes and is considered to be editorial in nature.
Standard.2 - Create.the Possibility of a New or Different Kind of Accident j
from any Accident Previously Evaluated H
These changes do not create the possibility of a new or different kind of l
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accident from any accident'previously evaluated.
The proposed changes are administrative in natures No physical alterations to the plant equipment or l
plant operations are proposed.
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Standard 3 - Involve a Significant Reduction in a Margin of Safety i
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-The proposed amendment does not involve a significant reduction in a margin of safety..
This change meraly deletes references to a table which was-previously removed from Technical Specifications.
This ' change is an editorial change which has no effect on any margin of safety.
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The commission has provided guidance concerning the application of the i
standards in.10 CFR 50.92 by providing examples of amendments that are not likely to involve a Significant Hazards Consideration (51 CFR 7751).
Among 1
those examples are "A
' purely administrative change to technical specifications:
for example, a change to achieve consistency throughout the Technical Specifications, corrections of an error, or a change in i
nomenclature" and "A
change that constitutes an additional limitation.
l restriction, or control not presently included in
'the Technical J
Specifications..."
Based on the above discussions and those presented in Attachment I,.it has been detennined that the requested Technical Specification revisions do not involve a significant increase in the probability or consequencea of an accident or other adverse condition over previous evaluations: or create the possibility of a new or different kind of accident over previous evaluations; or involve a significant reduction in a margin of safety.
Therefore, the requested changes do not involve a significant hazards consideration.
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