ML20044H150
| ML20044H150 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 06/01/1993 |
| From: | Hagan J WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20044H151 | List: |
| References | |
| NA-93-0133, NA-93-133, NUDOCS 9306080001 | |
| Download: ML20044H150 (8) | |
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WOLF CREEK
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' NUCLEAR OPERATING CORPORATION 4
'l June 1, 1993 Robert C Hagan NA 93-0133 Vice President Nuclear Assurance U.
S.
Nuclear Regulatory Commission i
ATTN:
Document Control Desk Mail Station F1-137 Washington, D.
C.
20555
Subject:
Docket No. 50-482:
Revision to Technical Specification Section 6.9.1.7 - Semiannual Radioactive Effluent Release Report Gentlemen:
This letter transmits an application for amendment to Facility Operating License No. NPF-42 for Wolf Creek Generating Station (WCGS), Unit No.
1.
This license amendment request proposes revising Technical Specification Section 6.9.1.7, Semiannual Radioactive Effluent Release Report, and_ associated reporting requirements in Technical Specification Sections 3.11 and 6.14 to extend the reporting period from semiannually to annually and to change the report submission date from 60 days after January 1 and-July 1 of each year to before May 1 of each year.
These changes implement an amendment to 10 CFR 50.36a noticed in the Federal Register dated Monday, August 31, 1992 (57 FR 39353).
This request also proposes one minor editorial change to reflect amendment history on a bases page.
Attachment I provides a description of the amendment along with a Safety Evaluation.
Attachment II provides the No Significant Hazards Consideration Determination.
Attachment III provides the Environmental Impact Determination.
The proposed changes to the Technical Specification are provided as Attachment IV.
In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated Kansas State Official.
If you have any questions concerning this request, please contact me at (316) 364-8831, extension 4553 or Mr. Kevin J. Moles at extension 4565.
Very truly yours, It Robert C. Hagan
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Vice President Nuclear Assurance i
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Attachments:
I-Safety Evaluation
'l II - No Significant Ha::ards Consideration Determination l
III - Environmental Impact Determination
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IV - Proposed Technical Specification Changes cc:
G.
W.
Allen (KDHE), w/a I f W.
D.
Johnson (NRC), w/a f
J.
L. Milhoan (NRC), w/a i
G.
A.
Pick (NRC), w/a
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W.
D.
Reckley (NRC), w/a f
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PO Box 411/ Burhngton. KS 66839 i Phone: (316) 364-8831 i
9306080001 930601 An Egwd Opportumty Employer M FeHCNET PDR ADOCK 05000482 P
STATE OF KANSAS
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Robert C. Hagan, of lawful age, being first duly sworn upon oath says that he is Vice President Nuclear Assurance of Wolf Creek Nuclear Operating Corporation; 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.
By
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Rober). C. Hagan" Vice/ President g
Nuclear Assurance SF day of '-)Luu-SUBSCRIBED and sworn to before me this 1993.
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. :j Attachment I'to NA 93-0133 4
Page 1 of 2 l
Attachment'I 1
Safety Evaluation l
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l Attachment I to NA 93-0133 Page 2 of 2 l
Safety Evaluation Proposed Change I
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The proposed technical specification change extends the reporting period of the Semiannual Radioactive Effluent Release Report from semiannually to-annually and changes the report submission date from 60 days after January 1.
and July 1 of each year to before May 1 of each year.
The changes to reporting period and report date are being made to implement the August 31, 1992 amendment to 10 CFR 50.36a.
Other references in technical specifications to the Semiannual Radioactive Effluent Release Report will also be changed to reflect an annual submittal.
This technical specification amendment request also proposes a minor editorial change to add amendment history to a bases page.
Evaluation I
changing the reporting period from semiannual to annual is consistent with the final rule published in the Federal Register on August 31, 1992 (57 FR 39353),
amending 10 CFR 50.36a.
The amendment to 10 CFR 50.36a,
" reduces the requirements for the submission of reports concerning the quantity of principal nuclides released to unres t ricted areas in liquid and ~ gaseous ef fluents from semiannually to annually. "
It is also proposed to change the report submission date from 60 days after January 1 and July 1 of each year to before May 1 of each year.
This report date would then be consistent with the reporting requirement for the Annual Radiological Environmental Operating Report as stipulated by Wolf Creek Generating Station (WCGS) Technical Specification 6.9.1.6.
This. revised report date would also allow for the compilation of a more lengthy report resulting from the 12 month report period.
other references to the Semiannual Radioactive Effluent Release Report will also be changed to annual.
These references are located in Technical 4
Specification 3.11.1.4, 3.11.2.6 and 6,14c.
These sections require reporting i
of events or submittal of changes to the Offsite Dose Calculation Manual with the Semiannual Radioactive Effluent Release Report.
Changing the reporting to an annual frequency does not change the-required actions, controls or administrative requirements.
Only the reporting time frame is proposed to be changed to make it consistent with the proposed reporting requirement.
The minor correction to the bases page B 3/4 0-1 to add the amendment history is editorial in nature and will provide historical information.
The proposed changes do not alter any administrative controls over radioactive effluent, nor do the proposed changes involve any physical alterations to the plant with respect to radioactive effluent.
The proposed changes are administrative in nature and will not affect or impact plant components, systems or equipment.
Based on the above discussions and the considerations presented in Attachment II, the proposed changes do 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 report; or create the possibility for an accident or malfunction of a different type than any previously evaluated in the safety analysis report; or reduce the margin of safety as defined in the basis for any technical specification. Therefore, the proposed changes do not adversely. affect or endanger the health or safety of. the general public or involve a significant safety hazard.
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Attachment II to NA 93-0133 Page 1 of 2 l
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Attachment II No Significant Hazards Consideration Determination i
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m t-Attachment II to NA 93-0133 Page 2 of 2 No Significant Hazard Consideration Determination The proposed changes would revise Technical Specification Section 3.11.1.4, 3.11.2.6, 6.9.1.7, and 6.14e to extend the reporting period of the Semiannual Radioactive Effluent Release Report from semiannual to annual and change the
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report date to before May 1 of each year.
Standard 1 - Involves a Significant Increase in the Probability or Consequences of an Accident Previously Evaluated I
The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
These changes involve an administrative change and as such, have no effec; on plant equipment or accident evaluations.
Standard 2 - Create the Possibility of a New or Different Kind of Accident from any Previously E'aluated The proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
These changes either do not impact any administrative controls nor involve physical alterations to the plant with respect to radioactive effluent.
These changes'do not involve any l
change to the installed plant systems or the overall operating philosophy of WCGS.
Standard 3 - Involve a Significant Reduction in the Margin of Safety The proposed changes are an administrative change and do not involve a significant reduction in a margin of safety.
Based on the above discussions it has been determined that the requested technical specification revision does not involve a significant iacrease in the probability or consequences of an accident or other adverse condition over previous evaluations; or create the possibility of a new or different. kind of accident or condition over previous evaluations; or involve ' a -significant reduction in a margin of safety.
The requested license amendment does not involve a significant hazards consideration.
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Attischment III to NA 93-0133 1
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Attachment III Environmental Impact Determination i
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Attachment III to NA 93-0133 Page 2 of 2 Environmental Impact Determination 10 CFR 51. 22 (b) specifies the criteria for categorical exclusions from the requirement for a specific environmental assessment per 10 CFR 51.21.
This amendment request meets the criteria specitied in 10 CFR
- 51. 22 (c) ( 9).
Specific criteria contained in this section are discussed below.
(1)
The amendment involves no significant hazards consideration As demonstrated in the No Significant Hazards Consideration Determination in Attachment II, the requested license amendment does not involve any-significant hazards considerations.
(ii)
There is not significant change in the types or significant increase in the amounts of any effluents that may be released offsite The requested license amendment involves no change to the facility or operating procedures which would cause an increase in the amounts of effluents or create new types of effluents.
This change only extends the reporting period of the Radioactive Effluent Release Report to annual.
(iii)
There is no significant increase in individual or cumulative occupational radiation exposure The nature of the changes is administrative and does not require additional exposure by personnel nor effect levels of radiation present.
The proposed change does not result in significant individual or cumulative occupational radiation exposure.
Based on the above it is concluded that there will be no impact on the environmer.t resulting from this change and the change meets the criteria specified in 10 CFR 51.22 for a categorical exclusion from the requirements of 10 CFR 51.21 relative to specific environmental assessment by the Commission.
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