ML20150F299

Application for Amend to License NPF-42,revising Tech Spec 3.4.8 Re RCS Specific Activity.Fee Paid

ML20150F299
Person / Time
Site:	Wolf Creek
Issue date:	07/06/1988
From:	Withers B WOLF CREEK NUCLEAR OPERATING CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20150F302	List: ML20150F299 ML20150F304
References
WM-88-0181, WM-88-181, NUDOCS 8807180222
Download: ML20150F299 (8)

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I W$LF CREEK NUCLEAR OPERATING CORPORATION Bart D. Withers President and Chief Executhre offcer July 6, 1988 WM 88-0181 U. S. Nuclear Rugulatory Com:nission ATTN: Document Control Desk Mall Station F1-137 1 Washington, D. C. 20555 l

Subject:

Docket No. 50-482: Revision to Technical Specification i 3.4.8 - Specific Activity Gentlemen:

The purpose of this letter is to transmit 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 3.4.8 and its associated Bases which addresses Reactor-Coolant System Specific Activity.

The proposed revision to Technical Specification 3.4.8 and its associated Bases modifies the requirements for reporting iodine spiking from a short-term report to an item which is to be included in the Annual Report, and eliminates the requirement to shut down the plant after 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> of operation with a dose equivalent I-131 value of 1 microcurie per gram or greater. This amendment request complies with the guidance provided by Generic Letter 85-19, dated September 27, 1985.

A complete Safety Evaluation and No Significant Hazards Consideration determination are provided as Attachments I and II respectively. The proposed changes to the Technical Specifications are provided as Attachment III.

In accordance with 10 CFR 50.91, a copy of this application, with attachments is being provided to the designated Kansas state official.

Enclosed is a check (No. 1878) for the $150.00 application fee required by 10 CFR 170.21.

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I P.O. Box 411/ Buriington, KS 66839 / Phone:(316) 364-8831 tg

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t WM 88-0181 Page 2 of 2 July 6,1988 Th'e proposed revision to the Wolf . Creek Generating Station Technical Specifications will be fully implemented within 30 days of formal Nuclear Regulatory Commission; approval.

If you have any questions concerning this natter, please contact me or O. L.

Maynard of my staff.

Very truly-yours, Bart D. Withers President and Chief Executive Officer

'BDW/jad Enclosure Attachments: I - Safety Evaluation II - Addressing the Standards in 10 CFR 50.92 III - Proposed Technical Specification Change cci G. W. Allen (KDHE), w/a B. L. Bartlett (NRC), w/a-D. D. Chamberlain (NRC), w/a R. D. Martin (NRC), w/a P. W. O'Connor (NRC), w/a (2)

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1 Bart D. Withers, of lawful age, being first duly sworn upon oath says that he is President and Chief Executive Officer of Wolf Creek Nuclear Oporating 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 beat of his knowledge ,

information and beliof.

By Bart D. Withers President and Chief Executive Officer SUBSCRIBED and sworn to before me this b day of dj ., 1988.

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Attachment I to WM 88-0181 Page 1 of 2 July 6, 1988 SAFETY EVALUATION DESCRIPTION OF PROPOSED AMENDMENT This proposed amendment to Technical Specification 3.4.8 and its associated bases revises the requirements for reporting iodine spiking from a short-term report to an item which is to be included in the Annual Report, and eliminates the requirement to shut down the plant after 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> of operation with a dose equivalent I-131 value of 1 microcurie per gram or greater. This amendment request complies with the guidance provided by Generic Letter 85-19, dated September 27, 1985.

REASON FOR PROPOSED AMENDMENT Generic letter 85-19 Reporting Requirements on Primary Coolant Iodine Spikes, stated that reporting requirements for iodine spiking could be reduced from a l short-term report (Special Report or Licensee Event Report) to an item which would be included in the Annual Report. The information to be included in the  ;

Annual Report is similar to that previously required but would be changed to more clearly designate the results to be included from a primary coolant specific activity analysis, and to delete the information regarding fuel l burnup by core region. )

Since there has been improvement throughout the industry in the quality of I nuclear fuel and operational history has demonstrated that normal coolant l iodine activity (i.e., in the absence of iodine spiking) is well below the l existing Technical Specification limit, existing requirements to shutdown the i plant if coolant iodine activity limits are exceeded for 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in a twelve month period can be eliminated. In addition, regulations require the Nuclear Regulatory Commission to be notified of fuel cladding failures that exceed expected values or that are caused by unexpected factors. Proper fuel management and existing reporting requirements should preclude ever approaching the present shutdown limit.

1) The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report has not increased. Generic Letter 85-19 i stated that the improved quality of fuel and the existence of I adequate reporting requirements precludes the operation of the facility with primary system activity that is excessive.

2) The possibility for an accident or malfunction of a different-type than any evaluated previously in the safety analysis report has not been created. This proposed amendment does not involve the creation of an accident, because there has been no changes in plant equipment, operating modes or safety analysis.

3) The margin of safety as defined in the basis for any technical specification has not been reduced. This proposed amendment does not involve any changes in plant equipment,- operating modes or safety analyses are involved.

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Attachment I to WM 88-0181 Page 2 of 2 July 6, 1988 Based on the above discussions and the considerations presented in Attachment II, the proposed revisions to the WCGS Technical Specifications 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 reports or create a 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 revisions do not adversely affect or endanger the health or safety of the general public or involve a significant safety hazard, l

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i ATTACHMENT II ADDRESSING THE STANDARDS IN 10 CFR 50.92 1

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Attachment II to WM 88-0181 Page 1 of 1 July. 6 ,1988 ADDRESSING THE STANDARDS IN 10 CFR 50.92 This proposed amendment to Technical Specification 3.4.8 and its associated bases revises the requirements for reporting lodine spiking from a short-term report to an item which is to.be included in the Annual Report, and-eliminates the requirement to shut down the plant after 800 hour0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />sy of operation with a dose equivalent I-131 value of 1 microcurie per gram or greater. .This amendment request complies with the guidance provided by Generic Letter 85-19, dated September 27, 1985.

1) This -proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.

Generic Letter 85-19, states, the improved quality of fuel and the existence of adequate reporting requirements precludes the operation of the facility with primary system activity that is excessive.

2) This proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.

No changes in plant equipment, operating modes or safety analyses-are involved.

3) This proposed amendment does not involve a significant reduction in a margin of safety. No changes in plant-equipment, operating modes or safety analyses are invsived.

Based on the above discussions and those presented in Attachment I, it has been determined that the requested Technical Specification revisions do not involve a significant increase 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 over previous evaluations; j or involve a significant reduction in a margin of safety. Therefore, the l requested license amendment does not involve a significant hazards j consideration.

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