ML20059D762
| ML20059D762 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 10/27/1993 |
| From: | Hagan R WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20059D766 | List: |
| References | |
| NA-93-0203, NA-93-203, NUDOCS 9311020396 | |
| Download: ML20059D762 (9) | |
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.t WQLF CREEK
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NUCLEAR OPERATING CORPORATION -
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Robert C. Hagan Vice F#esident Nuclear Assurance October 27, 1993 I
NA 93-0203 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk 5
Mail Station P1-137 Washington, D. C.
20555
Subject:
Docket No. 50-482: Revision to Technical ~ Specification Reactor Trip System Instrumentation Table 4.3-1 Surveillance Requirements Gentlemen:
I This letter transmits an application for amendment to Facility Operating License No. NPF-42 for Wolf Creek Generating Station (WCGS)
This license amendment request proposes revising Technical Specification Table ' 4.3-1, Note 5, to reflect that integral bias curves, rather than detector' plateau-'
curves, are used to calibrate the source range nuclear instrumentation.
The Intermediate Range and Power Range nuclear instrumentation channels will cor.tinue to be. calibrated using detector plateau curves.
.l Attachment I provides a safety evaluation including a description of the-proposed change.
Attachment II provides a no significant hazards consideration determination and Attachment III provides an environmental impact determination.
The specific change to the' technical specification' i
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proposed by this request is provided'in Attachment IV.
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In accordance with 10 CFR 50.91, a copy of_
this application, -with attachments, is being 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.
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PO. Box 411/ Burhngton, KS 66839 / Phone: (316) 364-8831
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. i NA 93-0203 Page 2 of 2 i
If you have any questions concerning this matter, please contact me at' (316) 364-8831, extension 4553, or Mr. Kevin J. Moles, at extension 4565.
Very truly yours,
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R bert C.'Hagan d'
Vice President Nuclear Assurance RCH/jra Attachments I - Change Description and Safety Evaluation II - No Significant Hazards Consideration Determination
-4 III - Environmental Impact Determination IV - Proposed Technical Specification Change cc:
G.
W. Allen (KDHE), w/a J. L. M11hoan (NRC), w/a G.
A.
Pick (NRC), w/a W.
D.
Reckley (NRC), w/a L.
A. Yandell (NRC), w/a
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i STATE OF KANSAS
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l Robert C. Hagan, of lawful age, being first duly sworn upon oath says that he.
i 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.
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Ro'bget C. Hagan f
Vic6 President
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- P () B L\\ F Nuclear Assurance SUBSCRIBED and sworn to before me this 07 day of O./C[2>L.
1993.
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Notary Public is ff!O !9f Expiration Date i
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Attachment I to NA 93-0203 Page 1 of 2 t
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ATTACHMENT.I SAFETY EVALUATIOli-e p
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Attachment I to NA 93-0203 Page 2 of 2 i
Safety Evaluation i
Proposed Chance This license amendment request propuses
.a-revision ~
to-Technical Specification Table 4.3-1, Note 5,
to reflect that integral blas curves, rather than detector plateau curves, are used to calibrate the source range nuclear instrumentation.
Intermediate Range and Power Range nuclear instrumentation channels will continue to be calibrated using detector
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plateau curves.
The implementation of the Boron ~ Mitigation System added a low-noise -
- i preamplifier to the source range detector channel of the Nuclear Instrumentation System (NIS) during the original design.
The low-noise preamplifiers provided for the NIS do not provide a means of determining the detector voltage setting using the traditional high voltage ' plateau l
curves.
Because the preamplifier is a voltage sensitive design, the detector plateau curve no longer retains the typical " knee" of the curve.
and the plateau length.
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Evaluation The calibration of the source range NIS is currently performed by using an iritegral bias curve rather than a plateau curve.
The integral bias curve sets up the high voltage as well as the preamplifier gains and
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discriminator bias.
It is a more inclusive calibration than the plateau.
curve and provides the same information, i.e.,
the high voltage operating
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point.
Using the integral bias curve method, the operating bias point is determined from a graph of the curve of count rate versus discriminator bias.
The operating point for the discriminator is determined by ' adding margin against possible noise pulses to the value where the curve departs-from the best fit straight line.
The detector high voltage is adjusted if L
the discriminator operating bias point is not where it is required to b3 Based on the above discussions and the no significant hazards consideration-determination presented ' in Attachment II, the proposed change does not' in. ease 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 a possibility for; an accident or malfunction of a different type than any previously evaluated in the safety'
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analysis report; or reduce the margin of. safety as defined in the basis for any technical specification.
Therefore, the proposed change does not 1
adversely affect or endanger the health or safety of the: general public or i
involve a significant safety hazard.
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Att'chment IT.
NA 93-0203 a
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ATTACIDIENT II NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION 1
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s Attachment II to NA 93-0203 Page 2 of 2 No Significant Hazards Consideration Determination This license amendment request proposes a
revision to Technical Specification Table 4.3-1, Note 5,
to reflect that integral bias curves,'
rather than detector plateau curves, are used to calibrate the source range nuclear instrumentation.
Intermediate Range and Power Range nuclear instrumentation channels will continue to be calibrated using detector.
plateau curves.
Standard I - Involve a Significant Increase in the Probability 'r Consequence 4 of an Accident Previously Evaluated Plant equipment is not modified by calibrating the NIS source range instrumentation using the integral bias curve.
Using the integral bias curve is a more inclusive calibration than the plateau curve and provides the same information, i.e.,
the high voltage cperating point.
The change does not affect accident initiators or assumptions.
The consequences'due to accidents previously evaluated are not being changed.
Standard II - Create the Possibility of a New or Different Kind of Accident from any Previously Evaluated No new accidents are created by the changes being made.
No new equipment is being added.
No new modes of operation or means of control are being made.
The probability of a malfunction of equipment important to safety is unchanged since the calibration of the NIS source range instrumentation using the integral bias curve, rather than the plateau curve, provides the same information.
The consequences of Alfunctions of equipment important to safety are not changed.
No new malfunctions are being created.
No new controlling modes or equipment operations are being created.
Standard III - Involve a Significant Reduction in the Margin of Safety Using the integral bias curve is a more inclusive calibration than the plateau curve and Irovides the same information,. i. e., the high voltage operating point.
Based on the above discussions, it has been determined that the requested technical specification revision does not involve a significant increase in the probability or consequences of an accident or other adverse condition over previous evaluatiors; or create the possibility of an new or different kind of accident or cundition over previous evaluations;.or involve a significant reduction in a margin of safety.
The requested license t
a.nendment does not involve a significant hazards consideration.
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Attachment III to NA 93 0203 Page 1 of 2 I
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ATTAC'HMENT III ENVIRONMENTAL IMPACT DETERMINATION 1
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, Att'achment III to NA 93-0203 Page 2 of 2 Environmental Impact Determination This amendment request meets the criteria specified in 10 CFR 51. 22 (c) (9) as specified below:
(i) the amendment involves no.significant hazards consideration As demonstrated in Attachment II, the proposed change does not involve any.
'ignificant hazards consideration.
(ii) there is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite.
The proposed change does not involve a change to the facility or operating procedures which would cause an increase in the amounts of effluents or<
create new types of effluents.
(iii).there is no significant increase in individual or cumulative occupational radiation exposure The proposed change is administrative in nature and does not create additional exposure to' personnel nor affect levels of radiation present,
Also, the proposed change does not result in any increase in individual or i
I cumulative' occupational radiation exposure.
Based on the above it is concluded that there will be no impact on the environment resulting from this change and the change meets-the criteria specified in 10 CFR 51.22 for a cateoorical exclusion from the requirements of 10 CFR 51.21 relative to requiring a specific environmental assessment by the Commission.
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