ML20206S277
| ML20206S277 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 09/15/1986 |
| From: | Koester G KANSAS GAS & ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| KMLNRC-86-167, TAC-57896, NUDOCS 8609220152 | |
| Download: ML20206S277 (4) | |
Text
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KANSAS GAS AND ELECTRIC COMPANY Tm aseme e-mv /
September 15, 1986 u,,,,.,o,,,,,,
W3CE PRE $fDENT NUCLEAfD Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 KMLNRC 86-167 Re:
Docket No. STN 50-482 Subj:
Supplemental Information Regarding Revision to Technical Specification Table 2.2-1
Dear Mr. Denton:
The purpose of this letter is to provide supplemental information regarding 3
the Reference.
Additional information concerning the application of the standards in 10 CPR 50 92 was requested during discussions with your Staff.
This detailed information has been provided as an attachment to this letter. The Reference transmitted a complete Safety Evaluation and proposed changes to the Wolf Creek Generating Station, Unit No.
1, Technical Specifications.
If you have any questions concerning this matter, please contact me or Mr.
O. L. Maynard of my staff.
Very truly yours, h
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1 Glenn L. Koester Vice President - Nuclear GLK:see Enclosure Attachment oc P0'Connor (2)
JCummins GAllen EJohnson
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201 N. Market - Wichota, Kansas - Mail Address: RO. Box 208 I W1chita, Kansas 67201 - Telephone: Arca Code (316) 2616451
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STATE OP KANSAS )
) SS CITY OF WICHITA )
I, John A.
Bailey, of lawful age, being first duly sworn upon oath, do depose, state and affirm that I am Director Engineering and Technical Services of Kansas Gas and Electric Company, Wichita, Kansas, that I have signed the foregoing letter of transmittal for Glenn L.
- Koester, Vice President - Nuclear of Kansas Gas and Electric Company, know the content thereof; and that all statements contained therein are true.
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John A. Bailey
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il Director Engine ring and Tefhnical Services
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o, SUBSCRIBED and sworn to before me this / I day of
., 1986.
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Notary Public Erpiration Ihte
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' Mr. H. R. Dent::n September 15, 1986
Attachment.to XMLNRC 86-167-Page 1 of'2.
SIGNIFICANT HAZARDS CONSIDERATION This -significant hazards consideration supplements the submittal dated May 31,1985 (KMLNRC 85-130) ooneerning Wolf Creek Generating Station, Unit No. 1, Technical Specification Table 2.2-1.
This table is being revised to refloot changes in the narrow range RdP resistance temperature detector (RTD) uncertainties.
The changes in RTD uncertainties, which are utilized 'in setpoint uncertainty analyses, resulted in a change to the Total Allowance for Overtemperature-Delta-T; ohanges to Sensor Error for the functions Overtemperature Delta-T, Overpower Delta-T, and Reactor Coolent Plow-Iow; a change to Z for Reactor Coolant Plow-Low; and changes to the' Allowable Values for Overtemperature Delta-T, and Overpower Delta-T.
The proposed changes do not. involve a Significant Hazards Consideration because operation of Wolf Croek Generating Station, Unit No.
1, in accordance with this change would not:
- 1) Involve a significant increase in the probability or consequences of an aooident previously evaluated. The proposed changes to Table 2.2-1 are being made to reflect a revision to the narrow range RdP RTD uncertainties.
The annotated changes to Table 2.2-1 affecting the Allowable Values for Overtemperature Delta-T and Overpower Delta-T represent more stringent or restrictive limits since the existing allowable band between the Reactor-Trip'Setpoints and their Allowable Values is being reduced.
Changes to Total Allowance (TA), Sensor Error (S), and Z affect the threshold value for Reportable Events as defined in Bases 2.2-1, Reactor Trip System Instrumentation Setpoints.
There are no changes to any Reactor Trip Setpoint Limits specified in Table 2.2-1.
Since the Trip Setpoints, which ensure that the core and Reactor Coolant System are prevented from exceeding their Safety Limits, remain unchanged,. it has been concluded that these changes do not involve a signifloant increase in the probability or consequences of an aooident previously evaluated.
- 2) Create the possibility of a new or different kind of accident from any sooident previously evaluated.
Kansas Gas and Electric Company has determined that the proposed changes narrow existing allowable operational bands and alter threshold values for Reportable Events.
Therefore, these changes cannot create the possibility of a new or different kind of aooident from any sooident previously evaluated.
- 3) Involve a significant reduction in a margin of safety.
The margin of safety is not affected by these changes.
These changes do not alter any Reactor Trip System instrumentation trip setpoints, nor is there any change to Reactor Trip System design, functional diversity, or safety limits described in Chapter 15 of the PSAR.
- Hence, th~e proposed changes do not involve a significant reduction in a margin of aufety.
L Mr. H. R. L nton September 15, 1986 Attachment to N1LNRC 86-167 Page 2 of 2 The Commission has provided guidance concerning the application of the standards in 10 CPR 50.92 by providing examples of Amendments that are not likely to involve Significant Hazards Considerations (48 PR 14870).
Among these examples are, "A change that constitutes an additional limitation, restriction, or control not presently included in the technical specifications..." The proposed changes, although presently included in the technical specifications, constitute changes to existing limitations and controls similar to those mentioned in the example above.
Based on the above analysis, the safety evaluation provided by the Reference and utilizing the guidance provided by the Commission, it has been concluded that the proposed revisions to the Wolf Creek Generating Station Technical Specification involve no signficant hazards consideration.
1
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