ML20205H664
| ML20205H664 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 08/13/1986 |
| From: | Koester G KANSAS GAS & ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20205H669 | List: |
| References | |
| KMLNRC-86-147, NUDOCS 8608200130 | |
| Download: ML20205H664 (9) | |
Text
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KANSAS GAS AND ELECTRIC COMPANY TM ELECTAC COMPANY GLENN L ROESTER August 13, 1986 v,c. m....,.
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Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Connission Washington, D.C.
20555 IC1LNRC 86-147 Re:
Docket No. STN 50-482 Subj: Revision to Technical Specification 5.3.1
Dear Mr. Denton:
The purpose of this letter is to transmit three original and 40 conformed copies of an application for Amendment to Facility Operating License No.
NPP-42 for Wolf Creek Generating Station, Unit No.
1.
The application for Amendment revises Wolf Creek Generating Station, Unit No.
1, Technical Specification Section 5 31 to delete the maximum uranium weight per fuel rod value.
This Technical Specification value was intended to be descriptive and representative of the fuel loading, and has not been used as a direct input to any safety analyses.
No safety analyses will be affected by the deletion of this value.
The proposed changes to the Technical Specifications are provided in Attachment III.
A complete Safety Evaluation and Significent Hazards Consideration are provided in Attachments : and II respectively.
In accordance with 10 CPR 50.91, a copy of the application, with attachments is being provided to the designated Kansas State Official.
Enclosed is a check (No. 2345) for the $150.00 application fee required by 10 CPR 170.21.
8609200130 860813 DR ADOCK 0500 2
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og.s 201 N. Market - Wichts, Kansas - Mail Address: PO. Box 208 I wichts, Kansas 67201 - Telephone: Area Code (316) 261-6451
Mr. H. R. Denton August 13, 1986 KMLNRC 86-147 Page 2 If you have any questions concerning this matter, please contact me or Mr.
Otto Maynard of my staff.
J Yours very truly, Glenn L. Koester GLK:see Enclosure Attachment I Safety Evaluation Attachment II Significant Hazards Consideration Attachment III Propose Technical Specification Changes con P0'Connor (2) i JCummins GAllen EJohnson 1
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STATE OF KANSAS )) SS CITY OF WICHITA )
s Glenn L.
Koester, of lawful age, being first duly sworn upon oath Officer of Kansas says that he is Vice President - Nuclear and an Gas and Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed that same for and on behalf of said Company with full power and authority to do to the and that the facts therein stated are true and correct so; best of his knowledge, information and belief.
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Clehn L. Koes'ter Vice President - Nuclear
/J ^ day of
,A 1986.
SUBSCRIBED and sworn to before me this
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e ATTACHPfENT I
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Mr. H. R. Dent:n August 13, 1986
' Attachment I to MiLNRC 86-147 Page 1 of 1 SAFETY EVALUATION This application requests a revision to the Wolf Creek Generating Station, Unit No.
1, Technical Specifications Section 5 3 1 to delete the maximum fuel rod weight limit of 1766 grams of uranium.
The purpose of the change is to permit the use of assemblies with fuel rods over the weight limit ' and also to reflect the relative insensitivities of this technical specification parameter in the safety analysis.
It is judged that this weight difference does not have a significant impact on the safety analyses.
Other Technical Specifications cover more important fuel related parameters, therefore, deletion of the Design Features fuel rod weight limit is not significant to the safe operation of the Plant.
The proposed change to the Technical Specifications is provided in Attachment III.
Although a number of safety analyses are affected indirectly by fuel weight, the analyses are more sensitive to fuel configuration,
- length, enrichment and physical design which are also specified in the plant Technical Specifications.
The Technical Specifications limit power and power distribution, thus controlling the fission rate and the rate of decay heat production.
Puel rod weight does not have any direct bearing on the power limits, power operating level, or deca'y heat rate.
The composition of the fuel is closely monitored to assure acceptable fuel performance.
The fuel weight changes that could be made without a Technical Specification limit are not of sufficient magnitude to cause a significant difference in fuel performance as a,nalyzed. There are no expected observable changes in normal operation due to the noted fuel rod weight changes, and the remaining fuel parameters listed in the Technical Specifications are considered in the Reload Safety Evaluation.
Other Design Basis Events were examined to assess the effects of possible changes in fuel rod weight. Puel rod weight will only change as a result of a specific change in the physical design, which is addressed in the Reload Safety Evaluation, or within the manufacturing tolerances, in which case the changes in fuel rod weight are relatively insignificant. Changes in nuclear design resulting from fuel rod weight changes are controlled as discussed abo ve.
For these changes, the effect on new and spent fuel criticality and fuel handling analyses remain bounded by the existing analyses and Technical Specification Design Feature limits. Puel-handling equipnent and procedures are not affected by these weight changes.
Seismic /LOCA analyses contain sufficient conservatism to bound these weight changes.
Other accident analyses are not affected by rod weight as a direct parameter, and the existing analyses remain bounding.
Based on the above analysis, the proposed revision to the Wolf Creek Generating Station, Unit No. 1, Technical Specifications does not adversely affect or endanger the health or safety of the general public or involve an unreviewed safety question.
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ATTACHMENT II L
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Mr. H. R. Denton August 13, 1986 l
Attachment II to XMLNRC 86-147 Page 1 of 2 SIGNIFICANT HAZARDS CONSIDERATION This application requests a revision to the Wolf Creek Generating Station, Unit No.
1, Technical Specifications Section 5 3.1 to delete the maximum fuel rod weight limit of 1766 grams of uranium.
The purpose of the change is to per: nit the use of assemblies with fuel rods over the weight limit and also to reflect the relative insensitivities of this technical specification paramoter in the safety analysis.
It is judged that this weight difference does not have a significant impact on the safety analyssa.
Other Technical Specifications cover more important fuel related parameters,
therefore, deletion of the Design Peatures fuel rod weight limit is not significant to the safe operation of the Plant.
The proposed change to the Technical Specifications is provided in Attachment III.
Although a numb (r of safety naalyses are affected indirectly by fuel weight, the analyses are more sensitive to fuel configuration,
- length, enrichment and physical design which are also specified in the plant Technical Specifiestions.
The Technical Specifications limit power and power distribution, thus controlling the fission rate and the rate of decay heat production.
Puel rod weight does not have any direct bearing on the power limits, power operating level, or decay heat rate.
The composition of the fuel is closely monitored to assure acceptable fuel performance.
The fuel weight changes that could be made without a Technical Specification limit are not of sufficient magnitude to cause d significant difference in fuel performance as analyzed by Westinghouse.
There are no expected observable changes in normal operabion due to the noted fuel rod weight changes, and the remaining fuel parameters listed in the Technical Specifications are considered in the Reload Safety Evaluation.
Other Design Basis Events were examined to assess the effects of possible changes in fuel rod weight. Puel rod weight will only change as a result of a specific change in the physical design, which is addressed in the Reload Safety Evaluation, or within the manufacturing tolerances, in which case the changes in fuol rod weight are relatively insignificant. Changes in nuclear design ruaulting from fuel rod weight changes are controlled as discussed above. Por these changes, the effect on new and spent fuel criticality and fuel handling analyses remain bounded by the existing analyses and Technical Specification Design Feature limits. Puel-handling equipment and procedures are not affected by these weight changes.
Seismic /LOCA analyses contain sufficient conservatism to bound these weight changes.
Other accident analyses are not affected by rod weight as a direct parameter, and the existing analyses remain bounding.
The deletion of the fuel rod uranium weight limit does not significantly increase the probability or consequences of previously evaluated accidents.
The mriation in fuel rod weight + hat can occur even without a Technical Specification limit is small based on other fuel design constraints, e.g.,
rod diameter, gap size, UO density and active fuel length; all of which 2
r Mr. H. R. Denten Auguot 13, 1986 Attschmsnt II to NHLNRC 86-147 Page 2 of 2 pro vtJe acce limit on the variation in rod weight.
The current safety analyees are not taaed directly on fuel rod weight, but rather on design parametare such as power, and fuel dimensions.
These parameters are either
( O r.ot affacted kt all by fuel rod weight, or (2) are only slightly affectcd.
iiowa ver,
a review of design parameters which may be affected indicates that a change in fuel weight does not cause other design yarameters to exoped the values assumed in the various safety analyses, or to onusa acceptance critoria to be exceeded.
The effects are not significant with respect to measured nuclear parameters (power, power diatribetion, cuolear coefficients),
i.e.,
they renain within their Technical Specificaion limita.
- Thus, it is concluded that the Technical Specification modification does not involve a significant increase in the probability cr coceequences of a previously evaluated accident.
The ersation of a new, different kind of accident from any previously evaluated accident is not considered a possibility.
All of the fuel contained in the fas1 rod is similar to and designed to function similar to previoua fuel.
- Thus, the existing new and spent fuel storage criticality analyses bound the changes observed.
This change is considered as administrstivo in nature and does not create the possibility of a new or different Aind of accident.
The margin of cAfety is maintained by adherence to other fuel related Technical Cpecification ilmits and the PSAR design bases.
The deletion of fuel rod weight limits in the Technical Specifications Design Features Section 5 3 1 does not directly affect any safety system or the safety licita, thus, cot affecting the plant margin to safety.
Baoed on the abo ve,
the proposed revision to the Wolf Creek Generating Station, Unit No.
1, Technical Specification does not constitute a Significant Hszards Conoideration.
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S ATTACIMENT III I
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