ML20204D975

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{{#if:ML20204D975|Download: [[URL::http://pbadupws.nrc.gov/docs/{{#sub:ML20204D975%7C0%7C6}}/ML20204D975.pdf%7CML20204D975]]|[[URL::http://pbadupws.nrc.gov/docs/{{#sub:%7C0%7C6}}/.pdf%7C]]}} {{#if:6|(page count::6)}}
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}}{{#if:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES, TEXT-SAFETY REPORT|{{#arraymap:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES, TEXT-SAFETY REPORT|,|x|| }}{{#if:{{#show:ML20204D975|?site}}|{{#invoke:Navbox|navbox}}

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{{#Wiki_filter:r: o g g~ i UNITED STATES g j NUCLEAR REGULATORY COMMISSION o WASHINGTON, D.C. - =1 \\,.. SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.185 TO FACILITY OPERATING LICENSE NO. DPR-29 AMENDMENT NO.182 TO FACILITY OPERATING LICENSE NO. DPR-30 COMMONWEALTH EDISON COMPANY AND i MIDAMERICAN ENERGY COMPANY QUAD CITIES NUCLEAR POWER STATION. UNITS 1 AND 2 DOCKET NOS 50-254 AND 50-265 1.0 INTRODUQIJ.QM By {{#if: 

| {{#if:{{#show:ML20204D975|?site|limit=1|link=none}}
  | [[letter::{{#ask:from::[[site::{{#show:ML20204D975|?site|limit=1|link=none}}]]Issue date::August 14, 1998|limit=1|link=none|searchlabel=}}|letter dated August 14,1998]]
  | {{#ask:from::Issue date::August 14, 1998|limit=0|searchlabel=letter dated August 14,1998 }}
  }}
| {{#if:{{#show:ML20204D975|?site|limit=1|link=none}}
  | {{#if:{{#ask:[[site::{{#show:ML20204D975|?site|limit=1|link=none}}]]Issue date::August 14, 1998!~Information Notice*!~Press Release*}}
    | [[letter::{{#ask:[[site::{{#show:ML20204D975|?site|limit=1|link=none}}]]Issue date::August 14, 1998!~Information Notice*!~Press Release*|limit=1|link=none|searchlabel=}}|letter dated August 14,1998]]
    | letter dated August 14,1998
    }}
  | letter dated August 14,1998
  }}

}} (Reference 1), Commonwealth Edison Company (Comed, the licensee) requested changes to the Technical Specifications (TS) for Quad Cities Nuclear Power Station, Units 1 and 2. Additionalinformation was submitted by letters dated October 13,1998 (Reference 2) and December 23,1998 (Reference 8). The proposed changes are due to the transition to Siemens Power Corporation (SPC) ATRIUM-9B fuel. The key items are: 1. incorporation of SPC's new methodologies that would enhance operational flexibility and reduce the likelihood of futur6 plant derates, 2. administrative changes that eliminets both the avele-specific implementation of i ATRIUM-9B fuel and adopt improved Technical Specification language where appropriate, and 3. changes to the Quad Cities Minimum Critical Power Ratio (MCPR) safety limits. Amendment No.182 for Quad Cities, Unit 1, was issued on December 3,1998, as an exigent amendment to acccmmodate these changes before restart from refueling outage Q1R15. This new amendment deletes the unique Unit 1 pages issued in Amendment No.182 and provides identical pages for both units to support the common TS for Quad Cities, Units 1 and 2. 2.0 EVALUATION The requested TS changes can be categorized into five differen! teoics: 1. addition of SPC Generic Methodology for Application of Advanced Nuclear Fuel for Boiling Water Reactors (ANFB) Critical Power Correlation to Non-SPC Fuel-EMF-1125(P)(A), Supplement 1, Appendix C, dated August 1997 (Reference 3); 9903240320 990317 PDR ADOCK 05000254 p PDR

. 2. addition of SPC Topical for ATRIUM-98 fuel ANF-1125(P)(A), Supplement 1, Appendix E, September,1998 (Reference 4) 3. change to MCPR safety limit; 4. ~ removal of footnotes limiting operation witt. iTRIUM-9B fuel reloads; and 5. revision to thermal limit descriptions. Currently, Quad Cities Units 1 and 2, are undergoing a transition from General Electric (GE) to SPC fuel, including the associated methodologies. Due to the transition to SPC fuel it was necessary for SPC to provide a methodology for application of their ANFB critical power correlation to the coresident GE fuel. This topical report has been reviewed and approved by the NRC (Reference 3) and is applicable to Quad Cities. The approval of this report listed two conditions. By {{#if: 

| {{#if:{{#show:ML20204D975|?site|limit=1|link=none}}
  | [[letter::{{#ask:from::[[site::{{#show:ML20204D975|?site|limit=1|link=none}}]]Issue date::July 21, 1998|limit=1|link=none|searchlabel=}}|letter dated July 21,1998]]
  | {{#ask:from::Issue date::July 21, 1998|limit=0|searchlabel=letter dated July 21,1998 }}
  }}
| {{#if:{{#show:ML20204D975|?site|limit=1|link=none}}
  | {{#if:{{#ask:[[site::{{#show:ML20204D975|?site|limit=1|link=none}}]]Issue date::July 21, 1998!~Information Notice*!~Press Release*}}
    | [[letter::{{#ask:[[site::{{#show:ML20204D975|?site|limit=1|link=none}}]]Issue date::July 21, 1998!~Information Notice*!~Press Release*|limit=1|link=none|searchlabel=}}|letter dated July 21,1998]]
    | letter dated July 21,1998
    }}
  | letter dated July 21,1998
  }}

}} (Reference 5), Comed provided the information to address the conditions. This information was reviewed and NRC responded by {{#if: 

| {{#if:{{#show:ML20204D975|?site|limit=1|link=none}}
  | [[letter::{{#ask:from::[[site::{{#show:ML20204D975|?site|limit=1|link=none}}]]Issue date::August 18, 1998|limit=1|link=none|searchlabel=}}|letter dated August 18,1998]]
  | {{#ask:from::Issue date::August 18, 1998|limit=0|searchlabel=letter dated August 18,1998 }}
  }}
| {{#if:{{#show:ML20204D975|?site|limit=1|link=none}}
  | {{#if:{{#ask:[[site::{{#show:ML20204D975|?site|limit=1|link=none}}]]Issue date::August 18, 1998!~Information Notice*!~Press Release*}}
    | [[letter::{{#ask:[[site::{{#show:ML20204D975|?site|limit=1|link=none}}]]Issue date::August 18, 1998!~Information Notice*!~Press Release*|limit=1|link=none|searchlabel=}}|letter dated August 18,1998]]
    | letter dated August 18,1998
    }}
  | letter dated August 18,1998
  }}

}} (Reference 6), that the data provided satisfies the safety evaluation (SE) conditions. By {{#if: 

| {{#if:{{#show:ML20204D975|?site|limit=1|link=none}}
  | [[letter::{{#ask:from::[[site::{{#show:ML20204D975|?site|limit=1|link=none}}]]Issue date::December 23, 1998|limit=1|link=none|searchlabel=}}|letter dated December 23,1998]]
  | {{#ask:from::Issue date::December 23, 1998|limit=0|searchlabel=letter dated December 23,1998 }}
  }}
| {{#if:{{#show:ML20204D975|?site|limit=1|link=none}}
  | {{#if:{{#ask:[[site::{{#show:ML20204D975|?site|limit=1|link=none}}]]Issue date::December 23, 1998!~Information Notice*!~Press Release*}}
    | [[letter::{{#ask:[[site::{{#show:ML20204D975|?site|limit=1|link=none}}]]Issue date::December 23, 1998!~Information Notice*!~Press Release*|limit=1|link=none|searchlabel=}}|letter dated December 23,1998]]
    | letter dated December 23,1998
    }}
  | letter dated December 23,1998
  }}

}}. Comed reaffirmed their commitment to comply' to these conditions. Thus, the addition of SPC Generic Methodology for Application of ANFB Critical Power Correlation to Non-SPC Fuel-EMF-1125(P)(A), Supplement 1, Appendix C, is acceptable. The addition of this methodology will ensure that values of cycle-specific parameters are determined such that all applicable limits of the safety analysis are met. SPC Topical for ATRIUM-9B fuel-ANF-1125(P)(A), Supplement 1, Appendix E, was recently reviewed and approved by NRC (Reference 4) and is applicable to Quad Cities. The restrictions on the additive constant uncertainty from Appendix E are equal to or less restrictive than those used for the analysis of Quad Cities, Unit 1, Cycle 16. The approval of this report (Reference 4) listed three conditions. By {{#if: 

| {{#if:{{#show:ML20204D975|?site|limit=1|link=none}}
  | [[letter::{{#ask:from::[[site::{{#show:ML20204D975|?site|limit=1|link=none}}]]Issue date::December 23, 1998|limit=1|link=none|searchlabel=}}|letter dated December 23,1998]]
  | {{#ask:from::Issue date::December 23, 1998|limit=0|searchlabel=letter dated December 23,1998 }}
  }}
| {{#if:{{#show:ML20204D975|?site|limit=1|link=none}}
  | {{#if:{{#ask:[[site::{{#show:ML20204D975|?site|limit=1|link=none}}]]Issue date::December 23, 1998!~Information Notice*!~Press Release*}}
    | [[letter::{{#ask:[[site::{{#show:ML20204D975|?site|limit=1|link=none}}]]Issue date::December 23, 1998!~Information Notice*!~Press Release*|limit=1|link=none|searchlabel=}}|letter dated December 23,1998]]
    | letter dated December 23,1998
    }}
  | letter dated December 23,1998
  }}

}} (Reference 8), Comed provided the information addressing these issues by committing to comply to these conditions. Thus, the addition of SPC Topical for ATRIUM-98 fuel-ANF-1125(P)(A), Supplement 1, Appendix E, is acceptable. The addition of this methodology will ensure that values of cycle-specific parameters are determined such that all applicable limits of the safety analysis are met. - The change to the MCPR safety limit was due to the change to SPC fuel. Using the SPC ANFB critical power correlation methodology and the ATRIUM-98 additive constant uncertainty r6sulting from the approval of Appendix E (Reference 4) which is applicable to Quad Cities, the MCPR safeiy limit for Quad Cities, Unit 1 is 1.11 as applied in {{#if: 

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  | [[letter::{{#ask:from::[[site::{{#show:ML20204D975|?site|limit=1|link=none}}]]Issue date::December 3, 1998|limit=1|link=none|searchlabel=}}|letter dated December 3,1998]]
  | {{#ask:from::Issue date::December 3, 1998|limit=0|searchlabel=letter dated December 3,1998 }}
  }}
| {{#if:{{#show:ML20204D975|?site|limit=1|link=none}}
  | {{#if:{{#ask:[[site::{{#show:ML20204D975|?site|limit=1|link=none}}]]Issue date::December 3, 1998!~Information Notice*!~Press Release*}}
    | [[letter::{{#ask:[[site::{{#show:ML20204D975|?site|limit=1|link=none}}]]Issue date::December 3, 1998!~Information Notice*!~Press Release*|limit=1|link=none|searchlabel=}}|letter dated December 3,1998]]
    | letter dated December 3,1998
    }}
  | letter dated December 3,1998
  }}

}} (Reference 7). This bounds Cycle 16 operation for Unit 1. Establishing a 1.11 MCPR safety limit will establish a consistent safety limit for boih Units 1 and 2. The applicability of the MCPR safety limit will be confirmed on a cycle-by-cycle basis. The value of 1.11 is anticipated to bound the actual MCPR safety limit for future Quad Cities SPC reloads. Since the MCPR safety limit of 1.11 is calculated with an approved methodology and uses the approved additive constant uncertainty from Appendix E, the change to this value will ensure that 99.9 percent of the fuel avoids transition boiling erd is acceptable.

3-The removal of footnotes limiting operation with ATRIUM-9B fuel reloads is due to the fact that they are no longer needed, since the methodology for ATRIUM-9B fuel has been approved. Tnes, this change is acceptable. The change to revise the thermal limit descriptions is to generalize the definitions of the Average Planar Linear Heat Generation Rate (APLHGR) limits to allow either bundle average or average planar exposure based APLHGR limits, consistent with the loss-of-coolant accident (LOCA) analysis of record. This generalization of the definition of APLHGR is consistent with the improved Standard Technical Specifications (NUREG 1433/1434, Revision 1) wording. Both maximum average planar linear heat-generation rate (MAPLHGRs) (bundle average exposure based and planar average exposure based) are acceptable for Appendix K of 10 CFR. Part 50. Thus, this change is acceptable. Based on the staff evaluation as discussed in 2.0 above, the staff concludes that the proposed TS changes are acceptable for Quad Cities, Unit 1 and 2. 3.0 TECHNICAL SPECIFICATION CHANGES TSs - Page I and 1 Table of Contents and TS Section 1-Delete item in Table of Contents for definition of Average Planar Exposure and delete definition of Average Planar Exposure in TS Section 1. This is acceptable because the Average Planar Exposure is no longer used. TS - Page la and 1-1a for Unit 1 - Delete these pages. The reason for these pages was the issuance of the Unit 1 exigent Amendment No.182, dated December 3,1998 (Reference 7). Since this amendment authorizes the same change for Unit 2, the proposed change deletes the unique Unit 1 pages issued in Amendment No.182 and provides an identical page for both units to support the Quad Cities, Units 1 and 2, common TS. Therefore, this change is acceptable. TS 2.1.B - Page 2 Change the MCPR to 1.11 (from 1.07 and 1.10, respectively). Thi: change results from the use of ATRIUM 9B fuel and is, therefore, acceptable. TS - Page 2-ia - Delete this page. The reason for this page was the footnote stating that the page was applicable to Unit 2, Cycle 15, only. The footnote is no lo.,ger needed since a cycle-specific limitation on the MCPR safety limit is not necessary, and thus, it la acceptable to delete the page. TS - Page 2-1b - Delete this page. The reason for this page was the issuance of the Unit i exigent Amendment No.182, dated December 3,1998 (Reference 7). Since this amendment authorizes the same change for Unit 2, the proposed change deletes the unique Unit 1 page issued in Amendment No.182 and provides an identical page for both units to support the Quad Cities, Units 1 and 2, common TS. Therefore, this change is acceptable. TS - Page 3/4.11 The description of the APLHGR Limiting Condition for Operation (LCO) is changed to not specify that the APLHGR should be a function of average planar exposure. .This change is acceptable because the APLHGR is based on the bundle average exposure consistent with the LOCA analysis.

4 TS - Page 3/4.11 -1a - Delete this page. The reason for this page was the issuance of the Unit 1 exigent Amendment No.182, dated December 3,1998 (Reference 7). Since this amendment authorizes the same change for Unit 2, the proposed change deletes the unique Unit 1 page incorporated by Amendment No.182 and provides an identical page for both units to support the Quad Cities, Units 1 and 2, common TS and is, therefore, acceptable. TS 6.9 - Page 6 -16a - Removal of the Cycle 15 specific footnote and the Cycle 15 specific methodology and addition of the topical reports EMF-1125(P)(A), Supplement 1, Appendix C, dated August 1997 and ANF-1125(P), Supplement 1, Appendix E, dated September 1998, to the list of references. These changes are needed for use of the ATRIUM-9B fuel and reflect the use of NRC-approved methodologies which are not limited to Cycle 15. The addition of these methodologies will ensure that values for cycle-specific parameters are determined such that all applicable limits of the safety analysis are met. Page 6 - 16b has been deleted because i it is identical to the new page 6 - 16a which is applicable to Units 1 and 2. Therefore, these changes are acceptable. Changes to the Bases Section 2.1 - Eliminating Cycle 15 specific footnotes and methodologies for Unit 2. These changes are necessary to make the bases for Unit 2 consistent with the removal of the cycle - specific limitation in the TSs. Bases page B2-3 is reissued to reflect that the page is again applicable to Units 1 and 2. Bases page B2-3a has been deleted. Therefore, these bases changes are acceptable. Based on this staff evaluation as discussed 2.0 and 3.0 above, the staff concludes that j the proposed TS changes are acceptable for Quad Cities, Unit 1 and 2.

4.0 STATE CONSULTATION

in accordance with the Commission's regulations, the Illinois State official was notified of the proposed issuance of the amendments. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (63 FR 59588). The amendments also change recordkeeping or reporting requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and (c)(10). Pursuant to 10 CFR 51.22(b), no environmentalimpact statement or environmental assessment racd be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there 4 is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public. Principal Contributor: M. Chatterton R. Pulsifer Date: March 17,1999

7.0 REFERENCES

. 1. Letter from R.M. Krich, Commonwealth Edison Company, to NRC, dated August 14, 1998. 2. Letter from R.M. Krich, Commonwealth Edison Company, to NRC, dated October 13, 1998. 3. EMF-1125(P)(A), Supplement 1, Appendix C, "ANFB Critical Power Correlation Application for Coresident Fuel," August 1997, and NRC SE, " Acceptance for Referencing of Licensing Topical Report EMF-1125(P), Supplement 1, Appendix C, "ANFB Critical Power Correlation Application for Co-Resident Fuel, " J.E. Lyons to R.A. Copeland, May 9,1997. 4. ANF-1125(P), Supplement 1, Appendix E, "ANFB Critical Power Correlation Determination of ATRIUM-98 Additive Constant Uncertainties," September 1998 and NRC SE, " Acceptance for Referencing of Licensing Topical Report ANF-1125(P), Supplement 1, Appendix E, Critical Power Correlation Determination of ATRIUM-9B Additive Constant Uncertainties," T. H. Essig to H.D. Curet, September 23,1998. 5. Letter from J.P. Dimmest, Commonwealth Edison Company, to NRC, dated July 21, 1998. 1 6. Letter from R.M. Pulsifer, NRC, to 0.D. Kingsley, Commonwealth Edison Company, dated August 18,1998. 1 7. Letter from R. M. Pulsifer, NRC, to O.D. Kingsley, Commonwealth Edison Cr, rop any, dated December 3,1998, " Issuance of Amendment - Quad Cities Nuclear Po.:ar Station, Unit 1 (TAC No. M99552). i 8. Letter from R. M. Krich, Commonwealth Edison Company, to NRC, dated December 23, 1998. . _ _}}

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