ML20248L195
| ML20248L195 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 03/13/1998 |
| From: | Hammer M NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20013F613 | List: |
| References | |
| NUDOCS 9803190078 | |
| Download: ML20248L195 (5) | |
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l UWED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COM%NY MONTICELLO NUCLEAR GENERN.NG PLANT DOCKET NO. 50-263 REQUEST FOR AMENDMENT TO OPERATING LICENSE DPR-22 LICENSE AMENDMENT REQUEST DATED March 13,1998 Northern States Power Company, a Minnesota corporation, requests authorization for changes to Appendix A of the Monticello Operating License as shown on the attachments labeled Exhibits A, B, and C. Exhibit A describes the proposed changes, describes the reasons for the changes, and contains a Safety Evaluation, a Determination of No Significant Hazards Consideration and an Environmental Assessment. Exhibit B contains current Technical Specification pages marked up with the proposed changes. Exhibit C is a copy of the Monticello Technical Specifications incorporating the proposed changes.
Also attached are Exhibits D and F which provide specific information from fuel vendors in support of the proposed amendment. These documents contain information considered proprietary by the vendors and are requested to be withheld from public disclosure in accordance with 10 CFR 2.790(b)(1)(ii). Exhibit E is the Siemens Power Corporation Proprietary information Affidavit for Exhibit F.
NORTHERN STATES POWER COMPANY By M
Michael F; Hammer Plant Manam k anticello b uclear Generating Plant On this 6 day of hauch j 9%
b fore me a notary public in and for said i
County, personally appeared Michael F. Hamer, Plant Manager, Monticello Nuclear Generating Plant, and being first duly swom acknowledged th0t he is authorized to execute this document on behalf of Northern States Power Company, that he knows the contents thereof, and that to the best of his knowledge, information, and belief the staiements made in it are true and that it is not interposed for delay.
e,
SAMUEb. SHIREY Yaniuel1. Shirey U
h) NOTARY PUBUC WIWetSOT Notary Public - Minnesota Sherbume County p g co p Exp.Jan.,31,2000;,
My Commission Expires January 31,2000
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9803190078 980313 PDR ADOCK 05000263 P
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EXHIBIT A MONTICELLO NUCLEAR GENERATING PLANT License Amendment Request Dated March 13,1998 Safety Limit Minimum Critical Power Ratio.
Evaluation of Proposed Changes to the Technical Specifications for Operating License DPR-22.
Pursuant to 10 CFR Part 50, Section 50.90, Northern States Power Company hereby propose the following changes to Appendix A, of the Monticello Technical Specifications:
Proposed Changes in section 2.1.A on page 6, Safety Limit Minimum Critical Power Ratio (SLMCPR) change values from "1.08" to "1.10" for two recirculation loop operation, and from "1.09" to "1.11" for single loop operation.
On pages 6 and 249b, revise footnotes from applying to cycle 18 only, to applying to cycle 19 only. Also, since the NRC issued page 249b including the SER approval date for cycle 18, this should also be updated for cycle 19.
On page 6, change MWT to MWt, and on page 249b, change " Linear Heat Generation Ratio Limits" to " Linear Heat Generation Rate Limits".
Reason for Changes Calculation of the cycle-specific, two-loop and single-loop operation SLMCPR values for Monticello Cycle 19, are based upon the following methodology previously transmitted to the i
NRC.
I
- 1. " General Electric Standard Application for Reactor Fuel," NEDE-24011-P-A-13, including US Supplement, NEDE-24011-P-A-13-US, August,1996, and
- 2.
- Proposed Amendment 25 to GE Licensing Topical Report NEDE-24011-P-A (GESTAR 11) on Cycle Specific Safety Lirait MCPR."
Proposed Amendment 25 was submitted by General Electric Nuclear Energy (GENE) to the NRC on December 13,1996. NEDE-24011-P-A-13-US requires that SLMCPR be reconfirmed each cycle. This reconfirmation was performed using procedures contained in proposed Amendment 25 to GESTAR 11.
GE reconfirmation analysis for Monticello determined the maximum SLMCPR value to be 1.10 for two loop operation, and 1.11 for single loop operation.
A-1
Revised footnotes on pages 6 and 249b will limit the applicability of SLMCPR values to cycle 19.
Format and wording used for these changes is identical to that previously approved for SLMCPR cycle 18. Only the specific values have changed.
On page 6, section 2.3.A.1.a, MWT is being changed to MWt for technical accuracy and consistency with the remainder of the Monticello Technical Specifications.
Changing " Linear Heat Generation Ratio Limits" to " Linear Heat Generation Rate Limits" corrects a previous error.
Sefety Evaluation This proposed Technical Specification (TS) change will revise TS 2.1.A to reflect changes in SLMCPRs due to the cycle-specific analysis performed by GENE for Monticello, Cycle 19. New SLMCPRs were calculated using methodology previously transmitted to the NRC. SLMCPRs are set high enough to ensure that greater than 99.9% of all fuel rods in the core avoid transition boiling if the limit is not violated. MCPRs are calculated to include cycle-specific parameters which include: 1) planned loading,2) conservative variations of projected control blade pattems,
- 3) actual bundle parameters (e.g., local peaking), and 4) full cycle exposure range.
The Monticello cycle 19 core contains 8 Siemens Power Corporation (SPC) Qualification Fuel Assemblies (QFAs). Exhibit F notes that the MCPR safety limit applicable to a given core design without any consideration of the QFAs is also valid for the core design including consideration of QFAs for 3 reasons: (1)The QFA characteristics affecting the number of rods predicted to be in boiling transition are not expected to be significantly different that the characteristics of the coresident fuel i.e. the GE fuel whose performance SPC designed the QFAs to match assumed in the MCPR safety analysis. (2)The QFAs represent a small fraction of the assemblies in the core.
(3)The QFAs are loaded in core locations such that the QFAs have significant CPR margin relative to the limiting MCPR assemblies in the core.
Cycle 19 SLMCPR values quoted in Exhibit F by SPC were 1.11 for two loop recirculation pump operation, and 1.13 for single loop operation based on a preliminary cycle 19 core design. A later core redesign by NSP and resulting SLMCPR calculated by GE resulted in recalculated cycle 19 l
SLMCPR values of 1.10 for two loop recirculation pump operation and 1.11 for single loop l
operation. Since a second review by SPC was not obtained for these new SLMCPR values, the l
Operating Limit MCPR valva for the QFAs in the core monitoring computer databank will be mcreased by 0.02 to ensure that the prior SPC review results are bounded.
l Determination of No Significant Hazards Considerations The proposed change to Monticello's Operating License has been evaluated to determine whether it constitutes a significant hazards consideration as required by 10 CFR Part 50, Section 50.91 using standards provided in Section 50.92. This analysis is provided below:
A-2
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The proposed amendment will not involve a significant increase in the probability or consequences of an accident previously evaluated.
SLMCPR calculations are based on ensuring that greater than 99.9% of all fuel rods in the core avoid transition boiling if the limit is not violated. Proposed SLMCPRs preserve existing margin to transition boiling and fuel damage in the event of a postulated transient. Fuel licensing acceptance criteria for SLMCPR calculations apply to Monticello Cycle 19 in the same manner as previously applied. The probability of fuel damage is not increased.
Therefore, the proposed TS changes do not involve an increase in the probability or consequences of an accident previously evaluated.
The proposed amendment will not create the possibility of a new or different kind of accident frorr.
any accident previously evaluated.
SLMCPR is a TS numerical value designed to ensure that transition boiling does not occur in 99.9% of all fuel rods in the core during the limiting postulated transient.' A change in SLMCPR cannot create the possibility of any new type of accident. SLMCPR values for the new fuel cycle are calculated using previously transmitted methodology. Additionally, the Operating Limit MCPR value for the QFAs in the core monitoring computer databank will be increased by 0.02 to ensure that the prior SPC review results are bounded.
Therefore, the proposed TS changes do not create the possibility of a new or different kind of accident, from any accident previously evaluated.
s The proposed amendment will not involve a significant reduction in the margin of safety.
Fuel licensing acceptance criteria for SLMCPR calculations apply to Monticello Cycle 19 in the same manner as previously applied. SLMCPRs prepared by GE using methodology previously transmitted to the NRC ensure that greater than 99.9% of all fuel rods in the core will avoid transition boiling if the limit is not violated, thereby preserving fuel cladding integrity.
Therefore, the proposed TS changes do not involve a reduction in a margin of safety.
Environmental Assessment Northem States Power has evaluated the proposed changes and determined that the changes:
1.
Do not involve a significant hazards consideration.
2 Do not involve a significant change in the types or significant increase in the amounts of l
any effluent that may be released offsite, and 3.
Do not involve a significant increase in individual or cumulative occupational radiation exposure.
A-3
Accordingly, the proposed changes meet the eligibility criterion for categorical exclusion set forth in 10 CFR Part 51, Section 51.22(b), and an environmental assessment of the proposed changes is not required.
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