RS-02-073, Request for Amendment, Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit
| ML021120297 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 04/08/2002 |
| From: | Jury K Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RS-02-073 | |
| Download: ML021120297 (14) | |
Text
Exelonm Exelon Generation www.exeloncorp.com Nliiclear 4300 Winfield Road 10 CFR .
WaTrenville, IL60555 RS-02-073 April 8, 2002 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Quad Cities Nuclear Power Station, Unit 1 Facility Operating License No. DPR-29 NRC Docket No. 50-254
Subject:
Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit In accordance with 10 CFR 50.90, "Application for amendment of license or construction permit," Exelon Generation Company (EGC), LLC, requests a change to the Technical Specifications (TS) of Facility Operating License Number DPR-29 for the Quad Cities Nuclear Power Station (QCNPS), Unit 1. The proposed change revises the values of the Safety Limit for the Minimum Critical Power Ratio (SLMCPR) in TS Section 2.1.1, "Reactor Core SLs," for Unit 1 Cycle 17A for both two loop operation (TLO) and single loop operation (SLO).
QCNPS, Unit 1 shutdown during Cycle 17 on January 9, 2002, to investigate indications of a jet pump failure. The unit was restarted on February 5, 2002, following replacement of jet pump hold down beams. During this shutdown period EGC replaced a leaking fuel assembly and shuffled fuel assemblies in the reactor core in order to obtain additional thermal energy from the reactor core to reduce a planned coastdown at the end of Cycle 17.
Due to this mid-cycle core shuffle, new safety analyses were performed to justify operation with the current operating limits. Analysis results for this revised core (termed Cycle 17A) continue to support the current TLO SLMCPR of 1.11 and SLO SLMCPR of 1.12 to a Cycle 17A exposure of 4,140 megawatt days per metric ton uranium (MWD/MTU). However, for operation beyond 4,140 MWD/MTU, the required TLO SLMCPR is 1.15 and the required SLO SLMCPR is 1.16. The proposed change revises the SLMCPR for Cycle 17A exposure greater than 4,000 MWD/MTU.
The Cycle 17A exposure of 4,000 MWD/MTU is projected to occur on approximately August 21, 2002. Therefore, EGC requests approval of this proposed change prior to July 29, 2002, to support operation of QCNPS, Unit 1 through the end of the cycle in November 2002.
This request is subdivided as follows.
Attachment A gives a description and safety analysis of the proposed change.
A00I
April 8, 2002 U. S. Nuclear Regulatory Commission Page 2 Attachment B includes the marked-up TS page with the proposed change indicated.
Attachment C includes the revised TS page.
Attachment D describes our evaluation performed using the criteria in 10 CFR 50.91 (a)(1) that provides information supporting a finding of no significant hazards consideration using the standards in 10 CFR 50.92(c).
Attachment E provides information supporting an Environmental Assessment.
This proposed change has been reviewed by the Plant Operations Review Committee and the Nuclear Safety Review Board in accordance with the Quality Assurance program.
EGC is notifying the State of Illinois of this application request for a change to the TS by transmitting a copy of this letter and its attachments to the designated State Official.
Should you have any questions concerning his letter, please contact Mr. Don Cecchett at (630) 657-2826.
Resppe/ully, je.jl' Keith R. Jury LI Director - Licensing Mid-West Regional Operating Group Attachments:
Affidavit Attachment A: Description and Safety Analysis for Proposed Changes Attachment B: Marked - Up Technical Specifications Page Attachment C: Revised Technical Specifications Pages for Proposed Changes Attachment D: Information Supporting a Finding of No Significant Hazards Consideration Attachment E: Information Supporting an Environmental Assessment cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - Quad Cities Nuclear Power Station Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety
STATE OF ILLINOIS )
COUNTY OF DUPAGE )
IN THE MATTER OF )
EXELON GENERATION COMPANY ) Docket Number QUAD CITIES NUCLEAR POWER STATION, UNIT 1) 50-254
SUBJECT:
Request for Technical Specifications Change Minimum Critical Power Ratio Safety Limit AFFIDAVIT I affirm that the content of this transmittal is true and correct to the best of my knowledge, information and belief.
Keith R. Jury Director - Licensing Mid-West Regional Operating Group Subscribed and sworn to before me, a Notary Public in and for the State above named, this ____, _ day of
__2002-.
EOFFICIAL SEA PAC TMTYA. BYAM Not ry Public MTO om
Attachment A Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit DESCRIPTION AND SAFETY ANALYSIS FOR PROPOSED CHANGES A.
SUMMARY
OF PROPOSED CHANGES Pursuant to 10 CFR 50.90, "Application for amendment of license or construction permit," Exelon Generation Company (EGC), LLC, requests a change to the Technical Specifications (TS) for Quad Cities Nuclear Power Station (QCNPS), Unit 1. The proposed change revises the values of the Safety Limit for the Minimum Critical Power Ratio (SLMCPR) in TS Section 2.1.1, "Reactor Core SLs," for Unit 1 Cycle 17A for both two loop operation (TLO) and single loop operation (SLO).
QCNPS, Unit 1 shut down during Cycle 17 on January 9, 2002, to investigate indications of a jet pump failure. The unit was restarted on February 5, 2002, following replacement of jet pump hold down beams. During this shutdown period EGC replaced a leaking fuel assembly and re-shuffled the fuel assemblies in the reactor core in order to obtain additional thermal energy from the reactor core to reduce a planned end of cycle coastdown. To support operation following this mid-cycle core shuffle, new safety analyses were performed to justify operation with the current operating limits.
Analysis results for this revised core (termed Cycle 17A, or QCI C1 7A) continue to support a TLO SLMCPR of 1.11 and SLO SLMCPR of 1.12 to a cycle exposure of 4,140 Mega Watt Days/Metric Ton Uranium (MWD/MTU). However, for operation beyond 4,140 MWD/MTU, the required TLO SLMCPR is 1.15 and the required SLO SLMCPR is 1.16.
The proposed change is described in detail in Section E of this Attachment. The marked up TS page is provided in Attachment B. Attachment C contains the TS page with the proposed change incorporated.
B. DESCRIPTION OF THE CURRENT REQUIREMENTS TS Section 2.1.1, "Reactor Core SLs," contains the SLMCPR for TLO and SLO. TS Section 2.1.1.2 reads, "MCPR shall be Ž_ 1.11 for two recirculation loop operation orŽ 1.12 for single recirculation loop operation."
C. BASES FOR THE CURRENT REQUIREMENTS The fuel cladding integrity SLMCPR is established to assure that at least 99.9% of the fuel rods in the core do not experience boiling transition during an anticipated operational occurrence. To determine the specific value for the cycle specific safety limit, a full core statistical analysis is performed. The core model incorporates the uncertainty effects in the measurement of core operating parameters, critical power ratio calculational uncertainties, and the statistical uncertainty associated with the fuel vendor's correlation.
The probability of boiling transition occurring, and the number of rods that might possibly experience boiling transition as a function of the nominal MCPR, is then calculated. The Page 1 of 3
Attachment A Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit SLMCPR for the current QCNPS cycle (i.e., QC1C17A) is based on Siemens Power Corporation reload fuel and calculation methodologies as described in the current TS.
C. NEED FOR REVISION OF THE REQUIREMENT QCNPS, Unit 1 shut down during Cycle 17 on January 9, 2002, to investigate indications of a jet pump failure. The unit was restarted on February 5, 2002, following replacement of jet pump hold down beams. Also, during Cycle 17, one fuel assembly was identified to have developed a small cladding leak. When QCNPS, Unit 1 was shut down in January 2002, this fuel assembly was replaced with an exposed GEl0 fuel assembly and the existing fuel assemblies were shuffled in order to obtain additional thermal energy from the reactor core to reduce a planned coastdown at the end of Cycle 17.
To support operation following this mid-cycle core shuffle, new safety analyses were performed to justify operation with the current operating limits. Although the analysis results continue to support a TLO SLMCPR of 1.11 and a SLO safety limit MCPR of 1.12 for a Cycle 17A exposure of 4,140 MWD/MTU, changes to these limits were necessary for higher exposure. For operation beyond 4,140 MWD/MTU, the required TLO safety limit MCPR is 1.15 and the required SLO safety limit MCPR is 1.16.
D. DESCRIPTION OF THE PROPOSED CHANGE The value of the SLMCPR in TS Section 2.1.1.2 is revised to read, "For Unit 1, with Cycle 17A exposure less than or equal to 4,000 MWD/MT, for two recirculation loop operation, MCPR shall be _>1.11, or for single recirculation loop operation, MCPR shall be Ž1.12. For Unit 1, with Cycle 17A exposure greater than 4,000 MWD/MTU, for two recirculation loop operation MCPR shall be > 1.15, or for single recirculation loop operation MCPR shall be > 1.16.
For Unit 2, MCPR shall be > 1.11 for two recirulation loop operation, or for single recirculation loop operation, MCPR shall be Ž 1.12. "
F. SAFETY ANALYSIS OF THE PROPOSED CHANGE The QCNPS, Unit 1, Cycle 17 core contained a mixture of fuel supplied by Siemens Power Corporation, now Framatome ANP (FANP), and by Global Nuclear Fuel (GNF).
During Cycle 17, one fuel assembly was identified to have developed a small cladding leak. When QCNPS, Unit 1 was shut down in January 2002, this fuel assembly was replaced with an exposed GEl 0 fuel assembly and the existing fuel assemblies were shuffled. No fresh fuel was added during this shuffle. Thus, the QCNPS, Unit 1 Cycle 17A core contains a mixture of FANP (i.e., ATRIUM-9B) and GNF (i.e., GEl0) fuel.
FANP has performed a full core statistical analysis for the Cycle 17A core. This analysis evaluated the SLMCPR using the Reference 1 NRC-approved correlation with the ATRIUM-9B additive constant uncertainty that was approved by the NRC in Reference
- 2. These calculations use the ANFB correlation for all fuel types including the co resident GEl0 fuel as approved in Reference 3.
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Attachment A Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit The results of the SLMCPR analysis indicate that the current Unit 1 SLMCPR of 1.11 for TLO is supportable up to a cycle exposure of 4,140 MWD/MTU. This cycle exposure is measured from the beginning of Cycle 17A (i.e., February 2002). However, for cycle exposure greater than 4,140 MWD/MTU, a SLMCPR of 1.15 for TLO and 1.16 for single recirculation loop operation are required to ensure that fewer than 0.1% of the rods are predicted to experience boiling transition. The exposure of 4,000 MWD/MTU reflected in the proposed TS was conservatively chosen to account for any potential effects of operation which may increase bundle exposure beyond the assumptions in the analysis.
The increased SLMCPR for Cycle 17A exposure greater than 4,000 MWD/MTU is primarily due to increased bundle exposures in the Cycle 17A core design. The mid cycle core shuffle relocated peripheral, high exposure GEl 0 bundles nearer to limiting core locations. The resulting increased exposures of these bundles result in a significant increase in the impact of channel bow uncertainties on the SLMCPR calculation. All bundle exposures at end of cycle (EOC) remain within the limits specified in the QCNPS, Unit loperating license.
G. IMPACT ON PREVIOUS SUBMITTALS There are no pending submittals for which the proposed change would have an impact.
H. SCHEDULE REQUIREMENTS The Cycle 17A exposure of 4,000 MWD/MTU is projected to occur on approximately August 21, 2002. Therefore, EGC requests approval of this proposed change prior to July 29, 2002, to support operation of QCNPS, Unit I through the end of the cycle in November 2002.
I. REFERENCES
- 1) ANF-1 125(P)(A) and Supplements 1 and 2, "ANFB Critical Power Correlation," April 1990
- 2) ANF-1 125(P)(A), Supplement 1, Appendix E, "ANFB Critical Power Correlation Determination of ATRIUM-9B Additive Constant Uncertainties," Siemens Power Corporation, September 1998
- 3) EMF-1 125(P)(A) Supplement 1 Appendix C, "ANFB Critical Power Correlation Application for Co-Resident Fuel," Siemens Power Corporation, August 1997 Page 3 of 3
Attachment B Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit MARKED-UP TECHNICAL SPECIFICATIONS PAGE
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:
THERMAL POWER shall be _ 25% RTP.
With the reactor steam dome pressure >_ 785 psig and core 2.1.1.2 flow >_ 10% rated core flow:
A.
MCPR. shal be _ 1.11 for/wo recircula ion loop op ation or _ 1. for single re irculation lopo 2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be < 1345 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.
Quad Cities 1 and 2 2.0-1 Amendment No.
Insert A For Unit 1, with Cycle 17A exposure less than or equal to 4,000 MWD/MT, for two recirculation loop operation, MCPR shall be > 1.11, or for single recirculation loop operation, MCPR shall be > 1.12. For Unit 1, with Cycle 17A exposure greater than 4,000 MWD/MTU, for two recirculation loop operation MCPR shall be > 1.15, or for single recirculation loop operation MCPR shall be > 1.16.
For Unit 2, MCPR shall be > 1.11 for two recirulation loop operation, or for single recirculation loop operation, MCPR shall be Ž_1.12.
Attachment C Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit REVISED TECHNICAL SPECIFICATIONS PAGE
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs or core 2.1.1.1 With the reactor steam dome pressure < 785 psig flow < 10% rated core flow:
THERMAL POWER shall be <_ 25% RTP.
and core 2.1.1.2 With the reactor steam dome pressure >- 785 psig flow > 10% rated core flow:
equal to For Unit 1, with Cycle 17A exposure less than or operation, MCPR 4,000 MWD/MT, for two recirculation loop shall be > 1.11, or for single recirculation loop operation, MCPR shall be >- 1.12. For Unit 1, with Cycle 17A exposure greater than 4,000 MWD/MTU, for two 1.15, or for recirculation loop operation MCPR shall be >
be > 1.16.
single recirculation loop operation MCPR shall For Unit 2, MCPR shall be > 1.11 for two recirulation loop operation, or for single recirculation loop operation, MCPR shall be >_ 1.12.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be < 1345 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.
2.0-1 Amendment No.
Quad Cities 1 and 2
Attachment D Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit INFORMATION SUPPORTING A FINDING OF NO SIGNIFICANT HAZARDS CONSIDERATION According to 10 CFR 50.92(c), "Issuance of amendment," a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not:
Involve a significant increase in the probability or consequences of an accident previously evaluated; or Create the possibility of a new or different kind of accident from any accident previously evaluated; or Involve a significant reduction in a margin of safety.
Exelon Generation Company (EGC), LLC, is proposing to amend the Quad Cities Nuclear Power Station (QCNPS) Technical Specifications (TS) to revise the Safety Limit Minimum Critical Power Ratio (SLMCPR) to support operation following a mid-cycle core shuffle. The proposed change revises the SLMCPR for Unit 1. For cycle exposure greater than 4,140 megawatt days per metric ton uranium (MWD/MTU), the two loop operation SLMCPR increases from 1.11 to 1.15, and the single loop operation SLMCPR increases from 1.12 to 1.16.
Information supporting the determination that the criteria set forth in 10 CFR 50.92 is met for this amendment request is indicated below.
Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
The probability of an evaluated accident is derived from the probabilities of the individual precursors to that accident. The consequences of an evaluated accident are determined by the operability of plant systems designed to mitigate those consequences. Limits have been established consistent with NRC approved methods to ensure that fuel performance during normal, transient, and accident conditions is acceptable. The proposed change conservatively establishes the safety limit for the minimum critical power ratio (SLMCPR) for Quad Cities Nuclear Power Station (QCNPS), Unit 1 such that the fuel is protected during normal operation and during any plant transients or anticipated operational occurrences.
Changing the SLMCPR does not increase the probability of an evaluated accident. The change does not require any physical plant modifications, physically affect any plant components, or entail changes in plant operation. Therefore, no individual precursors of an accident are affected.
The proposed change revises the SLMCPR to protect the fuel during normal operation as well as during any transients or anticipated operational occurrences. Operational limits will be established based on the proposed SLMCPR to ensure that the SLMCPR is Page 1 of 2
Attachment D Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit not violated during all modes of operation. This will ensure that the fuel design safety criteria (i.e., that at least 99.9% of the fuel rods do not experience transition boiling during normal operation and anticipated operational occurrences) is met. Since the operability of plant systems designed to mitigate any consequences of accidents has not changed, the consequences of an accident previously evaluated are not expected to increase.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Creation of the possibility of a new or different kind of accident would require the creation of one or more new precursors of that accident. New accident precursors may be created by modifications of the plant configuration, including changes in allowable modes of operation. The proposed change does not involve any modifications of the plant configuration or allowable modes of operation. The proposed change to the SLMCPR assures that safety criteria are maintained for QCNPS, Unit 1.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
Does the proposed change involve a significant reduction in a margin of safety?
The value of the proposed SLMCPR provides a margin of safety by ensuring that no more than 0.1% of the rods are expected to be in boiling transition if the MCPR limit is not violated. The proposed change will ensure the appropriate level of fuel protection.
Additionally, operational limits will be established based on the proposed SLMCPR to ensure that the SLMCPR is not violated during all modes of operation. This will ensure that the fuel design safety criteria (i.e., that at least 99.9% of the fuel rods do not experience transition boiling during normal operation as well as anticipated operational occurrences) are met.
Therefore, the proposed change does not involve a significant reduction in the margin of safety.
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Attachment E Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit INFORMATION SUPPORTING AN ENVIRONMENTAL ASSESSMENT Exelon Generation Company (EGC), LLC, has evaluated this proposed change against the criteria for identification of licensing and regulatory actions requiring environmental assessment in accordance with 10 CFR 51.21, "Criteria for and identification of licensing and regulatory actions requiring environmental assessment." EGC has determined that this proposed change meets the criteria for a categorical exclusion set forth in 10 CFR 51.22(c)(9), "Criteria for categorical exclusion; identification of licensing and regulatory actions eligible for categorical exclusion or otherwise not requiring environmental review," and as such, has determined that no irreversible consequences exist in accordance with 10 CFR 50.92(b), "Issuance of amendment." This determination is based on the fact that this change is being proposed as an amendment to a license issued pursuant to 10 CFR 50, "Domestic Licensing of Production and Utilization Facilities," which changes a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, "Standards for Protection Against Radiation," or that changes an inspection or a surveillance requirement, and the amendment meets the following specific criteria.
(i) The amendment involves no significant hazards consideration.
As demonstrated in Attachment D, this proposed change does not involve any significant hazards consideration.
(ii) There is no significant change in the types or significant increase in the amounts of any effluent that may be released offsite.
The proposed change is limited to revising the Safety Limit Minimum Critical Power Ratio. This change does not by itself allow for an increase in the unit power level, does not increase the production, nor alter the flow path or method of disposal of radioactive waste or byproducts. Therefore, the proposed change does not affect actual unit effluents.
(iii) There is no significant increase in individual or cumulative occupational radiation exposure.
The proposed change will not result in changes in the operation or configuration of the facility. There will be no change in the level of controls or methodology used for processing of radioactive effluents or handling of solid radioactive waste, nor will the proposal result in any change in the normal radiation levels within the plant. Therefore, there will be no increase in individual or cumulative occupational radiation exposure resulting from this change.
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