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'@ Xcel Energye August 26,201 1 Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 L-MT-11-05 1 10 CFR 50.73 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50-263 Renewed Facility Operating License No. DPR-22 LER 201 1-005, "Power Ranae Monitor Channels Out of Alinnment" The Licensee Event Report (LER) for this occurrence is attached.
Summaw of Commitments and no revisions to existing commitments.
Plant Enclosure cc:
Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC
ANRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (1 0-201 0)
LICENSEE EVENT REPORT (LER)
(See reverse for re uired number of digits/characters?or each block)
- 1. FACILITY NAME Monticello Nuclear Generating Plant APPROVED BY OMB NO. 3150-0104 EXPIRES 1013112013
, the RRC m?y not conduct or sponsor, and a person IS not requlred to respond to, the lnformatlon collectlon.
- 2. DOCKET NUMBER 05000 263
- 4. TITLt Power Range Monitor Channels Out of Alignment
- 3. PAGE 1 of 3
- 5. EVENT DATE MONTH 06
- 6. LER NUMBER I
I
- 12. LICENSEE CONTACT FOR THlS LER FACILITY NAME TELtPHONE NU f v
i E
p
- 11. THlS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 5: (Check all that apply)
C] 20.2201(b)
C] 20.2203(a)(3)(i)
C] 50.73(a)(2)(i)(C)
C] 50.73(a)(2)(vii) 20.2201 (d)
C] 20.2203(a)(3)(ii)
C] 50.73(a)(2)(ii)(A)
C] 50.73(a)(2)(viii)(A)
C] 20.2203(a)(I)
C] 20.2203(a)(4)
C] 50,73(a)(2)(ii)(B)
C] 50,73(a)(2)(viii)(B)
C] 20.2203(a)(2)(i)
C] 50.36(c)(l)(i)(A)
C] 50,73(a)(2)(iii)
C] 50,73(a)(2)(ix)(A)
C] 20.2203(a)(2)(ii)
C] 50,36(c)(l)(ii)(A)
[XI 50.73(a)(2)(iv)(A)
C] 50.73(a)(2)(x)
C] 20.2203(a)(2)(iii)
C] 50.36(~)(2)
C] 50,73(a)(2)(v)(A)
C] 73.71 (a)(4)
C] 20.2203(a)(2)(iv)
C] 50,46(a)(3)(ii)
C] 50.73(a)(2)(v)(B)
C] 73.71 (a)@)
C] 20.2203(a)(2)(v)
C] 50,73(a)(2)(i)(A) 50.73(a)(2)(v)(~)
C] OTHER S eci in Abstract below or in C] 20.2203(a)(2)(vi)
C] 50.73(a)(2)(i)(B)
[XI 50.73(a)(2)(v)(D)
N ~ C (10-2010)
1 CORRECTIVE ACTIONS
An interim corrective action includes revising reactivity management procedures to include guidance for monitoring and adjusting gains on APRM's prior to each reactivity maneuvering step which could challenge the +I-2% criteria. Additional actions will be implemented based on the results of the causal evaluation.
LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET
PREVIOUS SIMILAR EVENTS
U.S. NUCLEAR REGULATORY COMMISSION On November 4, 2010 all four APRM channels failed to meet the +I-2% tolerance with respect to RTP following isolation of the 15B feedwater heater for repair (LER 201 0-005).
- 1. FACILITY NAME Monticello Nuclear Generating Plant 2. DOCKET 05000 263
- 3. PAGE 3 o f 3
- 6. LER NUMBER YEAR SEQUENTIAL NUMBER REV NO
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| 05000263/LER-2011-001, For Monticello Nuclear Generating Plant, Reactor Vessel Overfill in Appendix R Scenario | For Monticello Nuclear Generating Plant, Reactor Vessel Overfill in Appendix R Scenario | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000263/LER-2011-002, Regarding ESF Actuation Due to Failed Power Supply | Regarding ESF Actuation Due to Failed Power Supply | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000263/LER-2011-003, Regarding Secondary Containment Damper Icing | Regarding Secondary Containment Damper Icing | 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(viii)(B) | | 05000263/LER-2011-004, Regarding Secondary Containment Inoperability Due to Ventilation Alignment Issue | Regarding Secondary Containment Inoperability Due to Ventilation Alignment Issue | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000263/LER-2011-005, Regarding Power Range Monitor Channels Out of Alignment | Regarding Power Range Monitor Channels Out of Alignment | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) | | 05000263/LER-2011-006, Regarding Lntake Structure Fire Suppression System Blockage | Regarding Lntake Structure Fire Suppression System Blockage | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000263/LER-2011-007, Regarding Both Emergency Diesel Generators Declared Inoperable Due to Inadequate Surveillance | Regarding Both Emergency Diesel Generators Declared Inoperable Due to Inadequate Surveillance | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000263/LER-2011-008, Regarding Reactor Scram Due to Loss of Normal Offsite Power | Regarding Reactor Scram Due to Loss of Normal Offsite Power | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000263/LER-2011-009, Regarding Automatic Reactor Scram While Performing Turbine-Generator Testing | Regarding Automatic Reactor Scram While Performing Turbine-Generator Testing | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000263/LER-2011-010, Regarding Rod Worth Minimizer Bypassed During Startup | Regarding Rod Worth Minimizer Bypassed During Startup | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) | | 05000263/LER-2011-011, Regarding Failure to Lock Mode Switch in Refuel Position During Control Rod Exercise | Regarding Failure to Lock Mode Switch in Refuel Position During Control Rod Exercise | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown |
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