LER-2006-005, Re Startup Rate Trip Bypass Enabling Function Below Setpoint |
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| Report date: |
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| Reporting criterion: |
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(viii)(B)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(ix)(A)
10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(x)
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)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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| 3172006005R00 - NRC Website |
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I Calvert Cliffs Nuclear Power Plant Constellation Generation Group, LLC 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 0Constellation Energy February 15, 2007 U.S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
SUBJECT:
Document Control Desk Calvert Cliffs Nuclear Power Plant Unit Nos. 1 and 2; Docket Nos. 50-317 and 50-318; License Nos. DPR 53 and DPR 69 Licensee Event Report 2006-005 Startup Rate Trip Bypass Enabling Function Below Setpoint The attached report is being sent to you as required by 10 CFR 50.73.
Should you have questions regarding this report, please contact Mr. Jay S. Gaines at (410) 495-5219.
Very truly yours, Plant General Manager JEP/MJY/bjd
Attachment:
As stated cc:
D. V. Pickett, NRC S. J. Collins, NRC Resident Inspector, NRC R. I. McLean, DNR
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/3012007
- 6-2004)
, the NRC may digits/characters for each block) nnot conduct or sponsor, and a person Is not required to respond to, the
- 3. PAGE Calvert Cliffs Nuclear Power Plant 05000317 1 OF 004
. TITLE Startup Rate Trip Bypass Enabling Function Below Setpoint
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MNH DY YA YERSEQUENTIAL REV MOT A
ER FACILITY NAMEDOKTNME MONTH DAY YEAR YEAR YEAR Calvert Cliffs, Unit 2 05000318 2 17 j
FACILITY NAME DOCKET NUMBER 1
2006 2006 005 00 02 15 2007 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) 0 20.2201(b)
[I 20.2203(a)(3)(i) 10 50.73(a)(2)(i)(C) 0I 50.73(a)(2)(vii)
[1 20.2201(d)
[0 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A) oI 20.2203(a)(1)
[0 20.2203(a)(4) 0 50.73(a)(2)(ii)(B)
[0 50.73(a)(2)(viii)(B)
[o 20.2203(a)(2)(i)
[I 50.36(c)(1)(i)(A)
[] 50.73(a)(2)(iii)
[0 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL D 20.2203(a)(2)(ii)
[] 50.36(c)(1)(ii)(A) 03 50.73(a)(2)(iv)(A)
[0 50.73(a)(2)(x)
[o 20.2203(a)(2)(iii)
[0 50.36(c)(2) 03 50.73(a)(2)(v)(A)
El 73.71(a)(4)
[o 20.2203(a)(2)(iv)
[0 50.46(a)(3)(ii)
[0 50.73(a)(2)(v)(B) 0 73.71 (a)(5) 100 0 20.2203(a)(2)(v)
[0 50.73(a)(2)(i)(A)
[0 50.73(a)(2)(v)(C) 0 OTHER [o 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B) 0 50.73(a)(2)(v)(D)
Specify In Abstract below or In (If more space is required, use additional copies of (If more space Is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A4)
IV.
CORRECTIVE ACTIONS
A.
The STP M-3 10 was reperformed on both operating units to adjust the bistable setpoints upward and restore operability to the affected channels.
B.
Revise the Technical Specifications Basis description of the Rate of Change of Power-High Trip to include a description of the system's automatic bypass removal feature.
C.
Revise STPs M-310-1 and M-310-2 to include a specification for the reset function of the Linear Range Nuclear Instrument Level One Bistable bypass removal feature.
D.
A review of all RPS STPs will be performed to ensure that no additional components have undefined acceptance criteria for Technical Specification required values.
V.
ADDITIONAL INFORMATION
A.
Component Identification Component Reactor Protection System NI Level 1 Bistable B.
Previous Occurrences
IEEE 803 EIIS Function JD IEEE 805 System ID RLY A review of Calvert Cliffs' licensee event reports over the past three years was performed. The review identified no similar reportable events.
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| 05000318/LER-2006-001, Regarding Reactor Trip During Performance of Maintenance Clearance Order | Regarding Reactor Trip During Performance of Maintenance Clearance Order | 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)(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) | | 05000317/LER-2006-001, Re 1A Diesel Generator Feeder Breaker Tripped Due to Low Design Setpoint | Re 1A Diesel Generator Feeder Breaker Tripped Due to Low Design Setpoint | 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) | | 05000317/LER-2006-002, Regarding Control Element Assembly Determined to Be Untrippable | Regarding Control Element Assembly Determined to Be Untrippable | 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) | | 05000317/LER-2006-003, Re Impact on Safety-Related Equipment Not Considered When High Energy Line Break Barrier Removed | Re Impact on Safety-Related Equipment Not Considered When High Energy Line Break Barrier Removed | 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) | | 05000317/LER-2006-004, Re Reactor Trip Due to Loose Wire During Maintenance on Turbine Control System | Re Reactor Trip Due to Loose Wire During Maintenance on Turbine Control System | 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) 10 CFR 50.73(a)(2)(viii)(A) | | 05000317/LER-2006-005, Re Startup Rate Trip Bypass Enabling Function Below Setpoint | Re Startup Rate Trip Bypass Enabling Function Below Setpoint | 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) |
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