05000244/LER-2007-002, Regarding Closure of Main Steam Isolation Valve Results in Safety Injection Signal and Plant Trip
| ML071410281 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/14/2007 |
| From: | Korsnick M Constellation Energy Group, Ginna |
| To: | Document Control Desk, Plant Licensing Branch III-2 |
| References | |
| LER 07-002-00 | |
| Download: ML071410281 (8) | |
| Event date: | |
|---|---|
| Report date: | |
| 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 |
| 2442007002R00 - NRC Website | |
text
Maria Korsnick Site Vice President 0
Constellation Energy Generation Group R.E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, New York 14519-9364 585.771.5200 585.771.3943 Fax maria.korsnick@constellation.com May 14, 2007 U.S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
SUBJECT:
Document Control Desk R.E. Ginna Nuclear Power Plant Docket No. 50-244 LER 2007-002, Closure of Main Steam Isolation Valve Results in Safety Injection Signal and Plant Trip The attached Licensee Event Report (LER) 2007-002 is submitted in accordance with 10 CFR 50.73, Licensee Event Report System. There are no new commitments contained in this submittal. Should you have questions regarding the information in this submittal, please contact Mr. Robert Randall at (585) 771-5219 or robert.randall@constellation.com.
Very truly yours, May.Korsnick Attachments: (1)
LER 2007-002 cc:
S. J. Collins, NRC D. V. Pickett, NRC Resident Inspector, NRC (Ginna) 1001-7qo
Attachment 1
LER 2007-002 Closure of Main Steam Isolation Valve Results in Safety Injection Signal and Plant Trip
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information digits/characters for each block) collection.
- 3. PAGE R.E. Ginna Nuclear Power Plant 05000244
- 4. TITLE Closure of Main Steam Isolation Valve Results in Safety Injection Signal and Plant Trip
- 5. EVENT DATE
- 6. LER NUMBER _
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER YER NUMBER NO.
MOT A
ER05000 FACILITY NAME DOCKET NUMBER 03 16 2007 2007 - 002 -
00 5
14 2007 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
El 20.2201(b)
E] 20.2203(a)(3)(i)
[E 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii)
El 20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
El 20.2203(a)(4)
[I 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
El 20.2203(a)(2)(i)
[E 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL
[] 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A)
[I 50.73(a)(2)(x)
[] 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71 (a)(4)
El 20.2203(a)(2)(iv)
E] 50.46(a)(3)(ii)
[J 50.73(a)(2)(v)(B)
El 73.71(a)(5) 100 [E 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
[E OTHER El 20.2203(a)(2)(vi)
[E 50.73(a)(2)(i)(B)
El 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 (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A)
VI.
ADDITIONAL INFORMATION
A.
FAILED COMPONENTS:
Following the event, during component realignment, the motor driven fire pump breaker failed to close remotely.
B.
PREVIOUS LERs ON SIMILAR EVENTS:
A similar Ginna LER event historical search was conducted which resulted in a determination that the drilled plug was initially installed as a result of early plant events. This was described in event 75-03, Spurious Closing of Main Steam Isolation Valves.
C.
THE ENERGY INDUSTRY IDENTIFICATION SYSTEM (EIIS) COMPONENT FUNCTION IDENTIFIER AND SYSTEM NAME OF EACH COMPONENT OR SYSTEM REFERRED TO IN THIS LER:
COMPONENT IEEE 803 IEEE 805 FUNCTION NUMBER SYSTEM IDENTIFICATION Valve, Isolation ISV SB