05000482/LER-2008-001, Regarding Completion of a Technical Specification Required Shutdown

Regarding Completion of a Technical Specification Required Shutdown

ML080780416
Person / Time
Site:	Wolf Creek
Issue date:	03/07/2008
From:	Matthew Sunseri Wolf Creek
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
WO 08-0008 LER 08-001-00
Download: ML080780416 (5)

LER-2008-001, Regarding Completion of a Technical Specification Required Shutdown

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
4822008001R00 - NRC Website

text

W9LF CREEK NUCLEAR OPERATING CORPORATION Matthew W. Sunseri Vice President Operations and Plant Manager March 7, 2008 WO 08-0008 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555

Subject:

Docket No. 50-482: Licensee Event Report 2008-001-00, Completion of a Technical Specification Required Shutdown Gentlemen, As a result of Technical Specification surveillance testing, gas voids were found in the suction piping of the Emergency Core Cooling System (ECCS).

The plant conservatively entered Technical Specification 3.0.3 and placed the unit in Mode 3. Engineering evaluation of the void content concluded that the ECCS would still have performed its safety function. The enclosed Licensee Event Report (LER) 2008-001-00 is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(A) to document this condition.

This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4008, or Mr. Richard D. Flannigan, Manager Regulatory Affairs at (620) 364-4117.

Sincerely, Matthew W. Sunseri MWS/rlt Enclosure cc:

E. E. Collins (NRC), w/e V. G. Gaddy (NRC), w/e B. K. Singal (NRC), w/e Senior Resident Inspector (NRC), w/e P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)

, the NRC may (See reverse for required number of not conduct or sponsor, and a person is not required to respond to, the digits/characters for each block) information collection.

3. PAGE WOLF CREEK GENERATING STATION 05000 482 1 OF 4

4. TITLE Completion of a Technical Specification Required Shutdown

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED SEUNIA IE FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEUENTIAL REV MONTH DAY YEAR 05000 NUMBER NO. I05000 FACILITY NAME DOCKET NUMBER 01 10 2008 2008 001 00 03 07 2008 05000

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) 1 I]

20.2201(b)

[]

20.2203(a)(3)(i)

[]

50.73(a)(2)(i)(C)

[]

50.73(a)(2)(vii) o 20.2201(d)

E] 20.2203(a)(3)(ii)

[]

50.73(a)(2)(ii)(A)

E] 50.73(a)(2)(viii)(A)

O 20.2203(a)(1)

El 20.2203(a)(4)

[

50.73(a)(2)(ii)(B)

[J 50.73(a)(2)(viii)(B)

[]

20.2203(a)(2)(i)

El 50.36(c)(1)(i)(A)

E] 50.73(a)(2)(iii)

El 50.73(a)(2)(ix)(A)

10. POWER LEVEL 5

20.2203(a)(2)(ii) 5 50.36(c)(1)(ii)(A) fl 50.73(a)(2)(iv)(A) fl 50.73(a)(2)(x) j]

20.2203(a)(2)(iii) fl 50.36(c)(2)

El 50.73(a)(2)(v)(A)

El 73.71(a)(4) 100 5 20.2203(a)(2)(iv)

[] 50.46(a)(3)(ii)

EJ 50.73(a)(2)(v)(B)

El 73.71 (a)(5)

El 20.2203(a)(2)(v)

[]

50.73(a)(2)(i)(A) 5 50.73(a)(2)(v)(C)

Q OTHER

[]

20.2203(a)(2)(vi)

E] 50.73(a)(2)(i)(B)

E] 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 366A)

SAFETY SIGNIFICANCE

The presence of non-condensable gas volumes in the suction side of the ECCS pumps has the potential to gas-bind the pump or to reduce the discharge pressure, affecting the pump function during cold leg recirculation. Of specific concern at Wolf Creek was the gas volumes found in the piggy-back piping between the RHR discharge and the high and intermediate head injection pumps. Depending on which RHR pump is operating, this piping provides a common flow path to both trains of the CCPs or both trains of the SI pumps. Gas volumes in this piping could potentially affect either both CCPs or both SI pumps. Depending upon which RHR pump or train has failed, flow through this piping will only flow to one subsystem (CCP or SI), but not both. Thus it could not adversely affect both subsystems simultaneously.

This event had a low safety significance since the presence of the voids would not have prevented the ECCS pumps from performing their safety function.

OPERATING EXPERIENCE/PREVIOUS EVENTS:

None.