05000255/LER-2007-004, Regarding Shutdown Cooling Train Inoperable
| ML071360101 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 05/03/2007 |
| From: | Schwarz C Entergy Nuclear Operations |
| To: | Document Control Desk, Plant Licensing Branch III-2 |
| References | |
| LER 07-004-00 | |
| Download: ML071360101 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(B) |
| 2552007004R00 - NRC Website | |
text
- Entergy Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043 May 3, 2007 10 CFR 50.73(a)(2)(i)(B)
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Palisades Nuclear Plant Docket 50-255 License No. DPR-20 Licensee Event Report 07-004, Shutdown Cooling Train Inoperable
Dear Sir or Madam:
Licensee Event Report (LER)07-004 is enclosed. The LER describes the occurrence of one inoperable shutdown cooling train when two trains were required to be operable by Technical Specifications. This event is reportable in accordance with 10 CFR 50.73(a)(2)(i)(B).
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
'Christopher J. Sc Site Vice President Palisades Nuclear Plant Enclosure (1)
CC Administrator, Region IIl, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC J &2~
ENCLOSURE 1 LER 07-004, Shutdown Cooling Train Inoperable 3 Pages Follow
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 6-30-2007 (6-2004)
Estimated burden per response to comply with this mandatory collection request: 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />.
Reported lessons learned are incorporated into the licensing process and fed back to industry.
LICENSEE EVENT REPORT (LER)
Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-(See reverse for required number of mail to infocollects@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-1 0202, (3150-0066), Office of Management and Budget, Washington, DC 20503.
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If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
FACILITY NAME (1)
DOCKET NUMBER (2)
PAGE (3)
Palisades Nuclear Plant 05000-255 1 of 3
TITLE (4)
Shutdown Cooling Train Inoperable EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
EAL REV FACILITY NAME DOCKETNUMBER MO DAY YEAR YEAR NUMBER NO MO DAY YEAR 04 25 2006 2007
-- 004 00 05 03 2007 FACILITY NAME DOCKETNUMBER OPERATING 6
THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 3: (Check all that apply) (11)
MODE (9) 20.2201 (b) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)
POWER 000 20.2201 (d) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LEVEL (10) 20.2203(a)(1) 50.36(c)(1 )(i)(A) 50.73(a)(2)(iv)(A) 73.71 (a)(4) 20.2203(a)(2)(i) 50.36(c)(1 )(ii)(A) 50.73(a)(2)(v)(A) 73.71 (a)(5) 20.2203(a)(2)(ii) 50.36(c)(2) 50.73(a)(2)(v)(B)
OTHER 20.2203(a)(2)(iii) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C)
Specify in Abstract below or in 20.2203(a)(2)(iv) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(D) 20.2203(a)(2)(v)
X 50.73(a)(2)(i)(B) 50.73(a)(2)(vii) 20.2203(a)(2)(vi) 50.73(a)(2)(i)(C) 50.73(a)(2)(viii)(A) 20.2203(a)(3)(i) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(B)
LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (Include Area Code)
Daniel G. Malone 1
(269) 764-2463 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
MANU-REPORTABLE MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT FACTURER TO EPIX
CAUSE
SYSTEM COMPONENT FA CTURER TO EPIX SUPPLEMENTAL REPORT EXPECTED (14)
EXPECTED MONTH DAY YEAR YES (If yes, complete EXPECTED SUBMISSION DATE).
X NO SUBMISSION(15)
ABSTRACT In the period between April 25, 2006, and April 30, 2006, maintenance was performed on a valve that necessitated the isolation of shutdown cooling heat exchanger (SDCHX) E-60B to facilitate the work.
Isolating one SDCHX was considered to have no effect on the requirement to maintain two operable shutdown cooling (SDC) trains, as it was considered acceptable to credit a single SDCHX to both operable SDC trains, provided that sufficient heat removal capacity could be obtained with one SDCHX.
Subsequently, on March 5, 2007, it was determined that the practice of simultaneously crediting a single SDCHX to both operable SDC trains was not supported by the plant licensing bases, and that a distinct SDCHX is required for each operable SDC train. Therefore, during the time SDCHX E-60B was isolated in April 2006, one train of SDC was inoperable when two trains were required, and action to immediately restore the inoperable SDC train to operable status in accordance with Technical Specification (TS) 3.9.5 Condition A and TS 3.4.8 Condition A was not taken.
This occurrence is reportable in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by the Technical Specifications.U.S. NUCLEAR REGULATORY COMMISSION (1-2001)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)
DOCKET NUMBER (2)
LER NUMBER (6)
PAGE (3)
SEQUENTIAL REVISION YEAR NUMBER NUMBER 2 of 3 Palisades Nuclear Plant 05000-255 2007 004 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
EVENT DESCRIPTION
In the period between April 25, 2006, and April 30, 2006, maintenance was performed on a valve that necessitated the isolation of shutdown cooling heat exchanger (SDCHX) [HX;BP] E-60B to facilitate the work. At the time, the plant was initially in Mode 6, with Technical Specification (TS)
Limiting Condition For Operation (LCO) 3.9.5, "Shutdown Cooling (SDC) and Coolant Circulation -
Low Water Level," being applicable. Later in the period, Mode 5 was entered with TS LCO 3.4.8, "PCS Loops - Mode 5, Loops Not Filled," being applicable. Each TS LCO required two SDC trains to be operable.
Isolating one SDCHX was considered to have no effect on the requirement to maintain two operable SDC trains. The two SDCHXs were considered to operate as a single heat exchanger comprised of two partial capacity units. A single SDCHX was allowed to be credited to both operable SDC trains, provided that sufficient heat removal capacity could be obtained with one SDCHX.
Subsequently, on March 5, 2007, it was determined that the practice of simultaneously crediting a single SDCHX to both operable SDC trains was not supported by the plant licensing bases, and that a distinct SDCHX is required for each operable SDC train. Therefore, during the time SDCHX E-60B was isolated in April 2006, one train of SDC was inoperable when two trains were required, and action to immediately restore the inoperable SDC train to operable status in accordance with TS 3.9.5 Condition A and TS 3.4.8 Condition A was not taken.
This occurrence is reportable in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications.
CAUSE OF THE EVENT
The occurrence resulted from a long-standing interpretation of Custom Technical Specifications, Improved Technical Specifications and the plant's design and licensing bases, which led to the belief that it was permissible to credit one SDCHX to either or both SDC trains if sufficient heat removal capacity existed.
CORRECTIVE ACTIONS
Procedures and design documents will be revised to clarify that a distinct SDCHX is required for each operable SDC train.U.S. NUCLEAR REGULATORY COMMISSION (1-200 1)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1 DOCKET NUMBER (2)
LER NUMBER (6)
PAGE (3)
Y SEQUENTIAL REVISION YEAR NUMBER NUMBER 3 of 3 Palisades Nuclear Plant 05000-255 2007 004 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
SAFETY SIGNIFICANCE
The safety significance of this occurrence is considered to be minimal. The one operating SDCHX was providing sufficient heat removal capacity throughout the period, requiring no active response to fulfill its safety function in either SDC train.
PREVIOUS SIMILAR EVENTS
None