05000454/LER-2008-001, Technical Specification Noncompliance of Containment Sump Monitor Due to Improper Installation During Original Construction

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Technical Specification Noncompliance of Containment Sump Monitor Due to Improper Installation During Original Construction
ML081650453
Person / Time
Site: Byron Constellation icon.png
Issue date: 06/13/2008
From: Hoots D
Exelon Corp, Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BYRON 2008-0061 LER-08-001-00
Download: ML081650453 (5)


LER-2008-001, Technical Specification Noncompliance of Containment Sump Monitor Due to Improper Installation During Original Construction
Event date:
Report date:
Reporting criterion: 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)(vii), Common Cause Inoperability

10 CFR 50.73(a)(2)(viii)(A)

10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition

10 CFR 50.73(a)(2)(iii)

10 CFR 50.73(a)(2)(ix)(A)

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)

10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown

10 CFR 50.73(a)(2)(v), Loss of Safety Function
4542008001R00 - NRC Website

text

Nuclear June 13,2008 LTR: BY RON 2008-0061 File:

2.01.0700 1.10.0101 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Byron Station, Unit 1 Facility Operating License No. NPF-37 NRC Docket No. STN 50-454

Subject:

Licensee Event Report (LER) 454-2008-001 -00, "Technical Specification Non-compliance of Containment Sump Monitor Due to Improper Installation During Original Construction" Enclosed is an LER involving the discovery of a long term inoperable condition on the Unit 1 Containment Sump Monitor. This event is reportable to the NRC accordance with10 CFR 50.73 (a)(2)(i)(B).

There are no regulatory commitments contained in this report. Should you have any questions concerning this matter, please contact Mr. William Grundmann, Regulatory Assurance Manager, at (81 5) 234-5441, extension 2800.

Site Vice President Byron Station

Attachment:

LER 454-2008-001 -00

NRC FORM 366 (9-2007)

PRINTED ON RECYCLED PAPER NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (9-2007)

LICENSEE EVENT REPORT (LER)

(See reverse for required number of digitsfcharacters for each block)

1. FACILITY NAME Byron Station, Unit 1 APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08!31/2010

, the NRC may not conduct or sponsor, and a person is not required to respond to, the infnrmntinn rnilwtinn

2. DOCKET NUMBER
13. PAGE 05000454 I

1 of 4

4. TITLE Technical Specification Non-Compliance of Containment Sump Monitor Due to Improper Installation During Oriainal construction
5. EVENT DATE MONTH 03
6. LER NUMBER
12. LICENSEE CONTACT FOR THIS LER
11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 9: (Check all that apply) 20.2201(b)
  • 20.2203(a)(3)(i) 50.73(a)(2)(i)(C)
  • 50.73(a)(2)(vii) 20.2201(d)

C) 20.2203(a)(3)(ii) 50,73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) rn 20.2203(a)(l)

[7 20.2203(a)(4) rn 50.73(a)(2)(ii)(B) rn 50,73(a)(2)(viii)(B)

[7 20.2203(a)(2) (i) rn 50.36(~)(1

)(i)(A) 50.73(a)(2)(iii)

[7 50.73(a)(2)(ix)(A) 1 20.2203(a)(2)(ii) 50,36(c)(l)(ii)(A) rn 50,73(a)(2)(iv)(A) 50.73(a)(2)(x)

C] 20.2203(a)(2)(iii) 50.36(~)(2)

[7 50.73(a)(2)(v)(A)

[7 73,71(a)(4)

[7 20.2203(a)(2)(iv)

[7 50.46(a)(3)(ii) 50.73(a)(2)(~)(B)

[7 73.71 (a)(5) 20.2203(a)(2)(v) rn 50.73(a)(2)(i)(A) rn 50.73(a)(2)(v)(C)

OTHER 20.2203(a)(2)(vi)

(XI 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)

Specify in Abstract below or in 1

until the actual leak was at two gpm. Based on engineering judgment, this is still considered small enough for Operators to take appropriate actions to place Unit 1 in a safe condition (i.e., Mode 5)

The TS required 1 PRO1 1A was capable of detecting a RCS leak of one gpm within an hour. During the brief periods of time when both 1 RF008 and 1 PRO1 1 A were inoperable, Operators had several additional means to identify RCS unidentified leakage. These include the RCS Volume Control Tank level indicators, post accident containment sump [IP] level instruments, containment pressure and temperature indicators, and Pressurizer [AB] Level indicators.

E. Corrective Actions

The 1 RF008 penetration openings were blocked such that RCS leakage could not enter the sump via the sump cover.

The design drawings for the Unit 1 and Unit 2 RF008 will be revised to indicate the as-built installation.

The Engineering lessons learned from the missed opportunities in identifying this condition will be communicated to the Engineering staff.

F. Previous Occurrences

Issue Report (IR) 113088 dated June 24, 2002, describes incorrect installation issue with the RF008 instrumentation.

lR 5221 60 dated August 21, 2006, describes the removal of the six inch lio at the bottom of the ECCS