05000247/LER-2006-002, Re Technical Specification Prohibited Condition for Two Inoperable Channels of PAM Instrumentation

From kanterella
(Redirected from 05000247/LER-2006-002)
Jump to navigation Jump to search
Re Technical Specification Prohibited Condition for Two Inoperable Channels of PAM Instrumentation
ML062720147
Person / Time
Site: Indian Point 
Issue date: 09/22/2006
From: Dacimo F
Entergy Nuclear Northeast
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-06-093 LER 06-002-00
Download: ML062720147 (6)


LER-2006-002, Re Technical Specification Prohibited Condition for Two Inoperable Channels of PAM Instrumentation
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
2472006002R00 - NRC Website

text

Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 n

tBuchanan, NY 10511-0249 Tel 914 734 6700 Fred Daclmo Site Vice President Administration September 22, 2006 Re: Indian Point Unit No. 2 Docket No. 50-247 NL-06-093 Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop O-PI-17 Washington, DC 20555-0001

Subject:

Licensee Event Report 2006-002-00, "Technical Specification Prohibited Condition for Two Inoperable Channels of PAM Instrumentation".

Dear Sir or Madam:

The attached Licensee Event Report (LER) 2006-002-00 is submitted in accordance with 10 CFR 50.73. The enclosed LER identifies an event where the plant was operated in a condition prohibited by Technical Specifications, which is reportable under 10 CFR 50.73(a)(2)(i)(B). This condition has been recorded in the Entergy corrective action program as Condition Report CR-IP2-2006-04402.

There are no new commitments identified in this letter. Should you or your staff have any questions regarding this submittal, please contact Mr. Patric W. Conroy, Manager, Licensing, at (914) 734-6668.

Very truly yours, Fred R. Dacimo Site Vice President Indian Point Energy Center cc: next page J1IZ2-

Docket No. 50-247 NL-06-093 Page 2 of 2 Attachment: LER-2006-002-00 cc:

Mr. Samuel J. Collins, Regional Administrator, Region I IPEC NRC Resident Inspector's Office, Indian Point Unit 2 Mr. Paul Eddy, New York State Department of Public Service INPO Record Center

Abstract

On July 24, 2006, Post Accident Monitoring (PAM) instrument LT-3300 was determined to be inoperable. This determination was made when reviewing data taken during a July 22, 2006 containment pressure relief. The containment level transmitter LT-3300, which indicates sump water level, unexpectedly responded to changes in containment pressure. It was subsequently determined that LT-3300 had been inoperable since May, 16,.2006, the date Unit 2 exceeded Mode 3 upon startup from the 2R17 refuel outage.

The instrument, LT 3300, was one of three containment water level (containment sump) instruments required to be operable in accordance with Technical Specification (TS) 3.3.3. One other required PAM instrument, LT-940, had previously been declared inoperable since May 16, 2006. Therefore, two required channels had been inoperable since May, 16, 2006. This time period exceeded the TS 3.3.3, Condition C, 7 day completion time. In addition, entry into Mode 3 on May 16, 2006, and subsequent return to full power, was made with these two channels inoperable without meeting the requirements of LCO 3.0.4.

The apparent cause of the failure of LT-3300 is indeterminate at this time due to instrument inaccessibility during plant operation. Corrective actions are to include troubleshooting and replacement or repair of LT-3300 during 2R18 refuel outage. The cause of LT-3300 inoperability will be further evaluated at that time.

This event had no effect on public health and safety.

(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)

EVENT ANALYSIS

The event is reportable under 10CFR50.73(a) (2) (i) (B).

The licensee shall report any event or condition which was prohibited by the plant TS.

This event meets the reporting criteria because two containment water level (containment sump) instruments required to be operable in accordance with TS 3.3.3 were determined to be inoperable for greater than the TS allowed completion time of 7 days. The requirements of TS 3.3.3, Condition C, were not met from May 16, 2006, until LT-940 was removed from the TS on July 28, 2006 via an emergency TS amendment (TS Amendment No. 249).

The amended TS allow for continued operation with one of two channels inoperable. In addition, entry into Mode 3 on May 16, 2006, and subsequent return to full power, was made with these two channels inoperable without meeting the requirements of LCO 3.0.4.

PAST SIMILAR EVENTS A review of the past two years of Licensee Event Reports (LERs) was performed for events that involved inoperable components that exceeded the TS allowed completion time and identified two issues when AOTs were exceeded.

LER 2005-001 described an event where an auxiliary component cooling water pump was determined to be inoperable due to an improperly serviced discharge check valve.

LER 2005-002 described an event where one train of ECCS was inoperable due to gas intrusion from a leaking check valve.

SAFETY SIGNIFICANCE

This event had no effect on the health and safety of the public.

There were no actual safety consequences for the event because there were no accidents or transients requiring the use of these instruments.

There were no significant potential safety consequences of this event under reasonable and credible alternative conditions. The TS in force at the time of the event specified three required channels (LT-940, LT-941 and LT-3300) for the containment sump water level instrumentation.

Subsequent to the event a TS amendment was approved that specifies two required channels (LT-941 and LT-3300).

The amended TS allows for continued operation with one of these two channels inoperable provided a report is submitted to the NRC pursuant to TS 5.6.6. This report was provided on August 7, 2006 (NL-06-083).

The amended TS represents a safe operating condition and mirrors the configuration of the plant covered by this event report (LT-941 operable, LT-3300 inoperable).

Therefore, the plant was in a safe operating condition during the event.