BSEP 03-0130, Technical Specification 5.6.6 Post Accident Monitoring (PAM) Instrumentation Report
| ML032460849 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/28/2003 |
| From: | Noll W Progress Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BSEP 03-0130 | |
| Download: ML032460849 (3) | |
Text
Cjj Progress Energy August 28, 2003 10 CFR 50.4 SERIAL: BSEP 03-0130 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 1 DOCKET NO. 50-325/LICENSE NO. DPR-71 TECHNICAL SPECIFICATION 5.6.6 POST ACCIDENT MONITORING (PAM)
INSTRUMENTATION REPORT Ladies and Gentlemen:
Introduction In accordance with Technical Specification (TS) 5.6.6, "Post Accident Monitoring (PAM)
Instrumentation Report," this letter provides notification of PAM instrumentation that was not restored to OPERABLE status within 30 days as required by TS Limiting Condition for Operation (LCO) 3.3.3.1, "Post Accident Monitoring (PAM) Instrumentation."
On August 19, 2003, it was determined that two electrical connectors on the back of temperature recorders 1-CAC-TR-4426-2A and 1-CAC-TR-4426-2B (i.e., four connectors total) were not fully seated and that the condition resulted in the equipment not meeting the seismic requirements for Regulatory Guide 1.97 Post Accident Monitoring instrumentation functions. The equipment was declared inoperable although the equipment continued to provide indication functions. The appropriate LCOs and Technical Requirements Manual Specification (TRMS) Conditions were entered as follows:
1-CAC-TR-4426-2A - TS LCO 3.3.3.1, Condition A, for TS Function 4 "Suppression Chamber Water Temperature," and TS Function 7 "Drywell Temperature" (Restore required channel to operable status within 30 days).
TRMS 3.4, Accident Monitoring Instrumentation, Condition A, for Function 1 "Suppression Chamber Atmosphere Temperature" (Restore required channel to operable status within 31 days).
TRMS 3.8, Suppression Chamber Water Temperature, Condition A, (Restore channel to operable status within 7 days).
Progress Energy Carolinas, Inc.
Brunswick Nuclear Plant P.O.
Box 10429 Southport, NC 28461 4¢
,O
Document Control Desk BSEP 03-0130 / Page 2 1-CAC-TR-4426-2B - TS LCO 3.3.3.1, Condition A, for TS Function 7 "Drywell Temperature" (Restore required channel to operable status within 30 days).
Evaluation of the equipment condition and previous maintenance activities provided firm evidence that the associated instrumentation functions were inoperable since July 15, 2003.
Based on this information, for reportability purposes, the TS LCO 3.3.3.1, Condition A completion time of 30 days to restore the required channels to operable status expired on August 14, 2003. TS LCO 3.3.3.1, Condition B states that if the Required Action and associated Completion Time of Condition A are not met, initiate action in accordance with Specification 5.6.6 immediately. Specification 5.6.6 states that when a report is required by Condition B of LCO 3.3.3.1, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrument channels of the Function to operable status. The required information is addressed below.
Preplanned Alternate Method of Monitoring This equipment was returned to operable status on August 27, 2003, so no preplanned alternate method of monitoring is required at this time.
Cause of the Inoperability Instrumentation and Controls technicians initiated a Nuclear Condition Report, Action Request (AR) 99321 on July 20, 2003, due to the difficulty they experienced installing the electrical connectors on the recorders. On August 19, 2003, the investigator of the AR performed a visual inspection of the recorders and noted that the connectors did not appear properly seated. Subsequent inspection by the seismic equipment design engineer confirmed that the installation was not seismically qualified. The control room operators were notified and AR 102404102404was initiated.
The inability to properly seat the connectors was due to a deformation of the connector clips, introduced during connector installation, such that the clips interfered with the proper insertion and subsequent holding of the connector in the receptacle. Further details of the investigations and corrective actions will be documented in AR 99321 and AR 102404102404
Plans for Restoring the Instrumentation to Operable Status The subject connectors were replaced on recorders 1-CAC-TR-4426-2A and 2B and the wires trained to allow proper installation of the connectors. The equipment was declared operable and the applicable LCOsITRMs were exited on August 27, 2003.
Document Control Desk BSEP 03-0130 / Page 3 No commitments are identified in this report. Please refer any questions regarding this submittal to Mr. Edward T. O'Neil, Manager - Support Services, at (910) 457-3512.
Sincerely, W. G Noll Plant General Manager Brunswick Steam Electric Plant CRE/cre cc: U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Luis A. Reyes, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Eugene M. DiPaolo, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)
ATTN: Ms. Brenda L. Mozafari (Mail Stop OWFN 8G9) 11555 Rockville Pike Rockville, MD 20852-2738 Ms. Jo A. Sanford Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510