BSEP 04-0077, Technical Specification 5.6.6 Post Accident Monitoring Instrumentation Report
| ML042030258 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 07/15/2004 |
| From: | O'Neil E Carolina Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BSEP 04-0077 | |
| Download: ML042030258 (2) | |
Text
- s CCP&L APmgressm Il Crfnlpa 10 CFR 50.4 JUL 1 5 2004 SERIAL: BSEP 04-0077 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:
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 in Condition A of TS Limiting Condition for Operation (LCO) 3.3.3.1, "Post Accident Monitoring (PAM)
Instrumentation."
On June 12, 2004, main steam line isolation valve position indicating switch I-B21-F028D-LS-2 failed. This switch provides a Unit 1 input to Function 8, "PCIV Position," of Table 3.3.3.1-1, "Post Accident Monitoring Instrumentation." Condition A of TS LCO 3.3.3.1 was entered, with a Required Action to restore the required channel to OPERABLE status within 30 days. The cause of the failed position indicating switch cannot be conclusively determined with the unit at power operation since the switch is located within the main steam tunnel where personnel access is not allowed due to dose and high temperature conditions. The failed switch will be repaired or replaced, as necessary, at the next available opportunity, but not to exceed the next Unit 1 refuel outage in 2006.
Until the position indicating switch 1-B21-F028D-LS-2 can be repaired, a daily check is being performed of the control logic relays which receive a signal from the Reactor Protection System (RPS) related main steam line isolation valve position indicating switches, 1-B21-F028D-LS-3 and 1-B21-F028D-LS-6. Use of this alternate monitoring method is considered adequate for validating the position of the affected main steam line isolation valve since the setpoints for the RPS related switches and the 1-B21-F028D-LS-2 are identical. In addition, main steam flow indication checks are performed by Operations staff twice per shift during control board walkdowns.
Brunswick Nuclear Plant P.O.
Box 10429 Southport, NC 28461
At Document Control Desk BSEP 04-0077 / Page 2 No commitments are identified in this report. Please refer any questions regarding this submittal to Mr. Leonard R. Beller, Supervisor-Licensing, at (910) 457-2073.
Sincerely, Edward T. O'Neil Manager - Support Services Brunswick Steam Electric Plant SFT/sft cc: U. S. Nuclear Regulatory Commission, Region II ATTN: Dr. William D. Travers, 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