05000325/LER-2005-003, Regarding Inappropriate Use of Technical Specification 3.0.5 During Control Rod Manipulations
| ML051790199 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/16/2005 |
| From: | Hinds D Progress Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BSEP 05-0069 LER 05-003-00 | |
| Download: ML051790199 (8) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 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)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 3252005003R00 - NRC Website | |
text
Progress Energy JUN 1 6 2005 SERIAL: BSEP 05-0069 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Brunswick Steam Electric Plant, Unit No. 1 Docket No. 50-325/License No. DPR-71 Licensee Event Report 1-2005-003 Ladies and Gentlemen:
In accordance with the Code of Federal Regulations, Title 10, Part 50.73, Carolina Power & Light Company, now doing business as Progress Energy Carolinas, Inc., submits the enclosed Licensee Event Report. This report fulfills the requirement for a written report within sixty (60) days of a reportable occurrence.
Please refer any questions regarding this submittal to Mr. Edward T. O'Neil, Manager-Support Services, at (910) 457-3512.
Sincerely, David Hinds Plant General Manager Brunswick Steam Electric Plant WRM/wrm Enclosure: Licensee Event Report Progress Energy Carolinas. Inc.
Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461
Document Control Desk BSEP 05-0069 / Page 2 cc (with enclosure):
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
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 06130/2007 (6-2004)
Estilated btiden per response to corrpiy weih his rmandatlry binorunibon rcection reqiest 50 hmm Repoled lessons learned am incuorpraed Im to ie censing prtceiss and fed back to LICENSEEEVENTREPORT(LER) a (T-F2) U. Near Reatory Csr WasingW DC 20555-0001. or by (See reverse for required number of Internet h
- - rral to intoc:0ectsonrc9ov, and lo tie Desk Otecer, Otfce d Honoeition aid digits/characters for each block)
RegtJatory Mairs, NE0OB1020 (3150-0104), Orfe ot Maianednt and Bude Wastirvton DC 205.
I a rneans used to irpose an inomrrnatin soedwn does not dsplay a clrareny vald OMB crlr,urmter, tie NRC may rot cwnkct or spa sor, and a person is not reclired to respond to the kitomn aon colecton.
- 3. PAGE Brunswick Steam Electric Plant (BSEP), Unit 1 05000325 1 OF 6
- 4. TITLE Inappropriate Use of Technical Specification 3.0.5 During Control Rod Manipulations
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY l YEAR YEAR I SEUENTIAL REV MONTH DAY YEAR FACILRY NAME DOCKET NUMBER NUMBER NO 105000 04 20 205 205 2005 FACIUTY NAME DOCKETNUMBER
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBM7TED PURSUANT TOTHE REQUIREMENTS OF 10 CFR §: (Check one or more) 5 0 20.2201 (b) 0 20.2203(a)(3)(i) 0 50.73(a)(2)(i)(C) 0 50.73(a)(2)(vii) o 20.2201 (d) 0 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A) o 20.2203(a)(1) 0 20.2203(a)(4) 0 50.73(a)(2)(ii)(B) 0 50.73(a)(2)(viii)(B)
Dl 20.2203(a)(2)(i) 0 50.36(c)(1)(i)(A) 0 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 0 20.2203(a)(2)(ii) 0 50.36(c)(1)(ii)(A)
E 50.73(a)(2fiv)(A) 0 50.73(a)(2)(x) 000 0 20.2203(a)(2)(iii) 0 50.36(c)(2) 0 50.73(a)(2)(v)(A) 0 73.71(a)(4) o 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(B)
D 73.71 (a)(5)
O 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(C)
OTHER El 20.2203(a)(2)(vi)
El 50.73(a)(2)(v)(D)
Spo n Fobstra below
- 12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Include Area Code)
William R. Murray, Lead Licensing Engineer 1(910) 457-2842CAS SYTE COPNN MANU-REPORTABLE CAUSEMANLI-REPORTABLE FACTURER TO EPIX FACTURER TO EPIX
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MO DAY YEAR SUBMISSION YES (If yes, complete EXPECTED SUBMISSION DATE).
X NO DATE ABSTRACT (Umit to 1400 spaces, I.e., approximately 15 single-spaced typewritten lines)
On April 20, 2005, Unit 1 was in Mode 5 for a fuel bundle replacement outage. Following completion of maintenance to the position indicating probe (PIP) for control rod 46-15, a PIP position simulator, being used to provide full-in indication to the one-rod-out interlock, was not removed prior to performing single control rod subcriticality testing and operability testing for the control rod. Plant operators determined that performance of single control rod subcriticality testing was a prerequisite for performing operability testing of the control rod. Operators incorrectly used Technical Specification (TS) 3.0.5 to return control rod 46-15 to service before beginning the single control rod subcriticality testing. Following single control rod subcriticality testing for two control rods and encountering problems with the operability testing for control rod 46-15, operators continued to use TS 3.0.5 while performing testing of another control rod. This resulted in a failure to comply with Technical Specification required actions. To prevent recurrence of this event, training on the proper use of TS 3.0.5 will be provided to licensed operators. In addition, enhancements are planned to the plant procedures which govern the installation and removal of PIP jumpers and to plant procedures to prohibit use of the PIP position simulator as a jumper for the one-rod-out interlock.
NRC FORM 366 (6-2004)
(If more space Is required, use additional copies of (If more space Is required, use additional copies of (if more space Is required, use additionalcopies of (If more space Is required, use additional copies of (If more space Is required, use additional copies of NRC Form 366A) (17)
COMMWTMENTS No regulatory commitments are contained in this report. Those actions discussed in this submittal will be implemented in accordance with corrective action program requirements.