05000302/LER-2005-001, Regarding Design Change Creates Engineered Safeguards Bus Protective Relay Scheme Single Failure Vulnerability
| ML050910115 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/23/2005 |
| From: | Franke J Progress Energy Florida |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 3F0305-02 LER 05-001-00 | |
| Download: ML050910115 (15) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(ix)(A) 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)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 3022005001R00 - NRC Website | |
text
a Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Ref: 10 CFR 50.73 March 23, 2005 3F0305-02 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
LICENSEE EVENT REPORT 50-302/2005-001-00
Dear Sir:
Please find enclosed Licensee Event Report (LER) 50-302/2005-001-00. The LER discusses single failure vulnerability of 4160 volt Engineered Safeguards Bus protective relay schemes created by inadequate design changes implemented in 1990 and 1993. This report is being submitted pursuant to 1 OCFR50.73(a)(2)(ii)(B) and 1 OCFR50.73(a)(2)(ix)(A).
No new regulatory commitments are made in this letter.
If you have any questions regarding this submittal, please contact Mr. Sid Powell, Supervisor, Licensing and Regulatory Programs at (352) 563-4883.
ly, on A. Franke Plant General Manager Crystal River Nuclear Plant JAF/dwh Enclosure xc:
Regional Administrator, Region II Senior Resident Inspector NRR Project Manager Progress Energy Florida, Inc.
Crystal River Nuclear Plant 15760 W. Powerline Street Crystal River, FL 34428
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
Estimated burden per response to comply with this mandatory collection request: 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the Records and FOlNAPrivacy Service Branch (T-5 F52), U.S.
LICENSEE EVENT REPORT (LER)
Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet e-mail to infocollects~nragov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEB-0202, (3150-0104), Office of Management and (See reverse for required number of Budget, Washington, DthC 2050N3.FICa means use to Imp e
rmthon digits/characters for each block) may not conduct or sponsor, and a person is not required to respond to, the digis/caracersinformation collection.
- 3. PAGE CRYSTAL RIVER UNIT 3 05000302 1 OF 14
- 4. TITLE Design Change Creates Engineered Safeguards Bus Protective Relay Scheme Single Failure Vulnerability
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTIAL REV MNH DY YA FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO.
R MONTH DAY YEAR NA 05000 FACILITY NAME DOCKET NUMBER 01 27 2005 2005 - 001 -
00 03 23 2005 N/A 05000
- 9. OPERATING MODE 11.THIS REPORTISSUBMITTED PURSUANTTO THEREQUIREMENTS OFIOCFR§: (Check allthatapply) o 20.2201(b)
E 20.2203(a)(3)(i) 0 50.73(a)(2)(i)(C)
D 50.73(a)(2)(vii) 1 l 20.2201(d)
E 20.2203(a)(3)(ii)
D 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
Ea 20.2203(a)(1) 0 20.2203(a)(4) 0 50.73(a)(2)(ii)(B) 0 50.73(a)(2)(viii)(B) 0_O 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
D] 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL E
20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A) al 50.73(a)(2)(x) o 20.2203(a)(2)(iii)
El 50.36(c)(2)
Dl 50.73(a)(2)(v)(A)
El 73.71 (a)(4) ol 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(B) 0 73.71(a)(5) 100%
El 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
[I OTHER E0 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B)
E 50.73(a)(2)(v)(D)
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ATTACHMENT 2 LIST OF COMMITMENTS The following table identifies those actions committed to by PEF in this document. Any other actions discussed in the submittal represent intended or planned actions by PEF. They are described for the NRC's information and are not regulatory commitments. Please notify the Supervisor, Licensing & Regulatory Programs, of any questions regarding this document or any associated regulatory commitments.
RESPONSE
COMMITMENT
DUE DATE SECTION No regulatory commitments are being made in this submittal.