05000244/LER-2003-003, R. E. Ginna Regarding Containment Sump as-found Condition Not in Accordance with Design Requirements
| ML033210144 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/10/2003 |
| From: | Mecredy R Rochester Gas & Electric Corp |
| To: | Clark R Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 03-003-00 | |
| Download: ML033210144 (14) | |
| 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)(iii) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(v), Loss of Safety Function |
| 2442003003R00 - NRC Website | |
text
Always at Your Service November 10, 2003 Mr. Robert L. Clark Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C. 20555-0001 Robert C. Mecredy Vice President Nuclear Operations
Subject:
LER 2003-003, Containment Sump As-found Condition not in Accordance With Design Requirements R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Clark:
The attached License Event Report (LER) is submitted in accordance with NUREG-1022, License Event Reporting System 10 CFR 50.72 and 50.73, as a voluntary report of a condition of generic interest or concern.
This event has in no way affected the public's health and safety.
Very Robert C. Mecredy An equal opportunity employer 89 East Avenue I Rochester, NY 14649 tel (585) 546-2700 www.rge.com I OODZiW*
An Energy East Company
.1
xc:
Mr. Robert Clark (Mail Stop 0-8-C2)
Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852 Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector
NRC'FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 EXPIRES 7-31-2004 (7.2001)
COMMISSION
, the NRC
- 3. PAGE R. E. Ginna Nuclear Power Plant 05000244 1 OF 12
- 4. TITLE Containment Sump As-found Condition not in Accordance with Design Requirements
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MO DAY YEAR YEAR SEUENAL R MO DAY Y
FACILITY NAME DOCKET NUMBER MO D
AYYE RY EANUMBER NO DAY YEAR 05000 09 1 8 2003 2003 -
003 -
00 111 10 2003 FACILITY NAME DOCKET NUMBER
- 9. OPERATING
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
MODE 5
20.2201 (b) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)
- 10. POWER 0
20.2201 (d) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LEVEL 000 20.2203(a)(1) 50.36(c)(1)(i)(A) 50.73(a)(2)(iv)(A) 73.71 (a)(4) 20.2203(a)(2)(i) 50.36(c)(1)(ii)(A) 50.73(a)(2)(v)(A) 73.71 (a)(5) 20.2203(a)(2)(ii) 50.36(c)(2) 50.73(a)(2)(v)(B)
X OTHER
-,.E i<
_ 0232)i)_
.46(a)(3)ii) 50.73(a)(2)(v)(C)
Specify in Abstract below or In 20.2203(a)(2)(iii) 50.46(a)(3)(ii) 073a2)vC)
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Figure 3 ELEVATION B-B Containment Sump B Inner Screen Support Frame