05000327/LER-2006-001-01, Potential Loss of Component Cooling Water to the Seal Water Heat Exchanger During an Appendix R Fire
| ML073040013 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/26/2007 |
| From: | Morris G Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 06-001-01 | |
| Download: ML073040013 (8) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(ix)(A) 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 |
| 3272006001R01 - NRC Website | |
text
Tennessee Valley Authority, Post Office Box 2000, Soddy-Daisy, Tennessee 37384-2000 October 26, 2007 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C. 20555-0001 10 CFR 50.73 Gentlemen:
TENNESSEE VALLEY AUTHORITY -
SEQUOYAH NUCLEAR PLANT (SQN)
UNITS 1 AND 2 -
DOCKET NO.
50-327 AND 50-328 -
FACILITY OPERATING LICENSES DPR-77 AND DPR LICENSEE EVENT REPORT (LER) 50-327/2006-001-01 The enclosed revised report provides additional conditions and corrective actions concerning the potential loss of component cooling water to the seal water heat exchanger during an.Appendix R fire event.
Revisions are annotated by a vertical bar to the right of the text.
This original report was submitted to NRC on April 10, 2006.
The condition was reported, in accordance with 10 CFR 50.73(a)(2)(ii)(B),
as the plant being in an unanalyzed condition that significantly degraded plant safety.
Sincerely, Glenn W. Morris Manager, Site Licensing and Industry Affairs Enclosure Printed on recycled paper
U.S. Nuclear Regulatory Commission Page 2 October 26, 2007 cc (Enclosure):
Mr.
Brendan T.
Moroney, Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop 08G-9a One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2739 INPO Records Center Institute of Nuclear Power Operations 700 Galleria Parkway, SE, Suite 100 Atlanta, Georgia 30339-5957
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 FOIA/Privacy Service Branch (T-5 F52),
LICENSEE EVENT REPORT (LER)
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to infocollects@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to (See reverse for required number of impose an information collection does not display a currently valid OMB digits/characters for each block) control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
7
- 3. PAGE Sequoyah Nuclear Plant (SQN) Unit 1 05000327 1 OF 6
- 4. TITLE Potential Loss of Component Cooling Water to the Seal Water Heat Exchanger During an Appendix R Fire
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED M
TSEQUENTIAL REV FACILITY NAME DOCKET NUMBER NUMBER N
MONTH DAY Unit 2 05000328 I I FACILITY NAME DOCKET NUMBER 02 09 2006 2006 001 01 10 26 2007 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) o 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
[I 50.73(a)(2)(vii) 1 0l 20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
[I 50.73(a)(2)(viii)(A) 0l 20.2203(a)(1)
El 20.2203(a)(4) 0 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B) 0] 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A) 0l 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL El 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A) 0l 50.73(a)(2)(iv)(A)
[I 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
[I 50.36(c)(2) 0l 50.73(a)(2)(v)(A) 0l 73.71(a)(4) 100 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71(a)(5) 100
[
20.2203(a)(2)(v)
[I 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
El OTHER
-- 20.2203(a)(2)(vi)
El 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specify in Abstract below or in (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A)
C.
Additional Information
None D. Safety System Functional Failure:
This event did not result in a safety system functional failure in accordance with 10 CFR 50.73(a)(2)(v).
E.
Loss of Normal Heat Removal Consideration:
This condition did not result in a loss of normal heat removal.
VIII.
COMMITMENTS
None.