05000327/LER-2009-001, Appendix R Unanalyzed Condition Affecting Safety Related Shutdown Boards

Appendix R Unanalyzed Condition Affecting Safety Related Shutdown Boards

ML090900310
Person / Time
Site:	Sequoyah
Issue date:	03/27/2009
From:	Cleary T Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 09-001-00
Download: ML090900310 (9)

LER-2009-001, Appendix R Unanalyzed Condition Affecting Safety Related Shutdown Boards

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
3272009001R00 - NRC Website

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Tennessee Valley Authority Post Office Box 2000 Soddy Daisy, Tennessee 37384-2000 Timothy P. Cleary Site Vice President Sequoyah Nuclear Plant March 27, 2009 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 NOS. 50-327 AND 50-328 - FACILITY OPERATING LICENSE DPR-77 AND DPR LICENSEE EVENT REPORT (LER) 50-327/2009-001-00 The enclosed LER provides details concerning the discovery of a condition where fire safe shutdown equipment might not be available during a postulated Appendix R fire event. This condition could adversely affect Appendix R safe shutdown capability in the event of a fire in two areas in the Auxiliary Building. This condition is reportable in accordance with 10 CFR 50.73(a)(2)(ii)(B), an unanalyzed condition that significantly degraded plant safety.

Sincerely, Timothy

. Cleary' Enclosure cc: See page 2 PIZ printed on recycled paper

U.S. Nuclear Regulatory Commission Page 2 March 27, 2009 Enclosure cc (Enclosure):

INPO Records Center Institute of Nuclear Power Operations 700 Galleria Parkway, SE, Suite 100 Atlanta, Georgia 30339-5957 Mr. Tracy J. Orf, Project Manager U.S. Nuclear Regulatory Commission Mail Stop 08G-9a One White Flint North 11555 Rockville Pike Rockville,,Maryland 20852-2739 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379

U.S. Nuclear Regulatory Commission Page 3 March 27, 2009 JWP:NRT:SKD Enclosure cc (Enclosure):

G. Arent, EQB 1 B-WBN P. M. Billingsley, OPS-4C-SQN (For Web posting)

C. R. Church, POB 2B-SQN T. P. Cleary, OPS 4A-SQN L. D. Clift, OPS 4G-SQN T. Coutu, LP 3R-C D. E. Jernigan, LP 3R-C K. R. Jones, OPS 4A-SQN M. J. Lorek, LP 3R-C L. E. Nicholson, BR 4X-C NSRB Support, BR 4X-C M. A. Purcell, BR 4X-C P. D. Swafford, LP 3R-C L. E. Thibault, LP 3R-C S. A. Vance, ET 10A-K E. J. Vigluicci, ET 1OA-K WBN Site Licensing Files, ADM 1L-WBN EDMS, WT CA-K I:licensellers/2009/LER 1-2009-001.doc

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 08/31/2010,

(9-2007)

, the NRC may not conduct or sponsor, and a pereon is not required to respond to, the information digits/characters for each block) collection.

3. PAGE Sequoyah Nuclear Plant Unit 1 05000327 1 of 6

4. TITLE:

Appendix R Una'alyzed Condition Affecting Safety Related Shutdown Boards

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED MNH DY YA YER SEQUENTIALI REV MOT A

ER FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SUMEN R

EN MONTH DAY YEAR Sequoyah Nuclear Plant Unit 2 05000328 N B FACILITY NAME DOCKETNUMBER 1

28 2009 2009 001 00 3

27 2009

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)

El 20.2201(b)

El 20.2203(a)(3)(i)

El 50.73(a)(2)(i)(C)

[1 50.73(a)(2)(vii)

El 20.2201(d)

[] 20.2203(a)(3)(ii)

[E 50.73(a)(2)(ii)(A)

El 50.73(a)(2)(viii)(A)

[E 20.2203(a)(1)

El 20.2203(a)(4) 0 50.73(a)(2)(ii)(B)

El 50.73(a)(2)(viii)(B)

[E 20.2203(a)(2)(i)

[]

50.36(c)(1)(i)(A)

[E 50.73(a)(2)(iii)

[]

50.73(a)(2)(ix)(A)

10. POWER LEVEL El 20.2203(a)(2)(ii)

[E 50.36(c)(1)(ii)(A)

E] 50.73(a)(2)(iv)(A)

[E 50.73(a)(2)(x)

El 20.2203(a)(2)(iii)

[_] 50.36(c)(2)

El 50.73(a)(2)(v)(A)

[1 73.71(a)(4)

El 20.2203(a)(2)(iv)

El 50.46(a)(3)(ii)

El 50.73(a)(2)(v)(B)

El 73.71 (a)(5) 100 [E

20.2203(a)(2)(v)

El 50.73(a)(2)(i)(A)

[E 50.73(a)(2)(v)(C)

El OTHER El 20.2203(a)(2)(vi)

El 50.73(a)(2)(i)(B)

[] 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)

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.

Unplanned Scram with Complications:

This condition did not result in an unplanned scram with complications.

VIII.

COMMITMENTS

None.

1