05000387/LER-2010-001, Regarding Secondary Containment Bypass Leakage Exceeded

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Regarding Secondary Containment Bypass Leakage Exceeded
ML101450395
Person / Time
Site: Susquehanna Talen Energy icon.png
Issue date: 05/14/2010
From: Rausch T
Susquehanna
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-6619 LER 10-001-00
Download: ML101450395 (4)


LER-2010-001, Regarding Secondary Containment Bypass Leakage Exceeded
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded

10 CFR 50.73(a)(2)(i)

10 CFR 50.73(a)(2)(vii), Common Cause Inoperability

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)(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
3872010001R00 - NRC Website

text

Timothy S. Rausch Sr. Vice President & Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3445 Fax 570.542.1504 tsrausch@pplweb.com pp1 '4%

49A 14 2K1 U. S. Nuclear Regu'latoiy Ccmiirnission Attn: Ddcuimefnt C6ontro6 Desk`

Mail Stop OP 117`

Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-387/2010-001-00 LICENSENO.1NPF-14 PLA;6619 Docket No 50-387 Attached is Licensee Event Report (LER) 50-387/2010-001-00. This event was determined to be reportable under 10 CFR 50.73(a)(2)(ii)(A) in that the secondary containment bypass leakage limit for Susquehanna SES Unit 1 was exceeded during regularly scheduled Local Leak Rate Tesfing.

There were no actual consequences to the health and safety of the public as a result of this event.

Officer Attachment Copy:

NRC Region I Mr. P. Fififiey, NRC Sr. Resident Inspector Mr. R'.V. Giizman, NRC Si.r. Project Manager Mr. R. R. Janati, DEP/BRP

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ýJ' NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2010 (9-2007)

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

3. PAGE Susquehanna Steam Electric Station Unit 1 05000387 1 OF3
4. TITLE Unit 1 Secondary Containment Bypass Leakage Exceeded
5. EVENT DATE
6. LER NUMBER
7. REPORT DATE
8. OTHER FACILITIES INVOLVED

.SEQUENTIALI I

FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEUMENTA REV MONTH DAY YEAR 05000 T

FACILITY NAME DOCKET NUMBER 03 15 2010 2010 - 001 -

00 05000

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

[1 20.2201(b)

El 20.2203(a)(3)(i)

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

El 50.73(a)(2)(vii) 5 [1 20.2201(d)

El 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(A)

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

El 20.2203(a)(1)

El 20.2203(a)(4)

[I 50.73(a)(2)(ii)(B)

[I 50.73(a)(2)(viii)(B)

__ E 20.2203(a)(2)(i)

[I 50.36(c)(1)(i)(A)

El 50.73(a)(2)(iii)

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

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

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

El 50.73(a)(2)(iv)(A)

El 50.73(a)(2)(x)

[j 20.2203(a)(2)(iii)

E]; 50.36(c)(2)

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

El 73.71(a)(4)

[I 20.2203(a)(2)(iv)

El 50.46(a)(3)(ii)

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

El 73.71(a)(5) 0%

[E 20.2203(a)(2)(v)

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

El 50.73(a)(2)(v)(C)

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

E] 50.73(a)(2)(i)(B)

El 50.73(a)(2)(v)(D)

Specify in Abstract below or in

CORRECTIVE ACTIONS

The following corrective action has been completed:

Valve maintenance was performed and the as-left SCBL value meets the Technical Specifications limit.

The following corrective action is planned:

Evaluate design of the Emergency Core Cooling Systems (ECCS) SCBL penetrations including valve design and configuration to determine methods to reduce the leakage.

Perform a training needs analysis for maintenance personnel for valve rework on specific valves.

Evaluate and submit, if appropriate, a Technical Specification amendment to raise the SCBL limit.

No regulatory commitments are associated with this report.

ADDITIONAL INFORMATION

Failed Component Information:

Component:

HV151F016B; 12 inch globe valve Model:

W8522332B Manufacturer:

Anchor Darling Valve Co.

Previous Similar Events

LER 96-002-00, Docket No. 387/License No. NPF-14 LER 96-011-00, Docket No. 387/License No. NPF-14 LER 99-002-00, Docket No. 388/License No. NPF-22 LER 01-003-00, Docket No. 388/License No. NPF-22 LER 07-001-00, Docket No. 388/License No. NPF-22