05000387/LER-2006-002, Regarding Missed Technical Specification Surveillance Requirement

Regarding Missed Technical Specification Surveillance Requirement

ML061440460
Person / Time
Site:	Susquehanna
Issue date:	05/15/2006
From:	Saccone R Susquehanna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-6043 LER 06-002-00
Download: ML061440460 (5)

LER-2006-002, Regarding Missed Technical Specification Surveillance Requirement

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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) 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
3872006002R00 - NRC Website

text

r-d, Robert A. Saccone Vice President - Nuclear Operations PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3698 Fax 570.542.1504 rasaccone@pplweb.com A

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%m TM MAY 15 2006 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop OPI-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT, 50-387/2006-002-00 LICENSE NO. NPF-14 PLA-6043 Docket No. 50-387 Attached is Licensee Event Report 50-387/2006-002-00. This event was determined to be reportable under 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by the plant's Technical Specifications.

On March 23, 2006 during a refuel outage it was discovered that a required pre-modification Local Leak Rate test (LLRT) on a containment penetration had not been performed as required by the station's containment leakage rate program. This constituted a missed surveillance in accordance with the plant's Technical Specification surveillance requirement SR 3.6.1.1.1. Because the original configuration no longer existed, the containment leakage rate prior to the modification could not be quantified.

This event did not result in any actual adverse consequences to the health and safety of the public.

No commitments are associated with this LER.

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ý Vice President - Nuclear Operations Attachment

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,-.J C Document Control Desk PLA-6043 cc:

Mr. S. Collins Regional Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Alan Blamey Sr. Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 35 Berwick, PA 18603-0035 Mr. R. Osborne Allegheny Electric Cooperative P. 0. Box 1266 Harrisburg, PA 17108-1266 Mr. R. R. Janati Bureau of Radiation Protection Rachel Carson State Office Building P. 0. Box 8469 Harrisburg, PA 17105-8469

NRC FORM 366 U.S. NUCLEAR REGULATORY APPROVEDBYOMB: NO. 3150-0104 EXPIRES: 06/30/2007

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

Information collection.

1. FACILITY NAME Susquehanna Steam Electric Station Unit 1

2. DOCKET NUMBER

3. PAGE 05000387 1 OF3

4. liTLE Missed Technical Specification surveillance requirement

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED MONTH DAY YEAR SEQUENTIAL REV FACILITY NAME DOCKET NUMBER NUMBER NO.

MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 3

23 2006 2006 002 00 5

15 2006

9. OPERATING MODE

11. THIS REPORT IS SUBMITrED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 5

[] 20.2201 (b)

[I 20.2203(a)(3)(i) 0l 50.73(a)(2)(i)(C)

[I 50.73(a)(2)(vii)

10. POWER LEVEL

[ 20.2201(d) 0l 20.2203(a)(3)(ii)

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

El 50.73(a)(2)(vlii)(A) o 20.2203(a)(1)

[] 20.2203(a)(4)

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

El 50.73(a)(2)(viii)(B) 0%

[1 20.2203(a)(2)(i)

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

[I 50.73(a)(2)(iii) 0l 50.73(a)(2)(ix)(A) 0 20.2203(a)(2)(ii)

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

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

[I 50.73(a)(2)(x)

El 20.2203(a)(2)(iii) 0l 50.36(c)(2)

El 50.73(a)(2)(v)(A) 0l 73.71 (a)(4)

El 20.2203(a)(2)(iv)

[I 50.46(a)(3)(ii)

[I 50.73(a)(2)(v)(B) 0l 73.71 (a)(5)

El 20.2203(a)(2)(v)

[I 50.73(a)(2)(i)(A)

[I 50.73(a)(2)(v)(C) 0l OTHER 0l 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B)

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

Specify in Abstract below or in (if more space is reqdred, we addiional copies of (if more space is required, use additonal copies of NRC

CORRECTIVE ACTIONS

Completed Actions

1) Because the penetration was disturbed during the modification, the periodic testing requirement was re-established at a 30 month interval.

Planned Actions

1) Review scheduled work on similar containment penetrations governed by the Appendix J Program for the 2007 Unit 2 Refuel Outage.

2) Provide for a peer review of final LLRT/ILRT outage plans and testing requirements prior to future outages.

ADDITIONAL INFORMATION

Past similar events:

Docket 50-387 LER 00-001-00 NRC FORM 366 (6-2004)