05000388/LER-2013-001, Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 1

Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 1

ML13168A375
Person / Time
Site:	Susquehanna
Issue date:	06/14/2013
From:	Franke J Susquehanna
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
PLA-7018 LER 13-001-00
Download: ML13168A375 (5)

LER-2013-001, Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 1

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)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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
3882013001R00 - NRC Website

text

1L 4 201~.

Jon A. Franke Site Vice President U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 jfranke@pplweb.com SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-388/2013-001-00 LICENSE NO. NPF-22 PLA-7018 I

I I

~

\\

I I

I

'~ \\***/ ~"'

ppl.~~~:

TM Docket No. 50-388 Attached is Licensee Event Report (LER) 50-388/2013-001-00. The condition reported by this LER was an expected condition, which was the result of planned activities in support of a routine refueling outage. As described in the LER, the U.S Nuclear Regulatory Commission (NRC) provided enforcement guidance, applicable to boiling water reactor licensees, that allows the reported condition. Although this allowance is provided by the NRC's enforcement guidance, the planned activities are still considered reportable in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications (TS).

Specifically, operations with the potential for draining the reactor vessel (OPDRVs) were performed while in Mode 5 without secondary containment being operable, as expected and allowed by the enforcement guidance. With the exception noted in the LER, the provisions contained in NRC enforcement guidance memorandum (EGM)11-003, Revision 1, "Dispositioning Boiling Water Reactor Licensee Noncompliance with Technical Specification Containment Requirements during Operations with a Potential for Draining the Reactor Vessel," were used during performance of the OPDRVs reported in the enclosed LER.

No regulatory commitments are associated with this LER.

0~{2_()

J. A. Franke Attachment: LER 50-3 88/2013-001-00 Copy:

NRC Region I Mr. P. W. Finney, NRC Sr. Resident Inspector Mr. J. A. Whited, NRC Project Manager Mr. L. J. Winker, DEP/BRP Document Control Desk PLA-7018

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES:10/31/2013 (10-2010)

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

3. PAGE Susquehanna Steam Electric Station Unit 2 05000388 1 OF 3 f4. TITLE Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 1

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

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

MONTH DAY YEAR NUMBER 0/.i; It/

FACILITY NAME DOCKET NUMBER 04 17 2013 2013

- 001

- 00 2013

9. OPERATING MODE

11. THIS REPORT IS SUBMI1TED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 5 D 20.2201(b)

D 20.2203(a)(3)(i)

D 50.73(a)(2)(i)(C)

D 50.73(a)(2)(vii)

D 20.2201 (d)

D 20.2203(a)(3)(ii)

D 50.73(a)(2)(ii)(A)

D 50.73(a)(2)(viii)(A)

D 20.2203(a)(1)

D 20.2203(a)(4)

D 50.73(a)(2)(ii)(B)

D 50. 73(a)(2)(viii)(B)

10. POWER LEVEL D 20.2203(a)(2)(i)

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

D 50.73(a)(2)(iii)

D 50.73(a)(2)(ix)(A) 000 D 20.2203(a)(2)(ii)

D 50.36(c)(1 )(ii)(A)

D 50.73(a)(2)(iv)(A)

D 50.73(a)(2)(x)

D 20.2203(a)(2)(iii)

D 50.36(c)(2)

D 50.73(a)(2)(v)(A)

D 73.71 (a)(4)

D 20.2203(a)(2)(iv)

D 50.46(a)(3)(ii)

D 50.73(a)(2)(v)(B)

D 73.71 (a)(5)

D 20.2203(a)(2)(v)

D 50.73(a)(2)(i)(A)

D 50.73(a)(2)(v)(C) 0 OTHER D 20.2203(a)(2)(vi)

[8] 50.73(a)(2)(i)(B)

D 50. 73(a)(2)(v)(D)

Specify in Abstract below or in The exception of TS 3.8.2 was due to an unrecognized condition prohibited by the TS when more than one required AC power source was inoperable during OPDRV activities. Specifically, required emergency diesel generators were rendered inoperable by the failure of an electrical synchronizing switch. The duration of the exception was approximately 75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />.

Because the inoperable AC power sources were determined to have maintained their ability to perform their necessary shutdown risk function, the impact to OPDRV activities was determined to be of low shutdown risk significance. Details of the condition prohibited by TS 3.8.2 are planned to be reported in a separate LER.

CORRECTIVE ACTIONS

SSES will submit a license amendment following NRC approval of the Technical Specifications Task Force traveler associated with generic resolution of this issue within the time constraints given in EGM 11-003, Revision 1.

No regulatory commitments are associated with this report.

ADDITIONAL INFORMATION

Component Information: None

Previous Similar Events

None