ML15202A378

Limerick Generating Station, Units 1 and 2, Draft Request for Additional Information (TAC Nos. MF6094 and MF6095)

ML15202A378
Person / Time
Site:	Limerick
Issue date:	07/21/2015
From:	Richard Ennis Plant Licensing Branch 1
To:	Broaddus D A Plant Licensing Branch 1
Ennis R B, NRR/DORL/LPLI-2, 415-1420
References
TAC MF6094, TAC MF6095
Download: ML15202A378 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 21, 2015

MEMORANDUM TO: Douglas A. Broaddus, Chief Plant Licensing Branch I-2

Division of Operating Reactor Licensing

Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager

/RA/ Plant Licensing Branch I-2

Division of Operating Reactor Licensing

Office of Nuclear Reactor Regulation

SUBJECT:

LIMERICK GENERATING STATION, UNITS 1 AND 2, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MF6094

AND MF6095)

The attached draft request for additional information (RAI) was transmitted on July 13, 2015, to

Ms. Stephanie Hanson of Exelon Generation Company, LLC (Exelon, the licensee). This

information was transmitted in order to clarify the licensee's relief request dated April 13, 2015, for Limerick Generating Station (LGS), Units 1 and 2. The proposed relief request concerns the

use American Society of Mechanical Engineers (ASME)

Boiler and Pressure Vessel Code (Code) Case OMN-18, "Alternate Testing Requirements for Pumps Tested Quarterly Within

+/-20% of Design Flow."

The draft RAI was sent to Exelon to ensure that the questions are understandable, the

regulatory basis for the questions is clear, and to determine if the information was previously

docketed. This memorandum and the attachment do not convey or represent an NRC staff

position regarding the licensee's request.

Docket Nos. 50-352 and 50-353

Attachment:

Draft RAI

July 21, 2015

MEMORANDUM TO: Douglas A. Broaddus, Chief Plant Licensing Branch I-2

Division of Operating Reactor Licensing

Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager

/RA/ Plant Licensing Branch I-2

Division of Operating Reactor Licensing

Office of Nuclear Reactor Regulation

SUBJECT:

LIMERICK GENERATING STATION, UNITS 1 AND 2, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MF6094

AND MF6095)

The attached draft request for additional information (RAI) was transmitted on July 13, 2015, to

Ms. Stephanie Hanson of Exelon Generation Company, LLC (Exelon, the licensee). This

information was transmitted in order to clarify the licensee's relief request dated April 13, 2015, for Limerick Generating Station (LGS), Units 1 and 2. The proposed relief request concerns the

use American Society of Mechanical Engineers (ASME)

Boiler and Pressure Vessel Code (Code) Case OMN-18, "Alternate Testing Requirements for Pumps Tested Quarterly Within

+/-20% of Design Flow."

The draft RAI was sent to Exelon to ensure that the questions are understandable, the

regulatory basis for the questions is clear, and to determine if the information was previously

docketed. This memorandum and the attachment do not convey or represent an NRC staff

position regarding the licensee's request.

Docket Nos. 50-352 and 50-353

Attachment:

Draft RAI

DISTRIBUTION PUBLIC LPL1-2 R/F RidsNrrDorlLpl1-2 Resource RidsNrrDorlDpr Resource RidsNrrPMLimerick Resource RidsNrrDeEpnb Resource RWolfgang, NRR/EPNB ACCESSION NO.: ML15202A378 OFFICE LPL1-2/PM NAME REnnis DATE 7/21/15 OFFICIAL RECORD COPY DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED RELIEF REQUEST TO UTILIZE CODE CASE OMN-18 EXELON GENERATION COMPANY, LLC LIMERICK GENERATING STATION, UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353

By letter dated April 13, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15104A531), Exelon Gener ation Company, LLC submitted a relief request for Limerick Generating Station, Units 1 and 2. The proposed relief request concerns

the use American Society of Mechanical Engineers (ASME)

Boiler and Pressure Vessel Code (Code) Case OMN-18, "Alternate Testing Requirements for Pumps Tested Quarterly Within

+/-20% of Design Flow."

The Nuclear Regulatory Commission (NRC) staff has reviewed the information the licensee

provided that supports the proposed relief request and would like to discuss the following issues

to clarify the submittal.

RAI 1 Code Case OMN-18 has a note that states, "Subsection ISTB allows the Owner to categorize

the pumps in their program. As such, an Owner could categorize a pump that otherwise meets

the requirements of Group B, as a Group A pump, and test according to this Code Case.

However, in doing so they are obtaining additional data (vibration and flow or differential

pressure) quarterly, rather than once every 2 yr." Confirm that the pumps listed in Section 1, "ASME Code Component(s) Affected," of the relief request that are categorized as Group B

pumps, will be re-categorized as Group A pumps.

Attachment