ML120870169

Electronic Transmission, Draft Request for Additional Information Regarding Fourth Interval Inservice Testing Relief Request PR-05

ML120870169
Person / Time
Site:	Three Mile Island
Issue date:	03/28/2012
From:	Peter Bamford Plant Licensing Branch 1
To:	Meena Khanna Plant Licensing Branch 1
Bamford, Peter J., NRR/DORL 415-2833
References
TAC ME7532
Download: ML120870169 (3)

Text

March 28, 2012 MEMORANDUM TO: Meena Khanna, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Peter Bamford, Project Manager /ra/

Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

THREE MILE ISLAND, UNIT NO. 1 - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING FOURTH INTERVAL INSERVICE TESTING RELIEF REQUEST PR-05 (TAC NO. ME7532)

The attached draft request for additional information (RAI) was transmitted by electronic transmission on March 26, 2012, to Mr. Thomas Loomis, at Exelon Generation Company, LLC (Exelon, the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call (if needed) with Exelon in order to clarify the licensees relief request regarding the fourth interval inservice testing program. The draft RAI is related to the licensees submittal dated October 28, 2011. The draft question was sent to ensure that it was understandable, the regulatory basis was clear, and to determine if the information was previously docketed.

Additionally, review of the draft RAI would allow Exelon to evaluate and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position.

Docket Nos. 50-289

Enclosure:

As stated

March 28, 2012 MEMORANDUM TO: Meena Khanna, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Peter Bamford, Project Manager /ra/

Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

THREE MILE ISLAND, UNIT NO. 1 - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING FOURTH INTERVAL INSERVICE TESTING RELIEF REQUEST PR-05 (TAC NO. ME7532)

The attached draft request for additional information (RAI) was transmitted by electronic transmission on March 26, 2012, to Mr. Thomas Loomis, at Exelon Generation Company, LLC (Exelon, the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call (if needed) with Exelon in order to clarify the licensees relief request regarding the fourth interval inservice testing program. The draft RAI is related to the licensees submittal dated October 28, 2011. The draft question was sent to ensure that it was understandable, the regulatory basis was clear, and to determine if the information was previously docketed.

Additionally, review of the draft RAI would allow Exelon to evaluate and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position.

Docket Nos. 50-289

Enclosure:

As stated DISTRIBUTION:

Public RidsNrrPMPBamford LPL1-2 R/F Accession No.: ML120870169

• via email OFFICE LPL1-2/PM SPTB/BC NAME PBamford AMcMurtray*

DATE 3/28/12 03/26/2012 OFFICIAL RECORD COPY

REQUEST FOR ADDITIONAL INFORMATION THREE MILE ISLAND NUCLEAR STATION, UNIT 1 RELIEF REQUEST ASSOCIATED WITH THE FOURTH INSERVICE TESTING INTERVAL RELIEF REQUEST PR-05 DOCKET NO. 50-289 By letter dated October 28, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML113010335), Exelon Generation Company, LLC submitted a relief request for Three Mile Island Nuclear Station, Unit 1 (TMI-1). The relief request is associated with the fourth Inservice Testing (IST) interval at TMI-1 and it proposes alternative testing of the Reactor Building Emergency Cooling River Water Pumps. The U.S. Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and, based on the information provided, it appears that relief from the requirements of the American Society of Mechanical Engineers (ASME) Operation and Maintenance Code (OM Code) is not required. Therefore, please review the following request for additional information and provide an appropriate response.

PR Request for Additional Information:

Does the test proposed in your submittal use a fixed system resistance to establish a repeatable reference condition and then measure, record, and evaluate pump differential pressure to assess pump performance trends? If so, then this approach does not appear to the NRC technical staff to be a deviation from the requirements of OM Code and, therefore, does not require relief. Please note that NRC regional inspection staff have previously reached a similar conclusion regarding testing of these pumps as documented in Inspection Report No.

050000289/2004004, dated November 8, 2004 (ADAMS Accession No. ML043150481). Also please note that, interpretation of ASME OM Code requirements is the purview of the ASME Committee on Operations and Maintenance and, if needed, their inquiry process is available for assistance in clarifying OM Code requirements.