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ML101340691 +

10 CFR 50.55a +, 10 CFR 50.55a#a3i +, 10 CFR 50.55a#b +, 10 CFR 50.55a#a3ii +, 10 CFR 50.55a#f4ii +, 10 CFR 50.55a#f4iv +, 10 CFR 50.55a#3i +, 10 CFR 50.55a#b6 + and 10 CFR 50.55a#3ii +

Code case

ASME Code Case OMN-17 +

Contact

DiFrancesco N, NRR/DORL/LPL3-2, 415-1115 +

Docket

05000461 + and 00461 +

Document

ML101340691 +, ML091690167 + and RS-10-044, Response to Request for Additional Information Related to Request for Approval of Relief Requests for Third Inservice Testing Interval +

From

Shawn Campbell + and Plant Licensing Branch III +

GE report

MPR-1807 + and MPR-2524-A +

Generic letter

NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +, NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves + and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

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June 10, 2010 +

ML091690167 + and RS-10-043, Response to Request for Additional Information Related to Request for NRC Approval of Changes to Emergency Plan +

Manufacturer

Westinghouse +

Modification date"Modification date" is a predefined property that corresponds to the date of the last modification of a subject and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.

09:57:11, 14 January 2025 +

NUREG

NUREG-1482, Revision 4, Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants Final Report +

Page count

11 +

Person

Robert Wolfgang +

Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.

Approval +

Regulatory Guide 1.192 +

SR

SR-3.5.1.1 +

SSC

1B21-F047A +, 1O-year +, 1E51-C003 +, 1B21-F047B +, 1B21-F041 +, 1B21-F051B +, 1B21-F051D +, 1B21-F051C +, 1E21-C002 +, 1E12-C003 +, 1B21-F051 +, 1B21-F047D +, 1B21-F047C +, 1B21-F041A +, 1B21-F041B +, 1B21-F041C +, 1B21-F041D +, 1B21-F041F +, 1B21-F041G +, 1B21-F041L +, 1B21-F047F +, 1B21-F051G + and J1E12-C003 +

June 10, 2010 +

Core Spray +, Residual Heat Removal +, Safety Relief Valve + and Main Steam +

Title

Safety Evaluation of Relief Request Nos. 2201, 2202, and 3201, for the Third 10-Year Inservice Testing Interval +

To

Exelon + and Pacilio M +

Topic

Stroke time +, Incorporated by reference +, Grace period + and Water hammer +

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http://pbadupws.nrc.gov/docs/ML1013/ML101340691.pdf +

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