ML080590373

Technical Specifications 5.5, Programs and Manuals, Pages 5 .5-12 Through 5 .5-14, Dresden Units 2 and 3, to CR Habitability Amendment

ML080590373
Person / Time
Site:	Dresden, Quad Cities
Issue date:	03/20/2008
From:	Joel Wiebe Plant Licensing Branch III-2
To:	Pardee C Exelon Generation Co
Wiebe, Joel NRR/DORL/LPL3-2, 415-6606
References
Download: ML080590373 (3)

Text

5.5 Programs and Manuals Programs and Manuals 5.5 5.5.12 Primary Containment Leakage Rate Testing Program (continued)

2. NEI 94 1995, Section 9.2.3: The first Unit 3 Type A test performed after the July 14, 1994, Type A test shall be performed no later than July 13, 2009. b. The peak calculated primary containment internal pressure for the design basis loss of coolant accident, P a , is 43.9 psig. c. The maximum allowable primary containment leakage rate, L a , at P a , is 3% of primary containment air weight per day. d. Leakage rate acceptance criteria are: 1. Primary containment overall leakage rate acceptance criterion is <_ 1.0 L a. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are <_ 0.60 L a for the combined Type B and Type C tests, and <_ 0.75 L a for Type A tests. 2. Air lock testing acceptance criteria is the overall air lock leakage rate is <_ 0.05 L a when tested at _> Pa. e. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program. 5.5.13 Battery Monitoring and Maintenance Program This Program provides for restoration and maintenance, based on the recommendations of IEEE Standard 450-1995, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications," including the following: a. Actions to restore battery cells with float voltage < 2.13 V, and b. Actions to equalize and test battery cells that had been discovered with electrolyte level below the minimum established design limit. (continued)

Dresden 2 and 3 5.5-12 Amendment No.

5.5 Programs and Manuals 5.5.14 Control Room Envelope Habitability Pr oqram Programs and Manuals 5.5 A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation (CREV) System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident. The program shall include the following elements: a. The definition of the CRE and the CRE boundary. b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance. c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0. d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by the CREV system, operating at the flow rate required by the VFTP, at a Frequency of 24 months. The results shall be trended and used as part of the 24 month assessment of the CRE boundary. e. The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph

c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis. f. The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered (continued)

Dresden 2 and 3 5.5-13 Amendment No.

5.5 Programs and Manuals 5.5.14 Control Room Envelope Habitability Program (continued)

Programs and Manuals 5.5 inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively. Dresden 2 and 3 5.5-14 Amendment No.