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Browns Ferry Technical Specification 5.5.4 … Browns Ferry Technical Specification 5.5.4 requires compliance with ODCM requirements. ODCM 1.1.1 requires that the radioactive liquid effluent monitoring instrumentation listed in Table 1.1-1 be OPERABLE with the applicability as shown in Tables 1.1-1 and 2.1-1. ODCM 1.1-1 allows for a liquid effluent release to occur with less than the minimum channels OPERABLE requirement if the appropriate actions from Table 1.1-1 are taken. The applicable specific requirements from Table 1.1-1 are: ACTION A During release of radioactive wastes from the radwaste processing system, the following shall be met: (1) liquid waste activity and flowrate shall be continuously monitored during release and shall be set to alarm and automatically close the waste discharge valve before exceeding the limits specified in Control 1.2.1.1, (2) if this cannot be met, two independent samples of the tank being discharged shall be analyzed in accordance with the sampling and analysis program specified in Table 2.2-1 and two qualified station personnel shall independently verify the release rate calculations and check valving before the discharge. Otherwise, suspend releases via this pathway. Contrary to the above stated requirements, on February 12, 2014, the licensee released approximately 38,000 gallons of water via Unit 3 discharge to CCW conduit valve 3-FCV-77-0061 without meeting condition (2) of Table 1.1-1 Action A. The valve that was supposed to provide the isolation function (3-FCV-77-0061) had been inoperable since June 17, 2013 (greater than 30 days out of service), for a missed channel functional test surveillance 3-SI-4.8.A.3. The valve had been danger tagged closed on June 18, 2013 and the tag was inadvertently removed on October 24, 2013 when a clearance for other work was removed. The licensee discovered the error upon review of the previous nights logs and documented the event in PER 849316. Post release data indicates that release was within ODCM limits. The issue was evaluated using the Public Radiation Safety Significance Determination Process Inspection Manual Chapter 0609 Appendix D. The issue was determined to be, (Green), because it was an abnormal release to the environment which the licensee had sufficient data to assess dose to members of the public and the dose impact was substantially less that the dose values in Appendix I to 10 CFR 50 and 10 CFR 20.1301(e).ndix I to 10 CFR 50 and 10 CFR 20.1301(e).

Discovered date

23:59:59, 31 March 2014 +

Docket

05000259 +, 05000260 + and 05000296 +

Event date

23:59:59, 31 March 2014 +

Finding integer

7 +

Finding type

Non-cited violation +

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Identified by

Licensee-identified +

Inspection Manual Chapter

NRC Inspection Manual 0609 Appendix D +

Inspection report

IR 05000259/2014002 +

Inspector

J Bartley +, C Kontz +, M Coursey +, R Hamilton +, David Dumbacher +, Lundy Pressley +, William Pursley + and Tom Stephen +

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>.

15:49:48, 30 May 2018 +

Person