ML20004E831
| ML20004E831 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/10/1981 |
| From: | ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20004E828 | List: |
| References | |
| NUDOCS 8106150349 | |
| Download: ML20004E831 (4) | |
Text
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\ - PLANT SYSTEM
$ SECONDARY WATER CHEMISTRY LIMITING CONDITION FOR OPERATION UE.'
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3 . 7 .1. The secondary water chemistry shall be maintained within e limits of le 3.7-3. APPLICABILITY: tw rS 1, 2 and 3. ACTION: ' ;;^.
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(To be. determined in the manner t for in the bases in approximately , six months after commercial opfgt1 and to be imposed by a change to ' this Specification.) 6@p SURVEILLANCE REQUIREMENTS 4.7.1.6 The s e ary wat.er chemistry shall be determi n' be within the limits by analysi # those parameters at equencies specified in Table 4.7-3. - - t w', F ARKANSAS - UNIT 2 3/4 7-11 810 615 0%$
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- Sample locations, parameters and limits s lished in approximately 6 months after commercial
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- Sample locations, param rs and frequencies to be established in a roximately 6 months after commercial 3 operation based upon st program described in bases. '
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a PLANT SYSTEMS BASES 5-yj .. 3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture. This dose also includes the effects of a coincident 1.0 GPM primary to secondary tube leak in the : team generator of the affected steam line and a , ,. concurrent loss of offsite electrical power. These values are consistent ;l4. with the assumptions used in the accident analyses. 3/4.7.1.5 MAIN STEAM ISOLATION VALVES The OPERABILITY of the main steam isolation valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture. This restriction is required to 1) minimize the ".,. positive reactivity effects of the Reactor Coolant System cooldown 9: associated with the blowdown, and 2) limit the pressure rise within containment in the 3 vent the steam line rupture occurs within contain- "
' ment. The OPERABILITY of the main steam isolation valves within the s closure times of the surveillance requirements are consistent with the .
assumptions used in the accident analyses. 3/4.7.1.6 SECONDARY WATER CHEMISTRY A test program will be conducted during approximately the first 6 month f operation after initial criticality to establish the appropr' e _ limits o he secondary water chemistry parameter. :nd the determi he appropriate equencies for monitoring these parameters. The r a ts of this test prog n will be submitted to the Commission for r ' 'ew. The Commission will t. issue a revision to this specificat' specifying the limits on the ch 'stry parameters and the f a u - ies for monitoring these parameters. b -LN.ef This test program will in an ysis of the chemicol con-stitutents of the condenser cool s+ . The analysis shall identify the various traces of ions which u . centration in the condenser may have the potential for inducem for w% s corrosion in the steam generator tubing. The test ogram shall alyze concentration phenomena and the concentration r s in t'ie steam gene tor and the secondary water system.
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