ML20052E911

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Proposed Changes to Tech Specs Deleting All Requirements Associated W/Drywell Sprinkler Sys
ML20052E911
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 05/03/1982
From:
GEORGIA POWER CO.
To:
Shared Package
ML20052E908 List:
References
TAC-48338, TAC-48339, NUDOCS 8205110532
Download: ML20052E911 (3)


Text

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GeorgiaPower d ATTACFNENT 1 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 PROPOSA'. FOR DELETION OF DRYWELL SPRINKLER SYSTEM i TECHNICAL SPECIFICATION REQUIREMENTS The proposed changes to Technical. Specifications (Appendix A to Operating License DPR-57) would be incorporated as follows:

Remove Page Insert Page 3/4 6-3 3/4 6-3 3/4 7-25 3/4 7-25 h kD 0 P

PLANT SYSTEMS SPRINKLER SYSTEMS LIMITING C0tOITION FOR OPERATION 3.7.6.2 The following sprinkler systems shall be OPERABLE:

Turbine lube oil storage Turbine lube oil reservoir RCIC room HPCI room West cableway East cableway Recirculation pump motor generator room Cable spreading room RPS vertical cableway Control Building Corridor (El.130 ')

Reactor Building HVAC room l APPLICABILITY : Whenever equipment in the sprinkler protected areas is requireo to be OPERABLE.

ACTION:

a. With one or more of the above required sprinkler systems inoperable, establish a continuous fire watch with backup fire suppression equipment for the unprotected area (s) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, provided radiation levels permit personnel access; restore the system to OPERABLE status eithin 14 days or, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

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HATCH - UNIT 2 3/4 7-25

CONTAINMENT SYSTEMS PRIMARY CONTAIPNENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Primary containment leakage rates shall be limited to:

a. An overall integrated leakage rate of:
1. < La,1.2 percent be weight of the containment air per 24 Kours at Pa, 57.5 psig, or
2. < Lt, 0.849 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a reduced pressure of Pt , 28.8 psig.
b. A combined leakage rate of:
l. $ 0.60 La for all penetrations and valves, except for main steam isolation valves, subject to Type B and C tests when pressurized to Pa, and
2. 5 0.009 La for the following penetrations *:

(a) Main steam condensate drain, penetration 8; (b) Primary feedwater, penetrations 9A cnd 96; (c) Reactor water cleanup, penetration 14; (d) Equipment drain sump discharge, penetration 18; (e) Floor drain sump discharge, penetration 19; (f) Chemical drain aump discharge, penetration 55; and (g) Torus drainage and purification, penetration 234A.

c. 11.5 scf per hour for any one main steam isloation valve when tested at 28.8 psig.**

APPLICABILITY: When PRIMARY CONTAltNENT INTEGRITY is required per Specification 3.6.1.1.

  • Potential bypass leakage paths.
** Exemption to Appendix J of 10 CFR 50.

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