ML19319A655
| ML19319A655 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/15/1977 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Parker W DUKE POWER CO. |
| References | |
| NUDOCS 7911190643 | |
| Download: ML19319A655 (3) | |
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REQUEST FOR ADDITIONAL INFORMATION ON DUKE POWER COMPANY LETTER OF NOVEMBER 30, 1976 1.
In Table 4.4.1, valves Nos. 4, 43, 47, 53, 59, 55, and 51 were identified as not being required to be leak tested.
Provide additional justification why these valves should not be leak tested.
2.
Table 5-4 of the FSAR lists twenty-three penetrations which were not listed in your submittal as requiring leak testing.
The penetrations are:
a.
Penetration No. 8, loop nozzle warming lines; b.
Penetration No. 9, normal make-up to RC system; c.
Penetration No. 10, RCP seal injection lines; d.
Penetration Nos.13 and la, RB spray inlet lines; e.
Penetrations Nos.15 and 16, LPI and decay heat removal lines; f.
Penetration No.17, emergency feedwater inlet line; g.
Penetration No. 23, RCP seal injection line; h.
Penetrations Nos. 25, 26,27 and 28, feedwater and steam lines; i.
Penetration Nos. 30, 31, 32, 33, 34 and 35, RB emergency cooler outlet and inlet lines; J.
Penetration Nos. 36 and 37, RB sump recirculation lines; k.
Penetration No. 50, emergency feedwater inlet line; and 1.
Penetration No. 52, emergency reactor injection line.
For those penetrations listed, provide further justification why the valves will not be required to perform a containment isolation function and leak testing is not required.
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