ML19309B050
| ML19309B050 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 08/16/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| References | |
| NUDOCS 8004020526 | |
| Download: ML19309B050 (3) | |
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ORB #4 Reading
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Docket No. 50-312 VStello BGrimes BReid t.._.
GZwetzig TAbernathy C-Glainis C "
JBuchanan Sacramento Municipal Pility District PCheck ACRS(16)
E ATTH: Mr. J. J. Mat; 3 RIngram Gray file
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Assistant Ge.-
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.==i.=j and Chief E, 6201 S Street DEisenhut j;l.g.g.]
P. O. Box 15830
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Sacramento, California 95813
}d F= E Gentlemen:
By letter dated July 20, 1978, you proposed certain modifications I.
at Rancho Seco Nuclear Generating Station to eliminate the need for operator action in the event of a small break in the discharge piping
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from the reactor coolant pumps. These prorosed modifications consisted Ei.. ?..
- 1) Maintaining the valves in the cross-tie line connecting the two
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High Pressure Injection (HPI) loops open whenever the HPI system is in service,
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- 2) Supplyino power to the HPI Loop A injection valves (one in 555 each leg) from the 125 volt DC, Class I, C battery and to
. -E the HPI Loop B injection valves similarly from the D battery, IC2.
- 3) Supplying power to the makeup isolation valve from the 125 f.[
volt DC, Class I, C battery, and p)))EE
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- 4) Supplying an "Open' sijnal to all four injection valves from I.'."..;
both Channels A and B of the safety features actuation system.
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Your submittal also presented a failure analysis of the proposed modified l;;;;=
system, and referenced an analysis which is stated to verify the adequacy z
of the battery capacity to power the valves and existing loads.
=r..s This is to advise you that based on our review of your submittal, we r-find the proposed modifications acceptable with respect to the overall 9"=,"
concept.
Lhether the rodifications will be fully acceptable in practice, r
howeJer, will depend upon the manner in which they are actually gf h
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Considerations bearing on this final acceptability L
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include: the environmental and seismic qualification of new compo-
.cs nents; the extent to which required operator action would differ from that required prior to discovery of the small break problem; the F = "i results of our review of the battery loading analysis; the proposed pre-operational test program; and conformance with other regulatory gufdance applied to safety-related systems of this type.
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Therefore, if you believe the proposed modifications, when implemented,
- _...:d will meet regulatory requiremants, you should consider initiating pre-
'.. 3 parations for implementing the modifications as described, at an early gg date, and should submit information and/or comitments related to the jer...~ _
above considerations at least 60 days prior to implementation, r=~;;
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Sincerely,
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Robert W. Reid, Chief
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Operating Reactors Branch f4 mm; Division of Operating Reactors
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- David S. Kaplan, Secretary and
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General Counsel
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6201 S Street Post Office Box 15830
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Sacramento, California 95813 Business and Municipal Department Sacramento City-County Library 828-I Street Sacramento, California 95814 g====.
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