ML19291A452
| ML19291A452 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 01/16/1979 |
| From: | Jordan E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | Grimes B Office of Nuclear Reactor Regulation |
| References | |
| FOIA-79-98, TASK-TF, TASK-TMR IE:ROI:TP-79-01, IE:ROI:TP-79-1, NUDOCS 7905100445 | |
| Download: ML19291A452 (3) | |
Text
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IE:R01 TP-79-01
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TRANSFER OF LEAD RESPONSIEILITY E. K. Grimes, Assistant Director for Engineering and Projects, Divisien of Operating Reactors, Office of Nuclear Reactor Regulatien TO:
STEAM GENERATOR LEVEL CONTROL DURING AUXIL SUEJECT:
DAVIS EESSE
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FEEDWATER OPERATION E. L. Jordan, Assistant Director for RESPONSIELE ASSISTANT DIRECTOR:
Tecnnical Programs, Division of Reactor Operati:ns Inspection, Office of Inspection and Enforcement INTR 000CTION:
This confirms and formalizes a Transfer of Lead Responsibility which was 23, 1978. Timely involvement and assistance by verbally made Decemberthe Office of Nuclear Reactor Regulation (NRR is acknowledged and appreciated.
DESCRIPTION OF ITEM REOUIRING RESOLUTION:
During startup testing of the Davis Besse reactor the pressurizer level fell below the level indicating range, following a loss of offsite pow and scram frem 3% power. contraction caused by the large volume of cold pumped in to bring the steam generator levels up to 120 inches from th Of.fice of Inspection normal operating (level of about 30 inches at this power.IE) rev identified potential unreviewed safety questions since the small break and Enforcement analyses were perfonr.ed assuming a 120 inch steam generation leve actual pressuri:er level drop for a loss of offsite power at 100% power was not determined.
The licensee intends to permanently correct the p f
the auxiliary feedwater system from 120 inches to 35 inches unless a sa ety Until this change can be implemented, in the event injecticn is received.
of loss of offsite power, the steam generator levels are cc be held at The 3E inches by manual control, in accordance with a revisec procedure.
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centrol at 120 inches
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in :ne e.ar.t of a safe y injection signal power.
The licer.see reports tnat a recent natural circulation test at Davis 7.:
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Besse ceronstrated that the 35 inch level provides adecuate natura rercval (enciesed).
circula-icn for decay hea:
The licens=e believes that the temporary procedure change and
,770 d can, there-permanent fix cc not involve an unreviewed safety cuestion an
- Hcwever, fore, be made without NRC approval, in accordance with 10CFR 50 (fi n NRR several questions were raised during joint discussions between IE, mas ce c 23, 1978.
wiec and the licensee en December REC 0b"GDATICNS AND PROPOSED COURSE OF ACTION:
ION NRR will determine the acceptability of the tet tart 1-of a loss of offsite power and to control at 120 inches in the even.
DW t
' f" of a safety injection following a loss of cifs1:e power.
ICU tive NRR will determine the acceptability of the licensee's permanent c 1 to:
- era 1 2.
'cemi action.
imposed will' verify adequacy of administrative centrols temporarily id pc.
were 3-I:
ess'4 by the licensee in cennection with item 1.
f NRR will verify ccmpliance with any requirements established by fe te n.
and examine any plant modifications associated with a permane 1:
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to this problem.
l a r.Y 1 "e STAFF CONTACT:
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D. C. Kirkpatrick (28180) c-yY T IE:
V G. S. Vissinc (274351 I
NRR:
f-CONCURRENCE:
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