ML19246A585
| ML19246A585 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 05/23/1979 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| FOIA-79-98 NUDOCS 7907050005 | |
| Download: ML19246A585 (2) | |
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' DAIRYLAND POTVER COOPERATIVE Ea Gna, 0%mu
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May 23, 1979
)"l In reply, please refer to LAC-6315 Mr. James G. Keppler Regional Director U.
S. Nuclear Regulatory Commission Directorate of Regulatory Operations Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137
SUBJECT:
DAIRYLAND POWFR COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 IE BULLETIN NO. 79 ADDITIONAL INFORP.ATION -
EVENTS RELEVANT TO BWR'S IDENTIFIED DURING THREE MILE ISLAND INCIDENT
Reference:
(1)
NRC Letter, Keppler to Linder, dated April 14, 1979.
(2)
DPC Letter, Linder to Keppler, dated May 2, 1979.
Dear Mr. Keppler:
Our response (Reference 2) to question 7c of IE Bulletin No. 79-08 enclosed with Reference 1 required further action by us.
The basis on which continued operability of automatic isolation of systems designed to transfer potentially radioactive gases and liquids out of the primary containment is shown on Figure 1, attached.
If there are any questions concerning this matter, please contact us.
Very truly yours, DAIRYLAND POWER COOPERATIVE Frank Linder, General Manager FL:PJW:af Attachment
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U.
S. Nuclear Regulatory Commission Office of. inspection and Enforcement Division of Reactor Operations Inspection 79 7 050g6 f,O )s Washington, D. C.
20555 0
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IE Bulletin 79-03 FIGURE 1 FAIL POSITION Automatic
- Tech.
Operating Manual Loss of Isolation Spec.
Surveillance Motive Loss of System Signal Section Procedure Fluid Power Retention 3
4.2.1.1 Vol. XI, close C1cse Tank Pump 5.2.2 Sec. 4.1.1 Discharge Decay 2,3 4.2.1.1 Vol. XI, close close Heat 5.2.2 Sec. 4.1.1 Blowdown for 3; Vol. XI, Sec. 4.2.2 for 2.
Main 2,4,6 4.2.1.1 vol. XI, As is Close Steam 4.2.1.7 Sec. 4.2.2 Close Close Isolation 5.2.2 for 2,4 & 6 Valve and MSIV By-pass Valve Reactor 1,3,5 4.2.1.1 Vol. XI, Close Close cuilding 4.2.1.6 Sec. 4.1.1 Ventila-
- 5. 2. 2 for 1,3 & 5 tion System Reactor 1,3,5 4.2.1.1 Vol. XI, Close to close te Building
- 5. 2. 2 Sec. 4.1.1 Vent Vent Ventila-for 1,3 & 5 Fan Fan tion Header
- Automatic Isolation Signals:
(1)
High Radiation (2)
Low Reactor Water Level (-12")
(3)
High Containment Building Pressure (5 psig)
(4) 1000 psig Main Steam Line Pressure (5) 1325 psig Reactor Pressure (6)
Low Main Condenser Vacuum (19" Hg)
All surveillance tests listed in this table are required to be perforr.ed prior to every cold startup, but not more often than at 30-day invervals (Ref. Tech. Spec. 5.2.2).
SETa17
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