ML19225A345
| ML19225A345 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 05/29/1979 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| LAC-6319, NUDOCS 7907190015 | |
| Download: ML19225A345 (2) | |
Text
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D.tIItYLAND POWEIt COOPEftATIVE Sa Groue, Chconan
$4601 May 29, 1979 In reply, please refer to LAC-6319 o
DOCKET NO. 50-409 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 POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 IE BULLETIN NO. 79 ADDITIONA5 INFORMATION -
EVENTS RELEVANT TO BWR'S IDENTIFIED DURING THREE MILE ISLAND INCIDENT
Reference:
(1)
DPC Letter, LAC-6315, Linder to Keppler, dated May 23, 1979.
Dear Mr. Keppler:
Our letter (Reference 1) forwarded information regarding sur-veillance of automatic isolation features for those systems designed to transfer potentially radioactive gasses and liquids out of primary containment.
Based on additional review of this information, we have determined that some minor revisions to Figure 1 are necessary.
Therefore, Revision 1 of Figure 1 is enclosed.
If there are any questions regarding this submittal, plcase contact us.
Very truly yours, DAIRYLAND POWER COCPERATIVE LJN J,
Frank Linder, General Manager FL:PJW:af Enclosure cc:
U. S.
Nuclear Regulatory Commission
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Office of Inspection and Enforcement Division of Reactor Operations Inspection 90069 790"i Washington, D. C.
20555 Mr. Larry Witt - American Nuclear Insurers
/ 3 1 1979
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IE Bulletin 79-08 FIGURE 1 - (Revision 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 Close Tank Pump 5.2.2 Sec. 4.1.1 Discharge Decay 2
4.2.1.1 Vol. XI, Close Close Heat 5.2.2 Sec. 4.2.2 Blowdown 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 Sy-pass Valve Reactor 1,3,5 4.2.1.1 Vol. XI, Close Close Building
- 4. 2.1. 6 Sec. 4.1.1 Ventila-S.2.2 for 1,3&5 tion System Reactor 3,5 4.2.1.1 Vol. XI, Close Close Building 5.2.2 Sec. 4.1.1 Ventila-for 3& 5 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 Reacto).' Pressure (6)
Low Mair. Condenser Vacuum (19" Hg)
All surveillance tests listed in this table are required to be performed prior to every cold startup, but not more often than at 30-day intervals (Ref. Tech. Spec. 5.2.2).
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