ML19305E341
| ML19305E341 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 04/14/1980 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0578, RTR-NUREG-578 LAC-6860, NUDOCS 8004230426 | |
| Download: ML19305E341 (4) | |
Text
w D
DA/RYLAND h
[k COOPERAT/VE eo Box 8 7 26is EAST AV SOUTH
- LA CROSSE WISCONSIN 54601 (608) 788 4 000 April 14, 1980 In reply, please refer to LAC-6860 DOCKET NO. 50-409 Director of Nuclear Reactor Regulation ATTN:
Mr. Harold Denton, Director Office of Nuclear Reactor Regulation U.
S.
Nuclear Regulatory Commission Washington, D. C.
20555
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 ADDITIONAL INFORMATION - THREE MILE ISLAND LESSONS LEARNED (NUREG-0578 )
Reference:
(1)
DPC Letter, Linder to Denton, LAC-6853, dated April 9, 1980.
Gentlemen:
The attached information is in response to requests for additional information resulting from a site review of compliance with NUREG-0578 and an initial review of our previous submittal (Reference 1).
If you have any questions regarding this submittal, please contact us.
Very truly yours, DAIRYLAND POWER COOPERATIVE da ~ L/g Frank Linder, General Manager FL:JDP:af Attachment cc:
J.
Keppler, Reg. Dir., NRC-DRO III l 2b 8004230
RESPONSE TO REQUESTS FOR ADDITIONAL INFORMATION NRC REQUEST 2.1. 4 ( 4)l.
(Refer to DPC Letter LAC-6853 dated April 9, 1990).
Change final sentence to read:
"If the signals are due to a single instrument malfunction, either the low reactor water level signal or the high containment building pressure signal would require the use of jumper signals for bypassing."
NRC REQUEST:
2.1. 6. a (1)
Provide the measured leak rate data, tuo veeks after startup from April, 1980 outage, for the off-gas system, component cooling vater system (i. e., outside containment) and isolation condencer vent to off-gas cycten.
Describe periodic testing program including sample lineo uhen installed.
DPC RESPONSE:
Leak rate tests will be conducted during the April 1980 outage, for the off-gas and component cooling water systems.
The component cooling system will be tested to approximately 50 psi and the off-gas system and isolation condenser vent line to off-gas system to approximately 5 psi, based on the pressures that systems could see after an accident, if the boundaries between these systems and the primary system do not hold.
These tests will be repeated during each refueling outage.
Details on the sampling system testing will be submitted after it is installed.
The leak rate data from the above tests will be submitted after the startup from the April 1980 outage.
NRC REQUEST:
2.1. 6. a (2 )
Formalize your preventive maintenance (continuous program) to maintain leakage from cyatema outside containment that could contain radioactivity after an accident to ALAP levela.
Deceribe to the NRC, briefly, this program, including list of eyetens (sampling later uhen installed),
hou you handle ALAP considerations.
DPC RESPONSE:
Leakage from the off-gas system would be detected by Area Monitor
- 15 in the pipe tunnel, which has a readout at the top of the tunnel stairn and in the control Room.
Alarm C7-4 would alarm on an e
DPC RESPONSE - (Cont'd) increase in radiation level.
One of the immediate actions for this alarm is to investigate its cause.
Once the leakage point was found, repair efforts would be made.
Leakage out of the component cooling system can be detected by a decrease in the surge tank level.
Surge tank level is logged by the Auxiliary Operator.
High radiation levels in the CCW system can be detected by a continuous flow through radiation monitor, which read out in the control room and causes Alarm C9-1 to annunciate.
As soon as significant leakage from any system is detected, corrective action is taken, as deemed necessary.
LACBWR will submit details on detection of leakage from the sample system after its design is complete and it is installed.
NRC REQUEST:
2.1.6.b(1)
Provide a shiciding study of the control room, long term technical support center, long term campling stations, health physica lab and location for iodine particulate cartridgea for effluent lines.
Provide any proposed modifications prior to June 1, 1980.
DPC RESPONSE:
DPC has identified four areas which require post-accident entry or habitability:
(a)
Control Room (b)
Post-Accident Sampling Station (c)
Health Physics Laboratory (d)
In DPC letter LAC-6769, DPC reported that the dose levels in some of these locations exceeded GDC 19 limits based on a conservative L
analysis performed by Allis-Chalmers in ACNP-66564 DPC has decided to perform a more realistic analysis with the expectation that GDC 19 limits will be met without adding more shielding to any areas, except for the Technical Support Center.
The new shielding analysis vill be performed in accordance with Section 2.1.6.b of the "TMI-2 Lessons Learned Task Force Status Report and Short Term Recommendations", (NUREG- 057 8 ).
The source term will be bisd! on the TID fractions for noble gases, iodine and particulates, and the isotopes specified in G.E. Document No. 22A2703R, Rev.
5,
" Radiation Sources."
The computer code LORS (B&W version of ORIGEN) will be used in calculating the source term.
DPC RESPONSE - (Cont' d)
The shielding evaluation report as well as any proposed modifications required to meet GDC 19 guidelines in the four areas specified above will be reported to the NRC prior to June 1, 1980.
NRC REQUEST:
2.1.6.b(2)
Please add the following to the response given in LAC-6853:
"The environmental qualifications of mechanical equipment outside containment are being reviewed under Systematic Evaluation Program (SEP) Topic III-12."
NRC REQUES1:
2.1. 6. a (2)
(Refer to DPC Letter LAC-6853 dated April 9, i;80)
Change the second sentence to read:
'" Location "a, b, and c" all sample water from the bottom of the reactor vessel and would be the normal sample points."
NRC REQUEST:
2.1. B. a (3)
(Refer to DPC Letter LAC-6833 dated April 9, 1980)
Change the last part of the second sentel.ce to read:
"...... and 1.16 inches of steel."
NRC REQUEST:
2.1.S.b(2)
(Refer to DPC Letter LAC-6853 dated April 9, 1980)
Change the last sentence of the first paragraph to read:
"They are powered from the Turbine Building 120 Volt Regulated Bus, which is supplied by the Emergency Diesel Generator lA."
Add a last sentence to this section:
"DPC is considering the upgrading of iodine and particulate. effluent sampling capability by the purchase of an Eberline Model SPING 4 or equivalent." !