ML19207B854
| ML19207B854 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 08/28/1979 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| LAC-6484, NUDOCS 7909050432 | |
| Download: ML19207B854 (12) | |
Text
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D.SIItYLitND POWEll C00PEft.1TIVE Ba Crone 0Yisconsin 54601 August 28, 1979 In reply, please refer to LAC-6484 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 SU3 JECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 SPECIAL REPORT NO. 79-02
Reference:
(1)
LACBWR Technical Specifications, Section 4.2.2.22, Action g.
(2)
LACBWR Technical Specifications, Section 3.9.4.1.
Dear Mr. Keppler:
In accordance with the provisions of Reference (1), a Special Report conforming to the requirements set forth in Reference (2) is submitted covering results of sampling and analysis actions together with additional operational information for five separate occasions when reactor thermal power changed by more than 15% of rated thermal power within one hour while in Oper-ational Condition 1 or 2.
The saparate occasions are discussed in Sections as follows:
Section 1 - May 30, 1979 Section 2 - June 1, 1979 Section 3 - June 18, 1979 Section 4 - July 3, 1979 Section 5 - July 7, 1979 Each section provides a summary of operating data and radiological O Vtbd^
7909050 h/ rg f
Mr. James G.
Keppler LAC-6484 Regional Director August 28, 1979 data for the time period prior to the thermal power change, along with the results of the additional sampling required.
If there are any questions concerning the report, please con-tact us.
Very truly yours, DAIRYLAND POWER COOPERATIVE Frank Linder, General Manager FL:LGP:af Attachment cc:
Director, Office of Inspection and Enforcement (30)
U.
S.
Nuclear Regulatory Commission Washington, D.
C.
20555 Director, sffice of Management Information and (3)
Program Control U.
S.
Nuclear Regulatory Commission Washington, D.
C.
20555 OId$.I$.8
Special Report No. 79-02 INTRODUCTION LACBWR Technical Specifications Section 4.2.2.22, Action g, requires sampling and analysis for Iodine-131, 133 and 135, as well as gross beta and gamma activity between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following a thermal power change of greater than 15% of rated thermal power within one hour.
This special report is required to contain the information determined by the analysis plus additional information regarding reactor power history, fuel burnup, cleanup flow history, off-gas activity levels and gross alpha activity levels.
Section 1 A reactor scram occurred at 1738 hours0.0201 days <br />0.483 hours <br />0.00287 weeks <br />6.61309e-4 months <br /> on May 30, 1979 due to a loss of control power.
A shorted coil in relay K103/1 caused rod control power fuse FB-55(2) to fail which in turn de-energized the all-rod scram relays resulting in an all-rod scram.
The reactor was operating at 30% of rated thermal power (9 MWe-net) at the time of the scram.
Gross By Activity and Iodine Analysis Time of Sample:
2008 Hours, 5/30/79 Sample Results:
Gross By:
4.89 x 10-1 pCi/ gram I l31:
1.072 x 10~3 pCi/ gram I l33:
1.803 x 10-2 pCi/ gram I 135:
2.586 x 10-2 pCi/ gram Additional Information:
1.
Reactor Thermal Power Level starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the Thermal Power Change:
Reactor shut down at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />, 5/28/79.
Reactor taken critical at 1825 hours0.0211 days <br />0.507 hours <br />0.00302 weeks <br />6.944125e-4 months <br />, S/28/79.
1825, 5/28/79 - 1200, 5/29/79:
0-15% (escalation) 1200-2400, 5/29/79:
15-29% (escalation) 0000-1200, 5/30/79:
29%
1200-1700, 5/30/79:
29-31%
2.
The approximate fuel burnup of assemblies in a symmetrical core region is depicted in Figure 1. 3.M123
Special Report No. 79-02 3.
Cleanup Flow History starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the Thermal Power Change:
Primary Purification Flow Rate 1700-2300, 5/28/79:
System shut down 2300, 5/28/79 - 1700, 5/30/79:
40-41 gpm Primary Purification Deco.itamination Factors (By) 5/28/79:
95.1/1 6/4/79:
734.2/1 4.
Of f-Gas Activity Levels for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to Thermal Power Change:
1600 hrs., 5/29/79:
116.7 Ci/d 0000-0800 hrs., 5/30/79:
182 Ci/d 0800-1600 hrs., 5/30/79:
93 Ci/d 5.
Gross Alpha Activity Level starting with the last sample taken prior to the Thermal Power Change:
0114 hrs., 5/30/79:
9.18 x 10-7 pCi/ gram 1738 hrs., 5/30/79:
Thermal Power Change 2008 hrs., 5/30/79:
2.39 x 10-6 pCi/ gram Section 2 A reactor scram occurred at 2220 hours0.0257 days <br />0.617 hours <br />0.00367 weeks <br />8.4471e-4 months <br /> on June 1, 1979, due to closure of the Main Steam Isolation Valve (MSIV).
The closure was attributed to two loose wires on Relay SK18/l which is part of the valve control circuitry.
The reactor was operating at 39% of rated thermal power at the time of scram.
Gross By Activity and Iodine Analysis Time of Sample:
0140 Hours, 6/2/79 Sample Results:
Gross By:
0.407 pCi/ gram I l31:
1.53 x 10-3 pCi/ gram Il33:
1.34 x 10-2 uCi/ gram I 135:
1,406 x 10-2 uCi/ gram 314 24
Special Report No-79-02 Additional Information 1.
Reactor Thermal Power Level starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the Thermal Power Change:
1200-1700, 5/30/79:
29-31%
1738, 5/30/79:
Reactor Scram 1738, 5/30/79 - 0325, 5/31/79:
Reactor Shutdown 0325-2400, 5/31/79:
0-32% (escalation) 0000-2200, 6/1/79:
32-39% (escalation) 2.
The approximate fuel burnup of assemblies in a symmetrical core region is depicted in Figure 1.
3.
Cleanup Flow History starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the Thermal Power Change:
Primary Purification Flow Rate 2200, 5/30/79 - 0600, 5/31/79:
System shut down 0600, 5/31/79 - 2200, 6/1/79:
39-41 gpm Primary Purification Decontamination Factors (Sy) 5/28/79:
95.1/1 6/4/79:
734.2/1 4.
Off-Gas Activity Levels for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to Thermal Power Change:
0800-1600 hrs., 5/30/79:
93 Ci/d 1600-2400 hrs., 5/30/79:
Reactor Scram at 1738 hrs.
0000-0800 hrs., 5/31/79:
Reactor Startup/ Escalation OS
-1600 hrs., 5/31/79:
0-95 Ci/d 1600-2400 hrs., 5/31/79:
110 Ci/d 0000-0800 hrs., 6/1/79:
110 Ci/d 0800-1600 hrs., 6/1/79:
122 Ci/d 5.
Gross Alpha Activity Level starting with the last sample taken prior to the Thermal Power Change:
0047 hrs., 6/1/79:
4.66 x 107 uCi/ gram 2200 hrs., 6/1/79:
Thermal Power Change 0133 hrs., 6/4/79:
1.328 x 10-6 uCi/ gram fjkM' 5 2
Special Report 79-02 Section 3 A reactor scram occurred on June 18, 1979 at 1110 hours0.0128 days <br />0.308 hours <br />0.00184 weeks <br />4.22355e-4 months <br /> due to personnel action while performing maintenance on a multipoint recorder.
A momentary short circuit induced a signal to close the Main Steam Isolation Valve (MSIV) which caused the automatic reactor scram.
The reactor was operating at 92% of rated thermal power at the time of scram.
Gross By Activity and Iodine Analysis Time of Sample:
1340 Hours, 6/18/79 Sample Results:
Gross Sy:
1.05 pCi/ gram I l31:
1.428 x 10-3 uCi/ gram I l33:
1.517 x 10-2 pCi/ gram Il35:
2.02 x 10-2 pCi/ gram Additional Information 1.
Reactor Thermal Povar Level starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the Thermal Power Change:
1100, 6/16/79 - 1100, 6/18/79:
87-92% (slow escalation) 2.
The approximate fuel burnup of assemblies in a symmetrical core region is depicted in Figure 2.
3.
Cleanup Flow History starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the Thermal Power Change:
Primary Purification Flow Rate 1100 hrs., 6/16/79 - 1100 hrs., 6/18/79:
41-42 gpm Primary rurification Decontamination Factors (Sy) 6/18/79 (prior to scram):
1360/1 6/21/79: 1421/1 4.
Off-Gas Activity Levels for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to Thermal Power Change:
0800-1600 hrs., 6/16/79:
497 Ci/d 1600-2400 hrs., 6/16/79:
497 Ci/d 0000-0800 hrs., 6/17/79:
516 Ci/d 0800-1600 hrs., 6/17/79:
600 Ci/d 1600-2400 hrs., 6/17/79:
582 Ci/d G000-0800 hrs., 6/18/79:
613 Ci/d g,yg
Special Report No. 79-02 5.
Gross Alpha Activity Level starting with the last sample taken prior to the Thermal Power Change:
0107 hrs., 6/18/79:
- 4. 3 3 x 10- 7 pCi/ gram 1110 hrs., 6/18/79:
Thermal Power Change 0228 hrs., 6/19/79:
1.49 x 10-6 pCi/ gram Section 4 A reactor scram occurred at 1520 hours0.0176 days <br />0.422 hours <br />0.00251 weeks <br />5.7836e-4 months <br /> on July 3, 1979, due te closure of the Main Steam Isolation Valve (MSIV).
The closure was indirectly initiated by personnel action when a fuse was removed from an instrumentation circuit for maintenance purposes.
Gross By Activity and Iodine Analysis Time of Sample:
1809 IIours, 7/3/79 Sample Results:
Gross By:
0.876 Ci/ gram I131:
1.502 x 10-2 uCi/ gram Il33:
1.460 x 10-1 pCi/ gram I135: < 6. 9 7 x 10 3 uCi/ gram Additional Information 1.
Reactor Thernal Power Level starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the Thermal Power Change:
1500 hrs., 7/1/79 - 1520 hrs., 7/3/79:
92-93%
2.
The approximate fuel burnup of assemblies in a symmetrical core region is depicted in Figure 3.
3.
Cleanup Flow History st:-iting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the Thermal Power Change:
Primary Purification Flow Rate 1500 hrs., 7/1/79 - 1520 hours0.0176 days <br />0.422 hours <br />0.00251 weeks <br />5.7836e-4 months <br />, 7/3/79:
41 gpm Primary Purification Decontamination Factors (Sy) 7/2/79:
1469/1 7/9/79:
1260/1 314127
Special Report No. 79-02 4.
Off-Gas Activity Levels for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to Thermal Power Change:
0800-1600 hrs., 7/1/79:
495 Ci/d 1600-2400 hrs., 7/1/79:
527 Ci/d 0000-0800 hrs., 7/2/79:
516 Ci/d 0800-1600 hrs., 7/2/79:
522 Ci/d 1600-2400 hrs., 7/2/79:
491 Ci/d 0000-0800 hrs., 7/3/79:
493 Ci/d 0800-1500 hrs., 7/3/79:
563 Ci/d 5.
Gross Alpha Activity Level starting with the last sample taken prior to the Thermal Power Change:
0140 hrs., 7/2/79:
6.51 x 10-7 pCi/ gram 1520 hrs., 7/3/79:
Thermal Power Change 1004 hrs., 7/6/79:
3.46 x 10-7 pCi/ gram Section 5 At 1837 hours0.0213 days <br />0.51 hours <br />0.00304 weeks <br />6.989785e-4 months <br /> on July 7, 1979, a reactor scram occurred at a power level of 75% of rated thermal power.
A condition of low seal injection differential pressure, which was a result of a faulty differential pressure transmitter, tripped both forced circulation pumps which prompted the safety system to scram the reactor.
Gross By Activity and Iodine Analysis Time of Sample:
2047 hours0.0237 days <br />0.569 hours <br />0.00338 weeks <br />7.788835e-4 months <br />, 7/7/79 Sample Results:
Gross By:
0.876 pCi/ gram I l31:
2.178 x 10-3 pCi/ gram I 133:
8.073 x 10-3 pCi/ gram I l34:
6.017 x 10-2 pCi/ gram Additional Information 1.
Reactor Thermal Power Level starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the Thermal Power Change:
2200 hrs., 7/4/79 - 1955 hrs., 7/5/79:
Reactor Shut Down 1955 hrs., 7/5/79 - 0800 hrs., 7/6/79:
0-28% (Reactor Startup) 0800-1600 hrs., 7/6/79:
28-51% (Escalation) 1600-2400 hrs., 7/6/79:
51-58% (Escalation) 0000-0800 hrs., 7/7/79:
58-67% (Escalation) 0800-1800 hrs., 7/7/79:
67-75% (Escalation) 6-01d Ud8 i
Special Report No. 79-02 2.
The approximate fuel burnup of assemblies in a symmetrical core region is depicted in Figure 3.
3.
Cleanup Flow IIistory starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the Thermal Power Change:
Primary Purification Flow 1800-2200 hrs., 7/5/79:
System Shut Down 2200 hrs., 7/5/79 - 1800 hrs., 7/7/79:
40-41 gpm Primary Purification Decantamination Factors (Sy) 7/2/79:
1469/1 7/9/79:
1260/1 4.
Off-Gas Activity Levels for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to Thermal Power Change:
1600 hrs., 7/5/79 - 1600 hrs., 7/6/79:
Reactor Startup/ Escalation in Progress 1600-2400 hrs., 7/6/79:
210 Ci/d 0000-0800 hrs., 7/7/79:
247 Ci/d 0800-1600 hrs., 7/7/79:
324 Ci/d 5.
Gross Alpha Activity Level starting with the last sample taken prior to the Thermal Power Change:
1004 hrs., 7/6/79:
3.46 x 10-7 pCi/ gram 1837 hrs., 7/7/79:
Thermal Power Change 1024 hrs., 7/8/79:
4.26 x 10-7 pCi/ gram 33.d$ Id3 Quarter Core Fuel Exposure Estimation (GWD,MTU)
.As An Indication of Regional Exposure as of May 31, 1979.
Core Average Exposure:
4.214 GWD/MTU.
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, Quarter Core Fuel Exposure Estimation (GWD/MTU) As An Indiration of Regional Exposure as of July 3, 1976. Core Average Exposure: 4.691 MWD /MTU A B C D E F G H K L I b2(l~D 2 L /4 ~2=J IQ C/C))@[y]_] Id6 =d b/.o@c ro 4 Ii TI j f L U, $ _ -- - = 2.- = -I ( ~ -- :"I C- [=".,.q -- _] ~ = M =- --)) l ---- ;j-)@,t;_. j,L__ _ a t ___ l [.__ j i--- "2$1 II L_---- ,L - /__ _ ) (___y = __ __g _ 7__ 9 7') I l (M 052D S*(eil7 c.S67 (2.e37 0 l 'l L_. J J m_ # L__. __ _I k.=-m= _,f4i k _ l,b__m_.,,S _] __m ['_T 4,T__1 L _ _.,Io _ _J i i i l J ' ll = ; ul 0.W9 fZg . Sn 1
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