|
|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20235S2441989-02-16016 February 1989
Suppl to 880104 Special Rept Re Inoperability of High Pressure Svc Water Diesel 1B.Fuel Supplu Sys Was Source of Problem.Fuel Supply Sys Will Be Replaced W/Above Ground Tanks for Both Diesels
ML20237C6781987-11-30030 November 1987
Special Rept:On 871118,internal Portion of Fire Suppression Water Sys Removed from Svc to Replace Section of Piping.On 871120,piping Successfully Hydrostatically Tested & Fire Suppression Sys Returned to Svc
ML20236W2731987-11-23023 November 1987
Special Rept:On 871028,following Initiation of 24 H Run for 18-month Diesel Generator Test,Emergency Diesel Generator 1B Stopped Running.No Cause for Trip Determined.Procedure Will Be Revised So Alarm Conditions Tested Before Run
ML20236X0081987-11-18018 November 1987
Special Rept Re Inoperability of Fire Suppression Water Sys. Internal Portion of Sys Removed from Svc on 871118 to Replace Section of Piping.Initially Reported on 871118.Plant Permanently Shut Down & Reactor Defueled
ML20236Y2151987-05-15015 May 1987
Special Rept 87-02:on 870216,reactor Manually Scrammed Due to Erroneous Indication of Low Voltage on Turbine Bldg MCC1A.On 870406,reactor Power Dropped Following Trip of 1A Forced Circulation Pump
ML20211E4971986-06-0404 June 1986
Special Rept 86-02:on 860307 & 0525,thermal Power Changed by Greater than 15% of Rated Thermal Power within 1 H on Three Occasions.Caused by Bus 1B Power Loss,Reactor Forced Circulation Pump Trip & Control Air Sys
ML20138B7861986-03-11011 March 1986
Special Rept:On 860311,internal Portion of High Pressure Svc Water Sys Which Supplies Fire Suppression Sys Removed from Svc to Replace Valve Required to Be Tested by Inservice Testing Program
ML20141P1241986-03-0606 March 1986
Incident Rept DPC-86-1:on 860104,seal Inject Supply Line Separated at Swagelock Fitting,Spraying Water & Resulting in Reactor Shutdown.Cause Unknown.Mechanical Seal on CRD 2 Reworked
ML20138L8431985-10-21021 October 1985
Special Rept 85-02:on 850725,0909 & 14,reactor Thermal Power Changed by More than 15% of Rated Thermal Power within 1 H. Power History,Fuel Burnup,Cleanup Flow History,Offgas Activity Levels & Gross Alpha Activity Levels Discussed
ML20138L7451985-10-0808 October 1985
Special Rept:Discusses Circumstances Which Led to Inaccuracies in Personnel Cumulative Lifetime Dose Records. Cumulative Permanent Doses in Radiation Dosimetry Rept Do Not Agree W/Records Maintained in Computer File
ML20128N9141985-07-18018 July 1985
Special Rept 85-01:providing Results of Sampling & Analysis Actions & Addl Operational Info for Six Occasions When Reactor Thermal Power Changed by More than 15% of Rated Thermal Power within 1 H
ML20062D1601982-07-26026 July 1982
Ro:On 820726,internal Portion of Fire Suppression Water Sys Removed from Svc in Order to Replace Fire Hose Cabinets Rendering Fire Suppression Water Sys Inoperable.Backup Capability Provided
ML20054F1711982-06-0707 June 1982
RO 82-14:on 820605,w/reactor in Operating Condition 2 at 50 X 10-6% Power,Review of Shift Supervisor Log Revealed Primary Water Alpha Activity of 7.46 X 10-6 Uci/Gm.Reactor Shutdown Conducted 820605 in Accordance W/Tech Spec
1989-02-16
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20210A6361999-04-30030 April 1999
Rev 13 to Quality Assurance Program Description
ML20206J3751999-04-29029 April 1999
Rev 13 to QA Program Description
ML20207A9591999-01-31031 January 1999
Revised LACBWR Decommissioning Plan
ML20196G0751998-12-31031 December 1998
1998 Annual Rept for Dairyland Power Cooperative
ML20204D8371998-12-31031 December 1998
Annual Rept for 1998 - Rept of Changes,Tests & Experiments for Lacbwr. with
ML20237E2701998-07-31031 July 1998
Rev 12 to QA Program Description
ML20196A9241998-07-31031 July 1998
Rev 12 to LACBWR QA Program Description (Qapd)
ML20202J0691998-01-31031 January 1998
Revised LACBWR Decommissioning Plan
ML20202J0781998-01-31031 January 1998
Revised LACBWR Initial Site Characterization Survey for Safstor
ML20203K0041997-12-31031 December 1997
Annual Operating Rept for 1997 - Rept of Changes,Tests & Experiments
ML20249B7101997-12-31031 December 1997
Navigating for Our Future Dairyland Power 1997 Annual Rept. W/O Ltr
ML20138B7771997-04-25025 April 1997
Corrected Page 8 of SE for Amend 69 to La Crosse Boiling Water Reactor License
ML20137R7731997-04-11011 April 1997
Safety Evaluation Approving Changes to QAP Description
ML20149K2071996-12-31031 December 1996
Conquering New Frontiers,Dairyland Power Cooperative 1996 Annual Rept
ML20135C3901996-12-31031 December 1996
Annual Rept for 1996 - Rept of Changes,Tests & Experiments
ML20132F8721996-10-31031 October 1996
Revised LACBWR Decommissioning Plan
ML20134M2531996-02-20020 February 1996
Revised Rev 11 to QA Program Description
ML18012A9001995-12-31031 December 1995
Annual Rept - 1995 of Changes,Tests & Experiments. W/ 960220 Ltr
ML18011B1461995-04-20020 April 1995
LER 95-001-00:on 950417,noted That HPSW to Containment Building Isolated.Caused by Momentary LOP Due to Operational Test of 1A Edg.Procedures for Test Being Modified to Include Instructions to Verify Value Being open.W/950420 Ltr
ML20056E2631993-08-10010 August 1993
LACBWR Containment Bldg Structural Analysis. W/One Oversize Drawing
ML20056E2621993-07-31031 July 1993
Nonproprietary Analysis of Potential Blast Effects on LACBWR Reactor Bldg Due to 16 Inch Natural Gas Pipeline Failure,Suppl Analysis for Fast Closing Valve
ML20127D3901993-01-13013 January 1993
SE Supporting Amend 67 to License DPR-45
ML20128K6011992-12-31031 December 1992
Corrected App a Re Std Format for Reporting Number of Personnel & man-rem by Work & Job Function,To Annual Rept for 1992 - Rept of Changes,Tests & Experiments
ML20128D3421992-12-31031 December 1992
LACBWR Annual Rept 1992
ML20062B4761990-09-30030 September 1990
Monthly Operating Rept for Sept 1990 for LACBWR
ML20248D0941989-08-31031 August 1989
Monthly Operating Rept for Aug 1989 for LACBWR
ML20245G6571989-07-31031 July 1989
Monthly Operating Rept for Jul 1989 for LACBWR
ML20245F9681989-06-30030 June 1989
Monthly Operating Rept for June 1989 for LACBWR
ML20245J7351989-04-26026 April 1989
Safety Evaluation Supporting Amend 65 to License DPR-45
ML20245F8241989-02-28028 February 1989
Monthly Operating Rept for Feb 1989 for La Crosse Bwr.W/
ML20235S2441989-02-16016 February 1989
Suppl to 880104 Special Rept Re Inoperability of High Pressure Svc Water Diesel 1B.Fuel Supplu Sys Was Source of Problem.Fuel Supply Sys Will Be Replaced W/Above Ground Tanks for Both Diesels
ML20245F7771989-01-31031 January 1989
Monthly Operating Rept for Jan 1989 for LACBWR
ML20246H8771988-12-31031 December 1988
1988 Dairyland Power Cooperative Annual Rept
ML20205T1271988-10-31031 October 1988
Monthly Operating Rept for Oct 1988 for La Crosse Bwr.W/
ML20151T0991988-08-0808 August 1988
Safety Evaluation Supporting Approval of Util Rev 10 to Emergency Plan
ML20150D7051988-07-0808 July 1988
Safety Evaluation Supporting Rev 10 to Emergency Plan
ML20155F9161988-05-31031 May 1988
Safety Evaluation Supporting Amend 62 to License DPR-45
ML20151G0591988-04-11011 April 1988
Safety Evaluation Supporting Amend 60 to Provisional License DPR-45
ML20148C3941988-03-15015 March 1988
Safety Evaluation Supporting Amend 59 to License DPR-45
ML20149G0711988-01-0404 January 1988
Safety Evaluation Supporting Amend 58 to License DPR-45
ML20147A9731987-12-31031 December 1987
Decommissioning Plan
ML20149J3441987-12-31031 December 1987
LACBWR Annual Rept 1987
ML20195D7811987-12-31031 December 1987
1987 Dairyland Power Cooperative Annual Rept
ML20237C6781987-11-30030 November 1987
Special Rept:On 871118,internal Portion of Fire Suppression Water Sys Removed from Svc to Replace Section of Piping.On 871120,piping Successfully Hydrostatically Tested & Fire Suppression Sys Returned to Svc
ML20236W2731987-11-23023 November 1987
Special Rept:On 871028,following Initiation of 24 H Run for 18-month Diesel Generator Test,Emergency Diesel Generator 1B Stopped Running.No Cause for Trip Determined.Procedure Will Be Revised So Alarm Conditions Tested Before Run
ML20236X0081987-11-18018 November 1987
Special Rept Re Inoperability of Fire Suppression Water Sys. Internal Portion of Sys Removed from Svc on 871118 to Replace Section of Piping.Initially Reported on 871118.Plant Permanently Shut Down & Reactor Defueled
ML20234C3931987-10-20020 October 1987
Rev 5 to QA Program Description
ML20151B2351987-10-20020 October 1987
Revised Rev 5 to QA Program Description
ML20235R0531987-09-30030 September 1987
Determination of Potential Radiological Consequences to Members of Public from Fuel Handling Accident at La Crosse Nuclear Facility
ML20235B5711987-09-15015 September 1987
Safety Evaluation Supporting Amend 57 to License DPR-45
1999-04-30
[Table view] |
Text
_
a p
D DA/RYLAND
_/ h [k COOPERAT/VE eO BOxsi7 .
2sts EAST AV SOUTH = LA CROSSE WISCONSIN 54601 October 21, 1985 (608) 788 4 000 In reply, please refer to LAC-lll97 DOCKET No. 50-409 Mr. James G. Keppler, Regional Administrator U. S. Nuclear Regulatory Commission PMMITY @Sll@.
Directorate of Regulatory Operations {E hy Region III 799 Roosevelt Road Eo Q .. ' %
Glen Ellyn, IL 60137 4{ -QL-pF7 t%
'p l it 7 tm
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR @
PROVISIONAL OPERATING LICENSE NO. DPR-45 SPECIAL REPORT 85-02
Reference:
(1) LACBWR Technical Specifications Section 4.2.2.22, Action g.
Dear Mr. Keppler:
In accordance with the provisions of Reference (1), a Special Report is submitted covering results of sampling and analysis actions together with additional operational information for three separate occasions when reacto.
thermal power changed by more than 15% of Rated Thermal Power within one hour while in Operational Condition 1 and 2.
The separate occasions are discussed in sections 1, 2 and 3 as follows:
SECTION 1 July 25, 1985 SECTION 2- -September 9, 1985 SECTION 3-- -September 14, 1985 >
Each section provides a summary of operating data and radiological data for the time period prior to the thermal power change along with the results of the additional samplitg required.
If there are any questions concerning this report, please contact us.
Sincerely, 8510310423 851021 DAIRYLAND POWER COOPERATIVE PPR ADOCK 05000409 g PDR James W. Taylor General Manager JWT:PDB:sks Attachments 4 l
407251985 N' WPl.8.1 LEM
r 9
Mr. James G. Keppler, Regional Administrator October 21, 1985 U. S. Nuclear Regulatory Commission LAC-lll97 cc: Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555 Document Control Desk i
U. S. Nuclear Regulatory Commission l
Wachington, DC 20555 Resident Inspector l
l WPl.8.1 i
INTRODUCTION SPECIAL REPORT 85-03 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 ga ama 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 greatet 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, offgas activity levels and gross alpha activity levels.
SECTION 1 At 1115 on July 25, 1985, the reactor scrammed from 96.5% power due to a ground in the gas pressure scram circuit on the Control Rod Drive No. 8.
GROSS 4-y ACTIVITY AND IODINE ANALYSIS Time of Sample: 1322, 07/25/85 Sample Results: Gross a-Y - .0791 pCi/ml I-131 -1.04 x 10-3 pCi/ml I-133- -2.69 x 10-3 pCi/ml 1-135 -------1.09 x 10-3 pCi/ml ADDITIONAL INF0DiATION (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 thermal power change:
1115, 07/23/85 - 1115, 07/25/85-- ~ 96%.
(2) The approximate fuel burnup of assemblies in a symmetrical core region is shown 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 thermal power change:
Primary Purification Flow Rate 1115, 07/23/85 - 1115, 07/25/85 --42 gpm.
Primary Purification Decontamination Factors (d-Y) 0152, 07/25/85 -
-- 1126:1 0205, 07/29/85 --
737:1 1
(
WPl.8.1
i (4) Offgas Activity Levels Starting 48 Hours Prior to Thermal Power Change:
0800-1600 07/23/85 ---- - -- 152 Ci/ day 1600-2400, 07/23/85 - 148 Ci/ day 0000-0800, 07/24/85 --- -- - 157 Ci/ day J 0800-1600, 07/24/85 ------== =-- - 146 Ci/ day J 1600-2400, 07/24/85 ----- 146 Ci/ day 0000-0800, 07/25/85 --- --- 146 Ci/ day (5) Gross Alpha Activity Level Starting With Sample Prior to Thermal Power Change:
0154, 07/25/85 ------ ------------ < 4.86 x 10-8 pCi/ml 1115, 07/25/85 --
Rated Thermal Power Change 0205, 07/29/85 - -
- 1.09 x 10-7 pCi/ml WPl.8.1 L
SECTION 2 At 0210 on September 9, 1985 the 1A FCP Discharge Valve closed due to an erroneous Forced Circulation Loop A Temperature signal. The reactor power dropped from 96% to 68%.
GROSS o-y ACTIVITY AND IODINE ANALYSIS Time of Sample: 0557, 09/09/85 Sample Results: Gross s-y .204 LCi/ml 1-131 ---9.20 x 10-4 uCi/ml 1-133- ----- --1.15 x 10-2 pCi/ml I-135---- - - 2.47 x 10-2 pCi/ml 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 thermal power change:
0210, 09/07/85 - 0210, 09/09/85 ~ 96%.
(2) The approximate fuel burnup of assemblies in a symmetrical core region is shown 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 thermal power change:
Primary Purification Flow Rate 0210, 09/07/85 - 0210, 09/09/85 -- 42 gpm.
Primary Purification Decontamination Factors (8-Y) 0207, 09/09/85 -- ----
828:1 0118, 09/12/85 -- 740:1 (4) Of fgas Activity Levels Starting 48 Hours Prior to Thermal Power Change:
0000-0800, 09/07/85 ------
147 Ci/ day 0800-1600, 09/07/85 -
--- 149 Ci/ day 1600-2400, 09/07/85 ------
145 Ci/ day 0000-0800, 09/08/85 ----- ---
145 Ci/ day 0800-1600, 09/08/85 145 C1/ day 1600-2400, 09/08/85 --------- 150 Ci/ day (5) Gross Alpha Activity Level Starting With Sample Prior to Thermal Power Change:
0208, 09/09/85 -------------- < 4.66 x 10-8 pCi/ml 0210, 09/09/85 ---Rated Thermal Power Change 0122, 09/12/85 -- 1.29 x 10-7 pCi/ml WP1.8.1
7 e
9 4
i 4
I I
l f
T .
SECTION 3
( At 1555 on September 14, 1985 the reactor scrammed from 96% power due to High l
Reactor Water Level when power was lost to an Irstrument Bus in the Control
! Room.
GROSS J-Y ACTIVITY AND IODINE ANALYSIS Time of Sample: 1850, 09/14/85 Sample Results: Gross d-Y --- .116 pCi/ml I-131 ----1.14 x 10-3 pCi/ml
( I-133 ----9. .c 3 x 10-3 pCi/ml I-135 --
-1.21 x 10-2 pCi/ml ADDITIONAL INFORMATION (1) Reacter 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 thermal power change:
l 1555, 09/07/85 - 1555, 09/09/85 -- --
~ 96%.
(2) The approximate fuel burnup of assemblies in a symmetrical core region is shown 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 thermal power change:
Primary Purification Flow Rate 1555, 09/07/85 - 1555, 09/09/85 42 spm.
Primary Purification Decontamination Factors (d-Y) 0118, 09/12/85 ------ -
740:1 0111, 09/16/85 - - -- ----=--- -
689:1 (4) Offras Activity Levels Starting 48 Hours Prior to Thermal Power Change:
0800-1600, 09/12/85 -- 144 Ci/ day l 1600-2400, 09/12/85 -- -
145 Ci/ day 0000-0800, 09/13/85 ---- ---
148 Ci/ day 0800-1600, 09/13/85 ---
-- 137 Ci/ day 1600-2400, 09/13/85 --
- 149 Ci/ day 0000-0800, 09/14/85 - 149 Ci/ day 1
(5) Gross Alpha Activity Level Starting With Sample Prior to Thermal Power Chano e:
0122, 09/12/85 -
1.29 x 10-7 pCi/ml 1555, 09/14/85 -----------
-Rated Thermal Power Change 0114, 09/16/85 - 1.00 x 10-7 pCi/ml WP1.8.1
e A B C D E F G H K L
/
I PC I I(7 -
i _ /f 9 -
i /A I@l_
/T I 3 ~
I 69 _
l 19WF 8 I 4 _ _ _
I .?% I i 2 t@F'3'9 I /M I 5 L _ _ _
I 247 F' / gtg77
_Le 1 9
6 ~
12.4 3.5 ~
ll.8 3.0
~
16.6 L___.
l 1
65 1 l 4 1 I /c ' i 7 3.l la.9 3.4 15 ]
hl I? 1 I // lhl /( '
I 8 _ _
11.3 3.3 _
10.1 95 l #1 I I ?P l A f>d l
1@ I
a.8 19.7 I3.5 tu f
QL> T
/0 tro.s I
v IN CORE FLUX MONITORS Q
. PLANT yQQ[g Quarter Core Fuel Exposure Distribution (GWD/MTU) as of September 9, 1985. The Core Average Exposure is 9.921 GWD/MTU.
j FIGURE 2
)
i I
1
_ __ ._ _ - __ . _ _ . _ . _ _ _ _-. _ _ _ .. _ _.-- _ .__...~__ _ .. _ .
