Environ Event Rept 80-02:on 800513-14,reclaiming Ion Exchanger Out of Svc When Steam Generator Blowdown Water Discharged Into River.Sample of Outfall Revealed Ph Value Greater than 8.5.Caused by Seasonal Change of River| ML19323G941 |
| Person / Time |
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| Site: |
Prairie Island  |
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| Issue date: |
06/04/1980 |
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| From: |
Ward E
NORTHERN STATES POWER CO. |
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| To: |
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| References |
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| NUDOCS 8006090289 |
| Download: ML19323G941 (2) |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML19320C3261980-07-0101 July 1980
RO 80-18:on 800629,steam Generator 12 Experienced Minor primary-to-secondary Leakage of About 0.006 Gallons Per Minute.Leakage Was Carefully Monitored & Showed Increase. Facility Is Shutdown.Cooldown Is Planned
ML19309G7291980-04-30030 April 1980
RO 80-15:on 800429,volumetric Test of Facility Containment Main Airlock Showed Leakge of 600 Scc/Minute,Exceeding Tech Specs.Caused by Opening of Inner Airlock Door.Seals for Inner Door Were Replaced.Leakage Was Acceptable
ML19296A6521980-01-24024 January 1980
RO-80-06:on 800123,diesel Generator D2 Tripped on High Crankcase Pressure When Crankcase Eductor Supply Pipe Came Loose.During Operability Testing of Other Diesel Generates, Jacket Coolant Hose on Water Pump Ruptured
ML19291C1991980-01-15015 January 1980
Supplemental Info to RO 80-3.One Tube Defective on Steam Generator Hot Leg 21.One Tube Defective & Ten Tubes Degraded on Cold Leg 21.Hot Leg 22 to Be Inspected.Four Tubes Defective & 42 Degraded on Cold Leg 22.Cause Unknown
ML19210C6831979-11-0101 November 1979
Environ Event Rept 79-10 Re Operation of Circulating Water Sys in Partial Recycle Mode W/Daily Average Blowdown Flow in Excess of 150 Cfs.Higher Flow Required to Maintain Cooling Water Inlet Temps at Less than 85 F
ML19209B7041979-10-0303 October 1979
RO 79-27:on 791003,reactor Tripped on Low Pressurizer Pressure Followed by Safety Injection & Containment Isolation.Caused by Steam Generator Tube Leakage.Failed Tubes Will Be Plugged & Inspected
1980-07-01
[Table view]
Category:LER)
MONTHYEARML19320C3261980-07-0101 July 1980
RO 80-18:on 800629,steam Generator 12 Experienced Minor primary-to-secondary Leakage of About 0.006 Gallons Per Minute.Leakage Was Carefully Monitored & Showed Increase. Facility Is Shutdown.Cooldown Is Planned
ML19309G7291980-04-30030 April 1980
RO 80-15:on 800429,volumetric Test of Facility Containment Main Airlock Showed Leakge of 600 Scc/Minute,Exceeding Tech Specs.Caused by Opening of Inner Airlock Door.Seals for Inner Door Were Replaced.Leakage Was Acceptable
ML19296A6521980-01-24024 January 1980
RO-80-06:on 800123,diesel Generator D2 Tripped on High Crankcase Pressure When Crankcase Eductor Supply Pipe Came Loose.During Operability Testing of Other Diesel Generates, Jacket Coolant Hose on Water Pump Ruptured
ML19291C1991980-01-15015 January 1980
Supplemental Info to RO 80-3.One Tube Defective on Steam Generator Hot Leg 21.One Tube Defective & Ten Tubes Degraded on Cold Leg 21.Hot Leg 22 to Be Inspected.Four Tubes Defective & 42 Degraded on Cold Leg 22.Cause Unknown
ML19210C6831979-11-0101 November 1979
Environ Event Rept 79-10 Re Operation of Circulating Water Sys in Partial Recycle Mode W/Daily Average Blowdown Flow in Excess of 150 Cfs.Higher Flow Required to Maintain Cooling Water Inlet Temps at Less than 85 F
ML19209B7041979-10-0303 October 1979
RO 79-27:on 791003,reactor Tripped on Low Pressurizer Pressure Followed by Safety Injection & Containment Isolation.Caused by Steam Generator Tube Leakage.Failed Tubes Will Be Plugged & Inspected
1980-07-01
[Table view]
Category:TEXT-SAFETY REPORT
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ML20217A9931999-09-30030 September 1999
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Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers
ML20216E7151999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Pingp,Units 1 & 2. with
ML20211J2851999-08-26026 August 1999
Safety Evaluation Supporting Amends 146 & 137 to Licenses DPR-42 & DPR-60,respectively
ML20211D3981999-08-24024 August 1999
Safety Evaluation Supporting Requested Actions to Licenses DPR-42 & DPR-60,respectively
ML20211C2531999-08-0404 August 1999
Unit 1 ISI Summary Rept Interval 3,Period 2 Refueling Outage Dates 990425-990526 Cycle 19 971212-990526
ML20210Q4891999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Pingp,Units 1 & 2. with
ML20211B5971999-07-31031 July 1999
Cycle 20 Voltage-Based Repair Criteria 90-Day Rept
05000282/LER-1999-007-01, :on 990625,loss of CR Special Ventilation Function Was Noted.Caused by Broken Door Latch Pins on CR Chiller Door.Ts Amend Request to Establish Allowed OOS Time Was Submitted1999-07-23023 July 1999
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ML20209J1131999-07-15015 July 1999
Safety Evaluation of Topical Rept NSPNAD-8102,rev 7 Reload Safety Evaluation Methods for Application to PI Units. Rept Acceptable for Referencing in Prairie Island Licensing Actions
ML20209F9811999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML20196F4081999-06-23023 June 1999
Revised Pages 71,72 & 298 to Rev 7 of NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units
ML20195G5181999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With . Page 3 in Final Rept of Incoming Submittal Was Not Included
ML20207B5931999-05-26026 May 1999
SER Accepting Licensee Proposed Alternative to ASME Code for Surface Exam (PT) of Seal Welds on Threaded Caps for Unit 1 Reactor Vessel Head Penetrations for part-length CRDMs
ML20196L2501999-05-13013 May 1999
Rev 0 to PINGP Unit 1 COLR Cycle 20
05000282/LER-1999-005-01, :on 990508,containment Inservice Purge Sys Was Not Isolated During Heavy Load Movement Over Fuel.Caused by Missing Procedure Step in D58.1.6.PINGP 1224 Was Initiated to Communicate Event & Forestall Repeating Event1999-05-0808 May 1999
- on 990508,containment Inservice Purge Sys Was Not Isolated During Heavy Load Movement Over Fuel.Caused by Missing Procedure Step in D58.1.6.PINGP 1224 Was Initiated to Communicate Event & Forestall Repeating Event
ML20206L6191999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Pingp,Units 1 & 2. with
ML20205N1081999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Pingp,Units 1 & 2. with
ML20205B3351999-03-17017 March 1999
Safety Evaluation Supporting Amends 143 & 134 to Licenses DPR-42 & DPR-60,respectively
ML20205Q5101999-03-15015 March 1999
Inservice Insp Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 981109-1229 Cycle 19,970327-981229
05000306/LER-1999-001-01, :on 990206,TS Required Reactor Protection Logic Test Was Missed.Caused by Personnel Error.Sd Banks Were Inserted at 0544,RT Breakers Were Opened & Test Was Performed.With1999-03-0808 March 1999
- on 990206,TS Required Reactor Protection Logic Test Was Missed.Caused by Personnel Error.Sd Banks Were Inserted at 0544,RT Breakers Were Opened & Test Was Performed.With
ML20207J6951999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Prairie Island Nuclear Generating Plant
ML20202J7711999-02-0404 February 1999
Simulator Certification Rept for Prairie Island Plant Simulation Facility,1998 Annual Rept
ML20207L2811999-01-31031 January 1999
Revised Monthly Operating Repts for Jan 1999 for Pingp,Units 1 & 2
ML20202G3761999-01-31031 January 1999
Non-proprietary Rev 7 to NSPNAD-8102-NP, Prairie Island Nuclear Power Plant Reload SE Methods for Application to PI Units
ML20202J1731999-01-22022 January 1999
Safety Evaluation Concluding That NSP Proposed Alternative to Surface Exam Requirements of ASME BPV Code for CRD Mechanism Canopy Seal Welds Will Provide Acceptable Level of Quality & Safety
05000306/LER-1998-006-01, :on 981219,unplanned Actuation of ESF Equipment During Performance of Sp.Caused by Personnel Error.Control Room Took Prompt Action & Returned Plant to Proper Status & Second pre-job Briefing for SP-2126 Was Conducted1999-01-18018 January 1999
- on 981219,unplanned Actuation of ESF Equipment During Performance of Sp.Caused by Personnel Error.Control Room Took Prompt Action & Returned Plant to Proper Status & Second pre-job Briefing for SP-2126 Was Conducted
ML20205H0561998-12-31031 December 1998
Northern States Power Co 1998 Annual Rept. with
ML20206P7861998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Prairie Island Nuclear Generating Plant.With
ML20198J6441998-12-17017 December 1998
Rev 0 to PINGP COLR Unit 2-Cycle 19
05000306/LER-1998-005-02, :on 981109,RT from 22% Power During Planned SD Operation Was Noted.Caused by Tt.Fw Heater Drain Level Control Was Thoroughly Inspected & Calibrated.With1998-12-0909 December 1998
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ML20198L2211998-12-0707 December 1998
Safety Evaluation Supporting Amends 141 & 132 to Licenses DPR-42 & DPR-60,respectively
ML20206N2731998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With
05000282/LER-1998-016, :on 981029,negative Flux Rate RT Occurred Upon CR Insertion After Failure of CRD Cable.Caused by Internal Short Circuit Developing in CRDM Patch Cables at Reactor Head Connector.Replaced CRDM Patch Cables.With1998-11-24024 November 1998
- on 981029,negative Flux Rate RT Occurred Upon CR Insertion After Failure of CRD Cable.Caused by Internal Short Circuit Developing in CRDM Patch Cables at Reactor Head Connector.Replaced CRDM Patch Cables.With
ML20196D7341998-11-20020 November 1998
Third Quarter 1998 & Oct 1998 Data Rept for Prairie Island Isfsi
ML20195D3821998-11-0404 November 1998
Safety Evaluation Supporting Amends 140 & 131 to Licenses DPR-42 & DPR-60,respectively
ML20155K6301998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With
ML20195D3761998-10-30030 October 1998
Safety Evaluation Supporting Amends 139 & 130 to Licenses DPR-42 & DPR-60
05000306/LER-1998-004-01, :on 980910,shield Building Integrity Was Breached.Caused by Inadequate TS Change.Revised Affected Procedures.With1998-10-0505 October 1998
- on 980910,shield Building Integrity Was Breached.Caused by Inadequate TS Change.Revised Affected Procedures.With
ML20202J7991998-09-30030 September 1998
Non-proprietary Version of Rev 3 to CEN-629-NP, Repair of W Series 44 & 51 SG Tubes Using Leaktight Sleeves,Final Rept
ML20154H4061998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for Prairie Island Nuclear Generating Plant.With
ML20198R8061998-09-30030 September 1998
Rev 1 to NSPLMI-96001, Prairie Island Nuclear Generating Plant Ipeee
ML20154B9241998-09-22022 September 1998
Safety Evaluation Supporting Amends 138 & 129 to Licenses DPR-42 & DPR-60,respectively
ML20198P0571998-09-0303 September 1998
Rev 1 to 95T047, Back-up Compressed Air Supply for Cooling Water Strainer Backwash Valve Actuator
ML20153B0761998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for Prairie Island Nuclear Generating Plant.With
05000282/LER-1998-009-01, :on 980731,noted That Recent Testing of RCS Vent Paths Had Not Been Performed in Literal Compliance with Wording of TS 4.18.1.Caused by Misunderstanding of Wording in TS Section 4.18.Will Modify Surveillance Procedures1998-08-27027 August 1998
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ML20237D6491998-08-13013 August 1998
Safety Evaluation Supporting Amends 137 & 128 to Licenses DPR-42 & DPR-60,respectively
ML20237A3961998-08-11011 August 1998
Safety Evaluation on Westinghouse Owners Group Proposed Insp Program for part-length CRDM Housing Issue.Insp Program for Type 309 Welds Inadequate from Statistical Point of View
1999-09-30
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Text
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&
l' Nf3P NORTHERN STATES POWER COMPANY e MIN N E A POLt S, MI N N E SOTA 55401 June 4, 1980 Mr J G Keppler, Director, Region III Of fice of Inspection and Enforcement U S Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
Dear Mr Keppler:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 License No. DPR-42 50-306 DPR-60
,
,
Environmental Event Report 80-02 pH of Discharges TS B-2.4.3
'
Under TS B-5.4.2A we are required to report as an Environmental Event when a protection condition is exceeded. According to TS B-2.4.3 the effluent streams from the steam generator blowdown treatment system and the turbine building sumps shall be controlled to ensure that the .ater discharged at the outf all has a pH value no less than 6.5 nor greater than 8.5.
Ordinarily, the steam generator blowdown water is recycled back into the plant, however, during the period of May 13 (9:00 PM) to May 14 (11:00 PM)
= the reclaiming ion exchanger was out of service for a resin change and this blowdown was then discharged to the river. The autfall was sampled accord-ing to TS B-3.4.3 requirement.
On May 14, 1980, about 10:00 l.M the outfall pH was measured at 8.72.
Approximately 20 minutes later, the pH on the river side of the skimmer wall measured 8.69. The same day at 1:00 PM these two points were sampled again and the inlet pH measured 8.67 and the outfall measured 8.66.
Additional pH measurements were made on the river in the plant area on the same day and the results are as follows:
_pH Upstream - Main Channel Top 8.7
.
Bottom 8.6
,
Intake Channel Top 9.0 Bottom 9.0 Discharge - Main Channel Top 9.0 Bottom 9.0 Lock & Dam #3 Top 9.0 Bottom 8.8 OUUdogo
___
O
, NORTHERN CTATES POWER COMPANY
.
Mr J G Keppler June 6, 1980 Page The elevated pil measurements are a river related phenomena caused by measonable changes of chemical and physical variations that impact on the pil of the water.
This was a natural condition and a seasonal phenomenon, but on the advise of our resident NRC inspector we are making this report.
Yours very truly,
- E C Ward, PE Manager-Nuclear Environmental Service ECW/BWC/jh cc: Director, NRR c/o DSB (17)
MPCA Attn: J W Ferman
.
e