Offnormal Event Procedure 05-1-02-I-5, Resin Intrusion Into Reactor Vessel,Safety-Related, Revision 11ML20054J968 |
Person / Time |
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Site: |
Grand Gulf |
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Issue date: |
06/12/1982 |
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From: |
MISSISSIPPI POWER & LIGHT CO. |
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To: |
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Shared Package |
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ML20054J949 |
List: |
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References |
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05-1-02-I-5, 5-1-2-I-5, NUDOCS 8206300248 |
Download: ML20054J968 (4) |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211E7151999-08-20020 August 1999 Proposed Tech Specs,Incorporating Many Generic Improvements Agreed Upon Between Industry & NRC Since GGNS Conversion to ITS ML20196K0831999-06-29029 June 1999 Proposed Tech Specs Page 3.4-3,reflecting Implementation of BWROG Enhanced Option I-A,reactor Stability long-term Solution ML20196G7131999-06-23023 June 1999 Proposed Tech Specs Revising TS Associated with Various Esfss Which Need No Longer Be Credited Following Design Basis Fuel Handling Accident ML20206K5361999-05-0606 May 1999 Proposed Tech Specs Pages,Changing SLMCPR ML20206R9351999-01-12012 January 1999 Proposed Tech Specs Re Refueling Equipment Interlocks Required Actions ML20154Q4511998-10-16016 October 1998 TS Bases Update for Period of 970410 Through 981015 ML20236T1661998-07-20020 July 1998 Proposed Tech Specs 3.2.4,3.3.1.1,3.3.1.3,3.4.1,5.6.5, B 3.2.4,B 3.3.1.1,B 3.3.1.3 & B 3.4.1,enabling Full Implementation of Enhanced Option I-A Long Term Solution to Address Neutronic/Thermal Hydraulic Instability Issue ML20198J3581998-01-0909 January 1998 Proposed Tech Specs,Providing Certain Clarifications to Amend & Adding Restriction to Allowed Interval Extensoions ML20210F6651997-12-22022 December 1997 Redeacted Version of Test Rept M-J5.08-Q1-45161-0-8.0-1-0, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators for Entergy Operations ML20217H6211997-12-15015 December 1997 Rev 21 to Odcm ML20199L5711997-11-26026 November 1997 Rev 8 to Program Plan GGNS-M-189.1, Grand Gulf Nuclear Station Pump & Valve IST Program - Safety Related ML20198N3231997-11-0606 November 1997 Rev 11 to GGNS-M-489.1, Program Plan for ASME Section XI ISI Plan ML20198N3941997-10-28028 October 1997 Proposed Tech Specs Implementing Option B & Ref SE Issued by NRR for Ggns'S App J Exemption as Implementing Document for performance-based Leakage Testing Program ML20211M8481997-10-0606 October 1997 Proposed Tech Specs Replacement Bases Pages Associated W/Proposed Amend to License Re Response Time Testing ML20210V5581997-09-18018 September 1997 Proposed Tech Specs Reflecting Decrease of Two Recirculation Loop SLMCPR Limit to 1.11 & Single Recirculation Loop SLMCPR Limit to 1.12 ML20210H0871997-08-0606 August 1997 Proposed Tech Specs Changing TS 3.8.1, AC Sources Operating. Removal of Accelerated Testing Requirements for Standby DGs as Advised by GL 94-01 ML20141A1681997-05-0707 May 1997 Proposed Tech Specs Re Eliminating Selected Response Time Testing Requirements ML20140E3211997-04-18018 April 1997 Proposed Tech Specs,Revising TS Bases to Include Changes Made Since Rev 1 Was Sent to NRC 960201 ML20134N7841996-11-21021 November 1996 Proposed Tech Specs Pp 5.0-20 & 5.0-21,revised by Adding Footnote Indicating Proposed Change Applicable Only for Cycle 9 ML20134N7611996-11-20020 November 1996 Proposed Tech Specs Re MCPR Limits for Two Recirculation Loop Operation ML20134E1261996-10-22022 October 1996 Proposed Tech Specs Revising TS Figure 3.4.11-1, Minimum Reactor Vessel Metal Temperature Vs Reactor Vessel Procedure, Curves Using Methodology of NRC Reg Guide 1.99, Rev 2, Radiation Embrittlement of Reactor Vessel Matls ML20128M5681996-10-0909 October 1996 Proposed Tech Specs 3.8.1.14 Re Surveillance Requirements ML20117P4461996-09-19019 September 1996 Proposed Tech Specs Re Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20117M7021996-09-0505 September 1996 Proposed Tech Specs Re Min Critical Power Safety Limit ML20117G6781996-08-27027 August 1996 Proposed Tech Specs Re Surveillance Requirements for Safety/Relief Valves ML20116F0211996-07-31031 July 1996 Proposed Tech Specs Required to Support Cycle 9,reload 8 ML20113B7381996-06-20020 June 1996 Proposed Tech Specs,Redefining Secondary Containment Boundary to Allow Encl Bldg to Be Inoperable During Upcoming Refueling Outage ML20117L2581996-06-0404 June 1996 Proposed Tech Specs Re Replacement Page for Ltr RBG-42764, Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks1996-05-31031 May 1996 Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks ML20117D6941996-05-0909 May 1996 Proposed Tech Specs Required to Support Unit 1 Cycle 9, Including Changes to SLMCPR & Ref for Analytical Methods Used to Determine Core Operating Limits.Addl Methodology Ref in Various TS Bases Revised to Reflect GE Methodologies ML20117F4661996-05-0909 May 1996 Proposed Tech Specs,Modifying SRV Surveillance Test for Relief Mode of Operation ML20111B2701996-05-0808 May 1996 Proposed Tech Specs,Placing Containment Purge Valves W/ Resilient Seals on Performance Based Leakage Testing Frequency ML20108E3591996-05-0606 May 1996 Proposed Tech Specs Re Change in Co Name from Mississipi Power & Light to Entergy Mississippi,Inc ML20107E4681996-04-18018 April 1996 Proposed Tech Specs Re Fuel Loading W/Control Rods Withdrawn or Removed from Defueled Core Cells ML20100J8391996-02-22022 February 1996 Proposed Tech Specs Re Safety Setpoint Tolerance Requirements for Safety/Relief Valves ML20097C3541996-02-0101 February 1996 Proposed Tech Specs,Revising TS Bases to Include Changes Since 950221 Approval of TS Bases ML20094M8001995-11-20020 November 1995 Proposed Tech Specs Re Drywell Leak Rate Testing Requirements ML20087B5061995-08-0404 August 1995 Proposed Tech Specs Assoc W/Various ESF Sys Following Design Basis Fuel Handling Accident ML20082K3451995-04-13013 April 1995 Proposed Tech Specs Re Change to Be Reduced to Leave in TS Requirement to Test Outboard MSIV LCS Blowers ML20108A2691995-03-10010 March 1995 Rev 17 to ODCM ML20078S5141995-02-14014 February 1995 Proposed TS Consisting of Changes to SR 4.4.1.4.a.1 & 4.6.1.4.a.2 ML20078N6611995-02-10010 February 1995 Proposed Tech Specs Supporting Performance of Drywell Bypass Leakage Rate Surveillance on Performance Based Interval ML20079B4501994-11-0909 November 1994 Proposed Tech Specs Associated W/Various ESF Systems Following Design Basis Fuel Handling Accident ML20070C9751994-06-24024 June 1994 Proposed TS Pages 3/4 6-4 & 3/4 6-6 Associated W/Proposed Exemption to 10CFR50,App J ML20065L4971994-04-15015 April 1994 Proposed Tech Specs Re Administrative Controls ML20059H6101994-01-14014 January 1994 Cycle 7 Startup Physics Test Summary Rept for Physics Testing Completed on 931220 ML20059H6061994-01-13013 January 1994 Proposed Tech Specs,Removing 2,324 Spent Fuel Pool Storage Limit ML20029D6451993-11-30030 November 1993 Reactor Containment Bldg 1993 Integrated Leakage Rate Test. ML20058D3911993-11-23023 November 1993 Proposed Tech Specs Bases Pages Re Cycle 7 Reload ML20059A4871993-10-22022 October 1993 Proposed Tech Specs Modifying Testing Frequencies for Drywell Test & Airlock Tests 1999-08-20
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20217H6211997-12-15015 December 1997 Rev 21 to Odcm ML20199L5711997-11-26026 November 1997 Rev 8 to Program Plan GGNS-M-189.1, Grand Gulf Nuclear Station Pump & Valve IST Program - Safety Related ML20198N3231997-11-0606 November 1997 Rev 11 to GGNS-M-489.1, Program Plan for ASME Section XI ISI Plan ML20108A2691995-03-10010 March 1995 Rev 17 to ODCM ML20056C9241993-06-30030 June 1993 GGNS GL 89-10 MOV Program ML20095J9471992-03-31031 March 1992 Quarterly Status Rept for Period Ending 920331 Re Degraded Core Accident Hydrogen Control Program ML20114B8011992-01-23023 January 1992 Rev 13 to Offsite Dose Calculation Manual ML20086A4101991-11-0707 November 1991 Rev 0 to Administrative Procedure 01-S-10-4, Emergency Plan Training & Drills, Reflecting Cancellation of Emergency Plan Procedure 10-S-01-23,Rev 11 ML20043H0541990-06-19019 June 1990 Receipt,Routing & Disposition Form for Procedures S-330, Security Training & Qualification Plan & S-480, Physical Security Plan. ML20043B2501990-05-14014 May 1990 Rev 4 to Spec SERI-M-189.1, Pump & Valve Inservice Testing Program. ML20059C9231990-04-11011 April 1990 Rev 3 to Process Control Program ML20196E9331988-11-30030 November 1988 Cycle 4 Proposed Startup Physics Tests ML20154L7771988-04-27027 April 1988 Rev 3 to SERI-M-189.1, Pump & Valve Inservice Testing Program ML20153G7031988-01-0101 January 1988 Temporary Change Notice 6,Directive 04-1-01-EX-1 to Rev 18 to Administrative Procedure 04-1-01-E32-1, MSIV Leakage Control ML20235Y9141987-09-22022 September 1987 Rev 0 to Procedure 07-S-53-C11-22, Loop Calibr Instruction Backup Scram Valve B Functional Test,Safety-Related ML20235Y8951987-09-22022 September 1987 Rev 0 to Procedure 07-S-53-C11-21, Loop Calibr Instruction Backup Scram Valve a Functional Test,Safety-Related ML20212E0031986-12-10010 December 1986 Rev 10 to Offsite Dose Calculation Manual ML20207G9301986-11-24024 November 1986 Rev 2 to MP&L-M-189.1, Mississippi Power & Light Pump & Valve Inservice Insp Program ML20212G1571986-10-31031 October 1986 Revised Pages to Procedures Generation Package ML20215L2871986-10-15015 October 1986 Rev 2 to Process Control Program Description ML20212E0751986-10-15015 October 1986 Rev 2 to Process Control Program Description ML20212D9411986-08-28028 August 1986 Rev 9 to Offsite Dose Calculation Manual. Marked-up Rev 9 to Manual Encl ML20212D8001986-08-25025 August 1986 Rev 8 to Offsite Dose Calculation Manual. Marked-up Rev 8 to Manual Encl ML20215C1921986-08-25025 August 1986 Rev 8 to Offsite Dose Calculation Manual ML20211Q9111986-07-31031 July 1986 Rev 1 to Grand Gulf Nuclear Station-Unit 1 Emergency Procedures Upgrade Program Procedures Generation Package ML20137L6891985-11-15015 November 1985 Rev 6 to Vol 8,Section 3,Procedure 08-S-03-17, Chemistry Procedure Core Damage Estimation Safety-Related ML20133G9951985-09-27027 September 1985 Rev 6 to Offsite Dose Calculation Manual ML20133F3731985-07-31031 July 1985 SPDS Safety Analysis & Implementation Plan ML20128K6621985-06-28028 June 1985 Rev 0 to App a of Spec MP&L-M-189.1, Max Stroke Times for Power Actuated Valves ML20115G5241985-04-30030 April 1985 Emergency Procedures Upgrade Program,Procedures Generation Package ML20126D3521985-02-0505 February 1985 Rev 15 to Sys Operating Instruction 04-S-01-P64-1, Fire Protection Water Sys AECM-84-0537, Detailed Control Room Design Review Program Plan1984-12-19019 December 1984 Detailed Control Room Design Review Program Plan ML20098B7801984-08-31031 August 1984 Rev 4 to Offsite Dose Calculation Manual ML20093A2691984-07-31031 July 1984 Phase 1B Program,Div I Diesel Generator Disassembly,Reinsp & Verification of Div II Diesel Generator As-Mfg Similarity ML20092P2831984-07-0303 July 1984 Rev 2 to Offsite Dose Calculation Manual ML20093J5121984-06-29029 June 1984 Vols I-III to Inservice Insp 10-Yr Program ML20092P2841984-05-31031 May 1984 Rev 3 to Offsite Dose Calculation Manual - Safety-Related ML20127B5201984-04-14014 April 1984 Rev 13 to Procedure 05-1-02-I-4, Loss of Offsite Power ML20127B5301984-04-14014 April 1984 Rev 11 to Procedure 05-1-02-I-6, Station Blackout ML20087H5071984-03-31031 March 1984 Tech Spec Review Program Description ML20127B5241984-03-31031 March 1984 Rev 0 to Gas/Turbine Generator Sys Maint & Operation Procedure AECM-84-0180, Rev 1 to Procedure 14-S-01-4, Training & Administrative Section Procedure1984-03-30030 March 1984 Rev 1 to Procedure 14-S-01-4, Training & Administrative Section Procedure ML20087N6031984-03-23023 March 1984 Rev 2 to Administrative Procedure TS-1, Grand Gulf Nuclear Station Tech Spec Review,Safety-Related. W/840323 Memo ML20087N5951984-03-22022 March 1984 Administrative Procedure TS-1, Requirements for Grand Gulf Nuclear Station Tech Spec Review ML20087N6001984-03-18018 March 1984 Rev 1 to Administrative Procedure TS-1, Grand Gulf Nuclear Station Tech Spec Review,Safety-Related. W/840318 Memo ML20087N5981984-03-13013 March 1984 Rev 0 to Administrative Procedure TS-1, Grand Gulf Nuclear Station Tech Spec Review,Safety-Related ML20212E0311984-02-29029 February 1984 Rev 1 to Process Control Program Description ML20127B5331983-12-0606 December 1983 Rev 12 to Procedure 05-1-02-VI-2,Hurricanes,Tornados & Severe Weather ML20083G3421983-11-0707 November 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures 10-S-01-19 Re Personnel injury,10-S-01-25 Re Onsite Personnel Response & 10-S-01-26 Re Offsite Emergency Response ML20080E1111983-09-24024 September 1983 Rev 1 to Procedure 08-S-04-109, Chemistry Instruction: Operation of Orion 701 Ion Analyzer,Safety Related 1997-12-15
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- PLANT OPERATIONS MANUAL I
Volume 05 05-1-02-I-5 Section 02 Revision: 11 Date: 6-12-82 i
0FF-NORMAL EVENT PROCEDURE RESIN INTRUSION INTO THE REACTOR VESSEL SAFETY RELATED
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List of Effective Pages:
Page:
1-3 List of TCN's Incorporated:
Revision TCN No.
10 None 11 None 8206300248 820625 PDR ADOCK 05000416 P PDR
.- ORAND CULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE
Title:
Resin Intrusion Into The No.: 05-1-02-I-5 Revision: 11 Page: 1 Reactor Vessel 1.0 PURPOSE / DISCUSSION 1.1' The purpose of this procedure is to describe the actions to be taken in the event resin is injected into the reactor from either the Condensate Cleanup System or the Reactor Water Cleanup System (RWCU).
1.2 This procedure may interface with the Emergency Plan since a reactor scram and ECCS initiation are possible. This procedure may also interface with one or more of the Emergency Procedures.
1.3 Resin may be injected into the reactor from either the RWCU filter-demineralizers (F/D) or the condensate filters or demineralizers.
In either case the results are the same. The resin intrusion will cause water conductivity and activity to increase substantially while pH decreases substantially. Depending upon the amount and rate of resin injected, these changes may become detectable immediately or only after several hours. The most serious injection could cause a rapid change in vessel chemistry resulting in a large release of nitrogen-16 into the steam lines, causing a steam line high radiation scrum and MVIS isolation. Care shoul4_ht exercised to ensure a. main steam.line.
- radrition trip is not the result of a fissdE' product release, caus'e3'by a ~ t fuel element failure.
SYMPTOMS .. ..;, '
2.1 An unexplained increase in heactor water conductivity accompanied by a very low pH. -
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2.2 'hn unexplained increase in reactor water activity.
2.3_[An unexpl.ained decrease in reactor . power (due . to increased. surface tension of the water). .
.' 2.4 An unexplained increase in levels _.on the MSL. RAD monitors, and .possibly
. . _ , . _ . . .the OFF GAS RAD monitors. .-~. a - . . .~ -- - - -
~ ~ ~[ ' 2.5_,_An unexplained change in condensate o'rI RWCU F/D_ parameter, particularly flow or dp. .
2.6 One of more of the the following control room annunciators:
2.6.1 REACTOR RECIRC HIGH-LOW CONDUCTIVITY 2.6.2 FILTER' DEMIN TROUBLE CONT 2.6.3 CONDENSATE DMNRLZER SYSTEM TROUBLE 2.6.4 RFP DISCHARGE CONDUCTIVITY HICH 2.6.5 CONDENSER DMNRLZR COMB EFL CNDCT HIGH 2.6.6 00NDENSER PUMP DISCHARGE CNDCT HIGH
- GRAND CULF NUCLEAR STATION OFF-MORMAL EVENT PROCEDURE
Title:
Resin Intrusion Into The JNo.: 05-1-02-I-5 Revision: 11 Page: 2 Reactor Vessel l 2.6.7 MSL Rad High 2.6.8 MSL A/D or B/C Rad Hi Hi/Inop 2.6.9 RWCU FLTR DMIN EFF CNDCT HI/LO 2.7 The following local annunciators:
2.7.1 STRAINER "A" DIFF PRESS HI (IG36-P002) 2.7.2 STRAINER "B" DIFF PRESS HI (IG36-P002) 2.7.3 "A" CONDUCTIVITY HI (1G36-P002) 2.7.4 "B" CONDUCTIVITY HI (lG36-P002) 2.7.5 COND DEM POST STR DIFF PRESS HIGH (A-H) (IH22-P474) ft 2.7.6 COND DEM EFFLUENT CONDUCTIVITY HIGH (A-H) (1H22-P474)
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3.0 AUTOMATIC ACTIONS '- - k
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3.5 Possible Reactor Scram and' MSIV Isolation on MSL HIGH RAD.
-' 4.0 IMMEDIATE OPERAT0[ ACTIONS .
4.1 If Reactor Scram and MSIV Isolation occurred, refer to ONEP 05-1-02-I-1 Reactor Scram, and EP-1 Level Control.
4.2 Notify the Shif t Supervisor / Superintendent and Chemistry.
I 4.3 Obse rve the Off Gas Pre-Treatment Radiation Monitor on panel 1H13-P600.
, , , , Refer to ONEP 05-1-02-II-2, Off Cas Activity High, if necessary.
[,~, 5.0 SUBSEQUENT ACTIONS ,,,,.._ _ _ _ _ . . _ . ._
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5.1~ Proceed to implement the Emergency Plan if necessary, as directed by the Shift Supervisor / Shift Superintendent.
5.2 Reduce reactor power to slow the rate of Conductivity / Activity increase.
5.3 Check Condensate /Feedwater Conductivity and refer to ONEP 05-1-02-V-12, Condensate High Conductivity if necessary.
5.4 Attempt to determine the source of the resin by observing RWCU and Condensate F/D's , and Condensate Deep Bed Demineralizer Parameters.
Check the records on each for anything recently logged cut of the ordinary.
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! . SRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE
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Title:
Rasin Intrusion Into The No.: 05-1-02-I-5 Revision: 11 Page: 3 ;
I Reactor Vessel 5.5 Re fer to Tech. Specs . 3/4.4.4, Reactor Coolant System Chemistry, for operating limits.
, 5.6 Continue to monitor MSL Radiation and Off Gas Radiation Instrumentation.
l 5.7 If it can be determined that the resin is not (or no longer) coming from the RWCU System, place all available RWCU F/D's service, and begin rejecting reactor water to the condenser.
i' 5.8 As Condensate F/D's and Deep Bed Demineralizers are found not to be the source of resin, place them in service, monitor vessel chemistry indications and take samples to ensure pH, conductivity, and activity are returning to normal.
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! 5.9 If conditions return to normal and Tech. Specs. are complied with, continue operating in accordance with the appropriate IOI, or else
- continue to shutdown in accordance with 10I 03-1-01-3, Plant Shutdown.,r
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