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MONTHYEARML20137P7121986-01-29029 January 1986 Proposed Tech Spec Changes to Reflect Design Change in Progress to Complete Installation of Drywell Chilling Water Sys Project stage: Other ML20137P6931986-01-29029 January 1986 Application for Amend to License NPF-29,revising Tech Specs to Reflect Design Changes in Progress to Complete Installation of Drywell Chilling Water Sys Project stage: Request AECM-86-0023, Forwards Application for Amend to License NPF-29,revising Tech Specs to Reflect Design Change in Progress to Complete Installation of Drywell Chilling Water Sys.Fee Paid1986-01-29029 January 1986 Forwards Application for Amend to License NPF-29,revising Tech Specs to Reflect Design Change in Progress to Complete Installation of Drywell Chilling Water Sys.Fee Paid Project stage: Request ML20203D6791986-04-14014 April 1986 Proposed Tech Specs Re Design Changes to Scram Discharge Vol & post-LOCA Vacuum Breakers Project stage: Other ML20199E9111986-06-13013 June 1986 Proposed Changes to Tech Specs 3.5.1 & 4.5.1,revising Automatic Depressurization sys-related Air Sys Per Prior Commitments to Add Extrapolated Pressure Decay Test & Instrument Quality Test Project stage: Request AECM-86-0188, Application for Amend to License NPF-29,revising Tech Spec 4.5.1 to Change Automatic Depressurization sys-related Air Sys,Per Prior Commitments to Add Extrapolated Pressure Decay Test & Instrument Air Quality Test.Fee Paid1986-06-13013 June 1986 Application for Amend to License NPF-29,revising Tech Spec 4.5.1 to Change Automatic Depressurization sys-related Air Sys,Per Prior Commitments to Add Extrapolated Pressure Decay Test & Instrument Air Quality Test.Fee Paid Project stage: Request ML20207G5201986-07-16016 July 1986 Proposed Tech Specs Combining Drywell Vacuum Relief Requirements w/post-LOCA & Combustible Gas Purge Sys Into One Tech Spec Project stage: Other AECM-86-0225, Application for Amend to License NPF-29,combining Drywell Vacuum Relief Requirements for post-LOCA & Combustible Gas Purge Sys Into One Tech Spec.Fee Paid1986-07-16016 July 1986 Application for Amend to License NPF-29,combining Drywell Vacuum Relief Requirements for post-LOCA & Combustible Gas Purge Sys Into One Tech Spec.Fee Paid Project stage: Request ML20212P4701986-08-26026 August 1986 Proposed Tech Specs Allowing Entry Into Operational Conditions 1 & 2 W/O Performing Surveillance Requirement 4.1.3.1.4.a for Scram Discharge Vol Vents Provided Test Performed at Least Every 18 Months Project stage: Other ML20212P4641986-08-26026 August 1986 Revised Application for Amend to License NPF-29,allowing Entry Into Operational Conditions 1 & 2 W/O Performing Surveillance Requirement 4.1.3.1.4.a for Scram Discharge Vol Vents Provided Test Performed at Least Every 18 Months Project stage: Request AECM-86-0238, Forwards Revised Application for Amend to License NPF-29, Allowing Entry Into Operational Conditions 1 & 2 W/O Performing Surveillance Requirement 4.1.3.1.4.a Provided Test Performed at Least Every 18 Months1986-08-26026 August 1986 Forwards Revised Application for Amend to License NPF-29, Allowing Entry Into Operational Conditions 1 & 2 W/O Performing Surveillance Requirement 4.1.3.1.4.a Provided Test Performed at Least Every 18 Months Project stage: Request 1986-06-13
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Category:TECHNICAL SPECIFICATIONS
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 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 ML20117F4661996-05-0909 May 1996 Proposed Tech Specs,Modifying SRV Surveillance Test for Relief Mode of Operation 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 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 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 ML20059H6061994-01-13013 January 1994 Proposed Tech Specs,Removing 2,324 Spent Fuel Pool Storage Limit 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 ML20059B0351993-10-15015 October 1993 Proposed Tech Specs Converting Current GGNS TS to TS Based Largely on NUREG-1434,Rev 0 ML20057C7281993-09-23023 September 1993 Proposed Tech Specs Removing Surveillance Requirement 4.4.1.2.2 Due to Problems Encountered W/Jet Pump Differential Pressure Instrumentation Measurements ML20056E4511993-08-12012 August 1993 Proposed Tech Specs 3/4 6-3,6-4,6-4a,6-6,6-12 Re Exemption to 10CFR50,App J, Primary Reactor Containment..., for Local Leak Rate ML20056D5621993-08-11011 August 1993 Proposed Tech Specs Section 3/4.3.7.5 Reflecting Relocation of Certain Accident Monitoring Instrumentation to Administrative Control ML20046D2081993-08-11011 August 1993 Proposed Tech Specs Section 3/4.3.7.10, Loose Part Detection Sys, Relocating Loose Part Detection Instrumentation from TS to Administrative Control ML20046D1961993-08-11011 August 1993 Proposed Tech Specs Supporting Compliance W/New Requirements of 10CFR20 & 10CFR50.36a ML20056C7141993-07-15015 July 1993 Proposed Tech Specs Removing Operability Requirements for auto-test Feature of Load Shedding & Sequencing Sys & Increase AOT for Inoperable Load Shedding & Sequencing Sys from Eight to Twelve 1999-08-20
[Table view] 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
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REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.1.3.1.4 The scram discharge volume shall be determined OPERABLE by demonstrating:
a.A The scram discharge volume drain and vent valves OPERABLE, when control rods are scram tested from a normal control rod configuration of less than or equal to 50% R00 DENSITY at least once ;.sr 18 months, by verifying that the drain and vent valves:
- 1. Close within 30 seconds after receipt'of a signal for control rods to scram, and -
- 2. Open when the scram signal is reset.
- b. Proper level sensor response by performance of a CHANNEL FUNCTIONAL TEST of the scram discharge volume scram and control rod block level instrumentation at least once per 31 days.
- Th provi siom o.F Gae;Keatiou 4.0,+ ar e.
nsT~ ajoyl;eul lz prov;)ad tMs surveilaca ls pa%neh # laasT onea- pr IT nonrks .
. GRAND GULF-UNIT 1 8609030149 860326 3/4 1-5 h e S u nT No. _
PDR ADOCK 05000416 P PDR
o Item 2 PS-86/03 Additional Submittal
SUBJECT:
Technical Specifications 3.5.1 and 4.5.1, pages 3/4 5-3 and 5-5 DISCUSSION: The proposed technical specification changes result from prior commitments made by Mississippi Power & Light (MP&L) to monitor and test the Automatic Depressurization System (ADS) related air system. These comitments were subsequently placed in Facility Operating License NPF-29 as operating license condition 2.C.(33)g with solutions to be provided to the Nuclear Regulatory Commission (NRC) prior to start-up following the first refueling outage.
JUSTIFICATION: In a letter to Mr. Harold R. Denton from L. F. Dale dated October 26, 1982 (AECM-82/0510), Mississippi Power & Light (MP&L) committed to perform an integrated leak test on the ADS air system every 18 months. This test is initiated by turning off the instrument air booster compressors and by venting the booster compressor discharge to atmosphere. The pressure decay rate in each of the two ADS air headers is monitored and an extrapolated seven-day air pressure is determined. The leakage test is considered successful if the air pressure after seven days (based on extrapolation from test data) is above 110 psig.
Tests have shown that with the ADS air system at 110 psig, each ADS valve'can Le actuated two times against 70% of drywell
~ design pressure.
This seven day test period is a recomendation from the General Electric "BWR Plant Requirement; Plant Air" document which is
.to be applied on an individual plant basis. It is.not a General Electric design requirement. However, the seven day pressure decay test is being placed in the technical specifications in order to demonstrate system conformance to these GE recommendations.
Instrumentation to be provided before startup following the first refueling outage to monitor ADS air receiver pressure is shown on the attached drawing to this proposed change. This instrumentation to monitor. ADS air receiver pressure will consist of a separate alarm and pressure indicator in the control room for each Division 1 and 2. MP&L committed to install instrumentation to monitor ADS air receiver pressure in a letter dated October 26, 1982 (AECM-82/0510). Environmental
. Qualification of pressure transmitters will be in accordance with 10CFR50.49. Design codes for installation will be in accordance with IEEE-323, 1974 and all applicable codes listed in the FSAR. The trip setpoint for the ADS air receiver pressure alarm is based on an analytical lower limit of 147 psig. The lower limit is determined by the minimum pressure required to provide two actuations for each ADS valve and then hold the ADS valves open for five days under the most limiting accident conditions (Letter from NRC to MP&L dated March 15, J19 MISC 86080802 - 1
1985). The seven day air supply is a measured capacity and serves to demonstrate the adequacy of the system under normal plant conditions. The successful completion of the seven day leakage testing ensures that the assumed leakage rate of 1 SCFH per valve, which is also the basis for the calculated five day supply, is a valid assumption. The upper limit for the alarm will be administratively controlled to ensure that it is below the ADS booster start signal trip setpoint currently set at a nominal 160 psig. To ensure that an alarm is generated well before the minimum required ADS air receiver pressure is reached, the nominal trip setpoint will be 2 150 psig. This nominal trip setpoint will be maintained to ensure that an alarm is not generated before the booster compressor starts. If an alarm is generated, operators will "ake appropriate action in accordance with alarm response instructions including declaring the ADS system inoperable if required by the technical specifications. These alarm response instructions will replace the operators Round Sheet instructions to read the pressure indication every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Surveillances will be added to the technical specifications for the accumulator low pressure alarm channels. These changes will include a CHANNEL CALIBRATION to be performed once per 18 months and a CHANNEL FUNCTIONAL TEST to be performed once per 31 days. These surveillance requirements are being added to conform with the GE standard technical specification. In addition to the surveillance requirements, an action statement will be added as the appropriate action to take for an inoperable instrumentation channel. This action statement will require that local monitoring of ADS accumulator pressure be performed at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when an ADS low pressure alarm instrumentation channel (s) is inoperable. In addition, .
the inoperable channel (s) must be restored to operable status within 7 days. Otherwise, the ADS valves will be declared inoperable. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> surveillance is adequate to detect problems with the air system since the present surveillance interval is once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (without alarm instrumentation installed) and has been demonstrated to be adequate. The 7 day requirement allows sufficient time to effect repairs while assuring that instrumentation is restored to operable status in an appropriate time frame.
In addition to the proposed technical specification changes, MP&L will implement administrative procedures to test the instrument air quality to ADS. A sample of instrument air will be taken every 6 months to ensure that the proper air quality is maintained. These air samples will be analyzed for moisture content, particle size, and oil content and will be required to meet the General Electric design (22A2738, Rev. 3) requirements for ADS system safety-related components. This General Electric designspecificationrequiresthattheADSairsgpplybe oil-free ( <. 1 ppm), dried to a dew point of - 40 F at 100 psig, and filtered to 50 microns.
J19 MISC 86080802 - 2
p,*
The proposed' administrative procedure will require that the instrument air quality be verified-to be within the. required' limits at least once per every 6 months. The 6 month test interval will allow for comparisons of test' data for determining if system degradation is taking place. In the event the instrument air quality fails to meet the design requirements.
. .an engineering evaluation will be performed within 7-days.
MP&L at present contracts to an off-site laboratory the sampling of ADS instrument air quality. The laboratory supplies the evacuated cylinders used to collect the air sample. These cylinders must be requested from the laboratory just prior to collecting a sample. Once the sample is drawn, the cylinder is shipped back to the laboratory for analysis. Total analysis time from the time the cylinder is requested until results are received from the sample is approximately 3 to 4 weeks. Based on this time period, MP&L believes that a testing interval of less than six months would place undue constraints on the operation of the plant. The six month testing interval will allow for the comparison of previous tests and the early detection of. system degradation.
SIGNIFICANT HAZARDS' CONSIDERATIONS:
g Thel proposed amendment would add a 7 day extrapolated pressure decay test on the ADS air system to Technical Specification 4.5.1. The proposed amendment would also add control room indication and surveillances of the ADS air receiver pressure.
These changes are being made to meet prior commitments and to satisfy the provisions of operating license condition 2.C.(33)g before startup following the first refueling outage.
The-18 month leak test and CHANNEL CALIBRATION along with the 31 day CHANNEL FUNCTIONAL TEST will be performed to help ensure proper functioning of the safety related components in the ADS air system. The implementation of these test procedures'and the addition of instrumentation in the' control room to monitor ADS air receiver pressure does not alter the evaluations of previous
-accidents. These new test requirements are in addition to and are more restrictive than present technical specification requirements. Therefore the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated because the change will' add improvements to the ADS air system which will result in direct notification of control room personnel to the loss of the ADS air supply. The addition of leak' testing will also help to ensure proper functioning of the ADS safety-related components. The possibility of a new or i different kind of accident will not be created by the performance of the 18 month leak test because this test will be conducted while the plant is in modes 4 & 5 and the ADS system is not required to be operable during these modes.
J19 MISC 86090802 - 3
Ts Itaposing the 18 month leak ' test, CHANNEL CALIBRATION, and the 31 day CHANNEL FUNCTIONAL TEST helps to further ensure that the ADS air system will perform its safety function thus there is no significant reduction in the margin of safety. The margin of: safety will.be increased by the addition of pressure indication and alarms in the control room by ensuring a faster operator response to loss of instrument' air.
Therefore, the proposed change involves no significant hazards considerations.
l 1
l 6
i J19 MISC 86080802 - 4
EMERGENCY CORE COOLING SYSTEMS :
/
l LIMITING CONDITION FOR OPERATION (Continued)
ACTION: (Continued)
- e. For ECCS divisions 1 and 2, provided that ECCS division 3 is OPERABLE and divisions 1 and 2 are otherwise OPERA 8LE:
- 1. With one of the above required ADS valves inoperable, restore the inoperable ADS valve to OPERA 8LE status within 14 days or be in at least HOT SHUT 00WN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and reduce reactor steam dome pressure to i 135 psig within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 2. With two or more of the above required AOS valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and reduce reactor steam dome pressure to i 135 psig within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- f. With an ECC'S discharge line " keep filled" pressure alarm instrumentation channel inoperable, perform Surveillance Requirement 4.5.1.a.1 at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- g. With an ECCS header delta P instrumentation channel inoperable, restore the inoperable channel to OPERABLE status with 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or determine ECCS header delta P. locally at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; otherwise declare the associated ECCS inoperable.
- h. In the event an ECCS system is actuated and infects water into the Reactor Coolant System, a Special Report shall,be prepared and sub-mitted to the Commission pursuant to Specification 6.9.2 within 50 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the i useage factor for each affected safety injection nozzle shall be i
provided in this Special Report whenever its value exceeds 0.70.
j --
"Whenever two or more RHR subsystems are inoperable, if unable to attain COLD SHUTDOWN as required by this ACTION, maintain reactor coolant temperature as low as practical by use of alternate heat removal methods.
- 1. With an ADS ic e pressure alarm system instrumentation channel (s) '
inoperable, determine the associated ADS accumulator pressure locally at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; restore the inoperable channel (s) to OPERABLE status within 7 days; otherwise declare the associated ADS valves inoperable.
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EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- 2) Low pressure setpoint of the:
(a) LPCI A and B subsystem loop to be 1 38 psig.
(b) LPCI C subsystem loop and LPCS system to be 1 22 psig.
(c) HPCS system to be 1 18 psig, b) Header delta P instrumentation and verifying the setpoint of the HPCS system and LPCS system and LPCI subsystems to be 1.2 0.1 psid change from the normal indicated AP.
3.' Verifying that the suction for the HPCS system is automatically transferred from the condensate storage tank to the suppression pool on a condensate storage tank low water level signal and on a suppression pool high water level signal,
- d. For the ADS at least once per 18 months by:
4 ba
- 1. Performing a system functional test which includes simulated e-automatic actuation of the system throughout its emergency '
operating sequence, but excluding actual valve actuation. ((
- 5. Manually opening each ADS valve when the reactor steam dome pressure is greater than or equal to 100 psig* and observing
]3 that either: 'l
-s a) The control valve or oypass valve position responds gg accordingly, or -
b) There is a corresponding change in the measured steam f
(g flow.
- 3. Performing an extrapolated pressure decay test on the ADS air system to demonstrate system pressure will be maintained for 7 days at a value Jk;110 psig without makeup air available.
- 4. Performing a CHANNEL CALIBRATION of the accumulator low pressure alarm channels and verifying an alarm setpoint of jt 150 psig on decreasing pressure.
- e. For the ADS at least once per 31 days by performing a CHANNEL FUNCTIONAL TEST of the accumulator low pressure alarm channels.
The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is ~
adequate to perform the test.
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