Letter Sequence Other |
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Results
Other: AECM-85-0303, Proposed Tech Specs,Changing Table 3.3.7.4-1, Remote Shutdown Sys Controls by Deleting Item 20, RHR to RCIC Head Spray Line, AECM-85-0350, Discusses Util Commitments Resulting from Proposed Tech Spec Changes Re Acceptable High/Low Pressure Boundary Design for RHR Headspray Line.Handswitches Will Be Removed from Remote Shutdown Panel for Valves E12-F023 & E12-F394, ML20133P171, ML20135E723, ML20135G134, ML20138H894, ML20138J716
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MONTHYEARML20133P1711985-08-12012 August 1985 Proposed Tech Specs,Reflecting Design Changes & Editorial Clarification Re Leak Rate Testing of RHR to Head Spray Isolation Valve & ECCS Actuation Instrumentation Project stage: Other AECM-85-0228, Application for Amend to License NPF-29,changing Tech Specs to Reflect Design Changes & Editorial Clarifications.Fee Paid1985-08-12012 August 1985 Application for Amend to License NPF-29,changing Tech Specs to Reflect Design Changes & Editorial Clarifications.Fee Paid Project stage: Request ML20135E7231985-08-30030 August 1985 Notice of Violation from Insp on 850708-12 Project stage: Other ML20135G1341985-09-13013 September 1985 Proposed Tech Specs Reflecting one-time Exception for Qualifications of Replacement Individual for Chemistry/ Radiation Control Superintendent Position Project stage: Other ML20135G1291985-09-13013 September 1985 Application for Amend to License NPF-29,requesting one-time Tech Spec Exception for Qualifications of Replacement Individual for Chemistry/Radiation Control Superintendent Position Project stage: Request ML20135F1051985-09-13013 September 1985 Application for Amend to License NPF-29,changing Tech Spec Table 3.3.7.4-1, Remote Shutdown Sys Controls, by Deleting Item 20, RHR to RCIC Head Spray Line. Fee Paid Project stage: Request AECM-85-0263, Forwards Application for Amend to License NPF-29,requesting one-time Tech Spec Exception for Qualifications of Replacement Individual for Chemistry/Radiation Control Superintendent Position.Fee Paid1985-09-13013 September 1985 Forwards Application for Amend to License NPF-29,requesting one-time Tech Spec Exception for Qualifications of Replacement Individual for Chemistry/Radiation Control Superintendent Position.Fee Paid Project stage: Request AECM-85-0303, Proposed Tech Specs,Changing Table 3.3.7.4-1, Remote Shutdown Sys Controls by Deleting Item 20, RHR to RCIC Head Spray Line1985-09-13013 September 1985 Proposed Tech Specs,Changing Table 3.3.7.4-1, Remote Shutdown Sys Controls by Deleting Item 20, RHR to RCIC Head Spray Line Project stage: Other AECM-85-0305, Forwards Resumes of Two Individuals Appointed as Supervisors to Organization Radiation Control Function,Per Request for Addl Info Re 850712 Proposed Change to Tech Spec Figure 6.2.2.-11985-10-0202 October 1985 Forwards Resumes of Two Individuals Appointed as Supervisors to Organization Radiation Control Function,Per Request for Addl Info Re 850712 Proposed Change to Tech Spec Figure 6.2.2.-1 Project stage: Request ML20138J7161985-10-23023 October 1985 Proposed Tech Spec 6.3.1 for one-time Exception of Reg Guide 1.8 Re Qualifications of Chemistry/Radiation Control Superintendent Project stage: Other AECM-85-0346, Application for Amend to License NPF-29,revising Tech Spec 6.3.1 for one-time Exception of Reg Guide 1.8 Re Qualifications of Chemistry/Radiation Control Superintendent1985-10-23023 October 1985 Application for Amend to License NPF-29,revising Tech Spec 6.3.1 for one-time Exception of Reg Guide 1.8 Re Qualifications of Chemistry/Radiation Control Superintendent Project stage: Request ML20138J7011985-10-24024 October 1985 Forwards Application for Amend to License NPF-29,revising Tech Spec 6.3.1 for one-time Exception of Reg Guide 1.8 Re Qualifications of Chemistry/Radiation Control Superintendent.Fee Paid Project stage: Request AECM-85-0350, Discusses Util Commitments Resulting from Proposed Tech Spec Changes Re Acceptable High/Low Pressure Boundary Design for RHR Headspray Line.Handswitches Will Be Removed from Remote Shutdown Panel for Valves E12-F023 & E12-F3941985-10-30030 October 1985 Discusses Util Commitments Resulting from Proposed Tech Spec Changes Re Acceptable High/Low Pressure Boundary Design for RHR Headspray Line.Handswitches Will Be Removed from Remote Shutdown Panel for Valves E12-F023 & E12-F394 Project stage: Other ML20138H8941985-12-11011 December 1985 Proposed Tech Spec,Allowing one-time Exception Re Qualifications of Chemistry/Radiation Control Superintendent Project stage: Other AECM-85-0404, Application for Amend to License NPF-29,revising Tech Spec 6.3.1 to Allow one-time Exception Re Qualifications of Chemistry/Radiation Control Superintendent1985-12-11011 December 1985 Application for Amend to License NPF-29,revising Tech Spec 6.3.1 to Allow one-time Exception Re Qualifications of Chemistry/Radiation Control Superintendent Project stage: Request 1985-10-30
[Table View] |
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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
[Table view] |
Text
.-- . - . - ~ . - - _. - . ~_ --- __ - . - .
l . Attachmnt to AECM-85/0303
SUBJECT:
NLS-85/10 Technical Specification Table 3.3.7.4-1, page 3/4 3-71 ;
1 i
DISCUSSION: It is proposed to delete item 20. RHR to RCIC Head Spray Line Valve, from the subject Remote Shutdown System Controls table. l (It should be noted that the affected technical specification ,
page reflects change NPE-85/06 previously requested by MP&L l serial AECM-85/0228, dated August 12,1985.)
JUSTIFICATION: The original design of the Reactor Core Isolation Cooling (RCIC) system incorporated coolant injection into the vessel !
head through the RHR Head Spray line. Design evolution resulted !
in this injection path design being abandoned in favor of the conventional injection path through the feedwater line used in earlier BWR designs. Operability of the RHR to RCIC Head Spray .
Line Valve is therefore not required for RCIC injection to the vessel. The remaining functions of the valve are to provide l an injection path for RHR Head Spray, which is not a safety
( function, and to provide containment and reactor coolant
! boundary isolation as required. The head spray function could .
be used to aid in the transition from hot to cold shutdown by introducing spray into the steam done to directly cool and condense steam in the vessel, thereby reducing pressure and ;
temperature. However, RHR Head Spray is not required to effect safe shutdown of the reactor or mitigate the consequences of any ,
event analyzed in the CCNS FSAR.
A design change has been partially implemented which added a second motor operated valve to this line that in intended to serve as the containment isolation valve for this line. Qh valve will be powered from a separate ESF division than that of the valve which this change addresses, and is located inside the drywell. After approval of the requested license amendment which will allow this valve to be credited with the containment isolation function (see the MP&L memorandum dated August 12, 1985, O. D. Kingsley, Jr., to Mr. Harold R. Denton, MP&L serial '
AECM-85/0228), the new valve will be closed and help to provide ,
redundant assurance that the line will remain isolated and !
diversion of coolant flow through the head spray line during !
shutdown cooling or LPCI operation will not occur. ]
i Since the valve is not assumed for any safe shutdown or accident '
analysis, operability of it from the remote shutdown panel is not required, and the requirements of specification 3.3.7.4 are ;
not applicable. Operability of the valve for the containment ,
and reactor coolant boundary isolation function will continue to be maintained in accordance with the requirements of Technical Specifications 4.6.4 and 4.4.3.2.2.
P DR h PDR
$b J13 MISC 85090401 - 1 l
I .
Attrchment to AECM-85/0303 l SIGNIFICANT llAZARDS CONSIDERATIONS:
The proposed technical specification change is administrative in nature in that it deletes inappropriate remote shutdown operability requirements for the containment isolation valve in the RIIR to RCIC Head Spray Line from Technical Specification i Table 3.3.7.4-1. The proposed change does not involve a change to the valve itself.
The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated or create the possibility of a new or different kind of accident from any accident previously evaluated because the l valve's primary function is containment and reactor coolant i
boundary isolation, it is normally closed and its operability l 1s not assumed for any safe shutdown or accident analysis.
\
l The proposed change does not involve a significant reduction in i a margin of safety because remote shutdown operability of the l valve is not required for safe shutdown.
l l Therefore, the proposed change involves no significant hazards l
considerations.
l l
l l
l I
l J13HISC85090401 - 2
INSTRUMENTATION TABLE 3.3.7.4-1 (Continued)
REMOTE SHUTDOWN SYSTEM CONTROLS MINIMUM CHANNELS OPERABLE CONTROL Div 1 Div 2
- 12. RHR Injection Valves D b 2 2
- 13. RHR Test Line Valve 1 1
- 14. RHR HX Cond. to RCIC Valve 1 1
- 15. RHR HX Flow to Suppression Pool Valve 1 1
- 16. RHR Discharge to Radwaste Valve 1 1
- 17. b b RCIC Steam to RHR HX Valve 2 2
- 18. Diesel Generator HX Inlet Valve 1 1
- 19. Safety / Relief Valves b b 6 6
- 20. to k C liead Spray Lir.c Valve 1 " ^ -
- 21. RCIC Turbine Flow Controller 1 NA
- 22. RCIC Suction Flow Suppression Pool Valve 1 NA
- 23. RCIC Injection Shutoff Valve 1 NA
- 24. RCIC Suction From CST 1 NA
- 25. RCIC Recire. Nain Flow Bypass Valve 1 NA
- 26. RCIC Test M V to CST IB va/u OB 1 NA f
00
- 27. RCIC Test RTN to CSTA Valve 1 NA
- 28. Steam to RCIC Turbine Valve 1 NA
- 29. RCIC Turbine Trip & Throttle Valve 1 NA
- 30. RCIC Turbine Cooling Water Valve 1 NA
- 31. RCIC Turbine Local Control Select Switch 1 NA
- 32. RCIC Gland Seal Compressor 1 NA
- 33. Shutdown Cooling Isolation Valve Reset Switch 1 1 NOTE: a. 1 per cooling tower fan
- b. I per valve GRAND GULF-UNIT 1 3/4 3-71 Amendmen t No. __ l
. - - - _ __
Text
.-- . - . - ~ . - - _. - . ~_ --- __ - . - .
l . Attachmnt to AECM-85/0303
SUBJECT:
NLS-85/10 Technical Specification Table 3.3.7.4-1, page 3/4 3-71 ;
1 i
DISCUSSION: It is proposed to delete item 20. RHR to RCIC Head Spray Line Valve, from the subject Remote Shutdown System Controls table. l (It should be noted that the affected technical specification ,
page reflects change NPE-85/06 previously requested by MP&L l serial AECM-85/0228, dated August 12,1985.)
JUSTIFICATION: The original design of the Reactor Core Isolation Cooling (RCIC) system incorporated coolant injection into the vessel !
head through the RHR Head Spray line. Design evolution resulted !
in this injection path design being abandoned in favor of the conventional injection path through the feedwater line used in earlier BWR designs. Operability of the RHR to RCIC Head Spray .
Line Valve is therefore not required for RCIC injection to the vessel. The remaining functions of the valve are to provide l an injection path for RHR Head Spray, which is not a safety
( function, and to provide containment and reactor coolant
! boundary isolation as required. The head spray function could .
be used to aid in the transition from hot to cold shutdown by introducing spray into the steam done to directly cool and condense steam in the vessel, thereby reducing pressure and ;
temperature. However, RHR Head Spray is not required to effect safe shutdown of the reactor or mitigate the consequences of any ,
event analyzed in the CCNS FSAR.
A design change has been partially implemented which added a second motor operated valve to this line that in intended to serve as the containment isolation valve for this line. Qh valve will be powered from a separate ESF division than that of the valve which this change addresses, and is located inside the drywell. After approval of the requested license amendment which will allow this valve to be credited with the containment isolation function (see the MP&L memorandum dated August 12, 1985, O. D. Kingsley, Jr., to Mr. Harold R. Denton, MP&L serial '
AECM-85/0228), the new valve will be closed and help to provide ,
redundant assurance that the line will remain isolated and !
diversion of coolant flow through the head spray line during !
shutdown cooling or LPCI operation will not occur. ]
i Since the valve is not assumed for any safe shutdown or accident '
analysis, operability of it from the remote shutdown panel is not required, and the requirements of specification 3.3.7.4 are ;
not applicable. Operability of the valve for the containment ,
and reactor coolant boundary isolation function will continue to be maintained in accordance with the requirements of Technical Specifications 4.6.4 and 4.4.3.2.2.
P DR h PDR
$b J13 MISC 85090401 - 1 l
I .
Attrchment to AECM-85/0303 l SIGNIFICANT llAZARDS CONSIDERATIONS:
The proposed technical specification change is administrative in nature in that it deletes inappropriate remote shutdown operability requirements for the containment isolation valve in the RIIR to RCIC Head Spray Line from Technical Specification i Table 3.3.7.4-1. The proposed change does not involve a change to the valve itself.
The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated or create the possibility of a new or different kind of accident from any accident previously evaluated because the l valve's primary function is containment and reactor coolant i
boundary isolation, it is normally closed and its operability l 1s not assumed for any safe shutdown or accident analysis.
\
l The proposed change does not involve a significant reduction in i a margin of safety because remote shutdown operability of the l valve is not required for safe shutdown.
l l Therefore, the proposed change involves no significant hazards l
considerations.
l l
l l
l I
l J13HISC85090401 - 2
INSTRUMENTATION TABLE 3.3.7.4-1 (Continued)
REMOTE SHUTDOWN SYSTEM CONTROLS MINIMUM CHANNELS OPERABLE CONTROL Div 1 Div 2
- 12. RHR Injection Valves D b 2 2
- 13. RHR Test Line Valve 1 1
- 14. RHR HX Cond. to RCIC Valve 1 1
- 15. RHR HX Flow to Suppression Pool Valve 1 1
- 16. RHR Discharge to Radwaste Valve 1 1
- 17. b b RCIC Steam to RHR HX Valve 2 2
- 18. Diesel Generator HX Inlet Valve 1 1
- 19. Safety / Relief Valves b b 6 6
- 20. to k C liead Spray Lir.c Valve 1 " ^ -
- 21. RCIC Turbine Flow Controller 1 NA
- 22. RCIC Suction Flow Suppression Pool Valve 1 NA
- 23. RCIC Injection Shutoff Valve 1 NA
- 24. RCIC Suction From CST 1 NA
- 25. RCIC Recire. Nain Flow Bypass Valve 1 NA
- 26. RCIC Test M V to CST IB va/u OB 1 NA f
00
- 27. RCIC Test RTN to CSTA Valve 1 NA
- 28. Steam to RCIC Turbine Valve 1 NA
- 29. RCIC Turbine Trip & Throttle Valve 1 NA
- 30. RCIC Turbine Cooling Water Valve 1 NA
- 31. RCIC Turbine Local Control Select Switch 1 NA
- 32. RCIC Gland Seal Compressor 1 NA
- 33. Shutdown Cooling Isolation Valve Reset Switch 1 1 NOTE: a. 1 per cooling tower fan
- b. I per valve GRAND GULF-UNIT 1 3/4 3-71 Amendmen t No. __ l
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