Letter Sequence Approval |
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Results
Other: AECM-82-492, Requests That License Condition 2.C.(44)(i)(a) Be Revised to Require Submittal Re Automatic Depressurization Sys Logic Mods by 821215.Previous Submittal Date of 821029 Erroneously Requested Due to Revised BWR Owners Group Schedule, AECM-82-603, Comments on BWROG-8260, NUREG-0737,Item II.K.3.18,Mod of Automatic Depressurization Sys Logic. Option 4,providing Bypass Timer Delay,Will Assure Adequate Core Cooling During Worst Case Conditions, AECM-85-0014, Forwards Addl Info,Requested in ,Re Concerns Involving Transfer of Control to Remote Shutdown Panel Resulting in Change in Operating Status of Load That May Be Detrimental to Safe Shutdown, AECM-85-0341, Forwards Addl Info Re ECCS Performance Analysis Which Supports Increase in Peak Cladding Temp of 51 F Compared to Current FSAR Analysis,Per Request.Fsar Changes Will Be Made If Design Change Implemented, AECM-86-0006, Forwards Technical Justification for Proposal to Delete Peak Recording Accelerographs Currently Installed on Reactor Piping Locations,Per Section 16.3.1 of Sser 6 (NUREG-0831).Response by 860228 Requested.Fee Paid, AECM-86-0329, Submits List of Affected Tech Spec Pages,Effective Dates & Associated Amend Numbers,In Response to NRC 860827 & 1006 Requests, AECM-86-0332, Advises of Effective Dates for Amends 6 & 8 to License NPF-29 for Listed Tech Specs,In Response to 851021 & 860827 Requests, ML20133P171, ML20154R546, ML20209D136, ML20209D152, ML20210L795, ML20215E405
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MONTHYEARAECM-82-492, Requests That License Condition 2.C.(44)(i)(a) Be Revised to Require Submittal Re Automatic Depressurization Sys Logic Mods by 821215.Previous Submittal Date of 821029 Erroneously Requested Due to Revised BWR Owners Group Schedule1982-10-21021 October 1982 Requests That License Condition 2.C.(44)(i)(a) Be Revised to Require Submittal Re Automatic Depressurization Sys Logic Mods by 821215.Previous Submittal Date of 821029 Erroneously Requested Due to Revised BWR Owners Group Schedule Project stage: Other AECM-82-603, Comments on BWROG-8260, NUREG-0737,Item II.K.3.18,Mod of Automatic Depressurization Sys Logic. Option 4,providing Bypass Timer Delay,Will Assure Adequate Core Cooling During Worst Case Conditions1982-12-14014 December 1982 Comments on BWROG-8260, NUREG-0737,Item II.K.3.18,Mod of Automatic Depressurization Sys Logic. Option 4,providing Bypass Timer Delay,Will Assure Adequate Core Cooling During Worst Case Conditions Project stage: Other AECM-85-0014, Forwards Addl Info,Requested in ,Re Concerns Involving Transfer of Control to Remote Shutdown Panel Resulting in Change in Operating Status of Load That May Be Detrimental to Safe Shutdown1985-01-17017 January 1985 Forwards Addl Info,Requested in ,Re Concerns Involving Transfer of Control to Remote Shutdown Panel Resulting in Change in Operating Status of Load That May Be Detrimental to Safe Shutdown 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 ML20133P1711985-08-12012 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-85-0304, Application for Amend to License NPF-29,supplementing 850812,23 & 30 Submittals,To Provide Justification for Exemption from Tech Spec 6.3.1 & 6.4.1 Requirements for Senior Reactor Operator Qualifications1985-09-25025 September 1985 Application for Amend to License NPF-29,supplementing 850812,23 & 30 Submittals,To Provide Justification for Exemption from Tech Spec 6.3.1 & 6.4.1 Requirements for Senior Reactor Operator Qualifications Project stage: Supplement ML20133A7611985-09-25025 September 1985 Proposed Changes to Tech Specs 6.3.1 & 6.4.1,providing Justification for Exemption from Requirements for Senior Reactor Operator Qualifications Project stage: Request AECM-85-0306, Responds to Request for Addl Info Re 850812 Application for Amend to License NPF-29.Prompt Resolution of Questions & Approval of Previously Submitted Tech Specs Needed for Outage Scheduled to Start on 8510121985-10-0505 October 1985 Responds to Request for Addl Info Re 850812 Application for Amend to License NPF-29.Prompt Resolution of Questions & Approval of Previously Submitted Tech Specs Needed for Outage Scheduled to Start on 851012 Project stage: Request AECM-85-0341, Forwards Addl Info Re ECCS Performance Analysis Which Supports Increase in Peak Cladding Temp of 51 F Compared to Current FSAR Analysis,Per Request.Fsar Changes Will Be Made If Design Change Implemented1985-10-22022 October 1985 Forwards Addl Info Re ECCS Performance Analysis Which Supports Increase in Peak Cladding Temp of 51 F Compared to Current FSAR Analysis,Per Request.Fsar Changes Will Be Made If Design Change Implemented Project stage: Other ML20137Q8971985-11-22022 November 1985 Safety Evaluation Re Low Pressure ECCS Sys Pressure Permissive Interlocks.Exceeding ASME Code Allowable Design Pressure for Interlocks Unacceptable Project stage: Approval ML20137Q8901985-11-22022 November 1985 Forwards Safety Evaluation Re 850812 Request for Amend to License NPF-29,adding Pressure Permissive Interlocks to Control Circuits for Low Pressure ECCS Injection Valves,Item 13 of 850812 Request Should Be Revised Project stage: Approval AECM-86-0006, Forwards Technical Justification for Proposal to Delete Peak Recording Accelerographs Currently Installed on Reactor Piping Locations,Per Section 16.3.1 of Sser 6 (NUREG-0831).Response by 860228 Requested.Fee Paid1986-01-10010 January 1986 Forwards Technical Justification for Proposal to Delete Peak Recording Accelerographs Currently Installed on Reactor Piping Locations,Per Section 16.3.1 of Sser 6 (NUREG-0831).Response by 860228 Requested.Fee Paid Project stage: Other AECM-86-0082, Supplemental Application for Amend to License NPF-29, Modifying 851114 Proposed Change Re License Condition 2.C.(28) & Revising Tech Specs Concerning Design Changes to Be Implemented During First Refueling Outage.Fee Paid1986-03-21021 March 1986 Supplemental Application for Amend to License NPF-29, Modifying 851114 Proposed Change Re License Condition 2.C.(28) & Revising Tech Specs Concerning Design Changes to Be Implemented During First Refueling Outage.Fee Paid Project stage: Supplement ML20154R5461986-03-21021 March 1986 Proposed Tech Specs Revising License Condition 2.C.(28) Re Requirement for Corporate Mgt Officials on Nuclear Operations Staff & Modifying Tables 3.3.7.2-1 & 4.3.7.2-1 to Reflect Design Change Project stage: Other ML20155D8101986-04-0808 April 1986 Summary of 860401 Meeting W/Utils Re Resolution of Issue of Interlocks for ECCS Injection Valves Which Also Function as Pressure Isolation Valves.Viewgraphs & List of Attendees Encl Project stage: Meeting ML20205S2021986-05-27027 May 1986 Forwards Safety Evaluation Supporting Util 860110 Proposal to Remove Four Peak Recording Accelerographs Installed on Reactor Piping Due to Inoperability Caused by Operating Transients & Adequacy of Other Seismic Instrumentation Project stage: Approval ML20205S2151986-05-27027 May 1986 Safety Evaluation Supporting Util 860110 Proposal to Remove Four Peak Recording Accelerographs Mounted on Reactor Piping Project stage: Approval AECM-86-0163, Provides Addl Info to 860321 Proposed Change PCOL-86/04 to License NPF-29 Re Mods to Automatic Depressurization Sys Per BWR Owners Group Evaluation of NUREG-0737,Item II.K.3.18. Info Clarifies Changes Made to Sys Initiation Circuitry1986-05-30030 May 1986 Provides Addl Info to 860321 Proposed Change PCOL-86/04 to License NPF-29 Re Mods to Automatic Depressurization Sys Per BWR Owners Group Evaluation of NUREG-0737,Item II.K.3.18. Info Clarifies Changes Made to Sys Initiation Circuitry Project stage: Request AECM-86-0111, Forwards Supplemental Info Re Design Change to Add Interlocks to ECCS Injection Valves,Per NRC 860403 Telcon. Approval of 850812 Proposed Amend to Tech Specs Also Requested1986-05-30030 May 1986 Forwards Supplemental Info Re Design Change to Add Interlocks to ECCS Injection Valves,Per NRC 860403 Telcon. Approval of 850812 Proposed Amend to Tech Specs Also Requested Project stage: Supplement ML20207E7261986-07-15015 July 1986 Proposed Changes to Tech Spec Seismic Monitoring Instrumentation Tables 3.3.7.2-1 & 4.3.7.2-1 to Delete four- Peak Recording Accelerographs on Reactor Piping & Make Measurement Values Consistent Project stage: Request AECM-86-0208, Forwards Addl Info Re Emergency Containment Venting in Response to Item 1.1 of 860527 Request.Encl Rev 1 to ...Emergency Procedures Upgrade Program Procedures Generation Package Addresses Remaining Request1986-07-15015 July 1986 Forwards Addl Info Re Emergency Containment Venting in Response to Item 1.1 of 860527 Request.Encl Rev 1 to ...Emergency Procedures Upgrade Program Procedures Generation Package Addresses Remaining Request Project stage: Request AECM-86-0221, Application for Amend to License NPF-29,changing Tech Spec Seismic Monitoring Instrumentation Tables to Delete four- Peak Recording Accelerographs on Reactor Piping & Make Measurement Values Consistent.Fee Paid1986-07-15015 July 1986 Application for Amend to License NPF-29,changing Tech Spec Seismic Monitoring Instrumentation Tables to Delete four- Peak Recording Accelerographs on Reactor Piping & Make Measurement Values Consistent.Fee Paid Project stage: Request ML20209D1521986-08-28028 August 1986 Notice of Consideration of Issuance of Amend to License NPF-29 & Proposed NSHC Determination & Opportunity for Hearing Re Addition of Specs to Table 3.3.3-1, ECCS Actuation Instrumentation Project stage: Other ML20210L7951986-08-28028 August 1986 Notice of Consideration of Issuance of Amend to License NPF-29 & Proposed Nhsc Determination & Opportunity for Hearing Re 850812,0925,1005 & 22 Requests for Revs to Listed Tech Spec Tables on ECCS Actuation Instrumentation Project stage: Other ML20209D1361986-09-0202 September 1986 Requests Notice of Consideration of Issuance of Amend to License NPF-29 & Proposed NSHC Determination & Opportunity for Hearing Re Addition of Specs to Table 3.3.3-1, ECCS Actuation Instrumentation Be Expeditiously Published in Fr Project stage: Other ML20215E4051986-10-0606 October 1986 Amend 20 to License NPF-29,revising Tech Specs to Reflect Installation of Pressure Interlocks for Injection Valves in Low Pressure ECCS & Mod to Automatic Depressurization Sys Actuation Logic Project stage: Other ML20215E4131986-10-0606 October 1986 Safety Evaluation Supporting Amend 20 to License NPF-29 Project stage: Approval AECM-86-0329, Submits List of Affected Tech Spec Pages,Effective Dates & Associated Amend Numbers,In Response to NRC 860827 & 1006 Requests1986-10-14014 October 1986 Submits List of Affected Tech Spec Pages,Effective Dates & Associated Amend Numbers,In Response to NRC 860827 & 1006 Requests Project stage: Other AECM-86-0332, Advises of Effective Dates for Amends 6 & 8 to License NPF-29 for Listed Tech Specs,In Response to 851021 & 860827 Requests1986-10-17017 October 1986 Advises of Effective Dates for Amends 6 & 8 to License NPF-29 for Listed Tech Specs,In Response to 851021 & 860827 Requests Project stage: Other 1986-10-14
[Table View] |
Safety Evaluation Re Low Pressure ECCS Sys Pressure Permissive Interlocks.Exceeding ASME Code Allowable Design Pressure for Interlocks Unacceptable| ML20137Q897 |
| Person / Time |
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| Site: |
Grand Gulf  |
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| Issue date: |
11/22/1985 |
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| From: |
NRC |
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| To: |
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| Shared Package |
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| ML20137Q894 |
List: |
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| References |
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| TAC-59440, NUDOCS 8512050379 |
| Download: ML20137Q897 (6) |
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Text
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Enclosure SAFETY EVALUATION GRAND GULF UNIT 1 LOW PRESSURE ECCS SYSTEM PRESSURE PERMISSIVE INTERLOCKS Facility Operating License NPF-29, Condition 2.C.(18) requires the licensee to implement isolation protection against overpressurization of the low pressure emergency core cooling systems (RHR/LPCI and LPCS) through the implementation of reactor vessel pressure permissive interlocks. The licensee has proposed Technical Specification (T.S.) changes to support the required design change.
-The Instrumentation and Control Systems Branch (ICSB) focused its review on the revisions to T.S. Tables 3.3.3-1 and 4.3.3.1-1.
The Reactor Systems Branch with the assistance of the Mechanical Engineering Branch focused its attention on systems and piping design aspects of the proposed changes.
Instrumentation and Control Systems Aspects The licensee proposes to include the new high/ low pressure permissive inter-locks for the low pressure ECCS injection valves in T.S. Table 3.3.3-1 (ECCSActuationInstrumentation). The Technical Specifications will require a minimum of three channels operable for all operating conditions with Action 31 (declare ADS trip system or ECCS inoperable) applicable for Operating Conditions 1, 2, and 3 and Action 35 (trip inoperable channel after one hour or declare associated systems inoperable) applicable for Operating Conditions 4 and 5.
Upon request, the licensee provided information (Letter dated October 5,1985) to clarify what constitutes a channel for the pressure 8512050379 851122 PDR ADOCK 05000416 P
PDR
2 permissive interlocks. The licensee states that the minimum requirement of 3 operating channels per trip function is applicable to the "one-out-of-two twice" logic utilized in the design change and is adequate to assure operability of the required low pressure injection function considering the diversity of injection systems and logic channels available (four per trip function).
The licensee also proposes to add the surveillance requirements for the new interlock channels to T.S. Table 4.3.3.1-1 (ECCS Actuation Instrumentation Surveillance Requirements). The surveillance frequencies will be once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for channel check, once per month for channel functional test, and once per refueling cycle for channel calibration for all operating conditions.
Based on the above information, the staff finds the channel operability require-ments proposed for revised T.S. Table 3.3.3-1 to be acceptable. We also' find the channel surveillance frequencies proposed in T.S. Table 4.3.3.1-1 to be acceptable.
After implementation of the proposed design, the high/ low pressure permissive interlocks for the low pressure ECCS injection valves will be active for both automatic and manual control room operation.
The licensee has proposed not to include such an interlock for the remote shutdown panel (RSP) control circuits for the ECCS injection valves. Based on the current information provided by the licensee, the staff finds the requested interlock omission to be unacceptable.
- It is the staff's position that pressure permissive interlocks should be installed as part of the RSP control circuits consistent with the corresponding control room control circuits. This position is based on the Standard Review Plan (SRP Section 7.4) interpretation of GDC 19 which requires that the remote shutdown station equipment be designed to the same standards as the corre-sponding equipment in the main control room. Also, Section 6.3.4 of the Grand Gulf, Unit 1 SER Supplement No. 2 requires that interlocks be present at all times for both manual and automatic actuation unless the reactor vessel pressure is lower than the design pressure of the ECCS involved. Thus, without special control over the operation of these valves, inadvertent operation must be assumed from the RSP which could result in overpressurization of the low pressure ECCS.
The following is an acceptable alternative (method of special control) to the implementation of pressure permissive interlocks for the RSP control circuits associated with the low pressure ECCS injection valves:
(1) the provision of spring-return-to-normal control switches on the RSPs which would alleviate the concern related to the change-of-state of equipment upon transfer of control to the l
RSP and (2) (A) Continue to implement special Technical Specification j
4.4.3.2.2.b for LPCS and LPCI outboard check valves to ensure integrity since the licensee takes credit for these valves as part of the omission justification, or
_4 i
(B)
Implementation of a keylocked control switch separate from the RSP controls (preferably at MCC) which would block operation of the valve via the RSP control. This should include administrative controls to ensure that RSP control of the valve is actually blocked when the valve is closed.
Also, valve position indication should not be negated in the control room or at the RSP by the implementation of this special control scheme.
Systems and Piping Design The licensee has proposed Technical Specification (TS) changes regarding the low pressure ECCS injection system, in response to an NRC position regarding the prevention of an intersystem LOCA which was expressed in Supplement No. 2 to the Grand Gulf Nuclear Station (GGNS) Safety Evaluation Report (NUREG-0831) and which became License Condition 2.C.(18)..
These TS changes would implement design changes adding pressure interlocks to the injection valves on the low pressure ECCS systems, require respective trip setpoints, and require periodic l
surveillance of associated ECCS actuation instrumentation.
l l
Two of the proposed changes are administrative in nature.
For instance, in connection with the installment of pressure interlocks, an additional trip function has been added to the ECCS low pressure systems. The minimum number l
of operable channels, applicable. operational conditions, and action to be
4..
. taken are supplied for the new trip function (see Tables 1 and 2).
Instru-mentation surveillance intervals are also designated for this function (see Table 3). These proposals are acceptable to us, as discussed above.
In the original submittal, MP&L proposed to delete ECCS response times for low pressure systems. Subsequently, in a letter dated September 25, 1985, MD&L proposedtouse"f29 seconds"asresponsetimesforbothLPCIandLPCSinjection valves. This is acceptable to us because this response time is within the value used in analyses of loss of coolant accidents.
One issue that has not been resolved is the interlock setpoint for the high pressure to low pressure interface valve. The setpoint 534 psig, is above the design pressure of the low pressure system, 500 psig. The ASME Code, dated 1977, which was the first Code edition to address such interlocks, required the interlocks to prevent the pressure from exceeding the design pressure of the low pressure side. Section 6.3.4 of GGNS SSER's (June 1982),
states that the valves in question should be " interlocked to prevent opening unless the reactor vessel pressure is lower than the design pressure of the ECCSs involved." From discussions with the licensee, we understand that main-taining the setpoint below the design pressure will result in increased peak cladding temperature for. the postulated loss of accident from 2151*F to 2157*F, which is still less than the limiting value of 2200*F required by 10 CFR 50.46. The staff concludes that exceeding the Code allowable design pressure for the interlocks is unacceptable because the Code position can be
- met without reducing the acceptable margin of safety for peak cladding temperature.
If meeting the Code requirement results in a hardship, the hardship should be described and justification should be provided for our consideration.
Include in the justification the results of an analysis to show that pressure in the ECCS piping equal to the upper analytical limit of the interlock setpoint will satisfy the ASME Code stress allowable values for the piping, valves and other components of the affected portions of the ECCS.
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