Letter Sequence Other |
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MONTHYEARML20203N4171986-04-30030 April 1986 Rev 2 to Tdi Owners Group App Ii:Generic Maint Matrix & Justifications Project stage: Other ML20199L6241986-06-26026 June 1986 SER Re Operability/Reliability of Tdi Emergency Diesel generator.Three-phase Plan for Assuring Generator Reliability Discussed.Sample License Conditions Encl Project stage: Other ML20199L5971986-06-26026 June 1986 Forwards Generic SER of Operability/Reliability of Emergency Diesel Generators Mfg by Tdi.Plans for Program Implementation Requested by 860715 Project stage: Other AECM-86-0172, Explains Actions in Response to Final Evaluations from Tdi Owners Group Program & Plans for Implementation of Programs Identified in NRC SER of Operability/Reliability of Tdi Emergency Diesel Generators.Fee Paid1986-07-18018 July 1986 Explains Actions in Response to Final Evaluations from Tdi Owners Group Program & Plans for Implementation of Programs Identified in NRC SER of Operability/Reliability of Tdi Emergency Diesel Generators.Fee Paid Project stage: Other ML20210E2471986-09-12012 September 1986 Proposed Tech Specs,Adding Addl Controls Re Maint & Surveillance & Mods of Tdi Owners Group Recommendations Project stage: Other AECM-86-0282, Application for Amend to License NPF-29,adding Addl Controls Re Maint & Surveillance & Mods of Tdi Owners Group Recommendations to Enhance Emergency Diesel Program.Fee Paid1986-09-12012 September 1986 Application for Amend to License NPF-29,adding Addl Controls Re Maint & Surveillance & Mods of Tdi Owners Group Recommendations to Enhance Emergency Diesel Program.Fee Paid Project stage: Request ML20213G0931986-11-0707 November 1986 Requests Deletion of Parenthetical Expressions Added to 860912 Proposed Change to License Condition 2.C.(25)(b),per 860929 Telcon.Change Proposed to Be Consistent W/Ser Re Tdi Emergency Diesel Generators.Expressions No Longer Necessary Project stage: Request AECM-86-0394, Forwards Application for Amend to License NPF-29,revising Tech Specs for Diesel Generator Testing,Allowed out-of-svc Time & Surveillance Requirements for Offsite & Onsite Ac Electrical Sources.Fee Paid1986-12-0909 December 1986 Forwards Application for Amend to License NPF-29,revising Tech Specs for Diesel Generator Testing,Allowed out-of-svc Time & Surveillance Requirements for Offsite & Onsite Ac Electrical Sources.Fee Paid Project stage: Request 1986-04-30
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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
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sf Attachment 1 OLCR-NLS-86/D3 SLBJECT: Facility Operating License No. NPF-29, Page 9, License Condition 2.C.(25)(b) TDI Emergency Diesel Generators DESCRIPTION OF CHANGE:
Mississipp(iPower& Light be Condition 0LC) 2.C.(25)(b) (MP&L)proposesthatOperatingLicense changed to the following:
(b) NP&L shall comply with the TDI emergency diesel generator requirements specified in Attachment 2 to this license.
It is proposed that Attachment 2 to this submittal will become Attachment 2 to Facility Operating License No. NPF-29.
DISCUSSION: In response to concerns regardin Transamerica Delaval, Inc. (TDI)g the overall emergency dieselreliability of a generators, TDI Diesel Generator Owners Group (TDI OG) was formed to address operational and regulatory issues relative to TDI diesel generator sets used for standby emergency power at nuclear power stations. The TDI OG submitted on March 2, 1984 a program to the NRC proposing a combination of design reviews, quality revalidations, engine tests and component inspections to provide an in depth assessment of the adequacy of the TDI emergency diesel generators (EDG) to perform their safety related function.
In . lune of 1986 the NRC Safety Evaluation Report of the Operability / Reliability of Emergen:y Diesel Generators Manufactured by Transamerica Delaval, Inc. (NRC Generic SER) provided the NRC staff's final evaluation of the findings and recommendations of the TDI OG and Pacific Northwest Laboratory (under contract to the NRC). The NRC Generic SER specified the actions necessary to resolve issues surrounding the TDI EDGs for all affected utilities. Resolution of the issue for the Grand Gulf Nuclear Station (GGNS) requires incorporating the recommendations of the TDI OG and the NRC Generic SER into the GGN5 EDG progran. In addition, the NRC Generic SER specified that certain key maintenance and surveillance recommendations be a condition of the Operating License. The proposed license condition for GGNS is described above and in Attachment 2 to this submittal.
On July 18, 1986 MP&L submitted proposed actions in response to the final evaluations and recommendations from the TDI OG Program as required by GGNS OLC 2.C.(25)(b) and MP&L's plans for implementation of the actions specified in the NRC Generic SER.
6609220100 860912 ADR ADOCK 05000416 P PDR J16ATTC86080801 - 1
Attachment 1 MP&L proposes that OLC 2.C.(25)(b) be revised from the present requirement to the License Condition as stated in the Description of Change.
JUSTIFICATION: By letter dated July 18, 1986 (AECM-86/0172), MP&L submitted actions in response to the final evaluations and recommendations from the TDI OG Program applicable to GGNS Unit 1, as required by OLC 2.C.(25)(b). It is MP&L's position that this submittal satisfiedthepresentOLC2.C.(25)(b). The NRC Generic SER requires that the Operating License for GGNS contain key TDI EDG maintenance and surveillance actions to ensure implementation. The NRC Generic SER contains detailed justification for the proposed key component recommendations.
In Part 1 of the license condition entitled " GENERAL" (Attachment 2), MPAL proposes to utilize the 10 CFR 50.59 process to evaluate any changes to TDI OG recommendations, with the exception of Phase 1 component recomendations. The provisions of the 10 CFR 50.59 process ensures (1) a technical basis exists for any proposed change, (2) that an unreviewed safety question is not involved and (3) provides for periodic NRC review of the basis for determining that an unreviewed safety question is not involved in the revision of a TDI OG recenmendation.
Additionally, the staff has required that the key maintenance and surveillance actions be a condition of the operating license at GGNS, thus ensuring that changes relative to the key TDI OG and Pacific Northwest Labs recommendations are subject to NRC appraval pr ior to revision.
The frequency of major engine overhauls referenced in Attachment 2 is a TDI OG recommendation and is included to define the overhaul frequency for specific components. The original major overhaul frequency was based on a TDI recommendation for engines which were in continuous service. Engines in emergency standby service receive only a small fraction of the service time that continuous service engines receive. For this reason the major engine overhaul frequency was increased from 5 year intervals to 10 year intervals. Additionally, a one time inspection after 5 years of engine service, will be performed on major engine components. The retcrence to frequency of major overhaul is consistent with the " Semple License Condition" as presented in Appendix A to the NRC Generic SEP.
The maintenance and surveillance actions for key components of the GGNS EDGs are derived from the appl 1rable sections of the NRC Generic SER. These maintenance and surveillance requirements will insure that key components rem a special emphasis. L The proposed change to the license condition will wd additienal controls regardir.g maintenance, survri~ nco ami rodification et TDI N recowandations. These con unis will enhance the GGNS 101 EDG prcgran by providina furtW acsunna of the adcQuacy of the TD1 FDtPs to perform their saMy related functicn.
J16ATTC86080001 - 2
- - -___ ______ - ._ _ _ J
Attachment 1 SIGNIFICANT HAZARDS CONSIDERATION:
The proposed change to the operating license condition does not involve:
- 1) a significant increase in the probability or consequences-of a previously evaluated accident because:
the proposed change adds requirements to the operating license for certain key _rmintenance and surveillance actions consistent with the guidance in the NRC Generic SER on the TDI EDG reliability. The proposed change also applies- the 10CFR50.59 process for evaluating future changes to other TDI OG recommendations. These additional requirements help to ensure the EDGs are capable of performing their intended function and do not affect the assumptions of any previously evaluated accident. Thus, the probability or consequences of a previously evaluated accident is not changed.
- 2) creating the possibility of a new or different kind of accident from any previously evaluated accident because:
the placement in the operating license of additional controls on EDG maintenance and surveillance actions does not create a new or different kind of accident. In addition, evaluation of changes to other TDI OG recommendations utilizing the 10CFR50.59 process provides added assurance that new or different kinds of accidents are not created.
- 3) a significant reduction in a margin of safety because:
th aeditional controls are intended to place special s phasis on maintenance and surveillance activities and thereby enhance the reliability ^f the EDGs to perform their safety function. Thus, the margin of safety is not reduced.
In summary, MP&L concludes that the proposed change to the operating license do not involve a significant hazards consideration.
J16AT1C86000301 + 3 C
Attachment 2 PROPOSED LICENSE CONDITION TDI EMERGENCY DIESEL GENERATOR
- 1. General Changes to the GGNS DR/QR report recommendations as identified in MP&L letters dated November 28, 1984 - AECM-84/0525, April 16, 1985 -
AECM-85/120, July 18, 1986 - AECM-86/0172, with the exception of Phase 1 component recommendations, shall be subject to the provisions of 10CFR50.59.
The frequency of the major engine overhauls referred to in the license conditions below shall be consistent with Section IV.1. " Overhaul Frequency" in Revision 2 of Appendix II of the Design Review / Quality Revalidation report which was transmitted by letter dated May 1, 1986, from J. George, Owners Group, to H. Denton, NRC.
- 2. Connecting Rods Connecting rod assemblies shall be subjected to the following inspections at each major engine overhaul:
- a. The surfaces of the rack teeth should be inspected for signs of fretting. If fretting has occurred, it should be subject to an engineering evaluation for appropriate corrective action.
- b. All connecting-rod bolts should be lubricated in accordance with the engine manufacturer's instructions and torqued to the specifications of the manufacturer. The lengths of the two pairs of bolts above the crankpin should be measured ultrasonically pre and post-tensioning.
- c. The lengths of the two pair of bolts above the crankpin should be
~
measured ultrasonically prior to dete:nsioning and disassembly of the bolts. If bolt tension is less than an equivalent of 2400 ft-lbs, the cause should be determined, appropriate corrective action should be taken, and the interval between checks of bolt tension should be re-evaluated,
- d. All connecting-rod bolts should be visually inspected for thread damage (e.g., galling), and the two pairs of connecting rod bolts above the crankpin should be inspected by magnetic particle testing (MT) to verify the continued absence of cracking. All washers used with the bolts should be examined visually for signs of galling or cracking, and replaced if damaged,
- e. A visual inspection should be performed of accessible external surfaces of the link rod box to verify the absence of any signs of service induced distress,
- f. All of the bolt holes in the link rod box should be inspected for thread damage (e.g., galling) or other signs of abnormalities. In addition, the bolt holes subject to the highest stresses (i.e., the pair immediately above the crankpin) should be examined with an J16ATTC86080801 - 4
Attachment 2 1
appropriate nondestructive method to verify the continued absence of.
cracking. Any indications should be recorded for engineering evaluation and appropriate corrective action.
- g. The following actions shall be performed if the engines are operated in excess of 5740 KW steady state: n All connecting rods shall be disassembled and inspected at an interval of approximately 5 years coincident with end of cycle.
The above connecting rod disassembly and inspection interval is not required for limited post maintenance testing over 5740 KW for the purpose of seating new piston rings as described in MP&L letter AECM-85/0395 dated December 6, 1985.
- 3. Cylinder Blocks
- a. Cylinder blocks shall be inspected for " ligament" cracks,
" stud-to-stud" cracks and " stud-to-end" cracks as defined in a report
- by Failure Analysis Associates, Inc. (FaAA) entitled,
" Design Review of TDI R-4'and RV-4 Series Emergency Diesel Generator Cylii m. Blocks" (FaAA report no. FaAA-84-9-11.1) and dated December 1984. (Note that the FaAA report specifies additional inspections to be performed for blocks with "known" or " assumed" ligament cracks).
he inspection intervals (i.e., frequency) shall not exceed the intervals calculated using the cumulative damage index model in the subject FaAA report. In addition, inspection method shall be consistent with or equivalent to those identified in the subject FaAA report.
(Condition 3.a applies to the Division I diesel generator and will apply to the Division II diesel generator upon successful completion of inspections required by Condition 3.b.)
- b. In addition to inspections specified in the aforementioned FaAA report, blocks with "known" or " assumed" ligament cracks (as defined in the FaAA report) should be inspected at each refueling outage to determine whether or not cracks have initiated on the top surface exposed by the removal of two or more cylinder heads. This process should be repeated ever several refueling outages until the entire block top has been inspected. Liquid-penetrant testing or a similarly sensitive nondestructive testing technique should be used to detect cracking, and eddy current should be used as appropriate to determine the depth of any cracks discovered.
(Condition 3.b applies to the Division II diesel generator until block top inspections per this condition are completed.)
J16ATTC86080801 - 5
'I'
. . s 7 ,
- e. g
- c. If inspection reveals cracks in the cylinder blocks between stud holes of adjacent cylinders (" stud-to-stud" cracks) or " stud-to-end"
!) .
cracks, this condition shall be reported promptly to the NRC staff-
- and the affected< engine shall be considered inoperable. The engine shall not be restored to " operable" status until the proposed disposition and/or corrective actions have been approved by the NRC
,, staff.
- 4. ' Cylinder Heads '<-
. The follnwing air 'rol.1 test shall be performed as specified below, except when the plant is. already in an Action Statement of Technical Specification 3/4.8.1, " Electric Power Systems, A.C. Sources":
+
- The engines shall be rolled over with the airstart system and with the
'sylinder stopcocks open prior to eac'n planned start, unless that start occurs within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of a shutdown. The engines shall also be rolled over with the airstart system and with the cylinder stopcocks open after 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, but no more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after engine shutdown and then rolled over once again approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after each shutdown. (In the event < an engine is removed from service for any reason other than the rolling over pr,. eaure prior to expiration of the 8-hour or 24-hour-periods noted above, that engine need not be rolled over while it is out of service. The licensee shall air roll the engine over with the stopcocks open at the time it is returned to service.) The origin of any water detected _in the cylinder must be determined and any cylinder head which leaks'due to a crack shall be replaced. The above air roll test may be discontinued following the first refueling outage subject to the following conditions:
- a. All c linder heads are Group III heads (i.e., cast after September 1980.
- b. Quality revalidation inspections, as identified in the Design Review / Quality Revalidation report, have been completed for all cylinder heads.
. c. Group III heads continue to demonstrate favorable leakage performance. This should be confirmed with TDI prior to deleting air roll tests.
- 5. Turbochargers Periodic inspections of the turbochargers shall include the following:
l
- a. The turbocharger thrust bearings should be visually inspected for excessive wear after 40 non-prelubed starts since the previous visual inspection. ;
i
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, l J16ATTC86080801 - 6 g
Attachment 2
- b. Turbocharger rotor axial clearance should be measured at each refueling outage to verify compliance with TDI/Elliott specifications. In addition, thrust bearing measurements should be compared with measurements taken previously to determine a need for further inspection or corrective action.
- c. Spectrographic and ferrographic engine oil analysis shall be performed quarterly to provide early evidence of bearing degradation. Particular attention should be paid to copper level and particulate size which could signify thrust bearing degradation.
- d. The nozzle ring components and inlet guide vanes should be visually inspected at each refueling cutage for missing parts or parts showing distress. If such are noted, the entire ring assembly should be replaced.
- This report was transmitted to H. R. Denton, NRC, from C. L. Ray, Jr.,
TDI Owners Group, by letter dated December 11, 1984.
J16ATTC86080801 - 7
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