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| $* ',,'..ja '. p / ,,' f ,1 , | | 'f, Commonwealth Edison ' |
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| ,' 4 : ji 'f, Commonwealth Edison '
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| 72 West Adams Street, Chicago, Illinois | | ,' 4 : ji 72 West Adams Street, Chicago, Illinois N:' ', |
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| N:' , | | f ATdress Reply to: Post Omc3 Box 167~ |
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| A%> . : Chicago,f ATdress Reply to: Post Omc3 Box 167~
| | %>. : Chicago, lihnois 60690 0767 ' |
| lihnois 60690 0767 ' ' | | ,.- l E i i |
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| | October 24, 1989 T. |
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| w October 24, 1989 T.
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| t , | | T Dr.-Thomas E. Murley, Director-e' Offlee of Nuclear Reactor Regulation U.S.' Nuclear Regulatory Commission Washington, DC 20555 Q, |
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| T Dr.-Thomas E. Murley, Director-Offlee of Nuclear Reactor Regulation | |
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| , U.S.' Nuclear Regulatory Commission Washington, DC 20555
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| ==Subject:== | | ==Subject:== |
| LaSalle County Station Units 1 and 2 , d Inservice Testing (IST) Program , | | LaSalle County Station Units 1 and 2 d |
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| | Inservice Testing (IST) Program l |
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| | E C Dx tet Nos. 50-373 and 50-374 q |
| l 4 | | 4 Reference (a):. H.E. Morgan letter to T.E. Murley dated' October 2, 1989 (LaSalle County Station Units'1 and 2) Inservice Testing (IST)' Program. |
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| E C Dx tet Nos. 50-373 and 50-374 q Reference (a):. H.E. Morgan letter to T.E. Murley dated' | |
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| October 2, 1989 (LaSalle County Station : | |
| Units'1 and 2) Inservice Testing (IST)' Program. | |
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| ==Dear Dr. Murley:== | | ==Dear Dr. Murley:== |
| | i Reference (a) transmitted LaSalle County Station's Inservice Testing Program (Revision 2). |
| | For clarification purposes, the attached document provides a summary of the changes made in Revision 2 of the LaSalle County. |
| | ' Station Inservice Testing Program. |
| | If'there are any further questions regarding this matter, please' f |
| | contact this office. |
| | Very truly yours, W |
| | 6: |
| | H. 4 Morgan Nuclear Licensing Administrator im Attachment i' |
| | cc: |
| | P.C. Shemanski - Project Manager, NRR AoT7 A.B. Davis - Regional Administrator, RIII I |
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| | Senior Resident Inspector - LaSalle County i |
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| | 8911010179 891024 o, |
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| | PDR ADOCK 05000373 |
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| | .P PDC a |
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| i Reference (a) transmitted LaSalle County Station's Inservice Testing ,
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| Program (Revision 2). For clarification purposes, the attached document ;
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| provides a summary of the changes made in Revision 2 of the LaSalle County.
| | ; Inservice Testing Program' i |
| ' Station Inservice Testing Program.
| | y Summary of Changes for Revision 2 i |
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| If'there are any further questions regarding this matter, please' f contact this office. -
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| * Very truly yours, W 6:
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| H. 4 Morgan Nuclear Licensing Administrator im
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| Attachment i'
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| cc: P.C. Shemanski - Project Manager, NRR AoT7 t A.B. Davis - Regional Administrator, RIII I Senior Resident Inspector - LaSalle County ' I :
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| 8911010179 891024 1: PDR ADOCK 05000373 '
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| ; Inservice Testing Program'
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| , y Summary of Changes for Revision 2
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| ==REFERENCES:== | | ==REFERENCES:== |
| : 1) AIR NO. 373-104-89-00400. documents response to Generic.
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| | AIR NO. 373-104-89-00400. documents response to Generic. |
| l Letter 89-04, . | | l Letter 89-04, i |
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| i l 2) AIR NO. 373-251-88-00226, documents review of the IST L,;
| | AIR NO. 373-251-88-00226, documents review of the IST L,; |
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| | program to the Q-List (list of safety-related components). |
| program to the Q-List (list of safety-related components). ' | |
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| ':' The Inservice. Testing Program for pumps and valves is being revised based
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| | The Inservice. Testing Program for pumps and valves is being revised based |
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| | ;m on Generic Letter 89-04 (documented in reference 1). |
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| | The scope of the IST Program was also ' reviewed carefully to ensure the inclusion of the necessary pumps and valves in the program. This was accomplished by using LaSa11e's 3 |
| ' on Generic Letter 89-04 (documented in reference 1). The scope of the IST '
| | Q-List and Component Classification documents. The following is a short |
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| 3 Program was also ' reviewed carefully to ensure the inclusion of the necessary
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| .; pumps and valves in the program. This was accomplished by using LaSa11e's ,
| | discussion of the program changes. |
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| Q-List and Component Classification documents. The following is a short ~ | |
| } discussion of the program changes.
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| | ,SECTIOt in Table of Contente f |
| ,SECTIOt in Table of Contente f
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| | A " Technical' Approach (es) and Position (s)" section was added to the j |
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| j A " Technical' Approach (es) and Position (s)" section was added to the
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| IST program, therefore, it is referenced in the ' contents section. | | IST program, therefore, it is referenced in the ' contents section. |
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| SECTION 21 Inmarvice' Testina Procram Descrintion | | SECTION 21 Inmarvice' Testina Procram Descrintion |
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| [ 2.2 - Innervlee Testina
| | 2.2 - Innervlee Testina |
| ,j, 1. Added requirement to identify approval document to each relief
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| | Added requirement to identify approval document to each relief request and cold shutdown justification (2.2.1.7). |
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| request and cold shutdown justification (2.2.1.7) . | | .Added section 2.2.3 which discusses when and why a Technical l |
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| 2.. .Added section 2.2.3 which discusses when and why a Technical ' | |
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| Approach / Position is Utilised. | | Approach / Position is Utilised. |
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| SECTIGt 31 Format Leoend and Notes | | SECTIGt 31 Format Leoend and Notes 3.0 - AEME Class 1. |
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| | 2, and 3 Pumns a |
| 3.0 - AEME Class 1. 2, and 3 Pumns | | 1. |
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| | Added " Technical Approach (es) and Position (s)" to the field section 1 |
| a 1. Added " Technical Approach (es) and Position (s)" to the field section 1
| | for pumps. The description is also given for the new field. The |
| for pumps. The description is also given for the new field. The 3 | | " notes" field was changed to No. 13. |
| " notes" field was changed to No. 13.
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| 1 | | , Inservice Testing Program-Summary.of Changes for Revisior 2 l |
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| | mad 3 Valves 3.'1 - ARMR Clama ~1. |
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| | The field section for valves has been changed. |
| ?. , Inservice Testing Program- !
| | " Technical-Approach (es) and Position (s)" was labeled No.10 and replaced the "masimum stroke time" field. The maximum stroke time will not be.a part of the NRC submittal due'to establishing limiting values of |
| Summary.of Changes for Revisior 2 l | | -f 'I full-stroke based on reference values. |
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| | 2. |
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| | Added " disassemble and inspect"'(DI) an a new test type. |
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| 3.'1 - ARMR Clama ~1. 2. mad 3 Valves , | | Test abbreviation SA (semi-annual) has been added to the " test schedule" field. |
| i | | SECTION di Innervice Testina Plan-Pumns |
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| : 1. The field section for valves has been changed. " Technical-Approach (es) and Position (s)" was labeled No.10 and replaced the "masimum stroke time" field. The maximum stroke time will not be.a ;
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| part of the NRC submittal due'to establishing limiting values of l | |
| -f 'I full-stroke based on reference values. | |
| : 2. Added " disassemble and inspect"'(DI) an a new test type. f
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| : 3. Test abbreviation SA (semi-annual) has been added to the " test .
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| schedule" field. | |
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| SECTION di Innervice Testina Plan-Pumns | |
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| : 1. .A " Technical Approach (es) and Position (s)" column was added prior to ,
| | 1. |
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| | .A " Technical Approach (es) and Position (s)" column was added prior to the'" notes" field. The " notes" column became field no.13. |
| the'" notes" field. The " notes" column became field no.13. | | SECTION 51 Pumn Relief Reauesta p |
| p SECTION 51 Pumn Relief Reauesta ;
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| | 1. |
| An " Approval / Reference Document (s)" field was added to each relief | | An " Approval / Reference Document (s)" field was added to each relief |
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| : 1. [
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| ?- request to depict the approval document or identify any applicable l | | request to depict the approval document or identify any applicable l |
| ; reference (s) used.
| | reference (s) used. |
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| | SECTION 6: |
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| | Inservice Teatino Plan - Valves Svatem Description |
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| SECTION 6: Inservice Teatino Plan - Valves | | ALL 1. |
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| | Added TP-01 to all power operated valves that are stroked timed. |
| Svatem Description | | CM 1. |
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| | All SOVs will use the " rapid-acting valves" position per RV-56. |
| ALL 1. Added TP-01 to all power operated valves that are stroked timed. | | DG 2. |
| CM 1. All SOVs will use the " rapid-acting valves" position per RV-56. | | 1(2)DG049A/B, ODG023A/B, 1(2)E22-F362A/B (DG air compressor i |
| ..
| | discharge check valves) have been classified as active class 3 components, and therefore will be tested in the IST program per 7 |
| DG 2. 1(2)DG049A/B, ODG023A/B, 1(2)E22-F362A/B (DG air compressor i discharge check valves) have been classified as active class 3 components, and therefore will be tested in the IST program per 7 | | 1 RV-51. |
| * 1 RV-51. ;
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| | , Inservice Testing program |
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| | .i Summary of Changes.for Revision 2 |
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| , Inservice Testing program
| | .J Inzervico Testl' a Plan - Valven J'~ |
| .i Summary of Changes.for Revision 2
| | SECTION 6: |
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| | System Descrintian IKi 2. |
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| | 1(2)DG055A/B, ODG029A/B, 1(2)E22-f369A/B, 1(2)E22-F370A/B (DG |
| Inzervico Testl' na Plan - Valven | | 'i' Air Receiver Check Valves) have been added to the IST program t |
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| | even=though they are non-code. 'At LaSalle they are considered 3' |
| J'~ SECTION 6: , | | to be safety-related passive, but a setpoint test will be' performed to ensure their operational readiness.- |
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| | DO 1. |
| System Descrintian | | 1(2)DOO24 have been classified as passive and will be deleted |
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| | :t from the IST program. |
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| | FC 1. |
| IKi 2. 1(2)DG055A/B, ODG029A/B, 1(2)E22-f369A/B, 1(2)E22-F370A/B (DG : | | 1(2)TC105A/B have been deleted from the IST program due to the-u fact.that FC is a non-safety related system and does not fall j |
| 'i' Air Receiver Check Valves) have been added to the IST program t even=though they are non-code. 'At LaSalle they are considered ' | | within the scope of the IST program. |
| 3' to be safety-related passive, but a setpoint test will be' .
| | l 1 |
| performed to ensure their operational readiness.- | | HG 1.. |
| DO 1. 1(2)DOO24 have been classified as passive and will be deleted | | 1(2)HG017A/B '(H2 Recombiner Water-Spray cooler supply CV's) have i |
| , from the IST program. :t u FC 1. 1(2)TC105A/B have been deleted from the IST program due to the-
| | been classified as active class 2 valves and will be included in I |
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| | the'IST program. A cold shutdown justification (CS-53) has been written describing their test method and equivalent cold shutdown frequency. |
| fact.that FC is a non-safety related system and does not fall j | | i-2. |
| ->
| | 1(2)HG016 and 1(2)HG007 have also been classified active and will be tested in the IST program per Tech Specs on a 6 month 3 |
| l within the scope of the IST program.
| | frequency. A c/s justification (CS-54) has been written describing the basis for this test frequency. |
| 1 : | | l HP 1. |
| HG 1.. 1(2)HG017A/B '(H2 Recombiner Water-Spray cooler supply CV's) have i | | 1(2)E22-F006 (Water Leg Pump Disch Check Valves) have been added |
| ; been classified as active class 2 valves and will be included in ,
| | [ |
| the'IST program. A cold shutdown justification (CS-53) has been I written describing their test method and equivalent cold | | to the IST program. A relief requent (RV-50) has been written for testing the plants ECCS WL pump discharge check valves. |
| ; shutdown frequency.
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| | also explains why the upstream cv's must be disassembled and |
| i- 2. 1(2)HG016 and 1(2)HG007 have also been classified active and | | ~ |
| !
| | inspected during reactor refueling per RV-46. |
| 3 will be tested in the IST program per Tech Specs on a 6 month
| | E IA 1. |
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| | The outboard MSIV accumulatur check valves have been moved from IN to IA system designation. |
| frequency. A c/s justification (CS-54) has been written describing the basis for this test frequency. l | | ^ |
| $ ,
| | I IN 1. |
| HP 1. 1(2)E22-F006 (Water Leg Pump Disch Check Valves) have been added | | INO31, IN100, and IN101 solenoid valves will use RV-56, |
| [ to the IST program. A relief requent (RV-50) has been written , | | " rapid-acting valves" position. |
| ' '
| | 5 LP 1. |
| for testing the plants ECCS WL pump discharge check valves. It ~ | | 1(2)E21-F034 (Water Leg Pump Discharge Stop Check Valves) have j'' |
| c' also explains why the upstream cv's must be disassembled and inspected during reactor refueling per RV-46. | | been added to the program. These valves will be tested 1 |
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| | quarterly per RV-50. |
| E IA 1. The outboard MSIV accumulatur check valves have been moved from | | j' 2. |
| . IN to IA system designation.
| | 1(2)E21-F033 (water leg pump disch cv/s) testing methods have been changed to partial exercising quarterly per RV-50 with K |
| ^
| | disassembly and inspection during refueling outages per RV-46. |
| I IN 1. INO31, IN100, and IN101 solenoid valves will use RV-56, | |
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| " rapid-acting valves" position.
| |
| 5 j'' LP 1. 1(2)E21-F034 (Water Leg Pump Discharge Stop Check Valves) have | |
| ; , been added to the program. These valves will be tested 1 quarterly per RV-50.
| |
| j' 2. 1(2)E21-F033 (water leg pump disch cv/s) testing methods have | |
| ! been changed to partial exercising quarterly per RV-50 with ,
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| K disassembly and inspection during refueling outages per RV-46.
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| | ,s Inservice Testing Program |
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| | . Summary of Changes for Wevision 2 9 |
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| | SECTION 6: |
| I ,'i s , | | Inservice Testina' Plan - Valves System Description |
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| | 'MS 1. |
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| | 1(2)E32-F010,'1(2)E32-F011, 1(2)E32-F310A/B/C/D have been added to the IST program due to the component classification review. |
| ...
| | These' valves have been determined to be class 2, active |
| Inservice Testing Program | | <o components ~. Disassembly and inspection is the method of testing which will be used on a reactor refueling basis per RV-52 and RV-46. |
| . Summary of Changes for Wevision 2 9
| | 'NR 1. |
| '*-
| | The following valves are non-code, however,.they are safety-related active. The valves are currently exercised and' leak tested per Technical Specifications, however, now they i |
| SECTION 6: Inservice Testina' Plan - Valves System Description | | require a stroke time and PIT per GL 89-04. |
| 'MS 1. 1(2)E32-F010,'1(2)E32-F011, 1(2)E32-F310A/B/C/D have been added to the IST program due to the component classification review.
| | .a. |
| <o These' valves have been determined to be class 2, active ;
| | 1(2)C51-C004A b. |
| components ~. Disassembly and inspection is the method of testing which will be used on a reactor refueling basis per RV-52 and | | 1(2)C51-C004B c. |
| ## RV-46. ,,
| | 1(2)C51-C004C d. |
| 'NR 1. The following valves are non-code, however,.they are safety-related active. The valves are currently exercised and' leak tested per Technical Specifications, however, now they i
| | 1(2)C51-C004D e. |
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| | 1(2)C51-C004E |
| - require a stroke time and PIT per GL 89-04. ,
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| | i RD 1.- |
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| | The 1(2)C11-D001-115 and 1(2)C11-D001-138 valves have been added to the program per GL 89-04. |
| , .a. 1(2)C51-C004A
| | Relief Request RV-45 documents the testing methods. |
| : ,
| | RH 1. |
| : b. 1(2)C51-C004B '
| | 1(2)E12-F060A/B (will use RV-56), 1(2)E12-F075A/B (will use RV-56): process sample valves are class 2, active and will be tested per normal code testing methods. |
| : c. 1(2)C51-C004C
| | 2. |
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| | 1(2)E12-TC89/93/94/97, are also going to be added to the IST program. These valves'have been determined to perform a safety-related function and will be tested per normal code testing methods. |
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| : d. 1(2)C51-C004D .
| | 3. |
| *
| | The 1(2)E12-F046A/B/C minimum flow line check valves will be partially stroked quarterly per RV-49, and disassembled and inspected per RV-46 per GL 89-04. |
| ! e. 1(2)C51-C004E
| | 4. |
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| | 1(2)E12-F040A/B, RHR drain isolation valves to radwaste are class 2, active and will be tested per normal code testing methods. |
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| RD 1.- The 1(2)C11-D001-115 and 1(2)C11-D001-138 valves have been added to the program per GL 89-04. Relief Request RV-45 documents the ; | |
| testing methods. , | |
| RH 1. 1(2)E12-F060A/B (will use RV-56), 1(2)E12-F075A/B (will use , | |
| , RV-56): process sample valves are class 2, active and will be tested per normal code testing methods.
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| ;. 2. 1(2)E12-TC89/93/94/97, are also going to be added to the IST ,
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| program. These valves'have been determined to perform a safety-related function and will be tested per normal code | |
| ! testing methods. t r
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| : 3. The 1(2)E12-F046A/B/C minimum flow line check valves will be
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| partially stroked quarterly per RV-49, and disassembled and inspected per RV-46 per GL 89-04. | |
| ! 4. 1(2)E12-F040A/B, RHR drain isolation valves to radwaste are
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| class 2, active and will be tested per normal code testing | |
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| methods. | |
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| Summary'of Changes forJRevision.2. | | Summary'of Changes forJRevision.2. |
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| | SECTION'6t- -Innervice Testina Plan ~- Valygg E, |
| ,
| | Sy.g tagg Description |
| SECTION'6t- -Innervice Testina Plan ~- Valygg ' | | '5 RH '. |
| E, Sy.g tagg Description | | ?l.< |
| '5 RH ' . ?l.< 'The'following relief valves have had their classification changed to passive (per reference 2), however, they will remain
| | 'The'following relief valves have had their classification changed to passive (per reference 2), however, they will remain in the IST. program and the setpoint. testing will continue. |
| , in the IST. program and the setpoint. testing will continue.
| | i a. |
| i | | 1(2)E12-F005s_ |
| : a. 1(2)E12-F005s_ h. 1(2)E12-F088A j
| | h. |
| *
| | 1(2)E12-F088A j |
| : b. 1(2)E12-F025A 1. 1(2)E12-F088B
| | b. |
| '
| | 1(2)E12-F025A 1. |
| .c. 1(2)E12-F025B j. 1(2)E12-F088C .
| | 1(2)E12-F088B |
| : d. 1(2)E12-F025C k. 1(2)E12-F311A [
| | .c. |
| : e. 1(2)E12-F030- 1. 1(2)E12-F311B'
| | 1(2)E12-F025B j. |
| : f. 1(2)E32-F055A' m. 1(2)E12-F313A ,
| | 1(2)E12-F088C d. |
| 'g. 1(2)E12-F0558 n. 1(2)E12-F313B y
| | 1(2)E12-F025C k. |
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| | 1(2)E12-F311A |
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| | [ |
| : 5. 1(2)E12-F073A/B and 1(2)E12-F074A/B have been changed to ,
| | e. |
| active. They are already esercised in a station surveillance, however, they must now be stroke timed and have a position- a indication test performed for the IST program. | | 1(2)E12-F030-1. |
| 1(2)E12-F084A/B/C (Water Leg Pump Disch CV's) will be added to
| | 1(2)E12-F311B' f. |
| '
| | 1(2)E32-F055A' m. |
| | 1(2)E12-F313A |
| | 'g. |
| | 1(2)E12-F0558 n. |
| | 1(2)E12-F313B y |
| | 5. |
| | 1(2)E12-F073A/B and 1(2)E12-F074A/B have been changed to active. They are already esercised in a station surveillance, however, they must now be stroke timed and have a position-a indication test performed for the IST program. |
| 6. | | 6. |
| p the IST program. They will be partial stroke tested quarterly. | | 1(2)E12-F084A/B/C (Water Leg Pump Disch CV's) will be added to p |
| '
| | the IST program. They will be partial stroke tested quarterly. |
| per RV-50 with disassembly and inspection every refuel outage | | per RV-50 with disassembly and inspection every refuel outage per RV-46. |
| * per RV-46.
| | 7. |
| .' .
| | 1(2)E12-F085A/B/C (Water Leg Pump CV's) have been added to the program and will be tested quarterly pet.RV-50. |
| ' 7. 1(2)E12-F085A/B/C (Water Leg Pump CV's) have been added to the '
| | t RI 1. |
| program and will be tested quarterly pet.RV-50. | | 1(2)E12-F036A/B have been given a pessive classification, however, testing will continue as with other relief valves. |
| t RI 1. 1(2)E12-F036A/B have been given a pessive classification, | | t 2. |
| ' however, testing will continue as with other relief valves. ;
| | TP-02 was added to E51-F028/F040/F047 valves to document and 1 |
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| : 2. TP-02 was added to E51-F028/F040/F047 valves to document and 1
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| clarify testing in the IST program. | | clarify testing in the IST program. |
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| ;.4 -Inservice Testing Program i Summary of Changes'for Revision 2
| | RR 1. |
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| | The following valves are presently tested per LOS-PC-R1, j |
| ur : 1 | | 2 however, due to reference 1 these valves are'now required tv be y |
| : I' 'd .. \ . | | added to the IST program'(CIVs, Appendix J osempted).- The L |
| l" RECT 10N-6 | | inboard valves can on3y be tested during c/s or refueling outages, but the outboard valves can.be tested quarterly.. C5. J5 explains the c/s basis. |
| '
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| Innervice Testina Plan - Valves 0: )
| | 1(2)B33-F338A 1. |
| Egitta Description ! | | 1(2)B33-F342A |
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| q RR 1. The following valves are presently tested per LOS-PC-R1, j 2 however, due to reference 1 these valves are'now required tv be ,
| | b. |
| y added to the IST program'(CIVs, Appendix J osempted).- The L inboard valves can on3y be tested during c/s or refueling ,!
| | 1(2)B33-F338B |
| outages, but the outboard valves can.be tested quarterly. . C5. J5 ! | | : j. 1(2)B33-73428. |
| explains the c/s basis. , | | 4 i, |
| a.' 1(2)B33-F338A 1. 1(2)B33-F342A [ | | c. |
| : b. !
| | 1(2)B33-F339A-k. |
| 1(2)B33-F338B j. 1(2)B33-73428. 4 i, c. 1(2)B33-F339A- k. 1(2)B33-F343A l | | 1(2)B33-F343A l |
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| | 1(2)B33-F3398 |
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| | : 1. '1(2)B33-F343B e. |
| .f. 1(2)B33-F340B n. 1(2)B33-F344B' ..
| | 1(2)B33-F340A-m. |
| : f. g. 1(2)B33-F341A o. 1(2)B33-F345A I 4
| | 1(2)B33-F344A |
| : h. 1(2)B33-F341B p. 1(2)B33-F345B ,
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| | 1(2)B33-F340B n. |
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| | 1(2)B33-F341A o. |
| , RT 1. The following relief valves have been deleted from the IST '
| | 1(2)B33-F345A I |
| ,, , ' program since the reactor water cleanup system is non-safety ,
| | 4 h. |
| E -related. l j ,
| | 1(2)B33-F341B p. |
| ' a. 1(2)G33-F339A d. 1(2)G33-F340B
| | 1(2)B33-F345B O< |
| : b. 1(2)G33-F339B e. 1(2)G33-F341A t
| | The following relief valves have been deleted from the IST RT 1. |
| ~ c. 1(2)G33-F340A f. 1(2)G33-F341B .
| | ' program since the reactor water cleanup system is non-safety E |
| f VG3 1. 1(2)VG0001 and VG0003 are classified as class 3 active valves
| | -related. |
| '
| | l j |
| and have been added to the IST program. Testing will include bn F | | ) |
| ' stroke timing and PITS.
| | a. |
| I ' VQ ' 1. VQ041 is a non-code valve and has been deleted from IST per E' reference 2 documentation. The valves are classified as passive. | | 1(2)G33-F339A d. |
| i' ' | | 1(2)G33-F340B b. |
| SECTION 7e Valve Rollef Recuests/ Cold Shutdown Justifications -[ ' | | 1(2)G33-F339B e. |
| | 1(2)G33-F341A t |
| | ~ c. |
| | 1(2)G33-F340A f. |
| | 1(2)G33-F341B f |
| | VG3 1. |
| | 1(2)VG0001 and VG0003 are classified as class 3 active valves and have been added to the IST program. Testing will include bn |
| | ' stroke timing and PITS. |
| | F I |
| | ' VQ ' |
| | 1. |
| | VQ041 is a non-code valve and has been deleted from IST per E' |
| | reference 2 documentation. The valves are classified as passive. |
| | i' SECTION 7e Valve Rollef Recuests/ Cold Shutdown Justifications |
| | -[ |
| 1: | | 1: |
| _(. ' ALL An " Approval / Reference Document (s)" field was added to each , | | _(. ' |
| relief request and cold shutdown justification to depict the ; | | ALL An " Approval / Reference Document (s)" field was added to each relief request and cold shutdown justification to depict the approval document or identify any applicable reference (s) used. |
| . approval document or identify any applicable reference (s) used.
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| 1 SECTION 71 Valve Reljaf Reaumata/ Cold Ehutdown Justificationa | | 1 SECTION 71 Valve Reljaf Reaumata/ Cold Ehutdown Justificationa |
| >
| | -Y 1-RV. Describes the basis for relief and alternate test methods for i |
| -Y p 1- RV . Describes the basis for relief and alternate test methods for i the Gontrol Rod Drive.(CRD) charging water header cv's and the
| | p the Gontrol Rod Drive.(CRD) charging water header cv's and the |
| [" ~ CRD' coo'.ing water cv's. | | [" ~ |
| | CRD' coo'.ing water cv's. |
| t | | t |
| : 2. .RV-46; Describes the GL 89-04 approved alternative to full-stroke esercising check. valves -- disassembly and inspection. t | | : 2..RV-46; Describes the GL 89-04 approved alternative to full-stroke esercising check. valves -- disassembly and inspection. |
| : 3. RV-47 Explains the' basis for relief and alternate testing for the LPCS motor cooler water outlet ev's~which deviates from c0de testing l
| | t 3. |
| '
| | RV-47 Explains the' basis for relief and alternate testing for the LPCS motor cooler water outlet ev's~which deviates from c0de testing l because it only proves a partial stroke according to Generic Letter 89-04. |
| because it only proves a partial stroke according to Generic Letter 89-04. . -l L | | L 4. |
| : 4. RV-48 (RCIC min flow line cv's); The present testing only proves a partial stroke according to Generic Letter 89-04. This' relief request explains the basis for relief and testing method for-these valves.
| | RV-48 (RCIC min flow line cv's); The present testing only proves a partial stroke according to Generic Letter 89-04. |
| :d 5. RV-49. (LPCI min flow line ev's);' Explains basis for relief and alternate test methods for these. valves. | | This' relief request explains the basis for relief and testing method for-these valves. |
| IS i | | :d 5. |
| ''
| | RV-49. |
| : 6. RV-50 (Water leg pump discharge cv's); Describes the reasoning and method of testing these valves.
| | (LPCI min flow line ev's);' Explains basis for relief and alternate test methods for these. valves. |
| :
| | IS i |
| '
| | 6. |
| : 7. RV-51 Describes the basis for relief and alternate testing for the DG, compressor discharge cv's which have been added to the IST 3 i- , program.
| | RV-50 (Water leg pump discharge cv's); Describes the reasoning and method of testing these valves. |
| '
| | 7. |
| ,
| | RV-51 Describes the basis for relief and alternate testing for the DG, compressor discharge cv's which have been added to the IST 3 |
| : 8. RV-52 Explains basis for relief and alternate testing for the MSIV-LCS
| | i-program. |
| * Cv's.
| | 8. |
| !
| | RV-52 Explains basis for relief and alternate testing for the MSIV-LCS Cv's. |
| : 9. CS-53 (Hydrogen Recombiner water-spray cooler supply cv's); Describes
| | 9. |
| * the reasoning behind the method of testing these. valves once a year (equivalent to c/s testing) for the IST program.
| | CS-53 (Hydrogen Recombiner water-spray cooler supply cv's); Describes the reasoning behind the method of testing these. valves once a year (equivalent to c/s testing) for the IST program. |
| i 10. CS-54 (Hydrogen Recombiner containment suction ev's); Explains basis for cold shutdown testing of these valves. | | i 10. |
| .
| | CS-54 (Hydrogen Recombiner containment suction ev's); Explains basis for cold shutdown testing of these valves. |
| : 11. CS-55 (Reactor Recirc hydraulic line inboard cv's); Describes the
| | 11. |
| ,.
| | CS-55 (Reactor Recirc hydraulic line inboard cv's); Describes the basis for relief and why these valves will be tested only during refueling outages. Explains that the outboard valves con be |
| ;; basis for relief and why these valves will be tested only during
| |
| [ | | [ |
| i refueling outages. Explains that the outboard valves con be g. | | i tested quarterly. |
| tested quarterly. ' | | g. |
| ,
| | 12. |
| t 12. CS-56 Describes the limits imposed on rapid-acting solenoid valves in
| | CS-56 Describes the limits imposed on rapid-acting solenoid valves in t |
| ; the IST program per the NRC staff's position described in GL
| | the IST program per the NRC staff's position described in GL 89-04. |
| '
| |
| , 89-04.
| |
| . | |
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| e '. :. ,= , , . | | TP-01' Developed to describe stroke, time testing of valves in'the IST program and the acceptance criteria involved with establishing alert and required action rLage limits. |
| Q-c s.? | | F Describes the method'of-full-stroke' testing'of the T |
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| '2. TP-02: Describes the method'of-full-stroke' testing'of the T
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| E51-r028/F040/F047 RCIC systern ev's. | | E51-r028/F040/F047 RCIC systern ev's. |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217H6341999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for Kh Curran,Lm Gerlach,Rc Weber & Bt Rhodes Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC Form 396 Encl.Proprietary Info Withheld ML20217H6251999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for MR Kahn,Aj Mclaughlin,De Montgomery & Kr Murphy Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC from 396 Encl.Proprietary Info Withheld ML20217F4301999-10-14014 October 1999 Responds to 991012 Rai,Based on 991001 Telcon Re Suppl to Request for TS Change to Revise MCPR Safety Limit & Add Approved Siemens Topical Rept for LaSalle County Station, Unit 1 ML20217D3191999-10-12012 October 1999 Submits Request for Addl Info Re Licensee 990707 Proposed License Amend to Revise Min Critical Power Ratio.Listed Questions Were Discussed with Util in 991001 Telcon ML20217C1671999-10-0808 October 1999 Provides Suppl to RAI for Approval of Unreviewed Safety Question Re Assessment of Certain safety-related Concrete Block Walls at LaSalle County Station,Units 1 & 2 ML20217A7601999-10-0606 October 1999 Forwards Insp Repts 50-373/99-15 & 50-374/99-15 on 990729-0916.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20212M0931999-10-0404 October 1999 Refers to 990922-23 Meeting Conducted by Region II at LaSalle Nuclear Power Station.Purpose of Visit,To Meet with Licensee Risk Mgt Staff to Discuss Util Initiatives in Risk Area & to Establish Dialog Between SRAs & Risk Mgt Staff 05000373/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl1999-10-0404 October 1999 Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl ML20217A6201999-09-30030 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issue Matrix & Insp Plan Encl ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr ML20212E7171999-09-22022 September 1999 Forwards RAI Re Requesting Approval of License Amend to Use Different Methodology & Acceptance Criteria for Reassessment of Certain Masonry Walls Subjected to Transient HELB Pressurization Loads 05000374/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl1999-09-20020 September 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl ML20212C0591999-09-17017 September 1999 Informs That NRC Reviewed Licensee Justifications for Deviations from NEDO-31558 & Determined That Justifications acceptable.Post-accident Neutron Flux Monitoring Instrumentation Acceptable Alternative to Reg Guide 1.97 ML20212A3581999-09-13013 September 1999 Confirms That Fuel MCPR Data for LaSalle County Station,Unit 1,Cyle 9,sent by Ltr Meets Condition 2,as Stated in 970509 NRC Ltr ML20211Q9911999-09-10010 September 1999 Informs That License SOP-4048-4,for Wp Sly May Be Terminated Due to Individual Retiring ML20212A1141999-09-10010 September 1999 Forwards RAI Re Licensee 990519 Amend Request,Which Proposed to Relocate Chemistry TSs from TS to licensee-controlled Documents.Response Requested by 990930,so That Amend May Be Issued to Support Upcoming Unit 1 Refueling Outage ML20211P2211999-09-0808 September 1999 Forwards Insp Repts 50-373/99-14 & 50-374/99-14 on 990809- 13.No Violations Noted.Insp Concluded That Emergency Preparedness Program Maintained in Good State of Operational Readiness ML20212A8571999-09-0707 September 1999 Informs That Proprietary Document, Power Uprate SAR for LaSalle County Station,Units 1 & 2, Rev 2,Class III, NEDC-32701P,submitted in ,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20211Q6861999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant License Applicants During Wks of 001113 & 20. Validation of Exam Will Occur at Station During Wk of 001023 05000374/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl1999-09-0303 September 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl ML20211M1151999-08-31031 August 1999 Requests That Following Eleven Individuals Take BWR Gfes of Written Operator Licensing Exam to Be Administered on 991006 ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20211G1831999-08-27027 August 1999 Provides Addl Clarification of Proposed Refueling Practices Under Proposed Core Alterations Definition Re 990813 Application for Amend to TS ML20211F8731999-08-25025 August 1999 Forwards Insp Repts 50-373/99-13 & 50-374/99-13 on 990804-06 & 09-11.No Violations Noted.Fire Protection Program Strengths Includes Low Number of Fire Protection Impairments & Excellent Control of Transient Combustibles ML20210U3201999-08-17017 August 1999 Forwards Insp Repts 50-373/99-12 & 50-374/99-12 on 990623-0728.No Violations Noted ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML17191B4031999-07-23023 July 1999 Informs That NRC Plans to Administer GFE Section of Written Operator Licensing Exam on 991006.Ltr Should Be Submitted to Appropriate Regional Administrator at Listed Address to Register Personnel to Take GFE 05000373/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed1999-07-23023 July 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed ML20210E0501999-07-22022 July 1999 Submits Summary of 990630 Management Meeting Re Licensee Performance Activities Since Start Up of Unit 2.List of Attendees & Matl Used in Presentation Enclosed ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) ML17191B3951999-07-15015 July 1999 Forwards Environ Assessment & Finding of No Significant Impact Related to Proposed Exemptions for Braidwood,Byron, Dresden,Lasalle & Quad Cities Stations.Proposed Exemptions Would Provide Relief from Requirements of 10CFR50.71(e)(4) ML20209H5171999-07-15015 July 1999 Discusses 990701 Telcon Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at LaSalle County Nuclear Generating Station for Weeks of 990913,1018 & 1129 ML20209G4031999-07-14014 July 1999 Forwards Insp Repts 50-373/99-11 & 50-374/99-11 on 990614-18.No Violations Noted ML20209E1211999-07-14014 July 1999 Submits mid-cycle Rev of COLR IAW LaSalle County Tech Spec 6.6.A.6.d.Rev to COLR Was Necessary Due to Implementation of TS Change Approved by Ltr Dtd 990212,which Changed Turbine Stop Valve & Turbine Control Valve Scram ML20209F6931999-07-13013 July 1999 Forwards Insp Repts 50-373/99-04 & 50-374/99-04 on 990513-0622.No Violations Noted.Determined That Multiple Challenges to Main Control Room Operators Occurred During Insp Period Due to Human Performance Weaknesses ML20209G3901999-07-0909 July 1999 Informs NRC of Status of Commitments & Requests NRC Concurrence for Use of ASME Section III App F Acceptance Criteria to Permanently Qualify Units 1 & 2 Penetrations M-49 & M-50 ML20209E0341999-07-0909 July 1999 Provides NRC with Siemens Power Corp (SPC) Fuel & GE Fuel MCPR Data for LaSalle Unit 1 Cycle 9.LaSalle Unit 1 Is Currently Scheduled to Start Cycle 9 in 991101 ML20210C1521999-07-0909 July 1999 Forwards Post-Outage (90 Day) Summary Rept for ISI Examinations & Repair/Replacement Activities Conducted from Beginning of First Insp Period of Second ten-yr Insp Interval Through L2R07 Refueling Outage ML20209E0361999-07-0808 July 1999 Forwards LaSalle County Station Unit 2 Cycle 8 Startup Test Rept Summary,Iaw TS NPF-18,Section 6.6.A.1.Startup Test Program Was Satisfactorily Completed on 990501 ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes ML20196J4711999-06-30030 June 1999 Discusses Closure of GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Plant,Units 1 & 2 ML20212J0311999-06-21021 June 1999 Informs of Actions Taken to Close Remaining Open Items in .Attachment Provides Detailed Justification for Closure of Open Items in Sections 5.2.2 & 5.2.8 ML20196B1951999-06-18018 June 1999 Informs NRC That Do Werts,License OP-30373-2,no Longer Requires Use of NRC License for LaSalle County Station. License May Be Terminated ML20195J7761999-06-15015 June 1999 Submits Request Relief CR-23,requesting Relief from Code Required Selection & Examinations of Noted Integral Attachments & Proposes to Utilize Alternative Selection & Examination Requirements Similar to Code Case N-509 ML20196G8021999-06-15015 June 1999 Requests Renewal of SRO License for Vv Masterson.Current License for Vv Masterson Will Expire Jul 1999.NRC Forms 398 & 396,encl.Without Encls ML20195G7101999-06-11011 June 1999 Informs That Effective 990514,GH Mccallum,License SOP-31412, No Longer Requires Use of NRC License for LaSalle Station. License Should Be Terminated 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217H6251999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for MR Kahn,Aj Mclaughlin,De Montgomery & Kr Murphy Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC from 396 Encl.Proprietary Info Withheld ML20217H6341999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for Kh Curran,Lm Gerlach,Rc Weber & Bt Rhodes Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC Form 396 Encl.Proprietary Info Withheld ML20217F4301999-10-14014 October 1999 Responds to 991012 Rai,Based on 991001 Telcon Re Suppl to Request for TS Change to Revise MCPR Safety Limit & Add Approved Siemens Topical Rept for LaSalle County Station, Unit 1 ML20217C1671999-10-0808 October 1999 Provides Suppl to RAI for Approval of Unreviewed Safety Question Re Assessment of Certain safety-related Concrete Block Walls at LaSalle County Station,Units 1 & 2 05000373/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl1999-10-0404 October 1999 Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr 05000374/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl1999-09-20020 September 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl ML20211Q9911999-09-10010 September 1999 Informs That License SOP-4048-4,for Wp Sly May Be Terminated Due to Individual Retiring 05000374/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl1999-09-0303 September 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl ML20211M1151999-08-31031 August 1999 Requests That Following Eleven Individuals Take BWR Gfes of Written Operator Licensing Exam to Be Administered on 991006 ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20211G1831999-08-27027 August 1999 Provides Addl Clarification of Proposed Refueling Practices Under Proposed Core Alterations Definition Re 990813 Application for Amend to TS ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed 05000373/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed1999-07-23023 July 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed ML20209E1211999-07-14014 July 1999 Submits mid-cycle Rev of COLR IAW LaSalle County Tech Spec 6.6.A.6.d.Rev to COLR Was Necessary Due to Implementation of TS Change Approved by Ltr Dtd 990212,which Changed Turbine Stop Valve & Turbine Control Valve Scram ML20210C1521999-07-0909 July 1999 Forwards Post-Outage (90 Day) Summary Rept for ISI Examinations & Repair/Replacement Activities Conducted from Beginning of First Insp Period of Second ten-yr Insp Interval Through L2R07 Refueling Outage ML20209E0341999-07-0909 July 1999 Provides NRC with Siemens Power Corp (SPC) Fuel & GE Fuel MCPR Data for LaSalle Unit 1 Cycle 9.LaSalle Unit 1 Is Currently Scheduled to Start Cycle 9 in 991101 ML20209G3901999-07-0909 July 1999 Informs NRC of Status of Commitments & Requests NRC Concurrence for Use of ASME Section III App F Acceptance Criteria to Permanently Qualify Units 1 & 2 Penetrations M-49 & M-50 ML20209E0361999-07-0808 July 1999 Forwards LaSalle County Station Unit 2 Cycle 8 Startup Test Rept Summary,Iaw TS NPF-18,Section 6.6.A.1.Startup Test Program Was Satisfactorily Completed on 990501 ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes ML20212J0311999-06-21021 June 1999 Informs of Actions Taken to Close Remaining Open Items in .Attachment Provides Detailed Justification for Closure of Open Items in Sections 5.2.2 & 5.2.8 ML20196B1951999-06-18018 June 1999 Informs NRC That Do Werts,License OP-30373-2,no Longer Requires Use of NRC License for LaSalle County Station. License May Be Terminated ML20196G8021999-06-15015 June 1999 Requests Renewal of SRO License for Vv Masterson.Current License for Vv Masterson Will Expire Jul 1999.NRC Forms 398 & 396,encl.Without Encls ML20195J7761999-06-15015 June 1999 Submits Request Relief CR-23,requesting Relief from Code Required Selection & Examinations of Noted Integral Attachments & Proposes to Utilize Alternative Selection & Examination Requirements Similar to Code Case N-509 ML20195G7101999-06-11011 June 1999 Informs That Effective 990514,GH Mccallum,License SOP-31412, No Longer Requires Use of NRC License for LaSalle Station. License Should Be Terminated ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20207D2821999-05-27027 May 1999 Requests That Implementation Date for Unit 1 Be Changed Prior to Startup for L1C10 to Allow Best Allocation of Resources to Implement Unit 1 Amend Prior to Startup for Either L1C9 or L1C10.Unit 2 Will Implement Mod IAW Request ML20195B2301999-05-19019 May 1999 Requests Approval of Proposed Changes to QA Topical Rept CE-1-A,rev 66a.Attachment a Describes Changes,Reason for Change & Basis for Concluding That Revised QAP Incorporating Proposed Changes Continues to Satisfy 10CFR50AppB ML20206R4561999-05-12012 May 1999 Provides Notification That Ws Jakielski,License SOP-30168-3, Is Being Reassigned & No Longer Requires Use of NRC License, IAW 10CFR50.74 ML20206K7081999-05-0707 May 1999 Forwards 10CFR50.46(a)(3) Rept Re Significant Change in Calculated Pct.Loca Analyses for Both GE Fuel & Siemens Power Corp Fuel Demonstrates Results within All of Acceptance Criteria Set Forth in 10CFR50.46 05000373/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii).Attachment a Provides Commitments for Submittal1999-05-0707 May 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii).Attachment a Provides Commitments for Submittal ML20206R0751999-04-30030 April 1999 Forwards License Renewal Applications & Certification of Medical Examinations for LaSalle County Station Personnel Whose Licenses Expire in Nov.Personnel Listed.Without Encls ML20206K1861999-04-30030 April 1999 Informs That in Comed Submitted Annual Exposure Rept for Personnel Receiving Greater than 0 Mrem/Yr Rather than 100 Mrem/Yr.Updated Rept Limiting Data to Personnel Receiving Greater than 100 Mrem/Yr,Attached ML20206F0931999-04-30030 April 1999 Forwards LaSalle County Nuclear Power Station,Units 1 & 2 Effluent & Waste Disposal Semi-Annual Rept for 1998. LaSalle County Station Tech Specs Recently Revised to Reduce Periodicity of 10CFR50.36a ML20206D5921999-04-28028 April 1999 Forwards Annual Environ Operating Rept for 1998 for Environ Protection Plan, for LaSalle County Station,Units 1 & 2. Rept Includes Info Required by Listed Subsections of App B to Licenses NPF-11 & NPF-18 ML20206B2471999-04-20020 April 1999 Informs That SE Kuczynski Has Been Transferred to Position No Longer Requiring SRO License.Cancel License SOP-31030-1, Effective 990412 ML20205L8161999-04-0808 April 1999 Advises NRC of Util Review & Approval of Cycle 8 Reload Under Provisions of 10CFR50.59 & Transmit COLR for Upcoming Cycle Consistent with GL 88-16.Reload Licensing Analyses Performed for Cycle 8 Utilize NRC-approved Methodologies ML20205J9451999-04-0505 April 1999 Submits Petition Per 10CFR2.206 Requesting That LaSalle County Nuclear Plant Be Immediately Shut Down & OL Suspended or Modified Until Such Time That Facility Design & Licensing Bases Are Properly Updated ML20205K5841999-03-31031 March 1999 Submits Rept on Status of Decommissioning Funding for Reactors Owned by Comm Ed.Attachment 1 Contains Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) ML20205B4241999-03-23023 March 1999 Provides Results of drive-in Drill Conducted on 990208,as Well as Augmentation Phone Drills Conducted Since 981015,as Committed to in Util ML17191B2671999-03-12012 March 1999 Forwards Revs to Dresden,Quad Cities,Zion,Lasalle,Byron & Braidwood Station Odcm,Current as of 981231.ODCM Manual & Summary of Changes,Included ML20207J9841999-03-0505 March 1999 Informs That Effective 990212,KC Dorwick Has Resigned & No Longer Requires Use of NRC License for LaSalle County Station ML20207C7251999-03-0101 March 1999 Forwards Annual Rept for LaSalle County Station, for Period of 980101-981231.App E to Rept Provides Info on All Personnel Receiving Exposures of More than 0 Mrem/Yr Rather than 100 Mrem/Yr Requirement of TS 6.6.A.2 ML20207D6831999-03-0101 March 1999 Forwards fitness-for-duty Program Performance Data for Each Comed Nuclear Power Station & Corporate Support Employees for Six Month Period Ending 981231,per 10CFR26.71(d) ML20207F9581999-03-0101 March 1999 Requests That Initial License Examination Currently Scheduled for Weeks of May 15 & 22,2000 Be Changed to Weeks of Nov 13 & 20,2000.Class Size Is Projected to Be Twelve RO & SRO Candidates ML20207C8401999-02-25025 February 1999 Forwards Rev 60 of Comed LSCS Security Plan,Iaw 10CFR50.4(b) (4).Rev Eliminates Requirement for Annual change-out of Vital & PA Keys & Locks & re-configuration of PA Fence Around North Access Facility.Rev Withheld 1999-09-30
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059H5321990-09-11011 September 1990 Requests Withdrawal of Application for Amend to Licenses NPF-11 & NPF-18,per 891215 & s.Amend Would Have Removed Applicability of Tech Spec (TS) 3.0.4 to TS 3.6.5.2, Secondary Containment Automatic Isolation Dampers ML20059H4271990-09-0707 September 1990 Provides Supplemental Response to NRC Bulletin 90-001.Plant Initial Review of Calibr Records Completed on 900831 ML20059G0941990-09-0505 September 1990 Forwards LaSalle County Station Unit 2 Third Refueling Outage,Asme Section XI Summary Rept for Spring 1990 Insp ML20059C6891990-08-30030 August 1990 Forwards LaSalle County Nuclear Power Station Unit 2,Cycle 4 Startup Test Rept & Test Rept Summary ML20056B4061990-08-21021 August 1990 Submits Supplemental Response to Generic Ltr 88-14 Re Design & Verification of Instrument Air Sys.Mfg Purchase Specs & Vendor Manuals Reviewed for Air Quality Requirements ML20059B8961990-08-14014 August 1990 Documents Approval of Schedular Extension & Accepts Human Engineering Discrepancies Discussed ML20059D1731990-08-10010 August 1990 Responds to NRC Re Exercise Weaknesses Noted in Insp Repts 50-373/90-05 & 50-374/90-06.Corrective Actions: LOA-FP-01, Fire Alarm Response Will Be Revised to Alert Control Room Operators to Refer to Emergency Action Levels ML20058N2971990-08-0606 August 1990 Forwards Rev 34 to Security Plan.Rev Details Addl Gate Position for Security Testing & Maint.Rev Withheld (Ref 10CFR73.21) ML20064A5491990-07-27027 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-373/90-12 & 50-374/90-13.Corrective Actions:Program Implemented Identifying & Correcting Repetitive Local Leak Rate Failures Through Testing & LER Investigation ML20056A7031990-07-27027 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-373/90-13 & 50-374/90-14.Corrective actions:LRP-1250-3 Revised to Include Addl Requirement for Extremity Monitoring ML20055H7631990-07-25025 July 1990 Forwards Financial Info Re Decommissioning of Plants ML20055H7661990-07-24024 July 1990 Forwards Supplemental Response to Generic Ltr 90-04, Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions ML20055G2011990-07-13013 July 1990 Forwards Corrected Monthly Operating Rept for June 1990 for LaSalle County Unit 1.Outage/Reduction 16 Corrected ML20044B1751990-07-0909 July 1990 Responds to NRC Request for Addl Info Re Util 890726 Proposed Amend to Tech Specs to Allow Continued Operation for Period of 12 H W/Main Steam Tunnel High Ambient Temp & High Ventilation Sys Differential Trips Bypassed ML20055F1831990-07-0909 July 1990 Provides Status Rept on Breaker Replacements in Response to NRC Bulletin 88-010.Breaker Replacements for Plants Scheduled to Be Completed by 901031 ML17202L2861990-07-0202 July 1990 Forwards Dresden II Upper Vessel Contract Variation Review, La Salle II Upper Vessel Fabrication Summary & Quad-Cities II Upper Vessel Fabrication Summary. ML20055D1921990-06-29029 June 1990 Responds to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues ML20055J2021990-06-26026 June 1990 Responds to NRC Re Violations Noted in Insp Repts 50-373/90-06 & 50-374/90-06.Corrective Actions:Perimeter Zone Repairs Commenced on Schedule & Completely Functional & Out of Compensatory Measures on 900614 ML20044A5071990-06-22022 June 1990 Forwards Revised Response to Station Blackout Rule for Plant.During Blackout Event,Plant Can Utilize RCIC Sys or HPCS to Provide Required Reactor Vessel Inventory Makeup ML20043E8651990-06-0707 June 1990 Forwards Relief Request RV-57 for Emergency Fuel Pool Makeup Crosstive Vent Valve 1(2)E12-F097.Expedious Review of Request Requested Because Valve 1(2)E12-F097 Inoperable & Will Remain So Until NRC Approval Received ML20043D3221990-06-0101 June 1990 Forwards Rev 33 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043C8241990-06-0101 June 1990 Advises of Intentions to Review & Approve Cycle 4 Reload,Per 10CFR50.59 & Forwards Rev 1 to LAP-1200-16, Core Operating Limits Repts for LaSalle County Station Unit 2,Reload 3, Cycle 4, Per Generic Ltr 88-16 ML20043B6581990-05-25025 May 1990 Requests Schedular Extension of Two Human Engineering Deficiencies Re CRT Displays W/Current Ramtek Sys & Approval to Leave Seven Human Engineering Discrepancies Accepted as Is. ML20043B7921990-05-23023 May 1990 Forwards Endorsements 14 to Nelia Policy N-71 & Maelu Policy M-71 & Endorsements 12 to Nelia & Maelu Policies N-83 & M-83,respectively ML20042E8841990-04-30030 April 1990 Responds to Generic Ltr 89-04 Re Weaknesses of Inservice Testing Programs.Plant Has Implemented Rev 2 of Inservice Testing Program Submitted by Util 891002 & 24 Ltrs.No Equipment Mods Required as Result of Generic Ltr ML20042F3591990-04-29029 April 1990 Provides Suppl Response to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Precaution Added to Operating Procedures Which Allows ECCS Pump to Be Secured & Restarted as Necessary to Preclude Running Pumps at Min Flow ML20042F0341990-04-23023 April 1990 Forwards Part 3 to 1989 Operating Rept,Containing Results of Radiological Environ & Meteorological Monitoring Programs. W/O Encl ML20034B6901990-04-12012 April 1990 Forwards Rev 58 to CE-1-A, QA Program for Nuclear Generating Stations. Rev Being Made to Reflect Correct Frequency of Cumulative Deviation Reporting & to Clarify Applicability of Other ANSI N45.2 Stds ML20034A1811990-04-0505 April 1990 Withdraws Request for Approval of Piping Operability Criteria for Plant,Per 890412 Meeting W/Nrc ML20034A8111990-04-0303 April 1990 Responds to Weaknesses Noted in Insp Repts 50-373/89-24 & 50-374/89-23 on 891116-900105.Corrective Actions:Importance of Need to Perform Early Nasal Surveys Emphasized & Procedures LRP-1240-25 & LRP-1470-5 Revised ML20064A6281990-03-30030 March 1990 Submits Supplemental Response to Insp Repts 50-373/86-04 & 50-374/86-04 Re Fire Detection Concerns,Per NRC 900214 Request.Proposed Administrative Controls & Training Will Eliminate Concerns That Assure Protection of Personnel ML20055E1461990-03-29029 March 1990 Provides Supplemental Response to Re Violations Noted in Insp Repts 50-373/89-18 & 50-374/89-18 on 890724- 0825.Corrective Actions:Plant Performs Safety Evaluation for Mods Not Designed by Corporate Nuclear Engineering Dept ML20012C6991990-03-15015 March 1990 Forwards Corrected Tech Spec Page to 881129 Application for Amend to Licenses NPF-11 & NPF-18,removing Specific Load Profiles for Each Dc Battery ML20012B6541990-02-26026 February 1990 Forwards LaSalle County Station Unit 1 Third Refueling Outage ASME Section XI Summary Rept, for Fall 1989 Inservice Insps Performed.Conditions Observed & Corrective Measures Taken Also Contained in Rept ML20006E7421990-02-0909 February 1990 Responds to NRC Re Violations Noted in Insp Repts 50-373/89-23 & 50-374/89-22.Corrective Actions:Ltr from Station Manager to All Dept Heads Was Issued on 891218, Discussing Personnel Performance Issues ML20005F5771990-01-0808 January 1990 Documents Guidance Given by P Shemanski Re Typos in Earlier Approved Amend to License NPF-11.Guidance Should Adhere to Wording of Unit 2 Tech Specs.Guidance Given on 900105 & Will Be Followed Until Correction Made at NRR Ofcs ML20011D9661989-12-22022 December 1989 Forwards Core Operating Limits Rept for LaSalle County Station Unit 1,Reload 3 (Cycle 4). Intention to Review & Approve Cycle 4 Reload Under Provisions of 10CFR50.59 Stated ML20005E1661989-12-22022 December 1989 Forwards Rev 32 to Security Plan,Reflecting Administrative Changes in Mgt Structure at Facilities.Rev Withheld (Ref 10CFR73.21) ML20011D6121989-12-13013 December 1989 Forwards Rev 57 to Topical Rept CE-1-A, QA Program ML19332E4531989-11-29029 November 1989 Responds to Generic Ltr 89-21, Status of Implementation of USI Requirements. Response to USI A-48 Expected by 900319 ML19332C2461989-11-0808 November 1989 Provides Supplemental Response to Insp Repts 50-373/88-05 & 50-374/88-05 on 890302-10.Scheduled Completion Dates for Sample Panel Mods Changed from Third to Fourth Refueling Outages of Each Unit ML19325E5191989-10-31031 October 1989 Forwards Qualification Test Rept QTR87-018, Max Credible Fault Tests CM249-Q2 Carrier Modulator for Fermi 2 SPDS, in Response to NRC 890304 Request for Addl Info Re Facility Validyne Isolator CM-249 ML19325E1661989-10-27027 October 1989 Responds to Generic Ltr 89-07, Power Reactor Safeguards Contingency for Surface Vehicle Bombs. Site Features Reviewed to Determine Land Vehicle Approach Paths & short-range Measures Adopted.Encl Withheld (Ref 10CFR73.21) ML19325E3601989-10-26026 October 1989 Forwards Addl Info Re Application for Amend to Licenses NPF-11 & NPF-18,revising Tech Specs to Conform W/Diesel Generator Test Schedule Recommendations,Per Generic Ltr 84-15 ML19325E0941989-10-24024 October 1989 Forwards Clarification to Summary of Changes Made in Rev 2 to Plant Inservice Testing Program ML19325E7921989-10-24024 October 1989 Submits Response to SALP 8 Board Repts 50-373/89-01 & 50-374/89-01.Expresses Appreciation for NRC Recognition of High Level of Performance in Area of Plant Operations, Emergency Preparedness & Security ML19353A9051989-10-23023 October 1989 Responds to NRC Re Violations Noted in Insp Repts 50-373/89-19 & 50-374/89-19.Corrective Actions:Hose Connection That cross-connected Svc Air Sys W/Clean Condensate Sys Uncoupled & Secured ML17285A8081989-10-18018 October 1989 Responds to Request for Info on Environ Qualification of Taped Electrical Splices.Scotch Tapes Allowed by Electrical Test Guide Included Scotch 33,23 & 70 GO2-89-185, Responds to Request for Info on Environ Qualification of Taped Electrical Splices.Scotch Tapes Allowed by Electrical Test Guide Included Scotch 33,23 & 701989-10-18018 October 1989 Responds to Request for Info on Environ Qualification of Taped Electrical Splices.Scotch Tapes Allowed by Electrical Test Guide Included Scotch 33,23 & 70 ML19325D1931989-10-13013 October 1989 Forwards Quarterly Rept on Static-O-Ring Failures Third Quarter 1989,per IE Bulletin 86-002.Stated Switches Replaced 1990-09-07
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October 24, 1989 T.
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T Dr.-Thomas E. Murley, Director-e' Offlee of Nuclear Reactor Regulation U.S.' Nuclear Regulatory Commission Washington, DC 20555 Q,
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Subject:
LaSalle County Station Units 1 and 2 d
Inservice Testing (IST) Program l
E C Dx tet Nos. 50-373 and 50-374 q
4 Reference (a):. H.E. Morgan letter to T.E. Murley dated' October 2, 1989 (LaSalle County Station Units'1 and 2) Inservice Testing (IST)' Program.
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Dear Dr. Murley:
i Reference (a) transmitted LaSalle County Station's Inservice Testing Program (Revision 2).
For clarification purposes, the attached document provides a summary of the changes made in Revision 2 of the LaSalle County.
' Station Inservice Testing Program.
If'there are any further questions regarding this matter, please' f
contact this office.
Very truly yours, W
6:
H. 4 Morgan Nuclear Licensing Administrator im Attachment i'
cc:
P.C. Shemanski - Project Manager, NRR AoT7 A.B. Davis - Regional Administrator, RIII I
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Senior Resident Inspector - LaSalle County i
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- Inservice Testing Program' i
y Summary of Changes for Revision 2 i
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REFERENCES:
1)
AIR NO. 373-104-89-00400. documents response to Generic.
l Letter 89-04, i
l 2)
AIR NO. 373-251-88-00226, documents review of the IST L,;
program to the Q-List (list of safety-related components).
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+
The Inservice. Testing Program for pumps and valves is being revised based
- m on Generic Letter 89-04 (documented in reference 1).
The scope of the IST Program was also ' reviewed carefully to ensure the inclusion of the necessary pumps and valves in the program. This was accomplished by using LaSa11e's 3
Q-List and Component Classification documents. The following is a short
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discussion of the program changes.
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,SECTIOt in Table of Contente f
1.
A " Technical' Approach (es) and Position (s)" section was added to the j
IST program, therefore, it is referenced in the ' contents section.
?-
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SECTION 21 Inmarvice' Testina Procram Descrintion
.[
2.2 - Innervlee Testina
,j, 1.
Added requirement to identify approval document to each relief request and cold shutdown justification (2.2.1.7).
2..
.Added section 2.2.3 which discusses when and why a Technical l
Approach / Position is Utilised.
', l '
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SECTIGt 31 Format Leoend and Notes 3.0 - AEME Class 1.
2, and 3 Pumns a
1.
Added " Technical Approach (es) and Position (s)" to the field section 1
for pumps. The description is also given for the new field. The
" notes" field was changed to No. 13.
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, Inservice Testing Program-Summary.of Changes for Revisior 2 l
2.
mad 3 Valves 3.'1 - ARMR Clama ~1.
i 1.
The field section for valves has been changed.
" Technical-Approach (es) and Position (s)" was labeled No.10 and replaced the "masimum stroke time" field. The maximum stroke time will not be.a part of the NRC submittal due'to establishing limiting values of
-f 'I full-stroke based on reference values.
2.
Added " disassemble and inspect"'(DI) an a new test type.
f 3.
Test abbreviation SA (semi-annual) has been added to the " test schedule" field.
SECTION di Innervice Testina Plan-Pumns
^
1.
.A " Technical Approach (es) and Position (s)" column was added prior to the'" notes" field. The " notes" column became field no.13.
SECTION 51 Pumn Relief Reauesta p
?.
1.
An " Approval / Reference Document (s)" field was added to each relief
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request to depict the approval document or identify any applicable l
reference (s) used.
SECTION 6:
Inservice Teatino Plan - Valves Svatem Description
~
ALL 1.
Added TP-01 to all power operated valves that are stroked timed.
CM 1.
All SOVs will use the " rapid-acting valves" position per RV-56.
DG 2.
1(2)DG049A/B, ODG023A/B, 1(2)E22-F362A/B (DG air compressor i
discharge check valves) have been classified as active class 3 components, and therefore will be tested in the IST program per 7
1 RV-51.
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, Inservice Testing program
.i Summary of Changes.for Revision 2
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.J Inzervico Testl' a Plan - Valven J'~
SECTION 6:
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System Descrintian IKi 2.
1(2)DG055A/B, ODG029A/B, 1(2)E22-f369A/B, 1(2)E22-F370A/B (DG
'i' Air Receiver Check Valves) have been added to the IST program t
even=though they are non-code. 'At LaSalle they are considered 3'
to be safety-related passive, but a setpoint test will be' performed to ensure their operational readiness.-
DO 1.
1(2)DOO24 have been classified as passive and will be deleted
- t from the IST program.
FC 1.
1(2)TC105A/B have been deleted from the IST program due to the-u fact.that FC is a non-safety related system and does not fall j
within the scope of the IST program.
l 1
HG 1..
1(2)HG017A/B '(H2 Recombiner Water-Spray cooler supply CV's) have i
been classified as active class 2 valves and will be included in I
the'IST program. A cold shutdown justification (CS-53) has been written describing their test method and equivalent cold shutdown frequency.
i-2.
1(2)HG016 and 1(2)HG007 have also been classified active and will be tested in the IST program per Tech Specs on a 6 month 3
frequency. A c/s justification (CS-54) has been written describing the basis for this test frequency.
l HP 1.
1(2)E22-F006 (Water Leg Pump Disch Check Valves) have been added
[
to the IST program. A relief requent (RV-50) has been written for testing the plants ECCS WL pump discharge check valves.
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also explains why the upstream cv's must be disassembled and
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inspected during reactor refueling per RV-46.
E IA 1.
The outboard MSIV accumulatur check valves have been moved from IN to IA system designation.
^
I IN 1.
INO31, IN100, and IN101 solenoid valves will use RV-56,
" rapid-acting valves" position.
5 LP 1.
1(2)E21-F034 (Water Leg Pump Discharge Stop Check Valves) have j
been added to the program. These valves will be tested 1
quarterly per RV-50.
j' 2.
1(2)E21-F033 (water leg pump disch cv/s) testing methods have been changed to partial exercising quarterly per RV-50 with K
disassembly and inspection during refueling outages per RV-46.
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,s Inservice Testing Program
. Summary of Changes for Wevision 2 9
SECTION 6:
Inservice Testina' Plan - Valves System Description
'MS 1.
1(2)E32-F010,'1(2)E32-F011, 1(2)E32-F310A/B/C/D have been added to the IST program due to the component classification review.
These' valves have been determined to be class 2, active
<o components ~. Disassembly and inspection is the method of testing which will be used on a reactor refueling basis per RV-52 and RV-46.
'NR 1.
The following valves are non-code, however,.they are safety-related active. The valves are currently exercised and' leak tested per Technical Specifications, however, now they i
require a stroke time and PIT per GL 89-04.
.a.
1(2)C51-C004A b.
1(2)C51-C004B c.
1(2)C51-C004C d.
1(2)C51-C004D e.
1(2)C51-C004E
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i RD 1.-
The 1(2)C11-D001-115 and 1(2)C11-D001-138 valves have been added to the program per GL 89-04.
Relief Request RV-45 documents the testing methods.
RH 1.
1(2)E12-F060A/B (will use RV-56), 1(2)E12-F075A/B (will use RV-56): process sample valves are class 2, active and will be tested per normal code testing methods.
2.
1(2)E12-TC89/93/94/97, are also going to be added to the IST program. These valves'have been determined to perform a safety-related function and will be tested per normal code testing methods.
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3.
The 1(2)E12-F046A/B/C minimum flow line check valves will be partially stroked quarterly per RV-49, and disassembled and inspected per RV-46 per GL 89-04.
4.
1(2)E12-F040A/B, RHR drain isolation valves to radwaste are class 2, active and will be tested per normal code testing methods.
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Summary'of Changes forJRevision.2.
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SECTION'6t- -Innervice Testina Plan ~- Valygg E,
Sy.g tagg Description
'5 RH '.
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'The'following relief valves have had their classification changed to passive (per reference 2), however, they will remain in the IST. program and the setpoint. testing will continue.
i a.
1(2)E12-F005s_
h.
1(2)E12-F088A j
b.
1(2)E12-F025A 1.
1(2)E12-F088B
.c.
1(2)E12-F025B j.
1(2)E12-F088C d.
1(2)E12-F025C k.
1(2)E12-F311A
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1(2)E12-F030-1.
1(2)E12-F311B' f.
1(2)E32-F055A' m.
1(2)E12-F313A
'g.
1(2)E12-F0558 n.
1(2)E12-F313B y
5.
1(2)E12-F073A/B and 1(2)E12-F074A/B have been changed to active. They are already esercised in a station surveillance, however, they must now be stroke timed and have a position-a indication test performed for the IST program.
6.
1(2)E12-F084A/B/C (Water Leg Pump Disch CV's) will be added to p
the IST program. They will be partial stroke tested quarterly.
per RV-50 with disassembly and inspection every refuel outage per RV-46.
7.
1(2)E12-F085A/B/C (Water Leg Pump CV's) have been added to the program and will be tested quarterly pet.RV-50.
t RI 1.
1(2)E12-F036A/B have been given a pessive classification, however, testing will continue as with other relief valves.
t 2.
TP-02 was added to E51-F028/F040/F047 valves to document and 1
clarify testing in the IST program.
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Innervice Testina Plan - Valves "l
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Egitta Description q
RR 1.
The following valves are presently tested per LOS-PC-R1, j
2 however, due to reference 1 these valves are'now required tv be y
added to the IST program'(CIVs, Appendix J osempted).- The L
inboard valves can on3y be tested during c/s or refueling outages, but the outboard valves can.be tested quarterly.. C5. J5 explains the c/s basis.
a.'
1(2)B33-F338A 1.
1(2)B33-F342A
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b.
1(2)B33-F338B
- j. 1(2)B33-73428.
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c.
1(2)B33-F339A-k.
1(2)B33-F343A l
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d.
1(2)B33-F3398
- 1. '1(2)B33-F343B e.
1(2)B33-F340A-m.
1(2)B33-F344A
.f.
1(2)B33-F340B n.
1(2)B33-F344B' f.
g.
1(2)B33-F341A o.
1(2)B33-F345A I
4 h.
1(2)B33-F341B p.
1(2)B33-F345B O<
The following relief valves have been deleted from the IST RT 1.
' program since the reactor water cleanup system is non-safety E
-related.
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a.
1(2)G33-F339A d.
1(2)G33-F340B b.
1(2)G33-F339B e.
1(2)G33-F341A t
~ c.
1(2)G33-F340A f.
1(2)G33-F341B f
VG3 1.
1(2)VG0001 and VG0003 are classified as class 3 active valves and have been added to the IST program. Testing will include bn
' stroke timing and PITS.
F I
' VQ '
1.
VQ041 is a non-code valve and has been deleted from IST per E'
reference 2 documentation. The valves are classified as passive.
i' SECTION 7e Valve Rollef Recuests/ Cold Shutdown Justifications
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ALL An " Approval / Reference Document (s)" field was added to each relief request and cold shutdown justification to depict the approval document or identify any applicable reference (s) used.
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Summary of Changes for Revision 2
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1 SECTION 71 Valve Reljaf Reaumata/ Cold Ehutdown Justificationa
-Y 1-RV. Describes the basis for relief and alternate test methods for i
p the Gontrol Rod Drive.(CRD) charging water header cv's and the
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CRD' coo'.ing water cv's.
t
- 2..RV-46; Describes the GL 89-04 approved alternative to full-stroke esercising check. valves -- disassembly and inspection.
t 3.
RV-47 Explains the' basis for relief and alternate testing for the LPCS motor cooler water outlet ev's~which deviates from c0de testing l because it only proves a partial stroke according to Generic Letter 89-04.
L 4.
RV-48 (RCIC min flow line cv's); The present testing only proves a partial stroke according to Generic Letter 89-04.
This' relief request explains the basis for relief and testing method for-these valves.
- d 5.
RV-49.
(LPCI min flow line ev's);' Explains basis for relief and alternate test methods for these. valves.
IS i
6.
RV-50 (Water leg pump discharge cv's); Describes the reasoning and method of testing these valves.
7.
RV-51 Describes the basis for relief and alternate testing for the DG, compressor discharge cv's which have been added to the IST 3
i-program.
8.
RV-52 Explains basis for relief and alternate testing for the MSIV-LCS Cv's.
9.
CS-53 (Hydrogen Recombiner water-spray cooler supply cv's); Describes the reasoning behind the method of testing these. valves once a year (equivalent to c/s testing) for the IST program.
i 10.
CS-54 (Hydrogen Recombiner containment suction ev's); Explains basis for cold shutdown testing of these valves.
11.
CS-55 (Reactor Recirc hydraulic line inboard cv's); Describes the basis for relief and why these valves will be tested only during refueling outages. Explains that the outboard valves con be
[
i tested quarterly.
g.
12.
CS-56 Describes the limits imposed on rapid-acting solenoid valves in t
the IST program per the NRC staff's position described in GL 89-04.
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S weary of Changes-for Revision 2 I
'EECTItM'as-Technical Approachas and Positions
- 1.
TP-01' Developed to describe stroke, time testing of valves in'the IST program and the acceptance criteria involved with establishing alert and required action rLage limits.
F Describes the method'of-full-stroke' testing'of the T
'2.
TP-02:
E51-r028/F040/F047 RCIC systern ev's.
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