Proposed Tech Specs,Integrity of Containment Vessel Be Maintained at Level Consistent to Criteria in Spec 4.6.1.6ML20246N677 |
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Site: |
Callaway |
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Issue date: |
05/09/1989 |
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From: |
UNION ELECTRIC CO. |
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To: |
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Shared Package |
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ML20246N661 |
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References |
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NUDOCS 8905190496 |
Download: ML20246N677 (4) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211Q5411999-09-0808 September 1999 Proposed Tech Specs Reflecting USQ Associated with Increases in Offsite Dose Consequences Reported in FSAR for SGTR & MSLB Accidents ML20195C5191999-05-28028 May 1999 Proposed Tech Specs Sections 3.9.1,revised to Maintain CTS Requirements on Refueling Pool Boron Concentration Limits & 5.6.5,revised to Delete Item 5.6.5.a ML20207F4801999-05-27027 May 1999 Proposed Improved TSs & ITS Bases ML20206G3621999-04-30030 April 1999 Proposed Conversion Tech Specs Section 1.0/ITS Section 1.0 ML20205S9141999-04-21021 April 1999 Proposed Tech Specs Sections 1.0,3.3,3.4,3.6,3.7 & 3.9, Converting to ITS ML20205L0901999-04-0707 April 1999 Proposed Tech Specs Section 3.3,3.4,3.5,3.6,3.7,3.8 & 4.0, Converting to ITS ML20207L1061999-03-0909 March 1999 Proposed Tech Specs Re Conversion to ITSs Sections 3.3,3.4, 3.6,3.7.3 8,3.9 & 5.0 ML20196G1731998-11-25025 November 1998 Proposed Tech Specs Section 3.3, Intstrumentation, Converting to Improved Tech Specs ML20196D0011998-11-23023 November 1998 Proposed Tech Specs Pages Re follow-up Items Related to 970515 Request for Amend to License NPF-30 ML20155B5791998-10-27027 October 1998 Proposed Tech Specs for Use of Electrosleeves on Two Cycle Basis ML20154S2371998-10-21021 October 1998 Proposed Tech Specs Sections 3.1,3.2,3.4,3.5 & 5.0 Re Reactivity Control Sys,Power Distribution Sys,Rcs,Eccs & Administrative Controls,Respectively ML20154F8311998-09-29029 September 1998 Proposed Tech Specs Revising ESFAS Functional Unit 6.f Re Loss of Offsite power-start turbine-driven Pump ML20154A2901998-09-24024 September 1998 Proposed Tech Specs Converting to Improved TS Re Section 3.4, RCS, Consistent w/NUREG-1431 ML20151U1031998-08-27027 August 1998 Proposed Tech Specs Sections 1.0,2.0 & 3.0,converting to Improved Tech Specs ML20236Y1721998-08-0404 August 1998 Proposed Tech Specs Re Conversion to Improved STS Sections 3.1,3.2,3.5,3.9 & 4.0 ML20236W3721998-07-30030 July 1998 Proposed Tech Specs Revising Table 4.3-2 by Adding Table Notation to Clarify That Verification of Time Delays Associated W/Esfas Functional Units 8.a & 8.b Is Only Performed as Part of Channel Calibr ML20236J0821998-06-29029 June 1998 Proposed Tech Specs 3.7.1.7,4.7.1.7.1,4.7.1.7.2 & Bases 3/4.7.1.7 Revising to Address All Four Atmospheric Steam Dump Lines ML20236E9651998-06-26026 June 1998 Proposed Tech Specs Pages Re Conversion to Improved STS, Section 3.6 ML20216F3791998-03-0909 March 1998 Proposed Tech Specs SR 3/4.5.2b.1 Adding Clarification in Regard to Venting ECCS Pump Casings & Accessible Discharge Piping High Points ML20217P8161998-02-23023 February 1998 Proposed Tech Specs Replacement Page B 3.8-34 Re AC Sources Shutdown ML20198T3521998-01-16016 January 1998 Proposed Tech Specs 3/4.3,revising Ms & Feedwater Isolation Sys Slave Relay Surveillance from Quarterly Actuation Logic Test to Monthly Actuation Logic Test on Staggered Test Basis ML20197D6461997-12-16016 December 1997 Proposed Tech Specs Table Revising Lift Setting Tolerance for Main Steam Line Safety Valves ML20199B4261997-11-10010 November 1997 Proposed Tech Specs Re Page 5 of 8 for FW Isolation Changes ML20198P3361997-10-31031 October 1997 Proposed Tech Specs Reducing Repeated Alarms,Rod Blocks & Partial Reactor Trips That Continue to Manifest,During Beginning of Cycle Operation Following Refueling Outages ML20198P4141997-10-31031 October 1997 Proposed Tech Specs,Revising ESFAS Functional Unit 6.f, Loss of Offsite Power-Start Turbine-Driven Pump, in Tables 3.3-3,3.3-4 & 4.3-2 ULNRC-03664, Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits1997-10-17017 October 1997 Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits ML20198F3911997-08-0808 August 1997 Proposed Tech Specs Changes,Revising Feedwater Isolation ESFAS Functions in TS Tables 3.3-3,3.3-4 & 4.3-2 ML20198F3411997-08-0808 August 1997 Proposed Tech Specs,Revising Table 3-7.2 to Specify That Lift Setting Tolerance for Main Steam Line Safety Valves Is +3/-1% as-found & +1% as-left.Table 2.2-1 Revised by Reducing Sensor Error for Pressurizer pressure-high Trip ML20210H2151997-08-0808 August 1997 Proposed TS Revising SRs 3/4.7.4, Essential Svc Water Sys by Removing Requirement to Perform SRs 4.7.4.b.1, 4.7.4.b.2 & 4.7.4.c During Shutdown ML20217H8031997-08-0808 August 1997 Proposed Tech Specs 3/4.3 Re Instrumentation ML20198J7301997-05-15015 May 1997 Proposed Conversion to ITS Sections 1.0,3.1,3.2,3.3,3.4,3.7, 3.9 & 5.0 for Plant ML20154Q1191997-05-15015 May 1997 Proposed Improved TS Section 3.7, Plant Sys ML20138B7421997-04-24024 April 1997 Proposed Tech Specs 6.0 Revising Title Senior Vice President,Nuclear to Vice President & Chief Nuclear Officer ML20137N6111997-04-0101 April 1997 Proposed Tech Specs Table 3.3-3 Re Engineered Safety Features Actuation Sys Instrumentation ML20117K6431996-09-0505 September 1996 Proposed Tech Specs,Revising TS 3/4.4 Re RCS ML20115J0181996-07-18018 July 1996 Proposed Tech Specs 3/4.7.7,3/4.9.13 & Corresponding Bases Re Charcoal Test Methodology for Emergency Exhaust Sys ML20107H3931996-04-17017 April 1996 Proposed Tech Specs 3/4.3 Re Adding Ms & FW Isolation Sys Actuation Logic & Relays to Functional Units 4.b & 5.a of Tables 3.3-3,3.3-4 & 4.3-2 & Revising Table 3.3-3 by Adding Action Statements 27a & 34a ML20107F0791996-04-12012 April 1996 Proposed Tech Specs 3/4.4 Re Changing TS, RCS & Associated Bases to Address Installation of Electrosleeves in Callaway Plant SGs ML20107E3251996-04-12012 April 1996 Proposed Tech Specs 3/4.4.5, SGs & 3.4.6.2, Operational Leakage & Associated Bases,Addressing Installation of Laser Welded Tube Sleeves in Plant SGs ML20101R4211996-04-0909 April 1996 Revised TS Pages That Adhere to Testing Methods of ASTM Std D2276-78,Method a for Diesel Fuel Oil Particulate Concentration ML20101J0381996-03-22022 March 1996 Proposed Tech Specs,Implementing Containment Integrated Leakage Rate Program That Would Allow Ilrt,Presently Scheduled for Refuel 8,to Be Rescheduled ML20106G4351996-02-28028 February 1996 Proposed TS 3/4.8.1,ac Sources ML20106G4131996-02-23023 February 1996 Proposed Tech Specs Paragraph 1.A. Re Operating License Change to Reflect Union Electric as wholly-owned Subsidiary of Ameren Corp ML20097D5801996-02-0909 February 1996 Proposed Tech Specs Allowing Use of Alternate Zirconium Based Fuel Cladding Material ML20097D6151996-02-0909 February 1996 Proposed Tech Specs & Bases Re Containment Systems ML20097D6341996-02-0909 February 1996 Proposed Tech Specs Re AFW Sys ML20097F8991996-02-0404 February 1996 Proposed Tech Specs 4.6.1.2.a Re Containment Sys ML20097C2791996-02-0202 February 1996 Proposed Tech Spec 3/4.6.3, Containment Isolation Valves ML20096B1891996-01-0202 January 1996 Proposed Tech Specs 3.9.4, Containment Bldg Penetrations & Associated Bases Section to Allow Containment Personnel Airlock Doors to Be Open During Core Alterations ML20094A1721995-10-23023 October 1995 Proposed Tech Specs,Relocating Audit Frequencies in Former TS 6.5.2.9 to Operational QA Manual 1999-09-08
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211Q5411999-09-0808 September 1999 Proposed Tech Specs Reflecting USQ Associated with Increases in Offsite Dose Consequences Reported in FSAR for SGTR & MSLB Accidents ML20195C5191999-05-28028 May 1999 Proposed Tech Specs Sections 3.9.1,revised to Maintain CTS Requirements on Refueling Pool Boron Concentration Limits & 5.6.5,revised to Delete Item 5.6.5.a ML20207F4801999-05-27027 May 1999 Proposed Improved TSs & ITS Bases ML20206G3621999-04-30030 April 1999 Proposed Conversion Tech Specs Section 1.0/ITS Section 1.0 ML20205S9141999-04-21021 April 1999 Proposed Tech Specs Sections 1.0,3.3,3.4,3.6,3.7 & 3.9, Converting to ITS ML20205L0901999-04-0707 April 1999 Proposed Tech Specs Section 3.3,3.4,3.5,3.6,3.7,3.8 & 4.0, Converting to ITS ML20207L1061999-03-0909 March 1999 Proposed Tech Specs Re Conversion to ITSs Sections 3.3,3.4, 3.6,3.7.3 8,3.9 & 5.0 ML20196G1731998-11-25025 November 1998 Proposed Tech Specs Section 3.3, Intstrumentation, Converting to Improved Tech Specs ML20196D0011998-11-23023 November 1998 Proposed Tech Specs Pages Re follow-up Items Related to 970515 Request for Amend to License NPF-30 ML20155B5791998-10-27027 October 1998 Proposed Tech Specs for Use of Electrosleeves on Two Cycle Basis ML20154S2371998-10-21021 October 1998 Proposed Tech Specs Sections 3.1,3.2,3.4,3.5 & 5.0 Re Reactivity Control Sys,Power Distribution Sys,Rcs,Eccs & Administrative Controls,Respectively ML20154F8311998-09-29029 September 1998 Proposed Tech Specs Revising ESFAS Functional Unit 6.f Re Loss of Offsite power-start turbine-driven Pump ML20154A2901998-09-24024 September 1998 Proposed Tech Specs Converting to Improved TS Re Section 3.4, RCS, Consistent w/NUREG-1431 ML20151U1031998-08-27027 August 1998 Proposed Tech Specs Sections 1.0,2.0 & 3.0,converting to Improved Tech Specs ML20236Y1721998-08-0404 August 1998 Proposed Tech Specs Re Conversion to Improved STS Sections 3.1,3.2,3.5,3.9 & 4.0 ML20198D3201998-07-31031 July 1998 Rev 20 to Inservice Testing Program at Callaway Nuclear Plant ML20236W3721998-07-30030 July 1998 Proposed Tech Specs Revising Table 4.3-2 by Adding Table Notation to Clarify That Verification of Time Delays Associated W/Esfas Functional Units 8.a & 8.b Is Only Performed as Part of Channel Calibr ML20236J0821998-06-29029 June 1998 Proposed Tech Specs 3.7.1.7,4.7.1.7.1,4.7.1.7.2 & Bases 3/4.7.1.7 Revising to Address All Four Atmospheric Steam Dump Lines ML20236E9651998-06-26026 June 1998 Proposed Tech Specs Pages Re Conversion to Improved STS, Section 3.6 ML20216F3791998-03-0909 March 1998 Proposed Tech Specs SR 3/4.5.2b.1 Adding Clarification in Regard to Venting ECCS Pump Casings & Accessible Discharge Piping High Points ML20195B5651998-03-0202 March 1998 Rev 22 to QC Procedure QCP-ZZ-03003, Matl Receipt Insp ML20217P8161998-02-23023 February 1998 Proposed Tech Specs Replacement Page B 3.8-34 Re AC Sources Shutdown ML20198T3521998-01-16016 January 1998 Proposed Tech Specs 3/4.3,revising Ms & Feedwater Isolation Sys Slave Relay Surveillance from Quarterly Actuation Logic Test to Monthly Actuation Logic Test on Staggered Test Basis ML20197D6461997-12-16016 December 1997 Proposed Tech Specs Table Revising Lift Setting Tolerance for Main Steam Line Safety Valves ML20199B4261997-11-10010 November 1997 Proposed Tech Specs Re Page 5 of 8 for FW Isolation Changes ML20198P3361997-10-31031 October 1997 Proposed Tech Specs Reducing Repeated Alarms,Rod Blocks & Partial Reactor Trips That Continue to Manifest,During Beginning of Cycle Operation Following Refueling Outages ML20198P4141997-10-31031 October 1997 Proposed Tech Specs,Revising ESFAS Functional Unit 6.f, Loss of Offsite Power-Start Turbine-Driven Pump, in Tables 3.3-3,3.3-4 & 4.3-2 ML20217B3261997-10-22022 October 1997 Procedure MPE-ZZ-QY128, Operational Test Sequence of 4.16KV Diesel Generator NE02 Air Circuit Breaker 152NB0211 ULNRC-03664, Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits1997-10-17017 October 1997 Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits ML20217B3001997-09-14014 September 1997 Procedure ETP-NF-00001, MDAFW Pump (DPAL01A) Start Inhibit Circuit Test,Lsels Relay K1102 ML20217B3081997-09-0404 September 1997 Procedure ETP-BF-00002, Mdaew Pump (DPAL01B) Start Inhibit Circuit Test,Lsels Relay K4102 ML20217H8031997-08-0808 August 1997 Proposed Tech Specs 3/4.3 Re Instrumentation ML20210H2151997-08-0808 August 1997 Proposed TS Revising SRs 3/4.7.4, Essential Svc Water Sys by Removing Requirement to Perform SRs 4.7.4.b.1, 4.7.4.b.2 & 4.7.4.c During Shutdown ML20198F3411997-08-0808 August 1997 Proposed Tech Specs,Revising Table 3-7.2 to Specify That Lift Setting Tolerance for Main Steam Line Safety Valves Is +3/-1% as-found & +1% as-left.Table 2.2-1 Revised by Reducing Sensor Error for Pressurizer pressure-high Trip ML20198F3911997-08-0808 August 1997 Proposed Tech Specs Changes,Revising Feedwater Isolation ESFAS Functions in TS Tables 3.3-3,3.3-4 & 4.3-2 ML20195B5261997-05-20020 May 1997 Rev 6 to EDP-ZZ-03000, Containment Building Coatings ML20154Q1191997-05-15015 May 1997 Proposed Improved TS Section 3.7, Plant Sys ML20198J7301997-05-15015 May 1997 Proposed Conversion to ITS Sections 1.0,3.1,3.2,3.3,3.4,3.7, 3.9 & 5.0 for Plant ML20138B7421997-04-24024 April 1997 Proposed Tech Specs 6.0 Revising Title Senior Vice President,Nuclear to Vice President & Chief Nuclear Officer ML20141D9331997-04-14014 April 1997 Rev 18 to Inservice Testing Program for Callaway Nuclear Plant ML20141C3401997-04-14014 April 1997 Rev 18 to CNP IST Program ML20137N6111997-04-0101 April 1997 Proposed Tech Specs Table 3.3-3 Re Engineered Safety Features Actuation Sys Instrumentation ML20195B5581997-03-11011 March 1997 Rev 12 to Matls Engineering Procedure WEP-ZZ-00015, Preparation of Procurement Documents ML20195B5491997-01-31031 January 1997 Rev 22 to Administrative Procedure APA-ZZ-00400, Procurement of Parts,Supplies,Matls & Svcs ML20135E7351996-12-11011 December 1996 Tests to Determine Ampacity Derating Factors for Electrical Conductors Installed in 1 & 4 Diameter Rigid Steel Conduits Encapsulated by KM1 Darmatt One H Replacement Matl ML20135E7391996-12-11011 December 1996 Tests to Determine Ampacity Derating Factors for Electrical Conductors Installed in 1 & 4 Diameter Rigid Steel Conduits Encapsulated by KM1 Darmatt Three H Replacement Matl ML20135E7431996-12-11011 December 1996 Test to Determine Ampacity Derating Factor for Electrical Conductors Installed in 600mm X 101mm X 3650mm Long Cable Tray Encapsulated by KM1 Darmatt Three H Replacement Matl ML20140G2331996-10-31031 October 1996 Rev 6 to Callaway Plant Offsite Dose Calculation Manual ML20217B2951996-10-0303 October 1996 Procedure ISP-SA-2413A, Diesel Generator & Sequencer Testing (Train a) ML20117K6431996-09-0505 September 1996 Proposed Tech Specs,Revising TS 3/4.4 Re RCS 1999-09-08
[Table view] |
Text
_ _____-.
_ ULNRC-2003
_ 4. J '.' ***.
~, ' ATTAcw Mewt SAMPLE TECHMICAL SPECIFICATION l CONTA1NMENT SYSTEMS '
l CONTAINMENT VESSEL STRUCTURAL INTEGRITY 1.1HITING CONDITION F0P OPERATION 3.6.1.6 The structural integrity of the containment vessel shall be main-tained at a level consistent with the acceptance criteria in Specification 4.6.1.6.
jg l y
APPLICABILITY: Modes 1, 2, 3, and 4.
ACTION:
- a. With the abnorma d gradation ndicated by the conditions in Speci-fication 4.6 thin . .la.4, resto the tendons to the required level of integrity 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> a d perform an engineering evaluation of the containment and provid a Special Report to the Comission with-in 15 days in accordance ith Specification 6.9.2 or be in at least -
~
HOT STANDBY within the xt 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the '
following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- b. With the indicated atrnormal degradation of the structural integrity other than ACTION a at a level below the acceptance criteria of Specification 4.6.16, restore the containment vessel to the required level of integrity ithin 15 days; perform an engineering evaluation of the containment and provide a Special Report to the Comission within 30 days in accordance with Specification 6.9.2 or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN o, .scw cuea 3C4 within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. & % u,..n vu. m pmout. .
SURVEILLANCE REQUIREMENTS .
4.6.1.6.1 CONTAINMENT YESSEL TENI;DNS r. 5' The structural integrity of the prestr ing tendons of the containment vessel no shall be demonstrated at the end of 1. *. ::t 5 years following the initial containment vessel structural integrity test and at 5-year intervals ia ' " there-Mmo after. != : -M :t ' :;:0 + ' r - r e ' + = > ^ - + " --~ + - " A ~
+ tS h: M :: 90
- *tre t-td. The structural'integri-ox '-:-*-t'er ;;h;d k
$8 ty of the tendons :h::'d be demonstrated by:
om AAsLQ.
M a. Determining that a random but representative sam lec of at least
$cc // tendons ( 7 hoop, A y \ fSh(f orce within the P e-
. 4
& invertedU)eachhaveaobservedlifT-off dicted limits established for each tendon. For each subsequent in-i l spection one tendon from each group shall be kept unchanged to de- / 2 velop a history and to correlate the observed data. The procedure '
of inspection and the tendon acceptance criteria shall be as follows:
, +--H-I- - ---- ..-- _ ---- - ULNRC-2003
- - l q
.l l
- 1. If the measured prestressing force of the selected tendon in a group 4 lies above the prescribed lower limit, the lift-off test is con- l E
sidered to be a positive indication of the sample tendon's accept-
- 2. If the measured pre ressing force of the selected tendon in a group lies between the escribed lower limit and 90% of the prescribed e MM lower limit, two endons, one on each side of this tendon d eolo checked for their prestressing forces. If the prestressing forces of these two tendons are above 95% of e prescribed lower limits for the tendons, all three tendons be rest ed to the required level of integrity, and the tendon group be considered as acceptable. If the measured prestressing force of any two tendons fallsbelow95%ofthepregibedlowerlimitsofthetendons,ad- '
ditionallift-offtesting....1dbedonetope"ectthecauseand extent.cf such occurrence. The condition L. Y be considered as an indication of abnormal degradation of the containment structure.
sI.LL below 90% of
- 3. Ifthemeasuredprestressingforceofanytendonlie[idbecompletely the prescribed lower limit, the defective tend g h..
detensioned and additional lift-off testing 2 ... be done so as to determine the cause and extent of such occurrence. The condition 9 4 ; buld be considered as an indication of abnormal degradation of the containment structure.
4.- If the average of all measured p estressing forces for each group (corrected for average condition is found to be less than the mini-mumrequiredpregsslevelat/anchoragelocatior6forthatgroup, the condition d....-be considered as abnormal degradation of the containment structure.
- 5. If from consecutive surveillance the measured prestressing forces for the same tendon or tendons in a group indicate a trend of pre-stress loss larger than expected and the resulting prestressing forces will be less than the minimum required for the group before the next scheduled surveillance, additional lift-off testingd:uld.ALL be done so as to determine the cause and extent of such occurrence.
The condition 2:uld be considered as an indication of abnormal '
degradationof)tgcontainmentstructure.
- 6. .Unless there is abnormal degradation of the containment vessel during the first three inspections, the sample population for subsequent ins tendons ( 3 hoop,, @
@pectionsshallinclydeatleast
.- @ r^3 inverte .
- b. performing tendon detensioning, inspections, and material tests on a previously stressed tendon from each group. A randomly selected tendon from each group shall be completely detensioned in order to identify broken or damaged wires and determining that over the entire length of the removed wire sample (which skuld include the broken wire if so identified) that: M
ULNRC.-2003 p ." 2 .l =. . _ _ _ ._. . _ . . , _ _ , _ _,
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.s..
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sa aur- na in uiwou u 9'.c.t.t.1.5 6uu r i,your,,, , m wr. K 4M*r'~'d " M - -
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- 1. The tendon wires are free of corrosion, cracks, and damageg
- 2. A minimum tensile strength of f4t/ hsi (guaranteed ultimate i strength.of the tendon material) exists for at least three wire sampiegs i (onefromeachendandoneatmid-length)cutfromeachremovedwire. the-m4nhun tendie F44kre et Sry e'e of the wtre-sampler ta maat W strength-test-4s-tir-indkat+on-ef-stmormal degradation-of-the-coetain-mantw e:::1 struct; e.
- c. Performing tendon re ensioning of those tendons detensioned for in-spection to at least' force level recorded prior to detensioning or the predicted value, whichever is greater, with the tolerance wi retensioning df these ten-mate tensile strength Sf the tendons. Dugd-be measured simultaneous-dons; the changes in load and elongation ....-. sly at a minimum of th If the elongation corresponding to a between zero and the seating force.
specific loed)(differs by moreg10% from that recorded during the in- g stallation, an investigation L .w be made to ensure that the differenceanchora is not related to wire failures or s. lip ofm,uuns. wires in/ c+ m u m,,, m ,.r- .awa ,
- u. ca.rweas a e isoiw,.s a w wr.
h
- d. Verifying the OPERABILITYwoA of the sheat,hing filler grease by$ assuring:
ru tww- e ua .
There are no changes in e pres'i6ce orpFysTH1 appiiarance of the
- 1. puid '
i sheathing filler-grees . /exceedi SY of the net duct volume, when in-
- 2. Amount df crease replaced 1 insta11at' ion pressure jected at8the 4rigin:
T EF / /W
- 3. Minimum grease coverage exists for the diffe,ren't~' parts of the ancher-sr u e age system, eed-d;te:t:d c rn general A examination visual '"nM M~of the con-d_rY
- 4. 4re::: h:E:;: "
tainment exterior surface .
r~
- 5. The chemical propertie 1er ma&al teri are witYn the Nr g am-"
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m namwnwn ance limits p:if u' Water Content f M :: ..g%
C-1co, on mwr-(Sr tend:n: 0"TSM50T-)-
s cizding 0--1% L.y *t.
' L.. den: C"T U ZT' f d i . . , Z L., .J .
j g.-a. u .t.t.l..l 0 - 10 ppm v- de u,moua > Chlorides 0 - 10 ppm 4 & mo uw a Nitrates 0-cKppm J N% M e Sulfides Reserved Alkalinity 0---405-cf ths-installed-valuet-W tw. c,sa-Nrwrua. Dise Lii.Lers)- > 0 - 5 (fer elder-grease} AA-
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s an assurance 4.6.1.6.[ End Anchorages and Adjacent Concrete Surfaces ndon anchorage as-of the structural integrity of the containment vessel, ts, wedges, and but-sembly hardware (such as bearing plates, stressing wastonheads) net o Ber4ng :ea.bincd inspec4 ton _isee_ Attachment 14rfor-the-containment Tendon 4esselv having 411 h: pen (en, enty-v4sua.1 inspectinn need-to-txe-performed.be visual anchorages selected for inspection '
practical without dismantling the load bearing components of the anchorages.
sML
ULNRC-2003 l
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Bottom grease caps of all vertical tendons M beThe visually inspected surrounding to concrete l detect grease leakage or grease cap deformations. l spu. s w id also be checked visually for indication of any abnormal condition. -
~ i the con- l The exterior surf 4
[ 4.6.1.6.3 ~ Containment "
E be visuallyYessel examined Surfaces to detect areas of arge spall, severe ~
tainment scaling,Dt @lflFcking in an area of 25 sq. f t. or more, hgr, surface deteriora-tion or disintegration, or grease leakage, each of .r ::r be considered as y evidence of abnormal degradation of structural integr ty of the containment, This inspection shall be performed prior to the Type A containment leakage l rate test.
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