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Category:CORRESPONDENCE-LETTERS
MONTHYEAR05000482/LER-1999-002, Forwards LER 99-002-00,re Identification of Surveillance Performed in Modes Other than Those Required by TS SR 4.6.3.2.a.Commitments Made by Util Are Encl1999-10-15015 October 1999 Forwards LER 99-002-00,re Identification of Surveillance Performed in Modes Other than Those Required by TS SR 4.6.3.2.a.Commitments Made by Util Are Encl 05000482/LER-1994-014, Forwards LER 94-014-00 Re Util Identification of Missed Surveillance Required by TS Prior to Changing Modes.List of Commitments Made by Licensee,Encl1999-10-15015 October 1999 Forwards LER 94-014-00 Re Util Identification of Missed Surveillance Required by TS Prior to Changing Modes.List of Commitments Made by Licensee,Encl ML20217F7481999-10-14014 October 1999 Informs That Based on Approval of Core Assessment Damage Guidance in WCAP-14696,rev 1 for Westinghouse Nuclear Power Plants,Licensee May Use WCAP-14696,rev 1 at Wolf Creek Generating Station ML20217F8701999-10-13013 October 1999 Provides Summary of Meeting on 991007 with Representatives of Wolf Creek Nuclear Station in Burlington,Kansas Re Status of Licensee Radiation Protection Program.List of Meeting Attendees & Licensee Presentation Encl ML20217C1721999-10-0707 October 1999 Forwards Insp Rept 50-482/99-09 on 990830-0903.No Violations Noted.Purpose of Insp to Perform Routine Operational Status Insp of Emergency Preparedness Program & to Resolve Questions Re Revised Emergency Plan ML20217A4881999-09-29029 September 1999 Forwards Changes to Plant Data Point Library,Iaw 10CFR50,App E,Section VI.3.a.ERDS Point Affected Is RDS0001 ML20216H9291999-09-29029 September 1999 Informs That Licensee Responses to GL 97-06, Degradation of Steam Generator Internals Acceptable & Did Not Identify Any New Concerns with Condition of SG Intervals at Plant ML20212G1681999-09-24024 September 1999 Notifies NRC of Change in Status of Licensed Individual at Plant,Per 10CFR50.74.RL Acree Holds License OP-42654 at Plant,But Has Been Permanently Reassigned from Position for Which Plant Has Certified Need for RO License ML20216F9591999-09-22022 September 1999 Forwards Withdrawal of Amend Request Re Ultimate Heat Sink Temp for Wolf Creek Generating Station ML20212G5641999-09-20020 September 1999 Forwards Insp Rept 50-482/99-13 on 990725-0904.Three Violations Being Treated as Noncited Violations 05000482/LER-1999-011, Forwards LER 99-011-00 Re Identification of Missed Surveillance Due to Exceeding Flow Rate Specified in TS for Ccps.List of Util Commitments Contained in Attachment I1999-09-17017 September 1999 Forwards LER 99-011-00 Re Identification of Missed Surveillance Due to Exceeding Flow Rate Specified in TS for Ccps.List of Util Commitments Contained in Attachment I 05000482/LER-1999-010, Forwards LER 99-010-00,re Failure to Correctly Perform TS Surveillance 4.3.3.6.Encl Identifies Actions Committed to by Util1999-09-16016 September 1999 Forwards LER 99-010-00,re Failure to Correctly Perform TS Surveillance 4.3.3.6.Encl Identifies Actions Committed to by Util ML20212D9381999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of WCGS on 990818.Areas of EP & Engineering Warranted Increase in NRC Action.Nrc Plan to Conduct Add Insp Beyond Core Insp Program Over Next 7 Months to Address Listed Questions 05000482/LER-1999-006, Forwards LER 99-006-01,re Identification of Failure to Enter LCO for TS 3.6.1.1 While Taking Containment Atmosphere Samples During Power Operation.Commitments Made by Util Are Encl1999-09-15015 September 1999 Forwards LER 99-006-01,re Identification of Failure to Enter LCO for TS 3.6.1.1 While Taking Containment Atmosphere Samples During Power Operation.Commitments Made by Util Are Encl ML20212C9211999-09-15015 September 1999 Forwards NRC Form 536, Operating Licensing Examination Data, in Response to NRC Administrative Ltr 99-03 ML20216F1641999-09-14014 September 1999 Forwards Insp Rept 50-482/99-12 on 990816-20.No Violation Noted.Determined That Solid Radwaste Mgt & Radioactive Matls Transportation Programs Were Properly Implemented 05000482/LER-1999-009, Forwards LER 99-009-00 Re Util Identification of Fire Suppression Issue Affecting Safe Shutdown Components. Attachment I Identifies Actions Committed to by Licensee in Encl LER1999-09-10010 September 1999 Forwards LER 99-009-00 Re Util Identification of Fire Suppression Issue Affecting Safe Shutdown Components. Attachment I Identifies Actions Committed to by Licensee in Encl LER ML20212A5651999-09-10010 September 1999 Informs of Completion of Review of & Encl Objectives for Wolf Creek Generating Station 1999 Emergency Preparedness Exercise Scheduled for 991117.Determined Exercise Objectives Appropriate to Meet EP Requirements 05000482/LER-1999-008, Forwards LER 99-008-00,re Efsa at Plant.Attachment I Identifies Actions Committed to by Licensee in LER1999-09-0303 September 1999 Forwards LER 99-008-00,re Efsa at Plant.Attachment I Identifies Actions Committed to by Licensee in LER ML20211M7151999-09-0303 September 1999 Forwards Changes to Wolf Creek Generating Station Data Point Library.Emergency Response Data Sys Points Affected Are EJL0007 & EJL0008 ML20211N0081999-09-0202 September 1999 Informs That NRC Staff Has Reviewed Submittals & Concluded Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power- Operated Gate Valves ML20211K8301999-09-0202 September 1999 Forwards marked-up TS Page Deleting Inequality Signs from Trip Setpoints in SR 3.3.5.3 & Reflecting Info on Calibr Tolerance Band,Per 990708 Application to Amend License NPF-42 ML20211K1941999-08-31031 August 1999 Forwards Rev 31 to WCGS Physical Security Plan,Safeguards Contingency Plan & Training & Qualification Plan,Iaw 10CFR50.54(p).Encl Withheld,Per 10CFR73.21 ML20211H1491999-08-26026 August 1999 Forwards Insp Rept 50-482/99-16 on 990809-13.No Violations Noted.Insp Focused on Low as Is Reasonably Achievable Program,Training Program for Contract Radiation Protection Personnel & Radiation Protection QA Program ML20211A8581999-08-18018 August 1999 Forwards Insp Rept 50-482/99-08 on 990316-0724.One Violation Being Treated as Noncited Violation ML20211G2201999-08-17017 August 1999 Forwards Exam Rept 50-482/99-301 on 990726-29.Exam Evaluated Six Applicants for SO Licenses & Three Applicants for RO Licenses ML20210U0991999-08-13013 August 1999 Forwards Insp Rept 50-482/99-11 on 990712-16.No Violations Noted.Insp Was to Review Radiological Environ Monitoring Program ML20210U9751999-08-13013 August 1999 Informs That Licensee Identified That Answer Key for One Question on 990720 Written Exam & Event Classification for on Job Performance Measure Required Mod.Description & Justification for Proposed Mod,Including Technical Ref,Encl ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210R5621999-08-12012 August 1999 Forwards Monthly Operating Rept for July 1999 for Wolf Creek Generating Station,Per TS 6.9.1.8 & GL 97-02.Revised Repts for Apr,May & June 1999,correcting Number of Hours Reactor Critical,Encl ML20210P7491999-08-0909 August 1999 Ack Receipt of ,Which Transmitted Wolf Creek Radiological Emergency Response Plan 06-002,Rev 0,under Provisions of 10CFR50,App E,Section V ML20210N0061999-08-0303 August 1999 Forwards Response to NRC 990401 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Motor-Operated Gate Valves ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210H2551999-07-29029 July 1999 Provides 180-day Response to NRC Request for Info Re GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20210J1371999-07-29029 July 1999 Requests NRC Approval of Methodology for Determining RCS Pressure & Temp & Overpressure Mitigation Sys PORV Limits. Attachment I Provides Proposed Changes to Improved TS ML20210F5931999-07-27027 July 1999 Forwards semi-annual Fitness for Duty Performance Data Rept for Wcnoc,Per 10CFR26.71(d).Rept Covers Period of 990101- 0630 ML20210F5881999-07-23023 July 1999 Submits Response to Administrative Ltr 99-02, Operator Reactor Licensing Action Estimates, ML20210B8191999-07-20020 July 1999 Ack Receipt of ,Which Transmitted Wolf Creek EP Implementing Procedure 06-005,Rev 1.Implementation of Changes Will Be Subj to Insp to Confirm That Changes Does Not Decrease Effectiveness of EP ML20209H5411999-07-15015 July 1999 Forwards Insp Rept 50-482/99-07 on 990614-18.No Violations Noted.Insp Focused on Radiation Program During Normal Operating Conditions ML20209H0441999-07-14014 July 1999 Forwards Response to NRC 990326 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. Summary of Util Commitments Provided in Attachment 2 ML20209H0751999-07-14014 July 1999 Forwards Monthly Operating Rept for June 1999 for Wolf Creek Generating Station,Per TS 6.9.1.8 & GL 97-02.Max Dependable Capacity Has Been Updated from 1163 to 1170,as Determined by Calculations Based on Capacity Test Results of July 1998 ML20209G9871999-07-14014 July 1999 Informs of Changes Affecting Wolf Creek Security Plan,Per 10CFR50.54(p)(2).Encl Provides Description of Changes & Justification for Changes ML20209E3581999-07-12012 July 1999 Discusses Util 980925 Response to GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Wolf Creek Generating Station ML20209E0611999-07-0808 July 1999 Forwards Addl Pages to Rev 12 of USAR & Commitment Changes, Inadvertently Omitted from 990311 Submittal ML20196K8231999-07-0606 July 1999 Submits Kansas Electric Power Cooperative,Inc Ltr Pursuant to Commission Direction in Memo & Order CLI-99-19.Addresses Disposition of Existing Antitrust Conditions Attached to License for Wolf Creek Unit 1 Re Proposed License Transfer ML20209C6031999-07-0606 July 1999 Provides Applicants View as Result of 990618 Memo & Order Directing Parties to Address Proper Disposition of Existing Antitrust License Condition Attached to OL for Facility Due to Planned Changes in Ownership of Facility.With Svc List ML20196K0501999-07-0202 July 1999 Forwards Insp Rept 50-482/99-06 on 990502-0612.Three Violations Occurred & Being Treated as Noncited Violations, Consistent with App C of Enforcement Policy ML20209B7131999-07-0101 July 1999 Submits Response to NRC Request for Info Re GL 98-01, Suppl 1, Y2K Readiness of Computer Sys at Npps. Response on Status of Facility Y2K Readiness Was Requested by 990701.Disclosure Encl ML20209A7461999-06-29029 June 1999 Informs of Changes in Project Mgt Staff Assigned to Wcgs. Effective 990628,J Donohew Will Assume PM Responsibilities ML20209B5151999-06-29029 June 1999 Informs That Util Completed Analyses & Modifications to Address Items Discussed in GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions 1999-09-03
[Table view] Category:EXTERNAL CORRESPONDENCE
MONTHYEARML20141K4131997-05-20020 May 1997 Submits Evaluation of Ameron Corrective Action Status Rept to Wolf Creek Supplier Quality Audit Findings ML20141K4041997-03-28028 March 1997 Informs That Wolf Creek Evaluated Ameron Response to Findings Identified During Audit Conducted on 970122-23 & 970128-31.Evaluation Found Responses to Findings Ron 01/97-001-011 Conditionally Accepted ML20141K6441997-02-27027 February 1997 Forwards WCNOC Supplier Quality Rept of NUPIC Joint Audit Performed by Wcnoc,Union Electric & TVA of Brea,California Facility on 970122-23 & Little Rock,Ar Facility on 970128-31 ML20081D5081995-03-0101 March 1995 Forwards Analysis Summary Rept Re RCS Drain Down Event,Rept Summarizes Analyses to Determine RCS & ECCS Conditions During Actual Event ML20077K4511991-07-25025 July 1991 Forwards Chapter 14 to Updated Sar,Initial Startup Rept, Documents in Response to Item 4,operating License for Facility & Milestone Schedule,Per NRC ML20072P0161983-07-13013 July 1983 Informs That No Changes to Emergency Plan Adopted Since Nov 1982 Rev,In Response to .Certificate of Svc Encl ML20076L5781983-07-11011 July 1983 Discusses Status of 830406 Proposed Stipulation of Contentions.No Agreement Reached Amongst Counsel at 830427 Conference Call.Fema Cannot Commit Resources to Preparing Testimony for 830830 Prefiling ML20076L6011983-07-11011 July 1983 Discusses Status of 830406 Proposed Stipulation of Contentions.No Agreement Reached Amongst Counsel at 830427 Conference Call.Fema Cannot Commit Resources to Preparing Testimony for 830830 Prefiling ML20083P3761983-01-13013 January 1983 Advises of Establishment of Task Force to Oversee Completion of Bm,Ef & Eg Sys,Preparation & Completion of Associated Quality Documentation & Review of Documentation.Task Force Will Commence on 830120 & Be Chartered for 30 Days ML20010J5791981-09-29029 September 1981 Forwards Applicant Further Response to Financial Qualifications Discovery Requests of Intervenor Kansans for Sensible Energy.Related Correspondence ML20010D1901981-08-17017 August 1981 Ack Receipt of 810813 Ltr Requesting Rescheduling of Osann Deposition.Lists Available Dates for Rescheduling.Related Correspondence ML19352A9501981-05-29029 May 1981 Comments on Revision 1 to Environ Rept for Facility,Per 810506 Request.Lists Species Present in Proposed Project Area.Nrc Should Evaluate Possible Effects of Const on Listed Endangered Species ML20005B3311981-05-29029 May 1981 Informs That 810529 Ltr Forwarding Constituent 810320 Comments on Proposed Rule 10CFR2 Allowing Interim Licensing of Nuclear Reactors Before Safety Procedure Completion Has Been Sent to NRC ML19350E2901981-05-29029 May 1981 Ack Receipt of Constituent Ltr.Subj of Ltr Does Not Fall within DOE Purview & Will Be Forwarded to NRC ML19347F4221981-05-14014 May 1981 Advises That Proposed Action Re Revision 1 to Environ Rept Does Not Affect Ongoing or Planned Water & Power Projects ML19350E3031981-03-20020 March 1981 Requests Congressional Assistance to Require NRC to Expedite Licensing of Nuclear Power Plants.Facility Fuel Load Delays Discussed.Aif Ltr Dtd 810217 Forwarded ML19270G1781979-04-27027 April 1979 Supports Nationwide Halt to Nuclear Plant Const.Cites Wolf Creek Controversy as Example ML20027A4981978-11-30030 November 1978 Presents Results of Review of Low Strength Values for Facility Base Mat 90-day Concrete Cylinders.Base Mat Concrete Meets Spec Requirements & All Matls Used in Mix Are Acceptable ML20027A5001978-04-19019 April 1978 Forwards Dh Campbell & Lm Meyer Repts W/Results of Petrographic Examination,Compressive Strengths & Chem Analysis of Concrete Cylinders & Other Samples.Basemat Concrete Probably Exceeds 5000 Psi Strength Requirement 1997-05-20
[Table view] Category:EXTERNAL LETTERS ROUTED TO NRC
MONTHYEARML20072P0161983-07-13013 July 1983 Informs That No Changes to Emergency Plan Adopted Since Nov 1982 Rev,In Response to .Certificate of Svc Encl ML20076L6011983-07-11011 July 1983 Discusses Status of 830406 Proposed Stipulation of Contentions.No Agreement Reached Amongst Counsel at 830427 Conference Call.Fema Cannot Commit Resources to Preparing Testimony for 830830 Prefiling ML20076L5781983-07-11011 July 1983 Discusses Status of 830406 Proposed Stipulation of Contentions.No Agreement Reached Amongst Counsel at 830427 Conference Call.Fema Cannot Commit Resources to Preparing Testimony for 830830 Prefiling ML20083P3761983-01-13013 January 1983 Advises of Establishment of Task Force to Oversee Completion of Bm,Ef & Eg Sys,Preparation & Completion of Associated Quality Documentation & Review of Documentation.Task Force Will Commence on 830120 & Be Chartered for 30 Days ML20010J5791981-09-29029 September 1981 Forwards Applicant Further Response to Financial Qualifications Discovery Requests of Intervenor Kansans for Sensible Energy.Related Correspondence ML20010D1901981-08-17017 August 1981 Ack Receipt of 810813 Ltr Requesting Rescheduling of Osann Deposition.Lists Available Dates for Rescheduling.Related Correspondence ML20005B3311981-05-29029 May 1981 Informs That 810529 Ltr Forwarding Constituent 810320 Comments on Proposed Rule 10CFR2 Allowing Interim Licensing of Nuclear Reactors Before Safety Procedure Completion Has Been Sent to NRC ML19350E2901981-05-29029 May 1981 Ack Receipt of Constituent Ltr.Subj of Ltr Does Not Fall within DOE Purview & Will Be Forwarded to NRC ML19352A9501981-05-29029 May 1981 Comments on Revision 1 to Environ Rept for Facility,Per 810506 Request.Lists Species Present in Proposed Project Area.Nrc Should Evaluate Possible Effects of Const on Listed Endangered Species ML19347F4221981-05-14014 May 1981 Advises That Proposed Action Re Revision 1 to Environ Rept Does Not Affect Ongoing or Planned Water & Power Projects ML19350E3031981-03-20020 March 1981 Requests Congressional Assistance to Require NRC to Expedite Licensing of Nuclear Power Plants.Facility Fuel Load Delays Discussed.Aif Ltr Dtd 810217 Forwarded ML19270G1781979-04-27027 April 1979 Supports Nationwide Halt to Nuclear Plant Const.Cites Wolf Creek Controversy as Example ML20027A4981978-11-30030 November 1978 Presents Results of Review of Low Strength Values for Facility Base Mat 90-day Concrete Cylinders.Base Mat Concrete Meets Spec Requirements & All Matls Used in Mix Are Acceptable ML20027A5001978-04-19019 April 1978 Forwards Dh Campbell & Lm Meyer Repts W/Results of Petrographic Examination,Compressive Strengths & Chem Analysis of Concrete Cylinders & Other Samples.Basemat Concrete Probably Exceeds 5000 Psi Strength Requirement 1983-07-13
[Table view] |
Text
. - ._
,e . ' . $ . - ,.' 7. ' * * * " . ** M I hu d - J w.s w._.s:!,.vw Mr. Phillips: .
,, sw>J sJ J v 4. C/ ",N, ,i b.o w.,% roattso cte.itur anoci4nou O This letter and report were trans6itte by telecopier to you on 4/20/78 and te Mr.. Bernie Meyers at BechtelPower Corp on 4/20/78. Copy is also being r. nile @
. April 19, 1978 to Mr. Meyers. .
. 4/24/78 ,
J. J. Shideler Mr. Chris L. Phillips Project Civil Enginecr' Daniel International Corporation P.O. Box 146 Strawn, Kansas 6G839 -
Re: Reactor Basement Concrete D wo2f Creek Generating Station .
Mr. Phillips: . .
Campbell and L. M. Meyer,giving Attached are reports by D. H.
results of petrographic examination, compressive strengths and chemical analysis of concrcte. cylinders and other samples -
covered by your Purchace. Order 7158-NS-00417 dated 3/27/74i.
- Thesei reports will confirm information diccessed with you at our meeting on April 6 and in subsequent telephone conversatit I beliebe the reports are complete and self-explanatory, but ylease consider them.tontative at thic time. .
It is our opinion that the concrete in the "basemat', as repr sented by the comples tested, is of high quality and most lik
~
exceeds the 5000 psi stren'gth requirement of the specificatic It would appear to us that the disparity betwe.:n the 90--day strength data for the "basemat" and the more recent comparati sers.es with PCA may have been due to improved maintenance of '
the testing equipment, and tecting proced'uies by Daniel.
Sincercly yours, - ,*
n /0
'h eler, Director
, J.
i Administrative & Technical Services .
I 1g .
4 I
- Cd O407 Copy to - , .,
E E. Kunre
, e E. Hognestad . .- , , ,,, , ,, ,
~
I L. M. Meyer '
D. E. Campbell 78121102 19 .
- l. April 19, 1978 Subicer: Wolf Creek Generating Station *
(Daniel International Corp.) ,
This report concerns petrographic examination, air content, and compressive-s trength tests.
Eleven compression-tested 6x12" concrete cylinders, and.sar.ples of coarse and fine aggregates, cement, and admixtures were received (late March) from Mr. Chris L. Phillips of Daniel International for study relating to reported loss of strength-at 90 days. The samples represent materials reportedly used in the Wolf Creek Reactor Basemat. In addition, 20 previously
. untested Gx12" cylinders and 32 remnants of broken (compression =
fr tested) cylinders were received,on April 13, 1978, for further testing Pctrographic examination and' air content, determinations were performed on the following cylinders: ,
cylinder No. ~90 Day comeressive st/eneth (psi, Danici cata)
.' 6503 4190 6444 , 4640 ,
6784 4780
. . 6850 6640 Conclusions Microscopic analysis reveal's no evidence which could conceif-ably cause 'significant strength reduction at 90 days. Cylinder strength may have been affected slightly by minor differences in air content und water-ccment ratio.
The concrete appears to be of high quality, with strengths apparently well above the 5000 psi specification at 90 days.
PCA determined compressive strengths on 2x2" cubes cut from previously tested cylinders representing the December 12-13 pour. The average comprescive strength of these cubes was 5970 psi with a minimum value of 5060. These values are 80 percent of the actual test values to correct for the differen=e between cylinder and cube strengths. In a series to' determine the comparability of the Daniel testing procedures with those of PCA, twenty companion cylinders' cast about January 14 (from '
the power block) were tested both by Daniel and PCA. There is remarkable aggreement between the two sets of test data. cyline der fracture patterns developed on PCA-tested and Daniel-tested cylinders are broadly similar, being a ccabination of diagonal
_1_ ,
a ge .w ur ei'---'
knc-Conical forms. It was noted that many of the untested 6x12*
cylinders displayed rounded bottom-cnds, reflecting a non-planar cold curfact, and perhaps explaining the ccourrence of diago-nelly formed becaks.
Methods Each cylinder in the above list was sawn transversely at a dis-
. tance of approximately 2 inches from the capped cnd. The capped end-pieces were then poliched for determination of air content by Lin.mv Tescovea ( LcT,5 C-457). .% amall coro (3/4 inoh diam-cuer) was taken from each capped end-piece for thin sectioning.
A thin section is a concrete clice mounted on a glass ' microscope slide with epoxy cement and reduced to a thicknecc of 25 microns for microscopic eramination with plane polarized light. Thin sections were numerically coded so that observations would not be bisced by strength data.
The rcmaining portion of the cylinder was crushed for cement content determination. .
Description and Discussion cylinder _Mo. 6784 - Fracture surface produced by compression test passes through aggregates. Fracture surfaces "orm sub-conical pattern with transverse crcck'at mid-cylinder. Paste is hard and firmly binds the aggregates. Aggregaten appea'r evenly graded, properly proportioned, and unif ormly distributed.
coarse aggregatc . is crushed l'imestone described an fossili-ferous, pyritic, medium-grained, microcrystalline, or combinn-ticas of thecc types. Aggregate top-sire ic 3/4 inch.
Fine aggregate co: wists of a natural sand containing quartz, microcline feldspar , and metaquar tzite. Chert is scarce.
Aggregate (limestone) dust occurs in truce amounts.
The' aggregates are normally' considered non-renetive in low-alkali cements and are judged to be of low porosity and per-meability and moderate durability. No reactioh products were observed.
l The paste centtins portland coment ydration products (calcium silicate hydrate and calcium hydroxide, primarily) and unhy-drated portland cement grains (UPC's), the latter ranking 5 on 0-10.e. UPQ's consist anuncance mainiv of a d relati dark ne ahnn.
ferrite andanr.*ll.snn ye ow-amber la of 5011 Ahe relative of f errite suggests an iron-rich cement.- Residual alite crys-tals show prominent rims. calcium hydroxide crystals occur as small irregular massen in the paste and adjacent to aggregates; y blade-form crystals are common. The abundance of calcium hydroxide and UPC'c suggest a moderate water-cement ratio.
Minor concentration of UPC's adjacent to coar:0 aggregates sug-gests the possibility of some inadecuate mixing. Most of the t
4
. =
\
l
. - ,. .. .-- _ . , , . . _ . ,, . . - _ . , , . . . . . , , _ m_,_ , _ _ , . . . - . - , _
voide contain tracer. of calcium silicate hydente or attringite
^
occurring as very thin films only partially concing the void surfaces. .
Cylinder No. ,6444 - Fracture surfaces and aggregates as pre ~
viously described. F racture surfaces f orm half-conical pattera' with transverse fracture at mid-cylinder. Paste characteris-ties are apparently no different from Cylinder 7 No. G784, except UFC's are slightly more abundant, ranking 5 . In addition,
=**rinn i te needles nnnnr in trage agou,n ts in a few voids.
Cglinder No. 6S50 - Compression test Fracture fracture surfaces surf acccand oriented aggregater as previously described.
mainly along cylinder length. 6784, but UFC abundance isgen-Paste characteristics are erolly similar to.C higher, ranking G" ylinder No. scale, suggesting a relatively on the 0-10 low wa ter-cement ratio. Relative air content is lowest in., this
. sa'mple ,
r Cylinder Ko. G503 - Tracture surfaces and cggregates Tracture as pre'-
pattern show viously described for Cylinder No. 6764. Paste characteris-prominent. orientation along cylinder length.
tics are also similar. .
Ecsults of Linear Traverse Tests (ASTM C-4571 specific spacing Surface Factor Absorpt
, Unit Wt.
cv1. yo. ecf % Ai'r vioids/in. in.2 jth,3 in, t 7.7 640 .007 5.4 6503 145.5 4.8 600 .007 S . */
6444 146.3 5.8 8.7 145.8 5.6 8.9 639 .007 5.0 6784 4.3 515 .011 5.8 G850 147.1 3.3 These date indiente a relatively low air content and water-
~
~
rati6 for the reported high ctrength cylinder, and ray account, in part, for some of the differences in strength cement between the cylinders.
Comoressive Strencth Tests-Compressive strength' data for the 2x2" cubec' cut from selected broken cylinders, received April 13, 1978, are given in Table I.
Note .that these have been corrected by a value of 80 percent to indica te the difference between cylinder and cube strenghts.
The compressive strength cf the cvlinders tested by Daniel,-
from which the cubes were cut, are strength of also . reported the cubes in the table.
(corrected by the i
The averace compressivewas 5970 psi as compared to 5370 psi on the cy'lin-20 percent) l ders. The average compressive strengths of the 20 cylinders tested by Daniel and PCA are 6470 and 6220 psi, respectively, which indicates good agreement. .
_3_ . . ; .
{
... o .
, . Attachment to CLY.-:
. ,,p e t i .19 , 1978 PC92 M. cf G Subicct:
Wolf Creek Generating Station
( c a . 1 w :. rut _arnationc2. cur.p. ) ,
Attached is our chemical analysis report. covering the results of tests for the cement content, approximate water-cement rctio and admixture content of hardened concrete. Also included are the results of selected tests performed on the two samplos of Ash Grove Typc II cement we received on April 13, 1979. This work was conducted relative to reports that concrete placed in the Reacter Basemat was low in compressive , strength at 90 days.
Conclusions
't
~
- 1. The ecment contents of all the samples selected for analysis were cc=uarc0ic' to tha t noecified in the concrete mi desier (564 lbs/yd'). The c ooroxima te wa te r-cep.en_t _ ra_ tics deter-nined for the same samples were.below the level incicated
.in the mix desian.
- 2. The chemical admixtures specified in the mix design appearec to be Dresent in tne concrete samples we tested at the
' appropFinte_eosao* 1evels. No indication of improper adv.ix-ture rormulation (Poz=o tith, 3 0 0-N and M3VR). was observed.
- 3. To date no significant . differences between the two samples of Ash Grove Type II cement (C-UT-16 and C-UT-17) have baen detected.
i c[,7% M L. M. Meyer, Manager ff ,
Technical Services section ,
0 9
1
. a.
. t ..
. . r.
~; ~ ~- - ,- * *
. . . . . . s Chemical _Analvcis Reuort A. Datermination of Cement Content and Approximate Wate:-Cement Ratio of Hardened Concrete The cement contents and approximate water-ccment ratios of the four tested cylinders chosen by Dr. Campbell for petrographic annlyses and moucurements of air content also were determined. .
The results are presented in the attached analytical report by '
its. D. L. Glochowsky. .
The data shows the cement contents of Cylinder Nos. 6503, 6.784 and 6850 were comparable to that specified in the concrete mir design _(5G4 lbs/yd#). Although ne cement content of cylin-der No. 6444 was slightly below the specified amount, the value obtalnco was wir.181st L.lse L a n g e o r c 7. p e t 4 t.e sat. a 1 m et r o s: norman;r anticipated for this test ( 30 lbs/yd-') . The approximate water-ccment ratio of all four' cylinders, assuming an overall
/ aggregate absorption of 1. 5%, was below the level indicated in the mix' design (w/c = ~0.49). ,
E. Analysis of Chemical Admixtures, ,
The samp1'es of water-reducing admixture, identified as Master Buildere pozcolith 300-N (ASTM C-494, Type A), and air-
<_ n t. . . i n i n s none. La nt.ifi.ca me 14 = = i =
- un i l ,% n :.mVR (ASTM C-260), were subjected to certain chemien1 and physical tests for purposes of characteri=ntion.
The results of our tests showed both . admixtures were similar in physical and chemical properties to other samolesOne similarly of the identifica and characterized previously at PCA.
major components of Pozzolith 300-N, lignin sul.fonnte, appeared to have been. sulfonated to a somewhat lesser ertent than had been found in the earlier samples, but we do not know what affect, if any, this might hsve on admixture performance at -
j this time. ,
C. Analysis of Hardened Concrete for Presence of Che=ical Admixtures Four concrete cylinders were selected for che:ical analysis en the basis of their reported 90 day compressive strength values.
- These cylinderc were as follows: No. 6857 (6420 psi) , No. 6432
- (5020 psi), No. 6414 (5110 psi) and No. 6623 (2870 psi?) . The-
. latter two cylinders were combined into one sample because of The th'ree concre te samples then vare -
insufficient unmple sice. ?
annly=ed for the presenc.e of a water-reducing admixture, -
po==olith 300-M and an air-entraining agent.
~
i " .:. r ' The results of our chemical analyses showed a water-reducing ed .ixture similar in co=pesition to ?c==olith 300-N was presr.:,
l ' -; '. , . .
l l
l- - _- __ . _ __ . _ _ _ _ _ _ . _ . _
' ~ '
'in nll three samples of ' concrete at a level of lese than 3 f1'.or./100 lbs of cement (app roxima te' threshold level of detec-J tabili ty) . No significant difference in admixture level was observed between the three samples.
. Analyciz of the concrete semples for the presence of th:r air-entraining admixture was more difficult due to some minor cen- '
tamination by " oxidized" oils (possibly materials from lubri-cating agents or materials present in sulfur cepping compound) .
The r. noun t of these "exdined" oils was lens than 0.005% by weight of concreto. The air-en. training agent (*nMr1 hav.* haen masked by these " oxidized" cils, but it appears there was not -
an excess of air-entraining agent present in the concrete.
D. Analysis of. Portland Cement -
Two camples of portland ecment, reported to ba Ash Grove Type
. II (Chanute, Kansas plant) and identified as C-UT-lG (Bin f36,
.c 11/21/77) and C-UT-17 (Bin 136, 12/12/77) , were subjected to select.ed chemical and physien1 tests to determine if signifi-cant dif ferences existed between them. The chemical tests include.d X-ray diffraction analyses (XRD) and determinaticas of 50 content and loss on ignition (LOI); the physical tests indluded specific surface (Blaine, air permeability) and parti-
- cle size distribution (Sedigraph 5000). ,
The results showed there were no significant dif farences between' cement samples based upon the test results obtained to date. ' Soth XED scans and sedigraph particle size distributic .
curves were vir tut.lly iden t.ica.L. Tne other valisen uid.m in=d won == ro.1.w==
L . O . 't '.
SO 3 Contant Specific Surf' ace Sample _ (% by vt. ) . (% by wt.) _
(Bla ine , em /cm) 3460 C-UT-16 . 1.07 2,08 C-UT-17 0.96 2.09 3465 9
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,mm.,_ . . _ , . ~ . . . ~ . . . , . _ . _ . , . _ - , . , _ _ , . _ . . _ _ _ . _ _ . _ . , _ _ , . . . t _ .. . - - . . _ _ _ _ _ _ _ _ _ _
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CompletionD$tus
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Project No.: CT-0407 -
4/5/7h .
Tcst. He D.cd -
Sulfur Trioxide Method j'.. ~,,-
.n . ' i.
Sneple Identification: . 6444 6503 s784 68!
Cemen t cc: stent, lb s . /yd .'.3 : .540 S70- 560 ,,575 Unit weight, 1bs./ft.3:
S.S.D. -
, . 145.4 145.5. 145.8 i47.
Oven Dry (G 105 'C) .
. 137.6 138,0 138.9 ,
129, Free water z.bscrption, V,: 5.7 5.4 50 5.
(Oven dry weigh t basis) .
- a. .
' Combined water centent, %: 2.41 2.61 2.59 2.
(Oven dry weight basic) . .
I Total water', lbs./yd. : 300 '. 300 285 310 (Frea wat' r)~ater w t goinbined . .
c Approximate W/C: 0.47' O.45 -
0.42 0.
(Corrected for aggregate ' " ~
. absorption) ., .
Total dry aggregate, lbs./yd.": 30,S5 3060 3090, 3075 Approximate C.A./F.A.: .Not Determined Air void content - ,
"' ASTM C457: -
'.sse' report by D.
H.. Cdmpbell
~ . Estimated- .
Comments : ASTM C-ll4 Diodified) ..-..-
l "
l Sabule % SO, (by vt.)
! Cod m ;c: .
46444 . . 0.33 .
45503 . 0.35
' 96784
. 0.34 16850 ,
0.35 Aggregates . Nogligible -
(Fine and C% arse) . . .
Cement 50 < ,281 as determined by Leco Induction Turnace (tote i
culfur as SO 2). *
.s t f d M
', D. L. GLGCHCWE n' Assistant F. eses.rch Cher.is:
Technical Services St tien l