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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20153E4221988-08-29029 August 1988 Forwards Order Revoking CPPR-172 & CPPR-173 & NRC Staff Evaluation of Site Stabilization Plan Per from Util ML20153E2331988-08-26026 August 1988 Forwards Status of Site Stabilization Activities,Per R Auluck Request.Tva Has Completed All Major Site Stabilization Activities at Plant W/Only Minor Maint Activities Remaining ML20215C5661986-10-0606 October 1986 Further Response to FOIA Request for All Records Concerning Allegations That Pullman Power Products Employees Intimidated QC Inspectors.Forwards App F Documents.App G & H Documents Withheld (Ref FOIA Exemptions 7 & 5) ML20133N7321985-10-24024 October 1985 Forwards Proposed Cancellation Plans for Plants Officially Canceled on 840829.Requests Withdrawal of CPPR-150,CPPR-152, CPPR-172 & CPPR-173.W/two Oversize Drawings ML20128Q2441985-05-17017 May 1985 Further Response to FOIA Request for Six Categories of Records Re Nuclear Waste Policy Act.App B Documents Available in Pdr.Forwards App C Documents ML18029A3981985-02-27027 February 1985 Responds to RM Diggs 850117 & 0211 Ltrs Re Determination of Fees for Const Extension Requests.Util Supports NRC Determination & Will Submit Fees ML20096F8731984-09-0505 September 1984 Forwards Motion to Terminate Appellate Jurisdiction.W/O Encl.Related Correspondence ML20077G6661983-07-27027 July 1983 Part 21 Rept Re Circuit Breakers Mfg Between Nov 1981 & Feb 1982.Breakers Should Be Inspected for Broken Puffer Linkage Studs.Stud Identified as Part Number 192247A.List of Circuit Breakers for Nuclear Plants Encl ML20023C3361983-05-12012 May 1983 Forwards Details of Deferral Plans for Yellow Creek Nuclear Plant. ML20073S5851983-02-24024 February 1983 FOIA Request for All Documents Re Decision to Terminate Const of Facility ML20071B9741983-02-24024 February 1983 Reiterates 830121 Request for CP Extension Until 870901 to Permit Final Decision Re Future of Nuclear Units Based on Load Growth/Demand.Deferral Plan Details to Be Submitted by 830506 ML20069D8691982-09-20020 September 1982 Forwards Black Fox Station Soil Stabilization & Erosion Control Program, Per ASLB 820618 Memorandum & Order.Plan Addresses Concerns Raised in NRC 820602 Submittal ML20055C0611982-08-0606 August 1982 Forwards Info Re QA for Deferred Plants,In Response to NRC .Possible Cancellation of Some Units Will Be Discussed at Future Meeting of TVA Board of Directors ML20054K8881982-06-29029 June 1982 Forwards Yellow Creek Nuclear Plant Socioeconomic Monitoring & Mitigation Rept YCNP-SMR-7, Jan-June 1981 ML20054K1531982-06-23023 June 1982 Informs That Final Deficiency Repts for Listed Nonconformances Will Not Be Submitted Until Final Decision Is Made Re Const of Projects ML20052F0901982-05-0404 May 1982 Informs That Addl Action Will Be Required in Order to Fully Comply W/Asme Code Requirements for Radiography of safe-end Welds.Discrepancy Will Be Resolved by re-radiographing Affected Welds ML20069B9611982-03-0202 March 1982 Informs of Changes Re Slowdown in Const Activities.Busing of Employees No Longer Justifiable Due to Lower Employment Levels & Const Schedule Changes.Waterfowl Wetlands Wildlife Monitoring Results Show Const Has Not Affected Wildlife ML20040H4141982-02-10010 February 1982 Notifies That Facilities Ref CENPD-210,Revision 3 Per 820202 Request.Info Based on Review of PSARs ML20039B5581981-12-17017 December 1981 Forwards Yellow Creek Nuclear Plant Socioeconomic Monitoring & Mitigation Rept, Per Fes Section 4.5.2.5 ML20039A2811981-12-0404 December 1981 Notifies That Environ Const Noise Monitoring Procedures Will Be Revised at Hartsville & Yellow Creek & Terminated at Phipps Bend.Changes Caused by Slowdown & Cessation of Const. Summary of Const Noise Monitoring Program History Encl ML20009D9311981-07-0808 July 1981 Forwards Response to IE Bulletin 81-03, Flow Blockage of Cooling Water to Safety Sys Components by Corbicula Sp (Asiatic Clam) & Mytilus Sp (Mussel). ML20004B4021981-05-21021 May 1981 Responds to Violations Noted in IE Insp Repts 50-566/81-02 & 50-567/81-02 Re Failure to Establish Adequate Measures to Control Welding & Nondestructive Exam.Rept Revises 810330 Rept to Reflect Bend Sample Fissure Evaluation Results ML19350D9121981-05-20020 May 1981 Forwards Yellow Creek Nuclear Plant Socioeconomic Monitoring & Mitigation Rept, Jan-June 1981 ML19350C7811981-03-30030 March 1981 Responds to NRC 810304 Ltr Re Violations Noted in IE Insp Repts 50-566/81-02 & 50-567/81-02.Corrective Actions: Certification of Welders Previously Certified Were Revoked & Are Tracking Potentially Unacceptable Welds ML19341D3021981-02-26026 February 1981 Forwards Revised Description of Onsite Meteorological Measurements Program.Revision Will Be Included in OL Application ML20003A0731981-01-26026 January 1981 Advises of Work W/Three Counties in Ms to Upgrade Emergency Response Capabilities.Requests That NRC Ltr Be Sent to Local Officials Explaining Use of Mitigation Funds for Emergency Response ML19341A0831980-12-23023 December 1980 Responds to NRC 801125 Ltr Re Violations Noted in IE Insp Repts 50-566/80-17 & 50-567/80-17.Corrective Actions:Part Ii,Section 5.1 of Div of Nuclear Power Operational QA Manual Rewritten ML19345D5871980-12-0505 December 1980 Forwards Socioeconomic Monitoring & Mitigation Rept, Semiannual Rept for Jul-Dec.Rept Prepared for Fes ML19338G6101980-10-24024 October 1980 Requests Expedited Review of Newport News Industrial Corp Draft Topical Rept Re Vol Reduction Sys.Util Plans to Utilize Sys at Units 1 & 2 ML19338G2151980-10-21021 October 1980 Forwards Response to NRC 800926 Lr Re Violation Noted in IE Insp Repts 50-566/80-14 & 50-567/80-14.Corrective Actions: Review of Concrete Test Dispositioned in Qcir 51057 Showed Design Strength Should Be Realized at Later than Design Age ML19338G4281980-10-0303 October 1980 Submits Second Revised Response to Infraction Noted in IE Insp Repts 50-566/80-03 & 50-567/80-03.Corrective Actions: Radiographs Made Before 800207 re-examined for Deficiencies. Film Processing & Shim Placement Guidelines Established ML19338E1241980-08-18018 August 1980 Responds to NRC 800228 Ltr Re Violations Noted in IE Insp Repts 50-566/80-03 & 50-567/80-03.Corrective Actions: Radiographs Before 800207 re-examined & Radiographers Instructed in Requirements of Shim Placement ML19331D1441980-08-18018 August 1980 Forwards Revised Final Response to IE Insp Repts 50-566/ 80-03 & 50-567/80-03.Response Reflects Util Decision to Radiograph Addl Seven Welds.Rept Will Be Submitted by 801027 Re Film Darkening Problem,Per NRC Request ML19320C0241980-07-11011 July 1980 Forwards Revised Final Deficiency Rept Re Placement of Earthfill in Essential Raw Cooling Water Spray Pond ML19320C5471980-07-10010 July 1980 Forwards Final Deficiency Rept Re Const QA Audit ML19320C5371980-07-10010 July 1980 Forwards Final Deficiency Rept Re Placement of Earthfill in ERCW Spray Pond ML19320C2251980-07-0909 July 1980 Forwards Second Interim Deficiency Rept Re Const QA Audit. Next Rept Will Be Submitted by 800820.W/o Encl ML19318A3751980-06-13013 June 1980 Forwards Final Deficiency Rept Re Defective Concrete Pour in Auxiliary Bldg ML19310A4311980-06-10010 June 1980 Responds to IE Insp Repts 50-566/80-03 & 50-567/80-03 Re Failure to Establish Adequate Measures to Control Radiography.Radiography of Welds Scheduled for Completion by 800701 ML19320D6471980-06-0303 June 1980 Forwards Do Jourdan 800328 Ltr for Consideration ML19316B0711980-05-27027 May 1980 Forwards First Interim Deficiency Rept Re Const QA Audit YC-C-80-05.Next Rept Will Be Submitted by 800710 ML19312E4851980-05-27027 May 1980 Forwards First Interim Deficiency Rept Re Placement & Compaction of Concrete Pour A2-D1 ML19323F1361980-05-21021 May 1980 Forwards First Interim Deficiency Rept Re Const QA Audit ML19316A7591980-05-19019 May 1980 Requests NRC Cooperation in Expediting Approval of York Model 299 Type 3G Moisture Separator Discussed in Topical Rept York 80-67459,submitted 800331.Separators Required by Util by 800822 Due to Const Delays ML19323G6001980-05-19019 May 1980 Advises That Ah Gutterman Will No Longer Appear in Proceedings on Behalf of Util ML19323J0771980-05-19019 May 1980 Responds to NRC 800424 Ltr Re Violations Noted in IE Insp Repts 50-566/80-07 & 50-567/80-07.Corrective Actions:Purge Air Blower Filters & Solenoid Valve Cleaned ML19309H4951980-05-0505 May 1980 Forwards Second Interim Deficiency Rept Re Incorrect Use of Inertia Resulting in shear-related,cross-sectional Property Calculations for Control Bldg ML19309G4161980-04-28028 April 1980 Forwards Revised Response to Violation Noted in IE Insp Repts 50-566/80-03 & 50-567/80-03 Re Failure to Establish & Control Radiography.Film Interpreters & Radiographers Instructed in Shim Placement ML19312E3331980-04-28028 April 1980 Responds to NRC 800228 Ltr Re Violations Noted in IE Insp Repts 50-566/80-03 & 50-567/80-03.Corrective actions:800324 & 0421 Submittals revised.Re-evaluation of Radiographs Showed Only Seven Welds Will Require Reradiographing ML19344D6381980-04-21021 April 1980 Forwards First Interim Deficiency Rept Re Improper Documentation & Utilization of Computer Program Inertia. Next Rept Will Be Submitted by 800801 1988-08-29
[Table view] Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20148N3841980-12-11011 December 1980 Forwards Geologic Rept Re Suggested Graben in Gravelly Springs,Al Area.Distance to Facilities Precludes Significance of Structures.Related Documentation Encl ML20197E5561980-02-0707 February 1980 Submits Reasonable Values for CP Environ Review Charges, Based on NRC Computer Printouts of Charges,Examination of Lab Monthly Repts & Info from Anl ML20150D2641978-11-14014 November 1978 Forwards Recent NRC Memos Re Problems Associated W/Pipe Support Base Plate Design Which Apply to Subj Facil.W/Encl ANO:7811020332,7811020343 & 7811020336 ML20148M8171978-11-0606 November 1978 Repts on Analysis Which Indicates post-LOCA Hydrogen Production Due to Corrosion of Matl Inside Primary Containment May Not Have Been Adequately Considered in Eval of Combustible Gas Control Sys ML20148M8261978-10-17017 October 1978 Repts on post-LOCA Hydrogen Production from Matl Inside Containment.Finds Effects Eval Re post-LOCA Generation of H in Both BWR & PWR Pressure Suppression Type Containments Do Not Lead to Significant New Safety Concerns.W/Encl Ref ML20147D6381978-09-29029 September 1978 During Semiscale Experiments Conducted to Model Aspects of ECCS Performance,One Test Run Showed Behavior Unanticipated by ECCS Models.Believed That Results Were Atypical.Matter Is Under Further Study.Bds Will Be Informed of Addl Info ML20128Q4821977-04-22022 April 1977 Forwards Review Summary for Use in Des.Economic Costs of Coal & Nuclear Power Generation Alternatives Addressed 1980-02-07
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20148N3841980-12-11011 December 1980 Forwards Geologic Rept Re Suggested Graben in Gravelly Springs,Al Area.Distance to Facilities Precludes Significance of Structures.Related Documentation Encl ML20197E5561980-02-0707 February 1980 Submits Reasonable Values for CP Environ Review Charges, Based on NRC Computer Printouts of Charges,Examination of Lab Monthly Repts & Info from Anl ML20150D2641978-11-14014 November 1978 Forwards Recent NRC Memos Re Problems Associated W/Pipe Support Base Plate Design Which Apply to Subj Facil.W/Encl ANO:7811020332,7811020343 & 7811020336 ML20148M8171978-11-0606 November 1978 Repts on Analysis Which Indicates post-LOCA Hydrogen Production Due to Corrosion of Matl Inside Primary Containment May Not Have Been Adequately Considered in Eval of Combustible Gas Control Sys ML20148M8261978-10-17017 October 1978 Repts on post-LOCA Hydrogen Production from Matl Inside Containment.Finds Effects Eval Re post-LOCA Generation of H in Both BWR & PWR Pressure Suppression Type Containments Do Not Lead to Significant New Safety Concerns.W/Encl Ref ML20147D6381978-09-29029 September 1978 During Semiscale Experiments Conducted to Model Aspects of ECCS Performance,One Test Run Showed Behavior Unanticipated by ECCS Models.Believed That Results Were Atypical.Matter Is Under Further Study.Bds Will Be Informed of Addl Info ML20128Q4821977-04-22022 April 1977 Forwards Review Summary for Use in Des.Economic Costs of Coal & Nuclear Power Generation Alternatives Addressed 1980-02-07
[Table view] Category:NRC TO ASLP
MONTHYEARML20148M8171978-11-0606 November 1978 Repts on Analysis Which Indicates post-LOCA Hydrogen Production Due to Corrosion of Matl Inside Primary Containment May Not Have Been Adequately Considered in Eval of Combustible Gas Control Sys ML20147D6381978-09-29029 September 1978 During Semiscale Experiments Conducted to Model Aspects of ECCS Performance,One Test Run Showed Behavior Unanticipated by ECCS Models.Believed That Results Were Atypical.Matter Is Under Further Study.Bds Will Be Informed of Addl Info 1978-09-29
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. UNITED STATES g
~\j NUCLEAR REGULATORY COMMISslON WASHINGTON, D. C. 20556 September 29, 1978 k***** NRC PUBLIC DOCUMENT ROOM Ivan W. Smith, Esq., Chairman Dr. Oscar H. Paris Atomic Safety and Licensing Board Atomic Safety and oard
~ U.S. Nuclear Regulatory Commission U.S. Nuclear Re ion Washington, D. C. 20555 Washington, D. 0555 Mr. Lester Kornblith f.h, f Atomic Safety and Licensing Board U.S. Nuclear Regulatory Comission ( q, g-r$
Washington, D. C. 20555' "
fas#/
&/ 6 In the Matter of * "
TENNESSEE VALLEY AUTHORITY co (Yellow Creek Nuclear Plant, Units 1 & 2)
Docket Nos. 50-566 & 50-567 Gentlemen:
Recently during the course of certain'semiscale experiments, conducted '
at Idaho Nuclear Engineering Laboratory to model various aspects of ECCS performance, one test run exhibited behavior unanticipated by current' ECCS performance models.
Semiscale experiment Mod-3, S-A7-6 was run on September 12, 1978. It was intended to model' an integral blowdown-refill-reflood scenario for a double-ended cold-leg break. Some of the detailed results were un-anticipated. For example, the heated core simulator was predicted by the RELAP code to quench at 110 seconds. Instead, it dried out again ,
and went through several cycles of dryout and rewet (see enclosed Figure 1). Other portions of the cladding temperature profile also y
showed discrepancies in that test temperatures in some instances were somewhat above those predicted and in some instances were somewhat below
! those predicted (see Figure 2 and 3). During_ the test, the downcomer voided several times in the 100 to 400 seconds period of time. This
/; also was not predicted by RELAP (Figure 4 shows one such void). During the periods of downcomer voiding there was also negative (downward) flow from the heater to the lower plenum.
As indicated above, nearly complete downcomer voiding occurred after ;
downcomer fill . This is not predicted by the ECCS evaluation models 1 (for PWR's) used in connection with 10 CFR 550.46 and Appendix K !
applications. Also, typical Appendix K calculations do not show successive i dryout and rewets over the extended reflood cycle. A quick-look -
report on this experiment will be published by INEL about October 1,1978.
3 % %4-h n5't w-,e-- ,
2 The present judgment of INEL is that these unanticipated results are atypical and have been produced by certain characteristics of the experiment which are not typical of reactor systems, particularly the stored heat in the downcomer pipe and'in the one-dimensional arrangement of the downcomer.
These matters are under further study by the NRC Staff and INEL. When further information or conclusions concerning this matter become available, we will inform the Boards.
Sincerely, Edward G. Ketchen
)
Counsel for NRC Staff Enclosure as Stated cc (w/ encl .):
I ra L . Mye rs , M. D.
Atomic Safety and Licensing Board Panel Atomic Safety and Licensing Appeal Panel Docketing and Service Section Herbert S. Sanger, Jr., Esq.
Honorable A. F. Summer Alton B. Cobb, M.D.
William B. Hubbard, Esq.
l l
r
Figure 1 -
COMPARISON OF ROD CLADDING TEMPERATURES AT CORE HIGH POWER ZONE WITH RELAP4 FOR TEST S-A7-6 4'
1200 , , , i iiiii;iiiiiiiiiiiiiiiiiii
n _
Y 9 u .
.1 t
t 1000 - -
k _ e _
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e ! 3 RELAP4(SRD7)
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400
-100 0 100 -200 300 400 500 . -
r . A n.- no,so . c...a
Figure 2 '
~
COMPARISON OF MEASURED AND CALCULATED CLADDING TEMPERAUTRE IN LOWER PART OF CORE FOR TEST S-A7-6 I
If I l l l l l l l 1000 - '
n Y
u -
, 900 -
L 3 '
r 800 - "
A < TH-C3-115 -
E
/
e TH-E2-109 F
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4-4 3-3 l +-RELAP4 h 600 -
1 500 -
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" ' ' ' ' ' ' ' ' "b'"i t * "ew 400 g ' ' '
,g , ,_A
---**~
-50 0 50 100 150 200 250 300 350 400 450 500 .
Twn. Af ter Rup t ure C=3 l
9
~.
COMPARISON OF MEASURED AND CALCULATED CLADDING TEMPERATURE -
IN UPPER PART OF CORE FOR TEST S-A7-6 '*
1050 .
gr , , , , , , , , ,
1000 TH-C2-277 950 -
n -
6 900 -
!= 850 -
j 800 -
f 7~ ~ ~ f -
1 750 -
TH-A3-291 _
E p' 700 -
(
3 600 -
+-R E L A P 4 ___
e 550 -
500 -
450 -
I I I 400 I I I I I I
-50 0 50 100 150 200 250 300 350 400 450 500 .
T.m. Avi. no so . c.2
vrgarn
, .. i CALCULATED COLLAPSED DOWNCOMER LIQUID LEVEL FOR TEST S-A7-6 ,, .,
I,
) i I I I I I I I I i I .,
' 91 . . . . . . . .
6 e
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'a li lf ' RELAP4 CALCULATION 5 -
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DATA
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-CALCULATION -
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0 l I I I I I I I I I I I I I 50 60 70 80 90 100 110 120 130 140 150 160 170 180 190 200 '
Tim. A e s.r nu,*ue. c.s
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