|
---|
Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217N5121999-10-25025 October 1999 Forwards NRC Operating Licensing Exam Rept 50-331/99-302(OL) (Including as-given Witten Exam) for Tests Administered During Week of 990920 ML20212J7691999-10-0101 October 1999 Notification of 991015 Meeting with Util in Rockville,Md to Discuss Licensee Submittal Schedule.Draft Agenda Encl ML20212F5461999-09-23023 September 1999 Notification of 991004 Meeting with Utils in Rockville,Md to Update Status of Nuclear Mgt Company & Provide Details of Member Licensees Impending License Transfer Applications & Operating Agreement ML20210A6141999-07-13013 July 1999 Forwards facility-submitted Outline & Initial Written Exam Submittal for Operator Licensing Exam Administered on 990525 ML20207H6651999-07-13013 July 1999 Forwards NRC Operator Licensing Exam Rept 50-331/99-301(OL) (Including Completed & Graded Tests) for Tests Administered on 990525 ML20206H5181999-05-0505 May 1999 Notification,For Docket 7200032,of 990521 Meeting with Util in Rockville,Md to Discuss Util Plan for General License to Store Spent Fuel at ISFSI at Duane Arnold Plant.Meeting Agenda Encl ML20195D8781998-11-12012 November 1998 Responds to TIA 98-008 Requesting Assistance in Establishing Generic Regulatory Position on Period of Time & Under What Circumstances Acceptable to Remove Rod Control from Service ML20154R3691998-10-19019 October 1998 Notification of 981029 Meeting with Listed Utils in Rockville,Md to Discuss Proposed Consortium of Utils ML20237D8641998-08-25025 August 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980706-10 ML20237D8421998-08-25025 August 1998 Forwards NRC Operator Licensing Exam Rept 50-331/98-301OL for Exam Administered During Wk of 980706 ML20236X3891998-08-0303 August 1998 Responds to Technical Assistance Request (AIT 96-0278) Re Entering Limiting Conditions for Operation at Duane Arnold Energy Ctr ML20195D8931998-06-18018 June 1998 Requests Assistance Re Technical Issue Limitations of Removing Normal Control Rod System Controls from Service on Operating Reactor (TIA 98-008) ML20237B9781998-04-15015 April 1998 Informs That on 980205-06,NRC Staff Attended Severe Accident Mgt Implementation Demonstration at Ies Utilities,Duane Arnold Energy Ctr in Cedar Rapids,Ia ML20199J6631998-01-29029 January 1998 Forwards Info Re Plant Responses to Staff Requests for Info on Section 3.3 of Plant Improved TS Submittal.Part of GE 24A5369,Rev 0,Class I, Supplemental Reload Licensing Rept for Plant Reload 14 Cycle 15, for Sept 1996 Encl ML20199A3061998-01-21021 January 1998 Notification of 980204 Meeting W/Util in Rockville,Md to Discuss Util Resolution to NRC Bulletin 96-003 ML20198M9751998-01-0909 January 1998 Requests Encl Info Documenting Conference Call Between NRC & Ies Utilities Re Duane Arnold Energy Center Responses to Staff Requests for Info on Section 3.6 of Improved TS Be Placed on the DAEC Docket ML20198A5161997-12-19019 December 1997 Summarizes 971217-18 Meeting W/Ies Utils,Inc to Address Responses Provided by Licensee Re RAIs on DAEC Improved Ts. Discussions Resulted in or Documented Closure of Most Rais. List of Attendees & Handouts Encl ML20198A5121997-12-19019 December 1997 Forwards Info Which Documents Series of Conference Calls & Fax Between NRC & Ies Utils,Inc Re DAEC Responses to Staff Requests for Info on Section 3.8 of DAEC Improved TS Submittal ML20203G3121997-12-11011 December 1997 Forwards Info Which Documents RAI Re Conversion from Current to Improved TSs at Plant.Subj Info Requested to Be Placed on Plant Docket ML20203C3061997-12-0505 December 1997 Forwards Info Documenting Telcon Between NRC Staff & Ies Utilities,Inc Re Conversion from Current to Improved TS at Daec.Requests Info Be Placed on Docket ML20203C4141997-12-0505 December 1997 Forwards Info Received from Ies Utilities,Inc Re Discussions About Conversion from Current to Improved TS at Daec. Requests That Info Be Placed on Docket ML20203B2491997-12-0303 December 1997 Forwards Info Supplied by Ies Utilities Inc.Info Provided Subsequent to Discussions About Conversion from Current to Improved TS at Duane Arnold Energy Center ML20199K9191997-11-24024 November 1997 Notification of 971217-18 Meeting W/Ies Utilities Inc in Rockville,Maryland to Discuss Responses to Requests for Info on Conversion of Duane Arnold Energy Ctr Current TS to Improved TSs ML20217K8031997-10-20020 October 1997 Notification of 971105 Meeting W/Util Re Responses to Requests for Info on Conversion of Plant Current TS to Improved TS ML20217E8451997-10-0101 October 1997 Forwards Info Provided by Ies Utilities Inc Re Staff Questions Concerning Discrepancies Between UFSAR & How Licensee Operated Spent Fuel Pool During Core Offloads & Fuel Shuffles ML20217E8411997-10-0101 October 1997 Forwards Info Provided by Ies Utilities Inc Re Improved TS ML20216G5881997-09-0404 September 1997 Notification of 970909 & 10 Meeting W/Util in Rockville,Md to Discuss Portions of ITS That Seek to Delay Entry Into Limiting Conditions for Operation When Performing Surveillances ML20236N0471997-04-0808 April 1997 Discusses Suppl Response to TIA Re TS Practices at Plant. Based on Meeting Held W/Licensee on 970320,listed Info Was Discussed ML20137B2971997-03-19019 March 1997 Notification of 970403 Meeting W/Util in Rockville,Md to Discuss Status of Spent Fuel Storage at Plant ML20136D5871997-03-10010 March 1997 Notification of 970320 Meeting W/Util in Rockville,Md to Discuss Licensee Practices of Treating TS Setpoints & Practices of Not Entering LCO Action Statements During Certain Surveillances ML20138J7671997-02-0505 February 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licenseing Exam on 970409. Ltr W/Copy to Chief,Operator Licensing Branch Must Be Submitted to Listed Address in Order to Register Personnel ML20236M1481997-01-16016 January 1997 Recommends That PD III-3 Take Appropriate Formal Action to Direct Licensee to Change Current Practice of Not Entering LCO When Equipment Rendered Inoperable Due to Surveillance Testing or Support Sys Inoperability to Ensure Compliance NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20058P0711993-09-0909 September 1993 Forwards Answers to Ti 2500/028 Questionnaire Re Employee Concerns Programs ML20127B9131993-01-0808 January 1993 Summary of Util 921130 IPE Rept in Accordance W/Generic Ltr 88-20, IPE for Severe Accident Vulnerabilities ML20245H5501989-08-0101 August 1989 Requests Waiver of Plant Observation Training for H Peterson,Due to Close Association W/Operation of Commercial & Naval Nuclear Power Plants ML20245C4091987-06-26026 June 1987 Submits Daily Staff Notes for 870626.Staff Will Meet W/Util on 870629 & Independent Oversight Committee to Review Current Status of Facility & Readiness to Exceed Current 50% Power Restriction ML20205D1321987-03-20020 March 1987 Discusses FEMA Concerns Re Adequacy of Util Offsite Emergency Plans for City of Cedar Rapids,Ia.Requires That If 10-mile EPZ Intersects Portion of City,Then Entire City Limits Must Be Included in EPZ ML20207R5761987-03-11011 March 1987 Advises of Const of Low Level Radwaste Processing & Storage Facility at Site.Assistance in Determining Acceptability of Using Liquid Radwaste Tanks in Nonseismic Facility Due to Unclear Guidance in Generic Ltr 81-38 Requested ML20212B0231986-12-17017 December 1986 Forwards, Emergency Diesel Generator Component Failures Due to Vibration, Engineering Evaluation Rept.Info Notice Informing Licensees of Potential Safety Concern of Fatigue Cracks in Fuel Oil & Cooling Lines Should Be Issued ML20154A2831986-12-13013 December 1986 Forwards Assessments by Enforcement Staff of Regional Performance in Enforcement Area from Jul-Nov 1985 ML20214C6861986-11-17017 November 1986 Forwards List of Missing SALP Evaluation Forms (0516B). Requests Review of Files to Locate Missing Forms.Recognizing That RP 0516B Issued in Mar 1986,request Applies Only to Repts Issued After Mar 1986 ML20203H2741986-07-28028 July 1986 Forwards,For Review,Latest Update of SALP Ratings ML20206F1641986-06-21021 June 1986 Requests That Evaluations of Licensee Responses to Encl IE Bulletin 86-001 Re Min Flow Logic Problems That Could Disable RHR Pumps Not Be Closed Until Temporary Instruction for Guidance Issued ML20195C9961986-05-27027 May 1986 Notification of Significant Licensee Meeting on 860528 at Region III Ofc to Discuss SALP ML20199A8271986-05-0808 May 1986 Forwards,For Review & Action,Draft Proposed Info Notice Re Incorrect FSAR Designation of GDC 55 & 56 as Not Applicable to Transversing in-core Probe Sys Lines.Condition Described in Encl Generically Important to Nuclear Safety.W/O Encl ML20213F1111985-01-0909 January 1985 Advises That Power Uprating Amend Request Should Be Treated as plant-specific Action & Be Reviewed According to Current Codes,Stds,Reg Guides & Calculational Models ML20062E0791982-07-29029 July 1982 Forwards Incident Reporting Sys Repts Re Spill of Contaminated Water & Contamination of Personnel in Auxiliary Bldg & Failure of Control Rod Guide Tube Support Pins for Transmittal to NEA ML20151D1941981-02-20020 February 1981 Informs That 810122 & 07 Memos Re Groundwater Monitoring Covered by Current Std Radiological Tech Specs & Radiological Assessment Branch Technical Position. Radiological Environ Monitoring Program Encl ML20148P6001980-12-24024 December 1980 Discusses Followup Study Re Degradation of Internal Appurtenances in LWR Piping During Normal Plant Operation & Potential Effects When Degraded Appurtenances Are Subj to Accident Loads.Recommends Review of Recurrent Problems 1999-09-23
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217N5121999-10-25025 October 1999 Forwards NRC Operating Licensing Exam Rept 50-331/99-302(OL) (Including as-given Witten Exam) for Tests Administered During Week of 990920 ML20212J7691999-10-0101 October 1999 Notification of 991015 Meeting with Util in Rockville,Md to Discuss Licensee Submittal Schedule.Draft Agenda Encl ML20212F5461999-09-23023 September 1999 Notification of 991004 Meeting with Utils in Rockville,Md to Update Status of Nuclear Mgt Company & Provide Details of Member Licensees Impending License Transfer Applications & Operating Agreement ML20210A6141999-07-13013 July 1999 Forwards facility-submitted Outline & Initial Written Exam Submittal for Operator Licensing Exam Administered on 990525 ML20207H6651999-07-13013 July 1999 Forwards NRC Operator Licensing Exam Rept 50-331/99-301(OL) (Including Completed & Graded Tests) for Tests Administered on 990525 ML20206H5181999-05-0505 May 1999 Notification,For Docket 7200032,of 990521 Meeting with Util in Rockville,Md to Discuss Util Plan for General License to Store Spent Fuel at ISFSI at Duane Arnold Plant.Meeting Agenda Encl ML20195D8781998-11-12012 November 1998 Responds to TIA 98-008 Requesting Assistance in Establishing Generic Regulatory Position on Period of Time & Under What Circumstances Acceptable to Remove Rod Control from Service ML20154R3691998-10-19019 October 1998 Notification of 981029 Meeting with Listed Utils in Rockville,Md to Discuss Proposed Consortium of Utils ML20237D8641998-08-25025 August 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980706-10 ML20237D8421998-08-25025 August 1998 Forwards NRC Operator Licensing Exam Rept 50-331/98-301OL for Exam Administered During Wk of 980706 ML20236X3891998-08-0303 August 1998 Responds to Technical Assistance Request (AIT 96-0278) Re Entering Limiting Conditions for Operation at Duane Arnold Energy Ctr ML20195D8931998-06-18018 June 1998 Requests Assistance Re Technical Issue Limitations of Removing Normal Control Rod System Controls from Service on Operating Reactor (TIA 98-008) ML20237B9781998-04-15015 April 1998 Informs That on 980205-06,NRC Staff Attended Severe Accident Mgt Implementation Demonstration at Ies Utilities,Duane Arnold Energy Ctr in Cedar Rapids,Ia ML20199J6631998-01-29029 January 1998 Forwards Info Re Plant Responses to Staff Requests for Info on Section 3.3 of Plant Improved TS Submittal.Part of GE 24A5369,Rev 0,Class I, Supplemental Reload Licensing Rept for Plant Reload 14 Cycle 15, for Sept 1996 Encl ML20199A3061998-01-21021 January 1998 Notification of 980204 Meeting W/Util in Rockville,Md to Discuss Util Resolution to NRC Bulletin 96-003 ML20198M9751998-01-0909 January 1998 Requests Encl Info Documenting Conference Call Between NRC & Ies Utilities Re Duane Arnold Energy Center Responses to Staff Requests for Info on Section 3.6 of Improved TS Be Placed on the DAEC Docket ML20198A5161997-12-19019 December 1997 Summarizes 971217-18 Meeting W/Ies Utils,Inc to Address Responses Provided by Licensee Re RAIs on DAEC Improved Ts. Discussions Resulted in or Documented Closure of Most Rais. List of Attendees & Handouts Encl ML20198A5121997-12-19019 December 1997 Forwards Info Which Documents Series of Conference Calls & Fax Between NRC & Ies Utils,Inc Re DAEC Responses to Staff Requests for Info on Section 3.8 of DAEC Improved TS Submittal ML20203G3121997-12-11011 December 1997 Forwards Info Which Documents RAI Re Conversion from Current to Improved TSs at Plant.Subj Info Requested to Be Placed on Plant Docket ML20203C3061997-12-0505 December 1997 Forwards Info Documenting Telcon Between NRC Staff & Ies Utilities,Inc Re Conversion from Current to Improved TS at Daec.Requests Info Be Placed on Docket ML20203C4141997-12-0505 December 1997 Forwards Info Received from Ies Utilities,Inc Re Discussions About Conversion from Current to Improved TS at Daec. Requests That Info Be Placed on Docket ML20203B2491997-12-0303 December 1997 Forwards Info Supplied by Ies Utilities Inc.Info Provided Subsequent to Discussions About Conversion from Current to Improved TS at Duane Arnold Energy Center ML20199K9191997-11-24024 November 1997 Notification of 971217-18 Meeting W/Ies Utilities Inc in Rockville,Maryland to Discuss Responses to Requests for Info on Conversion of Duane Arnold Energy Ctr Current TS to Improved TSs ML20217K8031997-10-20020 October 1997 Notification of 971105 Meeting W/Util Re Responses to Requests for Info on Conversion of Plant Current TS to Improved TS ML20217E8451997-10-0101 October 1997 Forwards Info Provided by Ies Utilities Inc Re Staff Questions Concerning Discrepancies Between UFSAR & How Licensee Operated Spent Fuel Pool During Core Offloads & Fuel Shuffles ML20217E8411997-10-0101 October 1997 Forwards Info Provided by Ies Utilities Inc Re Improved TS ML20216G5881997-09-0404 September 1997 Notification of 970909 & 10 Meeting W/Util in Rockville,Md to Discuss Portions of ITS That Seek to Delay Entry Into Limiting Conditions for Operation When Performing Surveillances ML20236N0471997-04-0808 April 1997 Discusses Suppl Response to TIA Re TS Practices at Plant. Based on Meeting Held W/Licensee on 970320,listed Info Was Discussed ML20137B2971997-03-19019 March 1997 Notification of 970403 Meeting W/Util in Rockville,Md to Discuss Status of Spent Fuel Storage at Plant ML20136D5871997-03-10010 March 1997 Notification of 970320 Meeting W/Util in Rockville,Md to Discuss Licensee Practices of Treating TS Setpoints & Practices of Not Entering LCO Action Statements During Certain Surveillances ML20138J7671997-02-0505 February 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licenseing Exam on 970409. Ltr W/Copy to Chief,Operator Licensing Branch Must Be Submitted to Listed Address in Order to Register Personnel ML20236M1481997-01-16016 January 1997 Recommends That PD III-3 Take Appropriate Formal Action to Direct Licensee to Change Current Practice of Not Entering LCO When Equipment Rendered Inoperable Due to Surveillance Testing or Support Sys Inoperability to Ensure Compliance NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20058P0711993-09-0909 September 1993 Forwards Answers to Ti 2500/028 Questionnaire Re Employee Concerns Programs ML20127B9131993-01-0808 January 1993 Summary of Util 921130 IPE Rept in Accordance W/Generic Ltr 88-20, IPE for Severe Accident Vulnerabilities ML20245H5501989-08-0101 August 1989 Requests Waiver of Plant Observation Training for H Peterson,Due to Close Association W/Operation of Commercial & Naval Nuclear Power Plants ML20245C4091987-06-26026 June 1987 Submits Daily Staff Notes for 870626.Staff Will Meet W/Util on 870629 & Independent Oversight Committee to Review Current Status of Facility & Readiness to Exceed Current 50% Power Restriction ML20205D1321987-03-20020 March 1987 Discusses FEMA Concerns Re Adequacy of Util Offsite Emergency Plans for City of Cedar Rapids,Ia.Requires That If 10-mile EPZ Intersects Portion of City,Then Entire City Limits Must Be Included in EPZ ML20207R5761987-03-11011 March 1987 Advises of Const of Low Level Radwaste Processing & Storage Facility at Site.Assistance in Determining Acceptability of Using Liquid Radwaste Tanks in Nonseismic Facility Due to Unclear Guidance in Generic Ltr 81-38 Requested ML20212B0231986-12-17017 December 1986 Forwards, Emergency Diesel Generator Component Failures Due to Vibration, Engineering Evaluation Rept.Info Notice Informing Licensees of Potential Safety Concern of Fatigue Cracks in Fuel Oil & Cooling Lines Should Be Issued ML20154A2831986-12-13013 December 1986 Forwards Assessments by Enforcement Staff of Regional Performance in Enforcement Area from Jul-Nov 1985 ML20214C6861986-11-17017 November 1986 Forwards List of Missing SALP Evaluation Forms (0516B). Requests Review of Files to Locate Missing Forms.Recognizing That RP 0516B Issued in Mar 1986,request Applies Only to Repts Issued After Mar 1986 ML20203H2741986-07-28028 July 1986 Forwards,For Review,Latest Update of SALP Ratings ML20206F1641986-06-21021 June 1986 Requests That Evaluations of Licensee Responses to Encl IE Bulletin 86-001 Re Min Flow Logic Problems That Could Disable RHR Pumps Not Be Closed Until Temporary Instruction for Guidance Issued ML20195C9961986-05-27027 May 1986 Notification of Significant Licensee Meeting on 860528 at Region III Ofc to Discuss SALP ML20199A8271986-05-0808 May 1986 Forwards,For Review & Action,Draft Proposed Info Notice Re Incorrect FSAR Designation of GDC 55 & 56 as Not Applicable to Transversing in-core Probe Sys Lines.Condition Described in Encl Generically Important to Nuclear Safety.W/O Encl ML20213F1111985-01-0909 January 1985 Advises That Power Uprating Amend Request Should Be Treated as plant-specific Action & Be Reviewed According to Current Codes,Stds,Reg Guides & Calculational Models ML20062E0791982-07-29029 July 1982 Forwards Incident Reporting Sys Repts Re Spill of Contaminated Water & Contamination of Personnel in Auxiliary Bldg & Failure of Control Rod Guide Tube Support Pins for Transmittal to NEA ML20151D1941981-02-20020 February 1981 Informs That 810122 & 07 Memos Re Groundwater Monitoring Covered by Current Std Radiological Tech Specs & Radiological Assessment Branch Technical Position. Radiological Environ Monitoring Program Encl ML20148P6001980-12-24024 December 1980 Discusses Followup Study Re Degradation of Internal Appurtenances in LWR Piping During Normal Plant Operation & Potential Effects When Degraded Appurtenances Are Subj to Accident Loads.Recommends Review of Recurrent Problems 1999-09-23
[Table view] |
Text
.
+
o..' - Date: SEP 2 91978 SeH al ~ No. : IE:ROI: 78-10 TRANSFER OF LEAD RESPONSIBILITY 0
.T,0,:
B. K. Grimes, Assistant Director for Engineering and Projects, NRR
SUBJECT:
SAFE ENDS FOR RECIRCULATION N0ZILES _
RESPONSIBLE ASSISTANT DIRECTOR: E. L. Jordan DESCRIPTION OF ITEM RE00 IRING' RESOLUTION:
With regard to operating BWR's,1has identified five types of s afe ends which have been used to connect recircuTation inlet 11nes (to fEactor vessel nozzles.Four cf these types include thermal sleeves which are welded to the safe ends. The material is inconel for Type 1 safe ends and stainless steel for Types 2, 3, and 4 saf~e ends. The design of Tvoes 1 and 3 safe ends includes a crevice at the thermal sleeve to safe end joint. The design of Types 2 and 4 safe ends preciuoes the crevice at the joint,~ but does include stagnant water.*
_nunne Arnold has Type 1 safe ends. All of them have cracked and one crack extendLthru_ the_ safe _end wall. The safe ends have been Mand are being rsplaced witn otners of modified design.
Metallographic examination of the cracked safe ends is in progress' M-to detemine the cause of cracking. This work is being performed 6 O, by independent laboratories under contract to the licensee and IE.
Two other units, Brunswick 1 and 2, have Type 1 safe ends. Based on preliminary metalTogr5phic resiiTts from Duane Arnold, an imediate action letter has been sent to the licensee for Brunswick specifyina
.y.olmet ri c namination of the safe ends in the vicinity of the .
~
N" thermal sleeve to safe end wetos. (/v Preliminary metallographic results obtained for Duan Arnold safe ends indicate that the cause of cracking may be str ss corrosion at the tip of the crevice. Nevertheless, vibration induced fatione originating from the jet pump riser may be 'a contributing factor.
Because of the presence of crevices and stagnant water in the Type 3 design, NRR and IE do have some concern for the long term integrity l
- See Enclosure for identity of safe ends at each operating plant.
CONTACT: W. J. Collins, TP 49-28180 7 7 p rc o q q 3
\
l .
- ' , B. K. Grimes 2 SEP 2 81978 l -
t of these safe ends. Type 4 safe ends have a more complex geometry which eliminatu the crevice or locates it away from the safe end wall, but does not eliminate stagnant water.
For BWR's operating and under construction which have Type 1, 2, 3 or 4 safe ends, resolution is needed in the areas of inservice inspection, me.iification, and design qualification.
RECOMMENDATRNS AND PROPOSED COURSE OF ACTION:
1.
'NRR will evaluate the basis for continued operation of affected plants including assurance that appropriate interim actions are taken.
2.
NRR will evaluate on a priority basis the need for installing
@celeromegd on a safe end at Duane Arnold and other units.
3.
IE will obtain refueling outage schedules from Type 3 plants and other plants as requested by NRR.
[4'.~ 'IE wi i nfom NRR and the NRC Pipe C c
\ results of safe end inspections and metallographic examinations 7 q _they are obtained.
- 5. E inspect for compliance with any requirements established CONCURRENCE:
Edward L. Jordan, Assistavit Director hr S[LL[76 Date for Technical Programs, DROI IE 9
e5. K. Grimes, Assistant Director j/ 7ky Date for t.:.cineering and Projecte . 10R, NRR 4
~ * *'
n' e . . ,
e
-B. K. Grimes 3 SEP 2 9 p l
Enclosures:
- 1. Recirc Inlet Nozzle Sutms:y
- 2. PNO-78-163 cc: R. S. Boyd, DPM -
V. Stello, D0R D. G. Eisenhut, DDR R. W. Reid, DDR W. S. Hazelton, DDR V. S. Noonan, DDR R. W. Klecker, DDR M. B. Fairtile, DDR J. G. Davis, IE N. C. Moseley, IE H. D. Thornburg, IE J. H. Sniezek, IE G. W. Reinmuth', IE B. H. Grier, RI J. P. O'Reilly, RII J. G. Keppler, RIII "
K. V. Seyfrit, RIV R. H. Engelken, RV K. Terney, MPA S. H. Hanauer, EDO R. J. Mattson, DSS
[MThao, RES -
e 1
p .
i .
i I
e
.. W. .'.l e
- m. a a .s .e, .<r. . . ,e.w
.- .m, s t *--
..- )
f %: . = -a.
.. m. w , , m. ..r.a. m.Z~I v , c ,
M. > i S.
1 T -t 9 & * - - * = = ..
t .=>.?%.f.* E ~a 7. .L'sk" an D' *"g.~
- 7*#~"'"'W '** ** * * * * * * - * ? **
- A* .*.=u. a .i.=.= nca.AA
. 91m w3 is . .==**
. , <. . 5 . .
).
. .. g.
'.'*.*"":".r T.'".".# -T * *# L e.+. a === aD a &. . . . C= e - -*
.. .N.. , u* w M ",,,;.W. ;;- . ,LT ,"g*
--r,-.w=> .c. r. r , ; f ...
e
%. .:r.=**=.==
- r. wve 9 e e y k. .v. . v. c.%"G.
_s .: L *.*
. - m* .C.'- 2.* v f. .t .3 *- ..==v, :
.eM- *w.
v .,r .* 8, ,
eat
. ,, ;,. ;,, ,-m ,r-_.,==.-,
C".> .';"* ;* --
r ==. t=.- r=
e.*==w.m'". .." .* ==i. *% *w s..k C. ?. / . e4y= pr g).
\
'B.*.*"."w'".".".*.*.*!..i.*.9.,
t a -
%y e r S. T. .'.3.?."" t. am. . . .%. . ;,. S . .e .gap
.4.,~v s.
. %, *s
. r- ,,_ A ,;, ,
at ag . .: g, p. . g ., ,,
- a. , <==*w -3 g wsw w.. . . . . ,
.,. e a : .' L ** .
- ==== .,: g y*r.".'L"".'.:"a
-= **""'.*..Va-w # .O.*--'""* ( .*4* / *b%) "i - ,,.s .v .g
.e3g,,,,,,,,,. .;,
7Q c,y,q ,,,,;g ; , ,,,; ,
"'%"".".".*."".J, s '..'r"".".
. .a.~ .C. r.. 'Ta 7.".Ts ..
~~' * *
".* 7 *""'----% ~% r * *'Q. 'y =.m*='l: se g w'% *!".~'"".*.',
. w.. . 41Q .n. ,
=~*r.L ..r4 f*.l w> 7. E e., .c...
.t
't
- y. .s-.-w ~'- .c . i . (. .c >. . .n. . .- v. ~., r= j= ws..
.v.. .c. y>.. :.a. zmm. ;, .
!? ".>.,a*.'* 8, @*aw P yJ Qg ~.* ===n e.
9'e".7.'"e
- 9 % V'3 . . A ; ***".'~e.~.
. = . - * . %.
,."./..:."."**."'." .(,=/
.i. . ".!
O e
S #I*.'.,y 9~ / e .t
...es.=
Nm
. ~
s- '
PRELIMINARY NOTIFICATION
,- . September 14, 1978 i
O PRELIMINARY NOT;FICATION OF EVENT OR UNUSUAL OCCURRENCE--PNO-78-163 This oreliminary notification constitutes EARLY notice of an event of POSSIELE safety or oubiic interest sien1ficance. The information presentec is as initially receivec witncut verification or evaiuation and u casicaily ali inat is known ov IE staff on this cate.
Facility: Iowa Electric Light & Power Company, Duane Amold (DN 50-331), Palo, IA
Subject:
JET PUMP RISER CRACK The jet pump riser crack problem at Iowa Electric Light and Power Company's Duane Arnold facility has been previously reported by PNO-78-125 and 12EA, ,
dated June 19 and 20, 1978, respectively. Metallographic samples were ._. .___
taken from the nozzles and sent to Battelle-Columbus and Southwest Research for examination. Preliminary results obtained to date indicate that the cracks are inter-granular in nature and initiate in the area of the crevice formed by the thermal sleeve and inconel transition piece.
l' Carolina Power and Light Company's (CPLL) Brunswick Nuclear Plants i and 2 are similar in design and material fabrication to the Duane Arnold
. plant. Due o the similarity, plans have been made for CP&L to concuct nondestructive examination of a selective number of nozzles for crack indications. Brunswick Unit 2 is presently shutdown, and' testing will be conducted prior to its return to power.
There is some potential for the crack' problem to exist at other similar plants. Th : probicm is currently being reviewed by the NRC staff.
These plants are: Browns Ferry Units 1, 2, & 3 Dresden Units 2 & 3 Peach Bottom Units 2 & 3 ..
Quad Cities Uryi ts._1 & .2 __ ..
Contact:
WCollins, IE x2BlBO RWoodruff, IE 28180 GKlingler, IE x28180 Distribution: Transmitted H St b Commissioner Bradford S. J. Chilk, SECY Chairman Hendrie C. C. Karrenerer, CA Commissioner Kennedy Commissioner Ahearne Comissioner Gilinsky (For Distribution)
Transmitted: MNBB P Bida k J. G. Davis, IE L. V. Gossick, ED0 "
~
,H. R.'Denton, NRR Region T 7 Ll M S. H. Hanauer, EDO 3
J, 3. Fouchard, PA SS Bldg g - .,9.q (p.IL) ry gg 44:4. 'g$,
N. M. Haller, MPA C. V. Smith, NMSS .0. G. Abston, DIA p R. G. Ryan, OSP R. Minooue, SD H. K. Shepar, ELD
~
% zl_gl t'RELIMINARY NOTIFICATION
%l@bM --
d
I Ferry Pester Than Browns A 270* crack in ils reactor piping may have brought the Duane Arnold Nuclear Pla meltdown accident than did the renowned fire at the Browns Ferry Nuclear Plan '
et by David Dinsmore Comey Electric will probably spen more than panying photo.) As a result, the reactor '
Until recently, the March 22,1975, fire. $15 million to purchase power liom at the Browns Ferry Nuclear Power Plant was cooled down and the fuelin the re- other utilities while the plant is shut ,
actor core was removed to the spent ntar Decatur, Alabama, was the closest Radiographic and ultrasonic down.The Commission's chairman.Mor. ,
fuel po the American nuclear industry had come ris Van Nostrand, says he expects the i testing showed that, although the visible to a major accident at a civilian nuclear utihty to make an " aggressive" attempt-crack was four inches long, this crack i power plant. The fire destroyed the re- to recover repair costs from General actuatl, extended approximately 270 cctor coritrol circuits, starting a "boit- Electric. '
degree s around the circumference of off" of primary coolant in the reactor the pipe. When the other seven recircu-The original safe ends were manutac-core. At the same time,it disabled emer
- lation pipe safe ends were radrographed tured bv Lanape Forge in Pennsylvania.
psney core coohng systems Fortunate- and ultrasonically tested, all seven were ly, the " boil-ott" wee halted before a under subcontract to Chicago Bridge found to be cracked to some extent; four and iron, which in turn wr,s a subcon-core meltdown began? had significant indicahons of intermit-On June 17, 1978, however, the tractor to General Electric, the reacts tent cracking around their entire circum- manufacturer. A drawing error ca : sed Duane Arnold Energy Center in Cedar Rapids, Iowa, came closer - according feiences machinists at Lanape to cut a groom As of this writing, all eight safe ends that was 3/8 of an inch too deep arouno -
to industry experts - to a " loss of- are scheduled to be replaced by newly coolant" accident than did Browns Ferry each pipe. These grooves were then designed forgings being faM#Cated at in 1975. This incident has received very filled in with weld metal. Recoros at Coulter Steel and Forge Company m Lanape, CB&l, and GE show that these little media attentiert Berkeley, California The plant cannot On June 17,1978, reactor operators repairs were approved as meeting re r De restarted before late October, and Quired safety codes. !
were testing the control valves on the .ne utility estimates that repair costs Duane Arnold Center, a 538 megawatt An NRC official says,"Ouite obvious.
boiling water reactor operated by lowa will be about $2 million. The Iowa Com- ly we werer 't aware of the repai*s, a'ic Electric Light and Power Company. Sud. merce Commission eshmates that towa deniy because of problems wsth e(ectri- ,, ggg ,, ,,,, ,n;, , ,,,,,,, ,, gn, ,,,,g.s first nuclear shower Wa ter spurts from cal relays sn the reactor protection sys' pipe even after the reactor.has been depressursted 3
tem,the reactor accidentally shut down. a '
Only then,when an inspection of the re- j ,
ccior dryweit was made, was it discov-cred that a primary coolant pipe was
- *j , ,
leaking from a four-inch long crack, ,
[% ,,.
The leaking pipe was one of eight 10- s A inch diameter pipes used to transfer
- k>h % o cooling water from the recirculation td '% ,
system to the jet pumps inside the reac-
- tor, The crack was located in a section f F, * *Q % \ ', , -l j,'y ',8p \
of the pipe known as a " safe end forg- i ,
- (d ing" that joins the pipe to the inlet nozzle N- .f g .
on the reactor pressure vessel, This ,N r -:,n.!
- sale end," located near the bottom of the reactor core,is a highly undesirable j j'/c' b , ..!'5.h[
e
- [, O location at which to have a pipe break. A i
- .' [. #, . , ' ' e
- Dgr ,M r /
.y M.'.[ 'd'y[
" design basis accident" analysis per- 4 %' :.,,,, ,
lormed by the U.S. Nuclear Regulatory . .
- F ]
Commission (NRC) states that "a com-b e' s,', ,~ 7 7.*d# "I -(*
,T D,,,," ,,"~~~" $.d." /,7'(([,,',N[
plete circumferentiat break cf one of the S , ,,
recircutation 1000 pioes" would result in J, N - ?2.Y the worst " loss of coolant" accident I , .[,
i possible at a boshng water reactor.' #* h, U g,..g- ,,,
The leak continued even after the re-actor was de pressurized. (See accom-
'(.
l
, .- n
,/ l Civil Liberties Confmred from pape 7. less intrusive, "non-investigative safe-no one here is happy repaired parts guard measures which would not under-were used." But an NRC inspector says measures would be expensive. But nu-mine the Constitutional rights of nuclear that the repairs would have met even the clear facilities could be tumed into im-pregnable "tortresses." 11 this were the industry employees."*
more stringent safety codes in force to- .I case, there would be no necessity of The ACLU position seems to be thatit day.
Because the three companies in- condu,cting Surveillance in order io be s possible to operate a major nuclear volved in fabricating the safe ends at aware 'of potential threats; any attack power program and still protect the ctvil could be repelled. liberties of the people employed in this Duane Arnold manufactured similar fit-lings for the Brunswick Nuclear Plant piogram. But i disagree. Only thorough naar Wilmington, North Carolina, which investigations will protect against the is owned by Carolina Power and Lighi, "IS it better to torture a possibility of sabolage from within a nu-CBE has questioned whether Brunswirt suspected terrorist than to clear power plant and the loss of might not suffer the same problem as ]ct a City 90 Up in flames 7" hundreds of thousands of lives. This Du6ne Arnold. Because the safe end situation can be described in the sa ne w:lts at Brunswick are approximately terms used by Russell Ayres with re-Such measures would not, however, one inch thick, however, while those at spect to a plutonium economy: To pro-
- protect against the possibility that an lect the public it is necessary to deny Duane Amold are only '/rinch thick, the employee might smuggle in explosives the civil liberties of a significant seg-NRC believes that Brunswick shows no or os orride sately devices in such a way cause for concern. Alt GE nuclear power ment of the population. -
as to cause a reactor to melt down or a plants other than Brunswick use a differ, waste. storage facility to disperse its cnt safe-end design from that at Duane radioactive contents over a wide area.
Amold. in crder to protect against potential The ACLU Calls the NRC'S But it is worth noting that, at another sanotage from within the facility, the security pTOpOSals GE plant, approximately two months be. NRC recently proposed an " accession u alar TTling,"
fore the incident at Duane Arnofd, an un. authorization program" tot employees at scheduled inspection conducted on nuclear power plants. The program April 26,1978, during the romling of would include " background investiga. Nuclear power thus represents a the Cooper Station of Nebraska Public tions as to character, associations, and threat to our civit liberties as greaf as Power south of Omaha discovered indi. loyalty, conducted under standards and any other this country has faced The cations of cracking on three of the recir. specifications established by the Com- many other drawbacks and hazards o!
culation loop pipes where the safe-end mission." Employees would be subject- nuclear power have become obvious is welds join the nozzles The delects ed to " full field background investiga' recent years. But on civil fibertieg
'were ground out without violating mini. tions" by the Federal Bureau of in- grounds alone,fiuclear power deservec mal wall thickness codes. W the NRC vestigation and other agencies,in which to be abandoned.
has acwpted the repairs atisfacto.
past fellow employees, landlords, per-ry. sonal and professional acquaintances, ,
The NRC still does not know why the heiDhbors, and intimate personal rela-sale ends at Duane Arnold cracked,3 Footnotes tions would be interviewed.Other meth-even though the repairs made to the im. ods of investigation being discussed ' David D. Comey, " Nuclear Power the Uit properly machined piping met both past wouto 5clude psychological testing, mate intemat Subversion". Decemoer $$
197 c n add 55 oA ic and prese'nt code requirements. clinical evaluation, and polygraph ex- D Fortunately.neither it'e Duane Amold .. Die sonalen Zwknge der Kemenergie ..
aminations.
or Cooper reactors were operating Mr. Shattuck,in his testimony on be- Kernenerg,e (Frankfurt am Main. Fischer Ve' wt , the cracks were discovered. We lag.1976) pp 122-138 half of the ACLU.said that most of these
- David D Comey, "The Perlect Tro,a may not be so lucky the next time. proposed measures are infringements or Horse / Buum of W Afornic Sem b violations of protections now 9uaran- June 1976. p 34.
Details may be found in David D Comer, teed by the Constitution and by case 3 Russell W. Ayres, auoted in Chicapo Da "The incident at Browns Ferry,' Not Man News. Nov 29,1975, p 3 See atso r.
Apart. September 1975, reprinted sn. Peter law. The NRC has estimated that more "Pobceng Plutonium The Cml libefUes FC Taulkner (ed ), The S, lent Bomb (N Y., Ran- than 21,600 people will be subject to out." Harvard C,vis R,gnts - Curs levert-dom Hm,st 1977) such investigative clearances by 1985' Law Revoew,Vol 10.No 2 (Soring 197bL t 369 40 morents may be cotained for 53:
- Pretsminary Salery Analysts Report. Bailly and Mr. Shattuck characterized this General,np Star,on Nuclear 1.p 14 612. number as " alarming / He said. "The trom W,itiam S Hein. loc.,1285 Main Stre a The NRC has obtained one of the cracked proposal would set a dangerous prece- Duffalo. NY 14209).
safe ends and sent it to Battene Memorial
- Russell W. Ayres Quoted so Wash 4 Laboratory in Columbus. On,o for destructive dent by extending a security clearance posf. Nov 17.1975.0 A24 lesting stat may reveal the cause of the ,
- John H F. Shattuck." Testimony of Ames cracking This testing will be an endependent government positions to an entire indus- Cmt Liberties Union " June B. 1978 000 check on the testing being performed for lows No RM.50J. U S Nuclear Regulato y Cc try, thereby broadly affecting the private mission. Wasnmpen Dr v 555 Electric at Southwest Research an San Anto- sector." He proposed that the NRC Seek n'o. T e8*s OCTOBER 191 r
.- 10 .
"