|
---|
Category:ANY EXTERNAL MEMORANDUM ROUTED TO NRC & NOTES
MONTHYEARML20080G9581983-09-26026 September 1983 Provides Resolution for Loose Bolts on Structural Steel Found During NRC Const Assessment Team (Cat) Insp.Item Considered Closed.Related Info Encl ML20080T4961983-03-30030 March 1983 Forwards Dept of Labor 830324 Recommended Decision & Order of Administrative Law Judge in W Royce Vs Bechtel Corp Case ML20080T5261982-06-15015 June 1982 Discusses NRC Insp Entrance Interview Conducted on 830615,to Describe NRC Planned Insp Activities.Lists NRC Inspectors & Areas of Investigation.Nrc Will Be Primarily Investigating Allegations During Visit.Related Matl Encl ML17296B2011981-01-19019 January 1981 Forwards FSAR Pages 9.5-1/9.5-1A & 9.5-1B/9.5-2 to Replace Pages 9.5-1/9.5-2 Erroneously Provided as Part of FSAR Amend 3 in Vol 8 1983-09-26
[Table view] Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217A8641999-10-0606 October 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990829-0903 ML20211H4441999-08-27027 August 1999 Notification of Significant Meeting with Util on 990916 & 17 in Arlington,Tx to Improve Utility & NRC Understanding of Industry & Regulatory Perspectives on Current Issues ML20138K0131997-05-0606 May 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal) for Tests Administered on 970324-28 ML20138K0091997-05-0606 May 1997 Forwards NRC Approved Operator Licensing Exam (as-given Operating Exam) for Tests Administered on 970324-28 ML20137F2351997-03-24024 March 1997 Summary of 970207 Meeting W/Listed Attendees in Rockville,Md to Discuss Nuclear Energy Inst Concerns Re Graded Quality Assurance Activities W/Volunteer Plants ML20137C9201997-03-20020 March 1997 Forwards Documentation of Meeting Conducted in Region 4 Office on 970225 to Discuss NRC Enforcement Policy as Applied to Nonescalated Enforcement ML20135E7161997-03-0303 March 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 961118-22 ML20134P2231997-02-20020 February 1997 Discusses Ti 2515/122 Evaluation or Rosemount Pressure Transmitter Performance & Licensee Enhanced Surveillance Programs multi-plant Action B-122 ML20134M2471997-02-14014 February 1997 Submits List of Plants Not Meeting Selection Criteria for Ti 2515/118 Insp on Basis of Factors Such as SWS Operating Experience,Contribution of SWS to Plant Risk Assessment, Licensee Programs in Response to GL-89-13 ML20236U9391995-12-20020 December 1995 Discusses Oi,Region IV Rept of Investigation,Dtd 940511, Case 5-93-023R,which Reported OI Investigative Efforts Re Alleged Employee Discrimination at Plant Units 1,2 & 3.Rept Was Sent to Us Attorney Office in Phoenix,Az in May 1994 IA-96-341, Discusses Allegation RV-94-A-0004,Songs Vendor Manuals. Licensee Reviewed Allegation,Concluded Unfounded & Notified NRC for Conclusion by 940228 Ltr1994-08-0303 August 1994 Discusses Allegation RV-94-A-0004,Songs Vendor Manuals. Licensee Reviewed Allegation,Concluded Unfounded & Notified NRC for Conclusion by 940228 Ltr ML20138F9871994-08-0303 August 1994 Discusses Allegation RV-94-A-0004,Songs Vendor Manuals. Licensee Reviewed Allegation,Concluded Unfounded & Notified NRC for Conclusion by ML20056E5141993-08-12012 August 1993 Submits SALP Schedule for FY94 Per Mgt Directive 8.6 ML20198E3271992-10-20020 October 1992 Notification of Significant Licensee Meeting W/Util on 921027 to Discuss Transfer of Fire Watch Responsibilities to Security Dept & Ongoing Programs within Security Dept ML20126L8441992-09-14014 September 1992 Provides Status Rept Concerning Actions Re Det Performed at Plant ML20127C2461992-03-0202 March 1992 Forwards AEOD SALP Input for Facilities in Support of Ongoing SALP Reviews.Two of Six Important Operating Events Involved Deficiencies of Reactor Power Cutback Sys Which Relies on Proper Functioning of Steam Bypass to Condenser ML20127B6281990-12-31031 December 1990 Forwards Updated Status Rept on Actions Re Diagnostic Evaluation Performed at Facility IA-92-218, Forwards Updated Status Rept on Actions Re Diagnostic Evaluation Performed at Facility1990-12-31031 December 1990 Forwards Updated Status Rept on Actions Re Diagnostic Evaluation Performed at Facility ML20127B5671990-12-12012 December 1990 Forwards NRR Input for SALP Rept,Per NRC Ofc Ltr 907,Rev 1 ,NRC Manual Chapter 0516 & 901120 Memo ML20059M2041990-09-27027 September 1990 Notification of Significant Licensee Meeting W/Util on 901003 to Discuss Licensee Response to Diagnostic Evaluation Team Findings & Overall Status of Programs. Addl NRC Attendees Should Be Made Known by 901002 ML20059L6531990-09-20020 September 1990 Notification of 900921 Meeting W/Util in Walnut Creek,Ca to Discuss Licensee Initiatives & Status in Area of QA ML20059D6361990-08-27027 August 1990 Notification of 900831 Enforcement Conference W/Util in Walnut Creek,Ca to Discuss Medical Qualifications & Exams of Licensed Operators ML20127B4571990-08-24024 August 1990 Comments on Response to Facility Diagnostic Evaluation Team Rept.Suggests That Region V Followup & Closely Monitor Development & Implementation of Specific Tasks Which Will Address Team Findings ML20058M3441990-08-0606 August 1990 Forwards List of Open Items in Sims for Plant.Documented Basis Exists for Closure of TMI Related Items at Plant ML20126L8271990-06-14014 June 1990 Provides Summary of Schedule & Status of Items Re Det of Plant Performed by Aeod,In Response to 900314 Memo ML20127B2171990-01-18018 January 1990 Forwards AEOD Input for Commissioner Curtiss Visit to Plant on 900201,consisting of Summary of Operating Experience from Oct 1988 to Dec 1989 ML20127B1681989-11-0909 November 1989 Forwards NRR Input to SALP for Facilities.Category 2 Rating Assigned in Functional Areas of Plant Operations, Radiological Controls,Emergency Preparedness,Security & Safety Assessment/Quality Verification ML20246N7371989-08-29029 August 1989 Notification of Maint Team Insp Meeting on 890901 W/Util in Phoenix,Az to Discuss Status of Licensee Commitments from 890605 Mgt Meeting in Consideration of Unit 3 Restart ML20127B1401989-08-0707 August 1989 Forwards for Info & Consideration for Info Notice,Lers Describing Potter & Brumfield Relay Problems & Atmospheric Dump Valve Deficiencies.Info Provided as Part of AEOD Function to Identify Potential Adverse Events ML20127G5121989-03-15015 March 1989 Discusses Atmospheric Dump Valve Failures at Plant.Cause Still Under Investigation.Related Documentation Encl ML20236B4871989-03-14014 March 1989 Notification of 890316 Meeting W/Util in Rockville,Md to Discuss Electrical Distribution Sys as Related to Load Injection Event on 890303.Preliminary Agenda for Electrical Meeting Encl ML20195G8481988-11-21021 November 1988 Notification of Significant Meeting on 881201 in Wintersburg,Az to Review Util Action on NRC Concerns ML20206L6701988-11-21021 November 1988 Notification of 881209 Meeting W/Util in Rockville,Md to Present Engineering Excellence Program ML20207D6471988-08-0505 August 1988 Notification of Significant Meeting on 880817 W/Util in Walnut Creek,Ca for Enforcement Conference Re Early Criticality Event at Unit 1,personnel Radiation Overexposure at Unit 2 & Violation Re Essential Chiller Water Sys ML20196L2531988-06-28028 June 1988 Recommends Closeout of Eab Long-Term Followup Item 87-157 on Reactor Coolant Pump Shaft Cracking at Plant.Modified Shafts Installed & Vibration Monitoring Programs in Place ML20150A8971988-06-24024 June 1988 Advises That C-E 880108 Rept of Fuel Surveillance Test Results Previously Submitted to NRC as Nonproprietary Info, Should Be Considered Proprietary ML20196F9801988-06-23023 June 1988 Advises That Licensee 880609 Justification for Continued Operation Re Recent Auxiliary Feedwater Pump Degradation Event Acceptable.Licensee Will Perform Corrective Maint When Replacement Parts Received ML20154N1601988-05-25025 May 1988 Notification of 880531 Meeting W/Util in Rockville,Md to Discuss Evaluation of Failure of Auxiliary Feedwater Pump at Unit 1 & Planned Actions to Correct Root Cause of Failure ML20151E2061988-04-0808 April 1988 Notification of 880414 Meeting W/Util & BNL in Rockville,Md to Discuss Vibration Monitoring Program for Reactor Coolant Pump Shafts & Status on Plant Shaft Evaluations.Agenda Encl ML20148D9491988-03-15015 March 1988 Discusses 880315 Operating Reactors Events Meeting 88-11. List of Attendees,Events Discussed & Tabulation of long-term Followup Assignments Detailed in Encls ML20147H6821988-03-0404 March 1988 Confirms 880302 Telcon Re Evaluation of Justification for Continued Operation.Agreed That Continued Operation of Plant Presents No Undue Risk to Public Health & Safety.Util Received Which Confirms Info Provided by T Polich ML20236X7421987-12-10010 December 1987 Forwards Draft Director'S Decision Re Coalition for Responsible Energy 2.206 Petition Concerning Plant Submitted on 870716,for Comments & Concurrence ML20195F8761987-12-0202 December 1987 Requests Review of Encl Draft SALP Rept for Plant.Recipients Should Be Prepared to Comment on Rept at 871208 Board Meeting.Update of Tables 1-10 Which Includes All Pertinent Data Through End of SALP Period Also Encl ML20236X5801987-11-30030 November 1987 Comments on Draft Director'S Decision on Coalition for Responsible Energy Education 2.206 Petition Re Plant. Editorial Comments for Consideration Marked on Encl Draft ML20247G3591987-09-16016 September 1987 Forwards Info Re Preparedness for Full Power License, Including Open Items Including Allegations & License Conditions,Preoperational & Acceptance Testing Status,Const Status & Status of Insps Required by MC-2512,2513 & 2514 IA-89-226, Forwards Info Re Preparedness for Full Power License, Including Open Items Including Allegations & License Conditions,Preoperational & Acceptance Testing Status,Const Status & Status of Insps Required by MC-2512,2513 & 25141987-09-16016 September 1987 Forwards Info Re Preparedness for Full Power License, Including Open Items Including Allegations & License Conditions,Preoperational & Acceptance Testing Status,Const Status & Status of Insps Required by MC-2512,2513 & 2514 ML20237L7011987-08-31031 August 1987 Notification of 870909 Meeting W/Util in Bethesda,Md to Discuss Proposed Amend to Tech Specs Re Organizational Structure.Meeting Agenda Encl ML20195G3751987-08-21021 August 1987 Forwards Rept Re Licensing & Restart Schedules,Per EDO 870727 Memo.Info Will Be Provided Weekly ML20235V8251987-07-20020 July 1987 Notification of 870730 Meeting W/Util & C-E in Bethesda,Md to Discuss Licensee 870629 Submittal on Cycle 2 Reload IR 05000528/19860261987-07-16016 July 1987 Forwards marked-up Draft NRC Info Notice Entitled Control of Hot Particle Contamination at Nuclear Power Plants, Per 870626 Request.Issuance of Notice Suggested.W/O Encl. Portion of NRC Insp Rept 50-528/86-26 Also Encl 1999-08-27
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217A8641999-10-0606 October 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990829-0903 ML20211H4441999-08-27027 August 1999 Notification of Significant Meeting with Util on 990916 & 17 in Arlington,Tx to Improve Utility & NRC Understanding of Industry & Regulatory Perspectives on Current Issues ML20138K0131997-05-0606 May 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal) for Tests Administered on 970324-28 ML20138K0091997-05-0606 May 1997 Forwards NRC Approved Operator Licensing Exam (as-given Operating Exam) for Tests Administered on 970324-28 ML20137F2351997-03-24024 March 1997 Summary of 970207 Meeting W/Listed Attendees in Rockville,Md to Discuss Nuclear Energy Inst Concerns Re Graded Quality Assurance Activities W/Volunteer Plants ML20137C9201997-03-20020 March 1997 Forwards Documentation of Meeting Conducted in Region 4 Office on 970225 to Discuss NRC Enforcement Policy as Applied to Nonescalated Enforcement ML20135E7161997-03-0303 March 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 961118-22 ML20134P2231997-02-20020 February 1997 Discusses Ti 2515/122 Evaluation or Rosemount Pressure Transmitter Performance & Licensee Enhanced Surveillance Programs multi-plant Action B-122 ML20134M2471997-02-14014 February 1997 Submits List of Plants Not Meeting Selection Criteria for Ti 2515/118 Insp on Basis of Factors Such as SWS Operating Experience,Contribution of SWS to Plant Risk Assessment, Licensee Programs in Response to GL-89-13 ML20236U9391995-12-20020 December 1995 Discusses Oi,Region IV Rept of Investigation,Dtd 940511, Case 5-93-023R,which Reported OI Investigative Efforts Re Alleged Employee Discrimination at Plant Units 1,2 & 3.Rept Was Sent to Us Attorney Office in Phoenix,Az in May 1994 ML20138F9871994-08-0303 August 1994 Discusses Allegation RV-94-A-0004,Songs Vendor Manuals. Licensee Reviewed Allegation,Concluded Unfounded & Notified NRC for Conclusion by IA-96-341, Discusses Allegation RV-94-A-0004,Songs Vendor Manuals. Licensee Reviewed Allegation,Concluded Unfounded & Notified NRC for Conclusion by 940228 Ltr1994-08-0303 August 1994 Discusses Allegation RV-94-A-0004,Songs Vendor Manuals. Licensee Reviewed Allegation,Concluded Unfounded & Notified NRC for Conclusion by 940228 Ltr ML20056E5141993-08-12012 August 1993 Submits SALP Schedule for FY94 Per Mgt Directive 8.6 ML20198E3271992-10-20020 October 1992 Notification of Significant Licensee Meeting W/Util on 921027 to Discuss Transfer of Fire Watch Responsibilities to Security Dept & Ongoing Programs within Security Dept ML20126L8441992-09-14014 September 1992 Provides Status Rept Concerning Actions Re Det Performed at Plant ML20127C2461992-03-0202 March 1992 Forwards AEOD SALP Input for Facilities in Support of Ongoing SALP Reviews.Two of Six Important Operating Events Involved Deficiencies of Reactor Power Cutback Sys Which Relies on Proper Functioning of Steam Bypass to Condenser IA-92-218, Forwards Updated Status Rept on Actions Re Diagnostic Evaluation Performed at Facility1990-12-31031 December 1990 Forwards Updated Status Rept on Actions Re Diagnostic Evaluation Performed at Facility ML20127B6281990-12-31031 December 1990 Forwards Updated Status Rept on Actions Re Diagnostic Evaluation Performed at Facility ML20127B5671990-12-12012 December 1990 Forwards NRR Input for SALP Rept,Per NRC Ofc Ltr 907,Rev 1 ,NRC Manual Chapter 0516 & 901120 Memo ML20059M2041990-09-27027 September 1990 Notification of Significant Licensee Meeting W/Util on 901003 to Discuss Licensee Response to Diagnostic Evaluation Team Findings & Overall Status of Programs. Addl NRC Attendees Should Be Made Known by 901002 ML20059L6531990-09-20020 September 1990 Notification of 900921 Meeting W/Util in Walnut Creek,Ca to Discuss Licensee Initiatives & Status in Area of QA ML20059D6361990-08-27027 August 1990 Notification of 900831 Enforcement Conference W/Util in Walnut Creek,Ca to Discuss Medical Qualifications & Exams of Licensed Operators ML20127B4571990-08-24024 August 1990 Comments on Response to Facility Diagnostic Evaluation Team Rept.Suggests That Region V Followup & Closely Monitor Development & Implementation of Specific Tasks Which Will Address Team Findings ML20058M3441990-08-0606 August 1990 Forwards List of Open Items in Sims for Plant.Documented Basis Exists for Closure of TMI Related Items at Plant ML20126L8271990-06-14014 June 1990 Provides Summary of Schedule & Status of Items Re Det of Plant Performed by Aeod,In Response to 900314 Memo ML20127B2171990-01-18018 January 1990 Forwards AEOD Input for Commissioner Curtiss Visit to Plant on 900201,consisting of Summary of Operating Experience from Oct 1988 to Dec 1989 ML20127B1681989-11-0909 November 1989 Forwards NRR Input to SALP for Facilities.Category 2 Rating Assigned in Functional Areas of Plant Operations, Radiological Controls,Emergency Preparedness,Security & Safety Assessment/Quality Verification ML20246N7371989-08-29029 August 1989 Notification of Maint Team Insp Meeting on 890901 W/Util in Phoenix,Az to Discuss Status of Licensee Commitments from 890605 Mgt Meeting in Consideration of Unit 3 Restart ML20127B1401989-08-0707 August 1989 Forwards for Info & Consideration for Info Notice,Lers Describing Potter & Brumfield Relay Problems & Atmospheric Dump Valve Deficiencies.Info Provided as Part of AEOD Function to Identify Potential Adverse Events ML20127G5121989-03-15015 March 1989 Discusses Atmospheric Dump Valve Failures at Plant.Cause Still Under Investigation.Related Documentation Encl ML20236B4871989-03-14014 March 1989 Notification of 890316 Meeting W/Util in Rockville,Md to Discuss Electrical Distribution Sys as Related to Load Injection Event on 890303.Preliminary Agenda for Electrical Meeting Encl ML20206L6701988-11-21021 November 1988 Notification of 881209 Meeting W/Util in Rockville,Md to Present Engineering Excellence Program ML20195G8481988-11-21021 November 1988 Notification of Significant Meeting on 881201 in Wintersburg,Az to Review Util Action on NRC Concerns ML20207D6471988-08-0505 August 1988 Notification of Significant Meeting on 880817 W/Util in Walnut Creek,Ca for Enforcement Conference Re Early Criticality Event at Unit 1,personnel Radiation Overexposure at Unit 2 & Violation Re Essential Chiller Water Sys ML20196L2531988-06-28028 June 1988 Recommends Closeout of Eab Long-Term Followup Item 87-157 on Reactor Coolant Pump Shaft Cracking at Plant.Modified Shafts Installed & Vibration Monitoring Programs in Place ML20150A8971988-06-24024 June 1988 Advises That C-E 880108 Rept of Fuel Surveillance Test Results Previously Submitted to NRC as Nonproprietary Info, Should Be Considered Proprietary ML20196F9801988-06-23023 June 1988 Advises That Licensee 880609 Justification for Continued Operation Re Recent Auxiliary Feedwater Pump Degradation Event Acceptable.Licensee Will Perform Corrective Maint When Replacement Parts Received ML20154N1601988-05-25025 May 1988 Notification of 880531 Meeting W/Util in Rockville,Md to Discuss Evaluation of Failure of Auxiliary Feedwater Pump at Unit 1 & Planned Actions to Correct Root Cause of Failure ML20151E2061988-04-0808 April 1988 Notification of 880414 Meeting W/Util & BNL in Rockville,Md to Discuss Vibration Monitoring Program for Reactor Coolant Pump Shafts & Status on Plant Shaft Evaluations.Agenda Encl ML20148D9491988-03-15015 March 1988 Discusses 880315 Operating Reactors Events Meeting 88-11. List of Attendees,Events Discussed & Tabulation of long-term Followup Assignments Detailed in Encls ML20147H6821988-03-0404 March 1988 Confirms 880302 Telcon Re Evaluation of Justification for Continued Operation.Agreed That Continued Operation of Plant Presents No Undue Risk to Public Health & Safety.Util Received Which Confirms Info Provided by T Polich ML20236X7421987-12-10010 December 1987 Forwards Draft Director'S Decision Re Coalition for Responsible Energy 2.206 Petition Concerning Plant Submitted on 870716,for Comments & Concurrence ML20236W3181987-12-0404 December 1987 Staff Requirements Memo Re Commission 871125 Discussion/Vote in Washington,Dc on Full Power OL for Facility.Commission Requested Staff to Monitor Control Room & Corporate Mgt Activities & to Increase Number of Resident Inspectors ML20195F8761987-12-0202 December 1987 Requests Review of Encl Draft SALP Rept for Plant.Recipients Should Be Prepared to Comment on Rept at 871208 Board Meeting.Update of Tables 1-10 Which Includes All Pertinent Data Through End of SALP Period Also Encl ML20236X5801987-11-30030 November 1987 Comments on Draft Director'S Decision on Coalition for Responsible Energy Education 2.206 Petition Re Plant. Editorial Comments for Consideration Marked on Encl Draft ML20247G3591987-09-16016 September 1987 Forwards Info Re Preparedness for Full Power License, Including Open Items Including Allegations & License Conditions,Preoperational & Acceptance Testing Status,Const Status & Status of Insps Required by MC-2512,2513 & 2514 IA-89-226, Forwards Info Re Preparedness for Full Power License, Including Open Items Including Allegations & License Conditions,Preoperational & Acceptance Testing Status,Const Status & Status of Insps Required by MC-2512,2513 & 25141987-09-16016 September 1987 Forwards Info Re Preparedness for Full Power License, Including Open Items Including Allegations & License Conditions,Preoperational & Acceptance Testing Status,Const Status & Status of Insps Required by MC-2512,2513 & 2514 ML20237L7011987-08-31031 August 1987 Notification of 870909 Meeting W/Util in Bethesda,Md to Discuss Proposed Amend to Tech Specs Re Organizational Structure.Meeting Agenda Encl ML20195G3751987-08-21021 August 1987 Forwards Rept Re Licensing & Restart Schedules,Per EDO 870727 Memo.Info Will Be Provided Weekly ML20235V8251987-07-20020 July 1987 Notification of 870730 Meeting W/Util & C-E in Bethesda,Md to Discuss Licensee 870629 Submittal on Cycle 2 Reload 1999-08-27
[Table view] |
Text
r Ad. 9 Arizona Public Service Company
- 0 box 21t% + **10ENtx. ARIZONA 6503',
QUAllTY ASSURANCE DEPARTMENT OA Document No. 83-C-87/RDF Audit Report No.
DATE: 26 September 1983 TO. W. E. Ide F R O'A : R. D. Forrester
SUBJECT:
Loose bolts on structural steel Resolution for the loose bolts on structural .ateel found by the NRC CAT Inspection is as follows:
BPC Quality Assurance using marked-up drawings inspected the following areas per WPP/QCl 58.0, Erection of Structural and Miscellaneous Steel--
Auxiliary Building Elevation 100', Areas A1B, A1A Elevation 120', Areas A2A, A2B Containment Building Elevation 100', Areas CIA, C1B, CIC, C1D Elevation 140', Areas C3C, C3D One bolt in Containment Col. No. 12 did not have full ,
thread engagement. NCR No. CC-4337 was written.
I BPC Quality Assurance inspection findings determined the loose bolts found by the NRC to be an isolated case. This item is closed.
407mt R. D. Forrester RDF:19 l
l 8402140052 831220 PDR FOIA BERNABE83-598 PDR , l l
l
.s. ..
' ^'
PALO VCR DC NUCLE AR GENEG ATING ST ATION !
~
g, PAGE OF NO. kt/[N88
.(#
FIELD CHANGE REQUEST JOB NO.10 A07 ku Ass AL' @
3, payc 5 ##
3 3 n. u.
' F -
- s. M c F tswG OR SPLC RCV %. TSTLE / UX /UAA:7 St D4 ?~/LA Y // /r NG M '
/3 - E- 2 A C-O S S 6 t.AYour PLA N A r FL /CO Fr* LEVCL IQ
- s. Oc5 Gu OnlGini g cNGiNeca:NG 0 5urruca s'ac"7'rv av a^=ci 2- S U nit i 3 ] univ : v m 3 UNIT I _ COMMON
- 3. EAISTING CONDITION EMBED STRUT */ PLA TE A/O 'r A VA lL A };EL E l FOR l 0AIG / r u k>infA L BRACE H A A/Gl='M
/E2AIB H44 /Ne Ae A tT 4 A E)
- 9. CH ANGE REQUEST /5 KETCH APPROVE T N f W S E' pf form (4.) . /2 " P/.4.
c oNc. E.4e. AN'cHee s As gowM
{ T-. . - . .. .a . . .. . ,.... - - . .
p5 t _ \. .
o N 7 n --"
9
- . 1
- 4 ,
i
,'.(
r I et" <0"ts'rgeir +
yV g K 4 _r g .
l L X. .M&\
h ".l'.I a
a - lctcrre) i N.7' ' . * %--M-5"gf cewc.
\.- ,, ,,, , w s~s - .
. PETA /1 ..
D, ,
4 0 NG. BKACE CONA4 DTL
~'
3 HA NGEA' l FEAT B h'44
- 10. R E V I E W E D B Y : I I.
PM CP ARED SY s--
ostter6ent FIELD ENGSNE ER DATE S t. APPROV AL OF ~ TION:
- hw f/M$pt os.c e Pse ~. ,s. < o E e.G e o. E . o.v. Pao.r:v, aw. .co E E se o.ve
- n. .tCsTc t t uGiu c c aim, O o's a "" * * *
- RECEIVED Y I % 5 4 d -_ g .PP,.eavra$-do/ v's NA Gnour SUPS a vilom D A'T E NUCLE Am Gatour SUPE nveton ter a D4s- w bate Okh&eck-- Ph os t E t E NG ese t t m m' DaTS v-EP PQat as LIS E D Pte AND SeasG LE L UCTIONoav a
,I orTeoc m as neu a n n5___ AE t.n
'. ( )
D N %7 9 44 tS F io (A u s sBGt g M57 ALL tM L FMREADCB Si t_ uT 10 T W L\i M E 14%~A-L Ciiod Ol57RipOTION: osseGees aL = ement t oosepen avose s corest to - CLeENT. SklavEY. DeSCIPL90st. Aped setteDENT EPeGINE E pl ,
"""#"CT""**""""""Y"""""*" ****T"*"""'"*K" D5 M +
P7-s t as se Sect; at7 s
.w
,m y. -
hfY
~
l 4*%
, dDo CCRRECTIVE ACT10:1 RCPORT Page 1 of 1 Classification of Adverse Condition: (See Back of Form) CAR ;o. C83-135N
@ 0:CC'!PLI.V:CE
. . Deviation -
How Discovered: NRC CAT Audit !!o. @ Other Inneection O !!ot Reportable O ni r tio. ._
Orga.ization Responsible: Date Discoverec: Date Reply Due: g Bechtel 9/7/83 9/21/83 Initiator (s): Controlling Docu=ent: Discussed With:
D . M. Holt;[o 1. 10 CFR 50 Appendix B Part V.2 J. Black v'
[1 .-
/' 2_ 13-CM-307 Design Installation and Testing of Concrete Anchors G. Martin Recuiremen:: " Instructions, procedures, or drawings shall include appropriate quantative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished."
-)es:ri;:tica of Aaverse Ccadition: Contrary to the above, no acceptance criteria exists for
" Group D" (13-C:1-307) Anchor Systems, when expansion anchors are less ~ than " minimum edge" distance from existing embeds (unistrut, plate, etc.)
(Minimum edge distance is defined in 13-CM-307.)
Rzec:= ended Corrective Action:
- 1. Provide acceptance criteria for " Group D" (13-CM-307) Anchor Systems when expansion ~ ~
anchor is less than minimum edge distance from existing embeds.
- 2. Evaluate existing " Group D" installations and rework / reinspect as necessary. This applies to Units 1, 2, and 3.
Cerrective ' Action - Includin;; Action to Prevent Recurrence: (See Back of For2)
Prepared By: Authorized By: _ Date:
Corrective Action Cvaluation:
Co- ents Acceptable Not Acceptable Verification Required Yl:S NO Evaluator: Date:
'ier :i,atton:
Cc- ents Acceptable Not Acceptable Evaluator: Date:
, QAr-4A (Rev.0).
4 y
l .
j DOCUMENT ~
~'
. PAGE~ .
l PULLED
~
ANO~r2nha .e
/.
NO. OF PAGES 4 REASON O PAGEILtfGSJ. CF I D MAD CCet FnID Al PDR ose _
t J_ >_
D BETER COPf REOJE5ED ON _
7 PAGE1D0 LARGE10 AM 3 nAocoPVFdD Al PDRote
! D av.tDonmniant cnDNND
Q
' ' '--5wN r '
- 9 mince 9996 M 9 We NY Wf
~
M 8/ M ~
.0 m . 4.......
e esemen mT afv aEv ais.aeTeaE ee1aa Ja ATE peta NENTFIER Cat BATE se 185 (28 tal 449 ISI FLac OT
' WEB E l N5eenlete ITIE2JegeTyts 3 19eg03 45 13e825 198025 7906 4 000000 000000 - 3 7 ,3-< .
90825 CCI 3378 190003300130 001308001363 .
-1, Et2 821NZJC38 w e25Iett ',
E2 33tJ 1eos250
CC2 enE 7 ,0st40 P MJ -
CC2 K2 swa m e:04e )
CC2 37K sty 330 sew 130s250 7
CE2 3103.33 1909070 CC3 C m E4 E tW C553Ct!T elv000 CC4 ECit=C7:stio Giv000 _. I E4 BCipC718C2O 88v000 I CC4
3 E4
- ECitaC579CIO 01v000 CC4 BCit=C579C2O $14000 )
CC4 BCit0C599CIS Dtv000 N CC4 EttpC&2KIM tiv000 /
CC3 K185171KtXS 01v000 K4 ECitt!?!K2O 014000 i
E4 3CIAstiMing elv000 CC4 BCitSI730C2E8 Giv000 CC4 (Cit 31750CIIS 019000 CC4 ECidpC47BCIS 419000 E4 ECitDenKle elv000 CC4 ECitstS4KtO Stwoo CC4 EC?tal?tKtK 01v000 CC4 4
!!,!.!,!,!!'dII' Kt ,K4K elv000 ECitEW54KIRA 019000 M/4"7d M' CC4 (C1ES195BClRA Giv000
.CC4 ECtE31868CinA 089000
.C4 ECIESIP*KZMA 01v000 -
E4
^
ECitMf41KtEA titn00 ___
CC4 ECitKetBC2EA DlWC3
[*4 ECitsCA60Clut elv000 CC4 ECitW53KINA 01490 CC4 ECitK729CIEA 019010 K4 ECitgG729C12 019000 E4 ECitE123C2xA 01v000 CC4 ECit90723C27", Olv000 CC4 8 Cit 30723C3mA Div000 1
CC4 ECitsenatso tiv000 CC4 ECIIEG72WC4EA 919000 K4 Ettt9072BC4 4 OlWOO CC4 EC (31750C2O 014000 )P CC4 EtttDC23CIS Olv0W / [J *
..CC4. .... ECIL30573Cita 019000 CC4 EttEM5e8Csn'.OnV000 CC4 ECitW 50uCt p OlvC0C CC4 SCllM500ClK 019000 ,
24 SLitt0030CluO 4tv000 *'l CC4 KIE5003BCIe 0I4000 CC4 gEttm3sC2E elve00 1
J CC4 K183003sC2W 01v000 CC4 KIE9003BC28 etWOO 3
L 5
_4 i CC4 Kaf;30!WC2*.4 LTJ000 i CC4 BC O w3sC11! 019000
- CC4 SCit900'sC23tJ G19000 Kttet NC22 0'1900
'.'a CC4 CC4 BCaf43fC2ML etWo ' '
. ~
CC4 E*Fato3pC2m $19000 . -=Lch >
E4 K;2Wo3"l2We014000 , ,,
CC4 KIE3194stte 01v000 ,','
E4 BCIER1523Cl 5 014000 24 Kip 1520C2O elv000 .)
CC4 BCle :5:x ze elveet c; E4 EctssC3' Kit O'J000 p2 '
' * 'I' CC4 K4 ICLESGetKC=C rxC=i i. .stve06 1
- Ct3 Etttt045KIEC Siv000 CC4 Kak 06MBC2xC 019000 CC4 StittG M CIE 01v000 CC3 T , ,
CC4 K?f9E*4Klf 019000 - CC4 ETit2J#99txv5 051000 -
CC4 8"ttSS740C7NE 019000 CC4 ETit2J23PTYCA 05f000 FIL.L CAlta 6.7 1 *LLap 40.0 1 PtuxT FILL 041593 CC4 BCit3G7472W 019000 CO
+
CC4 f41tpC64KlO 01v900 l CC4 FCIERC748CIE ele 04 ' _fkTER CtpP!MNT IKh'fr ggg, I CC4 BCit2901K2O 4tv000 >
E4 dCIIZ W KI E elv000 A '
- CC4 j ECit290!K2W 019000 "5 Stifts;18C2h4 Olv000
\ CC4 EttL?9019C247 entW l ,
- /
[* gr~
n4 752 q=%?
z 1
)
2 s H-k,
- 3 D D ..
M f h. N
'7 M
4 7 t. x E E
N9 F 'O a 4 a .
1 T h
&A Z E A I*' R r C - c s A f R s 3 t s D 0$
/
O"N "
E C
a W
s v n /e a o - ]r. * >
w 7 H C 3 ^o
,A 5 J o e 4
k 2.U" 8,$TA '
t PE '
T N E
R R
vr o
7 A r
e s &
m r
c a x d
C s.,
).
s a kb
'cb# s O
/
/
n ""
4 c #s
} E.'A O
oM S"
U C c a d t'
s c
t e A-
o h YR Y i s_"L f
c CEAA N
r k s- s E p .
7 L/
7
/B
(
C.A ~a 1
1
'aC O
R L c C H
O e
r -
+d x
P M
c a
p 5
W /
W E A **
E /
IV R r s "
^P V ~
~
T. CC 7 .
E E a o r e
r t s A D o
E 't V A
- g. O R nu h N~
N o'
N I
J, R,
'2 d < r a
\
A P AN
,OT C G R 1
L O ?. OE h ,T*
I N J o Y > O c
(
4 h
R A~
C Q,A C H c O L2 ME r' P S
E D
J e
t s r
~
7 r
D
)
I d
r u r
d a
C, s.,
L
'v N: /s n t 2
l4
= E A7 OM O' u -
A t-f h 'O /i h3 e T rc
(
O MI .
E R ne i e i I E 2 t
f A D EA. D J
H
,_ T C o TX L P m
e lll2 A N
O. "'
N >
N S7S c c 4 D O U E x
k d, t
i V
5 1 E D
T I a
- [K t e f ~J /. L A
R u L
S I
- r. a w, s ,
~-
R u E N s V ;
d d U o t n -
i S. T E O z
i E C C T A H M P S - T C r - a D r.c
~
/
2 Y D L
N A-C r s_
R S E M
O NO S
e d M -
) e h T A I
O C
O B C I R O s < a 1 J L L T D
$ r e d R N -
E P /
ETE Q
\ IB R E ) R RIS E h_ r u s .-
L A O P -
O a V ZR IO R A E s i t T E
- I N RT DOI N e r r D~ A E
C N
k f'l IL P
P U c LP G E
I I FOE S N ~.
n e
a u
S N
C d
t a-w e e
r 3
~
c r
9 0 R R O
pOR T
TIS O
P S
E' D
OC HE TP US V R sr QO G *
. pW n T A S G -
.NO N 1pC AI C
n b F E 5A
/ L - a C. t ID ?
M a E c -
R N A G ar llA h P P 8
O OH s JA [L
. 1 O I T 5' T 7 1
- i t W l F P I C A c W'1 g N O
I R
Rs N b
C N
C S
E S
l-NB T
O DR OI LGS E
T
~
^ 8 O
N D
M C
8 U
EN IC FI EF
. O A
D d = ~
E 6 W e \ !
T l C S. 5 E f ~
N I
Q a
h V
4 N o S E /
l f V /
A i
OI R E V A S A T
/
R 0 TI D J/ /
E A N O y A N
O E 'G F- & f~ D I T
D C EE A W
k / 7 N T E J 7~ D I
O I
N E
7 B A D L A
A 0l T O V A
A E C C J E E~ /l !" S
.35 N R N -
[]
t-i "N T
S O
N 0o
- i L.A" e
P T
E Q~~
/
A O &' s 7 O I
T
^l D (
G T- h M V o f n i.
C j S E A
[ N I
T R
A C cC P T. T.S .
Q E
AT O C L. S
~
5A 2 ~
Y C
o h A R G'2 2.
8 R C
/
/ Y
/
S N I
2 ^=
N A
~~r 7
/
D E
N I
- O . E t - 5 1
- P E
L N W- N S R i
/ L R A f
AC- E5M aP
/ ;
E /
K C S
U G R G W
5 i' o A 6 L R - S I
M R
O D3 3T e /
T R 3 / f S Y s D
D. A S < % OA W
D F S T
A T
A A E
R 2 P S i S C
L P&
E i S-7 E \
R/ O P I
T A
I S L - P 0 sF E N C Y $U T- N J 7 ) ; GO S I R)6oa%
Y G U U O Y B lGE R R A
_ N AD f / A mO I T
N D 'r E C a C T P E E D eN N B
E E D ,
S i 6 $ E I
_ O R INR A R e E
- s T P E T T oD . y C
A /S A N C TD .
R E
M.
2 l 7 S
S E I S R ~
7 Cn F' d 7k R O
P imE P
ENL e, S U
M .
V O TI N lC o S
A L
DLO 2
8 J E (- f E
R 3 . JC. oo .
C A
9 C e O
S A
4
_ U ,
O 1 1 1
6 Eu /
_ 1
i dn ga1, '
o i.
t
, a e
g f r~ N c C A rs 6 g*
m u i /
3 "o *x e s- A W i i
T 7 /
!a D
a Y Y l~ M
, 1 A
g ,
g y.,
5' r
s s.
ct 7
C D p C c W-c M
(
e i
9 { o Xe o V 'N C
f g a c
i g Y c 7 4Q a a )o c ro s
A
~ f g cT r
s y U s r.
7 A
3 y ONE r r ~
s s
a a
n g e. L .
o d h[Q N
NE O RI M
w p
ot ri r d.
a.
s u
C t
A n
Z x, h O I t.
c c.
s T U a d e.
d T[ S Q I
A J.
r fA A a e )
'm T Ch O P R E
h d< U a
/ c 8 c
O R L N S E '
' s ] e
s f .
N O
P M
E DE N " -
a.
L.
s e
s M CI W (S
^L T
U E I.M S
E R DR .
A c A a. A e s A
z i
R E
NU E C ' e MN ~ x t 7 a n s e
A C..
- r. r r.
c VA C MO c C. d o a 4 i.
E B N A
OC C R T7 E E F4 b s
A n /
y a e 0 W ls a A
~7 RE D' 7 r A- o. s s m M DN A e t A
R L E G I
" c. e.
c r.
s e ni E c O
F w
c, I
F N
E E c A 9 -
8 q
u P 5 c L 6 .
.O "*"' W W A N
Y c &
1 a N o D T f $ T i
O 4 7
'7 as C C
N
/ 1 y N s.
O O AS N NA O
t OR S I
I g(, Y P M E LGC INL cZ RI FEO s C C .
a h 5 f
E DO MA TI C
C 6
1 4
N V&
E O
I M
T A N T O S
I Ta O
G N N l O
C I
T 3 T o T
E A O N E
E R N T
". S E
E H N R
A H
P S E P
/
T N G G N* .
M .
8 - Q O R W g E R .
I A *.
T A R C A E L
O Q,.
E P
3 S U C R 2
/
G N U V [ N D W ,
I N O .
T Y .
A ? T CSP I
- ,. N E D 9
7 .
PI /
- O >D R O R O 4
)
M 3 SC :N 7
1E 0 E NR 4 V 2 D TD S E 0 t
l
.S 0 t f
a s LO IR I.
4 e '
. 9 N l 7 %
- . p
-. U 8.
4h F P
\
~
e \
o lAks' #6' 3 059 BM k
<?
i @ ] N-
- a. ,PS -
i!i /fEISBNTRnB i /EETRAAfsan AlTSAO
$ ATRHB --
A)TS BB e ATRt/A NT$Rc sifVB A/15B D ATSHB
.: At150A ATsVA -
' AIT3CL '
_AIS VB NTSMA ArrBy -
, AIT).yB ATXVA -
AlTS VC-AIXVr NrSXo ATt'8A -
NIZAA _
_ ATWR NIXAO --
RTVAA --
NIXBB
\i 'ArVH8 -
NTXBL inzrsnETABn AITXCe BTRRf -
l M T1 k'A
_ __8726 B . NZX1'8 Braca- NzxRC -
-- -8 tags - N TX VD R75BA --
NZY.BO Buce _
a NTYLA Brsco NN HZXfB_.
BTYBA
-BTVd R NYRAA .
- N.TRAD A.![R8B i
I $[khY NZABD 16 .
MrAce-MTRVA bl)
N TR t/8_ _. - - _
~
~ ~ ~ , ~ ~
__ __gr .
...__ a n w : .. .
. .UJAil
. - _ L- - - 011t 3Wil N
I' 't _ _ __
'\-
. Al lZ feJ /759 h
- /dn
- in' h/Jro.r/rss4 .al' Bvure.- /;r.cm en-/
3 /f/az 71~12ec r, cuss 4 e ff.
l: lMstrcrru g w n-S n7s of, As /?rQ u s ac rp ,
a g
l t
l l h44 wn e.t Ccwfocorra ro 7-Hf f r6Wi.csv/svrr f
.cf D'izo rn smisusnw ws cru cssi r 6
i
/A s N ,
m
' T i .E i
E.
2
=
oz 1 ! ?
20 o O 2
, C m z , !
l 29 '
y A
l
" m iomt e -
1 I
' f, p !s
- - ..- .- .. .. n .. ..,= = ,
( .
PALO VERDE NUCLE AR GENER ATING STATION PAGE I OF PCN NO. 6h UNITS 1. 2 & 3 3, PROCEDURE CHANGE NOTICE (PCN)
JOB No.10407 C WP/P 0 oCI No. 5.0 ggy 23 Nonconforming Materials, Parts TITLE:and Components CH ANGE REQUESTED BY: CQA DOC OPE iNir ^TED av: M. Rosen
- 6. RE ASON FOR CH ANGE: unminnend by ('lient-OA en antinfy nn b Yok'ceN .
- 7. DESCRIPTION OF CH ANGE:
- 1. Section 6.0, renumber existing paragraph 6.6 to read 6.7.
- 2. Section 6.0, add new paragraph 6.6 to read as follows:
6.6 Rework and repair dispositions requiring removal and or disassembly shall provide adequate instructions for re-application (i.e. coatinnt u essmety and or re-installation of the items as VP lienhia- --
W 9.es'+1 l 8. APPROVED: ,
/ i
.b k () b !/l);o PeOlAd bb I '"F/ ~ (II PQCE 'D TE / D4TE
.b -
F 1 m /f x /
'A E Vltflf3 DATE h0 M CCOCE 9
DA1t OM III *
- W/
. ____ _ / H i -___
I s ..
'dM *r .,
ma,,c,,*oa p *** U.S. NUCLE A3 4 ECULATs4Y COwouulON Crout313 ms adAstsNG ADDRES5
- c. .... o r a e rT
,l . , ,
1450 FARIA LAME, SUITE 210 c sv y FACSIMILE TRANSMITTAL lstAit J. .,' k'AlliUT CRED; CA REQUEST
~
- pair at usigof,ea Ak A 4' ' #
,d i. * ) fi .
] vse p ado MESS AGE TO P AC98888LS Paohs wwwoan ve sse statsom puomo asupe s e wama Awo osesAnssaatsow b '
sh C ( I m .
w cerv lsvava autopAvec ,,u ] 'e or ,aese
,, , , , _ _g..e.
O! ' ' h * '
] was No MESSAGE FROM .
- wams jra6senonseso. ratstoa:Lt puo ws esu w man -
vt atFIC ATION TELtrHONE MuMDElt
-. nean sesse (we e. e J Lo . sere o dee==e=.6
%.. . c. G ^c s 3s d - .
4.U s LD s NG guasL STp AUTowATsC AU Tome ATit REGIDW V . l. 7, RAP 1 FAX 1 "*
3M PRECEDENCE l ovenweset? l l Foun odouns l lTmWNOURS l l opes eseum l lswwsosatz wassak tworsivtYacN5 KEW m'EE
-L ER - eR krnweet.
h4M/4NMM :
I SEA /Jr/A/d MV8.T eactsvto Tnanswerreo l p4 I
I e
4 1 -
e O
I
{ '. -
l ..
/9/
u .
r _
. , 0 ^-.
e ::. w r--
. uut.2n k nsa.wa g .:w. :;. ..m t. 1 L j . j,_1._j@ - m t ot ..... . ,,,t u t .. .om . m uom
.a. . . .
4
. 1l
..E J..l.iJ3J.t msm -.Ll IGL..a LoJ - I a .I a .u Ia a .,, I o. I o l- I a I o l@l.41..c.i I i 1. i .i 11GL.,
,. . l_J.G
%. .. J. .
~ Q, D I tJ- @t of s t ol o 1 o f 21 o I 5 @jo_lo l' Is la @t 8=i ofn.1181 a l 23@
. .a u =
,s- ;
. . .. .u . . - . . . .....
tvt43 041,CMPisO4 aka PeeOsatts CON *. tout 4tts h
? .l'ene.ing lines on all sta contain cat pressure t ransattters were few d copped of f im*Id_.J n.. . j j . . ant a i n wr.t . - This renJered the t ran. st aters inog crable and put the plant outside C f Il g'
' '[ L.C.O. 7.s. _3.5.c in that the z.Inisen et.annels required for ht-contef onent pressere
' . ..s ,
.?
g safety injecties actuatten and hi-hi enetain. seat pressure for centainment spray and j '
g ste.a:n line f zolation were esot available, tedundant instruneet.ation forjafety _
,j g anNerson and steam Ifne isolution res.afned operable. There was me forect te hblic _
j y j health'or safety during the period the transetttters were imoreraile.
~
[
' O - E3 Sv9,t a. C au.8 C
Du C0ptust CTI P v.4vt
' . . . C ODE COO ( Co.dPoetut Coat 9VV. Cat S.sa cu0t
,. - 1 si Al@ L..AJ@ L.U@ I 21 si s171 al vi@ pj@ lIC 1@
ye a oui . . - .cc,. . .ca v==
. L t # 87., a ve es, etas
.. ascoat se cong twe .ra
- - @ ,al,;;,1 la 121 r =(_) lo 131o I .(-) ol:I 7 sL.-3 f ._J a..,+ , . .
=.m m
-: i-.= c.
,,v,2,.. .
. . . .c, .
.ua.. ,.
.te co o m.e ..r.ne.,., a.
.. .m en co
-.c w.
K... )lEJ@ as . Lta. J@ [zJ ,
a @ a,0 lo lo I _I 1.
. e
(#
as j@ [.EJ @ l.aj g is IoIa foip es
-- camt c.tscatessow a40 consitcTavt actions 27 ' '. ..
,)[P,er1Erth'e i.er cer4nce of local'le'P4'rrte'tritt,DE_leat refyrDr_ rees vree inchyrtStid Ifv'elseed en the' emte df ti e, t sens!'nilines. There cen<(nr 1 Tere cent str.d 2fL- LE.h_ }
- f Suarc-1.nk if ttings sir.fler to all other vents eso drains store.Ily required te d es nn i t .. ,
[pubsemuent to lest rate' testing. Cepr' were 1.stediately ve::eved. Ti,e local Ir.at ratej
- ,' ttestin;:
prorei ure will Le upgraded and the penetration. teges to prevent future occu-*.N:
f g -
se
- '#.'@ : vs.. o, insnevs h EEmS .co<ein psic=e.,w
- j. l EJQ j 1 l 0 j 0 gj NA
, ] {Q Centalament Eatry st Operatc Feguest l
.c',..., < edia ns, ** ** *
......n--...... . m. m .,,,.,o. .... @
l.,Zj h lZJglt;A ,
..... .., @ l [ FA !
. .sasown r.cos.,at.
.. .. . ~
I of of 01 3[. 2j S[m ,,....c, NA
__,_l d*,,,fi..
,,,co
. - . . o,,..
..me .
I of of 0181.,SA ,.
1
.oss s',*
oa o.
- eavaca se e.c. tier g 82202e n o e 'i*f ' s b 4DC[u 8210ta -
a a
I - . . - . . - _
~
u.s. NUCLE AR LEGULATORY covm66 sow , Ltcut seau-8 asuuNG ADOZEas gy,,,o=%3+. .....,
' 1450 FARI A L A';E, SUITE 210 CST, lSr.T. '=
FACSIMILE TRANSMITTAL '*At!iUT
- CREEK CA REQUEST o.,s == , v gg,.,c; 4 i o >;
t
..u *ii t e..., c i m ai t ... =. m. auw
- 1. . j 1. J J._J._.J. O
.E1; h..uh. J.tlij@l..nJ
.. . oJ - I o I o..uI aa 1 ..,o Iao- l- - I n I o.13 4i111ili10L...LJ.G
..c. . . .
! o
- 1% 11Gi f)J.oj.oJ o o I )18 I 5 Gil.Jo_19 .....
Id Is la -@t =:1 ol il sj a 12J@ . .. =
- .. m . t . -.. . -
yis.104 s,tiori.04 440 rhosaett cowto.st%c15 @
j 'en in_f. I f nes on all sis containm-nt pressure t ranssist ers wer e fewend capped of f ,1ce,!!_$ t E.
. u s e i ne.c r.t . Tnis renJered the t ranssitta rs Inog crable and put the plant ov's !de t f l 4 l
T.S. 3.5.c in t hat the minimes channele required for h!-sontsic=ent pr es sure j :
1..C .O.
I'
( safety injectica actuatica and hi-h1 containneet pressure for ce'ntalmrefit spray a*f _j } l _
l ste,a= line isolation were u.at available, tedundant inttruneetation for,pefety . . ;.
_ _j
__ g
' an$ect ion and steam line l'.olation res41med operab1e. There was me f arect te paalic j I,
=
health or safety during the period the transmitters were loopera'ble. __
[
as 8 71,18. caust tawa tre.p v4vt 3l 4 OC4 code 9485 *0pt Cone'04,4mf fese S .m *.C.Dt 6.st tuot I. s l ^18 u.. j@ t,,*JG .i ni =1 si ti al v lO LU@ @ L]
u = =u .cc . .ca . =
y,,
4V8ef'Ea.
n atcoat aut sect Tm.te ==.rt ! l
$ ,*a' ga
,,7,7; la121 n
- [_J n to 13_fo l
. [d, tol l
[o
, J i i ,
b m_ri .:: = , r,= _ e a w 4 .-:. , = ;r. air,ma L I
h]a=Cl@
yg h
y@
a a l0 j0 lo l0 l es e
@ [e EJg W@ e la1]018to}{ as fun.t C,ts:asersoN an.D connectsyt actions I r9r the utferv.nce of local leet rrte tes tlDA l'.".Lif f.yr11pr_ _t t.L* vr t e in* #Te E !d -j ,
!fv rirred on the ende of thg, tene.f or_ If eer. There pena tor 1tr're _ ccr;t s.tr'y1 3fE- idu d 1
I )
[fwart-14 fittings sirflar to s_11 cther vents av.d drains r.ote.13y required ta E ca nri s 1
.i rubsequent to leak rate testing. Czps were instediately reseved. Ylee local It a'- rete _.,,,j i testinr procedure will he unraded and the penetrat tens togtes to prevent it.t vre e-c u- .:
ei.
a % PNta 01.dl A lf afu. 9 9 Darth tmMp.rgne pg.twisps
_ij@ 1210 f o l@lwA s I ( A )@t cc at =5 =aat 8atry a! o rrraten regout _1 g
O' . = . , .r (o% 8iem9 '$
- . .. c. c. .n i n. .ou, .c,..... soc .,,3., o. ,, . .a @
_u e t..zJ 3 p.. a @J ,.
i s^
- f M D*,-( t f . rDS.,a t l j'
anisme6 f A 1 * *( On.eiat t ats%
ot o f oGLjS! NA _ _ _ _ _
a*
l ;}
,, ,w. d'.s , . ' '. n
i; ot e ..e.,@ !.
of ol ol@}.. NA j M r
fd G25 Os 04 be***G4 'O #4CettiV 4) 7', d " *[" ( Qfhak@Jona, AD *
._.