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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20207H7621999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20207H7561999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20205L8421999-03-31031 March 1999 Rev 2 to EMF-96-125, LaSalle Unit 2 Cycle 8 Reload Analysis ML20205L8391999-03-22022 March 1999 Rev 2 to 960103, Neutronics Licensing Rept for LaSalle Unit 2,Cycle 8 ML20204H9941999-03-0303 March 1999 Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20207H7671998-10-0505 October 1998 Rv Weld Chemistry & Initial Rt Ndt ML20236U4751998-07-23023 July 1998 SG Eddy Current Insp Rept Cycle 7 Refueling Outage (B2R07) ML20198J5061998-01-0707 January 1998 Pressure Temp Limits Rept (Ptlr) ML20198J5201998-01-0707 January 1998 Pressure Temp Limits Rept (Ptlr) ML20198J5531998-01-0707 January 1998 Unit 1 Pressure & Temp Limits Rept ML20198J5641998-01-0707 January 1998 Unit 2 Pressure & Temp Limits Rept ML20198P6591997-12-31031 December 1997 .0 Volt IPC Full Cycle Operation Technical Basis Supplement to 'Braidwood Unit 1 Cycle 7 Interim Plugging Criteria Rept,Aug 1997.' ML20199E8751997-11-0303 November 1997 Revised Byron Unit 1 Pressure Temperature Limits Rept (Ptlr) ML20199E8801997-11-0303 November 1997 Revised Byron Unit 2 Pressure Temperature Limits Rept (PTLR) ML20210P8611997-08-31031 August 1997 Cycle 7 Interim Plugging Criteria Rept ML20217G6171997-07-22022 July 1997 Operability Assessment Process Form ML20141K0181997-05-21021 May 1997 Pressure & Temp Limits Rept ML20141K0241997-05-21021 May 1997 Pressure & Temp Limits Rept ML20141K0371997-05-21021 May 1997 Pressure & Temp Limits Rept ML20141K0431997-05-21021 May 1997 Pressure & Temp Limits Rept ML20148P8811997-05-16016 May 1997 Spent Fuel Rack Criticality Analysis Using Soluble B Credit ML20141G6361997-05-15015 May 1997 Interim Plugging Criteria Return to Power Rept ML20141F7141997-05-15015 May 1997 Operability Assessment Process Form ML20138H0001997-04-28028 April 1997 Locked Tube Tts Circumferential Indication Root Cause Determination Evaluation ML20134P8911997-02-18018 February 1997 Assessment of LaSalle County Nuclear Station ML20134M3131996-11-13013 November 1996 Revised SG Tube Rupture Analysis for Byron/Braidwood ML20134N3131996-10-31031 October 1996 Sys Design Description for Containment Spray ML20134N8011996-10-31031 October 1996 Spent Fuel Rack Criticality Analysis W/Credit for Soluble Boron ML20135E6951996-09-30030 September 1996 Rev 2,Addendum 1 to Safety Review for LaSalle County Station Unit 1 & 2 Safety/Relief Valves Reduction & Setpoint Tolerance Relaxation Analyses ML20129F8921996-09-30030 September 1996 Circumferential Indication Summary Rept ML20129D4081996-09-23023 September 1996 Final Rept on Foam Morphology & Transport Tests for La Salle Nuclear Plant ML20129D4141996-09-23023 September 1996 Foam Transport in La Salle Svc Water Tunnel ML20129G3881996-08-31031 August 1996 Unit-1 EOC 7B Interim Plugging Criteria Rept ML20116H1461996-08-0101 August 1996 Cycle Length Assessment Rept Addendum ML20116B6011996-07-0202 July 1996 Rev 0 to Addendum a to Piping Stress Rept, for Unit 1 ML20113B0951996-06-30030 June 1996 Interim Plugging Criteria Return to Power Rept ML20112B8521996-05-17017 May 1996 Cycle Length Assessment Rept Suppl ML20117J0491996-05-0808 May 1996 At&T Round Cell Nuclear Util User'S Council Charter ML20106G5891996-04-30030 April 1996 Training Dept Braidwood Simulator 1996 Certification Rept ML20107K8281996-03-31031 March 1996 County Station PRA Summary Document ML20101E7651996-03-31031 March 1996 Unit - 1 EOC 7A Interim Plugging Criteria Rept ML20100R7371996-02-29029 February 1996 Cycle 6 Interim Plugging Criteria 90 Day Rept B130178, Demonstration of Compliance W/10CFR50,App G for LaSalle Unit 2 Plate Matl1996-02-29029 February 1996 Demonstration of Compliance W/10CFR50,App G for LaSalle Unit 2 Plate Matl ML20135E6881996-02-29029 February 1996 Safety Review for LaSalle County Station Units 1 & 2 Safety Relief Valves Reduction & Setpoint Tolerance Relaxation Analyses ML20100L3551996-02-29029 February 1996 RPV Surveillance Matls Testing & Analysis ML20095G0691995-12-31031 December 1995 Interim Plugging Criteria Return to Power Rept ML20096D1181995-12-22022 December 1995 Course of Action Progress Rept ML20094K6101995-11-30030 November 1995 Interim Plugging Criteria Return to Power Rept ML20093G7171995-10-12012 October 1995 Rev 0 to PSA-B-95-18, RELAP5M3 Comparison of Model Boiler 2 MSLB from Hzp Test 1999-09-29
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G9961999-10-14014 October 1999 SER Accepting First 10-year Interval Inservice Insp Requests for Relief for Plant,Units 1 & ML20217C9121999-10-12012 October 1999 SER Input Authorizing Licensee Proposed Request to Modify Definition of Core Alteration in Section 1.0 of TS & Update Sections 3/4.1,3.4.3 & 3/4.9 to Reflect Proposed Definition Change BW990066, Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With ML20217F9091999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for LaSalle County Stations,Units 1 & 2.With ML20217H5221999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Byron Station, Units 1 & 2.With ML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212A7441999-09-10010 September 1999 Safety Evaluation Concluding That Alternatives Contained in Relief Request 12R-07 Provide Acceptable Level of Quality & Safety BW990056, Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With ML20212C4501999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for LaSalle County Station,Units 1 & 2.With ML20212B9261999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Byron Station,Units 1 & 2.With ML20210R6421999-08-13013 August 1999 ISI Outage Rept for A2R07 ML20210U8111999-08-0404 August 1999 SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval Because Relief Applies to Valves Not Required by 10CFR50.55a ML20210R0671999-07-31031 July 1999 Monthly Operating Repts for July 1999 for LaSalle County Station,Units 1 & 2.With BW990048, Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With ML20210R3431999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Byron Station, Units 1 & 2.With ML20210K9861999-07-30030 July 1999 Safety Evaluation Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20210E2251999-07-21021 July 1999 B1R09 ISI Summary Rept Spring 1999 Outage, 980309-990424 ML20216D3841999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function M990002, Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function1999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function ML20210C1681999-07-0909 July 1999 Seventh Refueling Outage ASME Section XI Summary Rept ML20209G1751999-07-0808 July 1999 SG Eddy Current Insp Rept,Cycle 9 Refueling Outage (B1R09) ML20207H8071999-06-30030 June 1999 Rev 0 to WCAP-15178, Byron Unit 2 Heatup & Cooldowm Limit Curves for Normal Operations ML20209H1501999-06-30030 June 1999 Monthly Operating Repts for June 1999 for LaSalle County Station,Units 1 & 2.With ML20207H7941999-06-30030 June 1999 Rev 0 to WCAP-15180, Commonwealth Edison Co Byron,Unit 2 Surveillance Program Credibility Evaluation ML20207H7851999-06-30030 June 1999 Rev 0 to WCAP-15183, Commonwealth Edison Co Byron,Unit 1 Surveillance Program Credibility Evaluation ML20207H7771999-06-30030 June 1999 Rev 0 to WCAP-15177, Evaluation of Pressurized Thermal Shock for Byron,Unit 2 BW990038, Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With ML20209H3711999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Byron Station, Units 1 & 2.With ML20207H7621999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20207H7561999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20209E1431999-05-31031 May 1999 Cycle 8 COLR, for May 1999 ML20209H7481999-05-31031 May 1999 Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2 ML20195J8001999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Byron Station,Units 1 & 2.With ML20195J7871999-05-31031 May 1999 Monthly Operating Repts for May 1999 for LaSalle County Station,Units 1 & 2.With BW990029, Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With ML20207B6481999-05-25025 May 1999 SER Accepting Revised SGTR Analysis for Byron & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations ML20206N2071999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for LaSalle County Station,Units 1 & 2.With ML20206R6991999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Byron Station Units 1 & 2.With BW990021, Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With ML20195C7961999-04-28028 April 1999 Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A) M980023, Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A)1999-04-28028 April 1999 Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A) ML20205L8301999-03-31031 March 1999 Administrative Technical Requirements App B (Amend 26) LaSalle Unit 2 Cycle 8 COLR & Reload Transient Analysis Results, for Mar 1999 ML20205P7001999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Byron Station,Units 1 & 2.With ML20205L8421999-03-31031 March 1999 Rev 2 to EMF-96-125, LaSalle Unit 2 Cycle 8 Reload Analysis BW990016, Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With ML20205R2721999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for LaSalle County Station,Units 1 & 2.With ML20205B5091999-03-26026 March 1999 SER Accepting Relief Requests 12R-24,Rev 0 & 12R-34,Rev 0, Related to Second 10-year Interval Inservice Insp for Byron Station,Units 1 & 2 ML20205L8391999-03-22022 March 1999 Rev 2 to 960103, Neutronics Licensing Rept for LaSalle Unit 2,Cycle 8 1999-09-30
[Table view] |
Text
( Q.P. FORM 18-1.2
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y Commonwealth Edison Ccmpany DE.Wei
(~ QUALITY ASSURANCE MANUAL -
AUDIT REPORT GENERAL OFFICE Type Audit: / / Program Audit M Product Inspection Point
/ / Records M /Special l
To: J. R. McFarland Project Byron /Braidwood Visit Date 9/29-30/81 Report Date 10/2/81 ,
Environmental
( System Qualification Component Identification N/A
! Material Description Electrical Eouiument Vendor Sargent & Lundy Location Chicaro. IL Subcontractor N/A Location N/A Contacts J.D. Regan, B.G. Treece, L.P. Dolder t P.O. No. N/A Spec. No.F/L 2773, 2804.01 Recommended Inspections: 6 mos 3.mos 1 mo Other: As recuired Notes:Please respond as indicated herein by October 28, 1981.
Auditor Date /0/g!#/ , ,
Rev ed -
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-) h Date/0hh/
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ng cc: Manager orGA /4-6-8 / I
-b o Manager of Projects 50' Project Manager
@@ Eng. Manager mg Director QA (Engr.-Const.)
h6 Site QA (Byron /Braidwood) 00 Auditee 0"c Sta. Nuclear Engr. Mgr.
$m Exec. Vice President gh Asst. Vice President V.P. (Nuclear Operations)
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( COMMONWEALTH EDISON AUDIT OF SARGENT & LUNDY September 29-30, 1981 :
The Commonwealth Edison General Office Quality Assurance Depart-ment conducted an audit of the Sargent & Lundy Byron /Braidwood Project Engineering Group on September 29th and 30th, 1981. The audit was conducted at the Chicago offices located at the Mid Continental Building. The scope of the audit was a review of Sargent & Lundy's evaluation / acceptance of environmental qualifi-cation documentation of Class 1E Electrical Equipment for Byron /Braidwood.
The purpose of this audit was to verify the conformance of the Sargent & Lundy review to that of the governing document:
NUREG 0588 for Comment - Interim staff position on Environ-mental Qualification of Safety Related Electrical Equipment.
The NUREG provides NRC positions and guidance to be followed for the environmental qualifications of items to the IEEE Standard 321, " Qualifying Class 1E Equipment for Nuclear Power Generating
\ Stations." The applicable IEEE Standard 323 printing date of 1974 was used since Byron /Braidwood construction permits SER were issued subsequent to July 1, 1974.
The pre-approved audit checklist consisted of ten (10) questions from NUREG-0588 and one (1) dealing with the status of NSSS supplied equipment qualification review. The first ten (10) questions were generic and were asked of a sample of balance of plant Class 1E equipment. Equipment selected had different qualification zones both inside and outside the containment.
Of the four (4) specific pieces of BOP equipment chosen to be ackages available for audited, review. Sargent & Lundy The audit showedhad that two (2) Up~/1 containment electrical only penetrations and RCFC fan / motors had been reviewed to date.
The review of NSSS equipment qualification was found not to be done under the scope of Sargent & Lundy's contract. This work was let by CECO. to NEQ who will perform an umbrella review of all Class 1E equipment for Byron /Braidwood.
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a CECO. Audit of Sergent & Lundy Septcmber 29-30, 1981 Both RCFC fan IVP01CC and neutron monitoring electrical penetra-tion qualification packages were examined by the audit team. The RCFC review work was in process and not complete whereas the Bunker Ramo penetration package had been reviewed and accepted by Sargent & Lundy. Of.the twenty (20) audit questions asked, two (2) problem _a prdiscovered. --.---
The first deficiency dealt with the complete and accepted electrical penetration 2NR04E. Contrary to NUREG 0588 Section 5(1), no description of the test setup and instrumentation used was available.
The RCFC package w~s a clearly in process of being reviewed and accepted. Careful inspection of available correspondence and checklists showed that four (4) attributes were not in the qualification package. This deficiency is in the fact that the open NUREG requirements were not being tracked and corrected.
These two (2) findings in the area of 1) lack of testing setup /
instrumentation description for electrical penetration and 2) lack of tracking missing performance characteristics, power supply variance, testing margins and testing failures are detailed in Appendix "A" of this report.
Overall quality of the review performed ~by Sargent & Lundy on I
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these qualification packages is acceptable. The areas which were reviewed in the audit and found acceptable were: methods supported by test sequence of testing, radiation environment, aging acceleration rate, caustic spray and developed test plan.
A project instruction with checklist is to be used in the near future which incorporates virtually all of the NUREG 0588 attributes.
The performance of the audit was as indicated in Appendix "B" (entrance briefing, exit debriefing). The audit team appreciated the cooperation shown by all Sargent & Lundy personnel involved.
l Sargent & Lundy is requested to report in writing to this audit by October 28, 1981. The response should indicate the corrective action taken, the action needed to prevent recurrence and the date of implementation. The response is to be directed to:
Mr. G. F. Marcus l Director of Quality Assurance Engineering and Construction l with copies to:
Mr. R. B. Klingler Mr. T. R. Sommerfield
( QA Supervisor QA Superintendent Byron Braidwood 1
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- APPENDIX "A" FINDING #1
Contrary to NUREG 0588 Section 5(1),.the design qualification report for electrical penetration 2NRO4E, did not contain a description of the test facilities (test setup) and tastrumenta-
- tion used (including calibration records reference).
Discussion:
A review of Bunker Ramo report #123-2220, Rev. 4, revealed that there was no description of the test setup nor was there any mention of the specific instrumentation being utilized.
FINDING #2:
,- Contrary to NUREG 0588 Sections 2.2(7), 2.2(10), 3(1) and 5(1),
the Sargent & Lundy review of Joy Manufacturing environmental qualification report is not adequately tracking unresolved items.
Discussion:
Review of Joy environmental qualification report X-604 (3/20/80)
( by the auditor showed various deficiencies for the darrier RCFC unit IVP01CC. Correspondence between Sargent & Lundy and Carrier Air Conditionery Co. dated June 23, 1980, April 23, 1981 and August 12, 1981 showed Sargent & Lundy was tracking many concerns regarding Joy Manufacturing qualification test #X-604 -
(revision dated April 20, 1980). The audit revealed the
's following initial items are either not being tracked as open s or were auestioned and closed.
- 1. Performance characteristics of LOCA - amperage and insulation resistance were not identified.
- 2. Power supply frequency variance (1 5%) was not applied during the test cycle.
3 Margins for ambient - temperature, pressure and time were not generated prior to testing. Sargent & Lundy questioned this item but closed the issue incorrectly in letter by F.A. Kosik dated 4/23/81. The vendor's response stated that no margins were used and reported parameter values were exact values. This does not address what are acceptable
, testing margins per IEEE 323 - 1974, and NUREG 0588.
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,j Appandix "A" g If the IEEE 323 - 1974 margin of +15 F for test temperature 0
isenvokedthemeasuredtesttemperatureofg30Fis10F belog the marginal temperature of 340 F (325 F required
+ 15 F margin) hence invalidating the test results.
4.
During occurredLOCA in the testing,(twenty-eight one (28) equipment outages of continuous testing 1) atyear Jo and fifty-seven (57)(days Manufacturing. Two 2) failures which occurred (3/ 9/76 for two (2) hours, 4/22/76 for five and one-half (5 1/ ) hours) had no explanation of cause or what procedure was envolved to restart the i unit under test was documented in report X-604 or available l correspondence.
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APPENDIX "B" l PRE AUDIT CONFERENCE DATE: Tuesday September 29. 1981 TIME: 8:30 a.m. Room 24D35 NAME TITLE COMPANY T.R. Sommerfield QA Superintendent CECO.
G.F. Marcus Director of QA CECO.
J.J. Dennehy Project Engineer CECO.
J.E. McFarland Head QA Division S&L L.P. Dolder QA Coordinator S&L R.B. Klingler QA Supervisor CECO.
J.D. Regan Electrical Eng. S&L J.E. Szupillo S&L B.G. Treece SEPE S&L POST AUDIT CONFERENCE DATE: Wednesday September 30, 1981 TIME: 2:10 p.m. Room 26018 t
NAME TITLE '
COMPANY
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J.J. Dennehy State Asst. CECO. ,
B.G. Treece SEPE S&L J.E. McFarland Head QA Division S&L D.L. Leone Project Director S&L L.E. Ackmann Director of Services S&L D.C. McClintock Mgr., Elec. Dept. S&L E.V. Abraham Asst. Mgr. Mech. Dept. S&L J.D. Regan Electrical Engineer S&L J.M. McLaughlin Mgr. Str. Dept. S&L L.P. Dolder QA Coordinator S&L R.B. Klingler QA Supervisor CECO.
T.R. Sommerfield QA Superintendent CECO.
Audit Conducted by:
R.B. Klingler Team Leader T.R. Sommerfield Auditor
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