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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212F7671999-09-24024 September 1999 SER Granting Relief Request C-4 Pursuant to 10CFR50.55a(g)(6)(i) for Unit 2,during First 10-year ISI Interval & Relief Requests B-15,B-16 & B-17 Pursuant to 10CFR50.55a(g)(6)(i) ML20210D8321999-07-23023 July 1999 Safety Evaluation Accepting Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp ML20209H7661999-07-15015 July 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Comanche Peak Steam Electric Station,Units 1 & 2 ML20196L0191999-07-0808 July 1999 Safety Evaluation Granting Request Relief B-6 (Rev 2),B-7 (Rev2),B-12,B-13,B-14 & C-9,pursuant to 10CFR50.55a(g)(6)(i).Technical Ltr Rept Also Encl ML20209G7501999-07-0808 July 1999 SER Finding That Licensee Individual Plant Exam of External Events Complete with Regard to Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given Design, Operation & History of Comanche Peak Steam Electric Station ML20196J0621999-06-29029 June 1999 Safety Evaluation Supporting Proposed Changes to Emergency Plan Re Licenses NPF-87 & NPF-89 Respectively ML20206Q0091999-05-14014 May 1999 Safety Evaluation Accepting GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Comanche Peak Electric Station,Unit 1 ML20206H2061999-05-0606 May 1999 SER Accepting Exemption to App K Re Leading Edge Flowmeter for Plant,Units 1 & 2 ML20203A4881999-02-0303 February 1999 Safety Evaluation Granting Requests for Relief B-3 - B-6,C-2 & C-3 for Plant,Unit 2 ML20202D0101999-01-27027 January 1999 Safety Evaluation Supporting First 10-yr Interval ISI Program Plan Requests for Relief B-9,B-10 & B-11 for CPSES, Unit 1 ML20154B5741998-09-30030 September 1998 Safety Evaluation Re Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Motor-Operated Valves. Licensee Has Established Acceptable Program ML20237C4061998-08-14014 August 1998 Safety Evaluation Supporting Request to Implement Risk Informed IST Program ML20135B7911996-11-29029 November 1996 Safety Evaluation Approving Corporate Restructuring of TU to Facilitate Acquisition of Enserch Corp ML20128C1721993-01-29029 January 1993 Safety Evaluation Accepting First 10-yr Interval Inservice Testing Program for Pumps & Valves ML20198D3331992-05-0606 May 1992 Safety Evaluation Supporting Licensee Response to Generic Ltr 82-33 Concerning Implementation of Reg Guide 1.97,rev 2 ML20247K2531989-09-11011 September 1989 Safety Evaluation Supporting Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively ML20247E3761989-09-0707 September 1989 Safety Evaluation Supporting Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20248C0731989-08-0303 August 1989 Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants ML20246L2571989-06-26026 June 1989 Safety Evaluation Supporting Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20245J0751989-04-25025 April 1989 Safety Evaluation Supporting Amends 114,30,141 & 33 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20235U5631989-02-24024 February 1989 Safety Evaluation Concluding That Stated 10CFR70 License Conditions Should Be Incorporated Into 10CFR50 License ML20205Q5721988-10-31031 October 1988 SER Re Const Mod & Licensing of Company Facility-1 Cpdf. Licensee Technically Qualified to Modify Existing Facility in Such Way as to Assure Adequate Protection of Common Defense & Security ML20205Q5761988-10-31031 October 1988 SER Re Application for CP for Alchemie Facility-2 Oliver Springs.Licensee Technically Qualified to Construct & Operate Proposed Facility in Such Way as to Assure Adequate Protection for Common Defense & Security ML20205M5731988-10-26026 October 1988 Safety Evaluation Supporting Amends 108,25,134 & 26 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20155G4801988-09-28028 September 1988 Safety Evaluation Supporting Amends 107,23,132 & 24 to Licenses DPR-61,DPR-21,DPR-65 & NPF-24,respectively ML20153C8171988-08-25025 August 1988 Safety Evaluation Supporting Corrections to Amends 9 & 8 to CPPR-126 & CPPR-127,respectively ML20195G5531988-06-24024 June 1988 Safety Evaluation Accepting Proposed Reracking of Util Spent Fuel Storage Pools from Criticality Standpoint.Enrichment of Fuel to 4.5 Weight % U-235 May Be in Conflict W/ 10CFR51 Table S4 & Should Be Investigated by NRC ML20154H2171988-05-18018 May 1988 Safety Evaluation Accepting Util 880414 Submittal Re Reload Startup Physics Test Program ML20147D9631988-02-25025 February 1988 Safety Evaluation Accepting Util 860404 Evaluation of Environ Qualification of Equipment Considering Superheat Effects of high-energy Line Breaks for Plants,Per IE Info Notice 84-90 ML20147E9261988-02-23023 February 1988 Safety Evaluation Supporting Amends 100,14,125 & 15 to Licenses DPR-61,DPR-21,DPR-65 & NPF-45,respectively ML20236M9631987-11-0606 November 1987 Safety Evaluation Accepting Util Proposed ATWS Mitigating Sys Actuation Circuitry for Facilities,Per 10CFR50.62(c)(1) & Pending Final Resolution of Tech Spec Issue ML20236L2001987-10-30030 October 1987 Safety Evaluation Supporting Amends 11 to Licenses NPF-37 & NPF-66,respectively & Amend 1 to License NPF-72 ML20195G5501987-10-28028 October 1987 Safety Evaluation Accepting Proposed Reracking of Util Spent Fuel Storage Pool.Licensee May Be Required to Perform Addl Analyses to Verify Maint of Required Subcriticality If Staff Boraflex Studies Reveal Gap Development in Subj Boraflex ML20236A5741987-10-13013 October 1987 Safety Evaluation Re Util 850502 Request to Eliminate Arbitrary Intermediate Pipe Breaks.Request Acceptable Provided Applicant Maintains Environ Qualification of safety-related Mechanical & Electrical Equipment ML20235A7331987-09-18018 September 1987 Safety Evaluation Re Installation of Alternate Rod Injection (ARI) Sys & Adequacy of Plant Reactor Coolant Recirculating Pump Trip (RPT) Sys,In Compliance W/Atws Rule 10CFR50.62. ARI & RPT Acceptable ML20195G5461987-08-21021 August 1987 Safety Evaluation Accepting Proposed Util Tech Specs Change to Increase Max Allowed Enrichment of Reload Fuel to 4.2 Weight % U-235 ML20236Y0221987-07-0808 July 1987 Safety Evaluation Clarifying Determination of Acceptability of Test Duration for Performance of Integrated Leak Rate Test at Plant ML20214X1801987-06-0808 June 1987 Safety Evaluation Supporting Modified Design Basis Documented in Amend 61 ML20214T7661987-05-28028 May 1987 Handwritten Sser on Allegation Re Qa/Qc Repair,Rework & Maint ML20214M3361987-05-22022 May 1987 Safety Evaluation Supporting Util Rept Entitled, Rod Swap Methodology Rept for Startup Physics Testing ML20214M1491987-05-21021 May 1987 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 2) Re Established Interface W/Nsss or Vendors of Each Component of Reactor Trip Sys ML20153F3851987-05-0404 May 1987 SER Accepting Util 870301 & 0407 Requests for Rev to Tech Specs,Modifying MSIV Actuation Control Sys,Per IEEE Std 279 & GDC 21 ML20153F3671987-04-30030 April 1987 Safety Evaluation Accepting Util 870311 Proposed Changes to Tech Spec Tables 2.2.1-1,3.6.1.2-1 & 3.6.3-1 Re MSIV-closure Setpoint ML20207R6481987-03-11011 March 1987 Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification.Program Acceptable ML20212J4041987-03-0202 March 1987 Safety Evaluation Re Util 831104 Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability,On-Line Testing. Licensee Meets NRC Position ML20212B5671987-02-24024 February 1987 Safety Evaluation Re Util Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Reliability On-Line Testing. Response Acceptable ML20211Q2971987-02-18018 February 1987 Safety Evaluation Re Auxiliary Feedwater Sys Reliability (Generic Issue 124) for Prairie Island Units 1 & 2 ML20211G4361987-02-14014 February 1987 Safety Evaluation Supporting Util 831110 Response to Generic Ltr 83-28,Item 4.5.2 Re on-line Testing for Reactor Trip Sys Reliability ML20153F3511987-02-0707 February 1987 Safety Evaluation Accepting Util Latest Design Mods to MSIV Actuation Control Sys,Per IEEE 279 & GDC 21 ML20210R2061987-02-0606 February 1987 Safety Evaluation Supporting Util 850517,0802,0823,1211 & 860429 Submittals Re Environ Effects of High Energy Line Breaks in Auxiliary Steam or Steam Generator Blowdown Sys. Design of Blowdown Sys Acceptable 1999-09-24
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E8021999-10-0707 October 1999 CPSES Unit 1 Cycle 8 Colr ML20217G4151999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Cpses,Units 1 & 2 ML20212F7671999-09-24024 September 1999 SER Granting Relief Request C-4 Pursuant to 10CFR50.55a(g)(6)(i) for Unit 2,during First 10-year ISI Interval & Relief Requests B-15,B-16 & B-17 Pursuant to 10CFR50.55a(g)(6)(i) ML20216J5701999-09-16016 September 1999 Rev 2 to CPSES Unit 2 Cycle 5 Colr TXX-9920, Monthly Operating Repts for Aug 1999 for Cpses.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Cpses.With ML20211M2981999-08-0606 August 1999 Rev 1 to CPSES Fuel Storage Licensing Rept, CPSES Credit for Soluble Boron & Expansion of Spent Fuel Storage Capacity, Consisting of Revised Title Page and 4-1 ML20210U4081999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Cpses,Units 1 & 2 ML20210D8321999-07-23023 July 1999 Safety Evaluation Accepting Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp ML20209H7661999-07-15015 July 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Comanche Peak Steam Electric Station,Units 1 & 2 ML20209H2721999-07-0909 July 1999 2RF04 Containment ISI Summary Rept First Interval,First Period,First Outage ML20209H2631999-07-0909 July 1999 2RF04 ISI Summary Rept First Interval,Second Period,Second Outage ML20209G7501999-07-0808 July 1999 SER Finding That Licensee Individual Plant Exam of External Events Complete with Regard to Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given Design, Operation & History of Comanche Peak Steam Electric Station ML20196L0191999-07-0808 July 1999 Safety Evaluation Granting Request Relief B-6 (Rev 2),B-7 (Rev2),B-12,B-13,B-14 & C-9,pursuant to 10CFR50.55a(g)(6)(i).Technical Ltr Rept Also Encl ML20210J9391999-06-30030 June 1999 CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20209G0801999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Cpses,Units 1 & 2 ML20196J0621999-06-29029 June 1999 Safety Evaluation Supporting Proposed Changes to Emergency Plan Re Licenses NPF-87 & NPF-89 Respectively ML20195G5141999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Comanche Peak Steam Electric Station,Units 1 & 2.With ML20216E0711999-05-21021 May 1999 1999 Graded Exercise - Comanche Peak Steam Electric Station ML20206Q0091999-05-14014 May 1999 Safety Evaluation Accepting GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Comanche Peak Electric Station,Unit 1 ML20206H2061999-05-0606 May 1999 SER Accepting Exemption to App K Re Leading Edge Flowmeter for Plant,Units 1 & 2 ML20196L2241999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Cpses,Units 1 & 2 ML20205R5701999-04-14014 April 1999 Rev 6 to ER-ME-067, TU Electric Engineering Rept,Evaluation of Thermo-Lag Fire Barrier Sys ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20205J7831999-04-0101 April 1999 Rev 0 to ERX-99-001, CPSES Unit 2 Cycle 5 Colr ML20205N3101999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Cpses,Units 1 & 2 ML20204H6371999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Comanche Peak Units 1 & 2 ML20205N1481999-02-28028 February 1999 Corrected Monthly Operating Rept for Feb 1999 for CPSES, Units 1 & 2 ML20203A4881999-02-0303 February 1999 Safety Evaluation Granting Requests for Relief B-3 - B-6,C-2 & C-3 for Plant,Unit 2 ML20210J9201999-02-0101 February 1999 CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802- 990201 ML20202D0101999-01-27027 January 1999 Safety Evaluation Supporting First 10-yr Interval ISI Program Plan Requests for Relief B-9,B-10 & B-11 for CPSES, Unit 1 ML20199E9961998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Cpses,Units 1 & 2 ML20207D6091998-12-31031 December 1998 1998 Annual Operating Rept for Cpses,Units 1 & 2. with ML20197K2371998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Cpses,Units 1 & 2 ML20195F3161998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Cpses,Units 1 & 2 ML20154B5741998-09-30030 September 1998 Safety Evaluation Re Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Motor-Operated Valves. Licensee Has Established Acceptable Program ML20154M8841998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Cpses,Units 1 & 2 ML20151W0361998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Cpses,Units 1 & 2. with ML20151Q1211998-08-14014 August 1998 Rev 0 to Control of Hazard Barriers ML20237C4061998-08-14014 August 1998 Safety Evaluation Supporting Request to Implement Risk Informed IST Program ML20237C6721998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Cpses,Units 1 & 2 ML20236V3121998-07-29029 July 1998 Final Part 21 Rept Re Enterprise DSR-4 & DSRV-4 Edgs.Short Term Instability Was Found During post-installation Testing & Setup as Part of Design mod/post-work Testing Process. Different Methods Were Developed to Correct Problem ML20236R0711998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Cpses,Units 1 & 2 ML20249B2581998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Cpses,Units 1 & 2 ML20248A1671998-05-22022 May 1998 Interim Part 21 Re Enterprise DSR-4 & DSRV-4 Emergency diesel.Post-installation Testing Revealed,High Em/Rfi Levels Affected New Controllers,Whereas Original Controllers Were unaffected.Follow-up Will Be Provided No Later than 980731 ML20247G3241998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Cpses,Units 1 & 2 ML20216B8661998-04-0101 April 1998 Rev 0 to ERX-98-001, CPSES Unit 1 Cycle 7 Colr ML20216J3061998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Cpses,Units 1 & 2 ML20216J1861998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Comanche Peak Steam Electric Station ML20197A6951998-02-24024 February 1998 Inservice Insp Summary Rept,First Interval,Second Period, First Outage ML20199J5391998-02-0202 February 1998 CPSES Commitment Matl Change Evaluation Rept 0002 for 960202-970801 1999-09-30
[Table view] |
Text
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AQ-98 CP4 REV l} - 10/:/37 Y 3,h3lW
- 1. Allegation Category: QA/QC 5A, Extensive Delays in Repairing "Q" Material
- 2. Allegation Number: AQ-98 Characterization: It is alleged that extensive delays occurred in the
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repair of' safety-related material.
- 4. Assessment of Safety Significance: The im ied si nificance o allegati n'is that exasUtiliObsElectrc ompany UEC) d(lays in repairing safety,related material nerease the proba ility that the material o't be ad ed but used as is.
driterion XVI of 10 CFR Pa t 50 Appe ix B, " ective Action," requires that rheasures e est ishd'oensbre at c ndit ns ich could
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adversely. af fect ua ity are promptly identified and corrected.
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TheNRCTechnicalReviewTeam(TRT)interviewedQA/QCmanagersandcon-firmed that some welding defects in the auxiliary feedwater (AFW) and component cooling system (CCS) systems were not repaired promptly.
The TRT found that, because of industry-wide concerns raised by.the accident at Three Mile Island, TUEC radiographed field welds on the AFW and CCS systems, even though the ASME Code does not require these types of welds to be examined radiographically. These radiographs were not inter-preted promptly because the lack of ASME radiographic requirements means that there are no ASME acceptance criteria for this class of welds. Sub-sequently, TUEC, having identified the defective welds, required them to 8606250292 860611 PDR FOIA GARDE 85-59 ,
PDR
be repai/ed, . re-radiographad, accepted, do:u::.ented, and sigr.ed cf f p r or i
to hydrostatic testing on these systems p The TRT found no other examples of extensive delays in repair of safety-related material.
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- 5. onclusion and Staff P5sitions: The TRT concludes that although this allegation was substantiated, TUEC's QA inspection program ensured that the welds in' question were re-examined and repaired prior to hydrostatic testing. Accordingly, this allegation has neither safety significance ner generic implications.
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- 6. Actions Reouired: None.
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S. Attachments: None.
- 9. Reference Documents:
- 1. CC-2-SB-42-1. -
- 2. GAP witness C #36, handwritten list dated April 84
- 10. This statement prepared by: [, .;wt<>fAAML L [23 - b g l. H. Jackson, Date TRT Technical Reviewer
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~ j s Reviewed.by: / ( , h t? /-Z3-3
- d. Livermore, Date Group Leader Approved by:
V. Noonan, Date Project Director
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..a , \) q y SSER WRITEUP' DOCUMENT C0tiTP[0L/ ROUTE SHEET
- df Allegation Numbers N ' // 7 b Subject of Ai1egation Du o I: ra -f.'. L, d ~ pia m G A r /c d C, n,, ,:,4, )
TRT Group QA/cc e l 7 E o' o t s.
- SOA Author: /h . M . 1/. e /c This sheet will be initialed by each reviewer. It stays with all revisions to the SSER writeup and serves as a routing and review record. It will be filed in the work package when the writeup is ' published.
Draft Number Draft 1 2 3 4 5 Author MM Group Leader i '/ , / 7 .
Tech. Editor \ / \/ / tofo 9//I ,
Wessman/Vietti \/ k' / . // /
J. Gaoliardo /\ /\ / // "I / 19 T. Ippolito e/ '
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Revision Number Q Final M b U % -
Author ]?L \ ' Y " Y .
Tech. Editor #4W#eA ' / 94 '/ k M Group Leader . // /' _. , r J. Gaoliardo f/ fe/ / , cwt.O h/&
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Administrative -
Writeup integrated into SSER Potential Violations to Region IV Vorkpackage File Complete
'Workpackage Returned to Group Leader 7
7# l D A -I coJagJiJ e==_ emmeunae e owee- +W--. m ewe- - " *
. Docum:nt Name:
AQ-117 Requestor's ID: '
JEAN Author's Name:
Poslusny Document Comments:
.14 % @5 REDRAFT 2l1klrf l
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Revisiond 10/9/84 CP3 QA/QC Category No. 53 SSER
- 1. Allegation Group: QA/QC Category No. 5A
- 2. Allegation Number: AQ-117
- 3. Characterizction: It is alleged that duplicate paperwork on flange travelers indicates a lack of communication between departments.
- 4. Assessment of Safety Sionificance: The implied sa e y signi - e of thisallga*ionisthatduplicatph'erwor co ! comp om 'ty Contr u 'QC ci eg rack e ork and th render he , tyjof are as i ~
e terminate.
The NRC Technical Review Team (TRT) reviewed the flange travelers 'identi-fied in the allegation and found that they did contain duplicate informa-tion, although'it did not involve material of safety significance. The duplication was verified by both vault paperwork and the Brown & Root (B&R) traveler coordinator. The paperwork in the vault shows that flange travelers MP 83-2389-F-1000 and M-83-2389-I-1000 were voided, and flange ,
travelers MP 83-2389-G-1000 and MP-83-2389-H-1000 contain essentially the
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same information; they differed orily in the stated reason why the flange required rewor.k. The voided travelers were voided for: valid but unrelated
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reasons, and the duplicate travelers. identified in the allegation were issued the same day. Flange travelers are basically all duplicates of each other in that-they contain standardized steps to assemble and dis-
' assemble the flange; they differ on,1y in the flange number and in the' reason why the flange required rework.
This duplication occurred during a turnover period between Brown & Root (B&R) piping and Texas Utilities Electric Company (TVEC) start-up depart-ments. Construction management, having recognized this duplication l problem, now processes all flange travelers through a single control F point, the Paper Flow Group (PFG). Other construction operation travelers o
,. 3 for su'ch items as valves, pumps, piping, and motors are also being coordinated by the PFG. The PFG has added the needed assurance that duplicate work orders are not being processed. A TRT review of rt:ent construction operation travelers revccic "r' "i "s = 'e -w T " could not detect any additional duplication since the PFG took .
control.
Conclusion and Staff Positions: The TRT concludes that the duplicate 5.
travelers did indicate a lack of communication betwe'en k " Y $ _
However, a B&R traveler coordinator did detect the problem and was able to prevent duplicate work on 3= flanges indicating'that they have an effective check and balance system. The TRT concludes this allecation has neither safety significance nor generic implications.
/
In a meeting with the alleger on December 10, 1984, t$e TRT pre,sented the.
results of the assessment of the allegation and the TRT's conclusion.a brief discussion ensued. There were no major items of disagreemen: Ed no new concerns or allegations were identified.
- 6. Actions Recuired: None.
'8. Attachments: None.
- 9. Reference Documents:
- 1. ISO DP-Y-AB-003.
- 2. Flange travelers MP-S3-2389-F-1000,
- 3. Flange travelers MP-S3-23S9-G-1000.
- 4. Flange travelers MP-S3-2389-H-1000.
'5. Flange travelers MP-33-2389-I-1000.
- 6. A-1 Statement #2 and A-1, Interview p. 80.
- 7. A -1 ,naZL w dm t g I 'tPy, f. V7
- 10. This statement prepared by:
Milton Bullock, TRT 08/84 Technical Reviewer Reviewed by:
Herbert Livermore, Date Group Leader 4
i Approved by:
Vincent Noonan, Date Project Director 9
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.11egation Numbers A C-/50 , + L, S .
Subject af ki1egation'7);iereoci,ea a:sV'LeLk,,4,. /GJe%s n Aware,.s ons />fe 4,,
TRT Group O/7/o + ' '
eg, Author: /. d. Uo ie se This sheet will be initialed by each reviewer. It stays witn all revis4ons to the SSER writeup and serves as a r' outing and review record. It will be filed in the work package when the writeup is published. /
Draft Number /
Draft 1 2 .
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Revision Number Final 1 2 3 4 5 -
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a Writeup integrated into SSER Potential Violations to Region IV -
Workpackage File Complete Workpackage Returned to Group Leader m
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