ML20211C402
| ML20211C402 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/01/1985 |
| From: | Thadani A NRC |
| To: | |
| Shared Package | |
| ML20211C348 | List: |
| References | |
| FOIA-85-312 NUDOCS 8606120308 | |
| Download: ML20211C402 (50) | |
Text
{{#Wiki_filter:__ ___ - __ _ Ashok Th'dani a DRAFT February l', 1985 Summary of. Presentation by Civil / Structure and. Mechanical / Piping Team ~ On Janu'ary 30, 1985, Larry Shao and several members of his' group met with ~ the Contention 5 Panel to discuss the findings of this TRT group. Larry's group.was formed in, July,1984 to evaluate allegations relating to Civil / Structure and Mechanical / Piping issues. The group was. divided in.two sub-groups with D. Jeng heading the Civil / Structure subgroup ~and S. Hou heading the Mechanical / Piping subgroup. Each' subgroup consisted of staff (mostly contractorpersonnel) withe $ tensive'experienceintherelatedfields(con-crete design and construction, piping des'ign and construction,. pipe support design and construction, welding, and inspection). A copy of the presenta-tion material used by this group is attached as Enclosure 1. ~ .The evaluations performed by the group included relevant allegations as well as the concerns 1.dentified in other NRC' studies such as the special Review Team Report. The group evaluated 57 Civil / Structural allegations / concerns and 147 Mechanical / Piping allegations / concerns. The Civil / Structural allegations ~ pertained to design deficiency, testing or inspection irregul'arities, -in-correct construction practices, inadequate repairs, uncorrected conditions in the completed structures, and premature structural loadings, whereas the Mechanical / Piping allegations pertained to violations in the broad areas of welding, piping and supports, etc. The basic approach' used by the group to evaluate the validity of these issues was to review relevant documents, conduct interviews with appropriate personnel, conduct analyses as needed, 8606120308 860606 hDE 12 PDR
and evaluate physical evidence.. If the issue was judged 'to be valid, an assessment was made to determine if the issue had potential safety significance or generic faplication.'. All valid generic issues"were given to j ? other TRT groups for generic considerations. Of the 57 Civil / Structural j 4 issues evaluated 16 were judged to be valid and 5 were considered to be J potentially significant to safety. Of the'147 Mechanical / Piping issues evaluated,18 were judged to be valid and 5 were ' considered to be l potentially significant to safety. All potentially safety significant issues were termed "Open" issues and the licensee has been required (Civil / Structure ~ Open Issues, letter from Eisennut to Spence dated 9/18/84, Mechanical / Piping Open~ Issues, letter from Eisenhut to Spence, dated 11/29/84) to address these issues. The Open issues are identified in the Enclosure 1 and additional information on these issues can be obtained from the two Eisenhut letters referenced above. . l.arry's overall assessment was that, with the possible exception of the control room ceiling issue, the plant design was safe and that the group identified some violations did not. surprise him in, view of the extensive evaluations conducted by the team. This overall judgment was also supported ~ by the members of the group present at the meeting. Some examples of the statements made by individual members of the group are: overall conservative design criteria containment tested to 1.15 design / pressure documentation fair'to good r-
concrete work pretty good QA on fixing problems good Mechanical / Piping QA group aggressively following u'p; sometimes , the proc,edures are confusing Visual inspection identified only one weld in'.the Main Steam Systemthatshould-havebeenrejected,QA,QC!inthisareaseemed weak. All problems identified are small and as a whole don't have much safety signifi.cance, except perhaps an indication of weak QA. No need for seismic related concerns with supports, rather the attention should be focused on the effects of valve actuation and thermal variations on the supports. + In summary, the group felt the plant ~was safe and they were satisfied that the applicant was seriously folding in his program all the potentially .significant issues identified by the group. My commendation to Larry Shao and lits staff-for a well organized and focused presentation. e
} COMANCHE PEAK ' CIVIL /STRUCTUPI'.AND ECHANICAL/ PIPING TEAM 'L. SHA0',' GROUP LEADER / J' b CIVIL / STRUCTURE - ECHANICAL/ PIPING D'. JENG', SUB-GROUP LEADER S.H0lf,'SUB-GROUPLEADER J, DEAVERS, PARAETER W. P'. CHEN, ETEC ~ C. HOFMAYER, INEL V. FERRARINI, EAS T. LANG0WSKI, ETEC , D. HANSEN, INEL R. U PINSKI, liRC R. HUBBARD', SANDSTONE, INC'. ~ R. PHILLE0', PARA ETER D. LANDERS,' TELEDYNE ~ J. MALONSON, TELEDYNE R'. MASTERSON',' EAS i C', RICHARDS',' AI l E',' THOMPSON',' ETEC l. 4 l
l ) CIVIUSTRUCTURAL AND ECHANICAUPIPING TEAM j ) e 6 STRUCTURAL ENGINEERS AND 10 ECHANICAL ENGINEERS i i l e EXPERTS IN: (A) CONCRETtDESIGNANDCONSTRUCTION i l l (n) PIPING DESIGN AND CONSTRUCTION s l (c) PIPE SUPPORTS DESIGN AND CONSTRUCTION ) l-l (n) ELDING AND INSPECTION.. t
e 4 l O e 9 e G G ALLEGATIONS 57 CIVIL / STRUCTURAL RELATED ALLEGATIONS: ~ lil7 ECHANICAl1 PIPING RELATED ALLEGATIONS ~ ~ ~ ~ I k e I i l l i g O e e O 4 4 5 9 e - -.,. - n.r.,,..\\,,,,, y crrr:rr- - 7 m -'-,~} y
e SCOPE OF CIVIL / MECHANICAL ALLEGATIONS l1 FIFTY--SEVEN (57) ALLEGATIONS IN CIVIL / STRUCTURAL AREA. THEALLEGATIONSPERTAINTOTHEFOLLONINGSIX' BROAD ^ AREAS: ~ 1. DESIGN' DEFICIENCY 2. TESTING OR INSPECTION IRREGULARITIES 3'l INCORRECT CONSTRUCTION PRACTICES '/.- [ INADEQUATE-REPAIRS ~ 5'l UNCORRECTED 7 UNSAFE CONDITIONS IN TH5 COMPLETED ~' STRUCTURES-j l l 6'l PREMATURE STRUCTURAL LOADINGS l i l
SCOPE OF MECHANICAL / PIPING ALLEGATIONS 1 1 ~ ONE HUNDRED FORTY.SEVEN ALLEGATIONS IN MECHANICAll PIPING AREA',' ALLEGATIONS PERTAIN TO THE FOLLOWING 4 BROAD AREAS:i E e WELDING e PIPING e SUPPORTS (f,. .s. ~0THERS e . 9 T 4 e 1
BASIC APPROACH o ' REVIEW ALL RELATED~ DOCUMENTS SUCH AS LLEGER' TESTIMONIES,- ASLB HEARING RECORDS, NEWSPAPER ' ARTICLES, 'I'NT'ERVIEW REC 0'RDS, ETC. TO FORMULATE ALLEGATIONS. i. o THROUGH INTERVIEWS:WITH ALLEGERS AND INFORMAL MEETINGS AND.DI.SCUSSIONS WITH THE APPLICANT AND THEIR CONTRACTORS, DEVELOP THE NECESSARY-BACKGROUND INFORMATION. o EVALUATE AND ANALYZE ALLEGATIONS IN RELATION TO CONSTRUCTION, ANALYSIS, DRAWINGS, SPECIFICATIONS, CODES, PROCEDURES, FSAR AND OTHER COMMITTED DOCUMENTS. o DETERMINE THE VALIDITY OF ALLEGATIONS ONCE THE l l ALLEGATION IS FOUND TO BE VALID, DETERMINE WHETHER IT HAS POTENTIAL SAFETY. SIGNIFICANCE AND GENERIC IMPLICATION. o THE VIOLATION THAT HAS POTENTIAL. SAFETY SIGNIFICA.NCE IS TERMED AN OPEN ISSUE. o OPEN ISSUES WERE TRANSMITTED TO THE APPLICANT FOR ACTION. o DISCUSS FINDINGS WITH ALLEGERS.
DEFINITION '0F " LACK OF SAFETY SIGNIFICANCE"' LACK'0F~"SAF5TYSIGNIFICANCE"PERTAININGT0,!0RASARESULT OFAGIVENDEFICIENCY,ORVIOLATIONOFAPPLICANT'S COMMITENTS, CODES, OR FSAR REQUIREMENTS MEANS THAT WHILE AN ACTIVITY OR ITE.5 DOES NOT FULLY CONFORM TO ALL APPLICANT'S COMT11TMENTS, OR APPLICABLE CODES OR FSAR REQUIREMENTS, TRT CONCLUDES ON A TECHNICAL BASIS THAT THE STRUCTURE OR COMPONENT WILL NEVERTHELESS FUNCTION PROPERLYWITHOUTINTERFERRINGWITHSAFETY',' e J e e I t 9
OPEN ISSUE . e ALLEGATIONISVALID ~ e THERE IS VIOLATION e THERE IS POTENTIAL SAFETY SIGNIFICANCE O S
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POTENTIAL OPEN ISSUES 1 CIVIL / STRUCTURES ' - f.~1. UNABLE TO JUSTIFY REINFORCING STEEL OMITTED IN REACTOR CAVITY f,2'FALSIFICATIONOFCONCRETECOMPRESSION STRENGTH TEST RESULTS 1.3 MAINTENANCE OF AIR GAP BETEEN CONCRETE I STRUCTURES 1.4 SEISMIC DESIGN OF CONTROL ROOM CEILING + I ELEMENTS f.5 UNAUTHORIZED CUTTING OF REBAR IN THE FUEL HANDl.INGBUILDING 2'. MECHANICAL AND PIPING i f.'1 INSPECTION OF CERTAIN TYPE OF SKEED FILLET EL f,'2 PIPING DESIGN CONSTRUCTION BETEEN CATEGORY AND NON CATEGORY I BUILDINGS f.3 UNAUTHORIZED CUTTING OF EQUIPMENT RESTRAIN BOLTS IN THE REACTOR BUILDING 1,4 UNCONTROLLED PLUG ELDS 1,5 PIPE INSTALLATION O e
.n l I CIVIL / STRUCTURAL ) CATEGORY NO 6 - UNABLE TO JUSTIFY REIE ORCING STFFI OMITTED IN REACTOR CAVITY WALL i POTENTIAL OPEN ISSUE 1 A PORTION OF REIFORCING STEEL WAS OMITTED IN A REACTOR CAVITY. CONCRETE. WA PLACEMENT BETWEEN ELEVATION 8.12' - 0* AND 819' - 01/2" ' l i ACTION REQUIRED ~BY TUEC i l TUEC SHOULD PROVIDE AN ANALYSIS THAT VERIFIES THE ADEQUACY OF THE REINFORC STEEL IN-THE AS-BUILT CONDITION OF THE REACTOR CAVITY WALL. l [ I-e e m
\\ ~ l CIVIL / STRUCTURAL _ ~~ CATEGORY M0. 8 - FALSIFICATION OF CONCRETE COMPRESSION STRENGTil TES l POTENTiALOPENISSUE l i ALLEGATION OH FALSIFICATION OF CONCRETE COMPRESSIVE l COULD MOT BE PROVED VALID OR INVALID. CONCRETE STRENGTH LOWER-THAN THAT. SPECIFIED IN THE DESIGM MAY REDUCE TiiE LOAD RESISTING CAPACITY OF ST i ACTION REQUIRED BY TUEC l ~ TUEC SHOULD DETERMIME AREAS WHERE SAFETY RELATED CONCRETE WAS PLACED i I DURING THE PERIOD FROM JANUARY 1975 TO FEBRUARY 1977 AND CONDUCT l APPROPRIATE RANDOM StifilDT HAITIER TESTS ON THE CONCRETE IN AREAS WHERE l 1 1' SAFETY IS' CRITICAL. 1 I e i i
1 8 CIVIL / STRUCTURAL CATEGORY NO.'11 - MAINTENANCE OF AIR GAP BETWEEN CONCRETE STRUCTURES l POTENTIAL OPEN ISSUE O ERVA I NS DS 0 t TH EE NEER, E TR CA f T E N ET ER AN ADEQUATE AIR GAP HAS BEEN PROVIDED BETWEEN CONCRETE STRUCTURES.. ACTION REQUIRED BY TUEC ~ PROVIDE DOCUMENTS OR INSPECTION RESULTS TO DEMONSTRATE THAT' ADEQUATE SEPARATION BETHEEf! ALL CONCRETE STRUCTURES HA'S BEEN PROVIDED. PERFORM ANALYSIS TO DEMONSTRATE THAT THE AS BUILT CONDITIONS DO NOT SIGNIFICANTLY INCREASE THE-SEISMIC RESPONSES.0F-l .tATEGORY I STRUCTURES APID COMPONENTS. ~ ? i i l l ~
. ' ~. l CIVI.USTRUCTURAL CATEGORY NO. 14 - SEISMIC DESIGN OF CONTROL ROOM CEILING ELEMENTS POTENTIAL OPEN ISSUE l )I FIELDRUNCONDUIT,THESUSPENDEDCEILINGELEMENTh',,AND.THELIGHTING'FI.3TURES INSTALLED IN THE CONTROL ROOM CEILING ARE CLA$SIFIED AS NON-SEISMIC.O.R SEISMIC CATEGORY II AND MAY FALL AS A RESULT OF A SEISMIC EVENT.
- l ACTION REQUIRED BY TUEC j
PROVIDEORMODIFYSEISMICCALCULATIONSONSEISMICCATEGORYIIANDNON-SEISMIC j ELEMENTS IN THE CONTROL ROOM CEILING TO DEMONSTRATE THAT THEIR FAILURES WILL l NOT AFFECT SAFETY RELATED COMPONENTS OR CAUSE INJURY TO OPERATORS. ' l-1
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i 1 CIVIUSTRUCTURAL CATEGORY NO.15 - UNAUTHORIZED CUTTIM OF REEAR IN THE FilEL llANDLING BUILDING' i ~ POTENTIAL OPEN ISSUE UNAUTl10RIZED CUTTINO OF REBAR ASSOCIATED WITH THE INSTALLATION OF'THE l TROLLEY PROCESS AISLE RAILS IN THE FUEL liANDLING BUILDING MAY HAVE-l OCCURRED. LOSS OF THE REBAR MY REDUCE THE l.0AD RESISTING CAPACITY OF THE ~ CONCRETE FLOOR SLAB.* '. - ACTION REQUIRED BY TUEC Pl10 VIDE Tile FOLLOWING INFORMTION REGARDING DRILLING OF RE3AR: (1) INFORM TION THAT DEMONSTRATES THAT ONLY THE UPPERMOST #.18 BAR WAS i CUT, OR l (2) DESIGN CALCULATIONS TilAT DEMONSTRATE THAT. STRUCTURAL -INTEGRITY IS l-MINTAINED.IF # 18 BARS IN THE UPPERMDST AND T!!E LOWERMOST LAYERS ~~ ARE CUT. ~ i l i i i .. ~.
~ E CHANICAL AND PIPING ~ CATEGORY No. 31 - INSPECTION OF CERTAIN TYPE OF SKEED FILLET ELDS IN NF SUPPORTS _ l i POTENTIAL OPEN ISSUE ~ i THERE WAS A LACK OF' PROPER INSPECTION DOCUENTATION FOR SKEWED FILLET. ELDS i WHENWELDINGAPIPESTANCHIONTOAPIPESTANCHION?ORAPIPESTANCHIONTOA~. ~ CURVED PLATE FOR CLASS 2 AND 3 NF SUPPORTS! IPPROPER INSPECTION tECHNIo0ES ~ i COULDRESULTINUNDERSINDFILLETELDS? i ACTION BY TUEC j PROVIDE THE FOLLOWING:. (1) REVISEB&RWELDINSPECTIONPROCEDURESCP-0AP-12.1AND QI-0AP-111-28TOPROPERLYADDRESSALLTYPES~0FSKEWED ~ 4 l' FILLETWELDS,INCLUDINGPIPETYPECONNECTIONS? l I (2) PROVIDE EVIDENCE TO VERIFY THAT PREVIOUS INSPECTION OF TESE TYPES OF SKEWED FILLET ELDS WAS PERFORED TO THE APPROPRIATEINSPECTIONTECHM100ES?
~ ~ i E CHANICAL AND PIPING CATEGORY N0',' 4 - UNCONTROLED PLUG WELDS ~- POTENTIAL OPEN. ISSUE ~ HOES IN UNIT 1 & 2 PIPE SUPPORTS',' CABLE TRAY SUPPORTS AND BASE PLATES l WHICH HAD BEEN MISDRILLED DURING FABRICATION HAVE BEEN REPAIRED IN AN UNCONTROLED MANNER BY PLUG WELDS'. l ACTIONS REQUIRED BY TUEC TUEC SHALL PERFORM ONE OF THE FOLLOWING l PROVIDE A PROPOSED PLAN OF RESOLUTION INCLUDING A SAPPLING INSPECTION OF ALL AREAS OF THE PLAN HAVING PLUG WELDS:WHICH INCLUDES CABE~ TRAY i. SUPPORTS,' PIPE SUPPORTS AND BASE PLATES ~ l 2',' PERFORM BOUNDING ANALYSIS TO ASSESS THE GENERIC SAFETY SIGNIFICANCE. OF. UNCONTROLED PLUG WELDS. j 1 i i 1
. 7_., i ECHANICAL AND PIPING CATEGORY N0. 11 - PIPE INSTALLATION' P0TENTIAL OPEN ISSUE ~ TEff0RARY SUPPORTS FOR THE UNIT 1, l'00P 17 MAIN STEAM LINE SETTLED DURING CONSTRUCTION.' THE LINE WAS SUBSEQUENTLY EPOSITIONED USING THE MAIN' POLAR CRANE AND COE ALONGS? ASSESSENTS OF EFFECTS ON QUALITY OF THE MAIN STEAM AND' FEEDWATER LINES HAVE NOT BEEN PERFORED FOR.THE FULL SEQUENCE OF ~ EVENTSINVOLVED? ~ ACTION REQUIRED" BY TUEC' (1) PERFORM AN ASSESSENT OF THE STESSES IN THE AFFECTED PIPING (2) PERFORM NDE OF AREAS WHERE STESSES EXCEED ALLOWABLES -(3) REVIEW RECORDS OF HYDROSTATIC TESTING TO VERIFY QUALITY OF AFFECTED PIPING ~ . (li) PROVIDE ASSESSENT OF EFFECTS ON OTHER SAFETY RELATED PIP.ING WHICH WAS INVOLVED IN SIMILAR INCIDENTS OF SETTLEENTS OF TEPPORARY SUPPORTS. e b
1 -ECHANICAL AND PIPING _ 1 CATEGORY N0! 18 UNAUTHORIZED C ING OF EQUIPENT ESTRAINT ANCHOR BOLTS IN THE EACTOR BUILDING 1 l POTENTIAL OPEN ISSUE l UNAUTHORIZED CUTTING OF.THE BASE PLATE ANCHORING BOLTS ON THE UPPER l LATERAL SUPPORTS FOR TE, STEAM GENERATOR MAY HAVE OCCURRED? THE CUTTING 0FTHESEBOLTSMAYREDUCETHELOADCAPACITY0FTHE-LATERALSUPPORTi ~ ~ l l ACTION REQUIED BY TUEC_ PROVIDE EVI.DENCE SUCH AS ULTRASONIC EASUREENT ESULTS T0., VERIFY TE INSTALLED . LENGTH OF BOLTING 7 SHOULD UNAUTHORIZED BOLT CUTTING BE VERIFIED'l TUEC SHALL: (. (1) EPLACE SHORTENED BOLTS WITH BOLTS ~ F PROPER LENGTH 7 OR PROVIE l ANALYSIS TO JUSTIFY TE ADEQUACY OF SHORTENED BOLTS AS. INSTALLED? -(2) PROVIDE JUSTIFICATION OR PROPOSE EASURES~TO~ ENSURE THAT.N0. SIMILAR CONCERN EXISTS FOR BOLTINti? ~ e
.4 - _ECHANICAL/ PIPING .. ? \\ i CATEGORY NO. 3G - PIPING DESIGN-CONSIDERATIONS BETWEEN CATEGORY 1 AND NON-CATEGORY l BUILDINGS I-POTENTIAL OPEN ISSUE j PIPING SYSTEMS SUCH AS MAIN STEAff) AUXILIARY STEAM AND FEEDWATER AR ROUTED FROM ELECTRICAL CONTROL BUILDING (SEISMIC CATEGORY I) TO TURBINE BUILDING -(NON-SEISMIC CATEGORY I) WITHOUT ANY ISOLATION'l EACH SEISMIC CATEGORY I PIPING l ' SYSTEM SH0lA.D BE ISOLDATED FROM ANY NON2 EISMIC CATEGORY I PIPING SYSTEM B S SEPARATION'lBARRIERORCONSTRAINT'l IFNOT)THEEFFECTOFTHEFAILUREOFNON' ~ SEISMIC CATEGORY I STRUCTURES AND PIPING ON SEISMIC CATEGORY I PIPING SYSTEMS l MUST BE CONSIDERElil i ACTIONS REQUIRED BY TUEC TUEC SHALL PROVIDE DOCUENTATION THAT PIPING SYSTEMS GOING BETWEEN CATEGORY I AND NON-CATEGORY I BUILDINGS EET THE STATED FSAR CRITERIA'l - a.
.~ _ I Comanche Psak Contention 5 Panel A Meeting Summary i The Contention 5 Panel met on 2/13/85 from 8:30am to 5:00pm. Attending were: Panel Members Advisors Presenters R. Vollmer, IE V. Noonan NRR S. Treby, ELD R. Warnick, RIII C. Poslusny, NRR J. Gagliardo, IE J. Sniezek, EDO J. Scinto. ELD D. Hunter, RIV A. Thadoni NRR J. Lieberman, ELD E. Jordan, IE J. Axelrad IE I B. Kaplan, EG&G D. Eisenhut, NRR E. Christenbury, ELD A. Meeting Agenda 1. Meet with Intimidation Panel 2. Receive briefing on hearing background 3. Meet with Eisenhut to summa'rize status and panel action to date 4. Discuss data collection test .B. Intimidation Panel l -(Enclosure 1), i C. Hearing Background l S. Treby briefed the panel on the sequence and major milestones of the 1 l Comanche Peak hearing. Since this presentation is for background no summary is provided. t n.-, -.-.,--,,---n
. 1 D. Meeting with Eisenhut ThepanelmetwithMr.!EisenhuttodiscussthestatusoftheContention5 Panel review and recommendations to date. 1. The preliminary view of the panel based upon review of~ documentation, discussions with technical reviewers and the site trip is that Comanche Peak is a licensable plant provided identified problems are corrected. t 2. The evidence and NRC findings must.be structured and carefully reviewed to provide clear technical findings area by area to the board. 3. The panel made the following recommendations on the process for continued technical review: a. Strengthen'the integration of Regional and HQ activities and ~ streamline process for release of Regional Reports. b. Technical findings should receive normal technical review by managers of each technical area. The matrix o'f work completed and scheduled to be performed c. should be formalized with dates, assignments of responsibility and a critical path. d. A simpler organization with dedicated personnel should be developed. The panel was advised by Mr. Eisenhut that the final charter would reflect the emphasis of the responsibility for the determinations regarding Comanche Peak by Mr. Noonan and the role of the panel to assist, make recommendations and only provide testimony if requested. i
3-D. Data Collection Program I The data collection program was discussed in view of the panel's role based on. discussions with Mr. Eisenhut. The panel consensus was that a test should be conducted using data from Mr. Shao's TRT area but the panel should leave implementation of the program as a decision for Mr. Noonan with recomendation from the. panel dependent on the test results. e O O 0 0 9 sams O 9 6 a
= HEETING WITH THE INTIMIDATION PANEL _ i from the Contention 5 Panel received a status brief ngdMs.:Axelrad). the Intimidation Panel (Messrs. Gagliardo, Hunter, lieberman an On February 13, 1985, Attached is the Th y were accompanied by the EG&G consultant, Bruce Kaplan. d by'the definition of Intimidation or Harassment and Discrimination being use ~ h re Intimidation Panel and the fonnat they are using to ana t ay have been this point believes there are a few instances whereby inspec ors mTh r:ceiving. i ing been established. In performing its review, the Intimidation Panel is exam n intimidated by management. d intends to have the EG8G Report, 01 Investigations and the Hearing Record an i ith numerous discussions with Vince Noonan and the member l d over the indicated that the allegations were essentially equally distribute i Attached is a time-line which they distributed during the In its analysis to date, the Intimidation Panel has found nothi time frame. 1981-84 h ' Peak site. to Indicate that record falsification was a problem at the Comanc e briefing. 1979 did [ The Intimidation Panel indicated that the QA organization change i This is contrary not change the hiring and. firing authority for QC insp i ith Region IV C personnel trans- ~ personnel; i.e., that the hiring and firing authority for QThe Intimida ferred from Brown and Root to TUGC0 in 1979. complete its review about mid-March 1985.
. DEFINITION OF INTIMIDATION, HARASSMENT AND DISCRIMINATION Intimidation or Harassment: Incidents, statements or other actions that are reasonable likely to influence employees to refrain from performing safety-related work in accordance with requirements or identifying or reporting quality discrepancies or safety problems. In detennining whether the incident, statement or actions was reasonably likely to influence employees, a number of factors will be considered including: 1)thenatureof .the statement or action; 2) the intent of the person making the statement or takivi the action; 3) the perception of the recipient of the statement or '~ ~ . action; and 4) the positions of and relationship between the person making the statement or taking the action and the recipient. Discrimination: The showing of prejudice in the treatment of employees for performing safety-related work or reporting quality discrepancies or safety problems to their management or to the NRC. The showing of prejudice may b include adverse actions such as discharge or oth r actions that relate to the t l ' terms, conditions, and privileges of employment. l l l l
'/ ~ FORMAT FOR ANALYSIS OF INTIMIDATION AND DISCRIMINATION AT COMANC'E PEAK H 1. Description of the intimidation / discrimination incident including: a) Name, posit.fon, and duties of person subject to intimidation; b)Name,positionanddutiesofpersonallegedtohaveintimidated; c) Names and positions of other persens either subject to or 1'nvolved in'the incident; d) Area of work involved - welding. coatings, etc.; e)Dateandplaceof, incident; f)thenatureofthestatementoraction; g) the intent of the person making the statement of taking the action; ~' h) the perception of the recipient of the statement or action; and i) the positions of and relationship between the' person making the statement or taking.the action and the recipient. 3. The effect of the statement on the ' recipient including any specific failures to report safety problems and the basis for the conclusion that ~ the effect occurred. 4. Reference to decuments where incident is described such as Investigation Reports, deposition, hearing transcripts, etc. (title, dated, pages). i l ,m~w w
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.e Comanche Peak Contention 5 Panel Meeting Summary The Contention 5 Panel conducted meetings at the following locations 2/5-8/85: 2/5 - 9:00am - 5:00pm - Comanche Peak Plant Inspection ~ 2/6 - 8:30am - 5:00pm - RIV Offices 2/7 - Meet with CASE 2f/ - Meet with TUGC0 2/8 - 8:30am - 11:00am - RIV Offices Panel Members ~ Advisors R. Vollmer, IE V. Noonan, NRR R. Warnick, RIII J. Scinto, ELD A. Herdt,' RII C. Poslusny, NRR J. Sniezek, EDO T. Sullivan, NRR A. Thadoni, NRR ~ E. Jordar, IE A. Comanche Peak Inspection The panel met with Resident Inspectors and TRT members at the plant site to discuss areas inspected and specific findings in Unit I reactor. The areas reviewed included Fuel Storage Pool lines, Cable Spreading Room, Component Cooling System Support, Control Room Seismic Modifications, Auxiliary Bldg. El? 852, Main Steam System " George Washington Bridge," Safety Valve Restraints South Yard Pipe Tunnel, Diesel Generator Rooms and Conteinment. In addition, Messrs. Jordan, Warnick and Herdt also inspected portions of Unit 2 including containment. The panel members noted that Unit I was extremely clean and r. at. B. Meeting with CASE The list'of participants is enclosed as Enclosure 1. A transcript of the meeting has been separately distributed.
'i C. Meeting with TUGC0 The list or participants in enclosed as Enclosure 2. A transcript of the meeting has been reparately distributed. ~ 4 D. Meeting with, F.IV Personnel The par.ei met with the following personnel to obtain an understanding of, the.tatus of the~ inspection program at Comanche Peak and the major findings: Shannon Phillips - Resident - 1984 - . Bob Stewart - Regional Inspector - 1973-78 Bob Taylor - Reside'nt - August 1978 - February 1984 Larry Martin - Regional Inspector Doyle Hunnicutt - Section Chief - July 1983 to Present Bill Seidle - Branch Chief - July 1976 - February 1981 Glen Madsen - Branch Chief - 1973 to July 1976 Joe Tapia - February 1981 to 1983 James Cummins - Resident Tom Westerman - Enforcement Officer Dick Bangart - Division Director Dick Denise - D'ivision Director - 1984 to Present . Bob Martin - Regional Administrator - 1984 to Present l: O b l
ENCLOSURE 1 bb5/f[f77A/S $ E / / 0 / k A l l $.. f N5~ A. Of %.... kWk .. p R C...,. P.cofe.c$. D n rec o c \\/mee. AJoo na u davn.s S n i e.2 e.K ..... N 4 c.....; Pa n e I n?e ns be c.. ;.. = o f. nu. ho r.... e .Iler4 t.............. ... a A e../....P ne r A/o.n.. \\ {- { .. bdC A n.. .... - N A C.., ... IS n t...C. hs t r4at rMh. f4ne.L.rne.wbei.. [ .A.sAok 7b 2 A.ni. _....._.... N 4.t.,..- A ie lu.d . V o il n, e v..... .._..A>4 C, b ef._.vne.s h r. f So hc.ci . Ido.v m t K.. h4 C.. 84 ne.l. m e.m Idec.. L r --
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' Contention 5 Panel Aasnda Wednesday - March 27 (Phillips - Rm. P-422) 8:30 am - 9:45 am Noonan Project Organization, Staffing, Schedule Anticipated Panel Product CYGNA Status 10:00 am - 10:45 am Hale QA/QC Status Results of Recent Meeting w/ Applicant 11:00 am - 11:45 am Keimig (phone) Testing Status / Meeting w/ Applicant (Phillips - Rm. P-114) 2:30 pm - 4:00 pm Panel Schedule / Assignments Thursday - March 28 (Phillips - Rm. P-422) 8:30 am - 9:30 am McCracken Coat,ings Status 10:00 am - 11:00 am Treby Hearing Concerns 11:00 am - 12:00 pm Landers Design QA Process 12:oo Pin floo m n I. 12:00 pm - 1:30 pm Panel Misc. Discussions / Lunch -2 : 3, ; - 1:30 pm - Si40 pm Shao, Masterson Civil / Structural Mech. Piping Status Fisher Results of Meetings ff3,pMy-Date Collection Status i I -St45 p: - 4: 30 p-r=1 ve;- Alestr-icaLStatus/_ Meetings O f*0lA 86~30) pp y ^!/n
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4 f i COMANCHE PEAK TECHNICAL REVIEW TEAM CATEGORIES OF ALLEGATION REVIEW i Electrical / Instrumentation: 1. Cable Terminations 2. Cable Tray / Conduit Installation 3. Equipm'ent Separation 4. Control Room Ceiling Fixture Supports 5. NRC Activities '6. QC Inspector Training and Qualifications I 7. Cable Installation 8. Procedures 9. Inspection Reports, Inspection Item Reinovel Notices, In Process Inspections Test Program i 1. Hot Functional Testing (HFT) 2. Unit 2 Testing 3. Containment Leak Testing 4. Prerequisite Testing 5. Preoperational Testing 6. Maragement Attitude 7. QA Surveillance of Testing Activities y f. /3 Foi 4 15-* 2 e yo
A Mechanical / Piping 1. ' Welding Proceduras Welding Control Deficient Welds 2. Piping Iaproper Handling 6f Dan, aged Pipes Design and Analysis Problems Installation Problems 3. Supports Design and Analysis Problems Installation, Fabrication Deficiencies Construction, Documentation Control Deficiencies 4. Damage Caused by Vessel Installation i O O
C L. ~~ ~ ~ ^ ^ C nf lL STauc_Tu n s t-l CATEGORIZAT10110F ALLEGAT10t'S i i CATEGORY fl0. CHARACTERIZATION NO._OF ALLEGATIONS 1 INADEQUATE MATERIALS USED 6 l IN CONCRETE 2 CONCRETE PLACEMENTS 3 3 P00R WEATHER CONDITIONS 3 4 C0l! CRETE VOIDS / CRACKED 7 i 5 MISCELLA!!EOUS CONCRETE 4 6 REBAR IMPROPERLY lilSTALLED/0MITTED 9 7 CONCRETE UNDOCUMENTED 1 8 FALSE / WRONG DOCUENTS 6 9 QC INSPECTOR TRAINING 1 10 IMPROPER TESTING 6 . 11 SEISMIC DESIGN /C0!1STRUCT10N 1 12 CONCPITE CONSTRUCTION AND 1 DEFICIENCIES / TOLERANCES .13 CRACKS IN CONCRETE BENEATH THE 1 REACTOR VESSEL 14 SEISMIC DESIGN OF CONTROL ROOM J CEILING ELEMEl!TS 15 REBAR IMPROPERLY DRILLED 5 16 EXCAVATION / BACKFILL 1 17 CONCRETE SAMPLING 1 TOTAL ALLEGATIONS X
i i Coatings 1. Backfit Test Program 2. DBA Qualification Testing 3. Coatings Traceability 4. Coatings Procedures 5. Coatings Inspections and NCR's 6. Coatings Exempt Log 7. Training and Qualification QA/QC 1. Design Process 2. Document Control 3. Records 4. Training / Qualification 5. Repair, Rework, Maintenance 6. Onsite Fabrication 7. Housekeeping 8. NCR's 9. Materials 10. QC Inspection 11. QA Secpe
- 12. As Built
i rs e TECHNICAL REVIEW TEAM (TRT) Project Director V.S. Noonan, NRR Assistant 1 R. Wessman Staff A. Vietti R.C. Tang J. Zudans-J l 1 I I Electrical / Civil / Mechan'ical QA/QC Leader Coatings Leader Test Programs InstrumenM ?. ion Leader Leader Lea:er J. Calvo, NRR L. Shao, RES H. Livermore, R-III C. McCracken, NRR R. Keimig, R-I n i L N L., i - Technical Issues Technical Issues - Programmatic and Technical Issues - Technical Issues Generic technical - Allegations Allegations issues and Allegations - Allegations allegations l QA/QC Related QA/QC Related QA/QC Related - QA/QC Related to E, I&C to Civil / Mech. - Integrate QA/QC to Coatings to Test Programs from other groups - Interface with other groups on QA/QC 9 e 9 e
Document Name: CP INFORMATION FOR TRT Requestor's ID: DEDIR01 Author's Name: Poslusny:Im Document Comments: Categories of Allegation Review e 4 l I
d .. c e,- 'o., UNITED STATES 8 NUCLEAR REGULATORY COMMISSION n g O *$ .t /b WASHINGTON, D. C. 20555 k..... # 4J I)EC 2 41984 MEMORANDUM FOR: Those on Attached List FROM: William J. Dircks Executive Director for Operations'
SUBJECT:
FORMATION OF PANEL TO PREPARE NRC STAFF POSITION ON COMANCHE PEAK HEARING CONTENTION NO. 5 The staff's formal positions on the Comanche Peak facility are nearing completion. The ASLB Hearings, which have been in progress for three years and are expected to resume in February 1985, have resolved all contentions except Contention,.No. 5. This contention concerns the Applicants' adherence to QA/QC requirements and is provided as Enclosure 1. The issue of construction QA/QC'at Comanche Peak is multi-faceted and is addressed, in part, by many records, documents and in testimony.from various sources including the Staff, Applicants, Intervenors, and Allegers. The background of this contention and associated records span several years. Various NRC offices have been involved, including Region IV, 01, NRR, OELD and IE. To properly evalu6te this contention and to prepare a comprehensive staff position, I am directing the formation of a panel composed of senior managers drawn from your offices. This panel is to be composed of the following individuals: Edward Jordan, IE (Chairperson) Richard Vollmer, NRR Alan Herdt, R-II Robert Warnick, R-III Roger Fortuna, 01 Because of their previous association with Comanche Peak regulatory activities, I am appointing the following advisors to the panel: Joe 5cinto, OELD Vince Noonan, NRR Thomas Ippolito, AE00 James Gagliardo IE Brooks Griffin. 01 Dorvin Hunter, R-IV Bruce Kaplan, EG&G The advisors may occasionally be asked to assist the panel when. issues involving their specific area of expertise are being considered, and I request your support in making them available on an "as-needed basis, i ~/ 3 Fot A 4 5 - 3 'a MN A /iq
a i Those on Attached List '. The product of the Panel's effort will be a report similar to a SSER, that states clear staff conclusions regarding this Contention. provides the outline of a Charter for this Panel. As the first order of business, the Panel will develop a working Charter which sh'all be submitted for my approval. The scheduled completion of the Panel's action is January 31, 1985. I expect the Panel to establish its own schedule, consistent with the resumption of the hearing process. Enclosure 3 provides a proposed milestone summary. ThePanelwillworkunderthedirectionofVincentS.Noonan,Directorof Comanche Peak Project, and should provide periodic status briefings to the Director of Licensing. kW[ William J. Dircks Executive Director for Operations
Enclosures:
As stated cc: B. Hayes, OI Panel Members Panel Advisors l L l l I f ~, - -., n-
e t Addressees List: Harold R. Denton, Director Office of Nuclear Reactor Regulation Richard C. DeYoung, Director Office of Inspection and Enforcement Guy H. Cunningham, III Executive Legal Director Jack Heltemes, Director Office of the Analysis and Evaluation of Operational Data James P. O'Reilly, Regional Administrator Region II James Keppler, Regional Administrator Region III Robert Martin, Regional Administrator Region IV l r
ENCLOSURE 1 COMANCHE PEAK CONTENTION 5* Contention 5. The Applicants' failure to adhere to the quality assurance / quality control provisions required by the construction permits for Comanche Peak, Units 1 and 2, and the requirements of Appendix B of 10 CFR Part 50, and the construction practices employed, specifically in regard to concrete work, mortar blocks, steel,' fracture toughness testing, expansion joints, placement of the reactor vessel for Unit 2, welding, inspection and testing, materials used, craft labor qualifications and working conditions (as they may affect QA/QC, and training and organization of QA/QC personnel, have raised substantial questions as to the adequacy of the construction of the facility. As a result, the Conmission cannot make the findings required by 10 CFR 50.57(a) necessary for issuance of an operating license for Comanche Peak. (CFUR 4A-ACORN 14-CASE 19 JOINT Contention) e ( I I I l
- Reproduced from Board Order Subsequent to the Pre-hearing Conference of April 30,1980 (dated June 16, 1980) e
(
I 2 ACTION ITEMS :
- 1) Define criteria for judging the adequacy of the Applicants' adherence to the QA/QC requirements described in Contention 5.
- 2) Conduct a records review. The Panel members should examine and analyze the following records.
a. CAT Report b. CYGNA Reports c. Hearing Records /Sumary Depositions d. 01 Reports e. Enforcement Actions f. SALP Reports g. Reg, IV. Inspection Reports h. TRT Reports 1. Special Rev.iew Team Report To make the workload manageable, sumaries of records or briefings to the panel by key individuals associated and familiar with the records may be requested.
- 3) Routinely interface with the Comanche Peak Intimidation Panel and consider input provided by that Panel.
- 4) For each type of records (a.-i.) the team members will prepare a sumary of findings highlighting problem areas and root causes, as related to Contention #5.
- 5) The panel, as a body, will consider the finding summaries, briefings provided by key NRC personnel, and other relevant information to I
develop the staff position on Contention #5 in the format of an SSER.
- 6) Tha panel will be required as necessary to provide both written and oral testimony before the ASLB.
l I l i l \\
j \\ ENCLOSURE 2 COMANCHE PEAK CGNTENTION b PANEL CHARTER OBJECTIVES f 1) To make the staff determination regarding the Applicants' adherence to the QA/QC requirements described in Contention 5. 2) Provide a report to managen.ent reflecting the panel's determination. 3) Provide panel testimony before the Comanche Peak ASLB. PURPOSE, The purpose of this Panel is to integrate the views and experience of senior NRC managers to yield a-staff determination regarding Contention 5. MFMBERSHIP Richard Vollmer,' NRR Edward Jordan, IE (Chairperson), Robert Warnick, R-III Alan Herdt, R-II Roger Fortuna, 01 Advisors Joe Scinto, OELD Vince Noonan, NRR Thomas Ippolito, AEOD James Gaglfardo, IE t Brooks Griffin, 01 Dorwin Hunter, R-IV Bruce Kaplan, EG&G O o l ~ I l l t
ENCLOSURE 3 CONTENTION 5 PANEL SCHEDULE December January Initial Panel Meet,ing Obtain relevant docuinents Document Reviews Consolidate Individual (Developed by Panel, consistent views, Develop Panel with resumption of hearings at consensus the end of January 1985) Prepare Panel Report Report Staff Position to Management Prepare Testimony l for ASLB 1 l l l
_=-- .. ~. 1 mr.\\ 8 UNITED STATES
- ,4 8
NUCLEAR REGULATORY COMMISSION o g %*****/,a WASHINGTON, D. C. 20855 .) DEC 2 41984 1 = MEMORANDUM FDR: Those on Attached List FROM: William J. Dircks Executive Director for Operations
SUBJECT:
FORMATION OF PANEL TO PREPARE NRC STAFF POSITION ON INTIMIDATION AT COMANCHE PEAK As the work of the Comanche Peak Technical Review Team (TRT) is nearing L j completion, the staff must evaluate all issues involving intimidation and -harassment at Comanche Peak. The ASLB hearings, which have been in progress i for three years and are expected to resume in February 1985, have insolved all contentions except Contention No. 5. This contention concerns the t Applicant's adherence to QA/QC requirements. As part of developing the staff. position on this Contention, the staff must evaluate whether intimidation or harassment occurring,.against empicyees or contractors occurred in the past or is now and make a detemination concerning the effects of any such intimidation on the overall QA/QC Program at Comanche Peak. ~ To properly evahate the intimidation issue and to prepare a comprehensive g staff position, I am directing the formation of a panel, composed of senior managers drawn from your offices. This panel is to be composed of the following individuals: James Gagliardo. IE (Chairperson) Jane Axelrad. IE James Lieberman, DELD Domin Hunter, Region IV BecauseoftheirpreviousassociationwithUomanchePeakregulatory activities. I am appointing the following individuals as advisors to the panel: Brooks Griffin, Of Thomas Ippolito, AEDD Joseph Scinto, DELD Vincent Noonan, NRR Bruce Kaplan EG&G The advisors may be asked to assist the panel.when issues involving their specific area of expertise are being considered, and I request your. support in making them available on an "as-needed" basis.' ~ The product o the Panel's effort will be a report similar to a SSER, that . states clear staff conclusions regarding the occurrence of intimida-tion and harassment at Comanche Peak. The Charter for this Panel is provided as Enclosure 1. The Charter provides the scope and objectives of the Panel but allows sufficient flexibility to enable the Panel to expand its scope, if necessary. yQ-jh38b (p ) t'O W % ~5 fh-/Y WlI5'
I.4 \\ t ge h a f ~ Those on Attached List i' I The scheduled. completion of the Panel's action is January 31,'1985. I expect the. Panel to meet at least once. per week and more frequently, if necessary. . provides a proposed milestone schedule'. The Panel will work under the d'irection of Vincent S. Noonan, birectorif .Comenche Peak Project, and should provide periodic status. briefings to the Director of Licensing. William. Dircks Executive Director for.Dperations
Enclosures:
As stated cc: B. Hayes, OI Pinel Members Panel Advisors Y, e 'l 9 een
- g. _
t .AddresseesTiIt: Harp 1d R. Denfon, Director Office of Nuclear Reactor Regulation Richard C. DeYoung, Director , Office of Inspection and_ Enforcement Guy H. Cunningham, III. Executive Legal Director -Jack Heltemes, Director . Office of the Analysis and Evaluation of Operational Data James Keppler Regional Administrator Region III. Robert Hartin, Regional Administrator ~ Region IV e e om W e S e D G .e e y. ~ _ _ _. :2. -
I ENCLOSURE 1 i_ ) Comanche Peak Intimidation Panel Charter ) OBJECTIVES: The objectives of the panel are: 1) To determine whether intimidation or harassment against employees or contractors occurre'd in the past or is now occurring at Comanche Peak; 2) To determine the extent'of the above conditions if they exist (ed) and to identify the circumstances surrounding the events including the personnel involved, the duration, the reasons for its occurrence and the applicant's manajement corrective. actions or recommendations for correc-tive actions. 3) To evaluate any other indicators of poor management practices or attitude toward the identification and correction of quality problems. PURPOSE: The panel will provide as products: 1) A po'sition on the intimidation question to NRC upper management; 2) Input to the Comanche Peak Contention 5 Panel. The Contention 5 P~nel a will determine the effects of any intimidation on the overall QA/QC Program at Comanche Peak. ' MEMBERSHIP: James Gagliardo IE (Chairperson)-- Jane Axelrad IE James Lieberman, DELD Dorwin Hunter, Region IV Bruce Kaplan EG8G Advisor Brooks Griffin 01 Advisor Thomas Ippolito AEOD (Advisor) Joseph Scinto, OELD Advisor Vincent Noonan, NRR Advisor 9 ? SM
- h---*-
,__s
--a..._...... l' ~ ACTION ITEMS S' ' -r 1. Define cs:iteria for detemining whether intimidation or harassment [ ..,, occurred. 2. Conduct as appropriate a review of relevant data bases: a. EGAS report on_ intimidation (9/84) b. Transcript of EG&G Intimidation Study Team briefing of NRC, applicant's, and intervenor's lawyers c. Enforcement packages related to intimidation. d. Depositions related to -intimidation and harassment. (A sumary will.be sought or prepamd as required) Proposed Tindings on intimidation (staff, applicants and e. .intervenors). f. Transcripts of: current ASLB hearings related to intimidation.. g. Office of Investigations reports on intimidation and status of outstandin the.above)gallegations. (B. Griffin should provide briefing on h. Information on Department'of. labor Hearings related to the subjects of concern. 3. Interface.with CP Contention 5 Panel routinely. 4. Based on the above data and any other" relevant data reviewed by the panel, develop a position which meets the stated objectives. 5. Prepare an SSER on intimidation, and provide testimony as required at ASLB hearings. f ~ e .__--__-__,w---,
i o i ENCLOSURE 2 ~ i 6 Intimidation Panel Schedule December January 5 Initial Panel Meeting, '.i Obtain' relevant documents Document Re. views Consolidate Individual (DevelopedbyPanel, consistent ~ views, Develop Farel with resumption of hearings a.t , consensus h the end of January 1985) Prepare Panel Input to QA/QC Panei Prepare Panel Report on Staff's Position m. b 4 O D f .00 s N _~
R. 44 eau 2 ![g g g 'g UNITED STATES NUCLEAR REGULATORY COMMISSION o
- gm,pg8. j wAsmuorow. o. c. 20sss J
y t a '+$,\\ / FEB 2 81985 MEMORANDUM FOR: Those on Attached List FROM: William J. Dircks Executive Director for Operations
SUBJECT:
PANEL TO PREPARE NRC STAFF POSITION ON COMANCHE PEAK HEARING CONTENTION NO. 5 On December 24, 1984, I established the subject panel and provided initial guidance regarding its charter. Since that time, the charter and the panel composition have been clarified to reflect a broader range of expertise and to acconinodate agency priorities. This memorandum reflects the panel's charter and changes. / To properly assist the Director, Comanche Peak Project in evaluating Contention 5 and to assist him in the preparation of a comprehensive staff position on Contention 5, a panel composed of senior managers has been fonned. The panel is composed of the following individuals: EdwardJordan,IE(Chairperson) Richard Vollmer, IE Alan Herdt, R-II Robert Warnick, R-III James Sniezek, DEDROGR U shok Thadani, NRR This contention concerns the applicant's adherence to QA/QC requirements and is provided as Enclosure 1. The issue of construction QA/QC at Comanche Peak is multifaceted and is addressed, in part, by many records, documents and in testimony from various sources including the staff, applicant, intervenor, and allegers. The background of this contention and associated records span several years. Various NRC offices have been involved, including Region IV, 01, NRR, OELD and IE. Because of their involvement with Comanche Peak regu-latory activities, I am appointing the following personnel as resource support to the panel in their areas of expertise: Joe Scinto, OELD Vince Noonan, NRR Thomas Ippolito, AE00 James Gagliardo. IE Brooks Griffin, OI Dorwin Hunter, R-IV Chet Poslusny, NRR* Ted Sullivan, NRR* -gff3I-5fSYl' f
- Administrative and technical support as requested by Panel Chairman Foi er ts-3m ju- /d ky'Ito
o These individuals may be asked to assist in this effort when issues involving their specific area of expertise are being considered, and I request your support in making them available on an "as-needed" basis. The product of this effort will be the assistance to the Director, Comanche Peak Project, in preparing a position that integrates the staff findings and conclusions regarding this Contention. In addition this effort may require panel members, or the panel as a whole, to be prepared to testify concerning panel recommendations in support of the staff position on Contention 5 as identified by the Director, Comanche Peak Project. provides the charter for the panel. The work schedule of the panel as developed by the Director, Comanche Peak Project, is to be consistent with the hearing schedule and shall be closely coordinated with ELD. The panel will work under the direction of Vincent S. Noonan, Director, Comanche Peak Project, and should provide periodic status briefings to the Deputy Director, NRR. Y l IM\\ Willia ircks Executive Director for Operations
Enclosures:
As stated cc: Panel Members Panel Resource Personnel T. Murley J. Martin l i l l
4 d ADDRESSEES FOR MEMORANDUM DATED FEB 2 s 95 Victor Stello, Jr, DEDROGR Harold R. Denton, NRR James Taylor, IE Guy H. Cunningham, III, ELD Clemens J. Heltemes, AE0D Nelson Grace, RII James Keppler, RIII Robert Martin, RIV Ben Hayes OI O b
-) ENCLOSURE 1 COMANCHE PEAK CONTENTION 5* Contention 5. The Applicants' failure to adhere to the quality assurance / quality control provisions required by the construction permits for Comanche Peak, Units 1 and 2, and the requirements of Appendix B of 10 CFR Part 50, and the construction practices employed, specifically in regard to concrete work, mortar blocks, steel, fracture toughness testing, expansion joints, placement of the reactor vessel for Unit 2, welding, inspection and testing, materials used, craft labor qualifications and working conditions (as they may affect QA/QC) and training and organization of QA/QC personnel, have raised substantial questions as to the adequacy of the construction of the facility (.the Commission can As a result, ~ for issuance of an operating license for Comanche Peak. (CFUR 4A-ACORN 14-CASE 19 JOINT Contention) i
- Reproduced from Board Order Subsequent to the Prehearing Conference of April 30,1980(datedJune 16,1980)
ENCLOSURE 2 COMANCHE PEAK CONTENTION 5 PANEL CHARTER I. PURPOSE The purpose of this panel is to assist the Director, Comanche Peak Project, to evaluate in an integrated manner the information developed by the staff which bears upon QA/QC and overall plant quality. The objectives are: A. To assist the Director, Comanche Peak Project to make the staff determination regarding the findings required by 10 CFR 50.57(a) as related to Contention 5. B. To provide an integrated review and feedback to the Director, Comanche Peak Project, on information bearing on Contention 5 along with the identification of problem areas and appropriate recommendations for NRC actions or proposed solutions. C. To be prepared to testify as needed individually or as a panel, concerning panel recommendations in support of the staff position on Contention 5 as identified by the Director. II. MEMBERSHIP EdwardJordan,IE(Chairperson) Richard Vollmer, IE Alan Herdt, R-II Robert Warnick, R-III James Sniezek, DEDROGR Ashok Thadani, NRR P III. PANEL SCOPE l l A. Under the guidance of the Director, Comanche Peak Project the panel shall become familiar with and consider findings of past j and current NRC staff activities and applicant actions in response i to NRC findings as they relate to the matters addressed in l Contention 5. Specifically, the panel shall consider the results of: 1) Region IV inspections 2) CAT inspections l l 1
3 OI investigations 4 Technical Review Team inspections 5 Enforcement actions 6 Special Review Team inspection 7 SALP reports 8 Staff analysis of CYGNA Report 9 Staff sumary of the Hearing Record Additionally, the panel may examine the result of other staff activities which may bear on their findings related to Contention 5 if directed to do so. B. The Director, Comanche Peak Project will arrange for staff members to t-fef the panel on findings related to Contention 5. The Director will also set up meetings with the intervenor and the applicant to discuss matters which they respectively believe are most significant as related to Contention 5. Any such meetings will be open to the public. The panel should properly characterize the collective concerns raised by the staff, intervenor and applicant and review /coment on the applicants plan to address these concerns. The panel should then advise the Director, Comanche Peak Project on its recomendations. C. During conduct of panel activities, the panel should advise the Director, Comanche Peak Project of areas where it appears additional NRC activity may be warranted in order to address the issues raised U in Contention 5. IV. PANEL OPERATING PROCEDURES A. Panel meetings will be held as established by the Chairperson. The Director, Comanche Peak Project will arrange all meetings with the applicant, intervenor or allegers. Meetings with NRC staff and staff consultants shall be considered predecisional. B. A quorum for conduct of panel business will consist of four members. In the temporary absence of the Chairperson, the Chairperson may designate an acting Chairperson. C. Briefings by the principal NRC reviewers in each of the areas identi-fied in Section III.A will be obtained. Reviewers will sumarize the scope of their reviews, deficiencies noted, root causes of such deficiencies and applicant corrective actions. Likewise, the reviewers are to discuss those areas where no deficiencies were found. l D. The panel should analyze D e information presented by NRC reviewers contained in source documents which the panel reviews, obtained by discussions with the applicant, intervenor and staff and observed during site reviews in arriving at its recomendations regarding Contention 5 and should continually provide feedback to the Director, Comanche Peak Project. I
l a s E. The panel should keep apprised of the ongoing agency activities related to Contention 5 and promptly identify conflicts or problems to the Director, Comanche Peak Project. V. RECORD AND REPORTING A. The panel will work under the direction of Vincent S. Noonan, Director of the Comanche Peak Project, and should provide periodic status briefings to the Deputy Director, NRR. L B. The 'ai.e ~
- , :1 keep such records of activities to assist it in arris."-
. commendations regarding Contention 5, as requested by the Lirector. Such records shall be considered predecisional until staff testimony regarding Contention 5 is provided to the Hearing Board. O l l t.
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s CPRT PRESENTATION TO CONTENTION 5 PANEL FEBRUARY 7, 1985 O
9
./}Y
)Wy TRT CIVIL / STRUCTURAL, MECHANICAL AND MISCELLANE0US ISSUES f f, (Y Y CIVIL / STRUCTURAL
' I.
C - ELECTRICAL CONDUIT SUPPORTS
' II. A - REINFORCING STEEL IN THE REACTOR CAVITY
' II. B - CONCRETE COMPRESSION STRENGTH
- II. C - MAINTENANCE OF AIR GAP BETWEEN CONCRETE STRUCTURES
' II. D - SEISMIC DESIGN OF CONTROL ROOM CEILING ELEMENTS
' II. E - REBAR IN THE FUEL HANDLING BUILDING MECHANICAL
' V. A - IdSPECTION FOR CERTAIN TYFES OF SKEWED WELDS Ill NF SUPPORTS
' V. B - Il1 PROPER SHORTENING OF ANCHOR BOLTS IN STEAM GENERATOR UPPER LATERAL SUPPORTS
' V, C - DESIGN CONSIDERATION FOR PIPING SYSTEMS BETWEEll SEISMIC CATEGORY I AND NON-SEISMIC CATEGORY I BUILDINGS
' V. D - PLUG WELDS
' V. E - INSTALLATION OF MAIN STEAM PIPES MISCEll ANE01LS
' VI. A - GAP BETWEEN REACTOR PRESSURE VESSEL REFLECTIVE INSULATION AND THE BIOLOGICAL SHIELD WALL
- VI. B - POLAR CRANE SHIMMlllG
MAliiTENANCE OF AIR GAP BETWEEN CONCRETE STRUCTURES JSSl{EDESCRIP_LLQd'
' EXTENT AND LOCATION OF DEBRIS BETWEEN STRUCTURES
' EFFECTIVENESS OF GC PROGRAM
- RECORD RETENTION
- FOLLOW-UP FOR UNSATIFACTORY CONDITIONS CONSISTENCY OF AS-BUILT C0fjDITION AND SEISf1IC ANALYSES BACKGROUNH FORMINGTECHNIQUES/ LOCATIONS
' HISTORY
' ENGINEERING SIGNIFICANCE OF ISSUE i
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~
REPORTING /
en INTERFACE
.E'*YEE't EXTERNAL TRT REPORT I
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PEaronu PNoritt or As-eviti PEnronu raoriLE or As-euiLT coNo,rioN roa sttEcTEo comoifioN ron stLecTEo utTAL FISPECTION/
actorotu ronuwons Antas
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THIRD res PARTY ACTIVITIES
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MAINTENANCE OF AIR GAP BETWEEN CONCRETE STRUCTURES (CONT.)
IUITIATIVES
' PROFILIllG OF CURRENT AS-BUILT CONDITION VIA VIDEO INSPECTION
- OVERVIEW BY SOUTHWEST RESEARCH INSTITUTE
' DETERMINATION OF CAUSE VIA:
- REVIEW OF C0ilSTRUCTION HISTORY
- REVIEW 0F AVAILABLE DOCUMEllTATION
- EVALUATION OF AS-BUILT CONDITION
' ASSESSMENT OF DESIGN ADEQUACY OF AS-BUILT CONDITION
^
- DESIGN REVIEW 0F CALCULATIONS
- REMOVAL OF DEBRIS (AS RE0'D)
STATUS
' DOCUMENTATION / HISTORICAL REVIEW COMPLETE
' AS-BUILT (VIDEO) PROGRAM INITIATED
- 10 L.F./ DAY / CREW (1 CREW, ADDING 1 MORE)
- APPROX. LI65 L.F. TOTAL SCOPE
' NRC SITE VISIT TO WITNESS GAP INSPECTIONS -
JANUARY 21 l
l l
SEISMIC DESIGN OF CONTROL ROOM CEILING ELEMENTS ISSUE DESCRIPTION
- SEISMIC DESIGN ADEQUACY OF CONTROL ROOM CEILING ELEMENTS
- FUNCTIONAL I.MPACT TO SAFETY RELATED EQUIPMENT
- INJURY TO OPERATORS
' INTERACTION 0F NON-SEISMIC AND SEISMIC CATEGORY II ITEMS WITH SEISMIC CATEGORY I ITEMS
- ADEQUACY OF SEISMIC CATEGORY II CRITERIA
- EVALUATION OF ARCHITECTRUAL FEATURES 2
' ADEQUACY OF NON SAFETY CONDUIT 2 INCHES DIAMETER AND LESS
- ANCHORAGE AND SUPPORT, OR
- DAMAGE ASSESSMENT 9
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SEISMIC DESIGN OF CONTROL ROOM CEILING ELEf1ENTS (Coll'T)
BACKGROUND
' RG 1.29 DESIGN CONCEPT FOR CR CEILING
' SEISMIC CATEGORY I AND II CRITERIA
' DAMAGE STUDY INITIATIVES
' CR CEILING DESIGN CHANGES
- ARCHITECTURAL ITEMS
- UNISTRUT SYSTEM
' ARCHITECTRUAL FEATURES / DAMAGE STUDY
_ METHODOLOGY / KEY ASSUMPTIONS
- If1PLEMENTATION
- EVALUATION OF ARCHITECTURAL FEATURES / CAT II CRITERIA
- EVALUATION OF SEISMIC INTERACTIONS AB0VE CR CEILING STATUS
' SLOPED WALL REMOVED / METAL PAN BEING INSTALLED
' ARCHITECTURAL FEATURES DESIGN COMPLETE UNISTRUT LATERAL RESTRAINT SYSTEM IN DESIGN
' ARCHITECTURAL FEATURES DAMAGE STUDY COMPLETE
' MARCH COMPLETION
CONCRETE COMPRESSION STRENGTH ISSUE DESCRIPTION ADEQUACY OF CONCRETE STRENGTH FALSIFICATION OF RECORDS BACKGROUND NRC REGION IV AND TRT INVESTIGATIONS
- PERIOD IN QUESTION:
1/76 - 2/77
" EVIDENCE SUGGESTS FALSIFICATION OF RESULTS DID NOT TAKE PLACE" l
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CONCRETE COMPRESSION STRENGTH (CON'T)
INITIATIVES
' VERIFICATION OF QUALITY OF PLACED CONCRETE VIA TEST
- RAND 0M SAMPLE FOR TWO POPULATIONS
- SCHMIDT HAMMER TESTING BY SOUTHWEST RESEARCH INSTITUTE
- STATISTICAL COMPARISON OF TEST RESULTS OF PERIOD IN OUESTION TO PERIOD SIX MONTHS FOLLOWING
' USE OF STATISTICAL CONSULTANTS
- JACK BENJAMIN AND ASSOCIATES
- DR. DANIELE VENEZIANO, M.I.T.
STATUS
' POPULATIONS IDENTIFIED / SAMPLE SELECTED
' 107/200 TESTS COMPLETE
' 47 TEST LOCATIONS BEING PREPARED, REMAINING 46 READY FOR TESTING
' NRC STAFF SITE VISITS
- JANUARY 7 - PREPARATION
- JANUARY 21 - TESTING
' MARCH COMPLETION
IMPROPER SHORTENING OF ANCHOR BOLTS IN STEAM GENERATOR UPPER LATERAL SUPPORT ISSUE DESCRIPTION
' STRUCTURAL ADEQUACY OF AS-BUILT CONDITION
- ADEQUACY OF OTHER DRILLED AND TAPPED CONDITIONS
' UNAUTHORIZED BOLT CUTTING / ADEQUACY OF FIELD INSTALLATION PROCEDURES
' EFFECTIVENESS OF QC PROGRAM
,- RECORD RETENTION
- INSPECTION PROGRAM BACKGROUND l
' FUNCTIONAL REQUIREMENTS OF SG UPPER LATERAL l
SUPPORTS
' SG UPPER LATERAL SUPPORT DETAILS
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IMPROPER SHORTENING OF ANCHOR BOLTS IN STEAM GENERATOR UPPER LATERAL SUPPORT (CON'T)
INITIATIVES
' UT~ INSPECTION TO DETERMINE BOLT ENGAGEMEllT
' EVALUATION DESIGN REQUIREMENTS F0R SG UPPER LATERAL SUPPORTS
' MODIFICATION (AS REQUIRED)
- VIDE 0 0F H0LES
' IDENTIFICATION OF OTHER DRILLED AND TAPPED CONNECTIONS
~
- SAMPLE SELECTION
- INSPECTION /3RD PARTY OVERVIEW
- EVALUATION
' REVIEW 0F BOLT CUTTING PROCEDURES AND CONSTRUCTION INSTALLATION PROCEDURES STATUS
- UT INSPECTION COMPLETE
' THIRD PARTY DESIGN REVIEW IN PROGRESS
' MODIFICATIONS TO BEGIN SHORTLY
' NRC SITE VISIT - 2/6
' MARCH COMPLETION l
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SliMMARY INITIATIVES FOR HIGHLIGHTED ISSUES ARE REPRESENTATIVE OF OTHER ISSUES ESTIMATED COMPLETION IN MARCH - APRIL TIME FRAME i
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TRT ELECTRICAL ISSUES hE Y
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1.A.1 HEAT SHRINKABLE CABLE INSULATION SLEEVES I.A.2 INSPECTION REPORTS ON BUTT SPLICES I.A.3 BUTT SPLICE QUALIFICATION I.A.4 AGREEMENT BETWEEN DRAWINGS AND FIELD TERMINATIONS 1
I.A.5 NCR's ON VENDOR INSTALLED AMP TERMINAL LUGS I.B.1 FLEXIBLE CONDUIT TO FLEXIBLE CONDUIT SEPARATION I.B.2 FLEXIBLE CONDUIT TO CABLE SEPARATION I.B.3 CONDUIT TO CABLE TRAY SEPARATION I.B.4 BARRIER REMOVAL I
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+I BUTT SPLICES IN CONTROL PANELS
/f ISSUES i
1 1
INSPECTION REPORTS DID HOT INDICATE THAT ALL SPLICE INSTALLATIONS WERE WITNESSED l
' QUALIFICATION REQUIREMENTS FOR BUTT SPLICE SLEEVES WERE NOT DOCU'MENTE
' BUTT SPLICES WERE NOT STAGGERED TO PREVENT TOUCHING EACH OTHER i
' INSTALLATION PROCEDURES DID NOT REQUIRE VERIFICATION OF CIRCUIT OPERABIL i
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Y4 TRT CONCERNS WITH BUTT' SPLICES 1.
THAT INSPECTION REPORTS DID NOT INDICATE THAT THE REQUIRED WITNESSING OF SPLICE INSTALLATION WAS DONE.
2.
THAT DRAWINGS DID NOT REFLECT THE LOCATION OF ALL BUTT SPLICES.
3.
THAT THE BUTT SPLICES WERE NOT QUALIFIED FOR THE SERVICE CONDITIONS.
fl.
THAT BUTT SPLICES WERE NOT STAGGERED SO AS TO NOT TOUCH EACH OTHER.
5.
THAT THERE WAS A LACK 0F PROVISIONS IN THE INSTALLATION PROCEDURES TO VERIFY THE OPERABILITY OF THE SPLICED CIRCUITS.
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BUTT SPLICES IN CONTROL PANELS INITIATIVES PHASE 1
' RETRAIN CABLES TO PREVENT SPLICES FROM TOUCHING ONE ANOTHER I
' REVISE PROCEDURES FOR TIGHTER CONTROL
' QUALIFY BUTT-SPLICE SLEEVES FOR SERVICE CONDITIONS
' REVIEW ADDITIONAL INSPECTION REPORTS FOR SPLICE WITNESSING PHASE 2
' THIRD PARTY INSPECTION OF BUTT! SPLICES IN PANELS
' UPDATE AND CORRECT DESIGN DOCUMENTS j
' CORRECT HARDWARE DEFICIENCIES l
' THIRD PARTY REVIEW 0F ALL INSPECTION REPORTS I
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BUTT SPLICES IN CONTROL PANELS STATUS t
' PHASE 2 INSPECTIONS COMPLETE IN CONTROL AND CABLE SPREADING ROOMS l
' CORRECTION OF HARDWARE DEFICIENCIES BEGUN
' DOCUMENTATION REVIEW BEGUN
'OTHER BUTT SPLICES HAVE BEEN IDENTIFIED FOR INSPECTION
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BUTT SPLICES IN CONTROL PANELS INITIATIVES i
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' EVALUATE SAFETY SIGNIFICANCE 4
' DETERMINE NEED TO INVESTIGATE RELATED AREAS DETERMINE ROOT CAUSE AND QA/QC IMPLICATIONS I
'TAKE LONG TERM CORRECTIVE ACTION I
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CONCERN MATRIX CONCERN CORRECTIVE ACTION WR0ilG CRIMP REPLACE REVISE PROCEDURES TOOL USED RETRAIN ELECTRICIANS WIRE STRANDS REPLACE REVISE PROCEDURES CURLED RETRAIN ELECTRICIANS INSULATION SPLIT REPLACE SAME AS AB0VE OR IMPROPER HEAT SHRINK UNSATISFACTORY CORRECT ISOLATED - NO LONG TERMINATIONS TERM ACTION REQUIRED INSPECTIONS CHECK TRAINING REVISE PROCEDURES INADEQUATE AND CERTIFICATIONS RETRAIN INSPECTORS INSUFFICIENT CONDUCT TESTS REINSPECT A!!D/UR CONDUCTOR PENETRATI0il ON REMOVED CONDUCTORS REPLACE ALL CONCERNS DETERMINE SAFETY ESTABLISH ROOT CAUSES SIGNIFICANCE THROUGH AND LINK TO QA/QC TESTS AHD/0R REVIEW 0F CONCERNS FUNCTION
FLEXIBLECONDUlfANDCABLE i
SEPARATION IN CONTROL ROOM PANELS ISSUES l
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'NO ANALYSIS WAS PERFORMED TO ALLOW USE OF FLEXIBLE CONDUIT AS A BARRIER IN CONTROL ROOM PANELS.
'SOME FLEXIBLE CONDUITS CONTAINING REDUNDANT TRAIN CABLES WERE
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l SEPARATED BY LESS THAN INCH OR WERE TOUCHING.
' CABLES IN CONTROL PANELS WERE IN DIRECT CONTACT WITH CONDUITS CONTAINING REDUNDANT TRAIN CABLES.
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FLEXIBLE CONDUIT AND CABLE SEPARATION IN CONTROL ROOM PANELS INITIATIVES
' PROVIDE ANALYSIS FOR THE USE OF FLEXIBLE CONDUIT PROVIDE INSPECTION CRITERIA FOR THIRD PARTY REINSPECTION OF PANELS
' THIRD PARTY REINSPECTION OF PANELS
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SEPARATION IN CONTROL ROOM PANELS STATUS
' DRAFT ANALYSIS BEING REVIEWED BY THIRD PARTY CONSULTANT
' INSPECTION CRITERIA HAS BEEN PROVIDED AND REINSPECTION PROCEDURES WRITTEN
' PHYSICAL TEST OF CABLE AND FLEXIBLE CONDUIT UNDER CONSIDERATION m
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- *4 TESTliiG PROGRAM OVERVIE'd 3
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TESTING PROGRAM ISSUES
- IDENTIFIED I!! 9/18/84 NRC LETTER TO BE EVALUATED IN SSER NO. 7 ISSilE SPECIFIC ACTI0fi PLA!iS
- (D HOT FUNCTIONAL TESTING (HFT) DATA PACKAGES (2) JTG APPROVAL OF TEST DATA (3) TECHilICAL SPECIFICATI05 FOR DEFERRED TESTS (4) TRACEABillTY OF TEST EQUIPMENT (S) CQi4 DUCT OF THE CILRT
- (6) PREREQUISITE TESTING (7) PREGPERATIONAL TESTING "To BE SPECIFICALLY PRESENTED
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HOT FUNCTIONAL TESTING (HFT) DATA PACKAGES 90 9
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' ISSUES
- NOT ALL TEST OBJECTIVES MET Irl THREE OF 17 PACKAGES th REVIEWED
- RETESTING NOT ADEQUATE
- OVERSIGHTS BY JOINT TEST GROUP (JTG) WHICH HAD PREVIOUSLY APPROVED DATA PACKAGES
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ISSUE SPECIFICS (1) BUS VOLTAGE TEST
'TRANSFORf1ER TAPS NOT IN CORRECT POSITION DURING TEST
~
'N0 RETEST PERFORMED AFTER REPOSITIONING TAPS (2)
STEAM GENERATOR LEVEL INSTRUMENTATION VERIFICATION 7" 9/D
'3 TEMPORARY TRANSMITTERS DURING TEST
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' HOT RETEST NOT SPECIFIED p
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PRESSURIZER LEVEL CONTROL
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'l1ARGINAL READINGS Oil ONE TRANSMITTER /
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' TRANSMITTER REPLACED Y fk
' HOT RETEST NOT SPECIFIED O
e INITIATIVES - HFT DATA PACKAGES JTG RE-EVALUATE APPROVED TEST RESULTS PACKAGES
'USING SPECIAL SAMPLING PLAN USING SPECIFIC GUIDELINES BASED ON TRT CONCERNS GUIDELINES APPROVED BY REVIEW TEAM LEADER AND SRT
'RE-EVALUATION CRITERIA INCLUDE:
- FSAR COMMITMENTS SATISFIED
- TEST OBJECTIVES-FULFILLED
- RETESTS PROPERLY SPECIFIED
- REG. P0S.
C.3 0F R.G.
1.68 PROPERLY APPLIED
- REVIEW TEAM LEADER MONITOR AND~ APPROVE RE-EVALUATION PROCESS AND RESULTS
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6 RE-EVALUATION AND SAMPLING PLAN t[
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- 3 PACKAGES QUESTIONED BY TRT 9: / / (( ty g
- 7 REMAINING HFT PACKAGES 49 3
- 20 PACKAGES AMONG tt0ST If1PORTANT TO SAFETY y
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- SECOND 20 IF ONE REJECT IN FIRST 20
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- ALL REMAINING IF ONE REJECT IN SECOND 20 Jr Y[/
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- IF NOT NECESSARY TO EXPAND, RAND 0M SAMPLE N"
AND RE-EVALUATE GUIDELINE ATTRIBUTES IN REMAINING PACKAGES
' ACTION PLAN STATUS
- 3 QUESTIONABLE PACKAGES EVALUATED
' BUS VOLTAGE TEST TO BE REPERFORMED
- TEST OBJECTIVES NOT CLEARLY STATED
- ACCEPTANCE CRITERIA MISLEADING
'OTHER 2. TRANSMITTERS TO BE CHECKED AT PROCEDURE -
SPECIFiED CONDITIONS
' SAFETY SIGNIFICANCE APPEARS TO BE NIL.
OUTCOME OF BUS VOLTAGE TEST WILL GOVERN.
- 7 REMAINING HFT PACKAGES RE-EVALUATED
'N0 REJECTS
- FIRST 20 RE-EVALUATIONS NEARING COMPLETION
'18 APPROVED BY JTG
' 5 REVIEWED / APPROVED BY THE REVIEW TEAM LEADER
'N0 REJECTS THUS FAR
' ACTION PLAN STATUS (CONT'D)
- FURTHER ACTIONS
' STARTED RAND 0M. SAMPLING PROCESS
' IDENTIFYING, LISTING GUIDELINE ATTRIBUTES
- FSAR COMMITMENTS
- TEST DEFICIENCY REPORTS
- TEST PROCEDURE DEVIATIONS
~
PREREQUISITE TESTING ISSUES
- MEM0 ISSUED THAT CHANGED PROCEDURAL REQUIREMENTS
- PROCEDURE NOT REVISED AS FOLLOW-UP
- POSSIBILITY PREREQUISITE CONDITIONS FOR OTHER PREREQUISITE TESTS SIGNED BY UNAUTHORIZED CRAFT PERSONNEL
- IF SITUATION HAD GREATER BREADTH, DID IT ADVERSELY IMPACT ON SUBSEQUENT TESTING?
- POSSIBILITY OTHER MEMOS ISSUED TO MODIFY PROCEDURAL REQUIREME
~
' ISSUE SPECIFICS
- MEMO SIM-83084 ISSUED MARCH 31, 1933 BY STARTUP MANAGER
' AUTHORIZED ELECTRICAL TEST GROUP (ETG) PERSONNEL TO VALIDATE PREREQUISITE CONDITIONS FOR TWO TYPES PREREQUISITE TEST PROCEDURES.
'CP-SAP-21 REQUIRES THIS DONE BY SYSTEM TEST ENGINEER
'CP-SAP-21 NOT REVISED TO REFLECT MEMO AUTHORIZATION PER CP-SAP-1 4
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'tf Y(Y, g'/q ISSUE SeEcIPlcS <CONr m
- OTHER PREREQUISITE TESTS PRE-CONDITIONS SIGNED BY 3s qo e
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UNAUTHORIZED CRAFT PERSONNEL?
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f SEVERAL OTHER TYPES PREREQUISITE TEST PROCEDURES h
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' SIGNING BY UNAUTHORIZED CRAFT PERSONNEL MAY HAVE OCCURRED d M
FOR OTHER TYPES OF TESTS
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' PREREQUISITE TESTS PREPARE FOR PREOPERATIONAL TESTS
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'WAS THERE ADVERSE IMPACT ON SUBSEQUENT PRE 0P TESTS?
I
' INITIATIVES
- MEMO SIM-83084 IMMEDIATELY RESCINDED
' ISSUED SIM-84220 DATED SEPTEMBER 25, 1984'T0 RESCIND
' SYSTEM TEST ENGINEERS RE-INSTRUCTED REGARDING THE MATTER
' CRAFT PERSONNEL RE-INSTRUCTED i
- ALL STARTUP INTEROFFICE MEMORANDA (SIM) REVIEWED FOR SIMILAR SITUATIONS
- ALL OTHER PREREQUISITE TESTS REVIEWED FOR SIMILAR HANDLING
- IMPACT ON SUBSEQUENT PRE 0P TESTS BEING EVALUATED
- SIGNIFICANCE OF NOT ADHERING TO PROCEDURE. REQUIREMENT BEING EVALUATED
j
' ACTION PLAN STATUS
- NO OTHER SIMILAR MEMO SITUATIONS HAPPENED
- OTHER PREREQUISITE TEST PRE-CONDITIONS WERE SIGNED BY UNAUTHORIZED CRAFT PERSONNEL
- PLANS FOR EVALUATING IMPACT ON SUBSEQUENT PRE 0P TESTS BEING DEVELOPED
- PLANS FOR EVALUATING SIGNIFICANCE OF NOT ADHERING TO PROCEDURE REQUIREMENT BEING DEVELOPED 4
.k CONCLUDIllG REMARKS
' PRESEllT SCHEDULE TO FINISH FIRST DRAFTS OF RESULTS REPORTS IN MARCH
' DESIGN DOCUMENT CONTROL CONCERNS MAY EXTEND ONE ISSUE
' TO DATE, NOTHING OF SAFETY SIGNIFICANCE HAS BEEN FOUND
' MY OBSERVATIONS INDICATE TESTING WAS PERFORMED BY A GROUP 0F EXPERIENCED PROFESSIONAL TESTING PERSONNEL
l QA/QC AREA l
' SEPTEMBER 18, 198tl LETTER 1
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- I.D.1 INSPECTOR QUALIFICATIONS
- I.D.2 INSPECTOR TESTING
- WILL DISCUSS B0Til TOGETHER
' JANUARY 8, 1985 LETTER
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INSPECTOR QUALIFICATION / CERTIFICATION ISSUE AND BACKGROUND INFORMATION PHASE I - DETAILED REVIEW 0F FILES PHASE II - EVALUATION OF QUESTIONABLE CERTIFICATION PHASE III - DETAILED EVALU TION OF PERSONS NOT PROPERLY QUALIFIED RELATED ACTIONS
INSPECTOR.
QUALIFICATION / CERTIFICATION ISSUES:
ADEQUACY OF SUPPORTIVE DOCUMENTATION REGARDING PERSONNEL
,fD QUALIFICATIONS IN TRAINING / CERTIFICATION Fli_ES.
e BACKGROUND:
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' AT TIME OF CP,10GC0 WAS COMMITTED TO 10 CFR 50 APP. B.
O'
/
' PERFORMANCE DEMONSTRATED BY EXAMINATION, VERIFIED BY 0JT
' 1981
- COMMITTED TO REG. GUIDE 1,58 REV. 1
' SAME AS AB0VE PLUS VERIFICATION OF EDUCATION / EXPERIENCE
' INSPECTORS TRAINED AND CERTIFIED TO SPECIFIC PROCEDURES / INSTRUCTIONS t
EACH INSPECTOR MAY HOLD MULTIPLE CERTIFICATION
ACTION - PHASE I
' TUGC0 AUDIT GROUP REVIEWED TRAINING, QUALIFICATION, CERTIFICATION, RECERTIFICATION FILES FOR:
' ALL ELECTRICAL INSPECTORS (CURRENT AND PAST)
' NON-ASME INSPECTORS (CURRENT)
'ASMEINSPECTORS(CURRENT)
' RECENT DECISION BASED ON NRC LETTER DATED 1/8/85
- CONDUCTED BY INDEPENDENT SPECIAL EVALUATION TEAM (SET)
' RESULTS
' TUGC0' AUDIT REVIEWED FILES FOR:
' 215 INSPECTORS
' 2386 CERTIFICATIONS
' CERTIFICATION
SUMMARY
FORMS PREPARED FOR EACH INSPECTOR ' EFFORT WAS AUDITED BY SET ' TO BE REVIEWED BY SET ' 133 INSPECTORS ' 270 CERTIFICATIONS
~ ~ ACTION PLAN - PHASE II ' SPECIAL EVALUATION TEAM INDEPENDENT MINIMUM 5 YEARS MANAGEMENT / SUPERVISORY QA/0C EXPERIENCE ' CONDUCTED A DETAILED REVIEW 0F EACH FILE ' SET REVIEW TO DETERMINE EXPERIENCE ' EDUCATION ' FORMAL TRAINING AT CPSES ' 0JT ' RESULTS OF WRITTEN EXAMINATIONS ' OTHER VALID CERTIFICATIONS IN RELATED AREAS CONSISTENT APPLICATION OF CRITERIA FOR EVALUATING RELATED EXPERIENCE ' RESULTS DOCUMENTED FOR EACH INSPECTOR CERTIFICATION, FILES UPDATED
O ACTION PLAN - PilASE 11 REQUIRE FURTilER RECORDS EVALUATION QUEST 10llABLE CATEGORY UPDATE REQUIRED QUALIFICATI0flS TOTAL CURRENT ELECTRICAL 25 3 28 CURRENT OTHER DISCIPLINES 38 38 CURRENT LEVEL 111 15 1 1 17 HISTORICAL ELECTRICAL 36 1 13 50 t TOTAL 1 111 5 133 /t b t g/!l)egl v
ACTION PLAN . PHASE III DETAILED EVALUATION OF QUESTIONABLE QUALIFICATIONS ' DETERMINE SAFETY RELATED WORK ACCOMPLISHED BY EACH INSPECTOR IN CHRONOLOGICA ORDER. ' IS IT STILL ACCESSIBLE, UNDISTURBED AND RECREATABLE? ' DEFINE WORK ACCOMPLISHED IN FIRST 90 DAYS, ' REINSPECT WORK ' USE THIRD PARTY INSPECTORS (ERC) INSPECT USING ORIGINAL CRITERIA ' EVALUATE RESULTS ' OBJECTIVE - 95% AGREEMENT ' SUBJECTIVE - 90% AGREEMENT ' IF INSPECTOR FAILS CRITERIA - INPUT NEXT 90 DAYS EFFORT ' EVALUATE TO SAME CRITERIA ' IF INSPECTOR FAILS - REINSPECT ALL REMAINING WORK ' INSPECTORS WHO DO NOT HAVE A SUFFICIENT NUMBER OF INSPECTIONS ' EVALUATE WORK FOR SAFETY SIGNIFICANCE ' IDENTIFY SUBSEQUENT INSPECTIONS THAT CAN VALIDATE RESULTS ' PERFORM OTHER TESTS OR INSPECTIONS . DOCUMENT HOW EACH CASE IS DISPOSITIONED
.d ) f RELATED ACTIONS 9g / ' RTL PROVIDE RECOMMENDATIONS ON IMPROVEMENTS TO CURRENT PROCEDURES ' CERTIFICATION PROCEDURES ' CERTIFICATE FILES ' TESTING PROCEDURES & CONTROLS ' COMPUTERIZED SYSTEM FOR TRACKING ALL CERTIFICATION /RECERTIFICATION ACTIONS ' NEW APPROACH TO INSPECTOR TESTING- ' BANKS OF QUESTIONS BEING DEVELOPED BY DISCIPLINE ' QUESTIONS CAN BE SCRAMBLED ' SYSTEM OPERATIONAL BY MID APRIL ' TRAIN TUGC0 QE's ON HOW TO TRAIN INSPECTORS MORE EFFECTIVELY ' INSPECTION PROCESS CONTROL SYSTEM ' EVALUATE INSPECTION ACTIVITIES, STUDY RESULTS, RECOMMEND IMPROVEMENTS ' INSPECTION RESULTS TRENDED TO IDENTIFY WEAKNESSES ' RESULTS TRENDED TO IDENTIFY CAUSE OF DISCREPANCY - IDENTIFY PREVENTATIVE ACTIONS
SUMMARY
i APPROACH WILL ENABLE SRT/TUGC0 TO IDENTIFY WEAKNESSES. IN CERTIFICATI0ft PROCESS
- IDENTIFY INSPECTORS WITH QUESTI0l1ABLE CERTIFICATIONS
' EVALUATE WORK PERFORMED BY THESE INSPECTORS TO ASSESS FOR [w % ;,ayet ['[j - ch "*I 'k SAFETY SIGNIFICANCE = t RECOMMEND IMPROVEMENTS FOR CERTIFICATION PROGRAM
=. / i QA/0C (NRC LETTER DATED 1/8/85) i l OVERALL APPROACH PROGP[AMMATICISSUES j IDENTIFIED HARDWARE ISSUES 1 l l l t .l
PROGR#f% TIC ISSES IIBITIFIED llARDWAE ISSES SYSTEfVPROCEDUE NRC/TRT/TUGC0 ISSE DID AFFECT IND [QUIKS FIX QC AC&PIATE E N0 YES NO ISSE DESIGN CONST. QA 7NITIAE-ET-Butt NCR GEERIC Splices 50,5I Locking Audits IfFLICATION Devices TBD 4
APPROACH WILL ENABLE - SRT/TUGC0 TO IDENTIFY SAFETY SIGNIFICANT DEFICIENCIES.
- l CAUSED BY EITHER PROGRAMATIC OR WORKMANSHIP WEAKNESSES, j
BOUND THOSE DEFICIENCIES AND IMPLEf1ENT EFFECTIVE CORRECTIVE ACTIONS.
PROGRAMMATIC ISSUES APPROACH ' REVIEW, SUMMARIZE AND ANALYZE HISTORICAL DATA ' DETERMINE IMPACT ON 11ARDWARE ' N0 HARDWARE IMPACT ' HARDWARE IMPACT ' DETERMINE AREAS WHERE ' RECLASSIFY AS A HARDWARE IMPROVEMENT CAN BE MADE ISSUE AND FOLLOW INVESTIGATIVE ' MAKE PROGRAM RECOMMENDATIONS LOGIC PLAN
0A/0C CONSTRUCTION RELATED ISSUES GENERAL APPROACH - IDENTIFIED ISSUES UNDERSTAND THE ISSUE AND IMPLICATIONS ON 0A/0C PROGRAM 9/18/84 LETTER 11/29/84 LETTER 1/08/85 LETTER GATHER ALL PERTINENT DATA ANALYZE DATA AND INSPECT HARDWARE IF REQUIRED B0UND AND QUANTIFY ISSUE DETERMINE WHEN AND HOW DISCREPANCY OCCURED AND ORGANIZATIONS INVOLVED EVALUATE FOR SAFETY SIGNIFICANCE DETERf11NE ROOT CAUSE AND GENERIC IMPLICATIONS i IDENTIFY NEW PROGRAMMATIC ISSUES THAT REQUIRE EVALUATION CATAGORIZE INITIAL QA/0C CONTROLS OK INITIAL QA/0C CONTROLS NOT OK
s. 4 0A/0C CONSTRUCTION RELATED ISSUES (IDENTIFIED ISSUES) i APPROACil - INITIAL QA/0C CONTROLS OK (DISTURBED SINCE INITIAL INSPECTION) i ' DEVELOP A DETAILED CORRECTIVE ACTION PLAN SPECIAL INSPECTIONS SPECIAL TESTS i DEVELOP PROCEDURAL CONTROLS RETRAINING i APPROACH - INITIAL QA/0C CONTROLS NOT OK I ADVANCE TO SAMPLE REINSPECTION OF llARDWARE i l i 5
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