ML20199G645

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Marked-up Ref to Qa/Qc Sser in Mechanical/Piping & Coating Draft Sser
ML20199G645
Person / Time
Site: Comanche Peak, 05000000
Issue date: 03/15/1985
From: Workinger T
NRC - COMANCHE PEAK PROJECT (TECHNICAL REVIEW TEAM)
To: Livermore H
NRC
Shared Package
ML20197J178 List: ... further results
References
FOIA-85-59 NUDOCS 8606250317
Download: ML20199G645 (5)


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Note to: Herbert Livermore  : h o- F l QA/QC Group Leader C' '

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T. R. Workinger, TRT '

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Subject:

Reference to QA/QC SSER in Mechanical / Piping and Coatings, draft SSERs I

i l The draft SSERs being prepared for Mechanical and Piping, and Coatings, were reviewed for cross references to the OA/nc SSE_R. The following cross

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references were identified, which do not appear to present any problems.

Mechanical and_ Piping Category No. 3, AW-32., 59 and 62 (pages 5 and 6)

With the imposition of DCA 13335 on May 18, 1982, specific limits were imposed on radial shrinkage of pipe girth welds. The gene rns of the TRT are being addressed by QA/QC Category 8, allegat n AQ-50.

Category No. 7, AW-4_8, (page 2)

-f i Since the [ fuel pool] liner weld inspection and welding has already been

. covered by mecnanical/P1 ping Lategory 4.5 and QA/QC Category _8, .it will not be discussed further here. " g 4 Category No. 47, AQW-7_f._,(page 3) v j For related information [ vendor welds of pipe whip restraints] see

QA/QC Category . o [g j Coatings q j Section 3. Summary of Evaluations (page M-12) 1 j However, based on TUEC's prior FSAR commitment to provide qualified j coatings inside Containment Buildings, coatings applied before issuance

]: of Appendix L of this supplement were required to .1 ave bei.n qualified.

TUEC's failure to fulfill that prior commitment indicates deficiencies in 6

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the coatings QA/0C program. These deficiencies, although not of safety significance in the coatings area, will be considered in the TRT's overall evaluation of the effectiveness of TUEC's quality assurance / quality control (QA/QC) program.

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L i MEMORANDUM FOR: V. Noonan, Director Comanche Peak Project -

FROM: H. H. Livermore '

[c , QA/QC Group Leader

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SUBJECT:

DESIGNATED QA/QC REVIEWERS 9

Your letter of March 15, 1985 requested designated QA/QC reviewers be assigned to each TRT group. In response, the following members of the QA/QC group are assigned:

Electrical - Tom Curry Piping / Mechanical - Rudy Bonnenburg

- Jim Malonson 4

Civil / Structural - Mark Eli Test Miscellaneous - Vern Watson
  • In addition, all QC qualification issues will be addressed by Mr. Vern Watson.

The assigned individuals will become familiar with the SSERs of each assigned TRT group as soon as possible. They will be responsible for the Quality Assurance aspects of all SSERs and future allegations addressed by each and every TRT group. The original TRT group reviewers, (Piping / Mechanical, Electrical, etc.) will remain responsible for follow-up plans and related ASLB proceedings. The designated QA/QC individuals will remain responsible

[f for all original QA/QC SSERs and related proccedings.

I request that the individual members of Piping / Mechanical, Electrical, Test,, Civil / Structural, Misc., and coatings groups extend aid in the form of a crash familiarity work session in order that the subject designees become familiar with the SSERs as soon as possible. I also request that the designees accompany the TRT group members to all work sessions, site interviews and inspections, and alleger interviews in order that they will be able to extract and address all quality assurance problems in a real-time frame.

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! In order to assure that the subject designees will be available (from a It contract standpoint) to carry out their functions, I contacted Mr. Chet Poslusny as directed. Since the designees are now assigned as members of the other TRT groups and thereby dependent on their continuing services, it is necessary that the Group Leaders include the designees in their contractural requirements at this time. I have taken the liberty to instruct Mr. Poslusny that the designees' services will be required through July ij 1985. This, of course, should be reassessed by the respective group leaders, l As you are aware, with the assignment of the designees to other TRT groups,

! the TRT QA/QC group no longer exists. Mr. C. Hale and I remain, but with *

! no clear cut lines of authority or responsibility once the QA/QC SSERs are j signed.

I expect you will advise us, with specificity, of our future function in the TRT.

LAsurt. G H. H. Livermore QA/QC Group Leader

, cc: D. Wessman A. Vietti J. Calvo R. Keinig C. McCracken C. Poslusny .

L. Shao R. Bangart (Region IV)

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. causes and appropriate corrective actions, o es is l

ud 4.1.3 Electrical Equipment Separation (See Attachment 2, E&I Categ Reinspect all panels at CPSES, in addition to those inithin the ma room for Units 1 and 2, that contain redundant safety-related cab ,

conduits or safety and nonsafety-related cables within conduits, l '

either correct each violation of the separatio where the minimum separation is not met.

Reinspect all panels at CPSES, in addition to those in,the t ma room identified in Table 1 of SSER for E&I Category 3, and either c d each violation of the separation criteria conce of the flexible conduit as a barrier.

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Correct two instances of violation of the separation criteria d inside panels CPI-EC-PRCB-09 and CPI-EC-PRCB-Submit the analysis that substantiates ithe a between independent conduits and cable trays. I adeouacy of the OC insoection orcaram as related to the

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/ deficiencies identified above to establish root causes \

corrective actions.

[ (. addressed under E&I Category.6, "E1.ectrical QC. Inspector Trai

' Qualifications," and QA/QC' Category 8, TAF8uilt."

4) 4.1.4 . Control Room Ceiling Fixture Supports (See Attachment 2. E Substantiate (1) the adequacy of the overall seismic support system installation for all the items located above th and (2) the adequacy of the seismic support system installation f nonsafety-related conduit in Seismic This action Category shall be integrated as Iappropriate areas" of the pl Seismic than the with othercontrol room.addressed under Civil / Structural Category 14, actions l Design of Control Room Ceiling Elements."

4.1.5 Electrical QC Inspector Training / Qualifications (See Atta

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E&I Category 6)~ '

Evaluate the testing program for QC electri .

i procedural requirements and test flexibility to assure that s

' proficiencyisachievedalndmaintained.

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control room panels which did not meet minimum separation requirements (AE-15). The TRT found no evidence that the lack of separation was justified by analysis. The TRT also concludes that in the absence of J

analysis to support the lack of minimum separation between separate flexible conduits inside the main control room panels, the existing design arrangement is in violation of regulatory requirements. Furthermore, the lack of separation in the installation of certain cables and flexible conduits is also inconsistent with TUEC's engineering drawings and docu-ments.(AQE-6). The Jack of analysis to substantiate the adequacy of separation in the above~casis iity be'an indication of weakness'in the l

1 lQA/QC program:concerni.ng ,bsign~ccitrol'. This ~ area is addressed in ,QA/QC -

1 Category 1.. " Design Process."*

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The TRT concludes that the unjustified installation of cables and flex- 1

ible conduits inside panels that do not meet minimum separation require-ments has potential generic implications. (AE-15)

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In regard to the criteria for 1-inch separation between rigid conduits and cable trays stated in G&H specification 2323-ES-100 (AQE-54 and AE-51),

the TRT concludes that the analyses performed by G&H to support acceptabil-

! ity of these criteria require NRC evaluation. The present FSAR contains no reference to this analysis. (AE-20)

' The TRT also concludes that the missir.g barrier in the auxiliary feedwater panel and the field wiring not being separated by the required 6 inches are two isolated instances of nonconformance and do not have generic implications.

g e TRT findi

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is r a dre 'ed c r ca and a rumentation Cat " Electrical Ins Training and Qualifi-tions." e addressed under .

.see GA/GC Ccdgsy kTmMy CAmiW. p

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l6. ~ ActionResuf@: TUEC shall accomplish the following actions prior to fuel , load:. g g (a) Reinspect all panels at Comanche Peak Steam Electric Station, in

  • j addition to those in the main control room for Units 1 and 2, that 4 contain (1) redundant safety-re?ated conduits, or (2) safety- and

) nonsafety-related conduits. TUEC shall either correct each violation of the separation criteria or demonstrate by analysis the accept-ability of the conduit as a barrier for each case where the minimum j separation is not unet. This analysis shall be accomplished in i accordance with the requirements specified in Section 5.6.2 of IEEE I Standard 384-1974. Furthermore, in the event that the acceptability 1 of the conduit as a barrier cannot be demonstrated, TUEC shall correct j the engineering drawings and related documents to indicate the revised 1

minimum separation of conduits inside the panel for each case.

I*TheTRTevaluationofQA/QCallegationsisinprogressandwillbepublished I in a subsequent supplement to this SSER.

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1. Allegation Category: Electrical and Instrumentation 7, Electrical Cable Installation i 2.

Allegation Number: AE-19, AE-28, AE-30, AE-50, Parts of AQE-5 and AE-29 l and Special Review Team SRT-10 l

3. Characterization: It is alleged that:

[CabW trays were everloade'd r (AE-19)._ .

  • t ples were not " trained" in a workmanlike manner in the cable spread-

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  • ring room and in junction boxes 1058 and 1059 (AE-28).

jHigher siderails were added to cable' trays' due to tray overfill con-l * (itions(PartofAE-29). ~"

Cable de.ssity/ compaction problems may exist due to tray overfill

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  • conditions (AE-30).

i Cables were spliced in cable trays in the cable spreading room in

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  • violation of regulatory requirements (AE-50).

! A nonconformance report pertaining to trash in cable trays, damaged cable, and improperly trained cable was improperly closed (Part of t

AQE-5).

!g The JSpecial' Review Team' Report ~on July 13?1984, identified the issue of l

( byerloaded cable trays"due to 'the installation of[thermolag", material (SRT-10).

4.

Assessment of Safety Stanificance: The implied safety significance of these allegations is that japroperly trained cables, improper cable splices l

huestioin.knd overloaded cable trays could place the p ~uality of the inst t.

cable ices in Racewa s. All tion AE-50 involve P.eview eam ewed NRC Region IV (RIV) s, nspection report 83-03 (November 8,1982) and found that the RIV investigation of the two cables specifically identified by the alleger

, adequately addressed this allegation. The RIV investigation determined 7

t that one cable no longer performs a safety-related function, and the at l cable had become a " spare" and was removed from the raceway. The TRT l

g determined that similar-appearing items in the same area were not splices -

i but were,. in fact, acceptable methods of repairing minor cable jacket I damage. The TRT concurs with the RIV determination but notes that ra regulatory requirements discourage the use of splices in raceways, as i

stated in position 9 o la Guide (RG) 1 ical I I i .of Electric Systems." '

, the his , area, The TRT examined the cable spreading room, identified two cables installed e

in raceway, which to the untrained eye could appear to have been spliced, yd s and inspected them in their as-installed condition. The TRT al:o reviewed l  ;

the applicable installation / inspection records. This inspection and g he TRT evaluation of QA/QC allegations is in progress and will be published l n a subsequent supplement to this SSER.

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The TRT found that the $ se terminations ~ hin the 11 'ti terminat on I h s. occurred as a fesult of an L

Jnvolving the Thomas and Betts RP-12 crimp-type insulated connectors.

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Ipumentjhange notice -(DCN) was issued 3 hanging the engirieering instruc[

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i SionJs~ed by craft personne1 (EE-8) to improve installation of lighting ~

j terminations; thereafter the' number of deficiency reports in lighting or i

The TRT found that the revisicos to procedure QI-QP-11.3-40 regarding emergency lighting inspections were justified to eliminate unnecessary inspection requirements.

Other Electrical Procedures (AQE-32, AQE-44 and Parts of AE-18 and AE-20).

Af ter a review of procedure QI-QP-11.14-12, " Reverification of Seismic i

' Electrical Equipment Mounting Details," the TRT could find no requirements in Revision 0 through 4 that established a fixed frequency for reverifica-tion of inspections concerning bolt tightening of seismic electrical equipment mountings. However, the procedure provided for reverification of inspections on a " case-by-case" basis (AQE-32).

The TRT also reviewed the following in process inspection procedures with respect to electrical equipment separation and the use of butt splices in panels (parts of AE-20 and AE-18):

(a) Procedure QI-QP-11.3-29, " Electrical Separation," (b) Procedure QI-QP-11.3-29.1, " Verify Electrical Separation," (c) Procedure QI-QP-11.3-28, " Class 1E Cable Terminations."

The TRT determined that in process inspection procedures QI-QP-11.3-29 and QI-QP-11.3-29.1, and post-construction procedure QI-QP-11.3-40, were used to identify deficiencies in the Fuel Handling Building and that these procedures allow the "use-as-is" disposition of nonconformance reports (NCRs). The subject of "use-as-is" disposition of NCRs (AQE-44) is dis-cussed in Electrical and Instrumentation Category 5, " Electrical Noncon-formance Report (NCR) Activities."

The separation of electrical equipment and installation of terminations in accordance with procedures, drawings, and specifications are discussed in Electrical and Instrumentation Category 1, " Electrical Cable Termina-tions," for part of AE-18 and Electrical and Instrumentation Category .

" Electrical Equipment Separation," for part of AE-20.

In a TRT review of otner electrical procedures, the TRT found no omissions in requirements for inspection of electrical equipment.

5. Conclusions and Staff Positions: Based on its review of procedures for in process inspections, por -construction, and turnover inspections, the l JRT. conc 1,udes that j [dures. [However, e,q_no

.. uipment.signi . cant concerns installation problemsexist with . electrical as related to non- proce- ~ '

gonformance with~_ procedures are being, addressed in the. hardware-related EAI . categories. The TRT, therefore, concludes that these electrical procedure related allegations could not be substantiated.

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PAGE 1 0F T

                                                                                                                     /

C (g

        ,f'     INCOMING        OUTGOING   X    TIME                 P.M.         DATE File No.4.12                -

j- - - * "

Title:

Not Requested -

            )

4.G 3 ,m q~ w w m n Tel. (301) 443-7660 , I

Title:

I6 Other Parties Involved: NONE t REF. TOPICS ITEM This call was made to confinn information obtained from a previous call n.ade to Mr. Eli on April 2,1985 (record attached) and to make sure that Mr. Eli reali:ec that I was a member of the Comanche Peak Response Team (CPRT). The information I wanted confinned was:

1. The TRT did not develop a unique set of inspection checklists and instructions and accept / reject. criteria forhtheir use during the TRT Comanche Peak Review referred to in the NRC letter of Jan. 8,1985.

d 1 2. The TRT does not have a list by support number of the supports inspected as listed in Table 3, page 16 of the NRC letter of Jan. 8,1985. The answer to Item 1 above was that the TRT used the CPSES procedures for in- } spection attributes and any documents and codes that the procedures referred j to. He indicated that any dccuments that the TRT did generate for their use could not be released to us. (CPRT per H. Livermore; NRC) The answer to Item 2 is that the TRT does not have a list of the subject pipe q g support numbers. f q~Y. ) rem.L Roger H. Brown ffman D. Alexander I T \b ' '

                                                                                                                               }

J. Christensen B. Singh I J. Hansel l j , I ) s .

                                                                                                     ~~

_ __~;

              ",                                --RE MRD OF TELEPHONE CONVERSATIO!i 0F 2
                                                    )

PAGE 1

  .                                                                                     )

X TIME 2:30 A.M. DATE. April 2,1985

       */           INCOMING         OUTGOING                             P . M .X Person called: Mark Eli

Title:

Not Reouired I 7660 BR3

                 ' Representing: Nuclear Regulartory Commission                            Tel . ( 301)443-460 Person Calling: Roger H. Brown

Title:

Issue Coordinator Representing: Evaluation Research Corporation (ERC) fTel. (817) 897-4881

            -     Other Parties Involved: B.P. Singh-ERC i

TOPICS REF. l-ITEM l1 Mr. Eli was informed that the purpose of the call was to obtain the following information. He was also informed that the cali was made at the suggestion of Mr. Herb Livermore of the NRC. A) Mark No's of 16 remaining pipe supports (from group of 42) not listed in NRC letter of Jan. 8,1985. (NOTE: only 26 of 42 supports were identified in letter in Table No.1.)

                           ' B) Mark No's of additional 92 supports identified in NRC letter of Jan. 8,1985 in Table No. 3.

C) Check lists and instructions used by the TRT in their review of pipe supports as delineated in the Jan. 8, 1985 NRC letter. D) Listing of attributes and acceptance criteria used by the TRT in the Item c above inspections. 2 In addtion, Mr. Eli was asked if he could identify the 200 fuel pool travelers mentioned on page 3 of the Jan. 8,1985 NRC letter. A) Mr. Eli supplied the Mark No's of the 16 pipe supports mentioned in Item la which are as follows:

1) RC-1-901-700-C82R
2) RC-1-901-703-C82R
3) H-CH-1-SB-008-022-3
4) CC-X-039-008-F43R
5) CC-X-039-009-F43R
6) RH-1-020-003-S22K
7) DD-1-012-026-Y33R
8) RH-1-006-006-C42R
9) CT-1-006-003-S22K
10) CT-1-013-004-S325
11) CT-1-013-011-522R
12) CT-1-013-013-532K
13) RC-1-035-700-C41R
14) AF-1-059-003-533R
15) AF-1-035-029-S33A
16) AF-1-001-701-533R B) Mr. Eli indicated that the TRT did not record the Mark numbers of the supports identified in Table 3 of the NRC -letter of Jan. 8,1983. (See Item 1B above)

He pointed out that these supports (which were confined to only one room) were looked at for certain types of deficiencies only. C) Mr. Eli indicated that during the TRT inspect 1on the team used the CPSES procedures for inspection attributes and any other documents or codes that the procedures refered to. He indicated that the TRT did generate some inhouse documents instructions, procedures, etc.) for their use but these documents were no't for publication to TUGCO.

                     .           5 EEC"7 0F TELEPH0f;E CO:;';EF.5 TION t

32 2 0F 2

                         ,                                              (CONT'D)
                             ,. m TOPICS
                 '$                REF.

i ITEM D) Mr. Eli indicated that he did not have any information pertaining to the 200 fuel pool travelers and we would have to contact a Mr. Tom Curry (NRC) who would not be available for two weeks. Mr. Curry can be reached through Mr. Herb Livermore of the NRC. I " f t 04f;, , .. M Roger H. Brown s' cc: M. Eli V. Hoffman i D.J. Alexander i J. Christensen  ! B.P. Singh j J. Hansel j l i 1 4 d T l k e L k 8

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