ML20137G805

Forwards DF Landers to V Noonan & Trip Rept 2192 of 851211-12 Site Visit Re Walkdown Audit of Cable Trays

ML20137G805
Person / Time
Site:	Comanche Peak
Issue date:	12/19/1985
From:	Lipinski R NRC - COMANCHE PEAK PROJECT (TECHNICAL REVIEW TEAM)
To:	Vietticook A NRC - COMANCHE PEAK PROJECT (TECHNICAL REVIEW TEAM)
Shared Package
ML20137G766	List: ML20137G760 ML20137G805
References
NUDOCS 8601210218
Download: ML20137G805 (7)

Text

--

c, # "" %,g UNITED STATES ye

--+ t NUCLEAR REGULATORY COMMISSION j

,j WASHINGTON, D.C. 20555

\\,.....,o December 19, 1985 MEMORANDUM FOR: Annette Vietti-Cook, Project Manager Comanche Peak Project FROM:

R. E. Lipinski, Comanche Peak Project TRT

SUBJECT:

TRIP REPORT ON DECEMBER 5,1985 AND WALKDOWN AUDIT OF UNIT 2 CABLE TRAY HANGERS DURING DECEMBER 11-12, 1985

REFERENCE:

1) Letter from Donald F. Landers to V. Noonan dated December 12, 1985

2) Trip Report 2192, Teledyne Engineering Services The referenced documents are forwarded for your files in accordance with your request.

.i.

R. E. Lipi ki Comanche Peak Project TRT cc: w/ encl.

L. Shao D. Jeng TRT files 8601210218 851227 PDR ADOCK 05000445 A

PDR

"#eTELEDYNE ENGINEERING SERVICES TRIP REPORT 2192 VIST TO COMMANCHE PEAK STEAM ELECTRIC STATION DECEMBER 11 - 12, 1985 The purpose of this trip was to audit the walkdown of the unit 2 cable trays which is being performed by TUCG0. A kic(4ff meeting was held with TUCG0 on December 11. Those in attendance are shown in attachment 1. TUCG0 distributed their current procedures which apply to the unit 2 walkdowns. They briefly explained the process for unit 2 and the differences between unit 1 and unit 2. A flow chart for unit 2 is shown in attachment 2. The major difference is that in unit 1 the QC inspector and the engineer perform 1 walkdown together but in unit 2 there is two seperate walkdowns done. One by the engineer before design verification and one by the QC inspetor after design verification. Twenty one supports were chosen for the walkdown.

The following is a list of the supports walked down:

Reactor Building Safegards Building CTH-2-11929 CTH-2-10264 CTH-2-11516 CTH-2-10420 CTH-2-10059 CTH-2-11068 CTH-2-11592 CTH 7137 CTH 9774 CTH-2-11391 CTH-2-10119 CTH-2-10101 Diesel Generator Building CTH-2-11529 CTH 9850 CTH-2-11570 CTH 9866 CTH 9977 CTH 9825 CTH 9901 CTH 9926 CTH 9947 We split into three teams nf two each with a level III inspector and a craft person supplied by TUCGO. The teams were:

Team # 1 Team # 2 Team # 3 Eric Salla R. Lipinski Vic Ferrarini Terry Langowskt Jim Dale Chuck Richards Jimmie Duncan William Kattness Denis Mercier (Level III)

A copy of.the as-built drawing and procedure was used for the walkdown. Each support was walked down by one of the teams using tolerances given in the TUCG0 procedures. Each t,ime a discrepancy was found the level III inspector would confirm the discrepancy.

'R TF1pnYNE ENGINEERING SERVICES The following is a list of the supports walked down and the problems encountered:

Reactor Building 1.

CTH-2-Il929:

No Comnents.

2.

CTH-2-11516:

No Comnents.

3.

CTH-2-10059:

No comments.

4.

CTH-2-Il592:

No Comnents.

5.

CTH 9774:

(a) Missing location of plate on cnannel in elev. B-B.

(b) Hissing location of tray clamp plate on channel.

6.

CTH-2-10119:

(a) Gage on bolt #1 measures 1-3/16",

given 1", tolerance 1/8".

7.

CTH-2-10101:

No Comments.

8.

CTH-2-Il529:

No Comments.

9.

CTH-2-Il570:

(a) 1/16" gap between vertical supporting angle and concreto over approx. 25 length of tne angle.

(b) Elevation of tne tray supporting channel l'-6" off. Measured 848'-1/2" vs 846'-6" on tne drawing.

(c) Hilti bolt projection marked on drawing 2-3/4" vs 2-1/4" measured.

Safegards Building 10.

CTH-2-10264:

(a) Plate of CTH-2-10263 misplaced by 1-3/4" (neighboring support ). This results in 3-1/4" off the location shown on the dw). (See soct. B-B)

11. CTH-2-10420:

(al Location of plate belnw the CTH support of f by 1-3/8" (measures 5-3/4" vs 4-3/8" on the dwg)

12. CTH-2-110ba:

No Comments.

13. CTH 7137:

(a) Neighboring CTH mislabled. Heat no.

(28879b) listed instead of CTH no.

(27136).

14 CTH-2-Il391:

No Comments.

'# P T F1 m Y N E ENGINEERING SERVICES Diesal Generator Building 15.

CTH 9850:

(a) Drawing "U" dim for bolt location from hot of clamp to Dolt centerline. Draw shows 1-5/16", actual 1-7/H",

tolerance 1/2".

16.

CTH 9866:

No Comments.

17.

CTH 9977:

No Comnents.

18.

CTH 9825:

(a) Drawing shows span dim to support 9822 3'-0". Actual dim is 5'-5".

19.

CTH 9901:

No Comnents.

20.

CTH 4926:

No Comments.

21.

CTH 9947:

No Comments.

On Thursday December 12 an exit meeting was held in which the findings wore presente<1. The people present are snown in attacnment 3.

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Eric A Solla cc TRIP REPORT FILE

.l AF DFL RDC WJC

'eTF1 ETVNE ENGINEERING SERVICES

. Kickoff Meeting December 11, 1985 Name Organization Terry Langowski NRC/TRT Eric Solla NRC/TES Jim Dale NRC/RN Romuald E. Lipinski NRC/TRT Charlie M. Trammell NRC David Jeng NRC Tom Westerman NRC/RIV Terry G Tyler.

TUCG0/CPRT W. G. Counsil TUCG0 J. F. Streeter TUCG0 H. A. Harrison TUCG0

0. B. Jones TUCG0 J. T. Merritt TUCG0 C. R. Hooton TUCG0 C. D. Richards NRC/TRT Curtis H. Biggs

,TUCG0 Jimmie Duncan TUCG0 William A Kattness TUCG0 Denis Mercier TUCG0 J. D. Hicks TUCG0 P. E. Halstead TUCG0 V. P. Ferrarini NRC/TRT e

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TEXAS UTILITIES GENERATING CO.

COMANCHE PEAK STEAM ELECTRIC STATION UNIT #2 CABW TRA Y J/ ANGER FRC4EAm N.'

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'A'TF1 CTT/NE ENGINEERING SERVICES Exit Meeting December 12, 1985 Name Organization Terry Langowski NRC/TRT Eric Solla NRC/TES Jim Dale NRC/RN Romuald E. Lipinski NRC/TRT Charlie M. Trammell NRC David Jeng NRC Tom Westerman NRC/RIV W. G. Counsil TUCG0 J. F. Streeter TUCG0 H. A. Harrison TUCG0

0. B. Jones TUCG0 J. T. Merritt TUCG0 C. R. Hooton TUCG0 C. D. Richards NRC/TRT Curtis H. Biggs TUCG0 Jimmie Duncan TUCG0 William A Kattness TUCG0 J. D. Hicks TUCG0 P.-E. Halstead TUCG0 V. P. Ferrarini NRC/TRT R. E. Camp TUCG0/IMPELL Edgar J. Hee RLCA/TUCG0 L. M. Popplewell TUCG0 t

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EA8 PTELEDYNE ENGINEERING SERVICES 130 SECO' D AvtWE W ALTH AM M A$$ 4.CM J$f T'5 C226S f617 893 3350 To a i71C,324 7508 December 12, 1985 6410-26 Mr. Vince Noonan, Project Director Comanche Peak Project U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Mail Stop P-234 Washington, D. C.

20555

Dear Mr. Noonan:

Attached please find our preliminary Trip Report for our visit to Comanche Peak Steam Electric Station to discuss the results of the NRC audit walkdown on the Unit 1 Cable Tray Supports.

If you have any questions please do not hesitate to contact me.

Very truly yours, TELEDYNE ENGINEERING SERVICES A

5 Donald F. Landers Executive Vice President DFL/lh Attachment (Trip Report No. 2188) cc:

L. Shao (USNRC)

C. Tramell (USNRC)

C. Poslusny (USRNC)

D. Jeng (USNRC) 6410 File (TES) n 7

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" M LEDYNE ENGINEERING SERVCES TRIP REPORT NO. 2188 VIST TO COMANCHE PEAK STEAM ELECTRIC STATION DECEMBER 5, 1985 On Thursday December 5,1985 a meeting was held with TUCG0 to discuss the results of the NRC audit walkdown on the unit I cable tray supports. A list of those in attendance is shown in attachment 1. TUCG0 has stopped the walkdowns and is currently revising the walkdown procedures. The causes of the NRC findings are being investigated and appropriate corrective action will be taken. Previously the walkdown teams consisted of a OC inspector and an engineer. The QC inspector and the engineer will now be split up into two walkdown teams.

TERA was asked if their review included looking at the walkdowns. They responded that they were reviewing the procedures but that implementation was not part of the current scope. They are considering, as a result of these findings, to include the 1mplimentation in their scope.

As a result of the NRC findings TUCG0 has sent level Ill inspectors out to walkdown the supports in which we had findings.

The following is a list of TUCG0 responses to the findings found during the NRC audit November 18 - 22, 1985.

1.

CTH-1-5817:

(a) Bottom two teirs are 1 member size smaller than what is shown on the drawing.

(b) Tray 1 is a 4" x 24" not a 4" x 12" as shown on the drawing.

(c) Tray 2 is a 4" x 24" not IA as shown on the drawing.

(d) Bolts G1 & G2 are given as type " BEVEL".

Actual type is A307 & A449.

(e) Conduit #11 span is too short.

TUCG0 Response:

(a) By measuring the webs the members were found to be the correct size. The differance in the flange widths is due to the mill tolerances on the steel. This item needs further investigation.

(b) Agree with finding.

(c) Accessability is defined as accesable at the tray. Since the tray was wrapped in a thermal blanket at the support it was marked IA.

The thermal blanket ended just after the support at which point the tray size could be measured but since this would involve the use of engineering judgement, which is not allowed in the procedure, the tray size is marked IA.

(d) Agree with finding.

(e) Agree with finding.

"RTFI FrT(NE

- ENGINEERING SERVIOES 2.

CTH-1-5787:

(a) Angle under tray was given as 3-1/2" x 2-1/2" x 5/16 with the 2-1/2" marked IA. Angle is actually 3-1/2" x 5" x 7/16".

(b) Weld of angle to baseplate marked IA but only weld on leg under tray was inaccesable the other leg was accesable.

TUCG0 Response:

(a) Agree with finding.

(b) Agree with finding.

3.

CTH-1-239:

(a) Span lengths incorrect. 4" dimension is 12" & 4'-0" dimension is 4'-10".

(b) Bolt G dimensions given as 2-13/16" &

2-5/8" but actually measure as 2-1/2 & 2-3/4.

TUCG0 Response:

(a) Agree with finding.

(b) Agree with finding.

4.

CTH-1-42:

(a) Bolt #1 G dim given as 2-1/8", actual dimension is 3-1/8".

(b) Welds A4 & 8 are written up as U.S.

measuring 3/16". Actual measurement is 1/4" which is what was called for.

(c) Tray clamps 3 & 4 narked IA but have beveld washers on them.

TUCG0 Response:

(a) Agree with finding.

(b) Agree with finding.

(c) According to the procedure the clamp and bolt are to be treated as a unit and since the clamp was inaccessable the bolts and washers were also marked IA.

5.

CTH-1-12075: (a) Tray clamp is shown as Type B,1/2" plate welded to channel. Actual tray clamp is Type C, botled to channel.

(b) Weld symbol of channel to angle is reversed.

TUCG0 Response:

(a) Agree with finding.

(b) Agree with finding.

6.

CTH-1-5942:

(a) Weld #1 arrow side is given as 5/16" but measures 1/4".

(b) Channel C4x5.4 is actually a C4x7.25.

(c) 7-5/8" dimension to edge of column is actually 8-5/8".

TUCG0 Response:

(a) Agree with finding.

(b) Agree with finding.

(c) Agree with finding.

'RTA mVNE

~

. ENGINEERING SERVIOES i

7.

CTH 636:

(a) Weld #1 measures 1/4" both sides.

Drawing shows 1/4" NS and 3/16" FS.

TUCG0 Response:

(a) TUCG0 inspectors found weld to be undersized for 27% of its length which is greater than 25% therefore the weld is unsat as shown in the walkdown.

8.

CTH 607:

(a) Support is marked inaccesable but base plate are accesable for dimensioning.

TUCG0 Response:

(a) TUCG0 did not know about this item.

9.

CTH-1-1853:

(a) Weld sizes for top of angle brace are given backwards.

(b) Gap under Richmond Insert is greater than 1/16" TUCG0 Response:

(a) Agree with finding.

(b) Copy of inspection report that was used for the walkdown was not the latest inspection report.

The latest inspection report contains the gap discrepancy.

10. CTH-1-1716:

(a) Bolt #2 has 2-3/4" projection given.

Actual projection 2-3/8".

TUCG0 Response:

(a) Agree with finding. Problems with bolt projections are due to techniques used to measure the projections. Since the procedure does not define the method to be used many different methods may have been used. The next revision to the walkdown procedure will clearly outline the method of measuring the bolt projection.

11. CTH-1-1845:

(a) Bolt Projections 3-3/4" & 3-3/8" given.

Actual projections are 3" 8 2-3/4".

(b) Tray clamp G1 contains no bolt and washer as called out in table. G1 is a Type B (welded) clamp.

(c) Tray clamp G2 contains a bevel and flat washer. Table shows only bevel washer.

(d) Angle at wall rotated 90 deg.

(e) Dimension against wall between attachments is wrong.

(f) Dimension of W.P. in det A is wrong.

(g) Weld size in Det B is given as 1/2".

Actual weld size is 3/16".

'WTA ctWNE

~

- ENGINEERING SERVICES TUCG0 Response:

(a) Agree with finding.

(b) Agree with finding.

(c) Agree with finding.

(d) Agree with finding.

(e) Agree with finding.

(f) Agree with finding.

(g) Agree with finding, but measure 1/4".

12. CTH-1-5517:

(a) Weld #1 arrowside udersized 5/16" - 1/4".

(b) Tray size marked IA due to thermal blanket.

Just down from support tray was accesable. Tray measures U " x 4".

(c) Weld #5 & 6 Q.C. marked unsat for undersized were found to be OK.

(d) The end prep on a bevel weld was found to be undersized.

(e) Plate size on clamp given as 1/2" x 3-3/4" x 6" measures 1/2" x 4-1/4" x 6".

TUCG0 Response:

(a) Agree with finding.

(b) See response 1 (c).

(c) Agree with finding.

(d) This attribute was not being checked for at this support.

(e) Agree with finding. The measurement tolerances included in the walkdown procedure did not apply to redlined dimensions but in the next revision they will apply. The discrepancy on the plate tolerance is within these tolerances.

13. CTH 1.-5488:

(a) Dimension from B.0.C. to top of vertical channel. Dwg called for 2'-6" (max) dimension was deleted.

(b) Weld #1 far side undersized. 5/16" called out 0.C. called unsat to 1/4", actually measured 3/16".

TUCG0 Response:

(a) Deleted dimension was added on a different section which was unclear due to copying.

(b) Agree with finding.

14. CTH-1-7047:

(a) Bolt projections found to be different.

Walkdown NRC Bolt #1 2-1/2" 2-1/4" Solt #2 1-7/8" 1-5/8" Bolt #3 2-11/16" 2-1/2" TUCG0 Response:

(a) Disagree with finding. See response to item 10 (a).

"eTAPTWNE s ENGINEERING SERVIOES

15. CTH-1-1963:

(a) 5'-1" dimension measures 4'-10".

(b) Weld #2 weld length called out as 3/4".

Actual weld lengths are 3-1/4".

(c) Plate size 6-3/4"1g measures 6-1/2".

TUCG0 Response:

(a) Agree with finding.

[b) This problem is due sto unclear copies.

Ori'g'ina,l has 3-1/4" for weld length.

(c) This plate is skeyep and tough to get an accurate measurement on. However the discrepancy will be within the tolerance of the procedure.

16. CTH-1-5538:

(a) Bevel en penetration weld found to be incorrect.

TUCG0 Response:

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(a) Agree with finding.

17. CTH-1-4738:

(a) Weld #1 is udersizpd.

TUCG0 Response:

(a) TUGC0 inspectors disagree however said part of weld was inaccesable. The discrepancy in weld size was found in the area they said was inaccesable.

This item needs further, investigation.

18. CTH-1-6631:

(a) Weld undercut.

(b) Std. hex nuts found in lieu of heavy hex nuts.

s TUCG0 Response:

(a) This tttribute. was not looked at for this support.

(b) This attribute was not checked. Since this is a bearing connection the size of the nut has no f

effect on the strength of the; connection.

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19)'CTH-1-5976:

(a) 3" dimension from back of channel to edge of plate was ceasured at 3-1/4" i

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(b')' Projection of bolt #1 given as 3-1/2" was measured as 3".

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TUCG0 Response:

(a) Agree with finding.

s (b) See response 10 (a).

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'RTRCTVNE

- ENGINEERING SERVIOES In the afternoon a meeting was held with Region I to find out what procedures they used for there walkdown. Region I used the VWAC procedure for performing the walkdown on September 9 -

10, 1985. Region IV performed there walkdown as per TUCG0 procedures that were used by TUCG0 for there walkdowns.

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Eric A Solla EAS Enclosures cc: DFL JAF WJC TRIP REPORT FILE i

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ENGINEERING SERVICES

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Cable Tray Meeting 12/5/85 hiame Organization Terry Langowski NRC/TRT Bob Philleo TRT Tom Brandt TUGC0 QA Philip Halstead TUGC0 QA J. S. Marshall TUGC0 LIC R. E. Camp IMPELL - PROJ MGR Victor Ferrarini NRC/TRT-Jim Date NRC/RIV DavidC.9eng NRC/TRT 3

Howard A. Levin CPRT/RTL Larry Shoa NRC inomas F. Westerman NRC/RIV Eric Solla NRC/TES C. R. Hooton TUCG0 R. M. Kissinger TUCG0 W. F. Rockwell EBASCO Ronald A. Muldoon EBASCO John Vorderbeneggem IMPELL H. A. Harrison "

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TE DE ENGINEERING SERVCES DRAFT TRIP REPORT NO. 2187a VISIT OF ROBERT D. H00KWAY AND R0GER W. STUART TO COMANCHE PEAK SITE NOVEMBER 20-22, 1985 Attendees:

R. Hookway (TES)

R. Stuart (TES)

D. Terao (NRC)

Purpose 1.

Audit the SWEC CPPP-8 walkdown effort.

2.

Meet with John Finneran to discuss the "oenetration schedule".

3.

Continue to investigate the ERC QA/QC samples related to piping an/ pipe supports.

(Ref. November 13,14 Trip Report) 1.

SWEC CPPP-8 Walkdown This audit will consist of a number of sub tasks as follows:

1.

Accompany SWEC walkdown teams during their actual problem walk-downs.

2.

TES/NRC independent walkdown of two problems in the sample.

3.

Review and evaluate all data packages.

4.

Review and evaluate SWEC final report on this walkdown.

Accompany SWEC Walkdown Teams We joined the SWEC walkdown teams to witness their efforts on the AF-system (Stress Problem 0108).

The SWEC teams consisted of one pipe stress analyst and one pipe support designer.

The team members that we talked to all appeared sufficiently competent to fulfill the purpose of the CPPP-8 walkdown.

During the walkdown they were alert to all the attributes of interest with respect to piping and pipe supports evaluation for Comanche Peak.

One of the teams found the famous "E-system clamp design" on the feedwater line near the steam generator. His sketch is Attachment I.

SPTF1 prWNE ENGINEERING SERVCES Trip Report No. 2187a (continued)

TES/NRC Independent Walkdowns We walked down portions of two systems in addition to looking at the SWEC concern on the Roto Hammer remote valve operators.

These walkdowns confirmed the accuracy and completeness of the SWEC efforts.

Review and Evaluate All Data Packages The completed data packages (about 50%) were reviewed by TES/NRC.

The remainder will be reviewed at a subsequent audit at SWEC.

In the evaluation, we hope to reach a conclusion regarding the need for further walkdowns.

Review and Evaluate Final Report An audit will be held in the SWEC New York office on December 6 to discuss the status of their effort.

At that time, the status of their -8 report will be discussed in addition to any questions we have on the subject. When the final report is available, we will review it in detail.

Preliminary Thoughts on CPPP-8 o

The penetration question came up a lot.

This will be followed up in detail with J. Finneran (see subsequent discussion herein),

o

" Moment Restraints" were found to be not clearly defined on the stress iso.

Something should be added to the SWEC procedures to avoid confusion.

II. Penetration Schedule Meeting (11/22/85, 7:30 A.M.)

John Finneran presented an overview of the procedure which describes the penetration info available.

All the required penetration info is apparently available.

It is just matter of knowing how to retrieve it.

The analyst must be aware that the info is available because it is not referenced on the stress iso.

In gen-eral, there are two types of penetration sealant used (hard and soft).

The hard is used in all cases for radiation isolation unless the pipe must be free to move.

In that case, an annular space will be left around the pipe and the annular space will be filled with a gel.

In addition, a rubber boot will be installed.

For most other protection, (i.e.,

fire, F,

pressure, P), a soft sealant will be used.

(Note:

the above is a simplified explanation).

SPTA prf(NE ENGINEERING SERVICES Trip Report No. 2187a (continued)

In the case of Unit I, all the sealant is installed, so it is up to the analyst to retrieve the required info for all penetrations on his prob-l em. This will be looked at during our audit of the analyses.

III. ERC Samples The large bore pipe support rigid and the non rigid and part of the small bore pipe support populations were looked at.

The info gathered is in Attachment II.

This info and a summary are included. Completion of the data and complete evaluation will be later when all of the data is evaluated.

With this i n fo, we hope to answer the question of homogeneity (at least for the piping and pipe supports samples) and also determine whether these sample populations are adequate.

That is, should additional popula-tions be defined (e.g., valves, etc.).

IV. Exit Interview Exit Meeting 11/22/85

Purpose:

Two Topics 1 CPPP-8 2 ERC continuing effort CPPP-8 o personnel qualified o noted generic concerns e.g., paddle washer / spaces lug load ERC*

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o Penetration schedule o Potential concern -(ERC walkdown did not address penetrations) o NCRs procedure problems - we will review them (new revs coming, etc.)

L Robert D. Hookway (

RDH:sig Attachments

Y YA C.///ff & Y $

J.O.No. 15454 Page of COMANC'#E PEAK UNIT 1 LARGE BORE PIPING WALKDOWN DETAIL SHEET Stress Problem No.

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'RTF1 prf(NE ENGINEERING SERVICES s DRAFT TRIP REPORT NO. 2190a NRC/TES AUDIT REPORT STONE & WEBSTER NEW YORK 0FFICE DECEMBER;6, 1985 Attendees: See Attachment II Agenda: See Attachment I Item I - CPPP-8 Walkdown Portions of the CPPP-8 walkdown had been witnessed by the NRC and TES (see Trip Report dated 11/20-11/22/85). In addition, approx-imately 50% of the data from the walkdown had been given to TES. This data was compiled by TES and a number of comments and ques-tions regarding it were discussed as follows. SWEC presented an overview of the CPPP-8 procedure using the outline included as Attachment III. They indicated that there are approximately 355 problems total and they sampled 70. Fifty problems were selected randomly and the remaining 20 problems are those which will be evaluated for fluid transients. They stressed that the walkdown teams did not have all the documents which are now available. These documents may have precluded some of the observations. They indicated that they are now in the process of reviewing the packages to isolate the observations which are of concern from those which have al ready been identified and/or are covered by CPPP-7. The categories into which the observations are being classified are shown on Attachment III, Page 2. The final report for this walkdown by SWEC will be completed in February 1986. The con-cerns which are identified as a result of this CPPP-8 walkdown will be subject to a " validity check" - i.e., a field walkdown for confirmation. Some of the issues of concern at this point included: o Gaps - Gaps continue to be a point of concern and will be addressed in the Validity Check. o Decoupling - The concern was raised where decoupling is used regarding the effect of a large pipe on a small pipe (especially a small pipe with a valve close by). SWEC agreed that this should be looked at carefully.

'eTF1 m(NE ENGINEERING SERVICES Trip Report No. 2190a (continued) o The stress problem boundaries that SWEC is presently using are those defined by G&H. All stress problem boundaries will be reviewed by SWEC. o Since the -8 population did not include small bore piping, the question of small bore as-built verification was discussed. The plan is as follows: 1. The CPPv-5 walkdown already performed includes only large bore piping, but the results apply to the small bore high energy piping as well as the Class 2 and 3 large bore piping. The SWEC justification for this is that the original TUGC0 79-14 walkdown included all large bore piping and the small bore high energy piping. 2. A sample of Class 2 and 3 low energy piping will be developed and an equivalent -5 walkdown will be per-formed. (This is as recommended by SWEC after the original -5 walkdown). This walkdown will be performed in mid-January 1986. Note: TES recommended that when the small bore -5 walkdown is performed, SWEC should consider adding some other attri-butes that might be more applicable to small bore (espec-ially gaps). SWEC will consider the recommendation. 3. An equivalent -8 small bore walkdown will not be per-formed. A number of concerns still exist regarding the small bore walk-down. a. Since the -8 walkdown population did not include small bore piping, why won't there be an equivalent -8 small bore walkdown? b. Why did the -5 walkdown populations include small bore high energy piping? If it included the small bore high energy piping, it would be easier to nderstand the extrapolation of applicability described above (item 1).

7 'RTm prVNE ENGINEERING SERVICES Trip Report No. 2190a (continued) TES presented their summary of the observations they compiled from the data which they had reviewed. These were only briefly discussed since SWEC was still in the compilation stage. It was confirrred that a number of items were insignificant or already covered by procedure CPPP-7. It was also confirmed that a final " stress reconciliation walkdown" will be performed which will resolve a number of concerns. Note: At the next audit, we should add an agenda item to discuss the " stress reconciliation walkdown" and any procedures that will be used. Item II - Small Bore Piping Status Update The small bore SWEC scope includes: a. all Class 1 small bore supports b. all Class 2 and 3 small bore pipe supports that are attached to large bore stress problems c. an engineered sample for the remainder of all small bore piping and supports Note: a and b will be 100% re-evaluated by SWEC similar to the large bore support effort. The above scope description is not yet in the CPRT Program Plan response, but it will be in Revision 3 of the Program Plan. At this time: 0 the small bore population is defined o the high stressed small bore lines are being identified o the small bore lines that will experience fluid transients are being identified o the small bore lines that were " nomograph hung" are being identified o small bore supports that are attached to large bore lines are being identified 0 only standard small bore supports that are identified (from above) will be analyzed (in the New York office). That is not all standard supports will be analyzed. There are 144 standard designs. j

r "WTF1 m(NE ENGINEERING SERVICES Trip Report No. 2190a (continued) Item III - Pipe Support Reevaluation Status o Support reevaluation is ongoing as the pipe stress analyses are completed. o Those supports involved with technical issues are put aside until the issue is completely resolved. o Approximately 200 supports have been completed. o Snubber optimization is frequent. At this time: o 265 stress packages of 316 have been received from TUGCO. All will be received by mid-December. 50% are assigned to the New York office 25% assigned to the Houston office 25% split up between remaining three SWEC offices o Approximately 200 engineers now working (100 on supports and 100 on piping). The support staffing will have to increase, o 109 stress packages are in process of analysis. o an additional 73 of the 109 are complete with confirmation required. o The 73 stress packages represent 854 supports. o 354 of the 854 supports are now in analysis. o There is a backlog of about 500 supports, o The Boston and Cherry Hill offices are just beginning their support analyses effort. o Supports on lines where transients will be experienced are on hold until the transients are analyzed by the Boston office. o There are 8000 supports total in Unit I. o Small bore typical supports will be analyzed by the New York office.

r "RTA mYNE o ENGINEERING SERVICES Trip Report No. 2190a (continued) o Modifications initiated at the site will cause the effected supports to be put on hold (e.g., the single tube steel-richmond insert mod which adds gussets). o Optimization (small sample, so far) approximately one per stress package. That is 47 snubbers eliminated and I snubber changed to a strut. All of these were due simply to good engineering (i.e., small loads, small displacements, etc.) and all work to date has been done with the original spectra. o The only modification thus far has been to add an anchor. This was done to facilitate analysis. o Only other noteworthy problem so far has been with valve accelerations. These will be reanalyzed using the N-411 spectra which is now available from G&H. Item IV - Technical Issues Update The status of the Technical Issues was discussed. As they are completed and reviewed by the third party, SWEC will make presentations to the staff during the audits. It looks like at least three audits will be required to cover the issues listed. Item V - SWEC vs. CPRT Program Plan To compare the SWEC scope of work versus the commitment in the CPRT Program Plan, the 6 items listed in paragraph C on Attachment 2 of DSAP IX will be used as reference. 1. Development of Comanche Peak Pipe Stress and Pipe Support Design Criteria. This will be verified by a thorough review of CPPP-7. 2. Verification of As-Built Information. This will be verified by review of all walkdowns (e.g., CPPP-5, CPPP-8, the " penetration schedule"*, the TUGC0 79-14 walkdowns, and selected ERC QA/QC san.pl es. 3. Review and Verification of System Design Input, Seismic Accel-eration and Fluid Transients. This will be verified by a review of CPPP-10, the ARS used and the dynamic loads developed. Note: Dr. Shou Hou recently performed an audit at the New York SWEC office and looked at some of these things. Our effort should be coordinated with his. 1 I suggest we do a brief walkdown at the site to verify the accuracy of the data in this schedule.

I SPTri prVNE ENGINEERING SERVICES Trio Report No. 2190a (continued) 4. Verification of Existing Pipe Support Design Documents. This item may be eliminated or changed to be consistent with the present scope. (e.g., "all supports will be requalified by SWEC"). 5. Resolution of Special Technical Concerns. This will be verified by thorough review as discussed in agenda item IV above. 6. Reanalysis of Piping Systems and Reevaluation of Pipe Support Designs. Any modifications required to supports will be covered in the Repair Replacement activity of ASME Section II. This item is somewhat redundant. It appears to be covered in Items 1 and 4. Item VI - Additional Items A. SWEC asked what was the staffs' feelings regarding the use of secondary stress classification in pipe supports!! This is of concern to them, for example, on floor to ceiling supports. Dave Terao explained that the staff accepts either the 74 or 80 version of the code. The 74 version allows the use of 3 Sm as an allowable for supports but continued that in this case failure due to gross plastic deformation must also be considered. B. SWEC asked this opinion on the recommended change on cinched U-Bolt design. The original design and suggested modifications are shown on the following page. Most agreed that the modification is an improvement but there was concern regarding the addition of so many lugs (welded attach-ments). It was suggested that pipe clamps be used in lieu of lugs. RobertD.HoQway N Moger W. Stuart RDH/RWS:sig Attachments i ~

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7; December 6, 1985 J.O. No. 15454 NRC AUDIT AGENDA 1. CPPP-8 WALKDOWN A. NRC COMMENTS QUESTIONS B. UPDATE ON EVALUATION OF DATA BY SWEC 2. SMALL BORE PIPING STATUS UPDATE 3. PIPE SUPPORT RE-EVALUATION STATUS LARGE BORE AND SMALL BORE I i l 4. TECHNICAL ISSUES UPDATE 5. SWEC SCOPE VS. CPRT PROGRAM PMN S 4 g ~ i 6 h

r ] itTA m(NE ENGINEERING SERVICES ATTACHMENT II NRC AUDIT ATTENDEES Name Company John Finneran TUGC0 David Terao NRC W.P. Chen ETEC Roger Stuart Teledyne Bob Hookway Teledyne Rick Normandeau S&W Ron Klause S&W Peter Dunlop S&W K.Y. Chu SWEC Don Hernon SWEC Ron Wrucke SWEC

r ~ FFi? - 2 A T TA t/fM & T /!I ,y COMANCHE PEAK UNIT 1 FIELD WALKDOWN PROGRAM

===1. Background=== A. Ne.ed B. Procedure CPPP-8 2. Selection A. Stress Packages ,.: c F ;n ces y g o ic_ ;c 2p f 8. Engineers 3. Training A. Required Reading C9? l B. Indoctrination Training 7 6 l'*'#- /03 d

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= w.,c..e :.- : i n ;: n r u er 4. Walkdown , saf 47 y llll& - r y a. g.;, -.t w.'.:.i : rwm: T= ?. - ; ' ~ A. observations 9, w., a - ~,. i " c '. w.s ,%.a. a iya B. Saily Meetings ,1. M/. 7:> hr cor;est >" LiJ w4 c:eu rit 5. Action A. Valfdity Check B. Evaluation 6. Final Report

y' wW@ kWMNh1WY Ag OBSERVATION CATEGORIES 1. ANALYTICAL MODEL AND INPUT T i d, L. ',.G a h u. s 2. AS-BUILT DRAWING RELATED 3. STRUTS AND SNUBBERS 4. GAPS BETWEEN PIPE AND SUPPORTS 5. CLEARANCES / INTERFERENCES 6. NON-SEISMIC PIPING AND SUPPORTS 7. INTEGRAL ATTACHMENTS 8. WELDING fd6 / 9. STANDARD-COMPONENT SUPPORT QUALIFICATION s 10. CONSTRUCTION RELATED O.,Q.cEn e,b y. wf > ' e_ 11. MISCELLANEOUS 2v - ~ < - - * * /4-HT* l e 0 e e 6

7' in P W NE ENGINEERING SERVCES ATTACHMENT IV CPPP Large Bore Summary A. Items not considered significant because it is assumed that they will be taken care of in normal course of SWEC program. But, want confir-mation. 1. Snubber washers are okay as observed. 2. Hydrolocks will be removed. 3. Shear lug load distribution adequately considered in CPPP-7. 4. Spring hanger on threads is okay. 5. Analyst package will include required drawings. a. BR41, BRP, Supports, Pipe Whip Restraint; i.e., can confirm support function. 6. Ambient temperature will be correct (sealed room). 7. Missing or added insulation as observed is not significant. 8. Snubber installed 1800 from drawing. 9. Bellows configuration will be confirmed. B. Will the following items be reconciled during final walkdown? 1. Strut / snubber problems. a. offset, alignment, end for end inversion b. interference with rear bracket, etc. c. hardware okay, cotter pins, sph washers 2. Interferences (local, adjacent). 3. Support functions at pipe whip restraints. 4. Required clearance at support and sleeves for pipe movement. 5. _s,

ay - 'A P W NE ENGINEERING SERVICES C. Will the following items be clarified in CPPP-7? 1. Missing tie back 2. Tie back modeling consideration 3. Square pipe function and modeling 4. Roto hammers 5. Stress boundary - 0 3-way, 0 1-way, modeling at penetration, at dotted Class 5, at vents 6. Treatment of sepa.ated u-bolts at single support (i.e., -6") 7. Treatment of moment restraint potential at wide cross pieces (i.e., -6" T.S.) 8. Consideration of all attachments to each support including those not shown. 9. Wind load

10. Curved pipe point contact

11. Unique welds a.

non wrap-around 9 two sided T.S. fillet b. weld to vendor valve extensions and over pipe / extension weld

12. Unique trunnion situations a.

two sided weld on pad b. split trunnion welded anchor c. trunnion to elbow with gusset plate d. 4-trunnions to one anchor e. pipe through and welded to trunnion pipe

13. Additional hangers / struts welded to riser clamps.

D. How will the following be handled? 1. Problems with fire protection system. Damage study by TUGC0 - walkdown on category 1 system. 2. Gaps slightly greater than 1/16" (TUGC0 uses 3/16") Will ask TUGC0 to confirm gaps within tolerance. 3. Gaps greater than 1/16" 4. Baseplates without grout or with distortion. Will grout to TUGC0 procedure.

r SPTri prWNE ENGNEERING SERVICES D. How will the following be handled? (continued) 5. Unequal strut length 6. Lugs on risers without D.W. load 7. Concerns with branch connections (3/14" to 2") 04ST, #3. SWEC will review stress boundary (valve acceleration). 8. Boundary at instr. branch connections beyond 1st valve and up to instr. connection or 1st root valve (051A, #2) 4 l}}