ML20107E192

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Discusses 850207 Design Documentation Audit Meeting in Monroeville,Including Design Rept on Pressurizer Surge Line, Wording for Valve Operability,Stress Rept for Class 1 Gate Valves & Control of Min Wall Thickness.Documentation Encl
ML20107E192
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 02/11/1985
From: Rodabaugh E
E.C. RODABAUGH ASSOCIATES, INC.
To: Scott Moore
OAK RIDGE NATIONAL LABORATORY
References
NUDOCS 8502250423
Download: ML20107E192 (10)


Text

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FOR /CK-

$. 0 h o N aLLg k k $$0clabt.$, hnc. e* Y 4625 CEMETERY ROAD e HILLIARD. c." J026 614/876 5719 February 11, 1985 Mr. S. E. Moore Oak Ridge National Laboratory P.O. Box Y Oak Ridge, TN 37830

Subject:

Vogtle, Design Documents Audit, Meeting at Monroeville, February 7, 1985

Dear Sa:

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My letter to you dated January 31, 1985 summarized the status of our audit

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, priortothe2/7/85 meeting. Thisletterdiscussesthe2/7/85eeetingunder ,

the headings (1) Design Report on Pressurizer Surge Line (ECR No. 18)

(2) Wording for Valve Operability Qualification As Applicable to Vogel (ECR Item 10)

-(3) Westinghouse Engineering Memorandum No. 5045, Stress Report for Class 1, 6-inch and Larger Gate Valves (ECR Item 8).

(4) Control of Minimum Wall Thickness C

(1) Desirn Report on Prescurizer Surco Line The Design Report was not available and, according to Westinghouse, vill not' be available in final form until after the "as-built" dimensions are avail-able. A completion date of July 1986 was suggested by Westinghouse.

A compilation of calculations identified as an Analysis Package for the surge line was available at the meeting. Enclosure 1 is a " Table of Contents". -

from the Analysis Package. Enclosure 2 is a page described by Westinghouse as

" Input Directions".

'While at the meeting, we reviewed the contents of the Analysis Package.

With one najor and two minor _ exceptions the contents of the Analysis Package-24 l A l DR _.

1

, appeared to comply with the Code definition in NCA-3551.1: "The Design Report 1

is the design document which includes stress or calculations or both to show ,

1 that the allovsble limits are not exceeded for the loadings specified in the l l

Design Specification".

The major exception concerns the important requirements contained in HB-3640, " Pressure Design". We found nothing in the Analysis Package that in-dicates that the requirements of % 3640 have been or vill be met.

The two minor exceptions consisted o'f (1) The Code requires an evaluation of the effect of out-of-roundness on stress-es due to cyclic internal pressure. The surge lines contain pipe bends which apparently can be out-of-round by up to 6L Westinghouse indicated

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that out-of-roundness has not been included in their fatigue evaluations

  • cade so far. (We describe this as a min'or exception because the surge line dimensions / pressures are such that we think the out-of-roundness effect will turn out to be small for this particular pl. ping.

(2) In evaluation of branch connections, the Code requires sinultaneous consid-eration of branch moments and run noments. In Deadweight and Thermal anal-yses, Westingh'ouse has apparently "decoupled" the Surge Line from the Main Coolant Loop. This leads to some uncertainty as to whethar the moments so obtained are sufficiently representative of the actual coupled lines. (We-describe this as a minor exception because the details of the surge line evaluation suggest that a coupled analysis would not differ significantly frem the decoupled analysis.) G Uhile the Design Report for the surge line was not available, it is appar-

- ent that if that Report were to contain the Analysis Packago data, it would be several inches thick. Further, the Analysis Fackage calculations are them -

selves abstracted from computer print-outs. If the 1:omputer outputs were in-cluded, the Design Report might be. several feet thick. There is no apparent'ad c vantage in having a Design Report which embodies all these detailed calcula-'

tions; provided g

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W . (.a) The Design Report includes a comprehensive andLunderstandable (to an in-

- dependent reviewer) road map to the . tiles in which the detailed results A , are stored, and a>

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(b) The Design Report includes a description of how assurance is obtain-ed that the loadings given in the Design Specification vere used in -

the evaluations.

l In summary, we deem our audit of the Design Report of 'the Surge Line would .

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be satisfactorily completed by a commitment from the applicant to include in the final Design Report the following:

( A) A section on meeting 133-3640 requirements that would address aspects such as: M (a) Selection of corrosion / erosion allowance, "A" in 1 B-3641.1 E (b) Branch connections, I;B-3643 (c) Attachments (if any),1;B-3645 M

The detailed evaluations need not be included in the Design Report, but the Design Report should clearly show where these detailed evaluations are filed and be in a form that can be understood by an independent reviewer.

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(D) A_ section ( Appendix 7) which provides a comprehensive and understandable (to an independent reviewer) road map to the files in which the detailed ]

results are stored, and a commitment to maintain these files for as long y as the Design Report is required to be kept. -

(C) A section (possibly as part of (B) above) which describes hov assurance was n j obtained that the loadings (e.g., earthquake spectra) given in the Design 2 Specification (identified: e.g., 955211, Revision number) were used in the r.

evaluations that show th.a t Code limits are not exceeded. r_

(D) A section which briefly tescribes evaluation aspects which do not follow directly from Code rules. Some examples may be:

h (a) Inclusion of out-Of-roundness effects in fatigue evaluations -

(b) Coupling of piping systems in analyses -

(c) Use of Stress Indices, if any, which are not included in the Code. -2 (d) Use of combinations of generic system analyses with Vogtle-specific y analyses. 9

  • 2 ii-(2) Wording for Valve Operability as Aeolicable to Vogtle (ECR No. 10) d ECR No. 10 concerned a missing portion in General Valve Spec. G-678852/

Vogtle-specific Valve Spec. 952172. In the Westinghouse submittal, dated Eiii 12/10/84, this missing portion was supplied but I did not recognize it as  !

R such. Theportionsuppliedatthe2/8/84meetingisincludedherewith,as 3 1

Enclosure 3 I deem the audit of this particular document as completed.

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. (3) Stress Report for Class 1. 6-inch and Larcer Cate Valves ,

A sheet (Enclosure 4 herewith) was furnished at the January meeting, which was parported to indicate that the owner (or his designee) had reviev-ed the Report as required by the Code. I pointed out that the sheet did not clearly indicate that Georgia Power, as owner of Vogtle, had reviewed the Re-port. During the subsequent discussion of disorder of the Report furnished to me by Westinghouse, Georgia Power representatives at the meeting seemed uncertain es to whether the sheet (Enclosure 4) did, in fact, represent their review of the Report by authorizing Westinghouse to conduct that review for them. A commitment was made by Georgia Power / Westinghouse to provide a writ-ten clarification to the question.

The Report itself is deficient from a quality control standpoint. For ex-ample, there are approximately 500 unnumbered sheets in the Report. As per-haps indicated by the disorganized two-inch collection of sheets (with at least several sheets missing) that was furnished to us by Westinghouse, there appears to be no way to assure that a copy of the Report is complete and the sheets are in the intended sequence; except, possibly, by a painstaking effort by the writer of the Report.

C However, frc= a technical standpoint, the Repcrt cppears to indicate a reasonable effort to demonstrate compliance with the Code rules of NB-3500.

Accordingly, I am willing to drop our audit of this Report upon receipt of a-satisfactory response on the Owner's reviev question.

(4} Control of Minimum Vall Thickness This item was not on my agenda for the' meeting but developed.during our_re-view of the Analysis Package for the surge line. The problem develops in con-.

nection with use of nominalvall thicknesses in Code Eqs. (9) through (14). -

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. m, a- a . m - ..#. -e; m.~ <

- _p If the only control on minimum vall thickness is Code Eq. (1) or (2), then the minimum vall may be much less than the nominal vall. The problem is par-tially" addressed in the present Code, NB-3683.5 by the restriction that vall thickness must be not less than 7/8 times the nominal vall thickness.

Westinghouse, at the meeting, could only state that minimum vall thickness-es are not less than required by Code Eqs. (1) or (2). Westinghouse made a commitment to review this potential problem, perhaps starting with an inquiry to piping fabricators involved with Vogtle piping to see if, by any chance, the fabricators maintained some control of minimum wall thickness equivalent to a 7/8timesnominalvall. A vritten response is expected.

(5) Summarv (a) Design Report on Pressurizer Surge Line A reply to the proposed commitment is expected.

(b) Stress Report for Class 1, 6-inch and Larger Cate Valves A reply concerning the Owner's revieu question is expected.

(c) Control of Minimum Wall Thickness

-A reply concerning control of minimum wall thickness, other c than by Code Eqs. (1) or (2), is expected.

  • We should review the adequacy of Code Class 1, 2 and 3 rules from this possible minimum versus nominal aspect, but not as a part of the Vogtle audit. ,

Yours very truly, ECR/ar E. C. 'Rodabaugh :

Enclosures:

(1) Table of Contents, Analysis Package "

(2) Input Directions, Surge Line Analysis (3)ValveOperabilityWording (4) _ Sheet for Stress Report on Valves cc: Melanie Miller Dave Terao -

&* VV & D Ecc 4'Jrq 2/nlPS SURGE LINE YCN!"]b'ustlYoj fle : '75lle ,se M /r.,/s b g m j ,u , Ri d gy e on feige Liire Ob /amed af- 2/7/rs Mce>%ry

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SECTION 1 Microfilm Log SECTION 2 Support Load Generation SECTION 3 Speciai Component Qualification and Additional Work

]. (Nozzle Loads. Etc.) .

SECTION 4 Secondary Stress Qualification /Breik Selection (Fatigue, Eq.#12, #13 Break Selection)

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f SECTION 5 Primary Stress Qualification (Eq. #9 Design / Faulted)

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SECTION 6 Computer Solutions / Select / Combine (Dwt., Seismic, Themal, Jet, Etc.)

./ SECTION 7 Modeling and UPDATES BPC Initial Package /All Subsequent Packages /REF's SECTION 8

.SECTION 9 Final As-Designed Reconciliation SECTION 10 BPC Final As Designed Input

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e kpa/ Diach M 2 t'at6. ng 2 pit WlVoy svge twe AM/y. sis Ob f ainac2 af '2/7/ IS Mechny ,f; IETTER DAIE DATA (1) BW-3202 1/30/81 original Surge Dwg. (Rev. 0) (2) GP-5052 6/31/81 Data clarification (3) GP-5124 8/13/81 Jet Dat,a Clarification Request (4) En'-3457 8/14/81 Revision of Jet Data (5) AM-SSA-1744 9/10/81 Re' solution of Jet Quest. -. (6) GP-5485 12/28/81 Identifies changes to (12/4 Mtg. Minutes) to Dwg's. & Jets

     ',(7) BW-3556                      12/17/81                Rev. 1     tranmitted With Hand Markups (8) BW-3565                    12/29/81                Revised Jet Loads (9) BW-4034                    6/21/83                 As-Designed Package 1X4DL4A17, Rev. 7 h

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3.5.3.5 Seismic Qualification - Compliance with Paragraph 3.1.)6 for seismic conditions shall be demonstrated. 3.5.3.5.1 An extended structure analysis shall te done by si=ultaneously applying static loads equivalent to t'.2 peak accelerations along three mutually perpendicular axes at the : enter of gravity and the resulting mo=ents and loads at the sectioas of the valve assembly considered most affected. The analysis shall be submitted toj NEED. 3.5.3.5.2 Extended structure deflections which result from faulted condition loads and which affect valve function shall be evaluated. Deter =ination of the deflections and their effect shall be included in the analysis.

     . 3.5.3.5.3       The =ethod of analysis shall be verified by a static deflection test of representative valves. The test shall enec= pass the following:

A. Valve countihg shall represent the vorst case installation. The valve asse=bly shall include all accessories intended to be valve.=ounted. B. The valve body shall be pressurized at design pressure. C. The faulted condition seismic loads shall be applied at the center of gravity of the exten:ed structure in the direction of the weakest axis cf the extended structure. D. Valves shall be cyc' led with the extended structure in the deflected position. E. klere a design differential pressure tends to oppose valve opening, tests shall be performed with the design differential pressure initially applied across the disc. khere a design differe'ntial pressure tends to assist valve opening, the test shall demoystrate the ability of the operator to maintain the valve in the closed position. e i

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F. Operating times in the Seflected and undeflected ;iositions -

               -                 shall be compared and the significance of any change shall                  f    [ aa be evaluated.                                                                    =a Sebsequent to deflection testing, the ef fect on the valves shall                              _

be evaluated: 2 A. A mainseat leakage test shall be conducted. . Seat leakage $ " shall be compared to production test acceptance criteria and the significance of any excess shall be evaluated. M i The valves shall be disassembled and examined. Any damage- d B. shall be evaluated. 3 = Test reports shall be submitted to W NEED. f - 3.5.3.5.4 Mountings shall be e ialuated when accessories are counted on the i valve assembly. Def'.ections, natural frequencies and their  ! effects on the =ounting and the counted accessory shall be w included in the eva*.uation. 7

                                                                                                                   -i 3.5.3.5.5          Valve operators, position indication devices and control units
        '                     shall be seismically qualified in accordance with IEEE-323 and                       _i IEEE-344. Qualification reports shall be submitted to V NEED.                         W
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