ELV-03975, Discusses Differential Settlement of Buried Pipes & Forwards Design Manual Change Notice

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Discusses Differential Settlement of Buried Pipes & Forwards Design Manual Change Notice
ML20127G130
Person / Time
Site: Vogtle  
Issue date: 01/08/1993
From: Mccoy C
GEORGIA POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
ELV-03975, ELV-3975, TAC-M80515, TAC-M80516, NUDOCS 9301210154
Download: ML20127G130 (15)
v • d • e


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50-424 50 425 TAC 80515 80516 U. S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D. C.

20555 Gentlemen:

V0GTLE ELECTRIC GENERATING PLANT DIFFERENTIAL SET 1LEMENT Of BURIED PIPE At a September 26, 1989, meeting with Georgia Power Company (GPC) at the Vogtle Electric Generating Plant (VEGP) site, the staff initiated the issue of differential settlement of buried pipes and requested additional information.

Letters of March 19,'1990, and August 30, 1990, from Mr. W. G. Hairston, !!! to the NRC provided this additional information and supporting data relative to the differential settlements experienced by safety related buried piping at their interfaces between compacted backfill and Category I structures.

The August 23, 1991, letter from the NRC to Mr. W. G. Hairston, Ill transmitted the Safety Evaluation Report (SER) regarding the VEGP settlement monitoring program.

In section 2.4 of the SER, " Differential Settlement of Buried Pipe,"

the staff questioned the validity of the piping analyses.

This letter responds to the SER concern regarding the validity of the piping analyses by reporting the evaluation of all safety related buried piping.

The settlement monitoring program, as outlined in the VEGP Final Safety Analysis Report (fSAR) section 2.5.4.13.2.6, was established to monitor the settlement of the Category I structures to ensure that the interconnecting pipes have not exceeded design capacity.

Currently, over 175 surveying markers are being monitored at either 60-day or 6-month intervals.

Engineering reviews compare the actual differential settlement of adjacent buildings as seen by approximately 350 interconnecting pipes to the design differential settlement

values, Da:

By comparison, a total of only 38 safety related buried pipes interface between o R compacted backfill and Category 1 structures.

(See attached sketch SK-A-SMP-002 gg for penetration details.) The differential settlement experienced by buried inn piping is not addressed by the VEGP settlement monitoring program; therefore, no l*O survey points exist in the backfill free field for collecting data regarding-L*$8 changes in backfill elevations.

In the absence of this data, GPC has taken the most conservative approach (assuming zero settlement of the backfill) in the SQ evaluation of these 38 buried pipe lines to address the staff's concern Q

regarding the validity of the piping analysis.

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GeorgiaPo er b U. S. Nuclear Regulatory Commission l

ELV 0397S Page 2 An evaluation of all these safety related buried pipes was conducted as indicated by the attached Settlement Monitoring Program flow Chart. Table 1 (attached) summarizes the results of the evaluation which was conducted.

The following are the assumptions used in the evaluation.

j 1.

ACTUAL DIFFERENTIAL SETTLEMENTS A.

Continued to conservatively assume zero settlement of the compacted backfill and the buried portions of the pipe.

B.

Determined the installation date of the pipe and/or support.

The plant's construction data bases were re-examined for additional information on the welding of spool pieces and installation of supports to reconfirm the installation dates. Where additional information was found, the latest relevant modification dates were used for the installation dates, o

Whenever the pipe penetrates a sleeve in the structure foundation, and movement is allowed, the differential settlement stresses were not indt.ced in the pipe until the support was installed.

The installation date used was that of the earliest installed support near the penetration, o

Whenever the piae is embedded in concrete or grout, the installation date used was t1at of the last spool piece weld connection of the buried pipe.

C.

The settlement of the structure, subsequent to the installation date of the pipe / support, was taken from the survey data of the marker in the area where the pipe enters the structure.- A straight line method of interpolation between two actual survey reading dates (taken at either 60 day or 6 month intervals) was used to determine the " initial"-

elevation of the structure on the specific installation date of the pipe support or spool piece weld.

This " initial" elevation was subtracted from the subsequent elevations of the structure to determine the actual settlement of the structure.

D.

The actual differential settlement of th'e buried pipe is the actual' settlement of the structure (as discussed in C above) minus the settlement of the compacted backfill (assumed to equal zero as discussed-in A above).

In other words, the differential-settlement between the l~

pipe and the structure will equal the settlement of the structure from the date the pipe or support was installed.

The only exceptions are where the buried pipe penetrates at a sleeve in the diesel fuel oil storage tank pumphouse (DFOST) footing.

Since soil is adjacent to the footing both inside and outside of'the structure, in

- these cases, the actual differential settlement of the buried pipe. is the actual settlement of the structure (as discussed in C above) minus the settlement of the compacted backfill (assumed to equal zero as discussed in A above) minus the clearance between the pipe and sleeve at the time of piping installation.

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s GeorgiaPower U. S. Nuclear Regulatory Comm'.ssion ELV 03975 Page 3 2.

ALLOWABLE DiffERENTl/L SETTLEMENT The allowable differential settlement is the maximum differential settlement that can be permitted without exceeding the applicable allowable stresses in the pipe or in the support structure. This value is always equal to, or greater than, the design differential settlement. The allowable differential settlement values are shown under either the pipe or support column of Table I to depict which is controlling.

In those cases where the support is controlling, more refined calculation evaluations were performed using the actual support qualification.

calculation to determine the controlling stresses resulting from the load combinations imposed on 'he piping system. These stresses were_ compared to the applicable code allowable stresses to determine the reserve load capacity. The allowable differential settlement values for supports were computed where appropriate to utilize this reserve capaci'.

3.

DESIGN DIFFERENTIAL SETTLEMENT Table 7 of design criteria 00-1017 includes the maximum differential building settlements used in the original design.

These were previously applicable to both non-safety related and safety related piping whether buried or exposed between structures.

Because of inherent conservatism of these original values and our historical data of the actual settlement of buildings, we have established new design differential settlement values for safety related buried piping. Design criteria DC-1017 has been revised by change notice DMCN-1017 2 (attached) to reference design criteria DC-2144-B specifically for safety related buried piping.

Change notice DMCN 2144-B-3 (attached) now includes the new values for each of the' safety related buried pipe lines.

These new design differential settlement values were t

I established based on the following:

o The design differential settlement value is sufficiently greater than the actual differential settlement (25 percent where possible or more) to minimize any concern for additional future settlement.

l-o The design differential settlement value must be less than or equal to the allowable differential settlement.

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'5 CCOfglil POWCT E-U. S. Nuclear Regulatory Commission ELV 03975 Page 4 All of the lines have been reanalyzed by performing pipe stress calculations using the new design differential settlement values. Also, the affected supports have been reanalyzed by aerforming calculations to confirm adequacy using the loads associated with t1e new design differential settlement values.-

The results of the reanalyses reaffirm the design integrity of these safety related buried pipe lines and that none are overstressed. This addresses the concern expressed in the SER of August 23, 1991, regarding the validity of the piping analyses.

Should you have additional questions please inquire.

Sincerely, i

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C. K. McCoy CKM/JLL/gmb Enclosures xc:

Georaia Power _ Company Mr. W. B. Shipman Mr. M. Sheibani NORMS U. S. Nuclear _Reaulatory Com_miM 100 Mr. S. D. Ebneter, Regional Administrator

'Mr. D. S. Hood, Licensing Project Manager, NRR Mr. B. R. Bonser, Senior Resident inspector, Vogtle i

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ALVIN W. V0GTLE NUCLEAR PLANT DESIGN MANUAL CHANGE NOTICE (DMCN)

DMCN NO. 1017 2 DATE 6/17/92 INSERT THIS CHANGE NOTICE FOLLOWING THE COVER PAGE OF THE APPLICABLE DESI

_ CRITERIA OR SECTION AND RETAIN UNTIL CHANGE NOTICE IS REPLACED BY A REVISION DM SECTION OR DC NO.

00-1017 TITLE Pioe Stress and Pioe Sucoorts REY. NO.

6 PRINCIPAL RESPONSIBILITY:

Civil Q LIST: (/.)YES ()NO SYSTEN CLASS!FICATION: (X)SAFETYRELATED

()SAFETYINPACT

()0THER CHANGE REQUESTED BY:

() CLIENT (X) ENGINEERING

() SUPPLIER / CONTRACTOR REASON FOR CHANGE:

Naximum differential settlement values for, items 14, 18, 33, and 38 in Table 7 have been revised as a result of REA VC-2002.

DESCRIPTION OF CHANGE:

Revise Table 7 to add Items 14a,18a, 33a, and 38a.

APPROVAL SIGNATURES - SCS ENGINEERIlig QAIE ORIGINATOR

/.//

~

4-17 92.

INTERDISCIPLINE REVIEW:

M/f/M dd L.c t Mb CDM/D' ATE' dEM/DATE

'HOM/DATE' OTHER N/A N/A

    • SAR CHANGE

() REQUIRED X NOT REQUIRED NUCLEAR SAFETY ENGINEER av742.

PROJECT QUALITY ENGINEER

. O lE=

b h 4%

PROJECT DESIGN NGR.

4-V-ft PROJECT ENGINEERING NGR. d ?

'M oe h

MN/

.. L.

A P-

/

    • COMPLETED BY NUCLEAR SAFETl 9 INEER U/

000094 VPO4-92

DC-1017 kki the follcuing itms to Table 7, %vimM Differential MNing._

Settlrennt".

Differential Settlement Itm Descriotian (Inci m i 14(a)

DG bldg / buried FO piping See DC-2144-B (category 1 pipirg) 18(a)

DFDS tank pucphouse/

See DC-2144-B buried to pipirn (category 1 pipirg) 33(a)

Emnel IT2B/ buried NSCW See DC-2144-B transfer lines (category 1 piping) 38(a)

NSCW valve house train A/

See DC-2144-B buried pipire (category 1 pipirg) l-r l.

i 1

ALVIN W. V0GTLE NUCLEAR PLANT QESIGN MANUAL j ANGE NOTICE (DMCN)

OMCN NO. 2144-B-3 DATE._9/03/92 INSERT THIS CHANGE NOTICE FOLLOWING THE COVER PAGE OF THE APPLICABLE DESIGN

_CRjT M]A OR SECTION AND RETAIN UNTil CHANGE NOTICE 15 REPLACED BY A REVISION DM SECTION OR DC NO.

DC-2144-B TITLE Seismic Category 1 Buried Pipe REY. N0.

3 PRINCIPAL RESPONSIBILITY:

Civil Q LIST: (X)YES ( )NO SYSTEM CLASSIFICATION: (X) SAFETY RELATED

( ) SAFETY IMPACT

( )0THER CHANGE REQUESTED BY:

( )Clif.NT (X) ENGINEERING

( ) SUPPLIER / CONTRACTOR REASON FOR CHANGE:

Maximum differential settlement values for category 1 buried pipe are required as a result of REA VC-2002.

DESCRIPTION OF CHANGE:

Revise Table 1, " Maximum Differential Settlement Category 1 Buried Piping".

NOTE:

This table was added by DMCN 2144-B-1 and revised by DMCN 2144-8-2.

APPROVAL SIGNATURES - SCS ENGlHEER.JN_G DATE 9-3-12 ORIGINATOR INTERDISCIPLINE REVIEW: M9[JM.2 (Lh A M 2.

537 u CDM/D'AT'E

$@/DATE MOM /DATE' OTHER N/A N/A

    • SAR CHANGE

( )REOUIRED (X)NOT REQUIRED NUCLEAR SAFETY ENGINEER

'4 D A 9 3 PROJECT QUALITY ENGINEER

.C_ Jh

't /3/4 2.

PROJECT DESIGN MGR.

b N.cf A _A W 7

[.2 f

' 7.

PROJECT ENGINEERING MGR, Oc.e#

[)f]D C i

~

    • COMPLETED BY HUCLEAR SAFFTY ENGINiER VU VP04-92

1 f

Revise Table 1 as follows:

TABLE 1 MAXIMUM DirFERENTIAL SETTLEMEt4T CATEGORY l BURIED PIPlf4G Design Differential Settlement Line tio.

Interface (Inches) 1-1202-029-6" flSCW Valvehouse Train A 0.50 1-1202-030-6" NSCW Valvehouse Train A 0.30 1-1202-029-6" lunnel IT2B 0.50 1-1202 030-6" Tunnel IT2B 0.50 1-2403-044-4" Diesel Generator Building 0.80 1-2403-066-3" Diesel Generator Building 0.80 1-2403-053-2" Diesel Generator Building 0.80 1-2403-051-2" Diesel Generator Building 0.44 1-2403-068 3" Diesel Generator Building 0.44 1 2403-043-4" Diesel Generator Building 0.41 1-2403-044-4" DFOST Pumphouse 0,70 1-2403-044-4" DFOST Pumphouse Footing (See note 1) 0.50 l

l-2403-066-3" DFOST Pumphouse 0.50 1-2403-053-2" DFOST Pumphouse 0.60 1-2403-069-2" DFOST Pumphouse 0.50 1-2403-069-2" DFOST Pumphouse Footing (See note 1) 0.50 l

l-2403-051-2" DFOST Pumphouse 0.60 1-2403-068-3" DFOST Pumphouse 0.50 1-2403-043-4" DFOST Pumphouse 0.50 2-1202-029-6" NSCW Valvehouse Train A 0.60 2-1202-030-6" NSCW Valvehouse Train A 0.30 2-1202-029-6" Tunnel 2T2B 0.80 2-1202-030-6" Tunnel 2T2B 0.80 2-2403-044-4" Diesel Generator Building 0.44 2-2403-066-3" Diesel Generator Building 0.44 2-2403-053-2" Diesel Generator Building 0.44 2-2403-051-2" Diesel Generator Building 0.70 2-2403-068-3" Diesel Generator Building 1.20 2-2403-043-4" Diesel Geaerator Building 1.00 2-2403-044-4" DFOST Pumphouse 0.50 2-2403-044-4" DFOST Pumphouse Footing (See note 1) 0.50 l

2-2403-066-3" DFOST Pumphouse 0.45 2-2403-053-2" DFOST Pumphouse 0.50 2-2403-069-2" DFOST Pumphouse 0.60 2-2403-069-2" DFOST Pumphouse Footing (See note 1) 0.60 l

2-2403-051-2" DFOST Pumphouse 0.60 2-2403-068-3" DFOST Pumphouse 0.40 2-2403-043-4" DFOST Pumphouse 0.50 Notes:

1.

This interface is at the DFOST Pumphouse Footing and has soil adjacent to the footing oath inside and outside of the structure.

VP04-92 t

1 1

MIDWEST INSPECTION SERVICES

- Ra vmord Enob, owner sac G!cn P.O Box 1229 2116 W 20th Porr/ ton, TX 7M70 Eik City, oK 73644 800 435 4043 405 225 2108 '

January 8.

1993 United States Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drave. Ste. 1000 A r l i n g t.o n. TX. 76011 Attn:

L.

J, Callan. Director Division of Radiation Safety and Safeguards h

2W RE: License No.-

35-27005-01 uh s

Docket No.

30-31327 Reply to a Notice of Violation gg This letter is in response to the violations identified during an NRC inspection conducted on December 2-3, 1992.

Violation A.

Recharging of Pocket nosimeters Radiographers pocket dosimeters were not always being recharged on a daily basis.

This is evident from the beginning dosimeter readings on the daily job sheets.

All the radiographers have been trained that recharging their dosimeters dai.ly is mandatory.

Apparently in the day to day routine of completing their paperwork some of them became lax in this area.

I also had become lax in my duties as I had not been reviewing each daily job sheet If I had done this, the problem would have been corrected prior to the inspection.

In order to correct this violation. I had a meeting immediately after the inspection with the radiographers and reiterated the requirement that pocket dosimetere be recharged daily and that no beginning readings were to exceed 10 mr/hr Another person ir nur company has also been assigned the responsibility of reviewing the daily job sheets in the event I may not be available.

Full compliance was achieved on-. December 4.

1992.

A review of all daily job sheets for the remainder of December shows no violations.

Violation B.

Field Examination Records Records of Field Examinations for Radiographers has'been maintained by Item 8.

Examination No. 3-(copy attached).

However this examination has not been' required in our policy and procedures for Radiographer Assistants.

A statement on the first 1

page.of Item 8.

Examination No.

1, (copy attached), certifies 4 n -11/

I

- ] "3 % 0

~

. x MIDWEST INSPECTION SERVICES P

' naymond Erzet. Owner

- Skip Gt0A -

P O Box 1229 2116 W. 20th Porrfton TX 79070 Em Cith oK 73644 MX, 4344043 405-225 2103 that the--individual has demonstrated his competence to use the sources of radiation, related handling tools, and radiation survey instruments.

This Examination No. 1 is given to all-Radiographer Assistants and is maintained in their file.

Field-examinations are given to each Radiographer Assistant to assure they know how to use the equipment.

In order to assure the requirements to maintain a record of field examinations is fulfilled. Examination No. 3 will also be given to Radiographer Assistants.

FulI compliance was achieved on December 4, 1992 with the implementation of Examination No. 3 in the radiographer assistanto training requirements.

I trust that by taking the corrective actions listed, we are now in compliance with the Nuclear Regulatory Commissions rules and regulations.

Radlation Safety Officer

[

Ship Glenn ec: US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC, 20555 t

1 J~

.17E%i TITLE fi EXAMINATION No.

3 - INDilSTPTAL PADIOGRAPHER D7di' 1

II.TXFfRIAL WOIO3MsPIIFPS PDGDi"ildG DiMJNSTWiTION OIFD11ST OJMPlJU W O103RAPHDI

'Ihis denonstration perfornunce test should consist of one or nore actual film exposures perfonmd by the individual being tested without the assistance of any other radiogralier.

i 1.

Film badge an3 dosinnter being used and dosirmter mcharged and reconkd.

0 1 2 3 4 5 6 7 2.

lenoval of canera from storag2 vault and signing it out on utlilzation log.

0 1 2 3 4 5 6 "i 3.

Surveying canura to insure source is in a safe position. Rtking sure that survey nuter is wrking, calibrated and readina radiation.

0 1 2 3 4 5 6 7 4.

Performxl a daily inspection of canera and related han.11ing equipmnt, and truck survey.

0 1 2 3 4 5 6 1

l 5.

Calculation of restricted area and posting of turriers and warning signs.

0 1 2 3 4 5 6 7 6.

Propir assenbly of source to crankout.

0 1 2 3 4 5 6 7.

Survey of the perireter of the restricted area.

0 1 2 3 4 5 6 7 l

I 8.

Survey of the canura and razce tube af ter each exposure.

0 1 2 3 4 5 6 7 l

l 9.

Emosure device locked after each exposure and i

b2 fore being noved.

0 1 2 3 4 5 6 7

10. Use of available shielding if present end collimator if available.

0 1 2 3 4 5 6 ll, renoving crankouts and source tube arrl replacing dust covers and safety plugs.

0 1 2 3 4 5 6

12. Storage vault secured and locked af ter re-l turning canura to storag2.

0 1 2 3 4 5 6 COMPANY ITEM

.8 24 26 PAGE Midwest inspection Services of

9 (El TITLE 8

EX AMIN ATION NUMBEll 3 - con t ' d.

13.

Ut.11ization log properly empleted.

0 1 2 3 4 5 6 7 14, Daily jcb sheet pmperly cxx:pleted.

0 1 2 3 4 5 6 7 15.

Ibsimiter Itcad and Ibcorded.

0 1 2 3 4 5 6 7 COMPANY ITEM PAGE g

25 26 Midwest inspection Services of

ITEM :

TITLE 8

HADIOGRAPHER'S ASSISTANT-EXAMINATION IUEER 1 03MPNTI PADIOGRAPHER DATE PADIOGRAPIER ASSISI 7#f tez1tSIER OJURSE This is to certify that on this day of has re ived instructions in the Operating and Dnergency Procedures and Regulations for Radiation Control as detailed belos ard has proved his understandina thereof by neans of a written test. Furtiernare, he has acronstrated his a2cpetence to use, under the personal supervision of the Radiographer, the sources of radiation, related handl.ing tools and radiation survey instnrnents.

The follcwing subjects are included in the Operating and Diergency Pro:cdures:

1.

The safe hanaling and use of the sources of radiation employed by the licensee.

2.

Use of the radiation survey maters and nethods and occasions for cc:dLW surveys.

3. - Methods for control. ling access to radiographic areas.

4.

K2thods and occasions for-locking ard sectL% sources'of rnAintions.

5.

Personnel nonitoring and use of personnel nonituring equip-l nent (fihn badges and dosincters).

6.

Transportation to field locations, including packing and post-inJ of vehicles and control sources.

7.

Minimizing exposure of perscris in the event of an accident.

8.

Procedure of notifying proper persons in the event of an n M Rent.

9.

Peaard 'reeping.

COMPANY ITEM PAGE Midwest inspection Servie.T

-8

  1. of 26 i

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