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Forwards Addl Info Re Technical Resolution of Nonseismically Qualified Discharge Piping for Emergency Equipment Cooling Water sys.W/51 Oversize Drawings
	ML20245J161
Person / Time
Site:	Browns Ferry
Issue date:	06/05/1989
From:	Michael Ray; TENNESSEE VALLEY AUTHORITY
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20245J165	List: ML20245J161; ML20260B894; ML20260B897; ML20260B903; ML20260B909; ML20260B915; ML20260B919; ML20260B925; ML20260B931; ML20260B936; ML20260B941; ML20260B947; ML20260B953; ML20260B958; ML20260B963; ML20260B969; ML20260B975; ML20260B981; ML20260B985; ML20260B991; ML20260B997; ML20260C001; ML20260C006; ML20260C009; ML20260C013; ML20260C017; ML20260C023; ML20260C028; ML20260C034; ML20260C037; ML20260C042; ML20260C048; ML20260C053; ML20260C059; ML20260C066; ML20260C071; ML20260C075; ML20260C082; ML20260C086; ML20260C092; ML20260C097; ML20260C103; ML20260C109; ML20260C113; ML20260C118; ML20260C124; ML20260C127; ML20260C132; ML20260C137; ML20260C141; ... further results
References
	NUDOCS 8906300201
	Download: ML20245J161 (70)
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l TENNESSEE VALLEY AUTHORITY CH ATTANOOGA, TENNESSEE 37401 SN 1578 Lookout Place 90N 051989 l

U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Hashington, D.C.

20555 Gentlemen:

l l

In the Matter of

)

Docket Nos. 50-259 Tennessee Valley Authority

)

50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - ADDITIONAL INFORMATION CONCERNING THE TECHNICAL RESOLUTION OF THE CLAY PIPE ISSUE This letter provides additional information concerning the technical i

resolution of the nonseismically qualified discharge piping for the emergency equipment cooling water (EECH) system.

This information was requested in a meeting between TVA and the NRC Paff at the NRC office in Rockville, Maryland on March 14 1989.

The information requested was also addressed in the meeting summary letter from Gerald E. Gears to TVA dated April 3, 1989. provides TVA's response to specific NRC concerns.

provides the EECH pressure drop calculation to demonstrate that the EECH system is capable of providing adequate flow to all essential users based on worst case conditions. Enclosure 4 provides marked-up system flow diagrams indicating the proposed modifications.

4 contains a list of commitments.

If you have any questions, please telephone Patrick P. Carier, Manager of Site Licensing, BFN, at (205) 729-3570.

Very truly yours, TENNESSEE VALLEY AUTHORITY NN'7\\\\cq k N

Managerf/ Nuclearl Licensing and Regulatory Affairs Enclosures cc:

See page 2

[OP I

8201 890605 p

,OCK 050002e;p FDC 4

An Equal opportunity Employer j

..u_________________________________________________

_ GUN 051989 U.S. Nuclear Regul4 tory Commission I

cc (Enclosures):

Ms. S. C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B. A. Hilson, Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NH, Suite 2900 Atlanta, Georgia 30323 Browns Ferry Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000 f

l 1

i ENCLOSURE 1 l

CLAY PIPE ISSUE COMMITMENT t'

The modifications to reroute the three emergency equipment cooling water l

(EECW) discharge paths which discharge into the vitrified clay pipe to seismically qualified EECW discharge piping will be completed before tensioning the reactor vessel head.

l h

I ENCLOSURE 2 TVA'S RESPONSE TO NRC'S CONCERNS 1.

NRC Concern:

To what code will the proposed modifications be designed?

TVA Response:

The emergency equipment cooling water (EECW) System Design Criteria, BFN-50-7067 Revision 1, Section 3.8.(2) and Final Safety Analysis Report (FSAR) Section 10.10.4 require the rerouted EECH discharge lines to be designed in accordance with USAS B31.1 (1967 edition).

j 2.

NRC Concern:

What potential technical specification issues need to be addressed if the modifications have not been made before

)

the reactor vessel head has been tensioned closed?

TVA Response:

The modifications for the proposed reroutes will be completed before tensioning the reactor vessel head; therefcre, no technical specification problems are anticipated pertaining to any mode changes at BFN.

Interim measures are documented as special requirements in the safety evaluations for each Design Change Notice to facilitate implementation of each proposed reroute.

These measures allow various EECH supplied users to be taken out of service while modifications are being made without violating any technical specification requirements.

3.

NRC Concern:

What are the effects of the proposed modifications on other Unit 2 systems or other Browns Ferry units as described in the FSAR?

TVA Response:

The proposed modifications will not adversely affect the performance of any other unit 2 systems or any other Browns Ferry units.

The proposed modifications involve equipment required for operability of each unit at BFN; therefore, the new configuration will support restart of any additional units after unit 2.

As stated above, interim measures are taken during implementation to ensure all affected systems are maintained within technical specification limits.

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tva sos 92 'cNE e ssi DNE CALCULATIONS TITLE PLANT / UNIT Pressure Drop Calculation For EECW (System 67) Piping BFN/1-3 PREPARING ORGAN 12 Af TON KEY NOUNS (Consult RIMS DESCRIPTORS LIST)

PI-TEP-BWP-HCG EECW, Headloss, Pressure BR ANCH/P AOJECT IDE NTIFIE RS Each time tnese calcuestions are esswed, preparers rnwst ensure that the or@nal (RO) RIMS accessica numoer is f elled in.

MD-Q2067-880346 Aev (for RIMS' use)

RIMS accession number aa E 04

'89 0509 200 APPLICABLE DESIGN OOCUMENTisi BTN-50-7067R1, DIM-l&-2.

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UN D $ YSTEM(St 67/24 R,,,,

Revision 0 Pd R2 R3 Safety f etatedP Yes C No O ECN No, (or encicate Not Appl 4ao6el

'4 / A Staternent of Problemt This calculation 15 serlorsed to satisiv resanning

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resuiresents uncer lettaen 5 cf ifk 5!F1 Nc. 67-53

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g, becked g /tg f/4/(9 shich is tBe response to Caservatten ko. SF-!M 5

( jul/A M U.f K1;u o tientshag th! Calculation ' tits 3rstes Pressure Drco Calculation', PEI'84 0928 010, F3 for revision.

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Appeeved /)

This calculation is also tenfig stricreed tesard yt nsolution cf Ct4E he.)ff87009 (Clay Pise issuel andP/Lltess 2-2113, 2-0068, 2-0080 and 2-0921.

Dau 5 V

jg This ululatip n tung nrfened to gnenute List all pages added that the ((CW Ivstes hrdraulat resistances are ja! by this tevision.

adasustely Ice considering the flor desand free

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List all pages deleted all essential users in addition 10 the effect of 3;f by this revision.

line breats in the sodius hypochlorate systes.

$*I List a:1 pages changed This calculatsen susersects Calculation by this revision.

P.El'84 0928 010. R3.

Abstract This calculation analyses the IECs pising of nine (9) essential users These calculations contairi ari unverified assurnetionis) to detersine the total dynaast headless throughout the cesconents ((CW that triust be verified later.

Yes O No @

fles sath fres EECW puso intate to the discharge catch testa. The g

gg difference tetseen the cesconents disttarge goint and the EECWsuasintate. The sus of dynesic and statat losses corresponding to each tescenent are subtracted free an appropriately derated puss head for a cuantity defined as sargin. A pos'tive sargin indstates the resistante of the tesponents f!ce satt configuration as adequately los persitting the recuired EEClf flos while a negative sargin toditates that tfie recuired fles say not be available for the assused conditions.

The assused conditions antlude the fo!!cstegs h op Derating 27 Percent

.a Header (cading All (ssential Users

Preten Hypoth] Ltees Pusos Ocerating = One on North Headert One on South Hester Pusp Intele El 5 ? ft. (Breech of Wheeler Cas) s torrosion level e-4Hearattle Fcr Carten Steel Table !! thces asong the nine tcaponent Iceps analy:ed rath here signalstantly pesstive targaris estest the U3 St6A enith has a larce negattie sargin. This Ce4ttency has teen greviouser scenttited and is aggressed in 8:2'88 1:06 013.

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MD-Q2067-880346 0

Calculation No.

evision Method of design verification (independent review) used (check method used):

1.

Design Review

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Alternate Calculation 3.

Qualification Test Justification (explain below):

l Method 1:

In the design revie,t method, justify the technical adequacy of the calculation and explain how the adequacy was verified (calculation is similar to another, based on accepted handbook methods, appropriate sensitivity studies included for confidence, etc.).

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Method 2:

In the alternhte calculation method, identify the pages where the alternate calculation has been included in the calculation package and explair. why this method is adequate.

Method 3: In the qualification test method, identify the QA documented source (s) where testing adequately demonstrates the adequacy of this calculation and explain.

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REVISION. LOG Te n,. Pressure Drop Calculation For EECW (System 67) Piping MD-Q2067-880346

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DESCRIPTION OF REVISION "l'

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Initial Issue

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f:Ett Untt 2 Restart C,d f 4/89 Date Preccure Drop Calculation,.

Prepared By For CECW System Piping 7

Drowns Ferry Nuclear Plant Chec t:ed ByNC Date 43)

TABLE OF CONTENTS Ees1 Lee Iille Ecse Pevision Log i

Table

.'f Contents 2

1.0 Purpost 3

2.0 Design Input Data 4

0.0 Assumptions 4

j 4.0 Justi ficatior of Assumptions 5

5.0 References 6

6.0 Discussion 9

7.O Method 9

8.O Results 13 9.O Conc 1usions 15 1

10.0 Appendixes 39 - 59 (Ref 5.22 through Ref 5.29 and 5.32) 11.0 Attachments 60 -102 (Ref 5.1 through 5.15)

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For EECW System Pipino 9rowns Ferry Nuc1 ear P1 ant Checied By M __Date_

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This analysis is being performed to satisfy remaining requirements under Section 5 of BFN SSFI No.

67-53 which is the respon.W to Observation No.

BF-SMK-5, Rev 1 identi f ying DNE Calculation "EECW System Pressure Drop Calculation", MEB'84 0928 010, R2 'or revision.

This calculation is also being performed toward resoluticn of CADP No.BFP89009 (Clay Pipe issue) and P/L Items 2-2113, 2-0068. 2-0080 and 2-0921 as i dent i fi ed i n Pe f 5. 28.

In addition to the above reasons the calculation is being performed to demonstrate that the EECW System can withstand the loss of water that would be associated with a line break in the sodium hypochlorite system.

This calculation therefore supersedes DNE Calculation "EECW System Pressure Drop Calculation", MEB'84 0928 010, R3.

This calculation determines hydraulic 1osses throughout portions of EECW supply and discharge piping which provide cooling water to essential users as required to support Unit 2 restart during Mode OG7-01-M-S.

The calculation further determines whether or not the total resistance (based on 40 year plant li fe corrosion) in the available flow path for each component is sufficiently low or alternately too high to permit adequate EECW cooling.

l h-m---_.___-_-__________

o 1

MD-02067-880346 Sh e e t __I__ _ O f __,.,

BFM Unit 2 Restart

resrure Drop Calculation Pr ep ar ed Byf_M__Da t e__Q8' For EECW System Piping j

i Orowns Ferry Nuc1 ear P1 ant Checled By M __Date_[/_

.3 2.0 E251GO 10291 Dg13 1.

System layout as defined in TVA drawings (Ptf 5.1 to 5.15) 2.

Peservior level of elevation 529 corresponds to Breech of Wheeler Dam.

i 1

3.

Unless otherwise designated, corrosion level of carbon steel piping corresponds to 40 year plant life as speci fi ed in Fig 7 of DS-M2.5.1, Rev 4 (Pef 5.16).

I 4

The minimum required flow rates to individual components for all essential users are as defined in Ref 5.20.

The resulting fl aw requirements are shown in Table XI of t hi s c alcul at i on.

5.

The maximum flow loss due to a break in the Hypochlor19e System Non-Ouali fied piping lines is speci fied in Pef 5.29 and 5.30 as 56 gpm per injection line.

3 0 655U2911205 1.0 Both operating EECW pumps (one on the North header and one cin the South Header) are both degraded equal 1y.

2.0 The maximum flow avail able will be based on an average of the EECW Pump degradations at the design fIowrate of 4500 gpm for all eight pumps.

These values are speci fied in Pef 5.19, Sheet 8, which gives an average pump degradation of 27.14 percent.

3.0 All loops containing temperature control valves will require maximum flow i.e.

no throttling at the TCV.

4.0 All non-essential loads are receiving their cooling water from raw cooling water (RCW) System 24. Therefore these loads are isolated from the EECW System.

5.0 EECW loads are evenly split between the North and South Headers.

6.O Perouted discharge connections used for U1/U2 Control Bay Chillers, U2 SDBR and U3 Control Bay Chiller are estimates based on.si: etches _f r.om t he.-DCN's -i ndi c at ed - i n-Fe f 5. 2 7. - ---

. g-02067-880346 Sheet __{___Of__##$__

sm Uni t 2 Restart hmgr.u r e Drop Calculation Prepared By $__ _Da t e[_d_/ e 9 eg EECW System Ptpina krewris Ferry Nuc] ear kl an t.

Checked ByNLh__Date_

8[

,4.0.!U21.111$21120 0 f 63;uggligg3

,hsumptions 1.0 and 2.0:

Pef 5.19, Sheet 8,

gives degradation of the eluht pumps as 33.22, 21.12, 24.40, 13.52, 27.55, 22.72, 22.80 and 26.08 percent.

The average i s 27.14 percent.

Using the best performing pump of 18.52 percent as a reference and degrading it an additional 10 percent gives 27.65 percent which compares to the average.

This parallels the standard practice of degrading new pumps 10-percent, but is more conservative.

Assumption 3.0:

This condition maintains the system flow demand at maximum values and is therefore conservative.

Assumption 4.0:

Pefer to Ref 5.19, Sheet 7,

item 4.

i 1

Assumption 5.O.

l I

It can be shown irom PPf 5.1 and 5.4 that the restetances 1 rom pump l

dircharges along the Nor th and South supply headers + m. t he c ommon i

supply tee to any load are of negligible di f f erence and ther ef or e the EECW 1 cad centributiens ere cons 1dered even1y splat between there two supply coutces.

-hZ/y/v,/e5 Ass mption 6. 0:

_.~

j The discharges from U1/U2 Contrel Bay Chil1ers, U2 SDBR and U3 Control Bay Chiller are are rerouted from RCW (System 24) discharge header to EECW (System 67) discharge header in accordance with the requirements of Pef 5.27.

Since the involved piping connections are short runs of approximately 8 feet or less the actual routing when avai1able from issued drawings should ref1ect minor differences from the assumed routing.

The hydraulic losses when computed from the geometry of actual connections should differ only slightly from the losses shown herein.

wy Sh ee t _y'____O f __s e g

@i00067-880346 L en.T Unit 2 Restart s est.ur e Drop Calcul ation Prepared By_kk __Date[_h/_89 r

%r EECW System Pipino BvM(__Date_[h_hf W ovn t, Ferry Nuclear Pl ant Checled

".o e:12aaaaa 5.1 EECW Flow Di agrams (CCD): 1-47E959-1 Roll I

2-47E859-1 RO11 l

2-47E859-1 ROO6 3-47E859-2 R004 5.2 FCW Flow Diagrams (CCD):

1-47EG44-2 R004 2-47E844-2 ROO6 5.3 ACCW Flow Diagrams (CCD):

3-47ES66-7 POO2 5.4 EECW Piping :

1 I

47W451-1RH, -ORF, -2RE, -4PH, -5PL, -7PD, -10RD TAC) 47W451-6R24, -7R23 (AD) 5.6 Standby D G Bldg - Exp sed Piping 47W586-1RE, -3RC, -5RB (AC) 5.7 Drains and Embedded Piping 47W587-1RB L-2RB 5.8 Reactor D1dg HVAC Piping 47W935-1 R12, -3R4. -5RS, -7RG (AD) 5.9 Reactor Bldg Piping CW,GS,& M-G Piping

.;7W446-2RE, -4RA, -11RA (AC) 47W446-5R12, -17P1 (AD) l

t

\\

MD-02067-880346 Sheet __2___Of_I_3___

i FFM Unit 2 Pestart W etcure Drop Calculation Prepared By_#k__Date_##f_/8]

'~, r ECCL 3 System Piping

?ro nc Ferry Nuclear Plant C hec t:ed Sy

_ _,_ _ D o t e.._ _ _..

5.10 St andby D G Bldg - Dr ains

?> Embeddted Piping 47W5C5-1 PD, -2PA (AC) l 5.11 Yard Piping - Bldg Drainage 17W405-1 R25, -OR7 (AD) 5.12 Pumping Sta & Water Treat - Piping & Eqpt 37W205-4RF (AC) 0-37W205-5 POOO (CCD) 5.13 Yard Piping Isometric - EECW 17W3OO-9PB (AC) 5.14 DG B1dg - Unit 2 - HVAC 17W925-4P8, ~5R5 (AC) 5.15 Standby DG Bldg - Exposed Piping 47W533-1RC, -2PB, & -4RA 5.16 Mech Design Std - Prensure Dr op Cal c ul at i on For Paw LJater Piping and Fittings, DS-M3.5.1, P4 5.17 Crane Technical Paper No.410, 23rd Printing, 1986.

5.18 DNE Calculation - EECW System Pressure Drop Calculation, MEB'84 0928 010, R3 5.19 DNE Calculation - EECW High Point Vent Check Functionality Veri fication of Diesel Generator Heat Exchanger Loop, B90 890210 204, RO mam___a_.

n n ~;OE 7-8SO3-16 Sheet __$___Of_#__3___

IFN Unib 2 Pestert Prepared By______Date_'_ y E9 9 nmur e Drop Calcul ati on -

%:. r E~CW System Pipina i

5, owns "erry Nuc1 ear P1 ant Checked By

_h_Date M

I 5.00 Baseline Tast Requirements Document, BFN-BTFD-026, Pev.;, 830 87 08 1210 001 and Change No 1,

B30 88 0812 507 5.21 Transactions of the ASME, Apri1, 1944, " Pressure Loss in Elbows and Duct Branches", By Andrew Va:sonyl, Cambridge, i

uass.

5.22 Contract 87NJG-75093A, Purc Peq NO. BFP7-OO9, Appendit G data sheet.

5.23 Contract 70C35-92302-2, Data Sheet 5H-431.

5.24 Contract 68C30-91068, Guaranteed Data - Sheet 2 5.25 Contract 74C35-85589, Data Sheet 6341.1.

5.26 Contract 74C35-84890-1, Data Sheet J2-A246.

{

5.27 Form 45D f rom W G Asl:ew to C W Fulwider dated March 16, 1989, enclosing sketches f rom DCN's H5120A lunit 1), H5121 (unit 2) and H5122A (unit 3).

5.28 Form 45D f r om W G Asi:ew to C W Fulwider dated Feb 2,

1989, identi fing eddi tional uafety related equipment to be included in the analysis.

5.29 Letter f r om Bechtel NAPC to TVA BFP Project Engr dated Aug 5, 1988.

5.30 DNE Calculation: "Hypochlorite Injection Pipe Failure",

MD-OOO50-88295.

5.31 Piping Bill of Material 47BM451-3 RO, Sheet 1 of 1, Mark No. 212.

5.32 BFN SSFI Action Item No 67-53, Attachment 3, Rev 1:

Response to Observation No BF-SMK-5, Rev 1.

5.33 Browns Ferry Nuc1 ear P1 ant "Petest of EECW F1ow Through U3 Shutdown Board Poom Chi 11ers" B22'88 1206 013.

. ~.,

.__m

re.c067-880346 Sheet __9___Of_[__E h Uni t 2 Pestart

- i.gsur e Dr op Cal c ul at i on Prepared By N ___Date_#ffff]

,c,,e EECM System Piping

~ dr,wn s Fer r y Nuc 1 e a r P3 ant Checied Dy

,h__Date [ d 1,0 EliGU55120 This calcul ation determines hydraulic losses under conditions of highest fl ow demand throughout representative portions of EECW supply and discharge piping which pr ovide cooling wat er to essential users as required to support Unit 2 restart during Mode 057-O!-M-S.

In addition, the calculation demonstrates whether or not the total resistance (based on 40 year plant life corrosion levels) In the available f l ow paths are 1ow enough to permit adequate EECW ccoling f1ows or alternately are too high and therefore would preclude adequate EECW cooling.

7.0 tigMgy Hydraulic 1osses throughout portions of the EECW system are computed based on the methods speci fied in Pef 5.16 and the piping con figur ations shown on AC drawings as 1isted in Pef 5.1 to 5.15.

Flow conditions analyzed correspond to the most demanding header f l ow with fully corroded carbon steel piping.

Headlosses are computed and totaled along the complete flow path which typically originates at Pump C-3 discharge, follows the North supply header to the exit tee of the components supply loop, procedes through the components supply proing until combining with the South header equal f l ow contribution, then passes through the components heat exchanger and discharge piping to combine wi th the discharges of one or more other components and enters the EECW discharge header to ex.t d

at an over flow basin.

The piping geometry as required for each flow path and the corresponding head loss computations are tabulated in enclosed spreadsheet Tables I through IX.

Each table consists of c on fi gur at i onal data as displayed in columns "A"

through "T"

and computational data as disp 1ayed in columns "V"

through

.,\\

"AO".

Each row of data in Table I through IX corresponds to an individual pipe segment which is anal y:ed end to end for headless contribution to the entire f l ow path.

e MD-02067-S80396 Sheet _'_0_ _ _ _ O 1_ _'_* S _ _

f BFN Unit 2 Restart Prescure Drop Calculation Pr ep ar ed By_#9__. *,at e[_/f_I_M i

For EECW System Piping Checked By k __Date_[_! 8)

I Brownc Ferry Nuclear Plant i

The spreadsheet columns A through AO are defined as f oll ows:

E21910 20d Desetigileg Egt (ggliggtgligggi Petgeeigt; i

A Node point at start of pipe segment.

B Node point at end of pipe segment.

C Nominal size of pipe, in.

D Pipe material: CS = carbon steel; ss = stainless steel.

E Length of pipe from start to end nodes, ft.

c..K Number of each type of elbow or valve as designated.

L..M Increaser or reducer at the end node.

N Number of ori fices.

O..O Nominal diameters of tee at the er'd node (minus denotes flow out; plus denotes fl ow i n :>.

The run of the tee consists of diameters D1 and D3 with D2 as the lateral.

Di ameters may be equal or unequal.

P Denotes flow path orientation through the tee in accordance with the convention of Pe f 5.16.

S Denotes nonpipe elements such as heat exchanger t.H X :1, strainer ( S t r :), or exit loss (EXIT.). et.

T Physical piping drawing for nodn analy:ed.

U Deleted

-:=.;

=

- -. ~ - - - - - -

1 i

i

MD-02067.-890346 Sheet Of

'#4

~~~~~~

~~~~~~~

EfN Unit 2 Restart roseure Drop Calculation Prepared By[_Y __Date_#/[_/89 o

Fer EECW System Pipinci Druwn: Ferry Nuclear klant Checked By

(__Date_

dj

$21200 ggd Dg;ggrigtigg [2E C200U12112001 C2C202.l2E2 V..W Same as columns A and B.

X Incide diameter of new pipe (in) minus 0.80 in. or alternate corrosion allowance as specified at top of column.

Y C-factor of pipe: C = 55 for carbon steel (or alternate as specified at the top of the column) and C=

100 for stainless steel.

Z Flow, gpm.

AA Friction loss in feet per 100 ft. of pipe as defined on page 2 of Ref 5.16.

AB Form loss in feet per 100 ft. of equivalent pipe length as defined on page 2 of Ref 5.16.

AC Total equivalent pipe length as determined for the elements indicated in columns F through K as based on Table I and Fig 1 of Ref 5.16.

Pefer to Table X for spec i fi c values used.

AD Velocity (fps) as determined from the equation on Form 1 of Ref 5.16.

AE Inside diameter of a converging tee at the side of the flow path not taken (pnt). This parameter is required for converging tees only.

1

- =: - : =.~ =.-..= =.~ _.

1 1

1

(

C MD-02067-8GOS46 Sheet _3____Of_#*4 BFN Unit 2 Pestart rressure Drop Calculation Prepared By_ $ __Date_#/[_/8'

)

For EECW System Pipina Browns Ferry Nuclear Plant Chected By_

__Date_

_ )

AF Vel oc i t y (fps) entering a converging tee at the side of the flow path not taken (pnt).

This parameter is required for converging tees only.

AG Flow loss or gain at a tee or exit (difference in f l ow shown on one row and the row below).

AH Increater loss based on Table 7 of Ref 5.16.

AI Reducer loss based on Table 8 of Ref 5.16.

AJ Ori fi ce loss computed from the data in Table XII.

AK Tee loss computed from equation II or III of Pef 5.21 (see Pe f 5. 2 o f DS-f13. 5.1).

AL Other loss computed from HX data (see Table XIII).

Af1 Friction loss = Col.E x Col.AA x 1/100 ft.

AN Form loss = Col.AB x Col.AC x1/100 + Sum Col.(AH..AL),

ft.

AO Tot al loss = (Col. AM + C::1. AN) which is the contribution of the respective pipe segment to the head loss of the entire fl ow path, ft.

-w-eMm w.-

.m f y gy,- --

l l

)

11D-02067-8G024G Sheet _I3_ _ _ _0 f _ I _"_#

P' FN Unit 2 Restart Dy/tf______Date_Uf/s9

eerture Drop Calcul ation Prepared For EECU System Piping

/u Erowns Ferry Nuclear Pl ant Chec t:ed By___.___Da t e_

_ _/_0_/

'.O Eggulig

.The demonttraticn of wl. ether or not the totnl flow path resistance (based on 40 year pl an t life corrosion) i s su f ficiently low or alternately too high to permit idequat e EECW cooling is found in Table XI.

Table XI includes the following information:

Col A - Description of component.

Col B - Components tetal fIow requirement, gpm Col C - South Header contribution to the components f l ow, gpm Col D - North Header contribution to the components f l ow, gpm Col E - North Header exit tee designated for supply to the component designated in column A.

Col F - Ci-Pump fl ow as obtained from summation of Col D values, ppm Col G - C1-Pump head tu c o n.p u t e d from a curve fit as given in sheet 21 of Pef 5.19 which is based on manufacturers pump data multiplied by the pump derating factor as given in Assumption No.

2.

Pump head therefore equal s:

C1-Pump Head (1.2714)*

=

(425.601.00449058*(Col F).0000064307*(Col F)^2) l n.,

n-

. ~. _ -.

,.-n.-

.-,.n.a-

.._a,

/4 MD-02067-880346 Sheet __L___Di_/ $___

f_

nFN Unit 2 Restart Prersure Drop Calculation ProparedBy'_$___Date_#/[_/#'

For EEClJ System Pipina Drovns Ferry Nuclear F'l an t Cb 'sc i:ed Dy_

_O__Date_8 d2 Col H - Elevation of water surface at pump intale. 529 ft Refer to item 2 of Design Input Data.

Col I - Elevation at EECW discharge as noted in Table XI.

Col J - C-factor for the carbon steel as analyzed for the piping for the component designated in Col A.

Col K - Diameter reduction due to corrosion, in.

Col L - Summation of dynamic losses for the entire flow path with origin at the pump discharge and destination at the over flow basin (or as otherwise indicated in Table XI.),

ft.

Col M - Margin of resistance which indicates the flow path resistance is suf ficiently low (positive margin) or too high (negative margin) to permit the required fl ow to the component designated in Col A.

Margin = Col G + Col H - Col I - Col M Col N-Denotes the Tables in this calculation from which the dynamic losses were summed by adding the appropriate Col AO values from each table as required to compile the losses for the entire flow path, l

.--e:_

. ~ _ _ _.... _ -

- - - +. - -

,-w--

l I

1 i

(

Mn-02067-08034E Sheet _)5_____Of_ joe ____

~5N Unit 2 Pestart Pr<wsure Drop Calculation.

Prepared By_ $ __Date__ 4/

__3 9 I

F :.r CECW System Piping Browns Ferry Nuclear Pl ant Checked By______Date______

t l

l 9.O

$$'OG1!.!21$'03 Table XI shows among the nine component loops analyzed each have signi ficantly positive margins except the U3 SDBP which has a si gni fi c antly negative margin.

Inspec tion of Table IX (U3 SDBR) shows that the responsible contributors toward the excessive loop losses include the following nodes:

Node Pipe Site Pipe Lenqth Head Lucs 121-122 2 in.

40.33 ft.

I19,32 ft.

131-132 2 in.

14.46 ft.

42.92 ft.

132-130 2 in.

125.30 ft.

351.20 ft.

The attached liet of ECN's (Pages 37 and 38 of this calculation) were revie.ed for impact ;in t hi s c al c ul at i on.

The piping segments listed above are carbon steel mater i al and eventually shall be replaced by stainless steel under ECN L-1970.

The de ficiency shown for U3 Shutdown Board Poom Chill >;>rs has been previously identi fi ed and the present r esol ut i or; is addresed in B22'CB 1206 010 (Re f. 5. 33).

.___m.

u

1 110-02067-890246 Sheet _'_0____Of_______

FM Unit 2 Pestart Pressure Drop Calculation Prepared Dy

__Date((f/jj l~o r EECW System Pipino Drowns Ferry Nuclear Pl ant Checked By h__Date_8 M

Punch List It em No 2-2113 i s in regard to Corrective Action Pequi r ed in Section 5 of DFN EEFI No 67-50 addressing concerns 1 through 5 as listed in Pesponse Eection 2.

This c al c ul at i on addressec each concern as follows:

Concern 1:

Pofer to Assumptions (Section 3),

Jus ti fi c at i on of Assumptions (Section 4) and Table XI of this calculation which determine that the North and South Headers are in reasonably even balance in terms of supply piping geometry and f l ow demand and therefore contribute equally to the fl ow required for each component.

Concern 2a: No response required.

Concern 2b: Refer to Tables XI of this calculation which indicatec all components discharge at the respective catch b ' 1ns as shown on drawing 17W300-9 except the Diesel Generator HX which remains vented to atmospheric pressure at the high point in the discharge piping (dwg 47W586-3 ) ac determined in Calculation B90 890310 204 PO (R,f 5.19).

Concern 3:

Fefer to Tabl e XI of thi s calculati on which demonstrates the control room chillers were analyzed.

Concern 4:

Pefer to Table XII of the Calculation which demonstrates the ori fice loss was included.

Concern 5:

Pefer to Design Input Data Item 4 (Section 2.0) of this calculation which speci fies component flow requirements are in accordance with BFN-BTRD-026, Rev 2 and CN No 1 (Ref 5.20).

1 CAOR No.BFP89009 (Clay Pipe Issue) and Punch List Items Nos 2-0068, 2-0080 and 2-0921 require the analyses of additional components included in tnis calculation as shown in Table XI.

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she 7 2? c x ' * ~1 CALC ULATI"" f.UMEER:

"B' Gio(a7 - 2 8 03 H.ThE FOLLCW~!.G ECN& HAVE EEEN FREPARER CATEEM/ 87 jpg.,;E,]h JAggg iVA CONTRAC7 N0.:7v E ga./73,*-r0; A ECN SYSTEM BOUNDS CEECRIPTICN L1970 057 REPLACE ALL a IN. & UNCER CAREON STEEL F:FE WITH STAINLESS STEEL PIPE PCOB3 057 F0157 057 REPLACE SEAL H!AT EXCHANGER DELETE CORE SERAY PUMP MOTCR EEAR*NG CC P02SS 067 PROVME NEW ANCHCRAGE-TO RE.:

BOLT ANCHORS THAT HAVE EEEN IMPROFERLYA INSTALLED P0289 C67 PROVIDE DOCUMENTATION FCR PIPING SYSTEMS SEISHIC ANALYSIS P0350 067 MODIFICATIONS FOR THE LONG TERM TORU3 i

INTEGRITY PROGRAM P0292 067 MODIFICATIONS TO THE CONTROL DRIVE HYCRAU SYSTEM P07C9 C67 ADD THROTTLING VLV UPSTREAM CF EACH DG ENGINE CCOLER AND LOCK OPEN DOWNSTREAM BALANCING VLV P0729 067 EECW DEDICATED RHR$W PUMP DISCHARGE A R RELEASE VALVE POS30 OS7 ELECTRICAL MODIFICATIONS TO COMPLY WITH APPENDIX R REQUIREMENTS PC955 057 J

INSTALL NEW AC EQUIPMENT AND ADD COOLING

(

. P2C42 LINES AS REOUIRED - UNIT 2 057 HANGER MODIFICATIONS PER NRC IE EULLETIN 79-02 AND 79-14 P3020 OS7 FURNISH INSTRUMENTATION FCR NRC IE EVLLET!N 79-013 TEST PROGRAM P5079 057 RELOCATE VALVE 1-VLV-57-C572 TD U.:ETRE AM C.:

VALVE 1-VLV-57-CESO P5302 057 HODIFY FLANGE JOINT CN 4-TCV-57-C052 - UNITS 1&2 F5492 057 ADO DOUELE END SHUTCFF CUICK CONNECT TEST FITTINGS FOR REACTCR WATER LEVEL INSTRUME P5453 067 DELETE VAC PRIMING PIPES DOWNSTREAM CF 3-67-0669, CAP LINE AND LOCK CLOSE 3-67-0559

- UNIT 3

-m.~g a

i j

- = -

"3 Ti FCLLOWING EC5s HAVE EEEN VIEWED FC R CALC. IMPACT CALC

. TION NUMBEil: #s o - Qq op-e l

M6 PREPAdERA W I(

TVA CONTRACT NO.:T\\*-7164A/T D AT E f/e /8 9

_ Ci'ECHER, A6C k

ECN SYSTEM BOUNDS DESCTtIPTION l

P0360 023 P0913 023 P0914 023 P0976 023 P0977 023 P0978 023 P2042 023 P0192 023 P0194 023 P0289 023 P0381 023 P0631 023 P0739 023 P0823 023 P0830 023 P0883 023 P3020 023 P3145 023 P3164 023 PS160 023 P5177 023 C

P5455 023 9

e

/

k 9

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reie testatrWIn e' stu m EE # -

15 5 #

q i

al funciame Euta &mnam h.a Aed s) seressust ess 33 ansant assa:

38. tasenamot Sete Shagg aJa

1. Assy E.5.P. Is. Is * *

31. Amor esta ses

'

r. me coerettee cru a**a-

32. system testen crtterte m e m f

3. Air Fles: trient/ArTgut SK.,,,34,

33. I M C1ese i E - innsame - -vumm 4

M. ASE Code / Class N " - ' P - saa = -

C) CDR.ts:

35. Selenic Catsgery

- - ses Arr 48 g

5. Est Air V e/sep 86"'" M *f*

35. Oesitty Group

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=*

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37. LSCatles IIOS/[] aa 2

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{

2. Tot Capacity. BTLAI LT **** MfE4 4

38. Oldg Column Lise mis.m *

8. Camd nas Wtr Temp 'F 8t as 39.

1 1

=-

i

9. Camd Mie Wtr Temp *F

- o N) tm!T ENIADIBUTAL CSSIT!WI5:

1

10. Camd Wtr Man Flow GFR

'? *

40. Temp V e Mas /Rio na N

11. Wtr Pressere Drop Ft M

41. R.N. 5 Man /Rio AP / As l

12. sw a na ===.am th** - ~ m h.

42. Aude Pressere MaanHe m / m.*

0) MOU5tNE DETAILS:

43. Radiaties Dese Total neds **. 6 e i m*

13. Water Coma Location seo

44. Air Quality- " Ana-I

14. Olscharge Location "Te r 45.

m a a m. m i

15. Mas Discharge Olm. WmL me'e m

.)) YENDOR SUPPLIED DATA:

16. Intake Location

- ma

44. Unit Maa KYA Inget

17. Ras Intake tie. WmL *W* EE*

47. Compr*sser Rated W

{

18. GA Length or Depth

- * ~

44. Fan Rated W

19. 0A Height ae ' -u' = V 'ma.

49.

20. 0A Width T * - r' ~

K) EB Doctp6T CDerTRE.11TA:

21. M w. a.n su re - Saa m w e 2.

50. Gen Reget TYA 5pec f sdLst-m-trti E) LMIT ACCESSORIES:

51. Tech Spec..TVA Spec #.6L4L

22. Filtar/ Type A / ( A M M

52. Motor Spec-TVA 5pec #

n u

23. Air Discharge Nozzle

53. Applic Setsste Criteria n.% oe..*a a.=n 1

24. Air Discharge Cowl

54. Applic QA Attoclueet F

%*

E e er

25. O t = ^* " M ; z t>sur on s'e=e F) ELECTRICAL DATA:

26. Power Supply y/tH/H2 albo d44'/4 tita 3Q MMN 7 h a

27. Thermostat Installed on Unit.gst,

28. Remote Thermostat /Yolts g P ng ye, Q, 29.

Comments: tT a >4 t4

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The bidder bereby guarantees that perfbraanee and cha'racteristics of Y.'

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of conflict.between data furnished below and any other data furnished with

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bid, that furnished below shall govern.

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not a bid meets specifications that omission of any of it could make impossible such decision and cause the bid to be noaresponsive.3 A bidder.

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accepted by TVA if offered by bidder after bid opening. If omission of information renders a bid nonresponsive, such bid will be re,jected. The

' '4' same restrictions apply to errors in data submitted in a bid.

..,s

.g General Overall espacity of each ebiller to cool 410

-sps water from 55 to b5 F

'g r )

with 500 gpm condenser coolin6 water at initial temperature of 90 F under pf, followinC operatin6 conditioned f,d..

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Condensing temperature 111.s degrees F

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Suction temperature ua degrees F P f'

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....i j Overall floor space required 44" wide x 166" long g-Mart =um headroom required 91 13/16" i' ';,',*;).

va p'.Q,

A. " " t prj 00eoressor.

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Rated 'especity 170.9 tons of refrigeration at 35.6 degrees F

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Brake horsepover,199

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Road lose throu6h condenser at 500 gpa, feet 70.4 i;

s Bated capacity with Soo gpa incoming vnter at 90 F, teos 170.9 Yolocity of water in tubes, feet per second '

9.3 Tested for 225 psig -psi water working pressure and 30 poig. psi refrigerant wornin6 pressure.

Chiller Itead loss through water cooler at blO gps, feet 14.0 g)

,.4 Velocity of water in tubes, feet per second 7.4

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~IN Eysporating temperature, degrees F 35.6 Rated capacity 170.9 toes with bio spa of vnter entering at 55 F

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(2) PCI 120-0 -Q UNIT MODEL

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CAPACITY-112. 5__ rONS, nFRiGruNT Q[ R.22 O Omrt R.

NP 135 CONDITIONS:

CHILLER CONDEN5ER rLUtD O % eY votuMe, O % SY WEIGHT H2O H2O FLOW RArg (GPM) ldU

.MU INTERjNG FLLAD TEMP (*F)

DU 95 l

LEAVING FLUID TEMP (*F) 45 105 PRES 5URE DROP (FT. EOR Pr.)

N ll FOUuNG FACTOR

.0005

.001 COMPRESSOR MOTOR FURNISHED sy. M DUNHAM.suSH O OTHER5 MOTOR 150 H P, 3600 RPM, Tyre, KOftN DRjr PROOF (570.1 O OTHet raMr$c, LOSTS ELECTRICAL CHARACTERISTIC 5 i

COMPR t550R Oft PUMP MOTOR tlNE VOLTAGE 460 vf of 60,

460 vf 3y 60,

N H

RAffD LOAD AMP 5 (RLA)

/

3*j LOCK!D ROTOR AMP 3 (LRA)

W5E / DELTA 1105 31.0 CONTROL ORCUTT 113V,18/

60 N,

sTAttrRs ruRNISHED BYs k DUNHAM.lV5H O OTHERsa wiring DGM. f C5--Ir,M 1405(X1309)a&B O wyr DetrA CPtN TRAN5 MON O WYE DELTA CLO5ED IRAN 5 MON kACRO5$.THf.UNE O AUTO rRANSFORut 1

STARTER Options Trans. Mounted On Unit.

2 COMTROL titan 5FoltMER / 3 KVA 2 KVA O AMMrTtt 1 PHA5e 3 phase w/swrtCH O COMBINATION /Di$ CONNECT O ruSED 0 UNFUSED 0 CiRCurr 3RzAxER "DUNHAM. BUSH RE5f tvts TNE RJGHT TO $ ELECT THE START'? MANUFACTURER FOR ANY ST ARI AVAILA8t! ON REOUIST. STAtitR$ MAY BE SUPPUED BY OTHt25 807 MU$7 CONFORM TO DUNH AND MUST BE APPROVED BY THE DUNHAM.8USH INGIN![RjNG DtPT, STANDARD fQUIPMENT

l. DIRECT ExPAH5 ON INN (R. FIN CHILL (R, ASME STAMPED Wi1H FLANGED CONNECTIONS.

7. PLOW $wrfCH SUPPLIED UNMOUNifD FOR FiftD IN5f ALLAt!ON.

2. WATER COOtt0 CLEANABLE CONCEN5ER. ASME $ TAMPED FLANGED8. COMPLrrt wiring wiTH PROvi$lON FO R SAFfrY INffRLOCKS CONNEC110N5.

st1wf!N CONDEN5ER AND CHILLER WAf!R PUMPS, COOUNG

3. COMPRt550R, wf1H COUPUNG.

TOWER FANS AND COMPRESSOR.

4. Ott $EPAllATOR/5 UMP Oil COOLER AND N!RMEDC PUMP WITH

9. MANUALLY ADNSTA4LE LOAD / CURRENT U4mNG CONTROL MOUNf(D AND WlRED Starter.

ID. COMPLETI FACTORY SUPPUED REFRIGlRANI AND Oil CPULAflNG

3. INf tRNAL CAPACITY CONTROL CHARGES.

6. CONTROL CENitR-CONTAINS NEC(5$ARY $AFETY CONTROL $,

II. V18RAtlON P ADS FOR NON.CRMCAL INSTALLAT)ON$,

GAUGt5 AND pitot LIGHT 5 FOR COMPLETELY AUTOMAtlC OPER.

12. FACTORY PfRPORN ANC( T[57 AllON. ADDmONALLY SUPPUID WITH ANil-RfCYCLE DMER AND

13. START.UP SERVICE-F A CTO RY REPREstNTATivt ON LOCAfiON" ELAP$lD DME METER.

Folt TMilf t CON 51CUTivE NORMAL WORfJNG DAYS.

OPTIONAL EQUIPMENT M chitter AND REraictRAtiON INSULAtlON 1 VIBRAt!ON ISOLATOR $

RJ5

$PRING TYPf_

Jg Orwit Reirmic Testinc

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d.'hp FE R FO R.MANC(, DIMINSIONS AND $P!CIFICAtlONS arf CtRMFIED CORRfCf WHEN SIGNED SY AN AufMORil!D IMPLOYE! OF DUNH AM. 8 U ey

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DESCRIPTION OF SCOPE m_m_e.

kEMOVE A Prox!KATELY 8 FEET OF 6 PIPE.

PLUG OR CAP C0t#ECTION TO 12' RCW HEADER.

o ADO A 45' OR 90' ELBOW TO 6" EXISTING DISCHARGE LIFE FROM COtCR BAY CHILL.ERS (WILL PROBABLY RE0VIRE WELOING).

WELDED ARE CARBON STEEL TO CARBON STEEL.

MATING MATERI ALS TO BE Ul/U2 C8 CHILLE,0.C 1

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DESCRIPTION OF SCOPE

= = :_:.

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KATING MATERIALS TO BE WELDED ARE CARBON STEEL TO CARBON STEEL.

(D CB CHILLER.O.C

____I__________________________________._______

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6FN P ~ EEQU SYSTEM (67) PREssMRE~

DROP CALCRLAT/CN PLEA S E ADD THE GoOLING LO A D S ho THRtt lo) THar /s snowra ou ATTACHMENT.L To TH E EECW PRESSLU?E OROP CA L C. MD -92gn-BS G346.

THESE Lopps ARE BEING Appe~D BECAuSE OF

'7HE FoLLowiMG KEAStd:

L 8AD A16.

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&&hl Bechtel Nort ' Amsrican Power Corporation -

ay e,-

Engineers - Constructors 4

1501 Freeman Drive

//2 EI L Q [>

Athens, Alabama 35611 (205)233 5600 August B,1988 Project Engineer Tennessee Valley Authority g

p.4 v " 4,0g...,0

{', f., i Post Office Box 2000

,.p,7,f v.

A10-EDB-BFN

,,,7 Decatur, Alabama 35602 Attention:

T. M. Brothers I

(A3-EDB-BFN)

TVA Contract 72163A Bechtel Job 19106 SODIUM HYPOCHLonITE SYSTEM MODIFICATIONS ECN E-0-P7165 BFT-8 8-16 41 File No. 0130 In order to decouple completion of sodium hypochlorkte system modifications, that will be done on ECN E-0-P7165, from the Unit

2. fuel load schedule, Bechtel has completed a calcul'ation that demonstrates that the EECW System can withstand the loss of water that would be associated 'with a line break in the sodium hypochlorite system.

The sod'um hypochlorite system that is currently installed is temporary and was not designed to withstand earthquake loads.

This temporary system needs to remain in place until the end of this year's chlorination season-which extends beyond the scheduled fuel load date.

The permanent system will be seismically qualified.

The calculation, which is attached, conservat.ively estimates the maxinum flow loss at 56 gpm per infection line.

This could result in a loss of 112 gpm from an EECW pump should both injection lines fail.

Although a flowrate of 112 gpm is only 2.5% of the EECW pump flow, TVA has expressed a concern that this could be a problem because~the pumps are operating with no spare capacity.

The EECW system is common to 'all three units at BFNP and in our opinion should have excess capacity since Units 1 and 3 vill not be in service and Unit 2' will not be operating at peak capacity.

Under these conditions, a break in a sodium hypochlorite line will not be a threat to the -integrity ~of the

~~

~~ ~

EECW system.

The sump pumps in the pump rooms are safety related which will alleviate any concerns about flooding.

These pumps are adequately sized to handle the flow from the hypochlorite line break.

/

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/

m o - ca cc,- sp a n Bechtel North American /d*" SJ V T "a t,," r t h ',",*

Power Corporation

,y 1

BFT-88 1641 Page 2 p C;,.,

,,. v,,.g..

(y - QN'g't j

su-1 Please review the attached calculation and if you agree with its 1

conclusions and the recommendations of this letter, break the schedule cie that requires the permanent sodium hypochlorite syster ';o be installed prior to fuel load.

1 This will allow the temporary system to provide necessary chlorination during the remainder of 1988.

prior to Unit 2 restart.The Bechtel design willethen be implemented Should you desire to discuss this subject further, please advise.

Very truly yours,

h R. E.

allagher Project Engineering Manager Written Response Req'd:

Yes Due Date:

AucJust 15, 1988 REG:DWH:ncb

Attachment:

Calculation MD-Q0050-8828F, Pev.'O - Hyp6 chlorite Injection Pipe Failure C. E. Anderson, w/1 (F43 EDB-BFN) cc:

1 D. S. Freeze, w/o (Trailer 9-BFN)

D. R. Gallien, w/1 (PEB-Al-BFN)

L. W. Holloway, w/1 (PEB-A4-BFM)

J. Kaelin, w/1 (Trailer 5-BFN)

G. R. Mozingo, w/o (F24-EDB-BFN J. L. Sparks, w/1 (PEB-A4-BFN),)

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MD-Q2067-880346 sheet s.f of /e g

( This Sheet Is Intentionally Left Blank)

Prepared By/Clf Date 5/9/89 By((T3CDate5[4[f)

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m :)- Q&o61 yege 1 of 5 t o o 3 h6 ATTACEMENT 3 pu r.s e BTN SSTI ACTION ITEM RESPONSE FORM Sa c p G o r (,

ACTION ITEM NO.67-53_ OBSERVATION NO. EF-SMK-5 FIV 1 RESPONSE REVISION NO.,_1 DATE PREPARED

//- 80 86

._ DATE PROVIDED TO SSTI TEAM

'NOTZS:

l{-

Respense should be provided with 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,.if possible.

8

. v Responsible organization should provide any specific information that la rtquested or any other information that could alleviate the concern.

Each of the folleving items should be specifically addressed if it is determined to be applicable.

1.

Probable root cause as to why the concern exists.

2. ' Extent of concern, and how determined (if bounded, why is it bounded)?

3.

Action necessary to correct recurrence, including date when action vill be implemented.

i 4.

Action necessary to prevent recurrence, including date when action 1

vill be implemented.

5.

Significance of concern and basis of significance.

6.

When 4. concern requires a Condition Adverse to Quality (Attachment 5) per SDSP 3.7) or a Maintenance Request (per SDSP 7.6) the number shell be referenced.

Use additional pages as required to provide a complete response.

1.

Observation (Issue):

(Attached)

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BFN SSFI ACTION ITEM RESPOUSE FORM p,9 c g y,y ACTION ITEM NUMBER 67-53 OBSERVATION NO.

_ BF-SMX-5 2.

Response

This observation primarily addresses. deficiencies associated with Design Calculation HCG WGA 072080 (MEB 840928010) titled "EECW Pressure Drop Calculation,"

and the lack of documented analysis on testing which demonstrates that safety related coc:ponents,will receiva adequate flow during emergency conditions.

were specifically noted:

The following concerns 1) t,ack of Engineering justification for c.nalyzing the selected flowpath.

Ea) The application of the methodology used may be inappropriate for the complex configuration of the EECW System.

2b) t,ack of engineering justification for assuming no pressure losses (travity flow) in the discharge header 3)

Control Room Chillers were not analyzed 4)

Orifice Pressure Drop was not factored into the analysis

~

5) Discrepancy in Diesel Generator Engine Cooler Flow Requirements TVA agrees that the analytical technique used in calculation HCG WGA 0720B0 would be inappropriate in a system that is operated without flow adjustment following installation.

In that case, iterative techniques such as Hardy-Cross or other numerical methods would be needed to determine flowrates delivered to all branch lines.

however, employs flow balancing valves within each heat exchanger

EECW, flowpath.

These valves are throttled dering preoperational and subsequent periodic functional testing to manipulate the flow-distribution.

Therefore, if the design is adequate, testing will assure the proper flow distribution.

The purpose of the EECW pressure drop analysis, therefore, was to demonstrate the capability of the design.

In a y arallel-flow network such as JCW, the pressure drop from the syeteu supply point to its dischar e point during system operation will be.identice.1 regardless of which individual cooler path is taken.

Furthermore, each cooler must receive at least design flow of ter, test adjustment of the balancing valves.

(Otherwise a test deficiency will be identified, and corrective action initiated.)

valve positions are generally not available at the time the pressure The drop design analysis is perfomed; however, this infomation is not needed since proof.of design can be achieved.as described in _the _

- - ~ ~ ~

l following discussion.

~~ ~

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3 3 of 5 BFN SSFI ACTION ITEM RESPOUSE FORM

~ m ACTION ITEM NUKBER 67-53 OBSERVATION NO.

_ BF-SMK-5 2.

Response (Continued) design flow to all users;' the

margin" through each loop cou determined.

(Margin is defined as the available pressure from the pump minus the required pressure to overcome fluid resistances.

would represent the pressure drop across the loop flow balancing This S

valves under the conditions assumed in the analysis.)

margin for all coolers would show a ringe of values; positive to all A tabulation of users would prove sdequacy of the design.

Although the overall pressure drop through each user could be calculated as described above, this would be laborious and time consuming.

If the flowpath having the greatest resistance - and therefore the least margin - could be identified by *nspection or other means, the analysis could be limited to this on.a loop.

margin in that " controlling" loop would then demonstrate the positive capability of the design to provide at least design flowrate to all users.

A variation of this simplified approach was adopted in HCC WCA 0720B0.

described above is a proof of designs it is not intended toIt sh demonstrate operability of the installed system at a particular point in time.

margins - s.no therefore flow deficiencies - to certain loops.In fa word " predict" is used because these type analyses generally assume The end-of-plant-life conditions.

11k11 hood that aging effects may eventually affect systemNegative margins wou I

operability.

evaluate the effectiveness of modifications to Irprove perfomance But regardless of the analytical results, effective demonstration of system, operability must look to test results, either the i

preoperational tests or periodic functional tests', as required by 10CFR$0, Appendix B, Article II.

To support the BFN Unit. 2 restart, the EECW Restart Test, RTP-067 beenperformedtoverifythatregt!redflowstoessentialcomponents

, has, are aphieved.

Calculation MD-Q206,'880368 (B90 881129 200) water level condition. completed which concludes that RTp-067 envelopes the min has been i

.. Flows were verified af ter final valve.,

adjustments and the valve positions documented in EECW System,,.

{

. Operating Instructions, 0-01-67.

per 0-OI-67 Section 3.13. "The i

the EECW system are preset and locked. throttle valves that control tj from full open in accordance with the valve checklist." change

]

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0103m-3 1

e l

J

(

Ly SM cs m

a

~MW Pago 4 of 5 BFN SSFI ACTION ITEM RESPONSE FORM (g s r x 32) i 4 d s' r or G ACTION ITEM NUMBER 67-53

_ OBSERVATION NO.

_ BF-SMK-5 2.

Response (Continued) for concern number 2a (page 2).It is therefore concluded by TVA that no c

.8 Note:

e described in the response to Observation BF-RB-3.the proced i

concerns l'through 5 (except 2a) are recognized as deficiencies and are being addressed in the Design Baseline and Verification Program (DB & Vp).

new calculation generated to determine minimum acceptable s pressures based on component flow requirements.

justification for the loop selected for analysisbeing tracked by D This calculation is for neglecting p? essure loss in the discharge header (concerns 1 and

, and justification 2b).

This calculation will also factor in the control room air conditioning units and the orifice pressure drop (concerns 3 and 4 Diesel Generator Flow requirements. Concern No. 5 is being addressed b will be factored into HCG WGA The results of this ca.1culation 072080 results.

and assessed against RTP-067 3.

Root Cause 4

As discussed in 'section 2 'of this response, the methodology used in the subject EECW pressure drop calculation is typical af TVA's approach to Raw Water System Design.

flows, adjust valves, and balance the system. System testing is used to verify Therefore, the root cause of concern 2a is not applicable.

Concerns I through 5 (except 2a) represent random design errors and/

are the result of poorly documented design bases.

or Design Baseline and Verification program to addre'ss thi e

sue.

4.

Extent o

As neled in section 3 of, this res; ase, the methodology used in'the subject pressure drop calculation nor EECW is typical of TVA approach to Raw Water System Design. Flow balancing and verification is achieved by systen testing.

typical examples of design basis document deficiencies orConcerns 1 through inconsistencies,which have been recognized by TVA.

being addressed for all safety related systems'by the Design Baseli This problem is and, Verification program.

ne

..u.

5.

Corrective Action and Date ~ ~ ~ ~ ~ ~

corrective action for concern 2a is not applicable as discussed in s'ection 2.

The remaining concerns will be factored into a revision to calculation HCG WGA 072080 This work will be completed by 1-31-89,in accordance with DD & V No. 2-2113.

em 0103m-4 1

~~

hN ~

C' MD' OcD b&~') ~ 93 0M i se 5 of 5 BFN SSFI ACTION ITEM RESPONSE FORM G? E F { Q) 53 pgcp ACTION ITEM NUMBER 67-53 BF - '

OBSERVATION NO.

hPM -SMK-5 Ccr ective Action and Date (Continued) 5.

In addition, a new calculation is being prepared to determine the Diesel Cenerator Engine Cooler Flow requirements (Concern 5).

calculation will consider actual temperature changes across theThis diesels and latest vendor data which suggests a higher allowable Jacket water temperature.

i the requirements of the response to observation BF-SFK-2.This calculation is calculation will be completed by 1-31L89.

This new 6.

Preventive Action and Date The Design Baseline and Verification Program has been established for BFN and as a result of this program the design bases will be documented and essential calt.ulations generated.

completed prior to unit 2 restart.

This action will be NEPs 3.1 and 5.2 are presently in documents are performed in a manner which assures a cons quality product.

7.

Significance The Design Baseline and Verification Program is tresently revising' existing calculations or generating new essential calculations.-

design deficiencies are discovered during this process, CAQR's 'will be If initiated and processed in accordance with NEP 9.1.

CORRECTIVE ACTION DUE DATE _ January 31. 1989 PREVENTIVE ACTION DUE DATE _ Unit 2 Restart PREPAR5D BY MMMM b NM DATE N*@ *88 -

SUPERVISOR * -v

/

DATE JA JW. ff-y REVIEWER **

DATE

Signature of supervisor indicates approval of above info I

for schedule, accuracy, and adequacy.

rmation

- signatu're of reviewer indicates agreement with the above information by the SSFI team.

~-

Ok03m-5

)

w--.--r,,,-

O ENCLOSURE 4 SYSTEM FLON DIAGRAMS INDICATING PROPOSED MODIFICATIONS l

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L

)

,7

\\-

1 OVERSIZE DOCUMENT PAGE PULLED SEE APERTURE CARDS NUMBER OF OVERSIZE PAGES FILMED ON APERTURE CARDS l

APERTURE CARD /HARD COPY AVAILABLE FROM QECORDS AND REPORTS MANAGEMENT BRANCH

,

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