Text

Summary of 990222-23 Meeting Between NRC & Industry Representatives at Altran Corp in Boston,Ma to Discuss Industry Initiatives to Address GL 96-06, Waterhammer Issue. with Attendance List & Handouts
	ML20207G313
Person / Time
Issue date:	03/09/1999
From:	Tatum J; NRC (Affiliation Not Assigned)
To:	Marsh L; NRC (Affiliation Not Assigned)
References
	PROJECT-689 GL-96-06, GL-96-6, NUDOCS 9903120047
	Download: ML20207G313 (163)
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{{#Wiki_filter:_ 's jong p k UNITED STATES j NUCLEAR REGULATORY COMMISSION t WASHINGTON, D.C. 20666-0001 Mmh 9, @ MEMORANDUM TO: Ledyard B. Marsh, Chief Plant Systems Branch Division of Systems Safety and Analysis // THROUGH: George T. Hubbard, Jr., Chief )f 'I Balance of Plant Section f f t? M ' h, e-Plant Systems Branch Division of Systems Safety arjd Analysis 6 n h FROM: James E. Tatum Balance of Plant ec on Plant Systems B(an Division of System Safety and Analysis

SUBJECT:

SUMMARY

OF THE FEBRUARY 22-23,1999, MEETING BE~iWEEN THE NRC STAFF AND INDUSTRY REPRESENTATIVES AT ALTRAN CORPORATION IN BOSTON, MASSACHUSETTS TO DISCUSS THE INDUSTRY INITIATIVE TO ADDRESS THE GL 96-06 WATERHAMMER ISSUE George Hubbard and Jim Tatum of DSSA/SPLB, Gary Hammer of DE/EMEB, and Al Serkiz of RES attended a meeting at Altran Corporation in Boston, Massachusetts on February 22 and February 23,1999, to discuss the current status of work being done to adaress the GL 96-06 waterhammer issue. This industry initiative is being sponsored by 12 utilities through the Nuclear Energy Institute (NEl), and the technical work is being coordinated by the Electdc Power Research Institute (EPRI). Waterhammer testing in support of this effort is being performed by Altran Corporation and Fauske and Associates, Inc. (FAI). The meeting was attended by representatives of the licensees who are sponsoring this effort, Altran Corporation, FAl, EPRI, and NEl. Doctor Fred Moody from General Electric, Doctor Benjamin Wylie from the University of Michigan, and Doctor Peter Griffith from the Massachusetts Institute of [fl Technology, who collectively represent thc industry's expert panel for this initiative, were also present at the meeting. A list of the attendees is included as Attachment 1, the meeting l agenda is included as Attachment 2, and meeting handouts are included as Attachment 3. I The purpose of this industry initiative is to develop a Technical Basis Report (TBR) that can be I used by licensees to evaluate the effects of waterhammer in low-pressure fluid systems. It is thought that existing methods (i.e., those provided in NUREG/CR-5220) are too conservative for low-pressure applications, and a less conservative methodology could result in substantial l savings to the industry. The staff met previously with industry representatives on December 10,1998, to discuss the TBR development plan, and provided comments to NEl in a letter dated December 23,1998. During the meeting on February 22 and 23, industry representatives discussed the status of TBR development and addressed previous staff comments. Information that was presented included system design information, existing data on waterhammer events in low-pressure fluid systems, data on waterhammer testing that has been completed by Altran Corporation and FAl, and plans for future testing. The staff also observed waterhammer testing being conducted in the Altran lab. A possible risk-informed 9903120047 990309 Crf% " ~ "W ECIEF M C@Y

1 o Ledyard B. March 2 approach for evaluating waterhammer was discussed, and an uncertainty table, listing the uncertainties described in Regulatory Guide 1.174, was used to identify areas where edditional information may be needed. Both, the risk-informed approach, and the uncertainty table were quite innovative and could prova to be very useful in developing a strategy for addressing waterhammer in low-pressure fluid systems. Thus far, the work that has been completed by the industry on this initiative appears to have been well thought out and orchestrated, and the qualifications and involvement of the three expert panel members instills confidence in the independent review and oversight process. The industry hopes to issue a draft of tho TBR within the next several months, with the final version being issued for NRC review and approval sometime in July,1999. Following the presentations, the staff offered the following comments and suggestions: lt is important that the TBR reflect the same high quality and standard as the work that = has already been completed. In continuing this effort, the industry should update the uncertainty table to include plant-specific considerations, perform additional testing as necessary to address plant-specific system configurations, and develop the TBR so that it is user-friendly and can be readily applied to address plant-specific system configurations. The TBR must be very clear on what the assumptions, limitations, and criteria are for its use, and endorsement by the expert panel is a prerequisite for staff review and approval. The existing condition of the fluid system is an important factor that should also be considered when preparing the TBR. For example, excessive wall thinning or corrosion could pose a problem, and programmatic requirements should be in place to assure that the system is being properly maintained and that valves do not leak where seat tightness is an important consideration. Developing a Phenomena identification and Ranking Table (PIRT), which is a logical = extension of the uncertainty table that has already been completed, could help focus additional research and testing efforts. It may be possible to find a role for PRA to play in the methodology that is being developed. Translating the dynamic pressure response due to waterhammer into system forces can l be complicated and should be addressed in some fashion by the TBR. While loads may l reduce as a result of new analysis methods, the resulting loads on piping and supports should be C. valuated using currently accepted methods and acceptance criteria. The Haddam Neck scenario should be revisited and used as a test case in developing the TBR to assure that any subtleties are well understood, and that results using the TBR methods are appropriate and conservative.

Ledyard B. Marsh 3 The NRC staff will continue to interface with the industry on this effort and provide comments as additional information is made available. The staff's goal is to complete its review of the TBR within approximately two months after it has been submitted for review. The interaction between the NRC staff and industry representatives went extremely well during the two-day meeting, and the staff is very much encouraged by this initiative. pistribution: Mtg. Summary Re GL 96-06 Waterhammer Initiative Hard Coov G SPLB R/F E Centud Pteg g PDR OGC ACRS E-Mail (w/o Attachment 2 and 3) SCollins/RZimmerman BSheron l GHolahan/TCollins JStrosnider/RWessman KManoly JFair CHammer i TMarsh j JHannon 1 SMagruder i l GHubbard JTatum BWetzel ASerkiz DOCUMENT NAME: G:\\SECTIONA\\TATUM\\MTGMIN.WPD SPLB:DSSA/ PGEB:DRPM SPLB:DSSA JTatum V SMagrude@ GTHubbard 3/ 9 /99 / 3/'t /99 3/'[/99 OFFICIAL RECORD COPY i i

l i l4 e Ledyard B. Marsh 3 i ,l. The NRC staff will continue to interface with the industry on this effort and provide { = comments as additional information is made available. The staff's goal is to complete its review of the TBR within approximately two months after it has been submitted for review. -The interaction between the NRC staff and industry representatives went extremely well during the two-day meeting, and the staff is very much encouraged by this initiative. l r i f l 6 ? l i i l l 1 l l r h

Nuclear Energy Institute Project No. 689 i cc:(w/o Attachment 3) i Mr. Ralph Beedle Ms. Lynnette Hendricks, Director Senior Vice President Plant Support and Chief Nuclear Officer Nuclear Energy Institute J Nuclear Energy Institute Suite 400 Suite 400 1776 i Street, NW 1776 i Street, NW Washington, DC 20006-3708 ) Washington, DC 20006-3708 Mr. Alex Marion, Director Mr. Charles B. Brinkman, Director Programs Washington Operations Nuclear Energy institute ABB-Combustion Engineering, Inc. Suite 400 12300 Twinbrook Parkway, Suite 330 1776 l Street, NW Rockville, Maryland 20852 Washington, DC 20006-3708 1 Mr. David Modeen, Director Engineering Nuclear Energy institute [ Suite 400 1776 i Street, NW Washington, DC 20006-3708 Mr. Anthony Pietrangelo, Director Licensing i Nuclear Energy Institute Suite 400 l 1776 i Street, NW Washington, DC 20006-3708 Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Activities Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. Jim Davis, Director Operations . Nuclear Energy Institute Suite 400 1776 l Street, NW Washington, DC 20006-3708 1

ATTACHMENT 1 MEETING PARTICIPANTS Name Affiliation A. Singh Electric Power Research Institute B.Kemp Wisconsin Electric Power Company D. Anderson Northem States Power Company H. Chang New York Power Authority L. Rochino Rochester Gas and Electric Corporation J. Wade Southern Nuclear Operating Company A. Nguyen Southern Nuclear Operating Company D. Riat Consumers Energy T. Webb Wisconsin Public Service Corporation M. Aulik Wisconsin Public Service Corporation D. Ray Southern Nuclear Operating Company B. Hammersley Fauske and Associates, incorporated T. Brown Duke Energy G. Hubbard Nuclear Regulatory Commission G. Hammer Nuclear Regulatory Commission J. Tatum Nuclear Regulatory Commission A. Serkiz Nuclear Regulatory Commission B. Wylie University of Michigan P. Griffith Massachusetts institute of Techno,ogy F. Moody General Electric Corporation B. Henry Fauske and Associates, incorporated A. Ginsberg Consolidated Edison Company K. Cozens Nuclear Energy Institute R. Randels Commonwealth Edison Company ) H. Fish New York Power Authority H. Lee Altran Corporation G. Zyst Altran Corporation M. Zweigle Altran Corporation T. Esselman Altran Corporation V. Wagoner Carolina Power and Light Company l

e ( l Attachm@nt 2 Agenda for the Second Meeting of the Waterhammer Expert Panel First Day,2/22/99 Time Topic Presenter 8:00 AM Introduction and objectives of the project and Expert V. Wagoner Panel. 9:00 AM Describe the fan cooler systems of a " typical" open T. Esselman and closed loop plant. Overview the thermal hydraulic conditions and specific characteristics of the plants that are participating. Results ofsystem characterization 10:00 AM Break 10:15 AM Describe Anticipated Waterhammers T. Esselman Overview the types of waterhammer expected to occur during the course of the LOOP /LOCA scenario. Relate to specific system configurations. 10:45 PM Present Plant Test Data - Describe available plant data. M.

Zweigle, R.

Ilammersley 11:15 AM TBR Plan Addressing GL 96-06 and the Request for T. Esselman Additional Information Describe Plan Describe prioritization performed e Describe linkage between the RAI and planned TBR e Risk-Based Characterization of Events 12:00 Noon Lunch 1:00 PM Discussion Session Expert Panel, All 2:00 PM Column Closure Waterhammer Altran Testing Plan / Implementation Corporation

Status Solution Approach Witness Test 3:00 PM Break 3:15 PM Column Closure Waterhammer Analysis Altran
Test Data Corporation Analysis - RELAP Analysis-ANSYS Additional Work - Plan for Close-Out 5:00 PM Adjourn e

s !g. ' s Agenda for the Second Meeting of the Waterhammer Expert Panel Second Day,2/23/99 Time Topic 8:00 AM Discussion Session Expert Panel, All ) 9:00 AM Study of Free Air in Single Pipe System B. Wylie j 9:30 AM Thermal Layer & Steam Air Content Testing R. Henry Solution Approach Testing Plan e Status 10:00 AM Break 10:15 AM Thennal Layer and Steam Air Content (continued) R. Henry 11:00 AM Condensation Induced Waterhammer T. Esselmkn Solution Approach Testing Plan Status i Plan for Close-Out 12:00 Lunch 1:00 PM Fluid Structure Attenuation / Amplification M. Zweigle l Potential Amplification Potential Attenuation l e Wave Reflection 2:00 PM Integration of Fluid Conditions, Waterhammer, Pulse T. Esselman lead l Propagation, and Structural Response discussion 3:00 PM Discussion and Comments All 3:30 PM Summary / Upcoming Work Plan Review / Meeting A. Singh/V. Schedule Wagoner 4:00 PM Adjourn i I 1

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EPRl/EC/NPG l EPRl/ industry Collaborative Project to Support Resolution of GL 96-06 Waterhammer RAls t Vaughn Wagoner, CP&L Avtar Singh, EPRI Second Waterhammer Expert Panel Meeting 1 Boston, February 22-23,1999 / l SARA / 3 .._.vam l l EPRUECMPG l-Topics Overall project scope and schedule a

Expert Panel scope and activities 1
NRC Interactions SARA 2

ow svam i 0 0

l I semempo - l Objectives of the EPRl/ Industry Collaborative Project i

Prepare a generic Technical Basis Report (TBR) for resolving GL 96-06 waterhammer issues and other similarissues:

- Focus will be on closure of the issues identified in RAls. -- Develop information that can be used by participating utilities to support plant-specific - responses to RAls. mu.. jsARA 5 1 EPRUECMPG l cae=r , Provide:.= w:= m_ t Provide Industry Tg7 M, Approach w to Develop n i a Generic 4 e meandu,y Technical industry Experts 4-Intecess Basis Report $$In".'id - 4 ~ pm

4. -

Recommendations i wac ne*- . 'aD } l Approval ( n, e e

smusc.m Technical Basis Report .1 . Establish Technical Basis for Analysis of Waterhammer Loads and System Response j - Gather Existing Data - Test Condensation induced Waterhnmmer (CIWH) - Test Column Closure Waterhammer (CCWH) ) - Benchmark Analysis Methods 1 I amuscam l NRC Interactions Maintain open communications with NRC: - NRC staff will be kept informed of the status and early results of project activities. - NRC staff will be invited to observe any testing that is performed. = identihcation of technical contacts. - NRC will be invited to meet with the Expert Panel. Positive Feedback from NRC received on the Overall Industry Plan to develop TBR. i i ]

i Description of the Generic Letter 96-06 Issues Generic Letter 96-06 identifies a potential concern due to combined Loss Of Offsite Power (LOOP) and Loss Of Coolant Accident (LOCA) or Main Steam Line Break (MSLB) accidents. The three main issues postulated to occur and requiring evaluation per GL96-06 are as follows: 1.Waterhammer in the fan cooler units (FCUs) 2.Two phase flow limiting accident heat removal by the FCUs

3. Thermal overpressurization ofisolated piping during a LOCA event This effort addresses only the first item - the waterhammer issues.

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Typical Open Loop System Open loop systems are most often found in fresh-water PWRs. i Nsmogr Wreetsare t-toontw Pwyn

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Typicol Open Loop SV Systen l 2

1 i i 1. l Variations i L e Some units have auxiliary coolers placed at higher I elevations in the containment. 4 i l Some SW systems utilize booster pumps to provide { increased pressure. E i Some SW systems feature a loop seal arrangement [ near the FCUs to prevent drainage during a loss of j pump pressure. Other FCUs can fully drain. . Some SW systems have check valves on the inlet sides that prevent the inlet side from draining. { e Some systems feature an outside containment vent / vacuum break that will open when the pressure drops below atmospheric. e The drainage path varies from plant to plant. Horizontal lines as long as 190 feet are present. Some drain constantly in the down direction - others have " loop seals" (past the initial loop seal).

Pipe size varies from 4" to 16" and the schedule varies from 10 to 80.

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l Loop Seal Arrangement Near the FCUs ) i Vater Enters Top of FCU l l 4 u l FCU i Supply / Return Piping summma-1 i 4

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Typical Closed Loop System l e Closed loop-systems can be typically found in salt-water PWRs. l \\ s.* s.~ i r c - w. l4 c -. l4l l4! W Y $,.. 4 s Typical Closed Loop SV Systen 1 e 7 l l l l

Description of the Event e In both the LOCA and MSLB accident scenarios, steam from the ruptured pipe fills the containment and the temperature inside the containment rises. 4 At the same time that the LOCA or MSLB occurs, all power.is assumed to be lost to the Service Water (SW) pumps and fans in the FCUs. Heat is transferred to the water in the FCUs and boiling occurs. As the FCUs are generally at high elevations, voids will form in piping as a result of column separation. The " voids" will be filled with steam coming from the FCUs. As the water drains with steam behind it, the potential is created for condensation induced waterhammer. 8

[-J' I i L l: l Containment Temperature Profile l l l 1 AUU ^ 2co. u. m, u r / 740 o na 220-u ( 3 k. 200 / o l-180 / ~~ s e, 8 _ { 160 -[ h . c., \\ l 140-T p_. 1 l 120 - ~ 1-I ' " "' ' tutir: Luum Luum. i i n mi iiu 10 id' 5 10 10 10 10 10 0 Time (s) l Containment Temgierneure somi, rei,,,,erni.,....... g : 1 1 9 l l

i I i i Fan Cooler Designs' l (Typical) i 4 l s 'Y o U d 7 ~ f 6 v [ ,ge I fESEs i R L T 0 30 10

Fan Cooler Designs (Typical) Containment Cooler Configuration 4 ~ g fI- \\

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i i Power Restoration i i i i i l

Power is restored in approximately 30 seconds (25 to 36 seconds).

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The SW pumps restart and the voided piping will begin to be refilled.

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The water column will be accelerated by the j

pump to a flow rate based on the hydraulic l losses in each flow path. 1 l

Column closure waterhammer events will

) occur in any voided lines as the voids j collapse. l l i 4 1 13 1

Safety Functions o Provide post-accident heat removal to help j cool and depressurize the containment.

Provide a containment boundary.

. The Service Water / Component Cooling Water System provides cooling to other safety related components. A non-safety related function is to provide containment temperature control during normal operation. 14 a

I Sequence of Events (largely applied to an open loop system) e When power is lost, the LOCA starts and the pumps and fans stop.

The pumps coast-down in approximately 5 seconds e The fans coast down in a longer time dependent on the fan design.

1 e When the water stops flowing, the tubes heat up, and the pressure drops, boiling begins in the tubes. . The water will start to " drain" due to the elevation change and steam will fill the pipe behind the water. Horizontal lines will become uncovered and empty during the draining process. L e The diesels will start and the service water pumps will be sequenced in and started. The water will flow into the fan cooler and " extinguish" the boiling. The water will then travel into the discharge side of the fan cooler and eventually catch-up to the other end of the column. 15

i Time Line 4 0 sec LOOP and LOCA occur simultaneously. 5 see SW Pumps have coasted down. j Voiding in high elevation piping has j started. l Boiling has started. l 10 sec Containment temperature has peaked for LOCA case { 20 sec Horizontallines are reached where { condensation induced waterhammer may occur [ 25 sec Fans may have fmally coasted down. 1 30 see Pumps restart. 37 sec Column closure waterhammer occurs. i 16

L [ i l l Waterhammers in CFC System: Geometry Considerations Two types of waterhammers may occur: Condensation Induced - during draining or ~ some refills i Column Closure - during refill I t l

6 Condensation Induced Waterhammer (CIWH) can occur in piping geometries that can produce a hot steam / cold water interface that can trap a steam bubble. Hot Steon Entering 7 Steon Propelling Stug q p g ollpose Pipe L > 24D ,/ m-

l t l Condensation Induced Waterhammer (CIWH) Horizontal Pipe - long and draining slowly - length typically > 24 times the diameter (ID) j - drain or refill velocity slow enough to produce stratified flow - Horizontal runs downstream of flow restrictions which could cause t stratified flow during refill: 1 orifices ficw control valves } t high pressure loss in-line components j

Vertical Pipe - draining up

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_4 Column Closure Waterhammer (CCWH) l i CCWH will occur when refilling water closes a steam void and impacts either the remaining water in the system or hard i points such as valves or orifices. I I

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q 1 Column Closure Waterhammer (CCWH) j i Two primary factors influence CCWH ) magmtude: i - Velocity - Characteristic ofimpact surface (voids terminating in a valve or other hard impact surface potentially increase the waterhammer magnitude by a factor of 2). l L

Geometry Considerations for CCWH:

Potentially voided dead ends:

= Branch lines in voided region. i = Closed branch valves

In line restrictions:

= Valves = Orifices

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I e i Overall System Changes Consider the following relative to CCWH Pump restart: l Multiple pumps, higher refill velocity, larger CCWH. - Fewer pumps, lower Froude number, potential CIWH. Valve position for supply side: More resistance, lower refill velocity, smaller CCWH. a Valve position for return side: More resistance, lower outlet j velocity, higher dV, larger CCWH (Unless the flow is reversed due to other paths) 1 l E

Nl alta l i ACTUAL PLANT C"WH EXPERIENCE 9 PLANTS: "A" THROL GH "I" 6 OF 9 HAVE RECORDED PRESSERE t DATA i I

Plant "A" LOOP Test i Q m. TypcalCmrt Cooler EL 1988" Simplified Configuration 2

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r t Plant "A" LOOP Test bent threaded rod on sway strut snubber clamp rotation insulation damage contact between support & concrete wall 4

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e Plant "B" LOOP Test .a [ Test 3 Fressute Spike tJpen SW Sump Restatt/ Column CItatare 130.. . yh ~ 11G_ f. '1002f 90d l \\ { 50 - i j s io : 'L m 20 10 - NNst kd**N N W M sNS Nd5 fN 'S

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~ Plant "C" Column Closure Test l Peak pressure of 193 psig with vlv 102 throttled to 35% open No waterhammer of significance with valve 102 throttled to 20% open j No waterhammer with air vent modification installed 13

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5 b k Plant "D" LOOP Test ~550 psig peak pressure pulse measured. ~1/2" pipe deflections noted during test. i i No observed damage following any test. 1 1 i t 18 l

9 6 i Plant "E" LOOP Test i EL 87* I i [ t Vacuum 3 breaker t CFC (Typ o? 5) M i other beds i Y t Simplified Configuration l9 i

i I I Waterhammer During Test f 6 Plant "E" LOOP LOCATION OF '\\ '/ COLUM1 CLOSl!E Test j b i 1 / N .h h$YM.Y00tER k y ("77s ed d k 1 \\ .g. ["l'e.seen I } t CPEN GATE VALVL I - ~ ~.. i e;

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Plant "E" LOOP Test 6, sitc er2 Test #1 --ni2cm2 a'>ca' $= I I

U I

l P = volts X (1000 psi / 5 volt) / (3.9) 2: p ~ where (3.9)= amplification 22 s k 1-nsh; N l &l -~~' -R w 3: e -2 9.00e-04 1.00e+0S t.10e,05 12Ce4 1.30e+05 1.40e+Ct Rcw Numbers Time = Row Number X (sec / 4000 Row Numbers) 21 ..m. = ____m_ _ _ _ _ _ _ _ _ _ _ _ _, _ _

a Plant "E" LOOP Test 1 Test #1 4 1 S110-PT21 8 *i P = volts X (1000 psi / 5 volt)/(3.9) 6.48 where (3.9)= amplification 69 g- => P = 6.48(1000/5)/3.9 = ~330 psi 0 Si o 4i 34 i 2 1j i l ',,g ( o i-- t i-r - ...,r' \\.10 sit 0 103f20 - 105230 1 cst 40 133180 103190 1082CD i ) n 22

i Plant "E" LOOP Test 6 Test #2 S11C-PT2 R12C-PT1 ~'- R120#T2 S11C-PT1 2-m lk. l ' q 'D 'i O O -2 1.89 +05 1.9e+C5 2.Cs+05

2. 5 0$

22e+C5 2.3e+0! t 23

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/ -a = 9 \\. W ed 4 ^ -2 I 219C"O 212%CC 111:50 219504 230ccu 24

5 Plant "E" LOOP Test 1 i No damage observed. ] ~330 psi pressure pulse l Pressure communicated through CFC 25 [

) i t Plant "F" LOOP Test EL 87' l v ? m CFC (Typof 5) M <ea m i r B. O Simplified Configuration j 26 i i

Plant "F" LOOP Test .me.-.,e*- %PPW"N.bea'* d

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emur m-sees.m DATA COMPARISON 3000 mw g - 2500-i - ~. = i \\\\ \\ t ---i --- 2000-1 1

o. 3 50g.

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t+i-t e 0

60 120 180 240 Time (5 sec increments) "F" "E" test 1 "E" test 2 "E" test 3 ' 27 1 i Y m m ,e

e.4 ..eA - = F i I j CO 1 (N N... LE l o n -j I I' 0 [' 4 d [ c-M U~W y Q C tr) g u.<vmi iwe.. i q) 9 $c H E \\,. $8y = t f i ate a s >:= .co .5 O 4 A-4>-4 i O f' a ne a n g 7 i --D W ^ 4 w. _., 3 S,, GR ls es a N // f 5 a G.# C / 9 N= t i + CY &+ / E F e u-eg M B 4: v. [- a a 0 W 2 m g (LS. ' 91'.il Ffi{y 9 .j l p}6-y L,. v .Q C: A I h '414 g -. ey o 26 1 1 I~ l

t Plant "F" LOOP Test l c.o f I A320-PT2 f Sitt-PT! l S11C-PT3 am-n: I c.<- P = (.4.15) volts ( 1000 psi / 5 volts) i P = 50 psi i I i l I l -; 2 g ig g g g g g g g l - i a

i

' i a 14C03 32000 (E003 64000 t00CC SECCC 1120C0 12E300 1440C0,- 25&cCC .1750CC j e Row Kurbers (43cc Reve = 1,0 reet 29 1 [

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Plant "F" LOOP Test L <50 psi pressure pulse i similar to Plant "E" i t no damage e 32 1

i Plant "G" Startup Testing Experience Column Closure Waterhammer j during startup testing in CFC supply lines. i t - Pump restart time delay set longer and waterhammer avoided. l A snubber was damaged. 33

Plant "H" Column Closure Column closure waterhammers experienced j in lines feeding pump coolers. Noise heard and pressure spikes detected. No damage. Vacuum breakers installed and waterhammers averted. u O

A Plant "I" LOOP Testing i Column Closure Waterhammers Experienced duringLOOP Testing. Damaged paddle at clamp for strut. i' t Three other adjacent supports moved on e i P Pe-i i 35

Plant CCWH Experience Summary PLANT MEASURED PRESSURE NUMBER OF l PRESSURE BOUNDARY DAMAGED DAMAGE? SUPPORTS A 205 NO 1 i I B 80 NO O C 193 NO O D 550 NO 0 E 330 NO O F 50 NO O G N/A NO 1 H N/A NO O I N/A NO 1 36 l (

PLANT TEST DATA PLANT: SUMMER (PWR) SYSTEM: REACTOR BUILDING COOLING (open loop; fresh water) TEST: COLD (75 F) TRANSIENT SW BOOSTER PUMP START (MOVATS EQUIPMENT USED TO RECORD PRESSURE DURING SWBP START AND STOP) CONFIGURATION: RBCUs ARE ELEVATED (15 FT) ABOVE SERVICE WATER POND; COOLING WATER FLOW SUPPLIED BY SW BOOSTER PUMP. WHEN PUMP IS STOPPED, COLUMN SEPARATION OCCURS IN RBCU DISCHARGE LINE DUE TO DRAIN DOWN OBSERVED PRESSURE: TRAIN A MAX PRESSURE: 200 psig TRAIN B MAX PRESSURE: 170 psig OBSERVED CONSEQUENCES: WALKDOWN FOUND NO DAMAGE TO PIPES, COMPONENTS OR ANCHORAGE (BOLTS AND BASEPLATES) FEBRUARY 22,1999 (BOSTON)

i l l Plan for EPRI Waterhammer Testing, Analysis, and Preparation of the TBR Scope of Work The following scope of work will be performed to assist the development of the utility Technical Basis Report (TBR). I The intent of the TBR is to respond to the issues raised by the NRC in the Generic Letter 96-06 Request for Additional Information (RAI) A table outlining the issues in the RAI and the corresponding TBR tasks that will respond to each of the RAI issues is provided in Attachment A. Task 1: Preparation of the Introdudorv Sections to the TBR Task 1.1: Write the Introduction to the TBR. Task 1.2: Write the System Descriptions for the TBR. All participating utilities will be contacted to assure that the system description in the TBR covers their particular configuration. The variations that can occur on a plant-to-plant basis will be described so that all participating utilities are covered. Task 1.3: Write the TBR section on the Description of the Postulated Event. Participating utilities will be contacted to assure that it covers their specific events. The low probability of the events will be described vdth details of PRA applicability to be discussed later in the TBR. Guidance for performance of the single active failure /FMEA analysis will be included. Deliverable: Completed Introductory sections to the TBR. Task 2: Plant Experience with Waterhammers Task 2.1: Summarize data obtained from plants over the last several years and any new data that will be collected. Data collection will be done so that calculations may be performed following the completion of the column closure tasks (Task 6) for comparison to the plant test results. Attenuation and duration of the waterhammer events will be characterized Participating utilities and other utilities will be contacted to assure that all available information is acquired. Test data and general conclusions from l the tests will be provided. Applicability of the data will be described. Deliverable: Completed Plant Experience section of the TBR providing correlation between plant experience and other sections of the TBR. l 1 l l l

I 1 Ta* 3: Waterhammar Occurrerce Task 3.1: Defme the waterhammers that'.need to be considered and prepare a ( checklist of configurations that may provide susceptibility. This checklist .will be used by individual plants for comparison to their system. This L checklist.will include specific system geometry issues such as column separation potential, horizontal runs, loop seals, dead legs, orifices, and l throttled valves. l Task 3.2: Prepare a TBR section describing the events including coast-down'of the ' pumps and the fans, boiling, pressurization of the piping, draining of the r.iping (open loop systems only), and eventual restart of the pumps. The - y hydiaulic events that 'may occur in each phase will be described. The { potential for waterhammer occurrence will be described. The specific plant i conditions that will need to be present for any of the described l-waterb..as will be described. l Deliverable: Completed Waterrem.cr Occurrence section of the TBR providing a full description of the waterhammers anticipated and a checklist for plants to L use to determine that they are enveloped by the water'un..as described in the TBR. T=4 4: Condaamion Tadaead Waterharma l The Task 4 tasks will evaluate the waterhammer that may occur during the draining process Task 4.1: Summarize testing and analytical work that is applicable to the draining Condensation Induced Waterisw.er configurations being evaluated. Describe proper use of the knowledge base and pitfalls in interpreting the data. Task 4.2: Develop a closed form analysis methodology to define the behavior of the flukt system in horizontal pipe. Professor Peter Griffith will be consulted on this task. This methodology will specify' critical input parameters and an analytical approach to allow plant specific determinations of Condensation Induced Waterts.roer. susceptibility. Containment Fan Cooler perfonnance, draining flow rates, design water temperatures, and piping configurations are probable parameters that a utility will need to define in order to apply the closed form solution. This part of the TBR will provide a means of calculating Condensation Induced Waterhammer susceptibility. F Thermal inertia effects of water, piping, and insulation will be addressed i The closed fonn solution will be finahzed following completion of the waterisw.er testing described in Tasks 4.3 and 4.4 to ensure the method corresponds with actual experience. 2 l-

l l t i Task 4.3: Perform testing to define the draining Condensation Induced Waterhammer t magnitude and duration. The behavior of the free surface and the support reaction loads will also be charactedzed This testing will benchmark the closed form scrwnh g calculation to determine susceptibility to condensation induced waterhammers and be used to confirm previous tests. Typical configurations will be simulated. The testing will simulate containment fan caoler (CFC) conditions " eloding steaming rates, draining m rates, pressures, and temperatures. The testing is planned to be performed using 4" piping. Ranges of conditions that result in CIWH will be defined Waterh.n.mer pressure pulse characteristics will be recorded using high frequency pressure transducers. Strain gages will be fitted to the support structure. Surface mounted temperature gages will be used to monitor subcooling margins. Measurements will be recorded on a PC for' data reduction and presentation purposes. Details of this testing are provided in Attachment B. l Task 4.4: Perform additional testing to further demonstrate the. effects of the thermal layers and steam air contents on the===dendes of condensation induced waterhammers This testing would supplement that " system testing" descdbed in Task 4.3 and provide additional insight for beschineri6g the j closed form solution described in Task 4.2. Details of this testing are provided in At**ehment C. Task 4.5: A technical methodology and basis for calculation of potential condensation induced waterhen-r.ers during the system refill will be developed and presented. The details of the methodology will depend upon the Froude number associated with the closing. This information will be obtained from each utility during the system characterization phase of the project (Task 1). Task 4.6: Prepare the section of the TBR describing the condensation induced waterhammer Methods to calculate the magnitude of this waterhammer and the bases for the calculation of the pressure magnitude will be provided. All the information necessary in order to acceptably calculate the magnitude and duration of the waterhammer will be provided. Deliverable: Completed Condensation Induced Waterhammer section of the TBR l providing methods for calculation and correlation to test data. This will include the definition of why the tests and analyses were selected and why l they are adequate for closeout. 1 2 1 3 E

~ b e 4 Task 5: Extranolation of Test R-Its to Larne Pines Task 5.1: Develop a basis for extending the results to piping sizes up to 12". Much j of the testing in the industry has been performed on pipe of diameters 2" or smaller. A part of this task will be to compare the Task 4 testing with the j Fauske & Associates testing and to reconcile / explain any differences to ~ j ensure acceptability of the scaling approach. i i Deliverable: Provide a basis in a TBR section for the use of results from 2" piping tests j (or less) to larger piping up to 12"in diameter. Task 6: Column Closure Waterhan = The Task 6 tasks will evaluate the waterhammer that will occur following pump restart i Task 6.1: Gather data and analyses previously developed for Column Closure Waterhammer following pump restart Specifically, column closure wateriwrerier testing previously performed by Altran will be provided. Testing performed by other labs will be described and applicability of results discussed. Task 6.2: Perform additional testing by performing relatively minor modifica: ions to Altran's current test configuration. _ The revised configuration will provide improved scaling capability to actual void sizes. A. larger void than previously tested will be created to evaluate the refilling behavior. In addition, the length of the accelerating water column will be increased to provide additionalinsight regarding the pressure pulse characteristics. The testing will allow wateriwinner correlations to b' developed relative to ~ e closure velocities, pipe lengths, steam pressures, and air content. Details of this testing are provided in Attachment D. Task 6.3: Prepare the section of the TBR describing how to predict the column closure waterhammer magnitude and pulse characteristics. The bases for the calculation will be provided. Comparisons between RELAP and/or Method of Characteristics predictions and test data'will be provided. Methods to minimize differences between predictions and test results will be provided. For open loop plants with " normal" column separation, it should be shown in the TBR that the waterhammer will not be more severe with LOCA than for a LOOP test without LOCA. The methods will also be used to calculate expected waterhanur pressures for the plants that have performed in-plant tests. These calculated pressures will be compared to the pressure measured. Deliverable: Completed Column Closure Wateriwinner section of the TBR providing methods for calculation and correlation to test data. 4

Task 7: Pressure Pulse Propanation Task 7.1: Perform analyses for piping systems typical of the participating plants to show when amplification from fluid-stmeture _ interaction should be considered. The application of the methodology developed by Wiggert will be used on piping systems typical of those participating plants and the extent of the amplification will be calculated. Task 7.2: Define methodology to be used to attenuate the pressure wave as the wave travels through the piping. The AP between each end of a pipe segment will provide a pipe segment load. For short duration pulses, the effects of viscous attenuation will be described. For all pipe mns and pulse durations, the effects of piping / restraint stiffnesses will be described. A detailed analytical approach will be laid out that will allow a plant to determine attenuation that may be credited when tracking a pulse through a system. 1 Task 7.3: Define the range of sonic velocities that should be used for transmitting the pressure pulse through the piping The theoretical sonic velocity calculation methods will be described. The theoretical approach will be compared with testing results to allow uncertainty and margin evaluations (sonic velocity can change dramatically for differing void ratios). Task 7.4: Prepare the section of the TBR describing the propagation of the pressure pulse in the piping system. This will summarize integration of sonic velocity, pressure attenuation, and fluid-structure interaction. Techniques for tracking the pressure pulse and resulting segment loads will be provided. Deliverable: Completed section of the TBR providing methods for transmitting a pressure wave through the piping. Amplification and attenuation through the piping will be described. Task 8: Ounlification of Supoorts and Comnonents Task 8.1: Characterize the methods utihzed in the industry today for determination of reaction loads in supports. Analytical methods such as the use of actual stiffnesses and attenuation will be described. Demonstrate the margm between those loads and the loads determined from the testing. Define the stress criteria that are typically used and the margin in the stress criteria. Development of new and more realistic methods of analysis is not proposed. Task 8.2: Prepare a TBR section that discusses the load determination and provide a statement of margin between those loads and the loads determined by test. 5 L

l Task 8.3: Prepare a TBR section describing the quali6 cation of piping stresses, fan l cooler tubes, and equipment nozzles. A description of appropriate load combinations will be provided. I l Deliverable: Completed section of the TBR discussing the conservatisms of the cla:sical l methods of analysis with comparison to test data. General methods that i can be used to qualify piping, supports, and components will be described. { Task 9: AMitional Teh Task 9.1: Define the applicability of the work included in this TBR to other weted-e iers and any limitations in the applicability will be described. Examples include Fire Prctection system column closure wateda...+ events, Condensate system CIWH events, and RHR system column closure events. The scope of this effon will be to summarize lessons learned from the test program, expert panel, and investigators. Task 9.2: Define both the censinties and the uncenainties associated with the approaches being recommended. Uncenainty discussions will address issues such as test instrumentation, data reduction, ~ corroboration of independent lab testing, scahng factors, plant parameter affects such as steaming and drainage rates, actual stiffnesses, water properties, scatter in the data, and others. Quantitative uncertainties will be defined and/or calculated to the extent practical. Appropriate methods for accounting for uncertainties wn! be described. A discussion'of the use of" engineering judgment"will be included. ' Task 9.3: Prepare a section of the TBR that uses PRA analyses to demonstrate the low probabilities of occurrence of the loads calculated. A typical configuration will be used to provide additional assurance as to the low risk associated with the methods being recommended. Task 9.4: Prepare a TBR section of Conclusions. Deliverable: The work that will be prepared in these tasks wili be integrated into sections or subsections of the TBR. I Deliverable The overall deliverable from this project will be an integrated Technical Basis Report j suitable for submittal to the NRC for review. All technical inputs provided to EPRI will . be integrated into the report. Schedule l An overall project schedule is provided in Attachment E. l 6

Attachment A i .RAI Issue Resolution Request for Additional Technical Basis Repott Infonnation if a==el==lalagy edur than that e The TBR will e= ;.Lddj address this request. dismised in NUREGER-5220, e De TBR will prende==*kade to predict n=h== clamme and " Diagnosis of t'a=rh===*=a= 1=d==rt <=rl===emn mduced wakrka=== prcasures and support iondings. He Waserktanner", was used in evaluatmg methods will be de==r=mrated to be appropnately consavative with the en=rea of wstorhauuner, describe this supportag test data. h test data will reDect actual plant waterh====s ahernate mesbadologyin drtail.. Also, (TBR Task 2) and laboratory waterh====rs (IBR Tasks 4,5, and 6). l exP am why this mesbodologyis apphoeble and giws oneservative resuks (typecally accomplished through nearaus lP antM =adal=g testsag, and analysis). Id 'y any conspuser codes that were e & TBR vl not i i ;;,c specdic computer codes. mood in 1% waksh===wr and two-phase e h TBR method and data will provide a means for a specdic plant to Gow analyses and desenbe the==*had= h-ch==rk particular aspects of the codes used. For example, pressure used to h==ah==* the codes for the pulse propagation anods to be appropnately parut=eral TBR secteam 7 will specdic land =g r=d*== mvolved. provide a method and data for' Cling codes forpressure pulse P'8Pagation. . In general, the TBR is intended to serve as a==== of M " N the i codes and methods that a =~ ~6 utility==~i Desmibe andj ; ", all=====penans and e Fluid strodure interschon will be addressed under UR Task 7.1 and input parameters (Wind =g those used in 7.2. j any computer codes) anch as . r'=h% w21 be addresand undu TBR Task 4 & 6 wbme==whade for , "=c- = due to fluid structure psodicting column closure and anad==m==. mdmond waterh===s will be noteractsca,==hir==g speed ofsound, provided. force r=l=*===, and meek sians, and e Speed of sound will be addressed under 1BR Task 73 and 7.4. explan why thevalmas selected give e Force reductions will be addre==ad under TBR Taa 7.2. conservatiwreamks. Alsoprovide e Mesh sizes will not be specifically addressed under the TBR since the i=8'E=a= for a==n=g any crects tha'. TBR will not prescrAie codes. The mask size can bejudged to be j may be relevant to the analysis (e.g. fluid acceptable if the results from the code correlate well with the IBR. mructure intsraction, flow indnood e Jostdication for appropnate connevatuans will be addressed in the TBR vibraison, and oromon). for the specific valueshnathods being m=andarl la addstace, TBR Tasks 9.2 and 93 will provide further r==rrvatismjustifications na===tremg uncertanties and risk =-s= . Justification will be provided for onuttag cEacts such as flow induced vibrataan and a:npli&==== due to fluid nructure interaction under TBR Task 7.1. F>osion is not a waterh===wr issac and will not be addressed by abe TBR.

RAIIssue Resolution (continned) Proddc a dotaded A--dption of the - e Cnudence for defining " worst case" evcats will be provided under TBR l " worst case" scenarios for wu --'-- Task 13 where susceptible configurahams and FMEA will be described. and two-phase fbw, tal.ing into More speedic gnwi==ne will be provided under TBR Task 3 to alkyw a na===In-shoo the courjlete range of event plant to deGne particular sections and configur=hana of systems that may r-ra" = sysicanoosdiguratAoAs,and be Oceducrve to the postulated watgrhanumw$ paranwers. Forext.mpic,all e ne awehade for calenlahng tbc waterkanm-s and pressure pulse waterha===nr typei and watar alug charactenstics will describe the effects of pressure, ^, --.., flow ^acasanos should be considered, as well as rases, and wiid fractions under TBR Tasks 4,5,6, and 7. , -_- -.s, prassures, flow rates, load e Imad combensha== will be addressed under "IBR Task 8 and 93. combinstions, md possahal nampan=t . pnammhat ansnpnn=t failures will be addressed under TBR Task 1.3 and fadures Ad6ticed ev==planincande; 3. .the esects ofvoid fraceca on flow balance aM hest transfar e steam for==ha=4ransport will only be addressed as it relates so the - the coerequences of steam formahan, occurrence of waterhammers under TBR Tasks 4 & 6 but not as it relaks to two phase flow i ' 9 <-- transport and =~===tasia= . cavisAion, r=a==ae and fangue cKects

Fama==ne will be addressed under TBR Task 7.

e Fatigue effects will be addressed under TBR Task 8. ~" " - 28 e Cavitaboe and eroman will not be addressed under the TBR as they are nan==lared two-phase flow piping wear issues. Emhrm that the analyses==nhutad a e Omdance for FMEA will be provided under TBR Task 13. (.corplete failure modes and effects analysis (FMEA) for all na-pa==*= or > cxplain why a casuplete and fully dar=== sad FMEA was not perfonned. Fvf'iandj 4allusesof "cosmeenngjeterun=t". e ne IBR approach is tojustify assumpeans and "engmeenng judgarnant" with test data (TBR Tasks 2,4, and 6), seestmty comedershoes when developing methods, uncertamty eval==ha== (TBR Task 9.2), and risk mamanarnansa (TBR Task 93).

A plant will be able to compare their uses of"enemaarmgjwlemaant"in previous evaluations agamat the TBR =wehada/nsults andjustify the cas.nervatuun of their

='-- Desermine the== r, , in the e Uncertanty (and certamty) is addressed undar TBR Task 9.2. watash===ane and twar Aase flow analyses,explam how it was ' and how it was accounsed for to assure conservaarve resmits. !bdie a simplified diagnun of the affe.1cui syidan,shawag major e The TBR wi;l pnmde sianpli6ed de==hne of typical syssans repe===nad by the plants involved under TBR Task 1.2. Dotaded system ~==pa-a=*= adive onapa==es relatrve diagrams for the spoosfic plaats are not unehm the scope of the TBR and elevahoes, hogths of piping runs, and the will have to be supplied by the particolar plants iar=e-= orany on6aes and fiow restruzions.

l l Attachment B Condensation Induced Waterhammer Testing Preliminary designs for the Condensation Induced Waterhammer Testing are shown below in . Figures 1 & 2. The instmments and other devices are designated as follows: PT - inessure transducer, TE - thermocouple, FE - flow element, LG - level gage, and V - valve. i i @g @ 'S V-1 ic usmi-, % 49 L ii ii T an,e@ @.s e,y,g_P'@ -l s Prelhninary ~15 a AR vabes met shown. Ah=1 bustrimmenhdiom EspecteL h Instriumenteden met shswn: -receberlevelgauge V-3 X l - strain gauges vacu l -otherpressure transducers tank -beDerlevelgange l Mgure 1 Loop Seal Downstream of Hori/ ental Run \\ J

8"@4 tW-M 4 H in u @ ts. v.,@ f nosise tein,e@ @.. q u Preliminary -15 a AH vabes met shown. Addideaallastnamentaden Fayectet Instr====hel== met sherm: .seceberlevelgauge V.3 K .stmla gassee -ethorpressure tremedecem tank .beDerlevelgange Figure 2 Straight Run with No Leop Seal Overall Test Description i l Testing will be performed for at least two different steam pressures. Once the pressures are selected, the steam supply will have to be adequate to maintain the selected steam pressure. At each steam pressure, testing will be performed with the following loop seal configurations: l (1) No loop seal (2) Loop seal downstream of horizontal run (3) Loop seal upstream of horizontal run or initial hot water upstream of V-2.

For each pressure / loop seal combination, testing will be performed for at least three Froude numbers. The drainage rates will determine the Froude number and these will be scaled from typical drainage rates from the participating plants.

L The number of runs made at each Froude number / pressure / loop seal combm' ation and the L specific combination of variables will be determined during testing. It is anticipated that at j least 3 runs will be performed for each combination. The following measurements are intended to be taken/ monitored.- Dissolved oxygen content Water drainage rates Total void fraction in horizontal run Waterhammer pressure pulse characteristics Support loads Water temperature gradients . Steam pressure and temperature Steam flow rates Steam condensation on piping upstream of the horizontal run will be aia:aihM by preheating and insulating the piping in the vertical riser. Steam condensation rates have the potential to challenge the steam generation capabihty of the primary boiler. An auxiliary boiler will be made available if the test indicates that condensation rates are exceeding generation capabilities. This will allow more accurate simulation of postulated CFC conditions where generation rates will typically exceed condensation rates. The pressure in the steam space will be monitored to demonstrate whether the " generation rate"is keeping up with the condensation rate. Detailed layout of the piping is required. A vacuum tank or sufficient elevation changes will be provided to accurately simulate the low steam pressures postulated in the CFCs and associated piping. The length of the horizontal run will be approximately 20 feet to ensure an L/D ratio of at least 48 is simulated. Various IJD ratios will be considered if seen to be important. Water will be sampled after nmning a test and the free air content will be quantified. This sampling will be performed at least once for each test configuration. These results will allow definition of typical free air content in the water for column closure waterhammer evaluations. The supports on the piping system will be varied. A " rigid" support system will be developed and utilized for one series of tests and a support system typical of nuclear plant systems will be utilized for a second series of tests. Test Procedure The test rig will be constructed and instrumented. Shakedown tests will be performed in order to verify that all features are working accurately. An individual test will proceed in accordance with the following steps:

1. Close V-1, open V-2 and V-3. Fill horizontal line with water and measure the oxygen level.

2. Close V-2, V-3, and V-4. Open V-1. Build a steam pressure in the boiler and heat the l

vertical riser upstream of the horizontal run. Drain condensate that will develop in the riser by opening V-4. Blow steam through the drain to establish steam with a predictable t air content (measure the air content of the water in the boiler). Close V-4.

3. Inject desired amount of air into the steam space to simulate the accumulation of non-condensables.

4. Open V-2 to allow the steam and water to interface. A prototypical thennal layer will be l

developed in the water in the vertical riser..

5. Initiate draining from Valve V-3. Measure draining rate.

6. Record thermocouples, pressure transducers, strain gages, and steam flow rate l

dynamically throughout the test.

7. When the line is fully drained, stop the test.

At the conclusion of each test, the data will be reviewed to assure that sufficient steam delivery was provided to " keep up" with the condensation in the pipe. Adjustments in steam i delivery will be made ifnecessary The test will be repeated with the same variables or with different system configuration and variables Test Matrices Testing Without Loop Seal Support Steam air Drain Number Stiffness content Rate of Tests slow 3 "none" med. 3 fast 3 Stiff #1 slow 3 (RIGID) "modemte" med. 3 fast 3 slow 3 "high" med. 3 fast 3 slow 3 "none" med. 3 fast 3 Stiff #2 slow 3 (TYP.) "modemte" med. 3 fast 3 slow 3 "high" med. 3 i fast 3

1 Testing With Loop Seal Downstream i Support Emm air Drain Number Stiffness content Rate of Tests slow 3 "none" med. 3 fast 3 Stiff #1 slow 3 (RIGID) " moderate" med. 3 fast 3 slow 3 "high" med. 3 fast 3 Testing With Loop Seal Upstream or Hot Water Upstream of V-2 Support Emm air Drain Number Stiffness content Rate of Tests slow 3 "none" med. 3 fast 3 Stiff #1 slow 3 (RIGID) " moderate

med.

3 fast 3 slow 3 "high" med. 3 fast 3

F 1 Attachment C Thermal Layer & Steam Air Content Testing Figure 1 illustrates the apparatus which will be constructed of 2-inch carbon steel pipe. As shown, the water reservoir and 2-inch piping will be separated from the steam space by a quick opening valve. The pducipal variables to be studied are the pressure in the water reservoir gas space, the water temperature in the 2-inch piping, the pressure / temperature in the steam space and the air content in the steam space Consider for example that the water in the 2-inch piping is at a j pressure of I bar and a temperature of 20"C with the steam space at a pressure of 1 bar and l 100*C. Opening of the valve exposes the steam to very cold water and strong condaneadon l would be expected at the water-steam interface. Reduction of the steam space pressure due.to condensation initiates flow; these conditions would be anticipated to lead to rapid, complete l j condensation of the steam space with the water impacting on the top of the pipe causing a strong l waterhammer event. Such experimental conditions are similar to the 1.5" ID " water cannon" experiments reported by Rothe et al. (1977) and Block (1980). As was obtained in the " water cannon" ey&imeins, the measured waterhammer events were as large as 8.3 MPa (1200 psi) and were sustained during the time that the compression wave traveled to the free surface and the rarefactive wave returned to the impact location. l ? For the example given above, the event is tmly a condensation induced acceleration of the water column and therefore a condensation induced waterhammer event However, with this l apparatus the influence of an increased pressure in the water reservoir can also be investigated. j l For example, initial conditions such as a steam space pressure of I bar and a temperature 100"C could be investigated with a water reservoir pressure of 2 bars. In this case, the initial water column movement is by the imposed pressure differential, but as the gas space pressurizes, the condensation induced behavior would be initiated. Here again, the influence of the thermal layers L is an important aspect of the subsequent condensation process Measurements of condensation induced waterhammer events in this apparatus will be an important link between these experiments and those performed in previous experimental systems. This link will be established through a set of reference (baseline) gm. sins in this apparatus. l Following these h==alina tests, the influence of thermal layers will be investigated through a series of gm.cias with different thermal layers in the water column below the quick opening valve i prior to initiating the transient. These thennal layers will have elevated temperatures for several diameters below the valve, as shown in Figure 2a or a continually varying thermal layer over several diameters as illustrated in Figure 2b. In either case, the potential influence of the changing j thermal layer will be measured in terms of the behavior for the reference Jakob number as defined by the equation

p. c. (T. (P.)-T )

P, ha i

r I i Pmposed Apparatus tbr lovestigating the Influence of a Thermal Laver f AirW steam I }-&- O. g - h sesam g. l Trace ,Heming @l Gas @ l w m. w / 4

orain l

+-o&*openhg "" N -l-- @ m water wo Line l = = f N Trace, -h---h Heatng =

-HD h-@

AP g ( v m waar ibw h menspan w. where the variable T is the water temperature far removed from the steam-water interface, p. and p, are the respective densities of water and steam, hr, is the latent heat of vapcni,.iion for water, c. is the water specific heat and T. (P,) is the saturation temperature corresponding to the initial steam space pressure. The thermal conditions in the water column are the essential variai>les for this part of the experimental investigation. This temperature profile will be developed through the external trace heating shown in Figure I with the region next to the quick opening valve being the hottest as i illustrated in Figure 2. This figure illustrates representative axial temperature profiles above and below the quick opening valve. The region above the quick opening valve will be at the { saturation conditions associated with the gas pressure (T. (P )) and the water immediately below l the valve will have two different types of thermal layers developed. That shown in Figure 2a is a i constant temperature for a few pipe diameters below the valve and then sharply transitioning to the. water temperature far removed from the valve (T ). The axial pro 61e shown in Figure 2b is a

linear transition from the saturation temperature to the temperature far removed from the valve with this transition occuning over several pipe diameters; the initial planned characterization considers this transition length up to 10 pipe diameters. These representative the.. a layers would be developed by the trace heating on the pipe wall. Since this represents a thermally stable stratification, this temperature profile can be developed and sustained until the quick opening j valve is stroked to initiate the event. To ensure that the water immediately under the valve is the i desired temperature, a water bleed valve is included to purge that which may become too hot due ] to heat transfer through the valve. 1 The instrumentation for this experimental apparatus will include high response pressure j transducers in the steam space to measure the waterhrui is event, a minimum of two pressure transducers in the water reservoir gas space and thermocouples in the water lines to measure the initial temperature profile for the thermal layer upstream of the quick opening valve. Also, i thermocouples will be provided in the steam space to monitor the steam conditions prior to the l initiatien of the transient. A flow meter in the water piping will monitor the water column displacement into the steam space as condensation occurs j ) Additionally, the experimental system includes the capability to enhance the air in the l steam space immediately prior to initiating the transient through either the heating technique, which is the prefened approach, or with the special air cylinder shown in Figure 1. As was discussed in the Boston Expert Panel meeting, steam vaporized from tap water, which is the typical condition for an open service water system in nuclear power plant, would volatize the dissolved air in proportion to the steam produced. Such a behavior would also occur in this facility since the steam produced in the steam generator would include the volatkation of the air associated with the vaporized water mass. In this regard, the experiment is consistent with the base case conditions of interest for the plant configurations, i.e. this is the minimum air concentration in the steam void. Furthermore, as the steam bubble grows during the voiding phase for the Design Basis Accident (DBA) transient, the energy transfened to the steel pipe wall promotes substantial condensation. However, tie air associated with this condensate would go back into solution very slowly, thus enhancing the noncondensable gas (air) concentration in the steam void region. Basic calculations related to the heat sink thermal mass simw that this enhancement of the air concentration could be an order of magnitude. It is important that these experiments also investigate the influence of this enhard air concentration on the waterhammer events in this basic study. Using steam addition to heat the piping in the steam space to establish the steady-state steam space temperature prior to initiating a transient can accomplish the desired effect. Typically, the steam space will be heated by the trace heating and steam addition through the steam supply line with the condensate removed by draining. If a low air concentration (typical of the minimal value) is desired, the condensate will be continued vented until steam is continually observed at the outlet of the condensate drain and the measured pipe wall temperatures are equal to the saturation temperature correspondmg to the steam space pressure. Conversely, if an increased air concentration is desired, the piping will be heated partially, or completely, by steam addition until the steady-state concentration is achieved. Under these conditions, the condensate drain will be opened for condensate only and will be closed immediately if steam is observed to be vented. The extent to which steam is used to increase the wall temperature will determine the enhancement of the air concentration. Using this technique, tests will be performed with varying initial air concentrations to investigate the influence on waterhammer events. This will enable this basic experiment to study the spectrum of conditions ofinterest in open and closed service water systems which experience boiling.

i-I i 1 l Representative Thermal Layers ,1- ........,.- Quick Opening Valve i 4< i To T i(P,) i (a) i -.................. --- ;- Quick Opening Valve i s T., T,(P,) i (b) RH96cOSS.CDR 10448 l. As an alternative strategy, the air cylinder, which has been pressurized to a preset value, can be opened to enable pressure equilibrium to be developed between the air cylinder and the steam space, i.e. air will be added to the steam space. Once equilibrium is established, the air 4 cylinder will be isolated and the system will be ready for the quick opening valve to begin the l transient.

- - - - - - - - -... -. -.. ~. - - - -. _.. - _.. - _ _o l Task 2-a In this task we will investigate the influences of varying thermal layers and noncondensable gas concentrations on the mitigation of waterhammer events. Initially, a set of reference / baseline j data will be developeo by measuring waterbn+r loads for condensation induced conditions in which the water temperature below the quick opening valve is cold and uniform. Data will also ? i' be taken for variations in the water reservoir pressure as well as the water temperature. Once this set of reference data is obtained, temperature pro 61es like that represented in Figure 2a will be ] investigated with the length of the increased water tenperature being varied from' I to 10 diameters. Initial evaluations presented to the WEP suggest that 5 diameters is a value that 4 substantially la-law the cold water from the steam-water interface Furthermore, the energy coaha=ad at the interface is convected back to the free stream as a result of the high temperature - water being laid down as a film on the pipe surface as the water column progresses into the steam r j-space. This value of 5 diameters will be used as the initial planning basis for determining what myeziwets should be investigated with respect to a sufficiently thick thermal layer to essentially be considered as infinitely thick. Table 1 is a reference test matrix for the experimental program Once a thermal layer configuration like that shown in Figure 2a is defined, the experimental program will consider linear temperature variations from the quick opening valve down to the coldest temperature as illustrated in Figure 2b. Here again, the extent of the temperature variation and the length of the variation will be changed to examine the influences of such thermal layers in mitigating the waterhammer events (see Table 1). As before, a value of 5 diameters will be used as the planning guide to construct the initial test matrix with several tests left undefined,to pursue after initial experimental evidence has been obtained Several nominal conditions, such as a water reservoir pressure of I bar, an initial water temperature of 60?C and an initial steam pressure of I bar will be examined. with a number of experiments to clearly determine the extent ofugiustal scatter that can be expected. At least two conditions in each of the three parts of the test matrix will be repeated up to ten times to determine the extent of scatter that is expected to characterize these results A clear demonstration of the experimental scatter is important in implementing the results of these tests. Lastly, the influence of the noncondensable gas concentration that is increased to twice, five times and ten times that typical of the air nominally available in the steam space will be investigated. These results will be compared to those obtained in the reference cases for given water temperature and driving pressure in the. water reservoir. Such experimental results will demonstrate the respective influence of an m' creased air concentration in the steam space as a result of extensive condensation due to heating of the surrounding pipe walls in the fan cooler systems considered in the evaluations for Generic Letter 96-06 This basic ' formation with m anh-*J gas concentrations will provide the needed insights to represent these influences on the service water system in open plan configurations and will also demonstrate the influence that such enhanced gas concentrations have on waterhanuner events as compared to those events investigated in NUREG-5220, 18

.-..~.- i f i l Table 1 - Reference Test Matrix l . 1. REFERENCE /BASELINEDATA L Water Reservoir Pressure 1.0 bar,1.5 bars,2.0 bars Inital Water Temperature-20*C,40*C,60*C and 80*C ~ Initial Steam Pressure 1.0 bar,1.5 bars,2.0 bars

2. THERMALLAYERDATA Water Reservoir Pressure.

1.0 bar,1.5 bars,2.0 bars WaterReservoir Temperature. 20*C Water Thermal Layer (Constant Temperature): Temp. Length 80*C 1dia 80*C 2dia 80*C 5dia 80*C 10 dia 60*C 1dia J 60*C 2dia 60*C 5dia 60*C 10 dia Water Thermal Layer (Linear Profile): 80*C to 20*C Over 1 dia 80 *C to 20*C Over 2 dia 80*C to 20*C Over 5 dia 80*C to 20*C Over 10 dia l l t

3. INFLUENCE OF NONCONDENSABLES Water Reservoir Pressure:

1.0 bar,1.5 bars,2.0 bars Initial Water Temperature: 20*C,40*C and 60*C Initial Steam Pressure: Ibar Initial Air Content: 2 x nominal,5 x nominal,10 x nominal 19 i l^ l ll'

... - - -. -. ~. l l l l 1 i i References i Block, J. A.,1980, " Condensation-Driven Fluid Motions," International Journal of Multiphase - Flow, Volume 6, pp.113-129. l I . Chou, Y, and GrifHth, P.,1990, " Admitting Cold Water hto Steam Filled Pipes Without Water Hammer Due to Steam Bubble Collapse," Nuclear En@-xdng and Design 121, pp. 367-378. Rothe, P. H., Block, J. A., Crowley, C. J., Wallis, G. B. and Young, L. R.,1977, "An Evaluation of PWR Steam Generator Waterht;nmer," Creare Report TN-251, NUREG-0291. l 1 i l I l l I t l l 20

r 1 i.. ) l I l 1 Attachment D Column Closure Waterhammer Testing The additional Colunm Closure Waterhammer testing to be performed involves a modification to the existing Altran " Configuration 2" Waterhammer system. A simplified diagram is shown in Figure 1. M* 6 A(aswconfig) ) [ 21/2 A(existconfig) WaterTank SteamtVeld [ Heating Steemt [ 3 t 1 >aA 5E Kf) 2 wm SisyHiled diagrant ef==amd Configmtiem 2 Ma$or change is to length efsteam veld Figure 1 Overall Test Description The test piping configuration consists of a driving water column, a waterhammer generation section, and downstream piping through which the generated pressure pulse travels. The configuration referred to as " Configuration 2" allows for the study of the effects of water conditions on the generated waterhammer. This is accomplished by using tlw water in the pipe to generate steam voids though extemal heating, thereby releasing any non-condensables l as would happen in actual plant piping. The piping in configuration #2 features a heat exchanger consisting of a 6" pipe jacketed around the 2" test pipe. This arrangement induces 21

boiling and void formation in the test pipe, and is representative of the Fan Cooler Units that are central to the generic letter GL96-06 issue. - The piping system consists primarily of 2", schedule 80 pipe. The driving water column upstream of the test section consists of a length of pipe, pressurized from above using an air accumulator tank. This column is isolated from the watdeiwiier producing section using a ball valve. The ball valve isolating the driving, pressurized fluid from the test section is designated as Valve 1. Downstream of the watdeinrs test section, the outlet piping runs approximately 70' through a series of elbows to a closed volume (tank) with a free surface This piping is instrumented with pressure transducers at the end of each run. Pipe supports are also instrumented to provide the transient forces as the pressure pulse passes through the ii PPng. Non-condensable content in the water is controlled from the filling tank (free surface) at the end of the pipe run. This tank is equipped with a pressurized air source at the bottom that can be used to aerate the water before filhng the test section. The tank is also equipped with a screw-in heating coil that can be used to boil (deserate) the test fluid. Enough water can be treated to fill the piping for a series of 5 tests before re-filling of the tank is required. The dissolved oxygen content is measured as a representative number for the total amount of j dissolved non-condensables which are primarily nitrogen and oxygen. A full series of tests have already been performed by Altran. This testmg configuration already used will be modified. The modified configuration includes a lonFer steam void to I more closely simulate postulated CFC/LOCA/ LOOP conditions. The longer steam void will allow evaluation of the thennal layer and air cushioning attenuation affects during column closures A longer closing water column than used in the earlier testing is also provided to increase the pulse duration beyond prior testing The closure velocities will be moddied to closely simulate the closing velocities expected in the participatmg plants - particularly the closed loop plants. The data to be recorded is similar to previous Configuration 2 testing with some additions. The data to be collected willinclude: Dissolved oxygen concentrations Pressure pulse characteristics Support Loads Upstream and downstream vertical leg temperature gradients Testing'will be performed for at least three Froude numbers (all greater than unity typical of postulated plant configuration Froude numbers) and three ranges of dissolved oxygen concentration. 22 a

__.m J Test Procedure The following steps are used to perform the test:

1) -

Water is fdled to a ' desired column height in the driving section, isolated, and pressurized to a desired driving pressure. Control of the column height and pressure allow control of waterhammer duration and magnitudes. . 2) The dissolved oxygen content of the water is measured. 3) Steam voids are created in the test section piping by boiling the fluid in'the pipe. This is accomplished by introducing steam into the heat exchangerjacket around the test . pipe. Steam is supplied from the 1.5 BHP boiler, set to approximately 12 psig. 4) Sufficient steam is produced to void the horizontal section of pipe above the jacket heat exchanger. Ultra-sonic level instrumentation is used to verify the length of the steam void. The test section of pipe is sloped to cause the steam void to form at the top of the pipe loop, away from Valve #1. 5) When it is verified that the horizontal section is fully voided, Valve 1 is opened The incoming. water collapses the steam void and produces waterhammer. The waterhammer pressure pulse transmitted through the downstream piping is then measured utilizing the downstream pressure transducers and support reaction forces are also measured. Test Matrix A proposed test matrix consists of the following scope of tests and variables to be measured. Test Matrix Variable Values No. of Tests Total Objective Vary Drmag Calculatepressures to 5 at each 15 Desenmne redillvelocnyoffacts. Pressure provule closure velocatmos of velocity 10,20, and 40 ft/sec Vary Water. Normal, Aersted Demerated 5 each for 15 With high 'and lowdissolved Characseristnes

normal, 02,determee the offect an acrated, and waterhammer pressure and deserated sonic velocity I -

23

- - =-___ - - -_-- ------ - Attachment E Waterhammer Project Schedule i 4 Qtr 4,1998 Otr 1,1999 Otr 2,1999 Otr 3,1990 Qtr4,199G ID Tank Name Start Sep Oct i Nov i Dec Jan i Feb i Mar Apr i Nay l Jun Jul l Aug l Sep Oct l Nov { 1 TSR Plan Preparation Mon 9/14/96 -l 2 Waterharnmer Expert Panet (WEP) Meeting Tuo 10498 104 l 3 WEP Review Telecon Tue 11/10f98 41/10 l $e ) a j 4 Authorization to Proceed Fd 11/20/98 11/20 i 5 Teoung Fd 11/20/98 l l l l 4 { 6 Analysis Fd 11/20/98 s 7 Draft of TSR Fd 11/20/98 l 8 WEP & Utilty Meeting (Tentative) Wed 1/8/99 g qfg 9 Review TBR Mon 2/1/90 l l l l i 10 Additional Analysis & Testing Mon 2/1/99 g { .f g { 11 2nd Draft of TBR Mon 2/15/90 12 WEP & Utility Review Meeting Tue 3/2/99 4 g; l l 13 TL.R Review Tue 3/18/99 l l l l l' 4 14 WEP & Utility Review Meeting Thu 4/15/90 18 [ i 15 Final Analysie & Testing Fd 4/18/90 l l l l 18 Final Draft of TSR FH 4/18/99 l l 17 TBR Dra8 Complete Tuo 8/1/SG = 1 *. 18 Final Review of TSR Wed 6/2/99 l l l 19 Final Commente incorporated Thu 7/1/90 l l a-20 TBR to NRC Thu 7;+Mie g { l I [ 7/15 f 25

l TBR Plan Determination o Topics were described and discussed in the last Expert Panel meeting (October 6 and 7, 1998) o Following that meeting, a Proposed TBR Plan was prepared and distributed. o Comments were received from participating utilities and the Expert Panel o Comments were discussed. with the Expert Panel (November 10,1998) and modifications were subsequently made to the Plan. l o The final plan was issued on November 30, 1998. 1

Uncertainty (definitions extracted from R. G.1.174) Aleatory Uncertainty - Uncertainty associated with the events occurring in a " random" or " stochastic" manner. l Epistemic Uncertainty l - Uncertainty associated with the j analyst's confidence of the predictions j of the model. It reflects how well the j model represents the actual system [ being modeled. i - Three classes of epistemic uncertainty l are parameter uncertainty, model uncertainty, and completeness uncertainty. i 2

l Epistemic Uncertainty Paramet.er Uncertainty - Uncertainties associated with the values of the fundamental parameters of the model. These express the j analyst's degree of beliefin the values that these parameters could take. Model Uncertainty - Uncertainty associated with the industry's state ofknowledge of the models to be used for specific events or phenomena. Completeness Uncertainty j - Uncertainty associated with unanalyzec j contributors 3

1 l Waterhammer Progression r 1. Loss of Power 2. Begin Draining 3. Draining down through a Vertical Pipe 4. Draining up through a Vertical Pipe 5. Draining through a Horizontal Pipe l 6. Pump Start 7. Filling a Vertical Pipe 8. Filling a Horizontal Pipe 9. Column Collapse

10. Wave Propagation

11. Piping / Component Reaction l

12. Component Qualification l

l l 1 4 I

i i ) i 8 3 t 9 , e i t .a Laas of Drainage dew through [ Draining thsough Penny FM a W he Waw g Ptwer Hydraulics a Vestical a Herimental Pipe Start IJee Cesaper Propagaties Itencelsa QuaWhea*E== y Wechselsen T.-p, Fluid When dranung When Ptnentsal for Pamps Einturget Passon or Two coliunns Waw travels at. Segment fonze Benchngisomessa, coast column in wrtical "draanag" in strattfaed steam and come up piston flow or strasified, impact at sonic velocity, in pipe dee to axial forces, down and slowly down vertical up subcooled waser to speed annularflow dependmgon given reflects froni nadiatance assgiort forces, and flow moving dmxtron, get direction, get and dyearkna on flow rate velocity changes in r===rc pipe internal press cause eventually towards a " piston" bubtdingand flow duection and dir=$ian area stress and stresses in fan stops steady-state drainage steam break-begins flow rate change or supportloads aioler, pipeg, and condition through density change pipe supports. If Fr< 1 watery L L L M H L M M M M M M Uncertainty Parameter L L L M M L M M M M M L Uncertalary

del L

L L M H L L H M M M M Uncertainty C--. 4 ~- L L L L M L L M L L. L L Uncertalary TB J Plan None None None (I) 4' QWH (I) 4' QWH Test None Fr <0.67 Fr < l I)CCWH

1) Qtsantify Compenson of Tabulate methods Action Test with in Horuantalpipe investigation, investigation,if Testmg

==aH % analyus to tests Selected loop seal (2)Thermellayer if n~~=ry necessary

2) Compare

2) Quantify (2)Thermat Test to Plant test attenuation Layer Test

3) Dewtop

3) Wave me.winingy Propagatior

4) Sonic Velocity Task None None None Task 4.3 and Tasks 4.1,4.2,4.3, None Tast 4.5 Task 4.5 Task 6.I and Task 7 Task 6.3 Task 8 Number 4.4 and 4.4 6.2 Task 6.3 Task 2 l

s. m

m. -

. u- -6. _.___________.__._.--_.___.._._,_.______u.n.___.______._

Additional Tasks i i e e Write the System Descriptions for the TBR. (Task l 1.2) c, l e Define the waterhammers that need to be considered and prepare a checklist of { configurations or operating conditions that may l provide susceptibility. (Task 3.1) ll } e Develop a basis for extending the test results to pipmg sizes up to 12". (Task 5.1) t i e Define the applicability of the work included in this TBR to other waterhammers and any limitations in the applicability will be described. (Task 9.1) e Define both the certainties and the uncertainties associated with the approaches being recommended. (Task 9.2)

Use PRA analyses to demonstrate the low probabilities of occurrence of the loads calculated.

(Task 9.3)

i l i l-EPRI, Second Meeting of the Waterhammer Panel, February 22-23,1999 s i STUDY OF FREE AIR IN SINGLE PIPE SYSTEM i L OBJECTIVE: To examine the infhacrice of free air on the pressure response during pump startup in i combination with condensation induced water hammer. SYSTEM: ne system was schematized as a 250 A long 6" ID pipe, beginning with a pump and check valve, 50' horizontal, 50' vertical,' 50' heruantal,50' vertically down to the original elevation, and 50' . horizontal to an open valve at the receiving tank. He 50' downward leg was visualized to be vapor at 212 l degrees, with the rest of the system filled with stationary cold water. ne downstream tank level was 20'. ' he pump curve was described by: H = H (1.25a - 0.25 (Q/Q )2),in'which Q = 2.356 cfs, the rated Gow, 2 a = the dimaisionless speed, and H, = 67 A, the rated head. De pump came up to speed in approximately ' O.5 s. In the simulation 20 reaches at 12.5 A wwe used for the pipe, f = 0.02 (0.06 at the location of the fan i coolers), and a = 4000 A/s, the wave speed in pure water. In this model' the free gas was assumed lumped at computing sections with pure water in the reaches. With vapor pressure at atmospheric pressure for 212 degrees the water in the rendes required that the system be modified to accommodate the no-flow initial conditions, that is, thwe was a fluid statics compatibility problem. He pipe layout, ar modeled starting at the pump, consisted of 50' of horizontal pipe at elevation 0,25' ofpipe up to elevation 20',100' horizontal at elevation 20',25' down to elevation 0, and 50' horizontal to the tank. RESULTS: An estimate for the available mass of free air was made by assuming 50 A of pipe filled with water saturated at atmospheric conditions, then boiling it yielding 4.17(10)dslugs (0.0134 lb. 6.08(10)-5 ' kg). A cavity volume equal to 50' of pipe (9.82 cu A) was assumed at section 15 in the system,75' from the downstream end. Vapor pressure in the cavity only was assumed to be atmospheric pressure, nree conditions were modeled, one beginning with a no. flow initial condition at a pressure level of 20' (equal to the downstream tank). De transient event was initiated by starting the upstream pump. i 1. - All of the air was located in the cavity. He results in Figs.1 & 2 show the pressure to rise to 317' l -(137 psi) at about 4.5 s. Again, section 15 is the location of the initial cavity, and section 11 is 50' l upstream. His result is very sensitive to the mass of free air, Fig. 3, along with other parameters. - . Figure 4 shows the variation of Ap between Sections ! I & 15, and Fig. 5 shows the resultant force. on this reach. 2. . De air was distributed upstream of the cavity, beginning with no air 50' upstream, thcn linearly . increasing to a maximum amount at the cavity. Figures 6 & 7 (labeled case 3) show the pressure to rise to 517'(224 psi) at section 15, followed by 740' (320 psi) at section 11. Figure 8 shows the variation of the resultant force on this reach. 3. . A vapor cavity was assumed without any free air at section 15. Figures 9 & 10 (labeled case 5) show a standard water hammer event with a pressure rise to about 1050'(455 psi).This value is ' close to Ap = p a AV/2, in which AV is the velocity change at the cavity at the time of minimum volume. nree additional parallel cases were modeled, with vapor pressure assumed to be that of cold water (cases 2,4, & 6). His required a modification to the system to be able to begin the evait from the same initial conditions. In each case the resuking pressure rise was more severe. g Prepared by E. B. Wylie February,1999 I ' Wylie and Streeter, Fluid 7hmstents in Systems, Chaptu 8, Prentice Hall,1993. Li

j ( y r~ fl% ,I L sI & ~t n 's 4 <W ~ I g i f O + i I 'm .-) d Is. 4 0 I Q^) .4 o I n gy 4 g a 'i g* q ::it / I* / O ~. + n-o o-o i Q l ( / a 'Eh )Y E ', a f c 1 0.n " ~ d h ad 2

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EPRI, Case 1, Concentrated Air @212 350 ,b 300 - g I I 250 - Section 11 1- - C i --- Section 15 i ( g $ 200 - \\ I i g E I l150 ,L - - -\\ E 1 \\ CL i '\\ 100-50 - / 0 4 4.2 4.4 4.6 4.8 5 Time, s i 5 2 ? -.--.- -..--.n. x n

k w m ,-o 6 Q') i e m 8 e m .o -M od i v'6 E .c m e a m a m 4 i e o O i .C o e e m 4 m m S 2 me a uo. x 5 me 9 4' n. o 0: a.w o .o o o o o o o o o o o o o o o o o o o o> m s e o v m m y 'peeH eJnsseJd

-i

l

'i i EPRI, Case 1, Concentrated Air @ 212 Pressure Difference between Sections 11 & 15 I 80 - i' t 60 - i t 40 - e l j 20 - j a 2 0-Se { p15-p11 - \\V 40 4.4 4.5 4.6 4.7 4.8 4.9 Time, s G. + ~)

m EPRI, Case 1, Concentrated Air @ 212 Force on Reach Between Sections 11 & 15 1000 t 800-600 - l t m 400-8 0-5 l -200 - I ) x -400 - _-- DF, Ibs e -600 - -800 - 4.4 4.5 4,6 4.7 4.8 4.9 i time, s F~ :. 5 i

L ri.

j EPRI, Case 3, Distributed Air @212 800 700 -

600 - .c l Section 11 i i 500 - --- Section 15 W i I g it e 400 - l lI i 1 '3 I I E 300 l 'I e l

a. 200 -

) l 1 1 100-i i m }A l 0 i 0 1 2 3 4 5 i Time, s l a

m EPRI, Case 3, Distributed Air @212 800 l 700 \\ I 600 Section 11 i-

500 c--- Section 15 A

I f I \\ l 1 3C i \\ g400 ,,I 3 ( en i II l \\ 8 Il \\ t t & 300

-j,1-h r

i I ll 1: 1 l \\ I 200 i I \\ \\ l l 100 e i } } 0 4 4.1 4.2 4.3 4.4 4.5 4.6 Time, s

63. 7

=

EPRI, case 3, Distributed Air @ 212-Force on Reach Between Sections 11 & 15 '6000 - 4000 - 2000 - 0 J o u_ i j -2000 - 3 5 - DF, Ibs j -4000 - -6000 - l -8000. l 4.1 4.2 4.3 - 4.4 4.5 4.6 time, s fg. 7 i

y l EPRI, Case 5, No Air @212 l ~ 1200 [ 1 1000 l i 1 \\ i \\ ai l l 800-Section 11 i ' -u l i + g --- Section 15 ll I l i 600 - l e l 'a i I (/) 11 i U) l 1 2 400-p o. i h 200- -ll u l I ,--r__-_ 5 j 0 1 2 3 4 5 Time, s 6.7 2/3S9 3

EPRI, Case ~ 5, No Air @212 1200-P i 1000 - t- -t-I I I I I I 800 - l. I i Section 11 d i W I I --- Section 15 y i i g 600 l 5 I V) i I l dt 400 --L i-1 I I I I I 200' L L I i i I D 0 4 4.1 4.2 4.3 4.4 4.5 Time, s E. /o J

) i 4 PRESSURE PULSE i i PROPAGATION i h Attenuation i i l Amplification i ^ Fluid Structure Interaction t t I [ i

1 Amplification & Attenuation MECHANISM AMPLIFICATION ATTENUATION AREA CHANGES X X t FRICTION X L DENSITY CHANGES X POISSON X COUPLING JUNCTION X X COUPLING +

I Area Changes n N 1 .' ll P1 i P0 A0 Al / P i-P sys 2 P 0-P A l sys y A 0 n 2 P sys := 0 psi A 6 A 0 = 28.274 0 := 7 x 2 P 0 := 200 psi A 14 A i = 153.938 i := 4 P i P i := 62 psi = 0.31 P 0

m 1 Friction t High frequency frictional attenuation is of most significance in high frequency, high viscosity, low reynolds number configurations 4]. The RELAP model appears to simulate j frictional attenuation. i

Density Lower density regions compress & attenuate the propagating pulse. The pulse propagates more slowly through 1 lower density regions. Reflections occur when density changes are encountered. Free air or steam bubbles are an example. i - - J

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r i 1 Poisson Coupling 1 "The incremental pressure and axial stress caused by the Poisson effect are on the j order of 1 and 10 percent, respectively, of the primary pressure". [4] The small contraction of the pipe due to the l tension wave cannot cause a significant pressure rise. j

i Junction Coupling 4 Amplification i A comparison between Junction Coupling amplification and decoupled " dynamic amplification factor" methods was made under Reference [4] for 8" sch 40 pipe. While the Junction Coupling analysis of 4] showed pressure amplification from 213 psi to 263 psi, the decoupled analysis resulted in j more conservative piping and support loads. i

Junction Coupling Attenuation i Swaffield reported pressure pulse attenuation on the order of 10-20% going through 90 degree direction changes :1: . Swaffied reported that the attenuation was solely a function of bend geometry. i The attenuation shown in the Swaffield report is regarded as sound data however it is considered to 3e dependent in part upon support stiffness :2,3:.

i Junction Coupling Attenuation Attenuation of a pressure pulse is simulated L by modeling a spring-mass system with a time dependent forcing function ~6~. Pressure pulse attenuation with orders of magnitude similar to the Swaffield report j are calculated using "his approach.

References i [1] Swaflield & Phil, "The Influence of Bends on Fluid Transients Propagated In Incompressible Pipe Flow", Thermal Dynamics and Fluid Mechanics Group, Proceedings of Institution of Mechanical Engineers, Vol.183, Part 1, No. 29 (1968-1969). [2] Wiggert, Otwell, Hatfield, "The Effect of Elbow Restraint on Pressure Transients", Transactions of the ASME, Vol.107, Sep 1985. [3] Wilkinson, " Dynamic Response of Pipework Systems to Waterhammer", Proc. Third Intl. Conf. On Pressure Surges, Vol. I, BHRA, Fluid Engr., Canterbury, England, Mar.1980. [4] Wylie & Streeter, " Fluid Transients in Systems",1993. [5] Hatfield and Wiggert, " Water Hammer Response of Flexible Piping by Component Synthesis", Journal of Pressure Vessel Technology, Feb.1991. [6] Moody, "Non-Intuitive Thermal-Hydraulic Loads In Reactor and Containment Technology",1989 ASME Pressure Vessels and Piping Conference, July 1989. ...m. .m m m mm

1 811El 1

e Condensation Induced Water Hammer Test Program 1

f { Test Plan February 23,1999 l l r ?

Purpose of Testing s- >To Understand the Dynamics of i Condensation Induced Waterhammer i Events >During Horizontal Pipe Draining >with Loop Seal i > Generate Waterhammer Data in Carefully Controlled Laboratory Environment > Compare Test Results to Current Analytical 2/22/9 Methods CCWH Test Program 2

b i Test Apparatus ,s." r l f veet Sieon Supply s,.+ tne av c2c 4' Dion. x 20' Tesi Section Tro ned steon buba e Downstreon Droin Control l A 2/22/99 CCWH Test Program 3

Test Loop Schematic Bati volve 73 4' Tesi Section Sieon Accunutat or Conical Volves 2' Steon Supply (f 2' De ein O W High Pressure Vocuun Tonk VN M Sieon Supply Volune Glob e Boll Volve Volve 2/22/99 CCWH Test Program 4

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b } Test Design l > High Pressure Steam Volume 250 gal tank at 85 psig can supply 7.5 lbs of steam through two control valves j > Steam Supply Control Valves 2" and 2.5" valves in i parallel can supply steam at a rate of up to approximately 6000#/hr > Low Pressure Steam Volume 80 gal tank (plus piping) contains 1/2 lb o* steam to absorb " condensation shocks" > Accumulator Tank 80 gal tank provides low pressure volume and drives flow j > Flow Control Valve manual globe valve controls drain rate l 2/22/99 CCWH Test Program 6 o

. k h Test Design > Initial Conditions at start of test: j >Php = 100 psia > P = 15 psia ip >P = 5 psia acc > Drain rate can be varied from Froude of 1/2 to 2. > Froude =.(gd)1/2 > Test Sections will be swapped for Lexan sections > Test Sections will be swapped with LOOP seal section j i h ? 2/22/99 CCWH Test Program 7 j f m. .. m

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THERMAL LAYER AND STEAM AIR CONTENT TESTING R. E. Henry Presented to the Waterhammer Expert Panel Boston, Massachusetts February 23,1999 !! YOW 22399.A

ISSUES TO BE ADDRESSED FOR CONTAINMENT COOLER WATERHAMMER EVALUATIONS Geometry Flow Coastdown and Startup System Pressure Extent of the Voiding Transient (Duration / Length of the Void) System Temperature Distribution Resulting From the Voiding Phase Air Concentration in the Steam Void Voiding Into Horizontal Piping HVOW22399 A

l i Basic Issue for Point Beach Prior to GL96-06 l } j DBA requires loss of off-site power. Service water flow is loss for about 30 j seconds before the pumps are loaded on by j the sequencer. i l l Energy transfer to the fan cooler causes a l two-phase state in the cooler and beyond. FSAR states that the fan cooler would be removing the DBA stated heat load in 60 j seconds. i I Waterhammer was never analyzed in the fan cooler piping. i Could steam voiding progress outside of the 4 l containment? i Could waterhammer challenge the fan cooler integrity? HV0il496

E "~N g p E / \\ / g i 1HX-15A I - 85 l s l - 80 1 I l - 75 12-1G" '~ -ta-t y - 70 2 s I t I E i - 65 el l a - 60 l [I - 55 al 8" El l 8-o - 50 l OI l c l o g 4

-45 4

^ 1 1HX-15A i .e _4o tu l - 1HX-15C 20* SW [ I - 35 l Return HDR. I D 4% - 30 l i C -A-.r - 25 l lr n i *To I 4 I - 20 1HX-15Cl --1 HX-15B ( - 15 l From Unit 2J C 3 l 1HX-15D CFCS -10 1 Unit 1 I I l 1HX-15A l Unit 2 / Unit i / g SW Disch. SW Disch. I To CW System To CW System. g E- 0 I my,anm Figure 4

a Basic Issues for Prairie i Island Prior to GL96-06 Same as Point Beach issues except for the i following. Drain down of the supply piping. Dedicated diesel for the service water can limit or eliminate the voiding in the fan cooler coils. Limited potential for column separation. -im

i Initial Questions i 1. Would column separation occur? Yes & No 1 I 2. How much steam could be generated and at what rate? j 3. How far would the steam void progress into j the service water piping and would it l progress into horizontal segments? l 4. What are the magnitude of waterhammer events during the voiding phase? 5. Does the rate of water refill strongly influence the magnitude of waterhammer events 9 1 6. What, if anything, is different about this situation / configuration than what was evaluated in NUREG-5220? HVO\\l498

IMPORTANT CHARACTERISTICS IF VOIDING OCCURS Voiding Phac.e Pressure in the cooling coils is determined by heat transfer from the containment - this is efficient due to large surface area, condensing heat transfer, etc. Steaming rate is large and displaces the water in a a one-dimensional manner including the heat losses to the surrounding piping. Steam condenses on the pipe wall thereby concentrating the air and also builds a thermal boundary layer. Refill Phnc.e Water refilling the piping will pass through the 4 cooling coils increasing the temperature significantly. Condensing on the steam-water interface will help develop a thick thermal boundary layer adjacent to the steam bubble. j The thermal boundary layer in the surrounding water will determine the condensation behavior. Air is compressed into the remaining steam void. i H VO w22399-A

r Initial Approach Experimentally address the potential for substantial voiding of the fan coolers and the discharge piping. Experimentally investigate the influence of Tall configurations with the potential for column separation. Different durations of the voiding transient due to different pump restart timing, o dryout of the fan cooler tubes, o variations in the containment o atmosphere due to different LOCA scenarios. Voiding into horizontal piping. Voiding the entire discharge piping through the throttle valve. Drain-down of the supply header (Prairie Island), leakage through check valves (Point Beach). HVO\\t498

DURING THE VOIDING TRANSIENT Consider the heat transfer in a fan cooler to be 10 MW (34 MBTU/hr). The resulting steam velocity in the 8" pipe is about 416 ft/sec (127 m/sec) which is an order of magnitude greater than the entrainment velocity (56.8 ft/sec /17.3 m/sec) 4 - 3.7 gga i'pr - Ps) U,, _ }p, Thus, unless the energy transfer is very low or condensation on the heat sinks is very high, there will be no stratification during the voiding transient. l.\\HVml01696A

i L t j VOIDING IN THE FAN COOLER i Sustained steam generation in the fan cooler l requires the presence of water. l If the voiding rate is too high, the steam l would " flood" the water in the cooling coils and dynamically remove the water. This l would terminate the voiding leaving only column separation and rejoining. i l The maximum energy transfer that could i occur in the fan cooler coils with water l remaining to support continued steaming is ] about 1 MW. Thus, high voiding rates can not be j sustained. I 4 IAHVmt0196.A

4 l Pipe Wall Thermal Capacity This influences the voiding rate and is an important consideration for the two-phase flow pattern in horizontal lines. In addition this strongly influences the ailr content in the steam void. The wall thermal capacity also influences the thermal layer during the refill phase. i Thermal time constant needs to be short compared to the respective process. HVOW22399-A

Maior Features to be Addressed Voiding Phase Column separation can occur (design dependent). Steam generation rate. Mass of steam generated. Could be vertical dcwnflow, vertical upflow and!cr liorizontal flow. Steam is pushing the water. Pipe wall heat sink. Depth (length) of the thermal layer. Refill Phase Refill rate (Froude number). Pipe wall heat sink.. Length of the voided region. Could be vertical downflow, vertical upflow and/or horizontal flow / Depth of the thermal layer including the condensate. Additional-steam generated. Heat added to the water during refill of the fan cooler coils. HVO\\t498

. _. _.. _. _.. _ _ _.. ~.. _. _..... _ _.... _ _ _ _ _.. _ _ l 4 I i i 4 i 4, i: h i [ l b' ) ie ?l:3

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,111 1.1 ei r "j 4 8 .C c d 3 r, U l \\--j - =.-- t' T 81 ~ m !.1 $_11][ { l 15 t ) i 5 k I 5 i %I11 if I I o i 4 5-Experimental configuration for investigating possible waterhammer conditions in the service water system. i-

6-WATER HAMMER TEST tt6 (11-14-96) 0-L 95-I C F ?. ? ~ G_ c m m [* % i f

" P MM h m hy pp g g g p I

o 9 9 9 I I I I f I I f I E f 9 f f 1 1 t t l I t 1 j { g g g ~ 50 55 60 65 70 ' 75 80 85 90 g .... g ... g.... g.rine eseCr n ... g....g..,,,.,,,,,. i

TC9" i

eg :- ' TCl2" ---- 'TCl3*........ o 2 :- U ? m w ~o a_ E C. f r^ o ,I V~ T ' ' ' ' - o U l h E8 E.- i ,3 g o e ,r / o :. / / .,e =e.=.'.............***......'... o ,,",,,,I,,,.Ii,,,Ii,,,i,,,,!,,,,!,,, 50 55 60 65 70 75 80 85 90 -TIME' *CSECY Figure 3 Comparison of waterhammer incidents and the thermocouple response during voiding of the horizontal loop seal.

Basic Considerations for The Condensation Process Condensation Rate W = p, A U co, i and therefore the rate of energy absorbed on the advancing water interface is i Enerev Transfer Rate 4 Dcon = Pg AUh re = h A f, - T,) con HVO\\l0 98

Basic Considerations for The Condensation Process ] (Continued) Heat Transfer Coefficient (Reynolds Analogy) h = f/2 p, c U, h = K, p, c, U Inequality for Condensation Pg h s K, p, c, y,,, (P,) - T ) re g Ja 21/Ko where Ja is the Jakob number defined by Ja = Pe hrg HVOW22399 A

1 1 l p n / / / /, / / / /j-P,T,p j e g g g t / / i / Steam / i f Space j i / / / / / / / / / / i / / / / i / In / / U / i / / A k / / i / / 1 / / l / / i / / / / W1, T, l F / i / p t 7 / ' h / l $.$' Colum $ / / E / / 0 / / i

/

/ R / / / / 1 e / i 4 j P = Upsteam Stagnation Pressure ( A = Cross-sectional Area j 1 1 i l i Schematic Representation of a Water Column Advancing Into a Steam Space i NYS10te97.A

t .i, \\ ~ l sendusImma

==- I { E I1 o r.--1 l r==e C i g BoTen-* o i rune f..__.., y l Schematic Diagram of the Experimental Facility - l as taken from Liang and Griffith (1994) I

u I y LOWHEQEhCY ad BBildh6 a o S .O, lMSTAa S TA R E i 4E XT \\ ST g

STEAM Mcal a

'ChlAiG C K3f NU I .i f f[$ i, O ) i 4 Y El Ii C p., f fl f STEAas asAss FLuz, e, Schematic Flow Regime Map of Steam in Water as Characterized by Liang and GritYith (1994)

4 ol = e. eses ej 3-o; ButHeling & Jetting w ga-eI = s = m. m r er. 3.,g g, 86 Chugging .i se 4e se se see iae ie Water Jacete Nesmber, Ja Criterion for the Chugging Transition as Represented by Liang and Griffith (1994)

t e 1 4 4 FLUSH WOUNTED i TRANSOUCER) % STE A M j OVERPRESSURE) l 3 STANDOFF - MOUNTED i TRANSDUCER (DE PRESSURIZ ATION) 3 !U \\Y\\ x s \\ 'N x i N NN

s

) \\ // / /,/,/ /, I / / / { i l l l b, I i METAL PIPE OR ! 28" ACRYLIC TURE i { t i I i J l l 4 l s--1.5'10 WATER RESERV0lR --ei i j i i 1 i I _ _-_ _ m v _ _ = _ _ -e =,

s. ~.s i

m el A.se w-l p ~ I P _w e m -_ v ~ w ~ 4 l WATER CANNON MODEL i i i i i Schematic of a basic experiment on condensation induced waterhammer reported l by Block et al. (1977). 4 4

.. ~.... -........... l l i ME TAL PIPE ,2 RESOUNO j 8 OVERPRELSURE $ PIKE SPIKE . 2400 j_ (PEAK OFF SCALE) f E 2000 $~ p a l200 psi 7; ) i h y{l600 j l Q E~,1200 l =. .-4 W 800 - a. 8 -8 DEPRESSURIZAfl0N 400 ) -12 i l 0 I j 0 60 0 200 300 400 500 0 a 2 3 t i 9 RESOUNO OVERPI ISURE SPIKE g spigt ~ 2400 8 ~ (PCAK > "* ALE ) K / 9 w n e a 2000 % 4 g 3000 5-I__. p ol000 psi ~ o h N g,1200 \\ j ga g -4 400 - a. w* 8 ~8 O 400 j '"0EPRESSURIZATION j -12 t I e i e i i I e o e I i f i 1 0 10 0 200 300 400 500 0 1 2 3 t i b 1 i i 12 RESOUNO i ~ OVERPRE$$URE SMK$ Sp KE 2400 i j l 8 ""(PtAK OFFSCALEA; gg J 2000 ~ 4 5 w-{ 4 t nT 1600 g*i200 / gal 200pst { n j R- 0 c j g

e.,a j

t -4 5 .00 l U -s __DEPRESSURl1Atl000 400 -12 l a l l l I 'kI ~ O 10 0 200 300 400 SUO O I 2 3 TIME (m see ) TIME (m ses) 1 SIMUL.TANEOUS PRESSURE TRACES IN WATER CANNON MODEL Expanded plots of selected waterhammer pressure reported by Block et al. (1977).

= Influence of Temperature Profile in Water Steam 2

x Water I

I I I I I 20 60 100 Temprature, *C (a) Typical Experimental Condition Steam 2

_-_ :A

/ water l l 4 a l l I I l 20 60 100 Temprature *C (b) Temperature Profile with Heat Addition RH980021.CDR 10-5-98 M -- e ,w

...-- - - - -. - -.- -.........~.... l 4 1 35 i y g l WATER CANNON MODEL METAL PIPE $ 30 z d i g i W l $ 25 / i I i w b o 20 w ) TOTAL NUMBER OF EVENTS

80 E IS n

a W i w to s 5 i O a I I I I I 'I I a i O 200 400 600 800 1000 1200 1400 1600 RANGE OF OVERPRESSURE MEASURED j SCATTER OF OVERPRESSURE DATA ) i l Histogram of the maximum measured waterhammer pressures for the Water { Cannon Experiment (Block et al.,1977). b i i l

d e 4 400 +,a 350 3Co 57.s* I E sr .o. ~R;-@ -~~ ee t zoo s. s e\\. e .e s i so ee s e e \\ .\\\\ .t *. ico e e e .re e i e ew 4 se e 5 So \\o = s \\N-a o 20 .to so so 100 Temperature ('C) Peak Steam Bubble Collapse Induced Pressure Measured in the Apparatus Shown at the Upper Right HVm1016F7-A}}

ML20207G313

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