ML20035C665

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Summary of 930317 Meeting W/Bwrog in Charlotte,Nc Re Ongoing Testing & to Discuss Staff Concerns About Test Program Which Were Forwarded to BWROG by Ltr .List of Attendees,Slides Used & Summary of Issues Discussed Encl
ML20035C665
Person / Time
Issue date: 03/30/1993
From: Amy Cubbage
Office of Nuclear Reactor Regulation
To: Rosalyn Jones
Office of Nuclear Reactor Regulation
References
NUDOCS 9304080270
Download: ML20035C665 (54)
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Text

m March 30,1993 MEMORANDUM.FOR:

Robert C. Junes, Chief Reactor Systems Branch Division of Systems Safety and Analysis THRU:

Timothy E. Collins, Chief BWR Reactor Systems Section Reactor Systems Branch Division of Systems Safety and Analysis FROM:

Amy E. Cubbage, Reactor Systems Engineer BWR Reactor Systems Section Reactor Systems Branch Division of Systems Safety and Analysis

SUBJECT:

MEETING

SUMMARY

FROM BWROG MEETING A meeting was held with the 3WR Owners' Group (BWROG) on March 17, 1993, at the EPRI NDE facility in Charlotte, North Carolina. The BWROG is conducting a reference leg de-gas test at this facility. The purpose of the meeting was to observe the ongoing testing and to discuss staff concerns about the test program which were forwarded to the BWROG by 1

letter dated March 4,1993 from W. T. Russell, NRC, to George Beck, BWROG. The list of attendees is provided in Enclosure 1, a copy of the slides used by the BWROG during.the meeting is provided in Enclosure 2, and a summary of the issues discussed is provided below.

The BWROG provided a brief overview of the BWROG program, and reviewed the actions that have been taken to date to address the issue of-potential errors in water level instrumentation due to non-condentible gases. They proceeded to describe the test.

I program, including the full-scale reference leg de-gas test and bench top testing. The purpose of the benchtop testing is to evaluate the effect of the following parameters on de-gassing: (1) reference leg material; (2) reference leg diameter; (3) reference leg slope; (4) temperature; and (5) vibration.

The reference leg de-gas test procedure and test matrix were described to the. staff. At a meeting on February, 17, 1993, the BWROG discussed their test plan and the 6 reference leg configurations that were to be tested.

In a letter dated March 4,1993 to the BWROG, the staff expressed concerns that the test program should include configurations more similar in geometry and reference leg diameter to those found in actual plants. The BWROG is i

considering including reference leg configurations more indicative of actual plaat.

configurations. At this time the test matrix includes two depressurization rates, one simulates the large break LOCA depressurization rate, and the other simulates the rate.of - g depressurization for ADS actuation. After this discussion, the staff was given a tour of the reference leg de-gas test facility. During this_ tour, the staff observed the ongoing-p;'

testing.

/.

Next, the BWROG discussed the activities cf the reactor water level measurement modifications and procedures committee to evaluate potential modifications to the reac or water level instrumentation system. Three potential modifications were identified by the N b g' @ )-

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committee which do not require the condensing chamber test for verification or validation, these are: (1) condensing chanber vent; (2) backfill systems; and (3) core range j

monitoring (a design in which the variable leg of the narrow range is used for the -

reference leg af the fuel zone range). Five other modifications were also discussed which would require the condensing chamber test for verification and validation. All of these i

potential modifications involved different designs of the condensing chamber.

At the end of their formal presentation, the BWROG addressed staff concerns discussed in the March 4, 1993 letter. The staff re-emphasized its position that 1/2 inch tubing, and more complex configurations need to be included in the full-scale reference leg de-gas i

test plan.

l 1

The staff noted that level instrumentation is important for BWRs, and enough evidence exists today to say that the reliability of the instrumentation needs to be improved.

i Further, an event occurred recently at WNP-2, during a slow plant depressurization, involving both level indication " notching" and a sustained level indication error of significant magnitude. While the staff believes that the test program is good scientific work that will lead to a better understanding of the phenomenon, the objective of the i

program is not sufficiently oriented toward testing-the effectiveness of hardware j

modifications. Therefore the staff re-iterated its belief that modifications will be a

needed to improve the functional reliability of the water level instrumentation.

i In addition, as a result of the WNP-2 event, the staff discussed the need for the BWROG program to include potential level errors during slow depressurization. The staff requested that the BWROG supplement their August 28, 1992 report, which evaluated the

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safety implicaticus of potential level indication errors, to include events that initiate at a low reactor pressure. Finally, the staff expressed its expectation that all BWR utilities will provide a response, by July 30, 1993, informing the NRC of their plans and schedule for hardware modifications.

j M

Amy E. Cubbage, Reactor Systems Engineer 1

BWR Reactor Systems Section j

Reactor Systems Branch i

Division of Systems Safety and Analysis j

Enclosures:

As stated i

cc w/ enclosure:

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E. Hadley j

DISTRIBUTION: w/o closures Central Filesk PDR AThadani SRXB R/F RJones~

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TCollins JClifford (13E-!6)

REaton (14D-1)

GKelly (Region 1)

JLee (9A-2)

ACubbage ACubbage R/F-OFFICIAL RECORD COPY Document Name: G:mtgsum03.17 f

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ENCLOSURE 1 MEETING ATTENDEES NAME' AFFILIATION TELEPHONE A. Thadani NRC/DSSA 301-504-2884 R. Jones

.NRC/SRXB 301-504-2895 T. Collins HRC

-301-504-2897 A. Cubbage NRC 301-504-2875-G. Beck PEC0/BWROG 215-64026450-G. Stramback GE 408-925-1913-G. Sealy PEC0/BWROG 215-327-1200 ext. 3551 B. McKillip Continuum Dynamics 609-734-9282-A. Kaufman Continuum Dynamics 609-734-9282 D. Weber PEC0/BWROG 215-892-3918-T. Best CEC 0/BWROG

-708-663-7447 J. Wade SNC/BWROG' 205-877-7408 J. Morgan GSU/BWROG-504-38124228 J. Henchausen EPRI 704-547-6058 T. Mulford EPRI/PSE 704-547-6087 S. Wood WPPSS/BWROG 509-377-4797 T. Green GE-408-925-1308-T. Miles WPPSS/BWROG 509-337-4632

-M.

Monson WPPSS/BWR03

.509-377-4536 J. Refling PP&L/BWROG 215-774-7717-J. Moore GPUN/BWROG 201-316-7057-

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BWR OWNERS' GROUP 4

i Meeting and Te.st Facility Tour with NRC On Reactor Water Level instrumentation

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1 BWR Owners' Group Reactor Water Level Instrumentation Agenda I ntrod u ctio n.........................................G. J. Beck (P ECo)

Committee Chairman P ro g ra m Pla n.......................................T. G. B est (C ECo)

Steering Committee Chairman Test Configuration..............................J. W. Morgan (GSU)

Model & Test Committee Chairman Bench Top Testing............................. A. E. Kaufman (CDI)

Test Conductor De-Gas Testin g....................................R. McKillip (CDI)

Test Conductor Modifications.......................................J. A. Wade (SNC)

Modifications & Procedures Committee Chairman Review NRC March 5,19.93 Letter......J. W. Morgan (GSU)

Model & Test Committee Chairman Tour De-Gas Facility /.

Test Observation Discussion Period s

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1 Rapid RPV Depressurization Postulated to Affect Non-Condensable Gases in Water Level

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Reactor Water Level Instrumentation History February 1992 NRC Requests Report on. Water Level Indication n ; July 1992 Information Notice No. 92-54

...the staff is concerned; that non-condensable gases may become

- dissolved in the reference. leg of BWR' water level instrumentation and can lead to a. false.high level indication after a rapid depressuritation event."

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July 1992 BWROG/RRG Meeting with NRC ~

Mr. Russell::"...The meeting' today is to review the actions that have

-been taken or are proposed by the BWR Owners' Regulatory Resp _onse

. Group _-tol address staff concerns with respect to reliability of reactor.

. vessel water level indication under rapid depressurization."

August 1992 BWROG Submits Generic Report n September 1992 BWR. Utilities Submit GL 92-04 Response October 1992 BWROG Technical Meeting with NRC.

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'l' History (continued) n November 13,1992 BWROG Operator Guidance entitled " Determination of RPV Water Level following a Rapid RPV Depressurization" December 1992 NRC Revises Modifications implementation-January 1993 L

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BWR Owners' Group Reactor Water Level Instrumentation De-Gas Test:

  • A full-scale depressurization of cold reference leg geometries filled with water solutions containing non-condensable gas in known concentrations Test Configurations:
  • Obtained information regarding actual plant geometries and reduced the data to determine boundary conditions
  • Plant geometries normalized by. cumulative volume / total volume versus cumulative height / total height
  • Six (6) geometries selected to bound data
  • Added Benchtop testing to determine other important geometric parameters

-- Materials

- Piping Diameter

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- Quantify Temperature Effects:

- Vibration

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c BWR Owners' Group Reactor Water Level Instrumentation n Benchtop Test Objectives

= Demonstrate that single dissolved gas comes out of solution in time scales ti/pical of a H and O mixture.

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- VibrationL

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  • Purpose

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  • Orientation

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  • Results

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- Current program will. check horizontal orientation

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BWR-Owners' Group Reactor Water Level Instrumentation Test - Temperature Purpose

- Determine if de-gassing rate is temperature sensitiva Apparatus

- 1" ID nominally 3' long stainless steel pipe -

Orientation

=

- Vertical Starting pressure -

- ~ 735 psig

  • - Result

- Heating speeds up de-gassing rate in vertical legs. However, de-gassing is rapid compared to blowdown' time and little change in level error is.. expected.

Also, 'only several1 feet of:

the.line. are iat. unknown elevated temperatures.

Note' that' initial depressurization will bring:up cold ' water'from below partially mitigating this effect.

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Time Preliminary Information 93240001.18 27

BWR Owners' Group Reactor Water Level Instrumentation Remaining Tests Notching

--Smaller diameter. horizontal leg

- Elbow in horizontal leg Benchtop De-Gas

- Horizontal tubing

- Lower initial pressure data

- Vibration

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- BWR Owners' Group Reactor Water Level Instrumentation Conclusions i

  • No observed difference between carbon steel and stainless for 1000 psig depressurization using O as dissolved gas 2
  • A stoichiometric mixture of H and O de-gasses. from 1000 2

2 psig slightly faster than O alone. The LEER code can be used 2

-to correct the data for this difference.

O then is the best 2

selection for the gas to be dissolved in solution

  • From. higher pressures, small tubes do not de-gas more quickly than larger diameter tubes.
  • Horizontal one-inch.lD pipe de-gasses much more slowly than vertical pipe from high pressure
  • Notching - slope and geometry dependent-

_~ _ --

93240001.18 31

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Outline Shakedown Testing Results Test Procedures Test Observations Configuration 1 Matrix 32 93240001.18

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Shakedown Testing Results l

Pre-mixed gas + water solutions may be made to reach equilibrium

.quickly, provided sufficient wave motion is set up in mixing tank End

-point pressure control has been demonstrated through solenoid-operated valve actuation Differential pressure cell requires correction for I

static

" head" of N2 gas when system is at pressure

. Dissolved gas measurement is simplified with volumetric displacement technique

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Test Procedures Separated into functional groups:

> configuration measurement

> pre-mixed solution preparation

> de-min water injection

> system pressurization

> pre-mixed solution injection

> solution sampling

> final injection and pressurization

> rapid depressurization

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Test Observations Strong influence of end-point pressure and depressurization rate on reference leg level error-Repeatability has been demonstrated in final level and time history of DP cell-Orifice sizing;has produced LOCA and ATWS-ADS type of depressurization time histories

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REACTOR WATER LEVEL MEASUREMENT '

MODIFICATIONS AND PROCEDURES COMM11 IEE (MAPC) '

March 17,1993 t

CATEGORY l

t.t MODIRCATIONS THAT DO NOT REQUIRE CONDENSING CHAMBER TESTFOR VALIDATION /VERIMCATION 4

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.I MODIRCATIONS THAT DO REQUIRE CONDENSING CHAMBER TEST FOR VALIDATION /VERIRCATION -'

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REACTORWATER LEVEL MEASUREMENT MODIFICATIONS AND PROCEDURES COMMITTEE (MAPC)

March 17,1993 PROPOSED MODIFICATIONS i

MODIFICATIONS THAT DO NOT REQUIRE CONDENSING CHAMBER TEST FORVALIDATION/ VERIFICATION t

I DESCRIPTION CONDENSING CHAMBER VENT BACKFILLSYSTEMS f

l CORERANGEMONITORING i

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MODIFICATIONS AND PROCEDURES COMMIITEE (MAPC) l March 17.1993 l

i PROPOSED MODIFICATIONS t

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MODIFICATIONS TIIAT DO REQUIRE CONDENSING CHAMBER TEST FOR VALIDATION /VERIECATION DESCRIPTION j

l 1

l ABB TYFE CONDENSING CHAMBER l

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BWR Owners' Group Reactor Water Level Instrumentation n Review of Issues from NRC March 5,

1993 Letter (AIIIssues Already Being Addressed by BWROG)

Issue Addressed Where Enclosure 1)

Plant Piping Diameters Benchtop Testing 2)

Multiple Test Gasses Benchtop Testing and Two Gasses in De-Gas Test 3)

Pipe Test Configurations De-Gas Test and Analytical Model 4)

Temperature Relationship Benchtop Test I

5)

Plant-specific Observations Committee Reviewing with Utility i

Personnel

. Letter A)

Benchtop Test Information Benchtop Testing B)

Modifications Modifications-C)

Response to NRC Letter-BWROG Response

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  • BWR Owners' Group Reactor Water Level Instrumentation 6

Tour of De-Gas Facility / Test Observation.

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BWR Owners' Group Reactor Water Level Instrumentation Discussion

~_

-93240001.18 51

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