ML20005H062

Requests Exemption from GDC 57 Requirement for Automatic, Locked Closed or Remote Manual Containment Isolation Valve in Recirculation Spray HX River Water Radiation Monitor Sample Lines

ML20005H062
Person / Time
Site:	Beaver Valley
Issue date:	01/11/1990
From:	Sieber J DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20005H058	List: ML20005H057 ML20005H062
References
NUDOCS 9001240094
Download: ML20005H062 (2)

Text

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G Beaver Vaticy Power Station Shippingport, PA 15077 0004

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a. wcmarGroup January 11, 1990 U. S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Application for Exemption from GDC-57 Gentlemen:

Duquesne Light Company hereby requests an exemption from General Design Criterion (GDC) 57 requirement for an automatic, or locked

closed, or remote manual containment isolation valve in the recirculation spray heat exchanger river water. radiation monitor sample lines.

(Reference UFSAR Figure 9.9-1A, penetrations 83, 84,-

85 and 86).

The existing plant configuration presents no adverse effects as a I

result of postulated accidents since flow of contaminated fluid through the sample line would require that a passive failure be assumed (recirculation spray heat exchanger tube-leak) in the short term following the initiating accident.

Assumption of this' type is

[

not within the BVPS-1 licensing basis for a

passive' failure in addition to design bases events.

A postulated tube failure presents no adverse effects in the long term since existing operating procedures contain provisions for shutdown of.the recirculation spray pump to stop any releases.

This removes the driving force for the tube leak since the containment is subatmospheric and provides time for isolation of the sample line as well.

operators to complete manual i

i Based on the

above, continued operation of the plant with the existing configuration will health and safety.

not present an undue risk to the public i

Special circumstances are present in that application of'GDC-57 in this particular case is not necessary to achieve the underlying purpose of the rule.

9001240094 900111 PDR ADOCK 05000334 9

P PDC l

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$ caver Valloy Pow 0r Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Page 2 k

The attachment represents our justification for continued operation during the interim period while the exemption request is being evaluated.

Please contact my office if additional information is required.

Very.truly yours,

$Ai D.

Sieber-Vice President Nuclear Group cc:

Mr.

J.

Beall, Sr. Resident Inspector Mr.

W. T.

Russell, NRC Region I Administrator Mr. P. Tam, Sr. Project Manager Mr. R. Saunders (VEPCO) i l

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,g UNITED STATES NUCLEAR REGULATORY COMMISSION g

l WASHING Tow, p. c. rosss May 2,1980 Docket flo. 50-334 LICEllSEE: Duquesne Light Company

SUBJECT:

MEETING

SUMMARY

- ECCS DECAY HEAT EXCHN!GER I$lTEGRITY FO BEAVER VALLEY UNIT N0. 1 On April 22, 1980, the licensee and Stone and Webster met with the Staff to discuss the consequences of failure and methods to assure integrity of the recirculation spray heat exchanger system for the Beaver Valley Unit No. 1.

The list of attendees is attached (Attachment 1).

-(

The licensee had previously met with the Staff on March 25, 1980.

The details of that meeting and background information are included in the meeting sucinary dated April 7,1980. This meeting was held to discuss the consequences of failure of the heat exchanger and components and methods to mitigate unacceptable consequences.

Discussion The consequence analysis performed-by Stone and Webster assumed the TID 14844 source term in the reactor containment sump and with the releases held to the 10 CFR 20 limits, the recirculation heat exchanger leak rate can be no more than 2 x 10-6 spm from the 3400 tubes in the four heat exchangers.

Assuming a dilution factor of 10 in the river, the doses in the drinking water at the Midland water intake would be as follows for one liter of water consumed:

Adult Thyroid Dose 190 mrem Child Thyroid Dose 583 mrem Infant -Thyroid Dose 1400 mrem The potential air borne dose would be.less than 10-2 mrem /hr at the site i

boundary when 2% evaporation rate is assumed in the cooling tower.

It is not clear that this accounts for potential iodine releases from the L

water as the sump leakage pH drops from 8 in' the sump to 7 in the cooling-l tower.

The significance of the dose calculations is that almost any l in the heat exchanger would produce unacceptable results.

The 2 x 10-*gakage leakage is for less than one tube breaking out of the 3400; it is something gpm just larger than a pin hole leak in a single abe.

4

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Meeting Sumary for l

Beaver Valley The licensee provided a basic infonnation sheet on the irecirculation heat exchangers which is attached (Attachment 2).

Stone and! Webster investigated l

the design for vibration damage between the tubes and tubes /baffel plates, i

Little potential exists for damage of this type.

The tubes are rolled into-a double grove in the tubesheets and seal welded so thart a high initial j

integrity can be assumed. The tubes, baffels, and tubesheets are all 304L stainless steel and operate in an environment which is mot expected to l

produce stress corrosion cracking or other modes of faimure.

While it is not apparent that the heat exchanger will deteriorate aind fail, there is no assurance against tube degradation and eventual failure over the 30-40 year life of the plant.

The licensee had hydrotested the heat exchanger during (construction and due to the containment isolation configuration, they had alsso performed a type C leak test on the tube side. No failures had beem detected by these To provide further assurance of integrity, the 111censee performed i

mea ns.

a freon test on the tube side.

Water was drained-from thoth the tube and shell side and about 10 to 20 lbs of freon at 70.psig was applied to the tubes. The test was allowed to " soak" for a period of ttime to allow any freon leak to accumulate on t with a sensitivity of 1 x 10 ge shell side. A portable

• detection instrument freon /cc of air did not (detect any leakage i

from the four heat exchangers.

The radiation monitors on the discharge river water sidte are' set for a sensitivity of 10-6 9 ci/cc with a background of 5 mremi/hr.

The licensee did not quantify the expected radiation levels in-the alrea'of the monitors following an accident although the largest souce of radi.iation is expected to be from the sample line from the failed heat exchangier (assuming an accident and a leaking recirculation spray heat exchangier).

The radiation monitors are seismic Class ! designed to the 198 ASME (Code.

The Hi-Hi-alarm setpoint is equivalent to 2.2 x 105 cpm which alsap corresponds to 10 CFR 20 limits.

The monitor pumps, flow indicators amd radiation detector /

circuitry are tested and calibrated periodically.

The river water piping, the bellows expansion joints, amd pressure relief j

valves were not tested during the freon tests by the liicensee. The river water piping is carbon steel.

A carbon steel to stainless stfeel transition joint is employed outside the heat exchanger on the inlet and. outlet lines.

Following a LOCA, it is not clear how a leak in the riv<er pipes or bellows l

l expansion joint inside containment would be detected ancd boron dilution of l

the sump prevented. The pressure relief valve outside containment on the river water discharge will relieve to the auxiliary buillding sump.

Water i

l discharge will be detected by the sump pump operation amd by area monitors in the auxiliary building.

Conclusions and Positions The licensee proposed an 18 month freon test of the hea4t c'xchangers tube side, as being adequate to detect leakage and assure integrity.

While the Staff

o Meeting Sumary for Beaver Valley.

believes the freon test to be highly sensitive to leaks and does provide adequate assurance of the existing Icak-tightness, it does not provide information on the required integrity for the subsequent periods of operation should the heat exchanger be called upon.

The test recently performed by the licensee and the fact that the heat exchangers are relatively young in life led the staff to conclude there is reacnnable assurance of continued IIRegri ty sGhat the Beaver Vallev Unit flo. I can be returned to 00 war _

{os iowing cne current outage without a tube degradation inspection.

The licensee was instructed to include a freon test at each refueling outage (normal 18 month cycle) to be preceded by a pneumatic or other presse test along the requirements of Section XI of. the ASME Code.

This test is expected to produce leaks that are about to occur and then be detected by the freon test.

The details of such a test are to be develooed bv the licensee and included in their Inservice Inspectinn Pennram before th'e '

second refueling outage.

~

~

The test for tube and tubesheet degradation is an open issue.

At some point in the heat exchanger life, the licensee must begin to examine for

• degradation to assure continued integrity should operation ever be required.

The licensee was instructed to consider means for testing for heat exchanger degradation including a schedule and basis for beginning such testing.

The type of test, basis for acceptance criteria, and schedule for periodic performance of the tests is to be developed by the licensee, submitted to the NRC for review, and subsequently included in the licensee's Inservice Inspection Program.

The Staff did not reach a position on the preferred normal condition of the heat exchanger. The licensee was requested to develop a position and provide a technical basis for draining and drying the he'at exchanger to include

- discussion of concentrating chlorine by drying and creating a water hamer problem by having a river water system charging to an empty heat exchanger.

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Dave Wigginton ject Manager Operating Reactors Branch #1 Division of Licensing Attachments:

1.

List of Attendees

2.. Heat Exchanger Spec Sheet cc: w/ attachments See next page

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'o r:cetir3 Stuaary f or Beaver Valley 1.

Docket files lac PDR Local PW

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0.461 Reading laR Readirev H. Denton E. Case D. Eisenhut R. Tedesco G. Zech B. - Grimes W. Gammill L. bhao J. Miller R. Volimer T. J. Carter A. Schwencer D. Ziemann P. Cileck G. Lainas

. D. Crutchfield

8. Grfraes T. Ippolito R. Reia V. itoonan G. Knighton D. brinkman Project Manager, OELO 018E (3)

C. Parrish/P. Kreutzer ACRS (16)

I<RC Participants NSIC TERA-Licensee Short Service List

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ATTACliMENT 1 DECAY HEAT EXCHA?lGER MEETING BEAVER VALLEY POWER STATION 1 APRIL 22, 1980 Name Organization D. Wigginton NRC D. Shum NRC J. D. Sieber DLC - Licensing K. D. Grada DLC-Operations P. C. Hearn NRC Frank H. Timpano VEPC0' R. E. Vanasse Stone and Webster C. E. Ader Stone and Webster R. C. Tappan Stone and Webster C. F. Andreone Stone and Webster-W. C. Drotleff Stone and Webster B. Turovlin NRC H. F. Conrad NRC J. E. Rosenthal NRC l

L. B. Engle NRC R. Woods NRC C. Y. Cheng NRC '

George Johnson NRC K. R. Wichman NRC J. Zudans NRC.

-Vince Noonan (part time)

NRC I

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UNITED STATES d,

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NUCLEAR REGULATORY COMMISSION a

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<f WASHINGTON, D. C. 20555 s., *...*/

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March 12,1981 e

Docket No. 50-334

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-i Mr. C. 'N. Dunn, Vice President Operations Division Duquesne Light Company 435 Sixth Avenue Pittsburgh, Pennsylvania 15219

Dear Mr. Dunn:

The NRC staff met with members of your staff and your architect-engineer of April 22, 1980, to discuss the-system integrity of the recirculation spray heat exchangers for Beaver Valley, Unit No.1.

As specified in-g the meeting summary dated May 2,1980, Duquesne Light Company agreed to-conduct a freon test at tach refuelinc outaae (normal la =^ath eyrie)-to V

/ 6e preceded by a pneumatic or other practurn teet alnna tha vanuirementt

/

or section XI of the ASME Code. The details of such a te5Lare to be. __

avveivpeu oy sne i1censee, ana T6cluded in their Inservice Inspection Program Deforei_ Loc jwco. v_. a uwi ing outage.

It is requested that you prepose a change to your Inservice Inspection-Program-to satisfy ~this requiremint.

Sj erely 'p Y

Ok iS'tevenA.6 cN

Varga, ef Operating Reactors ranch #1-Division of Licensing cc: See next page f

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Mr. C. N. Dunn Duquesne Light Conpany cc: Gerald Charnoff, Esquire Mr. James A. Werling Jay E. Silberg, Esquire Plant Superintendent Shaw, Pittr:sn. Potts and Trowbridge Beaver Valley Power Station 1800 M Street, N.W.

P. O. Box 4 Washington, D. C.

20036 Shippingport, Pennsylvania 15077 Kartn Carter, Esquire Mr. John A. Levin Special Assistant Attorney General Public Utility Comission l

Bureau of Administrative Enforcement P. O. Box 3265 5th Floor. Executive House l

Harrisburg, Pennsylvania 17120_

Harrisburg, Pennsylvania 17120 Mr. J. D. Sieber, Superintendent Mr. Roger Tapan of Licensing and Compliance Stone and Webster Engineering Duquesne Light Conpany Corporation Post Office Box 4 P. O. Box 2325 Shippingport, Pennsylvania 15077 Boston, Massachusetts 02107 Irwin A. Popowsky, Esquire Mr. F. Noon Office of Consumer Advocate R & D Center 1425 Strawberry Square Westinghouse Electric Corporation Harrisburg, Pennsylvania 17120 l

Building 7-303 Pittsburgh, Pennsylvania 15230 Mr. Charles E. Thomas, Esquire Thomas and Thomas B. F. Jones Memorial Library 212 Locust Street 663 Franklin Avenue Box 999

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Aliquippa, Pennsylvania 15001 Harrisburg, Pennsylvania 17108 Mr. John Carey, Director Resident Inspector Nuclear Operations V. S. Nuclear Regulatory Comission Duquesne Light Cogany Post Office Box 298 435 Sixth Avenue

.Shippingport, Pennsylvania 15077 Pittsburgh, Pennsylvania 15219 l

Mr. R. E. Martin Duquesne Light Conpany 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 Marvin Fein Utility Counsel City of Pittsburgh 313 City-County Building Pittsburgh, Pennsylvania 15219 e

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• c %'o, UNITED STATES

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g NUCLEAR REGULATORY COMMISSION e'

g WAsW NG TON. D. C. 20555 n

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March 12,1981 Docket No. 50-334 Mr. C.

'N. Dunn, Vice President Operations Division Duquesne Light. Company 435 Sixth Avenue Pittsburgh, Pennsylvania 15219

Dear Mr. Dunn:

The NRC staff met with members of your staff and your architect-engineer of April 22, 1980, to discuss the system integrity of the recirculation spray heat exchangers for Beaver Valley, Unit No.1.

As specified in the meeting summary dated May 2,1980, Duquesne Light Company agreed to conduct a freon test at each refueling outage (normal 18 month cycle) to be preceded by a pneumatic or other pressure test along the requirements of Section XI of the ASME Code. The details of such a test are to be developed by the licensee and included in their Inservice Inspection c

Program before the second refueling outage.

It is requested that you prcpose a change to your Inservice Inspection -

Program to satisfy 'this requirem nt.

S,j erely

<S'teven A. G >C % arga, cN V

, 'ef Operating ~ Reactors oranch #1 Division of Licensing cc: See next page i

~?!c'MoS?& app'

','Mr. C. N. Dunn.

Duquesne Light Corpany cc: Gerald Charnoff, Esquire Mr. Janes A. Werling Jay E. Silberg, Esquire Plant Superintendent Shaw, Pittran, Potts and Trowbridge Beaver Valley Power Station 1800 M Street, N.W.

P. O. Box 4 t

Washington, D. C.

20036 Shippingport, Pennsylvania 15077 Karin Carter, Esquire Mr. John A. Levin Special Assistant Attorney General Public Utility Commission Bureau of Administrative Enforcement P. O. Box 3265 5th Floor, Executive House Harrisburg, Pennsylvania 17120 Harrisburg, Pennsylvania 17120 Mr. J. D. Sieber,' Superintendent Mr. Roger Tapan of Licensing and Compliance

.t Stone and Webster Engineering Daquesne Light Corpany Corporation Post Office Box 4 P. O. Box 2325 Shippingport, Pennsylvania 15077 Boston, Massachusetts 02107 Irwin A. Popowsky, Esquire Mr. F. Noon,

Office of Consumer Advocate R & D Center 1425 Strawberry Square Westinghouse Electric Corporation Harrisburg, Pennsylvania 17120 Building 7-303 Pittsburgh, Pennsylvania 15230 Mr. Charles E. Thomas, Esquire Thoaas and Thomas B. F. Jones Memorial Library 212 Locust Street-663 Franklin Avenus Box 999 Aliquippa, Pennsylvania 15001 Harrisburg, Pennsylvania 17108 L

Mr. John Carey, Director Resident Inspector Nuclear 0perations U. S. Nuclear Regulatory Commission Duquesne Light Coapany Post Office Box 298 435 Sixth Avenue Shippingport, Pennsylvania 15077 Pittsburgh, Pennsyl vania 15219 Mr. R. E. Martin Duquesne Light Company 425 Sixth Avenue j

Pittsburgh, Pennsylvania 15219 Marvin Fein Utility Counsel City of Pittsburgh 313 City-Crunty Building Pittsburgh, Pennsylvania 15219 8

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