ML20133P485

Ltr Contract,To Task Order 2, Assessment of Debris Accumulation on PWR Sump Performance, Under Contract NRC-04-97-036

ML20133P485
Person / Time
Issue date:	01/08/1996
From:	Mearse S NRC OFFICE OF ADMINISTRATION (ADM)
To:	Colina I SCIENCE & ENGINEERING ASSOCIATES, INC.
References
CON-FIN-W-6650, CON-NRC-04-97-036, CON-NRC-4-97-36 NUDOCS 9701240273
Download: ML20133P485 (6)

Text

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[-, . ,8% UNITED STATES j

l NUCLEAR REGULATORY COMMISSION

{f & WASHINGTON, D.C. 20a55 0001 o%..o. */ January 2, 1997 Science and-Engineering Associates. Inc.  !

Attn: Ilene R. Colina Contract Administrator '

6100 Upton B1vd., NE Albuquerque. New Mexico 87110

Subject:

Task Order No. 2, Entitled " Assessment of Debris Accumulation on PWR i Sump Performance," Under Contract No. NRC-04-97-036 l In accordance with Section G.4(c), of the subject contract, this letter ,

definitizes the subject task order. This effort shall be performed in accordance with the enclosed Statement of Work and the contractor's technical proposal dated December 5, 1996, which is hereby incorporated by reference and made a part of the subject task order.

' Task Order No. 2 shall be in effect from January 2,1997 through July 1,1997, with a ceiling amount of $69,430.00. The amount of $64,442.00 represents the total estimated reimbursable costs and the amount of $4.988.00 represents the fixed fee.

The obligated amount of this task order shall at no time exceed the task order ceiling. When and if the amount (s) paid and Jayable to the Contractor -

hereunder shall equal the obligated amount, tie contractor shall not be obligated to continue performance of the work unless and until the Contracting Officer shall increase the amount obligated with res3ect to this task order.

Any work undertaken by the Contractor in excess of tie obligated amount specified below is done so at the Contractor's sole risk.

The amount currently obligated by the Government with respect to this task i

. order is $64,000.00, of which the sum of $59.480.00 represents the estimated l reimbursable costs, and of which $4.520.00 represents the fixed fee. It is estimated that the amount currently allotted will cover performance through June 16. 1997.

Accounting Data for Task Order No. 2 is as follows: -

L RES C97-318 Commitment No:  ;

l APPN No: 31X0200.760 l l

B&R No: 76015115050 '

{

i JOB CODE:

BOC No:

W6650 252A h)e1)6 Obligated Amount: $64,000.00

The following individual is considered to be essential to the successful performance of work hereunder:

! Dr. V. Rao (y RI) 1 9701240273 960108 PDR CONTR NRC-04-97-036 PDR

l i

l NRC-04-97-036 Tast Order No. 2 Page 2 of 2 l The Contracter aarr , that key personnel shall not be removed from the task i order effort w dnout compliance with Contract Clause H.3, " Key Personnel."

Your contacts during the course of this task order are:

Technical Matters: Michael Marshall (301) 415-5895 l Contractual Matters: Sharon Mearse (301) 415-6591

! The issuance of this task order does not amend any terms or cor.ditions of the subject contract.

Please indicate your acceptance of Task Order No. 2 by having an official, authorized to bind your organization, execute three copies of this document in the space provided and return two copies to the Contracting Officer. You

should retain the third copy for your records.

l If you have any questions regarding this matter, please contact me on

! 301/415-6591.

Sincerg, ,

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u.,,- J -

[

.horon D. Mearse Contracting Officer Technical Acquisition Branch No. 1 Division of Contracts Office of Administration l

l

Enclosure:

l As stated l

ACCEPTED:

\ W k au NAME l

'LU TITLE

,/rNo DATE l

l l

Task Order 002

" Assessment of Debris Accumulation on Pressurized Water Reactors Sump Performance" I of NRC Contract NRC-04-97-036

" Technical Assistance in Resolving Generic Safety issues "

I (FIN No. W6650)

BACKGROUND l

The United States Nuclear Regulatory Commission (NRC) first addressed the concem with pressurized water reactor (PWR) sump performance as part of the resolution of unresolved safety issue (USI) A-43, " Containment Emergency Sump Performance." The resolution was l published in 1985 (Refs. 6,13, and 15). The USl A-43 evaluation and resolution focused l primely on PWRs, but its results were considered applicable to boiling water reactors (BWRs).

After several suction strainer debris blockage events at BWRs, in 1993, the NRC initiated I reevaluation of the potential of loss-of-coolant accident (LOCA) generated debris to block BWR suction strainers and prevent the emergency cose cooling system (ECCS) from performing its long-term cooling function. The study (see Ref. 20) concluded that debris during a LOCA may prevent the ECCS from performing its long-term cooling function. Light water reactor licensees

! are required to ensure long-term cooling to the reactor core in accordance with Code of Federal l Regulations (CFR), specifically 10 CFR 50.46 " Acceptance Criteria for Emergency Core Cooling l Systems for Light Water Nuclear Power Reactors." Based on the study and operational events, the NRC will request (see Refs. 9 and 14) that licensees evaluate their plants and, if necessary, make changes to their plants to prevent any detrimental efiacts from debris blockages.

In light of the resolution of S-081, "Poter wl for Loss of Emergency Cooling in BWR Due to LOCA Generated Debris," (i.e., the BW". :,uction strainer blockage issue) the NRC has decided l

to reassess debris blockage of PWR sumps to determine if there is a need for further actions to be taken for PWRs beyond the original resolution of USI A-43.

OBJECTIVES The objectives of this reevaluation are to (1) assess the adequacy of the technical basis of the USl A-43 resolution and (2) assess adequacy of regulatory guide 1.82, Rev.1 guidance conceming debris blockage of PWR sumps.

l SCOPE OF WORK e Identify and review the physical features of the plant, aspects of the postulated LOCA, calculations, and assumptions used in the technical basis of the resolution of USl A-43.

• Identify information or models used in the USl A-43 evaluation that are obsolete.

e Identify and review the debris sources in PWRs (esp. particulate debris sources).

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• Identify and review differences between PWR and BWR guidance.

e Review issues concoming sump blockage raised by Swedish Nuclear Power inspectorate and Finnish Centre for Radiation and Nuclear Safety.

e The reevaluation should consider the major containment types (i.e., large dry, sub-atmospheric, ice condenser).

e The probabilistic aspect of USI A-43 should not be included in the reevaluation.

REPORTING REQUIREMENTS No additional reporting requirement beyond those already agreed to in NRC contract NRC i 97-036.

l DELIVERABLES AND DELIVERY SCHEDULE l 1. An interim letter report shall be submitted to the NRC Project Officer (PO) and NRC l Technical Monitor (TM) three months after the effective date of this task.

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2. A draft report shall be submitted to the NRC PO and TM five months after the effective date of this task. A final, camera-ready report shall be submitted to the NRC PO and TM 30-days after receipt of NRC PO's and TM's comments on the draft report. The format l

of the final report shall meet the design specifications for NUREG/CR reports.

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! MEETING AND TRAVEL REQUIREMENTS All travel shall be approved by and coordinated with the NRC PO or TM. Allowances should be l made for the following trips:

1. Two two-days, two-people trip to NRC headquarters from contractor site to discuss results of reevaluation.

2. One one-day, two-people trip to NRC headquarters from contractor site to participate in intemal NRC review of reevaluation.

ESTIMATED LEVEL OF EFFORT l

The estimated level of effort for this task is 620 people-hours.

PERIOD OF PERFORM ANCE The period of performance for this task is 6 months from the effective date of the task order.

TECHNICAL DIRECTION Technical direction will be provided by Michael Marshall. Mr. Marshall can be reached at (301) 415-5895 (voice), (301) 415-5062 (fax), and mxm2@nrc. gov (email).

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REFERENCES AND BIBLIOGRAPHY

1. Knowledge Base for Emeroency Core Coolina System Recirculation Reliability.

NEA/CSNI/R(95)11, Organization for Economec Cooperation and Development, Nuclear Energy Agency, France, February 1996. (Restricted)

2. Snnckman, K., Resuhs of Hydraulic Tests on ECCS Strainer Blockaae and Material Transoort in a BWet Sucoression Pool. EC-059-1006, Pennsylvania Power & Light Company, Allentown, PA, May 1994.

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! 3. Brocard, D., Buovancv. Transoort. and Hand Loss of Fibrous Reactor Insulation.

NUREGICR-2982, (SAND 82-7205, Sandse National Laboratories), U. S. Nuclear Regulatory Commission, Washington, DC, July 1983.'

4. Durgin, W. and Noreika, J., The Sume=MMi*v of Fibrous Insulation oillows to Debris Formation Under Exposure to Eneraetic Jet Flows. (SAND 83-7008, Sandia National Laboratories), U. S. Nuclear Regulatory Commission, Washington, DC, March 1983.'

5. Fredell, J., Karshamn Tests 1992: Steam Blast on insulated Obiects. Loabook. RVE 92-202, ABB Atom, November 1992.

6. Generic Letter 85-22, " Potential for Loss of Post-LOCA Recirculation Capability Due to insulation Debris Blockage," U. S. Nuclear Regulatory Commission, Washington, DC, December 1985.2

7. Hallstrom, B., Guaranteed Emeraency Core and Containment Coolina. Laboratory Exoeriments Concemina insulation. RVD 92-192, ABB Atom, November 1992.

8. Kamath, P., et. al., An Assessment of Residual Heat Removal and Containment Sorav

! Pumo Performance Under Air and Debris Inaestina Conditions. NUREG/CR-2792, (CREARE TM-825, Creare, inc), U. S. Nuclear Regulatory Commission, Washington, DC, September 1982.'

9. NRC Bulletin 96-03, " Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling Water Reactors," U. S. Nuclear Regulatory Commission, Washington, DC, May 1996.8

10. Padmanabhan, M., Hydraulic Performance of Performance of Pumo Suction inlets for Emeroency Core Coolina Systems in Boilina Water Reactors. NUREG/CR-2772, (ARL-398A, Alden Research Laboratory), U. S. Nuclear Regulatory Commission, Washington, DC, June 1982.'

11. Persson, B., Downward Transoort and Sedimentation of Insulation Material and the 8

Thi. er w p.1 a e,. i.chn,cw t a m. . aui,on a usi us.

2 Thi. +, cum i. p i a ou,on a usi us.

Thi. docum.nt 1. p.et a th. no.clution a S41.

3 arvsowis.TxT October 25,1996

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Build-Up of Pressure Loss in the Suction Filters. OKG, Sweden, March 1992.

12. Rao, D. and Souto, F., Exoerimental Study of Head Loss and Filtration for LOCA Debris.

NUREG/CR-6367, (SEA 95-554-06-A:8, Science and Engineering Associates, Inc.), U.

j S. Nuclear Regulatory Commission, Washington, DC, February 1990.d

13. Regulatory Guide 1.82, Rev.1, " Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident," U. S. Nuclear Regulatory Commission, Washington, DC, November 1985.2

14. Regulatory Guide 1.82, Rev. 2,'" Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident," U. S. Nuclear Regulatory Commission, Washington, DC, May 19%.8

, 15. Serkiz, A., USl A-43 Reaulatory Analysis. NUREG-0869, Rev.1, U. S. Nuclear Regulatory Commission, Washington, DC, October 1985.'

16. Souto, F. and Rao, D., Experimental Investiaation of Sedimentation of LOCA-Generated Fibrous Debris and Studae in BWR Sucoression Pools. NUREG/CR-6368, (SEA 95 554-4 06-A

8, Science and Engineering Associates, Inc.), U. S. Nuclear Regulatory Commission, Washington, DC, December 1995.d l 17. Wysocia, J. and Kolbe, R., Methodoloav for Evaluation of insulation Debris Effects.

NUREG/CR-2791, (SAND 82-7067, Sandia National Laboratories), U. S. Nuclear Regulatory Commission, Washington, DC, September 1982.

18. Wysocki, J., Probabilistic Assessment of Recirculation Sumo Blockaae Due to Loss of Coolant Accidents, NUREG/CR-3394, (SAND 83-7116, Sandia National Laboratories), U.

S. Nuclear Regulatory Commission, Washington, DC, July 1983.'

, 19. Zigler, G, (ed), Exoerimental Investiaation of Head Loss and Sedimentation i Characterist:cs of Reflective Metallic Insulation Debris. SEA No. 95-970-01-A:2, Science

. and Engineering Associates, Inc., Albuquerque, NM, May 1996.'

l 20. Zigter, Beaty, et. al., Parametric Study of the Potential for BWR ECCS Strainer Blockaae Due to LOCA Generated Debris. NUREG/CR-6224, (SEA No. 93-554-06-A:1, Science and Engineering Associates, Inc.), U. S. Nuclear Regulatory Commission, Washington '

DC, October 1995.'

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Th,e doeurnent is part of sta lectwiecal bous of the resolution of S481.

october 25.1996 4 RFPSOW15 TXT I

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