ML20050P693
| ML20050P693 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 04/12/1982 |
| From: | Hodges M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20050N853 | List: |
| References | |
| ISSUANCES-OL, NUDOCS 8204140470 | |
| Download: ML20050P693 (6) | |
Text
e UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION L//l7L/3Z-BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
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LONG ISLAND LIGHTING COMPANY
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Docket Nos. 50-322
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(0L)
(ShorehamNuclearPowerStation,
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Unit 1)
)
NRC STAFF TESTitiONY OF MARVIN W.
(WAYNE) H0DGES REGARDING ECCS PUMP BLOCKAGE (Suffolk County Contention 9) 8204140470 820412 PDR ADOCK 05000322 l
1 OUTLINE OF TESTIMONY Suffolk County Contention 9 is concerned with the possibility that insulation loosened during a LOCA might block ECCS flow from the suppression pool. Witness Hodges refutes this contention by pointing out that the design for Shoreham ensures that insulation loosened during a LOCA will not degrade ECCS flow since the ECCS suction pipes include strainers and the downconer pipes are capped with jet deflectors.
Moreover, he points out that debris reaching the suppression pool would tend to settle on the bottom and would not be drawn into the pump suction.
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i UNITED STATES OF AMERICA NUCLEAR DEGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the fiatter of
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LONG ISLAND LIGHTING COMPANY
)
Docket Nos. 50-322
)
(0L)
(Shoreham Nuclear Power Station,
)
Unit 1)
)
NRC STAFF TESTIMONY OF MARVIN W.
(WAYNE) H0DGES ON SUFFOLK COUNTY CONTENTION 9 Q.
Please state your name and position with the NRC.
A.
My name is Marvin W. (Wayne) Hodges.
I am employed by the U.S. Nuclear Regulatory Commission as a Section Leader in the Reactor Systems Branch of the Division of Systems Integration. A copy of my 1
professional qualifications is attached.
Q.
What is the purpose of your testimony?
A.
The purpose of this testimony is to respond to Suffolk County Contention 9, which states:
Suffolk County contends that LILC0 has not adequately demonstrated that drywell piping and equipment insulation loosened and/or damaged during a postulated loss of coolant accident will not unduly degrade the ECCS flow through the ECCS suction strainers located in the suppression pool.
Therefore, the Shoreham design does not satisfy 10 C.F.R. 50, Appendix A, GDC 35.
Q.
Is the NRC investigating the problem of blocking of suction
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lines of ECCS generically?
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-2 A.
Yes. This is part of generic issue A-43 " Containment Emergency Sump Reliability." The NRC investigation has concentrated on PWR containment sumps and blockaaa of ECCS suction lines to those punps. The reason for this is that PWR sumps are more likely to have problems with debris than BWR suppression pools.
Q.
How does the Shoreham design ensure that insulation loosened during LOCA will not unduly degrade the ECCS flow through the ECCS suction strainers?
A.
The likelihood of any insulation being drawn into an emergency core cooling system pump suction line is very small. The potential debris in the drywell could only be swept into the suppression pool via the downcomer piping. However, the downcomer pipes (approximately two feet in diameter) are capped with jet deflectors and would prevent any large pieces from reaching the suppression pool. Any smaller pieces reaching the pool would tend to settle on the bottom and would not be drawn into the pump suction since it is located several feet above the pool bottom (about 8 ft. at SNPS-1).
In addition, SNPS-1 design employs strainers within the suction piping, and net positive suction head calculations for the pump are based on an assumed 50 percent blockage.
The strainer is designed to prevent introduction of objects greater than 0.125 in, diameter into the reactor vessel. Blockage of ECCS suction lines in BWR suppression pools is not considered to be a problem.
Q.
Would you please state your conclusion for this contention?
A.
Based upon the safeguards included in the Shoreham design, I see no basis for the Intervenor's contention that loosened insulation will
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. t degrade ECCS flow through ECCS suction strainers located in the suppression pool.
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Parvin k'. D a;. (? hNoes i
Professional Osalifications Reactor Systems Branch
_ Division of Systems Integration U. S. Nuclear Reoulatory Commission
- I am employed as a Section Leader in Section B of the Reactor Systems Branch, DSI.
I graduated from Auburn University with a Mechanical Engineering Degree in 1965.
I received a Master of Science degree in Mechanical Engineering from Auburn University in 1967.
In my present work assignment at the NRC, I supervise the work of 6 graduate engineers; my section is responsible for the review of primary and safety systems for BWRs.
I have ser,ved as principal reviewer in the area of boiling water reactor systems.
I have also participated in the review of analytical models use in the licensing evaluations of boiling water reactors and I have the technical revicu responsibility for nany of the codifications and analyses being impler.icnted on boiling water reactors post the Three Mile Island, Unit-2 accident.
As a camber of the Bulletin ard Orders Task Force which was formed after the 1MI-2 accident, I was responsible for the review of the capability of BWR
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systcms to cope with loss of feedwater transient and small break loss-of-coolant accidents.
s I have also served at the NRC as a reviewer in the Analysis Branch of the NRC in the area of thermal-hydrulic performance of the reactor core.
I served as a consultant to the RrS representative to the program management group for the EWR Bloudown/ Emergency Core Cooling Program.
Prior to joining the NRC staff in March, 3974, I tras employed by E. I. DuPont s
at the Savanr.ah River Laboratory as a research engineer.
At SRL, I conducted s hydraulic and heat transfer testing to support operation of the reactors at the Savannah River Plant.
1 also perforced safety limit calculations and participated in the developn.ent of analytical m?dels for use in transient ar.alyses at Savannah River.
My tenure at SRL was from June 1967 to March 1974.
from Septur.bar 1965 to June 1967, tehile in graduate school, I taught courses in therm 3dyr.amics, statics, nechanical engineering rr.easurements, conputer prograrr.ing and assisted in a course in the history of engineering.
During the surc.:.er of 1966, I worl:ed at the Savannah River Laboratory doing hydraulic testing.
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