ML19344F213
| ML19344F213 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire |
| Issue date: | 08/26/1980 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Parker W DUKE POWER CO. |
| References | |
| NUDOCS 8009120623 | |
| Download: ML19344F213 (6) | |
Text
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION g.
.E WASHINGTON, D. C. 20555
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AUG 2 61c80 Cocket Nos.:
50-369 and 50-370 Duke Power Company ATTN: Mr. William O. Parker, Jr.
Vice President - Steam Production Post Office Box 33189 422 South Church Street Charlotte, North Carolina 28242
Dear Mr. Parker:
Subject:
Containment Emergency Sump Debris (Post-LOCA)
(McGuire Nuclear Station, Units 1 and 2)
As a result of our review of you; application we find that we are in need of some specific information regarding the containment emergency sump performance under post-LOCA conditions. This information is described in the Enclosure. Our consu'. tant, Burns and Roe, previously obtained information from you on this matter which is also being used in our evaluation.
We request that you provide this information no later than September 3,1980.
Sincerely, Robert L. Tedesco, Assistant Director for Licensing Division of Licensing
Enclosure:
As stated cc: See next page 8009220 Q 3
c.
v REACTOR SYSTEMS BRANCH 210.1 The safety issues of containment emergency sump performance under post [0bAconditionscanbeviewedastwoparts:
(1) containment l
sump hydraulic performance (i.e., providing adequate NPSH) to the recirculation pumps'with up to.50 percent of the screen area blocked) and (2) the effects ;f debris. The first part, sump hydraulic performance, i
has previously been addressed in the McGuire plant, and has been acceptably resolved. The problem addressed herein is the potential for debris from insulation and other sources within contaitment to collect and compromise the ability of the ECCS to' recirculate coolant from the g
containment sump through the RHR heat exchangers to the vessel.
Information on insulation debris for McGuire has already been supplied; the following additional information is requested.
For items that have been previously resolved, you may respond by referring to the previous documentation. The following items must be resolved prior to full power operaticn.
j 1.
In a'ddition t'o insulation debris resulting from LOCA effects, t
debris can be generated within the containment from other sources, i
suc h as (1) degraded materials (paint chips), and (2) items which are taken into and left in the containment following maintenance and inspecti:n activities.
Describe how the housekeepi.ng program for McGuire will control and l
limit debris accumulation from these sources. The objectives are to o
assure that debris capable of defeating the post-LOCA core cooling l
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. functions are identified and removed from the containment. The responsbshouldincludereferencestospecificproceduresorother means to assure that "as licensed" cleanliness will be attained prior to initial operation and prior to each resumption of operation.
2.
Addressthedegreeofcomp}ianceofMcGuirewiththefollowingrecommendations-st which is also set forth as item C.14 of Regulatory Guide 1.82:
"In-service inspection requirements for coolant pump components (trash racks, screens, and pump suction inlets) should include the following:
s a.
Coolant sump components should be inspected during every refueling period downtime, and b.
The inspection sould be a visual examination of the components for evidence of structural distress or corrosion."
3.
The resolution of the concerns noted below plus the provisions of adequate UpSH under non-debris conditions, and adequate housekeeping f
l practices are expected to reduce the likelihout of problems during j
recirculation. However, in the event that LPI recirculation system problems such as pump cavitation or air entrainment do occur, the l
operator should have the capability to recognize and contend with the problems.
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. Both cavitation and air entreinment could be expecteo to cause pump vibrAlfon and oscillations in system flow rate and pressure.
Show that the operator will be provided with sufficient instrumentation and appropriate indications to allow and enable detection of these problems. List the instrumentation available giving both the location
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of the ' sensor and the readout.
The incidence of cavitation, air entrainment or vortex formation could be reduced by reducting the system flow rate. The operator should have s
the capability to perform indicated actions (e.g., throttling or terminating flow, resort to alternate cooling system, etc.). Show that the emergency I
operating instructions and the operator training consider the need to monitor the long-term performance of the recirculation system and consider the need for corrective actions to alleviate problems.
4.
Does McGuire utilize similar materials in the containment during power operation for purposes such as reactor cavity annulus biological l
shielding (e.g., sand tanks or sand bags) or reactor cavity blow out l
sand plugs?
l 5.
Discuss the potential for paint chips d.egrading ECCS performance.
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7 Mr. William 0. Parker, Jr.
Vice President, Steam Production Duke Power Company P. O. Box 2178 422 South Church.jtseet Charlotte, North Carolina 28242 cc: Mr. W. L. Porter David Flesichaker, Esq.
Duke Power Company 1735 Eye Street, N. W.
P. O. Box 2178 Suite 709 422 South Church Street Washington, D. C.
20006 Charlotte, North Carolina 28242
)
Richard P. Wilson, Esq.
Mr. R. S. Howard 4,
Assistant Attorney General Power Systems Division State of South Carolina Westinghouse Electric Corporation 2600 Bull Street P. O. Box 355 Columbia, South Carolina 29201 Pittsburgh, Pennsylvania 15230 Mr. E. J. Keith EDS Nuclear Incor porated 220 Montgomery Street San Francisco, California 94104 Mr. J. E. Houghtaling NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 Mr. Jesse L. Riley, President The Carolina Environmental Study Group 854 Henley Place l
Charlotte, North Carolina 28207 J. Michael McGarry, III, Esq.
Debevoise & Liberman 1200 Seventeenth Street, N. W.
Washington, D. C.
20036 Robert M. Lazo, Esq., Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 1
1 Dr. Emmeth A. Luebke Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 l
Dr. Cadet H. Hand, Jr., Director Bodega Marine Lab of California P. O. Box 247 5
Bodega Bay, California 94923 1
Mr. William 0. Parker, Jr.
cc: David Flesichaker, Esq.
1735 Eye Strset, N. W.,
Suite 709 Washington, D. C.
20006 Richard P. Wilson, Esq.
Assistant Attorney General State of South Carolina 2600 Bull Street Columbia, South Carolina 29201 w\\
Office of Intergovernmental Relations 116 West Jones Street Raleigh, North Carolina 27603 County Manager of Mecklenburg County 720 East Fourth Street Charlotte, North Carolina 28202 U. S. Environmental Protection Agency ATTN: EIS Coordinator Region IV Office 345 Courtland Street, N. W.
Atlanta, Georgia 30308 6
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