ML19320C558
| ML19320C558 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/09/1980 |
| From: | Swartz L NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| To: | Chesapeake Energy Alliance |
| References | |
| NUDOCS 8007170370 | |
| Download: ML19320C558 (7) | |
Text
_ _ _ _ _ _
UNITED STATES OF AMERICA NUCLEAR REGULATOKY COVilSSION BEFORE THE AT0i11C SAFETY AND LICENSING BOARD In the Matter of
)
)
METROPOLITAN EDIS0N C0i4PANY,
)
)
)
(Three Mile Island Nuclear Station
)
Unit 1)
)
NRC STAFF RESPONSE TO CHESAPEAKE EllERGY ALLIANCE INTERROGATORY 6-9 The liRC Staff has responded to Chesapeake Energy Alliance Interrogatory 6-9 which relates to Contention 6.
Signed affidavits verifying the response will be sent at a later date.
Respectfully submitted, Lucinda Low Swartz Counsel for NRC Staff s
Dated at Bethesda, Maryland this 9tn day of July,1980 8007170.370
h Chesapeake Eneray Alliance (CEA) Interroaatory 6-9 Identify, any-and all sequences of events at fid-2 that could result in any substantial loss of reactor coolant at TMI-2. Distinguish between those sequences that are predicated on operator error from those that are pred.icated on equipment error or malfunction.
In particular, descriM in detail any and all of such sequences that would require site evacuation at TMI.
Response
A substantial loss of reactor ccolant at Tril-2 is not likely. The reactor plant is in a natural circulation mode with decay heat removal via the
'A' steam generator to the main condenser.
Heat is also being rejected directly to the containment environment.
Equipment malfunctions which would result in a loss of coolant during the current reactor plant configuration include reactor coolant pump seal failures, valv? packing failures, boundary valve failures (including pressurizer safety or relief valves), or reactor coolant system pressure boundary degradation or rupture.
Each of these types of failures is very unlikely since the reactor coolant system has been depressurized to approximately 100 psig, which is far below the reactor coolant system design pressure of 2500 psig and normal operating pressure of 2150 psig. Reactor coolant pump seal failure is very unlikely ::ince the reactor coolant pumps are not running. A small amount of leakage (about 200 gallons per day) from the reactor coolant system is currently being replaced by makeup from the standby pressure control system (SPC).
Increased leakage or loss of coolant from other sources, should it occur, would also be replaced by the SPC or nomal plant makeup system.
Procedures covering such occurrences are available at the plant.
A loss of coolant due to operator error would result if somehow the power-operated relief valve (PORV) or other boundary valves were opened. This is very unlikely due to the procedural controls, operato, training, and system modifications such as securing electrical power to the PORV.
If any of these failures were to occur, however,1.he standby pressure control system (SPC) and makeup system are available to provide borated makeup water.
Current reactor coolant system leakage is being collected and contained in the reactor building. Additional reactor coolant loss would be collected here also. Several hundred thousand gallons of water can be" added to the present volume in the containnent before any significant impact would result to equipment or instrumentation. The NRC required and the licensee has comm'itted to maintain additional storage capability (approximately 160,000 gallons) to store waste water from TMI-2 should additional storage capacity become necessary.
Due to the very low reactor core decay heat levels, makeup
~
requirements following a postulated loss of coolant are very low, such that addi-tional accumulation of reactor coolant in the containment would be at a very low rate. Should it become necessary to limit the generation of additional radioactive contaminated water, suction could be shifted from the SPC system tanks to the containment sump using the low pressure injection system and operation in the closed cycle low pressure recirculation mode can be initiated.
Prior to removal of the reactor vessel head, core cooling must be shifted to a decay heat removal system.
Current plans are to use a small decsy heat removal system which has been constructed in the auxiliary and fuel handling buildings. Although unlikely, should a loss of coolant occur as a result of a failure in this system or operator error, the leakage could be isolated by shutting the system isolation valves which are operable from the control room.
The consequences of such a rupture would not require site evacuation since the water would be collected and contained in the auxiliary bu!1 ding sump, the gasecus fission products have decayed to negligible values since the TMI-2 accident in March 1979, and the resultant doses on or off site would be insignificant.
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
METROPOLITAN EDISON COMPANY, et al.
)
Docket No. 50-289
)
(Three Mile Island, Unit 1)
)
AFFIDAVIT OF SCOTT NEWBERRY I, Scott Newberry, being duly sworn, to depose and state:
1.
I am employed by the TMI Program Office, Office of Nuclear Reactor Regulation of the United States Nuclear Regulatory Commission.
2.
The answers to CEA Interrogatory 6-9 was partially prepared by me.
I certify that the answer given is true and accurate to the best of my knowledge.
Scott Newberry Subscribed and sworn to before me this day of 1980.
Notary Public My Comnission Expires:
UNITED STATES OF AMERICA NUCLEAR REGULATORY _COMMI.5310N BEFORE THE ATOMIC SAFETY AND LICENSING BOARD IntheN'atterof
)
)
METROPOLITAN EDISON COMPANY, et al.
)
Docket No. 50-289
)
(Three Mile Island, Unit 1)
)
AFFIDAVIT OF JAY LEE I, Jay Lee, being duly sworn, to depose and state:
1.
I am employed by the TMI Program Office, Office of Nuclear Reactor Regulation of the United States Nuclear Regulatory Commission.
2.
The answers to CEA Interrogatory 6-9 was partially prepared by me.
I certify that the answer given is true and accurate to the best of my knowledge.
Jay Lee
' Subscribed'ans sworn to before me this day of 1980.
Notary Public My Commission Expires:
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATONIC SAFETY AND LICENSING BOARD In the Matter of
)
METROPOLITAN EDIS0N COMPANY, Docket No. 50-289 ET AL.
)
)
(Three Mile Island, Unit 1)
)
CERTIFICATE OF SERVICE I hereby certify that copies of "NRC STAFF RESPONSE TO CHESAPEAKE ENERGY ALLIANCE INTERROGATORY 6-9", dated July 9,1980, in the above-captioned proceeding, have been served on the following, by deposit in the United States mail, first class, or, as indicated by an asterisk through deposit in the Nuclear Regulatory Commission's internal mail system, this 9th day of July 1980:
- Ivan W. Smith, Esq.
Mr. Steven C. Sholly Atomic Safety & Licensing Board Panel 304. South Market Street U.S. Nuclear Regulatory Commission Mechanicsburg, Pennsylvania 170.i5 Washington, D.
C.
20555 Mr. Thomas Gerusky Dr. Walter H. Jordan Bureau of Radiation Protection 881 W. Outer Drive Dept. of Environmental Resources Oak Ridge, Tennessee 37830 P.O. Box 2063 Harrisburg, Pennsylvania 17120 Dr. Linda W. Little 5000 Hermitage Drive Mr. Marvin I. Lewis Raleigh, North Carolina 27612 6504 Bradford Terrace Philadelphia, Pennsylvania 19149 George F. Trowbridge, Esq.
Shaw, Pittman, Potts & Trowbridge Metropolitan Edison Company 1800 M Street, N.W.
Attn: J.G. Herbein, Vice President Washington, D. C.
20006 F.O. Box 542 Reading, Pennsylvania 19603 Karin W. Carter, Esq.
505 Executive House Ms. Jane Lee P.O. Box 2357 R.D. 3; Box 3521 Harrisburg, Pennsylvania 17120 Etters, Pennsylvania 17319 i
Honorable Mark Cohen Walter W. Cohen, Consumer Advocate 512 D-3 Main Capital Building Department of Justice Harrisburg, Pennsylvania 17120 Strawberry Square,14th Floor
-Harrisburg, Pennsylvania 17127
John Levin, Esq.
Pennsylvania Public Utilities Com.
~
Box 3265 Harrisburg, Pennsylvania 17120 Jordan D. Cunningham, Esq.
Allen R. Carter, Chairman Fox, Farr and Cunninoham Joint Legislative Committee on Energy 2320 North 2nd Street 0
ce Box 142 Harrisburg, Pennsylvania 17110 Senate Gressette Building Theodore A. Adler, Esq.
Columbia, South Carolina 29202 WID0FF REAGER SELK0WITZ & ADLER Post Office Box 1547
- Atomic Safety and Licensing Appeal Board Harrisburg, Pent vania 17105 U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Ms. Ellyn R. Weiss Sheldon, Harmon, Roisman & Weiss
- Atomic Safety and Licensing Board Panel 1725 I Street, N.W.
U.S. Nuclear Regulatory Commission Suite 506 Washington, D. C.
20555 Washington, D. C.
20006
- Secretary Ms. Karen Sheldon U.S. Nuclear Regulatory Commission Sheldon, Harmon, Roisman & Weiss ATTN:
Chief, Docketing & Service Br.
1725 I Street, N.W.
Washington, D.C.
20555 Suite 506 Robert Q. Pollard Washington, D. C.
20006 609 Montpelier Street Baltimore, Mar 3'and 21218 Ms. Marjorie M. Aamodt R.D. #5 Coatesville, Pennsylvania 19320 Chauncey Kepford Judith H. Johnsrud Environmental Coalition on Nuclear Power 433 Orlando Avenue State College, Pennsylvania 16801
/
r Ms. Frieda Berryhill. Chairman f'
.,L Coalition for Nuclear Power Plant Q M.i/LItL M MM&j Postponement Counsel for NRC Staff 2610 Grendon Drive Wilmington, Delaware 19808 Holly S. Keck Anti-Nuclear Group Representing York 245 W. Philadelphia Street' York, Pennsylvania 17404 n