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Docket File (ENVIRON)
AEC PDR JAN % 0 ISl4 Local PDR GErtter (DR-6397).
DR Reading JCook L Reading Elughes Docket No. 50-219 RP Reading OCR.(3)
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JF0' Leary (3)
Senator.Clifford P. Case AGiambusso EC DRMuller United States Senate.
WHRegan RBBevan
Dear Senator Case:
SSheppard
,This is in further response to your communication of_Uovember 20, 1973 transmitting Mr. Kurtz's' letter of hovember 15, 1973 regarding the operation of the _0yster Creek liuclear Generating Station, and
' supplements our letter to you of December 10, 1973.
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Eln his letter of November 15, 1973, Mr. Kurtz expresseo concern for the effect of dredging spoils containing radioactivity on the health and safety of residents living near the dredged canal._ These concerns arose from statements contained in a letter from Mr. John Russo, Chief, Lureau of Radiation Protection, New Jersey Department of Environmental Protection, to the ALC, dated August 22, 1973. Mr. Russo's letter stated that s.amples taken by the State from the sediment in the bottom of the discharge canal show a ranioactivity 1cvel that coulu result in a "significant" dose to individuals on the canal banks if the canal were dredged and spoils were placed along the canal banks.
In subsequent discussions between the Commission and Mr. Russo, ho pointed out that the New Jersey Department of Environmental P)otection is not concerned at this time that this is a problem, but that his comment on the dredging spoils was made only to ensure that the ALC was made aware of a potentially sensitive situation.
Mr. Russo stated that the State of New Jersey 18, in fact, committed to stonitor any dredging operations at Oyster Creek and to determine the final f ate of any material taken from the canal in any future dredging operations.
In response to inquirics, the Jersey Central Power and Light Company had stated that no dredging has occurred in the discharge canal since before the Oyster Creek Station con.menced operation.
Mr. Huuso also has said that the State knows of no dreaging operations in the canal in recent years.
Data contained in a July 1973 report issued by the hew Jersey bepartment of~Environcental Protection indicate that the radioactivity fu tne Oyster Creek sedircent ia-confined to the uppermost two inch layer.
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e Senator Clifford P. Case 2,
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on the basis of the concentration found in the sediment and the conservative assumption that any dredging operation would effectively mix the radionuclide-rich layer with ten times its volume of non-active sediment, it is esticated that a dose of.up to 10 millirecs per year could be received by an individual who resided continuously on the
-spoils pile. Thia.is a small fraction of the average dose to an individual from natural background radiation of 125 mil 11rema per.
year. However, the upper range of this dose estimate could exceed the Commission's as-low-as-practicable guidelines for radiation exposure. Accordingly, as indicated above, any~ dredging operations will be carried out under close surveillance, and disposition of spoils will be made in a manner and location which minimizes exposure to the general public.
The Commission, through periodic radiological monitoring which has been required by the technical specifications in the Oyster Creek Operating Liccuse since operation began, will continue to maintain surveillance over the radioactivity levels in the canal as well as all other aspects of plant operation relating to the. health and safety of the public.
The Cot:: mission requires that "any operations at the plant which could i
potentially result in radiation exposure to the public will be c'onducted in auch a way as to keep these exposures within existing limits and us low as practicable.
Sincerely, om - Q ued py A Giraeusso 4
A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing i-SEE ATTACHED YELLOW FOR PREVIOUS CONCURRENCE OGC t rE p _,, _,, _ __ L:RP _ ____ _0,g _ _ _
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y - a b l' Jersey Central. Power & Light Company MADISON AVENUE AT PUNCH BOWL ROAD
- MORRISTOWN, N.J. 07960
- 201-539 6111
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January 18, 1974 0?
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Operating Reactors Branch #2 Directorate of Licensing tf.'% k I[!'
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Dear Mr. Ziemann:
TMs is in response to your letter of December 19, 1973 request-
-ing electromatic relief valve operational ' data regarding our Oyster Creek Nuclear Genarating Station. Attached herewith is a summary tabulation of 1
electromatic relief valve operation covering the period of plant startup testing and operation from January 1,1969 to present.
It is understood that this letter is in response to Item 1 of your request and we intend to respond to Item 2 before the specified deadline.
It is also our intention to report future relief valve operation in our facility semi-annual operating reports in a similar manner.
Very truly yours, b'of
'ify Ivan R. Finfrock, Jr.
Vice President cs Attachment I
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Summary of Electromatic Relief Valve Operation January'1, 1969 to December.31, 1969 a
t Date of Operation:. June 30,.1969 a
a Purpose of Operation _: ' Operability Test
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Mods of Initiation:
Automatic.
Reactor Conditions Prior to Operation: The reactor was'suberitical.
Comments:- Reactor triph low water level, drywell high pressure, and core spray booster pump discharge pressure signals were created to cause automatic operation of the relief valves, i
Date of Operation:
August 11, 1969 i
Purpose of Operat' ion: Operability Test Mode of Initiations Automatic Reactor Condition Prior to Operation _: The reactor was suberitical.
Comments: Reactor triple low water level, drywell high pressure, and core spray booster pump discharge pressure signals were created to cause ' automatic operation of the relief valves.
i Date of Operation:
September 21, 1969 Purpose of Operation: Startup Test #16 Mode of Initiation: Manual Reactor Conditions Prior to Operation:
6 h
Steam Flow
- 1.2 x 10 lbm/hr Reactor Pressure - 980 psig Electrical Output - 385 MW(e)
Comments: Each of the four (4) electromatic relief valves were independently 6
tested and found to discharge.5 x 10 lbm/hr (8.55% rated steam a
flow) at the above conditions.
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O Summary of Electromatic Relief Valve Operation January 1,1970 to December 31, 1970' t.-?M -
Date of Operation:
February 15, 1970 Purpose 'of Operation:
Primary coolant system depressurization.
Mode of Initiation: Automatic 4
Reactor Conditions Prior to Operation:
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Steam Flow
- 4.95 x 106 lbm/hr
's Reactor Pressure - 985 psig Electrical Output - 450 MW(e) i Comments: ' The reactor scrammed due to a high neutron flux sign'l following a
a turbine trip.
The steam pressure subsequently increased to the set point of the electrouatic relief valves (1125 psig) causing them to actuate.
s Date of Operation:
December 25, 1970 Purpose of Operation:
Primary coolant syste'm depressurization.
Mode of Initiation:. Automatic
. Reactor Conditions Prior to Operation:
6 Steam Flow
- 6.12 x 10 lbm/hr Reactor Pressure - 1000 psig Electrical Output - 582 MW(e)
Comments: The reactor underwent an anticipatory scram due to a momentary closure of all four (4) main stop valves.
The steam pressure subsequently increased to the set point of the electromatic relief valves (1125 psig) causing them to actuate.
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. Summary of Electromatic Relief Valv'e Operation January 1, '1971 to December 31, 1971
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Date of Operation:. November 7, 1971 Purpose of Operation:
Operability Test
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Mode of Initiation:
Automatic Ra' actor Conditions Prior to Operation: The reactor was subcritical.
I Comments:
Reactor triple low water level, drywell high pressure, and core spray booster pump _ discharge pressure signals were created to cause automatic operation of the relief valves.
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Summary of Electromatic Relief Valve Operation January 1,1972 to December 31, 1972 4
Date of Operation:
December 29, 1972.
Purpose of Operation:
Primary coolant system depressurization.
Mode of Initiation:
Automatic
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Reactor Conditions Prior to Operation:
Steam Flow
- 7.35 x 106 lbm/hr Reactor Pressure - 1000 psig Electrical Output - 645 MW(e)
Comments: The reactor scrammed as the result of a generator trip from a loss of field.
The reactor pressure increased to 1070 psig, which opened the electromatic relief valves., one of which did not reseat and the vessel depressurized to 200 psig in 60 minutes.
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Summary of Electromatic Relief Valve Operation January 1,1973 to December 31, 1973 Date of Operation: -May 28, 1973 Purpose' of Operation: Operability Test Mode of Initiation: Automatic Reactor Conditions Prior to Operation: The reactor was suberitical.
Comments:
Reactor triple low. water level, drywell high pressure, and core -
spray booster pump discharge pressure signals were created to cause automatic operation of the relief valves.
'Date of Operation: June 30, 1973 Purpose of Operation:
Primary coolant system depressurization.
Mode of Initiation:
Automatic Reactor Conditions Prior to Operation:
6 Steam Flow
- 7.45 x 10 lbm/hr Reactor Pressure - 1020 psig Electrical Output - 625 MW(e)
Comments: The reactor scrammed due to a generator trip.
The reactor pressure subsequently increased to the set point of the electromatic relief valves of 1070 psig, causing them to open.
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