ML17345B418

FOIA Request for Documents Re Incident at Facilities Described in Encl B,Page 2 of Weekly Info Rept for Wk Ending 831007

ML17345B418
Person / Time
Site:	Turkey Point
Issue date:	10/20/1983
From:	SHOLLY S C UNION OF CONCERNED SCIENTISTS
To:	FELTON J M NRC OFFICE OF ADMINISTRATION (ADM)
References
FOIA-83-615 NUDOCS 8402010399
Download: ML17345B418 (6)

Text

UNION OF CONCERNED CIENTISTS 1366 Connecticut A enue.N,W.~2.1101~Washington, DC 20036~(202)2064600 28 October 1983 Mr.J.M.Felton, Director Division of Rules and Records Office of Administration U.S.Nuclear Regulatory Comtission Washington, D.C.28555 FREEDOM OF tNFORit.e A Dear Mr.Peltont Pursuant to the Freedcm of Information Act, please make available at the Ccmnission's Washington, D.C., Public Docunent Room copies of docunents in the following categories:

A.All docunents concerning the incident at Turkey Point Units 3 and 4 described in Enclosure B, page 2, of the wkly Information Report for the~k Ending October 7, 1983 (copy attached).Should you or your staff.have any questions regarding this request, please do not hesitate to contact me at (282)296-5688.Sincerely, Steven C.Sholly Technical Research Associate Main Office: 26 Church Street~Cambridge, Massachusetts 02238~(617)547-SSS2 IS~'

EMiERGENCY OPERATING PROCEDURE?0000 (E-O), PAGE 5'"iEDIATE ACTIONS AND DIAGNOSTIC 4///54 ENCLOSURE 3 5.1.5 I 3.Upon verification that the Appendix A alignments are complete, verify that the function selector switches on the H2 analyzer panels (primary and backup)are in the sample position./Turn the control switches to analyze and depress the remote selector buttons.v henev ent Hi-HI ressure set oint is reached, verify tatty o ows g l.on a.inmen orav.ss ml sa 2.ontainment Zolation phase is initiated 3.Main Steam Isolation Valves have closed I f not, manually initiate Containment Spray, Containment Isol ation Phase B and close Main Steam Isolation Valves.NOTE: If the Containment Hi Hi pressure setpoint i s reached with indications of a LOCA, this constitutes a GENERAL EMERGENCY.

Notify the Plant Supervisor

-Nuclear.4.Close or verify closed, pressurizer relief tank gas analyzer isolation valve SV-*-6385 and the excess letdown/RCP seal water return isolation valve MOV-*-38)and MOV-*-6386.

5.2 ACCIDENT DIAGNOSTICS:

5.2.I Evaluate reactor coo1ant pressure to determine if it is low or decreasing in an uncontrolled manner.If it is low or decreasing, verify that: l.All pressurizer spray line valves are closed and 2.all pressurizer relief valves are closed;If not, manually close the valves from the console.NOTE: A failed open pressurizer relief valve or pressurizer safe y is an UNUSUAL EYENT.Notify the Plant Supervisor

-iluclear.If the RCS pressure is above the low pressure reactor trip setpoirt ()843 psig)and is stable or increasing, go to Step 5.2.7.5.2.2 Stop ALL Reactor Coolant Pumps after the high head safety injection pump operation has been verified and when the wide range reactor coolant pressure is at 1400 psi'g as seen on PI-*-403 VPA or PI-*-405 VPB.CAUTION: If component cooling water to'the reactor coolant pumps is isolated on a containment pressure signal, all reactor coolant pumps should be stopped because of loss of motor bearing cooling and thermal barrier cooling.Increased component cooling water flow resulting from safety injection, may cause closure of FCV-*-626.

Verify that FCV-*-626 is open.NOTE: The conditions given above for stopping reactor coolant pumps should be continuously monitored throughout thi's instruction.

4~i'u r 0 AtNIK15%ATIYE PRKEDJRE 0103.12~PAGE:,6 ICJTjF7CATlQL 5 GNIFICANT KVEhi S TQ&C'fl<igf ENCLOSURE?~'PPENDEX A (cont'd)5.Any-event requrlring initiation of shutdown of Unit 3 or 4 in accordance with Technical Specification Limiting Conditions for Operation.

Examples: (1)If a Technical Specification Limiting Condition of Operation is not met and a shutdown is coamenced, this must be reported.(2)If the time allowed for remedial action expires and the Limiting Condition for Operation is still not met and a shutdown is commenced, this must be reported.Personnel error or procedural inadequacy which, during normal operations, 6.anticipa e opera rona occurrences, or aces ent condst>ons, prevents or cou d prevent, by itself, the fulfillment of the safety function of those structures, systems, and components important to safety that are needed to (1)shutdown the reactor, safely and maintain it in a safe shutdown condition, or (2)remove residual heat following reactor shutdown, or (3)limit the release of radioactive material to acceptable levels or reduce the potential for such release.Examples: (1)Personnel error-complete loss of wa er in a steam generator due to lack of feed control.7.Any event resulting in manual or automatic actuation of Engineered Safety Features, including the Reactor Protection System.Examples: (1)Any ac.ual trip of the reactor from a critical condition.

(2)Any initiation o-.sa ety in'e"tion.

NOTE: Actuation of Engineered Safety Feature including the Reactor Protection System which result from and are part of the planned sequence during surveillance testing does not constitute an event reportable under this item.8.Any accidental, unplanned, or uncontrolled radioactive rel ease.(Normal or expected releases from maintenance or other operational activities are not included).

Examples: (1)Spent Fuel Pit cooling piping leakage going ou of Heat Exchanger Room.

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