ML19352A510
| ML19352A510 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 10/22/1979 |
| From: | Thadani A Office of Nuclear Reactor Regulation |
| To: | Birkel R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18025B195 | List:
|
| References | |
| FOIA-80-587 NUDOCS 8104170156 | |
| Download: ML19352A510 (2) | |
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gl NOTE TO:
R. A. Birkel
SUBJECT:
ORAFT ATWS PROCEDURES FOR MCGUIRE NUCLEAR STATION The following are our comments on the draft ATWS procedures for McGuire Station:
1.0 Symptoms i) The procedure does not idt.atify the initiating event. For example, would all rod bottom lights illuminate if the initiating event is loss of offsite power.
ii) The operator is not given any aid in knowing what the symptoms of ATWS events might be.
Further the symptoms would depend on initiating event.
It seems to me that they ought to carefully look at at least the following three events:
a) Loss of Main Feedwater b) Loss of Offsite Power c) Stuck Open PORY 111) The first item of impartance is that the operator recognize that scram action was called for but did not occur.
2.0 Immediate Actions 2.1 Automatic - These statements don't say anything about an ATWS. As a matter of fact, item 2.1.2 may not occur at all if the scram breakers don't i
open. This section should discuss other automatic signals such as auxiliary feedwater actuation and emergency core cooling system actuation.
l 2.2 Manual - What is the time frame for these act' ions.
Item 2.2.3 - For what ATWS events would T decrease to 546 F for av immediate action, Why is there no discussion of auxiliary feedwater and HPSI actuation.
These systems are critical during ATWS events. The auxiliary feedwater system is needed immediately and the flow should be verified.
3.0 Subsecuent Actions Provide time frame for these actions:
'.1 How can the operator verify that these parameters are normal. What 3
is the operator to do if these parameters take on abnomal values as would be the case during an ATWS event.
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W2 21979 R. A. Birkel 3.2 Can this instruction be accomplished for loss of offsite power event.
This comment applies to several subsequent instructions.
3.8 What is the role of this statement during an ArdS?
General Comment. After reading this procedure, I came to the conclusion that people who wrote this' procedure probably don't have a good understanding of ATWS events.
I recommend that you ask the utilities to:
a) review ATJS analyses, b) combine procedures for those AT45 events where such combination is warranted by similar required actions (I believe two or three procedures should do it).
c) keep in mind the comments on the draft procedure, and d) submit a revised set of procedures.
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A. Thadani
Enclosure:
cc:
S. Hanauer T. Speis S. Varga R. Baer M. Srinivasan K. Parczewski H. Vander Molen l
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Drzz Powra COMPA.NY Powsm Berz.nnro 4a2 Socra Caracu Srazzr. Cniernrtz. N. C. asa4a m u o...anza...
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n w.est Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Cemission Washington, DC 20555 Attention:
Mr. R. L. Saar, Chief Light Water Reactors Project Branch No. 2 Re: McGuire Nuclear Station.
Units 1 and 2 Docket Nos. 50-369, 50-370
Dear Mr. Denton:
Your letter of August 17, 1979, transmitted interim requirements for AT45 which nust be satisfactorily 1:.plemented to support issuance of an operating license. The basic requirements were to:
- 1) Provide e=ergency procedures to provide for operator recognition of and proper response to an AT4S event, and
- 2) Provide operator training to assure proper i=plementat!on of these pro-cedures.
The emergency procedures, in general, at McGuire consist of a general reactor trip procedure and a series of specific transient and accident procedures.
In order to address AT4S concerns it is our intention to revise the reactor trip procedure to include specific indications which nust be observed for a reactor trip followed by necessary sitigating operator actions in the event a trip does not occur. The specific transient procedures which require a reactor trip will also be revised to refer the operator to the reactor trip procedure if an AT45 event is identified. Attached for your review is a draft copy of the revised reactor trip procedure.
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Mr. Harold 1. Denton, Director September 25, 1979 Page Two It is our intentien to provide the necessary training to assure operator familiarity with the above ATWS provisiens. If there are questions regarding this matter, do not hesitate to contact us.
Very truly yours, an a..
William O. Parker, Jr.
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1.1 Any Alarm on Reactor Trip Tirst cut Fanel.
\\'yf 1.2 All rod bot:om lights are illtunNted.
7 1.3 Nuclear Ins:rumentation indicating a rapid decrease in Neutron
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1.4 If there is not a rapid drop in nuclear power and the control rods are not inserred, then this is an " Anticipated Transient Without Scram" event.
2.0
!= mediate Action 2.1 Automatic 2.1.1 All rods drop into core.
2.1.2 Turbine-Generator trip.
2.1.3 Feedvater Isolation when Tavg decreases to 564*F.
2.1.4 Steazr. Dumps Arm-Ac:ua:e and/or POR7 lift.
2.2 Manual NOTE: Do not place systa=s in manual unless sisoperation in automatic is apparent.
2.2.1 If all rods do not drcp into the core : hen:
2.2.1.1
.anually trip :he reactor.
w 2.2.1.2 If a reactor trip has not yet occurred, : hen sanually trip the .G set 3krs. locally.
2.2.1.3 If a reac:or : rip has no: yet occurred, i= media:ely ac:uate safety inj ec:icn 2.2.1.4 If a reactor trip has not yet occurred, place the Centrol Rod Drive Sank Selector Swi:ch in =anual and inser: rods.
2.2.2 If turbine generator did not : rip, : hen:
2.2.2.1 Manually trip :urbine fr:s Control Rocs or locally a: the :urbine.
2.2.2.2 If a turbine : rip has not yet occurred, : hen piace OEH Con:rol in anual, and manually close :he Governor valves.
2.0.3
!! 7eedva:er :sola: ion d:es no occur when : avg decreases :s 564*?, : hen:
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2.2.3.1 Close the =ain feedva:er regulading ralves and- :he bypass y
valves.
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2.2.3.2 If feedvater i olation has not yet occurred, the main yeedvater Containment Isol. Valves.
84f4 2.2.3.3 If feedvacer isolation has not yet occurred, manually h 04 trip the feedvater pumps.
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2.2.4 If steam dumps fail to arm-actuate and/or PORV's fail to lif:,
then:
g 2.2.4.1 Check steam pressure mode set:ing at 1090 psig and place y
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2.2.4.2 Close all PCRV manual loaders and place PCR7 selector p;e
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switch in :aanual. Regulate PCRV's to maintain steam
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2.2.5 Secure all boren dilution operations.
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