ML20039E693
| ML20039E693 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/29/1979 |
| From: | Voglewede J Office of Nuclear Reactor Regulation |
| To: | Boger B, Fitzpatrick R, Silver H NRC |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201110181 | |
| Download: ML20039E693 (11) | |
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%[0, UNITED STATES 8 '. e.t.[ h NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20555 5.j
~..f November 29, 1979 e, f
%,.....f NOTE TO:
H. Silver B. Boger R. Fitzpatrick S. Newberry J. Wermiel FROM:
J. Voglewede
SUBJECT:
LE 50NS LEARNED SER ON TMI-1 RESTART Attached are the draft sections of the Lessons Learned SER on the TMI-1 Restart Submittal for which you have lead review responsibility. These sections were submitted by each of you two weeks ago. Also attached are retyped versions of your sections.
1.
Harley Silver's hand-written conracnts appear on the original draft.
Please incorporate his suggestions into your final evaluation if this has not already been done. See Harley if you don't understand his comments.
2.
The retyped version of the SER is on magnetic cards at CRESS. Please make changes on the retyped version and give it back to'me for retyping.
3.
Please use the following format:
a.
NUREG-0578 item number and title.
b.
Item requirement as stated in NUREG-0578.
c.
Your evaluation.
d.
Your conclusions.
v John C. Yoglewede Core Performance Branch cc:
H. Silver B. Boger 2.2.1.a. 2.2.1.b, 2.2.1.c, 2.2.2.a R. Fitzpatrick 2.1.1, 2.1.4 l
S. Newberry 2.1.2.2.1.3.a. 2.2.2.b,2.2.2.c, Denton #1 J. Vog1wede 2.1.3.b ACRS #1, ACRS #2, ACRS #3
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J. Wermiel 2.1.5.a. 2.1.5.b, 2.1.7.a. 2.1.7.b i
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w.d.os A 2.1.3.B INSTRUMENT 6 TION FOR DETECTION OF IHADEQUATE CORE COOLING POSITION THE LICENSEE SHALL DEVELOP PROCEDURES TO BE USED BY THE OPERATOR TO RECOGilIZE IHADEO.UATE CORE C00LIllG WITH CURRENTLY AVAILABLE INSTRU-11EllT ATION.
THE LICENSEE SHALL PROVIDE A DESCRIPTION OF THE EXISTING IHSTRUMENTATION FOR THE OPERATORS TO USE TO RECOGNIZE THESE CONDITIONS.
A DETAILED DESCRIPTION OF THE ANALYSES HEEDED TO FORM THE BASIS FOR OPERATOR TRAINING AND PROCEDURE DEVELOPMEllT SHALL BE PROVIDED PUPSUAlli TO AH0THER SHORT-TERM P.EQUIREMENT, " ANALYSIS OF 0FF-HORMAL CollDITIOHS, INCLUDING HATURAL CIRCULATION (SEE SECTIDH 2.1.9 0F HUREG-0587).
69
/ DISCUSSI0H
[*'
DURING THE TMI-2 ACCIDENT,'A CONDITICH OF LOW WATER LEVEL IN THE REACTOR UESSEL AND INADEQUATE CORE C00LIrlG EXISTED AND liAS NOT RECOGHIZED FOR A
-\\o LONG PERIOD OF TIME.
THIS PROBLEM WAS THE RESULT OF A COMBIHATION OF I
FACTORS IHCLUDING AN INSUFF~CIENT RANGE OF EXISTING INSTRUMENTATION, IHADEQUATE EMERGENCY PROCEDURES, INADEQUATE OPERATOR TRAINING AND UHFAVORABLE INSTRUMENT LOCATION (SCATTERED INFORHATIOH).
THE ilRC LESSONS LEARNED TASK FORCE CONCLUDED, H0HEUER, THAT THE AS-DESIGHED AHD FIELD-MODIFIED IllSTP.UMENTS AT THREE MILE ISLAND UNIT 2 PROVIDED SUFFICIENT INFORMATION TO INDICATE REDUCED REACTOR VESSEL COOLANT LEVEL, CORE VOIDING, AHD DETERIORATED CORE THERNAL CONDITI0 tis.
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- f-litSTRUKr TATION FOR DETECT 10to 0F IfiADEOUATE CORE C00LitiG (2.1.3.b)
SUBC00 Lit G ETER POSITIOri Licensees shall develop procedures to be used by the operator to recognize inadequate core cooling with currently available instrumentation.
The licensee shall provide a description of the existing instrumentation for the operators to use to recognize these conditions.
A detailed description of the analyses needed to fom the basis for operator training and procedure development shall be provided pursuant to another short-term requirement, " Analysis of Of f-fiomal Conditions, Including tiatural Circulation " (see Section 2.1.9 of tiUREG-0578)
In aadition, each PWR shall install a primary coolant saturation rneter to provide on-line indication of coolant saturation condition.
Operator instruction as to use of this meter shall incluae consideration that is not to be used exclusive of other relatea plant parameters..
Li ensees shall provide a decription of any aaditional instrumentation or controls (primary or backup) proposed for the plant to supplement those devices cited in the preceding section giving an unambiguous, easy-to-interpret indication of inadequate core cooling.
A description of the functional design requirements for the system shall also be included.
A description of the procedures to be used with the proposed equipment, the analysis used in developing these proceoures, and a schedule for installing the equipment shall be provioed.
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2.1.3.b Instrumentation for Detection of Inadequate Core Cooling The licensee shall develop procedures to be used by the operator to recognize inadequate core cooling with currently available instru-mentation.
The licensee shall provide a description of the existing instrumentation for the operators to use to recognize these conditions.
A detailed description of the analysis needed to form the basis for operator training and procedure development shall be provided pursuant to another short-term requirement, " analysis of off-normal conditions, including natural circulation" (see Section 2.1.9 of NUREG-0587).
During the TMI-2 accident, a condition of low water level in the reactor vessel and inadequate core cooling existed and was not recognized for a long period of time.
This problem was the result of a combination of factors including an insufficient range of existing instrumentation, inadequate emergency procedures, inadequate operator training and unfavorable instrument location (scattered information).
The NRC Lessons Learned Task Force con-cluded, however, that the as-designed and field-modified instruments at Three Mile Island Unit 2 provided sufficient information to indicate reduced reactor vessel coolant level, core voiding, and deteriorated core thermal conditions.
The similarities between the instruments used at Three Mile Island Units 1 and 2 lead us to conclude that the detection of reduced coolant level or the existence of core voiding in the Unit 1 facility is possible with the existing plant instrumentation. The licensee has described two short-term modifica-L tions to existing instruments to satisfy this requirement.
These changes j
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9 include connecting the in-core thermocouples to the plant computer (for dis-play purposes) and poviding an extended range for reactor outlet (TH) temperature measurement.
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Conclusions The licensee has described only those instruments subject to short-term modi-fication. The staff believe several existing, unmodified instruments will contribute to the operator's ability to recognize inadequate core cooling conditions. These include reactor coolant pump current, reactor inlet temperature channels, in-core and ex-core neutron detectors, core flow and g-letdown line radiation monitor.
We further believe that diverse and redundant indications of inadequate core cooling can readily be provided by these additional instruments.
Because the licensee has not addressed these existing, unmodified instruments, we find the response to this item to be inadequate.
The licensee has not submitted procedures to be used by the operator to recog-nize inadequate core cooling. Because the Ifconsee has not addressed this ctr.ern, we find the response to this item to be inadequate.
t The licensee has not submitted a description of the analyses needed to form the basis for operator training and p?acedure development for inadequate core cooling. Because of these omissions, we find the response incomplete.
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"The licensee shall install a primary coolant saturation meter to provide on-line indication of coolant saturation condition. Operator m
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tastruction as to use of this meter shall include consideration that is not to be used exclusive of other related plant parameters."
A saturation meter provides an indication of whether temperature and pressure conditions are such that boiling can occur.
In a pressurized water reactor, such as Three Mile Island Unit 1, boiling in the primary coolant system is an indication of deteriorated core thermal conditions.
The saturation meter is anew instrument for TMI-1 and is required by a staff position found in NUREG-0578.
Properly' designed and installed, a saturation meter not'only indicates boiling conditions in the primary coolant, but also the proximity to such conditions.
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The licensee has proposed the addition of an instrument which will display the margin between actual primary plant pressure and the saturation pressure (tne pressure at which boiling occurs).
This instrument conceptually satisfies the requirements of NUREG-0578.
Conclusion The licensee has n.ot provided a detailed description of the proposed satura-tion meter as requested in the NRC letters of October 26 and October 30, 1979, however. A description beyond a conceptual basis is required for our evalua-tion.
Because insufficient detail has been provided on this item, we conclude that this portion of the submittal is incomplete.
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