ML20112F930
| ML20112F930 | |
| Person / Time | |
|---|---|
| Site: | 05000447 |
| Issue date: | 03/13/1984 |
| From: | Quirk J GENERAL ELECTRIC CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20112F916 | List: |
| References | |
| FOIA-84-220, FOIA-84-221 MFN-029-84, MFN-29-84, NUDOCS 8501160104 | |
| Download: ML20112F930 (3) | |
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GENER.Al ELECTRIC COMM e 175 CU*dNER AVENUE
- 5'.N JCSI, CAUFCAN!A C5195 s
MC 682. (408) 925-2606 MFN-029-84 March 13, 1984 U.S. Nuc1sar Regulatory Comission Offict of Na:1ect Ret:*ar Regulation Washington, D.C.
20555 Attention:
Mr. D. G. Eisenhut Director Division of Licensing Gentlemen:
SUBJECT:
IN THE MATTER OF 238 HUCLEAR ISLAND CENERAL ELECTRIC STANDAFJ) SAFETY ANALYSIS REPORT (GE$$AR !!) DOCKET NQ. STM 50-447 GE PROPOSED EVALUATION PLAN FOR THE CCHSIDERATION OF SOURCE TERM ISSUES In the meeting involving GE and NRC Staff personnel held on February 22,*
1984, an action plan was proposed to address source tene issues as part of the GESSAR II Severe Accident Review.
It is General Electric's intent to perfnem a series of sensitivity studies on various parar4ters af fecting containment failure ecodes and timing and fission product release.
These sensitivity studies will be evaluated to define the impact on the GESSAR II plant risk as quantifies by the GE Probabilistic Risk Assessment.
They will also be used in GE studies of proposed design mocifications, fhe attachment provides additional details of the propuced t.unsitiylty studies.
It is nur intent to perfons the indicated studies and discuss the results with the Staff on March 20, 1984.
If Lliere are any questions on the information contained herein, please contact me or Mr. Kevin Holtzclaw (408-975-7506).
Very truly yours, f
J c.
uirk, Manager Systests I irentina N lear Safety & Licensing Operation JFQ: rf: rm/G03084 Attacheren,t cc:
T. J. Miraglia (NRC)
C. O. Thomas (NRC)
D. C. Scaletti (NRC)
L. S. Gifford (GE-Bethesda)
A. Thadant (NRC)
R. Villa (GE) 8501160104 840619 PDR FOIA SHDLLYS4-220 PDR
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,-SUES-SENSITkVITYSTUDIES SOURCE TERT 1)
' Core heatup GE will vary the MARCH ir.put parameters over a reasonable renge (such that fuel temperatures are'less than 5080'F)
Core slum.p fraction will be explicitly varied around the 65 percent value lasert in the PRA.
2)
.0xidation model following node melt GE will show the sensitivity of the MARCH results ta alternativa assucptions on ficw blockage by melted nodes.
3)
In-vessel vaporization GE 'will show' the sensitivity in the source terms to release of significant fractions of cesium iodine and tellerium after vessel
. failure.
4)
Primary system retention GE will vary the in-vessel retention factor from 1 to 10.
5)
Core slump fraction This parameter will be varied in step 1).
6)
Helt-through of vessel lower head GE will assess alternative vessel failure modes and their impact on timing and fission product release.
7)
Ex-voccol vsporization GE will assess the impact of various concrete compositions and fission product release assumptione.
8)
Suppression pool scrubbing GE will vary the pool DF's over a reasonable range which accounts for uncertanties in the inputs (e.g. particle size distribution).
and which is consistent'with current scrubbing data.
9)
Suppression pool bypass CE will pruvide en evaluation of potential bypass pathweys and" assess their potential impact on plant risk.
10)
Site sensitivity G E 111...= = = tiew plant s ink t.1,sivts popul Liuo dens ity >ile.
JFQ: rf: rm/0030358-1 9
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I/AR 15 GM N
MEETING NOTICE e
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j Docket File
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MSIC SSPB READING FILES P. Anderson Project Manager D. Scaletti':'
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-e E. Case De Eisenhut/R. Purple F. Miraglia C. Thomas J. Youngblood A. Schwencer E. Adensam J. Miller G. Lainas T. Novak C. Grimes D. Crutchfield G. Holahan
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- J. P. Knight W. Johnston D. Muller F. Rowsome-R.. Houston L. Rubenstein F. Schroeder W. Russ' ell Attorney, OELD E. L. Jordan J. Partlow Regional Administrator," Region ACRS Receptionist., Beth, NRC Particicants:
J. Rosenthal J. Lane M. Rubin e
Y T'g UNITED STATES y
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NUCLEAR REGULATORY COMMISSION y.
p WASHINGTON, D. C. 20555 Y'
MAR 151934 STN 50-447
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' MEMORANDUM FOR:
Cecil 0. Thomas, Chief Standardization and Special Projects Branch Division of Licensi'ng FROM:
Dino Scaletti, Project Manager i Standardization and Special Projects Branch Division of Licensing
SUBJECT:
FORTHCOMING MEETING WITH GENERAL ELECTRIC COMPANY GESSAR II SEVERE ACCIDENT REVIEW DATE & TIME:
Tuesday, March 20, 1984 8:30 AM - 5:00 PM LOCATION:
Maryland National Bank Building Room 6110 Bethesda, MD PURPOSE:
To discuss GESSAR II Source Term Reanalysis, see attached letter e
8:30 AM - Management Overview
- 10:30 AM - Discussion of the resulti of sensitivity studies on various parameters affecting fission product release.
- (10:30 AM meeting will discuss G. E. proprietary v.
information, Closed to the Public).
)
PARTICIPANTS:
NRC BNL g
R. Ma'ttson J. Hulman T. Prutt J. Quirk R. Bernero R. Frahm H. Ludewig K. Holtzclaw R. Vollmer B. Hardin T. Speis J. Mitchell b
C S' Re J
Dino Scaletti, Project Manager Standardization and Special Projects Branch 4.gyg Division of Licensing
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cc:
See next page.
Gt0 FROFRIETARY SUBJECT MATyRWILLBEDISCUSSED
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GENER AL @ ELECTRIC h
HUCLEAA POM.R.SY3T7.M3 DMalON GENELA1 ELECT 2tC COW ANY e 175 CURINEE AVENUE e SAN JOSE, CAUFCNA C5125 HC 682 (408) 925-2606 MFN-029-84 March 13, 1984 U.S. Nuclear Regulatory Connission
~
Office of Nuclear Reactor Regulation Washington, D.C.
20555 Attention:
Mr. D. G. Eisenhut, Director Division of Licensing Gentlemen:
SUBJECT:
IN THE MATTER OF 238 NUCLEAR ISL910 CENERAL ELECTRIC STANDARD SAFETY ANALYSIS REPORT (GESSAR II) potAET NO STN 50-447 GE PROPOSED EVALUATION PLAN FOR THE CONSIDERATION OF SOURCE TERM ISSUES In the meeting involving GE and NRC Staff personnel held on February 22, 1984, an actlen plan was proposed to address source term issues as part of.the GESSAR II Severt Accident Review.
It is General Electric's intent to pnrfe.rm a series of sensitivity studies on various parameters affecting containment failure modes and timing and fission product release.
These sensitivity studies will be evaluated to define the impact on the GESSAR II plant risk as quantified by the GE Probabilistic Risk Assessment. They wi11 also be used in GE studies of proposed oesign socifications.
The
- attachment provides additional details of the proput.ed t.unsitivity studies.
It is nur intent to perform the indicated studies and discuss the results with the Staff on March 20,,1984.
If there are any quesLlans on the information contained herein, please contact me or Mr. Kevin Holtzclaw (408-975-7506).
Very truly yours.,
r-J utrk, Manager Systems Iirensina N 1 ear Safety & Licensing Operation JFQ: rf: rm/G03084 Attacheen,t cc:
F. J. Miraglia (NRC)
C. O. Thos:as (NRC)
D. C. Scaletti (NRC)
L. S. Gifford (GE-Bethesda)
A. Thadani (NRC)
R. Villa (GE)
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NO.025 003
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SOURCE TERM ISSUES - SENSITIVITY STUDIES s
1)
Core heatup GE will vary t.he MARCH input parameters over a. reasonable range (such that fuel temperatures are less than 5080'F)
Core slump fraction will be explicitly varied around the 65 percent valise tisert in t.he PRA.
2)
Oxidation model following node melt GE will show the sensitivity of the NARCH results to alternativa assumptions on flow blockage by melted nodes.
3)
In-vessel vaporization GE will show the sensitivity in the source terms to release of significant fractions of cesium, iodine and tellerium after vessel failure.
4)
Primary system retention GE will vary the in-vessel retention factor from 1 to 10.
5)
Core slump fraction 7-.
This parameter will be varied in step 1).
6)
Melt-through of vessel lower head GE will assess alternative vessel failure modes and their impact on timing and fission product release.
7)
Ex-voscol vaporization GE will assess the impact of various concrete compositions and fission product release assumptionc.
8)
Suppression pool scrubbing
[
GE will vary the pool DF's over a reasonable range which accounts for'uncertanties in the inputs (e.g. particle size distribution) and which is consistent'with current scrubbing date.
9)
Suppression pool bypass CE will p;avide en evaluation of potential bypass pathways and assess their potential impact on plant risk.
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- Site sensitivity l
10) l GE will...=== tl.a plant i k.t.,hiwfe pupul Liun d4ns i ty s ilw.
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STAFF REVIEW GESSAR Il PRA SOURE TERMS
> RISK
- P/M STUDY FOR JULY 84 SER RANGE CALCULATIONS RELEASE FROM FUEL
'DEPOSITIONINPRIMARYSYSTEM EX-VESSEL RELEASES POOL DF CONTAltFENT PROCESSES BASED ON 3 GRAND GULF SEQUENES SEQUENE SENSITIVITY STUDIES 15 " SEQUENCES" PRODUCED
" FULL" EXERCISE OF ASTP0 CODES FOR, LIMITED SEQUENE SET BY-PASS OF POOL HYDROGEN DETONATION FAILUPE LOCATION STRUCTURAL ANALYSES IN PROGRESS TREATING AS TW P.ATHS HYDROGEN BURN -OPEN FREE PATH e
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4 SITES FOR CONSEQUENCES - USE EXISTING SITES HIGH, EDIUM, LOW POPULATION SITES
-EVACUATICI' PARA 6 TOR NOP?AL AND DISASTER C0:OIT10ts SITE SPECIFIC ETEOROLOGY PREVENTION / MITIGATION STUDY REGULATORY BASIS IN 10CFR50,34(F)(1)(1)
POTENTIAL FOR GE/ STAFF DISAGREBfhT DIFFEPS T CHARAtitKlZATION OF SAME CCDF m_
DIFFEREhT RANGES OF CCDF SOME DECISIONS ON P/M FEATURES CAN BE MADE REGARDLESS OF DISAGRECMENT BETWEEN STAFF AND GE r
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VANESA RESULTS FOR J}
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B N L -T C - S E Q U E N C E A T G R A N D G U L F
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l SIZE RATE
. TIME TEMP GAS C0pC DENSIFY (9 cm )
(um)
(q/S)'
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(S)
(K)
(MOLES /S)
(g/M STP)
O 2151 11.75 40.90 5.53 0.52 11.76 1200 2361 35.80 127.21 3.01 0.93 111.36 2400 2357 53.73 123.25 2.99 0.92 161.94 3600 2325 46.18 119.12 2.94 0.91 134 52 4000 2321 43.32 119.88 2.90 0.92 126.99 6000 2325 42.38 120.84 2.88 0.92 125.23 7200 2329 43.16 121.39 2.86 0.93 128.10 8400 2330 43.87 121.21 2.85 0.93 130.04 _
9600 2319 44.78 119.12 2.85 0.92 130.44 10800 2304 45.78 116.24 2.84 0.92 130.14 12000 2291 46.70 113.80 2.84 0.91 129.96 13200 2282 47.05 111.74 2.84 0.90 128.55 14400 2274 46.23 109.89 2.84 0.90 134.21 15600 2266 45.09 108.13
- 2. 84 0.09 119.21 16800 2260 44.05 106.46 2.84 0.89 114.68 10000 2253 42.90 _
104.84 2.:84 0.88 109.98 19200
,2246 42.30 103.32 __
2.85 0.88 106.88 20400 2240 42.38 101.84 2.85 0.88 105.55
- 0. 87 105.08 21600 2235 42.8,3 100.34 2.85 _
44.00 98.68 2.86 0.86 _
106.1G_
22800 2229 96.20 2.88 0.86 109.56 24000 2224
,46.57 25200 2220 47.70 9.28 3.06 0.36 10.82 26400 2215 46.30 9.23-3.04 0.38 10.45 27600__
2209 55.14 9.16 3.02.
0.38 12.35
.