ML19346A106
| ML19346A106 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 05/26/1981 |
| From: | Burwell S Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8106050086 | |
| Download: ML19346A106 (50) | |
Text
,.
s MAY 2 6 1961 MEETING S'""'"'" DISTRIBUTION Docket File G. Lear
"*C PDR W. Johnston Local PDR S. Pawlicki illC/NSIC/ Tera V. Benaroya N. Hughes
- 2. Rosztoczy
- ."#1 Reading W. Haass u Denton D. Muller E. Case R. Ballard O. Eisenhut W. Regan R. Purple D. Ross B. J. Youngblood P. Check A. Schwencer Chief, Power Systems Branch F. Miraglia
- 0. Parr
" filer F. Rosa G. Lainas W. Butler R..uiiiner W. Kreger J. P. Knight R. Houston R. Bosnak Chief, Radiological Assessment Branch F. Senauer L. Rubenstein R. C. Jackson T. Speis Project Manager S. B. Burwell M. Srinivasan Attornev. OELD J. Stolz M. Rushbrook S. Hanauer 0IE (3)
W. Gammill ACRS (16)
T. Murlev A
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F. Schroeder R. Tedesco o
4/ -
C\\I' 9 D. Skovholt p
f/
M. Ernst (ri)[
$9 R. Baer NRC
Participants:
? JUN 011981
- 1)'
b-C. Berlinger
- 5. durwell K. Knic' Hulbert Li T. Dunning i p,, w "i nc u m n $
G. Knighton a
s A. Thadani C. Rossi (p/
f D. Tondi J. Guttman S. Diab J, Kramer S. Shum D, Vassallo
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Chang Li P, Collins D. Ziemann bec: Applicant & Service List l
.N 1,,
8106050 0 %
6
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- ?g@ REC%
UNITED STATES O
E j ) 5.( (j NUCLEAR REGULATORY COMMISSION j
.p WASHINGTON, D. C. 20555 g
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MAY 2 61981 Docket Nos. 50-445 and 50-466 APPLICANT:
Texas Utilities Generating Company FACILITY:
Comanche Peak Steam Electric Station Units 1 and 2
SUBJECT:
SUMMARY
OF MEETING ON COMANCHE PEAK DESIGN CHANGE AND RESPONSES TO RSB QUESTIONS Summary A meeting was held at NRC Headquarters, 7920 Norfolk Avenue, Bethesda, Maryland on Tuesday, March 10, 1981. The purpose of the meeting was to permit Westinghouse to brief the NRC staff on a proposed design change to eliminate the boron injection tank from the emergency core cooling system, and to discuss information submitted in FSAR Amendments 14 and 15 on baron dilution transients and responses to Reactor Systems Branch questions. Attendance at the meeting is listed in Enclosure 1.
Meeting Details The applicant opened the meeting by advising that FSAR Amendment 16 to be submitted March 31, 1981 will show the proposed deletion of the boron injection tank from the emergency core cooling system. Comanche Peak will be the first Westinghouse reactor to be licensed without the baron injection tank.
However l
the concept has been reviewed on RESAR 414, Byron-Braidwood and South Texas.
t I
G. Narasimhan, Westinghouse, gave the first part of the presentation on the deletion of the boron injection tank using the slides identified as Boron Injection Tank Removal, Enclosure 2.
This presentation reviewed the impact of deleting the boron injection tank on Westinghouse power reactors in general.
The steam line break is the only design basis accident (Chapter 15) for which credit is taken for the boron injection tank. The presentation concentrated on the response of the nuclear syster to a steam line break with and without the boron injection tank.
I F. Thomson, Weu,.inghouse, gave the second part of the presentation using the slides identified as Comanche Peak Baron Injection Tank, Enclosure 3.
This presentation reviewed the impact of deleting the boron injection tank on Comanche Peak.
Again, the presentation concentrated on tha steam line break accident with and without the boron injection tank.
Comparison of the transient response shows that core power becomes essentially the same with and without the boron injection tank in about 300 seconds.
t l
l l
2 l-The applicant described the removal of the boron injection tank as an operational advantage, using FSAR Figure 6.3-1 Sheet 1 to illustrate the auxiliary equipment needed to support the boron injection tank.
The second part of the meeting started with a presentation by V. Koch, Westing-house, on the design modification responding to the boron dilution transients using the slides identified as Inadvertent Baron Dilution, Enclosure 4.
The presentation tracked the earlier Westinghouse presentation given at the meeting of October 15, 1980.
The staff raised questions about the administrative controls on valves within the chemical and volume control system which were resolved in the discussion.
The staff raised questions on how the electrical controls of these valves tie into the instrumentation and control drawings and the impact of control failures on system performance.
The applicant will provide additional information on these matters.
The last part of the meeting consisted of a discussion of the applicants responses to Reactor Systems Branch questions.
Of the 51 questions issued in our letter of November 20, 1980, the applicant has responded to 40 questions in FSAR Amendments 14 and 15. The applicant expects to respond to 9 more in FSAR Amendment 16 at the end of March, and the remaining 2 in April. We discussed the applicants responses to several of the questions.
In most cases the discussion resolved the matter.
The applicant agreed to revise the response to Question 212.96(f) to clarify the consideration on decay and plate-out.
The atplicant also advised it is revising the low pressure overpressure protection system.
S/
/
n S. B. Burwell i
Licensing Project Manager Licensing Branch No. 2 Division of Licensing
Enclosure:
As stated cc w/ enclosures:
l See next page
_ ~
Mr. h. O. Omsj Exec;+4"a "*-a Dresident and General Monover Texas U" " : 0:r. rstir.; C0mpany 2001 Bryan Tw-ee Dallas, Tc.;;
75201
- Mi:h:!:: !. D.cynclds, Esq.
Mr. Richard i ennke Debavnica A Liberman Citizens for Fair Utility Regulation 1200 Seventeenth Street 1668-B Carter Detve Washinaton, D. C.
20036 Arlington, Texas 76010 Spencer C. Relyea, Eso.
Resident Inspector /Lomanche Peak Worsham, Forsythe & Sampels Nuclear Power dtation 2001 Bryan Tower c/o V. S. huclear Regulatory Commission Dallas, Texas. 75201 P. O. Box 38 Glen Rose, Texas 76043 Mr. Homer C. Schmidt Manager - Nuclear Services Texas Utilities Services, Inc.
2001 Bryan Tower Dalias, Texas 75231 Mr. H. R. Rock i
Gibbs and Hill, Inc.
~
~
393 Seventh Avenue New York, New York 10001 Mr. A. T. Parker Westinghouse Electric Corporation P. O. Box 355 Pittsburgh, Pennsylvania 15230 David J. Preister Assistant Attorney General Environmental Protection Division P. O. Box 12548, Capitol Station Austin, Texas 78711 Mrs. Juanita Ellis, President l
Citizens Association for Sound Energy i
l 1426 South Polk Dallas, Texas 75224 Geoffrey M. Gay, Esq.
West Texas Legal Services l
100 Main Street (Lawyers Bldg.)
i Fort Worth, Texas 76102 l
l
ENCLOSURE 1 ATTENDANCE LIST FOR MARCH 10, 1981 MEETING COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 Texas Utilities Services, Inc.
NRC Staff F. Madden S. Burwell J. Shrewsberry Hulbert Li T. Dunning Westinghouse C. Rossi J. Guttman
- 0. Popp S. Diab G. Narasimhan D. Shum R. Steifler Chang Li F. Thomson V. Koch EG&G M. Torcaso S. Bruske Gibbs & Hill
- 9. Kumar i
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1 SIM%RY OF BIT RBiNAL RESULTS NRCCRITERIA CONDITION II/IV + 10CFR20/10CFR100 l
l COREINTEGRITY RR ALL CASES, WITH OR WITHOLTf BIT l
l DNBR " 1.3 l
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NO FUEL FAIUJRES CONTAINUf INTEGRITY W/ BIT W/0 BIT PEAK TEMP (*F) 333 334 PEAK PS (PSIA) 37.5 37.5 l
ALL SAFETY CRITERIA MET i
3-16
2(LOSURE4 INAINERHT BORON DIUJTION COMANQE PEAK FSAR SECTION 15A.6:
IEWS AND CVCS OPEFATION AND FAILUE MODES SYSTEM HARDWARE MTIFICATIONS TO ADDESS REG. GJIDE 1.70 REV. 2 REDUIREENTS ANALYSIS ASSlWTIONS AND ESULTS 4-1
IESCRIPTION OF ACCIENT INITIATION IMS/CVCS FAIWE MEES:
l D
VALVE El.ECTRICAL OR EOMNICAL FAIWES 2)
MAKEUP CONTROLL9 FAIWES 3)
OPERATOR INITIATED FAIWES l
ESULT IS INCEASED MAEUP FLOW #0/0R DECEASED BORIC ACID FLOW TORCS l
OPERATOR HAS SEVERAL It01 CATIONS AVAllABLE TO HIM TO VERIFY CHANGE INSTATUSOFRCSMAkEUP 1
1 i
9 4-2
l ANALYSIS ASSLNPTIONS ANALYSIS COERS ALL MEES OF OPERATION AS DEFIED BY STS CONSERVATIVE ASSlfFTIONS MADE FOR BORON CONCENTRATIONS, BORON WORTHS, SHJTDOWN MARGINS, #0 RCS VOLLES DIUJTION RATE LIMITED BY ADMINISTRATIVE CONTR0lS WHIl.E RCS IS DEPRESSlJRIZED.
DIUJTION RATE LIMIED BY CHARGING PlfP CAPACITY WITH RCS AT PRESSURE 4-3 l
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RERJELING DIlllTION PRECUJDED BY MINISTPATIVE COUR0LS WICH ISOLATE RCS FRm UNB0 RATED MAEljP WATER s
COLD SHRI)0WN MINIM SHJTDOWN MARGIN OF 1% WK MOST LIMITING W N RCS WER LEVEL DRAIED TO MID-N0ZZLE WHILE ONRHR MAEUP FLOW RESTRICTED TO 150 GPM FOR llilS CASE u Sana M u STMBy MINI M SRITDOWN MARGIN G 1.6% W K MET LIMITING WHILE ON OE TFAIN OF RHR WITH RCS FILLED E VENTED MAXIM PERMISSIBLE MAEUP FLOW PATE IS L125 GPM (ND RESTRICTIONS EESSARY FOR CWANCE PEA 10
STARTUP MINIM SHJTDOWN MARGIN OF 1.6% $/K ALL4RCP'SOPERATING DIllJTION FLOW LIMITED BY CAPACIT/ OF TW OMRGING PLPFS FULL RCS ElfE MIMJS PESSURIZER ASSUMED AVAILABLE FOR DILLITION POWEROPERATION i
DILUTION FLDW LIMITED TO MAXIM LEIDOWN FLOW WEN IN
- 1T0MATIC PESSURIZER LEVEL CONTROL DILUTION Fl.0W LIMITED BY MAXI M OF 2 0%RGING FU PS IN OPERATION WEN IN MANJAL PRESSURIZER LEVEL CONTFDL (M)ST LIMITING) 4-5
RESULTSOFANALYSIS I
COLD SMHDOWN, HDT SRIIDOWN, RIT STMBY SOURCE RANGE NIS, BY WAY OF A MIC80Pidfiil, IEICATES DOUBLIE OF EUTRON FUJX DUE TO DIUJTION ALARM ALERTS TE OPERATOR TO A FUJX DOUBLING CVCS AUTO %TICALLY EALIGED TO SWITCH SUCTION F10M VOLIE CONTROL TANK TD RWST (CLOSE VALVES 1-LCV-112B E C, OPEN VALVES 1-LCV-112D E E IN TE CVCS) j THIS AlfiU% TIC ACTION MINIMI2ES BE APPRDACH 10 CRITICALITY M REGAINS LOST SRJfDOWN MARGIN 4-6 i
STAR 11JP OPERATOR INTENTIONAL 1Y DIWTES IN THIS MODE TO GO TO POWER IN TE EVENT OF AN INADVERIBT DIlllTION WHILE ESCAl.ATING IN POWER, THE R. ANT TRIPS ON TE LOW SETPOINT OF PLWER RANGE HIGH fEJiRON FWX OPERATOR HAS > 15 MINJ1ES FROM TRIP TO MANUAL 1Y TERMINALE DIlliTION AND INITIA1E B0 RATION BEFORE COPLETE I.0SS OF SHJTDOWN MARGIN I
l 4-7
POWER MANJAL E CONIRCL:
TE EACTIVITY EXCURSION ESULTS IN E/GR TRIP ON OHIBfEPATUE N-16 OPERATOR HAS > 15 MINJ1ES FE TRIP TO TEMINATE DILUTION ANDINITIATEB0 RATION THIS TPANSIENT BOLN)ED BY UNCONTROU.ED E WF&PAWAL AT F9WERTRANSIENT AUTm ATIC E CONTROL:
OPEPATOR ALERIED TO DILUTION BY E INSERTION LIMIT ALARMS
> 15 MINJTES IS AVAllABLE FRm MNS FOR OPEPATOR TO TEMINATE DIlllTION Am INITIATE B0 RATION 4-8
CONCulSIONS I
IN ALL MTES OF OPERATION, AN IMNERTENT DIUJTION IS PECLUDED, AllTO-MATICAU.Y TERMIMTED, OR TER11MTED BY OPERATOR ACTION TE REACTOR IS BROUGHT TO A STABLE C0f0lTION WITH EE LOST SWIDOWN MMGIN EMIED, 4-9
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