ML20126M388
| ML20126M388 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 12/23/1992 |
| From: | Boyce T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9301080290 | |
| Download: ML20126M388 (76) | |
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UNITED STATES l"
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NUCLE AR REGULATORY COMMISSION g
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December 23, 1992 Docket No.52-001 APPLICANT: GE Nuclear Energy Company (GE)
PROJECT:
Adv nced Boiling Water Reactor (ABWR)
SUBJECT:
SUMMARY
OF MEETING WITH GE ON DECEMBER 15, 1992 A public meeting was held between the Nuclear Regulatory Commission (NRC) staff and GE Nuclear Energy (GE) at the NRC office in Rockville, Maryland, on December 15, 1992.
The purpose of this meeting was to discuss issues related to the indust ~ and staff review of the ABWR inspections, tests, haalyses, and acceptance criteria (ITAAC). is a list of those who attended, contains the viewgraphs presented at the meeting, and Enclosure 3 contains GE's markups to the ITAAC for several systems of the ABWR.
GE opened the meeting by presenting a short summary of the progress of the development of the ITAAC.
The nature of the changes to the Tier 1 material were discussed; however, no conclusions were reached on the material.
The staff will evaluate the changes as part of the resolution of open items in the draft final safety evaluation report (DFSER) for the ABWR, GE will provide the related Tier 1 material to the NRC in conjunction with these open items.
GE will include in the submittal their responses to the staff's comments provided in a letter of August 12, 1992, pertaining to the Tier 1 design certification material (Stage 3).
The staff proposed to send a multi-disciplined team to GE to review the proposed markups to the ITAAC, and tentatively projected this to occur during the week of January 10-15, 1993.
This effort and the further development of the ITAAC will be discussed at the next senior management meeting with GE on January 21, 1993.
The staff reiterated that the Commission's metric policy should be implemented for all federal publications.
This means that the Tier 1 material for the ABWR should specify metric units with english units in parentheses.
Ta staff expressed its concerns over the treatment of motor-operated and
! mr-operated valves in the Tier 1 material.
The staff indicated that the
. acerns of Generic Letter 89-10, up to and including supplement 4, needed to be addressed appropriately by GE.
An approach was discussed whereby GE would identify the safety functions of important valves, and specify the testing requirements applicable to the ITAAC.
This issue required parallel resolution in the standard safety analysis report as well.
The staff commented that the main steamline material in the ITAAC appeared not to address the agreements reached previously that the main steamline would meet the seismic and stress requirements necessary to address radiological j
release considerations, not merely maintain leak tightness.
GE stated that they wot.1d correct the apparent inconsistency to appropriately reflect the design commitments needed for not having a main steamline leakage control system.
07002,v f;^b I
9301080290 921223 PDR ADOCK 05200001 f
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s December 23, 1992 The use of boilerplate 11AAC entries to verify particular aspects of the design were discussed.
GE agreed to provide these to the staff prior to the review team going to GE in January 1993.
The requirements for interfaces were discussed.
The staff reiterated the requirements of 10 CFR Part 52 for GE. The staff emphasized that only site-specific features should be true interfaces, and that it was the responsibil-ity of the combined license (COL) applicant to propose the details of meeting these in the COL application.
(Original signed by)
Thomas H. Boyce, Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License R"newal Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/ enclosures:
See next page DISTRIBUTION w/ enclosures:
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NAME: PShea ey DATE: 12g/2 12/p/92 12/
/92 12/
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0FFICIAL RECORD COPY:
GE-MTG92,THB g-
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GE Nuclear Energy Docket.No.52-001 cc:
Mr. Patrick W. Harriott, Manager-Mr. Joseph Quirk Licensing & Consulting Services GE Nuclear Energy GE Nuclear Energy General Electric Company 175 Curtner Avenue 175 Curtner Avenue, Mail Code 782 San Jose, California 95125 San Jose, California -95125 Mr. Robert Mitchell General Electric Company i
175 Curtner Avenue San Jose, California 95125 1
Mr. L. Gifford, Program Manager Regulatory Programs GE Nuclear Energy 12300 Twinbrook Parkway Suite 315 Rockville, Maryland 20852 Director, Criteria & Standards Division Office of Radiation Programs U. S. Environmental Protection Agency 401 M Street,-S.W.
Washington, D.C.
20460 Mr. Daniel F. Giessing U. S. Department of Energy NE-42 Washington, D.C.
20585 Mr. Steve Goldberg Budget Examiner 725 17th Street, N.W.
Room 8002 Washington, D.C.
20503 Mr. Frank A. Ross U.S. Department of Energy, NE-42 Office of LWR Safety and Technology 19901-Germantown Road Germantown, Maryland 20874 Mr. Raymond Ng 1776 Eye Street, N.W.
Suite 300 Washington, D.C.
20006 Marcus A. Rowden,-Esq.
Fried, Frank,- Marris, Shriver & Jacobson 1001 Pennsylvania Avenue, N.W.
Suite 800 Washington, D.C.
20004 L
' Jay M. Gutierrez, Esq.
1 Newman & Holtzinger, P.C.
1 1615 L Street, N.W.
Suite 1000
. Washington, D.C.
_20036
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o, GE ABWR ITAAC MEETING DECEMBER 15, 1992 NAME QRGANIZATION William Russell NRR/ADT Jerry Wilson NRR/ADAR/PDST Mike Finkelstein OGC/H&E/ Advanced Reactors Tom Boyce NRR/ADAR/PDST Conrad McCracken NRR/ADT/SPLB Jim Lyons NRR/ADT/DSSA William Burton NRR/ADT/DSSA Goutam Bagchi NRR/ADT/DET
=
Chet Poslusny NRR/ADAR/PDST Bob Pierson NRR/ADAR/PDST Adrian Heymer NUMARC Steve Franz GE Tony James GE
j-ISSUES DISCUSSED / RAISED AT THE 12/8-12/10 PLANT SYSTEMS BRANCH MFETINGS ISSUE STATUS RELATIONSHIP OF TIER 1/ITAAC TO SAR GE:
TIER 1/ITAAC CAN ONLY BE WRITTEN AFTER'SAR DESIGN ISSUES ISSUES RESOLVED; I.E., ITAAC-IS NOT A' VEHICLE FOR ISSUE RESOLUTION STAFF:
CONCUR DESCRIPTION OF ANALYSES CALLED FOR GE:
DESCRIPTION CAN BE IN EITHER ITAAC TABLE DR BY ITAAC SAR STAFF:
CONCUR LEVEL 0F. DETAIL IN TIER 1 GE:
GRADED APPROACH AS DISCUSSED AND AGREED TO 4
OVER THE LAST-TWELVE MONTHS STAFF:
NEEDS FURTHER DISCUSSION TREATNENT OF 89-10 GE:
NOT FULLY RESOLVED AT THE SSAR LEVEL, THUS TricooGH 5v09:401C/1f 't TIER 1 COfMITNENTS NOT FINALIZED.
LIMITED MOV TESTING C0fMITNENTS (RCIC,_RWCU) mi STAFF:'
NEEDS FURTHER DISCUSSION 8
f AJJ 12/15/S2
I l
ISSUES DISCUSSED / RAISED AT THE 12/8-12/10 PLANT SYST MS BRANCH MEET l
l l
l STATUS ISSUE SYSTEM SCOPE DEFINITION GE:
CURRENT LEVEL OF DEFINITION IN TIER 1 FUNCTIONAL DIAGRAM IS SUFFICIENT STAFF:
CONCUR, BUT THINK SOME FINE-TUNING IS NEEDED CASE-BY-CASE (CLEAR DEFINITION OF SYSTEN BOUNDARIES)
GE:
SAR, TIER 1 MKS NETRIC UNITS STAFF:
WANTS DUAL UNITS BU1 UNDERSTAND, ACCEPT GE APPROACH ANALYSIS ISSUE ON 2.10.1 ITEN 2 GE:
CRISP ACCEPTANCE CRITERIA (APPLIES TO PIPING DAC AL50)
STAFF:
LOOKING FOR TECHNICAL DEFINITION OF ACCEPTANCE CRITERIA USE OF ASNE N STAMP AS ACCEPTANCE GE:
FULLY ACCEPTABLE CONCEPT STAFF:
PROCESS NOT HARDWARE-ORIENTED CRITERION 1
AJJ I2/15/92
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ISSUES DISCUSSED / RAISED AT THE 12/8-12/10 PLANT SYSTEMS BRANCH MEETING STATUS ISSUE COMPONENT TESTING -- HOW MUCH IN GE:
CASE-BY-CASE TREATMENT OF KEY ITEMS:
I.E.,
NOT COMPREHENSIVE ITAAC7 STAFF:
NEEDS FURTHER DISCUSSION BY MECHANICAL PEOPLE l
l DRAINS ADDED TO DESIGN CERTIFICATION GE.
NEEDS A TIER I ENTRY (NEW ITEM)
STAFF:
SCOPE BOILERPLATE ITEMS GE:
IT WOULD BE MORE EFFICIENT IF THERE COULD BE A ONE-SHOT SIG O FF OF A SET OF STANDARDIZED STAFF:
ITAAC TABLE ENTRIES PHYSICAL VS. MECHANICAL SEPARATION GE:
USE PHYSICAL.
BASIS:
WORD USED IN REGULATIONS MORE DESCRIPTIVE (NOTE:
NOT IMPLEMENTED 100%)
STAFF:
CONCUR l
AJJ I2/I5/92
ISSUES DISCUSSED / RAISED AT THE 12/8-12/10 PLANT SYSTEMS BRANCH MEETING STATUS ISSUE GE:
{0N HOLD STAFF:
l l
INTERFACE ITAAC GE:
A) PROPOSING THE COL APPLICANT SAR STRATEGY
- NEEDS STAFF REVIEW B) CONTENTS NEED FURTHER DEVELOPMENT l
STAFF:
A)
B) CONCUR 1
GE:
- 1) CODE CLASS ON FUNCTIONAL DIAGRANS; NO HOW TO HANDLE:
DIRECT ITAAC ENTRY I) ASME CODE CLASS,
- 2) QUALITY GROUP (USUALLY) IN TEXT; NO l
- 2) QUALITY GROUP,
~~
DIRECT ITAAC-ENTRY
- 3) SAFETY CLASS IN TIER 1
- 3) SAFETY CLASS NOT ADDRESSED IN TIER 1 STAFF:
REVIEWING THE ISSUE l
AJJ 12/15/92
~
ISSUES DISCUSSED / RAISED AT THE 12/8-12/10 PLANT SYSTEMS BRANCH MEETINGS ISSUE STATUS BACKFLOW PROTECTION
.GE:
SAR/ DESIGN ISSUE.
ITAAC TO BE USED (IF f
APPROPRIATE) TO VERIFY DESIGN FEATURE (S). IN PLACE STAFF:
CONCUR i
ENVIRONMENTAL SEPARATION GE:
VERIFIED BY BUILDING ARRANGEMENT AND HVAC CONFIGURATION ITAAC.
NO SEPARATE ITAAC REQUIRED STAFF:
CONCUR-(?)
ELECTRICAL SEPARATION GE:
ISSUE PART OF THE GENERIC ITAAC DISCUSSIONS STAFF:
AJJ I2/15/92
3
-Q ABWR DESIGN CERTIFICATION WHAT WILL IT TAKE TO CLOSE OUT TIER 17
- 1. CLOSE OUT SAR DESIGN ISSUES
- 2. RESOLVE GENERIC ISSUES APPROACH
- 4. SCHEDULE LONG, HARD, GRIND-IT-00T MEETINGS WITH FULL-TIME ATTENDANCE KNOWLEDGEABLE ENGINEERS PART-52, TIER-1,.ITAAC EXPERTS NO EASY WAY TO DO IT Jb)
AJJ
- 12/15/92 l
l 1
ENVIRONMENTAL QUALIFICATION OF ABWR MSIV ACTUATOR DEFINITION'0F CONDITIONS - SPEC OPERATING TIME TWO ENTRIES PROFILE,10+ ENTRIES TEMPERATURE PRESSURE-PROFILE, 10+ ENTRIES HUMIDITY ONE ENTRY TABULAR ENTRIES-RADIATION TABULAR ENTRIES AGING DYNAMIC LOADS TIMES AND CYCLES PLUS 4 PAGES RRS 10-15 PAGES OF DETAILED TECHNICAL INFORMATION L
OTHER ISSUES y
SOME INPUT DATA DESIGN-DEPENDENT TESTING METHODOLOGIES DESIGN / MATERIALS DEPENDENT i
l l
~
ENVIRONMENTAL QUALIFICATION 0F ABWR MSIV ACTUAIAR TEST SEQUENCE INSPECTION / BASELINE TEST NORMAL RADIATION AGING FUNCTIONAL TEST THERMAL AGING FUNCTIONAL TEST MECHANICAL AGING FUNCTIONAL TEST DBE RADIATION FUNCTIONAL TEST DYNAMIC / SEISMIC FUNCTIONAL TEST DBE - POST DBE FUNCTIONAL TEST DISASSEMBLY / INSPECTION
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, ABWR onign Document 4putb*l.IMb SCCf/CAU-TITl. G GLily Tabla of Contents
- T'M / eerg
/ ttevif:W6S Sf M U M 4M-
((gj App ppt /@
10 Intr oduction L1 Ceneral Phnt Devrintion l. ),
6 EI)G Aht. F #but t r es s.(
} Tier 1 Materbl for AMWR Systenv, g,3 p g pf gjg
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?1 Nuclear Steam Supply
./2.1.1 Dractor Preuure Vessel Sptem
- 2.1.2 Nuclear P, oiler System d o 1.3 Revtor Recirculation System oo Control and Instrument
- 2.2.1 bd Control and Information System
/ 12.2 Control Rod Drive System v'?.23 Feedwater Control System
+/ 2.2.4 Sondby Liquid Control System t 2.2.5 Wutron Monitoring Sptem
./ 2.2.6 Remote Shutdown Sptem
- 2.2.7 Fesctor Protection Sptem
/ 2.2.8 Recirculation Flow Control System
,/ 9.2.9 Autnmade Power Regulator Sptem v 2.2.10 Mm Bypn.u and Pressure Control Sptem
@.2,11 Pmceu Computer System 2.2.12
- ,% fueling Platform Control Comouter
- 2.2.13
[CRD.RemonLMachine Control Computer o.!
Radiation Monitoring d 2.3.1 Pmeess Radiation Monitoring (PRM) Sprem
- 2.3.2 Area Radiation Monitoring Sptem 044
-% @JSi='S:ti.gSptr-o.3./ 3 Nnntement Atmcspheric Monitodng Sptem 94 Core Cooling
/ 2.4.1 Residttal Heat Removal Sptem
,/ 2.4.2.
High Premure Core Flooder (HPCF) Sptem
/2.4.3 Iok Detection and holation Sptem 4.4.4 Reactor Core bolation Cooling System 25 Reactor Servicing Equipment
- 2.5.1 bei Servici.nr Eauioment
- 2.5.2
.Mkcellmeous Servicing Equipment
, - 2.5.3 Rnctor Preuure Venel Servicing Eeninment
- 2.5.4 ffV Internal Servicing Equioment
./ 2_.5.5 Refueling Equipment
/ 2.5.ti Fuel Storage Fr9/ BACk6
+ - 2.5.7
.Under Venel Servicing Equioment
- 2.5.8
.CRD Mainten2nce F2cility
- 2.5.9 Jntemal Pumo Maintenance Facility
< - 2.5.10 fuel Cask Cleaning Facilitt 6/1/97
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. 41; p-ARWR oesign Document
--93 11 Pj;mt Stan uo Test Eouiomerit
-- P 5.10 IntqnKe In3necdon Eauinment c
Reactor \\uviharv
/ '.t 6.1 Reactor Water Cleanup Sptem
-- 262 Fuel Pool Cooling and Cleanup Sptem
-263 sunnression Pool Cleanup System 97 Control Panch
'/R7 !
Main L,ontrol Room Panel
- 2.72(110 Radioactive Waste Conuol Panel
- 273
!ecal Control Paneb
- 2 7 4(110 Instrument Racks da75 Multiplexing
- " 7 Ah.15)Iocal Control Box Nuclear Fuel
/281 Nuclear Fuel v'2.8.2 Fuel Channel (2A3 ConnolRod 2, g Lgg3g pggyg gpg;7ogips 2.0
' Radioactive Waste 4 9.1 Pedw2ste Sptem 2 10 Power Cvcle s/2.10.1 Turbine Main Steun Sptem
' '2.10.2 Cor.densate Feedwater and Condensate Air Extraction Sptem 2.10 3 Jinyr Drain and Vent Sptem
'1.10 A Condansate PunScation Sptem
- 2.10.50dOndennte Filter Facility
- 2.10.@n* Condensate Deminers1her v'2.103 Main Turbine
-- 2.10.8p.1 Turbine Control Sptem
2.10.9 Turbine Gland Steam Sy.em
- 2.10.10 Turbine I.ubricating Oil Sntem
- 2.10.11 Moisture Sewrator Henter
- 2.10.12 fatraction Sntem
/ 2.10.15 Turbine Bypau Sptem
- 2.10.14de$ Reactor Feedwater Pump Drier
- 2.10.15 Aghias Auxiliary 8tCam bntem
- 2.10.1@etenerator
- 2.10.17 Hydrogen Can Cooline Sntem
- 2.10.18 Sener2tnr Cooling Sverm
- 2.10.19 GeneratorSeallnr Oil Sntem
- 2.10.20 far A.10.21 Main Condenser 2.10.22 Off-Gas Sptem
/ 2.10.23 Circulating Water Sptem
- 2.10.24 Condenser Geanup Facility in uw2
.. =
EG GIi 4
ABWR oesign Document 2 11 Station Auxiliarv
-2111 Meeup Water (Punfied) System 2 11.2 Mneup Water (Condensate) Systern
/ 2 11.3 Reactor Building Cooling Water Sptem
-- 2.11.4 Turbine Building Cooling Water Syste a
~ 2,11.5 HVAC Normal Cooling Water System W 11.6 IWM' F.mergency Cooling Water System
-- 2.11.7 Lhygen Iniection System e').ll.8(4.1) l'Hmate Heat Sink v2.11.9 Feacw Senice Water System
-- 2.11.10 7erbine Service Water System
- 2.11.11 Stuinn Semce Air System 4 11.12 Instrument Air System
/ 2.11.13 High Pressure Nitrogen Gas Supply Ststem -
- 2 11.14 lleating Steam and Conderaate Water RegirpAs,1cn)
- 2 11.15
}iouse Boiler
-211.16 Hot Water Heating Sntem t 411.17 Hydrogen Water Chemistry Sntem
< - 211.18, Zinc Iniettion System
- 2,11.19 Breathing Air System
- 2.11.20 Prm-* Sampling System
- - 2 11.21 Freeze Protection System
< -o.11.22
, Iron Injection System 9 19 Station Electrical
/ 2 12.1 Electrical Power Distribution System
- 2 12.2 l' nit Auxiliary Transformer
- 2.12.3 Imlated Phase Bus
-2.12.4 yA'onwgregated Phase Bus
- 2.12.5 h!ctal Clad Switchgear
- ? 12.6 Pnwer Center
- 2.12.7 Motor Control Center
- 2.12.8 Rac way System
-2.12.9)
Grounding Wire
/ 2.12.10 Electrical Wtring Penetrations A.12.11 Combustion Turbine Generator d.12.12 Direct Current Power Supply 2
/ 2.12.13 Emergency Diesel Generator System (Standby AC Power Supply) 9!2,11 "me "s&Sy ten Mtern- %- h= cupply
- 2.12.lM Vital AC Power Supply And AC Instrument and Control Power 5
Supply Systems
~ 2.12.lF(ny3nstniment and Control Power Supply
- 2.12.lT6 Communicat'on System
-212.18.7 1.ighting and Servicing Power Supply Systems 2 19 Power Transmission
- 2.13.lfu,0Rewrve Auxiliary Transformer iv 6/1/92 w
A RWR oesign Documn'.._._ _ _ _
2 14 Containment nd Environmental Control
/2.14 = 1 P man Containment System
, - 2.14.Rin!bncainme nt Internal Structures
-2.14.S't.N) Reactor Pressure Veuel Pedestal
-2144 Standby Ga.s Treatment System
~ 2.14.5 P.Q'.ff.q.nule and Leak Testing Facuny
- 2.14 6 Atmospheric Control System
. 2.14.7 Dnwell Cooling System
/ 2.14.8 Fbmmability Control System
- 2.14,9 Suopreuinn Pool Temperature Monitonng System 2 15 Stmetures and Servicing 215.Yt % Foundation Work
- 215.bMTurbine Pedestal
- 2 15.5 Cranes and Hoists
.- 2.15. 4 Flavaton 4.15.5 Heating, Ventilating and Air Condidoning
/ 2.15.6 Fire Protection System
~2.15.7
_FlpstLJc,tge DetectioLSvsteni
- 2.15.8 Vagnum Sween System.
-2.15.9
.De_qqntJuninEloJL6Ditm A115.10 Pector Building 2.15.11 Turbine Building M.15.12 Control Building
- 2.15.15 Padwute Building
- 9.15.1 d hice Buildine 04 Yvd Strucaires md Equipment
'p.16.??!i? Stack Sy: tem 2.16.2 M Storage and Transfer System
- 2 16.3
- W Gwdtv V
"nnssystem it.. A 'F~ 1 %tcht Eauipmant Ou,Ji6 cation (EO)
~~ 3.2 Instnunent Setpoint Methodology S
Piping Desirn i 4.4 Safety System logic and Control 165 Software Development V 3.6 Human Factors Engineering
'/3.7 Radiation Protection M
L1M ur,a e t__
7, : Sg_2
- 396 Weldina l
mm
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ABWR oesign Document 40 interface Tier I Material i/41 1:1riniate Ha,t Sink
/4
Oihite P%er $v% tem t
-43 Potable and Sanitary Water Sptem
-<4 Turhma S-mec Water Sptem
,/ 4 5 Reactor Senk* Water Sptem
_4 f.
Makeup Water Preparation Sptem
-.4" Cnmmunication System
- 4 F-Airborne Panintiate Radiat.on Monitoring 4n_
c.,_g. w.
5.0 </ Site Parameterr Aapendicce Antwndix 4 l evend For Fivurn
. wv._._J:- ri crummbde: Mem--
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lh c r, ARWR DESIGN CERTIFICATION 10/23/92 GE/NRC ABWR REHEW NUMARC_ITAACJ EYIEW1._QYERYIEW_.0F CHANGES n
STANDARDIZED ENTRIES FOR SIMILAR SYSTEM CONFIGilRATION HYDRO TEST CONTROL ROOM FEATURES REMOTE SHUTDOWN INTERFACE POWER SilPPLIES MECHANICAL. SEPARATION o
MODIFICATION OF ACCEPTANCE CRITERIA CONSIDERED T00 TMPRECISE 00 AMBIGUOUS DELETION OF SELECTED SYSTEMS NOT MERITING TIER 1 TRFATHENT (SERVICING, CHEMICAL SYSTEMS) c OCLETED DIRECT TIER 1 REFERENCES TO CODES AND STANDARDt (EXCEPT ASME) o CERTAIN GENERIC ISSVES PUT ON HOLD PENDING FURTHER NUMARC/NRC DISCUSSIONS EQUIPMENT'0VALIFICATION MOTOR-0PERATED VALVES INSTRUMENT SETPOINTS EMI/RFI/SWC SEISMIC QUALIFICATION WELDING ELECTRICAL SEPARATION BUILDING DIMENSIONS AJJ-4 10/23/92
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ARWR DESIGN CERTIFICATION 10/231.92JiE/NRC ABWR=REYlEW NUMRC_ITAAC_REHER_0XERUEW_OF CHANGES;
. TRENDS SAFET RELATED SYSTEMS:
SAME OR MORE ITAAC ENTRIES WORKING MORE PRECISE NON-S AFF.T.Y LESS ITAAC BUT HORE. FOCUSED RELATED SYSTEMS ON ISSUES OF SAFETY'
. SIGNIFICANCE
?
MINOR SYSTEMS DELETED-GENERIC ISSUES ON HOLD n
J AJJ-5 10/23/92
n F..
1 ARWR nESIGN CERTIFICATION 10/23492_GE/NRC ABWR REYlEW
.NUMARC_ITAAC_ REVIEW:
LES10Rij. EARNED TIER 1 PRFPARATTON REQUIRES CONSIDERATION OF TECHNICAL n
AND l.EGAl. TSSUES CAREFtlL WORDING TIMELY DEFINITION OF TIER 1 REQUIRES:
6 ONE-ON-ONE TECHNICAL INTERACTIONS r0NTINilotlS HANAGERIAL INVOLVEMENT SnME paRTTCIPANTS FAMILIAR WITH PART 57.
9 IMPORTANT TO HAVE A STYLE GUIDE AND TRAINING SESSIONS-MULTIPLE AUTHOR CONSISTENCY STANDARD SET OF DEFINITIONS DREPARERS AND REVIEWERS NEED TO IINDERSTAND THE "60 vFAR" SIGNIFICANCE OF TIER 1 ENTRIES FLEXIBILITY IMPORTANT AND LEGITIMATE IN SOME AREAS o
OEFINING PRECISE, UNAMBIGUOUS ITAAC FOR-GENERIC ISSUES IS A REAl. CHALLENGE o
INITIAL SAR PREPARATION SHOULD RECOGNIZE THE.
SIGNIFICANCE OF TIERE0 DESIGN CERTIFICATION RETROFIT SITUATION FOR ABWR AJJ-6 10/23/92
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ARWR DESIGN CERTIFICATION 10/23/92 GELNRC AEWILREVIEW NUEARC_UAAC_REHEW:
EXAMP1ES OF REVISEDJ AT.ERIAL STANDRY LIQUID CONTROL SYSTEM CONTROL 9UILDING CEEDWATER CONTROL SYSTEM-ELECTRICAL POWER DISTRIBUTION SYSTEM AJJ-7 10/23/92
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ABWR JESIGN CERTZFICATION i0/23dL2 3EdfBC fMR JE'llfi
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OCT l
NOV i
aEC MARK tJP STAGE 3 t
PER NUMARC i'J.
g RESPOND TO NRC
~- -
ITAAC COMMENTS GE/NRC44UMARC W
TTAAC MEETINGS AND RESOttJTICt1 TIER 1/ ITAAC
._ _. _ /
_.,_.._._...__..s ERIFICATION
' ND SUD14fTTAL ADORESS DFSER OPEN ITEMS h
l (INCL SEVERE ACCIDENT)
I SAR VERIFICATION u
SAR AMENDMiiNTS 2
COVER VER:FICATKXJ AND DFSER ITEMS
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ARWR DESIGN CERTIFICATION
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10/23/92JELNRC_ARWR; REVIEW i
PRIORITY LIST FOR EARI.Y-NOVIM ER_HRC DISCUSSIONS.
DPV AND INTERNALS SLCS i
PPS RWR OWCII CTRCULATING WATER narus FMERGENCY D-9 CONTROL BULDING
~
PTPING DAC:
SITE PARAMETERS GENERIC = ITEMS ON HOLO-4 SEPARATE GE/NRC INTERACTIONS ON~HFE AND SOFTWARE'DAC AJJ-9 10/23/92
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ARWR DESIGN CERTIFICATION 10/23/9UE/NRC ABWR REVIEW
]
imay GE/NRC MllST INITIATE INTENSIVE SYSTEM-BY-SYSTEM REVIEW 0F TIER ) FNTRIES I.INE-BY-LINE REVIEWS; TAKE AS LONG AS IS NEEDED IISF STAGE 3 MARKUPS
- NOVEMBER, DECEMBER 1992 unc OR SAN-JOSE
~
- NFE0 Full-TIME MANAGEMENT PARTICIPATION ARWR TIER 1 SCHEDULES INFLUENCFn RY NUMARC/NRC oFSOLUTIny nF GENERIC ISSUES TARGET IS TO SUBMIT AGREED-T0 VERIFIED ABWR TIER 1 BY o
7/28/92 AJJ-10 10/23/92
3;,...
7.-
ARWR DESIGN CERTIFICATION 101.23/92_fiEINRC_ AWILREYlEW TREATMENT OF GENERIC ISSUES INDui1RLYlEW SUKMARY:
TIFR 2 HECHANISMS (NOT TIER I ITAAC) SHOULD DE IISED FOR VERIFYING CERTAIN GENERIC ISSUES RACKGROUND:
F?,/7 CALLS FOR SUBMITTAL. OF AN SAR COMPARABLE Tr. e pART 50 FSAR 5?,47 CALLS FOR ITAAC TO CONFIRH AS-BUILT IS TN ACCORDANCE WITH DESIGN CERTIFICATION o
NOT EVERY ISSUE IN THE SAR NEED BE THE SUBJECT OF AN ITAAC TWO TIERED DESIGN CERTIFICATION IS ACCEPTED (2/15/91 SRM)
IMPLEMENTATIOi, 0F TIER 1 IS VERIFIED BY e
ITAAC o
IMPLEMENTATION OF TIER 2 IS VERIFIED BY THE QA PLAN CALLED FOR BY PARTS 52/50 l
e IDEA 0F A DISCIPLINED SIGN-AS-YOU-GO
(
PROGRAM TO CONFIRM IMPLEMENTATION OF LICENSEE COMMITMENTS IS GENERALLY ACCEPTED 1
AJJ 10/23/97.
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ARWR DESIGN CERTIFICATION 10/23492_GElBRC_ABWR_REVIIW IREATHENT OF GENERIC ISS11ES_(CONL1 CONCLUSION:
0A PLAN PLUS SIGN-AS-YOU-GO CAN BE USED TO VFPTFY GENERIC ISSUES AJJ 10/23/92
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12/8/92 PLANTSYSTEMS BRANCH COMMENTS 2.10.1 TURBINE MAIN STEAM SYSTEM COMMENT 10:
SPLB 2,10.11 List all loads served by the MS system (e.g. SJAE) and system layout (e.g.
flow restrictors and MSIVs)
GE RESPONSE:
Comment rejected.
Beyond the tcope of TIER 1/ ITAAC.
ROMMENT ID:
SPLB 2,10.12 Olscuss MSIV's ability to shut during maximum DP and flow conditions GE RESPONSE:
Comment rejected.
Not practical to test MSIVs for closure speed against maximum differential pressure and maximum flow.
Closure times are expected to be faster ender maximum dP and flow because upstream pressure tends to seat the valve (i.e. the disk is on the upstream side of the valve seat).
The stroke time of the valycs will be tested.
IIowever, stroke rate testing of MSIVs ahainst high pressure steam cannot cecur until start-up.
COMMENT ID:
SPLB 2.10.1-3 Identify seismic interface restraint GE RESPONSE:
Comment accepted.
The seismic interface restraint is shown on Figure 2.1.2b "Steamline" in the NBS ITAAC.
COMMENT ID:
S PLB-2,10,1 4 t
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,,,, o 12/8/92 PLANT SYSTEMS BRANCilCOMMENTS Identify solsmic class and quality group (including nitrogen accumulators for MSIVs and safetyhellet valves and system branch lines)
OE RESPONSE:
4 I
Comment partially accepted.
The Seismic Class and Quality Group of the of the MSLs within the reactor building is discussed in the " Design Description" section of the NBS ITAAC.
The Seismic Class and Quality Group of the pneumatic supply lines for the MSIVs and SRVs is not discussed in the NBS ITAAC.
COMMENT IDt SPLD 2,10.15 Discuss features to protect MS line from water entrainment GE RESPONSE:
Comment rejected. No changes will be made to the NBS ITAAC as a result of this comment.
The MSLs have drain lines to drain the MSLs during startup, before full power operation.
The steam separator / steam dryer inside the RPV prevent moisture carryover during normal power operation.
Also, the MSLs are insulated to limit the generation of condensate.
Closure of the turbine stop valves on RPV high water level 8 initiates a teactor scram.
This limits rnoisture carryover when the steam separators are flooded.
COMMENT ID:
SPLB 2.10.16 Stato that the shutoff valves will close in 2 seconds 6,E RESPONSEt 14
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'2 12/8/92 PLANT SYSTEMS BRANCH COMMENTS 2.10.2 CONDENSATE FEEDWATER AND CONDENSATE AIR EXTRACTION SYSTEMS This section dlscusses 2 systems; the Condensate and Feedwater System (CFS) and the Maln Condenser Evacuation System (MCES).
CONDENSATE AND FEEDWATER SYSTEM COMMENT 10:
SPLB 2,10.21 Provide drawing GE RESPONSE:
Not appropriate for Tier 1 material.
COMMENT ID:
SPLB 2.10.2 2 Identify all cooling loads (e.g. offgas, SJAE, gland steam)
GE RESPONSE:
Not appropriate for Tier i material.
COMMENT ID:
SPLB 2,10.2 3 Discuss isolation provisions and supporting instrumentation GE RESPONSE:
This topic applicable to Nuclear Boiler System, Section 2.1.2.
COMMENT ID:
SPLB 2,10.2 4 Discuss power supply for remote shutoff valve GE RESPONSE:
This topio applicable to Nuclear Boiler System, Section 2.1.2.
C_OMMENT ID:
SPLB 2,10,2 5 15
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12/8/92 PLANT SYSTEMS BRANCH COMhENTS Identify seismic interface restraint GE RESPONSE:
This topic applicable to Nuclear Boller System, Section 2.1.2.
MAIN CONDENSER EVACUATION SYSTEM C_OMMENT ID:
SPLB 2.10.2 6 State that the system is designed for hydrogen OE RESPONSE:
This will be included in Design Description.
COMMENT 10:
SPLB 2,10.2 7 It is not clear that the flow instrument shown on the diagram is what is used for isolation of offgas on low flow GE RESPONSE:
Flow element is shown at inlet to 2d stage ejector and discussed in Design Description.
COMMENT ID:
SPLB 2,10.2 8 Identlfy functions of the pressure Instrumentation GE RESPONSE:
Will clarify Design Description to show that pressure indicator indicates operability.
COMMENT IR:
SPLB 2,10.2-9 Indicate that the mechanical vacuum pump trips on high main steam line radiation GE RESPONSE:
This is discussed in Design Description and ITAAC.
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12/8/92 PLANTSYSTEMS BRANCH COMMENTS COMMENT ID:
SPLS.2.10.210 Include the fact that hydrogen in the dilution stream is kept below 4% by volume GE RESPONSE:
Too detailed for Tier 1. No action taken.
COMMENT ID:
SPL8 2.10.211 Show the hydrogen analyzers on the drawing GE RESPONSE:
This level of detall is not appropriate for Tier i material.
2.10.4 CONDENSATE PURIFICATION SYSTEM COMMENT ID:
SPLS 2.10.41 SPLB has no responslbillty for this system and should be removed Ls the primary review branch GE RESPONSE No GE action.
2.10.7 MAIN TURBINE COMMENT ID:
SPLB 2.10.7.1 Clarify which valves trip and which modulate GE RESPONSE:
Will add to Design Description "MSVs and CIVs trip and CVs modulate".
COMMENT -ID:. SPLB 2.10.7 2 Discuss hydrogen-protection features on the ' generator 17
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12/8!92 f
PLANTSYSTEMS BRANCH COMMENTS GE RESPONSE:
Not appropriate for Tier 1 material.
2.10.9 TURBINE GLAND STEAM SYSTEM COMMENT ID:
SPLB 2.10.91 Provide a drawing GE RESPONSE:
A simplified SSAR drawing (10.4.2) will be provided.
COMMENT ID:
SPLB 2.10.9 2 Include the blower exhaust rad monitor on the drawing GE RESPONSE:
This will be included on simpilfied SSAR drawing provided for comment SPLB.2.10.9 2.
COMMENT ID:
SPLB.2.10,9 3 Clarify steam sources (auxiliary steam, main steam, process steam from high pressure heater drain tank vent header)
GE RESPONSE:
This will be clarified on simplified SSAR drawing provided for comment SPLB 2.10.9 2.
COMMENT ID:
SPLB 2.10.9 4 ldentity the cooling source for the condenser GE RESPONSE:
This will be included on simplified SSAR drawing provided for comment SPLB 2.10.9 2.
COMMENT ID:
SPLB 2.10.9 5 18 4
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PLANTSYSTEMS BRANCH COMMEN13 b
Clarify how the steam source is changed on high radiation, is it done maqually.or automatically?-
GE RESPONSE:
Too detailed for Tier 1 material and site specific.
COMMENT - ID:
SPLB 2.10.9 6 1
Include the fact that the system provides sealing steam for the turbine stop and control valves and the combined intermediate valves
-j GE RESPONSEt This will be included on simplified SSAR drawing provided for comment 1
SPLB 2.10.9 2.
2.10.13 TURBINE BYPASS SYSTEM COMMENT IDt SPLB 2.10.131 Include statement that system can accommodate a fullload rejection without lifting main steam safety / relief valves GE RESPONSEt No.
SRVs will lift on full load rejection.
COMMENT ID:
SPLB 2.10.13 2 Identify that turbine bypass valves (TBVs) close on loss. of vacuum, LOSP, and loss of hydraulle pressure GE RESPONSEt This will be added to Design Description..
COMMENT ID:
-SPLB 2.10.13 3 State in description (and test) that valves open when steam ' pressure exceeds preset pressure
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PLANT SYS'IEMS BRANCH COMhENTS f
GE RESPONSE:
This will be added to Design Description, COMMENT ID:
SPLB 2,10.13 4 include drawing GERESPONSE:
Not necessary refer to 2.10.1 schematic.
COMMENT ID:
SPLB 2.10.13 5 Ensure that all the high energy lines associated with this system are located in the Turbine Bldg (Turbine Bldg ITAAC)
OE RESPONSE:
OK in Turbine Building ITAAC.
COMMENT ID:
SPLB 2.10.13 6 State that piping up to and including the TBVs are seismic Category 1 and Safety Class 2 and that remainder of piping up to the condenser can withstand an SSE GE RESPONSE:
No This piping is not safety related.
2.10.21 MAIN CONDENSER COMMENT ID!
SPLB 2,10.21 1 include drawing _
GE RESPONSE:
Too detailed - Not required in any SSAR (or Tier i material).
COMMENT ID:- - SPLB 2.10.21 2 -
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GE RESPONSE:
No This In in Design Description.
COMMENT 10:
SPL8 2.10.213 List all connections to condenser OE RESPONSE:
This is not appropriate for Tier 1 material.
COMMENT ID:
SPLB 2.10.214 Include fact that system receives and collects condensate flows, removes
This is included in Design. Description.
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COMMENT ' ID:
SPLB 2.10.215 include 4 minute con 6.,1 sate retention-capability OE RESPONSE:
This is in Design Description.
1 COMMENT ID:
SPLB 2.10.216 include fact that maximum flood level is less than grade if condensate-
-system should fall.
GE RESPONSE The CWS System, 2.10.23, is flood limiting clarify.
2.10.23
. CIRDUI.ATING WATER 21
7 12/8/92 Pl. ANT SYSTEMS BRANCH COMMENTS COMMENT ID:
SPLB 2,10.231 Indicate that system dumps heat to the power cycle heat sink.
OE RESPONSE:
C_OMMENT ID:
SPLB 2.10.23 2 Where will the level switches be shown (the Turbine Bldg ITAAC)?
GE RESPONSE:
COMMENT ID:
SPLB 2.10.23 3 Indicate and show that the logic scheme minimizes potential for spurious
'hlgh level system" isolation trips GE RESPONSE:--
Not Tier 1.
This level of detall not appropriate for Tier 1 material.
COMMENT 10:
SPLB 2.10.23 4 State that there will be features _provided to prevent organic fouling GE RESPONSE:
Not Tier 1.
This-level of detall not appropriate for Tier I meterial.
COMMENT ID:
SPLB 2.10.23 5 Identify that the system will function on low level in the power cycle ' heat sink GE RESPONSE:
Not Tier 1.
This level of detail not appropriate for Tier 1 material.
22
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...e 12/8/92 PLANT SYSTEMS BRANCH COMMENTS COMMENT ID:
SPLB 2.10.23 8 Include the fact that features are provided to maintain a minimum circulating water temperature GE RESPONSE:
Not Tier 1.
This level of detall not appropriate for Tier 1 material..
COMMENT ID:
SPLB 2.10.23 7 Ensure that all Turbine.Bullding flooding will be confined to the _ condenser pit (Turbine Building ITAAC) t GE RESPONSE:
See Turbine Building Section 2.15.11.
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Division of Engineering Technology Comments Comment ID Comment /GE Response COMMENT IDt DET 2.10.1 1 2.10.1 Turbint hiain Steam Svstem 4
The ABWR plant design has eliminated the main steam isolation valve leakage control system. Instead, OB proposes to rely on the use of an alternate leakage path which takes advantage of the large volume and surface area in the main steam piping, by pass line, and condenser to hold up and plate out the release of fission products following core damage. Therefore, these components are used to mitigate the consequences of an accident and are required to remain functional during and after a safe shutdown earthquake. The commitments that GE has made relative to this issue are in Section 3.2 of the SSAR and are summarized in Section 3.2.1 of the staff's Final Safety Evaluation Report for the ABWR, The discussion in Section 2.10.1 and the ITAAC in Table 2.10.1 should be revised to reflect this information and to confirm that it has been implemented in accordance with the SSAR commitments.
GE RESPONSEt See response to Radiation Protection Branch ' comment RPB 2.10.11.
COMMENT IDt DET.2.10.4 1 2.10.4 Condensate Purification ly.itam The proposed Certified Design Commitment and ITAAC do not address the primary function of the system and how to_ verify its operability. OE should revise the ITAAC accordingly See comments on attached marked up page.
GE RESPONSEt GE.will delete reference to. water treatment additions since there may be several,_-
depending on final detailed material selection, e.g. 02. H2i Fe, etc.
32
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RADIATION PROTECTION BRANCH COMMENTS RADIATION PROTECTION BRANCH COMMENTS
- 1. SectIon 210.1 Turbine Mala Steam Svetem CQMMENT IDI RPB 2,10.1 1 The staff has reviewed Section 2.10.1, Turbine Main Steam System !n the Tier 1 Design Certification Material (TDCM) and finds that the design description and its related ITAAC (Table 2.10.1) should include (1) the operability requirement of main steam draln valve from main control room via essential power supply (Class IE), (2) the structural integrity reQulrement for main steam lines, drain lines, and main condenser for their leak tightness following a postulated LOCA.
GE RESPONSE:
COMMENT ID: R P B 2.10.1 2 The main steam lines from MSIV to the main condenser, including the drain lines, should be analyzed, and (3) using a seismic analysis to demonstrate appropriate structural integrity for leak tightness under SSE loading conditions. The staff has provided a credit for iodine removal in the main steam lines, drain lines, and condenser following a postulated LOCA and accepted the ABWR design without a MSIV icskage control system. This is Open itsm 2.3.6-1.
GE RESPONSE:
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12/8/92 RADIATION PROTECTION BRANCl! COMMENTS
?.0 jisl!an 2.10.1. Turbina Maln SieAm Svstem COMMENT ID: RPB 2.10.13 3.1 Add the following two certified design commitments in Table 2.10.1 as ITAAC ltems.
(I) the main steam drain valves are operable from the main control room via essential power supply (class (E).
(2) the main steam piping from MSIV to the condenser inlet includir.:; the maln steam drain pipe is analyzed to demonstrate appropriate leaktightness under SSE loading conditions.
3.2 The basis for adding the above ITAAC items are that (1) the staff has provided a credit for alrborne radioactive lodine removal in the main steam (and drain) piping and in the main condenser following a postulated LOCA, and (2) the staff accepted the ABWR design without a MSIV leakage control system.
3.3 A marked up copy of Section 2.10.1 is enclosed.
incorporates comment 3.1 GERESPONSE:
Agree to add.
18
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12/8/92 ACRS COMMENTS COMMENT ID: ACRS 2.10.2-1 Section 2.10.2. page 1 thru 5 (6/1/92)
Condensate and Feedwater System, Design Descripdon, Page 2.10.2-1, Paragraph,l.ast Sentence, states:
This portion of the piping is analyzed for dynamic effects from postulated events and safety / relief valve discharges.
Table 2.10.2a, inspections, Tests, Analyses and Acceptance Criteria, Page 2.10.2 4, doesn't explicitly provide verification that this analysis has been performed. (Perhaps Certified Design Commitment number 1 was intended to imply this verification; however, that commitment could be met without coverage of the analysis mendoned here.)
GB RBSPONSE:
This sentence deleted. The referenced piping applies to NBS.
COMMENT ID; ACRS 2.10.2-2 Section 2.10.2, page 1 thru 5 (6/1/92)
' Main Condenser Evacuation System, Design Description, Page 2.10.2-2, Third Paragraph, states:
The MCE System is designed to Qpality Group D.
Table 3.0, Page -5, the entry for 2.10.2 shows 3.3 Piping Design as not applicable. Quality Group D requires piping designed to B31.1.
GB RESPONSE:
Section 3.3 Piping Design is not applicable to non safety-related Qpality Group D. No change.
45
" v;s. e n c..w n n.v an non s.sss 4.. v t. g ACRS COMMENTS COMMENT ID! ACRS 2.10.41 Section 2.10.4, page 1 and 2 (6/1/92)
Design Description. Page 2.10.4 -1. Third Paragraph, states:
The CP System is designed to Qpality Group D.
Table 3.0, Page -5, the entry for 2.10.4 shows 3.3 Piping Design as not applicable. Qpality Group D requires piping designed to B31.1.
GB RESPONSB:
Section 3.3 Piping Design is not applicable to non safety-related Qpality Group D. No change.
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f 12/8/92 ACRS COMMENTS COMMENT ID: ACRS 2.10.7-1 Section 2.10.7, page 1 and 2 (6/1/92)
Fage 2.10.7-2, Table 2.10.7, ITAAC doesn't include any coverage of verification that LP rotors have been center bored. See David A. Ward's letter to James M. Taylor of April 13,1992, Item 6 on page 4.
GB RESPONSB:
Too detailed for Tier 1. Center boring 1.P rotors is dependent on available technology and should be at the discretion of vendor and customer. No action taken.
COMMENT TD ACRS 2.10.7 2 Section 2.10.7, page -1 and -2 (6/1/92)
Section 2.10.7 barely mentioned the Turbine Controls. Yet Section 10.2.8, Turbine Controls, says that the topic is covered in Section 2.10.7. Figure 2.2.7a Reactor Protection System, on Page 2.2.7 8, provides a block ("C71 RPS") of four (4) input signal from turbine I&C. The RPS ITAAC don't include verification of the l&C for these turbine inputs. Coverage is required somewhere.
GB RESPONSB:
The RPS ITAAC includes input signals from Turbine Controls. ITAAC 2.2.7, item 3, simulation testing will verify that I&C provides signal to RPS.
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12/8/92 ACRS COMMENTS COMMENT IDI ACRS 2.10.91 Section 2.10.9, page 1 and 2 (6/1/92)
Design Description, Page 2.10.91, Fourth Paragraph, states:
The TGS System is designed to Qpality Group D.
Table 3.0, Page -5, the entry for 2.10.9 shows 3.3 Piping Design as not applicable. Opality Group D requires piping designed to B31.1.
Further, Design Description, Page 2.10.91, tast Paragraph, states:
Relief valves on the seal steam header prevent excessive seal steam pressure.
This also involves " piping design."
GE RESPONSE:
Section 3.3 Piping Design is not applicable to non safety related Opality Group D. No change.
48
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=t ACRS COMMENTS COMMENT ID; ACRS 2.10.131 Section 2.10.13, page 1 and -2 (6/1/92)
The failure or malfunction of the Turbine Bypass System has the potential to cause severe transients effects on the Reactor Coolant System. The coverage in Section 2.10.13 doesn't appear consistent with that importance.
Design Description, Page 2.10.13 1, Fourth Paragraph, Last Sentence, and last Paragraph, state respectively:
The TB System is designed to bypass nominally 33% of the rated main steam flow to the condenscr.
The TB System in conjunction with the reactor systems, provides the capability to shed 40% of the turbine-generator rated load without reactor trip.
These important capabilities are no doubt assumed in various transient analyses and should be confirmed by the ITAAC.
GB RESPONSE:
Too detailed for Tier 1. In addition the TBS is not safety related.
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e ABWR outon Danmut Mr. C. Posluany 11-H 3 U.S. Nuclear Regulatory Commission 2.10 Power Cycle Oflice of Nuclear Reactor Reguladon Washington, DC 20555 2,10.1 Turbine Main Steam System Design Description The Main Steam (MS) System (Figure 2.10.1) supplies steam gen: rated in the reactor to the turbine. This Tier 1 enuy addrenes that portion of the MS System that ranges between, bundoca-not4nc4ader4h: :ute:moet<ontainer+n44scht!:n-mlvee-and4h+4wW: :tep v.dve., but does not include. the schmic restraint.
dawnstream or the outermost containment holation valves and the turbine stop vah es.,
The MS System b not r'equired to effect or suppon safe shutdown of the reactor or to perfonn in the operation of rector safety features; however, the MS S)1 tem b designed:
(1) To sempl#dapplicab' "-
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- accommodate operational streues such as internal preuure and dynamic loads without riskw4 fallures, mad 4eaa+quendd r6r:
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(2) Tc acc::::ned::: n =d and4bnorm4 ee4+maea4441adia, Provide alca). age path to the main condensers under Sebmic condidont (S) Te =ur: Set fMur+6dmon S6.h St:ge:yI:quipnma*.
ewemru er-pipe 4mck: er b::& L-M;h :: :nademie p!p!n; 'n h -
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w-yv (3) With suitable acceu to permit in+ervice testing and inspections.
The MS Sptem main steam piping consists of four lines from the nehmic restraint outboard-main ete=En: k* den -&-: to the main turbine stop valves. The header arrangement upstream of the turbine stop valves allows them to be tested on4ine with minimum load reduction and aho supplies steam to the power cycle mudilaries, as required.
The MS Spiem is cuality group D not safety related.
Inspections, Tests, Analyses and Acceptance critoria Table 2.10.1 provides a definition of the inspections, tests, and/or analyses, together with associated acceptance criteda which dll be undertaken for the MS System.
2.10 1
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' ABWRontenDocumnt 2.10.2 Condensate Feedwater and Condensate Air Extraction System The Condensate Feedwater and Condemate Air Extraction Sptem /COWQ comhts of two subsptems, the Condensate and Feedwater.(CE).Sptem and the Main Condemer Evacuation Sptem (MCES).
Condensate and feedwater System Design 00scription The function of the C4md+nsate =d Feedwate (GF) (Figure 2.10.2a)Sptem is to receive condensate from the condenser hotweth, supply condemate to the cleanup sptem, and deliver h!gh pudiy feedwater to the reactors: e: reqdd Gow rute, p=weand4emperatw+, Condemate is pumped from the main condemer hotwell by the condemate pumps, passes through the feedwater heaten to the feedwater pumps, and then b pumped through the high pressure heaten to the nuclear Steam Supply Sptem.
The CF System boundaries eensid::ed bre extend from the main condenser outlet to (but not including) the zecend !:chtion & setunic restraint outside the containment and downstream of the outermost ho12 tion valve.The CF System combts of the piping, vahen, heat exchangers, controh and instnunentation, and the associated equipment and subsystems which supply the reactor with heated feedwater in a cloxd steam cycle utilizing regenerative feedwater heating.
The CF System does not serve or support any safety function and has no safety design basis. System analyses show that failure of this sptem cannot comprombe any safety related sptems or prevent safe shutdown.
The CF System b destened to-qmilty Group D non safety related.
1 Fordewef die ept:.. S:t ce.mdk=S: dudng Opemtiotuwe.eMeldd ie ac++u.eentrel fer !=p:sdom, Le&;: E -! nim!=d Mi welded ~~~4"
" %rever p=:4iceWe, Relief discharges and operating vents are channeled through closed systems.
Operational sptem redundancy b prcnided with respect to feedwater heaters, pumps, or control valves by using multi-string arrangements and provblons for holating and bypassing equipment and sections of the aptem.
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The majority of the condensate and feedwater piping semidered !n ib ::
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outside ec centainmer' ' "ted !n se mam4unnenetween4h+4whin: =4 2.10.2 1
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hadre+ypem-pipinghmalysedhnerhammw-Joaduhat eculd potent"!!y :::e from-and:!pe:d !kn" u=:!:re.
inspections, Tests, Analyses and Acceptance Criterin Table 2.10.2a provides a definition of the inspectioru, tesu, and/or analyses, together with associated acceptance criteria which will be undertaken for the CF System.
Main Condenser Eyacuntlon System Design Description Nensonden6able ge n re-remc=d &cm Se-pereer :y:!: by4Ihe Main Condenser Evacuation (MCE) System (Figure 2.10.2b). n: MCE Sy:te:m removes the hydrogen and oxygen produced by the mdiolysis of water in the reactor, and other power cycle noncondensable gases, and exhausts them to the offgas system during plant power operation, and to the turbine building compartment exhaust system at the beginning of each startup.
The MCE System does not serve or support any safety function and has no safety design basis.
The MCE System is designed to Quality Group D,Non-Safety Rehted The MCE System consists c' ;: !005 :: pac!ty, dcub!: :tage, of redundant steamJet air ejectors (SJAE) units (complete He Eterconde6w) for power plant operation, and a mechanical vacuum pump for use during startup. The !=:
Stag + cf 6: Sy?.mit E nn =1!y in operat!cn =d S: cier b :n n=dby.
Steam supply to the seccnd :mge :j:: tor SJAE is maintained at a minimum specified flow nte to ensure adequate dilution of the hydrogen and prevent the offgas from reaching the Dammable limit of hydrogen.
Sur pr:=u:e =d new4s4entinuemly :
n! cred ed = ne c1!:d4n 6: :j:ne:
t,sen:n :upply !he. Ed=dantp enut: : cut:c!!:r: ::=: ce=n preenme-auhe-seamd-stag 4nkt =d nmiutate ee :::=n eupply4cne;! =lveaup6tr+amef4he.
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- we cut of4hree bg':, :Should the steam now drop below acceptable limits for offga6-stream dilutionrthe Off cas System will be isolated.
The vacuurn pump exhaust stream is discharged to the turbine building compartment exhaust system which provides for radiation monitoring of the 2.10.2 2-12/4/92
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The vacumn pump is tripped and its discharge vahe is closed upon receiving a main steam high hlgh radladon algnal, inspections, Teste, Analyses and Acceptance Criterls Table 2.10.2b provides a definition of the inspeedons, tests, and/or anal)ws, together with usociated acceptance criteria which wdl be undenaken for the MCE System.
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ABWR Dulan oocument 2.10.4 Condensate Purification System Deelen Deeoription The Condensate Pudfication (CP) System purifles and treau the condensate e.
wguind to maintain reactor feedwater purity, tuing filtration to remow insoluble solids n ::S: p::d=*,lon exchange to remove moluble solids from condenser leakage and other impurities, and water treatment additions to
- nb!mbe reduct corrosion / erosion releases in the power cycle.
The CP System does not serve or support any safety function and has no safety design bash.
The CP System is designed to Quality Group D nondetv-related standards.
The CP System consists of full flow high efficiency paniculate fihers followed by fullflow deep bed deminers1hers.
Eh!:! ding b predd:d f:r 6: O *p::-
Vent gases and other wastes from the CP System are collected in radiation controlled areas and sent to the radwaste system for treatment and/or disposal.
The CP System is located in the 4Iurbine bBuildingu rd p!ph; er :qdp
=t fer:: R ::: "r p'--::6 j.
InspectIone, Tests, Analyses and Acceptance Criteria Table 2.10.4 provides a definidon of the inspections, tests, and/or analyws, together with usociated acceptance enteria which will be undertaken for the CP System.
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m.. ( a ABWR Dnign Documnt 2.10.7 Main Tuitine Design Description The main Turbine Generator (TC) System converts the energy in steam from the nuclear steam supply system into electrical energy.
The TG System does not sent nor support any safety function and has no safety design bash. However, the TG System is a potential source of high energy missiles that could damage safety related equipment or structures.
'Ihe TG Sptem is designed to prevent ovenpeed and thus W* reducing the possibility of high energy missue generation from TG System modng parts.
The foUowing empe et instmmentation. controb and vaMng redundancies are employed to guard against ovenpeed:
(1) Main stop valves (MSV)/ Control valves LCY), IMS% trip /CVs modulatel.
(2) Intermediate stop vahts/ Intercept vahrs (CIVs) ICI% tripl.
(3) Primary speed control / Backup speed control.
(4) Fut acting solenoid vahts/ Emergency tdp Duid system (ETS).
(5) Speed control /Chenpeed tdp/ Backup ovenpeed trip.
Temocrature. pressure and soced indications. as well as oversneed alarm are erovided in the mMn control room.
The TG Sptem is enclosed within the Gurbine bBuilding, which contains no safety related equipment or structures. The turbine generator is orientated within the turbine building to be inline with the #Eeactor and eControl bHulldings to misdadne reduce the potential for any high energy TG System generated missiles from damaging any safety related equipment or structures.
Inspections, Teets, Analyses and Acceptance Criterls Table 2.10.7 proddes a dermition of the inspections, tests, and/or analpes, together with asociated acceptance criteria which will be undertaken for the TG System.
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ABWR oosion Document 2,10,9 Turbine Gland Steam System Design Description The Turbine Gland Sealing (TGS) System Wirure 2.10.91 prevents the escape of radioacthe steam from the turbine shaft / casing penetrations and vahc stems and prevents air inleakage through subatmosphe& turbine glands.
Le TGS System consists of a sealing steam pressure regulator, sealing steam header, a gland steam condenser, with two full capacity exhaust blowers, and the associated piping, s alves and instrumentadon.
The TGS System does not serve or support any safety funcdon and has no safety design basis.
The TGS System b designed to Quality Group D standards non safetv-rel2ted.
S.: cuter-pertion erall gkwd::fi: =hin =d =in ::e= de: b :=.::::d t 6: gl=d :::= cendemer, rh!d b -dnSed 2:::1!ghe.ccuum by S:
""-*er b!c..tr. Dudng p!=: epe=tica,6: gland :::= :=d== =d one-of-th: :vic !=talled 1^0% =pcej.0:= d.9cen b!cycer: = != :p=d=, U.-
exh =::: b!c.= :0 ee tudh: b"'!d!ng ecmp=tment :6=: r,::= :Su:nt-sueam b cont!nuoudy==!:=:d pd= : being dbch=g:d.
Dur!ng nemd ep =d=, the :::= :ea! head = b =pp":d f cm :hunainweam.
pai S: =d"nq :::=,::= pre 'de:: !^^% :::= =pply b :kup "ch=
high =dbd= !=b =: d::=::d in se b!c = =h=: cr 6: =in : e= p^6-seues:(:) =: =r.
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and :: ia:!=!:Ihe TGSS steam supply she*M wm be switched to the aux %g
$ource,if the dhcharge steam radiation level exceeds utnoint.
Relief valves on the seal steam header prevent excessive seal steam pressure.
l Inspections, Tests, Analyses and Acceptance Criterls Table 2.10.9 provides a definidon of the inspecdons, tests, and/or analyses, L
together with associated acceptance criteria which will be undertaken for the TGS System.
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2.10.13 Turbine Bypass System Design Description The Turbine Bypass (TB) System provides capability to discharge main steam from the reactor directly to the condenser to minimize step load reduedon transients effecu on the reactor coolant system. The system is also used to discharge main steam during reactor hot standby and cooldown operadons.
The TB System does not serve or support any safety function and has no safety design basis. The TB Sgtggla desirned to Oumiltv Groun D non4afety tch.ttsL Th:-- E : -
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J., J a_t ~.. _ _ _..~... _7 Inspections, Tests, Analyses end Acceptance Criteria Table 2.10.15 provides a dermition of the inspections, tests, and/or analyses, together with associated acceptance criteria which will be undertaken for the TB System.
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s ABWR onle Doomut 2,10.21 Main Condenser Design Descr> tion The main condenser h designed to condense and deaerate the exhaust steam from the main turbine and provide a heat alnk for the Turbine Bypus (TB)
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The main condenser does not serve or support any safety function and has no safe t)' de sign basis. '., '..,,......, '.- ',.,. J A..'. -..
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The condenser h deniened to Oum11tv Groue D non aafety related. The main condenser h desirned'io be sup'norted und'er schmic condidonn.
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e Since the main condenser operates at a vacuum, anyleakage is into the shell side of the main condenser. Tubeside or circulating water inleakage h detected by measudng the conductivity of sample water extracted beneath the tube bundles.
In addidon, conductivityis m"-"-d; monitored at the discharge of the condensate pumps and alarms provided in the main control room.
A slenal h provided to the reactor protecdon system on lots of vacuum.
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The main condenser potendal for flooding is less than the Circulating Water (CW) System and, consequently flooding protecdon is the same as the CW System (2.10.23). Condenser pressure indicaton are located above dedan hah any-peemeialflood lew1.
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Table 2.10.21 provides a defbidon of the inspeedons, tesu, and/or analyses, together with associated acceptance criteria which will be undertaken for the main condenser.
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ABWk ossion Docuinent 2.10.23 Circulating Water System Design Description The Circulating Water (CW) System meure 2.10.231 provides a centhmus supply of cooling water to the main condenser to remove the heat rejected by the turbine cycle and auxiliary systems.
The CW System does not serve or support any safety funcdon and has no safety design basis.
To prevent flooding of the turbine building, the CW System is designed to automadcally isolate in the event of guesa system leakage. The circidating water pumps are tripped and the pump and condenser vahts are closed in the event of a system isolation signal from the condenser area high.high level switches. A condenser area high level alarm is provided in the main contro1 room.
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The CW System is designed m =d :==ced i. =:: dan = with Quality Group D ep+ehdene non safety related.
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Inspections, Tests, Analyses and Acceptance Critella Table 2.10.23 provides a definition of the inspection, tests, and/or analyses, together with associated scceptance criteria which will be undertaken for the CW System.
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