ML20077M095
| ML20077M095 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 01/31/1995 |
| From: | Drews M, Larson C, Mccandless R GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20077M083 | List: |
| References | |
| RE-020-NP, RE-20-NP, NUDOCS 9501120149 | |
| Download: ML20077M095 (22) | |
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RE-020-NP . .
DRF A00-02-02119-D/ !
DRF C71-00101 hulmuy 1995 j l
TECHNICAL SPECITICATION IMPROVDENT )
ANALYSIS FOR THE DERGENCY CORE COOLING '
SYSTEM ACTUATION INSTRUMENTATION FOR PEACH BOTIOM ATOMIC POWER STATION, UNITS 2 & 3 l
(THIS REPORT HAS BEEN PREFARED FOR PHITADELPHIA ELECTRIC COMPANY THROUGH THE TECHNICAL SPECITICATION I IMPROVDENT COMMITTEE :
OF THE BWR OWNERS' GROUP)
PREPARED BY: W. b A44%
M. A. Drews. Program f.ngineer l Reliability Engineering j i
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- VERIPIED BY: I C. L. Larson Principal Engineer l Reliability Engineering APPROVED BY:
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l R.J. McCandless, Manager Reliability Engineering P
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The information contained in this document is furnished for the purpose of ?
providing the members of the BWR Owners' Group with plant specific analysis related to changes to the Emergency Core Cooling System actuation instrumentation Technical Specification testing intervals i and allowable out-of-service times. No other use, direct or indirect, of the_ document or the information it contains is authorized. The ,
information shall not be reproduced or furnished to third parties or l made public without the prior express written consent of the General i Electric Company. ;
IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT l Please Read Carefully The only undertakings of General Electric Compay respecting- '
information in this document are contained in the contract between the purchasing customer and the General Electric Company as referenced in !
General Electric Proposals Number 355-1525 Revisions 1 and 2, and nothing contained in this document shall be construed as changing the contract. The use of this information by anyone who har, not contracted i for its use for any purpose other than that for which it is intended, is !
not authorized; and with respect to any unauthorized use General l Electric Company makes no representation or warranty, and assumes no !
liability as to the completeness, accuracy, or usefulness of the j information contained in this document. ;
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I TABLE OF CONTDi7S f i
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- 1. INTRODUCTION 1 t
- 2. EVALUATION METHOD 2 i
- 3. RESULTS OF ECCS EVALUATION 4 -
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SUMMARY
AND CONCLUSIONS 7. ;
i S. REFERENCES 8 APPENDIX A: EC'S ACTUATION INSTRUMENTATION A-1 l
r . TION FOR THE PEACE BCnTOM l arm 1IC PCfdER STATION, UNITS 2 & 3 ,
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- 1. LNTRODUCTICH This report extends the generic study of modifying the technical specification requirements of the emergency core cooling system (ECCS) on a plant specific basis for Peach Bottom Atomic Power Station (PBAPS). Units 2 and 3 at PBAPS are BWR 4s. The generic study (References 1 and 2) provides a technical basis to modify the surveillance test intervals and ,
allowable out-of-service times of the ECCS actuation instnunentation from those of tFe generic technical specifications. The generic study also.
provides additional analyses of various known different ECCS configurations to support the application of the generic basis on a plant specific basis.
The generic basis and the supporting analyses were utilized in this plant specific evaluation. The results of the plant specific evaluation for ,
Peach Bottom are presented herein.
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- 2. EVALUATICN METHOD 1
The plant specific evaluation of the modification of the surveillance test I frequencies and allowable out-of-service times of the ECCS actuation j
instrumentation was performed in the following steps:
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- a. Gather plant specific information on the ECCS from Philadelphia
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Electric Company (PECO). The information includes the following: !
(1) Piping and Instrumentation Diagrams (P& ids) of ECCS, i reactor core isolation cooling (RCIC) system, emergency service water systems, and air systems to ADS valves.
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(2) Elementary Diagrams of the ECCS, RCIC, and related systems.
(3) ECCS, RCIC and electric power distribution system ,
descriptions such as those in the plant Final Safety i Analysis Report (FSAR). l (4) Technical specifications on the ECCS, RCIC, the suppression .i pool, and the electrical systems.
(5) Information on ECCS surveillance test procedures. '
(6) Dependency matrices showing dependence of ECCS and RCIC systems on support systems and on actuatico instrumentation.
(7) Available data on actuation instrumentation failures.
The latest revisions of the above items were supplied by PECO. l Section I of the checklist in Appendix A was used to identify the data source of the plant specific information.
- b. Construct the plant specific ECCS configuration from the l
Plant specific information. Sections "A" through "E" in Section .
II of the Appendix A checklist was used for this process.
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- c. Compare the plant specific ECCS configuration with the generic ECCS configuration using the generic ECCS fault trees ECCS description, technical specification requirements, and other generic inputs.Section III of the checklist was used for this process.
- d. Classify the differences in ECCS system design, in support systems, and in instrumentation, into three categories:
(1) Differences which obviously have no negative effect on the reliability of the ECCS. Examples of these "no effect" items are component name differences, symbol differences.
l and other minor non-functional differences. Other effects t not requiring analysis are those in which the specific plant - I has greater redundancy than the generic model. Disposition of the items with obviously no negative effect is done with "no analysis required".
(2) Differences which require engineering judgment for disposition because of the functional differences. Examples {
of these differences are the use of shared room cooling systems in a specific plant compared with individual room cooling systems in the generic plant. The disposition of such items would require engineering assessment in a " simple study" as shown in Appendix F of Reference 2.
(3) Differences which require additional analyses to evaluate the effect on the ECCS reliability. Examples of such i differences are use of two diesel generators and two l electrical systems in a specific plant compared with a larger number of diesel generators and electrical systems in i the generic evaluation. Disposition of these items would require additional analyses (" Modify fault treu and perf orm analysis.") to compare with the generic results. These analyses are documentted in Reference 2.
- e. Compile a list of plant specific differences of Categories (2) and (3).
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- f. Assess the reliability effect of the differences identified in l Step (e)'on the generic results. The results of the assessment are documented in Section III of the checklist. Appendix A. !
- g. Document the results of the plant specific evaluation.
The above seven step process is documented in Appendix A of this report.
- 3. RESULTS OP ECCS EVALUATION The results of the plant specific evaluation of the ECCS for PBAPS are- -
documented in Appendix A of this report. The results show that the ECCS l and support' systems configuration of PRAPS has five differences from the- ~
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BWR 3/4 generic model* which are classified Category (3), and one in ;
Category (2). '
l 3.1 Detailed Analvses I The PBAPS differences in Category (3), requiring detailed analysis, are as follows: l
- a. The generic model has four emergency service water loops, with loops 3 and 4 primarily providing cooling water to diesel !
generators 3 and 4. The PBAPS emergency service water system !
has two loops. I
divisions of onsite AC power. Also, the 4 diesel generators are shared between Units 2 and 3.
- c. The generic model has 4 divisions of DC power, PRAPS has 2 ,
divisions of DC power.
The term " generic model" means the ECCS configuration used in the generic analysis.
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- d. The generic model has 1 turbine-driven EPCI pump PBAPS has 2 turbine driven HPCI pumps, both on the same shaft. ,
- e. The generic model has eight instrument channels for Level 1 Level 2 and drywell pressure, PBAPS has four instrument channels j and it also has different actuation logic for core spray and LPCI.
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General Electric Company RE-020-NP "The total number of standby diesel generator units is such that sufficient poser is available to provide for the functioning of required engineered safeguard systems for one reactor unit and the=
shutting down of the other unit, assuming failure of one standby diesel generator and loss of all off-site power sources."
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i 3.2 Simple study
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The PBAPS difference in Category (2), requiring a simple study, is: ,
i The generic model requires 2 out of 5 ADS valves to open for success, ,
whereas PRAPS requires 2 out of 4.
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RE-020-NP 4
SUMMARY
AND CONCLUSIONS I
A plant specific evaluation of modifying the surveillance test intervals and allowable out-of-service times of the ECCS from the technical specifications of PBAPS has been performed.~The evaluation utilized the plant specific information supplied by PECO and the generic basis and the additional analyses documented in References 1 and 2. The results indicate that the ECCS configuration for PBAPS is similar to the ECCS configuration in the generic evaluation, with five significant differences.
The differences between PBAPS and the generic model have been modeled by envelope case 4A of Reference 2, which shows that the proposed changes to l ECCS actuation instrumentation Technical Specifications would meet the .
acceptance criteria in Reference 2. Also, the sharing of diesel generators between Units 2 and 3 for onsite AC power has been qualitatively considered for its impact on proposed Technical Specification changes, and judged to have no limiting impact. Therefore. the generic basis in References 1 and 2 is applicable to PBAPS. '
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- 5. RETEENCES (1) D. B. Atcheson, et al., "BWR Owners' Group Technical Specification Improvement Methodology (with Demonstration for ,
BWR ECCS Actuation Instrumentation) Part 1", General Electric Company, NEDC-30936P, November 1985.
(2) D. B. Atcheson, et al., "BWR Owners' Group Technical Specification Improvement Methodology (with Demonstration for BWR ECCS Actuation Instrumentation) Part 2", General Electric Company, NEDC-30936P, to be issued February 1987. ,
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RE-020-NP l
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i APPENDIX A ;
i ECCS ACTUATION INSTRUMINTATION EVALUATION !
FOR THE PEACH BOTTOM ATOMIC POWER STATION, ;
UNITS 2 & 3 l h
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i Section I - ECCS Plant Specific Data Source Utility: Philadelphia Electric Company Plant: Peach Bottom Atomic Power Station, Units 2 & 3 '
Source Number
- 2. Emergency Service Water PEIDs
- 3. Eler3rical Drawings -
- 4. Instrumentation Logic Diagrams ;
- 5. ECCS Fault Trees
- 6. Final Safety Analysis Report
- 7. Technical Specifications 1
- 8. Other Drawings
- 9. Dependency Matrices
- 10. Failure Data
- 11. Test Procedure Questionnaire
- 12. Telephone Call Records l
- 13. NEDC-30936P, Part 1 l e
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D Section II - ECCS Configuration Data A. ECCS Svstem GENERIC Difference Data * !
PRAPS liWR 3 /4 (Y/N) Source.
- 1. Number of:
Core Spray Pumps / Loops 4/2 4/2 N 1 ;
LPCI Pumps 4 4 N 1 l ADS Valves 4 5 Y 1 HPCI Pumps 2 1 Y 1
- 2. Needed for Success, Number of: '
Core Spray Pumps / Loops 2/1 2/1 N 6 LPCI Pumps 1 1 N 13 ADS Valves 2 2 N 13
- 3. Number of Diesel Generators 4 4 N 3,6- ,
Electrical Divisions 4 4 N 3,6 l 4 IC or RCIC PCIC RCIC N 1 I
- 5. Loop Selection Logic N N N 6 The numbers shown in the Data Source coluart refer to the documents listed in Section 1.
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General Electric Company RE-020-NP Section II - ECCS Configuration Data I B. SUPPORT SYSTEM DEPENDENCIES The dependencies each front line ECCS system has on the listed support subsystems for the generic and specific plants are shown. ,
FB00ft LINE SYSTEMS ?
SUPPOEI LPCI LOOPS CORE SPRAY ADS ADS RCIC HPCI DIESELS SUBSYSTEMS A B C D A/C B/D A C A B C D OFFSITI AC POWER X X X X X X X X ONSITE AC POWER >
DIVISION 1 X X X X X X DIVISION 2 X X X X X X DIVISION 3 X X X X DIVISION 4 X X X X -
ONSITI DC POWER DIVISION 1* X X X X X X S
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DIVISION 2* X X X X X S
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DIVISION 3 G G G G G G G DIVISION 4 G G G G G ;
SERVICE WATER EMERGENCY A X S X S X S X S X S S S EMERGENCY B S X S X S X X S X S S ;
EMERGENCY C G G EMERGINCY D G-WATER SUPPLY SUPPRESSION POOL X X X X X X X X CONDENSATE TANK X X X '
X SPRAY POND /EMERG COOLING TOWER X X X X AIR I CoffrROL DIVISION 1 X CONTROL DIVISION 2 X CONTAINMENT INSTR. DIV 1 X I CONTAINMElfr INSTR. DIV 2 X !
ROOM COOLING LPCI X X X X LPCS X X RCIC X HPCI X DIESELS X X X X i
X = IN BOTH GENERIC AND SPECIFIC BWR 3/4s l G = ONLY IN GENERIC EWR 3/4 i S = ONLY IN SPECITIC BWR 3/4 EACE DIVISION HAS 2 DIISEL GENERATORS !
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Section II - ECCS Configuration Data l C. INSTRLHENTATION DEPENDENCIES
- , . The depencencies eacn front line ECCS system has on the listed actua- !
tion instrumentatica for the generic and specific plants are'shown. 2 FRONT LDIE SYSTEMS l CORE SPRAY ADS i' ACTUATICII \ --LPCI PLHPS--- --140PS-- LOGIC DISTRIBENIATICIE \ A B C D A/C B/D C D RCIC HPCI RPV WATER LEVEL 1 !
(LW LOW LOW) !
LSL-2-3-72A X S S S X S X S l -72B S X S S S X X X
-72C S S X S X S S X !
-72D S S S X S X G G l i
RPV WATER LEVEL 2 . [
(LOW LOW) '
LSL-2-3-725,C S X !
-72A.D X S .
RFV WA N LEVEL 3 (LOW)
LT-2 .',-72A X I
-72C X' ,
RPV VATER LEVEL 8 (HIGH) !
LISH-2-3-72A.C X S
-723,D X ;
DRWT.LL PRESSURE HIGH i PISHH-10-100A X S S S X S X G S
-100B S X S S- S X G X X .
-100C S S X S- X S S G G S !
-100D S S S X S X. G X X [
X = IN BOT 1t GENERIC AND SPECIFIC BWR 3/4s l G = ONLY IN GENERIC BWR 3/4 S = ONLY IN SPECIFIC BWR 3/4 l.
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Section II - ECCS Configuration Data C. INSTRUMENTATICN DEPENDENCIES (Continued) !
The dependencias each front line ECCS system has on the listed actua- I tion instrumentation for the generic and specific plants are shown. l
-l FRolff LDIE SYSTEMS l CORE SPRAY ADS ,
ACTUATION \ --LPCI PUMPS--- --LOOPS-- LOGIC l DISTRINGifEATION \ A B C D A/C B/D A C RCIC HPCI l l
?ISL-2-3-52A X S S S X S i
-523- S X S S S G I
-52C S S X S X 5 .!
-52D S S S X S X l INJECTION VALVE DELTA P ^
i DPR58A G t DPR58B G !
DPR58C G i DPR58D G LPCI PUMP DISCHARGE i PRESSURE HIGH 655A.E; 656A.E X !
655C G; 656C,G X l
.i CS PUMP DISCHARGE
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PRESSURE HIGH l 44A.C X :
44B.D X , !
-l ADS DRYWELL PRESSURE !
BYPASS TDER A/C -X !
B/D X ,
i ADS TDER X X f
MANUAL INITIATION SW X X X X X X X X X X ,
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X = IN BOTH GENERIC AND SPECIFIC BWR 3/4s i G = ONLY IN GENERIC BWR 3/4 !
S = ONLY IN SPECIFIC BWR 3/4 ,
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i General Electric Company RE-020-NP Section II - ECCS Configuration Data C. INSTEVENTATION DEPENDENCIES (Continued)
The dependencias each front line ECCS system has on the listed actua-tion instrumentation for the generic and specific plants are shown.
FRONT LDE SYSTDtS l RELATED CORE SPRAY ADS NON-ACTUATION \ --LPCI PUMPS--- --LOOPS-- LOGIC DISTRUGNEATION \ A B C D A/C B/D A C RCIC HPCI LPCI PUMP DISCHARGE FLOW LOW A X 3 B X :
C X D X CS SYS DISCHARGE t FLOW LOW A,C X B,D X CST LEVEL LOW (661B,F) X X f
SUPPRESSION POOL LEVEL HIGH X X ADS INHIBIT SWITCH i A/C X i B/D X j HPCI PUMP DISCHARGE '
FLOW LOW X l HPCI TURBINE EXHAUST PRESSURE HIGH (6563,F) X
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HPCI PUMP SUCTION PRESSURE 14W (653) X j X = IN BOTH GENERIC AND SPECIFIC BWR 3/4s G = ONLY IN GDERIC BWR 3/4 S = ONLY IN SPECIPIC BWR 3/4 i
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Section II - ECCS Configuration Data !
D. Minimum Number of Sensors, Channels, or Components for Failure. PBAPS. j A: = MINIMLH SENSOR FAILURES REQUIRED TO FAIL TRIP FUNCTION
- l B: = MINIMUM NUMBER SENSOR FAILURES REQUIRED TO FAIL FUNCTION - TOTAL ,
C: = MINIMLH NUMBER OF SENSOR TYPES REQUIRED TO FAIL FUNCTION !
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DIFFERENT i Th0K GENERIC !
TRIP (Y/N)
FUNCTIOP A B C B 'C i LPCS PUMP 2 DRYWELL PRESSURE AND 4 2 N N f INITIATION 2 RPV LEVEL 1 (LOW LOW LOW) .i LPCS INJ VALVE 2 RPV LOW PRESSURE PER LOOP 4 1 N N LPCI PUMP 2 DRYWELL PRESSURE AND 4 2 N N .
INITIATION 2 RPV LEVEL 1 i LPCI INJ VALVE 4 INJECTION VALVE DELTA P 4 1 N N :
f ADS INITIATION 2 RPV LEVEL 1 OR 2 1 N N !
2 RPV LEVIL 3 (LOW) l ADS TIME DELAY 2 TIMERS 2 1 N N HPCI 2 DRYWELL PRESSURE AND 4 2 N N l INITIATION 2 RPV LEVEL 2 (LOW I4W) ,
l HPCI LEVEL 8 2 RPV LEVEL 8 (HIGE) 2 1 N N 1
HPCI INJ VALVE 2 DtYWELL PRESCURE AND 4 2 N N l 2 RPV LEVEL 2 -
KPCI WATER 1 CST 1DW LEVEL 1 1 Y N ,
SOURCE RCIC 2 RPV LEVEL 2 2 1 N N INITIATION RCIC TRIP 1 TACH OVERSPEED 1 1 Y N RCIC WATER 1 CST LOW LEVEL TRANSFER 1 1 Y N SOURCE LOGIC OR 1 AUTO XTER LOGIC RCIC INJ VALVE 2 RPV LEVEL 2 2 1 N .N
- Based on data sources a L 6. I I
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RE-020-NP Section II - ECCS Configuration Data ;
E. Surveillance Recuirements, ECCS Instrumentation and Related Subsystemm a ;
SURVEILLANCE
' REQUIREMENTS ** DIFTERENCE !
GENERIC 3/4 PBAPS (Y/N) ;
CORE SPRAY SYSTEM i
REACTOR WATER LEVEL 1 (LOW LOW LOW) M M N DRYWELL PRESSURE HIGH M M N !
REACTOR PRESSURE LOW M M N i MANUAL INITIATION R R N LPCI REACTOR WATER LEVEL 1 M M N DRYWELL PRESSURE HIGH M M N REACTOR PRESSURE LOW M M N l INJECTION VALVE DITTERENTIAL . !
PRESSURE LOW M N/A Y !
MANUAL INITIATION R R N l
HPCI ,
REACTOR WATER LEVIL 2 (LOW LOW) M M N DRYWELL PRESSURE HIGH M M N CST LEVEL LOW M M N SUPPRESSION POOL LEVEL HIGH H M N REACTOR WATER LEVEL 8 (HIGH) M M N t MANUAL INITIATION R R N !
ADS i REACTOR WATER LEVEL 1 M M N !
DRYWELL PRESSURE HIGH. M M N ADS DRYWELL PRESSURE ;
BYPASS TIMER M 6M Y ;
ADS TIMER M M N ;
CORE SPRAY PUMP DISCHARGE PRESSURE M M N LPCI PUMP DISCHARGE PRESSURE M 6M Y -
REACTOR WATER LEVEL 3 (14W) M M N MANUAL INITIATION R R N JNJECTION VALVE STROKE TEST Q M Y !
DIESEL GENERATOR M M N t ELECTRIC M ESSENTIAL AC W W N ESSENTIAL DC W W N ESSENTIAL AC BUSSES W W N r
Based on Technical Specifications, data source No. 7, and source 12. !
- M = MONTHLY, W = WEEKLY, R = REFUELING, Q = QUARTERLY, 6M = 6 MONTHS, !
CSD = COLD SH m W '
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General Electric Company RE-020-NP Section III - ECCS Configuration Differences Classification (Peach Bottom Atomic Power Station)
Plant Specific Classification (Justifi- ,
EWR 3/4 Generic Model Difference cation if Insignificant)
A. ECCS System Differences
- 1. EPCI has 1 pump. PRAPS uses a set of 2 EPCI pumps, both turbine driven on the i same shaft.
- 2. EPCI and RCIC have HPCI and RCIC have a separate suction common gate valve lines from the CST. (locked open) and a common section of pipe '
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of 5 valves to open 4 valves to open for )
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B. Support Systems Differences
- 1. Emergency service ESW has 2 loops. Modify fault tree and water has A loops. perform analysis.
- 2. Onsite AC power has PBAPS has 4 diesel Modify fault tree and 4 independent generators, 2 divi- perform analysis.
divisions. sions. Also, Units 2 and 3 share the same 4 diesels.
- 3. Onsite DC power has PRAPS has 2 DC divi- Modify fault tres and 4 independent sions, each division perform analysis. )
divisions. has 2 sets of batteries.
4 Each ESW loop cools Each ESW loop can pro-one diesel gener- vide cooling to each of ,
ator. the 4 diesel generators. ,,,,
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i Section III - ECCS Configuration Differences Classification (Continued)
(Peach Bottom Atomic Power Station)
Plant Specific Classification (Justifi-BWR 3/4 Generic Model Difference cation if Insignificant)
C. Instrumentation and Procedures Differences j i
- 1. Injection valves Injection valve stroke -
are stroke tested tests performed. ;
quarterly. monthly. ;
- 2. The number of Number of instrument instrument channels channels for Level 1 for Level 1. Level Level 2 and drywell '
2 and DW pressure pressure is 4. Actua- :
is 8. tion logic for CS and LPCI is different.
- 3. Core spray and LPCI PRAPS has process pump discharge switches and the pressure signals funettonal test is are ATUs. tested quarterly.
monthly.
4 LPCI injection LPCI permissive is valve permissive RFV low pressure.
is delta pressure.
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