ML20070R535

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TS Improvement Analysis for ECCS Actuation Instrumentation for Oyster Creek Nuclear Generating Station
ML20070R535
Person / Time
Site: Oyster Creek
Issue date: 01/31/1987
From: Ha C, Larson C, Mccandless R
GENERAL ELECTRIC CO.
To:
Shared Package
ML19304C150 List:
References
RE-004, RE-4, NUDOCS 9405200248
Download: ML20070R535 (17)
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Text

GENERAL ELECTRIC COMPANY RE-004 DRF A00-02558E JANUARY 1987 TECHNICAL SPECIFICATION IMPROVEMENT ANALYSIS FOR THE EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION FOR OYSTER CREEK NUCLEAR GENERATING STATION ,

(THIS REPORT HAS BEEN PREPARED FOR GENERAL PUBLIC UTILITIES NUCLEAR CORPORATION THROUGH THE TECHNICAL SPECIFICATION IMPROVEMENT COMMITTEE OF THE BWR OWNERS' GROUP)

PREPARED BY: -

C. Ha, Senior Engineer Reliability Engineering VERIFIED BY:

C. L. Larson, Principal Engineer Reliability Engineering APPROVED BY:  ! hh R.J. McCandless, Manager N

Reliability Engineering e

9405200249 940512 PDR ADOCK 05000219 P POR

IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT i Please Read Carefully The only undertakings of General Electric Company 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 has not contracted for its use for any purpose other than that for which it is intended, is net authori:ed; and with respect to any unauthorized use, General Electric Company makes no representation or warranty, and assumes no liability as to the completeness, accuracy, or usefulness of the

nformation contained in this document, l

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TABLE OF CONTENTS Page 1

1. INTRODUCTION 2
2. EVALUATION METHOD 4
3. RESULTS OF ECCS EVALUATION 5
4.

SUMMARY

AND CONCLUSIONS 6

5. REFERENCES A-1 APPENDIX A: ECCS ACTUATION INSTRUMENTATION EVALUATION FOR OYSTER CREEK (OC) i t

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1. INTRODUCTION  !

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This report extends the generic study of modifying the technical specification requirements of the amergency core cooling system (ECCS) on a plant specific basis for Oyster Creek Nuclear Generating Station (OC), a BWR 2. The generic study (Reference 1) provides a technical basis to modify the surveillance test intervals and allowable out-of-service times of the ECCS actuation instrumentation from those of the 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 Oyster Creek are presented herein.

GENERAL ELECTRIC COMPAh7

2. EVALUATION METHOD I

The plant specific evaluation of the modification of the surveillance test frequencies and allouable out-of-service times of the ECCS actuation instrumentation was r,erformed in the following steps:

a. Gather plant specific inforsation on the ECCS from General Public Utilities (GPU) Nuclear Corperation. The information includes the following: l I

(1) Piping and Instrumentation Diagrams (P& ids) of ECCS, isolation condenser, emergency service water systems, and air systems r.o ADS valves. l (2) Elementary Diagrams of the ECCS and related systems. l (3) ECCS and electric power distribution system descriptions l such as those in the plant Final Safety Analysis Report (FSAR).

(4) Technical specifications on the ECCS, the suppression I

chamber, and the electrical systems.

(5) Informatien on ECCS surveillance test procedures.

(6) Dependency matrices showing dependence of ECCS systems on.  :

support systems and on actuation instrumentation.

(7) Available data on actuation instrumentation failures.

The latest revisions of the above items were supplied by GPU Nuclear Corporation.Section I of the checklist in Appendix A vas used to identify the data source of the plant specific information.

b. Construct the plant specific ECCS configuration from the plant specific information. Sections "A" through "E" in Section II of the Appendix A checklist was used for this process. -l l

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T GENERAL ELECTRIC COMPA.l

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 dif ferences, symbol diff erences, and other minor non-functional differences. Other effects not requiring analysis are those in which the specific plant 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 vould require engineering assessment in a " simple study" as shown in Appendix 7 of Reference 2.

(3) Differences which require additional analyses to evaluate the effect on the ECCS reliability. Examples of such differences are use of two diesel generators and two electrical systems in a specific plant compared with a larger number of diesel generators and electrical systems in the generic evaluation. Disposition of these items would require additional analyses (" Modify fault trees and perform analysis.") to compare with the generic results. These analyses are documented in Reference 2. i

e. Compile a list of plant specific differences of Categories (2) and (3).

GENERAL ELECTRIC COMPANY

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f. Assess the reliability effect of the differences identified in 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 OF ECCS EVALUATION The results of the plant specific evaluation of the ECCS for Oyster Creek are documented in Appendix A of this report. The results show that the ECCS configuration of Oyster Creek has no differences from the BWR 2 generic model* which are classified Category (2) or (3). (Because there are only two BWR 2 models in the study, few differences were expected.) .

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  • The term " generic model" means the ECCS configuration used in the generic analysis.

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GENERAL ELECTRIC COMPAN'i

4.

SUMMARY

AND CONCLUSIONS A plant specific evaluation of modifying the surveillance test intervals and allowable out-of-service times of the ECCS from the technical specifications of Oyster Creek has been performed. The evaluation utilized the plant specific information supplied by GPU Nuclear Corporation and the generic basis and the additional analyses documented in References 1 and 2.

The results indicate that the ECCS configuration for Oyster Creek is similar to the ECCS configuration in the generic evaluation, with no significant differences. Therefore, the generic basis in References 1 and 2 is applicable to Oyster Creek.

GENERAL ELECTRIC COMPANY I

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5. REFERENCES l

1 (1) D. B. Atcheson, et al., "BWR Owners' Group Technical l

-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 wmenstration for BWR ECCS Actuation Instrumentation) Part 2", General Electric Company, NEDC-30936P, to be issued, February 1987.

GENI 2RAL ELECTRIC COMPANY APPENDIX A ECCS ACTUATION INSTRUKENTATION EVALUATION FOR OYSTER CREEK NUCLEAR GENERATING STATION 9

A-1

GENERAL ELECTRTC COMPAhY Section I - ECCS Plant Specific Data Sources Utilityt General Pub'.ic Utilities b'uclear Corporation Plant Oyster Crtek Nuclear Generating Station Source Number

1. ECCS and Isolation Condenser P&lDs
2. Emergency Service Water P& ids
3. Electrical Drawings
4. Instrumentation Logic Diagrams
5. ECCS Fault Trees
6. Final Safety Analysis Report -
7. Technical Specifications 4
8. Other Drawings
9. Dependency Matrices
10. Failure Data
11. Test Procedure Questionnaire
12. Telephone Call Records
13. NEDC-30936P, Part 1 i

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GENERAL E12CTRIC COMPANY Section II - ECCS Configuration Data A. ECCS Svstam Generic Difference Data

  • OC BWR 2 (Y/N) Source
1. Number of:

- CS Pumps / Loops 8/2 8/2 N 6 ADS Valves 5 5 N 6

2. Needed for Success, Number of:

- LPCS Pumps / Loop 2/1 2/1 N 13 ADS Valves 3 3 N 13

3. Number of:

- Diesel Generators 2 2 N 9,6 Electrical Divisions 2 2 N 9,6

4. Isolation Condenser Tanks / Loops 2/2 2/2 N 6
  • The numbers shown in the Data Source column refer to the documents listed in Section 1.

A-3

GENERAL ELECTRIC COMPANY Section II - ECCS Configuration Data B. SUPPORT SYSTEM DEPENDENCIES The dependencies each front line ECCS system 1as on the listed support subsystems for the generic and specific plants are shown.

FRONT LINE SYSTEMS SUPPORT \ CS CS ADS ADS IC IC DIESELS SUBSYSTEMS \ 1 2 1 2 1 2 1 2 0FFSITE AC POWER X X ONSITE AC POWER DIVISION 1 X X X X X DIVISION 2 X X X X X ONSITE DC P0bTR DIVISION 1 X X X X X X X DIVISION 2 X X X X X X X SERVICE WATER (NONE REQUIRED)

WATER SUPPLY SUPPRESSION POOL X X CONDENSATE TANK X X X X AIR SERVICE AIR X X X X INSTRUMEhI AIR AIR START ROOM COOLING (NONE REQUIRED)

X = IN BOTH GENERIC AND SPECITIC Bk1 2s G = ONLY IN GENERIC BWR 2 S = ONLY IN SPECI7IC BWR 2 A-4 l

GENERAL ELECTRIC COMPANY Section II - ECCS Configuration Data C. INSTRtHENTATION DEPENDENCIES The dependencies each front line ECCS system has on the listed actua-tion instrumentation for the generic and specific plants are shown.

FRONT LINE SYSTDiS ACTUATION \ CS CS ADS ADS IC IC INSTRUMENIATION \ 1 2 1 2 1 2 RPV WATER LEVEL 1 (LOW LOW LOW)

A,B X X C.D X X RPV WATER LEVEL 2 (LOW LOW)

A,C X X X X B.D X X X X DRYWELL PRESSURE A,C X X X X B,D X X X X RPV PRESSURE A,B X X C,D X X RPV PRESSURE PERMISSIVE A,C X X BD X X ADS TIMER X X CS DISCH FLOW LOW A,C X X X X B,D X X X X X = IN BOTH GENERIC AND SPECIFIC BWR 2s G = ONLY IN GENERIC BWR 2 S = ONLY IN SPECIFIC BWR 2 A-5

GENTLRAL ELECTRIC COMPANY Section II - ECCS Configuration Data D. Minimum Number of Sensors. Channels, or Components for Failure, Oyster Creek.

A: = MINIMUM SENSOR FAILURES REQUIRED TO FAIL TRIP FUNCTION B: = MINIMUM NUMBER SENSOR FAILURES REQUIRED TO FAII. FUNCTION - TOTAL C: = MINIMUM NUMBER OF SENSOR TYPES REQUIRED TO FAIL FUNCTION DIFFERENT FROM GENERIC DATA TRIP (Y/N) SOURCE FUNCTION A B C B C CS PUMP 2 MAIN PUMP DISCHARGE 4 1 N N 4.6 INITIATION PRESSURE / LOOP, 2 LOOPS CS INJ 2 RPV LOW PRESSURE 4 1 N N 4,6 VALVE PERMISSIVE / LOOP ADS 2 HIGH DRYWELL 4 1 N N 4,6 INITIATION PRESSURE / DIVISION a

ADS TIME 1 TIMFR/ DIVISION 2 1 N N 4,6 DELAY IC 2 RPV LEVEL 2 4 2 N N 4,6 INITIATION (LOW LOW) AND 2 RPV OVERPRESSLTE i

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- GENERAL ELECTRIC COMPANY Section II - ECCS Configuration Data E. ECCS Instrumentation and Related Subsystem Surveillance Requirements SURVEILLANCE REQUIREMENTS DITTERENCE DATA GENERIC 2 OC (Y/N) SOURCE CORE SPRAY SYSTEM M M N 7 REACTOR WATER LEVEL 2 (LOW LOW)

M M N 7 DRWTLL PRESSURE HIGH M M N 7 REACTOR PRESSURE LOW ADS M M N 7 REACTOR WATER LEVEL 1 (LOW LOW LOW)

M M N 7 DRYWELL PRESSURE HIGH R R N 7 ADS TIMER CORE SPRAY PUMP DISCHARGE PRESSURE R R N 7 V

DIESEL GE.ERATOR 2/M 2/H N 7 ELECTRIC P0kTR D D N 7 ESSENTIAL AC ESSENTIAL DC W W N 7 D D N 7 ESSENTIAL AC BUSSES ISOLATION CONDENSER M M N 7 RPV LEVEL LOW LOW RPV PRESSURE HIGH M M N 7 M = MONTHLY W = WEEKLY D = DAILY R = REFUELING A-7

  • GENERAL ELECTR1C COMPAhY Section III - ECCS Configuration Differences Classification (Oyster Creek)

Plant Specific Classification (Justifi-BWR 2 Generic Model Difference cation if significant)

A. ECCS System Differences No Differences B. Support Systems Differences No Differences C. Instrumentation Differences No Differences.

e A-8 FINAL

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