ML20199B484
| ML20199B484 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/13/1986 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| NLR-N86090, NUDOCS 8606170160 | |
| Download: ML20199B484 (10) | |
Text
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Pubhc Service Electric and Gas Company C:rbin A. McNeill, Jr.
Public Service Electnc and Gas Company P.O. Box 236 Hancocks Bndge, NJ 08038 609339-4800 Vice Presdent -
F4uclear June 13, 1986 NLR-N86090 Director of Nuclear Reactor Regulation US Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MA 20814 Attention:
Ms. Elinor Adensam, Director Project Directorate #3 Division of BWR Licensing
Dear Ms. Adensam:
BAILEY 862 SOLID STATE LOGIC MODULE RELIABILITY PROGRAM HOPE CREEK GENERATING STATION DOCKET NO. 50-354 A telephone conference was held on June 9, 1986, between representatives of Public Service Electric and Gas Company t
(PSE&G) and the NRC to discuss the Bailey 862 Solid State Logic Module (SSLM) Reliability Program as identified in a letter from
- t. A. McNeill (PSE&G) to E.
Adensam (NRC) dated May 23, 1986.
PSE&G stated in the aforementioned letter that a program could be developed from which reliability data associated with the Bailey 862 SSLMs could be generated and applied to further substantiate the reliability of these modules.
In order co develop this program, PSE&G has had discussions with individuals who represent l
several accredited laboratories, one of which will be selected in the near term to perform the actual reliability testing of the Bailey 862 SSLMs.
PSE&G has contracted ASTA Engineering Inc. of Exton, PA. to develop through an independent effort, specific test acceptance criteria in conjunction with a reliability test specification which defines the methodology to be utilized throughout the reliability test program.
A conceptual outline of the test acceptance criteria and test specification are presented in Attachment 1, finalized versions of these documents will be prepared in accordance with the schedule presented below.
A QA program will be applied to the reliability test program.
In J
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N Director of Nuclear Reactor 6-13-86 Regulation addition to the reliability data obtained from the test program, PSE&G has implemented an "in-house" reliability program to monitor the performance of the Bailey 862 SSLMs.
Details of this program are presented in Attachment 2.
PSE&G has been in contact with Bailey Controls in order to obtain reliability data from other. owners of Bailey 862 SSLMs.
In this regard, Bailey has committed to provide PSE&G this information on a quarterly basis.
The schedule for performing the Bailey 862 SSLM reliability test program is as follows:
i a)
Develop test specification including test methodology 1'
and acceptance criteria.
Submit for NRC review by August 15, 1986.
b)
Resolve NRC comments by September 1, 1986.
c)
Initiate testing program by September 15, 1986.
d)
Complete testing program by March 16, 1987.
e)
Submit final report to NRC by May 1, 1987.
I FSU&G believes that the results of the reliability test program will confirm PSE&G's contention that the Bailey 862 SSLMs are highly reliable devices which provide an added margin of safety I
beyond that of standard relay devices.used in other nuclear power j
plant applications.
L l
In the event there are.any questions with respect to the above do not hesitate to contact us.
Sincerely, l
C -Mr.
D.
H. Wagner Licensing Project Manager i
Mr.
R.
W.
Borchardt Senior Resident Inspector i
i l
I
PUBLIC SERVICE ELECTRIC AND GAS COMPANY HOPE CREEK GENERATING STATION BAILEY SSLM RELIABILITY PROGRAM OUTLINE A.
Develop Program Plan, Associated Pro-cedures, and Acceptance Criteria Document V
B.
De te rmine initial sample size from Plant Population (Establish Groups)
V C.
Identify Failure Mechanism of Module / Components V
E.
Evalua te D. Prepare Test Nominal and Specification Worst Case Actuations Rates V
F.
Pe rf o rm ag ing and Reliability testing V
G.
Evaluate Test Results V
H.
Prepare Final Report I
V DOCUMENT
PUBLIC SERVICE ELECTRIC AND GAS COMPANY HOPE CREEK GENERATING STATION BAILEY SSLM RELIABILITY PROGRAM RELIABILITY PROGRAM OUTLINE A.
DEVELOP PROGRAM PLAN, PROCEDURES AND CRITERIA DOCUMENT This initial activity will include detail planning and scheduling of all program activities.
A detailed program plan document will be developed.
In addition, the following program documents will be prepared: QA procedure, Acceptance Criteria, Technical Approach and Methodology.
The following are typical standards that will be used for guidance in defining the requirements for the overall program:
IEEE Standards 279 (Required by 10CFR50.55(h)), 323, 352, 381, 500, 577, 603; and MIL Standard HD BK-217B.
The Acceptance Criteria document will address the reliability goal that a 95% confidence level of successful operation for a period of at least two years can be achieved.
The two year period is based upon compliance with IEEE standard 577 section 4.3.8.
The confidence level is expressed as i 2 sigma where sigma is the standard deviation of the population distribution.
B.
DETERMINATION OF INITIAL SAMPLE SIZE An initial representative test sample will be established based upon the total population of applicable modules.
The sample then will be subdivided into several groups that will be subjected to varying degrees of advance life testing to determine the overall effects of aging (i.e., a result of natural, operational and environmental phenomena) of significant performance characteristics.
C.
IDENTIFY FAILURE MECHANISM OF MODULE / COMPONENTS Before meaningful aging can be performed, the failure mechanism of modules / components related to the aging parameters identified in item "D" will be ascertained in order to assure the validity of the life prediction.
Page 1 of 3
D.
PREPARE TEST SPECIFICATION The Test Specification will define the following requirements:
'measurment of baseline operation characteristics of mod ules/ components.
- perf ormance of the pre-conditioning or accelerated aging of modules.
- performance of the test sequence reliability testing.
- acceptance criteria for performance of post-test inspections.
Aging considerations shall include thermal af fects ( Arrhenius modeling), stress cycling which includes voltage and power fluctuations, humidity, radiation and vibration effects.
The test specification will incorporate actuation rates determined in step E, as guidelines for the determination of module reliability.
Proper simulation of pulsing and sensing of monitoring systems will also be addressed in the specification.
E.
EVALUATE WORST CASE AND NONIMAL MODULE ACTUATION RATES This evaluation will determine the worst case module operation rate (cycles / unit time) of the applicable population of modules.
The actuation rates will be a function of anticipated sys tem operation.
F.
PERFORM AGING AND RELIABILITY TESTING Prior to performing these tests on the module, the end of qualified-life shall be simulated by subjecting the modules to a varying degree of anticipated degradation by accelerated thermal aging using Arrhenius Methodology.
Prior to performing tnis testing, a written procedure shall be prepared, reviewed and approved.
The test shall be performed in an established sequence and monitored using equipment that can provide sufficient resolution for detecting meaning f ul changes in the measured variables.
Page 2 of 3
G.
EVALUATE TEST RESULTS Upon completion of the tes ts, appropriate analysis will be performed with the test results in accordance with the relevant IEEE standards in order to verify that these modules will perform their intended safety f unctions under service conditions.
H.
PREPARE FINAL REPORT WITH RECOMMENDATIONS This report will provide the results of the aging and reliability testing and the reliability analyses.
It will also provide, if required, specific recommendations related to qualified life, surveillance requirements, testing frequency, identification of specific parameters for degradation monitoring, preventive maintenance requirements, limiting conditions of operation and any corrective action.
Page 3 of 3
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1 IC-AP.ZZ-OXX(D) l BAILEY MODULE RELIABILITY PROGRAM i
TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE 2
2.0 REFERENCES
2 3.0 DEFINITIONS 2
4.0 RESPONSIBILITIES 2
5.0 PROCEDURE 3
5.1 Completetion of Work Sheets e
5.2 Routing of Work Sheets 5.3 Reliability Reports ATTACHMENTS 1
BAILEY MODULE WORK SHEET
.i e
J IC-AP.ZZ-OXX(Q) 1 Rev. O
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at 0
I IC-AP.ZZ-OXX(0)
BAILEY MODULE RELIABILITY PROGRAM 1.0 PURPOSE 1.1 This procedure describes the manner in which the I & C Group obtains reliability data for Bailey Modules and provides for periodic reports to the Hope Creek Site Engineering Group.
2.0 REFERENCES
2.1 IC-GP.ZZ-031(Q), " Device / Equipment Calibration:
Bailey Logic Module, type 862."
2.2 IC-GP.ZZ-057(Q), " Rework / Retest of Bailey Optic Transmitter Modules and Optic Receiver Modules.
2.3 IC-GP.ZZ-058(O), " Rework / Retest of Bailey Multi-Plexed Digital input & Multiplexed Output Modules 2.4 IC-GP.ZZ-059(O), " Rework / Retest of Bailey Contact Output Modules."
3.0 DEFINITIONS 3.1 NONE 4.0 RESPONSIBILITIES 4.1 All I&C Personnel shall ensure that any work performed on Bailey Logic Modules be documented on a " Bailey Module Work Sheet" (attachment 1).
4.2 The RL system Lead Engineer shall ensure that the Bailey Module Work Sheets are reviewed and periodic reports generated to Hope Creek Site Engineering, i
IC-AP.ZZ-OXX(Q) 2 Rev. O
1 IC-AP. Z Z-OX X (0)
BAILEY MODULE RELIABILITY PROGRAM 5.0 PROCEDURE 5.1 Completion of Bailey Module Work Sheets 5.1.1 Work Sheets are required to be completed with as much detail as possible for all rework, repair, replacement and/or testing of Bailey Modules.
5.1.2 Work Sheets shall be reviewed for completeness and accuracy by the
.responible I &C Supervisor.
5.2 Routing of Bailey Module Work Sheets 5.2.1 The orginal copy of the Work Sheet shall remain with the orginating W.O.
5.2.2 A copy of the completed and signed Work Sheet shall be sent to the System Engineering Group-for review and f ailure -characteristic analysis.
5.3 Bailev Module Reliability Reports 5.3.1 Bailey Module Work Sheets of O and Non-Q modules shall be analyzed as to similarity of failure characteristics and a data base shall be maintained i
for Bailey Module reliability data.
5.3.2 A report, containing Bailey reliability data and failure characteristic inform-l tion, to the Hope Creek Site Engineering Group shall be compiled on an interval not to exceed 3 months.
IC-AP.ZZ-OXX(Q) 3 Rev. O L.
aur IC-AP.ZZ-OXX(Q)
ATTACHMENT 1
BAILEY MODULE WORK SHEET Work Order
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PANEL:
SLOT:
MODULE TYPE:
OLD S/N NEW S/N PROCEDURE:
WORK PERFORMED:
(And Components Replaced)
PROBLEM WITH OLD MODULE (And Suspected Cause of Failure)
__________/______
\\
Tech Date
/
Supv Date IC-AP.ZZ-OXX(Q) 1 of 1 Rev. O
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