ML20151A578

Forwards Overall Executive Summary of Reliability Program & Related Repts Detailing Bases for Summary.Proprietary Repts, Functional Verification Rept... & ...Feasibility Study for In-Situ Testing... Also Encl.Repts Withheld

ML20151A578
Person / Time
Site:	Hope Creek
Issue date:	04/04/1988
From:	Miltenberger S Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML19302D405	List: ML20151A578 ML20151A581 ML20151A660
References
NLR-N88051, NUDOCS 8804070088
Download: ML20151A578 (24)

Text

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s Pubhc Service Electric and Gas Company Steven E. Miltenberger Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, NJ 08038 609 339-4199 Vce Pres 6 dent -

twear opvatens April 4, 1988 NLR-N88051 United States Nuclear Regulatory Commission '

Document Control Desk Washington, DC 20555 i Gentlement i BAILEY RELIABILITY PROGRAM - FINAL REPORT HOPE CREEK GENERATING STATION DOCKET NO. 50-354 License Condition 2.C.(5) of the Hope Creek Operating License '

NPF-57 requires that "PSE&G shall implement a reliability program, to demonstrate solid state logic module reliability, as described i in its letters dated June 13 and 24, 1986. The results of the  !

reliability program shall be submitte( to the staff prior to the i' end of the first refueling outage." This letter satisfies the License Condition. Attachment 1 to this letter is an overall [

executive summary of the reliability program. Attachments 2 thru 8 contain the detailed bases for the executive summary.  !

Should you have any questions on this transmittal, do not hesitate -

to call.

Slncerely, bw Attachments L,' $$$k a s t t ar}e 4Pt e,,e  ;

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C904070099 990404 PDR ADOCK 05000354 DCD i o

s Document Control Desk 2 04-04-88 C Mr. G. W. Rivenbark USNRC Licensing Project Manager Mr. G. W. Meyer USNRC Senior Resident Inspector Mr. W. T. Russell, Administrator USNRC Region I '

Mr. D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628

. ATTACHMENT 3 SITE RELATED NODULE RELIABILITY IMPROVEMENTS Attached is a copy of a letter from Bailey Controls Company to PSE&G dated December 17, 1986. This letter documents the results of an inspection held by Bailey at Hope Creek for the purpose of identifying potential methods to improve Bailey module reliability at Hope Creek. A number of recommendations were incorporated in this letter. PSE&G's resolution to the recommendations, are attached following the Bailey letter.

This letter and PSE&G's resolutica satisfies the requirement to have Bailey review Hope Creek handling of Bailey modules, as documented in PSE&G letter NLR-N86148, dated October 5, 1986, i

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Bailey Controls Company Babcock & Wilcox a McDermott company 29801 Euclid Avenue -.

Wickkffe, ONo 44092 (216) 585 8500 Telex: 980621 - Cable: Bailymater December 17, 1986 i

Public Service Electric and Gas Co.

Hope Creek Generating Station Buttonwood Road Hancocks Bridge, NJ 08038 ,

Attention Mr. G..Tenenbaum Nuclear Systems Engineering

Reference:

BCCo Inspection / Observation and Audit (10/29 - 11/5/86) 4 Gentlemen During the period October 29 to November 5, 1986 a team consisting of six Bailey

Controls Company personnel (Quality Assurance, Engineering and Field Service) conducted an Inspection / Observation and Audit of storage, shipping and trouble-shooting of the 862 system at the Hope Creek site.

The Inspection / Observation and Audit consisted of a complete review of the i implementation of PSE&G applicable procedures relative to Receipt Inspection,

, Testing and Calibration, Insta11atien, Handling of Nonconforming Material and Shipment of Defective Equipment with special emphasis on items of special

interest to the Bailey Controls Company such as training and qualification of personnel, handling of Static Sensitive Devices, Troubleshooting of the 862 System and Logic Modules.

The following items are identified deficiencies and recommendations resulting from the Inspection / Observation and Audit by the BCCo Team.

I. Material Control Decartment (TB-1 Warehouse):

A) Nuclear Procurement and Material Control Procedures (M11-I-208, Shipping, M11-P-200, Receiving, M11-P-110, Indoctrination and Training, M11-P-410, Receive Material, M11-P-500, Classification and Storage of Material) and Nuclear Quality Assurance Procedures (QAP-4-1, Receiving Inspection, QAP-4-2, Receiving Inspection Nonconformances) used in receiving and inspection of 862 modules l do not address or define the handling requirements for equ*pment l containing Static Sensitive Devices.

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B) The warehouse does not contain a static free work station in an access controlled area for module receiving, inspection and I shipping.

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December 17, 1986 Public Service Electric & Gas Co.

C) Warehouse control of static sensitive equipment should be improved to prevent inadvertent handling by unqualified personnel.

D) The BCCo Team observed several improperly packaged 862 modules (P/N 6631291A1, S/N 1011, 1973, 2181) being accepted by Nuc'. ear Procurament and Materials Controls (TB-1 varehouse) for return to veridor for repair.

E) Procurement and Material Controls personnel (Receiving, Shipping) are not trained in the proper Handling of Static Sensitive Devices.

II Material Control Department (Hope Creek Storeroom)

A) Several cases of improperly packaged modules were found in the Class 'A' storage area. BCCo recommends that the Nuclear packaging ce maintained during storage.

B) Implement a periodic inspection program for Nuclear Packaged equipment to review the humidity indicators and Level *B' packaging requirements for Class 'A' (ANSI N45.2 Level 'B' packaging) storage.

III I&C Departaent (Testino and Calibration. Installation):

A) Procedures (IC-GP.ZZ-008(Q), I&C Troubleshooting, IC-AP.ZZ-014 (Q), I&C Personnel Qualification and Training, IC-GP.ZZ-031(Q),

General Procedure Bailey Logic Module Type 862, IC-GP.ZZ-048(Q),

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Device / Equipment Calibration Circuit Board Revork) should be updated to address the training and qualification of personnel in the proper grounding / removal, installation and transportation etc., of the 862 modules as documented by the BCCo team for for submittal to PSE&G (attached).

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B) 862 hodules returned to Class 'A' storage after testing, etc.

must be packaged to meet the original Level 'B' Packaging requirements.

C) 862 Cabinets in the upper (Level 163) and lover (Level 102)

Control Equipment Rooms should remain closed and locked at all times.

D) The BCCo team recommends that training for 862 System troubleshooting be formalized and improved in the following areas:

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Public Service Electric & Gas Co. December 17, 1986 3-

1. Handling of Equipment containing Static Sensitive Devices

2. FPLA Program Select determination

3. Module Backplane and location Inspection E) The 862 Logic Module tester should be redesigned to increase the ease of use and reduce the likelihood of damage to the module under test due to technician error.

F) Perform a periodic test review on the FFLA Test Chip (GP027) since this chip is used to check modules.

G) BCCo. recommends push-on-Jacks be used in place of clip on's when troubleshooting wirevrap posts on backplane to prevent inadvertent shorting.

H) Procedure IC-GP.ZZ-031, attachments 1 through 4, should be updated to identify the proper jumper pin locations for each Buffered Input, and the location of Pin 1 on the FPLA chip.

Attachments 1 through 4 must be more legible.

. IV Operations Depart,ggptt, A) Procedure OP-AP.ZZ-109(Q) (Equipment Operational Control) requires updating to identify the required bulb replacement number to be used when replacing bulbs for each pushbutton assembly for the RZ's, Master Specialties, Cutler-Hammer.

i i B) Update procedure GP-AP.ZZ-109 (Q) section 5.11.2.1 to allow j removal of light bulbs as designed by the front access of lamp vindow to reduce module cycling. It is understood that care should be exercised to ' Avoid cycling equipment' next to the replacement l

, area. .

C) Add Bulb types for RZ's (#327), Master Specialities (#327)

and Cutler Hammer (#28PSB) to the above procedure to prevent

the usage of incorrect bulb types. The below bulbs were obser-ved to be in a common storage area.

j Voltage Current Filament 327 28V .04A C-2F i 328 6V .20A C-2R 382 14V .08A C-2F

! 387 28V .04A C-2F Sylvania (327) has slightly different (lower) light output than GE.

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Public Service Electric & Gas Co. December 17, 1986 4

D) 862 Cabinets in the upper (Level 163) and Jover (Level 102)

Control Equipment Rooms should remain closed and locked at all times.

I Y Ooerations (Plannina)

A) The BCCO team recommends that circuit isolation be performed by methods other than disconnecting pre-fabricated cables or removing logic modules. i VI Enaineerina Decartment e

A) Develop a procedure / standard defining the proper handling requirements for equipment containing Static Sensitive Devices which could then be referenced in all applicable 7 PSE&G procedures.

B) A sechanism should be available to identify and properly coordinate concurrent changes to FPLA programming sheets.

VII I&C Decartment (Nonconformina Material): (Reference Section I C)

! A) Procedure SA-AP.ZZ-20(Q) (Nonconformance Program) should be updated to address the proper handling and packaging of non-conforming 862 modules prior to authorization for return to Vendor by the Shipping Department.

r B) All nonconforming 862 modules should be appropriately packaged, tagged and immediately placed in the defective equipment locker and remain there until proper authorization / release to l ship to the Vendor is received. At that time the 862 modules -

are transported directly to the shipping department by qualified personnel 1

! In order for PSE&G to accomplish the above recommendations in the most expeditious manner, the BCCo Team vill provide the following:

1 A) Establish a system at BCCo for identifying the special i

handling requirements for 862 modules containing Static I Sensitive Devices on the PSE&G copy of the packing ,

List for Receivi g personnel.

B) Establish a system at BCCo for applying the ' Static Sensitive Devices

• 1abel adjacent to the shipping label to insure proper handling by qualified personnel upon receipt.

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Public Service Electric & Gas December 17, 1966

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C) Review and indicate ti.e recommended changes to the above reference procedures to improve product reliability anu

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submit marked copies to PSE&G for review, publication and irplementation.

D) Prior to the next surveillance cycle (date to be determined) one (1) or two (2) principals of the Bailey Inspection /

Observation and Audit Team will revisit the site to perfore an implementation audit and review.

All PSE&G personnel contacted during this Inspection / Observation and Audit were courteous, cooperative and knowledgeable in their assigned areas. The BCCo Team thanks them for their cooperation and hospitality during the Inspection / Observation and Audit.

Sincerely, BAILEY CONTROLS COMPANY 0

A. J. Xukva l Audit Coordinator Quality Assurance AJX tgg

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O PSEG Put c Se"..ce EWM ana Gn Compaai PO Bev 236 Hrc03s B' age Nee, wie, CE038 Nuc! ear Department

'I March 29, 1988 ELE-88-0078 To The General Manager - Enginee ring & Plant Be tte rme nt RESPONSE TO BAILEY TEAM RECOMMENDATIONS TO IMPROVE 862 SYSTEM RELIABILITY REF: BAILEY CONTROLS CO. LETTER TO PSE&G DATED 12/17/86.

PSE&G recently contracted Bailey Controls Co. to pe rf o rm a n Inspection / Observation and audit for the purpose of identifying potential methods of improving 862 system reliability. The results of that audit and subsequent recommendations are outlined in the re fe re nce letter f rom Bailey Controls Co. to PSE&G dated 12/17/86.

The following discussion has been provided to document the actions which were taken to disposition each recommendation:

ITEM I.A Nuclear Procurement and Material Control Procedures, used in receiving and inspection of 862 modules, do not address or de fine the handling requirements for equipment containing Static Sensitive devices.

Disposition:

This recommendation has been incorporated. The Procu rement and l Material Control department has identified the need and prope r technique for handling static sensitive devices in lette r PMC-87-340 tc Distribution. The techniques outlined are consistent with Bailey Controls Co. standards for handling of

static sensitive equipment. The specific procedures for shipping and receiving are being revised to incorporate conside rations for static sensitive equipment.

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6 General Manager -

Engineering & Plant Betterment 3/29/88 ITEM I.B The warehouse does not contain a static f ree work station in an access controlled area for module re ce iv ing, inspection and shipping.

Disposition:

This recommendation has been incorporated. A static f ree work station has been installed in the TB1 warehouse.

ITEM I.C Warehouse control of static sensitive equipment should be improved to prevent the inadvertent handling by unqualified pe rsonne l .

Disposition:

This recommendation has been incorporated. Warehouse employees are trained to Nuclear Procurement and Material Control Procedures which are being revised to includo considerations for -

static sensitive equipment. Letter PMC-87-340 referenced in the disposition to I. A has been issued to address handling static sensitive equipment in the interim pe riod.

ITEM I.D The BCCo team identified several improperly packaged 862 modules

• being accepted by NP&MC for return to the vendor.

Disposition:

Non-conforming modules are sent from I&C to NP&MC for shipping to the vendor. Shipping packaging is applied in the NP&MC department in accordance with the device requirements.

ITEM I.E NP&MC personnel are not trained in proper handling of static sensitive devices.

Disposition:

This recommendation has been incorporated. See the disposition to item 1.C ITEM II.A t

Several cases of improperly packaged modules were found in the Class "A" storage area. BCCo recommends that the Nuclear packaging be maintained during storage.

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General Manager -

Engineering & Plant Be t te rme nt 3/29/88 Dispositions ,,

Bailey electronic modules are maintained in Class "A" storage in accordance with ANSI N45.2.2. Packaging will be maintained as provided for in the level A storage requirements.

ITEM II.B Implement 'a periodic inspection program for Nuclear Packaged equipment to review the humidity indicators and level "B" packaging requirements for Class "A" storage.

Disposition This recommendation will not be incorporated. The Class "A" storage area is equipped with temperature and humidity control eliminating the need for periodic inspection of individual humidity indicators.

ITEM III.A Station I&C procedures should be updated to address the training and qualification of personnel in the proper grounding / removal, installation and transportation etc. , of the 862 modules as documented by the BCCo team for submittal to PSEkG.

Dispos itior.:

l This recommendation has been incorporated. Technician training addresses the proper use of static sensitive techniques, and the

, applicable procedures require that qualified individuals are l assigned to perform the work .

ITEM III.B 862 modules returned to Class "A" storage af ter testing, etc.

must be packaged to meet the original level "B" pack aging re qu ireme n ts .

Disposition:

This recommendation will not he incorporated. As per procedure IC-GP.ZZ-031(0), anti-static precautions must be exercised when handling this device and its components. This would include handling when returning the modules to folio. Af ter return to folio they are placed in a Class A storage facility. Le ve l B pack aging is only required when the modules are shipped offsite.

ITEM III.C Bailey cabinets in the Upper and Lower Equipment Control P,ooms should remain c,'osed and locked at all times.

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4 Gene ral Manage r -

Engineering & Plant Be t te rme nt 3/29/88 Disposition:

The subject cabinets are ncrmally locked. The keys for these cabinets are maintained for sign-out from the Operations Department of fice located outside the Main Control Room and the I&C Department.

ITEM III.,D The BCCo team recommends that training for 862 system troubleshooting be formalized and improved in the following a re as :

1. Handling of equipment containing static censitive devices.

2. FPLA program sheet determination.

3. Module backplane and location inspection.

Disposition:

This recommendation has been partially incorporated. Te chnic ian training on the Bailey 862 system has been enhanced to include proper techniques in handling static sensitive modules and instruction on FPLA burn-in. Module backplane and location inspection would typically be pe r f orme d whe n the no rmal troubleshooting process does not identify the cause of the anomoly.

ITEM III.E The 862 logic tester should be redesigned to inc re ase the ease of use and reduce the likelihood of damage to the module under test due to technician error.

Disposition:

This recommendation has been incorporated. A new automated 862 Solid State Logic Module tester has been purchased which incorporates the above re comme nda t ions .

ITEM III.F Perf orm a pe riodic test review on the FPLA test chip since this chip is used to check modules.

Disposition:

This recommendation will be satisfied in the normal course of pe rf orming SSLM testing. The ne w te s t f ixtu re tests SSLMs with the system circuit FPLA on board obsoleting the need for a test chip. In the cases whe re the te s t chip is used for module check-out, the tester will automatically test the chip logic.

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General Mannger ,

Engineering & Plant Be t te rme nt 3/29/88  ;

i ITEM TII.G

• Bailey Controls Co. recommends push-on-jacks be used in place of clip on's when troubleshooting wirewrap posts on backplane to p re ve nt inadvertent shorting.

Disposition:

- This recommendation has been incorporated. Push-on-jacks have been made available to the technicians and are commonly used for 862 system troubleshooting.

ITEM III.H Procedure IC-GP.22-031(0), attachments' l thru 4 should be updated to identify the proper jumper pin locations for each buffered input, and the location of pin 1 on the FPLA chip. Attachments 1 through 4 must be more le gible .

Disposition:

No change will be made as a result of this recommendation.

Revision 7 of IC-GP.22-031(O) legibly indicates staple j umpe r positions with associated Buf fer Input numbers, and depicts the FPLA notch associated with pin #1.

j ITEM IV.A

! Procedure OP-AP.ZZ-109(O) requires updating to identify the i required bulb replacement number to be used when replacing bulbs

! for each pashbutton assembly for the RZ's, Maste r Specialties,

and Cutle r Hamme r assemblies .

Disposition:

This recommendation will not be incorporated. The replacement lamp bulbs are maintained in a segregated cabinet located in the Main Control Room. The operator replaces the defective bulb with j

i the same part numbe r bulb, and the re fore procedure revision is not re qu ired .

1 ITEM IV.B

) Update procedu re OP-AP.22-109( 0) to allow removal of light bulbs I from R2 face.

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General Manager -

Enginee ring & Plant Be tte rme nt 3/29/88 Dispositions ,

This recommendation has been incorporated. Station Procedure OP-AP.22-109(0) Section 5.10.2.1 has been revised to instruct the Main Control Room operators to replace lamp bulbs without removing the R2 module unlese required for troubleshooting.

ITEM IV.C Add bulb numbe rs to procedu re OP- AP. 2 2-109 ( 0) to prevent incorrect bulb replacement.

Disposition:

This recommendation will not be incorporated. See the disposition to IV.A ITEM IV.D Bailey control cabinets should retain closed and locked at all times.

Disposition:

The subject cabinets are normally clcsed and locked. See disposition to item III.C ITEM V.A The BCCo team recommends that circuit isolation be pe rf orme d by methods other than disconnecting pre-f abricated cables or removing logic modules.

Disposition:

This recommendation has been incorporated. This practice has never been commonly employed and has since been eliminated in all cases except those in which the module is removed for protection or no othe r blocking means is available. In addition, the De s ign Memorandum discussed in the disposition to VI.B includes E&PB guidelines for signal blocking spe cif ied in besign Change Pa ck age s .

ITEM VI.A Engineering should develop a procedure / standard defining the requirements for equipment containing Static sensitive Devices which could be re f e re nce d in all applicable PSE&G procedures.

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e Gene ral Manager -

Engineering & Plant Be t te rme nt 3/29/88 l Disposition This recommendation is inconsistent with Departmental proce du re s . The standards and proper methods for handling static d

i sensitive equipment are included in the various I&C procedures.

ITEM VI.B i A mechanism should be available to identify and properly coordinate concurrent changes to FPLA programming sheets.

i l Dispositions This recommendation has been incorporated. Design Memorandum

. H-1-ZZXX-CDM-0616 has been written to document guidelines and instructions for Engineering and Plant Better.nent (E&PB) i modifications to the 862 system. The Design Memorandum includes guidelines for coordination of concurrent design changes to FPLA programming sheets.

ITEM VII.A Procedure SA-AP.22-20(O) (Nonconformance Program) should be updated to address the proper handling and packaging of non-conforming 862 modules prior to authorization for return to j vendor by the shipping department.

Disposition:

l This recommendation will not be incorporated. The purpose of procedure SA-AP.22-20(0) is to establish a program for identifying, controlling, documenting, dispositioning, and i

correcting nonconforming parts and components, and the refore j specific information on handling 862 modules is inappropriate.

l ITEM VII.B All nonconforming 862 modules should be appropriately packaged,

. tagged and immediately placed in the defective equipment locker and remain there until proper authorization / release to ship to the vendor is received. At the time the 862 modules are e .nsported directly to the shipping department by qualified

,)e rs o nne l .

l Disposition:

1 This recommendation is being partially met. Nonconforming 862 l

modules are tagged, packaged in anti-static bags, and placed in l

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Gene ral Manager -

Enginee ring & Plant Be t te rme nt 3/29/88 the defective parts locke r. Nuclear packaging is not used at this phase as modules are of ten removed for subsequent testing or inspection. The modules are typically transported to the shipping department for packaging by station technicians.

. . *0 P. P. J. O ' Donne ll Acting Manager -

Nuclear Electrical Engineering MJMrsrj C Gene ral Manage r - Hope Creek Ope ra tion Gene ral Manager - Quality Assurance Standards Records Coordinator cm-mjm3/16 8 ,

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ATTACHMENT 4 i BAILEY RELIABILITY DATA  !

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i The attached letters from Bailey Control company' dated May 23, 1986, May 23, 1987, and November 23, 1987 forward the results of' ,

Model 862 SSLM's. The surveys cover an approximate 18 month  :

period of time. The average yearly failure rate is signficantly less than the allowable 5% rate discussed in PSE&G and NRC  ;

correspondence.

This information satisfies the commitment documented in PSE&G l letter NLR-N86090, dated June 13, 1986 and NLR-N86076, dated June i 24, 1986. l 1

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m 29601 Euchd Av:n7 Wickliffe, otuo 44092 Sebcock & Cucos a McDermott company (316)S45 4500

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• I 1 May 23, 1986

' Upnimd 4 ELETWCAL K L r--siam MT. PYEL _

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g Publi e vice Electric and Gas --

M 07701 ' sum iss5_

Howark, NJ $ ag---'

Mr. Bob Rosko - Mail Code 21

'd sw su Attention: u, E

Subject:

Bailey 862 Systems Reliability in thi< raw 4o

Dear Bob,

k I surveyed users of 862 systems to obtain failure data fromThe s their records. There wore 62 failures (plus an time of 66,281 module months. "customer cdditional 6 for which the customer confessed were induced *).

1.12% as:

From this sample the failure rate per year is 12 M 62 i 66,281 = 0.0112 the largest user in the group has experienced a Significantly, (five hundret'ha of one percent).

very low failure rate of this 0.052%as is Public Service for Hope Creek, d Being a large user, customer has obviously maintained to 862aequipment, staff of knowledgeable anand we both know that skilled people with respect this contributes to equipment reliability.

we expect that In summary, after the usual start-up anomalies, the Hope Creek 862 Systems will be highly reliable.

Very truly yours, BAILEY CONTROLS COMPANY w &

,xsMcMahon, Manager R. D.

Quality Assurance RDM ]ms

i Bailey Controls Company

. a wn... a ueo.<mw comuny moi sueno wenu. t Wicklitfe, Ohio 44092  ;

(216) 545-8500  !

Telen: 960621 - cable: saitymeter l May 5, 1987  !

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l Public Service Electric and Gas Co. l Hope Creek Generating Station  !

Buttonwood Road  !

Hancocks Bridge, NJ 08038 Attention: Mr. Mike Massaro l I

Dear Mike j The following information is a summary of the failure data collected i from other 862 system users. The survey covered 2267 modules with an operating time of 60,888 module months. There were 50 failures during  ;

this time period.

From this sample the failure rate per year is .98% as:

12 x 50 i 60888 a 0.00985 We also ask the customer to report separately the failures of the 862 logic modules. This portion of the survey covered 971 logic modules sith an operating time of 28,848 module months. There were 29 failures during this period.

From this sample the failure rate per year is 1.2% as:

12 x 29 + 28848 s 0.01:06 For your information another questionnaire has Just been sent out.

You can expect another report as soon as the questionnaires are completed and returned.

Very truly yours, BAILEY CONTROLS COMPANY Mark E. Mrazek MEM:dz Quality Assurance

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Bailey Controls Company Sabcock & WHcom a McDermott company 29601 Euckd Avenue Wickhtfe, Ohio 44092 (216) 585 8500 Telen: 960621 - Cable: Bailymeter November 23, 1987 public Service Electric and Gas Co.

Hope Creek Generating Station Buttonwood Road Hancocks Bridge, NJ 68838 Attention: Mr. Mike Massaro Dear Mike The following information. .a a sumunary of the failure data collected from other 862 system users. The survey covered 2055 modules with an operating time of 76,979 module months. There were 47 failures during this time period.

From this sample the failure rate' per year is .73% as:

12 x 47 76,979 = .98732 We also ask the customer to report separately the failures of the 862 logie modules. This portion of the survey covered 1964 logie nodules with an operating time of 41,749 module months. There were 24 failures during this period.

From this sample the failure rate per year is .69% as:

12 x 24 41,749 = .09689 For your information another questionnaire has just been sent out.

You can expect another report as soon as the questionnaires are completed and, returned.

Very truly yours, BAILEY CONTROLS COMPANY

/ /

Mark E. Mrarek MEM/dr Quality Assurance I

O ATTACHMENT 5 MODIFICATION OF EXISTING TEST EQUIPMENT 1

s PSE&G letter NLR-N86148, dated October 15, 1986, documents the ccarsitment to modify the then existing module test equipment and procedures to permit module testing without staple jumper removal by mid-Novembe r, 198 6. The existing test module was modified to permit testing without removing staple jumpers. Additionally, procedure IC-GP.ZZ-0310, General Proceduro - Bailey Logic Module t Type 862, was revised Novamber 14, 1986 to allow functional test of SSLM's without manipulation of tP9 staple jumpers.

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VERIFICATION OF SAFETY RELATED FUNCTIONS l

P3E&G lette r NLR-N86142, dated October 3, 1986, committed to retest and verify all safety-related functions of a Bailey SSLM by procedure whenever a logic change is made to a module. Hope Creek Station Administrative Procedure, SA-AP.22-050, Station ,

Retest Program, and I&C Procedure IC-GP.22-031(0), General Procedure - Bailey Logic Module, Type 862, requires the retest of safety features in a logic module.

Additionally, the same letter required QA verification of all re-programmed SSLM's during the FPLA re-verification program.

Hope Creek OA participated in the FPLA re-verification program until its conclusion. 0A verified re-programmed SSLM's as -

witnessed by their signature on the OA maintenance semi-annual assessment, H0A87-0163 dated March 9, 1987 and numerous Station OA Surveillance Reports performed during September and October, ,

1986.

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ATTACHMENT 7 IN-SITU TESTING FEASIBILITY STUDY Attached is report MPR-1056, "liope Creek Nuclear Generating Station Peasiblity Study for In-Situ Testing of Bailey 862 Solid State Logic System for Class lE Equipment", prepared by MPR Associates, Inc.

This report presents the results of a feasibility study of in-situ testing of Bailey logic modules at ilope Creek. The report concludes that reliable in-situ testing is obtainable.

This report satisfies PSE&G's commitment to investigate in-situ testing as documented in PSE&G letters NLR-N86148, dated October 15, 1986 and NLR-N86186, dated December 9, 1986.

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j ATTACHMENT 8 i 2 ACCELERATED AGING AND CYCLING r

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Attached is report 48815 "Reliability Test Program" prepared by i WYLE Laboratories.

, This report provides the results of a test program performed to  !

document the reliability of Bailey Logic modules after a simulated long term plant usage. The testing simulated plant lifetime of 2, 5, and 10 years and includes cycling and environ-  ;

mental conditions. l This report satisfies PSE&G's commitment to demonstrate the long term reliability of Bailey modules as documented in PSE&G letters NLR-N86148, dated October 15, 1986, and NLR-N86076, dated June 24, 1986,  ;

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