Information Notice 1996-02, Inoperability of Power-Operated Relief Valves Masked by Downstream Indications During Testing

Inoperability of Power-Operated Relief Valves Masked by Downstream Indications During Testing

ML031060329
Person / Time
Site:	Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant
Issue date:	01/05/1996
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:
References
IN-96-002, NUDOCS 9512290129
Download: ML031060329 (13)

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555-0001 January 5, 1996 NRC INFORMATION NOTICE 96-02: INOPERABILITY OF POWER-OPERATED RELIEF VALVES

MASKED BY DOWNSTREAM INDICATIONS DURING TESTING

Addressees

All holders of operating licenses or construction permits for pressurized

water reactors.

Purpose

The United States Nuclear Regulatory Commission (NRC) is issuing this

information notice to alert addressees to a recent incident involving improper

installation of power-operated relief valve (PORV) internals which rendered

the PORVs inoperable, and inaccurate indications of the actuation of PORVs

based upon tailpipe acoustic monitoring data during testing. The erroneous

data led a licensee to conclude that two inoperable PORYs were functioning

properly. It is expected that recipients will review the information for

applicability to their facilities and consider actions, as appropriate, to

avoid similar problems. However, suggestions contained in this notice do not

constitute NRC requirements; therefore, no specific action or written response

is required.

Description of Circumstances

On August 9, 1995, surveillance testing at Saint Lucie Plant, Unit 1, conducted in accordance with Section XI of the American Society of Mechanical

Engineers Boiler and Pressure Vessel Code, indicated that the PORVs were not

operating properly. The licensee cooled and depressurized the unit and

removed and inspected the PORVs. Inspection of the internals of the valves

revealed that a part required for proper operation of each of the two PORVs

was installed backwards, thus rendering each valve inoperable. The valves had

been in service since being rebuilt during a refueling outage approximately

10 months earlier.

In reviewing the methodology and acceptance criteria for PORV surveillances, the licensee found that the valve stroke time had been based upon the time

lapse between the changing of a switch position and the receipt at the control

room panel of acoustic indication from the detectors on the tailpipes of the

subject valves. After this event, the licensee determined that flow through

internal clearances within an inoperable valve could provide low-level

acoustic responses in the tailpipes.

9512290129 o D E 4°ce. ,-O2 9 0oS

'1'

IN 96-02 January 5, 1996 Thus, without verifying that parameters were changing at the terminating point

of the tailpipe (in the case of Saint Lucie, a quench tank), valve operation

could not be determined based upon acoustic data alone.

Failure Mechanism

The PORVs used at Saint Lucie Unit 1 are Dresser Industries Model 31533VX-30

pilot-operated valves. The principles of valve operation are as follows:

• When PORV actuation is required, a signal is sent to an actuating

solenoid within the pilot assembly, which strokes the pilot valve lever

to open the pilot valve. A vent path is thus established from the main

valve, through the bleed-off port and the pilot valve, to a low-pressure

area.

• A differential pressure is established across the main disc when the

valve pilot valve opens, thus venting a space inside the main disc (see

Attachment 1) to a low-pressure area (in the case of Saint Lucie, the

tailpipe) via the main valve bleed-off port. The differential pressure

exists because the area above the main disc is pressurized to reactor

coolant system pressure through internal passages in the main valve (not

shown in Attachment 1).

• The main disc (responsible for actual reactor coolant system pressure

relief) is opened by the force of water or steam acting on the main valve

disc/seat interface. The main disc moves within a guide cylinder, and

its movement is governed by the differential pressure established across

the disc and spring force, which tends to move the disc into a closed

position.

• When pressure relief is no longer required, the actuating solenoid closes

the pilot valve and the space inside the main disc is pressurized by

system pressure thiv.uugn Lhe equalizing port. Differential pressure

across the main disc is thus reduced, and the main disc is returned to

the closed position under force of spring pressure.

In the case of the subject PORV inoperability, the licensee found that the

main disc guide, a metal cylinder within which the main disc moves, was

incorrectly oriented in the valve. One end of the guide contains a number of

holes, which provide a vent path for the pilot valve of the PORV from the

inner surfaces of the main disc. With the main disc guide incorrectly

oriented upside down, the venting of the space within the main disc was

severely restricted. This restriction resulted in insufficient venting of the

space and a subsequent failure to create the differential pressure across the

main disc necessary for the main disc to move and open the valve.

Although venting through the pilot valve was insufficient to result in a

change of state in the main valve, subsequent testing revealed that internal

clearances in the main valve are sufficient to pass water or steam through the

pilot valve despite a failure of the main valve to lift. The tests the

b

2 IN 96-02 January 5, 1996 licensee conducted in conjunction with Wyle Laboratories indicated that

significant pressures can be developed at the discharge of the pilot valve

(because of internal bypass flow paths) without movement of the main valve.

Pilot valve discharge pressures ranging from 10.5 to 12.5 megapascals [1,500

to 1,800 pounds per square inch gage] were recorded when 16.7 megapascals

[2,400 pounds per square inch gage] steam was applied to an incorrectly

assembled PORV of the same manufacture as those on Saint Lucie Unit 1.

Surveillance Testing

The licensee had performed surveillance testing twice on the subject valves

before they were identified as inoperable, once in November 1994 (after

installation in the system) and once in February 1995. The November 1994 test

was performed at 1.69 megapascals [245 pounds per square inch absolute]

reactor coolant system pressure and the February 1995 test was conducted at

12.1 megapascals [1,750 pounds per square inch absolute]. In both cases, stroke times, as measured using tailpipe acoustic data, were found to be

satisfactory. At the time, reactor coolant system and surge tank parameters

were not used to verify that the main valves of the PORVs had changed state.

On August 9, 1995, surveillance testing results were unsatisfactory because

threshold acoustic levels for control room indication were not achieved.

Subsequent testing indicated that, although acoustic data were received, changes in reactor coolant system pressure and in quench tank parameters had

not taken place. These anomalous indications led the licensee to perform the

valve inspections previously described which, in turn, led to the subject

findings.

The acoustic monitors employed in the PORV tailpipes register 10 discrete

steps of 200 millivolts each. The surveillance test methodology involved

timing of the interval by the operator from the moment a control switch was

cycled until an acoustic monitor annunciator, used to indicate when the

monitor exceeded the 400 millivolts output threshold, alarmed at the control

panel. The acoustic level received in the erroncoubly accepted tests is not

known; however, in the in-situ tests of the repaired valves on August 16,

1995, at approximately 1.72 megapascals [250 pounds per square inch absolute]

reactor coolant system pressure, the valves reached the maximum design output

of the monitors on opening. In addition, the licensee noted that the reactor

coolant system pressure dropped by approximately 0.04 megapascals [6 pounds

per square inch absolute] and the quench tank parameters indicated that energy

had been introduced into the quench tank when the valves opened.

Discussion

The licensee determined that the test methodology used to verify PORV main

valve actuation was inadequate. The licensee changed its maintenance

procedure for the PORVs to verify that the main valve disc actuates when test

pressure is applied at the valve lift setpoint. This verification will be

performed during bench testing prior to installation of the valve. This

functional testing will confirm that the PORVs have been assembled correctly.

The licensee also changed the procedure for conducting inservice testing on

the PORVs to provide more positive indication of PORV main valve actuation

'--- ~IN 96-02 January 5, 1996 main

by using quench tank and pressurizer parameters for confirmation of PORV

valve actuation during testing.

Acoustic monitors were added to the discharge piping of safety and relief of TMI

valves in response to Action Item II.D.3 of NUREG-0737, "Clarification have

Action Plan Requirements." Some licensees of pressurized water reactors

stroke times of the

attempted to use similar acoustic monitors for measuring to

atmospheric dump valves. However, the measurements have generally proven

be ineffective for determining if the valves have fully opened. Accordingly, have

alternative means of monitoring the power-operated function of the valves for

been employed. Other types of acoustic monitoring equipment are used

verify

testing the stroking of other types of valves, such as check valves, to

movement.

If

This information notice requires no specific action or written response.contact

you have any questions about the information in this notice, please

of

one of the technical contacts listed below or the appropriate Office

Nuclear Reactor Regulation (NRR) project manager.

f/ Dennis M. Crutchfield, Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: Mark S. Miller, RII

(407) 464-7822 Internet:msm@nrc.gov

Eric J. Benner, NRR

(301) 415-1171 Internet:ejblnrc.gov

Attachments:

1. Partial Section View of Power-Operated

Relief Valve

2. List of Recently Issued NRC Information Notices

ak4_

Attachment 1 I V W IN 96-02 January 5, 1996 Partial Section View of Power-Operated Relief Valve

Outlet Main Valve

Main Disc

Main Disc Seat

Main Disc

Guide

Bleed-Off Port

(To Pilot Assembly)

Spring _

_. _ A__

Main Disc Guide Ir~ZZZA^- 1_ 51eed-Ofr~onl

(Proper Orientation) (To Pilot Assembl ly)

Detail of Main Disc & Main Disc Guide Assembly

K-> Attachment 2 IN 96-02 January 5, 1996 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

96-01 Potential for High Post- 01/03/96 All holders of OLs for CPs

Accident Closed-Cycle for PWRs

Cooling Water Temperatures

to Disable Equipment

Important to Safety

95-58 10 CFR 34.20; Final 12/18/95 Industrial Radiography

Effective Date Licensees

95-57 Risk Impact Study Regarding 12/18/95 All holders of OLs or CPs

Maintenance During Low-Power for nuclear power reactors.

Operation and Shutdown

95-56 Shielding Deficiency in 12/11/95 All holders of OLs or CPs

Spent Fuel Transfer Canal for nuclear power reactors.

at a Boiling-Water Reactor

95-55 Handling Uncontained 12/06/95 All Uranium Recovery

Yellowcake Outside of a Licensees.

Facility Processing

Circuit

95-54 Decay Heat Management 12/01/95 All holders of OLs or CPs

Practices dt.,.,i* for nuclear power reactors.

Refueling Outages

95-53 Failures of Main Steam 12/01/95 All holders of OLs or CPs

Isolation Valves as a for nuclear power reactors.

Result of Sticking

Solenoid Pilot Valves

OL - Operating License

CP - Construction Permit

IN 96-02 January 5, 1996 by using quench tank and pressurizer parameters for confirmation of PORV main

valve actuation during testing.

Acoustic monitors were added to the discharge piping of safety and relief

valves in response to Action Item II.D.3 of NUREG-0737, "Clarification of TMI

Action Plan Requirements." Some licensees of pressurized water reactors have

attempted to use similar acoustic monitors for measuring stroke times of the

atmospheric dump valves. However, the measurements have generally proven to

be ineffective for determining if the valves have fully opened. Accordingly, alternative means of monitoring the power-operated function of the valves have

been employed. Other types of acoustic monitoring equipment are used for

testing the stroking of other types of valves, such as check valves, to verify

movement.

This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

original signed by B.K. Grimes

ennis M. Crutchfield, Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: Mark S. Miller, RII

(407) 464-7822 Internet:msm@nrc.gov

Eric J. Benner, NRR

(301) 415-1171 Internet:eJbl@nrc.gov

Attachments:

1. Partial Section View of Power-Operated

Relief Valve

2. List of Recently Issued NRC Information Notices

Tech Editor reviewed and concurred on 9/8/95 DOCUMENT NAME: 96-02.IN *See previous concurrence

To receive a copy of this document, Indicate Inthe box: 'C"

• Copy wit end s 'E Copy with enclosures 'N' - No copy

OFFICE PECB/DRPM PECB:DRPM / I I I

NAME EBenner* AChaffee* utc ield I

DATE 09/17/95 12/08l95 OF ICI RECORD COPY

- E X

IN 95-XX

'KI December xx, 1995 by using quench tank and pressurizer parameters for confirmation of PORV main

valve actuation during testing.

Acoustic monitors were added to the discharge piping of safety and relief

valves in response to Action Item II.D.3 of NUREG-0737, "Clarification of THI

Action Plan Requirements.w Some licensees of pressurized water reactors have

attempted to use similar acoustic monitors for measuring stroke times of the

atmospheric dump valves. However, the measurements have generally proven to

be ineffective for determining If the valves have fully opened. Accordingly, alternative means of monitoring the power-operated function of the valves have

been employed. Other types of acoustic monitoring equipment are used for

testing the stroking of other types of valves, such as check valves, to verify

movement.

This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

Dennis M. Crutchfield, Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: Mark S. Miller, RII

(407) 464-7822 E-mail: MSM@NRC.G0V

Eric J. Benner, NRR

(301) 415-1171 E-mail: EJBIQNRC.GOV

Attachments:

1. Partial Section View of Power-Operated

Relief Valve

2. List of Recently Issued NRC

Information Notices

Tech Editor reviewed and concurred on 9/8/95 DOCUMENT NAME: G:\IN\ST LUCIE.IN *See previous concurrence

To meccive a copy fthis document, huicateln lb. box 'C' - Copy witout attachmentlenclosuro 'E - Copy with attochmentlenclosur 'N' a No copy

I

OFFICE C/EMEB:DE E C/HICB:DRCH E C/SRXB:DSSA I E C/PECB:DRPM I E D/DRPM

NAME RWessman JWermiel* RJones* AChaffee* DCrutclhi el

DATE 09/22/95* 09/27/95 09/28/95 12/08/95 12/ i

---

eOFFICIAL RECORD COPY

/ -

IN 1__

December xx, 1995 operated relief valves to provides more positive indication of power-operated

relief valve main valve actuation by using quench tank and pressurizer

parameters for confirmation of power-operated relief Valve main valve

actuation during testing.

Acoustic monitors were added to the discharge piping of safety and relief

valves in response to Action Item II.D.3 of NUREG-0737, 'Clarification of TMI

Action Plan Requirements." Some licensees of pressurized water reactors have

attempted to use these acoustic monitors for measuring stroke times of the

atmospheric dump valves. However, the measurements have generally proven to

be ineffective for determining if the valves have fully opened. Accordingly, alternative means of monitoring the power-operated function of the valves have

been employed. Other types of acoustic monitoring equipment are used for

testing the stroking of other types of valves, such as check valves, to verify

movement.

This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation project manager.

Dennis M. Crutchfield, Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: Mark S. Miller, Region II

(407) 464-7822 Eric J. Benner, NRR

(301) 415-1171 Attachments:

1. Partial Section View of Power-Operated

Relief Valve

2. List of Recently Issued NRC

Information Notices

w- 4tV

DOCUMENT NAME: G:\IN\ST OlCIE.IN *See previous concurrence

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NAME EBenner* Tech Editor* EGoodwin* GHammer* RWessman*

DATE 09/17/95 09/08/95 9/18/95/11/29/95 09/09/95 09/22/95 OFFICE [HICB:DRCH lE C/HICB:DRCH UE SRXB:DSSA IE C/SRXB:DSSA I E PE:DRPg, NAME BMarcus* JWermiel* IHAbelson* RJones* RKi &~!

DATE 09/27/95 09/27/95 09/28/95 09/28/95 p1 /95 OFFICE C/PECBAQRPM I ID/DRPM II I I

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DATE k /95 A8% 109/ /95 AVTI

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K Notice 95-XX

December xx, 1995 operated relief valves to provides more positive indication of power-operated

relief valve main valve actuation by using quench tank and pressurizer

parameters for confirmation of power-operated relief valve main valve

actuation during testing.

Acoustic monitors were added to the discharge piping of safety and relief

valves in response to Action Item II.D.3 of NUREG-0737, "Clarification of TMI

Action Plan Requirements." Some licensees of pressurized water reactors have

attempted to use these acoustic monitors for measuring stroke times of the

atmospheric dump valves. However, the measurements have generally proven to

be Ineffective for determining if the valves have fully opened. Accordingly, alternative means of monitoring the power-operated function of the valves have

been employed. Other types of acoustic monitoring equipment are used for

testing the stroking of other types of valves, such as check valves, to verify

movement.

This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation project manager.

Dennis M. Crutchfield, Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: Mark S. Miller, Region II

(407) 464-7822 Eric J. Benner, Office of Nuclear Reactor Regulation

(301) 415-1171 Attachments:

1. Partial Section View of Power-Operated Relief Valve

2. List of Recently Issued United States Nuclear Regulatory Commission

Information Notices

DOCUMENT NAME: G:\IN\ST LUCIE.IN *See previous concurrence

To receive a copy of this document. ndlcatiln the box: 'C- = Copy without attachmentlenclosure 'E - Copy with attschmentlenclosure AN" a No copy

OFFICE PECB:DRPM ADM:PUBjE IN SC/PECB:DRPM I E E C/EMEB:DE E

NAME EBenner* Tech Editor* EGoodwin* GHammer* RWessman*

DATE 09/17/95 09/08/95 09/18/95 -09/09/95 09/22/95 OFFICE HICB:DRCH E tC/HICB:DRCH IE SRXB:DSSA EI C/SRXB:DSSA E [!>zDRPM Ii

NAME BMarcus* JWermiel* HAbelson* fRJones* RKJAa

DATE 09/27/95 0 1 295109/28/95 109/28/95 05/ /95- lOFFICE C/PECB:DRPM D/DRPM

NAME AChaffee DCrutchfield

DATE 09/ /95 09/ /95 _

OFFICIAL RECORD COPY

I '1__ IN 95-XX

November xx, 1995 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation project manager.

Dennis M. Crutchfield, Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: Mark S. Miller, RII

(407) 464-7822 Eric J. Benner, NRR

(301) 415-1171 Attachment: List of Recently Issued NRC Information Notices

DOCUMENT NAME: G:\IN\ST LUCIE.IN *See previous concurrence

To acalwo a Cnyr ofthis document. ndc n the box: 'C'

• Cpy without attachment/enclosure 'E' Copy with attachmentlenclosuro 'N' - No copy

[OFFICE PECB:DRPM E AM:PUB IN SC /PECB:DRPM I E EMEB:DE E EC/EMEB:DE E

NAME EBenner* ITech Editor* EGoodwin* GHammer* RWessman*

DATE 09/17/95 109/08/95 09/18/95 09/09/95 09/22/95 OFFICE [HICB:DRCH E C/HICB:DRCH _EJSRXB:DSSA E C/SRXB:DSSA E PEC RPM ]

NAME BMarcus* JWermiel* IHAbelson* RJones* RKieu I

DATE 09/27/95 09/27/95 109/28/95 09/28/95 09/ ' /95' "K

OFFICE C/PECB:DRPM D/DRPM

NAME AChaffee DCrutchfield l

DATE 09/ /95 09/ /95 OFFICIAL RECORD COPY

ig

I IN95-XX

Y..- f >--J September xx, 1995 This information notice requires no specific action or written response. If

you have any questions about the Information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation project manager.

Dennis M. Crutchfield, Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: Mark S. Miller, RII

(407) 464-7822 Eric J. Benner, NRR

(301) 415-1171 Attachment: List of Recently Issued NRC Information Notices

DOCUMENTa__.1 NAME: An.lG:\IN\ST LUCIE.IN previous concurrence

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NAME EBenner* Tech Editor* EGoodwin* IGHammer* RWessman*

DATE 09/17/95 09/08/95 09/18/95 109/09/95 09/22/95 OFFICE JB C C/HI H H S

SRXB: I [A C/SRXB:D A [PECB: DRPM

NAME J

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DATE 09lk3i/95 09/Z/99-r/ .95 109/Z.U95 109/ /95 OFFICE C/PECB:DRPM L D/DRPM 1 NAME AChaffee DCrutchfield

DATE 09/ /95 09/ /95 OFFICIAL RECORD COPY

- IN 95-XX

"~'~' September xx, 1995 Surveillance Testing

The licensee had performed surveillance testing twice on the subject valves

before they were identified as inoperable: once in November 1994 (after post- outage installation in the system) and once in February 1995. The

November 1994 test was performed at 245-psia RCS pressure and the

February 1995 test was conducted at 1,750 psia. In both cases, stroke times, as evidenced by tailpipe acoustic data, were found to be satisfactory. At the

time, RCS and surge tank parameters were not used to verify that the main

valves of the PORVs had changed state. On August 9, 1995, surveillance

testing results were unsatisfactory because threshold acoustic levels for

control room indication were not achieved. Subsequent testing indicated that, although acoustic data were received, changes in RCS pressure and in quench

tank parameters had not taken place. These anomalous indications led the

licensee to perform the valve inspections previously described which, in turn, led to the subject findings.

The acoustic monitors employed in the PORV tailpipes were TEC Model 914, and

they registered a O-to-2V output in 10 discrete steps of 200mV each. The

surveillance test methodology involved timing of the interval by the operator

from the moment a control switch was cycled until an acoustic monitor

annunciator, used to indicate when the monitor exceeded the 400mV output

threshold, alarmed at the control panel. As a result, the acoustic level

received in the erroneously accepted tests is not known; however, in the in

situ tests of the repaired valves on August 16, 1995, at approximately

250-psia RCS pressure, the valves reached the design output of the monitors.

Additionally, the licensee noted that the RCS pressure dropped by

approximately 6 psia and the quench tank parameters indicated that energy had

been introduced into the quench tank.

This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation project manager.

Dennis M. Crutchfield, Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts: Mark S. Miller, RII

(407) 464-7822 Eric J. Benner, NRR

(301) 415-1171 o fZ £ PjIV

Attachment: List of Recently Issued NRC Information Notices

DOCUMENT NAME: G:\IN\ST LUCIE.IN *See previous concurrence

To receive a copy of this document, IndIcate1n the box: TC - Copy without attachment/enclosure 'E' - Copy with attachrnent/enclosure

74 AN - No copy

OFFICE PECB:DRPM l ADM:PUB N IS/PECB:DRPM EMEB:DE I F C/EMEB:Dt- £

NAME _~~~ EBenner S F._ Tech Editor* =EGoodwin GHammer CaPO

Ad Res-",k)

DATE 09/7 0/95r 09/08/95 09//S? /95 J 09/ i /95 c>eM1."a'

OFFICE HICB:DRCH C/HICB:DRCH SRXB:DSSA C/SRXB:DSSA PECB:DRPM

NAME BMarcus JWermiel HAbelson RJones RKiessel

DATE 109/ /95 09/ /95 0 09/ /95 09/ /95 OFFICE JC/PECB:DRPM l D/DRPM I

NAME AChaffee AIt. DCrutchfield

DATE 09/ /95 09/ /95 DA--TE_ Ie19 UFICIAL RECURD CUPY

- - - --