Information Notice 1993-84, Determination of Westinghouse Reactor Coolant Pump Seal Failure

Determination of Westinghouse Reactor Coolant Pump Seal Failure

ML031070307
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:	10/20/1993
From:	Grimes B Office of Nuclear Reactor Regulation
To:
References
IN-93-084, NUDOCS 9310140192
Download: ML031070307 (16)

UNITED STATES

NUCLEAR'REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555 October 20, 1993 NRC INFORMATION NOTICE 93-84: DETERMINATION OF WESTINGHOUSE REACTOR COOLANT

PUMP SEAL FAILURE

Addressees

All holders of operating licenses or construction permits for pressurized

water reactors (PWRs).

PurDose

The U.S. Nuclear Regulatory Commission (NRC) is'issuing this information the

notice to alert addressees to a potential problem that could result from

use of Westinghouse-designed reactor coolant pump (RCP) shutdown procedures

for pumps whose No. 1 seals have failed. 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 no

contained in this information notice are not NRC requirements; therefore, specific action or written response is required.

Background

Westinghouse supplied the Braidwood Station RCPs, incorporating a three-stage 1 seal series arrangement to limit coolant flow up the pump shaft. The No.

riding face

seal, the main seal of the pump, is a controlled-leakage, film

seal. The No. 2 and No. 3 seals are rubbing face seals. During normal

operation, an injection flow of nominally 30.3 liters [8 gallons] per minute

enters the pump below the No. 1 seal (see Attachment 1). Here the flow

splits. A portion (approximately 18.9 liters [5 gallons] per minute) flows

down through the thermal barrier heat exchanger and enters the reactor coolant

the

system. In this manner, the primary coolant is prevented from entering liters

radial bearing and seal section of the pump unit. The remainder (11.4

[3 gallons] per minute) (controlled leakage) passes through the pump radial

bearing and enters the No. 1 seal. Above the No. 1 seal, most of the flow

leaves the pump through the No. 1 seal leakoff line and returns to the 2 seal

chemical and volume control system. Minor flow passes through the No.

and its leakoff line to the reactor coolant drain tank. A back flush into

injection of 0.8 liters [0.21 gallons] per hour from a head tank flows of the

the No. 3 seal between its "double dam" seal area. At this point, half line

flow passes through one side of the seal and out the No. 2 seal leakoff

while the remaining flow passes through the other side and out the No. 3 seal

leakoff line. This arrangement ensures essentially zero leakage of reactor

coolant from the pump.

9310140192 o W q 3.O3

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IN 93-84 Octoer 20, 1993 During normal operation, the No. 1 seal is subject to full reactor coolant

system pressure. When the injection flow passes through the No. 1 seal, it

produces a pressure drop of approximately 15.41 MPa [2235 psi]. The No. 2 seal has the capability to withstand full operating pressure, and its major

function is to act as a backup in case the No. 1 seal fails. If the No. 1 seal fails, leakage through the No. 2 seal increases. The No. 2 seal high

leak flow alarm actuates at 3.8 liters [1 gallon] per minute.

Description of Circumstances

In the middle of 1992, while developing shutdown procedures for the RCPs at

the Braidwood Station, Commonwealth Edison Company (the licensee) found that

its abnormal operating procedure contained inadequate instructions for

responding to a failure of the RCP No. 1 seal. On a high RCP No. 1 seal

leakoff condition, the abnormal operating procedure directed the operating

personnel to check the condition of the No. 2 seal. If the No. 2 seal was

acting as the primary pressure boundary on the basis of leakage of at least

3.8 liters [1 gallon] per minute from the No. 2 seal, the procedure required

that the RCP be shut down. If the condition of the No. 2 seal was normal, the

procedure required no further action and gave no further guidance.

Discussions with Westinghouse indicated that the condition of the No. 2 seal

might not be a sufficient indication of the operability of the No. 1 seal.

Discussion

The inadequacies in the operating procedure stem from the limitations of the

instrumentation used to monitor the leakage. The relevant No. 1 seal

instrumentation limits maximum readings to 22.7 liters [6 gallons] per minute.

Although the No. 2 seal high leak flow alarm was set at 3.8 liters [1 gallon]

per minute, very high No. 1 seal leak rates, more than 113.6 liters

(30 gallons] per minute, are needed for the No. 2 seal to reach this flow

rate. Thus, the No. 1 seal could have substantial leakage (e.g., 22.7-113.6 liters (6-30 gallons] per minute) even though the No. 2 seal high leak flow

alarm was not actuated. In the mean time, the RCP seal system might be

severely damaged if loss of injection were to occur or the No. 1 seal leak

rates were more than 30.3 liters [8 gallons] per minute. Therefore, monitoring for high No. 2 seal leakage is not a reliable method of determining

whether the No. 1 seal has failed.

After finding that the condition of the No. 2 seal might not indicate the

operability of the No. 1 seal, Westinghouse provided guidance for the

Braidwood Station that significantly enhances operator ability to determine if

immediate shutdown of an RCP is required or if a more orderly shutdown can be

conducted. Westinghouse completed a safety evaluation and issued Technical

Bulletin, NSD-TB-93-01-RO, "Revised Procedures for RCP Shutdown with No. 1 Seal Leakage Outside Operating Limits," dated March 30, 1993, to other PWRs

that might be affected. An excerpt from this document is attached to this

information notice (see Attachment 2).

IN 93-84 October 14, 1993 response. If

This information notice requires no specific action or writtenplease contact

you have any questions about the information in this notice, Office of

one of the technical contacts listed below or the appropriate

Nuclear Reactor Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts: Steve DuPont, RIII

(815) 458-2852 Martin Farber, RIII

(708) 790-5774 Chu-Yu Liang, NRR

(301) 504-2878 Attachments:

1. Simplified Braidwood Seal Water Injection

and Leakoff Flow Diagram

2. Excerpt from Westinghouse Technical

Bulletin, NSD-TB-93-01-RO, "Revised

Procedures for RCP Shutdown with No. 1 Seal Leakage Outside Operating Limits"

3. List of Recently Issued NRC Information Notices

2=. "I'I' TO SEAL WATER HAT EXCHANGER

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LEAKOFF FLOW DIAGRAM

SIMPLIFIED BRAIDWOOD SEAL WATER INJECTION AND

I>

Attachment 2 IN 93-84 October 20 1993 Nuclear Westinghouse Page 1 of I

Services Technical Bulletin

Division

irts.ation or operation of Wastghous&suppi*d Nudr

An advisory notice of a recent technical development pertining to th- aIRonl, and initite action wh-r aomopriabt.

Plant equipment. Recipients shouSd evaluate the Information and recomnM

P.O. SOX 35, Pltttxzu PA 15o

REVISED PROCEDURES FOR ROP SHUTDOWN WITH NO.

.o

Subject NSD-TB- 93-01-RO

'.FAl I FAKA(LF OUTSIDE OPERATING UMITS

REACTOR COOLANT SYSTEM Date 03r3/9 System(s)

PLant ALL WESTINGHOUSE REACTOR COOLANT PUMPS WITH lr SO(s) 125 CONTROLLED LEAKAGE SEALS (See Aftacivelt B)

References _- -- , .nA~. cten

C Is Safety Related Yes 0 Page 1 Of 8 h M L) rilv Vl..I Vr-ij' 1 Q %- W I E2o m e t adgq No O1

BACKGROUND

failure of the No. 1 Years of Westinghouse RCP operating experience has demonstrated that complete

in conjunction

seal is a rare occurrence. A complete failure is defined as excessive No. 1 seal leakage

or exceeding the maximum

with pump bearing/seal inlet and/or No. 1 leakoff temperatures approaching

leakoff be isolated

limits. Current operating procedures for failed No. 1 seals direct that the No. I seal

These procedures are specified in the RCP

within 5 minutes and RCP shutdown witlin 30 minutes.

instruction books or addenda to the books.

high and low leaking

After a review of current operating procedures and actual operating experiences with

emergency and orderly

No. 1 seals, it was concluded ftht distinct procedures could specify steps for both

procedures in this

RCP shutdowns. The two iems that follow have been incorporated into the revised

mrefers to a condition that is related

technical bulletin. As used within this bulletin, the term 'emergefly

as defined in

only to RCP operation and in no way pertains to emergency conditions for plant operation

a plant hnal Safety Analysis Report (FSAR).

the

I) A damaged No. 1 seal may produce debris or leak at a high enough rate to exceed

In the

injection rate and introduce unfiltered, high temperature reactor coolant into the seals.

for the

presence of debris. the ability of the No. 2 seal to survive and function as a backup

have pump

No. 1 seal is more favorable under static conditions. Thus, it is preferred to

shutdown precede No. 1 seal leakoff isolation.

0rawc Teb hoffl 412- 963-5634 or (W) 29-5634 AJol" W omutfi. Flequd. may be Obhuned fron @fe

Appmvi.

T. W. Dunn, Manager, Fied Service & RCP Engineerng L J.Haper

Ener Systes Saes Suport

'q7--t-. N

R. F pleiter. mwnA~e CR 4-&Seal Engineain

corame inW"t "Pon or - wy reqpo-"kdy 1b "ik&ym

an dafiQ$ ~iC flf umastamtom am of mooh irdofflol.

at tr* gwonmul)Of

Attachment 2 IN 93-84 October 20, 1993 NSD-TB-93-01-RO 2) High No. 1 seal leakage (> 6.0 9pm) or low No. 1 seal leakage (< 0.8 gpen) can occur

while no other RCP parameter limits are approached or violated. In these cases. pump

shutdowns within several hours are within the capabilities of the RCPs and are more

conducive to orderly plant shutdowns.

The following new procedures are provided to address each of four conditions that

irncate No. 1 seal flow outside of the operating limits (0.8-6.0 gpm). The first three conditiors address

high

No. I seal leakage and the fourth condition addresses low leakage. Each condition

with its

respective procedure is specified below and is summarized in Attachment A.

PROCEDURES

The following procedures supersede those in the RCP instruction books or addenda

to the books

relative to:

1) RCP emergency operation and shutdown procedures for high or low No. 1 seal

leakage. Apply the Conditions 1 through 4 procedures that follow.

2) RCP emergency operation and shutdown procedure for No. 2 and No. 3 seals. Apply

the procedure for shutdown specified under Condition 1 below. The No. 2 and No. 3 seal parameters tat indicate emergency operation remain the same as specified in

the RCP instruction books.

Definitions:

No. 1 seal leakoff indication: Flowmeter readout of No. 1 seal leak rate

No. 2 seal leakoff indication: Flowmeter readout or estimate of No. 2 seal leak rate

Total No. 1 Seal Flow: Sum of No. 1 and No. 2 seal leakoff indications

Immediate Shutdown: RCP shutdown and isolation of No. 1 seal leakoff within

5 minutes

Orderly Shutdown: RCP shutdown within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of higtow No. 1 seal leakoff

flow indication

NOTE; A manual plant trip must precede an "Emergency or 'Ordery RCP shutdown. This will

prevent an automatic plant tip on a low flows signal which represents an unnecessary

challenge to installed safety systems.

Attachment 2 IN 93-84 October 20, 1993 NSD-TB-93-011-RO to address a specfic RCP seal

If no alternative Westinghouse direction has been provided

the recommended shutdown procedures for

performance condition at a plant, the following are

gpm).

No. 1 seal leak rates outside the operating limits (08-6.0

Condition 1: a) No. 1 sea leakoff indication > 6.0 gpcn.

b) Increasing pump beanngfseal inlet temnperature.

and/or

increasing No. I seal leakoff temperature.

Procedure: 1) Shut down the RCP immediately.

complete stop.

2) Isolate the No. 1 seal leakoff after the RCP has come to a

flow and

3) Monitor component cooling water (CCW) to ensure adequate

in the

manually override automatic isotation as required. (Local boiling

the CCW

thermal barrier of the affected pump may cause isolation of

system.)

has been

4) Do not restart the pump until the cause of the seal malfunction

determined and corrected.

Condition 2; a) No. I seal leakoff indication > 6.0 gpm.

andfor

Total No. 1 seal flow > 6.0 gpm and < 8.0 gpm.

b) Ppump bearing/seal inlet temperature is not increasing.

c) No. 1 seal leakoff temPerature (if equipped) is not increasing.

of

Procedure: 1) Prepare for an orderly pump shutdown to take effect within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />

flow rate is

exceeding 6.0 gpm No. I seal flow. Ensure that seal injection

9 gpm or greater to the affected RCR

Attachment 2 IN 93-84 October 20, 1993 NSD-TB-93-o -RO 2) Continue to monitor the No. 1 seal for further degradation durng the

orderly

shutdown. If the total No. 1 seal flow exceeds 8.0 gpm or temperatures

begn to increase, proceed with immediate shutdown in accordance

with

the Condition 3 procedure. Otherwise, proceed with the orderly shutdown.

3) Secure the pump within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of exceeding a No. 1seal eamkof

indication

or total No. 1 seal flow of 6.0 gpn.

4) Moritor component cooing waler (CCOW to ensure adequate flow

and

manually override as required. (Local boiling in the thermal banier

of the

affected pump may cause isolaton of the CCW system.)

5) No. I seal leakoff may be isolated at the discretion of operations to mitigate

inventory loss and to assure that seal injection flow exceeds total

No. 1 seal

flow on the affected pump.

6) Do not restart the pump until the cause of the seal malfunction has

been

determined and corrected.

Condition 3: a) Total No. 1 seal flow x 8.0 gpm.

Procedure: 1) Shut down the RCP immediately.

2) Isolate the No. 1 seal leakoff after the RCP has come to a complete

stop.

3) Monitor component cooling water (CCW) to ensure adequate flow and

rnanaly override automatic Isolation as required. (Local boiling in

the

thermal banier of the affected pump may cause isolation of the CCW

system.)

4) . Do not restart the pump until the cause of the seal malfunction has

been

determined and corected.

Condition 4: a) No. I seal leakoff indication c 0.8 gpm.

b) Zero (or negligible) No. 2 seal leak rate such that total No. 1 seal

flow < 0.8 gprn.

c) Pump bearingfseal inlet temperature and No. 1 seal leakoff temperature

(if equipped) are stable (i.e.. not coninuously increasing) and

within limits.

Attachient 2 IN 93-84 October 20, 1993 NSD-TB-93"01-RO Procedure: 1) Prepare for an orderly pump shutdown to take effect within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of

violating the rninimum 0.8 No. 1 seal leak rate Knit

2) Continue to monitor the No. 1 seal for further degradation duing the

orderly shutdown. If the bw No. 1sa lealkge reverses to high leakage

(> 6.0 gpim) or temperatures start to increase, proceed with immeciate

shutdown in accordance with the Condcion 1 procedure. Otherwise, proceed with the orderly shutdown.

3) Secure the pump within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of violasts the rnirnmum 0.8 No. 1seal leak

rate limit.

4) Do not restart the pump until the cause of the seal malfunction has been

determined and corrected.

ATTACHMENT A

No. 1 Leakotf No. 2 Leakoft Total Pump Bearing/Seal

Condition Indication Indication No. 1 Seal Flow Inlet and/or RCP Shutdown

No. 1 Leakoff Temp.

1 > 6.0 gpm 6.0 gpm

> Increasing Immediate

(wilhin 5 minutes)

(

2 > 6.0 gpm > 6.0 and < 8.0 gpm Stable Orderly

(within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />)

3 > 8.0 gpm Stable or Immediate

increasing (within 5 minutes)

4 < 0.8 gpm zero < 0.8 gpm Stable Orderly

(or negligible) (within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />)

Note: 0

q4

3IF

0

Total No. 1seal flow a No. 1 leakoff plus No. 2 leakoff indications 0

oz

Pz n

wo

MD0

rt

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Attachment 3 IN 93-84 October 20, 1993 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

93-83 Potential Loss of Spent 10/07/93 All holders of OLs or CPs

Fuel Pool Cooling for boiling water reactors

Following A Loss of (BWRs).

Coolant Accident (LOCA)

93-82 Recent Fuel and Core 10/12/93 All holders of OLs or CPs

Performance Problems in for nuclear power reactors

Operating Reactors and all NRC-approved fuel

suppliers.

93-81 Implementation of 10/12/93 All holders of OLs or CPs

Engineering Expertise for nuclear power reactors.

on Shift

93-80 Implementation of the 10/08/93 All byproduct, source, and

Revised 10 CFR Part 20 and special nuclear material

licensees.

93-79 Core Shroud Cracking at 09/30/93 All holders of operating

Beltline Region Welds licenses or construction

in Boiling-Water Reactors permits for boiling-water

reactors (BWRs).

93-78 Inoperable Safety Systems 10/04/93 All holders of OLs or CPs

At A Non-Power Reactor for test and research

reactors.

93-77 Human Errors that Result 10/04/93 All nuclear fuel cycle

in Inadvertent Transfers licensees.

of Special Nuclear

Material at Fuel Cycle

Facilities

93-76 Inadequate Control of 09/21/93 All holders of OLs or CPs

Paint and Cleaners for for nuclear power reactors.

Safety-Related Equipment

93-75 Spurious Tripping of 09/17/93 All holders of OLs or CPs

Low-Voltage Power Circuit for nuclear power reactors.

Breakers with GE'RMS-9 Digital Trip Units

OL = Operating License

CP = Construction Permit

IN 93-84 October 14, 1993 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.

Original signed bY

Brian K. Grimef

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts: Steve DuPont, RIII

(815) 458-2852 Martin Farber, RIII

(708) 790-5774 Chu-Yu Liang, NRR

(301) 504-2878 Attachments:

1. Simplified Braidwood Seal Water Injection

and Leakoff Flow Diagram

2. Excerpt from Westinghouse Technical

Bulletin, NSD-TB-93-01-RO, "Revised

Procedures for RCP Shutdown with No. I

Seal Leakage Outside Operating Limits"

3. List of Recently Issued NRC Information Notices

• SEE PREVIOUS CONCURRENCE

OFF *OGCB:DORS *SRXB:DSSA *SRI:DRP:RIII *TECH ED

NAME PCWen CYLiang SGDuPont MMejac

DATE 07/26/93 07/26/93 07/26/93 07/27/93

• SC/DRP:RIII *C/DRP:RIII *SC/SRXB:DSSA *C/SRXB:DSSA

MJFarber BClayton MACaruso RCJones

07/29/93 08/05-93 08/09/93

07/29/93

• D/DSSA *C/OGCB:DORS .4:;tes

ACThadani GHMarcus

09/23/93 09/28/93 10//r 93 DOCUMENT NAME: 93-84.IN

IN 93-xx

October xx, 1993 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.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts: Steve DuPont, RIII

(815) 458-2852 Martin Farber, RIII

(708) 790-5774 Chu-Yu Liang, NRR

(301) 504-2878 Attachments:

1. Simplified Braidwood Seal Water Injection and Leakoff Flow Diagram

2. Excerpt from Westinghouse Technical Bulletin, NSD-TB-93-01-RO, "Revised

Procedures for RCP Shutdown with No. 1 Seal Leakage Outside Operating

Limits"

3. List of Recently Issued NRC Information Notices

• SEE PREVIOUS CONCURRENCE

OFF *OGCB:DORS *SRXB:DSSA *SRI:DRP:RIII *TECH ED

NAME PCWen CYLiang SGDuPont MMejac

DATE 07/26/93 07/26/93 07/26/93 07/27/93

• SC/DRP:RIII *C/DRP:RIII *SC/SRXB:DSSA *C/SRXB:DSSA

MJFarber BClayton MACaruso RCJones

07/29/93 07/29/93 08/05/93 08/09/93

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IN 93-xx

September xx, 1993 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.

Brian K. Grimes, Director

Division of Operating Reactor

Support

Office of Nuclear Reactor Regulation

Technical contacts: Steve DuPont, RIII

(815) 458-2852 Martin Farber, RIII

(708) 790-5774 Chu-Yu Liang, NRR

(301) 504-2878 Attachments:

1. Simplified Braidwood Seal Water Injection and Leakoff Flow Diagram

2. Excerpt from Westinghouse Technical Bulletin, NSD-TB-93-01-RO, 'Revised

Procedures for RCP Shutdown with No. 1 Seal Leakage Outside Operating

Limits'

3. List of Recently Issued NRC Information Notices

• SEE PREVIOUS CONCURRENCE

OFF *OGCB:DORS *SRXB:DSSA *SRI:DRP:RIII *TECH ED

NAME PCWen CYLiang SGDuPont MMejac

DATE 07/26/93 07/26/93 07/26/93 07/27/93

• SC/DRP:RIII *C/DRP:RIII *SC/SRXB:DSSA *C/SRXB:DSSA

MJFarber BClayton MACaruso RCJones

AF 07/29/93 08/05/93 08/09/93

07/29/

D/DSS ai' _ C/OGCB:DORS D/DORS

ACThadani GHMarcus BKGrimes

09/2_/93 09/ /93 09/ /93 DOCUMENT NAME: WRCPSEAL.WEN

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts: Steve DuPont, RIII

(815) 458-2852 Martin Farber, RIII

(708) 790-5774 Chu-Yu Liang, NRR

(301) 504-2878 Attachments:

1. Simplified Braidwood Seal Water Injection and Leakoff Flow Diagram

2. Excerpt from Westinghouse Technical Bulletin, NSD-TB-93-01-RO, 'Revised

Procedures for RCP Shutdown with No. 1 Seal Leakage Outside Operating

Limits"

3. List of Recently Issued NRC Information Notices

• SEE PREVIOUS CONCURRENCE

OFF *OGCB:DORS *SRXB:DSSA *SRI:DRP:RIII *TECH ED SC/SRXB:DSSAL

NAME PCWen CYLiang SGDuPont MMejac MACaruso `y r

DATE 07/26/93 O7/26/93 07/26/93 07/27/93 r/4r/93 / r

STW :I I I

RD C/R J.:RIII ,JSRXB:DSSA

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ACThadani GHMarcus BKGrimes

07/ /93 07/ /93 07/ /93

\s-/

Martin Farber, RIII

(708) 790-5774 Chu-Yu Liang, NRR

(301) 504-2878 Attachments:

1. Braidwood Seal Water Injection and Leakoff Flow Diagram..r-

2. Excerpt from Westinghouse Technical Bulletin, NSD-TB-93-01-RO, "Revised

Procedures for RCP Shutdown with No. 1 Seal Leakage Outside Operating

Limits"

3. -List-ef Recently IssueFd4RC-4nf-4fmation.-Not-ies-.-

OFF OCB:DORS SRXB SA L S I RIII TECH ED SC/SRXB:DSSA

NAME PCWen CYLiang _ SGDuPont MR- MMejac*M MACaruso

DATE 07/a6/93 07/;xb/93 V~ 07/Vb/93 T1-e'A.@i 07/1.7/93 07/ /93 SC/DRP:RIII C/DRP:RIII C/SRXB:DSSA

MJFarber BClayton RCJones

07/ /93 07/ /93 07/ /93 D/DSSA C/OGCB:DORS D/DORS

ACThadani GHMarcus BKGrimes

07/ /93 07/ /93 07/ /93

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