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 K 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

notice to alert addressees

to a potential

problem that could result from the 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

contained

in this information

notice are not NRC requirements;

therefore, no specific action or written response is required.Background

Westinghouse

supplied the Braidwood

Station RCPs, incorporating

a three-stage

seal series arrangement

to limit coolant flow up the pump shaft. The No. 1 seal, the main seal of the pump, is a controlled-leakage, film riding face 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 system. In this manner, the primary coolant is prevented

from entering the radial bearing and seal section of the pump unit. The remainder

(11.4 liters[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 chemical and volume control system. Minor flow passes through the No. 2 seal and its leakoff line to the reactor coolant drain tank. A back flush injection

of 0.8 liters [0.21 gallons] per hour from a head tank flows into the No. 3 seal between its "double dam" seal area. At this point, half of the flow passes through one side of the seal and out the No. 2 seal leakoff line 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;Afe4% ;IivftC

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 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

2=."I 'I'TO SEAL WATER HAT EXCHANGER CO IrRo.D my LEVEL IN STAOPIPE TO REGENERATIWE1 HEAT EXCHANGER DR DRAIN IIMP go 0 Zrt aq ct (D j xD O m 00 MS 0 t I-'.II-h' LAl -NIN sAN ThERL ARRHER HEAT EXCHANGERF"U.t,&ID w SIMPLIFIED

BRAIDWOOD

SEAL WATER INJECTION

AND LEAKOFF FLOW DIAGRAM

I>Attachment

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

Technical

Bulletin An advisory notice of a recent technical

development

pertining

to th- irts.ation

or operation

of Wastghous&suppi*d

Nudr Plant equipment.

Recipients

shouSd evaluate the Information

and recomnM aIRonl, and initite action wh-r aomopriabt.

P.O. SOX 35, Pltttxzu PA 15o Subject REVISED PROCEDURES

FOR ROP SHUTDOWN WITH NO.'.FAl I FAKA(LF OUTSIDE OPERATING

UMITS.o NSD-TB- 93-01-RO System(s)

REACTOR COOLANT SYSTEM Date 03r3/9 PLant ALL WESTINGHOUSE

REACTOR COOLANT PUMPS WITH lr SO(s) 125 CONTROLLED

LEAKAGE SEALS (See Aftacivelt

B)References

_- -- C , .nA~. cten 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

Years of Westinghouse

RCP operating

experience

has demonstrated

that complete failure of the No. 1 seal is a rare occurrence.

A complete failure is defined as excessive

No. 1 seal leakage in conjunction

with pump bearing/seal

inlet and/or No. 1 leakoff temperatures

approaching

or exceeding

the maximum limits. Current operating

procedures

for failed No. 1 seals direct that the No. I seal leakoff be isolated within 5 minutes and RCP shutdown witlin 30 minutes. These procedures

are specified

in the RCP instruction

books or addenda to the books.After a review of current operating

procedures

and actual operating

experiences

with high and low leaking No. 1 seals, it was concluded

ftht distinct procedures

could specify steps for both emergency

and orderly RCP shutdowns.

The two iems that follow have been incorporated

into the revised procedures

in this technical

bulletin.

As used within this bulletin, the term 'emergefly

m refers to a condition

that is related only to RCP operation

and in no way pertains to emergency

conditions

for plant operation

as defined in a plant hnal Safety Analysis Report (FSAR).I) A damaged No. 1 seal may produce debris or leak at a high enough rate to exceed the injection

rate and introduce

unfiltered, high temperature

reactor coolant into the seals. In the presence of debris. the ability of the No. 2 seal to survive and function as a backup for the No. 1 seal is more favorable

under static conditions.

Thus, it is preferred

to have pump shutdown precede No. 1 seal leakoff isolation.

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

corame in W"t "Pon or -an wy reqpo-"kdy

1b "ik&ym dafiQ$ ~iC flf umastamtom

am of mooh irdofflol.

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 If no alternative

Westinghouse

direction

has been provided to address a specfic RCP seal performance

condition

at a plant, the following

are the recommended

shutdown procedures

for No. 1 seal leak rates outside the operating

limits (08-6.0 gpm).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.

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 manually override automatic

isotation

as required. (Local boiling in the thermal barrier 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 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.

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 exceeding

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

flow rate is 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. 1 seal 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. 1 sa 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. 1 seal 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: Total No. 1 seal flow a No. 1 leakoff plus No. 2 leakoff indications

(0 0 q4 0 oz 3 IF wo I'd Pz n MD 0 a% ID 0 0'-P-a (J.%D rt*r1-U) 0 i2w~,r

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 Fuel Pool Cooling Following

A Loss of Coolant Accident (LOCA)10/07/93 All holders for boiling (BWRs).of OLs or CPs water reactors 93-82 93-81 93-80 93-79 93-78 93-77 93-76 93-75 Recent Fuel and Core Performance

Problems in Operating

Reactors Implementation

of Engineering

Expertise on Shift Implementation

of the Revised 10 CFR Part 20 Core Shroud Cracking at Beltline Region Welds in Boiling-Water

Reactors Inoperable

Safety Systems At A Non-Power

Reactor Human Errors that Result in Inadvertent

Transfers of Special Nuclear Material at Fuel Cycle Facilities

Inadequate

Control of Paint and Cleaners for Safety-Related

Equipment Spurious Tripping of Low-Voltage

Power Circuit Breakers with GE'RMS-9 Digital Trip Units 10/12/93 10/12/93 10/08/93 09/30/93 10/04/93 10/04/93 09/21/93 09/17/93 All holders of OLs or CPs for nuclear power reactors and all NRC-approved

fuel suppliers.

All holders of OLs or CPs for nuclear power reactors.All byproduct, source, and and special nuclear material licensees.

All holders of operating licenses or construction

permits for boiling-water

reactors (BWRs).All holders of OLs or CPs for test and research reactors.All nuclear fuel cycle licensees.

All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.OL = Operating

License CP = Construction

Permit

IN 93-84 October 14, 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.Original signed bY Brian K. Grimef Brian K. Grimes, Director Division of Operating

Reactor Support Office of Nuclear Reactor Regulation

Technical

contacts: Steve (815)DuPont, RIII 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 NAME DATE*OGCB:DORS

PCWen 07/26/93*SRXB:DSSA

CYLiang 07/26/93*SRI:DRP:RIII

SGDuPont 07/26/93*TECH ED MMejac 07/27/93*SC/DRP:RIII

MJFarber 07/29/93*D/DSSA ACThadani 09/23/93*C/DRP:RIII

BClayton 07/29/93*C/OGCB:DORS

GHMarcus 09/28/93*SC/SRXB:DSSA

MACaruso 08/05-93.4:;tes 10// r 93*C/SRXB:DSSA

RCJones 08/09/93 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 NAME DATE*OGCB:DORS

PCWen 07/26/93*SRXB:DSSA

CYLiang 07/26/93*SRI:DRP:RIII

SGDuPont 07/26/93*TECH ED MMejac 07/27/93*SC/DRP:RIII

MJFarber 07/29/93*C/DRP:RIII

BClayton 07/29/93*SC/SRXB:DSSA

MACaruso 08/05/93*C/SRXB:DSSA

RCJones 08/09/93*D/DSSA ACThadani 09/23/93 DOCUMENT NAME: C/OGCB:DOi,_

D/DORS PcEY GHMarcu$s&

!:' BKGrimesng

P4it P (so-.-qI),MAM

WRCPSEAL.We

0fFnfS T HE 049 /9o o3eevat lro 1hE NftC 41TA03rA*

THS g*Sr*qWS C _ %,A _ } U. .O ' 0a* W S~--.W""i r. MOFbV4' ( H& S5ef ) vvia %;nfgnri&

dr i tw LWI44n44t

et-K'%$ U -te pnvi.d %e ,W Tec6-,.p^

MoTtwcdL.

?et hk~

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 NAME DATE*OGCB:DORS

PCWen 07/26/93*SRXB:DSSA

CYLiang 07/26/93*SRI:DRP:RIII

SGDuPont 07/26/93*TECH ED MMejac 07/27/93*SC/DRP:RIII

MJFarber 07/29/ AF D/DSS ai' _ACThadani 09/2_/93 DOCUMENT NAME:*C/DRP:RIII

BClayton 07/29/93 C/OGCB:DORS

GHMarcus 09/ /93 WRCPSEAL.WEN

• SC/SRXB:DSSA

MACaruso 08/05/93*C/SRXB:DSSA

RCJones 08/09/93 D/DORS BKGrimes 09/ /93 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

NAME PCWen CYLiang DATE 07/26/93 O7/26/93 STW RD I :I I C/R J.:RIII MJFarber 4 BClayton 07ial/93 J 07/< /93 we 74FCoo .7,6/93 D/DSSA C/OGCB:DORS

ACThadani

GHMarcus 07/ /93 07/ /93*SRI:DRP:RIII

SGDuPont 07/26/93 ,JSRXB:DSSA

C ones?/ /93*TECH ED MMejac 07/27/93 SC/SRXB:DSSAL

MACaruso `y r r/4r/93 / r D/DORS BKGrimes 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 NAME DATE OCB:DORS PCWen 07/a6/93 SRXB L SA S I RIII CYLiang _ SGDuPont MR-07/;xb/93 V~ 07/Vb/93 T1-e'A.@TECH ED MMejac *M i 07/1.7/93 SC/SRXB:DSSA

MACaruso 07/ /93 SC/DRP:RIII

MJFarber 07/ /93 C/DRP:RIII

BClayton 07/ /93 C/SRXB:DSSA

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

GHMarcus 07/ /93 D/DORS BKGrimes 07/ /93! .