ML20137T233

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Rev 8 to 1OM-53C.4.1.6.4(ISS3A), SG Tube Leakage
ML20137T233
Person / Time
Site: Beaver Valley
Issue date: 04/09/1997
From:
DUQUESNE LIGHT CO.
To:
References
1OM-53C.4.1.6.4, NUDOCS 9704160037
Download: ML20137T233 (15)
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Text

.-

5 BEAVER VALLEY POWER STATION l

N CONTROLLED DOCUMENT DISTRIBUTION FORM 4

TO:

NUC. REG. COMMISSION TRANSMITTAL NO.

970407101NCOMMISSION NRC OFFSITE FROM :

Beaver Valley Records Center Document Control i

i The document (s) identified below are enclosed. Please review to verify receipt, incorporate the document (s) into your controlled 1

document file, properly disposition superseded documents, and sign and return the receipt acknowledgement below within fourteen (14) calendar days to the BVRC, at mail drop BV-SEB1.

DOCUMENT SHEET REVISION INT /

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A9.350 C BV1 10M-53C.4.1.6.4(ISS3A) 000 008 1

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10M-53C.4.1.6.4(ISS3A) 000 007 4

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Receipt of the above listed document (s)is hereby acknowledged and I certify that all void or superseded copies of the above listed document (s) in my possession have been removed from use or marked void.

15016G Signature Date 9704160037 970409

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PDR ADOCK 05000334 P

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Record Type SA9.350C DUQUESNE LIGHT COMPANY j

Beaver Valley Power Station UNIT 1 a

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10M-53C.4.1.6.4(ISS3A) i Steam Generator Tube Leakage

}

issue 3A Revision 8 Prepared by Date Pagesissued Effective Date M. P. Flynn 12/18/96 1 through 13 APR 0 91997 Reviewed by Date Validated by Date C. O'Neill 12/18/96 N/A OSC Meeting No.

Date Ap rovedb Date M

j yqg_ y BV-OSC-51-96 12/18/96 O

y CONTROLLED 4

S BVPS UNDT 1

8 BVPS - AOP 10M-53C. 4.1. 6.4 (ISS3A)

Number Title 1.6.4 Steam Generator Tube Leakage Issue 3A Revision 8

' J t

A.

PURPOSE This procedure provides symptoms and actions to be taken in event of a small steam generator tube leak.

B.

SYMPTOMS OR ENTRY CONDITIONS 1.' Rising radiation levels or alarm conditions on any of the foilowing radiation monitors:

[RM-1BD-100]

Steam Generator Blowdown Tank Effluent Radiation e

Monitor

'RM-1SV-100' Condenser Air Ejector Vent e

'RM-1SS-100' Steam Generator Blowdown Sample e

'RM-1DA-100' Aux Feed Drains Tank e

lRM-1BD-101 High Capacity SG Blowdown System Monitor (at SPING e

CT-1)

[RM-1MS-102A,B,C] N-16 Steam Generator Leak Monitor e

2.

Secondary side activity detected by routine chemistry monitoring j

procedures.

C.

AUTOMATIC ACTIONS i

1.

[RM-ISV-100] Conden'ser Air Ejector Vent High-High Level causes the i

following:

e Closes [TV-ISV-100B Air Ej Disch To GW Sys TV e Opens [TV-ISV-100A)) Air Ej Disch To CNMT TV 2.

[RM-1DA-100] Aux Feed Drains Tank High Level causes the following:

. Closes [TV-IDA-105B e Open [TV-1DA-105A] ] Tunnel Sump IsolTurb Plant Oil Separator Isol A0P164 3/11/97 1 of 13

BVPS - A0P 10M-53C.4.1.6 e4'(ISS3A) '

l Number Title 1.6.4 Steam Generator Tube Leakage Issue.3A ^l Revision STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED fiOIE This procedure may be performed in conjunction with AOP 1.51.1, " Emergency Shutdown".

1.

Reauest Chemistry Suonort l

a. Calculate SG primary-to-secondary leakrate.
b. Perform isotopic analysis for i

dose equivalent I-131 for the leaking SG.

Primary "o-Secondarv Leakrate Should Be Close' v Monitored Durina The Performance Of This Procedure *

(

l

a. The leakrate can be detennined using the N-16 monitor (preferable) or Chemistry sample results.

(There is no need to wait for Chemistry to verify the N-16 monitor readings.)

b. The leakrate should be plotted and the rate of change determined,
c. lE SG primary-to-secondary leakrate exceeds 150 GPD in any one SG, IEEE shutdown to Mode 3 within 6 HOURS.

l (step continued next page)

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BVPS - A0P 10M-53C.4.1.6.4 (ISS3A) humber Title 1.6.4 Steam Generator Tube Leakage Issue 3A Revision 8 (continued fr previouspage)

d. IE SG primary-to-secondary.

j leakrate exceeds 30 GPD in any one SG, I113 perform the

[

following':

4 1

1) Have Chemistry increase i

sample monitoring to requantify SG primary-to-secondary leakrate.

4

2) Have Health Physics monitor

'3 radiation monitors and estimate SG primary-to-secondary leakrate by I

converting CPM to GPD every j

15 minutes.

'RM-ISV-100' e

RM-180-101 e

}

e. The following actions should be j

based on the highest primary-to-secondary leakrates obtained from N-16 monitor, Chemistry or Health Physics estimates:

Primary-To-Secondary Leakrate l

For Any One SG Required Actions f

SG leakrate rate of rise 160 Perform an emergency shutdown in i

GPD/HR accordance with AOP 1.51.1, " Emergency i

Shutdown" and be in Mode 3 as quickly as possible.

I SG leakrate 2 150 GPD AND rate Shutdown plant and be in Mode 3 within 6 of rise < 60 GPD/HR hours.

O AoP164 3/11/97 3 of 13

BVPS - A0P 10M-53C.4.1.6:4(ISS3A)6 Number Title l

1.6.4 Steam Generator Tube Leakage Issue 3A _

l Revision STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 3.

Disoatch An Ooerator To iRM-1MS-102A.B.Cl N-16 Steam Generator Leak Monitor (Service Bida

- 752')

a. Mark [RR-1MS-102] Recorder N-16 Monitoring Lines A, B, & C.
b. Notify the NSS/ANSS of the leak rate displayed at

[RI-1MS-102A1, B1,C1].

l

c. Request Chemistry perfom Chemistry Manual Chapter 5.12

" Enhanced Primary-To-Secondary Leakrate Monitoring Program."

d. Monitor SG leaktate as follows:
1) Request Health Physics to reset alarm setpoint 30 GPD above existing baseline

(

)

reading (pemits detection of rapidly rising leakrate).

'RM-ISV-100' e

RM-1BD-101 e

2) Use a temporary log and monitor leakrate every 10 MINUTES until alarm is cleared.

l Ii A0P164 3/11/97 4 of 13

)

i 4

BVPS - A0P 10M-53C.4.1.6.4(ISS3A)

Number Title 1.6.4 Steam Generator Tube Leakage Issue 3A Revision' 8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION 10ST-6.2 (10ST-6.2A) and Chemistry leakage estimates will not agree as l

primary-to-secondary leakage rises greater than 0.5 GPM. Chemistry leakage estimates become less accurate as leakage rises.

1 4.

Perform Either Of The Followina:

I 10ST-6.2, " Reactor Coolant e

System Water Inventory Balance" l

-OR-10ST-6.2A, " Computer Generated e

Reactor Coolant System Water i

Inventory Balance" i

()

5.

Reauest chemistry Samnle Secondary Coolant For Soecific Activity I

I 6.

Verifv Como' iance With T.S. 3.4.6.2.

Take action in accordance with "Doerat i ona' Lea caae" And 3. 7.1.4.

Technical Specifications.

" Activity" Refer to EPP for notification l

requirements.

't l

.i i

l AOPlH 3/11/97 5 of 13

-w-,n~w,n,,

=

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BVPS - A0P 10M-53C.4.1.6.4(ISS3A)*

l Number Title 1.6.4 Steam Generator Tube Leakage Issue 3A _I Revision

~

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 7.

DiSDatch ODerator With Kev 0.F To Isolate Steam Sunolv From Affected SG To

'1FW-P-21. Steam Driven Ajg Feed Pumo (MSVR)

a. Close valve for the affected SG:

SG-A [1MS-15], IA SG Steam e

Supply To [1FW-P-2] Isolation SG-B [1MS-16],1B SG Steam e

Supply To [1FW-P-2] Isolation i

SG-C [1MS-17],1C SG Steam e

Supply To [1FW-P-2] Isolation

b. Ensure [1FW-P-2] is capable of being supplied by checking open the following for the two unaffected SGs:

SG-A [1MS-15], IA SG Steam e

Supply To [1FW-P-2]

Isolation SG-B[1MS-16],IBSGSteam e

~

Supply To [1FW-P-2]

Isolation SG-C [1MS-17], IC SG Steam e

59pply To [1FW-P-2]

Isolation l

I A0P164 3/11/97 6 of 13

e BVPS - A0P 10M-53C.4.1.6.4 '(ISS3A)

Number Title 1,6.4 Steam Generator Tube Leakage Issue 3A 4 (

Revision 8' STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 8.

Isolate Atmosoberic Steam Release Canability From Affected SG

a. Place affected SGs atmospheric
a. WiiEH affected SGs pressure is 3

steam dumps in MANUAL and verify less than 1035 PSIG, ItiEM verify valves - CLOSED SG Atm Stm Dumps close.

'PCV-1MS-101A

)

e SG-A

'PCV-1MS-101B IE HQI, IBEM locally isolate SG e

SG-B Atm Stm Dump for the affected SG e

SG-C PCV-1MS-101C' by closing the ap(MSVR - 768'):

propriate isolation valve e

SG-A

'IMS-23' e

SG-B

'1MS-24' F

e SG-C l1MS-25'

~

i

b. Close [HCV-1MS-104], Residual
b. Perform the following:

Heat Release Control Valve.

Manually or locally close

[HCV-1MS-104] Residual Heat p

Release Control Valve (MSVR -

Q 768')

1

-0R-Close [1MS-26] Residual Heat e.

~

Release Isol Viv (MSVR -

768')

i 9.

Realian SG Blowdown Flowoath l

a. Monitor blowdown discharge and perfom valve lineup to dump discharge into [1LW-TK-7A & 7B],

Steam Generator Drain Tanks by performing the following:

" Processing Blowdown To [1LW-TK-7A(B)]"

i

-AND-10M-17.4.0, " Operating the e

Steam Generator Drain Tank Subsystem" O

ADP164 3/11/97 7 of 13

BVPS - A0P 10M-53C.4.1.6Af!>

Y Number Title 1.6.4 Steam Generator Tube Leakage

. Issue 3A Revision STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED j

10. Re-alian Blowdown Samole Sink Drain From River Water System To North Sumo (Aux Blda - 735'. Primary Samole Room)
a. Close [ISS-196], Reactor Plant Panel Drain to River Water.
b. Open [ISS-195], Reactor Plant Sample Panel Drain to North Sump.

Primarv-To-Secondary Leakrate - LESS Isolate Turbine Sumps as follows:

IHAN 142 GPD

a. Place [1PL-P-2A and 2C], Ground Floor Turbine Room Sump Pumps in 0FF (Turb Bldg - 693', NW).
b. Close [1RD-61 and 57], Discharge Isolation for [1PL-P-2A(2C)]

l I

(Turb Bldg - 693', NW).

c. Place [1PL-P-2B and 2D], Ground Floor Turbine Room Sump Pumps in 0FF (Turb Bldg - 693', NE).
d. Close [1RD-63 and 59], Discharge Isolation for [1PL-P-2B(2D)]

(Turb Bldg - 693', NE).

e. Have Health Physics sample before discharging sumps.
f. Refer to 0DCM Appendix C 4.11.1.1.3, " Liquid Effluents -

Concentration" for sample requirements.

l I

ADP164 3/11/97 8 of 13

v BVPS - A0P 10M-53C.4.1.6.4(ISS3A)

Number Title 1.6.4 Steam Generator Tube Leakage Issue 3A Revision 8 STEF ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

12. Reauest Health Physics Assistance
a. Request Health Physics support for the following:
1) Have Health Physics reset alam setpoints 30 GPD above existing baseline reading (pemits detection of rapidly rising leakrate).
2) On a predetemined frequency, have Health Physics record and trend readings of radiation monitors listed under SYMPTOMS.
3) Perfom water and air sampling at various areas in Turbine Building and other areas deemed necessary by Health Physics supervision.
4) Survey blowdown water transport path at frequency established by Health Physics to ensure positive radiological control.
13. Detemine Need To Transfer Auxiliary Steam From Main Steam System To Unit 2 Auxiliary Steam System Refer to 1/20M-27.4A.A, " Supplying e

Unit I With Auxiliary Steam From Unit 2"

14. If The Plant Is In Modes 3. 4. 5 Or
6. And It Is Desired To Cleanuo Condensate Or To Process Condensate As Liauid Waste. Perfom 10M-22.4. I.

"Processina Condensate As Liouid Waste / Condensate Cleanuo Usina The Hiah Caoacity Blowdown System" O

ADP164 3/11/97 9 of 13 1:

BVPS - A0P 10M-53C.4.1.6.4(ISS3A)

)!

Number Title 1.6.4 Steam Generator Tube Leakage Issue.3A _l Revision STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

15. Continue These Surveillances Until Leakino Steam Generator Is Isolated For Reoair

- END -

l I

l A0P164 3/11/97 10 of 13

e BVPS - A0P 10M-53C.4.1.6.4(ISS3A)

Number Title 1.6.4 Steam Generator Tube Leakage Issue 3A Revision 8 i

1 i

PROCESSING BLOWDOWN T0 flLW-TK-7A(7Bll 1.

Obtain Key 0P3 for [1LW-409(410)].

2.

Close [TV-1BD-107A(B)(C)], Flash Tank Inlet for affected SG.

3.

Close [PCV-1BD-100), Blowdown Sys Pressure Reg (Turb Bldg - 693', at

[1FW-E-1B]).

4.

Check open [1LW-300], SG Drain PP [1LW-P-11] Suct Isol (Aux Bldg - 722').

5.

Check open [1LW-302], SG Drain PP [1LW-P-11] Disch Isol (Aux Bldg -

722').

i 6.

Close [1LW-400], Disch Drain For [1LW-P-11] (SFGDS - 722', by pump, Key GP3).

7.

Close [1LW-411], Tell-Tale Drain (SFGDS - 722', by [1LW-P-11]).

8.

Open [1LW-409], Series Isol Fcr [1LW-P-11] (SFGDS - 722', by pump, Key 0P3).

9.

Open [1LW-410], Series Isol For [1LW-P-11] (SFGDS - 722', by pump, Key OP3).

10.

Jf desired to use [1LW-TK-7B],1118 perform the following:

Close [MOV-1LW-11A], SG Bldn To Drain Tk 7A Inlet Isol Vlv.

4 a.

b.

Open [MOV-1LW-11B], SG Bldn To Drain Tk 7B Inlet Isol Vlv.

11.

Open the following to establish flow to [1FW-E-7] (SFGDS - 76S'):

[1CCR-65], Bldn Drain Hx [1FW-E-7] CCR Inlet Isol.

a.

b.

[1CCR-66], Bldn Drain Hx [1FW-E-7] CCR Outlet Throttle.

12.-

Check open [TV-1BD-100A(B)(C)], SG Bldn CNMT Isol Vlv for affected SG.

13.

Check open [TV-1BD-101A1(B1)(C1)], SG Bldn Isol Vlv for affected SG.

14.

Check open [TV-1BD-101A2(B2)(C2)], SG Bldn Isol Vlv for affected SG.

15.

Open [1BD-7(8)(9)], Stm Gen IA )(C) Blowdown To Tank Isol for affected SG (SFGDS - 765', by [1FW-TK-1 A0?164 3/11/97 11 of 13

BVPS - A0P 10M-53C.4.1.6.4(ISS3A)*

Number Title 1.6.4 Steam Generator Tube Leakage Issue 3A I (continued) 16.

Throttle open [HCV-1BD-101A(B)(C)], Stm Gen IA(B)(C) B1owdown Throttle for affected SG to establish flow to [1FW-TK-1] (SFGDS - 765', near tank).

Throttle [18D-29], [PCV-1BD-100] Bypass (Turb Bldg (a-693', at [1FW-E-17.

to maintain

.1FW-TK-1] SG Blowdown Tank pressure s indicated on

[PIC-1BD-100;, at [1FW-TK-1]) less than 50 PSIG.

18.

WHEN level in [1FM-TK-1] rises to 50% as locally indicated on

[LG-1BD-101], Steam Generator Tank Level, IBfB start [1LW-P-11], Steam Generator Drain Pump (SFGDS - 722').

maintain 50% level in }1FW-TK-1] (SFGDS - 722'). Adjust [HCV-1BD-101 (C)], Stm Gen 1A(B)(C) Blowdown Throttle to a.

19.

RETURN TO Step in effect.

-END-O i

A0P164 3/11/97 12 of 13

.BVPS - A0P 10M-53C.4.1.6.4(ISS3A)

Number Title 1,6.4 Steam Generator Tube Leakage issue 3A Rev!sion 8-i i

l REFERENCES 1.

Issue 3,. Revision 11: OMDR 1-88-0516, 87-0333, 88-0298, 86-1771, 86-2186; l

1985 INP0 Evaluation Finding OP.5-la, Ib Appendix I.

2.

Issue 3, Revision 14:

1598, 1-88-1736.

OMDR 1-85-0876, 1-86-2003, 2158, 0166, 1-87-0185, 3.

Issue 3A, Revision 0:

0MDR 1-90-0710, 1-90-0717, 1-89-0737, 1-90-0718, 1-90-0638.

4.

Issue 3A, Revision 1: 0MDR 1-90-0717, 1-93-0295; Walkthrough Validation Comment (10/24/90), OSC Subcommittee Comments (6/30/93).

5.

Issue 3A, Revision 2: OMCN 1-94-02; SOER 93-1; N01DMS:0252.

6.

Issue 3A, Revision 3: 0MDR 1-93-0705.

7.

Issue 3A, Revision 4:

Table Top Validation Coment (3/17/95).

8.. Issue 3A, Revision 5:

OMCR 1-94-0869, 2-95-0410; TS Amendment 188.

9.

Issue 3A, Revision 6: OMCR 1-95-0615; ODCM (Issue 3, Revision 1).

10. Issue 3A, Revision 7:

INP0 SOER 93-1, " Diagnosis and Mitigation Of-Reactor Coolant System Leakage Including Steam Generator Tube Ruptures".

11.

Issue 3A, Revision 8: 0MCR 1-96-0882, 1-97-0065; EPRI TR-104788, "PWR Primary /96).-To-Secondary Leak Guidelines"; OSC Subcommittee Comment:

(12/16

'i O

O I

l l

A0P164 3/11/97 13 of 13 j

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