ML20137T220

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Rev 8 to 2OM-53C.4.2.6.4(ISS1A), SG Tube Leakage
ML20137T220
Person / Time
Site: Beaver Valley
Issue date: 04/09/1997
From:
DUQUESNE LIGHT CO.
To:
References
2OM-53C.4.2.6.4, NUDOCS 9704160028
Download: ML20137T220 (14)
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Text

3

, BEAVER VALLEY POWER STATION

, , CONTROLLED DOCUMENT DISTRIBUTION FORM TO: NUC. REG. COMMISSION TRANSMITTAL NO. 970407102NCOMMISSION NRC OFFSITE FROM : Beaver Valley Records Center Document Control The document (s) identified below are enclosed. Please review to verify receipt, incorporate the document (s) into your controlled document file, properly disposition superseded documents, and sign and return the receipt acknowledgement below within fourteen (14) calendar days to the BVRC, at mail drop BV-SEB1.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 / FULL 35M M RTYPE UNIT IDENTIFICATION NUMBER NO. NUMBER ADD QTY QTY APPLICABLE DOC-ID.

A9.350 C BV2 20M-53C.4.2.6.4(ISSIA) 000 008 1 0 l REPLACES: 20M-53C.4.2.6.4(ISSIA) 000 007 1

l i

i Receipt of the above listed document (s) is hereby acknowledged and I certify that all void or superseded copies of the above listed document (s) in my possession have been removed from use or marked void.

00k eg Signature , Date 9704160028 970409 ,k.!f5 ,N,N, PDR ADOCK 05000334 P PDR

p 1

  • Record Type SA9.350C

[ DUQUESNE LIGHT COMPANY Beaver Valley Power Station UNIT 2

)

i i

l 2ou-sac.4.2.s.4(ISS1A) i Steam Generator Tube Leakage

,o O i

I issue 1A Revision 8 i ,

l Prepared by Date Pagesissued

! M. P. Flynn 12/18/96 1 through 12 Eff ' ~ e 6abe 1997 Reviewed by Date Validated by Date C. O'Neill 12/18/96 N/A OSC Meeting No. Date Date BV-OSC-51-96 12/18/96 Ap rov [ed by j ,

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BVPS - A0P 20M-S3C.4.2.6.4(ISSIA)

, e Number Title i 2.6.4 Steam Generator Tube Leakage Issue 1A Revision 8 i l

A. PURPOSE ~

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

l

\

B. SYMPTOMS OR ENTRY CONDITIONS l

l

1. Rising radiation levels or alarm conditions on any of the following radiation monitors:

l e '2 ARC-RQ100' Air Ej Discharge (1007) e ',2GWS-RQ102' , Ej D-bed Exh (1047)

. 2SSR-RQ100 Blowdown (1062)

2. Secondary side activity detected by routine chemistry monitoring procedures.

4 C. AUTOMATIC ACTIONS j

i 1. [2SSR-RQ100] Blowdown monitor causes the following valves to close; e ,2SSR*A0M17A,B.C] 21A,B C SG Blowdown Sample Outside CNMT Isol e 2BDG*A0V100.\1.B1.C1] 21A,B,C SG Blowdown Outside CNMT Isol Vlvs 4

O ACP264 3/11/97 1 of 12

l 1

BVPS - AOP 20M-53C.4.2.6.4(ISSIA) I Number T1 tie '

i 2.6.4 Steam Generator Tube Leakege Issue 1A i

Revisiongllg l STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i fl01E This procedure may be performed in conjunction with A0P 2.51.1, " Emergency Shutdown." l

1. Reauest Suooort As Follows:

l

a. Request Chemistry to calculate SG primary-to-secondary le. :.r4 ?.
b. Request Chemistry to perform isotopic analysis for dose equivalent I-131 for the leaking ,

SG. I

c. Request Health Physics to '

estimate SG primary-to-secondary leakrate using:

e '

,2 ARC-RQ100,'

e 2SSR-RQ100, 1

l l

l l

l I A0P264 3/11/97 2 of 12

BVPS - A0P 20M-53C.4.2.6.4(ISSIA)

- Number Title Steam Generator Tube Leakage Issue 1A 2 6.4 Revision 8 O RESPONSE NOT OBTAINED STEP ACTION / EXPECTED RESPONSE Primary-To-Secondary Leakrate Should Be Closelv Monitored Durira The Performance of This Procec ure'

a. Detemine leakrate by Chemistry sample results or Health Physics results. (There is no need to wait for Chemistry to verify Air EjectorMonitorresults.)
b. The leakrate should be plotted and the rate of change detemined.
c. E SG primary-to-secondary leakrate exceeds 150 GPD in any one SG, Ilim shutdown to Mode 3 l within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
d. E SG primary-to-secondary leakrate exceeds 30 GPD in any O one SG, Illm perform the following:
1) Have Chemistry increase sample monitoring to requantify SG primary-to-secondary leakrate.
2) Have Health Physics monitor radiation monitors and estimate SG primary-to-secondary leakrate by converting pCi/cc to GPD every 15 minutes.

. '2 ARC-RQ100' e [2SSR-RQ100

e. Request Chemistry perform Chemistry Manual Chapter 5.12,

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

O (stepcontinuednextpage)

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BVPS - A0P 20M-53C.4.2.6 4(ISSIA)

Number Ttt1o 2.6.4 Steam Generator Tube Leakage Issue 1A Revision -

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED (continued from previous page)

f. The following actions should be based on the highest 3rimary-to- i secondary leakrates o)tained from l Chemistry or Health Physics  !

estimates:

l Primary-To-Secondary Leakrate For Any One SG Required Actions i

SG leakrate rate of rise 2 60 Perform an emergency shutdown in accordance GPD/HR with AOP 2.51.1, " Emergency Shutdown" and I

be in Mode 3 as quickly as possible.

SG leakrate 2150 GPD AND Shutdown plant and be in Mode 3 within 6 rate of rise < 60 GPD/HR hours.

l CAUTION 20ST-6.2 (20ST-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.  :

3. Perform Either Of The Followina:

e 20ST-6.2, " Reactor Coolant System Water Inventory Balance"

-0R-e 20ST-6.2A, " Computer Generated Reactor Coolant System Water Inventory Balance"

4. Reouest Chemistry Samole Secondary Coolant For Soecific Activity l l AOP264 3/11/97 4 of 12

BVPS - A0P 20M-53C.4.2.6.4(ISSIA) i Number Title Issue 1A Steam Generator Tube Leakage 2.6.4 Revision 8 RESPONSE NOT OBTAINED STEP ACTION / EXPECTED RESPONSE

5. Verify como11ance With T.S. 3.4.6.2. Take action in accordance with "00erational Leakaae" And 3.7.1.4. Technical Specifications.

" Activity" Refer to EPP for notification requirements.

6. Check f2 MSS *R0101 A. (B) . (C)1 (1005.

2005: 3005. 4005: 5005. 6005). Main Steam Line Radiation Monitors -

AVAILABLE

a. Notify Health Physics that Main Steam Line Radiation Monitors will be placed in service. .
b. Open [2 MSS *S0V120], Main Steamline Rad Monitor Disch Isol.

O O  :

AOP264 3/11/97 5 of 12

BVPS - A0P tiumber 20M-53C. 4.2. 6.4(!SSIA) j Titio 2.6.4 -

Steam Generator Tube Leakage Issue 1A STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 7.

. Isolate Steam Sunolv From Affected feed To SG Pumof2FWE*P221. Steam Driven Aux

a. Dispatch operator with Key SR/14 to close valve for affected SG (MSCV - 773'):
  • SG 21A [2 MSS-15], Stm Supply IsolTo[2FWE*T22]
  • SG 21B [2 MSS-16], Stm Supply Isol To [2FWE*T22]
  • SG 21C [2 MSS-17], Stm Supply Isol To [2FWE*T22]
b. Ensure [2FWE*P22] is capable of being supplied by checking open the following for the two unaffected SGs:
  • SG 21A [2 MSS-15], Stm Supply Isol To [2FWE*T22]
  • SG 218 [2 MSS-16], Stm Supply Isol To [2FWE*T22]
  • SG 21C [2 MSS-17], Stm Supply Isol To [2FWE*T22]

l I (step continued next page)

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s

. BVPS - AOP 20M-53C.4.2.6.4(ISSIA)

, Humbir T1 tie 2.6.4 Steam Generator Tube Leakage f Issue 1A i

Revision 8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

7. (continued from previous page) 1
c. Since the turbine driven aux feed pump steam supply isolation SOVs from SG 21C are dual power  ;

supplied, it is necessary to

" HARDEN" the supply from SG 21C as follows:"

1E SG 21C is affected, IEEN GO TO Step 8.  !

1E SG 21A is affected, IREN perfonn the following:

Trip And I

1) Thrott Closee :2FWE*TTV22],[2FWE*P22]

Valve For (SFGDS - 718').

2) Open and then close

[2 MSS *S0V105C Turb Driven AFW Pump Stm Hdr C ], Supply Isol.

O Q 3) Open and caution tag Pump Stm Hdr ]C Supply Isol.[2 MSS *SOV105F , Turb Driven AFW

)

4) Open [2FWE*TTV22], Trip And l

Throttle Valve For [2FWE*P22]

in accordance with 20M-24.4.R.

" Resetting And Opening TDAFW Pump Trip And Throttle Valve."

5) GO TO Step 8. '

If SG 218 is affected, IEEN perform the following:

Trip And

1) Thrott'e Close :2FWE*TTV22],[2FWE*P22]

Valve For (SFGDS - 718').

2) Open and caution tag

[2 MSS *S0V105C), Turb Driven AFW Pump Stm Hdr C Supply Isol.

3) Open [2FWE*TTV22], Trip And Throttle Valve For [2FWE*P22]

in accordance with 20M-24.4.R.

" Resetting And Opening TDAFW p Pump Trip And Throttle Valve."

A0P264  ?/11/97 7 of 12

BVPS - A0P 20M-53C .4. 2. 6.,4 (ISSI A)'

Number Title 2.6.4 Steam Generator Tube Leakage Issue 1A ^

Revision STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

8. Isolate Flow From Affected SG
a. Adjust affected SG Atm Stm Dump setpoint to 100%:

. SG 21A '2SVS*PCV101A' e SG 21B '2SVS*PCV101B'

. SG 21C l2SVS*PCV101C.'

b. Verify affected SG Atm Stm Dump - b. E affected SGs pressure is CLOSED less than 1040 PSIG, M verify

~

e SG 21A '2SVS*PCV101A' e SG 21B l2SVS*PCV1018 If EQI, M locally isolate the e SG 21C 2SVS*PCV101C. SG Atm Stm Dump for~the affected 4 SG by closing the appropriate--

isolation valve (MSVR - 773'):

. SG 21A '2SVS*23' e SG 21B '2SVS*24' e SG 21C l2SVS*25:

c. Dispatch operator to locally isolate [2SVS*HCV104], Residual Heat Release Valve from affected SG by closing appropriate valve (MSVR-773'):

e SG 21A [2SVS*27], Main Steam Residual Heat Release Isol Valve e SG 21B 2SVS*28], Main Steam Residua' Heat Release Isol Valve l

e SG 21C [2SYS*29], Main Steam Residual Heat Release Isol Valve

! 9. Perform 20M-25.4.H. "Oceratina With Primary To Secondary Leakaae" l

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e BVPS - A0P 20M-53C.4.2.6.4(ISSIA)

Number Title 2,.6.4 Steam Generator Tube Leakage Issue 1A Revision 8 J

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED Primarv-To-Secondary Leakrate - LESS Perfonn the following:

THAN 142 GPD

a. Realign [2WOS-0WS21,22,23,24]

Oil / Water Separators' effluent to Steam Generator Blowdown Hold Tanks in accordance with 20M-41D.4.D, " Operation of the Oil / Water Separators."

b. Control contamination by performing the following:
1) Close [2DBS-91], Floor Drain Isolation To 2DBS System (MSCV

- 718').

~

2) Open [2DBS-124], Floor Drain l

Isolation To [2DAS-TK206]

(MSCV - 718') .

c. Refer to 0DCM Appendix C 4.11.1.1.4, " Liquid Effluents -

Concentrattons" for sample requirements.

O AOP264 3/11/97 9 of 12  ;

BVPS - AOP 20H-53C.4.2.6.4(ISSIA)

Number T121e l 2.6.4 Steam Generator Tube Leakage Issue 1A _

Revision STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

11. 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 (permits detection of rapidly .

rising leakrate).

2) On a predetermined frequency, i have Health Physics record trend readings on radiation monitors showing above normal 4

or alarm activity levels.

3) Perform water and air sampling at various areas in Turbine  !

Building and other areas deemed necessary by Health Physics supervision.

4) Survey Steam Generator Blowdown path at frequency established by Health Physics to ensure positive radiological control.
12. Determine Need To Transfer Auxiliary Steam From Main Steam System In Accordance With Either Of The Followina e 20M-27A.4.B. " Transferring Auxiliary Steam Supply From Main Steam Tn The Auxiliary Boilers" e 1/.'0M-27.4A.8, " Supplying Unit 2 With Auxiliary Steam From Unit 1"
13. If Desired To cleanuo Condensate.

Perform 20M-228.4.A. "Placino The Condensate Demineralizers In Service" l l AOP264 3/11/97 10 of 12

BVPS - A0P

' 20M-53C.4.2.6.4(ISSIA)

Number Title 2,6.4 Steam Generator Tube Leakage Issue 1A (v] Revision 8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

14. If The Plant Is In Mode 3. 4. 5 Or
6. And It Is Desired To Process }

Condensate As Liauid Waste. Perform  !

The Fol10 wino:

a. Open any one drain valve on the condensate side of the 2nd, 3rd, 4th or 5th point heaters to allow draining of condensate to the nearest floor drain (Turb Bldg -

730').

b. Process Turbine Bldg Sump 1 effluent in accordance with l 20M-41D.4.D, " Operation Of The '

Oil / Water Separators."

c. Liquid waste should be processed in accordance with 20M-17.4 Operating Procedures, as

( appropriate.

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

- END -

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A0P264 3/11/97 11 of 12

BVPS - A0P 20M-53C.4.2.6.S(ISSIA)

Nurser Title 2.6.4 Steam Generator Tube Leakage . Issue.1A

Revision HEFERENCES

1. Issue 1, Revision 10: BVPS Radcon Manual.
2. Issue 1, Revision 10: BVPS-2 Technical Specifications.
3. Issue 1A, Revision 0: 0MDR 2-90-0649, OMCN 2-90-15, 2-89-1509.
4. Issue IA, Revision 1: DLW-93-195 dated 3/9/93; ND2NSM:5905 dated 2/5/93; ND2N02:0373 dated 2/1/93; ND3NSM:5892 dated 1/28/93; ND3NSM:5906 dated 2/5/93; OMDR 2-89-0488, 0489, 2-90-0818, 0839, 1013, 2-91-0183, 0269, 0271, 2-92-0921, 2-93-0176; Walkthrough Validation Comment (9/24/92);

Table Top Validation Comment (6/25/93), OSC Subcommittee Comments (6/30/93).

5. Issue 1A, Revision 2: OMCN 2-94-01; SOER 93-1; NDIDMS:0252; OMCN 2-94-25.
6. Issue 1A, Revision 3: 0MCR 2-95-0106; Table Top Validation Comment (3/8/95).
7. Issue 1A, Revision 4: 0MCR 2-95-0410; TS Amendment 70.
8. Issue 1A, Revision 5: PR 2-95-304.
9. Issue 1A, Revision 6: ODCM (Issue 3, Revision 1).
10. Issue 1A, Revision 7: OMCR 1-95-0615; INP0 SOER 93-1, " Diagnosis And Mitigation Of Reactor Coolant System Leakage Including Steam Generator Tube Ruptures"; OSC Subcommittee Comment (8/29/95).
11. Issue 1A, Revision 8: OMCR 2-96-0749; EPRI TR-104788, "PWR Primary-To-Secondary Leak Guidelines"; OSC Subcommittee Comment (12/16/96).

4 AOP264 3/11/97 12 of 12

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