ML19340E122

to Inservice Insp Program

ML19340E122
Person / Time
Site:	Davis Besse
Issue date:	11/30/1980
From:	TOLEDO EDISON CO.
To:
Shared Package
ML19340E120	List: ML19340E119 ML19340E122
References
PROC-801130, TAC-10985, TAC-11316, NUDOCS 8101060459
Download: ML19340E122 (60)

Text

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i REVISION 1, NOVEMBER 1980 l 4

i l Pace Page ,

I I I-4 II-45 j I-7 II-46 II-47 II-7 II-52 II-B II-53 i II-ll II-55

II-12 II-59 II-14 II-60 4

II-15 II-61 II-16 II-63 II-17 II-64 II-18 II-64a 4

II-19 II-66 II-22 II-68 +

II-23 II-69 i

II-24 II-70a II-25 II-70b l II-26 l II-27 III-l 1

II-28 III-2

. II-30 III-3 i II-31 III-3a II-32 III-7 5

II-34 , III-30

II-35 III-42 ,

II-36 III-46

! II-37 III-66a l II-38 III-66b j II-40 j

II-41 II-42 II-44 f

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DAVIS -BESSE NUCLEAll POWEll STATIOrl UNIT NO. 1 PUMP TEST PitOGitAM Page 1 of 2 SYSTEtt TEST PARAMETER MPAStillED

& y IllLI:T DIFFEitENTIAL FLOW DRAWING VIllRATION DEARING LUHRICANT Q PtittP SPEED PilESSilRE PRESSURE RATE AMPLITilDI: TEMPERATUlU; LEVEL OR NUtti1ER oU NO. n* Pi Ap Q V Tb CODE PIU:SSURE EXCEPTION AUXILIARY J-8 P14-1 Q Q Q Q Q NR NR 1,2,3 FEEIMATER 006R K-9 P14-2 Q Q Q Q Q NR NH 1,2,3 IIIGII E-9 P58-1 NR Q PRESSURE Q Q Q NR NR 1,2,3 INJECTION C-9 P58-2 NR Q Q Q y 033 Q NR NH 1,2,3 b

IDW 11 - 7 P42-1 NR Q Q Q Q NR NR PilESSURE 1,2,3 INJECTION G-10 P42-2 NR Q 033 Q Q Q NR NR 1,2,3 CONTAINMENT D-9 P56-1 NR Q Q Q Q NR NR SPRAY 1,2,3 l

034 C-9 P56-2 NR Q Q Q Q NR NR 1,2,3 COMPONEttr 11 - 2 P43-1 NR Q Q Q Q NR NR COOLING ,

1,2,3,4 036 J-2 P43-2 NR Q Q Q Q NH NR 1,2,3,4 K-2 P43-3 NR Q Q Q Q NR NR 1,2,3,4 t.

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• SYNCllROrlOUS OR It3DUCTIOli itOTORS DO NOT REQUIRE SPEED CilECK (IWP-4400).

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per year for data reduction, analysis, and record keeping. This amounts to a total of 774 man-hours per year. At a conservative total cost of $20 per man-hour, this amounts to $15,480 per year.

Based upon the average exposure rates in the areas of the Auxiliary Feedwater, High Pressure Injection, Low Pressure Injection, and Containment Spray Pumps, the total man rems exposure per year for pump testing is approximately 2.0 man rems. At the present conservatively estimated cost of $10,000 per man rem to plant personnel, this exposure costs an additional S20,000 per year. Total cost to our customers is approximately $35,490 per year for no significant increase in safety.

. Alternate Testing: Pumps will be tested in ecepliance with ASME Section XI once per quarter and will be g Jogged monthly and ficw measured. This is in agreenent g with present changes that are being implemented in Subsection IWP of the Code.

The revision to change pump testing to a three month interval in IWP-3400 has been approved and will be included in future Addenda. See Minutes of the November 28, 1979, meeting of the Operating and Maintenance Working Group - Testing of Pumps and Valves, in San Jose, California, dated January 9, 1980.

b. Code Exception Number 2

. Components: Auxiliary Feedwater Pumps P14-1, P14-2 High Pressure Injection Pumps P56-1, P58-2 Low Pressure Injection Pumps P42-1, P42-2 l Containment Spray Pumps P56-1, P56-2 Component Cooling Pumps P4 3-1, P4 3-2, P4 3-3 Service Water Pumps P3-1, P3-2, P3-3

. Function: Emergency Core Cooling Safety Related Equipment Cooling

. Clasa: 2 and 3

. Test Requirements: Measure pump bearing temperature yearly

. Basis for Exception: The referenced edition of the Code requires bearing temperature to be recorded annually.

It has been demonstrated by experience that bearing temperature rise occurs only minutes prior to bearing failure. Therefore, the detection of possible bearing f ailure by a yearly temperature measurement I-7 Rev. 1-11/80

DAVIS-IlESSE NllCI.F.All POWEft STATION UNIT NO. 1 Page _ L of 2 VAINE TEST PitOGItAM System f1AIN STEAf1 Drawi ng flo. 003 IleV . 29 E

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DAVIS-DESSE NUCLEAR POWER STATION UNIT NO. 1 Page I of 3 VAINE TEST PROGRAM Syst.em FEEDWATER SYSTEM Drawing No. 00611 Rev. 32 y

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DAVIS-BESSE NUCI. EAR POWER STATION UNIT NO. 1 Page L of 3 VAINE TI'ST PROGRAM System STEAM GENERATOR SECONDARY SYSTFM Drawing No. 007 Rev. 29 E

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I DAVIS-IlESSE PJilCI,ITAR POWER STATIO!J UtJI T tJO . I page g or g VAINI: TEST l'ROG13 AM Syst.em CotJTArtJMEllT AtJD pet 3ETRATIOf3 ROOMS Drawing flO. 029A Ile V . 24 E

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1 DAVIS-BESSE tJUCI, EAR POWER STATIOri Uf1IT 110. 1 Page 1 of 1 VAINE TEST PROGRAM System COtrrAltMEtrP AND PENETRATION R(WWS Drawing flo. 0298 Rev. 24 E

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DAVIS-BESSE NUCLEAll POWER STATIOff UNIT NO. 1 Page 3 of 3

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CV50llE 2 1I-12 X 1 GA MO OP S Q LEAK TEST PER APPENDIX J T Q 15 CV5010D 2 G-11 X 1 BL MO OP S Q LEAK TEST PER APPENDIX J T Q 15 CV50llD 2 ' 10 X 1 DL MO OP S Q I.EAK TEST PER APPENDIX J T Q 15 cv5010n 2 11 - 4 X 1 BL MO OP S Q LEAK TEST PER APPENDIX J T Q 15

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DAV I S-BI::SSI: NUCLI:All POWi'It STATION UfJ IT fl0. 1 Page 1 of 1 VAI.V! TI;ST PitOGitAM System REAC'lY)R COOI.Affr tiraWi ng flO. 030 Ite v . 27 E

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RC240A 1 D-2 X 1 cn' MO CL S Q LI:AK TEST PER APPENDIX J T Q 30 RC240H 2 11 - 2 X 1 GA MO CL S Q LEAK TEST PER APPEt3 DIX J T Q 30 RCl3H 1 A-5 X 4 RL SA -- p p g RCl3A 1 n-6 X 4 RL SA --

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y RCll 1 A-3 X 2.5 GA MO OP S Q T Q 30 IK'2A 1 A-3 X 2.5 GA SO CL S 12 S R T - -

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DAV I S -It ESS E fiUCI. EAR POWE ft STATIOt1 UtJI T 110 . 1 Page 1 of 2 VAINE TI:ST PitOGitAM S ys t.em MAKEUP AtJD PURIFICATIOri Drawing tio. 031 Itev . 31 m o en G C M e y Valve _ g, e g y ,* D Cy E$ Cat _. f $ S g.3 $ ,'j j E @ y$

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'm ll jp .y p@ $$ fM 8y Q$ fd' y Pemarks MU33 2 P-5 X 2.5 GA' AO OP S 13 S C LEAK TEST PER APPEtJDIX J P F C T T C 10 MU242 2 K-2 X X X 1.5 SC SA ID S 14 S R LEAK TEST PER APPENDIX J L R MU66A 2 K-3 X 1.5 GI, AO OP S 15 S R LEAK TEST PER APPEtJDIX J P P R N' T T R 12 MU243 2 J-2 X X X 1.5 SC SA ID S 14 S R LEAK TEST PER APPEllDIX J L R MU66D 2 J-3 X 1.5 GL AO OP S 15 S R LEAK TEST PER APPEtJDIX J P P R T T I4 12 MU244 2 11- 2 X X X 1.5 SC SA ID E 14 S R LEAK TEST PER APPEtJDIX J L R HU66C 2 II- 3 X 1.5 GL AO OP S 15 S R LEAK TEST PER APPEtJDIX J F F R T T R 12 MU245 2 11 - 2 X X X 1.5 SC SA ID S 14 S R LEAK TEST PER APPEt1 DIX J L R

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DAVI S-ilESSE NUCI EAlt POWElt STATIOt1 Ut1IT tJO. 1 Page 2 of 2 VAINE TEST FitOGRAM System MAKEUP AND PUHIDICATION 1)rawi ng flo. Oll Rev. 31 y

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" MU59A 2 D-2 X GL 1 MO OP S 15 S R LEAK TEST PER APPENDIX J

,', T T R 30 4

MU38 2 E-5 X 1 GL AO OP S 15 S R LEAK TEST PER APPENDIX J F F R T T R 12 MU3 2 C-5 X 2.5 GA AO OP S Q LEAK TEST PER APPENDIX J P Q T Q 10 MU2A 2 C-4 X 2.5 GA MO OP S 26 S C LEAK TEST PER APPENDIX J T T C 15

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DAVIS-DESSE NilCLEAR POWER STATION tlNIT NO. I page 3~

VAINE TEST PROGRAM or ,,

S y s t.em DECAY 11 EAT At3D EMERGEtJCY col 4E COOLIllG Drawilig flo. 013 Rev. 34

$ i$ $7 y Valve _ u e $ @ $ b 8y it 'i Cat. g g 3 a g 7 g g 3; e I $E $ n$ $* 0* 0$ t; b 8$' $p$ L; {' *n Valve thamber C $0 A 16 C D $ $H .( j M jj f ,$ 0y Qf fdj j1 Remarks Dil23 1 11 - 3 X X 8 GA MA I,C I. R LEAK TEST I'l-:R APPENDIX J D1121 1 Il- 2 X X 8 GA MA LC I. R VALVE ItJTEGitITY TESTED WITil Dil23 LEAK TEST BY DRAINItJG AtlD PRESSURIZATION liETWEEN Tile VALVES Dil20 1 11-2 X X O.75 GL MA LO L H DlI24 1 II- 2 X X 0.75 GA MA LO L R H

7 u Dill 1 1 11 - 3 X X 12 GA MO CL P R ai Dlit 2 1 11 - 2 X X 12 GA MO CL P R Dil4849 2 11 - 4 X 4 RI. SA --

R R Dit9A 2 K-5 X 14 GA MO CI. S 16 S R T T R 120 Dii98 2 J-5 X 14 GA MO CL S 16 S R T T R 120 Dil82 2 K-ll X 14 CK SA --

S Q FOltWARD FIDW TEST WITil DECAY llEAT l'IlMP TEST Dil2733 2 J-6 X X 10 GA MO OP P R Dil81 2 J-lO X 14 CK SA --

S Q FORWARD FLOW TEST WITil DECAY g IIE'AT P81MP TEST Dill 517 2 11-5 X X 12 GA MO CL P R w

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DAVIS-BESSE NilCLEAR POWER STATION UNIT NO. 1 Page 3 of a VAINE Ti'.ST PROGRAM System DECAY llEAT Ar1D EMERGENCY CORE C M LIr1G Drawilig No. 033 Ile v . 34 y

N $7 valve _ n e $ $ $ i? Oy EN Cat- a0 $

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B C D $ Mh @S g*, O$ Qf 'g1 Remarks Dii44 2 11 - 1 1 X X 10 GA. MA ID L R Dil4 2 2 11 - 1 1 X 10 CK SA S FORWARD FIDW TEST WITil PUMP TEST Q

D112734 2 K-9 X y 18 GA MO OP P R DtiH7 2 F-5 X X H GA MA LC L H LEAK TEST PER APPENDIX J DilRH 2 F-4 X X H GA MA 1,C I. R LEAK TEST PER APPI:NDIX J CF29 1 B-2 X 14 CK SA --

S 17 S R

" CF31 B-2 1 X 14 CK SA --

S 18 S C VALVE INTEGRITY TESTED d, PER ST 5050.03 o

DII77 1 C-2 X X 10 SC SA LO S 10 S C VAINE INTEGRITY TESTED L R PER ST 5050.0 3 flP51 1 C-2 X 2.5 CK SA --

S 19 S R FORWARD FIDW TEST IIP 49 1 C-2 X X 2.5 SC SA ID S 19 S R FORWARD FIDW TEST L R IIP 50 1 C-2 X 2.5 CK SA --

S 19 S R FORWARD PLOW TEST llP48 1 C-2 X X 2.5 SC SA ID S 19 S R FORWARD FIDW TEST L R CF20 1 B-3 X 14 CK SA --

S 17 S R CF30 1 0-3 X 14 CK SA --

S 18 S C VAINE INTEGRITY TESTED PER ST5050.03 DII76 1 D-4 X X 10 SC SA ID S 18 S C VALVE INTEGRITY TESTED L R PER ST5050.0 3 vi s

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DAVIS-IlrSSE NtlCIEAR POWER STATION UNIT NO. I page 4 of a VAINI; TEST PROGRAM System DECAY IIEAT At3D EMERGEtJCY CORE COOLit1G Drawing No. 933 Rev. 34 E

Valve N $7

'd _ u e $ $ $ D 8O E .$ Cat.. $ $ 0 g.3 $ 'O $E @ M$

as e$ 4 'u I$ $ 4 N *$

Valve titunber C $0 A B C D $ d11 $ M O2 [M O5 Qf $M y Remarks IIP 59 1 C-4 X X 2.5 CK SA S 19 S R FORWARD FIDW TEST WITil tJORMAL ttAKEUP llP57 1 C-4 X X 2.5 SC SA 10 S 19 S R FORWARD PLOW TEST WITil tJORMAL L R MAKEUP IIP 50 1 C-4 X 2.5 CK SA --

S 19 S It FORWARD FIOW TEST IIP 56 1 C-4 X X 2.5 SC SA LO S 19 S R FORWARD FIOW TEST g L R Y

g itP2A 2 C-5 X 2.5 GL MO CL S 27 S C T T C 15 IIP 2B 2 C-5 x 2.5 CL MO CL S 27 S C T T C 15 IIP 2 7 2 C-7 X X 4 GA MA LC L R Dill A 2 B-6 X X 10 GA MO OP P R DtI2736 2 H-5 X X 1.5 GL MO CL P R LEAK TEST PER APPEllDIX J DIl2735 1 B-4 X X 1.5 GA MO CL P 11 LEAK TEST PER APPEtJDIX J IIP 25 2 C-8 X X 4 GA MA IO L R llP2 3 2 C-8 X 4 CK SA --

S Q FORWARD FIDW TEST WITII PUMP TEST v IIP 31 2 B-8 X X X 2 SC SA --

S Q FORWARD FIOW TEST WITil PUMP TEST MO OP P R

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DAVIS-IlESSE NUCLEAR POWER STATION UNIT NO. ] Page 7 of 8 val.VI: TEST PROGHAM System DECAY llEAT AtJD EMERGEtJCY CORE COOLItJG Drawing ?!O. 033 Rev. 34 E

y Valve N $7

_ u c ,9 @ $ D SS E" Cdt- $ $ U .-4 O 0 Ys fE $ u$ 3 0 $ $ Ob $* 5\* 05 U?r 8$ b$ U ?:

Valve iluml>er O [j O A B C D 2 "6j " y ,y g @j f$ 0$ Qf fU * 'gf, Remarks DtI60 2 E-ll X X 1 GA' MA IC L R IIP 32 2 D-7 X X X 1.5 SC SA -- S O FORWARD FIDW TEST WITil PUMP MO OP P R TEST.

Dill 0 2 II-4 X X 2.5 GA MA '.0 L R Dil26 2 II-4 X X 2.5 GA MA ID I. R IIP 1556 -

A-8 X X 3 GA MA ID L R llP35 -

A-9 X X 2.5 GA MA ID L R IIP 107 3+ 11- 8 X X 0.5 GA MA ID L R IIP 207 3' II-8 X X 0.5 GA MA ID L R IIP 33 -

A-9 X 3.0 CK SA --

S Q FORWARD FIDW TEST IIP 108 3* II-8 X X 0.5 GA MA ID L R IIP 208 3+ 61- 8 X X 0.5 GA MA ID L R IIP 103 3+ J-7 X X 0.5 GA MA lo I. R llP203 3+ J-7 X X 0.5 GA MA ID L R llP106 3+ J-8 X X 0.5 GA MA ID L R 3 IIP 206 3+ J-8 X X 0.5 GA MA ID L R Y

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DAVIS-BESSE flUCI. EAR POWER STATION UNIT NO. 1 Page 8 of 8 VAINE TEST PROGItAM System DECAY IIEAT AtJI) Ef1ERGEtJCY CORE COOI ItJG Drawing FIO. 033 ItOV. 34 E I$ .0 7

% Valve _ u e 8 8 9 D C8 ES Cat. #  : .9 ~.3 n '1

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IIP 101 3 J-8 X X 0.5 GA ,

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6 Dill 4B 2 F-8 X X 10 BF AO OP P R w

IIP 102 3 J-8 X O.5 CK SA --

S Q FORWARD FIDW TEST.

IIP 202 3' J-8 X 0.5 CK SA --

S Q FORWARD FIDW TEST.

+

llP105 3 J-8 x 0.5 CK SA --

S Q FORWARD FIDW TEST.

+

IIP 205 3 J-8 X 0.5 CK SA --

S Q FORWARD FUM TEST.

Dill 3 A 2 Il- 11 X X 6 ilF AO CI. P R Dill 3B 2 G-9 X X 6 UP AO CL P R f

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DAVIS-IlESSE NUCLEAll POWER STATION UNIT NO. I page L of 3 VAINE TEST PROGitAM EMERGENCY CORE COOLItJG, gY, Cot 4TAINMENT SPRAY, AND CORE FIDOD DrawiD9 f!O. 0 34 Ile V . 20

$ N .b C y Valve _ 5, c $ $ $ D R8 n' S Ca. #  : 3 .S n ~I: ir S MS I $ '$ $ R$ t l? 0$ uib 8$ ly

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CF100 2 G-3 X X 1 GA MA ID L R CP15 2 G-3 X X 1 SC SA --

S 25 S R I.EAK TEST PER APPENDIX J REVERSE FLOW TEST CF7A 2 G-3 X 2 RL SA --

R R CFSA 2 G-4 X X 1 GL MO CL P R LEAK TEST PER APPENDIX J CFSB 2 G-7 X X 1 GL MO CL P R LEAK TEST PER APPENDIX J CF7B 2 G-7 X 2 RL SA --

R R CF103 2 G-7 X X 1 GA MA ID L R CP16 2 G- fl X X 1 SC SA --

S 25 S R LEAK TEST PER APPENDIX J y REVERSE FIDW TEST (n

CF1544 2 G-9 X 1 GL AO CL S Q LEAK TEST PER APPENDIX J 7 P Q O T Q 10 s

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DAVIS-BISSE: NUCI. EAR l'OWER STATION tlNIT NO. 1 Page 2 of 3 EMERGENCY CORE COOLING, System CONTAItir1ENT SPHAY At3D COI4: FinoD Drawing No. 0 34 Rev. 20 e N $Q

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[j CF1542 2 E-13 X 1 GI, AO CL S Q LEAK TEST PER APPENDIX J l

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S Q FORWARD FIDW TEST WI111 Pt1MP TES'l .

CS2 2 D-10 X X 10 GA t1A to L R SA532 2 C-5 X X 2 GL MA LC L R LEAK TEST PER APPENDIX J l CS19 2 C-5 X X 8 GA MA LC L R CS17 2 C-6 X X 8 GL MA LC L R 31 7

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DAVIS-13 ESSE NUCI EAlt POWElt STATION UNIT NO. 1 Page 1 of 6 VAI,VE TEST l'ItOGitAM Syst.em COMPot1ENT COOLIt3G WATER Drawing No. 036 Ite V . 28 y

E Valve N $7

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Valve Ntaml>er O Ij O A B C D $ MU $ jj fy 0y Qf y[j g Remarks CC19 3 K-3 X 14 CK SA --

S Q FOFWARD FIDW TEST WITil PtJMP TI:ST.

+

CCIO 3 J-3 X 14 CK SA --

S Q FOIMARD FIDW TEST WITil PIIMP TEST.

4 CC17 3 11 - 3 X 14 CK SA --

S Q FOIMARD FIDW TEST k iTil Ptit!P TEST.

CC1495 3 Il-6 X 16 HP AO OP S O P Q T Q 60 0

j. CC1411n 2 G-5 x 12 HP MO OP S 21 S R I,EAK TEST PER APPENDIX J T T R 15 CC1411A 2 G-3 X 12 HP MO OP S 21 S R T T R 15 CCl407A 2 C-6 X 12 BP MO OP S 21 S R T T R 15 CC1407B 2 B-6 X 12 BP MO OP S 21 S R I,EAK TEST PER APPENDIX J T T R 15 CC1643 3 A-3 X 3 RL SA --

R R CC3602 3 A-3 X 3 RL SA --

R R CC659 3 C-9 X X 1.5 GA MA I,C L R 31 +

y ONE PLIMP IS AN If1STALI,ED SPAPE AtJD EI.ECTRICALLY DISCONNECTED. ThO PUMPS ARE IN SERVICI: DilRING tJORMAI, OPERATION AND ONLY TIIE CIIECK VALVES ASSOCI ATED WITil Tile NOld!AI, OPEIU\TIf4G Pl!ttPS WILL DE TESTED. TIIE TIIIRD VAI,VE WII.1, DE

';' TESTED wi!EN TIIE PUMP IS Pl. ACED IN SERVICE.

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DAVIS-HESSE ?JUCI,EAll POWER STATIOf1 Uf1IT NO. 1 Page ~2 Of 6

VAINE TI'ST P ROGithM Syst.em COMPONEf1T COOLIrlG WATER Drawing IIO. 036 ROV. 28 y

N

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[3 y" Q$ $U 3, yay Remarks CC660 3 C-9 X X 1.5 GA P1A LC L R CC661 3 C-9 X X 1.5 GA F1A ID L R CC662 3 C-9 X X 1.5 GA MA IC L R CC151* 3 E-lO X X X .75 SC SA ID S Q FORWARD FIDW TI:ST.

L R CC152* 3 E-lO X X .5 SC SA IC L R U

i CC153* 3 E-lO X X X .5 SC SA ID S H

Q FORWARD FIIM TEST.

L R CC154* 3 E-lO X X .5 SC SA If L R CCl49* 3 E-11 X X X .5 SC SA ID S Q FORWARD FIDW TEST.

L R CC150* 3 P-ll X X .5 SC SA If L R CCl48* 3 P-lO X X X .5 SC SA ID S Q FORWARD FIDW TEST L R CCl47* 3 P-lO X X .5 SC SA If L R CCl32* 3 11 - 1 0 X X X .75 SC SA ID S Q PORWARD FIDW TEST L R I

g CCl31* 3 11-10 X X .75 SC SA IC L R s I g

• TESTING REFLECTS flOletAL SYSTEM ALIGNt11'tJT. IF ALTEIOJATE ALIGNMENT IS USED, ALTERNATE VALVES WILL DE TESTED.

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DAVIS-IlESSE NUCl.EAll POWEll STATIOt1 UNIT t10. 1 page VAI.VE TEST PROGitAM 3 o f _L System COMPONErrr COOI.It1G WATER Drawing flo. 036 POV. 28 y Valve

$ $7

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L R CCl34* 3 11 - 1 1 X X .75 SC SA LC L R CCl 36

• 3 G-9 X X X .75 SC SA ID S Q FORWAftD FIDW TEST.

I. R CCl35* 3 G-lO X X .75 SC SA If L R CCl37* 3 G-10 X X X .75 SC SA LO S Q FORWARD FIDW TEST.

C L R CCl30* 3 G-10 X X .75 SC SA LC L R CC244 3 E-11 X X .75 GL MA If L R CC242 3 E-11 X X .75 GL 11A ID I. R CC241 3 E-ll X X .75 GL MA LC L R CC243 3 E-11 X X 75 GL MA ID L R CC239 3 E-12 X X .75 GA MA ID L R CC237 3 E-12 X X .75 GA MA LC I. R CC238 3 E-12 X X .75 GA MA ID L 11

.3 CC240 3 E-12 X X .75 GA MA If L R s

Y *TESTItiG REFLECTS NORMAL SYSTEM ALIGNMENT. IF ALTERNATE ALIGNMFNT IS USED, ALTERNATP val.VES WILL BE TESTED.

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DAVIS-IIESSE NUCI, EAR POWER STATIOPJ UtJ IT tJO. 1 VAINE TEST PROGRAti Page 6 of G System COMPONENT COOLING WATER Drawing flO. 036 UOV. 28 E N $7

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ONE PUMP IS AN INSTALLED SPARE AND El.ECTRICALLY DISCONNECTED. TIIE VALVES ASSOCI ATED WITil TIIE INSERVICE PUMPS WILL BE IN TI!E OPEN POSITION AND TESTED AS PASSIVE.

N 8

DAVIS-IlESSE NilCI. EAR POWEll STATION tlNIT NO. 1 Page 1 of 2 VAI.VE TEST l'ROGRAM System REACTOR COOI. ANT SYSTEM DFTAII.S Drawing flO . 040A ROV. 26 E N .0 7 y valve _ n e $ $ $ b 8@

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--6W l-31 3

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2. Specific Crde Exceptions

a. Code Exception Number 1

. . Components: MS100, MS101

. Function: Main Steam Isolation Valve -

. Class: 2

. Test Requirements: Quarterly stroking Basis for Exception: Cycling valve during normal operatien results in loss of main steam to turbine which causes a reactor trip.

. Alternate Testing: Valve will be full stroke tested during cold shutdown. Partial stroking during normal operation is not possible because partial stroking can only be performed locally at the valve. If valve was to inadvertently fail close during test, the main steam reliefs would lift. The local test statien is located in the ar-a which fills with steam from the main steam reliefs. Entry into area is strictly controlled during operation. No remote partial stroke capability is available.

b. Code Exception Number 2 1 Deleted II-59 j Rev. 1-11/80 V

/

c. Code Exception Number 3 Deleted

d. Code Exception Number 4

. Components: AT39, AF43, AF72, AF73, AF74, AF75 -

. Function: Auxiliary feedwater check valves to tht:

steam generators

. Class: 3 Test Requirements: Quarterly forward flow stroking Basis for Exception: Cycling valve would require injection of auxiliary feedwater into the steam generator which would thermal shock the auxiliary feedwater no::les.

. Alternate Testing: Valve will be partial stroke forward flow cycled during refueling when the steam generator is cold. Valve cannot be partial strcked during normal operation or full stroked at any time without injecting auxiliary feedwater into the steam generator and thermal shocking the auxiliary feedwater no::les.

e. Code Exception Number 5 l

l

. Components: FW601, FW612 I

l . Function : Main feedwater isolation valve to the steam generator II-60 Rev. 1-11/80

. Class: 2 Test Requirements- Quarterly stroking

. Basis for E;::eption: Cycling valve during normal operation would cause loss of main feedwater to steam generator which would cause reactor trip.

. Alternate Testing: Valve will be full stroke tested at cold shutdown. Valve design precludes partial stroke testing during normal operation,

f. Code Exception Number 6 Ocleted 9 Code Exceptien Number 7 Deleted 1

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II-61 i

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Rev. 1-11/80 1

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. Alternate Testing: Valve will be verifiec for freedom of valve movement at cold shutdewn. Valve design precludes partial stroking during normal ope ration.

j. Code Exception Number 10 Deleted

k. Code Exception Number 11

. Components: RC10

. Function: Pressurizer spray control

. Class 1

. Test Requirements : Quarterly stroking and timing

. Basis for Exception: Failure of valve in the closed position would result in loss of reactor coolant system pressure centrol which is required during normal operation. ,

. Alternate Testing: Valve will be full stroke tested during cold shutdown. Valve design precludes partial stroke testing during normal operation.

II-63 Re v. 1-11/80

1. Code Exception Number 12

. Ccmponents: RC2A

. Function: Pressurizer pressure control valve

. Class: 1

. Test Requirements: Quarterly stroking and timing

. Basis for Exception: Full strokinc cannot be visually verified en this valve since the valve mechanism is all internal. A test can be performed by closing the block valve and seeing if RC2A solenoid energizes and de-energizes properly. Stroke timing is impractical as the valve mechanism is all internal and the valve is pilot actuated. You can measure the position of the pilot but not of the valve itself. This is not a meter operated valve. There is nc fail-safe position of this valve. RC2A is tested in PT 5164.02, Pressurizer Power Relief Valve Periodic Test, in conjunction with ST 5030.04, RCS Pressure to the RPS Refueling Period Calibration Procedure, at least once per 18 months with the unit in cold shutdown (or refueling mode) . This test verifies that RC2A will open when its associated solenoid is energized and will close when the solenoid is de-energized. This test is normally run with the RCS pressure at 2155 psig but can also be performed at (2155 psig but > 500 psig in the RCS. This test also verifies that the scienoid associated with RC2A will be energized at a signal equivalent to an RCS pressure of 2400 + 16 psig and de-energized by a signal equivalent to an RCS pressure of 2350 + 16 psig.

This phase is run by simulating output 44gnals from the RPS to PSEL-RC2-5 in the NNI cabinets and verifying proper operation of the solenoid at RC2A. ST 5030.04 will verify that the instrument strings for the RPS pressure transmitters selectable for use in the NNI are calibrated from the pressure transmitters to the output of the RPS cabinets.

An acoustic monitor is used to verify valve opening and closing.

. Alternate Testing: Valve may be effectively part stroked during normal operation in response to pressurizer conditions. Valve will be full stroked at refueling during performance of plant procedure PT 5164.02 which also verifies pressure set point.

No valve timing is possible.

II-64 Rev. 1-11/80

m. Code Exception Number 13

. Cceponents: MU33

. Functi on: Nor=al makeup water to the Reactor Coolant System

. Class: 2 Test Requirements : Quarterly stroking

. Basis for Exception: Failure of valve in the closed position during test would result in total loss of normal makeup to the Reactor Coolant System. Makeup is required during normal operation.

. Alternate Testing: Valve will be cycled at cold shutdown when makeup water is not required. Valve design precludes partial stroking during normal operation.

II-64a Rev. 1-11/80 l

p. Code Exception Number 16

. Ccepenents: OH9A, OH93

. Function: Containment emergency sump isolation valve

. Class: 2

. Test Requirements: Quarterly stroking

. Basis for Exception: Cycling valve would introduce borated water from the borated water storage tank directly into the containment emergency sump. Valve is interlocked with DH7A (DH7B) and can only be tested when the bcrated water storage tank can be isolated.

. Alternate Testing: Valve will be cycled at refueling when the borated water storage tank can be isolated.

Valve cannot be partial stroke tested during normal operation without injecting borated water into the containment emergency sump.

q. Code Exceptien Number 17

. Components: CF28, CF29

. Function: Cere flood tank isolation check valve

. Class: 1

. Test Requirements: Quarterly forward flow stroking

. Basis for Exception: Forward flow cycling cannot be performed during normal operation or cold shutdown l when the Reactor Coolant System is filled and

pressurized to pressure greater than that of the core flood tank. Full stroke is precluded by system design.

. Alternate Testing: Valve will be part stroke tested at refueling when the contents of the core flood tank can be partially dumped into the Reactor Coolant System while monitoring i core flood tank level.

1 r

II-66 I

Rev. 1-11/80 l

A

t. Code Exception Number 20 Deleted

u. Code Exception Number 21

. Components: CC1411A, CC1411B, CCl407A, CC1407B

. Function : Component cooling water isolation valve

. Class: 2

. Test Requirements: Quarterly stroking

. Basis for Exception: Cycling valve during normal operation or cold shutdown requires shutting off cooling water to the reactor coolant pumps which would cause extensive damage to the purps. Cooling water to the reactor coolant pumps is required except at refueling.

. Alternate Testing: Valve will be full stroke tested at refueling. Valve design precludes partial stroke testing during normal operation.

I i

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II-68 Rev. 1-11/80 L

/

v. Code Exception Number 22

. Components: CC1460

. Function : Component cooling water isolation valve

. Class: 3

. Test Requirements: Quarterly stroking

. Basis for Exception: Cycling valve during normal operation or cold shutdown requires shutting of f cooling water to the makeup pump coolers which could cause damage to the pumps. Cooling water to the pumps can only be shut off during cold shutdown.

. Alternate Testing: Valve will be full stroke tested at cold shutdown. Valve design precludes partial stroke testing during normal operation.

w. Code Exception Number 21

- Components: CC156 7A, CC1567B

. Function: Component cooling water isolation valve

. Class: 2

. Test Requirements: Quarterly stroking

. Basis for Exception: Cycling valve would require shutting off cooling water to the control rod drives which can only be done at cold shutdown.

l

. Alternate Testing: Valve will be full stroke tested at cold shutdown. Valve design precludes partial stroke testing during normal operation.

l II-69 Rev. 1-11/B0

y. Code Exception Number 25

. Components: IA501, SA502, NN5 8, CV209, CV210, CV124, CV125, CF15, CF16, RC113

. Function: Containment isolation check valves .

. Class 1 or 2

. Test Requirements: Quarterly reverse flow stroking

. Bacis for Exception: Verification of reverse flow closing can only practicably be acccmplished by leak testing. This testing can only be performed at refueling.

. Alternate Testing: Valve will be reverse flow closure tested at refueling during the performance of an Appendix J, Type C, test,

z. Code Exception Number 26

. Components: MU2A

. Function: Letdown isciation valve

. Class 2

. Test Requirements: Quarterly stroking and timing

. Basis for Exception: If this valve were to fail in the closed position during testing, loss of normal letdown would result. Letdown is required to control reactor coolant inventory as the requd ' ed reactor coolant pump seal injection continuously adds water to the reacter coolant system. Access to the valve during normal operation is precluded

by high radiation.

l . Alternate Testing: Exercise valve and measure stroke time during cold shutdown when access to the valve is not prohibited.

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II-70a i

i Rev. 1-11/80 i

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aa. Code Exception Number 27

. Components: HP2A, HP2B, HP2C, HP2D

. Function: High pressure injection isolation valves

. Class: 2

. Test Requirements : Quarterly stroking and timing

. Basis for Exception: No pressure monitor devices I

are installed en the upstream side of these valves.

The upstream piping is isolated from reactor coolant system pressure by two check valves. Cycling these valves during normal operation may allow high pressure water to be released into the high pressure injection system.

. Alternate Testing: Valves will be stroked and timed at cold shutdown when the reactor coolant system is depressurized.

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II-70b Rev. 1-11/80 L

III. WELD, SUPPORT AND B7LTING INSPECTICN PROGRAM A. PROGRAM

SUMMARY

The Weld, Support and Bolting Inspection Prcgram identifies the nondestructive examination (NOE) requirements for all piping and component welds, supports and bolting within the boundaries of safety related systems, both those welds, supports and bolting examined in accordance with the requirements of Subsection IWB, IWC, or IWO, as appropriate, of the ASME Boiler and Pressure Vessel Code, 1977 Edition and Addenda through Summer 1978 Addenda and those welds, supports and bolting for which the Code require-ments have been found to be impractical. The Weld, Support and Bolting Inspection Program will be applicable for the remainder of the 120-month interval, which started on June 27, 1977 after which the Program will be reviewed and updated, as appropriate, with the Edition of the Code and Addenda in effect not more than 12 months prior to the start of the next 120-month interval. All examinations shall be conducted in accordance with Inspection Program B of Section XI.

The Weld, Support and Bolting NDE requirements are presented in Section 'C' by coded Weld and Support Inspection Program Tables, Component Nondestructive Examination Tables and Bolting Nonde-structive Examination Tables. The codes used for these Tables are defined in Section 'B'. The Weld and Support Inspection Program Tables of Section 'C' are arranged by system. Component Nondestructive Exanination Tables and Bolting Nondestructive Examination T' ables are arranged by Class and System. SecticT 'D'

provides justification for exceptions taken to Code examination requirements as provided for in 10 CFR 50.55a (g) (iii) .

All Class 3 welds and supports will be inspected to the require-I ments of Table IWD-2500-1 of the Code. The examination will be conducted to the extent practicable within the limitations of the component or system design and geometry. l 1

l III-l Rev. 1-11/80 i

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5. WEI.D , SUPPORT AND BCLTING INSPECTION PROGRAM TABLE TCPS TS

1. The Weld and Support Inspectien Tables are coded as follows:

a. Subsystem / Description. A brief description of the line segment under consideration.

b. Item Number. A unique number is assigned to each line segment sequentially in the direction of flow. If an alphabetic character is included in the part of the number af ter the dash (-) , the line segment is a branch.

c. Line Number. A non-unique number used to identify the line.

The first set of numbers shows the nominal piping diameter in inches. The second letter shows the material of construction as follows:

. B - carbon steel

. C - stainless steel

. D - copper

. R - carbon steel radwaste

. S - stainless steel radwaste

d. ISID. The Inservice Inspection Drawing on which the line segment is located,

e. Coordinates. The location on the ISID where one end of the line segment is found.

f. Normar Operating Pressure. The normal operating pressure in psig.

g. Normal Operating Temperature. The normal operating temperature in O F.

h. Material in5[4 Inches. A 'CS' indicates that the line segment is exempted from surface or volumetric examination per IWC-1220(c),

j[,4inchesnominalpipesize. This exemption is generally used for ferritic material only. AusIenitic material is exempted based upon(2-1/2 inches nominal pipe size. If the exemption of IWC-1220(c) (< 4" nominal pipe size) is used, " exempt per IWC-1220 ( c) " is placed in the Remarks column. These exemptions are applied to Class 2 piping only. Other Code Exemptions used in developing the Program were:

. IWB-1220(b) -Class 1pipingj[1inchnominalpipesize

. IWC-1220(a) - Class 2 piping maintained under static conditions of at least 80 percent normal operating pressure

! III-2 Rev. 1-11/80

B. WELD, SUPPORT AND BCLTING INSPECTICN PROGPM TABLE FCFF.ATS (continued)

1. Thickness. The nominal pipe wall thickness in inches.

j. Weld Inspection. The numbers in each column indicate the number of welds in the line segment which will be inspected -

by that method.

. VCL & SUR/VCL - The welds will be inspected by either volumetric and surface examination or by volumetric examination only.

. SUR - The welds will be inspected by surf ace examination.

. PRT - Pressure Test per IWB-5000 or IWC-5000 as applicable.

This is only used when no other weld examination is applied.

. F/T - Flow Test at 100 percent minimum rated flow. This is only used when no other weld examinaticn is applied.

Systems or pcrtions of systems that are full flow tested were exempted from volumetric and surface examination requirements per TECo response to I&E Bulletin 79-17.

Based upon TECo's full flow testing schedule and calculations of flow rates through the af fected systems, it was concluded that the full flow tested lines do not contain stagnant oxygenated borated water. Full flow is established in these lines at least once every 92 days. A system walk down is performed at least once every six months.

The' welds in the lines of the following systems are exempted frem volumetric or surface examination because these lines are subject to full flow testing:

l The welds in the lines of the Containment Spray System which include the suction lines from the Decay Heat Removal i

System to the containment spray pumps and the discharge lines from the containment spray pumps to the full flow l

test return lines.

The welds in the lines of the Decay Heat Removal System which include the suction lines from the berated water i storage tank to the decay heat pumps and the discharge lines from the decay heat pumps up to and including the safety related portion of the full flow test return lines.

III-3 Rev. 1-11/80

The welds in the lines of the High Pressure Injection System which include the suction lines from the Cecay Heat Removal System to the high pressure injection pumps and the discharge lines from the high pressure injection pumps to the full flow test return lines.

. A/T ' Air Test of open ended, normally dry pipe. This is -

only used when no other weld examination is applied.

k. Suppo rt Inspection. The numbers in each column indicate the number of supports which will be inspected by that me thod.

. SUR & VT The integral attachment weld will receive a surface examination, and the complete support will receive a VT-3 visual examination.

. SUR & VT The integral attachment weld will receive a surface examination, and the complete support will receive a VT-4 visual examination.

. VT The support which has no integral attachment weld and will receive a VT-3 visual examination.

. VT The support which has no integral attachment weld and will receive a VT-4 visual examination.

m. Remarks. This column is provided for pertinent information as appropriate.

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DAVIS-BESSE NUCIEAR POWER STATION PAGE 3 OF 3 REVIEWED BY , g.o DATE f/7/f0 UNIT NO. 1

/ ISID NO. 030 CLASS 1 SYSTEM _1MAWINLIWT REV. O, 2-15-80 COMPONENT SECTION XI SECTION e DRAWING BASE MAT'L O COMPONENT INFORMATION W/S DESCRIPTION NO.

ITEM THICKNESS $$ NOE NUMBER COORD NO. CAT. (INCHES) 3$ NO.

HAME: PRESSURIZER W llEATER TO DIAPilRAGM MK-28 TO MK-13 70 154598E I:-9 114 . 2 0 D-E NA VT-2 W SIIKI.L TO IDWl:R IIEAD t1K-4, 40 TO 154592f (25s) l 1 I-4 112.11 H-Il 4.750 MIN- VOL NUMBER: T2 MK-6 W SUIh;E NOZZIE TO IDWER IIEAD MK-8 1 1545951: C-7 113.30 n-D 4.750 MIN VOL TO MK-6 Il3.40 H-D DRAWING COORD: C-4 W SAFE Et!D TO SURGE NOZZIE MK-37 TO 1 154600E C-7 [15.20 D-F 1.344 NOM 5 MK-8 VOL &

ea SUR i DESIGN OPERATING PRESSURE 2750 psig Tsv.FERATURE 600 F i .

1

~

PREPARED.B /, L,[ j DATE(/ h [d COMPONENT NONDESTRUCTIVE EXAMINATION DAVIS-BESSE NUCLEAR POWER STATION REVIEWED BY p DATEf/7/fg UNIT NO. 1 CLASS 2 SYSTEM DECAY llEAT REMOVAI.

REV. O. 2-15-00 COMPONENT SECTION XI SECTIOtl ,

DRAWING BASE MAT'L d COMPONENT INFORMATION W/S DESCRIPTION NO.

ITEM TilICKNESS $$ NO1E NUMBER COORD NO. CAT.

{(INCIIES) 6$ NO.

NAME: DEACAY IIEAT W llEAD TO SIII:LL WELD A 1 D2552-6 NA Cl.20 C-A O.625 NOM VOL (19)

COOLER W SilEl.L IDNGITUDINAL WEl.tsS It AND II 2 D2552-6 NA NA C-A O.625 NOM (TYPICAL OF 2) VOL (lH)

(19)

NUMBER: E27- 1, E27-2 (2!)

W NOZZIE TO SilELI. WELDS C AND E 2 D2552-6 NA C2.lO C-H 0.365 NOM SUR (19) g W NOZZIE TO FLANGE WELDS D AND F 2 D2552-6 NA C5.ll C-F O.365 NOM SUR (19)

U^ " '

• W SiiELL 'IU FI.ANGE WEI.D G 1 D2552-6 NA u G-II Cl.10 C-A O.625 NOM VOL (19)

W NOZZLE REENFORCING PAD TO SilELL 2 D2552-6 NA (27)

NA NA 0.750 tHM SUR (18)

DESIGN OPERATING W SOCKET 'IU NOZZIE 4 D2552-6 NA C5.30 C-F- NA SUR (19)

PRESSURE 410 psig S SADDIE TYPE SUPPORT NOT WELDED 2 D2552-6 NA C 3. 20 C-C NA VT-3 (19)

TEMPERATURE 200 0F NO SECTION XI CATEGORY AND/OR ITEM NUMBER GIVEN IN TAlllE IWB-2500-1/IWC-2500-1.

EXAMINATION PERFOletED ON CNE COMPONEtJT ONI.Y.

(21) EXAMI NATIONIS ONE FOOT AT INTERSECTION Willi CIRCUMFERENTI AL WELD.

(27) VOLUMETRIC EXAMINATION PERFORMED FIOM ONE SIDE ONLY, SEE CODE EXCEPTION' NUMBER 3

. _. _ _ _ _ _ _ _ _ _ _ . . . . ~

._m. . . _ . _ . . _ _ __ _ _ . _ . . . . -

l

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k D. CODE EXCEPTIONS (Continued) i

3. Code Exception Number 3

. Components: Decay Heat Removal Cooler E27-1 and E27-2

. Function: Decay Heat Removal -

i

, , Class: 2 i

l . Test Requirement: Volumetric examination of shell to flange weld 'G' l

1

. Basis for Exception: On the flange side of the weld, the slope of

the base material precludes ultrasonie examination from this side of the weld.

j . Alternate Testing: Volumetric examination from one side of weld i only. (Refer to sketch) 1 t

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