ML20114D716
| ML20114D716 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/31/1992 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20114D714 | List: |
| References | |
| PROC-920831, NUDOCS 9209090275 | |
| Download: ML20114D716 (122) | |
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BROWNS PERRY IRICLEAR PLANT UNITS 1, 2 AND 3 INSERVICE TESTING PROGRAM FOR l' UMPS AND VALVES FOR T!!E SECOND 10-YEAR INTERVAL 9209090275 920831 PDR ADOCK 05000259 P pga
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l INSERVICI_IISTING PROGRAM _ FOR PlfMPS _AND VAINES Ovt .: Tennessee Valley Authority Address of Corporate Office: Knoxville Office Complex 400 Conmerce Avenue Knoxville, Tennessee 37902 Names and Address of lirowns Ferry Nuclear Plant i Nucicar Power Plants P.O.11ox 2000 Decatur, Alabama 35602 l
Applicable Nuclear Unitst 1, 2 and 3 Commercial Operation Dates Unit 1 - August 1, 1974 Unit 2 - March 1, 1975 Unit 3 - March 1, 1977 i
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TABLE OP CONTI:l{Il g I. INTRODUCTION / POLICY STATEMENTS II. PUMP AND VALVE INSERVICE TEST DESCRIPTIONS III. RELIEF REQUESTS IV. COLD SifUTDOWN TESTING JUSTIFICATIONS 2
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- 1. INTp0 DUCTION /p0LICY_ STATEMENTS i
i A. Introdnetton I
> Under the provisions of 10 CFR 50.55a, inservice testing of safety-related pumps and valves will be-performed in accordance with Section XI of the ASME Boller and Pressure Vessel Code and applicable addenda. Specific exceptions to these requirements are included here
- as Relief Requests. As specified in 10_CFR 50.55a(b) and 10 CFR 50.55a(g)(4)(ii), the effective edition of Section XI with regard to this program is the 1986 Edition for unita 1, 2 an'i 3. The effective I interval dates for this inservice testing program are September 1, 1992 to August 31, 2002. The program identifies the pump and_ valve inservice testing that will be. performed at Browns Ferry Hucicar Plant to comply with the requirements _of 10 CFR 50 and plant technical specifications. Where this program refers to specific paragraphs in Section XI, the paragraphs in the 1986 Edition are referenced.
B. ]h:22 Inservice Testljlg prontam The p.np test program shall be conducted in accordance with Subs tion IWp of Section-XI of the ASMC Boiler and pressure Vessel -
C ^> except where relief has bran requested under the provisions of 10 CF 50.55a(g)(5)(iii). Part II details the inservice testing program for all safety-related pumps at Browns Ferry Nuclear Plant.
Each parameter to be measured as well as specific notes concerning
- requeats for-relief-are also listed.
C. Valve Inservlee TestiDE prortam The valve test program shall be conducted in accordance with Subsection IWV of Section XI of the ASME Boiler and Pressure Vessel
, Code except where relief has been requested under the provisions of 10 CPR 50.55a(g)(5)(iii). The valve test program is included in part II.-
l 1. Catenory A Valves Valves for which seat leakage is important may generally be classified as preneure icolation valves (PIV), containment isolation valves (CIV), or both pressure and containment isolation valves (PIV/CIV). Containment isolation valves are tested in accordance with Cection XI requirements for category A-valves with the exception of the seat leakage tests (IWV-3420). The seat.
leakage testing of these valves (IWV-3421 through IWV-3425) meets the intent of Section XI, but the actual test methods shall be in accordance with the Browns Ferry Appendix J testing program.
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I. INTRODUCTION /p0ld,QY STATEMENTS (Continued)
C. Valve Inservice-.Testina. prorJam (Continued;
- 2. Ihermal Relief Check Valtgg . (TRCE21 i
l One penetration has been fitted with small check valves desi6ned !
) to relieve pressure due to thermal expansion of fluid between j normally shut isolation valves. TRCVs will be leak tested in-the ,
l closed position per Appendix J (10 CFR 50). :
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- 3. Excess Flow Chttk Valven Excess flow check valves are installed in lustrument lines j penetrating containment in accordance with Regulatory Guide 1.1.
! As such, the lines are sized and/or orificed such that offaite
- doses will be substantially below 10 CFR 100 limits in the event 1 of a rupture. Therefore, individuni leak rate testing of these i valves is not required for conformance with Appendix J 10 CFR 50
- requirements. Functional testing of valves to verify closure can j be accomplished by the process of venting the instrument side of the valve while the process side is under pressure. Such testing
- is required by Technical specification 4.7.D.1.d at lea.i once per 1 operating cycle. Testing on a more frequent basis is not feasible
! for several reasons. Instruments serviced by these valves frequently have interlock or actuation functions that would be l-interfered with should testing be performed during plant operation. Also, process liquid will be contaminated to some j degree, requiring opecial measures to collect flow from the vented j instrument side. Functional testing with verification that flow i is checked will be performed at least once per operatin6 cycle per i Technical Specification 4.7.D.I.d.
! 4 Fall-Safe Actualpig ,
i i Normal operation of all fail-safe valvt utilizes the fail-safe l actuator with the exception of MSIVs and Control Air. MSIVs and l Control Air valves are tested in accordance with IWV-3415.
l 5. .Gelerory e B-Paesive Valvea i These valves which have no Section XI testing requirements are j valves in r lety-related systems ' Sich are not required to change
- - position in order to accomplish their required safety function.
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- 1. 11fTRODUCTION/ POLICY S_ TAT 1;$' nil (Continued)
C. yalve .. Inservice Tutin.. P; or.nm (Continued)
! 6. f_gld Shutde31leplinn (CS1Q CSD valve testing as identifled by the licensee wil? ue conducted pursuant to the following conditions!
Valve testing will cownenc., as soon as possible, but no later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after reaching CSD conditions. Valve testing will proceed in a normal manner until all testing is complete or the unit is ready to return to power. A completion of all valve testing in NOT-a prerequisite to return to power. Any testinC not corryleted by the end of one cold shutdown will be performed during subsequent cold shutdowns, starting from the last test performed at the previous cold shutdown.
For planned cold shutdowns where ample time is availabic and testing all the valves identified for the cold shutdown test frequency in the IST program will be completed, exceptions to the 48-hour requirement may be-taken.
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i TI. PUMP AND */ALVE INSERVICE TEST ' DESCRIPTIONS -
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Valve Tvoes _ . Valve Actuator Tvegg Code Symbol Meaninn Code Mgan(ng GA Gate A0 Air Operator
-BP Butterfly. 11 Manual Operator
} BA Ball M0 Motor Operator J
l CK Cheak SELF Self Actuated GL Globe S Solenoid Operator AN Angle (Globe) X Explosive RD Rupture Disk !!O llydraulic Operator RV Relief Valve E/il Electro-liydraulic Oper.
SC Stop Check Cy1 Cylinder XFC Excess Flow Check PL Plug Valve Por'tions Valve Testing Reauirements Codg Meaning Gade Meaninn 0 Open Full Stroke Quarterly
-Q C Closed ST Stroke Time !
O/C Open or Closed LT Leak Test LO Locked Open LT(R) Leak Test in Reverse.
Direction 3 ' LO - Electrically RR Full Stroke Refuel Locked Open Cycle
.' Locked Closed FS Fail Safe Per-IWV-3415 til Throttled CSD Full Stroke Cold Shutdown CV Full Stroke Chack Valve
-Quarterly RV Relief Valve Per-IWV 3510 DT Destructive Test Per IWV 3610 1955C D
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BROWNS FERRY NUCLEAR PLANT PUMP TEST PROGRAM UNITS 1, 2 AND 3 Inlet Differential . Flow Vibration Bearing ' Observe Lube' Oil Pumo ,_ Class. Drawinc # Speed e Pressure Pressure- Rate Amolitude Temperature LevellPreifurg RHR (4) 2 4N811-1 NR. Q C Q PV-34 PV-1 PV-1 HPCI (1) 2 47WB12-1 Q Q Q Q PV-34 PV-1 Q RCIC (1) 2 4N813-1 Q .Q Q Q Pt-34 PV-1 Q CS (4) 2 4N814-1 NR Q Q Q PV-34 PV-1 PV-1 SLC (2) ? 47W854-1 NR- PV-2 PV-2 Q PV-34 PV-1 Q RHR5W (12) 3 4N858-1. NR Q (Note 2) 'Q Q PV PV-1 PV-1 4N859-1
-Diesel Fuel NC. 47W840-1 NR PV-2.5 PV-2,5 PV-2,5 PV-34 PV-1,3 PV-1 Transfer (16)
'NOTESh 1. Number in (' ' ) denote number of pumps per unit except for d'.RSW and diesel fuel transfer.
RHR$W pumps are. comon. There are eight diesel fuel transfer pumps for Units 1 and 2 diesel generators and eight for Unit 3 diesel generators.
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. 2. River level will be recorded for suction pressure for..the RHRSV pumps.
- 3. Legend ' NR - Not required to be measured by Section XI
-Q - Quantity measured in accordance with Section XI requirements ,
PV - Alternative testing specified in relief request in Part III of this program l
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CATEGORY.B - PASSIVE VALVES System RHRSW (23)- Drawing No.~-47E858-1 Valve Position p_ tawing Coordinates- 1 1-23-31 0 D-7 1-23-37 0 D-7 1-23-43 0 D-5 1-23-49' O D-5_
2-23-31 0 D-6 2-23-37 0 D-7.
2-23-43 0 D-4 2-23-49 0 D-4 3-23-31 0 D-7 3-23-37 0 ~D-7 3-23-43 0 D-5 3-23-49 0 D-4 l
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CATEGORY B - PASFIVE VALVES System: RAW COOLING WATER (24) Drawing No. 47E844-2~
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Valve Position' Drawina Coordinates '24-706 LC= F-8,E-3,E-3 ,
1 24-729 LC F-4,F-2,G-3 l l
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1 CATEGORY 11 - PASSIVE VALVES -
i System: SLC (63) Drawing No. 47E854-1
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Valve Position Drawing Coordinates
- 63-12 0 C-7
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63-502 LC F-3
I j 63-511 LC D-5 63-515 LO E-5 l
63-517 LO E-4
l 63-522 LC D-6 63-524 LO E-7 i
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CATEGORY B - PASSIVE VALVES.
Systems EECW (671 Draving'No. .4_21859-1 l
Valve Position Drawing Coordinatta 0-67-13 0 F-7 0-67-14 0 B-7 0-67-17 0 G-5 0-67-18 0 C-5 0-67-21 0 G-1 0-67 0 0-3 0-67-25 0 G-3.
0-67-26 0 C-2 67-504 C C-7 67-505 C C-7
CATECORY B - PASSIVE VALVES g
t System -HPCI (73) Drawing No. 47E812 T Valve f.gsition Drawinz Coonlinates
'/3-34 0 F-6 73-25 0 B-6 73-64 0 D-8 73-592 LO F-2 73-593 LO F-2' 73-58 (C Passive) C F-3 73-600 (C Passive) C F-3 1
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CATEGORY B - PASSIVE VALVES System: RCIC (71) Drawing No. 47E813-1 l'
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i yJLlY.s Position DrawinR C00rdinatPJ
. 71-16 0 B-7 .
71-37 0 F-5 71-570 LO- F-1 t
B 71-571 LO- E-1 71-588 C B-3 i
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CATECORY B --PASSIVE VALVES System: RHR (74) Drawing No. 47E811-1 yg m Positio.D Drawinem Coordinates 74-55 0 F-6 74-49 0 F-5
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74-69 .0 F-4 74-670 LC E-5 74-624 LC E-8
, 74-22 0 D-8 74-10 0 B-8 74-570A LC B-7 74-570B LC - C-3 74-570C LC C-7 74-570D LC C-3 74-525A LC B-6 4- 74-525B LC C-4
- 74-525C -LC C-6 74-525D LC- B-3 74-532A LC B-6 i
74-532B -LC- _B-4 74-532C LC B .
-- 74-532D LC B-4 i i
- 74-765A LC -B-5 'l l
74-765B LC B-4 1
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CATEGORY B --PASSIVE VALVES System: ElLR (74) Drawing No. 47E811-1
. Valve Position Drawinc. Coordinates 74-33 0 C-1 74-44 0 C-1 74-86 0 C-6 74-87 0 D-7 74-89 0 D-3 74-90 0 C-3 74-91 C D-3 74-817 0 F-7 74-46 C D-2 74-85 0 D-5 74-88 0 D-5 74-575A C B-7 74-575B C C-2'
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i 1 CATEGORY B - PASSIVE VALVES-1 i System: Core Sprav (75) Drawing No. 47E814-1 l4 1
l f Valve- Position Drawing Coordinates-l 4
75-1 0 B-7 1
] 75-29 0 . B-8 ,
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) 75-11 0 B-6 1
75-30 0 B-3 75-39 0 B-4 I
s 75-17 0 D-6 t
' 75-18 0 E-6 1
l 75-8 0 D-5 4
75-10 0 E-5 1
l- 75-45 0 D-4 4
- 75-46 0 E-4 i
j_ 75-36 0 D-2 75-38 0 E-3 h
l 75-55 0 G-7 1
k i 75-27 0 --
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SROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3 System: Main Straarr (1)
Drawing No. 47E801-1 Relief Request /-
Drawing. Siza Valve Actuator Normal Safety Testing Cold Shutdown Valve ASME Required Justification Position Position Class Coordinates Category (in.) Type Type Number Function-G-7 6 RV SELF C 0 RV 1-4 Line A Relief 1 C 6 .RV SELF/ C 0 RV,Q PV-6 1-5 Line A Relief 1 G-6 BC G-5 A 26 GL A0 0 C Q,ST PV-27, 32 l 1-14 Line A Inbd Isol 1 LT FS CS-6 G-4 A 26 GL A0 0 C Q,ST CS-6 1-15 .Line A Outbd Isol 1 LT.FS F- ? 6 RV- SELF C 0 RV PV-6 l 1-18 Line B Relief 1 C F-7 6 RV SELF/ C 0 RV,Q PV-6 1-19 Line 8 Relief 1 BC G-6 6 RV SELF/ C 0 RV,Q PV-6 1-22' 'Line 8 Relief 1 BC 6 RV SELF 0 RY,0 1-23 Line B Relief 1 G-6 .C lC A 26 GL A0 0 C Q,ST TV-27, 32 1-26 Line B Inbd Isol 1 G-5 1T,FS CS-ti ,
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G-4 A 26 GL A0 0' C Q.ST .CS-6 1-27 Line B Outbd'Isol 1 LT,FS F-8 BC 6 RV SELF/ C. O RV,Q PV-6 1-30 Line'C Relief. 1 F-7 6 RV SELF/ C 0 RV,Q. PV-6 1-31 Line C Relief 1 BC E-6 BC 6 RV SELF/ C. O RY,Q PV 1-34 Line C Relief 1 E-5 A 26' GL A0 0 C R.ST PV-27, 32 1-37 Line C Inbd Isol 1-LT,FS CS-6 l Q,ST CS-6 Line C Outbd Isol 1 E-4 A 26 GL A0 0 C 1-38 LT,FS l
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BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3 Sys ten: Main Stream (1)
Drawing No. 47E801-1 Relief Request /
Drawing Size Valve Actuator Nonnal Safety Testing l Cold Shutdown Valve ASME Number Tunction Class Coordinates Category (in.) Tvoe Type Position Position Recuired Justification 6 RV SELF C 0 RV PV-6 1-41 Line D Relief 1 E-7 C 1-42 Line D Relief 1 E-6 C 6 RV. SELF C 0 RV y'
1-51 Line D Inbd Isol 1 E-5 A 26 GL A0 0 C 0.ST lPV-27,32 LT,FS C5-6 Line C Outbd Isol E-4 A 26 GL A0 0 C Q,ST CS-6 1-52 1
'LT.FS Drain Inbd Isol F-5 A 3 GA M0 C C Q.ST PV-20 1-55 1 LT i
Orain Outbd Isol F-4 A 3 GA MO C C Q,ST 1-56 1 LT 1-179 Line A Relief 1 G-6 C 6 RV SELF C 0 RV 1-180 Line D Relief 1- E-6 C 6 'V SELF C 0 R/
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BROWS rERRY NOCLEAR PLANT UNITS 1. 2, and 3 System: Demineralized Water (2)
Drawing No. 47E856 , Relief Request /
Valve ASME Drawing Sire Valve Actuator Normal Safety Testing Cold Shutdown N eber Function Class Coordinates Cateoorv (in.) Type Tvoe Positien Position Pecuired Justification 2-1192 Cont' Check 2 E-7 AC(P) i CK SELF C C LT 2-1383 Cont Isol 2 E-7 AC(p) GA H C C LT I i I
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BROWS TERRY NUCLEAR PLANT UNITS 1. 2. and 3 System: Reactor Feedwater (3)
Drawing No. 47E803-1 1 .
Relief Request /
Valv e ' ASME Drawing Sire Valve Actuator Normal Safety Testing Cold Shutdown-Number F;nction Class Coordinates Category (in.) Tyrg_Jype Position Position Recuired Justification 24 SELF' O C CV,LT PV-8 3-554 Line A Outbd Isol Check 1 G-C AC CK G-7 24 CK SFLF 0 0/C CV,LT PV-8 3-558 Line A Inbd Isol Check 1 AC F-6 24 CK SELF 0 C CV.LT PV-8 3-568 Line B Outbd Isol Check 1 AC ,
F-6 AC 24 CK. SELF 0 O/C 1 CV,LT PV-8 3-572 Line A Innd Isol Check 1 i
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BROWNS FERRY NUCLEAR P!./JJT UNITS 1, 2, and 3 System: Main Stream Relief Valve (10)
Drawing No. 47E817-1
! Relief Request /
Valve ASME Drawing Sire Val-e Ac tuatt,rlNonnal Safety- Testing Cold Shutdown Number Function Class Cocrdinates Cu tec,or y (in.) Tvoe Type fosition Positio- Recuired Justification 10-529 Tail Pipe J Vac Relief NC D-1 C 10 CK SCLF C 0 CV PV-7 10-530 Tail Pipe K Vac Ralief NC E-1 L 10 CK SELF C 0 CV PV-7 10-531 Tail Pipe L Vac Relief .NC D-1 0 10 CK SRF C 0 CV PV-7 10-532 Tail Pipe M Vac Relief NC D-1 C 10 CR SELF C 0 CV PV-7 10-533 Tail Pipe N Vac Relief f4 D-1 C 10 CK SELF C 0 CV- PV-7 I
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I BROVNS FERRY NUCLEAR PLANT UNITS 1, 2. and 3 System: Main Stream Relief Valve (10)
Drawing No. 47E817-1 Relief Request /
Valv e ' ASME Drawing Size Valve Actuator Normal Safety Testing Cold Shutdown Number Function Class Coordinates Catecory (in.) Tvoe - Tvoe Position Position Recuired Justification Tail Pipe A Vac Relief NC E-1 C 2-1/2 CK SELF C: O CV PV-7 10-506 Tail Pipe B Vac Relief NC D-1 C 2-1/2 CK SELF C. O CV PV-7 10-507 ,
Tail Pipe C Vac Relief NC E-1 C 2-1/2 CK SELF' C 0 CV- PV-7 10-508 10-509 Tail Pipe D Vac Relief' NC E-1 C, 2-1/2 CK SELF C 0 CV PV-7 10-510 Tail Pipe E Vac Relief NC D-1 C 2-1/2 CK SELF- C 0 CV PV-7 NC E-1 C 2-1/2 CK SELF C 0 CV PV-7 10-511 Tall Pipe F Vac Felief Tail Pipe G Vac Relief E-1 C 2-1/2 CK SELF C 0 CV PV-7 10412 NC Tail Pipe H Vac Reliet NC E-1 C 2-1/2 CK SELF C 0 CV ' PV-7 10-513 10-514 Tail Pipe J Vac Relief NC- D-1 C 2-1/2 CK SELF. C 0 CV PV-7 lail Pipe K Vac Relief NC E-1 C 2-1/2 CK SELF C 0 CV PV-7
- 10-515 l PV-7 10-516 Tail Pipe L Vac Relief NC D-1 C 2-1/2 CK SELF- C 0 CV Tail . Pipe M Vac Relief NC D-1 C 2-1/2 CK SELF C 0 CV PV-7
!10-519 Tail Pipe N Vac Pelief NC D-1 C 2-1/2 CK . SELF C 0 CV PV-7 10-520 Tail Pipe A vac Relief NC' E-1 C ,10 CK- 'SELF C 0 CV PV-7 10-521
' Tail Pipe.B Vac Relief- NC D-1 C 10 CK - SELF C 0 CV PV-7 10-522 Tail Pipe. C Vac Relief NC E-1 C. 10 CK SELF C 0 CV PV-7 10-523 Tail Pipe D Vac Relief NC E-1 C 10 CK: .SELF ' C 0 CV. PV-7 10-524 Tail Pipe E Vac Relief NC D-1 C 10 CK SELF C 0 CV PV-7 10-525 Tail Pipe F Vac Relief NC E-1 C 10 CK SELF C 0 CV PV-7 10-526 Tail Pipe G Vac Relief NC - E-1 C 10 CK SELF C 0 CV PV-7'10-527' 10-528 Tail Pipe,H Vac Relief NC 'E-1 C. 10 CK. SELF C 0 CV PV-7 ~
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r>ROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3 l System: Auxiliary Boiler (12)
Drawing No. 47E815-3 i L
Relief Request /-
Valve ASME Drawing Size Valve Actuator' Normal Safety Testing Cold Shutdown '
Number ' Function Class Coordinates Cateoorv fin.) Type Tvoe Position Position Recui red Justification 12-738 Blowdown to PSC Check 2 0-5 A(P) 2 CK SELF C C LT f 12-741- Blowdown to PSC Check 2 D-4 A(P) 2 CK SELF C C- LT t I
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BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3 System: Residual Heat Removal Service Water (23)-
Drawing No. 47E858-1 Relief Request /
Valve ASME Drawing Size Valve Actuator Normal Safety Testing Cold Shutdown Number function Class Coordinates Catecorv (in.) Tvre Type Position Position Pecuired Justification 23-34 RHR Ntx A Cooling Wtr Outlet 3 F-8 B 12 GL PO C TH Q,ST PV-12 23-40 RHR Htx C Cooling Wtr Outlet 3 H-8 8 12 GL MD C TH Q,ST PV 23-46 RHR Htz B Cooliu2 Wtr Outlet- 3 F-5 B 12 GL to C TH Q,ST PV-12 23-52 RHR Htx 0 Cooling Wir Outlet 3 H-5 8 12 GL to C TH Q,$T- PV-12 1-23-57 Standby Coolant 3 6-5 B 10 GA MO C O/C Q/ST 2-23-57 Standby Coolant 3 E-3 8 10 GA M0 C O/C Q/ST 0-23-502 Al Pump Disch Check. 3 B-5 C 18 CK SELF C O/C CV 0-23-504- Al-A2 Pump Crosstie 3 B-5 8 18 GA H 0 0/C Q 0-23-506 A2 Pump Disch Check 3 B-5 C 18 CK SELF C O/C CV 23-509 Htx A Supply Relief. 3 D-7 C 1 RV SELF C 0 RV l' 0 1-23-510 Htx A Inlet Che:k 3 E-7 C 16 CK SELF C- CV 23-516 Htx A Tube Relief 3 F-7 C~ 1 RV SELF C 0 RV 0-23-522 81 Pump Disch Check' 3 B-4 C 18 CK SELF C O/C CV' 0-23-524 B1-B2 Pump Crosstle 3 6-4 B 18 GA . H 0 0/C Q C-23-526 B2 Pump Disch Check 3 B-4 C 18 CK SELF C O/C CV 23-529 Htx B Supply Relief 3 E-5 C 1 RV SELF C 0 RV 1-23-530 Htx B Inlet Check 's E-5 C 16 CK SELF C 0 CV 23-536 Hts B T'ube Relief 3 'F-6 C 1 RV SELF C 0- RV 0-23-542 C2 Pump Disch Check 3 B-4 C 18 CK SELF C O/C CV 0-23-544- C1-C2 Pump' Crosstie 3 B-3 B 18 GA H 0 0/C Q 0-23-546 C1 Pump Disch Check 3 8-3 C 18 CK SELF C O/C ' CV
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,, s., , i BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3 System: . Residual Heat Removal Service Water (23)
Drawing No. 47E858-1 Relief Request /
Valve ASME Drawing Size Valve Actuator Nonnal : Safety Testing Cold Shutdown-Number function Class Coordinates Catecory (in.) Type Tvoe Position Position Recuired Jus ti fica tion 23-549 Htx C Sus. ply Relief 3 E-8 C 1 RV SELF C 0 RV 1-23-550 .Htx C Inlet Check 3 E-8 C 16 CK - SEl f C 0 CV 23-555 Htx C Tube Relief -3 H-6 C 1 RV SELF C 0 RV 0-23-561 D2 Pump Disch Check 3 B-4 C 18 CK SELF C O/C CV 0-23-563 D1-02 Pump Crosstie 3 8-3 8 18 GA H 0 O/C Q 0-23-565 D1 Pump Disch Check 3 8-3 C 18 CK SELF C O/C CV 23-568 Htu D Supply Relief 3 E-5 C 1 RV SELF. C 0 RV 1-23-569 Htx D Inlet Check 3 E-5 C 16 CK SELF C 0 CV 23-574 Htx D Tube Relief 3 H-6 C 1 RV SELF C 0 RV 2,3-23-579 Hts A Inlet Check 3 E-6 C: 16 CK SELF C 0 CV 2,3-23-580 Htx B Inlet Check 3 E-4 C 16 CK SELF C 0 'CV 2,3-23-581 Htx C Inlet Check 3 E-7 C 16 CK SELF C 0 CV 2,3-23-582 Htx D Inlet Cleck 3 E-4 C 16 CK SELF C 0 CV l
0-23-588 A3 Pump Disch Check 3 B-5 C '18 CK SELF C O/C CV 0-23-591 83 Pump Disch Check 3 'B-4 C 18 CK SELF C O/C CV 0-23-594- C3 Pump Disch Check 3 B-3 C 18 CK SELF C O/C CV 0-23-597 D3 Pump'Disch Check 3 B-2 C 18 CK SELF C O/C ' CV 0-23-601 Header C Check from R$W 3 E-4 C 1-1/2 CK SELF 0 C CV PV-13 0-23-603 Header A Check from RSW 3 E-4 C 1-1/2 CK SELF 0 C CV FV-13 0-23-605 Header B Check from RSW 3 E-3 C- 1-1/2 CK SELF 0 C CV PV-13 1-1/2 0- PV '
0-23-607 Huader D Check from RSW 3 E-3 .C CK SELF- C CW'
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- 4. 3 BROWNS FERRY NUCLEAR PLANT UNI'S 1, 2. and 3
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- Raw Cooling Water (24)
Drawing No. 47E844-2
!- 'l Relief Request / [
Valve- ASME Drawi n;r Sire Valve Actuator Normal- Safety Testing Cold Shutdove j
< Number- Function Class Coordi. nates Cateaory (in.) Tvoe Tvoe Position Position Recuired Justification l .0-24-712A Wtr Chiller A'Disch Isolation 3 E-8 B 6 GA H 0/C O/C 0 !
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0-24-7128 Wtr Chiller A Disch Isolation 3 E-8 8 6 GA H 0/C O/C Q 0-24-796 HVAC RM A Supply Check 3 F-2 C' 2 CK SELF 0 C CV PV-14 j 0-24-798 HVAC RM A Supply' Check 3 F-1 C 2 CK. SELF 0 C CV PV-14 t
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BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3 System: Control Air (32)
Drawing No. 47E1847-6 Relief Request /
Valve ASME Drawing Size Valve Actuator Normal Safety Testing Cold Shutdown-Number Function Class Coordinates Cateoorv (in.) Tvoe Type Position Position Reevired Justification 1-32-336 Outbd DV Check NC E-3 Ar. 1 CK SELF 0/C C CV,LT PV-22 1-32-2521- Outbd DW Check NC D-3 AC 3/4 CK SELF ' 0/C C CV,LT DV-22, l'
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System: Control Air (32)'
a Drawing No. 47E1847-9 l t
Rellef Request /' i Valve ASME Drawing Sire Valve Actuator Nonnal Safety Testing Cold Shutdown Number Function Class Coordinates Catecorv fin.) Type Tvoe Position Position Recuired Jus tification ,
h i 1-3242 DW Cmpsr Suction 1501 NC D-7 A 3 PL AO O C' Q.$T LT FS i 1-3243 DW Cmpsr Suction Isol NC D-7 A 3 PL A0 0 C Q,ST f 1 LT,FS !
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Drawing No. 47E1847-10 Relief Request /
ASME Drawing Size Valve l Actuator Nomal Safety Testing Cold Shutdown Valve Number function Class Coordinates Catecory (in.) Type Type Position Position Retrai red Justification D-5 AC CK SELF 0/C Cl CV.LT. PV-22 1-32-915 Inbd DV Check NC 1
BROWNS FERRY NUCLEAR PLANT UNITS 1, 2 and 3 System: Control Air (32)
Drawing No. 47E2847-5 Relief Request /
Valve ASME Drawing Size Valve Actuator Normal Safety Testing Cold Shutdown Number function Class Coordinates Category (in.) Tvoe Tvoe Position Position Recuired Justification 2-32-336 Outbd DW Check NC D-4 AC 1 CK SILF 0/C C CV,LT PV-22 2-32-2521 Outbd DW Check NC C-4 AC 3/4 CK SELF 0/C C CV,LT PV-2.2 1
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SROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3 System: Control Air (32)
Drawing No. 47E2847-8 Relief Pequest/
Valve ASME Drawing Size Valve Actuator Normal Safety Testing Cold $hutd yt Position Position Recuired Justification Number Function Class Coordinates Caterorv (in.) Tvoe Tvoe 2-32-62 DW Cmpsr Suction 15o1 NC G-4 A 3 PL: A0 0 C Q,ST >
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BROWNS FERRY NUCLEAR PLANT UNITS 1, 2 and 3 System: Control Air (32) ,
Drawing No. 47E2847-9 H Relief'Reque'st/
Valve ASME Drawing Size Valve Actuator Normal Safety Testing Cold Shutdown Number Functiou Class Coordinates Category (in.) Tvoe Tvoe Position Position Recuired Justification 2-32-2163 Inbd DW Check NC G-7 AC 1 CK SELF O/C C CV,t.T PV-22 Inbd DW CheE,k-2-32-2516 NC C-3 AC 3/4 CK SELF 0/C C CV.LT PV-22
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BRLbHS FERRY NUCLEAR PLANT LWITS 1, 2, and 3 System: Control Air (32)
Drawing No. 47E3PA7-$
Relief Revnest/
Valve ASME Drawing Size Valve l Actuator Normal Safety Testing Cold Shutdown Ntr6er Ft.me ti er. Class Coordie,a tes Catecery (in.) Tvre Twee -*?sitioe Positie, teesired Justificati n 3-32-62 W Cmpsr Svetion Isol NC E4 A 3 PL A0 0 C Q.ST LT.FS 3-32-63 W Cmpsr Suction Isol NC E-4 a FL A0 0 C O.57 LT,FS 3-32-336 Outbd W Check NC D-4 AC 1 Ca SELF C/C C CV LT lFV-22 1
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Drawing No. 47E3847-9
' Relief Request /
Valve ASME Drawing Size Vaive Act.itor Normai Safety Testing Cold Shutdown Number Function Class Coc-dinates Category (in.) Type Tyre Positien Fesition Recuired Justificati v 3-32-2163 Inbd DW Check NC H-7 AC 1 CK SELF 0/C C CV.LT PV-22 i
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Drawing No._47L610-43-1 Felief Reesest/
Valve A5ME Drawing Size Valve Actuator Normal Safety Testing Cold Shutdown
'hrd>e r Function Class Coordinates Category (ie.) Tee Twe Pesition Position Ce?; fred Justificatica 43-13 Reactor Recire Inbd Isol i H-4 A 1 GL A0 C C LT 43-14 Reactor Recire Outbd Isol 1 G-4 A 1 GL A0 C C LT 43-28A PSC Disch to RHR Pumps A&C 2 E-3 A T/2 GL 5 C C LT 43-23B PSC Disch to RHR Pumps A&C 2 D-3 A 1/2 GL $ C C LT 43-29A PSC Disch to RHR Furnps B&D 2 E-2 A T/2 GL 5 C C- LT 43-298 PSC Disch to EHR Pumps B&D 2 D-2 A 1/2 GL $ C C LT
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- Drawing No. 47E867-3 I Relief Request /
l Valve ASME Drawing Size Valve Actuator Normal . Safety Testing Cold Shutdown [
, Nir6er function Cl ass Coordinates Catecory (in.) Tree Tve* Positien position pemired Justification ;
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_. _ = _ t 1 l BROWNS FERRY MJCLE/-R PLANT UNI 75 1, 2, and 3 I-System: Emergency Equipment Cooling Water (67) I Drawing No. 47EB59-2 l Relief Request / Valve ASME Drawing Size Valve Actuator l Normal Safety Testing Cold Shutdown Nurber Function Class Coordinates Category On.) 7voe Tvoe Position Position recuired Justification 3-67-693 3A DG Cooler N Ndr Supply Check 3 C-7 C 4 CK SELF 0/C O/C CV PV-14 i
- 347-694 3A DG Cooler N Hdr Supply Check 3 C-6 C 4 CK SELF 0/C C/C CV FV-14 h 3-67-695 3A DG Cooler S Mdr Supply Check 3 C-7 C 4 CK - SELF 0/C O/C CV PV-14 j 3-67-696 3A DG Cooler S Hdr Supply Check 3 C-6 C 4 CK SELF 0/C O/C CV PV-14 !
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BRCA'NS FERRY NUCLEAR PLANT UNITS 1. 2. and 3 System: Emergency Equipnent Cooling Water (67) Drawing No 47E866-7 Relief Fequest/ Valve ASME Drawing Size Valve Actuator. Normal Safety Testing Cold Shuto m Number Function Class Coordinates Catecory (in.) Type Type Position Position Cewired Justificatica 3-67-761- 3A Water Chiller N Hdr 3 E4 C 6 CK SELF C O/C CV PV-14 Supply Cbeck t 3-67-762 3A Water Chiller N Hdr - 3 E-6 C 6 CK SELF C O/C CV FV-14 Supply Check { 3-67-764 3A Water Chiller S Hdr 3 E-6 C 6 CK 5 ELF C O/C CV FV-14 Supply Check 3-67-765 3A Water Chiller S Hdr 3 E-6 C 6 CK SELF C O/C CV PV-14 Supply Check l 3-67-769 34 Water Chiller Disch Isol NC ' E-6 B 6 EF H C 0 0 , 3-67-771 3B Vater Chiller N Hdr 3 G-5 C 6 CK SELF C O/C CV PV-14 Supply Check 3-67-772 38' Water Chiller N Ndr 3 G-5 C 6 CK SELF C- 0/C CV PV-14 Supply Check l 3-67-774 3B water Chiller S Ndr 3 G-5 C 6 CK SELF C O/C CV FV-14 I Supply Check t 3-67-775 3B Water Chiller S Mdr 3 G-5 C 6 CK SELF C O/C CV PV-14 ; Supply Check 3-67-779 3B Water Chiller Disch Isol NC A-6 B 6 EF H O/C O/C 0
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I I EROW';5 FERRY MJCLEAR FLANT LWITS 1, 2, and 3 System: Reactor Building Closed Cooling water (70) Drawing No. 47E822-1 Telief Fecuest/ Valve ASME Drawing Size Valve Actuator Nemal Safety Testieg Cold Shutdcwn N*rber Functien Class Ceordinates Catecorv (in.) Twe TWe PO!itic" Fesitice Fewired Justi8icati e 70-47 Cont Disch Isol 2 G-2 A 8 CA N O C Q.5T.LT C50-2 70-500 Cent Supply Check 2 G-2 AC 8 CK SEtr 0 C CV.LT P'/-15 l
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m SEC%NS FERRY MJCLEAR FLANT LNITS 1, 2. and 3 System: Reactor Core Isolation Ceoling (71) Drawing No. 47E313-1 Celief Remest/ Valve A5"E Drawing Sire Vaive Actuator Nomal Safety Testing Cold Shutdown Nebe r Functio, Class Cecrdiaates Category fin.) Tpe- Tvee P: si tim cesitien re cired Justificat4& 77-547 Min Flow Bypass Check 2 E-5 AC 2 Ca; SELF C O/C CV.LT FV 16 71-550 Turbire Enhaust Check 2 E-3/4 AC 10 CE SELF C GeC CV.LT FV-17 71- 2 9 CoMs F.rm f rom Barecet ric 2 G/H-8/9 C 2 SELF C C CV FV-29 Cend Check l CK 71-592 Vac P.r p Disch Check
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~52-I- - . - . .
BROWNS FERRY NUCLEAR PLANT UNITS 1. 2 and 3 System: High Pressure Coolant Injection (73) Drawing No. 47E812-1' Relief Fequest/ Valve ASME Drawing Size Valve Actuator Normal Safety l Testing Cold Shutdown Pesitice Position Pecuired J'es ti fica tien Number ,_ Function Class Coordinates Category fin.) Type Type 73-2 Steam Line Inbd Isol 1 G-7 A 10- GA MO O 0/C Q,ST.LT PV-20
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73-3 Steam Line Outbd Isol 1 G-6 A 10 GA PO b Q,ST,LT 73-6A Steam Line to Cond Drain 2 E-2 B 1 GA A0 . 0/C Q,ST 73-16 Turbine Steam Supply; 2 .G-2 e 10 GA N C 0 Q.ST 73-18 Turbine Stop 2 G-3 8 10 GA E/H C 0 Q ST.FS PV-23 73-23 Turbine Enhaust 2 D-7 AC 16 SC H/SELF C Orc CV.LT CSD-8 73-24 Turbine Cu Conds Pct Disch 2 0-6 AC 2 SC H/SELF C O/C CV,LT CSD-8 73-26 PSC Inbd Suction 2 B-6 A 16 GA M0 C O/C Q,ST.LT PV-20 73-27 PSC Outbd Section 2- G-5 A 16 GA M0 C O/C Q,ST,L? 73-30 ' Pump Min Flow 2 D-5 A 4 GL PC C O/C Q.ST.LT 73-34 OutbJ Injection Isol 2 F-5 9 14 GA MG 0 0 Q,ST 73-35 Pump Test Return to CST 2 F-6 B 10 G4 M0 C C Q,ST 73-44 Inbd Disch Isol 2 F-6 A 14 GA MO C: 0/C Q,ST 73-45 Testable Chet.t 1 E-6 AC 14 CK A0/SELF C O/C CV.LT CSD-4 73-81 73-3 eypass 1 G-6 A 1 GL MO O C Q,ST.LT 73-505 CST Suction Check 2 H-5 C 14 CK SELF C C CV PV-29 73-506 Pump Suction Relief 2 G-4 C 1 RV SELF t 0 RV 73-517 PSC Suction Check 2 B-6 C 16 CK S :.F C C CV PV-19'
- 73-559 Min Flow Bypass Check 2 0-5 AC 4 CK SELF C O/C CV/LT PV-16
i EROWNS FERRY NUCLEAR PLANT LNITS 1, 2, and 3 System: High Pressure Coolant Injection (73) Drawing No. 47E812-1
' Relief Request /
Valve ASME Drawing < Size Valve Actuator Normal Safety Testing Cold Shutdown Nurter , Function Class Ceordinates Ca tecorvf;f in. ) Tvoe Tvoe Position Position Fecuired Justification , 73-574 Cooling Water to Gland Seal 2 F-7/8 C 1 RV SELF C 0 RV Cond Relief 73-603 .Turb Enhaust Check 2 D-7 AC 20 CK SELF C O/C CV/LT W-17 73-609 Turb E=naust Drain Check 2 D-6 AC 2 CK SELF C' C LT PV-17 73-625 Gland Cond Return Check 2 G-7/8 C 2 CK SELF C C CV PV-29 73-633 Turbine Exhaust Vac Relief 2 E-T C 2 CK SELF C O/C CV PV-18 73-634 Turbine Exhaust Vac Relief NC E-1 C 2 CK SELF C O/C CV W-18 73-635 Turbine Enhaust Vac Relief 2 E-1 C 2 CK $ ELF C O/C CV PV-18 73-636 Turbine Exhaust Vac Relief NC E-1 C 2 CK $ ELF C C/C CV PV-18
-7 BROWNS FERRY NUCLEAR PLANT 174ITS 1, 2, and 3 System: Residual Heat Removal (74)
Drawing No. 47E811-1 i Relief Request / Valve ASME D awing Sire Valve Actuator Normal Safety Testing Cold Shutdown i Nu-ser - Function Class Coordinates Category (in.) Tvoe Tne position Position Pe d red Justification ) t 74-1 Pump A PSC Suction 2 B/C-5 8 24 GA- fo 0 0/C Q,ST 74-2 Ps.cip A SD Cooling Suction 2 C-6 6 20- GA. ' M0 C O/C Q,ST 74-7 Loop I Min Flow 2 0-6 B 4 GA M0 O 0/C 0,ST 74-12' Pump C PSC Suction 2 D-5 B 24 GA M0 O 0/C 0,ST 74-13 Fump C SD Cooling Suction 2 D-5/6 B 20 GA M0 C O/C Q,ST 74-24 Pump C PSC Suction 2 C/D-4 8 24 GA MO O 0/C ' Q,ST ! 74-25 Pump B SD Cooling Suction 2 D-4 B- 20 GA N C O/C Q/ST 74-30 Loop II Min Flow 2 D/E-3 B 4 GA MO O 0/C 0,ST 74-35 Pump D PSC Suction 2 B4 8 24 GA M0 O 0/C Q,ST 74-36 Pump D SD Cooling suction 2 C-4 B 20 GL M0 C O/C 0,ST 74-47 SD Cooling Outbd Isol 1 E-5 A 20 GA MO C C/C 0,$T.LT CSD-5 74-48 SD Ceoling Irbd Isol 1 E/F-5 A 20 GA M0 C O/C Q,ST.LT CSU-S 74-52 Loop I Throttle 2 F-7 8 24 AN M0 O O Q,ST 74-53' Loop I Injection 1 F-6 A 24 GA MO C O/C Q,ST.LT 74-54 Loop'I Testable Check 1 F-6 AC 24 CK: AC/SELF- C O/C CV,LT PV-25 t + 74-57 Loop I PSC Return 2 F/G-7/8 A 18 CA' M0 C O/C Q,ST,LT i f 74-58 Loop I PSC Spray 2 F-7/8 A 4 GL' N C O/C Q,ST.LT d
- 74-59 Loop I Pump Test Return 2 F-8 A. 12 GL' M0 C O/C Q,ST.LT F g j.
74-60 Loop I Cont Spray Outbd Isol '2 G-6 A 12 GL . NO C O/C Q.ST LT
'74 Loop I Cont Spray Inbd Isol 2 G-5 A 12 GL MD C O/C Q,ST,LT PV-20 t 74-66 Loop II Throttle 2 F-3 8 24 AN- MO O- 0 Q,ST l
l 74-67 Loop .II' Injection i F-3 A 24 GA .. M0 C O/C Q,ST,LT r i i i
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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . __ . _ _ _ _ _ _ _ _ _ __ _ = . _ _ _ _ _ . . - _ _ _ . . __.._. m _ _ . _ . __ _. EROWNS FERRY NUCLEAR PLANT UNITS 1. 2, and 3 System: Residual Heat Removal (74) Drawing No. 47E811 I Relief Rec-;est/ i Testing Cold Shutdewn ' Valve ASME Drawing Sire Valve Actuator Normal Safety Number Fuaction Class Coordinates Category (in.) Tvoe Tyre Position Position Perni red hstification 74-63 Loop II Testable Check 1 F-4 AC 24 CK A0/SELF C O/C CV.LT PV-25 74-71 Loop II PSC Return 2 G-2 A 18 GA NO C O/C Q.ST.LT 74-72 Loop II PSC Sj .- 2 F-2 A 4 GL' MO C O/C Q,ST,L7 74-73 Loop II Pump Test Return 2 F-2 A 12 GL ' M0 C O/C Q,ST,LT 74-74 Loop II Cont Spray Outbd 2 G4 A 12 GA M0 C O/C Q.ST LT 74-75 Loop II' Cont Spray Inbd 2 G-5 A 12 M MD C O/C Q,ST.LT, FV-70 2-74-% Pump A Suction Crosstie ,2 C-5 B 14 GA N C 0 Q.ST 3-74-96' Pump A Suction Crosstie 2 C-5 B 14 GA N C 0 Q,ST 2-74-97 Pump C Suction Crosstie 2 C-5 B 14 GA N C 0 Q,ST 3-74-97 Puep C Suction Crosstie 2 C-5 B 14 GA N C 0 Q,ST 1-74-98 Pump B Suction Crosstie 2 C-4 S 14 M N C 0 Q,ST 2-74-98 Pump B Suction Crosstie 2 C-4 B 14 GA MO' C 0 0.ST 1-74-99 Pump D Suction Crosstie 2 C-4 5 14 GA M0 C 0 Q,ST 2-74-99 Pump D Suction Crosstie 2 C-4 6 14 GA M0 C 0 0.5T 2-74-100 Hta A4 Crosstie to U-1 B-D Hts 2 C-8 8 10 GA M0 C- 0 Q.ST l 3-74-100 Hta A-C Crosstie to U-2 B-D 2 C-B B 10 GA MO C 0 Q,ST 4 1-74-101 Htz B-D Disch Crosstie 2 D/E-1 S 10 GA N C C Q,ST S 2-74-101 Htm B-D Disch Crosstie 2 C-1 9 10 GA N C' O Q,ST i' i i !- , li '. i i 5 i-i i _ , - ,. _ . . . , _ _ _ . _ _ , , _ . - - .-_ _ . ~ - , . . . _ -__ __ _ . . .
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! BT'J W5 FERRY NUCLEAR PLANT LHITS 1. 2, and 3 i System: Residual Heat Removal (74) j D/ awing No. 47E311-1 t Relief Reesest/ j Valve ASME Drawing Sire Valve Actuator Normal Safety Testing Cold Shutdown Nuwter Function Class Coordinates Catecorv fin.) Type Tyre Positice Position Decuired Justificatica 74-509A Pump A Suctica Relief 2 B/C-6 C 1 RV SELF C 0 RV i 74-5038 Pump B Suction Relief 2 B-4 C 1 cv SELF C 0 RV i 74-509C Pump C Suction Relief 2 D-6 C 1 RV SELF C 0 RV , 74-5090 Pump D Suction Relief 2 B-3 C 1 RV SELF C 0 RV ! 74-559A Pump A Di ch Check 2 B-7 C 20 CK SELF C O/C CV 74-5598 Pep B Disch Check 2 CID-3 C 20 CK SELF C O/C CV 1 74-559C Pump C Disch Check 2 C/D-7 C 20 CK SELF C O/C CV f k 74-5590 Pump D Jisch Check 2 B-3 C 20 CK SELF C O/C CV y 74-560A Pump A Min Flow Bypass Check 2 B/C-6 C 3 CK SELF C O/C CV I 74-560B Pump B Min Flow Bypass Check 2 D-3 C 3 CK SELF C O/C CV 74-560C Pep C Min Flow Bypass Check 2 0-6 C 3 CK- SELF C O/C CV 74- W D Pump D Min Flow Bypass Check 2 B-3 C 3 CK SELF C O/C CV 74-578A Htx A' Relief 2 B-7. C 1 RV SELF C 0 RV 74-5788 Htm B Relief 2 D-2 C 1 FV SELF C 0 RV 74-578C Htz C Relief 2 C-7 C 1 RV , SELF- C 0 PV 74-5780 Htu D Relief 2 B-2 C 1 RV SELF C 0 RV ! i 74-S87A Loop I Disch Hdr Relief 2 G-7 C 1 RV SELF C 0 RV 74-587B' Loop II Disch Hdr Relief 2 G-3 C 1 RV 1 SELF C 0 RV
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74-659 SD Coeling Supply Relief 2- E-5 C 1 RV SELF C 0 RV [ 74-661 Thereal Relief Check 1 F-5 AC 3/4 CK. SELF C O/C CV.LT PV-28 i 74-662 Thermal Relief Check 1 F-5 AC 3/4 CK SELF C O/C CV.LT ' FV-28 f 74-722 PSC Drain 2 E-3/4 A(P) 8 GA HAND C C LT l l I I [ i
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. NS FERRY NUCLEAR PLANT LHITS 1, 2, and 3 System: Core Spray (75)
Drawing No. 47E814-1 Felief Request./ Valve ASME Drawing $ize Valve Actuator Normal Safety Testing Cold Shutdown Npber Function Class Coordinates Otecory fin.) Type Type Position Position Petd red J stification 75-9 Loop I Min Flow 2 E/F-5 8 3 GA MO O 0/C Q,ST 75-22 Loop I Pump Test. 2 F-5 B 10 GL M0 O C Q.57 75-23 Loop I Injection 2 F-5/6 B 12 GA' MO O O Q.5T 75-25 Loop I Injection . 1 F-6 A 12 GA. MD 0 0 0,5T LT 75-26 Loop I Testable Check i F-7 AC 12 CK AC/SELF C O/C CV/LT FY-25 75-37 Loop II Min Flow 2 E-4 8 3 GA MO O 0/C Q.57 75-50 L.oop II Pump Test 2 F-4 B 10 GL MO C C Q ST ,75-51 Loop II Injection 2 6-6 B 12' GA M0 O O Q.57 75-53 Loop II Injection 1 G-6 A 12 GA' MD C O/C Q,ST.LT 75-54 Loop II Testable Check 1 C-7 AC 12 CK A0/SELF C O/C CV/LT PV-25 75-57 Drain Pump A Inbd Isol 2 B-4 A 3 GA' A0 0 C Q,5T.LT 75-58 Drain Pump A Outbd Isol 2 B-5 A 3 GA A0 0 C Q.57,LT 75-507A Pump A Suction Relief 2 C-4 C 1 RV SELF C 0 FY 75-507B Pump B Suction Relief 2 C-2 C 1- KV SELF C 0 FV 75-507C Pumo C Suction Relief 2 C C 1 FV : SELF C 0 RV 75-507D Pump D Suction Relief 2 C-4 C 1 RV SELF C 0 RV 75-537A Pump A Disch Check 2 D-4 C 12 CK SELF C O CV 75-537B ' Pump B Disch Check 2 D-3 C 12 CK ' SELF C 0 CV 75-537C Pump C Disch Check 2 D-6 C 12 CK SELF C 0 CV 75-537C Psmp'D Disch Check 2 D-4 C 12 CK ' SELF C 0 CV 75-543A Loop I Disch Relief 2 F- ' C 1 RV : SELF C. O RV 75-543B' Loop II Disch Relief 2 E-4 C 1 RV SELF C 0 RV
__m mo _ = - . - - - _ --. -- - - . . . BRLWNS FERRY NUCLEAR PLANT UNITS 1, 2. and 3 System: Core Spray (75) Drawing No. 47E814-1 l Relief Reesest/ Valve ASME Drawing - Size Valve Actuator Normal Safety Testing Cold Shutdown
* -wter Function Class Coordinates Cateeory (in.) Type Twee Pesitico Position FeTJired Justification 75 'iM S w A Min F1cw Bypass Check 2 D-4/5 C 3 CM SELF C O/C CV 75-5M. Pump B Min Flow Bypass Check 2 D-2 C 3 CK SELF C O/C CV 75-570C Pump C Min Flow Bypass Check 2 0-6 C 3 CK SELF C O/C CV 75-570D Pump D Min Flow Bypass Check 2 D-4 C 3 CK SELF C O/C CV 75-606 Loop I Fill from Hd Tank 2 F-5 AC 2 CK- SELF 0/C C CV,LT CSD-10 75-607 Loop I Fill from Hd Tank 2 r-5 AC 2 CK SELF 0/C C CV.LT CSD-10 75-609 Loop II Fill from HJ Tank 2 H-4/5 AC 2 CK SELF 0/C C CV,LT CSD-10 75-610 Loop II Fill from W 'ank 2 H-4 AC 2 CK SEL? O/C C CV.LT CSD-10 9
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M BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3 System: Contaimnt Inerting (76) Drawing No. 47E1619-76-3 47E2610-76-3
'47E3610-76 '
3 Relief Request /- Valve ASME Drawing Size Valve Actuator Normal Safety Testing Cold Shutdown Number Function Class Coordinates Catecory fin.) Tvoc Tvoe Position Posi tion Ree; ired Justification 76-49 DW H2 Analyzer A Inbd Isol 2 A-7 A 1/2 GA S 0/C O/C Q,ST,LT PV-23 76-50 DW H2 Analyrer A Outbd Isol 2 A-7 A 1/2 GA S 0/C O/C Q,ST,LT PV '3 1,3-76-51 DW 02 Analyzer A Outbd Isol 2 D-7 A 1/2 GA 5 0/C O/C Q,ST.LT PV-23 1,3-76-52' DW 02 Analyzer A Inbd Isol 2 D-7 A 1/2 GA S 0/C O/C- Q,ST,LT PV-23 1,3-76-53 PSC 02 An&ly2er A Inbd Isol 2 C-7 A 1/2 GA 5 O/C O/C Q,ST,LT PV-23 1,3-75-54 PSC 02 Analyzer A Outbd Isol- 2 C-7 A 1/2 GA S 0/C 9/C Q,ST.LT PV-23 76-55 PSC H2, Analyzer A Inbd Isol 2 B-7 A 1/2 GA 5 O/C 0. *C 0,ST LT PV-23 76-56 TSC F2 Analyzer A Outbd Isol 2 B-7 A 1/2 GA S 0/C O/C Q,ST.LT PV-23 f 76-57' PSC Return Inbd Isol 2 B-7 A 1/2 GA - S ? s- O/C Q,ST,LT PV-23 . 76-58 PSC Return Outbd'Isol 2- B-7 A 1/2 GA S 0 0/C Q,ST LT PV-23 76-59 DW H2 Analyzer. B Inbd Isol 2 E-7 A 1/2 GA S 0/C O/C Q,ST,LT PV 76-60, DW H2 Analyzer B Outbd.Isol. 2 E-7 A 1/2 GA -5 O/C O/C Q,$T,LT PV-23 11,3-76-61 DW 02 Analyzer B Inbd Isol. 2 G-7 A 1/2 GA S 0/C O/C - Q,$T,LT PV-23 1,3-76-62 DW 02 Analyzer B Outbd Isol 2 G-7 A- ' 1/2 GA S 0/C O/C Q,ST.LT PV-23 1,3-76-63 PSC 02 Analyzer B'Inbd Isol 2 G-7 A 1/2 GA S 0/C O/C , Q,ST.LT PV-23 1,3-76-64 PSC 02. Analyzer B Outbd Isol . 2 G-7 A 1/2 GA 5 O/C O/C Q,ST.LT PV-23 76-65 PSC H2 Analyzer B Inbd Isol - 2 F-7 A 1/2 GA S 0/C O/C Q,ST,LT PV -23 l. 76-66l PSC H2 Analyrer B Outbd Isol 2 F-7 A 1/2 GA ' S 0/C O/C Q,ST,LT PV-23
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76-67: PSC Return Inbd Isol d'2 B-7 A l/2 GA S 0 0/C Q,ST,LT PV-23 76-68 PSC Return Outbd Isol 2 B-7 A 1/2 GA S 0 0/C 7,ST,LT PV-23 I l
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w . BROW'G FERRY NUCLEAR PLANT UNITS 1, 2. and 3 System: Containment Inerting (76) Drawing No. 47E860-1 Relief Request / Valve ASME Drawing . Size Valve Actuator Normal Safety Testing Cold Shutdown Number Function Class Coordinates Cateoory fin.) Tvoe Type Position Position Recui erf Justification 76-17' r Cont N2 Makeup- 2 C-5 A 2 BF CYL 0/C C Q,ST,LT 76-18 DW N2 Makeup Inbd Isoi 7 C-6 A 2 BF CYL O/C C Q,ST,LT 76-19 PSC N2 Makeup Inbd Isol 2 B-5 A 2 BF CYL 0/C_ C Q 57,LT 76-24, r nt N2 Purge 2 B/C-5 A 10 BF CYL C C Q,57,LT I b
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BROWNS FERRY MJCLEAR PLANT UNITS 1, 2, and 3 System: Containment Inerting (76) Drawing No. 47E600-14 Relief PeqJest/ Valve ASME . Drawing Size Valve Actuator Nonnal Safety Testing Cold Shutdown (in.) Type Position Posi tion Required Justification lumber Function Class' Coordinates Category Tvoe 76-653 Tip Indener Purge Check 2 .1-5 AC 1/2 CK SELF C C Q,LT PV-24 i t
BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3 System: Floor and Dirty Radwaste Drainage (77) Drawing No. 47E852-1 Relief Request / Valve ASME- Drawing Size Valve Actuator Normal Safety Testing Cold Shutdown Number Function Class Coordinates Category fin.) Type Tvoe Position Position Reovired Justification 77-2A DW FD Sump Outbd Isol 2 C4 A 3 GA A0 0 C Q,ST,LT 77-28 PSC N2. Makeup Inbd Isol 2 C4 A 3 GA A0 0 C Q.ST.LT 3 1 _ _ . _ _ . _ . _ _ , - _ . _ . . . . . . _ . . - . _ . _ ~ . - . _ _ _ , . _ . . . . . - _ _ . _ _ _ _ . - . _ . . . . . _ . . . _ . _ _ _ . . - , _ _ _ _ _ _ . _ _ _ _ _ . . . . . . .._.- BROWNS FERRY HUCLEAR PLANT UNITS 1, 2, and 3 System: Clean Radwaste & Decon Drainage (77) Drawing No. 47E852-2 Relief Request / Valve ASME Drawing Size Valve Actuator Normal Safety Testing Cold Shutdown Number Function Class Coordinates Cateoorv (8n.) Tvoe Tvoe Position Position Recuired Justification 77-15A DW Eq Dr Sump Inbd Isol 2 D-3 A- 3 GA . ,AD 3 C Q,ST.LT 77-15B DW 'Eq Sump Dr Outbd Isol 2- D-3 A 3' GA .A0 O. C Q,ST.tT i t i t i i 7 t 45-i 1 l { i , m . ...: s . ._, . . . . _ , __________;
BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3 System: Fuel Pool Cooling System (78) Drawing No. 47E855-1 Relief Request /- Valve lASMEDrawing Size Valve Actuator Normal Safety Testing Cold Shutdown Nomber Function Class Coordinates Category (in.) Type Tvoe Position Position Reevired Justification 78-61 RHR to FPC Supply' 2 H-6 B 6 GA MD C 0 Q,ST 78-62 RHR to FPC Supply 3 H-5 B 6 GA H C 0 0 78-526 To Pool Diffuser A 3 G-5 C 8 CK SELF 0/C 0 CV 78-527 To Pool Diffuser B 3 G-5 C 8 CK SELF O/C 0 CV
_ . . _ _ _ _ _ _ . . . . . . . . . _ _ . _ _ _ . _ - - . _ , . . - _ _ _ _ _ . . . - - . . m , r BROWNS FERRY NUCLEAR PLANT LHITS 1, 2, and 3 i
. System: Diesel Generator Air Start (82)
Drawing No. 47E861-5,6,7,8, Relief Request / Valve ASME Drawing Site Valve Actuator Nonnal Safety Testing Cold Shutdown Number Function Class Coordinates Category (in.) Type Tvoe Pos i tion Position Recui red Justification .[ 3-82-503 Air Start : DG-3C NC E-3/4 B 1-1/2 GL A0 C O/C Q,ST PV-31 '- 3-82-504 Air Start D6-3C NC E-1/2 B 1-1/2 GL A0 C O/C Q,ST PV-31 ! 3-82-516 Air Start .DG-3D NC E-3 8 1-1/2 GL A0 C O/C Q,$T PV-31 3-82-517 Air Start = DG-3D NC E-2 8 1-1/2 GL A0 C O/C Q,ST PV-31 ; 0-82-529 Air Start DG-B NC F-4 8 1-1/2 GL . A0 C O/C' Q,ST PV-31 0-82-530 Air Start DG-8 'NC F-2 B 1-1/2 GL A0 C O/C Q,ST PV-31 3-82-540 Air Start DG-3A NC .F-4 B 1-1/2 GL A0 C O/C Q,ST PV-31 3-82-541 Air Start DG-3A NC F-2 B l-1/2 GL A0 C O/C Q,ST PV-31 0-82-553 Air Start DG-C NC . E-4 B 1-1/2 GL ,AO. .C O/C Q,ST PV-31 0-82-554 Air Start DG-C NC . E-2 8 1-1/2 GL A0 C O/C Q,ST PV-31' 0-82-566 Air Start DG-D NC F-4 8 1-1/2 GL A0 C. 0/C . Q,ST PV-31 0-82-567 Air Start DG-D NC F-2 B 1-1/2 GL A0 C O/C. Q,ST PV !
'3-82-579 Air Start DG-38 NC E-3/4 B 1-1/2 GL A0 C O/C Q,ST PV-31 3-82-S80 Air Start DG-3B NC E-2 B. 1-1/2 GL A0 C O/C Q,ST PV-31 f 0-82-592 Air Start DG-A i NC .F-4 B 1-1/2 GL A0 C O/C' .Q,ST PV-31 0-82-593 Air Start DG-A NC F-2 B 1-1/2 GL- AO . - C O/C Q,$T PV-31~ >
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BROWNS FERRY NUCLEAR PLANT UNITS 1.-2, and 3 System: Containment Atmosphere Dilution (84) Drawing No. 47E862-1
' Relief Request /.
Drawing Site Valve Actuator Nonnal Safety Testing Cold Shutdown Valve ASME Position Recuired Position Justification Class Coordinates Cateoory (in.) Tvoe Type Number Function E-7 A 2 GA S 'C O/C Q,ST LT PV-23 84-8A DW N2 Supply Train A 2 PSC N2 Supply Train A 2 E-S A 2 GA S C O/C - Q,ST,LT PV-23
~84-8B 2 E-5 A 2 S C O/C Q,ST.LT PV-23 84-8C PSC N2 Supply Train B GA ' .
DW N2 Supply Train B 2 E-S A 2 GA S C O/C Q,ST LT W-23 84 8D 2 E-3 A- 2' GA- A0 C O/C Q,ST,LT 84-19 DW/PSC Disch to SBGT 2 G-2 A 2 GA - A0 C O/C Q,ST.LT 84-20 DW/PSC Disch to SBGT 2 E-7 A 2 CK SELF C O/C Q,LT CSD-7, PV-28 84-600 CW Supply Check A 84-601 PSC Supply Check A 2- E-7 A 2 CK SELF C 0/C Q.LT CSD-7. PV-28' 2 , E-5 A 2 CK SELF C O/C- 0,LT CSD-7, W-28 84-602 DW Supply Check 8 2 E-5 A- 2 CK SELF C O/C Q,LT CSD-7, PV-28 84-603 PSC Supply Check 8 F-4 A 2 CK SELF C O/C Q LT CSD-7, PV-28 84-617 Contai:eent Isol Valve 2 F-6/7 A 1/2 CK SELF C C Q,LT CSD-7, PV-28 84-680 Outhd Cont.Isol Check NC l-L
- - . _._ _ ._ _._ _.._ __ _ .. _ . .___ - - ____ -..__. _ ... _ . _ _ _ _ ... _ _ _ _ . .._ _ ..~.. . _ _ . _ . -
1 I BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3
- System
- Control Rod Drive (85) 4 Drawing No. 47E820-2 l Relief Request /
- Valve ASME Drawing Size Valve Actuator INomal Safety Testing Cold Shutdown Number Function Class Coordinates Catecorv (in.) Type Twe Position Position Recui red Justification 85-39A Scram Inlet 1 C-8 B 1 PL AO - C- 0 Q,ST PV-21 (1-185) 85-398 Scram' Outlet 1 C-7 8 3/4 PL A0 ' C 0 0,ST PV-21
, (1-185) 85-576 Isol' check to RWCU 1 F-9 AC 4 CK SELF C C CV,LT PV-26 85-589 Charging Water Check 2 C-9 C 1/2 CK SELF C O/C CV CSD-9 l- PV-21' (1-185) 85-597' Cooling Water Check 'l B-9 C 1/2 CK SELF C C CV PV-21 (1-185) ! 85-616 Scram Outlet Check 2 D-7 C 3/4 CK SELF C 0 CV PV-21 ! (1-185) i l 1 1 d h i I i '; 4 l 'i 1 , t , i t ,i i i j~ .I l 2 o I t
BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3 System: Control Rod Drive (85) . Drawing No.' 47E820-6 (Units 1 and 3) 47ES20-5 (Unit 2) Relief Request / Drawing Size Valve Actuator Normal Safety Testing Cold Shutdown Valve ASME Function Class Coordinates Catecory fin.) Type Type Position Position Recuired Justification Number 8 2 GL A0 0 C Q,ST,FS 85-37C SDIV. Drain Isol West 2 B-6 2 B-5 8 2 GL AO O C Q.ST.FS 85-37D SDIV Drain Isol West . 2 B-3 8 2 GL .0 0 C Q.ST.FS 85-37E SDIV Drain Isol East B-3 8 2 GL A0 0 C Q,ST,FS 85-37F SDIV Drain Isol East 2 G/H-7 8 2 G1 A0 0 C Q,ST,FS
'S5-82 Scram Disch Hes. der Vent West 2 G/H-7 8 2 G' ,. AO O C Q ST,FS 85-82A Scram Dirch Header Vent West' 2 G/H-2/3 B 2 GL A0 0 C Q,ST,FS 85-83' Scram Disch Header Vent East 2 2 G/H-2/3 8 2 GL A0 0 C Q.ST,fS 85-83A .. Scram Disch Header Vent East I
I
. . _ . . _ . . . _ . . _ . . _ . . . . .__ . . . . . . . . . . = . . . . . . . . . . .
BROWMS FERRY NUCLEAR PLANT UNITS 1. 2, and 3 System: Radiation Monitoring Drawing No. 47E610-90-I Relief Request / Valve ASME Drawing Site Valve Actuator Normal. Safety Testing Cold Shutdown Number Function Class Coordinates Cateoorv (in.) Type Type Posi ti on Position Recui red Justification 90-254A DW Leak Det Upper Inbd Isol 2 H-2 A 1 PL 70 0 0/C Q,ST.LT 90-2548 DW Leak Det Lower Inbd Isol 2 G-2 A 1 PL MO O 0/C Q ST.LT 90-255.. CW Leak Det Intake Outbd Isol 2 H/G-2 A 1 PL 70 0 0/C Q.ST.LT 90-257A DW Leak Det Outbd Isol 2 H-2 A 1 PL 70 0 0/C Q,ST,LT 90-2578 DW Leak Det Inbd Isol 2 H-2 A 1 PL to 0 0/C Q,ST,LT
BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3 System: .Transversing Incore Probe Drawing No. 47E600-14 Relief Request /- Valve ASME- Drawing. Sire Valve Actuator Normal Safety Testing Cold Shutdown Number Function _ Class Coordinates Cateoorv (in.) Tvoe Tvoe Posi ti on Position Recuired Justification Tip Indexer Ball Valve g2 B-8 A 1/2 BA S C C Q,ST,LT PV-23 94-501 , Tip Indexer Ball Valve . 2 A-8 A 1/2 BA S C C Q ST,LT PV-23 94-502 Tip Indener Ball Valve 2 A-8 A 1/2 BA S C C Q,ST.LT PV-23 94-503 Tip Indexer Ball Valve 2 A-8 A 1/2 EA S C C Q,ST.LT PV-23 94-504 Tip Indexer Ball Valve 2 A-8 A 1/2 BA S C C Q.ST,LT PV-23 94-505 i i--
III. RELIEP REQ'UEST
4 i 1 l l } i-Relief Request lio. PV-1:(continued) {- 4 }- Alternative
- i. Testing: Vibration measurements are_taken on all the pumps in the Section XI program during testing to detect changes in'
[
- _ bearing performance. -Temperature and lubricant
- - level / pressure _are monitored on pumps which are equipped i with instrumentation, b ,
i b a 1 4 i i 1 e 4-3 4 i~ l s i e
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~74-u
i-i e i Relief Request No. PV-1 l-l System: Residue.1 Heat Removal (RilR)- , liigh Pressure Coolant Injection (teCI) i i Reactor Core.Isolatlon Cooling (RCIC) I. Core Spray (CS) j Standby Liquid Control--(SLC) j RHR Service Water (RIIRSW) l Diesel Fuel Transfer (DFT) i a Drawings: RHR 47E811-1 I HPCI 47E812-1 l RCIC 47E813-1.
- CS 47E814-1 i SLC 47E854-1
{ RHRSW 47E858-1
- i DFT 47E840-2 i
i Components: RHR pumps A, B, C, D HPCI pump , RCIC pump j CS pumps A, B, C, D l SLC pumps A, B j RHRSW pumps Al, A2, A3, B1, B2, B3, Cl, C2, C3, Dl, D2, D3 j DFT pumps IAl, lA2, 1B1, 1B2, 101, 102, 101,-1D2, 3Al, 3A2,. ] W1, 3B2, 3Cl,-3C2, 3D1, 3D2 i i Class: RHR Class-2 l HPCI - Class 2 RCIC - Class 2 1 CS - Class 2 l SLC - Class 2 i RHRSW - Class 3 j DFT .3n-Code Class l Function: RHR - Reactor Core residual heat removal ( HPCI - Emergency core cooling; j RCIC - Emergency core cooling ! ~ CS - Emergency core cooling I SLC - Emergency core boration } RHRSW - Emergency' equipment cooling DFT - Emergency diesel generator fuel supply _ _ - !- Impractical Test j^ Requirement: IWP-3100 - Monitor pump bearing temperatures and observe [ lube oil level / pressure.during inservice testing. J
- Basis for Relief
- The bearings for.the-RHR, CS, RHRSW, and DFT pumps are i lubricatedsby the pumped. fluid. These pumps and the SLC l and RCIC pumps are.not equipped-with temperature indicators.
s
- The RCIC and HPCI pumps have oil cooled bearings. However, l- these pumps cannot be operated long enough for the bearing
[ oil to reach stable temperatures without overheating the j torus and causing unit shutdown. 1--s-- --r,. . -c , .w.,- ,.m..-c-,m,,%.y..n+.wp.,_,%,m,m,.r.,.s,%,,,,y .,,.,.w,,,,,..,,,,,,,,,,,,,~w,,c.,,4.c.,,,,,,.,,,y.....y.,-,w wem,,w-,, .,,,w,~ ,e+
Relief Request No. PV-2
-Systems Standby Liquid Control (SLC) (63)
Diesel Puel Transfer (DFT) (18) Drawing: SLC 47E854-1 DFT 47E840-2 Components: SLC Pumps A, B DFT Pumps 1A1,1A2,1B1,1B2,1C1,102, IDI, ID2, 3A1, 3A2, 3B1, 3B2, 3C1, 3C2, 3D1, 3D2 Class: SLC-Class 2 DFT-Non-Code Class Punction: SLC-Injection of Sodium Pentaborate into Rx Vessel DPT-Transfer Diesel Puel to Day Tank Impractf_ cal Test Requirement: IWP-3100 - Measure inlet pressure prior to and during pump test and measure' pump delta P during pump tes;. Basis for Relief: During testing, these pumps take auction from a tank that has a relatively small range of IcVel variation during pumps operation. In addition, these_are positive displacement pumps whose inlet pressure does not affect pump operating characteristics. Therefore, differential-pressure measurement is not meaningful in monitoring pump performance. Also, the diesel fuel transfer pumps are not instrumented or-constructed to allow measurement of discharge pressure. Alternative
. Testing: SLC: Pump discharge pressure will be measured during quarterly testing.
Diesel Fuel Transfer: Flow rate is measured monthly as required by plant Technical Specifications utilizing existing tank-IcVel instrumentation. l
Relief Request No. PV-3 System: Diesel-Fuel Transfer (DFT) (18) Drawing: 47E840-1 Components: DPT Pumps 1A1, lA2, 1B1, IB2, IC1, 102, IDI, ID2, 3A1, 3A2,. 3B1, 3B2, 3B1, 3C2, 3DI, 3D2 Class: Non-Code Class Function: Pump diesel from seven-day tank to day tank Impractical Test Requirement: IWP-3500(a), five-minute mini num run time Basis for Relief: Depending on the level of the day tank when the surveillance procedure is performed, the high-level switch could stop the pump before data is accumulated. Alte rnative Testing: Measure parametera during the two-minute minimum test. Test will be performed when level of tank permits pumps to be run for as long as possible, at least once per six months. The existing fuel level gauge will be utilized to measure flow.
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Relief Request No. PV-4 System: All ASME Section XI Addressed by Technical Specifications i Drawing: Various Components: All Safety-Related Valves in Systems Addressed by Plant Technical Specifications Class: 1, 2, 3, and Non-Code Class Punction: Various Impractical Test Requirement: IWV-3416, all valves operable for system to be operable, IWV-3417(b), testing _ valves that failed during CSD prior to startup. Basis for Relief: IWV-3416 states that valves shall be exercised within 30 days prior to return of-the system to service. IWV-3417 states that when corrective action is required as a result of tests made during CSD, the condition shall be corrected before stsrtup. The plant technical specifications limiting evnditions of operation cicarly state the minimum requirements for safe operation of the plant. -The failure of a particular valve may not require plant shutdown or prevent startup,_ System requirements for operation will be per technical specification requirements. Alternative Testing: In accordance with plant technical specification requirements. _ _ _ _ _ _ , _ _ , ---a-.-,---,-- ------- - - - - - - - " ' " - ~ ' - " -
Relief Request No, pV-S System: Diesel Puel Transfer (DFT) (18) Drawing: 47E840-2 Components: Dieuel Fuel Transfer Pumps 1A1,-1A2, IB1, 1B2, 1C1, IC2, IDI, 1D2, 3A1, 3A2, 3Bl. 3B2, 3C1, 3C2, 3D1, 3D2 Class: Non-Code Clasa-runction: Transfer diesel fuel to engine day tank. Impractical Test Requirement: IWP-4110 instrument accuracy shall be within the limits aof Table IWP-4110-1, , IWP-3210, Allowable Ranges of Inservice Test Quantities, Basis for Relief: The diesel fuel. transfer pumps are not instrumented to
. measure flow other than a level gage on the day tank. We have attempted to measure the pump discharge 110w-using externally mounted flow metering devices; however, the system piping configuration-is not compatible with such devices, At the present-time the day tank-level gage is the only means available for flow measurement and its.
repeatability is insufficient for pump performance trending, t Plant Technical Specification 4.9.A.1,a requires that the diesel fuel transfer pumps be tested monthly to demonstrate . operability. This testing consists of demonstrating that the transfer pumps are capable of pumping fuel at a rate greatcr than the consumption rate of the diesel engine.- (5 gallons /minutei Alternative Testing: The hbility of the pumps to exceed the engine consumption-rate of $ gallons per minute will_be demonstrated monthly, and vibration measurements (n1 the pumps will be recorded and evaluated per Table IWP-3100-2 quarterly, in lieu of measuring pump hydraulic parameters.(pressure and flow rate).
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- N Relief Request No. PV-6 System: Main Steam (1)
Drawing: 47E801-1 Components: Valves 1,2-PCV-1-5, 19, 22, 30, 31, 34 3-PCV-1-5, 18, 19, 22, 34, 41 Category: B, C Class: 1 Function: Automatic Depressurization Statem (ADS) Valve, Code Safety / Relief Valve Impractical Test Requirement: IWV-3412 - Exercise valve once every three months. Basis for Relief: The six safety relief valves assigned to the ADS system q perform an essential safety function'when operated by the a pneumatic actuator with gas supplied through the-ADS solenoid valves. Operation of these valves it not practical during power operations-because this action will i vent main steam to the suppression pool, inducing a , transient condition and increasing the potentiality for an open failure of a safety relief valve. Also, no stroke timing is practical as these are pneumatic assisted SRVs. Since " position indication" of the SRVs is provided by acoustic monitors attached to the valve discharge piping, exercising during cold shutdown cannot be accomplished because of lack of steam flow (and attendant noise). Alternative Testing: The ADS valves will be exercised once each operating cycle in accordance with Technical Specification 4.6.D.2 which provides manual opening of each ADS valve observing an indication of steam flow through each valve. 6
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Relief Request No. PV-7 ! System: -Reactor-Vessel Vents and Drains,(IO) Drawing: 47E801-1 Components: Valves 10-506, 507, 508,-509, 510, 511,.512, 513,_514, 515, 516, 519, 520, 521, 522, 523, 524, 525, 526, 527, 528, 529, 530, 531, 532, 533 Category: C l j Class: 3 Function: Main Steam Relief Valve (MSRV) Discharge Pipe Vacuum Breaker Impractical Test Requirement: IWV-3521 and 3522 - Exercise valve once every three months. Basis for Relief: These valves are located in the drywell and access during operation is not practical. The dryvell is inerted with nitrogen, and entry would involve personnel safety hazards or deinerting. Alternative Testing: Valve will be proven to move freely throughout the full range by manually cycling. In cases during CSD when drywell entry is made, these valves will be tested with the other CSD valves (i.e., time permitting) with a minimum of each refueling. i t
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e Relief Request No. PV System: Reactor Feedwater (3) Drawing: 47E803-1 Components: Valves 3-554, 558, 568, 572 Category: A, C Class: 1 Function: Containment Isolation Impractical Test Requirement: 1WV-3521 and 3522 - Exercise: valve closed once every three months. Basis for Relief: All four check valves remain open, maintaining the flow path to the reactor vessel whenever the. . feedvater/ condensate systems are supplying feedvater to the reactor vessel. . When RCIC or RWCU are returning flow to the reactor vessel, check valve 3-572. remains open. When HPCI is injecting to the vessel, check valve 3-558 remains open. -Due to the necessity of maintaining this flow path in virtually all modes of operation, closure testing is only practical during extended outages such as refueling during which these systems =are' shutdown. Also, plant ._ design does not provide a practical means of demonstrating closure other than by upstream pressurization performed during leak rate testing in accordance with Appendix J 10 CFR 50. This testing involves significant effort for installation of temporary equipment, and requires entry-into an inerted reactor containment. Such~ entry into , containment' poses-a hazard to personnel safety or deinerting. Alternative Testing: Valve closure vill be verified-by completion of local leak rate testing performed in accordance with 10 CFR 50 Appendix J, at each refueling outage.
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n ] j Relief Request No. PV-28 l_ .
. l t . System: . Residual Heat Removal (RHR) (74) j Containment Atmosphere Dilution (CAD) (84) f Drawing: 47E811-1
! 47E862-1
; Components: Valves 74-661, 662 84-600, 601, 602, 603, 617, 680 l
j Class: (R!lR) 1 ! (CAD) 2 j Function: (RllR) Thermal Relief / Containment Isolation U (CAD) Containment Atmosphere Control MSRV-Air Supply i i Impractical Test Requirement: IWV-3521 and 3522 - Cycle valve quarterly. 6- . . i Basis for Relief: RHR:- These valves provide thermal relief between the l inboard and outboard shutdown cooling suction valves. i Since these valves are in series with no-inolation valve or j rest connection between them,-they individually cannot be i proven to close. Since.these valves are located inside i containment, access to perform testing during operation is ! impractical due to the drywell being inerted. Cycling by
- system manipulation is not possible during reactor
- operation due to pressure interlocks which' prevent the-
- j. suction valves from operating.
CAD: These valves provide an injection path when open and containment isolation when closed. Cycling the valve
- closed would require setup of temporary test equipment and j abnormal valve lineups.
Alternative ! Testing: Proper valve opening for the RHR valves will be-proven by: l cold shutdown alternative test methods such as passing flow l during CSD, assuming drywell entry and adequate time. ,The. CAD valves will be stroked open during CSD. ' Proper valve i closure of the RHR and CAD valves will be verified.by l completion of local leak rate testing performed in j accordance with 10 CFR 50 Appendix J. I 1 1 I l
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( - 1 i 1 4 Relief Request No. PV-29 b ' i System: Reactor Core Isolation Cooling (RCIC) (71) Iligh Pressure Coolant Injection.(llPCI) (73) { I i Drawing: 47E813-1 [ 47E812-1 i 3 Components: Valves 71-589, 502 i 73-625, 505 1 i Function: Prevent backflow from condensate storage tank and pressure j suppression chamber head tank. ' Impractical Test l Requirement: IWV-3521 and 3522 - Exercise valves closed every three 1 months. t j Basis for Relief: System design prevents the valves from being verified
- closed by reverse flow or other conventional means.
Therefore, closure verification by disassembly will be. j -required. Since the valves can be verified open quarterly
- by flow verification, apparent disc free movement will be
! indicated. l l Alternative Testing: Valves vill be proven to close once per refueling cycle by , disassembly and inspection on a rotating basis in-l accordance with Position 2 of NRC Generic-Letter 89-04. i l' i .. I i I l a $ l I
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- ~102-i 4
e
Request for Relief PV-30 Units: 1,2,3 System: Standby Liquid Control (SLC) (63) Drawing: 47E854-1 Components: Valves 63-514, ~516 Category: C Class 2 Function: Provides standby liquid control from accumulator discharge flowpath and prevents backflow. Impractical Test Requirement: IWV-3421 and 3422 - Exercist valve once every three months. Basis for Relief: The standby liquid control system pumps are positive displacement pumps which by their design prohibit backflow through the pump. Their ex'sts no flowpath by which the backst ting capability of these check valves, 63-514 and 516, cut be demonstrated either during system operation or , plant shutdown. Alternate Testing: One check valve will be disassembled at each refueling outage on a rotational basis in accordance with Position 2 of NRC Generic Letter 89-04. Should the disassembled valve fail to function properly, the other valve will also be disassembled and examined. These valves will be full stroked in the open position during quarterly pump testing.
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Request for Relief PV-31 Units: 1,2,3 System: Diesel Generator Air Starting. l Drawings: 47E861-5,6,7,8 Components: Valves 0-82-529, 530, 553, 554,-566, 567, 592, 593 3-82-503,.504, 516, $17, 540, 541, 579, 580 Category: B Class: Non-Code Class Function:- To provide initial compression to start the diesel-generator engines. Impractical Test Requirement: IWV-3521 and 3522 - Stroke time test-valves on a quarterly basis. Basis for Relief: The diesel air start valves are solenoid valves which are accessible only by disassembling the engine starter system. These valves cannot be operated independently, and operate only from a diesel engine start signal. There exists no indicator lights or visible obturator by which to time the stroking of these valves. Alternate Testing: Due to the configuration of the diesel air start system,- there exists no method-to individually time the stroke of each air start valve. The plant Technical Specifications require that the period between the initiation of a diesel engine fast start signal and the actual engine start not to exceed ten seconds. This specification is verified semi-annually as required by the Technical Specification surveillance requirements. In addition, each engine is: tested using the normal = start technique once each month. During a diesel engine start, a diesel air start valve must nove from the closed position to the open position-to cause the engine to start. Failure of the valves to operate properly will prevent the engine from starting. The successful start of a diesel engine within ten seconds of the fast start initiation signal will-be acceptable to demonstrate the proper operation of the air start valves. This test vill be conducted as required by the plant Technicsl Specifications.
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Request-_for Relief PV-32 System: Main Steam (1) Drawing: 47E801-1 9 Components: Valves FCV-1-14, 26, 37, 51 Class: 1 Function: Main Steam Isolation Valve Inboard of Primary Containment Impractical Test Requirement: IWV-3415 fail-safe position testing of valves once each quarter or on a cold shutdown basis. Basis for. Relief: The fail-safe testing of these main steam' isolation valves-(MSIVs) requires the isolation of control air to the valve operator and the venting of the control air' accumulator for the valve. The MSIV, the control air isolation valve, and accumulator are located;inside primary _ containment. _ Entry is precluded during operation because the containment atmosphere is inerted with nicrogen gas for oxygen control. In addition, the inert atmosphere is maintained during short duration cold shutdown periods when entry:into containment is not mandatory. The extended downtime and the cost required to purge the containment vessel to allow entry for the test and to re-inert the vessel prior to restart place an-operational and rinancial hardship on_the utility without a commensurate increase in safety. Alternative Testing: The fail-safe function of these valves vill be test ed at each cold shutdown during which the containment vessel atmosphere does not remain inerted, provided they have not i been tested within the previous three months. Should the containment vessel atmosphere remain inerted for an entire fuel cycle, these valves vill-be tested at a minimum of once each refueling outage.
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m Request-for Relief PV-33 System: Various Drawing: Various Components: All valves safety-related valves which are stroke time tested Class: 1, 2, 3, non-code Function: Various Impractical Test Requiremen;: IWV-3417(a) requires comparison of the latest test stroke time with the prev.ious test stroke time to determine **1ve testing frequency Basis for Relief: NRC Ceneric Letter 89-04 states that measuring changes in stroke times from a reference value as opposed to measuring changes from the previous test is an acceptable alternative for valves with e roke times 10 seconds or less. The NRC further stated in response to questions on GL 89-04'that the use of reference valve stroke times as a bataline for comparison of routine test stroke times is a better method of evaluating changes in valve performance (including valves with stroke times over 10 seconds) than that required by the ASME Code (IWV-3400). ASME-0M-10 specifies the use of reference values for comparicou-9f routine test stroke times. Alternative Testing: Use reference values determined when the talve is known to be operating acceptably as the baseline for evaluating routine test stroke times for corrective action. ,4
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l 1 l Relief Request No. PV-34 ] i System Residusti llent Removal (Ri!R) l liigh Pressure Coolant Injection (llPCI) i Reactor Core Isolation Cooling (RCIC) ! Core Spray (CS) j Standby Liquid Control (SLC) i RilR Service Water (RilRSW) } Diesel fuel Transfer (DIT) i 3 Urawings: RilR 47E811-1 ] !!PCI 471:812-1 , l RCIC 47E813-1 l j CS 47E814-1 , 3 SLC 47E854-1 l I EllRSW 47E858-1 i ! DIT 47E840-2 i i Components: Ri!R pumps A, B, C, D 1 IIPCI pump j j RCIC pump l CS pumps A, B, C, D j SLC pumps A, B v PJ"'SW pump A1, A2, A3, B1, ot, B3, C1, C2, C3, D1, D2, D3 ; l D}*1 pumps I A1, I A2, IB1, 1B2, 101, 102, 1D1, 1D2, 3A1, *,A4, j 3B1, 3B2, 301, 3C2, 3D1, 3D2
- Claunt RilR - Class-2 ,
j llPCI - Class 2 i RCIC - Class 2 CS - Class ?. .- SLC - Class 2 ' Ri!RSW - Class 3 t D}T - Non-Code Class ,. 1 i Function: RilR - Reactor Core residual heat removal 1 IIPCI - Emergency core cooling i , RCIC - Emergency core cooling ' l CS - Emergency core cooling j SLC - Emergency core boration ' j RilRSW - Emergency equipment cooling
- D}T - Er . ency diesel generator fuel supply l
4 Impractical Test
- j. Requirement: IWP-4510 - Vibration amplitude based on displacement measurements.
], ) Basis for Relief The vibration data collected on these pumps during the- . j first ten-year inspection interval was based on vibration <
- velocities. This data allows a spectral analysis by ?
frequency to be performed and trended.- An analysis of vibration velocities provides better information on the ! condition of the component than vibration displacement
- measurements.
1 , -107-1
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Relief Request lio. PV-34 (continued) Alternative Testing: Measurement of velocity shall be used to determine vibration amplitude. The acceptable and alert rangen are as stated below. One point will be-trended, utilizing broad band unfiltered measuremento with an instrument with a calibration frequency response range of 10-1000 liz. Test Acceptable Alert Required Qilantitv Intre _liant e ._Aetion Ranr.e V 0<V11.5V r 1.5V r<V13.0V r V>3.0V r fl0TE: V is defined as vibration velocity in in/sec and Vr is the reference value.
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s IV. COLD SHUTDOWN TESTING JUSTIFICATICINS
i ! CidsLS131Ldertthiatification Number 1 i ' j System: Reactor Recirculation j Drawing: 47E817-1 Valves FCV 68-3, 79 l Category: 11 Class 1 hinction Pump A&B dischar6e isolation Justificed v The recirculation pump diocharge loolation valves are in the main flow path of the reactor recirculation system, which is necessary to maintain proper cooling and reactivity control of the reactor._ Cycling of these' valves
- during power operations would interrupt the driving core flow, possibly resulting in severe changes in core power icvel. Cycling of these valves vould also isolate that loop of the recirculation system. Failure of the valve to reopen could result in a plant shutdown as required by technical specificationn with one loop recirculation operation permitted for not longer than 12 hours.
i.
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Cald shutdown Justificati.mi fiumber 2 System: Heactor lluilding Closed Cooling Water i Drawing: 47E822-1 j Valves: l'CV 70-47 (; Category: A j Class: 2 l' unction: Contaitudent discharge isolation 4 4 Justification: This valve is in the cooling water return lines for'the j reactor recirculation pump bearing and seal coolers. , j Cycling of this valve during power operation would l interrupt this cooling water flow, possibly causing pump. l bearing damage or seal failure. - 1 1 1 ! l ! i
)
f i I i i i i P l
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X C91AJhut1991thitiilsat19n_1hbst_1 Systemt Reactor Core Isolation Cooling Drawing: 47E813-1 Valvest FCV 71-40 Category: AC Classt 1 Punctient Containment testable check Justification: This testabic check valve cannot be cycled using the actuator during power operation due to the high pressure differential across the valve. The only way to cycle this valve during power operation is to eliminate the pressure differential. This may be accomplished but would require RCIC injection, set up of I tasurizing equipment, or jumper installation, which-are considered impractical. Additionally, this valve is located in the steam tunnel, and testing would require personnel to enter the steam-tunnel during power operation.
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f C21d Shuidavjt_49g11 fi eat ion fing&f r _4 System Ilich Pressure Coolant Injection Drawing: 471:812-1 Valves FCV 73-45 Category AC Class: 1 Function Containment testable check Justification: The testable check valve cannot be cycled using the actuator during power operation due to the high pressure differential across the valve. The only way to cycle this valve during power operation is to eliminate the pressure differential. This may be acanrplished but would require ! IIPCI injection, set up of pressurizing equipment, or jumper installation, which are considered impractical. Additionally,-this valve is located in the steam tunnel, and testing would require personnel to enter the steam tunnel during power operation.
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Cold shutdown JustifientlQu_lhlthr d System: Residual lleat Removal Drawint, 47E811-1 l ! 4 ! Valves: 74-47, 48 i i l Categery: A Class: 1 ! Function: Shutdown cooling isolation i , Justification: These normally closed isolation valves are only required to
- open when bringing the unit to a cold shutdown cooling mode l
of Ri!R. Cycling these valves at pressures greater than 100 psig is prevented by logic interlocks.
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l i I I l l l
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Go l d S h u t dpyILutpli f i e a t i on_l{p;nhrL,6 System Main Steam Drawing: 47E801-1 Valves: 1-14, 15, 26, 27, 37, 38, 51, 52 Category: A Class: 1 Function: Main Steam Isolation Justification: Cycling of these valves during power operation requires a reduction in power to less than 70 percent of full power.
-Per IWV-3412(a), valves shall be exercised unicas such=
operation is not practical during plant operation. Valven vill be partially stroked quarterly, and full stroked on a cold ohutdown basis. The valves located outside primary containment, 1-15, 27, 38, and 52 vill be fail-nafe tested-on a cold shutdovn basis. 4 i
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E01d_.Elll3149YlLJ13. fit i f i e a t LQE_,JharAtr_l System Containment Atmosphere Dilution (84) Drav!ngi 47E862-1 Valves 84-600, 601, 602, 603, 617, 680 Categoryl A Class; 2 Function: Dryvell/ pressure Suppression Chamber Supply Check Valves Justification: Iroving the valves open quarterly requires injection of nitrogen into the dryvell which is not practical due to the effect on drywell preneure. I
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Cpid Shuistwn_dnull fieat icatlinntard Systems flich Pressure Coolant injection Reactor Core Isolation Cooling l Drawing: 47E812-1 1 47E813-1 Valves ilCV 73-23, 24 I IICV 71-14, 32 Category: A, C Classa 2 { j Function: Containment Isolation i ! Justification: These are manual valves. Cycling the valves would render { the system inoperable since no system logic controls the j position of a manual valve for system initiation. 4 4 I x i I a i i l 1 l l t
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! I Cold ShutAlvn._19m ifR n ion. Number 9 1 Systems Control Rod Drive l I
j Drawing: 471:820-2 , j Valvest 85-589(1-185) , Category: C ;
.i Class 2 ,
f Function: Charging water check , Justification: Verifying these valves cloacd would require inolating the
, charEing water and cooling water to the drives. This is i j not practical during operation.
1 a N i t i e E if l 1 i f (
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Cold Shutdown JustiflLalign Number _1.Q System: Residual llent Removal (74) Core Spray (75) Drawing: 47E811-1 47E814-1 Valves: 74-792, 802, 803, 804 7$-606, 607, 609, 610 Category: C Class: 2 Function: Provides isolation between the safety system and the non-safety system which is used to fill the safety system and maintain it (111ed while it is in the standby status. Justification: The valve alignments which are necessary to provide positive indication of the full, or partial exercising of these check valves requires that the safety system-be
-declared inoperable during the testing procedure. Normal testing of these valves during unit operation would require placing the plant in limiting condition operation (LCO) on a quarterly basis for the testing of each valve. As required by paragraph IWV-3522 of Section XI, these valves vill be verified closed on a cold shutdown basis-and leak tested in accordance with Appendix J.
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Relief Request flo, pV-9 System Standby Liquid Control (SLC) (63) Drawing: 47E854-1 Components: Valves 63-525 and $?6 j Category: A, C 3 j Class: 1 l Tunction: Containment Isolation 1 f Impractical Test j Requirement: IW-3521 and 3522 - Exercise valve once every three months. i } Basis for Relief: To verify proper opening of these check valves, it is j- necessary to pass _ fluid through each valve. This action l would result in an injection into the vessel and would i require actuation of an crplosive valve, both undesirable j during power _ operations. Closure testing is only practical by pressurizing downstream of the valve (the upstream side l being vented) and verifying absence of flow in the upstream i side. This requires installation of temporary equipment - and access to the containment which is inerted during power i operation. i i Alternative i Testing: The proper functioning of the standby liquid control system ) injection flow path, including opening of 63-525 and } 63-526, will be demonstrated once each operating cycle in accordance vl_th Technical Specifications. Proper valve-l closure will be verified by completion of local leak j testing performed in accordance with 10 CTR 50 Appendix J. ( 5 l l l i I t i
', Relief Request lio. PV-10 2
j System: Reactor Recirculation'(68) ] I Drawing: 47E817-1 \ } Components: Valves 68-508, 523, 550, 555 i j Category: A, C I ( Class: 1 l 1 i I Function: Containment Isolation i j' Inpractical Test l Requirement: IWV-3521 and 3522 - Exercise closed every three months. i l Basis for Relief: These check valves-serve as inboard and outboard j containment isolation valves. The valves are not equipped , i with remote indication, and there is no pressure indication i
- downstream of the valves. For these valves,-closure i testing is.only practical through pressurization dovnstream- l
! of the valve, with the upstream piping vented and ! verification of the absence of flow upstream.. Interruption ) of the CRD flow (seal injcetion) is required to perform
- this testing, and during reactor recirculation-pump
- operation, could result in seal-damage. This type of
- tenting can only be performed during a-period when the
! containment is accessible. The deinerting of the l containment will 7nly be performed during major outages. Based on the Imp,.. of having to install temporary te'.t j equipment, the required testing vill be performed during Category A leak rate testing. i l- Alternative l Testing: Proper valve closure will be verified by completion'of l local leak rate _ testing performed in accordance with l 10 CFR 50 Appendix J. i t 1 f l
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Relief Request No, pV-11 System: Reactor Water Cleanup (RWCll) (69) i Drawing: 47E810-1 \ i Components: Valves 69-579, 3-69-624 1 i j Category: A, C Class: 1
) Function: Containment isolation; prevents backflow into RWCU System.
! Impractical Test i Requirement: IWV-3521 a.id 3522 - Exercise valve closed every three 2 months. i { Basis for Relief: This check valve remains open to return water to the i reactor vessel whenever the reactor water cleanup system is j operating. This valve is not testable whenever the RWCU, 4 feedwater/ condensate, or RCIC system is-returning flow to 1 the reactor vessel. Testing requires entry into primary 1 containment and the disruption of system flow (RWCU, feedwater/ condensate or RCIC). For these reasons, closure j testing is only practical during extended outages such as 1 refuelings during which these systems are shutdown. Also, i plant design does not provide a practical means of l demonstrating closure other than by upstream pressurization i performed during leak rate testing conducted in accordance with 10 CFR 50 Appendix J. This testing involvers i significant effort for installation of temporary equipment. This would require valve lineups to abnormal , positions, installation of pressurizing equipment and associated test lines, as well as deinerting the drywell , for safe entry.
- Alternative
- Testing
- Proper valve closure vill be verified by completion of
, local leak rate testing performed in accordance with 10 CFE 50 Appendix J. 4 i l !
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i l l Request for Relief pV-12 System Reactor IIcat Removal Service Water (RllRSW) (23) Drawing: 47E858-1 l Cotnponents: Valves 23-34, 40, 46, 52 l l Category: B Function: E!!RSW Throttle Valve l Impractical Test [ Requirement: IWV-3521 and 3522 - Stroke.tt'oe valve every three montha. I
!! asis for Relieft In order to obtain a good stroke time for baseline value, the valve would have to be stroked from the same position.
Since these valves are throttle valves, the position to-l obtain the desired flow of 4500 gpm would change due to system variables such as corrosion, tube blockage, plugged i tubes, etc. Additionally, full opening the valve would overflow the heat exchanger and-possibly damage it. _-- Alternative Testing The valves will be stroke timed to a reference position corresponding to 1 4500 gpm quarterly. l l l l i l
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i kellef Request flo. pV-13 System Ri!R Service Wat er (kilRSW) (23) Drawing: 47E858-1 Components: Valves 23-601, -603, ~605, -607 Category: C Class: 3 Function: Prevent Backflow through " Keep Fill" lit, Impractical Test Requirement: 1WV-3521 and 3522 - Exercise valves closed once every three months. Basis for Relief: These check valves, located in keep fill lines for the RilR service water system permit raw service water flow into the respective _ headers while preventing process flow in the-- i reverse direction during RilRSV system operation.- These are- y two check valves in each line located in parallel. There a are no vent, drain, or test connections located upstream of the check valves. Therefore, no practical method exists to directly verify closure of either valve upon cessation or reversal of flow. Alternative Testing: The valves will be proven to close once every 24 months, by disassembly, acoustic monitoring techniques, or other proven methods. Disassembly will be performed on a rotating basis in accordance with position 2 in HD.C Ceneric Letter 89-04. O { l
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- Helief Request No PV-14 j
{ Systems Emergency Equipment Cooling Water (EECk) (67) 3 Raw Cooling Water (RCW) (24) I j Drawing: 47E859-1 1 47E859-2 l 47E866-7 1 , Components: Valves 67-541, 542, 558, 559, 584, 585, 600, 601, 638, 639, i 648, 649, 656, 657, 659, 660 0-67-502, 507, 508, 514, 515, 521, 522, 528, 529, 538, 539, 619, 622, 624, 625, 627, 628, 630, 631, 634,- 635, 652, 653,
=
671, 679 i 1 1-67-787, 789 l 2-67-873, 876 1 3-67-693, 694, 695, 696,-703, 704, 705, 706,-713, 714, 715, 716, 723, 724, 725, 726, 735, 736, 737, 738, 761, 762, 764,-1 _ _ _ j 765, 771, 772, 774, 775 t , 0-24-796, 798 4 l Cat ego ry: C , Class: 3 and Hon-Code Class Function: EECW: Pass rated-flow for the emergency coolers and prevent backflow from opposite header. , RWC: Prevent backflow of EECW into RCW, , Impractical Test i Requirement: IWV-3521 and 3522 - Exercice valves closed every three months. Basis for Relief: System design prevents the valves from being verified _ , closed by reverse flow or other conventional means. ' Therefore, closure verification by disassembly will be required. Since the valves can be verified open quarterly by flow verification, apparent disc free movement will be indicated. Alternative i Testing:- Valves will be proven to close once per refueling cycle by-disassembly and inspection. This will be performed on a , rotating basis in accordance with Position 2 in NRC Generic. Letter 89-04. I' T
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3 Relief Request No. pV-15 System Reactor building Closed Cooling Water (RBCCW) (70) q Drawingt 47E822-1 Components: Valve 70-506 Category: A, C Class: 2 Punction Containment Isolation Impractical Test Requirement: IWV-3521 and 3522 - Exercise closed once every three months. Basis for Relief: This valve is in the cooling water supply for the reactor recirculation pump bearing aud-seal coolers. Testing this valve closed during power operation would interrupt this cooling water flow, possibly causing pump bearing damage or seal failure.- Due to the necessity of maintaining thic flow path in virtually all modes of operation, closure testing is only practical ~during extended-outages such as refuelings during which this system is shutdown, plant design does not provide a practical means of demonstrating closure other than by downstream pressurization performed during leak rate testing. This testing involves significant effort for installation of temporary equipment, abnormal valve lineups for test boundaries, and complete purging of the inerted reactor containment. Alternative Testing: proper valve closure will be verified by completion of local leak rate testing performed in accordance with 10 CPR 50 Appendix J. 1 _1____
Relief Request No. pV-16 System Ilich Pressure Coolant Injection (IIPCI) (73) Reactor Core Isolation Cooling (RCIC) (71) ] Drawing: 47E812-1 (llPCI) 47E813-1 (RCIC) Componentat Valves 73-559 i 71-547 i j Category: A, C I Class: 2 , Function: Containment Isolation Impractical Test Requirement: IWV-3521 and 3522 - Exercise closed once every three months. h -Basis.for Relief: These valves are not equipped with position indication. Its configuration with an open discharge into the t uuppression pool prevents usage of reverse flow to demonstrate closure. No practical method exists to perform closure testing other than the downstream pressuritation by icek rate testing. Such testing conducted pe:' Appendix J' requires installation of temporary equipment and closure of valves which renders the system inoptsable. I Alternative Testing proper valve closure will be verified by completion of local leak rate testi3g performed in accordance with 10 CFR 50 Appendix.J. l l Relief Request No. PV-17 System: High Pressure Coolant Injection (llPCI) (73) Reactor Core Isolation Cooling (RCIC) (71) j Drawing: 47EB12-1 j 47E813-1 1 Components: Valves 73-603, 609 71-$80, 592 Category: A, C l Class: 1 l Function: Containment Isolation l i
! Impractical Test l Requirement: IWV-3521 and 3522 - Exercise valve closed once every three months Basis for Relief: These check valves are not equipped with position 4 indication, and' system design does not provide any l practical method of verifying closure other than i pressurization similar to leak rate testing.- Such testing l
requires. installation of temporary equipment which is
- impractical on a quarterly basis, and it would render the.
system inoperable during the testing period. ! Additionally, the valve location (top of torus).could } present a personnel safety hazard during' operation.
- Normally, testing of this type is accompliohed by required containment local leak rate testing in accordance with i Appendix J.
l Alternative i Testing: Proper valve closure vill be verified by completion of i local leak rate testing performed in accordance with 10 CFR ! 50 Appendix J. l 1 1 i i I l-1
Relief Request No. PV-18 Systemt liigh Pressure Co
- at Injection (llPCI) (73)
Reactor Core Isolation Cooling (RCIC) (71) h Drawing: 47E812-1 (llPCI) 47E813-1 (RCIC) Valves 73-633, 634, 635, 636 71-597, 598, 599, 600 Category: C Classt 2 Functiont liPCI Turbine Exhaust Vacuum Relief RCIC Turbine Exhaust Vacuum Relief Impractical Test Requirement IVV-3521 and 3522 - Cycle valve every three months. Basis for Relief: Valve-configuration prevents the valves from being individually proven open or closed. No test connections or isolation valves exist to allow reverse testing. Additionally, the valves are located in the torus room adjacent to the top of the torus. Access requires scaffold erection which would present a safety hazard during operation. Alternative Testingt One of the four valves shall be disassembled and inspected each refueling outage in accordance with NRC Ceneric Letter 89-04, Position 2.
Relief Request No. PV-19 Systems liigh Pressure Coolant Injection (llPCI) (73) Reactor Core Isolation Cooling (RCIC) (71) l Drawing: 47E812-1 (llPC1) 47E813-1 (RCIC) Valves: 73-517 71-508 Category: C Class: 2 Function: Backflow Prevention to Suppression Pool Impractical Test Requirement: IWV-3521 and 3522 - Exercise valve once every three months.- Basis for Relief: To verify proper opening of these check valves, it is necessary to initiate system flow while taking suction from the suppression pool. Since the water quality in the suppression pool is not maintained at reactor coolant standards, it is not advisable to initiate this flow at any time during normal operations. The_resulting contamination of the llPCI or RCIC system from such flow testing would affect the condensate storage tank purity and ultimately affect the chemistry control of the reactor coolant system. There exists no other practical method of verifying proper valve operation. Alternative Testing: Verify operability by disaunembly, each refueling outage, in accordance with Position 2 of HRC Generic l.etter_89-04. _.- 1 2
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I Rellet Request llo. I'V-20 System: Main Stean (1) Residual lleat Removal (RllR) (74) liigh Pressure Coolant Injection (11PIC) (73) Reactor Core Isolation Cooling (RCIC) (71) Drawing: 47E801-1 47E811-1 47EB12-1 47E833-1 Components: Valves FCV-1-55 FCV-74-61, 75 FCV-70-2, 26 FCV-71-2, 17 Class: 1 and 2 . Category: A runction: Containment Isolation Impractical Test Requirement: IWV-3423 Leak test gate valve with pressure differential in same direction as safety function Basis for Relief: These valves are configured such that there is no practical means of pressurizing in the direction of safety function (lack of proper isolation valves, test connections, etc.). Pressurization in the direction of safety function vould-require actions such as pressurizing the containment (equivalent to an ILRT) or precisely controlling the entire RCS at the valve test pressure. Alternative Testing: Leak rate test each valve in the reverse direction. Penetration vill be subjected to test pressures in the correct direction during containment integrated leak rate tests.
)
Relief Request No. PV-21 Systems Control Rod Drive (CRD) (85) Drawingt 47E820-2 47E820-5 (U2) 47E820-6 (Ul&3) ; Components: FCV-85-39A (1-185) FCV-85-39D (1-185) 85-589 (1-185) 85-597 (1-185) 85-616 (1-185) , Classt 2 Category: D, AC, C 1 Function: Control Rod Scram Water Flow Path > Impractical Test IWV-3521 ar.d 3522 - Exercise once every three months and Requirements measure stroke times. Basis for Relief: These valves located on the hydraulic control units for the 185 control rod drives function on a reactor scram signal from the reactor protection system to insert the control rods rapidly into the reactor core. Cycling these valves requires scramming a control rod. There are 185 control rods in the reactor. Scramming every rod once every three months is not practical for the following,reasonst
~
- a. A power reduction is required to test t.he scram function. Reducing power for the length of time required to scram 185 rods is not practical.
- b. Fuel preconditioning must follow this power reduction to avoid possible fuel damage. The longer the reduction in power, the longer the preconditioning.
Their proper functioning is most practically verified by an actual scram test (except for closure of 85-589). Alternative Scram testing and rod insertion timing will be performed in Testing: accordance with Technical Specifications Section 4.3.c (at reactor coolant pressure 800 psig) for:
- a. All control rods-prior to THERT.AL POWER exceeding 40 percent after each_ refueling outage. --
- b. 10 percent on a rotating basis at leapt once every 16 weeks. ,
i c. Valve 85-589 vill be proven to-close by pressure decay testing. This testing will be performed in accordance.with Position 7 of HRC Generic Letter 89-04. ;
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Relief Request lio. PV-22 System Control Air (32) j Drawing: 47E1847-6, 10 47E2847-5, 9 47E3847-5, 9 Components: Valves 1-32-336, 915, 2516, 2521 2-32-336, 2163, 2516, 2521 3-32-336, 2163 Class: Non-code Class Punction: Containment loolation Impractical Test Requirement: IWV-3521 and 3522 - Exercise valves every three months. liasis for Relief The closure testing of these containment foolation check valves vould isolate control air to vital equipment inside the dryvell. The intoard valves are inside containment and therefore = could not be proven closed without entry into the dryveli. The drywell is inerted, and entry would be a hazard to personnel safety. Alternative Testing: proper valves closure vill be verified by completion of local leak rate testing performed in accordance with 10 CFR 50 Appendix J, and will be performed each refueling cycle. 4 _ _ _ . . _ _ _ . _ _ _ . . _ _ _ - _ _ _ _ _ _ . . _ _ _ _ _ _ . _ _ ~ . _ _
Relief Request No. PV-23 System: Various Drawing: Various Components: All safety-related valves with reference stroke times of 1 2 seconds. Class: 1, 2, 3 and non-code class Punction: Various Impractical Test Requirement: IWV-3417(a) - Stroke time corrective action Basis for Relief: Valves with stroke times 1 2 seconds cannot be accurately timed. Alternate Testing: Valves with reference stroke times 1-2 seconds will be cycled and timed-to verify the ve ve stroken in 1 2 seconds. Increased frequency requirements of IWV-3417(a) vill not be applied. This-is in compliance with Position 6 of Generic Letter 89-04
5 Relief Request tio. PV-24 Systems Con t a i n>..e n t Inerting System (76) Drawing: 2-47E860-1 Component Valve 76-653 Categcry: A, C Class: 2 Function: Purge check vcive for traverse incore probe guide tubes. Impractical Test Requirement: IWV-3521 and 3522 - Exercise valve closed once every three months. Basis for Relief: This purge check valve serves as an outboard containment u slation valve. Testing of this valve requires entry into
, containbant disconnecs.ian of the purge line for ic .ilat'on of test equipment. Because of the plant design, demonstrating closure can only practically be accomplished by pressurizing dovnstream, as is performed during leak rate testing in accordanc^ with 10 CPR 50 Appendix J. Conducting such a test would therefore pose a hazard to personnel safety or require the deinerting of containment for safe entry and would also require the depressurization of the purge line which could result in the introduction of moisture in these lines.
Alternate Testing: Proper valve closure will be verified by completion of local leak rate testing performed in accordance with 10 CFR 50 Appendix J. 4 l
Relief Request No. PV-25 System: Residual Heal Removal (RHR) (74) Core Spray (75) l Drawing: 47E811-1 47EB14-1. Components: Valves 74-54, -68 75-26, -54 Class: 1 Function: Testable Check Impractical Test Requirement: IWV-3521 and 3522.- Cycic quarterly, if not quarterly, perform cold shutdown. Basis for-Relief: Due to potentially inadvertent valve operation caused by non-class IE circuitry to the-valve operator, the air - supply is normally disconnected. Since these valves are located in containment,-entry to connect the air supply is not practical during operation and may not be practical during cold shutdown. Alternate Testing: Valves will be stroked by reconnection of the actuator air in cases durinc CSD when drywell entry is made. This testing vill be performed along with the other CSD valves-(i.e. , time permitting) with a rainimum of each refueling. b L _ _ _ _ _ _ _ _ _ . -
Relief Request No. PV-26 System: Control Rod Drive (CRD) (85) j Drawing: 47E820-2 Components: Valve 85-576 Class: 1 Function: Isolation Check to Feedwater Impractical Test Requirement: IWV-3521 and 3522 - Cycle valve closed quarterly. Btsis for Relief: This check valve may be open or closed during system operation. Plant design does not provide a practical means of demonstrating closure other than upstream pressurization, disassembly, or acoustical monitor techniques. Upstream pressurization or disassembly would require entry into primary containment to isolate feedwater from the vessel. i ernate ) 'ng: Proper valve closure will be verified by completion of local leak rate testing, performed in accordance with 10 CPR 50 Appendix J.
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Relief Request No. PV-27 System Main Steam (1) l Lraving: 47E801-1 k d- Components: Valves FCV-1-14, -26, -37, -51 1 l Class: 1 i j- Punction: Containment Isolation Impractical Test Pequirement: IWV-3423 - Leak test at full maximum function pressure
-differential.
t Basis for Relief: Due to testing techniques, valve manifold design does not allow testing at full function pressure differential. Such j' a test would subject the valve manifold to potentially- } damaging loads. Alternative l l Testing: Valves vill be reduced pressure tested at a differential j pressure. of 26 psig. i, } 3 4 i e i 1. i J. h x s J l d 3. - -100-i j .- 1 3~
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