ML20245C712
| ML20245C712 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/22/1989 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TAC-11324, TAC-11325, TAC-11326, NUDOCS 8906260262 | |
| Download: ML20245C712 (24) | |
Text
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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNES$EE 37401 5N 157B' Lookout Place JUN 221989 1 IJ.S iNuclear. Regulatory Commission ATTN: DocumenteControl Desk Washington, D.C. "20555
.Centlemen:
In the Matter of ') Docket'Nos. 50-259 Tennessee Valley Authority ) .50-260-50-296-BROWNS FERRY NUCLEAR PLANT'.(BFN) - AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME).SECTION 11 - PUMP.AND VALVE TESTING PROGRAM (TAC NOS. 11324, 11325, 11326):
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Reference:
- 1. NRC letter to.TVA dated May 19, 1989, " Safety Evaluation Report on the Inservice Test Program for Pumps and Valves, for Browns Ferry Nuclear Plant, Units 1 2, and 3" We have received the NRC Safety Evaluation Report (SER), reference 1,'and are l: evaluating:it. In addition to the relief requests that have already beeni
! granted by NRC SER (reference 1) there are several revisions to the pump and; valve program that were determined to be necessary during a recently completed surveillance procedure improvement program at BFN. Enclosure 1 contains a - '
. complete explanation of'the proposed changes to BFN's Pump and Valve (P&V)
L program, and enclosure 2 provides a summary list of the revisions.
1, L If you havo.any. questions, please telephone Patrick P.'Carler, BFN, (205) 729-3570.
Very truly your::,
1 l TENNEZSEE VALLEY AUTHORITY l
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Manager, Nuclear censing and Regulatory Affairs Rnclosures cc: See page 2 l:
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'8906260262 890622
.PDR- ADOCK 05000259 P PDC An Equal Opportunity Employer
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, . - JUN 221989 i> &
',. U.S. Wuclear Regulatory Commission pf- cc (Enclosures):
+ Ms. S. C. Black, Assistant Director
'.for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 p Mr. B. A. Wilson, Assistant Director for Inspection Programs TVA Projects Division-U.S. Nuclear. Regulatory Commission i "
Region II
'101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Browns Ferry Nuclear Plant
. Route 12, Box 637 p' Athens, Alabama- 35609-2000
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ENCLOSURE 1 REVI IONS To UPN's PUMP AND VALyg PROGRAM W
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- g. , Page 147 Relief Request number PV-14*
System Emergency Equipment Cooling Water (67) and Raw Cooling Water (24) 9 Drawing: 47W859-1 47W859-2 47W866-7 Valves: 67-541, 542, 584,'585, 648, 649, 657, 558, 559, 638, 639, 600, 601, 659, 660, 528, 529, 634, 635, 521, 522, 630, 631, 624, 625, 514, 515, 627, 628, 507, 508, 502, 622, 619, 656, 671, 679, 638, 3-24-831, 833, 796, 798, 709 (unit 1) 3-67-693, 694, 695, 696, 703, 704, 705, 706, 715, 716, 713, 714, 723, 724, 725, 726, 771' 772, 774, 775, 761, 762, 764, 765, 737, 738, 735, 736 Function: EECW: pass rated flow for the emergency coolers and provent backflow from opposito header.
RWC: Proveat backflow of EECW into RCW.
Impractical Test Requirement: Exercise valves closed every three months.
Basis for Relief System design prevents the valves from being verified closed by reverso flow or other conventional means. Therefore, closuro verification by disassembly will be reiuired.
l Since the valves can be verified open quarterly by flow verification, apparent disc free movement will be indicated.
Alicenativo Testing: Valves will be proven to close once per refueling cycle by disassembly and inspection.
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, page 156 Ealief Request number pV-23* page 1 of 2 System: Control Rod Drive Ilydraulic (85)
. *I' Drawing: 47W820-2 47820-5 (U2) 47820-6 (Ul&3)
Cater,ory Valves: FCV 85-39A (1-185) B FCV 85-398 (1-185) B 85-589 (1-185) C 85-597 (1-185) C 85-616 (1-185) C 85-617 (1-185) C Class: 2 i
Function: Control Rod Scram Water Flow path Imp ectical Test l Requirement: Exercise once every three months and measure stroke times. l Basis for Relief: These valves located on tho 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 reasons:
- a. A power reduction is required to test the scram function. Reducing power for the length of timo required to scram 185 rods is not practical,
- b. Fuol preconditioning must follow this power reduction to avoid possible fuel damage. The longer the reduction in powce, the longer the preconditioning.
Their proper functioning is most practically verified by an actual scram test.
- revised 5/89 0253k/20 l
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Relief Request Number PV-23 ~
Pagc 2'of 2 r a, :]
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~ Alternative- :)
- Test.ing: Scram' testing and rod' insert.lon timing will' be performed , .
'in accordance with Technical' Specifications'Section 4.3.c
.. (at: reactor coolant pressure 800 psig) for: t S.
1
- a. All control rods prior.to TIIERMAL POWER exceeding e 40 percent after each refueling outage.
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- b. 10' percent on a rotating. basis at least onco every 16 ~
weeks.
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- rovised 5/89 0253k/21
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ReIlef' Request Number PV-25*' Page 1 of 1.
[I' System:'
lo Containment Inerting (76),; Containment Atmosphere .
- -Diluting (84), Residual IIcat Removal Service Water (23),
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and Traversing Incore Probo (94).
Drawing: - 4 7W610-4 3-1, 4 7W812-1, 4 7W610 3, 4 7W862-1, ' 4 7W858-l',
l = T' , Impractical, Test-
!c Requirement: Stroke time corrective action, IWV-3417(a).
L h' Basic-for-l lRelieff Valves with stroko. times 5 2 seconds cannot be accurately .
. Limed.
Alternate Testing: Valves with.stroko times 5 2 seconds will be cycled and timed.to varify the valvo strokes in s 2 seconds.
Increased frequency requirements of IWV-3417(a) will'not i be applied.
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i Relief Request Number PV-31* page 1 of 1 )
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-' System: Reactor Core Isolation Cooling (71) ,
1tish Pressure Coolant Injection (73) ,
Drawing: 47W813 i 47W812-1
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Valves: 71-589, 502 73-625, 505 l
Function: Prevent backflow from CGT and PSC Impractical Test Requirement: Exercise valves closed very three months.
Basis for Relief: System design prevents the valves from being verified j closed by reverso flow or other conventional means. ,;
Therefore, closure verification by disassembly will be !
required. Since tho valves can be verified open quarterly by flow verification, apparent disc free moverent will bo indicated.
Alternative Testing: Valves will bo proven to close onco por refueling cycle by disassembly and inspection.
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- revised S/69 0253k/23 hu._. ---_m -
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, ~ Request for Relief PV-32*
1 Units - 1, 2 , 3 '
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'Cystem .- Standby Liquid Control l
. Drawing' -
. Valves- 63-514, 63-516
= Category - C Class. - 2 Function' -
Provides standby liquid control'from accumulator discharge flowpath and prevents backflow.
Impractical Test Requirement - Exerciso Valves 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 exists no flowpath by which the backscating capability of these check valves,63-514 and 516, can 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, to verify its, backsoating capability. Should.the disassembled valvo fail to function properly, the other' valve will also be disa'esembled and examined. These valves will-be
' full stroked in the open position during quarterly pump testing.
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Page 165b
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n . Y : Request for Relief PV-33*
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P , . (Units: - 1,2,3 System -
Emergency Equipment' Cooling Water I1 e ,
? Drawing -
.47W859-l' LValves- 67-538, 5'39, 652, 653, 787, 789 r z.:. Category - C. .
Class. - 3 Function- -
Prevents short-circuiting of the cooling water to the control air conditioning water chillers, and ' the cross connection of the EECW supply headers.
Impractical Test Requirement -
Exerciso valvec once every three months.
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Basis for. Relief -
The system configuration provides no means by which to verify the backseating capability of these valves c during plant opetttion or shutdown.
- Alternate Testing -
A minimum of two check valves will be disassembled at each refueling out. age,'on a rott.tlonal basis, to verify its backseat.ing capability. Should the disassembled valve fail to function properly, all other valvus in this category will-also be disassembled and examined. These valves will be full' stroked- in the open position quarterly as required.
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Page 165c-Request for Relief PV-34*
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- Units. -
1,2,3 I System' -
Diesel Cenerator Air Starting i]1 Drawings -
. Valves. -
3-A-SV-3,*3-A-SV-4, 3-B-SV-3, 3-B-SV-4, 3-C-SV-3, 3-C-SV-4, 3-D-SV-3, 3-D-SV-4 1 Category' - B Class -
WNCC l a
Function -
To provide initial compression to start the diesel generator engines.
Impractical Test Requirement -
Stroke time test valves on a quarterly basis.
Basis for Relief -
The diosol air start valves'aro solenoid-valvos which are accessible only by disassembling the engine starter system. These valves cannot be operated
. independently, and operate only from a diesel engine sta'rt signal. Thoro exists'no indicator lights or
, visible obturator by which to time the stroking of those. valves.
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Alternato Testing -
Due to the configuration of the diosol air' start system, there exists no method to individually time '
i the stroke of each air start valvo. The plant Technical Specifications require that the period between:the initiation of a diesel engine start signal and the actual engine start not to exceed ten.
seconds. ..This specification is verified monthly as required by the Technical Specification surveillance requirements. During a diosol onsino start, the diesel air start valves must move from the closed position to the open position to.cause the engine to ,
start. Failure of the valves to operate properly will 1 prevent tho ensino from starting.
Tho successful start of a diosol engine start within.
ten seconds of the fast start initiation signal will be acceptable to demonstrate the proper operation of the air start valves. This test will be conducted as required by the plant Technical Specifications, i
- added 5/89 0253k/26
) Page 173 Cold Shutdown Justification Nutuber 7*
System: Main Steam Drawing: 47W801-1 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 T.W-3412(a) , valves shall be exercised unless such i operation is not practical during plant operation. Valves will be partially stroked quarterly, full stroke tested at j
cold shutdown and fail-safe tested at each refueling outage. j 4
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L' 4. System: . Control Air (32) . . .
. Drawing: 4 7W84 7-9
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.. ( Valves:- .32-62,.32-63 li Category: a f:, Class: 2' Function! To isolate:the control air system to the drywell during a primary containment isolation. ;
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Justification: These valves are leak tested in tho Appendix J Test Program,
,"' and are stroke timed remotely in accordance with ASME Section XI requirements-on a quartorly basis. . ilowever, these valves
'p can only be fail-safe position tested.when the plant status allows the isolation of the cc.atrol air system to the drywell. The fall-safe testing will be performed only when 7: the plant is in cold shutdown and the control air system to
"( the drywell is not required to be in service.
0253k/28
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ENCLOSURE 2
SUMMARY
LIST OF REVIS10HS TO UFN's PbdP AND VALVE PROGRAM e
t h
I l
9 w
REVIS?ONS TO Tile BROWNS FERRY PUMP & VALVE PROGRAM A. Additions to the PV Program
- 1. Raw Cooling Water Supply Check Valvo 1-24-709, to the Control Room .
Water chillers, performs a safety function in the cloopd position and is being added to the program and tested in the closed position.
Because this valve cannot be tested in the closed position during I plant operation, it has been added to relief request. No. PV-14 and will be removed and visually inspected at each refueling outage in accordance with URC Ceneric Letter 89-04.
- 2. Control Room Chiller Raw Cooling Water Check Valvo 24-851 has been determined to perform a safety function in the open position and is being added to the program.
- 3. EllR System Fill Check Valves74-192, 802, 803, and 804 have been determined to perform safety functions only in the closed position.
The program is being revised to reflect this determination.
- 4. Core Spray System Fill check Valves75-606, 607, 609, and 510 have been determined to perform safety functions only in the closed posit.lon. The program is being revised to reflect this determination.
D. Deletions from the PV Program
- 1. Standby Coolant Drain Valvo FSV-23-56, is a 3/4-inch drain valve which is normally opened and closes on the opening of one of the standby coolant. valves to the RitR heat exchangers. Those drain valves are currently listed in the program but cannot be stroko time tested since there are no position indicators, and the valve operates on a signal from another valvo. The failure of these valves would not increase the probability or consequences of an accident nor would it provent the reactor from being brought to or maintained at. safe shutdown.
This valve is not safety-related and, thereforo, should not be included in the program. The program is being changed t.o remove this valve.
- 2. RCIC Turbine Stop and Control Valves 71-9 and 71-10, respectively, are currently listed in the program. The turbino stop valvo must open to allow steam to the turbino and must close to protect. the turbino from over speeding and, therefore, must be tested in the open direction and in the fail-safe mode. Fall-safe testing for this valvo la being added to the program. The control valvo is exempt from testing since it is provided only for system control and is being removed from the testing program.
- 3. IIPCI Turbine Exhaust condensato Pot. Level Control valvo 73-8 is provided for system control and is exempted from the Section XI Program. The function of this valvo is verified by the quart.ccly operation of the ItPCI turbino in accordanco with TS 4.5.E. This valvo is being deleted from the testing program.
0253k/16
,: 4 L B. Deletions from the PV program (Continued) f
- 4. HPCI Turbine Stop and Control Valves 73-18 and 19, respectively, are currently listed in the program. The turbine stop valve must open to ,
allow steam to the turbino and must close to protect the turbine from over speeding and, therefore, must be tested in the open direction and in the fail-safe mode. Fall-safe testing for this valve is being added to the program. The control valve is exempt from testing since it is provided oaly for offstem control and is being removed from the testing program. Such valves are tested by system operation.
- 5. HPCI Turbine Exhaust. Drain Check Valve 73-609 performs a safety function in the closed position and is tested in this position by the Appendix J Program. This valve provides system control in the open position and thus doen not require testing in this position. The program is being changed to delete the requirement for open position testing.
- 6. Steam Supply Drain Level Control Isolation Valve 71-5 is provided for
. system control only and is exempt from the Section XI testing program. This valve is being removed from the program.
- 7. Drywell oxygen Analyzer Isolation valves 76-51, 52, 53, 54, 61, 62, 63, and 64 have been removed from t.he unit 2 Containment Inerting System and are, therefore, being deleted for that unit.
C. Changes to Existing Relief Request
- 1. Drywell Compressor Suction Isolation Valves 32-62 and 63 are required to fail to the closed position. The program is being bevised to reflect the fail-safo testing which is performed on these valves.
This testing, as required by IWV-3415, can only be performed during cold shutdown when it is permissible to isolato control air to the drywell. Cold Shutdown Jusilfication No.12 is being added concerning the testing of these valves.
I
- 2. RCIC Putnp Inlet Check Valve from Condensato Storage Tank 71-502 cannot i be tested quarterly in the closed position due to the system i configuration. This valve is being added to Relief Roquest PV-31 to be disassembled and inspected at each refueling outage in accordance with NRC Concric Letter 89-04.
- 3. The ASME Code Class for valves67-556, 598, 785, and 24-765 is currently shown as class 3 in the program. These valves are actually in non-code portions of their respective systems. Itowever, since these valves are required to open to provido a cooling water dischargo flowpath, they are included in the valve testing program. The program is being revised to reflect the correct codo class for these valves.
- 4. Fuel Pool Cooling Supply Check Valves78-526 and 527 have been modifled and no longer have a safety function in the closed position.
The program is being revised to r' emove the requirement for closed position testing. PV-22 should be doloted, because these valves no longer have a closed safety position.
0253k/17
l 1
c,, , .. ..
C. Changes to Existing Relief Request (Continued) )
- 5. Condensate Cupply Check Valve 73-505 to HPCI is required to be full stroked to the closed position quarterly. However, this valve has no neans by which to verify iLa position. Valve 73-505 is being added to Relief Request PV-31 and will be disassembled and inspccLod in
,f, accordance with NEC Conoric Letter 89-04. i l
- 6. Relief Fequest PV-25 is being revised to include the RCIC (71) which was c.. . - by alstake.
- 7. Main Steam Isolation Valves 1-14, 1-15, 1-26, 1-27, 1-37, 1-38. 1-51, and 1-52 can only undergo fail-safe testing when access to the drywell is permitt.ed. Cold Shutdown Justification No. 7 will be reviso$ to state that fail-safe testing will be performed at cach refuelint cutage. Part stroke testing will be performed quarterly and full stroke testing will be performed at cold shutdown, per the requirements of TS Tabic 4.1.A.
- 8. Control Rod Drive Cooling Water and SCRAM Accumulator Charging Check Valves85-589 and 85-597, respectively, are listed in Relief Request PV-23. It has been determined that 85-597 does not perform a safety i
[ function in the open position based on paragraph 3.4.5.3.1c of f.he FSAR. Valve 85-589 is tested in the open position during the technical specification required control rod SCRAM and ecset tests.
Both 85-597 and 85-589 are verified closed during these control rod SCRAM time tests. This testing will be performed at the frequency required by TS 4.3.C. Relief Roquest PV-23 is being revised to reflect this testing.
D. New Relief Request '
- 1. SLC Pump check valves63-514 and 516 perform a safety functio in the closed position based on the FSAR supposition that the opposite pump relief valve could stick in the open position. These valves can only be tested by removal and inspection at refueling outages. This test will be performed per the requirement of TS 4.4. A.2.B. Relief Request 4 PV-32 has been added to allow disassembly and inspection at each !
refueling outage in accordance with NRC Cenoric Letter 89-04.
- 2. EECW Supply Choc'k Valves to the Control Room Chillors67-538, 539, 652, 653, 787 and 789 are required to open to supply emergency cooling water to the control Bay Chillers and are required to close to provent cross connection of the EU W headers. The program is being revised to test these valves in both directions. The closed position verification cannot be performed due to the system configuration.
proper valvo closure will bo performed by disassembly and inspection at refueling outages in accordance with NRC Ceneric Letter 89-04 as described in Relief Request PV-33.
- 3. ' Diesel Generator Air Start valves 3-A,B,C,D-SV-3 and 4 cannot be tested individually or stroke timed. Relief Request PV-34 is being submitted to use the surveillance'insttmetion which verifles the fast start of the diesel generator within 10 seconds of initiation as tho
( time test for these valves. These valves perform no safety function
{ in the closed position and, therefore, will not be tested in this I direction.
0253k/18
__ ______ ______ i