Text

ASME Section XI, Revised Pump & Valve Test Program
	ML20148G614
Person / Time
Site:	Browns Ferry
Issue date:	03/25/1988
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20148G601	List: ML20148G596; ML20148G614;
References
	PROC-880325, NUDOCS 8803290188
	Download: ML20148G614 (189)
	v • d • e

-

a ENCLOSURE 1 ASME SECTION XI REVISED PUMP & VALVE TEST PROGRAM 46 a

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TABLE OF CONTENTS e

I.

Introduction / Policy Statements.

2 II.

Pump and Valve Inservice Test Program.

8 III. Relief Requests.......................

132 IV.

Cold Shutdown Justifications..

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Page 2 I.

INTRODUCTION / POLICY STATEMENTS A.

Introduction 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 Boiler and Pressure Vessel Code and appilcable addenda. Specific exceptions to these requirements ar9 included here as Relief Requests. As specified in 10 CFR 50.55a(b) and 10 CFR 50.55a(g)(4)(ii), the effective odition of Section XI with regard to this program is the 1980 edition through the winter 1980 addenda for units 1, 2, and 3.

The effective interval dates for this inservice testing program are August 31, 1982, to August 31, 1992.

The program identifies the pump and valve inservice testing that will be performed at Browns Ferry Nuclear Plant to comply with the requirements of 10 CFR 50 and plant technical specifications. Where this test refers to specific paragraphs in Section XI, the paragraphs

- in the 1980 edition through winter 1980 addenda are referenced.

B.

Pump Inservice Testing Program The pump test program shall be conducted in accordance with Subsection IWP of Section XI of the ASME Boiler and Pressure Vessel Code except where relief has been requested under the provisions of 10 CFR 50.55a(s)(5)(lii).Section 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 requests for relief are also listed.

6 1.

The pump acceptable and allowable ranges have been expanded from 1.02 to 1.05 and 1.03 to 1.06, respectively, based on instrumentation accuracies. This has been in effect since 1980 with no catastrophic pump failures. The pump program has f

successfully identified pumps requiring maintenance prior to significant pump performance degradation. This is within the guidelines of IWP-3210.

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Page 3 I.

INTRODUCTION / POLICY STATEMENTS (Continued)

C.

Valve Inservice Testing Program 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 CFR 50.55a(g)(5)(ill). The valve test program is included in part II.

1.

Category A Valves Valves for which seat leakage is important may generally be classified as pressure isolation valves (PIV), containment isolation valves (CIV), or both pressure and containment isolation valves (PIII/CIV).

Containment isolation valves are tested in accordance with Section XI requirements for category A valves with the exception of the seat leakage tests (IW-3420).

~

The seat leakage testing of these valves (IW-3421 through IW-3425) meets the intent of Section XI, but the actual test I

methods shall be in accordance with the Appendir J 10 CFR 50 type C CIV test program.

The pertinent leak rate criteria for CIVs is that the total leak k

rate for all penetrations and valves be less than 0.60 L,*.

The Browns Ferry plant was not designed to perform the individual Section XI Category A leak test.

Accordingly, CIV seat leakage testing shall be performed in accordance with the requirements of 10 CFR 50 Appendix J type C, in lieu of the category A i

requirements of Section XI for those penetrations where valves f

cannot be tested individually.

Where individual valve leakage rates are applicable, the requirements for analysis of leakage rates and corrective actions, paragraphs IW-3426 and IW-3427, are met as follows for CIVs.

CIVs are assigned conservative reference leak rates based upon the valve size and the total

L, - Maximum allowable leakage rate 9

0379B Jj

Page 4 I.

INTRODUCTION / POLICY STATEMENTS (Continued)

C.

Valve Inservice Testing Program (Continued) 1.

Category A Valves (Continued) allowable containment penetration leakage. 0.6 L,.

The total of all of the reference leak rates is set equal to approximately 40 percent of the total allowable containment leakage, (i.e.,

40 percent of 0.6 L,); this provides a comfortable margin even if all valves are leaking their respective reference leak rates.

This criteria is more stringent than specifically required by either Section XI or Appendix J.

During refueling outages, maintenance is performed, if required, in an attempt to restore all CIVs to below their reference leak rates and as close to zero leakage as reasonably achievable; this ensures the ability of the containment system to satisfy the integrated leak rate testing criteria and to provide adequate margin for valve degradation over the next fuel cycle.

While every attempt is made to maintain CIVs at zero leakage or below their reference leak rates at all times, a valve leaking in excess of its reference value may remain operable and left "as is" in certain situations, provided that an evaluation by a Nondestructive Examination Level III local leak rate test examiner finds it acceptable.

While the maximum permissible leak rate at this time would, by plant technical specifications, be limited to the current margin between overall containment leakage and 0.6 L,, maximum single penetration leakage is at all times administratively limited to 20 percent of 0.6 L,.

Any such valve exceeding the referenced leak rate but not in excess of 20 percent of 0.6 L, would be repaired or replaced no later than the next refueling outage or even during the next cold a

shutdown of sufficient duration, if practical, I

2.

Thermal Relief Check Valves (TRCVs)

One penetration has been fitted with small check valvec designed to relieve pressure due to thermal expansion of fluid between normally shut isolation valves.

TRCVs will be leak tested in the closed position per Appendix J (10 CFR 50).

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Page 5 I.

INTRODUCTION / POLICY STATEMENTS (Continued)

C.

Valve Inservice Testing Program (Continued) 3.

Excess Flow Check Valves Excess flow check valves are installed in instrument lines penetrating containment in accordance with Regulatory Guide 1.1.

As such, the lines are sized and/or orificed such that offsite doses will be substantially below 10 CFR 100 limits in the event of a rupture.

Therefore, individual leak rate testing of these valves is not required for conformance with Appendix J 10 CFR 50 requirements.

Functional testing of valves to verify closure can 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 Techn'ical Specification 4.7.D.l.d at least once per 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 interfered with should testing be performed during plant operation.

Also, process liquid will be contaminated to some degree, requiring special measures to collect flow from the vented instrument side. Functional testing with verification that flow is checked will be performed at least once per operating cycle per Technical Specification 4.7.D.l.d.

4.

Fall-Safe Actuators Normal operation of all fall-safe valves utilizes the fail-safe actuator with the exception 'st MSIVs. MSIVs are tested in accordance with IWV-3415.

'l 5.

Valve Timing

('

During each full-stroke test of a power operated valve, the 4

full-stroke time shall be measured in accordance with Article IWV-3413.

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Page 6 I.

INTRODUCTION / POLICY STATEMENTS (Continued)

C.

Valve Inservice Testing Program (Continued) 6.

Position Indication Verification Valves with remote position indicators shall be observed at least once every two years to verify that valve operation is accurately indicated, except as allowed by IWV-3416.

7.

Exercising of Normally Closed Check Valves Check valves, whose safety function is to open, will be full-stroke tested as required in IWV-3522(b).

Since disc position is not always observable, verification of the safety

?

analysis design flow rate through the valve is considered an adequate demonstration of the full-stroke requirement.

8.

Revision of Valve Stroke Time Valve stroke times are listed in the implementing surveillance instructions (sis).

In the event of a repair, replacement, or system redesign, stroke times may be changed in accordance with IWV-3413 consistent with design criteria for the valve.

In addition, changes in Final Safety Analysis Report or technical specification stroke times may require program SI changes.

9.

Instrumentation for Testing Where devices monitoring appropriate parameters exist, permanently installed instrumentation will be used during pump performance testing.

Reference RFR PV-5.

+ 4 10.

Category B-Passive Valves These valves which have no Section XI testing requirements are

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valves in safety-related systems which are not required to change

'i position in order to accomplish their required safety function.

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Page 7 I.

INTRODUCTION / POLICY STATEMENTS (Continued)

C.

Valve Inservice Testing Program (Continued) 11.

Cold Shutdown Testing (CSD)

CSD valve testing as identified by the licensee will be conducted pursuant to the following conditions.

Valve testing will commence as soon as possible, but no later than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after reaching CSD conditions. Valve testing will proceed in a normal manner until all testing is complete or the plant is ready to return to power. A completion of all valve testing is NOT a prerequisite to return to power.

Any testing not completed 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.

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For planned cold shutdowns where ample time is available 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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PUMP AND VALVE INSERVICE TEST PROGRAM m

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Page 9 Valve Types l

Valve Actuator Types Code Sviabol Meaning l

Code Meaning l

GA Gate l

A0 Air Operator I

BF Butterfly l

H Manual Operator I

BA Ball l

M0 Motor Operator l

CK Check l

SELF Self Actuated i

GL Globe l

S Solenoid Operator I

AN Angle (Globe) l X

Explosive i

RD Rupture Disk l

H0 Hydraulic Operator l

RV Relief Valve l

E/H Electro-Hydraulic Operator i

SC Stop Check l

Cy1 Cylinder i

XFC Excess Flow Check l 1

PL Plug l

l l

Valve Positions l

Valve Testing Requirements Code Meaning l

Code Meaning i

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Q Full Stroke Quarterly l

C Closed l

ST Stroke Time 1

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LT Leak Test LO Locked Open l

LT(R)

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Refuel Cycle I

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FS Fall Safe Per l

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Shutdown l

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Pago 10 System Abbreviation System Number Flow Diagram Main Steam MS 1

47W801 Domineralized Water DW 2

47W856 Feedwater FW 3

47W803 Main Steam (Vac Beke)

MS 10 47W801 Auxiliary Boiler AB 12 47W815 Diesel Fuel Transfer DFT 18 47W840 Residual Heat Removal RHRSW 23 47W858 Service Water Raw Cooling Water RCW 24 47W844 Control Air CA 32 47W1847 l

47W2847 47W3847 Service Air SA 33 47W845 Sampling and SAWQ 43 47W610-43 Water Quality Standby Liquid Control SLC 63 47W854 Reactor Building RB HVAC 64 47W865 Heating and Ventilation Emergency Equipment EECW 67 47W859 Cooling Water 47W866 Reactor Water RECIRC 68 47W817 Recirculation i

Reactor Water Cleanup RWCU 69 47W810 Reactor Building RBCCW 70 47W822 Closed Cooling Water Reactor Core RCIC 71 47W813 Isolation Cooling High Pressure HPCI 73 48W812 I

i Coolant Injection i

Residual Heat Removal RHR 74 47W811 Core Spray CS 75 47W814 Containment Inerting CI 76 47W860 l

Radwaste RW 77 47W852 Fuel Pool Cooling FPC 78 47W855 h

and Domineralizing 1

Containment Atmosphere CAD 84 47W862 Dilution

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Radiation Monitoring RM 90 47W610-90

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Page 11 ABBREVIATIONS Ata Atmosphere CIV Containment Isolation Valve Capsr Compressor Cond Condenser Cont Containment CSD Cold Shutdown CST Condensate Storage Tank Det Detection DG Diesel Generator Disch Discharge Dr Drain DW Drywell Eq Equipment Ex Exhaust FD Floor Drain Hd Tk Head Tant Hde Header HP High Pressure i

Htz Heat Exchanger Inbd Inboard Isol Isolation Min Minimum MSIV Main Steam Isolation Valve N

North Outbd Outboard d

' PIV Pressure Isolation Valve PSC Pressure Suppression Chamber Rm Room S

South SD Shutdown

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SDIV Scram Discharge Instrument Volume Sect Sectionalizing Turb Turbine Wtr Water Yd Yard h

03798 A

Pcg2 12 BR0hses FEHRY 81UCLEAR PLANT PupF TEST PROGRAM UNITS 1, 2, AND 3 1

Inlet Differential Flov Vibration Bearing Observe Lube Oil Class Drawines Speed Pressure Pressure Rate Amplitude Temperature Level l Pressure RHR (4) 2 47W881-1 NR 0

0 0

0 PV-1 PV-1 HPCI (I) 2 47W812-1 0

0 0

PV-l 0

RCic (I) 2 47W813-1 0

0 0

PV-1 0

i CS (4) 2 47W814-1 NR 0

0 0

0*

PV-l PV-1 SLC (2) 2 47W854-1 NR PV-2 PV-2 0

0 PV_I,3 0

RHRSW (12) 3 47W858-l NR 0 (Note 2) 0 0

0 PV-1 PV-1 47W859-1 Diesel Fuel NC 47W840-1 NR PV-2 PV-2 0

0 PV-I PV-8 Transfer (16)

NOTES:

I.

Nun 6ers in (

) denote number of pumps per unit except for RHRSW end diesel fuel transfer. AlstSW pumps i: '

There are four diesel fuel transfer pumps for units I and 2 diesel generators and four for are comanon.

unit 3 diesel generators.

2.

River level will be recorded for suction pressure for the RHRSW pumps.

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TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant Units 1.2.&3 Inservice Testing Program System: Main Steam (1)

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t TENNESSEE VALLEY AUTHORITY i

Browns Ferry Nuclear Plant

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i Inservice Testing Program j

Page 2 of 13 P

System: Emergency Equipment Cooling Water (67)

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TENNESSEE VALLEY AUTHORITY j

Browns Ferry Nuclear Plant

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Units 1,2,&3 j

Inservice Testing Program i

Page 5 of 13 '

1 System: Emergency Equipment Cooling Water (67)

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TENNESSEE VALLEY AUTHORITY j

Browns Ferry Nuclear Plant Units 1,2,&3 Inservice Testing Program' i

Page 6 of 13 "

j System: Emergency Equipment Cooling Water (67)

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TENNESSEE VALLEY AUTHORITY f

Browns Ferry Nuclear Plant i

Units 1,2,&3 Inservice Testing Program Page 7 of 13 System: Emergency Egalpment Cooling Water (67)

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a TENNESSEE VALLEY AUTHORITY f

Lrowns Ferry Nuclear Plant Units 1,2,&3 Inservice Testing Program Page 8 of 13 System: Emergency Equipment Cooling Water ((,7)

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'i TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant Units 1,2,&3 Inservice Testing Program Page 11 of 13 System: Emergency Equipment Cooling Water (67)

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I ii TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant Units 1,2,&3 Inservice Testing Program Page 12 of 13 System: Emergency Equipment Cooling Water (67)

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Browns Ferry Nuclear Plant if Units 1,2,&3 Inservice Testing Program Page 13 of 13 j

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Units 1.2.&3 Inservice Testing Program Page 1 of 4 System: Emergency Equipment Cooling Water (67)

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Units 1,2,&3 Inservice Testing Program -

Page 6 of 13 System: Residual Heat Removal (74) i 47W811-1

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TENNESSEE VALLEY AUTHORITY

4 j

Browns Ferry Nuclear Plant

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Inservice Testing Program -

Page 8 of 13 System: Residual Heat Removal (74)

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TENNESSEE VALLEY AUTHORITY f

Browns Ferry Nuclear Plant Units 1,2,&3 Inservice Testing Program -

Page 9 of 13 System: Residual Heat Reinoval (74) i 47W811-1 D

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i 4l TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant Units 1,2,&3 Inservice Testing Program Page 11 of 13 System: Residual Heat Removal (74) 47W811-1 i

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TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant Units 1,2,&3 Inservice Testing Program Page 12 of 13 System: Residual Heat Removal (74) i 47W811-1 y

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Browns Ferry Nuclear Plant Units 1,2,&3 Inservice Testing Progren a

Pags 13 of 13 System: Residual Heat Removal (74) i 47W811-1

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Page 124 CATEGORY B - PASSIVE VALVES System:
RHRSW (23)
Drawing No. 47W858-1 Valve Positior.
Drawing Coordinates 1-23-37 0
E-1 1-23-31 0
E-1 1-23-43 0
E-3 1-23-49 0
E-4 2-23-37 0
E-5 2-23-31 0
E-5 2-23-43 0
E-7 2-23-49 O
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Page 125 CATEGORY B - PASSIVE VALVES System:
SLC (63)
Drawing No. 47W854-1 Valve Position Drawint Coordinates63-522 LC D-4 63-509 LC E-4 63-518 LC B-4 63-515 LO D-5 63-517 LO D-6 63-506 LO E-4 63-507 LO E-6 63-511 LC E-6 63-504 C
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Page 126 CATEGORY B - PASSIVE VALVES System:
EECW (67)
Drawing No. 47W866-7 4
Valve Position Drawing Coordinates L
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D-5 3-67-779 0
H-6 Drawing No. 47W859-1 67-504 C
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Page 127 CATEGORY B - PASSIVE VALVES System:
HPCI (73)
Drawing No. 47W812-1 Valve Position Drawing Coordinates i
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Page 128 CATEGORY B - PASSIVE VALVES System:
RCIC (71)
Drawing No. 47W813-1 Valve Position Drawing Co>rdinates 71-16 LO G/H-3/4 71-37 0
D-5 71-570 LC D-10 71-571 LO D-10 71-588 (C Passive)
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Page 129 CATEGORY B - PASSIVE VALVES System:
RHR (74)
Drawing No. 47W811-1 Valve Position Drawing Coordinates 74-55 LO C-5 4
74-49 LO C-6 74-69 LO C-7 74-670 LC D-6 4
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Page 130 CATEGORY B - PASSIVE VALVES System:
RHR (74)
Drawing No. 47W811-1 Valve Position Drawing Coordinates 74-33 LO G-10 74-44 LO E/F-10 74-86 LO F-4 74-87 LO E-4 74-89 LO F-8 74-90 LO E-8 74-91 LC E-7 74-817 0
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Page 131 9
CATEGORY B - PASSIVE VALVES System: Core Spray (75)
Drawing No. 47W814-1 Valve Position Drawing Coordinates 75-1 0
F-3 75-29 0
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G-7 75-11 0
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Page 133 Relief Request Number PV_-1 Page 1 of 1 System:
Various Drawing:
Various Pumps:
RER pumps A, B, C, D; HPCI pump; RCIC pump; CS pumps A, B, C, D, SLC pumps A, B; RHRSW pumps A1, A2, A3, B1, B2, 83, C1, C2, C3, Dl, D2,D3; Diesel Fuel Transfer lAl, lA2, 181, 182, 1C1, IC2, IDI, ID2, 3A1, 3A2, 3B1, 3B2, 301, 3C2, 3Dl, 3D2 Class:
Class 2, except RHRSW pumps which are class 3 and Diesel Fuel Transfer which are NC.
4 Function:
ECCS and Core Heat Removal (RHRSW pumps).
I Provide DG fuel.
4 Impractical Test Requirement:
Monitoring bearing temperatures annually during inservice testing and observing lube oil level / pressure.
Basis for Relief:
All of these pumps except SLC, HPCI, RCIC, and Diesel Fuel Transfer have water lubricated pump bearings. The RHR, CS, and RHRSW pump bearings are lubricated by water supplied by the pump itself.
DFTPs are lubricated by the diesel fuel they are pumping.
Satisfactory pump operation is indicative of sufficient bearing lubrication.
HPCI and RCIC have oil cooled bearings, but these pumps cannot be operated lons enough to reach stable bearing temperatures without overheating the torus and causing plant shutdown.
SLC and Diesel Fuel Transfer i
boarings are not instrumented.
The HPCI bearings, which are instrumented, are monitored during testing.
RCIC bearings do not have temperature instrumentation.
i
,a Alternative Testing:
Vibration measuremonts are taken on all of the Section XI pumps to ensure detection and correction of changes in bearing performance while the pumps are still capable of
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satisfactory operation in place of temperature c.
I monitoring.
Lube oil level / pressure is observed on tho
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pumps which are not water or diesel fuel lubricated.
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Page 134 Relief Request Number PV-2 Page 1 of 1 System:
Standby Liquid Control (63), Diesel Fuel Transfer (18)
Drawing:
47W854-1, 47W840-1 Pumps:
A,B (SLC), lA1, lA2, 181, 1B2, 1C1, 102, 1D1, ID2, 3A1, 3A2, 381, 3B2, 3C1, 3C2, 3Dl, 3D2 (Diesel Fuel Transfer)
Class:
Class 2 (SLC), NC (Diesel Fuel Transfer)
Function:
Injection of Sodium Pentaborate into Rx Vessel (SLC)
Transfer Diesel Fuel to Day Tank (DFT)
Impractical Test 4
Requirement:
Measure inlet pressure prior to and during pump test and I
measure pump delta P during pump test.
a 1
(
Basis for Relief:
During testing, these pumps take suction from a tank that has a relatively small range of level 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.
i l
Alternative Testing:
SLC:
Pump discharge pressure will be measured during quarterly testing.
Diesel Fuel Transfer:
Flow rate will be measured
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l quarterly utilizing existing tant level instrumentation.
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Page 135 Relief Request Number PV-3 Page 1 of 1 System:
(1)
Standby Liquid Control (63)
(2)
Diesel Fuel Transfer (1B)
Drawing:
(1) 47W854-1 (2) 47W840-1 Pumps:
(1)
A,B (2) 1A, 18, 10, 1D, 3 A, 3B, 3C, 3D Class:
(1)
Class 2 (2) NC Function:
(1)
Injection of Sodium Pentaborate into RI Vessel (2)
Pump diesel from seven-day tank to day tant Impractical Test Requirement:
IWP-3500(a), five-minute minimum run time.
Basis for Relief:
(1)
The volume of the test tank (210 gallon capacity) prohibits running the pumps (flow rate of approximately 55 spm) for five minutes.
These pumps are tested by circulating liquid from a test tank for two minutes and measuring the volume change in the tank. A five-minute minimum functional test which involves recirculating water back to the test tank is run before the system is lined up for the Section XI test requirement.
This five-minute test is of sufficient length for all parameters to stabilize and the two-minute minimum test is run immediately afterward.
(2)
Depending on the level of the day tank when the surveillance procedure is performed, the high lovel
']
switch could stop the pump before data is accumulated, iy Alternative 15 Testing:
(1) Measure parameters during the two-minute minimum test.
9 (2). Test will be performed when level of tank permits N
pumps to be run for as long as possible, at least once per six months.
The existing fuel level gauge l
will be utilized to measure flow.
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0302B
Page 136 Relief Request Number PV-4 Page 1 of 1 System:
All ASME Section XI Addressed by Tech Specs Drawing:
All ASME Section XI Component:
All ASME Section XI Pumps & Valves Class:
2, 3, and NC Function:
Various Impractical Tast Requirement:
IWV-3416, all valves operable for system to be operable.
IWV-3417, (a), testing valves that failed during CSD prior to startup.
s 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 startup. The plant technical specifications limiting conditions of operation clearly 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.
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Page 137 x
Relief Request Number PV-5 Page 1 of 2 System:
As listed on page 11 Drawing:
As listed on page 11 Components:
Installed plant instrumentation used to measure pump parameters.
Class:
2, 3, and NC Function:
Measurement of pump parameters.
Impractical Test Requirement:
a.
Instrument accuracy shall be within the limits of table IWP-4110-1, Paragraph IWP-3210, Allowable Ranges of Inservice Test Quantities and Paragraph IWP-4120, 3
Full-Scale Range Requirement.
~
b.
Velocity measurement shall be used instead of displacement as an alternative method of determining vibration amplitude.
^
Basis for Relief:
The accuracy of installed plant indicators is 1 2% of full scale.
However, the accuracy of installed transmitters and square rooters is 0.5% and, when these are taken into account, the instrument loop accuracies are 2.5% and 3.0% for l
pressure loops and flow loops, respectively.
The diesel fuel transfer pumps are not instrumented to measure flow other than a level gage on the day tank. The plant installed instruments will continue to be used since any alternate method such as connecting instruments into the system or replacing plant instrumentation will not significantly increase the repeatability of the instruments for trending, j
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Page 138 Relief Request Number PV-5 Page 2 of 2 Alternative Testing:
Inservice tests will be completed utilizing existing plant instrumentation.
The pump acceptable and allowable ranges have been expanded from 1.02 to 1.05 and 1.03 to 1.06, respectively, based on instrumentation accuracies.
The diesel fuel transfer pumps will be proven to pump within 10 percent of their baseline value flow rate, utilizing existing plant instrumentation.
Measurement of velocity shall be used to determine vibration amplitude. The acceptable and alert ranges are as stated below.
One point will be trended, utilizing broad band unfiltered measurements with an instrument with a calibrated frequency response range of 10-1000 HZ.
Test Acceptable Alert Required Quantity Range Range Action Range V
0<V11.5Vr 1.5V <V13.0Vr V>3.0Vr r
NOTE:
V is defined as vibration velocity in in/sec and Vr is the baseline value.
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page 139 Relief Request Number PV-6 Page 1 of 1 System:
Main Steam Drawing:
47W801-1 Valves:
1-5, 1-19, 1-22, 1-30, 1-31, 1-34 Category:
B,C Class:
1 Punction:
ADS Valve, Code Safety / Relief Valve Impractical Test Requirement:
Exercise valve once every three months.
Basis for Relief:
The six safety relief valves assigned to the ADS system perform an essential safety function when operated by the pneumatic actuator with gas supplied through the ADS solenoid valves. Operation of these valves is not j
practical during power operations because this action will 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 time trending 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 i
attendant noise).
1 Alternative Testing:
The ADS valves will be exercised once each operating I
cycle in accordance with Technical Specification 4.6.D.2 which provides manual opening of each ADS valve (with i
reactor dome pressure greater than or equal to 100 psis) 1 observing either control valve or bypass valve response or corresponding change in measured steam flow.
Valves will be verified to stroke time in two seconds or loss.
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Page 140 Relief Requast Number PV-7 Page 1 of 1 System:
Nuclear Boller Drawing:
47W801-1 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 Class:
3 Function:
MSRV Discharge Pipe Vacuum Breaker Impractical Test Requirement:
Exercise valve once every three months.
Basis for Relief:
These valves are located in the drywell and access during operation is not practical.. The drywell 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 3
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.
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Page 141 Relief Request Number PV-8 Page 1 of 1 System:
Reactor Feedwater Drawing:
47W803-1 Valves:
3-554, 558, 568, 572 Category:
A,C Class:
1 Function:
Containment Isolation Impractical Test Requirement:
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 feedwater/ condensate systems are supplying feedwater 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 l
remains open.
Due to the necessity of maintaining this flow path in virtually all modes of operation, closure i
testing is only practical during extended outages such as refueling during which these systems are shutdown. Also, j
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.
"j A
Alternative d
Testing:
Valve closure will be verified by completion of local j
leak rate testing performed in accordance with 10 CFR 50 Appendix J.
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- - -. - -, - - - - - - - - + -
Page 142 Relief Request Number PV-9 Page 1 of 1 System:
Standby Liquid Control Drawing:
47W854-1 Valves:
63-525 and 63-526 Category:
A,C Class:
1 Function:
Containment Isolation Impractical Test 3
Requirement:
Exercise valve once every three months.
Basis for Relief:
To verify proper opening of these check valves, it is necessary to pass fluid through each valve.
This action would result in an injection into the vessel and would require actuation of an explosive valve, both undesirable during power operations.
Closure testing is only practical by pressurizing downstream of the valve (the upstream side being vented) and verifying absence of flow in the upstream side. This requires installation of temporary equipment and access to the containment which is inerted during power operation.
Alternative Testing:
The proper functioning of the standby liquid control system injection flow path, including opening of 63-525 l
and 63-526, will be demonstrated once each operating cycle in accordance with Technical Specifications.
Proper valve closure will be verified by completion of I
local leak testing performed in accordance with 10 CFR 50 Appendix J.
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03028 I
Page 143 Rollet Request Number PV-10 Page 1 of 1 System:
Reactor Recirculation (68)
Drawing:
47W817-1 Valves:
68-508, 523, 550, 555 Category:
A,C Class:
1 Function:
Containment Isolation Impractical Test Requirement:
Exercise closed every three months.
~
Basis for Relief:
These check valves serve as inboard and outboard containment isolation valves. The valves are not equipped with remote indication, and there is no pressure indication downstream of the valves.
For these valves, closure testing is only practical through pressurization downstream of the valve, with the upstream piping vented and verification of the absence of flow upstream.
Interruption of the CRD flow (soal injection) is required to perform this testing, and during reactor recirculation u
pump operation, could result in seal damage. This type of testing can only be performed during a period when the containment is accessible.
The deinerting of the containment will only be performed during major outages.
Based on the impact of having to install temporary test l
equipment, the required testing will be performed during category A leak rate testing.
l Alternative 5
l Testing:
Proper valve closure will be verified by completion of i
local leak rate testing performed in accordance with 1
10 CFR 50 Appendix J.
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Page 144 Relief Request Number PV-ll Page 1 of 1 System:
Reactor Water Cleanup (RWC) (69)
Drawing:
47W810-1 Valves:
69-579 69-624 (U3)
Category:
A,C Class:
1 Function:
Containment Isolation; Prevents Backflow into RWCU System Impractical Test
~
Requirement:
Exercise valve closed every three months.
l Basis for Relief:
This check valve remains open to return water to the reactor vessel whenever the reactor water cleanup system is operating.
This valve is not testable whenever the RWCU, feedwater/ condensate, or RCIC system is returning flow to the reactor vessel. Testing requires entry into primary containment and the disruption of system flow (RWCU, foedwater/ condensate or RCIC). For these reasons, closure testing is only practical during extended outages such as refuelings 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 i
testing conducted in accordance with 10 CFR 50 Appendix J.
This testing involves significant effort for installation l
of temporary equipment.
This would require valve lineups I
to abnormal positions, installation of pressurizing l
equipment and associated test lines, as well as deinerting the drywell for safe entry.
(
Alternative Ly Testing:
Proper valve closure will be verified by completion of local leak rate testing performed in accordance with a
10 CFR 50 Appendix J.
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Page 145 Relief Request Number PV-12 Page 1 of 1 System:
Reactor Heat Removal Service Water (RHRSW)
Drawing:
47W858-1 Valves:
23-34, 40, 46, 52 Category:
B Class:
3 Function:
RHRSW Throttle Valve Impractical Test Requirement:
Stroke time valve every three months.
Basis for Relief:
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 obtain the desired flow of 4500 gpm would change due to system variables such as corrosion, tube blockage, plugged 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 < 4500 gpm quarterly.
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0302B
j Page 146 Relief Request Number PV-13 Page 1 of 1 System:
R}{R Service Water (23)
Drawing:
47W858-1 Valves:
23-601,23-603, 23-605,23-607 Category:
C Class:
3 Function:
Prevent Backflow through "Keep Fill" line Impractical Test Requirement:
Exercise valves closed once every three months.
4 Basis for Relief:
These check valves, located in keep fill lines for the RHR service water system permit raw service water flow into the respective headers while preventing process flow in the reverse direction during RiiRSW system operation.
There are two check valves in each line located in parallel. There 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, I
by disassembly, acoustic monie.oring techniques, or other I
proven methods.
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Page 147 Relief Request Number PV-14 Page 1 of 1 System:
Emergency Cooling Water (67) and Raw Cooling Water (24)
Drawing:
47W859-1 47W859-2 41W866-7 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, 1
679, 638 A
3-24-831, 833, 796, 798 3-67-639, 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 prevent backflow from opposite header.
~
C RCW:
Prevent backflow of EECW into RCW.
Impractical Test N
Requirement:
Exercise valves closed every three months.
j Basis for Tr Relief:
System design prevents the valves from being verified 1
closed by reverse flow or other conventional means.
Therefore, an alternate test such as acoustic monitor verification or disassembly will be required.
Since the valves can be verified open quarterly by flow 7
verification, apparent disc free movement will be l
indicated.
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Alternative 3
Testing:
Valves will be proven to close once per refueling cycle by other positive means such as disassembly, acoustic monitoring techniques, or other proven methods.
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Page 148 Relief Request Number PV-15 Page 1 of 1 System:
Reactor Building Closed Cooling Water (RBCCW) (70)
Drawing:
47W822-1 Valves:
70-506 Category:
A,C Class:
2 Function:
Containment Isolation Impractical Test Requirement:
Exercise closed once every three months.
~
Basis for Relief:
This valve is in the cooling water supply for the reactor recirculation pump bearing and 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 this 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.
Alternctive Testing:
Proper valve closure will be verified by completion of l
local leak rate testing performed in accordance with 10 CFR 50 Appendix J.
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0302B
Page 149 Relief Request Number PV-16 Page 1 of 1 System:
High Pressure Coolant Injection (HPCI) (73)
Reactor Core Isolation Cooling (HPCI) (71)
Drawing:
47W812-1 (HPCI) 47W813-1 (RCIC)
Valves:
HPCI 73-559 RCIC 71-547 Category:
A,C Class:
2 Function:
Containment Isolation Impractical Test Requirement:
Exercise closed once every three months.
Basis for Relief:
This valve is not equipped with position indication. Its configuration with an open discharge into the suppression pool prevents usage of reverse flow to demonstrate closure. No practical method exists to perform closure testing other than the downstream pressurization by leak rate testing.
Such testing conducted per Appendix J requires installation of temporary equipment and closure of valves which renders the system inoperable.
Alternative Testing:
Proper valve closure will be verified by completion of local leak rate testing performed in accordance with 10 CFR 50 Appendix J.
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0302B
r-Page 150 Relief Request Number PV-17 Page 1 of 1 System:
Main Steam (1)
Drawing:
47W801-1 Valves:
1-4, 1-5, 1-18, 2-19, 1-22, 1-23, 1-30, 1-31, 1-34, 1-41, 1-42, 1-179, 1-180 Class:
1 Function:
RPV pressure relief Impractical Test Requirement:
Additional tests of IWV-3513.
Basis for Relief:
The current Technical Specification 4.6.D.1 requires one-half of all relief valves to be bench checked or replaced with a bench checked valve. All 13 valves will have b6en checked or replaced upon completion of every second cycle. Although this does not require additional sampling based on results, the valves are tested at a l
minimum of every other refueling, which is more stringent than the potential of every five years per code.
Also, in short outages, it may not be practical to' remove the valves, ship them offsite for testing, and have the tests completed in time to determine additional testing without delaying unit startup.
l Alternative l
Testing:
Valves will be tested or replaced in accordance with l
Technical Specification 4.6.D.1.
As-found and as-left l
set pressures will be determined. Valves will be tested prior to the respective unit's startup or within 120 days of removal from the system, whichevar is longer.
[
Failures will be evaluated for additional testing 0
requirements.
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Page 151 Roller Request Number PV-18 Page 1 of 1 System:
High Freecure Coolant Injection (HPCI) (73)
RIactor Core Isolation Cooling (RCIC) (71)
Drawing:
47W812-1 (HPCI) 47WS13-1 ;dCIC)
Valves:
HPCI 73-605. 609 RCIC 71-580, 592 Category:
A,C Class:
2 Function:
Cc:
Inment Isolation s
Impractical Test Requirement:
Exercise valve closed once every three months.
Basis for Relief:
These theek valves are not equipped with position indication, and system design does not provide any practical method of verifying closure other than pressurization similar to leak rate testing.
Such testing 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 peerant a personnel safety hazard during operation.
Normally, testing of this type is accomplished by required containment local leak rate testing in accordance with Appendix J.
Alternative
.a Testing:
Proper valve closure will be verified by completion of
[
local leak rate testing performed in act rdance with
]
10 CFR 50 Appendix J.
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0302B
Page 152 Relief Request Number PV-19 Page 1 of 1 System:
High Pressure Coolant Injection (HPCI) (73)
Reactor Core Isolation Cooling (RCIC) (71)
Drawing:
47W812-1 (HPCI) 47W813-1 (RCIC)
Valves:
HPCI 73-633, 634, 635, 636 RCIC 71-597, 598, 599, 600 Category:
C Class:
2 Function:
HPCI Turbine Exhaust Vacuum Relief RCIC Turbine Exhaust Vacuum Relief l
Impractical Test Requirement:
Cycle valve every three months.
Basis for Relief:-
Valve configuration prevents;the valves from being l
individually proven open o.r closed. No test connectiot.8 l
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 hszard during operation.
Alternative Testing:
Each of the four valves shall be cycled each refueling outage by disassembly, acoustic monitor techniques, or other positive means.
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Page 153 Relief Request Number PV-20 Page 1 of 1 System:
High Pressure Coolant Injection (HPCI) (73)
Reactor Core Isolation Cooling (RCIC) (71)
Drawing:
47W812-1 (HPCI) 47W813-1 (RCIC)
Valves:
HPCI 73-517 RCIC 71-508 Category:
C Class:
2 Function:
Backflow Prevention to Suppression Pool Impractical Test Requirement:
Exercise valve once every three months.
Basis for Relief:
To verify proper opening of this check valve, it is necessary to initiate system flow while taking suction l
from the suppression pool.
Since the water quality in the suppression pool is not maintained at reactor coolant l
standards, it is not advisable to initiate this flow at any time during normal operations. The resulting I
contamination of the HPCI 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.
Alterr.ative Testing:
Verify operability by disassembly, acoustic monitoring techniques, or by other positive means. The valve will
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be tested once each refueling outage.
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03028
Page 154 Relief Request Number PV-21 Page 1 of 1 System Drawing Valve Cl a_s_s Main Steam (1) 47W801-1 FCV 1-55 1
RHR (74) 47W811-1 FCV 74-61,75 2
HPCI (73) 47W812-1 FCV 73-2 2
FCV 73-26 2
RCIC (71) 47W813-1 FCV 71-2 1
FCV 71-17 2
Floor & Dirty 47W852-1 FCV 77-2A 2
Radwaste Drainage (77)
I Clean Radwaste 47W852-2 FCV 77-15A 2
& Decontamination Drainage (77)
Category A
Function:
Containment Isolation Impractical Test Requirement 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 would require actions such as pressurizing the containment (equivalent to l
an ILRT) or precisely controlling the entire RCS at the valve test pressure.
,j Alternative l
Testing Leak rate test each valve in the reverse direction.
1 Penetration will be subjected to test pressures in the correct direction during containment integrated 4
leak rate tests.
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0302B t
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Page 155 Relief Request Number pV-22 Page 1 of 1 System:
Fuel Pool Cooling and Cleanup Drawing:
47W855-1 Valves:
78-526 and 78-527 Category:
C Class:
^
Function:
Prevent Backflow from Fuel Storage Pool In. practical Test Requirement:
2xercise valves once every three months.
Basis for Relief:
These valves are located directly over the fuel pool.
Valve conf!;uraticn (open ended to fuel pool) prevents reverse flow testing to prove closure.
Alternative Testing:
Verify valve closure by disassembly, acoustic monitor techniques, or other positive means each refueling outage.
Valve will be verified open quarterly.
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Page 156
-Relief Request Number PV-23 Page 1 of 2 System:
Control Rod Drive Hydraulic (85)
Drawing:
47W820-2 47820-5 (U2) 47820-6 (Ul&3)
Cateaory 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 Function:
Control Rod Scram Water Flow Path Impractical Test j
Requirement:
Exercise once every three months and measure stroke times.
i l
Basis for Ralief:
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.
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Cycling thesa valves requires scramming a control rod.
~
There see 185 control rods in the reactor. Scramming every rod once every three months is not practical for
~j the following reasons:
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a.
A power reduction is required to test the scram function. Reducing power for the length of time required to scram 185 rods is not practical.
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Fuel preconditioning must follow this power reduction l
to avoid possible fuel damage. The longer the reduction in power, the longer the preconditioning.
Their proper functioning is most practically verified by
.I an actual scram test (except for closure of 85-589 a,
and 85-597).
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0302B
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Page 157 Relief Request Number pV-23 Page 2 of 2 Alternative Testing:
Scram testing and rod insertion timing will be performed in accordance with Technical Specifications Section 4.3.c (at reactor coolant pressure 800 psig) for:
a.
All control rods prior to THERMAL POWER exceeding 40 percent after each refueling outage, b.
10 percent on a rotating basis at least once every 16 weeks.
c.
Valves85-589 (1-185) and 85-597 (1-185) will be proven closed by disassembly, acoustic monitoring techniques, or by other positive means during CSD, assuming adequate time.
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0302B
Page 158 Relief Request Number PV-24 Page 1 of 1 System:
Control Air (32)
Drawing:
47W1847-9, 10 47W2847-5, 8, 9 47W3847-5, 9 Valves:
32-336 32-2521 32-2163 32-2516 l
Class:
2 Function:
Containment Isolation Impractical Test Requirement:
Exercise valves every three months.
Basis for Relief:
The inboard valves are inside containment and therefore could not be proven closed without entry into the drywell. The drywell is inerted, and entry would be a hazard to personnel safety, l
l Alternative Testing:
Proper valve closure will be verified by completion of local leak rate testing performed in accordance with 10 j
CFR 50 Appendix J.
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j 0302B
Page 159 Relief Request Number PV-25 Page 1 of 1 System:
Sampling and Water Quality (43), HPCI (73), Containment Inerting (76), Containment AtacJphere Diluting (84),
Control Rod Drive (85), Diesel Generator Air Start (86),
Service Water (23), Residual Heat Removal Service Water (23) and Traversing Incore Probe Drawing:
47W610-43-1, 47W812-1, 47W610-76-3, 47W862-1 47W820-2, 3,4-47E861-1, 47W858-1, GE 729E761-1 Impractical Test Requirement:
Stroke time corrective action, IWV-3417(a).
Basis for Relief:
Valves with stroke times 5 2 seconds cannot be accurately timed.
Alternate Testing:
Valves with stroke times 5 2 seconds will be cycled and timed to verify the valve strokes in 5 2 seconds.
Increased frequency requirements of IWV-3417(a) will not be applied.
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0302B
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Page 160 Relief Request Number PV-26 Page 1 of 1 System:
Containment Inerting System Drawing:
729E761 Valve:
X-3Sf Category:
A,C Class:
2 Function:
Purge check valve for Traverse Incore Probe guide tubes.
Impractical Test Requirement:
E;tercise valve closed once every three months.
Basis for Relief:
This purge check valve serves as an outboard containment isolatian valve. Testing of this valve requit es entry into prisery containment and disconnection of the purge lino for 10stallation of test equipment.
Because of the plant desigra, demonstrating closure can only practically be accompl'.shed by pressurizing downstream, as is performed during lesk rate testing in accordance with 10 CFR 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 wht:h 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 la accordance with
'O CFR 50 Appendix J.
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Page 161 Relief Request Number PV-27 Page 1 of 1 System:
RHR (74)
Core Spray (75)
Drawing:
47W811-1 47W814-1 Valves:
74-54, 74-68 75-26, 75-54 Class:
1 Function:
Testable Check i
Impractical Test Requirement:
Cyclo quarterly, if not quarterly, perform cold shutdown.
Basis for Relief:
Due to potentially inadvertent valve operation caused by nonclass lE 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 passing design flow or by reconnection of the actuator air in cases during CSD when crywell entry is made.
This testing will be performed aions with the other CSD valves (i.e., time permitting) with a minimum of each refueling.
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Page 162 Relief Request Number PV-28 Page 1 of 1 System:
CRD (85)
Drawing:
47W820-2 Valve:
85-576 Class:
1 Function:
Isolation Check to Feedwater Impractical Test Requirement:
Cycle valve closed quarterly.
Basis 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.
-j Alternato Testing:
Proper valve closure will be verified by completion of local leak rate testing, perfocmed in accordance with 10 CFR 50 Appendix J.
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Page 163 Relief Request Number PV-29 Page 1 of 1 System:
Main Steam (1)
Drawing:
47W801-1 Valves:
1-14, 1-26. 1-37, 1-51 Class:
1 Function:
Containment Isolation Impractical Test Requirement:
Leak test at full maximum function pressure differential.
Basis for Relief:
Due to testing techniques, valve manifold design does not allow testing at full function pressure differential.
Such a test would subject the valve manifold to potentially damaging loads.
Alternative Testing:
Valves will be reduced pressure tested at a differential pressure of 26 psig.
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03028
Page 164 Relief Request Number PV-30 Page 1 of 1 System:
RHR (74)
CAD (84)
Drawing:
47W811-1 47W862-1 Valves:
74-661,74-662 84-600, 601, 602, 603 84-617 Class:
RHR:
1 CAD:
2 Function:
RI'S: Thermal Relief / Containment Isolation CAD:
Containment Atmosphere Control MSRV Air Supply Impractical Test Requirement:
Cycle valve quarterly.
Basis for Relief:
RHR:
These valves provide thermal relief betwoen the inboard and outboard shutdown cooling suction valves.
Since these valves are in series with no isolation valve, or test connection between them, they individually cannot be proven to close.
Since these valves are located inside containment, access to perform testing during operation is impractical due to the drywell being i
inerted.
Cycling by system manipulation is not possible l
during reactor operation due to pressure interlocks which prevent the suction valves from operating.
CAD:
These valves provide an injection path when open and containment isolation when closed. Cycling the valve 3
closed would require setup of temporary test equipment and abnormal valve lineups.
j
't Alternative
' A; Testing:
Proper valve opening will be proven by alternative test methods such as passing flow during CSD, assuming DW 4
entry and adequate time.
Proper valve closure will be verified by completion of local leak rate testi.ig 4
performed in accordance with 10 CFR 50 Appendix J.
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a 0302B
O Page 165 i
Relief Request Number PV-31 Page 1 of 1 System:
Reactor Core Isolation Cooling (71)
High Pressure Coolant Injection (73)
Drawing:
47W813-1 47W812-1 Valves:
71-589 73-625 Function:
Prevent backflow from CST and PSC Impractical Test Requirement:
Exercise 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, an alternate test such as acoustic monitor verification or disassembly will be required.
Since the valves can be verified open quarterly by flow verification, apparent dise free movement will be indicated, i
Alternative Testing:
Valves will be proven to close once per refueling cycle by other positive means such as disassembly, acoustic.
monitoring techniques, or other proven methods.
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03028
t IV.
COLD SHUTDOWN JUSTIFICATIONS t
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Page 167 Cold Shutdown Justification Number 1 System: Reactor Recirculation Drawing:
47W817-1 Valves:
FCV 68-3, 79 Category: B Class:
1 Function: Pump A&B discharge isolation Justification: The recirculation pump discharge isolation 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 level.
Cycling of these valves would also isolate that loop of the recirculation system.
Failure of the valve to reopen could result in a plant shutdown as required by technical specifications with one loop recirculation operation for greater than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
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02968
Page 168 Cold Shutdown Justification Number 2 System:
Reactor Building Closed Cooling Water Drawing:
47W822-1 Valves:
FCV 70-47 Category: A Class:
2 Function: Containment discharge isolation Justification: This valve is in the cooling water supply and return lines for the reactor recirculation pump bearing and seal coolers.
Cycling of this valve during power operation would interrupt this cooling water flow, possibly causing pump bearing damage or seal failure.
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0296B
l Page 169 Cold Shutdown Justification Number 3 System: Reactor Core Isolation Cooling Drawing:
47W813-1 Valves: FCV 71-40 Category: AC Class:
1 Function: Containment testable check Justification: This 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 accomplished but would require RCIC 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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02968
r Page 170 Cold Shutdown Justification Number 4 System: High Pressure Coolant Injection Drawing:
47W812-1 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 accomplished but would require HPCI injection, set up of pressurizing equipment, or jumper instellation, 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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Page 171
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Cold Shutdown Justifle.tica Number S System:
Residual Heat Removal Drawing:
47W811-1 Valves:
74-47, 48 Category: A i
Class:
1 Function: Shutdown cooling isolation Justification:
These normally closed isolation valves are only required to open when bringing the unit to a cold shutdown cooling mode of RHR.
Cycling these valves at pressures greater than 1
100 psig is prevented by logic interlocks.
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4 Page 172 Cold Shutdown Justification Number 6 System:
Residual Heat Removal Drawing:
47W811-1 Valves:
74-53, 67 Category: A Class:
1 Function:
Containment isolation Justification: These normally closed isolation valves serve as the pressura isolation between RHR system piping and reactor coolant pressure.
Cycling these valves every three months during power operation increases the probability of exposing the downstream low pressure piping to reactor coolant pressure.
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Page 173 Cold Shutdown Justification Number 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 IWV-3412(a), valves shall be exercised unless such operation is not practical during plant operation.
Valves will be partially stroked quarterly.
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Page 174 Cold Shutdown Justification Number 8 System:
Reactor Core Isolation Cooling High Pressure Coolant Injection Drawing:
47W813-1 47W812-1 Valves:
71-2, 3 73-2, 3 Category:
A, B Class:
1 Function: Steam Supply Isolation to Pump Turbine Justification: Failure of any of these valves to return to the open position would cause the system to be inoperable and place the unit in a technical specification limiting condition for operation.
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Page 175 Cold Shutdown Justification Number 9 System: CAD (84)
Drawing:
47W862-1 Valves:
84-600, 601, 602, and 603 Category: A i
Class: 2 Function: DW/PSC Supply Check Valves (CIV)
Justification:
Proving the valves open quarterly requires injection of citrogen into the drywell which is not practical due to the effects on drywell pressure.
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Page 176 Cold Shutdown Justification Number 10 System: HPCI RCIC Drawing:
47W812-1 47W813-1 valves:
HPCI HCV 73-23, 24 RCIC HCY 71-14, 32 Category:
A,C Class:
2 1
Function: Containment Isolation
~
Justification: These are manual valves. Cycling the valves would render the system inoperable since no system logic controls the position of a manual valve for system initiation.
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e Page 177 Cold Shutdown Justification Number 11 System: CRD Drawing:
47W820-2 Valves:
(1)85-589 (2)85-597 Category: C Class:
(1) 2 (2) 1 Function:
(1) Charging water check 4
(2) Cooling water check Justification: Verifying these valves closed would require isolating the charging water and cooling water to the drives.
This is not practical during operation.
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ENCLOSURE 2 t
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ASME Section XI Pump & Valve Program -
Summary of Changes to December 23, 1986 Submittal P, age, Chanae Reason 1
I.A - Change wording of the To clarify testing interval.
fourth sentence such that the inservice testing program interval is referred to as "effective interval dates" instead of the term "second 10-year" interval.
1 I.B.1 - Change 1.03 and Resolution of NRC question No. 19.
1.04 to 1.02 and 1.03, respectively.
4 I.C.4 - Delete.
Resolution of NRC question No. 1 (Replaced with RFR PV-4).
Change I.C.5 to I.C.4.
I.C.4 deleted.
Split I.C.6 into I.C.5 and Resolution of NRC question No. 2.
reword portion addressing remote position verification.
5 I.C.9 - Add reference to Resolution to NRC question No. 4.
PV-5.
9 Change 47W830 to Typographical error.
47W852.
11 Add note 2 and reference Addition to program to PV-3 on DFTP.
for clarification.
12 Add reference to PV-17 Change to program (Request for for valves 1-4,
-5,
-18, relief from code for testing and -19.
MSRVs. Tech Spec requirements Will be utilized.).
4 i
13 Add reference to PV-17 Change to program (Request for for valves 1-22
-23, ~30, relief from code foi testing and -31.
MSRVs. Tech Spec requirements 1
will be utilized.).
t 14 Add reference to PV-17 Change to program (Request for for valves 1-34
-41, relief from code for testing and -42.
MSRVs. Toch Spec requirements will be utilized.).
15 Add reference to PV-17 Change to program (Request for
~
for valves 1-179 and -180, relief from code for testing MSRVs.
Tech Spec requirements will be utiliz'ed.).
I sd
r ASME Section XI Pump & Valve Program -
Summary of Changes to December 23, 1986 Submittal (Continued)
Eage Jhange Reason la Change testing to CSD per Resolution of NRC question No. 10.
PV-7 versus RR for all valves listed.
19 Change testing to CSD per Resolution of NRC question No. 10.
PV-7 versus RR for all Valvos listed.
20 Change testing to CSD per Resolution of KRC question No. 10.
PV-7 versus RR for all valves listed.
21 Change testing to CSD per Resolution of NRC question No. 10.
PV-7 versus RR for all valves listed.
33 Delete reference to PV-24 and Resolution of NRC question No. 14.
different testing performed for valves 3-62 and -63.
36 Delete reference to PV-24 and Resolution of NRC question No. 14.
different testing performed for valves 3-62 and -63.
38 Delete reference to PV-24 and Resolution of NRC quescien No. 14.
different testing performed for valves 3-62 and -63.
48 Add valves64-800 and -801.
Program addition (valve number assigned after December 23, 1986 submittal).
52 Delete reference to PV-26 Resolution of NRC question No. 16.
and different testing performed for valves 67-50,
-51, and 1-67-53.
4 72 Change valve 71-6A category Incorrectly identified as CIV in f
from A to B and delete December 23, 1986 submittal.
LT requirement.
Delete valve 71-6B.
Incorrectly identified as CIV in December 23, 1986 submittal.
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r ASME Section XI Pump & Valve Frognt -
Summary of Changes to December 23, 1986 Submittai (Continued)
~~Eage, Channe~~
,Rn soq 73 Delete LT requireinent Incorrectly identified as CIV in for valve 71-7A.
December 23 1986 submittal.
3 Delete valva 71-7B.
Incorrectly identified as CIV in December 23, 1986 submittui.
Change PV-17 to CSD-10 Resolution of NRC question No. 5.
and RR to CSD on valve 71-14.
74 Change PV-17 to CSD-10 Resolution of NRC question No. 5.
and RR to CSD for valve 71-32.
Delete reference to CSDJ-9 Valve can be cycled quarterly.
for valve 71-37.
75 Change code classification Classification incorrectly for valve 71-39 from ASME identified in December 23, 1986 Class 1 to ASME Class 2.
submittal.
78 Change valve 73-6A category Incorrectly identified as CIV in from A to B and delete December 23, 1986 submittal.
LT requirement.
Delete valve 73-6B.
Incorrectly identified as CIV in December 23, 1986 submittal.
79 Change safety reisted Additional information per system position on valve 73-8 from engineer's review.
O to O/C.
~~
Delete valves73-17A and 17-B. Incorrectly identified as CIV in December 23, 1986 submittal.
1 80 Change PV-17 to CSD-10 and Resolution of NRC question No. $.
RR to CSD for valvec 73-23 and 24.
81 Delete reference to CSDJ-9 Valve can be cycled quarterly.
for valve 73-34 Change code classification Classification incoerectly for valve 73-44 from ASME identified in December 23, 1986 Class I to ASME Class 2.
submittal.
{
Delete reference to CSDJ-8 Valvo can be cycled quarterly, for valve 73-81.
9
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ASME Section XI Pump & Valve Program -
Summary of Changes to December 23, 1986 Submittal (Continued)
Eggs Chanze Reason 82 Delete valve 73-600.
Determined to passive valve (added to passive list).
86 Change Outhd to Inbd on Typographical error, valve 74-48.
Change RR to CSD per PV-27 Resolution of NRC question No. 17.
for valve 74-54.
88 Change RR to CSD per PV-27 Resolution of NRC question No. 17.
for valve 74-68.
97 Change RR to CSD per PV-27 Resolution of NRC question No. 17.
for valve 75-26.
98 Change RR to CSD per PV-27 Resolution of KRC question No. 17.
for valve 75-54.
110 Delete reference to PV-21 Valves now testable in correct for valves 84-8A, -8B, -8C, direction as a result of and -8D.
modification.
111 Add valve 84-617.
Resolution of NRC question No. 20.
Change reference PV-30 to Resolution to NRC question No. 18.
CSD and change RR to CSD on valves84-600, ~601, -602, l
and -603.
I 112 Add reference to CSD-11 Resolution of NRC question No. 13.
l on valves85-589 and -597.
119 Add reference to PV-26 and Valve wac overlooked in original add RR and LT (in the submittal with respect to the need Testing Performed column) for relief from quarterly testing for T.I.P. valve X-35f.
requirement.
l l
122 Add reference to 47W859-1 Inadvertently left out of first and valves67-504 and 67-505.
submittal, f
123 Add 73-600 to passive list.
Determined to be passive (deleted I
from active valve list).
129 Additional infornation Resolution of NRC question No. 6.
k6:ed for clarity.
2 I
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ASME Swetion II Pump & Valve Program -
Susunary of Changes to. December 23, 1986 Submittal (Continued)
EA&R Channe Reason 131 Change reference from Additional information to reflect 15-minute to 5-minute changes in Survelliance Instruction test and note 2-minute per vendor and system engineer.
minimum test versus 2-minute.
Add reference to diesel Addition to program, fuel transfer pumps.
132 Original RFR deleted and Resolution of NRC questions No. 1 replaced with RFR fer policy and No. 7.
3 previously stated in t]
paragraph I.C.4.
133 Change reference from Typographical error.
i Table IWP-4100-1 to
~
IWP-4110-1 in the Impractical Test Requirement paragraph.
In alternative test.ing.
Resolution of NRC question No. 19.
change 1.03 and 1.04 to 1.02 and 1.03, respectively.
Add information on vibration Resolution of KRC questions 8a testing and revise diesel and 8b.
fuel transfer acceptance criteria.
In NOTE, change amplitude Typographical error.
j to velocity.
In table, change the Change to program.
j multiplication factor
+
l from 2.5 to 3.0.
134 In alternative testing.
Typographical error.
change word one to once.
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1 In alternative testing.
Resolution of NRC question No. 9.
+
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change the last sentence to l
require valves to be verified to stroke in s 2s.
In alternative testing.
original technical specification T
~~
change the technical reference was incorrect.
rpecification reference 4
from 4.5.G to 4.6.D.2.
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ASME Section XI Pump & Valve Program -
Summary of Changes to. December 23, 1986 Submittal (Continued)
Paget Channe Reason 135 In alternative testing, Resolution of NRC question No. 10.
change frequency from refueling to CSD assuming DW entry.
140 In alternative testing, Addition to program for add the word reference clarification.
for the position.
141 In alternative testing, Addition to program for add methods to be clarification.
utilized.
145 Original RFR deleted and Resolution of NRC questions No. S replaced with RFR and No. 21.
addressing MSRV testing.
149 Delete valves74-102 Valves are now noncode class per and -103.
modification.
Delete valve 75-57.
Valve is globe type (reverso flow testing acceptable per code).
Delete valves 84-8A, -8B, Valves now testable in correct
-8C, and -8D.
direction as a result of modification.
150 In alternative testing, Resolution of NRC question No. 12.
l closure will be required refueling and opening quarterly.
l 152 In alternative testing C, Resolution of NRC question No. 13.
l change refueling to CSD.
~4 153 Delete valves 32-62 Resolution of NRC question No. 14.
and -63.
154 Add reference to corrective Addition to program for
-[
action, IWV-3417(a) in clarification.
Impractical Test Requirement.
In alternative testing, add Resolution of NRC question No. 15.
the requirement to verify valve strokes in s 2s.
- j Also, add that increased frequency requirements of IWV-3417(a) do not apply.
' T' s a. *~~ - v -.
m
r-ASME Section XI Pu7p & Valve Program -
Summary of Changes to Lecember 23, 1986 Submittal (Continued)
Eage Change Reason 155 Original RFR deleted and Original RFR deleted in response to replaced with RFR addressing resolution of NRC question No. 16.
testing of T.I.P.
Revised RFR to seek relief in valve X-3Sf.
testing requirements of T.I.P.
val ** ?: due to plant design contiguration.
156 In alternative testing, Resolution of NRC question No. 17, require testing duriag CSD, assuming DW entry versus only refueling.
159 Delete reference to proving Resolution of NRC quo 3 tion No. 18.
valves84-600, -601, -602, and
(
-603 open RR (replac.d by CSDJ-10).
In alternative testing, add Resolution of NRC question No. 18.
l that valves will be proven open CSD, assuming DW entry and delete last sentence.
Add valve 84-617.
Resol'ation of Nhd question No. 20.
169 Delete valve 73-81.
Valve can be tested quarterly.
170 Replaced with CSDJ for Original valves in CSDJ-9 can be 1
84-600, -601, -602, cycled quarterly.
New valves as a l
and -603.
result of resolution to NRC question No. 18.
Add CSDJ-10.
Resolution of NRC question No. S.
2 l
Add CSDJ-11.
Resolution of NRC question No. 13.
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ENCLOSURE 3 QUESTIONS AND TOPICS OF DISCUSSION FROM AUGUST 25, 1987 MEETING l
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QUESTIONS AND TOPICS FOR DISCUSSION REGARDING THE BROWNS FERRY PROGRAM FOR INSERVICE TESTING PUMPS AND VALVES (DECEMBER 03, 1986 SUBMITTAL)
AUGUST 25, 1987 TVA/NRC MEETING 1.
Discuss / clarify *.he position stated in Browns Ferry IST Program paragraph I.C.4.
2.
Discuss / clarify the p1sition stated in paragraph I.C.6, second sentence.
3.
Discuas/ clarify the position stated in paragraph I.C.8.
Limiting values of stroke time should be set to assure that imminent valve failure may be detected and corrected.
4.
Instrumentation that does not conform to Code requirements may not be used for IST unless the NRC grants relief (refer to I.C.9).
5.
Discuss the access difficulties involved in closure exercising the stop check valves referred to in relief request PV-17.
l 6.
Relief request PV-1, in part, requests relief.' rom lubricant level / pressure measurement requirements, but no basis for granting relief is stated.
If a basis is not provided relief with regard to lubricant level / pressure will be denied.
j 7.
Relief request PV-4 cannot be granted.
N l
8.
For PV-5 to be acceptable -
1 l
a.
Vibration testing commitments should conform to the proposed standard OM-10 requirements or alternative requirements should be st.ated and justified.
l l
l b.
Proposed DFT pump flow limits appear too loose.
9.
The valves in PV-6 should rae stroke timed to verify a stroke time of a
< 2 seconds.
1
..a,
r QUESTIONS AND TOPICS FOR DISCUSSION REGARDING THE BROWNS FERRY PROGRAM FOR INSERVICE TESTING PUMPS AND VALVES (DECEMBER 23, 1986 SUBMITTAL)
AUGUST 25, 1987 TVA/NRC MEETING (Continued) 10.
The valves in PV-7 must be exorcised at cold shutdown if the drywell is deinerted, 11.
The PV-21 request is granted only if the testing is acceptable per 10 CFR 50, Appendix J.
An examption is required to meet the Appendix J requirement.
12.
Discuss the reasons the valves in PV-22 cannot be stroked open.
I 13.
Discuss the functioning of the check valves referred to in PV-23.
t 14 There is insufficient basis stated in PV-24 to provide the relief requested for valves 32-62 and -63.
mi 15.
The valves in PV-25 must be stroke-timed to verify a < 2 second limit.
Trending requirements of IWV-3417(a) need not be met.
J 16.
Discuss the basis for relief request PV-26.
17.
Discuss the basis for relief request PV-27.
How burdensome is reconnecting the air supply for the valves?
i 18.
Discuss the basis for granting relief from open exercising the velves in PV-30.
4 19.
The flow and differential pressure and multipliers in PV-5 and paragraph I.B.1 require correction.
20.
Should valve 84-617 (penetration X22) be included in the program?
21.
Discus: PV-32.
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ML20148G614

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ML20148G614

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