ML19253C959

Description of Inservice Test Program for Pumps & Valves & Requests for Relief from Specific ASME Code Requirements

ML19253C959
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	12/07/1979
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML19253C955	List: ML19253C953 ML19253C959
References
NUDOCS 7912120436
Download: ML19253C959 (41)

Text

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BIG ROCK POINT PLANT Description of Inservice Test Program for Pumps and Valves and Requests for Relief From Specific ASME Code Requirements 1536 168 7912120

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1 DEFINITIONS APPLICABLE TO PUMP AND VALVE TESTING PROGRN4 1536 169

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SHUTDOWU TESTING REQUIRFl4ENTS Inservice valve testing during a shutdown

• or a cold shutdown

• shall commence no later than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the shutdown or the celd shutueen has started.

This testing shall continue until all valve testing is performed or until the plant is ready to return to power operation. The inservice valve testing program shall not delay plant start-up if not completed during the shutdown i

period. Testing that has not been completed during any shutdown shall be performed during subsequent shutdowns. In case of frequent cold shutdowns *,

valve testing shall not be performed at lecs than quarterly intervals.

• Fer Big Rock Point Technical Specification Definition.

1536 170

3 II.

COMPONENT LEAKAGE The acceptance criteria for containment leakage is based on the total leakage from all components. The individual leakage rates are obtained from tests performed in accordance with 10CFR50, Appendix J.

These test results are logged, graphed and compared historically.

If leakage on a component is observed to be increasing, corrective action is taken to prevent exceeding the total leakage acceptance criteria.

1536 171

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PUMP TESTING PROGRR4 MID REQUEST FOR RELIEF 1536 172

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IWP Testing This Pumps provided with emergency power sources are required to be tested.

includes pumps povered by the emergency diesel generator, the two core spray pumps and the electric fire pump, and the self-powered diesel fire pump.

Tests to be performed on these pumps are as follows:

Core Spray Pumps - The pumps vill be tested once each reactor shut-1.

down for refueling. See request for relief.

Electric Fire Pu=p - The electric fire pump will be tested each reactor (But not more frequently than monthly.)

2.

shutdown.

Diesel Fire Pu=p - This pump vill be tested each reactor shutdown.

(But not more frequently than conthly. )

3 The Parameters to be measured during these tests are tabulated below.

Bearing Rotative Inlet Flow Pump Name Speed Pressure g

Rate Vibration Temperature Core Spray R

R R

NA*

R NM Electric ES ES ES NA*

ES NM Fire Diesel ES ES ES NA*

ES NM Fire ES - Every Shutdown (But not more frequently than monthly)

Y - Yearly

_R - Once/ Refueling NM - No measurement possible - just monitor vibration "Per IWP3100, differential pressure vill be used to establish pump acceptability.

The acceptable rances of parameters vill te as required in Table IWP-3100-2.

Note:

153'6 173

6 RELIEF REQUEST Item: Relief Bequest for Electric and Diesel Driven Fire Pumps Test Requirement: Monthly during plant operation and within one week after plant startup if not tested during the shutdown Basis for Relief: These fire pumps must be tested on a monthly basis as required by ASME Section XI IWP testing. To perform the test vould require fire water flow through the shell side of the core spray heat exchanger. This fire water is then discharged back to the lake.

This flow test, which is the only valid test, vill reduce the flow available to the ECCS to below that calculated as necessary. Thus, to prevent degradation of the Emergency Core Cooling System, relief is requested to allow testing each reactor shutdown.

The granting of this relief request vill insure' there vill be adequate flow available to the Emergency Core Cooling System.

This relief request vill also apply to the fire pump discharge check valves, VFP30h and VFP309 Alternate Testing: Once per reactor shutdown but not more frequently than monthly.

no 1536 174

.A 7

_ RELIEF REQUEST _

Item; Relief request for core spray pumps.

Test Requirement: Monthly during plant operation and within one week after plant startup if not tested during the shutdown.

Basis for Relief: These pu=ps are part of the Emergency Core Cooling System.

Testing during power operations vould require a valve line-up which would preclude their performing their required function after a loss of coolant accident (LOCA).

In the event of a LOCA, areas which must be entered to change this valve lineup would be untenable.

In addition, testing during power operation vould require personnel entry into the very high radiation area directly beneath the reactor vessel.

In addition, the overall time required to perform testing (preparation, performance and restoration to normal) is about 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The additional radiation exposure received for each test vould be about 100 mR.

(Assumes the reactor in cold shutdown and 1/2 hour of occupancy in a 200 mR/hr radiation area under the reactor vessel). This could possibly mean about 1200 mR additional exposure if the reactor was in

~

cold shutdown every =onth of the year, due to other problems.

This relief request also applies to all associated valves.

(VPI306, VPI307, VPI300).

Alternate Testing: Once per reactor shutdown for refueling.

1536 175

VALVE TESTING PROGRMI A!ID REQUESTS FOR RELIEF 1536 176 o

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9 LISTING OF NEW TEST REQUIREMENTS VALVE EXERCISING REQUIREMENTS VALVES TO BE EXERCIGED Each Reactor Each Cold Reactor Quarterly iRefueling Shutdown Shutdown Valves & Testing Requirements M07052,53, M07052, 53, 62, & 63 - Energency 62, & 63 condenser Valves CV4020 CV4020 - Poison System - Disc - M-107 CV4050 CVh050 - Poison System - Inlet - M-121 CV4105 CV4105 - Demin H O - M-110 2

CV4031, CVh102 CVh031, 4102 - Enc. Clean Su=p - M-108 CV4125 CV4103 CV4025,4103 - Enc. Dirty Sump - M-108 CV4049 CV40h9 - Treated Waste to Fuel Pool M-108 CV4091,92

&93 CV4091, 92, & 93 - Resin Sluice - M-107 CV4027,h117 CVh027, 4117 - Fuel Pool Iso Valves-M-107 M07050 M07050 - Main Steam - M-121 CVNC09,10 CVNC09,10 - CRD Scram Valves - M-122-

CVNC11, CVNC12 CVNC11,12 - Dump Tank Vent Valves -M-122

M07051, M07061 MOT 051, 61 - CS Valve - M-123

M07070, M07071 M07070, 71 - RCD CS Valve - M-123 M07064,68 M07064,68 - T180 Enc. Spray - M-123 CV409h-CV4097 CV4094-4097 - Vent valves - M-125 CVh180-CVh183 CV4180-4183 - RDS Iso. Valves - A-203 CV4184 CV4184 - RDS Bypass Iso. A-203 VP300 Liquid Poison Drum Suction - Exercise RV5050&51 CRD Pump - Check settings RV5049 Liquif. Poison Relief - Check setting.

RV5018&l9

' Shutdown Cooling, Relief - Check Setting VPI301&302 Liquid Poison Check Valves - Disassemble and Inspect 3g }))

RV50k3,5062,

& 5063 Fire Systen Relief Valves - Check setting

t 10 LISTING OF NEW TEST REQUIREEUTS VALVE EXERCISING REQUIREMENTS VALVE 3 TO BE EXERCISED Each Reactor Each Cold Reactor Quarterly Fefueline Shntdown Sbutdown Valves te Testine Femtf wa-ant e

VPI306, 307,300 Core Spray Check Valves - Exercise By Testing Pump VPI301,302 Core Spray Check Valves - Exercise By Flow Service Water Shut off and Fire Water Discharge to Canal VPI303&304 Core Spray Check Valves - Disassemble and Inspect VFP30h&3C9 Fire Pump Discharge Check - Exercise During Pump Test Other testing requirements written in margins of the proposed IWV Te.eing.

"But not more frequently than quarterly.

1536 178

a 11 -

. LEGEND FOR IWV TESTIIIG CHARTS Valve Tree Actuator Type Normal Position BF - Butterfly AO - Air Operator ALT - Alternating BL - Ball EXP - Explosive C

Closed CK - Check FL - Flow D - Disabled EXP - Explosive MO - Motor Operator 0 - Open GL - Globe PR - Pressure GT - Gate SO - Solenoid Operator RV - Relief Testing Requirements CLHR - Check leakage during NSSS Hydrostatic Testing performed each reactor shutdown for refueling DRR - Disassemble and inspect each reactor shutdown for refueling.

ECS - Exercise valve each reactor cold shutdown

• But not more frequently than Quarterly ES Exercise valve each reactor shutdown

• But not more frequently than Quarterly LRR - Leak rate test during each reactor shutdown for refueling 2xercise once per three months (Quarterly)

Q RR - Exercise / check setting during each reactor shutdown for refueling SRP - Each shutdown in which both recirculation pumps are secured or at most each reactor shutdown for refueling 1/RR - One per each reactor shutdown for refueling 2/RR - Tvo per cac.h reactor shutdown for refueling 2/20 - 207 of valves in two years

• Per Big Rock Point Technical Specification Definition Systems CRD - Control Rod Drive CS - Core Spray RDS - Reactor Depressurization System Other Definitions

]h 11 - ao Y - Yes

• In stroke time column, means to be determined by testing,nrogram - The stroke time limit is not established now.

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Nu nber Mumber g 1/RH CRD Pump Relief Valves IlV5050 M-106 R-19 X

3/4" RV PR C

5051 7RD310 M-106 0-21 X

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2" CK FL 0

Q/LRR Y LRR CRD Pump Supply Check Valve Q/LRH Y LRR CRD Pump Suction Poppet Valves Control M-106 R-19 X

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CK FL ALT flod Driv :

Funp Suc'. ion iPorput

' Valves t'

407052 M-107 E-H X

6" GT M0 O

Q Y

ES Emer6ency Condenser Isolation Valves l

C 7053 i

7062 ll-l!'

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i JV4020 M-107 C-19 X

3" GL A0 0

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ECS Liquid Poison System - Discharge Isolation Valve VP300 M-107 B-17 X

2" CK FL ALT Q

Y ECS Liquid Poison System Steam Drum Suction Check Valve 20/E N Liquid Poison Explosive Outlet Valve CVhll8 M-107 C-20 X

3" EXP EXP C 1119 4

LT1 4120

.CVhl21 M-107 B-19 X

2" EXP EXP C 20/E N Liquid Poison Explosive Inlet Valves u

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1" EXP EXP C Va ves CVh12h CD -

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3/h" RV PR C

'97056 M-107 11-1 5 X

8" GT MO C

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Shutdown Cooling System Isolation j

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Valves 7057 n

7053 11 - 1 5 7059 Shutdown Cooling System Pressure 1/R 1N

'iV5018 M-107 1618 X

3/h" RV PR C

Protection 5019

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CVh091 M-107 P. 6 X

11" BL A0 C

2RR/

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4092 G-6 X

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!!-7 X

CV4027 M-107 l'.- 15 X

2" GL A0 0

LRR/ Y LBR Reactor and Fuel Pit Drain Isolation 4117 c-15 X

Q Valves JV4031 M-108 X

2" GL A0 0

LRR/N

- Reactor Enclosure Clean Sump Isolation bl02 X

Q Valve JVh023 M-108 X

2" GL A0 0

LRR/N Reactor Enclosure Dirty Sump Isolatic n Q

Valve 4103 X

Vh0h9 M-108 X

3" GL A0 C

LRR/Y LRR Treated Waste Return Isolation Valve 0

'IRU313 X

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CK FL C

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Vh050 M-121 M-B X

3" GL A0 0

Q Y

SRP Liquid Poison Supply to the P;cciic Line Ch VP301 M-121

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3" CK FL C

Q Y

DRR Liquid Poison Supply to Recire Line VP302 M-121 L-12 X

3" CK FL C

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DRR Liquid Poison Supply to the Reactor I

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CVl4105 M-110 J-22 X

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Valve M-110 J-21, X

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Valve t/RR H

av5000 M-121 D9-1 L X

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Steam Drum Relier Valves 5001 5002 D15-5003 17 50 45 50h0

107050 M-121 A-17 X

L2" GT MO O

2RR/

Y ES Main Steam Isolation Valve Q

CLHR 107065 M-121 E-17 X

1" GT M0 DC LRRJY CLHR Main Steam Drain Isolation Valve Q

VW9 M-121 E'-15 X

X 10" CK FL 0

LRR/Y LRR Feedvater Check and Stop Check Valves

/FW30L Q

LD CVIIC09 M-122

!!-21 X

3 / 16 " GL A0 C

Q Y-ECS Scram Inlet and Outlet Valves I

U JVNCIO

!!-19 Q

N Scram Dump Tank Vent and Drain Valve s

VNCll M-122 P-8 X

1" GL A0 0

JVNCl2 11 - 8 2"

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Ed Fire System Relief Valves at Pump HV5013 1-123 E-15 X

3/h" RV PR C

1/RI: N 5062 1-15 h"

'RV PR C

1/Bl. N Discharge 5003 u -l's 1/h" RV PR C

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• .07051 M-123 0-9 X

4" GT M0 C

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Core Spray and Redundant Core Spray Isolation Valves 7061 (1-10 7070

! -9 7071 u-lO N0706h M-123

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h" GT M0 C

Q Y

RR Enclosure Spray Isolation Valve Backup Enclosure Spray Isolation Valve M07068

• -13 VPI306 M-123 y-lh X

h" CK FL C

Q Y

RR* Core Spray Pump Discharge Check Valvc VPI307

.c-16 X

h" CK FL C

Q Y

RR* Core Spray Pump Discharge Check Valyc VPI300 u-lh X

4" CK FL C

Q Y

RR* Core Spray Test Tank Inlet Check Val'.e

• The above three check valves are dependent upon testing of the core spray pump. Thus, see the relief request for the core spray pump.

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6" CK FL C

7PI30h 0-10 X

h" CK FL C

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DRR IPI301

!!-123 ll-8 X

h" CK FL C

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ECS Redundant Core Spray Check Valves 7PI303 11-10 X

h" CK FL C

Q Y

DRR

{VFP30h M-123 C-14 X

8" CK FL C

Q Y

ES See Relief Request for Diesel and VFP309 l'-15 X

8" CK FL C

Q Y

ES Electric Fire Pumps X

X 2h" CK A0 0

6 Q/LDR H Containment Ventilation Valves CV409h M-125 kCVh095 X

2h" BF A0 0

6 Q/LlR H JV40?6 X

X 2h" CK A0 0

6 Q/LHR N CV40/T X

24" BF A0 0

6 Q/LI:R N CVhl80 A-203 X

6" GT A0 C

5:

Q N

RDS Isolation Valves h161 5'

h182 5

h183 5

Spool Piece Warming lineIsolation Va] ve

Vhl64 A-203 X

2" GT A0 0

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N SVh984 A-203 X

6" RV SO C

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17 Relief Requer-Basis Control Rod Drive (Print M-106)

System:

VCRD310 and CRD Pump Suction Poppet Valves Valve:

Category: AC AS!E Cicss: 2 To prevent backflow from containment through the CRD Supply line Function:

Exercise quarterly and' local leak rate test each reactor Test Requirement:

. shutdown for refueling.

The closing function cannot be verified except during times Basis for Relief:

of local leak rate testing which is performed each reactor shutdown for refueling per 10CFR50, Appendix J.

Alternate Testing:

Local leak rate test each reactor shutdown for refueling I

1536 185

~

18 Relier Requent Basis System: Emergency Condenser (Print M-107) valve:

LD7052, M07053, M07062, to-7063 Category: B ASME Class: 1 Function: Emergency Condenser Inlet and Discharge Isolation Valves Test Requirement:

Exercise valves for op6rability every three months Basis for Relief:

The exercising of these valves at power would admit steam to the emergency condenser.

This action vould cause un-necessary thermal stresses in the tube bundles. The pro-posed alternate testing vill minimize thermal cycles.

Alternate Testing: Once each reactor shutdown or when one loop becomes inoperative.

t 1536 186

19 5

Relier Request' Basis System: Containment Isolation Valves (Prints M-107, M-108)

Valve:

Cvh031, CV4102, Cvh025, CVh103, CV4091, CV4092, CV4093, Cvh027, CVh117, CV4094-CV4097, CV4105 Category:

A ASME Class: 1 for CV4092, CV4093 CV4102 CV4025 CVh103, CVh027, CVh117, CV4091, 2 for CV4031,CV4097,,and CV4f05 CV4094-Function:

'1b Isolate Containment Test Requirement: Exercise quarterly and l'ocal leak rate test each reae. tor shutdown for refueling Basis for Relief: Technical Specifications require leak rate test every 12 r.onths.

A Technical Specifications change has been submitted to change this interval'to each reactor shutdown for refueling, but not to exceed every two years.

The following valves are in the position to perform their intended function.

CV4091 h092 4093 h027 4117 Thus, these valves need not be exercised on a quarterly basis.

~

~

Alternate Testin6:

Test in accordance with Technical Specifications and exercise valves CV4031, CV4102, CV4025, CVh103, CV4094-4097, CV4105 on a quarterly basis 1536 187 e

29 S

Relief Request Basic System:

Liquid Poison System (Print M-107)

Valve:

CV4020 Category: B ASME Class: 1 Function: Liquid Poison Tank Discharge Isolation Valve Exercise valve for oper' ability every three months.

Test Requirement:

Closing this valve prevents injection of liquid poison and Basis for Relief:

prevents system from being available for operation as re-quired by Technical Specifications. Testing can only occur during cold shutdown.

/

t Alternate Testing: Exercise valve each reactor cold shutdown but not more frequently than quarterly.

1536 188

~ ' ~

21 Relief Requect Basis Systen: Liquid Poison System (Print M-107)

Valve:

Check Valve VP300 Category: C ASME Class: 1 Function:

Once system is actuated, check valve prevents nitrogen fro = escaping -

~

to the steam drum while establishing a syphon Test Requirement: Exercise valve for operability every three months Basis for Relief: The valve has no operator.

In addition, pressure cannot be

~

applied to test valve operation without breaching primary pressure boundary.

Alternate Testing: Exercise valve every cold shutdown but not more frequently than quarterly.

1536 189

22 Relief Request Basis System: Shutdown Cooling System (Print M-lot) valve:

Mo7056,107057, MOT 058, MoTos9 Category: B ASME Class: 1 Function:

Shutdown Cooling System Inler, and Discharge Isolation Valves Test Requirement:

Exercise valves for op'erability every three months Basis for Relief:

Exercising these valves while the reactor is at operating pressure would overpressurize the shutdown cooling system (design pressure 300 psig).

In addition, admend=ent 28 to the Technical Specifications requires opening of the valve breakers at system pressure greater than 300 psig.

Alternate Testing:

The valves are exercised as part of putting the system in service during each shutdown.

1536 190

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=.+.-e....e 23 Relief Request-Basis s

System: Treated Waste Return (Print M-108)

Valve:

Isolation Valve CV4049 and Check Valve VRW 313 Category: A and A/C AS!E Class:

2 Function: To Isolate Containment Test Requirement:

Exercise quarterly and' local leak rate test each reactor shutdown for refueling Basis for Relief:

The valves are passive valves that are in the position that vill perform their intended function. Thus, exercising will not provide any additional margin.of safety.

Alternate Testing: Local leak rate test at each reactor shutdown for refueling.

1536 10

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Relier Requent Basis Denineralized Water Supply (Print M-110)

System:

Valve:

Inlet Check Valve Category:

A/C ASME Class: 2 Function: To Isolate Containnent Exercise quarterly and' local leak rate test each reactor Test Requirement:

shutdown for refueling There is no means to verify closure of the check valve except Basis for Relief:

during a local leak rate test. Thus, the local leak rate test vill be the only means of testing.

Alternate Testing:

Local leak rate test each reactor shutdown for refueling.

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Relier Request Bauis System:

Liquid Poison System (M-121)

Valve:

CV4050 Category:

B ASME Class: 1 Function: Isolate Flow of Liquid Poison to Recirculation Pump Suction

. Test Requirement:

Exercise valve for operability every three months.

Basis for Relief:

An interlock opens this valve automatically when either recirculating pump is in service. Thus, exercising this valve requires taking both recirculating pumps out of ser-vice.

Alternate Testing:

Exercise valve and verify valve position indication during any shutdown in which both recirculation pu=ps are secured, or as a minimum., each reactor shutdown for refueling.

1536 193

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• Relier Request Basis System:

Liquid Poison Supply to Reactor Vessel (Print M-121)

Valve:

Check Valve in Liquid Poison Supply Line to Reactor Vessel (VP302) and check Valve in Liquid Poison Supply Line to Recirculating Pumps (VP301)

Category: C ASIE Class:

1 Function: To prevent reactor vater backflow through Liquid Poison Line Test Requirement: Exercise valves for operability every three months Basis for Relief:

The check valves have no operators. Exercising these valves by initiating flow in the system would introduce liqu'd poison into the reactor during operation or shutdown.

Alternate Testing:

Visually inspect valves each reactor shutdown for refueling by removing valve internals Discussion: The liquid poison check valves are a Chapman Type V tilting disc check valve which has a three-piece body construction. Tha seat ring, disc and pivot pins are located in the center section which is secured between two flanges with twelve studs.

This type of check valve construction lends itself to ease of disassembly, inspec tion, and reasaembly.

In order to accomodate this inspection, a 3" cate valve must be inst,.lled dosTistress of VP302 so the check valve can be isolated from the re.. r vessel.

1536 194

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Ratings List Rating 923V 900 lb. ASA and API: 900 lb. at 350" F.

IS23V 1500 lb. ASA and API: 1500 lb. at 850' F.

2023V 2000 lb. ASA and API: 2000 lb. at 850' F.

2523V 2500 lb. ASA and API: 2500 lb. at S5,0* F.

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29 P

=

Relief Request Bacia System:

Main Steam System (Print it-121)

Vr.1ve :

M07050 Category: A AS!E. Class:

1 Function: To isolate main steam line prior to leaving the containment Test Requirement: Exercise valve for operability every three months and leak test each reactor shutdown for refueling.

Basis for Relief: Exercising this valve interrupts all main steam flow thus exercising must occur during a cold shutdown condition.

Leak testin6 is only possible during USSS hydrostatic test.

Alternate Testing: Exercise valve during each reactor shutdown. iiote valve leakage during each NSSS hydrostatic test associated with a reactor shutdown for refueling.

1536 197

~

30 Relier Request Basic Main Stean Line Drain Isolation Valve (Print M-121)

Systen:

Valve:

M07065 Category: A ASME Class: 1 To Isolate Main Steam Line Drain to Condenser Function:

Exercise valve for operability every three months and Test Requirement: leak test each reactor shutdown for refueling The valve is electrically disabled in the closed position and Basis for Relief:

does not have to change position to perform its intended function; hus, no exercising of the valve vill be performed Note leakage rate through the valve during each USSS Alternate Testing:

hydrostatic test associated with a reactor shutdown for refueling.

\\5% \\%

31 k

Relier Request 3 asis Systen:

FeedWater System (Print M-121)

Valve:

FeedWater Check (VFW9) and Stop Check (VFW304)

Category:

A&C ASME Clr.ss:

1 Function: Tb prevent feedvater backflow from steam drun Test Requirement: Exercise for operability every three months and leak. test each reactor shutdown for refueling Basin for Relief: The check valve has no operator. The stop check valve cannot be closed against the pressure present in this line through which all feedvater to the reactor flows.

Each reactor shut-down for refueling, a local leak rate test using air is per-formed on these valves.

The added benefit resulting from the hand operation of the feedvatet stop check valve, VFW9,. each reactor shutdown, would be minimal.

All that vould be proven is that the check valve disc can be forced down upon its seat (it can't be hnnd operated after an accident).

This does not in any way prove the proper operation of the check valve.

In addition, an operator will spend about one-half hour in

~ ~ '

a high radiation area (e-350 mR/hr).

A quarterly valve testing would result in about 700 mR/yr additional exposure. This addi-tional personnel exposure is not offset by the incremental benefit resulting from the exercising of the feedvater checP valve.

Alternate Testing: Perform a leak rate test each reactor shutdown for refueling.

\\

32' Roller Requent Basis System:

Control Rod Drive (Print M-122)

Valve:

Scram Inlet (CVUC09) and Outlet (CVUC10) Isolation Valves (32 Sets of 2 valves)

Category: B ASME Class: 2 Function: To cause a control rod drive to insert rapidly Test Requirement: Exercise valves for opeiability every three months.

Basis for Relief: Exercising these valves vould cause the associated control rod to scram.

Alternate Testing:

Exercise valves prior to reactor critical approach following a cold shutdown.

~

33 Relief Request 31 sis s

Systen: Enclosure Spray System (Print ::-123)

Valve:

FD7064, mot 068 (Diasbled closed)

Category:

B AS!E Class: 2 Function: Enclosure Spray Isolation Valves Test Requirement:' Exercise valves for op'erability every three months.

Basis for Relief:

Exercising these valves during power operation vould result in spraying water on energized electrical equipment inside containcent. Even though M07068 is disabled closed, it is a backup for M07064; thus, testing would be required.

MOTC64 and M07068 cannot be exercised during cold shutdowns because the fire system header cust be taken out of service and drained to allow the exercising of the valves. This vill pose an unwarranted fire hazard if the fire system is not available in the containment. Testing during each reactor shutdown foi-refueling presents a c: ore acceptable risk as far as fire suppression capabilities in the containment.

?

Alternate Testing: Exercise valves each reactor shutdown for refueling.

S 1536 201

3h Relier Request Basis System: Core Spray System (Print M-123)

Core Spray Pump Discharge Check Valves (VPI306, VPI307) and Core Spray.

Valve:

Test Tank Inlet Check Valve (VPI300)

Category: C ASME Class:

3 Function: To prevent backflow in the Core Spray System Test Requirement:

Exercise valves for operability every three months.

~

Basis for Relief:

The valves have no operators. They cannot be exercised by initiating flow in the system during power operation because the core spray pumps cannot be operated for test during power operation.

Alternate Testing:

Once each reactor shutdown for refueling.

(See Core Spray Pump Relier Request discussion because these valves can only be tested when the pump is tested. )

1536 202

1 35

~

s Relier Request 31 sis System:

Core Spray Sytem (Print !!-123)

Valve:

Primary Check Valves (VPI 303 and VPI 30h)

Category:

C ASME Class:

1 Function: Primary check valves in the c, ore spray lines to prevent reactor pressure from pressurizing'Iines if the isolation valves were opened Test Requirement: Exercise for operabilitiy every three months Basis for Relief: The primary check valvec have no operators. The valves cannot be opened against operating reactor pressure by initiating flow through these lines, because core spray system pressure is much less tnan operating reactor pressure. During shutdown, the initiation of flow through these lines would introduce nonreactor grade water into the core. The only means to insure ' proper valve operation is to disassemble and inspect the valve during each reactor shutdown for refueling. There exists no method to insure disc movement torque requirements are met.

The valve vill be in-spected and verified that the disc is free to move.

i Alternate Testing:

Disassemble and inspect each reactor shutdown for refueling 1536 203

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List 2023V 2 0 0 0 !!3 r

List 2523V 2500 lla-ASA and API t

Inc Jonnections

- List 923V,1523V,2023V and 2523V valves are available wit! welding en& onry.

' Dimensions

-List 923V.

Size cf Wive 3

4 5

6 8

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AB 11 IS 22 24 29 33 AI 9M 11M 12M 16M 19M 22 d'

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39 Relief Ilequest Basis System: Core Spray System (Print 11-123)

Valve:

Secondary Check Valves (VPI301 and VPI302)

CateSory:

C ASIE Class: 1 Function:

To prevent water backflow fro = the reactor to the fire water system

~ Test Requirement: Exercise for operabilit"y every three months Basis for Relief: The secondary check valves have no operators. Testing of the valves vill take the core spray system out of service. Thus a full flow test will be performed by allowing the fire water to enter the service water system and then be discharged to the canal.

(Note that proper sampling and analysis of the fire water will be performed to insure no uncontrolled release.) This full flow testing vill be scheduled each reactor cold shutdown (but not more frequently than three months).

s J

Alternate Testing:

Full flow test the check valves each reactor cold shutdown (but not more frequently than three months).

e 9

1536 207 b

w

-=

D ho Relier Bequest Basis Reactor Depressuriation System (Print A-203)

System:

valve:

SV4984 - sv4987 Category:

A ASME Class: 1 Function: Depressurization Valve Test Requirement:

Exercise for operability every three conths.

Basis for Relief:

The valve cannot be fully stroked unless continuous primary system presqure is applied.

During testing, pressure in the spool piece between the isolation valve and the depressuri-zation vuve is relieved before the depressurization valve reaches the fully stroked position. Thus, only partial stroking of the valve is possible during testing and no valve stroke timing can be performed.

Alternate Testin6:

Exercise the depressurization valve each reactor cold shutdown, but not more frequently than three months.

This exercising vill only entail a partial stroking of the valve 2na no inve stroke timin;;.

15 % 208 S

.