ML20198S828

Notification of 860610-11 Meetings W/Util & Eg&G in Bethesda,Md to Discuss Encl Eg&G Questions & Comments Re Util Inservice Testing Program

ML20198S828
Person / Time
Site:	South Texas
Issue date:	06/02/1986
From:	Kadambi N Office of Nuclear Reactor Regulation
To:	Noonan V Office of Nuclear Reactor Regulation
References
NUDOCS 8606100572
Download: ML20198S828 (12)

Text

. . wae w -

Docket Nos.: 50-498 and 50-499 2M h MEMORANDUM FOR: Vincent S. Noonan, Director PWR Project Directorate #5 Division of PWR licensing-A FROM: N. P. Kadambi, Project Manager PWR Project Directorate #5 Division of PWR licensing-A

SUBJECT:

NOTICE OF MEETING WITH SOUTH TEXAS PROJECT (STP)

ON PUMP AND VAI.VE IN-SERVICE TESTING ,

DATES & TIME: June 10 and 11, 1986, 8:30 am each day LOCATION: Room P-114 Phillips Building Bethesda, Maryland PURPOSE: Staff contractors at EG8G, Idaho have reviewed the In-Service Testing program submitted by STP and provided the comments and questions enclosed. The enclosure will constitute the agenda for the meeting.

PARTICIPANTS: NRC N. P. Kadambi, S. Hou et.al.

EG&G T. Cook, D. Monnie et.al.

HL&P M. McBurnett et.al.

N. Prasad Kadambi, Project Manager PWR Project Directorate #5 3 Division of PWR licensing-A

Enclosure:

As stated l cc: See next page NOTE: NRC meetings are open to members of the public to attend as I observers. Those wishing to attend must contact N. P. Kadambi at l (301) 424-0508.

I Il

• PD#5

\

NPKadambi .

[p/M86 8606100572 860602 PDR A

ADOCK 05000498 PDR

Meeting Notice Distribution eigecket: files. NRC Participants NRC PDR local PDR N. P. Kadambi PD#5 R/F S. Fou ORAS ,.

H. Denton T. Novak N. P. Kadambi OELD E. Jordan B. Grimes J. Partlow Receptionist (Building where meeting is being held)

ACRS (10)

OPA N. Olson Resident Inspector Regional Administrator cc: Licensee / applicant & Service list a-k

o UNITED STATES f[ g y p, NUCLEAR REGULATORY COMMISSION j WASHINGTON, D. C. 20555 5 &g

% .....J P gg 6; Docket Nos.: 50-498 and 50-499 MEMORANDUM FOR: Vincent S. Noonan, Director PWR Project Directorate #5 Division of PWR I.icensing-A FROM: N. P. Kadambi, Project Manager PWR Project Directorate #5 Division of PWR licensing-A

SUBJECT:

NOTICE OF MEETING WITH SOUTP TEXAS PROJECT (STP)

ON PUMP AND VALVE IN-SERVICE TESTING DATES & TIME: June 10 and 11, 1986, 8:30 am each day

,. LOCATION: Room P-114 Phillips Building Bethesda, Maryland PURPOSE: Staff contractors at EG&G, Idaho have reviewed the In-Service Testing program submitted by STP and provided the comments and questions enclosed. The enclosure will constitute ~ the agenda for the meeting.

PARTICIPANTS: NRC l

N. P. Kadambi, S. Pou et.al.

EG&G T. Cook, D. Monnie et.al.

Pl&P l

M. McBurnett et.al.

il l

/6 (! r ow b, l I

N. Prasad Kadambi, Project Manager PWR Project Directorate #5 Division of PWR I.icensing-A

Enclosure:

As stated cc: See next page NOTE: NRC meetings are open to members of the public to attend as observers. Those wishing to attend must contact N. P. Kadambi at (301) 424-0508.

l l

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION UNIT 1 PUMP AND VALVE INSERVICE TESTING PROGRAM COMMENTS AND OUESTIONS A. General Comments and Ouestions

~.

1. Are all valves that are Appendix J, Type C, leak tested included in the IST program and categorized A or A/C as appropriate?

2. Provide the limiting value of full stroke time for all power operated valves in the IST program that currently do not have this time identified.

3. Solenoid operated valves are not exempted from the stroke time measurement requirements of Section XI; their stroke times must be measured and corrective action taken if these times exceed the

• ,. limiting value of full-stroke time. The NRC staff will grant

-- relief from the trending requirements of Section XI (Paragraph IWV-3417 (a)) for these rapid acting valves, however, l

in order to obtain this relief the licensee must assign a maximum  !

limiting stroke time of 2 seconds to these valves. Does the maximum value of limiting stroke time assigned to the solenoid

~

operated valves in the IST program meet the above staff position? Valve relief request number 8 (RR-8) may be affected.

4. Relief from exercising passive valves is unnecessary if those j valves are identified as passive in the IST program. I (Reference valve relief request numbers 4 and 5, RR-4 and RR-5.)

5. The NRC staff position is that the emergency diesel generators perform a safety-related function and the appropriate pumps and valves in the emergency diesel air start, diesel cooling water, and fuel o11 transfer systems should be inc19ded in the IST program and tested in accordance with the Code. Engine mounted ,

pumps are considered to be part of the diesel and need not be tested separately.

1

. l

4

6. Do the spent fuel pool pumps perform a safety related function at the South Texas Project Unit 17 If so, these pumps should be included in the IST program and tested in accordance with the requirements of Section XI.

~.

B. Auxiliary Feedwater System

1. Why are valves AF-0036, AF-0058, AF-0091 and AF-0011 categorized BC and only a check valve (CV) test performed? Provide a discussion of how operability of these valves is demonstrated during the quarterly test.

2. Valves MOV-0048, MOV-0065, MOV-0085 and MOV-0019 have a test requirement of "CV" which states the valve will be exercised quarterly and a "CS" test which states the valve is only tested

,- dur16g cold shutdowns and refueling outages. Which of these entries is correct for these valves? Why are these valves categorized both as B and BC7

3. Can. flow from the main feedwater system be used to quarterly full-stroke exercise check valves AF-0119, AF-0120, AF-0121

~

and AF-0122?

4. Is the motor operator on valve MOV-0143 normally closed rather than normally open as indicated in the IST program? How is the check valve function verified to full stroke during the quarterly testing?

5. Is valve MOV-0514 normally closed as indicated in the IST program or normally open as shown in the P&ID?

6. Provide P&ID 9F00020 that shows the auxiliary feedwater storage tank.

2

, , . . , . _ , , , . _ _ , . _ _ . , , .._y..,. _,, . .,y_ - -, ,,g_,

i I

. C. Component Coolina Water System

1. Review the safety related function of the following valves to determine if they should be categorized A:

MOV-0057 MOV-0136 MOV-0197 MOV-0059 MOV-0137 MOV-0199 MOV-0069 MOV-0148 MOV-0210 MOV-0070 MOV-0149 MOV-0209 MOV-0012 MOV-0122 MOV-0182 MOV-0050 MOV-0130 MOV-0190

2. Review the safety related function of the following valves to determine if they should be categorized C:

CC-0058 CC-0138 CC-0198

' "! "-d CC-0013 CC-0123 CC-0183 CC-0315 CC-0313 CC-0311 CC-0746 l

3. What is the safety position of check valves CC-0315, CC-0313

. and CC-03117 If this position is closed, how is the valve ,

position verified? I

4. Will exercising valves MOV-0235 and MOV-0236 result in thermal shock to the letdown heat exchanger?

1

5. Review the safety-related function of valves CC-0051, CC-0131 l and CC-0191 to determine if they should be included in the IST program.

6. Review the safety-related function of valve CC-0319 to determine if it should be included in the IST program.

7. Review the safety-related function of valves MOV-0318, MOV-0291, FV-4493 and MOV-0404 to determine if they should be Category A.

3

..- , ~ _ , . . _ _ - , _ _y___-- ._,_ __

_,__ . _,_.___ g . _ _ _ _ _ , - . . _ - _ , 77.m.,__-, . 7,__ .,m.9, ,,- . .. -,.

D. Essential Chilled Water System i

1. Provide a detailed technical justification for not exercising valves MOV-0254, M0V-0268 and MOV-0269 quarterly. ,,

2. Review the safety-related function of check valves CH-0286, CH-0295 and CH-0304 to determine if they should be Category C.

f

3. The NRC staff position is that if a control valve has a required fail-safe position then it must be fail-safe tested to that position and stroke timed if possible.

Can valves TV-9476, TV-9477, TV-9486, TV-9487, TV-9496 and TV-9497 be fail-safe tested from the closed position?

,- E. Containment Hydrocen Monitorina System -

1. Review the safety-related function of valves FV-4100, FV-4124, i FV-4125, FV-4126, FV-4103, FV-4129','FV-4130 and FV-4131 to determine if t' hey should be included in the IST program.

~

F. Containment Soray System

1. Is the flow during the testing of check valves CS-0018A, CS-00188 1

and CS-0018C equivalent to the accident flow rate from the spray 4

additive tanks? Should these valves be Category C7

'r .

2. Review the safety-related function of valves MOV-000?A, MOV-00018 and MOV-001C to determine if they should be Category A.

3. When flow through a check valve is used to indicate a full-stroke exercise of the valve disk, the NRC staff position is that verification of the maximum flow rate identified in any of the plant's safety analyses through the valve would be an adequate demonstration of the full-stroke requirement. Any flow rate less i 4 4

. . _ _ _ _ _ _ _ _ _ _ ~ _ _ - .~,. .. _ . . _ _ ,, _.___. . . . . _ _ _ _ . _ . _ _ . _ _ _ . _. _ , _ . _ . . _ . - _ . _ , .

than this will be considered partial-stroke exercising unless it can be shown (by some means such as measurement of the differential pressure across the valve), that the check valve's disk position at the lower flow rate would permit maximum required flow through the valve. .,

Does the licensee's testing procedure which is based on air flow testing meet this staff position concerning valves CS-0002, CS-0004, CS-0005 and CS-00067

4. Review the safety-related function of valves CS-0002, CS-0004, CS-0005 and CS-0006 to determine if they should be Category A/C.

In reference to these valves, relief must be requested from the test frequency requirements of Section XI whenever the proposed alternate test frequency does not meet these requirements.

Chemical and Volume Control System I G.

1. Are valves LCV-0465 and LCV-0468 accessible during power operations? Would failure of either of these valves in the closed position affect plant operation?

2. Are valves MOV-0023 and MOV-0024 accessible during power operation? Would failure of either of these valves in the closed position affect plant operation? j

3. What are the consequences of loss of the charging pump normal j suction from the VCT while exercising valves MOV-0113A l and MOV-01128 during power operation? l

4. How is valve CV-0224 full-stroke exercised during cold shutdown?

Should this valve be Category C7 1

5. How are valves CV-235A, CV-2358 and CV-0670 full-stroke exercised during power operation? Should these valves De Category C?

6. How are valves CV-234A and CV-234B individually verified to full-stroke exercise? Should these valves be Category C7

7. Provide a more detailed technical justification for not full-stroke exercising valve FCV-0205 during power operatio'n.

Can this valve be stroke timed while it is being full-stroke exercised?

8. Provide a more detailed technical justification for not full-stroke exercising valve MOV-0025 during power operation.

9. Are valves CV-0001, CV-0002, CV-0004 and CV-0005 full-stroke exercised quarterly? Should these valves be categorized C7

10. Does relief request four (RR-4) apply to LV-31197 a- .

11. Should CV-0009, CV-0334, CV-0338, CV-0349, CV-0351, CV-0346 and CV-0217 be categorized C7

12. How are valves CV-0338 and CV-0349' full-stroke exercised quarterly? .

13. How is CV-0217 full-stroke exercised during cold shutdowns?

14. Is thernal shock to the injection nozzles and piping a consideration while exercising charging isolation valves MOV-0003 and MOV-00067 H. Essential Coo 11no Water System

1. Do check valves EW-0262, EW-0263 EW-0264. EW-0006, EW-0042 and EW-0079 perform a safety function in both the open and closed positions?

6

-.-. .- . . . - - , - - - - - -m . , v.-.n.. ,,-.,. .- . . , - - , - - . .

~

, I. Feedwater System

1. Is thermal shock to auxiliary feedwater nozzles a consideration while exercising valves FV-7189, FV-7190, FV-7191 and FV-71927

2. Review the safety-related function of valves AF-0308, AF-0309, AF-0310 and AF-0311 to determine if they should be included in the IST program.

J. Reactor Containment Buildina Normal Purae System

1. Describe the leak testing procedure utilized to demonstrate the leak tight integrity of valves MOV-0007, MOV-0008, MOV-0009 and MOV-0010.

K. Reactor Containment Buildina Supplementary Purae System 7

-- 1. Describe the leak testing procedure utilized to demonstrate the leak tight integrity of valves MOV-0001, MOV-0003, MOV-0005 and MOV-0006.

L. Main Steam System -

1. Can the stroke time of valves PV-7411, PV-7421, PV-7431 and PV-7441 be measured during cold shutdown exercising?

M. Residual Heat Removal Service

1. Provide a detailed technical justification for not stroke timing the following valves while exercising them: HCV-864, HCV-865, HCV-866 FCV-851, FCV-852 and FCV-853.

2. Review the isolation function of valves MOV-0060A, MOV-00608, MOV-0060C, MOV-0061A, MOV-0061B and MOV-0061C to determine if they should be classified as pressure boundary isolation valves.

7 -

__2_.

3. Review the safety-related function of valves PSV-3851 PSV-3852 and PSV-3853 to determine if they should be included in the IST program.

~.

4. Review the safety function of valves RH0166, RH0167, RH0168 RH0169, RH0170 and RH017'1 to determine if they should be included in the IST program.

N. Safety Injection System

1. Do valves XSI-0002A, XSI-0002B and XSI-0002C perform a safety function in both the open and closed positions?

2. Should valves MOV-0016A, MOV-00168 and MOV-0016C be categorized A instead of 87 .

3. Review the safety-related function of valves MOV-0018A, MOV-00188 and MOV-0018C to determine if they should be categorized A.

4. Review the safety-related function of valves XSI-0030A, XSI-0030B and XSI-0030C to determine if they should be categorized A/C.

5. Review the safety-related function of valves MOV-0004A, MOV-0004B and MOV-0004C to determine if they should be categorized A.

6. Review the safety-related function of valves XSI-0005A, XSI-0005B and XSI-0005C to determine if they should be categorized A/C.

7. What alternate methods have been investigated to demonstrate full-stroke operability of valves XSI-0046A, XSI-00468 and XSI-0046C? The NRC staff has determined that a sample disassembly and inspection program is an acceptable alternate method to utilize to demonstrate full-stroke capability of these valves.

8

~ . . ,

B. Does the safety injection pump test performed during refueling outages demonstrate that valves XSI-0038A, XSI-00388 i and XSI-0038C will accommodate the required design flow rate for which credit is taken in the safety analysis? ,,

O. Pumos

1. Is inlet pressure of the auxiliary feedwater pumps calculated or measured directly during pump testing?

2. Is inlet pressure of the essential chilled water pumps calculated or measured directly during pump testing?

3. Is inlet pressure of the boric acid transfer pumps calculated or measured directly during pump testing? How is flow measured during the testing of these pumps?

~

4. How is flow of the essential cooling water pumps measured during pump testing?

O 1

l 9

. _ _ _