ML20053E534

Forwards Questions & Comments Re Inservice Testing Program for Pumps & Valves,Which Will Serve as Agenda for 820629-30 Site Meeting

ML20053E534
Person / Time
Site:	Sequoyah
Issue date:	06/02/1982
From:	Adensam E Office of Nuclear Reactor Regulation
To:	Parris H TENNESSEE VALLEY AUTHORITY
References
NUDOCS 8206080503
Download: ML20053E534 (14)

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J U.'l 2 1932 DISTRIBUT50N: m 6 Docket No. 50-327/328 NRC P9R V Local PDR LB #4 r/f Docket flos: 50-327 R. Tedesco and 50-328 E. Adensam C. Stable M. Duncan Mr. H. G. Parris OELD tianrger of Power NSIC Tennessee Valley Authority TIC 500A Chestnut Street, Tower II ACRS (16)

Chat;anooga, Tennessee 37401

Subject:

Sequoyah Pump and Valve Inservice Testing Program EGEG, Idaho is assisting NRC in the review of Inservice Testing Program for pumps and valves for nuclear power plants. Enclosed is a list of questions on Sequoyah related to this test program, which is to serve as an agenda for a meeting at the Sequoyah site on June 29-30, 1982.

Your staff has agreed to these dates.

If there are any questions concerning the topics for discussion, please contact J. Page, the NRC reviewer at (301) 492-8422.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely, e

Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing

Enclosure:

As stated cc: Herbert Rockhold '

EG&G, Inc.

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8206000503 920602 Nm PDR ADOCK 05000327 OFFICIAL RECORD COPY usam mi-mm p

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SEQUOYAH Mr. H. G. Parris Manager of Power Tennessee Valley Authority 500A Chestnut Street, Tower II Chattanooga, Tennessee 37401

'cc: Herbert S. Sanger, Jr., Esq.

General Counsel Tennessee Valley Authority 400 Commerce Avenue E 11B 33 Knoxville, Tennessee 37902 Mr. H. N. Culver Tennessee Valley Authority 400 Commerce Avenue, 249A HBB Knoxville, Tennessee 37902 Mr. Bob Faas Westinghouse Electric Corp.

P.O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. Jerry Wills Tennessee Valley Authority 400 Chestnut Street, Tower II Chattanooga, Tennessee 37401 l

Mr. J. F. Cox Tennessee Valley Authority 400 Commerce Avenue, W10C131C Knoxville, Tennessee 37902 Resident Inspector /Sequoyah NPS c/o U.S. Nuclear Regulatory Commission 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 James P. O'Reilly, Regi.onal Administrator U.S. Nuclear Regulatory Commission, Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 me e 9

Ol77j QUESTIONS AND COMMENTS CONCERNING THE TENNESSEE VALLEY AUTHORITY INSERVICE TESTING PROGRAM FOR SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 (Ref:

Docket Number 50-327 and 50-328)

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Valve Testing Program A.

General Conments and Ouestions r

1.

These questions and coments primarily address Unit 1 unless otherwise specified. Any differences betvaen Unit 1 and Unit 2 should be identified during the w rking meeting.

2.

The objective of measurement of stroke times for power operated valves is for early detection or predicting valve degradation and ultimate f ailure.

Therefore, stroke times must be measured and analyzed per IW-3413 for all power operated valves unless a specific technical justification is provided that demonstrates

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that stroke timing is impractical.

3.

It is the current NRC position that the emergency d.iesel generator subsystems can be tested with the diesel gener'ator as a unit and need not be tested separately per Section XI. Howeier, the diesel fuel oil transfer pumps and valves and the air start valves (if applicable) are required to be included in the IST program, tested and documented per Section XI.

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4.

Are all valves with f ail safe actuators tested by observing the operation of the valves upon loss of actuator power as stated in IWV-34157

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5.

Provide the following P&ID's for our review at the working meeting.

47W865-5 Air Conditioning Chilled Wcter 47W548 Canpressed Air

~ 47W846-2 Control and Service Air 47W855-1 Fuel Pool Cooling Diesel Starting Air (if applicable) 6.

Are all containment isolation valves that are le,ak-rate t.ested contained in the IST program?

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B.

Main Steam System l

1.

Provide the specific technical justification for.'not f ull stroke '

h exercising Valves FCV-1-4, FCV-1-11, FCV-1-22, and FCV-1-29 during power operation.

C.

Feedwater System 0

l.

Can Valves FCV-3-33, FCV-3-47, FCV-3-87, and FCV-3-100 be partial stroke exercised quarterly?

2.

How are check Valves 3-508, 3-509, 3-510, and 3-5.11 verified shut during hot standby and hot shutdown?

D.

Auxiliary Feedwater System 1.

Ar'e.each of the following check valves full stroke exercised during hot standby or hot shutdown?

2.

3-805 3-891 3-806 3-892 3-810

2..

Provide the specific

• technical justification for not exercising 3-805, 3-806, and 3-810 to the shut position quarterly.

3.

Do Valves 3-891 and 3-892 perform any safety related function in the closed position?.

4 Are each of the valves listed in relief request PV-12 full stroke exercised during each hot standby or hot shutdown mode (not to exceed once per quarter)?

5.

Provide the specific technical justification for not full stroke exercising Valves FCV-1-17 and FCV-1-18 quart'erly.

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6.

Review the safety related function of check Valves 3-894 and 3-895 (locations B-6 and B-7) to determine if they shoUld be included in the IST program and categorized C.

E.

Fire Protection System l.

What is the safety related function of Valves FCV-26-241, FCV-26-2'2, FCV-26-24t and FCV-26-2457 t.

F.

Heating and Ventilating Air Flow System 1.

Do Valves30-571, 30-572, and 30-573 perfonn any safety function in the open position?

G.

' Demineralized hter and Cask Decontamination System 1.

How does normally open passive Valve 59-529 perform a containment isolation function?

H.

Chemical and Volume Control Sy' stem 1.

Do Valves FCV-62-90 and FCV-62-91 perform a containme[t isolation 1

function?

2.

Provide a more detailed technical justification for not

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exercising Valves LCV-62-135, LCV-62-136, FCV-62-132, and FCV-62-133 during power operation.

3.

Is Valve 62-519 always shut during power operation?

4 Provide the specific technical 'ostification for not full stroke exerc'ising check Valves62-525 and 62-532 during cold shutdowns.

5.

Provide the specific technical justification for not full stroke exercising check Valve 62-504 during cold shutdown.

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6.

What is the safety related function of check Valve 62-6977 i

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7.

Review the safety related functions of the following valves to o

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determine if they should be included in the IST program and categorized as indicated.

Categori A Category A/C FCV-62-69 (A-2)62-717 (A-2)

FCV-62-70 (A-2)62-660 (A-2)

FCV-62-84 (B-2)62-716 (A-2)62-659 (B-2)62-661 (B-2)62-560 (F-6)62-561 (F-6)62-562 (H-5)62-563 (H-5)

I.

Safety Injection System 1.

How does exercising Valves FCV-63-8 and FCV-63-il result in flooding the containment?

2.

Provide the specific

• technical justification for not full stroke exercising Valves FCV-63-72 and FCV-63-73 during power operation.

Are the position indicators for these valves verified to a'ctually reflect valve position per IWV-33007

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3.

Provide a more detailed technical justification for not full stroke exercising Valves FCV-63-67, FCV-63-80, FCV-63-98, and FCV-63-il8 during power operation.

4.

If closure of Valve FCV-63-152 or FCV-63-153 does not result in inoperability of cold leg injection, then how can this be true for Valves FCV-63-156 and FCV-63-157?

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5.

If closure of Valve FCV-74-33 or FCV-74-35 does not result in inoperability of cold leg injection, then how can this be true for Valve FCV-63-1727 6.

Can check Valve 63-502 be full or partial stroke exercised during power operation via the flowpath through HCV-74-34 back to the RHR suction line?

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7 Does " pump test" in the remarks column for Valves63-524 f :

and 63-526 imply these valves are partial stroke exercised during the quarterly pump tests?

8.

How are the check valves in relief request PV-5 partial stroke exercised during cold shutdowns? How are these valves verified shut (a safety related posi,'on)?

9.

Review the safety related functions of Valves63-558 and 63-559 to determine if they should be categorized A/C.

2.

10. How is a full stroke exercise of check Valves63-560, 63-561,63-562, and 63-563 verified during the cold shutdown exercising tests?

11. How is valve closure (a safety related. position) verified for the following valves:

63-563 63-635 63-640 63-560 63-633 63-641 63-561 63-632 63-643 63-562 63-634 63-644

12. Could' partial stroke exercising the check valves identified in relief request PV-6 during cold shutdowns result in a low temperature overpressurization of the RCS?

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When are the Technical Specifications as indicated by flote 1 on Page C-27 of your IST program expected to be revised?

14. What alternate tests have been considered for full stroke-exercising check Valves63-622, 63-623,63-624, and 63.-625?

15. Provide a more ' specific technical justification for not exercising check Valve 63-570 shut during power operation.

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Essential Raw Cooling Water System 1.

Review the safety related function of the follosihg valves to determine if they should be included in the IST program and categorized as indicated.

Sheet 1 Category C_

Location 1-67 -508B C-7 1-67-513B D-7 1-67-517A C-8 l-67-512B C-8 1-67-508A C-ll 1-67-513A 0-11 1-67-512A C-10

• 1-67-517B C-10

.2.

Can the component cooling heat removal load be shifted to the "C" heat exchanger to permit exercising Val'ves 1-FCV-67-146 and 1-FCV-67-478 quarterly?

3.

Should Valve 1-FCV-67-223 be categorized B-ACT rather than C?

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4.

How are the following check valves verified shut (the safety-related position) quarterly?

67-580D 67-580B 67-580C 67 530A 5.

How are the following check valves verified shut (the safety related position) during cold shutdown?

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Why are Valves 2-FCV-67-217 and 2-FCV-67-219 (apparently Unit 2 valves) included in the Unit 1 IST program?

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Reactor Coolant System' 1.

Review the safety related functions of check Valve 68-559 (location B-9) to determine if it should be included in the IST program and categorized A/C.

2.

Do the following valves perform any safety related functions?

FSV-68.394

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(location D-7)

FSV-68-395 (loc,ation D-7)

FSV-68-396 (location D-7)

FSV-68-397 (location D-7)

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Waste Disposal System 1.

Provide a more specific technical justification for 'iot exercising check Valves77-868 and 77-849 during,,pcVer operation.

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Component Cooling System 1.

How are check Valves70-679 and 70-692 verified' shut (their. -

safety related position) during cold shutdown?

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Containment Soray System 1.

How can exercising Valves FCV-72-40 and FCV-72-41 during power operation result in flooding of lower containment? Do these valves perform a containment isolation function?

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2.

Can design accident analysis flow be achieved through the containment

• spray pumps suction and discharge check Valves 72-506, 72-507, 72-528, and 72-529 utilizing the test line to the RWST?

3.

Vhat alternate tests have been considered for full stroke exercising check Valves 72-548, 72-547, 72-555, and 72-556 to ;

comply with the code specified testing frequency?

Should these valves be categor.ized A/C?

4.

Review the. safety related function of the following valves to determine if 'they should *be included in the IST program and categorized A-passive.

72-546 (location B-4)

"72-545 (location C-4) 72-554 (location E-4) 72-553 (location F-4)

P.

Residual Heat Removal System 1.

How are Valves FCV-74-12 and FCV-74-24 full stroke exercised quarterly?

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2.

Provide the specific technical justification for not full stroke exercising check Valves74-514 and 74-515 during power ope' at. ion.

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Primary Water System

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1 1.

How is Valve 81-502 exercised shut (its safety related position) during cold shutdowns?

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Upper Head Injection System 1.

Do Valves FCV-87-7 and FCV-87-8 perform a pressure isolation function?

2.

Do Valves FCV-87-10 and FCV-87-11 perform a containment isolation function?

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3.

What alternate tests have been considered for full stroke exercising the following check valves?87-558 87-561 87-559 87-562 87-560 87-563 O'

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Pump Testing Program

, 1.

'Can a hand h' eld temperature monitor be utilized to meIsure bearing temperatur~e for pumps to which Note 6 in your IST program applies?

2.

Hov =is differential pressure measured for the turbine driven auxiliary feedwater pump?

3.

Are the centrifugal charging pumps always tested in a fixed resistance test loop during power operation?

4 When are the Sequoy~ah Unit 1 Technical Specifications' eapected to be revised to delete' the testing requirements for the' auxiliary ERCW p unps?

5.

How is inlet piessure for the ERCW and the auxiliary ERCW pumps measured?

6.

Have pump curves eitablishing.a relationship between pump flow and differential pressure.been developed for the auxiliary ERCW, ERCW and component cooling warar pumps?

If so, provide these curves for our review at the working nieeting.

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What alternate tests have been considered for determining the imechanical condition of the ERCW and the auxiliary ERCW pumps in lieu of the vibration amplitude msasurements?

8.

How many ERSW pumps exist for each Sequoyah Unit?

9.

How is flowrate measured for the containment spray pumps?

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Do any of the following pumps receive emergency power or perform a specific function in shutting down the reactor or in mitigating the consequences of an accident.

a Spent Fuel Pool Cooling Pumps Boric Acid Transfer Ptsnps Diesel Fuel Oil Transfer Pumps Chilled Water Ptsnps E

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