L-83-168, Forwards Final Response to TMI Item II.D.1, Performance Testing of BWR & PWR Relief & Safety Valves. Conclusions Reached in Encl Evaluation on Operability of Pressurizer Safety Valves & PORVs Satisfy Commitment

From kanterella
(Redirected from L-83-168)
Jump to navigation Jump to search
Forwards Final Response to TMI Item II.D.1, Performance Testing of BWR & PWR Relief & Safety Valves. Conclusions Reached in Encl Evaluation on Operability of Pressurizer Safety Valves & PORVs Satisfy Commitment
ML17213B171
Person / Time
Site: Saint Lucie 
Issue date: 03/22/1983
From: Robert E. Uhrig
FLORIDA POWER & LIGHT CO.
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM L-83-168, NUDOCS 8303250017
Download: ML17213B171 (17)


Text

REGULATORY i ORMATION DISTRIBUTION SYS

'RIDS)

ACCESSION NUP:6303250017 DOC.DATE: 83/03/22 NOTARIZED; NO FACIL:50-389 St, Lucie Plant~

Unit 2E Flor ida Power kN Light Co.

AUTH ~ NAME AUTHOR AFFILIATION UHRIGr R ~ E B Florida Power kk Light Co, REC IP ~ NAME RECIPIENk AFFILIATION EI SENHUT E D s G ~

Assistant Director for Licensing DOCKET 05000389

SUBJECT:

Forwards final response to TMI Item II,D.ig" Testing of BKH 6,

PYR Relief kk Safety Valves.

reached in encl evaluation on operability of safety valves kk, PURVs satisfy commitment.

DISTRIBUTION CODE:

BOOIS COPIES RECEIVED:LTR J ENCL TITLE: Licensing Submittal'SAR/FSAR Amdts 8, Related NOTES:

Performance Conclusions pressurizer SIZE:

Correspondence RECIPIENT ID CODE/NAME A/D LICENSNG LIC BR P3 LA INTERNAL: ELD/HDS2 IE/DEPER/EPB 36 NRH/DE/AEAB NRH/DE/EMEB, NRH/DE/GB 28 NRH/DE/MEB 16 NRR/DE/QAB 21 NRH/DHFS/HFEB40 NRH/DL/SSPB NRR/DSI/ASB NRH/DSI/CS8 09 NRR/DS I/METB 12 RAB 22 G

ILk 04 OAMI/MIB EXTERNAL!'CHS 41 DMB/DSS (AMDTS)

LPDR 03 NSIC 05 COPIES LTTR ENCL 1

0 1

0 1

0 3

1 0

1 1

2 2

1 1

1 1

1 1

1 0

1 1

1 1

1 1.

1 1

1 1

1 0

b 6

1 1

1 1

1 1

RKC IP IENT ID CODE/NAME LIC BR 43 BC

NERSESyV, 01 IE F ILE IE/DKPER/IRB 35 NRR/DE/CEB 11 NRR/DE/EQB 13 NRR/DE/HGEB 30 NRR/DE/MTEB 17 NRR/DE/SAB 24 NRR/DHFS/LQB 32 NRR/DS I/AEB 26 NRR/DSI/CPB 10 NRR/DSI/ICSB 16 NRR/DSI/PSB 19

'RR/DS I/RSB 23 RGN2 BNL(AMDTS ONLY)

FEMA~REP DIV 39 NRC PDR 02 NTIS COPIES LTTR ENCL 1

0 1

1 1

1 1

1 1

1 2

2 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 3

3 1

1 1

,1

,TOTAL NUMBER OF COPIES REQUIRED:

LTTR 52 ENCL 45 I

WW fN Iwc tr "N 1

N1 f ~'

hr " '0 1 f Nf

~,, )

1 s

l'

~

I l N

~ 1 lip l l~

I

' I'I"N" 4.

Ps<>>

N

~ 1 I

Nt Nlf 1fcf'1)NC N

IN Pr'I tft'cr' hr W '" ~ r f th ~,I t

WN ~ 'f

'l )

rr WIIIW I

~

lt'I P Ni

."Pi

) NN

) h'I NOPP/w f P 'Ill

'1 P ] qctt")

f 4II11:>>

"i hlP,>> P'1,]

t);v drPr

$ N1II>

I

<)

IP rwi"NN>

g f 'atbf IIN*>f <I, i>>

P P

gtr"'f fl rw I'wg,'

'W

~ V'1 I ~<<N t

rtht 10th-1 1

i NN)

IP,>

v t 11'Nf N 'rll1 '1 hl

)NW I 'ff'

,';IN.

~ 051 th) w I 1 A,I Nr N

~ Q f)

P.P Ni,ff)

N l(I( f 1

]I 1

1

'", Pf

]WrIwP

',',ght 0

~

N'wII I

'5 'l ilt. NP, I7~tcig cf 0'tW ll y fht 1,PI fl>>,

1 c"',Pfrw,'t 3 Pf 1

$ lg JL If

' I WW g N >

ref 'i "hr A Ng I Nt rch I

I N,

A WPW N

J II

'Nfl j I 1l'P w

I, HX W

WQ,N ll (If III

'r P

'l p,'7 tlh P,i N

I't i

II I p rrl i ttg Il,. I

~

P L

Iih N

II t hht 1

P,I r

fN

<<t

)

N h 'gI 1,,

<<[

1 1

N P

I jtc

P OX 14000, JUNO BEACH, FL 33408

+ Ib 0

CZ FLORIDA POWER & LIGHT COMPANY March 22, 1983 L-83-168 Office of Nuclear Reactor Regulations Attention:

Mr. Darrell G

~ Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Mr. Eisenhut:

Re:

ST.

LUCIE UNIT NO.

2 DOCKET NO. 50-389 POST-TMI REQUIREMENTS ITEM II.D.1 - FINAL RESPONSE The purpose of this letter is to provide the NRC with Florida Power Light Company's final response to the requirement II.D.1, "Performance Testing of Boiling Water Reactor and Pressurized Water Reactor Relief and Safety Valves" of NUREG-0737.

Our response to II.D.1 utilizes the results from Electric. Power Research Institute's valve testing program.

Attached are the results of our evaluation on the operability of the St.

Lucie Unit 2 Pressurizer Safety Valves, Power Operated Relief Valves (PORV's),

electric motor operated gate valves (block valves) and the Safety and Relief Valve Piping Evaluation.

The conclusions reached in the attachment satisfy FP&L's commitment to address the concerns of NUREG-0737, Item II.D.1 ~

If you have -any questions regarding this submittal please contact us.

Very truly yours, Robert E. Uhrig Vice President Advanced Systems and Technology REU/RJS/JES/rms Attachment goo 1

cc:

J.

P. O'Reilly, Region II Harold F. Reis, Esquire 8gQ~QQQ$ 7 PQQQ89 8~22 ppR gQOGK pg

( A PEOPLE... SERVING PEOPLE

e

~

F ~

I 1

ATTACHMENT FLORIDA POWER

& LIGHT COMPANY ST.

LUCIE UNIT 2

RESPONSE

TO NUREG"0737, ITEM II.D.1 "Performance Testing o'f Boiling Water Reactor and Pressurized Water Reactor Relief and Safety Valves."

I l

II I

CONTENTS PAGE I)

SAFETY VALVE OPERABILITY.

. I II)

POWER OPERATED RELIEF VALVE (PORV) OPERABILITY.

2 III)

ELECTRIC MOTOR OPERATED GATE

.VALVE ('LOCK 'VALVE) OPERABILITY

~

~

~

0 3

I IV)

SAFETY AND RELIEF VALVE PIPING EVALUATION 4

V)

REFERENCES 5

~ I.

SAFETY VALVE OPERABILITY In order to facilitate an expeditious evaluation of the test

data, the utilities operating and constructing

. Combustion Engineering (CE) designed plants

have, through the CE Owners
Group, requested that CE implement a

program to evaluate and apply the EPRI test results'he CE Owners Group program was subsequently initiated in April, 1982 and completed in

December, 1982.

Florida Power and Light is a participant in this program.

The approach being applied by the CE Owners Group is to show that particular EPRI tests were directly representative of plant-specific safety valve models and valve installations and that acceptable valve operation was demonstrated.

Accordingly, CE report CEN-227, entitled "Summary Report on the Operability of Pressurizer Safety Valves in CE Designed Plants",

was forwarded on December 20, 1982 to the NRC by Mr.

R.

W. Wells, Chairman of the CE Owners Group.

Florida Power and Light considers report CEN-227 to provide the required information on safety valve operability for St.

Lucie Unit 2 and finds its contents acceptable.

l

~II-POWER OPERATED RELIEF VALVE OPERABILITY (PORV)

As with the safety valves, the utilities operating and constructing Combustion Engineering (CE) designed plants

have, through the CE Owners
Group, requested that CE implement a

program to evaluate and apply the EPRI test results.

The CE Owners Group program was subsequently initiated in April, 1982 and completed in

December, 1982.

Florida Power and Light is a participant in this program.

The approach being applied by the CE Owners Group is to show that particular EPRI tests were directly representative of plant-specific PORV models and valve installations, and that acceptable valve operation was demonstrated.

Accordingly, CE report CEN-213, entitled "Summary Report on the Operability of Power Operated Relief Valves in CE Designed Plant",

was forwarded on July 1,

1982 separately to the NRC by Mr.

K.

P.

Baskin, Chairman of the CE Owners Group.

Florida Power and Light considers report CEN-213 to provide the required information on PORV operability for St.

Lucie Unit 2

and finds its contents acceptable.

~

V

~

0 34r I.

ELECTRIC MOTOR OPERATED GATE VALVE (BLOCK VALVE) OPERABILITY NUREG-0737, Item II.D.1.B contains the provision that PWR utilities demonstrate that PORV block valves function properly over the range of expected operating and accident conditions.

Florida Power and Light is a

member utility participating in the EPRI program to demonstrate the operability of these valves.

During a

meeting with NRC staff and utility representatives held on July 17,

1982, the above provision was discussed in detail and substantial agreement was reached regarding resolution of the requirement.

The details of the utility position is contained in a letter to Harold Denton,.

NRC by R.

C.

Youngdahl, Consumers

Power, dated July 24,
1981, Prototype testing of representative valve and operator configurations was performed under the EPRI program.

These test results were transmitted to Harold

Denton, NRC by R.

C.

Youngdahl, Consumers

Power, on June 1,
1982, on behalf of the member utilities, References (1) and (2).

The block valves at St.

Lucie Unit 2

are model

.0306GM88FNH (88 Series) motor operated gate valves supplied by the Westinghouse Corporation.

Florida Power and Light considers the contents of References (1) and (2) to be fully applicable to St.

Lucie Unit 2

block valves and adopts them in satisfying the requirements of NUREG-0737, Item II.D.1.B.

0

~ t+

l R

~

~

Q

~

,iIV.

SAFETY AND RELIEF VALVE PIPING EVALUATION NUREG-0737 Item II.D.l.A requires that all utilities operating and constructing Pressurized Water Reactors (PWR) plants provide a submittal that demonstrates the adequacy of the pressurizer safety and relief valve piping and supports.

In order to

~ comply with the requirement, Ebasco

Services, Inc.,

has performed a

computer analysis on the safety and relief valve piping at St.

Lucie Unit 2 to evaluate the adequacy of the piping and support system.

The SRV piping isometrics at St

~

Lucie Unit 2

were utilized to provide input to the EPRI developed RELAP 5

computer code.

The thermal-hydraulic properties developed by RELAP 5

were then inputted into a

post-processor code CALPLOTF III, developed and written by Ebasco to compute the forces for each piping segment.

The three valve actuating scenarios analyzed were the following:

a)

Two PORV's open simultaneously, SRV's closed.

b)

PORV's do not open.

All three SRV's open simultaneously.

c)

PORV's.

open.

Pressurizer pressure continues to increase and SRV's open simultaneously.

The valve opening times were selected from the data given in the EPRI Safety and Relief Valve Test Report from valve tests representative of the St.

Lucie Unit 2

valves.

The results of this present analyses were then compared to the previous analyses which resulted in the present system design.

Based on the results of this evaluation, Florida Power and Light has concluded that the St.

Lucie Unit 2

SRV piping and support system in its present configuration is adequate for the presently calculated hydraulic loads.

This satisfies Florida Power and Light's responsibility to demonstrate adequacy of the St.

Lucie Unit 2 safety and relief valve piping and support system.

~ p

~

1 N

~

~

J

~

~

REFERENCES 1.

"EPRI-Marshall Electric Motor-Operated Valve (Block Valve)

Interim Test Data Report",

NP-2514-LD, Research Project V-102, prepared by Intermountain Technologies, Inc.

2.

"EPRI Summary Report:

Westinghouse Gate Valve Closure Test-ing Program", Engineering Memorandum 5683, Revision 1, pre-pared by Westinghouse Electro-Mechanical Division, March 31, 1982.

0 E v e

I

,n

'I I

i