ML20246G108
| ML20246G108 | |
| Person / Time | |
|---|---|
| Issue date: | 04/10/1989 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| REF-GTECI-087, REF-GTECI-NI, TASK-087, TASK-87, TASK-OR ACRS-2624, NUDOCS 8905150188 | |
| Download: ML20246G108 (8) | |
Text
.
CERTIFIED COPY y <*
DATE ISSUED: April 10, 1989 J. m,
- rz, ' _ O e
fg.
hbh*0hhf J
0 tzs r < M n
a
- . g. g,j,
t.:
w Summary / Minutes of the ACRS Subcommittee on Mechanical Components February 28,.1989 Bethasda, Maryland The ACRS Subcommittee on Hechanical Components met on February 28, 1989 in Room 110 at Bethesda, MD., to coi.tinue its review of the NRC Staff's proposed generic letter relating to frequency of testing and surveillance of' safety related motor operated valves (MOVs).
Notice of the meeting was published in the Federal Register on February 17, 1989, (Attachment A).
The schedule of items covered in the meeting is in Attachment B.
A list of handouts kept with the office copy of the minutes is included in Attachment C.
There were no written or oral statements received or presented from members of the public at the meeting. 'E. G. Igne was Cognizant ACRS staff member for the meeting.
Principal Attendees ACRS C. Michelson, Chairman E. Wylie, Member J. Carroll, Member P. Wohld, ACRS consultant y mp ~ m
~C y
W GULLUw ""
DESIGNATED ORIGINAL Certified By_ [g 1
~
8905150188 890410 PDR ACRS 2624 PDC J
L____________________.
J i
4' t
iNRC Others i
'O. Rothberg R. Carr, M0 VATS R. Baer-J. Nadeau, M0 VATS F. Eherny P. Carier, General Physics i
R. Kiessel N. Ester, Duke Power
)
,L' G.:Weidenhammer B. Curry, Philadelphia Electric
{
J. Mazetis C. Callaway, NUMARC J. Huang R. Van Leav,-B & W
)
Q. Persinko M.' Schmidt, Bechtel -
R. Woods KWU Alliance
]
s W, Minnus R. Leon, Liberty Technolgy
]
W. Grave, MPR Asso.
R. Elfstrom, Toledo Edison i
Highlights 1.
G. Weidenhammer, RES, briefly presented a summary of the expert meeting held on February 1, 1989 on gate valve isolation during high energy BWR.line breaks.
The project's purpose was to provide technical assistance to the NRC in resolv-ing Generic Issue 87, " Failure of HPCI Steam Line Without Isolation." The safety significance of this testing project was to determine the ability of the isolation valves in BWR process lines to close against the flow resulting from a high energy.line break outside the containment. The tests were performed on
.3 and 10 inches, 600-900 lb., flexible wedge gate valves with Limitorque SMB-type motor operators, both AC and DC operated.
2
t j.
Some general conclusions of the panel are as listed below.
With some exceptions, the results are valid for the conditions and
. particular valve designs.
Data adds to understanding design and performance aspects of valve, 4
motor operator and diagnostic equipment.
More testing and analysis are needed before general conclusions are
)
possible.
The data should be made available for review by others.
The expert panel of 21 people consisting of valve manufacturers, i
diagnostic equipment designers, utilities, motor operator manufacturers, EPRI, ASME, NRC and national labs, specific findings are as listed below:
Unpredictat>1y high stem thrust was observed on one of the valves during closure near saturated flow conditions (referred to as a nonlinearity). This was likely due to the mechanical clearance between disc and guide allowing the disc to tilt during closure. Material hardness may contribute to this effect. The question on thermal / hydraulic flashing effects remains an unknown.
The current thrust equation with friction factor of. 5 may be 0
appropriate for estimating closing and opening thrust under blowdownconditions(forlinearvalvesonly).
Diagnostic capabilities are more valuable when both stem thrust and motor torque parameters are measured.
The efficiency of converting torque to thrust is affected by loading. This is important when setting the torque switch. ;
~ _ _ _ _ _ - _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _. - - - _
j'..
7 The load rate effects are also important when setting the torque switch.
Thrusts at which the motor will trip depends on the rate effects.
1 G.'Weidenhammer highlighted the proposed future research testing effort and budget.
For FY 1989, hot water environmental tests using 2 extra discs (0.25 and 0.125 clearances) will be considered. About $375,000 is budgeted.
Steam environmental tanks on 2-10 inch valves are planned.
About $475,000 is budgeted.
For FY 1990 more hot water environmental blowdown tests at an approxi-mate cost of $500,000 are planned.
For FY 1991, about $1000K Ccentative) will be used to provide testing for other valves as the need arises.
2.
O. Rothberg, RES, provided an overview of the status of the generic letter on MOV's meetings with the industry, implications of INEL test results and the recent CRGRM meeting on February 22, 1989.
)
The following comments on the generic letter on in-situ testing of motor operated valves as. approved by CRGR on February 22, 1989, are listed below:
Licensees must set-up a program for MOV testing for all safety-related MOVs within one year or one refue'ing outage of date of letter, whichever is later.
The program will consist of determination and verification of design basis operability, verification and adjustment of switch settings, and n
surveillance to detect deterioration or misadjustment of components.
Testing / surveillance must be accomplished at least once within 5 years or three refueling outages from the date of the letter, whichever is later.
4 n
b, I
Testing / surveillance will be continued by licensees at-intervals
{
l*
based on safety significance of MOV, maintenance history and failure history, but at least every 5 years or three refueling outages, whichever is later.
}
~
The 1icensees will reply to the letter within 6 months and then keep records; the intent is to perform an audit.
Generic Letter 87 blowdown test results are discussed.
Emphasis on design basis testing augmented by prototype testi ' is suggested in the background portion of the letter.
(The generic letter has been revised to point out the importance of testing at high delta'P.
whenever possible.)
The generic letter applies to all safety-related MOVs without exception.
Subcommittee Discussion The subcommittee will not take this matter to the full ACRS during the March 1989 meeting because the redrafted generic letter, after the Feb. 22, 1989 CRGR meeting, was not approved by senior NRC management. Another subcommittee meeting is planned for the morning of March 29,1989, if necessary, to discuss the approved generic letter.
If no significant changes are made to the generic letter reviewed during this meeting, the chairman may forego the' planned March 29, 1989 and take this matter to the full ACRS in April 1989.
The approved letter according to 0. Rothberg should be in the public document room by March 8, 1989.
NUMARC may want to comment on the NRC staff's generic letter at the March 29, 1989 meeting and/or at the April 1989 meeting.
1 l
NOTE: A transcript of the meeting is available at the NRC Public Document Room, Gelman B1dg. 2120 "L" Street, NW., Washington, D.C.
Telephone (202) 634-3383 or can be purchased from Heritage Reporting Corporation, 1220 L Street, NW., Washington, D.C. 20005, Telephone (202) 628-4888.
1 w-
- g '$y.g ATTACHMENT A
[
M Foderal Rjglst r] V{54,Jo)32'/ Friday @rsry 17,Q980'j.gj J 2 7309
.t For the Nuclear Regulatory Comminion.
changes in sch6dule, etc., which may ~
accident prevlously evaldated;%r (8)
Jer, g j'. John N.Hannon.
have occuned."
5 involve a significant reduction in"a '
the 74"y
?
Director. Prv]ect Directomte llim1. Division of Date": February 10,1980.
margtn ot safety, c 8'#'
M tion W.Ubarklo, De licensee evaluatNd the gir'opose'd
/ects. /ce uc/ rReac Regulation.
. Assistant. Executive Directorfor Project changes a alast the standards in 10 CFR ev/ene, 50.92 and as determined that,the
' h, 2
[FR Doc.80-3785 Filed 2-16-89; 8:45 em]
(FR Doc. 89-3792 Filed 2-16-80: 8;45 am) amendment wo, ld not:.
9, g l
,u
.;k, h
,gooog 7,, g-on.uwo coot reco o,-u The licenseg evaluatN the proposed
~
changes against the standards in 10 CFR 3
I gj Advisory Coinmittee on Fleactor 50.92 and has detennined that the y
Safeguards, Subcommittee on (Docket No. 60-318] '
amendment would not:.
Mechanical Components; Meeting Baltimore Osa and Electric Co.;
(1) Involve a significant increase in the I
g
- p The ACRS Subcommittee on Consideration of issuance of probability or consequences of an -
Mechanical Components will hold a Amendment to Facility Operating accident previously evaluated * *
- meeting on Februaly 28,1989. Room P-License and Proposed No Significant Since 1978, the licenses has 110,7920 Norfolk Avenue, Bethesda.
Hazards Consideration Determination functionally tested 413 snubbers on 0
js MD.
and Opportunity for Hearing Units 1 and 2, with only 8 test failures.
2 11 The entire meeting will be open to The U.S. N0 clear Regulatory..
This corresponds to a failure rate of public attendance.
approximately 0.7% over a period of
^
k(
The agenda for subject meeting shall Commission (the Commission)is.J.:. greater than to ears.The licensee is be as follows:-
consideringissuance of an amendment requesting, in C ange l,'a' surveillance '
f 7besday, February 28,1989-8:30 a.m.
f9, t tY alt are Ga a'n fnub$er s
cti I te eq Untilthe Conclusion ofBus/ ness Electric Company (the licensee), for-4JA1.c.This extension is needed g[
The Subcommittee will continue its' operation of the Calvert Cliffs Nuclear
. primarily for the snubbers required to be i
discussion on the NRC's proposed Power Plant, Unit No. 2, located in operable during cold shutdown and y
generic letter on MOVs.
Calvert County, Maryland, refueling operations, because the TS g
Oral statements may be presented by
. The amendment would make the allowable surveillance interval (18 y
members of the public with the following changes in accordance with months plus 25%) expires at -
concurrence of the Subcommittee the licensee's application for approximately the same date 'that Unit 2 g
p Chairman; written statements will be amendment dated October 14,1988: ~
is scheduled to be shut down for '
p accepted and made available to the
- 1. Modify Technical Specification (IS) refu' ling.
"- '~ -
e I
Committee. Recordings will be permitted Surveillance Requirement 45.8.1.c by Due~to the typse of snubbers th0**
I !
only duri those portions of the' extending the surveillance interval for meeting w1en a transcript is bein kept,snubber functional tests beyond the
$u(ad for modes 5 and 8 only..and to
' and uestions may be asked onlyky current maximum interval of 18 months ' extens$on, the prob 1
/
memkers of the Subcommittee,its plus 25% This proposed extension ty o
- 'equences of any accidents l
consultants, and Staff. Persons desiring would be for 54 days or prior to entry E" go s y evaluated would not increase into Mode 4 following the Unit 2 Cycle 9 to make oral statements should notif
)
g;ca y as a nsuh f this the ACRS staff member identified befow refueling outage, whichever comes first.dange to 6e snubr f,un,cgon. pro test y
i as far in advance as practicable so that This extension is a one-time request.
surveillance 9 interval.,
i appropriate arrangements can be made.
- 2. Correct nomenclature errors in TS 1
During the initial portion of the 3/4JA " Snubbers.*
Changes 2 and 3 are strictly I
meeting, the Subcommittee, along with
- 3. Delete an obsolete note in13 43.8.1 administrative in nature in tha't they (1) c rrect several nomenclature errors in any of its consultants who may be which states that "The steam generator present, may exchange preliminary snubbers 2-63-11 through 2-63-28 need TS 3/43.8 (TS 45.8.1.b and 41.8.1.d were referred to as TS 45.8.b and 45.8.d
~
views regarding matters to be not be functionally tested until the considered during the balance of the refueling outage following june 30, -
in several places in the body of the 'IS) and (2) delete an obsolete note to *IS 3/
l i
meeting.
1985."
{
The Subconuntttee will then hear Before issuance of the proposed 47 8 Which permitted the functional L
presentations by and hold discussions license amendment, the Commission testing of several steam generator '
l i
with representatives of the NRC Staff, willhave made findings required by the snubbers to be deferred until the i
its consultants, and other interested Atomic Energy Act of1954, as amended refueling outage following june 30,1985.
Consequently, Changes 2 and 3 do not persons regarding this review.
(the Act) and the Commission's Further information regarding topics regulations, involve any increase in the probability to be discussed, whether the meeting The Commission has made a proposed or consequences of any previously i
has been cancelled or rescheduled, the determination that the amendment evaluated accident.
Chairman's ruling on requests for the requested involves no significant (ii) Create the possibility of a new or opportunity to present oral statements hazards considerations. Under the
.different type of accident from any and the time allotted therefor can be Commission's regulations in 10 CFR accident previously evaluated * *
- obtained by a prepaid telephone call to 50.92, this means that operation of.the Since these proposed changes do not the cognizant ACRS staff member, Mr.
facility in accordance with the proposed alter any plant operations, other than Elpidio Igne (telephone 301/492-8192) amendment would not (1) involve a the snubber functional test surveillance between 7:30 a.m. and 4:15 p.m. Persons significant increase in the probability of interval, maintenance requirements, or planning to attend this meeting are a new or different kind of accident from system design or functions, no wged to contact the above named any accident previously evaluated; or (2) possibility of creating a new or different individual one or two days before the create the possibility of a new or type of accident would result from the scheduled meeting to be advised of any different kind of accident from any proposed changes.
L________-_-__
ATTACHMENT B-w.
a' IGNE: AGENDA FEB
- TENTATIVE SCHEDULE 4.
1:1 ACRS SUBCOMMITTEE MEETING ON MECHANICAL COMPONENTS "E
=
74 -
FEBRUARY 28, 1989 3
BETHESDA, MARYLAND.
8:30 a.m.
. Chairman's Opening Statement - C. Michelson 2',3f-to'.to Tr45 - h 4S a.m.
Blowdown Test:. Expert Panel Meeting Summary, G. Weidenhammer, RES j ydo. (0'. 3b"
--9+45 - 10:00 a.m.
BREAK
'to. y - 1g'd 0 W vaiOce25.'-@cM kiV W t
-10:00 - 11:00 a.m.
Generic Letter on Additional p t/g-yg
~ t o ;d-o. _ s t '. go Testing and Surveillance for Safety-Related Motor-operated Valves - 0. Rothberg, RES
\\\\'A O - \\\\ 5
( 5 % VtA ss w & M UJs A 42+00 tiO0ii ADJOURNMENT
\\ *> 5 Note:
NUMARC has declined to make a presentation.
Instead, they will be in the audience and answer questions from the subcommittee, if any.
O
____.-_____m_i_-___._--
ATTACHMENT C i
LIST OF HAND 0UTS
=1l
[
^
f 1.
GATE VALVE ISOLATION DURING HIGH ENERGY BWR LINE BREAKS - Dr. G. H. Weidenhamer, USNRC Technical Monitor l
2.
MEETING WITH INDUSTRY-Owen Rothberg m-__
_____