ML20039C119
| ML20039C119 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 12/16/1981 |
| From: | William Jones OMAHA PUBLIC POWER DISTRICT |
| To: | Clark R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8112280427 | |
| Download: ML20039C119 (46) | |
Text
~.
~
Omaha Public Power District 1623 HARNEY 8 OM AH A, NEBRASMA EstC2 e TELEPHO N E 536 4000 AREA CODE 402 December 16, 1981 Mr. Robert A. Clark, Chief LLTyh,
U. S. Nuclear Regulatory Commission c4 o
Office of Nuclear Reactor Regulation Division of Licensing d
fg,
y,.,
U C
Operating Reactors Branch No. 3 g8 f-0 Washington, D.C.
20555 g
eg E
g$.g r
U,r.
dj
Reference:
Docket No. 50-285 g::
m u
Dear Mr. Clark:
h
%~
~
As requested by Mr. C. Trammell of your staff, Mr. John (Collettif EG&G recently visited Omaha Public Power District's corporate offices to review Event V valve concerns.
It is the District's understanding that Mr. Collett has been contracted by the Commission to conduct a study of problems experienced by utilities in testing of Event V valves.
During this visit, Mr. Collett left a list of questions for which he desired additional information.
The responses to Mr. Collett's questions are attached.
Please note that a copy of this information has also been forwarded directly to Mr. Collett.
Please note that in our discussions with Mr. Collett of EG&G, he clarified his request for completion of the attached survey sheet.
He is particularly interested in Event V isolation check valves.
None of the valves in the Fort Calhoun Station can properly be referred to as
" Event V"; therefore, only those check valves which were called out in the Commission's April 20, 1981 Order for Modification of License have been considered in responding to this survey.
It ccatinues to be the District's position that the existence of motor operated isolation valves upstream of the two check valves in each injection line and the fact that these valves are maintained in the closed position throughout normal operation offers a significant difference from the Event V situation described by WASH-1400.
Sinc rely, NW W. C. Jones 00I DivijonManager y
Production Operations WCJ/KJM/TLP:jmm ff Attachment cc: Mr. John G. Collett EG&G Idaho P.O. Box 1625 Idaho Fa1 4, Idaho 83401 TAN-606 Oj2280427811216 o
ADOCK 05000285 p
LeBoeuf, Lamb, Leiby & MacRae 1333.New Hampshire Avenue, N.W.
Washington, D.C.
20036
O RESPONSES T0 INSERVICE TESTING Gr VA!VES IN NUCLEAR POWER PLANTS SURiEY SHEET Request 1 What version, year and addenda of the ASME Boiler and Pressure-Vessel Code,Section XI, is implemented for " inservice testing require-ments" for your facility?
Response
ISI program is implemented under ASME Boiler and Pressure Vessel Code,1974 Edition, with Summer 1975 addenda.
_ Request 2
~
List all " Category A" primary pressure isolation valves, Event V, in your facility for which the applicable edition and addenda of the e
2 ASME Boiler and Pressure Vessel Code,Section XI, Technical Specifi-cations, or NRC orders require periodic leak testing.
Provide valve name, manufacturer, identification number, age, type, and size.
Response
No " Category A" primary pressure isolation 7alves (Event V) exist-at the Fort Calhoun Station for which ef ISI criteria exists. As required by a Commission Order dated April ?0,1981, the District initiated a leak check program for 8 of our 12 primary. system / safety injection check valves. The remaining 4 valves have instrumentation in-place to allow continuous monitoring for excessive leakage.
The Commission's Order dated April 20, 1981 (Attachment 1) resulted Table 2.9, and 3.3, Attachment 2)pecifications (Sections 2.1.1(12),
in an addition to our Technical S ~
requiring., leak tests of 4 Low Pressure Safety Injection-(LPSI) system check valves'and 4 High Pressure Safety injection (HPSI) check valves. The HPSI check valves were manufactured by Dresser Industries (see Attachment 3), and the 4 LPSI check valves were manufactured by Mission (now TRW-Mission) (see Attachment 4).
The valves are:
Mission Type,
Size Years Since Manufactured Yea rs. Used SI-194 Butterfly 6"
11 8
SI-197 Butterfly 6"
11-
_8
- SI-200 Butterfly 6"
11 8
SI-203 Butterfly 6"
11 8
t T
s' f
a t
i-p-
,y
---.--r-*--*P'v*-'Y~'v=vV-
- '-'v m
-*T
' - * -h
-e-
='e
nU
- C-ew'-
-1=-*
- e-r--1-*
---e**-
4*
Dresser Type Size Years Since Manufactured Years Used SI-195 Puppet 2"
11 8
SI-198 Poppet 2"
11 8
SI-201 Poppet 2"
11 8
SI-204 Poppet 2"
11 8
Request 2a Of the valves listed above, provide a history of the inservice leak testing they have received.
Provide test medium, test pressure, and leak rates observed.
List those valves found to be deficient during tes ti ng.
Include the number of deficiencies observed for each valve over its service life to date.
Describe each deficiency and the cor-rective action taken.
Response
Included in Attachment 5 (ST-CV-1, ST-CV-2) is a total history of
~
our " inservice" leak testing of the 8 safety injection chect isolation valves. So far, no deficiencies have been found.
Request 2b Of the valves listed above, list-those which at some time during their inservice life to date have missed a required inservice leak test.
For each omission, describe the circumstances which caused the leak test to be omitted.
Response
Since the inclusion of.our new Technical Specification (2.1.1(12)),
none of the valves listed above (response to Request 2) have missed a required leak test.
Request 3 Provide a list and description of the various testing methods utilized to comply with ASME Section XI, as it applies to leak testing of " Category A" valves at your facility.
Include sketches of equipment used, together with test piping diagrams, and instrumentation types and locations. Also, include copies of operating procedures used for leak testing, together with examples of logs, records, or other documentation utilized to record the testing data for each valve type.
Response
Since our plant has no ASME Section XI " Category A" valves, we have no leak tests for same (one should refer to Attachment 5 for details on the leak testing of the safety injection isolation valves).
Request 4 What problems have been encountered in your facility with applicable inservice leak testing requirements and procedures?
Response
We have had no difficulty in complying with our required check valve leak tests, ST-CV-1 and 2.
Request 4a To what extent has personnel exposure to radiation presented problems in meeting inservice leak testing requirements?
Response
Our required check valve leak tests were performed in low radiation areas; approximately.05 manrem exposure was received during those tests.
Request 4b Has the availability of personnel qualified to perform inservice leak testing presented problems or caused inservice leak testing to be delayed?
Response
Because our leak tests were not ASME Section XI tests, personnel qualification was not a problem.
Request 4c Has component accessibility presented problems in performing inservice leak testing?
Response
All testing was designed so that it could be performed outside containment; thus, accessibility was not a problem.
Request 4d Has the original design of the facility, in regard to the avail-ability and location of test teps or orifices, been adequate to allow performance of inservice leak testing?
Response
As indicated in the test procedure (ST-CV-1, Page 6), one special test rig was installed.
This was in a low radiation area, with adequate accessibili ty.
L
Request 4e Have documentation requirements been restrictive to an extent you consider unnecessary? Explain.
Response
Standard surveillance procedure formats were used but presented no di fficul ty.
Request 4f Has inservice leak testing been hindered by the availability of test equipment or procedures?
Response
New procedures were prepared for the testing required by the new Technical Specifications, with no delays in testing.
Request 4q Has interpretation of ASME Section XI presented problems in es-tablishing your inservice leak testing program?
Response
As noted above, ASME XI does not apply to the required check valve tests.
Request 5 List -- as a function of valve type, servb.v, size, age, and manufacturer -- the allowable leak rate you consider practica; from the standpoint of measurement and valve repair.
Response
Our leakage criteria are based on the NRC Order and Technical Specification, Table 2.9 (Attachment 2).
Request 6 Provide examples of design reports or comparable documentation which delineates the manner in which ASME Sections III and XI code requirements for valves were met at the time of the original install-a tion.
Response
Copies of the original hydrostatic tests of SI-194,197, 200, and 203 and SI-195,198, 201, and 204 are attached (Attachment 6). Our original tests were conducted pursuant to ASME B31.70, not ASME III or XI.
t
__)
- Request 7 Provide examples of applicable portions of Plant Operating Manuals, Inservice Inspection Manuals, Technical Specifications, or comparable documentation which outline inservice leak testing of " Category A" Vdives in your facility,
Response
i See Attachment 2 (Technical Specifications) and Attachment 5 (leak rate tests) for examples of our documentation of the required check valve tests.
,,h-a
-a_.
4 s_-
a_
--h.m.
A m
O 4
h 1
h e
ATTACHMENT 1 l
t i
h i
k i
4 1
e i
t d
L a
l I
f v
M " 9 4yM e% ew9*Weg wgggggr >weg e,-4-wo--
g y m*hwe_
_m way w w,--www-w w
-w w w w rn,.=
w e %w aw wm%w m
-.ww--w
- e -wwww
-e m
m w-w'wr
9/;4/01 - cc.r., mwe
- a
- v'**
- w*,
' '- w e
---s
- a--
- -*--****-***=*,-ww eeus, suu s, FCFile (2)
- [p ar UNITED STATES
!E
.r, (fb-NUCLEAR REGULATORY COMMISSION
'$hd/hy,E WASHINGTON, D. C. 20555 s 4%f a
'%..... /
April 20, 1981 Docket No. 50-285 Mr. W. C. Jones Division Manager, Production Operations Omaha Public Power District 1623 Harney Street Omaha, Nebraska 68102
Dear Mr. Jones:
SUBJECT:
ORDER FOR MODIFICATION OF LICENSE CONCERNING PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVES This letter transmits an Order for Modification of License which revises the Technical Specifications for Facility Operating License No. DPR-40 for the Fort Calhoun Station, Unit No.1 Nuclear Plant. The change is a result of the infor: nation you provided in response to our 10 CFR 50.54(f) letter of February 23, 1980, regarding primary coolant system pressure isolation valves.
Based upon our review of your response, as wel
=c ether pre * "Cy-4 ted infonnation, we have concluded that a
. ASH-1400 Event V valve co ratiojterhts at your facility and that corrective action as defined in the attached Order is necessary.
Attached to the Order for Modification of License is the Technical Evaluation Report (TER) which supports the Order; and the plant Technical Specifications which will ensure public health and safety over the operating life of your facility. We are aware that there may be edi-torial corrections to the attached TER.
Please note that the Technical Specifications correctly delineate the requirements for your facility.
_11LLdition to Evont v._vahe_Sonfiayr_ali_ons, we are continuing our d
e_fforts-to_Ieyiew other_c.onfigurations located at hi_ghjressure/ low i
pressure system bowidaries for their potential risk contBbution to an intersystem LOCA. Therefore, f_urth_er activity regarding the broader topic of intersystem LOCA's m p e expected in the future.
e
.~.
1 i ;
A copy of the enclosed Order is being filed with the Office of.the Federal Register for publication.
Sincerely, i
$ 'E.
.)
~ ; /
Robert A. Clark, Chief i
Operating Reactors Branch #3 Division of Licensing
Enclosure:
Order for Modification of License i
a i
cc w/ enclosure:
See next page i
i 4
+
)
f J
I T
T d'
d r
-y, we,--
---,r.
<--m,...,,,.-.
..w--
..-wn-,
....w-7
-v
,----v-v..-.
.. _. =......-
b.
s ATTACHMENT ?
4 I
J I
i 1
1 I
1 7
4 1
1 -
Y f
I i
t J
1 l.
s s
4 v
4 w-.----a-xn
,--n-,-7-..-.
.,,n.
.av,-.~.r,-nnn--,nn,-+
,.,.,-~u n-..-,
..--,--n.-.----.
~
)
LIMITING CONDITIONS FOR OPERATION 2.0 2.1 Reactor Coolant Svstem (Continued) 2.1.1 Ocerable Components (Continued)
(a) A pressurizer steam space of 60% by volume or greater exists, or (b)
The stea= ganerator secondary side temperature is less than 50 F above that of the reactor coolant system cold leg.
(12) Reactor Coolant System Pressure Isolation Valves -
(a) The integrity of all pressure isolation valves lisced in Table 2-9 shall be demonstrated, except as specified in (b). Valve leakage shall not exceed the a=ounts indicated.
(b)
In the event that the integrity of any pressure isolation valve specified in Table 2-9 cannot be demonstrated, reactor operation may continue, provided that at least two valves in each high pressure line having a non-functional valve are in and remain in, the mode corresponding to the isolated condition.*
(c)
If Specifications (a) and (b) above cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Basis The plant is designed to operate with both reactor coolant loops and associated reactor coolant pumps in operation and maintain DNER above 1.30 during all normal cperations and anticipated transients.
In the hot shutdown mode, a single reactor coolant loop provides sufficient heat removal capability for removing decay heat; however, single failure considerations require that two loops be operable.
In the cold shutdown = ode, a single reactor coolant loop or shutdown cooling loop provides sufficient hcct rencval capability for removing decay heat, but single failure considerations require that at 1 cast two loops be operable.
Thus, if the reactor coolant loops are not operabic, this specification requires two shutdown cooling pumps to be operable.
The requirement that at least one shutdown cooling loop be in operation during refueling ensures that:
(1) sufficient cooling capacity is avail-able to remove decay heat and maintain the water in the reactor pressure vessel below 210 F as required during the refueling mode, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.
~
I Manual valves shall be locked in the closed position; motor operated valves shall be placed in the closed position and power supplies deenergized.
Amend =ent No. 56, Order dated 4/20/81 2-2b r-' D+R o f L l '7l ~'
y 2.0 LTMITING CONDITIONS FOR OPERATIOM' f,
2.1 Reactor Coolant System (Continued) 2.1.1 Operable Co conents (Continued)
The requirement to have two shutdown cooling pu=ps operable when there is less than 15 feet of water above the core ensures that a single failure of the operating shutdown cooling loop will not result in a co=plete loss of decay heat re= oval capability. With the reactor vessel head re=oved-and 15 feet of water above the core, a large heat sink is available for core cooling; thus, in the event of a failure of the operating shutdown cooling loop, adequate ti=e is provided to initiate e=ergency procedures to cool the core.
When reactor coolant boron concentration is being changed, the process must be unifor= throughout the reactor coolant system volume to prevent stratification of reactor coolant at lower boron concentration which could result in a reactivity insertion.
Sufficient mixing of the reactor coolant is assured if one low pressure safety injection pu=p or one reactor coolant pu=p is in operation. The low pressure safety injection pu=p will circulate the reactor coolant syste= volu=e in less than 35 minutes when operated at rated capacity.
The pressurizer-volu=e is.
relatively inactive; therefore, it will tend to have a boron concentration higher than the rest of the reactor coolant syste= during a dilution operation. Ad=inistrative procedures will provide for use of pressurizer spraystomaintain.anominalspreadbetweentheborenconcentrationintgg) pressurizer and the reactor coolant syste= during the addition of boron.
Both steam generators are required to be filled above the low steam gener-ator water '.evel trip set point whenever the temperature of the reactor coolant is greater than the design temperature of the shutdown cooling syste= to assure a redundant heat removal syste= for the reactor.
The design cyclic transients for the reactor system are given in FSAR Section 4.2.2.
In addition, the stca= generators are designed for addi-tional conditions listed in FS.'.R Section 4.3.4 Flooded and pressurized conditions on the steam side assure mini =u=
tube sheet temperature differential during luck testing. The mini =u= te perature for pressuri:-
ing the steam generator steam side is 70 F.
Formation of a 60% steam space ensures that the resulting pressure increase would not result in cn overprcccurization, should a reactor coolant purp I
be started when the steam generator secondary side te=perature is greater than that of the RCS cold leg.
For the case in which no pressurizer steam space exists, limitation of the stea= generator secondary side /RCS cold leg AT to 50 F ensures that-a single low set point PORV would prevent an overpressurization due to actuation of a reactor coolant pump.
4 The exception to Specification 2.1.l(4) requiring all containment penetra-tions providing direct access from the containment-to the outside atmos-phere be closed within-4' hours requires that the equipment hatch be closed and held in place by a minimum of four bolts.
i
^
References (1)
FSAR Section 4.3.7 A=endment No. 7h, Order dated 2c A /O A 101
.. ~
4 TABLE 2-9 REACTOR COOLANT SYSTEM PRESSURE ISOLATION' VAL'/ES Maximum (a)(b)
Svstem-Valve No.
Allowable Leakace
~
High-Pressure Safety Injection Loop 1A, Cold leg SI-216 15 gpm SI-201 15 sp=.
Loop 1B, cold les SI-220.
1 5 gpm SI-204 1 5 spm Loop 2A, cold leg SI-208 1 5 spm SI-195 1 5 gpm Loop 2B, cold leg SI-212 1 5 gpm SI-198 1 5 gpm F
Low-Pressure Safety Injection Loop 1A, cold leg SI-200 1 5 spm Loop 1B, cold leg SI-203
-- 5 gpm Loop 2A, cold leg SI-194 1 5 spm Loop 2B, cold leg
-SI-197 1 5 spm i
Footnotes:
(a) 1.
Leakage rates less than or equal tg,)S pm aie considered acceptable.
N. Leakage rates greater than 1.0 gpm'but less than or equal to 5.0 gpm.
e-2 are considered acceptable if ne latest measui ed rate has not exceeded the rate determi by the previous t est by an amount that the margin'between seasured leakage rnte and the maximum V
reduces permissible rate of 5.0 gpm by 50% or~ greater less t..a or equal to 5.0 gpm i
3.
Leat. age rates greater than 1.0 gpa but are considered unacceptable'if the latest meayured rate exceeded the l
rate determined by the previous test by an am,.unt that reduces 'the cargin between measured leakage rate and the r.aximum permissibic rate
- 3.0 spt by 500 er creater.
o; I
4.
Leakage rates greater than 5.0 gpa are consid red unacceptable.
(b) Minimum test differential pressure shall not be loss.than150psid('
i Order dated 4/20/81 2-2d
?
4 3.0 SURVEILLANCE REQUIREMENTS 3.3 Reactor Coolant Svstem, Steam-Generator Tubes, and Other Co=conents Subieet to ASME XI Boiler & Pressure Vessel Code Inspection and Testing Surveillance (Continued)
Tube Insnection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.
(ii)
The steam generator shall be determined OPERABLE
..af tet completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 3-8.
e.
Reoorting Recuirements (i)
Following each in-service inspection of steam generator tubes, the'nu=ber-of tubes plugged in each steam generator-shall be reported to the Co==ission within 30 days.
(ii)
The co=plete results of the steam generator tube inservice inspection shall be reported to the Co==ission within six (6) months following com-pletion of the inspection.
This report shall include:
1.
Number and extent of tubes inspected.
2.
Location and percent of wall thickness pene-tration for each i= perfection.
3.
Identification of tubcs plugged.
(iii) Results of steam generator tube inspections which fall into Category C-3 and require pro =pt notifica-tion of the Commission shall be reported pursuant to Section 5.9.2 of the Technical Specifications prior to resu=ption of plant operation.
The written follow-up of this report shall provide a description of inves-tigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
(3)
Surveillance of Reactor Coolant System Pressure Isolation Valves a.
Periodic Icakage testing
- on each valve listed in Table 2-9 shall be accomplished prior 'to entering the power operation To satisfy ALARA requirements, leakage may be measured indirectly (as from-the perfor=ance of pressure indicators) if accomplished in accordance with approved procedures and supported by computations showing that the method is capable of uemonstrjting valve comp 11aace with tha leaka;e criteria.
Amendment No. f6, Order dated 3-25 4/20/A1
/3.0L SURVEILLANCE REQUIRDIENTS 3.3 Reactor Coolant Svster. Stea= Generator Tubes. and Other Components Subieet to ASMI XI Boiler & Pressure Vessel Code inspection and Testing Surveill_ance (Continued) mode every time the plant is placed in the cold shutdown condition for refueling, each time the plant is placed in a cold shutdown condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if testing has not been accomplished in the preceding 9 months, and prior to return-ing the valve to service after maintenance, repair or re-placement work is performed.
b.
Whenever the int $rrity of a pressure isolation _ valve listed in Table 2-9.cannot be demonstrated the integrity of the remaining valve in each high pressure line having a leaking valve shall be determined and recorded daily.- In addition, the position of one other valve located in the high pressure line shall be recorded daily.
'J 9
'AEendment No. f5. Order. dated 3-26 4/20/81
m 4
O e
ATTACHMENT 3 4
'I.
i i
4 4
i I
e i
r 1
1 l
l l
l t
I i
l l -
l l
f i
l I
L
..e.
~ ' ' ~
r
.l. re-
'.' M
,o.g e,.
?,.
,.f,-
[
v+
,c;
. ;,. -i v5. ;
.f '.
?'
~
r
~
~..
.7....,,,
~.y
';t -Qm.,O.*.',J., e h., '. +. NJ.a #.... 1,.:.. q,..a,. s..
J*r<Q*c * ; N. 7. *.
- -,. 4 dl..
4-n4 w*
-~ R.;
' {
. ~... E.
i,.
.. =
. ~ ~. -
a t,.
n.
\\=.
A t
,s..v.-
.f.
- ~ ~,.,.
- s...- g r s ;.~.~.,; a,. m....,
JOJe;{7,.,,p.j[n
': ~.
+
...'.-h,.s,,4'h.'}*
' ',. ',; e ( * ~
.s
..--,., rs q.
r"
-I" g[;.:
- N,.
t
'I*
. * ',~
~
a
..'l.{.-f~
~;h';
l & j h.n.(LlkNi$'.%
i
.a
..: s..~ 3
... 2. *'[' '$'.. I' ',*
t-ns.
- '.2..t *f ft- "
g
.f' r !.,
,w 1
P.4. -.
c.- r
. ' ';'. f.
i
-,..y~
M 1 -,,. m.,]f. ;~&,:.-
m f.
s s..%
.A m
.\\ '
y Z
.'s*a F..' "
6 i
- =
. v.
%p r
.a 8 a
\\ \\
\\
..s, 6
n 3
l ;s
'" y.
.m 4-(' N
- N S, I
g c3 ua C $d
.O,
\\
j M
se, c.
~%
t o
N-N) y-
-w
- a...
..b-
.u-
.L.'...
O_ Cq f,
g
\\~
9 **
m m'
~ ~
m_
4,Qy "i
'l. *...s"(-. N','r t-4, my
-t m m, s"y ~
C,-L:]
i M
=
7
(
g. '.g
's.
1 1
/
, r i,.
.y, g
M M b
y a
,, u,.i
.3.
_j.
u, y,
s W
M3 CF3 J'8 g*
-?
.,J. ; -
O C3 C3 4
c) as as f
- f. 2
- .,- '.a*.**..
" -- =--*
.y s
4.3.
L g
i e
c3 c.,3 i
g
,j
.,2
- ~
l r,,'s
.p
,4..
= f. "
g.,,,5
a p
I
'b
_f a
e em.
9 s
e o o
e
- 3 1,.
. t gg
. un M
==C 2M M
auC
- C3
).
a i
I e
kf 8
i 9
-W
- q M k G
e4 c3 c3 I
w
==r W
W V
f 8
r~4 r~s r
e l
,e vs
-.. m s
M i
I' f
1 4
i
'l t
, r)
M G3 O
,i g o O
e
- J d
P I,
7 o
t e*
O e..
l S
q -
CJ ' *.
=
A es$
9 4
..e g
g
.' 7
' s' a
c x.
1
, ~ -,.
,... 'r.
i I
~
l 6.
1,.
t I;
i i
.i I :'
.-'!f
' PETER KIEWIT S0 tis C0tlTRACT t10. ItC !
DRESSER ORDER tl0. 40-85200-0 l
l l
l b
I L
i i
- h j
- d:'y.
t
' )).
6..
T.,.
l t
t.
I f Eh A}f-16 '%- TC L/
^
=.
- - ~ -.. "
'.)&
- 5. - -- -
.l 3
. r LIST OF MATERIAL 2
NO PART f4AT ERI A't.
j SPL 4
.s::.; M :.c......]'
2 CAP Si AINI ESS Sitit l,,i,.
i,o
.,,,,,,,,,,,,i,.
- r -.,.,.
_m 5..... ?4 _M 4
l'
. WM.yg.na & ~~.:*""".-**"*' :r ** 7 3
"
- Nr * *-
-..p
, g n s.
~. $ c+.,...
.' h gs
~ ~. g : ~ r-;.:g er. q s.* ~~.
. '-=. ' ' ' '
.s b,'~
'e t*
['
- g-
,., d '.
Wh..,'.if..'Us'[ ?.?. ?. Sbl.%.. q,5 RQi ?, 9."$'*% $.,... :.? l.
-s.
' '+':*
~
'.*d.-
le.".'.,')g*_., l,, (. y :.
!'A
- g^ ::. _.
'
- I."* '. - [,: ~
- '.r.'
l T.$*' Sh-? >,,_ i.f,4 *.
~
,'?k; ~
? 's a-i,
, s q
,J
'3, i c < r.1
- 7...
l..
-[*-
- G i'
,.s,
- i n, * *$ ',,,
T-
~
l
.M N t,,
l*-l'
- .t.
s y
9. g
[,.-X ^[ y
.i
- n'-
i
.Q, Q2
- ;n
~
g O_.
k4
..e..
uw, A.
f
.. ~.
O x o,
=c3 i
Q-a
' _r
+r-gs b., a sr N
n%
~
A%
f-M '"- '
Q q'
l-L
..~
o=
..e I
l I ~~-
. 9x t
.n
~
^
k e[h l
- .d
- _ f
,. l'..'
5
- J..
3 e.,.
~
I l
.O
-e,.-A.
~
-]
s i
- . =~
.L
. 'ai g
l
.~*s'
.c e,
l 1,
+1-
...~.
- ., fo #
I s
s
@9 d.
e
. Sd.
., =
4 9
O Q
- e w 2 c FDa
.,J -
ag I
O C' 0 <;-
2,4 0
cr2 m
>= g.t g '6
-g ac kr CT)
- i
- a. ym3 ;
Jov A
Q 7x J-c.2 y-g C
- 4 w; h' C D.
.T' w a 3
- ~
y N
c-m3 Z S e F
.c; e o ra.'
- w.
cw
- s***
A jy ~2
.), ],)
t Y
..N w
E 'J
-3 K6 Z
'2 g3 o
O l~
>==
s-vs Q
M K
O o
a== G had
=
0 5
in fi v5<W r%/'
gg u _..; _ ; _ _ __ _
e
.a J _
LIST OF MATERIAL I
2 NO PART NI ATERI At'.
SPEC I
BODY l
\\'N 4
SIAINtI,SS SitEt oT SEAL WEL
\\
y 2
CAP STAINLESS Siff t
['
i
/
's 3
3 VALVE STAIN (ESS STfft u.
f\\-['\\,-
l 4 [ BODY EXT.
SiAiHtESSSiEE!
k t,N l
l
,o
\\
j 7
7[
gg.
_/
N0if
- 1. SEATING SURFACE HARDFACED wrrH STELLtTI h
i N0it 2. HARDf ACING & ADI ACENT StJRf ACE' 10 DE iili h
M 1
INSPECTED PER ENC.lNSTR. MS.I I Wi fH ACO 5
s s
5 QS 19.
j L g -- 4 g SOCKET WELD ENDS TO A S A 816.11
^
/
NOTE 3. ll 01110 PENEIRANT INSPECTED PER ENG IN!!-
/
E-
=E i
y, p
l.-
G
=
t V AlVES TO DE IN ACCOR0 ANCE WiiH ENG!!NSTR. OSit-
~
TABLE OF DIMENSIONS SIZE
.A.'
B' C
D E
F G
I 500* 1250*F SE alt '
wr te3_
CHECK VALVE TYPE
.. I@ 3.
[g- }
2i 5-9 f
.855
~ -
d Il 3
-fi i
2i 5
9 j
toss I
L330.21 3
1I I
I 4
m y
2 7 5
9
@amtf m,,,,,,,,,_,_,,,,,,,
.2(( 44 16-.i
.4f 8f 25
.i.~.
If i.675 N
If 34 4A l} f 4f 8f 25
- i. sis
" ^ "
5"' - ~
LA CHECKED
-4 4
3$ 4d.l}
~{: '4$
8 25 cerrrmeo: /).It!
~
ffg{D 6'
2
-2.406 i
4.
u t.
x..r.n.
~
, :.c.gc..., -.....
. : - ' ' ' " ' - ; ~ " n. a.....~.
n,.v
+
8 4
e O
ATTACHMENT 4 h
4 0
,a a
n
\\
m e....g
, \\g
\\g' wows e*
.d_
T~
l 2
,g,,,,,,__,,G OPPD r 8 @
Edko!
J
-r s.
r.,
/ <bo*
p.
- \\
I r,..
.p.
, L,..
s.
ww 9
'g * \\
, (.-
-it i t.
h.q j
a
/j
-/e 6
_m 3
s >
(
.g
-.... p
_,e W%g.
y~g....
s s
y/
=
N \\_
k h
i I
C
~~~\\
\\
t o.
i 1
x-g \\i h5
- /C
/
i f 9 4p,r. a.,V j'
~
^
ls
.r.
o x
1
~
\\
\\
W6
/
/
/
l-i N
l i
pi-
.7
.e 1;
I' a
.{
r at.. I W
o
_______--,-,.r--
0 Op p o-h $
S S
S' S ' S
'S 76. p i, N
\\
N -
n u
mo, O
x.
g
_ =
x\\
s
%s x
'\\ x,
=
\\
I k ;.h.
C 2
,r; u
{Q _
. i; i.;.d s_
4
~
n
'l l.
I t
\\ N; i
G 9
O 1 ll em o
e e
O 2-2 o
?.a--
L u
. b nTo g
"A
's
..'As
's N.,
't
- s. xx 5
c s,
g s
1
\\
\\.
I v
\\,
"g
\\
N
.i
.s yx 'N; %-
E -y Nh'\\
\\
N.
' s N-9
)
g x
o
~
kb N
i.
y
~y N
g P
l@
t
.6 L
JJ e
~ ~
v p
7//f
/
s
/
/
l l
l'
/ /
/ //
/
!Y.i=f i
. r. ;
go.
Srcrion A A tytYg PART NAM [
41RTfR/RL.
N REQUIRED
/
/
Booy ASTM A3SI Ganor CF-BM U'O'*
2 2
Pipit ASTAf A35/ Gnnot CF-8M J O/ Coz
~
4.01 Ain 3
/
Hinar Pin 316 SrniNitss Srett
- 4_o33, 4
/
SPRING lNCONEL ggc 5
i SrOP fin 3l6 STAtWl[3S Sr((L 9
3 0) gh 6
2 Pinri LUG Bran.
3/6 SrntntrSS 37tti 701 $, )
T i
Booy Luc Bcan.
3/6 SrniwicSS Srtti Rooi 8
4 pin Rcin/N[Rs ~
3/6 Srnivicss Srcri fos S
4 Boirs
( ASTAf A/93 68 GRnor 87, % ~ /O'3
'~f 9' 703 a L 10
/
Coven 316 Sinivitss Src L'~~"
IO*
I It i
Rtininca RiNo 316 Srni.vitss SitEL
- O 8 02 12 1
SPnCER AING 316 Ora;NLESS Sr!EL g,g; 13 l
Stat RING Sofr /hCN Suven Pinito
(
14 1
Scni Pzua 316 3rnivirSS SrstL g yazygs' O
/5
/
Vant Scnz Ale rat To 41c rat - 3/6'& S.
fiw
(...-
~~
L.
.,m.-
4
1' g&tW W
o.
sg a
I 9.,
H5
.Q
. DRDQ'
-,jn a
i
,G ngs gQ '.:
L E
L i
C n ~~J ".
A t
c.
- S I{
y q
O S
A MN O
T
(
EO A%
6 HI' C
S g
1 CS 7,,
l,\\
r,(.
N$,
2-E g
(.
" Q N
OE/
{
M /; G e
,~.
I U
g;
,c.,~_
D D f,,,, F.M.
U D/
I 0
S OTol s:
7 O
3 u~
5, p..
,:w, M~
N f
p b
INN c"
g c
/
ta 7 g, o
E 2
E N g,, N e. H L
U 0/gc I-O h' S, 9 LU T t.
J r :
(
- I7o, O..
z_
- f. "
0 T
O t:q,.
Aj A
N C.
- a s -
21 ld, S
I 6
U C
OR 0 l g.C I0 A g.D S 2 "C
/
E 1
r fW f
~C 2
c 5 T
_nC M o
S, 2 I
/S s
p e
i;
/ 2 N i
., r I
'l I m.
o s
/ t DiA 2-p C
r k
I T
s s
S
/, /
n na
,c o
eB 8 v S7w8 0
t 5oE 2Vn f
S, n,
/1PN f
As I
4
,1 r
c 7
isiMr w ot ut 0 o F o H.(t t
tL t
u eJe o s 2i t
e U
K P /s U i
o
- c I
y 3
l i
,I a
Sp W Nl. '-
L g
a3 nCn
.s r,
a
=
3 3
o ce o u 3
W'A i
i C Tr g.
n a
rtAnRn gy P 1
e O fo S Tn a r
/
g
- r 8s
"..k~
,p s
(y~ To d
. 3 n i
_g ni 5.C M2. [,
.1 t
gh
,, g O
W 0,
" A D S s,_.
o n
, tee eLxN PC 2
-3 r sw Co.
r e
0 2-N.
n
, y, t
rc r 5I 5~.w. ::.,..*,'.
E S,
,, anrs
/
6:
vyi g,, SPC "2 /
9
.2
. s C %"."j,
/
.\\ s.
s-L'. rI
.,. m u U'c '.,
I t
c A
PS M t
.."a J*
r '~ ia. :: }".,g._
i E
e d
8 T.
s ?' m " '
a A
t
~
T
/
t A
~
m.
4 1
t s
oN s
e E
f._
r i
lp e
0Sh R
4 s S, 8 o u o __ y
)8
\\/
r4_,m
/ c
~
i 8
4 c6 6 i 5
o 8o9 c e m. A e
s L w 1C1
'j v t
A
/
v 1
A-o o
1 HW o/
s x [1e R */ (N r
n..
t a
c 5
e i er a
e gTu ic.p w
Se 4
c t
z
- l
,'.l-f n
t 6
i f S ' o >. S
!I V r, A w :i itt1 n!
j i
~
c t.
v i
a S.mrP B
o 1
L C g c.
n r
e X
c t
$ A s
n S. R n n a
e,.
A o cDe w
i VG vi.x i
o 3,
t x
n 21 Ff st.
vr.c
. Tz r
x D
i O i
t r.
OsR4nc S G t
ei oR
/
, p i o e. N v
o P N.
D r.
t t
e t 7f ri air t
v a
M 0
M e t-s BVrA3 n e
- t. G r
s o
2 4 s-i j
?
t A
o /x a 2 6.f i
S o
i
- C 1 r n
s n S
4 14 c
Ano4
~
r i
t1 I e 7 3' 1.S fl
'f 8
u".rOa t
t o 1 s sP a
cc r fo v
o h 3 S
s u r
/
i r
5X r A'o C a s0
/./jj /,['
v a
a
.o
$ f. 6 n
/sn t
D% V%* s i s,ako cp8V L
af iv/
A
,V a nnsiN
, ar e w R b, n o 2: W c:.
.rt o w
~n rCcn a
t e s n rr n
]v /'[J 1
n x 2, o nA i
e j
-Qnir
/
n 's OeD 1lI a
/
n
/, 2 a i,
s a r C nsc
. cm nos r
'n % u S O q7 Pe s>S o
- = *n r
t
';T-
.m... (Q\\...a
- 2...: :w Q
-1 ) 1
,r}
\\
\\
.j t
vs i -r-~!.s
~
4 t
/ ]&
w s
- $6 l
\\sk 4
,,1 sw 3
.~
s k-
. td.
f l
l D
{-
l,.'.
y i
I Q. L.
Q-1-
i
{7
- l D'
Q I
Ug D
1
,/
O i h,
.'~_E' t,.>
/l
. N q
X
( V.*
- \\
4%y y
~
~
. n o,..
9
- t q-N %
'. :h b '\\
A Q' s
b
-. %) h.
..b.
- r..,.
tt \\
y
/3i
. '4 Q '
~ 'i[ } Q g ~[%
--l } $ 9 9 R Il 0 lN Nu
~ m % -1.%' 3 ms l
)l-
~1 R
- 1.'::..:_.
w,;
. y-.
.%t
. K p
. 6,. g~
\\g,..,.
X j,i.If'
~.WI f.c -
,/
1
-}.
to w
7*;-
7.
... ~...
~, \\ N,.
,f y
i
(' \\'
.... y -.
.g%
g
[
N ek-
'.. N: % %...
/
4 s
/
'... O -
- m s'
gn
- t.,;sg :c
.k ; (
~
, c nk}
A
(.
L{ d) t
- Q" Q.
5' 3
b 5
q'- f.
'i' N [..
e g
4.
~
,'*-i q,.,
c si N..sW C""
q&)..
N
- N
^
o'
- a s.to q-t G,f....
p (o
~
-+
-s q:we
.w m
i-
... v
.t
, ;f.
- k y..-.
l
,q 3
~..
.t f
O..'R r
. -;U tQ
,.s 3
., : J
.I ;.:W -.. t..{
..k
. k..gg g.
WM (
g1 q %y 9
' h W.:. '
.' V. %.o : -
& ^. %
~% a x y :. sn 5 s. Q 4 tty n
u q
'Y ' g.
-.. :.h kQ.
4
.$q(.k'
- ..k. j. g { %.~.
N Q Y
- a
- Qm p*' ' a. g2
- ~ - '8
/.N.h A T
~
. ' ',, -. l" Lt2' yG '
. ;.Q
- f.
Y
-?..f,._,
- 3
' t3 f j
'kI f
h-
.}: I. h Y
.L
. t Q &
NM.
4'
~
~
-?.:.*.*Q',t
. Q %}
. x : 9 q,. %
R>
,s
-Q M
.. '. :..c,:.t -W
.3.
t.
~
s-
. p
..r..%..
. -h.
hJ
_4 R Q. c)
/*
..... n
,' }...
o.
. 9 ',3 h 4( s a
i R..-
ysw
,' }%
3
,'. D
,'Q ~
. ka y.Q y C g
..f
.j
- 4.f, N M MX
'i
= :... :.<: ;.,: - >.
m o u.
- .."v.-
.5:..
2 Q
....y Q
..,...., ~ n ;..ug. ; 3.- e. -4 y
N.
a
..: w :.
~ :-
.v-w.
~.:.
-Q
......,fu.. ;.. -
+;-
o
O 1
l e
O w,
C.y * *B wi en %E, o
>- 4 @ $ -
C I*oO C*"J C5$ch N til r ' c:
s..
o.
\\
\\
O e %
e w $33D r.; a a, 2 '
\\
\\
~
6 i: Eii i
\\
4 E=
\\
!1 l
.c s
\\
\\
,\\
l e
' \\
.\\. ' \\ d b
^
ji.
N. \\l
(
9
~
['
y q.
\\h r
.,pa f
f cq s
~
/
~
/
+
WWVANNW1 m
s F
//,
9' i
~
,..'/~
~
, r e
- f
/ *~
l j'
g y
w 9
F*
l k
3 4
f
/)
//
gg) f 1
_l 1ll I
,f'
~
l'
\\\\
~.
g-3
}' }\\ \\ \\ /
,f N
\\.
l N'g
' h _\\
4
,f l
- f N.
E
, s?
n.es i
V.
i t
l f
k i
m%
g l
'? K
.,A-i
' ~
wusu"nw-- -- -
/ o c. z, y
)
Secr/0N A-[
~
I 0
valve VA L.VE A=
B C
D e.; U n. I.~~. T ~~
6$ -
r'
a
.S I Z E
.$ ERIES
' R t'.
FEB Z6 B70 6'
/500' 8,7 /6y
//
f 4
.._ _....... '_. j q, 't 'L._.:12 "
1500
/5}- 23l 20 (//,(
wp i
.y 4-p g 6" CMbf n
(,
!T' CA6dF;
[,
D s,...- - '.
~
150 C/%538
,,e -
- .u-8
'g
, :." :/9,n.'
/=' ren'Riswir 4 Sons Co. i..: ?~.' ll FT. Chk-H 9yy 3y$
{ l.
s
~
UMT1 Mb-33 t/oa 4/67
',*.a.,a..v $
~
~
v,:
- s.., >..
.pn; ; g 7- _ g n -, _.
- 0MAHN ?/./BUC fbnfER 0/ STRICT.; *. {
7"' T A = ;U; V. h IS
- c., -
e
,.. r.
-1 F
e 13 c= r.r
^
3 1970
_ ORr CAL.Houw, NEBRASMA y '.,,..
~
' ' ;him Sration Unir j.
'l
.. _. y, s
- ~
'(:.,l:.I'.
'"; ' :., 'J'
_.'l
...s.
t
' y..,, '
_ } ',.'-
1
- , L -
-I..:.,
e 4
e,;
'OT74E3'r UO - O/@<
f 3.' ' '. 7.
s.
MATERI AL ' '. ~ ~ ' '
6 4,
lNS TA LJ.A TION Disensions
~"
HEAT TBLAn'_. '.
^ \\.
USE Y'/0 N o m casioNe seJ m eurs RL'V DATE BY HD1 ARES
I :
? ART *$',l157' ANO setTorcrirons unn.tes EAM
.A, & d 69 CEO G
~
!i orn r r wist tnwrnsieNro cg,c,,
,,7,oy,o i
g,,,, y tJ ut_yt v ots n ANc;r e B
/f 13 s9 crn H
J, A 7~
g/)-
pH.E No.
<a,cutanroiarimct.
b.9-x cco 1):
.,. [, S
'. MISSION 4 MFG. CO.
/625.9 c'
,,.w.
. un
- m,..uu co.m o A
..c r.
l mmu-u-l 1 11 g.u t,1.,1 Ltr e' M r t n.,u,o m.,, os sm,,
o,.,,,
c1
., r'.
00Z
{
P/N n'l v b 7 DE VE R 7* ic A s r c3 n ROI Hom z o u r nt.
Fl o w.
)
t v.
4 i.
- - EN PART NAME 9TX
. NA TER/AL
. -. - -i.: - =..,
- p.. :::.: -
c
.I 316 S.S.~ ASTM A351-CF8M
.5 i.
l
^i Booy.
x
..- -. +
'2
..}L Pt.s 7.t 2
316 S.S. ASTM A35/-CF8M ' -
-....-. ~
~.
,p META 1. To Ms+EtM16 S.S.'.
.,J *
.j 3
[.5em.}
- !4
- 5 f.7.c f%v.
l' I 3I6. STAINLESS STEEL. '
3, UBMITTC O L_
g
/
Poacunst on 5
- Pr.y._.----
Cusrouse G
s. MQ m. c.
}:
INCONEL.
_....s...,- /.
-.~
-...___._'..__ _huc Ben.wc ' ' '
1
-4 3/6 STAINt E SS ' STEEL.
s 7
_u g
? 8 P.N Rcrmnen.
4;-
l3/6 SrAint,e ss Sresi 1
=
+.-
c
,..,, s...
E)See D c. A623&- AN A.O. ZbErAN. Ass >'. dWWY500 WND ~&O Yr Sce.' Drs. A259 48 : hh,e Dmex Assv Or Wd5dC. WEw-Em MkVE -
i c
M.
.rt.
+
w 4
.c N.
> :;f.,s, /N$4} DWG..
e d
q O
m.
4 s.
,.e
4,--
ya Y
tw e
O e
ATTACHMENT 5 i
4 e
i I
i l.
e l
l l
i w
I 4
h
=
p.
,,s.--ag--
w
~
FROCEDURE l
- %'sdELI.Nu p
l
, CV7-SE'? VEF.IFICa:IC'l ST-Cv-2-i O.. 9:r F.riis1. n He.-
0 I
i
-g g,.f>g,j l Fort Calhoun Station Unit. No.1 Surveillance Test Procedure!
-2 "N/f/fl l
J SURVEILLANCE ~ TEST Section F.
Mte ST-CV-2 Due Date:
Leak Test of LPSI System Secondary Check Valves Month No.
Weo/n A.
PURPOSE 1.
The purpose of this test is to detect the quantity leakage past LPSI check valves SI-194, 197, 200, and 203.
B.
REFERENCES 1.
CE Drawing E-23866-210-130, Sheets 1 and 2.
2.
GHD&R Drawing ll405-M-12 O/Ab 3.
Surveillance Test ST-CV-l' " Leak Test of HPSI System Secondary Check Valves".
4.
Order for Modification of License Concerning Primary Coolant System Pressure Isolation Valves, NRC letter April 20, 1981, and Technical Evaluation Report, " Primary Coolant System Pressure Isolation Valves".
5.
Mission Manufactur'ing Company drawing 16259, Sheet 1A.
6.
Technical Specifications 2.3 and 2.4.
C.
SPECIAL INSTRUMENTATION /EOUIPMENT 1.
Clock or stopwatch.
2.
Container for collecting leakage (approximately 1 - 2 gal.)
D.
PREREOUISITES SIGN OFF/DATE
/f!f[
1.
The reactor is subcritical.
/
O.,,f, [
2.
RCS pressure must be at least 1500 psig.
3.
Decay heat is being removed via the steam generators.
/ f//9/Y/
ff l
Shutdown cooling is not in service.
/
/
4.
An appropriate Radiation Work Pennit is obtained:
RWP No.
'223 I d b / k //
/
HP 5.
Close SI-186.
/
f
/
/
/
RO 9-18-81 SEP 18198 REFUELING
ST-CV-2-2 E.
PRECAUTIONS 1.
Do not allow safety injection tank level to drop more than 12" during the test.
2.
If a SIAS is generated during the course of the test, LPSI warmup valve SI-186 should be closed.
O ISSllED SEP 181981
~
ST-CV-2-3 F.
TEST PROCEDURE 1.
Leak Test of LPSI Check Valves Frequency:
Each. Refueling or other Cold Shutdowns longer than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if not tested within the previous 9 months.
Responsibility:
Engineering / Operations a.
Initial Conditions SIGN OFF/DATE (1)
All four safety injection tanks are pressurized to at least 240 psig with a tank liquid < level of at least 116.2 inches (67%) and a maximum level of 129.1 inches (74%) with refueling Baron
//
coacentration:
/ /N////
/)
f (2)
SI tank discharge valves open.
(HCV-2954/
/
2974/2914/2934).
W5*r /
/
(3)
LPSI loop isolation vlaves HCV-327,.329, 331, and 333 are closed.
/
If
_/
(4)
Close valve HCV-294Q (LPSI pump SI-1A outlet).
/
/
(5)
Close Valve HCV-335 (LPSI to Shutdown Ccoling HX).
/ T (6)
Close Valves SI-167 (inlet to Shutdown CoolPg HX) and SI-169 (Shutdown Cooling HX's inlets crosstie).
</ 7
/
b.
Test Procedure 7
)
(1)
Notify Shift Supervisor at the beginning
)
f of the test. * '
(2) bserve Pressure on P_I-325; am psig.
/9//tsi
/
(3)
Open sample line between PI-325 and SL-173 per the following method:
(a) Close (or check closed) HCV-2504, A and B.
Indicate as found position:
- W pffd A
8
( /
/
b.
Close SL-191, indicate as found position:
(lo Se 04tif / 9 lMkl
I8-8I SEP 1. 81981
ST-CV-2-4 F.1 TEST PROCEDURE (Continued)
SIGN OFF/DATE b.
(3)
(Continued)
(c) Close SL-169 and 161.
Indicate as found positions:
Cloud Ou O M /9//9[F/
169 161 (d) Open SL-159.
Indicate as found position:
Clossel OMR/7ll$T/
g (e) Open SL-208 and 160.
Indicate as found positions:
E b ks on ou 04()fl./ 9(il9ff/
G08 160 (f) Open SL-170.
Indicate as found position:
Caco el Ok/l/919k)
(g) OpenSi-173.
Indicate as found position:
Clovci.
G4d/L / 9/19k/
(4)
If the pressure on PI-32,5 does not drop rapidly enough on'ce fTow through SL-173 is initiated, then open HCV-2948 (LPSI S'.1A outlet), close HCV-2947 (LPSI SI-1A inlet isolation) and Open SI-131 (SI-1A discharge
//
drain) to depressurize trie loop.M IM Sidb / (/i f!
T l
l (Sess 1 h PI-325 dugd hc A N"hI-325 ' stops *iliopping3$$5DaYilizes, l
(5) close HCV-2948 (0 pen HCV-2947); Close SI-131.
NOTE: The differential pressure between the SI tanks and Pi-325 must be greater than 150 psi to use the l
allowable SI check valve leakage limits curve. Ensure PI-2316 reads below 75 psig because relief valve g/
SL-171 lifts a at su (6)
After waiting 10 minutes for the flow to stabilize, measure flow out of SL-173, I
measure 2 or 3 times to verify stability l
+ 10% of previous reading. Record PI-325, PIC-2909, and flow rate on Data Sheet, f
00]E.i9k9tr/
Test #0.
SEP 181981 250 m4 2 3 e sec, R0 9-18-81 l
250 & -> 2M 0 x
/
2so M -9245_stc.
ST-CV-2-5 F.1 TEST PROCEDURE (Continued)
SIGN OFF/DATE (7)
Open HCV-327; after 10 minutes measure flow rate out of SL-173.
PIC-2909, and flow rate on Data Sheet, Record PI-325 Test #1.
2 % 4
- 2 M M '-
//
2 s e,w.i --, zz,5 ac n
! rM/f t (8)
Close HCV-327 open HCV-329; after 10 minutes, measu,re flow rate out of SL-173.
Record PI-325, PIC-2929, and flow rate on Data Sheet, Test #2. 250 W n 22.9 nc
/
Zsa > zy.c ue
/ f// 9/P/
(9)
Close HCV-329 Open HCV-333; after 10 minutes measur,e flow rate out of SL-173.
Record PI-325,.PIC-2969 and flow rate on]ata S eet, Teg#g,PwJsg g PfpM
/ N f/d'/
Tile CV-33 (10) minutes measu,re flow out of SL-173Open HCV-331; Rdbil&d w;&
7 Record PI-325, PIC-2949, and flow rate j p ggye3 cre d on Data Sheet, Test #4 250 4 in 8%7" = o.2dy* (11) d; 8-/fd/
gro a.,4 49.9 u<
0 22I V" Close HCV-331.
NOTE:
If excessive leakage is noted on any of the LPSI loop check valves, proceed to Step (12).
If all are within allowable leakage limits per attached leakage limit curva, proceed to Step (18).
Excessive leakage (greater than allowed
/ 9-/f4/
'l (12) for Fig.particular aP as indicated on attached
- 1) through the check valves may be caused by improper seating.
Seating of ing procedures.the valves may be improved by the follow-and are to be per(formed at the discretion These steps are optional of the test engineer).
(a)
Close the leakage cooler outlet valve for that loop.to prevent automatic opening or place (SI-277, 276, 275, or 274) the leakage cooler pressure control valves (PCV-2949/2969 2909) or the loops being-press /2929/
in manua1.
urized py_ gqq
)i
/&lVk L
(b) Start a HPSI pump.
[
/ bN/
SU D R0 9-18-81 iEP 181981
~'
3
..e
..?...,....J : _...
a
.:,, %... a......
l
ST-CV-2-6 F.1 TEST PROCEDURE (Continued)
SIGN OFF/DATE (12)
(c) Pressurize the downstream side of the LPSI check valve by opening the appro-priate HPSI loop isolation valve.
(HCV-311, 314, 320, 317, 312, 315, 321, or 318). Monitor the pressure and level of all four safety injection tanks to ensure the SI tank discharge check valves'are holding.
If pressure or level increases significantly, franediately stop the running HPSI n
pump.
A/
/ Nfd (d) Observe the pressure on PIC-2909, 2929, 2969, or 2949.
P_M psig IV 7'$~ 9/
(e) Close the HPSI loop isolation valve (HCV-311,314,320,317,312,315, 321, or 318).
/ O/ M/
(f) Stop. the HPSI pump.
/ b/IN NOTE: ; Steps (13) thru (17) will now
[ repeat the leak test.
NOTE:
If the leakage is considered to be partially thecugh HCV-2938 (SI-1B outlet), it may be closed at the discretion of the. Shift Supervisor.
If HCV-2938 is to be closed ensure that at least two hours have lapsed between reducing station power to <10%
of rated power and time of clos-gdb ing valve. Record both times:
-!C
/ 9llTl7l
/
Time @ <10%
Time for Closing g q ( Power HCV-2938
/'
(13) Open HCV-327; after 10 minutes measure 4-
[j[ gad flow rate out of SL-173. Record PI-235, PIC-2909, and flow rate on Data Sheet, Test #1.
/
(14) Close HCV-327, open HCV-329; after 10 Ij{ G g minutes, measure flow rate out of SL-173.
Record PI-325, PIC-2929, and flow rate on Data Sheet, Test #2.
/
ST-CV-2-7 F.1 TEST PROCEDURE (Continued)
SIGN OFF/DATE (15) Close HCV-329, Open HC/-333; after 10 Mc W - > st.f a c.
minutes measure ficw rate out of SL-173.
Record PI-325, PIC-2969, and flow rate no ci e it. ) :.c on Data Sheet, Test #3.
/F/9-8 (16).Close HCV-333, Open HCV-331; after 10 Og minutes measure flow out of SL-173.
Record PI-325, PIC-2949, and flow rate on Data Sheet, Test #4.
A//@ /
O&lM_./9//7h[
(17) Close HCV-333 (18) Review Steps b.(3) and (12); return valves to original position or as directed by the Shift Sepervisor.
M / T-6-81 0 46/2 / !/9 k /
9 (19) Open HCV-2948 38 HCVJs,HCVJ35.
N c v-3 3 5 SF6 uo d s a 3 food E t'%
/
/ f d ['
b (20) Open 'lalves SI-167 and 169.Lt A (21) N tify Shif Supervisor of completion of 55
//
c.
Remarks:
Sl. ' 20 %
Non not 'lta d A bvass bac VG Vf On ltW 0 0vb f(Itc VLesd b
bYCLSS h2 ct -
0-loa.L g
l l
Test Completed By: /M h Date/ Time 9-/P6/ 7 '13 m w w U E. W RO 9-18-81 SEP 181981
~~-
ST-CV-2-8 F.1 TEST PROCEDURE Wentinued) sigil 0FF/DATE DATA SHEET LPSI CHECK VALVES Test #0 Flcw through SL-173 0,/65 gpm PI-325:
23 PSIG, PIC-2909:
2 80 PSIG (Step b.(6))
Test #1 Flow through SL-173 caused by leakage through SI-203.
(Step b.(7) and (13))
Leakage Rate O. l'75 gal./ min (observed)
Pressures: PI-325:
23 PIC-2909:
227 Allowable leak rate (Fig. 1) =
/. b6 a %.
642]E/19!TI 44 Test #2 Flow through SL-173, caused by leakage through SI-200 (Step b.(8) and (14))
Leakage Rate O. /'7 3 gal./ min (Ob:erved)
Pressures: PI-325:
23 PIC-2929:
- 2. S o aP (PIC-2929 - PI-325) =
22'7 9!ff A11cwable leak rate (Fig. 1) =
/.66 noy Of<>// /
1 Ni Test #3 95t i
'5#g p"5 '" (Step b.(9) and (15))
R w thr ugh SL-173 caused by leakage through SI-197 l
Leakage Rate O.357 gal./ min (Observed) l I(L.
Pressures: PI-325:
/dC PIC-2969:
265 UUULy AP (PIC-2969 - PI-325) =
/65 g
,4,g SEP 181981 Allowable leak rate (Fig. 1) =
f.
R0 9-18-81
ST-CV-2-9 F.1 TEST PROCEDURE (Continued) sigil 0FF/DATE DATE SHEET LPSI CHECK VALVES (Continued)
Test #4
' low through SL-173 caused by leakage through SI-194 (Step b.(10) and (16))
Leakage Rate C. N opm. (Observed)
Pressures: PI-325:
//0 PIC-2949:
200 aP (PIC-2949 - PI-325) =
/8d Allowable leak rate (Fig. 1) =
/.36 o0%
Ohl[ /
/9!f[
+
Comments:
l t
i l
r R0 9-18-81 SEP 181981
- -10 TEST PROCEDURE (Cont'd{BLE SI CHECK VALVE L e
F.1 ALL0h an m msas E EN H 2.5
~
u
/
v
/
I
/
m
/
u
/
u y
a
}
~
g -/
\\
u 7 a
L2 I
i
' ' ' f f
'?
f f f f f f f 8
f f
f f f
f f
f f
f f
f 1
S M
B B
B M
S E Il M !BIE PSI R0 9-18-81 SEP 181981
L
=
r
! tEFUELING
.?r;ISI::I Unn'IC.JIO:?
j ST-CV-1-1 C
reit _:n o r,y
,i Fort Calhoun Station Unit No.1 Sur/eiHance Test
. c.,leh $! 7 cda.d.
SURVEILLANCE TEST c..
Procedur
. Ir.$ ;.
Y/f[Il f
Section F.
Leak 78st of HPSI System Secondary Check Valvei
~
'~~~~
~-
Dua Date:
Month No.
f/m /h A.
PURPOSE 1.
The purpose of this test is to detect and quantify leakage past the primary coolant system secondary check valves.
B REFERENCES 1.
CE Drawing E-23866-210-130, Sheets 1 and 2.
2.
Technical Specification 2.3(1).
3.
Order for Modification of License Concerning Primary Coolant System Pressure Isolation Valves, NRC letter April 20,1981, and Technical Evaluation Report, " Primary Coolant System".
C.
SPECIAL INSTRUMENTATION /EOUIPMENT 1.
Container for collecting leakage (approximately 1 - 2 gal.)
2.
Stopwatch D.
PRERE0VISITES SIGNOFF/DATE 1.
An appropriate Radiation Work Permit is posted.
/ g/,j,,
2 I
'23 RMP No.
'/ V il
' 2 / k/9, /
2.
The test rig shown in Figure 1 has been installed.
1 3.
A minimum of AP of 150 psi must be obtained for the
/
/_,
test to be valid.
61/M /9//9/6i E.
PRECAUTIONS 1.
Obey provisions of the Radiation Work Pemit.
2.
The pressure of the water inside of the pipin! may be over 200 psig. Caution should be exercisej whec opening test valves.
RO 9-18-81 REFUELING}
SEP 181981 i
9 ST-CV-1-2 F.
TEST PROCEDURE 1.
Leak Test of Secondary Check Valves Frequency:
Each Refueling or other Cold Shutdowns longer than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if not tested within the previous 9 months.
Responsibility:
Engineering / Operations a.
Initial Conditions SIGROFF/DATE (1)
Reactor coolant T is greater thar. 500 F,
/fNIL 0
cold (2)
The reactor is suberitical,
/
(3)
Reactor primary pressure is > 1500 pstg.
/
I f
(4)
All four safety injection tanks are pressur-ized to at least 24_0 psig with a tank liquid level of at least 116.2 inches (67%) and a maximum level of 128.1 inches.(74%) with refueling boron concentration.-
ec /
/
{
(5)
The following valves are open:
HCV-2914, SI-6A discharge HCV-2934, SI-6B discharge HCV-2954, SI-6C discharge HCV-2974, SI-6D discharge A / 1 b.
Test Procedure (1) fot Shift Supervisor that test is to SS I
I (2)
Open, or check open, the following HPSI valves:
HCV-311, loop 1B i
HCV-314, loop 1A l
HCV-317, loop 2A
/
i HCV-320, loop 2B g
(3)
Close, or check closed, HPSI header isolation
/
valve HCV-306.
/ //d o l
\\
l (4)
Open the test valve shown in Figure 1.
If j
no water issues from the test line after 10 minutes of observation, record pressures on p.O data sheet, Test #0, then proceed to Step (8).
94
' fyater does issue from the test line, close or mwd closed the following r21ves:
l UED %%.leako w1% au %v-HPsr h; isciala ValQ g.1a.81 SEP 181981 s kss A moted b e,
,ad,Vidud Wu Wuau f, u4 i
JDs not ruassant be usu.a de kakay % da indiv,-L llPn S"%dagdgk vches. &ced Q ltakay ud passans e duk sbk
ST-CV-1-3 F.1 TEST PROCEDURE SIGN OFF/DATE b.
Test Procedure (Continued)
(4)
(Continued)
HCV-304 HCV-2908, SI-2'B discharge Closing these valves will provide additior.s1 assurance that the observed leakage is not
//
coming from the SIRWT.
O fd 8 / 9//8/ O (5)
Observe the test line discharge for at least 10 minutes. After the first few minutes, any water issuing from the test line will be due h{d{
to leakage past the HPSI secondary check valves.
If there is leakage, measure the leakage rate and record the value on the Q
attached data sheet.
/
(6)
If leakage was observed in Step-(5), ose the HPSI loop valves (HCV-311, 314, 317, and 320) to isolate three of the four loops. _ Measure the. leakage rate from the unisolated loop and record the value on the attached. date sheet.
f{40-Repeat for the other three HPSI loops. Ensure p
test valve shown in Figure 1 is closed at the b
end of test,
/
(7)
If any (or all) of the HPSI (15005) check valves fail this test (See Figure 2), the reason may be improper seating of the check valves. To seat the valves better, the following procedure may be used:
(a) Close the leakage cooler outlet valve for the loop being pressurized to pre-vent automatic opening.
(SI-277,276, 275 and 274) or place the leakage
,)f cooler pressure control valves, PCV-2949/
2969/2929/2909, on the loops being y
pressurized in manual.
/
(b) Start HPSI pump SI-2A or SI-2C.
/
(c) Pressurize the downstr7am side of the 1500# HPSI check in question by opening the appropriate HPSI (2500#) isolation valve (i.e., HCV-321, 318, 315, or 312).
Monitor the pressure and level of all four safety injection tanks to ensure I
UED the SI tank discharge check valves are R0 9-18-81 SEP 181981
ST-CV-1-4 F.1 TEST PROCEDURE (Continued)
SIGN OFF/DATE (c)
(Continued)
/@ 0 '61{
holding.
If pressure or lesel increases significantly, inrediately stop the running HPSI pump.
/
(d) Observe the pressure on PIC-2909, 2929, f gd${
2969, or 2949.
Observed =
/
(e) Close HPSI (2500#) isolation valve (s),
g 00E (HCV-312, 315, 318, or 321),
/
(f) Stop the HPSI pumps.
If the pressure on PIC-2909, 2929, 2969 or 2949 remains le Old'//
above 500 psia, bleed the pressure down to just below 500 psia using the manual kN control on the associated PCV.
1 (g)
Repeat. Steps (4) and (5).
b (8)
Close or check closed:
HCV-311
.HCV-314
/9 h1 (9)
Open, or check open, the following vlaves:
HCV-306, HPSI header isolation HCV-304, HPSI header isolation HCV-2908,-SI-2B discharge
//# //
M /f ah, (10) Close valve SI-235.
(11) Remove test rig.
Install a swagelok cap on
/j tees between SI-235 and PI-309. Open 51-235.
798 / f/J3(g (12) Notify Shift Supervisor of completion of f, l 4Sy/
s/
c.
Remarks:
/4c/ in ktid kth Eta d u :
0 2 6Pm I%gJ dwam be w.nle fat - o G GPM Z ed Juv.xs 133/y m.M fed- 015' 6/x 3'ksed dui as 3 0 W < h t'
- 0. // GPM QyyL Test Completed By:
O.M.
6C!(/7/[
Date/Tirre:f!Eh/ / /O RO 9-18-81 SEP 181981
.' F.1 TEST PROCEDURE (Continued)
ST-CV-1-5 g DATE SHEET Test #0
- 0. ll n
.w(measured). E na e h5 Entire System Leakage = M 6#
PIC-2909 =
25o PSIG, PIC-2929 =
250 PSIG, PIC-2949 = 2 6CPSIG, PIC-2969 = 2(-C PSIG, PI-309 =
0 PSIG Allowable. Liabec fut wt$vt ( P as 2) -
0 gh,6 Test #1 Flow out of test valve caused by leakage through SI-195 =
gpm (observed)
Pressu'e in SI-6C =
PSIG (PIC-2949) PI-309 =
PSIG aP = (PIC-2949 - PI-309) =
PSI Allowable leak (Figure 2) =
GPM Test #2 Flow out of test valve caused by leakage through SI-198 =
opm (observed)
Pressure in SI-6D =
PSIG (PIC-2969)
PI-309 =
PSIG AP = (PIC-2969 - PI-309) =
PSI Allowable leak (Figure 2) =
GPM Test #3 Flow out of test valve caused by leakage through SI-201 = __ _gpm (observed)
Pressure in SI-6B =
PSIG (PIC-2929)
PI-309 =
PSIG AP = (PIC-2929 - PI-309) =
PSI Allowable leak (Figure 2) =
GPM Test #4 Flow out of test valve caused by leakage through SI-204 =
opm (observed)
Pressure in SI-6A =
PSIG (PIC-2909)
PI-309 =
PSIG AP = (PIC-2909 - PI-309) =
PSI Allowable leak (Figure 2) =
GPM lS U=lls
=
\\
4 s
F.1 TEST PROCEDURE (Continued) s 8
o ts a
C E
o b
Q h g
n2 W
3$
2 54
=
2 t 4
DW G
2 y
iT) h 2
K 2.
M 4
3 F
me w
7
.7 i
3w.
Y
?
^
~
V_
<p-y:,
s
_ p d
I R0 9-18-81 SEP 181981 FIGURE is
~
F.1 TEST PROCEDURE (Continued)
,m ALL0iiABLESICHECKVALVELEAKAGELIMITS H YS 21.3 7 X25 VE sE s Lane H 2.5
/
~
/
r
~
u I
X u
u u
s g
u y
l
=
u -/
- u. 7 a
u u
s u
a a
a a
a a
i eu ?tEUE?5 Figure 2 RO 9-18-81 SEP 1 a'1981
,a~, - +
,, =
J FORT CAI.EOUN STATICE UN!"' NO.1 N?
SECTICN I SETPOIN-'/PROCE URE CHANGE
- 6965 PROCEDUP3
~
oa~.,.o'.~ ~. / 2..c ~^ ~ ~ =..'t " e r :
P.27ISION VIRIFICATION
~
Title:
Master Revision No.
Change: (Attach copy of procedure with changes if extensive)
Date 4
f.
< m c.
s,cs v
ko, sd
[\\
r ', et(?
tjf*, { ff s
't. *
'tn i s 'k i p*
. roay 4 y s s t.,,,,,
.t or o s l '.
s. n !r'*ra g i N.tw (G s.
isVi: L o c.---
^ ' r' I is' <!c< 1 's
.1 r - = : c.: s i l'
- n
- n : t o va
'. e i.
. l w.. l.G
- (!
I. a ?r. e: 6 1 c'r-Jiv e E cn ;rik
-!.o l-- T */ :/ O
/O <-
- , f I n ta * * '*
? +.o ' fr,... ;.o t.^ ) *
.L 1 Jt d %I vK u usti s it, u, t W.,.
l e t t-<,n.,t />
- f. i'!'1
- t..
. s -s e
-i< !~
'7
- ! -r *~ ~ ano
! f: /. e Vr.'
.'o Y Reason:
.tr<
in tr fit y tr, fnyw usrd :,, h {etf
't5 kc{aj h(, hr, c o
\\ c c..<
C. ( '
)r,tr g VG f p.
- M l4 '[S bls.
finc.) c/Ecu cod 13v it,,
- i,tliviclu<a sn. / a.
THIS SETFOI'IT/ PROCEDURE CHANGE CCNSTITE A$i UNREVII"FID SAFETY QUESTION? YES (-) NO (W (Cenplete For= FC-15h for Cc=plete evaluation).
If YES, SAEC approval required when an SECTICN I Cc=pleted 37:
Unreviewed Safety Question is involved.
' h//hr I d ((A*N &
/ 'el N b Approved:
/
Initiator Sirnatu e
/
Date__
SARC Chair an
/
Date i
SEC-' ION II - To be Cc=pleted by Shift Supervisor t
^
Route to,PRC A.
Is Setpoint/ Procedure Change required
(_)
NO i=nediately (Cn-The-Spot)?
,s
( 7 YES - Obtain two apprevals telev
' l0 /9 ?!
ths '/d. f/ L WrAr/
/ V, /9 ['/
x-<
NRC Senior Licensed FRC Me=5er/ '? Dave PRC Member
/
Date
/ if i'
bN n& MiM
/ 9 / '7 h/
3.
SECTION II Cc=pleted By:
Shift Su :ervisor
/
Date SEC"' ION III - Route to PRC for Approval:
i
/
/
Supervisor-I&C and Elect.
/
Date Supervisor-Operations
/
Date ield Maintenance
/
/
Superviscr-Technical
/
Date Reactor Engineer
/
Date
/
/
Superviscr-Maintenance
/
Date Plant Engineer
/
Date
/
/
Surerviser-Chem. L Rad.P ot. /
Date Manairer-Fort Calhoun Station /
Date SICTICN IV To be Cc=pleted by a PRC Me=ber A.
Is Procedure Change to be Incorporated into Operating Manual?
(_) YES
(_) NO If No, State Reason NCE:
If M is checked, this Procedure Change vill be reviewed at a PRC Meeting to ensure that the Syste:/ Equip =ent/ Procedure has been returned to nor-='.
A-G-30-8 3.
SECTICN IV Cc=pleted 3y
/
FC-68 FRC Member
/
Date R9 12-1-80 nas vus'ennienov
4 ATTACHMENT 6 I
a l
l f
I I
I I
1 o
m A
- W e
. I..,
EYERCSTATIC TIST FOK4 E
FLO'd DII.GR.M1 d6 ' #// - /.7 0 TIST I!GE S "2' - (T DATE
/O-/ 5 -7 2 COUTRACT 03 SISTI4 IDEUT.
M MAMTEACTURER
/#7-7[.3 CODE USE
.A,7/. 7 MATERIAL S, E,
CO'GCIIII!T/SYSTEt d'E No 'T< M TEST PRESSURE M//d /8/d SIZE /
S_fA/'.I'Y
/4leys L DURATIC:1 3/a
//o ~
H/osmam GlDE IDS 1T.
CALIERATIC:I DATE
/0 -/'F-7 A RESPC::SISLE LA30PaTORY
&##8
~
QUA!!TITY TESTED (IIICLUDI ALL JOE 7IS IF PIPII:G)
$ce C ^Z - 7 i
RESULTS MMS
/e 2S7 ee/YAMV-C,
1 j
m REMARKS 6 u,,,
.,. 7 L (3 (c4 14Nera 1
. ~ _ _ _
~
Ne w s n,,..
I f ",T '. rl *'" ' - - n.'.. _,,,.;i i~
y),,?? a, m.,Q gj n
,a ; d aj j 3 j
-.3 QUALITY COLTROL FU'?CTIOi!S CERTIFIED CC:9LETE[YrDT-j gEAT TRIALE:IT
.l M & ID CECX i
l [ TRACEAsILITY (331 7).
l
~
e r
G PXS Q.A.
QCF-5 R2 OD,3R UI':1ESSf Mr &gWpppy
~
~!
<> L /A JW /D.//
f- ',
.h:dS'u /7/t,I.h". A_4f f.b, PROCEDUEE
.]*
hn.i *.T %.O. 9.1 5 D," T tl %
il 8:.
CCL D t-WD@.
F0R LEAK TESTl::G f
c i,
) i ;,,:
,,. g i:.\\ el' z/'2:.+K,.'.y.:t
- ,e
.. /., ',- - p,-l/-
\\
..s Test No.
,,$_7_~- 8//'h 2 \\
a:.'. :
is.,
/3,. /,, /,,,N - -
a t., m t,_- i _.,..An_,gg r. S m RcsPcnsibic Suyt. /,6 /_ G o u,~
C. O L,t, H 'C l ^,
,Q ;.;.<, n
~
C 5 et/c:- %
.sp;y.~y:,,,?-
I. DESCRIPTION OF SYSTEM System: b4'f2 7Y'. A/M:./~/G//F1cu Diagram: 0E-E30,$$-E/O -/.3'0 rc,
/
~
Piping Class : 2,Cc/7('
Piping Group:
I Applicable Code:,C54 7 151;152,etc.
System Design Pressure :
System Desisn Te::p:
~
II. SCOPE OF TEST Isc=e tric D.ig. Nos.1~C - 77 7 9,, 80
..SZ-2O B 7. //2
- 2 0 3 8 / /,/
- 20 B9 / /'/
s i
(
/
-2c48 /k Other Descriptive Remarks :
ik/.S ' ES,l f.kJ/// bt' M ish 7/$/I' d **// $ M :N:!;;.C//bl D///-
/Ac 6H E/s a.:.... -/ n/// /e - A.
E xi.c-w/:.?.1 s?'
bi'i.- l{>
l&'C,l/f.A ;!'
67 Gi. CC i.'. </.? !' /, ^l*
.C.Z~-/?G /?,'^~i /?'7', /?S, i
Ecs,Ec/, to 3,. O / 2M
- .. :,i d:w,c/i:. > : u' Go!,'s / w/x l
A c v' 35/, E/7. 35 B, EEC C E 9, I ': 4, ! 7 a i: a' 3/,' ffJ,-:2-///94.,
i
/
/
llv%1)Wr- !>>lc s.)i // Of8J'.C tl/I 6/Y'S /* v.> l*/f.5,
^^' o
! 6.-? 'l b ;
~
III. des"C'PI.(: 0,..z 'kl!_,,dd/f// c't. /t_.?
0 ((./ //Yb2'.c
/'ffS[.s[G.
l / !
n1 4 Or u.s t Type of Tes t:
is ' W S.4 77'C Testing _ Medium:
Cclc/ 4'y.,:o Tes t Pressure :r c r
,':J.-: Pressure Gauge Range: d*'#'/ / /C/2 9 C Mdt"'
Equiptent Included:
Max. Allouable Tes t Pres :
Pg. Z. of Z.-
C n
-: ;i PreCI:DllPR FOR 1.fMK TI:STTI.O d[~ M / b System:
Test No._
IV. PP2PAluTIO?: AND PP.OCI:DUPS A
A
. P R @,.: M n c dci.),i: ee. ain -daf A. {coowIn7 Conro/ lle' /ns c"'=
C /0== =ll (s) Mc6 331 re) #cv'-- 329 (b) Nc'/ - B/7 c,f) Mc V-3/4 te) //cv
.333 (9) Alc /
5 2 7
(/) NcY - 3//
b0 NN - $20 t
ACD u:ily/a//
% Ai d,,,7 s i/a ste. A, a m i;, s'> m c :C.c i s o 1 :1.+.
0
//ed 25-n.
sacle.ciitr o/ /Arte cArchJ: &cA Jsmni Aid wi//
utur%.y ccipadi),y.
hsut.//s cwa y
ta >.cz - /#
re>.st-zco (b) 6Z - /?5
(/) $ 7 - 2'o /
(c) M- /97 (9) 3.T - 2o 3 l
(d). 12^ '/ G8 l -)
6.7-2's 4
& B, R2x.n,,c 5 o) wka
-/.0
.w.c %
amnc),,,.: ; og A, a4,, c;x,,.g r
unlues is. 8/ :v.8 Er
-Hs stetA.ve,.a, ace.' A.:::.a. -
s
.li!;
,4. /i2 >. e/ t'ii'as i.u
-?.:. si/L.1 in 9/ 'r kc ' is cil60. k/hi!6 -
Ut'n I
&.s* fEG'd (5, CW:/ri$D -/Ar y'!//s.. 6 A
uf /c ciohs A 4to
,ata c.m/
/0 NO lu$rn. -/^s s Ysk.:.t c-:nn G M'Ck.
?'//C' t'S/6,(YS SA6c.i,=/s-% i5 db
//c/s/ /$r/J;'t.
n'scMwe, ava &w is Jutueni A ecc isa; n's Aes.
ib cr'a.4 oS N& (8) eM4. /*.fs:L'r ade.v?.s d' 4*r.pd-E
& A AMr o= R=~ ' wee.rio.o o e z k L a r c,c D:&- CCL% 0f. h SY w c.} e
'O
,b$
~
f4/
- k ([f/$A.f h) $f $
ll.
$. UllfG..D ' h;fff!
l/hoD ;
e 9
i i-'d d..,.
PEo:EDURE NO. VEL-Q -550 APPENDIX "A" 5:L-QC-550 Rey,11 C Cf10 t! a T* l C N d NR.
h,d g
h; ;
j FINAL TEST AND Ii;5PECTION REPORT 4
5' I. li.l.
VALVI STJ.IAL tiO.
/d24 TESTS PER MC3-SF-61 '. LTc_
i -
ll 6
VALVE ITDI T
CUSTCHER SPEC -@
c s
MOTCR SERIAL NO.
9 98 9 e s0 TAG UO. //CV 3 fC MOTOR TYPE 8 h O - C 6 - M' DATE TESTS CONDUCTEb h 9j P
SIZE AND DE30RIPTION f$da/M: _ h'*d o c /, 4 S S S / w
__"i f
l
- i. i. i,,
j i
h
i
.SIGliAThRE 1.
HIDRO s:c.L TEST (30 cin.).
.RESULTS
~
2.
STm GLAND TEST (30 min.)
1.
GR l
[ ll' ;!
4 l
h poig 9/f 00 I d ein)
TEST Pev.u.
07 0'V
['
i;,h i
i I " t"bl )
36oD 2.
Oc.
[
lVl-l j
j^
l Sido A Sido 3 Sido!A Side B!!
~
Il i
l'I
.: i-i I [
3 SEAT LEAYAGE (30 cin.)
3l.h 'i ' b M
- 3. f K O L' 4
BACK3 FAT LEAKAGE (10 min.)
r
[13 klk),
b i, f.[ f[
t
- 4. 04 I
TEST PPaiSURE 3 BOO psig i
/
{
< it
~;i 1;.j.
(see table) i I. I ii i
b,
.i -
l..
j 3'
MOTOR OPERATED VALVES l
i D
(see Valve Spec. Snects) 5 ;
}'
I E.jj i..I T[
l0 S&c. ' 41 t1*H h'M O P3l-
),
- TIME IN SEO. TO OPER. VALVE i
f,;.,l'( -
UNDER THE FCILO'.IING CONDITIONS:
A, _of/ O tt h a 7" 8 ffJn q
2
(
1 :,.~
i cl e
A) MAXI! UM PRESS.
DI::utENTIAL
'[....
- j D) TORQUE t,Ln
- IT SWITOH SUITING b.
b 5
4
- 4 o
~
'I l'
I l 's Remarks:
'i i}
$!E000 eT R T %
(* / A n (*
^
l
_t/cwn n y s c e..n c e F e m m e j
p A,s Ru? Mu Wars 9.g 6
b
- n. f n
=
i n 5 tfm -(bc~~S.Tn- /Fett R 1i L
h@u cC IITLE_C/ttEF./Nopacro A
, DATE:_ h g d b dr--
CERTIFIED
[
7 7 Ass m nLT TEST InsPEcToa 3 7. 84 %s<'#
l.
I as:As.e t
DA=Ei nm t
?
I l i
u-p e
- i!
3 l-I
..j e
,I i.,
- li-1 l ~
l
)
.'. !,. ' N..
'l
-d.
~
.j.
i 1
p
$y,
. I __
- i.
. u ~. q;,..
l.i.
- %.,~
f
~'
. j,
.l_
ij
',3
' * ' A,.
t
,a l
1 3
o-
'] E,
- N..
PROCEDURE NO. VEL-C.C-550 APPENDIX "A"
'/EL-QC-550 Ray. '1 C C h Q t.L a T* l o N 6 b.R.
]l g
~
h; 3 FINAL TEST AND INSPECTICN F TORT Ia VALVE SE3IAL NO.
/A3 u TESTS PER !!SS-SP-61 ' 1!
l l
I 4
V ALVI I:::t f
CUSTOMEa SPZe l'Y1 i
P i
13 99e9sA.
TAG NO.
NCV $17 ij j narca 3Ea:AL NO.
s n0 TOR TYPE 6'h 6-C O'- M ~
DATE TESTS CONDUCTED; he 7 9
l
' SIZE AIO DE3CRIPTION _f!":ba: /fdo C AMS S[w _
f l
I il lj ja l ;
1.
iiYDRO S:L LL TEST (30 cin.).
RESULTS d
. GIGNA' BEE b lb j l)}
i l
1 2.
STEi GLAND TEST (30 min.)
1.
Of.
I Y h I
t h poig 6/yOO
. brk 5
i TI.3T PRESSURE
.a 4Jace table) 360D 2.
ON.
l'.
' ;}.
\\.. i b,
I l
1 i
et
-s Side A Side 3 Sido,.A Side Bi',
i i
e I
I 4
3 SEAT LEAK /GE (30 cin.)
j
.j 4
SACKSEAT LEAXAGE (10 =in.)
- 3. OK G/c
,+,0'i d
- i f
?.-
+
TEST PRI3SURE 3bCO poig l+. f' E IIMA/f)
I' f
k f d ;i 'p" (see table)
' V
(
.6
-l,y 4
.?
l l
MCTOR OPERATED VALVE 3 i
'I i'
4 4
f l
i
?
. ]
(see Valve Spec. Sheeta) i i
]Q Si?.C ki tTH. 4s 8 O P3l-
'.l
^
.i..j '1
- TIME IN SEC. TO OPER. VALVE UNDER THE 70ILC'.IING CONDITICNS:
4g. 0.y O tt '71G 7" 7//)A l
g, I
A) MAXII:UM PRESS. DI:::.nENTI L E _. - -..
!. h 4
.4 s
B) ICRQUE L LIMIT SWITCli SEI'I'ING b.
,l
^'
'~
)4 t
l Recarks:
J i:
Y?ou?
8;:' T % CAo,G k
i hkrti nr Stv.du~n ?/ar.~rn2G] +
lt l
i A.\\ /E70.S/'twen.',
Wo'OE 05 l-
-N
'~ -
t'.LC' ll~L' 0 C~~ S S'O - $ tl O Y
J CERTIFIED -.
4(/
TIT 1-CNt6E 1N0fCIC fd A DATE:__
<< T -9 ~
g
<l
/^
f g' N.
/
f
.i ASSE!BLY TEST INSPECTOR
" b_
,.s 1
jd'fY C-5
.'i lY DATEk Wy A '/4'.:V
'l V
y N
L q-l.l' t
'I 1
- l' f'
l i
1
. :j-
- }l I
=g I
t 1
e tt 3
0
~.s i
a-is 3
s.
i,
.~
t a
I 1
1
I 13 PRCCEDURE NO. VEL-QC-550 APPENDIX "A" TdL-QC-550 nsv. 1 9e h
. h' d
, C Ch Q tJ S T~ l o N 6.0 k.
l' t-g FINAL TEST AND IN3PECTION REPORT; i
I'!1 i-
.;l j VALVE 3ERIAL NO.
/Ad 3 TEST 3 PER !!S3-GP 61 $ @. ;.
i e'
ag VALVE ITD!
D_
CUSTCliER GTEC l
I.,
' NC V h/M
'g i
h;j naTcR JERIAL NO.
99%394 TAG N0.
n0 TOR TyTE 3h3 oe 1C DATETEsTSCCNDU5.TED. Mu; 7/$9
' SIZE AND DE3CRIPTION f 6 L3ng /mo_ g3&f S/w I _.
.__ T '
'.i[,,[
j i-Ji
,i i
]i
' ! h. l!
1.
syDRo SRELL TEST (30 ein.).
.RE3ULTS
. SIGNATURE l
h 50
', lli l!
2.
STm GLAND TEST (30 cin.)
1.
G/C h pois 6/fCO
.N $'I' ll TE3T PRE 3SURE iface table) 5600 2.
@D I
\\\\.ibl I !
l1{('
i jj
$l l'
l, i
I i
I Side A
.Sido B Gido A Side 3 :!,
I
..l ;,
4 3
SEAT LFXGGE (30 cin.)
.1 i.:.
l i-si
[i ;'
i i
x 4.1,M,! M 4
BACK3 EAT LEAKAGE (10 =in.)
- 3. Ok.
Os h.l,'
j ~
<3 i
i+. O ld l l} 7/Y
- {~
i
!! 3.
h I
TEST PPT;35URE 3 600 psig i
'if 7V
.j ::t [4 (see table) 8 j
3 o.
1.
MCTOR OPERATED VALVE 3 l
T I
j' i
1 ii j.
~
l tsee Valve Spec. Sileets) t i
.! 3
/0 S/2.!O W '7'N G83 0 P3/-
.}.,1
- TD:5 IN SEO. TO OPER. VALVE 1,,.
UNDER THE FOLI.O'4ING CCNDITICNS:
3, _d u G u"7,4.iR7"
,P //)n i
(
t --... /
A) MAXIMUM PRE 3S.
DI:::.EiTIAL
- J e
'. [-
B.g
., 7.-
... _. p./j' p./ };.
[
i
)
i
- .I, L*-
Re :: arks:
J i:
a MA609 eTR' '7' '7n'
(* As.n G E
l t
tbwro a r-nw nre Rrsswn.il
{
. l l
l As Pad 3A wn.<,
WoTa
- 9. L
[
p
\\
i oehi_-Qc.sen hvR o
CERTIFIED f h/b.. - TULE_ C/ttGF'./#5FCCEoA.
'DATEt-
/
~*
I' ASS EBLY TEST USPECTOR
/
fr se 24Ju 1
f DA=E(s,ww.
9 d.-
n
+
i.
i) i.
]
l i
e
.(
i
-l
,i.
^
l,]
J i
g.
1 l
1
+l ri 2.4 8
-i
?
ej J\\,
i,
'i
- l,.,..
3:
l M
ll i
,'l
7.
1 o
PROCEDURE NO. VEI,-qC-550 APPDiDIX 'A"
'lEL-QC-330 Hav. 1 i f..
C eh 0 e.4 T" l o N E Mi.
Od 1; f t
s-j FINAL TFM AND INSPECTION REPORT l'
I il i
VALVE 3ERIAL ;;0.
/'A' T.i TESTO PER !!S3-GP. 61 'M
]}
i I. '
'~
VALVE IIDI i
CUSTCl!ER SPEC l
.I l
!:0 TOR 3E3IAL Iic.
97 & S '7 A TAG NO. WCl' 3 h/
'i i
i l
HOTOR TIPE 8 b 13 - C C -? T DATE TE3TS CONDUCTED Mictn i
'SICE AND DESCRIPTION Ml$bM 4"do _ CMSS S/t.O _.Q_ _..
.._b f
f,;
[
.c z.
l.,
l l
I l
i j8 g
l 1.
HYDRO SHELL TEST (30 cin.).
RE3ULTS
. SIG:iATiiRE
)
td
}
7 0 il 2.
STET GLAND TEST (JO cin.)
1.
4. A',
j i
b i,
l
! j
.. h TEST PRE 33URE I
poig 6400 Ae Y/b/4M rgi u,
t h !,.
360D 2.
d.K.
Il[7dI AI' h!,
4(ceotablo) i q.-
?,.
Sido A Side B lSidoA Side Bq
{c.
O e
s I
a
.d.
- f..
I g
g.j, {.
1,. i 3
SEAT LEAKAGE (30 min.)
f 4./{I
.i h
I-
$.5 *h 4.
BACKSEAT LEAKAGE (-10 =in.)
i.3.d.N d/.
i q
11 UWb~ l.
L.
,a d
' i.i TEST PRESSU"-tE 3 b0 0 pois i, 4. A./<.
s
[!..l g
,1
'j./ /j (see tablo) i:
{
~,
3; MOTOR OPERATE 3 VAL */ES i
~
l l i.'
].
i f
(see Valve Spec. Sheeta) i
/OS$C tJ a7'**,'~ @ 3 0 P8l b.
t
's
- TD:5 IN SE3. TO OPER. VALVE i aq i
UNDER TRE FCLLO' JING CCNDITICN3:
A, J _tf O ttIA n T*
.9 //JR 1
I.. M.
. L.
i.--.-
t O
A A) MAXIMUM PRESS. Dit m d:iTIAL
[- 3 $'m ^o--
'j
.p
.[....
~
g s.
B. ggg-l-
~
- 3) TCRQUE i.e LD1IT S*4 ITCH SEZrING i
,l.
l I
Recarks:
1 t.
=
Mr?nup 5'R T* %
t' 4.s r, G l~
l, G. ' ?
1bk!R pr SnAdwe Pfar.tuaGj -
I l.
A.\\ Pn/2 JAwu WaT2 95{.
Y p
O C 6; t~ Q C~~ SS'O
[2tr R
'I -
CERTIFIED
[8 ~
tit 3_.chiggfyspgcrAA DATE _
' F-
,9 I8MIa I
ASSI:ELY TEST INSPECTOR DATEfDemWd'S),
h
.-fd'dAbg 1
' l' V
...i.
,9:
g i
i, ll it 9--
r
- j
.I
.li' i
I j
.l-i
.i ]2.4 i
a
.... ~ ~.
-' - j-
~
m.
~.
i, j-y
.s y
L
.