ML20003F542
| ML20003F542 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 04/16/1981 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML17193B328 | List: |
| References | |
| NUDOCS 8104220478 | |
| Download: ML20003F542 (10) | |
Text
.
Quad Cities Station Unit 2, UPR-30 Proposed Technical Specification Loangea Revisco Pages:
3.6/4.6-Sa 3.6/4.6-6 3.6/4.6-7 3.6/4.6-14 3.6/4.6-1), Taole 3.o-1 3.6/4.6-loa, Taule 3.o-1 3.6/4.6-150, fable 3.o-1 New Pages:
3.6/4.5-15c, Table 3.6-1 3.6/4.6-150, IdDie 3.6-1 Deleted Page:
3.6/4.6-13a 810.4220YNi
QUAD-CITIES DpR-30 sooner returned to service, l.
Shock Suppressors (Snubbers) 1.
Shock Suppressors (Snubbers)
The following surveillance l
1.
During all modes of operation requirements apply to all l
except Shutdown and Refuel, all snubbers listed in Table 3.6-1.
i snubbers listed in Tabic 3.6-1 4
shall be operable except as 1.
Visual Inspections shall bc l
noted in 3.6.l.2 following.
performed in accordance with the following schedule uti-
?.
From and af ter the time that a snubber is determined to be in-lizing the acceptance criteria given by Specifica-operable, continued reactor tion 4.6.1.2.
operation is permissibic during the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> only if the snubber is sooner made ilumber of Snubbers Found inoperabic Next operable.
During Inspection Required I
3 If the requirements of 3.6.l.1 or During Inspec-Inspection l
and 3.6.l.2 cannot be met, an tion interval Interval i
orderly shutdown shall be 18 months 0
initiated and the reactor shall 1 25%
be in a cold shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
12 months 1
4.
If a snubber is determined to be 1 25%
inoperable while the reactor is 6 months 2
In the Shutdown or Refuel mode, 1 25%
the snubber shall be made operable prior to reactor start-3,4 124 days i
up.
1 25%
5 Snubbers may be added to safety-related systems without prior 5,6,7 62 days license Amendment to Table 3.6-1 1 25%
provided that a revision to Table
>8 31 days 3.6-1 is included with the next 1 25%
1icense amendment request.
The required inspection interval shall not be lengthened more than one step at a time.
Snubbers may be categorized in two groups, ' accessible' or 'inacces-sible' based on their accessibility for inspection during reactor operation.
Thenc'two groups may be inspected independently according to the above schedule.
3.6/4.6-Sa
QUAD-CITIES DPR-30
-2.
Visual inspections shall verify:
There are no visible a.
Indications of damage or impaired operabiitty, and b.
Attachments to the foundation or supporting structure are secure.
For hydraulic snubbers, c.
the hydraulic fluid reservoir and fluid connections shall be inspected for operability.
Once each refueling cycle a 3
representative sample of 10% !
l of the total of each type of snubber in use in the plant j
shall be functionally tested I
cither in place or in a bench l For each snubber that !
test.
does not meet the functional {
test criteria, an additional 10% of that type of snubber shall be functionally tested.
4.
The hydraulic snubber shall be functionally tested for operability, including verification of proper piston; lockup, and bleed.
- movement, The mechanical snubber func-5 tional test shall verify that; the breakaway force that j
initiates free movement of i
the snubber rod in either l-tensien or compression is less than the specified maximum force.
1 i
a 3.6/4.6-6
CUlO CIT 8PS
. DPR-30 6.
khen a nnulter is deemed
= inoperable, a review cha11 be conducted to determine the mode of failure and to decide if an engineering evaluation should be perfoared.
If the engineerirg evaluation is deemed necoccary, it Oill determine whether or not the snubber noie of failure 4
has imparted a significant i
effect or degradation on the supported comtunent or system.
I 7.
In addition to the regular sample, snubM rs which failed the previous functional test shall be retested during the next test period.
If a l'
spare snubber has been installed l
in place of a failcd snubber, f
then both the failed snubN r i
(if it is repaired and installed in another position) and the spare snubber shall be rotested.1 Test results of these snubbers l
may not be included for the resamplirg.
0 h
r
[
1 i
i 4
f 3.6/4.6-7
. _,. _,. _,,, _,, _... ~. _. _, ~. _.. _. -. -... _
QUAD-CITIES DPR-30 l.
SNUBBERS All snubbers 1are required-0PERABLE to ensure that the structural Integr'ty of the reactor coolant system and all other safety related systems is main-tained during and following a scismic or other event initiating dynamic loads.
Snubbers excluded from this inspection program are titase installed on non-safety-related systems and then only if their f ailure or failure of the system on which they are installed, would have no adverse affect on any safety-related system.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.
Therefore, the required inspection interval varies inversely with the observed snubber failures'and is determined by the number of inoperable snubbers found during an inspection.
Inspecticas performed before that interval has clapsed may be used as a new reference inspection, llowever, the resul ts of such early point to determine.the next inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.
When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperabic.
Generically susceptible snubbers are those which-arc of a specific ruke or nodel and have the same design features directly related to rejection of the snubber by visual inspection, or are similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration.
To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plant shutdowns at refueling cycle intervals.
hten a snubber is found inoperable, a review shall be performed to determine the snubber mode of failure.
Results of the review shall be used to determine if an engineering evaluation of the safety-related system or ccitponent is necessary. The er.gineering evaluation shall determine Whether or not the snubber mcde of failure has irparted a siunificant effect or degradation on the support comconent or system.
I' Observed failures of these sampic snobbers shall require functional testing of additional units.
1 Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.
3.6/4.6-14 i
QUAD-CITIES 1)PR-30 Table 3.6-1 SAFETY RELATED SHOCK SUPPRESSORS (SNUBBERS) 4 i
Snubbers Snubbers Snubbers Snubber in High Especially inaccessible Accessible i
Snubber Elevation Radiation Area Difficult During Normal During Normal Typa* Number Location (feet)
During Shutdown to Remove Opera tion Operation X
M 2-1 Drywell; core spray return 644 X
line 2-1403-10" M
2-2 Drywell; core spray return 644 X
X line 2-1403-10" M
2-3 Drywell; core spray.eturn 642 X
X line 2-1404-10" 1
M 2-4 Drywell; core spray return 642 X
X line 2-1404-10" M
2-5 Drywell; RHR return line 603 X
X 2-1012A-16" 1
M 2-6 Drywell; RHR. return line 599 X
X 2-1012A-16" M
2-7 Drywell; RHR return line 598 X
X
~
2-1012B-16" M
2-8 Drywell; RHR return ilne 603 X
X i
2-1012B-16" M
2-9 Drywell; RHR shutdown 601 X
X cooling supply line 2-1025-20" 1*
- e n. r_ i c
OVAD-CITIES DPR-30 Table 3 6-1 SAFETY RELATED SHOCK SUPPRESSORS (SNUBBERS)
Snubbers Snubbers Snubbers Snubber in High Especially inaccessible Accessible Snubber Elevation Radiation Area Difficult During Normal During Normal Tyoa* Number Location (fect)
During Shutdown to Remove Operation Operation M
2-10 Drywell; RHR shutdown 601 l
X X
cooling supply line 2-1025-20" M
2-11 Drywell; "A" recirculation 586 at 135 X
X X
pump to shield wall M
2-12 Drywell; "B" reci rculation 586 at-315 X
X X-pump to shield wall M
2-13 Drywell; "A" recirculation 586 at 146.5 X
X X
pump to support M
2-14 Drywell; "B" reci rculation 586 at 326.5 X
X X
pump to support M
2-15 orywell; "B" recirculation 586 at 304 X
X X
pump to support 0
X X
X M
2-16 Drywell; reci rculation ring 610 at 90 header 0
X X
X
)
M 2-17 Drywell; recirculation ring 610 at 270 header M
2-18 Drywell; "A" reci rculation 612 at 135 X
X X
pump motor to support
QUAD-CITIES DPR-30 Table 3.6-1 SAFETY RELATED SHOCK SUPPRESSORS. (SNUBBERS)
Snubber in High Especially inaccessible Accessible Snubber Elevation Radiation Area Difficult During Normal During Normal
}
Typc* Number.
Location (feet)
During Shutdown to Remove Operation Coerotion M
2-19 Drywell; "B" reci rculation 612 at 3150 I
X X
X pump motor to support f'
M 2-20 Drywell; recirculation ring 612 at 1950 X
X X
header to support M
2-21 Drywell; "A" reci rculation 588 at 1240 X
X X
j pump to support M
2-22 Drywell; "A" recirculation 602 at 1220 X
X pump motor to shle'id wall M
2-23 Drywell; "A" reci rculat,on 602 at 1480 X
X pump notor to shield wall M
2-24 Drywell; "B" recirculation 602 at 3020 X
X pump motor.to shield wall j
M 2-25 Drywell; "B" reci rculation 602 at 3280 X
X pump motor to shield wall i
619 X
X X
M 2-26 Drywell; main stream relief valve 2-203-3A i
M 2-27 Drywell; main stream 619 X
X X
relief valve 2-203-3A i
i 3.6/4.6-15b
QUAD-CITIES DPR-30 l
Table 3.6-1 j
~
SAFETY RELATED SHOCK SUPPRESSORS (SNUBBERS)
Snubbers Snubbers Snubbers Snubber in High Especially inaccessible Accessible Elevation Radiation Area Difficult During Normal During Normal
?
Snubber Typc* Number Location (feet)
During Shutdown to Remove Operation Operation M
2-28 Drywell; main stream 619
}
X X
X re. lief valve 2-203-3A M
2-29 D rywel l ; mai n s t ream 619 X
X X
relief valve 2-203-3A M
2-30 Drywell; northeast end of 605 X
X CRD cluster M
2-31 Drywell; northwest end of 605 X
X CRD cluster M
2-32 Dry. ell; southeast end of 605 X
X CRD cluster M
2-33 Drywell; southwest end of 605 X
X CRD cluster X
H 2-34 Reactor bldg; RHR Pump D 558 X
supply line 2-1016D-14" X
H 2-35 Reactor bldg; RHR Pump D 558 X
supply line 2-1016D-14" H
2-36 Reactor bidg; RHR shutdown 591 X
X cooling supply line 2-1025-20"
\\
3.6/4.6-15c
QUAD-CITIES DPR-30 Table 3.6-1 SAFETY RELATED SHOCK SUPPRESSORS (SNUBBERS)
Snubbers Snubbers Snubbers Snubber in High Especially inaccessible Accessible i
Snubber Elevation Radiation Area Difficult During Normal During Normal Tyoa* Number Location (feet)
During Shutdown to Remove Operation Operation H
2-37 Reactor bldg; HPCI steam 588 j
x X
supply line 2-2305-10" X
l H
2-38 Reactor bldg; Pressure 646 Suppression vent line 2-1603-18" X
11 2-39 Reactor bldg; SSGTS 655 t
vent line 2-1607-6" l
X H
2-40 Reactor bldg; SBGTS 655 vent line 2-1607-6" X
H 2-41 MSIV Rm; RCIC steam 605 X
l line 2-1307-3" l
X 6
1 H
2-42 MSIV Rn; RCIC steam 605 X
{
line 2-1307-3" i
1