ML20003F541
| ML20003F541 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 04/16/1981 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML17193B328 | List: |
| References | |
| NUDOCS 8104220471 | |
| Download: ML20003F541 (12) | |
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Quad Cities Station Unit 1, DPR-29 Proposed Technical Specification Changes Revised Pages:
3.6/4.6->a 3.6/4.6-6 3.6/4.6-7 3.6/4.6-14 3.6/4.6-15, Table 3.6-1 3.6/4.6-15a, Table 3.6-1 3.6/4.6-150, Table 3.o-1 New Pages:
3.6/4.6-15c, Toole 3.6-1 3.6/4.6-150, Teole 3.o-1 3.6/4.6-15e, Table 3.6-1 3.6/4.6-15f, Ta01e 3.6-1 Deleted Page:
3.6/4.6-13a 810.4220471
QUAD-CITIES DPR-29 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unienn the loon i
is cooner returncd to cervice, l.
Shock Suppressors (Snubbers)
I.
Shock Suppressors (Snubbers) 1.
During all modes of operation The following surveillance except Shutdown and Refuel, all requirements apply to all l
snubbers listed in Table 3.6-1 snubbers listed in Table 3.6-1.
shall be operable except as l
noted in 3.6.l.2 following.
1.
Visual inspections shall be performed in accordance with 2.
From and af ter the time that a the following schedule uti-l snubber is determined to be in-lizing the acceptance operabic, cor.tinued reactor criteria given by Specifica-operation !s permissibic during tion 4.6.1.2.
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 Number of Snubbers operable.
Found inoperabic Next During Inspection Required 3
If the requirements of 3.6.l.1 or During inspec-Inspection and 3.6.l.2 cannot be met, an tion Interval interval i
orderly shutdown shall be initiated and the reactor shall 0
18 months be in a cold shutdown condition i 25%
within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
j 1
12 months 4.
If a snubber is determined to be 1 25%
inoperable while the reactor is l
In the Shutdown or Refuel mode, 2
6 months the snubber shall be made i 25%
operabic prior to reactor start-3,4 124 days up.
i 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 i
3.6-1 is included with the next 2.8 31 days license amendment request.
1 25%
i 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' ba_cJ on their accessibility for inspection during reactor operation. Thesc two groups may be
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inspected independently according to the above schedule.
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QUAD-CITIES DPR-29 2.
Visual inspections shall verify:
a.
There are no visible indications of damage or impaired operability, and L
b.
Attachments to the foundation or supporting structure are secure.
c.
For hydraulic snubbers, the hydraulic fluid reservoir and fluid connections shall be inspected for operability.
3 Once each refueling cycle a representative sample of 10%
of the total of each type of snubber in use in the plant shall be functionally tested either in place or in a bench test.
For each snubber that ;
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 movement, lockup, and bleed.
5 The mechanical snubber func-tional test shall verify that the breakaway force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum force.
3.6/4.6-o
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QUAD CZTIf3 DPR-29 6.
hten a snubber is deemed inoperabic, a review shall l
be conducted to determine the mxle of failure and to decide if an engineering evaluation should be performed.
If the engineering evaluation is deemed necessary, it Qill determine whether or not the snubber rncle of failure has iqurted a significant effect or degradation on the supported ccitponent or system.
- 7..In addition to the regular j
sample, snubters which failed l
the previous functional test shall be rrtested during the next test period.
If a spare snubber has been installcd in place of a failal snubber, i
then both the failed snubber j
(if it is repaired and installedi l
in another position) and the I
j spare snubber shall be rotested.1 i
Test results of these snubbers may not be included for the resampling.
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L 3.6/4.6-7
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QUAD-CITIEL DPR-29 l.
SNUSDERS the structural Integrity All snubbers are required OPERABLE to ensure that of the reactor coolant syst em and all other safety 'rciated systems i..uin-initiating dynamic loads. -
tained during and following a seismic or other event Snubbers excluded from this inspection program are those installed on non-safety-related systens and then only if their. failure or failure of the system on which they are installed, would have no adverse ef fect on any safety-related system.
The visual inspection frequency is based upon maintaining a constant-4 Therefore, the required inspection level of snubber protection to systems.
interval varies inversely with the observed snubber failures and is determined 4
Inspections by the number of inoperable snubbers found during an inspection.
performed before that interval has elapsed may be used as a new reference the next inspection.
I!owever, the results of such early point to determintinspections performed before the original required time interval has (nominal time less 25's) may not be used to lengthen the required inspection i
Any inspection whose results require a shorter inspection interval i
interval.
i will override the previous schedule.
When the cause of the rejection of a snubber is cicarly 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 Generically susceptible snubbers exempted from being counted as inoperable.
are those which-are of a specific make or oedel 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.
Ehen a snubber is found inoperable, a review shall be performed to determine the snobber mode of failure.
Results of the review shall be used to i
determine if an engineering evaluation of the safety-related system or component is necessary. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant ef fcet or degradation on the support comconent or pystem.
Observed failures of these sample snubbers shall require functional l
testing of additional units.
Hydraulic snubbers and mechanical snubbers may each be treated as a j
different entity for the above surveillance programs.
3.6/4.6-14
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QUAD-CITIES DPR-29 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 Tyoc* Number Location (feet)
During Shutdown to Remove Operation Operation M
l-1 Orywell; core spray return 644 h
X X
line 1-1403-10" M
l-2 Drywell; core spray return 644 X
X lina 1-1403-10" l
M l-3 Dryuell; core spray return 642 X
X j
J line 1-1404-10" M
l-4 Drywell; core spray return 642 X
X line 1-1404-10" M
1-5 Drywell; RHR return line 603 X
X l-1012A-16" M
l-6 Drywell; RHR return line 599 X
X l-1012A-16" M
l-7 Drywell; RHR return line 598 X
X l-1012B-16" M
l-8 Drywell; RHR return line 603 X
X i
\\
1-1012S-16" M
l-9 Drywell; RHR shutdown 601 X
X cooling supply line 1-1025-20"
3.6/4.6-15
QUAD-CITIES DPR-29 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 Type
- Number Location (feet)
During Shutdown to Remove Operation Operation M
l-10 Drywell; RPR shutdown 601 I
X X
cooling supply line 1-1025-20" M
l-11 Drywell; "A" recirculation 586 at 135 X
X X
pump to shield wall M
l-12 Drywell; "B" recirculation 586 at 315 X
X X
pump to shield wall M
l-13 Drywell; "A" reci rculation 586 at 146.5 X
X X
pump to support M
1-14 Drywell ; "B" reci rculation 586 at 304 X.
X X
pump to support M
l-15 Drywell; "B" reci rculation 586 at 326.5 X
x x
pump to support M
1-16 Drywell; recirculation ring 610 at 900 X
X X
header M
1-17 Drywell; recirculation ring 610 at 2700 X
X X
header X
X M
l-18 Drywell ; "A" reci rculation
'612 at 1350 pump motor to support
- M = Mechanical Snubber H = Hydraulic Snubbar 3.6/4.6-15a
QUA!O-MUVULG DPR-29 Tobic 3.6-1 SAFETY RELATED Si10CK SUPPRESTORS (SNUBBERS)
Snubbers Snubbers Snubbers Snubber in High Especially inaccessible Accessibic Elevation Radiation Area Difficult During Normal During Normal i'
Snubber Type
- Number Location (feet)
During Shutdown to Remove Operation Occration M
1-19 Drywell; "B" racirculation 612 at 315 I
X X
X pump motor to support X
X X
M 1-20 Drywell; recirculation ring 612 at 1950 header to support M
1-21 Dry.. ell; "A" reci rculation 588 at 1240 X
X X
pump to support M
1-22 Drywell; "A" recirculation 602 at 1220 X
X pump motor to shield wall M
1-23 Drywell; "A" recirculation 602 at 1480 X
X pump motor to shield wall M
1-24 Drywell; "B" recirculation 602 at 302 X
X pump motor to shield wall M
1 25 Drywell; "B" recirculation 602 at 3280 X
X l
pump motor to shield wall M
1-26 Drywell; main stream 619 X
X X
relief valve 1-203-3A l
M 1-27 orywell; main stream 619 X
X X
relief valve 1-203-3A
l 3.6/4.6-15b
DPR-29 l
Table 3.6-1 SAFETY RELATED SHOCK SUPPRESSORS (SNUBBERS)
Snubbers Snubbers Snubbers Snubber,in High Especially inaccessible Accessible Elevation Radiation Area Difficult During Normal During Normal
'l 1
- Typc* Number Location (feet)
During Shutdown to Remove Operation Operation Snubber M
l-28 Drywell; main stream 619 l
X X-relief valve 1-203-3A X
X X
M 1-29 Drywell; main stream 619 relief valve 1-203-3A M
1-30 Drywell; northeast end of 605 X
X CRD cluster M
1-31 Drywell; northwest end of 605 X
X CR0 cluster-M l-32 Drywell; southeast end of 605 X
X CRD cluster M
l-33 Dryuell; southwest end of 605 X
X CRD cluster i
X H
1-34 Reactor b1dg; RHR fuel pool 642 system cross tic return line 1-1070-6" X
H 1-35 Reactor b1dg; RHR fuel pool 642 system cross tic return line 1-1070-6"
quad-MUVUMM DPR-29 Table 3 6-1 SAFETY RELATED SHOCK SUPPRESSORS (SNUBBERS)
Snubbers Snubbers Snubbers Snubber in High Especially inaccessible Accessible Elevation Radiation Area Difficult During Normal During Normal Snubber hType* Humber Location (feet)
During Shutdown to Remove Operation Operation X
H 1-36 Reactor bldg; RHR shutdown 590 cooling supply line 1-1025-20" H
1-37 Reactor bldg; RHR shutdown 573 X
X cooling supply line 1-1024A-20" X
X H'
l-38 Reactor b1dg; RHR shutdown 573 cooling supply line 1-1024A-20" X
X H
1-39 Reactor bldg; RHR shutdown 573 cooling supply line 1-1024A-20" 573 X
X H
1-40 Reactor bldg; RHR shutdown cooling supply line I-1024A-20" X
H 1-41 Reactor bidg; RHR pump 562 X
supply line 1-1015A-24" X
H 1-42 Reactor bldg; RHR pump 562 X
supply line 1-1015-24" 610 X
X X
M l-43 Drywell; Recirc line l-201-22"
QUAD-CITIES DPR-29 Tabic 3.6-1 SAFETY RELATED SHOCK SUPPRESSORS (SNUBBERS)
Snubbers Snubbers Snubbers Snubber in High Especially inaccessible Accessible Elevation' Radiation Area Difficult During Normal During Normal Snubber Type
- Number Location (feet)
During Shutdown to Remove Operction Operation I
M 1-44 Drywell; Recirc line 614 X
X X
1-201C-12" M
l-45 Drywell; Recirc line 614 X
X X
l-20 l M-12" M
l-46 Dryucil; Reci rc line 613 X
X X
l-2010-28" M
l-47 Drywell; Reci rc line 613 X
X X
l-201C-12" M
l-48 Drywell; Reci rc line 594 X.
X X
l-202A-28" M
1-49 Drywell; RHRS line 627 X
X X
1-1011-4" M
l-50 MSIV Rm; Main Steam 615 X
X X
li ne 1-3001 A-24" M
1-51 MSIV Rn; Main Steam 615 X
X X
line 1-3001A-24"
-*M = Mechanical Snubber H = Hydraulic Snubber 3.6/4.6-15e
vjusr-winnnte DPR-29 Tabic 3.6-I SAFETY RELATED SHOCK SUPPRESSORS (SNUBBERS)
Snubbers Snubbers Snubbers Snubber,in High Especially inaccessible Accessible Elevation Radiation Area Difficult During Normal During Normal l
Snubber Typn* Number location (feet)
During Shutdown to Remove Operation Operation X
M l-52 MSIV Rm; Main Steam 615 i
X X
line 1-3001B-24" X
X X
M l-53 MSIV Rm; tiain Steam 615 line 1-30010-24" M
1-54 MSIV Rm; Main Steam 615 X
X X
line 1-3001C-24" M
1-55 MSIV nm; Main Steam 615 X
X X-line 1-3001C-24".
M 1-56 MSIV nm; Main Steam 615 X
X X
line 1-30010-24" M
1-57 MSIV Rm; Main Steam 615 X
X X
line 1-30010-24"