ML20003F539
| ML20003F539 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/16/1981 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML17193B328 | List: |
| References | |
| NUDOCS 8104220459 | |
| Download: ML20003F539 (10) | |
Text
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Attacnment 1 Dresden Station Unit 2, UPR-19 Proposed Technical Specification Changes Revised Pages:
91b 91c 99a 99b New Pages:
91c-1 910-1, Table 3.o.la 910-2, Table 3.6.la 91e-1, Table 3.6.1b 91e-2, Table 3.6.10 l
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i 8104220l5T t
DPRJ19
.6 LIMITING CONDITION FOR OPERATION 4.6 SURVEILLANCE REQUIREMENT Snubbers (Shock Suppressors)
I.
Snubbers (Shock Suppressors) 1.
During all modes of operation except cold shut-The following surveillance requirements apply to all down and refuel, all safety related snubbers safety related snubbers listed in Tables 3.6.la and listed in Table 3.6.la and 3.6.lb shall be oper-3.6.lb.
able except as noted in Specification 3.6.I.2 through 3.6.1. 4.
1.
Visual Inspection 2.
From und after the time a anubber is determined An independent visual inspection shall be per-to be inoperable, continued reactor operation is formed on the safety related hydraulic and permissible only during the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> mechanical snubbers contained in Tables 3.6.la unless the snubber is sooner made operable or and 3.6.lb in accordance with the below schedule.
replaced.
a.
All hydraulic snubbers whose seal material 3.
If the requirements of 3.6.I.1 and 3.6.I.2 can-has been demonstrated by operating exper-not be met, an orderly shutdown shall be ini-ience, lab testing or analysis to be com-tiated and the reactor shall be in cold shutdown patible with the operating environment or refuel condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
shall be visually inspected. This inspec-tion shall include, but not necessarily be 4*
If a snubber is determined to be inoperable limited to, inspection of the hydraulic while the reactor is in the cold shutdown or re-fluid reservoir, fluid connections, and fuel mode, the snubber shall be made operable or linkage connection to the piping and anchor replaced prior to reactor startup, to verify snubber operability.
- 5. Snubbers may be added to safety related systems b.
All mechanical snubbers shall be visually without prior license amendment to Tables inspected.
This inspection shall consist 3.6.la and/or 3.6.lb provided that a revision of, but not necessarily be limited to, in-to Tables 3.6.la and/or 3.6.lb is included with spection of the snubber and attachments to the next license amendment request.
the piping and anchor for indications of damage or impaired operability.
No. of Snubbers Found Inoperable During Next Required f
Inspection Is.rerval Inspection Interval-i 0
18 months.+. 25%
I 12 months + 25%
2 6 months I 25%
3, 4 124 days i25%
5,'6, 7
62 days
_,25%
+
>8 31 days
+ 25%
91b
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.~
DPR-19 3.6 LYMITINC CONDITYON FOR OPERATION 6.6 SURVEILLANCE REQUIREMENT The required -inspection interval shall not be 1engthened more than one step at a time.
Snubbers may be categorized in two groups,
" accessible" or " inaccessible," based on their accessibility for inspection during reactor operation. These two groups may be inspected' ir. dependently according to the above schedule.
2.
Functional Testing
)
a.
Once each refueling cycle, a representative l
sample of approximately 10% of the hydraulic l
snubbers contained in Table 3.6.la shall be functionally tested for operability,.in-cluding verification of proper piston move-ment, lock-up and bleed.
For each unit and subsequent unit found inoperable, an addi-tional 10% of the hydraulic snubbers shall be tested until no n. ore failures are found or all units have been tested.
b.
Once each refueling cycle, a representative a"
sample of approxiiaately 10% of the mechani-cal snubbers contained in Table 3.6.lb shall be functionally tested for operability.
The test shall verify that the forca that initiates f re e cover..e n t of the' snubber in either tension or compression is less than the specified u.aximum breakaway /frictica force.
For each unit and subsequent unit found inoperable, an additional 10% of the mechanical snubbers shall be se tested until no more failures are found or all units have been tested.
o G
91c
DPR-19 3.6 LIMITING CONDITION FOR OPERATION 6.6 SURVEILLANCE REQUIREMENT d.
In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period.
If a spare snubber has been installed in place of a failed snubber, then'both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested. Test results of these snubbers may.not be included for the resampling, e.
Snubbers of rated capacity greater than 50,000 lbs, need not be functionally tested.
- 3. When a snubber is deemed inoperable, a review of all pertinent facts s, hall be conducted to determine the snubber mode of failure and to de-cide if an engineering evaluation-should be per-formed on the supported system or components.
If said evaluation is deen.ed necessary, it will determine whether or not the snubber n. ode of failure has imparted a significant effect or de-gradation on the supported component or system.
'S, s
DPR-19 H.
Recirculation Pump Flow Mismatch an earthquake or severe transient while allowing normal thermal motion during startup and shutdown.
The LPCI loop selection logic has been described in The consequench of an inoperable snubber is an in-the Dresden Nuclear Power Station Units 2 and 3 crease in the probability of structural damage to FSAR, Amendments 7 and 8.
For some limited low piping as a result of a seismic,or other event initiating dynamic loads.
It is therefore required probability accidents with the recirculation loop operating with large speed differences, it is pos-that all snubbers required to protect the primary sible for the logic to select the wrong loop for coolant system or any other safety system or com-injection.
For these limited conditions, the core ponent be operable during reactor operation, spray itself is adequate to prevcnt fuel tempera-tures from exceeding allowable limits. However, Because the snubber protection is required only to limit the probability even further, a procedural during lou probability events, a period of 72 linitation has been placed on the allowable vari-hours is allowed for repairs or replacements.
In ation in speed between the recirculation pumps, case a shutdown is required, the allowance of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to reach a cold shutdown condition will per-The licensee's analyses indicate that above 80%
mit an orderly shutdown consistent with standard power the loop select logic could not be expected operating procedures.
Since plant startup should to function at a speed differential of 15%.
Below not comuence with knowingly defective safety re-80% power, the loop select logic would not be ex-lated equipment, Specification 3.6.I.4 prohibits pected to function at a speed differential of 20%.
startup with inoperable snubbers.
This specification provides a margin of 5% in pump speed dif ferential before a problem could arise.
When a snubber is found inoperable, a review shall If the reactor is operating on one pump, the loop be performed to determine the snubber mode of select logic trips that pump before making the failure.
Results of the review shall be used to loop selection.
determine if an engineering evaluation of the safety-related system or component is necessary. The In addition, during the start-up of Dresden Unit 2, engineering evaluation shall determine whether or it was found that a flow nismatch between the two not the snubber node of failure has imparted a signi-sets of jet pumps caused by a difference in re-ficant effect or degradation on the support component circulation loops could set up a vibration until or system, a miscatch in speed of 27% occurred. The 10% and 15% speed mismatch restrictions provide additiona?
All safety related hydraulic snubbers are visually margin before a pump vibration problem will occur.
inspectt' for overall integrity and operability.
The inspection will include verification of proper ECCS performance-during reactor operation with one orientation, adequate hydraulic fluid level and
- recirculation loop out of service has not been proper attachment of snubber to piping and structures.-
analy:cd. Therefore, sustained reactor operation under such conditions is not permitted.
All safety related mechanical snubbers are visu-ally inspected for overall integrity and opera-1.
Snubbera (Shock Suppressors) bility. The inspeccion will include verification of proper orientation and attachments to the piping Snubbers are designed to prevent unrestrained pipe and anchor for indications of damage or impaired motion under dynamic loads as might occur during operability.
99a
DPR-19 The inspection frequency is based upon maintaining Hydraulic caubbara and mechanical enubbers may esch a' constant level of snubber protection. Thus, the be treated as different entities for the above required inspection interval varies inversely with.
surveillance pr' grams.
o the observed snubber failures. The number of in-operable snubbers found during a required inspection Hydrualic snubber testing will include stroking of determines the tine interval for'the next required the snubbers to verify proper piston movement, inspection.
Inspections performed before that'in-lock-up and bleed.
Mechanical snubber testing will terval has elapsed may be used us a new reference include that the force that initiates free movement point to determine the next inspection. However, of the snubber in either tension or compression is the results of such early inspectiors_ performed less than the specified maximum breakaway / friction before the original required time interval has force.
. elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspec-tion interval will override the previous schedule.
When the cause of rejection of the 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 exenpted from being counted as inoperable. Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual in-spection or are similarly located or exposed to the same environmental conditions such as tempera-ture, radiation, and vibration.
To further increase the assurance of snubber re-liability, functional tests will be performed once each refueling cycle. A representative sample of 10% of the safety-related snubbers will be func-tionally tested. Observed failures'on these samples will require testing of. additional units. Those j
snubbers designated in Tables 3.6.la and 3.6.lb as being in high radiation areas need not be selected for functional tests provided operability,was pre-viously verified.
Snubbers of rated capacity greater than 50,000 lbs. are exempt from the func-tional testing requirements'because,of the im-practicability of testing such large units.
996
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O TABLE 3.6.1m SAFETY RELATED llYDRAULIC SNUBBERS SNUBBERS SNUBBERS SNUBBER IN llICil INACCESSIBLE ACCESSIBLE SNUBBER LOCATION ELEVATION AZ1HUTil RADIATION AREA DURING NOR}tAL DURING NORMAL f
NO.
DURING Sil0TDOWN OPERATION OPERATION 2
Torus Ring lleader 1501-24" 483' 83*
X 3
Torus Ring Ileader 1501-24" 483' 74*
X 4
Torus Ring.IIcader 1501-24" 485' 38' X
5 Torus Ring lleader 1501-24" 483' 29*
X 7
Torus Ring Ileader 1501-24" 483' 331*
X 8
Torus Ring Ileader 1501-24" 483' 322*
X 9
Torus Ring lleader 1501-24" 483' 286*
X 10 Torus Ring Ileader 1501-24" 483' 277*
X 12 Torus Ring lleader 1501-24" 483' 218" X
13 Torus Ring llender 1501-24" 483' 209*
X 15 Torus Ring IIeader 1501-24" 483' 151*
X 16 Torus Ring lleader 1501-24" 483' 142" X
- Modifications to this table due to changes in high radiation should be submitted to the NRC as part of the next license Emendment request.
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TABbE 3.6.la (Continued)
SAFETY RELATED I!YDRAULIC SNUBBERS SNUBBERS SNUhBERS S!!UBBER IN 111C11
- INACCESSIBLE ACCESSIELE S: LUBBER LOCATION ELEVATION AZIMUTil llADIAT10t1 AltEA DURitiG N010tAL DULLING tiO!U!AL t10.
DilRIllC SituTDOWN OPERATIO!!
OPEttATIO!!
Isolation Condenser Pipeway Room:
1 Isolation Condenser Line 1303-12" 558' 180*
X X
2 Isolation Condenser Line 1303-12" 568' 180*
X X
3 Isolation Condenser Line 1302-14" 580' 195*
X X
- Madifications to this table due to changes in high radiation should be' submitted to tlee NRC as part of the next license smendment request.
41a_,DPR-19
TABLE 3.6.11 SAFETY RELATED MECllANICAL SNUBBERS SNUB 11ERS SilUlillERS SNUBilER IN tilCll INACCESSIBLE ACCESSIBLE St1Ull15ER LOCATION ELEVAT1011 AZlHUTil RADIATION AREA DURll!G F10RitAL DURit1G 110R!!AL 11 0.
DURING SilUTDOWN OPl:llATION OPERATIOt1 1
Drywell Recire. Motor 215-202 524' 328*
X X
2 Drywell Recire. Motor 2B-202 524' 302*
X a
3 Drywell Hecire. Motor 211-202 524' 315*
X X
4 Dryuell Recire. Motor 2A-202 524' 148 X
X 5
Drywell Hecire. Motor 2A-202
- 524' 122*
X X
6 Dr yuc li Hec irc. Motor 2A-202 524' 135' X
X 7
Drywell Recirc. Pump 211-202 512' 326' X
X 8
Orywell itecire. Pump 211-202 512' 304*
X X
9 Dryuell Hecire. Pump 211-202 517' 315*
X X
10 Daywell Hecire. Pinap 2A-202 512' 124*
X X
11 Drywell Recire. Purnp 2A-202 512' 146*
X X
12 br ywe ll kec ire. Pur.ip 2A 202 507' 135*
X X
13-36 7c.Toved 17 I ryuell Itecire. lleader 20115-22 "
533'6" 195*
X X
18-20 Fe oved 21 Isrywell Hecire. Ileader 201 A-22 "
533'6" 22*
X X
22-23 Pemoved 24 bryue ll Feeduater Line 3204 D-12 "
538' 108*
X X
25-29
%:renel 30 Drywell Core Spray 1.ine 1403-10" 575' 336*
X X
31 Dryvell Core Spray Line 1404-10" 562' 231*
X X
32 Drywell Target Rock Valve 203-3A 542'6" 16*
X X
33 Dryuell Target Rock Valve 203-3A
'42'4" 31*
X X
34 Drywell Target Rock Valve 203-3A 540'0" 19*
X X
35 Drywell Target Rock valve 203-3A 540'3" 34*
X X
l36 Drywell Recirc. Line 201B-28" 518' 270*
X X
- Modifications to this table due to changes in high radiation should be submitted to the flRC as part of the next license amendment request.
TABLE 3.6.lb (Continued)
SAFETY RELATED MECilANICAL SNUBBERS SNUllBERS StlulillERS i
4 SHUBBER IN 111C11 INACCESS illI.E ACCESSitiLE
- SilullBER LOCATION ELEVATION AZlHUTil itADI ATION AltEA DURI!!G tl0RMAL DUltIllG tlouttAL
!!O.
DURifl0 SiluTDOUll OPERATIOt1 OPE 1 TAT ION 1
e 37 Drywell Recire. Line 201A-28" 518' 9C X
X 38 Drywell Shutdown Cooling Line 1001A-16" 523' 0*
X X
39 Drywell Rx Water Cleanup Line 1201-8" 533' 316 X
X 40 Drywell Rx Water Cleanup Line 1201-8" 533' 30l*
X X
t t
?
1 l
l l
0 Modifications to this table due to changes in high radiation should be submitted to the flRC as part of the next license amendment request.