ML20003F540
| ML20003F540 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/16/1981 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML17193B328 | List: |
| References | |
| NUDOCS 8104220466 | |
| Download: ML20003F540 (10) | |
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Dresden' Station Unit 3, DPR-25 i
Proposed Technical Specification Changes 4
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91b 91c l
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91d-1, Table 3.6.la, 91a-2, Table 3.6.la 91e-1, Table'3.6.lb j
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DPR-25 4.6 SURVEILLANCE REQUIREMENT 3.6 LIMITINC CONDITION FOR OPERATION I.
Snubbers (Shock Suppressors)
I.
Snubbers (Shock Suppressors) 1.
During all modce 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.
c able except as noted in Specification 3.6.I.2 through 3.6.I. 4.
1.
Visual Inspection 2.
From and after the time a snubber is determined An independent visual inspection shall be per-to be inoperable, continued reactor operation is formed on the safety related hydraulic and mechanical snubbers contained in Tables 3.6.la 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 /> unless the snubber is sooner made operable or and 3.6.lb in accordance with the below schedule.
replaced.
All hydraulic snubbers whose seal material a.
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-tinted and the reactor shall be in cold shutdown patible with the operating environment shall be visually inspected. This inspec-or refuel condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
tion shall include, but'not necessarily be If a snubber is determined to be inoperable limited to, inspection of the hydraulic-4* uhile 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 Inspection Interval Inspection Interval 0
18 months 3; 25%
1 12 months 3;25%
2 6 months j;25%
3, 4 124 days 3; 25%
5,~6, 7
62 days 3;25%
>8 31 days j; 25%
91b
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T DPR-25 3.6' LIMITING CONDITION FOR OPERATION 4.6 SURVEILLANCE REQUIREMENT The required inspection interval shall not b'e lengthened more than one step at a time.
Snubbers may.be categorized in two groups,
" accessible" or " inaccessible," based on their accessibilityLforJinspection during reactor operation. These two group's may be inspected independently according to the above schedule.
2.
Functional Testing a.
Once each refueling cycle, a representative sample of approximately 10% of the hydraulic 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 more failures are found or all units have been tested.
b.
Once cach refueling cycle, a representative
~
sample of approximately 10% of the mechani '
cal snubbers contained in Table 3.6.lb shall be functionally tested for operability.
The test si.all verify that the force that initiates free movement of the snubber in' cither. tension'or compression.is less than the specified maximum breakaway / friction force.
For each unit and subsequent unit found' inoperable, an additional 10% of the mechanical snubbers shall be so tested until no more failures are found or all units have been tested.
0 91c
DPR-25 l
4.6 SURVEILLANCE REQUIREMENT 3.6 LIMITING CONDITION FOR OPERATION r
- d. ~ In additior. to the regular sample, snubbers
,f which failed the previous functional test shall be retested during the next test period.
If a sparc 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 be included for the resampling.
may not Snubbers of rated capacity greater than e.
50,000 lbs. need not'be functionally tested.
- 3. When a snubber is~ deemed inoperable, a review of all pertinent facts shall be conducted to determine the anubber 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 deemed necessary, it will determine whether or not the-snubber mcde of f ailure has inaparted a significant ef fect or de-gradation on the supported component or system.
I e
)
H.
Recirculation Pump Flow Mismatch an earthquake or severe transient while allowing normal thermal motion during startup and shutdown.
The LPCI loop nelection logic has been described in The consequence.of an inoperable snubber is an in-.
the Dresden Nuclear Power Station Unita 2 and 3 crease in the probability of structural damage to FSAR, Anendments 7 and 8.
For some limited low piping as a result of a seismic or, other event probability accidents with the recirculation loop initiating dynamic loads.
It is therefore required 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 prevent fuel tempera-tures from exceeding allowable limits. Ilowever, Because the snubber protection is required only to limit the probability even further, a procedural during low probability events, a period of 72 liriitation has been placed on the allowable vari-hours is allowed for r.epairs or replacements.
In ation in speed between the recirculation pumps, case a shutdoun is requi ed, 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 snalyses 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 commence with knowingly defective safety re-80% power, the loop select logic would not be ex-lated equipment, Specification 3.6.1.4 prohibits pected to function at a speed differential of 20%.
startup with inoperable snubbers.
This specification provides a margin of 5% in pump speed differential before a problem could arise.
When a snubber is found inoperabic, 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 revieu 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 mismatch between the two not the snubber mode 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 cculd set up a vibration until or system.
a misnatch in speed of 27% occurred. The 10% and 15* speed misostch restrictions provide additional All safety related hydraulic snubbers are visually rargin before a pump vibration problem will occur.
inspected 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-l 1.
Snubbers (Shock Suppressors) bility. The inspection 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
.q DPR-25 Th2 inspection frequency is baced upcn maintoining Ilydrculic enubbars and mechanical snubbero msy occh.
.j a constant level of snubber protection. Thus, the be treated as different entities for th9 abcv2 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 Ilydrualic snubber testing will include stroking of determines the time interval for the next required the snubbers to verify proper piston movement, inspection.
Inspections performed before that in-lock-up and biced. Mechanical snubber testing will include that the force that initiates free movement terval has elapsed may be used as a new reference of the snubber in either tension or compression is point to determine the next. inspection.
Iloweve r,
the results of such early inspections performed less than the specified maximum breakaway / friction force.
before the original required tinac interval has l
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 exempted 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 sinilarly located or exposed to the same environmental c,onditions 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 sampic 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.
99b
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9 TADLE 3.6.la SAFETY RELATED llYDRAULIC SNUBBERS
~
St;UTIBERS SNUBBERS SNUBBER IN 111C11 INACCESSIHLE ACCESSIBLE SNUBBER LOCATION ELEVATION AZIMUTil RADIATION AREA DURINC NO101AL DURING NORMAL 1:0.
DURING SilVTDOWil Ol'ERATION Ol'ERATION 2
Torus Ring fleader 1501-24" 483' 83*
X 3
Torus Ring 11eader 1501-24" 483' 74*
X 4
Torus Ring Ileader 1501-24" 483' 38*
X 5
Torus Ring lleader 1501-24" 483' 29*
X 7
Torus Ring lleader 1501-24" 483' 331*
X 8
Torus Ring lleader 1501-24" 483' 322" X
9 Torus Ring IIcader 1501-24" 483' 286*
X, 10 Torus Ring llcader 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 lleader 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 cu:ndment request.
DPR 25 oia 1
TABLE 3.6.la (Continued)
SAFETY RELATED IIYDRAULIC SNUBBERS l
SNU:1DERS SNUBBERS I
SHUBBER IN 111C11 INACCESSIl3LE ACCESSIBLE a
S!1UBBER LOCATIO!1 ELEVATION AZIMUTil RADIATION AREA DURit:G NORMAL DURING N0!!'.AL 11 0 DURIt:G SituTDOWN OPERATION OPERATI0tt Isolotion 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 CHodifications to this table due to changes in high radiation should be submitted to the IIRC as part of the next license amendment request.
npp -);
TABLE 3.6.lb g
i SAFETY RELATED MECllA!11 CAL SNUBBERS SilUBBERS St4UllBEllS SNUBBER IN IllGli IllACCESSIBLE ACCESS illLE S! LUBBER LOCATION ELEVATION AZlHUTil naDIAT10tl AREA DURlllG !!ORMAL DURiflC NORMAL DURIllC SilUTDOW11 OPERATIOtl OPERATlutt 11 0.
i Dryuell Recirc. Motor 311-202 328*
X X
2 Dryuell Recirc. Motor 3b-202 5
30 7 X
X 3
Drywell Recirc. Motor 3B-202 524' 315*
X X
4 Dryuell itecirc. Motor 3A-202 524' 148*
X X
5 Dryuell Recirc. Motor 3A-202 524' 122*
X X
6 Dryuell Recirc. Motor 3A-202 524' 135*
X X
7 Dryuell Recire. Pump 311-202 512' 326*
X X
8 Dryuell Recire. l' ump 311-202 512' 304*
X X
9 Dryuell Recirc. Pump 3B-202 507' 3 T 5*
X X
10 Dryuell Recirc. Pump 3A-202 512' 124*
X X
11 Dryuell Recire. Pump 3A-202 512' 146*
X X
12 Drywell Recirc. Pump 3A-202 501' 135*
X X
j 13 Drywell Recire. Line 201B-28" 507' 305*
X X
14 Dryuell Recire. Line 2OlA-28" 507' 105*
X X
15 Dryuell LPCI Line 1506-16" 513' 256*
X X
16 Drywell LPCI Line 1519-16" 513' 95*
X X
17 Dryuell Recire.-Ileader 201B-22" 533'6" 195*
X X
18 19 20 21 Dryuell Recirc. IIeader 201A-22" 533'6" 22*
X X
22 Dryuell llPCI Line 2305-10" 550' 121*
X X
eModifications to this table due to changes in high radiation should be submitted to the llRC as part of the next license amendment request.
i TABI.E 3.6. lb (Continued)
- *l SAFETY RELATED MECllANICAL SNUBBERS t
I SNUBBERS SNUB 11ERS SNUBBER IN 111C11 INACCESSillLE ACCESSIBLE
{,S!!UliBER I.0 CAT 10N ELEVATION AZittuTil RADIATION AREA DURitiC t10!L'1AL DURitlC 110RttAL
!10.
DURING Sil0TDOUN OPERATIOtt OPERN!'IO!!
23 Drywell Cleanup Line 1201-8" 537'6" 84*
X X
24 Dryuell Feeduater Line 3204D-12" 538' 106*
X X
25 Drywell Cleanup Line 1201-8" 537'6" 7f X
X 26 Drywell Feeduater Line 3204A-18" 53/'6" 66*
X X
27 Drywell Cleanup 1.ine 1201-8" 538'6" 61 X
X 28 Drywell Feedwater Line 3204C-12" 540' 73' X
X 29 Dryvell Core Spray Line 1404-10'.'
573' 231*
X X
30 brywell Core Spray Line 1403-10" 563' 336*
X X
t 31 Dryuell llPCI Line 2305-10" 563' 14 &
X X
32 Drywell Target Rock Valve 203-3A 542'6" 14*
X X
33 Dryuell Target Iock Valve 203-3A 542'2" 31*
X X
34 Dryuell Target Rock valve 203-3A 540' 19*
X X
35 Drywell larget Rock Valve 203-3A 540'6" 34*
X X
i l
l 1
- Hodifications to this table due to changes in high radiation should be submitted to the llRC as part of the next license amendment request.
DPR-25 01 n ')