ML20031F278
| ML20031F278 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 10/15/1981 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20031F275 | List: |
| References | |
| NUDOCS 8110190469 | |
| Download: ML20031F278 (12) | |
Text
_
LIMITING CONDITION FoR OPERATION SURVEILLANCE REQUIREMENT 3.6.I Shock Suppre eern (Snubb rn) 4.6.1 Shock Supprasnors (Snubbers) 1.
During all modes of opera-The following surveillance tion except Cold Shutdown requirements apply to all and Refuel, all safety-hydraulic and mechanical related snubbers listed in snubbers listed in Tables Table 3.6.I(a) and 3.6.I(b) 3.6.I(a) and 3.6.I(b).
shall be operable except as noted in 3.6.I.2 through The required visual inspec-3.6.I.3 below.
tion interval varies inverselv with the observed cumulative An Inoperable Snubber is a number of inoperable snubbers properly fabricated, installed found during an inspection.
and sized snubber which can-Inspections performed before not pass its functional test.
that interval has elapsed may be used as a new reference Upon determination that a snubber point to determine the next is either improperly fabricated, inspection. However, the installed or sized, the correc-results of such early inspec-tive action will be as spealfied tions performed before the for an inoperable snubber in original time interval has Section 3.6.I.2.
elapsed may not be used to lengthen the required inter-2.
From and after the time that a val.
snubber is determined to be in-operable, replace or repair the Number of snubbers found in-snubber during the next 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, operable during inspection or and initiate an engineering evalu-during inspection interval:
ation to determine if the com-ponents supported by the snubber (s)
Subsequent were adversely affected by the Inoperable visual Inspec-inoperability of the snubbers and Snubbers tion Interval to ensure that the supported component remains capable of 0
18 Ponths
- 25%
meeting its intended function in 1
12 Honths
- 25%
the specific safety system in-2 6 Ponths i 25%
volved.
3,4 124 Days i 25%
5,6,7 62 nays i 25%
Further corrective action for this 8 or more 31 Davs snubber, and all generically sus-ceptible snubbers, shall be The required inspection inter-determined by an engineering val shall not be lengthened evaluation more than one step at a time.
3.
From and after the time a snubber Snubbers.may be categorized is determined to be inoperable, in two groups, " accessible" improperly fabricated, improperly or " inaccessible" based on installed or improperly sized, if their accessibility for inspec-the requirements of Section(s) tion during reactor operation.
3.6.I.1 and 3.6.I.2 cannot be met, These two groups.may be in-then the affected safety system, spected independently accord-or affected portions of that ing to the above schedble.
system, shall be declared inoper-able, and the limiting condition 1.
visual Inspection Acceptance for that system entered, as criteria appropriate.
A. visual inspections shall verify:
137a 8110190469 811015_
'PDR ADOCK 05000293 l
P PM
LIMITING CONDITION FOR OPERATION SULfjIlANCEREQUIREMENT 4.6.I Shock Suppt?ssors (Snubbers) 1.
That there are no visible in-dications of damage or impaired 4
Snubbers say be added to, or operJbility.
removed from, per 10 CFR 50.59, 2.
Attachments to the founda-safety related systems without tion or support atructure prior License Amendment to are such that the ftinc-Table 3.6.I(a) or 3.6.I(b) tional capability of the provided that a revision to snubber is not suspect.
,the appropriate Table is in-cluded with the next license B. Snubbers which appear _INOPER-amendment request.
ABLE as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval provided that:
1.
The cause of the rejection -
is clearly established and remedied for that particular snubber, and 2.
The affected snubber is functionally tested, when necessary, in the as found condition and determined OPERABLE per spacifications applicable,4.6.I.2.C.,as 4.6 I.2.B.
3.
For any snubber determined inoperable per specifica-tion 4.6.1.2, clearly establish the cause of re-jection and remedy the prob-lem for that snubber, and any generically susceptible snubber.
2.
Functional Tests (llydraulic and Mechanical Snubbers)
A.
Schedule At least once per operating cycle (18 months), a representa-tive sample (107. of the total of each type: hydraulic, mechanical) o.f snubbers in use in the plant shall be functionally tested, either 16 place or in a bench test.
For each snubber th,t does not meet the functional test
" acceptance criteria of 137b
e.
F 11MITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 4.6.I Shock Suppressors (Snubbers)
Specification 4.6.I.2.B. or 4.6.I.2.C. as applicable, an additional 10% of that type of snubber shall be functionally tested.
B.
General Snubber Functional Test Acceptance Criteria (Hydraulic and Mechenical)
The general snubber functional test shall verify that:
1.
Activation (restrain-ing action) is achieved within the specified range of velocity or acceleration in both tension and compression.
2.
Snubber release, or bleed-rate, as applicable, where requiredt is wit in the specified range in compression or tension.
For snubbers specifi-cally required not to displace under contin-uous load, the ability of the snubber to with-stand load without dis-placement shall be veri-fied.
C.
Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:
1.
The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force. Drag force shall not have inc-reased more than 50% since the last functional test.
3.
Snubber Service Life !4onitoring A.
A record of the service life 137c w
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 4.6.I Shock Suppressors (Snubbersl of each snubber, the date at which the designated service liia commences and the instal-lation and maintenance records on which the designated service life is based shall be maintained.
B.
At least once per cycle, the in-stallation and maintenance records for each snubber listed in Tables 3.6.I(a) and 3.6.I(b) shall be reviewed to verify that the in-dicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review.
If the indicated service lif'e will be exceeded prior to the next scheduled snubber service life review, the snubber service life shall be reevaluated, or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review. This reevaluation, replecement or reconditioning shall be indicated in the records.
C.
This Snubber Service Life Moni-toring Program shall become ef fective July 1,1982.
"I 137d
s Table 3.6.I(c)
SAFETY RELATED HYDRAULIC SHOCK SUPPRESSORS (SNUBBERS)
Snubber No.
14 cation Elevation Snubber in High Snubbers Snubbers Snubbers Radiation Area Especially Inaccessible Accessible During Shutdown Difficult to During Normal During Normal Remove Operation Operation SS-1-10-1 Main Steam Line 42' X (Drywell)
SS-1-10-2 Main Steam Line 42' X (Drywell)
SS-1-10-3 Main Steam Line 42' X (Drywell)
SS-1-10-4 Main Steam Line 42' X (Drywell)
SS-1-10-5 Main Steam Line 42' X (Drywell)
SS-1-10-6 Main Steam Line 42' X (Drywell)
SS-1-10-7 Main Steam Line 42' X (Drywell)
SS-1-10-8 Main Steam Line 42' X (Dryvell)
SS-1-10-9 Main Steam Line 42' X (Drywell)
SS-1-10-10 Main Steam Line 42' X (Drywell)
SS-1-10-11 Main Steam Line 42' X (Drywell) 3 SS-1-10-12 Main Steam Line 42' X (Drywell)
SS-6-10-6 Feedwater Sys.
41' X (Drywell)
SS-6-10-7 Feedwater Sys.
41' X (Drywell)
SS-6-10-8 Feedwater Sys.
44' X (Drywell)
SS-6-10-9 Feedwater Sys.
41' I
X (Drywell)
SS-6-10-10 Feedwater Sys.
44' X (Drywell)
SS-10-30-1 RHR System 52' X (Drywell)
SS-10-20-2 RHR System 52' X (Drywell)
SS-10-20-3 RHR System 52' X (Drywell)
SS-10-20-4 RHR System 52' X (Drywell)
SS-10-30-5 RHR Syster.
24' X (Drywell)
I SS-10-30-6 RHR System 24' X (Drywell)
SS-10-20-7 RHR Systed 24' X (Drywell) l SS-10-20-8 RHR System 24' X (Drywell)
SS-10-3-9 RHR System 67' X (Drywell)
SS-10-3-10 RHR System 90' X (Drywell)
SS-2-20-1 Re'cir. System 42' X
X (Dryvell)
SS-2-20-2 Recir. System 42' X
X (Dryvell) l SS-2-20-3 Recir. System 42' X
X (Drywell)
SS-2-20-4 Recir. System 42' X
X (Drywell)
SS-2-30-5 Recir. System 15' X
X (Drywell)
SS-2-30-6 Recir. System 15' X
X (Drywell)
SS-2-30-7 Recir. System
- 15' X
X (Drywell)
C W
a Tabl,9 3.6.I(a) i SAFETY RELATED HYDRAULIC SHOCK SUPPRESSORS (SN1JBBERS)
Snubber No.
Location Elevatior.
Snubber in High Snubbars Snubbers Snabbers Radiation Area Especially Inaccessible Accessible o
During Shutdown Difficult to During Normal During Normal Remove Operation Operation I
L SS-2-30-8 Recir. System 15' X
X (Drywell) 1 SS-2-30-9 Recir. System 11' X
X (Drywell) i' SS-2-30-10 Recir. System 11' X
X (Drywell)
SS-2-30-11 Recir. System 27' X
X (Drywell)
J SS-2-30-12 Recir. System 27' X
X (Dryvell)
S S-2-30-13 Recir. System 27' X
X (Drywell)
SS-2-30-14 Recir. System 27' X
X (Drywell)
SS-2-30-15 Recir. System 27' X
X (Drywell) i:
SS-2-30-16 Recir. System 27' X
X (Drywell) 1 SS-2-20-19 Recir. System 16' X
X (Drywell) j SS-2-20-20 Recir. System 16' X
X (Drywell)
SS-2-20-21 Recir. System 19' X
X (Drywell)
SS-2-20-22 Recir. System 16' X
X (Drywell)
SS-2-50-23 Recir. System 17' X
X (Drywell)
SS-2-20-24 Recir. System id' X
X (Drywell)
SS-2-20-25 Recir. System 16' X
X (Drywell)
SS-2-50-26 Recir. System 16' X
X (Drywell) 4.
P 1
T X
Table 3.6 I(a)
SAFETY RELATED HYDRAULIC SHOCK SUPPRESSORS (SNUBBERS)
Snubber No.
Locatica Elevation Snubber in liigh Snubbers Snubbers Snubbers Radiation Area Especially Inaccessible Accessible During shutdown Difficult to During Normal During Normal Remove Operation Operation S S-6-10-1 Feedwater System 42' X (Drywell)
S S 10-2 Feedwater System 42' X (Drywell)
S S-6-10-3 Feedwater System 42' X (Drywell)
S S 10-4 Feedwater System 42' X (Dryvell)
SS-6-10-5 Feedwater System 42' X (Drywell)
SS-13-3-1 RCIC 38' X (Drywell)
SS-13-3-2 RCIC 38' X (Drywell)
SS-14-3-1 Core Spray 65' X (Drywell)
SS-14-3-2 Core Spray 65' X (Drywell)
S S-14-3-3 Core Spray 65' X (Drywell)
SS-14-3-4 Core Spray 65' X (Drywell)
SS-23-10-1 II.P.C.I.
42' X (Dr"well)
SS-23-10-2 II.P. C. I.
42' X (Drywell)
SS-23-3-30
- 11. P. C. I.
-3' 09" X ll.P.C.I. Quadrant SS-23-3-31
- 11. P. C. I.
-3' 09" X 11.P.C. I. Quad rant SS-23-10-32
- 11. P. C. I.
-3' 09" X 11. P. C. I. Quad ran t SS-23-10-34 ll. P. C. I.
- 6' X ll.P.C.I. Quadrant SS 10-35
- 11. P. C. I.
- 6' X 11.P.C. I. Quadrmt SS-23-3-36 li.P.C.I.
-3' 09" X ll.P.C.I. Quadrant SS-23-3-37
- 11. P. C. I.
-3' 09" X 11.P.C. I. Quad rant SS-10-3-4 3 RilR
-3' 06" X RilR Pump Room SS-10-20-44 RIIR
- 3' 06" X RJIR Pump Room SS-30-3-45 RBCCW 83'5" X Reactor Building SS-10-10-46 RilP 6"
X Torus Compartment H-3-1-1292 CRD System Modificatinns to this Table due to changes in high radiation areas should be submitted to the NRC as part of the next license amendment.
O m
i
Table 3.6.I(b)
SAFEl'Y RELATED MECHANICAL SHOCK SUPPRESS 0PS (SNUBBEPS)
Snubber No.
Location Elevation Snubber in liigh Snubbers Snubbers Snubbers Railiation Area Especially Inaccessible Accessible During Shutdown Difficult to During Normal During Normal Remove Operation Operation MS-S-500 M.S. Relief Line A X (Drywell)
MS-S-501 M.S. Relief Line A X (Drywell)
MS-S-502 M.S. Relief Line A X (Drywell)
MS-S-503 M.S. Relief Line A-X (Drywell)
MS-S-504 M.S. Relief Line A X (Drywell)
MS-S-505 M.S. Relief Line A X (Drywell)
MS-S-506 M.S. Relief Line A X (Drywell)
MS-S-507 M.S. Relief Line A X (Drywell) 4 MS-S-508 M.S. Relief Line B X (Drywell)
MS-S-509 M.S. Relief Line B X (Drywell)
MS-S-510 M.S. Relief Line B X (Drywell)
MS-S-511 M.S. Relief Line B X (Drywell)
MS-S-512 M.S. Relief Line B X (Drywell)
MS-S-513 M.S. Relief Line B I (Drywell)
MS-S-514 M.S. Relief Line B X (Drywell)
MS-S-515 M.S. Relief Line B X (Drywell)
MS-S-516 M.S. Relief Line C MS-5-517 M.S. Relief Line C X (Drywell)
MS-5-518 M.S. Relief Line, C X (Drywell)
MS-5-519 M.S. Relief Line-C X (Drywell)
MS-S-520 M.S. Relief Line C X (Drywell)
MS-5-521 M.S. Relie f Line C X (Drywell)
MS-5-522 M.S. Relief Line C X (Drywell)
MS-S-523 M.S. Relief Line C X (Drywell)
MS-S-524 M.S. Relief Line C X (Drywell) l X (Drywell)
W
~
l i
Table 3.6.I(b)
SAFEIT RELATED MEGIANICAL S110CK SUPPRESSORS (SNUBBE'RS)
Snubber No.
Location Ele.*ation Snubber in liigh Snubbers Snubbers Snubbers Railiation Area Especially Inaccessible Accessible During Shutdown Difficult to During Normal During Normal Hemove Operation Operation S-5-525 M.S. Relief Line D l
X (Drywell)
MS-5-526 M.S. Relief Line D X (Drywell)
MS-S-527 M.S. Relief Line D X (Drywell)
MS-5-528 M.S. Relief Line D X (Drywell)
MS-S-529 M.S. Relief Line D X (Drywell)
MS-5-530 M.S. Relief Line D X (Drywell)
MS-S-531 M.S. Relief Line D X (Drywell)
MS-5-532 M.S. Relief Line 3 X (Drywell)
MS-5-533 M.S. Relief Line D X (Drywell)
MS-S-534 M.S. Relief Line D X (Drywell) h C
1
BASES:
3.6.I & 4.6.I SHOCK SUPPRESSORS (Sh'UBBERS)
Snubbers are designed to prevent unrestrained ;ipe motion under dynamic loals as might occur during an earthquake or severe transient, while allowing normal thermal motion during startup and shutdown. The consequence of an inoperable snubber is an increase in the probability of structural damage to piping as a result of a seistic or other event initiating dynamic loads.
It is therefore required that all snubbers required to protect the primary coolant system and all other safety related systems or components be operable during reactor operation.
The visual inspection frequency is based on maintaining a constant level of snubber protection to systems.
The cumulative number of inoperable snubbers detected during any inspection interval is the basis for establishment of the subsequent inspection interval and the existing inspection interval should remain in effect. until its completion.
When the cause of the rejection of a snubber is clearly established and remedied for that snubber and verified by inservice functional testing, that snubber may be exempted f rom 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 inspection, and are exposed to the same environmental conditions such as temperature, radiation, and vibration.
When a snubber is found inoperable, an engineering evaluation is initiated, in addition to the determination of the snubber mode of failure, in order to determine if any safety-related component or system has been adversely affected by the inoperability of the snubber.
Initiating this evaluation within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ensures that prompt corrective action will be afforded.
Hy<lraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.
The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service condf rions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperat ure area, etc...). The requirement to monitor the snubber service life is included to ensure that the snubbers period-ically undergo a performance evaluation in view of their age and operating condi-tions. These records will provide statistical bases for future consideration of j
snubber service life. The requirements for the maintanance of records and the l-snubber service life review are not intended to affect plant operation. Due to the number and complexity of the relevant interacting factors necessary to develop a comprehensive Service Life Program, this program shall become effective July 1, 1982.
t 151a
3.
Special Reports Special reports shall be submitted as indicated in Table 6.9.1.
6.10 RECORD RETENTION A.
The following records shall be retained for at least five years:
1.
Records of facility operation covering time interval at each power level.
2.
Records of principal maintenance activities, inspections, repair
~
and replacesent of principal items of equipment related to nuclear safety.
3.
Reportable Occurrence Reports.
4.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
5.
Records of react:r tests and experiments.
6.
Records of changes made to Operating Procedures.
7.
Records of radicactive shipments.
8.
Records of sealed source leak tests and results.
9.
Records of annual physical inventory of all source material of record.
B.
The following records shall be retained for the duration of the Operating License:
1.
Record and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.
2.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
3.
Records of facility radiation and contamination surveys.
4.
Records of radiation exposure for all individuals entering radiation control areas.
5.
Records of the service lives of all hydraulic and mechanical snubbers listed on Tables 3.6.I(a) and 3.6.I(b) including e
date at which the service life commences and associated ins,alla-tion and maintenance records.
224
_.