ML19345G777
| ML19345G777 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 04/07/1981 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML19345G776 | List: |
| References | |
| TAC-43606, NUDOCS 8104220302 | |
| Download: ML19345G777 (9) | |
Text
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O RANCHO SECO UNIT I TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.12 SNUBBERS All snubbers listed in Table 3.12-1 shall be OPERABLE.
Acolicability When the reactor system is at HOT SHUTDOWN, HOT STANDBY, STARTUP or POWER OPERATION. During COLD SHUTDOWN snubbers located on systems required to be OPERABLE for nuclear safety.
Action With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.14.c en the supported component or declare the supported system inoperable and follow the appropriate specification statement for that sy s t e'm.
Bases Snubbers are designed to prevent unrestrained pipe motion under dynamic loads as might occur during an earthquake or severe transient, while allowing normal thermal motion during startup and shutdown. The conse-quence of an inoperable snubber is an increase in the probabilit/ of structural damage to piping as a result of a seismic or other event initiating dynamic loads.
It is therefore required that all snubbers required to arotect the primary coolant system or any other safety system or component be operable during reactor operation.
1 PROPOSEDONLY l
NOTYETufflWL l
3-51 Proposed' Amendment No. 75 8104220802
4
- 6 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation TABLE 3.12-1 SAFETY RELATED HYDRAULIC SNUBBERSA Accessible or Snubber System Snubber installed inaccessible I.D. No.
On, Location and Elevation **
(A or 1)
MS-20528-SW-1 MSS, TB, 13' A
MS-20521-SW-11 MSS, TB, 13' A
MS-20520-SW-3 MSS, TB,13' A
MS-20521-SW-13 MSS, TB, 13' A
MS-20520-SW-5 MSS, RBY,'13' A
MS-20521-SW-14 MSS, RBY, 13' A
MS-20520-SW-13A MSS, RBY, 4' A
MS-20520-SW-6 MSS, RBY, 36' A
MS-20526-SW-9 MSS, RBY, 36' A
9-SW-30709o3A MSS, TB, 20' A
9-54-30708-4 M55, TB, 29' A
9-SW-30708-5A MSS, TB, 23' A
9-SW-39709-4 MSS, TB, 23' A
9-SW-30709-3 MSS, TB, 30' A
5-SW-20530-7A MSS, RBY, 30' A
5-SW-20529-3A MSS, TB, 39' A
5-SW-53520-3 HVS, RBY, 20' A
5-SW-32141-1A FWS, RBY, 20' A
5-SW-32141-2 FWS, RBY, 26' A
10-SW-20530-3A MSS, TB, 35' A
12-SW-20530-3A MSS, TB, 26' A
7-SW-32120-1B FWS, RBY, 14' A
7-SW-32120-1A FWS, RBY, O' A
7-SW-32120-1C FWS, RBY, 2' A
MS-20550-SW-1 MSS, RBY, 16' A
MS-20558-SW-1 MSS, RBY, 17' A
MS-20532-SW-1 MSS, RBY, 15' A
MS-20531-SW-1 MSS, RBY, 16' A
7-SW-32140-2 FWS, RBY, 16' A
4-SW-20523-5A SFC, AB, ~36' A
4-SW-20523-8A SFC, AB, ~37' A
PROPOSEDONLY
=* YET utr;.m:. f!
Proposed Amendment No. 75
- a.si
s~
e RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation TABLE 3.12-1 (Continued)
SAFETY RELATED HYDRAULIC SNUBBERS
- Accessible or System Snubber Installed inaccessible I.D. No.
On, Location and Elevation **
(A or I) 4-SW-26022-13A DHS, AB, -6' A
4-SW-23620-3A SIM, AB, -7' A
4-SW-53520-3 HVS, AB, 23' A
1-SW-10-B&W-5 RCS, RBISS, 2' l
1-SW-10-B&W-6 RCS, RBISS, 2' i
1-SW-10-B&W-7 RCS, RBISS, 2' I
1-SW-20025-3 RCS, RDISS,
-2' i
1-SW-20025-1A RCS, RBISS,
-2' i
OHS, RBOSS, -15' I
1-SW-26020-5A 1-SW-26524-4A CFS, RBISS, -15' i
1-SW-50060-8A NSW, RBOSS,
-2' I
1-SW-22000-9 PLS, RBOSS, -14' i
1-SW-26021-5A OHS, RBOSS, -15' i
1-SW-26021-7A DHS, RBOSS, -15' i
1-SW-26021-11A DHS, RBOSS, -15' i
1-SW-50063-2A NSW, RBOSS, -8' i
1-SW-23823-8 SIM, RBISS, 3' i
i 1-SW-23620-15A SIM, RBISS, 12' 1-SW-23625-3A SIM, RBISS, 4' I
I 1-SW-29122-28A CBS, RBOSS, 38'.
CBS, RBOSS, 34' I
1-SW-29125-7A i
1-SW-29125-7C CBS, RBOSS, 37' I
MS-20523-SW-2 MSS, RBOSS, 25' I
MS-20521-SW-17 MSS, RBOSS, 25' 1
1-SW-29125-9A CBS, RBOSS, 35' I
1-SW-50050-2A NSW, RBOSS, 36' I
MS-20520-SW-18 MSS, RBOSS, 25' l
l MS-70522-SW-2 MSS, P. BOSS, 25' i
1-SW-50060-3A NSW, RBOSS, 36' i
1-SW-32140-4 FWS, RBOSS, 3' i
1-SW-32140-2 FWS, RBOSS, 7' i
1-SW-32141-4 FWS, RBOSS, 3' i
1-SW-32141-2 FWS, R60SS, 7' I
l-5W-50053-2A NSW, RBOSS, -8' I
3-51b l Im
2 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation TABLE 3.12-1 (Continued)
SAFETY RELATED HYDRAULIC SNUBBERS
On, location and Elevation **
(A or I) 10-SW-20553-1A MSS, TB, 26' A
5-SW-20529-1A MSS, TB, 35' A
5-SW-20529-4A MSS, RBY, 41' A
5-SW-20530-8 MSS, RBY, 28' A
7-SW-30800-6 MSS, RBY, 25' A
7-SW-3 0800-8 MSS, RBY, 25' A
7-SW-30800-12 MSS, RBY, 38' A
7-SW-30800-14 MSS, RBY, 41' A
7-SW-30804-1 MSS, RBY, 28' A
7-SW-30805-2 MSS, RBY, 28' A
4-SW-60014-4A RCD, TB, -30' A
1-SW-22000-12 PLS, RBOSS, -19' l
1-SW-22000-2A PLS, RBISS, -15' i
1-SW-22001-2 PLS, RBOSS, -19' i
1-SW-21007-7 SIM, RBISS,
-2' i
1-SW-21022-5 RCS, RBISS, 0.5' I
(
1-SW-21006-6A SIM, RBISS, 3' i
1-SW-23626-1A SIM, RBISS, S' I
1-SW-21022-1 RCS, RBISS, 11' i
1-SW-21021-3 RCS, RBISS, 15' i
1-SW-23823-7A SIM, RBISS, -5' i
1-SW-21025-9A RCS, RBISS, -3' I
l 1-SW-21005-8 RCS, RBISS,
-2' I
1-SW-23822-78 SIM, RBISS, 8' i
1-SW-21028-2 RCS, RBISS, 16' I
1-SW-2602C-6A OHS, RBOSS, -16' i
1-SW-20082-12A SFC, RBOSS, -14' i
1-SW-26521-2A CFS, RBISS, -14' i
-2' 1-SW-23823-13A SIM, RBISS, S' i
1-SW-21501-20 SIM, RBISS, 13' I
1 -SW-21501 - 28 SIM, RBISS, 7' l
1-SW-50050-6A NSW, RSOSS, -5' i
SS-17 RCS, RBISS, 6' I
SS-22 RCS, RBISS, 6' I
PROPOSEDONLY 3-51c NOTYETOFMA.
RANCHO SECO Uh.T 1 TECHNICAL SPECIFICATIONS l
Limiting Conditions for Operation
[
l TABLE 3.12-1 (Continued)
{
i SAFETY RELATED HYDRAULIC SNUBBERS
- l Snubbers may be added to safety related systems wit'iout prior License Amend-ment to Table 3.12-1 provided that a revision to Table 3.12-1 is included with the next License Amendment request.
- Snubber Location Key AB Auxiliary Building CBS Containment Building Spray System CCW Component Cooling Water CFS Core Flood System DHS Decay Heat System FWS Feedwater System HVS Heating / Ventilating /Ai r Conditioning System PLS Purification and Let-down System MSS Main Steam System NSW Nuclear Service Cooling Water RBISS Reactor Building - Inside Secondary Shield RBOSS Reactor Building - Outside Secondary Shield RCD Reactor Cooiant Drain System RCS Reactor Coolant System RBY Reactor Building Yard l
SFC Spent Fuel Cooling System SIM Seal injection and Make-up System TB Turbine Building l
l l
PROPOSEDONLY
,.,,d NOT YET Uff1
- - - - ~
RANCHO SECO UNIT 1 TECHNICAL SPECIFICtTIONS Surveillance Standards 4.14 SNUBBERS Each snubber shall be demonstrated OPERABLE by performance of the following:
a.
Visual Inspections The first inservice visual inspection of snubbers shall be performed after four months but within 10 months of commencing POWER OPERATION and shall include ell snubbers listed in Table 3.12-1.
If less than two (2) snubbers are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months + 25% from the date of the first inspection.
Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule:
No. Inoperable Snubbers Subsequent Visual per Inspection Period Inspection Period
- O 18 months + 25%
1 12 months T 25%
2 6 months T 25%
3,4 124 days T 25%
5,6,7 62 days T 25%
8 or more 31daysE25%
The snubbers may be categorized into two groups: Those accessible and those inaccessible during reactor operation. Each group may be inspected independently in accordance with the above schedule.
b.
Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indica-
% 'N tions of damage or impaired OPERABILITY, (2) attachments to the N
foundation or supporting structure are secure, and (3) in those O
locations where snubber movement can be manually induced without Q
disconnecting the snubber, that the snubber has freedom of movement and is not frozen up.
Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of g;
estabiishing the next visual inspection interval, providing that g
(1) the cause of the rejection is clearly established and remedied pO M for that particular snubber and for other snubbers that may be
- d D 5 -4mm) generically susceptible; and (2) the affected snubber is functionally bh M C3 % *The inspection interval shall not be lengthened more than one step at a time.
k 4-47 E
Proposed Amendment No. 75
r RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards tested in the as found condition and determined OPERABLE per Specifi-fication 4.14.d.
However, when the fluid reservoir of a hydraulic snabber is found to be empty, the snubber shall be determined inoperable and may be determined OPERABLE via functional testing for the purpose of establishing the n' ext visual inspection interval. All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.
c.
Functional Tests At least once per 18 months during shutdown, a representative sample (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 acceptance criteria of Specification 4.14.d. an additional 10% of that type of snubber shall be functionally tested).
The respresentative sample selected for functional testing shall include the various configurations, operating environcents and the range of size and capacity of snubbers. At least 25% of the snubbers in the representative sample shall include snubbers from the following three categories:
1.
The first snubber away f rom each reactor vessel nozzle
,,gg 2.
Snubbers within 5 feet of heavy equipment (valve, pump, bg turbine, motor, etc.)
_] wn 7"7*7*5rs /2,j7) 3 Snubbers within 10 feet of the discharge from a safety
- mt-mui relief valve C36%.
l 3,&,.
Snubbers identified in Table 3 12-1 as "Especially Difficult to Remove" in "Hign Radiation Zones During Shutdown" shall also be included in j@ {Q or 4,3,,g the representative sample.*
Table 3 12-1 may be used as the basis for the sampling plan.
g;f} :
m 8"N ' hj In addition to the regular sample, snubbers which failed the previous unrs5
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functional test and were reinstalled shall be restested during the test period if the cause of failure is due to environmental condi-
{l"")?mmum next tions or the cause of failure is undetermined. Test results of these 42gsm j snubbers may not be included for the re-sampiing.
- Permanent or other e::emptions f rom functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their' fabrication or at a subsequent date.
4-47 a Proposed Amendment No. 75
r RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all snubbers of the same design subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.
For the snubber (s) found inoperable, an engineering evaluation shall be,serformed on the components which are supported by the snubber (s).
and have undergone a transient which would require them to perform their intended functions. The purpose of this enoineerina evaluation shall be to determine if the components supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meetina the designed service.
d.
Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:
1.
Activation. (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
2.
Snubber bleed, or release rate, where required, is within the specifled range in compression or tension. For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
e.
Snubber Service Life Monitoring The installation and maintenance records for each snubb3r shall be maintained as required by Specification 6.10.2.m.
At least once per 18 months, the installation and maintenance records for each snubber listed in Table 3.12-1 shall be reviewed. Each snubber shall be evaluated and replacement or reconditioning shall be performed as requi red.
This reevaluation, replacement, or recon-ditioning shall be indicated in the records.
1 4-47b g YET OFF M L Pr-sed Ame-e t No m 1
e l
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards i
Bases All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiatir; dynamic loads. Snubbers excluded from this inspection program are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect an any safety-related system.
The visual Inspection frequency is based upon mair*,aining 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.
Inspections performed before that interval has elapsed may be used as a new reference point to deter-mine the next inspection. However, the results of such early 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 achedule.
W1en 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 inoperable. Generically susceptible snuobers 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, or are similary located or exposed to the same evnironmental conditions such as temperature, radiation, and vibration.
When a snubber is found inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, in order to determine if any safety-related component or system has been adversly affected j
i by the inoperability of the snubber. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.
The reouirement to monitor the snubbar maintenance records is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide the bases for future l
consideration of snubber service life. The requirements for the mainterance of records and the snubber service life review are not intended to affect plant
{
operation.
PROPOSEDDM
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4-47 c Proposed Amendment No. 75 i
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ADMINISTRATIVE CONTROLS b.
Records of new and Irradiated fuel inventory, fuel transfers and assembly burnup histories, j
Records of facility radiation and contamination surveys.
c.
d.
Records of radiation exposure for all individuals entering radiat ion cont rol areas.
e.
' Records of gaseous and liquid radioactive material released to the environs.
f.
Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.
Records of training and qualification for current members of the g.
l plant operating staff.
h.
Records of in-service Lnspections performed pursuant to these Technical Specifications.
2
- i. Records of Quality Assurance activities required by the QA Manual.
J.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59 k.
Records of meetings of the PRC and the MSRC.
1.
Records for Environmental qualification which are covered under the provisions of paragraph 6.14 Records of the maintenance of all hydraulic snubbers listed in m.
Table 3.12-1.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent I
l with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 - Deleted PRDPDSEDDU Proposed Amendment No. 75
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