ML20100D454
| ML20100D454 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/19/1985 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Philadelphia Electric Co, Public Service Electric & Gas Co, Delmarva Power & Light Co, Atlantic City Electric Co |
| Shared Package | |
| ML20100D456 | List: |
| References | |
| DPR-44-A-107, DPR-56-A-111 NUDOCS 8504020452 | |
| Download: ML20100D454 (22) | |
Text
.
..aiog jC UNITED STATES g
,y g
NUCLEAR REGULATORY COMMISSION 3
j WASHINGTON, D. C. 20555
's.,...../
PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.107 License No. DPR-44 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated September 14, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; s
C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuanca of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and j
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment.
.+
and paragraph 2.C.(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows-e 8504020452 850319 PDR ADOCK 05000277 P
2 Technical Specifications The Technical Specifications contained in Apperdices A and B, as revised through Amendment No.107 are hereby incorporated in the license. PECO shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR RE ULATORY COMMISSION Jo n F. Stolz, Chief 0 erating Reactors B nch #4 ivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 19,1985 m
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ATTACHMENT TO LICENSE AMENDMENT N0.107 FACILITY OPERATING LICENSE NO. OPR-44 DOCKET NO. 50-277 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
Remove Insert vii vii 234a 234a -
234b 234b 234c 234c 4
234d 234d 4
234e 234e 234f thru 234s 235a 235a 236b 236b
+
esp 9
s i
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.c.
PBAPS Unit 2 IJST OF TABLES Table Title Pace 4.8.3.c Maximum Values for Minimum Detectable 21Ed-6 Levels of Activity 3.14.C.1 Fire Detectors 240m 3.15 Seismic Monitoring Instrumentation 240u 3.15 Seismic Monitoring Instrumentation Surveillance 240v Requirements 1
Amendment No. YG7, MM,107 vii
(",d ted "rch'!?, '999),
e e
o e
pagyg LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.11.D. Shock Suppressors 4.11.D. Shock Suppressors (Snubbers) on Safety Related (Snubbers) on Safety Related Systems Systems 3.11.D.1 During all modes 4.11.D.1 of operation all snubbers on safety-related Snubbers required to be systems shall be operable operable under the provisions except as noted in of 3.11.D.1 shall be demonstrated 3.11.D.2 and 3.11.D.3 OPERABLE by performance of the below.
Snubbers on following augmented inservice non-safety related inspection program and the systems are excluded from requirements of Specif1-this requirement if their cation 4.6.G.
failure or failure of the system on which installed has no adverse effect on a safety-related system.
3.11.D'.2 During operation in the 4.11.D.2 cold shutdown or refueling modes, snubbers located on Snubbers required to be systems required to.be operable operable under the shall be operable except provisions of 3.11.D.1 as noted in 3.11.D.3.
shall be visually inspected according to the following schedule.
No. of Snubbers
'Next Visual Found Inoperable Inspection During Inspec-Period 3.11.D.3 With one or more tion Period snubbers inoperable under the requirements of 0
18 mo. + 25%
3.11.D.1, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, 1
12 mo. 1 254
~
replace or restore the 2
6 mo. f 254 inoperable snubber to the 3,4 4 mo.
2 mo. 1 25%
operable status and perform 5,6,7 1 25%
an engineering evaluation per 8 or more 1 mo. 3 254 specification 4.11.D.6.
If these requirements cannot be met, declare the supported The required inspection system inoperable and follow interval shall not be the applicable Limiting lengthened mare than one step condition for Operation for at a' time.
The provisions for that System.
extending surveillance frequency included in Section 1.0 Defini-tions do not apply.
Snubbers may be categorized in two groups,
" accessible or " inaccessible",
- 1 based on their accessibility for l
inspection during reactor operation. These two groups -
?
- may be inspected independently l
according to the above schedule.
l Amendment No. JJ,19J.107
-234a-
J I
PBAPS i
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.11.D.3 i
Visual inspection of snubbers j
required to be operable under l
the provisions of 3.11.D 1 shall verify that 1) there are i
no indications of damage or impaired operability, 2) attach-ments are secure, and 3) there i
is freedom of move ~ ment l
if this can be verified without disconnecting the snubber.
Snubbers which appear to be
' inoperable may be made oprable for the purpose of establishing the next visual inspection interval, providing that 1) the cause of the rejection is clearly established and remedied for that particular snubber and for other generically susceptable snubbers; and 2) the affected j
snubber is functionally tested in the as found condition and l'
determined operable per Specification 4.11.D.7 or 4.11.D.8, as applicable.
When
]'
the fluid port of a hydraulic anubber is found to be l
uncovered, the snubber shall be determined to be inop r(ble for
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the purpose of establishing the ll next visual inspection interval.
l 4.11.D.4 i
I Functional Test a) Once each operating cycle, during shutdown, a
(,
representative sample of 10% of i-each tne of (mechanical or I
hydraulic) snubber required to be operable under the provisions of 3.11.D.1 shall be functionally tested either in place or in a bench test.
For every unit found to be I
inoperable an additional 10% of that type of snubber shall be functionally tested until no 4
l more failures are found or all snubbers of that type have been tested.
The functional test Amendment No. 191, 107 requirements for mechanical
-234b-
~.
PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS snubbers will not take effect until the first refueling outage commencing one year after the issuance of Amendment No. 101/103 to the Technical Specifications, b) The representative sample selected for functional testing shall include various configurations, operating environments, sizes, and capacities of snubbers.
At least 25% of the sample shall include snubbers from the following categories:
1.-The first snubber away.from each reactor nozzle.
- 2. Snubbers within five feet of heavy equipment (valves, pumps, turbines, motors)
- 3. Snubbers connected to safety / relief valve discharge piping within 10 feet of the valve.
i c)
If any snubber selected for functional test either fails to lock up or fails to move, the cause shall be evaluated and if the failure is caused by manufacturing or design deficiency, all snubbers of the same design subject to the same defect shall be functionally tested.
This testing requirement is independent of the requirements above for snubbers not meeting the functional test acceptance criteria.
d)
Snubbers which are especially difficult to remove or are in high radiation areas l.
during shutdown (dose greater than 100 arem/ hour) shall be included in the representative sample except for those snubbers specifically exempted by the NRC.
4.11.D.5 In addition to the regular sample, snubbers required to be ktendment No. 191,107
-234c-
-f,IMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS of 3.11.D.1 which failed the l
previous functional test shall be ratested during the next testing cycle.
If such a failed snubber was replaced, both the replacement snubber and the repaired snubber (if it had been repaired and installed in another position) shall be ratested.
The test results of these snubbers may not be included for the resampling of 4.11.D.4.a.
4.ll.D.6 For snubbers required to be ope'rable under the provisions of 3.11.D.1 found inoperable, an engineering evaluation shall f
be performed to determine a) mode of failure, and b) if there is any adverse effect on the supported piping or components due to the snubb'er inoperability.
4.ll.D.7 Hydraulic Snubbers Functional Test Criteria:
i Functional test shall verify that:
1 a)
Restraining action is achieved within specified range of velocity or acceleration in both compression and tension.
b)
Snubber bleed rate is within the specified range in both tension and compression.
Snubbers specifically required not to displace under continuous load shall have this capability verified.
'I 4.ll.D.8 Mechanical Snubber Functional Test Criteria Functional tests shall verify thats a)
The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force.
Drag i
force shall not have Amendment No.19J,107
-234d-
' /
~
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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS increased more ttsn 50%
~
since the last functional test.
b)
Restraining Action is achieved within the specified range of velocity or acceleration in both tension and compression.
c)
Snubber release rate, where required, is'within the specified range in compression or tension.
Snubbers specifically required not to displace under continuous load shall have this capability verified.
4.11.D.9 Service Life Monitoring A record of the service life of each snubber required to be operable under the provisions of 3.11.D.1, the date of commencement of service life, (January 1,1978, unless otherwise specified) and the installation and maintenance records upn s
which the service life is based shall be maintained.
Once each operating cycle, these records shall be reviewed to verify that no snubber service life shall be exceeded prior to the next review.
If the service life will be exceeded then either recondition or replace the i
snubbers or re-evaluate the service life, d
i AmendmentNo,f97,107 t
-234e-
PBAPS 3.11 BASES Alternate Heat Sink The alternate heat sink Is provided as an alternate source of cooling water to the plants in the unlikely event of loss of the normal heat sink (Conowingo Pond) or the maximum credible flood.
For the condition of loss of the normal heat sink, the contained' volume of water (approximately 3.7 million gallons, which corresponds to a gauge reading of 17'T provides a minimum of seven days cooling water to both plants for decay heat removal.
The operability requirements for the alternate heat sink are specified in Specification 3.9.
C.
Emergency Shutdown Control Panels The Emergency Shutdown Control Panels are provided to assure the capability of taking the plants to the hot shutdown condition external to the control room for the unlikely condition that the control room.becomes uninhabitable.
D.
Shock Suppressors (Snubbers) on Safety Related Systems i
Snubbers are provided to ensure that the structural integrity of the reactor coolant system and all other safety-related systems are maintained during and following a seismic or other event initiating dynamic loads.
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 consequence of an inoperable snubber is an increase in the probability of structural damage to piping as a result of seismic or other event l
initiating dynamic loads.
It is therefore required that all anubbers necessary to protect the primary coolant system or l
any other safety system or components be operable during reactor operation.
Because the snubber protection is required only during low probability events a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for repairs or replacements.
A determined effort will be made to repair the snubber as soon as possible.
This allowable -
repair period is consistent with the allowable repair items e
of other safety related components such as RER pumps, HPCI subsystems, ADS valves and diesel generators.
An engineering analysis must be performed on aupported components when a snubber is datermined to be inoperable.
The purpose of this analysis is to assure that the supported components have not been damaged as a result of the snubber inoperability.
-235a-l Amendment No. 7@7.107 t
m.*
.._____-...m PBAPS Ten percent of each type (hydraulic or mechanical) of snubber on each unit shall constitute an adequate sample, t
High radiation areas (as defined in CFR 10 Part 20.202) means any crea, accessible to personnel,-in which there exists radiation at such Invals that a major portion of the body could receive, in any one hour, a dose in excess of 100 millirem.
Snubbers considered g
cspecially difficult to remove are those which because of size, l
weight, or geometry of installation require the use of unusual rigging equipment or arrangements for their removal, or require more than three hours of effort in their removal.
The service life of a snubber is monitored to assure that consideration is taken for the age of the expendable components.
The cervice life is based upon manufacturer's recommendation, service conditions, maintenance history, operating experience and test and inspection results.
When the review of service life records reveals that a snubber is nearing the end of its design service life, efforts are made to include that snubber in the next functional test cycle or
. the service life is reevaluated.
The purpose of the reevaluation is to extend the service life based upon experience and information gained during operations.
The results of functional testing and inspection may be used to alter the service lives of a21 snubbers of similar design operating under similar conditions.
4
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-236b-1 Amendment No. 797, 107
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UNITED STATES c
g NUCLEAR REGULATORY COMMISSION 3*.,
l WASHINGTON, D. C. 20555 SiQ*.C'4 $
p PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 111 License No. DPR-56 1.
The Nuclear Regulatory Comission (the Cortnission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. f the licensee) dated September 14, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),.
and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission;
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l C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and
~
l safety of the public, and (ii) that such activities will be conducted l
in compliance with the Comission's regulations;
^
t D.
The issuance of this amendment will.not be inimical to the comon defense and security or to the health and safety of the public,; and E.
The issuance of this amendment is in accordance w'ith 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
?.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this' license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows-l l
l
. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.111 are hereby incorporated in the license. PECO shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION r
Jo 1. Stolz, Chief Op rating Reactors B ch #4 vision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 19,1985
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1 ATTACHMENT TO LICENSE AMENDMENT NO.111 FACILITY OPERATING LICENSE NO. OPR-56 DOCKET NO. 50-278 ij Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
Remove Insert I
vii vii 234a 234a -
234b 234b 234c 234c 234d 234d i
234e 234e j
234f thru 234s 235a 235a
.. j 236b 236b
. i i
i I
4 8
O f
9
PBAPS Unit 3 I.IST OF TABI.ES Table Title Pace 4.8.3.c Maximum Values for Minimum Detectable 216d-6 e _
Levels of Activity 3.14.C.1 Fire Detectors 240m i
3.15 Seismic Monitoring Instrumentatiod 240u 4.15 Seismic Monitoring Instrumentation Surveillance 240v Requirements 2
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f e
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m N
I I
1 Amendment No. T M, 306 111 vii tea.ma r. :. :::, :=;
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PBAPS LIMITING CONDITIONS FOR OPERATION StiRVEILLANCE REQUIREMENTS 3.11.D. Shock Suppressors 4.11.D. Shock Suppressors (Snubbers) on Safety Related (Snubbers) on Safety Related Systems Systems 3.11.D.1 During all modes 4.11.D.1 of operation all snubbers on safety-related Snubbers required to be systems shall be operable operable under the provisions except as noted.in of 3.11.D.1 shall be demonstrated 3.11.D.2 and 3.11.D.3 OPERABLE by performance of the below.
Snubbers on following augmented inservice non-safety related inspection program and the systems are excluded from requirements of Specifi-
,i this requirement if their cation 4.6.G.
I failure or failure of the system on which installed has no adverse effect on a
'l safety-related system.
i.]
3.11.D'.2 During operation in the 4.11.D.2
'l cold shutdown or refueling
'j modes, snubbers located on Snubbers required to be
- 'a systems required to be operable operable under the
/:
shall be operable except provisions of 3.11.D.1 I
as noted in 3.11.D.3.
shall be visually inspected according to the following schedule.
No. of Snubbers Next Visual
- {
Found Inoperable Inspection During Inspec-Period 3.11.D.3 With one or more tion Period snubbers inoperable under the requirements of 0
18 mo. 1 25%
l 3.ll.D.1, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, 1
12 mo. 1 25%
replace or restore the 2
6 mo. 1 25%
' a, inoperable snubber to the 3,4 4 mo. 1 25%
'I operable status and perform 5,6,7 2 mo. 1 25%
i an engineering evaluation per 8 or more 1 mo. 1 25%
,l specification 4.11.D.6.
If l
- j these requirements cannot be i
met, declare the supported The required inspection 1
system inoperable and follow interval shall not be ni the applicable Limiting lengthened more than one step i
Condition for Operation for at a' time.
The provisions for that System.
extending surveillance frequency included in Section 1.0 Defini-1 tions do not apply.
Snubbers j
may be categorized in two groups,
" accessible or " inaccessible",
based on their accessibility for inspection during reactor operation. These two groups --
may be inspected independently according to the above schedule.
Amendment No. E, 77, $$, ML lli
-234a-4
PBAPS LI ITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.ll.D.3 Visual inspection of snubbers required to be operable under the provisions of 3.ll.D.1 shall verify that 1) there are no indications of damage or impaired operability, 2) attach-ments are secure, and 3) there is freedom of movement if this can be verified
~"
without disconnecting the snubber.
Snubbers which appear to be j
~
' inoperable may be made operable for the purpose of establishing the next visual inspection interval, providing that 1) the cause of the rejection is clearly established and remedied for that particular snubber and for other generically susceptable snubbers; and 2) the affected snubber is functionally tested in the as found condition and determined operable per Specification 4.11.D.7 or 4.ll.D.8, as applicable.
When the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be g
determined to be inoper(ble for the purpose of establishing the
?
next visual inspection interval.
4.ll.D.4 Functional Test a) Once each operating cycle, during shutdown, a representative sample of 10% of j
each type of (mechanical or hydraulic) snubber required to i
be operable under the i
provisions of 3.ll.D.1 shall be functionally tested either in place or in a bench test.
For
- y every unit found to be inopere.~ ole an additional 10% of that type of snubber shall be functionhlly tested until no e-mere failures are found or all snubSers of that type have been Amendment No. 7@),111 tested.
The functional test requirements for mechanical m
PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS snubbers will not take effect until the first refueling outage commencing one year after the issuance of Amendment No. 101/103 to the Technical Specifications.
b) The representative sample
~
selected for functional testing shall include various configurations, operating environments, sizes, and capacities of snubbers.
At least 25% of the sample shall include snubbers from the following categories:
- 1. The first snubber away.from each reactor nozzle.
- 2. Snubbers within five feet of heavy equipment (valves, pumps, turbines, motors)
- 3. Snubbers connected to safety / relief valve discharge piping within 10 feet of the valve.
c)
If any snubber selected for functional test either fails to lock up or fails to move, the cause shall be evaluated and if the failure is caused by manufacturing or design deficiency, all snubbers of the l
same design subject to the same defect shall be functionally l
tested.
This testing requirement is independent of l
the requirements above for l
snubbers not meeting the functional test acceptance I
criteria.
d)
Snubbers which are especially difficult to remove or are in high radiation areas during shutdown (dose greater i
than 100 mrem / hour) shall be included in the representative sample except for those snubbers specifically exempted by the NRC.
4.ll.D.5
{
In addition to the regular sample, snubbers required to be perable under the provisions Amenchent No. 79), 111
-234c-
PBAPS L'IMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS of 3.11.D.1 which failed the l
previous functional test shall be retested during the next testing cycle.
If such a failed snubber was replaced, both the replacement snubber and the repaired snubber (if it had been repaired and installed in another position) shall be retested.
The test results of these snubbers may not be included for the resampling of 4.11.D.4.a.
4.ll.D.6 4
For snubbers required to be operable under the provisions
~
of 3.11.D.1 found inoperable, an engineering evaluation shall be performed to determine a) mode of failure, and b) if there is any adverse effect on the supported piping or components due to the snubber l
inoperability.
4.11.D.7 Hydraulic Snubbers Functional Test Criteria:
Functional test shall verify that:
a)
Restraining action is achieved within specified range of velocity or acceleration in both compression and tension.
b)
Snubber bleed rate is within the specified range in both tension and compression.
Snubbers specifically required not to displace under continuous load shall have this capability verified.
4.11.D.8 Mechanical Snubber Functional Test Criteria:
Functional tests shall verify that:
a)
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 Amendment No. JN,111
-234d-
. - ~
~ - ~ ~ - ~
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS increased more than 50%
since the last functional test.
b)
Restraining Action is achieved within the specified range of velocity or acceleration in both tension and compression.
c)
Snubber release rate, where required, is'within the specified range in compression or tension.
Snubbers specifically required not to displace under continuous load shall have this capability verified.
4.11.D.9 Service Life Monitoring A record of the service life of each snubber required to be operable under the provisions of 3.11.D.1, the'date of commencement of service life, (January 1,1978, unless otherwise specified) and the installation and maintenance records upon which the service life is y
based shall be maintained.
Once each operating cycle, these records shall be l.
reviewed to verify that no snubber service life shall be e~xceeded prior to the next review.
If the service life will be exceeded then either recondition or replace the snubbers or re-evaluate the service life.
l i*
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i Amendment No. Jp),111 l
-234e-
PBAPS 3.11 BASES Alternate Heat Sink The alternate heat sink is provided as an alternate source of cooling water to the plants in the unlikely event of loss of l
the normal neat sink (conowingo Pond) or the maximum credible flood.
For the condition of loss of the normal heat sink, the contained' volume of water (approximately 3.7 million gallons, which corresponds to a gauge reading of 17'T provides a minimum of seven days cooling water to both plants for decay heat removal.
The operability requirements for the alternate heat sink are specified in Specification 3.9.
C.
Emergency Shutdown Control Panels The Emergency Shutdown Control Panels are provided.to assure the capability of taking the plants to the hot shutdown condition external to the control room for the unlikely condition that the control room becomes uninhabitable.
D.
Shock Suppressors (Snubbers) on Safety Related Systems Snubbers are provided to ensure that the structural integrity of the reactor coolant system and all other safety-related systems are maintained during and following a seismic or other event initiating dynamic loads.
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 consequence of an inoperable snubber is an increase in the probability of structural damage to piping as a result of seismic or other event initiating dynamic loads.
It is therefore required that all snubbers nec'essary to protect the primary coolant system or any other safety system or components be operable during j
reactor operation.
Because the snubber protection is required only during low 4
probability events a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for repairs or replacements.
A determined effort will be made to repair the snubber as soon as possible.
This allowable repair period is consistent with the allowable repair items of other safety related components such as RER pumps, HPCI subsystems, ADS valves and diesel generators.
l An engineering analysis must be performed on supported components when a snubber is determined to be inoperable.
l The purpose of this analysis is to assure-that the supported components have not been damaged as a result of the snubber
'inoperability.
.~
-235a-Amendment No. J@),111
,-------w-,ww,--.y-,-------,, -
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- - - -, - - - - - *..w
,--,-e-
- g., -, --- - ----
y e-----sr
PBAPS Ten percent of each type (hydraulic or mechanical) of snubber on each unit shall constitute an adequate sample.
High radiation areas (as defined in CFR 10 Part 20.202) means any crea, accessible to personnel,-in which there exists radiation at such levels that a major portion of the body could receive, in any one hour, a dose in excess of 100 millirem.
Snubbers considered g
~
ospecially difficult to remove are those which because of size, I
weight, or geometry of installation require the use of unusual rigging cquipment or arrangements for their removal, or require more than three hours of effort in their removal.
The s'ervice life of a-snubber is monitored to assure that consideration is taken for the age of the expendable components.
The tervice life is based upon manufacturer's recommendation, service conditions, maintenance history, operating experience and test and inspection results.
When the review of service life records reveals that a snubber is nearing the end of its design service life, efforts are made to include that snubber in the next functional test cycle or the service life is reevaluated.
The purpose of the reevaluation is to extend the service life based upon experience and information gained during operations.
The results of functional testing and inspection may be used to alter the service lives of all snubbers of similar design operating under similar conditions.
'j
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4
-236b-
- 9 Amendment No. 76,111 i
s.,....___