ML20091P533
| ML20091P533 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/15/1992 |
| From: | Larkins J Office of Nuclear Reactor Regulation |
| To: | Entergy Operations |
| Shared Package | |
| ML20091P534 | List: |
| References | |
| DPR-51-A-156, GL-90-009, NPF-06-A-129 NUDOCS 9202030153 | |
| Download: ML20091P533 (23) | |
Text
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MGERGYOPERATIONS,INC3 DOCKETNO.(0313 ARKANSAS NUCLEAR ONE, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.156 License No. DPR-(1 1.
The Nuclear Regulatory Commission (the Cenissien) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated October 15, 1991, complies with the standards and requirenents of the Atomic Energy Act of 1954, as amended (the Act),
and the conmission's rules and regulations set forth in 10 CFR i
Chapter In B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Connission; C.
There is taasonable assurance:
(1) that the activities authori:ed by this amendnent can be condaleted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Conmission's regulations; D.
The issuance of this license amendment will not be inimical to the et,mmon defense and security or to the health and safety of the public; and E.
The issuance of this emendment is in accordance with 10 CFR Part 51 of the Cormission's regulations and all applicable requirements have been satisfied.
920203C153 92011S PDR ADOcK 05000313 P
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2 2.
Accordingly, the lictnse is atended by changas to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. DPR-51 it hereby arwnded to reed as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Anendnont No.156, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license atendnent is effective as of 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION a+
John T. Larkins, Director Project Directorate IV-1 Division of Reactor Projects 111, IV, and V Office of Huclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 15, 1992
6 ATTACINENT TO LICEt$E AMENDMENT NO.156 FACILITY OPERATING LICENSE t;0. DPR.51 DOCKCT NO. E0 313 Revise the following pages of the tppendix "A" Technical Specifications with the attached paget.
The revised peges are ider,tified by Arnendment numbcr and contein vertical lines indicating the area of change.
REMOVE PAGES INSERT PAGES vi vi 001 0 01 110e 110e 110f 110f 1109 2 110g.2 1109 3 1109 4
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4.18.i UPPER TUDE 8tiEET VIEW OF SPECIAL GROUPS PER SFECIFICATION 110o2 4.18.3.a.3
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Amendtent N). 86. E5, #, 156 v1
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3.16 Shock Suooressors (Snubbers)
Agglicability This technical specification applies to all shock suppressors (snubbers).
The only snubbers excluded from this requirement 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 on any safety-related system.
Obiective To assure adequate shock suppression protection for primary coolant system piping and any other safety related system or component under dynamic loads as might occur during an earthquake or severe transient, while allowing normal thermal motion during startup and shutdown. This is done-by assuring the operability of those shock suppressors installed for that purpose.
Soeciffention 3.16.1 With one or more applicable snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> either:
a.
Replace or restore tha inoperable snubbers to an OPERABLE status and perform an engineering evaluation of the attached components per Specification 4.16.1.f or, b.
Perform a review and evaluation which justifies continued l
operation with the inoperable snubber (s) and perform an engineering. evaluation of the attached component (s) per Specification 4.16.1.f or, c.
Declare the attached system inoperable and follow the appropriate ACTION statement for that system.
BAA L Shock suppressors are designed to prevent unrestrained pipe motion. under y
dynamic. loads at might occur during an earthquake or severe transient, while alloring nc; mal thermal motion during startup and shutdown. The consequence of an inoperable shock suppressor is an increase in the probability of structural damage to piping as a result of a seismic or other event initiating dynamic loads.
It is therefore required that all l
shock suppressors' required to protect the primary coolant system or any
(
other safety system or compenent be operable during reactor operation.
L L
Because the shock suppressor protection is required only during low L
proLability 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, replacements or evaluations.
If a reveiw and evaluation of an INOPERABLE snubber is preformed and documented to justify continued operation, and providod all design criteria are met with the INOPERABLE snubber, then the INOPERABLE snubber would not need to be restored or replaced.
In case a sbutdown 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 l-condition will permit an,
irly shutdown consistent with standard operating L
-precedures.
Amendment No. 23, EA, 199, 156 661
.?
4
4.16 SHOCK SUPPRESSORS (Snubbers)
Anolicability This technical specification applies to all shock suppressors (saubbers).
The only snubbers excluded from this requirement are those installed on nonsafety-related systems and then only if their failure er f ailure of the system on which they are installed would have no adverse effect ua any safoty-related system.
Obiective Verify an acceptable level of operability of the shock suporessors protecting the primary system and any other safety-related system or component.
Soetificatiga 4.16.1 The following surveillance requirements apply to all appliceule chock suppressor=.
a.
Insocetion Typea As used in this specification, type of snubber shall mean snuboers of the same design and manufacturer, irrespective of
- capacity, b.
Visual Insnectigns
-Sn>;5bers may be categorized as inaccessible or accessible during reactor operation. Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4.16-1.
The visual inspection interval for each category of snubber shall be determined based upon the criteria provided in Table 4.16.1.
e Amandmert No. 23, EA, Jf t, 3 56 110e
c.
ylsual Inspection Acceptance Criteria Visual inspectioas shall verify (1) that there are no visible indications of damage or impaired operability, and (2) attachments to the foundation or supporting structure cre functional and (3) f astners for the attachment of the snubber to the component and to the snubber anchorage are functional.
~
Snubbers which appear inoperable as a result of visual inspections shall be classified as INOPERABLE and may be reclassified 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 snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition and determined operable per Specifications 4.16.1.d or 4.16.1.e, as applicable.
However, when the fluid port oi a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable and cannot be determined opcrable ~ia functional testing for the purpase of establishing the next visual inspection interval. All snubbers connected to a common hydraulic fluid reservoir shall be evaluated for operability if any snubber connected to that reservoir is determined to be inoperable.
d.
[ynctional Tears At least once each refueling shutdown a representative sample of snubbers shall be tested using the following sample plan.
At least 10% of the snubbers required by Specification 3.16.1 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 4.16.1.e, an additional 10% of the snubbers suall be functionally tested until no more failures are found or until all snubbers have been functionally tested.
The representative samples for the functional test sample plans shall be randomly selected from the snubbers required by Specification 3.16.1 and reviewed before beginidng thu The review shall ensure as far as practics1 that test
..g.
they are representative of the various configurations, operating environments, range of sizes, and capacities.
Snubbers placed in the same locations as snubbers which failed the previous functional test shall be retested at the time uf the next functional test but shall not be included in the rample plan.
If during the function 91 testing, add 3tional sampling is required due to failure of only one type of snubber, the functional testing results shall be reviewed at that time to determine if additionsl samples should be limited to the type of snubber which nos failed the functional testing.
AmerAment No. 23, 74, 156 110f 2
s TABLE 4.16-1 ESUBBER VISUAL INSPICTION INTERVAL NUMBER OF INOPERABLE SFUBBERS Population Column A Column B Column C per Category Excend Interval Repeat Interval Reduce Interval (Notes 1 and 2)
(Notes 3 and 6)
(Notes 4 and 6)
(Notes 5 and 6) 1 3
0 1
80 0
0 2
100 0
1 4
150 0
?
8 200 2
5 13 300 5
12 25 400 8
18 36 500 12 24 48 750 20 40 78 1000 or greater 29 56 109 Note 1: The next visual inspection interval for a snubber category shall be determined based upon the previous inspection interval and the number of INOPERABLE snubbers found during that interval.
Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible. These categoriet may be examined separately or jointly. However, categories must be determined and documented before any inspection and that determinatici. shall be the basis upon which to determine the next inspection interval for that category.
Note 2: Interpolation between population per category and the number of INOPEPABLE anubbers is permissible. Use next lower integer for the value of the limit for Columns A, B, and C if that integer includes a fractional value of INOPERABLE snubbers as deter:=ined by interpolation.
156 Amendment No.
110g-2 J
-. - -. ~...
TABLE 6.16-1 (Cont inuedl t
SNU3BER VISUAL INSPECTION INTERVAL Note 3: If the_ number of INOPERABLE snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previo'is interval but not greater than 48 months.
Note 4: If the number of INOPERABLE snubbers is equal to or less than the number in Column B but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.
Note 5: If the number of INOPERABLE snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval.
However, if the number of INOPERABLE snubbers is less than the nunber in Column C but greater than the number in Column B, the next interval shall be reduce 1 proportionally by interpolation, that is, the previous interval shall be reduced by a factor that is one-third of the ratio of the difference between the number of INOPERABLE snubbers found during he previous interval and the number in Column B to the dif ference in the. numbers in Column r and C.
Note 6: Specified surveillance intervals may be adjusted plus or minus 25 percent to accommodate normal test and surveillance schedule intervals up to and including 48 months, with +.he exception that inspection of inaccessible snubbc.rs may be deferred to the next shutdown when plant conditions allow five days for inspection.
See Note 7 for definition of interval as eoplied to anubber visual inspections. The provisions of Specificatien 4 regarding surveillance intervals are not applicable.
Note 7: Interval as defined for the shock suppressors (snubbers) visual inspection surveillance requirements is the period of time starting when the unit went into cold ahutdown for refueling, and ending when the unit goes into cold shutdown for its next scheduled refunling.
This period of time is nominally considered to be an 18 month period, or a 24 month period based on the type
(
of fuel.being used. However, the period of time (interval) could be shorter or longer due to plant operating variables such as fuel life and operating performance.
l l
l l
l Amendment Ei.
156 110g-3
4 BASES
- All safety related snubbers are required to be operatle to enen a that the structural integrity of _ the reactor coolant system and all other safety related systems is _ maintair.ed during and following a selsnic or-other -
- )
event initiating 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 on'any safety related system.
The vistal inspection f requency is based upon maintaining a constant level of snubber protection to plant systems.
Therefore, the required inspection: interval' varies based upon the number of INOPERABLE snubbers found during _ the previous inspection in proportion to the sizes of the
- various snubber populations or categories and the previous inspection interval as specified.in NRC Generic Letter 90-09,." Alternative Requirements For_ Snubber Visual Inspection Intervals and Corrective Actions".
Inspections performed before that-fnterval has elapsed may be i
used as 4 new-reference point to determine the next inspection.
However.
the result, of such' early inspections _ performed before the original i
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 schedule.
When tha cause of the rejection of a snubbor is learly established-and remedied for that snubber and for any other enubbers 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 c.~ a specific make or model and have the same design features directly related to rejection of 1the snubber by visual inspection, or are similarly-located or exposed to the same1 environmental conditions such as temperature, radiation and vibration.
'When a snubber is found inoperable, an engineering ovaluation-is-fperformed,: in addition to the determination of the snubber mode of failure, in order to determine if any safety _related ccaponent or system has been adversely affected by anoperability of the snubber. The engineering evaluation'is performed to determine whether or not the snubber mode of failure has imparted. a significant effect or degradation on the supported component or system.
Iffs review-and' evaluation of an INOPERABLE snubber is. performed and documented to justify; continued operation, and provided that all design.
criteria ~are met with.che INOPERABLE snubber, then the INOPERABLE snubber-
~
would:not need' to be restored or replaced.
110 -4 l-
' Amendment No. 54, 156 8
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NUCLEAR REGULATORY COMMISSION 0, h WASHINGTON. D C. 20066 g '.v
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ENTERGY OPERATIONS, INC.
C0CKET NO. 50-3f>8 ARKANSAS NUCLEAR ONE, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.129 License No. NPF-6 The Nuclear Regulatory Comission (the Commission) has found that:
A.
The applicaties for amendment by Entergy Oparations, Inc.
l (the licensee) dated October 15, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission't 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 C,e Comission; C.
There is reasonable assurance:
(i) that the activitier 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 issuance of this license amendment will not be-inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance cf this amendmert is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
l l-l l
l
2.
Accordingly, the license is atended 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.
NPF-6 is hereby amended to read as follows.
(2) Technical Specifications The Technical Specifications contained in Appendix A., as revised through Amendment No.129 are hereby incorporated in the license.
The licensca shall operate the facility in accordance with the Technical Specifications.
3.
The license am.'ndment is effective as of 30 days f rom the date of issuance.
FOR THE NL' CLEAR REGULATORY COMMISSION John T. Larkins, Director Project Directorate IV-1 Division of Reactor Projects III, IV, and V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical l
Specifications Date of Issuance: January-15, 1992 L
P l
j.
1 4
ATTACHMENT TO LICENSE AMENDMENT NO. 3pq FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Revise the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document
- completeness, REMOVE PAGES INSERT PAGES 3/4 7-22 3/4 7-22 S/4 7-23 3/4 7-23 3/4 7-23c 3/4 7-23d B 3/4 7 5 8 3/4 7 5 9
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4 4
ARKANSAS - UNIT 2 3/4 7-21
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- PLANT SYSILES 3/4.7.8 SHOCK SUPPRESSORS_(SNUBBERSJ LIMITING CONDITION FOR OPERATION 3.7.8 All snubbers shall be OPERABLE.
The only snL5sers excluded f rom this requirement are those installed on nonsafety-related systems and then only if their failure or failure of the systea on which they are installed, would have no adverse effect on any safety-related system.
APPLICABILITY:
MODES 1, 2, 3 and 4.
MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.
ACTION:
With one or more applicable snubber inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> either:
a.
Replace or restore the inoperable snubber (s) to an OPER.'.BLE
~
status and perform an engineering evaluation of the attached component (s) per Spec!.fication 4.7.8.f or, b.
Perform a reviev and evalua. ion which justifies continued operation with the inoperable snubber (s) and perform an engineering evaluatic" of the attached component (s) per Specification 4.7.8.f or, c.
Declare the attached system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REOUIREMENTS 4.7.8 Each applicable snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection prograr. and the requirements of Specification 4.J.S.
a.
Insoection Tynes
~
As used in this specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of
- capacity, b.
Visual Insoections Snubbers may be categorized as inaccessible or accessible during reactor operation.
Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by fable 4.7.8-1.
The visual inspection interval for each category of snubber shall be determined based upon the criteria provided in Table 4.7.8-1.
o ARKANSAS UNIT 2 3/4 7-22 Amendment No. 62,72,JJ3, 129 l
4 PLANT SYSIDiS SURVEILLANCE REOUIREMENTS (Continued) e l
c.
Yltnal Insoection Acceptance Criteria Visual inspections shall verify that (1) there are no visible indications of damage or impaired OPERABILITY, and (2) attachments to the foundation or supporting structure are functional and (3) fastnets for the attachment of the snubber to the component and to the snubber aachorage are functionel.
Snubbers which appear inoperable as a result of visual inspections shall be classified as INOPERABLE and may be reclassified OPERABLE for the purpose of establishing the next visual inspection interval, previding that (1) the cause of the rejection is clearly established and re:.edied for that particular snabber and for other snu'obers that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specifications 4.7.8.d or 4.7.8.e, as applicable.
However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall ba determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.
All snubbers connected to a common hydraulic fluid reservoir shall be evaluated for operability if any snubber connected to that reservoir le determined to bo inoperable, d.
Functienal Tests At least once each refueling shutdown a representative sample or snubbers shall'be tested using the following sample plan.
At least 10% of the snubbers required by Specification 3.7.8 shall be functionally tested either in place or in bench test.
For each snubber that does not meet the functional test acceptance criteria of Specification 4.7.8.e, an additional 10%
of the snubbers'shall be functionally tested until no moru failures are found or until all snubbers havs neen functionally tested.
The representative samples for the functional test sample plans shall be randomly selected from the snubbers required by Specification 3.7.8 and reviewed before beginning the test'",.
The review shall ensure as far as practical that they are representative of the various configurations,-operating environments, range of sizes, and capaciti'es.
Snubbers placed in the same locations as snubbers which failed the previous functional test shall be retested at the
- ARKANSAS - UNIT 2 7-23 Amendment No. 62, 129-a
l l
1 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued',
time of the next functional test but shall not be included in the sample pla'n.
If during the functional testing, additional sampling is required due to failure of only one type of snubber, the func-tional testing results shall be reviewed at that time to detemine if additional samples should be limited to the type of snubber which has failed the functional testing, e.
Functional Test Acceotance Criteria The snubber functional test sha'il verify that:
Activation (restrainirg action) is achieved within the speci-fied range in both tension and compression, except that inertia dependent, acceleration limiting mechanical snubbers may be tested to verify only that activation takes place in both directions of travel; 2)
Snubber bleed, or release rate where required, is present in both tension and compression, within the specified range; 3)
Where required, the force required to initiate or maintain motien of the snubber is within the specified range in both directir m of travel; and 4)
For snuobers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement.
Testing methods may be used to measure parameters indirectly or i
parameters other than those specified if those results can be cor-related to the specified paramsters through established methods.
f.
Functional Test Failure Analysis An evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause of the failure.
~
The results of this evaluation shall be used, if applicable, in selecting snubbers to be tested in an effort to determine the OPERABILITY of other snubbers irrespective of type if they may be subject to the same failure mode.
For the snubbers found inoperable, an engineering evaluatior, shall be performed on the components to which the inoperable snubbers are attached. The purpose of this engineering evaluation shall be to determine if the components to which the inoperable snubbers are attached were adversely affected by the inoperability of the snubber in order to ensure that the component remains capable of meeting the designed service.
ARKANSAS - UNIT 2 3/4 7-23a Amendment No.
62
PLAMT SYSTEMS SyRVEILLANCE REQUIREMENTS (Continued)
If any snubber selected for functional testing either fails to activate or fails to nove, i.e., frozen-in-place, the cause will be evaluated and, if caused by manufacturer or design deficiency, all snubbers of the same type subject to the same defect shall be evaluated in a manner to ensure their OPERABILITY. This require-ment shall be independent of the requirements stated in Specifica-tion 4.7.S.d for snubbers not meeting the functional test acceptance criteria.
g.
Preservice Testing of Pepatred, Replacement and New Snubbers Preservice operacility testing shall be performed on repaired, replacement or new snubbers prior to installation. Testing may be at the manufacturer's facility.
The testing shall verify the functieaal test ac:eptance criteria in 4.7.8.e.
In addition, a prer2rvice inspection shall be perfonned'on each repaired, replacement or new snobber ar.d shall verify that:
1)
There are no visible signs of damage or impaired operability as a result of storage, nandling or installation; j
2)
The snubbc-load rating, location, orientation, position setting and configuration (attachments, extensions, etc.),
are in accordance with design; 3)
Adequate swing clearance is provided to allow snubber movement; a)
If applicable, fluid is at the recommended level and fluid is not leaking from the snubber systemt 5)
Structural connections such as pins, bearings, studs, fasteners and other connecting hardware such.as lock iats, tabs, wire, and cotter ains are installed correctly.
h.
Snubber Seal Replacement Progiam The seal service life of hydraulic snubbers shall be monitored to ensure that the service life is not exceeded between surveillance inspections. The expected service life for the varicus seals, seal materials, and applications shall be determined and established based on engineering information and the seals shall be replaced so that the expected service life will not be exceeded during a period when the snubber is required to be OPERABLE. The seal r2 placements shall be documented and the docucantation shall be retained in accordance with Specification 6.10.2.
i ARKANSAS-UNIT 2 3/4 7-23b Amendment No.
62 a
TABLE 4.7.8-1 SNUBBER VISUAL INSPECTION INTERVAL t
NUMBER OF INOPERABLE SNUBBERS Population Column A Column B Column C e,r C=+cgory Extend Interval Repeat Interval Reduce Interval (Notes 1 and 2)
(Notes 3 and 6)
(Notes 4 and 6)
(Notes 3 and 6) 1 0
O 1
80 0
0 2
100 0
1 4
150 0
3 8
200 2
5 13 300 5
12 25 400 8
18 36 500 12 24 48 750 20 40 78 1000 or greater 29 56 109 Note 1: The next visual inspection interval for a snubber category shall be determined based upon the previous inspection interval and the number of INOPERABLE snubbers found during that interval.
Snubbers may be categorized, based upon their accessibility during power operat 2n, as accessible or inaccessible. These categories may be examinei separately or jointly. Ilowever, cater;ories must be determined and documented before any inspection and that determination shall be the basis upen which to determine the next inspection interval for that category.
Note 2: Interpolation between population per category and the number of INOPERABLE snubbers is permissible. Use next lower integer'for the value of the limit for Columns A, B, and C if that integer includes a fractional value of INOPERABLE snubbers as determined by interpolation.
ARKANSAS - UNIT 2 3/A 7-23e Amendment No. 129
. = _
4 ZABLE 4.7 R-J (Continymd]
i SNUBBER VISUAL INSPECTION INTERVAL Note 3: If the number of INOPERABLE snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the j
previous interval but not greater than 48 months.
l Note 4: If the number of INOPERABLE snubbers is equal to or less than the number in Column B but greater than the number in Column A, che next inspection interval shall be the same as the prevsoun interval.
Note 5: If the number of INOPERABLE snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two-thirdr. of the prev' us interval.
However, if the number of INOPERABLE snubbers is less than the number in Column C but greater than the number in Column B, the next interval shall be reduced proportionally by interpolation, that is, the previous interval shall be reduced by a factor that is one-third of the ratio of _ the dif ference between the number nf INOPERABLE snuhbers found during the previous interval and the number in Column D to the difference in the numbers in Column B and C.
Note 6: Specified surveillance intervals may be adjusted plus or minus 25 l
percent to accommodate normal test and surveillance schedule 4,ntervals up to and including 48 months, with the exception that inspection of inaccessible snuhbers may be deferred to the naxt i
shutdown when plant conditions allow five days for inspection.
See Note 7 for definition of interval as applied to snubber visual inspections. The provisions of Specification 4.0.2 regarding surveillance intervals are not applicabl6.
Note 7: Interval as deiined for the shock suppressors (snubbers) visual inspection surveillance requirements is the period of time starting when the unit went into cold shutdown for refueling, and ending when the unit goes into cold shutdewn for its next scheduled refueling.
This period of time is nominally considered to be an 18 month period, or a 24 month period based on the type g
j of fuel being used.
However, the period of ti:ne (interval) could be shorter or longer due to plant operating variables such as fuel i
life and operating performance.
4 ARKANSAS - UNIT 2 3/4 7-23d Amendment No.129
t TABLE 3.7-4 SAFETY RELATED HYORAULIC SNUBBERS (DELETED)
ARKANSAS - UNIT 2 3/4 7-24 (NEXT PAGE 3/4 7-26)
AMENDMENT NO. 72.
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PLANT SYSTIBS BASES following all credible accident conditicus.
The OPERABILITY of this system in conjunction with contaal room design trovisions is based on limiting the radiation exposure to personnel occupying the control toom to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of General DeLign Criteria 19 of Appendix "A",
10 CFR 50, 3/4.7.8 SHOCK SUPPRESSORS (SNUBBERS)
All snubbers are required OPERABLE to ensure that the structura'i integ-ity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating 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 on any safety-related system.
The visual inspection frequency is based upon maintaining a constant level of snubbet protection to systems. Therefore, the required inspection interval varies based upon the number of INOPERABLE anubbers found during the previous inspection in proportion to the 412es of the various snubber populations or categories and the previous inspection interval es speciflod in NRC Ganeric Letter 90-09, " Alt arnative Requirements For Snubber Visuel Inspection Intervals and Corrective Actions".
Inspections performed before that interval has elapsed may be used as a new reference point to datermine the next inspection. Howrver, the result of such early-inspections >arformed before the original required time in*.erval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval, Any inspection whese results require a shorter inspection intervai will override the previous schedule.
When the cause of the rejection of a snubber is clearly ectablished and remedied for that snubber and foi any other snubbers that may be generically susceptible and verified by inservice functional testing, that anubber 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 sne'er by visual inspection, or are similarly located or exposed to the same env.'ronmental conditions such as temperature, radiation and vibration.
-When a anubber is found inope'able, an enginerring evaluation is performed, in addition to the determination of the stabber mode of f ailure.
in order to determine if any saf ety-related component or system has been adversely affected by the inoperability of the snubber.
The engineering
- evalut. tion is performed to determine whether or not the snubber mode of fa!!ure has imparted a significant effect or deg.adation on the supported component or system.
If a review and evaluation of an INOPERABLE snubber is performed and documented to justify continued operation and prov!ded that all design criteria are met tr!b the INOPERABLE snubber, then the INOPERABLE snubber would not need to be.nstored or replaced ARKANSAS - UNIT 2 B 3/4 7-5 Amendment No. 62,129
PLANT SYSTEMS BASES To provide further assurance of snubber reliability, a represea+a-tive sample of the installed snubbers will be functionally tested during plant shutdowns at 18 month intervals.
These tests will include stroking of the snubbers to verify proper piston movement, lock-up and biced. Observed failures of these sample snubbers will require functional testing of additional units. To minimize personnel exposures, snobbers installed in areas which have high radiation fields during shutdown or in especially difficult to remove locations may be exempted from these functionti testing requirements provided the OPERABILITY of these snubbers was demonstrated during functional testing at either the completion of their febrication or at a subsequent date.
3/4.7.9 SEALED SOURCE CONTAMINATION _
The limitations on removable centanination for sources requirin leak testing, including alpha emitters, is based on 10 CFR 70.39(c) g limits for plutonium. This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.
_3/4.7.10 FIRE SUFPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in-any portion of the facility where safety related equipment is located. The fi e suppression system consists of the water system, spray and/or sprinklers, and fire hose stations. The collective capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the f acility fire protection program.
In the event the portions of the fire suppression cystems are ino~perable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service.
In the event the fire suppre'sion water system becomes inoperable, innediate corrective measures must be taken since this system provides the major fire suppression capability of the plant.
The requirement for a twenty-four hour report to the Commission provides for prompt evaluation l
of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.
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