ML20083B266
| ML20083B266 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 09/04/1991 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20083B267 | List: |
| References | |
| NUDOCS 9109250012 | |
| Download: ML20083B266 (20) | |
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UNITED STATES i
i NUCLEAR REGULATORY COMMISSION b.
A f
WASHINGTON D C 20555 e
BALTIMORE, GAS,, App,ElECTRJC,Cpf,PMQ 00,C,K,ET, p0. 50-317 CALVERT CLIFFS !!UCLE AR Pp' PEP [t,Ap,T, ppjT,pp,1
$U.EppF,Ep,T,,T,0, f,A,CJ,L,1,T,Y, OPERATIflG LICENSE Amendtrent t;o.159 License flo. DPR-E3 1.
The t;uclear Regulatory Commission (the Commission) has found that:
A.
The applicatien for amendtrent by Ealtincre Gas and Electric Company (the licensee) dated May 24, 1991, and supplemented on July 1,1991, cortpliec with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission'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 Conmission; C.
There is reasonable assurance (i) 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 corpliance with the Commission's regulations; D.
The issuance of this amendtrent will rat be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendtrent is in accordance with IC CFR Part 51 of the Commission'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.(?) of Facility Operating License fio. OPP-53 is hereby amended to read as follows:
9109250012 910904 l
ADOCK 05000317 PDR PDR P
(2) T,e c,h,ni,c a,1 Sp,ec i f i ca t i on s The Technical Specifications contained in Appendices A bod C, as revised through Artendment ?!o.159, are hereby ircerporated in the license.
The licensee shall operate the f acility in accordance with the Technical Specifications.
3.
Tnis liccnse ar.endmen* is effective as of the date of its issuance and shall be irplemented within 30 days.
FOR THE t;UCLEAR REGULATORY C0ftlES10tl M c>ld 0 - OW Pobert A. Capra, Director Project Directorate 1-1 Disision of Reactor Projects - 1/11 Office of huclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
Sept ember 4,1991 l
'?
UNITED STATES i '
! i NUCLEAR REGULATORY COMMISSION 4
k\\ Ef,f VV ASHINGTON D C 20%5
%,......?
B AtT 1tJORE G,AS., App, g,ECT,Rj C, CDP,P,A!q 00g,ET,140.50-318 C ALVERT CLIFl S tiUCLEAR POWER PL A!41,,l'p,lT,140,, 2 At1Et 0tiEtiT TO FAClllTY Of ERATit1G LICEt4SE Amendment I;o. 139 Litense 140. DPR-C0 1.
The fluclear Regulatory Coneission (the Commission) has found that:
A.
The application for arendn'ent by Baltimore Gas and Electric Company (the licensee) dated iday 24, 1991 and supplemented on July 1,1991, conplies with the standards and requirec.ents of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter 1; C.
The f acility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the dctivities authorized by this anendr.ent can be conducted without endangering the health and safety of the public, and (ii) that such activities vill be conducted in compliance with the Concission's regulations:
D.
The issuance of this toendnent will rot be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this cmendnent is in accordance with 10 CFR Part 51 of the Concission's regulations and all applicable requiremerits have been satisfied.
2.
Accordingly, the license is amended by chcoges to the Technical Specifications as indicated in the attachmen* to this license amendment, and paragraph ?.C.? of Facility Operating License t;o.
CPR-f9 is hereby amended to read as follows:
2-(E) Techn,ica1 Sp,ecifications The Technical Specifications contained in Appendice, A ar.d B, as revised thrcu5h Artendn'ent No. I'9, are hereby ircerporated in the license. The licensee shall operate the f acility in accordance with the Technical Erecifications.
3.
This license amendrent is effective as of the date of its issuar,ce and 5
shall be iniplerented within 30 days.
FOR THE !!UCLEAR REGt'L ATORY COW 1 510ti NM 8, CW' Robert A. Capra, Director Project Directorate 1-1 Division of Reacter Projects - 1/li Of fice of flucleat Reactor Fesulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 4, 1991
ATTACH!'.Et4T TO LICENSE AliEtiDPEt:TS
_A!'[!@!'.E!i,T,li,0;,15,9,_f,A,C,1 L,1,Ty,,0f,E,P AT11:G L 1CE!4SE, ti,0_, DPR-53 AtiEtlDPEt;T t10.130 F AClllTY OPERATit:0 LJCEti,5,E,t10,. DPR-69
.D.O.C.K.E.T. tiO S. 5 0 -317..A.N.D 50- 318 Pevise Appendix A as follows:
Perove Pages Insert Pages 3/4 7-25 3/4 7-25 3/4 7-26 3/4 7-26 3/4 7-2Ec 3/4 7-26d B 3/4 7-5 B 3/4 7-5 B 3/4 7-6 B 3/4 7-6 B 3/4 7-7 B 3/4 7 7 F
1 s,
Y.
PtANT SYSTEM 1 3/4.7.8 SNUE[M
.UMITING JONDlUDRJOR OPERATID!L l
3.7.8.1 All safety related snubbers shall be OPERABLE.
APPLICABilllY: MODES 1, 2, 3 and 4.
on systems required OPERABLE in those MODES.)(MOD A,[J.193:
l
\\
t With one or more snubbers inoperable, within 72 h r restore or declare the supported system inoperable and fo eering l
ACTION statement for that system.
XVRYflLL3ELEEQl1LR[M1NTS 4.7.8.1 the following augmented inservice inspection program in requirements of Specification 4.0.5.
on to the of snubber shall mean snubbers of the same design and manufacturerA l
irrespective of capacity, Visual inspecti_oni a.
o Visual inspections shall be performed in accordance with the schedule determined by Table 4.7-3.
as inaccessible or accessible during reactor operation. Snubbers are cat of these categories (inaccessible and accessible)
Each determined by Table 4.7-3.
each population or category of snubbers shall be determinedT based upon the criteria provided in Table 4.7-3 and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before Amendment 159 1
Safety related snubbers include those snubbers installed on safet related systems and snubbers on non-safety related systems if their y
failure or the failure of the system on which they are installed would have an adverse effect on any safety related system A documented, visual inspection shall be sufficient to meet the requirements for an engineering evaluation.
needed, shall be completed in a reasonable period of timeAdditional analyses, as v
_y.
_ _ _ - ~ ~ " "
t l
PLANT SYSTEMS I
SURVEILLANCE REQUIREMENTS (Conthled)
Visual Insoection Accentance Criteria b.
Visual inspections shall verify (1) that there are 9 snubber installation exhibits no visual indications of Snubbers detachment from foundations or supporting structures.
i y
which appear inoperable as a result of visual inspect ons na be determined OPERABLE for the purpose of e rejection is clearly established, remedied and func.tioaally tested for that particular snubber and for other snubbers that is may be cenerically susceptible; or (2) the affected When the l
OPERABLE per Specification 4.7.8.1.d. as applicab snubber shall be determined inoperable unless it c establishing the next visual inspection interval.
For the snubber (s) found inoperable, an engineering evaluation shall be performed on the component (s) which are sup be consistent with the licensee's engineering judgment and uay the snubber (s).
be limited to a visual inspection of the supported The purpose of this engineering evaluation shall be to determine if the component (s) supported by the snubber (
component (s).
bber(s) were adversely affected by the inoperability of the of meeting the designed service.
[unctional Testi c.
At least once per 18 months during shutdown, a representative sample of 10% of each type of snubbers in use in the plant shall be functionally tested either in place or in a bench For each snubber that does not meet the functiona l
l acceptance criteria of Specification 4.7.8.1.d, test.*
have more f ailurcs are fcund or until all snubbers of that type been fenctionally tested.
be The Steam Generator snubbers 1-63-13 throu 1985.
Amendment No. EE/E HJE UJJE, E
3/4 7-26 159 1>
CALVERT Cliffs - UNIT 1
TABLE 4.7-1 SNyBBER VISVAl.
[NSPECTION
!!!TERVAL NUMBER OF INOPERABLE SNUBBERS Population Column A Column B Column C or Category Extend Interval Repeat Interval Reduce Interval (NqLes 1 and 2)
(Notes 3 and 6)
(Notes 4 and 6)
(Notes 5 and 6) 1 0
0 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 l
CALVERT CLIFFS - UNIT 1 3/4 7-25c Amendment No.159
IABLE 4.7-3 (Continue 41 TABLE NOTATION Note 1:
The next visual inspection interval for a snubber population or category size 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 categories may be examined separately or avintly.
However, the licensee must make and document that decision before any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.
Note 2:
Interpolation between population or category sizes and the number of inoperable snubbers is permissible.
Use next lower integer for the value of the limit for Columns A, 0, or C if that integer includes a fractional value of inoperable snubbers as determined by in' arpolation.
l Note 3:
If the numbe'
~
aoperable snubbers is equal to or less than the number. column A, the next inspection interval may be twice the previous 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 number in Column C but greater than the number in Calumn 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 difference between the number of inoperabic snubbers found during the previous interval and the number in Column B to the difference in the numbers in Columns B and C.
Note 6:
The provisions of Specification 4.0.2 are applicable for all inspection intervals up to and including 48 months.
CALVERT CLIFFS - UNIT 1 3/4 7-26d Amendment No. 159
PLANT SYSTEMJ MRS environment.
The operation of this system and the resultant effects on offsite dosage calculations was assumed in the accident analyses.
3/4.7.8 SNVBBERS All safety related snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all othar 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 non-safety related systems and then only if their f ailure 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 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 the previous inspection, the total population or category size, and the previous inspection interval.
Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible.
These categories may be examined separately or jointly.
However, that decision must be made and documented before any inspection and that decision shall be used as the basis upon which to determine the next inspection interval for that
- category, inspections perfermed before that interval has t. lapsed may be used as s new reference point to determine the next inspection. However, the results of such early inspections performed before the original required time interval has elapsed (nominai 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 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 snubbers are those which are (1) of a specific make or model, (2) of the same desig, and (3) similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration.
These characteristics of the snubber installation shall be evaluated to determine if further functional testing of similar snubber installations is warranted.
A snubber is considered inoperable if it fails to satisfy the acceptance criteria of the visual inspection. 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 adversely affected by the inopeiability of the snubber.
The engineering evaluation shall determine whether or not the snubber mode cf f.iilure has imparted a significant I
CALVERT CLIFFS - UNIT 1 B 3/4 7-5 Amendnent No. E,4/IJEll25,159
PLANT SYSTEMS BASES-effect or degradation on the supported component or system. Operation
~
may continue indefinitely if an engineering review and evaluation _ can document within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> that the equipment connected to the snubber can continus to perform its required function (s) with the snubber inoperable.
If the review and evaluation.cannot justify that the supported equipment will perform its required function (s), the equipment must be declared inoperableL and the applicable action requirements met.
The Specification allows inspection intervals to be compatible with a 24 month fuel cycle, up to and including an increase to every other refueling outage. To provide assurance of snubber functional reliability, a representative sample of the installed snubbers of each type
- will be functionally tested during plant shutdowns at 18 month intervals.
Observed failures of these sample snubbers shall require functional testing of additional units.
The service-life of a snubber is evaluated via manufacturer input and1 information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc...
.).
The requiiement to monitor the snubber service life is included to ensure that the_ snubbers periodically undergo
.a performance evaluation in view of their age and operating conditions.
The service life program is designed to uniquely reflect the conditions at-Calvert Cliffs.
The criteria for evaluating service life shall be determinea, and documented, by the licensee, Records will provide statistical bases for future consideration of snubber service life.
The requirements for the maintenance of records and-the snubber service life review are not intended to affect plant operation.
3/4,7.9 SEALED SOURCE CONTAMINATION The limitations on removable contamination for-sources requiring leak testing,-including alpha emitters, is based on_10 CFR 70.39(c) limits for plutonium.
This limitation will ensure that leakage from-byproduct, source, and special nuclear material sources will not exceed allowable i
intake' values.
3/4.7.10 WATERTIGHT DOORS 1
This specification is provided to ensure the protection of safety related equipment from the effects of water or steam escaping from ruptured pipes or components in adjoining rooms.
Small-bore (18") and large bore (>8") hydraulic snubbers are examples of different types of snubbers.
CALVERT CLIFFS - UNIT I B 3/4 7-6 Amendment No. 7E/EJ/Ef,159 l
~
PL ANT SYSTEMS BASES 3/4.7.11 FIRE SQPPRESSION 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 fire suppression system consists of the water system, spray and/or sprinklers, Halon 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 facility fire protection program, in the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service. Where a continuous fire watch is required in lieu of fire protection equipment and habitability due to heat or radiation is a concern, the fire watch should be stationed in a habitable area as close as possible to the inoperable equipment, in the event the fire suppression water system becomes inoperable, immediate 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 of the acceptability of the corrective easures to provide adequate fire suppression capability for the continued protection of the nuclear plant.
3/4.7.12 PENETRATION FIRE BARRIERS The functional integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility.
This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment.
The penetration fire barriers are a passive element in the facility fire protection program and are subject to pericdic inspections.
During periods of time when the barriers are not functional, a continuous fire watch is required to be maintained in the vicinity of the affected barrier until the barrier is restore to functional status.
1 CALVERT CLIFFS - UNIT 1 B 3/4 7-7 Amendment No. 2f/99/JJ/,159
~. ~. -
y..-
PLANT: SYSTQiS 3/4.7.8 SNUBBERS LIMITING CQNDITION FOR OPERATION l
ApPLICABillTY: MODES 1, 2, 3 ano 4.
(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.)
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 engineerir.g evaluation
- per Specification 4.7.8.1.b and c on the supported component or declare the supported system inoperable and follow the appropriate 4'
ACTION statement for that system.
EREEJLLMCLEEQUIREMENTS 4.7.8.1 Each snubber shall be demonstrated OPERABl E by performance of the following-augmented inservice inspection program in addition to the l
- requirements of Specification 4.0.5.
As used in this Specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity.
4.
Visual insoectipm Visual inspections shall br performed in accordance with the schedule determined by Table 4.7-3.
Snubbers are categorized as inaccessible or accessible during reactor operation.
Each of these categories (inaccessible and accessible) may be inspected independently or jointly according to the schedule determined by Table 4.7-3.
The visual inspection interval for each population or category of snubbers shall be determined based upon the criteria provided in Table 4.7-3 and the first inspection interval determined using this criteria shall be based upon the previous inspection' interval as established by the requirements in effect before Amendment 139, i
1 Safety related snubbers include those snubbers installed on safety related systems and snubbers on non-safety related systems if their failure or the failure of the system on which they are installed would have an adverse effect on any safety related system.
2 A documented, visual inspection shall be sufficient to meet the requirements for an engineering evaluation.
Additional analyses, as needed, shall be completed in a reascnable period of time.
l CALVERT CLIFFS - UNIT 2 3/4 7-25 Amendment No. J0/,4E/J00/JPE/JJ9, 139
[
I PLANT SYSTEMS lijRVEILLANCE RE0VIMMENTSlContinuedL b.-
Visual Insoection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, and (2) that the snubber installation exhibits no visual indications of j
detachment from foundations or supporting structures, Snubbers which appear inoperable-as a result of visual inspections may-be determined OPERABLE for the purpose of establishiag the next visual inspection interval, providing that (1) the cause=of the rejection is clearly. established, remedied and functionally tested for'that particular snubber and for other snubbers that
-may: be generically susceptible; or (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specification 4.7.8.1,d, as applicable. When the fluid, port of a hydraulic snubber is found to be uncove-ed, the snubber shall be determined inoperable unless. it can be determined OPERABLE via functional testing for the purpose of-establishing the next visual inspection interval.
For the snubber (s) found inoperable, an engineering evaluation' shall be performed on the compontat(s) which are supported by.
the snubber (s).- The scope of this engineering evaluation shall be consistent with the licensee's engineering judgment and may.-
be limited to a visual inspection of the supported component (s).
The purpose of this engir,eering evaluation shall i
be to determine if-the component (s) 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 4
of meeting the designed service.
j
}
c.
-Functional Tests a
At least once per 18 months' during shutdown, a representative sample of 10'4 of each type of snubbers in use in the plant shall be functionally tested either -inplace or in a bench
-test.
For each snubber that ioes not meet the functional-test acceptance criteria of Specification 4.7.8.1.d.-an additional
- 57. of that type snubber shall be functionally tested until no -
more-failures are found-or until all snubbers of that type.have.
been functionally tested.
0 Effective at 11:59 p.m. on May 17, 1989 or upon reaching 199.9 F average reactor coolant system (RCS) temperature during. initial RCS heatup following-the Unit 2 Cycle 9 refueling outage, whichever occurs first.
Replaces page 3/4 7-26(t).
CALVERT-CLIFFS UNIT 2 3/4 7 26 Amendment No. Jp/M/#/U/JpplJh 139
m 1
JMLL 4.74 S!n!MI1._Y15UlL_11LsP t C110tL.iti1LC.ML NUMBER OF INOPERADtE SNVBBERS Population Column A Column B Column C or Category Extend Interval Repeat Interval Reduce Interval
._ JNotes 1 pnd 2)
(Notes 3_and 6)
Olotes 4 c.nd 6)
(Notej 5 and 6) 1 0
0 1
60 0
0 2
100 3
1 4
150 0
3 8
200 2
S 13 300 5
12 25 400 8
18 36 500 12 24 48 750 20 40 78 1000 or greater 29 56 109 l
CALVERT CLIFFS - UNIT 2 3/4 7-26t Amendment No.139
IABLE 4.7-3 (Con 1109tdl TABLE N01AllD8 Note 1:
The next visual inspection inter"al for a snubber population or category size shall be determineu based upon the previous inspection interval and the number of inoperable snubbers found during that interval.
Snubbers may be categorized, based upo' their accessibility during power operation, as accessible or inaccessible.
These categories may be examined separately or jointly. However, the licensee must make and document that decision before any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.
Note 2:
Interpolation between population or category sizes and the number of inoperable snubbers is permissible. Use next lower integer for the value of the limit for Columns A, B, or C if that integer includes a fractional value of inoperable snubbers as determined by interpolation.
Nete 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 previous interval but not greater than 48 months.
Note 4:
If the number of inoperable snubbers is equal to or lest 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 inoptrable snubbers is equal to or greater than the number in Colt.mn C, the next inspection interval shall be two thirds of the previous 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 difference Detween the number of inoperable snubbers found during the previous interval and the number in Column B to the difference in the numbers in Columns B and C.
Note 6:
The provisions of Specification 4.0.2 are applicable for all 1
inspection intervals up to and including 48 months.
I
+
s CALVCRT CLIFFS - UNIT 2 3/4 7-26d Amendment No.139
PLANT SYS1fMS MSLS environment, lhe operation of this system and the resultant effects on offsite dosage calculatiors was assumed in the accident analyses.
3/4.7.8 SH@HES All safety related 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 initiating dynamic loads.
Snubbers excluded from this inspection program are those installed on non safety related syst2ms 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 snubber protection to systems.
Therefore, the required inspection interval varies inversely with the observed snubber f ailures and is determined by the number of inoperable snubbers found during the previous inspection, the total population or category size, and the s
previous inspection interval, i
Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible.
These categories may be examined separately or jointly.
However, that decision must be made and documented oefore any inspection and that decision shall be used as the basis upon which to determine the next inspection interval for that
- category, inspections performed before that interval has elapsed may be used as a new reference point to determine 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 inspecticn interval wil', override the previous schedule.
When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be q
puerically susceptible, and verified by inservice functional testing, that snubber may be exempted frbm being counted as inoperable.
Generically susceptible snubbers are those which are (1) of a specific make or model, (2) of the same design, and (3) similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration.
These characteristics of the snubber in$tallation shall be evaluated to determine if further functional testing of similar snubber installations is warranted.
A snubber is considered inoperable if it f ails to satisfy the acceptance criteria of the visual inspection.
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 adversely affected by the inoperability of the snubber.
The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a sign:ficant CALVERT CLlif S - UtHT 2 B 3/4 7-5 Amendment No ffl100lJ06,139
ELANI.11SluiS SMIS effect or degradation on the supported component or system.
Operation may continue indefinitely if an engineering review and evaluation an document within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> that the equipment connected to the snut r can continue to perform its required function (s) with the snubber inoperable.
If the review and evaluation cannot justify that the supported equipment will perform its required function (s), the equipment must be declared inoperable and the applicable action requirements met.
The Specification allows inspection intervals to be compatible with a 24 month fuel cycle, up to and including an increase to every other refueling outage.
To provide assurance of snubber functional reliability, a representative sample of the installed snubbers of each type
- will be functionally tested during plant shutdowns at 18 month intervals.
Observed failures of these sampie snubbers shall require functional testing of additional units.
The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installaticn and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature trea, etc..,,).
The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.
The service life program is designed to uniquely reflect the conditions at Calvert Citffs.
lhe criteria for evaluating service life shall be determined, and documented, by the licensee.
Records will provide statistical bases for future consideration of snubber service life.
The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.
311 7.9 SEALE_D jLOURCE C04TAtiUPT104 The limitations on removable contamination 'or sources requiring leak testing, inc'luding alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.
This limitation will ensure that leakage from byproduct, tource, and special nuclear material sources will not exceed allowable intake values.
3/4.7.10 WATERTIGHT DRORS This specification is provided to ensure the protection of safety related equipment from the effects of water or steam escaping from ruptured pipes or components in adjoining rooms.
Small bore (sB") and large bore (>B") hydraulic snubbers are examples of different types of snubbers.
CALVERT CLIFFS - UNIT 2 B 3/4 7-6 Amendment tio. JJ//3//E 139 i
11M1 SYSlBS M515 3/4. 7. ll f lR(_SVPPR(ISRdL11SlLMS The OPERAllllllY 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 fire suppression system consists of the water system, spray and/or sprinklers, Halon 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 facility fire protection program, in the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service. Where a continuous fire watch is required in lieu of fire protection equipment and habitability due to beat or radiation is a concern, the fire watch should be stationed in a habitable area as close as possible to the inoperable equipment.
In the event the fire suppression water system becomes inoperable, immediate 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 of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.
3/4,7,1L_E[tRTRAT10f4 flPE BADRl[R5 The functional integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility, lhis design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment.
The penetration fire barriers are a passive element in the facility fire protection program and are subject to periodic inspections.
During periods of time when the barriers are not functional, a continuous fire watch is required to be maintained in the vicinity of the affected barrier until the barrier is restore to functional status.
9LVERI CllffS - Uf411 2 B 3/4 7-7 Amendment tio JUEUM, D9
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