ML20086C003
| ML20086C003 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 11/18/1991 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20086C005 | List: |
| References | |
| NUDOCS 9111210308 | |
| Download: ML20086C003 (15) | |
Text
,
.~.
'o, UNITED STATES
't NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20$55
\\ *****/
B_ALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 1 AMENDMENT __TO FACILITY OPERATING LICENSE
- Amendment Wo.165 License No. DPR-53 1.
The Nuclear Regulatory Ccmission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (thelicensee)datedAugust 27, 1991, complies 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 Comission; 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 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 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-53 is hereby amended to read as follows:
9111210308 91111D PDR ADOCK 05000317 P
a c
4 2
s t
(2) Technical-Specifications The Technical Specifications contained in Appendices A and B, as _ revised through Amendment No.165, are hereby incorporated in the-license.
The Itcensee shall i
. opera e-the facility in accordance with the Technical t
Specifications.
- 3.-
This license amendment is effectiva as of the date of its issuance and-shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMIS510N RU T-Wl Robert A. Capra, Director Project Directorate I-I Division of Reactor Projects - I/II.
Office of Nuclear Reactor Regulation t
Attachment:
iChanges.to_the Technical
. Specifications
- Date of Issuance: Evember 18, 1991 t
b 1
9
+
l-i-
o
~
D-a v..v e e
-e,
.,r e
.-,.e
- w1-
_. _. - _. _ _ _ _ _ _ m _.. _ _ _ _ _ _ _ _ ~ _. _ _.~. - _ _. _._ _ _. _ _ _ _. _
[po otory o
UNITE D cTATEs
['
g NUCLEAR RFGULATORY COMMISSION 7,,
s WASHING TON. D. C. 20f>66 c, *****/
e i
BALTIMORF GAS AND ELECTRIC COMPANY DOCKET No. 50-?l8 j
CALVERTCLIFF)NUCLEARPOWERPLANT,UNITNO.?
AMENOMENT TO FACILITY CPERATING LICENSE Amendment No. 145 License No. OPR-69 1.
TheNuclearRegulatoryCommission(theCommission)hasfoundthat:
A.
The application for amendment by Baltimore Gas and Electric Company (thelicensee)datedAugust 27, 1991, complies with the standards and
-requirements of the Atomic Energy Act of 1954, as amended (the Act)-
and the Comission's rules a id regulat.ons set forth in 10 CFR Chapter Is B..
The facility will operate in conformity with the appitcation, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that-the activities authorized l
by this amendment can be conducted without endangering the health and safety-of-the public, and (ii) that such activities will be conducted in cunpliance with the Comission's regulations; O.
The issuance of this amendment will not be inimical to the' common defense and security or to the health and safety of the public; and 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 satisfieo.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license i
amendment, and paragraph 2.C.2 of Facility Operating License No.
DPR-69 is hereby amended to read as follows:
P P
.a
-., w, - - -
.,_.~ -.-
- = - - -.. -
2 (2) Technical SEecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.145, are herety incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be irnplemented within 30 days.
FOR THE NUCLEAR REGUl.ATORY COMMISSION
% & Os0 h Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: November id, 1991
r ATTACHMENT TO LICENSE AM,ENDMENTS AMENDMENT _NO. 165 FAClllTy OPERATING LICENSE NO. DPR-53 AMENDM,ENT NO. 145 FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NCS. 50-317 AND 50-318 Revise Appendix A as follows:
Remove Pages insert Pages 3/4 7-26 3/4 7-26 3/4 7-26a*
3/4 7 26a*
3/4 7-26b 3/4 7-26b B3/4 0-3 B3/4 0-3 B7/4 7-6 B3/4 7-6
- PG 3/4 7-26a did not change for OPR-53, but was an overleaf. The page did charge for DRP-69.
PLAtiL1YJJJJiS SMEE1LLANCLAIOVLRUiUG1Emt11md b.
Visual Insotetion AcceptanrJ Criterig 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 detachment from foundations or supporting structures.
Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing 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 uncovered, 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 component (s) which are supported by the snubber (s).
The scope of this engineering evaluation shall be cunsistent with the licensee's engineering judgment and may be limited tu a visual inspection of the supported component (s).
The purpose of this engineering evaluation shall be to determine if the component (s) supported by the snubber (s) were :dversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service.
Eqn tional Tests c.
a At least once per REFUELING INTERVAL, a representative sanple l
of 107, of each type of snubbers in use in the plant shall be functionally tested either in place or in a bench test.* For each snubber that does not meet the functional test acceptance criteria of Specification 4.7.8.1.d, an additional St. 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.
The Steam Generator snubbers 1-63-13 through 1 63-28 need not be functionally tested until the refueling outage following June 30, 1985.
I CALVERT CLIFFS UNIT 1 3/4 7-26 Amendment No. EE/EMJph/JEl JEN 165
ElANT SYS1Etil t
il)RVElttANCE E M MELMENTS ([ontinu d)
Snubbers identified as "Especially Difficult to Remove" or in l
"High Exposure Zones" shall.lso be included in the l
representative sampic.*
In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period.
If a spare snubber has been installed in place of a i
failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested during the next test period.
Failure of these snubbers shall not entail functional testing of additional snabbers.
If any snubber selected for functional testing either fails to lock up or falls to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency l
all generically susceptible snubbers of the same design subject to the same defect shall be functionally tested.
This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance
- criteria, for the snubber (s) fuund inoperable, an engineering evaluation shall be performed on the component (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 engineering evaluation shall 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 of meeting the designed service.
d.
Hydraulic Snubbers Fu gtiqngl Test Acceptance Criteria The hydraulic snubber fonctional test shall verify that:
l.
Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
2.
Snubber bleed, or release rate, where required, is within the specified range in compression or tension.
For
+
snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
Permanent or other exemptions from functional testing for individual snubbers _in these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performeo to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.
CALVERT Ci.!FFS --UNIT l-3/4 7-26a Amendment No. JM125
PLANT SYSTEM,1 SUkVEILLANr.E RE0VIREMENTS (Continued) o e.
Inybber Service Life Monitorina A record of the service life of ecch sr.ubber, the date at which the designated service life commences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.m.
At least once per REFUELING INTERVAL **, the installation and l
maintenance records for each safety related snubber shall be reviewed to verify that-the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled-snubber service life review.*
If the indicated service life will be exceeded prior to the ner.t scheduled snubber service life review, the snubber service life shall be reevaluated or the snubber shall be-replaced or reconditioned so as to extend its _ service life beyond the date of the next scheduled _ service life review.- This reevaluatioti, replacement, or reconditioning shall be indicated in the records.
The provisions of Specification 4.0.2 are applicable.
-The first snubber service life review following Amendment No.165 shall be performed within 18 months
- of the previous review.
CALVERT CLIFFS
-UNIT 1 3/4 7 26b Amendment No. E//JpJ/J2El165
APPLICABILITY BASES mean that for one division the emergency power source must be OPERARLE (as must be the components supplied by the emergency power source) and all redundant systems, subsystems, trains, components and devices in the other division must be OPERABLE or likewise satisfy Specification 3.0.5 (i.e., be capable-of performing their design functions and have an i
emergency power source OPERABLE).
In other words, both emergency power sources must be OPERAi!LE and all redundant systems, subsystems, trains, components and d1 vices in both divisions must also be OPERABLE.
If these conditions are not satisfieo, action is required in accordance with this e
specification.
t In MODES 5 or 6 Specification 3.C.5 is not applicable, and thus the individual ACTION statements for each applicable Limiting Condition for Operation in these MODES must be adhered to.
4.0.1 This-specification provides that surveillance activities necessary to insure the Limiting Conditions for Operation are met an't will be performed during the OPERATIONAL MODES or other conditions for which the Limiting Conditions for Operation are applicable.
Provisions for additional surveillance activities to be performed without regard to
~ the applicable OPERATIONAL MODES or other conditions are provided in the individual Surveillance Requirements.
Surveillance Requirements for Special Test Exceptions need only be performed when the Special test Exception is being utilized as an exception to an individual specification.
4.0.2 This specification establishes the limit for which the specified time lnterval for Surve111anco Requirements may be extended.
It permits an allowable extension of the norni surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance, e.g., transient conditions or other ongoing surveillance or maintenance activities.
It also:provides flexibility to accommodate the length of a fuel cycle for surveillances that are specified to be performed at least l
once each REFUELING INTERVAL.
' t is nM intended that this provision be l
used repeatedly as a convenience te extend surveillance intervals beyond that specified for. surveillarmes that are not performed once each REFUELING INTERVAL.
Likewise, it is Mt the intent that REFUELING INTERVAL surveillances be performed during power operation unless it is l
consistent with safe plant operation.
The limitation of Specification I
4.0.2 is based on engineering judgment and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveilland llequirements.
This provision is sufficient to ensure that the rel, ability ensured thrnugh surveillance activities is not significantly degrn'ed beyond that L
obtained from the specified surveillance interval, l
l
- CALVERT CLIFFS - UNIT 1 B 3/4 0-3 Amendment flo. EJ/UJ/JEp/165 l I.
-ywa--e*e.paceap+p y
yq t qy F-
,ysppyy-g eyp. q-ne
--pp.w-e
,-m,-
-oy
--,--Mp, ppyqw9aqpepg
.,&rrgy-yyem4.-wmp..3.-m--g-ng m y y-.y
--.9 mg=T.&9' W
9 4-W--
c 1
W'
-**7"'*
f ptANT SYSTEMS fLAXE 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 cor.nected to the snubber 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 mtt.
The specification allows inspection intervals to oe 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 REFUELING l
IN1ERVALS. Observed failures of these sample snubbers shall require I
functional testing of additional units.
The service life of a snubber is evaluated vig manufacturer input and information through consideration of the snubber service conditions and associated installation rnd maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, 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 Cliffs.
The 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 rnview are not intended to affect plant operation.
3/4.7.9 ji[MD JQURCL CONTAMINATION The limitation on removable contamination for sources requiring leak 4
testing, including alphe 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 intake values.
. 3/4.7.10 WATERTIGHT D0 ORS 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.
l L
l I
Suall bore-(18") and large bore (>8") hydraulic snubbers are examples of different types of snubbers.
CALVERT CLIFFS - UNIT 1 B 3/4 7-6 Amendment No. 26/6/M//#/165
PLANT SYSTEMS i
JSRVElliANCERl0VIREMEN1SjContinued) b.
Visual inspection Acceptance Criteria
[
Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABilllY, and (2) that the snubber installation exhibits no visual indications of detachment from foundations er supporting structures.
Snubbers which apnear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing 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 uncovered, the snubber shall be determined inoperable unless it can be determined OPERABLE via functional testing for the purpose of establi;hing the next visual inspection interval.
for the snubber (s) found inoperable, an engineering evaluation shall be performed on the component (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 engineering evaluation shall be to determine if the component (s) su) ported by the snubber (s) were adversely affected by the inopera)ility of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service, c.
Functional Tests At least once per REFUELING INTERVAL, a representative sample l
of 10% 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 does not meet the functional test acceptance criteria of Specification 4.7.8.1.d, an additional 5% 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, t
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.
Replacespage3/47-26(t).
i CALVERT CLIFFS - UNIT 2 3/4 7 26 Amendment No. IS/JE//#/lJ/JpJ/
lil/l)PA 145
-.-,-,,s.-
-,--v.--
---.m y.-.
.,.,_,,m,...w.m.,wm..-..,-
,--,.r
.i._....,,,-,
,_~
.,n~._,,,m,--_.r e,-.
w._y.,yg y
,,m,..g,m----.
p.,.
l 2
I I
[
EL&NT SYSTDQ SURVElllAEEEQREt1 ELL (aplineD Snubbers identified as "Especially Difficult to Remove" or in "High Exposure Zones" shall also be included in the representative sample.*
In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period.
If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested during the next test period.
Failure of these snubbers shall not entail functional testing of additicnal snubbers.
If any snubber selected for functional testing either fails to lock up or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency
-all generically susceptible snubbers of.the same design subject to the saae defect shall be functionally tested. This testing requirement shall be inuependent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.
For the snubber (s) found inoperable, an engineering evaluation shall be performed on the component (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 engineering evaluation shall 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 componsnt remains capable of meeting the designed service, d.
Hydraulic Snubbers fonctional Test Acceptance Criteria The_ hydraulic snubber functional test shall verify that:
1.
Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
I Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only
.if a-justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion:of their fabrication or at a subsequent date.
CALVERT CLIFFS - UNIT 2 3/4 7-26a Amendment No. JE//fMPE/ 145
= - a..
=
PLANT SYSTEMS SURVElLLANCE REQUIREMENTS (Continued) 2.
Snubber bleed, or release rate, where required, is within the specified range in compression or tension.
For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
e.
Enuhber Service Life Monitorina A record of the service life of each snubber, the date at which the designated service life commences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.m.
At least once per REFUELING INTERVAL **, the installation and l
maintenance records for each safety related snubber shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review.*
If the indicated service-life will be exceeded prior to the next scheduled snubber service life review, the snubber service life shall be reevaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review.
This reevaluation, replacement, or reconditioning shall be indicated in the records.
The provisions of Specification 4.0.2 are applicable.
The first. snubber service life review following Amendment No.145 shall be performed within 18 months
- of the previous review, t
CALVERT CLIFFS - UNIT 2 3/4 7-26b Amendment No. JE//E//J/JEE/145 2-
4 APPLICABILITY BASES mean that for one division the emergency power source must be OPERABLE (as must be the components supplied by the emergency power source) and all redundant systems, subsystems, trains, components and devices in the other division must be OPERABLE or likewise satisfy Specification 3.0.5 (i.e., be capable of performing their design functions and have an energencypowersourceOPERABLEj.
In other vords, both emergency power sources must be OPERABLE and al. redundant systems, subsystems, trains, components and devices in both divisions must also be OPERABLE.
If those conditions are not satisfied, action is required in accordance with this specification.
In MODES 5 or 6 Specification 3.0.5 is not applicable, and thus the individual ACTION statements foi Mch applicable Limiting Condition for Operation in these MODES must be adhered to.
4.0.1 This specification provides that surveillance activities necessary to insure the Limiting Conditions for Operation are met and will be performed during the OPERATIONAL MODES or other conditions for which the Limiting Conditions for Operation are applicable.
Provisions for additional surveillance activities to be performed without regard to the applicable OPERATIONAL MODES or other conditions are provided in the individual Surveillance Requirements. Surveillance Requirements for Special Test Exceptions need only be performed when the Special Test Exception is being utilized as an exception to an individual specification.
4.0.2 This specification establishes the limit for which the specified time interval for Surveillance Requiren.ents may be extended.
it permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance, e.g., transient conditions or other ongoing surveillance or maintenance activities, it also provides flexibility to accommodate the length of a
- fuel cycle for surveillances that are specified to be performed at least l
once each REFUELING INTERVAL.
It is not intended that this provision be I
used repeatedly as a convenience.to extend surveillance intervals beyond that specified for surveillances that are not performed once each REFUELING INTERVAL.
Likewise, it is not the intent that REFUELING INTERVAL surveillances be performed ouring power operation unless it is consistent with safe plant operation.
The limitation of Specification 4.0.2 is based on engineering judgment and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements.
This
- provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond'that obtained -from the specified surveillance interval.
CALVERT CLIFFS - UNIT 2 B 3/4 0-3 Amendment No. M/J///U2/145
1 PLANT SYSTEMS EASES 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 continue to perform its required function (s) with the snubber inoperable, l
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 REFUELING INTERVALS. Observed failures of these sample snubbers shall require Junctional testing of additional units.
The service life of a snubber is evaluated via roanufacturer input and information through considoration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replachd, in high radiation area, in high temperature area, 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 Cliffs.
The 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.
J 3/4.7.9 SEALED SOURCE CONTAMINATION The limitation 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 intake values, i
l 3/4.7.10 WATERTIGHT D0 ORS 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.
l Small bore (18") and large bore (>G") hydraulic snubbers are examples of different types of snubbers.
~CALVERT CLIFFS - UNIT 2 B 3/4 7-6 Amendment No. JJ/f)//E/JJ9/145 l'
1l.~
z.--.
-. - - - ---= - - -
=~-
,,