ML20064H546
| ML20064H546 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  (NPF-037, NPF-066, NPF-072, NPF-077) |
| Issue date: | 03/11/1994 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20064H550 | List: |
| References | |
| GL-90-009, NPF-37-A-060, NPF-66-A-060, NPF-72-A-048, NPF-77-A-048 NUDOCS 9403180058 | |
| Download: ML20064H546 (28) | |
Text
.
g* *%g
. '.7. -
UNITED STATES
[ [ihf..i NUCLEAR REGULATORY COMMISSION g
f WAsNNGToN. O C. FR 0001 COMMON)lEALTH EQ1 SON COMPANY DOCKET NO. STN 50-_454 BYRON STATION. UNIT NO 1 MiENDHENT TO FACILITY 0.ffRATING LICENSE Amendment No. 60 License No. NPF-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated August 27, 1993, as supplemented February 21, 1994, 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 Commission; 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 compliance with the Commission's regulations; D.
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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of facility Operating License t-NPF-37 is hereby amended to read as follows:
9403180058 940311
{DR ADOCK 05000454 PDR:
c.,
~.
E 14 (2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 60 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION AklL f.
ll0V ames E. Dyer, Director Project Directorate 111-2 Division of Reactor Projects - Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
March 11, 1994
t,'$pa %qI\\
UNITED STATES j, k 0 [. }
NUCLEAR REGULATORY COMMISSION
'jj{s f
WASHINGTON, D C. 20566-0001
's,
,p OfLMONWEALTH EDIS0fLCOMPANY
[ LOCKET N0. STN 50-455 BYRON STATION. UNIT NO. 2 AMEN 0 MENT TO FACillTY OPERATING LICENSE Amendment No.'60 License No. NPF-66 J
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated August 27, 1993, as supplemented February 21, 1994, 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 1; B.
The facility 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 (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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the commor, 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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-66 is hereby amended to read as follows:
. (2)
InchnicAl Specifications The Technical Specifications contained in Appendix A (NUREG-lll3),
as revised through Amendment No. 60 and revised by Attachment 2 to NPF-66, and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No NPF-37, dated' February 14, 1985, are hereby incorporated into this license. Attachment 2 contains a revision to Appendix A which is hereby incorporated into this license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION J
ylKl4 {.
f/V James E. Dyer, Director Project Directorate 111-2 Division of Reactor Projects - Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
March 11, 1994
n ATTACHMENT TO LICENSE AMENDMENT NOS. 60 AND 60 FACILITY OPERATING LICENSE NOS. NPF-37_AND NPF-66 DOCKET NOS, STN 50-454 AND STN 50-455 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by the captioned amendment number and contain marginal li as indicating the area of change.
Remove Paaes Insert Paaes X
X 3/4 7-22 3/4 7-22 3/4 7-23 3/4 7-23 3/4 7-24 3/4 7-24 3/4 7-25 3/4 7-25 3/4 7-27 3/4 7-27 3/4 7-27a 3/4 7-27b B 3/4 7-6 B 3/4 7-6 e
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3!4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves............................................
3/4 7-1 TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING FOUR LOOP OPERATION.........................................
3/4 7-2 TABLE 3.7-2 STEAM LINE SAFETY VALVES PER LOOP...................
3/4 7-3 Auxiliary feedwater System.....
3/4 7-4 Condensate Storage Tank......
3/4 7-6 Specific Activity.....................
3/4 7-7 TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM.........................
3/4 7-8 Main Steam L ine I sol at ion Valves........................
3/4 7-9 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..........
3/4 7-10 3/4.7.3 COMPONENT COOLING WATER SYSTEM...........................
3/4 7-11 3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM...........................
3/4 7-12 3/4.7.5 ULTIMATE HEAT SINK..............................
3/4 7-13 3/4.7.6 CONTROL ROOM VENTILATION SYSTEM..........................
3/4 7-16 3/4.7.7 NON-ACCESSIBLE AREA EXHAUST FILTER PLENUM VENTILATION SYSTEM.......................................
3/4 7-19 3/4.7.8 SNUBBERS.........................................
3/4 7-22 FIGURE 4.7-1 THIS FIGURE NOT USED................................
3/4 7-27 TABLE 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL...................
3/4 7-27a 3/4.7.9 SEALED SOURCE CONTAMINATION........................
3/4 7-28 I
BYRON - UNITS 1 & 2 X
AMENDMENT NO. 60
PLANT SYSTEMS 3A7.8 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.8 All snubbers shall be OPERABLE.
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.
APPLICABillTY: 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 snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.8. on the attached component or declare the attached 9
system inoperable and follow the appropriate ACTION statement for that system.
S_URVEILiANCE REQUIREMENTS 4.7.8 Each snubber shall be demonstrated OPERABLE by perforniance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
a.
Inspection Tvoes As used in this specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity.
b.
Visual Inspections Snubbers are 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 4.7-2.
The visual inspection interval for each type shall be determined based upon the criteria provided in Table 4.7-2 and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect prior to amendment.
i i
BYRON - UNITS 1 & 2 3/4 7-22 AMEN 0 MENT NO. 60
~
PLANT SYSTEMS SVR'VEILLANCE RE0VIREMENTS (Continued) c.
Visual Insoection Acceotance Criteria Visual inspections shall verify that:
(1) there are no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting struch ' are functional and (3) fasteners for attachment of the snubber to e component and to the snubber
. anchorage are functional. Snubbe-which appear inoperable as a r
reruit of visual inspectior., sha',
be classified as unacceptable and 1
the purpose of establishing the may be reclassified accerL i ^ # r next visual inspection f,u ral, provided that:
(1) the cause of the rejection is clearly e',taoiished and remedied for that particular snubber and for other scubbers irrespective of type that may be generically susceptible; and (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per Specification 4.7.8f.
All snubbers found connected to an inoperable common hydraulic fluid reservior shall be counted as unacceptable for determining the next inspection interval. A review and evaluation shall be performed and documented to justify. continued operation with an inoperable snubber.
If continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be met, d.
Transient Event Inspection An inspection shall be performed of all snubbers attached to sections of systems that-have experienced unexpected, potentially damaging transients as determined from a review of operational data and a visual inspection of the.<.ystems within 6 months following such an event.
In addition to satisfying the visual inspection acceptance criteria, freedom-of-cotion of mechanical snubbers shall be verified using at least one of the following:
(1) manually induced snubber movement; or (2) evaluation of in-place snubber pistorc setting; or-(3) stroking the mecharical snubber through its full range of travel.
BYRON'- UNITS 1 & 2 3/4 7-23 AMENDMENT. NO. 60
PLANT SYSTEMS SURVElllANCE REQUIREMENTS (Continued) e.
Functional Tests At least once per 18 months during shutdown, at least 10% of the total of each type of snubber shall be functionally tested either in-place or in a bench test.
For each snubber of a type that does not meet the functional test acceptance criteria of Specification 4.7.8f., an additional 10% of that type of snubber shall be functionally tested until no more failures are found or until all snubbers of that type have been functionally tested.
BYRON - UNITS 1 & 2 3/4 7-24 AMENDMENT N0. 60
PLANT SYSTEMS SVRVElllANCE_ REQUIREMENTS (Continued)
Testing equipment failure during functional testing may invalidate that day's testing and allow the day's testing to resume anew at a later time provided all snubbers tested with the failed equipment during the day of equipment failure are retested.
The representative sample selected for the functional test sample plans shall be randomly selected from the snubbers of each type and reviewed before beginning the testing. The review shall ensure, as far as prac-ticable, that they are representative of the various configurations, operating environments, range of size, and capacity of snubbers of each type. Snubbers placed in the same lo:ation as snubbers which failed the previous functional test shall be retested at the time of the next functional test but shall not be included in th9 sample plan.
If during the functional testing, additional sampling is required due to failure of only one type of snubber, the functional test results shall be reviewed at that time to determine if additional samples should be limited to the type of snubber which has failed the functional testing.
f.
Functional Test Acceptance Criteria The snubber functional test shall verify that:
1)
Activation (restraining action) is achieved within the specified range in both tension and compression; 2)
Snubber bleed, or release rate where required, is present in both tension and compression, within the specified range; 3)
For mechanical snubbers the force required to initiate or main-tain motion of the snubber is within the specified range in both directions of travel; and 4)
For snubbers 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 parameters other than those specified if those results can be correlated to the specified parameters through established methods, i
BYRON - UNITS 1 & 2 3/4 7-25 AMENDMENT NO. 60
6 6
FIGURE 4.7-1 (THIS FIGURE NOT USED)
BYRON - UNITS 1 & 2 3/4 7-27 AMENDMENT N0. 60
TABLE 4.7-2
.SNVBBER VISUAL INSPECTION INTERVAL NUMBER OF UNACCEPTABLE SNUBBERS l
Population Column A Column B Column C or Category Extend Interval Repeat Interval Reduce Interval (Notes 1 & 2)
(Notes 3 & 6)
(Notes 4 & 61 (Notes 5 & Q 1-79 0
0 1
80-99 0
0 2
100-149 0
1 4
150-199 0
3 8
200-299 2
5 13 300-399 5
12 25 400-499 8
18 36 500-599 12 24 48 750-999 20 40 78 1000 or greater 29 56 109 Note 1: The next visual inspection interval for a snubber population or category size shall be determined based upon the previous inspection i
interval and the number of unacceptable 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 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 unacceptable 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 unacceptable snubbers as determined by interpolation.
Note 3:
If the number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval shall be twice the previous interval but not greater that 48 months.
Note 4:
If the number of unacceptable 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.
l BYRON - UNITS 1 & 2 3/4 7-27a AMENDMENT N0. 60
TABLE 4.7-2 (Continued)
NOTATIONS (Continued)
Note 5:
If the number of unacceptable 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 unacceptable 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. The previous interval shall be reduced by a factor of one-third of the ratio of the difference between the number of unacceptable snubbers found during the previous interval and the number in Column 8 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.
l
)
BYRON - UNITS 1 & 2 3/4 7-27b AMENDMENT NO. 60
PLANT SY.jlLMJ BASES SEBBERS (Continued) that the frequency of snubber failures and initiating events is constant with time and that the failure of any snubber on that system could cause the system to be unprotected and to result in failure during an initiating event.
USNRC Generic Letter 90-09 " Alternate Requirements for Snubber Visual Inspection Intervals and Corrective Actions" provides information necessary to establish a method of extending or shortening the subsequent visual inspection frequency based upon the failure rates from the previous inspection.
The acceptance criteria are to be used in the visual inspection to determine OPERABILITY of the snubbers.
For example, if a fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be declared inoperable and shall not be determined OPERABLE via functional testing.
To provide assurance of snubber functional reliability at least 10% of each type of snubber shall be functionally tested at least once per 18 months with an additional 10% tested for each functional testing failure.
Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubber for the applicable design conditions at either the completion of their fabrication or at a subsequent date.
Snubbers so exempted shall be listed in the list of individual snubbers indicating the extent of the exemptions.
The service life of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubbers, 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.
These records will provide statistical bases for future consideration of snubber service life.
BYRON - UNITS 1 & 2 8 3/4 7-6 AMENDMENT NO. 60
_ _ _ ~ _.
~ _ _.. _ _. _ _
4 p' "* y 7
UNITED STATES f.'!h[.\\j NUCLEAR REGULATORY COMMISSION
';3fg f
WASHINGTON. D C. 20566-0001 g-
,,c COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-456 BJAIDWOOD STATION. UNIT NO. 1 AMENDMlNT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. NPF-72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated August 27, 1993, as supplemented February 21, 1994, 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 Commission; 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 compliance with the Commission's regulations; D.
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 Commission's regulations and all applicable requirements have been satisfied.
4 2.
Accordingly, the license is amended by changes to the Technical Specifi'-
cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating Lict;nse No. NPF-72 is hereby amended to read as follows:
. (2)
Jechnical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 48 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION (4 M f.
04' ames E. Dyer, Director Project Directorate 111-2 Division of Reactor Projects - Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 11, 1994
g *oic.g
.k UNITED STATES N((./2 )
j.
j NUCLEAR REGULATORY COMMISSION
- 3' g ;y j
WASHINGTON. o C. 20664 0001 g
% m:
- s..*
COMMONWEALTH EDISON COMPANY DOCKET N0. STN 50-457 BRAIDWOOD STATION. UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. NPF-77 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated August 27, 1993, as supplemented February 21, 1994, 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 1; B.
The facility 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 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 Commission's regulations; D.
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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-77 is hereby amended to read as follows:
=
. (2)
Ipchnical Specifications The Technical Specifications contained in Appendix A as revised i
through Amendment No. 48 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-72, dated July 2, 1987, are hereby incorporated into this license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date if its issuance, FOR THE NUCLEAR REGULATORY COMMISSION 1ML f.YlfW James E. Dyer, Director i
Project Directorate 111-2 Division of Reactor Projects - Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 11, 1994 1
.-e-
~
m
,rm
~.,,,,
, - ~, <,
y
,p
-,.e--
_. _ _. ~. - _. - _.. _.. __
1 ATTACHMENT TO LICENSE AMEN 0 MENT NOS. 48 AND 48 FACILITY OPERATitlG llCENSE NOS, NPF-72 AND NPF-77 4
QQ[EET N05 STN 50-456 AND STN 50-457 l
Replace the fo'llowing 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,
't Remove Paaes insert Paaes X
X 3/4 7-20 3/4 7-20 3/4 7-21 3/4 7-21 3/4 7-22 3/4 7-22 3/4 7-23 3/4 7-23 l;
3/4 7-25 3/4 7-25 3/4 7-25a i-3/4 7-25b B 3/4 7-5 8 3/4 7-5 i
1 3
i i
+.
a
- -. = -..
QQlTJNG CONDITIONS FOR OPERATION AND SURVElllANCE REQUIREMENTS SIE110d EAGE 3/4.7 PLANT SYST(M1 3/4.7.1 TURBINE CYCLE Safety Valves............................................
3/4 7-1 TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING FOUR LOOP OPERAT10N...........................................
3/4 7-2 TABLE 3.7-2 STEAM LINE SAFETY VALVES PER L00P.....................
3/4 7-3 Auxiliary feedwater System.......
3/4 7-4 Condensate Storage Tank...........
3/4 7-6 Specific Activity........................................
3/4 7-7 TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY 4
SAMPLE AND ANALYSIS PR0 GRAM.........................
3/4 7-8 Main Steam Line Isolation Valves..............
3/4 7-9 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..........
3/4 7-10 3/4.7.3 COMPONENT COOLING WATER SYSTEM...........................
3/4 7-Il 3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM...........................
3/4 7-12 3/4.7.5 ULTIMATE HEAT SINK.......................................
3/4 7-13 3/4.7.6 CONTROL ROOM VENTILATION SYSTEM..........................
3/4 7-14 3/4.7.7 NON-ACCESSIBLE AREA EXHAUST FILTER PLENUM VENTILATION SYSTEM.......................................
3/4 7-17 3/4.7.8 SNUBBERS..................
3/4 7-20 FIGURE 4.7-1 THis FIGURE NOT USED................................
3/4 7-25 TABLE 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL...................
3/47-253 3/4.7.9 SEALED SOURLt t.0NTAMINATION..............................
3/4 7-26 1
l BRAIDWOOD - UNITS 1 & 2 X
AMENDMENT NO. 48
& ANT SJjill!15 314.7.8 SNVjjlRS llMITING COND] TION FOR OPERATION 3.7.8 All snubbers shall be OPERABLE.
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.
APPLICABlLLIX: MODES 1, 2, 3, and 4.
MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.
KU_03:
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.8. on the attached component or declare the attached 9
system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQULREMENTS 4.7.8 Each snubber shall be demonstrated GDERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5, LrtsJttyti_o_p Typ_ed t
a.
As used in this specificatlon, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity, b.
Visual inspections Snubbers are 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 4.7-2.
The visual inspection interval for each type shall be astermined based upon the criteria provided in Table 4.7-2 and the first inspection interval determined using this criteria shall be tused uoan the previous inspection interval as establimed by the requiren,ents in effect prior to amendment.
BRAIDWOOD - UNITS 1 & 2 3/4 7-20 AMENDMENT NO. 48
P1 ANT SYSTEMS SURVEIll.ANCE REQUIREMENTS (Continued) c.
Yintal Insoection Acceptance Criteria Visual inspections shall verify that:
(1) there are no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are functional and (3) fasteners for 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 unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that:
(1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type that may be generically susceptible; and (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per Specification 4.7.8f.
All snubbers found connected to an inoperable common hydraulic fluid reservlor shall be counted as unacceptable for determining the next inspection interval.
A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber.
If continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be met.
d.
Transient Event Insoection An inspection shall be performed of all snubbers attached to sections of systems that have experienced unexpected, potentially damaging transients as determined from a review of operational data and a visual inspection of the systems within 6 months following such an event.
In addition to satisfying the visual inspection acceptance criteria, freedom-of-motion of mechanical snubbers shall be verified using at least one of the following:
(1) manually induced snubber movement; or (2) evaluation of in-place snubber piston setting; or (3) stroking the mechanical snubber through its full range of travel.
BRAIDWOOD - UNITS 1 & 2 3/4 7-21 AMENDMENT NO. 48
PLANT SYSTEMS SURVElllANCE REQUIREMENTS (Continued) e.
Egnctional Tests At least once per 18 months during shutdown, at least 10% of the total of each type of snubber shall be functionally tested either in-place or in a bench test.
For each snubber of a type that does not meet the Danctional test acceptance criteria of Specificatico 4.7.8f., an additional 10% of that type of snubber shall be functionally tested until no more failures are found or until all snubbers of that type have been functionally tested.
BRAIDWOOD - UNITS 1 & 2 3/4 7-22 AMENDMENT NO. 48
PLANT SYSTEMS SVRVEllLANCE REQUIREMENTS (Continued)
Testing equipment failure during functional testing may invalidate that day's testing and allow the day's testing to resume anew at a later time provided all snubbers tested with the failed equipment during the day of equipment failure are retested. The representative sample selected for the 'unctional test sample plans shall be randomly selected from the snuchers of each type and reviewed before beginning the testing. The review shall ensure, as far as prac-ticable, that they are representative of the various configurations, operating environments, range of size, and capacity of snubbers of each type. Snubbers placed in the same location as snubbers which failed the previous functional test shall be retested at the time of the next functional test but shall not be included in the sample plan.
If during the functional testing, additional sampling is required due to failure of only one type of snubber, the functional test results shall be reviewed at that time to determine if additional samples should be limited to the type of snubber which has J
failed the functional testing.
f.
Eynctional Test Acceptance Criteria The snubber functional test shall verify that:
1)
Activation (restraining action) is achieved within the specified range in both tension and compression; 2)
Snubber bleed, or release rate where required, is present in both tension and compression, within the specified range; 3)
For mechanical snubbers the force required to initiate or main-tain motion of the snubber is within the specified range in both directions of travel; and 4) foi sn1bbers specifically required not to displace under concinuous load, the ability of the snubber to withstand load witht.ut displacement.
Testing methods may be used to measure parameters indirectly or parameters other than those specified if those results can be correlated to the specified parameters through established methods.
BRAIDWOOD - UNITS 1 & 2 3/4 7-23 AMENDMENT NO. 48
A e
FIGURE 4.7-1 (THIS FIGURE NOT USED)
BRAIDWOOD - UNITS 1 & 2 3/4 7-25 AMENOMENT NO. 48
PLANT SYSTffi$
J BASES SNUBBERS (Continued)
The visual inspection frequency is based upon maintaining a constant level of snubber protection during an earthquake or severe transient. Therefore, the required inspection interval varies inversely with the observed snubber failures on a given type and is determined by the number of inoperable snubbers found during an inspection of each type.
In order to establish the inspection frequency for each type of snubber on a safety-related system, it was assumed thht the frequency of snubber failures and initiating events is constant with time and that the failure of any snubber on that system could cause the system to be unprotected and to result in failure during an initiating event. USNRC Generic Letter 90-09 " Alternate Requirements for Snubber Visual Inspection Intervals and Corrective Actions" provides information necessary to establish a method of extending or shortening the subsequent visual inspection frequency based upon the failure rates from the previous inspection.
The acceptance criteria are to be used in the visual inspection to deter-mine OPERABILITY of the snubbers.
For example, if a fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be declared inoperable and shall not be determined OPERABLE via functional testing.
To provide assurance of snubber functional reliability at least 10% of each type of snubber shall be functionally tested at least once per 18 months with an additional 10% tested for each functional testing failure.
Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, if appilcable, snubber life destructive testing was performed to qualify the snubber for the applicable design conditions at either the com-pletion of thei-fabrication or at a subsequent date.
Snubbers so exempted shall be liste n the list of individual snubbers indicating the extent of the exemptions.
The rervice life of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubbers, seal replaced, spring replaced, in high radiation area, in high temperature area, BRAIDWOOD - UNITS 1 & 2 B 3/4 7-5 AMEN 0 MENT N0, 48