ML20057A356
| ML20057A356 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 09/01/1993 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20057A357 | List: |
| References | |
| GL-90-09, GL-90-9, NUDOCS 9309140070 | |
| Download: ML20057A356 (20) | |
Text
_ _ _ _ _ _ _ - _ _ _ _.
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'c UNITED STATES
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j NUCLEAR REGULATORY COMMISSION 3
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p W ASHINGTON, D. C. 20555
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-373 LASALLE COUNTY STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSI Amendment No. 91 License No. NPF-ll 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated March 2,1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 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 set forth in 10 CFR Chapter I; 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 Specifications as indicated in the enclosure to this license amendment l
and paragraph 2.C.(2) of the Facility Operating License No. NPF-ll is hereby amended to read as follows:
)
9309140070 930901 PDR ADOCK 05000373 P
_2_
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 91_, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective upon date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION dA A/
jfsn.JamesE. Dyer, Director Project Directorate 111-2 Division of Reactor Projects - lil/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
September 1, 1993 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 91 FACILITY OPERATING LICENSE NO. NPF-11 i
DOCKET NO. 50-373
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Replace the following pages of the Appendix "A" Technical Specifications with l
the enclosed pages.
The revised pages are identified by amendment number and contain a vertical line indicating the area of change.
I REMOVE INSERT 1
f XXIII XXIII l
3/4 7-27 3/4 7-27 3/4 7-28 3/4 7-28 I
3/4 7-32a 3/4 7-32b B 3/4 7-4 8 3/4 7-4 l
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INDEX l
LIST OF TABLES (Continued)
TABLE PAGE l
4.6.1.5-2 TENDON LIFT-0FF FORCE.............................
3/4 6-12 l
3.6.3-1 PRIMARY CONTAINMENT ISOLATION VALVES..............
3/4 6-24 l
3.6.5.2-1 SECONDARY CONTAINMENT VENTILATION SYSTEM AUTOMATIC ISOLATION DAMPERS.......................
3/4 6-39 3.7.5.2-1 DELUGE AND SPRINKLER SYSTEMS......................
3/4 7-16 3.7.5.4-1 FIRE HOSE STATIONS................................
3/4 7-19 3.7.7-1 AREA TEMPERATURE MONITORING.......................
3/4 7-25 1
4.7.9-1 SNUBBER VISUAL INSPECTION INTERVAL.................
3/4 7-32a 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE....................
3/4 8-7b 4.8.2.3.2-1 BATTERY SURVEILLANCE REQUIREMENTS.................
3/4 8-18 3.8.3.3-1 MOTOR-0PERATEC VALVES THERMAL OVERLOAD PROTECTION........................................
3/4 8-27 l
l B3/4.4.6-1 REACTOR VESSEL TOUGHNESS..........................
B 3/4 4-6 5.7.1-1 COMPONENT CYCLIC OR TRANSIENT LIMITS..............
5-6 l
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l LA SALLE - UNIT 1 XXIII Amendment No. 91 l
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PLANT SYSTEMS 3/4.7.9 SNUBBERS LIMITING CONDITJON FOR OPERATION 3.7.9 All hydraulic and mechanical snubbers shall be OPERABLE.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
OPERATIONAL CONDITIONS 4 and 5 for snubbers located on systems required OPERABLE in those OPERATIONAL CONDITIONS.
ACTION:
With one or more snubbers inoperable, on any system, 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 4.7.9. on the attached component or 9
declare the attached system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REOUIREMENTS 4.7.9 Each snubber shall be demonstrated OPERABLE by performance 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 4.7.9-1.
The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 4.7.9-I and the first inspection interval determined using this criteria shall be based upon tha previous inspection intervc! as established by the requirements in effect before amendment 91.
c.
Visual Inspection Acceptance Criteria Visual inspections shall verify that (1) the snubber has no visible l
indications of damage or impaired OPERABILITY, (2) attachments to l
the foundation or supporting structure are functional, and 1
l LA SALLE - UNIT 1 3/4 7-27 Amendment No. 91
\\
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
(3) fasteners for the attachment of the snubber to the component and to the snubber anchorage are functional. Snubbers which appear inoperable as a result of visual inspections shall be classified as 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 4.7.9f.
All snubbers found connected to an inoperable common hydraulic fluid reservoir shall be i
counted as unacceptable for determining the next inspection j
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 Inspection An inspection shall be performed of all hydralic and mechanical l
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.
e.
Functional Tests At least once per 18 months during shutdown, a representative sample of snubbers shall be tested using one of the following sample plans.
The sample plan shall be selected prior to the test period and cannot be changed during the test period. The NRC Regional Administrator shall be notified in writing of the sample plan selected prior to the test period or the sample plan used in the prior test period shall be implecented:
1)
At least 10% of the total of each type of snubber shall be functionally tested either in-place or in a bench test.
For l
each snubber of a type that does not meet the functional test acceptance criteria of Specification 4.7.9f., an additional 10%
of that type of snubber shall be functionally tested until no l
more failures are found or until all snubbers of that type have been functionally tested; or 2)
A representative sample of each type of snubber shall be func-tionally tested, in accordance with Figure 4.7-1.
"C" is the l
LA SALLE - UNIT 1 3/4 7-28 Amendment No. 91
l TABLE 4.7.9-1 l
SNUBBER VISUAL INdPECTION INTERVAL i
NUMBER OF UNACCEPTABLE SNUBBERS Population or Column A' Column B Column C Category Extend Interval Repeat interval Reduce Interval (Notes 1 and 2)
(Notes 3 and 6)
(Notes 4 and 6)
(Notes 5 and 6) j 1
0 0
1 l
80 0
0 2
l 100 0
1 4
150 0
3 C
200 2
5 13-300 5
12 25 l
l 400 8
18 36
)
i 500 12 24 48 750 20 40 78 l
1000 or greater 29 56 109 i
l I
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 unacceptable snubbers found during that l
interval. Snubbers may be categorized, based upon their l
accessibility during power operation, as accessible or inaccessible.
l These categories may be examined separately or jointly. However, l
the licensee must make and document that decision before any l
inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.
l Note 2:
Interpolation between population or category sizes and the number of l
unacceptable snubbers is permissible. Use the next lower integer l
for the value of the limit for Columns A, B, or C if that integer l
includes a fractional value of unacceptable snubbers as determined l
by interpolation.
LA SALLE - UNIT 1 3/4 7-32a Amendment No. 91 l
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l TABLE 4.7.9-1 SNUBBER VISUAL INSPECTION INTERVAL (Continued)
Note 3:
If the number of unacceptable 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 tLan 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.
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, 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 unacceptable 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.
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l LA SALLE - UNIT 1 3/4 7-32 b Amendment No. 91 i
i PLANT SYSTEMS BASES SNUBBERS (Continued) j snubber shall be determined and approved by the Onsite Review and Investigative Function. The determination shall be based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g., temperature, atmosphere, location, etc.), and the recommendations of Regulatory Guide 8.8 and 8.10.
The addition or deletion of any hydraulic or mechanical snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to the safety-related systems, as given in Generic Letter 90-09, Alternative Visual Inspection Intervals and Corrective Actions.
Therefore, the required schedule is based on the number of unacceptable snubbers found during the previous inspection in proportion to the sizes of various snubber populations or categories. The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 4.7.9-1 and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the i
requirements in effect before amendment 91.
The acceptance crite. ia are to be used in the visual inspection to deter-mine ACCEPTABILITY of the snubbers. For example, if a fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be declared unacceptable and shall not be determined ACCEPTABLE via functional testing.
)
To provide assurance of snubber functional reliability, one of three functional testing methods is used with stated acceptance criteria:
i 1.
Functionally test 10% of a type of snubber with an additional 10%
tested for each functional testing failure, or 2.
Functionally test a sample size and determine sample acceptance or rejection using Figure 4.7-1, or 3.
Functionally test a sample size and determine sample acceptance or refection using the stated equation.
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j LA SALLE - UNIT 1 B 3/4 7-4 Amendment No. 91 l
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'o UNITED STATES
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!"y,gj NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20555 gv.... /
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@ MMONWEALTH EDISON COMPANY C0CKET NO. 50-374 i
LASALLE COUNTY STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 75 License No. NPF-18 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment files by the Commonwealth Edison Company (the licensee), dated March 2, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 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 set forth in 10 CFR Chapter I; 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 Specifications as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-18 is hereby amended to read as follows:
' (2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 75, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective upon date of isst.ance.
FOR THE NUCLEAR REGULATORY COMMISSION frh'/
l
'h
\\
h James E. Dyer, Director l
Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 1, 1993 l
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9 ATTACHMENT TO LICENSE AMENDMENT NO. 75 FACILITY OPERATING LICENSE NO. NpF-18 DOCKET NO. 50-374 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain a vertical line indicating the area of change. The corresponding overleaf pages, as indicated by an asterisk, are provided to maintain document completeness.
REMOVE INSERT XXIII XXIII 3/4 7-28 3/4 7-28 3/4 7-29 3/4 7-29 l
- 3/4 7-30
- 3/4 7-30 3/4 7-33a 3/4 7-33b
- B 3/4 7-3
- B 3/4 7-3 B 3/4 7-4 B 3/4 7-4 l
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INDEX LIST OF TABLES (Continued)
TABLE PAGE 3.6.5.2-1 SECONDARY CONTAIhMENT VENTILATION SYSTEM AUTOMATIC ISOLATION DAMPERS.......................
3/4 6-42 3.7.5.2-1 DELUGE AND SPRINKLER SYSTEMS......................
3/4 7-16 3.7.5.4-1 FIRE H0SE SThi10NS................................
3/4 7-19 3.7.7-1 AREA TEMPERATURE MONITORING.......................
3/4 7-26 l
l 4.7.9-1 SNUBBER VISUAL INSPECTION INTERVAL.................
3/4 7-33a 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE....................
3/4 8-7b l
4.8.2.3.2-1 BATTERY SURVEILLANCE REQUIREMENTS.................
3/4 8-18 l
3.8.3.3-1 MOTOR-0PERATED VALVES THERMAL OVERLOAD l
PROTECTION........................................
3/4 8-27 I
B3/4.4.6-1 REACTOR VESSEL TOUGHNESS..........................
B 3/4 4-6 5.7.1-1 COMPONENT CYCLIC OR TRANSIENT LIMITS..............
5-6
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i LA SALLE - UNIT 2 XXIII Amendment No. 75
I PLANT SYSTEMS 3/4.7.9 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.9 All hydraulic and mechanical snubbers shall be OPERABLE.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
OPERATIONAL CONDITIONS 4 and 5 for snubbers located on systems required OPERABLE in those OPERATIONAL CONDITIONS.
ACTION:
With one or more snubbers inoperable, on any system, 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 4.7.9. on the attached component or 9
declare the attached system inoperable and follow the appropriate ACTION statement for that system.
I SURVEILLANCE REQUIREMENTS l
4.7.9 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
a.
Insoection 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 4.7.9-1.
The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 4.7.9-I 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 75 c.
Visual Inspection Acceptance Criteria Visual inspections shall verify that (1) the snubber ha; no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are functional, and l
LA SALLE - UNIT 2 3/4 7-28 Amendment No. 75 l
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PLANT SYSTEMS l
SURVElllANCE RE0VIREMENTS (Continued) l (3) fasteners for the attachment of the snubber to the component and 1
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 l
snubber is functionally tested in the as-found condition and determined OPERABLE per Specification 4.7.9f.
All snubbers found i
connected to an inoperable common hydraulic fluid reservoir shall be I
counted as unacceptable for determining the next inspection l
interval. A review and evaluation shall be performed and documented 2
to justify continued operation with an unacceptable snubber.
If l
continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be met, t
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d.
Transient Event Inspection An inspection shall be performed of all hydralic and mechanical snubbers attached to sections of systems that.have experienced unexpected, potentially damaging transients.as determined from a l
review of operational data and a visual inspection of the systems within 6 months following such-an event.
In addition to satisfying j
the visual inspection acceptance criteria, freedom-of-motion of mechanical snubbers'shall be verified using at least one of the a
following:
(1) manually induced snubber movement; or (2) evaluation i
of in-place snubber piston setting; or (3) stroking the mechanical j
snubber through its full range of travel.
.j e.
Functional Tests At least once per 18 months during shutdown, a representative sample l
of snubbers shall be tested using one of the following sample plans.
The sample plan shall be selected prior to the test period and cannot be changed during the test period. The NRC Regional Administrator shall be notified'in writing of the sample plan selected prior to the test period or the sample plan used in the prior test period shall be implemented:
1)
At least 10% of the total of each type of snubber shall be functionally tested either in-place or in a bench test. Fo' each snubber of a type that does not meet the functional tes acceptance criteria of Specification 4.7.9f., 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; or 2)
A representative sample of each type of snubber shall be func-tionally tested, in accordance with Figure 4.7-1.
'"C" is the LA SALLE - UNIT 2 3/4 7-29 Amendment No. 75
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Pk.ANTSYSTEMS i
l '
SURVEILLANCE REQUIREMENTS (Continued) e.
Functional Tests (Continued) total number of snubbers of a type found not meeting the accep-tance requirements of Specification 4.7.9f.
The cumulative number of snubbers of a type tested is denoted by "N".
At the end of each day's testing, the new values of "N" and "C" (pre-l vious day's total plus current day's increments) shall be plotted on Figure 4.7-1.
If at any time the point plotted falls in the " Reject" region, all snubbers of that type may be functionally tested.
If at any time the point plotted falls in the " Accept" region, testing of snubbers of that ty;a may be terminated.
When the point plotted lies in the " Continue I
Testing" region, additional snubbers of that type shell be tested until the point falls in the " Accept" region or the
" Reject" region, or all the snubbers of that type have been tested.
Testing equipment failure during functional testing l
may invalidate that day's testing and allow that 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; or l
3)
An initial representative sample of 55 snubbers shall be func-tionally tested.
For each snubber type which does not meet the functional test acceptance criteria, another sample of at least one-half the size of the initial sample shall be tested until the total number tested is equal to the initial sample size l
multiplied by the factor, 1 + C/2, where "C" is the number of snubbers found which do not meet the functional test acceptance criteria.
The results from this sample plan shall be plotted l
using an " Accept" line which follows the equation N = 55(1 +
C/2).
Each snubber point should be plotted as soon as the snubber is tested.
If the point plotted falls on or below the
" Accept" line, testing of that type of snubber may be terminated.
If the point plotted falls above the " Accept" line, testing must continue until the point falls in the " Accept" region or all the snubbers of that type have been tested.
l 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 l
far as practicable, that they are representative of the various con-figurations, 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 func-tional test results shall be reviewed at that time to determine if l
additional samples should be limited to the type of snubber which l
has failed the functional testing.
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LA SALLE - UNIT 2 3/4 7-30 i
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i TABLE 4.7.9-1 SNUBBER VISUAL INSPECTION INTERVAL NUMBER OF UNACCEPTABLE SNUBBERS Popula', ion or Column A Column B Column C Cat egory Extend Interval Repeat Interval Reduce Interval (Notes 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
i 150 0
3 8
200 2
5 13 300 5
12 25 l
400 8
18 36 500 12 24 48-750 20 40 78 1000 or greater 29 56 109 t
1 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 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 the 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.
LA SALLE - UNIT 2 3/4 7-33a Amendment No. 75 i
TABLE 4.7.9-I SNUBBER VISUAL INSPECTION INTERVAL l
(Continued)
Note 3:
If the number of unacceptable snubbers is equal it, or less than the l
l 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 unacceptable snubbers is equal to or less than the number in Column B but greater than the number in Column A, the next j
inspection interval shall be the same as the previous interval.
l Note 5:
If the number of unacceptable snubbers is equal to or greater than i
the number in Column C, the next inspection interval shall be two-I thirds of the previous interval. However, if the number of unacceptable snubbers is less than the number in Column C but i
greater than the number in Column B, the next interval shall be i
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 unacceptable snubbers found I
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.
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LA SALLE - UNIT 2 3/4 7-33 b Amendment No. 75 l
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E I
i PLANT SYSTEMS BASES 3/4.7.6 FIRE RATED ASSEMBLIES The OPERABILITY of the fire barriers and barrier penetrations ensure that fire damage will be limited. These design features minimize the possibility of a single fire involving more than one fire area prior to detection and extinguishment.
The fire barriers, fire barrier penetrations for conduits, cable trays and piping, fire windows, fire dampers, and fire doors are periodically inspected to verify their OPERABILITY.
3/4.7.7 AREA TEMPERATURE MONITORING l
l The area temperature limitations ensure that safety-relateo equipment will l
not be subjected to temperatures in excess of their environmental qualification temperatures.
Exposure to excessive temperatures may degrade equipment and can cause loss of its OPERABILITY. The temperature limits include allowance for an l
instrument error of i 7'F.
l 3/4.7.8 STRUCTURAL INTEGRITY OF CLASS 1 STRUCTURES i
In order to assure that settlement does not exceed predicted and allowable
.l settlement values, a program has been established to conduct a survey at the site.
The allowable total differential settlement values are based on original settlement predictions.
In establishing these tabulated values, an assumption is made that pipe and conduit connection have been designed to safely withstand the stresses which would develop due to total and differential settlement.
3/4.7.9 SNUBBERS All 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 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.
Snubbers are classified and grouped by design and manufacturer but not by size.
For example, mechanical snubbers utilizing the same design features of the 2-kip,10-kip, and 100-kip capacity manufactured by Company "A" are of the same type.
The same design mechanical snubbers manufactured by Company "B" for the purpose of this Technical Specification would be of a different type, as would hydraulic snubbers from either manufacturer.
LA SALLE - UNIT 2 B 3/4 7-3
i I-PLANT SYSTEMS i
BASES SNUBBERS (Continued)
)
A list of individual snubbers with detailed information of snubbers loca-tion and size and of system affected shall be available at the plant in accordance with Section 50.71(c) of 10 CFR Part 50. The accessibility of each snubber shall be determined and approved by the Onsite Review and Investigative Function. The determination shall be based upon the existing i
radiation levels and the expected time to perform a visual inspection in each j
snubber location as well as other factors associated with accessibility during plant operations (e.g., temperature, atmosphere, location, etc.), and the i
recommendations of Regulatory Guide 8.8 and 8.10.
The addition or deletion of any hydraulic or mechanical snubber shall be made in accordance with i
Section 50.59 of 10 CFR Part 50.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to the safety-related systems, as given in Generic Letter 90-09, Alternative Visual Inspection Intervals and Corrective Actions.
Therefore, the required schedule is based on the number of unacceptable j
snubbers found during the previous inspection in proportion to the sizes of i
various snubber populations or categories. The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 4.7.9-1 and first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the i
requirements in effect before amendment 75.
The acceptance criteria are to be used in the visual inspection to determine ACCEPTABILITY of the snubbers.
For example, if a fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be declared unacceptable and shall not be determined ACCEPTABLE via functional testing.
l To provide assurance of snubber functional reliability, one of three functional testing methods is used with stated acceptance criteria:
1.
Functionally test 10% of a type of snubber with an additional 10%
tested for each functional testing failure, or 2.
Functionally test a sample size and determine sample acceptance or rejection using Figure 4.7-1, or 3.
Functionally test a representative sample size and determine sample acceptance or rejection using the stated equation.
l LA SALLE - UNIT 2 B 3/4 7-4 Amendment. No. 75
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