ML20106G247
| ML20106G247 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/29/1985 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20106G251 | List: |
| References | |
| NUDOCS 8502140293 | |
| Download: ML20106G247 (30) | |
Text
'
%A;
- UNITED STATES e
NUCLEAR REGULATORY COMMISSION
{
j WASHINGTON, D. C. 20555 e
'%,,,,,/
.. ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 62 License No. NPF-6 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power & Light Company (the licensee) dated June 30, 1983, as superseded by letter dated May 19, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and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 (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 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.
8502140293 850129 PDR ADOCK 05000368 p
- 2.
Accordingly, the l'icense 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. NPF-6 is hereby amended to read as follows:
)
(2) Technical Specification ~s The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 62, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical'Specifica-tions, except where otherwise stated in specific license conditions.
3.
This license amendment is effective upon start up after the fourth refueling outage but no later than July 30, 1985.
FOR THE NUCLEAR REGUL RY COMMISSION
.;r
/
iller, Chief
/
Operating Reactors Branch #3
/
Division of Licensing
Attachment:
Changes to the Technical Specificatiors Date of Issuance: January 29, 1985 O
e i
w wer
)
ATTACHMENT TO LICENSE AMENDMENT NO. 62 FACILTIY OPERATING LICENSE NO. NPF-6 DOCKET'NO. 50-368 L
Revise the Appendix A Technical Specifications as follows. The revised pages are identifed by amendment number and contain marginal lines indicating the area of change. Corresponding overleaf pages are included to maintain document completeness.
Remove Insert VIII VIII XIII XIII 3/4 7-22 3/4 7-22 3/4 7-23 3/4 7-23 3/4 7-23a.
3/4 7-23b 3/4 7-26 3/4 7-26 3/4 7-26a 3/4 7-26b 3/4 7-26c 3/4 7-26d 3/4 7-26e 3/4 7-26f 3/4 7-26g 3/4 7-26h 3/4 7-26i 3/4 7-26f-3/4 7-26k B 3/4 7-5 B 3/4 7-5 6-23 6-23 gm-
~
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.5.2 ECCS SUBSYSTEMS - T 1 300'F........................
3/4 5-3 avg 3/4.5.3 ECCS' SUBSYSTEMS - T i 300*F........................
3/4 5-6 avg 3/4.5.4 REFUELING WATER TANK..................................
3/4 5-7 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Contai nment Integri ty.................................
3/4 6-1 Containment Leakage...................................
3/4 6-2 Containment Air Locks.................................
3/4 6-4 Internal Pressure, Air Temperature and Relative Humidity...................................
3/4 6-6 Containment Structural Integri ty......................
3/4 6-8 Containment Ventilation System........................
3/4 6-9a 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System..............................
3/4 6-10 Sodium Hydroxide Addition System......................
3/4 6-12 Containment Cooling System............................
3/4 6-14 3/4.6.3 CONTAINMENT ISOLATION VALVES..........................
3/4 6-16 3/4.6.4 COMBUSTIBLE GAS CONTROL-Hydrogen Analyzers....................................
3/4 6-22 Electric Hydrogen Recombin'ers - }{.....................
3/4 6-23 Containment Recirculation System......................
3/4 6-24 i
1 I
ARXANSAS - UNIT 2 VII Amendment No. 60 i
e
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS-SECTION PAGE 3/4.7 PLANT-SYSTEMS 3/4.7.1 TURBINE-CYCLE 5
Safety Va1ves........................................
3/4 7-1
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Emergency Feedwater System...........................
3/4 7-5 Condensate Storage Tank..............................
3/4 7-7 Activity............................................
3/4 7-8 Main' Steam Isolation Valves.........................
3/4 7-10 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION......
3/4 7-14 3/4.7.3 SERVICE WATER SYSTEM.................................
3/4 7-15 3/4.7.4 EMERGENCY COOLING P0ND................................ 3/4 7-16 3/4.7.5 FLOOD PR0TECTION.....................................
3/4 7-16a 3/4.7.6 CONTROL ROOM EMERGENCY AIR CONDITIONING AND AIR FILTRATION SYSTEM..................................
3/4 7-17 3/4.7.8 SH0CKSUPPRESSORS(SHUCBERS).........................
3/4 7-22 l
3/4.7.9 SEALED SOURCE CONTAMINATION..........................
3/4 7-27 3.4.7.10 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System........................
3/4 7-29 Spray and/or Sprinkler Systems.......................
3/4 7-33 Fire Hose Stations...................................
3/4 7-35 3/4.7.11 PENETRATION FIRE BARRIERS............................
3/ 4 7-37 3/4.7.12 SPENT FUEL P0OL STRUCTURAL INTEGRITY................
3/4 7-38 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0perating.............................................
3/4 8-1 Shutdown..............................................
3/4 8-5 ARKANSAS - UNIT 2 VIII Amendment No./77,66,62 l
i
._.__.,,_--,m..,
-.- m
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INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE.......................................
B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.....
B 3/4 7-4,
3/4.7.3 SERVICE WATER SYSTEM................................
B 3/4 7-4 3/4.7.4 EMERGENCY COOLING P0ND..............................
B 3/4 7-4 3/4.7.5 FLOOD PROTECTION....................................
B 3/4 7-4 3/4.7.6 CONTROL ROOM EMERGENCY AIR CONJITIONING/ AIR FILTRA-T I ON S Y ST EM.......................................
B-3/4 7-4 3/4.7.8 SHOCK SUPPRESSORS (SNUBBERS)........................
B 3/4.7-5 l
3/4.7.9 SEALED SOURCE CONTAMINATION.........................
B 3/4 7-6 3/4.7.10 FIRE SUPPRESSION SYSTEMS............................
B 3/4 7-6 3/4.7.11 PENETRATION FIRE BARRIERS...........................
B 3/4 7-7 3/4.7.12 SPENT FUEL P0OL STRUCTURAL INTEGRITY................
B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS..............................
B 3/4 8-1 i
3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.................................
B 3/4 9-1 3/4.9.2 INSTRUMEN1aTION.....................................
B 3/4 9-1 3/4.9.3 DECAY TIME..........................................
B 3/4 9-1 3/4.9.4 CONTAINMENT PENETRATIONS............................
B 3/4 9-1 Amendment No. 69. 62 ARKANSAS - UNIT 2 XIII i
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INDEX BASES PAGE SECTION 3/4.9.5 COMMUNICATIONS......................................... B 3/4 9-2 3/4.9.6 REFUELING MACHINE OPERABILITY.......................... B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING............. B 3/4 9-2, 3/4.9.8 COOLANT CIRCULATION.................................... B 3/4 9-2 3/4.9.9 and 3/4.9.10 WATER LEVEL - REACTOR VESSEL AND STORAGE POOL WATER LEVEL............................. B 3/4 9-3 3/4.9.11 FUEL HANDLING AREA VENTILATION SYSTEM.................. B 3/4 9-3 3/4.10 SPECIAL' TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGI N........................................ B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION L I MI TS............................................... B 3/ 4 10- 1 3/4.10.3 REACTOR COOLANT L00PS.................................. B 3/4 10-1 3/4.10.4 CENTER CEA MISALIGNMENT................................ B 3/4 10-1 3/4.10.5 MINIMUM TEMPERATURE FOR CRITICALITY.................... B 3/4 10-1
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3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS....................................... B 3/4 11 -1 3/4.11.2 GASEOUS EFFLUENTS...................................... B 3/4 11-2 3/4.11.3 TOTAL D0SE............................................. B 3/4 11-4 3/4.11.4 SOLID RADI0 ACTIVE WASTE................................ B 3/4 11-4 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING l
3/4.12.1 MONITORING PR0 GRAM..................................... B 3/4 12-1 3/4.12.2 LAND USE CENSUS........................................ B 3/4 12-1 l
' 3/4.12.3 INTERLABORATORY COMPARISON PR0 GRAM..................... B 3/4 12-1 l
l ARKANSAS - UNIT 2 XIV Amendment No. 60
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e 9
e ARKANSAS - UNIT 2 3/4 7-21
PLANT SYSTEMS 3/4.7.8 SH0CK SUPPRESSORS (SNUBBERS) l LIMITING CONDITION FOR OPERATION 3.7.8 All snubbers listed in Tables 3.7-4 and 3.7-4a shall be OPERABLE.
l APPLICABILITY:
MODES 1, 2, 3 and 4.
MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.
ACTION:
With one or more 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 evalua-tion per Specification 4.7.8.f on the attached component, or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.8 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 Types As used in this specification, type of snubber shall mean sr.9bbers of the same design and manufacturer, irrespective of capacity.
Snubbers are categorized as inaccessible or accessible during reactor operation.
b.
Visual Inspections Visual inspections shall be performed in accordance with the following schedule:
No. Inoperable Snubbers Subsequent Visual per Inspection Period
' Inspection Period 0
18 months + 25%
1 12 months T 25%
2 6 months T 25%
3, 4 124 days + 75%
5,6,7 62 days T 25%
8 or more 31 days +~25%
The snubbers may be categorized into groups based on type and accessibility.
Each group may be inspected independently in accordance with the above schedule.
ARKANSAS - UNIT 2 3/4 7-22 Amendment No. 62
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
The inspection interval for each type of snubber shall not be lengthened more than one step at a time unless a generic problem has been identified and corrected; in that event the inspection interval may be lengthened one step the first time and two steps thereafter if no inoperable snubbers of that type are found.
.The provisions of Specification 4.0.2 are not applicable.
~
c.
Visual Inspection Acceptance Criteria Visual inspections shall verify that (1) there are no visible indications of damage or impaired OPERABILITY, and (2) attachments to the foundation or supporting structure are secure. Snubbers which are determined to be inoperable as a result of visual inspec-tions 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 and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affectid snubber is functionally tested in the as found condition and determined OPERABLE per Specifica-tions '4.7.8.d or 4.7.8.e, as applicable.
However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.
All snubbers connected to a corunon hydraulic fluid reservoir shall be evaluated for operability if any sn.ubber connected.to thatireservoir.is determined.to be : inoperable. '
d.
Functional Tests At least once each refueling shutdown a representative sample of snubbers shall be test 6d-using.the following sample plan.
At least 10% of the snubbers required by Specification 3.7.8 shall be functionally tested either in place or in a bench test.
For each snubber that does not meet the functional. test acceptance criteria of Specification 4.7.8.e, an additional 10% of. the snubbers i
shall be functionally tested until no more failures are found or until all snubbers have been functionally tes,ted.
The representative samples for the functional test sample plans j
shall be randomly selected from the snubbers required by Specifica-tion 3.7.8 and reviewed before begining the testing. The review 1
shall ensure as far as practical that they are representative of the various configurations, operating environments, range of sizes, 4
and capacities.
Snubbers placed in the same locations 'as snubbers which failed the previous functional test shall be retested at the ARKANSAS - UNIT 2 3/4 7-23 Amendment No. 62
=
=
4 PLANT SYSTEMS ~
SURVEILLANCE REQUIREMENTS (Continued) time of the next functional test but shall not be included in the l
sample pla'n.
If during the functional testing, additional sampling is required due to failure of only one type of snubber, the func -
tional testing results shall be reviewed at that time to determine if additional samples should be limited to the type of snubber which has failed the functional testing.
e.
Functional Test Acceptance Criteria l
The snubber functional test shall verify that:
1)
Activation (restraining action) is achieved within the speci-i fied range in both tension and compression, except that inertia dependent,. acceleration limiting mechanical snubbers may be tested to verify only that activation takes place in both directions of travel;
}
2)
Snubber bleed, or release rate where required, is present in both tension and compression, within the specified range; 3)
-Where required, the force required to initiate or maintain 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 cor-related to the specified parameters through established methods.
i f.
Functional Test Failure Analysis I
i An evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause of the failure.
l The results of this evaluation shall be used, if applicable, in l
selecting snubbers to be tested in an effort to determine the OPERABILITY of other snubbers irrespective of type if they may be subject to the same failure mode.
For the snubbers found inoperable, an engineering evaluation shall be performed on the components to which the inoperable snubbers are attached.
The purpose of this engineering evaluation shall be to determine if the components to which the inoperable snubbers are l
attached.were adversely affected by the inoperability of the snubbers in order to ensure that the component remains capable of meeting the designed service.
l i
j ARKANSAS - UNIT 2 3/4 7-23a
' Amendment No.
62
l PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
If any snubber selected for functional testing either fails to activate or fails to move, i.e., frozen-in-place, the cause will be evaluated and, if caused by manufacturer or design deficiency, all snubbers of the same type subject to the same defect shall be evaluated in a manner to ensure their OPERABILITY. This require-ment shall be independent of the requirements stated in Specifica-tion 4.7.8 d for snubbers not meeting the functional test acceptance criteria.
g.
'Preservice Testing of Repatred, Replacement and New Snubbers Preservice operability testing shall be perfomed on repaired, replacement or new snubbers prior to installation. Testing may be at the manufacturer's facility. The testing shall verify the functional test acceptance criteria in 4.7.8.e.
In addition, a preservice inspection shall be perfomed'on each repaired,-replacement or new snubber and shall verify that:
1)
There are no visible signs of damage or impatied operability as a result of storage, handling or installation; 2)
The snubber load rating, location, orientation, position settingandconfiguration(attachments, extensions,etc.),
are in accordance with design; 3)
Adequate swing clearance is provided to allow snubber movement; 4)
If applicable, fluid is at the recomended level and fluid is not leaking from the snubber system; 5)
Structural connections such as pins, bearings, studs, fasteners and other connecting hardware such as lock nuts, tabs, wire, and cotter pins are installed correctly.
h.
Snubber Seal Replacement Program The seal service life of hydraulic snubbers shall be monitored to ensure that the service life is not exceeded between surveillance inspections. The expected service life for the various seals, seal materials, and applications shall be determined and established based on engineering information and the seals shall be replaced so i
that the expected service life will not be exceeded during a period F
when the snubber is required to be OPERABLE. The seal replacements shall be documented and the documentation shall be retained in i
accordance with Specification 6.10.2.
ARKANSAS-UNIT 2 3/4 7-23b Amendment No.
62
- ~
E9 i
'i TABLE 3.7-4 SAFETY RELATED HYDRAULIC SNUBBERS
- i HIGH' RADIATION
-1 SMUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT N
NO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **
TO REMOVE (A or I)
(Yes or No)
(Yes or No)
I Yes Yes On Reactor Coolant Pump)A HS-RCPA-E (South Secondary Cavity,
{
East Side, Elev. 390' 10" I
Yes Yes On Reactor Coolant Pump)A HS-RCPA-W (South Secondary cavity,
West Side, Eley. 390' 10" w
a g
I Yes Yes On Reactor Coolant Pump)B HS-RCPB-E y
(South Secondary Cavity,
4, 4
East Side, Elev. 390' 10" I
Yes Yes
.i I
HS-RCPB-W On Reactor Coolant Pump)B (South Secondary Cavity,
i West Side, Elev. 390' 10" HS-RCPC-E On Reactor Coolant Pump C I
Yes Yes (North Secondary cavity),
East Side, Eley. 390' 10" I
Yes Yes On"ReactorCoolantPump)C HS-RCPC-W (North Secondary Cavity,
3 West Side, Elev. 390' 10" t
I Yes Yes On Reactor Coolant Pump)D HS-RCPD-E 1
(North Secondary Cavity,
East Side, Eley. 390' 10" 1
j 4
2
?!
2>{}-
TABLE 3.7-4 (Continued) vi SAFETY RELATED HYDRAULIC SNUBBERS
- e C
35 HIGH RADIATION
-d SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT NO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **
TO REMOVE (A or I)
(Yes or No)
(Yes or No)
HS-RCPD-W On Reactor Coolant Pump)D I
Yes
.Yes (North Secondary Cavity,
West Side, Eley. 390' 10" HS-SGA-E On Steam Generator A I
Yes Yes (South Secondary Cavity),
ye East Side, Elev. 403' 7" a
HS-SGA-W On Steam Generator A I
Yes Yes A>
(South Secondary Cavity),
West Side, Elev. 403' 7" HS-SGB-E On Steam Generator B I
Yes Yes (North Secondary Cavity),
East Side. Elev. 403' 7" HS-SGB-W On Steam Generator B I
Yes Yes (North Secondary Cavity),
West Side, Eley. 403' 7"
- Snubbers may be added to safety related systems without prior License Amendment to Table 3.7-4 provided that a revision to Table 3.7-4 is included with the next License Amendment request.
- Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided'that a revision to Table 3.7-4 is included with the next License Amendment request.
9 4
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a A.RKANSAS - UNIT 2 3/4 7-26' Amendment No. 62 9
4.
TABLE 3.7-4n SAFETY RELATED MECHANCIAL SHOCK SUPPRESSORS (SNUB 8ERS)*
l l
l l SNUB 8ER l SNUB 8ER l SNUB 8ERS l SNUB 8ERS l j >! - I i5 l
l lIN HIGH IESPECI4LLYl INACCESSIBLE lACCESSISLEl
$E I l
I.
l RADIATION l DIFFICULT-lDURING lDURING l
y1 SNUB 8ER NUMBER I
LOCATION I'
ELEVATION l AREA lTO REMOVE lNDRMAL l NORMAL
,l l
l l
lDURING l SHUTDOMjl--
l0PERATION l0PERATION l I
l-l l
l l
$E 28CA1H2 Pressure Surge Line 376* 2 3/4" X
lQ 28CA1H3 Pressure Surge Line 376' 2 3/4" X
l 28CA14H1 Pressurizer Vent Line 415' 5" X
m i
28CA14H2 Pressurizer Vent Line 415' 5" X
j 28CA14H3 Pressurizer Vent.Line 414' 7 3/4"
'X 1
28CA14H5 Pressurizer Vent Line 415' 5" X
28CA14H7 Pressurizer Vent Line 407' 3" X
j 28CA14H10 Pressurizer Vent Line 413' 5" X
28CA14H12 Pressurizer Vent Line 415' 4 7/8" X
28CA14H13 Pressurizer Vent Line 415' 5" X
28CA14H14 Pressurizer Vent Line 415' 5" X
!w 28CA14H15 Pressurizer Vent Line 415' 5" X
~
l) 28 cal 6H3 (A)
Reactor Coolant System Vent 416' 3 3/8" X
28CA16H3 (8)
Reactor Coolant System Vent 416' 3 3/8" X
y
' A, 28CA16H5 (A)
Reactor Coolant System Vent 415' 8 5/16" X
g' 28CA16HS (8)
Reactor Coolant System Vent 415' 8 5/16" X
28CA16H10 (A)
Reactor Coolant System Vent 415' 6 3/16" X
28CA16H10 (8)
Reactor Coolant System Vent 415' 6 3/16" X
]
28CA16H12 Reactor Coolant System Vent 415' 8 1/2" X
a 28C82H12 Reactor Coolant System 368' 0" X
28C82H32 Reactor Coolant System 368' 0" X
2CCA13H2 Reactor Miscellaneous System 372' 3 11/16" X
4'"
2CCA13H3 Reactor Miscellaneous System 372' 3" X
2CCA13H4 Reactor Miscellaneous System 372' 0" X
2CCA14H2 Reactor Miscellaneous System 371' 9" X
2CCA14H3 Reactor Miscellaneous System 372' 1"
'X 2CCA14H4 Reactor Miscellaneous System 371'11" X
l'*0 2CCA15H17 Reactor Miscellaneous System 384' 0" X
2CCA15H9 Reactor Miscellaneous System 370' 9" X
2CCA15H19 Reactor Miscellaneous System 384' 0" X
i 2CCA15H24 Reactor Miscellaneous System 371' 0" X
}
2CCA15H26 Reactor Miscellaneous System 370' 9" X
i 2CCA15H27 Reactor Miscellaneous System 370' 9" X
}
2CCA15H29 Reactor Miscellaneous System 412' 6" X
4 I
i._,,_
ll TABLE 3.7-4m (Continued) 3 SAFETY RELATED MECHANCIAL SHOCK SUPPRESSORS (SNUB 8ERS)*
}3 l l
l lSNU88ER lSNU88ER l SNUB 8ERS lSNU88ERS -l
' {l-l l
lIN HIGH lESPECIALLYlINACCESSIBLEIACCESSISLEl 2 I i
l IRADIATIONl0IFFICULT lDURING lDURING.
l 4
- yi SNUBBER NupeER l
LOCATION I
ELEVATION l AREA lTO REMOVE l NORMAL INORMAL l
'a l
l 1
lDURING I
10PERATION-l0PERATION l l
l l
lMTMl l
l
~l
{E 2CCA15H30 Reactor Miscellaneous System 412' 6" X
1 jQ 2CCA160etail F Chemical and Volume Control 336' 6" X
l 2CCA160etail 1 Chemical and Volume Control 336' 6" X
i]
m 2CCA16H3 Chemical and Volume Control 336' 6"
,X 2CCA16HS Chemical and Volume Control 336' 6"
- X I
2CCA16H8 Chemical-and Volume Control 336' 6" X
n 2CCA16H9 Chemical and Volume Control 336' 6" X
1 l
2CCA17H15 (A)
Reactor Coolant System Vent 415'11 5/8" X
i 2CCA17H15 (8)
Reactor Coolant System Vent 415'11 5/8" X
I 2CCA17H22 (A)
Reactor Coolant System Vent 418' 1 3/4" X
2CCA17H22 (8)
Reactor Coolant System Vent 418' 1 3/4" X
iw 2CCA17H24 (A)
Reactor Coolant System Vent 418' 3 1/2" X
1 2CA17H24 (8)
Reactor Coolant System Vent 418' 3 1/2" X
2CCA17H25 (A)
Reactor Coolant System Vent 418' 3 5/16"
'X y
l A, 2CCA17H25 (8)
Reactor Coolant Syster Vent-418' 3 5/16" X
l g! 2CCA18H2 Reactor Coolant System 357' 0" X
j 2CCA18H4 Reactor Coolant System 357' 0" X
2CCA21H10 Safety Injection / Shutdown Cooling 378' 6" X
2CCA21H12 Safety Injection 384' 4 7/8" X
- g 2CCA21H16 (A)
Safety Injection 372' 0" X
X i
.5 2CCA21H16 (8)
Safety Injection 372' 0"
)5E 2CCA21H18 (A)
Safety Injection 388' 0" X
L 2CCA21H18 (8)
Safety Injection 388' 0" X
l 5 2CCA21H19 (A)
Safety Injection 372' 0" X
l.g 2CCA21H19 (8),
Safety Injection 372' 0" X
I I
2CCA21H15 Safety Injection 372' 0" X
i $ 2CCA21H17 Safety Injection 375' 0" X
Safety Injection 376' 0" X
i 2CCA22H13 2CCA22H14 Safety Injection 375' 4 7/16" X
2CCA22H15 (A)
Safety Injection 375' 4 7/16" X
l 2CCA22H15 (8)
Safety Injection 375' 4 7/16" X
2CCA22H17 Safety Injection 375' 4 7/16" X
t j
2CCA22H18 Safety Injection 384' 4" X
i
-2CCA22H19 Safety Injection 383' 4" X
]
+, -
.,.-__._n
TABLE 3.7-49 (Ct'ntinued)
SAFETY RELATED MECHANCIAL SHOCK SUPPRESSORS (SNUB 8ERS)*
~
I I
I ISNUB8ER ISNUB8ER lSNU88ERS l SNUB 8ERS l
>I l
l lIN HIGH N
IESPECI'LLYlINACCESSIBLEIACCESSIBLEl A
1 RI l
I lRADIATIONIDIFFICULT IDURING lDURING gl SNUB 8ER NUMBER l
LOCATION I
ELEVATION l AREA ITO REMOVE INORMAL INORMAL-1 I
i l
IDURING l
l0PERATION 10PERATION l i
'I i~
l_
12HlIIMDitLI I
l l
b l
g 2CCA22H21 Safety Injection 388' 0" X
q 2CCA22H22 Safety Injection 390' 8 1/8" X
2CCA23H11 Safety Injection 388' 0" X
m 2CCA23H18 Safety Injection 371' 4" X
2CCA23H21 Safety Injection 356'10 3/4" X
2CCA23H23 Safety Injection 351' 2" X
2CCA23H26 Safety Injection 377' 6 3/4" X
2CCA23H27 (A)
Safety Injection 377' 6 3/4" X
2CCA23H27 (8)
Safety Injection 377' 6 3/4" X
2CCA23H28 Safety Injection 369' 6" X
2CCA24H15 Safety Injection 388' 0" X
2CCA24H17 Safety Injection 386' 0" X
m g 2CCA24H19 Safety Injection 377' 0" X
2CCA24H24 Safety Injection 351' 2" X
y L 2CCA24H27 Safety Injection 351' 2" X
gi 2CCA25H3 Safety Injection 350'10" X
2CCA25H4 Safety Injection 350' 2" X
2CCA25H5 Safety Injection 347' 6" X
2CCA25H6 Safety Injection 353' 9" X
2CCA25H10 Safety Injection 354' 6" X
'2CCA25H13 Safety Injection 352' 1 1/2" X
k 2CCA25H14 Safety Injection 354' 6" X
1 R
2CCA26H2 Chemical and Volume Control 336' 6" X.
j g
2CCA32H2 Reactor Coolant Drain 357' 0" X
E 2CCA38H1 Reactor Coolant Drain 357' 0" X
2CCA38H3 Reactor Coolant Drain 357' 0" X
,o 2CC81H3 (A)
Letdown Line 345' 3 1/2" X
2CC81H3 (8)
Letdown Line 345' 3 1/2"~
X E 2CC82H2 Chemical and Volume Control 360' 0" X
2CC82HS Chemical and Volume Control 360' 0" X
2CC84H2 Safety injection 363' 0" X
2CC88H8 Charging Pump Discharge 342' 3" X
2CC88H11 Charging Pump Discharge 342' 3" X
2CC88H18 Charging Pump. Discharge 342' 3" X
1
TABLE 3.7-4m (Continued)
SAFETY RELATED MECHANCIAL SHOCK SUPPRESSORS (SNUB 8ERS)*
l l
>l l
l l SNUB 8ER l SNUB 8Elt l SNUBBERS l SNUB 8ERS l 1
$.1 1
l lIN HIGH lESPECIALLYlINACCESSI8LElACCESSI8tEl El l
l l RADIATION l DIFFICULT lDURING lDURING l
yl SNUB 8ER NupeER l
LOCATION l
ELEVATION l AREA lTO REMOVE l NORMAL l NORMAL l
t 1
l l
lDURING l0PERATION l0PERATION l.;
l5HUTDOMl i
l l
l l
l l
l i
E 2CC854H2 Sample System 357' 0" X
l Z 2CC854H3 Sample System 357' 0" X
2CC869H1 Reactor' Coolant Drain 336' 6"
~
X m
2CC869H3 Reactor Coolant Drain 336' 6" X
2CC869H4 Reactor Coolant Drain 336' 6" X,
-2CC876H2 (A)
Reactor Coolant System Vent 418' 2 3/4" X
4 2CC876H2 (8)
Reactor Coolant System Vent 416'11" X
{
2CC876H10 (A)
Reactor Coolant System Vent 416'11" X
l 2CCB76H10 (8)
Reactor Coolant System Vent 416'11" X
2CC876H11 (A)
Reactor Coolant System Vent 415' 5" X
2CC876H11 (B)
Reactor Coolant System Vent 415' 5" X
2CC876H12 Reactor Coolant System Vent 416' 5 1/2" X
w
}
} 2CC876H14 Reactor Coolant System Vent 418'11 1/4" X
j 2CC876H17 (A)
Reactor Coolant System Vent 417' 6" X
y k 2CC876H17 (8)
Reactor Coolant System Vent 417' 6",
X E 20881H2 (A)
Main Feedwater 402' O 11/32" X
l 20881H2 (8)
Main Fe dvater 402' O 11/32" X
20881H3 Main FeeJwater 402' 0 3/8" X
Main Feedwater 404' 0" X
l k,,20881H4(A) 20881H4 (8)
Main Feedwater 404' 0" X
r g 20881H6 Main Feedwater 404' 4" X
g 2D881H8 Main Feedwater 387' 0" X
i g
20881H9 Main Feedwater 388' 0 3/8" X
_. 20881H10 Main Feedwater 386' 0" X
j f 20881H12 Main Feedwater 369' 4 1/2" X
20081H13 Main Feedwater 368' 4 1/2" X
j 20881H14 Main Feedwater 355' 6" X
j 20881H17 Main Feedwater 402' 0 5/16" X
20082H2 (A)
Main Feedwater 391' 1 1/4" X
J 3
1 20082H2 (8)
Main Feedwater 391' 1 1/4" X
{
20082H8 Main Feedwater 358' 6" X
j 20082H11 Main Feedwater 347' 6" X
i 20882H13 Main Feedwater 351' 7" X
l 20882H15 Main Feedwater 362'11 1/8" X
j
l TABLE 3.7-4a (Continued) l
~
SAFETY RELATED MECHANCIAL SHOCK SUPPRESSORS (SNUB 8ERS)*
q i
> I l
l l$ NUB 8ER ISNUB8EJt ISNUB8ERS l SNUB 8ERS l
$-l i
I lIN HIGH lESPECIALLYlINACCESSIBLEIACCESS18LEl I
= l l
l l RADIATION l0IFFICULT l0URING l00 RING l
y i SNUB 8ER NUBBER I
LOCATION I
ELEVATION l AREA lTO REMOVE IMORMAL l NORMAL,, l 1
I l
10PERATION 10PERATION l lDURING ISHUTDOMl
!ii i I'
l l
l l
l Q
20882H16 Main Feedwater 374' 0" X
i 20882H17 (A)
Main Feedwater 347' 6" X-ro 20882H17 (8)
Main Feedwater 347' 6" X
20882H19 Main Feedwater 353' 6" X
4 l
20883H1 Emergency Feedwater 399' 8 5/16" X
1 20883H2 MFW to SG 2E26A 400' 4 3/16" X
l 20883H5 Emergency Feedwater 377' 6" X
.20883H13 Emergency Feedwater 400' 4 5/16" X
20883H15 Emergency Feedwater 400' 4 3/16" X
i 20883H16 Emergency Feedwater 399' 4 5/16" X
20883H17 Emergency Feedwater 399' 4 3/16" X
20884H1 Emergency Feedwater 370' 0" X
,w 2 20884H2 Emergency Feedwater 372' 2 13/16" X
+
20884H3 (A)
Emergency Feedwater 370' 0" X
y j
s'o 20884H3 (8)
Emergency Feedwater 370' 0" X
j E'
20884HS Emergency Feedwater 370' 0" X
j 20887H5 Reactor Miscellaneous System 376' 2" X
208814H1 Steam Generator Secondary System 386' 0" X
4 Steam Generator Secondary System 386' 0" X
F.208814H2 208814H3 Steam Generator Secondary System 386' 0-x 208814H4 Steam Generator Secondary System 386' 0" X
i 3
20801H11 Main Feedwater 336'11 7/8" X
l 3
20801H17 (A)
Main Feedwater 364' 8" X
20801H17 (8)
Main Feedwater 364' 8" X
l E
20802H11 Main Feedwater 363' 5" X
20802H12 Main Feedwater 386' 0" X
i E 20802H13 Main Feedwater 380' 9" X
20802H14 (A)
Main Feedwater 380' 9" X
20802H14 (8)
Main Feedwater 380' 9" X
2E881AH4 Main Steam 425' 1 1/2" X
2E881AHS Main Steam 436' 2 31/32" X
4 2E881AH6 (A)
Main Steam 436' 3" X
2E881AH6 (8)
Main Steam 436' 3" X
j 436' 2 31/32" X
2E881AH7 Main Steam
i i
TABLE 3.7-49 (Centinued) i 4
{
SAFETY RELATED MECHANCIAL SHOCK SUPPRESSORS (SNU88ERS)*
i l
>l l
l lSNU88ER l SNUB 8ER l SNUB 8ERS l SNUB 8ERS l
- -l l
l lIN HIGH IESPECIALLYlINACCESSIBLEIACCESSIBLEl I
3E l l
l lRADIATIONIDIFFICULT lDURING IDURING l
!O I SNUB 8ER HUSSER l
LOCATION l
ELEVATION l AREA lTO REMOVE l NORMAL l NORMAL l
'f I I
I lDURING l
10PERATION l0PERATION l EI l
I of I
l l
l 1
Q 2E881H4 Main Steam 428' 4" X
i 2E882AH4 Main Steam 436' 2 31/32" X
m 4
2EB82AHS Main Steam 436' 2 31/32" X
2E882AH6 (A)
Main Steam 436' 3" i
2EB82AH6 (B)
Main Steam 436' 3" X
X 2E882AH7 Main Steam 436' 2 31/32" X
2EB82H4 Main Steam 436' 3" X
2EB82HS (A)
Main Steam 413' 8 1/2" X
r i
2 EBB 2HS (B)
Main Steam 413' 8 1/2" X
1 2EB82H6 (A)
Main Steam 414' 6" X
l 2 EBB 2H6 (B)
414' 6" X
2E887H2 Main Steam 440' 3" X
w l
1 2EB88H2 Main Steam 426' 2 7/8" X
j 2EB816H3 Steam Generator Secondary System 386' 0" X.
y i
4 2EB816HS Steam Generator SecondaryiSystem 386' 0" X
2E8816H6 Steam Generator Secondary System 386' 0" X
2E8816H7 Steam Generator Secondary System 386' 0" X
Steam Generator Secondary System 386' 0" X
[ 2EB816H8
}
2fB817-1H002 Steam Generator Secondary System Above 386' 0" X
g.2E8817-1H003 Steam Generator Secondary System Above 386' 0" X
t j
g 2EB817-1H004 Steam Generator Secondary System Above 386' 0" X
=
2E8817-1H005' Steam Generator Secondary System Above 386' C" X
2E8817-1H006 Steam Generator Secondary System Above 386' 0" X-6 2EB830H3 Steam Generator Secondary System 405' 6" X
'm 2E8830H4 Steam Generator Secondary System 405' 6" X
2E8830H7 Steam Generator Secondary System 405' 6" X
2EB830H8 Steam Generator Secondary System 405' 6" X
i 2EB831H2 Steam Generator Secondary System 405' 6" X
j 2E8C1H9 (A)
Main Steam 350' 3" X
l 2EBC1H9 (8)
Main Steam 350' 3" X.
l 2E8C1H26 Main Steam 343' 2"
~X 2EBC1H29 Main Steam 340' 2"
~
X X
2EBC1H30 Main Steam 339' 6 5/8" l
2E8C1H31 Main Steam 414' 0" X
l l
i TABLE 3.7-43 (Centinued)
{
SAFETY RELATED MECHANCIAL SHOCK SUPPRESSORS (SNU88ERS)*
> l l
l lSNU88ER ISNUBBElt ISNU88ERS ISNU88ERS l
$-l l
l lIN HIGH lESPECIALLYl INACCESSIBLE lACCESSI8LEl E l l
l l RADIATION 10lFFICULT lDURING l00 RING l
yl SNUB 8ER NUNBER l
LOCATION
'l ELEVATION l AREA lTO REMOVE INORMAL-
-l NORMAL.
l l
l l
lDURING lSHUTD M ll l0PERATION l0PERATION l l
1 i
l
-l l
l E
2EBC2H4 Main Steam 421' 1" X
Z 2E8C2H7 Main Steam 421' 1"
-X.
d i
ro 2E801H1 (A)
Main Steam 404' 9" X
1 2E801H1 (8)
Main Steam 404' 9" X
2E801H2 (A)
Main Steam 403' 6" X
2E801H2 (8)
Main Steam 403' 6" X
i 2E801H11 (A)
Main Steam 346' 0" X
j
- 2E801H11 (8)
Main Steam 346' 0" X
j 2E801H12' Main Steam 346' 0" X-2E801H13 (A)
Main Steam 354' 0" X
l 2E801H13 (B)
Main Steam 354' 0"-
X i
2E801H14 Main Steam 354' 0" X
w1 2E801H15 Main Steam 353' 9" X
2E801H16 Main Steam 354' 0" X
l y
s'o 2E802H1 (A)
404' 6 1/2" X-2E802H1 (B)
Main Steam 404' 6 1/2" X
2E802H2 (A)
Main Steam 403' 6" X
l 2E802H2 (B)
Main Steam 403' 6" X
-2E802H11 Main Steam 346' 2" X
f 2E802H12 Main Steam 346' 0" X
iy 2E802H13 Main Steam 346' 0" X
5 2E802H14 Main Steam 346' 0" X
)
)
- E 2E802H15 (A)
Main Steam 346' 0" X
i 2
2E802H15 (8)
Main Steam 346' 0" X
i 5
2E802H16 Main Steam 346' 0" X
1 2E8022HB Main Steam Dump to Condensate 358' 0" X
- z P
2E8028H7 Main Steam 358' 0" X
l 2E8056-2H001 Main Steam 423'10 7/8"~
X
$E 2E8056-2H002 Main Steam 423'10 7/8" X
2E8056-2H003 Main Steam 423'10 7/8"
'X 2E8056-2H004 Main Steam 423'10 7/8" X
l
-2E8056-3H002 Main Steam 437' 6" X
i 2E8056-3H003 Main Steam 437' 6" X
i 2E8080H001 Steam Generator Secondary System 404' 0" X
}
I
4 TABLE 3.7-4m (Centinued)
SAFETY RELATED MECHANCIAL SHOCK SUPPRESSORS (SNUB 8ERS)*
l l
j; I I
I ISNUB8ER l SNUB 8EJt l SNUB 8ERS ISNUB8ERS l y.1 l
l
.lIN HIGH lESPECIALLYl INACCESSIBLE lACCESSI8LEl j
gi l
i 1 RADIATION l DIFFICULT lDURING lDURING l
SNUB 8ER NUH8ER I
LOCATION l
ELEVATION l AREA ITO REMOVE l NORMAL l NORMAL i
g ll I
1-l lDURING I M Toon"l l0PERATION l0PERATION l l
E l2FCC1H8 I
I I
I I
i 1
Pressurizer Relief Piping 412' 2 3/4" X
U 2FCC1H9 Pressurizer Relief Piping 401' 9" X
ro 2FCC1H10 Pressurizer Relief Piping 401' 9" X
2FCC1H11 Reactor Miscellaneous 398' 3" X
2FCC1H12 Reactor Miscellaneous 358'11" X.
l 2FCC1H22 (A)
Pressurizer Relief Piping 416'11 11/16" X
j 2FCC1H22 (8)
Pressurizer Relief Piping 416'11 11/16" X
2FCC1H23 Pressurizer Relief Piping 416'11 11/16" X
j 2FCC1H24 (A)
Pressurizer Relief Piping 413'10 1/16" X
2FCC1H24 (8)
Pressurizer Relief Piping 413'10 1/16" X
2FCC2HS Pressurizer Relief Piping 394' 6" X
w 2FCC2H6 Pressurizer Relief Piping 386' 6" X
1 2FCC2H8 Pressurizer Relief Piping 416'11 11/16" X
u 2FCC2H9 Pressurizer Relief Piping 415' 7 1/2" X
l s'o 2FCC2H12 Pressurizer Relief Piping 412' 9 7/16" X
E 2FCC2H13 Pressurizer Relief Piping 412' 9 7/16" X
- 2FCC2H16 -
Pressurizer Relief Piping 409' 2 3/4" X
l 2G8075H3 Steam Relief Stacks to Atmosphere X
i
- p 2G8076H3 Steam Rellef Stacks to Atmosphere 445' O 1/4" X-j s
2G8076H5 Steam Relief Stacks to Atmosphere 441' 8" X
l l
E "2GC82H3 Safety Injection 318' 6 3/4" X
1 2
2GC82H22 Safety Injection 329' 4 3/4" X
l 5
2GC83H24 Safety Injection 329' 9" X
t
=
2GC85H21 Safety Injection 347' 6" X
l 2GC85H23 (A)
Safety Injection 342' 3" X
2GC85H23 (8)
Safety Injection 342' 3" X
l
'u 2GC85H26 Safety Injection 348' 3" X,
2GC85H28 Safety Injection 349' 0" X-2GC85H31 (A)
Safety Injection 318' 6 3/4"
.X 2GC85H31 (8)
Safety Injection 318' 6 3/4" X.
2GC89H24 Safety Injection 3263" X
t i
2GC810HS Containment Spray 330' 6 1/2" X
l X
l 2GC811HS
. Spray Pump 2P358 Discharge 329' 6 3/4" 2GC8513H2 Auto. Pressurizer Vent Line' 415' 5" X
I
. TABLE 3.7-4n (Continued)
SAFETY RELATED HECHANCIAL SHOCK SUPPRESSORS (SNUB 8ERS)*
>I l
l iSNUB8ER l$ NUB 8ER l SNUB 8ERS l SNUB 8ERS l "i
I I
IIN HIGH lESPECI'ALLYlINACCESSI8LElACCESSIBLEl hl I
i 1 RADIATION l0IFFICULT l0URING 100 RING l
gi SNU88ER NLNBER I
LOCATION 1-ELEVATION l AREA lTO RENOVE l NORMAL lN0fMAL
-l "I
1 l
lDURING I
l0PERATION 10PERATION l I
I I
ljgLTM) l l
l g 2GC8514H2 Auto. Pressurizer Vent Line 415' 5" X
q 2GC8514H3 Auto. Pressurizer Vent Line 415' 5" X
2HBC41H2O SW from 2HBC63 to 2VEIA 391' 7 3/4" X
2HBC98H9 SW from 2H8C64 to 2VE18 391' 7 3/4" X
2MBCIC3H17 Service Water Supply 367'10" X
2HBC103H18 Service Water Supply 370' 2 3/4" X
2teC103H2O Service Water Supply 370' 3" X
2teC103H22
-Service Water 370' 4" X
2teC104H16 Service Water 371' 9"-
X 2teC104H18 Service Water 371' 9" X
2teC105H4 Service Water Return 371' 1 7/8" X
2teC105H14 (A)
Service Water 367' 5 3/4" X
R 2H8C105H14 (8)
Service Water 367' S 3/4" X
~
" 2teC105H16 Service Water Branches 371'10"
' 'X 7 2 HOC 105H17 Service Water Branches 371'10" X
E 2HBC105H18 Service Water Branches 371'10" X
^
2HBC105H27 Service Water 389' 0" X
2090750H6 Main Feedwater 371' 4" X-2090750H9 Main Feedwater 373' 1 9/16" X
y 2HC83H170 Containment Spray Header 351' S 1/4" X
g 2HC83H177 Containment Spray 421' 6" X
g 2HC84H176 Containment Spray 347' 6" X
g 2HC84H179 Containment Spray 347' 6" X
2HC84H188 (A)
Containment Spray 347' 6" X
e y
2HC84H188 (8)
Containment Spray 347' 6" X
2HC84H189 Containment Spray 347' 6" X
g 2HC84H190 Containment Spray 349' 0" X
2HC84H194 Containment Spray 356' 7"
~
X 2HC813H14 (A)
Containment Spray 320'10" X
2HC813H14 (B)
Containment Spray 320'10" X
2HC815H15 (A)
ESFAS Pump Section and Vent Pump 320' 7 7/8" X
2HC815H15 (8)
ESFAS Pump Suction and Vent Pump 320' 7 7/8" X
2HC827H7 (A)
Containment Spray 326' 6" X
2HC827H7 (8)
Containment Spray 326' 6" X
I
TABLE 3.7-4,(Continued)
SAFETY RELATED MECHANCIAL SHOCK SUPPRESSORS (SNU68ERS)*
.g l l
l lSNU68ER lSNU68Elt l$ NUB 8ERS lSNU68ERS l g.I l
l IIN HIGH lESPECIALLYlINACCESSIBLEIACCESSIBLEl 3l l
l l RADIATION l DIFFICULT lDURING lDURING l
3 lI SNUBBER NUMBER l
LOCATION l
ELEVATION l AREA ITO REMOVE l NORMAL l NORMAL l
l l
lDURING l
l0PERATION l0PERATION l b
,I I
l 12BLIlmtLi i
I l
E 2tKC53H9 fuel Pool System
-351' 6" X
G 2tKCS3H10 Fuel Pool System 347' 8" X
m 2fECS3H14 Fuel Pool System 335' 0" X
2HCCS3H15 Fuel Pool System 343' 6" X
2HCC77H6 Reactor Coolant Drain 336' 6" X
2HCC77H7 Reactor Coolant Drain 336' 6" X
2J8D20lH8 (A)
Diesel and Fuel Oil 380'10 9/16" X
- 2J8D201H8 (8)
Diesel and Fuel Oil 380'10 9/16" X
2J8020lH9 Diesel and Fuel Oil 380'10 9/16" X
2J8020lH11 (A)
Diesel and Fuel Oil 380' 7 1/16" X
2J8020lH11 (8)
Diesel and Fuel Oil 380' 7 1/16" X
2J8D202H8 (A)
Diesel and Fuel 011 381'11 1/2" X
w1 2J80202H8 (8)
Dier.el and Fuel 011 381'11 1/2" X
y 2J80202tt9 Diesel and Fuel 011 381'11 1/2" X
h 2J80202H11 (A)
Diesel and Fuel 011 381' 3",
X E'
2J80202H11 (8)
Diesel and Fuel Oil 381' 3" X
~
iir o.
3 A
?
n e
9
e TABLE 3.7-4a (Continued)
TABLE NOTATION l
l a.
Snubbers mhy be added to safety-related systems without prior License Amendment to Table 3.7-4a provided that a revision to Table 3.7-4a is included with the next License Amendment Request.
b.
Modifications to this column due' to changes in high radiation.
areas may be made without prior License Amendment provided that a revision to Table 3.7-4a is included with the next License Amendment Request.
l l
t
- ARKANSAS - UNIT 2 3/4 7-26k Amandment No. 62
+.
PLANT SYSTEMS BASES following all credible accident conditions.
The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the-requirements of General Design Criteria 19 of Appendix "A",10 CFR 50.
3/4.7.8 SH0CK SUPPRESSORS (SNUBBERS)
All snubbers are required OPERABLE to ensure that the structural integ-I rity 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 I
on non-safety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.
The.isual inspection frequency is based upon maintaining a constant l
level of snubber protection to systems.
Therefore, the required inspection interval varies inversely with the observed snubber failure and is determined by the number of inoperable snubbers found during an inspection.
Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection.
However, the result of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval.
Any inspection whose results require a shorter inspection interval will override the previous schedule.
When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible and, verified by inservice functional testing, that snubber may be exempted from being counted as inoperable.
Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection, or are similarly located or exposed to the same environmental conditions such as temperature, radiation and vibration.
When a snubber is found inoperable, an engineering evaluatidn is per-formed, in addition to the determination of the snubber mode of failure, in order to determine if any safety-related component or system has been adversely affected by the inoperability of the snubber.
The engineering evaluation is performed to determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.
ARKANSAS - UNIT 2 B 3/4 7-5 Amendment No. 62 G
~
PLANT SYSTEMS BASES l
(
i To provide further assurance of snubber reliability, a representa-i tive' sample of the installed snubbers will be functionally tested during plant shutdowns at 18 month intervals.
These tests will include stroking of the snubbers to verify proper piston movement, lock-up and i
bleed. Observed failures of these sample snubbers will require functional testing of additional units. To minimize personnel exposures, snubbers installed in areas which have high radiation fields during shutdown or in.
especially difficult to remove locations may be exempted from these functional testing requirements provided the OPERABILITY of these snubbers was demonstrated during functional testing at either the completion of j
their fabrication or at a subsequent date.
)
l 3/4.7.9 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requirin leaktesting,includingalphaemitters,isbasedon10CFR70.39(c)g limits for plutonium. This limitation will ensure that leakage from i
byproduct, source, and special nuclear material sources will not exceed l
allowable intake values.
3/4.7.10 FIRE SUPPRESSION SYSTEMS _
The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires i
occurring in any portion of the facility where safety related equipment is located. The fire suppression system consists of the water system, spray and/or sprinklers, and fire hose stations. The collective capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program.
In the event the portions of the fire suppression systems are ino'perable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is l
restored to service.
In the event the fire suppression water system becomes inoperable.
[
imediate corrective measures must be taken since this system provides the major fire suppression capability of the plant.
The requirement for i
a twenty-four hour report to the Comission provides for prompt evaluation 1
of the acceptability of the corrective measures to provide adequate fire j
suppression capability for the continued protection of the nuclear plant.
l ARKANSAS -UNIT 2 B 3/4 7-6 l
l n,+.,--
,,,,n-.~.,--n-----.,n_.,-,,,-,,-,,n-m,,,.,,,,,-,__,.,,nn,.~
am-n.--_,-.-,--,-,,.-------n----,,
ADMINISTRATIVE CONTROLS f.
Records of reactor tests and experiments.
g.
Records of training and qualification for current members of the unit staff.
h.
Records of in-service inspections performed pursuant to these Technical Specifications.
1.
Records of Quality Assurance activities required by the QA Manual.
j.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k.
Records of meetings of the PSC and the SRC.
1.
Records of changes to the Core Protection Calculator System (CPCS) SOFTWARE.
Changes to the CPCS SOFTWARE shall be made in accordance with methods approved by the NRC.
These records shall include the following:
1.
Purpose of change.
2.
Detailed description of change including algorithms, changes to the assembly listings, checksums and disk identification numbers.
3.
Summary of validation test results.
m; Records of Environmental Qualification which are covered under the provisions of paragraph 6.12.
n.
Records of the service lives of the seals of all hydraulic snubbers listed on Tables.3.7-4,'includ,ing the date at which the service life commences and. associated installation and-maintenance records.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 ENVIRONMENTAL QUALIFICATION 6.12.1 By no later.than June 30, 1982 all safety-related electrical equip-ment in the facility shall be qualified in accordance with the provisions of:
Division of Operating Reactors " Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors" (DOR Guidelines); or NUREG-0588 " Interim Staff Position on Environmental Qualifi-cation of Safety-Related Electrical Equipment" December 1979.
Copies of these documents are attached to Order for Modification of License NPF-6 dated October 24, 1980.
ARKANSAS - UNIT 2 6-23 Amendment No. 52, SD,62
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t 1 ADMINISTRATIVE CONTROLS
'6.12.2 By no later than December 1,1980, complete and auditable records must be available and maintained at a central location which describe the environ-i-
mental qualification method used.for all safety-related electrical equipment in sufficient detail to document the. degree of compliance with the D0R Guide-lines or NUREG-0588.
Thereafter, such records should be updated and maintained current as equipment:4s replaced,.further tested, or otherwise further qualified.
16. 1 3 HIGH RADIATION AREA 6.13.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area (as defined in 20.202(b)(3) of 10 CFR 20) in which the intensity of radiation is 1000 mrea/hr or less i
shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring-the issuance of a radiation work permit. ' Any individual or group of individuals pennitted to'enteF'suc~h' '
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j areas shall be provided with or accompanied by one or, mor_e of the, follow 1,ng:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
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b.
A'Eadiation monitoring device whi.ch continuously integrates the
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l radiation dose rate in the area and alarms when a.present.
integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in tha area has been established and personnel have been made knowledge-able of them.
4 c.
An individual qualified in radiation protection' procedures who is l
equipped with a radiation dose rate monitoring device.
This l
individual shall be responsible for providing positive control j
over the activities within the area and shall perform periodic radiation surveillance at the frequency specified in the radiation work permit.
l 6.13.2 The requirements of 6.13.1, above, shall also apply to each high j
radiation area in which the intensity of radiation is greater than 1000 mrem /hr.
In addition; locked doors shall be provided to prevent unauthorized entry into such areas and access to these areas shall be maintained under the i
administrative control of the Shift Supervisor on duty and/or the Health Physics Superintendent.
L ARKANSAS - UNIT 2 624 Orddf digid pdidpdf gif Jppp q
Amendment No. f)* D* 60 l
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