ML20084R402

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Proposed Tech Specs Increasing Total Number of safety-related Snubbers & Scope of Surveillance Requirements.Significant Hazards Determination Encl
ML20084R402
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 05/19/1984
From:
ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20084R398 List:
References
NUDOCS 8405220347
Download: ML20084R402 (25)
v • d • e


Text

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE SE@lFEMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves.............................. 3/4 7-1 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 f 3/4.7.5 FLOOD PROTECTION........................... 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 SH0CK SUPPRESSORS (SNUBBERS)............... 3/4 7-22 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 POOL STRUCTURAL INTEGRITY....... 3/4 7-38 3/4.8 ELECTRICAL POWER SYSTEMS 3i.8.1 A. C.' SOURCES 0perating.................................. 3/4 8-1 Shutdown................................... 3/4 8-5 ARKANSAS - UNIT 2- VII kho!

P 0

.~

J INDEX BASES SECTION

' 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 CONDITIONING / AIR FILITRATION SYSTEM......................... B 3/4 7-4 3/4.7.8 SHOCK SUPPRESSORS (SNUBBERS)............... B 3/4 7-5 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 e 3/4.7.12 SPENT FUEL POOL STRUCTURAL INTEGRITY. . . . . . . B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS................... B 3/4 8-1 3/4.9 REFUELING OPERATIONS ,

3/4.9.1 BORON CONCENTRATION........................ B 3/4 9-1 3/4.9.2 INSTRUMENTATION............................ B-3/4 9-1 3/4.9.3 DECAY TIME.......................I......... B 3/4 9-1 3/4.9.4 CONTAINMENT PENETRATIONS................... .B 3/4 9-1 ARKANSAS - UNIT 2 XI-l c.

_i____-_____.___ _ _ _ . . _ .

PLANT SYSTEMS 3/4.7.8 SHOCK SUPPRESSORS (SNUBBERS 1 LIMITING CONDITION FOR OPERATION _

3.7.8 All snubbers listed in Tables 3.7-4 and 3.7-4a shall be OPERABLE.

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 evaluation 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 I

As used in this specification, type of snubber shall mean snubbers 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 I 25%

2 6 months I 25%

3, 4 124 days i25%

5,6,7 62 days 1 25%

8 or more 31 days 1 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.

i ARKANSAS - UNIT 2 3/4 7-22 l

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l 4

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.

ARKANSAS - UNIT 2 3/4 7-22a

r PLANT SYSTEMS SURVEILLANCE' REQUIREMENTS (Continued)

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 inspections may be determined OPERABLE for the purpose of-establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested fr: the as found condition and determined OPERABLE per Specifications 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 common hydraulic fluid reservoir shall be evaluated for operability _if any snubber connected to that reservoir is determined to be inoperable.

d. Functional Tests At least once each refueling shutdown a representative sample of snubbers shall be tested 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 shall be functionally tested until no more failures are found or until all snubbers have been functionally tested.

The representative samples for the functional test sample plans shall be randomly selected from the snubbers required by~

Specification 3.7.8 and reviewed before beginning the testing.

The review shall ensure as far as practical that they are representative of the various configurations, operating erivironments,-range of sizes, and capacities. Snubbers placed in the same locations 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 l during the functional testing, additional sampling is required due to failure of only one type of snubber, the functional 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.

1

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l l ARKANSAS - UNIT 2 3/4 7-23 i

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PLANT SYSTEMS f

, SURVEILLANCE REQUIREMENTS (Continued)

e. Functional Test Acceptance Criteria The snubber functional test shall verify that:

i

1) Activation (restraining action) is achieved within the I

specified 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; 4

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 j direction of travel; and I 4) For snubbers specifically required not to displace under

{ continuous load, the ability of the snubber to withstand load

without displacement.

I

}' Testing methods may be used to measure parameters indirectly or parameters other than those specified if those results can be j correlated to the specified parameters through established

-methods.

f. Functional Test Failure Analysis i An evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause of the failure.

The results of this evaluation shall be used, if applicable, in selecting snubbers to be tested in an effort to determine the j OPERABILITY of other snubbers irrespective of type if they may be t subject to the same failure mode.

i l

For the snubbers found inoperable, an engineering evaluation shall ,

t,e 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 attached were adversely affected by the inoperability of the

snubbers in order to ensure that the component remains capable of meeting the designed service.

I If any snubber selected for functional testing either fails to I

activate or falls'tn move, i.e., frozen-in place, the cause will i

be evaluated and, if caused by manufacturer or design deficiency, i f all snubbers of the same type subject to the same defect shall be l

ARKANSAS - UNIT 2 3/4 7-23a

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) evaluated in a manner to ensure their OPERABILITY. This requirement shall be independent of the requirements stated in Specification 4.7.8.d for snubbers not meeting the functional test acceptance criteria.

g. Preservice Testing of Repaired, Replacement and New Snubbers Preservice operability testing shall be performed 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 performed on each repaired, replacement or new snubber and shall verify that:

1) There are no visible signs of damage or impaired operability as a result of storage, handling or installation;
2) 'The snubber load rating, location, orientation, positien setting and configuration (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 recommended 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 that the' expected service life will not be exceeded during a period when the snubber is required to be OPERA 8LE. The seal replacements shall be oocumented and the documentation shall be retained in accordance with Specification 6.10.2.

ARKANSAS - UNIT 2 3/4 7-23b c-_

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9 1 I TABLE 4.7-4 (Deleted) \

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', ARKANSAS - UNIT 2 3/4 7-26 i

TABLE 3.7-4a SAFETY RELATED MECHANCIAL SHOCK SUPPRESSORS (SNUBBERS)a 3, l l l l SNUBBER l SNUBBER l SNUBBERS l SNUBBERS I

?! l l l lIN HIGH IESPECIALLYl INACCESSIBLE lACCESSIBLEl 3E l l l l RADIATION l DIFFICULT lDURING lDURING l

$0 l SNUBBER NUMBER l LOCATION l ELEVATION l AREA lTO REMOVE l NORMAL INORMAL l

l l l lDURING bl l0PERATION 10PERATION l l I I I12LIQQMLI l I _l Ei 2BCAlH2 Pressure Surge Line 376' 2 3/4" X

  • 2BCA1H3 Pressure Surge Line 376' 2 3/4" X na 2BCA14H1 Pressurizer Vent Line 415' 5" X 2BCA14H2 Pressurizer Vent Line 415' 5" X 2BCA14H3 Pressurizer Vent Line 414' 7 3/4" X 2BCA14HS Pressurizer Vent Line 415' 5" X 2BCA14H7 Pressurizer Vent Line 407' 3" X 2BCA14H10 Pressurizer Vent Line 413' 5" X 2BCA14H12 Pressurizer Vent Line 415' 4 7/8" X 2BCA14H13 Pressurizer Vent Line 415' 5" X 2BCA14H14 Pressurizer Vent Line 415' 5" X o, 2BCA14H15 Pressurizer Vent Line 415' 5" X

]s 2BCA16H3 (A) Reactor Coolant System Vent 416' 3 3/8" X

,, 2BCA16H3 (B) Reactor Coolant System Vent 416' 3 3/8" X 43 2BCA16H5 (A) Reactor Coolant System Vent 415' 8 5/16" X 27 2BCA16HS (B) Reactor Coolant System Vent 415' 8 5/16" X 2BCA16H10 (A) Reactor Coolant System Vent 415' 6 3/16" X 2BCA16H10 (B) Reactor Coolant System Vent 415' 6 3/16" X 28CA16H12 Reactor Coolant System Vent 415' 8 1/2" . X 2BCB2H12 Reactor Coolant System 368' 0" X .

2BCB2H32 Reactor Coolant System 368' 0" X 2CCA13H2 Reactor Miscellaneous System 372' 3 11/16" X 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 2CCA15H9 Reacto- Miscellaneous System 370' 9" X 2CCA15H17 Reactor Miscellaneous System 384' 0" X 2CCA15H19 Reactor Miscellaneous System 384' 0" X 2CCA15H24 Reactor Miscellaneous System 371' 0" X 2CCA15H26 Reactor Miscellaneous System 370' 9" X 2CCA15H27 Reactor Miscellaneous System 370' 9" X 2CCA15H29 Reactor Miscellaneous System 412' 6" X

a TABLE 3.7-4a (Continued) .

SAFETY RELATED MECHANCIAL SHOCK SUPPRESSORS (SNUBBERS)a

{g l l l l SNUBBER l SNUBBER l SNUBBERS l SNUBBERS l l l lIN HIGH lESPECIALLYlINACCESSIBLEIACCESSIBLE!

!hll l l l RADIATION l DIFFICULT lDURING IDURING l E2 l SNUB 8ER NUMBER l LOCATION l ELEVATION l AREA lTO REMOVE l NORMAL l NORMAL l l

I Ei 2CCA15H30 l

I -

Reactor Miscellaneous System l

1 412' 6" ldl i

DURING i

l0PERATION l

X l0PERATION l i I 1 2CCA160etati F Chemical and Volume Control 336' 6" X n3 2CCA16 Detail 1 Chemical and Volume Control 336' 6" X 2CCA16H3 Chemical and Volume Control 336' 6" X 2CCA16H5 Chemical and Volume Control 336' 6" X 2CCA16H8 Chemical and Volume Control 336' 6" X 2CCA16H9 Chemical and Volume Control 336' 6" X 2CCA17H15 (A) Reactor Coolant System Vent 415'11 5/8" X 2CCA17H15 (B) Reactor Coolant System Vent 415'11 5/8" X 2CCA17H22 (A) Reactor Coolant System Vent 418' 1 3/4" X 2CCA17H22 (B) Reactor Coolant System Vent 418' 1 3/4" X u, 2CCA17H24 (A) Reactor Coolant System Vent 418' 3 1/2" X

]; 2CCA17H24 (B) Reactor Coolant System Vent 418' 3 1/2" X sa 2CCA17H25 (A) Reactor Coolant System Vent 418' 3 5/16" X 43 2CCA17H25 (B) Reactor Coolant System Vent 418' 3 5/16" X Ep 2CCA18H2 Reactor Coolant System 357' 0" X 2CCA18H4 Reactor Coolant System 357' 0" X 2CCA21H10 Safety Injection / Shutdown Cooling 378' 6" X 2CCA21H12 Safety Injection 384' 4 7/8" X 2CCA21H16 (A) Safety Injection 372' 0" X 2CCA21H16 (B) Safety Injection 372' 0" .

2CCA21H18 (A) Safety Injection 388' 0" X 2CCA21H18 (B) Safety Injection 388' 0" X 2CCA21H19 (A) Safety Injection 372' 0" X 2CCA21H19 (B) Safety Injection 372' 0" X 2CCA21H15 Safety Injection 372' 0" X 2CCA21H17 Safety Injection 375' 9" X 2CCA22H13 Safety Injection 376' 0" X 2CCA22H14 Safety Injection 375' 4 7/16" X 2CCA22H15 (A) Safety Injection 375' 4 7/15" X 2CCA22H15 (B) Safety Injection 375' 4 7/16" X 2CCA22H17 Safety Injection 375' 4 7/16" X 2CCA22H18 Safety Injection 384' 4" X 2CCA22H19 Safety Injection 383' 4" X i

TABLE 3.7-4a (Continued) .

SAFETY RELATED MECHANCIAL SHOCK SUPPRESSORS (SNUBBERS)a 3 l l l l SNUBBER l SNUBBER l SNUBBERS ISNUB8ERS l gl l l lIN HIGH lESPECIALLYlINACCESSIBLElACCESSIBLEl 3: 1 1 l l RADIATION l DIFFICULT IDURING lDURING l gi SNUBBER NUPEER l LOCATIC l ELEVATION l AREA lTO REMOVE l NORMAL l NORMAL l

  • 1 1 l lDURING bl l0PERATION l0PERATION l

' I I l 12SLI221dtLI I I l g 2CCA22H21 Safety Injection 388' 0" X q 2CCA22H22 Safety Injection 390' 8 1/8" X m 2CCA23H11 Safety Injection 388' 0" X 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 (B) Safety Injection 377' 6 3/4" X 2CCA23H28 Safety Injection 369' 6" X 2CCA24H15 Safety Injection 388' 0" X m 2CCA24H17 Safety Injection 386' 0" X g 2CCA24H19 Safety Injection 377' 0" X y 2CCA24H24 Safety Injection 351' 2" X 4 2CCA24H27 Safety Injection 351' 2" X p 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 20CA25H13 Safety Injection 352' 1 1/2" X 2CCA25H14 Safety Injection 354' 6" X 2CCA26H2 Chemical and Volume Control 336' 6" X 2CCA32H2 Reactor Coolant Drain 357' 0" X 2CCA38H1 Reactor Coolant Drain 357' 0" X 2CCA38H3 Reactor Coolant Drain 357' 0" X 2CCB1H3 (A) Letdown Line 345' 3 1/2" X 2CCBlH3 (B) Letdown Line 345' 3 1/2" X 2CCB2H2 Chemical and Volume Control 360' 0" X 2CC82H5 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

TABLE 3.7-4a (Continued)

~

SAFETY RFLATED HECHANCIAL SHCCK SUPPRESSORS (SNUB 8ERS)*

>l l l l SNUB 8ER ISPueBER lSMS3BERS l SNUB 8ERS l l l lIN HIG14 IESPECIALLYlINACCESSIBLEIACCESSIBLEl bI T. I SNUSSER NLDSER l

I LOCATION l

l l ELEVATION lRADIATIONIDIFFICULT lDURING l AREA lTO REMOVE INORML lDURING

. DML l

l I I I lDURING l 10FER/T10N 10PERATION l

, I I  ! l l _l _

l_ l

.E 2CC854H2 Sample System 357' 0 _X Z 2CC854H3 Sample System 357' 0" X ro 2CC86SH1 Reactor Coolant Drain 336' 6" X 2CC869H3 Reactor Coolant Drain 336' 6" X 2CC869H4 Reactor Coolant Drain 236' 6' X 2CC876H2 (A) Reactor Coolant System Vent 418' 2 3/4" X 2CC876H2 (8) Reactor Coolant System Vent 415'11" X 2CCB76H10 (A) Reactor Coolant System Vent 416'11" X 2CC876H10 (8) Reactor Coolant System Vent 416'11" X 2CC876H11 (A) Reactor Coolant System Vent 415' t," X 2CC876H11 (8) Reacter Coolant Systen Vent 415' 5" X ca 2CC876H12 Reactor Coolant System Vent 416' S 1/2' X

'jl: 2CC876H14 Reactor Coolant System Vent 418'11 1/4" X y 2CC876H17 (A) Reactor Coolant System Vent 417' 6" X

,o 2CC876H17 (8) Reactor Coolant System Vent 417' 6" X E 20081H2 (A) Main Feedwater 402' O 11/32" X 20081H2 (8) Main Feedwater 402' O 11/32" X 20081H3 Main feedwater 402' O 3/8" X 20081H4 (A) Main Feedwater 44' 0" X 20881H4 (8) Main Feedwater 404' 0' X 20081H6 Main Feedwater 404' 4" X 20081H8 Main Feedwater 387' 0" X 20081H9 Main Feed >ater 388' O 3/8" X 20081H19 Main Feedwater 386' 0" X 20081H12 Main F.:edwater 369' 4 1/2" X 20881H13 Main Feedwater 368' 4 1/2" X 20081H14 Main Fee &sater 355* 6" X 20081H17 Main Fee &sater 402' O 5/16" X 20082H2 (A) Main Feessater 391' 1 1/4" X 29882H2 (8) Main Fe :$ water 391* 1 1/4" X 20082H8 Main Feessater 358' 6" X

PGARM11 Main Fee &sater 347' 6" X
PGAR:PH13 Main Feedwater 351' 7" X
PnARM15 Main Fee &sater 362'11 1/8" X

TABLE 3.7-4a (Continued) .

SAFETY RELATED MECHANCIAL SHOCK SL'PPRESSORS (SNUB 8ERS)*

>1 l l lSNOSSER l SNUB 8ER lSNU86ERS l SNUB 8ERS l

[1 z

$i t

SNUSSER NupSER l

1 I LOCATION l

l ELEVATION lIN HIGH lESPECIALLYl INACCESSIBLE l ACCESSIBLE!

lRADIATIONIDIFFICULT lDURING lDURING l l l AREA lTO REMOVE l NORMAL l NORMAL l

'S I I EI

~.

- 7BARM16 l

Main Feedwater I

_I 374' 0" ldi I

DURING 1 l0PEkATION I

X l0PERATION l I _l m 20AR7417 (A) Main Feedwater 347' 6" A 2 nan M17 (8) Main Fee &sater 347' 6" X 2nmRM19 Main Fee &sater 353' 6" X 20083H1 Emergency Fee &sater 399' 8 5/16" X 2nARM2 Inf to SG 2E26A 400' 4 3/16" X 2nnaWS Emergency Fee &sater 377' 6" X 2namW13 Emergency Feessater 400' 4 5/16" X

>emaW15 Emergency Fee &sater 400' 4 3/16" X 2nanM16 Emergency Feedwater 399' 4 5/16" X 20083H17 Emergency Fee &sater 399* 4 3/16" X w 20004H1 Emergency Fee &sater 370' 0" X

, 1 20094H2 Emergency Fee &sater 372' 2 13/16" X y 200Sah3 (A) Emergen y Fee &sater 370' 0" X h 20084H3 (B) Emergency Feedwater 370' 0" X S' 2 DOS 4M5 Emergency Feedwater 370' 0" X 20087H5 Reactor Miscellaneous System 376' 2" X 200814H1 Steam Generator Secondary . System 5d6' 0" X 200814H2 Steam Generator Secondary System 386' 0" X 200B14H3 Steam Generator Secondary System 386' 0" X 2tM 14H4 Steam Generator Secondary System 386' 0" X 20001H11 Main Feeesater 336'11 7/8" X 20301H17 (A) hin Fee &sater 364' 8" X 20001H17 (B) Main Feedseter 364' 8" X 7eARM11 Main Fee &sater 363' 5" .'

X 70002H12 Main Feedwater 386' 0" X 2naR7H13 Main Feedwater 380' 9" X 7eARM14 (A) Main Fee &sater 380' 9" X 7EARM14 (B) Main Fee &sater 380' 9" X 2E081AH4 Main Steam 425' 1 1/2* X 2FER14HS Main Steam 436' 2 31/32" X 2E081AH6 (A) Main Steam 436' 3" X 2EM1AH6 (B) Main Steam 436' 3" X l 7FER14H7 Main Steam 436' 2 31/32" X

TABLE 3.7-4a (Continued) .

SAFETY RELATED MECHANCIAL S}9CK SUPPRESSORS (SNUB 8ERS)E

>I I i  ! SNUB 8ER l SNUB 8ER jSNUB8ERS ISNUSSERS l "I I l IIN HIGH IESPECIALLYl INACCESSIBLE lACCESSIBLEl hl l j lRADIATIONIDIFFICULT IDURING lDURING l 5l SIRISbER IRBSER l LOCATION l ELEVATION (AREA ITO REMOVE IN0fWqAL l NORMAL l TI I I lDURING I l0PERATION IOPERATION l EI I I l l I l I Q 2ESS1H4 Main Steam 428' 4" X ro 2Faa?4H4 Main Steam 436' 2 31/32" X

?FM74HS Main Steam 436' 2 31/32" X 2 Fan 2AH6 (A) Main Steam 436' 3" X 2E M2AH6 (8) Main Steam 436' 3" X 2 Fan?4H7 Main Steam 436' 2 31/32" X 2 Fan 244 Main Steam 436' 3" X 2FER2HS (A) Main Steam 413' 8 1/2" X 2EBS2HS (B) Main Steam 413' 8 1/2" X 2EBS2H6 (A) Main Steam 414' 6" X 2FER2H6 (8) Main Steam 414' 6" X w 2EBS7H2 Main Steam 440' 3" X 1 2EBS8H2 Main Steam 426' 2 7/8" X y 2 EBB 16H3 Steam Generator Secondary System 386' 0" X

,'o 2EN 16H5 Steam Generator Secondary System -386' 0" X R 2EBil16H6 Steam Generator Secondary System 386' 0" X 2EBS16h7 Steam Generator Secondary System 386' 0" X 2EBS16H8 Steam Generator Secondary System 386' 0" X 2EBS17-1H002 Steam Generator Secondary System Above 386' 0" X 2EBS17-1M003 Steam Generator Secondary System Above 386' G" X 2EBS17-1H004 Steam Generator Secondary System Above 386' 0" X 2ERS17-1H005 Steam Generator Secondary System Above 386' 0" X 2EN 17-1H0C6 Stem Generator Secondary System Above 386' 0" X 2EM30H3 Steam Generator Secondary System 405' 6" X 2EM30H4 Steam Generator Secondary Systcm 405' 6" X 2ERS30N7 Stem Generator Secondary System 405' 6" X 2EBS30MB Steam Generator Secondary System 405' 6" X 2ERS31H2 Steam Generator Secondary System 405' 6" X 2EBC1HS (A) Main Steam 350' 3" X 2EBCIN9 (B) Main Steam 350' 3"- X 2EBC1H26 Main Steam 343' 2" X 2EBCIM29 Main Steam 340' 2" X 2EBC1H30 i8-in Steam 339' 6 5/8" X 2EBCIN31 Main Steam 414' 0" X

TABLE 3.7-4a (Contir.ued)

SAFETY RELATED HECHANCIAL SHOCK SUPPRESSORS (SNUB 8ERS)a I I l l SNUBBER ISNUBBER l SNUBBERS l SNUB 8ERS l l I l lIN HIGH lESPECIALLYlINACCESSIBLEIACCESSIBLEl i 1 l lRADIATIONIDIFFICULT IDL' RING IDURING l

$I ShdB8ER NUPEER I LOCATION l ELEVATION l AREA lTO REMOVE lh0RMAL IN0RMAL l l l l lDURING [0PERATION l0PERATION l I I l lSHUTD0hekll l l l E 2EBC2H4 Main Steam 421' 1" X Q 2EBC2H7 Main Steam 421' 1" X

n. 2EB01H1 (A) Main Steam 404' 9" X 2EB01H1 (B) Main Steam 404' 9" X 2EB01H2 (A) Main Steam 403' 6" X 2EB01H2 (B) Main Steam 403' 6" X 2EB01H11 (A) Main Steam 346' 0" X 2ES01H11 (B) Main Steam 346' 0" X 2E801H12 Main Steam 346' 0" X 2EB01H13 (A) Main Steam 354' 0" X 2EB01H13 (B) Main Steam 354' 0" X w 2EB01H14 Main Steam 354' 0" X 1 2E301H15 Main Steam 353' 9" X y 2EB01H16 Main Steam 354' 0" X 43 2EB02H1 (A) Main Steam 404' 6 1/2" X

@ 2EBD2H1 (B) Main Steam 404' 6 1/2" X 2EB02H2 (A) Main Steam 403' 6" X 2EBC2H2 (B) min Steam 403' 6" X 2EB02H11 Main Steam 346' 2" X 2EB02H12 Main Steam 346' 0" X 2EB02H13 Main Steam 346' 0" X 2EB02H14 Main Steam 346' 0" X 2EBD2H15 (A) Main Steam 346' 0" X 2EB02H15 (B) Main Steam 346' 0" X 2EB02H16 Main Steam 346' 0" X 2EB022HS Main Steam Dump to Condensate 358' 0" X 2 ERD 28H7 Men Steam 358' 0" X c M -2H001 Main Steam 423'10 7/8" X 2EB056-2H002 Main Steam 423'10 7/8" X 2EBD56-2H003 Main Steam 423'1C 7/8" X 2EB056-2H004 Main Steam 423'10 7/8" X 2EB056-3H002 Main Steam 437' 6" X 2EB056-3H003 Main Steam 437' 6" X 2EB000H001 Steam Generator Secondary System 404' 0" X

TABLE 3.7-4a (Continued) .

SAFETY RELATED MECFANCIAL SHOCK SUPPRESSORS (SNUBBERS)*

gl l l l SNUBBER l SNUB 8ER l SNUBBERS l SNUB 8ERS l gI I l lIN HIGH lESPECIALLYl INACCESSIBLE l ACCESSIBLE l z I l 1 l RADIATION l DIFFICULT lDURING lDURING l 3i SNUB 8ER NUBSER l l

LOCATION l ELEVATION l AREA lTO REMOVE l NORMAL l NORMAL l 1 lDURING l l0PERATION l0PERATION l I I l l hl2fCC1H8 z Pressurizer Relief Piping 412' 2 3/4" I l X

l 1 Z 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 2FCC1H22 (A) Pressurizer Relief Piping 416'11 11/16" X 2FCC1H22 (B) Pressurizer Relief Piping 416'11 11/16" X 2FCC1H23 Pressurizer Relief Piping 416'11 11/16" X 2FCC1H24 (A) Pressurizer Relief Piping 413'10 1/16" X 2FCC1H24 (B) Pressurizer Relief Piping 413'10 1/16" X 2FCC2h5 Pressurizer Relief Piping 394' 6" X u 2FCC2H6 Pressurizer Relief Piping 386* 6" X 1 2FCC2H8 Pressurizer Relief Piping 416'11 11/16" X

~ 2FCC2H9 Pressurizer Relief Piping 415' 7 1/2" X io 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 2G8075H3 Steam Relief Stacks to Atmosphere X 2G8076H3 Steam Relief Stacks to Atmosphere 445' O 1/4" X 2G8076HS Steam Relief Stacks to Atmosphere 441' 8" X 2GC82H3 Safety Injection 318' 6 3/4" X 2GC82H22 Safety Injection 329' 4 3/4" X 2GCB3H24 Safety Injection 329' 9" I 2GC85H21 Safety Injection 347' 6" X 2GC85H23 (A) Safety Injection 342' 3" X 2GC85H23 (B) Safety Injection 342' 3" X 2GC85H26 Safety Injection 348' 3" X 2GC85H2S Safety Injection 349' 0* X 2GC85H31 (A) Safety Injection 318' 6 3/4" X 2GC85H31 (B) Safety Injection 318' 6 3/4" X 2GC89H24 Safety Injection 326' 3" X 2GC810HS Containment Spray 330' 6 1/2" X 2GC811HS Spray Pump 2P358 Discharge 329' 6 3/4" X 2GC8513H2 Auto. Pressurizer Vent Line 415' 5" X

_ _ _ _ _ . ._m _ _ _ _ _ _ _ _ _ _ _ _

TABLE 3.7-4a (Continued)

SAFETY RELATED HECHANCIAL SHOCK SUPPRESSORS (SNUB 8ERS)*

,I I I ISNUB8ER ISNUB8ER l SNUB 8ERS l SNUB 8ERS I

= l 1 lIN HIGH IESPECIALLYlINACCESSIBLEIACCESSIBLEl I I hli g

  • ^ l SNUBSER 3ENGER I LOCATION 1

I ELEVATION lRADIATIONIDIFFICULT IDURING l AREA lTO REMOVE l NORMAL IDURING INORMAL l

i i I IDURING l l OPERATION l0PERATION I

  • I I l l l l l l

' n 2GCS$14M2 Auto. Pressurizer vent Line 415* 5" X 4 2GCS$14N3 Auto. Pressurizer Vent Line 415' 5" X 2NBC41H2O SW from 2H8C63 to 2VEIA 391' 7 3/4"

" X 2BSC98H9 SW from 2teC64 to 2VE18 391* 7 3/4" X 20eC103H17 . Service Water Supply 367'10" X 2teC103H18 Service Water Supply 370' 2 3/4" X 2teC103H2O Service Water Supply 370' 3" X 2BGC103H22 Service Water 370' 4" X 2teCIO4H16 Service Water 371' 9" X 20SC104H18 Service Water 371' 9" X 2teC105H4 Service Water Return 371' 1 7/8" X 2tSC105H14 (A) Service Water 367' S 3/4" X Y

? 2BSC105H17 Service Water Branches 371'10" X 2

^

2teC105N18 Service Water Branches 371'10" X 2teC105H27 Service Water 389' 0" X 2030750H6 Main Feedwater 371' 4" X 2tS0750H9 Main Feedwater 373' 1 9/16" X 2MC33H170 Containmert Spray Header 351' S 1/4" X 2HCS3H177 Containment Spray 421' 6" X 2NCS4H176 Containment Spray 347' 6" X 2HCS4H179 Containment Spray 347' 6" X 2HCS4H188 (A) Containment Spray 347' 6" X 2MCS4H188 (8) Containment Spray 347' 6" X 2MCS4H189 Containment Spray 347' 6" X 2MCS4H190 Containment Spray 349' 0" X 2HCS4H194 Containment Spray 356' 7" X 2BE313H14 (A) Containment Spray 320'10" X 2HCS13H14 (8) Containment Spray 320'10" X 2MCS15H15 (A) ESFAS Pump Suction and Vent Pump 320' 7 7/8" X 2MCB15H15 (8) ESFAS P g Suction and Vent Pump 320' 7 7/8" X 2HCS27H7 (A) Containment Spray 326' 6" X 2NCS27H7 (8) Containment Spray 326' 6" X

TABLE 3.7-4a (Continued) '

SAFETY RELATED MECHANCIAL SHOCK SUPPRESSORS (SNUB 8ERS)*

> I i l l SNUBBER lSMUBBER ISNUEBERS ISNUBBERS l SE I I l lIN HIGH IESPECIALLYl INACCESSIBLE lACCESSIBLEl 5l 1 l IRADIATIONIDIFFICULT lDURING lDURING l

$1 SNUB 8ER NL96ER I LOCATION l ELEVATION l AREA ITO REMOVE l NORMAL INGRMAL l "l I l lDURING l l0PERATION l0PERATION l I l _l I l I l hl2MCC53H9 z Fuel Pool System 351' 6" x Q 2HCC53H10 Fuel Pool System 347' 8" X m 2HCC53H14 Fuel Pool System 335' 0" X 2HCC53H15 Fuel Pool System 343' 6" X 2HCC77H6 Reactor Coolant Drain 336' 6" X 2HCC77H7 Reactor Coolant Drain 336' 6" X 2J80201HB (A) Diesel and Fuel Oil 380'10 9/16" X 2J80201HB (B) Diesel and Fuel 011 380'10 9/16" X 2J80201H9 Diesel and Fuel Oil 380'10 9/16" X 2J80201H11 (A) Diesel and fuel Oil 380' 7 1/16" X 2J80201H11 (B) Diesel and Fuel Oil 380' 7 1/16" X c., 2J80202HB (A) Diesel and Fuel Oil 381'11 1/2" X 1 2J80202MB (8) Diesel and Fuel Oil 381'11 1/2" X y 2J80202H9 Diesel and Fuel Oil 381'11 1/2" X da 2J80202H11 (A) Diesel and Fuel Oil 381' 3" X E 2J80202Hil (B) Diesel and Fuel Gil 381' 3" X

. -- -_ _ _ _ - - _ ~ _

TA8LE 3.7-4a (Continued)

TABLE NOTATION l

a. Snubbers may 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.

l b. Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that a  ;

i revision to Table 3.7-4a is included with the next License ,

Amendment Request.

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l ARKANSAS - UNIT 2 3/4 7-2h

PLANT SYSTEMS BASES following all credible accident conditions. The OPERABILITY of this system I in conjunction with control room design provisions is based on limiting the r 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", 10CFR50.

3/4.7.8 SHOCK SUPPRESSORS (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 .

l on non-safety-related system and then only if their failure or failure of the system on which they are installed, would have no adverse of fect on any safety-related system.

i The visual inspection frequency is based upon maintaining a constant level l 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 inspe.tlon.

Inspections perforrod before that interval has elapsed may be used as a new I reference point to determine the next inspection. Hovever, the result of

. such early inspections performed before the original required time interval I has elapsed (nosinal time less 25%) may not be used to lengthen the required t i inspection interval. Any inspection whose results require a shorter  !

l inspection interval will override the previous schedule.

I 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 verf fled 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 f

design features directly related to rejection of the snubber by visual inspection, or are similarly located or exposed to the same environmental i conditions such as temperature, radiation and vibration.

I When a snubber is found inoperable, an engineering evaluation is performed,

", in addition to the determination of the snubber mode of failure, in nrder to deterlijne if any safety-related component or system has been adversely affet.ted by the inoperability of the snubber. The engineering evaluation is performed to deturmine whet'4er or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.

ARKANSAS - UN!f 2 B 3/4 */-6

i I

i PLANT SYSTEMS r ,

murs i i t

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t

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i I i I

I f

3/4.7,9 SEALED 500 ACE CONTAMINATION l The Ilmitations on removable contamination for sources requiring leak -

testing, including alpha emitters, is based on 10CFR70.39(c) Ilmits for i plutonium. This lleltation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake  :

values.

3/4.7.10 FIRE $UPPRESSION SYSTEMS l i

The OPERASILITY of the fire suppression systems ensures that adequate fire ,

l suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located. The fire suppression system consists of the water system spray .

and/or sprinklers, and fire hose stations. Theco11ectivecapabi1Ityofthe '

fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program. '

l In the event the portions of the fire suppression systems are inoperable,.

alternate backup fire fighting equipment is required to be made avellable in the affected areas untti the 'noperable equipment is restored to service.

In the event the fire suppression water system becomes inoperable, immediate l corrective measures must be taken since this system provides ther major fire suppression capability of the plant. The requirement for a twenty four hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.

ARMANSAS - UNIT 2 0 3/4 7 6

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-servico inspections performed pursuant to these Technical Specifications.
1. Records of Quality Assurance activities requ, *d by the QA manual.

J. Records of review performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10CFR50.59.

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:

I

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 Ilves of the seals of a11 hydraulic snubbers listed on Tables 3.7 4, including 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 10CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 INVIRONHCNfAL_QUALIFICAT10N 6.12.1 By no later than June 30, 1982 all safety related electrical equipment in the facility shall be quellfled in accordance with the provisions oft Olvision of Operating Reactors ' Guidelines for Evaluating

[nvironmental Qualification of Class IC Clactrical [quipment in Operating ANKAN$AS = UNIT 2 6 20

7 ADM1h1STRATIVE CONTROLS Reactors" (00R Guidelines); or NUREG-0558 " Interim Staff hsition on Environmental Qualification of Safetv-Related Electrical Equipment".

December 1979. Copies of these documents are attached to Order for Modification of License NPF-6 dated October 24, 1980.

ARKAN$AS - UNIT 2 6 204

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$1GNIFICANT HAZARDS DETERMINATION (ATTACHMENT 2 TO 2CAN#58481) a

1 1

1 (ATTACHMENT 2 TO 2CAN058491)

SIGNIFICANT HAZARDS DETERMINATION In. response to NRC's generic request for licensees to submit revised Technical Specifications for mechanical shock suppressor (snubber) surveillance, AP&L is proposing an updated snubber surveillance program for ANO-1 & 2. As a result of these proposed Technical Specification changes for ANO-2, certain mechanical snubbers would be added to the existing list of safety related hydraulic snubbers to increase the quantity of snubbers requiring surveillance. Consequently, this would constitute a more stringent overall surveillance requirement.

In consideration of 10CFR50.59(a)(2), AP&L has determined that this action does not involve an unreviewed safety question because the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety as previously analyzed will not be ircreased, nor will there be created a possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report.

Therefore, the margin of safety as related to the health and safety of public is not reduced.

In summary, AP&L has determined that this action would not involve a significant hazards consideration. The addition of safety related mechanical snubbers to our list of snubbers required to be periodically examined and tested for functional operability would constitute a more stringent Technical Specification surveillance requirement and, as such, j"rt4*ic: AP&L's determination of no significant hazards consideration per DLOP 228, Federal Register, Vol. 48, p.14870 i

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