ML20099F380

Proposed Tech Specs Revising Limiting Conditions for Operation & Surveillance Requirements for safety-related Hydraulic Snubbers & Establishing Requirements for safety-related Mechanical Snubbers

ML20099F380
Person / Time
Site:	Hatch
Issue date:	11/19/1984
From:	GEORGIA POWER CO.
To:
Shared Package
ML20099F364	List: ML20099F359 ML20099F380
References
TAC-08298, TAC-08310, TAC-48362, TAC-48363, TAC-8298, TAC-8310, NUDOCS 8411260391
Download: ML20099F380 (30)

Text

~

., ta i \

l ENCIOSURE 2 NRC DOGET 50-321

. OPERATING LICENSE DPR-57 ENIN I. HA'IG NUCLEAR FIANT UNIT 1 REVISION 'IO PICIOSED SNUBBER TECHNICAL SPECIFICATIONS

'Ihe proposed changes to Unit 1 Technical . Specifications (Appendix "A" to

. Operating License DPR-57) wculd be incorporated as 'follows:

Remove Page Insert ' Page-iv iv.

viil viii 3.6-10a. thrcugh 3.6-10g : 3.6-10a through 3.6-10d 3.6-31 3.6-31

-3.6 3.6-32 6-20 6-20

, e l

8411260391 841119 PDR ADOCK 05000321 P

PDR ,

p - . -

-Section Section Page LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREPR7IS 3.6 PRIMARY SYSTEM BOUNDARY 4.6 PRIMARY bYSTEM IOUNDARY 3.6-1 A. Reactor Coolant Haatup A. Reactor Coolant Heatup 3.6-1 and Cooldown and Ccoldown B. Reactor Vessel Teperature B. Reactor vessel Teperature 3.6-1 and Pressore ~ and Pressure C. Reactor Vessel Head Stud C. Reactor Vessel Head Stud 3.6-2

. Tensioning Tensioning D. Idle Recirculation Icop D. Idle Recirculation Icop 3.6-2 Startup Startup E. Recirculation Pm p Start E. Recirculation Pump Start 3.6-3 F. Reactor Coolant Chenistry F. Reactor Coolant Ch mistry 3.6-4 G. Reactor Coolant Leakage G. Reactor Coolant Leakage 3.6-7 H. Safety and Relief Valves H. Safety and Relief Valves 3.6-9 I. Jet Pmps I. Jet Pmps 3.6-9 J. Recirculation Ptsp Speeds J. Recirculation Pm p Speeds 3.6-10 K. Structural Integrity of K. Structural Integrity of Primary Systm Boundary Primary Syste Boundary 3.6-10 L. Snubbers L. Snubbers 3.6-10a i

3.7 CONTAI?NENP SYSTEMS 4.7 CONTAIN4ENT SYSTEMS 3.7-1 A. Primary Contalment A. Prihtary Contaiment 3.7-1 B. Standby Gas Treatment Systen B. Standby Gas Treatment Systen 3.7-10 C. Secondary Contaiment C. Secondary Contalment 3.7-12 D. Primary Contaiment D. Primary Contalment 3.7-13 Isolation Valves Isolation Valves 3.8. RADIOACTIVE MATERIAIS 4.8 RADIOACTIVE MATERIALS 3.8-1 A. Fiscellaneous Radioactive A. Miscellantous Radioactive 3.8-1 Materials Sources Materials Sources 3.9 AUXILIARY ELECIRICAL SYSTEMS 4.9 AUXILIARY ELECIRICAL SYSTEMS 3.9-1 A.-.

Requirenents for Reactor A. Auxiliary Electrical 3.9-1 Startup Systems Bluipnent iv E

- LIST OF TABIIS (Concluded)

Table Title Page 4.2-7 Check, Rinctional Test, and Calibration Mininum Frecalency 3.2-40 For Naltron Monitoring Instrumentation Which Initiates control Rod Blccks 4.2-8 Check, Rinctional Test, and Calibration Mininum Frequency - 3.2-42 for Radiation militoring Systens Which Limit Radioactivity Release 4.2-9 C;eck and Calibration Minim 1m Frecntency for Instrumentation 3.2-45 Which Initiates Recirculation Ring Trip 4.2-10 Check, R1octional 7est, and Calibration Mininum Frecpency 3.2-46 for Instrumentation Khich Monitors Leakage into the Drywell 4.2-11 Check and Calibration Mininum Freglency for Instrumentation 3.2-48 Which Provides alrveillance Information 4.2-12 Instrumentation which Initiates the Disconnection of Offsite 3.2-49a Power Sources 4.2-13 Instrumentation Which Initiates Energization by Onsite 3.2-49b Rwer Scurces 4.6-1 Inservice Inspection Program 3.6-11

'3.7-1 Primary Containment Isolation Valves 3.7-16 3.7-2 Testable Ibnetrations with Double O-Ring Seals 3.7-21 3.7-3 Testable Penetrations with Testable Bellows 3.7-22 3.7-4 Primary (bntainment Testable Isolation Valves 3.7-23 3.13-1 Fire Detectors 3.13-2 3.13-2 Fire Hose Stations 3.13-9 6.2.2-1 Mininum Shift Crew Composition 6-3 6.9-1 Special Reporting Becuirements 6-19 viii

c,  ; ,

w , ,

< w. -

- ,'; . ; p. (,; , ' 'p A _

y .

m

-_~.

.g_

~

, a 1 , ,  ;

~ - ~

s r -

" ~#

53/4.6.L SN0BBERS <

~ ,

5  !, _' fLIMITING COBOITIN FOR OPERATION -

~q n~

The L only. snubbers ' excluded fran -

'~

43.6.L . i A111 snubbers * ~ shall [be[ OPERABIE.

this requirment are thoselinstalled on non-safety;related .systens

~

and. 'then:only:if their Lfailure or failureL of the systeni on which 1theyi :are , : installed - would have. no? adverse effect - Eon . any '

. safety-related systen.:

, APPLICABILITY: 'Conditionsfl, 2, and 35

ACTIm:U _

lWith oneLor 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 ' ~ OPERABIE ; status - and -perform 'an Ll engineering- ,

evaluatiori per Specification- 4.6.L.3.. on the ' supported component or ideclare the sut: ported system Linoperable and l follow the appropriate limiting condition c of operation -statenent(s) for that systen.

' ; SURVEILIANCE REQUIREMENTS 14.6.L : Each . snubber.- shall be denonstrated OfERABLE by performance y of the following inservice inspection progran.

1. Visual' Inspections All safety-related snubbers shall .be visually exmined to verify snubber.' operability. . Visual ir.spections :shall; be. performed in accordance.with the following schedule:

No.' Inoperable Sn'ubbers Subsequent Visual per Inspection Period Inspection Period **

0 18 mor.ths + 25%

1 12 nonths.T 25% -

2 6 months I 25%

3, 4 124 days T 25%

5,6,7 62 days T 25% '

8 or more 31 days T 25%

%e snubbers may be categorized into two groups: %ose accessible and those inaccessible during reactor operation. Each group may be  ;

inspected independently in accordance with the above schedule.

2. Visual Inspection Acceptance Criteria .

Visual inspections shall verify (1) that. there are - no visible indications of dwage or impaired OPERABILITY, (2) attachtents to the foundation or supporting structure are secure, and ~ (3) for

. mechanicallsnubbers whereisnubber inovement 'can be manually. induced,

! the snubbers shall be' inspected'as follows: (a) At each Iefueling,

• W e applicable snubbers chall.be identified in plant procedures.

• • @e ' inspection interval'shall not be lengthened n. ore than one step at a thne.x l I-

, HA'IG - UNIT 1 3.6-10a

~ '

77'.& , >V -

,g~ >

, y

="-

, pg.[ c, ' '

-n n 1 ,

q-u , .,

\

u ~q q - -

g , ,

1

.x

~

y r

~

~

y }]-  ;- _

f' .

+

~ ,s }

i

' 16 V3/4.6.L SN mRFRS .

o ,~ ,. .

SURVEILINKE REQUIREMBUS'(Continued) -

.7 ~

? systes : associated 'with;the safety-selatedimechanical' snubbers 'shallL '

beLinspected to .determineiif there has been ' a severe dynamic ! event. i

?(b)1In ' th'e event of. a severe;dynmic event, snubbers 'in _that .syste

/

3

?which experienced;theievent -shall:be1 inspected during the refueling.  :

Loutage' to' ' assure ;theisnubbers have freedom of: movment~ and are not -

^

frozen? up. L %e x inspection :shall: consist i of verifying freede ;of; motion iusing1one ofc the following':- (i)1 Manually; induced c snubber

- . movement;1 (ii)- - stroking ' the f mechanical J snubber J through its 2 full range of travel. If one or more mechanical snubbers are found to bet (frozen Jup ' during "this ' inspection,D those snubbers _ shall : be : replaced

- 1(or'5 overhauled) .beforei returning. to power. .Re-inspection';shall

subsequently. be performed accordingL to the schedule of 4.6.L.1,E but

the scope ? ofithelfexmination shall be . limited to lthe .syste s associated with Lthe safety-related mechanical snubbers. Snubbers l

'whichl appear inoperable Eas ' a ' result.: of visual . inspections may be -

M

+. determined . OPERABLE for..the purpose of _ establishing the i next ~ visual-inspectionE interval ~, : providing . that (1): ther cause ;of. the rejection is clearly , established and Jrmedied for Lthat particular : snubber and

.for .other snubbers that may be generically susceptible; and ' (2) the affected snubber ' is functionally: tested in' the "as ! found" condition

" and ? determined OPERABIEiper . Specification 4.6.L.4 or L4.6.L.5, as applicable.~ However, . if 'a, hydraulic snubber is found 'to contain less thr.n the required minimm volme of reserve fluid or if visible

~

' signs of. leakage are;present, the-. snubber shall. be determined inoperable and cannot be determined : OPERABLE via functional . testing for. the purpose of establishing' the next visual inspection interval.

~

> 3. Functional Tests-At least once per 18 months during shutdown,'a representative saple ,

of 10% of the total of each type (hydraulic or mechanical)

_ safety-related snubber in 'use in the plant shall be functionally ,

, ' tested either in place or in a bench ~ test. For each - snubber that p does not meet .the functional test acceptance criteria . of r Specification 4.6.L.4 or 4.6.L.5, an additional saple of at 'least r 1/2 the size of-- the = initial lot of that type of snubber shall be j functionally tested.

I Ebnctional testing shall continue until no additional inoperable l snubbers of a particular type are found within a sm ple or until all safety-related snubbers of that type have been functionally tested..

%e ' representative smple selected for functional testing shall

linclude the various configurations, operating enviroments and the-range of size and capacity of snubbers. We representative smple '

1shall be Jselected randomly frm - the ' total population of

- safety-related snubbers. At least 25% of the snubbers in the-f.I

[ - HA'IG ' : UNIT 1 .

3.6-10b i:

~

b. .

.--.m+,*I,-=.i---e=

wy- e , , - , , 4 e-[ , , c ,,v . , . - - , n - m-4.--,=.--.m- , - ,<~=,Le .. -

g, m 3/4.6.L SNUBBERS SURVEIILANCE RECUIRIMENTS (Continued) x representative smple shall . include snubbers - frm' : the following three categoriesi-

1. %e first snubber away frm each reactor vessel nozzle,

- 2. -Snubbers within 5 feet of heavy equipnent (valve, pmp, turbine, motor, etc.), and -

3. Snubbers within 10 feet of the discharge frm a safety-relief valve.

Snubbers identified in plant procedures as "Especially Difficult to Reove" or in "High Radiation Zones During Shutdown" shall also be included ~ in the representative smple*. The populations of safety-related hydraulic and safety-related mechanical snubbers may be used jointly or separately as the basis for the smpling plan.

In addition to_ the regular sm ple, snubbers placed in the sme location as snubbers which failed the previous functional test shall be retested during the next test period. Test results of these snubbers shall not be included in the smpling plan.

If any snubber selected for functional testing either fails to lockup 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 see design subject to the sme defect shall be functionally tested. %is testing requirment shall be ind.. pendent of the requirments stated above for snubbers not meeting the functional test criteria.

Ebr the snubber (s) found inoperable, an engineering evaluation shall be performed on the cmponents which are supported by the snubber (s) . %e purpose of this engineering evaluation shall be to determine if the cmiponents supported by the- snubber (s) w&e adversely affected by the inoperability of the snubber (s) in order to ensure that the supported cmponent reains capable of meeting the designed service.

4. ' Hydraulic Snubbers Functional ibst Acceptance Criteria

%e hydraulic snubber functional test shall verify that:

• Permanent or other exenptions frm functional testing for individual snubbers in those categories may be granted by the Comission only if a justifiable basis for exs ption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all decign conditions at either the cm.pletion of their fabrication or at a subsequent date.

- HATCH - UNIT 1 3.6-10c L__

v4 6 '

s =

x= mNUm n=

y f;i.

g @y - 9

- - + -t u . s - - t

- - 7 , .

,' H

% - - +-

7 ;> ,

_ , ; }:k F3/4.6'.L } SNtBBERS

/ SERVEILIAN3 REQUIRBENFS : (Continued) -

-; a. -- '. Activstion f (restiaining L action) ~ tis achieved 'withisTthe ; specified! q range . .of = -velocity or acceleration: inE Lbothr tension? and '

capression.

is JSnubber bleed, EorL release rate, j where rquired, cis . within /the'-

specified ; range .in; capressionD ort ; tension.' Ebr- i snubbers

~

- specifically requiredi to not displm underf continuous : load, the;

{dbility ~ of- the snubber : to withstand load ~ without1 displacments

-shall'be verified.. ,

- 5. . Mechanical Snubbers Functionalmst Acceptance criterij

- %e mechanical;anubber function'al' test shall' verify that':

a. %eisnlubber operates freely over the ' stroke- in both tension and s ccepression. ~ ~

b. %e forceEthat initiates free - movment of -the ' snubber rod in.

either tension or cmpression is less. than the specified maximum

. drag force.

c. Activation : trestraining action) -is achieved within the- specified ,

range of velocity or acceleration in both-tension and ca pression.

6. Unit Outage Inaccessible Snubber-Inspection

- In the event that all inaccessible snubbers are inspected, functionally-tested, and repaired as necessary during a unit outage,<and that it'is

~

thus dmonstrated that all inaccessible snubbers - are operable, the schedule in Specification 4.6.L.1 may . be . re-entered ~on ' a 6-month inspection interval for the inaccessible snubbers.

7. Snubber Service Life Monitoring A record of the service life ~ of each snubber, the date at which the designated service life canences and the installation and maintenance records on which the -designated _ service life is based shall be maintained as rq uired by Specification 6.10.2.1.

Concurrent with the inservice visual inspection performed during . the-first . refueling outage - following - issuance of this amendment and at

-least once- per 18 months thereafter, the installation and maintenance i records for each safety-related snubber shall be reviewed to L verify that the indicated service. life has not been exceeded or will ~ cat be exceeded by more than 10% prior-'to .the next scheduled snubber service life = review.- If the indicated service life will be exceeded by _more than 10% prior to the next scheduled snutter service life review, the snubber service life . shall- be ' reevaluated or the snubber shall be replaced.or reconditioned so as to extend its service life beyond the

-.date of the next scheduled service' life review. %e results of the 1 reevaluation may be used to justify a change to the service life of the anubber. %is reevaluation 1 replacment . or reconditioning shall be .

' indicated in the records. l

- HMG - UNIT 1 - "3.6-10d.

BASES _

3/4.6.L SNUBBERS All snutbers . are re uired OPERABIE to ensure that the structural integrity of the reactor coolant syste and all other safety-related systes-is maintained ~ during and following a seimic- or other event initiating dynamic -. loads. Snubbers excluded frm this inspection progra are those installed on nonsafety-related systss and then only if their failure or failure of the syste on which they are installed, would have -no adverse effect on any safety-related system.

The visual inspection frquency is based upon maintaining a constant level of snubber protection to systes. Therefore, the required insprction interval varies inversely with the observed snubber failures and is determined by the nmber of inoperable snubbers found during an inspection.

Inspections performed before the interval has elapsed may be used as a new reference point to determine the next inspection. However, the results 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 reedied for the snubber and for any other snubbers that may be generically susceptible,_ and verified by inservice functional testing, that snubber may be exempted frm being counted as inoperable. Generically susceptible snubbers are those which are of a specific make or model and have the see design features directly related to' rejection of the snubber by visual inspection, or are similarly located or exposed to the see enviromental conditions such as ta perature, radiation, and vibration.

When a snubber. is found inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, t in order to determine if any safety-related cmponent or systs has been adversely affected by the inoperability of the snubber. The engineering evaluation shall determine whether cr not the snubber mode of failure has imparted a significant effect or degradation on the supported cmponent or systs.

To provide assurance of snubber functional reliability, a representative smple of the installed snubbers will be functionally tested during plant shutdowns at 18-month intervals. Observed failures of sample snubbers shall raluire functional testing of additional units.

Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance progras.

HATOf - UNIT 1 3.6-31

w ,

1 a: a l i

1

)

~

i aAsa;

' 3/4.6.'L - SNUBBERS (Continued) ,

. % el service life of L snubber is evaluated via manufacturer input and information through consideration of the snubber' service conditions and .l associated instellation .and maintenance- records: (newly installed snubber,

- seal replaced, spring replaced, in high radiation area, in 'high taperature area, etc...). The re;uir ment to monitor the snubber service life is included to ensure that the snubbers . periodically undergo a performance evaluation 'in view of their age - and operating conditicns. These records will provide statistical bases for future consideration of snubber service life. . %e requirments for . the maintenance of records and the snubber service life review are not intended to affect plant operation.

HA'IGI - UNIT 1 3.6.32

I AD4INISTRATIVE CWIROL RD00RD RIMENTIN (Continued)

c. Records of radiation exposure for all . individuals' entering radiation control areas.

d; ' Records of gaseous 'and liquid radioactive material released to 'the environs.

. e.. ~ Records of transient- or operational cycles for those unit cmponents identified in Table 5.7.1-1.'

f. Records of reactor tests and experiments.

g. Records of training and qualification for current mmbers for the unit staff.

h. Records of in-service'. inspections performed pursuant to these Technical Specifications.

i. . Records of Quality Assurance activities required by the OA Manual.

j. Records of reviews perfonted for changes. made to procedures or equiptent or reviews of tests and experiments . pursuant to 10 CFR 50.59.

k. Records of meetings of tale PPB and SPB.

1. Records of the service lives of all safety-related hydraulic and mechanical snubbers including the date at which the service life comences and associated installation and maintenance records.

6.11 RADIATION PROIECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirments of 10 CFR Part 20 and diall be approved, maintained and adhered to for all operations involving personnel raCiation exposure.

6.12 HIGH RADIATION ARPA 6.12.1 In lieu of the " control device" or " alarm signal" required by

. paragraph 20.203(c) (2) of 10 CFR 20, each high radiation area in which the itcensity of radiation is greater than 100 mrs/hr but less than 1000 mre/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit *. Any individual or group of individuals permitted

• Health Physics personnel, or personnel escorted by Health physics personnel l in accordance wita approved emergency procedures, shall be exmpt fra the

[ RWP issuance' raluirment during the performance of their assigned radiation protection duties, provided they cmply with approved radiation protection procedures for entry into high radiation areas.

HAICH - UNIT 1 6-20

n _. ..

ENCIOSURE 3

.NRC DOCKET 50-366

.. OPERATING. LICENSE NPF-5

_ ^

EDWIN I. HATOf NUCIEAR PLANT UNIT 2 L REVISION 'IO P90IOSED SNUBBER 'IECHNICAL SPECIFICATIONS

'Ihe proposed change to Unit 2- Technical. Specifications '(Appendix "A" to

' Operating License NPF-5) would be incorporated as follows:.

Renove Page Insert Page VIII. VIII XIII XIII-3/4 7-r tnrough 3/4 7-18 3/4 7-11 through 3/4 7-18 B 3/4 7-2 B 3/4 7-2 B 3/4 7 B 3/4 7-3 6-18 6-18 i

, y y y. , ..-----,,.-.c. . , , , - - , , _, u -

p -

INDEY LIMITING CONDITIOS EUR OPERATION AND SURVFTTTANCE REQUIRDENTS

' SECTIOT PAGE 3/4~. 7 PIAVr SYS1HE 3/4.7.1 SERVICE KATER SYSTUiS

' Residual Heat-Removal' Service Water System..... 3/4 7-1 Service M ter' Systems.......................... 3/4 7-3 3/4.7.2 MAIN 00NfBOL ROCM ENVIRONMENTAL CONTROL SYSTH4. 3/4 7-6 3/4.7.3 REACTOR CORE ISCLATION COOLING SYSPH1.......... 3/4 7-9 3/4.7.4 SNUBBERS....................................... 3/4 7-11 3/4.7.5 SEALED SOUFCE CrJNTAMINATION. . . . . . . . . . . . . . . . . . . . 3/4 7-19 3/4.7.6 FIRE SUPPRESSION SYSTDE Fire Suppression Water System.................. 3/4 7-21 Sprinkler Systems.............................. 3/4 7-25 Iow Pressure CO2 Systems..................... 3/4 7-27 Fire Hose Stations............................. 3/4 7 3/4.7.7 PHErRATION FIRE BARRIERS. . . . . . . . . . . . . . . . . . . . . . - 3/4 7-30 3/4.7.8 SerTLaeNr OF CLASS I 9fRUCTURES. . . . . . . . . . . . . . . 3/4 7-31 3/4.0 ELDCTRICAL POWER SYSTH4S 3/4.8.1 A.C. SOURCES A.C . Sources-Operatirg. . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-1 A.C. Sources-Shutdown.......................... 3/4 8-9 3/4.8.2 O?EITE POWER DISTRIBUTION SYSTHiS A.C. Distribution - Jperatirg.................. 3/4 8-10 A.C. Distrihiticm - Shutdown. . . . . . . . . . . . . . . . . . . 3/4 8-12 D.C. Distribution - Operating.................. 3/4 8-13 D.C. Distribution - Shutdown. . . . . . . . . . . . . . . . . . . 3/4 8-16 A.C. Circuits Inside Primary Containment....... 3/4 8-17 Primary Containment Penetration Conductor Overcurrent Protective Devices................. 3/4 8-18 i

HA'1UI - UNIT 2 VIII l

1 INDEX BASES SECTION PAGE PLAtTP SYSPDiS (Continued) 3/4.7.3 RIACTOR 00RE ISGATION COOLING SYSTDi. . . . . . . . . . . B 3/4 7 3/4.7.4 SbUBBERS........................................ B 3/4 7-2 3/4.7.5 SEALED SOUFCE 00NTM1ItmTION. . . . . . . . . . . . . . . . . . . . . B 3/4 7-3 3/4.7.6 FIRE SUPPRESSION SYSPD1S. . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-3 3/4.7.7 PENEFRATION FIRE BAPRIERS....................... B 3/4 7-4 3/4.7.8 SErrLD1ENT OF CLASS I STRUCTURES. . . . . . . . . . . . . . . . B 3/4 7-4 3/4.8 ELECTRICAL POWER SYSPDIS B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1- REACTOR MODE StilTCH. . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-1 3/4.9.2 INSTRUMENTATION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-1

~

3/4.9.3 CONTR1 ROD POSITION. . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-1 3/4.9.4 DECAY TIl4E...................................... B 3/4 9-1 3/4.9.5 MYYWDARY C0NTAIINENr. . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-1 3/4.9.6 CONUNICATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-2 3/4.9.7 CPANE AND EDIST OPEPABILITY. . . . . . . . . . . . . . . . . . . . . B 3/4 9-2 3/4.9.8 CRANE TRAVEL -SPENT EUEL STORAGE POOL. . . . . . . . . . . . B 3/4 9-2 3/4.9.9 and 3/4.9.10 NATER LEVEL - REACTOR VESSEL AND VATER LEVEL '- SPHTP EUEL STORAGE POOL. . . . . .. B 3/4 9-2 3/4.9-11 00NTR1 ROD RD1WAL. . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-2 3/4.9-12 REAC'IOR 00&#TP CIRCMATION. . . . . . . . . . . . . . . . . . . . . B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PPU!ARY CONTAINMENT INTEGRITY. . . . . . . . . . . . . . . . . . . B 3/4 10-1 3/4.10.2 nod ScouEsCE 00NrRob SYSrm. . . . . . . . . . . . . . . . . . . . . B 3/4 10 .t 3/4.10-3 SERJFDOWN MAFGIN DB4CESTRATIONS. . . . . . . . . . . . . . . . . B 3/4 10-1 3/4.10-4 RECIROJIATION II) OPS. . . . . . . . . . . . . . . . . s . . . . . . . . . . B 3/4 10-1 HATCH - UNIT 2 XIII l

l I

1

I A *

z - n

'pf v pg ,

fPIAUT SYS'HMS L3/4.7[4SNtBBERS LIMITING 00tOITION FOR OPERATION 3.7.4L AllLsnubbers* shall be operable.1 ' %'e only snubbers excluded fra :this

. ' requirement 7 are those installed on non-safety related7 systems and then only.

if their, faiure or : failure of the syste on which they are.-installed would

-have no adverse effect on any safety-related systa .-

s . APPLICABILITY:- C6nditions 1, 2, and 3.

g _; 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) ' l to OPERABLE - status and ~ perform .an engineering evaluation per Specification 4.7.4.c on the supported componer,t or - declare-

the supported .syste inoperable and follow the appropriate ACTION statment'-

+

for that system.

i SURVEILIANCE REQUIREMENTS

-4.7.4 Each snubber shall be deonstrated OPERABLE by performance of the-following inservice inspection progra and the requirments of Specification 4.0.5.

i a. Visual Inspections l All safety-related snubbers shall be visually exmined to verify i'

snubber operability. Visual inspections shall be performed in accordance with the following schedule:

1 No. Inoperable Snubbers Subsequent Visual

per Inspection Period Inspection Period **I O 18 months + 25%

1 12 months T 25%

2 6 months T 25%

. 3, 4 124 days T 25%

5,6,7 62 days -1 25%

8 or more 31 days 1 25%

l We snubbers may be categorized into two groups: %ose accessible

and those inaccessible during reactor operation. Each group may be inspected independently in accordance with the above schedule. i t *% e applicable snubbers shall be identified in plant procedures.

• • The inspection interval shall not be lengthened more than one step at

,a time..

1. %e provisions of. Specification 4.0.2 are not applicable.

- -HA'IQi-UNIT 2 3/4 7-11

-w,- . , -yw-. ,..,.---e y- -wr--- , - - , ,w.....w.,y-y  :'

e ,; -

r

y -

4 s - a SURVEILIANCE RBQUIRBENIS - (Continued)

-t

,b.~ ~ Visual Inspection Acceptance criteria 1 Visual;inspectionsished verify :(1). that there are no visible indicatione of daage or impaired OPERABILITY, (2) attachnents'

. to the foundation ;or - supporting structure are o secure, ' and (3)-

' for. mechanical snubbers where anubber movement -can be manually -

. induced, the snubberu shall be' inspected 1as L follows: = (a) . At each refueling,. systens associated with.= the safety-related mechanical snubbers shall be inspected to determine if there

-has been a severe dynmic event.. (b) . In the event of a severo L dynmic event, snutbers in. that ;systen which experi~enced the event shall be inspected during the refueling outage to. assure the snubbers have freedon of movement and .are not frozen up.

%e inspection shall. consist - of; verifying freedom of.-motion using one : of the' following: -(i) Manually rin3uced : snubber

movement; '(ii) stroking. the mechanical . snubber -through its-l full range of travel. - If one or more mechanical snubbers are found to be frozen up during this inspection,1those snubbers -

7 shall . be replaced - (or overhauled) before returning to power.

Re-inspection shall_ subsequently be performed according to the schedule of 4.7.4.a, but the scope of the exmination shall be limited. to the f systens associated with - the safety-related mechanical snubbers. Snubbers which appear _ inoperable as a result of visual inspections may be determined OPERABIE for

the purpose- c* establishing the next visual' inspection interval, providing .that (1) the cause of the rejection is-clearly established and renedied for that particular snubber and for other snubbers that may be generically ' susceptible; and (2) the affected snubter is functionally tested -in the "as found" condition and determined OPERABLE per Specification 4.7.4.d or 4.7.4.e, as applicable. However, if a hydraulic

anubber is found to contain less than the required minimum F volume of reserve fluid or if visible signs of leakage are r

present, the snubber'shall be detennined inoperable and cannot be determined OPERABLE via functional testing for the purpose 1

.of establishing the next visual inspection interval..

c. Rinctional 'I4sts ,

i i ~ At least once per 18 months during shutdown, a representative ample of 10% of the total of each type (hydraulic or mechanical) safety-related snubber in use in the plant shall

j. '

be functionally tested either in place or 'in a bench test.

Ebr each snubber that does not meet the functional test i acceptance criteria of Specification 4.7.4.d or 4.7.4.e, an  !

additional-smple of at least 1/2 the size of the initial lot of that type of snubber shall be functionally tested.

}

- HA'IG - UNIT 2 3/4 7-12.

l

g 5 ? ,-; s

• .a--

,. i ,

N ;; i '

s , - <

, " ' e f'

4~ l .,, PUWF SumMS .

g _.

[ , i SURVEILIANCE REQUIREMENTS J(Continued)

. ' Rinctional'. testing shall continue until - no : additional inoperable -

anubbers of. a particular type _ are found within a ample orJ until' all

~

E -

'sifety-related snubbers of that type have been functionally tested.

N '

-- S e- representative .,sanple .sslected for functional testing .shall include thes various confhurations, operating _ enviroments ? and the .

range of size and capacity .of - snubbers.' %e ' representative 1 sample; r :shall1 .be/ _ selected- randely. from the total. population- of safety-related - snubbers. At least. 25% of the ' snubbers ~_in the

representative saple shall include' snubbers from the- following three -

. categories:

1.- h e first snubber away from each reactor vessel nozzle, ,

2. Snubbers within 5 feet of- heavy equipnent- (valve, pop, -turbine,

. motor, etc.) , and

. 3. Snubbers within 10 feet of the discharge from a safety._ relief

, . valve..

. Snubbers identified in plant procedures as "Especially Difficult .to-l Remove" or in "High Radiation Zones During ' Shutdown" shall' also be included in' the . representative saple*.- he populations- of-safety-related _ hydraulic and safety-related mechanical snubbers may be used jointly or separately as the basis for the' sampling plan.

In addition-to the regular s a ple, snubbers placed in the sane location as snubbers which failed the-previous functional test shall be retested _ during the next test' period. Test results of these snubbers shall not be included in the sapling plan.-

! If any snubber selected for functional testing either fails to~ lockup 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 design subject to the see defect shall be functionally tested. Wis testing requirenent shall be independent of the

,. requirenents stated above for snubbers not meeting the functional l

} test critiera. l Pbr the snubber (s)' found inoperable, an engineering evaluation shall be perfonned on . the caponents which are supported by the snubber (s) . %e purpose of this engineering evaluation shall be to determine if the components supported by the snubber (s) were

, adversely affected by the inoperability of the snubber (s) in order to F ensure that the supported canponent remains capable of meeting the designed service.

' *Pennanent or other exemptions from functional testing for individual snubber; in those categories may, be granted by the Counission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at i either the copletion of-their fabrication or at a subsequent date )

o

. HMG -- UNIT 2 3/4 7-13

y #

9 m + -

4 a ..w.- s- . -- -a---

- :., f.

T

+

4, PIANT SY!m!MS SURVEILIANCE REQUIREMENIS (Continued)

(d. Hydraulic Snubbers Functional' Test' Acceptance Criteria

~

- %e hydraulic snubber functional' test shall- verify that:

1 ' 1.

.. Activation . (restraining ~ action) is achieved ~ within the Lspecified_ range of T velocity -or accelerationf in . both -

tension.and c apression.

2. Snubber bleeds or release rate, where required, is within -

the specified rangel in 'ca pression or : tension. 'For 4 . snubbers specifically rquired to not displace, under i continuous load,- the ability of the snubber to withstand -

load without displacanent-shall be^ verified.  ;

" e . ,- Mechanical Snubbers Functional Test Acceptance Criteria

- % e mechanical snubber' functional test shall verify that:

^

h 1.- The snubber operates freely over -the stroke- in both tension and compression.

i' i

. 2. The force that initiates free movement-of the snubber rod '

in either tension or' capression is'. less than the i~ _

specified maximun drag force.

3. Activation -(restraining action) -is achieved within the

- -specified range of velocity or reeleration in both tension and compression.

i if. Unit Outage Inaccessible Snubber Inspection

! In the ' event ~t hat : all inaccessible snubbers are inspected ,

functionally tested, and repaired as necessary during a unit

outage, and that it is thus denonstrated that all inaccessible l snubbers are operable, the schedule in Specification 4.7.4.a may be re-entered ' on a 6-month inspection interval for the

, inaccessible snubbers.

l- g. Snubber Service Life Monitoring

. A. record 'of the service life of each snubber, the date at -

I which the. designated service life- ccspences and the installation and maintenance records on which the designated service life . is based shall be maintained as required by Specification 6.10.2.1.

HATCH - UNIT 2 3/4 7-14 6 s -s e e -w h v - e-e e w w w-+eece. --------s e- -

,<it *r --e '-ev i-- e

j

% N .. . g-

'p y;

-x 7 y , .v ., ,

d,.. _ . i s e g w~ , s.s N PIANT SYSThS --

-+3 .. :2 , w h- .,,,#

- /

SURVEILINCE RECUIRDefS:-(Continufd)

-mm

{ Concurrent., withL the inservice visual inspection performed during(the first: refueling cutage following -issuance of this mendaent and at least once per 18 months thereafter, the installation . and imaintenance records for each . safety-related snutter shall be reviewed to verify that the indicated-' service.

life has not been exceeded-or will not be1 exceeded by more than 10% prior to the next scheculed snubber service life review. If the indicated [cervice life will be exceeded by more'than 104 prior to the(next scheduled snubber service life review, the snubber service life'stl all be reevaluated or the snutber shall besreplaced or ~ reconditioned so as to extend its

~

service life beyond the date ~ of the next scheduled ' service g life review. %e fresults .,of .the reevaluation may be used to i

_ justify a change tF the service life of the snubbtxt. %is f-

'Neevaluation, replacanent "

'or reconditioning shall be indicated ,

in the records. , x' i ')

s L

bg 9

)

g

s_ ,

j ~s[ f .

~. g ,

9

/ '1 i

.]

s .

l' e e

r I' .

, w t.

i

/

HNICI - UNIT 2 3/4 7-15 ,

,.,,- . ,n p. - .,- --.

=

• ' H /

- , Y ';_.g. ,.-4 , [

d'

[ E S'

I s s

, , a

',Ac Y

s L }

4 ,

~

~

Y l

,- ,.-1

. ;-l '

. lt ,

1 0,

t w

b- .

3 s b

,, 'l '

/* ,j _

2 $ .g 1

k

!. Il

-u, . '

F -

,ju;,' ,- . z-- -( -.,

r

%' . i3 _' .. , . r

\, -l a v. <

g, p 'E I \

t, , . . .'. (DIIS PAGE LEFT 9 LATE INHNI'IOULLY)-

j 4. s t , ,,

t

--n-'

i' ,3- . .

'gf '3 a

1

& ~/

u.

^

v g .

. ? / l f'.,

/ri

. ' l, i g/.

'f  !

5 '[* '

i

/

- ;" . \ y .

r f

i

' "'. 5,

.y' gi i,

1

'g ,

e F

. HNIGI'. UNIT 2 - 3/4 7-16 a ,< ,

t

s i=l . . + ,

. r# ' g s *

. ~ > ,,.%..- ~

.g -

0 .

,\

.. . -j. - t.'

g_ .._

'" -' ~ -

-?'

' '- 3,4 n.s h

F"_':f-'n'.- ]l v ,J . . ..J':9 / " g 4*. ,

. r,

',0 "g j #' ys 4'

,-jg

.( N+ 7.- 'e 3/ +g';-giJ+>,,

4Q- _* s

-j-,

e.-.- , , p , _

s

.s g -e

".9.

'x,

' jlm, V,

'd'.=

,,, r

~ s. .

'{ te.

N 9

o 6_,. q

- . . . '.x  ;

.9 eX Y j

> -

• i g- I y ..c v v -

l g

m T

• f '

h ,' 4 u'

=

1 1 i N

3 ~- 4 4 -

r- ,

. *. Q

[9. ;

e s b

-w T

f 5 h . S l

T

~

4 l

('DIIS PAGE IEPT BIJNC. INIINFIONALLY) .

4 4 *.

.uz.

4-e K

4 w

e .3

%d' a ' HA'IGI ~- UNIT 2 3/4 7-17 4 ',

'g ,:

$(U; , '

44 s

/ m

• 6 h

4 t s' ! 1 ik'

'. lw .- m

% v N ** 7 N9FW* * ' '  ?

• y ?kf g '9'9t'=+@M T'h' - a* g-t"$'--f-'Fr'*- y'm4* p 39'1 4Wg -e -fT v- M e-*'Wg-r.+ Tee -4e c + 4 + w- *w p pei e- se &4

r <> - -

--l- ]

2_ ,

-,$- '_.h,'-

'.N%

s I

k .

=, s

• ..h 9 . e -

d i

w.

J t

9 Y

-(THIS PAGE LEET BIM INHNTIONALLY) .

6 i '

s I

. . HA101 - UNIT 2 3/4 7-18 O A l

a .I a

-,h+,} '

4 f

M - ..55 . s9 .,, , _ ., _ , , . . _ , . . ,, _ _ , _ _

w . ~ -- - . -- --

_d e_. ..- p. 1 ,

j

.t 1.e

~

j: ,

7' l

a  :

3/4.7 PIMf SYSTEMS

. - Bases REACTOR CORE ISOLATION COOLING SYS'ITM (Cmtinued)'

~ he . surveillance requirments provide. adequate assurance' that RCIC.will be

• s ..OPERABIE Lwhen re3uired. ! Although all active caponents - are testable ~ and full:

! flow can be dmonstrated by recirculation during reactor operation,> a cmplete functional tes't irequires ' reactor . shutdem..- : %e pop -discharge 7 piping i is -

E ' maintained - full to - prevent 1 water ' hamer . dmage and ' .to start ' cooling . ato the earliest mment.-

3/4.7.4 SNUBBERS An snubbers are re]uired OPERABIE to ensure that the structural integrity =

of the reactor coolant syste and all other-l safety-related ~syste s iis a seimic . or other event -: initiating dynmic

.maintained- during -and- following:his inspection progra are those installed on loads. Snubbers excluded from t nonsafety-related -'systes and then only if their failure or - failure of the

_ system -on which : they -are- instaned, would have no ' adverse - effect on any i safety-related system.

~

- %e visual. inspection frequency is based upon maintaining a constant level of snubber protection to systens.- %erefore, the required inspection interval ,

varies ' inversely l with the observed snubber failures and is determined ' by the

! number of inoperable snubbers found during an inspection. Inspections j perfomed before the interval has elapced may be used as a new reference point to determine -the- next. inspection. However, the results of ~ such early inspections performed before the original required time interval has elapsed j (nominal time less 25%) may not be used to lengthen the' required inspection F 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 renedied for the snubber and for any other snubbers that raay be generically i susceptible, and veified by inservice functional testing, that snubber may be i exmpted frm being counted as inoperable. Generically susceptible snubbers

' are those which are ' of ' a specific make or model and have the see design features directly related to rejection of the snubber by visual inspection, or

- are similarly located or exposed to the see enviromental conditions such as i tenperature, radiation, and vibration.

, - When a snubber is found inoperable, an engineering eval.uation is perfomed, l

in addition to the determination of the snubber mode of failure, in order to  ;

determine if any safety-related cmponent or systen has been adversely affected 1 by the inoperability of the snubber. %e engineering evaluation shall 1 determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported cmponent or systen.

p To provide assurance of snubber functional reliability, a representative saple > of the instaned snubbers will be functionally tested during plant shutdowns at 18-month intervals. Observed failures of smple snubbers shall rajuire functional testing of additional ~ units.-

-Hydraulic snubbers and mechanical snubbers may each be treated as a

-different' entity for.the above surveillance progras.

~

l HATCH - UNIf 2 B 3/4 7-2

_ . -. _ ._ . - . . . . - . _ . _ . - _ . . . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ __..I

~ "

" a r a

= PLANP SYSPEMS BASES 13/4.7.4' SNUBBERS (Continued)

We serviceKlife of ra snubber -is evaluated via' ranufacturer input and iinformation .through . consideration of' the snubber service conditions and -

-associated (installation and maintenance records (newly , installed snubber, seali. replaced, spring replaced, in high radiation area, in high temperature-

-area, etc...). De requirement to monitor the snubber'-- service -life is included to ensure ' that : the - snubbers - periodically undergo La performance -

. evaluation. in ~ view of . 5 their -age and operating cxxiditims. %ese remrds -

will provide statistical _ bases for future consideration of snubber service life. . Se requirements for ~ the maintenance of records and the snubber service life review are not intended to affect plant operation.

3/4.7;5 SEALED SOURCE (DNEAMINNFION .

We limitations on sealed source removable contamination ensure that the

-total body or individual organ irradiation does not exceed allowable limits in the . event of _ ingestion or inhalation of the source material. We limitations 'on removable contamination for sources requiring leak testing,-

l including' alpha emitters,' is based on 10 CFR 70.39(c) limits for_ plutonium.

Quantities . of interest to this specificatim which are ' exempt frm the -

leakage testing are- consistent with the criteria of 10 CFR Part 30.11-20 and

, 70.19. Isakage from sources excluded frm the rerjuirements of 'this specification is not likely ~to represent more than one maximum permissible body burden for total bo3y irradiation if the source material is inhaled or ingested.

'_ 3/4.7.6 FIRE SUPPRESSIOti SYSTH1S

[ 2e OPERABILITY of the - fire suppression systems ensures that adequate-i fire 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, 002 , and fire hose stations. he collective capatility

. 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 that porticus of the fire suppression systems are p inoperable, alternate backup fire fighting equipment is required to be made -

, available in the affected areas until the inoperable equipment is restored to service.

l - In the - event the fire suppression water. system becomes inopere,ble, l imediate corrective' measures must be taken since this system provides the

[

major fire = suppression capability of the plant. De requirement for a twenty-four hour report to the comission provides for prompt evaluation of l- thei acceptability of the mrrective measures ' to provide adequate fire suppression capability for the continued protection of the nuclear plant.

HNTOI-UNIT 2 B 3/4 7-3 gr '-~v-- yeg-g- e -

yg -4 g if yr-y-W*w 9 ge - t vi y- T- = My ywwww' v*wy-'-g-' gy-gm --'**---y w -c- - pyginesP9pvyg e arg--

,. . c

n-

- ,N *

~7 c - ,

.#. ~

ys

JUtINISMATIVE ONHEE, -

Dj_ ,

REXX)RD RPHNfIm (Continued) ~

c J- C c. .J Records. of radiationiexposure for ; alll individuals' entering ' radiation control areas.

[d.' . liecords ; ofigaseous and 1kluid radioactive material - released to . the -

c environs.' .

Le.? LRecords of transient or' operatiorial cycles- for;those unit components -

.; identified in Table 5.7.1-1.-

f. Records of reactor-tests and experiments.-

g. Records of training and_ qualificar. ion . for: current members of the -

unit: staff.-

h. Records Lof? in-service inspections -performed -pursuant- to these Technical Specifications.

l'. Records of Quality Assurance activities required by the OA Manual.

t

j. Records of reviews - performed for changes made to procedures or equipnenti.or reviews of tests and ~ experiments pursuant to 10 CFR -

50.59.

k. Records of meetings of the PRB and the SRB.

1. Records of the service lives of all safety-related hydraulic and mechanical snubbers, including the date at which the service life commences and associated installation and maintenance records.

6.11 RADIATION PROTECTION PROGRAM i

Procedures for personnel radiation protection shall be prepared consistent ,

with the requirments of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12,l' In lieu of the " control device" or " alarm signal" required by

paragraph 20.203(c) (2) of 10 CFR 20, each high radiation area in which the i

. intensity of radiation is greater than 100 mre/hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area ' and entrance thereto shall be controlled by rs;uiring issuance of a Radiation Nork Permit *. Any individual or groups of individuals permitted

• IIealth Physics personnel, or personnel escorted by Health Physics personnel in accordance' with approved emergency precedures, shall be exenpt fra the RWP issuance requirenent during the performance of their assigned radiation protection duties, lprovided - they cmply with approved radiation' protection 4

procedures.for entry into high' radiation areas.

HATG-UNIT 2 : 6-18 _,

1 g - 5e . ...m-+ -- , ,-e. ,...r. - ,ev.-,,,--o.., .- ,c..--e - , ~ . ,..-----%w-.* [ r + e -- i-*-e-e,-e-- -a-.-- *e,-e v e r. v+ .-

i

'(#. *-

n ENCICSURE 4 ~

NRC DOCKETS 50-321, 50-366.

OPEIRATING LICENSES DPR-57, NPF-5

_ EEWIN I. HATOI NUCLEAR PIANT UNITS 1, '2

REVISION TO PRO 10 SED SNUBBER TECHNICAL SPECIFICATIGE Pursuant to 10 CFR 50.92, ; Georgia Power Capany ~ has evaluated- the

attached proposed amenchents for _ the two Hatch units and has determined that their adoption would not involve ~a significant hazard. n e basis for this determination is as follows

a. PROPOSED CHANGE As rq uested by the NRC letter' dated Noveber 20, 1980, revise the Limiting Condition - for Operation to require that mechanical, as well as hydraulic safety-related snubbers be operable.

BASIS-h is change for both Hatch units constitutes an additional control not - previously ' included in the Technical Specifications. %is change does not affect the probability or ccnsequences of an accident or malfunction analyzed in the FSAR. This change does not create the possibility of an . accident or malfunction of a different type than analyzed in the ESAR. _ % e margin of safety as defined in the basis of any . Technical Specification is _ not affected. The effect of this change is therefore within the acceptance criteria and the change is consistent with Its (ii) of the "Exmples of Amenchents That Are Considered Not 'Likely to Involve Significant Hazards Considerations" listed on page 14870 of the April 6, 1983 issue of the Federal Register,

b. PROIOSED CHANGE As allowed by Generic Letter 84-13, delete the listings of safety-related hydraulic snubbers frm the - Technical Specifications. Specify in the Limiting Condition for Operation the hyd .ulic and mechanical snubbers which are required to be operable.

Wis change for both Hatch units is purely adninistrative in l- nature. %e change has no effect on which hydraulic snubbers are subject to the Technical Specification requirments. %is change does not' affect the probability or consquences of an accident or malfunction analyzed in.the FSAR. % is change does not create the possibility of an accident or malfunction of a different type than l

f i-

, . m. -

3... 7. .

-h . .

.z . > t:; ,

~

ENCIOSURE 4 (Continued'):

s NRC DOCKETS 50-321,,50-366-

OPERATING LICENSES DPR-57, NPF-5

^ ^

, ED(IN I. HATOI NUCIEAR PIANT WITS 1, , ~ REVISION TO PROPOSED SNUBBER TECHNICAL' SPECIFICATICES

.  ! BASIS- (Continued){

any analyzed in the ESAR. % e margin of safety as-defined in.the 1 basis ' for o any Technical Specification is -not L affected by. the

~

jchange. '%e J effect- of:' the ichange : is. therefore - within- the

~'

acceptance criteria and the change is consistent with Iten -(i) of . ,

~ the ~ "Exanples of Anendnents . %at - Are iConsidered Not' Likely to Involve Significant= Hazards Considerations"; listed on page:14870 of the April 6, 1983 issue of the Federal Register.

c. PROPOSED G ANGE As requested byL NRC; letter dated Novenber 20, 1980, revise the -

" Action"~ statenent :for the Snubbers Limiting Condition for -

Operation- to require .an .' engineering evaluation on . the supported conponent: or declare the supported ~ systen inoperable and . follow the -appropriate " Action" statenent for that systan if inoperable

~

snubber (s) .are -not returned to operable. status within 'the Technical Specification-allotted ~ time.

BASIS Wis change for 'both Hatch units constitutes an additional control not previously included in .the Technical Specifications. nis change does not affect the probability or consequences of an accident or malfunction analyzed in the FSAR. His . change does not create the possibility of an accident or ralfunction of ~ a different type than analyzed in the FSTR. % e margin of safety as defined' in the basis of any Technical Specification is not affected. %e effect of this change is therefore within the acceptance criteria and the change is consistent with Iten (ii) of

the -"Exanples of Anendments ' nat Are Considered Not Likely to Involve Significant Hazards Considerations". listed on' page 14870 of the April 6, 1983' issue of-the Federal Recister.

I l

i-r - . - . , . . . - _ .. - ,, , - -. .~o .- _ - - . . . - . - - ~ , , - . . ~ , .

_, -p<,.

J ENCIOSURE '4 (Continued) .

NRC DOCKETS 50-321, 50-366-OPERATING LICENSES DPR-57, NPF-5 ENIN I. HATOI NUCIEAR HJNr UNITS 1, 2 REVISIN 70 PROPOSED SNUBBER 7ECHNICAL SPECIFICATIONS d.- PROIOSID CHANGE As requested by 1BC letter dated Novenber - 20, 1980, revise , the

" Action" statenent 'for the Snubbers - Limiting : Condition for

. Operation such that if one or more inoperable snubber (s) is not -

' replaced or. returned to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, declare

-the supported systen inoperable 'and follow the appropriate limiting condition for operation statenent(s) for that systen.

BASIS

, -Since snubber protection is only reluired during low probability events such as eartiquakes or severe transients, changing of the Snubbers Limiting Condition for Operation such that the appropriate limiting condition for ~ operation statenent(a) is followed for the systen on which the 'affected snubber (s) is located does not' significantly affect the -probability or consequences 'of an accident or malfunction of a different type than analyzed in the FSAR. This change does not create the possibility of an accident or malfunction of a different type than analyzed in the FSAR. The margin of safety as defined in the basis of any Technical Specification is not significantly affected. The effect of this change is therefore within the accept ance criteria of Itan (vi) of the "Exarples of Amendnents That Are Not Likely to Involve Significant Hazards Consideration" listed on page 14870 of the April 6,1983 issue of the Federal Register.

! e. PROIOSED CHANGES i

As raluested by NRC letter dated Novenber 20, 1980, revise snubber surveillance raluirenents to incorporate the folowing:

i Y i _, , _ - - . , . _ _ _ _ . , m - . , . ,,.-,_.-,-1

~

^

Qf ..r.. >

~

.e

? Ql '

rQ

,6.,

D3CIOSURE'.4 (Continued)

NRC DO3ETS 50-321, 50-366 ~

_ 1 OPERATING LICENSES DPR-57, NPF-5 .

EDWIN I. HA101 NUCIEAR PIANT UNITS =1, 2

- REVISION 10 PROEOSED SNUBBER TECHNICAL SPECIFICATINS -

c; -~-

d.A'

,e wg "ei ~ PROPOSED N A ti M )

-; <l.; ~ Revise ~isnubber,. visual inspections. and visual- acceptance 1 criteria to include the following:

P a. Add visual . inspections requirments c for ; safety-related -

-. mechanical snubbers,

b. Add assurance that -snubber attachtents to foundation or supporting structure are-secure.'

c.- Add ' requirment that safety-related mechanical snubbers be inspected to determine -if there has been a : severe dynmic event and perform specific actions if such an event has occurred.

e. Provide statement for determination of operability. .

2. Revise functional test requiremer.ts to include the following:

~

.a.. Increase functional test saple size such that 10% of each type safety-related snubbers are exmined at least once per 18 months during shutdown.

b. Change re-se ple~ size for- each snubber failing functional test to at least one-half the size of the initial. saple . size for the particular snubbers functionally tested, c.. Add the requirment that 25% of the representative.

smple ~ for the functional test be selected from the three~ areas specified in Standard Technical

Specification Section 4.7.9.c.

t-

d. Add the requirment such that snubbers placed in the see location - as snubbers- which failed the previous functional test be tested during the next test period.

e. Add the requirment such that cause of failure will be evaluated for snubbers failing functional testing.

f. Add the requirment such that an . engineerire evaluation

~

will be perforced on ~ caponents which are found to be supported by failed snubbers.

J - .

~

a: ~' ~

^}. , ,, -

z * -

. w ,

_h i s

r s

r m

y ~

4 P.NCIDSURE-'4 ((bntinued) ' ,

,7NRC DOCIETS 50-321,l5U-366:

- _ ~

OPFRATING LICENSES DPR-57,1NPF-5 ~ . .f ,

J . m- / EEMIN'I. HMQi NUCIFAR PLANT IMITS '1, 2 2 . _ .

- REVISION 'IO PROPOSED SNMR 'IFUMICAL SPECIFICATIONS-

~

~

e .' ' PROPOSED OIANGES . (Continued)

? Add " functional . test : accept.ance . criteria y for i safety.-related .

" -3.'

i- ' ~ mechanical anubbersn 4

4 .- : AddEstatment7suchithat in the eventI that all inaccessible - -

^

snubbers are -inspected, functionally- tested, ? and repaired, ~ as:

necessary, during. a LunitJ outage, :and:.that2 -it; is: thus denonstrated ' all L inaccessible snubbers : are : operable, the-

visual examination ; scheduled may be ; reentered , on .a .6-month inspection Jinterval.- nisiaddition willfapply to Hatch ~

- . Unit-2 only 'asthis type ' statenant ~ is. presently 1in - the l existing - Hatch Unit ' 1 Technical Specifications land will be;

. included in the p oposed changes _ included herein.L requirement : for_

5. Add service : life monitoring . of . each safety-related snubber and retention of records thereof.

l BASIS

%ese changes for both Hatch units constitute additional condols L and/or limitations, as agpropriate, not presently included in the

! 'mchnical Specifications. %ese changec do not affect' the probability or consequences of an accident or malfunction analyzed in the FSAR.. Wese_ changes do not create the possibility -of an

~

accident or malfunction of a ~different type- than analyzed in the FSAR. . %e margin' of safety, as ' defined in the basis ' for any Technical Specification is not affected. %e effect of these changes ' is therefore within the acceptance criteria and these L changes are consistent with Item' (ii) of the " Examples of F 7merxinent hat . Are Considered Not Likely to Involve Significant L -

Hazards Considration"' listed on page 14870_ of the April: 6, 1983 issue of the Federal ~ Register.

L L

f. PROPOSED CHANGES As necessitated by the NPC letter dated November 20, 1980, revise ^

the- following to reflect changes- in snubber surveillance.

l-requirements:

l' l. Change Table of Contents" and " List of Tables" pages, where L_ appropriate, to correct, add,' or' delete tables, etc.-

resulting from these snubber surveillance changes. t

- e

'- a e ,5 .~-,.s ,'--+, N. - , , n, n A n -u-,NN. v ,,ev , ,,.n ,,,,w+,,-n.,.-e-vm..,--nm.. --w~w,,. ---e,- w ,rs .,, e, m.em,n~- -

n. a, m e .u-6: -

E  !

DEIOSURE 4 (Cohtinued)-

- NRC D00ETS 50-321, 50-366 .

OPERATING'LIONSES DPR-57, NPF-5 EDiIN I.- HA701 NUCLEAR PIANT UNI 75.1,- 2  ;

REVISION TO PROEOSED SNUBBER 7EGEICAL SPECIFICATIO_NS

- f .' PROPOSED CHANGES ' (Continued) .

2.- Change the bases sections to reflect - the revised ' snubber inservice surveillance requirenenta. =

3. Add record retention requirenents for service. life monitoring as a result of the revised snubber inservice surveillance in

- the achinistrative controls- section of Technical' specifications.

BASIS These changes to the Technical Specifications for both Hatch units are achinistrative in nature. - These . changes do r.ot affect the

, probability or consequences of an accident or malfunction analyzed in the FSAR. . These changes do not create the_ possiiiity of an accident or malfunction of a different type - than analyzed in the ESAR. She margin' of f safety as defined in the- basis for any Technical Specification is not affected.- The effect of ' these changer are therefore within' the acceptance criteria and these i changes are consistent with- Iten~ .(i) of the "E ax nples . of Amenchents That Are Considered Not Likely to' Involve Significant Hazards Considerations" listed on page 14870 of the April 6,1983 issue of the Federal Register.

i-d

• _h w a ., re . y ,++i wwr-vy--++ .w--a.*w w r .yery a v - w w w -p y y w y+&-,- y- .q- - , .--g.y -

pc e