Text

Proposed Tech Specs,Revising Sections 3.0.4 & 4.0.4 to Allow Entry Into Operational Condition,Per Action Requirements & 4.0.3 to Allow Delay of Up to 24 H to Permit Completion of Missed Surveillance
	ML18005A211
Person / Time
Site:	Harris
Issue date:	11/09/1987
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML18005A210	List: ML18005A209; ML18005A211;
References
	NUDOCS 8711180128
	Download: ML18005A211 (68)
	v • d • e

1 3/<. 0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.L Compliance wi h the Limiting Condi ions for Operation contained in he succeeding specifications is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requiremenw shall be me 3.0.2 Noncompliance with a specif'ica ion shall exist when the requirements of the Limiting Condi ion for Operation and associated ACTION requirements are not met within the specified time intervals.

If the Limi ing Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required unless otherwise noted'n he ACiION statement.

3.0.3 When a Limi ing Condition for Opera ion is not met, except as provided in the associated ACTION requirem'ents, within L hour action shall be ini ia-ed to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in:

a.

At leas HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

At least HOT SHUTDOWN within the following 6 bout, and c.

At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Where correc ive measures are completed that permit operation under the ACTION requirements, the action may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation.

Exceptions to these requirements are stated in the individual specifications.

This specifica ion is not applicable in MODE 5 or 6.

I 3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not e

be mad Thi s provision shall not preven-passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

Excep ions to these requirements are sta.ed in the individual specifications.

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APP LICABILITY SURVEILLANCE REOUIR MENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MQOES or other conditions specif'ied far individual Limiting Canditions for Operation unless otherwise s~ted in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:

a.

A maximum allowable extension not ta exceed 2~~" of ie surveillance interval, but b.

The combined time interval for any three consecutive surveillance intervals shall nat exceed 3.25

.imes the speci ied surveillance interval.

> ~<~Md Q-Gp<c.i ficcefion. l 0 Q >

+Q~~zu~g//~Q 4.0.3 Failure ta perform a 8'urveillance Requirement wi.hin thef~qee4+&

Lies interval shall cons-itute

~~e-eee4, the OPERABILITY requirements for a imitin Condition for 0 Surveillance Requirements do not have to be performed on inoperable equipment.

no~~lia~mi+Q 4.0.4 Entry into an OPERATIONAL MQGE or other specified condition shall not be made unless the Surveillance Requirement(s) associated wiN the Limiting Condition for Opera ion has been performed within the smted surveillance interval or as otherwise specified. Tl.z F eovi<ion. c4Jl nof.pte~iif P4~P 440+L4>W 4 GRRY zQQALg(48K 04 os~ kcowplg 4p> fL Rcl 40Q QlJire'-lkhcfg, 4.0.5 Surveillance Requirements for iRservice inspection and testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows:

a.

Inservice-inspection of ASME Code Class 1, 2, and 3 camaonents and inservice tes.ing af ASME Cade Class 1, 2, and 3 pumps and valves shall be performed in accardance with Section XI af the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR Part 50, Section 50.55a(g),

except where specific writ en relief has been granted by the Commission pursuant to 10 CFR Part 50, Sec ion 50.55a(g)(6)(i);

.+~ ii~e. IiMi+a of'EL~ RCTZoQ ~guii ~nj~~i~ ~pc ~pp((~~$ 1<

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~y yg~ ~~~pa; I/~~~ gal e~fja nflwah(~ c usa.gm g e~f'imipw ofVLe P~izQ)g re cilv'am"~~ ri~'Ww'TL-w'a'D14ii'rz'.""

~ 8" SHEARON HARRIS - UNIT I 3/4 0-2

tA CI FUIICTlgtlAL UNIT iH l.

Hanual Reactor Trip I

2.

I'ower Range, Neutron Flux a.

Iligh Setpolnt b.

Low Setpo}nt 3.

Power Range, Neutron F lux lligh Positive Rate TAIILE 3.3-1

'TOTAL HO.

OF CIIANNELS CIIAtlllEl.S IO Tlllp HINlHUH CI IANtIEL5 OPERAOI.E

.2 2

REACTOR TRII'YSTEH IIISIRUHEIITAT]011 APPLICARLE HOOES 1

2 3L g*

54 l, 2

]HP, 2

li 2 Source

Range, Heutron Flux a.

Startup b.

Shutdown Overtemperature AT 7.

Power Range, Heutron Flux, illgh Negative Rate 5.

Intereedlate

Range, Neutron Flux 6.

'. 3 2

2 1I 2

lPPP, 2

2H 3, 4, 5

1, 2

0.

Overpower AT 9.

Pressurizer Pressure Low {Above P-7) 3 10.

Pressurizer Pressure lligti 11.

Pressurizer Mater levellllgh

{Above P-7) 1, 2

1 1,

2

I

.4,

'L ~

1

TABLE 3. 3-1 Continned REACTOR TRlP SYSTEH IIISIAUIILHTATlOll FuIICTiOHAL UAIT 12.

I Reactor Coolant Flow--Low a.

Single Loop (Above P-0) 13.

5teara Generator Mater Level--Low-Low b.

Two Loops (Above P-7 anrl below P-O)

TOTAL tin.

OF CIIAIIHELS

]/loop 3/loop

'/stm.

gen.

CllhllHELS IO TRIP 2/loop I rl any oper-a t Ing Ioop 2/loop in two oper" ating loops 2/stm.

gen.

in arry oper-ating stm.

gen.

l HIHlllUH CllnIIAELS OPEAAOLE 2/loop In each oper" ating loop 2/loop 'In-each oper" ating loop 2/stm.

gen.

each oper" ating stm.

gen.

APPLlCAOLE INOES 1,

2 ACTI Otl 6 (1) 14.

Steam Generator Mater LevelLow Coincident Mith Steam/

Feedwater Flow Hisraatch l5.

Undervo I tage Reactor Coolant Pujrlps (Above p-7) 2 stm.

gen.

level and 2 stlrr./feed-water flow mismatch in eacll s tm.

gen.

2/pr rrrlp 1 slm.

gen.

level coin-cirlent wl 'th 1 stm./feerl-water flow mismatch ln

~

same stm.

gen.

2/train 1 stm.

gen.

level and 2

s tm./feerl-water flow mismatch in same stra.

gen.

or 2 stm.

gen.

level and 1

s tm./feedwater flow mlsmatcli in same stra.

gen.

2/train 1,

2

I ~

I

~

ThIILE 3. 3-1 Cont. Inued}

REhCTOR TRIP SYSTEH IHSTRUHBITATIOH I

j>

I E'

~I.I C:

I'

~

I W

FUllCTIOHhL UHIT 16.

Underfrequency Reactor Coolant Pumps (Alcove P-7) 17.

Turbine Trip (hbove P-7) a.

Low Fluid Oil Pressure b.

Turbine Throttle Valve Closure 10.

Safety Injection input from ESF 19.

Reactor Trip System Interlocks a.

Intermediate Range Neutron Flux, P-6 Low Power Reactor Trips Olock, P-7

1) P-10 input, or

2) P-13 input c.

Power Range Neul.ron Flux, P-8 d.

Power Range Neut,ron Flux, P-10 e.

I<<rhine impulse CI>amber

Pressure, P-13 OlhL NO.

O CIIAHHELS 2/pump HINIHU4 CIIAHNELS CIIAHHELS IO 1IIIP OPERABLE 2/train 2/train APPLICABLE HODES 1,

2 1,

2 ACIIQH 6

10

~~

7

'I

) ~

ly

.0

. TAB[ >> 3.3-1 Continued TABLE NOTATIONS f

'%hen the Reactor Trip System breakers are closed and the Con ol Rod Drive Sys em is capable of rad withdrawal.

Whenever Reactor Trip Breakers are ta be +us ed.

AFBelaw the P"6 (Intermediate Range Neutron Flux Interlock) Setpoin..

WBelaw the P-'0 (Law Setpoint Power Range Neutron Flux In erlock)

Se pain

~

(1)The applicable MODES and ACTION Statement far these channels na ed in Table 3.3-3 are more restric ive and, therefore, applicable.

ACTION STAT&>>. EHTS ACTION 1 - Wi h the number of OPERABLE channels ane less than the Minimum Channels OPERABLE requirement, restore the inoaerable channel to OPERABLE status widin 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be fn HOT STANDBY within the next 6 haul s ~

A~iOH 2 - With the number af OPERABI

>> channels one less than the Total.

~

Number of Channels, STARTUP and/ar POWER OPERATION may proceed provided the following conditions are satisfied a.

ihe inopershle uhsnnel is p'laded in the t ipp-.ed donditiod within d hours, h.

c The Minimum Channels OPERABL>> requiremen is met; however, he inoperable channel may be bypassed for up ta 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

,or surveillance tes ing of o Her channels per Specifica ion 4.3.1.1, and ii>er, THERMAL POWER is res riced to less San or equal ta 7~~ of RA'ii) THERMAL POWER and Ne Power Range Neutron Flux Trip Setpoint is reduced ta less than ar equal to.,

85 of RAT2l THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitared at least ance per 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months per Specification 4.2.4.2.

SHEAROH HARRIS - UNIT 1 3l4 3-6

~ ~

~

TABLE 3.3-3 Continueii EHGIHEEnL'0 Shf ETY FEATURES ACTUATIOH SYSTEH IHSTRUHEHTATIOH FUHCTIOHAL UHIT TOTAL HO.

OF CIIAHHELS CimHHELS TQ TRIP HIHIHUH CHAHHELS OPERABLE APPL ICAOLE HOOES hCT ION tH l

.I I

4.

Hain Steam Line Isolation (Continued)

. b.

Automatic Actuat.ion Logic and Actuatfon Relays-1, 2, 3, 4

21 I'

I c.-

Containaent Pressure--

iiigh-2 3

ls 2s 3

]54 if., Steaii Line Pressure--

Low See Item l.e.

above for Steam i.lne Pressure Los fnltiat.ing functions and requirements.

-; 5.

e..

Kegative Steaa Line Pressure Rate illgh Turbine Trip and Feeilwater Isolation a;

, Autoiiatfc Actuation, Logic and Actuation Relays r

b,'team Generator

Mater Level-

. Iiigh-High (P-14) c.'afety InJection I

I

~

I I

tl 3/steaa line 2 ln any steaii line 4/ste.

gen.

2/sto.

gen.

in any stM. gen.

See Item l. above (or all requirements.

2/steaiw line 3+"" 4"""

15+

l, 2

24 1,

2 3/sts.

gen.,

19+

in each stia.

gen.

Safety InJectfon lnltlating functions anif 4.

INS i RUMENTATION 3/4. 3. 3 MONITORING INSTRUMNTATION RADIATION MONITORING FOR PLANT OPERATIONS LIMITING CONDIiION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels for plant operations shown in Table 3.3-6 shall be OPERABLE with their Alarm/Trip Setpoints ~ithin the specified limits.

APPLICABILTii':

As shown in Table 3.3-6.

ACTION:

ae With a radiation monitaring channel Alarm/irip Se~aint far plant operations exceeding the value shown in Table 3.3"6, adjus the Setpaint ta within tne limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ar declare the channel inoperable.

With one or mare radia ion monitoring channels far plant aperations inoperable, take the ACTION shown in Table 3.3-6.

The provisjons of Specification 3.0.3 wa4-Q~ are nat applicable.

SURVEILLANCE REOUIRBIEHTS

/

4.3.3.1 Each radiation monitoring instrumentation channel for plant operations shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANHEL CALIBRATION and OIGZiAL CHANHEL OPERATIONAL icST for the MODES and a the frequencies shown in Table.4.3-3.

SHEAROH HARRIS UNIT 1 3/4 3-50

I

~ ~

IHSTRVMEHTATION MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The Movable Incore Detection System shall be OPERABLE vith-a4 Rt leas 38 detector

thimbles, b.

A minimum of ~o detector thimbles per care quadrant, and C.

Sufficient movable detectors, drive, and readout equipment ta map these thimbles.

APPLICABILITY: When the Movable Incare Detection System is used for:

..a..

b.

C.

ACiIDH:

Recalibration of.the Excore Heutron, Flux Detection System, or Monitoring he QUADRANT POWER TILT RATIO, or Measurement of F~

F~(Z) and F N

P 7

With the Movable Incore Detection System inoperable, do not use the system for the above appl jcable monitoring or calibration func ions.

The provisions of Specificatiagf 3.0.3 ~4444. are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.2 The, Movable Incare Detection Sys~ shall be demonstrated

OPERABLE, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to use, by irradia ing each detector used and deter mining the acceptability of its voltage curve ~hen required for:

a.

Recalibratian af he Excore Heu ron Flux Detection System, or b.

Monitoring the QUADRANT POWER TILT RATIO, or

-c. Measurement a

F>

F~(Z) and Fxy SHEARQH HARRIS - UHIT.L 3/4 3-56

1 g1 tf,'f

IN~iUMENTATION SEISMIC INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.3 The seismic mani-aring instrumentation shown in Table 3.3-7 shall be OPERABLE.

APPLICABIL~i. At al 1 times.

ACTEDN:

a ~

b.

Nth one or more of the above required seismic monitoring ins ruments inoperable for more than 30 days, prepare and submit a Special Repor't ta the Canmission pursuant ta Specificatian 6.9.2 withsn the next 10 days outlining the cause af the malfunc ion and the plans for restoring Ne instrument(s) ta OPERABLE status.

The provisions of Speci, fcatia 3.0.3 end-i4444 are not applicable.

SURVEILLANCE REOUIREMENTS 4.3.3.3.1 Each of the above required seismic monitoring instruments shall be demons rated OPERABL>> by Ne performance of the CHANNEL CHECK, CHANNEL CALI-BRATION, and an ANALOG CHANNEL OPERATIONAL TEST a the frequencies shown in Table 4.3-4..

4.3.3.3.2 Each af the abave required seismic monitaring ins ruments ac uated.

during a seismic-even ~eater than ar equal ta 0.03, g shall be restored to OPERAB!>> status wiDin 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and a CHANNEL CALIBRATION performed within 10 days following the seismic event.

Data shall be retrieved from ac~ted inst~ents and analyzed ta determine Ne magnitude of the vibr'atary ground motion.

A Special Report, shall be prepared and submitted m the Canmission pursuant to Specifica-.ion 6.9.2 wi Win 14 days describing the magnitude, frequency spect~,

and resultant ef ec upon facility features imporent a

safety.

SHEARON HARRIS - UNIT 1 3/4 3-57

A).

INSTRUMENTATION MET"OROLOGICAL INS<RUMENTA<ION LIMITING COND~<ON FOR OPERA) ION 3.3.3.4 The meteorological monitoring instrumentation channels sho~n in Table 3.3-8 shall be OPERABLE.

APPLICABILITY: At all imes.

ACTION:

a.

b.

ND one or mare required meteorological monitoring channels inaperable for more than 7 days, prepare and submit a Special Report to he Commission pursuant to Specification 6.9.2 within the next 10 days ou.lining the cause of the malfunction and the plans for restoring the. channel(s) to OPERABL"- status.

4 The provisions of Specificatian 3.0.3 ~~~ are not, applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.4.

Each of the above meteorologicaI monitoring instrumentation channels shall be demanstrated OPERABI n'y the performance of the CHANNEL CHECK and CHANNEL CALIBRATION at, the frequencies shown in Table 4.3-6; SHEARON HARRIS - UNIT 1 3/4 3-60

I

~l r

INS i RUMENTATIOX CHLORINE O~iCTION SYSiEHS LIMITING CONDITION FOR OPERATION 3.3.3.7 Two independent Chlarine Detector Trains, with their Trip Setpoin s

adjusted to actuate at a chlorine concentration of'ess than or equal to five ppm, shall be OPERABLE.

Each train shall cansist of a detector at each Con rol Room Area Ventilation System intake (both narmal and emergency) and a detec or at the chlarine storage area.

4 APPLICABILITY: All HQDES.

ACTI0ii:

a.

With one Chlorine Detector Train inaperable, restore the inoperable system to OPERABl ~ status wi hin 7 days or within the next, 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ini rate and maintain opera ion of the Control Room Area Ventilation System in the recirculation mode of opera ion.

Wi h bo h Chlorine Detector Trains inoperable, wi hin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ini iate and maintain operation of the Control Roam Area Venti 1 ati on System in the recirculation mode of operation.

SURVEILLANCE'EOUIRBIENTS 4.3.3.7 Each Chlorine Detector Train shall be demonstrated OPERABLE by performance af-a-CHANNEL CHECK at least once per 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months , an ANALOG CHANNEL OPHNTIONAL TEST at leas~

ance per 31 days and a

CHANNEL CALIBRATION at least once per XB months.

SHEARON HARRIS - UNIT 1 3/4 3-72

't

~

r,i..i~ ~,

INSTRUMENTATION METAL IMPACT MONITORING Sy~i LIMITING CONOITION FOR OPERATION 3.3.3.9 The Metal Impact Monitoring Sys em shall be OPERABLE.

APPLICABILITY:

MQOES 1 and 2.

ACTION:

ao Mith one or mare Metal Impact Monitoring System channels inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specifica ion 6.9.2 within the next 10 days

'utlining the cause of the malfunc ion and the plans for res.oring the channel(s) to OPERABLE status.

The provisions of Specification 3.0.3 ~3-.9.

$ are not applicable.

SURyEILLANCE REQUIREMENT 4.3.3.9 Each channel of the Metal Impact Monitoring System shall be demon-strated OPERABI ~ by performance of:

a c

A CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , An ANALOG CHANNEL OPERATIONAL TW, excep for verification o setpoint, at least once per 31 days, and A CHANNEL CALIBRATION at least once per M months.

SHEARON HARRIS - UNIT l.

3/4 3-74

l'

$ 1<

)s iil

,J c

P A

7'5 J

l

IN JUMENT A ( ION RADIOA~iVE LIQUID EFFLUEHi MONITORING INSTRUMENTATION LIHITING CONDITION FOR OPcRATION 3.3.3.10 The radioactive liquid effluent mani wring ins rumentation channels shown in Table 3.3-LZ shall be OPERABI c with their Alarm/Trip Setpoints set to ensure that he limits of Specification 3.E1.1.1 are not exceeded.

The Alarm/

Trip Setpoints of'hese chanrels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSIiE DOSE CALCULATION MANUAL (OOCR).

APPLICABILlTY:. At all times.

ACTlOM:

a0 5.

With a radioac.ive liquid.effluent manitor ing ins rumenta ion channel Alarm/Trip Setpoint less conservative ian required by the above specification, immediately (1) suspend Ne release of radioactive liquid effluents monitored by the affec.ed channel ar (2) declare the channel inoperable and take ACiION as directed by b. below.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLc, take the ACTION sho~n in Table 3.3-U..

Exert best effort to return the ins rument to OPERABLE status within 30 days and, if 'unsuccessful, explain in the next Semiannual Radioac-ive Effluent Release Report pursuant to Specification 6.9.L4 why this inoperability was not corrected in a

imely manner.

The provisions af'pecifics ion 3 m4-Q ~, are not applicable.

1 SURVcILLANCE RcOUIRBIENTS 4.3.'3.~0 Each radioac ive liquid effluent monitoring inst~enmtion channel shall be demonstrated OPERABLc by performance of the CHANHEL CHECK, SOURCE

CHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPGNTIONAL TEST at the re-quencies shown in Table 4.3-8.

SHEARON HARRIS - UNIT I 3/4 3-75

~

~ +'

4 IHSTRUHEHTATIQH RADIOACTIVE GASeOUS EFFLU'EHT HQHITORIHG IH~iUHEHTATIOH LIHITIHG CONDITION FOR OPERATION 3.3.3.11 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Specifications 3.11.2.1 and 3.11.2.5 are no-exceeded.

The Alarm/Trip Setpaints of these channels meeting Specification 3.11.2.1 shall be determined and adjusted in accordance with the methadology and parameters in the DDT.

APPLICABILI7Y:

As shown in Table 3.3-U ACTION:

c With a radioactive gaseous ef'fluen monitoring fnstrumenta ian channel Alarm/Trip Setpoint less conservative than reauired by the above'pecification, immediately (1) suspend the release of radio-active gaseous effluents monitored by the affected channel or (2) declare. the channel inoperable and eke ACTION as direc ed by b.

bel ow.

With the number of OPERABLE radioactive gaseous effluent monitoring instrumentation channels less than the Minimum Channels OPERABI e, take the ACTION shown in Table 3.3-13.

Exert best effort ta return the ins rument to QPERABLE status within 30 days.

If unsuccessful, explain in the next Semiannual Radiaac ive Effluen Release Report pursuant ta Specification 6.9.1.4 why this inoperability was na carrec ed in a timely manner.

The provisions of Specificatia 3.0.3 ws4-4@44 are not applicable.

SURYEIL&iNCE REOUIR&EHi S 4.3.3.L~.

Each radioac ive gaseous effluen manitaring instrument ian channel shall be demons rated OPERABl e by performance of the CHANNEL CHECK, SOURCE

CHECK, CHANNEL CALIBRATION and a DIGITAL CHANNEL OPERATIONAL TEST or an ANALOG QNNHEL OPERATIONAL TEST at the frequencies shown in Table 4.3-9.

SHEARQH HARRIS - UNIT 1 3/4 3-82

REACTOR COOLANT SYST=M 3/4.4.10 STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.4.10 The s ructural integrity of ASME Cade Class 1, 2, and 3 camponen.s shall be maintained in accordance with Specifica ion 4.4.10.

APPLICABILITY: All MODES.

ACTION:

co Mfth the s ruc.ural integrity of any ASME Code Class 1 component(s) not conforming to the above requirements, restate the structural integrity of the affected component(s). w withiw its. limit or isola e

the affected component(s) priar ta increasing the Reactor Coolant System temperature more than 50'F above the minimum temperature required by NDT cansideratians.

Mith the s ruc ural integrity of any ASHE Code Class 2 component(s) nat conforming to he above requirements, restore the struc.ural integrity of the affected component(s) to within its limi or isola e

the affected campanent(s) prior ta increasing the Reactor Coolant Sys em temperature above 200'F.

With the structural integrity of any ASME Code Class 3 camponent(s) not conforming to the above requirements, restore the s ructural integri y of the affected campanent(s) ta wiNin its limit or isolate the affec ed component(s) fram service.

SURVEILLANCE REOUIRBiENTS 4.4.10 In addition ta the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspec.ed per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August ~&75.

SHEARON HARRIS - UNIT 1 3/4 4-43

PLANT SvST iS 3/4 7 9 SEAL D SOURCE COHTAHINATION LIMITIHG CONDITION FOR QP RATION 3.7.9 Each sealed source (excluding startup sources and fission detec.ors previously subjected to core flux) containing radioactive material either in excess of 100 microCuries of beta and/or gamma emitting material or EO micro-Curies of alpha emitting ma erial shall be free of greater than or equal 0.005 microCurie of removable con~ination.

APPLICABILITYr At all times.

ACTION:

b.

Mi h a sealed source having removable contamination in excess of the above limi s, immedia ely withdraw the sealed sour e from use and either:

1.

Decontaminate and repair the sealed

source, or Z.

Dispose of the sealed source in accordance wi"h Commission Regulations.

The provisions of Specification 3.0.3~~ are not applicable.'URVEILLANCE REQUIREMENTS 4.7.9.1 Test Requirements - Each sealed sou.

e shall be tested for leakage andlor contamination by:

P a.

The 11censee, or b.

0 Her persons specifi.cally authorized by the Commission or an Agreemen State; The tes method shall have a detec ion sensi ivity of at leas 0.005 microCurie per test sample.

4.7.9.2 Test Frequencies -

ach category of sealed sour es (excluding startup sources and fission dete~mrs previously subjected to core flux) shall be tested a

the frequency described below.

a.

Sources in use - At least once per 6 months for'll sealed sour es can aining radioactive materials:

II 1.

R P. a hal f-life greater than 30 days (excluding Hydrogerr 3),

and

~

Z.

In any form other than gas.

SHEARON HARRIS - UNiT 1 3/4'-25 '

PLANT SYSTBlS 3/4.7.U AREA T>PERATURE MONITORING LIHITING CONOITION FOR OPERATION 3.7.12 The temperature of'ach area shown in Table 3.7-6 shall not be. exceeded for more than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or by more than 30'F.

~

APPLICABILITY:

Whenever De equipment in an affected area is required to be gf.

A&iOM:

aO With one or more areas exceeding the temperature limi (s) shown in Table 3.7-6 for more than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a

Special Report that provides a record of the cumulative time and the amount by which the temperature in the affected area(s) exceeded the limit(s) arid an analysis to demons rate the con.inued OPERABI of the affec.ed equipment.

The provisions of Specifi-catio

3. 0.3 ~4444 are not applicable..

Mith one or more areas exceeding the temperature limi (s) sho~n in Table 3.7-6 by more than 304F, prepare and submit a Special Repot as required by ACTION a.

above and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either restore the area(s) to within.the temperature limi (s) or declare the equip-ment in the affected area(s) inoperable.

SURYEILLANCc REOUIRBlENTS 4.7.~M The temperature in each of the areas shown in Table 3.7-6 sha11 be determined to be within its limit a 1east once per 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months .

SHEARON HARRIS - UNIT E 3/4 7-2S

ELECTRICAL POMER SYS~c.,S 3/4.8. 4 ELECTRICAL EQUIPMENT PROTE~iVE DEVICES COHTAIHMEHT PEHETRATIOH CONDUCTOR OVERCURREHT PROTFCTIVE DEVICES '-

LIMITIHG CONDITION FOR OPERATION 3.8.4.1 Each containment penetration conductor overcurrent protective device shall be OPERABI ~.

APPLICABILITY:

MOQES 1, 2, 3, and 4.

ACTION:

With one or more of the containment penetration conductor overcurrent protec ive device(s) inoperable:

a.

Restore the protective device(s) to OPERABLE status or deenergize-the circuit(s) by tripping the associated backup circuit breaker or racking out or removing the inoperable circuit breaker within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , declare the affected system or component inoperable, and verify the backup circuit breaker to be tripped or the inoper able circuit breaker racked out or removed at least once per 7 days thereaf ter; b.

t maned; or t

Be in at least HOT STAHDEY within the nex 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD. "

SHUTDSO wi don the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REOQIREMEHTS (p

4.8.4.1 Each containment penetration conductor overcurrent protective devices'.

shall be demons rated OPERABI ~:

a.

At least once per '18 months:

1.

By verifying that, the 6900-volt circuit breakers are OPERABLE by selecting,.

on a rotating basis, at least 10 of.he circuit

breakers, and performing,the following:

1 a}

A CHANNEL CALIBRATION of.the associated protective relay>,

b)

An integrated sys~ functional test which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and control circuits function as designed, and 0

SH~rON HARRIS UNIT 1 3/4 8-19

RErUELING OPERATIONS 3/4. 9.7 CRANE TRAVEL - FUEL HANDLING BUILDING LIHITIHG CONDITION FOR OPERATION 3.9.7 Loads in excess of 2300 pounds shall be prohibited from fuel assemblies in the storage pool.

APPLICABIL~i.. Mith irradiated fuel assemblies in the s orage ACTION:

a.

With the requirements of the above specification no he crane load in a sa e condi ion.

b.

The provisions of Specific;a ion 3.0.3 +ad-B-.f~ are travel over pool.

satisfied, place not app1 i cable.

SURVEILLANCE REOUIRBlEHTS 4.9.7 Crane interlocks and physical stops which prevent crane travel with loads in excess of 2300 pounds over fuel assemblies shall be demonstrated OPERABLE within 7 days prior to,.crane use and at least once per 7 days thereafter during crane.operation.

SHEARON HARRIS - UNIT 1 3/4 9-8

RK."UELIHG OPERATIONS 3/4. 9. 9 CONTAINMKHT VENTILATION ISOLATION SYSTEM LIMITIHG COHOITION FOR OPERATION 3.9.9 The Containment Ventilation Isolation System shall be OPBNBLK..

~

APPLICABILITY: Ouring CORE ALTcRATIONS or movement of irradiated fuel within

-ne conwlnment.

ACiIQN:

Mith the Containment Ventilation Isolation Sys em inoperable, close each of the containment purge makeup and exhaust penetra ions provid-ing direct access from the conMinment aerosphere to the outside a~osphere.

The provisions of Specificatio 3.0.3~~444 are-not applicable; SURVEiLL'ANCE REOUIREMEHTS 4.9.9 The Conwinment Ventilation Isola ion Sys em shall be demonstrated OPERABLE widlin l00 hours prior to the start of and at least once per'7 days during COR ALTERATIONS by verifying that containment, ventilation isolation occurs on a two-out-of-four High Radiation test signal from the containment area radiation monitors (Table 3.3-6, i em l.a) and by verifying that isolation occurs for each valve using its con wl swtch in the main contwl room.

SHKARON HARRIS - UNITl 3/4 9-~D

l~l'I C'lg V

REFUELING OPERATIONS 3/4.9. 11 MATER LEYEL -

NEW ANO SPENT FUEL POOLS LIHITING CONOITION FOR OP RATION 3.9.11 At leas 23 feet. of water shall be maintained over the top of irradiated fuel assemblies seated in the storage racks.

APPLICABILITY: whenever irradiated fuel assemblies are in a pool.

A~iON:

a.

With the requirements of the above specification not satis ied, suspend all movement of fuel, assemblies and crane operations with loads in the affected pool area and restore the wa er level to within its limit wiNin 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b.

The provisions of Specificationp 3.0.3 ~d-8:+A are not app1icable.

SURYEILLANCE REOVIRPlENTS 4.9."~

At least once per 7 days, when irradiated fuel assemblies are in a pool, the water level in hat pool shall be determined to be at least its minimum required depth.

SHEARQN HARRIS - UNIT 1 3/4 9-13

REFUELING OPERATIONS 3/4.9.12 FUEL HANDLIHG BUILDING E4ERGENCY EXHAUST SYS "M

LIMITIHG CONDITION FOR OPERATIO 3.9.12 Two independent Fuel Handling Building Emergency Exhaus System Trains shall be OPERABLE.

APPLICABILITY:

Whenever irradiated fuel is in a storage pool.

ALiION:

a.

Wi.h one Fuel Handling Building Emergency Exhaust System rrain inoperable, fuel movement wi>in-the s.wrage poal or crane aperatioA with loads over the storage pool may proceed provided the OP~ABLE Fuel Hand'Iing Building ~emergency Exhaust Sys em Train is capable of being powered from an OPERABLEr-emergency power source and is in operation and discharging thraugh at. least ane train of HEPA fil ers and charcoal adsorber.

Ci With no Fuel Handling Building Emergency Exhaust Sys em Trains OP RABLE, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool un il at least one Fuel Handling Building Emergency Exhaus-Sys em Train is restored ta QPERABI c status.

The provisions of Specifications 3.0.3 ~3-.hA are no-applicable.

SURVEILLANCE REOUIRBIEHTS 4.9.12 The above required Fuel Handling Bui1ding Emergency Exhaus System trains shall be demonstrated OPHABLE:

ae A

least once pe.

31 days on a STAGGERB) iD BASIS by ini ia ing, fram the control

room, low through the HEPA fil ers and charcoal adsorbers and verifying that the system operates for at lees 10 can inuous hours with the heaters apera ing; At leas once per 18 months or (1) after any s-rucmraI maintenance on the HEPA filter or charcoal adsorbcr

housings, or (2) following significant-painting,,ire, or chemical release in any ven ilation zone carrmrunicating wiN the sys~ by:

Verifying tha the cleanup sys em satisfies the in-place penetra ion and bypass leakage testing acceptance criteria of less than 0.0~~ and uses the tes procedure guidance in Regulatory Positions C.5.a, C.S.c, and C.S.d af Regulatory Guide 1.52, Revision 2, March 1978, and the unit flow rate

- is 6600 cfm a 1~~ during sysm apera-ion when tes ed in

'ccordance with ANSI N510-~280.

SHEAROH HARRIS - UNIT 1 3/4 9-14

(l

RADIOACTIVE EFFLUENTS OOSE LIMiTING CONOITION FOR OPERATION 3.H..1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioac ive materials in liquid effluents released to UNRESTRICTED ARM {see Figure 5.3.-3) shall be limited:

a.

Quring any calendar quarter to less than or equal to 3..5 mrems to the whole body and w less than or equal to 5 mrems to any organ, and P'.

Ouring any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 3.0 mrems to any organ.

APPLICABILITY: At a11 times.

ACTION:

b.

Mith he calculated dose from the release of radioac:ive materials in liquid effluents exceeding any of the above limi.s, prepare and submit to he Commission within 30 days, pursuant to Specification 6.9. 2, a Speci al Report tha: identi fies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed correc ive ac ions to be taken to assure that subsequent releases will be in compliance. wi>

the above limits.

The provisions of Specification 3.0.3 ~~~ are no. applicable.

4 SURVEILLANCE REOUIRBIENTS 4.~~.'. 2 Cumula ive dose contributions from liquid effluents for he current calendar quarter and the current calendar year shall be determined in accordance wi D he methodology and parameters in the OOCM at leas once per 31 days.

SHEARON HARRIS - UNIT 1 3(4 Q-5'

~ 'I

RAOIOACi IVE EFFLUENTS LIOUID RAOMASTE TREATMENT SYSTBf LIMITING CONDITION FOR OP RATION 3 ll.L.3 The Liquid Radwaste Treatment System shall be OPERABLE and apprapriate portions of the sys em shall be used ta reduce releases of radioactivity when the projected dases due ta the liquid effluent, to UHRESTRICTJl AREAS (see Figure 5.1-3) would exceed 0.06 mrem to the whole bady or 0.2 mrem ta any organ in a 33."day period.

APPLICABILITY: At all times.

ACTINO)):

a.

Mith radiaac+ive liquid ~aste being discharged without treatment and in excess of the above limits and any portion af the Liquid Radwas e

Treatment System not in operation, prepare and submi. to the Commis-sion within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:

2.

Explanation af why liquid radwaste was being discharged wi.hout treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability, Action(s) taken to restore the inoperable equipment to OPERABLE

status, and 3.

Summary description of ac ion(s) taken ta prevent a recurrence.

b.

The provisions of Specifica iong 3.0.3 ~44K-are not applicable.

SURVEILLANCE REOUIR RENTS 4.~'.~.3.1 Doses due to liquid releases to UHRESTRICii) AREAS shall be projec=ed a

lees once per 3'i days in accordance with the methodology and parameters in the ODCM when Liquid Radwas e Treatment Sys~

are not being fully utilized.

4."".1.3.2 The insmlled Liquid Radwaste Treatment Sys~ shall be considered OP%ABLE by me ting Specifications 3.~&.1.1 and 3.&~.1.2.

SHEAROH HARRIS - UNIT 1 3/4 11-6

RAOIOACTIYE EFFLUEN i 5 LEOUvD HOLDUP TANKSx LIMITING CONOETION FOR OPERATION 3.1L1.4 The quantity of radioactive ma erial contained in each of the following unprotected outdoor tanks shall be limited to less than or equal to 10 Curies, excluding tri ium and dissolved or entrained noble gases:

a.

Outside temporary tank, excluding demineralizer vessels and liners used to solidi,y or to dewater radioac-ive wasps.

APPLICABILTR:

At all times.

ACTIOX:

a.

b.

kith the quantity of'adioac ive material in any of the above listed tanks exceeding the above limit,,imnedia ely suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Repor,'ursuant to Speci, ication 6.9.'.

The provisions of Specificatio 3.0.3 a~A44 are no applicable.

~L SURVEILLANCE REOUIREM NTS

~ ~

4.".1.4 The quantity of radioac ive materia) confined in each of'he above listed tanks shall be determined to be wi>in the above limit by analyzing a

representative sample of the tank's con~ts within 7 days following any addition of radioac ive material to the ~k.

"Tanks included in this specification are those outdoor tanks tha are not surrounded by liners, dikes, or walls capable of holding the tank contenw and that do not have tank overflows and surrounding area drains connected to the Liquid Radwasa Trea~ Sysm.

3/4 2-7

RAGIOACTIVc i.".""LUENi5 DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.~~.2.2 The air dose due to noble gases released in'gaseous effluents, to areas at and beyond he SITE BOUNDARY (see Figure S.l-3) shall be limited to the following:

a.

During any calendar quarter:

Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radia ion, cUld b.

During any calendar year:

Less than or equal to 10 mrads for gamma..

radiation and less than or equal to 20 mrads for beta radiation.

APPLICABILITY: At all times.

ACTMN lith the calculated air dose from radioac ive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a

Special Report that identifies the cause{s) for exceeding the limit{s) and defines he cor. ective ac ions that have been taken to reduce the releases and the proposed cor rec.ive actions to be taken to assure.Rat subsequent releases will be in compliance with the above limits.

The provisions of Specification 3.0.3 md-i~ are not applicable.

SURVEILLANCE REOUIRBfBCH 4.~&.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at leas once per 3L days.

~

r SHEARQK'HARRIS'- UNIT 1:

'";. 3/4" ZL-.XZ',:

~

P

~

~ ~

~

I l

RADIOACTIVE EFFLUENTS DOSE - IODIN -131.

IODIN=-133 TR<<UM.

AND RADIOACTIVE MAi "RIAL IN PARt CULA > "

ORM.

LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose ta a

MEMBER OF THE PUBLIC fram Iodine-?31, Iodine-~&3, tritium, and all radionuclides in particulate farm with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited ta the fallowing:

a.

During any calendar quarter:

Less than or equal to 7.5 mrems ta any organ and, b.

During any calendar year:

Less than ar equal ta 15 mrems to'ny organ.

APPLICABILITY: At all times.

ACiION:

With the calcula ed dose, from the release of Iodine-13", Iodine"1"3, tritium, and radionuclides in particulate orm with half-lives greater than 8 days, in gaseous ef,luents exceeding any of the abave limits, prepare and submit the the Commission within 30 days, pursuant to Specificatian 6.9.2, a Special Report that identifies the cause(s) ar exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective ac ians ta be taken w assure that subsequent releases will be in compliance with the above limiw.

The provisions af Specification 3.0.3 ~~are nat applicable.-

SURVEILLANC" REOUIRBfENTS 4.~&.2.3 Cumulative dose contributions for the cu~nt.calendar quarter and current calendar year for Iodine-131, Iodine-~D3, tritium and radionuclides in particulate farm with half-lives greater Pan 8 days shall be determined in accordance wi 5 the methodology and parameters in the QDQI a least once per 31 days.

'HEARON'ARRIS' UNIT':

3/4 Q-13'

RADIOACTIVE EFFLUEHTS QASFOUS RAOWAST= TREATMENT SYSicM LIMITIHG CONDITION FOR OPERATION

,3.1'i.2.4 The VEHTILATION EXHAUST.TREATMENT SYSTEM and the GASEOUS RAOWASTE TREATMENT SYSTB1 shall be OPERABLE and apprapriate portions of these sys.ems shall be used ta reduce releases of radioactivi y when the projected doses in 31 days due to gaseous eff1uent releases ta areas at and beyond the SITE BOUN-DARY (see Figure 5.1-3) ~ould exceed:

ao 0.2 mrad ta air fram gamma radiation, or b.

0'.4 mead ta air fram beta radiation, or c.

0.3 mrem ta any organ o

a MBlBER OF THE PUBLIC.

APPLICABILWi: At al I times.

ACiION:

Wi.h radioac ive gaseous waste being discharaed wi hout treatment and in excess of the above limits, prepare and submi ta. the Commission within 30 days, pursuant ta Specifica ion 6.9.2, a

Special Report tha includes the following information:

b.

2.

,3-Identification of any inapei able equipment or subsys~s.,

and the reasan for the inoperability, Action(s) taken to restore the inoperable equipment ta OPERABl ~

status

~ and Suaeary descriptian af ac-ion(s)

+ken ta prevent a recurrence.

provisions af Specif'icatio 3.0.3~6-8 ~ are not applicable.

SURVEILiLANCE REOUIR=MENTS 4-11.2.4.1 Doses due ta gaseaus r'eleases ta areas at and beyond the SITE BOUNDARY shall be prajec~ at least once per 31 days in accordance wi h the methodology and parameters in he QDCM when the GASEOUS RADWASTE TREATMENT SYSTEM is nat being fully u ilized.

-.'-4;11-;2.4.2 The insalled YBPiILATION EXHAUST TREATMEHT SYSTBt and GASEOUS RAOWASTE TRA~ THEHT SYSTEM shall be considered OPERABLE by meeting Specifica-tions 3.1'i.2.1 and 3.11.2.2 or 3.>>.2.3.

SHEAROH HARRIS - UNIT"1 3/4 11-14

RAOIOACi IVE EFFLUENTS XPLOSIVE GAS MIXTURE LIMITIHG COHDITIOH FOR OPERATION 3.~~.2.5 The concen ration of oxygen in the GASEOUS RADWASiE TREATMENT SYST=ii downs ream of the hydroaen recombiners shall be limi ed to less than or equal to 2" by volume whenever the hydragen concentration exceeds 4~ by volume.

APPLICABILITY:

A al 1 imes.

ACTION:

Wi h the concentra ion of oxygen in.he GASEOUS RADWASTE TREATMEHT.

SYSTEM downs

". earn of the hydragen recambiners greater than 2" by volume but less than or equal to 4~ by volume, reduce the axygen concentration to the above limits wi Win 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b.

Wi h the concentration of oxygen in the GASEOUS RADWASTE TREATMENT

. SYSiEM downstream of the hydrogen recombiners greater than 4~ by volume and the hydrogen concentration grea er than-4~ by volume, immediately suspend all addi.ions of waste gases to the system and reduce the concentration of oxygen to less Wan ar equal to 4" by volume, then ake ACTION a.,

above.

c.

The provisions of Specification 3.0.3 ~~~ are not applicable.

SURVEILLANC" REQUIREMENTS 4.~~.2.5 The concentrations of. hydrogen and oxygen in the GASFOUS RADWASir.

TREATM~M'YSTBl shall be determined to be within the above limits by mani mring, at. least once per XZ hours, the waste gases in the GASEOUS RAOWASTE TREATMENT SY~i" with the hydrogen and oxygen monitors required OPERABI= by Table 3.3-D of Specifica-ion 3.3.3.H..

SHBNON HARRIS - UNIT*1'14H.-35'

RADIOACi IYE E;FLUEH i 5 GAS STORAGE TANKS LIMITIHG CONDITION FOR OPERATION 3.11.2.6 The quantity of radioac.ivity con ained in each gas s.orage tank shall be limited to less than or equal to 1.05 x 10s Curies of noble gases (considered as Xe-333 equivalent).

APPLICABILITY: At all times.

A&iOM:

b.

With the quantity of radioac-ive material in any gas storage tank exceeding the above limit, immediawly suspend aTl additions of radioactive material to the tank, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioac ive Effluent Release

Report, pursuant to Specification 6.9. 1.4.

The provisions of Specificationp 3.0.3 end-3-.9-.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.1L2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be wiDin the above limit at least, once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials are being added to the tank.

~ 0 SHEARQH HARRIS - UNITl 3/4 Xl-~B

I

)

U h

(

+71 r-I 4

RADIOACTIVE EFFLUENTS 3/<. 1I. 3 SOLID RADIOACTIVE WAST:5 LIMITING CONDITION FOR OPERATION 3.11.3 Radiaac.ive wastes shall be solidified or dewatered in accordance wi h the PROCESS CONTRQL PROGRAM to meet shipping and ranspar wtion requirements during transit, and disposal site requirements when received at the disposal site.

APPLICAEILITY: At all times.

ACTION:

a.

C.

With SOLIDIFICATION or dewatering nat meeting disposal site and shipping and transpormtion requiremenw, suspend shipmen. of the inadequately processed was es and correct the PROCESS CONTROL PROGRAM, the procedures, and/or the Solid Waste System as necessary ta prevent recurrence.

With SOLIDIFICATION or dewatering not performed in accordance with the PROCESS CONTRQL PROGRAM, test the improperly processed waste in each container to ensure that it meets burial ground and shipping requirements and take appropriate administrative ac ion ta prevent recurrence.

The provisions of Specificatioy 3.0.3 +a4-4Ah4-are not applicable.

SURVEILLANCE REOUIRBfENTS 4.XL3 SOLIDIFICATION of at least ane representative tes specimen.- fram a least every tenth batch of each type of wet radioactive wastes (e.g., filter

sludges, spent resins, evaporator bo toms, boric acid solutions, and sodium sulfate solutions) shall be verified in accordance with the PROCESS CQ~iOL PROGRAM:

If any tes specimen fails to verify SOI EDIFICATION, the SOLIDIFICATION of the bat h under test shall be suspended until such time as additional tes specimens can be abtainecf, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CQtPiROL PROGRAM, and a subsequent tes veri,ies SOLIDIFICATION.

SOLIDIFICATION af the batch may then be resumed using Ne alternative SOLIDIFICATION parameters determined by Ne PROW~

CONTROL PROGRAM; SHEARON HARRIS " UNIT' 3/4 I1-17',

A

'C 1!

RAQIOACT gs i UcN 5 3/4.1'. < TOTAL DOS"-

LIHITING CONDITION FOR OPERATION 3."1.4 The annual (calendar year) dose or dose commitment ta any HB6ER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited ta less than cr equal ta ZS mrems tc the whole body or any organ, except the thyroid, which shall be limited tc less than or equal ta 75 mrems.

APPLICABILITY: A. all times.

ACTION:

a.

With the calculated doses fram the release of radioac ive materials in liquid or gaseous effluents exceeding twice the limits of Speci i-catian 3.U..1.2a.,

3.~D..i Zb., 3.11.2.2a.,

3.~&.Z.Zb., 3.11.2.3a.,

or 3.i&.2.3b.

calculations shall be made including direc" radiation contributions fram the uni w'nd from outside s orage tanks tc deter mine whether the above limits of Specifica-icn 3.~~.4 have been exceeded.

If such is ie case, prepare and submit ta the Commission within 30 days, pursuant tc Specification 6.9.2, a Special Report that defines the corrective ac ion to be taken to reduce subsequent releases ta prevent recurrence of exceeding the above limits and includes the schedule tcr achieving confarmance with the above limits.

This Special

Report, as defined in 10 CFR 20.405(c), shall include an analysis that estimates the radiation exposure (dose) to a MEHBER OF THE PUBLIC fram uranium fuel cycle sources, including all effluen pathways and direct radiation, for the calendar year that includes

. 4e re'lease(s) covered by this repcr I

shall also describe levels of radiaMan and cancentra icns of radioactive ~terial involved, and the cause of the exposure levels or concentrations.

If~s imated dase(s) exceeds the above limia, and if the release candi ion result-ing in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a reques for a variance in acccr dance with the pravisicns of 40 CFR Par UO.

Submittal of he report is considered a timely request, and a variance is granted until staff ac.ion on ie request is complete.

b.

,The provisions of Speci,ica ion 3.0.3 ~3-.6-.4 are not applicable; SURVEILLANCE REOUIRBIENTS

4. ii.4.1 Cumula ive dose, contribu ions from liquid and gaseous effluents shall be determined in accordance wi4 Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the ODCM-0 4.~~.4.2 Curn~lative dose cantributions fram direct radiation from the units and fram radwaste storage tanks shall be determined in accordance w'.th the methodology and parameters in the ODDS.

This requirement is applicable only under conditions set fork in A&i.ON a. of Specification 3.11.4.

SHEARON HARRIS - UNIT 1 3/4 11-~D

t-Cp I

~

fll

RADIOLOGICAL EHY RONMEHTAL MONITORING MONITORING PROGRAM LIMITING CONDITION FOR OPERATION ACTION (Continued)

c kith milk ar fresh leafy vegetation samples unavailable from one or more of the sample lacatians required by Table 3.X2"1, iden ify specific locations for obtaining replacement samples and add'them widrin 30 days w Ne Radiological Environmenml Honi wring Program given in the DDT. 'he specific locations from which samples were unavailable may then be deleted from the mani wring program.

Pursuant ta Specification 6.14, submit in the next Semiannual Radioac-.ive Effluent Release Report documentation for a change in the OOCM including a revised figure(s) and tab3e for the ODCM reflecting he new location(s) with supporting information identifying the cause of the unavailability af samples and justifying the selection of the new loca ion(s) for obtaining samples.

The provisions of Specificatio 3.0.3 a~~ are not applicable.

SURYEILLANCE REOUIRBlEHTS 4.?2;1 The radialogical environmental monitoring samples shall be callected pursuan ta Table 3.IZ-X from the specific locations given in the table and figure(s) in the ODCM, and shall be analyzed pursuant ta the requirements of Table 3.U-l and the detec ion capabili ies required by Table 4.12-'I.

SHEARQN HARRIS - UNIT'*

3/4 32-2

RADIOLOGICAL i'HV~ROHHENTAL HON>TOR~HG 3/4.i~. 2 LAND L'S'E CENSUS LINITIHG CONDITION FOR OPERATION 3.i&.2 A Land Use Census shall be canducted and sha11 identify within a diswnce of 8 km (5 mi1es) De location in each of the 16 meteorological sec ors of the nearest milk animal, the nearest residence, and the nearest garden" af greater than 50 & (500 ft~) praducing broad leaf vegetation.

APPLICABILITY: At all times.

A&iON:

a.

- With a Land Use Census identifying a location(s) that yields a calcuIated dose or dose commitment greater than the values currently being calcula ed in Specifica.ion 4.11.2.3, pursuant ta Specifica-tion 6.9.1.4, identify De new loca ion(s) in De next Semiannual Radioactive Effluent Release Repor.

b.'ith a Land Use Census identifying a loca.-.ion(s) Dat yields a calcu-lated dose or dose commitment (via the same'xposure pathway)

Zt greater than at a loca ian fram which samples are currently being obtained in accordance with Specification 3.12.1, add the new loca-ion(s) within 30 days ta De Radiological Environmental Monitoring Program given in the QDCM.

The sampling lacation(s),

excluding the cantral station-location, having the lowest calculated dose or dose commi went(s), via the same expasure

paDway, may be deleted from

~

. Dis monitoring program after October 31 of De year in which this Land Use Census was canducted.

Pursuant to Specification 6.9.1.4, submit in ie nex Semiannual Radioactive Effluent Release Repart documentation for a change in the ODCN including a revised figure(s) and table(s) far the ODCN reflecting ~Dc new locatian(s) wiD informa-tion supparting the change in sampling. loca ians.

c.

The provisions af Specification 3.0.3 ~~are not applicable.

SURYEILLAHCE REOUIRBIEN i S 4.12.2 The Land Use Census shall be conduced during De growing season at I'eas once per 12 months using that information that will provide the bes

results, such as by a door ~door survey, aerial survey, or by consulting local agricul are auDorities.

The results af the Land Use Census shall bc included in the Annual Radiological Enviranmental Operating Report pursuant to Specification 6.9.1.3.

"Broad leaf vegetation sampl'ing of at least Dree different kinds of vegeta ion may be performed at the SITE BOUNDARY in each of twa different direction sectors wiD the highest predicted D1gs in lieu of the garden census.

Speci-fications for broad leaf vegetation sampling in Table 3.12-1, Part 4-c-, shall

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be followed, including analysis of control 'samples.

SHEARQN HARRIS - UNIT 1 3/4 12-13'

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RADIOLOGICAL ENYIRONM NTAL HONI ORING 3/<.~U.3 INi "RLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.l2.3 Analyses shall be performed on all radioac ive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission, that correspond to samples required by Table 3.l2-l.

APPLICABILITY:'t all times.

ACTION:

a.

With analyses not being performed as required above, report the correc ive ac ions taken to prevent a recurrence o the Commission in the Annual Radiological Environmental Operating Report pursuan to Specification 6.9.1.3.

b.

The provisions of Specificatio 3.0.3 +~AD-are not applicable.

'I SURVEILLANCE REOVIRBIENTS

4. 12.3 The Interlaboratory Comparison Program shall be described in the 00CM.

A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.3.

SHEARQN HARRIS - UNIT X.

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3/4. 0 APPLICABIL~i BASES Aap4~

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The specit'icatians ot'is section provide the general requirements applicable ta each of the Limiting Conditions for Operation and Surveillance Requiremenw within Section 3/4.

In the event of a disagreement between the requirements stated in these Technical Specifications and those stated in an applicable Federal Regulation or Act, the requirements stated in the applicable Federal Regulation or Ac shall take precedence and sha11 be met.

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ces nct directly'provided for in the ACTiON statements and whose occurr c

ul violate the intent of a specifica ion.

For example, 'Specification

.S.Z.

require twc independent ECCS subsys ems ta be QPBABI ~ and provides licit

'CTION re irements if one ECCS subsystem is inoperable.

Under th quiremen ct'pecifica ian 3.0.3, if both the required ECCS subsystems are noperable, Win 1 haur m asures must be initia~ ta place the uni. in least HOT STANDBY within th next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in at. least HOT SHUTD within the fol-lowing 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

As further example, Specit'icatian 3..1 requires two Con-tainment Spray Sys ta be OPERABI ~ and provides icit.AKRON requiremen if one Spray System is i erable.

Under the requ ents of Specifica-tion 3.0.3, if bath the ired Containment Spr Systems are inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months measures must b initiated to p ce the uni in at least HOT STANDBY within the nex" 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , in at le HOT SHlfii)QWH within De fallowing 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in COLD SHUTDOWN wi th uhsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . It fs ac"ep~l ta initiate and complete a reduction 'PTIONAL MODES in a shorter time'nterval than required in the ACTI s

nt and to add the unused portion o

%is allowable ou=of-service ti to th rovided for operation in suhsequen lower OPTATION MODE(S}.

Sta d allowable

-ot-service times are applicable regardless of the OPHATIQ MODE(5) in wh inoperability ig discovered but the times provided t'chieving a mode reduc z

are not applicable if th inoperability is dis ered in a mode lower than ~M licable mode.

For ex-ample if the Ccnta n

Spray Sys~

was discovered ta b

inoperable while in STARTUP, de N Sta~nt would allow up ta ~26 hours to ieve COLD SHUT GQW. If HOT ANDBY is attained in 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months rather than the a owed 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months , 140 hours0.00162 days 0.0389 hours 2.314815e-4 weeks 5.327e-5 months uld still be available before >e plant would be requi to be in CQLQ However, if this sysm was discovered ta be inaperab while i HOT DBY, the 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided to achieve HQT STANDBY would not be a 've De time available ta achieve COLD SHUTDOWN so that the total allowable me

&cpm'~

Cugj'g pecified app qul red systems equipment ecified in.

an must be made with:

(1 ement of or c

an (2) all other parameters as ons for Operation being rd tor SHEARON HARRIS - UNIT 1 B 3/4 0-1,

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IH:"ERT 1

3.0.1 Th!s specificat!on establishes the Applicability statenent within each indiv!dual specification as the requireaent for when (i.e., in which OPERATIONAL NOD"S or other specified conditionsi conioraance to the Liuiting Conditions for Operation is required for safe operation of the facility.

The ACTION requirements establish those reeedial neasures that aust be taxe within soeci!ied tiwe Iicits when the requireaents of a Limiting Condition for Operation are not set.

There are two basic types of ACTIOM requireaents.

The first specifies the reaeoial aeasures that perwit continued operation of the facility which is not further restricted by the tice limits of the ACTION requireaents.

In this case, conforoance to the ACTION requireaents provides an acceptable level of safety for unlieiied continued operation as long as the ACTION requirewents continue to be net.

The second type o! ACTION requireaent specifies a tice licit in which conforoance to the conditions of the Liaiting Condition.'or Operation aust be net.

This tiae liait is the allowable outaoe tioe to restore an inoperable systee or coeoonent to OpiRABL": status or for restoring the paraneters within specified lioits.

If these actions are not completed within the allowable outage tiae lioits, a shutdown is required to place the facility in a NODE or condition in which the specification no longer applies.

It is not intended tnat the shutdown portion of the ACTIOH requireoents be used as an operational convenience which peroits reaoval of a redundant systea<s) or coeponent(s)

!ron service.

The specified tine Iiaits of the ACT1OM requireoents are applirable iron the point in tine it is identified that a Liriting Condition !or Operation is not aet.

The tiae lirits of the ACTIOH requiresents are also applicable when a systeu or cooponent is reaoved froa service for surveillance testing or investigation of operational problens.

Individual specifications nay include a specified tice Iioit for the coopietion of a Surveillance Requireaent when equipoent is reooved froa servire.

In this case, the allowable outage tine Iioiis of the ACTION requireaents are applicable when this liait expires if the surveillance has not been coopieted.

Mhen a shutdown is required to coaply with ACTION requireaents, the plant nay have entered a

MODE in which a new specification becooes applicable.

In this case, the tine liuits o! the ACTION requirenents would apply froa the point in tiae that the new specification becoaes applicable if the requirenents o! the Lioiting Condition for Operation are not aet.

INS'.PT 2

3.0.2 This specification establishes that nonconpliance with a specification exists when the requirenents of the iiaiting Conditions for Operation are not net and the associated ACTIOM requirenents have not been inpleaented within the specified tine interval.

The purpose of this specification is to clarify that tll iaplenentation of the ACT1OM requirenents within the specified tine interval constitutes conpliance with a specification and

<2) coapletion of the reaedi al aeasures of the ACTTOM requirenents is not required when conpliance with a Liniting Condition of Operation is restored within the tine interval spe ified in the associated ACT10M requirenents.

INSERT 3 3 0.3 This soeci! ication establishes the shutoown ACTION requireaents triat aust be iapleaented when a

Liaiting Condition for Operation is not net and the condition is not speci!ically adcresseo by the associated ACTIGH reouireaents.

The purpose)f oi this specification is to delineate the tiae liaits for placing the unit in a safe shutdown NODE when plant operation cannot be aaintained within the liaits ior safe operation de!i ned by the Liaiiing Conditions for Operation and its ACT)OH requireaents, It is not intended that the shutdown portion of the RCTIOH requireaents be used as an operational convenience which oeraits reaoval of a redundant systea(s) or cocponent(s)

!roa service.

Gne hour is allo~ed to prepare ior an oroerly shutdown before initiating a cnange in plant operation.

This tiae peraits the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability o! the electrical grid.

The tine liaits speci!ied to reach lo~er NODES of operation perait the shutdown to proceed in a controlled and orderly aanner that is well within the specified aaxiaua cocldown rate and within the cooldown capabilities of thE'aci)ity assuaing only the ainiaua required equipaent is OPERABLE.

This reduces theraa) stresses on corponents of the priaary coolant systen ano the potential ior a plant upset that could challenge safety systeas under conditions for which this speci!ication applies.

li reaedial aeasures peraitting liaited continued operation of the facility under the provisions of the ACT)OH requireaents are cocpleted, the shutdown nay be terainated.

The tiae liaits oi the ACT)OH requireaents are applicable froa the point in tice there was a failure to neet a Liaiting Condition for Operation.

There!ore, the shutdown aay be terainated ii the ACT)OH requireaents have been aet or the tine liaits o! the ACT)OH requireaents have not expired, thus providing an allowance for the coapletion cf the required actions.

The tiae liaits o! Specification 3.0.3 a!low 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months for the plant to be in the CDLD SHUTDGHH NDE when a shutdown is reouirec during the PDi(EP. NDE o! operation.

If the plant is in a lower NDDE of operation when a shutdown is reouired, the tiae liait ior reaching the next lower NODE of operation applies.

However, if a lower NDE of operation is reached in !ess tiae than allowed, the total a!Iowable tiae to reach COLD SHUTDQI(H, or other appiicab)e NODE, is not reduced.

ior exaaple, if HDT STAHDBy is reached in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , the tice allowed to reach HOT SHUTDOHH is the next I) hours because the total tiae to reach HOT SHUTGDHH is not reduced froa the allowable liait of 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months .

Therefore, if reaedia) aeasures are coapleted that would perait a return to PGViER operation, a penalty is not incurred by having to reach a lo~er NODE of operation in less than the total tiae allowed.

The saae principle applies with reoard to the allowable outage tine liaits of the ACTIOH recuireaents, if coapliance with the ACT)OH requireaents ior one specification resu!ts in entry into a NODE or condition of cperation ior another specification in which the requireaents of the Liaiiing Ccncition ior Operation are not aet.

Ii the new specification becoaes applicable in less tine than speciiied, the oiiierence aay be aoded to the allowable outaoe tine !iaits of the seccnd speciiication.

Ho~ever, the allowable outage tine liaits of ACT)OH requireaents ior a hioher NDD. of operation aay not be used to extend the allowable outage tiae that is applicable when a Liaitinc Condition ior Operation is not aet in a lower NDCE of operation.

The shutdown requireaents o! Speciiication 3,0.3 do not apply in NODES 5 and 6 because the ACTION requirenents oi indi vidual specifications deiine the reaedial aeasures to be taken.

a ~ 0.4 This specification estab!isnes Iioitations on HOD: changes when a Liaiting Condition for Goeration is not net.

It precluoes placing the facility in a higher HOD:" of operation when the requireeents for a Liaiting Condition for Operation are not aet and continued noncoapliance to these conditions would result in a shutdown to conply >>ith the ACTION requireaents if a chanoe in HDDES were peraitted.

The purpose of this specification is to ensure tnat facility operation is not initiated or that hioher HOi.S of operation are not entered

>>hen corrective action is being taVen to obtain coapliance >>ith a specification by restoring equipaent to OpiRADL.."status or paraoeters to specified linits.

Coop!lance >>ith ACT!OH requireaents that perait continued operation of the facility for an unliaited period of tine provides an acceptable level of safety'for continued operation without reoard to the status of the plant before or after a

HOD." change.

Therefore, in this case, entry into an QiiRATIOHAL HODE or other specified condition nay be nade in accordance with the provisions of tne ACTIDH requireoents.

The provisions of this specification should not, ho>>ever, be interpreted as endorsing the failure to exercise good practice in restoring systens or conponents to OPERA"LE status before plant startup.

linen a shutdown is required to co..ply >>ith ACTION requireaents, the provisions of Specification 3.0,4 do not app!y because they >>ould delay placing the facility in a lo~er HOD. of operation.

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'I APPLICABILm BASES

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ated wi ~

quired equipment or sys~

inoperable or othe led limits being exceede Exceptions to this provfsfon have b

ol a Iimited number of speci-fications when star

'rable equipment wou ec plant saf ety.

ihese ex re stated in the A~iON statements of the apprapr P~p l~e~

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nsure

'ng Conditions far Operation are met and will be

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ed dur-ng the OPERATIONA r ather canditions for which sting Conditions or Operation are applicable.

ons for a al surveillance actfvftfe be performed without regard ta th OPERATIONAL HODES or other ondi dans are provided in

>dual Surveil a

ufremenw. Surveil-ance Requir'emen pecial Test Exceptions need o'nly be rmed when the pecial ception is being utilized as an exception to an fndr erfo 'urveillance ac ivitics beyond those specified in lc nomin

~ eillancc i

'1.

These tolerances are necessary ta pravide o

ionaI lexibility because scheduling and performance cansider s.

The phrase at least4 associated wft urvefllance t'requcncy not negate this allow-le tolerance value and permits er,o more frequent surveillance ctivities.

e tolerance values, m

er vndivfdually o.

ecutively over three s

intervals ficiently res rfctivc '~ ensure liabili y soci th the surveillance acti vi y is not significantly degra ond Z'~e$ 7 inat f compliance with the OPERABILITY requirements of the Limitf n- '

ions for tion.

Under these criteria, equipment;-

sys em components re assumed to be I l: ft'he associated surveiIIanc svftfes have been atfs acmrily performed w 'he speci. fied ti rval.

Nothing in this rovision is to be construed as 'ng, systems or components OP~'t LK when such fleas are found or inaperable al ~ugh still mee in

~he Surveillance Requireme may be c

ed inoperable during use, urfng surveillance, or fn accardanca with this ica ion.

Therefo CTION sta are entered when the Surveillance Requf remen auld have een rmcd rather than at the time it is discavered-that the tcs no p~~(~~

<Wez+ P, ith.a Lfmi n for Operation have been performed wf ecifie me fntcrval prfor to entry c

TIONAL HQ cr applicable mon-ition.

The intent af this pravisio survefllanca activitfcs ve been sati s rated on a cu~nt basis as ta meet SHEARON HARRIS - UNIT 1 a 3/W 0-4

lH5ERT 5 4,0, 1 This speci:ication establishes the reo ireaent that survei llances aust be perforned during tne OPERATIOHAL HOOFS or other conoitions for which the requireeents of the Linitino Conditions for Operation apply unless otherwise stated in an individual Surveillan e Reouirenent.

The purpose of this specification is to ensure that surveillances are perforaed to verify the operational status o

systeas and conponents and that paraneters are within specified lioits to ensure safe operation of the facility when the plant is in a

NOOE or other specified condition for which the associated Liniting Conditions for Operation are applicable.

Surveillance Reouireaents do not have to be perforaed when the facility is in an OPERATIOHAL NODE for which the requirenents of ihe associated Liniting Condition for Operation do not apply unless otherwise specified.

The 5urveillance Requireeents associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to tne requireaenis of a specification.

4.0.2 This speci..'!cation establ!snes the conditions unoer which the specified tine interval for Surveillance Requireaents say be extended.

Iten a. peraits an allowable extension of the noraal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that nay not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or naintenance activities.

Iten b. Iioiis the use of the provisions of itea a. to ensure that it is not used repeatedly to extend the surveillance interval beyond that specified.

The liaits of Specification 4 ~ 0.2 are based on engineering judoaent and the recoonition that the nost probable result of any particular surveillance being perforaed is the verification of conforoance with the Surveillance Requireaents.

These provisions are sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraoed beyond that obtained fron the specified surveillance interval.

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INSERT 7 4.0 ~ 3 This specification establishes the failure to perform a Surveillance Reouirement within the allowed surveillance interval, defined by the provisions of Specification 4.0,2, as a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.

Under the provisions of this specification, systems and components are assumed to be OPERABLE wnen Surveillance Requirements have been satisfactorily performed within the specified time interval.

However, nothing in this provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the Survei)lance Requirements.

This specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completed witnin the allo~ed surveillance interva) and that the tice linits of the ACTIOH requirenents apply from the point in time it is ioentified that a

surveillance has not been performed and not at the time that the allowed s rveillance interval was exceeded.

Completion of the Surveillance Requirement within the allo~able outage time limits of the ACTIOH requirements restores compliance with the requirements of Specification 4.0.3.

Ho~ever, this does not negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0',

was a violation of tne OPERABILITY requirements of a Limitino Condition for Operation that is subject to enforcement

action, Further, the failure to perform a surveillance within the provisions of Specification 4.0,2 is a violation of a Technical Specification requirement and is, therefore, a reportable event under the requirements of 10 CFR 50,73(a)(2)(i) (B) because it is a condition prohibited by the plant's Technical Speci fi cati ons.

lf the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or a shutdown is required to comply <<ith ACTION requirements, e.o ~, Specification 3.0.3, a 24-hour allo~ance is provided to permit a delay in implementino the ACTIOH requirements.

This provides an adequate time limit to complete Surveillance Requirements that have not been performed.

The purpose of this allowance is to permit the completion of,a surveillance before a shutdown is required to comply with ACTION requirements or before other remedial measures

~ould be required that may prec)ude completion of a surve111ance, The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, and the safety sionificance of the oelay in completing the required surveillance.

This provision a?so provides a

time limit for the completion of Surveillance Requirements that become applicable as a consequence of NODE changes imposed by ACTION requirements and for completing Surveillance Reouirements that are applicable

<<hen an exception to the requirements of Specification 4.0,4 is allowed, If a surveillance is not completed within the 24-hour allowance, the tine limits o! the ACTiON requirements are applicable at that time.

@hen a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not m'et, the time limits of the ACTION requiremen+a are applicable at the time that"the surveillance is terminated.

Surveillance Req irements do not have to be performed on inoperable equipment because the ACTION requirements define the remedial measures that apply.

However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status,

1HSEPT 6

4.0.4 This specification establishes the requireaent that a!) applicable surveillances rust be net before entry into an OPERATIOHAL NODE or other condition of operation specified in the Applicability stateaent.

The purpose of this specification is to ensure that systen and corponent O.ERA91L1TY requirenents or paraneter lirits are aet before entry into a NODE or condition for uhich these systens and conponents ensure safe operation of the facility.

This provision applies to chanoes in OPERATTOHAL NODES or other specified conditions associated uith plant shutdoun as mell as startup, Under the provisions of this specification, the applicable Surveillance Requireaents aust be perforaed uithin the specified surveillance interval to ensure that the Liniting Conditions for Operation are net during initial plant startup or following a plant outage.

Mhen a shutdown is required to coaply uith ACTIOH requireaents, the provisions of Specification 4.0.4 do not apply because this uould delay placing the facility in a loner NODE of operation.

BASES r following exten e

ust be performed w

a 1 icabl 1

an zvities to lacing or d 3 components and inservica ~sting of ASME Code Class 1, 2 and 3 pumps nd,v ves will be performed in.ac"ordance with a periodically updated ver on f Sec.

XI of the ASHE Boiler and Pressure Vessel Code and Addenda require y 10 CFR 55a.

Relief from any of'he above requirements has be provided in writing by e Commission and is not a part of these Technica pecifications is specification ludes a clarification of the frequen es for performing.,

e inservice inspec io and testing ac.ivities require Sec ion XI of the HE Boiler and Pressure sel Code and applicable denda.

This'larification is provided to ensure~consist cy in surveillanc ntervals throughout these echnical Specifications and to ve any ities relative to the frequen-,

ies for performing the required in rvice 'pection and tes ing activities.

nder the terms of this specificatio

, th re restrictive requirements of the echnical Specifications take p dence ove e ASME Boiler and Pressure Ves-el Code and, applicable Adden For example, requirements of Specifica-io'n 4.0.4 to perform surv lance activities prior entry into an OPERATIONA DE or other specifi plicability condition takes p

adence over the ASHE oiler and Pressure essel Code provision which allows p ta.be tested up ~

week after re to normal operation.

And for example, the echnical Speci-ication def tion of OPERABLE does not grant a grace period be a device capable of performing iw specified function is declared 'perable d

s precedence over the ASHE Boiler and Pressure Vessel Code prov>

n h'llows a valve to be incapable of performing its specified function SHEARQH HARRIS UNIT 1 B 3/4 0-3

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IhS":RT 0 4,0.5 Tnis specification establishes the requireaent that inservice inspection of ASIDE Code Class l, 2,

and 3 coaponents and inservice testino of ASIfE Cone Class l, 2, and 3 pueps and valves shall be perforeed in accordance uith a periodically updated version of Section XI of the ASIDE Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a.

Tnese requireaents apply except

<<hen relief has been provided in cwriting by the Connission.

This specification includes a clarification of the frequencies for perforeing the inservice inspection and testino activities required by Section Xl of the ASHE Boiler and Pressure Vessel Code and applicable Adoenda.

This clarification is provided to ensure consistency in surveillance intervals throuohout the Technical Specifications and to reeove any aabiguities relative to the frequencies for perfuming the required inservice inspection and testing activities.

Under the terns of this specification, the nore restrictive requireaents of the Technical Specifications take precedence over the ASIDE Boiler and Pressure Vessel Code and applicable Addenda.

The requireeents of Specification 4.0.4 to perforo surveillance activities before entry into an OPERAT1OMAL llGDE or other specified condition takes precedence over the ASRE Boiler and Pressure Vessel Code provision arhich al)ops puaps and valves to be tested up to one week after return to noraal operation.

The Technical Specification definition of OPERABLE ooes not allou a grace period before a

coaponent, that is not capable'of, performing its speci fied functi on, is declared inoperable and takes precedence over the ASIfE Boiler and Pressure Vessel Code provision uhich allows a valve to be incapable of perforning its specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable.

ML18005A211

Text

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