Text

Proposed Tech Specs Reflecting Administrative Corrections
	ML18005A243
Person / Time
Site:	Harris
Issue date:	12/17/1987
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML18005A242	List: ML18005A241; ML18005A243;
References
	NUDOCS 8712230280
	Download: ML18005A243 (27)
	v • d • e

5 4

TNDEX

. LIMITING CONDITIONS FOR OPERATION ANO SURVEILLANCE REOUIREMENTS TABLE TABLE 3.3"1 RcACTOR TRIP SYSTEM INSTRUMENTATION (DE5 ETC' A 2 Q

v V

EECTIDN 3/4 2 POWcR DISTRIBUTION LIMITS 3/4. 2. 1 AXIAL FLUX DIFFERENCE...

FIGURE 3.2"1 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER...

3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR " FQ(Z)

FIGURE 3.2-2 K(Z) -

LOCAL AXIAL PENALTY FUNCTION FOR F (Z)....

3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL ACTOR o

~

~ ~ ~ ~ ~

~

~ ~

~

~ o ~ ~

~

~ ~ o

~

F 3/4.2.4 QUADRANT POWER TILT RATIO..........

3/4. 2. 5 DNB PARAMETERS 3/4.

INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION.

PAGE 3/4 2-1 3/4 2-4 3/4 2-5 3/4 2"8 3/4 2-9 3/4 2-11 3/4 2"14 3/4 3-1 3/4 3-2.

3/4 3-9 TABLE 3/4.3.

4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 2

ENGINEERED SAFE FEATURES ACTUATION SYSTEM INSTRUMENTATION..

3/4 3"ll 3/4 3-16 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.

3/4 3-18 TABLE TABLE TABLE 3/4.3.

3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS (oc~e~~c 3

-5 I

Ih V V

~ u aJ

~

1 a

I 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM

. INSTRUMENTATION SURVEILLANCE REQUIRcMENTS 3

MONITORING INSTRUMENTATION'adiation Monitoring For Pjant Operations.....

3/4 3-28 3/4 3-37 3/4 3-41 3/4 3"50 PDR ADOCN, 05000400I V

SHEARON HARRIS - UNIT "-

'I 4 I

i+

INDEX LIMITING CONDITIONS FOR OPERATION AND SURV ILLANCE REQUIREMENTS 3/4 4 10 STRUCTURAL INTEGRITY 3/4.4. 11 'EACTOR COOLANT SYSTEM VENTS 3/4. 5 EMERGENCY CORE COOLING SYSTEMS

~

~ ~ ~

~

~ ~

SECTION 3/4.4. 9 PRESSURE/TEMPERATURE LIMITS Reactor Coolant System.............

~

~ ~

~

FIGURE 3.4"2 REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS-APPLICABLE UP TO 4 EFPY FIGURE 3.4"3 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS" APPLICABLE UP TO 4 EFPY...:.............

fbca.eve)

T BLE 4.4-5

~ ~ ~

~

~ ~

~

~ ~ ~

~ ~

~

~ ~

~

~ ~

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~ 1

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TABLE 4.4"6 MAXIMUM HEATUP AND COOLDOWN RATES FOR MODES 4, 5

AND 6 (WITH REACTOR VESSEL HEAD ON).............-........

Pressurizer...........

Overpressure Protection Systems FIGURE 3.4-4 MAXIMUM ALLOWED PORV SETPOINT FOR THE LOW TEMPERATURE OVERPRESSURE SYSTEM.

PAGE 3/4 4-33 3/4 4-35 3/4 4-36 3/4 4-37 3/4 4-38 3/4 4-39 3/4 4-40 3/4 4-41 3/4 4-43 3/4 4"44 3/4. 5. 1 3/4.5. 2 3/4. 5. 3 3/4. 5. 4 ACCUMULATORS.

ECCS SUBSYSTEMS - T GREATER THAN OR avg ECCS SUBSYSTEMS " T LESS THAN 350 F

avg REFUELING WATER STORAGE TANK...

EQUAL TO 350 F....

3/4 5-1

~ 3/4 5-3 3/4 5-7 3/4 5-9 SHEARON HARRIS " UNIT 1 viii

INOEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION 3/4.6 CONTAINMENT SYSTEMS 3/4. 6. 1 PRIMARY CONTAINHENT PAGE 3/4. 6. 2 Containment Integrity Containment Leakage......................

Containment Air Locks...

Internal Pressure.........

A)r Temperature..........

Containment Vessel Structural Integrity..................

Containment Ventilation System..;.........

DEPRESSURIZATION AND COOLING SYSTEMS 3/4 6-1 3/4 6-2 3/4 6"4 3/4 6-6 3/4 6-7 3/4 6"8 3/4 6-9 Containment Spray System...

Spray Additive System...

Containment Cooling System..

3/4. 6. 3, CONTAINMENT ISOL'ATION VALVES............. -.

TABLE 3.6-1 (i -.+~O) 3/4. 6. 4 COMBUSTIBLE GAS CONTROL Hydrogen Monitors Electric Hydrogen Recombiners VACUUM RELIEF SYSTEM.

3/4.6.5 3/4.7 PLANT SYSTEMS 3/4.7. 1 TURB>Nc CYCLE Safety Valves......

TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINL SAFETY VALVES DURING 3/4 6-11 3/4 6"12 3/4 6-13 3/4 6-14 3/4 6"16 3/4 6"30 3/4 6-31 3/4 6-32 3/4 7"1 3

LOOP OPERATION.

TABLE 3.7-2 STEAM LINE SAFc~l VALVES PER LOOP Auxiliary Feedwater System...

'Condensate Storage Tank...............

Specific Ac ivity

~ ~

~

3/4 7-2 3/4 7-3 3/4 7-4 3/4 7-6 3/4 7-7 TABLE 4.7"1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM.

3/4 7-8 Hain Steam Line Isolation Valves 3/4 7-9 SHEARON HARRIS - UNIT 1 ix

~ ~

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEiLLANCE REQUIREMENTS TABLE 3.7"6 AREA TEMPERATURE MONITORING.....

3/4.7.13 ESSENTIAL SERVICiS CHILLED WATER SYSTiM; 3/4 8

ELECTRICAL POW R SvST~MS 3/4.8.1 A.C.

SOURCES

~

~ 0 ~ ~ ~ ~ ~ ~

SECTION 3/4. 7. 2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION..........

3/4.7.3 COMPONENT COOLING WATER SYSTEM...........................

'/4.7.4 EMERGENCY SERVICE WATER SYSTEM.

3/4.7.5 ULTIMATE HEAT SINK...........

3/4..7.6 CONTROL ROOM EMERGENCY FILTRATION SYSTEM.......-...'.....

/4 7 7 REACTOR AUXILIARYBUILDING (RAB) EMERGENCY EXHAUST S YSTEMo ~

~

~ ~

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3/4.7. 8 SNUBBERS (DE<~CCO)

FIGURE 4. 7"1

/4 7 9 S

ALED SOURCE CONTAMINATION 3/4..7 ~ 10 (DELETED)...

TABLE 3.7-3 (DELETED)..

TABLE 3.7-4 (DELETED)..

TABLE 3. 7-5 (DELETiD)....................

~ - - -.... -.

3/4. 7. 11 (DELETFD).......

3/4.7.12 AREA TEMPERATURE MONITORING.....;.......

PAGE 3/4 7-10 3/4 7-11 3/4 7-12 3/4 7-13 3/4 7"14 3/4 7-17 3/4 7-19 3/4 7-24 3/4 7-25 3/4 7"27 3/4 7-27 3/4 7-27.

3/4 7-27 3/4 7-27 3/4 7-28 3/4 7-29 3/4 7-30 Operating.

TABLE 4.8-1 DIESiL GENiRATOR TEST SCHEDULi Shutdown..

3/4.8.2 D.C.

SOURCES 3/4 8-1 3/4 8-10

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~ s'/4 8 11 0 er t+

pe cxtl ng o

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TABLE 4. 8-2 BATTERY SURVEILLANCE Ri(UIREME Shutdown....

3/4. 8. 3 ONSITE POWER DISTRIBUTION 3/4 8-12 3/4 8-14 3/4 8-15 Opera ing.

Shutdown.

~

3/4 8-16 3/4 8-18 SHEARON HARRIS " UNIT 1

IND X LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMrNTS SANCTION 3/4.8.4 ELECTRICAL E(UIPMENT PROTECTIVE DEVICES Containment Penetration Conductor Overcurrent Protective Devices......

C bE(E'-rGb)

TABLE 3.8-1 PAGE 3/4 8-19 Motor Operated Valves Thermal Overload Protection......

( DC~-,m )

TABLE 3.8-2 3/4. 9 REFUELING OPERATIONS 3/4 3/4 3/4 8-'21 8-39 8"40

/4.9.1 BORON CONCENTRATION 3/4 9-1 3/4. 9. 3 3/4. 9. 4 3/4. 9. 3 3/4. 9. 6 3/4. 9. 7 3/4. 9. 8 DECAY TIME

~

CONTAINMENT BUILDING PENETRATIONS........................

COMMUNICATIONS..............

REFUELING MACHINE CRANE TRAViL - FUEL HANDLING BUILDING.

RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Level....

Low Water Level.

3/4;9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM 3/4.9.10 WATiR LiViL-REACTOR VESSEL 3/4.9.11 WATiR LEVEL -

NEW AND SPENT FUEL POOLS......-.

~.

3/4. 9. 12 FUEL HANDLING BUILDING EMERGENCY EXHAUST SYSTEM.

TABLE 4.9-1 ADMINISTRATIVE CONTROLS TO PREVENT DILUTION DURING REFUEI ING 3/4 9 2 INSTRUMENTATION 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 0

9"3 9-4 9-5 9-6 9-7 0

9 9-10 0 l1 C

c 13 9-14 3/4. 10 SPECIAL TEST EXCEPTIONS 3/4. 10. 1 SHUTDOWN MARGIN.

3/4 10 2 GROUP HEIGHT INSERTION AND POWiR DISTRIBUTION 3/4. 10. 3 PHYSICS TESTS 3/4.10.4 REACTOR COOLANT LOOPS...

3/4.10. 5 POSITION INDICATION SYSTEM " SHUTDOWN...........

LIMITS...

3/4 3/4 3/4 3/4 3/4 10-1 10" 2 10" 3 10-4 10" 5 SHEARON HARRIS " UNIT 1 Xi

TABLE 2.2-1 Continued TAOLE HOTATIOHS IIOTE 1:

OVERTEHPERATURE 4T (1 t x S)

I (1

+ t S) 1 r)T (~S) (~)

< rrT (Kr - Kr (~ r ~S)

T (~T~

)-

K3{P - P') - fg{41))

Where:

4T Measured 4T by RTD Hani fold Instrumentation;

~lrr S

1

+ x2S ZI T T2 Lead-lag compensator on measured 4T; Time constants utilized in lead-lag compensator for 4T, x> = 8 s, zz

= 3 5>

1+

zq 4T K)

Lag compensator on measured 4T; Time constants utilized in the lag compensator for 4T,.xa

= 0 s; I

Indicated 4T at RATED TllERHAL POMER; 1.09; 0.0102/ I';

~1+r S

1 i ~sS.

I + teS The function generated by the lead-lag compensator for Tavg dynamic compensation; Time constants utilized in the lead-lag compensator for T t~

20 s, ts

4 s; Average temperature,

'F; Lag compensator on measured T ;

Time constant utilized in the measured T

lag compensator, ts

= 0 s; avg

C7an

/ h i ~ Vert lc

( 5 de lePeH Ewe.~

I erbn'ca f 5~ pc r +~'<cg+~~ ~

7Ac

~.~ /mal~+- n:n 4h's v'cadre i 0 r o.~Pion/ca'~pre.g P<uc~cl>ie F a P-rag qecg~n'ca / ~prig 7g r '~

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pc P<opY SHiARON HARRiS - UNiT 1 3/4 3-9 and 3-~0

PFSPgA/$

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Pr'OC&~rC PCS 106 7 Whn.'CO/ S~PCr'Pu AC~ Qg~yr'.~~y g 'S.+

8r'der vW.

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SHEARON HARRIS - UNIT 1 3/4 3"37 through 3-40

J I'

INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels sho~n in Table 3.3-10 shall be OPERABLE.

APPI ICABILITY:

MODES 1, 2, and 3.

ACTION:

a.

lA'th the number of OPERABLE accident monitoring instrumentation channels less than the Total Required Number of Channels shown in Table 3.3-10, except for the pressurizer safety valve position indicator or the sub-cooling margin monitor, restore the inoperable channel(s) to OPERABLE status within 7 days, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; or b.

C.

<he aeX+

With the number of OPERABLE accident monitoring instrumentation

channels, except the radiation monitors, the pressurizer safety valve position indicator, or the sub"cooling margin monitor, less than the Minimum Channels OPERABLE requirements of Table 3.3"10, restore the inoperable channel(s) to OPERABLE s atus within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; or With he number of OPERABLE channels for the radiation monitors, the pressurizer safety valve position indicator", or the sub-'ooling mar gin monitor8, less than required by the Minimum Channels OPERABLE requirements, initia e the preplanned alternate method of monitoring the appropriate parameter(s),

within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , ancf.either res.ore the inoperable channel(s) to OPERABI ~ sta us within 7 days or prepare and submi a Special RepoW to the Commission, pursuant to Specification 6.9.2, wi~lanr14 days~ that provides actions taken, cause of he inop-erabili y, and the plans and schedule for restoring the channels to OPERA"-LE s.atus.

The provisions of Specifica ion 3.0.4 are not applicable.

" The al ernate method shall be a check of safe.y valve piping temperatures and evaluation to Cetemine pos-t ion.

0 The alternate me.hod shall be the initiation of the backup method as reouired by Specificat;on 6.8.4.cf.

SHEARON HARRIS - UNIT 1 3/4 3-66

lA m

C3 TADLE 4.3-8 RADIOACTIVE LI UID EFFLUEHT HOtlITORIHG ItlSTRUHEttTATIOH SURVEILLANCE RE UIREHEHTS INST RUHEHT I

1:

Radio ctiity Monitors Providing Alarm and hu c Termination of Release a.

Liquid Radwaste Effluent Ljnes ClthtlHEL CllECK DIGITAL CllhtlNEL SOURCE OPERATIONAL CIIECK TEST ta>

I LD O

1)

Treated Laundry and llot Sl>ower Tanks. Discharge Honi tor.

2)

Waste Honil.or Tanks and

Maste Evaporator Condensate Tanks Discharge tkonitor C

3)

. Secondary Maste Sample Tank

, Dischar e Honitor g

b.

Turbine Building Floor Drains Effluent Line c.

Outdopr Tank brea Drain Transfer Pump Honitor 2.

Radioactivity Honi tors Providing Alarm But Not Providing Automatic Termination of Release a.

tlormal Service Water System Return From the Waste Processing Building to the Circulating Mater System P, H(5)

H R(3)

R(3)

Q(1)

Q(1) 0(1)

Q(1)

Q(Z)

~

I ~

REACTOR COOLANT SYSTEM HOT SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.1.3 At leas.

two of the loops listed below shall be OPERABLE and at least one of these loops shall be in operation:"

a.

Reactor Coolant Loop A and 'its associated steam generator and reactor coolant pump,""

b:

Reactor Coolant Loop B and its associated steam generator and reactor coolant pump,""

c.

Reactor Coolant Loop C and its associated steam generator and reactor coolant pump,""

d.

RHR Loop A

, or e.

RHR Loop APPLICABILITY:

MODE 4.

ACTION:

a.

With less than the above required loops OPERABLE, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible; if the remaining OPERABLE loop is an RHR

loop, be in COLD SHUTDOWN within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

With no loop in operation, suspend all operations involving a r educ-tion in boron concentration of the Reactor Coolant System and immediately ini iate correc ive action to return the required loop to operation.

~."All reactor coolant pumps and RHR pumps may be deenergized for up to

~ hour provided:

(1) no operations ar'e permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature

.is maintained at least 10 F below saturation temperature.

""A reactor coolant pump shall not be started with one or more of the Reactor Coolant Sys.em cold leg temperatures less than or equal to,335'F unless the secondary water temperature ofeach steam generator is less than 50'F above each of the Reactor Coolant Sys em cold leg temperatures.

SHFARQN HARRIS - UNIT I 3/4 4-4

REACTOR COOLANT SYSTEH STEAM GENERATOR SURVEILLANCE REOUIREHENTS Continued 4.4.5.4 Acceo ance Criteria (Continued b.

The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through"wall cracks) required by Tables 4.4-ZA and B.

4.4.5.5 a.

b.

c Spec.

6.9.2 Renorts Within 15 days following the completion of each inservice inspection of steam generator

tubes, the number of tubes plugged in each steam generator shall be reported to the Commission in a Special Report pursuant to Specification 6.9.2; The complete results of the steam generator tube inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection.

This Special Report shall include:

1.

Number and extent of tubes inspected, 2.

Location and percent of wall-thickness penetration for each indication of an imperfection, and 3.

Identification of tubes plugged.'esults of steam generator tube inspections which, fall into Category C"3 shall be reported in a Special Report within 30 days and prior to resumption of plant~

operation.

This report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

SHEARON HARRIS - UNIT 1 3/4 4-17

REACTOR COOLANT SYS t &

REACTOR COOLANT SYSTEH LIMITING CONDITION FOR OPERATION 3.4.9.2 The Reactor Coolant System (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figures 3.4-2 and 3.4-3 during heatup, cooldown, criticality, and inservice leak and hydrostatic testing with:

a.

A maximum heatup rate as shown on Table 4.4-6.

b.

A maximum cooldown rate as shown on Table 4.4"6.

c.

A maximum temperature change of less than or equal to 10 F in any 1-hour period during inservice hydrostatic and leak testing opera-tions above the heatup and cooldown limit curves.

APPLICABILITY:

MOOES 4, 5, and 6 with reactor vessel head on.

\\

ACTIDN:

With any of the. above limits exceeded, restore the temperature and/or pressure to within the limit within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the Reactor Coolant System; determine that the Reac or Coolant System remains acceptable for.'ontinued oper ation or main ain the RCS T v and pressure at less than 200'F and 500 psig, respec ively.

SURYEILLANCE REOUIRBIBPS 1,4%%

4.4.9.2.1 The Reactor Coolant System temperature and pressure shall be determined to be within the limiw at least once per 30 minutes during sys em

heatup, cooldown, and inservice leak and hydrosta ic testing opera ions.

1 4.4.9.2.2 Deleted./io~

I alan

<o I'p~i'4'ccc+.n~. /Ed'f+ 76/Id1+pt'dc-cc(r~

~~~r ~<<~~'~> ~ ZPr CrVi'COVV~ PPCj.<<~g lrJ+ Pi O~CrOm.

SHEARON HARRIS - UNIT 1 3/4.4"34 0

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7 3gcE

4. 0-5 gEHcw

$$'s F

/ 7/dr/c zc/g p/yc z~

J XO GA'Wm I @~ P

~ +>r~~+>

~

'~ +> < s' 6~c /s con gioyr~cf $

- /~

~p Can p pc'Qclu/4

/ ti t +6+

/ pc~~ c&/ gjopcrg Pt'op~anf.

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SHEARON HARRIS - UNG' 3/0 0-37

~i p'ONTAINMENT SYSTEMS CONTAINMENT ISOLATION VALVES SURVEILLANCE REQUIREMENTS (Continued l

4.6.3.2 Each isolation valve shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per l8 months by:

a.

Verifying that on a Phase "A" Isolation test signal, each Phase "A" isolation valve actuates to its.isolation position;-

b.

C.

Verifying that on a Phase "B" Isolation test signal, each Phase "B" isolation valve actuates to its isolation position.;

and t

Verifying that on a Containment Ventilation Isolation test signal, each normal, preentry purge makeup and exhaust, and containment vacuum relief valve actuates to its isolation position, and d.

Verifying that, on a Safety Injection "S" test signal, each containment isolation valve receiving an "S" signal actuates to its isolati.on position, and e.

Verifying that, on a Main Steam Isolation test signal,

'each main steam isola ion valve actuates to its isolation position, and f.

Verifying that, on a Main Feedwater Isolation test signal, each feedwater isolation valve actuates to its isolation position.

4.6.3.3 The isolation time of each power"operated or automatic valve e+

hll l

d h

lhl l lid h

Specification 4. O. 5.

SHEARON HARRIS " UNIT 1 3/4 6-"5

R >-h d~ed Ref~~~ant-procedure-PLP 106.

jkdcF R g

(

C OA'7RiAJWA/7

/'SQggprag V8d O'8>

/ Ri5 +a 6

r S n e le6 a Y~~

r ec~n ca i SP eC. 8 ra+bwS.

7hz i'n gGiwc 7' en 7h.'s guAe 5 con rr~b'ru'~ g(in ~

grace'louie. j CP-i'G4~ / pc>nr ca I'pecs ~ Cai-c ~ Zy~~m~

~

I.'s + Piopzaw.

SHEARON HARRIS - UN' 3/4 6-16 through 6-29

~Meted-.Refer-to-pi antprocedure P~106.

77)e inset v c e i~ yc-n,zn prdyxn~ g~e Srv&cg/pg~:J o&rk+d 7Fdw 7 d'<lie 'ec 1 $j)pp~'gg~ -/;-~g geo( i'g C'angry hr u',ree~ecie PL+- re @r

/~~i~ car /gee.gccy

~

+gc~p~cn

//de<

SHe&RON HARRIS - UNIT 1 3/4 7-20 through 7-23

7 r

SAWr cF C~nnl (E

- Fe< >~ud/FA E~~i~aa4C xuSi

'A

~g, f.pure r J wt fc r'c'd gro.~ 7 wee< cg f SjP('er 8'cab"c.<s' c-c~ YroP~cg i'n g/yz +gloc Cdure r <i -i<4 Te4~ car Spy'cr 7 r'6 +'o-<. Zg /<<4 7 2 4 v plop.<o&

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SH~DROH HARRIS - UNIT 1 3/4 7-24

C C ~1 Ri&AE'Mi i FA/FrA'AmOA) CD VDUC70+

o @ED'c.~w/F>.

PA'omcpzu4 See iced' AIS 7 > 6/{

rS cfpI 0 Fl c/ )~a~

ia~

/PCkniCO r'pC C

iranCC 6 ~nS r.n yz:iarnHa w

7 RES Pad

/C

/ 5 conge~b'c a

~A P< + r> 6 i econ r c a 1 Z~

i'<a a,~ ~gwy~ ~F

/:s + Prop-~~.

SHEAROH HARRIS - UN' 3/< 8"21 through 8-388

SHEARON HARRIS - UNG' 3/4 8"40 Plough 8-43

A

~

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POWER DISTRIBUTION LIMITS

'ASES OUADRAHT POWER TILT RATIO Continued For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, the moveable incore detectors are used to confirm that the normalized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO.

The incore dete=tor monitoring is done with a full incore flux map or two sets of four symmetric thimbles.

The preferred sets of four sym-metric thimbles is a unique set of eight detector locations. 'hese locations are C-&, E"5, E-11, M"3, M-13, L-5, L-11, N"&. If other locations must be

used, a special r eport to 4RR<should be submitted within 30 days. in accordance wi~a 10CFR50.4.

~< AC 3/4. 2. 5 DNB PARAMETERS The limits on the DNB-related parameters assure that each of the parameters are maintained within the normal steady-state envelope of operation assumed in the transient and accident analyses.

The limits are consistent with the ini-tial FSAR ass'umptions and have been analytically demonstrated adequate to mainthih a minimum DNBR of 1. 30 throughout each analyzed transient.

The indi-cated T

value and the indicated pressurizer, pressure value are compared to avg analytical limits of 592.6oF and 2205 psig, respectively, with allowance for measurement uncertainty.

The 12-hour periodic surveillance of these parameters through instrument rea"-

out is sufficien to ensure that the parameters are restored within heir limits following load changes and other expected transient operation.

SMEAROH HARR'.S - UHIT 1 B 3/4 2

6

~

~ 4 r

f>"

AOMINISTRATIVE CONTROLS 6.9 REPORT:NG RsOUIREMsNTS ROUTINE REPOR: 5 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the~~

4 C

C 4

.iRC 'n accordance witn ~ CFR50.4.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following:

(1) receipt of an Operating License, (2) amendment to the license involving a planned increase in po~er level, (3) installation of fuel that has a different design or has been manufactured by a different fuel

supplier, and (4) modifications that may have significantly altered the nuclear,

thermal, or hydraulic performance of the unit.

The Startup Report shall address each of the tests identified in the Final Safety Analysis Report and shall include a description of the measured values

.of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.

Any corrective actions that were required to obtain satisfactory operation shall also be described.

Any additional specific details required in license condi-tions based on other commitments shall be included in this report.

Startup Reports shall be submitted within:

(1) 90 days following completion of the Startup Test Program,

('2) 90 days following resumption or commencement of commercial po~er operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and resumption or commencement of commercial operation),

supplementary reports shall be sub-mitted at least every 3 months until all three events have been completed.

I ANNUAL RsPORTS 6.9.1.2 Annual Reports covering the activities of the unit as described below for the previous-calendar year shall be submit=ed prior to March 1 of each year.

The initial report shall be submitted prior to March 1 of the year following. initial criticality.

Reports required on an annual basis shall include:

a.

A tabulation on an annual basis of the number of station, utility,

. and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated man-rem exposure according to work and job functions" (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance

[describe maintenancej,

~aste processing, and refuelincj.

The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or "This tabulation supplements the requirements of 520.407 of 10 CFR Part 20.

SHEARON HARRIS " UNIT 1 6-20

ADMINISTRATIVE CONTROLS RADIAL PEAKING FACTOR LIMIT RcPORT 6.9. 1.6 The F limits for RATED THERMAL POWER (F

) shall be p'rovided :o RTP

,in accordance wj.th 10CFR50.4 the NRC f%

1 I

PP l

for all core planes containing Bank "0" control rods and all unrodded core planes and the plot of predicted (F

~

PR 1) vs Axial Core Height with the limit enve-

- q Rel lope at least 60 days prior to each cycle initial criticality unless otherwise approved by the Commission by letter.

In addition, in the event that the limit should change requiring a new substantial or an amended submittal to the Radial Peaking Factor Limit Report, it will be submitted 60 days prior to the date the limit would become effective unless otherwise approved by the Commission by letter.

Any information needed to support F

will be by request from the NRC xy and need not be included in this report.

SPECIAL REPORTS NRC in acco"dance wi& 10CPR50.4 6.9.2 Special reports shall be submitted to the

" within the time period specified for each report.

6. 10 RECORD RETEHTION

'6.10.1 In addition to the 'applicable record retention requirements of Ti le 10, Code of Federal Regulations, the following records 'shall be retained for at least the minimum period indicated.

6.10.2 The following records shall be retained for at least 5 years:

a.

Records and logs of unit, operation covering time interval a

each power level; b.

C.

e.

Records and logs of principal maintenance activities, inspections,

repair, and replacement of principal items of equipment related to nuclear safety All RcPORTABLE EYEHTS Records of surveillance activities, inspections, and calibrations required by these Technical Specifications; Records of changes made to the procedures required by Specifica-tion 6.8.1; Records of radioactive shipments;,

Records of sealed source and fission detector leak tests and resul:s; and SHEARON HARRIS " UNIT 1 6-24

C 4

- C

,el~i ~

ML18005A243

Text

20 s, ts

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