ML18012A636

Proposed Tech Specs,Incorporating Enhancements to TS Identified in Plant Review Performed IAW GL 96-01.Changes Affected Specs 4.3.2.1.1.a,4.3.2.1.4.b,4.3.2.1.6.g, 4.3.2.1.10.a,4.3.2.1.10.b & 4.7.3.b.3

ML18012A636
Person / Time
Site:	Harris
Issue date:	04/23/1997
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18012A635	List: ML18012A634 ML18012A636
References
GL-96-01, GL-96-1, NUDOCS 9704290313
Download: ML18012A636 (23)

Text

ENCLOSURE TO SERIAL: HNP-97-066 ENCLOSURE4 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT CHANGES TO SURVEILLANCEREQUIREMENTS IDENTIFIED IN GL 96-01 REVIEW PAGE CHANGE INSTRUCTIONS Removed Pa e Inserted Pa e 3/4 3-41 3/4 3<1 3/4 3-42 3/4 3-42*

3/4 3-43 3/4 3-43~

3/4 3-44 3/4 3-44 3/4 3-45 3/43-45~

3/4 3-46 3/4 3-46 3/4 3-47 3/4 347 3/4 3-48 3/4 3-48~

3/4 3-49 3/4 3-49 3/4 7-11 3/4 7-11

~ Changed location/orientation of page footer only.

97042903i3 970423 PDR ADOCK 05000400 P PDR

~AB F 4.~3-O N NE R 0 AF TY F AT A A N Y T M N M A

( RV AN R NT I

aE I

C TRIP ANALOG ACTUATING MODES I

CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE

~IIEET III I Nl ~CN K C~ABNAT N T~T ~TST EEBL~ET I~ET EE ~IE I'II I

1. Safety Injection (Reactor Trip. Feedwater Isolation.

Control Room Isolation.

Start Diesel Generators.

Containment Ventilation Isolation. Phase A Containment Isolation.

Start Auxiliary Feedwater System Motor-Driven Pumps.

c Start Containment Fan Coolers. Start Emergency Service Water Emergency Service Pumps'tart Water Booster Pumps)

a. Manual Initiation N.A. N.A. N.A. N.A. N.A. N.A. 1. 2. 3. 4 I

b. Automatic Actuation N.A. N.A. N.A. M(1) M(1) 0(3) 1. 2. 3. 4 Logic and Actuation Relays

c. Containment S R N.A. N.A. N.A. 1. 2. 3. 4 Pressure--High-1

d. Pressurizer S R N.A. N.A. N.A. N.A. l. 2. 3 Pressure--Low

e. Steam Line S R N.A. N.A. N.A. N,A. 1. 2. 3 Pr sure--Low ote: *R = The B SSPS input from the Main Control Board Panel C Manual Safety Injectio n Switch is to be tested before reactor startup from Refueling Outage No. 7. or when the plant is in Mode 5 for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

whichever occurs- first.

B[B~ J Chang~ DAcndatT EENN

TABLE '4) 3-2 Continued EHGIHEEREll SAFETY FEATURES ACTUATIOH SYSTEH INSTRNKHTATIOH R IR NS TRlP ANALOG ACTUATING i@DES CHAHHEL -

MVICE NSTER SLAVE FOR NIICII I CIIAHHKL CIIAHHEL CIIANKL OPKRATIOHAL OPERATIOHAL ACTUATION RELAY RELAY SURVEILLAHCE TI UNIT QIECK CAL BRA1 ION TES'f. TEST LOGIC TEST TEST t% ~IRE 1 E q 2; Contalpaent Spray

a. Hanual initiation N.A. N.h. N.A. N.h. N.h. N.h'. 1, 2, 3, 4

b. Autoaatic Actuation N.h. N.A. N.A. H.h. H(1) H(l) Q l~ 2~ 3 ~ 4 Logic and Actuation Relays

c. Containaent Pressure- S N.A. N.A. N.A. N.A. 1, 2, 3 lligh-3

$ . Contaioaent Iso)ation

a. Phase "A" Isolation

1) Nanual Initiation N.h. N.h. R N.A. N.A. N.A 1,2,3,4 Rj I H(j)

2) hut~tie Actuation H.h. N.A. N.h. H.A. H(1) Q(3) 1, 2, 3, 4 0 logic an4 Actuation Relays C 3) Safety In)ection See It+ l. above for all Safety Injection SurveiIIance Require nts.

b. Phase "8" Isolation

1) Hanual Containaent Sea Itea 2.a. above for Hanual Containaent Spray Surveilian e Require t Spray Initiation

2) Automatic Actuation H.A. N.h. H.A. H.A. H(1) H(1) Q 1, 2, 3, 4 Logic Actuation Relays 3

TABLE 4. 3-2 Continued EHGlNEEREO SAFETY FEATURES ACTUATlON SYSTEH lHSTRUHENTATlON TRIP ANALOG ACTUATlHG HGDES CIIAQlEL OEVlCE HASTER SLAVE FOR MIIECII CIIANIIEL CHANHEL OP ERAT lONAL OPKRAT lONAL ACTUATlOH RELAY RELAY SURVElLLANCE CtNNHEL NlT TEST lOGIC TEST TEST TEST lS RE UlREO UNCT lONAL 3, Containwent isolation (Continued)

R H H.A, H.A. H.A. H.A; 1, 2, 3

3) Containeent S Pressure--IIigh-3 I

c. Containaent 1/entilation isolation l) Hanual initiation Containaent See ltea 2.a. above for Hanual Containoent Spray Surveillance Requireaents.

Spray

2) Autoaatic Actuation H.A. H.h. H.A. N.A. H(l 2)

~ H(l 2) Q(2)

~ l, 2, 3, 6N Logic an4 Actuation Relays

3) Safety ln)ection See ltea l. above for all Safety injection Surveillance Requireaents..

4) gontainaent Radioactivity

) brea Nonitors See Table I.3-3, ltea la, for surveillance requlreaents.

(botb preentry and norsal purges) y) Airborne Gaseous Radioactivity (l) RCS leak See Table i.3-3, itea lbl, for surveillance requireients.

Oetection (qoraal purge)

TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEH INSTRUMENTATION SURVEILLANCE RE UIREHENTS TRIP ANALOG ACTUATING HODES OlANNEL DEVICE HASTER SLAVE FOR MIICH CHANNEL CNNNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE CIIANNEL'UNCTIONAL UNIT 'HECK CALIBRATION TEST TEST LOGIC TEST TEST TEST E

3. Containment Isolation (Continued)

(2) Preentry See Table 4.3-3, Item 1b2, for surveillance requirements.

Purge Detector c) Airborne Particulate Radioactivity (1) RCS Leak See Table 4.3-3, Item lCl, for surveillance requirements.

Detection (normal purge)

(2) Preentry See Table 4.3-3, Item 1C2, for surveillance requirements.

Purge Detector

5) Hanual Phase A See Item 3.a.l) above for Hanual Phase A Isolation Surveillance Requirements.

Isolat.ion

4. Hain Steam Line Isolation

a. Hanual Initiation N.A. N.A. N.A. A. N.A. N.A.- 1, 2, 3, 4

b. Automatic actuation N.A. N.A N.A N. A. H(1) Q 1,2,3,4 Logic and Actuation Relays

c. Containment Pressure S N.A. N. A. N.A. N.A. I, 2, 3 Iligh-2

~ TNLE I. 3-2 Continued EHGlkEEREO SAFE FEATURES ACTUATIOH SYSTEH IHSTRUHEHTATIOH E R H TRlP ANLOG ACTUATlNG NSES CIIAHNEL OEVlCE HASTER SLAVE FOR MII1CII CIIAHHEL CIIAIIIEL OPERATlONI. OPERATIONl ACTUATlOH RElAY RELAY SURVElLLAHCE CIIAHHEL T1OHAL UHlT Clli K RLIBRIIIN %SI DESI LMI e 1 TEH TBT IS EISIIRE Q isolation

g. Hain Steaa Line

d. Steaa i.ine See itea l.e, above for Steaa line Pressure-"Le>> Surveillance Requireaents.

Pressure-Lov N.h. N.A. N.h, N A 3aa gaa

e. Hegat]ve Stem line Pressure Rate-"High Trip an4 Fear%rater

$ . Turbine isolation N.A. N.h, N.A. H.A. H(i) Q 1, 2

a. Autoaatic Actuation Logic and hc~tion Relays H II.A. N.h. N.A. 1, 2

b. Steam Generator Mater S R Level -illgh-High (P-ll)

S Coty lnjecMon

c. Safety n ec on See ltea l. above for Safety injection Surveillance Requireaents.

p, Auxiliary Feaster

a. Nagual lnitiition N.A. N.h. N.A. 'R N.A. N.h. l, 2, 3

b. Automatic Actuation N.h. N,h ~ N.h. N.A. H(i) H(l) Q,. 1, 2, 3 and Actuation Relays W5

c. Steaa Generator Mater S R N.A'.A 1, 2, 3

', level--Lcm-LW Safety injection

$ tart Hotor-Driven Pumps See ltea ), above for all Safety injection Surveillance Requireaents.

Poeal'ul'aettlaeca toes-ot-Qffstta potter Sae Iteo 9. ballet foe all Loss-of-Offsite Raqeteeeaots.

a.

Start Hotor-P'r iven Pueps and Turbine-Driven Puap

TNLE l. 3-2 Continued ENGlNEERED SAFFTY FEATURES ACTUATlON SYSTEM lNSTRljNENTATION RV 1 LLAHC R Ul RENENTS 78lP AHALOG ACTUATlNG HODES CIIAHHEL 0EV ICE HASTER SLAVE. FOR MllCN CHANNEL CHAHHEL C)lAHNEL OPERATlOHAL OPERATlOHAL ACTUATlON RELAY RELAY SURVElLLAHCE FUHCT lOHAL UNl T CIIECK CALIBRATLOU TEST TEST LOGIC 'TEST TEST TEST ~IS RE UIREO

6. Auxiliary Fee%tater (Continued)

- f. Trip of All Hain Feed- N.A. N.h. N.h. N.A. N.h. N.A 1, 2 vater Peaps Start Hotor-Driven Pumps

g. Steaa Line Differen- S N.A. N.A. N.h.

tial Pressure-High Coincident Mith Hain See ltea 4. above for all Hain Steal Line isolation Surveillance Requireeents.

Steae Line isolation (Causes AFM isolation)

l. Safety injection Switchover to Containaent Suap

a. hutoaatic Actuation N.h. N.h. N.A. N.A. N(l)

Logic and Actuation Relays

b. RMST i.evel Lertw R H N.A. N.A. N.A. Q(3) 1, 2, 3, 4 Coincident Mlth See itea l. above for all Safety inject.ion Surveillance Requireaents.

Safety injection

8. Contaioaent Spray Switch-over to Containeent SuaLp

a. Autoaatlc Actuation N.A. N.A. N.A. N.A. H(1) Q(3) 1, 2, 3, I Logic aml Actuation Relays

TADLE i.3-2 Continu~ed ENGINEERED SAFETY FEATURES ACTUhllON SYSTEN INSTRUHENTATIOH R C 0 KHEH S

~CLA<~A ~

Ut TRIP ANALOG ACTUATlHG NODES CINNHEL DEVICE HASTER SLAVE FOR MIIICII CHANNEL CIIANHEL CIIAHHEL OPERAT IONL OPERATIONL ACTUATIOH REI.AY RELAY SURVEILLANCE fUHCTIONL UNIT CIIECK CALIBRATloll 1ESI TEST E7 I

8. Containaent Spray Switch-over to Containaent Suap (Continued)

b. RMST Level""LorLmt See Itea 7.b. above for NST Level Lo~-Le> Surveillance Requireaents Coincident with See Item 2. above for Containaent Spray Surveillance Requireaents.

Contalnaent Spray

9. Loss-of-Offsite Pumr

a. 6.9 kV Eaergency 8us H.A. R H.A. N.A. H.A. N.A. 1, 2, 3, 4 Undervol tage-Priaary

b. 6.9 kV Eaergency Sus H.A. R. H.h. N.A. H.A. N.h. 1, 2, 3, 4 Undervoltage Secondary

10. Engineered Safety features Actuation Systea Interlocks

a. Pressurizer Pressure, P-ll H.A. R N.A. ~~fi)

~ m (i)

.A.'(')

.A.

Hot P-ll N.A. R N.A. ~(])

b. Los-Los Tav ~ P 12 N.h. R N.h. l, 2, 3

TABLE 1.3-2 Continued EHGIIIEERED SAFETY FEATURES ACTUATIOH SYSTEII lIISTRNIEIITATION TRIP ANUS ACT UATTIIG HGOES CININEL DEVICE HASTER SLAVE FOR MIllCII

@AIIIIEi. CIIAINIEL CIIANEL OPERATlONL OPERAT lONL ACTUAT til RELAY TEST RELAY

'fEST SURVETLLANCE IS RE IRED CAL RRATIRR TEST TEST LOGIC TEST NCTltNAL NIlT , CIIECX I

1Q. Engineered Sifety Features Actuation Systea 1nterlocks (Continued) I II.A. A.A. N.h. II.A. 1, 2, 3

c. Reactor Trip, P-i II.A. R ii.A.

d. Slew Generator See item S,h. above for P-N Surveillance Requireaents.

hk Mater Level, P-14 Ok I

~ ~

TABLE 4. 3-2 Cantfnued TABLE NOTATION (1) Each trafn shall be tested at least every 62 days on a STAGQEREQ TEST BASIS.

(2) The Survefllance Requfreaents of'pecfffcatfon 4.9.9 apply durfng CORE ALTERATIONS or aoveeent of frradfated fuel fn contafnaent.

(3) Except f 0'r rel ays K601 K602 y K603 ~ K608 f K610 y K61$ ~ K6 16 y K617 ~ K622 ~

K636, K739, K740 and K741 whfch shall be tested at least once per 18 months and durfng each COLO SNJTONH exceedfng 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> unless they have been tested wfthfn the prevfous 92 days.

Setpofnt ver if fcatfon not requfred.

Ourfng CORE ALTERATIONS or aoveaent of frradfated fuel fn contafnment.

Trfp func.fon autoaatfcally blocked above P-11 and say be blocked below P-11 when safety fnfectfon or low steaaltne pressure fs not blocked.

gt ~ t + ~ 5~/ Q gg~gg4 Pe (l3I ck-"

(~)) g ~

T k t.'s ceo bl e Saic'c +4 ocp hJo~ k ae Sp~t L~>e. )Re SS v n e

+ke F-/I k,el0~

~~+ -- ~<<~ ~()~.t (,]e. <..) ~[<~ ~seJ

~~<""s oot. Nesee 5 e S>

56+$ oi+~ V4Ri Cf @Rope+ 0 ~~ $ r pA 8,Ack fi~e SNEARON HARRIS NTT 1 3/4 3-49

p SYSTl98 I

3 4.1. COXPON9fF COOQN MATER SYSTEM

% CONITTOS FOR OP%ATION 3.7.3 At.least ~ coeponent cool fny star

~ sssntfal flaw paths shall ba OPstASLK.

(CCM) pusps~, heat sxchsngars and APP CA8: NOES l, R, 3, and 4.

CfIN:

fifth only one ~onent coolfny ~r Pet path OPStNLE, rsstoro at least two flee paths to OMQlLS status Nthfn 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be fn at least, HQT $TANOSY Athfn the next 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and fn COLO $ NlTDOiN Hthfn the follerlny 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

4.7.3 At least too coaponsnt coolfny star fTer paths sha11 ba deaanstrscad OPNASLK:

ao At least ance per 3X days by wrffyfno that each valve (aanual, p~eerated. m automtfc) sarvfcfno safety related equfpeent that fs not locked, saalef, or othetrfso seems fn posftfon fs fn fts amdt poof tfon; and At least ones per I mnths durfni sfeidew, by verffyfng that:

L Each amtoiatic valve servfcfnN safety related equiparant or fsolatfni non.safety~'lated coeeaaCs actuates to fta correct peeftfm oa a Safety Enfectfm test sfyel, and

~ CoeponeC Coelfnj Meta Systea starts automtfcally on a

~ reydrod to be OPSN8LK Safety le$ ectfon test sf anal.

3; CaN eitoiatfc valve servfni the Iross fafled fuel detector acet'e fts correct poa tfon oo a Lao Surge Tan@ Level tee sf yah pe/ ~>e sys4~

bio ~ excA+<pq~s.

The bteakNr for COt (SA e'I) fs roofs out.

~ XC (bless the breaher QI shal1 not be tree the applfcahle CCM ~

roofs'nto efther peat 11.$

(IA.SA or source 1) 5HMN IQRQI LNQT I 3I4 7 iX

ENCLOSURE TO SERIAL: HNP-97-066 ENCLOSURE5 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT CHANGES TO SURVEILLANCEREQUIREMENTS IDENTIFIED IN GL 96-01 REVIEW TECHNICAL SPECIFICATION PAGES

TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST 1tBIC TEST TEST TEST ~IS RE UIREO Safety Injection (Reactor Trip, Feedwater Isolation.

Control Room Isolation, Start Diesel Generators.

Containment Ventilation Isolation, Phase A Containment Isolation.

Start Auxiliary Feedwater System Motor-Driven Pumps.

Start Containment Fan Coolers. Start Emergency Service Water Pumps, Start Emergency Service Water Booster Pumps)

a. Manual Initiation N.A. N.A. N.A. R N.A. N.A. N.A. 1, 2, 3, 4

b. Automatic Actuation N.A. N.A. N.A. N.A. M(1) M(1) 0(3) 1, 2, 3. 4 Logic and Actuation Relays

c. Containment N.A. N.A. N.A. N.A. 1. 2, 3, 4 Pressure--High-1

d. Pressurizer N.A. N.A. N.A. N.A. 1. 2, 3 Pressure--Low

e. Steam Line N.A. N.A. N.A. N.A. 1, 2, 3 Pressure--Low SHEARON HARRIS - UNIT 1 3/4 3-41 Amendment No.

TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR MHICH CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK CAIISEATttlll TEST TEST I-IIEIC TEST TEST TEST ~IS EE UIKEU

2. Containment Spray

a. Manual Initiation N.A. N.A. N.A. R N.A. N.A. N.A. 1. 2. 3. 4

b. Automatic Actuation Logic and Actuation Relays N.A. N.A. N.A. N.A. M(1) M(1) Q 1,2.3.4

c. Containment Pressure-- S R N.A. N.A. N.A. N.A. 1, 2, 3 High-3

3. Containment Isolation

a. Phase "A" Isolation

1) Manual Initiation N.A. N.A. N.A. R N.A. N.A. N.A 1, 2. 3. 4

2) Automatic Actuation N.A. N.A. N.A. N.A. M(l) M(l) 0(3) 1. 2. 3, 4 Logic and Actuation Relays

3) Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

b. Phase "B" Isolation

1) Manual Containment See Item 2.a. above for Manual Containment Spray Surveillance Requirements.

Spray Initiation

2) Automatic Actuation N.A. N.A. N.A. M(1) M(1) 0 1, 2, 3, 4 Logic Actuation Relays SHEARON HARRIS - UNIT 1 3/4 3-42 Amendment No.

TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVE ILLANC FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST ~IR RE UIRER

3. Containment Isolation (Continued)

3) Containment S R M N.A. N.A N.A. N.A. 1, 2, 3 Pressure--High-3

c. Containment Ventilation Isolation

1) Manual Containment See Item 2.a. above for Manual Containment Spray Surveillance Requirements.

Spray Initiation

2) Automatic Actuation N.A. N.A. N.A. N.A M(1, 2) M(1. 2) 0(2) 1. 2, 3, Logic and Actuation Relays

3) Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

4) Containment Radioactivity a) Area Monitors See Table 4.3-3, Item la, for surveillance requirements.

(both preentry and normal purges) b) Airborne Gaseous Radioactivity (1) RCS Leak See Table 4.3-3. Item lbl, for surveillance requirements.

Detection (normal purge)

SHEARON HARRIS - UNIT 1 3/4 3-43 Amendment No.

TABLE 4.3-2 Continu d ENGINEERED SAFETY FEATURES ACTUATION SYSTEH INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP ANALOG ACTUATING NODES CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEI CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION REl AY RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK CAI IAIIATIOA TEST TEST I OSIC TEST TEST TEST ~IS AE HIKES

3. Containment Isolation (Continued)

(2) Preentry Purge See Table 4.3-3, Item 1b2. for surveillance requirements.

Detector c) Airborne Particulate Radioactivity (1) RCS Leak Detection See Table 4.3-3, Item 1C1, for surveillance requirements.

(normal purge)

(2) Preentry Purge See Table 4.3-3, Item 1C2. for surveillance requirements.

Detector

5) Manual Phase A Isolation See Item 3.a.l) above for Manual Phase A Isolation Survei llance Requirements.

4. Main Steam Line Isolation

a. Manual Initiation N.A. N.A. N.A. R N.A. N.A. N.A. 1, 2, 3, 4

b. Automatic Actuation Logic and N.A. N.A N.A N.A. H(1)(4) M(1) 0 l. 2. 3, 4 Actuation Relays

c. Containment Pressure--High-2 N.A. N.A. N.A. 1, 2, 3 SHEARON HARRIS - UNIT 1 3/4 3-44 Amendment No.

TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS RE UIRE

4. Main Steam Line Isolation (Continued)

d. Steam Line Pressure--Low See Item l.e. above for Steam Line Pressure--Low Surveillanc e Requirements.

e. Negative Steam Line Pressure S R M N.A. N.A. N.A. N.A. 3**. 4 Rate--High

5. Turbine Trip and Feedwater Isolation

a. Automatic Actuation Logic and N.A. N.A. N.A. N.A M(1) M(1) Q 1, 2 Actuation Relays

b. Steam Generator Water S R M N.A N.A. N.A. N.A. 1, 2 Level--High-High (P-14)

c. Safety Injection See Item l. above for Safety Injection Surveillance Requirements.

6. Auxiliary Feedwater

a. Manual Initiation

b. Automatic Actuation and N.A.

N.A.

N.A.

N.A N.A N.A R

N.A.

N.A.

M(1)

M(1) 0 1, 2. 3 e

Actuation Relays

c. Steam Generator Water S R M N.A. N.A N.A N.A 1, 2 ~ 3 Level--Low-Low

d. Safety Injection Start See Item l. above for all Safety Injection Surveillance Requirements.

Motor-Driven Pumps Loss of Offsite Power Start See Item 9. below for all Loss-of-Offsite Power Surveillance Requirements.

Motor -Driven Pumps and Turbine-Driven Pump SHEARON HARRIS - UNIT 1 3/4 3-45 Amendment No

TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHIC CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAI ACTUATION RELAY RELAY RRVEILLANCE FUNCTIONAL UNIT CHECK CAIISSATIEH TEST TEST I ESIC TEST TEST TEST ~IS IIE IIIEII

6. Auxiliary Feedwater (Continued)

Trip of All Main Feedwater N.A. N.A. N.A. N.A. N.A. N.A 1, 2 Pumps Start Motor-Driven Pumps

g. Steam Line Differential N.A. N.A. N.A. Q(3) 1, 2, 3 I Pressure--High Coincident With Main Steam See Item 4. above for all Main Steam Line Isolation Surveillance Requirements.

Line Isolation (Causes AFW Isolation)

?. Safety Injection Switchover to Containment Sump

a. Automatic Actuation Logic N.A. N.A. N.A. N.A. M(1) M(1) Q(3) 1, 2, 3. 4 and Actuation Relays

b. RWST Level--Low-Low S R M N.A. N.A. N.A. Q(3) 1, 2. 3. 4 Coincident With Safety See Item l. above for all Safety Injection Surveillance Requirements.

Injection

8. Containment Spray Switchover to Containment Sump

a. Automatic Actuation Logic N.A. N.A. N.A. M(1) M(1) Q(3) 1, 2, 3. 4 and Actuation Relays SHEARON HARRIS - UNIT 1 3/4 3-46 Amendment No.

TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER Sl AVE FOR WHICH CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY RRVEILLANCE FUNCTIONAL UNIT CHECK CAI ISIIATIIIE TEST TEST CASES TEST TEST TEST ~IS SE ISEC

8. Containment Spray Switchover to Containment Sump (Continued)

b. RWST Level--Low-Low See Item 7.b. above for RWST Level--Low-Low Surveillance Requirements.

Coincident with Containment See Item 2. above for Containment Spray Surveillance Requirements.

Spr ay

9. Loss-of-Offsite Power

a. 6.9 kV Emergency Bus N.A. R N.A. M* N.A. N.A. N.A. 1. 2, 3. 4 Undervoltage--Primary

b. 6.9 kV Emergency Bus N.A. R N.A. M* N.A. N.A. N.A. 1, 2. 3, 4 Undervoltage--Secondary

10. Engineered Safety Features Actuation System Interlocks

a. Pressurizer Pressure.

P-11 N.A. R M N.A M(1) M(l) N.A. 1, 2, 3 Not P-11 N.A. R M N.A M(1) M(l) N.A. 1, 2, 3

b. Low-Low T,~, P-12 N.A. R M N.A M(l) M(l) N.A. 1, 2. 3 SHEARON HARRIS - UNIT 1 3/4 3-47 Amendment No.

TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP ANAI OG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK CAI TRIIATIOE TEST TEST lOGIC TEST TERT TEST ~IS RE HIRER

10. Engineered Safety Features Actuation System Interlocks (Continued)

c. Reactor Trip, P-4 N.A. N.A. N.A. R N.A. N.A. N.A. 1,2.3

d. Steam Generator Water Level, See Item 5.b. above for P-14 Surveillance Requirements.

P-14 SHEARON HARRIS - UNIT 1 3/4 3-48 Amendment No.

TABLE 4.3-2 Continued TABLE NOTATION (1) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(2) The Surveillance Requirements of Specification 4.9.9 apply during CORE ALTERATIONS or movement of irradiated fuel in containment.

(3) Except for relays K601, K602. K603, K608, K610. K615, K616. K617, K622.

K636. K739, K740 and K741 which shall be tested at least once per 18 months and during each COLD SHUTDOWN exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> unless they have been tested within the previous 92 days.

(4) The Steam Line Isolation-Safety Injection (Block-Reset) switches enable the Negative Steam Line Pressure Rate--High signal (item 4.e) when used below the P-11 setpoint. Verify proper operation of these switches each time they are used.

Setpoint verification not required.

During CORE ALTERATIONS or movement of irradiated fuel in containment.

Trip Function automatically blocked above P-11 and may be blocked below P-ll when safety injection or low steamline pressure is not blocked.

SHEARON HARRIS - UNIT 1 3/4 3-49 Amendment No.

PLANT .SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3 At least two component cooling water (CCW) pumps'. heat exchangers and essential flow paths shall be OPERABLE.

APPLICABILITY: MODES 1. 2. 3. and 4.

ACTION:

With only one component cooling water flow path OPERABLE. restore at least two flow paths to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.7.3 At least two component cooling water flow paths shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) servicing safety-related equipment that is not locked, sealed, or otherwise secured in position is in its correct position; and

b. At least once per 18 months during shutdown. by verifying that:

1. Each automatic valve servicing safety-related equipment or isolating non-safety-related components actuates to its correct position on a Safety Injection test signal, and

2. Each Component Cooling Water System pump required to be OPERABLE starts automatically on a Safety Injection test signal.

3. Each automatic valve serving the, gross failed fuel detector and sample system heat exchangers actuates to its correct position on a Low Surge Tank Level test signal.

The breaker for CCW pump 1C-SAB shall not be racked into either power source (SA or SB) unless the breaker from the applicable CCW pump (1A-SA or 1B-SB) is racked out.

SHEARON HARRIS - UNIT 1 3/4 7-11 Amendment No.

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