Text

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: HNP-97-066, Application for Amend to License NPF-63,incorporating Enhancements to TS Identified in Plant Review Performed IAW GL 96-01.Changes Affect 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;
References
	GL-96-01, GL-96-1, NUDOCS 9704290313
	Download: ML18012A636 (23)
	v • d • e

ENCLOSURE TO SERIAL: HNP-97-066 ENCLOSURE4 SHEARON HARRIS NUCLEARPOWER PLANT NRC DOCKETNO. 50400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT CHANGES TO SURVEILLANCEREQUIREMENTS IDENTIFIEDIN GL 96-01 REVIEW PAGE CHANGE INSTRUCTIONS Removed Pa e

3/4 3-41 3/4 3-42 3/4 3-43 3/4 3-44 3/4 3-45 3/4 3-46 3/4 3-47 3/4 3-48 3/4 3-49 3/4 7-11 Inserted Pa e

3/4 3<1 3/4 3-42*

3/4 3-43~

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

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

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

~ Changed location/orientation ofpage footer only.

97042903i3 970423 PDR ADOCK 05000400 P

PDR

~AB F 4.~3-N NE R 0 AF TY F AT A

A N

Y T M

N M

A RV AN R

NT O

(I I

aE C

I CHANNEL

~IIEETIII I Nl 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 Pumps'tart Emergency Service Water Booster Pumps) a.

Manual Initiation N.A.

N.A.

b. Automatic Actuation N.A.

N.A.

Logic and Actuation Relays

c. Containment S

R Pressure--High-1

d. Pressurizer S

R Pressure--Low e.

Steam Line S

R Pr sure--Low ote:

R = The B SSPS input fr before reactor startup fr whichever occurs-first.

N.A.

1. 2. 3.

4 I

M(1) 0(3)

1. 2. 3.

4 N.A.

N.A.

M(1)

N.A.

1. 2. 3.

4 N.A.

N.A.

l. 2.

3 N.A.

N,A.

1. 2.

3 N.A.

N.A.

n Switch is to be tested 5 for at least 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

om the Main Control Board Panel C Manual Safety Injectio om Refueling Outage No. 7. or when the plant is in Mode TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE

~CN K

C~ABNAT N

T~T

~TST EEBL~ET I~ET EE

~IE I'II I B[B~ J Chang~ DAcndatT EENN

I q

CIIAHHKL TI UNIT 2; Contalpaent Spray TABLE '4) 3-2 Continued EHGIHEEREll SAFETY FEATURES ACTUATIOH SYSTEH INSTRNKHTATIOH R

IR NS TRlP ANALOG ACTUATING CHAHHEL MVICE NSTER CIIAHHEL CIIANKL OPKRATIOHAL OPERATIOHAL ACTUATION RELAY QIECK CAL BRA1ION TES'f.

TEST LOGIC TEST TEST i@DES SLAVE FOR NIICII RELAY SURVEILLAHCE t%

~IRE 1

E N.A.

a. Hanual initiation

b. Autoaatic Actuation N.h.

Logic and Actuation Relays

c. Containaent Pressure-S lligh-3

$. Contaioaent Iso)ation a.

Phase "A" Isolation N.h.

N.A.

H.h.

N.A.

N.h.

H(1)

N.A.

N.h.

N.h'.

1, 2, 3, 4 H(l)

Q l~ 2~ 3 ~ 4 N.A.

N.A.

1, 2, 3 Rj 0

C 3

1) Nanual Initiation N.h.

R I

2) hut~tie Actuation H.h.

N.A.

H.A.

logic an4 Actuation Relays

3) Safety In)ection See It+ l. above for all Safety Injection SurveiIIance Require nts.

N.h.

N.A.

H(j)

N.A.

N.A 1,2,3,4 H(1)

Q(3) 1, 2, 3, 4 N.h.

H.A.

1, 2, 3, 4 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(1)

Q Logic Actuation Relays

TABLE 4. 3-2 Continued EHGlNEEREO SAFETY FEATURES ACTUATlON SYSTEH lHSTRUHENTATlON ANALOG CIIAQlEL CtNNHEL CIIANIIEL CHANHEL OP ERATlONAL UNCTlONAL NlT 3, Containwent isolation (Continued)

TRIP ACTUATlHG HGDES OEVlCE HASTER SLAVE FOR MIIECII OPKRATlONAL ACTUATlOH RELAY RELAY SURVElLLANCE TEST lOGIC TEST TEST TEST lS RE UlREO H.A,

3) Containeent S

R H

Pressure--IIigh-3 I

c. Containaent 1/entilation isolation l) Hanual Containaent See ltea 2.a.

above for Hanual Containoent Spray initiation

2) Autoaatic Actuation H.A.

H.h.

H.A.

N.A.

Logic an4 Actuation Relays

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

4) gontainaent Radioactivity

)

brea Nonitors See Table I.3-3, ltea la, for surveillance (botb preentry and norsal purges)

H.A.

H.A; 1, 2, 3 l, 2, 3, 6N Surveillance Requireaents..

requlreaents.

Spray Surveillance Requireaents.

H(l~ 2)

H(l~ 2) Q(2) y)

Airborne Gaseous Radioactivity (l) RCS leak See Table i.3-3, itea lbl, for surveillance requireients.

Oetection (qoraal purge)

CIIANNEL'UNCTIONAL UNIT TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEH INSTRUMENTATION SURVEILLANCE RE UIREHENTS TRIP ANALOG ACTUATING OlANNEL DEVICE HASTER SLAVE CHANNEL CNNNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY

'HECK CALIBRATION TEST TEST LOGIC TEST TEST TEST HODES FOR MIICH SURVEILLANCE E

3.

Containment Isolation (Continued)

(2) Preentry Purge Detector c)

Airborne Particulate Radioactivity See Table 4.3-3, Item 1b2, for surveillance requirements.

(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

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

4. Hain Steam Line Isolation a.

Hanual Initiation N.A.

b. Automatic actuation N.A.

Logic and Actuation Relays

c. Containment Pressure S Iligh-2 N.A.

N.A N.A.

N.A N. A.

N.A.

A.

N. A.

N.A.

N.A.-

1, 2, 3, 4 H(1)

Q 1,2,3,4 N.A.

N.A.

I, 2, 3

~

TNLE I.3-2 Continued EHGlkEEREO SAFE FEATURES ACTUATIOH SYSTEH IHSTRUHEHTATIOH E

R H

CIIAHHEL T1OHAL UHlT

g. Hain Steaa Line isolation Q

d. Steaa i.ine Pressure-Lov

e. Hegat]ve Stem line Pressure Rate-"High N.h.

N.A.

N.h, N A 3aa gaa TRlP ANLOG ACTUATlNG NSES CIIAHNEL OEVlCE HASTER SLAVE FOR MII1CII CIIAHHEL CIIAIIIEL OPERATlONI.

OPERATIONl ACTUATlOH RElAY RELAY SURVElLLAHCE Clli K RLIBRIIIN %SI DESI LMI e 1 TEH TBT IS EISIIRE See itea l.e, above for Steaa line Pressure-"Le>>

Surveillance Requireaents.

$. Turbine Trip an4 Fear%rater isolation

a. Autoaatic Actuation N.A.

Logic and hc~tion N.A.

1, 2 II.A.

N.h.

N.A.

1, 2

N.h.

N,h

'R N.A.

N.h.

l, 2, 3 H(l)

Q,.

1, 2, 3

~ N.h.

N.A'.A 1, 2, 3

N.h, H.A.

H(i)

Q Relays b.

Steam Generator Mater S

R H

Level -illgh-High (P-ll)

S Coty lnjecMon See ltea l. above for Safety injection Surveillance Requireaents.

c. Safety n ec on p, Auxiliary Feaster

a. Nagual lnitiition N.A.

N.A.

b. Automatic Actuation N.h.

N.A.

H(i)

W5 and Actuation Relays

c. Steaa Generator Mater S

R level--Lcm-LW

', Safety injection See ltea ), above for all Safety injection Surveillance Requireaents.

$tart Hotor-Driven Pumps

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

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

UlRENENTS CHANNEL FUHCTlOHAL UNlT CHAHHEL CIIECK 78lP AHALOG ACTUATlNG HODES CIIAHHEL 0EV ICE HASTER SLAVE.

FOR MllCN C)lAHNEL OPERATlOHAL OPERATlOHAL ACTUATlON RELAY RELAY SURVElLLAHCE CALIBRATLOU TEST TEST LOGIC 'TEST TEST TEST

~IS RE UIREO

6. Auxiliary Fee%tater (Continued)

- f. Trip of All Hain Feed-N.A.

vater Peaps Start Hotor-Driven Pumps

g. Steaa Line Differen-S tial Pressure-High Coincident Mith Hain See ltea Steae Line isolation (Causes AFM isolation) l.

Safety injection Switchover to Containaent Suap N.h.

N.h.

N.A.

N.h.

N.A 1, 2 N.A.

N.A.

N.h.

4.

above for all Hain Steal Line isolation Surveillance Requireeents.

a. hutoaatic Actuation Logic and Actuation Relays b.

RMST i.evelLertw N.h.

N.h.

N.A.

N(l)

R H

N.A.

Q(3) 1, 2, 3, 4 Coincident Mlth Safety injection

8. Contaioaent Spray Switch-over to Containeent SuaLp See itea l. above for all Safety inject.ion Surveillance Requireaents.

a. Autoaatlc Actuation N.A.

Logic aml Actuation Relays N.A.

N.A.

H(1)

Q(3) 1, 2, 3, I

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 LevelLo~-Le> Surveillance Requireaents Coincident with Contalnaent Spray

9. Loss-of-Offsite Pumr See Item 2.

above for Containaent Spray Surveillance Requireaents.

a. 6.9 kV Eaergency 8us Undervol tage-Priaary

b. 6.9 kV Eaergency Sus Undervoltage Secondary

10. Engineered Safety features Actuation Systea Interlocks

a. Pressurizer

Pressure, P-ll Hot P-ll

b. Los-Los Tav

~

P 12 H.A.

R H.A.

R.

H.A.

R N.A.

R N.h.

R H.A.

H.h.

N.A.

N.h.

N.A.

~~fi)

~ ~(])

H.A.

N.A.

1, 2, 3, 4 H.A.

N.h.

1, 2, 3, 4 m (i)

.A.'(').A.

l, 2, 3

TABLE 1.3-2 Continued EHGIIIEERED SAFETY FEATURES ACTUATIOH SYSTEII lIISTRNIEIITATION

@AIIIIEi.

NCTltNAL NIlT I

1Q.

Engineered Sifety Features Actuation Systea 1nterlocks (Continued)

TRIP ANUS ACT UATTIIG HGOES CININEL DEVICE HASTER SLAVE FOR MIllCII CIIAINIEL CIIANEL OPERATlONL OPERAT lONL ACTUATtil RELAY RELAY SURVETLLANCE

, CIIECX CAL RRATIRR TEST TEST LOGIC TEST TEST

'fEST IS RE IRED hk OkI

c. Reactor Trip, P-i

d. Slew Generator Mater Level, P-14 I

A.A.

ii.A.

II.A.

R See item S,h.

above for P-N Surveillance Requireaents.

N.h.

II.A.

1, 2, 3

~

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 f0'r rel ays K601 K602 y K603 ~ K608 f K610 y K61$ ~

K616 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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.

(~))

g gt

~

t + ~

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

Saic'c t.'s ceo e

T k bl

+4 hJo~ k ae Sp~t L~>e. )Re SS v n e ocp

+ke F-/I

~~+ -- ~<<~

~()~.t (,]e. <..) ~[<~ ~~seJ k,el0~

ot. Nese S> ~~<""s 56+$ oi+~

V4Ri Cf

@Rope+

0~~ $rpA o

e 5 e 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 (CCM) pusps~,

heat sxchsngars and

~sssntfal flaw paths shall ba OPstASLK.

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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be fn at least, HQT $TANOSY Athfn the next 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and fn COLO $NlTDOiN Hthfn the follerlny 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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 pooftfon; 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 ~ reydrod to be OPSN8LK starts automtfcally on a Safety le$ectfon test sfanal.

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

bio~

excA+<pq~s.

The bteakNr for COt~ XC QI shal1 not be roofs'nto efther peat source (SA e'I) (bless the breaher tree the applfcahle CCM~ (IA.SA or 11.$1) fs roofs out.

5HMN IQRQI LNQTI 3I4 7 iX

ENCLOSURE TO SERIAL: HNP-97-066 ENCLOSURE5 SHEARON HARRIS NUCLEARPOWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT CHANGES TO SURVEILLANCEREQUIREMENTS IDENTIFIEDIN GL 96-01 REVIEW TECHNICALSPECIFICATION PAGES

TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL FUNCTIONAL UNIT TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE 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

b. Automatic Actuation Logic and Actuation Relays

c. Containment Pressure--High-1

d. Pressurizer Pressure--Low e.

Steam Line Pressure--Low N.A.

N.A.

R N.A.

N.A.

M(1)

N.A.

1, 2, 3, 4

M(1) 0(3) 1, 2, 3. 4 N.A.

N.A.

1. 2, 3, 4

N.A.

1. 2, 3

N.A.

1, 2, 3

SHEARON HARRIS - UNIT 1 3/4 3-41 Amendment No.

TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL FUNCTIONAL UNIT 2.

Containment Spray a.

Manual Initiation N.A.

N.A.

b. Automatic Actuation Logic N.A.

N.A.

and Actuation Relays

c. Containment Pressure--

S R

High-3 3.

Containment Isolation a.

Phase "A" Isolation 1)

Manual Initiation N.A.

N.A.

2)

Automatic Actuation N.A.

N.A.

Logic and Actuation Relays 3)

Safety Injection b.

Phase "B" Isolation 1)

Manual Containment Spray Initiation 2)

Automatic Actuation N.A.

N.A.

Logic Actuation Relays N.A.

N.A.

1. 2. 3.

4 M(1)

Q 1,2.3.4 N.A.

N.A.

R N.A.

N.A.

M(1)

N.A.

1, 2, 3

N.A.

R N.A.

N.A.

M(l)

N.A.

N.A 1, 2. 3.

4 M(l) 0(3)

1. 2. 3, 4 See Item 1.

above for all Safety Injection Surveillance Requirements.

See Item 2.a.

above for Manual Containment Spray Surveillance Requirements.

1, 2, 3, 4

M(1) 0 M(1)

N.A.

TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR MHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE CHECK CAIISEATttlll TEST TEST I-IIEIC TEST TEST TEST

~IS EE UIKEU SHEARON HARRIS - UNIT 1 3/4 3-42 Amendment No.

TABLE 4.3-2 Continued MODES FOR WHICH SURVE ILLANC

~IR RE UIRER N.A N.A.

1, 2, 3

N.A M(1, 2)

M(1. 2) 0(2)

1. 2, 3, ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP ANALOG ACTUATING CHANNEL DEVICE MASTER SLAVE CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST 3.

Containment Isolation (Continued) 3)

Containment S

R M

N.A.

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.

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 CHANNEI FUNCTIONAL UNIT 3.

Containment Isolation (Continued)

(2) Preentry Purge Detector c)

Airborne Particulate Radioactivity (1)

RCS Leak Detection (normal purge)

(2) Preentry Purge Detector 5)

Manual Phase A Isolation 4.

Main Steam Line Isolation a.

Manual Initiation

b. Automatic Actuation Logic and Actuation Relays

c. Containment Pressure--High-2 See Table 4.3-3, Item 1b2. for surveillance requirements.

See Table 4.3-3, Item 1C1, for surveillance requirements.

See Table 4.3-3, Item 1C2. for surveillance requirements.

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

N.A.

N.A N.A.

N.A R

N.A.

1, 2, 3, 4

H(1)(4)

M(1) 0

l. 2. 3, 4

N.A.

1, 2, 3

TRIP ANALOG ACTUATING NODES CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION REl AY RELAY SURVEILLANCE CHECK CAI IAIIATIOATEST TEST I OSIC TEST TEST TEST

~IS AE HIKES SHEARON HARRIS - UNIT 1 3/4 3-44 Amendment No.

TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS MODES R SLAVE FOR WHICH RELAY SURVEILLANCE TEST IS RE UIRE e Requirements.

N.A.

3**. 4 N.A M(1)

Q N.A N.A.

N.A.

1, 2

,...,,, e M(1) 0 1, 2.

3 N.A.

M(1)

N.A N.A N.A N.A 1,

2

~

3 N.A TRIP ANALOG ACTUATING CHANNEL DEVICE MASTE CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST 4.

Main Steam Line Isolation (Continued) d.

Steam Line Pressure--Low See Item l.e.

above for Steam Line Pressure--Low Surveillanc

e. Negative Steam Line Pressure S

R M

N.A.

Rate--High 5.

Turbine Trip and Feedwater Isolation

a. Automatic Actuation Logic and N.A.

N.A.

M(1) 1, 2

Actuation Relays b.

Steam Generator Water S

R M

N.A.

Level--High-High (P-14)

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

6.

Auxiliary Feedwater a.

Manual Initiation N.A.

N.A.

R

b. Automatic Actuation and N.A.

N.A N.A.

Actuation Relays c.

Steam Generator Water S

R M

N.A.

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 CHANNEL FUNCTIONAL UNIT 6.

Auxiliary Feedwater (Continued)

Trip of All Main Feedwater Pumps Start Motor-Driven Pumps g.

Steam Line Differential Pressure--High Coincident With Main Steam Line Isolation (Causes AFW Isolation)

?.

Safety Injection Switchover to Containment Sump a.

Automatic Actuation Logic and Actuation Relays b.

RWST Level--Low-Low Coincident With Safety Injection 8.

Containment Spray Switchover to Containment Sump a.

Automatic Actuation Logic and Actuation Relays N.A.

N.A.

N.A 1,

2 N.A.

N.A.

Q(3) 1, 2, 3

I See Item 4. above for all Main Steam Line Isolation Surveillance Requirements.

N.A.

M(1)

Q(3) 1, 2, 3.

4 S

R M

N.A.

Q(3) 1, 2. 3.

4 See Item l. above for all Safety Injection Surveillance Requirements.

N.A.

M(1)

Q(3) 1, 2, 3. 4 TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHIC CHANNEL CHANNEL OPERATIONAL OPERATIONAI ACTUATION RELAY RELAY RRVEILLANCE CHECK CAIISSATIEH TEST TEST I ESIC TEST TEST TEST

~IS IIE IIIEII 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 OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY RRVEILLANCE CHECK CAI ISIIATIIIE TEST TEST CASES TEST TEST TEST

~IS SE ISEC N.A.

N.A.

1. 2, 3. 4 N.A.

R N.A.

N.A.

1, 2. 3, 4 N.A N.A N.A M(l)

N.A.

1, 2, 3 M(l)

N.A.

1, 2, 3 M(l)

N.A.

1, 2. 3 CHANNEL FUNCTIONAL UNIT 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.

M*

N.A.

Undervoltage--Primary b.

6.9 kV Emergency Bus N.A.

M*

N.A.

Undervoltage--Secondary 10.

Engineered Safety Features Actuation System Interlocks a.

Pressurizer Pressure.

P-11 N.A.

R M

M(1)

Not P-11 N.A.

R M

M(1) b.

Low-Low T,~, P-12 N.A.

R M

M(l)

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 OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE CHECK CAI TRIIATIOE TEST TEST lOGIC TEST TERT TEST

~IS RE HIRER N.A.

N.A.

1,2.3 CHANNEL FUNCTIONAL UNIT 10.

Engineered Safety Features Actuation System Interlocks (Continued)

c. Reactor Trip, P-4 N.A.

N.A.

R N.A.

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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 0.02 hours 1.190476e-4 weeks 2.7396e-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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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.

h f

ML18012A636

Text

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