ATTACHMENT 2 TECHNICAL SPECIFICATION MARKUPSPower Range , Neutron Flux 4 2 • 3 1 • 2 2' High Positive Rate 4. Power Range, Neutron Flux, 4 2 High Negative Rate 3 1 • 2 2' -w

... •

:3 1==1(>'~ l :~: 05000272

PDC

ATTACHMENT 2

TECHNICAL SPECIFICATION

MARKUPS

·'

Vl

TABLI: 3.3-1 );:> r - - - - - -ITl 3:

REACTOR TRIP SYSTEM INSTRUMENTATION c

MINIMUM z ~

TOTAL NO. O~ANNELS CHANNELS APPLICABLE -i

FUNCTIONAL UNIT Of CllANNELS TO TRIP OPERABLE MODES ACTION --- -3• 4* J. ~-l. Manual Reactor Trip 2 2 1 • 2,~ 12

2. Power Range. Neutron flux 4 2 3 1 • 2 2* 3. Power Range, Neutron flux 4 2 3 1 • 2 211 High Positive Rate

4. Power Ran9e. Neutron Flux. 4 2 3 l • 2 2' w High Negative Rate ....... .p.

3* 4*)a..d ~if w 5. Intermediate Range. Neutron Flux 2 2 1 • 2) 1lftd-* 3 I

N

6. Source Range, Neutron Flux ~ fl' !) .. u ¥:,3 '4 ) a...d A. Sta Ftt1p Co.,,h'Ol Roel Or1ic Sys+~ 2 1 2 2 an 4 B. Shutdown E~rr.J1~•0 2 0 1

)

5 3, 4 and 5 7. Overtemperature l\T

2* Four Loop Operation 4 2 3 1 • 2 Three Loop Operation 4 1 ** 3 l • 2 9

8 . Overpower L\T

2* Four Loop Operation 4 2 3 l • 2 Three Loop Operation 4 l** 3 l • 2 9

9. Pressurizer Pressure-Low 4 2 3 J • 2 6# . 10. Pressurizer Pres sure- -It i gh 4 2 3 l • 2 6#

'·

TABLE l.1-1 (Conttnued) Vl ~ ' r REACTOR TRIP SYSTEM INSTltlffNTATIOH fll 3:

HINIHllt c TOTAL NO. CHANNELS CHANNELS APPLICABLE :z fUHCTIOHAL UNIT Of CHANNELS TO TRIP OPERABLE HODES ACTION ~ -.. - - · .....

IL Pr•••urtzer Water Level--Htgh l 2 2 1 I 2 1'

12. Los• ot flow - Single Loop l/loop 2/loop tn 2/loop tn l 1' (Above P-8) •ny oper- Heh oper-

•ting loop •ttng loop

13. Loss ot flow - Two Loopi l/loop 2/loop tn Z/loop l 1' w (Above P-7 •nd below P-8) two oper-· Heh oper-- Attng loopi •ting loop ~

w 1' l 14 . Stea. Generator Water l/loop 2/loop tn 2/loop. tn l, 2 w

Leve1--Low-low 1ny oper- Heh o~er 1tlng )oopi •ting oop

15. Steaa/feedwater flow 2/loop-1evel I/loop-level I/loop-level l, 2 1' Hl•••tch •nd Low Steaa .nd cot net dent 1nd Generator Water level 2/loop-flow wt th 2/loop-flo'W

•hliatch I/loop-flow •hutch or •i•utch tn 2/1oop-level iMe loop And

l/1oop-tlow •h•atch

16. Undervoltage-leactor Coolant 3 6, Puiaps 4-l/bus l/2 twice

l7. Undertrequency-Aeactor Coolant 3 r/' PUllpS 4- 1/bus l/2 twice

c :z ...... -I

w -"""' w I ......

N

TABLE 4.l-1 (Continued)

REACTOR TRlP.J:i}'STEH lNSTIWHENTATION SURVEILLANCE REQUIREMENTS

FUNCTIONAL UNIT

13. Loss of Flow - Two Loops

14. Steam Genecatoc Water Level-Low-Low

15. Steam/Feedwatec Flow Mismatch & Low Steam Gene1· ~tor Water Level

16. Undervoltage - Reactor Coolant Pumps

17. Underfrequency - Reactor Coolant Pumps

18. Turbine Trip A. Low Autostop Oil Pressure B. Turbine Stop Valve Closure

19. Safety Injection Input from SSPS

20. Reactor Coolant Pump Breaker Position Trip

21. Reactor Trip Breaker

22 . Automatic Trip Logic

CHANNEL CHECK

s

N.A.

N.A.

N.A. N.A.

N.A.

N.A.

N.A.

N. A.

CALI BRAT ION

R

R

R

H

R

N.A. N.A.

N.A.

N.A.

N.A.

N.A.

CHANNEL FUNCTIONAL

TEST

N.A.

H

H

H

S/U(1) S/U(1)

H( 4)

R

S/U( 10), H( 11, 13), SA(12,13) and R(14) H(5)

HODES IN WHICH SURVEILLANCE

REQUIRED

1, L

I, 2

1

1, 2 1, 2

1, L

N.A.

c: 7.

t.J -.... .p.

...... I

N 0 ~

)> 3 il)

::J a. 3 11> ::J rt-

:z 0

Ul m

TABLE 3.3-3 (Conttnued) I

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRU~f~TAT!ON TRIP SETPOINTS

FUNCTIONAL UNIT

8. AUXILIARY FEEOWATER

a • Autom~ttc Actuation Logic **

b. Manual I n I ti a ti on

c. Steam Generator Water Level--Low- Low

1. Start Motor Ortven Pumps

11. Start Turbine-Or1 ven Pumps

d. Undervoltage - RCP Start Turbine-Driven Pump

e. s. I. Start Hotor-Or1 ven Pumµs

f. Emergency Trip of Steam Generator f eedwaler Pumµs Starl Motor Ori ven Pumps

g. St at I on B I a ck 011 L

"•App Ii es l o i l ems ( .i 1111 ti.

rnr AL MO. Of CP.ANNELS

2

I/pump

3/stm. gen.

3/stm. gen.

4(1/bus)

See I above (All

2(1/pump)

ptAN~1H. S lf(l r~~r

~ /~u:r.,> .

. 2/stpi. gen.

MINIMUM CHANNELS OPERABLE

2

I/pump

2 stm. ?en.

2/stm. gen. 2 stm. gen.

1/2 x 2 3

.. S.I. tnttlating functions

2 2 ( l /jJUIUjl)

See 6 and 7 above (SEC and U/V Vital Bu s )

and

APPLICABLE HODES

1. 2. 3

l • 2. 3

l. 2. 3

l. 2 . 3

l. 2

requirements)

®

ACT ION .

20

22 ]

14*

14*

19

21

• TABLE 3.3-3 (Cont i nued )

AC TION 13 - Wf t h t he number of OPERABLE Channels one less t han : he 7ota 1 Number of Channels, STARTUP and/or POW ER OP:RAT tO N may proceed prov i ded the following condit i ons are sat i sf i ed :

a. The inoperable channel· is placed in the tripped cond i t i on within l hour.

b. The Minimum Channels OPERABLE requirements is met; however, one additional channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.l.l

ENGINEERED SAFETY FATURES INTERLOCKS DESIGNATION CONDITION ANO ·SETPOINT FUNCTION

P-11

P-12

With 2 of 3 pressurizer pressure channels > 1925 psig.

With 3 of 4 Tavg channels > 545°F.

P-11 prevents or defeats manual block of safety injection actuation on low pressurizer pressure.

P-12 prevents or def eats manual block of safety injection actuation high steam line flow and low steam line pressure.

With 2 of 4 Tavg channels Allows manual block of safety < 541°F. injection actuation on high

steam line flow and low steam line pressure. Causes steam line isolation on high steam flow. Affects steam dump blocks.

ACTION 20 - · With the number of OPERABLE channels one less than the Total Number of Channels, be in at least HOT STANDBY within 6 hours and in at least HOT SHUTDOWN within the following 6 hours; however, one ~hannel may be bypassed -for up to hou~t.for surveillance testing. ~ (.§)

ACTION 21 - With the number of OPERABLE channels one less than the Minimum Number of Channels, operation may proceed provided that either:

a. The inoperable channel is restored to OPERABLE within 72 hours, or

b. If the affected Steam Generator Feedwater Pump is expected to be out of service for more than 72 hours, the inoperable channel is jumpered so as to enable the Start Circuit of the Auxiliary Feedwater Pumps upon the loss of the other Steam Generator Feedwater Pump.

ACTION 22 - With the number of OPERABLE channels relating directly wi th the number of OPERABLE auxiliary feedwater pumps, the ACTIONS of . L.C.O. 3.7.l.2 apply.

SALEM - urHT l ' 3/4 3-22 Arnendnent No. 56

c z - t

w I w w

):>

3 11> ::I 0. ..,, '1> ::I rt

:z 0

U1

°'

.,..

TABLE ~.3-2 (Copt1hued}

, . . ' ~ ....

ENGINEERED SAFETY FEATURE ACTUATION s•1s1r.:;-.1 H"SHlUHEtH~TION TRIP SETPOINTS .·SURVE lllM!CE R~QU ~ flEMf HTS

CHANNEL CHANNEL CHANNEL FUNCTIONAL

f UNCT IONAL UN IT CHECK CALI ORI. T !ON TEST

8. AUXILIARY FEEOWATER

a. Automattc Actua.tton ~ogk N.A.· ·M.A. H(2).

b. Manual lnH talion N.A. ~.A. H(4)

c. Steam Generator Water s .:R H Level--Low-Low

d. Undervoltage - RCP s R H(2)

e. S. I. See 1 above (A:! S.I. survet l lance requtrements)

t. Emergency Trip of Steam Generator Feedwater Pumps N.A. ~) ~A. R

g. Station Blackout See 6b and 7 ~hove (SEC and U/V Vital eus)

..

HODES · IN WHIClt SIJRVE ILLANCE e itEgUIREO

'

l • 2 .. 3

I I 2, 3 ] 1 I 2, 3

l I 2

8

_,,. .

.. - ,.J

Ul )::.> TABLE 3.3-1 r S2

REACTOR TRIP SYSTEM INSTRUMENTATION c: z MINIMUM ...... -l TOTAL NO. CHANNELS CHANNELS APPLICABLE N FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

3* 'I •o....J. S'+ 1. Manual Reactor Trip 2 1 2 1, 2, amtJ 12

2. Power Range, Neutron Flux 4 2 3 1 • 2 2'

3. Power Range , Neutron Flux 4 2 • 3 1 • 2 2' High Positive Rate

4. Power Range, Neutron Flux, 4 2 High Negative Rate

3 1 • 2 2' 311' "l * .,.,.J ~¥ w -~ 5. Intermediate Range, Neutron Flux 2 1 2 1. 2. ilftd-*- 3

w I

3*4'*"~S' .. N 6. Source Range, Neutron Flux A. St artyt1 Co'n ~r~l l?txl lJrlr~ S!J.s;:; 2 1 2 2''. amt-*- 4 B. Shutdown eA.>et;Jil 2 0 1 3, 4 and 5 5

7. Overtemperature AT 6, I Four Loop·Operation 4 2 3 1 • 2 .

Three Loop Operation 4 1** 3 1 • 2 9

8 . Overpower AT 6, I

e four Loop Operation 4 2 3 1, 2 Three loop Operation 4 1** 3 1, 2 9

9. Pressurizer Pressure-Low 4 2 3 1 • 2 6, 10. Pressurizer Pressure--High 4 2 3 1 • 2 s'

Vl TABLE 3.3-l (Continued) ):o

' !i! REACTOR TRIP SYSTEM INSTRUMENTATION

c MINIMUM :z TOTAL NO . CHANNELS CHANNELS APPLICABLE ......

-t FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE HODES ACTION N

l l. Pressurizer Water Level--High 3 2 2 j • 2 1* 12. Loss of fl ow - Single Loop 3/loop 2/loop in 2/loop in 7#

(Above P-8) any oper- each oper-ating loop ating loop

13. Loss of Flow - Two Loops 3/loop 2/loop in 2/loop l 7'' w (Above P-7 and below P-8) two oper- each oper-- ating loops ating loop ~

w

1' I 14. Steam Generator Water 3/loop 2/loop in 2/loop in l • 2 w Level--Low-Low any oper- each oper

ating loops ating loop

15. Steam/feedwater Flow 2/loop-level l/loop-level l/loop-level l • 2 7# Mismatch and Low Stea• and coincident and Generator Water Level 2/loop-flow with 2/loop-flow

mismatch l/loop-flow mismatch or •is11atch in 2/loop-level same loop and

l/loop-f Jow mismatch

16. Undervoltage-Reactor Coolant 6# Pumps 4-1/bus 1/2 twice 3

17. Underfrequency-Reactor Coolant 3 611 Pumps 4-1/bus 1/2 twice

N I s doo1 3l6UJS - "'1IJ Jo sso1 ·zt .., "'

l • 1 N I s q6J"--13A31 J31'" J3lJJnSS3Jd . ti • : .. • 1 l N I s ·q6t"--3JnSS9Jd J8lJJnSS3Jd ·01 c

' l . ' N I s ""11--3JnSS9Jd J8lfJnSS3Jd ., i l . ' l V J8MOdJ8AO

.t M I s •g

l • t M • s t V9Jn1•J••1J•AO •t

~{l. Cj " • " 't 'l (t)n/s put M (9)1 (l)s xnfJ uoJ1ng11 •e&ut1 "'Jnos ., -r-"'7 .....

._J).Utl ( l • ' (t)n/s (9)1 xnu "J1""" ..... s ' i'".5 ~ '\'h ( 'i~ •e&u•1 •1•JPlll.l81UI •g M

~ ....... l • t " (9)1 ., ... .

•1•1 ""' 1'6811 "''" M

•xntJ uoJ1ne11 •e&u•1 J8flt0d •• l ., M (9)1 ·y·11 . ~1•1 ""'1''°" "''" •xntJ uoJ1n•11 •e&U•I J3"0d ·c

-- (9)b , .. l • ' N . (t)N • (Z)O s xntJ uoJ1ne11 •86ut1 J8flt0d ·z ·v·N (6)n/s ·v·11 ·v·11 q'1JMS dtJl J01''31 t•nU'N . t

CJJlltnhJll lSU NOIJYlll lYJ ~J)ft:J llffn lVNOl l:JNOJ N

]JNYT1111U1nS lVNOIJJNnJ llNNYHJ .... .... ID111'1 NI s:mow llNtmtJ :I!:

:::>

SlNJMlUrifiJI l:JNY111lft11f1S NOllY1NMUUSNI MUSAS dUfl lfOlJVllf ra 1-c·• Jl&Yl

_, ct;

"' ..

TABLE 4.3-1 {Continued! l/l

RFACIDU TIUP ;;?YS'J'9! : .lNSTRlJMEN'l'A'I' lUN SURVEI LLANCE f@J_I H~J1'flli • )> r

~ rri 3:

CHANNEL MODES IN WHICH c CllANN EL FUNCTIONAL SURVEILLANCE :z FUNCTIONAL UNIT CHECK __ CALIBRATION TEST REQUIRED -i

N B. Loss of Flow - Two Loops s R N.A .

14. Steam Generator Water Level -- s I< M 1 t 'l. Low- Low

15 . Steani/Feedwa te1 Flow Misaiatc h & s R M I, l

Low Steam Generator Wat e r Level

16. Unde rvoltage - Re.1c tor Coolant N. A. M w - Pumps ~

w I 17. Underfrequency - Reactor Coolant N. A. R H ~

N Pumps

18. Turbine Trip a . Low Autostop Oil Pressure N.A. N.A. S/U( 1) N.A. b. Turbine Stop Valve Closure N. A. N.A . S/U( 1) N.A.

19. Safety Injection Input from SSPS N. A. N.A. M( 4) 1. .!. )>

~ 20. Reactor Coolant Pump Breaker N. A. N.A. R N.A. :l a. Position Trip

,. 3 Ill

l 'l*," *1o-..J._5* :l

rt 21. Reactor Trip Breaker N.A . N.A. S/U( 10), 1 t 2 anti * :z H( 11, 13), 0 . SA(12,13) ...... and R(14) ~

13"fri 11 , c..- ..($"11.

22 . Automati c Tr ip Logi c N. A. N.A. H( 5) 1 , 2 4lfl1't-'*'

c :z ...... -j

N

TABLE l.l~l (Conitnued)

ENGINEERED SAFETY FEATURE ACTUATION SVSTEH INSTRlltENTATION

FUNCTIONAL UNIT

8. AUXILIARY FEEOWATEI

a. Autoaattc Actuatton logtcu

b. Manual lntttatton

c. Sta. Gen. Water level-Low-Low

t. Start Hotor Driven Pu.ps

tt. Start TurbtneOrt ven Pumps

d. Undervoltaoe-RCP Start TurbfneOrlven Pump

e. s. I.

TOTAL HO •. Of CllANHELS

2

l/pu1ap

l/st•. gen

l/sta. gen.

4-1/bus

HIHIHUH CtlAHHELS ·. CllAHHELS TC!_ TR~ . ·OPERABLE

1 2

l/pu•p l/puap

2/st•. gen. -· · 2 st.. gen. any 1t.. gep.

• 2/5la. gen • . ·. 2 il•. gen. any 2 sta. gen.

1/2 x 2 l

APPLICABLE K>OES

1; 2. l

1. 2. 3

' 1. 2. l

1. 2. l

1, 2

ACI JOH

20

23

14"

19

Start Hotor~ Driven Pumps See 1 above (All S. I. Initiating functions and requh-e•ents)

t · TriJl ot Hain Feedwater PuJ111•s Start Holor-Orlvcn P~ian1as 2/Pump

**Appli es t o Items c and d.

.· ~~ 1 , 2

.. .. 2(1 /pump J

_ I

e

]

. '

' .

TABLE 3.3-3 (Continued)

ACT ION 19 - With the number of OPERABLE Channels one less than t he To t al Numcer of Channels, STARTUP and/or POWER OPERATION may proc eed provided the follO'Wing conditions are satisfied:

DESIGNATION

P·l 1

I : ·P-l2

1 . The inoperable chann1l is placed in the tripped condition within 1 hour.

b. The Minimum Channels OPERABLE requirements is met; ho~ever , one additional chann1l may be bypass1d for up to Z hours · for surv1ill1nc1 testing per Specificaticn 4. 3.Z. 1.

ENGINEERED SAFETY FEATURES INTERLOCKS CONDITIOH ANO SETPOIHT FUNCTION

With 2 of 3 pressurizer pr9ssure channels ~ 19Z5 psi;.

With·-3 ."of 4 :r~v· 9

. C:h4'nnels > ·54s.•F. . • . -With 2 of 4 T

1vg ehannels

< 5-i1°F.

P-11 prevents or defea~ manual block of safety inj1ction actuation on lO'tit pr9ssur1 ;1r preuur9 • ..

· : .. p.:12 · pr9vents :or· defeats : manual 'block of safety 1njec~1on . ac:tuat1on high steam line flow and low st11J11 line pressure.

• Allows manual block of safety injection actuation on high st1111 line flow and low steam line .pressure. Causes steam line isolation on high steam flow. Affects steam dump blocks.

ACTION ZO - With the numeer of OPERABLE c~annels ont less than t~e Total Number o·f Channels, be in at least HOT STANOBY within 6 hours

· and in at 11.ast MOT SHUTOOWN within th• following 6 hour~ however, one channel may be bypassed for up to hourJ for surveillance t1~ting provided the other chan 1 is OPERABLE.

ACT!OH Zl - ~1th the number of OPERABLE channels one less han the Total Humeer of Channels, restore the inoperabl1 channel to OP:RASLE s~tus within 48 hours or be in at least HOT STANOBY with i n 6 hours and in HOT SHUTOO'WN within the following 6 hours.

ACTION 22 - With the number of OPERABLE channels one less than the Minimum Channe1s OPERABLE, operation may praceed until performance of the nex.t required CHANNEL FUHCTlONAl TEST.

ACTION 23 - With the number of OPERABLE channels relating directly wit h t he ] number of OPERABLE auxi l ·i ary feedwater pumps , the ACTIONs of L.C.O. 3.7.1.2 apply.

SALEH - UNIT 2 3/4 3-ZJ Amendment No. 24

• '

I' ••

I~se-RT A ?~ 3/4 3-23

Ac+·,ou tt

With the number of OPERABLE channels one less than the Minimum Number of Channels, operation may proceed provided that either:

a . The inoperable channel is restored to OPERABLE within 72 hours, or


TABLE 3.3-6 (Cont inued )

TABLE NOTATION

ACTION 23 - With the number of channels OPERABLE les1 than required by the Minimu~ Channels OPERABLE requirement, perfonn area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours.

ACTION 24 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply wiJh the ACTION requirements of Specification 3.4.,,6.l.

7 ACTION 25 - With the rl.l~ber of channels OPERABLE less than

required by the M1n1111Jm Channels OPERABLE requirement~ comply with the ACTION requirements of Specification 3.9.9.

ACTION 26 - With the number of OPERABLE Channels' 1 ess than required by the Mini""m Channels OPERABLE requirements, initiate the preplanned alternate method of 111>nitoring the appropriat• parameter(s), within 72 hours, and:

SALEM - UNIT 2

1) either restore the inoperable Channel(s) to OPERABLE status within 7 days of the event, or

2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken·, th• cause of the inoperabi11ty and the plans and schedule for restoring the system to OPERABLE status.

3/4 3-40 Amenmnent No. 53

• REACTOR COOl.Ml' SYSTEM

OPERAilOML WJCAGE LIMmNS CONDMOI FOR OPERATION

3.4. 7.% Ructor Coolant. Sy1U. leakage shall be 11•ttad to:

a.

b. 1 GPM UNIDEHTIFIED LEAICAGE,

c. 1 GPM total pri•ry-to-secondary leakage throUGfl all sta• generators and 500 ga 11 on1 per day through any one sta• generato .. ,

d. 10 GPM IDEHTIFIED LEAJCAG£ fra11 the Reactor Coolant SysU., and

•· 40 GPM CONTROUED L.EAICAG£ at a Ructor Coolant. System p1"811ure of 2230 j: zo Pl f g.

1. 1 GPM lHlcage at a Ructor Coolant. Sy1U. pre11UN of 2230 + 20 ps1g . ,.,._ any Raector Coolant. System '"91ure Iaolat.fon Valve spicffied

.. · · · fn Table,. 3.4-1. ~ •Yi

APPUCAIIUTY: MODES. l,· 2, 1 and 4. · ~ v

ACTIOll:

a.

b.

Wftb any PRESSURE BOUNDARY w.m .. be· fn at. 1 ... t HOT STANDBY witbfn I -hours ~· fn COLD SHUTDCM·with1n tM _fo110Wfhg 30 hou1"S.

Wf tb any ReKtor Cootan• System lHJcage greatar than any one of th• above lfsttl, excluding PRESSURE BOUNDdY LEAICAGE and leakage froa

. RHctor Coolant System PN11ure I~Tat.fon Yahn,. 1"8duc• the leauge 'l"IU to within lf•ftl witbfn 4. houn OP be 1n at 1Htt HOT STANDBY wi tltf n the nut I houn and t n COLD SHUTDCMt wt tht n the fo 11 aw1 ng 30 ....... .-... .. .. .... .. ! ~ - ' f • .J

... ........ 9\. t ,,,,,_ l ! • • ~ . .. . . ~ .. ~ f '

Wftb _, IMctor: Coolant Sy1U. PNlmre ·Itolat<ioft: Vahe ltalcage grHter .UMtft the above lfllit., t.aolate the llfgb- pressure po'l"tion of tlte atfect.A _sysU. fra11 u.. la. p1"ellU"1 pol"tfon within 4 hours by

. Ille of at 1 ... t. two closed lllnUal o .. deactivated autallatic valves, .. .: 01' be tn. at. leut HOT STANDBY within the 11Ut 6 hours and in COLD

: .SllUTDCMI within the following 30 houn. , · ".

SURYEILLMCI AEQUIREMEHTS

•I 4.4. 7.2V Reactor Coolant Systall leakages shall be dMantt'l"ated to b• within each of tM above lf •f ti by;

a. Monftorf ng the cantaf nllef1t atllosphere pal"tf culata radioactivity 110nftor at least once per l2 hours.

b. Mon1to'l"fng. the conuh,..nt sump inventory at least once per 12 hours.

SALEM - UNIT 2 3/4 4-17

• . ___ , _____ _

-

• REACTOR COOLANT SYSTEM

SURVEILLANCE REQUIREMfNTS (Continued) I

c.

d.

Measurement of the CONTROLLED LEAKAGE from the reactor coolant pump seals at least once per 31 days when the Reactor Coolant System pressure is 2230 t 20 psig and valve 2CV71 is fully closed ,

Performance of a Reactor Coolant Syste11 water inventory balance <\l

least once per 72 hours. The water inventory balance shall be performed with the plant at steady state conditions. The provisions of specification 4.0.4 are not applicable for entry into Mode 4, and

e. Monitoring the reactor head flange leakoff system at least once per 24 hours.

· 2. 4.4.7.2Y Each Reactor Coolant Syste• Pressure Isolation Valve specified in Table 3.4-1 shall be demonstrated OPERABLE pursuant to Specification 4. 0. 5, except that in lieu of any leakage testing required by Specification 4.0 . S, each valve shall be de110nstrated OPERABLE by verifying leakage to be within its limit:

a. At least once per 18 months.

b. Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 72 hours or more and if leakage testing has not been performed in the previous 9 months.

c. Prior to returning the valve to service following maintenance repair or replacement work on the valve.

d. For the Residual Heat R111<>val and Safety Injection Systems hot and cold leg injection valves and accumul~tor valves listed in Table 3.4-1 the testing will be done within 24 hours following valve actuation due to auta11atic or mAnual action or flow through the valve. For all other syste•s testing will be done once per refueling.

The provisions of specification 4.0 . 4 are not applicable for entry into MODE 3 or 4.

SALEM - UN IT 2 3/4 4-18 Amendment No. 27

I _J

. \

• · e

REACTOR COOLANT SYSTEM

VALVE NO .

21SJ43 22SJ43 23SJ43 24SJ43 21SJ55 22SJ55 23SJ55 24SJ55 21SJ56 22SJ56 23SJ56 24SJ56 21SJ17 22SJ17 23SJ17 24SJ17 2SJ15(} 21SJ139. 22SJ139J 23SJ139 24SJ139: 21SJ156.' . 22SJ156 23SJ156 24SJ156 21SJ144 22SJ144 23SJ144 24SJ144 2RH1 2RH2 23RH27 24RH27

SALEM - UN IT 2

TABLE 3.4-1

REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES ·

FUNCTION

Safety Injection (L.P. froa RHR Pumps to Cold Legs) Safety Injection (L.P. frOll RHR Pumps to Cold Legs) Safety Injection (L.P. froa RHR Pumps to Cold Legs) Safety Injection (L.P. f~ RHR Pumps to Cold Legs) Safety Inject.ion (AccU11Ul ator Discharge to Co 1 d Legs) Safety Injection (AccU11Ulator_ Discharg• to Cold legs) Safety Injection (AccU11Ulator Discharge to Cold Legs) Safety Injection (Accumla~r Discharge .~ Cold Legs) Safety Injection (Accmulator Dhcharge tO Cold Legs) Safe~~ Injection (Acca.Ula~r-. Di;charge t0'. Cold Legs):. Safety Injection (AcctmUlator Discharg "to .ColdfLegs) Safety. Injection (Accumtlator D1sch4rge. to Col cl Lags) Safety Injection. (Boron Inject.ion to Cold Lags') , - .

. . .~ t Safety Injection (Boron Injection to told. egs) · - ' ·

Safety Injection (Boron Injection to Cold Legs) Safetx Injection (Boron Injection to Cold, Legs.)._ Safety Injection (Boron Injection to Co.ld Legs)-• ~ ..,- . .. .._

.:. s.re~ . IhJect on. CH,. p:, f~ S.I'. Puiip ·:to Hot_ ~~sJ .... . :-: Slfety. lnJM:tion (tt. P. 51' PulP .tct· HO Legs) ··; .1 •

~ .. ,;I ~ • ... .,. ' .. 1 ,.f.,;

S&fitY.J i\IKtioli (~.J.~ f~ , PUllPI to;1fot· Legs) : ' ~ : Saf.ty Inject1oft! (H •• fra." SI P.-·-to· Hot 'legs}.· y

S&fetj Injection (H.P. frOt1 SI Pumps to Hot Legs) Safety Injection (H.P. from SI PUllps to Hot Legs) _ Safety_ Injection (H-; P. fro11 SI PUllPS to--Hot ltgs) .-.: -Saftty Injection (H.P. frot1 SI PUlllPS to Hot Legs) C.OL D Saf1ty Injection (H.P. from SI Pulips to Saf1ty Injection (H.P. fro• SI Pumps to Safety Injection (H.P. frOll SI Pumps to Safety Injection (H.P. from SI Pumps to RHR Suction f rom Hot Leg Ho. 21 RHR Suction from Hot Leg Ho . 21 RHR Discharge to Hot Leg No. 23 RHR Discharge to Hot Leg No. 24

3/4 4-19

:

....

ATTACHMENT 3

TECHNICAL SPECIFICATION

CORRECTED PAGES

TABLE 3.3-1

REACTOR TRIP SYSTEM INSTRUMENTATION

MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

1. Manual Reactor Trip 2 1 2 1, 2, 3*, 4* 12 and 5*

2. Power Range, Neutron Flux 4 2 3 1, 2 2#

3. Power Range, Neutron Flux 4 2 3 1, 2 2# High Positive Rate

4. Power Range, Neutron Flux, 4 2 3 1, 2 2# High Negative Rate

5. Intermediate Range, Neutron Flux 2 1 2 1, 2, 3*, 4* 3 I and 5* 6. Source Range, Neutron Flux

A. Control Rod Drive System Energized 2 1 2 2##, 3*, 4* 4 r and 5*

B. Shutdown 2 0 1 3, 4 and 5 5

7. Overtemperature 6.T Four Loop Operation 4 2 3 1, 2 2# Three Loop Operation 4 l** 3 1, 2 9

8. Overpower b.T Four Loop Operation 4 2 3 1, 2 2# Three Loop Operation 4 l** 3 1, 2 9

9. Pressurizer Pressure-Low 4 2 3 1, 2 6#

10. Pressurizer Pressure--High 4 2 3 1, 2 6#

SALEM - UNIT 1 3/4 3-2 Amendment No.





11. Pressurizer Water Level--High 3 2 2 1, 2 7#

12. Loss of Flow - Single Loop 3/loop 2/loop in 2/loop in 1 7# (Above P-8) any aper- each aper-

ating loop ating loop

13. Loss of Flow - Two Loops 3/loop 2/loop in 2/loop in 1 7# (Above P-7 and below P-8) two oper- each oper-


14. Steam Generator Water Level-- 3/loop 2/loop in 2/loop in 1, 2 7# Low-Low any oper- each oper-


15. Steam/Feedwater Flow Mismatch 2/loop-level 1/loop-level l/loop-level 1, 2 7# and Low Steam Generator Water and 2/loop- coincident and 2/loop-Level flow mismatch with flow mismatch

l/loop-flow or 2/loop-mismatch in level and same loop l/loop-flow

mismatch

16. Undervoltage-Reactor Coolant Pumps 4-ljbus 1/2 twice 3 1 6# I e 17. Underfrequency-Reactor Coolant Pumps 4-1/bus 1/2 twice 3 1 6# I


.• TABLE 4.3-1 .

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS ,.,

CHANNEL MODES IN WHICH CHANNEL FUNCTJ;ONAL SURVEILLANCE

FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

1. Manual Reactor Trip Switch N.A. N.A. S/U(9) N.A.

2. Power Range, Neutron Flux s D(2), M(3) M 1, 2 and Q(6)

3. Power Range, Neutron Flux, N.A. R(6) M 1, 2 High Positive Rate

N.A. R(6) M 1, 2 4. Power Range, Neutron Flux,

High Negative Rate

5. Intermediate Range, Neutron Flux s R(6) S/U(l) 1, 2, 3*, 4* and 5*

6. Source Range, Neutron Flux S(7) R(6) M and S/U(l) 2, 3, 4, and 5

7. Overtemperature ~T s R M 1, 2

8. Overpower b..T s R M 1, 2

9. Pressurizer Pressure--Low s R M 1, 2

10. Pressurizer Pressure--High s R M 1, 2

11. Pressurizer Water Level--High s R M 1, 2

12. Loss of Flow - Single Loop s R M 1

SALEM - UNIT 1 3/4 3-11 Amendment No. ·


REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS

FUNCTIONAL UNIT


14. Steam Generator Water Level-Low-Low

15. Steam/Feedwater Flow Mismatch & Low Steam Generator Water Level

16. Undervoltage - Reactor Coolant Pwnps

17. Underfrequency - Reactor Coolant Pwnps

18. Turbine Trip A. Low Autostop Oil Pressure B. Turbine Stop Valve Closure


20. Reactor Coolant Pwnp Breaker Position Trip


22. Automatic Trip Logic

SALEM - UNIT 1

CHANNEL CHECK

s

s

s

N.A.

N.A.

N.A. N.A.

N.A.

N.A.

N.A.

N.A.

CALIBRATION

R

R

R

R

R

N.A. N.A.

N.A.

N.A.

N.A.

N.A.

3/4 3-12

CHANNEL FUNCTIONAL

TEST

N.A.

M

M

M

M

S/U(l) S/U(l)

M(4)

R

S/U(lO), M(ll,13), SA(l2,13) and R(14)

M(5)

MODES IN WHICH SURVEILLANCE

REQUIRED

1

1, 2

1, 2

1

1

1, 2 1, 2

1, 2

N.A.

1, 2, 3*, 4* and 5*

1, 2, 3*, 4* and 5*

Amendment No ..


ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION

FUNCTIONAL UNIT

8. AUXILIARY FEEDWATER

a. Automatic Actuation Logic**

b. Manual Initiation

c. Steam Generator Water Level-Low-Low

i. Start Motor Driven Pumps

ii. Start Turbine-Driven Pumps

d. Undervoltage - RCP Start Turbine - Driven Pump

TOTAL NO. OF CHANNELS

2

l/pump

3/stm. gen.

3/stm. gen.

4(1/bus)

CHANNELS TO TRIP

1

l/pump

MINIMUM CHANNELS OPERABLE

2

l/pump

APPLICABLE MODES

1, 2, 3

1, 2, 3

2/stm. gen. 2 stm. gen. 1, 2, 3

2/stm. gen. 2 stm. gen. 1, 2, 3

1/2 x 2 3 1, 2

ACTION

20

22

14*

14*

19

e. S.I. Start Motor-Driven Pumps See 1 above (All S.I. initiating functions and requirements)

f. Emergency Trip of Steam Generator 2(1/pump) Feedwater Pumps Start Motor Driven Pumps

2 2(1/pump)

g. Station Blackout See 6 and 7 above (SEC and U/V Vital Bus)

**Applies to items c and d.

SALEM - UNIT 1 3/4 3-20a

1, 2 21

Amendment No.

ACTION 19 -~ TABLE 3.3-3 (Continued~

With the number of OPERABLE Channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 1 hour.

b. The Minimum Channels OPERABLE requirements is met; however, one additional channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1.1

ENGINEERED SAFETY FEATURES INTERLOCKS DESIGNATION CONDITION AND SETPOINT FUNCTION

P-11

P-12

ACTION 20 -

ACTION 21 -

ACTION 22 -

SALEM - UNIT 1

With 2 of 3 pressurizer pressure channels > 1925 psig.

With 3 of 4 T channels > 545°F. avg

With 2 of 4 T channels < 541°F. avg

P-11 prevents or defeats manual block of safety injection actuation.on low pressurizer pressure.

P-12 prevents or defeats manual block of safety injection actuation high steam line flow and low steam line pressure.

Allows manual block of safety injection actuation on high steam line flow and low steam line pressure. Causes steam line isolation on high steam flow. Affects steam dump blocks.

With the number of OPERABLE channels one less than the Total Number of Channels, be in at least HOT STANDBY within 6 hours and in at least HOT SHUTDOWN within the following 6 hours; however, one channel may be bypassed for up to 2 hours for surveillance testing.

With the number of OPERABLE channels one less than the Minimum Number of Channels, operation may proceed provided that either: a. The inoperable channel is restored to OPERABLE within

72 hours, or

b. If the affected Stearn Generator Feedwater Pump is expected to be out of service for more than 72 hours, the inoperable channel is jumpered so as to enable the Start Circuit of the Auxiliary Feedwater Pumps upon the loss of the other Steam Generator Feedwater Pump.

With the number of OPERABLE channels relating directly with the number of OPERABLE auxiliary feedwater pumps, the ACTIONs of L.C.O. 3.7.1.2 apply.

3/4 3-22 Amendment No. 56


ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS

FUNCTIONAL UNIT

8 . AUXILIARY FEEDWATER

a. Automatic Actuation Logic


c. Steam Generator Water Level--Low-Low

d. Undervoltage - RCP

CHANNEL CHECK

N.A.

N.A.

s

s

CHANNEL CALIBRATION

N.A.

N.A.

R

R

CHANNEL FUNCTIONAL TEST

M(2)

M(4)

M

M(2)

MODES IN WHICH SURVEILLANCE REQUIRED

1, 2, 3

1, 2, 3

1, 2, 3

1, 2

e. S. I. See 1 above (All s. I. surveillance requirements)

f. Emergency Trip of Steam Generator Feedwater Pumps

g. Station Blackout

SALEM - UNIT 1

N.A. N.A. R

See 6b and 7 above (SEC and U/V Vital Bus)

3/4 3-33

1, 2

Amendment No.

•.

TABLE 3.3-1




1. Manual Reactor Trip 2 1 2 1, 2, 3*, 4* 12 and 5*

2. Power Range, Neutron Flux 4 2 3 1, 2 2#

3. Power Range, Neutron Flux 4 2 3 1, 2 2# High Positive Rate

4. Power Range, Neutron Flux, 4 2 3 1, 2 2# High Negative Rate

5. Intermediate Range, Neutron Flux 2 1 2 1, 2, 3*, 4* 3 and 5*

6. Source Range, Neutron Flux A. Control Rod Drive System 2 1 2 2##, 3*, 4* 4

Energized and 5* B. Shutdown 2 0 1 3, 4 and 5 5

7. Overtemperature 6,T Four Loop Operation 4 2 3 1, 2 6# Three Loop Operation 4 l** 3 1, 2 9

8. Overpower AT Four Loop Operation 4 2 3 1, 2 6# Three Loop Operation 4 l** 3 1, 2 9

9. Pressurizer Pressure-Low 4 2 3 1, 2 6#

10. Pressurizer Pressure--High 4 2 3 1, 2 6#




FUNCTIONAL UNIT

11. Pressurizer Water Level--High

12. Loss of Flow - Single Loop (Above P-8)

13. Loss of Flow - Two Loops (Above P-7 and below P-8)

14. Steam Generator Water Level--Low-Low

15. Steam/Feedwater Flow Mismatch and Low Steam Generator Water Level

16. Undervoltage-Reactor Coolant Pumps

17. Underfrequency-Reactor Coolant Pumps

SALEM - UNIT 2

TOTAL NUMBER CHANNELS OF CHANNELS TO TRIP

3 2

3/loop 2/loop in any oper-ating loop

3/loop 2/loop in two oper-ating loops

3/loop 2/loop in any oper-ating loops

2/loop-level l/loop-level and 2/loop- coincident flow mismatch with

l/loop-flow mismatch in same loop

4-1/bus 1/2 twice

4-ljbus 1/2 twice

3/4 3-3

MINIMUM CHANNELS APPLICABLE OPERABLE MODES ACTION

2 1, 2 7#

2/loop in 1 7# each oper-ating loop

2/loop in 1 7# each oper-ating loop

2/loop in 1, 2 7# each oper-ating loop

l/loop-level 1, 2 7# and 2/loop-flow mismatch or 2/loop-level and l/loop-flow mismatch

3 1 6#

3 1 6#

Amendment No.

1e I

TABLE 4.3-1


FUNCTIONAL UNIT

1. Manual Reactor Trip Switch

2. Power Range, Neutron Flux

3. Power Range, Neutron Flux, High Positive Rate

4. Power Range, Neutron Flux, High Negative Rate

5. Intermediate Range, Neutron Flux

6. Source Range, Neutron Flux

7. Overtemperature 6T

8 . Overpower 6 T

9. Pressurizer Pressure--Low

10. Pressurizer Pressure--High

11. Pressurizer Water Level--High

12. Loss of Flow - Single Loop

SALEM - UNIT 2

CHANNEL CHECK

N.A.

s

N.A.

N.A.

s

S(7)

s

s

s

s

s

s

CALIBRATION

N.A.

D(2), M(3) and Q(6)

R(6)

R(6)

R(6)

R(6)

R

R

R

R

R

R

3/4 3-11

CHANNEL FUNCTIONAL

TEST

S/U(9)

M

M

M

S/U(l)

M and S/U(l)

M

M

M

M

M

M


REQUIRED

N.A

1, 2

1, 2

1, 2

1, 2, 3*, 4* and 5*

2, 3, 4, and 5

1, 2

1, 2

1, 2

1, 2

1, 2

1

Amendment No.

t



FUNCTIONAL UNIT


14. Steam Generator Water Level-Low-Low

15. Steam/Feedwater Flow Mismatch & Low Steam Generator Water Level

16. Undervoltage - Reactor Coolant Pumps

17. Underfrequency - Reactor Coolant Pumps

18. Turbine Trip a. Low Autostop Oil Pressure b. Turbine Stop Valve Closure


20. Reactor Coolant Pump Breaker Position Trip


22. Automatic Trip Logic

SALEM - UNIT 2

CHANNEL CHECK CALIBRATION

s R

s R

s R

N.A. R

N.A. R

N.A. N.A. N.A. N.A.

N.A. N.A.

N.A. N.A.

N.A. N.A.

N.A. N.A.

3/4 3-12

CHANNEL FUNCTIONAL

TEST

N.A.

M

M

M

M

S/U(l) S/U(l)

M(4)

R

S/U(lO), M(ll, 13), SA(l2,13), and R(l4)

M(5)


REQUIRED

1

1, 2

1, 2

1

1

N.A. N.A.

1, 2

N.A.

1, 2, 3*, 4* and 5*

1, 2, 3*, 4* and 5*

Amendment No.


ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM

FUNCTIONAL UNIT

8 . AUXILIARY FEEDWATER

a. Automatic Actuation Logic**


c. Stm. Gen. Water LevelLow-Low

i. Start Motor Driven Pumps

ii. Start Turbine-Driven Pumps

d. Undervoltage - RCP Start Turbine - Driven Pump

TOTAL NO. CHANNELS CHANNELS OF CHANNELS

2

l/pump

3/stm. gen.

3/stm. gen.

4-1/bus

TO TRIP OPERABLE

1 2

l/pump l/pump

2/stm. gen. 2 stm. gen. any stm. gen.

2/stm. gen. 2 stm. gen. any 2 stm. gen.

1/2 x 2 3

APPLICABLE MODES

1, 2, 3

1, 2' 3

1, 2, 3

1, 2, 3

1, 2

ACTION

20

23

14*

14*

19

e. S.I. Start Motor-Driven Pumps See 1 above (All S.I. initiating functions and requirements)

f. Trip of Main Feedwater Pumps Start MotorDriven Pumps

**Applies to items c and d.

SALEM - UNIT 2

2/pump 2 2(1/pump) 1, 2 22

3/4 3-21 Amendment No. ·

·' . ~

~

"" ACTION 19 -

DESIGNATION

P-11

P-12

ACTION 20 -

ACTION 21 -

SALEM - UNIT 2

TABLE 3.3-3 (Continued~ With the number of OPERABLE Channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 1 hour.

b. The Minimum Channels OPERABLE requirements is met; however, one additional channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1.

ENGINEERED SAFETY FEATURES INTERLOCKS

CONDITION AND SETPOINT

With 2 of 3 pressurizer pressure channels >1925 psig.

With 3 of 4 T channels > 545°F. avg

With 2 of 4 T channels < 541°F. avg

FUNCTION

P-11 prevents or defeats manual block of safety injection actuation on low pressurizer pressure.

P-12 prevents or defeats manual block of safety injection actuation high steam line flow and low steam line pressure.

Allows manual block of safety injection actuation on high steam line flow and low steam line pressure. Causes steam line isolation on high steam flow. Affects steam dump blocks.

With the number of OPERABLE channels one less than the Total Number of Channels, be in at least HOT STANDBY within 6 hours and in at least HOT SHUTDOWN within the following 6 hours; however, one channel may be bypassed' for up to 2 hours for surveillance testing provided the other channel is OPERABLE.

With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours or be in at least HOT STANDBY within 6 hours and in HOT SHUTDOWN within the following 6 hours.

3/4 3-23 Amendment No. 24

ACTION 22 -

ACTION 23 -

SALEM - UNIT 2

TABLE 3.3-3 (Continued~

With the number of OPERABLE channels one less than the Minimum Number of Channels, operation may proceed provided that either:

a. The inoperable channel is restored to OPERABLE within 72 hours, or


With the Number of OPERABLE channels relating directly with the number of OPERABLE auxiliary feedwater pumps, the ACTIONs of L.C.O. 3.7.1.2 apply.

3/4 3-23a Amendment No.

•'

•

ACTION 23 -

ACTION 24 -

ACTION 25 -

ACTION 26 -

SALEM - UNIT 2

TABLE 3.3-6 (Continued~ TABLE NOTATION

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.7.1.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements, initiate the preplanned alternate method of monitoring the appropriate parameter(s), within 72 hours, and:

1) either restore the inoperable Channel(s) to OPERABLE status within 7 days of the event, or

2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

3/4 3-40 Amendment No.

I ... • •

" REACTOR COOLANT S~EM OPERATIONAL LEAKAGE

LIMITING CONDITION FOR OPERATION

3.4.7.2 Reactor Coolant System leakage shall be limited to:

a.

b.

c.

No PRESSURE BOUNDARY LEAKAGE,

1 GPM UNIDENTIFIED LEAKAGE,

1 GPM total primary-to-secondary leakage through all steam generators and 500 gallons per day through any one steam generator,

d. 10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, and

e. 40 GPM CONTROLLED LEAKAGE at a Reactor Coolant System pressure of 2230 ± 20 psig.

f. 1 GPM leakage at a Reactor Coolant System pressure of 2230 ± 20 psig from any Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a. With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY within 6 hours and in COLD SHUTDOWN within the following 30 hours.

b. With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE and leakage from Reactor Coolant System Pressure Isolation Valves, reduce the leakage rate to within limits within 4 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.

c. With any Reactor Coolant System Pressure Isolation Valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours by use of at least two closed manual or deactivated automatic valves, or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.

SURVEILLANCE REQUIREMENTS

4.4.7.2.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by;

a. Monitoring the containment atmosphere particulate radioactivity monitor at least once per 12 hours.

b. Monitoring the containment sump inventory at least once per 12 hours.


REACTOR COOLANT S~EM • SURVEILLANCE REQUIREMENTS (Continued)

c. Measurement of the CONTROLLED LEAKAGE from the reactor coolant pump seals at least once per 31 days when the Reactor Coolant System pressure is 2230 ± 20 psig and valve 2CV71 is fully closed,

d. Performance of a Reactor Coolant System water inventory balance at least once per 72 hours. The water inventory balance shall be performed with the plant at steady state conditions. The provisions of specification 4.0.4 are not applicable for entry into Mode 4, and

e. Monitoring the reactor head flange leakoff system at least once per 24 hours.

4.4.7.2.2 Each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1 shall be demonstrated OPERABLE pursuant to Specification 4.0.5, except that in lieu of any leakage testing required by Specification 4.0.5, each valve shall be demonstrated OPERABLE by verifying leakage to be within its limit:

a. At least once per 18 months.

b. Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 72 hours or more .and if leakage testing has not been performed in the previous 9 months.

c. Prior to returning the valve to service following maintenance repair or replacement work on the valve.

d. For the Residual Heat Removal and Safety Injection Systems hot and cold leg injection valves and accumulator valves listed in Table 3.4-1 the testing will be done within 24 hours following valve actuation due to automatic or manual action or flow through the valve. For all other systems testing will be done once per refueling.

The provisions of specification 4.0.4 are not applicable for entry into MODE 3 or 4.


(i J ':. ..L .I ,:.- - e REACTOR COOLANT SYSTEM~

i:: ~' . •• -<, ,.., •

TABLE 3.4-1

REACTOR COOLANT SYSTEM·PRESSURE ISOLATION VALVES

VALVE NO FUNCTION

21SJ43 Safety Injection (L.P. from RHR Pumps to Cold Legs) 22SJ43 Safety Injection (L.P. from RHR Pumps to Cold Legs) 23SJ43 Safety Injection (L.P. from RHR Pumps to Cold Legs) 24SJ43 Safety Injection (L.P. from RHR Pumps to Cold Legs) 21SJSS Safety Injection (Accumulator Discharge to Cold Legs) 22SJSS Safety Injection (Accumulator Discharge to Cold Legs) 23SJSS Safety Injection (Accumulator Discharge to Cold Legs) 24SJSS Safety Injection (Accumulator Discharge to Cold Legs) 21SJS6 Safety Injection (Accumulator Discharge to Cold Legs) 22SJS6 Safety Injection (Accumulator Discharge to Cold Legs) 23SJ56 Safety Injection (Accumulator Discharge to Cold Legs) 24SJS6 Safety Injection (Accumulator Discharge to Cold Legs) 21SJ17 Safety Injection (Boron Injection to Cold Legs) 22SJ17 Safety Injection (Boron Injection to Cold Legs) 23SJ17 Safety Injection (Boron Injection to Cold Legs) 24SJ17 Safety Injection (Boron Injection to Cold Legs) 2SJ150 Safety Injection (Boron Injection to Cold Legs) 21SJ139 Safety Injection (H.P. from SI Pumps to Hot Legs) 22SJ139 Safety Injection (H.P. from SI Pumps to Hot Legs) 23SJ139 Safety Injection (H.P. from SI Pumps to Hot Legs) 24SJ139 Safety Injection (H.P. from SI Pumps to Hot Legs) 21SJ156 Safety Injection (H.P. from SI Pumps to Hot Legs) 22SJ156 Safety Injection (H.P. from SI Pumps to Hot Legs) 23SJ156 Safety Injection (H.P. from SI Pumps to Hot Legs) 24SJ156 Safety Injection (H.P. from SI Pumps to Hot Legs) 21SJ144 Safety Injection (H.P. from SI Pumps to Cold Legs) 21SJ144 Safety Injection (H.P. from SI Pumps to Cold Legs) 23SJ144 Safety Injection (H.P. from SI Pumps to Cold Legs) 24SJ144 Safety Injection (H.P. from SI Pumps to Cold Legs) 2RH1 RHR Suction from Hot Leg No. 21 2RH2 RHR Suction from Hot Leg No. 21 23RH27 RHR Discharge to Hot Leg No. 23 24RH27 RHR Discharge to Hot Leg No. 24


Documents

ATTACHMENT 2 TECHNICAL SPECIFICATION MARKUPSPower Range , Neutron Flux 4 2 • 3 1 • 2 2' High Positive Rate 4. Power Range, Neutron Flux, 4 2 High Negative Rate 3 1 • 2 2' -w