Text

Amends 56 & 24 to Licenses DPR-70 & DPR-75,respectively, Adding Existing Manual Initiation Function for Auxiliary Feedwater Sys to Tech Specs & Changing Containment Sys Air Lock Surveillance Requirement in Tech Specs
	ML20093K234
Person / Time
Site:	Salem
Issue date:	07/16/1984
From:	Varga S; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20093K235	List: ML20093K234; ML20093K238;
References
	NUDOCS 8407310005
	Download: ML20093K234 (22)
	v • d • e

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'o, UNITED STATES IT NUCLEAR REGULATORY COMMISSION 1,

5J WASHINGTON, D. C. 20SSS 1

+,,

j-s PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILAULLPHIA ELEGIMIG CUrWANT D

ATLANTIC CITT EttGIRIC currant DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION. UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.56 License No. OPR-70 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the Itcensees).

dated March 28, 1983, as supplemented February 6,1984, complies with the standards and req)uirements of the Atomic Energy Act of 1954, as amended (the Act and the Comission's rules and regulations set forth in 10 CFR Chapter It B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (11) that such act'wities will be conducted in compliance with the Comission's regulations D.

Tha issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the publici and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-70 is hereby amended to read as follows:

0407310005 040716 PDR ADOCK 00000gyg U

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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 56, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This licens'e amendment is effective as of the date of its issuance.

F0 THE NUCLE REDWLATORY Com!SSION l

T oa k,$.

lt!*A. Varga,' Chief k Gen Operating Reactors 8r

1 Division of Licensing i

Attachment:

Changes to the Technical Specifications Date of !ssuance: July 16,1984 O

b I

i 52

l I

ATTACHMENT 70 LICENSE AMEN 0 MENT N0. 56 FACILITY OPERATING LICENSE NO. DPR-70 l

DOCKET N0, 50-272 i

Revise Appendix A as follows:

Remove Pages Insert Paees i

3/4 3-20e 3/4 3-20e 3/4 3-21 3/4 3-21 3/4 3-22 3/4 3-72 3/4 3-26 3/4 3-26 3/4 3-33 3/4 3-33 3/4 3-34 3/4 3-34 3/4 6-5 3/4 6-5 3/4 6-4 3/4 6-6 a,

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1ABLE 3.3-3 (Centlemed)

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ApptICARLE FuKTISML uuIT y ruesmurLS 18 1 RIP WERABLE SMS ACTIN.

s.'

AmaILIAaY FEfauRIER i

a.

Antenatic Actuaties Logic **

2 1

2 1, 2, 3 29 l

^

1/pielp IM I/W l. 2, 3 22 b.

Itsemal Initiation c.

Steam Generater Meter Level-Lew-Law R

1.

Start lister

{

Brives Pumps 3/sta. gen.

2/sta. gen.

2 sta. pen.

1, 2, 3 14*

E li. Start Terbine-Driven Pamps 3/sta. gen.

2/sta. gen.

2 sim. gen.

I, 2, 3 14*

d.

Underveltage - SCP Start Turbine-Drives Pimmy 4(t/ bus)

I/2 x 2 3

I, 2 19 3

a k

e.

5.I.

3 Start sister-Brives 2

Pumps See I above (All 5.I. Initiating faectless and requirements) f.

Emergency Irlp of Steam Eeterator Feedsater P g s Start sloter 3rivem Pumps 2(I/ pump) 2 2(l/per.p)

I 25 g.

Station Blacteet See 6 and 7 above (SEC and U/V Vital Ses)

" Applies to items c and d 3m -

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+ - - - + - - - - - - -

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TABLE 3.3 3 (Continued)

TA8(F NOTATION

Trip function may be bypassed in this MODE below P 11.

dicip function may be bypassed in this MODE below P 12

ddirip channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop.shall be placed in the tripped mode.

'The provisions of Specification 3.0.4 are not applicable.

ACit0N STATEMENTS ACTION 13 - With the number of OPERABLE Chanrels one less than the Total Number of Channels. be in HOT STANOBY within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and in COLO $HUTD0WN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one chenael may be bypassed for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for survet11ance testing per Specification 4.3.2.1.1.

ACTION 14 - With the number of OPERABLE Channels one less than the Total f

Number of Channels, operation may proceed until performance i

of the next required CHANNEL FUNCTIONAL TEST, provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

l ACTION 15 - With a channel associated with an operating loop inoperable, restore the inoperaale channel to OPERAILE status wit',in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT SHUT 00WN within the following 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months st however, one channel associated with an operating 1000 may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Speci fication 4.3.2.1.1.

ACTION 16 With the nomeer of OPERA 8LE Channels one less than the Total Number of Channels, operation may proceed provided the inop-erable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is demonstrated within 1 hourt one additional channel may be bypassed for up to 2 1

hours for surveillance testing per Specification 4.3.2.1.1.

ACTION 17 - With less than the Minimum Channels OPERABLE, operation may continue provided the containment purge and exhaust valves are maintained closed.

ACTION 18 - With the number of OPERA 8LE Channels one less than the Total i

Number of Channels, restore the inoperable channel to l

OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STAN08Y 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 nours, 5ALEM UNIT 1 3/4 3 21 Amendment Nn. 56

TABLE 3.3 3 (Continued)

ACT!0N 19 - With the number of OPERABLE Channels cne less than the Total Number of Channels, STARTUP and/or POWER OPERAT!;N may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b.

The Minimum Channels OPERABLE requirements is met; however, one additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for survet11ance testing per Specification 4.3.2.1.1 ENGINEERED SAFETY FATURES INTERLOCKS' OESIGNAT10N CONDITION AND 50 POINT FUNCTION P 11 With 2 of 3 pressurizer P-11 prevents or defeats pressure channels ) 1925 manual block of safety

~

psig.

injection actuation on low pressurizer pressure.

P 12 With 3 of 4 Tavg channels P-12 prevents or defeats

> 545'F.

manual block of safety

~

injection actuation high,

steam line flow and low steam line pressure.

With 2 of 4 Tayg 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 nigh steam flow. Affects steam dump blocks.

ACTION 20 - With the number of OPERABLE channels one less than the Total Numoer of, Channels, be in at least HOT STANOBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT $HUTDOWN witnin the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; how-ever, one channel may be bypassed for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for surveillance testing.

ACTION 21 - With the number of OPERABLE channels one less than the Minimum Numoer of Channell, operation may proceed provided that eithert a.

The inoperable channel is restored to OPERABLE within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or b.

If the affected Steam Generator Feedwater Pump is espected to be out of service for more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , the inoperable channel *is jumpered so as to enaole the Start Circuit of the Austliary feedwater Pumps upon the loss of tne other Steam Generator Feedwater Pumo.

ACTION 22 With the number of OPERABLE channels relating directly with tne numoer of OPERAOLE auxiliary feedwater rumos, the ACTIONS of L.C.0. 3.7.1.2 apply.

$ALEM UNIT 1 3/4 3 2:

i TABLE 3.3-4 (Continu g y

!p

. ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS i

c,r i

p FUNCTIONAL UNIT TRIP SETPOINTS ALLOWABLE VALUES S.

iURBINE1 TRIP AND FEEDWATER ISOLATION SthamGeneratorWaterr(evel--

< 67% pf narrow range

< 68% of narrow range j.

a.

I High-High Tnstrument span each Tnstrument span each steam 'enerator steam generator

,/

g V-

\\

l:'

6.

sMEGUARDS EQUIPMENT CONTROL

-> 13 SYSTEM (SEC)

Not Appilcable Not Applicable 1

1 UNDERVOLTAGE, VITAL BUS g9 a.

Loss of Voltage'

> 70% of bus voltage

> 65% of bus voltage r

1' b.

Suste'ined Degraded Voltage

> 91% of bus voltage for

> 90% of bus voltage for

< 13 seconds

< 15 seconds 2

t' rI T 8.

AUXILIA.4Y FEEDWATER

.a i

A3 a.

Automat Jc Actuation Logic Not Appilcable Not Applicable m

F Manual 1)d tlation Not Applicable Not Appilcable b.

A

)

'}

c.! Steam. Gent rator Water Level --

> 18% of narrow range

> 17% of nurrow range i

f-Low-Low Tutrument span each Tnstrument span each j

steam generator steam generator 3

R d.

Undervoltage - RCP

> 70% RCP bus volta.

> 65% RCP bus voltage o.

R e.

S.I.

See 1 above (All S.I. setpoints)

E

=

f.

Emergency Irlp of Steam P

Generator Feedwater Pumps Not Appricable Not Applicable j

r ui 9

Station Blackout See 6 and 7 above (SEC and Undervoltage, Vital Bus) i-i 1

i

_ - - : 2 v, O

L 52 G;

TABLE 4.3-2 (Continued) ac I

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSlRUMENTATION TRIP SETPOINTS l

l E

SURVEILLANCE REQUIREMENTS El CHANNEL MODES IN WHICH CilANNEL tilANNEL' FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 8.

AUXILIARY FEEDWATER Automatic Actuation L,ogic N.A.

N.A.

M(2).

1, 2 ' 3 a.

b.

Manual Initiation N.A.

N.A.

M(4) 1, 2, 3

]

c.

Steam Generator Water S

R H

1, 2, 3 Level--Low-Low kt d.

Undervoltage - RCP S

R M(2) 1, 2 Y'd e.

S.I.

See I above (All S.I. surveillance requirements) f.

Emergency Trip of Steam i

Generator feedwater Pumps N.A.

N.A.

R 1

g.

Station Blackout See 6b and 7 above (SEC and U/V Vital Bus) 5 t

E i

a

.if

.8 4

4 e

~

TABLE 4.3-2 (Continued)

TABLE NOTATION (1) Each logic channel shall be tested at least once.per 62 days on a STAGGERED TEST BASIS. The CHANNEL FUNCTION TEST of each logic channel shall verify that its associated diesel generator automatic load sequence timer is OPERABLE with the interval between each load block within 1 second of its design interval.

(2) Each train or logic channel shall be tested at least every 62 days on a staggered basis.

(3) The CHANNEL FUNCTIONAL TEST shall include exercising the transmitter by applying either a vacuum or pressure to the appropriate side of the transmitter.

(4) The CHANNEL FUNCTIONAL TEST shall be conducted in conjunction with the SURVEILLANCE REQUIREMENT OF 4.7.1.2. 4 e

SALEM - UNIT 1 3/4 3-34

~

CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS l

LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with:

a.

Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and b.

An overall air lock leakage rate of < 0.05 La at design pressure

~~

(47.0 psig).

APPLICABILITY: MODES 1, 2, 3 and 4 ACTION:

With an air lock inoperable, restore the air lock to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 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 .

4 SURVEILLANCE REQUIREMENTS i

4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

a.

After each opening, except when the air lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months by pressurizing the volume between the air lock door gaskets to > 10.0 psig and checking for an extrapolated ** seal leakage rate equal to or less than 0.01 La.

b.

At least once per 6 months by conducting an overall air lock leakage test at design pressure (47.0 psig) and by verifying that the overall air lock leakage rate is within its limit, and c.

At least once per 6 months by verifying that only one door in each air lock can be opened at a time.

Exemption to Appendix "J" of 10 CFR 50.

1

- The measured leakage at the test pressure (10 psig) shall, be multiplied by an extrapolation factor of 9.1 to determine what the seal leakage flow rate would be if tested at design pressure (47.0 psig).

This extrapolated seal leakage rate shall be less than or equal to 0.01 La.

SALEM - UNIT 1 3/46-5 Amendment No. 56

~

~ g CONTAINMENT SYSTEMS INTERNAL PRESSURE LIMITING CONDITION FOR OPERATION 1

3.6.1.4 Primary containment internal pressure shall be maintained bstween -1.5 and +0.3 psig.

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

ACTION:

With the containment internal pressure outside of the limits above, restore the internal pressure to within the limits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STAND 8Y 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

^

4.6.1.4 The primary containment internal pressure shall be determined to ba within the limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

n s

l SALEM - UNIT 1 3/4 6-6 Amendment No. 56

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1 UNITED STATES NUCLEAR REGULATORY COMMISSION l

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WASHINGTON, D. C. 20555

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PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELEGIRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELEt,TRIC COMPANY DOCKET NO. 50-311 SALEM N'JCLEAR GENERATING STATION, UNIT N0. 2 I

AMENDMENT TO FACILITY OPERATING LICENSE

{}

Amendment No.24 License No. DPR-75 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and

)

Light Company and Atlantic City Electric Company (the licensees) i dated March 28, 1983, as supplemented February 6,1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health j

and safety of the public, and (ii) that such activities will be t

conducted in compliance with the Comission's regulations;

]ii D.

The issuance of this amendment will not be inimical to the common j

defense and security or to the health and safety of the public;

.1 and l-E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:

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. 1 (2) Technical Specifications 3

The Technical Specifications contained in Appendices A and 3, as revised through Amendment No. 29,are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical a

Specifications.

!j 3.

This license amendment is effective as of the date of its issuance.

l-FOR THE NUCLEAR REGULATORY COMMISSION (N

~l ri, hi Operating Reactors r nch #1 j

Division of Licensing i

Attachment:

d Changes to the Technical

!j Specifications

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I Date of Issuance: July 16, 1984

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ATTACHMENT TO LICENSE AMENDMENT NO. 24 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 1

(

Revise Appendix A as follows:

l Remove Pages Insert Pages j

3/4 3-21 3/4 3-21 3/4 3-22 3/4 3-22 3/4 3-23 3/4 3-23 3/4 3-27 3/4 3-27 3/4 3-36 3/4 3-36 5

3/4 3-37 3/4 3-37 3/4 6-5 3/4 6-5 3/4 6-6 3/4 6-6

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TABLE 3.3-i3 (Continued) u.D

!E ENGINEERED SAFETY FEAluRE AC1UATION SYSTEH INSTRUMENTATION HINIHuH tj TOTAL NO.

CilANNELS CilANNELS APPLICABLE FUNCTIONAL UNIT OF CilANNELS TO TRIP _ _

GPERABLE HDDES ACIION m

8.

AUXILIARY FEEDWATER

~

a.

Automatic Actuation Logic"*

2 1

2 1,' 2, 3 20

~

h-Manual Initiation 1/ pump 1/ pump 1/ pump 1, 2, 3 23 c.

Sim. Gen. Water 1

Level-Low-low m2 1.

Start Hator

/,

Driven Pumps 3/sta. gen 2/sta. gen.

2 sim. gen.

1, 2 ' 3 14" m

P any sim. gen.

i 11.

Start Turbine-Oriven Pumps 3/sta. gen.

2/sta. gan.

2 sim. gen.

1, 2, 3 lia

any 2 sim. gen.

\\

E d.

Undervoltage-RCP g

g Start Turbine-g Driven Pump 4-1/ bus 1/2 x 2 3

1, 2 19 r+

g e.

S.I.

Start Motor'-Driven g

Pianps See 1 above (All S.I. Inillating functions and requirements)

~

I-Irlp of Hain feedwater Pupps Start Hotor-Driven i

Ppaps 2/ Pump 1/ pump 1/ pump 1, 2 22*

i j

ooApplies to iterns c and d.

i

}

i

^-

TABLE 3.3-3 (Continued) 1 TABLE NOTATION r

rip function may be bypassed in this MODE below P-11 (Pressuri:er Pressure T

Block of Safety Injection) setpoint.

9#

Trip function may be bypassed in this M00E:below P-12 (T"'I Block of Safety Injection) setpoint.

X The provisions of Specification 3.0.4 are not applicable.

l ACTION STATEMENTS f

ACTION 13 With the number of OPERABLE Channels one less than the Total 5

Number of Channels, be in at least HOT STANOBY within 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 ; however, one channel say be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance Earting per Specification 4.3.2.1 provided the other channel is OPERABLE.

ACTION 14 With the number of OPERABLI channels one less than the Total Number of Channels, operation may proceed until performance of j

~

the next required CHANNEL FU.NCTIONAL TEST, provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 15 With a channel. associated with'an operating loop inoperable, b,I restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months l

or be in HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; however,

[![

up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.

one channel associated with an operating loop may be bypassed for ACTION 16 With the number of OPERABLE Channels one less than the Total

]

Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERA 8LE requirement is demonstrated by CHANNEL CHECK within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; one additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1. -

\\

ACTION 17 With less than' the Minimum Channels OPERABLE, operation may continue provided the containment purge and exhaust valves.are i

maintained closed.

ACTION 18 With the number of OPERABLE Channels one less than the Total Number of Channels, restore'the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANOBY 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 .

SALEM - UNIT 2 3/4 3-22 Amendment No. 24.

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TABLE 3.3-3 (Continued)

ACTION 19 With the number of OPERA 8LE 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 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b.

The Minimum Channels' OPERABLE requirements is met; however, one additional channel nay be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specificatien 4.3.2.1.

ENGINEERED SAFETY FEATURES INTERLOCKS DESIGNATION CONDITION AND SETPOINT FUNCTION P-11 With 2 of 3 pressurizer P-11 prevents or defeats pressure channels 21925 sanual block of safety psig.

injection actuation on low pressurizer pressure.

P-12 With 3.of 4 T**9 channels P-12 prevents or defeats

> 545PF.

sanual block of safety injection _ actuation high c

steam line flow and low steam line pressure.

With 2 of 4 T"V9 thannels

- Allows manual block of safety

< 541*F.

injection actuation on high steam line flow and low steam ifne. pressure.

Causes steam line isolation on high steam fl ow.

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 STANOBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at le.ast HOT SHUT 00WN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; how-ever, one channel say be bypassed for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for surveillance testing provided the other channel is OPERA 8LE.

L ACTION 21 With the number of OPERABLE channels one less than the Total i'

Nuncer of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY witnin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 22 With the number of OPERABLE channels one less than the. Minimum Channels OPERABLE, operation may proceed until performance of the nex: required CHANNEL FUNCTIONAL TEST.

I ACTION 23 With the number of OPERABLE channels relating directly with the

~

number of OPERABLE auxiliary feecwater pumps, the ACTIONS of L.C.0. 3.7.1.2 apply.

SALEM - UNIT 2 3/4 3-23 Amendment No. 24

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C 5 UDs - UNIT 2 3/A 3-17 Amendment No. 24

g TABLE 4.3-2 (Continued)

ENGINEERED SAFE 1Y FEATURE ACTUATION SYSTEH INSTRUNENTATION SURWIITAKE RQlffRTIERTS i

Eq CilANNEL MODES IN WillCil CilANNEL CilANNEL FUNCTIONAL 5NtVEILLANCE f

filHCTIONAL UNIT CilECK CAllBRATION TEST REQUIRED 8.

AUXILIARY FEEDWATER i

l.

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Automatic Actuation Logic N.A.

N.A.

M(2) 1, 2, 3 b.

Hanual Initiation M.A.

N.A.

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TABLE 4.3-2 (Continued) 1 TABLE NOTATION (1)

Each logic channel shall be tested at least once per 62 days on a STAGGERED TEST SASIS.

The CHANNEL FUNCTION TEST of each logic channel shall verify that its associated diesel generator automatic load sequence timer is OPERABLE with the interval between each load block within 1 second of its design interval.

(2) Each train or logic channel shall be tasted at least every 62 days on a STAGGERED TEST BASIS.

2 (3) The CHANNEL FUNCTIONAL TEST shall include exercising the transmitter by applying either a vacuum or pressure to the appropriate side of the transmittar.

(4)

If not performed in the previous 92 days.

(5) The CHANNEL FUNCTIONAL. TEST shall be. conducted in conjunction with the SURVEILLANCE REQUIRENENT of 4.7.1.2.a N...

i

'i i-l' i

I SALEM - UNIT 2 3/4 3-37 Amendment No. 24.-

l t

CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS SURVEILLANCE REQUIREMENTS (Continued a.

Afte each opening, except when the air lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months by pressurizing the volume betwean the air lock door gaskets to > 10.0 psig and checking for an extrapolated

seal leakage rate equal to or less than 0.01 La.

b.

Prior to establishing CONTAINMENT INTEGRITY, if opened when CONTAIN-MENT INTEGRITY was not required, and at least once per 6 months by conducting an overall air lock leakage test at design pressure (47.0 psig) and by verifying that the overall air lock leakage rate is within its limiti, and c.

At least once per 6 months by verifying that only one door in each air lock can be opened at a time.

The measured leakage at the test pressure (Tne what the seal leakage flow rat

> 10.0 psig) shall be multiplied by an extrapolation factor of 9.1 to determ

c would be at design pressure (47.0 psig). This extrapolated seal leakage rate shall be equal to or less than 0.01 La.

The provisions of Specification 4.0.2 are not applicable.

A w

SALEM - UNIT 2 3/46-5

. Amendment No. 24 m

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CONTAINMENT SYSTEMS XNTERNAL PRESSURE LIMITING CONDITION FOR OPERATION 3.6.1.4 Primary containment internal pressure shall be maintained between

-1.5 and +0.3 psig.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With the containment internal pressure outside of the limits above, restore the internal pressure to within the limits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STAND 8Y 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 4.6.1.4 ' The primary containment internal pressure shall be determined to be within the limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

j:

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SALEM - UNIT 2 3/4 6-6 Amendment No. 24 n

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ML20093K234

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