ML18079A304

Submits Request for Amend of Tech Specs Re Removal of Coincident Pressurizer Pressure/Level Logic for Safeguards Actuation.W/Class III Amend Fee

ML18079A304
Person / Time
Site:	Salem
Issue date:	05/07/1979
From:	Librizzi F Public Service Enterprise Group
To:	Schwencer A Office of Nuclear Reactor Regulation
References
79-10, NUDOCS 7905170263
Download: ML18079A304 (8)

Text

'~.

Ps~c!

Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 May 7, 1979 Director of Nuclear Reactor Regulation

u. S. Nuclear Regulatory Commission Washington, D. C.

20555 Attention:

Mr. Albert Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors Gentlemen:

REQUEST FOR AMENDMENT FACILITY OPERATING LICENSE DPR-70 UNIT NO. 1 SALEM GENERATING STATION DOCKET NO. 50-272 Ref. 79-10 In accordance with the Atomic Energy Act of 1954, as amended and the regulations thereunder, we hereby transmit copies of our reque~t for amendment and our analysis of the changes to Facility Operating License DPR-70 for Salem Generating Station, Unit No. 1.

This request consists of proposed changes to the Safety Technical Specifications (Appendix A) involving the removal of the coinci-dent pre~surizer pressure -

leVel logic for safeguards actuation.

This change has acceptability clearly identified by an NRC position, _and is deemed not to involve a significant hazards consideration.

It is, therefore, determined to be a Class III Amendment as defined by 10CFR 170.22.

A check for the amount of $4,000 is enclosed.

This submittal includes three (3) originals and forty (40) copies.

The Energy People Very truly yours, Fra~i General Manager -

Electric Production 95-2001 (400M) 9-77

Ref. LCR 79-10 U.S. NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-272 PUBLIC SERVICE ELECTRIC AND GAS COMPANY FACILITY OPERATING LICENSE NO. DPR-70 NO. 1 UNIT SALEM GENERATING STATION Public Service Electric and Gas Company hereby submits proposed changes to Facility Operating License No. DPR-70 for Salem Gen-erating Station, Unit No. 1.

This change request relates to the Safety Technical Specifications (Appendix A) of the Operating License, and pertains to removal of the coincident pressurizer pressure - level logic for safeguards actuation.

Respectfully submitted, PUBLIC SERVICE ELECTRIC AND GAS COMPANY VICE PRESIDENT

Ref. LCR 79-10 STATE OF NEW JERSEY)

)

SS:

COUNTY OF ESSEX

)

FREDERICK W. SCHNEIDER, being duly sworn according to law deposes and says:

I am a Vice President of Public Service Electric and Gas Company, and as such, I signed the request for change to FACILITY OPERATING LICENSE NO. DPR-70.

The matters set forth in said change request are true to the best of my knowledge, information, and belief.

~<<~

FREDERICK W:SS"cHNEIDER Subscribed and sworn to before me this /s't;{;..

day of ~ ' 1979.

~otary Public of New Jersel'l"ARBARA VALLEE A NOTARY PUBLIC OF NEW JERSEY My Commiss*ion expires on My Commission Expjres Nov a, ID83

Ref 79-10 PROPOSED CHANGE REMOVAL OF COINCIDENT PRESSURIZER PRESSURE -

LEVEL LOGIC FOR SAFEGUARDS ACTUATION TECHNICAL SPECIFICATIONS SALEM UNIT NO. 1 DESCRIPTION OF CHANGE This change involves removal of the coincident pressurizer pressure -

level logic for safeguards actuation.

Rather than requiring 1 of 3 pressurizer pressure low and 1 of 3 pressurizer level low for a safe-guards actuation signal, the logic will require 2 of 3 pressurizer pressure low and will not use pressurizer level.

REASON FOR CHANGE This change is being made because of the demonstrated unreliability of the pressurizer level signal under certain transient conditions as evidenced at Three Mile Island.

SAFETY EVALUATION Deletion of the coincidence requirements for low pressurizer level is a direct result of NRC assessments of the Three Mile Island event.

Failure to delete the level circuit and change the pressure circuit would result in an unacceptable 1 of 3 logic configuration for pressurizer pressure.

Existing analyses are not affected by this change.

11 i

I:

e c:

z:

--l w

~

w I __,

<.n

,.,.-***-'\\

~--

. )

TABLE 3.3-3 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT

1.

SAFETY INJECTION, TURBINE TRIP AND FEEDWATER ISOLATION

a.

b.

c.

d.

Manual Initiation Automatic Actuation Logic Containment Pressure-High Pressurizer Pressure - Low wit~ Press~ri~er Lc*o*el Le11

e.

Differential Pressure Between Steam Lines - High Four Loops Operating Three Loops Operating TOTAL NO.

OF CHANNELS 2

2 3

3 13ress1:n*e

-a.ft&

a level CHANNELS TO TRIP 1

1 2

.2

~ 13ress1::i1re 68~AG~EleRt

~dtfl 1 level MINIMUM CHANNELS OPERABLE 2

2 2

2 13ress1::i1re

~

2 level 3/steam line 2/steam line 2/steam line any steam line 3/operating 1###/steam 2/operating steam line line, any steam line operating steam line APPLICABLE MODES 1 ' 2, 3, 4 1 ' 2, 3, 4 1 ' 2, 3 1 ' 2, 3#

1 ' 2, 3##

. ~**' ~

}.,

... ~.,

~

1 ACTION 18 13 14 14 14 15

c :z

--i w

.i:::.

w I

N w

~-.

TABLE 3.3-4 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT

l.

SAFETY INJECTION, TURBINE TRIP AND FEEDWATER ISOLATION

a.

b.

c.

d.

e.

f.

Manual Initiation Automatic Actuation Logic Containment Pressure--High Pressurizer Pressure--Low G$iRcideRt with Press~rizer Water Level Lm\\l Differential Pressure Between Steam Lines--High Steam Flow in Two Steam Lines--

High Coincident with Ta

--Low-Low or Steam Line Pressure-~~ow

.. ~.. *. -~**** ::... -.:--**-.

TRIP SETPOINT Not Applicable Not Applicable

2. 4.7 psig

> 1765 psig

~

< 100 psi

< A function defined as follows: A ~p corresponding to 40% of full steam flow between 0% and 20% load and then a ~p increasing linearly to a ~p correspond-ing to 110% of full steam flow at full load T

> 543°F avg -

~ 500 psig steam line pressure ALLOWABLE VALUES Not Applicable Not Applicable

2. 5.2 psig

> 1755 psig

) 4. O?~

< 112 psi

< A function defined as follows: A ~p corresponding to 44% of full steam flow between 0% and 20% load and then a ~p increasing linearly to a ~p corresponding to 111.5% of full steam flow at full load Tavg ~ 541°F

~ 480 psig steam line pressure

TABLE 3.3-5 (Continued)

ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS

3.

4.

5.

Pressurizer Pressure-Low ~~~'!:A P!Qess1:.1~~ i!:e~ bei.1e~

a.

Safety Injection (ECCS)

b.

Reactor Trip (from SI)

c.

Feedwater Isolation

d.

Containment Isolation-Phase 11A11

e.

Containment Ventilation Isolation

f.

Auxiliary Feedwater Pumps

g.

Service Water System Differenti a 1 Pressure Between Steam Lines-High

a.

Safety Injection (ECCS)

b.

Reactor Trip (from SI)

c.

Feedwater Isolation

d.

Containment Isolation-Phase 11A11

e.

Containment Ventilation Isolation

f.

Auxiliary Feedwater Pumps

g.

Service Water System Steam Flow in Two Steam Lines - High Coincident with T

--Low-Low avg

a.

Safety Injection (ECCS)

b.

Reactor Trip (from SI) c.

Feed water Is o 1 at ion

d.

Containment Isolation-Phase 11A11

e.

Containment Ventilation Isolation

f.

Auxiliary Feedwater Pumps

g.

Service Water System

h.

Steam Line Isolation SALEM - UNIT 1 3/4 3-28 Levi

~ 27. O* /13. 0#

< 3.0

< 8. 0

< 18.0#

Not Applicable Not Applicable

.2. 48.0*/13.0#

~ 13.0#/23.0##

< 3.0

< 8.0

~ 18.0#/28.0##

Not Applicable Not Applicable

.2. 13.0#/48.0##

.2. 15.0#/25.0##

< 5.0

< 10.0

.2. 20.0#/30.0##

Not Applicable Not Applicable

.2. 15.0#/50.0##

< 10. 0 J

),

--~ *.

• .o:*,*;/~.-.;--~.,*.:.r1-***-~**.........

.. *:;~.~;~*:*-** *......

(~

\\

/rfl>&:A.co...

r

(

I

~*

.... ~. =~

~*

(

I I'

Vl TABLE 4.3-2

)::>

I r

!'Tl t

3:

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION r

SURVEILLANCE REQUIREMENTS c:

z CHANNEL MODES IN WHICH

-I CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

.. e

1.

SAFETY INJECTION, TURBINE TRIP AND FEEDWATER ISOLATION

a.

Manual Initiation N.A.

N.A.

R 1,. 2' 3, 4

b. Automatic Actuation Logic N.A.

N.A.

M(2) 1 ' 2, 3, 4 w -

c. Containment Pressure-High s

R M(3) 1 ' 2. 3

~

w I

d. Pressurizer Pressure--Low s

R M

l ' 2, 3 I

w ee; Re; eleR'I: ~~~=!:A P~eSSl:IF~ ;r,;Qf' Uater Level lQ"'

e. Differential Pressure s

R M

1 ' 2, 3 Between Steam Lines--High

f. Steam Flow in Two Steam s

R M

1 ' 2, 3 Lines--High Coincident with T

--Low or Steam Line P~~~sure--Low

2.

CONTAINMENT SPRAY

a. Manual Initiation N.A.

N.A.

R 1 ' 2, 3, 4

b. Automatic Actuation Logic N.A.

N.A.

M( 2) l ' 2, 3, 4

~

c. Containment Pressure--High-s R

M(3) 1 ' 2, 3

<)

High