ML18095A461

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Proposed Tech Specs Sections 2.2 & 3/4.3.2,Tables 2-2.1 & 3.3-4,respectively Re New Setpoints for Steam Generator Water Level Low Low & Steam Line Pressure Low
ML18095A461
Person / Time
Site: Salem  PSEG icon.png
Issue date: 09/04/1990
From:
Public Service Enterprise Group
To:
Shared Package
ML18095A460 List:
References
NUDOCS 9009110156
Download: ML18095A461 (9)
v • d • e


Text

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0 TABLE 2.2-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT

13. Steam Generator Water Level--Low-Low
14. Steam/Feedwater Flow Mismatch and Low Steam Generator Water Level
15. Undervoltage-Reactor Coolant Pumps
16. Underf requency-Reactor Coolant Pumps
17. Turbine Trip A.

Low Trip System Pressure B.

Turbine Stop Valve Closure

18. Safety Injection Input f rOll SSPS
19. Reactor Coolant Pump Breaker Position Trip TRIP SETPOINT ALLOWABLE VALUES

~ 1-..8'%.

1,,.r:7D ~f narrow range instruwent

~ of narrow range instrument span-each stea* generator span-each steam generator

< 401 of full steam flow at

< 42.51 of full stea* flow at

~

RATED THERMAL P<MER coincident RATED THERMAL P<MER co1nc1dent with steam generator water level with steam generator water level

> 25$ of narrow range instru-

> 241 of narrow range instru-ment span--each stea* generator iiient span--each steam generator

  • >2900 volts-each bus

> 2850 volts-each bus

..:.~.

> 56.5 Hz - each bus

> 56.4 Hz - each bus

~ 45 psig

~ 45 ps1g

~ 151 Off full open

~ 151 off full open e

Not Applicable Not Applicable Not Applicable Not Appl1cable

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TABLE 3.3-4 (Continued)

ENGi NHHEO SAFE fY flA I UHE ACTUATION S VS IEH INSTMlltENTATION TIU P SET ffilNTS F UNC T IONAL UN IT

2. Contain111ent Atmosphere Gaseous Radioactivity
4.

STEAM LINE ISOLATION

a. Manual
b. Automat tc Actuation Logic
c. Containment Pressure--High-High
d. Stea* Flow tn Two Steam lines --

High Coincident with Tavg -- low-l<M or Stea* Line Pressure--low

> (.pOO TR IP SET NINT ALLOWABLE VALUES per Tab I e 3. 3-6 rfot App 1t cab le Not App 1i cab le

~ ~3.5 psig

< A function defined as follows:

A AP corresponding to 4UI of full stea* flow betwee* OJ and 20I load and then a AP increasing linearly to a AP correspond-ing to 1101 of full stea*

flow at full load Not App 1 i cab le Not App 1 t cab le

~ 24 pstg

<A function defined as Tollows:

A AP corresponding to 441 of full stec1111 flow between oi and 201 load and then a AP increasing linearly to a AP corresponding to 111.51 of full stea* flow at full load

!ay~~ 543°f

~ psig stea* line pressure

!a~g,_~ 541°F

~.579 ~ psig steam line pressure

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TABlI 3.3-4 (Continued)

ENGINEERED SAFETY FEAT~E ACTUATION SYSTEM INSTRIMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINTS A ll.OWAB LE VA LlES

5. TlRB INE TR IP AND FEE OllATER ISOlAT ION
6.
7.
8.
a. Steam Generator Water level --

H1 ~-High SAFEGUAR(l) EQUIPMENT CONTROL SYSTEM (SEC)

UNll:RVOLTAGE, VITAL BUS

a.

loss of Voltage b

  • Sustained ~graded Voltage AUXILIARY FEE OllATER
a. Automatic Actuation logic
b. Manual Intttat1on

< 671 of narr<M ra*nge Tnstrument span edch steam generator Not App 11 cab 1 e

~ 701 of bus volta ~e

> 91.61 of bus voltage for

< 13 seconds Not App 11cab1 e Not App 11 cab 1 e

< 68S of narr<M range Tnstrument span each stea* generator Not App 11cab1 e

> 65S of bus voltage

> 911 of bus voltage for

< 15 seconds Not App 11cab1 e Not App 11 cab 1 e

c. Stea11 Generator Water level--_? /f..~o >

f narr<M rdnge low-low tnstru.ent span each stea11 generator

..?tv.t.t >__l..-5f-of narr<M range "Tnstru11ent span each steaa generator

d.

Undervoltage - RCP

e. S.I.
f. Emergency Trip of Steam Generator Feediifater Pu~s
g.

Station Blackout

~ 70S RCP bus voltage See 1 above (All S.I. setpoints)

Not App 11cab1 e

> 65S RCP bus voltage Not App 11cab 1 e See 6 and 7 above (SEC and Undervoltage, Vital Bus)

Salem Unit 2

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FUNCTIONAL UNIT IJ. Stea* Generator Water level--Low-low

14. Stea*/feedwater Flow Hl1*atch and Low SteUI Generator Water level
15. Undervoltage-Aeactor Coolant Puap1
16. Underfrequency-Reactor Coolant Pu.ps
17. Turbine Trip A.

Low Trip Sylte*

Preuure B.

Turbine Stop Valve Closure

18. Safety Injection Input f roa SSPS
19. Reactor Coolant PU11p Breaker Positton Trtp TABLE 2.2-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS TRIP SETPOINT ALLOWABLE VALUES

> /'/.~<:po

~

~~o ~of narrow range fn1trU11ent ~ of narrow **nge in1truaent spap-each s~e.. generator span-each steaa generator

< 4~ of full ate.. flow at IATEO THERMAL POWER cotncfdent with ste.. generator water level

> 2sr of narrow range lnstru-aent ipan--each Ilea. generator

~ 2900 volti-each bus

~ 56.5. Hz - each but

~ 45 p1tg

~ 15¥ off full open Not Appltcable Hot Appltcable

< 42.5¥ of full 1teU1 flow at IATEO THERMAL POWEi coincident with ste.. generator water level

> 24¥ of narrow range tnstru-aent span--each ilea. generator

~ 2850 volts-each bus

~ 56.4 Hz - each bus

~ 45 pslg

~ 15¥ off full open Not Applicable Not Applicable I

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TA8lf 3. 3-4 (ConU nued)

ENGINHREO SAFETY FEATURE ACTUATION SYSTEM INSTMll4ENTATION TRIP SETKllNTS F UNC Tl ONAl UN IT

2. Contain11ent Atnosphere Gaseous Radioactivity
4.

STEAH LINE ISOLATION

a. Manual
b. Auto.atic Actuation logic
c. Contai0111ent Pressure--High-High
d. Stea* Flow in Two Stea~ lines --

Htgh Coincident with Tavg -- low-l0111 or Stea* line Pressure--low TR I P SET RH NT AlLOWAttlE VALUES per Table 3.3-6 Not App 1 i cab le Not App 1 i cab le

~ 23.~ tJS ig

< A func.tion defined as follows: A AP corresponding to 4UI of full steaa flow hetwee* 01 and 201 load and then a AP increasing linearly to a AP correspond-ing to 1101 of full stea.

flow at full load Hot App 1i cab le Not App 1 i cab le

~ 24 psig

< A function '1ef i ned as follows:

A /'jJ1 corresponding to 441 of full steam flow between 01 and 201 load and then a AP increasing linearly to a jp corresponding lo 111.~I of full steam flow al f u 11 load Tayg_!. 543°F

!ay!J_~ 541°f

>~ 00..}.-belrpsig stea* line.:?!'"79 ~ psig steclm line pressure pressure

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N TABLI 3.3-4 (Continued)

ENGINHREO SAFETY HATLRE ACTlMHION SYSTEM INSTRIHENTATION TRIP SETPOINTS F UNCT IONA l UN IT TRIP SETPOINTS All.OWAB lf VAU£S

5.

Tl~BINE TRIP AND FEEIMATER ISOlATION

a. Stea* Generator W.ter ~vel Htgh-Htgh
6.

SAHGUARffi EQUIPMENT CONTROL SYSTEM (SEC)

1.

llU~RVOlTAGE

  • VITAL BUS
a. loss of Voltage
b. Sustained legraded Voltage
8. AUXILIARY FEE IMATER
a. Aut0111ttc Actuatton logic
b. Manual ln1t1at1on
c. Stea* Generator Water ~ve 1--*

Low d. Undervoltage - RCP

e. S.I.
f. Trip of Main FeeBllater Pu9'>S

< 67S of narrow range Tnstru.ent span edch stea* generator Not App 1t cab 1 e

> 70S of bus volta~

> 91.6S of bus voltage for

< ll seconds Not App 1i cab 1 e Hot Applicable

.:?IG.Cfo~ of narrow r,mge Tnstna.ent span each stea* generator

~ 70S RCP bus volta~

< 68S of narrow range Tnstru.ent span each stea* generator Not App Ii cab le

> 65S of bus voltage

> 91S of bus voltage for

< 15 seconds Not App 11 cab 1 e Not App 11 cab I e

~ J '/. fc;:>0~f narrow range Tnstru.ent span each stea* generator

> 651 RCP bus voltage See 1 above (All S.I. setpotnts)

Not App 1i cable Not App I icab le r

~,.,

PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department AUG 2 1 1990 NLR-N90168 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION CORRECTION OF TYPOGRAPHICAL ERROR SALEM GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50-272 AND 50-311 A typographical error was made in PSE&G's Letter NLR-N90159, dated August 10, 1990.

The letter provided additional information requested by the NRC pertaining to PSE&G's request for restatement of the operating license expiration dates based on issuance of the operating license rather than issuance of the construction permits.

The error occurred at the end of the third paragraph on the front page.

The affected sentence currently reads:

"April 18, 1990 is the correct date."

This sentence should correctly read:

"April 18, 2020 is the correct date."

Should you have any questions regarding this correction, please feel free to contact us.

Thank you.

9008310171 900821 PDR ADOCK 05000272 P

PNU The Energy People

& Regulation 95-2168 (40M) 6-89 J

Document Control Desk NLR-N90168 c

Mr. J. c. Stone Licensing Project Manager Mr. T. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief 2

New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 AUG 2 1 1990

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