ML18095A461

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
Issue date:	09/04/1990
From:	Public Service Enterprise Group
To:
Shared Package
ML18095A460	List: ML18095A459 ML18095A461
References
NUDOCS 9009110156
Download: ML18095A461 (9)

Text

'1J ,....,,-,

'1J '(1 TABLE 2.2-1 (Continued)

oo**.o

..... REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS D .....

-

t:.10 c: FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

z

• =*..-

()fJ1

...... ~ 1-..8'%.

7' 1")-

13. Steam Generator Water :1,,.r:7D ~f narrow range instruwent ~ of narrow range instrument Level--Low-Low span-each stea* generator span-each steam generator

14. Steam/Feedwater Flow < 401 of full steam flow at < 42.51 of full stea* flow at ~

Mismatch and Low Steam RATED THERMAL P<MER coincident RATED THERMAL P<MER co1nc1dent Generator Water Level 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

15. Undervoltage-Reactor * >2900 volts-each bus > 2850 volts-each bus Coolant Pumps . : - ...:.~ .

N I

0\ 16. Underf requency-Reactor > 56.5 Hz - each bus > 56.4 Hz - each bus Coolant Pumps

17. Turbine Trip A. Low Trip System ~ 45 psig ~ 45 ps1g Pressure B. Turbine Stop Valve Closure

~ 151 Off full open ~ 151 off full open e

18. Safety Injection Input Not Applicable Not Applicable f rOll SSPS

19. Reactor Coolant Pump Not Applicable Not Appl1cable

..... Breaker Position Trip 0

TABLE 3.3-4 (Continued)

ENGi NHHEO SAFE fY flA I UHE ACTUATION SVS IEH INSTMlltENTATION TIU P SET ffilNTS c

z H

to) FUNC T IONAL UN IT TR IP SET NINT ALLOWABLE VALUES

2. Contain111ent Atmosphere per Tab I e 3. 3-6 Gaseous Radioactivity

4. STEAM LINE ISOLATION

a. Manual rfot App 1t cab le Not App 1 i cab le

b. Automat tc Actuation Logic Not App 1i cab le Not App 1t cab le

c. Containment Pressure--High-High ~ ~3.5 psig ~ 24 pstg

d. Stea* Flow tn Two Steam lines -- < A function defined as <A function defined as w

High Coincident with Tavg -- low-l<M follows: A AP corresponding Tollows: A AP corresponding I or Stea* Line Pressure--low to 4UI of full stea* flow to 441 of full stec1111 flow

"'

VI betwee* OJ and 20I load between oi and 201 load and and then a AP increasing then a AP increasing linearly linearly to a AP correspond- to a AP corresponding to ing to 1101 of full stea* 111.51 of full stea* flow at flow at full load full load

!ay~~ 543°f !a~g,_~ 541°F

- > (.pOO ~ psig pressure stea* line ~.579 ~ psig steam pressure line 0

TABlI 3.3-4 (Continued)

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

5. TlRB INE TR IP AND FEE OllATER ISOlAT ION

a. Steam Generator Water level -- < 671 of narr<M ra*nge < 68S of narr<M range H1 ~-High Tnstrument span edch Tnstrument span each steam generator stea* generator

6. SAFEGUAR(l) EQUIPMENT CONTROL Not App 11 cab 1e Not App 11cab1 e SYSTEM (SEC)

7. UNll:RVOLTAGE, VITAL BUS

a. loss of Voltage ~ 701 of bus volta ~e > 65S of bus voltage w

.......... b* Sustained ~graded Voltage > 91.61 of bus voltage for > 911 of bus voltage for

""' < 13 w

I seconds < 15 seconds N

0\

8. AUXILIARY FEE OllATER

a. Automatic Actuation logic Not App 11cab1 e Not App 11cab1 e

b. Manual Intttat1on Not App 11 cab 1e Not App 11 cab 1e

c. Stea11 Generator Water level--_? /f..~o > f narr<M rdnge ..?tv.t.t >__l..-5f-of narr<M range low-low tnstru.ent span each "Tnstru11ent span each stea11 generator steaa generator

d. Undervoltage - RCP ~ 70S RCP bus voltage > 65S RCP bus voltage

....

c e. S.I.

N See 1 above (All S.I. setpoints)

f. Emergency Trip of Steam Not App 11cab1 e Not App 11cab 1e Generator Feediifater Pu~s

g. Station Blackout See 6 and 7 above (SEC and Undervoltage, Vital Bus)

Salem Unit 2 TABLE 2.2-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS c

-

z

-t FUNCTIONAL UNIT IJ. Stea* Generator Water TRIP SETPOINT

~ ;~~o ~of narrow range fn1trU11ent ALLOWABLE VALUES

> /'/.~<:po

~ of narrow **nge in1truaent N

level--Low-low spap-each s~e.. generator span-each steaa generator I

14. Stea*/feedwater Flow < 4~ of full ate.. flow at Hl1*atch and Low SteUI < 42.5¥ of full 1teU1 flow at IATEO THERMAL POWER cotncfdent IATEO THERMAL POWEi coincident Generator Water level with ste.. generator water level with ste.. generator water level

> 2sr of narrow range lnstru- > 24¥ of narrow range tnstru-aent ipan--each Ilea. generator aent span--each ilea. generator

15. Undervoltage-Aeactor ~ 2900 volti-each bus Coolant Puap1 ~ 2850 volts-each bus

16. Underfrequency-Reactor ~ 56.5. Hz - each but Coolant Pu.ps ~ 56.4 Hz - each bus N

• 17. Turbine Trip

"' A. Low Trip Sylte* ~ 45 p1tg ~ 45 pslg Preuure B. Turbine Stop Valve ~ 15¥ off full open Closure ~ 15¥ off full open

18. Safety Injection Input Not Appltcable f roa SSPS Not Applicable

19. Reactor Coolant PU11p Hot Appltcable Breaker Positton Trtp Not Applicable

..,.

.

0

TA8lf 3. 3-4 (ConU nued)

ENGINHREO SAFETY FEATURE ACTUATION SYSTEM INSTMll4ENTATION TRIP SETKllNTS c

z FUNC Tl ONAl UN IT TR I P SET RH NT H AlLOWAttlE VALUES t-j

2. Contain11ent Atnosphere per Table 3.3-6 Gaseous Radioactivity

4. STEAH LINE ISOLATION

a. Manual Not App 1i cab le Hot App 1i cab le

b. Auto.atic Actuation logic Not App 1i cab le Not App 1i cab le

c. Contai0111ent Pressure--High-High ~ 23.~ tJS ig ~ 24 psig w

I

d. Stea* Flow in Two Stea~ lines -- < A func.tion defined as < A function '1ef i ned as Htgh Coincident with Tavg -- low-l0111 follows: A AP corresponding follows: A /'jJ1 corresponding

"'

<J\

or Stea* line Pressure--low to 4UI of full steaa flow to 441 of full steam flow hetwee* 01 and 201 load between 01 and 201 load and and then a AP increasing then a AP increasing linearly linearly to a AP correspond- to a jp corresponding lo ing to 1101 of full stea. 111.~I of full steam flow al flow at full load f u 11 load Tayg_!. 543°F !ay!J_~ 541°f

>~ 00 ..}.-belrpsig stea* line .:?!'"79 ~ psig steclm line pressure pressure U1 w

,.

• r TABLI 3.3-4 (Continued)

ENGINHREO SAFETY HATLRE ACTlMHION SYSTEM INSTRIHENTATION TRIP SETPOINTS c:

....::J

~

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 < 67S of narrow range < 68S of narrow range Htgh-Htgh Tnstru.ent span edch Tnstru.ent span each stea* generator stea* generator

6. SAHGUARffi EQUIPMENT CONTROL Not App 1t cab 1e Not App Ii cab le SYSTEM (SEC)

1. llU~RVOlTAGE

• VITAL BUS

a. loss of Voltage > 70S of bus volta~ > 65S of bus voltage

b. Sustained legraded Voltage > 91.6S of bus voltage for > 91S of bus voltage for w

I

< ll seconds < 15 seconds N

...... 8. AUXILIARY FEE IMATER

a. Aut0111ttc Actuatton logic Not App 1i cab 1e Not App 11 cab 1e

b. Manual ln1t1at1on Hot Applicable Not App 11 cab I e

c. Stea* Generator Water ~ve 1--* .:?IG.Cfo~ of narrow r,mge ~ J '/. fc;:>0 ~f narrow range Low Tnstna.ent span each Tnstru.ent span each stea* generator stea* generator

d. Undervoltage - RCP ~ 70S RCP bus volta~ > 651 RCP bus voltage

e. S.I. See 1 above (All S.I. setpotnts)

f. Trip of Main FeeBllater Pu9'>S Not App 1i cable Not App I icab le

,,

.....

~,

.., ...

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.

& Regulation 9008310171 900821 PDR ADOCK 05000272 P PNU The Energy People 95-2168 (40M) 6-89

,. .

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