ML20065H905

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Proposed Tech Spec Tables 2.2-1 & 3.3-4 Re Reactor Trip Sys Instrumentation Trip Setpoints & ESF Actuation Sys Instrumentation Trip Setpoint
ML20065H905
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 10/26/1990
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20065H903 List:
References
NUDOCS 9010310097
Download: ML20065H905 (8)
v • d • e


Text

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.EttJPOSED CHANGES TO APPENDIX A,

-i- TECHNICAL SPECIFICATIONS S' OF FACILITY OPERATING-LICENSES NPF-37; NPF 66,'NPF-72 AND NPF-77  ;

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.TA8LE 2.2-1 (Continued)

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5 SENSOR TOTAL d FUNCTIONAL UNIT- -

ALLOWANCE (TA) Z ERROR (SE) TRIP SETPOINT ALLOWABLE VALUE

[ 12. . Reactor Coolant Flow-Low. 2. 5 ' 1;77 0.6 190% of loop mini- >89.2% of hop mini-num measured flow

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13. Steam Generator Water . .

Level Low-Low M8

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a. Unit 1- ~27A - 18.28 1.5 >49: M of narrow >39-1% of narrow l

' range instrument range instrument i span span -

b. Unit 2 17.0 14.78 1.5 >17% of narrow >15.3% of narrow range instrument range instrument 1

rp span w span '

14. Undervoltage - Reactor -12.0 0. 7 0 >5268 volts -

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Coolant Pumps >4728 volts -

each bus each cars

15. Underfrequency Reactor 14.4 13.3 0 >57.0 Hz 1

Coolant Pumps >56.5 Hz

16. Turbine Trip - s
a. Emergency Trip Header N.A. M.A. N.A. >540 psig. >520 psig '

Pressure

b. Turbine Throttle Valve N.A. M.A. l

.M.A. 117 open >1A open Closure

17. Safety Injection Input N. A. N.A. N.A. N.A. N.A.

from ESF i

18. Reactor Coolant Pump . N.A. N.A. N.A. ' N. A. N.A. '

Breaker Position Trip

  • Minimum measured flow = 97,600 jgm - , . , , , ,, o

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TABLE 3.3-4 (Continued) -

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g ENGINEERED SA/ETY FEATURES ACTUATION SYSTEM INSTRUNENTATION TRIP SETPOINTS TOTAL' SENSOR TRIP ALLOWABLE g- FUNCTIONAL UNIT ALLOWANCE (TA) Z ERROR (SE) SETPOINT VALUE Z

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, c. Safety Injection See Item 1. above for 'all Safety Injection Trip Setpoints and Allowable Values.

6. Auxiliary Feedwater .
a. Manual Initiation N.A. M.A. N.A. M.A. N.P.
b. Automatic Actuation logic and Actuation

, Re1ays N.A. h.A. N.A. M.A. N.A.

A c. Steam Generator Water (p Level-Low-Low-Start g Motor-Driven Pump and Diesel-Driven Pump 21.1 34.5 33.1.

1)' Unit 1 -2A 18.28 1.5 140-8E of 139-1% of l narrow range narrow range instrument instrument span span

2) Unit 2 . 17.0- 14.78 1.5 117% of 115.3% of narrow range narrow range

, inst.rument instrument span span i

d. Undervoltage-RCP Bus- N.A. N.A. M.A.

Start Motor Driven Pump 15268 volts 14728 volts and Diesel-Driven Pump . ,

e. Sa.4ty Injection-Start Motor-- ,

Driven Pump and See Item 1. above for all Safety Injection Trip Setpoints and Diesel-Driven Pump Allowable Values. '

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TABLE 2.2-1 (Continued)

_2 REACTOR TRIP'SYSTEN INSTRtBENTATION TRIP SETPOINTS g_

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  • SENSOR TOTAL- ERROR Z (SE) TRIP SETPOINT ALLOWA8LE VALUE E FUNCTIONAL UNIT ALLOWANCE (TA) 2.5 1.77 0.6 >90% of loop mini- >89.2% of loop mini-d 12. Reactor Coolant Flow-Low num measured flow
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>M of narrow 1- 18.28 1.5 549MIE of narrow l

a. Unit 1 range instrument range instrument span span 14.78 1. 5 >17% of narrow >15.3% of narrow

>b. Unit 2 ~17. 0 Fange instrument range instrument

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. 12.0 0.7 0 >5268 volts - >4728 volts -

14. Undervoltage - Reactor _

each bus Coolant Pumps-- each bus 14.4 13.3 0 >57.0 Hz >56.5 Hz

15. Underfrequency -~ Reactor Coolant Pumps
16. Turbine Trip N.A. N.A. N.A. >540 psig >520 psig
a. Emergency Trip Header Pressure N.A. N.A. >1% open >1% open
b. Turbine Throttle Valve M.A.

Closure N.A. N.A. N.A. N.A.

17. -Safety Injection Input N.A.

from ESF N.A. N.A. N.A. N.A. N.A.

18. Reactor Coolant Pump Breaker Position Trip
  • Ninimum' measured flow = 97,600 gpa I

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TABLE 3.3-4 (Continued)-

ENGINEERED SAFETY. FEATURES ACTUATIOM MSTEN INSTENENTATION TRIP SEIPOINTS

-TOTAL _ SENSOR TRIP ALLOW 8tE ,

o- FUNCTIONAL UNIT- ALLOWNCE (TA) . -Z ERROR (SE) SETPOINT VALUE~ '

E 5. Turbine Trip and . .

Q Feedwater Isolation (continued)

[. c. Safety Injection See Item 1.-above for all Safety Injection Trip Setpoints and  ;

Allowable Values.

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6.. Auxiliary Feedwater .

a. Manual: Initiation N.A. N.A. N.A. M.A. M.A.
b. Automatic Actuation Logic and Actuation w Relays. N.A. N.A. N.A. N.A. N.A.

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y Motor-Driven Pump and .

Diesel-Driven Pump 21 L 34.3 33.1

>40:M of

1) Unit 1 =27.1 18.28 1.5 , 13Dr1% of l  :

narrow range narrow range i instrument instrument span span

2) Unit 2 17.0 14.78 1.5 >17% of >15.3K.of narrow range narrow range instrument instrument span spar.
d. Undervoltage-RCP Bus- N.A. N.A. N.A. >5268 volts >4728 volts i Start Motor Driven Pump i and Diesel-Driven Pump l
e. Safety Injection-Start Motor-Driven Pump and See Item 1. above for all Safety Injection Trip Setpoints and -

Diesel-Driven Pump' Allowable Values.  !

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. ATIACEtittiLC l

, l EVALUATION _OF_SIGNIFICANT HAZARDS CONSIDERATIONS Commonwealth Edison has evaluated this proposed unendment and determined that it involves no slgnificant hazards considerations. According to 10 CTR 50.92(c), a proposed unendment to an operating license involves no significant hazards considerations if operation of the facility in accordance with the proposed unendment would not

1. Involve a significant increase in the probability or consequences of an accident previously evaluated; or
2. Create the possibility of a new or different kind of accident from any accident previously evaluated; or
3. Involve a significant reduction in a margin of safety.

Tho proposed changes have been reviewed by Commonwealth Edison Co. and Westinghouse in accordance with these criteria. The basis for determining y that no significant hazards considerations are introduced is presented below.

The stenm generator water level instrumentation is a safety grade system designed to actuate a reactor trip due to a loss of heat sink. The basic function of the reactor protection circuits associated with Low-Low Steam Generator Water Level is to preserve the Steam Generator heat sink for removal of long term residual heat. Should a complete loss of feedwater occur, the reactor would be tripped on a Low-Low Steam Generator Water Level. In addition, an auto-start signal is provided at the same setpoint to two redundant auxiliary f eedwater pumps to supply feedwater in order to maintain residual heat removal capability after the trip. The reactor trip acts prior to Steam Generator tube uncovery. This reduces the required auxiliary feedwater capacity, increases the~ time interval before the auxiliary feedwater pumps are required, and minimizes the thermal transient on the Steam Generator and Reactor Coolant System. -The auto-start of the auxiliary feedwater pumps

'at the same setpoint as the trip ensures a secondary heat sink is continually available af ter a trip coincident with a loss of normal feedwater.

The reactor trip function generated at the Low-Low Steam Generator Water Level trip setpoint is assumed to provide primary protection for the loss of Normal reedwater/ Loss of All Non-Emergency AC Power events,.Feedline Break event, Loss of Load / Turbine Trip event and certain cases of the superheated Steam

-Line Break Mass and Energy Release Calculations outside containment. All of r.

these analyses assume a " Safety Analysis Limit" value for the reactor trip setpoint lower-(more conservative) than the nominal Technical Specification trip setpoint value because it must account for.all applicable errors and uncertaintles associated with the Low-Low Steam Generator Level trip function. The " Safety Analysis Limit" value essumed for these accidents for the Low-Low Steam Generator Water Level Reactor Trip / Auxiliary Feedwater initiation was 13.7% of span and remains at that value for the proposed l

l /sc1 ID362:6

. A22ACitiEttLC EVALUATION OLSIGH1flCANT HAZARDLCORSIDERATIDMS (continued) changes. The margin between the original Technical Specifiestion setpoint for l Trip / Auxiliary Feedwater Initiation (40.8%) and the " Safety Analysis Limit" l value of 13.7% contained an excess margin of 7.8% of span. This excess margin j was in excess of that required to account for instrument error and uncertainties identifled in the statistical setpoint study. This change will j permit reduction of the Unit 1 Low-Low Steam Generator Water Level Reactor ,

Trip / Auxiliary Feedwater Initiation Setpoint from 40.8% to 34.8%, reducing the I excess margin from 7.8% of span to 1.8% of span. However, as stated previously, the margin of safety is unaffected since the new Reactor Trip / Auxiliary Feedwater Initiation setpoint is bounded by the original

" Safety Analyses Limit" value used in the applicable safety analyses.

The use of a revised Steam Generator nominal Trip / Auxiliary feedwater Initiation setpoint'does not involve a significant increase in the probability or consequences of any accident previously evaluated. The non-LOCA and LOCA accidents were reviewed verifying that the applicable regulatory or design limit was satisfied for each case defined in the UrSAR. The small and large break analyses which calculate peak cledding temperatures presented in the UFSAR remain valid. In addition, the safety analysis limit of 13.7% of span for the steam generator water level low-low trip setpoint remains unchanged.

The use of a revised Steam Generator nominal Trip / Auxiliary Feedwater Initiation setpoint does not create the possibility for a new or different kind of accident from any accident previously evaluated. Since the accident analysis conclusions as presented in Chapters 3, 6 and 15 of the UFSAR are bounding and remain valid, and no new failure mechanism has been identified, ita possibility of a different accident being created does not exist.

The effect of the revised Reactor Trip / Auxiliary Feedwater Initiation setpoint does not involve a significant reduction in a margin of safety. The i investigation of the affect of these changes on non-LOCA and LOCA transients has' verified that plant operation will remain within the bounds of safe, analyzed conditions as defined in the UFSAR. Conclusions presented in the UFSAR remain. valid. As such, no reduction in the margin of safety between the-UFSAR safety analyses limit and the-Technical Specifications safety limits (such as DNDR or pressure) has taken place for operation with the revised Stenm Generator nominal Reactor Trip / Auxiliary Feedwater Initiation setpoint.

Based on the above, this change will not increase the probability or s consequences of a previously analyzed accident, introduce the possibility of an accident not previously evaluated, or significantly decrease the margin of safety. Therefore, this change does not involve a significant hazards consideration.

/scitID362 7

ATTACIIMENT D

.. ENVIRONMENTAL ASSESSMENT STATEMSHT_ APPLICABILITY REVIEW Commonwealth Edison has evaluated the proposed amendment against the criteria for and identification of licensing and regulatory actions requiring environmental assessment in accordance with 10 CFR 51.21. The proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) in that:

1. The proposed amendment involves no significant hazards consideration (See Attachment C).
2. There is no significant change in the types or significant increase in the amount of any effluents that may be released offsite, and
3. There is no significant increase in individual or cumulative occupational radiation exposure.

Pursuant to 10 CFR 51.22(b), no environmental assessment or environmental impact statement is required with the issuance of the proposed snandment.

/scitID362:8

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