ML19319C041

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Notifies That Facility FSAR & Tech Specs Will Be Revised to Allow Safety Features Actuation Sys High Radiation Setpoint to Be Established After Full PWR Testing.Setpoint Tables Encl
ML19319C041
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 04/04/1977
From: Roe L
TOLEDO EDISON CO.
To: Stolz J
Office of Nuclear Reactor Regulation
References
255, NUDOCS 8001300772
Download: ML19319C041 (5)


Text

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NFtCFOnM 195 U.S. NUCLE AR F.EGULATORY COP"";SSION 00

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. 5 0== 3 e216i NRC DISTRIBUTION FOR PART 50 DOCKET M ATERI AL FROM:

DATE OF D UMW TO:

J, y, goLZ TOLEDO, EDISON 4/ /77 TOLEDO, OHIO ATE RECf j;Dy E

L.E. ROE 4

% E.TTER ONOTORIZED PRCP INPUT FORM NUMBER OF COPtES RECElvED URIGIN AL M NC L ASSIFIE D C C C"'

1 STCNED OE S C RIP TIO N ENCLOSU R E LTR. ADVISING THAT THE FSAR AND TECH. SPECS W LL REVISED TO ALLOW THE SFAS HIGH RADIATION SETPC INT TO BE ESTABLISHED AFTER FULL PWR TESTING.....

W/ ATTACHMENTS....

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NCC FORM 195(2 76)

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%m EDISON LOWELL E. roe Docket No. 50-346

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April 4, 1977 Serial No. 255

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Director of Nuclear Reactor Regulation Attn:

Mr. John F. Stolz, Chief Light Water Reactors Branch No. 1

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Division of Project Management

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United States Nuclear Regulatory Cocmission Washington, D.C.

20555 s n w-

Dear Mr. Stolz:

In establishing the setpoints for the Safety Features Actuation System (SFAS) it has recently come to our attention that because of neutron streaming inside the containment, the background gamma radiation level inside containment may be higher than the SFAS high radiation setpoint (25 mr/hr). The Davis-Besse Nuclear Power Station Unit No. 1 FSAR and Technical Specifications will be revised as shown in the attachments to allcw the SFAS high radiation setpoint to be established after full power testing. The high radiation trip setpoint is not relied upon during unit operation in any accident analyses, but rather provides a second backup to the RCS low pressure trip and the containment high pressure trip.

Therefore, there is no risk to safety created by the changes to the FSAR and Technical Specifications as attached.

Yours very truly, glhr dh d/13 l

Attachments:

Davis-Besse Nuclear Power Station Unit 1 FSAR, Pages 7-88 and 7-90 and Technical Specification Page 3/4 3-13 THE 'CLECO ECISCN CCMPANY ECISCN PLAZA 300 MACISCN AVENUE TCLECO, CHIO 42652

TABLE 3.3-4 b

SAFETY FEATURES ACTUATION SYSTEl4 lilSTRtMENTATION TRIP SETPOINTS G

m' Io' FUNCTIONAL UNIT TRIP SETPOINT_

Al.LOWABLE val.UES r's INSTRtI4ENT STRINGS c=

Q a.

Containment Radiation 1

  • mR/hr 1*

..iH/hr b.

Containnwnt Pressure - High 1 18.4 psia 1 18.52 psia c.

Containment Pressure - liigh-liigh 1 38.4 psia 1 38.52 psia d.

RCS Pressure - Low t 1620.75 psig

> 1615.75 psig e.

RCS Pressure - Low-Low

> 420.75 psig

> 415,75 psig u

f.

BWST Level

> 49.5 and < 55.0 in.110

-> 48.3 and 2

-'^'

1 55.7 in. H O 2

SEQUENCE LOGIC CllANNELS a.

EssentialBusFeederBreakerTrip(90%)

> 3744 volts for

> 3558 volts for 10 + 1.5 sec for 10 & l.5 sec b.

Diesel Generator Start, Load Shed on Essential Bus (59%)

> 2071 and < 2450 volts

-> 2071 and < 2450

~ for 0.5 + 0.1 sec volts for-

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0.5 + 0.1 sec INTERLOCK CllANNELS 1 1!0 psig 2

Decay lleat Isolation Valve 1 280 psig a.

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  • To tie determ ne.i arter rott power testing i

Table 7-5.

SFAS Actuation Summary Operational limits under power and Margin between normal 11easured generating hot-standby operttional limits station variable Protective action syste-m or.e rn t i on Trip setpoints and trip setpoints

1. CV radiation Sturt. emergency ventillat. ion To be deterrained after full power t sting 27 i

system Cloce CV purge valve isola-To be determined after full power testing tion system 11.16 paia 118.4 psia h psi

2. CV pressure St. art emergency ventilution 4

system (118.52 psia) psia 118.h psia la psi Close CV purge valve isola-14.14 tion system (118.52 psia) i (118.h psia 14 psi 1

14.16 pula St. art high pressure 118.52 psia) injection aystem pain la psi (118.1 11.l: psia St. art containment air 6

4 118.52 psia) cooling system with

-o Y

fan in low speed.

to co as 14 psi (118.1 13.14 psia 4 psia St.arL component cooling 4

118.52 psia) unter system 14.16 ps2 a 118.h psia (118.52 psia)l 1

4 psi Start, service water system 11.h pula 118.h psia la psi St.;rt.er.w'y diesel 4

gene rat.or (118.52 psia) 6 psia I* psi (118.1 ll.l+ pala Clone CV inolat, ion system i

118.52 psia) 11 0. 1 and 2 16 psi 11.14 psia 118.l; pain St.a rt low pressure inj ec-4 t ion nyut.em (118.52 psia) si Start Containment spray l le.16 psia s 38. li pela 24 psi a

l l1 system T138.52poia)

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I psia 24 psi l

sj Close CV isolation system l le. li pala 138.1 4

Ho. 3 (138.52 puin)

3. Itc pressure Start emergency ventilat. ion 2185-2250 psig 11620.75 psig 585-650 psi i

synt em (11615 75 psig) 4 Clone CV purge valve 2185-2250 psig 11620,75 psig 585-650 psi Inolat.lon Syst.em (11615.75 psig) i I

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