ML19319B919
| ML19319B919 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 04/06/1977 |
| From: | Roe L TOLEDO EDISON CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8001290654 | |
| Download: ML19319B919 (6) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _
u.s. NUCLEAR RICULATORY COWUSSION _:2.0,* 4 ]R{
DOJCET NUM NRC%cRM M5 n
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NnC DISTRIBUTION POn PART 50 DOCKET MATERIAL TO:
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FROM:
DATE OP OCCUMENT Toledo Edison Company 4/6/77 Mr. John F. Stolz Toledo, Ohio oxyg,geaive o Lowell E. Roe 4/15/77
.XETTE R O NOTORIZ E D PROP tNPUT PORM NUMBER OF COPIES RECEIVED
} $h.&/Uk or DESCRIPTION ENCLOSURE Ltr. trans the following:
Consists of information concerning the Unit No. 1 Saf ety Analysis....
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(5-P)
PLANT-NAME:
Davis-Besse RJL SAFETY FOR ACTION /INFORMATION FNUTun
/ ASSIGNED AD:
Va sse //o AggTr NPn An.
[ BRANCH CMTUFr
_Sfo/L RRAMcM r'WTFT.
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PROJECT MANAGERt En A / e.
PROJECT FANAGER:
/ LIC. ASST. :
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INTERNAL DISTRIBUTION
/TREG FT3W SYSTEMS GAFETY PLANT SYSTEMS SITE SAFETT & -
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l 7 onc PDR HEINEMAN
/ TEDESCO ENVTRO ANAINSTS
/ I & E [1)
SCHROEDER
/ BENAROYA DENTON & MT'TT ru i
OELD
/ tlTNAM GOSSICK & STAFF ENGINEERING
/
'PPOLITO ENVIRO TECH..
MIPC mar.ARRY KTRKWOOD ERNST i
CadE
/
BOS W BALLARD i
HANAUER
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OPERATING REACTORS YOUNGBLOOD I
HARLESS
/1 PAWLICKI STELLO SITE TECH.
PROJECT MANAGEMENT REACTOR CAFETY OPERATING TECH.
p' GAMMILL [A)
BOYD
/
ROSS EISENHUr STEPP P. COLLINS
/
NOVAK SHAO HULMAN HOUSTON
/
ROSZTOCZT BAER PETERSON
/
CHECK BUILER SITE ANALYSIS MELTZ GR'MES
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VOLLMER HELTEMES AT & I
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BUNCR SKOVHOLT SALTZMAN
/ J. COLLINS RUTBERG I
/ KREGER EXTERN AL DISTRIBUTION CONTROL NUMBE R
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NAT. LAB:
BROOKHAVEN MAT. TAR _
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CONSULTANTS :
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NECPORM 196[2 73) 8 0 012$0 [57 4 "
TOLEDO mm EDISON
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LOWELL E. ROE Docket No. 50-346
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..n April 6, 1977 i
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Serial No. 261 i,..; 2" C s.
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Director of Nuclear Reactor Regulation gqp ggg ngp!
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Mr. John F. Stolz, Chief ILLut Lnl Uni UUL%..
0.. U U I.lj Light Water Reactor Branch No. 1
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Division of Project Management United States Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Stolz:
The Davis-Besse Nuclear Power Station Unit 1 Technical Specification Bases 2.2.1 states in part that "...each Allowable Value is equal to or less than the drift allowance assumed for each trip in the Safety Analyses."
In general the Safety Analyses took credit for periodic testing and calibration of the instrumentation. A conservative drift rate was applied to the trip setpoint along with other instrument uncertainties to determine the value that the parameter assumed in the Safety Analyses.
This conservative drift rate would then give a different drift for a monthly Channel Functional Test than for 'n 18 month Channel Calibration.
Therefore, the attached changes to the Da'is-Besse Nuclear Power Station Unit 1 Technical Specifications provide these dual allowable values which will also be included in the next revision of the FSAR.
Yours very truly, i
1 Attachment dh c/18 THE TOLEDO EDISON COMPANY EDtSON PLAZA 300 MACISCN AVENUE TOLEDO. CHIO 43652
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TABLE 2.2-1 9
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y REACTOR PROTECTION SYSTEM INSTRU!iENTATION TRIP SETPOINTS cn
.c U
FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES M
[-
1.
Manual Reactor Tril Not Applicable Not Applic;' 'e
~
2
- i 2.
High Flux
< 105.5% of RATED TilERMAL POWER
< 105.6% of RATED THERMAL POWER r
With four pumps operating sith four pumps operating * * *
- b
< 80.7% of RATED TilERMAL POWER
< 80.8% of RATED THERMAL POWER with three pumps operating Eith three pumps operating * * *
)
1
.i
< 53.0% of RATED TilERMAL POWER with
< 53.1% of RATED THERMAL POWER with
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one pump operating in each loop one pump operating in each loop * * *
.k.
3.
RC liigh Temperature
< 619*F
< 619.08 * *
- j{
'Y; 4.
Flux - A Flux-Flow (I)
Trip Setpoint not to Allowable Values not to exceed exceed the limit line of the limit line of Figure 2.2-2. * *j
- L' Figure 2.2-1.
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II)
LO 5.
RC Low Pressure
~> 1985 psig
> 1976.5 psig
- E 1984.0 psig * *
' E.)
-].4 6.
RC High Pressure 1 2355 psi 9 1 2363.5 psig
- i 9356.0 *
- d; RC Pressure-Temperature (j)
> (13.01 T F - 5973) psig f.!13.01 OF - 5973.64) psig h *
- 7.
T
'g,-,
out out If k' i?
Yg*;4 For Channel Calibration
.f n
'i For Channel Functional Testing (7
- A' *The -110wable value for channel calibration is the same as the allowable value for channel functional testing.
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TABLE 2.2-1 REACTOR PROTECTION SYSIEM INSTRUMENTATION TRIP SETPOINTS
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FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES
- f jq M
8.
High Flux / Number of
< 55.0% of RATED THERMAL POWER
<55.28% of RATED THERMAL POWER g) p,'-
g Reactor Coolant Pumps On with one pump operatiag in each with one pump operating in each f, i.
g loop loop
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< 0.0% of RATED THERMAL POWER with
<0.28% of RATED THERMAL POWER with two pump operating in one loop and two pumps operating in one loof nd no pumps operating in the other loop no pump operating in the other ioop
't
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< 0.0% of RATED THERMAL POWER with
< 0.28% of RATED THERMAL POWER wi th
/AI no pumps operating or only one pump no pumps operating or only one pump e,
opera ting operating * *
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9.
Containment Pressure High
< 4 psig
, 4 psig i-t's k
%'x J
b b } Trip may be manually bypassed when RCS pressure < 1820 psig by actuating Shutdown Bypass provided that:
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The High Flux Trip Setpoint is < 5% of RATED THERMAL POWER b.
The Shutdown Bypass High Pressure Trip Setpoint of < 1820 psig is imposed, and The Shutdown Bypass is removed when RCS Pressure > T820 psig.
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For Channel Calibration C
M
- For Channel Func*ional Testing
)
- * *The allowable value for channel calibration is the same as the allowable value for channal
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func-lonal testing.
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TABLE 3.3-4 o
E SAFETY FEATURES ACTUATidN SYSTEi! INSTRUMENTATION TRIP SETPOINTS r
70 01 FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES M
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INSTRtNENT STRINGS z
a.
Containment' Radiation 1
- mR/hr mR/hr * *
)
b.
Containment Pressure - High 1 18.4 psia 1 18.52 psia *
- c.
Containtnent Pressure - liigh-liigh 1 38.4 psia 1 38.52 psia *
- d.
RCS Pressure - Low 1 1620.75 psig
> 1615.75 psig *
- e.
RCS Pressure - Low-Low
> 420.75 psig
> 415.75 nsig **
w f.
BWST Level
> 49.5 and < 55.0 in. 11 0
-> 48.3 and 2
1 56.7 in. H 0
- 2 SEQUENCE LOGIC CilANNELS a.
Essential Bus Feeder Breaker Trip (90%)
> 3744 volts for
> 3558 volts for 10 + 1.5 sec
_ for 10 + 1.5 sec*
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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 CilANNELS
$ 530 4 535 **
3 381 5 376' *
- a.
Decay lleat Isolation Valve psig
- psig
- To be determined af ter full power testing
[.
- The allowable value for channel calibration is the same as the allowable value for channel functional testing
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TARLE 3.3-12 El
- 5 STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM
'f INSTRUMENTATION TRIP SE1 POINTS E$
FUNCTIONAL UNITS TRIP SETPOINTS ALLO'.!ABLE VALUES l.
Steam Line Pressure - Low 3.591.6 psig 1 586.6 psig ***
.2.591.6 psig ***'j 2.
Steam Generator Level - Low
- 3,20" H O 1 20" 11 0 * * * *
- 2 2
3.
Steam Generator Feedwater Dif ferential Pressure,- liigh**
3,197.6 psid
- 3. 19 fJ. 6 p s i d * *
- 2;197.6 psid ****
4.
Reactor Coolant Pumps - Loss of High 1 1384.6 amps 1 1384.6 amps Low 3.
106.5 amps 3.
106.5 amps *** **
R u
Y O!
- Measured above the lower steam generator tubesheet.
i
- **Where differential pressure is steam generator minus feedwater pressure,
- *
- For Channel Calibration
- * *
- For Channel Functional Test
- * * *
- The allowable value for channel calibration is the same as the allowable value for channel functional
- n testing.
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