ML20205P954

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Proposed Tech Specs,Adding Silicon Controlled Rectifier to Functional Unit Lists for Table 3.3-1, Reactor Protection Sys Instrumentation & Table 4.3-1, Reactor Protection Sys Instrumentation Surveillance Requirements
ML20205P954
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 03/27/1987
From:
TOLEDO EDISON CO.
To:
Shared Package
ML20205P917 List:
References
TAC-55352, TAC-59932, NUDOCS 8704030413
Download: ML20205P954 (10)
v • d • e


Text

/$2:

Sirial No. 1312 THIS PAGE PROVIDED FORINFORMATION ONLY 3/4.3 !?lSTRUMENTATICN '

3/4.3.1 OEACTOR PROTECTICN SYSTEM I'ISTRUMENTATIC?l LIMITI!!G CONDITION FOR OPERATICN 3.3.1.1 As a minimum, the Reactor Protection fystem instrumentation-channels and bypasses of Table 3.3-1.shall be-0PERABLE with RESPONSE TIMES as shown in Table 3.3-2.

APPLICABILITY: As shown in Table 3.3-1.

ACTICN:

As shown in Table 3.3-1.

)-

SURVE!LLANCE REQUIREMENTS 4.3.1.1.1 Each Reactor Protection System instrumentation channel shall be demonstrated OPERABLE by the performance of the CHATIEL CHECK, CHA'n;EL CALIBRATICN and CHANNEL FUNCTIONAL TEST operations during the MODES and at tne frequencies shown in Table 4.3-1.

2.3.1.1.2 The total byoass function shall be demonstrated CPEF.AELE at least once cer 18 montns during CHA?iNEL CALIBRATI0tt testing of ea:h  ;

channel affected by cypass operation.

4.3.1.1.3 The REACTOR PROTECTION SYSTEM DES?ONSE.T!ME of-sach reactor trip function shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one channel per functior such that all channels are tested at least once every N ti: es 18 month 3 where N is tne total number of redundant channels in a s:ecific reacter  :

trip function as shown in the " Total No. of Channels" column of Tacle l 3.3-1.

DAVIS-SESSE, UNIT 1 3/4 3-1 l

58.* m,

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ERE Ma

]ABLE 3.3-1 $$f

" Tw*%f a REACIOR PROTECTIUN SYSTEM INS 1RUMENTATION U

, g .

it!NIMUM A, TOTAL NO. CitANNEL S CllANNELS APPLICABLE g FUNCTIONAL UNIT OF CilANllELS TO TRIP OPERABl.E MODES ACIl0N

1. Mariual Reactor Trip 2 1 2 1, 2 and
  • I C

,5 2. liigh flux 4 2 3 1, 2 '2#

2 3. RC liigh Temperature 4 2 3 1, 2 3#

, 4. I' lux - A flux - flow 4 2(a)(b) 3 1, 2 2#

5. RC Low Pressure 4- 2(a) 3 1, 2 3#
6. RC liigh Pressure 4 2 3 1, 2 3#
7. RC Pressure-Temperature 4 2(a) 3 1, 2 3#
8. Iligh Flux / Number of Reactor Coolant Pumps On 4 2(a)(b) 3 1, 2 3#
9. Contairuiiesit liigh Pressure 4 2 3 1, 2 3# ,

R 10. Intennediate Range, Neutron flux a and Rate 2 0 2(c) 1, 2 and

  • 4 A, 11. Source Range, Neutron Flux and Rate A. Startup 2 0 2 24# and
  • 5 B. Shutdown 2 0 l' 3, 4 and 5 6

, 12. Control Rod Drive Trip Breakers 2 per trip 1 per trip 2 per ,

1,.2 and

  • 7#, 9 # l t system system trip system

-! 13. Reactor Trip Module 2 per trip 1 per trip 2 per 1, 2 and

  • 7#

system system trip system

14. Shutdown Bypass liigh Pressure 4 2 3 2**, 3** 6#

4**, 5**

Is. Sc.R Relay.s 2. 2. 2. . s> 2. and + sod

/ .

Dock';t No. 50-346.

P Lic:nts No. NPF-3 y ,4

'Scrial No. 1312- '

in t0RINFOREil0N DE TABLE 3.3-1 (Continued)

TABLE NOTATION

  • With the control rod drive trip breakers in the closed position and the centrol: rod drive system capable of rod' withdrawal.

"When Shutdown Bypass is actuated.

  1. The provisions of Specification 3.0.4 are not applicable.
    1. High voltage _ to detector may be .de-energized 'above 10-10 amps en both I Intermediate Range channels.

(a) Trip may be manually bypassed when RCS pressure 1 1820 psig by actuating Shutdown Bypass provided that:

(1) The High Flux Trip Setpoint is 1 % of5 RATED THEPPAL PCWER, (2) The Shutdown Bypass High Pressure Trip Setpoint of 1 820 1 psig is imposed, and (3) The Shutcown Bypass is removed when RCS pressure > 1820 p:ig.

(b) Trip may be manually bypassed when ~ Specification 3.10.3 is in effect. <

I (c) The minimum channels OPERABLE requirement may be reduced to one wnen Specification 3.10.1 or 3.10.2 is in effect. l ACTION STATEMENTS l

ACTICN 1 -

With the number of channels OPEPABLE :ne less than required by the Minimum Channel: OPERABLE requirement, restore tr.e inoperable channel to OPERABLE status within t3 hours er l be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/ r open the control rod drive trip breakers.

ACTION 2 - With the nuccer of 0FERABLE channels one less than the Total Number of Channels STARTUP and/or PC',iER OPERATION may proceed provided all of the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within ene hour.
b. The Minimum Channels OPERABLE requirement is. et; however, one additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1.1, DMIS-BESSE, UNIT I 3/4 3-3

Dock t No. 50-346 Licin:o No. NPF-3 Snrici No. 1312 k hb It,U 5 MdL h f FORINFORffAiiD1DNIY TABLE 3.3-1 (Continued ACT!ON STATEME*iTS (Contirued) and the inoperable channel above may be bypassed for up to 30 minutes in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> perico when necessary to test the trip breaker associated with the logic of the channel being tested per Specification 4.3.1.1.1, and

c. Either, THERMAL POWER is restricted to < 75% of RATED RATED THERMAL and the High Flux Trip Setooint is reduced to < SS" of RATED THERMAL POWER witnin a hours or the QEADRANT POWER TILT is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTIC13 -

Witn the number of CPERABLE channels one less than the Total Number of Channels STARTUP and POWER OPERATION may proceed provided both of the following conditions are satisfied:

. a. The inoperable channel is placed in the tripped condition within one hour,

b. The Minimum Channels OPERABLE requirement is met; however, one additional cnannel may be bypassec for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specificati:n a.3.1.1.1, and the inocerable channel above may be bycassed for uo to 30 minutes in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period when necessary to test the trio creaker associated with the logic of the cnancel being tested per Specification 1.3.1.1.1.
C
C'. * -

With the number of char.nels CPE3)3LE one less tran re-cuired by the Minimum Channels OPERABLE recuirement and with the THERMAL Power level:

a. < 5'; of RATED THERMAL PCWER restcre Obe incper231e channel to OPERABLE status prior to increasing THEP24AL POWER above 55 of RATED THERMAL PC'aER.
b. > 55 of RATED THERMAL CWER, POWER OPERAT:C?i may continue.

CA'/IS-5EE5E, 'JNIT l 3/4 3-4

- Dockst No.L 50--346 i Licin!u No..NPF

  • 2Strial No. 1312 TABLE' 3.3-1 (ContiEued)

ACTION STATEMENTS (Cantinued)-

ACTION 5 - With the number of-channels CPERABLE ene less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a. 3, 10-10 amps on the . Intermediate Range -(IR)in-strumentation, restore the inocerable channel to' OPERABLE gatus prior to increasing THERMAL POWER above 10' amps on the IR instrumentation.
b. > 10-10 acos on the IR instrumentation, operation may continue.

ACTION 6 - With the number of channels OPERABLE one'less than re-quired by the Minimum Channels OPERABLE requirement, verify compliance with the SHUT 00WN MARGIN requirements of Specification 3.1.1.1 within one hour and at _least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> .thereaf ter.

ACTION 7 -

With the number of OPERABLE channels one less than the Total N=ber of Channels STARTUP and/or POWER OPERATION may proceed provided all of the following conditions are satisfied:

) a. Within I hour:

1. Place the inoperable channel in the trip;ed .

i condition, or

2. Remove ;cwer supplied to the control ~ roc trip Avice associated with the inoperative channel.

I **

b. One additional chanrel may ce byoassed f ar up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Soecification 4.3.1.1.1, and the inoperable cr.annel abcvs may be byparsed for to 30 minates in any 24 tour period wnen necessary to test the trip breaker assccisted with the logic of tne channel being tested per Specification 4.3.1.1.1. The inoperaale channel aucve

, muy net be bypassed to test the logic o# a cnannel

! of the trip system associated with tne inoperable cnannel.

ACTICN 3 -

Witn the nuccer of channels OPERA 3LE less than recuired by the Minimum Channels OPERA 3LE requirement, te in at least.

HOT STANCBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

.Tn.ser4 "A" OA'/IS-3E3SE, UNIT 1 3/4 3-5 i

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DocketiN2.: 50-346' Lic:nsd No. NPF-3

' Serini No. 1312 INSERT '?A" ACTION 9 - With one of'the Reactor Trip Breaker diverse trip features (undervoltage or shunt trip devices) inoperable, restore

, it to OPERABLE status in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> ~ or place .the breaker in trip in the next hour.

' ACTION 10'- ~ With one or both channels of SCR Relays' inoperable,.

restore the channels to OPERABLE status during the next COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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TABLE 3.3-2 -

WZO U "2 REACTOR PROTECT 10ll SYSTEM INSTRUMENTATION RESP 0ll5E TlHES

v. ,,

t RESP 0tlSE T!HE5**

E FUt{CTIONAL UNIT U ' (seconds')

s m ' *

i. Manual Reactor Trip ' Not Applicable c

_.c

2. liigh Flux
  • 1 0.266

[ Not Appilcable

3. RC liigh Temperature
4. Flux - A Flux - Flow * - Variable Flow 1 1.77

' - Constant Flow 1 0.266 t

5. RC Low Pressure 1 D.341 u

1

< 0.341 m D 6. RC liigh Pressure --

===4#

w E 7. RC Pressure - Temperature - Constant Temperature Hot Applicable  %

C/>l

< 0.4 51 * *

  • g
8. High . Flux / Number of Reactor Coolant Pumps On* _.
9. Contal'nment liigh Pressure Not Applicable [ ag:sn

-

  • y m,
mg e)3t r=rt, -*

3ll48

! y N

  • Hautron detectors are exempt from response time testing. Response time of the neutron flux d .

R signal portion of the channel shall be measured from detector output or input of first electronic g OE.g S coniponent in chaune1. - .

    • Including sensor (except as noted), RPS instrument delay and the breaker delay. gC jf
      • A 0.24..sec delay tine has been assumed for puny contact monitor. g PT"5 N'

&M i

E' E E EE 4~

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" 7' W g 1ABLL 4.3-1 ,

5 HEACTOR PROTECTIO:1 SYSTEH IllSTilllNENTATION SURVEILLANCE REQUIRENENTS

.n

Ul .

CilANNEL H0 DES IN WHICH I E CilAt4NEL CllANNEL F11NCTIONAL SURVEILLANCE FUNCTIONAL UNIT CilECK CALIllRATIO 1 TEST

{i REQUIRE 0

1. Manual IIcactor Trip . N.A. N.A. S/U(1) N.A.
2. Illgli flux 5 D(2). cud Q(7) It .

1, 2

3. RC liigh leciperature S R H 1. 2

~

4. Flux - Aflux - flou- S(4) M(3) and Q(7.8) H 1. 2

~

~

5. NC Lou Pressure 5 -R'** H 1. 2
6. IIC liigh Pressure S R*** H 1, 2 w 7. RC Pressure-Twiperature S R H 1. 2 8 liigh flux / Number of Reactor

[, Coolant Pumps un S R H 1. 2

7. Containaent liigh I ressure . S R H .
1. 2
10. Inte wediate Range, ileutron 3

Flux and lu.te S R(7) S/U(5)(1) 1. 2 and* ,

d 11. Sousce Range. Heutro.. Flux -

E' and Rate 5 R(7) H and S/U(1)(5) 2. 3. 4 and'5

12. Control Rod Uri m Trip ureskers li . A . N.A. MkndS/U(1)(9) 1. 2 and*

j 6

13. ;teactor Trip Hodale Lugic H.A. -

N.A. -

H 1. 2 and*

14 Sliotdonn Bypa.s liigh i'ressura S R. H 2**.3**.4** 5**

l h

_! l 5*. SC R Reldys sh . AlA R I,2 and v O .

Docket No. 50-346 1

. Licen'e s No. NPF-3 I Serial No. 1312 TAst.! 4.3-1 (Centinued) l NOTATION (1) - If not perfor=ed in previous 7 days.

(2) - Heat balance only, above 15% of RATED THERMAL F0WER.

(3) -

When THERMAL PCWER (TP] is above 30% of RATED THETO'AL POWER (RTP], compare out-of-core c:easured AXIAL POWER IMBALANCE (API ] to incere measured AXIAL POWER IMSALANCE -

[ API].g Recalibrate if:

h [ API, - API ] gy,,3.5%

(4) - AX1AL POWER IMSALANCE and 1cep flow indications only.

4 (5) - Verify at least ene decade overlap if not verified in previcus 7 days. .

(S) - Each train tested every other inonth.

(7) - Neutron detectors r.ay be excluded frein CHANNEL CALI3 RATION.

(3) - Flow rate measurement sansers may be excluded frem C4ANNEL CALIBRATION. Mowever, each flow mea:urement sensor shall be calibrated at least once per 18 months.++*

N $$o$$AYunde?N$ab$6 apY?f$lhhWj[]' p

  • - With any control red drive trip breaker close-.
    • - Wen Shutdown Sypass is actuated.

i Eighteen-month :urveillance test due in March 1952 delayed until Maren 31, 1932. .

l l

l l

I 2AVI3.-3E35E, UNIT 1 3/4 3-8 Amendment .'io . .:3

Docket No. 50-346 ,

License No. WPF-3 l S'e rial No. 1312 3/4.3 !NSTRUMENTATION BASES FORINFORWl0N OMY l j 1

3/4.3.1 and 3/4.3.2 REACTOR PROTECTION SYSTEM Akg ,

5 M TTY 5Y5 TEM INSTRUMENTATION l The OPERABILITY of the RPS, SFAS and SFRCS instrumentation systems l ensure that 1) the associated action and/or trip will be initiated when '

the parameter monitored by each channel or combination thereof exceeds its setpoint 2) the specified coincidence logic is maintained, 3) sufficient redundancy is maintained to pennit a channel to be out of service for testing or maintenance, and 4) sufficient system functional capability is available for RPS, SFAS and SFRCS purposes from diverse parameters.

The OPERABILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility design for the protection and mitigation of accident and transient con-di t. ions. The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.

ihe surveillance requirements specified for these systems ensure that the overall systen functional capability is maintained comparable to the original design standards. The periodic surveillance tests perfonned at the minimum frequencies are sufficient to demonstrate this capability.

The measurement of response time at the specified frequencies provides assurance that the RPS, SFAS, and SFRCS action function associated l with each channel is completed within the time limit assumed in the safety analyses. No credit was taken in the analyses for those channels with response times indicated as not applicable.

Response time may be demonstrated by any series of sequential, overlapping or total channel test seasurements provided that such test demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either 1) in place, onsite or offsite test measurements or 2) utilizint replacement sehsors with certified response times.

An SFRCS channel consists of 1) the sarsing device (s) 2) associated logic and output relays (including Isolation of Main Feedwater Non Essential Valves and Turbine Trip), and 3) power sources.

Safety-grade anticipatory reactor trip is initiated by a turb.ine trip (above 25 percent of RATED THERMANL POWER) or trip of both main feedwater i

pump turbines. This anticipatory trip will operate in advance of the reactor coolant system high pressure reactor trip to reduce the peak-reactor coolant systes pressure and thus reduce challenges to the power i operated relief valve. This anticipatory reactor trip system was

, installed to satisfy Item II.K.2.10 of NUREG-0737.

l l

DAVIS-BESSE Unit 1 8 3/4 3-1 Amendment No. 73 .

_ __ _ __ _ - _ _ _ _ _ _ _ ._. __ . . _ . . . _ . _ . _ . _ _ _ _ _ _ _ _ _

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