ML20137F822

Proposed Tech Specs Re Operability & Surveillance Requirements for Reactor Trip Sys Instrumentation

ML20137F822
Person / Time
Site:	Callaway
Issue date:	01/09/1986
From:	UNION ELECTRIC CO.
To:
Shared Package
ML20137F764	List: ML20137F757 ML20137F822
References
ULNRC-1240, NUDOCS 8601170583
Download: ML20137F822 (8)

Text

Attachmnnt 3 4- ULNRC- 1240 PROPOSED TECHNICAL SPECIFICATION CHANGES Pages 3/4.3-4 3/4.3-6 3/4.3-9 3/4.3-12 Insert Page

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TABLE 3.3-1 (Continued) ,

g REAC10R TRIP SYSTEM INSTRtJMENTATION h

'i.i

'< NINIMUM

• TOIAL NO. CilANNELS CliANNEL5 APPLICA8LE MODES ACTION g FUNCTIONAL (JNIT Of CilANNELS 10 TRIP DPERABLE

=s y 18. Reactor Trip System Interlocks

a. Intermediate Range Neutron flux, P-6 2 1 2 28# .8

h. Low Power Reactor Trips Block, P-7 -

8 P-10 Input 4 2 3 1 or P-1] Inpet 2 1 2 1 8 Y c. Power Range Neutron Flux, P-8 4 2 3 1 8

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d. Power Range Neutron flux, P-9 2 3 1 8 1

e. Power Rangt Neutron Flux, P-10 4 2 3 1, 2 8

f. Turbine lopulse Chamber Pressure, P-13 2 .

I 2 1 8

19. Reactor Trip areakers 2 1 2 1, 2 9 311 {

, 2 1 2 3*, 4*, Sa 10 ,

20. Automatic Trip and Interlock Logic 2' 1 2 1, 2 9 2 1 2 34, 48, 5* 10 m rrs 5

) 9 o

R 6

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1,

F . . ~ _. . . _ .

', ' TABLE L ?-1 (Continusel .e:endment No. 4 .

ACT*CN STA *:':E!.T S -( Cce t i nM ACTION 4 - With the number of CPERABLE channels one less tha, na Minimum Channels OPERA 8LE requirement .. spend all operations involving positive reactivity cnanges.

ACTION 5 - a. With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the in-

. operable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the Raactor trip breakers, suspend all operations involving positive reactivity changes and verify Valves BG-V178 and BG-V601 are closed and secured in position within the next

, hour. .

b. With no channels OPERABLE, ooen the Reactor Trip Breakers, suspend all operations involving positive reactivity changes h

i and verify compliance with the SHUTDOWN MARGIN requirements )

of Specification 3.1.1.1 or 3.1.1.2, as applicabla, within (

IMour and every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter, and verify valves )

BG-V178 and BG-V501 are :losed and secured in position y within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and verified to be closed and secured in (

position every 14 days.

ACTION 6 - With the number of OPERABLE channels one less than the Total

(

Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and

b. The Minimum Channels CPERABLE recuirement is met; however, the inoperable channel may ba bypassed for un 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 of other channels per Specification 4.3.1.1.

ACTION 7 - With the numcer of OPERABLE channels one less than the Total Numoer of Channels, STARTUP and/or POWER OPERATION may proceed until performanca of the next required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 3 - With less than the Minimum Numcer of Channels OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

ACTION 9 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STAN0BY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one 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 surveillanca testing per Saecification 4.3.l'.1, provided the other channel is OPERABLE.

ACTIC" 10 - With the number of CPERABLE channels ona less than the Minimum Channels OPERABLE recuirement, restore the inoperacle c.annel to GPERABLE status.within a8 hours or open the Reactor trio treakers witnin the 1 ext hour.

ACTION 11 - W.ith the numcer of GPERABLE cnannels less than :na Total Numcer of Channels, caeration may continue provided the inoperable channels are placed in the tripped canaition within i hour.

ACTION 81- 5 4a. IM A CALL".!AY - UNIT 1 3/4 3-i

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TABLE 4.3-1 .

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REACTOR TRIP SYSTEM INjlRIMENTATION SuRVEILL ANCE REQulREMENTS h

4 TRIP .

ANALOG ACluATING HODES FOR CllANNEL DEVICE WHICH fj CilANNEL CliANNEL OPERATIONAL OPERATIONAL ACluATION SURVEILLANCE q fimC110NAI.1MI T CllECK CAtlilRATION TEST TEST LOGIC 1EST IS REQUIRED l

1. M4nual Reactor Trip N.A. N.A. N.A. N.A. 1, 2, 3 * , 4 * , 5*

R (M)

2. Power Range, Neutron flux .

4. liigt: Setpoint S D(2, 4), M N.A. N.A. 1, 2

H(3, 4),

4(4, 6),

R(4, 5)

I

h. Low Setpoint . 5 R(4) M N.A. M.A. IAN, 2

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, m 3.. Power Range, Neutron flux. N.A. R(4) M N.A. N.A. 1, 2

) liluh Positive Rate

$ 4. Power R4n0e. Neutron flux, Iligh Hegativa Rate N.A. R(4) H N.A. N.A. 1, 2

5. Internettiate Ran0e, S R(4, 5) S/u(1),H N.A. ' N.A. 1H#, 2 Neutron flux

6. Source Range, Neutron flux 5 R(4, 5, 12) S/U(1),H(9) N.A. N.A. 2N, 3, 4, 5

1. Overtemperature AT S R(13) M N.A. N.A. 1, 2

8. Overpower AI 5 R H

, N.A. N.A. 1, 2

, '3 . Pressurizer Pressure-Low S P

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M N.A. N.A. 1

( '

-O

10. Pressurizer Pressure-liigh 5 A H N.A. H.A. 1, 2 j  !!.

Pressurizer Water level-lituis S R H N.A. N.A. 1

12. desctor Coolant flow-tow 5 O

R H N.A. N.A. 1 20 g

) TA8LE 4.3-1 (Continuec)

/

TABLE NOTATICNS E "Only if the Reactor Trip System breakers hacpen to ce closed and the Con-trol Rod Drive System is capacle of red witndrawal. .

1. The specified 18 month frecuency may be waived for Cycle I providec :ne surveillance is performed orior to restart following the first refueling [)

outage or June 1,1986, whienever occurs first. The provisions of- },

Specification 4.0.2 are reset from performance of nis surveillance. (

2 M8elow P-6 (Intermediate Range Neutron Flux interlock) Setpoint. .

1. W8elow P-10 (Low Setpoint Power Range Neutron Flux interlock) Setpoint.

(1) If not performed in previous 7 days.

Comcarison of calorimetric to excore power indication above 15%'of RATEU; (2) THERMAL POWER. Adjust excore enannel gains consistent with calorimetric power if assolute difference is greater nan :'%. The provisions of Specification 4.0.4 are not acclicscle for entry into MODE 2 or 1.

(3) Single point comoarison of incere to excore AXIAL FLUX OIFFERENCE above 15% ,

of RATED THERMAL POWER. Recalibrata if tne aosolute difference is greater tnan or equal to 3%. Toe provisions of Soecification 4.0.4 are not appli-cable for entry into M0]E 2 or 1.

(4) Neutron detectors may t a excluden from CHANNEL CALIBRATION.

(5) Detactor plateau curves For shall be cotained, evaluated and ccmaared to manu-tna Intamediate Range- and Fewer Range Neutron Flux facturer's dats.

channels the provisions of Saecification 4.0.4 are not applicaole for entry into MODE 2 or 1.

Incore - Execre Calibration, above 75% of RATED THERMAL PCWER. The provi-(6) sions of Scacifiestion 4.0.4 are not acalicante for entry 'into MODE 2 or 1. s, (7)

Eaca train sna11 be tested at least every 62 days on a STAGGERED TEST SASIS.(2-M (8). Wita power greater than or acual to the intarlock See:oint tne required ANALOG CHANNEL OPERATICNAL TEST snali consist of verifying that the inter-lock is in tne required state ty observing tne pernissive annunciator window.

(9) Monthly surveillanca in NUE5 3", 4", and 5" shall also include verifiestion that permissives F-6 and P-10 are in their recuired state for-existing Mcntaly piant conditions by esservation of the permissive annunciator window.

surveillanca sna11 incluce verification of the Baron 011ution Alarm Set:oint of less nan or equal to an increase of twice tne count rate witnin a 10-minuta period.

(10) Set:oint verifiestion is not required.

f (11) ". ' a m ; r 1:: = m / llowing l 1:aintananca or adjustment of the Reactor trip breakers, tne TRIP ACTUATING OEVICE OPERATIONAL TEST snail include independent verifiestion of tne Uncervoltage and Shunt trips.

(12) At inast. ancs car 13 montas during snutdown, verify that on a simulatad Soron Oilutton Coucling test signal the normal CVC5 disenarge valves alli close anc the cantrifugal cnarging pumas suction valves from the WST will open *itatn 30 seconcs.

(13) CHANNEL CALIBRATION sna11 include tne RTD sypass locos flow rata.

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[I T w $. C. 3/4 3-12 MenCGnt MO. 3 DAL 4WAY - UNIT i

J INSERT A ACTION 12 - With one of the diverse trip features (Undervoltage or Shunt Trip Attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the affected breaXer inoperable and apply ACTION 9.

The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.

INSERT B The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the Undervoltage and Shunt Trip

-Attachments of the Reactors Trip Breakers.

INSERT C (14) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the Undervoltage and Shunt Trip circuits for the Manual Reactor Trip function. The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit.

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Attachmsnt 4 ULNRC-REACTOR TRIP BYPASS BREAKER TESTING In order to assess the need to include bypass breaker testing in the Technical Specifications, the Westinghouse Owners Group (WOG) has calculated the impact of the bypass breakcr failure probability on the reactor trip system failure probability and concludes that the bypass breaker contribution is insignificant. .These calculations are based on the reactor trip breaker fault tree model presented in Supplement 1 to WCAP-10271.

In WOG Letter No. OG-106, which transmitted the WOG response to NRC questions on WCAP-10271, a typical Westinghouse PWR reactor trip unavailability is estimated to be 1.5 E-5. No credit was taken for operation of the bypass breaker in the evaluation from which these calculations were derived. The impact on the reactor trip system unavailability including the unavailability of the reactor trip bypass breakers was calculated with the following results:

1. The bypass breakers are placed in service only when one train of the RPS is in test. The only circumstance in which the bypass breaker could affect RPS unavail-ability is the cutset when one train is in test, a signal is generated in th+ operable redundant train and the main breaker fails to open.

2. The unavailability of the RPS attributable to failure of a main trip breaker with the opposite train in test is 3.7 E -7 or 2.5% of the total RPS unavailability (i.e., 1.5 E -5). This cutset constitutes the only configuration in which the bypass breaker can affect RPS unavailability.

3. Taking credit for the bypass breaker would reduce the probability value of this cutset to (3.7 E -7) (3.5 E -4) = 1.3 E -10 where 3.5 E -4 is the unavailability of the bypass breaker assuming bimonthly testing or, (3.7 E -7) (3.5 E -3) = 1.3 E-9 where 3.5 E -3 is the unavailability of the bypass breaker assuming testing on an 18 month interval.

Based on the above, it is Union Electric's position that testing of bypass breakers is not necessary in the Callaway Plant Technical Specification periodic test of the main trip breakers.

As shown above, testing the bypass breakers on a 2 month or 18 month test interval will result in a E -9 or E -10 level

g. .~

Attcchmsnt 4 ULNRC-contribution to the RPS unavailability of approximately E -5.

Alternatively, the RPS unavailability increase that occurs by increasing the bypass breaker failure probability from 0% to 100%

is only 2.5% at the RPS level.

Given the minimal impact of bypass breaker testing it is ,

recommended that.Callaway Plant be allowed to administratively control bypass breaker testing outside of the technical specifications.