ML20097F350

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Proposed TS Table 4.3-1 Re Reactor Trip Sys Instrumentation Surveillance Requirements & 3.3-3 Re Testing ESFAS Instrumentation
ML20097F350
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 06/08/1992
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20097F346 List:
References
NUDOCS 9206150259
Download: ML20097F350 (8)
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Attachment 2 Proposed Technical Specification _ Change North- Anna Units 1 and 2 l

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TABLE 4.3-1 (Continued) z REACTOR TRIP SYSTEM INSTRUMENTAT!ON SURVFi' f ANCE REQUIREMEPHS O

CHAbte. MODESIN WHCH d

I CHAPNEL CHAffEL RfCT10NAL SURVEILL44CE

> FUNCTIONAL UNIT CHECK CAIIARATION TEST REQUIRED Z

Z

> 13. Lossof Flow-Two Loops S R NA -

1 l

14. Steam Generator Water Level- S R M 1, 2 z

9 Low-Low a

15. SteanVFeedwater Flow Minnatch S R M 1, 2 and Low Steam Generator 'Nater Level
16. Undervoltage-ReactorCoolant NA R NA 1 Pump Busses ca E 17. Underfrequency - Reactor Coolant NA R NA 1 (d - Pump Busses ca
18. Turbine Trip -

A Low Auto Stop Oil Pressure NA NA S/U(1) 1, 2 B. Turbine Stop Valve Closure NA NA S/U(1) 1, 2

19. Safety injection input from ESF NA NA M(4) & (5) 1, 2
20. Reactor Coolant Pump Breaker NA NA R NA Position Trip 3

e Reactor Trip Breaker NA NA M(5), (8), & (10) 1, 2, & *

21. A S B. Reactor Trip Bypass Breaker NA NA M(5), (8), & R(9) 1, 2, &
  • 3

$ 22. Automatic Trip Logic NA NA M(5) 1, 2, &

  • 2 9

I 1

TABLE 3.3 3 ICantinued)

ACTION 17 - With the number of OPERABLE channels one less than the Total Number of Channels i operation may proceed 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 /> and the Minimum Channels OPERABLE requirement is met. One l additional whannel 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 4 Specification 4.3.2.1.1, ACTION 18 - With the number of OPERABLE Channels one less than the Total Number of Channels, restore the Inoperable 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 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 ' i COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, ACTION 19 - With the number of OPERABLE Channels one less than the Total Number of Channels, I 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 />,
b. The Minimum Channels OPERABLE requirement is met; however, one additional l 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 survsillance testing per Specification 4.3.2.1.1. j ACTION 20- With the number of OPERABLE Channels one less than the Total Number of Channels, be j in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and at least HOT SHUTDOWN within the i following 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 surveillance testing por Specification 4.3.2.1.1 provided the other Channel la OPERABLE.

ACTION 21 - With the number of OPERABLE Channels one less than the Total Number of Cnannels,  ;

restore the inoperable 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 be in at least ' l 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 in at least HOT. SHUTDOWN within the l following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. .l l

l NORTH ANNA- UNIT 1 3/4 3-22 Amendment No.46,33, l

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TABLE 4.31 tContinued)

Z -

O REACTOR TRIP Shi INSTRUMENTATION SURVAf f ANCE REOt3REMENT S O

$ CFWM MODESIN WHICH

> C;M CWMEL REJCTIOr4Ai. SUiWEft1ANCE y FUNCTIONAL UNII CHECK cat IARATION TEST R EOUIR ED_

C

13. I.oss of Flow-Two Loops 3 R NA 1 Z

q 14. Steam Generator Water Level- S R M 1, 2 to Low-Low

15. Steam /Feedwater Flow Mismatch S 'R M 1, 2 and Low Steam Generator Water Level
16. Undervoltage-ReactorCoolant NA R M 1 ca Pump Busses R

(? 17. Underfrequency - Reactor Coolant NA R M 1 g Pump Busses

18. Turbine Trip A. Low Auto Stop Oil Pressure NA NA S/U(1) NA B. Turbine Stop Valve Closure NA NA S/U(1) NA
19. Safety injection input from ESF NA NA M(4) & (5) 1, 2 2u. Reactor Coolant Pump Breaker NA NA R 1 g Poshion Trip R 21. A Reactor Trip Breaker NA NA M(5), (9), & (11) 1. 2, &
  • B B. Reactor Trip Bypass Breaker NA NA M(5), (9). & R(10) 1, 2, & *

$^

7 22; Automatic Trip Logb NA NA M(5) 1, 2, &

  • I P

l .

TABLE 3.3-3 (Continued)

ACTION 17- With the number of OPERABLE channels one less than the Total Number of Channels operation may proceed 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 /> and the Minimum Channels OPERABLE requiremont is met. One l 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 surveillanco testing per Specification 4.3.2.1.1.

ACTION 18- With the number of OPERABLE Channele one less than the Total Number of Channels, restore the inoperable 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 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 in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

ACTION 19 - With the number of OPERABLE Channels one loss 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 />.
b. The Minimum Channels OPERABLE requirement is met; however, one add;tional l channel may be bypassed for up to 2 houts for surveillance testing por Specification 4.3.2.1.1.

ACTION 20- With the number of CPERABLE Channels one less than the Total Number of Channels, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and at least HOT SHUTDOWN within the following 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 i

surveillance testing per Spec!fication 4.3.2.1.1 provided the other Channel is OPERABLE.

ACTION 21 - With the number of OPERABLE Channels one less than the Total Number of Chsmnels, restore the Inoperable 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 be in at least HOT STANDBY following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the {

NORTH ANNA-UNIT 2 3/4323 Amendment No.

Attachment 3 10 CFR 50.92, Significant Hazards Consideration North Anna Units--1 and 2 Virginia Electric and Powwr Company;

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10 CFR 50.92, Significant Hazards Consideration Technical Specification 3.3.1.1 requires that the Reactor Trip System Instrumentation Channels and Interlocks of Table 3.31 shall be operable with response times as shown in Table 3.3 2. Technical Specification 3.3.2.1 requires that the Engineered Safety Feature Actuation System (ESFAS) instrumentation channels shown ir. Table 3.3 3 shall be operable with their trip setpoints set consistent with the values shown in the trip setpoint column of Table 3.3 4 and with response times as shown in Table 3.3 5.

The proposed changes revise Technical Specification 4.3.1.1.1, Reactor Trip System Instrumentation, Table 4.31, item 19, Safety injection input from ESF, to increase the surveillance interval from overy month to every 62 days on a staggered test basis and Technical Specification 3.3.2.1, Table 3.3 3, Action j 20, to allow a channel to be bypassed for up to two hours for testing purposes.  !

The proposed changes also rnake administrative changes that do not affect the technical content of the specifications. j lt has been determined that the proposed changes do not involve a significant hazards consideration as defined in 10 CFR 50.92. This determination was based on the following points. I

1. The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed changes revise Technical Specification 4.3.1.1.1 such that the amount of time each train of React.: Trip System

!nstrumentation is inoperable for testing is decreased and Technical Specification 3.3.2.1 such that sufficient time is allowed for testing the ESFAS logic without having to enter a shutdown action statement.

These changes to Reactor Trip System and ESFAS instrumentation testing have no significant effect on the probability of an accident because the time spent testing is not significantly' increased and

! becau.co it only affects one train at a time.

Likewise, the consequences of the accidents previously evaluated will not increase as a result of the proposed Technical Specification changes. Testing the Safety injection input from ESF. function on a staggered test basis increases the operability time for the two trains of Reactor Trip System instrumentation. The consequences of allowing up to an additional hour to test 'each train of ESFAS logic are not significantly increased because the time spent -testing is not i significantly increased and the opposite train is still availablo to I perform its design function. The proposed changes are consistent with other testing requirements and are at least as stringent as the requirements of NUREG 0452, Ftandard Technical Specifications for Westinghouse Pressurized Watar Reactors, Revision 4.

Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. The ;)toposed changes do not create the possibility of a new or d fferent kind of acc! dent from -any accident previously evaluated. The changes proposed berelii do not involve any changes to plant design nor methods of operation. The proposed changes do not involve operation of any plant equipment in a different manner from which it was design 9d to operate. Since a new failure mode is not created, a new or different type of accident is not made possib!o.
3. The proposed changes do not involve a significant reduction in a margin of safety. The proposed operational configure *lon does not involve changes to safety limits or limiting safety cysten, settings.

Setpoints and operating parameters are not afiected. Safety margins are, thereiore, not reduced.

Virginia Electric and Power Company concludes that the activities associated with these proposed Technical Specification changes satisfy the no significant

- hazards consideration standards of 10 CFR 50,92 (c) and, accordingly, a no -

significant hazards consideration finding is justified -

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