Text

Proposed Changes to Tech Spec Tables 3.3-1 & 4.3-1,revising Limiting Condition for Operation & Surveillance Requirements for Reactor Trip Bypass Breakers & Undervoltage & Shunt Trip Logic
	ML20115H778
Person / Time
Site:	North Anna
Issue date:	04/12/1985
From:	; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
Shared Package
ML20115H742	List: ML20115H740; ML20115H778;
References
	NUDOCS 8504230262
	Download: ML20115H778 (11)
	v • d • e

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H-TABLE 3.3-1 (Continued)

N

$ REACTOR TRIP SYSTEM INSTRUMENTATION I

d MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UN1! OF CHANNELS TO TRIP OPERABLE MODES ACTION

16. Undervoltage-Reactor Coolant Pump Busses 3-1/ bus 2 2 1 7f

17. Underfrequency-Reactor c Coolant Pump Busses 3-1/ bus k 2 2 1 7#

18. Turbine Trip A. Low Auto Stop Oil Pressure 3 2 2 1 7f M

B. Turbine Stop Valve Closure 4 4 4 1 7#

19. Safety Injection Input j Y from ESF 2 1 2 1,2 1 e

20. Reactor Coolant Pump Breaker Position Trip A. Above P-8 1/ breaker 1 1/ breaker 1 10 B. Above P-7 1/ breaker 2 1/ breaker 1 11 per operating loop

21. A. Reactor Trip Breakers 2 1 2 1,2 and

1 B. Reactor Trip Bypass Breakers 2 1 1 *** 13

22. Automatic Trip Logic A. Undervoltage Trip Logic 2 1 2 1,2 and

1 B. Shunt Trip Logic 2 1 2 1,2 and

1 8504230262 850412 PDR ADOCK 05000338 p PDR

.g. - . - _ .-. - .

TABLE 3.3-1 (Continu d)

TABLE NOTATION With the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.

The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped condition.

1

- - With the Reactor Trip Breaker open for surveillance testing in accordance with Specification Table 4.3-1 (item 21A).

9 The provisions of Specification 3.0.4 are not applicable.

it High voltage to detector may be de-energized above P-6.

ACTION STATEMENTS ACTION 1 - With the number of channels OPERABLE one less than required 1

by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.1.

ACTION 2 - With the number of OPERABLE channels one less than the Total

. Number of Channels, STARTUP and 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

! b. The Minimum Channels OPERABLE requirement is met; how-ever, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of the redundant channel (s) per Specification 4.3.1.1.1.

c. Either, THERMAL POWER is restricted to s 75% of RATED THERMAL POWER and the Power Range, Neutron Flux trip i setpoint is reduced to s 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

d. The QUADRANT POWER TILT RATIO shall be determined to be l within the limit when above 75 percent of RATED THERMAL i POWER with one Power Range Channel inoperable by using the moveable incore detectors to confirm that the normal-ized symmetric power distribution, obtained from 2 sets l of 4 symmetric thimble locations or a full-core flux map, is consistent with the indicated QUADRANT POWER - TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

i ACTION 3 - With the number of channens OPERABLE one less than required by the Minimum Channels OPERABLE requirement and l with the THERMAL POWER level:

I NORTH ANNA - UNIT 1 3/4 3-5

TABLE 3.3-1 (Continued)

ACTION 9 - With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel associated with an operating loop may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.1.

ACTIOh 10 - With one channel inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to below P-8 within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Operation below P-8 may continue pursuant to ACTION 11.

ACTION 11 - With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 12 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the reactor trip breakers.

ACTION 13 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within (1) hour or terminate testing of the Reactor Trip Breaker and open the Reactor Trip Bypass Breaker.

NORTH ANNA - UNIT 1 3/4 3-7

TABLE 4.3-1 (Cantinu:d) o

N REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS x

CHANNEL MODES IN WHICH h

> CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE i FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED E

q 13. Loss of Flow - Two Loops S R N.A. 1

~

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

15. Steam /Feedwater Flow Mismatch S R M 1,2 and Low Steam Generator Water Level

16. Undervoltage - Reactor Coolant N.A. R N.A 1 ,

Pump Busses

17. Underfrequency - Reactor Coolant N.A. R N.A. 1

(( Pump Busses u

18. Turbine Trip h

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

19. Jsafety Injection Input from ESF N.A. N.A. M(4) 1,2

20. Reactor Coolant Pump Breaker N.A. N.A. R N.A.

Position Trip

21. A. Reactor Trip Breaker N.A. N.A. M(5) and S/U(1) 1,2 and

B. Reactor Trip Bypass Breaker N.A. N.A. M(5) and S/U(1) 1,2 and *

22. Automatic Trip Logic A. Undervoltage Trip Logic N.A. N.A. M(5) 1,2 and

B. Shunt Trip Logic N.A. N.A. M(5) 1,2 and

f b' -- -

1 e e ATTACHMENT 2 1

5 1

i i

i f

L -. __-_ ____ _ .._._.. _ _ _ . _ . . - . _ _ _ _ . - . . . , . . _ _ . . _ _ . _ _ _ _ _ . , . . - - ,_ .___ _

TABLE 3.3 -1 (Continued) 2

@ REACTOR TRIP SYSTEM INSTRUMENTATION E!

h MINIMUM

> TOTAL NO. CHANNELS CHANNELS APPLICABLE 8

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION e

y 16. Unde rvoltage-Reactor y Coolant Pump Busses 3-1/ bus 2 2 1 7f

17. Underfrequency-Reactor Coolant Pump Busses 3-1/ bus 2 2 1 7f

18. Turbine Trip <

A. Low Auto Stop Oil Pressure 3 2 2 1 7f B. Turbine Stop Valve Closure 4 4 4 1 7#

19. Safety Injection Input from ESF 2 1 2 1,2 1 23, 20. Reactor Coolant Pump Breaker

' Position Trip y A. Above P-8 1/ breaker 1 1/ breaker 1 10 8' B. Above P-7 1/ breaker 2 1/ breaker 1 11 per operating loop

21. A. Reactor Trip Breakers 2 1 2 1,2 and

1 B. Reactor Trip Bypass Breakers 2 1 1 *** 13

22. Automatic Trip Logic A. Undervoltage Trip Logic 2 1 2 1,2 and

1 B. Shunt Trip Logic 2 1 2 1,2 and

1

5-TABLE 3.3-1 (Continued)

TABLE NOTATION With the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.

The channel (s) associated with the protective functions derived from the cut of service Reactor Coolant Loop shall be placed in the tripped condition.

- - With the Reactor Trip Breaker open for surveillance testing in accordance with Specification Table 4.3-1 (item 21A).

9 The provisions of Specification 3.0.4 are not applicable.

High voltage to detector may be de-energized above the P-6, (Block of Source Range Reactor Trip), setpoint.

ACTION STATEMENTS ACTION 1 - With the number of channels OPERABLE one less than re-quired by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.1 provided the other channel is OPERABLE.

ACTION 2 -

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condi-tion within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of the redundant channel (s) per Specification 4.3.1.1.1.

c. Either, THERMAL POWER is restricted to s75% of RATED THERMAL POWER and the Power Range, Neutron Flux trip setpoint is reduced to s85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

d. The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75 percent of RATED THERMAL POWER with one Power Range Channel inoperable by using the moveable incore detectors to confirm that the normalized symmetric power distribution, obtained from 2 sets of 4 symmetric thimble locations or a full-core flux map, is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

NORTH ANNA - UNIT 2 3/4 3-5

TABLE 3.3-1 (Continued)

ACTION 9 - With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel associated with.an operating loop may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.1.

ACTION 10 - With one channel inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to below P-8, (Block of Low Reactor Coolant Pump Flow and Reactor Coolant 1

Pump Breaker Position) setpoint, within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Operation below P-8, (Block of Low Reactor Coolant Pump Flow and Reactor Coolant Pump Breaker Position) setpoint, may continue

pursuant to ACTION 11.

ACTION 11 - With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within I hour.

r

. ACTION 12 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the incperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or opern the reactor trip breakers.

l ACTION 13 - With the number of channels OPERABLE one less than required by

the Minimum Channels OPERABLE requirement, restore the inoperable l channel to OPERABLE status within (1) hour or terminate testing of the Reactor Trip Breaker and open the Reactor Trip Bypass Breaker.

i l

l l

i I

NORTH ANNA - UNIT 2 3/4 3-7

TABLE 4.3-1 (C:ntinu;d) z REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS x CHANNEL MODES IN WHICH

> CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

[

z

13. Loss of Flow - Two Loops S R N.A. 1 U 14. Steam Generator Water Level S R M 1,2 N Low-Low

15. Steam /Feedwater Flow Mismatch S R M 1,2 and Low Steam Generator Water Level

16. Undervoltage - Reactor Coolant N.A. R M 1 Pump Busses

17. Underfrequency - Reactor Coolant N.A. R M 1 33 Pump Busses y 18. Turbine Trip 4

C N.A.

A. Low Auto Stop 011 Pressure N.A. N.A. S/U(1)

B. Turbine Stop Valve Closure N.A. N.A. S/U(1) N.A.

19. Safety Injection Input from ESF N.A. N.A. M(4) 1,2

20. Reactor Coolant Pump Breaker N.A. N.A. R 1 Position Trip

21. A. Reactor Trip Breaker N.A. N.A. M(5) and S/U(1) 1,2 and

B. Reactor Trip Bypass Breaker N.A. N.A. M(5) and S/U(1) 1,2 and *

22. Automatic Trip Logic A. Undervoltage Trip Logic N.A. N.A. M(5) 1,2 and

B. Shunt Trip Logic N.A. N.A. M(5) 1,2 and *

^ -

1 I

2 d

1

.I ATTACHMENT 3 y

O '

DISCUSSION OF PROPOSED TECHNICAL SPECIFICATION CHANGES Revisions to the North Anna 1 and 2 Technical Specifications are required as a result of the Regulatory Staff's issuance, on July 24, 1984, of their Safety Evaluation Report (SER) for the Auto Shunt Trip Modification. The Staff's review approved the Auto Shunt Trip Modification and indicated a need for additional testing of the Reactor Trip Break :s and its associated equipment.

To meet these requirements, revised specif. cations are submitted for the Reactor Trip Bypass Breakers, Undervoltage Trip Logic and Shunt Trip Logic.

Revised Limiting Condition for Operation (LCO) and Surveillance Requirements (SR) require Reactor Trip Bypass Breaker testing prior to the routine testing of the Reactor Trip Breakers to further assure the Operability of the Bypass Breaker during the testing of the Main Breaker. Secondly, LCO's and SR's are submitted which require Operability and Surveillance of both the Undervoltage and Shunt Trip Logic features. Testing of the newly installed Auto Shunt Trip feature will be accomplished in accordance with the Westinghouse Owners Group Technique. Thirdly, existing specifications for the Manual Trip feature adequately assure Operability and Surveillance of this feature including testing at a Refueling interval. Testing of the Manual feature will be accomplished in accordance with approved station procedure and by the method described in the SER.

The proposed changes do not alter the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the UFSAR because the additional testing of the reactor trip breakers will ensure continued operability. The changes will ensure that the reactor trip and bypass breakers are tested in accordance with the findings of the SER. The proposed changes do not create the possibility of an accident or malfunction of a different type than was previously evaluated in the UFSAR. The addition of the auto trip function to the shunt coil will increase the probability that the reactor will be tripped when called for by the RPS logic. The proposed changes do not reduce the margin of safety as defined in the bases for any technical specification. The changes add requirements for operability and testing of the reactor trip breakers and associated components therefore increasing the margin of safety in relation to the Technical Specification requirements of the reactor protection system.

It has been determined that these changes do not pose a significant hazards consideration as stated in the Federal Register dated April 6, 1983. Example

(ii) of examples of amendments that are considered not likely to involve a significant hazards consideration states, "A change that constitutes an additional limitation, restriction or control not presently included in the Technical Specifications: for example, a more stringent surveillance requirement. "In addition, example (vii) applies to these proposed changes and this example states, "A change to make a license conform to changes in the regulations, where the license change results in very minor changes in facility operations clearly in keeping with the regulations." The proposed changes add a limiting condition for operation, action statements and surveillance requirements for the reactor trip bypass breakers, undervoltage trip logic and shunt trip logic as required by the NRC's safety evaluation report for the Auto Shunt Trip Modification, dated July 24, 1984.

JHL/acm/m4/040

ML20115H778

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