ML20202C338

Proposed Tech Specs Modifying Testing Requirements for Reactor Trip Bypass Breaker

ML20202C338
Person / Time
Site:	North Anna
Issue date:	02/03/1998
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20202C333	List: ML20202C328 ML20202C338
References
NUDOCS 9802120221
Download: ML20202C338 (10)

Text

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ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATIONS CHANGES NORTH ANNA UNITS 1 AND 2

. VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA UNITS 1 AND 2 9802120221 980203'"

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' TABLE 3.3-1 (CnatW) .

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!M MCTORTRIP SYSTEM INSTRUMENTATION 8 -: _

$>1 -MINIMUM

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FUNCTIONAL UNIT -

TOTAL NO.-

OF CHANNELS CHANNELS TOTRIP CHANNELS:

OPERABLE APPLICABLE _ '

MODES ACTION

16. Undervoltage-Reactor Coolant ;3 - I/ bus 2- 2 I '- 7f

-A Pump Busses -

17. Underfrequency - Reactor Coolant 3 - 1/ bus ' 2  ? I l7*-

Pump Busses

l. 18. Turbine Trip A. Low Auto Stop Oil Pressure '3- 2l > 2 .1- L7#

u 3::

4: 4 .;7 8 l

w B. Turbine Stop Valve Closure -4 11 L

19.~ Safety Injection Input frc>m ESF L2L 1 2' I,;2 20. Reactor Coolant Pump Breaker Position Trip A. Above P-8 : libreaker: "1 1/ breaker. 1. .10 B. Above P 1/bitaker- 2: 1/ breaker per 1~ -11 -

operating loop;

21. A. ReactorTrip Breakers . '2 2 1, 2 - 1, 14--

? - I' -

M ~

$ .2. l1 6

l2l 3*,4*,5* 15 -

R E B. ReactorTrip Bypass Breakers '2 I'

'I' .*** 113 . ['

9 12 '1' 2 'I, 2 1'

$ 22. Automatic Trip Logic

.21 1:- 1 2; 3*,4*,5*- 15 i ,

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TABLE 4.3-1 (Continued)

NOTATION

• - With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

• " - Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

(1)- If not performed in previous 7 days.

(2)- Heat balance only, above 15% of RATED TilERMAL POWER.

(3)- Compare incore to excore axial offset above 15% of RATED THERM AL POWER.

Adjust channel if absolute difference 2 3 percent.

(4) - Manual ESF functional input check every 18 months.

(5) - Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST B ASIS.

(6) - Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7) - The CHANNEL FUNCTIONAL 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 (s).

(8)- Local manual shunt trip the reactor trip bypass breaker immediately after placing the bypass breaker into service, but prior to commencing reactor trip system testing or reactor trip breaker maintenance.

(9) - Automatic undervoltage trip.

(10)- The CH ANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

(11)- _ Monthly Surveillance in Modes 3*,4* and 5* shall also include verification that Permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.

(12)- Detector plateau curves shall be obtained and evaluated. The provisions of

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Specification 4.0.4 are not applicable for entry into Mode 2 or 1.

NORTH ANNA - UNIT 1 3/4 3-14 Amendment No. 4,206

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c. NOTATION ; .

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. *-- With the reactor trip system breakers closed and the control rod drive system ,

, capable of rod withdrawal..-

-**-

Surveillance requirements for the' manual ESF functional test of the safety injection input to ths reactor trip breakers is suspended for the duration of Cycle 9 operation.-

L"*- 1 Below P-10_(Low Setpoint Power Range Neutron Flux Interlock) Setpoint. ,

- (1)'- : If not performed in pre _vious 7 days. _

(2)- = ' Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if -

-absolute difference >2 percent.1 (3) - . Compare incon: to excore axial offset above 15% of RATED THERMAL POWER.

Recalibrate if absolute difference 2 3 percent.

3 (4)I-- Manual ESF functional input check every 18 months.

( (5) - > . Each train or logic channel shall be tested at least every 62 days on a STAGGERED D TEST BASIS.

W  : (6) - - Neutron' detectors may be excluded from CHANNEL CALIBRATION; 4 x

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l (7)- ~ Below the P-6,(Block of Source Range Reactor Trip) Setpoint..  ;

(8)- ' The CHANNEL FUNCTIONAL TEST shall independently verify the

.  ; OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor-0' Trip Function. The test shall also verify the OPERABILITY of the Bypass Breaker -

l trip circult(s).-

_( 9) - Local manual shunt trip the reactor trip bypass breaker immediately _after placing -

the bypass breaker into service, but prior to commencing reactor trip system testing or reactor trip breaker maintenance.

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- (10) - Automatic undervoltage trip. 4 4 c i (11)- The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

.(12) - Monthly Surveillance in Modes 3*,4* and 5* shall also include verification that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.

(13)- Detector plateau curves shall be obtained and evaluated. The provisions of Specification 4.0.4 are not applicable for entry into Mode 2 or 1.

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NORTH ANNA - UNIT 2 - 3/4 3-14 Amendment No. 450,4Et

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~ :O . REACTOR TRIP SYSTEM INSTRUMENTATION '

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_.. MINIMUM-L

-TOTAL NO.

CHANNELS CHANNELS APPLICABLEf

7 ._

OPERABLE MODES ACTION

>: FUNCTIONAL UNITE. OF CHANNELS I RTRIE

16. Undervoltage-Reactor Coolant 3-1/ bus ' _2 2' ,

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4: . . Pump Busses W ..

'7'-

17. Underfrequency-Reactor Coolant 3-1/ bus 2 2 I

- Pump Busses

18. Turbine Trip ,,

8 A. Low Auto Stop. Oil Pressure ~. 3 2  : 2. .I 7 'i B._ Turbine Stop Valve Closure w 4 :4- 4 11! - '7#

w 19. Safety Injection Input from ESF . .2 .I 2. 1. 2 - 1:

3:

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A 20. Reactor Coolant Pump Breaker ' -

. Position Trip A. Above P-8 . -.1/ breaker - :1i 1/ breaker;. 'I- 10 B. Above P-7 12- 1/ breaker per s - 1 :! -- I I

> 1/ breaker 5  ; operating loop ^

5. '

21. A. ReactorTrip Breakers 2; -

1 2- 1,2 'I '!4;- <

2 - 1 i:. 2 =- 3*,4*,5* 15 '-

g "l ***' 13-B. Reactor Trip Bypass Breakers .2l 1 J

22. Automatic Trip logic '21 1? z2 1,2? . LI

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= ATTACHMENT 3 ~

SIGNIFICANT HAZARDS CONSIDERATION VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA UNITS 1 AND 2

SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION Virginia Electric and Power Company has reviewed the requirements of 10 CFR 50.92 as they relate to the proposed changes for the North Anna Units 1 and 2 and determined that a significant hazards consideration is not invo!ved. The proposed changes will allow the bypass breakers to be tested in the racked in position. This change will continue to ensure the operability of the breakers and eliminate unnecessary movement caused by racking the breakers, thus, reducing the wear and tear on the breakers and the possibility of a reactor trip.

The operation of the Reactor Protection System and the reactor trip and reactor trip bypass breakers are not being changed. The proposed changes in the test sequence i for the reactor trip bypass breakers continue to provide assurance that the reactor trip bypass breakers will operate as dedgned to mitigate the consequence of any unsafe or improper reactor operation during steady state or transient power operations when the bypass breakers are placed in service for reactor trip system testing or trip breaker maintenance. In support of this conclusion, the Niowing analyses is provided, a) Operation and testing of the reactor uq R t.kers does not increase the probability of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report.

The testing sequence will continue to ensure that the reactor trip system will be operable to mitigate the consequences of any unsafe or improper reactor operation during steady state or transient power operations. Although the breaker is placed in service before it is tested, the breaker is tested as soon as practicable to reestablish operability prior to performing testing of the reactor trip system or maintenance on the reactor trip breakers. During the shon period of time the breaker is closed before the local shunt trip device test, the operability of the breaker is established based on satisfactory breaker testing conducted during the previous surveillance interval.

Changing the minimum channels operable requirement for the reactor trip bypass breakers does not affect the operation of the reactor trip system since only one reactor trip bypass breaker can be inservice for testing or maintenance of the reactor protection system. Therefore, the proposed test sequence does not significantly increase the probability of occurrence or the consequences of any previously analyzed accident, b) The proposed Technical Specifications do not create the possibility of an accident or malfunction of a different type than any evaluated previously in the safety analysis report.

The proposed test sequence change does not alter the actual test performed to establish operability of the reactor trip bypass breakers. The bypass breakers will be proven operable prior to reactor trip system testing or reactor trip breaker maintenance. Although the breaker is placed in service l

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m' _ . before it is tested,' the bioaker is tested as soon' as practicable to_ reestablish

• : operability; prior to J pedorming ; testing of:: the reactor - trip system, or-maintenance on the reactor trip breakers. During the_ short period of time the breaker is closed before the local shunt trip _ device test, the operability of the breaker is established based Lont satisfactory breaker testing conducted

during the previous surveillance interval. Changing the minimum channelc' operable requir'ement for the reactor trip bypass breakers does not affect the (operation of:the. reactor trip l system:since only_ one reactor trip; bypass breaker can be inservice for testing or maintenance of the reactor protection J system. Therefore, it is concluded that no new or different kind of accident -

or malfunction from any previously evaluated has been created, c) Thef proposed Technical Specifications change? does- not result- inia 4 significant reduction in margin of safety. -

The: proposed change in ;the reactor trip bypass breaker test sequence provides: assurance that the reactor: trip. system remainsfoperable during

= normal opsrations or during reactor trip system testing and reactor trip breaker maintenance to mitigate the consequences'of 'any unsafe or improper reactor

- operation.; Changing the - minimum channels operable requirement for the .

reactor trip bypass _ breakers does not affect the~ operation lof_ the reactor. trip system since only one reactor' trip bypass breaker can be inservice for testing .

-or maintenance of the-: reactor- protection system. Therefore, the; proposed

? change;in the test sequence for the' reactor-trip _ bypass: breaker: doesEnot significantly reduce the margin of safety.

This analysis demonstrates that the proposed amendment to the North Anna Units'1 -

- and 2 Technical Specifications does not involve a significant increase in the probability-1 or consequences of a previously evaluated accident, does not create the possibility of a:

new or different kind of accident and 'does not involve a significant reduction in a margin --

of safety.-

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