ML20151U986

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Proposed Tech Spec Table 3.3-1 Re Instrument Operability Requirements & Associated Action Statements for Reactor Trip Sys Instrumentation
ML20151U986
Person / Time
Site: North Anna Dominion icon.png
Issue date: 02/05/1986
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20151U979 List:
References
NUDOCS 8602110166
Download: ML20151U986 (5)


Text

F-O ATTACIDfENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGE FOR UNIT I B602110166 860205

~ PDR ADOCK 05000330 PDR' p

.g.

4 3:

TABLE 3.3 *

'h~

REACTOR' TRIP SYSTEM INSTRUMENTATION'.

MINIMUM S

TOTAL NO.

CHANNELS

' CHANNELS-APPLICABLE 5

FUNCTIONAL UNIT OF CHANNELS.

TO TRIP-OPERABLE-MODES-ACTION. _

l '. Manual Reactor Trip 2

1 2-

.1, 2'and.*'

- 12 ' -

2.

Power Range, Neutron Flux 4'

'2 3

1, 2-2#4 3.

Power Range, Neutron Flux 4

2 3

1,-2 2#

High Positive' Rate 4.

Power Range, Neutron Flux, 4

2 3

1, 2 2#

High Negative Rate 5.

Intermediate Range, Neutron Flux 2

1 2

1, 2 and

  • 3 6.

Source Range, Neutron Flux g

.4 2## and

  • A.

Startup 2

1 2

1 y

B.

Shutdown 2

0 1

3, 4 and 5 5

7.

Overtemperature AT Three Loop Operation-3 2

2 1, 2 7# l.

Two Loop Operation 3

1**

2 1, 2

'9

~,

f g;

~

~~

f]

m

~

;.4 TABLE 3.3-1. ;(Continued)?

I S

E

_ REACTOR' TRIP' SYSTEM?-INSTRUMENTATION' v

E

. CHANNELS

CHANNELS-
APPLICABLE
MINIMUM

' TOTAL NO...

OF CHANNELS' TO TRIP-OPERABLE-MODES-ACTION c:

FUNCTIONAL UNIT 2j.

8.

Overpower AT-Three Loop Operation

'3 2.

'2 1, 2 7f Two Loop Operation 3

1**

2

' 1, 2 :

9-9.

Pressurizer Pressure-Low' 3

2 2-1, 2 '

.7f-

+

10. Pressurizer Pressure-High 3

2 2

'~1,L2' j7f

'11. Pressurizer Water Level--High 3

2

'2' l', ;2 7#'

12. Loss of Flow - Single Loop 3/ loop 2/ loop in.

2/ loop iri 11 7f' (Above P-8) any operating.

each-oper-loop ating loop N

~

13. Loss of Flow - Two Loops.

3/ loop 2/ loop __in 2/ loop.

1" 17 f.

Y

'(Above P-7 and below P-8) two operating each oper-loops.

ating loop _

14. Steam Generator Water.

3/ loop 2/ loop in.

2/ loop in l ', 2 7f 2

Level-Low-Low any operating each oper-loops ating loop 15.

Steam /Feedwater Flow 2/ loop-level 1/ loop-level 1/lo'op 1, 2 7f Mismatch and Low Steam and.

coincident level'and Generator Water Level.

2/ loop-flow

'with' 2/ loop-flow.

mismatch-1/ loop-flow mismatch or mismatch in- :2/ loop-level.

same-loop and 1/ loop-flow misinatch y

e d

9

h 4

e I

ATTACHMENT 2 SAFETY EVALUATION l

.m

i l -

SAFETY EVALUATION The proposed changes to Table 3.3-1 correct a typographicci error in the action statements for the Overtemperature Delta T and Overpower Delta T trip function instrumentation. Action statement number 2 is presently specified. The correct action statement number is 7.

Correcting this error makes the Unit 1 table consistent with Unit 2 and the Standard Technical Specifications.

.It is believed that the presently specified number.is the result of a typographical error which was introduced during initial plant ifcensing.

Action statement number 2 is clearly not applicable as it refers to nuclear instrumentation inoperability. We intend to follow the correct action statement (i.e. #7) for these trip functions during three loop operation pending correction of this error.

l 50.59 and Significant Hazards Review Pursuant to 10 CFR 50.59, we have reviewed the proposed Technical Specification changes and have concluded that no unreviewed safety question exists: (1) the possibility of occurrence or the consequence of a malfunction of the equipment previously evaluated in the UFSAR is not increased, (ii) the possibility of a different type of accident other than discussed in the UFSAR has not been created, and (iii) the margin of safety as described in the BASES Section cif any part of Technical Specifications has not been reduced.

~ ilia proposed changes are administrative and only involve the correction of typographical errors.

For the same reasons given in the 50.59 review, the proposed' change does not pose a significant hazards consideration as defined in 10 CFR 50.92.

3 The Commission has provided examples (48FR14870) of changes that l

constitute no significant hazards consideration. Example (i) involves "A l

purely administrative change to technical specifications: for example, a change to achieve consistency throughout the technical specifications, correction of an error,...."

The proposed changes clearly fall under examp'.e (1) in that they correct typographical errors.

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