ML20078E429

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Corrected TS Pages to Amends 181 & 61 to Licenses DPR-66 & NPF-73,respectively
ML20078E429
Person / Time
Site: Beaver Valley
Issue date: 11/07/1994
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20078E430 List:
References
NUDOCS 9411140021
Download: ML20078E429 (5)


Text

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ADMINISTRATIVE ERRORS IN AMENDMENT NOS. 181 AND 61 There were four errors reported by DLC in the October 25, 1994, teleconference, one involving Unit 1 and the remaining three involving Unit 2.

1.

Unit 1 (Amendment No. 181) - Page 3/4 3-4 Functional Unit: 21. Reactor Trip Breakers Description of error: APPLICABLE H0DE 3 is in the same row as ACTION 40.

Correction: APPLICABLE H0DE 3 changed to be in the same row as ACTION 39.

Functional Unit: 22. Automatic Trip Logic Description of error: APPLICABLE H0DE 3 is in the same row as ACTION 1.

Correction: APPLICABLE MODE 3 changed to be in the same row as ACTION 39.

2.

Unit 2 (Amendment No. 61) - P:ge 3/4 3-4 Functional Unit: 21. Reactor Trip Breakers Description of error: APPLICABLE MODE 3 is in the same row as ACTION 40.

Correction: APPLICABLE N0DE 3 changed to be in the same row as ACTION 39.

Functional Unit: 22. Automatic Trip Logic Description of error: APPLICABLE MODE 3 is in the same row as ACTION 1.

Correction: APPLICABLE H0DE 3 changed to be in the same row as ACTION 39.

3.

Unit 2 (Amendment No. 61) - Page 3/4 3-4 Functional Unit: 23. Reactor Trip System Interlocks

a. Intermediate Range Neutron Flux, P-6 Description of error: MINIMUM CHANNELS OPERABLE reads 1.

Correction: MINIMUM CHANNELS OPERABLE changed to read 2.

4.

Unit 2 (Amendment No. 61) - Page 3/4 3-18 Functional Unit: 4. Steam Line Isolation Description of error: Part b. reads " Automatic Actuation Logic".

Correction: Part b. changed to read " Automatic Actuation Logic and Actuation Relays".

hDR DO 0500 34 P

PDR j

CORRECTIONS TO LICENSE AMENDMENT NOS. 181 AND 61 FACILITY OPERATING LICENSE NOS. DPR-66 AND NPF-73 DOCKET NOS. 50-334 AND 50-412 Replace the following pages of Appendix A, Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert Unit 1, 3/4 3-4 Unit 1, 3/4 3-4 Unit 2, 3/4 3-4 Unit 2, 3/4 3-4 Unit 2, 3/4 3-18 Unit 2, 3/4 3-18

T TABLE 3.3-1 (Continued)

DPR-66 REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 18.

Turbine Trip (Above P-9)

A. Auto Stop Oil Pressure 3

2 2

1 7

B. Turbine Stop Valve 4

4 4

1

'-'8 Closure 19.

Safety Injection Input 2

1 2

1, 2

1 from ESF 20.

Reactor Coolant Pump 1/ breaker 2

1/ breaker 1

11 Breaker Position Trip per (Above P-7) operating loop 21.

Reactor Trip Breakers 2

1 2

1, 2

40 2

1 2

3(88,4(8',5(38 39 22.

Automatic Trip Logic 2

1 2

1, 2

1 2

1 2

3 (33, 4 (3),5"3 39 23.

Reactor Trip System Interlocks A.

Intermediate Range 2

1 1

2 3

Neutron Flux, P-6 B.

Power Range 4

2 3

1 12 Neutron Flux, P-8 C.

Power Range 4

2 3

1 12 Neutron Flux, P-9 D. Power Range 4

2 3

1 12 Neutron Flux, P-10 E. Turbine Impulse 2

1 1

-1 12 Chamber Pressure, P-13 BEAVER VALLEY - UNIT 1 3/4 3-4 Amendment No. 181 r-,

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4 TABLE 3.3-1 (Continued NPF-73 REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICAPLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODFS ACTION 19.

Safety Injection Input 2

1 2

1, 2

1 from ESF 20.

Reactor Coolant Pump 1/ breaker 2

1/ breaker 1

11 Breaker Position Trip per (Above P-7) operating loop 21.

Reactor Trip Breakers 2

1 2

1, 2

40 2

1 2

3(8), 4 (33, 5 (33 39 22.

Automatic Trip Logic 2

1 2

1, 2

1 2

1 2

3 (3 3, 4 (, 5(8 8 39 23.

Reactor Trip System Interlocks a.

Intermediate Range 2

1 2

2 44 Neutron Flux, P-6

b. Power Range 4

2 3

1 44 Neutron Flux, P-8

c. Power Range 4

2 3

1 44 Neutron Flux, P-9 I

d. Power Range 4

2 3

1, 2

44 Neutron Flux, P-10 l

e. Turbine Impulse 2

1 2

1 44 Chamber Pressure, P-13 l

l BEAVER VALLEY - UNIT 2 3/4 3-4 Amendment No. 61

TABLE 3.3-3 (Continued)

NPF-73 9

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE i

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERARLE MODES ACTION i

4.

STEAM LINE ISOLATION

a. Manual Initiation 1.

' Individual 1/ steam line 1/ steam 1/ operating 1,

2, 3

41-line steam line 2.

System 2 sets (2 1 set

2. sets 1,

2, 3

18 switches / set)

b. Automatic Actuation 2

1 2

1, 2,

3-13 Logic and Actuation Relays

c. Containment Pressure 3

2 2

1, 2,

3 14 Intermediate-High-High

d. Steamline Pressure-Low 3/ loop 2/ loop any 2/ operating i

2, 14 loop loop 3 U l

e.

Steamline Pressure 3/ loop 2/ loop any 2/ operating 3

14 l

83 Rate--High Negative loop loop S.

TURBINE TRIP & FEEDWATER 1

ISOLATION f

a.

Automatic Actuation 2

1 2

1, 2

42 i

Logic and Actuation

)

Relays

b. Steam Generator 3/ loop 2/ loop in 2/ loop in 1, _ 2, 3 14 Water Level --

any oper-each oper-High-High, P-14 ating loop ating loop

+

i BEAVER VALLEY - UNIT 2 3/4 3-18 Amendment No. 61

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