ML18031B191
| ML18031B191 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/09/1987 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18031B190 | List: |
| References | |
| TAC-64706, TAC-64707, TAC-64708, NUDOCS 8702180282 | |
| Download: ML18031B191 (13) | |
Text
ENCLOSURE 1
PROPOSED TECHNICAL SPECIFICATIONS REVISIONS BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 (TVA BFN TS 226) 8702180282 870209 PDR ADQCK 05000259 P
TABLE 3.1.A REACTOR PROTECTION SYSTEM (SCRAM)
INSTRUMENTATION REQUIREMENTS Hin. No. of Operable Instr.
Channels Per Trip S stem 1
23 Tri Function Tri Level Settin Shut-down Hodes in Which Function ust era e
tar up/
~Refuel 7
~not Standb Run A~ction i
Hode Switch in Shutdown Hanual Scram IRH (16)
High Flux Inoperable X
X
<120/125 Indicated X(22)
X(22)
X on scale X
X (5)
(5) 1.A 1.A 1.A 1.A APRH (16) (24) (25)
High Flux LFlow Biased)
High Flux (Fixed Trip)
High Flux Inoperative Oownscale High Reactor Pressure High Orwell Pressure (14)
See Spec.
- 2. 1.A.l
< 12(4 15'L rated power T13)
> 3 Indicated on Scale;
< 1055 psig
< 2.5 psig X(21)
X(17)
X(21)
X(17)
(11)
(11)
X(10)
X X(8)
X(8)
X 1.A or 1.B X
1.A or 1.B (15) 1.A X
1.A X(12) 1.A or 1.B 1.A 1.A Reactor Low Water Level (14)
> 538" above vessel zero 1.A BFN-Unit 1
TABLE 3.1.A REACTOR PROTECTION SYSTEH (SCRAH)
INSTRUHENTATION REQJIREHENTS Hin. No. of Operable Instr.
Channels Per Trip S stem 1
23 Tri Function Shut-Tri Level Settin down Hodes in Which Function us e
era e
tai up
~Refuel 1
H~tot Standb Run A~ction i
High Water Level in West Scram Discharqe Tank (LS-85-45A-D)
High Water Level in East Scram Discharqe Tank (LS-85-45E-H)
Hain Steam Line Isolation Valve Closure Turbine Control Valve Fast Closure or Turbine Trip Turbine Stop Valve Closure Turbine First Stage Pressure Permissive
< 50 Gallons
< 50 Gallons
<l(5 Valve Closure
>550 psig
<l(C Valve Closure not >154 psig X(2)
X(2)
X(2)
X(2)
X X(3) (6)
X(3) (6)
X(18)
X(18) 1.A X
1.A X(6) 1.A or 1.C X(4) 1.A or 1.0 X(4) 1.A or 1.D X(18) 1.A or 1.0 (19)
Hain Steam Line Hiqh Radiation (14) 3 X Normal Full Power Background (20)
X(9)
X(9)
X(9) 1.A or 1.C BFN-Unit 1
TABLE 3.1.A REACTOR PROTECTION SYSTEH (SCRAH)
INSTRUHENTATION REQUIREHENTS Hin. No. of Operable Instr.
Channels Per Trip S stem 1 (23 Tri Function Tri Level Settin Shut-down Hodes in which Function ust e
er e
ar up/
~Refuel 7
H~tot Standb Run A~ction i
Hode Switch in Shutdown Hanual Scram IRH (16)
High Flux Inoperable X
X
<120/125 Indicated X(22)
X(22)
X on scale X
X (5)
(5) 1.A 1.A 1.A 1.A APRH (16) (24) (25)
High Flux
]Flow Biased)
High Flux (Fixed Trip)
High Flux Inoperative Downscale See Spec.
- 2. 1.A. 1
< 12(5 15% rated power (13)
> 3 Indicated on Scale X(21)
X(17)
X(21)
X(17)
(11)
(11)
X 1.A or 1.B X
1.A or 1.B (15) 1.A X
1.A X(12) 1.A or 1.B High Reactor Pressure
< 1055 psig (P IS-3-22AA,BB,C,6)
X(10)
X 1.A High Drywell Pressure (14)
< 2.5 psig (PIS-64-56 A-D)
Reactor Low Water Level (14)
> 538" above (LIS-3-203 A-0) vessel zero X(8)
X(8) 1.A 1.A BFN-Unit 2
TABLE 3.1.A REACTOR PROTECTION SYSTEH (SCRAH)
INSTRUHENTATION REQUIREHENTS Hin. No. of Operable
~
Instr.
Channels Per TripLlLu Tri Function Hodes in which Function Hust Be er e
Shut-Startup/
fri Level Settin down
~Refuel 7
~wot Standb Run A~ction l
High Water Level in West Scram Discharge Tank (LS-85-45A-0)
High Water Level in East Scram Discharge Tank (LS-85-45E-H)
Hain Steam Line Isolation Valve Closure Turbine Control Valve Fast Closure or Turbine Trip Turbine Stop Valve Closure Turbine First Stage Pressure Permissive (PI5-1-8MB, PIS-1-9 lAEB)
< 50 Gallons
< 50 Gallons
<1lS Valve Closure
>550 psig
<l(5 Valve Closure not >154 psig X(2)
X(2)
X(2)
X(2)
X(18)
X(18) 1.A X
1.A X(6) 1.A or 1.C X(4) 1.A or 1.0 X(4) 1.A oi 1.D X(18) 1.A or 1.0 (19)
Hain Steam Line High Radiation (14)
Low Scram Pilot Air Header Pressure 3 X Normal Full Power Background (20)
>50 psig X(9)
X(2)
X(2)
X(9)
X(9) 1.A or 1.C 1.A BFN-Unit 2
~
~
~
TABLE 3.1.A REACTOR PROTECTION SYSTEM (SCRAH)
INSTRUMENTATION REQUIREMENTS Hin. No. of Operable Instr.
Channels Per Trip S stem 1
23 Tri Level Settin Shut-down Hodes in Which Function us e
r e
artup/
~Refuel 7
~Hot Standb Run A~ction i
Mode Switch in Shutdown Hanual Scram IRH (16)
High Flux Inoperative X
X
<120/125 Indicated X(22)
X(22)
X on scale X
X (5)
(5) 1.A 1.A 1.A 1.A APRH (16) (24) (25)
High Flux (Fixed Trip)
High Flux (Flow Biased)
High Flux Inoperative Downscale High Reactor Pressure
< 12(4 See Spec.
2.1.A.1 15% rated power T13)
> 3 Indicated on Scale
< 1055 psig X(21)
X(17)
X(21)
X(17)
(11)
(11)
X(10)
X X
1.A or 1.B X
1.A or 1.B (15) 1.A X
1.A X(12) 1.A or 1.B 1.A High Orwell Pressure (14)
< 2.5 psig Reactor Low Water Level (14)
> 538" above vessel zero X(8)
X(8) 1.A 1.A BFN&nit 3
~
~
TABLE 3.1.A REACTOR PROTECTION SYSTEH (SCRAH)
INSTRUHENTATION REQUIREHENTS Hin. No. of Operable Instr.
Channels Per Trip S stem 1
23 Tri Function Shut-Tri Level Settin down Hodes in Which Function Hust Be era e
ar up
~Refuel 7
~Hot Standb Run A~ction i
High Mater Level in West Scram Discharge Tank (LS-85-45A-0)
High Water Level in East Scram Discharge Tank (LS-85-45E-H)
Hain Steam Line Isolation Valve Closure Turbine Control Valve Fast Closure or Turbine Trip Turbine Stop Valve Closure Turbine First Stage Pressure Permissive
< 50 Gallons
< 50 Gallons
<l(5 Valve Closure
>550 psig
<l(5 Valve Closure not >154 psig X(2)
X(2)
X(2)
X(2)
X(18)
X(18) 1.A X
1.A X(6) 1.A or 1.C X(4) 1 A or 1
D X(4) 1.A or 1.D X(18) 1.A or 1.D (19)
Hain Steam Line High Radiation (14) 3 X Normal Full Power Background (20)
X(9)
X(9)
X(9) 1.A or 1.C BFN-Unit 3
ENCLOSURE 2
DESCRIPTION AND JUSTIFICATION BROWNS FERRY NUCLEAR PLANT (BFN)
Descri tion of Chan es Table 3.1.A requires one substantive change and two administrative changes.
I.
Substantive Change A.
In table 3.1.A for units 1, 2, and 3, the specified alternative action "or 1.B" is deleted for the ARPM High Flux and Inoperative trip functions.
II. Administrative Changes A.
In table 3.1,A for units 1, 2, and 3, note 2 is added in the Shutdown column for the High Water Level in West and East, Scram Discharge Tanks trip functions.
Note 2 specifies that it is applicable for shutdown or refueling.
B.
In table 3.1,A for units 1, 2,and 3, "1.A or 1.D" is added in the Action column for the Turbine First Stage Pressure Permissive trip function.
The action column currently just references note 19 which specifies when actions 1.A or 1.D are required.
Reasons for Chan es The changes are made to provide more applicable action statements for the APRM instrumentation and to enhance the consistency and clarity of the table and its notes.
Justification for Chan es I. Substantive change:
A.
The APRM High Flux and Inoperative trip functions are required to be operable in the Run and Startup/Hot Standby modes.
When the APRM High Flux or Inoperative trip function is inoperable, taking alternative action 1.B would result in the plant being placed in the Startup/Hot Standby mode, a mode where this inoperable instrumentation is still required to be operable.
Therefore, deletion of this option is appropriate and will result in an additional restriction thereby improving the margin of nuclear safety.
II. Administrative Changes:
A.
Addition of note 2 in the Shutdown column enhances table consistency with and clarifies the intent of note 2, Since the note itself currently specifies its applicability during shutdown, the intent of the requirement is not changed.
Justification for Chan es (Continued)
B.
Addition of "1.A or 1.D" in the Action column is consistent with the content of and clarifies the intent of note 19 and enhances consistency throughout the table.
These changes are administrative in nature in that no current requirements are changed and therefore will not significantly affect the margin of safety.
ENCLOSURE 3
DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION Descri tion of Amendment Re uest The proposed amendment would change the Technical Specifications (TS) of Browns Ferry Nuclear Plant (BFN) units 1, 2, and 3 by making one substantive and two administrative changes to TS table 3.1.A.
The substantive change to table 3.1.A deletes alternative action 1.B for when the APRM High Flux or Inoperative trip function minimum number of operable instrument channels per trip system is not satisfied.
The administrative changes involve changes in wording to improve the clarity and consistency of table 3.1.A requirements.
Basis for Pro osed No Si nificant Hazards Consideration Determination The Commission has provided standards for determining whether a significant hazards consideration exists as stated in 10 CFR 50.92(c).
A proposed amendment to an operating license involves no significant hazards considerations if operation of the facility in accordance with the proposed amendment would not:
(1) involve a significant increase in the probability or consequences of an accident previously evaluated, or (2) create the possibility of a new or different kind of accident from an accident previously evaluated, or (3) involve a significant reduction in a margin of safety.
A discussion of these standards as they relate to the proposed change to table 3.1.A to delete action 1.B for inoperability of APRM High Flux and Inoperative trip function instrumentation channels follows:
This change removes an alternative action which is not appropriate for the ARPM High Flux and Inoperative trip functions because these two trip functions are required to be operable in the Startup/Hot Standby Mode which is the mode to which action 1.B directs the plant to be taken when either of these two trip functions are inoperable.
While deletion of this alternative action 1.B would have no effect on the probability of a previously evaluated
- accident, this change could result in a decrease in the consequences of an accident since it will further restrict operational conditions allowed with these trip functions inoperable.
2.
This change removes an alternative action which is not appropriate for ARPM High Flux and Inoperative trip functions inoperability.
The primary action and alternate action 1.A remain available to the operator when these specified APRM trip function channels are inoperable.
Therefore, no new accident possibilities are created.
, Basis for Pro osed No Si nificant Hazards Consideration Determination (Continued) 3.
The margin oE saEety will be increased because an inappropriate alternative action will be deleted and only the correct actions will be specified.
A discussion of the above standards as they relate to the proposed administrative changes follows.
1.
These administrative changes provide additional consistency and clarification of table 3.1.A requirements and notes without altering the intent oE the requirements or information provided.
Therefore, no accident probabilities or consequences are affected.
2.
The possibility of a new kind of accident is not created since these administrative changes will not eliminate or modify any protective function nor permit any new operational conditions.
3.
These administrative changes will not result in any change to the requirements or intent oE table 3.1.A and, therefore, will not result in any reduction oE the margin of safety.
Since the application Eor amendment involves proposed changes that are encompassed by the criteria Eor which no significant hazards consideration
- exists, TVA has made a proposed determination that the application involves no significant hazards consideration.