ML20150D913

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Amend 21 to License NPF-43,revising Tech Specs to Delete Nonregenerative HX Outlet Temp High Signal from Listing of RWCU Sys Isolation Signals
ML20150D913
Person / Time
Site: Fermi 
(NPF-043)
Issue date: 07/06/1988
From: Muller D
Office of Nuclear Reactor Regulation
To:
Detroit Edison, Co, Wolverine Power Supply Cooperative
Shared Package
ML20150D916 List:
References
NPF-43-A-021 NUDOCS 8807140231
Download: ML20150D913 (15)
v • d • e


Text

. _ _ _.

/

~%,

UNITED STATES NUCLEAR REGULATORY COMMISSION o

(

WASHINGTON, D. C. 20555

%...../

DETROIT EDISON COMPANY WOLVERINE POWER SUPPLY COOPERATIVE, INCORPORATED DOCKET NO. 50-341 FERMI-2 AMENOMENT TO FACILITY OPERATING LICENSE Amendment No.21 License No. NPF-43 1.

The Nuclear Regulatory Commissio i (the Commission) has found that:

A.

The application for amendment by the Detroit Edison Company (the licensee) dated March 10, 1988, as supplemented April 21, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-43 is hereby amended to read as follows:

Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.

, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

DECO shall operate the facility in accordance with the Technical. Specifications and the Environmental Protection Plan.

8807140231 000706 ADOCK0500g1 PDR P

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Daniel R. Muller, Acting Director Project Directorate III-1 Division of Reactor Projects - III, IV, V

& Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: July 6, 1988

-. ~. -

ATTACHMENT TO LICENSE AMENDMENT NO. 21 FACILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.

The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE INSERT 3/4 3-12 3/4 3-12 3/4 3-16 3/4 3-16 3/4 3-18 3/4 3-18 3/4 3-21 3/4 3-21 3/4 6-25 3/4 6-25 3/4 6-45 3/4 6-45 3/4 6-46 3/4 6-46

TABLE 3.3.2-1 2

ISOLATION ACTUATION INSTRUNENTATION f

~

VALVE GROUPS MININUM APPLICABLE i

OPERATED BY OPERABLE CHANNELS OPERATIONAL E

TRIP FUNCTION SIGNAL PER TRIP SYSTEN(a)

CONDITION ACTION Z

1.

CONTAlleENT ISOLATION u

a.

Reactor vessel Low Water Level 1)

Level 3 4, 13, 15 2

1,2,3 20 2)

Level 2 2, 10, 11, 16, 17, 18 2

1,2,3 20 12,14(b) 2 1, 2, 3 and

  • 24 3)

Level 1 1

2 1,2,3 20 b.

Drywell Pressure - High 2, 13, 15, 16, 17, 18 2

1,2,3 20 12, 14(b) 2 1,'2, 3 24 R

c Main Steam Line w

h 1)

Radiation - High 1, 2 2

1,2,3 21 2)

Pressure - Low 1

2 1

22 3)

Flow - HIgh 1

2 1,2,3 21 d.

Main Steam Line Tunnel Temperature - High 1

2(c) 1, 2, 3 21 e.

Condenser Pressure - High 1

2 1, 2**, 3**

21 l

f.

Turbine 81dg. Area Temperature - High 1

2 1,2,3 21 g.

Fuel Pool Ventilation Exhaust Radiation - High 14(b), 16 2

1, 2, 3, and

  • 24 h.

Manual Initiation 1,2,4,12,13,14(b) 1/ valve 1, 2, 3 and

  • 26 15, 16, 17, 18

TABLE 3.3.2-1 (Continued) n m

ISOLATION ACTUATION INSTRUMENTATION e

VALVE GROUPS MININUM APPLICA8LE' 5

OPERATED BY OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION SIGNAL PER TRIP SYSTEM (a)

CONDITION ACTION 2.

REACTOR WATER CLEANUP SYSTEM ISOLATION a.

A Flow - High 10, 11 1

1,2,3 23 b.

Heat Exchanger / Pump /High Energy Piping Area Temperature - High 10, 11 1

1,2,3 23 c.

Heat Exchanger / Pump Arca Ventilation a Temp. -

High 10, 11 1

1,2,3 23 d.

SLCS Initiation 11 NA 1,2,3 23 5;'

e.

Reactor Vessel low Water g

Level - Level 2 10, 11(d) 2 1,2,3 23 f.

Deleted l

g.

Manual Initiation 10, 11 1/ valve 1,2,3 26 i

3.

REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION l

l RCIC Steam Line Flow - High a.

i 1.

Differential Pressure 8

1 1,2,3 23 2.

Time Delay 8

1 1,2,3 23 b.

RCIC Steam Supply g

Pressure - Low 8, 9 2

1,2,3 23

=

c.

RCIC Turbine exhaust I

Diaphrap Pressure - High 8

2 1,2,3 23 5

d.

RCIC Equipment Room g

Temperature - High 8

1 1,2,3 23 e.

Manual Initiation 8, 9 1/ valve 1, 2, 3 26 k

l TABLE 3.3.2-2 2

ISOLATION ACTUATION INSTRUMENTATION SETPOINTS l

~

ALLOWABLE i

TRIP FUNCTION TRIP SETPOINT VALUE l

E j

Z 1.

CONTAllMENT ISOLATION m

a.

Reactor Vessel Low Water Level 1)

Level 3 1 173.4 inches

  • 1 171.9 inches

~

2)

Level 2 2 110.8 inches

  • 1 103.8 inches 3)

Level 1 1 31.8 inches

  • 1 24.8 inches b.

Drywell Pressure - High 5 1.68 psig i 1.88 psig c.

Main Steam Line 1)

Radiation - High 5 3.0 x full power background s 3.6 x full power background R

2)

Pressure - Low 1 756 psig 1 736 psig i

[

3)

Flow - High 5 137.9% of rated flow /109.0 psid i 139.5% of rated flow /112.0 psid h

d.

Main Steam Line Tunnel j

Temperature - High 5 200*F**

1 206*F**

i e.

Condenser Pressure - High i 6.85 psia i 7.05 psia i

f.

Turbine 81dg. Area i

Temperature - High 5 200*F

$ 206*F 1

)

g.

Fuel Pool Ventilation Exhaust

)

Radiation - High 1 10 mR/hr**

5 15 mR/hr**

j h.

Manual Initiation NA NA i

TABLE 3.3.?-2 (Continued)

,m ISOLATION ACTUATION INSTRUNENTATION SETPOINTS e

TRIP FUNCTION ALLOWABLE

_ TRIP SETPOINT VALUE

.-e m

2.

REACTOR WATER CLEANUP SYSTEM ISOLATION a.

A Flow - High 5 55.1 gpm 5 63.4 gpm b.

Heat Exchanger / Pump /High Energy Piping Area Temperature - High 5 175*F**

$ 183*F**

c.

Heat Exchanger / Pump Area Ventilation a Temperature -

High 5 50*F**

$ 53*F**

g d.

SLCS Initiation NA NA e.

Reactor Vessel Low Water Level -

3 Level 2 1 110.8 inches

  • 1 103.8 inches f.

Deleted l

g.

Manual Initiation NA NA 3.

REACTOR CORE ISOLATION COOLING SYSTEN ISOLATION l

RCIC Steam Line Flow - High a.

1.

Differential Pressure 1 87.0 inches H20/90,875 lbe/hr**

$ 95.0 inches H 0/

l 2

94,865 lbe/hr 2.

Time Delay 3 seconds 312 seconds a

b.

RCIC Steam Supply Pressure - Low 1 62 psig 1 53 psig RCIC Turbine Exhaust Diaphragm c.

5 Pressure - High 5 10 psig i 20 psig I

1 RCIC Equipment Room

[

Temperature - High 5 150*F**

1 160*F**

~

e.

Manual Initiation NA NA A

j j

TA8LE 3.3.2-2 (Continued)

]

y ISOLATION ACTUATION INSTRUNENTATION SETPOINTS

)

ALLOWA8LE e

TRIP FUNCTION TRIP SETPOINT VALUE j

I g

4.

HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION 2

i a.

HPCI Steam Line Flow - High l

1.

Differential Pressure

$ 395.0 inches H20/536,625 5 410.0 inches H20/546,165 lbm/hr**

lbm/hr 2.

Time Delay 3 seconds 312 seconds i

b.

HPCI Steam Supply Pressure - Low 1 100 psig 1 90 psig c.

HPCI Turbine Exhaust i

Diaphragm Pressure - High 5 10 psig

$ 20 psig l

d.

HPCI Equipment Room Temperature - High 5 150*F**

$ 162*F**

j R

e.

Manual Initiation NA NA l

y 5.

RNR SYSTEM SHUTDOWN COOLING M00E ISOLATION i

N j

a.

Reactor Vessel Low Water Level -

l Level 3 1 173.4 inches

  • 1 171.9 inches l

b.

Reactor Vessel (Shutdown Cooling Cut-in 1

Pemissive Interlock) Pressure - High

$ 89.5 psig***

$ 95.5 psig***

)

l c.

Manual Initiation NA NA i

i i

See Bases Figure B 3/4 3-1.

    • Initial setpoint.

Final setpoint to be determined during startup test program. Any required change i

to this setpoint shall be submitted to the Commission within 90 days of test completion.

I

      • Represents steam done pressure; actual trip setpoint is corrected for cold water head with reactor l

vessel flooded.

i l

l

TABLE 3.3.2-3 ISOLATION ACTUATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPCNSE TIME (Seconds)#

1.

CONTAINMENT ISOLATION a.

Reactor Vessel Low Water Level 1)

Level 3

< 13(a) 2)

Level 2 7 13(a)**

3)

Level 1 7 1.0*/< 13(a)**

b.

Drywell Pressure - High h13(a)-

c.

Main Steam Line i

1)

Radiation - High(b)

<13(a){

)

a i 13((a))**

2)

Pressure - Low 3)

Flow - High 7 13 i

d.

Main Steam Line Tunnel Temperature - High NA l

Condenser Pressure - High NA e.

f.

Turbine Bldg. Area Temperature - High NA g.

Fuel Pool Ventilation Exhaust Radiation - Higb(b) i 73(a) h.

Manual Initiation NA 2.

REACTOR WATER CLEANUP SYSTEM ISOLATION a.

A Flow - High NA b.

Heat Exchanger / Pump /High Energy Piping Area Temperature - High NA c.

Heat Exchanger / Pump Area Ventilation Temperature AT - High NA d.

SLCS Initiation NA e.

Reactor Vessel Low Water Level - Level 2 1 13(a) f.

Deleted j

{

g.

Manual Initiation NA 3.

REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION a.

RCIC Steam Line Flow - High 1118) b.

RCIC Steam Supply Pressure - Low 1 13(8)

RCIC Turbine Exhaust Diaphragm Pressure - High NA c,

d.

RCIC Equipment Room Temperature - High NA e.

Manual Initiation NA FERMI - UNIT 2 3/4 3-18 Amendment No. 21

TABLE 4.3.2.1-1 (Continued) m E

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH h

TRIP FUNCTION CHECK TEST _

CALIBRATION SURVEILLANCE REQUIRED

-4 N

2.

REACTOR WATER CLEANUP SYSTEM ISOLATION 1

a.

A Flow - High S

M R

1, 2, 3 b.

Heat Exchanger / Pump /High Energy Piping Area Temperature - High S

M R

1,2,3 j

c.

Heat Exchanger / Pump Area i

Ventilation A Temperature -

High S

M R

1,2,3 i

d.

SLCS Initiation NA R

NA 1,2,3 ws*

e.

Reactor Vessel Low Water Y

Level - Level 2 S

M R

1,2,3 m

f.

Deleted l

[

g.

Manual Initiation NA R

NA 1,2,3 3.

REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION a.

RCIC Steam Line Flow - High 1.

Differential Pressure S

M R

1,2,3 l

2.

Time Delay NA M

R 1,2,3 I

b.

RCIC Steam Supply Pressure -

l Lew S

M R

1,2,3 3

5 g

c.

RCIC Turbine Exhaust Diaphragm i

g Pressure - High S

M R

1, 2, 3

)

h d.

RCIC Equipment Room Temperature - High S

M R

1,2,3 e.

Manual Initiation NA R

NA 1,2,3 i

1

}

l l

!j TABLE 4.3.2.1-1 (Continued) t

_ ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS

(

.E.

CHANNEL OPERATIONAL e

CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH j

g TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED 4.

fiGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION HPCI Steam Line Flow - High i

1.

Differential Pressure 5

M R

l',

2, 3 i,

2.

Time Delay NA M

R 1,2,3 l

b.

HPCI Steam Supply

]

Pressure - Low S

M R

1,2,3 i

c.

HPCI Turbine Exhaust f

Diaphragm Pressure - High 5

M R

1,2,3 l

d.

HPCI Equipment Room Temperature - High S

M R

1,2,3 1

e.

Manual Initiation NA R

NA 1,2,3 l

j 5.

RHR SYSTEM SHUTDOWN COOLING M00E ISOLATION I

a.

Reactor Vessel Low Water Level -

Level 3 S

M R

1,2,3 b.

Reactor Vessel (Shutdown Cooling Cut-in Permissive Interlock) i Pressure - High S

M R

1,2,3

}

c.

Manual Initiation NA R

NA 1,2,3 i

+ith a potential for draining the reactor vessel.

l

    • 'May be bypassed under administrative control.

8 l

m TALLE 3.6.3-1 (Continued)

)E PRIMARY CONTAINMENT IS0ld'.10N VALVES EM i4AXINUM ISOLATION TIME Gi'!E FUNCTION AND NUMB _ER R

_ _(Seconds)

At tocatic Isohtyi Valves (*) (Continued)

P i

rc.ctor Core Isolation Cooling (RCIC) Syster j

.M'. Une Isolation Valves 1

are:

E51-F007 15

--:ard:

E51-F008 4

15 J.

g,9 - Reactor Core Isolation Cooli % (RCIC) System Vacuum Bieakers

]

{

" 'Jae Exhaust Line Vacuum Brer.ker Isolation Valves 4

e JE

'ie.

60 h

ML4:J4 60

10. Group 10 - Reactor Water Cleanup (RWCU) System (Inboard) l Inboard:

G33-F001 10 f

11.

Group 11 - Reactor Water Cleanup (RWCU) System (Outboard) l Outboard:

G33-F004 10

12. G;oup 12 - Torus Water Management system (TWMS)

TWMS to RHR Line Isolation Val.es(b)(d) g G51-F605 60 4

G51-F604 60 f

TWMS to CSS Test Lir Isolation Valves (b)(d) k 5

G51-F607 60 i

z G51-F606 60 Torus Drain Isolation VairesID)Id)

G51-F600 60 G51-F602 m

60 G51-F601 I

60 G51-F603 60 i

TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTI9N STATEMENTS ACTION 30 -

With the number of OPERABLE channels less than requir2d by the Minimum OPERABLE Channels per Trip System requirement:

a.

For one trip system, place that trip system in the tripped condition within I hour

b.

For both trip systems, declare the associated ECCS inoperable.

ACTION 31 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, declare the associated ECCS inoperable.

j ACTION 32 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, place

{

the inoperable channel in the tripped conditf9n within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 33 -

Restore the manual initiation function to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or declare the associated ECCS inoperable.

ACTION 34 -

With the number of OPERABLE channels less than required by the i

Minimum OPERABLE Channels per Trip System requiremen:., place at least one inoperable channel in the tripped condition within I hour *, align the HPCI system to take suction from the suppres-sion pool, or declare the H.5CI system inoperable.

ACTION 35 -

With the number of OPERABLE channels:

1 One less than the Total Number of Channels, restore the a.

l inoperable channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or i

dociare the associated emergency diesel generator inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2, as appropriatc..

b.

Less than the Minimum Channels OPERABLE requirement, declare the associated diesel generator inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2, as appropriate.

l "The provisions of Specification 3.0.4 are not applicable.

I FEMMI - UNIT 2 3/4 3-26

TABLE 3.6.3-1 (Continued)

PRIMARY CONTii1NWENT ISOLATION VALVES M LE NOTATIONS (Continued) 8.

Group 8 - Reactor Core Isalation Cooling (RCIC) System RCIC Steam Line Flow - High RCIC Steam Supply Pressure - Low l

RCIC Turbine Exhaust Diaphragm Pressure - High l

RCIC Equipment Room Temperature - High 9.

Group 9 - Reactor Core Isolation Cooling (RCIC) Vacuum Breakers Drywell Pressure - High with simultaneous RCIC Steam Supply Pressure - Low

10. Group 10 - Reactor Water Cleanup (RWCU) System (Inboard)

RWCU Differential Flow - High RWCU Area Temperature - High RWCU Area Ventilation Differential Temperature - Hign Reactor Vessel Low Water Level - Level 2 11.

Group 11 - Reactor Water Cleanup (RWCU) System (Outboard) t SLCS Initiation (not a containment isolation signal)

RWCU Differential Flow - High RWCU Area Temperature - High i

RWCU Area Ventilation Differential Temperature - High Reactor Vessel Low Water Level - Level 2

12. Group 12 - Torus Water Management Systen (TWHS)

Reactor Vessel Low ', tater Level - Level 2 Drywell Pressure - High

13. Group 13 - Drywell Sumps Reactor Vessel Low Water Lev'l - Lovel 3 l

Drywell Pressure - High

14. Group 14 - Drywell and Suppression Pool Ventilation System l

Reactor Vessel Low Water Level - Level 2 Drywell Pressure - High Fuel Pool Yentilation Exhaust Radiation - High L

15. Group 15 - Traversing In-Core (TIP) System Reactor Vessel Low Water Level - Level 3 Drywell Pressure - High l

FERMI - UNI ( 2 3/4 6-45 Amendment do. 21

~

TABLE 3.6.3-1 (Continued)

PRIMARY CONTAINMENT ISOLATION VALVES TABLE NOTATIONS (Continued) 15.

Greep 15 - Traversing In-Core (TIP) System (Continued)

NOTE:

Either of these signals initiate TIP withdrawal which

)

results in cutomatic closure of the TIP Ball Valves when the TIP probe has entered the shield cask.

l 16.

Group 16 - Nitrogen Inertino System Reactor Vessel Low Water Level - Level 2 Drywell Pressure - High Fuel Pool Ventilation Exhaust Radiation - High 17.

Group 17 - Recirculation Pump System and Primary Containment Radiation Monitoring System Reactor Vessel Low Water Level - Level 2 Drywell Pressure - High 18.

Group 18 - Primary Containment Pneumatic Supply System Reactor Vessel Low Water Level - Level 2 Drywell Pressure - High (t:) These valves are hydrostatically leak tested.

(c). Deleted.

l (d) Also closes automatically as a result of Torus Room Floor Drain Senp Level - High - High and Drywell Floor Drain Sump Level - High - Hig').

(e) These valves may be closed remotely from one of the following locatians:

1) control room.

2) their respective local panels.

j (f) Will automatically reposition as a result of the actuation of the LPCI Loop Selection Logic.

(g) Will automatically close when the corresponding RHR loop flow is greater than 1500 gpm.

(h) Will automatically close when the corresponding core spray loop flow is greater than approximately 775 gpa.

(1) Will automatically close when a) HPCI Turbine Steam Stnp Valve E41-F067 closes or b) HPCI Turbine Steam Supply Isolation Valve E41-F001 closes.

(j) Will automatically close as a resuit of the condition listed in Note (i),

above.

211 as when HPCI flow is greater then 1200 gpm.

FERMI - UNIT 2 3/4 6-46 Amendment No. 17, 21

- ' - - ^

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