ML20092C388

From kanterella
Jump to navigation Jump to search

Amends 45 & 36 to Licenses NPF-2 & NPF-8,respectively, Deleting River Water Sys Specs & Modifying Diesel Generator Testing
ML20092C388
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 06/07/1984
From: Varga S
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20092C390 List:
References
TAC-49374, TAC-49375, NUDOCS 8406210158
Download: ML20092C388 (18)
v • d • e


Text

I Er7mm

-/m

't

  1. RIGO

[ h.,

,h o

UNITED STATES NUCLEAR REGULATORY COMMISSION 3,.'

WASHINGTON, D. C. 20555 E

3

'g

%.vf ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE

~

Amendment No.45 License No. NPF-2 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Alabama Power Company (the licensee) dated December 30, 1982,. supplemented March 2 and 27, 1984, complies with the standards and re Energy Act of 1954, as amended (the Act)quirements of the Atomic and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission; C.

There is reasonable assurance: (1) 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 license 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 Comission's regulations and all applicable requirements have been satisfied.

2.

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

8406210158 840607 PDR ADOCK 05000348 P

PDR

(2) Technical Specifications The Technical Specifications contained in Appendices i

A and B, as revised through Amendment No.45

, are hereby incorporated in the license.

The licensee shall operate _the facility in accordance with the Technical Specifications.

3.

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

FOR THE. NUCLEAR REGULATORY COMMISSION k

J

\\

Meven arga, Chief Operating Reactors ch i/1 Division of Licensin

Attachment:

Changes to the Technical Specifications Date of Issuance: June 7, 1984 l

\\

/

/

ATTACHMENT TO LICENSE AMENDMENT N0. 45 AMENDMENT N0. 45 FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 Revised Appendix A as follows:

Remove Pages Insert Pages VIII VIII 3/4 7-13 3/4 7-13 3/4 7-14 3/4 7-14 3/4 8-5 3/4 8-5 B 3/4 7-3 B 3/4 7-3 B 3/4 7-4 8 3/4 7-4 I

m w

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l

SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TUR8INE CYCLE Safety Valves.........,..................................

3/4 7-1 Auxiliary Feedwater Systas............'..................

3/47-4 Condensata Storage Tank........................,..........

3/4 7-6 Activity.................................................

3/4 7-7 Main Steam Line Isolation Va1ves.......,..................

3/4 7-9 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..........

3/4 7-10 3/4.7.3 COMPONENT COOLING WATER SYSTEM...........................

3/4 7-11 3/4.7.4 SERVICE WATER SYSTEM.....................................

3/4 7-12 3/4.7.5

-. m...-. m...(.D.e. l. e.t.e. d. }.......................... 3/4 7 13 oum 3/4.7.6 ULTIMATE. HEAT SINK

"' e.... I Dale tA41......................................

3/4 7-14 Pond.....................................................

3/4 7-15 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM................

3/4 7-16 1

3/4.7.8 PENETRATION ROOM FILTRATION SYSTEM.......................

3/4 7-18 3/4.7.9 SNUBRERS...............

5................................

3/4 7-20 3/4.7.10 SEALED SOURCE CONTAMINATION..............................

3/4 7-80 3/4.7.11 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System............................

3/4 7-82 Spray and/or Sprinkler Systems...........................

3/4 7-85 CO Systems..............................................

3/4 7-88 2

l Fire Hose Stations.......................................

3/4 7-90 l

Yard Fire Hydrants and Hydrant Hose Houses...............

3/4 7-92 l

3/4.7.12 FIRE BARRIER PENETRATIONS............'....................

3/4 7-94 FARLEY-UNIT 1 VIII AMEMOMENT NO.45

PLANT SYSTEMS 3/4.7.5 RIVER WATER SYSTEM

.This specification deleted.

O S

4 i

e f

l 1

4 i

FARLEY-UNIT 1 3/4 7-13 AMENDMENT NO. 45

PLANT SYSTEMS 3/4.7.6 ULTIMATE HEAT SINK RIVER This specification deleted.

f

'f i

1 i

e f

l

.FARLEY-UNIT 1-3/4 7-14 AMEN 0 MENT NO. 45

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads. After energization, the steady state voltage and frequency of the emergency busses shall be maintained at 4160 + 420 60 + 1.2 Hz during this test.

volts and c)

Verifying that all automatic diesel generator trips, exgept engine overspeed ar.d generator differential and low lube oil pressure, are automatically bypassed upon loss of voltage on the emergency bus and/or a safety injection test signal.

5)

Verifying the diesel generator operates for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

During the first two (2) hours of this test, the diesel generators shall be loaded to 4353 kw for the 4075 kw diesels and 3100 kw for the 2850 kw diesels and during the remaining 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> of the test, the diesel generators shall be loaded to greater than or equal to 4075 kw for the 4075 kw diesels and 2850 kw for the 2850 kw diesels. ' The steady-state generator voltage and frequency shall be maintained between 4160 + 420 volts and 60 + 1.2 Hz during this test.

Within 10 minutes after completing thTs 24-hour test, perform specification 4.8.1.1.2.a.4.

6)

Verifying that the auto-connected loads to each diesel generator do not exceed the 2000-hour rating of 4353 kw for the 4075 kw generator and 3100 kw for the 2850 kw generator.

7)

Verifying the diesel generator's capability to:

a)

Synchronize with the offsite power source while the generator is loaded with its emergency loads upon a simulated restoration of offsite power.

b)

Transfer its loads to the offsite power source, and c)

Be restored to its standby status.

8)

Verifying that with the diesel generators operating in a test mode (connected to its bus), a simulated safety injection signal overrides the test mode by returning the diesel generator to standby operation.

9)

Verifying that the automatic load sequence timer is OPERABLE with each load sequence time within + 10% of its required value or 0.5 seconds whichever is greater.

~

10)

Verifying that the following diesel generator lockout features prevent diesel generator starting only when required:

a) 011 Tamperature High (OTH) l FARLEY-UNIT 1 3/4 8-5 AMENDHENT NO.45

PLANT SYSTEMS BASES 3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture. This restriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and

2) Ifmit the pressure rise within containment in the event the steam line rupture occurs within containment.

The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements are consistent with the assumptions used in the accident analyses.

3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION

~

The limitation on steam generator pressure and tenperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits.

The ifmitations of 70*F and 200 psig are based on steam generator average impact Values taken at 10*F and are sufficient to prevent brittle fracture.

3/4.7.3 COMP 0NENT COOLING WATER SYSTEM The OPERABILITY of the component cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions.

The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.

3/4.7.4 SERVICE WATER SYSTEM The OPERABILITY of the service water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident conditions within acceptable limits.

3/4.7.5 RIVER WATER SYSTEM This specification deleted.

i l

FARLEY-UNIT 1 B 3/4 7-3 AMENDHENT NO. 45 S

w w

2

{

i PLANT SYSTEMS BASES 3/4 7.6.1 ULTIMATE HEAT SINK (RIVER)

This specification deleted.

3/4 7.6.2 ULTIMATE HEAT SINK (POND)

The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available to either 1) pro. vide normal cooldown of the facility, or 2) to mitigate the effects o# accident conditions within acceptable limits.

The limitations on minimum water level and maximum temperature are based on providing a 30 day cooling water supply to safety related equipment without exceeding their design basis temperature.

The measurement of the ground water seepage at least once per 5 years will provide assurance that the 30 day supply of water is available.

3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM The OPERABILITY of the control room ventilation system ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions.

The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criteria 19 of Appendix "A", 10CFR50.

Cumulative operation of the system with the heaters on for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filter.

3/4.7.8 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM (PENETRATION ROOM AIR FILTRATION SYSTEM)

The OPERABILITY of the penetration room air filtration system ensures that radioactive materials leaking from the ECCS equipment within the pump room following a LOCA are filtered prior to reaching the environment.

The operation of this system and the resultant effect on offsite dosage calculations was assumed in the accident analyses.

Cumulative operation of the system with the heaters on for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a,31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filter.

FARLEY-UNIT 1 B 3/4 7-4 AMENDMENT NO. 45

.',f "%s

,o UNITED STATES

,y 7

([g

'd,.[\\)

-/.C NUCLEAR REGULATORY COMMISSION g

WASHINGTON, D. C. 20555 guf

+....

ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE

~

Amendment No.36 License No. NPF-8 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Alabama Powdr Company (the licensee) dated December 30, 1982, supplemented March 2 and 27, 1984, complies with the standards and re Energy Act of 1954, as amended (the Act)quirements of the Atomic and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission; 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 Comission's regulations; D.

The issuance of this license amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-8 is hereby amended to read as follows:

i i

, (2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.36, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE'NtlCLEAR REGULATORY COMMISSION

[J

'\\

gh, fi f'

Operating Reactors Branch #1 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: June 7, 1984

ATTACHMENT TO LICENSE AMENDMENT NO.36 AMENDMENT N0.36 FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 l

Revised Appendix A as follows:

Remove Pages Insert Pages

~

VIII VIII 3/4 7-13 3/4 7-13 3/4 7-14 3/4 7-14 3/4 8-5 3/4 8-5 8 3/4 7-3 8 3/4 7-3 8 3/4 7-4 B 3/4 7-4

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE

' Safety Va1ves............................................

3/4 7-1 Auxil iary Feedwate r System..........'.....................

3/4 7-4 Condensate Storage Tank.....................,.............

3/4 7-6 Activ1ty..................................................

3/4 7-7 Main Steam Line Isolation Va1ves.........................

3/4 7-9 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..........3/4 7-10 3/4.7.3 COMPONENT COOLING WATER SYSTEM...........................

3/4 7-11 3/4.7.4 SERVICE WATER SYSTEM.....................................

3/4 7-12 3/4.7.5 RIVER WATER SYSTEr...(.D. ele.t.e.H..........................

3/4 7-13 3/4.7.6 ULTIMATE HEAT SINK R i. e....(.D.6 e.t,e.@........................................

3/4 7-14 Pond.....................................................

3/4 7-15 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM................ 3/4 7-16 3/4.7.8 PENETRATION ROOM FILTRATION SYSTEM.......................

3/4 7-18 3/4.7.9 SNUBBERS.................................................

3/4 7-20 3/4.7.10 SEALED SOURCE CONTAMINATION..............................

3/4 7-50 3/4.7.11 FIRE SUPPRESSION SYSTEMS Fi re Suppression Water System............................

3/4 7-52 Spray and/or Sprinkler Systems...........................

3/4 7-55 i

CO Systems..............................................

3/4 7-58 2

Fire Hose Stations.......................................

3/4 7-60 1

Yard Fire Hydrants and Hydrant Hose Houses...............

3/4 7-62 3/4.7.12 FIRE BARRIER PENETRATIONS................................

3/4 7-64 3/4.7.13 AREA TEMPERATURE MONITORING..............................

3/4 7-65 FARLEY-UNIT 2 VIII AliEND!iENT NO.36

\\

i PLANT SYSTEMS 3/4.7.5 RIVER WATER SYSTEM This specification deleted.

4 4

O

+

l 4

1 e

i I

f I

i i

l I

l FARLEY-UNIT 2' 3/4 7-13

- AMENDMENT NO.36 t

b t,

, +

e,

.a....

n..

1

.I

.[{ ')

(

P i

t PLANT SYSTEMS

/

3/4.7.6 ULTIMATE HEAT SINK

/

i

/ RIVER j

s

.This specification. deleted,

\\

i

,\\

4, 9

h J'

d t

t 1, -

N i

+

1,., '

.j

\\

'/

..:,e

- i f

q p

^

- /

4 j

/

j

,Y 1,

[

s s

k.

I j

t%

.i

)

~ $

f.

r Rs j

{

s 4

0 1

I4

>..il.,..

34 1,a.

i t

a

s.,.

o 4

I g

j -

s:,

4 4

y 1

i r,

('

~

1 e

. \\

f Ygl.,, ?

f

))

)

,g

<f

, \\[

/

x [t s

)

5 4

t\\

q'-

g e

s-e, a

_-w.,

,g a

k' is',3 t ',

  • 's-q.

s.

>.,, < a.

,s f

jQ,$

,(

f-i i

f( - O.,,

K.

a e

r c

s.

I '

' [ ',a )t

, ~.

1 e s,

.I h 4 t.f 1

v r A

c so h,f, I

ag(ARLEY-UNI'T'2-3/4-7pi4' p

AMEN 0 MENT NO.36

'I l.

f 1

- cd f.-

%m i

c-

-Me y-w-+e erM e-w y

wp*wwe'h - W 9

-f

-,9m ga-ww***

  • a?w

'+-

g-

-e ee pm7 y-'S.a-pr-p V' e M P-8'+M+***Mr-'?d#

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads. After energization, the steady state voltage and frequency of the emergency busses shall be maintained at 4160 + 420 60 + 1.2 Hz during this test.

volts and c)

Verifying that all automatic diesel generator trips, except engine overspeed and generator differential and low lube oil pressure, are automatically bypassed upon loss of voltage on the emergency bus and/or a safety injection test signal.

5)

Verifying the diesel generator operates for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

During the first two (2) hours of this test, the dien1 generators shall be loaded to 4353 kw for the 4075 kw diesels and 3100 kw for the 2850 kw diesels and during the remaining 22

~

hours of the test, the diesel generators shall be loaded to greater than or equal to 4075 kw for the 4075 kw diesels and 2850 kw for the 2850 kw diesels. 'The steady-state generator voltage and frequency shall be maintained between 4160 + 420 volts and 60 + 1.2 Hz during this test.

Within 10 min Zes after completing thTs 24-hour test, perform specification 4.8.1.1.2.a.4.

6)

Verifying that the auto-connected loads to each diesel generator do not exceed the 2000-hour rating of 4353 kw for the 4075 kw generator and 3100 kw for the 2850 kw generator.

7)

Verifying the diesel generator's capability to:

a)

Synchronize with the offsite power source while the generator is loaded with its emergency loads upon a simulated restoration of offsite power.

b) Transfer its loads to the offsite power source, and c)

Be restored to its standby status.

8)

Verifying that with the diesel generators operating in a test mode (connected to its bus), a simulated safety injection signal overrides the test mode by returning the diesel generator to standby operation.

9)

Verifying that the automatic load sequence timer is OPERABLE with each load sequence time within + 10% of its required value or 0.5 seconds whichever is greater.

10)

Verifying that the following diesel generator lockout features prevent diesel generator starting only when required:

a) 011 Temperature High (OTH)

FARLEY-UNIT 2 3/4 8-5 AMENDMENT NC.36

~

M '?p A

g 3

..s

~

PLANT-SYSTEMS ~

y BASES

rupture.. This restriction is' required /to 1) minimize the positive reactivity effects 6f the Reactor Coolant Systent cooldown associated with the blowdown, and

2) limit the pressure rise within containment in the event the steam line rupture' occurs within containment.

The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements are consistent with' the assumptions used in 'the accident analyses.

3/4.7.T STEAM GENERATOR PRESSURE / TEMPERATURE' LIMITATION The -limitation on steam generator pressure and tempe'rature ensures that the 4.

pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits' The limitations of 70 F and 200 t

L psig are based on steam generator average impact values taken at 10'F and are Y sufficient to pruent brittle fracture.

3/4.7.3 COMP 0NENT COOLING WATER SYSTEM.

t The OPERABILITY of the component cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions.

The. redundant cooling capacity of this system, assuming a single failure, 'is consistent with the assumptions'used in the accident analyses.

i i

3/4.7.4' SERVICE' WATER SYSTEM 4

The\\0PERABILITY of the service water system ensures that sufficient cooling capacity 'is availabl,e for~ continuetty operation of safety related equipment during normal and accident ceditions. ? The' redundant cooling capacity of this system, assuming a single failure, is consistent with the' assumptions used in the accident corjditions withfn acceptable limits.

l 3/4.7.5 RIVEP. WATER SYSTEM L

This specification deleted'.

,t f

. 3+

s k

FARLEY.-UN1f 2' 'i,

B 3/4 7-3 AMENDMENT NO. 36 y.

s y>,s

. 1 -

b

?%

s a

J

.f c

j

-i

PLANT SYSTEMS BASES 3/4 7.6.1 ULTIMATE HEAT SINK (RIVER)

This specification deleted.

3/4 7.6.2 ULTIMATE HEAT SINK (POND)

The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available to either 1) proyide normal cooldown of the facility, or 2) to mitigate the effects of accident conditions within acceptable limits.

The limitations on minimum water level and maximum temperature are based on providing a 30' day cooling water supply to safety related equipment without exceeding their design basis temperature.

The measurement of the ground water seepage at least once per 5 years will provide assurance that the 30 day supply of water is available.

3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM The OPERABILITY of the control room ventilation system ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions.

The OPERABILITY of this system in conjunction with control scom design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criteria 19 of Appendix "A",10CFR50.

Cumulative operation of the system with the heaters on for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filter.

3/4.7.8 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM (PENETRATION R00M' AIR FILTRATION SYSTEM)

The OPERABILITY of the penetration room air filtration system ensures that radioactive materials leaking from the ECCS equipment within the pump room following a LOCA are filtered prior to reaching the environment. The operation of this system and the resultant effect on offsite dosage calculations was l

assumed in the accident analyses.

Cumulative operation of the system with the heaters on for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filter.

FARLEY-UNIT 2 B 3/4 7-4

. AMENDMENT NO. 36

-.

Retrieved from "https://kanterella.com/w/index.php?title=ML20092C388&oldid=4333454"